ML20199E813
| ML20199E813 | |
| Person / Time | |
|---|---|
| Site: | Framatome ANP Richland |
| Issue date: | 12/23/1997 |
| From: | SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER |
| To: | |
| References | |
| NUDOCS 9802020253 | |
| Download: ML20199E813 (78) | |
Text
{{#Wiki_filter:' _- - ---- - --------w (N p/-W,jy (y s DOCUMENT REVISION INSTRUCTION SHEET PAGe - OF 1 1 EMF 2 DOCUMENT NUMBER: DOCUMENT TITLE: SiemenS Power Corporation - Application for Renewal of Special Nuclear Material License No, SNM-1227 b I 39 DOCUMENT REVISION: IDENTIFICATION REMOVE INSERT (1.E., SPECIFICATION, DRAWING, PROCEDURE, ETC.) PAGE(S) REVISION PAGE(S) REVISION Cover Sheet 38 39 Distribution 38 39 Table of Contents l-vi 38 1-vi 39 Chapter 1 1-10 36 1-10 39 { } Chapter 4 4-17 37 4-i ! 39 Chapter 10 10-soa & 10-50b 39 I' I Lm k. t 6 gD~ J l C v v 5.7. q y gg 9002020253 971223 PDR ADOCK 07001257 i C PDR l IF THE SPECIFICATIONS OR PAGES ARE ONLY REMOVED AND NOT REPLACED, PLACE DASHES IN THE INSERT COLUMNS IF THE SPECIFICATIONS OR PAGES ARE ONLY ADDITIONS (NO REPLACEMENTS), + PLACE DASHES IN THE REMOVE COLUMNS. SPC ND 4122.011 (R 2/10/92)
.o O EMF 2, Rev. 39 Issue Date: 12/23/97 Application for Renewal of Special Nuclear Material License No. SNM 1227 (HRC Docket No. 70-1257) O December 1997 O
SiernenS Power Corporation - Nuclear DiviSlon eur.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 70-1257 { TABLE OF CONTENTS REv. I '40 I l i ! CHAPTER 1 - STANDARD CONDITIONS AND SPECIAL AUTHORIZATIONS s 1.1 Corporate Information................. 11 1.2 Site Location............................... 1-1 1.3 License Number and Period of License...... 1-2 1.4 Possession Limits................................ 1-2 1.5 Authorized Activities................ 1-2 i 1.6 Exemptions and Special Authorizations....,........................, 1-2 i CHAPTER T.-ORGANIZATION AND ADMINISTRATION 2.1 Organizational Responsibilities and Authority........................ 2-1 2.2 Personnel Education and Experience Requirements............ .. 2-11 2.3 Safety Review Committees........................................,................. 2-14 2.4 Trainin g..................................................................... 2-16 2.5 Operating Procedures, Standards and Guides.............................. 2-18 2.6 O Configuration Control and Maintenance / Calibration of Safety Related E q uip m e nt................................. ............................2-18 h 2.7 Internal Audtts and Inspections.......................................... 2-19 2.8 investigations and Reporting of Reportable incidents................. 2-21 i 2.9 R e co rd s.................................... 2-22 CHAPTER 3 - RADIATION PROTECTION I 3.1 Administrative Requirements............. 3-1 3.2 Technical Requirements.................... 3-2 APPENDIX A..... 3-16 CHAPTER 4 - NUCLEAR CRITICALITY SAFETY 4.1 Administrative Practices..................... 4-1 4.2 Technical Practices.... 4-5 CHAPTER 5 - ENVIRONMENTAL PROTECTION 5.1 Effluent Control....... 5-1 5.2 Environmental Monitoring.. 5-5 CHAPTER 6 - SPECIAL PROGRAMS 6.1 Proprietary Information...... 6-1 6.2 Occupational Safety.... 6-1 6.3 Emergency UJlities...... 6-2 6.4 Radioactive Waste Management.......... 6-2 p 6.5 UF. Cylinders.......... 6-3 V4 AMENDMENT APPLICATION DATE; PAGE NO.: December 22,1997 i SPC-ND.3330 947 (R UO7/92)
l Siemens Power Corporation - Nuclear Division eur.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 I i TABLE OF CONTENTS REV. l L 39-- J , CHAPTER 7 - DECOMMISSIONING PLAN i l = i 7.1 Decommissioning Plan.... 7-1 l 7.2 Decommissioning Cost Estimate., 7-1 7.3 Decommissioning Funding Plan... 7-1 CHAPTER 8 - RADIOLOGICAL CONTINGENCY PLAN.. 8-1 CHAPTER 9 - GENERAL INFORMATION 9.1 Corporate Information... 9-1 1 9.2 Financial Qualification....... 9-1 9.3 Summary of Operating Objective and Process.. 9-1 9.4 Site Description............ 9-3 9.5 Location of Buildings On-Site.. 9-4 9.6 Maps and Plot Plans..... 9-4 i 9.7 License History. 9-5 APPENDIX A... 9-12 CHAPTER 10 - FACILITY DESCRIPTION 10.1 Plant Layout..... 10-1 10.2 Utilities and Support Systems.....-.,. 10-12 i 10.3 Heating. Ventilation, and Air Conditioning (HVAC). 10-22 10.4 Radioactive Waste Handling... 10-51 i 10.5 Fire Protection... _..... 10-64 10.6 Criticahty Accident Alarm System. 10-67 i APPENDIX A.. .10-115 CHAPTER 11 -ORGANIZATION AND PERSONNEL 11.1 Organizational Responsibilities........ 11-1 11.2 Functions of Key Personnel........_, 11-1 11.3 Education and Experience of Key Personnel. 11-1 11.4 Operating Procedures. 11-47 11.5 Training.. 11-47 i 11.6 Changes in Facilities and Equipment. 11-48 9 AMENOMENT APPLCAf0N DATE. PAGE No.: December 22,1997 ii SPC ND 3330 947 (R 1.07S2)
SiemenS Power Corporation - Nuclear DiviSlon eur.2 /' SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 l 4 i TABLE OF CONTENTS ! REV. l t '_10 i CHAPTER 12 - RADIATION PROTECTION i .l 12.1 Prog ra m.............................. 12-1 12.2 Posting and Labeling.................................... 12-1 ! l 12.3 Intemal and Extemal Radiation - Personnel Monitorin 12-1 l Radiation Surveys.............................. g........... 12.4-12-3 12.5 Radiation Safety Training...........,.......................... 12-3 l 12.6 Reports and Records................. 12-4 i 3 i 12.7 Instruments..,.............. 12-4 12.8 Protective Clothir 3....................................... ~....... 12 5 12.9 Administrative Cutrol Levels (including Effluent Control).... 12 5 12.10 Respiratory Protection................. 12 7 12.11 Occupational Exposure Analysis.................................. 12-8 12.12 Measures Taken io implement ALARA.......,..................... 12 9 12.13 Bioassey Program............................ 12-9 4 12.14 Air Sampling and Intemal Exposure Progre :....................... 12-10 i 12.15 Surface Contamination....................................... 12-12 APPENDIX A....... 12-i4 AP P E N DIX B............................................ 12-81 CHAPTER 13 - ENVIRONMENTAL SAFETY RADIOLOGICAL & NONRADIOLOGICAL i 1. 1 Extemal Radiation............ 13-1 13.2 Gaseous Effluents..............,.............. 13-1 ! 13.3 Liquid Effluents............................. 1 j 13.4 Groundwater.............. 13-2 I 13.5 Field Sampling................................ 13-4 l CHAPTER 14 - NUCLEAR CRITICALITY SAFETY i 14.1 Administrative Practices..... 14-1 14.2 Technical Practices................... 14-35 14.3 References................... 14-44 CHAPTER 15 - PROCESS DESCRIPTION AND SAFETY ANALYSIS 15.1 U O B uilding....................... 15-1 2 15.2 Speciality Fuels (SF) Building. .15-113 15.3 Engineenng Laboratory Operations (ELO) Building... .15-130 15.4 Warehouses.. .15-145 CHAPTER 16 - ACCIDENT ANALYSES...... 16-1 b 'd ; AMENOWENT APPLCATON DATE: PAGE NO.: l December 22,1997 iii SPC-NO.3330.947 (R.90742)
Siemens Power Corporation - Nuclear Division eur.2 SPECIAL NUG EAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 70-1257 TABLE OF CONTENTS l REV-l !w LIST OF TABLES i I i Table Paae l1.1 Specific Locations of Authorized Activities. 1-7 l3.1 Restric'ed Area Airbome Radioactivity Concentration Aed.on Levels and Actions......... ?-12 l3.2 Radiation Safety Instrument Capabilities.. _...... 3-13 i l3.3 Routine Urinalysis Program Action Levels and Actions.. 3-14 '3.4 Routine Lung-Counting Program Action Levels and Actions.... 3-15 l-4.1 System Criticality Safety Controlled Parameters.. 4 16 5 l 4.2 Safety Factors for Homogeneous Single Units. 4-32 l 4.3 Safety Factors for Heterogeneous Single Units.. 4-33 l5.1 Boundary Concentration Action Levels. 5-7 l5.2 Total Boundary Action Levels.._._......... 5-8 i l 5.3 Liquid Effluent Action Levels and Actions.. 5-9 ! l-7.1 Plant Decommissioning Cost Estimate Summary.. 7-2 i k 11-9. 1 Corporate information....... 9-6 i ll-10.1 Ammonia Recovery Major Equipment... 10-68 l 11-1 0. 2 LUR Process Equipment.... 10-C9 i 11-1 4. 1 Critical Parameters for U Compaunds Limited to 5 WT.% Enrichment.. 14-8 ll-14.2 Homogeneous & Heterogeneous Minimum Critical & Safe Masses.. 14-9 11-1 4. 3 Expressions for Geometnc Buckling in Terms of Actual Dimensions & Extrapolation Distances......._.._........... 14-10 11-1 4.4 Compare 25 Keno Va RSIC Tect Cases with SPC HP Work Stations.... 14-14 11-1 4. 5 PNL Critical Experiment Data on Clusters of 4.29 Wr% U22s Enriched UO Rods in Water.......... 14-18 2 11-1 4. 6 PNL Critical Experiment Cases Calculation Results with 16-Group, 27-Group,218-Group, and 123-Group Cross-Sections.. 14-20 11-1 4. 7 Properties of 2.46% Enriched UO Fuel Rods.. 14-24 2 11-1 4. 8 Certified Chemical Analysis of 8,C... 14-24 11 14.9 B&W Critical Expenment Cases Calculation Results with 16-Group Cross-Sections. 14-25 O AMENOMENUNON WE: ~ December 22,1997 iv SPc-ND.3330 947 (R 1/07/92)
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SiemenS Power Corporation - Nuclear Division eur.2 (3 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227 NRC DOCKET NO. 70-1257 \\ 1 'w/ i I f, I TABLE OF CONTENTS REV. f l , 39 I LIST OF FIGURES l Fiaure Paae l2.1 Organization Chart.................. 2-24 l-2.2 Organization Chart - Safety, Security, & Licensing. 2-25 ' l2.3 Approval and Responsibility Matrix.... 2-26 1 Il-5.1 Field Sample Station Locations.......... 5-10 l l 5.2 Lagoon Test Well Locations...... 5-11 1 119.1 Organization Chart................. 9-7 11-9. 2 Richland Area and SPC Engineering and Manufacturing Facility. 9-8. ll-9.3 Land Use Within 50-Mile Radius of SPC Site - Recreation. 9-9 i 119.4 Land Use Within 50-Mile Radius of SPC Site - Agriculture.... 9-10 11-9.5 Land Use Within 50-Mile Radius of SPC Site - Urban.. 9-11 , 11-1 0. 1 SPC Site General Arrangement.................. 10-72 1110.2 Plant Equipment Layout Specialty Fuels Building. 10-73 C' j ll-10.3 Plant Equipment Layout UO Building.... 10-74 2 !,"s, 11-10.4 Plant Equipment Laynut UO Building..... 10-75 : 2 /' 1L10.5 Plant Equipment Layout UO Building....... 10-76 2 ll 10.6 Plant Equipment Layout UO Building.,... 10-77 2 11-1 0. 7 Plant Equipment Layout UO Building..... 10-78 i 2 i 11-1 0. 8 Plant Equipment Layout UO Building., 10-79 l 2 ! 11 10.9 Plant Equipment Layout UO Building........ 10-80 t i 2 11-10.10 Plant Equipment Layout UO Building. 10-81 i i 1 2 11-10.11 Plant Equipment Layout UO Building.. 10-82 : 2 11-10.12 Plant Equipment Layout UO Building....... 10-83 2 ll-10.13 Plant Equipment Layout UO Building... 10-84 2 11-10.14 Plant Equipment Layout UO Building. 10-85 2 i 11-10.15 Plant Equipment Layout UO Building.. 10-86 2 11-10.16 Plant Equipment Layout UO Building.. 10-87 2 il-10.17 Plant Equipment Layout ELO Building. 10-88 11-10.18 Horn Repids Road Site and Arrangement - Fire & Water Supply.. 10-89 Il-10.18a Hom Rapids Road Site and Arrangement - Sanitary Drain...... 10-90 11-10.19 Simplified Schematic HVAC System - SF Building SWUR Facility.- 10-91 11-10.20 Simpirried Schematic HVAC Systcm - SF Building Prod.sction Facility. 10-92 Il-10.20a NAF Curnace Facility HVAC System Simplified Schematic...... 10-93 11-10.21 Simplified Schematic HVAC System - Original UO Building. 10-94 2 Il-10.21a Simplified Schematic HVAC System - Analytical Lab UO F ilding. 10-95 2 11-10.22 Simplified Schematic HVAC System - UO Building Line 2 Conversion 2 Are a.............. 10-96 ll-10.23 Simplified Schematic HVAC System - Main (South) Addition. 10-9'r /~N \\ '%.J' ^ " " ~ " December 22,1997 v SPC.ND:3330 947 (R 1/07S2)
1 Siemens Power Corporation - Nuclear Division eup.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 701257 TABLE OF CONTENTS I REV l i i I 3 9._ _, j List OF FIGURES (Cont.d) FiauLq Paae ll 10.24 Simplified Schematic HVAC System - U 0 Facility.. 10-98 3 1110.25 Simplified Schematic HVAC System - ELO Building..... 10-99 11-10.26 Simplified Schematic HVAC System - ELO Building Addition...- ... 10-100 ; 11-10.27 Simplified Schematic HVAC System - Contaminated Clothing Laundry Fa cility........... ..... ~..... _...... . 10-101 Il 10.27a Simplified Schematic - SWUR Incinerator Shroud Cooling System. .10-102 l ll 10.27b Lagoon Uranium Recovery / Solids Processing Facility Ventilation I System Flow Diagram. .. 10-103 11-10.28 Plant Equipment Layout - ARF Building..... . 10-104 i ll-10.29 Ammonia Recovery Waste Management Facility Engineering Flow Diagram.. .1G-105 ll-10.29a Flow Diagram Lagoon SA - Sewer lon Exchange i c.,,,ct. . 10-106 l ll-10.30 Plant Equipment Layout - LUR Facility........ .10-107 1110.31 Engineering Flow Diagram - LUR Production Facility........ .10-108 ll-10.32 Fire Alarm System.... .. 10-109 11-10.33 SPC Site General Arrangement Dry Conversion First Floor.. .. 10-110 l 1110.34 SPC Site General Arrangement Dry Conversion Second Floor. .10-111 11-10.35 SPC Site General Arrangement Dry Conversion Third Floor. . 10-112 i 11-10.36 SPC Site General Arrangement Dry Conversion Fourth Floor..., .10-113 + ll 10.37 Dry Conversion Simplified Air Flow Diagram. .10-114 1113.1 Monitoring Well Description... 13-5 i ll-14.1 PNL Critic # Experiment Layout (Reference 6). . 14-17 j tl-14.2 B&W Critical Experiment Layout.. 14-23 1 i j l l l l i i l I l !h I ussoussT amcaton oam ^ " " ' D M Q 1997 W SPC ND.3330 947 (A-1/07/92) __-______-__--__--_---__________________-____-____-_____-_____-____________________-_-_______________________A
