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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
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Jocts % (k 4 E14 p- +1 UNITED STATES s*
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20566-0001 l
. \ . . . . . p! March 10, 1997 Mr. Nicholas J. Liparulo, Marager 1
Nuclear Safety and Regulatory Analysis Nuclear and Advanced Technology Division Westinghouse Electric Corporation P.O. Box 355 i
- Pittsburgh, PA 15230
SUBJECT:
FOLLOWON QUESTIONS REGARDING THE AP600 DIFFUSION FLAME REPORT
Dear Mr. Liparulo:
j As a result of its review of the June 1992 application for design certifica-tion of tne APo00, the staff has determined that it needs additional informa-tion. Specifically, a set of questions were faxed to Westinghouse concerning the AP600 diffusion flame report. These questions are listed in Enclosure 1.
A telcon was held on February 7,1997, between the staff and Westinghouse to discuss the questions in Enclosure 1. As a result of this telcon, the ques-3 tions were focused and it was decided to turn them into formal requests for additional information (RAI). The questions in Enclosure 2 have been assigned i
unique nunaers and have been slightly modified. Therefore, it is requested that Westinghouse formally respond to the questions in Enclosure 2. Please )
- note that question 8 of Enclosure I was not turned into an RAI because during the telcun on February 7, 1997, Westinghouse referred the staff to Figure A-13
, of the diffusion flame report which addressed the staff's concern.
You have requested that portions of the information submitted in the l
June 1992, application for design certification be exempt from mandatory public disclosure. While the staff has not completed its review of your request in accordance with the requirements or 10 CFR 2.790, that portion of the submitted information i.s being withheld from public disclosure pending the staff's final determination. The staff concludes that these followor. ques-I tions do not contain those portions of the information for which ev.nption is 2
sought. However, the staff will withhold this letter from public disclosure for 30 calendar days from the date of this letter to allow Westinghouse the
- cpportunity to verify the staff's conclusions. If, after that time, you do
- not request that all or portions of the information in the enclosures be withheld from public disclosure in accordance with 10 CFR 2.790, this letter j will be placed in the NRC Public Document Room.
l r
NBC RE CENTER COPY 0400M
- 1 gob 3 9704240136 970316 PDR ADOCK052Og3
a Mr. Nicholas J. Liparulo March 10, 1997 If you have any questions regarding this matter, you may contact me at (301) 415-1132.
Sincerely, original signed by:
Joseph M. Sebrosky, Project Manager
. Standardization Project Directorate Division of Reactor Program Management s- Office of Nuclear Reactor Regulation Docket No.52-003
Enclosure:
As stated cc w/ enclosure:
} See next page DISTRIBUTION: Enclosure to be held for 30 days
- Docket File .PDST R/F TTMartin 7 *PUBLIC DChatthews TQuay g TKenyon DJackson BHuffman e JSebrosky WDean,,0-17 G21- JMoore, 0-15 B18 ACRS (11) <AMalliakos, T-10 K8 MSnodderly, 0-E H7 JKudrick, 0,8 H7 CBerlinger,,0-8 H7
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ut ettechment#pisew,e i"E* = Copy with ettschmentlencloswo *N* = No copy 0FFICE PM:PDST:DRPM BC:SCSB$fA1 D:PQSfhDRPM l !
NAME JSebrosky:sg JKudrick i TQuayU i DATE 7-/ 7//97 "f/(D/97 /y /97 0FFICIAL RECORD COPY l
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a Mr. Nicholas J. Liparulo Docket No.52-003 Westinghouse Electric Corporation AP600 i
l cc: Mr. B. A. McIntyre Ms. Cindy L. Haag Advanced Plant Safety & Licensing Advanced Plant Safety & Licensing I Westinghouse Electric Corporation Westinghouse Electric Corporation Energy Systems Business Unit Energy Systems Business Unit P.O. Box 355 Box 355 ,
Pittsburgh, PA 15230 Pittsburgh, PA 15230 )
Mr. M. D. Beaumont Mr. S. M. Modro Nuclear and Advanced Technology Division Nuclear Systems Analysis Technologies i Westinghouse Electric Corporation Lockheed Idaho Technologies Company l i
One Montrose Metro Post Office Box 1625 l 11921 Rockville Pike Idaho Falls, ID 83415 !
