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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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. December 15, 1997 I
Mr. Nicholas J. Liparulo, Manager Nuclear Safety and Regulatory Activities Nuclear and Advanced Technology Division Westinghouse Electric Corporation P.O. Box 355-Pittsburgh, PA 15230
Dear Mr. Liparulo:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION RN.ATED TO OPEN ITEMS ON THE AP600 As a result of its review of the June 1992 application for design certification of the AP600, the staff has prepared the final safety evaluation report (FSER) on Section 13.6 of the AP600 Standard Safety Analysis Report (SSAR), Revision 17, the AP600 Security Design Report, Revision 4, and the AP600 Security Design Vulnerability Analysis Report, Revision 1. The FSER identifies 22 open items needing resolution by Westinghouse before the staff can complete its review of this SSAR section. The open items are identified in the enclosure with the tracking numbers associated with them.
You have requested that portions of the information submitted in the June 1992 apr'ication for design certification be exempt from mandatory public disciocure. While the staff has not completed its review of your request in accordance with the requiremants of 10 CFR 2.790, that port'on of the submitted information is being withheld from public disclosure pending the staffs final detem11 nation. The staff concludes that the enclosure does not contain those portions of the information for which exemption is 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 opportunity to verify the staffs conclusions, if, after that time, you do not request that all or portions of the information in the enclosures be withheld from public disclohre in accordance with 10 CFR 2.790, this letter will be placed in the NRC's Public Document Room. T If you have any questions regarding this matter, you can contact me at (301) 415-1120.
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Sincerely, original signed by: i Thomas J. Kenyon, Project Manager J Standardization Project Directorate Division of Reacto: Program Management Office of Nuclear Reactor Regulation Docket No. 52 003
Enclosure:
As stated s
cc w/ encl: See next page 50 M R ET.d CDPV DISTRIBUTION:
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DOCUM'NT NAME: A:SFE-GRD.RAI To rcceive a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure "E" = Copy with attachment /enclopure "N" = No cyo OFFICE PM:PQW)ORPM D:PDST:pBRM -l l l TJKenyS:sg TRQuayL\Mi NAME DATE 12/n /97' 1216/97 \ P 9002030117 971215 OFFICIAL RECORD COPY PDR ADOCK 05200003 A .
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' DISTkfBUTION: Letter to Mr. Nicholas J. Lloarulo. Dated: December 15, 1997
, . Docket File
- Enclosure to be held for 30 days
- PUBLIC PDST R/F TQuay TKenyon WHuffman JSebrosky DScaletti
- JNWilson ACRS (ii)
WDean,0 5 E23 JMoore,015 B18 MPSelmen,015 B18 RAlbert,0-11 E22 1
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- Mr. Nicholas J. 'Jparuto Docket No.52-003 Westinghouse Electric Corporation AP600 cc: Mr. B. A. McIntyre Ms. Cindy L. Haag Advanced Plant Safety & Licensing Advanced Plant Safety & Licensing Westinghouse Electric Corporation Westinghouse Electric Corporation Energy Systems Business Unit Energy Systems Business Unit 1 P.O. Box 355 Box 355 Pittsburgh, PA 15230 Pittsburgh, PA 15230
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Enclosure to be distr!buted to the following addressees after the result of the propiietary evaluation is .
received from Westinghouse g
Mr. Russ Bell Ms. Lynn Connor x
} Senior Project Manage., Programs DOC-Search Associates Nuclear Energy Institute Post Office Box 34 1776 i Street, NW Cabin John, MD 20818 Suite 300 Washington, DC 20006 3706 Mr. Robert H. Buchholz GE Nuclear D:ergy Dr. Craig D. Sawyer, Manager 175 Curtner Avenue, MC-781 Advanced Reactor Programs San Jose, CA 95125
[ GE Nuclear Energy L 175 Curtner Avenue, MC 754 Mr. Sterling Franks San Jose, LA 95125 U.S. Department of Energy NE-50 Barton Z. Cowan, Esq. 19901 Germantown Road Eckert S?amans Cherin & Mellott Germantown, MD 20874 600 Grant Street 42nd Floor Pittsburgh, PA 15219 Mr. Charles Thompson, Nuclear Engineer AP600 Certification M: Frsrik A. Ross NE 50 U.S. Department of Energy, NE-42 19901 Germantown Road Office of LWR Safety and Technology Girmantown, MD 20874 x 19901 Germantown Road
- Germantown, MD 20874 Mr. Robert Ma!ers, P.E
- Pennsylva7ia Department of Mr. Ed Rodwell, Manager Environmental Protection PWR Design Certificat;on Bun au of Radiation Protection Electric Power Research Institute Rah Carson State Office Building
,, 3412 Hillview Avertue P.O. Box G469 Palo Alto, CA 94303 Harrisburg, PA 17105-8469 E-
4 OPEN ITEMS ON SSAR SECTION 13.6 920.6F Section 13.6 of the SSAR is titled " industrial Security." Industrial Security is a misnomer that does not accurately denote the level of protection required at a nuclear facility. The title " Nuclear Security" is preferred and has evolved as the industry standard. The staff recommends that Section 13.6 be revised ,
accordingly.
