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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:OUTGOING CORRESPONDENCE
MONTHYEARML20207G5411999-06-0808 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 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 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 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 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 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 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 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 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) 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 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 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 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 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 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) 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 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 ML20237C4801998-08-20020 August 1998 Informs That Staff Will Withhold from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended, Presentation Matl from 970212-14 ACRS Meeting Encl in W Ltr NSD-NRC-98-5744 Dtd 980803,until Policy Matter,Clarified ML20237D4391998-08-18018 August 1998 Confirms Phone Conversation Between NRC & W Re Submittal of Final Portions of Documentation Necessary to Complete Review & Issue Final SER & Final Design Approval for AP600 ML20236V6671998-07-30030 July 1998 Advises That Info Contained in WCAP-14601,rev 2,submitted in Westinghouse Ltr NSD-NRC-98-5712,dtd 980616 & Marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended ML20236V8621998-07-30030 July 1998 Informs That Proprietary Info Encl in Westinghouse Ltr NSD-NRC-98-5736,dtd 980713 Will Be Withheld from Public Disclosure Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended ML20236U7811998-07-29029 July 1998 Advises That WCAP-14270,rev 1, AP600 LP Integral Sys Test Facility Scaling Rept, Encl in Ltr NSD-NRC-98-5718,dtd 980619 & Marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA ML20236U7831998-07-29029 July 1998 Informs That Certain Info in AP600 Ssar,If Proposed for Change That Refs AP600 Std Design,Will Require Prior NRC Approval Before Proposed Change Can Be Implemented.Tier 2* Info for AP600 Design & Staff Decision Encl ML20236U8131998-07-29029 July 1998 Advises That WCAP-14471,rev 0, Steam Condensation Events at Osu AP600 Facility Submitted in Ltr NSD-NRC-96-4661,dtd 960306 & Marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA ML20236V0511998-07-29029 July 1998 Informs That AP600 Boron Dilution Transient Analysis Encl in Westinghouse Ltrs NSD-NRC-96-4792,dtd 960808 & NSD-NRC-98-5739,dtd 980720 & Marked as Proprietary Will Be Withheld from Public Disclosure Per 10CFR2.790 ML20236V0411998-07-28028 July 1998 Discusses Return of Proprietary Matl to Westinghouse Docketed Under AP600 Design Review.Proprietary Documents Listed in Encl 1 Removed from AP600 File & Returned for Disposition or Retention ML20236T3101998-07-22022 July 1998 Discusses W 941031 Submittal by Ltr (NTD-NRC-94-4330) of AP600 Notrump Core Makeup Tank Preliminary Validation Rept & Requests That Info Be Withheld from Public Disclosure. Determined Info Proprietary & Will Be Withheld from Public ML20236T4091998-07-22022 July 1998 Informs That Info Related to Wgothic lumped-parameter & Distributed Parameter Nodalization of AP600 & Wgothic Heat Sink & Flow Path Description Including Areas,Thickness & Evaluations Will Be Withheld,Per 10CFR2.790(b)(5) & 103(b) ML20236T1691998-07-22022 July 1998 Advises That Proprietary Matl Encl in NSD-NRC-96-4700,will Be Withheld from Public Disclosure,Per 10CFR2.790(b)5) & Section 103(b) of AEA of 1954,as Amended ML20236T1361998-07-22022 July 1998 Advises That Info Contained in TRs WCAP-12945-P-A & WCAP-14747,respectively Submitted in Ltr NTD-NRC-95-4406, Will Be Withheld from Public Disclosure Per 10CFR2.790(b)(5) & Section 103(b) of AEC of 1954,as Amended ML20236T0591998-07-22022 July 1998 Informs That Staff Plans to Return NSD-NRC-96-4762, NSD-NRC-96-4763,NSD-NRC-96-4790,... Transmittals to Westinghouse W/O Proprietary Determination,Due to Info Being Provided in Documents Submitted at Later Date ML20236S9841998-07-22022 July 1998 Informs That Staff Plans to Return NSD-NRC-94-4246, NSD-NRC-94-4327 & NSD-NRC-94-4318 Transmittals to Westinghouse W/O Proprietarty Determination,Due to Info Being Provided in Documents Submitted at Later Date ML20236S9621998-07-22022 July 1998 Advises That Info in NSD-NRC-97-5424 on AP600 Passive Containment Cooling Sys Will Be Withheld from Public Disclosure,Per 10CFR2.790 ML20236S9321998-07-22022 July 1998 Advises That Info in on AP600 Large Scale Test Facility Will Be Withheld from Public Disclosure,Per 10CFR2.790 ML20236S9131998-07-22022 July 1998 Informs That WCAP-14776 (Rev 2) Encl in Westinghouse Ltr NSD-NRC-97-5202,dtd 970620 Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20236S1601998-07-22022 July 1998 Informs That Encl Table,Associated W/Westinghouse AP600 Ltrs,Will Be Marked as Proprietary & Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20236S1511998-07-22022 July 1998 Informs That Matl Encl in NTD-NRC-94-4215 & NTD-NRC-95-4436, Marked as Proprietary,Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20236S1431998-07-22022 July 1998 Informs That Encl Table Associated W/Westinghouse AP600 Design Ltrs Will Be Marked as Proprietary & Will Be Withheld from Public Disclosure Pursuant 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20236S1321998-07-22022 July 1998 Informs That Matls Documented in Encl Table,Associated W/Westinghouse AP600 WCAPs Submitted in Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act of 1954,as Amended 1999-06-08
[Table view] |
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,%G t Mr. Nicholas J. Regulatory Liparulo,Analysis Manager? ..
