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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] |
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< Westingh0Lise Energy Systems Box 355 Pinsburgh Pennsylvania 15230-0355 Electric Corporation NSD-NRC-97-5194 DCP/NRC0923 i Docket No.: STN-52-003 I
June 18,1997 i .
l Document Control Desk
! U.S. Nuclear Reguhtory Commission l Washington, DC 20.155 ATTENTION: T. R. QUAY
SUBJECT:
CONTAINMENT SCREENS AND STRAINERS l
1
Dear Mr. Quay:
i During the review of the AP600 the NRC staff has asked a number of questions about the potential for clogging of strainers and screens in the AP600. This concern was raised by the staff in response to a number of occurrencer t.1 operating nuclear power plants (primarily boiling water reactors) in which debris was found in locatior.s trat were either clogging or had the potential to clog strainers in safety related systems.
The conclusion of the evaluation for AP600 was that the containment recirculation screens and IRWST screen are reliable and there is not a significant potential for clogging. This conclusion and justification supporting are outlined in the response to open items and requests for additional information attached to this letter. These items and the Westinghouse status in the open item tracking system are tabulated below.
Item Number OITS Number Status Meeting March 3,1994 460 Action N Action item 3B DSER 0150 #23 2019 Closed RAI 260.77 2933 Closed l RAI 640.59 (ITAAC) 5241 Confirm W The SSAR change; wili be included in Revision 14 of the SSAR. ,
Please contact D. A. Lindg:en at (412) 374-4856 if you have any additional questions.
( )
Brian A. McIntyre, Manager Advanced Plant Safety and Licensing 3*' ,! !l ec: W. Iluffman, NRC (w/ Attachment)
N. Liparulo, Westinghouse (w/o Attachment)
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Action item 3B, Meeting March 3,1994 (OITS #460)
, Meeting 3/94 Action Item 3B - Review information notice on clogging of wet well at Perry and confirm that the IRWST will not have a similar clogging issue.
- Response
A review of incidents related to BWR ECCS pump sitction strainer plugging in the suppression pools indicates that the most significant factors affecting plugging are the use of fibrous insulation that can be swept into the suppression pool tanks and the use of carbon steel material for the suppression pool tanks and the associated piping. The suppression pools accumulate sludge, mostly iron oxide corrosion products j from the carbon steel components in the BWR fluid systems. Fibrous insulation dislodges and has been swept into the suppression pool by post-accident forces and migrates to the suction strainers during ECCS
- pump operation. The fibrous insulation traps sludge particles causing plugging of the ECCS lines. Other incidents involve inadequate cleanliness programs which can result in blockage of the ECCS pump suction l
- strainers in lines from the suppression pools or sumps.
l AP600 IRWST Potential for Blockage:
i, l The AP600 IRWST is not subject to the problems that have occurred in BWRs with respect to clogging in their suppression pool strainers. The IRWST and the connected systems are constnicted of stainless steel which prevents the formation of significant amounts of corrosion products. The IRWST water is required to be maintained clean because it is used in the refueling canal during refueling operations. The use of stainless steel materials and the purification of the IRWST (filters and demineralizers) provided by the spent fuel cooling system during and following refueling operations maintains water cleanliness.
There are two inlets to the IRWST that return condensate from the containment shell to the IRWST from the IRWST gutter. The gutter is located at the top of the IRWST which is at the operating deck level.
This level is well above the high energy process lines that can become LOCAs. The gutter has a trash rack covering its inlet. The gutter flow enters the IRWST through two 4" lines. The probability of significant insulation debris entering the IRWST is very low. j SSAR subsection 6.1.2.1 discusses the use of protective coatings inside containment. The inorganic zinc coating applied to the inside surface of the containment shell is one potential source of debris that may enter the gutter and ti.e IRWST. As described in SSAR subsection 6.1.2.1.5, failure of this coating produces a heavy powder which if it enters the IRWST through the gutter will settle out on the bottom of the IRWST because of its high specific gravity. Settling is enhanced in the IRWST by low velocities in the tank and long tank drain down times (>5 hours).
Insulation is not used inside the IRWST. Air filters are not used in the IRWST vents or overflows.
Because of the location and the size (4") of the two inlets to the IRWST from the IRWST gutter, the probabilny of significant amounts of insulation being swept into the tank is very low. Outside of the IRWST, the AP600 ures stainless steel reflective insulation in areas that are subject to LOCA damage to limit the arnount of de'aris created by the LOCA.
