ML20210N935
| ML20210N935 | |
| Person / Time | |
|---|---|
| Site: | Framatome ANP Richland |
| Issue date: | 08/06/1999 |
| From: | Edgar J SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| JBE:99:040, NUDOCS 9908120014 | |
| Download: ML20210N935 (15) | |
Text
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SIEiMGNS August 6,1999.
JBE:99:040 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Gentlemen:
License Amendment Application - SNM - 1227, Docket 70-1257 Addition of the Fuel Services Building to the NRC License Siemens Power Corporation (SPC) requests that its NRC Materials License SNM-1227 be amended to include'its Fuel Services Building as a specific location for the authorized activities with special nuclear material (SNM) described below.
Backaround
.The Fuel Services Building is not currently included in SPC's NRC Materials License, SNM-1227, as a site for authorized activities involving enriched uranium (< 5% U-235).
Instead, this building is the site of radionuclide utilizing - activities licensed under SPC's State of Washington Radioactive Materials License WN-1062-1. The activities currently carried out in that building are comprised mainly of assembling equipment and tooling designed to examine irradiated fuel, and shipping the equipment and tooling to commercial reactor sites worldwide. At such nuclear sites personnel from SPC conduct fuel examinations, repackage the equipment and ship it back to SPC. When the equipment returns to SPC, it is unpackaged and decontaminated in the contaminated equipment areas (Rooms 926 and 927) of the Fuel Services Building. Contaminants include the typical array of fission and activation products found in reactors' spent fuel pools.
Buildino Description 2
2 The Fuel Services (FS) Building is a 7,800 ft office building, and a 7,200 ft processing building combined into a single facility.
The office building portion of the facility is a two-story building constructed of concrete masonry units (CMU). The poured in-place floors are of 3,000 psi concrete designed for 250 psf. The inner sides of all exterior walls are insulated and covered with fire-rated gypsum board., The gypsum panel joints are taped and sealed, and the interior surfaces are suitably painted. The interior partitions throughout the building are either CMU or fire-rated gypsum board.' The roof is comprised of steel deck plates supported on steel trusses, covered on both topside and underside with insulation, and a single-ply "Trocal" g roof system.
The process area of the f acility is a single-story building with two different roof heights.
The exterior walls are constructed of 10-inch thick, pre-insulated CMU sealed on the
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Siemens Power Corporation 110023 k
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i 2101 Horn Rapids Road Tel:
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RicNand, WA 99352 Fax:
4509) 375 8402
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I 9908120014 990806 PDR ADOCK 07001257 C
PDR 7 j
U.S. Nucint Rigulitory Commission J8E:99:040 August 6,1999 Page 2 interior and exterior against moisture and air leakage. The interiur partitions throughout the building are either concrete block or fire-related gypsum board. The roof height over the Contaminated Equipment Room (Room 926) is approximately 19 feet in order to allow a 12-foot hook height for the 2-ton bridge crane. The roof over the remaining process portion is approximately 12 feet high such that a ceiling height of 10 feet can be maintained. The roof is comprised of steel deck plates supported on steel trusses, j
covered with insulation, and a single-ply "Trocal" roof system.
I Process Descriotion Unitradiated fuel assemblies from power reactors, containing up to 5% enriched uranium, which have been contaminated by fission and activation products from having resided in a reactor's fuel pool, are decontaminated to the extent practicable at the reactor site prior to being shipped to SPC for disassembly and recovery of the enriched uranium in the fuel rods. The disassembly of the fuel assembly (the removal of the rods and their decontamination) will take place in the area of the Fuel Services Building currently used to handle and decontaminate equipment and tooling returning from reactor fuel examinations (Rooms 926 and 927).
The fuel assembly shipping container will be brought into this area and opened. The shipping container will serve as the " platform" upon which the fuel assembly rests during the disassembly operation. As the rods are removed from the fuel assembly, they are decontaminated and placed in trays which are restricted in depth to that of a critically safe slab. Each tray will be limited to one fuel assembly's rods. The trays will then be radiologically surveyed and transported to the UO Building for storage and j
2 subsequent downloading and recovery of uranium from the pellets contained in the rods.
The remaining fuel assembly hardware in the Fuel Services Building (tie plates, spacers, etc.) will be surveyed and disposed of appropriately. After the fuel assemblies in the shipping container have been disassembled and removed from the containers, the container will be surveyed, decontaminated as necessary and removed to storage.