4 Sufte 252 Rockville, MD 20852 l
Enclosure to be distributed to the following addressees after the result of the '
- proprietary evaluation is received from Westinghouse
Mr. Ronald Simard, Director Ms. Lynn Connor
- Advanced Reactor Programs DOC-Search Associates Nuclear Energy Institute Post Office Box 34 1776 Eye Street, N.W.
Cabin John, MD 20818 Suite 300 Washington, DC 20006-3706 Mr. Robert H. Buchholz GE Nuclear Energy Mr. James E. Quinn, Projects Manager 175 Curtner Avenue, MC-781 LMR and SBWR Programs San Jose, CA 95125 GE Nuclear Energy l 175 Curtner Avenue, M/C 165 Mr. Sterling Franks !
San Jose, CA 95125 U.S. Department of Energy i NE-50 !
Barton Z. Cowan, Esq. 19901 Germantown Road i Eckert Seamans Cherin & Mellott Germantown, MD 20874 600 Grant Street 42nd Floor Pittsburgh, PA 15219 Mr. Charles Thompson, Nuclear Engineer AP600 Certification Mr. Frank A. Ross NE-50 !
U.S. Department of Energy, NE-42 19901 Germantown Road 1 Office of LWR Safety and Technology Germantown, MD 20874 19901 Germantown Road Germantown, MD 20874 I
Mr. Ed Rodwell, Manager PWR Design Certification Electric Power Research Institute 3412 Hillview Avenue Palo Alto, CA 94303 l
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} The following comments and questions are in regards to the Westinghouse Electric Corporation report " Assessment of f he Potential Impact of Diffusion i Flames on the AP600 Containment Wall and Penetrations, AP600 Doc # PRA GSR 004, Nov. 1996".
5
- 1. The report uses correlations to determine the flame characteristics.
Please provide justification for the use of these correlations and address the following points:
a a. The report uses correlations applicable for an isolated plume. The hydrogen burn in the AP600 is not a single unconfined fire. The analysis predicts a linear series of as, proximately 16 flames that are closely spaced (spacing on the order of the flame diameter). Thus, the neighboring flames will compete for the same air, and the flow pattern will be altered. Potentially this altered flow pattern will cause the flames to be taller and hotter.
- b. Each flame is approximately 1 meter from a solid containment wall.
Thus, the flames are not in an unconfined space. Little air is available to enter the flame between the plume and the wall. The incoming momentum of the air entering from the direction opposite to the wall will cause the plume to become attached to the wall. This mechanism also makes the flame taller and hotter. Does the analysis assumes the flame will attach to the wall?
- c. The correlations are only for vertical exit planes, and the current AP6001RWST vent geometry includes a horizontal exit.
- 2. It appears that the report assumes that the hydrogen fuel is distributed between three sets of vents (16 IRWST sparger side vents, 5 IRWST PRHR Hx side vents and 5 vents of 24 inch pipe). The model for the flow resis- !
tances that effect the distribution for the hydrogen is not clearly described. Also, the model implicitly assumes that the flow is equally distributed between each of the individual vents within each set. The !
report has not demonstrated that this partitioning is accurate or I conservative.
1
- 3. The report does not give much detail on the heat transfer calculations performed. Only the final results are provided. However, the report indicates that the heat flux is entirely radiative from the flame to the containment wall. Independent calculations indicate that the tempera-tures obtained are reasonable for a radiative source, however, the itams listed above may invalidate the radiative assumption. The flame may be hotter than assumed, and the flame may become attached to the wall yielding a significant convective heat flux.
- 4. There is little design detail provided in the report. The most important items missing are:
- a. Distance between the IWRST sparger side vents.
Enclosure 1
j b. The report gives no information on the availability of air behind IWRST vents. Please clarify the geometry of the open volume behind the vents and below the operating deck (see Figure 11 of the report).
How much air is available to feed the diffusion flame between the IWRST vents and the containment wall?
l c. The detailed design of the various vents to the IWRST. The report does not give design details (existence of elbows or flappers, dimensions) and is not clear if these vents will release liquid or gas from the IRWST head space. The information must be provided for:
- 1. IWRST sparger side normal vents,
- 2. IWRST sparger side 24 inch pipe vents,
- 3. IWRST PRHR Hx side vents,
- 4. Refueling canal vents and
- 5. Reverse flow vents
- d. The pressure required to open the vents for full and partial flow of the vents.