The IRWST sevens and containment recirculation screens are designed to provide a reliable source of safety injection water to the passive core cooling system. Consideration is given to the types and locations l of insulation, coatings, corrosion products, and foreign materials. The screens are designed to Regulatory Guide 1.82, revision 2. The Combined License applicant is required (SSAR subsection 6.3.8.1) to have a cleanliness program, which controls foreign materials in the containment after refueling / maintenance ]
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shutdowns. The AP600 Technical Specifications require visual inspections of the screens during every refueling outage.
Based on these features the AP600 IRWST provides a reliable source of safety injection water following LOCAs.
Incidents:
Barseback Unit 2 (Sweden) - mineral wool (fibrous) insulation dislodged from relief valve partially plugs spray system suction strainers.
l Perry - RHR strainers clogged by operation debris l Perry - RHR strainers covered by glass fibers from maintenance air filters debris. The finer air filters collected corrosion products int he suppression pool which reduced RHR flow.
,. Limerick Unit 1 - RHR strainer (in uncleaned suppression pool) covered by miscellaneous fibers and iron l oxide sludge degrading RHR performance.
Potential Incidents:
Palisades - Maintenance use of plastic materials potential for plugging sumps.
Grand Gulf - Plastic covers inside containment could be dislodged during LOCA and plug sumps.
l Browns Ferry Unit 2 - Cloth and paper towels (cleaning debris) in pool potential for plugging.
i, Grand Gulf - Low suction pressure in RHR line due to clogging of strainers by pool debris.
- North Anna Unit 1 - steam generator and pressurizer paint failed on large sheets which could clog sumps.
LaSalle Unit 1 - Misc. debris in suppression pool including plastic bag on strainer. .
Quad Cities Unit 1 - Plastic bag in RHR pump suction.
Reviewed Documents:
Reg Guide 1.82, Revision 2 NRCB 93-02 Supp. I NRCB 95-02 NRCB 96-03 IN 95-47 IN 95-06 IN 93-02 and Supp I IN 92-85 IN 88-28 '
IN 90-07 IN 92-71 IN 93-34 and Supp 1 l
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't j DSER bl50 #23 (OITS 2019) i DSER-0150 #23 - Debris in IRWST and Containment Sumps The staff is concerned that the strainers in the IRWST and containment sumps could be clogged by debris.
Important factors are the use of non-safety related coatings in the AP600, and possible sensitivity in this design to screen clogging because of dependance on gravity-driven flows. (DSER Open Item 6.2.1.81).
1
Response
The IRWST screens and the containment recirculation screens of the AP600 are designed and located to provide a reliable source of safety injection following LOCAs. Refer to responses to ITAAC RAI 640.59 I Followup Question, Chapter 14 RAI Question 260.77, and Open Item 460 for additional information.
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't l NRC REQUEST FOR ADDITIONAL INFORMATION z= .
8A E RAI 260.77 (OITS #2933)
Westinghouse will provide the method (s) that will be used to prevent strainer clogging in the passive l safety systems.
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Response-l l The AP600 IRWST screens and the containment recirculation screens are designed to comply with NRC licensing criteria and to provide a reliable source of safety injection following LOCAs. The response to
! ITAAC RAI 640.59 followup question provides an additional SSAR subsection which describes the AP600 l
screens and the features that make them reliable. In addition, the response to Open Item 460 discusses events that have occurred at BWRs and their relevance to the AP600 IRWST design.
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t 260.77-1 W
Westinghouse
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$RC R$ QUEST FOR ADDITIONAL INFORMATION nn:m;r.-:
0 RAI 640.59, ITAAC Followup Question (OITS #5241) 4 The containment recirculation screens and IRWST strainers are designed in conformance with RG 1.82 and to address the technical concerns raised in Generis Safety Issue A-43, " Containment Emergency Sump Performance." The staff provided further clarification of these concerns in Bulletins 96-03 and 95-02.
The staff disagrees with Westinghouse's assessment that these bulletins only apply to boiling water reactor designs and are not applicable to the AP600 strainer design. Westinghouse needs to document in the SSAR what actions will be taken to address the conditions described in these bulletins on the IRWST i strainer design. Design commitments resulting from the review of RG 1.82. GSI-43, and the bulletins should be incorporated into the ITAAC.
