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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20073T0701994-07-0101 July 1994 Reports Changes & Errors in ECCS Evaluation Models ML20090J9651992-03-11011 March 1992 Forwards Piping Design Insps,Tests,Analysis & Acceptance Criteria (Itaac).Piping Design ITAAC Will Be Included as Part of Generic ITAAC ML20090J9701992-03-11011 March 1992 Forwards Proprietary Responses to Issues Re Sections 9.3,9.5 & 11.2 of Advanced BWR Ssar.Responses Reflect Correctons & Additions to Earlier Proprietary Submittals.Responses Withheld ML20090J9791992-03-11011 March 1992 Forwards Responses to Resolution of Issues Related to Advanced BWR Draft SER Chapters 1,2,3,5,6,9,10,12,13,14 & 15 (SECY-91-355) ML20090J9941992-03-11011 March 1992 Forwards Draft Rev 0 to Advanced BWR Srvdl Wetwell Piping Stress Analysis Design Rept & Draft Rev 0 to Design Rept, Main Steam Line a & Safety Relief Valve Discharge Piping Stress Analysis, Per 911209-10 Ge/Nrc Meeting ML20090G5801992-03-0909 March 1992 Summerizes Staff Position Re NRC Conference Call on Dser Comments to Advanced BWR Ssar ISI Requirements ML20090F6171992-03-0505 March 1992 Forwards Rev B to 23A6100AQ,Section 17.3 Re Responses to Request for Resolution of Issues Related to Reliability Assurance Program (Rap).Subj Responses Will Be Included as Amend to Advanced BWR Ssar in Future ML20094G9691992-03-0202 March 1992 Forwards Radwaste Bldg Seismic Analysis. Informs That GE Intends to Amend Ssar W/Subj Analysis in Future Amend ML20094G7141992-02-25025 February 1992 Forwards Proprietary Revised App 18E, Advanced BWR Man-Machine Interface Sys Design & Implementation Process, of Advanced BWR Ssar.App Withheld ML20092N1451992-02-25025 February 1992 Requests Addition of Listed Individual to Advanced BWR Document Distribution List ML20094G7401992-02-25025 February 1992 Forwards Proprietary Summary of 920127 Telcon W/Nrc & Brookhaven Lab to Clarify Aspects of Human Factors Review of Advanced Bwr,Specifically Review of Design Implementation Process.Summary Withheld ML20090A0441992-02-25025 February 1992 Forwards Proprietary Rev R-0 to Advanced BWR Project Common Engineering Work Plan. Plan Withheld ML20092L0801992-02-25025 February 1992 Forwards App 19P to Chapter 19 of Evaluation of Potential Mods to Advanced BWR Design ML20090B1881992-02-24024 February 1992 Forwards Draft Rev 0 to Advanced BWR Ssar Main Steam, Feedwater & Srvdl Piping Sys Design Criteria & Analysis Methods & Draft Rev 0 to Advanced BWR Feedwater Loop a Piping & Equipment Loads, Per Ge/Nrc 911209-10 Meeting ML20092M2931992-02-20020 February 1992 Forwards Discussion of Differences Between Us Advanced BWR & K-6/7 Project.Advanced BWR Design Under Review for for Differences to K 6/7 & Addl Differences Will Be Included in Future Ssar Amend ML20094G7201992-02-17017 February 1992 Forwards Proprietary Revised App 18E, Advanced BWR Man-Machine Interface Sys Design & Implementation Process, of Advanced BWR Ssar.App Withheld ML20092F4241992-02-14014 February 1992 Forwards Proprietary Portion of GE Response to Agenda Items Discussed During 911120-21 Meeting W/Nrc Reactor Sys Branch. Response Withheld ML20092F4601992-02-14014 February 1992 Forwards Nonproprietary Portion of GE Response to Agenda Items Discussed During 911120-21 Meeting W/Nrc Reactor Sys Branch Re Standby Liquid Control Sys Instrumentation & Controls ML20092F4971992-02-13013 February 1992 Forwards Proprietary App 18F, Emergency Operation Info & Controls to Chapter 18, Human Factors Engineering of Advanced BWR Std SAR Covering Control Room Inventory.App 18F Withheld ML20092F5251992-02-11011 February 1992 Responds to Performance & Quality Evaluation Branch Open Items