ORNL-CF-77-391.txt

-

DATE;

SUBJECT:

TO:

FROM:

Coe B =

OAK RIDGE NATIONAL LABORATORY

UNION CARBIDE CORPORATION

uumj;élsmn 0 R N L
rosr e s0x x CENTRAL FILES NUMBER

OAK RIDGE, TENNESSEE 37830

ORNL/CF-77/391

 

 

 

August 25, 1977

Decommissioning Study for the ORNL Molten-Salt Reactor
Experiment (MSRE)

Distribution

C. D. Cagle and L. P, Pugh

ABSTRACT

Job descriptions and cost estimates have been pre-
pared for two methods of decommissioning the shutdown
Molten-Salt Reactor Experiment (MSRE). Dismantling of all
process equipment for disposal in a solid-waste storage
area is estimated to cost $11,600,000. Transferring all
contaminated external equipment to the reactor containment
cell followed by filling the cell with concrete for in-
place entombment is estimated to cost $4,770,000. Also
included are a history of the reactor, a description of
the components, and a list of references.

This document has been approved for relesse
to the public by:

Damd (Jw«vm

chh.n_r ! mfannauon Officer

NOTICE This document contains information of a preliminary’
noture ond was prepared primarily for internal use ot the Oak
Ridge Notional Laboratory. It is subject to revision or cor-
rection ond therefore does not represent.a final report. The in-
formation is only for official use ond no release to the public
shall be made without the approval of the Law Department of
Union Carbide Corporatian, Nuclear Division.
 

 

 

 

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CONTENTS

ABSTRACT .
1. INTRODUCTION .
2, GENERAL INFORMATION

2,1 General Description
2.2 History |
2.3 Reactor Site and Building .
2.4 Shielded Containment Cells .
2.5 Reactor Primary System .
'2.5.1 Reactor Vessel and. Core
2.5.2 Thermal Shield .
2.5.3 Primary System Pump
2,.5.4 Primary System Heat Exchanger
5

2.5. Fuel Pump Overflow Tank

2.5.6  TFuel-Salt and Flush-Salt Drain and Storage Tanks .

2.6 Reactor Secondary System .
2.6.1 Heét Exchanger .
2,6.2 Coolant Circulating Pump .
2.6.3 Radiator .
2.6.4 Secondary System Piping
'2.6.5 Coolant Drain Tank .
2.7 Fuel-Pfocessing System .
2.8 TFreeze Flanges .
2.9 ?reeze Valves
2.10 Salt Systems Heaters and Therfial Insulation
- 2.10.1 Reactor Furnace |
2.10.2 Fuel-Salt-Pump Furnace .
2.10.3 Coolant-Salt-Pump Heaters and Insulation .
2

.10.4 Fuel- and Flush-Salt-Drain-Tank Heaters and
Insulation . '

N

.10.5 Fuel-Storage-Tank Heaters and Insulation .
2.10.6 Coolant-Salt-Drain-Tank Heaters and Insulation .

2.10.7 . Heat-Dump Radiator Heaters and Insulation

69
69
69
70
3.

4.

2.10.8 Piping Heaters and Insulation . . . . .
2.10.9 Heat-Exchanger Heaters and Insulation .

2.10.10 Heater and Thermocouple Leads . . . . .

2.11 Sampler-Enricher . . . . . . ¢« ¢ ¢« ¢ v ¢ o o . &
2.12 Nuclear Instrumentation . . . . « . « « « « .« &
2.13 Accessory Systems . . . . ¢ . ¢ ¢ o o 2 o 0 o .

2.13.1 Cover-Gas System . . . . .« « « « « o =
2.13.2 Leak-Detector System . . . . . . . 7';
2.13.3 Lubricating-0il Systems . . . . . . .
2.13.4 Component-Cooling Systems . . . . . . .
2.13.5 Cooling-Water System . . . . . . . .
2.13.6 0ff-Gas Disposal System . . . . . . . .
2.13.7 Containment Ventilation System .
2.13.8 Liquid-Waste -System . . . . . « . « .+ &
2.14 Vapor Condensing System . . . . . . . . . . ..

MSRE PRESENT CONDITIONS . . . « & ¢ « o« « o« o o o o o

3.1 Securing the Process Systems . . . . . . . . . .

- 3.2 Post-Operation Examination . . . . « . . . . . .

3.3 Surveillance . . . ¢ ¢ ¢ ¢ + « ¢ o e 0 s 4 s e
3.4 Surplus Equipment Removal . . . . . . . . . . .
3.5 Site Utilization . . . . . ¢« ¢« ¢« & « « & &+ & &
3.6 Current Radiation and Contamination Levels . . .
DECOMMISSIONING ALTERNATIVES . . . . . . « « « + « . .

4.1 Removal and Disposal of All Radibactifie Material
: the Containment Cell Structure . . . . . . . . .
4.2 Entombment in Place . . . . . ¢ % ¢ ¢ o « o o

4.3 Arguments Favoring Dismantling and Disposal of Radio-

active and Contaminated Items . . « « ¢ « « + =«

4.4 Arguments Favoring Entombing the Reactor and Associated

Radioactive and Contaminated Items and Materials
ReaCtor Cell . I. - L] . . - » [ ] - - * . . - . - * .

in the

5. WORK INVOLVED IN DISMANTLING AND DISPOSING OF RADIOACTIVE AND

CONTAMINATED ITEMS IN A SOLID-WASTE STORAGE AREA . . .

5.1 Preparatory Work . . . « . o « « &« ¢ o 0 4 o 0

* - .

97
97

98

99

99

99
5.1.

s

5.1.2
5.1.3
5.1.4
5.1.5
5.1.6
5.1.7

5.2.1

5.2.2

5.2.
5.2,
5.2.
5.2.
5.2.
- 5.2.
5.2,

O 0 ~N O W o~ W

Flushing System for the Reactor Tank and Other
Primary System Components

Reactor Cell Flooding System .

Work Shielding .

Transport Shields and Waste Storage Provisions .
Disposable Waste Containers

Miscellaneous Cutting and Handling Tools .

Retrievable Storage Requirements . . .

5.2 Remote bismantling Work

Clearing the Cell Around the Reactor .

Segmenting and Disposal of the Thermal Shield and
the Reactor Vessel . e i e e s e

5.2.2.a Alternative to Segmenting the Reactor
Vessel -

Drain-Tank Cell

Fuel-Processing Cell .

Cell Ventilation System

O0ff-Gas System .

Liquid-Waste Disposal System .
Coolant-Salt System

Miscellaneous Contaminated Items .

5.2.9.a Component-Cooling Air System .

15.2.9.b Sampler-Enricher

5.2.9.c Treated-Water System

WORK INVOLVED IN ENTOMBING ALL RADIOCACTIVE AND CONTAMINATED
ITEMS IN THE REACTOR CELL

6.1 Preparatory Work .

6.1.1 Flushing System for the Primary Salt Drain Tanks
and the Fuel-Processing Equipment
6.1.2 Air Exhaust System for the Reactor Cell
6.1.3 Tooling . . . .
6.2 Preparing Reactor Cell to Accommodate Contaminated Items
from Other Cells and Areas . . . . . .
6.2.1

Clearing Top of Cell and Installing Temporary
Ventilatlon Duct . . c e e e

’

99
104
104

105

105
105
106
106
107

. 107

108
108
110
110
110
111

. 111

111
111
112

112

113
113

113
116
116
116

116
6.2.2 Sealing the Existing 30-In. Cell Ventilation
Duct at the Cell Wall

6.2.3 Closure of the Opening Between the Reactor and
Drain-Tank Cells .

6.2.4 Enlarging Space in the Reactor Cell

6.3 Transfer of Disposable Items to the Reactor Cell .

6.3.1 Drain-Tank and Fuel-Processing Ceil Components .

6.3.2 Disposal of Existing Reactor Cell Ventilation
: Duct and Off-Gas Lines . . . . «. « « .« « .« .

6.3.3 Secondary Decay Volume and Charcoal Traps
6.4 | Filling the Reactor Cell with Concrete .
6.5 Decontamination of Afea.
6.5.1 Drain-Tank Cell
6.5.2 — Fuel-Processing Cell . . . . . . « . ¢« « « « &
6.5.3 Liquid-Waste Storage Cell
6.5.4 Containment Ventilation System .
6.5.5 Special Equipment Room - Coolant Cell Area .
7. REFERENCES .

APPENDIX A - JOB LISTING FOR DECOMMISSIONING THE MSRE BY
DISMANTLING AND DISPOSAL .

 APPENDIX B - JOB LISTING FOR DECOMMISSIONING THE MSRE BY
ENTOMBMENT . C e e e | .

DISTRIBUTION .

Page

117

117
117
118
118

119
119
120
120
120
120
121
121
121
121

123

215
275
Figure
Figure
Figure
Figure
Figure
Figure
Figure

Figure

Figure

Figure
Figure

Figure

Figure

Figure
Figure
Figure

Figure

Figure

Figure
Figure

Figure

Figure

Figure
Figure
Figure
Figure
Figure
Figure
Figure
Figure

Figure

O 0~ o U~ W -
. - . . . - - . .

Ny N &1 = = | = = = = = = et
N = O W Ny W N+ O
* . . . - * - - . * - - -

LIST OF FIGURES

" ORNL Area Map

Plot Plan, Molten-Salt Reactor Experiment.(Bldg. 7503)
Front View of Bldg. 7503 .

Rear View of Bldg. 7503 During MSRE Construction .
Plan at 852-ft Elevation .

Plan at 840-ft Elevation .

Elevation, Bldg. 7503

Shield Block Arrangement at Top of Reactor Cell
Shield Block Arrangement at Top of Drain-Tank Cell .
Typical Penetration Assembly - Reactor Cell

Fuel System_Process_Flow Sheet .

Simplified Design Flow Sheet of the MSRE .

Primary and Secondary Salt Systems .

Reactor Cell During Assembly of Components .

Reactor Vessel .

Cross Section - Reactor Vessel and Access Nozzle .
Reactor Vessel Hanger Rods .

Typical Graphite Block Arrangement .

Control Rod and Drive Assembly .

Thermal Shield Components

Fuel Pump

Fuel Pump Motor and Rotor Assembly Showing Flange Bolt
Extensions . . . .+ « ¢ ¢ ¢« o 0 v e e v e e e e e e e .
Primary Heat Exchanger . . . . . .

Primary Heat Exchanger Subassemblies .

Fuel Pump Overflow Tank

Fuel Drain Tank System Process Flow Sheet
Fuel-Salt Drain Tank .

Fuel Drain Tank Steam Dome Bayonet Assembly
Coolant System Process Flow Sheet

Radiator Assembly

Radiator Coil and Enclosure

Page
14
15
16
17
18
19
20
22
23
24
28
29
30
31
32
33
35
36
38
39
41

42
43
bt
46
47
48
49
51
53
54
Figure
Figure
Figure
Figure
Figure
Figure

Figure

Figure
Figure
Figure
vFigure
Figure

Figure

Figure
Figure
Figure

Figure

Figure
Figure

Figure

Fuel-Processing Cell . . . . . . . . . . . . . .
Simplified Fuel-Processing System Diagram . . .
Fuel-Processing System Process Flow Sheet . . .
Fuel Storage Tank . . . & ¢« ¢ v v ¢ « v o o o &
Sodium Fluoride Filled Trap . . « . + + « « « &

Freeze Flange and Clamp . . . . . . . . . . . .

-

*

Freeze Flange Clamping Frame Showing Assembly and Dis-

assembly . . . . . . . . 0 0 0 0 0 e 0 e e 0 e
Freeze Valve in Line 103 . . . . . . . . . . . .
Freeze Valve in Lines 107, 108, 109, and 110 . .
Freeze Valve in Lines 111 and 112 . . .

Freeze Valve in Lines 204 and 206 .. . . . . .

Removable Heater for 5-In. Pipe . . . . . . . .

Schematic Representation of Fuel-Salt Sampler-Enricher

Dry Box - . - . - - . . - . . . - - - . . - *

Elevation View of Nuclear Instrument Penetration .

Plan View of Nuclear Instrument Penetration . .

Schematic Diagram of Leak-Detected Flange Closure

Schematic of Air Flow Diagram Containment Ventilation
System . o & ¢« 4 4 e 4 4 v e e e e e e e e e e s

Liquid-Waste System Process Flow Sheet . . . . .

Diagram of Vapor-Condensing System . . . . . . .

Reactor Assembly Storage Container Concept . . .

63
64
65
66
67
71

74
76
77
80

86
87
89
109
Table 1
Table 2
Table 3

Table 4
Table 5

LIST OF TABLES

Composition and Properties of INOR-8 . . . . . . .
Reactor Vessel and Core Design Data and Dimensions .

Radiation Levels Measured in 1977 Using an Ionization
Chamber . . . ¢« & ¢ v ¢ o o s « s o o o o s o o =

Dismantling -~ Cost Estimate Summary Sheet . . . . .

Entombment - Cost Estimate Summary Sheet . . . . . .

Page

26
27

95
100
114
e &

I‘l"-

11

1. INTRODUCTION

Research and development programs dealing with nuclear reactors and
their radioactive products have been carried out at ORNL since its
beginning in 1943. An increasing number of radioactive and radioactively.
contaminated facilities have been shut down due to completion of programs

or to being supplanted by more up~to-date facilities. Since these shut-

: down facilities contain hazardous amounts of both fixed and removable

radioactive materials, they must be kept under constant surveillance and
structurally maintained to preclude unauthorized entry by personnel and
to ensure against the release of radioactive contaminants to the environ-

ment. A portion of the financing and all personnel attention required

. for surveillance and maintenance of these facilities must be supplied by

on-going programs not related to the original programs which produced

the facilities. Although some advantage is gained in delaying final dis-
position of such shutdown facilities to await decay of relatively short-—
lived nuclides, further delay not only penalizes other programs but also
increases the risk of violation of containments due to deterioration or
accident.

The shutdown facilities include four reactors: the Molten-Salt
Reactor Experiment (MSRE), shut down in 1969; the Homogeneous Reactor
Experiment No. 2 (HRE-2), shut down in 1961; fhe Low-Intensity Testing
Reactor (LITR); shut down in 1966; and the Oak Ridge Graphite Reactor
(OGR), shut down in 1963. This report considefs the final disposal of
the MSRE.

The two methods of disposal considered are: (1) removal and burial
of all radioactive and contaminated systems components in a solid-waste |
disposal area; and (2) entombment of the more radioactive items in con-
crete within the existing below-grade concrete-shielded cells. Both
approaches assume that the 233U now stored in drain tanks in a shielded
cell adjacent to the reactor cell will have been removed prior to begin-
ning the decommissioning.

- This Feport contains a brief history of the project and sufficiently

detailed descriptions of the radioactive and auxiliary systems to expiain
12

the work that will be required to accomplish the decommissioning. More
detailed descriptions of the systems and components can be found in the
references. -

The MSRE was a 10-MW reactor built to investigate the practicality
of_the molten-salt concept for central power station applications. The
reactor and its accessory components are located in a group of mostly
below-grade shielded concrete cells within a mill-type building remote
from the main ORNL area. The last charging of fuel salt containing 233y
as the fissionable species remains stored in two drain tanks in a cell
adjacent to the reactor cell. This salt must be heated to above
300°F annually to recombine radiolytically produced fluorine gas. Due
to.the presence of the fuel and the residual radiocactive fission and
corrosion products within it and distributed throughout the reactor pri-
mary system and fuel-processing system, a filtered ventilation system
must be maintained in operation. Additionally, varying degrees of sur-
veillance and maintenance efforts must be exercised on a daily, a monthly,
and an annual basis to guarantee that the reactor remains environmentally

safe.

2. GENERAL INFORMATION

2.1 General Description

The MSRE was a single-region, unclad—graphite—modérated, homogeneous -
fuel type reactor with a design heat generation of 10 MW. The cir-
culating fuel solution was a mixture of lithium, beryllium, and zirconium
fluoride salts containing uranium fluoride as the fuel. The mixture had
an euctectoid liquidus point of 840°F and operated normally at 1200°F core

outlet temperature. Reactor heat was transferred from the fuel salt to

a similar coolant salt and then dissipated to the atmosphere.

2.2 History

The MSRE was constructed during the years 1961-1964 in a building

originally built for molten-salt reactor experiments for the Aircraft

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13

Nuclear Propulsion Program (ANP). The purpose of the‘MSRE was to dem-
onstrate that such a reactor could be constructed and maintained without
undue difficulty and could be operated safely and reliably. Additional
objectives were to provide the first large-scale; long-term, high-
temperature tests in a reactor environment of the fuel sélt, graphite
moderator,-and high-nickel-base alloy (INOR~-8) construction material.

The reactor first reached criticality on June 1, 1965, and concluded
operation on December 12, 1969. During this time the reactor accumulated
72,441 MW-hrs using ‘23%U fuel and 33,296 MW;hrs.using 233y fuel for a
total of 105,737 MW~hrs which is equivalent to 13,217 equivalent full-power
hours at 8.0 MW full power.

2.3 Reactor Site and Building

The MSRE 1is located in Melton Valley about one~half mile southeast of

.the main ORNL area (Figure 1) near the High Flux Isotope Reactor (HFIR)

and the Homogeneous Reactor Test (HRT) sites. A plot plan of the reactor
building complex is shown in Figure 2. Figures 3 and 4 ére views of the
front and rear of the building.

The building is constructed of steel framing and.asbestos cement
type corrugated siding with a sheet steel interior finish. Essentially
all portions of the building below grade are constructed of reinforced
concrete. Figure 5 is a plan of the reactor building at grade level, and
Figure 6 1s a plan 12 ft below grade showing the shielded cells and adja-
cent working areas. Figure 7 is an elevation through the cells. The |
west half of the building at grade level is about 42 ft wide,'157 ft long,
and 33 ft high. This high-bay or "crane-bay" area houses the reactor cell
drain-tank cell, coolant-salt '"penthouse'", and most of the auxiliary cells.
It is serviced by two bridge cranes, one equipped with a 30-ton hoist and

the other with both a 3-ton and a 10-ton hoist. The east half is 38 ft

‘wide, 157 ft long, about 12 ft high. This section contains the control

rooms, maintenance shops, change rooms, and some offices. (As explained in

Section 3.5, some of these areas are now in use by groups not related to

the MSRE program.)
Most of the west half of the below-grade level is occupied by the
reactor cell, drain~tank cell, and auxiliary cells. The east half con-

tained an office, a maintenance shop, and a chemical_laboratory.
14

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Rear View of Bldg. 7503 During MSRE Construction

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Figure 5.

FUEL PROCESSING CELL

Plan at 825-ft Elevation

 
 
 
  
 
  
 
  
  
   

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18

ORNL-DWG 64-8726

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21
2.4 Shielded Containment Cells

As shown in Figures 5 and 6 the reactor and its accessory components
are located in a group of shielded cells rather than in a single contain-
ment. This arrangement enhanced accessibility for maintenance and greatly
reduced the number of components incurring induced radioactivity due td
neutron irradiation. Only those components and structures within the
reactor_shield tank were subjected to neutron irradiation and must be
partially or totally removed to reduce the radiation level. All other cells
will require only decontamination following either the removal or decon-
tamination of the items within them. Access to fhe cells is gained by
the removal of concrete roof plugs. The reactor cell and the adjacent
interconnected fuel-drain-tank cell have an ll-gage stainless steel mem-
brane between the two layers of concrete roof plugs as a containment |
seal. Access to the cells is gained by cutting an opening in the membrane..
When the cell is to be resealed, a patch is welded over the opening. The
top shielding arrangements for the reactor cell and drain-tank cell are
shown in Figures 8 and 9.

The reactor cell is a cylindrical carbon steel vessel 24 ft in
diameter and 33 ft in overall height with a hemispherical bottom and a
flat top. The bottom is 1 to 1 1/4 in. thick and the cylindrical portion
is 2 in. thick except for the section containing the large penetrations
where it is 4 in. thick. The reactor cell vessel is installed within
another cylindrical steel tank refefred to as the "shield tank". This
outer tank is 30 ft in diameter by 35 1/2 ft high. The flat bottom is
3/4 in. thick and the cylindrical section is 3/8 in. thick. The tank is
supported on a reinforced concrete base within an enclosure formed by con-
crete soil—retaining walls and the concrete walls of adjacent cells. The
reactor céll vessel rests upon a cylindrical steel skirt supported from
the bottom of the shield tank. The annulus between the two tanks is
filled with magnetite sand and water; the cavity encompassed by the sup-
port skirt is filled only with water. |

fenetrations into the reactor cell for pipes and conduits were pro-
vided by installing a bellows-equipped sleeve between openings in the two

vessels (Figure 10). The purpose of the bellows was to accommodate
22

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

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@,

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

PLAN HOLD-DOWN
BOLTS -

  

RREN

e A e W A e A e e e e R

.....
-----

SUPPORT BEAM ACCESS

SHIELDING ‘ PLUGS
INSERT SHIELDING

IRON

CELL WALL

SECTION "xX" ANNULUS

Figure 8. Shield Block Arrangement at.Tob of Reactor Cell
23

ORNL-IWNG 64-8809

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

- L 1l L ) A
(I( ! | 2 h )N
yl i b i
i T — >— — — 4
|lrL l] 1 ll !C
wx| © S l 1 H"l"'l "X X"
X r 1 10 l 1 ol 12 e
34 T =
B[yl ! ! I
H T 13 ' 14 15 I ol T
Tl ; ! NI
T 16 17 18 _|]l \
T T
1;| ?[ L Ly TG
1
22 | 23 H 24 H
N I | N7 !
25 ] 26 27 ¥V
J
PLAN

 

S

“CELL
ALL

SECTION "xX"

:Figure 9, Shield Block Arrangement at Top of Drain-Tank Cell

 

 

 
 

5 SAND ¢ WATER K

SEAL
WELD

CELL SIDE

 

 

T~ 24' [D REACTOR
CONTAINMENT CELL

 

30' 1D
REACTOR TANK

Figure 10. Typical Penetration Assembly - Reactor Cell

%l
25

dimensional changes due to temperature and pressure. Pipes and conduits
pass through stepped shielding plugs which fit into the penetration
sleeves. 'Thg pipes and conduits are seal-welded to the two faces of the
plugs aqd_aré curved or coffset within the plug to prevent radiation
streaming.' The'outer rim of the shield plug is seal-welded to the sleeve.

Since the reactor celllatmosphere extended to this seal weld, the sleeves

- and shield piugs are contaminated up to that region.

2.5 Reactor Primary System

The major components of the reactor primary system are the reactor
vessel, the fuel-salt pump, the heat exéhanger, and the interconnecting.
pipes and flanges. All of these components are located inside the reactor
cell, Figure 11 is the fuel system process flow sheet showing both the
primary system itself and the various_subsystems. |

Except for the graphite moderator, all the materials of the primary
system that were in contact with the fuel salt are Hastelloy-N (INOR-8),

a nickel-molybdenum-iron-chromium alloy which is highly resistant to cor-
rosion by molten fluoride salts and has high strength at eievated tempera-
tures. The properties of this material are lisfied in Table 1. Figfire 12
is a simplified flow diagram of the reactor primary and secondary systems
and Figure 13 is a layout of these systems, Figure 14 is a photograph of

the reactor cell with the components partially installed.

2.5.1 Reactor Vessel and Core

 

Physical characteristics of the reactor vessel and its contents are
listed in Table 2. | |

The feactor vessel is 58 in. I.D. and about 94 in. high (Figures 15
and 16). The wall thickness of the cylindrical portion is 9/16 in. except
for the top 16 in., which is 1 in. thick. An 8-in.-I.D. half-round

welded circumferentially to the tank over the l-in.-thick section served

'as the fuel-salt inlet flow distributor. The salt delivered by the dis-

tributor entered the tank through 3/4-in.-diameter holes drilled through

'the l-ifi.—thick section. The salt flow from the flow distfibutor entered

the annular space between the vessel and core container and flowed down-

ward providing efficient cooling for the core can and reactor vessel walls
26

Table 1. Composition and Properties of INOR-8

 

Chemical Properties:

 

 

 

Ni 66-71%

Mo 15-18

Cr _ 6-8

Fe, max 5

C 0.04-0.08

Ti + Al, max 0.50

S, max 0.02

Mn, max 1.

Si, max 1.0

Cu, max 0.35

B, max 0.010

W, max 0.50

P, max 0.015

Co, max 0.20

Phggical Properties:
Density, 1b/in.3 0.317
Melting point, °F 2470-2555
Thermal conductivity, BTU/hr-ft2(F/ft) 12.7
at 1300°F
Modulus of elasticity at ~1300°F, psi - 24.8 x 108
Specific heat, BTU/1b-°F at 1300°F 0.138
Mean coefficient of thermal expansion, 8.0 x 10°
70-1300°F range, in./in.-°F
Mechanical Properties:
Maximum allowable stress,* psi: at 1000°F - 17,000
| 1100°F 13,000
1200°F 6,000
1300°F 3,500

 

*ASME Boiler and Pressure Vessel Code Case 1315.

 
 

 

Outlet nozzle, Schedule 40, in., IPS

Reactor vessel

 

0.D., in.
I.D., in.
Wall thickness, in.

Overall height, in. (to centerline of
5-in. nozzle)

Head thickness, in.
Inlet
Cooling annulus I.D., in.

Cooling annulus 0.D., in.

Graphite core
Diameter, in.

Number of regular graphite core
blocks

 

Number of fractional core blocks

Core block size, in. (regular)

Core container
1.D., in.
0.D., in.
Wall thickness, in.

Height, in.

27
"/fl\
. Table 2. Reactor Vessel and Core Design Data and Dimensions
Construction material INOR-8
- Inlet nozzle, Schedule 40, in., IPS 5
5

59 1/8 (60 in. max)
58

9/16

100 3/4

1
Constant area distributor
56
58

55 1/4
513

104
2 x 2 x 67

55 1/2
56
1/4
68

 

 
 

el
ECIAL EQUIPMENT 1
v916

r.uur ~

T
i
|
|

—@TE = TWR gz
ECC-—

——

 

 

COMPONENT
COOLING
SYSTEM

 

.|—'~

Ewi
&a

rw---— L - a— SRt ’ - YL
im 938 m LEVEL HALL ' - v

i N
WO+ ey

l-(w/cv-{) oN
CrOLANT PUMP MOTOR

5 FUEL
PUMP

MOTOR

FROM LINE 508

 

——

3 PSIG
FUEL PUMP

-t

CONTAINMENT ENCLOSURE MO.2

L NI el S
SPECIAL  EQUIPMENT ROOM
PN AR _--— F

TRANSMITTER ROOM

" 10

13

10 SCFu

REACTOR
~ 800 SCFM MAX, R

 

COMPONENT ","OLING FUMP DATA

Ty

10 ERAIN SHYARTEW

FREEZE VALVE

00T IN1-a0-5 AUTO-RESISTANCE

NUCLEAR
INSTRUMENT
PENE TRATI

16 FLANGE PAIRS
WITH 4 REMOTE
LEAR DETECTORM
LINES ON tw TO
THERMAL SMIELD

L%) —iFan DETECTOR SERVES 2 FLAMGES
HEATING LUG THRCUGH CONNECTING -L TURING

b —REMCTE ©GAS LINE MSCONNECT

_7:45'._5_-‘1: 75-73 CF J Tohe
T bt B TN ..._.a...---n-’l . — NORMAL I./I
"DRAIN SANK CELL {

70 FUEL DRAIP; ) L_ e )
TANK SYSTEM; -

 

Figure 11. Fuel System Process Flow Sheet

TO EMRICHER SANMPLER

28

FUMP DATA REVISIONS

SEE DCN 249
SEE DCm 2881

v aL

" /@ SPECIAL EQUIPMENT KOOM

524
v5h24

SHIELD

iC “FF GAS
STSTEM

WOR-
WASTE COOLANT
DRAIN

CELL FUTURE FLANGES
33 GAL FF-200 & FF204

—— —ca—— 102%°F
1.3PSI6

oI
RECEIVER

 

HEAT EXCHANGER
H X o

HoceF (t
L]
47.3 . .

CHARCOAL BFO
<«

REACTOR
CFLL

LTEM LT CEACTOR P XFERIVENT
FUEL “YRTEM
Che RS OFLOW Cerh T
hE LT T R
OAKX ADOE NATIONAL LABORATORY
S
Union CARBIDE NUCLEAR COMPANY
W OF WNON CUBINE CONPORKRR

’ e YL 4

JOR 433-1.C Cul e | Desa-a-a0ggo

 
 

 

STACK

el

FAN :.-»I--N :
FROM
=== cooant |
i ~!  SYsTem
I b
| & l___i!'_—J _____________ === T T T T T T T T T T T T ':
| ——-—————————— —————frm— e ———— ———— e e e e y
Pt T ] - - ]
| ! # eracsnsants .“'i“ r. taeseissianasans .........u---up.............'.......l.......'...............E 2 | ) ™7 4
| ! Pt e e 0300 RBP o T
! ! WATER STEAM . ’ : e ';
} MAIN sy F o
| BED AuX. ;, '
1 CHARCOAL
| BED
I _
I
|
l
t TANK NO. t°
| |
I
LN |
e T J

OFF-GAS
HOLDUP
ABSOLUTE
FILTERS
BLDG.

3 VENTILATION

 

 

 

   

ORNL -DWG 63-11410R

 
  
     
 
 
 
   
   
   
 
   
 
  

   

FUEL
PUNP SAMPLER - P LEGEND
: ENRICHER SAMPLER S— FUEL SALT
e = —— — ——— : —camms COOLANT SALT

REACTOR
VESSEL

 

 

 

 

 

 

 

 

 

 

 

 

 

 

SODIUM
FLUORIDE BED

 

"Figure 12. Simplified Design Flow Sheet of the MSRE

cevesessenene HELIUM COVER GAS
————— RADIQACTIVE OFF -GAS

6¢
30

ORNL-DWG 63-1209R

     
   
 
  

l

REMOTE MAINTENANCE . !

GONTROL ROOM !
{

REACTOR CONTROL

M
ROOM, M >
e —T ,'i N,

A
' | ‘

/ .“\
mmet J 0o

-
'"'M"WTT"-‘%

. oy -
— e rawanw.a ™

~ " —‘_l

 

1. REACTOR VESSEL 7. RADIATOR
= 2. HEAT EXCHANGER 8. COOLANT DRAIN TANK
3. FUEL PUMP 9. FANS
4. FREEZE FLANGE 10. FUEL DRAIN TANKS
5. THERMAL SHIELD . FLUSH TANK
- 6. COOLANT PUMP 12. CONTAINMENT VESSEL

13. FREEZE VALVE

Figure 13. Primary and Secondary Salt Systems

 
Figure 14.

Reactor Cell During Assembly of Components

PHOTO 66372

 

It

 

 
QRNL-LR-DWG 6109/ HY

32

FLEXIBLE CONDUIT TO
CONTROL ROD DRIVES

S

o

257 ]
,....‘r“&.u \

GRAPHITE SAMPLE ACCESS PORT

COOLING AIR LINES

 

     
              

ACCESS PORT COOLING JACKETS

REACTOR ACCESS PORT

FUEL OQUTLET

OUTLET STRAINER

 

r

CORE

CONTROL ROD THIMBLES
CENTERING GRID

 

[ em———— A T

e
o
-
S
o
@
-
Q2
o
=
O
-
'S

AT o

 

S o | . ) . -
e (RO

Ee———— At

      

AONGORRE

 

 

 

 

 

NS

/

   

 

AYAYA

 

 

 

 

 

GRAPHITE-MODERATOR
STRINGER

TS

FUEL INLET

REACTOR CORE CAN—"

  

REACTOR VESSEL—

       
 

ANTI-SWIRL VANES

MODERATOR
SUPPORT GRID

   

 

VESSEL DRAIN LINE

Reactor Vessel

Figure 15.
RIS, (MG 1402
Jhe
1

SALY SEAL

 

   

GRAPHITE SANPLE
ACCEAS WORILE (1)

         

 

N

[
& - ;
# 3
& 5 !
3 3 -
x - L
: ¥ OIN
0 s 2 -2
< mm 2 ) -
= “ v

i

CIRCULATING PUNP !

SALT OUTLET TO

               

[
L]
4
x
-
-
-
-

T DISTRIBUTOR
PHITE AND
HIOR-0 SANME

ASSEMBLNS (X

GRAPHITE
STRINGERS

513 FuLL SIZE
104 FRACTIONAL
SIZE

-
£
| d
"
3

-
[
=z
o«

VANEY (48)

    
 

T T .uavu*EEEg

 

 

 

REMOVABLE QRAPWITE
STRINGERS {3)

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

i wwd
. ra e

 

 

 

 

=

 

 

 

     

CONTROL MO0 AND

 

 

 

 

 

THeeLE (R

 

 

 

 

 

 

 

 

 

 

 

 

  

HANGER
no0s (D)

RETAINER
REACTON
vEISEL
RESTRICTOR
Rine

GRIQ SUPPORT PLATES

GRAPHITE
RING

DRAIN LINE MOOD —

ORAIN TuBE

FiLL ANO DRAIN LINE

- Reactor Vessel and Access Nozzle

ion

Cross Sect

Figure 16,
34

by flowing countercurrent to the upflow of heated salt in the core. The
top and bottom of the vessel are 58-in.-I.D. flanged and dished heads.
The vessel is supported by 12 suspension rods from the top of the thermal
shield (to be described later). The suspension rods (Figure 17) are con-
nected to support lugs welded to the reactor vessel above the flow dis-
tributor.

The core can, or shell, is 55 1/2 in. I.D. and 67 15/16 in. high with
a wall thickness of 1/4 in. The can is supported by a ring at the top of
the can which is bolted to 36 lugs welded to the inside of the reactor
vessel wall. The can supports the graphite used as the moderator material

for the core.

The graphite moderator is formed of 513 blocks, each of which is 2 in.

x 2 in. x v67 in. These are stacked in a vertical close-packed array as
shown in Figure 18. In addition, there are 104 fractionai-sized blocks at
the periphery. Fuel passages were provided by milling a rectangular ver-
tical groove down each block face. When assembled, these grooves formed
0.4 in. x 1.2 in. vertical channels through which the fuel salt moved from
the bottom to the top of the core.

The vertical graphite blocks rest on a lattice of horizontal graphite
blocks, about 1 by 1 5/8 in. in cross section, laid in two 1ayérs at right
angles to each other. Holes in the lattice blocks accept the l-in.-
diameter doweled section at the lower end of each vertical block. The
upper horizontal surfaces of both the vertical blocks are tapered to pre-
vent salt from being retained on them when the vessel was drained. The
lattice blocks rest on a grid of 1/2-in.-thick INOR-8 plates set on edge
and varying in height from 1 5/8 in. at the core periphery to about
5 9/16 in. at the center. This support grid is fastened to the bottom of
the core can. Each of the vertical blocks is locked to the grid by 5/16-
in.-diameter rods which pass through holes in the grid and holes in the
doweled sections of the blocks. Forty-eight vertical fins located around
the periphery of the reactor vessel below the core support grid prevented
spiraling flow of the fuel salt in the region below the core.
| At the center of the bottom of the reactor vessel is a 1 1/2-in.

Schedule 40 drain line which extends about 2 3/4 in. into the vessel and

 
35

ORNL DWG 64-8819

    
 
 
 

AL L 7L L LD

Thermal Shield Cover

1-1/4 in. Dia Pin

 

S K A

 

|/ Hanger Rods (12)

 

+

-{— | l 1-1/k in. Dia INOR-8
3

"

¢

~ 24 in,

 

 

 

 

 

 

r @F““‘ 1-1/4 in. Dia INOR-8 Pin

/LT"!
3/4-in. Thick -~
INOR-8 Support

Lug ::i'::ll. to ‘—'{ I-—— 1-3/8 in.

 

 

T

Figure 17. Reactor Vessel Hanger Rods
36

ORNL-LR-DWG 56874R -

   

PLAN VIEW
TYPICAL MODERATOR STRINGERS

SAMPLE PIECE

 

 

- NOTE: NOT TO SCALE

 

 

 

 

Figure 18. Typical Graphite Block Arrangement

I
37

is covered with a protective hood to prevent debris from entering the
pipe. A 1/2-in.-diameter tube within the drain line opens into the vessel
just above the bottom surface to allow complete draihing.

The top head of the reactor vessel is equipped with a 10-in.-diameter,
40-in.-tall nozzle. A 5-in. nozzle emerging from the side of the exten-
sion is the fuel-salt exit line from the vessel. The 10-in. nozzle served
also as an entry port for the three control rods (Figures 15 and 19) and
as an access for inserting and removing replaceable core blocks and

materials—-testing specimens.

 

2.5.2 Thermal Shield

The primary functions of the thermal shield (Figures 6, 7, and 20)
were to reduce the radiation damage to the reactor containment vessel and
to cell equipment, to serve as part of the biological shielding, and to
provide the support for the reactor vessel which is suspended within it.