SPC expects to limit the amount and form of SNM in the Fuel Services Building to that contained in five fuel assemblies. The form of the SNM will include two fuel assemblies in licensed shipping containers to be disassembled and the rods from three disassembled fuel assemblies in trays or being individually decontaminated prior to being placed in trays.
Safety Considerations The licensed material will be contained in fuel rods and will be handled in the Fuel Services Building in accordance with the radiation protection, criticality safety and environmental protection programs described in chapters 3,4 and 5, respectively, m SPC's license application. From a fire protection standpoint, the Fuel Services Building is rated as noncumbustible. Fire loading is kept to a minimum through monthly inspections. Fire extinguishers (dry chemical or CO ), alarm pull boxes, and heat 2
detectors are strategically placed throughout the building.
Specifically, with regard to both radiation protection and environmental protection, the contamination on fuel assemblies brought into the building for disassembly is the same as that on fuel examination equipment and tooling returned from reactors. There are, therefore, no new issues in these fields.
4.fu U.S. Nucistr Re'gulatory Commission JBE:99:040 August 6,1999 Page 3 With regard to criticality safety, disassembly of fuel assemblies is routinely carried out at SPC, generally in the UO Building. The process, therefore, is well established as are 2
criticality safety measures which can readily be applied in the Fuel Services Building.
The rod handling (removal and decontamination) process will rely on geometry control; i
i.e., the rods will be placed in open ended trays whose height does not exceed that of a safe slab. It is further required that all equipment be free-draining to prevent water from accumulating in the interstitial spaces between the fuel rods and that no extraneous plastic be stored or used around or between the fuel rods. The criticality controls which may be used for rod storage trays and rod transfer carts are shown on Table I-4.1 on pages 4-24 and 4-29, respectively, in SPC's license application. In addition, a description of the criticality safety measures employed in various rod handling operations is presented in sections 15.1.10 and 15.1.11 in Chapter 15 of that application. The Fuel Services Building is covered by the site criticality detection / alarm system.
Enclosed, in support of this request, are six copies each of pages vi, 1-1 1, 10-1, 10-1 1 a,10-11b,10-50b,10-50c,10-50d,10-71,10-114b,10-114c, and 10-114d of SPC's license application.
if you require further information, please call me at 509-375-8663.
Very truly yours, R
Jam B. Edgar Staff Engineer - Licensing
/las Enclosures i
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SiemenS Power Corporation - Nuclear Division eup.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 e
i REV. I TABLE OF CONTENTS-4 LIST OF FIGURES (Cont.d) l Fiaure Paae I
ll-10.24 Simplified Schematic HVAC System - U30s Facility......................
10-98 ll-10.25 Simplified Schematic HVAC System - ELO Building........................ 10 99 11-10.26 Simplified Schematic HVAC System - ELO Building Addition.............10-100 ll-10.27 Simplified Schematic HVAC System - Contaminated Clothing Laundry F a cility. u...................................................................................... 1 0- 1 01 Il-10.27a Simplified Schematic - SWUR Incinerator Shroud Cooling System......10-102 li-10.27b Lagoon Uranium Recovery / Solids Processing Facility Ventilation i
- System Flow Diagram...................................................................10-103
- ll-10.28 Plant Equipment Layout - ARF Building......................,...................,10-104 11-10.29' Ammonia Recovery Waste Management Facility Engineering Flow i
D ia g ra m........................................................................................ 1 0- 1 0 5 ll-10.29a Flow Diagram Lagoon 5A - Sewer lon Exchange Project...................10-106 11-10.30 Plant Equipment Layout - LUR Facility..........................................10-107 l 11-10.31 Engineering Flow Diagram - LUR Production Facility.......................,10-108 11-10.32 Fire Ala rm S ystem....................................................................... 10- 10 9
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11-10.33 SPC Site General Arrangement Dry Conversion First Floor...............10-110 ll-10.34 SPC Site General Arrangement Dry Conversion Second Floor.........10-111 11-10.35 SPC Site General Arrangement Dry Conversion Third Floor..............10-112 ll-10.36 SPC Site General Arrangement Dry Conversion Fourth Floor............,10-113 11-10.37 Dry Conversion Simplified Air Flow Diagram....................................10-114 11-10.38 UFe Cylinder Recertification Facility Ventilation System.,
........ 10-1 14 a
! ll-10.39 SPC Site General Arrangement Fuel Services Building First Floor.....10-114b 11-10.40 SPC Site General Arrangement Fuel Services Building Second Floor 10-114c l 11-10.41 Simplified Schematic HVAC System - FS Building...........................10-114d l
11-1 3. 1 M onitoring Weil Description.........................................................
