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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20216J0681999-09-29029 September 1999
Forwards Rev 3 of AP600 Design Control Document, Incorporating Documentation Changes Resulting from Final Review Performed to Check Consistency of Implementation of Approved Design Change Proposals.With Summary of Changes
ML20207G5411999-06-0808 June 1999
Discusses Request Made by Westinghouse on 981109 That Proprietary WCAP-14252,Rev 1,be Withheld from Public Disclosure.Determined Info to Be Proprietary & Will Be Withheld from Public Disclosure
ML20195D5201999-06-0404 June 1999
Discusses Westinghouse Request That Change Pages Submitted on 980921 to WCAP-14292 Be Withheld from Public Disclosure. Determined Info to Be Proprietary & Will Be Withheld from Public Disclosure
ML20196G2431999-05-21021 May 1999
Informs That USNRC Has Published in Fr Encl Notice of Proposed Rulemaking Re AP600 Design Certification Rule. Rulemaking Allows Applicants or Licensees to Construct AP600 Std Plant Design by Referencing Design Certification Rule
ML20206G5411999-05-0505 May 1999
Forwards Draft Environ Assessment Re Proposed Certification of AP600 Std Plant Design.Environ Assessment Will Be Used as Basis for NRC Finding of No Significant Environ Impact Resulting from Certification of AP600 Design
ML20205J3351999-04-0707 April 1999
Informs That USNRC Staff Has Completed Review of Rev 2 of AP600 Design Control Document,Verified That All of Changes in Rev 2 Are Acceptable & Determined That AP600 Dcd,Rev 2, Can Now Be Used in Proposed Design Certification Rule
NSD-NRC-99-5827, Forwards Rev 2 to AP600 Design Control Document.Attachment 1 Provides Summary of Changes Made as Part of Mar 1999 Rev to AP600 Design Control Document1999-03-31031 March 1999
Forwards Rev 2 to AP600 Design Control Document.Attachment 1 Provides Summary of Changes Made as Part of Mar 1999 Rev to AP600 Design Control Document
ML20205D3051999-03-25025 March 1999
Requests Amend to 920626 Application for Design Certification of AP600,including AP600 Ssar & AP600 Dcd,To Reflect Sale of CBS Commercial Nuclear Business to W
ML20203C5481999-02-10010 February 1999
Forwards Rev 1 to AP600 Design Control Document (DCD) for Docket File.Dcd Provides Reference Basis for AP600 Design Certification
ML20199H8671999-01-20020 January 1999
Forwards Comments on AP600 Design Control Document,Submitted by Westinghouse
ML20199B1121999-01-0707 January 1999
Advises That Info Contained in NSRA-APSL-92-0268 & Containing Presentation Matl Used in 921209-10 Meeting,Marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA
ML20198B4601998-12-14014 December 1998
Discusses W Ltr NTD-NRC-95-4556,dtd 950918,provided as Status Rept on Proprietary Matl Submitted to NRC to Support AP600 Design Review Effort.Proprietary Info in Encl Have Been Removed from AP600 Docket File & Being Returned
ML20197G3501998-11-30030 November 1998
Forwards AP600 Design Control Document, Vols 1-12 for Docket File.Submittal Closes Confirmatory Items 1.5-1 & 1.5-2 from Sept 1998 Final SER Re Certification of AP600 Std Design
ML20195E9331998-11-0909 November 1998
Requests That Rev 1 to WCAP-14252, AP600 Low-Pressure Integral Sys Test at or State Univ Final Data Rept, Vols I- Iv,Be Withheld (Ref 10CFR2.790)
NSD-NRC-98-5806, Forwards non-proprietary Rev 1 to WCAP-14253 & Proprietary Rev 1 to WCAP-14252, AP600 Low-Pressure Integral Sys Test at or State Univ Final Data Rept. Proprietary Rept Includes Vols 1-4.Proprietary Info Withheld,Per 10CFR2.7901998-11-0909 November 1998
Forwards non-proprietary Rev 1 to WCAP-14253 & Proprietary Rev 1 to WCAP-14252, AP600 Low-Pressure Integral Sys Test at or State Univ Final Data Rept. Proprietary Rept Includes Vols 1-4.Proprietary Info Withheld,Per 10CFR2.790
ML20155G9021998-11-0303 November 1998
Advises That Info Contained in 981012 ltr,NSD-NRC-98-5795, Will Be Withheld from Public Disclosure,Per 10CFR2.790(b) (5) & Section 103(b) of AEA of 1954,as Amended
ML20155G9271998-11-0202 November 1998
Forwards Copy of NRC Staff FSER for Westinghouse AP600 Design.Staff Completed Review of Design & Issued Final Design Approval & FSER on 980903.Without Encl
ML20155G7591998-11-0202 November 1998
Forwards Copy of NRC Staff FSER for Westinghouse AP600 Design,Per Discussion at Sept 1997 Meeting.Staff Completed & Issued Final Design Approval of FSER on 980903.Without Encl
NSD-NRC-98-5795, Informs That Figures from Rev 0 & Rev 3 of PRA Which Indicate Location of H Igniters Should Be Considered Proprietary.Nonproprietary Versions of AP600 General Arrangement Drawings Were Provided in Rev 7 of Ssar1998-10-12012 October 1998
Informs That Figures from Rev 0 & Rev 3 of PRA Which Indicate Location of H Igniters Should Be Considered Proprietary.Nonproprietary Versions of AP600 General Arrangement Drawings Were Provided in Rev 7 of Ssar
ML20154A4091998-09-29029 September 1998
Advises That Certain Info Contained in Westinghouse Ltr NTD-NRC-95-4506,dtd 950713,submitting WCAP-14425,will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5).Figure 3-1 Will Be Placed Into Public Record
ML20153G2521998-09-25025 September 1998
Advises That Proprietary Matl Discovered by NRC in NSD-NRC-97-4966 & Proprietary Matl Noted by W in NSD-NRC-98-5772 Will Be Withhheld from Public Disclosure Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954
ML20153C1001998-09-15015 September 1998
Advises That Matls Re AP600 Notrump Final Validation Rept, WCAP-14807,marked Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended
NSD-NRC-98-5788, Forwards Formal Transmittal of Correspondence Previously Sent Informally Over Period of 980702-0826.Index of Encl Matl Provided1998-09-15015 September 1998
Forwards Formal Transmittal of Correspondence Previously Sent Informally Over Period of 980702-0826.Index of Encl Matl Provided
ML20151X4381998-09-15015 September 1998
Informs That Staff Has Decided to Accept Claim That Info in WCAP-14135,Rev 1 Is Proprietary & Will Be Withheld from Public Disclosure,Per W 980821 & 26 Ltrs
ML20151X4041998-09-11011 September 1998
Discusses Revised Tier 2 Info for AP600 Design.Staff Revised Decision on Whether Fire Protection Should Expire at First Full Power Encl
ML20151V1711998-09-0808 September 1998
Advises That Info Re Westinghouse AP600 Std Safety Analysis Rept Through Rev 4 & PRA Through Rev 5 Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5).Disposition of Ssar & PRA Proprietary Info Encl
ML20151V2231998-09-0808 September 1998