The shield is a water-cooled, steel ball and water filled container
which compietely surrounds the reactor vessel. It is about 10.4 ft 0.D.
by 7.8 ft I.D. and 12.5 ft tall. The l4-in.~wide annular space is filied
with l-in.-diameter carbon steel balls. The shiéld coolant circulated
through the interstitial spaces. The shield walls are made of 1-in.-
thick 304 stainless steel plate.

Six separate parts make up the thermal shield assembly: the flat

>semirectangu1ar base, the main cylindrical section, three removable seg-

ments of the cylindrical section, and the removable top cover. The
rémofiable segments fill slots in the cylindrical sections through which
the reactor fill and drain line and the fuel-salt inlet and outlet lines
to.the reactor passed as the reactor vessel was lowered into position.
The base and main cylindrical sections have many equipment support struc-

tures attached to them.

2.5.3 Primary System Pump

 

From the top of the reactor vessel the fuel flowed directly to the
primary system pump bowl through a 13.8 ft length of 5-in, Schedule 40
pipe which enlarges to 6 in. below the pump to adapt to the pump suction

nozzle size. The components and appearance of the centrifugal sump-type
38

 

SOLENOID ACTUATED
RELEASE

MECHANICAL CLUTCH
GEAR AND ARM

 

 

 

 

 

 

g SWITCH
DRIVE UNIT ——
SPACER
a LOWER LIMIT
L _ SWITCH
’ - -" : ‘ofi\' - <
Gfl' OR\\I . ,
p
e
: y
o ~ 3in. x 2in. ECCENTRIC
L REDUCER :

COOLANT EXHAUST

GUIDE BARS, ——_
4 AT 90°

BEADED POISON ELEMENTS —<]

2in. CONTAINMENT THIMBLE —~|

REVERSIBLE DRIVE MOTOR

COOLANT TO
POISON ELEMENTS

ORNL-LR-DWG 67511

  
 
  
  
  
 
  
 
 
 
 

COOLANT TO DRIVE
ASSEMBLY

COOLING
GAS INLET

COOLING GAS
CONTAINER

-

POSITION INDICATOR
SYNCHRO TRANSMITTER

FIXED DRIVE SUPPORT AND
3in. CONTAINMENT TUBE

%in.0.0.-304 S.S.- FLEXIBLE
HOSE CABLE

SPRING LOADED ANTIBACKLASH
HEAD AND IDLER GEAR

o
\1 §\

16 in. RADIUS x 30° BEND

-

 

 

 

 

 

 

E
{
Efi

Figure 19. Control Rod and Drive Assembly
Figure 20.

39

 

Thermal Shield Components

 
40

pump and pump bowl are shown in Figures 21 and 22. The pump bowl is about
36 in. in diameter and contains the pump casing, gas stripping manifold,
sampler—enricher cage, and off-gas connections. It served as a surge tank
for the loop with a cover-gas pressure maintained above the operating salt
level. The removable pump and 75-hp motor assembly is about 8 ft tall and
consists of all the rotary elements and bearings of the pump. The assembly
is mounted on a 2 1/2-in.-thick plate that can move horizontally and ver-
tically to accommodate thermal expansion of the system. This was necessary
since the reactor position is fixed. The mounting plate is, in turn,

supported by two 8-in. horizontal I-beams attached to the cell structure.

2.5.4 Primary System Heat Exchanger

 

From the pump discharge the fuel salt passed directly through a 6.0 ft
length of 5-in. Schedule 40 pipe to the primary system heat exchanger
(Figures 23 and 24) which is a horizontal, shell and U-tube type, in which
the fuel salt circulated through the shell side and the coolant salt
through the tubes. It is of all-welded construction and made entirely of
INOR-8 except for the brazing material that sealed the tubes to the sheet.

The shell is about 16 in. 0.D. by about 8 ft 3 in. long and is 1/2 in.
thick including both the cylindrical portion and the heads. The fuel salt
entered at the U-bend end through a 5-in. Schedule 40 nozzle and emerged
through a 7 in. by 5 in. reducing nozzle at the bottom of the shell at the
tube-sheet end and flowed to the reactor inlet through a 17.2 ft length
of 5~in. Schedule 40 INOR-8 pipe. The coolant salt entered the top mani-
fold at the tube-sheet end and exited from the bottom manifold. Both the
inlet and exit nozzles are 5 in. diameter Schedule 40.

The heat exchanger contains 159 U-tubes which are 1/2 in. 0.D. with
a wall thickness of 0.042 in. The tube sheet is 1 1/2 in. thick. The
tubes are spaced and supported by three baffle plates and one barrier
plate (near the tube sheet) and in addition are laced with 1/4 in. x
0,017 in. INOR-8 straps to suppress vibrationms.

Due to the short lengths of interconnecting pipes and the immov-
ability of the reactor vessel, the heat exchanger, like the fuel pump, had

to be supported in a manner that allowed horizontal and vertical movement
ORNL- LR-DWG-56043-8

  
    
  
 
   
   
   
 
  
 
 
 
    
  
  
 
 
  
  
  
   
  
   
  

  

SHAFT WATER

COUPLING COOLED

. MOTOR

SHAFT SEAL

{ See Inset) ———— - ——

LEak [
DETECTOR LUBE OIL BREATHER
LUBE OIL IN

BALL BEARINGS

(Face to Face) BEARING HOUSING

BALL BEARINGS GAS PURGE IN

(Back to Back)

 

SHAFT SEAL (See Inset)

LUBE OIL OUT SHIELD COOLANT PASSAGES

{in Parallel With Lube Qil)
SHIELD PLUG

SEAL OIL LEAKAGE
ORAIN
LEAK DETECTOR GAS PURGE OUT (See Inset)

SAMPLER ENRICHER GAS FILLED EXPANSION

{Out of Section) SPACE
{ See Inset) ENON STRIPPER
BUBBLE TYPE {Spray Ring)
LEVEL INDICATOR SPRAY

OPERATING
LEVEL

 

To Overfiow Tank

 

Figure 21. Fuel Pump

1%
 

PHOTO 66693

—-—

 

Figure 22. Fuel Pump Motor and Rotor Assembly Showing Flange
Bolt Extensions

 
ORNL-LR-OWG 32036

FUEL INLET

     
 
   

Vo-in.-OD HEAT
EXCHANGER TUBE

| CROSS BAFFLES

THERMAL-BARRIER PLATE (3% OF DIA) .

   
  
    
 

COOLANT INLET

COOLANT-STREAM COOLANT OUTLET

SEPARATING BAFFLE
FUEL QUTLET

Figure 23. Primary Heat Exchanger

£y
 

il

Figure 24.

Primary Heat Exchanger Subassemblies

PHOTO 39450

 

Y

 
45

to compensate for thermal expansion. Two support saddles welded to the
shell supply support from a complex motion-adapting system which, in turn,

rests upon an assembly of 8-in. I-beams fixed to the cell structure.

2.5.5 Fuel Pu@p,OVérflow Tank

 

The primary system pump bowl has an overflow pipe and catch tank
(Figure 25) which was provided to avoid problems from inadvertent over-
filling of the system or unexpected volume expansion. The catch tank is
torus-shaped and fits around the pump intake line immediately below the
pump bowl. The tank is 30 in. 0.D. x 18 in. I.D. x 27 3/4 in. tall. The
wall thickness is 1/2 in. and the annulus between the inner and outer walls
is 5 in. wide. The 1 1/2-in. pump bowl overflow pipe extends from the top
of the catch tank through the bottom of the pump bowl to 1 1/2 in. above
the normal fuel-salt level. The tank is supported from the pump support
with a system of movable plates that allow horizontal motion to accommodaté}

thermal effects.

2.5.6 Fuel-Salt and Flush-Salt Drain and Storage Tanks

 

The primary system is provided with two fuel-salt drain tanks and a
flush-salt drain tank located in a shielded cell adjacent to the reactor B
containment vessel. Figure 26 is a process flow sheet for the drain tanks;:
and their auxiliary systems. In addition, a fuel storage and reprocessing?
tank is located in the fuel-processing cell. It is described in Section.
2.7.

Each of the two fuel drain tanks (Figure 27) is 50 in. in diameter
and about 86 in. tall, not including the steam dome and has a fuel-salt
capacity of about 80 ft3. Each is equipped with thirty-two 1 1/2-in.
cooling thimbles. The steam dome which is mounted atop the tank (Figure
28) contains l-in.-diameter cooling fingers extending into each of the
thimbles. Water boiling in the inner l-in.-diameter fingers in the thim-
bles refioved both residual and fission-product decay heat from fuel salt
store& in the tank. The steam was routed to an external condenser and the
condensate returned to the fingers in a closed loop. _

The flush-salt drain tank is also located in the drain-tank cell and

contained the flush salt used to cleanse the primary system prior to
 

 

Figure 25.

Fuel Pump Overflow Tank

PHOTO 70698

 

9%
 

T0 FUEL
STORAGE
TANK

r_.._JE

CELL AR

COOLER

1-15 sCra

tognos oot N §-40-3
1-40-¢

AIN_TANK CELL ‘

ELECTRICAL SERVICE AREA

AN T

LO! N0,

DRAIN TANK CONDENSER DATA

STRUCTURAL MATERIAL

JuBE SIDE FLUID

SHELL DIAMETER
HEAT TRAMSFER AREA

SHELL
TUBE

TO 840 LEVEL MALL
ANC DUCT 937

304 §5

 

WATER
7 | DRAIN TANK DATA

[RUCTUR BATERIAL o
381q. h.

PSI
130PSI

F
DESIGN COOLING RATE

 

 

 

 

 

r oo o q ELECTRICAL SERVICE AREA

foot in}-s8

CONTALMMENT
I ENCLOSURE WO, @
AR e—_

Figure 26.

DRAIN TANK CELL

T AUaILIARY
CHARCOAL BED

b -
r -40-89S

 

T G
T, VAFUR

CONDENING
SYSTEM

1

ACCESS
FLANGE

 

 

Fuel Drain Tank éystem Process Flow Sheet

 

FLUSH TANK DATA

DRAIN TANK CELL

LEGEND

—P5IG
—r
— NORMAL L/M

VALVE POSITIONS ART FOR NORMAL *
REACTOR OPERATION

15 1 HEATER CNNTROL
CIRCUIT

T L

OAR RIDBE NATIONAL LABORATORY
FUEL DRAIN TANK SYSTEM

PROCESS FLOW SHEET
M.S.R.

D-AA-A40882- B

 

 

 

 
QRNL-LR-DWG 61719

INSPECTION, SAMPLER, AND
LEVEL PROBE ACCESS

  
 
 
 
  
  
  
  
    
 
  
  

~ : | STEAM QUTLET
‘ STEAM DOME

v CONDENSATE RETURN

WATER DOWNCOMER INLETS

CORRUGATED FLEXIBLE HOSE

BAYONET SUPPORT PLATE
STEAM RISER

BAYONET SUPPORT PLATE

STRIP WOUND FLEXIBLE
HANGER CABLE

HOSE WATER DOWNCOMER

GAS PRESSURIZATION

AND VENT LINES INSTRUMENT THIMBLE

FUEL SALY SYSTEM
- FILL AND DRAIN LINE

 

 

 

 

- " SUPPORT RING i
.2 g FUEL SALT DRAIN TANK
’ i
- BAYONET HEAT EXCHANGER
THIMBLES (32) pt TANK FILL LINE
&
32 &
- . v
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v
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49

PHOTO 39404

3

A

i b i oo S e o LB aa e
1. e L o

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e

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ey

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r

 

 

Fuel Drain Tank Steam Dome Bayonet Assembly

Figure 28.

 

 
50

charging it with fuel salt. This tank has the same dimensions as the - .
fuel drain tanks except for being 2 in. shorter. Since it has no cooling
thimbles, its salt storage capacity is about 2 fe3 greater than that of a
fuel drain tank.

Each of the three drain tanks is supported by two columns resting on
the cell floor. The columns are attached to support skirts welded to
tanks just above the upper head circumferential weld. An intermediate
supporting arrangement between the columns and skirts allowed the tanks
to be weighed by a pneumatically-operated weighing cell. The tare weight
of each of the fuel drain tanks is about 7,000 lbs; the fully loaded
weight is about 17,000 1bs.

The drain connection between the reactor vessel and the drain tanks
consists of a 1 1/2-in. Schedule 40 INOR-8 pipe which extends from the
bottom of the reactor vessel through the shield wall between the reactor
cell and the drain-tank cell where it connects to the l1-in. pipes leading
from the tops of the drain tanks. During operation of the reactor, the

drain tanks were sealed from it by freeze valves. -

2.6 Reactor Secondary System

The reactor secondary system consists of the tube side of the pri-
mary heat exchanger, the coolant circulating pump, the salt-to-air radiator,
the drain and fill system, and the interconnecting piping. The coolant

salt is similar to the fuel salt except that it contains no fissionable

materials. Figure 29 is the process flow diagram of the coolant system

and its auxiliary systems.

 

2.6.1 Heat Exchanger
The heat exchanger is described in Section 2.5.4.
2.6,2 Coolant Circulating Pump

The coolant-salt pump is of the same type and overall size as the
fuel-salt pump described in Section 2.5.3. It does not, however, have
an overflow tank. The pump is rigidly mounted in its own shielded cell i:

which is above the level of the other cells (Figures 7 and 13). .
 

| | 51

 

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1 . RADIATOR DATA

EQUIPMENT

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"~~~  PUMP ; MEAT TRANSFER SURFACE 706 sg. 1.
DESIGN TEMPERATURE 1300°F

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. 9.9"H, 0

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GAS COOLANT PUMP DATA APPLICATION DIAGRAM
CONTAINMENT GAS CONTAWMENT VENT.
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TO FUEL SYSTEM -
cgc:lunn fRCa2e PROCESSING CELL : 2
DRAIN FREEZE VALVES
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Figure 29. Coolant System Process Flow Sheet

 
 

... -

52

2.6.3 Radiator

 

The radiator coil is an assembly of one-hundred twenty 30-ft-long -
"S"-shaped 3/4-in.-0.D. INOR-8 tubes (Figure 30) connected to vertical ) o
manifolds which, in turn, are connected to the 9-in.-0.D. inlet and outlet "
headers. The 5-in. Schedule 40 inlet line connects to the outlet from
the heat exchanger, and the 5~in. Schedule 40 outlet line goes directly
to the suction side of the pump.

The coil is enclosed in a housing (Figure 31) which is equipped with
vertically operated doors which regulated the air flow passing through
the coil and thereby the coolant-salt temperature. The total assembly is
mounted at the entrance of a double-walled steel duct leading to the 10 ft
diameter x 75 ft high steel heat-dump stack. Two 250-hp blowers supplied
the 200,000 cfm of air used to remove heat from the coil at the maximum
reactor power level of 10 MW. A separate cooling system used two 10-hp,
10,000-cfm blowers to supply air to the annulus around the duct. This was
necessary to prevent buckling and damage to adjacent concrete when the
coil exhaust air reached temperatures up to 1000°F under low-flow con-

ditions.
2.6.4 Secondary System Piping | .

Like that of the primary system, the secondary system piping is 5-in.
Schedule 40 INOR-8 pipe. The sections of inlet and outlet lines to
the heat exchanger which are within the reactor cell are about 36.3 ft and
32.4 ft long, respectively. The lengths and arrangement of the piping
both within and outside the reactor cell allowed it to accommodate thermal

expansion so that the pump and the radiator could be rigidly mounted.
2.6.5 Coolant Drain Tank

The coolant-salt drain tank is located in a shielded cell almost
directly below the radiator. The coolant~salt piping has low points on
each side of the radiator; a 1 1/2-in. drain line runs from each of these
to the drain tank.

The drain tank is 40 in. 0.D. and about 78 in. tall with a wall
thickness of 3/8 in. in the cylindrical portion. The dished heads are
5/8 in. thick. The tank and all its attachments are made of INOR-S8.

 

 
53

PHOTO 70358

 

 

 

 

 

 

 

 

W e T

.fl!-

 

 

Radiator Assembly

Figure 30.

 

 
54

OfRL-LR-DWG 3884182

BLDG. 7503, FIRST FLOOR

(ELEV. 852t -Oin)

 

  

 

 

Radiator Coil and Enclosure

Figure 31
55

2.7 Fuel-Processing System

Other than the reactor primary system and its associated drain
tanks, the only other system that contained large quantities of both unir-
radiated and irradiated fuel salt at any time is the fuel-processing
system. The components of this system which contained fuel salt and/or
fission products are located in a below-grade-level concrete-shielded
cell just north of the drain-tank cell (Figures 6, 7, and 32). The two
purposes of the processing were to clean both new and used fuel salt of
oxides and water by sparging with hydrogen fluoride and to recover uranium
from used fuel salt by sparging with fluorine. A simplified flow diagram
of the system is shown in Figure 33. Figure 34 is a complete flow diagram
showing both the main system and its auxiliary systems.

The sparging tank, generally called the "fuel storage tank', is the
only component of the system that contained fuel salt. A 1/2-in. Schedule .
40 pipe from this tank to the fuel-salt and flush-salt storage tanks |
was used to transfer salt to and from the primary system. The tank
(Figure 35) is 50 in. 0.D. and 116 in. tall. 1Its cylindrical section is
1/2 in, thick and the dished heads are 3/4 in. thick. All parts are made
of INOR-8. It is mounted on a pneumatically-operated weighing cell sup-
ported from the cell floor.

Other large items in the fuel-processing cell include the NaF-filled
impurity trap (Figure 36) used to strip undesirable fluorides from UFg
during fluorination and the 42 in. diameter by 84 in. tall caustic scrub-
ber tank used for HF neutralization. The remaining items are small com-

ponents, piping, heaters, and insulation.

2.8 Freeze Flanges

Mechanical-type joints were provided in the 5-in. piping of
the fuel~ and coolant-salt system to permit the major components to be
disconnected remotely and removed for maintenance or replacement.. The
locations of the five flanged joints are shown in Figure 12.

As shown in Figure 37, the design of the flange utilized a large
diameter face as a heat sink to maintain a barrier of frozen salt to pro-

tect the gasket from contact with molten salt. Each flanged connection
 

 

56

PHOTO 68576

 

 

Fuel-Processing Cell

Figure 32.

&
 

 

 

 

57

 

 

 

 

 

 

 

 

 

 

 

ORNL—-DWG 63-3123AR

 

 

 

 

 

 

 

 

 

 

 

 

 

    

 

 

 
    
   
   
   

 

 

 

 

 

 

 

 

 

 

   

 

 

 

 

SALT 200°F NaF ABSORBERS IN CUBICLE . |
SAMPLER i
[ o _ _ ‘
i
SALT U .
CHARGING , S
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Fv 22 S—
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O IQUID
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750°F SYSTEM
, NEUTRALIZER |
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Figure 33. Simplified Fuel-Processing System Diagram

 

 

 
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Figure 34. Fuel-ProceSsing System Process

|

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FUEL STORAGE TANK DATA

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FUEL PROCESSING
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58

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AREA WEST OF FPC

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fUBL. LOADING & ATORAMGE SYSTEM
INSTRUMENT APPLICATION DIAGR AN

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FUEL PROCESSING SYSTEM
PROCESS FLOW SHEET
e —HEATERS |
6 in. |||
INSULATION T H
- {-in. AIR I
| P SPACE I
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OUTLET

59

ORNL-DWG 65-2509

  
   
  

SAMPLER
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SALT.
A INLET
CAS GAS AND
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60

 

 

  

 

 

 

 

 
  

  

 

 

 

 

 

 

 

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LIFTING
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LIFTING
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Figure 36. Sodium Fluoride Filled Trap -

 

  

 

 

 
61

ORNL-LR-DWG 63248R2

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NSRSy T T
FLANGE {in. *—1 0.030-in. '
CLAMP—— | \GAP WIDTH
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- - - A - - - - 1

 

 

 

 

 

 

 

Figure 37. Freeze Flange and Clamp
62

also contains a leak detecting-buffer gas connection to the ring groove
area. The semicircular flange clamps are made of spring steel so that
they remain in place when forced around the flange with no bolting being
required. Figure 38 shows the installed guide arrangement for the clamps

and the simple type of tool required for their removal and installation.

2.9 Freeze Valves

The flow of molten salt in the drain, fill, and processing systems

was controlled by freezing or thawing a short plug of salt in a flattened

section of 1 1/2-in. pipe, called a "freeze valve". This method of valving

was necessary because no mechanical-type valve had been developed for
molten-salt service. These valves were closed (frozen) by a regulated
cooling-air flow through a shroud around the flattened section of pipe and
opened (thawed) by shutting off the air and applying electrical heat to
the valve. All valves, except the reactor drain valve, also contain a
volume tank located vertically nearby to always provide enough residual
salt in the line to form the salt plug.

There are twelve freeie valves in the reactor systems, all of which
are fabricated of 1 1/2-in. INOR~8 pipe. Six are installed in 1 1/2-in.
lines and six in 1/2-in. lines. One valve, which is in the reactor drain
gnd fill line is inside the reactor thermal shield, six are in the drain-
‘tank cell, three are in the fuel-processing cell, and two are in the

coolant cell. Figures 39, 40, 41, and 42 show the various arrangements

and details of the twelve valves. The locations of the valves with respect

to other equipment are shown in the process flow diagrams (Figures 11, 26,
29, and 34). |

2.10 Ssalt Syétems Heaters and Thermal Insulation

All salt-cohtaining components and pipes in the MSRE are thermally
insulated and equipped with electrical heaters capable of maintaining the

salt above the liquidus temperature of 850°F. Because of the diversity

of sizes, shapes, orientation, and accessibility of the items to be heated,

a variety of both heater types and insulating methods and materials were

used.

 
Guide
Bars

Clamp —

1

 

 

 

 

Pin
Joint

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

‘ i
Representation of 1
Clemp Operator Tool ™\,
|  Clemp
Beam
) =

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- |

 

 

 

 

 

 

 

o

Putting Both Clemps On

 

 

 

 

ng Lower Clamp

Figure 38. Freeze Flange Clamping Frame Showing Assembly |
' and Disassembly ' -

ORNL DWG 64-8821

 

£9
ORNL-DWG. 64-6898

            
       
  
   

   
 
 

 

 

' THERMOCOUPLES COOLING GAS BELLOWS
SHROUD
THERMAL N 10 REACTOR
INSULATION _ COOLING GAS (D . B __,Egfiaj”"
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THERMOCOUPLE

M XXX '“ / “ SHEATHED
.‘ ’ oooe 1
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OUTLET

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E

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e e

COOLING GAS
INLET

COOLING GAS

OUTLET
THERMOCOUPLES

Figure 40. Freeze Valve in Lines 107, 108, 109, and 110i

G9
 

 

 

NOTE

NOT SHOWN.

THERMAL

 

ALL THERMOCOUPLES

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Figure 41.

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Freeze Valve in Lines 111 and 112

ORNL-DWG. 64-6900

99
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ELECTRIC RESISTANCE
HEATING ELEMENTS

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: CERAMIC
ELECTRIC RESISTANCE
HEATING ELEMENT

.......

  

CALROD

X il e : HEATER HEATERS
SN v LEADS

CALROD

HEATERS

    
  
 

f e —amm e ——— ==

   
    

COOLING AIR

COOLING AIR
INLET

INLET THERMOCOUPLES

Figure 42, Freeze Valve in Lines 204 and 206

L9
68

With few exceptions, salt-containing components and piping within the
reactor and drain-tank cells are heated with remotely removable heating sys-
tems. Consequently, flexible leads and remotely operable disconnects were
required for each heater unit. This power feed system, the bulky heater and
insulation units along with their respective support structures constitute a

very large portion of the total contaminated material within these cells.
2.10.1 Reactor Furnace

The inside of the thermal shield which encloses the reactor vessel is
insulated to a builtup thickness of 6 in. with ceramic insulation covered
with 16-gage 304 stainless steel sheet. The ll-in.-wide annulus between
this insulation and the reactor contains electrical resistance-type heaters
to form a furnace surrounding the reactor.. The heaters are 126 vertical
lengths of 3/8-in.—0;D., 0.035-in.-thick-walled Inconel tubing, each
8 ft 7 1/2 in. to 9 ft 11 in. in length, through which electrical current
- was passed. The heater tubing is in the form of 63 U-tubes which are
'arranged in nine removable sections of seven U-tubes each. Each U-tube is
contained in a 2-in.-0.D., 0.06 —in.-thick wall 304 stainless steel thimble

which is suspended from the top cover of the thermal shield.

 

2.10.2 Fuel-Salt-Pump Furnace

The lower half of the pump bowl, a 3-ft-long section of the pump suction
line, and the overflow tank were a;l heated in a common furnace which is
51 1/2 in. 0.D. by 66 in. tall. The heaters are 3/4-in.-diameter straight
tubes of 304 stainless steel containing ceramic~positioned resistance heat-
‘ing elements at the lower ends. Five of the heaters are about 8 ft long and
nine are 7 ft long. These 3/4-in.-0.D. heaters are contained in 1-in.-0.D.
304 stainless steel tubes. All the heaters were installed in assemblies
with lifting bails to simplify replacement.

The outer walls and bottom of the furnace are 5-in.-thick ceramic
block insulation covered with 20-gage 304 stainless steel sheet. The fur-
nace is suspended from the fuel-pump support plates and moved with the pump
in response to thermal effects. The heater elements have collars which also

rest on the support plate.

1, ‘f'.'
+ yoor by

 
69

2.10.3 Coolant-Salt-Pump Heaters and Insulation

Heat was applied to the coolant-salt pump bowl by fourteen 6 in. x
8 in. x 5/8 in. thick flat-plate ceramic heater units. Six of the heaters
are equally spaced at the bottom of the pump bowl and eight are arranged
vertically around the sides. The heaters are mounted in brackets in a 304
stainless steel basket which is hung by fourlhooks from the pump structure.
The outside of the heater basket is insulated fiith 4 in. of asbestos-

based insulation covered with asbestos finishing cement and glass cloth.

2.10.4 Fuel- and Flush-Salt-Drain-Tank Heaters and Insulation

 

The three drain tanks were heated by cylindrical furnaces made up of

insulated tanks with removable lids and removable heater units. The heaters
are located within the annuli between the drain tanks and furnace tanks.

Each furnace contains seven removable heater units spaced around its respec-

tive drain tank.

The outsides and bottoms of the furnaces are insulated by two 2-in.-
thick layers of asbestos-based insulation enclosed in l6-gage 347 stainless
steel. The removable furnace lids contain ceramic fibers as the insulating

material.
2.10.5 Fuel-Storage-Tank Heaters and Insulation

The fuel storage tank in the fuel-processing cell was heated by four
sets of heaters at the bottom, the lower half, the upper half, and the top.

Each heater had an installed spare and was not replaceable. The top and

side heaters are tubular, and the bottom heater is made up of flat ceramic-

plate units. The heaters are enclosed in 6 in. of asbestos-based insulation

finished with fiber glass cloth and insulating cement.

2.10.6 Coolant-Salt-Drain-Tank Heaters and Insulation

 

The coolant-salt drain tank was heated on the sides by thirty-two
0.315 in. 0.D. x 74 in. long tubular heating units and on the bottom by

sixteen flat ceramic heater plates.
70

The tank is insulated by a 5-in.~thick layer of ceramic-block insu-
lation applied over a 20-gage 304L stainless steel shell which séparates-
~ the insulation from the heaters. The insulation is. finished with fiber

glass cloth and insulating cement.
2.10.7 Heat-Dump Radiator Heaters and Insulation

The radiator coil is mounted in an insulated steel enclosure equipped
with large (8 ft tall by 11 ft wide) insulated vertically operated doors
- on the inlet and outlet sides of the coil. Heating was provided by 60
tubular heaters mounted vertically 3 1/2 in. apart across both faces of
the coil. These range in length from 48 in. to 102 in. The top and
bottom of the coil were heated by sixty 18 in. long by 7 1/2 in., wide flat
ceramic heater plates attached to steel baffle plates. The inlet and out-
let salt headers were heated by a total of forty-~two 4 in. by 12 in. flat
ceramic heater plates enclosed with 20-gage 304 stainless steel cans.

All the inside surfaces of the enclosure including the doors are
covered with’insulating ceramic block or insulating board and protected
with a sheath of 1l6-gage stainless steel where air erosion could be a

problem.
+2.10.8 Piping Heaters and Insulation

The heater types and insulating methods for the salt-bearing piping
depended primarily upon location and accessibility. All horizontal sections
of the fuel-salt and coolant~salt 5-in. pipes within the reactor cell
and‘the 1l 1/2-1in. drain lines in the drain-tank cell are equipped with
removable combined heater and reflective insulation modules as shown in
Figure 43. These contain molded ceramic heater plates arranged to heat
the top and sides of the pipe and rest upon permanently installed insu-
lated bases. The reflective metal insulation consists of nine layers of
0.006-in.-thick stainless steel and one 0.002-in.-thick layer of pure
silver encased in a stainless steel shell. The vertical leg of the fuel-
salt pipe jdst below the heat exchanger has permanently installed tubular
heaters covered with reflective insulation.

‘The section of the 1 1/2-in. drain line from the bottom of

the reactor vessel to the freeze valve manifold in the drain-tank cell

 

e
71

PHOTO 70759A

   
   
  

FEMALE DISCONNECT

TERMINAL BOX WITH MALE DISCONNECT

REMOVABLE LAP JOINT CLOSURE

!

!

Ptz it e 0 o

    

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Bid &
Bulfl. 8|

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Figure 43. Removable Heater for 5-In. Pipe

 
72

was heated by passing an electric current through the line itself. This por-

tion is insulated with permanently installed asbestos-based insulation.

Most of the 1 1/2-in.-diameter piping in the drain-tank cell was
heated and reflective insulated with the removable modular units. The
remainder, including the line to the fuel-processing cell, were heated
with tubular heaters and insulated with permanently installed asbestos-
based insulation.

All salt-bearing pipes in the fuel-processing cell were heated with
permanently installed tubular heaters and insulated with asbestos.

All the coolant-salt-bearing piping in the coolant and radiator
enclosures were heated by tubular heaters strapped to the pipes under

asbestos-based insulation.
2.10.9 Heat-Exchanger Heaters and Insulation

The heat exchanger was heated and insulated with removable modular

heating and reflective insulating units of the same type used for the 5-in.-

diameter pipes except that they were made to fit the 16-in.-0.D. shell.

2.10.10 Heater and Thermocouple Leads

 

The heater electrical supply leads within the reactor cell and drain-
tank cell are 1/2- and 3/8-in.-0.D., copper sheathed, mineral-insulated
multiconductor cables having flexible sections between the cable terminus
and the heater connector. The flexible length is made with ceramic-beaded
nickel alloy wire sheathed in 3/4-in.-0.D. flexible stainless steel hose.
The reactor cell contains 79 cables ranging in length from 5 to &15 ft
long, and the drain-tank cell contains 88 cables of about the same length
range. The flexible power leads terminate at junction boxes or disconnect
boxes that are conveniently located throughout the cells. A transition
from the flexible leads to the copper-sheathed cables is made at these
boxes. The cables then are routed via cable trays to the containment cell
penetratiofislfl‘Tfiéfhéater power cable system constitutes a large volume
of material dispersed throughout the entire volume of the cells.

There are ovér 1,050 thermocouples installed in the MSRE. A prepon-
derance of these are installed on the salt-containing components and

piping. In all cases, except as noted below, the thermocouples are duplex,

I
»

r

Lo owmy
73

mineral-insulated chromel-alumel wires in a 1/8-in.-0.D. Inconel sheath.
The thermocouples are attached to lugs on the surface of the pipe and com-

ponents by means of a small welded tab. The leads are strapped to the

 pipe or component and are routed in bundles to exit points from the insu-

lation and on to disconnect locations. The number, routing, and manner

of attachment of the thermocouples will present problems to be dealt with
when considering methods of removal. A few 1/16-in.-0.D. mineral-insulated,
Inconel-sheathed singie-conductor leads were used in special power moni-
toring and safety temperature measuring thermocouples. These are located
only on the réactor outlet nozzle and on the radiator inlet and outlet
headers.

Transition from the Inconel-sheathed couple leads to multiconductor,
mineral-insulated, copper-sheathed cables was made at conveniently located
disconnect boxes within the cells. The copper-sheathed cables were routed
via cable trays to cell penetration points. ' The total_system including
leads; cables, disconnects, support structures, trays, and junction boxes
constitutes a large volume of material that is dispersed over the entire

cell areas.

2.11 Sampler-Enricher

The fuel-salt and coolant-salt pump bowls and the fuel storage tank
in the fuel-processing cell are equipped with 1 1/2-in. Schedulé 40 access
pipes extending to shielded enclosures above the respective cells (Figure
44). These were used for taking samples of the salts as required for
analyses and for adding fuel, or other salt constituents, to the salts
during operation. The samples wére taken simply by lowerifig open capsules

attached to cables through the access pipes into the salt contained in the

}pump bowls and raising them through appropriate containment seals into

shielded transfer casks. Enrichment was accomplished by lowering a cap-
sule filled with concentrated fuel salt into the fuel pump bowl and
allowing the salt to melt out. _

The access pipes are about 14 ft long and have a bellows-sealed
expansion joint at about mid-length. The portion of the pipes below the

expansion joint is INOR-8 and the portion above it is 304 stainless steel.

1
74

ORNL-DWG 63-5848R

 

 
 
 
   
  

 

7 ' REMOVAL VALVE AND
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// PERISCOPE
CAPSULE DRIVE UNIT--KZ /)% LIoHT

CASTLE JOINT (SHIELDED
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4

T @ 0 CONTAINER
= S LEAD SHIELDING
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DISCONNECT - ME

 

 

 

 

 

 

 

OPERATIONAL AND
MAINTENANCE VALVES

 

 

 

 

 

 

 

 

 

 

 

 

 

TRANSFER TUBE
(PRIMARY CONTAINMENT )}~y

 

 

 

1

LATCH STOP —

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CRITICAL CLOSURES
REQUIRING A BUFFERED
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Z MIST SHIELD ! 0 ! 2
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Figure 44. Schematic Representation of Fuel-Salt Sampler-
Enricher Dry Box
75

The fuel-salt sampler-enricher is a complex mechanical, electrical,
and pneumatic system, heavily shielded and contained, and is equipped
for remote loading into and unloading the capsules from the sampler mecha-
nism and for transferring the capsules between the sampler containment

and shielded transport carriers. Since the sampler mechanism was alter-

‘nately exposed to the pump bowl atmosphere and to the sampler containment

enclosure as well és to the exposed salt in the capsules, all equipment
inside the enclosure is highly contaminated with fission products.

The coolant-salt sampler is a far simpler manually-actuated
system with appropriate interlocking buffer zones which did not reqfii;e
heavy shielding.

The fuel storage tank in the fuel-processing cell is equipped with a
shielded sampler system similar to that for the fuel pump bowl but less
complex. Since it wés used infrequently and was not subject to deposition
of daughter products of short-lived fission-product géses, it is far less

contaminated than the brimary system sampler-enricher.

_2.12 Nuclear Instrumefitation

Nuclear instrumentation ionization chambers were accommodated by a
single 3-ft-diameter slanted thimble shown in Figures 45 and 46. The lower
end of the thimble is welded to the reactor cell containment shell and the

upper end is embedded in earth fill and concrete. A bellows-type expansion

. joint between these regions accommodates thermal expansion and contraction.

The thimble contains four 5-in.-I.D. and six 4;in.-I.D; guide tubes
for ionizatibn chambers. These tubes are supported by four bulkheads
appropriately spaced aiong the length of the thimble.

For shielding and cooling purposes the thimble was kept full of water.
The water contained dissolved lithium nitrite and lithium borate which
served as a corrosion inhibitor and enhanced the neutron-shielding prop-
erties of the water. A dip tube terminating at the bottom of the thimble
allowed a small pump to circulate the water to minimize thermal gradients

and keep the corrosion inhibitor evenly dispersed.
MIDPLANE
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ORNL-DWG 64-625R
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ORNL-DWG 64-984R

 

 

 

 

 

 

 

 

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Plan View of Nuclear Instrument Penetration

Figure 46.

*USED ONLY DURING
INITIAL CRITICAL TESTS
78

2.13 Accessory Systems

In addition to the salt-containing systems, eleven accessory systems
required the use of piping or ducts either within the containment cells
or connected to them. These were: (1) the cover-gas system; (2) the leak-
detector system; (3) two component-cooling systems; (4) the cooling-water
system; (5) two lubricating-oil systems; (6) the off-gas disposal system;
(7) the containment ventilation system; (8) the liquid-waste system; and

(9) the instrument air system.
2.13.1 Cover-Gas System

The cover-gas system supplied purified helium for use as an inert
gas above the fuel and coolant salts in the pump bowls and drain tanks,
as a carrier for removing fission-product gases from the system, as a
‘pressure source for transferring salt frofi one vessel to anbther, as a
means of pressure control in the salt systems, and as a cover gas for oil
storage tanks in the fuel and coolant-salt pump lubricating systems. In
addition, a part of the helium purge through the pump bowls and the fuel-
pump overflow tank was introduced through bubbler lines to measure the
salt depths. All helium was discharged from the various systems to the
off-gas disposal system; none was recycled.