' 4 SiemenS Power Corporation - Nuclear Division eur.2 /N SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 70-1257 { l PART I-LICENSE CONDITIONS REV. l l 36 l r I TABLE l 1.1 Specific Locations of Authorized Activities (Cont.d) i l Location SNM Audiorized Activity i i ! Laundry Facility Uranium Compounds (up to Cleaning of contaminated 5 wt% U 235) protective clothing and equipment. UF. Cylinder Storage UF. (up to 5 wt% U 235) Outside storage of UF, Areas cylinders (full and empty). Packaged Fuel Uo, (up to 5 wt% U 235) Outside storage of fuel packed i Storage Areas for shipment; the transport containers are closed, sealed and properly labeled for shipment. 7 ('-}, Packaged Waste Uranium Compounds (up to Outside storage of Storage Areas 5 wt% U-235) contaminated materials i i (including low level waste and incinerator ash) wF h are I packaged, sealed, labeled and l externally free of contamination. i Process Chemical Uranium Compounds (up to Transfer, mixing, sampling, Waste Storage 5 wt% U-235) storage and solar evaporation 4 Lagoon System of contaminated liquid wastes. Rotention Tanks Uranium Compounds (up to Interim sto: age of potentially 5 wt% U 235) contaminated liquid wastes. I High Uranium Solids Uranium Compounds (up to Transfer of uranium bearing Pond 5 wt% U-235) solids, leaching for uranium recovery. 1 Solids Trench Uranium Compounds (up to Transfer and storage of 5 wt% U-235) contaminated solids awaiting leaching or burial, The locations described in this table are shown on the site plan, Figure 11-p)., 10.1 it weotNT mtc4 von oart: October 28,1996
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1-9 SPC ND 3330 947 (R-It07/92)
e i l l } Siemens Power Corporation - Nuclear Division Eur2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 701257 PART I-LICENSE CONDITIONS REV. t 39 i T ABLE l 1.1 Specific Locations of Authorized Activities (Cont.d) t Location SNM euthorized Activity Lagoon Uranium Uranium Compounds (up to Recovery of uranium ftom Recovery 5 wt% U-235) waste solutions. Ammonia Recovery Uranium Compounds hip to Removal and recovery of Facility 5 wt% U 235) ammonia from uranium contaminated liquid wastes. Lagoon SA IX Uranium Linuid Wastes tup Filtration and ion exchange of Process-ARF Building to 5 wt% U-235 and less uranium liquid wastes. than 140 gU/l concentrations in filters and resins) Any Permanent or Uranium solid waste (up to Sorting and compaction. Portable Building 5 wt% U-235) l having HEPA filtration and Isokinetic sampling. UFe Cylinder Uranium Compounds, solid Cylinder recertification Recertification and in water solution (up to activities, including hydrostatic Facility 5 wt% U-235) strength testing, wall thickness measurement, internal examination, and pressure testing. The locations described in this table are shown on the site plan, Figure Il-10.1 O ~ r aw a cutam carosoart pace e Augtist 4.1997 1-10 sPC ND 3330 947 (R ii0M2) 1I
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3g 2 >6 ? ~ m r3 l e y g UF, Cytoders X X X X y g-durmg cytmew 37 -4 wash w mc g recertification t-2E 6 MQ (D operatiorts (F mW N diameter oc less) Z' .o O mm' Vaporizadon X X Redundant devees prevent fissae q-chests (ADU solubon from eveeedog a safe O M g* 2 proces*J lines) geometry inside the vaporization g* h3 ttests. g Vaporization X No creditAe pathway exists to get b FO chetts and fissile solution into the dry O y 2 autoc! aves (dry conversion vaporization chest or g -m e) autocieves Z 3 tktfavorabie X X X O l geometry g j scrubber o systems / liquid Q a 5 I separators Xm m -4 f Z a O l N I b 4 9 ... ~ -. ~.. -.. _ ~ _. _ _.. _. _ -.... g E U3 fT1 e OA Nr a 7 i __ I - = - = - - - - - - ^
f _ _. - ~ _, g _.. O ? mO3 E >O l 3 M 1 Totate i 4 8 (Cont'af ) 7 T b C 5 Cout*Ofs[ tai COrdiflot TYPE fuSCt#Sstori OF AtiY SrfCtAl. O gI l S COtil1101S llSED / AfX):IOtaAt r- ? EXPT Ati4TIOta OF CotJIflot TYPE ITI O l i a 33 O l GEO VOL FliA f4AA CCtf CCM MCtl MC&; PPC AHA SPA o, I s I 2 yO -4 O Cyllsidsical my 2 c. Tenh a, Fittere yO O e,xt oihe, f I U h Equipment y f-rr i,5 < a r nondnel X x tsses may inchsde dissonstion or g g7 lD pesets. 7 mC g ZQ r-Cyliruhtcel tes>hs, titless, asul othes g-~ CD CD 2 03 eqidgwnevilless timen uds aEmenslost m l 0) ese also oppsopstalety spaced to Z Z [ Qh l essaue needson hdefections wt fi othes espdpmesd will sesidt be g g 5, ecceptelite h, Folkee of geometsy g zE os spacing Isetween limest gdoces n! z gO3 espdgwnesil is contso5ed Iny stes(pse O a -4 to 5 9 25' nominal X X t# sea ese liasilled to liomogeneoans y'O O 80. sohdlons / sbisslos sesos es t80, 7 powdess,410f, azul alm 1 (/) 7 T Cyllsulsical lenh s, itfloss. asuI all.es O eslidpmesti less lisen flels attiveevisitwo O l ese etso appsogelefely spaced to O esseus need.oss Intesscitoets wtifs [ Q ,n f cities eqidgwnent wtB sesidt les 7 ecceptalde k,, fasius of geswnetsy Ad os spechig between fieod pieces of g l eqidpsnesil is c.osdsolled t>y deskjn Z l 9 p I g g "e y O o E to -P v' m EM "E m a to e e 0 0.. L
SiemenS Power Corpontion - Nuclear Division Eur2 SPECIAL NUCLEAR MATE AIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART ll-SAFETY DEMONSTRATION nev. 39 l 10.3.13 UF, Cvlinder Recertification Facility (CRF) HVAC System I The general features of the CRF HVAC system include. a combination of a once-threugh airflow and recirculation supply system (K66) and a double HEPA filtered exhaust system (K67) A simplified schematic diagram of the HVAC system is shoven l in Figure 1110.38. 10.3.13.1 K66 Air Sunolv and Recirculation System The K66 air supply and recirculation system ;cpplies approximately 450 ft'/ min, of j l l outside air and also recirculates approximately 2350 ft'/ min. of building air. l Recirculated air is passed through a roughing filter and a single HEPA filter with an ; installed efficiency of 99.95% for 0.8 micron DOS cold-generated aerosol. Provision I .is made in the K66 recirculation system for continuous alpha radiation monitoring of i s [ recirculated air upstream of the HEPA filter bank. The alpha air monitor is set to alarm j and annunciate when alpha activity exceeds 40 DAC-br. + cQ ! 'g 10.3.13.2 K67 Air Exhqust System Air supplied to the CRF, plus infiltration, is exhausted through the K67 exhaust system. The double WEPA filter arrangement in this system consists of the final HEPA filter bank and upstream primary HEPA filter bank. The K67 system exhaust air (approximately 950 ft'/ min.) passes from the two stage HEPA filter bank through the main exhaust fan, past a uuct air monitor (measuring i airflow quantities) and is discharged from a stack extending 20 ft above ground on the south side of the building. The K67 exhaust system has one fan which is connected to normal power. All final HEPA filters are in-place tested to be 99.95% minimum efficient for O.8 micron DOS cold-generated aerosol. 10.3.13.3 System Controls i The HVAC systems are controlled with temperature, pressure and flow sensor actuating valving and damper positions to hold temperatures, pressures, and pressure ! differentials constant in the various building areas. The K66 sup?ly air system is interlocked with the K67 exhaust system to prevent operation of the K66 supply air
- system without the K67 exhaust system operating. Pressure sensors are provided to
! maintain a minimum negative differential pressure of 0.05 inch water gauge in the building relative to the atmosphere. AMENOMENT APPLCATON DATE-PAGE NO.: August 4,1997 10-50a l sPC-ND.3330 947 (R-1/0712)
SiemenS Power Corporation - Nuclear Division Eur-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227. NRC DOCKET NO. 701257 { PART 11 - SMtiTY DEMONSTRATION REV. 39 i 1 The K66 supply fan is interlocked so that a loss of exhaust duct flow (exhsust fan failure) or a signal from the exhaust duct heat detector will shut down the K66 air i supply system. i An automatic visual alarm is activated when the recirculation system is inoperable. l 10.3.13.4 HEEA Filter Bank i The final HEF, ters are enclosed in a sheet metal housing that, in turn, is mounted on structural sk si legs fastened to a concrete slab. The HEPA filters are rated at i 1000 ft'/ min at one-inch water gauge pressure drop and are mounted in welded steel i frames. Continuous air samplers are installed downstream of '.he filter bank. Visual i indicators for reading the pressure drop across the filters are permanently installed, ! and means are provided for in-place DOS testing. 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.
I l O AMG.NOMENT APPLCATION DATE: PAGE NOa August 4,1997 10-50b sPC-ND 3330 947 (R-1/07/92)
~.-. 4 ( EMF 2 Revision 39 APPLICATION FOR RENEWAL OF SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227 (NRC DOCKET NO. 70 1257) Distribution D. L. Belt B. F. Bentley (4) J. B. Edgar B. N. Femreite. R. L. Feuerbacher J. W. Fredericks s S. F. Gaines W. G. Keith D. C. Kilian - L. J. Maas C D. Manning C. S. Powers T. C. Probasco A. Reparaz l. J. Urza. 4 R. E. Vaughan C. A. Ward L. D. Weaver USNRC/M.F. Weber (6) USNRC RIV WCFO/C.A. Hooker DOH/L. Wainhouse [ Document Control (5) 1: 4 i G d
[ + DOCUMENT REVISION INSTRUCTION SHEET PAGE OF f^3 EMF 2 DOCUMENT NUMBER: SiemenS Power Corporation - Application for Renewal DOCUMENT TITLE: of Special Nuclear Material License No. SNM-1227 39 DOCUMENT REVISION: lOENTIFICATioN REMOVE INSERT (1 E., SPECIFICATION. DRAWIN
G. PROCEDURE
, ETC.) PAGE(S) REVISION PAG 2(S) REVISION Cover Sheet 38 39 Distribution 38 39 Table of Contents i-vi 38 i-vi 39 Chapter 1 1-10 36 1 10 39 ) { } Chapter 4 4-17 37 4-17 39 Chapter 10 10 50a a 10-50b 39 ( V IF THE SPECIFICATIONS OR PAGES ARE ONLY REMOVED AND NOT REPLACED. + I PLACE DASHES IN THE INSERT COLUMNS. IF THE SPECIFICATIONS OR PAGES ARE ONLY ADDITIONS (NO REPLACEMENTS). + PLACE DASHESIN THE REMOVE COLUMNS. SPC ND 4122.011 (R-2/10/92) l
.= i a i J' EMF 2, Rev. 39 lssue Date 12/23/97 I Application for Renewal L. of Special Nuclear Materia; License No. SNM 1227 i (NRC Docket No. 701257) l i i g I~ t i l l December 1997 l l l. A i l i i-i 1
SiemenS Power Corporation - Nuclear Division EMF.2 ( SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 701257 i TABLE OF CONTENTS REv. 90 _ j. Enae i i - CHAPTER 1 STANDARD CONDITIONS AND SPECIAL AUTHORIZATIONS i 1.1 Corporate Information...................... 11 * [ 1.2 S ite Loca tio n........................................................1-1 1.3 License Number and Period of License..................................... 1-2 1.4 Pos sessio n Limits................................................................ 1-2 1.5 Authorized Activities........................................ 1-2 1.6 Exemptions and Special Authorizations...................................... 1-2 ; CHAPTER 2 ORGANIZATION AND ADMINISTRATION i 2.1 Organizational Responsibilities and Authority................................. 2-1 2.2 Personnel Education and Experience Requirements........................ 2-11 2.3 Safety Review Committees..................................................... Training..................................,.................................... i 2.4 2-16 i 2.5 Operating Procedures, Standards and Guides....... .........................,2-18 2.6 Configuration Control and Maintenance / Calibration of Safety Related E q u i pm e nt..........................................................................,.. 2 - 1 8 l \\ 2.7 Intemal Audits and Inspections....................................................... 2-19 i 2.8 investigations and Reporting of Reportable incidents.......................... 2-21 ! 2.9 R e co rd s.................................,,............................................ 2-22 l 3 t CHAPTER 3 - RADIATION PROTECTION { 3.1 Administrative Requirements..................................................... 3-1 3.2 Technical Requirements............................... 3-2 AP P E N D I X A...................................................................... 3-16. CHAPTER 4 - NUCLEAR CRITICALITY SAFETY 4.1 Administrative Practices................................................. 4-1 4.2 Technical Practices.............................................. 4-5 CHAPTER 5 - ENVIRONMENTAL PROTECTION 5.1 Effluent Control...... 5-1 5.2 ~ Environmental Monitoring.............. 5-5 CHAPTER 6 - SPECIAL PROGRAMS 6.1 Proprietary Information................. 6-1 6.2 Occupational Safety............. 6-1 6.3 Emergency Utilities....................... 6-2 6.4 Radioactive Waste Management....... 6-2 O 6.5 U F. Cylinde rs............................................. 6-3 \\N i i - AMENDMENT ApptCATION DATE-PAGE NO; December 22,1997 i i i SPC ND 3330 947 (R-1/07/92)
+ e SiemenS Power Corporation - Nuclear Division eur.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 t' i TABLE OF CONTENTS REV. I L ' 39 I i , CHAPTER 7 - DECOMMISSIONING PLAN i t 7.1 Decommissioning Plan...... 71 i 7.2 Decommissioning Cost Estimate. 7-1 7.3 Decommissioning Funding Plan. 7-1 . CHAPTER 8 - RADIOLOGICAL CONTINGENCY PLAN., 81 CHAPTER 9 GENERALINFORMATION i 91 Corporate Information.. 9-1 9.2 Financial Qualification....-................ 9-1 9.3 Summary of Operating Objective and Process. 9-1 9.4 Site Description............... 9-3 ! 9.5 Location of Buildings On-Site... 9-4 9.6 Maps and Plot Plans... 9-4 i 9.7 License History. 9-5 APPENDlXA. 9-12 CHAPTER 10 - FACILITY DESCRIPTION 1 l 10.1 Plant Layout.................. 10-1 10.2 Utilities and Support Systems........ 10-12 l 10.3 Heating, Ventilation, and Air Conditioning (HVAC).... 10-22 l 10.4 Radioactive Waste Handling.. 10-51 l i 10.5 Fire Protection........~...... 10-64 : 10.6 Criticality Accident Alarm System. 10-67 l i APPENClX A. .10-115 CHAPTER 11 - ORGANIZATION AND PERSONNEL 11.1 Organizational Responsibilities.. 11-1 11.2 Functions of Key Personnel.......... 11-1 11.3 Education and Experience of Key Personnel. 11-1 11.4 Operating Procedures. 11-47 11.5 Training.. 11-47 11.6 Changes in Facilities and Equipment. 11-48 91
- AMENDWENT APPLCATON DATE.