Informs That NRC Determined That WCAP-14132 Encl in Westinghouse Ltr NTD-NRC-94-4244,dtd 940729 & Marked as Proprietary,Will Be Withheld from Public Disclosure,Per to 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954
ML20151S9181998-09-0303 September 1998
Advises That Info Marked as Proprietary Re Westinghouse AP600 Design Ltrs Concerning Pxs Scaling & Pirt Closure Rept WCAP-14727,will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5)
ML20239A1481998-09-0303 September 1998
Forwards Notice of Issuance of Final Design Approval & Final SER for AP600.FDA Allows AP600 Design to Be Referenced in Application for Construction Permit or Operating License Under 10CFR50 or Application for Combined License
ML20239A3111998-09-0303 September 1998
Forwards Final SER Which Summarizes Staff Safety Review of AP600 Design Against Requirements of Subpart B of 10CF5R52 & Delineates Scope of Technical Details Considered in Evaluating Proposed Design
ML20151V8521998-09-0101 September 1998
Extends Invitation to Attend Ceremony on 980911,where NRC Will Present Final Design Approval for AP600 Std Nuclear Reactor Design to Westinghouse
NSD-NRC-98-5781, Informs That W Determined That AP600 FSER Contains No Proprietary Info1998-09-0101 September 1998
Informs That W Determined That AP600 FSER Contains No Proprietary Info
ML20151V2201998-08-31031 August 1998
Informs That EPRI Documents, GOTHIC Containment Analysis Package Qualification Rept, GOTHIC Containment Analysis Qualification Manual, & Listed Documents Dtd Sept 1993 Will Be Withheld from Public Disclosure
ML20151V8431998-08-31031 August 1998
Extends Invitation to Attend Ceremony on 980911,where NRC Will Present Final Design Approval for AP600 Std Nuclear Reactor Design to Westinghouse
ML20238F3241998-08-31031 August 1998
Advises That AP600 RAI Responses Encl in Westinghouse Ltrs NTD-NRC-95-4598,dtd 951117,as Modified by NSD-NRC-98-5776, Dtd 980826,marked Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b)
ML20238F5991998-08-31031 August 1998
Refers to W 980821 Revised Response to Insp Rept 99900404/97-01 That Contained All Substantive Info Provided w/DCP/NRC-1074 Ltr.Nrc Will Destroy DCP/NRC-1074,as Requested
NSD-NRC-98-5783, Forwards non-proprietary Rev 2 to WCAP-14989, Accident Specification & Phenomena Evaluation for AP600 Passive Containment Cooling Sys1998-08-28028 August 1998
Forwards non-proprietary Rev 2 to WCAP-14989, Accident Specification & Phenomena Evaluation for AP600 Passive Containment Cooling Sys
NSD-NRC-98-5782, Forwards Corrected Pages 4-28 Through 4-32 to Be Inserted in Rev 2 to non-proprietary WCAP-14953, AP600 Pxs Scaling & Pirt Closure Rept. Pages Were Originally Submitted W/Incorrect Header Which Stated 'W Proprietary Class 2.'1998-08-28028 August 1998
Forwards Corrected Pages 4-28 Through 4-32 to Be Inserted in Rev 2 to non-proprietary WCAP-14953, AP600 Pxs Scaling & Pirt Closure Rept. Pages Were Originally Submitted W/Incorrect Header Which Stated 'W Proprietary Class 2.'
NSD-NRC-98-5778, Provides Commitment to Include Requested Changes Into AP600 Design Control Document.Discussion W/Vijuk on 980825 Re Disposition of Ltrs DCP/NRC1074,dtd 971016 & DCP/NRC1324,dtd 980403,formalized1998-08-27027 August 1998
Provides Commitment to Include Requested Changes Into AP600 Design Control Document.Discussion W/Vijuk on 980825 Re Disposition of Ltrs DCP/NRC1074,dtd 971016 & DCP/NRC1324,dtd 980403,formalized
ML20237E4421998-08-27027 August 1998
Advises That Info Contained in Ltr DCP/NRC-0985,dtd 970821, Sought to Be Withheld,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended
NSD-NRC-98-5777, Provides Revised Response to NRC Ltr Re W Requests for Withholding Info Re AP600 PCS Final Data rept,WCAP-14135 & WCAP-141381998-08-26026 August 1998
Provides Revised Response to NRC Ltr Re W Requests for Withholding Info Re AP600 PCS Final Data rept,WCAP-14135 & WCAP-14138
NSD-NRC-98-5776, Forwards Proprietary Revised Response to Ref NRC Ltr Re W Requests for Withholding Info Re AP600 Design Certification Test Program,Notrump Computer Code,Wcobra/Trac Computer Code & Loftran Computer Code.Proprietary Info Withheld1998-08-26026 August 1998
Forwards Proprietary Revised Response to Ref NRC Ltr Re W Requests for Withholding Info Re AP600 Design Certification Test Program,Notrump Computer Code,Wcobra/Trac Computer Code & Loftran Computer Code.Proprietary Info Withheld
ML20237E0731998-08-26026 August 1998
Advises That Info in WCAP-14812,revs 1 & 2, Accident Spec & Phenomena Evaluation for AP600 PCS, Will Be Withheld from Public Disclosure
ML20238F8031998-08-26026 August 1998
Requests That Proprietary W Revised Response to NRC Ltrs Re Requests for Withholding Info,Be Withheld from Public Disclosure IAW 10CFR2.790
NSD-NRC-98-5774, Informs That W Faxed Last Response Re Afser Open Item 1.1-1 to NRC on 980821.Last of Attachments Supporting Several of Responses Faxed to NRC Over Past Several Days Were Express Mailed to NRC on 980821.Responses Close Subject Open It1998-08-24024 August 1998
Informs That W Faxed Last Response Re Afser Open Item 1.1-1 to NRC on 980821.Last of Attachments Supporting Several of Responses Faxed to NRC Over Past Several Days Were Express Mailed to NRC on 980821.Responses Close Subject Open Item
NSD-NRC-98-5773, Responds to Questions Raised in NRC 971022 & s Re Proprietary Info Contained in 970930 Summary of Meeting Held on 970804-15 Concerning Structural Design of AP600.Figure 12-24 of WCAP-14407 Still Considered Proprietary by W1998-08-21021 August 1998
Responds to Questions Raised in NRC 971022 & s Re Proprietary Info Contained in 970930 Summary of Meeting Held on 970804-15 Concerning Structural Design of AP600.Figure 12-24 of WCAP-14407 Still Considered Proprietary by W
ML20237E7991998-08-21021 August 1998
Forwards non-proprietary Results of AP600 Design Assurance Review (Dar) That Was Commitment in W Response to NRC Insp Rept 99900404/97-02.Info Should Assist in Closing Nonconformances & Unresolved Item Identified in Insp Rept
NSD-NRC-98-5771, Forwards non-proprietary Rev 2 to WCAP-14138, Final Data Rept for PCS Large-Scale Tests,Phase 2 & Phase 3. Submittal Satisfies Verbal Commitment to Revise non-proprietary Version of PCS Final Data Rept Made by W1998-08-21021 August 1998
Forwards non-proprietary Rev 2 to WCAP-14138, Final Data Rept for PCS Large-Scale Tests,Phase 2 & Phase 3. Submittal Satisfies Verbal Commitment to Revise non-proprietary Version of PCS Final Data Rept Made by W
NSD-NRC-98-5769, Responds to NRC Ref Ltrs Re W Requests for Withholding Info. Info Provided as Proprietary in Ref 1 Has Either Been Moved from Ssar to Ref 3,which Includes non-proprietary Version of Rept or Made non-proprietary in Current Version of1998-08-21021 August 1998
