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i ,: - DF 1 - DF 3 - DF 3 DFJ - DF G Metal Waste Containers/ Drums Piue Ovwzlck Corttahers Tbe B Shi~~in~ Containers Desim Features Buildi~i~ Structure / Intermi Fire Barrier Ifire rated wall and fxe doors smmtina office area from Room 1341 Building Structurz : Exterior Walls and Concrete Roofs Building Stnicture / Hallwav Floor Comressed Gas Cvlinders Operation of the Building 991 Complex in conformance with this authorization basis assures there will be no undue risk to workers and the public. Revision September 1999 vi Building 991 Complex FSAR I
References Revision 1 SepTember 1999 Nuclear Safety Analysis Reports, DOE Order 5480.23, U. S. Department of Energy, Washington, D.C., April 30, 1992. Technical Safety Requirements, DOE Order 5480.22, U. S. Department of Energy, Washington, D.C., 1992. Document of Example Technical Safety Requirements, Volume I , Defense Programs, U. S. Department of Energy, Washington, D.C., November 1993. Safety Anafysis Report, Code of Federal Regulations, 10 CFR 830.110, U. S. Department of Energy, Washington, D.C., 1995. Guidance for Preparation of DOE 5480.22 PR) and DOE 5480.23 (SAR) Implementation Plans, DOESTD-3011-94, U. S. Department Of Energy, Washingt~~ D.C., November, 1994. Hazard Characterization and Accident Analysis Techniques for Compliance with DOE Order 5480.23, Nuclear Sale9 Analysis Reports, DOE-STD-1027-92, U. S. Department of Energy, Washington, D.C., Decembm, 1992. Preparation Guide for U. S. Department of Energy Non-reactor Nuclear Facility Safety Anafysis Reports, DOE-STD-3009-94, U. S. Deparhnent of Energy, Washington, D.C., July, 1994. Safe9 Analysis and Review System, DOE Order 5481.1B, U. S. Department of Energy, Washington, -D.C., September, 1986. Safe@ of Nuclear Facilities, DOE Order 5480.5, U. S. Department of Energy, Washington, D.C., September, 1986. vii Building 991 Complex FSAR i -
Page 2 and 3: ,._I REVIEW AND APPROVAL FOR BUILDI
Page 4 and 5: i L- FACILITY OVERWEW The Building
Page 6 and 7: Based on the information in Table 1
Page 10 and 11: AB AC ACI ALARA Am AOL ARCIE ASME B
Page 12 and 13: j ?,.- LCO L.L.C. LLW LSDW MAL MAR
Page 14 and 15: V Volt WAD Work Authorization Docum
Page 16 and 17: . 2.3.1 Fire Suppression. Detection
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Page 24 and 25: Chapter 6 Derivation of Technical S
Page 26 and 27: Table 1-1 DOE-STD-3009 and Building
Page 28 and 29: identified along with the change in
Page 30 and 31: area), and other types of hazardous
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Page 34 and 35: contamen received Accuracy Report &
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Page 38 and 39: polishing equipment. The Metallogra
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Page 42 and 43: specified in HSP 11.03 were met by
Page 44 and 45: USQD-991-98.0900-MIU (Ref. 20) was
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Page 50 and 51: During the 1980s, Final Quality Cer
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Bearing walls and intermediate conc
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concrete structure with exterior di
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1 ,j I Minor cracks and leaking hav
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uilding. Differential displacement
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in wooden waste containers and stor
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THIS PAGE HAS BEEN LEFT BLANK DUE-T
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Table 2-1 Fire Suppression Systems
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The sprinkler system consists of a
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connect hoses to a hydrant and flow
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Revision I Scptcmber 1999 Figure 2-
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filters against the impacts of larg
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2.3.2 Heating, Ventilation, and Air
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The S-1 system has outside air damp
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Supplv Zone 4 (S-4) The S-4 supply
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Table 2-2 Building 991 Complex Exha
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system contains an untested HEPA st
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The burners are Model LNR 8.4-G-20
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LSDW speakers are located throughou
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2.3.5.2 Steam and Condensate System
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2.3.5.4 Domestic Process Water Syst
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component (Schedule 40 pipe with 6-
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18 19 20 21 22 23 24 25 Building 99
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the successful completion of a PSC'
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hazards analysis approach to be use
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Site Integrating Management Contrac
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The Criticality Safety program is e
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safety SSCs relies on the developme
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3.14 RADIATION PROTECTION The Radia
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activities and hazard assessment an
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18 19 20 21 22 23 24 25 26 27 28 29
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*I L\ '. '/ CHAPTER 4 HAZARD AND AC
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pertinent to FSAR preparation, haza
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Facilities, DOE-HDBK-30 10-94 (Ref.
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PDC is the plume duration correctio
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0 Hazard Warning - The availability
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For hazardous materials that did no
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4.4.2 Hazard Classification The DOE
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scenarios. A total of 37 event tree
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Revision 1 Scpinnher 19% (2) extrem
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determined to represent a Standard
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The extremely unlikely impact of a
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750 Pad tank farm that migrates to
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4 3 M a p: X - a E 0 U N U
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4.6 RISK DOMINANT ACCIDENT SCENARIO
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A"" and Room 170 (including connect
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area, or the Building 996 waste sto
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consequence is low (0.084rem). If'
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! Movernent of waste containers fro
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The risk and conseauences of Punctu
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i ’ i, ! U” In summary, removal
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4 2 3 k J M fi .I 4 2 n
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ch ch
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I 1 I a rj i Y 4 d L J
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3 ci 3 N n i
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4.8 SAFETY ANALYSIS ASSUMPTIONS AND
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W 3
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c: --c m m 3
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I f dl
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c 3
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, UI
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~ 16 17 18 19 20 21 22 23 24 Revisi
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It Tip: 3 *-- Revision 1 September
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6.1 INTRODUCTION 6. DERIVATION OF T
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4 7 : i Maintenance of this Design
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NI -1 -4 Y) d
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-I I I c? 8 3 rA \ \ I I
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6.4 ADMINISTRATIVE CONTROLS 6.4.1 I
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; c .- > c .s cat 0 0 P d Q ?- VI 0
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H .I L * m CII 0 L c, El s .- c, E
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x .I L Y m 0 L E I Y 6 P) m L Y m .