13-5 ;
i i 11-1 4. 1 PNL Critical Experiment Layout (Reference 6)...........................
14-17 ~
ll-14.2 B&W Critical Experiment Layout.,........................................ 14-23 4
AMENOMENT APPt,1 CATION DATE; PAGE NO.:
August 6,1999 vi SPC ND:3330 947 (41/07S2;
SiemenS Power Corporation - Nuclear Division eup.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 I
I PART I-LICENSE CONDITIONS REv.
TABLE l-1.1 Specific Locations of Authorized Activities (Cont.d) "
Location SNM Authorized Activity Modular Extraction /
Uranium Solid Waste (up to 5 Sorting, shredding, compaction Recovery Facility wt. % U-235) and uranium recovery.
l i (MERF) l Sea-land Containers Uranium Compounds (up to 5 Storage of a planar array of wt. % U-235) closed containers of uranium compounds which are externally i free of significant contamination. I Fuel Services UO2 (up to Swt% U-235)
Disassembly of fuel assemblies i j Building and decontamination of fuel rods !
and components.
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The locations described in this table are shown on the site plan, Figure 11-10.1 AMENOMENT APPUCATON DATE:
PAGE NO.:
August 6,1999 1-11 SPC-ND 3330 947 (R-t07 921
1 SiemenS Power Corporation - Nuclear Division eur.2 S.PEClAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 l
PART ll-SAFETY DEMONSTRATION REV.
CHAPTER 10 FACILITY DESCRIPTION 10.1 Plant Layout The Siemens Power Corporation (SPC) Engineering and Manufacturing Facility at Richland consists of buildings and various outside facilities which are shown on Figure 11-10.1. Many of these buildings, such as the Office Complex, Guardhouse, Warehouse Complex, etc., are not utilized for uranium processing and are not addressed further.
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- Those facilities which are involved with enriched uranium handling and processing, and are therefore covered under this License Application, are listed below
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Specialty Fuels (SF) Building j
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Uranium Oxide (UO2) Building j
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3.
Engineering Laboratory (ELO) Building 4.
Dry Conversion (DC) Building 5.
Contaminated Clothing Laundry j
6.
Fuels Storage Warehouse (Bay 4)
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UNH Drum Storage Warehouse 8.
Radioactive Materials Storage Warehouse (Bay 6) 9.
Materials Warehouse (Bay 2) 10.
Product Development Test Facility (PDTF) 11.
UFe Receiving and Storage Facility
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Operations Scrap Warehouse (Bay 7) l l
13.
UFe Cylinder Recertification Facility l
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Waste Storage Facility j
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Lagoon Uranium Recovery and Solids Processing (LUR/SP) Facility 16.
Ammonia Recovery Facility (ARF) j i
17.
Fuel Services Building l
j A description of these facilities, including the licensed activities in each, follows. The.
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' LUR/SPF and ARF are described in Section 10.4, Radioactive Waste Handling.
All buildings and facilities on the SPC site were designed, constructed and inspected in accordance with the edition of the Uniform Building Code (UBC) current at the time of construction, the City of Richland Municipal Code, plus any special requirements as may have been dictated by their intended use. Unless otherwise indicated, the facilities 2
were all designed to withstand UBC Zone ll seismic loading and 20 lb/ft windward pressure.
AMENDMENT APPUCATION DATE:
P AGE No.:
August 6,1999 10-1 SPC-ND 3330 947 (R 1/07 92)
t Siemens Power Corporation - Nuclear Division eur.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 i
PART 11 - SAFETY DEMONSTRATION REV.
110.1.13 UF, CylinderRecertification Facility
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The location.of th'e Cylinder Recertification Facility is shown on Figure ll - 10.1. The f
building is a pre-engineered metal building 30 X 60 X 14 ft sloped eave height. The building is constructed with a sealed, insulated exterior-interior metal wall sandwiched j
constructed system that maintains pressure of not greater than negative 0.05 inch, i
j water gauge, with all doors closed when exhausting 500 cfm of air. The floor slab was j
made of 3000 psi concrete and designed for 250 psf.
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l The Recertification Facility will be used to hydrostatically test, internally inspect, f
I measure wall thickness and leak test Model 30 B cylinders that have been washed in j
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' ; another facility (the UO Building) to remove the UF " heel" that remains in the cyiinder i J
after the contents of the cylinder have been evacuated. The facility will be capable of i I
certifying 11 cylinders at a time.