on Advanced BWR Std SAR Chapter 14 ML20092F5181992-02-10010 February 1992 Forwards Responses to 920110-16 Requests for Addl Info on Advanced BWR Design for Severe Accidents ML20092C0251992-02-0303 February 1992 Forwards Proprietary Responses to Addl Info Noted in 911004 Draft SER for Chapter 7.Responses Are Cross Ref W/Summary Item Number Corresponding to Review Meeting in San Jose on 910807 & 08.Responses Withheld ML20092C1671992-02-0303 February 1992 Forwards Nonproprietary Responses to Addl Items of Concern Noted in Draft SER for Chapter 7.Advises That GE Will Amend Advanced BWR Ssar W/Responses in Future Amend ML20092C1831992-02-0303 February 1992 Forwards Response to Leak Before Break Issue Addressed in 911209-10 Ge/Nrc Meeting.Advises That GE Intend to Amend Ssar W/Response in Future Amend ML20100P9651992-01-31031 January 1992 Forwards Proprietary NEDC-30032 Joint Study Final Rept - Joint Study W/Regard to 'Study (II) Related to Advanced Bwr' - Thermal Margin During Rapid Coastdown,820401-830331. Rept Withheld ML20091K8911992-01-22022 January 1992 Forwards Response to Open Issue 3 of SECY-91-153 Re Main Steam Line Seismic Classification Including,Static Design Procedure to Be Utilized in Evaluation of Seismic Capability of Condenser Anchorage & Turbine Bldg ML20094E4571992-01-17017 January 1992 Forwards Tier 1 Design Certification Matl,Pilot Itacc Examples for GE Advanced BWR Design & Advanced BWR Design Certification Generic ITAAC for Seismic Category 1 Structures,Position Paper ML20087D2641992-01-10010 January 1992 Forwards Response to Agenda Items 1,5,9 & 16 Discussed at Ge/Nrc Reactor Sys Branch 911120-21 Meetings.Items Include, Stability Performance in Normal Operating Region,Loss of Ac Power & Loss of Feedwater Heating Transient ML20087D4771992-01-10010 January 1992 Forwards Responses to Agenda Item 12 Discussed During 911120-21 Meeting W/Reactor Sys Branch of Nrc.Responses Withheld ML20087D0011992-01-0606 January 1992 Forwards Proprietary Tables to App 18F to Chapter 18 Re Human Factors Engineering.Ge Will Amend Ssar to Include Subj Info in Future Amend.Encl Withheld ML20087B7161992-01-0606 January 1992 Forwards Response to Issues Raised at Ge/Nrc 911209-10 Meetings Re Inservice Insp Relief Requests for Reactor Pressure Vessel Bottom Head Weld & Reactor Pressure Vessel Bottom head-to-shell Weld ML20086U5451992-01-0606 January 1992 Forwards Response to NRC Request for Addl Info Re Incorporation of Operating Experience in Advanced BWR ML20086U1941991-12-20020 December 1991 Confirms That Licensee Advanced BWR Application Should Be Processed as Application for Part 52 Final Design Approval & Subsequent Design Certification Per 10CFR52.45 ML20086N9601991-12-19019 December 1991 Forwards Proprietary & Nonproprietary Versions of Rev B to Update of App 9A, Reactor Bldg Fire Hazard Analysis ML20086P2161991-12-19019 December 1991 Forwards Proprietary Responses to Resolution of Issues Re Advanced BWR Draft SER ML20086P2251991-12-19019 December 1991 Forwards Nonproprietary Responses to Resolution of Issues Re Advanced BWR Draft SER ML20091H4061991-12-13013 December 1991 Forwards Selected Sections of Chapter 9, Auxiliary Sys & Chapter 18, Human Factors Engineering of Ssar for Advanced Bwr,Amend 19,including Update of Control Bldg Fire Protection Drawings.Encl Withheld ML20086N2161991-12-13013 December 1991 Forwards Amend 19 to Advanced BWR Ssar ML20094D2041991-12-12012 December 1991 Forwards Proposed Advanced BWR Tech Specs,Per Vendor to Nrc.Specs Will Be Documented Via Amend to Chapter 16 of Advanced BWR Ssar,Once Specs Finalized ML20086H5741991-12-0202 December 1991 Describes Plan for Submitting Advanced BWR Tech Specs to Nrc,Per 911108 Meeting.First Submittal