Pressure monitoring and flow controi instruments for the fuel-salt-
pump cover-gas connections were located within containment enclosures
located outside the reactor containment cell with individual 1/4-in.-0.D.
stainless steel lines encased with 1/2-in. Schedule 40 pipe penetrating
the cell wall and connection to the pump. One line introduced the main
purge flow at the labrynth seal on the pump shaft. Two lines entering
the top of the pump bowl and terminating at the bottom of the bowl served
as salt-level-monitor bubblers. One line entering the top of the bowl was
used as the reference pressure tap for the bubbler system. Three similar
lines to the overflow tank were used to measure its salt level in the same
manner. The coolant-salt pump bowl is also equipped with two bubbler
tubes, a reference tube, and a purge supply tube.

Helium is also supplied to each of the three tanks in the drain-tank

celllby 1/4-in. stainless steel tubes in 1/2-in. stainless steel pipe and
79 .

in a similar manner to the fuel-processing system. The gas was used as
the cover atmosphere for stored salt and to pressurize the tanks to trans-
fer molten salt out of the tanks.

The cover-gas system supplies helium for the gas volume in the oil
storage tanks in the salt-pump 1ubricéting systems and provides purge

gas for the fuel and coolant samplers and the graphite sampling equipment.

2.13.2 Leak-Detector System

 

A leak-detector system using pressurized helium was used to monitor
all pipe flanges where leaks could have caused the escape of radioactive
materials or could have caused leakage of coolants or lubricants important
to operation and safety. Another use of the system was to show when
remotely coupled flanges were properly sealed. Figure~47 illustrates the
use of the pressurized gas to check the leak-tightness of gasket seals.
The helium was supplied from the cover-gas system through 1/4-in.-0.D.
stainless steel tubing having a wall thickness of 0.083 in. All important

‘pipe flanges in the reactor and drain-tank cells have one to two lines of

the leak-detector system connected to them, depending upon whether they
were individually monitored or were a part of a monitored group. Through-
out the reactor system and its accessory systems, V100 flanges were gas-

monitored.

 

2.13.3 Lubricating-0il Systems

Both the fuel-salt and coolant-salt pump bearing assemblies were
lubricated and cooled with forced-flow oil systems. The oil reservoir
tanks and the pumps are located in the shielded east tunnel. All oil
piping to the pumps is Schedule 40 stainless steel. A 3/4-in. pipe
delivered oil to the fuel-pump bearings, and a second 3/4-in. pipe supplied
0il to cool a shield block located between the pump bowl and motor. A
1/2-in. pipe connecting the gas space in the o0il reservoir to the pump
bearing assembly equalized the pressure between the two regions. The oil
supplied to the bearing and shield block combined to return to the reservoir
through a single 1l-in. pipe. The small amount of o0il that leaked downward
past the labrynth seal below the bearing was swept by helium from the cover-

gas supply into a 1/2-in. line that carried it to a shielded catch tank
ORNL IWG 64-8833 .

-/ / Vs
LEAK DETECTOR ‘
LINE FROM LEAK

DETECTOR STATION

 

SEALING SURFACES
—— OVAL RING GASKET
\ D
*

SO ASSAN

 

 

 

 

 

 

AL

 

aaline

 

 

SEALING SURFACES

 

LEAK DETECTOR
LINE TO NEXT
FLANGE OR MAY
BE CAPPED OFF

 

 

 

 

 

FLANGES

Figure 47.

Schematic Diagram of Leak-Detected Flange Closure

08
.'.a-

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81

in the special equipment room. Because of the low flow rate through this
pipe, it is shielded with 1 1/2 in. of lead to reduce radiation damage

to the oil. The éoolant salt pumps have the same arrangement of piping
from their lubricating oil supply except that the 1/2-in. line to the catch

tank is not lead-shielded.

2.13.4 Component—-Cooling Systems

The reactor-cell and drain~tank-cell atmosphere gas was circulated
through an external cooling system and returned to the cells through a

distribution system to cool freeze valves, the upper part of the fuel pump

bowl, the control-rod drives, the graphite sampler nozzle, the ipéide and

outside of the reactor access nozzle, and the off-gas exhaust line. The
external equipment consists of two 75-hp positive;diSplacement blowers
sealed in 6-ft~diameter, 8-ft-tall steel containment tanks located in the
adjoining special equipment room. The containment tanks are connected by
10-in.~-diameter pipes to a 30-in.~diameter containment ventilation pipe
which, in turn, is connected to the reactor cell containment vessel., Supply
gas for the blowers was taken from inside the containment tanks. The dis-
charge from the blowers passed through a vertical 8-in.-diameter, 9-ft-long,
shell-and-tube, water-cooled heat exchanger also located in the special
equipment roofi. The gas then flowed to a 6-in.-diameter header in the
reaétor cell from which it was distributed to the components to be cooled.
The lines to the pump bowl and the off-gas exhaust line are 3-in.-diameter
pipe; the line to the reactor drain freeze valve is 1 1/4 in. in diameter;
the line to the control-rod drives i1s 1 in. in diameter; and the lines to
the reactor access nozile, the graphite samplér nozzle, and the freeze
valves in the drain-tank cell are all 3/4 in. in diameter. After cooling
the several components, the gas discharged directly back to the cell atmo-
sphere and then returned to the blower suction via the cell containment
ventilation line.

The freeze valves in the coolant and fuel-processing cells were cooled
by atmospheric air supplied by a 5-hp positive displacement blower located
in the blower house at the southwest cbrner of the reactor building. The
supply header from this blower 1s 3-in.-diameter pipe. The distribution

lines to the two freeze valves in the coolant cell are l-in.-diameter carbon
82

steel, and those to the three freeze valves .in the fuel-processing cell are
3/4-in.-diameter carbon steel. After passing over the surfaces to be
cooled, the air discharged directly to the cell atmosphere was then

exhausted through the cell containment ventilation system.

2.13.5 Cooling-Water System

 

The cooling-water system is made up of two parts: the cooling-tower
water system and a closed treated-water system cooled by the cooling-tower
water. | . |

The cooling-tower water system was cooled by a forced-draft cooling
tower located southwest of the reactor building. From the cooling-tower
basin, water was circulated by either of two 547-gpm pumps to the treated-
water heat exchanger, the fuel-salt and coolant-salt pump lubricating-oil
reservoirs, the two fuel-drain-tank steam condensers, the coolant cell
coolers, the fuel—prdcessing caustic scrubber and hydrogen-fluoride trap
cooling coils, the charcoal beds in the off-gas dispersal system, and the
steam condenser that supplie& makeup condensate for the treated-water system.
It was also used to cool other items not directly related to the reactor
system. All the piping in this system is carbon steel.

The treated-water system is a closed cooling system filled with steam
condensate to which a corrosion inhibitor was added. This system was used
to cool equipment in which it was possible for the water to become radio-
actively contaminated. The water was circulated by either of two 320-gpm
pumps located in the blower house at the sduthwest corner of the reactor
building. The water passed through the tubé side of a shell-and-tube heat
exchanger located in the diesel house to a header from where it was piped
to the items to be cooled. The return lines terminate in a common header
leading to the pump suction side. A surge tank connected to the system was
used for volume control, makeup, and for a&ding the chemical corrosion
inhibitor. |

Treated water was use& to cool the reactor thermal shield, the fuel-
salt and coolant-salt pump motors, the two reactor cell air coolers, the
draifi-tank—cell air coolers, the nuclear instrumentatiQfi access thimble,

and the component-cooling systems gas heat exchanger and blower lubricating
.
@

83

oil system. The in-cell piping for this system is stainless steel ranging
from 1 in. to 3 in. depending upon the flow requirements.

All water lines penetrating the containment cells contained check
valves on thg inlet leg and a pneumatic safety block valve on the exit
leg with a rfipture disc relief to the vapor condensing system attached to
the trapped volume. The thermal shield cooiant return line contained a

degassing system for the removal of radiolytic gases.

2.13.6 O0Off-Gas Disposal System

 

The off-gas disposal system handled three types of gas flow: (1) a
continuous ‘discharge of helium and gaseous fission products“from the fuel-
salt pump'bowl; (2) intermittent discharges of contaminated helium during
s&lt-transfer operations; and (3) flows of up to 100 cfm of cell atmosphere.
The first two of these off-gas flows passed through a complex system of ‘
holdups, filters, and absorbers and were extensively monitored for activit&zr
prior to being discharged into the containment ventilation system effluent"

upstream of the final filters and stack discharge. The ejected cell gas

. was routed, after monitoring, directly to the containment ventilation

connection.

Helium sweep gas and gaseous fission products were drawn from the fuel
pump bowl and overflow tank through 1/2-in. stainless steel pipes which
merge and connect to a 4-in. pipe a short distance from the pump. This
4-in. pipe with a serpentine section is routed around the inside surface
of the reactor cell with a total length of 68 ft providing a holdup volume
of about 6 ft3 and a gas residence time of about one hour. The line con-
tinues then as 1/2-in. pipe through the cell wall penetration and then as
1/4-in. stainless steel pipe through the coolant drain-tank cell to a
sealed instrument box in the ventilation house. After passing through
pressure-control and monitoring systems, the line is joined by the 1/2-in.
Schedule 40 line from the fuél-pump seal and continues as 1/4-in. stainless
steel pipe to a second holdup volume in the charcoal-trap cell.

The charcoal-trap cell is a 10 ft diameter by 22.7 ft deep pit made of
reinforced concrete with a 3-ft-thick removable concrete cover. The cell
was kept filled with fiater, supplied by the cooling-tower water system, to

remove the decay heat from fission products trapped by the charcoal.
84

The second holdup volume consists of éix 19.8-ft lengths of 3-in.
pipe arranged as close-packed vertical "U" bends connected in séfies.

From the holdup volume, a 1/2-in. stainless steel pipe leads to the main
charcoal-trap ménifold., The main charcoal trap consiéts of four parallel
charcoal-filter sections each of which is made up of 80 ft of 1 1/2-in.
stainless steel pipe, 80 ft of 3;in. stainless steel pipe, and 80 ft of
6-in. stainless steel pipe arranged as compact vertical "U'" bends con-
nected in series. The weight of charcoal in each section is 725 1bs.

From the charcoal traps, a 1/2-in. stainless steel pipe'connects to a
1 1/2-in. pipe in the ventilation house. This line leads to the
containment ventilation system particulate filter enclosure where the gas
was filtered and diluted by flows from otfiér areas before being dischgrged
to the atmosphere through a 100-ft-tall steel stack by one of two 21,000-
scfm fans. _

One-quarter-inch or 1/2-in.-diameter stainless steel off-gas pipes
connected to each of the fuel-salt drain tanks, the graphite sampler, the
sampler-enricher, the coolant pump bowl and shaft seal, the lubricating-
0oil reservoirs, the coolant-salt drain tank, and the reactor and drain-
tank cells allowed these items to be continuously or intermittently purged
to the off-gas system. Those items which did not normally contain radio-
active gases but could under abnormal conditions were vented, past monitors,
directly to the particulate-filter enclosure. The fuel drain tanks and
flush-salt tank were normally vented through the auxiliary charcoal trap
located in the charcoal-trap cell but could be valved to discharge through
the reactor cell holdup volume and thence to the main charcoal traps.

The auxiliary charcoal trap consists of two vertical ~19-ft-tall "U"
bends, made of 6-in. stainless steel pipe, which are connected in series.
The trap contains 530 1bs of charcoal. The discharge from the trap merges
with the discharge line from the main charcoal traps ahead of the

particulate-filter enclosure.

2.13.7 Containment Ventilation System.

 

In addition to receiving and diluting-the reactor off-gas discharge,
as previously discussed, the containment véntilation system provided a

continuous flow of air or maintained a negative pressure through all areas

 
85

where radiocactive or beryllium contamination was likely to occur other
than the reactor and drain-tank cells. During maintenance operations,
however, this system was used to provide 100 linear feet per minute in-
flow through openings in the reactor and drain-tank cells made by removing
séctions of the top shields.

A system of steel ducts from the stack area draws air from the reac-
tor building through the six smaller shielded cells, the electric ser-
vice areas, transmitter room, service tunnel, special equipment room, and
coolant cell and from the main high-bay area. Air is also exhausted from
the ventilation house and charcoal-bed cell by this system. Many'small
containment enclosures were either exhausted or maintained at negative
pressures by this system.

Alr flow through the system is induced by either of two 21,000-cfm
centrifugal fans located at the base of the 100-ft-tall steel discharge
stack. Before discharge up the stack, the air passes through roughing andfll;
high-efficiency filters. ;

The connection to the combined reactor and drain-tank cells is a
30-in.-diameter duct leading from the bottom of the southwestern sector of
the reactor cell containment vessel. This duct was normally kept closed By
two motor-operated butterfly valves installed in series. Negative pressufe.
in the sealed cells was maintained by discharging a small portion of the )
recirculating component-cooling-system flow to the off-gas system.

Figure 48 is a schematic flow diagram of the containment ventilation

system.
2.13.8 Liquid-Waste System

Not including the sanitary sewer system, the MSRE building énd its
auxiliary structures have three waste water accumulation containers
(Figure 49) equipped with appropriate volume and radiation monitors and
with discharge pumps which route the waste water either‘to the ORNL radio-
active liquid-waste treatment system or to a drainage ditch.

Water discharged by steam- or air-operated jet-type ejectors from
the reactdr cell, the drain—tank cell, and the auxiliary cells and water
from decontamination sinks flowed directly to an ll-ft~diameter, 16-ft-
tall, 11,000-gallon stainless steel waste storage tank located in the
 

 

 

 

 

 

 

 

 

 

 

 

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Ventilation System

Figure 48.

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- 88

liquid-waste cell. A 140-gpm pump located in the remote maintenance
practice cell is used to dischargé accumulated water from the tank to the
ORNL liquid-waste treatment system.

A 42 in., diameter by 50 in. tall stainless steel filter tank is also
located in the liquid-waste cell. The filter is a 34-in.-deep bed con-
sisting of graded sand and gravel. The intended purpose of this filter
was to clarify water circulated through a decontamination tank proposed
for the decontamination cell. The decontamination tank, however, was
never installed due to lack of need.

A3 ft by 3 ft by 8 ft deep sump in the below-grade 8 ft by 16 ft by
-7 ft high sump room located at the northeast corner of the special equip-
ment room (Figure 6) is the lowest point of the MSRE complex and is used
to collect normally uncontaminated waste water from all areas of the MSRE
complex. These include the radiator air-duct floor, the blower house,
blower-house ramp, west tunnel, service room, service tunnel, coolant cell,
ventilation house valve pit, and French drains from the building founda-
tions and charcoal-trap cell. Water from this sump is discharged by either
of two 75-gpm pumps, located in the sump room, to a 2 ft by 3 ft by 6 ft
deep concrete catch basin located just west of the charcoal-trap cell. From
the catch basin, the water drains through a 150-ft-long, l2-in.-diameter
reinforced concrete pipe to a drainage ditch.

A 55-gallon stainless steel ‘drum located in the sump room was used to
collect drainage from the ventilation stack base and from the filter pit
since water from these sources could be contaminated. The drum was equipped
with a continuous radiation detector alarm as well as a high liquid level
alarm. Each batch of accumulated liquid was sampled prior to being trans-
ferred via a 200-gpm pump, also located in the sump room, from the drum to
either the liquid-waste storage tank or directly to the catch basin,

depehding upon whether the water was contaminated or not.

2.14 Vapor Condensing System

As illustrated in Figure 50, the MSRE is equipped with a vapor con-
densing system to accommodate overpressurization of the reactor containment

cell in the event of a catastrophic accident that caused mixing of hot fuel

 
ORNL-LR-DWG 67162R

40 ft FROM REACTOR BLDG. |

 

-y

2-in-DIA VENT LINE .
TO FILTERS AND STACK~_ /
SPECIAL EQUIPMENT ROOM | N\

IN REACTOR BLDG.

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FLOOR ELEV. ' GROUND ELEV. FILL
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~ 10-ft DIA x 23-ft HIGH - > SHALE
1800 f13-1200 113 OF WATER 7 )
ELEV. 824 f1

RS TR

-

Figure 50. Diagram of Vapor-Condensing System '

1
v

68
90

salt and the water used in the cell for cooling and shielding. This
equipment, consisting primarily of a vertical underground water tank and
a shielded horizontal gas storage tank, is located about 60 ft from the
southeast corner of the MSRE building. A 12-in.-diameter carbon ‘steel
line from the system ties into the 30-in. reactor cell ventilation pipe
just upstream from the normally closed butterfly val§es. Rupture discs
in the main 12-in. line and the 4-in. bypass- line are designed to rupture
at 20 psi and 15 psi, respectively, to cause the system to respond auto-
matically to overpressurization of the reaétor cell and to require that
the smaller-diameter path be opened first to reduce the dynamic impact on

the condensing tank.

3. MSRE PRESENT CONDITIONS

From shutdown of the MSRE in 1969 until now, portions of the reactor
system have undergone considerable change from the original operating
conditions. These changes will not, however, significantly affect the
effort required for decommissioning. Beginning at shutdown: (1) all
systems were secured or modified for safe standby; (2) a post-operation
examination program was initiated; (3) the system was placed under a con-

tinuing surveillance program; (4) excess material and equipment removal

began; and (5) nonhazardous building space was made available for offices,

shops, and laboratories for research and maintenance groups.

3.1 Securing the Process Systems

In general, preparing for safe standby involved deactivation of

process systefis so as to minimize surveillance and to prevent mishaps due

to freezing, fire, or rain in-leakage; securing the primary system to safe-

guard the salt solutions, including the 233y fuel; and protecting against
radiation and contamination hazards. The salts were all stored in their
respective drain tanks; the cooling water systems were drained, and lines
penetrating the containment cells were disconnected and blanked at the
cell walls; the cbvér—gas system and other service lines were disconnected
and blanked at penetrations; process electrical systems were deactivated

and circuits locked open; the instrument and service air systems were shut

 
-

% 4 '
.
.

91

down and temporary gas supplies (nitrogen cylinders) were installed at
necessary locations; selected radiation monitors with local indicator
alarms were retained and remote alarms installed at the ORNL Waste Moni-
toring Center; selected temperature sensors from the stored salt and cell
atmosphere were tied into a local recorder-indicator; and the off-gas and
containment ventilation systems were retained complete with the radia-
tion and flow monitoring of the stack flow with remote alarms to the Waste

Monitoring Center added.

3.2 Post-Operation Examination

The post-operation examination program was for inspection of the pri-
mary system and for obtaining material specimens for technical evaluation.

The sampler-enricher capsule cage was excised from the fuel pump bowl
for examination. This operation required the cutting loose or displacing
of auxiliary lines and equipment for access. All the loose items, as well
as many of the contaminated tools used fbr the excisions, remain at the
pump bowi area or were dropped to the cell floor. A patch was fabricated
and installed to.seal the pump opening. | |

Specimens were removed from the heat exchanger shell and from the tube
bundle. An oval-shaped patch of about 10 in. x 12 in. was cut out near
the top center of the shell. Sections of tubing were removed through this
opening. The hole through the shell was sealed by remotely welding a
patch over the opening. Since this cutting provided communication between
the fission-product-laden fuel-salt loop to the coolant-salt loop, the
5-1in. cooiant-salt lines were cut and seal-welded immediately outside the

cell wall. All the loose material, heaters, etc., along with many of the

. tools used for this job remain in the vicinity of the heat éxchénger.

Control-rod poison elements, 7/8-in. graphite sampler holder and
specimens, and a 2-in. graphite bar were removed from the reactor core.
This job required taking loose and displacing the graphite sampler con-
tainment tank, the control-rod drives, control-rod-drive shielding and
supports, the control-rod and reactor nozzle cooling air lines and thermo-
couple and heater disconnects and supports to gain access to the 10-in.
reactor access nozzle flange. The core access plug, containing the graphite

sampler flange, its holddown mechanism, and the control-rod thimbles, was
92

removed and suspended alongside the thermal shield. Other items are atop
the thermal shield or were dropped to the cell floor. The reactor was
sealed by placing a plain 10-in. blind stainiess steel flange on the
access nozzle. | _' '

In the drain-tank cell, two freeze valves were removed and heaters,
leads, and service lines were again moved for access. The open lines were
'sealed using mechanical plugs. |

The post-operation examination was performed in the fall of 1970,
approximately one year after shutdown of tfie reactor. The radiation level
had decreased tremendously from that encountered during maintenance while
the reactor wés still operable. All jobs were performed in the reactor
cell using the dry maintenance shield without the need for tool shielding
bushings in the access holes. The maximum radiation level above the shield
through a 6-in.-diameter hole was 125 mr/hf at the hole 0pefiing at the
beginning of the work. The maintenance shield was not required in the
drain-tank cell. The work there was performed through a 2 ft x 10 ft
lower roof plug opening. |

A heavy accumulation of dust (v1/2 in. deep on flat surféces) inside
both containment cells was easily handled by flushing the dust to the cell
floor using an ordinary water hose. By keeping the work areas wetted, no
contaminated dust was allowed to escape the containment cells.

At the completion of the post-dperatifin work, the primary system was
leak-tested to ensure that the patches were secure. The cell shielding
blocks and seal membrane were replaced and the containment ce;ls leak-

tested.

3.3 Surveillance

After futher instrument modification ;nd final shutdown of auxiliaries,
the MSRE was placed under a surveillance pfog:am as described in ORNL-TM-
3253, MSRE Procedures for the Period Betwéen Examination and Ultimate
Disposal, dated February 10, 1971. Thislaocument describes the condition
of the MSRE and specifies procedures to be followed after the post-
operation examinations and before the ultimate disposal of the fissile and
radioactive material in the reactor. The fuel salt has been kept frozen

in the sealed drain tanks, within the sealed containment cell. Surveillance
93

has been by remote monitoring and daily visits by ORNL personnel, with
monthly and annual checks by technical personnel. Remedial actions are
prescribed for any abnormal condition. Personnel access is controlled by
security fencing around the area as well as specific areas locked to pre-
vent unauthorized entry. Procedures and responsibilities for maintenance,

modification, and removal of surplus equipment are also specified.

3.4 Surplus Equipment Removal

All MSRE equipment except the items required‘for’surveillance of the
stored fuel and the fuel removal chemical-processing plant were placed on
a published list and made available to other projects. Surplus mechanical
supplies were all moved out, and the process computer was transferred to
the Tennessee Valley Authority's Bull Run Steam Plant.

A large portion of the process instrumentation was removed and used
by other ORNL projects. The coolant-salt pump and piping were removed and
used by research groups in continuing molten-salt development work. All
the remaining noncontaminated process equipment has been declared 'excess in
place'" and is available to others through the ORNL Operations Division.

The coolant-salt piping and pump was the only surplus equipment removal
that has affected the decommissioning study. The pump, pump support plate,
and the 5-in. piping outside the reactor cell were removed. Thé radiator,
sampler and drain-tank systems, including the coolant salt, remain in
place along with all the auxiliary systems. Other items removed, such as
process instrumehtation, were primarily from clear areas and have no

significant effect on the decommissioning effort.

3.5 Site Utilization

Peripheral areas at the site have been and are now being utilized by
other Léboratory groups. The office wing (Bldg. 7509) is occupied by a
research group; the shop building (Bldg. 7515) is used as an area mainte-
nance shop; the reactor building (Bldg. 7503) offices, high bay, and spare
experiment cells have been used by research groups; the stores building
(Bldg. 7507) is used for equipment storage; and the reactor building change

house and sanitary facilities are used by all personnel at the site.
94

3.6 Current Radiation and Contamination Levels

Periodic radiation and contamination surveys are conducted within
the site area, and all movement of personnel or eduipment into or out of
the controlled access areas 1is monifored by the Health Physics Division.
No spread of contamination or radiation exposure has occurred since the
reactor was shut down.

The results of radiation surveys made in January and February of
1977 with an lonization chamber are shown ifi Table 3.

Measurements made in the reactor vessel at the top of the graphite
with a thermoluminescent dosimeter (TLD) indicate a radiation level of
2,200 R/hr. A measurement made at the top of the access flange with a
TLD indicates a radiation level of 264 R/hr. Measurements made at the
top of the graphite with bare and lead-covered TLD's indicate that the
effective ténth—value layer for radiation in that area is 1.4 in. of lead.
Measurements made at a port over the reactor vessel at working level with a
Cutie-Pie indicate that the effective tenth-value layer for the radiation
beam through that port is also 1.4 in. of iead. Measurements made with |
a Cutie-Pie at the top of the opening in the top shield above the reactor
vessel indicate that the effective tenth-value layer for the radiation

through the opening is also 1.4 in. of lead.

4. DECOMMISSIONING ALTERNATIVES

Two alternatives have been considered for decommissioning the MSRE,
These are: (1) removal of all radioactive material except the containment
cell walls; and (2) entombment, in concrete, of all radioactive materials
at the site within the reactor containment cell.

For both decommissioning alternatives, it is assumed that the fuel
and flush salts have been removed from the drain tanks prior to starting
the decommissioning. A study and cost estimate for disposal of the salts
have been reported by P. N. Haubenreich afi& R. B. Lindauver in ORNL CF-72-1-1,
"Consideration of Possible Methods of Disposal of MSRE Salts", dated
January 28, 1972. At present, a total of 4,650 kg of solidified fuel salt

is stored in the two fuel drain tanks in the drain-tank cell. Also,

 
95

Table 3. Radiation Levels Measured in 1977

Using an Ionization Chamber

 

Radiation Level

 

Location (R/hr)
Measurements made in the area near fuel pump
1. Seal pan level over fuel pump with shield 6
plug removed
2. Seal pan level at SW corner of hole in shield 1
3. SW corner of the hole in shield even with the 15
bottom edge of shield concrete
4. ~3 ft below bottom of concrete at SW corner 37
of hole in shield
5. SW quadrant of pump bowl 14b
6. Sampler—enricher nozzle 15
7. SE quadrant of pump bowl 45
8. NW corner of hole in shield even with the 19
bottom edge of shield concrete
9, Pump bowl off-gas line (522) 160
10. North quadrant of pump bowl 250
11. Sampler-enricher spool piece 10
Measuremefits made in reactor cell above reactor
vessel
1. Bottom of shield plug 39
2. Core access nozzle at vessel 408
3. Bottom of holddown basket 960
4, .Control—rod thimble at 18" below basket 3,060
5. Core outlet nozzle 117
6; Core access flange 282
96

Table 3. (continued) .

 

) Radiation Level -t
Location (R/hr)

C. Meaéurements made In reactor vessel

l. Top of flange 312
2. ~2 1/2 ft below top of flange : 1,050
3. Top of graphite 1,740
4. 1 ft below top of graphite 510
5.'_2 ft below top of graphite 426
6. 3 ft below top of graphite | 510
7. 4 ft below top of graphite : 540

D. Measurements made in instrument penetration in
guide tube No. 2 _ -

 

*
1. At bottom ' 1,400 .
2. 6 in. from bottom _ 775 ;:
3. 12 in. from bottom 310 -
4, 24 in. from bottom 64

o
97

4,290 kg of solidified flush salt is stored in a third tank in the same
cell. The fuel salt contains 30.8 kg of 233U and the flush salt 0.49 kg.

The cost estimates for both of the decomfiissioning methods studied
include the assumption that an operating solid-waste disposal area exists
in the immediate vicinity. If the radioactive and contaminate& materials
must be packaged for shipment to a disposal site outside the ORNL area,
the packaging and shipping costs will be greatly increased, requiring a
new methods study and cost estimate.

It is also assumed that knowledgeable, experienced personnel will be
availablé to supervise and participate in the decommissioning activities.
If this is not true, the man-hours expended can increase significantly.
due to lack of familiarity with the reactor components and methods of

working with them.

4.1 Removal and Disposal of All Radioactive Material
Except the Containment Cell Structure
The first alternative involves cutting out, packaging, and trans-
porting to a solid-waste storage area all contaminated and radioactive
materials in the reactor cell, drain-tank cell, fuel-processing cell,
and portions of the gaseous-waste disposal system. The cell structures,

including the lower tier of shielding blocks over the reactor cell and

~ drain-tank cells, may be left intact for future use. Induced radio-

activity in the carbon steel walls of the reactor cell are expected to be
very low due to the neutron shielding provided by the thermal shield
which completely surrounds the reactor except for the instrumentation
thimble. Any areas of the cell wall found to have objectionable levels of
induced fadioactivity can be overlaid with fixed shielding after final

"decontamination.

A summary of work required and a cost estimate for this alternative

are given in Section 5. A detailed job listing is given in Appendik A.

4,2 Entombment in Place

The second alternative is to entomb, in concrete, all radioactive
and contaminated items within the reactor containment cell. The site and

the remaining containment cells could then be put to other uses with
98

esséntially no restrictions. This method of decommissioning is far less
expensive than dismantling and will provide complete containment indefi-
nitely. Entombment of 233y-contaminated méterials in solid;concrete,
however, violates the present requirement that such materials be stored in
a retrievable manner and will require a special permit as implied by ERDA'
Manual Chapter 0511.

This method will invqlve a minimal amount of remote cutting. Alli
pipes and conduits entering the cell through penetrations will be sevefed
inside the cell and cut back about 1 ft. Penetrations will be removed
where radioactive contamination is present and the openings sealed and
filled with concrete. Some cutting and collapsing of in-cell piping will
be necessary to fiermit the emptied drain tanks and the fuel—processing_
équipment to be added before entombing. The cell will then be filled with
concrete to the building floor level to prbvide a fiinimum thickness of
14 ft of concrete over the highest part of the reactor vessel.

A summary of work required and a cost estimate of this alternative

are given in Section 6. A detailed job liéting is given in Appendix B.

4.3 Arguments Favoring Dismantling and Disposal
of Radioactive and Contaminated Items

1. The MSRE is remote from populated areas and near a solid-waste storage
site so that transport of radioactive items to the storage site can
be accomplished with minimal shielding and with little risk to non-
involved personnel even in the event of a transport accident. The
233y-contaminated material will be packaged within‘%1,500 drums of
55-gallon capacity (v13,000 ft3) and 31 spécial containers of various
sizes (13,000 ft3).

2. Removal of the ?33U-contaminated items to retrievable storage will
meet the requirements for disposal of this type material.

3. Emptying the containment cells of all MSRE-related items will release

the facility for future usages requiring such cells.

 
99

4.4 Arguments Favoring Entombing the Reactor and
Associated Radiocactive and Contaminated Items
and Materials in the Reactor Cell

1. Entombment in concrete is far more economical than dismantling and
storage.
2. The transport of radioactive and contaminated items would be avoided.

3. A major portion of the building and cells would be released for other

usages.

5. WORK. INVOLVED IN DISMANTLING AND DISPOSING
OF RADIOACTIVE AND CONTAMINATED ITEMS IN A
SOLID-WASTE STORAGE AREA

5.1 Preparatory Work

Preparatory work required for dismantling and disposal in a solid-
waste storage area includes: (1) provision of a water flushing system for
the reactor primary system, the salt drain tanks, and the fuel-processing
equipment; (2) provision of a flooding system for the reactor cell;

(3) provision of working shielding, transport shields, and disposable waste
containers; and (4) tooling for cutting up the reactor tank and thermal
shield and for cutting up and handling of pipes, conduits, etc., located

within the containment cells.

5.1.1 Flushing System for the Reactor Tank and Other Primary System
Components

Although the reactor primary system was flushed out with a nonfuel-
bearing molten salt after it was drained of fuel, the systém is known to
contain large solidified globules of the flush salt which failed to com-
pletely drain to the storage tanks. In order to minimize the release of
this contaminated salt into the reactor cell during the dismantling opera-
tion, the primary system will be flushed with water and decontaminating
solutions prior to segmenting. The contaminated solutions can be dis-

charged directly into the existing buillding liquid-waste system and then

to the ORNL liquid-waste disposal system. Based upon a cell volume of

200,000 gallons, a flush rate of 5 gpm, and ‘a project time of one year, the

liquid waste generated would be about 3,000,000 gallons.
NUCLEAR DIVISION
DAK RIDGE, TENNESSEE 37830

Iy
(=120 ]

100

- UNION CARBIDE CORPORATION

TABLE 4
DISMANTLING .

COST ESTIMATE
SUMMARY SHEET

 

 

 

PROJECT TITLE AND BUILDING

 

ESO CR CRDER NO.,

A-28844-J1

ACCOUNT CHARGE

 

DATE BASE COST DATE

July, 1977 FY-77

 

 

ESTIMATE VALIOD UNTIL

 

 

TYPE OF ESTIMATE

e O Ou [] oruen

CONSTRUCTED BY

XX ueno XX] cPrr [Jussc (]

ESCALATION (%)

 

 

ESTIMATE BASED ON: [T} vERBAL INFORMATION

[[] skeTcHes (] MARKED PRINTS

(7] preLIM. DESIGN

[T} FinaL oEsiGN

 

 

 

 

 

 

 

 

 

FUND SOURCE ESTIMATED BY ORIGINALLY EST. DATE P. ENGR, ) EST. NO.
[Jexe. ] ceapr C. Kirby* C. D. Cagle
. SUBMITTED BY LAST REVISION CATE F. ENGR.
[(Joee  [] C. Kirby L. P. Pugh
Page No. ' CPFF UCC-ND TOTAL
PREPARATORY WORK
Flushing $ 94,200
Flooding 154,100
Cell Ventilation 47,800
Work Platforms 126,000
SUBTOTAL $ 422,100
TOOLING $3,071,100
SPECIAL TRANSPORT AND STORAGE CONTAINERS S _640,200
REACTOR CELL EQUIPMENT $ 419,500
DRAIN-TANK CELL
General $ 12,000
North Bay 77,000
Center Bay 30,000
South Bay 84,000
General : 56,000
$ 319,000

 

 

 

 

 

 

 

 

UCN-3128E
12y  1.72)

*Cost Engineer, UCC-ND ORNL General Engineering.
ESO OR ORDER N0, A=2884A-J1

101

TABLE 4. (CONTINUED) -
COST ESTIMATE

SUMMARY SHEET
(CONTINUATION SHEET)

 

 

 

 

Page No. CPFF UCC-ND TOTAL
FUEL-PROCESSING CELL $ 103,800
VENTILATION HOUSE AREA $ 79,900
SPECIAL EQUIPMENT ROOM $ 122,100
COOLANT CELL AREA $ 116,100
SOUTH YARD $ 160,800 |$ 11,100
TREATED WATER SYSTEM $ 40,500
SPARE CELL AREA . $ 52,000
$1,413,700 | $4,144,500
HEALTH PHYSICS REQUIREMENTS 706,300
$2,120,000 | $4,144,500
CPFF INDIRECT @ 35% 743,000
$2,863,000 | $4,144,500 |$ 7,007,500
ENGINEERING 20% | 1,401;500
$ 8,409,000
CONTINGENCY @ 30% | 2,591,000
FY-1977 COST $11,000,000
ADDITIONAL UCC-ND COSTS
Solid-Waste Storage S 400,000
Liquid—wasté Disposal (one year) 200,000
$ 600,000 _s___.e_og.gqg___
$11,600 ,000%

 

 

 

 

 

 

 

 

 

 

uven-s1zsr  XNOTE: This 1s 1977 costs.

(123 1.72) purposes.

Use ERDA-ORO Escalatlon Chart to eScalaté for funding
TABLE 4.

102

(CONTINUED)

COST ESTIMATE
SUMMARY SHEET

(CONTINUATION SHEET)

ESO OR ORDER NO. _A-2884A-J1

 

 

TOTAL

 

ESTIMATE GUIDE LINES:

Labor rates for CPFF contractor $100/day for crafts d

or radiation allowance.
UCC-ND degign based on operating account
UCC-ND fabrication based on operating af
G&A on UCC-ND procurement items @ 35%.

(Tocling). It was shown under material
escalating the Elk River costs which ing

b costs @ $183
rcount costs @
This was not

cost but the
tlude indirect

pes not includ

Yday including

hpplied to the
52,550,000 was

B .