Responds to NRC Ref Ltrs Re W Requests for Withholding Info. Info Provided as Proprietary in Ref 1 Has Either Been Moved from Ssar to Ref 3,which Includes non-proprietary Version of Rept or Made non-proprietary in Current Version of Ssar
NSD-NRC-98-5772, Forwards non-proprietary & Proprietary Info in Response to NRC Ltrs Re W Requests for Withholding Info.Separate Ltr & Affidavit Justifying Proprietary Nature of Info,Encl. Proprietary Info Withheld,Per 10CFR2.7901998-08-21021 August 1998
Forwards non-proprietary & Proprietary Info in Response to NRC Ltrs Re W Requests for Withholding Info.Separate Ltr & Affidavit Justifying Proprietary Nature of Info,Encl. Proprietary Info Withheld,Per 10CFR2.790
1999-09-29
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARML20216J0681999-09-29029 September 1999
Forwards Rev 3 of AP600 Design Control Document, Incorporating Documentation Changes Resulting from Final Review Performed to Check Consistency of Implementation of Approved Design Change Proposals.With Summary of Changes
NSD-NRC-99-5827, Forwards Rev 2 to AP600 Design Control Document.Attachment 1 Provides Summary of Changes Made as Part of Mar 1999 Rev to AP600 Design Control Document1999-03-31031 March 1999
Forwards Rev 2 to AP600 Design Control Document.Attachment 1 Provides Summary of Changes Made as Part of Mar 1999 Rev to AP600 Design Control Document
ML20205D3051999-03-25025 March 1999
Requests Amend to 920626 Application for Design Certification of AP600,including AP600 Ssar & AP600 Dcd,To Reflect Sale of CBS Commercial Nuclear Business to W
ML20203C5481999-02-10010 February 1999
Forwards Rev 1 to AP600 Design Control Document (DCD) for Docket File.Dcd Provides Reference Basis for AP600 Design Certification
ML20197G3501998-11-30030 November 1998
Forwards AP600 Design Control Document, Vols 1-12 for Docket File.Submittal Closes Confirmatory Items 1.5-1 & 1.5-2 from Sept 1998 Final SER Re Certification of AP600 Std Design
NSD-NRC-98-5806, Forwards non-proprietary Rev 1 to WCAP-14253 & Proprietary Rev 1 to WCAP-14252, AP600 Low-Pressure Integral Sys Test at or State Univ Final Data Rept. Proprietary Rept Includes Vols 1-4.Proprietary Info Withheld,Per 10CFR2.7901998-11-0909 November 1998
Forwards non-proprietary Rev 1 to WCAP-14253 & Proprietary Rev 1 to WCAP-14252, AP600 Low-Pressure Integral Sys Test at or State Univ Final Data Rept. Proprietary Rept Includes Vols 1-4.Proprietary Info Withheld,Per 10CFR2.790
ML20195E9331998-11-0909 November 1998
Requests That Rev 1 to WCAP-14252, AP600 Low-Pressure Integral Sys Test at or State Univ Final Data Rept, Vols I- Iv,Be Withheld (Ref 10CFR2.790)
NSD-NRC-98-5795, Informs That Figures from Rev 0 & Rev 3 of PRA Which Indicate Location of H Igniters Should Be Considered Proprietary.Nonproprietary Versions of AP600 General Arrangement Drawings Were Provided in Rev 7 of Ssar1998-10-12012 October 1998
Informs That Figures from Rev 0 & Rev 3 of PRA Which Indicate Location of H Igniters Should Be Considered Proprietary.Nonproprietary Versions of AP600 General Arrangement Drawings Were Provided in Rev 7 of Ssar
NSD-NRC-98-5788, Forwards Formal Transmittal of Correspondence Previously Sent Informally Over Period of 980702-0826.Index of Encl Matl Provided1998-09-15015 September 1998
Forwards Formal Transmittal of Correspondence Previously Sent Informally Over Period of 980702-0826.Index of Encl Matl Provided
NSD-NRC-98-5781, Informs That W Determined That AP600 FSER Contains No Proprietary Info1998-09-0101 September 1998
Informs That W Determined That AP600 FSER Contains No Proprietary Info
NSD-NRC-98-5782, Forwards Corrected Pages 4-28 Through 4-32 to Be Inserted in Rev 2 to non-proprietary WCAP-14953, AP600 Pxs Scaling & Pirt Closure Rept. Pages Were Originally Submitted W/Incorrect Header Which Stated 'W Proprietary Class 2.'1998-08-28028 August 1998
Forwards Corrected Pages 4-28 Through 4-32 to Be Inserted in Rev 2 to non-proprietary WCAP-14953, AP600 Pxs Scaling & Pirt Closure Rept. Pages Were Originally Submitted W/Incorrect Header Which Stated 'W Proprietary Class 2.'
NSD-NRC-98-5783, Forwards non-proprietary Rev 2 to WCAP-14989, Accident Specification & Phenomena Evaluation for AP600 Passive Containment Cooling Sys1998-08-28028 August 1998
Forwards non-proprietary Rev 2 to WCAP-14989, Accident Specification & Phenomena Evaluation for AP600 Passive Containment Cooling Sys
NSD-NRC-98-5778, Provides Commitment to Include Requested Changes Into AP600 Design Control Document.Discussion W/Vijuk on 980825 Re Disposition of Ltrs DCP/NRC1074,dtd 971016 & DCP/NRC1324,dtd 980403,formalized1998-08-27027 August 1998
Provides Commitment to Include Requested Changes Into AP600 Design Control Document.Discussion W/Vijuk on 980825 Re Disposition of Ltrs DCP/NRC1074,dtd 971016 & DCP/NRC1324,dtd 980403,formalized
ML20238F8031998-08-26026 August 1998
Requests That Proprietary W Revised Response to NRC Ltrs Re Requests for Withholding Info,Be Withheld from Public Disclosure IAW 10CFR2.790
NSD-NRC-98-5776, Forwards Proprietary Revised Response to Ref NRC Ltr Re W Requests for Withholding Info Re AP600 Design Certification Test Program,Notrump Computer Code,Wcobra/Trac Computer Code & Loftran Computer Code.Proprietary Info Withheld1998-08-26026 August 1998
Forwards Proprietary Revised Response to Ref NRC Ltr Re W Requests for Withholding Info Re AP600 Design Certification Test Program,Notrump Computer Code,Wcobra/Trac Computer Code & Loftran Computer Code.Proprietary Info Withheld
NSD-NRC-98-5777, Provides Revised Response to NRC Ltr Re W Requests for Withholding Info Re AP600 PCS Final Data rept,WCAP-14135 & WCAP-141381998-08-26026 August 1998
Provides Revised Response to NRC Ltr Re W Requests for Withholding Info Re AP600 PCS Final Data rept,WCAP-14135 & WCAP-14138
NSD-NRC-98-5774, Informs That W Faxed Last Response Re Afser Open Item 1.1-1 to NRC on 980821.Last of Attachments Supporting Several of Responses Faxed to NRC Over Past Several Days Were Express Mailed to NRC on 980821.Responses Close Subject Open It1998-08-24024 August 1998
Informs That W Faxed Last Response Re Afser Open Item 1.1-1 to NRC on 980821.Last of Attachments Supporting Several of Responses Faxed to NRC Over Past Several Days Were Express Mailed to NRC on 980821.Responses Close Subject Open Item
ML20237E7991998-08-21021 August 1998
Forwards non-proprietary Results of AP600 Design Assurance Review (Dar) That Was Commitment in W Response to NRC Insp Rept 99900404/97-02.Info Should Assist in Closing Nonconformances & Unresolved Item Identified in Insp Rept
