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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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Cover + Pages
- P l+10-Tho following pages are being sent from the Westinghouse Energy Center, East Tower, Munroeville, PA. If any problems occur during this transmission, please call:
WIN: 284-5125 (Janice) or Outside: (412)374-5125. _
COMMENTS:
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- 9. A0xhary Systems n ,; a ,
)
i pmcessed in the demineralized water transfer and storage system to remove dissolved oxygen.
In addition.to supplying water for makeup of systems which require pure water, the i
demineralized water is used to sluice spent radioactive resins from the ion exchange vessels l
i in the chemical and volume control system (as described in subsection 9.3.6), the spent fuel 1 pool cooling system (as described in subsection 9.1.3), and the liquid radwaste system (as '
I described in section 11.2) to the solid radwaste system.
h denuneralized water treatment system is described in subsection 9.2.3.
9.2.4.1 Design Basis 9.2.4.1.1 Safety Design Basis h deminerahzed water transfer and storage system serves no safety-related function other than contamment isolation, and therefore has no nuclear safety-related design basis except for containment isolation. See subsection 6.2.3 for the containment isolation system.
9.2.4.1.2 Power Generation Design Basis
+ he demineralized water transfer and storage system provides deminerahzed water j i through the demineralized water storage tank to fill the condensate storage tank and to i meet required demands and usages of demincralized water in other plant systems.
- The demineralized water transfer pumps provide adequate capacity and head for the distribunon of demineralized water.
l . De deminerahzed water storage tank supplies a source of demineralized water to the I
chenucal and volume control makeup pumps during startup and required boron dilution I
evolutions. De demineralized water transfer and storage system supplies the required I
amount of water to the chemical and volume control system for reactor water makeup.
1
- De oxygen content of water supplied to the demineralized water distribution system from the demineralized water storage tank is 100 ppb or less.
I 1
- Sufficient storage capacity is provided in the condensate storage tank to satisfy condenser i makeup demand based on maximum steam generator blowdown operation during a plant I startup duration.
!
- De condensate storage tank provides the water supply for the startup feedwater pumps I during startup, hot standby, and shutdown conditions.
- De condensate storage tank provides a sufficient supply of water to the startup feedwater i system to permit 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of hot standby operation, followed by an orderly plant I
cooldown from normal operating temperature to conditions which permit operation of the i
normal residual heat removal system over a pedod of approximately 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
L-Revision: 6 March 29,1996
$@ 9.2 21 200*390d 38f4 01 1833 f49IS3G 009dd WOdd 15:8 96. 9 ASW
I t NRC REQUEST FOR ADDmONAL INFORMATION eB&*#$b3 gm Ouestion 410.292 In Section 10.4.9.2.1 of the SSAR (Revision 4), Westinghouse changed the pump capacity of the stanup feedwater system to two 50-percent from two 100-percent pumps. Section 10.4.9.1.2 of the SSAR Item 11. states that two startup feedwater pumps are provided with a single pump capable of satisfying the startup feedwater system flo for decay heat removal. Justify how a single Spercent capacity pump (with one pump in standby) can satisfy th flow demand and redundancy requirements.
Response
The Stanup Feedwater Pump po: tion of SSAR subsection 10.4.9.2.2, Revision 6,is now consistent with subsection 10.4.9.1.2. Each startup feedwater pump can supply 100 percent of the required flow to the steam generators to meet decay heat requirements.
SSAR Revision: NONE w PRELIMINARY
- w 4
0 410.292-1 C00*399d OdN 01 Id3D NDI530 009dv Woda 49:8 96. 9 >Su
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- 3. Design of Structures, Comronents, Ihulpmrt end Systems I reactor plants (which have not experienced streu corrosion cracking in the auxiliary stainless
- i steel piping).
l 1 Main Steam Line and Main Feedwater Line I The rnain steam piping is constructed from ferritic steel. Stress corrosion cracking in ferritic I steels commonly result from a caustic environment. A source of a caustic environment in the I main steam piping would be moisture carryover from the steam generator. However, the I secondary side water treatment utilizes all volatile treatment. All volatile treatment effectively I precludes causticity in the steam generator bulk liquid environment. For some operating I plants prior to implementing all volatile treatment, the phosphate water treatment caused a I caustic chemical imbalance resulting in stress corrosion cracking of steam generator tubing.