Response
The AP600 IRWST screens and the containment recirculation screens are designed to comply with NRC licensing criteria and to provide a reliable source of safety injection following LOCAs. Attached is an additional SSAR subsection which describes the AP600 screens and the features that make them reliable.
Table 6.3-4 is revised to include the screens. Figures 6.3-6,6.3 7,6.3-8, and 6.3-9 are added to show the locations of the screens. Subsection 6.3.8 is revised to include the Combined License applicant information item for a cleanliness program. Sheet 3 of Table 6.3-5 is revised to remove the term " sump" which is not used in the AP600.
l In addition, the response to March 3,1994 meeting Action item 3B (OITS #460) discusses events that have occurred at BWRs and their relevance to the AP600 IRWST design.
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- 6. Engineered Safety Features j
i 'l 6.3.2.2.7 IRWST and Containment Recirculation Screens I
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l The passive core cooling systems has two different sets of screens that are used following a !
I LOCA; IRWST screens and containment recirculation screens. These screens prevent debris i I from entering the reactor and blocking core cooling passages during a LOCA. These screens
! I are designed to comply with applicable licensing regulations including: ;
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GDC 35 of 10 CFR 50 Appendix A I -
Regulatory Guide 1.82 1 -
NUREG-0897 I l 1 The operation of the passive core cooling system following a LOCA is described in subsection 1 6.3.2.1.3. Proper screen design, plant layout, and other factors prevent clogging of these I screens by debris during accident operations.
I I General Screen Design Criteria: !
I 1) Screens are designed to Regulatory Guide 1.82 including:
1 - Redundant screens are provided for each function 1 -
Separate locations are used for redundant screens 1 -
Screens are located well below containment floodup level. Each screen has a i coarse and a fine screen, and a debris curb I -
F!oors slope away from screens (not required for AP600) 1 -
Drains do not impinge on screens I - Screens can withstand accident loads and credible missiles I - Screens have conservative flow areas to account for plugging. Operation of the I non-safety-related normal residual heat removal pumps with suction from the l IRWST and the containment recirculation lines is considered in sizing screens.
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System and screen performance are evaluated 1 -
Screens have solid top cover 1 -
Screens are seismically qualified 1 - Screen openings are sized to prevent blockage of core cooling 1 -
Screens are designed for adequate pump performance. AP600 has no safety-I related pumps.
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Corrosion resistant materials are used for screens 1 - Access openings in screeris are provided for screen inspection 1 -
Screens are inspected each refueling i 2) Low screen approach velocities limit the transport of heavy debris even with operation I of normal residual heat removal pumps.
I 3) Use of stainless steel reflective insulation limits debris generated by high energy line I breaks.
I 4) Use of coatings designed for post accident conditions. Refer to subsection 6.1.2.1.0.
I 5) The IRWST is enclosed which limits debris egress to the IRWST screens.
I 6) Containment recirculation screens are located above lowest levels of containment.
I '7) Long settling times (> 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />) are provided before initiation of containment I recirculation.
Revision: 14. otuarni4ao3n r 4 m io97 Draft,1997 W Westliighouse 6.3 2
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l 8) Air ingestion by safety-related pumps is not an issue in the AP600 because there are no I safety-related pumps. The normal residual ha. removal system pumps are evaluated I to show that they can operate with minimum water levels in the IRWST and in the l l containment.
I 9) A COL commitment for cleanliness program to limit debris in containment is provided.
I 1 IRWST Screens:
1 The IRWST screens are located inside the IRWST at the bottom of the tank. Figure 6.3-6 I shows a plan view and Figure 6.3-72 shows a section view of these screens. Two sepaate I screens are provided in the IRWST, one at either end of the tank. The IRWST is closed off l 1 from the containment; its vents and overCows are normally closed by louvers. The potential i for introducing debris inadvertemly during plant operations is limited. A COL cleanliness I program (refer to 6.3.8.1) contr..'s foreign debris from being introduced into the tank during I maintenance and inspection operations. The Technical Specifications require visual I inspections of the screens during every refueling outage.