ML20237D3161998-08-21021 August 1998
Requests That W Response to NRC Ltrs Re Requests for Withholding Info Be Withheld from Public Disclosure,Per 10CFR2.790
NSD-NRC-98-5773, Responds to Questions Raised in NRC 971022 & s Re Proprietary Info Contained in 970930 Summary of Meeting Held on 970804-15 Concerning Structural Design of AP600.Figure 12-24 of WCAP-14407 Still Considered Proprietary by W1998-08-21021 August 1998
Responds to Questions Raised in NRC 971022 & s Re Proprietary Info Contained in 970930 Summary of Meeting Held on 970804-15 Concerning Structural Design of AP600.Figure 12-24 of WCAP-14407 Still Considered Proprietary by W
NSD-NRC-97-5370, Transmits Results of AP600 Foake Design Assurance Review as Requested in NRC .Info Is Being Provided to Close Unresolved Item Identified in Insp Rept 99900404/97-011998-08-21021 August 1998
Transmits Results of AP600 Foake Design Assurance Review as Requested in NRC .Info Is Being Provided to Close Unresolved Item Identified in Insp Rept 99900404/97-01
NSD-NRC-98-5763, Responds to NRC Ltrs Re W Claim for Treatment of Proprietary Info Submitted in .As Discussed W/Nrc on 980821, Info Contained in W Is self-critical Analysis of W QA Program & Therefore Falls Under Items of Affidavit1998-08-21021 August 1998
Responds to NRC Ltrs Re W Claim for Treatment of Proprietary Info Submitted in .As Discussed W/Nrc on 980821, Info Contained in W Is self-critical Analysis of W QA Program & Therefore Falls Under Items of Affidavit
NSD-NRC-98-5772, Forwards non-proprietary & Proprietary Info in Response to NRC Ltrs Re W Requests for Withholding Info.Separate Ltr & Affidavit Justifying Proprietary Nature of Info,Encl. Proprietary Info Withheld,Per 10CFR2.7901998-08-21021 August 1998
Forwards non-proprietary & Proprietary Info in Response to NRC Ltrs Re W Requests for Withholding Info.Separate Ltr & Affidavit Justifying Proprietary Nature of Info,Encl. Proprietary Info Withheld,Per 10CFR2.790
NSD-NRC-98-5769, Responds to NRC Ref Ltrs Re W Requests for Withholding Info. Info Provided as Proprietary in Ref 1 Has Either Been Moved from Ssar to Ref 3,which Includes non-proprietary Version of Rept or Made non-proprietary in Current Version of1998-08-21021 August 1998
Responds to NRC Ref Ltrs Re W Requests for Withholding Info. Info Provided as Proprietary in Ref 1 Has Either Been Moved from Ssar to Ref 3,which Includes non-proprietary Version of Rept or Made non-proprietary in Current Version of Ssar
NSD-NRC-98-5771, Forwards non-proprietary Rev 2 to WCAP-14138, Final Data Rept for PCS Large-Scale Tests,Phase 2 & Phase 3. Submittal Satisfies Verbal Commitment to Revise non-proprietary Version of PCS Final Data Rept Made by W1998-08-21021 August 1998
Forwards non-proprietary Rev 2 to WCAP-14138, Final Data Rept for PCS Large-Scale Tests,Phase 2 & Phase 3. Submittal Satisfies Verbal Commitment to Revise non-proprietary Version of PCS Final Data Rept Made by W
ML20237D3551998-08-20020 August 1998
Requests That Proprietary Info Re W Response to NRC Ltrs Re Requests for Withholding Info Concerning AP600 Pxs Scaling & Pirt Closure Rept, WCAP-14727 Be Withheld from Public Disclosure IAW 10CFR2.790
NSD-NRC-98-5762, Forwards Proprietary Change Pages for Chapters 7 & 8,for Inclusion as Rev 2 of TR WCAP-14727,in Response to NRC Ltr Dtd 980714.Non-proprietary Rev 2 to TR WCAP-14953 Re AP600 Scaling & Pirt Closure Encl.Proprietary Info Withheld1998-08-20020 August 1998
Forwards Proprietary Change Pages for Chapters 7 & 8,for Inclusion as Rev 2 of TR WCAP-14727,in Response to NRC Ltr Dtd 980714.Non-proprietary Rev 2 to TR WCAP-14953 Re AP600 Scaling & Pirt Closure Encl.Proprietary Info Withheld
NSD-NRC-98-5764, Responds to NRC Ltrs Re Requests for Withholding Info from Public Disclosure for W AP600 Design Ltr of 951117,dtd 960229.W Considers Matl Proprietary Since Matl Discusses Approach Used by W to Develop Analysis Models of Cctf Test1998-08-20020 August 1998
Responds to NRC Ltrs Re Requests for Withholding Info from Public Disclosure for W AP600 Design Ltr of 951117,dtd 960229.W Considers Matl Proprietary Since Matl Discusses Approach Used by W to Develop Analysis Models of Cctf Test
NSD-NRC-98-5768, Responds to NRC Ref Ltrs Re W Requests for Withholding Info. Specific Info Considered non-proprietary or Proprietary Discussed1998-08-20020 August 1998
Responds to NRC Ref Ltrs Re W Requests for Withholding Info. Specific Info Considered non-proprietary or Proprietary Discussed
NSD-NRC-98-5766, Provides Summary of 980813 Telcon W/Nrc Re W Explanation of Rationale Which Was Used to Determine What Info Was Considered to Be Proprietary in TR WCAP-148121998-08-20020 August 1998
Provides Summary of 980813 Telcon W/Nrc Re W Explanation of Rationale Which Was Used to Determine What Info Was Considered to Be Proprietary in TR WCAP-14812
NSD-NRC-98-5770, Responds to NRC Ltrs Re W Requests for Withholding Info.W Withdraws AP600 Rept Entitled, Wcobra/Trac Core Makeup Tank Preliminary Validation Rept, Since Rept Was Not Required by NRC to Make Safety Determination of AP6001998-08-20020 August 1998
Responds to NRC Ltrs Re W Requests for Withholding Info.W Withdraws AP600 Rept Entitled, Wcobra/Trac Core Makeup Tank Preliminary Validation Rept, Since Rept Was Not Required by NRC to Make Safety Determination of AP600
NSD-NRC-98-5760, Forwards Rev 25 to GW-GL-021, AP600 Ssar, Vols 1-11. Revised Tables of Contents,Change Page Instructions,List of Effective Pages,Document Cover Sheet & Change Roadmap Outlining Changes in Each Section Also Encl1998-08-19019 August 1998
Forwards Rev 25 to GW-GL-021, AP600 Ssar, Vols 1-11. Revised Tables of Contents,Change Page Instructions,List of Effective Pages,Document Cover Sheet & Change Roadmap Outlining Changes in Each Section Also Encl
NSD-NRC-98-5761, Provides Written Confirmation That Identified Figure Is Not Considered Proprietary by W.Refs 1-5,discussed1998-08-19019 August 1998
Provides Written Confirmation That Identified Figure Is Not Considered Proprietary by W.Refs 1-5,discussed
ML20237D2681998-08-18018 August 1998
Requests That Proprietary Informal Correspondence Be Withheld from Public Disclosure,Per 10CFR2.790
NSD-NRC-97-5046, Submits Rev 1 of W Ltr Originally Submitted 970917,which Transmitted Proprietary & non-proprietary Informal Correspondence.Rev Includes Notarized Affidavit as Part of Application for Withholding Info.Proprietary Info Withheld1998-08-18018 August 1998