PAGE NO.: December 22,1997 ii SPC-ND 3330 947 (R-1/07/92)
o Siernens Power Corporation - Nuclear Division Eur.2 O SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 i t i TABLE OF CONTENTS REv. 4_ 0_ ' CHAPTER 12 RADIATION PROTECTION 12.1 P rog ra m..................,...................... 12-1 i 12.2 Posting and Labeling...................................., 12-1. 12.3 Intemal and Extemal Radiation - Personnel Monitoring....,.......... 12-1 { 12.4 R adiatio n S u rve ys............................................................. 12 3 12.5 Radiation Safety Training........... 12-3 12.6 Reports and Records...................................................... 12-4 ; 12.7 I rist ru me nts............................................. 12-4 12.0 Prote ctive Clothing.............................................................. 12-5 i i 12.9 Administrative Control Levels (including Effluent Control)....... 12-5 t 12.10 Res piratory Protection..........................................................,, 12-7 > 12.11 Occupational Exposure Analysis............................... 12-8 12.12 Measures Taken to implement ALARA.................................... 12 9 : 3 12.13 Bio a ss a y Prog ra m............................................................... 12-9 12.14 Air Sampling and intemal Exposure Program............................... 12-10 12.15 Surface Contamination....... ..............................................12-12 AP P E N DlX A.................................................................. 12-14 APPE NDlX B.......................... 12-81 O! V ll CHAPTER 13 - ENVIRONMENTAL SAFETY RADIOLOGICAL & NONRADIOLOGICAL 13.1 Exte mal Radiation............................................,..... 13-1 13.2 Ga seou s E tfluents............................................................ 13-1 13.3 Liq uid Efflue nts................................................................. 13-1 i i 13.4 G ro u n dwa te r.................................................................. 13-2 l l i 13.5 Fie ld S a m pli n g.......................................................... 13-4 i CHAPTER 14 - NUCLEAR CRITICALITY SAFETY 4 14.1 Administrative Practices.......... 14-1 14.2 Technical Practices..................................................... 14-35 i 14.3 References................. 14-44 CHAPTER 15 - PROCESS DESCRIPTION AND SAFETY ANALYSIS 15.1 U O B uilding................................. 15-1 2 15.2 Speciality Fuels (SF) Building........................ ...' 15-113 15.3 Engineering Laboratory Ope:ations (ELO) Building... . 15-130 15.4 Warehouset,... .15 145 1 CHAPTER 16 - ACCIDENT ANALYSES.,............ 16-1 i J AMENOMENT APPLIC.ATION DATE: PAGE NOc i, December 22,1997 iii SPC.ND 3330.90 (R UOW92)
4 SiemenS Power Corporation - Nuclear Division g r.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 i TABLE OF CONTENTS REV. l ' SQ w ) LIST OF TABLES i Table Paae l 1.1 Specific Locations of Authorized Activities.. 1-7 ! l 3.1 Restricted Area Airbome Radioactivity Concentration Action Levels and Actions............ 3-12 l3.2 Radiation Safety Instrument Capabihties............................... 3-13 13.3 Routine Urinalysis Program Action Levels and Actions....... 3-14 l 3.4 Routine Lung-Counting Program Action Levels and Actions. 3-15 ; 14.1 System Criticality Safety Controlled Parameters.................. 4-16 l-4.2 Safety Factors for Homogeneous Single Units......... 4-32 i l-4.3 Safety Factors for Heterogeneous Single Units.............. 4-33 15.1 Boundary Concentration Action Levels... 5-7 I-5.2 Total Boundary Action Levels............................. 5-8 l 5.3 Liquid Effluent Action Levels and Actions...... 5-9 l-7.1 Plant Decommissioning Cost Estimate Summary... 7-2 ll-9.1 Corporate Infom1ation.. 9-6 1 ll-10.1 Ammonia Pecovery Major Equipment...... 10-68 l 11 10.2 LUR Process Equipment... 10-69 ! 11-1 4. 1 Critical Parameters for U Compounds Limited to 5 WT.% Enrichment... 14-8 11-1 4. 2 Homogeneous & Heterogeneous Minimum Critical & Safe Masses. 14-9 ll-14.3 Expressions for Geometric Buckling in Terms of Actuai Dimensions & Extrapolation Distances. 14-10 11-1 4. 4 Compare 25 Keno Va RSIC Test Cases with SPC HD Work Stations... 14-14 ll 14.5 PNL Cntical Experiment Data on Clusters of 4.29 WT% U* Enriched UO Rods in Water........ 14-18 2 11-1 4. 6 PNL Critical Experiment Cases Calculation Results with 16-Group, 27-Group, 218-Group, and 123-Group Cross-Sections. 14-20 ll 14.7 Properties of 2.46% Enriched UO, Fuel Rods.. 14.'4 11 14.8 Certified Chemical Analysis of B.C..... 14-24 1114.9 B&W Critical Experiment Cases Calculation Results with 16-Group Cross-Sections.. 14-25 i wsuouent amccon out ipaceNo: December 22,1997 l iv SPC ND:3330 947 (R-tio7/92)
Siemens Power Corporation - Nuclear Division EMF 2 O) SPECIAL NUCLEAR MATERIAL LICENCE NO. SNM-1227, NRC DOCKET NO. 701257 !Uj t TABLE OF CONTENTS REV. { l 30 I c LIST OF FIGURES Eioure Paoe !I l2.1 Organization Chart................... 2 24 I l 2.2 Organization Chart - Safety, Security, & Licensing.. 2-25 i i 12.3 Approval and Responsibility Matrix..... 2-26 k l-5.1 Field Sample Station Locations....... 5-10 j I-5.2 Lagcon Test Well Locations...... 5-11 119.1 Org anization Cha rt............................................................. 9-7 119.2 Richland Area and SPC Engineering and Manufacturing Facility...... 9-8 i 11 9. 3 Land Use Within 50-Mile Radius of SPC Site - Recreation............ 9-9 : ll 9.4 Land Use Within 50-Mile Radius of SPC Site - Agriculture.... 9-10 119.5 Land Use Within 50-Mile Radius of SPC Site - Urban. 9-11 l , ll-10.1 SPC Site General Arrangement........................ 10-72 - 1110.2 Plant Equipment Layout Specialty Fuels Building..................... 10-73 ll 10.3 Plant Equipment Layout UO Building. 10-74 2 (~] 11 10.4 Plant Equipment Layout UO Building........... 10-75 2 ) 11-1 0. 5 Plant Equipment Layout UO Building... 10-76 \\y: 2 l 11-1 0. 6 Plant Equipment Layout UO Building........... 10 77 2 l lh10.7 Plant Equipment Layout UO Building.......... 10-78 2 ll 10.8 Plant Equipment Layout UO Building.. '10-79 i 2 ll10.9 Plant Equipment Layout UO Building....... 10-80 t 2 i 11-10.10 Plant Equipment Layout UO Building.......... 10-81 l 2 11 10.11 Plant Equipment Layout UO Building. 10-82 : 2 ll-10.12 Plant Equipment Layout UO Building......... 10-83 2 11-10.13 Plant Equipment Layout UO Building.................. 10-84 2
- 11-10.14 Plant Equipment Layout UO Building..........
10-85 ! 2 11-10.15 Plant Equipment Layout UO Building.......... 10-86 2 11-10.16 Plant Equipment Layout UO Building............. 10-87 ; 2 11-10.17 Plard Equipment Layout ELO Building.................... 10-88 11-10.18 Horn Rapids Road S;te and Arrangement - Fire & Water Supply. 10-89 Il-10.18a Horn Rapids Road Site and Arrangement-Sanitary Drain........ 10-90 11-10.19 Simplified Schematic HVAC System - SF Building SWUR Facility. 10-91 11-10.20- Simplified Schematic HVAC System - SF Building Production Facility.. 10-92 Il 10.20a NAF Furnace Facility HVAC System Simplified Schematic.. 10-93 11-10.21 Simplified Schematic HVAC System - Original UO Building.... 10-94 2 Il-10.21a Simplified Schematic HVAC System - Analytical Lab UO Building. 10-95 2 11 10.22 Simplified Schematic HVAC S Area....................................ystem - UO Building Line 2 Conversion 2 10-96 1110.23 Simplified Schematic HVAC System - Main (South) Addition. 10-97 A I i Y N AMENOMENT APPLCATON DATE: PAGENO.. i December 22,1997 v SPC-ND 3330 947 (R 1/07/92)
1 Siemens Power Corporation - Nuclear Division Eur.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 I i TABLE OF CONTENTS lREV. i i ' 39 - l LIST OF FIGURES (Cont.d) 4 i I ELquLe Pane 1 l Il 10.24 Simplified Schematic HVAC System U 0, Facility........ ...... 10 98 ! 3 i 1110.25 Simplified Schematic HVAC System ELO Building.............. 10 99 i ll 10.26 Simplified Schematic HVAC System - ELO Duilding Addition............10100 l 11 10.27 Simplified Schematic HVAC System Contaminated Clothing Laundry Facility...................-............................................... .. 10 101 i ll 10.27a Simplified Schematic - SWUR Incinerator Ghroud Cooling System.. 10 102 ! ll 10.27b Lagoon Uranium Recovery / Solids Processing Facility Ventilation i System Flow Diagram., ... 10 103 i ll 10.28 Plant Equipment Layout ARF Building......~............... ..... 10 104 1110.29 Ammonia Recovery Waste Management Facility Engineering Flow Diagram...........................................~............................10105 ll 10.29a Flow Diagram Lagoon SA - Sewer lon Exchange Project........ 10-106 ll 10.30 Plant Equipment Layout LUR Facility.......................................... 10-107 11 10.31 Engineering Flow Diagram LUR Production Facility....................10108 t 11 10.32 F i r e Al a rn ; 3 y st e m..................................................................... 10- 10 9 11 10.33 SPC Site General Arrangement Dry Conversion First Floor.....,......10110 1110.34 SPC Site General Arrangement Dry Conversion Second Floor.,........10111 11 10.35 SPC Site General Arrangement Dry Conversion Third Floor.........,. 10 112 i 11 10.36 SPC Site General Arrangement Dry Conversion Fourth Floor............10113 i Il 10.37 Dry Conversion Simplified Air Flow Diagram................................10114 i j ll 13.1 Monitoring Well Description........................... 13-5 ll 14.1 PNL Critical Experiment Layout (Reference 6)...................... 14-17 l ll-14.2 B&W Critical Experiment Layout......... ......... 14 2 3 j i i t i l i l i 9 i AMENDMENT APP (CATON DAtt: PAGE NO.: December 22,1997 vi sPc-NO 3330 947 (R-UQ7Sh
4 Siemens Power Corporation Nuclear Division guF.2 SPECIAL NUCLEAR MATERIAL LICENS5 NO. SNM 1227, NRC DOCKET NO. 701257 C[ PARTI LICENSE CONDITIONS
- nev, 36 TABLE l 1.1 Specific Locations of Authorized Activities (Cont.d)
Location SHM Authorized Activity l 1 ! Laundry Facility Uranium Compounds (up to Cleaning of contaminated .I 5 wt% U 235) protective clothing and equipment, i i i t i ~ UF. Cylinder Storage UF, (up to 5 wt% U 235) Outside storage of UF, ' Areas cylinders (full and empty). Packaged Fuel UO (up to 5 wt% U 235) Outside storage of fuel packed j Storage Areas for shipment; the transport containers are closed, sealed i and properly labeled for shipment. l b{ Packaged Waste Uranium Compounds (up to Outside storage of l l Storage Areas 5 wt% U 235) contaminated materials I i (including low level waste and } incinerator ash) which are cackaged, sealed, labeled and i i { externally free of contamination. l 1 , Process Chemical Uranium Compounds (up to Transfer, mixing, sampling, l ' Waste Storage 5 wt% U 235) storage and solar evaporation i Lagoon System of contaminated liquid wastes. Retention Tanks Uranium Compounds (up to Interim storage of potentially 5 wt% U 235) contaminated liquid wastes, High Uranium Solids Uranium Compounds (up to Transfer of uranium bearing { Pond 5 wt% U 235) solids, leaching for uranium i recovery. i Solids Trench Uranium Compounds (up to Transfer and storage of 5 wt% U 235) contaminated solids awaiting leaching or burial. .H The locations described in this table are shown on the site plan, Figure ll-4 )l 10.1 .j autaswt amcatow oart: October 28,1996 Pet ma 19 . OM7 @' A b
SiemenS Power Corporation - Nuclear DivlSlon Eur2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART l. LICENSE CONDITIONS REV. i l39 l TABLE l 1.1 Specific Locations of Authorized Activities (Ccnt.d) I Location E1M Authorized 4, Lagoon Uranium Uranium Compounds (up to Recovery of uranium from Rocovery 5 wt% U 235) waste solutions, Ammonia Recovery Uraniu.n Compounds (up to Removal and recovery of Facility 5 wt% U-235) ammonia from uranium contaminated liquid wastes. Lagoon 5A IX Uranium Liquid Wastes (up Filtration and ion exchange of Process ARF Building to 5 wt% U 235 and less uranium liquid wastes, than 14o gU/l concentrations in filters and resins) Any Permanent or Uranium solid waste (up to Sorting and compaction. Portable Building 5 wt% U 235) having HEPA filtration and Isokincts sampling. UF, Cylinder Uranium Compounds, solid Cyii.1 der recertification Recertificatior and in water solution (up to ardvities, including hydrostatic Facility 5 wt% U 235) strength testing, wall thickness measurement, internal examination, and pressure testing. The locations described in this table are shown on the site plan, Figure li-10.1 9 AkV,WENT APPtCA7m DATE. PMENo. August 4.1997 1-10_ SPC-ND 3330 947 (R 1107%
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Siernens Power Corporation - Nuclear Division EMF.2 7 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 (d i PART 11. SAFETY DEMONSTRATION nev. l39 l I i j 10.3.13 UFm Cylinder Recertification Facility (CRF) HVAC Syste_m l l l The general features of the CRF HVAC system include a combination of a once-l l through ai. flow and recirculation supply system (K66) and a double HEPA filtered exhaust system (K67). A simplified schematic diagram of the HVAC system is shown ir. Figure 1110.38. 10.3.13.1 K66 Air Syonly and Recirculation System i The K66 air supply and recirculation system supplies approximately 450 ft'/ min, of outside air and also recirculates approximately 2350 ft'/ min. of building air. i Recirculated air is passed through a roughi.ig filter and a single HEPA filter with an ! installed efficiency of 99.95% for 0.8 micron DOS cold-generated aerosol. Provision I is made in the K66 recirculation system for continuous alpha radiation monitoring of recirculated air upstream of the HEPA filter bank. The alpha air monitor is set to alarm and annunciate when alpha activity exceeds 40 DAC hr. (v)lj 10.3.13.2 K67 Air Exhaust Svstem Air supplied to the CRF, plus infiltration, is exhausted through the K67 exhaust system. The double HEPA filter arrangement in this system consists of the final HEPA filter bank and upstream primary HEPA filter sank. The K67 system exhaust air (approximately 950 ft / min.) passes from the two stage 8 l HEPA filter bank through the main exhaust fan, past a duct air monitor (measuring l airflow quantities) and is discharged from a stack extending 20 f t above ground on tho south side of the building. The K67 exhaust system has one fan which is connected to norreal power. All final HEPA filters are in-place tested to be 99.95% minimum efficient for 0.8 micron DOS cold generated aeroset, j 10.3.13.3 System Controls TFe HVAC systems are con' rolled with temperature, pressure ano flow sensor i actuating valving and damper positions to hold temperatures, pressures, and pressure ! differentials constant in the various building areas. The K66 supply air system is l interlocked with the K67 exhaust system to prevent operation of the K66 supply air system without the K67 exhaust system operating. Pressure sensors are provided to i maintain a minimum negative differential pressure of 0.05 inch water gauge in the building relative to the atmosphere, (3 r ) O AwENDMENT APPUCAYON DAT1-PAGE No : August 4.1997 10-50a sPC-ND 3330 947 $ 1979h