of Noninstrumentation & Control Sys Will Be Submitted by 911213.Third Submittal Re 65 Unchanged LCOs Will Be Submitted by 920131 ML20086H6101991-11-27027 November 1991 Forwards Responses to Open Issues in GE Advanced BWR Ssar Chapter 8 Re Offsite Power Sys & Protective Sys for Reactor Internal Pumps,Per 910916-18 Meeting W/Nrc.Proprietary Versions of Response Withheld ML20086H6161991-11-27027 November 1991 Forwards Proprietary Responses to Open Issues 8.3.3.6 & 8.3.5 for Advanced BWR Ssar,Chapter 8,per Commitment at 910916-18 Meeting in San Jose.Encl Withheld ML20086E4831991-11-25025 November 1991 Forwards Tables Re Significant New Open Issues Included in Final,Draft Ser,Significant Open Items Included in All Draft Sers,Ge Future Submittals & Proposed Issues for Discussion at Dec Mgt Meeting,Per NRC ML20086C7201991-11-12012 November 1991 Forwards Proprietary Draft Writeup for Fire Protection PRA, as Requested in Draft SER on Advanced BWR Pra,Per SECY-91-309,dtd 911001.Encl Withheld ML20086A8121991-11-12012 November 1991 Forwards Draft Writeup for Fire Protection Probabilistic Risk Assessment Requested in Draft SER on Advanced BWR Probabilistic Risk Assessment.Ge Will Amend Ssar to Include Info When Finalized ML20079P1731991-11-0707 November 1991 Forwards Response to Discussion Item 7 from 910906 Conference Call Re Rod Block Algorithm & Setpoint ML20079L7461991-11-0101 November 1991 Forwards Summary of Major Advanced BWR Design Differences, Assessment of How TS Differ from Improved Ts,Including Summary of New,Different or Inapplicable & Example of How TS Would Be Written Where TS Differ from Improved TS ML20079M2561991-11-0101 November 1991 Forwards Proprietary GE Responses to Staff Position Re GE BWR Power Upgrade Program,Dtd 910930.Responses in Ref to Licensing Topical Rept NEDC-31897P-1, Generic Evaluations of GE BWR Power Uprate,June 1991. Responses Withheld ML20079L3121991-10-25025 October 1991 Forwards Rept Providing Update of in-reactor Surveillance Programs & Overall GE BWR Fuel Experience Through Dec 1990 ML20058L6811991-10-25025 October 1991 Forwards Rept Providing Update of in-reactor Surveillance Programs & Overall GE BWR Fuel Experience Through Dec 1990 1994-07-01
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20073T0701994-07-0101 July 1994 Reports Changes & Errors in ECCS Evaluation Models ML20090J9651992-03-11011 March 1992 Forwards Piping Design Insps,Tests,Analysis & Acceptance Criteria (Itaac).Piping Design ITAAC Will Be Included as Part of Generic ITAAC ML20090J9701992-03-11011 March 1992 Forwards Proprietary Responses to Issues Re Sections 9.3,9.5 & 11.2 of Advanced BWR Ssar.Responses Reflect Correctons & Additions to Earlier Proprietary Submittals.Responses Withheld ML20090J9791992-03-11011 March 1992 Forwards Responses to Resolution of Issues Related to Advanced BWR Draft SER Chapters 1,2,3,5,6,9,10,12,13,14 & 15 (SECY-91-355) ML20090J9941992-03-11011 March 1992 Forwards Draft Rev 0 to Advanced BWR Srvdl Wetwell Piping Stress Analysis Design Rept & Draft Rev 0 to Design Rept, Main Steam Line a & Safety Relief Valve Discharge Piping Stress Analysis, Per 911209-10 Ge/Nrc Meeting ML20090G5801992-03-0909 March 1992 Summerizes Staff Position Re NRC Conference Call on Dser Comments to Advanced BWR Ssar ISI Requirements ML20090F6171992-03-0505 March 1992 Forwards Rev B to 23A6100AQ,Section 17.3 Re Responses to Request for Resolution of Issues Related to Reliability Assurance Program (Rap).Subj Responses Will Be Included as Amend to Advanced BWR Ssar in Future ML20094G9691992-03-0202 March 1992 Forwards Radwaste Bldg Seismic Analysis. Informs That GE Intends to Amend Ssar W/Subj Analysis in Future Amend ML20094G7401992-02-25025 February 