10.1.14 Waste Storane Facility The location of the Waste Storage Facility is shown on Figure 11 - 10.1. The pad is an I i
asphalt pad 45 X 60 ft with a pre-engineered - metal 3-sided building l l
30 X 30 X 16 ft. sloped eave height centered on one side of the pad. The exterior walls are 26 gauge sheet metal and the roof is 24-gauge sheet metal.
The storage pad is used for the storage of containerized solid wastes classified as low-i level radioactive, chemically hazardous, or ' mixed low-level radioactive / chemically hazardous.
Ii 10.1.15 Fuel Services Buildina The Fuel Services (FS) Building is a 7,800 ft' office building, and a 7,200 ft processing building combined into a single facility. The footprint of the first and second floors of j the facility are shown on Figures 11-10.39 and ll-10.40, respectively.
The office building portion of the facility is a two-story building constructed of concrete masonry units (CMU). The poured in-place floors are of 3,000 psi concrete designed for 250 psf. The inner sides of all exterior walls are insulated and covered with fire-rated gypsum board. The gypsum panel joints are taped and sealed, and the interior surfaces are suitably painted. The interior partitions throughout the building are either CMU or fire-rated gypsum ~ board. The roof is steel deck plates supported on steel trusses, covered on both topside and underside with insulation, and a single-ply "Trocal" roof system.
. AMENDMENT APPLCATON DATE:-
PAGE NOa August 6,1999 10-11a SPC ND:3330 947 (R-1/07'921
J Siemens Power Corporation - Nuclear Division EMF 2
- SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART 11 - SAFETY DEMONSTRATION.
nsv.
l The process area of the facility is a single-story building with two different roof heights.
The exterior walls are constructed of 10-inch thick, pre-insulated CMU sealed on the interior and exterior against moisture and air leakage; The interior partitions throughout the building are either concrete block or fire-related gypsum board. The roof height over the Contaminated Equipment Room (Room 926, see Figure 11-10.39) is approximately 19 feet in order to allow a 12-foot hook height for the 2-ton bridge crane.
The roof over the remaining process portion is approximately 12 feet high such that a i
- ceiling height of 10 feet can be maintained. The roof is steel deck plates supported on steel trusses, covered with insulation, and a single ply "Trocal" roof system.
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AMENDMENT APPLICATION DATE:
PAGE NO.:
August 6,1999 10-11 b SPC-ND.3330.947 (R 1/07/92) j
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Siemens Power Corporation - Nuclear Division EMF.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART 11 - SAFETY DEMONSTRATION REV.
l The K66 supply fan is interlocked so that a loss of exhaust duct flow (exhaust fan failure) or a signal from the exhaust duct heat detector will shut down the K66 air supply system.
An automatic visual alcrm is activated when the recirculation system is inoperable.
10.3.13.4 HEPA Filter Bank l The final HEPA filters are enclosed in a sheet metal housing that, in turn, is mounted j on structural steel legs fastened to a concrete slab. The HEPA filters are rated at 1000 ft*/ min at one-inch water gauge pressure drop and are mounted in welded steel frames.
Continuous air samplers are installed downstream of the filter bank. Visual indicators l
for reading the pressure drop across the filters are permanently installed, and means i
are provided for in-place DOS testing.
The HEPA filter medium is 100% meisture-resistant fiberglass, pleated over ccrrugated l
separators and sealed in fire-resistant plywood frames. The individual filters are certified to remove 99.97% of 0.3 micron particles and meet or exceed Military l
j Specification MIL-F-51079.
10.3.14 Fuel Services (FS) Buildina HVAC System The FS Building has three independent HVAC systems. The two-story, non-nuclear i portion of the facility is served by two standara, commercial-type HVAC systems. The l
l single story process / service area portica of the facility is served by partially recirculated air, a downflow supply air system (K51) and a two-stage, HEPA-filtered exhaust system i
I (K52). A simplified schematic diagram of the K51 and K52 process area HVAC systems is furnished in Figure 11-10.41.
I 10.3.14.1 K51 Air Supply System I The K51 air supply system provides approximately 10,500 ft'/ min of air to the process and service areas of the facility. Approximately 4,200 ft / min of air is recirculated from 3
the service area to reduce thermalloads during normal operations. The service area i
includes the Electronics Shop, Storage Spare Parts,_and related areas-where _
radioactive contamination is not present. The process area includes the Machine Shop, Evaporate Pit, and change rooms. This area is supplied with approximately 6,300 ft3/ min of air and is naintained at a negative pressure to atmosphere and the adjacent office and service areas. Supply air is introduced form diffusers in ther upper part of the room and exhaust air is removed through process hoods or HEPA filter boxes located near floor level.