920.7F in Section 1.0, " Introduction," of the Secarity Design Report (SDR), second paragraph, a range of wall thickness is describ-d. The lower range is consistent with specificai!ons listed under security hardened walls, but the higher range exceeds it. It is not clear to the staff if any calculations were based on the higher range. If the higher range were needed to achieve the desired blast results, then Westingt.ouse needs to revise the AP600 minimum standard for hardened walls.
Address this concem.
920.8F in Section 1.2, " Security Portal," of the SDR, the full spectrum of alarms for doors,-
hatches, and tumstiles is act clear to the staff. The SDR reflects one type .of .
alarm, but is silent on others. Revise the SDR to reflect all alarm types.
- - In addition, in Section 13.6.7.2 of the SSAR, Westinghouse states that an intrusion detection system is u*ilized to notify the security organization of any unauthorized attempt to gain access into the protected area. Doors entering a protected tri.a are equipped with an alarm to detect tampering and unauthorized access into the protected area. It is not clear that this statement demonstrates that the requirements of 10 CFR 73.55(e)(2) and (3) are satisfied by the design.
Address this issue in both the SSAR and the 80R.
t 920.9F .in Section 4.2, " Controlled Access Areas," of the SDR, the title " Controlled Access Areas" contradicts the text and is not consistent with the definition specified in 10 CFR 73.2. Because contro',, access areas and vital areas are regulated differently, revise the title of ti = section for consistency.
920.10F in maction 4.3," Protected Area Enclosures," of the SDR, the phrase "provided with CCTV capability" is misleading. It is not clear to the staff if it means that CCTV shall be installed or that the capability to install CCTV will exist. Revise this section and other sect:ons with the referenced phrase to reflect that CCTV shall be installed.
920.11F in Section 4.3.1, " Primary Access Point," of the SDR, the phrasa "can be monitored" relative to CCTV is misleading. It is not clear to the staff t'it means that CCTV shall be monitored by the secunty organization or that they merely may be monitored. Revise this section to reflect that CCTV shall be monitored as appropriate.
920.12F Section 4.3.3," Containment Access," of the SDR is misiending. It reads as though scarches and positive identification can be performed by a member of Enclosure l
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2-the security organization or by control equipment independent of security personnel. Revise this section to reflect a security presence, even if access control equipment is usod.
920.13F in Section 4.4, "Alarrs Stations," of the SDR, the UL-752 rating (High Power Rifle Rating) needs to include a level 4 round (220 grein soft point with a muzzle velocity of 2,410 feet per second and a muzzle energy of 2,830 foot pounds)in the bullet-resisting criteria. Revise this section and any other section pertaining to bullet-resisting criteria to refioct a level 4 round.
920.14F in Section 4.5.2," Protected Area and Protected Area Enclosure Barriers," of the SDR, the use oi"typictt!!y" to describe a minimum standaid is unacceptable.
Replace " typically"in this section and all other sections whers it is used with r-ore appropriate language.
020.15F In Section 4.5.3, " Vital Area and PA/VA Barriers," of the SDR and Section 13.6.5.2 of the SSAR, the staff takes exception to the definition of "amsible" and requires expansion of the definition of'unmonitored." The issue conceming the definition of accessible was raised in writing to Westinghouse and also discussed with them during a meeting on May 13,1997. Westiaghouse has not given a rationale for its definition of accessible. Relative to 18 feet, the Commisson has give,) the industry guidance on this height pertain!ng to protected area barriers and protected area lighting. The guidance is as follows:
- For buildings and walls which constitute part of the protected crea barrier, ,
an acceptable security plan would typk. ally affirm that the buikiings and walls have non-scalable facades,18 feet or more in haight. Such buildings and walls need not be protected by a top quarc.
- An acceptable securi9 plan would typically affirm to maintain i!!umination of the tops and sides of all accessible structures. Note: A structure should be considered "accescible"if it is less than 18 feet in height or has a ready mans of access to the roo!, such as ladders, stairs, climbing bars, etc.
Since the accessible definiticn likely impacts vital-area openings, Westinghouse needs to ensure that such openings, even those above 18 feet, satisfy the requirements of 10 CFR 75.55(d)(7)(1)(D).