I Under all volatile treatment water treatment conditions, there is no instance of caustic stress I corrosion cracking on the ferritic steam lines indicating no significant caustic carryover. De I operating secondary side chemistry precludes stress corrosion cracking on the ferritic main i steam line.
I l Stress corrosion cracking is not expected to occur in the main feedwater ime piping because 1 of control of the oxygen to very low levels. There has been no experience with stress.
I corrosion cracking in feedwater lines in operating plants of Westinghouse design. De l operating secondary side chemistry precludes stress corrosion cracking on the main feedwater I line.
1 I Based on the above discussion, stress corrosion cracking does not have an adverse effect on I the integrity of AP600 leak-before-break piping systems.
I l 38.2.3 Water Hammer 1
l Primary Loop Piping i
i ne reactor coolant loop is designed to operate at a pressure greater than the saturation 1 pressure of the coolant, thus precluding the voiding conditions necessaiy for water hammer I to occur. De reactor coolant primary system is designed for Level A, B, C. and D (normal, I upset, emergency, and faulted) service condition transients. The design requirements are I conservative relative to both the number of transients and their severity. Relief valve I actuation and the associated hydraulic transients following valve opening have been considered I in the system design. Other valve and pump actuations cause relatively slow transients with l 1 no significant effect on the system dynamic loads.
I l 1 To provide dynamic system stability, reactor coolant parameters are controlled. Temperature l l during normal operation is maintained within a narrow range by control rod positioning.
I Pressure is controlled within a narrow range for steady-state conditions by pressurizer heaters I and pressurizer spray. De flow characteristics of the system remain constant during a fuel I cycle. He operating tram.ients of the reactor coolant system primary loop piping are such
' that significant water hammer loads are not expected to occur.
Revision: 7 3B-5 APril 30,1996 3 Weli$tghouli8 t' 00 ' 3 O d d ?dN 01 Id33 NOl93G 009dS WOdd e c, : 8 96. 9 wu i
- 3. Desip of Structures, Compon nts, Equiprnent cnd Systems
! Auxiliary Stainless Steel Piping I
I The passive core cooling system and automatic depressurization system are designed to I minimize the potential for water hammer induced dynamic loads. Design features include:
I I
- Continuously sloping core makeup tank and passive residual heat exchanger inlet lines I to eliminate local high points 1
1 - Inlet diffusers in the core makeup tanks to preclude adverse steam and water interactions l
- Vacuum breakers in the discharge lines of the automatic depressurization valves
! connected to the pressurizer I
l De AP600 pressurizer spray control valve is similar to what is used in the operating plants.
I nere is no history of water hammer caused by the spray control valve.
1 I The normal residual heat removal system isolation valves are slow closing valves, identical I to operating plants, and therefore would not be a source of water hammer.
I l Rese features minimize the potential of water hammer in the auxiliary stainless steel piping I system.
I i Main Feedwater Line 1
l The feedwater piping, steam generator design details, and c'.her component (.'etails in the i feedwater system are designed to minimize the potential and severity of water hanmer within I the feedwater piping. De following addresses each aspect of the design incoprated to I minimize water hammer.
I l Steam Generator Design: De AP600 steam generator design benefits from investigation of I water hammer events and the resulting design changes developed to address the events 1 (References 4 through 8).
I i
- Top discharge feed flow through spray tubes (similar to J-tubes) from the feedring I reduces the potential of void formation when the steam generator level drops below the i feedring level. Previous steam generator feedring designs had incorporated bottom i discharge holes that permitted feedring draining whenever the steam generator level I dropped below the feedring.
I l
i
- Feedwater nozzle design incorporates a welded thermal liner attached to the feedwater i nozzle forging to form a positive seal to limit the potential for feedring drainage and I therefore void formation within the feedring. Previous designs had included a "close fit" Revision: 7 April 30,1996 3B-6 *[ W86tingh00$6 500*390d ?dN 01 id3D N9153G 009de Wodd 89:e 96, 9 yeu
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- 3. Desigi of Struct:res, Cosoponerts, Eq11pment cnd Systems f
_ _J l but not a complete seal at the connection to the nozzle forging. The welded thermal ;
I liner design has no leak paths within the steam generator through which the water can i l drain from the feedring. l l Feedwater piping design: The AP600 feedwater piping layout has incorporated features to i limit void formation and water hammer initiation.
I 1
- A downward facing elbow is connected to the steam generator nozzle and thus complies I with industry recomrnendations to minimize the horizontal feedwater piping connected I to the steam generator. The short horizontal section minimizes amount of steam void I which can form.