- e. The diameter of the containment cylinder, the baffle, and the ID of the concrete shield building. The following three dimensions were obtained from older Westinghouse AP600 reports: 130 ft, 132 ft, 139 ft. Are these dimensions correct?
- f. The minimum head space (distance from the IWRST ceiling to the liquid surface) in the IWRST:
- 1. without liquid swell due to sparger operation and l
- 2. with liquid swell due to sparger operation
- 5. Numerous errors exist in the text.
- a. The report estimates that the maximum temperature of the diffusion flame will be approximately 900 K above ambient. This is equivalent to 1620 F above ambient (not 1160 F as reported on page 25).
- b. Equation 6.1 has two errors (910 should be 9.10 and tau _zero should be tau _ infinity).
- 6. The typical calculations provided seem to use 2 Kg/s total. flow of a fuel mixture of 5 percent hydrogen and 95 percent steam. However, the data plots show that the maximum hydrogen concentration can approach 85 percent. What is the justification for the assumption used?
I
- 7. Note #3 on Table 2 s'.ates that two of the vents "are being reserved for venting from the containment back into the IRWST te prevent over pressur-ization of the IRWST during a LOCA or SLB and as a result will not be
- available for venting out of the IRWST." It is not clear that allowing i venting into the IRWST will prevent over pressurization of the IRWST.
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' l i- 8. Page 14 states, "The existence of the flappers on each of the IRWST vent i paths to prevent mixing with the air in the rest of the containment i
' regions also impacts the diffusion flame assessment." However, the i
report does not specify what is the impact in the assessnent. Moreover, it is unclear if the mixing can be prevented since the flappers in two of the vents have reverse orientation from the rest. How this assumption was used in the analysis? '
I 9. The thermal limits on the containment vessel are calculated based on a
! reduction in the modules of elasticity of the structural steel. The modules of elasticity is a slope, and not a yield stress (or strength as
! implied by the caption given for Figure 13). To equate changes in the 4
modules of elasticity to strength limits one must assume an elastic 1 process up to failure and also assume that the strain to failure is equal j
at all temperatures. It would be better to use the reduction in the actual yield stress due to temperature increases. This is somewhat difficult due to the creep behavior that occurs at high temperatures, but
} classic handbooks (e.g. Engineer's Guide to High Temperature Materials, F.J. Clauss, Addison Wesley,1969) give plots of " Stress to cause rupture i in 10,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />," which would be a conservative measure to use in j developing strength limits. How were these details were included in the Westinghouse analysis?
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FOLLOW 0N QUESTIONS CONCERNING THE AP600 DIFFUSION FLAME REPORT The following questions are in regards to the Nestinghouse Electric Corpora- l tion report " Assessment of the Potential Impact of Diffusion Flames on the AP600 Containment Wall and Penetrations, AP600 Doc # PRA GSR 004, Nov. 1996".
480.947 The report uses correlations to determine the flame chara~cteristics l which may not be applicable to the AP600 application. For example, l i
the correlation for flame temperature is derived from calculations of a round heater on a horizontal floor, and thus contains no combustion physics (heats of formation, oxygen diffusion, etc.). Therefore, use of this correlation, in particular, must be justified when it is applied outside of its accepted range (vertical low velocity exits of hydrocarbon fuels in an unconfined space). Please provide justifica-tion for the use of flame correlations and address the following points: '
- a. The report uses correlations applicable for an isolated plume.
The hydrogen burn in the AP600 is not a single unconfined fire. i The analysis predicts a linear series of approximately 16 flames that are closely spaced (spacing on the order of the flame diametor). Thus, the neighboring flames will compete for the same air, and the flow pattern will be altered. Potentially, j this altered flow pattern will cause the flames to be taller and i hotter.
- b. Each flame is approximately 1 meter from a solid containment wall. Thus, the flames are not in an unconfined space. Little air is available to enter the flame between the plume and the wall. The incoming momentum of the air entering from the direc-tion opposite to the wall will cause the plume to become attached to the wall. This mechanism also makes the flame taller and hotter. Does the analysis assume the flame will attach to the wall?