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SUBJECT:
"OPEN ITEMS ASSOCIATED WITH THE AP600 SAFETY EVALUATION REPORTJ _ %i < i 3i "E\myijd,mfL -(SER)~ON THE AP600 CONTAINMENT DESIGN AND ACCIDENT ANALYSESsH. -r e-m -
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The Containment Systems and Sever Accident Branch of the U.S. Nuclear Regulatory : ,
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Commission (NRC) has provided an SER input to the Standardization Project Directorate on the ~ , , , ,
AP600 containment design features and accident analyses, SER Chapter 6.2. The input has ;1l lesues which have already been identified and captured by existing FSER open items. The staff t' tbolieves that labeling these issues as separate FSER open items would result in unnecessary ; ;
. iduplication of response. effort for Westinghouse.' However, a summary discussion of the staff's
, conoems with the AP600 containment analyses have been provided in the enclosure to this letter for Westinghouse's information to assist in its resolution of the open items in this area.-
if you have any questions regarding this matter, you may contact me at (301) 4151141. ,
Sincerely,
,. original signed by:
William C. Huffman, Froject Manager Standaroization Project Directorate ;
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Division of Reactor Program Management
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g Office of Nuclear Reactor Regulation e'
Docket No.52-003 -
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Mr. Nicholas J. Liparulo. - Docket No.52-003 Westinghouse Electric Corporation AP600 c . cc: Mr. B. A. McIntyre Mr. Russ Bell -
Advanced Plant Safety & Licensing Senior Project Manager, Programs -
, Westinghouse Electric Corporation Nuclear Energy Institute .
Energy Systems Business Unit 1776 i Street, NW '
P.O. Box 355 Suite 300
< Pittsburgh, PA 15230 Washington, DC 20006-3706 Ms. Cindy L Haag Ms. Lynn Connor Advanced Plant Safety & Licensing Doc-Search Associates.
Westinghouse Electric Corporation Post Office Box 34 -
Energy Systems Business Unit Cabin John, MD 20818
- Box 355 i Pittsburgh, PA 15230 Dr. Craig D. Sawyer, Manager Advanced Reactor Programs Mr. Stsrling Franks - GE Nuclear Energy >
U.S. Department of Energy 175 Curiner Avenue, MC-754 l NE-50 San Jose, CA 95125 19901 Germantown Road Germantown, MD 20874. Mr. Robert H. Buchholz GE Nuclear Energy Mr. Frank A. Ross 175 Curtner Avenue, MC-781 U.S. Department of Energy, NE 42 _ San Jose, CA 95125 Office of LWR Safety and Technology 19901 Germantown Road Barton Z. Cowan, Esq.
. Germantown, MD 20874 Eckert Seamans Cherin & Mellott 600 Grant Street 42nd Floor Mr. Charles Thompson, Nuclear Engineer Pittsburgh, PA 15219 AP600 Certification NE 50 ' Mr. Ed Rodwell, Manager 19901 Germantown Road PWR Design Certification Germantown, MD 20874 Electric Power Research Institute M12 Hillview Avenue Palo Alto, CA 94303 4
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SER CHAPTER 6.2 OPEN ITEMS ASSOCIATED WITH THE AP600 .