 

 

b 352 indirect

$156/day including indirects.

indirects.

plasma torch
arrived at by

 

 

 

 

UCN-8128F
(123 1-72)
 

103

 

 

 

 

 

 

 

 

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f
!
ERDA-ORD ! u
ESCALATION MULTIPLIERS BY QUARTER {End of Ouarter)
s cY.75 -l CY-76 ot cv.7? pofu cv-78 et cv.7e -t cv.80 - cv.81 -t cv82 e cv.e3 -l cviaa —— cv-es —
Oats Es1. 20% 1% ™ 10% % % % % % % % 8%
Made ft————Fv.7s -l FY.76 ! ol FY.77 —atet FY.78 ol et FY-79 e FY-80 ol FY-51 - FY.82 Iyt FY.83 Jut Fv.84 -l Fv-as————'
Quarter — 1 2 a 4 1 2 3 a I 5 1 2 3 4 ] 1 2 3 4 1 2 3 a 1 2 3 4 1 2 3 a —] 1 2 3 a r 1 2 3 a ’] 1 2 3 a 1 2 3 a
- N
FY.74
1st Onr LI 1154 1206 1259 1.296  1.334 1372 1410 1452 1488 1524 1561 1597 1629 1661 1693 1725 1759 1.793 1828 1.862 1.900 1937 1974 2011 2052 2092 2132 2172 2216 2269 2303 2346 2393 2440 2487 253 2585 2635 2686 2737 2792. 2846 2901 2956
ndQrr 1084 1136 1187 1239 1.276 1.313 1351 1388 1.429 1465 1501 153 1572 1604 1635 1666 1698 1732 1,766 1800 1.834  1.870 1907 1944 1980 2020 2.059 2099 2139 2181 2224 2267 2310 2356 2402 2449 2495 2545 2505 2645 2685 2749 2.803 2857 2911
Fdar 1087 1118 169 1219 1256 1293 1329 1366 1.407 1441 1477 1512 1547 1578 1609 1.640 1671 1704 1738 1771 1,806 1841 1,877 1813 1949 1888 2027 2066 2105 2147 2189 2231 2273 2318 2364 2409 2455 2504 2553 2602 2651 2704 2757 2410  2.863
«hQr 1050 1900 1150 1200 1235 1.272 1308 1344 1384 1419 1454 1488 1523 1553 1584 1614 1645 1677 1710 1743 1776 1.892 1.847 1883 1918 1956 1995 2033 2071 2113 2154 2196 2237 2282 2326 2371 2416 2464 28513 2561 2609 266t 2713 2766 2818
' 4
FY.76 . : ,
st Qu 1.000° 1050 1100 1150 1185 1219 1254 1288 1327 1366 1393 1427 1460 1488 1518 1547 1576  1.607 1.633 1670 1702 173 1770 1804 1.838 1875 1.812 1,848 1885 2025 2064 2104 2144 2187 2230 2273 2316 2362 2408 2454 2501 2551 2601 2651 2701
! 2nd Q1r 1000 1050 1100 1133 1166 1199 1232 1269 1301 1332 1364 1396 1424 1452 1479 1507 1537 1568 1508 1628 1661 1.693 172 1756 1793 1.828 1863 1899 1937 1975 2013 2050 2091 2132 2173 2214 2258 2303 2347 2391 2433 2487 2535 2584
! 3rd Qu 1000 1050 1082 1113 1345 1176 121 1241 1272 1302 1.332 1359 1386 1412 1439 1468 1496 1525 1554 1.585 1616 1.647 1678 1712 1745 LIIB 1812 1848 1885 1.921 1.957 1996 2035 2074 2114 2156 2108 2240 2283 2328 2374 2420 2.465
4th Ov 1.000 1030 1060 1080 1420 1354 1182 121y 1240 1260 1284 1.320 1345 1.370 1398 1426 1.453 1480 1510 1539 1568 1598 1.630 1.662 1684 1726 1761 1795 1830 1884 1.907 1939 1876 2013 2053 2084 2133 2174 2298 2261 2305 2.348
! FY-76 -
0 Qv 1000  1.030 1060 1.090 1123 1151 1179 1207 1.235  1.260 1.284 'j:l,aos 1334 1360  1.387 1414 1440 1.470 1.498 1.527 1555 1567 1.618 1.648 1680 1713 1767 1781 1814  1.850 1887 1923 1.859 1.089 2.008 2077 2116 2158 220t 2243  2.285
2nd Qur 1000 1030 1060 1092 1198 1146 1174 1201 1226 1249 .1.273 1297 1323  1.349 1,375 1401 1429 1457 1485 1513 1543 1574 1603 1634 1666 1700 1.732 1764 1799 +.835 1.870 1.05 1943 1,881 2019 2058 2099 2140 2.181  2.222
| d Gar 1000 1030 1.0661 1087 194 1140 1167 1180 1214 1237 1260 1285 131 1336  1.361  1.388° 1415 1443 1470 1500 520 1558 1.587 1610 1651 1683 1714 1748 1.783 1.517 1.851 1888 1925 1962 1.999 2038 2079 2119  2.159
) &h Qv . 1.000 1030 1056 1082 1107 1133 1156 1178 ¥9.201  1.228 3248 1273 1287 1371 1348 1374 1.401 1427 1456 1,484 1.513 1541 1572 1603 1.634 1684 1698 1732 1765 1798 1.834 1870 1906 1842 1881 2020 2.059  2.097
| - Sth Chr I{ 1.000 1.025 1.050 1.075 1.100 1.122 1.144 (‘,»1.185 t.188 1.212 1.236 1.259 1.283 1.309 1.3 1.360 1.386 1.413 1.441 1.469 14893 - 1.526 1.556 1.586 1.616 1.643 1.681 1.713 1.745 1.780 1.815 1.850 1.885 1923 1.960 1.998 2.038
2 i
- FY.77 A
15 Qv 3 1000 1025 1050 1075 1097 1118 3.140 1161 1484 1207 1.2 1254 1279 1304 1,320 1.354 1381 1408 1.436 1462 ' 1.492 1521 1550 1579  1.610 1.642 1674 4.J06 1740 1774 1808 1842 1879 1946 1.953  1.990
2nd Orr - 1.000 1025 1050 10717 1092 N3 1334 1157 4479 1202 1L.225 1249 1274 1.208  1.323 340 1376 1402 1.420 1457 1485 1514 1543 1574 1605 1635 1.666 1639 1733 1766 1799 1835 1871 1907  1.843
,- ad Qo v 1000 1025 1046 1066 1.087 1107 1129 LIST 1173 1196 1220 1244 1.268  1.202  1.318 1343 1389 1395 1.423 1451 1479 1507 1.5 1.567 1597, 1627 1660 1,692 1,775 1757 1792 1827 1863 1900
: ) &t Oar . 1.000 1020 1.040 1060 1080 1102 1323 1145 1166 1190  L213  1.236 260  1.285 1310 1336 1350 1388 1415  1.442 1.469 9.499 1528 1557 1587 1619 1650 1,682 1714 1748 1783 1,817 1851
- A
. Fv.78 ," )
[ 15t Qu \f 1.000 1.020 1.040 1.060 1.081 1.102 1124 1.145 1.168 1.191 1.213 1,236 1.21 1.286 1.310 1.335 1.362 1.389 1.415 1.442 147 +.499 1.528 1.557 1.538 1.619 1.651 1.682 1.718 1.748 1.783 1.816
N 2nd Gar b 1.000 1020 1040 1061 1.08 1102 1123 1346 1968 1181 1213 1.237 1262 1286 1.310 1336 1383 1.389 1415 1.443 1472 1500 1528 1580 1589 1620 1.650 1684 1716 1743 1782
d Qtr “; 1.000 1.020 1.0a0 1.061 1.081 1.102 1.124 t.146 1.15‘8 1.180 1.214 1.237 1.261 1.285 ’ .‘.311 1.336 1.362 1.388 1.415 1.443 141 1.499 1.529 1.559 1.569 1.81% 1.651 1.684 1.716 1.748
a1 O » 1.000 1020 1.040 1.060 1080 1102 1923 1145 1166 L1800 1213  1.238 1260 ‘1285 1310 1335 1360 1388 1415 1.442 1460 1499 1528 1.557 1567 1619 1650 1.682 1714
- ,‘J : . -
FY.-79
1t Qe 1000  1.020  1.040 1060 1.081 1102 1124 1145 1168 1191 1213 1236 281 1286 1311 1335 1,362 1389  1.416 1442 1.471 1.500 1620 1557 1589 1620 1651 1682
Znd Qur 1000 1020 1.040 1061 1.082 1102 1123 1148 1168 1191 1213 1,237 1262 1286 1310 1336 1,363 1389 1415 1443 1472 1500 1520 1559 1.589 1620 1.650
d Ou 1000  1.020  1.040 1061 1081 1102 1124 1148 1168 1980 1214 13237 1.261 1285 1311 1338 1352 1,388 1.416  1.443 1471 1499 152 1559 1589 1619
| ath Qv 1.000 1020 1040 1060 1080 1402 1323 1745 1168 1,190 1113 1235 1260 1.28% 1310 1338 1.351 1388 1.415 1442 1468 1499 1528 1558  1.587
| Exscalation Multipliers by FY - Mid Year i
|
Fram 20% 12% % 10% % 8% % &% 8% 8% ‘ 8%
Mid ¥r £v.75 £Y.76 5 Ev.77 FY.78 FY.79 FY.80 Fy-a1 Fv.82 FY.83 FY-54 FY-85
' Fv.74 1138 1313 1.408 1.501 1.835 1766 1.907 2.059 2.224 2.402 2595 2.803
: FY.75 1.000 1168 1.750 1.332 1.452 1.568 1693 1.828 1975 2132 2.303 2.48
) FY-76 1.000 1.076 1.146 1,249 1.349 1,457 1.574 1.700 1.835 1.981 2.140
FY.76A 1.000 1.050 1.144 1.236 1.334 1.441 1.556 1.681 -fi 1.815 1.960
' FyY-77 1.600 1.092 1.179 1.274 1.376 1.486 1.“)5 v \\ 1.733 1.871
| FY.78 1.000 1.082 1168 1.262 1.263 1.472 % 1.589 1.6
3 Fy-79 1,000 1.082 1.168 1.262 1.363 ‘1472 1.589
i i
' . €OST ENGINEERING 4-30.78
'
-
3
- 1 t

 

 

 
 

 

 

-~ 104

The equipment required for flushing will include a pump, mixing tanks
for decontaminating solutions, piping, and valves. The system will require
shielding. Multiple connections will have to be made into different
regions of the primary system to ensure solution circulation in all portions.
(The'connections can be made simply by trespanning holes into the: primary

system and connecting pipes with clamp-on compression fittings.)

5.1.2 Reactor Cell Flooding System

 

The interconnected reactor and drain-tank cells are capable of being
flooded with water if necessary; however, due to differences in elevation
it will be best to avoid flooding the drain-tank cell beyond its seal
membrane elevation since the water would be in contact with bare concrete.
Following flushing of the reactor primary system and the drain tanks, the
opening between the cells can be sealed at the drain-tank-cell side to con-
fine flooding to the reactor cell.

The flooding system will consist of a pump capable of delivering a
minimum of 1,000 gpm, a strainer, bypass or in-line filter, and necessary
piping, valves, and instrumentation. All components containing circulating
water will require shielding. The filter will be cleaned periodically by
backflushing to the existing liquid-waste disposal system. The concentra-
tion of dissolved contaminants can be controlled by continuously or
- periodically discharging a portion of the circulating water to the liquid-

waste disposal system.

5.1.3 Work Shielding

 

The dismantling work will require the erection of temporary shielding
structures around the flushing}and cell-flooding systems and elsewhere on
an as-needed basis. These shields should be made of material forms that
allow éome diversity of size, shape, and thickness and which can be readily
dismantled and the materials reused as required. The estifiated require-
‘ments for the dismantling of the reactor system are two-thousand 6 in. x
6 in. x 12 in. solid concrete blocks, six-hundred 2 in. x 4 in. x 8 in.
lead bricks, and one-hundred 1/8 in. x 2 ft x 4 ft lead sheets (21,000 1lbs
of lead total).
105

5.1.4 Transport Shields and Waste Storage Provisions

Present regulations require that all waste items contaminated with
233y be stored in a retrievable manner. This will apply to all. items
removed from the reactor cell, drain-tank cell, and fuel-processing cell.
Although it is planned to minimize further contamination by flushing the
primary system prior to dismantling it, some external contamination already
exists due to past maintenance and post-mortem work.
| Because of the large amount involved, special provisions will have
to be made for storing the material in the solid-waste storage area. For
estimating purposes, it is assumed that the present storage method for
such materials will be used. This requires that the waste items be placed
in specially designed storage shields or be segmented to fit within’
standard stainless steel 55-gallon drums for storage in 30—in.-diaméter
stainless steel lined wells which have a concrete bottom and are capped
with removable concrete top plugs. In 1976 dollars the cost per drum was
$750. Transport shields for 55-gallon drums must be bottom unloading and
have a shielding thickness equivalent to 6 in. of lead. At least three -
such shields should be provided to expedite transfer.

Special sealable storage casks will be provided for large items that
are difficult to segment. These include the reactor assembly, the primary
heat exchanger, the fuel-salt pump, and the pump motor. Except for the
reéctor assembly, the radiation level_from these items is expected to
require only 3 to 4 in. of lead for shielding. The reactor assembly will
require 6 to 7 in. of lead. | ' |

5.1.5 Disposable Waste Containers

All éolid waste contaminated with 233y will be segmented to fit within
55-gallon steel drums. Approximately 1,500 drums will be required.

5.1.6, Miscellaneous Cutting and Handling Tools

A large variety of long-handled tools will be required for unbolting
flanges and structures, for severing pipes and conduits, for tearing

insulation, and for handling loosened items. For the most part, this type

 

 
106

of tooling will consist of equipping standdrd items such as abrasive cutting
tools and hydraulically operated shears with long handles so that they can

be operated remotely.

 

5.1.7 Retrievable Storage Requirements

The packaging of the 233U-contaminated material from the MSRE will
generate a total volume of ~16,000 ft3 of packaged material and will require
0.2 acres of solid-waste storage area for retrievable storage. The major
portion of this volume (v13,000 ft3) will be in the form of 55-gallon
stainless steel drums (~1,500) without any-attached shielding. The remain-
der (03,000 ft3) will be packaged within 31 special containers of various
sizes and with various thicknesses of attached shielding material.

Current cost for preparatory work ana burial at the solid-waste disposal

area averages about $25 per ft3 for retriévable storage.

5.2 Remote Dismantling Work

The first stage of the dismantling work will be to flush out the
emptied fuel-salt and flush-salt drain tanks and the fuel-cell processing
equipment to reduce the radioactivity level in the dfain-tank cell. Piping
connections to the flushing system will be made remotely at various loca-
tions so that the flushing solutions will reach all portions of salt piping
and tanks. Prior to connecting the flushing piping, a gas éupplyAwill be.
connected across each freeze valve. The salt in the valve will then be
heated to molten by existing heaters. A gas flow will be maintained
-through the salt until it has cooled to establish a flow path for water
during the flushing operation.

After the flushing is complete and the flushing system removed, the
drain-tank-cell equipment and the piping and conduits through the penetra-
tion between the drain-tank and reactor cells will be removed and the
opening sealed to allow flooding of the feactor cell. The advantages of
clearing the drain-tank cell first are tfiat this: (1) allows direct access
to the reactor cell penetration for sealing; and (2) allows use of the
cell ventilation system while it is still operable.

After all_othef pipes and conduits:leadihg from the reactor cell have

been cut externally and sealed, the cell will be flooded to about 6 in.

.f,t- L%

 
107

below the bottom of the lower roof shield blocks. The top shield blocks
will be removed and set aside for possible usage as bridges during dis-
mantling operations. The stainless steel seal pan will be cut up and dis-
posed of in the solid-waste storage area. The lower shield blocks will
then be removed, wrapped in plastic, and disposed of in the solid-waste
storage area. The water level in the cell will then be raised to within

a foot of the cell liner top and the piping for water circulation installed
and shielded. After water circulation has been established, working
bridges will be installed and the dismantling of the reactor cell compo-

nents will begin.
5.2.1 Clearing the Cell Around the Reactor

The initial dismantling activity will be to segment and dispose of all
items in the cell that are external to the thermal shield. These include

the fuel-salt pump, the heat exchanger, the 5-in.-diameter primary and

| secondary piping, electrical heaters, insulation, off-gas piping, thermo-

couples, and support structures. The primary heat exchanger, the fuel-

salt pump motor, and the pump bowl will be separated from interconnecting
structures and placed in specially designed storage casks for disposal in
the solid-waste storage area. All other items will be segmented for dis-

posal in 55-gallon drums.

5.2.2 Segmenting and Disposal of the Thermal Shield and the Reactor Vessel

 

Since the reactor vessel is supported from the thermal shield 1id, it
will hafie to be cut loose and lowered to the bottom of the éhield‘prior to
removing the 1id. Following removal and disposal of the reactor vessel
heaters and the removable side sections of the thermal shield, a suspension
arrangement will be connected to the reactor vessel access flange and then
attached to a bridge.across the cell opening to allow the vessel support
hangers to be severed. The reactor vessel will then be lowered to the
bottom of the thermal.shield and the thermal shield 1lid moved aside to an
underwater support frame for segmenting.

Following disposal of the thermal shield lid, the reactor vessel and

. 1ts contents will be lifted over the side of the thermal shield and lowered

to a special support frame for segmenting. When the vessel is in place, a
108

circumferential cut will be made near the vessel base to allow the vessel
sides, top, and the attached core shell to bevlifted aside as a unit to
.expose the graphite core block assembly. After the graphite has been’
broken out and disposed of, the reactor vessel and core shell will be seg-
mented and disposed of in 55-gallon steel drums. The remainder of the
thermal shield will then be segmented and transferred to storage. In
addition to the segmented pieces of the thermal shield, there are 35 tons
of 7/8-in.-diameter carbon steel balls filling the annular space of the

cylindrical portion of the shield. These will also be packaged and stored.
5.2.2.a Alternative to Segmenting the Reactor Vessel

An attractive alternative to segmenting the reactor vessel is
removing it intact into a large, portable, sealed lead cask for indefi-
nite above-ground storage in the solid-waste storage area. The cask
(Figure 51) would be of simple cylindrical construction with a flat
base and top and made with a stainless steel liner. It would be top-
loading with the top seal-welded to the body following loading. A
small filtered vent would be provided to prevent internal pressuré
buildup due to radiolysis of residual moisture. To shield the
present radiation level to the acceptable storage level of <200 mr/hr,
a 6-in. thickness of lead would be required. The combined weight 6f
the cask and the intact reactor vessel would be 60 tons.

The cost of the cask and the associated handling equipment would
be considerably less than the cost of tooling for and segmenting the

vessel.
5.2.3 Drain-Tank Cell

The shielding thickness required for storing the emptied and flushed
drain tanks cannot be estimated without assuming a higher upper limit for
the radiation and prefabricating shields that may be excessively thick.

If the4decbntamifiation of the tanks 1s reasonably successful, little or no

shielding will be required for transporting the tanks to storage.

Because of the massiveness of the tanks and the material and complexity .

of theilr construction, remote segmenting for storage would be comparable in

expense to segmenting the reactor vessel even though the radiation levels

 
 

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Figure 51. Reactor Assembly Storage Container Concept
110

are much lower. If shielding is required for transport and storage, the
tanks will be lifted out of their furnaces'qnd moved to a temporary shield
where trénSport shields will be built around them. To do this, the tanks
will each be surrounded with a stainless steel form into which an annulus
of concrete of the required thickness will be poured. The shielded tanks
will be disposed of in the solid-waste storage area. All other items in
the cell will be segmented for disfiosal in 55-gallon drums. The cell walls
will be decontaminated and the top shield blocks reinstalled.

 

5.2.4 Fuel-Processing Cell

The fuel storage tank and other items in the fuel-processing cell
will be disposed of using the same techniques outlined for the drain-tank
cell. | |

5.2.5 Cell Ventilation System

 

The 30-in.-diameter carbon steel cell ventilation line from the south-

west side of the bottom of the reactor cell was used to maintain a negative

pressure in the cell during maintenance operations and is contaminated with

radioactive particles and fission producté released during these activities.

This line, the main 36-in.-diameter duct it joins, the filter pit, and the
discharge stack will be decontaminated and left in place. Smaller con-
taminated ducts from the auxiliary cells will be cut up and disposed of in

the solid-waste storage area.

5.2.6 Off-Gas System

 

Because of the gas holdup volumes in the off-gas line ahead of the
charcoal trap, essentially all the residual long-lived fission products in
the system will be plated out on the walls of the holdup volume pipes
rather than collected in the charcoal trabs. The holdup volume which

encircles the inside of the reactor cell will be segmented and disposed of
.along with the other contents of the cell, The remainder of the system up
to its juncture with the containment ventilation system particulate filter
enclosure will be segmented and disposed Af in the solid-waste storage area
unless there is a need for retaining the system for future projects using
the shielded cells.

 
111

5.2.7 Liquid-Waste Disposal System

 

The portion of the liquid-waste disposal system contaminated with 233y
will be removed, éegmen;ed, and disposed of'up to but not including the
waste storage tank in the liquid-waste cell. The storage tank and its con-
nections to the ORNL liquid-waste disposal system will be decontaminated

to the extent possible and retained for future programs.

5.2.8 Coolant-Salt System

 

The coolant salt was drained from the system to the storage tank in
the coolant drain cell when reactor operation was terminated. The salt
pump, pump support, and the 5-in. piping outside the reactor cell have
been removed for use in a development project; but the radiator, sampler,
and drain-tank system (including the coolant salt) remain in place along
with all the auxiliary systems. |

The system has only trace amounts of radioactive contamination and.
beryllium salt contamination. All the system components will be disposed

of by burial in the solid-waste storage area.

5.2.9 Miscellaneous Contaminated Items

 

Contamination outside the primary and secondary salt systems is con-
fined mainly to the component-cooling system, sampler-enricher, and the

treated-water system.

5.2.9.a Component-Cooling Air System

 

The component—cooling air blowers, heat exchanger, filter,
enclosures, and piping are located in the special equipment room
immediately south of the reactor containment cell. This system is
contaminated internally with cell atmospheric contaminants pulled in
from the reactor and drain-tank cells. _

The piping, valves, and strainer could be segmented and packaged
in 55-gallon drums for storage. The heat exchanger, blowers, and
motors will require special containers. The containment enclosures
could be decontaminated enough to allow direct burial more economically
than segmenting and storing. The radiation level from the components

of this systefi will be very low.
¥y
it

112

5.2.9.b Sampler-Enricher

 

Radiation readings taken February 25, 1977, at the 1/2-in.-thick
quartz periscope window and at the removal valve opening of the pri-
mary system sampler-enricher were 150 fir/hr and 1 R/hr, r¢Spective1y.
Temporary work shielding will be required after the existing shielding
is removed in order to discofinect and éemove the assembly.

Secondary containment of the asséfibly is provided by the upper
sample transfer box and the lower operational and maintenance valve
box. These boxes are joined together with seals at penetrations to’
prevent the 6ontamination due to sampling from entering the lower box.
Removal will require opening of thevvalve box in order to disconnect
the transfer tube as well as to discofinect the box from a floor flange.
Making these disconnections plus severing and sealing a multitude of
electrical, pneumatic, cover-gas, and off~gas connections will allow the
complete assembly to be removed to a éfiecial storage container.

Removal of the fuel~processing-system sampler will be done in a

similar manner.

5.2.9.c Treated-Water System

 

The treated-water system is a closed loop syétem that was used to
cool components within the cells. Ali the in~cell portions will be
removed with the cell equipment. The portions outside the cells are
located within a pipe chase along the south face of the reactor cell,
in the water room and in the diesel Shed. Contamination within this
system consists of activated oxides and chromates induced by exposure
to the reactor system. The contamination level is very low; so these
components will not require shielding, bnly simple containment with
plastic wraps, etc., and may be disposed of by burying in a trench in
the disposal area. _‘ |

The equipment in the pipe chasefconsists of piping and radiation
safety block valves. These may be removed by unbolting existing
flanges and by simple cutting procedfires with direct access available

for the work.
113

The water room contains two pumps, a surge tank, makeup tank, and all
valving, flow monitors, and piping for the distribution of the cooling
water. Direct access existgifor the removal of these items.

The diesel shed contaifis a heat exchanger and a particle filter.

The highest level of contamination within the system is concentrated in
the filter. The heat exchaflger and filter are connected to the wafer
room piping via underground iines which cross the west yard (v100 ft of
4-in. carbon steel pipe). Direct access exists for removal of the com-
ponents in the shed, and there are no obstacles in the way of excavating

g
the underground pipes. '

i

6. WORK INVOLVED IN ENTOMBING ALL RADIOACTIVE
AND CONTAMINATED ITEMS IN THE REACTOR CELL

6.1 Preparatory Work

Preparatory work for entombing all radiocactive and contaminated items
in the reactor cell in concrete includes: (1) provision of a water
flushing system for the fuel and flush-salt drain tanks and the fuel-
processing equipment; (2) provision of a 5,000 cfm (minimum) air exhaust
duct into the top of the reactor cell; and (3) tooling for cutting pipes
and structural materials in the reactor cell and for cutting loose and
transferring tanks, pipes, and structural materials from the drain-tank
and fuel-processing cells to the reactor cell.

6.1.1 Flushing System for the Primary Salt Drain Tanks and the Fuel-
Processing Equipment

This.system is the same as that described in Section 5.1.1; however,
it will not be necessary to flush out the reactor vessel nor the primary
system in the reactor cell. The drain tanks and their associated piping
as well as the equipment and piping in the fuel-processing cell are to be
flushed to reduce radiation levels and the probability of contamination

spread during their being cut out and transferred to the reactor cell for

entombment.
 

114

UNION CARBIDE CORPORATION

NUCLEAR DIVISION TABLE 5

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

o
OAk RIDGE, TENNESSEE 237830 ENTOMBMENT . *
COST ESTIMATE .
SUMMARY  SHEET o
PROJECT TITLE AND BJ',D,NG - — .
ESO QR ORDER NO. ACCOQUNT CHARGE CATE BASE COST DATE ESTIMATE VALID UNT'L
A-2884A-J1 July, 1977 FY~77 '
TYPE OF ESTIMATE CONSTRUCTED BY - ESCALATION (3
Tle s [On [J ortuer JE}ucmm B corr Jusse [ __
ESTIMATE BASED ON: [ verBaL inFORMATION [] skevcues 7] mrakgo prInTS ] PReLIM. DEsIGN "1 FINAL DESIGN
FUND SOURCE ESTIMATED BY QRIGINALLY EST. DATE p_. ENGR. EST. NO.
Jexp ] eopt C. Kirby=* C. D. Cagle
SUBMITTED BY LAST REVISION DATE F. ENGR.
(] srp ] C. Kirby L. P. Pugh
Page No. CPFF UCC-ND TOTAL
PREPARATORY WORK |
Flushing $ 94,200
Cell Ventilation $§ 35,500 25,600
Work Platforms 60,000 36,600
Miscellaneous Material 6,900 -
: ' T
SUBTOTAL $§ 95,500 $ 163,300 .
TOOLING $ 419,300 oo
REACTOR CELL EQUIPMENT $ 322,700 -
DRAIN-TANK CELL § 273,300
FUEL-PROCESSING CELL $ 53,300 .
VENTILATION HOUSE AREA $ 64,000 b
SPECIAL EQUIPMENT ROOM $ 93,900
COOLANT CELL AREA S 96,100
SOUTH YARD $ 135,500 $ 11,100
m . ~
UCN-312%E -
1123 t=T2) *
o
_.‘ ;

4
o

TABLE 5.

115

(CONTINUED)

COST ESTIMATE

SUMMARY SHEET
(CONTINUATION SHEET)

 

 

 

 

 

 

 

ESO OR ORDER NO, _ A-2884A~J1
Page No. CPFF UCC-ND TOTAL

TREATED WATER SYSTEM $ 40,500
SPARE CELL AREA 42;000

$1,216,800 $ 593,700
HEALTH PHYSICS REQUIREMENTS 608,200

$1,825,000 $ 593,700.
CPFF INDIRECTS @ 35% 639,000

$2,464,000 $ 593,700 $ 3,057,700

ENGINEERING 20%

CONTINGENCY, FY-1977 COST

ESTIMATE GUIDE LINES:

Labor rates for CPFF contractor $100/day
or radiation allowance.

 

UCC-ND design based on operating accou:[
UCC-ND fabrication based on operating

G&A on UCC-ND procurement items @ 35%.

 

for crafts d

costs @ $183

count costs @

 

oes not include 35% indirect

/day including indirects.

$156/day including indirect

‘ 612,300

$ 3,670,000

| 1,100,000

$ 4,770,000%*

 

 

 

 

ucn.1zsr  *NOTE:, This is 1977 costs. Use ERDA-ORO Escalation Chart (page 103) to escalate for

123 1.72}

funding purposes.
116

6.1.2 Air Exhaust System for the Reactor Cell

The existing 30-in.-diameter cell ventilation duct is connected to the
cell near the bottom; therefore, it cannot be used to vent the cell while -
concrete is being poured into it. Also, before concrete can be poured, it
must be severed.and sealed at the point of emergence from the cell structure
. and should not be further contaminated by the preparations for entombment.
To provide necessary ventilation for particle control, a temporary shielded
30 in. by 30 in. ventilation duct will Be provided to exhaust air from the
cell at the top near the south edge. This duct will be tied into the
existing 30 in. by 30 in. duct located at the east side of the cell that
normally exhausts the high-bay area. The existing particulate filters,

blowers, and exhaust stack can be used.

6.1.3 Tooling

Required tooling will include remotgiy operated saws, abrasive cutting
tools, hydraulic shears, cutting torches, lifting hooks, and tongs to be
used in the reactor cell to make space for other items. The same tools
will be used for cutting loose and transferring items from the drain-tank
and fuel-processing cells to the reactor cell. Most of these tools can
be made by adapting standard tools with long handles to allow remote opera-

tion.

6.2 Preparing Reactor Cell to Accommodate Contaminated
Items from Other Cells and Areas

6.2.1 Clearing Top of Cell and Installing Temporary Ventilation Duct

To allow access to all areas of the reactor cell, the upper tier of
shielding blocks will be set aside and the entire seal pan cut out in
easily'handled sections and temporarily stored for later disposal in the
reactor cell. During this work, a negative pressure will be maintained in
the cell using the existing 30-in.-diameter ventilation duct. One of the
smaller lower shield blocks on the south side will be removed and replaced
with a new shielded cover containing the temporary véntilation duct. When
‘the new duct has been installed, shielded, and opened to the ventilation

system, the existing duct will be closed.
117

6.2.2 Sealing the Existing 30-In. Cell Ventilation Duct at the Cell Wall

 

The existing cell ventilation duct will be severed and a short section
removed in the coolant cell where the duct exits the reactor cell outer
tank. The cell side of the opening will be blanked with a flange éontaining
a nozzle for pumping the penetration full of grout. The duct opening to

the filters will be temporarily sealed as the remainder of the duct will be

removed later.

The duct penetration extends %8 ft through the sand-filled annulus to
the reactér containment tank. The duct is horizontal for about 5 ft and
then turns upward at a 31° slope to intersect the hemispherical bottom
head of the reactor tank. The open and inside the cell is shielded by a
9—in.;thick carbon steel shadow shield. The grout should be pumped inward
until it extrudes from behind the shadow shield (40 ft3).

6.2.3 Closure of the Opening Between the Reactor and Drain-Tank Cells

 

Before concfete can be poured into the reactor cell, fhe opening
from there into the drain-tank cell must be cleared of pipes and conduits
and sealed. Since later work will further obscure the opening on the
reactor cell side, it will be necessary to clear and seal the opéning first.

To provide ventilation from the drain-tank cell after sealing the
opening, the upper layer of shielding blocks and the seal pan will be ’
removed and a lower shield block replaced with one containing an opening
for a ventilation duct as will be done for the reactor cell. This duct
will tie in to the temporary duct provided for the reactor cell.

When ventilation has been estéblished for both cells, the pipes and
conduits passing through the intercell opening will be severed in both
cells and drawn into the reactor cell. The opening will then be closed on

the reactor cell side with a large prefabricated plug or cap.

6.2.4 Enlarging Space in the Reactor Cell

 

There are two purposes for cufting loose and rearranging items in the
reactor cell, One purpose is to remove, on the inside of the cell, short
sections of all pipes and conduits that penetrate the cell walls to ensure
that all internal systems will be sealed from external communication fol-

lowing entombment. Prior to doing the internal cutting, the pipes and
118

.conduits will be cut and capped where theyiemerge externally from the cell.
After the cell has been filled with concrete, the caps will be removed to
allow backfilling with concrete prior to final sealing. The second purpose
is to rearrange some of the existing compénents to provide space for placing
other items in the cell for entombment.

The major items to be disconnected or cut loose and repositioned are
the fuel-salt pump and its associated conduits and piping, the heat
- exchanger, the primary and secondary salt piping and heaters, and the vari-
ous structures that support these items. ‘

This phase of the work will be relatively slow due both to limited
access and the type of work to be done. Since there will Be a dust and
particle control problefi during this fiork, only one working opening into
the cell will be used. The inflow of air through this opening to the ven-
tilation system will prevent the dust and particles from emerging.
Additional limited control will be exercised by drenching with water as
applicable. The water will collect in the sump at the low point of the
‘containment vessel and will be jetted to thelliquid—waste system. The
water ejection system will be the last piping cut loose in the cell.

Although preparation of the drain~-tank cell components, fuel-processing
cell components, and other items for transfer may be done simultaneously
with the space preparation in the reactor cell, no transfer of items to the
reactor cell will be done until all cutting and rearranging there is com-

plete.

6.3 Transfer of Disposable Items to the Reactor Cell
6.3.1 Drain-Tank and Fuel-Processing Cell Components

While the reactor cell is being prepéred to receive them, the emptied
and flushed tanks, piping, etc., in the drain-tank cell and the fuel-
processing equipment, piping, etc., will be prepared for transfer. Tanks
will be transferred as units, Smaller.iéems, such as pipe sections, will
be loaded into reusable steel drums or similar containers for tranmsfer.

Prior to the transfer, an opening large enough to receive the items
to be transferred can be provided through the reactor cell top by first

stacking temporary shielding to a height of about 6 ft above floor level
w2

"y
+

l"‘

119

to form a shielded chimney around the cell top shield blocks to be removed
and then removing the shield blocks. The vertical shielding will protect
pefsonnel from direct radiation from the cell and allow the access to remain
open while transferred items are being positioned in the cell by personnel
working through a smaller opening. Between transfers, the top of the

chimney will be closed with a light-weight cover. During transfers, the
shielded remote maintenance control room will be used by the hoist operator--
other personnel will remain at a safe distance while the items being trans-
ferred are unshielded.

As an altérnative-to using the shielded chimney as an access to the
cell, appropriate shielding blocks can be removed and replaced as required
by operating the hoist from the shielded remote maintenance control room.

As each tank is put into place in the reactor cell, grout will be
pumped into it through a pipe opening or a trespanned hole to prevent

floating during the filling of the cell with concrete.
6.3.2 Disposal of Existing Reactor Cell Ventilation Duct and Off-Gas Lines

The entire 30-in.-diameter reactor cell ventilation duct between the

. reactor cell and the 36-in. main ventilation duct will be cut into sections

and disposed of in the reactor cell. To do this, sectioning will begin at
the point of emergence from the reactor cell (already sealed from the reac-

tor cell) and proceed toward the main duct. This will allow an inward

 draft of air to be maintained for dust control. Prior to cutting each

section, the inner wall will be coated with a sealant to prevent particle:
release during subsequent handling. Removal of the duct outside the
building will involve excavation. |

Sectioning of off-gas lines will also be done while maintainifig an
inward draft; however, due to their small size, coating the sections

internally will not be required.
6.3.3  Secondary Decay Volume and Charcoal Traps

Due to only low-level contamination with long-lived fission products,
the secondary decay volume and charcoal traps (all located in the charcoal-
trap pit) will be sealed and transferred as intact units to the solid-waste

storage area for disposal in trenches.
120

6.4 Filling the Reactor Cell with Concrete

The filling of the reactor cell with concrete and grout will be done
in stages as the various items to be disposed of there are added. This
procedure will reduce the radiation level through openings in the top of
the cell as quickly as.possible. One of the first regions to be filled
with grout will be.the annulus befiween the reactor vessel and thermal shield
to reduce the radiation from the vessel into the cell.

When the reactor cell has been filled with concrete up to the bottoms
of the lower shield blocks, the temporary ventilation duct will be removed
and all the lower shield blocks will be reinstalled. A final grouting in
of the blocks fiill be made at the building floor level and the surface
finished to building floor specifications. The upper shield beams may be

checked for contamination and either retained for other uses or disposed of.

6.5 Decontamination 6f Area

6.5.1 Drain-Tank Cell

 

When the equipment removed from the drain-tank cell is complete, decon-
tamination of the interior surfaces and cell penetrations will be done. The
cell is stainless steel lined and will aliow strong solutions to be used
for cleaning. The solutions can be jetted to the existing liquid-waste
system., The transferrable contamination should be low enough to allow
unrestricted use of the cell.

The upper and lower shield plugs will be cleaned and reinstalled over

the cell for future use.
6.5.2 Fuel-Processing Cell

After removal of the fuel-processing-cell equipment, the cell will be
decontaminated in the same manner as the drain—tank cell except that the
cell surfaces are concrete. Chipping may be uséd where solution cleaning
is unsuccessful. |

The roof plugs will be cleaned and replaced for future use.