1992 Forwards Proprietary Summary of 920127 Telcon W/Nrc & Brookhaven Lab to Clarify Aspects of Human Factors Review of Advanced Bwr,Specifically Review of Design Implementation Process.Summary Withheld ML20090A0441992-02-25025 February 1992 Forwards Proprietary Rev R-0 to Advanced BWR Project Common Engineering Work Plan. Plan Withheld ML20094G7141992-02-25025 February 1992 Forwards Proprietary Revised App 18E, Advanced BWR Man-Machine Interface Sys Design & Implementation Process, of Advanced BWR Ssar.App Withheld ML20092N1451992-02-25025 February 1992 Requests Addition of Listed Individual to Advanced BWR Document Distribution List ML20092L0801992-02-25025 February 1992 Forwards App 19P to Chapter 19 of Evaluation of Potential Mods to Advanced BWR Design ML20090B1881992-02-24024 February 1992 Forwards Draft Rev 0 to Advanced BWR Ssar Main Steam, Feedwater & Srvdl Piping Sys Design Criteria & Analysis Methods & Draft Rev 0 to Advanced BWR Feedwater Loop a Piping & Equipment Loads, Per Ge/Nrc 911209-10 Meeting ML20092M2931992-02-20020 February 1992 Forwards Discussion of Differences Between Us Advanced BWR & K-6/7 Project.Advanced BWR Design Under Review for for Differences to K 6/7 & Addl Differences Will Be Included in Future Ssar Amend ML20094G7201992-02-17017 February 1992 Forwards Proprietary Revised App 18E, Advanced BWR Man-Machine Interface Sys Design & Implementation Process, of Advanced BWR Ssar.App Withheld ML20092F4241992-02-14014 February 1992 Forwards Proprietary Portion of GE Response to Agenda Items Discussed During 911120-21 Meeting W/Nrc Reactor Sys Branch. Response Withheld ML20092F4601992-02-14014 February 1992 Forwards Nonproprietary Portion of GE Response to Agenda Items Discussed During 911120-21 Meeting W/Nrc Reactor Sys Branch Re Standby Liquid Control Sys Instrumentation & Controls ML20092F4971992-02-13013 February 1992 Forwards Proprietary App 18F, Emergency Operation Info & Controls to Chapter 18, Human Factors Engineering of Advanced BWR Std SAR Covering Control Room Inventory.App 18F Withheld ML20092F5251992-02-11011 February 1992 Responds to Performance & Quality Evaluation Branch Open Items on Advanced BWR Std SAR Chapter 14 ML20092F5181992-02-10010 February 1992 Forwards Responses to 920110-16 Requests for Addl Info on Advanced BWR Design for Severe Accidents ML20092C0251992-02-0303 February 1992 Forwards Proprietary Responses to Addl Info Noted in 911004 Draft SER for Chapter 7.Responses Are Cross Ref W/Summary Item Number Corresponding to Review Meeting in San Jose on 910807 & 08.Responses Withheld ML20092C1671992-02-0303 February 1992 Forwards Nonproprietary Responses to Addl Items of Concern Noted in Draft SER for Chapter 7.Advises That GE Will Amend Advanced BWR Ssar W/Responses in Future Amend ML20092C1831992-02-0303 February 1992 Forwards Response to Leak Before Break Issue Addressed in 911209-10 Ge/Nrc Meeting.Advises That GE Intend to Amend Ssar W/Response in Future Amend ML20100P9651992-01-31031 January 1992 Forwards Proprietary NEDC-30032 Joint Study Final Rept - Joint Study W/Regard to 'Study (II) Related to Advanced Bwr' - Thermal Margin During Rapid Coastdown,820401-830331. Rept Withheld ML20091K8911992-01-22022 January 1992 Forwards Response to Open Issue 3 of SECY-91-153 Re Main Steam Line Seismic Classification Including,Static Design Procedure to Be Utilized in Evaluation of Seismic Capability of Condenser Anchorage & Turbine Bldg ML20094E4571992-01-17017 January 1992 Forwards Tier 1 Design Certification Matl,Pilot Itacc Examples for GE Advanced BWR Design & Advanced BWR Design Certification Generic ITAAC for Seismic Category 1 Structures,Position Paper ML20087D2641992-01-10010 January 1992 Forwards