SiemenS Power Corporation Nuclear DiviSlon eur.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART ll SAFETY DEMONSTRATION REV. 39 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. 3 j I An automatic visuel alarm is activated when the recirculation system is inoperable. I i 10.3.13.4 HEPA Filter Bank l The final HEPA filters are enclosed in a sheet metal housing that, in turn, is mounted l on structural steel legs f astened to a concrete stab. The HEPA filters are rated at { i 3 1000 ft / min at one inch water gauge pressure drop and are mounted in welded steel i frames. Continuous air samplers are installed downstream of the filter bank. Visual i i indicators for reading the pressure drop across the filters are permanently installed, ! and means are provided for in-place dos testing. I The HEPA filtei medium is 100% moisture resistant fiberglass, pleated over corrugated separators and sealed in fire resistant plywood frames. The individual l filters are certified to remove 99.97% of 0.3 micron particles and meet or exceed l Military Specification MIL F 51079. I h i i i \\ I 1 i AMENouf NT APPLCATION DATE: PAGE W).: i 1 August 4,1997 10-50b sPC ND 3330 947 (R 90742)
I EMF 2 Revision 39 APPLICATION FOR RENEWAL OF SPECiAL NUCLEAR MATERIAL LICENSE NO. SNM 1227 (NRC DOCKET NO. 70 1257) Distribution D. L. Belt B. F. Bentley (4) J. B. Edgar B. N. Femreite R. L. Feuerbacher O J. W. Fredericks S. F. Gaines W. G. Keith D. C. Kilian L. J. Maas C. D. Manning C. S. Powers T. C. - Probasco A. Reparaz 1. J. Urza R. E. Vaughan C. A. Ward L. D. Weaver USNRC/M.F. Weber (6) USNRC RIV WCFO/C.A. Hooker DOH/L Wainhouse Document Control (5) O
DOCUMENT REVISION INSTRUCTION SHEET PAGE OF I l a EMF 2 DOCUMENT NUMBER: SiemenS Power Corporation Application for Renewal DOCUMENT TITLE: of Special Nuclear Material License No. SNM 1227 1 1 39 DOCUMENT REVISION: IDENTIF1 CATION REMOVE INSERT (1 E., SPECIFICATION, DRAWING, PROCEDURE, ETC.) PAGE(S) REVISION PAGE(S) REVISION Cover Sheet 38 39 Distribution 38 39 Table of Contents i.Vi 38 l-vi 39 Chapter 1 1 10 36 1 10 39 { ) Chapter 4 4 17 37 4-17 39 Chapter 10 10 50a & 10-50b 39 i I IF THE SPECIFICATIONS OR PAGES ARE ONLY REMOVED AND NOT REPLACED, e PLACE DASHES IN THE INSERT COLUMNS. IF THE SPECIFICATIONS OR PAGES ARE ONLY ADDITIONS (NO REPLACEMENTS), PLACE DASHES IN THE REMOVE COLUMNS. SPC ND 4122 011 (R-7/1092)
u O EMF-2, Rev. 39 lsmue Date: 12/23/97 Application for Renewal of ' Special Nuclear Material License No. SNM 1227 (NRC Docket No. 701257) O December 1997 6 =-- = k O
U e e SiemenS Power Corporation Nuclear DMsion ew.a SPECIAL NUCLEAR MATERIAL Ll0ENSE NO. SNM 1227. NRC DOCKET NO. 701257 i TABLE OF CONTENTS REV. i I p '_"4 0_ c t i EEd I l CHAPTER 1 - STANDARD CONDITIONS AND SPECIAL AUTHORIZATIONS 1.1 C orpo rate i nfo rm atio n....................................................................... b1 1.2 Site Locatio n......................................................... 11 i 1.3 License Number and Period of License............................................. 12 i 1.4 P o s ses sion Limits............................................................................ 12 1.5 Authoriz ed Activities.......................................................................... 12 I i 1.6 Exemptions and Special Authorizations......................................... 12 CHAPTER 2 ORGANIZATION AND ADMINISTRATION 1 2.1 Organizational Responsibilities and Authonty...................................... 21 2.2 Personnel Education and Experience Requirements............................ 211 2.3 S afety R eview Comm rttees................................................... Trainir e g....................................................................... 2.4 2 16 2.5 Operating Procedures, Standards and Guides..................................... 218 2.6 Configuration Control and Maintenance / Calibration of Safety Related E q uip m e nt........................................................................................ 2 1 8 2.7 Intemal Audits and inspections.......................................................... 2 10 i 2.8 Investigations and Re Records..................... porting of Reportable Incidents.......................... 2 21 2.9 ........................................................................2-22 i CHAPTER 3 - RADIATION PROTECTION 3.1 Ad ministrative Req uirements.......................................,.................,. 3-1 3.2 Technical Req uirements.................................................................. 3-2 APPENDIXA...................................................................................... 3-16 CHAPTER 4 - NUCLEAR CRITICALITY SAFETY 4.1 Administrative Practices............................................................. 41 4.2 Te chnical Pra ctices................................................................. 45 CHAPTER 5 - ENVIRONMENTAL PROTECTION 5.1 E fflue nt C o ntrol.......................................................... 5-1 5.2 Environmental Monitoring................................................... 5-5 CHAPTER 6 - SPECIAL PROGRAMS - = 6.1 --. ;r oprietary information........................s... 6-1 ' - 6.2 Occu pational Sa fety............................................................. 6-1 6.3 E m e rgency Utilitie s................................................................ 6-2 6.4 Radioactive Waste Management............................................. 6-2 ( 6.5 U F. C ylinde rs............................................................................... 6-3 t 5 I . AWENOWEM APf4CAflDN DATE-PAGE Noa December 22,1997 i SPC No 3330 947 (R-UO7r9h
-l SiemenS Power Corporation - Nuclear DMslon l eur.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKu as. 701257 i l TABLE OF CONTENTS l REV. j r I h !3O l l CHAPTER 7 DECOMMISSIONING PLAN I i 7.1 Decommissioning Plan............... 71 i 7.2 Decommissioning Cost Estimate.... 7-1 7.3 Decommissioning Funding Plan......... 7-1 l CHAPTER 8 - RADIO' OGICAL CC."TINGENCY PLAN.. 81 CHAPTER 9 GENERALINFORMATION i i 9.1 Cornorate Information................... 91 9.2 Financial Oualification..................................... 9-1 9.3 Summary of Operating Objective and Process............ 9-1 9.4 Site De s cription........................... 9-3 l 9.5 Location of Buildings On Site.............. 9-4 ! 9.6 M a ps a nd Plot Pla ns.............................................. 9-4 l 9.7 License History................................ 9-5 APPEN DIX A..............,....... 9-12. i CHAPTER 10 FACILITY DESCRIPTION 10.1 Plant Layout................... 10-1 i 10.2 Utilities and Support Systems........................................... 10-12 10 3 Heating. Ventilation, and Air Condrtioning (HVAC).................. 10-22, l 10.4 Radioactive Waste Handling........ ....................................10-51 i 10.5 Fire P rot e ctio n................................................ 10-64 I i 10.6 Criticality Accident Alarm System................. . 10-67 i ~ APP E N DlX A............................ ... 10-115 CHAPTER 11 - ORGANIZATION AND PERSONNEL 11.1 Organizational Responsibilities...... 11 1 11.2 Functions of Key Personnel............ 11-1 11.3 Educatien and Experience of Key Personnel. 11 1 11.4 Operating Procedures.. . 11-47 11.5 Training.......... 11-47 ; 11.6 Changes in Facilities and Equipment.. 11-48 l l l O AWENDMLNT APPLCAW DATE. P A0! Noa Decembec 22,1997 ii i i SPc-ND 3330 947 ( A-UO712)
v SiemenS Power Corporation - Nuclear DivlSlon eur.2 p SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 U i, TABLE OF CONTENTS nEv. i I 39 _ i j CHAPTER 12 RADIATION PROTECTION i j 12.1 Program........................................................................... 12-1 12.2 Posting a nd La belin g................................................................. 12 1 12.3 Intemal and External Radiation Personnel Monitoring.................... 12 1 12.4 R a diatio n S u rv e ys................................................................12 3 12.5 Radiation S a fety Training......................................................... 12 3 l i 12.6 Re po rts a nd R e co rd s..................................................................... 12-4 i 12.7 I n st ru m e nt s............................................................................... 12-4 I 12.8 Protective Clothing........................................................................ 12-5 12.9 Administrative Control Levels (including Effluent Control)................. 12 5 12.10 Respiratory Protection.....................................................................12-7 12.11 Occupational Exposure Analysis................................................... 12-8 12.12 Measures Taken to implement ALARA............................................ 12 9 12.13 B i oa s s a y Prog ra m.......................................................................... 12 9 12.14 Air Sampling and Intemal Exposure Program................................ 1210 i 12.15 S urface Contamination......................................................... APPENDlXA...............................................................................1212 AP P E N D I X B................................................ 12-81 O h CHAPTER 13 - ENVIRONMENTAL SAFETY RADIOLOGICAL & NONRADIOLOGICAL i 13.1 Exte mal R ad iation........................................................................ 13-1 13.2 G a se ou s Efflue nts........................................................................... 13-1 13.3 Liq uid E ffl uent s........................................................................... 13-1 i l 13.4 G ro u n dw a t e r............................................................................... 13-2 } 13.5 Field S a m pli n g............................................................................ 13-4 4 ' CHAPTER 14 NUCLEAR CRITICALITY SAFETY t 14.1 Administrative Pra ctices.......................................................... 14 1 14.2 Te chnical Pra etices........................................................... 14 3 5 14.3 R efe re n ce s........................................... .............. 14-44 i CHAPTER 15 PROCESS DESCRIPTION AND SAFETY ANALYSIS 15.1 U O, B uild ing................... -................................. 15-1 15.2 Speciality Fuels (SF) Building...................................... ... 15113 15.3 Engineering Laborator . 15-130 Warehouses...............y Operations (ELO) Building....... 15.4 .................................................15-145 CHAPTER 16 - ACCIDENT ANALYSES....................... 16-1 (s h AMENDUENT APPLCATIONDATE: PAGE NQ.: December 22,1997 iii sPC.NO 3330 947 (R-1/07/92)
Siemens Power Corporation - Nuclear DiviSlon F.ur.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 I, i i TABLE OF CONTENTS REV. ! l 39 l l LIST OF TABLES l I Table Paae l 1.1 Specific Locations of Authorized Activities................. 17 l3.1 Restricted Area Airborne Radioactivity Concentration Action Levels a nd Action s.............................................. 3 12 i i l3.2 Radiation Safety Instrument Capabilities.............. 3-13 l3.3 Routine Urinalysis Program Action Levels and Actions....... 3-14 l3.4 Routine Lung-Counting Program Action Levels and Actions.... 3 15 l-4.1 System Criticality Safety Controlled Parameters................. 4-16 l-4.2 Safety Factors for Homogeneous Single Units. 4-32 i l-4.3 Safety Factors for Heterogeneous Single Units. 4 33 l5.1 Boundary Concentration Action Levels................. 5-7 15.2 Total Boundary Action Levels......................... 5-8 l5.3 Liquid Effluent Action Levels and Actions................... 5-9 l l 7.1 Plant Decommissioning Cost Estimate Summary.............. 72 l ll-9.1 Corporate Information.......... 9-6 ! i 11 10.1 Ammonia Recovery Major Equipment... 10-68 ; 1110.2 LUR Process Equipment.......... 10-69 i 11 14.1 Critical Parameters for U Compounds Limited to 5 WT.% Enrichment. 14 8 11 14.2 Homogeneous & Heterogeneous Minimum Critical & Safe Masses.... 14 9 d 11-1 4. 3 Expressions for Geometne Buckling in Terms of Actual Dimensions & Extrapolation Distances.. 14 10 11 14.4 Compare 25 Keno Va RSIC Test Cases with SPC HP Work Stations..... 14 14 11 14.5 PNL Critical Experiment Data on Clusters of 4.29 WT% U2" Enriched UO Rods in Water.......... 14-18 2 11 14.6 PNL Critical Experiment Cases Calculation Results with 16-Group, 27 Group,218 Group, and 123-Group Cross-Sections. 14-20 ll-14.7 Properties of 2.46% Enriched UO, Fuel Rods.... 14-24 11 14.8 Certified Chemical Analysis of B.C...... 14 24 ll-14.9 B&W Critical Experiment Cases Calculation Results with 16-Group Cross-Sections.. 14 2 5 l AVENDUENT APPLCATON DATE: P AGE NO; December 22,1997 iv SPC-ND 3330 947 (R 90792)
o l l S10rnenS Power Corporation - Nuclear DivlSlon
- 9. w.2 O SPECIAL NUCLEAR MAHRIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701267
( i I TABLE OF CONTENTS REV. I 7 '49M i LIST OF FIGURES Fiaure PAqs I l 2.1 Organization Chart...................... 2 24 l 2.2 Organization Chart Safety, Secunty, & Licensin 2 25 l Approval and Responsibihty Matrix...............g............ l l 2.3 2-26 : 1-5.1 Fie!d Sample Station Locations................................................. 5-10 ! l5.2 Lagoon Test Well Locations........................................................ 5 11 i I I ll 9.1 Org a n iz a t io n C h a rt............................................................................... 97 i 11 9. 2 Richland Area and SPC Engineering and Manufacturing Facihty.......... 9-8. 31 9. 3 Land Use Within 50-Mile Radius of SPC Site - Recreation................ 9-9 11 9. 4 Land Use W. thin 50-Mile Rad.as of SPC Site - Agriculture.................... 9-10 i 11 9. 5 Led Use Within 50-Mile Radius of SPC Site - Urban........................ 9 11 1110.1 SPC Gite General Arrangement..............._..................................... 10-72 1110.2 Plant Equipmt nt Layout Specialty Fuels Building................................ 10-73 i 1110.3 Plant Equipme,nt Layout UO, Building..................................... 10 74 (,) i 1110.4 Plant Equipment Layout UO, Building............................................. 10-75 i ()i 1110.5 Plant Equipment Layout UO, Building............................................. 10 76 ' I ll 10.6 Plant Equipment Layout UO, Duilding............................................ 10-77 ! 1110.7 Plant Equipment Layout UO, Building.,............................................ 10-78 ll 10.8 Plant Equipment Layout UO, Building.,.......................................... 10 79 i 1110.9 Plant Equipment Layout UO, Buil ding............................................ 10-80 i 1110.10 Plant Equipment Layout UO, Building...................... 10-81 4 1110.11 Plant Equipment Layout UO, Building........................................ 10-82 l 1110.12 Plant Equipment Layout UO, Building..................................... 10-83 ll 10.13 Plant Equipment Layout UO, Building............................................... 10-84 i 1110.14 Plant Equipment Layout UO, Building............................................. 10-85 i 1110.15 Plant Equipment Layout UO, Building..................................... 10-86 1110.16 Plant Equipment Layout UO, Building................................... ....... 10-87 : 1110.17 Plant Equipment Layout ELO Building....................................,..... 10-68 i 1110.18 Hom Rapids Road Site and Arrangemem - Fire & Water Supply....... 10-89 Il 10.18a Hom Rapids Road Site and Arrangement - Sanitary Drain................ 10 90 1110.19 Simplified Schematic HVAC System - SF Building SWUR Facility.-. 10 91 1110.20 Simphfied Schematic HVAC System - SF Building Production Facility.. 10-92 Il 10.20a NAF Fumace Facility HVAC System Simplified Schematic., 10-93 ; j 1110.21 Simplified Schematic HVAC System - Original UO, Building...... 10-94 ll 10.21a Simplified Schematic HVAC System - Analytical Lab UO, Building. 10-95 1110.22 Simphfied Schematic HVAC S Area......._......... _..............ystem - UO, Building Line 2 Conversion10-96 1110.23 Simplified Schematic HVAC System - Main (South) Addition... 10 97 ,p G awoutm amcatos oats: I eaat wo.: December 22,1997 v I SPC-ND.3330 947 (R-UO7/92)