.
4

T
121

6.5.3 Liquid-Waste Storage Cell

The liquid-waste system will be retained for future use. Contamination
in the storage tank, filter, pipes, and pump will be flushed out to the
Laboratory ILW system to allow the system to remain for future use with

restricted entry only into the waste-tank storage cell.
6.5.4 Containment Ventilation Systenm

After removal of the reactor cell exhaust duct and decontamination of
the stack filter bay, very little, if any, contamination will remain in the
ventilation system. Repairs to the duct where the cell exhaust line is

removed will be made, and the system will remain ready for use.

- 6.5.5 Special Equipment Room - Coolant Cell Area

A small amount of contamination exists in the special equipment room
as a result of maintenance on the component-cooling air blowers. Care
must be used to avoid further contamination during the removal of the cell

exhaust duct and the component-cooling air system. A simple mopping of the

cell area should remove the existing contamination.

7. REFERENCES

1. R. C. Robertson, MSRE Design and Operations Report, Part I--Description
of Reactor Design, ORNL-TM-728 (January, 1965).

2. J. R. Tallackson, MSRE Design and Operations Report, Part IIA--Nuclear
and Process Instrumentation, ORNL-TM-729, Part IIA (February, 1968).

3. R. B. Lindauer, MSRE Design and Operations Report, Part VII--Fuel
Handling and Processing Plant, ORNL-TM-907, Revised (December, 1967).

4. R. B. Lindauer, "MSRE Fuel Processing System Status', ORNL-CF-69-6-17
(June, 1969). | |

5. R. H, Guymon, MSRE Procedures for the Period Between Examination and
Ultimate Dispbsal (Phase 111 of Decommissioning Program), ORNL-TM-3253
(February, 1971). A |

6. P. N. Haubenreich and R. B. Lindauer, "Consideration of Possible

Methods of Disposal of MSRE Salts', ORNL-CF-72-1-1 (January, 1972).

 

 
123

APPENDIX A

JOB LISTING FOR

DECOMMISSIONING THE MSRE BY DISMANTLING AND DISPOSAL
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY REMOVAL OF RADIOACTIVE MATERIAL UNIT COSTS MATERIAL LABOR Reference
MAT'L | LABOR Drawing
1l ea. | Design and fabricate flushing system unit with ~50 gpm
flow and 500 gallons storage of decontamination solution
with connections for discharging solution to the ORNL ILW
system. Unit to be portable and shielded for use at
various areas in the reacfior, drain tank, and fuel
processing cell,
Design {100 md) $ 18,300
Material $10,000
Fabrication (100 md) i 15,600
6 jobd Connect and flush various sections of the system and -
tanks.
6 ea. @ 50 md (300 md) $ 46,800
G&A on materials: 10,000 x 0.35 $ 3,500
UCC-ND Subtotal $13,500 $ 80,700
NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL
PREPARATORY WORK - FLUSHING T i -
$ 94,200

 

 

 

UCN-1297
ts 7.7
‘II'! . 1’&
f) 1 - . 1

 

 

wel
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY REMOVAL OF RADIOACTIVE MATERIAL UNIT COSTS MATERIAL LABOR Reference
MAT'L | LABOR ]|_ Drawing
1 ea. | Design, fabricate and install filtering and demineral- .
izing system to control clarity and activity level of the
reactor cell and drain tank cell floéd water. The system
is to have a minimum flow capacity of 1,000 gpm and be L
located within a shielded area with piping connections to
the reactor and drain tank cell. B
Design (200 md) N *fl_i,_.“'.f_%é_’_f:g?_______fiw.__
Mate-rials $50,000 )
Fabrication & Installation (500 md) i $ 50,000
i
G&A on materials: 50,000 x 0.35 $17,500
| $67,500 $ 86,600
NET MATERIAL AND LABOR
PREPARATORY WORK - FLOODING CPFF FIXED PRICE ORNL
$154,100

 

 

 

 

UCN-1297
3 7172

6l
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY REMOVAL OF RADIOACTIVE MATERIAL UNIT COSTS MATER!AL LABOR ‘Reference
NIT MAT’'L | LABOR Drawing
1 job| Design, fabricate and install a temporary cell ventilation
duct from the top of the reactor cell to existing duct
work at the east side of the high bay.
Design (50 md) $ 9,200
Materials $5,000
Fabrication & Installation (50 md) 5,000
1 job| Design, fabricate and install a temporary cell ventilatioq
duct from the top of the drain tank cell to existing duct
work at the east side of the high bay.
Design (50 md) $ 9,200
Materials $7,500
Fabrication & Installation (75 md) 7,500
G&A on materials: 12,500 x 0.35 $4,400
$16,900 $ 30,900
NET MATERIAL AND LABOR
‘ CPFF FIXED PRICE ORNL
PREPARATORY WORK - CELL VENTILATION — -
| $ 47,800
UCN-1297 —— TrEiamedn e
13 772
. f ' f‘. ' ’ v .
. ” ‘o

9C1
QUANTITY
UNIT

REMOVAL OF RADIOACTIVE MATERTIAL

 

UNIT COSTS

 

MAT L LABOR

MATERI AL

LABOR"

Reference
Drawing

 

 

1l ea.

Design, fabricate and install a work platform to fit the

 

top of the reactor cell. The platform is to have remov-

 

able deck sections for access to all work areas of the

 

cell; contain tool securing devices; and lighting and

 

other visual aids necessary for underwater remote work.

 

 

Design (100 md)

$ 18,300

 

Materials

$10,000

 

Fabrication & Installation - (200 md)

 

31,200

 

 

1l ea.

Design, fabricate and install a work platform to fit the

 

top of the drain tank cell. The platform is to have

 

removable deck sections for access to all areas of the

 

cell; contain tool handling and securing devices; énd

 

lighting and other visual aids necessary for underwater

 

remote work.

 

Design ' ' (100 md)

$ 18,300

 

Materials

$10,000

 

31,200

 

Fabrication & Installation ‘ (200 md)

 

 

 

 

NET MATERIAL AND LABOR

 

PREPARATORY WORK - WORK PLATFORMS

CPFF

FIXED PRICE

ORNL

 

 

 

 

$126,000

 

UCN-1297
3 7-712)

Ll
 

QUANTITY REMOVAL OF RADIOACTIVE MATERIAL UNIT COSTS MATERIAL ce
UNIT MAT'L | LABOR Drawing

G&A on materials: 20,000 x 0.35 ' $ 7,000

$27,000 $ 99,000

 

 

 

 

NET MATERIAL AND LABOR

 

FIXED PRICE ORNL
PREPARATORY WORK - WORK PLATFORMS
$422,100
UCN-1297
1

 

87T
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY REH6VAL OF RADIOACTIVE MATERIAL UNIT COSTS MATERIAL LABOR | Reference
UNIT MAT'L | LaBOR Drawing
.l ea.| Pipe cutter, abrasive, for horizontal 5'" INOR-8 pipe.
Design (50 md) $ 9,200
Fabrication Labor (50 m&) 7,800
Materials $2,500
Mockup & Development (50 md) 500 7,800
1l ea.| Pipe cutter, abrasive, for vertical 5" INOR-8 pipe. B T
Design (50 md) i $ 9,200
Fabrication (SO_Fd) 7,800
Materials $2,500 ,’:
Mockup & Development flSO-fid) 500 7,800 ©
2 ea.| Pipe cutters, hydraulic, for vertical or horizontal /2"
thru 2" carbon séeel, stainless steel and INOR-8 pipe
(commercial hydrailic shears).
Design (50 md) $ 9,200
Fabrication. (30 md) 4,700
Haterial @ $2,500- each $5,000
Mockup & Development (50 md) 500 7,800
NET MATERIAL AND LABOR
TOOLING CPFF FIXED PRICE ORNL
UCN-1297

3y 7T-12)
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUG:ITTITY REMOVAL OF RADIQACTIVE MATERIAL UN‘”. COSTS MATERIAL LABOR Reference
MAT'L | LABOR Drawing
2 ea. -Cufters, hydraulic, for miscellaneous 1/4" to 1/2" tubing
MI cable, electrical leads, etc. (commercial hydraulic
units).
Design ' (50 md) $ 9,200
Fabrication (30 md) 4,700
M;terial @ $500 each $1,000
Mockup & Develcpment (50 md) 500 7,800
2 ea.| Snips, manual, for cutting thermocouple leads, electrical
leads, etc. ‘ |
Design (30 md) $ 5,500
Fabrication (30 md) 4,700
Material $ 500
. Mockup & Development (10 md) 100 ‘1,600
NET MATERIAL AND LABOR
TOOLING CPFF FIXED PRICE ORNL
772
‘Il! 1 ! . .'%,jll',, t, by

i
?s"-,

0tl
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY REMOVAL OF RADIOACTIVE MATERIAL UNIT COSTS MATERIAL LABOR Reference
UNIT MAT'L | LABOR j Drawing
2 ea.| Cutters, torch, acetylene, for cutting horizontal carbon

- steel support sfructures. |
Design (30 md) $ 5,500
Fabrication (30 md) 4,700
Material @ $500 each. $1,000
Mockup & Development (50 md) 500 7,800 _
2 ea.| Cutters, torch, acetylene for cutting vertical carbon
steel support structures.
Design {30 md) $" 5,500
Fabrication (30 md) | 4,700
Material @ $500 each $1,000
Mockup & Development (50 md) 500 7,800
l ea.| Tool, lifting, for removél of fuel pump motor.
Desgign (existing)
Fabrication (30 md) $ 4,700
Material § 500
NET MATERIAL AND LABOR
. CPFF FIXED PRICE ORNL
TOOLING
UCN-1297

3y 7-72)

TET
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY REMOVAL OF RADIOACTIVE MATERIAL UNIT COSTS MATER| AL LABOR “Reference
uNIT MAT'L | LABOR Drawing
1 ea.| Tool, lifting, for removal of fuel pump rotary elemen;.

Design (existing)
Fabrication (30 md)‘ $ 4,700
Material $ 500
1 ea.| Tool, 1lifting, for handling fuel pump bowl.
Design (existing) E-56336
Fabrication (50 md) '$ 7,800
Material $1,000
1 ea.| Tool, 1lifting, for handling fuel heat exchanger. |
Design (exist.i_ng) E-56340
Fabrication (75 md) $ 11,700
P;aterial $1,500
1 ea.; Tool, lifting, for removal of drain tank steam domes.
Design (existing) D-56339
Fabrication (30 md) § 4,700
Material $ 500
NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL
TOOLING
i )

.
; ot s /A

1.,.. o
"

cel
QUANTITY REMOVAL OF RADIOACTIVE MATERTAL UNIT COSTS MATERIAL
UNIT : MAT'L [ LABOR

for removal of fuel drain tanks.
Des
Fabrication

Material

2 ea.| Tool, lift for removal of heater units.
Des
F.

Ma

coolers.

for removal of thermal shield slides.
exist

Fabrication ‘ (50 md

. NET MATERIAL AND LABOR

TOOLING

UCHN-1297
s 7100

$ 7,800

FIXED PRICE

erence
Dr

D-56338

E-56345

 

€eT
 

QUANTITY REMOVAL OF RADIOACTIVE MATERIAL
UNIT .
1 for removal of fuel stor
Fabrica
Mater

6 ea.| Tool, 1lif and various 1

of s ts of ; (3" to 6").
Des
Fabrication
Material
TOOLING

UCN-1297

(3 11

¢

oL

UNIT cosT . MATERIAL
MAT'L | LABOR :

e tank.

for removal .

for removal

NET MATERIAL AND LABOR

 

T
Drawing

QRNL

el
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY REMOVAL OF RADIOACTIVE MATERIAL UNIT COSTS MATERIAL +AB0R Reference
UNIT : MaT‘'L | LABOR ‘ Drawing
6 ea.| Tool, lifting and handling, various lengths, for removal

of segments of structural components.

Design | (50 md) $ 9,200
Fabrication. (50 md) 7,800
Material $1,000

1 ea.| Tool, lifting, for removal of NaF absorber. _
Design (20 md) $ 3,700.
Fabrication (20 md) 3,100
Material e $ 200

1l ea.| Tool, 1lifting, for removal of caustic scrubber.
Design (10 md) $ 1,800
Fabrication (20 md) 7,800
Material . . . $ 200

NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL
TOOLING

 

 

 

 

 

UCN-1297
(s 772

GET
 

 

MATERIAL

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY REMOVAL OF RADICACTIVE MATERIAL UNIT COSTS LABOR Reference
UNIT MAT'L | LABOR Drawing
2 ea.| Tool, breaker, for breaking out core éraphite bars.

Design (30 md) -$ 5,500
Fabrication (30 md) 4,700
Material $1,000
Mockup & Development (20 md) 500 3,100
2 ea.| Tool, lifting and handling, for removal of core graphite
bars.
Design (30 md) ~ 1 $§ 5,500
Fabrication (30 md) 4,700
Material $1,000 N
Mockup & Development (30 md) 1,000 4,700
1 lot} Tools, lifting and handling, for removal of reactor core
can and vessel segments,
Design (100 md) $ 18,300
Fabrication (100 wmd) 15,600
Material $5,000 '
Mockup & Development (50 md) 1,000 7,800
NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL
TOOLING '
UCN-1297 == -—“‘;‘_‘.].‘_"f —
3 7721

9¢T
RADIOACTIVE MATERIAL

t wrench extensions
hammers, etc., des

tions (~100 tools).

terial

lasma rch, for t the reactor
tor core can and the thermal shield.

e from exist des

Estimate made on basis of actual cost plus

escalation from 1971 to 1977 @ 70% of similar
technique used on the Elk River Reactor dis-

mantling.

NET MATERIAL AND LABOR

 

MATER!} AL

$170,000

170,000
510,000
850,000

850,000

LET
MATERIAL

QUANTITY REMOVAL OF RADICACTIVE MATERIAL UNIT COSTS
UNIT MAT 'L LABOR

 
  

1 lot | Miscellaneous visual aids; i.e., lights $10,000

binoculars ris etc.

G&A on materials: 0.35(2,602,500 - 2,550,000) $18,400
UCC-ND . o 2,620,900 | $450,200

NET MATERIAL AND LABOR
‘ FIXED PRICE
TOOLING

UCN-1297
3y 772

Reference

ORNL

$3,071,100

8ET
QUANTITY REMOVAL OF RADIODACTIVE MATERIAL

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

UNIT COSTS __' MATERTAL l CaBoR Reference
UNIT MAT'L | LABOR | | Drawing
i ! :
1l ea.| Container, shielded, for transport and storage of the ! '
i
fuel pump rotary element. (~20" ID x 30" tall w/3" Pb ’ |
) i -
shielding) o '
" .
Design 4L $ 3,700
Fabrication 6,200
Materials: 4,000 lbs Pb L L_S 1,400 i
Other 509 _"iy . R D
:
] ]
|
1l ea. | Container, shielded, for transport and storage of the _ —— -
fuel pump bowl. (40" ID x 30" tall w/3" thick Pb i ;
| ,
; i
shielding) ! f
|
Design * L ! $ 3,700
Fabrication 6,200 |
Materials: 9,000 1bs Pb $ 3,200
Other 500
NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL
SPECIAL TRANSPORT AND STORAGE CONTAINERS

 

 

 

 

UCN-1297
3y 7-72

6Ll
 

QUANTITY REMOVAL QF RADIOACTIVE MATERIAL UNIT COSTS MATER!AL LABOR Reference
UNIT . MAT'L | LABOR Drawing

 

 

 

1 ea. | Container, shielded, for transport and storage of the fuel

 

pump overflow tank. (32" ID x 36" tall w/3" Pb shielding)

 

 

 

 

Design : (20 md) $ 3,700 -
Fabrication . (40 md) 6,200
Materials: 7,700 lbs Pb $ 2,Y700

Other 500

 

 

1l ea. | Container, shielded, for transport and storage of primary

 

heat exchanger. (40" x 60" x 100" inside w/3" Pb

 

 

o%T

 

 

shielding)
Design (30 md) 1% 5,500 |
Fabrication (40 md) ] 6,200
Materials: 33,500 lbs Pb ) $}1,700 L

 

Other ' 1,000

 

 

 

 

 

 

 

 

NET MATERIAL AND LABOR

 

 

CPFF FIXED PRICE ORNL

 

b—— - -

SPECIAL TRANSPORT AND STORAGE CONTAINERS

 

 

 

 

 

UCN-1297
3y 772}

 
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY REMOVAL OF RADIOACTIVE MATERIAL UNIT COSTS MATER1AL LABGR Reference
UNIT | maTL T LaBOR Drawing
S ea. | Containers, sfiielded, for transport and storage of freeze 40610.

flanges w/clamps. (35" x 60" x iO" inside w/3" Pb
shielding)
Design . ' (30 md) $ 5,500
Fabrication : (100 md) 15,600
Materiais: S @ 9,000 1bs = 45,000 1lbs Pb $15,800
Other - 5 @ $500 each 2,500
10 ea.| Containers, shielded for transport and storage of multiple
removable heater units. (30" x 36" x 120" inside w/2" Pb)
Design (30 md) $ 5,500
Fabrication: 10 @ 30 md (300 md) 46,800
Materials: 10 @ 15,000 i1bs = 150,000 lbs.Pb $52,500
Other - 10 @ $500 each 5,000
NET MATERIAL AND LABOR
CPFF ORNL

SPECIAL TRANSPORT AND STORAGE CONTAINERS

 

 

 

FIXED PRICE

 

 

UCN-1297
3y 772)

9T
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY REMOVAL OF RADIOACTIVE MATERIAL UnIT cosTs MATERTAL LCABOR Reference
NIt : MAT'L | LaBOR Drawing
1 ea. | Container, shielded, for transport and storage of Line

100 thermal shield slide. (24" x 30" x 48" w/4" Pb
shielding)
Design . (30 md) $. 5,500
Fabrication (30 md) |
Materials: 14,000 1bs Pb $74,900
Other 500 .
1 ea. Container. shielded, for transport and storage of Line
102 thermal shield slide. (34" x 30" x 72" w/4" Pb
shielding)
Design (30 md) $ 5,500
Fabrication (30 md)
Materials: 19,000 1lbs Pb $ 6,700 -
- Other ‘500
NET MATERIAL AND LABOR
CPFF ORNL

SPECIAL TRANSPORT AND STORAGE CONTAINERS

FIXED PRICE

 

 

 

 

 

UCN-1297
i 772

 

T
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

© QUANTITY REMOVAL OF RADICACTIVE MATERIAL UNIT COSTS MATERIAL LABOR Reference
UNIT . MaT'L | LABOR Drawing
1l ea.| Container, shielded, for transport and storage of Line
103 thermal shield slide. (24" x 30" x 140" w/4" Pb
shielding)
Design (30 md) $ 5,500
Fabrication (40 md) 6,200
| Materials: 36,000 lbs Pb 512,600
Other __n"___},OOO
1 ea.| Container, shielded, for transport and storage of the _
off-gas valve box with contents. (48" x 36" x 60" w/2"
Pb shielding)
Design (20 md) $ 3,700
Fabrication (30 md) 4,700
Materials: 10,000 lbs Pb | $ 3,500
Other 500
NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL
SPECIAL TRANSPORT AND STORAGE CONTAINERS
UCN-1297

 

 

 

 

» 7.1

€71
 

 

MATERIAL

LABOR

Reference

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY REMOVAL OF RADICACTIVE MATERIAL UNIT COSTS
UNIT MAT'L | LABOR Drawing
3 ea.| Shields, tranmsport, for transporting 55-gallon drums of
material, bottom loading and unloading w/6" lead shield-
ing. Approximate weight, 16,000 1bs each.
Cost: Design, matérial and fabrication based on pre-
vious similar items @ $400/1b = $60,000 each. $120,000
1 ea.| Container, shielded, for transport of the charcoal bed
valve box w/contents. (30" x 36" x 60" w/2" Pb shielding) .
Design : (20 nd) $ 3,700
Fabrication | (30 md) 4,700
Materials: 9,000 1bs Pb $ 3,200
Other 500
2 ea.| Containers, wo/shielding, for tramsport of ébmponent
cooling air blower motors (75 hp).
Désign (20 md) $ 3,700
Fabrication ' (40 md) 6,200
Materials: 2 @ $500 each $ 1,000
NET MATERIAL AND LABOR
SPECIAL TRANSPORT AND STORAGE CONTAINERS <t CLXER PRICE o
N -
@ . . @
e A

AA
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY REMOVAL OF RADIOACTIVE MATERIALS UNIT COSTS MATERIAL LABOR Reference
uNIT MAT'L | LABOR Drawing
2 ea.| Containers, wo/shielding, for containment of the compo-

nent cooling air blowers (size 10" x 15", Roots
Connersville). (40" x 50" x 60")
Design ] ~ (30 1-nd) $ 5,500
Fabrication: 2 @ 20 md each (40 md). 6,200
Material: 2 @ $500 each $ 1,000
1 ea.| Contalner, wo/shielding, for containment of off-gas
sampler assembly. (40" x 50" x 50") ] L
Design (30 md) $ 5,500
Fabrication (30 nd) 4,700
Material $ 590
3 ea.| Contailners, wo/shieidiné, for containment of the drain’
and flush salt tanks. (52" x 10" x 90" tall)
Design (30 md) $ 5,500
Fabrication: 3 @ 30 md each (90 md) 14,000
Material: 3 @ $§1,000 each $ 3,000
NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL

SPECIAL TRANSPORT AND STORAGE CONTAINERS

 

 

 

 

 

UCN-1297
3 7-72)

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QUANTITY REMOVAL OF RADIOACTIVE MATERIAL UNIT COSTS MATERIAL LABOR Reference
UNIT MAT'L | LABOR Drawing
1 ea.| Container, wo/shielding, for containment of the fuel

storage tank. (55" OD x 120" tall)
Design ‘ (30 md) $ 5,500
Fabrication (30 md) 4,700
Material $ 1,000
1l ea.| Container, shielded, for transport and storage of the
fuel sampler enricher. (48" x 48" x 60" w/6" Pb
shielding)
Design (50 md) 5 9,200
Fabrication (75 md) 11,700
" Materials: 50,000 1lbs Pb $l7,590
Other 2,500
NET MATERIAL AND LABOR
' : CPFF FIXED PRICE ORNL
SPECIAL TRANSPORT AND STORAGE CONTAINERS R

 

 

 

 

UCN-1297
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QUANTITY REMOVAL OF RADIOACTIVE MATERIAL UNIT COSTS MATER/I AL LABOR Reference
UNIT MAT'L | LABOR Drawing
1 ea.| Container, shielded, for transport of the fuel process

sampler assembly. (48" x 48" x 60" w/2" Pb shielding)
Design (50 md) $ 9,200
Fabrication (75 md) 11,700
Materials: 9,000 1lbs Pb $ 3,200
Other 2,500 o
G&A on material: 283,400 x 0.35 $ 99,200
$382,600 $257,600
NET MATERIAL AND LABOR |
CPFF FIXED PRICE ORNL
SPECTAL TRANSPORT AND STORAGE CONTAINERS
1$640,200

 

 

 

 

UCN-1297
3 772

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QUANTITY REMOVAL OF RADIOACTIVE MATERIAL UNIT COSTS MATERI AL LABOR Reference
UNIT MAT‘L | LABOR Drawing
50 ea. { Remove top beam holdown nuts and studs, (20 md) $ 2,000 40955
(2 1/4" 0D x 4'-0" long)
15 ea. ! Remove top beams to cutside storage. (30 md) $ 3,000 40951
2 each 2'-0" x 3'-6" x 15'-0" long
2 each 2'-0" x 3'-6" x 20'-4" long
2 each 2'-0" x 3'-6" x 24'-0" long
2 each 2'-0" x 3'-6" x 26'-6" long
7 each 2'-0" x 3'-6" x 30'-0" long
1 ea. | Remove seal membrane, section and haul to burial (40 md) $ 4,000 | 40972-74
ground. (24'-6" OD x 1/8" thick stainless steel)
!
1 job | Flood cell to bottom of lower plugs. (10 md)| $ 1,000 -
28 ea. | Remove lower roof plug steel crack fillers. (20 md)| - $ 2,000 40954 .
10 ea. | 55-gallon stainless steel drums. $1,000
NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL

REACTOR CELL EQUIPMENT

 

 

 

 

 

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QUANTITY REMOVAL OF RADIOACTIVE MATERIAL UNIT CosTs | MATERIAC LAeeR Reference
MAT'L | LABOR Drawing
31 ea. | Remove lower shieid plugs. _ (20 md) $ 2,000 40954
1 job | Install work platforms over cell. (10 md) $ 1,000
1 ea. | Remove and dispose of east cell cooler. (2 roof (20 md) $ 2,000 56292
plugs; cooler w/support)
1 job | Remove and dispose of west cell cooler. (2 roof (20 md) $ '2,000 56293
plugs, cooler and support structure) ~
24 ea. | Remove spacers from salt piping heaters. (60 md) $ 6,000 ! 51600
30 ea. | Remove salt piping heaters. - L 51600
2 ea. | Remove heat exchanger heater spacers. (10 md) $ 1,000 51600
3 ea. | Remove heat exchanger heaters. 51600
5 ea. | Remove fuel pump bayonett heaters. (10 md) $ 1,000 51600
5 ea. | 55-gallon drums stainless steel. $- 500
' NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL
REACTOE\ CELL EQUIPMENT

 

 

UCN-1297
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QUANTITY REMOVAL OF RADIOACTIVE MATERIAL UNIT COSTS | MATERIAL LABOR Reference
UNIT ‘ maT'L | LABOR Drawing
9 ea. | Remove reactor bayonett heaters. _ (20 md) $ 2,000 51600

10 ea. | 55-gallon stainless steel drums. $1,000

57 ea. | Remove electrical disconnects w/flexible leads. (30 md) $ 3,000 56350

20 ea. | 55-gallon stainless steel drums. $2,000

65 ea. | Remove thermocouple disconnects w/flexible leads. (30 md) $ 3,000 56350

20 ea. | 55~-gallon stainless steel drums $2,000
1 job| Cut and remove 5" coolant salt piping. (V55 (50 md) ’ $ 5,000 40700

lin ft; ~30 cuts)

10 ea. | 55-gallon stainless steel drums. $1,000
2 ea. | Cut and remove coolant salt line freeze flanges (30 wd) $ 3,000 40700

w/support nests.
' NET MATERIAL AND LABOR
cprk_ FIXED PRICE ORNL

REACTOR CELL EQUIPMENT

 

 

 

 

 

UCN-1297
1y 7-72)

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QUANTITY REMOVAL OF RADIOACTIVE MATERIAL UNIT COSTS MATER AL L-ABOR Reference
UNHT LABOR :

3,000 40700

3,000 40700

fuel ’ 40704

and 3/4" x ~10'

 

Remove fuel bowl.

1l ea.| Remove fuel overflow tank. (20 md ' 2.000 56418-19
' NET MATERIAL AND LABOR

- FIXED PRICE
REACTOR CELL EQUIPMENT

UCH-1297
(3 1724

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QUANTITY REMOVAL OF RADIOACTIVE MATERIAL UNIT COSTS MATERIAL LABOR Ref€rence
UNIT MAT'L | LABOR Drawing
1 iob | Remove fuel pump support structure. (30 md) $ 3,000 41463

10 ea. | 55-gallon stainless steel drums. $1,000

* 51606
1 ea. | Remove fuel pump furnace. (30 md) $ 3,000 51604
3 ea.| 55-gallon stainless steel drums. $ 300
1 ea. | Remove heat exchanger. (50 md) $ 5,000
1 job!| Remove heat exchanger heater bases. (10 mgd) $ 1,000 !
1 iob| Remove heat exchanger support structure. (20 md) $§ 2,000 |
. i
!

15 ea. | 55-gallon stainless steel drums. $1,500

5 ea.| Remove component cooling ailr control valves (20 md) $ 2,000
w/operators. (Size 1")
NET MATERIAL AND LABOR
CPFF FIXED PRICE OANL

REACTGR CELL EQUIPMENT T T T
UCN-1297 - T
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QUANTITY REMOVAL OF RADIOACTIVE MATERIAL

 

UNIT

Remove ent coo air control valves

w ators. Size 3"

on stainless steel drums.

Remove

structures.

teel drums.

6" oD x 20'-0"

on stainless steel

REACTOR CELL EQUIPMENT

 

UCN-1297.
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NET MATERIAL AND LABOR
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY REMOVAL OF RADIOACTIVE MATERIAL UNIT COSTS MATERIAL LABOR Reference
UNIT MAT'l. | LABOR Drawing
10 ea. | 55-gallon stainless steel drums. $1,000
40704
1 job | Remove miscellaneous auxiliary piping from cell (200 md) $ 20,000 56267
walls. Water, air, off-gas, etc. (~1,000 ft,
Size 1/2" to 2" pipe, carbon steel and stainless
steel)
20 ea. | 55-gallon stainless steel drums. $2,000
1 job| Remove electrical mineral insulated cables from (100 md) $ 10,000 56232
cell wall to various junction boxes. (3/8" OD
Cu sheathed, 84 each 10' to 40' long from
penetrations R2 and RS)
10 ea.| 55-gallon stainless steel drums. $1,000
1 job! Remove heater base insulation. (50 wd) $ 5.000
NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL

REACTOR CELL EQUIPMENT

 

 

 

 

 

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QUANTITY REMOVAL OF RADIOACTIVE MATERIAL UNIT COSTS MATERIAL LABOR Reference
UNIT MAT'L | LABOR Drawing
' T 41860
1 job | Remove fuel and coolant salt piping supports (100 md) $ 10,000 41861
: ’ 41862
w/heater base insulation supports. (v65 lin ft- :
base insulation carriage, 1l each, pipe . support
assemblies, 11 each, pipe hanger rods)
15 ea. | 55-gallon stainless steel drums. $1,500
40518
1 job!| Remove equipment support steel. (~75 1lin ft (100 mg) $ 10,000 40579
8" WF 24: 25 1in ft 10" WF 25; 130 lin ft
7' 9.8; miscellaneous c¢clips, etc.)
50 ea.| 55-gallon stainless steel drums. $5,000 .
1 job| Remove leak detector tubing from céll wall (40 md) S 4.000 55494
penetration to various flanged disconnects.
(40 each 1/4" OD x 0.083" wall stainless steel
x 20' to 50" long)
15 ea.| 55-gallon stainless steel drums. $1,500
NET MATERIAL AND LABOR
CPFE FIXED PRICE

REACTOR CELL EQUIPMENT

ORNL

 

 

 

 

UCN-1297
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QUANTITY REMOVAL OF RADIQACTIVE MATERIAL UNIT COS5TS MATERIAL LABOR Reterence
UNIT MAT'L | LABOR Drawing
1 job | Remove MI cable and TC lead cable tray. (30 md) $ 3,000 55489

10 ea.| 55-gallon stainless steel drums. $1,000
1 job| Remove fuel salt drain line from reactor to (20 md) $ 2,000
drain tank cell penetration. (1 1/2 Sch 40
INOR 8 x 15' long w/insulation)
6 ea.| 55-gallon stainless steel drums. $ 600
1 job| Remove drain line supports. (n15' carriage (20 mq) $ 2,000
asgembly)
10 ea.| 55-gallon stainless steel drums. $1,000
1 job| Clear top of thermal shield. Cut brackets, 30 md) $ 3,000 41894
TC, leak detector and heater disconnects, etc.
Cut cooling water lines connecting compartmefits.
NET MATERIAL AND LABOR
CPFFA FIXED PRICE ORNL

REACTOR CELL EQUIPMENT

 

 

 

 

 

 

UCN- 1297
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QUANTITY REMOVAL OF RADIOACTIVE MATERIAL UNIT COSTS MATER) AL LABOR Reference
uUNIT MAT'L | LABOR Drawing
6 ea. | 55-gallon stainiess steel drums. $ 600 B
1 ea. | Remove Line 103 slide assembly. (5 md) $ 500 40722
1 ea. | Remove Line 100 slide assembly. (5 md) | $ 500 40722
1 ea. | Remove Line 102 slide assembly. (5 md) 1§ 500 40722
1 job| Install reactor cutting support fixture. (20 md) _ $ 2,000
1 job | Remove reactor and thermal shield 1id to cutting (30 md) $ 3,000
support fixture, )
1 job| Cut reactor hanger rods and remove thermal (20 md) $ 2,000
shield 1id. i}
1 job| Install cutting tools and cut top head from (30 md) $ 3,000
‘reactor vessel,
NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL
REACTOR CELL EQUIPMENT
UCN-1297

- LGT
 

REMOVAL OF RADIOACTIVE MATERIAL

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY MATERIAL LABOR Keterence
UNIT Drawing
5 ea. | 55-gallon stainless steel drums. $ 500
1 job | Remove core graphite bars. (636 each 2" x 2" (200 md) $ 20,000 40416

x 67" long)

20 ea.| 55-gallon stainless steel drums. $2,000
1 job| Cut and remove remainder of reactor vessel and {200 md) $ 20,000 40402

core can.

50 ea.| 55-gallon stainless steel drums. $5,000
1 job| Install cutting fixture into thermal shield. (30 md) $ 3,000
1 job| Cut top from thermal shield main section. (30 md) $§ 3,000 40727-30

10 ea.| 55-gallon stainless steel drums. $1,000

NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL

REACTOR CELL EQUIPMENT

 

 

 

 

 

 

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QUANTITY ’ REMOVAL OF RADIOACTIVE MATERIAL ’ OSTS MATERIAL erence
UNIT LABOR :

27-30

Section and remove thermal shield main . $ 20,000

n950 ft? 1" thick stainless steel

66T

NET MATERIAL AND LABOR

FIXED PRICE

REACTOR CELL EQUIPMENT

 

UCN-1297
3 712
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY REMOVAL OF RADIOACTIVE MATERIAL UNIT COSTS MATERIAL LABOR Reference
UNIT MAT'L | LABOR Drawing
1 job | Remove Rashig rings from bottom of cell. (20 md) § 2,000 55493

{165 ft3 Borosilicate glass, 1 1/2" 0D x 1 3/16"
ID x 1 3/4" long, ~300 pe/ft> and 30 1b/ft>)
1 job | Decontaminate inside of reactor cell to allow (100 md) $ 10,000
entry.
30 ea. | 55-gallon stainless steel drums. $3,000
1 job | Remove sump poison-element strainer insert (10 md) $ 1,000 55493
assembly. Retain sump piping. (11 3/8" OD
x 2'=-3/4" long)
1 ea. | 55-gallon stainless steel drum. $ 100
1 ea. | Remove fuel pump auxiliary piping penetration (20 md) $ 2,000 40717
plug. (18" Sch 80 sleeve stainless steel and
carbon steel w/8 each 1/2" to 1" pipe penetra~
tions)
NET MATERIAL AND LABOR
FIXED PRICE ORNL

REACTOR CELL EQUIPMENT

CPFF

 

 

 

 

 

UCN-1297
3 7-72)

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QUANTITY REHOVAL OF RADIOACTIVE MATERIAL UNIT COSTS | MATERIAL LABCR Reterence
UNIT : MAT'L | LABOR | Drawing
i i
: |
2 ea.| 55-gallon stainless steel drums. | $§ 200
1 ea. | Remove nuclear instrument tube. (36" OD x 12°' (30 md) . $ 3,000 40715
long, inside cell only) 11
i
i
1 job| Remove sampler enricher assembly. (100 md) L $ 10,000
i
! : 3 -
1 jobi Remove sampler enricher penetration plug. (20 md) l 5 2,000
. 1
1l ea.| 55-gallon stainless steel drum. $ 100
! |
‘ - :
| {
2 ea.| Remove coolant salt anchor sleeve furnaces. (20 md) $ 2,000 | 51670
o |
- 41858(200)
.2 ea.| Remove coolant salt anchor sleeves. (30 md) | $ 3,000 55498(201)
2 ea.| 55-gallon stainless steel drums. $ 200
2 ea.f| Remove anchor sleeve shielding. (20 md) $ 2,000 55498
NET MATERIAL AND LABOR
CPFF FIXED PRICE ORMNL
REACTOR CELL EQUIPMENT

 

 

 

 

UCN-1297

(3

7-72)

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MATERI AL

 

LABOR

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY REMOVAL OF RADIOACTIVE MATERIAL UNIT COSTS Reference
u MAT'L ] LABOR Drawing
1 ea.| Remove 30" duct shadow shield. (20 md) $ 2,000 40749
2 ea.| 55-gallon stainless steel drums. $ 200
6 ea. | Remove cell penetration plugs R thru R, and R,. (180 md) $ 18,000 41863

(1'-10 1/2" oD x 3'-10 1/2" long)
6 ea.| 55-gallon stainless steel drums. $ 600
|
6 ea.| Decontaminate cell thimbles. (30 md) $ 3,000
A
1 job | Final decontamination of reactor cell. (50 md)] - L $ 5,000

31 ea.| Decontaminate lower shield plugs. (50 md) $ 5,000

31 ea.| Replace lower shield plugs. (20 md) $ 2,000

15 ea.| Decontaminate top beams. (30 md) $ 3,000

NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL
REACTOR CELL EQUIPMENT T —

 

 

 

UCN-1297
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QUANTITY REMOVAL OF RADIQACTIVE MATERIAL UNIT COSTS MATERIAL ~ LABOR Reference
UNIT MAT'L | LABOR Drawing
28 ea. | Decontaminate lower shield plug steel crack (20 md) $ 2,000
fillers.
28 ea. | Replace lower shield plug crack fillers. (10 md) $ 1,000
15 ea. | Replace top beams on cell. (20 md) $ 2,000
50 ea. | Decontaminate top beam holddown studs and nuts. (30 md) $ 3,000
50 ea. { Replace top beam holddown studs and nuts. (20 md) $ 2,000 .
: !
|
- | -
t I
T S
NET MATERIAL AND LABOR | $66 000 $353,500
'  CPFF FIXED PRICE ORNL
REACTOR CELL EQUIPMENT T T T T T
. ) $419,500 i _ N

 

 

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QUANTITY REMOVAL OF RADIOACTIVE MATERIAL UNIT COSTS MATER!AL LABOR Reference
UNET MAT'L | LABOR Drawing
82 eal Remove steel holddown keys from upper shield (5 md) $ 500 40946

plugs. (10" x 4 1/2" x 3 1/2")
Decontaminate beams and store for future use, (50 md) $ 5,000
40933
10 ea] Remove upper shield beams. (24'-7 1/2" x 2'-0" (25 md) $ 2,500 40946
X 3"'6")
Remove seal membrane (21'-10"x 21' x 1/8" thick (20 md) _ $ 2,000 40933
stainless steel) section and haul to burial
ground.
28 ea.| Remove steel shield plates from between lower (10 wd) $ 1,000 40939
plugs.
8 each, 1'-0" x 5'-6 1/2" x 1" thick
8 each, 1'-0" x 7'- 1 1/8" x 1" thick
8 each, 1'-0" x 5'-8" x 1" thick
2 each, 1'-0" x 1'-3 1/4" x 1" thick
2 each, 1'-0" x 2'-1/4" x 1" thick
MNET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL

DRAIN-TANK CELL - GENERAL

 

 

 

 

UCN-1297
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QUANTITY REMOVAL OF RADIOACTIVE MATERIAL UNIT_cosTs MATERIAL
UNIT . MAT'L | LABOR ) Drawing

Decontaminate shleld plates and store for future (10 md)

uge.