I l
- He muis feedwr.ter piping inside containment continuously rises to the steam generator I pmviding for natural venting of the steam generator in the event a steam void is formed.
I l
- Long straight piping runs in the feedwater line are limited.
I I Component and system design selection:
I I - A major cauw of water hammer problems in pressurized water reactor feedwater systems I has been control valve instability. Rese instabilities resulted from factors such as I oversized valve, unbalanced valve trim, damage to valve components, and incompatibility I of the feedwater control valve with the rest of the feedwater system. These problems are I minimized on AP600 by the following:
1 1 -
De specification of specialized vahe trim to avoid instability i
I - ne use of variable speed feedwater pumps to reduce the demands on the control I valve requirements l
1 - Reduced contml requirements on the main feedwater control valve by the use of a l stanup feedwater line that provides feedwater flow control from either the stanup 1 feedwater pump or the main feed pump at lower feed demand (power) levels.
I i - Main feedwater control valve positioning during normal oper. tion is the function I of the plant control system (see subsection 7.7.l.8) using a refinement of a standard I three element control scherne. ne control scheme provides greater steam generator i level stability and thus reduces potential feedwater transients.
I I - Rapid closure of some types of feedwater check valves may potentially cause water I hammer in main feedwater lines. The controlled closure check valve specified for the
! AP600 main feedwater lines limits the magnitude of the closing loads generated by vatve I closure caused by depressurization of the feedwater line upstream of the check valve.
\
Revision: 7 3B-7 April 30,1996 3 WOEdnghouse 900'390d 3dN 01 Ad3? N9153G 009dd WOdd SG 8 96. 9 Aeu
', f t" W'~~m
- 3. Design of Structures, Componen?., Equipment and Systems
[
1-
)
i I
- I heated feedwater is normally at least 250*F and heips teduce the possibility of water I hammer.
I l l
i l - Startup feedwater is piped directly to the steam generator. His feature helps prevent the 4
1 need to introduce cold water directly into the main feedwater and thus minimizes the l l chances of steam water counterflow or steam bubble collapse type of water hammer l 4
! events.
I
- I + Rapid resumption of feedwater flow to the steam generators is accomplished in the
~
l AP600 design. Numerous options are available to maintain or restore steam generator
. I level with the feedwater system design. Based on the flow demand signal and level of
- feedwater isolation either the main feedwater pump (s) or the startup feedwater pumps can I
I l adequately provide level control. If there is no engineered safeguard features feedwater i l isolation signal present, the main feedwater pumps will provide adequate steam generator 2
I inventory control. via the main feedwater line or the startup feedwater line. If a main
! I feedwater isolation signal exists then either the main feedwater pump (s) or the stanup I feedwater pump (s) provides startup feedwater flow via the startup feedwater line.
I 1 ne above design provisions make the potential for steam generator water hammer in the i feedwater line extremely low. However, with consideration for the main feedwater and steam ,
I generator design features, the susceptibility of the main feedwater line inside containment for I water hammer has been evaluated. He most common historic causes were evaluated as well l as the relevant modes of operation for susceptibility to the appropriate water hammer 1 mechanisms (Reference 4). He limiting anticipated and unanticipated events were evaluated.
I ne resuhs of the analysis demonstrate that the system is acceptable for leak before-break I application.
I I Main Steam Line i
l De steam lines are not subject to water hammer by the nature of the fluid transported. The I following system design provisions address concerns regarding steam hammer within the main i steam line and identify the significant dynamic loads included in the main steam piping i design.
I l . Design features that prevent water slug formations are included in the system design and i layout. In the main steam system, these include the use of drain pots and the proper i sloping of lines.
l l . De operating and maintenance procedures that protect against a potential occurrence of I steam hammer include system opera'ing procedures that provide for slowly heating up I (to avoid condensate formation from hotter steam on colder surfaces), operating i procedures that caution against fast closing of the main steam isolation valves except I when necessary, and operating and maintenance procedures that emphasir.e proper I draining.
Revision: 7 April 30,1996 3B-8 y Wes 4v)0086 100'390d Ddu 01 Ad3D N9153G 009de WOdd 00:6 96, 9 Aeu
- 3. Design of Structures, Components, Equipment End Systems [* %' 1
{
l - The stress analyses for the safety-related portion of the main steam system piping and I components include the dynamic loads from rapid valve actuations, including actuation 1 of the main steam isolation valvss and the safety vvhes 1
I Based on the above discussion, water hammer does not have an adverse effect on the integrity I of AP600 leak-before-break piping systems.