CONTAINMENT DESIGN AND ACCIDENT ANALYSES ,
I -- Open items related to the Development and use of the limited PCS water model to ,
pvaluate the performance of the PCS
< The AP600 WGOTHIC evaluation model, as used to support design certification,' does not have the capability to correctly model the variations in expected wetted surface coverage area as the PCS water flow rate is reduced over time. The treatment of the wetted surface area itself does not impact the peak pressure calculation for LOCA analyses. To account .
E for this modeling deficiency, Westinghouse has developed a limited PCS flow model to produce an input boundary condition, or forcing function, for WGOTHIC to describe the expected PCS behavior. However, the application of the limited PCS flow model, which artificially reduced the actual flow rate and therefore enhances evaporating cooling, may be misleading. In response to this concom, as identified in staff RAI 480.873, Westinghouse 4-ignored the specific issue. Further clarifications on the limited PCS flow model have been
, requested.
Issues concoming the limited PCS flow model are outlined in Table A below.
Table A - Evaluation of Westinghouse POS flow and heat transfer models Phenomena Effect Comment Coverage area Westinghouse assumes no These are small conservatisms.
- Height evaporation above second weir. Subcooling is usually eliminated *
- Stripe width Extent of subcooled region may be before second weir.
' ~
overpredicted.
90% flow from cold WDT tests at Constant 90% " wet" area throughout 832.8 liters / min (220 gpm), ,
conservative for 1,665.6 liters / min
~
event.
(440 gpm) (first 3 hrs). After 3 hrs, g
effect is not significant if above deck region is "well mixed".
L J
l' Heat convected Latent heat of PCS runoff is This is a small conservatism for
- bywater film neglected. peak pressure period. May be significant for the 1200 second to
! 30 hour3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> period when the runoff fraction becomes larger.
i i Resistance of- PCS film thickness may be This non-conservatism may be extemal water - significantly underpredicted, significant after peak pressure film ~ period ( >1200 sec.) when the i Film may reach saturation runoff
l temperature eartier.
Buoyancy driven Artificialwater coverage profile Skew expected only for post 3 air flow skews evaporation heat flux toward hour period. Effect is small, higher elevations conservative reduction in buoyant -
driving force.
Enclosure a- . .- - . ~ . .-. - - -- . - . -.
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F 2-Phenomena Effect Comment Convection and Artificial water coverage profile Skew expected only for post 3 -
radiatiu heat - lowers dry clime convection and hour period. Errors may be self transfer from dry radiation from upper elevations; compensating.
clime increases convection and radiation i from lower elevations.
4 Westinghouse failed to identify, or at least account for, the crucial need to consider two-dimensional (2-D) heat transfer for the long-term containment pressure response (after three
' hours when the PCS flow rate is first cut back to about one-half its initial value) in the
. selection of their analysis methodology (GOTHIC) and in their development of a model for
, the PCS 00fGOTHIC). With the coverage area less than the initial assumed 90 percent,
, heat transfer from the hot, dry regions of the shell into the cooler, wet regions of the shell would occur. To account for this deficiency, Westinghouse performs an ancillary calculation 4
to credit more PCS water in the evaporation process, effectively generating a correction factor, and applies it to the limited PCS flow model. This change to the limited PCS flow model was first presented to the staff in May 1997, i
ll Open items related to the use of lumo-carameter model by Westinohouse to evaluate the
- AP600 containment response to desian basis accidents (LOCAs and MSLBst These open
! item relates to the "well mixed" assumotion used by Westinohouse to model the above dagh reoions of the AP600 i
j Westinghouse uses the lumped-parameter modeling feature of the WGOTHIC computer program. There tre known limitations associated with this type of model. First, it must be demonstrated that the containment is "well mixed." This must be demonstrated for both LOCA and MSLB events. The lurr. ped-parameter model does not account for momentum
- transfer in regions and solves only a simplified momentum equation for the network of L junctions. The calculated non-condensable distribution within a horizontal plain is therefore uniform, or homogenized, if the "well mixed" assumption is proven then it would be reasonable to use the calculated non-condensable distribution to evaluate the mass and heat transfer on the inside condensing surface of the containment shell. If the containment i
cannot be shown to be "well mixed," then a penalty must be applied to account for the
- expected distiibution of non-condensables. Westinghouse has not provided sufficient d
information (experimental or analytical) for the staff to conclude that the containment is "well mixed" or tJ assess the possible magnitude or impact of attemative distributions of non-condensah..s.
issues related to the "well mixed" assumption are outlined in Table B.