' AMENOMENT APPUCATION DATE:
l PAGE NO.:
August 6,1999 l
10-50b l
SPC-ND 3330 947 ;R*0792)
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F-~
- Siemens Power Corporation - Nuclear Division -
eup.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART ll-SAFETY DEMONSTRATION asy.
10.3.14.2 K52 Air Exhaust System All air supplied to the area, as described above, plus infiltration (approximately 6,900 ft*/ min), is exhausted through the K52 exhaust system. The double HEPA filter arrangement in this system consists of the final HEPA filter bank and individual or smaller filter banks of prefilters and HEPA filters located in the area exhaust ducts or process equipment served.
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l j The K52 system exhaust air passes through a duct air monitor (measures airfiow -
j p quantities), the final HEPA filter bank, energy recovery coil, the exhaust fan, and is discharged form a stack located on grade adjacent to the building. The stack extends j 17 feet above the roof of the process area, or 35 feet above ground elevation.
l 10.3.14.3Systems Controls i
The HVAC systems are controlled with temperature, pressure, and flow sensors i
1 actuating valving and damper positions to hold temperature, pressures, and pressure differentials constant in the various building areas. The K51 supply air system is i
interlocked with the K52 exhaust system to prevent operation of the K51 supply air I
system without the K52 exhaust system operating. Pressure sensors are provided for damper control to maintain a negative pressure (minimum -0.05 inch water gauge) in the process areas relative to atmosphere and the adjacent service and office areas.
I Automatic audio and visual alarms are activated when any supply or exhaust system i
, upset occurs. Pressure differential indicating devices and airflow quantity meters are j
, located in the controlled zones and/or on the main HVAC panel to provide system and l
zone operating conditions. Air samplers are located upstream and downstream of the j
final HEPA filters.
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A rise or fall of K51 supply duct static pressure, beyond preset limits, will automatically deenergize the K51 supply fan and activate alarms on the main HVAC panel.
i An alarm signal from the exhaust duct heat detector will automatically deenergize both the K51. supply and K52 exhaust fans and activate signals on the main HVAC panel as well as the building fire alarm system.
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i AMENDMENT AP01.tCATION DATE; PAGE NOc i
August 6,1999 10-50c SPC NO:3330 947 (R-907/92)
L Siemens Power Corporation - Nuclear Division aus.2 SPECIA,L NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 PART 11 - SAFETY DEMONSTRATION REV.
l 10.3.14.4 Fin'ai Filter Bank l
The final filter bank is encased in a prefabricated sheet metal housing that, in turn, is fastened to a concrete slab. HEPA filters rated at 1000 ft'/ min at 1-inch H2O pressure drop are mounted in welded steel frames. The HEPA filter medium is 100% moisture-resistant fiberglass, pleated over corrugated separators, and sealed in fire-resistant plywood frames.' The individual filters are certified to remove 99.97% of 0.3 micron particles and meet or exceed Military Specification MIL-F-51079. The final filter bank is j tested in-place to be 99.95%(minimum) efficient for 0.8 micron DOS cold aerosol.
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AMENOMENT APPUCATION DATE:
PAGE NO.:
August 6,1999 10-50d SPC ND:3330 947 (R-1/07/92)
/
SiemenS Power Corporation.- Nuclear Division ew.2 SPECIAL-NUCLEAR MATERIAL LICENSE NO, SNM-1227, NRC DOCKET NO. 70-1257
/
PART ll-SAFETY DEMONSTRATION REV.
l ll-10.33 SPC Site General Arrangement Dry Conversion First Floor 11-10.34 SPC Site General Arrangement Dry Conversion Second Floor 11-10.35 SPC Site General Arrangement Dry Conversion Third Floor 11-10.36
. SPC Site General Arrangement Dry Conversion Fourth Floor 11-10.37
. Dry Conversion Simplified Air Flow Diagram ll-10.38 UFe Cylinder Recertification Facility Ventilation System 11-10.39 SPC Site General Arrangement Fuel Services Building First Floor 11-10.40 SPC Site General Arrangement Fuel Services Building Second Floor 11-10.41 Simplified Schematic HVAC System - FS Building l
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AMENDMENT APPLCATON DATE:
PAGE NO.:
August 6,1999 10-71 i
SPC-NO:3330 947 (R-1/07'92)
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