I I The IRWST design eliminates sources of debris from inside the tank. Insulation is not used I in the tank. Air filters are not used in the IRWST vents or overflows. Wetted surfaces in the l IRWST are corrosion resinant such as stainless steel or nickel alloys; the use of these I materials prevents the formation of significant amounts of corrosion products. In addition, I the water is required to be clean because it is used to fill the refueling cavity for refueling; I filtering and demineralizing by the spent fuel pit cooling system is provided during and after i refueling.
I I During a LOCA, steam vented from the reactor coolant system condenses on the containment I shell, drains down the shell to the operating deck elevation and is collected in a gutter. It is I very unlikely that debris generated by a LOCA can reach the gutter because of its location.
i The gutter is covered with a trash rack which prevents larger debris from clogging the gutter I or entering the IRWST through the two 4 inch drain pipes. The inorganic zinc coating I applied to the inside surface of the containment shell is one potential source of debris that I may enter the gutter and the IRWST. As described in subsection 6.1.2.1.5, failure of this I coating produces a heavy powder which if it enters the IRWST through the gutter will settle I out on the bottom of the ff.WST because of its high specific gravity. Settling is enhanced in i the IRWST by low velocities in the tank and long tank drain down times (>5 hours).
I I The design of the IRWST screens reduces the chance of debris reaching the screens. The I screens are orientated vertically such that debris that settles our of the water does not fall on I the screens. A debris curb located at the base of the IRWST screens prevents high density I debris from beirg swept along the floor by water flow to the IRWST screens. The IRWST I screens are made up of a trash rack and a fine screen. The trash tack prevents larger debris I from reaching the finer screen. The fine screen prevents debris larger than 0.25" from being i injected into the reactor coolant system and blocking fuel cooling passages.
I I The screen flow area is conservatively designed considering the operation of the nonsafety-i i related normal residual her.t removal system pumps which produce a higher flow than the 1
Revision: 14 Draft,1997
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l safety-related gravity driven IRWST injection / recirculation flows. As a result, when the l l normal residual heat removal system pumps are not operating there is a large margin to screen
! I clogging.
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I Containment Recirculation Screens:
1 The containment recirculation screens are oriented vertically along walls above the loop I compartment floor (elevation 83 feet). Figure 6.3-8 shows a plan view and Figure 6.3-9 shows I a section view of these screens. Two separate screens are provided as shown in figure 3. The I loop compartment floor elevation is significantly above the lowest level in the containment, the I reactor vessel cavity, which is 11.5 fee: below. The bottom of the recirculation screen is two foot I above the floor, providing a curb function.
I 1 During a LOCA, the reactor coolant system blowdown will tend to carry debris created by the I accident (pipe whip / jets) into the cavity under the reactor vessel which is located remote away I from and below the containment recirculation screens. As the accumulators, core makeup tanks I and IRWST inject, the containment water level will slowly rise up to the 108 foot elevation over I at least 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. The containment recirculation line opens when the water level in the IRWST I drops to a low level setpoint a few feet above the final containment floodup level. When the i recirculation lines initially open, the water level in the IRWST is higher than the containment and I water flows from the IRWST backwards through the containment recirculation screen. This back I flow tends to flush debris located close to the recirculation screens away from the screens.
I The water level in the containment when recirculation begins is well above (~ 10 feet) the ton of I
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I the recirculation screens. During the long containment floodup time (>5 hours), floating debris .
I does not move toward the screens and heavy materials settle to the floors of the loop j I compartments or the reactor vessel cavity. During recirculation operation the containment water i level will not change significantly nor will it drop below the top of the screens.
I I The amount of debris that may exist following an accident is limited. Reflective insulation is I used to limit the debris that can be generated by a high energy line break and be postulated to I reach the screens during recirculation. The nonsafety-related coatings used in the containment ;
I are designed to withstand the post accident environment. A COL evaluation (subsection 6.1.3.2)
I shows that these screens provide flow area margin considering the post accident generation and I transport of debris from coatings inside containment.
i l A COL cleanliness program (refer to 6.3.8.1) controls foreign debris introduced into the I containment during maintenance and inspection operations. The Technical Specifications require I visual inspections of the screens during every refueling outage.