SlemenS Power Corporation - Nuclear DivlSlon tw.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SN:.11227, NRC DOCKET NO. 701257 l TABLE OF CONTENTS REV. ! 39 - LIST OF FIGURES (Cont.d) i ! Finure Paae 11 10.24 Simplified Schematic HVAC System U 0. Facility... ........... 10 9 8 3 1110.25 Simplified Schematic HVAC System ELO Building............ 10 09 ll 10.26 Simplified Schematic HVAC System ELO Building Addition...........10-100 l 1110.27 Simplified Schematic HVAC System Contaminated Clothing Laundry F a ci lit y............................................................. _............. 1 0 1 01 i ll 10.27a Simplified Schematic SWUR Inciner ir Shroud Cooline System... 10102 l Il 10.27b Lagoon Uranium Recovery / Solids Pr, win i l ll 10.28 System Flow Diagram..........................g Facility Ventilation .................. 10 10 3 Plant Equipment Layout ARF Building.................. ... 10 104 I ll 10.29 Amma w Recovery Waste Management Facility Engineering Flow i i Diagram........................................................................10105 Il 10.29a Flow Diagram Lag'oon 5A - Sewer lon F.xchange Project............. 10 106 ll 10.30 Plant Equipment Layout - LUR Facility.................... .... 10 107 11 10.31 Engineering Flow Diagram LUR Production Facility............ ...... 10-108 ll 10.32 F i re Al a rm S y s t e m.................................................................... 10- 109 11 10 33 SPC Site General Arrangement Dry Conversion First Floor..............10110 ' 11 10.34 SPC Site General Arrangement Dry Conversion Second Floor.........10111 11 10.35 SPC Site General Atrangement Dry Conversion Third Floor..............10-112 i 11 10.36 SPC Site General Arrangement Dry Conversion Fourth Floor............. 10-113 11 10.37 Dry Conversion Simplified Air Fltw Diagram................................. 10-114 j I l 1113.1 Monitoring Well Description....................................... 13 5 l ! 11-1 4. 1 PNL Critical Experiment Layout (Reference 6).......................... 14 17 ! i ! 11 14.2 B&W Critical Experiment Layout. ....... 14 23 l i i i i i f i i i i e autose amcum oan: December 22,1997 vi SPC-ND 3330 047 (R 1107/92)
SiemenS Power Corporation - Nuclear DiviSlon euF.2 /~3 SPECIAL NUCLEAR MATERIAL LICENSE NO SNM 1227 NRC DOCKET NO 70 1257 br i i PARTI LICENSE CONDITIONS REV. 36 i TABLE l 1,1 Specific Locations of Authorized Activities (Cont.d) l l 1 i Location SILff Authorized Activity i I ! Laundry Facility Uranium Compounds (up to Cleaning of contaminated l 5 wt% U 235) protective clothing and equipment. l l UF. Cylinder Storage UF. (up to 5 wt% U 235) Outside storage of UF. Areas cylinders (full and empty). l Packaged Fuel UO. (up to 5 wt% U 235) Outside storage of fuel packed Storage Areas for shipment; the transport containers are closed, sealed and properly labeled for shipment. ( )) 4 (' Packaged Waste Uranium Compounds (up to Outside storage of , Storage Areas 5 wt% U-235) contaminated materials i i (including low level waste and I incinerator ash) which are s packaged, sealed, labeled and i l externally free of contamination. i Process Chemical Uranium Compounds (up to Transfer, mixing, sampling, Waste Storage 5 wt% U 2351 storage and solar evaporation Lagoon System of contaminated liquid wastes. Retention Tanks Uranium Compounds (up to interim storage of potentially 5 wt% U 235) contaminated liquid wastes. High Uranium Solids Uranium Compounds (up to Transfer of uranium bearing Pond 5 wt% U-235) r.ds, leaching for uranium l recovery. Solids Trench Uranium Compounds (up to Transfer and storage of 5 wt% U 235) contaminated solids awaiting leaching or burial, The locations described in this table are shown on the site plan, Figure 11-g w) ; 10.1 (.O aussourut amcatos oatt: October 28,1996 NEC 19 i sPC NO 3330 947 tRa4742)
SiemenS Power Corporation - Nuclear DiviSlon EMF 2 i SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART I-LICENSE CONDITIONS i . REV ! ! 39 TABLE l 1.1 Specific Locations of Authorized Activities (Cont.d) Location SNM Authorized Activity Lagoon Uranium Uranium Compounds (up to Recovery of uranium from Recovery 5 wt% U-235) waste solutions. Ammonia Recovery Uranium Compounds (up to 'lemoval and recovery of Facility 5 wt% U 235) ammonia from uranium contaminated liquid wastes. Lagoon SA IX Uranium Liquid Wastes (up Filtration and lo;i exchange of Process ARF Building to 5 wt% U 235 and less uranium liquid wastes, than 140 gU/l concentrations in filters and resins) Any Permanent or Uranium solid waste (up to Sorting and compaction, Portable Building 5 wt% U 235) having HEP A filtration anri Isokinetic sarnpling. UFe Cylinder Uranium Compounds, solid Cylinder recertification Recertification and in water solution (up to activities, including hydrostatic Facility 5 wt% U 235) strength testing, wall thickness measurement, interr.at examination, and pressure testing. The locations described in this table are shown on the site plan, Figure ll-10.1 0 %6~wsst 4= tcatios oats-pes uo August 4.1997 1 10 sPC-ND 3330 047 (R UO712)
Siemens Power Corporation NL', lear Division eur.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701 57 i -- PART l LICENSE CONDITIONS REV- { 39 i i f k j li, a I Il [I ll $I l** llj I Ill!ll h x x x x { I e I 5 i i g 9 I 5 I l j a f f x i u, t i l l o N x x ki a /]i AutNDWtNT Ap4 CATION DAiE: PAGE No ; SPC NO 3330 941(R 14792)
5, T-o m 1 E O5 - c) 7 y3 sM Totde i 4.3 (Cont *d ) J 7 y p O CoupOt:Etst COf4TDOt TYPE IMSCtfSSaOt4 0F AtfY SPECIAt. OI S COf 4IllOLS ttSED / ADOtt:0t4A4 g-T EXPT At4ATIOt1 M CutilitOI TYPE mO' g GEO VOL Ft4A IJAA CCU CCM MCU MCM PPC ARA SPA 33 O O E _n_ yy I 2 -f O Cyundrical my "D - Tenn e, Fater e O and Oisie, yO h Egedpment [ f-U v x c-e < 8 4* ricardriel X X tIses eney incheJe dissohdtrin el y g7 tD pesets. mC ,o h ZQ Cymrwhical teras,littees, erus otties g CD c) l a eT guneed less treen tids dirnenskxt ITI d G ese also appropstatoff speced to Z Z essses needrors kdorecakms wets. O _C g g 5. cilios erydprnord war sesidt be 0 ecceptalde k., Fennee etgeornetry g 7 _3 or spacing enesweeet smeet rdeces of z gO3 eydgwneed is contro8ed I,y etesign O H to 5 9 25' nominal X X lIses are an.ned so tournogeneones y to I D. sosuttons / sherles assolo es t90, 7 y powdess, tIOf, erwl AIM s (f) .,a E Cyarmbicos senhs, idiers, eres cit.se o erydgwneed less tiemn tfds eueneriskue g era mise eggwogwletee spaced to O r essees needsoriInteracthms witte g ouses erydprisent wnl resedl bi 7 ecceptalde k, Falkee of genenetry m 1 d ce speck'D 2etween Beed gdeces of y a y erydgwnerd is cordsoned I,y deskyi Z9 O ^ N y i In ? ~.. _. - Q nE UI FT1 w n ng a 5 E 7 - L h e e C-
Siemens Power Corporation - Nuclear Division Eur2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART 11 SAFE' DEMONSTRATION REV. t 39 i i 10.3.13 UF. Cylinder Recertification Facill (CRF) HVAC System The general features of the CRF HVAC system include a comt, nation of a once-through airflow and recirculation supply system (K66) and a double HEPA filtered exhaust system (K67) A simplified schematic diagram of the HVAC system is shown i in Figure ll 10.38. 10.3.13.1 K66 Air Sunolv and Recirculation System l The K66 air supply and recirculation system supplies approximately 450 ft*/ min of outside air and also recirculates approximately 2350 ft'/ min, of building air, j Recirculated air is passed through a roughing filter and a single HEPA filter with an i I installed efficiency of 99.95% for 0.8 micron DOS cold generated aerosol. Provision l is made in the K66 recirculation system for continuous alpha radiation monitoring of l l recirculated air upstream of the HEPA filter bank. The alpha air monitor is set to alarm i and annuncinte when alpha activity exceeds 40 DAC hr. 10.3.13.2 K67 Air Exhaust System i i Air supplied to the CRF, plus infiltration, is exhausted through the K67 exhaust system. The double HEPA filter arrangement in this system consists of the final HEPA filter bank and upstream primary HEPA filter bank. 6 The K67 system exhaust air (approximately 950 ft*/ min.) passes from the two stage HEPA filter bank through the main exhaust fan, past a duct air monitor (measuring i i airflow quantities) and is discharged from i stack extending 20 ft above ground on the i touth side of the building. The K67 exhaust system has one fan which is connected i to normal power. All final HEPA filters are in-place tested to be 99.95% minimum efficient for 0.8 micron DOS cold-generated aerosol. 10.3.13.3 System Controls The HVAC systems are controlled with temperature, pressure and flow sensor j actuating valving and damper positions to hold temperatures, pressures, and pressure i differentials constant in the various building areas. The K66 supply air system is i interlocked with the K67 exhaust system to prevent operation of the K66 supply air l system without the K67 exhaust system operating. Pressure sensors are provided to maintain a minimum negative differential p' essure of 0.05 inch water gauge in the building rela.tive to the atmosphere. i V N i l =catwetcaron oars- ] paos wo.: August 4,1997 10Saa sPc-ND 3330 9471RM742)
SiemenS Power Corporation - Nuclear DivlSlon Eup.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PARTll SAFETY 9EMONSTRATION REV. 39 The K66 supply fan is interlocked so hat a oss of exhaust duct flow (exhaust fan failure) or a signal from the exhaust enct b sat detector will shut down the K66 air ' supply system. I I An automatic visual alarm is activated when the recirculation system is inoperable. l i 10.3.13.4 HEPA filter Bank l The final HEPA filters are enclosed in a sheet metal housing that, in turn, is mounted i on structural steel legs fastened to a concrete slab. The HEPA filters are rated at j 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 I i indicators for reading the pressure drop across the filters are permanently installed, l and means are provided for in-place DOS testing. 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 micren particles and meet or exceed i Military Specification MIL F-51079. I i l i i i I i t g auteucut amcaron oats: nos m : l August 4.1997 10-50b sPC ND.3330 947 (R-it0742)
O EMF 2 Revision 39 APPLICATION FOR RENEWAL OF SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227 (NRC DOCKET NO. 70 1257) Distribution D. L. Belt B. F. Bentley (4) J. B. Edgar B. N. Femreite R. L. Feuerbacher O J. W. Fredericks S. F. Gaines W. G. Keith D. C. Kilian L. J. Maas C. D. Manning C. S. Powers T. C. Probasco A. Reparaz 1. J. Urza R. E. Vaughan C. A. Ward L, D. Weaver USNRC/M.F. Weber (6) USNRC RIV WCFO/C.A. Hooker DOH/L Wainhouse Document Control (5) = O
DOCUMENT REVISION INSTRUCTION SHEET PAGE OF 1 1 EMF 2 DOCUMENT NUMBER: SiemenS Power Corporation Application for Renewal DOCUMENT TITLE: of Special Nuclear M.cerial License No. SNM 1227 39 DOCUMENT REVISION: IDENTIFICATION REMOVE INSERT (i E., SPECIFICATION, DRAWING PROCEDURE, ETC.) PAGE(S) REVISION PAGE(S) REVISION Cover Sheet 38 39 Distribution 38 39 Table of Contents l-vi 38 i-vl 39 Chapter 1 1 10 36 1 10 39 { } Chapter 4 4 17 37 4 17 39 Chapter 10 10 50a a 10-50b 39 i IF THE SPECIFICATIONS OR PAGES ARE ONLY REMOVED AND NOT REPLACED, e PLACE DASHES IN THE INSERT COLUMNS. IF THE SPECIFICATIONS OR PAGES ARE ONLY ADOITIONS (NO REPLACEMENTS), PLACE DASHES IN THE REMOVE COLUMNS. $%ND 4122 011 (A 2/1092)
s O EMF 2, Rev. 39 issue Date: 12/23/97 Application for Renewal of Special Nuclear Material License No. SNM 1227 (NRC Docket No. 701257) O December 1997 O
4 Siemens Power Corporation - Nuclear DivlSlon ew.2 Q SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 V i i i TABLE OF CONTENTS !AEV. l i l 39 l H, i i i P_ase l I CHAPTER 1 STANDARD CONDITIONS AND SPECIAL AUTHORIZATIONS f 1.1 Corporate l nform ation.................................................................. 11 1.2 S it e L o ca t io n............................................................................... 11 ! 1.3 License Number and Period of License....................................... 12 i i 1.4 Pos s e s sion Limit s....................................................................... 12 l 1.5 Auth o rized Activitie s....................................................................... 12 i 1.6 Exemptions and Special Authorizations........................................... 12 CHAPTER 2 ORGANIZATION AND ADMINISTRATION i i 2.1 Organizational Responsibilities and Authority....................................... 2 1 l 2.2 Personnel Education and Experience Requirements........................... 211 2.3 S a fety R eview C o mm ittee s.................................................................. 2-14 i 2.4 Train i n g............................................................................................. 2 1 6 2.5 Operating Procedures, Standards and Guides.................................... 218 p 2.6 Configuration Control and Maintenance / Calibration of Safety Related I i E q ui p m e nt.......................................................................................... 2 1 8 V 2.7 Internal Audits and inspections........................................................, 2-19 1 2.8 Investigations and Reporting of Reportable incidents.......................... 2 21 l 2.9 Records..............................................................................................222 i CHAPTER 3 RADIATION PROTECTION i r 3.1 Administrative Requireme nts.............. 3-1 3.2 Technics' hq uirement s................................................................... 3-2 APPENDIXA.................................................................................... 3-16 CHAPTER 4 NUCLEAR CRITICALITY SAFETY 4.1 Administrative Pra ctices.......................................................... 41 4.2 Technical Practices.................. 45 CHAPTER 5 - ENVIRONMENTAL FROTECTION 5.1 Effluent Control............................... 5-1 5.2 Environmental Monitoring................ 5-5 CHAPTER 6 SPECIAL PROGRAMS 6.1 Proprietary information...................................................... 6-1 6.2 Occupational Safety............................... 6-1 6.3 Emergency Utilities............................... 6-2 6.4 Radioactive Waste Management............................................ 6-2 - O. 6.5 U F, C y lin de rs....................................................................... 6-3 ( Leen amcatomte Pacm December 22,1997 1 i $PC.ND 3330 941 ( A4 p9h