Response to Agenda Items 1,5,9 & 16 Discussed at Ge/Nrc Reactor Sys Branch 911120-21 Meetings.Items Include, Stability Performance in Normal Operating Region,Loss of Ac Power & Loss of Feedwater Heating Transient ML20087D4771992-01-10010 January 1992 Forwards Responses to Agenda Item 12 Discussed During 911120-21 Meeting W/Reactor Sys Branch of Nrc.Responses Withheld ML20087D0011992-01-0606 January 1992 Forwards Proprietary Tables to App 18F to Chapter 18 Re Human Factors Engineering.Ge Will Amend Ssar to Include Subj Info in Future Amend.Encl Withheld ML20087B7161992-01-0606 January 1992 Forwards Response to Issues Raised at Ge/Nrc 911209-10 Meetings Re Inservice Insp Relief Requests for Reactor Pressure Vessel Bottom Head Weld & Reactor Pressure Vessel Bottom head-to-shell Weld ML20086U5451992-01-0606 January 1992 Forwards Response to NRC Request for Addl Info Re Incorporation of Operating Experience in Advanced BWR ML20086U1941991-12-20020 December 1991 Confirms That Licensee Advanced BWR Application Should Be Processed as Application for Part 52 Final Design Approval & Subsequent Design Certification Per 10CFR52.45 ML20086N9601991-12-19019 December 1991 Forwards Proprietary & Nonproprietary Versions of Rev B to Update of App 9A, Reactor Bldg Fire Hazard Analysis ML20086P2251991-12-19019 December 1991 Forwards Nonproprietary Responses to Resolution of Issues Re Advanced BWR Draft SER ML20086P2161991-12-19019 December 1991 Forwards Proprietary Responses to Resolution of Issues Re Advanced BWR Draft SER ML20091H4061991-12-13013 December 1991 Forwards Selected Sections of Chapter 9, Auxiliary Sys & Chapter 18, Human Factors Engineering of Ssar for Advanced Bwr,Amend 19,including Update of Control Bldg Fire Protection Drawings.Encl Withheld ML20086N2161991-12-13013 December 1991 Forwards Amend 19 to Advanced BWR Ssar ML20094D2041991-12-12012 December 1991 Forwards Proposed Advanced BWR Tech Specs,Per Vendor to Nrc.Specs Will Be Documented Via Amend to Chapter 16 of Advanced BWR Ssar,Once Specs Finalized ML20086H5741991-12-0202 December 1991 Describes Plan for Submitting Advanced BWR Tech Specs to Nrc,Per 911108 Meeting.First Submittal of Noninstrumentation & Control Sys Will Be Submitted by 911213.Third Submittal Re 65 Unchanged LCOs Will Be Submitted by 920131 ML20086H6161991-11-27027 November 1991 Forwards Proprietary Responses to Open Issues 8.3.3.6 & 8.3.5 for Advanced BWR Ssar,Chapter 8,per Commitment at 910916-18 Meeting in San Jose.Encl Withheld ML20086H6101991-11-27027 November 1991 Forwards Responses to Open Issues in GE Advanced BWR Ssar Chapter 8 Re Offsite Power Sys & Protective Sys for Reactor Internal Pumps,Per 910916-18 Meeting W/Nrc.Proprietary Versions of Response Withheld ML20086E4831991-11-25025 November 1991 Forwards Tables Re Significant New Open Issues Included in Final,Draft Ser,Significant Open Items Included in All Draft Sers,Ge Future Submittals & Proposed Issues for Discussion at Dec Mgt Meeting,Per NRC ML20086C7201991-11-12012 November 1991 Forwards Proprietary Draft Writeup for Fire Protection PRA, as Requested in Draft SER on Advanced BWR Pra,Per SECY-91-309,dtd 911001.Encl Withheld ML20086A8121991-11-12012 November 1991 Forwards Draft Writeup for Fire Protection Probabilistic Risk Assessment Requested in Draft SER on Advanced BWR Probabilistic Risk Assessment.Ge Will Amend Ssar to Include Info When Finalized ML20079P1731991-11-0707 November 1991 Forwards Response to Discussion Item 7 from 910906 Conference Call Re Rod Block Algorithm & Setpoint ML20079M2561991-11-0101 November 1991 Forwards Proprietary GE Responses to Staff Position Re GE BWR Power Upgrade Program,Dtd 910930.Responses in Ref to Licensing Topical Rept NEDC-31897P-1, Generic