'NET MATERIAL AND LABOR $ 12,000

CPFF FIXED PRICE

DRAIN-TANK. CELL - GENERAL )
$ 12,000

 

UCN-t297
3 772

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QUANTITY ) REMOVAL OF RADIOACTIVE MATERIAL UNIT COSTS MATER) AL LABOR Reference
UNIT ’ MAT'L | LABOR Drawing
1 job | Flood the cell to bottom of lower plugs. $ 1,000

LUY33

12 ea. ! Remove lower roof plugs from north bay. $ 1,000 40946

9 each, 2' x 4' x 5'-6 1/2" long, 6,100 lbs,
MK-4

1 each, 1'-3 1/4" x 4' x 6"'-4 3/4" long,
3,700 1bs, MK-13

1 each, 1'-3 1/4" x 4' x 3'-11 1/2" long,
2,600 1bs, MK-14

1 each, 1'-3 1/4" x 4' x 4'-10 1/2" long, -
2,700 lbs, MK-15

12 ea. | Decontaminate plugs for future use. $ 5,000

1 ea. | Remove north shield plug support beam. (8" 100 40944
x 2'-1 1/2" x 17'-5 1/2" long)
1 ea. | Decontaminate for future use. 200
NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL

DRAIN-TANK CELL -~ NORTH BAY

 

 

 

 

 

UCN-1297
3 7-72)

 

991
S - M) . . . I- r
. ' ' . : : ! ! ! ' C. »ey
xi‘ r b‘\ ' ’ 'l"' ) > . I".c . J ’ o
. A .

QUANTITY REMOVAL OF RADIOACTIVE MATERIAL _UNIT COSTS MATERIAL erence
UNIT . MAT'L | LABOR Dr

Remove tic valves HCV-544

barr
stainless steel drum.

Remove valve su rts, HCV-544 and -573. One

barrel

NET MATERIAL AND LABOR

FIXED PRICE
DRAIN-TANK CELL - NORTH BAY

 

UCN-1297
3 7.7

L9T
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY REMOVAL® OF RADIOACTIVE MATERIAL UNIT COSTS MATERI AL LABOR ReTEerence
UNIT : MAT'L | LABOR Drawing
. _ §1512=13
1 job | Remove miscellaneous auxiliary piping, thermo- (200 md) $ 20,000 | 40708-09
couple leads, heater leads, leak detector lines,
and instrument air lines above drain tanks.
100 ft pipe, 1/2" to 1" Sch 40
22 each flexible heater lead assemblies _.40878
200 ft air lines, 1/4" and 3/8" ODT
55404, 55405;
n100 ft leak detector tubing, 1/4" OD stainless 55406
steel
Steam dome jumper lines, 3" and 2"
22 each heater disconnect junction boxes
L0878, 55404,
18 each thermcouple junction boxes 55405, 55406,
- §5478 T
25 fr, 6" x 6" cable trough _ ! .
|
50 ft, 4" x 4" cable trough o .
~500 ft mineral insulated cable from cell wall ‘ !
to junction boxes, 3/8" OD copper sheathed
2,500 ft thermocouple leads from cell wall to 40878
junction boxes, 1/4" OD copper sheathed and
1/8" OD stainless steel sheathed
NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL
DRAIN-TANK CELL - NORTH BAY -

 

 

 

 

UCN-1297
772

5
:‘.' “t‘,
T ~

89T
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY - REMOVAL OF RADIOACTIVE MATERIAL UNIT COSTS MATERIAL LABOR Reference

UNIT . ‘ MAT'L | LABOR Drawing
S0 ea.| 55-gallon stainless steel drums. $5,000

40%63, 40731,
1 ea. | Remove FDT-1 steam dome asgembly. (20 md) $ 2,000 |40708
, 57490
5 ea.| Remove heaters from Line 106." (5 md) $ 500 MIC-G-116
S ea.| 55-gallon stainless steel drums. $ 500
-

1 ea.! Remove FV-106. (1 1/2" INOR-8) (10 md) $ 1,000

1 éa.| 55-gallon stainless steel drum, § 100

15 ft | Remove Line 106. (1 1/2" Sch 40 INOR-8) (10 md) s 1,000

1 ea.| 55-gallon stainless steel drum. $§ 100

8 ea.| Remove Line 106'heater base insulation units (10 md) $ 1,000 MIC-G-117

(B-106-A thru B-106-G2).
NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL

DRAIN-TANK CELL - NORTH BAY

 

 

 

 

 

UCN-1297
» 7.7

691
 

QUANTITY RADIOACTIVE MATERIAL

UNIT

heater base rt structure.

stainless steel drums.
Remove FDT-1 heater units,

stainless steel drums.

rt from FDT-1.

drain tank weigh cells.’

DRAIN-TANK CELL - NORTH BAY

UCN-1297
s 7-72)

NET MATERIAL AND LABOR

erence
Dr

$ 2,000

FIXED PRICE

0LT
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

'QUG:ETY REMOVAL OF RADIOACTIVE MATERIAL UNIT COSTS MATERIAL LABOR Reference
e ' - MAT'L | LABOR Drawving
2 ea. |55-gallon stainless steel drums. $ 200
1 job | Remove drain tank furnace. (50 md) $ 5,000
10 ea. | 55-gallon stainless steel drums. $ 1,000
1 job | Remove drain tank supports. (20 md) $ 2,000
4 ea. | 55-gallon stainless steel drums. $ 400
1 job | Remove transfer line #109. (15 fr, 1/2" Sch (20 md) $ 2,000
40 INOR-8 w/Calrod heaters and insulation
attached)
3 ea. | 55-gallon stainless steel drums. $ 300
1 job [ Remove transfer line #110 from‘north wall to (40 md) $ 4,000 41512
south side of bay. (%10 ft, 1/2" Sch 40 INOR-8
w/Calrod heaters and insulation attached)
NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL

DRAIN-TANK CELL - NORTH BAY

 

 

 

 

 

UCN-1297
3 772

TLT
 

 

REMOVAL OF RADIOACTIVE MATERIAL

 

MATERI AL

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

JUANTITY UN!IT COSTS | LABOR Reference
T MAT'L | LABOR Drawing
1 ea. | 55-gallon stalnless steel drum. $§ 100
1 ea. | Remove FV-109 w/heaters attached. (10 md) $ 1,000 41512
1 ea. | 55-gallon stainless steel drum. $ 100
1 job | Clean up remaining miscellaneous support clips, (25 md) $ 2,500

lines, cables, etec.

10 ea. | 55-gallon stainless steel drums. $ 1,000
1 job | Replace north shield plug support beam. (1 =d)| $ 100
1 job| Replace lower shield plugs in north bay. (10 md) $ 1,000

NET MATERIAL AND LABOR $12,000 $ 65,000
DRAIN-TANK CELL - NORTH BAY CPFF FIXED PRICE ORNL
$77,000

uUCH- 1297

13 77D

LT
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY REMOVAL OF RADIOACTIVE MATERIAL UNIT COSTS ] MATERIAL LABOR Reference
uNIt : MAT'L | LABOR Drawing
9 ea. | Remove lower shield plugs from center bay. {10 md) $ 1,000 40933

8 each, 2' x 4' x 7'-1 1/2" long, 8,000 1lbs,

MK-3

1l each, 1'-6" x 4' x 7'-1 1/2" long, 6,100

lbs, MK-16
1 job | Decontaminate lower plugs. (50 md) $ 5,000
1 job | Install work platform w/vent control panels. (10 md) $ 1,000
41512
2 ea. | Remove pneumatic valves HCV-545 and -575. (10 md) $ 1,000 41513
l ea. | 55-gallon stainless steel drum. 100
2 ea. | Remove valve supports, HCV-545 and -575. (10 md) $ 1,000 41877
l ea. | 55-gallon stainless steel drum. 100
NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL

DRAIN-TANK CELL - CENTER BAY

 

 

 

 

 

UCN-1297
3y 7.72)-

€LT
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY REMOVAL OF RADIOACTIVE MATERTIAL UNIT COSTS MATER| AL LABOR Reference
uniT : MAT'L | LABOR Drawing
1 job | Remove miscellaneous auxiliary piping, thermo- (200 md) $ 20,000 41512-13

couple leads, heater leads, leak detector lines
and instrument air lines.
2100 ft pipe, 1/2" to 1" Sch 40 .
mzi flexible heater lead assemblies 40878
~200 ft air lines, 1/4" and 3/8" ODT
2 each steam dome jumper lines
‘ 55404, 55405,
100 ft leak detector tubing, 1/4" OD 55406
A500 ft mineral insulated cable from fiorth bay
to junction boxes, 3/8" 0D copper sheathed
2,000 ft mineral insulated thermocouple leads
from north bay to junction boxes, 1/4" OD
copper sheathed
22 each thermocouple junction boxes 40878
27 each heater disconnects
~20 ft, 4" x 4" cable trough 55478
n10 ft, 6" x 6" cable trough
50 ea; 55-gallon stainless steel drums. $5,000
NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL

" DRAIN-TANK CELL - CENTER BAY

 

 

 

 

 

UCN-1287
3 77

LT
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

. v' Fe ' I; - '

QUANTITY REMOVAL OF RADIOACTIVE MATERIAL UNIT COSTS MATERIAL LABOR Rererence

UNIT MAT'L | LABOR Drawing
. 40463, 4U471,

1 ea. | Remove FDT-2 steam dome, (20 md) $ 2,000 -(40708
8 ea. | Remove FDT-2 heater units. (30 md) $ 3,000

20 ea. | 55-gallon stainless steel drums. $2,000
1 ea. | Remove disconnect support ring from FDT-2. (10 md) $ 1,000
1 ea. | 55-gallon stainless steel drum. $ 100
1 ea. | Remove FDT-2 furnace lid. (20 md) $ 2,000 51869
2 ea. | 55-gallon stainless steel drums. $ 200
1 ea. | Remove FDT-2. (20 nd) $ 2,000 40457
2 ea. | Remove FDT—-2 weigh cells. (10 md) $ 1,000
2 ea.| 55-gallon stainless steel drums.‘ $ 200

NET MATERIAL AND LABOR
. . ‘ CPFF FIXED PRICE ORNL
DRAIN-TANK CELL - CENTER BAY

 

 

 

 

 

UCN-1297
3 771

GLT
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY REMOVAL OF RADIOACTIVE MATERIAL UNIT COSTS MATERIAL - LABOR Reference
uNIT MAT'L | LABOR Drawing
1 ea. | Remove FDT-2 furnace. (50 md) -$ 5,000

10 ea. | 55-gallon stainless steel drums. §1,000
2 ea. | Remove FDT~2 gupports. (20 md) $ 2,000
4 ea. | 55-gallon stainless steel drums, $ 400
5 ea. | Remove heater spacers from Lines 103, 104 and (10 md) $ 1,000

105 heaters.
1 ea. | 55-gallon stainless steel drum. $ 100
MIC-116
10 ea. | Remove removable heater units from Lines 103, (10 md) $ 1,000 57490
104 and 105.

10 ea. | 55~gallon stainless steel drums. $1,000

2 ea. | Remove FV-104 and -105. (1 1/2" INOR-8) (10 md) $ 1,000
NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL

DRAIN-TANK CELL - CENTER BAY

 

 

 

 

 

UCM-1297
3 172
® .
* . * T

91
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

r ’., ". 1 ' - v,
QUG:;"_;TY REMOVAL OF RADIOACTIVE MATERIAL UNIT COSTS MATERIAL LABOR Reference
. MAT'L | LABOR Draving
2 ea. | 55-gallon stainless steel drums. $ 200
n20 ft |Remove uninsulated portion of Line 103 and (30 md) $ 3,000
Lines 104 and 105. (1 1/2"-40 INOR-8)
1 ea. | 55-gallon stainless steel drum. $ 100
2] ea. | Remove heater base insulation units. (20 md) $ 2,000 MIC-G-117
6 ea. | 55~gallon stainless steel drums. $ 600
1 job | Remove heater base support structure. (40 md) s 4,000
6 ea. | 55-gallon stainless steel drums. $ 600
2 ea. | Remove freeze valves FV-108 and -109 w/heaters (12 md) $ 1,200 41512
attached.
2 ea 55-gallon stainless steel drums. $ 200
NET MATERIAL AND LABOR
CPFF ORNL

DRAIN-TANK CELL - CENTER BAY

FIXED PRICE

 

 

 

 

 

UCN-1297
3 T-72)

LLT
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY REMOVAL OF RADICACTIVE MATERIAL UNIT COSTS MATERIAL LABOR "Reference
uNIT MAT'L | LABOR ' Drawing
20 ft |Remove transfer lines 108, 109 and 110. (~20 ft, .(25 md) $ 2,500
1/2" Sch 40 INOR-8 w/Calrod heaters and insulation
attached)
4 ea. |55-gallon stainless steel drums. $ 400
20 ft |Remove resistance heated portion of Line 103 (25 md) $ 2,500
w/insulation and TC's attached. (20 ft,
1 1/2"-40 INOR-8 w/3" thick insulation)
4 ea. [55-gallon stainless steel drumg. $ 400
2 ea. |Remove Line 103 welding and brazing platforms. (40 md] $ 4,000 41514
6 ea. [ 55-gallon stainless steel drums. $ 600
5 ea. | Remove drain line supports; (s~8, S-9, S-10, (25 md $ 2,500 E-41505
S-11 and S-13)
NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL
DRAIN-TANK CELL - CENTER BAY
UCN-t 297
] 7.72)
‘ \ .‘o . \ . . 3 t.- L

8IT
QUANTITY REMOVAL OF RADIOACTIVE MATERIAL ‘ UNIT COST
UNIT MAT'L LABOR

   
  

rt cli

10 ea. | stainless steel drums.

9 ea. lace lower shield in center

NET MATERIAL AND LABOR

DRAIN-TANK CELL - CENTER BAY

UCN-1297
3 7721

MATERIAL

$14,800

CPFF

$90,000

.l v‘f

erence
Dr

E-40933

ORNL

L IR 4
.

6L1
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY REMOVAL OF RADIOACTIVE MATERIAL T cosTe MATERTAL TAmoR Reference
UNIT MAT'C | LABOR Drawing
10 ea.| Remove steel shield plates from lower plugs. (10 md) $ 1,000
10 ea.| Decontaminate steel plates. (10 md) $ 1,000
12 ea.| Remove lower roof plugs from south bay. (10 md) $ 1,000 E-40933

7 each, 2' x 4' x 5'-8 1/2" long, 6,200 1bs,
MK-5
1 each, 2" x 4' x 5'-8 1/2" long, 6,200 lbs, L
MK-8
1 each, 2' x 4' x 5'-8 1/2" long, 6,200 lbs,
MK-9
1 each, 2'-0" x 4' x 7'-1 3/4" long, 6,700
lbs, MK-10
1 each, 2'-0" x &' x 3'-11 1/2" long, 4,400
1bs, MK-11
1 each, 2" x 4' x 5'-7 1/2" long, 5,006 1bs,
MK-12
12 ea.| Decontaminate lower shield plugs. (50 md) $ 5,000
NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL
DRAIN-TANK CELL - SOUTH BAY
e
@ . @
Y L, . LoaAr e Cely o

* .

W A

08T
 

QUANTITY . REMOVAL OF RADIOACTIVE MATERIAL T WMATERTAL erence
UNIT MAT'L | LABOR D

1 shield E-40944
"ox 2'-1 1/2" x 17'-5_1 2" 1
E~56291
2 ea. | Remove HCV=546 and -577. E-41513

on stainless steel d

E-56424

"MET MATERIAL AND LABOR
) FIXED PRICE
DRAIN-TANK CELL - SOUTH BAY

UCN-1297
3 71

18T
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY REMOVAL OF RADIOACTIVE MATERIAL UNIT COSTS MATERIAL LABOR . Reference
UNIT : MAT'L | LABOR Drawing
1 job | Remove miscellaneous auxiliary piping,'thermo— (200 md) $ 20.000 .
couple leads, heater leads, and ‘instrument fiir .
lines.
100 ft pipe, 1/2" to 1 1/2" Sch 40
20 each flexible heater lead assemblies E-40878
300 ft leak detector tubing, 1/4" OD x 0.083" E-40878
wall
14 each leak detector disconnects w/supports E-55405
20 each heater disconnects
10 each thermocouple junction boxes
20 ft, 6" x 6" cable trough
20 ft, 4" x 4" cable trough
500 ft mineral insulated cable from center bay
to junction boxes
~2,500 ft thermocouple leads from center bay
to junction boxes, 1/4" OD copper sheathed
and 1/8" 0D stainless steel sheathed
50 ea. { 55-gallon stainless steel drums. $5,000
NET MATERIAL AND LABOR
; CPFF FIXED PRICE . ORNL
DRAIN-TANK CELL - SOUTH BAY
R
® . @
i? ; :.' ' - . :*?“.' f.r; ' "?fi

¢8T1
 
 

QUANTITY REMOVAL OF RADIOACTIVE MATERIAL UNIT COSTS MATERIAL
UNIT MAT L LABOR

04, - (6 fr, 1 1/2" Sch 40 INOR-8

inless steel

erence
Dr

MIC-G-117
E-48758

 

 

NET MATERIAL AND LABOR

FIXED PRICE

DRAIN-TANK CELL - SOUTH BAY

UCHN-1297
3 711

 

 

€871
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY REMOVAL OF RADIOACTIVE MATERIAL UNIT COSTS MATERIAL CABOR Retference
uNIT MAT'L | LABOR Drawing
20 ea. | 55-gallon stainless steel drums. $2,000
1 ea. | Remove flush salt tank furnace lid. (20 md) $ 2,000
2 ea. | 55~-gallon stainless steel drums, $ 200
1 ea. | Remove flush salt tank (FFT). (20 md) $ 2,000
2 ea. | Remove flush salt tank weigh cells. (10 md) § 1,000
2 ea. | 55-gallon stainless steel drums, $ 200
1 ea. | Remove flugh salt tank furance. (75 md) $ 7,500
10 ea.| 55-gallon stainless steel drums. $1,000
1 job| Remove flush salt tank supports. | (10 md) $ 1,000
4 ea.| 55-gallon stainless steel drums. $ 400
NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL
DRAIN-TANK CELL -~ SOUTH BAY * -
UCh-1297 = N
2 7172
N e . . QL

 

8T
Ve =z - i ot Ve

»
.
1 T o ' . g
"II' | - ']‘II‘4 |
T . .

 

QUANTITY REMOVAL OF RADIOACTIVE MATERIAL MATERI AL
UNIT

7 from c
INOR-8 w/Calrod
attached

2 ea. { 55- stainless steel drums.

1 ea. | Remove freeze valve FV-107. (1 1/2" Sch 40

steel drum.

tance heater 103 w tion
~n25 fe, 1 1/2"

i

rts S-6 and S-7. 10 md)

NET MATERIAL AND LABOR

DRAIN-TANK CELL - SOUTH BAY

UCN- 1297
3y 172

FIXED PRICE

Drawing

E-41506

E-41506

C8T
  

QUANTITY REMOVAL OF RADIOACTIVE WASTE UNIT COSTS MATERIAL LABOR Reference
UNIT MAT'L | LABOR - Dr

transformer. . $ 1,000 E-56241

teel drum.

E~56241
E-~56240 -
10 ea. | 5 stainless steel drums. _ $1,000
' NET MATERIAL AND LABOR | 14 000 $ 70,000
CPFF FIXED PRICE ORNL
DRAIN-TANK CELL - SOUTH BAY
- $84,000
UCN-1297
3 1T

981
REMOVAL OF RADIOACTIVEAMATERIAL

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY UNIT COSTS MATERIAL [ LABOR Reference
UNIT
MAT'L | LABOR i Drawing
1 job | Remove lower roof plugs from north and center (20 md) $ 2,000
bays.
1 job ! Dewater the coil to ILW. (20 md) $ 2,000
1 job | Decontaminate inside of cell to allow limited (100 md) $ 10,000
personnel access.
1 job | Erect work platforms for penetration assembly (10 md) i § 1,000
removal from east and south walls.
1 job | Remove lines from penetration XXIV from reactor (20 md) $ 2,000 E-56240
Page 48,
cell to DT cell. (1 1/2" INOR-8 draim line, Design Manual
1 1/2" carbon steel air line, 2 each 1/2" stain-
less steel off-gas and vent lines)
3 ea.} 55-gallon stainless steel drums. $ 300
E=41503
1 job| Remove support structures from penetration XXIV. (10 md) $ 1,000 D-40713
. NET MATERIAL AND LABOR
_ , » CPFF FIXED PRICE ORNL
DRAIN-TANK CELL - GENERAL

 

 

 

 

 

UCH-t297
3 7-72)

(8T
 

QUANTITY REMOVAL OF RADIOACTIVE MATERIAL UNIT COSTS MATERIAL erence
UNIT MAT 'L ABOR

tration XXIV f reactor cell. D-41413

D-40947
Page o
Des Manual

Remove r. water and leak detector tration

shield pl at east wall. 6" diameter

stainless steel drums.

D-40947

trations A, B

D-40947

trations thru south wall. (3/4" thru 3") - (10 md $ 1,000 D-40947

NET MATERIAL AND LABOR
FIXED PRICE

DRAIN-TANK CELL - GENERAL

UCN-1297
3 712

. ' - . l .
. .
* A’ -« v ' N, 3
v N 3 .

: » ‘ .
l', "" . ’ * ' l.‘l" ot ! . oy 1

881
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY REMOVAL OF RADIOACTIVE MATERIAL UNIT COSTS MATERIAL LABOR Reference
uNIT MAT'L | LABOR Drawing
1 ea. | Remove penetration shield plug thru north wall (20 md) $ 2,000 D-40947

to fuel processing cell. (10" diameter)
1 ea. | Decontaminate sleeve to fuel processing cell. (10 md) $ 1,000 D-40947
1 job| Decontaminate entire drain tank cell to lowest (100 md) $ 10,000
practical level.
1 job| Replace all lower shield plugs in drain tamk (20 md) $ 2,000
cell.
1 job| Replace lower shield plug steel shield plates. (10 md) $ 1,000
1 job| Replace all upper shield beams and holddown keys (30 md) $ 3,000
in drain tank cell.
1l ea.| 55-gallon stainless steel drum. $ 100
NET MATERIAL ANDLABOR | ¢ 1,800 | § 54,200
CPFF FIXED PRICE ORNL
DRAIN-TANK CELL - GENERAL -
- $56,000

 

 

 

 

UCH-1297
i 772

TOTAL

$319,000

68T
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY REMOVAL OF RADIOACTIVE MATERIAL UNIT COSTS MATERIAL CABOR Reference
uniT MAT'L j LABOR Drawing
1 job | Remove fuel process sampler. (60 md) $ 6,000 |Job #10415
4 ea. | Remove sampler instrument panels. (16 md) $ 1,600 [Job #10415

55435
1 ea. | Remove absorber cubicle w/contents. (30 md) $ 3,000 55452
4 ea. | 55-gallon stainless steel drums. $ 400
6 ea. | Remove cell roof plugs to storage. (6 each (20 md) $ 2,000 55431
various sizes)
1 ea. { Remove space cooler from roof plug P-6 and (10 md) $ 1,000
dispose.
1 job | Set up work platforms and "'C" zone. (10 md) $ 1,000
1 job| Cut, place into containers, and remove piping, (200 md) $ 20,000
valves, heater and thermocouple leads, dis-
connects, junction boxes, etc.
"NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL
FUEL-PROCESSING CELL
UVCN-1297
3 772
Ia * a.'.. v t n

06T
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY REMOVAL OF RADIOACTIVE_MATERIAL UNIT COSTS MATER) AL LABOR Reference
UNIT _ MAT'L | LABOR Drawing
50 ea. | 55-gallon stainless steel drums, $5,000
1 ea. | Remove fuel storage tank. (50" OD x 116" high' (30 md) $ 3,000 40430
w/heaters and insulation)
1 ea. | Remove caustic scrubber. (3'-6".0D x 7'-0" tall (20 md) $ 2,000 55441
w/heaters and insulation) ]
1 job | Remove sodium fluoride trap shielding. (~3' x (10_md) $ 1,000
3" x 4" thick lead)
1l ea. | 55-gallon stainless steel drum. _ $ 100
1 ea. | Remove sodium fluoride ‘trap. (1'-8" diam x (20 md) $ 2,000 55446
1'-10" tall)
1l ea. | 55-gallon stainless steel drum. $ 100
NET MATERIAL AND LABOR
' CPFF FIXED PRICE ORNL

FUEL-PROCESSING CELL

 

 

 

 

 

UCN-1297
(3 7-12)

T6T
REMOVAL OF RADIOACTIVE MATERIAL

 

 

Reference

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY UNIT COSTS MATERIAL LABOR
UNIT MAT'L | LABOR Drawing
1l ea. | Remove salt line filter assembly. (6" pipe x (20 md) $ 2,000 49036
8'-0" long)
35442
1 job | Remove miscellaneous small gas system components. (50 md) $° 5,000 55443
- 55444
(FZ reactor, cold trap, F2 preheater, 302 pre-~ 55445
heater)
I
i
6 ea. | 55-gallon stainless steel drums. 600
1l ea. | Remove HF trap. (30 md) $ 3,000 55443
2 . e, | 55-gallon stainless steel drums, 200
1 ea, | Remove NAF absorber. (30 md) $ 3,000 55447
1 ea. | 55-gallon stainless steel drum. 100
1 job | Remove remaining miscellaneous supports, service (100 md) $ 10,000
lines, electrical trays, etc.
NET MATERIAL AND LABOR
CPFF | FIXED PRICE ORNL

FUEL-PROCESSING CELL

 

 

 

 

UCN-1297

1y 772

e

'y

 

6T
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY REMOVAL OF RADIOACTIVE MATERIAL UNIT COSTS MATERIAL LASOR Reference
UNIT MAT'L | LABOR Drawing
25 ea. | 55-gallon stainlesa steel drums. $2,500
1 job | Decontaminate interior of cell. (50 md) $ 5,000
1 ea. | Remove salt line penetration assembly to drain (30 md) $ 3,000
tank cell.
1 ea. | 55-gallon stainless steel drum. $ 100
1 job | Decontaminate salt line penetration sleeve to (10 md) $ 1,000
DT cell. -
1 job | Remove salt addition and transfer lines from east (10 md) $ 1,000
wall.
1 ea. | 55-gallon stainless steel drum. $ 100
1 job | Decontaminate salt line penetration sleeve (10 md) $ 1,000
through east wall.
NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL

. FUEL-PROCESSING CELL

 

 

 

 

 

UCN-12987
1 772}

€61
QUANTITY REMOVAL OF RADIQACTIVE MATERIAL UNIT COSTS MATERIAL erence
UNIT MAT'L | LABOR Dr

distillation iment from s . 100 md)

20 ea. |5 allon stainless steel drums.

1 job |Remove filters, iodine tr duct, and

from cell.

on stainless steel drums.

NET MATERIAL AND LABOR 12.200 91,600

CPFF FIXED PRICE

$103,800

FUEL-PROCESSING CELL

 

UCR-1297
3 770

6T
 

 

- Reference

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY REMOVAL OF RADIOACTIVE MATERIAL UNIT COSTS MATERI AL LABOR
uNIT MAT'L | LABOR Drawing
1 job | Remove ventilation house roof. (20 md) $ 2,000
. B=56252
1 job | Remove all equipment above floor level (off- (100 md) $ 10,000 E-56253
gas sampler instrument panels, piping valves,
etc.)
10 ea. | 55-gallon stainless steel drums. $1,000
1 job { Remove floor grating and dry stacked lead and (100 md) $ 10,000 E-40755
concrete shielding blocks fromroom. (V75 Yda,
2" x 4" x 8" lead brick and 6" x 8" x 12" con-
crete blocks)
1 ea. | Remove off-gas valve box with contents. {50 md) $ 5,000 E-40771
E=4UL 1Y
1 ea. | Remove charcoal bed valve box w/contents. (50 =d) $ 5,000 E-41852
E=48783
1 ea. | Remove off-gas particle trap assembly. (30 md) $ 3,000 E-48792
NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL

VENTILATION HOUSE AREA

 

 

 

 

 

UCN-1297
{3 7-72)

G61
196

-

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QUANTITY REMOVAL OF. RADIOACTIVE MATERIAL UNIT COSTS MATERIAL LABOR Reference
UNIT MAT'L | LABOR Drawing
1 job |Drain water from absorber pit. (10 md) $ 1,000
5 ea. | Remove absorbers; 1-A, 1-B, 2-A, 2-B, and 3-A. (50 md) $ 5,000 E-41519
5 ea. | Remove absorber support structure. (30 .md) $ 3,000 E-41519
S5 ea. | 55~gallon stainless steel drums.. 500
1 job | Remove remaining piping and TC leads from (30 md) $ 3,000 E-41519

charcoal absorber pit and penetration from

ventilation house.
2 ea. | 55-gallon stainless steel drums. 200
1l job | Clean and decontaminate charcoal absorber pit. (20 md) $ 2,000

(v8' OD x 25' deep)
2 ea. | Replace charcoal absorber pit roof plugs. (10' (10 md) $ 1,000

OD x 1'-6" thick)

NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL

VERTILATION HOUSE AREA

 

 

 

 

 

UCN-1297
3 7.72)

‘q“

L61
i'h
l‘“

QUANTITY REMOVAL OF RADIOACTIVE MATERIAL
UNIT

lace ventilation house roof.