- c. The correlations are only for vertical exit planes, and the current AP600 IRWST vent geometry includes a horizontal exit. l 480.948 It appears that the report assumes that the hydrogen fuel is distrib-uted between three sets of vents (16 IRWST sparger side vents, 5 IRWST PRHR Hx side vents, and 5 vents of 24 inch pipe). The model for the flow resistances that effect the distribution for the hydro-gen is not clearly described. Also, the model implicitly assumes that the flow is equally distributed between each of the individual vents within each set. Provide further justification for the flow resistances and the assumption that the flow is equally distributed.
l l Enclosure 2 l __ _ ---
i 480.949 Further detail on the heat transfer calculations performed is needed !
for the staff to complete its review. Only the final results are I provided. The report (and a supplementary fax, dated February 6, 1997) indicates that the heat flux is both convective and radiative ,
from the flame to the containment wall. Independent calculations l indicate that the temperatures obtained are reasonable for a radia- i tive source only given the assumed flame temperatures. However, the items listed above laay NMidate the flame temperature used, and a convective flux for an attached flame suould yield a significant !
convective heat flux. Details and justifications for the heat trans-fer parameters (view factors, convection coefficient, etc.) should be provided.
480.950 Further design detail is needed. The following items are needed in order for the staff to complete its review of the report:
- a. Distance between the IWRST sparger side vents.
l
- b. The report gives no information on the availability of air behind j IWRST vents. Please clarify the geometry of the open volume i behin *re vents and below the operating deck (see Figure 11 of the report). How much air is available to feed the diffusion !
flame between the IWRST vents and the containment wall?
- c. The detailed design of the various vents to the IWRST. The report does not give design details (existence of elbows or flappers, dimensions) and is not clear if these vents will release liquid or gas from the IRWST head space. The information must be provided for:
- 1. IWRST sparger side normal vents,
- 2. IWRST sparger side 24 inch pipe vents,
- 3. IWRST PRHR Hx side vents,
- 4. Refueling canal vents and
- 5. Reverse flow vents
- d. The pressure required to open the vents for full and partial flow of the vents.
- e. The diameter of the containment cylinder, the baffle, and the ID of the concrete shield building. The following three dimensions were obtained from older Westinghouse AP600 reports: 130 ft.,
132 ft., and 139 ft respectively. Are these dimensions correct?
- f. The minimum head space (distance from the IWRST ceiling to the liquid surface) in the IWRST:
- 1. without liquid swell due to sparger operation and 2
- 2. with liquid swell due to sparger operation l
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- '480.951 The following discrepancies were identified in the text:
l a. The report estimates that the maximum temperature of the diffu-sion flame will be approximately 900 'K above ambient. This is ,
i equivalent to 1620 'F above ambient (not 1160 'F as reported on j page 25).
i i i
! b. Equation 6.1 has two errors (910 should be 9.10 and tau _zero l l should be tau _ infinity).
1 i
Please correct these values, or justify them.
- 480.952 Tne typical calculations provided seem to use 2 Kg/s total flow of a j fuel mixture of 5 percent hydrogen and 95 percent steam. However,
, the data plots show that the maximum hydrogen concentration can j
approach 85 percent. What is the justification for the assumption
- used?
480.953 Note #3 on Table 2 states that two of the vents "are being reserved 1 i
for venting from the containment back into the liiWST to prevent over-
. pressurization of the IRWST during a LOCA or SLB and as a result will l not be available for venting out of the IRWST." It is not clear that allowing venting into the IRWST will prevent over-pressurization of l the IRWST. Perhaps the authors meant to prevent under-pressuriza-l tion. Please clarify.
480.954 The thermal limits on the containment vessel are calculated based on i a reduction in the modules of elasticity of the structural steel.
- The modules of elasticity is a slope, and not a yield stress (or i strength as implied by the ca.ption given for Figure 13). To equate !
- changes in the modules of elasticity to strength limits one'must assume an elastic process up to failure and also assume that the strain to failure is equal at all temperatures. Why wasn't the !
reduction in the actual yield stress due to temperature increases used? Classic handbooks (e.g. Engineer's Guide to High Tempera-ture... Wesley,1969) give plots .of " Stress to cause rupture... in 10,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />," which may be more appropriate in developing strength limits.
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