Submits Rev 1 of W Ltr Originally Submitted 970917,which Transmitted Proprietary & non-proprietary Informal Correspondence.Rev Includes Notarized Affidavit as Part of Application for Withholding Info.Proprietary Info Withheld
NSD-NRC-98-5759, Submits Response to NRC Ltrs Re Request for Withholding Info.Figure 8-19 Will No Longer Be Considered Proprietary by W1998-08-17017 August 1998
Submits Response to NRC Ltrs Re Request for Withholding Info.Figure 8-19 Will No Longer Be Considered Proprietary by W
NSD-NRC-98-5756, Responds to NRC 980714 & 21 Ltrs Re Request for Withholding Proprietary Info That Was Not Clearly Identified Other than Being Marked W Proprietary Class 21998-08-14014 August 1998
Responds to NRC 980714 & 21 Ltrs Re Request for Withholding Proprietary Info That Was Not Clearly Identified Other than Being Marked W Proprietary Class 2
NSD-NRC-98-5757, Responds to Ref NRC Ltrs Re Request for Withholding Proprietary Info Re W AP600 Ltr.Per 980708 Telcon,W Has Reviewed TRs WCAP-13288 & WCAP-13289 & Considers None of Info to Be Proprietary1998-08-14014 August 1998
Responds to Ref NRC Ltrs Re Request for Withholding Proprietary Info Re W AP600 Ltr.Per 980708 Telcon,W Has Reviewed TRs WCAP-13288 & WCAP-13289 & Considers None of Info to Be Proprietary
ML20151Z0971998-08-13013 August 1998
Requests That Proprietary Rev 5 to WCAP-14807, Notrump Final Validation Rept, Be Withheld from Public Disclosure, Per 10CFR2.790
NSD-NRC-98-5754, Forwards non-proprietary Versions of Revs 3-5 to WCAP-14808 & Proprietary Version of Rev 5 to WCAP-14807, Notrump Final Validation Rept for AP600, in Form of Replacement Pages. Proprietary Encl Withheld1998-08-13013 August 1998
Forwards non-proprietary Versions of Revs 3-5 to WCAP-14808 & Proprietary Version of Rev 5 to WCAP-14807, Notrump Final Validation Rept for AP600, in Form of Replacement Pages. Proprietary Encl Withheld
NSD-NRC-98-5749, Forwards Rev 13 to AP600 PRA for Simplified Passive Advanced LWR Plant Program. Rev Represents Final Version of AP600 Pra.All NRC Comments Related to Rev 12 of AP600 PRA Have Been Resolved1998-08-13013 August 1998
Forwards Rev 13 to AP600 PRA for Simplified Passive Advanced LWR Plant Program. Rev Represents Final Version of AP600 Pra.All NRC Comments Related to Rev 12 of AP600 PRA Have Been Resolved
NSD-NRC-98-5753, Responds to Ref NRC Ltrs & W Ltr Re Request for Withholding Proprietary Info Re AP600 Design Ltrs1998-08-13013 August 1998
Responds to Ref NRC Ltrs & W Ltr Re Request for Withholding Proprietary Info Re AP600 Design Ltrs
NSD-NRC-98-5752, Responds to Open Item 1.1-2 Contained in 980501 Advance Final SER for AP600 Requesting Update of Comparison of AP600 to NRC Reviewed Version of Alwr Util Requirements Document. Changes Resulting from NRC Comments Re Plant Design,List1998-08-13013 August 1998
Responds to Open Item 1.1-2 Contained in 980501 Advance Final SER for AP600 Requesting Update of Comparison of AP600 to NRC Reviewed Version of Alwr Util Requirements Document. Changes Resulting from NRC Comments Re Plant Design,Listed
NSD-NRC-98-5755, Forwards Rev 7 to Simplified Passive Advance Light Water Reactor Plant Program AP600 Tier 1 Matl, Incorporating Comments Received from NRC Technical Staff,As of 980812.Encl Closes Open Item 14.3-1 from Advanced Final SER1998-08-13013 August 1998
Forwards Rev 7 to Simplified Passive Advance Light Water Reactor Plant Program AP600 Tier 1 Matl, Incorporating Comments Received from NRC Technical Staff,As of 980812.Encl Closes Open Item 14.3-1 from Advanced Final SER
ML20153D9491998-08-12012 August 1998
Submits Response to NRC Ltrs Re Requests for Withholding Info.Info Does Not Have Commercial Value & No Longer Considered to Be Proprietary by W
NSD-NRC-98-5751, Submits Response to NRC Ltrs Re Requests for Withholding Info.Info Does Not Have Commercial Value & Is No Longer Considered Proprietary by W1998-08-12012 August 1998
Submits Response to NRC Ltrs Re Requests for Withholding Info.Info Does Not Have Commercial Value & Is No Longer Considered Proprietary by W
NSD-NRC-98-5748, Forwards Rev 24 of AP600 Ssar.Revised Tables of Contents, Change Page Instructions,List of Effective Pages,Document Cover Sheet & Change Roadmap Outlining Changes in Each Section Also Encl.Rev Submitted Under Encl Oath1998-08-0707 August 1998
Forwards Rev 24 of AP600 Ssar.Revised Tables of Contents, Change Page Instructions,List of Effective Pages,Document Cover Sheet & Change Roadmap Outlining Changes in Each Section Also Encl.Rev Submitted Under Encl Oath
NSD-NRC-98-5743, Forwards Table Which Compares Combined License (COL) Info Items Identified in AP600 Design Certification Application W/Col Action Items Identified in AP600 Advance Final SER Provided to W by NRC on 9805061998-07-31031 July 1998
Forwards Table Which Compares Combined License (COL) Info Items Identified in AP600 Design Certification Application W/Col Action Items Identified in AP600 Advance Final SER Provided to W by NRC on 980506
NSD-NRC-98-5733, Forwards Rev 6 to GW-GL-030, Simplified Passive Advance LWR Plant Program,AP600 Tier 1 Matl, Which Incorporates Comments Received from NRC Technical Staff as of 9807221998-07-27027 July 1998
Forwards Rev 6 to GW-GL-030, Simplified Passive Advance LWR Plant Program,AP600 Tier 1 Matl, Which Incorporates Comments Received from NRC Technical Staff as of 980722
NSD-NRC-98-5742, Forwards Rev 12 to AP600 PRA Rept. All NRC Open Items Related to AP600 PRA Have Been Resolved1998-07-24024 July 1998
Forwards Rev 12 to AP600 PRA Rept. All NRC Open Items Related to AP600 PRA Have Been Resolved
1999-09-29
[Table view] |
Text
_ _ _ _ _ _ _ _ _ - _ _ _ _ ____ ___ _
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Westinghouse Energy Systems Box 355 Pinsbu@ Pennsylvania 15230 0355 Electric Corporation DCP/NRCl406 NSD-NRC-98-5749 i Docket No.: 52-003 August 13,1998 Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: T. R. QUAY
SUBJECT:
AP600 PROBABILISTIC RISK ASSESSMENT, REV1510N 13 l
Dear Mr. Quay:
Enclosed is Revision 13 of the AP600 Probabilistic Risk Assessment (PRA) Report. This revision represents the final version of the AP600 PRA. All NRC comments related to Revision 12 of the AP600 PRA have been resolved. !
l The enclosure is in the form of replacement pages to be a<ided to the existing PRA report. In addition, to reduce the amount of material per PRA volume, we are pro.iding two additional binders for the AP600 PRA document. Included with each AP600 PRA set is the change page instructions including a suggestion of how the chapters should be divided among the six PRA volumes.