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Table 8 - WOOTHic modela which tend to homogentre calculations Assumption Effect on "well mixed" or Tendency toward circulapn & stratification homogenization Lumood Parameter Overpredicts convective Artificially increases EM model has network of LP flows. Circulation artifcJally homogenization.
nodes; high.
few nodes below dock (1 or 2 layers). Underpredicts stratifcation.
- many stccked nodes above deck.
Heat Sink Utilization Reduces heat transfer. Artificially increases
- Elimination of horizontal Minimites energy storage in homogenization below deck.
surfaces and operating deck. containment structures and maximizes temperatures in Unknown effect on
- No heat structures in dead- pools. homogenization above deck. ,
ended compartments after {
blowdown (i.e., > 30 secs). Eliminates important heat !
sinks for circulation.
Reduces stratification.
- Maximizes atmospheric ,
energy content / steam i concentration for shell condensation. I Condensate Modelina - Hot condensate is Overpredicts
- 100% Stripping by polar crane instantaneously dumped to homogenization.
rail and intemal stiffeners. the sump, enhancing circulation and minimizing
- Chun and Seban model used stratification.
to predict effective thickness.
Distorts droplet / atmosphere irdaraction.
PCS Flow Modelina Artificially heats up dome Overpredicts
- Delayed initiation (to 337 shell and intemal homogenization by secs), atmosphere. Minimizes minimizing cooldown/ layering stratification at start of PCS of dense air on operating No evaporation above second flow. deck.
weir.
Provides ample time to mix
- Chun and Seban model used with air in dome.
to predict effective thickness.
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4
- Assumption Effect on "well mixed" or Tendency toward l circulation & stratification homogenization i
Modeling of openings between Supports closed natural increases homogenization of above and below deck circulation loop (particularly dome and below d%* ,
compartments. These paths after start of 4th stage regions affectec Dy loop.
are essential to provide - ADS).
4 circulation from above to below l deck. Entrains cold fluid, i
Repositioning of MSLB break to Enhances circulation and overpredicts operating dock level, entrainment in the above homogenization.
! dock regions.
Provides additional access to below deck region. .
1 Removes actual asymmetry.
. Many of the arguments to support the "well mixed
- assumption, as presented by Westinghouse in Section g of WCAP-14407, *WGOTHIC Application to AP600," Revision 1, July 1997, are based on convectior, Jominated entrainment flows in combustible fires. This assessment is not directly applicable to the condensation dominated entrainment expected in the AP600 as documented in the PIRT. Other arguments are based on flow patterns in enclosures which are not characteristic of the expected conditions in the AP600.
4 The staff is unable to determine if a sufficient design margin exists in the AP600 containment 3
to conclude that the requirements of 10 CFR 50, Appendix A, General Design Criteria (GDC) 16,38 and 50 are met. The analysis methodology 00(GOTHIC) used by Westinghouse in support of design certification does not contain appropriate features and modeling
. capabilities to evaluate the "best estimate" performance caeracteristics of the passive containment cooling system (PCS). This approach would require the uncertainties in the 4
methodology be identified, assessed and property treated, instead, Westinghouse has
, _ elected to use a conservative, " bounding" evaluation model (EM) approach. - However, the AP600 WGOTHIC EM may not adequately assess, and may not properly treat, known limitations associated with the use of the lumped-parameter approach and the PCS flow and heat transfer models.
The staff will consider a smaller margin, less then 10%, for the AP600 if it is determined that the licensing analyses that support design certification are conservative and that an appropriate initial test program, in combination with satisfactory initial test and acceptance criteria (certified design material), is developed.
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.s.
111 Open item related to the location of the MSLB used for licensina analysis The second limitation of the lumped-parameter model concems break location. Because momentum is not transferred between regioes, an elevated break, as compared to a break at a lower elevation, will result in a higher calculated containment pressure because steam is not readily circulated to regions below the assumed break location and some of the condensing surface is lost in the calculation. This is a well-known limitation of the lumped-parameter network chosen by Westinghouse to perform the licensing analyses.
Westinghouse models the MSLB at the operating deck level, not at its actual elevated location. This is unacceptable. Arguments concoming steam concentrations as observed in the LST to justify the selected location are inadequate. The LST configuration is too different, particulady in the below deck region, and because of the continued outflow through the below deck region in the LST (to provide a means to measure the condensate inside the facility) it is difficult to infer or speculate on behavior in the AP600. The MSLB analysis needs to be performed with the break at its reallocation. The limitations of the selected methodology must be accounted for in the design basis analyses.