Westinghouse's definition of unmonitored in Section 13.6.5.2 of the SSAR does not include the monitoring capabilities oithe alarm stations via closed circuit television (CCTV), as describcd in the SDR. Westinghouse needs to revise this section to reflect C,CTV capabilities.
Address these concems and revise the SDR and SSAR accordingly.
920.16F Section 5.2," Intrusion Detection and Surveillance System," of the SDR does not adequately address the requirement to check periodically all exterior creas within the protected area, as specified in 10 CFR 73.55(c)(4). Review the requiremer.ts and revise the SDR accordingly.
3, 920.17F in the section "AP600 Security Force Armed Response Team" of the Security Design Vulnerabitity Analysis Report (SDVAR), the contingency equipment listed did not include a protective mask, which is necessary to protect against one aspect of the design basis threat. Relative to the protective strategy, the duties and responsibilities of all responders are not clearly delineated. Review thess areas and revise the BDVAR accordingly.
920.18F in Section 13.6.1 of the S3AR, Westinghouse states that the objectives and functional requiremonts of the AP600 physir,al protection system and the i description of security features are provided in the submitted AP600 SDR, submitted under separate cover in accordance with 10 CFR 2.790(d). The report includes the security boundary drawings and a listing of vital equipraent and components. The vulnerability analysis, which demonstrates that the AP600 certified security design adeq ;ately protects the AP600 from radiological sabotage, is included in the report.
Westinghouse further states that the AP600 security design features a reduced protected area that does not require a perimeter fence such as found in current plant security plans. This results in a reduced requirement for security staffing.
Personnel screening, selection, performanc.e evaluation, and training aspects of the physical security program will be addressed by the Combined License (COL) epplicant ,
The staff concludes that Westinghouse did not support its rationale for reduced ,
staffing. It is not clear if Westinghouse's claim of reduced security staffing is being attributed to a reduced protected area or other factors. Clarify your rationale for reduced security staffing.
920.19F The staff requires that, at least 60 days before loading fuel, a COL applicant will confirm that security systems and programs described in its physical security plan, safeguards contingency plan, and training and qualification plan have achieved operational status and are available for the staff's inspection. Operational status meant, that the security systems and programs are functioning in their entirety, as they will when the reactor is operating, and will continue to do so. The COL applicant's determination that cperational status has been achieved must be based on tests conducted under realistic operating conditions of sufficient duration to demonstrate that:
- a. the equipment is properly operating and capable of long-term, reliable operation-b, proceduret 2.3 been c'eveloped, approved, and implemented; and
- c. personnel responsible for security operations and maintenance have been appropriately trained and have demonstrated their capability to perform their assigned duties and responsibilities This informrtion should be included in the SSAR as a COL Action item.
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020.20F In Section 13.6.3.1 of the SSAR, Wettinghouse states that a physical protection system and security organization is provided to protect the AP600 from '
radiological sabotage, as required by 10 CFR 73.55, and that, to achieve this objective, the physicel protection system;
- a. includes a security c ganization; =
- b. locates vital equipment within vital areas; c, controls points of personnel. vehicle, and material access into the a protected and vital areas;
- d. annunciates alarms in a continuously manned central alarm station ano at least one other continuously manned alarm station that is physically separated from the central alarm station; e, provides for continuous communications br r. -n the security officers and the continuously manned alarm stations;
- f. provides for testing and maintenance of the alarms, communications, and .
physical barriers; and
- g. responds to threats of radiological sabotage in accordance with a developed contingency plan.
The staff agrees that the SDR and SDVAR submitted by Westinghouse satisfy all but one of the stated regulatory requirements. The staff does not agree that the SDR or SDVAc is relevant to g because a contingency plan will be developed by (
the COL licensee. Even though Westinghouse did not develop a contingency plan, the reference in quest!on infers that it did. Revise the SSAR to clarify that a contingency plan will be developed by a COL licensee.
920.21F in the SDVAR, Westinghouse states that the AP600 design is less vulnerable to issues associated with the requirements of 10 CFR Part 26, " Fitness for Duty Progrcms," and did not provide any guidance on implementation of 10 CFR Part 26 relative to the AP600 design. To satisfy NRC Generic Letter 91-16, Westinghouse should include a COL Action item in the SSAR to require each COL applicant to describe in its physical security plan how the requirements of 10 CFR Part 26 will be met.
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- e 5-920.22F in Section 13.6.3.2 of the SSAR, Westinghouse states that the physical protection system protects against radiological sabotage events, following the requirements of 10 CFR 73.55(a) and the following assumptions:
- a. The insider tareat is based on one knowledgeable individual without armament or explosives,
- b. The intrusion detection systems cannot be di.?abled without detection and timely response by the security force.