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P d
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I ea 0 " E3 O Q zs P I .- 3 " 5 2 d
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n L .I c, 5! c! U
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6.5 TSR DERIVATION The TSRs were de
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6.6 REFERENCES 1 Safety Analysis fo
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Revision 1 September 1999 CHAPTER 5
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5.1 INTRODUCTION 5. SAFETY STRUCTUR
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Conditions for Operations (LCOs) in
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.-. g: ai cej ?i i:
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EI .- .- 4 3 I
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5.2.2 SC-3 SSCS This section summar
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5.3 SSC SAFETY CATEGORY DESfGNATIUl
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-I i
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0 N n
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APPENDIX A BUILDING 991 COMPLEX TEC
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5B.4.2 CREDITED PROGRAMMATIC ELEMEN
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TERM ' AFFECTED AREA BASISBASES BUI
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TERM OUT-OF-SERVICE OUT-OF-TOLERANC
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1.2 ACRONYMS AC AOL CSE DOE DOT FEV
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limits on container radioactive mat
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1.2 LOGICAL CONNECTORS (continued)
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2. SAFETY LIMITS AND LIMlTING CONTR
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LCO 3.0.7 LCO 3.0.8 LCO 3.0.9 LCO 3
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LCO 3.0.6 (cont.) Calibration that
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LCO 3.0.8 Planned OUT-OF-TOLERANCES
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3./4. LIMITING CONDITIONS FOR OPERA
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3./4. LIMITING CONDITIONS FOR OPERA
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BASES BACKGROUND The BUILDING 991 C
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BASES REQUIRED ACTION A. 1 LCO 3.1
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BASES ~ ~~~ ~ REQUIRED ACTION A.2 (
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BASES REQUIRED The four-hour COMPLE
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BASES REQUIRED ACTION C.2 (continue
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7 ;' LT 6, BASES REQUDRED ACTION D.
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BASES RE0UIKE.D ACTION E. 1 Revisio
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SURVEILLANCE REQUIREMENTS ]BASES SR
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3.2 LIMITING CONDITION FOR OPERATEO
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S LRkEIL LANCE REQLZEMEhT SR 4.2.1
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BASES BACKGROChD (continued) The Bu
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BASES BACGGROVhD (continued) APPLIC
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BASES APPLICA'TION TO SAFETY rzN At
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BASES REOUIRED ACTION A. I [continu
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BASES REO U1RE.D ACTION C 1 [contin
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BASES REQUIRED ACTION E. I REQUIRED
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?I 1i-l ~~ ~ ~ SR 4.2.1 The verific
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3J4. LIILlXTfNG CONDXTlUKS FOR OPER
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3.M. IJIR/EITXNG COLWXTIONS FOR OPE
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BASES BA4CKGRO'L'KD (continued) Rev
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BASES APPLICABILITY Jlis LCO is app
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BASES REO UIRED ACTIONB 1 The Build
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BASES REQUIRED ACTION B.2.2 {contin
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SK4 3.1 Thc verification of the com
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SURVEILLANCE RE 0 UIREMENTS 3A SE S
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, -I ,.i ’-, \ 5.0.3 AC Programma
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5.1 5.1.1 5.1.2 5.1.3 ORGANIZATION
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5.2 5.2.1 5.2.2 INVENTORY CONTROL A
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AOL 2 SNM containers staged in the
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AOL 4 The quantities of radioactive
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AOL 5 Wooden LLW crates stored at t
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AOL 7 All pallets of waste containe
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2 4’1 ACTIONS: CONDITION 1. ODmti
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5.3 CONTROL OF COMBUSTIBLE MATERIAL
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ACTIONS: CONDITION 1. High heat rel
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AOL 10 A flammable gas use control
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5.4 5.4.1 5.4.2 5.4.3 Revision 1 Sc
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Revision 1 Szptcrnber 1999 Table 2
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5.6 5.6.1 Revision I Sntcrnher t999
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-I -)y 5.8.1 fieauirenients for Wor
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5B.0 GENERAL APPLICATION BASES Revi
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5B. 1 ORGANIZATION AND MANAGEMENT B
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5B.2 INVENTORY CONTROL AND MATERIAL
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AOL 1 POC and waste containers are
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, 1 \,?i AOL 3 BASIS (cont'd) AOL 4
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AOL 5 This AQL applies to wooden LL
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AOL 7 BASIS (cont'd) AOL 8 BASIS: R
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AOL 8 BASIS [cont'dj Revision 1 Sep
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5B.3 CONTROL OF COMBUSTIBLE MATERIA
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-7 “q Y AOL 9 BASIS Combustible m
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5B.4 MAINTENANCE AND SURVEILLANCE O
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' I *r- ;:x 5B.5 EMERGENCY RESPONSE
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5B.S WORK COYTROL BASES 5B.S.l Requ
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6 DESIGN FEATURES The purpose of th
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7 REFERENCES A- 1 A-2 A-3 A4 A-5 A4
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k e- .. _. . .~,
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' Building 991 Complex FSAR/NSTR Ch
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1 Revisions NSTR-011-98. Safety Ana
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