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l The design of the containment recirculation screens reduces the chance of debris reaching the l
I screens. The screens are orientated vertically such that debris settling out of the water will not I fall on the screens. The bottom of the screens are raised about I foot above the floor, instead
, I of using a debris curb, to prevent high density debris from being swept along the floor by water flow to the containment recirculation screens. The containment recirculation screens are made
( l I up of a trash rack and a fine screen. The trash rack prevents larger debris from reaching the finer i
Revision: 14. owwrvimo603n ri4so61697 Draft,1997 [ W85tlligh0US8 6.3-4
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I screen. The fine screen prevents debris larger than 0.25" from being injected into the reactor I coolant system and blocking fuel cooling passages. 1 1
I The screen flow area is conservatively designed considering the operation of the normal residual I heat removal system pumps which produce a higher flow than the gravity driven IRWST I injection / recirculation flows. As a result, when the normal residual heat removal system pumps I are not operating there is even more margin in screen clogging. i I 6.3.2.2.87 Valves (This Subsection Renumbered) 6.3.8 Combined License Information This =ction has ac requ.re:nen: for addi:!cnal infc=a:!cn to be provided in =pport cf the Combined L-ieen= applicatica I 6.3.8.1 Containment Cleanliness Program I
l The Combined License applicants referencing the AP600 will address preparation of a program i to limit the amount of debris that might be left in the containment following refueling and I maintenance outages. 1 I
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Revision: 14 Draft,1997
[ W8Silngh00$8 6.3 5
- 6. Engineered Safety Features Table 6.3-4 (Sheet 2 of 2)
COMPONENT DATA PASSIVE CORE COOLING SYSTEM IRWST Number 1 Type Integral to containment internal structure Volume (gallons) 567,000
. Minimum required volume (gallons) 557,000 ,
Design pressure (psig) 5 !
Design temperature ( F) 150
- Material Wetted surfaces are stainless steel AP600 equipment class C Spargers Number 2 Type Cruciform Design pressure (psig) 600 Design temperature ( F) 500 Material Stainless steel AP600 equipment class C pH Adiustment Baskets Number 2 Type Rectangular Volume (cubic feet) 107 Material Stainless steel AP600 equipment class C I Screens IRWST Containment Recirculation i
I Number 2 2 i Surface Area (square feet) 70 70 l Material Stainless Steel Stainless Steel I AP600 Equipment Class C C
- Several times during plant life, the refueling water could reach 240*F.
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. 6. Engineered Safety Features i l l l
l Table 6.3-5 (Sheet 3 of 5) l l
l FAILURE MODE AND EFFECTS ANALYSIS PASSIVE CORE COOLING SYSTEN! l ACTIVE COSIPONENTS Failure Failure Plant Detection Component Mode Condition Effect on System Operation Method Remarks 1 I
IRWST gutter Failure to All design No safety-related effect since each valve Valve position )
isolation valves close basis events has a redundant, series isolation AOV, indication ;
actuated by a separate division, which alarm in MCR l V130A/B closes to divert the gutter flow into the and at RSW Normally IRWST open/ fait closed ;
Containment Failure to All design No safety-related effect since each valve Valve position j l recirculation semp open basis events has a redundant flow path through a indication l line check valves MOV and a squib valve, actuated by alarm in MCR l separate divisions, that open to provide and at RSW Vil9A/B recirculation through a parallel branch line. The other containment recirculation Normally closed line is unaffected. I Containment Failure to All design No safety-related effect since each valve Valve position I recirculation semp open basis events has a redundant flow path through a indication line squib valves MOV and a squib valve, actuated by alarm in MCR separate divisions, that open to provide and at RSW J V120A/B recirculation through a parallel branch l line. The other containment recirculation !
Normally closed / line is unaffected. )'
fail as is l
Containment Failure to All design No safety-related effect since each valve Valve position !
I recirculation sump open basis events has a redundant flow path through a indication line MOVs / check valve and a squib valve, actuated alarm in MCR squib valves by separate divisions, that independently and at RSW open to provide recirculation through a Vil7A/B, parallel bran:h line. The other contain.
VI,18A/B ment recircu.ation line is unaffected.
Normally closed /
fail as is Accumulator fill / Spurious All design No safety-related effect since each valve Valve position drain line isola- opening basis events has either a normally closed redundant, indication tion AOVs series isolation valve or a check valve in alarm in MCR each drain flow path, which prevents arid at RSW V232A/B draining water from the accumulator.
Normally closed /
fail closed Revision: 14 V" / W85tingh00$8 Draft,1997 6.3-7
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Revision: 12 April 30,1997 6.3-10 W Westinghouse
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