- c. Unless precluded by plant design features or prevented by the plant security system, insider s'abotage can potentially result in an initiating event requiring actuation of safe shutdown systems, disabling of safe shutdown systems, disabling of nonsafety-related systems (including offsite power), or any combiration of these,
- d. In evaluating vulnerability to intemal sabotage, onsite security system features, effsite resources or both are effective in preventing ur. detected penetration into the protected area by outsiders,
- e. While access to cont tinment for maintenance and testing during operation at poweris permitted, such access is controlled and typically nonroutine.
Therefore, if secuity systems are provided to pro +ect and control conta:nment access, equipment inside the containment is inaccessible to a saboteur during operation of the plant.
- f. The continuous presence of severd employees precludes acts of sadage in the control room. However, the control room is a vital area and will be prntacted in accordancu with 10 CFR 73.55.
- g. Equipment and systems designated as vital for full power operation shall be maintained as vitalin other modes of plant operation. However, during unit shutdown, a vital area can be declassified to nonvitalif app oved by the security plan.
- h. Sabotage events do not occur coincident with some other independent single failure or independently initiated event.
- 1. The security restrictions for access to equipment and plant regions will be compatible with loss of site power, access requirements, fire protection, health phys:es, and local operator actions required for event mitigation.
During operat:ng modes, security access control restrictions will not excessively impede operator functions.
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6-The staff has concems with assumptions a, e, and f, as discussed below:
Assumption a: Relative to the insider threat,10 CFR 73.1(a)(1) states, in part, that an insider includes an employee in any position. Sincs an amled responder is an employee, the assumption is that an insider could possess armaments. This issue was raised in writing to Westinghouse and discussed with them during a meeting on May 13,1997. Section 2.2, " Insider," of the SDR was subsequently revised to reflect that an insider is assumed not to be armed, even if he or she }
were a member of the security organization armed response team. Westinghouse did not provide a basis for this conclusion. Address this concem in the SSAR, the SDR, and the section, " Insider Threat," of the SDVAR.
Assumption e: Westinghouse stato that equipment inside containment is inaccessible to a saboteur during operation of the plant. However, neither the SDR nor the SDVAR Di ves a basis for this conclusion. Address this concem.
Assumption f: It is not clear to the staff how the continuous presence of several employees in the control room can preclude acts of sabotage. Neither the SDR nor the SDVAR gives a basis for this conclusion. This conclusion needs to be validated. Address this concem.
920.23F in Section 13.6.3.2 of the SSAR, Westinghouse states that the AP600 plant ecurity system conforms to the applicable portions of ANS 3.3-1988, "Secunty for Nuclear Power Plants." But the submitted documents do not reflect when adherence to ANS 3.3 takes place. Since the NRC did not endorse the ANS standard, Westinghouse neerte to revise the SDR and the SDVAR to indicate where ANS 3.3 was applied.
920.24F Westinghouse should include a COL Action item in the SSAR to require each COL applicant to address in its safeguards plans how the physical protection system will provide the protection assumed in items a, b, d, and e of Section 13.6.3.2 of the SSAR.
920.25F The SDR references the security organization and states that manning levels are contained in the SDVAR. However, the SDVAR only details minimum manning requirements for the alarm stations and response team. Neither document addresses the individual with the authority to direct physical protection aci /ities, as required and described in 10 CFR 73.55(b)(2). Address this matter.
920.26F in Section 13.6.5.1 of the SSAR, Westinghouse states that where there are portals for personnel or material access into the vital arees, " protected area enclosures" surround the portals with a protected area barrier. The protected area barriers provide an outer boundary to prevent unauthorized access to the vital areas of the plant without detection. The protected area barriers are constructed, as a minimum, of chain , ink fence equivalent to the physical barrier defined in 10 CFR 73.2 for fences. The protectea area barriers are constructed so that any attempt to penetrate into the protected areas will activate counter measures in response to the threat. The protected areas havt intrusicn detection equipment and aiarms that annunciate upon detection of penetration of the encbsure to alert security response forces that the enclosure has been breached.
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~7-The drawings identifying the protected areas are provided in the AP600 SDR.
Except for assessment capabilities, the staff agrees that the measures ir. this section satisfy regulatory re:luirements. Even though assessment capab!!ities are described in the SDR, Westinghouse did not incorponste them, ytiere applicable, into this section. Revise this section to reflect assessment capabilities.
g20.27F in Section 13.6.7.1 of the SSAR, Westinghouse states that because of the security features designed into the AP600, " intrusion detection at the perimeter of the plant is not required. With the exception of the special provisions provided for the Shield Building, the staff agrees. Revise the SSAR to c!arify this statement.
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