Twenty-five sets of Revision 13 to the PRA have been sent to Mr. Joe Sebrosky for distribution within NRC, to NRC subcontractors, and to the ACRS. He enclosure contains no Westinghouse proprietary information.
1 Pursuant to 10CFR50.30(b), this revision is submitted under the enclosed oath or affirmation.
Please contact Cynthia L. Haag on (412) 374-4277 if you have questions concerning this transmittal.
A 8 Brian A. McIntyre, Manager ,
Advanced Plant Safety and Licensing b&
jml Enclosures .O r
- cc: J. M. Sebrosky, NRC (25 copies Enclosure) Q6 u /,)J I
f pl -
J. E. Lyons NRC (w/o Enclosure) '
- 11. A. Sepp, Westinghouse (w/o Enclosure) 9808190036 0e0813 [M- } ')
PDR ADOCK 05200003 A A PDR.,
.m. ,1 I U i
e o UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION in the Matter of: )
)
Westinghouse Electric Company, )
)
A Division of CBS Corporation )
)
AP600 Standard Plant Design ) Docket No.52-003
)
Final Design Approval and Design )
)
Certification application )
APPLICATION FOR REVIEW OF "AP600 PROBABILISTIC RISK ASSESSMENT" FOR FINAL DESIGN APPROVAL AND DESIGN CERTIFICATION Charles W. Pryor, Jr. being duly sworn, states that he is President and Chief Executive Officer of Westinghouse Electric Company, a Division of CBS Corporation; that he is authorized on the part of said corporation to sign and file with the Nuclear Regulatory Commission this document; that all statements made and matters set forth therein are true and correct to the best of his kncwledge, information and belief.
WESTINGHOUSE ELECTRIC COMPANY, A DIVISION O BS CORPORATION By: 4Wh Charles W. Pryor, Jr.
President and Chief Executive Officer Westingiiouse Electric Company,
, A Division of CBS Corporation i
Subscaibed and sworn to before me this 120 day of duW p 1998.
d)h& h. #
@AAAL '
Notary Public
.Nrk -_. 1 _.
9 ,
[, M.Mb l
0630BAM.WPF l
l l
l Enclosure to Westinghouse l
Letter DCP/NRC1406 i
i August 13, 1.998 I
l I
1 l,
6 -.
i l
l 37 son wpr I
AP600 PRA Revision 13 n) f
,, ,. Page Change Instructions (Sheet 1 of 1)
Below are the page change instructions for incorporating Revision 13 of the AP600 PRA into the existing AP600 PRA report. Two additional binders, which represent PRA Volumes 5 and 6, are also provided. It is recommended that the volumes contain the following:
Volume 1 AP600 Document Cover Sheet, List of Effective Pages, Table of Contents, List of Tables, List of Figures, Chapters 1 through 18 Volume 2 Table of Contents, List of Tables, List of Figures, Chapters 19 through 33 Volume 3 Table of Contents, List of Tables, List of Figures, Chapters 34 through 41 Volutr.c 4 Table of Contents, List of Tables, List of Figures, Chapters 42 through 53 Volume 5 Table of Contents, List of Tables, List of Figures, Chapters 54 and 55 Volume 6 Table of Contents, List of Tables, List of Figures, Chapters 56 through 59, Appendices A through D Non Proprietary I p Chapter Remove Previous Revisions PRA Pages: Replace with Rev.13 PRA Page:
VOLUME 1 AP600 Document Remove from front of Volume 1 Place new cover sheet in front of Cover Sheet Volume 1 of AP600 PRA l List of Effective Remove pages 11 through 16 Replace with pages 11 through 16 l Pages VOLUME 3 34 Remove pages 34-15 & 34-16 Replace with pages 34-15 & 34-16 l
r VOLUME 4 45 Remove pages 45-9 & 45-10 Replace with pages 45-9 & 45-10 50 Remove pages 50-17 & 50-18 Replace with pages 50-17 & 50-18 i
Note: The Table of Contents List of Tables, and List of Figures for Volumes 5 and 6 were placed within those binders prior to shipment.
O V
. List cf Effective P;ges l
i AP600 PRA List of Effective Pages Page Revision Page Revision Page Revision Page Revision 29-15 7 30A-11 2 31-14 7 32 18 7 29-16 7 30A-12 2 31-15 7 32-19 7 29-17 7 30A-13 2 31-16 7 32-20 10 29-18 7 30A-14 2 31-17 7 32-21 7 29-19 7 30A-15 2 32-22 7 29-20 7 30A 16 2 32-1 7 32-23 7 29-21 7 30A-17 2 32-2 7 32-24 7 29-22 7 30A-18 2 32-3 7 32-25 7 29-23 7 32-4 7 32-26 7 31-1 7 32-5 7 32-27 7 30-1 7 31-2 7 32-6 7 32-28 7 through 30-115 31-3 7 32-7 7 32-29 7 30A-1 2 31-4 7 32-8 7 32-30 7 30A-2 2 31-5 7 32-9 7 32-31 7 10A-3 2 31-6 7 32-10 7 32-32 7 30A-4 2 31-7 7 32-11 7 32-33 7 30A-5 2 31-8 7 32-12 7 32 34 7 30A-6 2 31-9 7 32-13 10 32-35 7 !
30A-7 2 31-10 7 32-14 7 32-36 7 30A-8 2 31-11 7 32-15 7 32-37 7 30A 9 2 31-12 7 32-16 7 32-38 7 30A-10 2 31-13 7 32-17 7 32-39 7 l
, 1 Revision: 12 3 Westinghouse E. NEL ex='- July 1998 11 c:\ip0lWWy_12W-loe.wpf;lb l
! l List of Effective Pages .