IV Open items related to the cuality of documentation provided by Westinahouse to support desian certification includina corrections to supportina technical reports and expected revisions to the SSAR.
The documentation provided to the staff to support the design certification of the AP600 PCS is poorly organized and contains errors, omissions and inconsistencies, in addition, the objectives of the analysis methodology have changed with time, it is difficult to determine what documents and portions of documents represent the current Westinghouse Evaluation Methodology. This has resulted in the expenditure of a significant amount of steff resources on the review of material which has been subsequent ly withdrawn, or significantly revised as a result of the staff's review.
Westinghouse has informed that staff, in letter NSD-NRC-97-5338,"AP600 PCS PIRT/ Scaling Closure Meeting Summary," from R. A. McIntyre, Westinghouse, to T. R. Quay, NRC, dated September 22,1997, that staff ider,tu%t errors in WCAP-14326, Revision 1, WCAP-14812, Revision 2, and WCAP 14845, Rehon 1, will be corrected and revisions submitted, in addition, there is an error in the pressure rate equation developed in the scaling study (WCAP-14845) that must be corrected. The normalization, dimensionless substitutions and the n groups need to De reevaluated after the pressure rate equation is corrected and the PlRT confirmed, or appropriately modified and, if necessary, additional sensitivity studies performed to support the PIRT and the evaluation model, The SSAR (based on Revision 18) needs to be updated to reflect current commitments related to the initial test program (ITP), the initial test and acceptance criteria (ITAAC) or AP600 certified design material, and the technical specifications. SSAR references needs to be revised to properly identify the WGOTHIC computer program and the computer programs used to determine the mass and energy releases for the design basis accidents.
The PIRT, scaling and application reports need to provide a clear and consistent description of the AP600 PCS evaluation model to document the licensing analyses that support design
l
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. 6- >
certification. The SSAR needs to be updated to determine if the ITP, ITAAC and technical -
specifications are consistent with, and support, those features that are necessary to confirm the licensing analyses that support design certification.
Westinghouse needs to develop an ITAAC requirement based on acceptable indu'stry standards for the liner and concrete fabrication process and for the concrete mixture to assure that the 5 mil air gap is appropriate and conservative for the licensing analyses.
Westinghouse is also considering other means to allow for a larger air gap in the licensing aniyses, an upper bound value, if the ITAAC becomes over burdening on a licensee.
V. Open items related to the containment Testinn prooram To satisfy the requirements of 10 CFR 52.47(b)(2)(1)(A), Westinghouse has developed test programs to investigste the passive containment safety systems. These programs include both component and phenomenological (separate-effects) tests and integral-systems tests.
The Large-Scale Test (LST) is the only integral test for the AP600 PCS. The cold, water distribution test (WDT) is the only full scale representation of the PCS flow characteristics.
Additional separate-effects tests have been performed to extend the range existing mass and heat transfer correlations in the AP600 analysis codes, to comply with the last of the three requirements above.
The shortcomings of the LST include the following major issues:
e- The tests were primarily focused on steady state conditions to assess the mass and heat transfer correlations to be used in WGOTHIC Very limited transient information is available. The LST is usefulin evaluating the applicability of the mass and heat transfer correlations used in WGOTHIC, WGOTHIC analyses of LST tests are usefulin verifying the model changes made to GOTHIC by Westinghouse by demonstrating that these changes have been properly coded.
- The intemal configuration (below deck region and heat sinks) and PCS water delivery systems (J-tubes and unsteady flow rat _es) are significantly different from the AP600. Therefore interpretation of the test results to address expected behavior in the AP600 is uncertain and reliance on LST data alone is generally insufficient to reach closure.
e- - Limited data available to assess mixing issues and non-condensable distributions.-
7 Westinghouse contends that the LST was always "well mixed," but has not been
- able to denionstrate that the AP600 is also "well mixed."
The staff in unable to determine if the testing program is sufficient to understand the i containment response to the PCS or to address the modeling deficiencMs in the WGOTHIC computer program and its application to the AP600. Understanding the distortions in the LST, combined with proper accounting of important phenomena, as identified through an appropriate scaling analysis, in the development of the AP600 evaluation modelis necessary
- to conclude that the evaluation model is acceptable.
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