Evaluations of GE BWR Power Uprate,June 1991. Responses Withheld ML20079L7461991-11-0101 November 1991 Forwards Summary of Major Advanced BWR Design Differences, Assessment of How TS Differ from Improved Ts,Including Summary of New,Different or Inapplicable & Example of How TS Would Be Written Where TS Differ from Improved TS ML20079L3121991-10-25025 October 1991 Forwards Rept Providing Update of in-reactor Surveillance Programs & Overall GE BWR Fuel Experience Through Dec 1990 ML20085K2631991-10-25025 October 1991 Forwards Addl Documents,In Response to NRC Re Resolution of Issues Related to Chapter 18 of Ssar for Advanced BWR Design.Documents Withheld 1994-07-01
[Table view] |
Text
_. _ __ _
( )
, Gi Nuclear (netyy r ,,
November 12,1991 hil:N No.143 91 Docket No. STN 50-605 lil!N 9180 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attentiom Itobert C Pierson, Director Standardization and Non Power 1(cactor Project Directorate
Subject:
Fire Protection Prohnhilistle Risk Assessment, AllWR SSAR drall Appendix 19h1
Reference:
- 1. SIICY 9b309, dated October 1,1991
- 2. Fire Protection Probabilistic Risk Assessment, AllWR SSAR draf t Appendix 19M, Proprietary Information, MFN No.
144 91, dated November 12,1991
- 3. Submittal of Amendment 4 to Gli's AllWit SSAR MFN No.
005 89, dated January 31,1989 Enclosed are thirty four (34) copics of the dralt writeup for the Fire Protection PRA as requested in the Draft Safety livaluation Report on the AllWR PRA (Reference 1). This draf t was performed based on the same methods and models used for the original Pila (iteference 3). As a result of design changes that have occurred since that PRA submittal, the PRA model will be revised to reflect these changes and a new Pila, including Fire Protection, will be submitted next year. The results of the updated Fire Protection l'RA are not expected to be significantly different from the draft results contained in this submittal.
A major portion of the subject material contains information that is designated as General lilectsic Company proprietary information and is being submitted under separate cover (Reference 2).
It is intended that GE will amend the SSAll to include this information when it is finalized.
Sincerely, O
/ ,
t/
l P.W. hbrriott, Manager Regulatory and Analysis Services M/C 382, (408) 925 6948 cc: F. A. Ross (DOli)
N. D. Fletcher (Doli) i C. Posiusny, J r. (NRC) ']/
R. C. llerglund (GI!)
J.F.Ouirk ( 0 11) l p 9111190373 911112 /
PDR; ADOCK 05000603 t., PDR
P APPENDIX 19M -
FIRE PROTECTION PROIIAllILISTIC RISK ASSESSMENT L
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ABWR z w.i m s Slundard Plant nca APPENDIX 19M TAllLE OF CONTENTS Secilon 11t[c higc 19M FIRE PROTECTION PROllAlllLISTIC RISK ASSESSMENT I 19ht.1 Introductimi 19ht.1 1 ,
19ht.2 liasis of Analysis 19ht.21 ;
19ht3 Summitty of Results 19ht.3-1 19ht.4 Phase i SctrenIDg_RD.d.1'hnse ll l'irr Freauency Analtsis 19ht.41 19ht.4.1 Phase ! Qualitative Analysis 19ht.41 19ht.4.2 Phase 11 Quantitative Analysis 19ht.4 2 ;
19ht.5 Calculation of the 11re lenillorLFreauency 19ht.5 1 19ht.5.1 General Comments on Completion ,
of FIVE Table 19ht.51 19ht.5.2 Completed Ignition Source Data Sheets and Notes 19ht.5 2 1951.6 Calculation of Core I)aumge F rtqurndra 19ht.61 19ht.6.1 hiethodology 19ht.6-1 19ht.6.2 Results 19ht.6-1 1951.7 Interfqtts 19ht.71 1951.11 }{rferrnces 19ht.8-1 f
4 19ht ii Amendment
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AllWR mams SintidInnllSitilt na SECTION 19M.1 GE l'ItOl'IllETAln' pimided under separate cover l'au Anndant 19M,1 1 l
l Amendment 39g g ,3
ABWR nuuas Sinndani.flatti nev. ^
SECTION 19M.2 GE l'ROl'RIETARY provided under sepatraite cover bM 611!03111titi!!