e l AP600 PRA List of Effective Pages Page Revision Page Revision Page Revision Page Revision 32-40 7 35-1 8 35-20 8 36-1 8 32-41 7 35-2 8 35-21 8 36-2 8 32-42 7 35-3 8 35-22 8 36-3 8 32-43 7 35-4 8 35-23 8 36-4 8 32-44 7 35-5 8 35-24 8 36-5 8 32-45 7 35-6 8 35-25 8 36-6 9 32-46 7 35-7 8 35-26 8 36-7 10 32-47 7 35-8 8 35-27 8 36-8 8 35-9 8 35-28 8 36-9 8 33-1 7 35-10 8 35-29 10 36-10 8 through 33-17 33-18 8 35-11 8 35-30 8 33-19 7 35-12 8 through 33-66 35-13 8 34-1 8 35-14 10 through 34-14 1 34-15 13 35-15 8 34-16 8 35-16 8 through 34-487 35-17 8 35-18 8 35-19 8 O
Revision: 13 ENEL
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. List of Effectin P ges -
AP600 PRA List of Effective Pages Page Revision Page Revision Page Revision Page Revision 37-1 8 39-6 8 39-25 8 42-1 8 37 2 8 39-7 8 42 2 8 37-3 10 39-8 8 40-1 8 42-3 8 37-4 8 39-9 8 40-2 11 42-4 8 l
37-5 10 39-10 8 40-3 8 42-5 8
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39-11 8 40-4 11 42-6 8 I 38-1 8 39-12 8 40-5 8 42-7 8 38-2 8 39-13 8 42-8 8 38-3 8 39-14 11 41-1 8 42-9 8 38-4 10 39-15 8 41-2 8 42-10 8 38 5 10 39-16 8 41-3 8 42-11 8 V 38-6 10 39-17 8 41-4 8 42-12 8 38 7 10 39-18 8 41 5 10 42-13 8 39-19 8 41-6 8 42-14 8 ,
through I 41-123 l 39-1 8 39-20 8 39-2 8 39-21 8 41A-1 8 43-1 8 through through 41A-375 43-162 39-3 11 39-22 8 41B-1 8 through 41B-120 39-4 8 39-23 8 39-5 10 39-24 8
% T Westinghouse hh_ Revision: 12 July 1998
(
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l 13 c:bP 0lW** 12w-ioe.wpf:ib I
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. List of Effective Pages .
O AP600 PRA List of Effective Pages Page Revision Page Revision Page Revision Page Revision I 44-1 8 45-10 13 49-14 8 i I 44-2 8 45-11 8 49-15 8 I through I 45-136 44-3 8 49-16 8 44-4 8 46-1 8 49-17 8 44-5 8 40-18 8 44-6 8 47-1 8 49-19 9 44-7 8 49-20 8 through 49-47 44-8 8 48-1 8 49-48 11 44-9 8 44-10 8 49-1 8 44-11 8 49-2 8 44-12 9 49-3 8 49-4 8 45-1 8 49-5 8 45-2 8 49-6 8 45-3 8 49-7 8 45-4 8 49-8 9 45-5 8 49-9 8 45-6 8 49-10 8 45-7 9 49-11 8 45-8 8 49-12 8 I 45-9 8 49-13 8 Revision: 13 9
August 1998 i W Westirighouse oNp01\pra\rev.,13\pra-loe wpf.lb ]4
!HE .:. .
. List of Effective Pcges ~
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9, AP600 PRA List of Effective Pages Page Revision Page Revision Page Revision Page Revision 50-1 8 54-10 8 54C-1 11 56-1 8 through through and through 50-16 54-32 54C-4 56-11 1 50-17 13 54-33 9 50-18 8 through 50-76 50A-1 11 54-34 8 55-1 9 56-12 5 through through through through 50A-3 54-39 55-6 56-111 54-40 9 55-7 10 51-1 8 54-41 8 55-8 9 through through through 51-21 54-97 55-72
,A 54-98 9 55-73 10 52-1 8 54-99 9 55-74 9 57-1 9 through through through 52-30 55-75 57-156 52-31 9 54-100 8 55-76 10 through 54-319 52-32 8 54A-1 9 55-77 9 57A-1 9 through through through through 52-156 54A-5 55-140 57A-4 l
54A-6 11 53-1 8 54A-7 9 55A-1 9 57B-1 11 I through through through 54 A-154 55A-31 57B-18 1 54-1 8 54B-1 11 55B-1 9 i
through through through )
l 54-8 54B-248 55B-104 54-9 9 55C-1 11 58-1 4 )
through through 55C-6 58-3
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I o
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L Revision: 13 l W Westinghouse (k,,,. August 1998 15 oVlWa*v 13Wa-lePf:lb
List sf Effectiva P;ges ,
AP600 PRA O
List of Effective Pages Page Revision Page Revision Page Revision Page Revision 59-1 8 59-104 8 D-1 11 through through through 59-7 59-203 D-107 59-8 12 59-9 8 through 59-36 59-37 9 59-204 11 D-108 12 59 38 9 59-205 8 59 39 8 59-206 8 59-40 8 59-207 11 through 59-236
$9-41 9 59-42 8 A-1 2 through through 59-68 A 296 59-69 11 59-70 8 through 59-74 59-75 11 B-1 11 through through 59-82 B-5 59-83 8 B-6 12 through 59-86 59-87 9 B-7 11 through B-36 59-88 8 C-1 9 through through 59-100 C-10 59-101 9 C-Il 11 59-102 9 l 59-103 12 Revision: 12 July 1998 W W85tingh0USB o:Mp0lWVev.12Wloc.wpf.lb ]6 l ..
. 34. Severe Accident Phenomens Treitment ml
\ -
v
+ 0/2 IRWST recirculation lines
- 1/2 cavity flooding lines l
- Containment failure in CMT room due to hydrogen detonation (at time just after core relocation)
- Hydrogen igniters not operating The main events of the case are shown in Table 34-14, while relevant plots are presented in Figures34-131 through 34-150.
34.4.2.5 3BE Overpressure Containment Failure due to Passive Containment Cooling Failure (3BE-10)
The purpose of this case is to determine the thermal-hydraulic results and source term release fractions for an assumed overpressure containment failure due to failure of the passive containment cooling. No water or air cooling of the containment shellis credited. The timing of the containment failure is conservatively based on a containment failure pressure of 90 psig (see Chapter 42), with the pressurization rate calculated via an adiabatic heatup with MAAP4.
As described in subsection 34.4.1, the limiting scenario for 3BE is an intermediate LOCA with minimal systems available. The relevant assumptions from this case include:
I
= 0/2 ADS stage 2
- 4/4 ADS stage 4 - automatic
= 0/2 IRWST injection lines
= 0/2 IRWST recirculation lines I
- 1/2 cavity flooding lines
- Passive containment cooling fails
- Containment failure in valve vault at P = 90 psig
The main events of the case are shown in Table 34-15, while relevant plots are presented in Figures34-151 through 34-170.
34.4.3 Accident Class 3BL - Intact Containment As noted in Table 34-2, accident class 3BL sequences are fully depressurized sequences with successful gravity injection. In these cases, failure of recirculation causes core damage.
l These sequences contribute over 25 percent to the core damage frequency. 3BL sequences in the top 25 dominant core damage sequences include intermediate LOCA (#2 and #21),
medium LOCA (#8), small LOCA (#12), CMT line break (#13), large LOCA (#16 and #17) m (O)
NEL Revision: 13
[ W85tingh0tlS8 E,mi.th August 1998 34-15 orawvi3wcuugibm8m
- 34. Severt Accidst Phenom na Tre:tme t E' .
I medium LOCA (#8), small LOCA (#12), CMT line break (#13), large LOCA (#16 and #17)
I and RCS leakage (#20).
I To analyze 3BL sequences, the first step is an analysis of the dominant 3BL sequence. A i subsequent sensitivity is performed with respect to system assumptions to maximize source I term results. However, further sensitivities on break size are deemed unnecessary since the I success of ADS stage 4 will dominate break size effects. His is observed for the 3BE break I size sensitivities where the release fractions are essentially the rame. All cases described I within this section are intact containment analyses. These cases are discussed below.