SiemenS Power Corporation - Nuclear DiviSlon eur.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 g I I l l TABLE OF CONTENTS i REV i' l ( 4_Q I l CHAPTER 7 DECOMMISSIONING PLAN t 7.1 Decommissioning Plan................... 71 7.2 Decommissioning Cost Estimate. 7-1 7.3 Decornmissioning Funding Plan........................... 71 CH APTER 8 RADIOLOGICAL CONTINGENCY PLAN................. 8-1 i CHAPTER 9 GENERALINFORMATION i 9.1 Corporate Information.......................................... 91 9.2 Fina ncial O ua lifica tion........................................................ 91 9.3 Summary of Operating Objective and Process........................... 91 9.4 Site Description......................... 93 I 9.5 Location of Buildings On Site.,,,................................... 9-4 ! 9.6 M a ps a n d Plot Pla n s......................................................... 9-4 i 9.7 Lice n s e H i st o ry............................................................... 9-5 APPENDIXA.................................................................... 9 12 CHAPTER 10 FACILITY DESCRIPTION j 10.1 P la n t L a y o ut..................,................................................... 10-1 i 10.2 Utilities and Support Systems............ 10 12 10.3 Heating. Ventilation. and Air Conditioning (HVAC)....................... 10-22 l 10.4 Radioactive Waste Handling................................................... 1 0 51 10.5 Fire Pr ote ction................................................... 10-64 t 10.6 Criticahty Accident Alarm System........................................, 10-67 AP P E N D I X A......................................................................... 10- 1 1 CHAPTER 11 ORGANIZATION AND PERSONNEL 11.1 Organizational Responsibilities......... 11 1 11.2 Functions of Key Personnel................ 11 1 11.3 Education and Experience of Key Personnel..................... 11 1 11.4 Operating Procedures........... 11-47 11.5 Training.. _..................... 11-47 11.6 Changes in Facilities and Equipment... 11-48 O 4 AMENDMENT APP (CATION DATE: PAGE NO : December 22,1997 ii i SPC-ND 3330 947 (A+07/92)
e SlenienS Power Corporation Nuclear DivlSlon EMF.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 V ["~ i i TABLE OF CONTENTS REY. { 39 - r i i i CHAPTER 12 RADIATION PROTECTION i l 12.1 orogram.................................................................................... 12-1 12.2 Po stin g a nd La belin g.................................................................. 12 1 i 12.3 Internal and Extemal Radiation Personnel Monitorin 12 1 l R a diatio n S u rve y s..................................................g.............. 12.4 12 3 ! 12.5 Ra diation S afety Training........................................................... 12 3 l 12.6 R e ports a nd Record s................................................. 12-4 i 1 12.7 l n s t ru m e n t s............................................................................. 12-4 ; i 12.8 Prote ctive Clothin g....................................................................... 12 5 l 12.9 Administrative Control Levels (including Effluent Control).. 12 5 i 12.10 R e s piratory Prot e ction....................................................................... 12-7 12.11 Occupational E xpos ure Analysis...................................................... 12 8 : 12.12 Measures Taken to Implement ALARA........................................... 12-9 12.13 Bi oa s sa y Progra m............................................................................ 12 9 12.14 Air Sampling and Intemal Exposure Program.................................. 12-10 l 12.15 Surface Contamination...................................................... A P P E N D I X A................................................. A P P E N Dl X B................................................. 12 81 0 ( CHAPTER 13 - ENVIRONMENTAL SAFETY RADIOLOGICAL & NONRADIOLOGICAL u l i 13.1 E xte m al R a diation........................................................................ 13-1 13.2 G a se ou s E fflue nt s...................................................................... 13 1 13.3 Liq u id E ffl ue nt s............................................................................ 13 1 i i 13.4 G ro u n d w a t e r................................................................................... 13-2 I } 13.5 F ield S a m pli n g............................................................................. 13-4 i CHAPTER 14 NUCLEAR CRiliCALITY SAFETY i 14.1 Ad ministrative Pra ctice s............................................................. 14-1 14.2 T e chnical Pra etice s.........................,.......................................... 14 3 5 i 14.3 R e f e r e n ce s.................................................................................. 14-44 CHAPTER 15-PROCESS DESCRIPTION AND SAFETY ANALYSIS 15.1 U O, B u ild i n g............................................................................. 15-1 l 15.2 Speciality Fuels (SF) Building.................................................. 14113 15.3 Engineering Laborator Warehouses..............yOnerations (ELO) Building..................... 15-130 15.4 ...............................................................15-145 C H APTE R 16 ACCIDE NT AN ALYS ES.......................................................... 16-1 / f l i AWENOMENT APPLCA TON DA.O PAGE NOJ i December 22,1997 iii i sPC ND 3330 947 (Ra 07/92; 1 i
SiemenS Power Corporation - Nuclear Division EM F.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 I i TABLE OF CONTENTS l REV. } 90 l i 1.lST OF TABLES l 1 Table Paae I l-1.1 Specific Lor.ations of Authorized Activities.....,............. i7 1 13.1 Restricted Area Airborne Radioactivity Concentration Action Levels i and Actions........ 3-12 l3.2 Rcdiation Safety Instmment Capabilities..................,,,,.. 3-13 l-3.3 Routine Uriralysis Program Action Levels and Actions.. 3-14 4 l-3.4 Routine Lung-Counting Program Action Levels and Actions... 3-15 l-4.1 System Criticality Safety Controlled Parameters............. 4-16 l-4.2 Safety Factors for Homogeneous Single Units. 4-32 l-4.3 Safety Factors for Heterogeneous Single Units. 4-33 l5.1 Boundary Concentration Action Levels.......,........... 5-7 j I5.2 Total Boundary Action Levels.............. 5-8 I-5.3 Liquid Effluent Action Levels and Actions.............. 5-9 } l-7.1 Plant Decommissioning Cost Estimate Summary. 7-2 i i 11-9. 1 Corporate Infomiation....... 9-6 ll-10.1 Ammonia Recovery Major Equipment... 10-68 : 11-1 0. 2 LUR Process Equipment. 10-69 lb14.1 Catical Parameters for U Compounds Limited to 5 WT.% Enrichment. 14-8 11-1 4. 2 Homogeneous & Heterogeneous Minimum Critical & Safe Masses. 14-9 ll-14.3 Expressbns for Geometric Buckling in Terms of Actual Dimensions & Extrapolation Distances..._._....................... 14-10 11-1 4. 4 Compare 25 Keno Va RSIC Test Cases with SPC HP Work Stations... 14-14 11-1 4. 5 PNL Critical Experiment Data on Clusters of 4.29 WT% U22s Enriched UO Rods in Water.......... 14-18 2 11-1 4
- PNL Critical Experiment Cases Calculation Results with 16-Group, 27-Group,218-Group and 123-Group Cross-Sections.
14-20 11 14.7 Properties of 2.46% Enriched UO Fuel Rods.... 14-24 2 11-1 4. 8 Certifief Chemical Analysis of B.C.... 14-24 11-1 4. 9 B&W Critical Experiment Cases Calculation Results with 16-Group Cross-Sactions., 14-25 AMENDunNT AF71.tCATION DATE: PAGE NO.. December 22,1997 iv SPC-ND.3330 947 (A 1/07/92)
SiemenS Power Corporation - Nuclear Division EMF 2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO 701257 TABLE OF CONTENTS REV. 90 i LIST OF FIGURES ! Eipure Pace I l.2.1 Org anization C ha rt.......................................... 2-24 l 2.2 Organization Chart - Safety, Security, & Licensing... 2-25 ! l 2.3 Approval and Responsibility Matrix.................... 2-26 l i l5.1 rield Sample Station Locations.......... 5-10 l ll5.2 Lagoon Test Well Locations...... 5-11 i i 11 9. 1 Organization Cha rt............................................. 9-7 i . ll 9.2 Richland Area and SPC Enginaering and Manufacturing Facility... 9-8. ll 9.3 Land Use Within 50-Mile Radius of SPC Site - Recreation....... 9-9 1 11-9.4 Land Use Within 50-Mile Radius of SPC Site - Agriculture....... 9-10 I ll-9.5 Land Use Within 50-Mile Radius of SPC Site - Urban.............. 9-11 11-1 0. 1 SPC Site General Arrangement................................ 10-72 l j Il 10.2 Plant Equipment Layout Specialty Fuels Building................ 10-73 11-1 0. 3 Plant Equipment Layout UO, Building..................................... 10-74 i e i 1110.4 Plant Equipment Layout UO Building......................... 10-75 i 2 11-1 0. 5 Plant Equipment Layout UO, Building...................... 10-76 ' i ll 10.6 Plant Equipment Layout UO Building....................... 2 10-77 ll-10.7 Plant Equipment Layout UO Building......................... 10-78 2 11 10.8 Plant Equipment Layout UO Bu" ding.................... 10-79 l 2 l 1110.9 Plant Equipment Layout UO, Building.................. 10-80 j 11-10.10 Plant Equipment Layout UO Building....... 10-81 l 2 11-10.11 Plant Equipment Layout UO Building...................... 10-82 i 2 ' 11-10.12 Plant Equipment Layout UO Building........ 10-83 2 11-10.13 Plant Equipment Layout UO, Building.......................... 10-84 i 11-10.14 Plant Equipment Layout UO Building....... 10-85 2 11-10.15 Plant Equipment Layout UO Building....... 10-86 2 1110.16 Plant Equipment Layout UO Building..... 10-87 2
- 11-10.17 Plant tiquipment Layout ELO Building................................
10-88 11-10.18 Hom Rapids Road Site and Arrangement - Fire & Water Supply. 10-89 Il-10.18a Hom Rapids Road Site and Arrangement-Sanitary Drain......... 10-90 11-10.19 Simplified Schematic HVAC System - SF Building SWUR Facility.~ 10-91 ll-10.20 Simplified Schematic HVAC System - SF Building Production Facility. 10-92 ll 10.20a NAF Ft: iace Facility HVAC System Simplified Schematic.... 10-93 4 11-10.21 Simplified Schematic HVAC System - Original UO Building.... 10-94. 2 ll-10.21a Simplified Schematic HVAC System - Analytical Lab UO Building. 10-95 2 1110.22 Simplified Schematic HVAC System - UO EJilding Line 2 Conversion 2 Area..... 10-96 11-10.23 Simplified Schematic HVAC System - Main (South) Addition. 10-97 9. I iwesousmamcaronoart: pace so : December 22,1997 v SPc ND 3330 947 (R-U07/92)
SiemenS Power Corporation - Nuclear Division eup.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 i TABLE OF CONTENTS REv. i 39 LIST OF FIGURES (Cont.d) Fiaure Paoe ! 11-10.24 Simplified Schematic HVAC System - U 0. Facility......... 10-98 ! 3 ll-10.25 Simplified Schematic HVAC System - ELO Building............ 10-99 ll-10.26 Simplified Schematic HVAC System - ELO Building Addition..... . 10-100 l ll 10.27 Simplified Schematic HVAC System, Contaminated Clothing Laundry ll 10.27a rn ifie'd"5cEer'natic 2SWUNlnc'ine' rat $r'5No0d'Uo$' leg"5hstem. ' '. 1 - Il-10.27b Lagoon Uranium Recovery / Solids Processing Facility Ventilation System Flow Diagram. . 10-103 11-10.28 Plant Equipment Layout - ARF Building................ .10-104 i ll-10.29 Ammonia Recovery Waste Management Facility Engineering Flow Diagram.. .... 10-105 ll 10.iJa Flow Diagram Lagoon SA - Sewer lon Exchange Project...... ... 10-106 11 10.30 Plant Equipment Layout - LUR Facility................... .10-107 ll-10.31 Engineering Flow Diagram - LUR Production Facility.... .. 10-108 t 11-10.32 Fire Alarm System... .10-109 ll-10.33 SPC Site General Arrangement Dry Conversion First Floor.... .10-110 l 11-10.34 SPC Site General Arrangement Dry Conversion Second Floor. . 10-111 11-10.35 SPC Site General Arrangement Dry Conversion Third Floor... . 10-112 j 11-10.36 SPC Site General Arcangement Dry Conversion Fourth Floor.. .10-113 i 11-10.37 Dry Conversion Simplified Air Flow Diagram.. .10-114 i
- 11-1 3.1 Monitoring Well Description..
13-5 e! 11-14.1 PNL Critical Experiment Layout (Reference 6). 14-17 I i 11-1 4. 2 B&W Critical Experiment Layout....... . 14-23 t 3 I I I O asaam amccon o44-December 22,1997 vi I SPC ND.3330D47 (R-imh92)
SiemenS Power Corporation - Nuclear Division sup.2 (7 SPECIAL NUCLEAP. MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 701257 V, I i PART I-LICENSE CONDITIONS REV. 36 l i TABLE l-1.1 Specific Locations of Authorized Activities (Cont.d) I Location S.NM Authorized Activity i i ! Laundry Facility Uranium Compounds (up to Cleaning of contaminated l 5 wt% U 235) protective clothing and l equipment. l UFs Cylinder Storage UF (up to 5 wt% U 235) Outside storage of UF. Areas cylinders (full and empty). Packaged Fuel UO (up to 5 wt% U-235) Outside storage of fuel packed i 2 Storage Areas for sh pment; the transport containers are closed, sealed and properly labeled for
- shipment, p), Packaged Waste
( Uranium Compounds (up to Outside storage of l Storage Areas 5 wt% U-235) contaminated materials i i (including low level waste and incinerator ash) which ar~e packaged, sealed, labeled and i externally free of l contamination. Process Chemical Uranium Compounds (up to Transfer, mixing, sampling, Waste Storage 5 wt% U-235) storage and solar evaporation Lagoon System of contaminated liquid wastes. Retention Tanks Uranium Compounds (up to Interim storage of potentially 5 wt% U-235) contaminated liquid wastes. High Uranium Solids Uranium Compounds (up to Transfer of uranium bearing Pond 5 wt% U 235) solids, teaching for uraniuto recovery. Solids Trench Uranium Compounds (up to Transfer and storage of 5 wt% U-235) contaminated solids awaiting leaching or burial, n The locations described in this table are shown on the site plan, Figure 11-f )< 10.1 LJ' ausuousut amcarou o4rt: October 28,1993 PCE Wa 1.g sPC-ND:3330 947 (R 1/07/92)
SiemenS Power Corporation - Nuclear Division eur2 EPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 70-1257 PART I-LICENSE CONDITIONS REV. I 39 l 4 i TABLE l 1.1 Specific Locations of Authorized Activities (Cont.d) I I Location SNM Authorized Activity Lagoon Uranium Uranium Compounds (up to Recovery of uranium from Recovery 5 wt% U-235) waste solutions. l Ammonia Recovery Uranium Compounds (up to Removal and recovery of Facility 5 wt% U-235) ammonia from uranium contaminated liquid wastes. l Lagoon SA IX Uranium Liquid Wastes /JP Eiltration and ion exchange of l Process-ARF Building to 5 wt% U-235 and less uranium liquid wastes, than 140 gU/l concentrations in filters and resins) Any Permanent or Uranium solid waste (up to Sorting and compaction. Portable Building 5 wt% U-235) having HEPA filtration and l 1 Isokinetic sampling. UF. Cylinder Uranium Compounds, solid Cylinder recertification Recertification and in water solution (up to activities, including hydrostatic Facility 5 wt% U 235) strength testing, wall thickness measurement, internal excmination, and pressure testing. The locations described in this table are shown on the site plan, Figure 11-10.1 s O ~ AMENOMENT APPUCATON DATE: PAGE NO : ~ August 4.1997 1-10 sPC ND 3330 947 (R-1/07/92)
, _.. ~ _..... _ - ~ = _ .m. e1 4 i t 'g u _.. _. l. f e_._J_ i T a. ,.1 h O5 m y -e a >a r 3 g c Z T-c O 9 OrE E
- Table I-4.1 (Cont'd.).