I 38.2.4 Fatigue I
l Low-Cyene Fatigue 1
I Low cycle fatigue due to normal operation and anticipated transients is accounted for in the i design of the piping system. The Class I piping systems comply with the fatigue usage I requirements of the ASME Code,Section III.
1 I A fatigue evaluation at the main feedwater nozzle equivalent to ASME Class I piping is
! performed. Also. a fatigue crack growth analysis at the main feedwater nozzle is performed.
I l Due to the nature of operating parameters, main steam line piping systems are not subjected I to any significant transients to cause low-cycle fatigue.
I l Based on the above discussion, lo w-cycle fatigue is not a concem of AP600 leak-before-break l piping systems.
1 I High-Cycle Fatigue i i i High-cycle fatigue loads in the system result primarily from pump vibrations. He steam I generator is designed so that flow induced vibrations in the tubes are avoided (see I subsection 5.4.2). The loads from reactor coolant pump vibrations are minimized by criteria l for pump shaft vibrations during hot functional testing and operation. During operation, an I alarm signals when the reactor coolant pump vibration is greater than the limits.
J I
l Main feedwater pump vibration is isolated from the leak before-break feedwater line inside ;
I I containment via the piping and equipment supports.
l i
I With these precautions taken, the likelihood of leakage due to fatigue in piping systems i evaluated for leak before-break is very small.
I i 3B.2.5 Thermal Aging i
l Stainless Steel Piping 1
I Piping used in the reactor coolant loop and other auxiliary lines are wrought stainless steel I materials, rather than cast materials, so that thermal aging concems are not expected for the i AP600 piping and fittings. The welds used in the assembly of the AP600 are gas tungsten I arc welds (GTAW). Dese welds are essentially as resistant to the effects of thermal aging Revision: 7 3B-9 Airil 30,1996 T Westinghouse 800*39ed ?dt4 01 183D tJ91530 009dd WOdd 00:6 96. 9 Aell l l
The Main Feedwater Line portion of SSAR Appendix 3B, subsection 3B.2.3, Revision 7, provides a more detailed discussion of the AP600 design features for mininuzing water hammer. includmg piping layout features. As indicated in SSAR subsection 5.4.2.2, the starup feedwater piping layout includes the same feamres as the main feedwater piping layout. As indicated thoughout SSAR subsection 10.4.9, the startup feedwater system is sized, operated and has water sources consistent with mimminng the potential for water hammer.
SSAR Revision: None
- k tf ,
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f 1 l
l In Revision 6 of the SSAR, sections 10.4.9.2.1 and 10.4.9.2.2 have been revised to be consistent with the first bullet of section 10.4.9.1.2. 'Ihe main feedwater system and the startup feedwater i system are parallel systems. The main feedwater system draws water from the deserator' tank and delivers it to the main feed rings within the steam generators. The startup feedwater system draws l water from the enr*nme storage tank and delivers it to the startup feedwater nozzle on the steam I
generators. They have a manual cross-connect between their respective pumps and control valves.
This will allow the main feed pumps to supply water from the deaerator tank to the stattup feedwater nozzles on the steam generators. A check valve (in addition to the normally closed isolation valve) in the cross-connect prevents the stanup feedwater pumps from supplying water from the condensate storage tanks to the main feed header and steam generator main feed rings.
SSAR Rev: None f'$
l So",A v'w }C l
OIO*390d 3dt1 01 id3? ff 9I53G 009dd WOdd 20 6 96. 9 Aeu
~
SSAR subsectiom 10.4J.1.1 and 10.4.9.1.1, Revision 7, include a more consistent description of safety related functions of the main and startup feedwater control and isolation valves. Subsection 10.4.7.1.1 discusses only main feedwater system functions and components. Subsection 10.4.9.1.1 discusses only startup feedwater functions and components. Bullet sections of subsection 10A.9.1.1 are imW to reenforce the first paragraph of the subsection. Startup feedwater isolation valves close on any of comainmmt isolation, steam generator isolation or feedwater isolation signals. They can also be closed by a remote manual signat SSAR Revision: None h e%' p $ 0 2.9 3 v2' I10 396d 3dtt og d33 N9153G 009de WOdd -
c 26 96, 9 ggg