I 34.4.3.1 3BL Dominant Sequence (3BL-1)
I nis case determines the thermal hydraulic response and examines the fission-product releases I for the accident class 3BL dominant sequence. This sequence corresponds to core damage I sequence #2 from the level I results.
l The sequence description and assumptions are listed below:
I = 6-inch hot-leg break i = Failure of PRHR I
- 2/2 CMTs (both inject to RCS)
!
- 2/2 ADS stage 3 - automatic I
- 4/4 ADS stage 4 - automatic l = 2/2 IRWST gravity injection lines I
=
I Cavity flooding unnecessary since IRWST gravity injection successful I No containment failure is considered, thus the release category is IC (Intact Containment);
I however, normal leakage from the contamment is assumed. Reflooding the core via the l 1 hot leg break is not credited. His case is terminated at 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following core damage.
I he main events of the case are shown in Table 34-16, while relevant plots are presented in I Figures34-171 through 34-188.
I 34.4.3.2 3BL Dominant Sequence Sensitivity on System Availability Assumptions (3BL-2) l his case compares the results of changes to system assumptions to the dominant sequence I discussed above. He results of this comparison are used to define the system assumptions I for subsequent 3BL containment failure analyses. ,
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- 45. Fission-Product Source Terms ,
l Table 45-3 RELEASE CATEGORY IC CASES FOR COMPARISON Accident CET Report Class Case Sequence Description Path Section I 3BE 3BE- 4 6-inch Hot Leg Break I 34.4.1.4 4/4 ADS Stage 4 0/2 IRWST Injection 1/2 Cavity Flooding 3BL 3BL-1 6-inch Hot Leg Break 9 34.4.3.1 4/4 ADS Stage 4 f
2/2 IRWST Injection 0/2 IRWST Recirculation l
1/2 Cavity Flooding 3BR 3BR-1 10-inch Hot Leg Break 1 34.4.5.1 0/2 Accumulators 4/4 ADS Stage 4 1/2 IRWST Injection / Recirculation 1/2 Cavity Flooding 3C 3C-1 0.1 m2Vessel Rupture 1 34.4.7.1 4/4 ADS Stage 4 2/2 IRWST Injection / Recirculation 1/2 Cavity Flooding 3D 3D-1 DVI Line Break 9 34.4.9.1 0/4 ADS Stage 4 1/2 IRWST Injection / Recirculation 1/2 Cavity Flooding ,
Revision: 13 August,1998 di W WeStingh0USB >
otra\revl3\sec45.wpf;1b-081098 45-10
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- 50. Importance end S:nsitivity An-lysis I
( ,
v .
assumed to result in a relocation of the core out of the vessel, then containment failure would always result for the 3C accident class. The results of this sensitivity show the resulting large release frequency would be 2.7E-08 events per year, and the containment effectiveness would bc 84 percent. This is not a significant impact on the large rebase frequency.
PC Node The PC node models the success or failure of the passive containment cooling system (PCS).
If the air flow in the containment anwlar spaces is blocked, preventing the passive l containment cooling system from cooling the containment shell, the containment will eventually fail from overpressurization. Assuming the containment always fails makes the large release frequency the same as the core damage frequency,1.7E-07 events per year.
IG Node The IG aode models the reliability of the hydrogen control (hydrogen igniters). If the hydrogen igniters are assumed to fail, the potential for a hydrogen combustion event that could fail the containment is increased. (Hydrogen detonation events are assumed to fail the containment.) The result shows the large release frequency becomes 4.3E-08 events per year, and the containment effectiveness is 74 percent. This shows that the operation of the i hydrogen igniters is important to maintaining a low release frequency. An investigation of
( ) other (non-zero) values of the reliability of the hydrogen control system is discussed later.
v DF Node This sensitivity assumes that containment failure results whenever a diffusion flame occurs.
Accident classes 3D and 1 AP (successful recovery of RCS depressuri2.ation at node DP) can produce diffusion flames, and this node is set to 1.0 for these two accident classes. As discussed in Chapter 38,44 percent of the sequences for accident class 3BE release hydrogen I through the valve vault and can produce a diffusion flame. Design features of the phmt I prevent this flame from threatening containment .ntegrity. Therefore the 3BE diffusion flame I is not considered in this analysis. The results show a release frequency of 2.6E-08 events per l year, and a containment effectiveness of 84.5 percent.
DTE Node The DTE node models the failure of the containment from an early hydrogen detonation event. If the occurrence of an early hydrogen detonation event is assumed to fail the containment, the large release frequency is 1.9E-08 events per year and the containment effectiveness is 89 percent. Tliis is essentially the same as the baseline case because the j patential for early hydrogen detonation events is very low in the AP600 containment with the laydrogen igniters functioning.
O Revision: 13 f 3 Westingh00S8 6 August 1998 50-17 uwawvi3wcsoampr.ib-osio98 l
l
- 50. Importance and Sensi2vity Analysis
'. a l DFG Node i The DFG node models the potential for containment failure due to a hydrogen dedagration i event. This sensitivity assumes that all hydrogen deflagration events result in an intermediate I containment failure, and the resulting large release frequency is 1.9E-08 events per year, with I a containment effectiveness of 89 percent. His is essentially the same as the base case I because the potential for hydrogen deflagration events or the progression of a liydrogen I deflagration event into a hydrogen detonation event is very low in the AP600 containment I with the hydrogen igniters functioning.
I DTI Node l The DTI node models the potential for containment failure due to an hydrogen deflagration-to-I detonation event. 'Ihis sensitivity assumes that all hydrogen bums transition from i deflagration-to-detonation and result in an intermediate containment failure. The resulting i large release frequency is 1.9E-08 events per year, with a containment effectiveness of 89 I percent. His is essentially the same as the base case, because the potential for hydrogen I deflagration events or the progression of a hydrogen deflagration event into a hydrogen i detonation event is very low in the AP600 containment with the hydrogen igniters functioning.
I 50.6.1.2 Initiating Event Importances for Large Release Frequency i ne contribution of at-power initiating events to the large release frequency is shown in i Table 50-17. Table 5018 shows the containment effectiveness (C,,) and the containment I failure probability (CCFP) for the dominant initiating events.
l The C,, for a loss-of-coolant-accident is over 90 percent. This reflects the ability of the I containment to mitigate the effects of a serious accident. A loss-of-coolant-accident is a rare i event with serious potential consequences. In fact, the core damage frequency is dominated i by loss-of-coolant-accident sequences. In the unlikely event that a loss-of-coolant-accident l i results in core damage, the containment is designed to prevent a large release.
I For transients, the C , is relatively low, The core damage frequency from transients is small.
I But, if a transient does result in core damage, it is most likely as a result of a common cause I failure of the instrument and control systems. His is also a rare event. Conservatively, no I recovery action is modeled in the PRA for such failures. Rese recovery actions, such as I finding alternative ways to actuate the automatic depressurization system would certainly be I undertaken by the operr.; ors. Also, if a transient does result in core damage, it sometimes I results in a high-pressure event. These events are assumed to lead to a failure of the reactor I coolant system pressure boundary, which is assumed to fail the containment. These are i conservative assumptions in the PRA models for transients.
p i r 30,1996 mwsoosprawv.swc50umf:Ib 50-18 h_ 3 Westiflgh0Use
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