mG in O COMPONENT CONTROL TYPE DISCUSSION OF ANY SPECIAL 30 CONTROLS USED / ADDITIONAL E, EXPLANATION OF CONTROL TYPE >V -4 O GEO VOL FNA NAA CCU-CCM MCU MCM PPC ARA SPA -:m g. 3_ :!. g 1 2 t* yo g UF, Cyhnders X' -[, to X 'X X r"* 3 6 y g-- j e -{ during cyhnder H .g 7 wash and 7 mc recertification r-- ZO . t 8 operations (3tr Me g N diameter or less) m M ID Z Z' e 'W Vaporization X X Ikdundant devces prevent fissile m
- o. O g
chests (ADO solubon from execedwig a safe O M <- L 5 precets lines) geometry inside the vaporization :: g o 2 a Vaporization X No credible pathway exists to get d f0 I chests and autoclaves (dry conversion vapori:stion chest or y -y [ lissile solubon into the dry O l conversion) autoclaves Z t 3 i Unfavorable X X' .X O' M 'Y scrubber 'O i g' o m systems / liquid (). l 6 separators x m v 5 d [ o 5 Z g A -O A t o N Y I s s - ~ . - ~ -, _. -. _ - _,.,. _ ~.. - .a Wm w 2 Ng-5 2 P M P -f I i t )
w 5 TF m E Ob y > cp 2 f t-M Tattle 14.1 (Cone'd ) 7 T E1 OtSCtfSSlots OF At4Y SPEb 1. O 5 ct3aAl'Orl[tir COtilflOt TYPE gI COtilI101S tISED / ADDII80ia^t r-W EXPI AtlATIOta OF COtiliti)l. l..? N (D GLO VOL FliA fiAA CCU CCM MCU MCM PPC ATL*. SPA 33 O E9 I A I-. Cylindrical my Tank e. Fitters I c. O .no ottier >0 h Eqidpment [ f~ U u m r-G < 8 4* nondnal X X tises may inchale disschdlon of y g7 y ID panels. 7 mC 9 r-Z 9. Cylindelcal torphs, fitters, erut ottier 3 CD (D _a E% [ eqedpment less tfian tinfs dhnension m O-ase also appropelateff spaced 10 Z Z O9 assium netstroes biletactions witis g g 5, ollies %gedpmeret will residt he ac.ceptalete k, fm&wo ofDoometry O Z 9-or speckig laelneert lisent plecos of z gO3 eqidsunent is cotilaollad l>y closigen O 1 5 9 25' nominal X X tIses ese linalted to llornogeneoess -d fu O 80 10. sohdions / sliweles sim.fi es 410, g y powdess,110f, and ADti. (/) 7 CyRauhical tanks, htters, asut ottier Q eqidpenent loss Ilian tids abnenistors g + are also approgvlately spaced to O assime nessitoriintesettlons witis / g f offies e<pdpment will essedt he X ~ seceptalJe k,. Fa&me of geometry A or spacing tietween lined pieces of d y 9 ety Apment is contso!!ed lay deskjn Z g g y '? k O o Y i 2 ~ ro P (n m $M N E 5 S T to e e e 9 -l
s Ly,- SiemenS Power Corporation - Nuclear Division euF.2 - (" SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 \\ l-PART 11. SAFETY DEMONSTRATION nev. 39 l 10.3.13 Ub Cvlinder Recertification Faqility (CRF) HVAC System The general features of the CRF HVAC system include a combination of a once-1 through airflow and recirculation supply system (K66) and a double HEPA filtered exhaust system (K67).- A simplified schematic diagram of the HVAC system is shown [ in Figure ll 10.38. i i i 6 10.3.13.1 K66 Air Sunolv and Recirculation System i The K66 air supply and recirculation system supplies approximately 450 ft'/ min. of outside air and also recirculates approximately 2350 ft'/ min, of building air. t Recirculated air is passed through a roughing filter and a single HEPA filter with an { installed efficiency of 99.95% for 0.8 micron DOS cold-generated aerosol. Provision I is made in the K66 recirculation system for continuous alpha radiation monitoring of i i recircu!sted air upstream of the HEPA filter bank. The alpha air monitor is set to alarm i and annunciate when alpha activity exceeds 40 DAC-br. .I AQ 10.3.13.2 K67 Air Exhaust System I l Air supplieo to the CRF, plus infiltration, is exhausted through the K67 exhaust system. The double HEPA filter arrangement in this system consists of the final HEPA l filter bank and upstream primary HEPA filter bank. l i The K67 system exhaust air (approximately 950 ft'/ min.) passes from the two stage HEPA~ filter bank through the main exhaust fan, past a duct air monitor (measuring i i airflow quantities) and is discharged from a stack extending 20 ft above ground on the ! south side of the building. The K67 exhaust system has one fan which is connected I to normal power. All final HEPA filters are in-place tested to be 99.95% minimum i l efficient for 0.8 micron DOS cold-generated aerosol. 10.3.13.3. System Controls i i The HVAC systems are controlled with temperature, pressure and flow sensor t actuating valving and damper positions to hold temperatures, pressures, and pressure differentials constant in the various building areas. The_ K66 supply air system is interlocked with the K67 exhaust cystem to prevent operation of the K66 supply air system without the K67 exhaust system operating. Pressure sensors are provided to i maintain a minimum negative differential pressure of 0.05 inch water gauge in the i building relative to the atmosphere. O k AMENOMENT AP% CATION DATE: PAGE NO.: August 4,1997 10-50a l SPC ND 3330 947 (R-1/0742)
SiemenS Power Corporation - Nuclear Division EuF.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 701257 PART ll-SAFETY DEMONSTRATION REV. l 39 l ~~ The K66 supply fan is interlacked so tha'. a loss of exhaust duct flow (exhaust fan I failure) or a signal from the exhaust duct heat detector will shut down the K66 air supply system. i t
- An automatic visual alarm is activated when the recirculation system is inoperable.
l 1 ,' 10.3.13.4 HEPA Filter Bank l i The final HEPA filters are enclosed in a sheet me+al housing that, in turn, is mounted on structural steel legs fastened to a concrete slab. The HEPA filters are rated at i 1000 it'/ 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 i indicators for reading the pressure drop across the filters are permanently installed, ! and means are provided for in-place DOS testing. I The HEPA filter medium is 100 % moisture-resistant fiberglass, pleated over corrugated separators and sealed in fire-resistant plywood frames. The individual j filters are certified to remove 99.97% of 0.3 micron partic'es and meet or exceed j Military Specification MIL-F 51079. l I l l i l i I i 9 i
- AMENDMENT APPUCATON DATE:
PAGE NO.: August 4,1997 10-50b sPC ND-3330 947 (Aa107/92)
s EMF 2 g Revision 39 - APPLICATION FOR RENEWAL OF SPECIAL NUCLEAR MATERIAL LICENSE NO.- SNM 1227 (NRC DOCKET NO. 70-1257) Distribution D. L. Belt B. F. Bentley (4) J. B, Edgar B. - N. Femreite R. L. Feuerbacher O J. W. Fredericks S. F. Gaines W. G. Keith D. C. Kilian L. J. Maas C. D. Manning C. S. Powers - T. C. Probasco A. Reparaz 1. J. Urza R. E. Vaughan C. A. Ward L. D. Weaver USNRC/M.F. Weber (6) USNRC-RIV WCFO/C.A.- Hooker ' DOH/L. Wainhouse Document Control (5) O ~ l ____._m__ __.m.m.--
t c. I so DOCUMENT REVISION INSTRUCTION SHEET PAGE OF l \\ ) EMF-2 DOCUMENT NUMBER: SiemenS Power Corporation - Application for Renewal DOCUMENT TITLE: of Spec al Nuclear Material License No. SNM-1227 39 DOCUMENT REVISION: loENTIFICATION REMOVE INSERT (1.E., SPECIFICATION, DRAWING, PROCEDURE, ETC.) PAGE(S) REVISION PAGE(S) F EVISION Ccver Sheet 38 39 Distribution 38 39 Table of Contents l-vi 38 i-vi 39 Chapter 1 1-10 36 1-10 39 l } Chapter 4 4-17 37 4-17 39 Chapter 10 10-50a & 10-50b 39 IF THE SPECIFICATIONS OR PAGES ARE ONLY REMOVED AND NOT REPLACED, PLACE DASHES IN THE INSERT COLUMNS. IF THE SPECIFICATIONS OR PAGES ARE ONLY ADDITIONS (NO REPLACEMENTS), PLACE DASHES IN THE REMOVE COLUMNS. SPC N& 4122 011 (R 2/10S2)
' O EMF-2, Rev. 39 Issue Date: 12/23/97 Application for Renewal of Special Nuclear Material License No. SNM 1227 (NRC Docket No. 70-1257) O December 1997 t 1 O
SiemenS Power Corporation - Nuclear Division eup.2 (' Q SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 V i TABLE OF CONTENTS REV. ! 39 ) l Paoe l i j CHAPTER 1 - STANDARD CONDITIONS AND SPECIAL AUTHORIZATIONS 1.1 Corporate Information... 1-1 1.2 Site Location..................................... 1-1 1.3 License Number and Period of License.................. 1-2 i 1.4 Possession Limits....................................... 1-2 1.5 Authorized Activities................ 1-2 s 1.6 Exemptions and Special Authorizations............... 1-2 CHAPTER 2 - ORGANIZATION AND ADMINISTRATION 'i 2.1 Organizational Responsibilities and Authonty...................... 2-1 2.2 Personnel Education and Experience Requirements................ 2-11 2.3 Safety Review Committees....... Tra in ing........... _.............. _......... _............................... 2-14 2.4 2-16 2.5 Operating Procedures, Standards and Guides.... .........................2-18 _,m 2.6 Configuration Control and Maintenance / Calibration of Safety Related V) Equipment....................... ...................2-18 ( 2.7 Internal Audits and Inspections............................................... ' 2-19 Investigations and Reportin 2.8 Records..................g of Reportable incidents............ 21 j 2.9 2-22 i CHAPTER 3 - RADIATION PROTECTION i 3.1 Administrative Requirements.......... 3-1 3.2 Technical Requirements...................... 3-2 APPENDIX A................. 3-16 CHAPTER 4 - NUCLEAR CRITICALITY SAFETY 4.1 Administrative Practi:es. 4-1 4.2 Technical Practices..., 4-5 CHAPTER 5 - ENVIRONMENTAL PROTECTION 5.1 Effluent Control..... 5-1 5.2 Environmental Monitoring.... 5-5 CHAPTER 6 - SPECIAL PROGRAMS 6.1 Proprietary information.. 6-1 6.2 Occupational Safety. 6-1 6.3 Emergency Utilities...... 6-2 6.4 Radioactive Waste Management..... 6-2 p 6.5 UF Cylinders......... 6-3 D f AMENOMENT APPUCATION DATE: P AGE NO2 December 22,1997 i SPC ND.3330 947 (R te07/92)
SiemenS Power Corporation - Nuclear Division eur.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 i i l TABLE OF CONTENTS !REV I i 39 j ! CHAPTER 7 - DECOMMISSIONING PLAN f 7.1 Decommissioning Plan..... 7-1 i 7.2 Decommissioning Cost Estimate.... 7-1 7.3 Decommissioning Funding Plan.. '. - 1
- CHAPTER 8 - RADIOLOGICAL CONTINGENCY PLAN.,
8-1 CHAPTER 9 - GENERAL INFORMATION 9.1 Corporate Information.. 9-1 9.2 Financial Qualification........... 9-1 9.3 Summary of Operating Objective and Process. 9-1 9.4 Site Description.. 9-3 9.5 Location of Buildings On-Site. 9-4 9.6 Maps and Plot Plans... 9-4 9.7 License History., 9-5 APPENDin A.. 9-12 CHAPTER 10 - FACILITY DESCRIPTION 10.1 Plant Layout.............. 10-1 10.2 Utilities and Support Systems...... 10-12 10.3 Heating, Ventilation. and Air Conditioning (HVAC).. 10-22 10.4 Radioactive Waste Handling... 10-51 i i 10.5 Fire Protection....... 10-64 ' i 10.6 Criticality Accident Alarm System. APPENDIX A.. . 10-67 .10-115 CHAPTER 11 - ORGANIZATION AND PERSONNEL 11.1 Organizational Responsibilities... 11-1 11.2 Functions of Key Personnel........ 11-1 11.3 Education and Experience of Key Personnel. 11-1 11.4 Operating Procedures. 11-47 11.5 Training......... 11-47 11.6 Changes in Facilities and Equipment. 11-48 4 O AuENOMENT APP (CATON DATE: PAGE M)2 December 22.1997 ii SPC-ND 3330 947 (R 1/07/921
0 4 ~\\. lSlemenS Power Corporation - Nuclear Division EMF.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO,70-1257-TABLE OF CONTENTS REV. 39-- I - CHAPTER 12 - RADIATION PROTECTION 12.1 --Program....................................................................................... 12-1 12.2 Posting a nd Labeling................................................................ 12 ;- 12.3 Intemal and Extemal Radiation - Personnel Monitoring.................... 12-1 12.4 R adiation S u rveys....................................................................12-3 12.5 Radiation Safety Training............................................................... 12-3 ][ i_ 12.6 R eports and R ecords................................................................... 12-4 12.7 I n st ru m ents................................................................................... 12-4 ; 4 -12.8 Protective Clothing..................................................................,12-5 l 12.9-Administrative Control Levels (including Effluent Control)................ 12-5 i i 12.10 Respiratory Protection................................................................. 12-7 : 12.11 Occupational E.xposure Analysis........................................................ 12-8 ! 12.12 Meesures Taken to implement ALARA..................................... 12-9 l i 12.13 Bioassay Prog ram................................................................... 9 ! 12.14 Air Sampling and Intemal Exposure Program............................ 12 l 1 12.15 S u rface Conta mination...................................................... A P PE N DI X A................................................. A P P E N D I X B.................................................. i j 12-81 4 \\ CHAPTER 13 - ENVIRONMENTAL SAFETY - RADIOLOGICAL & NONRADIOLOGICAL - i 13.1-Extema l R adiation................................................................... 13-1 13.2 Ga seous Effl ue nts.................................................................... 13 l 13.3 Liq uid Effluents............................................................................. 13-1. 13.4 G ro u ndwat e r............................................................................ 13-2 l 13.5 F ield S a m pli ng.....................................................................13-4 i CHAPTER 14 - NUCLEAR CRITICALITY SAFETY i 1 i 14.1 Administrative Practices.......................................................... 14-1 14.2 Technical Practices.......................................................... 14-35 14.3 Refe re nces................................................ 14-44 CHAPTER 15 - PROCESS DESCRIPTION AND SAI-ETY ANALYSIS 1 3 15.1 U O B uildin g............. _.................................................... 15-1 2 15.2 Speciality Fuels (SF) Building..... ...... 15-113 15.3 Engineering Laboratory Operations ELO Buildin ........., 15-130 l Warehouses............................. (........)...........g.. 15.4 .................. 15-14 5 i CHAPTER 16 - ACCIDENT ANALYSES............... 16-1 p r-- i AMENOMENT APPUCATON DATE: PAGE Noa 6 1 December 22,1997 iii 4 { SPC.ND 3330.947 (R-U07/92)
Siernens Power Corporation - Nuclear Division EMF 2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 701257 i I TABLE OF CONTENTS REV. ' Mo e LIST OF TABLES i } l i i Table Pace ll-1.1 Specific Locations of Authorized Activities. 1-7 !l3.1 Restricted Area Airbome Radioactivity Concentration Action Levels i and Actions........ 3-12 s 13.2 Radiation Safety instrument Capabilities......._......... 3-13 l l3.3 Routine Urinalysis Program Action Levels and Actions.. 3-14 I3.4 Routine Lung-Counting Program Action Levels and Actions. 3 15 l-4.1 System Criticality Safety Controlled Parameters.......... 4-16
- l 4.2 Safety Factors for Homogeneous Single Units......