VENTILATION HOUSE AREA

UCN-1297
iy 7.7

UNIT COS5TS
MAT L LABOR

NET MATERIAL AND LABOR

MATERIAL

2,900
CPFF

§79,900

 

erence
Draw

$ 77,000
FIXED PRICE

861
REMOVAL OF RADIOACTIVE MATERIAL

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY UNIT COSTS MATERIAL LABOR Rererence
UNIT MAT'L | LABOR Drawing
20 ea. | Remove special equipment room roof plugs. (20 md) $ 2,000
E=20417
2 ea. | Segment and remove component cooling air (100 md) $ 10,000 E-55413
- E-25414
enclosures. (5' OD x 10' high carbon steel) E-41472
20 ea. SS-gélion stainless steel drums. $2,000
2 ea. | Remove component cooling air blower motors. (30 md) $ 3,000 E-41472
(75 HP electric) i
2 ea. | Remove component cooling air blowers. (10 x (30 md) $ 3,000 E-41472
15 Roots type)
1 job | Segment and remove blower and motor support (20 md) $ 2,000 E-41472
structures.
4 ea. | 55-gallon stainless steel drums. $ 400
1 ea. | Remove component cooling alr heat exchanger. (30 md) $ 3,000
NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL

SPECTAL EQUIPMENT ROOM

 

 

 

 

 

UCN-1297

3 7-72)

66T
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY REMOVAL OF RADIOACTIVE MATERIALS UNIT COSTS MATERLAL LABOR Reference
UNIT MAT'L | LABOR Drawing
25 ft | Segment and package cell exhaust line in special (200 md) $ 20,000 E-41026
equipment room. (30" OD x 0.312 wall carbon steel)
10 ea. | 55~gallon stainless steel drums. ‘ $1,000
2 ea. | Remove pump bowl bubbler containment enclosures. (50 md) $ 5,000 E-55423
(24" OD x 36" long flanged heads, stainless steel)
2 ea. | 55-gallon stainless steel drums. $ 200
! E=55412
1 job | Remove miscellaneous auxiliary piping, valves, (100 md) 5 10,000 E-55413
E-55414"
and instruments (air, water oil, cover gas,
etc.).
25 ea. | 55-gallon stainless steel drums. $2,500
. E=55412
1 job| Remove electrical cables and cable trays. (50 md) $ 5,000 E-55413
E=55414%
NET MATERIAL AND LABOR
CPFF | FIXED PRICE QRNL -

SPECIAL EQUIPMENT RCOM

 

 

 

 

 

 

UCN-1297
-1

3

 

00¢
QUANTITY

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

REMOVAL OF RADIOACTIVE MATERIAL UN;T COSTS WATERTAT LABOR Keference
uNIT . MAT'L | LABOR Drawing
1 job | Demolish concrete wall, excavate and remove 30" (200 md) $ 20,000 E-41026

cell exhaust line from special equipment room to
service tunnel,
25 ft | Segment and packagé 30" cell exhaust line from (200 md) $ 2,000 E-41026
special equipment room to service tunnel. (30"
OD x 0.312 wall carbon steel)
10 ea, | 55-gallon stainless steel drums. $ 1,000 |
1 job | Repair cell walls. (5 yd> concrete) (50 md) $ 5,000 | E-41026
1 job | Clean and decontaminate special equipment room. (50 md) $ 5,000
20 ea. | Replace special equipment room roof plugs. {20 md) $ 2,000
NET MATERIAL AND LABOR $ 7,100 $115,000
CPFF FIXED PRICE ORNL
SPECIAL EQUIPMENT ROOM
'$122,100

 

 

 

 

UCH-1297
3 7712

T0¢
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY REMOVAL OF RADIOACTIVE MATERIAL UNIT COSTS MATERIAL LABOR Referénce
uNIT o MAT'L | LaBOR Drawing
21 ea. | Remove ceoolant cell penthouse roof plugs. (20 md) $ 2,000 E-40979
(1'-0" x 2'-0" x 18' long)
. . . M-1U353-KF-=
1 ea. | Remove coolant salt sampler assembly. . (20 md) $ 2,000 001-E
D=40%50
1l ea. | Remove radiator door lifting mechanism. (30 md) $ 3,000 D-40451
D=40452
1 job | Remove coolant pump auxiliary piping. (15 md) $ 1,500
{
T D=40%40—
1 job | Remove radiator top insulation. (30 md) $ 3,000 E-40470
, E=40471
| E-40472
E-40473
— E<40746
1 job | Remove radiator doors. '(20 md) “$ 2,000 E-55510
E-41515
1 job| Remove radiator door lifting and coolant pump (30 md) $ 3,000 E-41866
support structures.
1 job| Remove radiator and enclosure asgsembly. (100 md) $ 10,000 E-40470
NET MATERIAL AND LABOR '
CPFF FIXED PRICE ORNL
COOLANT CELL AREA
YCN-1297
3 11
. ' . '._,; ! : \',

o
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY REMOVAL OF RADIOACTIVE MATERIAL UNIT COSTS MATERIAL LABOR Reference
UNIT ‘ MAT'L | LABOR Drawing
-1 job | Remove radiator suppor.ts and radiator door tracks. (50 md) $ 5,000 E~55516
_ E=40702
1 job | Remove coolant salt drain lines. (20 md) $ 2,000 E-41860
' E-41861
E-41862
1 ea. | Remove coolant salt drain tank. (50 md) $ 5,000 E-40702"
37,500 Tt T T
lbs | Remove lead shielding from off-gas pipe chase. (100 md) $ 10,000 E-41893
(44" x 9" OD x 1" ID = 19.2 ft> + 40" lead brick .
2" thick = 26.7 £t°) -
I
" 44 ft | Segment and remove off-gas lines. (1 each (20 md) $ 2,000
1/4" ODT in 1/2" pipe; 1 each 1/2" pipe in 1"
pipe)
1 ea. | 55-gallon stainless steel drum. $ 100
S ea. | Remove off-gas line supports. (10 md) $ 1,000 E-41892
NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL
COOLANT CELL AREA

 

 

 

 

 

UCN-1297
(3 7T-72)

£0¢
QUANTITY REMOVAL ‘OF RADIOACTIVE MATERIAL - s ATERTAC —Fanca
UNIT MAT'L | LABOR Dr

$ 40,000

    

E~41893
area (water, oil
20 ea. | 55- on stainless steel drums.
1 job | Clean and decontaminate coolant cell area. (100 md) . $ 10,000
NET MATERIAL AND LABOR 4600 111.500
CPFF FIXED PRICE ORNL

COOLANT CELL AREA
$116,100

UCN-1297
3 772

707
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY REMOVAL OF RADIOACTIVE MATERIAL UNIT COSTS MATERIAL LABOR Reference
uNIT ' - MAT'L | LABOR ' Drawing -
100 ft | Remove lube o1l and water piping from reactor (20 wmd) $ 2,000 E-40735
céll to service tunnel penetration.
: . E-55411
100 ft | Remove lube o0il and water piping from special . (20 md) $ 2,000 E-55414
equipment room to service tunnel penetration.
2 ea. | Remove reactor cell exhaust line valves. (30" (30 md) $ 3,000 D-41026
butterfly w/operators)
3 - - D-41026
75 yd~ | Machine excavate w/shoring 30" exhaust line from (100 md) $3,000 $ 10,000 D-41027
: : D-41028
special equipment room to service tunnel (%20’ - '
deep).
2 yd~ | Demolish reinforced concrete service tunnel wall (10 md) $ 1,000 D-41028
at 30" exhaust line penetration.
18 ft Segment and remove.30" exhaust line from special (200 md) $ 20,000 D-41027
equipment room to service tunnel. (30" OD x
0.312 wall carbon steel)
NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL
SOUTH YARD
UCN-1297

(3  7-72}

60¢
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY REMOVAL OF RADICACTIVE MATERIAL UNIT COSTS MATERIAL LABOR Reference
wIT MAT'L | LABOR ' Drawing
8 ea. | 55-gallon stainless steel drums. $ 800

75 yd3 Machine excavate w/shoring 30" exhaust line from (100 md) $3,000 $ 10,000 D-41028

service tunnel to stack filter (~n20' deep).
3 D-41027
1 yd~ | Demolish reinforced concrete wall of service (5 md) $ 500 D-41028
tunnel at 30" line penetration. _
50 ft | Segment and remove 30" exhaust line from service (500 md) ; ' $ 50,000 D-41028
tunnel to stack filters. (30" OD x 0.312 wall
!
carbon steel) N
|
|
——— i
i
20 ea. | 55-gallon stainless steel drums. $2,000 |
{
1 job| Check and remove all contaminated soil from (50 md) $ 5,000
excavated area.
NET MATERIAL AND LABOR
CPFF FIXED PRICE - ORNL
SOUTH YARD s - e e e — —_—
UCH-1297 =Tl e
i3 7-72)

90¢
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY REMOVAL OF RADIOACTIVE MATERIAL UNIT COSTS MATERIAL LABOR Reference
UNIT . MAT'L | LABOR Drawing
. D-41026
1 job | Form and pour concrete at special equipment room D-41028
. wall,'and two walls of service tunnel.
Labor (20 md) $ 2,000
.Material: 3 ydsg concrete form material $ 500
150 yd3 Backfill excavation from tunnel area (10 md) $1,500 $ 1,000.
w/stabilized f1ll to existing grade level. .
, - D-41071
1 job | Remove and decontaminate inlet manifold to stack (50 md) 1§ 5,000 D-41072
filter bays.
- D-41071
3 ea. | Remove and decontaminate stack filter inlet (20 md) $ 2,000 D=41072
dampers. (24" x 18™)
31 ea. | Remove and decontaminate stack filter pit roof (50 md) $ 5,000 D-41117
plugs.
105 ea. | Remove prefilters, decontaminate frames and (50 md) $ 5,000 D-41075
- replace filter media.
NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL
SOUTH YARD
UCH-1297

3y 7-72)

 

. oA

L02
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY REMOVAL™OF RADIOACTIVE MATERIAL UNIT COSTS - MATERIAL LABOR Reference
UNIT MAT'L | LABOR Drawing
6 ea. | Remove final filters, decontaminate frames and (50 md) s 5,000 D-41076
replace filters.
D-41117
1 job | Decontgminate interior of filter pit. Flush (30 md) $ 3,000 D-41273
solutions to the Laboratory ILW system thru
existing drain lines.
(uce- | —
6 ea. | Replace final filters. (30 md) $2,000 ND) [$ 3,000 . D-41076
i
(uce-
105 ea. | Replace prefilters. (50 md) $2,000 ND) ;$ 5,000 D-41075
31 ea. | Replace and seal filter pit roof plugs. (30 md) $ 500 $ 3,000 D-41117
3 ea. | Replace filter inlet dampers. (20 md) $ 2,000 D-41071
1 ea. | Replace filter inlet manifold. (30 md) $ 3,000 D-41072
NET MATERIAL AND L ABOR
CPFF FIXED PRICE ORNL
SOUTH YARD [ o I -
UCN-1297 - =
s 772
Ilg _',tl_- ' .";‘lQ‘ | ..

80¢
If? Tih ! . t - "-\.l.il- |

 

QUANTITY | REMOVAL OF RADIOCACTIVE MATERIAL UNIT COSTS MATER) AL erence

UNIT MAT'L | LABOR Dr

inst fixture D-41071
D-41
exhaust line was
Des $ 1,800 (Uc¢-ND)

Fab t ‘ : 500 ND) 3,200 -ND)

Ingstallation 2,000

G&A on material: 4,500 x 0.35 ° ' 51,600

UCC-ND Subtotals $6,100 $ 5,000
NET MATERIAL AND LABOR |4171 300 149500

CPFF FIXED PRICE ORNL

SOUTH YARD

$160,800 o $11,100

UCN-1297
{3 7-72)

60¢
 

 

 

 

 

 

 

 

 

 

 

 

 

 

0T?

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY | - REMOVAL' OF RADIOACTIVE MATERIAL UMIT cOSTS MATERTAL LABOR “Refeéfence
UNIT MAT'L | LABOR Drawing
2 ea. | Remove treated water storage tanks. (10 md) $ 1,000 ) D-41252
2 ea. | Remove treated water pumps (20 hp). (20 md) $ 2,000 D-41252
1 lot | Remove piping, valves, instruments, etc., from (50 md) $ 5,000 D-41252
water room.
1 lot | Remove piping and valves from radiator tunmnel. (30 md) - $ 3,000 D-41252
1 job | Remove thermal shield gas separation system from (30 md) $ 3,000
1
fan house. ) ) N
100 yd3 Machine  excavate underground 4" and 6" lines to (20 md) | $ 2,000
diesel shed. l
250 ft | Remove 4'" and 6" lines from water room to diesel (20 md) $ 2,000 D-41254
shed.
1 ea. | Remove treated water filter from diesel shed. (10 md) $ 1,000 D-41254
NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL
TREATED-WATER SYSTEM
_ .

UCN-1297
3 772
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

" quanTITY REMOVAL OF RADIOACTIVE MATERIAL UNIT COSTS MATERIAL CABOR Keféerence
UNIT MAT'L | LABOR Drawing
2 ea. | Remove treated water heat exchangers from diesel (30 md) $ 3,000 - D-41254
shed.
n150 ft | Remove piping and valves from diesel shed. (4" (30 md) $ 3,000 D-41254
and 6" carbon steel)
2 ea. | Remove steam dome heat exchangers from west (20 md) $ 2,000
tunnel.
2 ea. | Remove steam dome surge tanks from west tunnel. (20 md) $ 2,000
1 lot | Remove piping and valves from west tunnel. (30 md) $ 3,000
1 job | Decontaminate west tunnel. (30 md) $ 3,000
1 job | Decontaminate water room. (30 md) $ 3,000
"1 job | Decontaminate diesel shed. (10 md) $ 1,000
NET MATERIAL AND LABOR
' CPFF FIXED PRICE ORNL

TREATED-WATER SYSTEM

 

 

 

 

 

UCN-1297-

3 T-72)

T1¢
QUANTITY REMOVAL OF RADIOACTIVE MATERIAL ST costs MATERTAL
uniT ! MAT'L LABOR

3

100 yd Backfill west yard between water room and diesel 1,000

shed to exist ade.

Dr

erence

  

 

 

 

 

 

 

NET MATERIAL AND LABOR 1.000 19 500
CPFF FIXED PRICE
TREATED-WATER SYSTEM -
$40,500
UCN-1297
3 T-72)
'.g ('.J‘- \ '.,.." .

 

cic¢
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QL,ANT,TY REMOVAL OF RADIOACTIVE MATERIAL UNIT COSTS MATERI AL LABOR Reterence
UNIT MAT'L | LABOR Drawing
1 ea. | Disconnect and remove distillation experiment (25 md) $ 2,300

valve box,
1 job | Remove roof plugs and set up temporary work (50 md) $ 5,000
shielding. ] ~
1 job kemotely disconnect all lines from distillation (30 md) o $ 3,000
experiment. _ .
1 ea. | Remove distillation experiment assembly to (200 md) $ 20,000
transport-storage shield. ]
. ] -
1 job | Remove temporary work shielding. Install (50 md) 1% 5,000
ladders.
. _ ‘ 49026
2 ea. | Remove fuel process system charcoal traps. (10 md) $ 1,000 E-55454
1 ea. | Remove fuel process ventilation filters. (20 md) $ 2,000 E-55454
NET MATERIAL AND LABOR
"CPFF FIXED PRICE ORNL

SPARE CELL AREA

 

 

 

 

 

UCN-1297
(3 7.72)

£1¢
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY REMOVAL OF RADIOACTIVE MATERIAL UNIT COSTS MATER] AL LABOR Reference
UNIT MAT'L | LABOR Drawing
1l ea. | Remove fuel process soda lime trap. (20 md) $ 2,000 E-55454

E-55454
1 lot | Remove miscellaneous piping, supports, etc. (50 md) $ 5,000 E-55456
T 200 Remove dry stacked block from west wall. (25 md) $ 2,500
1l job | Decontaminate cell, (30 md) $__‘_3,000
1 job | Replace roof plugs (10 md) % 1,000
; |
_ — T :
| |
| i
— |
|
NET MATERIAL AND LABOR ' $ 52,000
CPFF FIXED PRICE ORNL
SPARE CELL AREA _
$52,000 i _

 

 

 

UCN-1297
3 7-72)

 

 

-~
.

.
‘A
e Ve

v1Z
215

APPENDIX B

JOB LISTING FOR

DECOMMISSIONING THE MSRE BY ENTOMBMENT
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY ENTOMBMENT OF RADIOACTIVE MATERIAL L_-INIT COSTS MATERIAL LABOR Reference
UNIT MAT'L | LABOR Drawing
1 ea.|Design and fabricate flushing system unit with 50 gpm

flow and 500 gallons storage of decontamination solution
wifh connections for discharging solution to the ORNL ILW
system. Unit to be portable and shielded for use at
various areas 1in the reactor, drain tank, and fuel
processing cell.
Design ‘ (100 md) $ 18,300
Material $10,000
Fabrication (100 md) 15,600
6 jobs Connect and flush various sections of the system and
tanks.
6 ea., @ 50 md (300 md) $ 46,800
G&A on materials: 10,000 x 0.35 $ 3,500
$13,500 $ 80,700
NET MATERIAL AND L ABOR
CPFF FIXED PRICE ORNL
PREPARATORY WORK - FLUSHING
$ 94,200
UCN-1297
(3 772
".14'\ IJ' vy - ". .’. P :-

9T¢
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY ENTOMBMENT OF RADIOACTIVE MATERIAL oMIT cosTs MATERTAL TABOR Reference
uNIT MAT'L | LABOR Drawing
1 job| Design, f;bricate and ingtall a temporary cell ventilation

duct and shiélded filter box from the top of the reactor
cell to existing'duct work at the east side of the high
bay. _
De.sifin (70 md) s' 12,800
Materials $10,000
Fabrication & Installation (75 nd) 7.500
1 job| Design, fabricate and install a temporary cell ventilation -
duct and shielded filter box from the top of the drain
tank cell to existing duct work at the east side of the
high bay.
Design (70 md) $ 12,800
Materials. $10,500
Fabrication & Installation (75 md) 7.500
NET MATERIAL AND LABOR $20,000 $ 15,000
CPFAF FEXED PRICE ORNL
PREPARATORY WORK - CELL VENTILATION
$35,000 $ 25,600

 

 

 

 

UCN-1297
3 771

LT1¢
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY ENTOMBMENT OF RADIOACTIVE MATERIAL UNIT COSTS MATERIAL Canon Relerence
uNIT MAT'L | LABOR Drawing
1 ea.|Design, fabricate and install a work platform to fit the

top of the reactor cell. The platform is to have remov-

able deck sectlons for access to all work areas of the

cell; contain tool securing devices; and lighting and

other visual ailds necessary for remote work.
Design (100 md) $ 18,300 (QRNL)
Materials $10,000
Fabrication & Installation (200 md) 20,000

1l ea.| Design, fabricate and install a work platform to fit the

top of the drain tank cell. The platform is to have

removable deck sections for access to all areas of the }

. B T
cell; contain tool handling and securing devices; and !
lighting and other visual aids necessary for remote work.

Design (100 md) $ 18,300 (QRNL)
Materials $10,000
Fabrication & Installation (200 md) 20,000
NET MATERIAL AND LABOR $20,000 $ 40,000
CPFF FIXED PRICE ORNL
PREPARATORY WORK - WORK PLATFORMS
$60,000 $ 36,600
UCN-1297
3 7-72})

8TC
QUANTITY ENTOMBMENT OF RADIOACTIVE MATERIAL _ : MATERTAL

UNIT

   
  

1 lot|Contamination control t:
Hoses for fl tools and items.
for removing wash Qater from cell.
Miscellaneous plastic sheeting, blotter paper,

etc.

G&A on materials: 6,200 x 0.35

NET MATERIAL AND LABOR
FIXED PRICE
PREPARATORY WORK — MISCELLANEOUS MATERIAL

UCN-1297
3  7-72}

Dr

rence

ORNL

$ 6,900

6T¢
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY ENTOMBMENT OF RADIOACTIVE MATERIAL UNIT COSTS MATERIAL T LABOR Reference
UNIT - MAT'L | LABOR Drawing
1 ea.|Pipe cutter, abrasive, for horizontal 5" INOR-8 pipe.

Design (50 md) _ $ 9,200
Fabrication Labor (50 md) 7,800
Materials $ 2,500
Mockup & Development (50 md) 500 7,800
S
1 ea.| Pipe cutter, abrasive, for vertical 5" INOR-8 pipe. !

Design (50 md) $ 9,200
Fabrication (50 md) 7,800
Materials { $ 2,500

— -
Mockup & Development ] (50 md) i 500 7,800

|
1 ea.| Pipe cutters, hydraulic, for vertical or horizontal 1/2"
thru 2" carbon steel, stainless steel and INOR-8 pipe
(commercial hydraulic shears).
Design (50 md) $ 9,200
Fabrication (30 md) 4,700
Material $ 2,500
Mockup & Development (50 mq) 500 7,800
' NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL
TOOLING
UCN-1297
3 71-72)

 

0ce¢
QUANTITY

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

ENTOMBMENT OF RADIOACTIVE MATERTAL UNIT COSTS MATERTAL LABOR Reference
UNIT MAT'L | LagoR Drawing
2 ea.|Cutters, hydraulic, for miscellaneous 1/4" to 1/2" tubing, .
MI cable, electrical leads, etc. (commercial hydraulic
units).
Design (50 md) $ 9,200
Fabrication (30 md) 4,700
T J
Material @ $500 each $ 1,000
Mockup & Development (50 md) 500 7,800
2 ea.| Snips, manual, for cutlting thermocouple leads, electrical
leads, etc.
Design (30 md) $ 5,500
Fabrication (30 md) 4,700 i
, i
Material $ 500 i
Mockup & Development ‘ | (10 md) 100 1,600 |
NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL
TOOLING -
ol ]
UCH-1297

3 772

1¢?
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY ENTOMBMENT -OF RADIOACTIVE MATERIAL UNIT COSTS © MATERIAL LABOR Reference
unIT MAT'L | LABOR Drawing
2 ea.| Cutters, torch, acetylene, for cutting horizontal carbon

steel support structures.
Design (30 wd) $ 5,500
Fabrication (30 md) 4,700
Material @ $500 each $ i,OOO
Mockup & Development (50 md) 500 7,800
2 ea.| Cutters, torch, acetylene for cutting vertical carbon
steel support structures. _ _
Design (30 md) $ 5,500
Fabrication o (30 md) 4,700
Material @ $500 each ' $ 1,000
Mockup & Development (50 md) 500 7,800
1l ea. Tool; 1ifting, for handling fuel pump motor.
Design (existing)
Fabrication (30 md) $§ 4,700
Material $ 506
NET MATERIAL AND L ABOR
TOOLING CPFF FIXED PRICE ORNL
i
o o

¢ce
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY ENTOMBMENT OF RADIOACTIVE MATERIAL U-NIT COSTS MATERI AL LABOR Referenée
uNIT MAT'L | LABOR Drawing
1 ea.|Tool, lifting, for removal of fuel pump rotary element.

Design (existing)
Fabrication (30 md) $ 4,700
Material $ 500
1 ea.| Tool, lifting, for handling fuel pump bowl.
.Design (existing) E-56336
Fabrication (50 md) $ 7,800
Material $ 1,000
1 ea.| Tool, lifting, for handling fuel heat exchanger. !
Design (existing) | E-56340
Fabrication (75 md) $ 11,700 !
Material $ 1,500
1 ea. Tool, lifting, for removal of drain tank steam domes.
Design (existing) D-56339
Fabrication (30 md) $ 4,700
" Material $ 500
NET MATERIAL AND LABOR
. CPFF FIXED PRICE ORNL
TOOLING
UCN-1297

3 712y

€z
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY ENTOMBMENT OF RADIOACTIVE MATERTAL e ATERTAL Treon Reference
uNT MAT'L | LABOR Drawing
1 ea.|{ Tool, 1lifting, for removal of fuel drain tanks.
Design (existing) D-56338
Fabrication (50 md) $ 7,800
Material $ 1,000

2 ea.  Tool, 1lifting, for removal of heater units.
Design (existing)
Fabrication (36 md) $ 4,700
Material _ § 500

1l ea.| Tool, 1lifting, for removal of cell coolers. L
Design (existing)
Fabrication (20 md) $ 3,100
Material $ 1,000

1 -ea. Tool, lifting, for removal of fuel storage tank.
Design (30 ‘md) $ 5,500
Fabrication t50 md) 7,800
Material $ 1,000

NET MATERIAL AND LABOR
TOOLING CPFF FIXED PRICE ORNL
R

%2¢
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY ENTOMBMENT OF RADIOACTIVE MATERIAL UNIT COSTS WATERTAC LABOR Reference
UNIT : ' . MAT'L | LABOR Drawing
3 ea.|Tool, lifting and handling, various lengths, for removal -

of segments of large piping (3" to 6").
Design ' | (50 md) $ 9,200
Fabrication (25 md) -3,900
Material - 500
3 ea.{Tool, lifting and handling, various lengths, for removal
of segments of small piping (1/4" to 2"),
Design (SO_md) 1§ 9,200 L
Fabrication (25 md) ‘I 3,900
Material 500 i
3 ea. To§1, lifting and handling, various lengths, for removal
of segments of structural components.
Design (50 md) $ 9,200
Fabrication (25 md) 3,900
Material $ 500
NET MATERIAL AND LABOR
. CPFF FIXED PRICE ORNL
TOOLING -
UCN-1297

3 77

sze
 

 

 

 

 

 

 

 

 

 

 

 

 

 

9¢7

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY ENTOMBMENT-OF RADIOACTIVE MATERTAL ' UNIT COSTS MATERIAL CABGR Reference
UNIT MAT'L | LABOR : Drawing
1 ea. Toocl, 1lifting, for removal of NaF absorber.

Design (20 md) $ 3,700
Fabrication . (20 rl‘ld) ' 3,100
Material _ $ 200
1 lot Long.handled hooks, tongs, socket wrench extensions, i
chisels, punches, saws, drills, hammers, etc., designed |
for general and special applications (~100 tools).
Design (300 md) 1§ 55,000
) Fabrication (300 md) 46,800
Material ) $ 5,000 | |
1 lot Miscéllanéous visual aid's; -1.e., lights, binoculars, .$10,000
periscopes, etc.
NET MATERIAL AND LABOR
TOOLING CPFF FIXED PRICE ORNL
A
-

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITS ENTOMBMENT OF RADIOACTIVE MATERIAL UNIT COSTS MATERI AL LABOR Reference
uNIT , MAT'L | LABOR Drawing
6 ea.| Drums, 55-gallon w/bails and dumping levers, for trans-

ferring material from all areas to reactor cell.
Design ' (20 md)| $ 3,700
Fabrication - . (30 md) 4,700
Material @ $150- each $ 900
1 lot| Miscellaneous concrete pouring and compacting equipment; $ 5,000
i.e., buckets, vibrators, chutes, etc.
1
|
G&A on materials: 44,200 x 0.35 $15,500
NET MATERIAL AND LABOR $59,700 $359,600
CPFF FIXED PRICE ORNL
TOOLING -
$419,300
UCN-1297.

3 7-72)

L2¢
ENTOMBMENT OF RADIOACTIVE MATERIAL

 

 

_LABOR

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY UNIT COSTS MATERI AL Kererence
UNIT MAT'L | LABOR Drawing
50 ea.| Remove top shield beam holddown nuts and studs. (20 md) $ 2,000 D-40955

(2-1/4" 0D x 4'-0" long)
15 ea., Remove tofi beams to outside storage. (30 md) $ 3,000 D-40951
2 each 2'-0" x 3'-6" x 15'-0" long
2 each 2'-0" x long
2 each 2'-0" x long
2 each 2'-0" x long
7 each 2'-0" x long
D=-40972
1 ea.| Remove seal membrane; section and package for (40 md) $ 4,000 D-40973
‘ D-40974
disposal into cell. (24'-6" 0D x 1/8" thick
stainless steel) L
28 ea.| Remove lower roof plugs steel crack fillers. (20 md) $ 2,000 D~40954
1 joH Remove reactor access lower plug and set up dry (10 md) $ 1,000 D-40954
maintenance shield over core vessel.
NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL

REACTOR CELL

 

 

 

 

 

UCN-1297
3 T-72)

..’ 1, .
s v‘* " .

8¢¢
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY ENTOMBMENT OF RADIOACTIVE MATERIAL UNIT COSTS MATERIAL LABOR Reference
UNIT MAT'L | LABOR Drawing
1 ea.| Remove core access flange and -source tube plugs (10 md) $ 1,000 E~40954

from thermal shield 1id.
1 job! Pump grout into coré, filling to core access E-40400
flange elevation.
Labor (20. md) $ 2,000
Material: 2 yd3 grout 100
E-4U727
1 job| Pump grout through existing penetrations through E-40730
thermal shield 1id filling the annulus between
the core vessel énd thermal shield.
Labor (30 md) _ $ 3,000
Material: 15 yd3 grout 700
1 jobl Remove roof plugs and set up maintenance shield (10 md) $ 1,000 D-40951
over the primary heat exchanger.
NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL

REACTOR CELL

 

 

 

 

 

 

UCN-1297
3 772}

6C¢
 

 

MATER!AL

LABOR

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY ENTOMBMENT OF RADIOACTIVE MATERIAL UNIT COSTS Reference
MAT'L LABOR Drawing
1 job| Cut opening and f11ll heat exchanger shell with D-40873
grout.
Labor © (20 md) $ 2,000
Material: 2 yd3'grout 100
1 job| Cut heat exchanger loose and lower to floor of (50 nd) $ 5,000 D-40873
cell. (4 cuts of 5" INOR-8 pipe and support
‘structures)
E=40700—
1 jobl Collapse all support structures and auxiliary (200 md) $ 20,000 E-40704
equipment in the heat exchangér area to the
cell floor.
1 jobl Set up maintenance shield over the fuel cir- (10 md) $ '1,00b D-40951
culating pump.
1 job| Remove fuel pump motor and rotary element and (50 md) $ 5,006 F-9700
lower to cell floor.
NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL
REACTOR CELL
UCN-1297
7.72)

0e?C
ENTOMBMENT OF RADIOACTIVE MATERIAL

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY GRIT COSTS TMATERIAL CABOR Reference
UNIT MAT'L | LABOR Drawing
1 job Pump fuel pump bowl full of grout. F-9700

Labor (20 md) $ 2,000
Material: i yd? grout 100
1 jolj Cut fuel pump bowl loose and lower to cell (100 md) $ 10,000 F-9700
floor.
1 jol Connect existing nozzle on fuel pump overflow E-56418
tank and pump full of grout.
Labor (30 md) $ 3.000
Material: 1 yd3 grout | 100 -
_ E-51604
1 jol Remove fuel pump furnace and lower to floor of (50 md) $ 5,000 E-51606
cell.
E-40700
1 joY Collapse all support and auxiliary materials in (300 md) $ 30,000 E-40704
the fuel pump area to the cell floor.
NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL

REACTOR CELL

 

 

 

 

 

UCN-1297.
3 7-72)

1ee
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY ENTOMBMENT OF RADIOACTIVE MATERIAL UNIT COSTS MATERIAL LABOR Reference
UNIT MAT'L | LaBOR Drawing
E-40700
1 jobl Collapse all support and auxiliary equipment at (200 md) $ 20,000 E-40704
area east of thermal shield.
E-40700
1 job! Collapse all support and auxiliary equipment at (200 md) $ 20,000 E-40704
area west of thermal shield.
1 job Flush cell walls and thermal shield to bottom of (10 md) ) $ 1,000
cell.
1 jobl Cut and remove section of cell exhaust line in (30 md) $ 3,000 D-41026
coolant cell at cell penetration to reactor cell. __
| Transfer removed section to reactor cell.
1 job| Fabricate and install blanking flange -w/nozzle
onto 30" cell exhaust penetration.
Labor (30 md) $ 3,000
Material 500
NET MATERIAL AND LABOR
. CPFF FIXED PRICE ORMNL
REACTOR CELL
UCN-1297
{3 7-72)
' ' #* ‘l Pl ll “r -’. .. ; 'I'

¢t
QUANTITY
UNIT

ENTOMBMENT OF RADIOACTIVE MATERIAL

 

UNIT COSTS

 

MAT L LABOR

MATERIAL

LABOR

Keterence .
Drawing

 

 

1 job

 

Attach hose and pump 30" cell exhaust penetra-

tion full of grout.

 

Labor

(20 md)

$ 2,000

 

Material: 35 yd3 grout

$ 300

 

 

1 job

Clear entrance to penetration from reactor cell

$ 20,000

 

to drain tank cell, Remotely install blanking

(200 md)

 

fixture at reactor cell opening.

 

 

1 job

Pour concrete into cell to an elevation of

 

6 ft above equipment support platform..

 

 

Labor

(30 md)

$ 3,000

 

Material: 350 yd3 concrete

$ 2,000

 

 

1l ea.

Remove component cooling air heat exchanger

E-41472

 

from gspecial equipment room. Fill shell with

 

grout and transfer to reactor cell,

 

Labor

(25 md)

$ 2,500

 

-Material: 1 yd3 grout

 

 

$ 100

 

 

NET MATERIAL AND LABOR

 

REACTOR CELL

CPFF

FIXED PRICE

ORNL

 

 

 

 

 

 

UCN-1297
3 7.7

£ee
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY ENTOMBMENT OF RADIOACTIVE MATERIAL UNIT COSTS MATERIAL LABOR Reference
UNIT MAT'L | LABOR Drawing
1 job| Fabricate and install flafige w/gfout nozzle onto ; E-41472

component cooling air penetration. Pump penetra- |
tion full of grout.
Labor (30 md) $ ,3;000
Material: 1 yd3 grout 100
Other 500
I E-55428 —
20 ea.| Cut auxiliary lines penetrating south wall of E-56377
cell, pump full of grout and cap off. (water, |
air, gas, etc., 1/4" to 3" size) | -
Labor (50 md) L _jfi$ 5,000
Material: 2 yd3 grout 100
Other 500
1 joH Pump interior cofipartments of sampler enrichér EJN-10301
full of grout through existing nozzles.
Labor (20 md) $ 2,000
Materials: 2 yd3 grout 100
NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL

REACTOR CELL

 

 

 

 

 

UCN-1297
3 7-72)

VAXA
ENTOMBMENT OF RADIOACTIVE MATERIAL

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY UNIT COSTS MATERIAL LABOR Kelerence
UNIT MAT'L | LABOR Drawing
1 job|Remove sampler-enricher assembly to reactor cell. (50 md) $ 5,000 EJN-10301
1 job|Remove sampler-enricher floor flange and cell (20 md) $ 2,000 E-55479

penetration to reactor cell.
1 jobj Cut auxiliary lines penetrating north wall at the E-41863
north electric service room area and pump lines
full of grout and seal ends.
Labor ! (100 md) $ 10,000
Material: 5 yd3 grout 300
Other _ 500
1 job| Cut auxiliary lines penetrating the west wall at
the west tunnel area and pump lines full of grout
and seal ends.
Labor (50 md) $. 5,000
Material: 1 yd3 grout 100
Other 500
NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL

REACTOR CELL

 

 

 

 

 

 

UCN-1297
iy 7-72)

Gee
 

QUANTITY
UNIT

ENTOMBMENT OF RADIQACTIVE MATERTIAL

 

UNIT COSTS

 

MAT'L LABOR

MATERIAL

LABOR

Relerence
Drawing

 

 

Continue pouring and vibra-packing concrete into

 

cell as other items from drain tank cell and fuel

 

processing cell are moved in. Pour to bottom

 

 

elevation of lower roof plugs.

Labor

(300 md)

| $ 30,000

 

$10,000

 

Material: ~250 yd3 concrete

 

 

1 job

Cut access door(s) into cell annulus from

(500 md)

$ 50,000

 

coolant drain tank cell. Remove magnetite sand

 

from annulus to burial ground. (%400 yd3 sand;

 

hand load and machine convey out of coolant

 

drain cell)

 

 

1 joH

Core drill through annulus ring at top of cell,

$ 6,000

$ 6,000

E-40974

 

4 places 12" .diameter. Seal openings at coolant

 

drain cell and f111 annulus with concrete.

 

(400 yd3 concrete)

 

 

 

 

 

 

NET MATERIAL AND LABOR

 

- REACTOR CELL

CPFF

FIXED PRICE

ORNL

 

 

 

 

 

UCN-1297
{3 7-72)

9¢?¢
QUANTITY

o ENTOMBMENT OF RADIOACTIVE MATERIAL » T MATERIAL

LABOR

   
 
  
 
 

1 job|Replace all lower roof shield plugs over cell and
grout in place. Finish floor smooth to existing
high bay elevation.

Labor

Material: 10 yd3 grout

NET MATERIAL AND LABOR | $23.200 | $299,500

CPFF FIXED PRICE

$322,700

REACTOR CELL

UCN-1297
{3 7.1

Reference

E-40951

ORNL

LET
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

OUANTITY ENTOMBMENT OF RADTOACTIVE MATERIAL o coors MATERTAL | CABoR I~ Reference
unIT MAT'L | LABOR’ ' ! Drawing
I .
82 ea.| Remove steel holddown keys from upper shield plugs. (5 md) $ 500 E-40946
E-40933
10 ea.| Remove upper shield plugs. (25 md) $ 2,500 E-40946
10 ea.| Decontaminate upper shield plugs and store for (50 md) N $ 5,000 i
i
future use. I
1 ea.| Remove seal membrane from cell, section and (20 md) $ 2,000 E-40933
transfer to reactor cell, _ ] L
28 ea.| Remove steel shield plates from between lower (10 md) % 1,000 [ g 40939
T
b
plugs. . |
!
, |
28 ea.| Decontaminate shield plates for future use. (10 md) $ 1,000
E=4U9%33
12 ea.| Remove lower roof plugs from north bay. (10 md) $ 1,000 E-40946
12 ea. Decontaminate plugs for future use. (50 md) $ 5,000
NET MATERIAL AND LABOR
CPEF FIXED PRICE ORNL
DRAIN-TANK CELL

 

 

 

 

UCN-1297
3 712

8BET
 

ENTOMBMENT OF RADIOACTIVE MATERIAL | T conTs

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY “TWMATERIAL LABOR .Reference
UNIT MAT'L | LABOR Drawing
1 ea.| Remove north shield plug support beam. (1 md) - $ 100 E~40944
1 ea.| Decontaminate support beam for futufe use. (2 md) $ 200
1 job Install work platform w/vent control panels. (10 md) $ 1,000
E-41512
2 ea.| Remove pneumatic valves and transfer to reactor (10 md) $ 1,000 E-41513
cell. (HCV~544 and -573)
2 ea. Remove valve supports. (6 md) 8 600 E-41877
- E-40708
1 joY Remove all miscellanmeous auxiliary piping, (200 md) $ 20,000 E-40709
- E-40878 —
thermocouple loads, heater leads, etc., from E-41512
‘ E-41513—
the north bay area to the reactor cell. E~55404
E-55405
E-55406
; _ E-404563
1 ea) Remove FDT-1 steam dome assembly to reactor cell. (20 md) $ 2.000 E-40708
: E-40731
E=3/749U.
5 eal Remove heaters from line 106 to reactor cell. (5 md) $ 500 MIC-G-116
) NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL

DRAIN-TANK CELL

 

 

 

 

 

UCN-1297
3 772y

6¢¢
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY ENTOMBMENT OF RADIOACTIVE MATERIAL TR oooTe WMATERTAC Casor Reference
UNIT ‘ - | mAT'L | LABOR Drawing
1 ea.|Remove FV-106 (1-1/2" INOR-8) to reactor cell, (10 md) $ 1,000

w15 ft | Remove line 106 to reactor cell, (1-1/2" INOR-8) (10 md) $ 1,000
8 ea.|Remove line 106 heater base insulation units to (10 md) $ 1,000 MIC~G~117

reactor cell.
1 jobj Remove line 106 heater base support structure to (20 md) $ 2,000 E-55504
reactor cell,
7 ea.| Remove FDT-1 heaters to reactor cell. (30 md) $ 3,000 E-51686
1 ea.| Remove disconnect support ring from FDT-1. (10 md) $ 1,000
1 ea.| Remove FDT-1 furnace 1id to reactor cell. (20 md) $ 2.000 E-51686
1 ea.| Remove FDT-1 to reactor cell. (20 md) $ 2.000
NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL

.DRAIN-TANK CELL

 

 

 

 

 

" UCN-1297
3 7-72)

o%¢
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY ENTOMBMENT OF RADIOACTIVE MATERIAL UNIT COSTS MATERIAL LABOR Reference
uNIT MAT'L | LABOR Drawing
1 jobl Emplace FDT-1 in reactor cell and pump tank full

of concrete.
Labor (20 md) $ 2,000
Material: 3 yd3 concrete $ 200
1 job Replace steam dome into FDT-1l and fill steam dome
with concrete. L
Labor (20 md) $ 2,000
Material: 1 yd3 concrete
2 ea, Remove. drain tank weigh cells to reactor cell, (10 md) $ 1,000 E-41500
1 joY Segment and remove drain tank furnace to reactor (50 md) $ 5,000 | E-51686
cell,
2 eaJ Remove drain tank supports to reactor cell. (20 md) $ 2,000 E-41500
NET MATERIAL AND LABOR
CPFF FIXED PRICE~ ORNL

DRAIN-TANK CELL

 

 

 

 

 

UCN-1297
772

%
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY ENTOMBMENT OF RADIOACTIVE MATERIAL UNIT COSTS MATERIAL LABOR ReTerence
UNIT MAT'L | LABOR Drawing
- .- E<41512
1 job| Remove transfer:'line #109 to reactor cell. (20 md) $ 2,000 E-41513
(~15 ft, 1/2" Sch 40 INOR-8 w/Calrod heaters
and insulation attached)
. : E=415172
1 job| Remove transfer line #110 from FDI-1 to north (20 md) $ 2,000 E~41513
wall, (~10 ft, 1/2" Sch 40 INOR-8 w/Calrod
heaters and insulation attached)
1l ea.| Remove FV-109 to reactor cell. (10 md)  $ 1,000 E-55509
! !
1 jobl Clean up remaining miscellaneous support clips, {25 md) I'§$ 2,500 !
lines, cables, etc., and move to reactor cell. l
1 ea.| Replace north shield plug support beam. (1 md) $ 100
12 ea.| Replace lower shield plugs in north bay. (10 md) $ 1,000
9 ea.| Remove lower shield plugs from center bay. (10 md) $ 1,000 E-40933
NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL
DRAIN-TANK CELL
UCN-1297
3 72
l“: .-lii'\ i 4o I- r‘t ‘. l"

e
 

 

 

 

 

 

 

 

QUANTITY ENTOMBMENT OF RADIOACTIVE MATERIAL UNIT cosTs MATERI AL LABOR Reference
UNIT o MAT'L | LABOR Drawing
9 ea.| Decontaminate lower shield plugs for future use. (50 md) $ 5,000
1 job; Install work platform w/vent control panels. (10 md) : $ 1,000

E-41512
2 ea.| Remove pneumatic valves to reactor cell. (6 md) : $ 600 E-41513

 

 

(HCV-545 and -575)

 

 

 

 

 

 

 

 

 

 

 

 

 

2 ea.| Remove valve supports to reactor cell. (HCV-545 (10 md) _ ' $ 1,000 E-41877
and -575) _ :
. : , I E-407087
1 job Remove miscellaneous auxiliary piping, thermo- (200 md) i § 20,000 | E-40709
. ‘ T E-40878 "
couple leads, heater leads, leak detector lines, E-41512
T T E-41513 7
instrument lines, etc., to reactor cell. I E-55404
i E=J304UD
E-55406
E=4U4b3
1 ea.| Remove FDT-2 steam dome to reactor cell. (20 md) $ 2,000 E-40471
E=4U/08
8 ea.| Remove FDT-2 heater units to reactor cell. : (30 md) $ 3,000 E-51686

 

 

 

J

NET MATERIAL AND LABOR

 

 

 

 

 

CPFF - FIXED PRICE ORNL
DRAIN-TANK CELL ) R '

 

 

 

. UCN-1297
13 772

£ve
QUANTITY ENTOMBMENT OF RADIOACTIVE MATERIAL

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

UNIT COSTS © MATERIAL LABOR Reference
UNIT MAT'L | LABOR Drawing
1l ea. | Remove disconnect support ring from FDT-2. (10 md) $ 1,000 E-51686
1 ea. | Remove FDT-2 furance 1lid to reactor cell. (20 md) $ 2,000 E-51686
1 ea. | Remove FDT-2 to reactor cell, (20 md) $ 2,000
1 job | Emplace FDT-2 in reactor cell and pump tank full
of concrete.