19M,2 1 Amendment 19M 2-1
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ABWR m<.nms SinililHIllI'lRill . na u
API'ENDIX 19M.3 TAllLE OF CONTENTS TA11LES ljil!!f 110.C l'11MC I 19M31 Fire Ilisk Screening Analysis Summary 19M3 2 I
l ILLUSTitATIONS l l
Deurs Illie P.aut )
l 19M31 l'hase ! Qualitative Analysis Flow Chart 19h13 3 19M3 2 l'hase 11 Oualitative Analysis flow Chari 19M3 4 19M3-il Amendment j
ABWR nums Stalidard1huit u SECTION 19M.3 GE l'ROl'RIETAlW - provided umler separate cover
}.*11XE 8]ll.t11dititJll 19hi31 19N13 2 l
I I
Amendment 19M .2
AllWR ,mtmo l
.Slandard Plant atv 3 ITVE Methodokw Nowmber 2.1WO Draft Report Page 13 of 63 +
?
PHASE I QUALITATIVE ANALYSIS IDENTIFY PLANT FIRE !
AREAS r (Use Table 1 Matris) ,
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t LIST SAFE SHUTDOWN SYSTT.MS (Use Table 1 Mauit)
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!DENI1FY SAFE SHU1VOWN SYSTEMS IN EACH FIRE AREA r
- (Use Table 1 Maint)
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SHUTDOWN EQUIPMENTIN FIRE AREA ,
y Yes FIRE CAUSES DEMAND NO FOR SAFE SHUTDOWN '
EQUIPMENT IM N l SCREENED OUT-t Yes U
SIGNIFICANT FIRE AREAS v
PHASEIII WALKDOWN/
VERIFICA110N OF DATA PHASE!!. ,
QUANITTATTVE ANALYSIS FIGURE 5.1 Figure 19M.3-1 PHASE I QUALITATIVE ANALYSIS FLOW CHART Amendment 19M.3-3 2
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ABWR nunus l Ma_ndard Plant uv4-i rI\T, Methodology November 2. Ifm
' Draft Report Page 18 of 63 P
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ABWR zw.m u l Simidard Elant nna l APPENDIX 19M.4 j TAllLE OF CONTENTS i
SeCilon Til.lf jhigt I 19M.4.1 Phase 1 Ounilinthe l Anchih 19M 41 19M.4.1.1 Identify Plant Fire Areas 19M.4 1 19M.4.1.2 List Safe Shutdown Systems 19M.4-2 19M.4.1.3 Identify Safe Shutdown Systems in Each Fire Arca 19M.4-2 19M.4.1.4 Shutdown Equipment in Fire Area 19M.4 2 19M.4.1.5 Fire Causes Demand for Safe Shutdown Equipment 19M.4 2 19M.4.1.6 Significant Fire Arcas 19M.4-2 19M.42 l' hose 11 Oululutaill .tA_rudnh 19M.4 2 19M.4.2.1 Identify Fire Compartments for Evaluation Purposes 19M.4 2 19M.4.2.2 Evaluate Fire Vulnerability Frequency for Fire Compartment 19M.4 3 19M.4.2.3 Determine Fire igniti(c Frequency 19M.4 3 19M.4.2.4 Choose 19M.4 3 19M.4.2.5 Probability for Redundant / Alternate System Unavailable 19M.4 3 19M.4.2.6 Can Fire Affect Redundant / Alternate Path 19M.4 3 l
19M.4-ii Amendment I
ABWR m,,ims Standard Plant nn. 3 SECTION 19M.4 GE PitOPRIETAltY provided under separate cover htXt Aniendment 19M.41 19M.4 2 19M.4-3 Amendment 19M.4-1 3
ABWR mmms Sandard Plant neu l APPENDIX 19M.5 l
TAllLE OF CONTENTS -
Secilon 31 tis hge 1951.5.1 Liencral Comments On Completion ,
Of FIVI:Tuble 3 19ht.5-1 1951.5.2 Completed lenition Source Data i Sheets and Notes 19ht.5 2
- 19ht.5J Completed Inn 11[un Sources Da.la Sheets and Notes 19ht.5 2 TAllLES Table 1111c bge
-d 19M 51 . Weighting Factors for Adjusting Generic location Fire Frequencies for Applications to Plant Specific Locations 19ht.5-3 19ht.5 2 Fire Compartment + Division 1 .