4-32 I-4.3 Safety Factors for Heterogeneous Single Un s.. 4 33 a 15.1 Boundary Concern. tion Action Levels... 5-7 l5.2 Total Boundary Action Levels.......... 5-8 l-5.3 Liquid Effluent Action Levels and Actions...... 5-9 i l 7.1 Plant Decommissioning Cost Estimate Summary..... 7-2 l 11 9. 1 Corporate Information.. 9-6 l i ll-10.1 Ammonia Recovery Major Equipment.... 10-68 : 1110.2 LUR Process Equipment..... 10-69 11-1 4. 1 Critical Parameters for U Compounds Limited to 5 WT.% Enrichment.. 14 8 11-1 4. 2 Homogeneous & Heterogeneous Minimum Critical & Safe Masses. 14-9 1114.3 Expressions for Geometric Buckling in Terms of Actual Dimensions & Extrapolation Distances. 14-10 11-1 4. 4 Compare 25 Keno Va RSIC Test Cases with SPC HP Work Statior's.. 14-14 11-1 4. 5 PNL Critical Experiment Data on Clusters of 4.29 Wi% U23s Enriched UO Rods in Water. 2 14-18 11 14.6 PNL Critical Experiment Cases Calculation Results with 16-Group, 27-Group,218 Group, and 123-Group Cross Sections. 14-20 ll-14.7 Properties of 2.46% Enriched UO Feel Rods.. 14-24 2 11-1 4. 8 Certified Chemical Analysis of B.C.... 14-24 11-1 4. 9 B&W Critical Experiment Cases Calculation Results with 16-Group Cross-Sections. 14-25 e i t AMENOMENT APpt,1 CATION C,*TE: PAGE NO. g g jgg7 IV spC.ND:3330 947 tA-ir07S2)
SiemenS Power Corporation - Nuclear Division eur.2 (V3 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 7012 TABLE OF CONTENTS REV. 30 i LIST OF FIGURES l Fiaure Pace l-2.1 Organization Chart................................... 2-24 { l-2.2 Organization Chart - Safety, Security, & Licensing.... 2-25 !
- 12.3 Approval and Responsibility Matrix......
2-26 15.1 Field Sample Station Locations........... 5-10 I l5.2 Lagoon Test Well Locations.......................... 5-11 i i Il-9.1 Org a nization Chart............................................... 9-7 ! 11-9. 2 Richland Area and SPC Engineering and Manufacturing Facility. 9-8 119.3 Land Use Within 50-Mile Radius of SPC Site - Recreation...... 9-9 ll 9.4 Land Use Within 50-Mile Radius of SPC Site - Agriculture...... 9-10 ! 11-9.5 Land Use Within 50-Mile Radius of SPC Site - Urban..... 9-11 ll-10.1 SPC Site General Arrangement............................ 10-72 1110.2 Plant Equipment Layout Specialty Fuels Building.. 10-73 ' j ll 10.3 Plant Equipment Layout UO Building........... 10-74 2 O ll-10.4 Plant Equipment Layout UO Building........... 10-75 2 (~) ! 11-10.5 Plant Equipment Layout UO Building.... 10-76 > 2 j 11-10.6 Plant Equipment Layout UO, Building...... 10-77 { i 1110.7 Plant Equipment Layout UO Building................... 10-78 2 11-1 0. 8 Plant Equipment Layout UO Building... 10-79 l 2 l 11-1 0. 9 Plant Equipment Layout UO Building. 10-80 l 2
- 1110.10 Plant Equipment Layout UO Building.,...
10-81 ! 2 11-10.11 Plant Equipment Layout UO Building....... 10-82 ! 2 11-10.12 Plant Equipment Layout UO, Building... 10-83 11-10.13 Plant Equipment Layout UO Building......... 10-84 2 11-10.14 Plant Equipment Layout UO Building..... 10-85 i 2 11-10.15 Plant Equipment Layout UO Building. 10-86 2 11 ' 0. 1 6 Plant Equipment Layout UO Building........ 10-87 2 ll-10.17 Plant Equipment Layout ELO Building....... _................ 10-88 11-10.18 Hom Rapids Road Site and Arrangement - Fire & Water Supply.. 10-89 Il 10.18a Horn Rapids Road Site and Arrangement-Sanitary Drain....._.. 10-90 ll 10.19 Simplified Schematic HVAC System - SF Building SWUR Facility... 10-91 11-10.20 Simplified Schematic HVAC System - SF Building Production Facility.. 10-92 Il-10.20a NAF Fumace Facility HVAC System Simplified Schematic... 10-93 1 1110.21 Simplified Schematic HVAC System - Original UO Building..... 10-94 2 Il-10.21a Simplified Schematic HVAC System - Analytical Lab UO Building. 10-95 2 1110.22 E;mplified Schematic HVAC System - UO Building Line 2 Conversion 2 Are a....... _.............. _... _ 10-96 11-10.23 Simplified Schematic HVAC System - Main (South) Addition. 10-97 r. AMENOMENT APPLCATON DATE; PAGE No.: December 22,1997 v SPC.ND 3330 947 (R-UO7/92) ~
4 SiemenS Power Corporation - Nuclear Division eur.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 701257 i i TABLE OF CONTENTS l REv. I I f 39 - LIST OF FIGURES (Cont.d) I Fiaure Pace ! ll-10.24 Simplified Schematic HVAC System - U 0 Facility.. 10-98 ! 3 I! 10.25 Simplified Schematic HVAC System - ELO Building........ 10-99 l1 10.26 Simplified Schematic HVAC System - ELO Building Addition.... .. 10-100 ! 11-10.27 Simplified Schematic HVAC System - Contaminated Clothing Laundry l Facility........ .10-101 i ! Il 10.27a Simplified Schematic - SWUR Incinerator Shroud Cooling System....10-102 i li-10.27b Lagoon Uranium Recovery / Solids Processing Facility Ventilation 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 Diagram..........
. 10-105 ll-10.29a Flow Diagram Lagoon SA - Sewer lon Exchange Project. ... 10-106 i 11-10.30 Plant Equipment Layout - LUR Facility... .. 10-137 11-10.31 Engineering Flow Diagram - LUP, Production Facility............10 *.08 ll-10.32 Fire Ala rm System.................... -......................,... .10-109 11-10.33 SPC Site General Arrangement Dry Coriversion First Floor..... . 10-110 11-10.34 SPC Site General Arrangement Dry Conversion Second Floor. .. 10-111 i ! 11-10.35 SPC Site General Arrangement Dry Conversion Third Floor... . 10-112 l ll-10.36 SPC Site General Arrangement Dry Conversion Fourth Floor. .10-113 i ll-10.37 Dry Conversion Simplified Air Flow Diagram... . 10-114 i i 11-1 3. 1 Monitoring Well Description.. 13-5 ! ll-14.1 PNL Critical Experiment Layout (Reference 6). 14-17 l j 11-1 4. 2 B&W Critical Experiment Layout. 14-23 j I l i I i i ^ i i i i I i I l \\ l@ aut o s m a m a t a catt: December 22,1997 vi i SPC-NO.3330.947 (R 1/07/92)
e SiemenS Power Corporation - Nuclear Division EMF 2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 70-1257 I i PART I-L! CENSE CONDITIONS REV. l 36 i i TABLE l-1.1 Specific Locations of Authorized Activities (Cont.d) l l Location SNM Authorized Activity i + ! Laundry Facility Uranium Compounds (up to Cleaning of contaminated I 5 wt% U 235) protective clothing and I equipment. l , UF. Cylinder Storage UF (up to 5 wt% U-235) Outside storage of UF, Areas cylinders (full end empty). Packaged Fuel UO (up to 5 wt% U-235) Outside storage of fuel packed i 2 Storage Areas for shipment; the transport containers are closed, sealed and properly labeled for shipment. Packaged Waste Uranium Compounds (up to Outside storage of
- Storage Areas 5 wt% U-235) contaminated materials j
i (including low level waste and j incinerator ash) which are i packaged, sealed, labeled and externally free of contamination. Process Chemical Uranium Compounds (up to Trcnsfer, mixing, sampling, Waste Storage 5 wt% U-235) storage and solar evaporation Lagoon System of contaminated liquid wastes. 1 Retention Tanks Uranium Compounds (up to Interim storage of potentia!!y 5 wt% U-235) contaminated liquid wastes. High Uranium Solids Uranium Compounds (up to Transfer of uranium bearing Pond 5 wt% U-235) solids, leaching for uranium
- recovery, Schds Trench Uranium Compounds (up to Transfer and storage of 5 wt% U-235) contaminated solids awaiting leaching or burial.
The locations described in this table are shown on the site plan, Figure ll-G, 10.1 autaest amcaron care: October 28,1996 '^ot No : 1-9 sPC No 3330 947 (R 1/07/92)
SiemenS Power Corporation - Nuclear Division eu. e SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO 701257 PART l-LICENSE CONDITIONS . REv I ! 39 l f f TABLE l 1.1 Specific Locations of Authorized Activities (Cont.d) i I I Location SNM Authorized Activity Lagoon Uranium Uranium Compounds (up to Recovery of uranium from Recovery 5 wt% U 235) waste solutions. Ammonia Recovery Uranium Compounds (up to Removal and recovery of Facility 5 wt% U-235) ammonia from uranium contaminated liquid wastes. Lagoon SA IX Uranium Liquid Wastes (up Filtration and ion exchange of Process-ARF Building to 5 wt% U 235 and less uranium liquid wastes. than 140 gU/l concentrations in filters and resins) Any Permanent or Uranium solid waste (up to Sorting and compaction. Portable Building 5 wt% U-235) heving HEPA I i filtration and Isokinetic sampling. UFe Cylinder Uranium Compounds, solid Cylinder recertification Recertification and in water solution (up to activities, including hydrostatic Facility 5 wt% U-235) strength testing, wall thickness measurement, internal examination, and pressure testing. The locations described in this table are shown on the site plan, Figure Il-10.1 ? O AMENDMENT ADPUCATON DATE pAGE No l August 4.1997 1-10 I sPC No.3330 947 (R-1/0742)
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E TF m i E O3 z >O z 3 t- = W Totale 14.3 (Coc*' Z g g COIAPOilElli COralFIC,YPE DISCllSSIOtt OF At.Y SPf'CIAI. O E gI COtilflOLS lfSED / ADDIllOt1Al r-- E t:XPt AtdATIOil Of COf4!Ilot TYPE ITI O p y GEO VOL fila IJAA CCtj CCM MCtl MCM PPC AHA SPA 3O Ek I E ~ Cyllsidsical my Tenh o. Flitare @ c. O and ouier >0 h Equipenent [ T~ U a x c-e < a 4 nondnal X X tises may loclude dissoh Ilon of y 37 y 10 patteis. A C-P g-ZQ Cylindelcal tarsks,it!ters, sauf othes 3 MQ a O eqidgunent less Ilinn Ilds dimension iTl O b ove also approgwleiety spaced so Z Z' ,O 9 assive neuteors intesecthms witti otties erydpmerd win ensidt tri g 5, g acceptal>Ie h, Feniva of geometry O Z E-os speckig hetnoen it ed places of z gO3 erpilpsnent is coritsolleil tey slasagri _O a d in ~ ~ S 9 25' nominal X X tises ero smited to loomogeneous y go lD sokdlons / shusles sista es 110, g ,N powdess, llO,F, azul Af sti f.o 7 3 Cylldwbical tanks, Idfers, asul other O eqidguliesil loss thern tids abnuenkwe g era also approgulately spaced t O g esseWe notettoriIntessottons wille / O m offief eqidpment w!!! #esedt ni X acceptat>le k, fasewe of gerwneley m d or spacing between tued p3cces ni y 9 erydprnent is controtted try alesign Z 8 9 e t y o o T i y ro m m 5 $k E l 5 7' l n _n -v+ -. * ** w --ew, -e-m e e 9!
. a Siemens Power Corporation - Nuclear Division eur.2 f]/ SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-125 \\_ l PART 11 - SAFET) DEMONSTRATION l nev, ! 39 I 10.3.13 UF, Cylinder Recertification Facility (CRF) HVAC System The general features of the CRF HVAC system include a combination of a once-through airflow and recirculation supply system (K66) and a double HEPA filtered exhaust system (K67). A simplified schematic diagram of the HVAC system is shown in Figure ll-10.38. 10.3.13.1 K66 Air Suoolv and Recirculation System i j! l l The K66 air supply and recirculation system supplies approximately 450 ft'/ min, of ) outside air and also recirculates approximately 2350 ft'/ min, of building air. l j Recirculated air is passed through a roughing filter and a single HEPA filter with an l l installed efficiency of 99.95% for 0.8 micron DOS cold-generated aerosol. Provision is made in the K66 recirculation system for continuous alpha radiation monitoring of
- recirculated air upstream of the HEPA filter bank. The alpha air monitor is set to alarm
! and annunciate when alpha activity exceeds 40 DAC-br. i p/ 10.3.13.2 K67 Air Exhaust System \\ v / 'r supplied to the CRF, plus infiltration, is exhausted through the K67 exhaust s ster-The double HEPA filter arrangement in this system consists of the final HEPA l fw i bank and upstream primary HEPA filter bank. { l l \\ I The K67 system exhaust air (approximately 950 ft'/ min.) passes from the two stage ! HEPA filter bank through the main exhaust fan, past a duct air monitor (measuring { l airflov quantities) and is discharged from a stack extending 20 ft above ground on the i south side of the building. The K67 exhaust system has one fan which is connected l l to normal power. All final HEPA filters are in-place tested to be 99.95% minimum 1 l efficient fo 0.8 micron DOS cold-generated aerosol. ! 10.3.13.3 System Controls ! The HVAC systems are controlled with temperature, pressure and flow sensor i ! actuating valving and damper positions to hold temperatures, pressures, and pressure ! differentials constant in the various building areas. The K66 supply air system is interlocked with the K67 exhaust system to prevent operation of the K66 supply air system without the K67 exhaust system operating. Pressure sensors are provided to i maintain a min 5um negative differential pressure of 0.05 inch water gauge in the building relative to the atmosphere, p ) 4 LJ ' AMENOMENT APPLICATON DATE: ' PAGE NO.: August 4.1997 10-50a i l sPC-ND 33JO 947 (R-1/07/92)
SiemenS Fower Corporation - Nuclear Division EMF 2 GPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 701257 l PART 11 - SAFE.Y DEMONSTRATION REV. 39 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 suppiy system. l i I i l l An automatic visual alarm is activated when the recirculation system is inoperable. I 10.3.13.4 HEPA Filter Bank t 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 I i 2 1000 ft / min at one-inch water gnuge pressure drop and are mounted in welded steel ! frames. Continuous air samplers are installed downstream of the filter bank. Visual I indicators for reading the pressure drop across the filters are permanently installed, { and means are provided for in place dos testing. The HEPA filter medium is 100 % moisture-resistant fiberglass, pleated over corrugated separators and sealed in fire-resistant plywood frames. The individual i filters are certified to remove 99.97% of 0.3 micron particles and meet or exceed 1 Military Specification MIL-F-51079. i 1 i i i eI mussousNT amxarrw onte pacewo: August 4,1997 10-50b sPC-ND 3330 947 (R it07/92)
'4 EMF 2 Revision 39-APPLICATION FOR RENEWAL OF-SPECIAL NUCLEAR MATEMIAL LICENSE NO SNM 1227 (NRC DOCKET NO. 70 1257) Distribution D. L. - Aelt B. F. Bentley (4) J. B. Edgar B. N, Femreite R. L. Feuerbacher O J. W. Fredericks S. F. Gaines W. G. Keith D. C. Kilian L. J. Maas C. D. Manning - C. S. Powers T. C. Probasco A. Reparaz 1. J. Urza R. E. Vaughan C. A. Ward L. D. Weaver USNRC/M.F. Weber (6) USNRC-RIV WCFO/C.A. Hooker DOH/L. Wainhouse Document Control (5) O}}