Labor (20 md) $ 2,000

Material: 3 yd3 concrete $ 200
1 job | Replace steam dome into FDT-2 and fill steam o

dome with .concrete.

Labor (20 md) $ 2,000

Material: 1 yd3 concrete
2 ea. | Remove FDT-2 weigh cells to reactor cell. (10 md) - $ 1,000 E~41500
1 ea. | Segment and remove FDT-2 furnace to reactor cell. (50 md) $ 5,000 E-51686

NET MATERIAL AND LABOR '
DRATIN-TANK CELL CPFF FIXED PRICE ORNL
UCN-1297
13 772
°

e
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY ENTOMBMENT OF RADIOACTIVE MATERIAL UNIT COSTS . MATERIAL LABOR Reference
UNIT MAT'L | LABOR Drawing
2 ea. | Remove FDT-2 supports. (20 md) $ 2,000 E-41500
5 ea., ; Remove heater spacers from line 103, 104, and (5 md) $ 500 MIC-G-116
105 heaters.
10 ea. { Remove removable heater units from lines 103, (20 md) $ 2,000 MIC-G-116
104, and 105,
2 ea. | Remove FV-104 and -105. (1-1/2“ Sch 40 INOR-8) (10_md) N $ 1,000 E-55509
| - E-41512
220 ft | Remove uninsulated portion of lines 103, 104, (20 md) $ 2,000 E-41513
and 105. (1-1/2" Sch 40 INOR-8)
21 ea. | Remove heater base insulation units. (20 md) $ 2,000 MIC-G-117
1 job | Remove heater base support structure, (40 md) $ 4,000 E-55504
2 ea. | Remove freeze valves FV-108 and -109 w/heaters (12 wd) $ 1,200 E-55509
and insulation attached. '
NET MATERIAL AND LABOR
CPFF ORNL

DRAIN-TANK CELL

 

 

 

FIXED.PRICE

 

 

 

UCM-1297

3

7-72}

S%e
QUANTITY ENTOMBMENT OF RADIOACTIVE MATERIAL ‘ UNIT COSTS MATERI AL erence
UNIT : . MAT'L | LABOR Dr

A lines 108, 1 10.  (1/2" ' E-41513

40 INOR-8 w/Calrod heaters and insulation

attached

 
 

 

E E-4151
220 ft | Remove 103 w/insulation and thermoc les . : E-41513
1 attached. 1-1/2" Sch 40 INOR-8 w/3" thick
insulation
|
latforms. ] E-41514 '
E 708
E-41505
in center
. E-40933
ea.| Remove from south bay. md) E-40946
NET MATERIAL AND LABOR
FIXED PRICE |, ORNL

DRAIN-TANK CELL

UCN-1297
3y 7-72)

9%¢
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY ENTOMBMENT OF RADIOACTIVE MATERIAL UNIT COSTS MATERIAL LABOR Reference
UNIT : MAT'L | LABOR Drawing
12 ea.| Decontaminate lower roof plugs for future use. (50 md) $ 5,000

1 ea. Remove south lower shield plug support beam. (1 md) $ 100 E-40944
1 ea. Decontaminate south support beam. (2 md) $ 200
1 ea. Remove cell cooler w/support. (20 md) $ 2,000 E-56291
E-41512
2 ea. Remove HCV-546 and -577. (10 md) $ 1,000 E-41513
I E-4U/708
1 joH Remove miscellaneous auxiliary piping, thermo- (200 md) __i 20,000 | E-40709
E-41512
couple leads, heater leads, instrument lines, etc. } E-41513
3 ea] Remove heaters from line 104. (10 md) $ 1,000 MIC-G-116
. - E=41512
6 ft | Remove line 104, (1-1/2" Sch 40 INOR-8) (10 md) $ 1,000 E~41513
5 eal Remove line 104 heater base insulation units. {10 md) $ 1,000 MIC-G-117
NET MATERIAL AND LABOR
DRAIN-TANK CELL CPFF FIXED PRICE ORNL

 

 

 

 

 

 

UCN-1297

3

7-72}

Lyt
 

ENTOMBMENT OF RADIOACTIVE MATERIAL

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY UNIT COSTS MATERI AL LABOR Reference
UNET MAT'L | LABOR ' Drawing
1 job| Remove line 104 heater base support structure. (20 md) $ 2,000 E-55504
7 ea.| Remove FFT heater units. (30 md) $ 3,000 E-51686
1 ea.| Remove FFT fufnace 1id. (20 md) $ 2,000 E-51686
1 ea.| Remove FFT to reactor cell. (20 md) $ 2,000
1 ea. Emplace FFT in reactor cell and pump full of concrete.

Labor (20 md) $ 2,000
Material: 4 yd3 concrete i 200
2 ea. Remove FFT weigh cells. (10 md) $ 1,000 E-41500
2 ea. Segment and remove FFT furnace. _ (50 md) $ 5,000 E-51686
2 eaJ Remove FFT supports. (10 md) $ 1,000 E-41500
NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL
DRAIN-TANK CELL
UVCN-1297
3 712

8%¢
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

. QUANTITY ENTOMBMENT OF RADIOACTIVE MATERIAL UNIT COSTS MATERIAL LABOR Reference
UNIT MAT'L | LABOR Drawing
E=4YS512
~6 ft | Remove line 107. (1/2" Sch 40 INOR-8 w/Calrod) (20 md) $ 2,000 |- E-41513
heaters and insulation attached)
1 ea.' Remove freeze valve FV-107. (1-1/2" Sch 40 (6 md) S 600 E-55509
INOR-8 w/heaters and insulation attached)
E-41512Z
25 ft { Remove drain line 103 w/insulation attached. (30 md) $ 3,000 E-41513
(v25 ftr, 1-1/2" Sch 40 INOR-8 w/3" thick insula-
tion) _ .
2 ea.{ Remove line 103 supports. i (10 md) $ 1,000 E-41505
; E-56240
1 ea.| Remove resistance heating transformer. (15 kVA) {10 md) $§ 1,000 ; E-56241
|
1 ea.| Remove transformer support stand. (2' x 2' x 9') (10 md) $ 1,000 E-56241
2 ea.| Remove line 103 welding and brazing platforms (40 md) $ 4,000 E-41514
and stands. (*3' x 3' x 10")
NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL

DRAIN-TANK CELL

 

 

 

 

 

UCN-1297
3y 7.72)

6%¢
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY ENTOMBMENT OF RADIOACTTIVE MATERIAL UNIT COSTS MATERTAL | CABOR Reference
uniT . MAT'L LABOR 1 DraWiflg
I '
[ :
1 job|Clean up remaining miscellaneous support_clips, (25 md)| N $ 2,500 . o
lines, cables, etc. i
1 job, Remove lower shield plugs from north and center (20 md) $ 2,000
bay to outside storage. o e b e
1 job| Decontaminate inside of drain tank cell to (100 md) oy +$120,000 ;
allow limited personnel access. L L _
- e ._-_' r— e e e~ s
1 jobl Erect work platforms for removal of penetration (10 md) 1% 1,000
1
contents from east and south walls. e ! _
i |
- T E-40947
1 jobl Remove lines from penetration XXIV from reactor (20 md) ___T__$__ 2,000 | E-40948
cell to drain tank cell. (1-1/2" INOR-8 line;
1-1/2" carbon steel line; 2 each 1/2" stainless
steel lines) R
D-40713
1 jobl Remove support structures from penetration XXIV. (10 ma) $ 1,000 D-41505
. ‘ NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL
DRAIN-TANK CELL

 

 

 

 

UCN-1297
3 7.72)

 

 

05z
AN

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY ENTOMBEMENT OF RADIOACTIVE MATERIAL UNIT cbsTs MATERIAL LABOR Reference
UNIT MAT'L | LABOR Drawing
1 job| Decontaminate penetration XXIV from reactor cell. (10 md) $ 1,000 D-41505
12 ea.| Remove alr, water and leak detector penetration (60 md) $ 6,000 D-40947
‘ Page 52 of MSRE
"+ shield plugs from east wall. (6" diameter) Design Manual
12 ea.| Decontaminate cell sleeves at east wall. (12 md) $ 1,200 D-40947
327 ea.| Decontaminate cables and lines from penetra- (50 md) - ‘$ 5,000 D-40947
tions A, B, C, D, E, and F thru east wall.
. — e s e e
(3/4" pipe sleeves) — l —
— — i -
I !
327 ea.| Decontaminate 3/4" penetrations thru east wall, (30 md) o $ 3,000 _ D-40947
|
e b
12 ea. Cap penetrations thru south wall. (3/4" thru3") (Qmwmd);  ; { $ 1,000 D-40947
1 ea.| Remove penetration shield plug thru north wall (20 md) $ 2,000 D-40947
to fuel processing cell. (10" diameter) |
1 ea] Decontaminate sleeve to fuel processing cell. (10 md) $ 1,000 D-40947
NET MATERIAL AND LABOR
. CPF¥ FIXED PRICE ORNL .
DRAIN-TANK CELL — T T
s e

 

 

 

UCN-1297
3 773

 

16¢
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

ATV ENTOMBMENT OF RADIOACTIVE MATERTAL ~IniT costs Wi | Tresr | ReFerence
INIT ' MAT'L | LaBOR | - l '~ Drawing
I : .
1 job|Decontaminate entire drain tank cell to lowest (100 md) | $ 10,000
practical level.
1 job' Replace all lower shield plugs in drain tank (20 md) ) $ 2,000
cell. | ! :
| s it et = e e} e e e
. ! .
i e e e
' | i
1 job| Replace lower shield plug steel shield plates. " (10 md) { e ] . ._$ 1,000 !
—_— — et i -l___ ——— v _i_ . ——r—— ___i e m et o ———————— .
1 job{ Replace all upper shield beams and holddown keys (}_O_md) !_ o o _‘: ‘5_7__3,0_0_0 ;
| i e
in drain tank cell. i ! !
e e : — ——— e b b s+ — -—-———?-—-_—.——_
‘ ;
i ' ‘
- e . —_— ' i -
1 ‘
i ]
. e . l
| i
|
NET MATERIAL AND LABOR | s 400 - $272,900
CPFF FIXED PRICE ORNL
DRAIN-TANK CELL
. $273,300 :
UCN-12587 -_
3 7-72)

[AYA
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY ENTOMBMENT OF RADIOACTIVE MATERIAL UNIT COSTS MATERIAL LABOR Reterence
UNIT MAT'L | LABOR Drawing
1 ea.! Remove fuel process sampler assembly to reactor (60 md}| $ 6,000 EJN-10415
cell,
4 ea.l Remove sampler instrument panels to salvage. (16 md) $ 1,600 EJN-10415
S E=S5435——
1 ea.| Remove absorber cubicle contents to reactor cell. (15 md) ! $ 1,500 | E-55452
i
1 job Remove miscellaneous auxiliary equipment from (10 md) [ ¢§ 1,000 :
_— — - ‘- e e g rm e e———
| ;
!
cell top area to salvage. jfl !
—— _.L_,H_.;_____ S N T
6 ea.| Remove cell roof plugs to storage. (20 md) J : ; $ 2,000 E-55431
- — —_ i e e m e et s mma e e g e e
! ! )
i
- e o _— . T
1 ea. Remove cell ccoler tc burial ground. (10 md) 'S 1,000 ; .
RS SO T —
|
1 joY Set up work platforms and "C" zone over cell. (10 md) $ 1,000 |
|
l
E=50447
1 jo4 Remove salt piping and miscellaneous auxiliary (150 md) I $ 15,000 E~55450
- ' i E=S5455—
plping, valves, heaters, etc., to reactor cell.
NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL
FUEL-PROCESSING CELL -0 T T Ty T T T T

 

UCN-1297
{3 ?-72)

 

 

€£6T
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

DUANTITY ENTOMBMENT OF RADIOACTIVE MATERIAL n .E_N'_T,CQ,S_T_S___,,_.T MATERI AL i LABOR Reference
UNIT MAT'L | LABOR Drawing
SR N S S B SR
! : .
1 ea.| Remove fuel storage tank to reactor cell. Y o '$ 2,000 E-40430
| |
- 1| ——— Hgfl_
1 job| Emplace fuel storage tank into reactor cell and i i ;
pump full of concrete. N
Labor ] o (20 md) b 1% 2,000 |
Material: 5 yd3 concrete ] . 8200 'i______ oy
; I
: e - T s
1 jobl Remove sodium fluoride trap shielding to salvage. (10 md)| _ . i__$ 1,000 | E-55446
1 ea.| Remove sodium fluoride trap to reactor cell. (20 md) i ; L $ 2,000
=1 e ;
. i ,
e e — d e e e e e o e e e
! i | i
1 ea.| Remove salt line filter to reactor cell. _(0wd}f 4 1§ 2,000 | E-49036
— - } i __A_= |
i
1 job Check remaining material; remove only the con- (30 md) C ”L_§ 3,000 |
taminated items to the reactor cell.
1 jobl Remove remaining material to salvage or burial (50 md) $ 5,000
ground (support structures, cables, gas lines,
instrument lines, etc.).
NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL,
FUEL-PROCESSING CELL
UCN-1297 =
3 7-72)
® @

®Se
QUANTITY
UNIT

ENTOMBMENT OF RADIOACTIVE MATERIAL

 

 

MATERI AL

LABOR

Reference
Drawing

 

 

| Decontaminate interior of cell to lowest prac- (50 md)

tical level.

$ 5,000

 

 

 

1l job

Replace cell roof plugs,

$ 2,000

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

e o e
I | R
: _ b e
- . e
S S S

—

 

 

 

 

 

 

$ 200

$ 53,100

 

FUEL-PROCESSING CELL

 

 

UCN-1297
3 7.72)

CPFF

}.853,300 |

 

FIXED PRICE

 

 

Ge?
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY ENTOMBMENT OF RADIOACTIVE MATERIAL UNIT COSTS MATERIAL I Lasor : Reference
UNIT ' MAT'L | LABOR . . Drawing
I l
SN SRR R _. i
1 job| Remove ventilation house roof to storage. (200md)| | o $ 2,000
1 iob| Remove all equipment above floor level to sal- (50 md) $ 5,000
vage and burial ground (instrument panels,
auxiliary piping, etc.) ,
|
' v e R - ; e
1 job| Remove floor grating and dry stacked lead and (100 md) 1 $ 10,000 J
| R
concrete shielding blocks from the room. ! i
;
(75 yd3 total material) ;
| | !
_— ! R |
i , I
-1 ea. Remove off-gas valve box w/contents to reactor (50 md) i ! . % 5,000
i' i I |
cell. ; | : ;
—_ e ————— t - [p—— j T -
| ;
S — - l
| i
1 ea.| Remove charcoal bed valve box w/contents to (50 md) i o $ 5,000
reactor cell.
1 ea.| Remove off-gas particle trap assembly to reactor (30 md) $ 3,000
cell.
NET MATERIAL AND LABOR
.CPFF FIXED PRICE ORNL
VENTILATION HOUSE AREA
UCN-1297 o T
{3 7-72)
. . . .d T ‘ .

96¢
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY ENTOMEMENT OF RADIOACTIVE MATERTAL UNIT COSTS MATERIAL LABOR Reference
uNIT MAT'L | LABOR Drawing
1 ea. Remove off-gas sampler assembly to reactor cell. (30 md) $ 3,000
1 job Remove all off-gas piping from ventilation house (50 md) $ 5,000.

to charcoal beds and to coolant cell and move to
reactor cell.
1 joY Remove all miscellaneous auxiliary systems, (30 md) -§ 3,000
support structures, etc., to burial ground.
-— — —_— i S ——— e ——_—_ e . e T
1 joY Decontaminate ventilation house. (30 md) $ 3,000
| '
i !
| o
1 joh Replace ventilation roof. (20 md) _ ‘$ 2,000 |
—fee !
t
2 eal Remove roof plugs from charcoal absorber pit. (10 md) ' § 1,000 '
1 joY Remove piping from absorber beds; seal ends. (30 md) $ 3,000
5 ea) Remove absorber beds to burial ground. (30 md) $ 3,000
NET MATERIAL AND LABOR
’ CPFF FIXED PRICE ORNL
VENTILATION HOUSE AREA L

 

 

 

 

 

VCHN-1297

T-72)

LT
QUANTITY ENTOMBMENT OF RADIOACTIVE MATERIAL T T meE ce
UNIT MAT'L | LABOR ‘ . Drawing

water from pit and remove support struc-—
ures to burial ound. Check and decontaminate

it as r red.

lace absorber pit rcof pl

 

 

 

 

86¢

 

 

NET MATERIAL AND LABOR 64.000
CPFF FIXED PRICE
VENTILATION HOUSE AREA
$64,000
UCN-1297
3 7-72)

o
@
@
ENTOMBMENT OF RADIOACTIVE MATERIAL

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY UNIT COSTS MATERIAL LABOR Reference
unIT MAT'L | LABOR Drawing
1 jobl Remove special equipment room roof plugs to (20 md) - § 2,000

storage.
2 ea. Remove componefit cooling air enclosures to reac- (25 md) $ 2,500
tor cell,
2 ea. Emplace component cooling air enclosures in reac- '
tor cell and fill with concrete.
Labor (25 md) $ 2,500
Material: 15 yd3 concrete $ 600
2 ea. Remove component cooling air blower motors to (20 md) ' $ 2,000
T ot T T T Tyt
!
reactor cell. (75 hp) -
2 ea) Remove component cooling air blowers to reactor (20 md) $ 2,000
cell. (10 x 15 Roots type)
2 ea] Remove component cooling air bottom domes (50 md) $ 5,000
w/piping manifolds to reactor cell.
NET MATERIAL AND LABOR
. CPFF FIXED PRICE ORNL
SPECIAL EQUIPMENT ROOM T

 

 

 

UCN-1297
(3 77D

65C
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY ENTOMBMENT OF RADIOACTIVE MATERIAL UNIT COSTS MATERIAL ! LABOR Reference
uNIT . MAT'L | LABOR Drawing
1 ea.| Remove component cooling alr heat exchanger to (20 md) $ 2,000
reactor cell.
25 ft | Segment and remove 30" OD cell exhaust line to (100 md) $ 10,000
reactor cell,
2 ea. Remove pump bowl bubbler contaimnment enclosures (30 nd) $ 3,000
w/contents to reactor cell,
1 jol Remove remaining auxiliary and support material (100 md) $ 10,000
to reactor cell or burial ground as required by
survey.
1 joY Demolish concrete wall, excavate, and remove 30" (200 md) $ 20,000
0D duct from special equipment room to service
tunnel.
25 ft | Remove cell exhaust line from special equipment (200 md) $ 20,000
room to service tunnel.
NET MATERIAL AND LABOR
. CPFF FIXED PRICE
SPECIAL EQUIPMENT ROOM RN~
UCN-1297
3 7-72)
.| - 'I.“ ! -

09¢
QUANTITY ENTOMBMENT OF RADIOACTIVE MATERIAL
UNIT

ir cell wall.'
Labor

Material: 5 3 concrete

Clean and decontaminate special equipment room.

1 Replace special equipment room roof plugs.

SPECTAL EQUIPMENT ROOM

UCN-1297
3 7-72)

UNIT COSTS
MAT'L LABOR

(50 md)

NET MATERIAL AND LABOR

MATERI AL

$ 900
CPFF

$93,900

$ 93,000
FIXED PRICE

Drawing

 

192
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY ENTOMBMENT OF RADIOACTIVE MATERTAL UNIT COSTS MATERIAL LABOR Reference
UNIT MAT'L | LABOR Drawing
NOTE: [ A1l material except as noted is to be removed to the burial ground.

21 ea.| Remove coolant cell penthouse roof plugs. (20 md) $ 2,000 E-40979
(1'-0" x 2'-0" x 18' long)
M-10333-
1 ea.| Remove coolant salt sampler assembly. (20 md) $ 2,000 RF-001-E
i . — D=40450
1 ea.| Remove radiator door lifting mechanism. (30 nd) $ 3,000 D-40451
D-40452
1 jobl Remove coolant pump auxiliary piping. (15 md) $ 1,500
D=-40440
1 job| Remove radiator top insulatiom. (30 md) $ 3,000 E-40470
- E-40471
E-40472
E-40473
E-40746
1 jobl Remove radiator doors. ' (20 md) $ 2,000 E-55510
E-4]1515
1 jobf Remove radiator door lifting and coolant pump (30 md) $ 3,000 E-41866
support structures. _
NET MATERIAL AND LABOR
' CPFF FIXED PRICE ORNL

COOLANT CELL AREA

 

 

 

 

 

UCN-1297
3 7-72

¢9¢
QUANTITY

ENTOMBMENT OF RADIOACTIVE MATERIAL

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

UNIT COSTS MATERIAL LABCR ) Reference
uNIT MAT'L | LABOR Drawing
1 job| Remove radiator and enclosure assembly, (100 md) $-10,000 E-40470
1 job| Remove radiator supports and radiator door . (50 md) $ 5,000 E-55516

tracks. ;
} E-4U/0U2
1 job| Remove coolant salt drain lines. (20 md) $ 2,000 E-41860
E-418061
E-41862 -
1 ea.| Remove coolant salt. drain tank. (50 md) i § 5,000 E-40702
A32,500 1bs| Remove lead shielding from off-gas pipe chase. (100 md) 1 $ 10,000 E-41893
(44' x 9" OD x 1" ID = 19,2 ft3 = 13,587 1bs )
and “40' lead brick 2" thick = 26.7 ft3 =
18,872 1bs)
44 ft | Segment and remove off-gas lines to reactor (20 nd) $ 2,000
cell. (1 each 1/4" OD in 1/2" pipe; 1 each
1/2" pipe in 1" pipe)
NET MATERIAL. AND LABOR
CPFF

COOLANT CELL AREA

"ORNL

 

 

FIXED PRICE

 

 

 

 

UCN-1297
(3 7-72)

£9¢
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY ENTOMBMENT OE. RADIOACTIVE MATERIAL T CosTs MATERTAL LABOR Reference
vy MAT'L | LASOR Drawing
5 ea.| Remove off-gas line supports. (10 md) $ 1,000 E-41892

60 ft | Segment and remove reactor cell exhaust line (200 md) $ 20,000

to reactor celi. (30" 0D x 0.312 wall carbon
steel)
1 job| Remove miscellaneous auxiliary lines from (100 wd) $ 10,000 E-41893
coolant cell area (water, oill, gas, off-gas,
etc.) to reactor cell or burial ground as |
required;
1 4obji Clean and decontaminate coclant cell area. (100 md) $ 10,000
1 lot] Miscellaneocus packaging, lifting, and handling $ 4,600
materials.
ET ol
NET MATERIAL AND LABOR $ 4.600 $ 91,500
CObLANT CELL AREA CPFF FIXED PRICE ORNL
'$96,100

 

 

 

 

UCN-1297
» 7-72

%9¢
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY ENTOMBMENT OF RADIQOACTIVE MATERIAL UNIT COSTS MATERIAL LABOR Reference
UNIT MAT'L { LABOR Drawing
NOTE: ; A1l material éxcept as noted is to be removed to the buriah ground.

100 ft | Remove lube oil and water piping from reactor (20 md) $ 2,000 E~40735

cell to service tunnel penetration.
E=50411

100 ft | Remove lube 01l and water piping from special (20 md) $ 2,000 E-55414

equipment room to service tunnel penetration. [
i |
— oo A
j o
2 eal Remove reactor cell exhaust line valves to reac- {30 md) . § 3,000 | D-41026
tor cell. (30" butterfly w/operators) | ;
v i
i 1
3 - - - - “"_r T T T D-41026
75 yd] Machine excavate w/shoring 30" exhaust line from (100 md) $ 3,000 | $ 10,000 | D-41027
, - T T T D078 T
special equipment room to service tunnel (~20' 1 ]l L
deep). :
2 yt:lJ Demolish reinforced concrete service tunnel wall (10 md) $ 1,000 | D-41028
¥
at 30" exhaust line penetration.’ ‘
NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL
SOUTH YARD - —
B S d o
UCN-1297

-1y T-72)

 

 

G9¢
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY ENTOMBMENT OF RADIOACTIVE MATERIAL ~ UNIT COSTS |  MATERiaL ] LABOR Reference
UNIT MAT'L | LABOR T Drawing
18 ft | Segment and remove to reactor cell 30" exhaust (125 md)| =, | $ 12,500 _12_—_4_1_0_2_7
line from special equipment room to service o .
tunnel. (30" OD x 0.312 wall carbon steel) - \
75 yd3 Machine excavate w/shoring 30" exhaust line from (100 md)| || $3,000 | $10,000 | D-41028
service tunnel to stack filter (~20' deep). e
3 ToTTTT TN T - T T T BAG1027
1 yd”| Demolish reinforced concrete wall of service _ _  (Smd) 1 &+ | § 500 ;| D-41028
tunnel at 30" line penetration. o I S ~
|
| o |
50 ft | Segment and remove to reactor cell 30" exhaust (350 md) L ____j__ 1§ 35,000 D-41028
| |
line from service tunnel to stack filters. L ! L _'[_
(30" OD x 0.312 wall carbon steel) . 1 I
T - = ! -
|
1 job Check and remove all contaminated soil from (50 md) $ 5,000
excavated area.
NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL
SOUTH YARD .
UCN-1297
172

99¢
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY ENTOMBMENT OF RADIOACTIVE MATERIAL UNIT COSTS MATER) AL LABOR Reference
UNIT MAT'L | LaBOR Drawing
¢
D=%1026
1 job| Form and pour concrete at special equipment room D-41028
wall, and two walls of service tunnel.
Labor (20 md) $ 2,000
Material: 3 yd3 concrete form material $ 500
1T
150 yd3 Backfill excavation from tunnel area (10 md) $ 1,500 $ 1,000 ¢+
w/stabilized fill to existing grade level. '
_ T - - T T D=RIOIT T
1 job Remove and decontaminate inlet manifold to stack (50 md) | _ $ 5,000 . D-41072
e
filter bays. :
P T i
i T T B T" """"'fi“"D:&I07r_—_"
3 ea.| Remove and decontaminate stack filter inlet (20 md) T $ 2,000 | D-41072
dampers. (24" x 18") B L o b ‘ i L
31 ea.| Remove and decontaminate stack filter pit roof (50 md) $ 5,000 D-41117
plugs.
105 ea. Remove prefilters, decontaminate frames and (50 md) L $ 5,000 ‘D-41075
replace filter media.
NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL
SOUTH YARD - T T T T
UCN-1297 T TR TR T AemATT T T e

 

3 112

£97
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY ENTOMBMENT. OF -RADIOACTIVE MATERIAL UNIT COSTS MATERIAL LABOR i Reference
UNIT MAT'L | LABOR " Drawing
|
i
6 ea.| Remove final filters, decontaminate frames and (50 md) $ 5,000 : D-41076
replace filters.
D-41117
1 job; Decontaminate interior of filter pit., Flush (30 md) $ 3,000 D-41273
solutions to the Laboratory ILW system thru _ ] s B
existing drain lines. _
6 ea.] Replace final filters. (30 md) 52,000 (UCC-ND) $ 3,000 | D-41076
. i
i
R T T ——
105 ea.| Replace prefilters. (50 _md) 52,000 (UCC-ND) $ 3,000 | D-41075
: |
" - - .-—.—E_-. e e ——— _i__
31 ea.| Replace and seal filter pit roof plugs. (30 md) ] - $ 500 | $-3,000 D-41117
| |
i —
3 ea.| Replace filter inlet dampers. (20 md) $ 2,000 | D-41071
1 ea.| Replace filter inlet manifold. ‘(30 md) $ 3,000 D~41072
‘NET MATERIAL AND LABOR
. CPFF FIXED PRICE ORNL
SOUTH YARD
UCN-1297
3 172

89¢
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY ENTOMBMENT OF RADIQACTIVE MATERTIAL UNIT COS5TS MATERI AL LABOR Reference
uNIT MAT'L | LABOR Drawing
. D=41028
1 job| Design, fabricate and install blanking fixture D-41071
. D-41072
where cell exhaust line was removed.

- Design {10 md) $ 1,800 (QCC-ND)
Fabrication (20 md) $§ 500 . 3,200 (ycC-ND)
Installation {20 md) $ 2,000

" G&A on materials: 4,500 x 0.35 $ 1,600
UCC-ND Subtotal $ 6,100 $ 5,000
NET MATERIAL AND LABOR | s 8,500 $127,000
CPFF FIXED PRICE ORNL
SOUTH YARD '
. ' $135,500 $11,100
UCN-1297 =

3

69¢
ENTOMBMENT OF RADIOACTIVE MATERIAL

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY UNIT COSTS MATERIAL ! LABOR Reference
UNIT MAT'L | LABOR | Drawing
NOTE: | A1l material is to be removed to the burial ground.

2 ea.| Remove treated water storage tanks. (10 md) $ 1,000 D-41252
2 ea. Remove treated water pumps. (20 hp) (20 md) $  2.000 D-41252
1 loyg Remove piping, valves, instruments, etc., from (50 md) i $ 5,000 D-41252
water room. .
1 lot Remove piping and valves from radiator tunnel. (30 mwd) $  3.000 D-41252
) B o
1 joh Remove thermal shield gas separation system from (30 md) L $ 3,000
fan house.
: 3
100 yd] Machine excavate underground 4" and 6" lines to (20, md) $ 2,000
diesel shed.
~250 ft| Remove 4" and 6" lines from water room to diesel (20 md) $ 2,000 D-41254
.shed.
NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL
TREATED-WATER SYSTEM
UCH-1297
3 1721
e, -, e A

042
?" ! ! | . q;'i ! ;

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY ENTOMBMENT OF RADIOACTIVE MATERIAL UNIT COSTS MATERIAL CasoR Reference
UNIT MAT'L | LABOR Drawing
1 ea.| Remove treated water filter from diesel shed. (10 md) $ 1,000 D-41254
2 ea.| Remove treated water heat exchangers from diesel (30 md) $ 3,000 D-41254
shed.
A150 ft | Remove piping and valves from diesel shed. (4" (30 md) $ 3,000 D-41254
and 6" carbon steel)
2 ea.| Remove steam dome heat exchangers from west (20 md) ) A 2,000 | _
tunnel.
i ] '
2 ea.| Remove steam dome surge tanks from west tunnel. (20 md) _ s 2,000 _
JN S | I -
1 lotj Remove piping and valves from west tunnel. (30 md) $ 3,000 |
1 jol Decontaminate west tunmnel. (30 md) $ 3,000
1 joH Decontaminate water room. (30 md) $. 3,000
NET MATERIAL AND LABOR
CPFF FIXED PRICE ORNL

TREATED-WATER SYSTEM

 

 

 

 

 

 

UCN-1297
3 7-72)

TL2
QUANTITY MATERI| AL

UNIT

ENTOMBMENT OF RADIODACTIVE MATERIAL UNIT COSTS

MAT"L LABOR

1 jobl Decontaminate diesel shed.

100 yd7| Backfill west yard between water room and diesel

shed to exist ade.

NET MATERIAL AND L ABOR

$ 1,000
CPFF
TREATED-WATER SYSTEM
$40,500
UCN-1297
3 1T

 

Reference

$ 39,500
FIXED PRICE

¢l
. .
. " -

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

QUANTITY ENTOMBMENT OF RADIOQACTIVE MATERIAL UNIT COSTS MATERIAL LABDR Reference
UNIT MAaT'C | LaBOR Drawing
NOTE: | A11 material except as noted is to be removed to the buria} ground.

1 ea.| Disconnect and remove distillation experiment (25 md) $ 2,500
valve box.
1 job Remove roof plugs and set up temporary work (50 nd) $ 5,000
shielding. ——
1 jobl Remotely disconnect all lines from distillation (30_md) ~ $ 3,000 L
experiment.
- t
"1 ea.| Remove distillation experiment assembly te (100 md) L $ 10,000
reactor cell. B i
i
i
1 joH Remove temporary work shielding. Install (50 md) $ 5,000
ladders.
49026
2 ea. Remove fuel process system charcoal traps. (10 md) $ 1,000 E-55454
NET MATERIAL AND LABOR
CPFF FIXED PRICE - ORNL
SPARE CELL AREA

 

 

 

 

 

UCN- 1297
3 7.7

€L2
 

QUANTITY ENTOMBMENT OF RADIOACTIVE MATERIAL _ T cosTs MATERTAL ChgoR ReFerence

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

unIT MAT'L | LaBOR Drawing ~
1 ea.| Remove fuel process ventilation filters. (20 md) $ 2,000 E-55454
1 ea.l Remove fuel process soda lime trap. (20 md) $ 2,000 E-55454
‘ - E-55454
1 lot) Remove miscellaneous piping, supports, etc. (50 md) ' __1.%¢ 5,000 E-55456
~200 'Remove dry stacked block from west wall. (25 md) o $ 2,500
1 joH Decontaminate cell. (30 md) _ r§ 3,000
1 job Replace roof plugs. L (10 md) A 1% 1,000

 

 

 

 

 

 

 

NET MATERIAL AND LABOR

 

 

 

 

 

 

 

$ 42,000 .
CPFF FIXED PRICE ORNL
SPARE CELL AREA
$ 42,000
UCN-1297
3 772

     

vie
 

 

 

 

5-12..

13.
14,
15,
16.

17.

18.
19.
20-24,
25-34.
35.
36-40.
41.
42.
43.
44,
45,
46-47.

48..

 49-50.
51.
52,

comaw

F. T.

. &
., ® - -

PEHOGORR PO T

P.
E.
A.
J.
E.
B.

*

UEQWKK“EQUHON?O"H

275

DISTRIBUTION

Binford

Blumberg

Burger
Bruce
Cagle
Cox
Culler
Dixon
Hill
King
Kirby
Kurtz -
Large, ERDA-ORO

. Lenhard, ERDA-ORO
Postma

Pugh

Ramsey

Robinson :
Schreiber, ERDA-ORO
Seagren

Trauger

Central Research Library
Document Reference Section
Laboratory Records Department
Laboratory Records, ORNL R.C.
ORNL Patent Office

ORNL/CF-77/391

e