Ignition Source Data Sheet (ISDS) 19ht.5 5 19ht.5-3 Fire Compartment Dhision 2 Ignition Source Data Sheet (ISDS) 19ht.5 7 19ht.5-4 Fire Compartment Dhision 3 .
Ignition Source Data Sheet (ISDS) - 19ht.5 9 19hl3-5 Reactor and Control Duilding Fire Areas - _ .
Explanatory Notes 19ht.511 19ht.5-6 Fire Compartment Turbine Building ignition Source Data Sheet (ISDS) 19ht.5-15 19M.5-7 Turbine Building - Explanatory Notes 19M.5-17 19M.5-8 Fire Compartment - Control Room Complex Ignition Source Data Sheet (ISDS) 19ht.5-21 19M.5-9 ' Control Room Complex Explanatory Notes 19M.5 22 19M.5 li Amendment
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ABWR z w , icons Standard Plant nea SECTION 19M 5 GE PitOPRIETARY - provided under separate cover ihr Amtn.dtatn1 19M.5-1 19ht.5-2 19M.5 3 19M.5-4 19M.5 5 19M.5-6 19M.5-7 19M.5-8 19M.5-9 19M.5-10 19M.5-11 19M.5-12 19M.5-13 19M.5-14 19M.5-15 19M.5-16 19M.517 19M.518 19M.5-19 19M.5-20 19M.5-21 19M.5-22 19M.5-23 Amendment 19MS 23
ABWR mams Standard Plant nm A APPENDIX 19M.6 I TAllLE OF CONTENTS ,
Secllon 'ntle hge :
l 19M.6.1 Methodology 19M.41 19M.6J Ecinita 19M.G1 TAllLES Table Htle hee 19M.6-1 AllWR Fire Risk Screening Analysis Summary 19M.G3.
19M.42 Divisional and Control Room Fire Risk W/ Remote Control of RCIC & 4 SRVs for CR Fires 19ht.6 4 19M.6-3 Summary of AllWR Fore Risk Screening Analyses for Turbine 11uilding Fire 19ht.45 19M 6-4 AllWR Control Room Fire Risk Screening Analysis Summary 19M.6-6 ILLUSTRATIONS Elgitte Iltis - bge 19M.G1 Division 1 Electrical Fire 19M.6-7 19M.6-2 Division 2 Electrical Fire 19M.6-8 19M.6-3 Division 3 Electrical Fire 19M.6-9 19M.6-4 Control Room Fire 19M.6-10 19M.G5 Turbine lluilding Fire (Loss of Offsite Power and Station Illackout Event Trec) 19M.6-11 19M.6-6 Loss of Offsite Power Event Tree 19M.612 19M.G7 Loss of Offsite Power Event Tree 19M.6-13 19M.6-8 Loss of Offsite Power Event Tree 19M.6-14 19M.6-ii Amendment
ABWR mum Standard Plant ne,. a APPENDIX 19M.6 ILLUSTRATIONS (Continued)
Denne lille Eage 19hi.6-9 Station Bhckout Event Tree 19h1.615 i 19ht.610 Station Blackout Event Tree 19ht.616 19ht.611 Station Blackout Event Tree 1951.6-17 l l
1 19hi.6-lii Amendment
ABWR U M MDAS Sundard I'lant n ~. ^
SECTION 19M.6 GE l'ROl'RIETARY provided under separate cover Jiigt 6tnendental 19M.61 19M.fr2 19M.6-3 19M.6 4 19M.6 5 19M.6-6 19M.6-7 19M.6-8 19MIr9 19M.6-10 19M.6-11 19M 612 19M.613 19M.6-14 19MIrl5 19M.(r16 19M.617 Ameridment 19M (rl .17 l
9 ABWR DM100A5 Standard Plant _
nev A 1 l
19M.7 INTERFACE Section 19M3 requires k> cal manual contro' of RCIC as one means of mitigation in case of a control nmm fire, it is a requirement that a procedure for local operation of the RCIC be provided by the utility.
Amendment 19M.7-1
ABWR 2 mums ELRDdard I'ltini nev ^
19M.8 REFERENCES
- 1. l' ire Vulnerability Evaluation Methodology, 171VE, I'lant Screening Guide, Electric l'ower Research Institute. I'rclitninary Draft.
l I
i Amendment 19ML)
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