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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20216J0681999-09-29029 September 1999 Forwards Rev 3 of AP600 Design Control Document, Incorporating Documentation Changes Resulting from Final Review Performed to Check Consistency of Implementation of Approved Design Change Proposals.With Summary of Changes ML20207G5411999-06-0808 June 1999 Discusses Request Made by Westinghouse on 981109 That Proprietary WCAP-14252,Rev 1,be Withheld from Public Disclosure.Determined Info to Be Proprietary & Will Be Withheld from Public Disclosure ML20195D5201999-06-0404 June 1999 Discusses Westinghouse Request That Change Pages Submitted on 980921 to WCAP-14292 Be Withheld from Public Disclosure. Determined Info to Be Proprietary & Will Be Withheld from Public Disclosure ML20196G2431999-05-21021 May 1999 Informs That USNRC Has Published in Fr Encl Notice of Proposed Rulemaking Re AP600 Design Certification Rule. Rulemaking Allows Applicants or Licensees to Construct AP600 Std Plant Design by Referencing Design Certification Rule ML20206G5411999-05-0505 May 1999 Forwards Draft Environ Assessment Re Proposed Certification of AP600 Std Plant Design.Environ Assessment Will Be Used as Basis for NRC Finding of No Significant Environ Impact Resulting from Certification of AP600 Design ML20205J3351999-04-0707 April 1999 Informs That USNRC Staff Has Completed Review of Rev 2 of AP600 Design Control Document,Verified That All of Changes in Rev 2 Are Acceptable & Determined That AP600 Dcd,Rev 2, Can Now Be Used in Proposed Design Certification Rule NSD-NRC-99-5827, Forwards Rev 2 to AP600 Design Control Document.Attachment 1 Provides Summary of Changes Made as Part of Mar 1999 Rev to AP600 Design Control Document1999-03-31031 March 1999 Forwards Rev 2 to AP600 Design Control Document.Attachment 1 Provides Summary of Changes Made as Part of Mar 1999 Rev to AP600 Design Control Document ML20205D3051999-03-25025 March 1999 Requests Amend to 920626 Application for Design Certification of AP600,including AP600 Ssar & AP600 Dcd,To Reflect Sale of CBS Commercial Nuclear Business to W ML20203C5481999-02-10010 February 1999 Forwards Rev 1 to AP600 Design Control Document (DCD) for Docket File.Dcd Provides Reference Basis for AP600 Design Certification ML20199H8671999-01-20020 January 1999 Forwards Comments on AP600 Design Control Document,Submitted by Westinghouse ML20199B1121999-01-0707 January 1999 Advises That Info Contained in NSRA-APSL-92-0268 & Containing Presentation Matl Used in 921209-10 Meeting,Marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA ML20198B4601998-12-14014 December 1998 Discusses W Ltr NTD-NRC-95-4556,dtd 950918,provided as Status Rept on Proprietary Matl Submitted to NRC to Support AP600 Design Review Effort.Proprietary Info in Encl Have Been Removed from AP600 Docket File & Being Returned ML20197G3501998-11-30030 November 1998 Forwards AP600 Design Control Document, Vols 1-12 for Docket File.Submittal Closes Confirmatory Items 1.5-1 & 1.5-2 from Sept 1998 Final SER Re Certification of AP600 Std Design ML20195E9331998-11-0909 November 1998 Requests That Rev 1 to WCAP-14252, AP600 Low-Pressure Integral Sys Test at or State Univ Final Data Rept, Vols I- Iv,Be Withheld (Ref 10CFR2.790) NSD-NRC-98-5806, Forwards non-proprietary Rev 1 to WCAP-14253 & Proprietary Rev 1 to WCAP-14252, AP600 Low-Pressure Integral Sys Test at or State Univ Final Data Rept. Proprietary Rept Includes Vols 1-4.Proprietary Info Withheld,Per 10CFR2.7901998-11-0909 November 1998 Forwards non-proprietary Rev 1 to WCAP-14253 & Proprietary Rev 1 to WCAP-14252, AP600 Low-Pressure Integral Sys Test at or State Univ Final Data Rept. Proprietary Rept Includes Vols 1-4.Proprietary Info Withheld,Per 10CFR2.790 ML20155G9021998-11-0303 November 1998 Advises That Info Contained in 981012 ltr,NSD-NRC-98-5795, Will Be Withheld from Public Disclosure,Per 10CFR2.790(b) (5) & Section 103(b) of AEA of 1954,as Amended ML20155G9271998-11-0202 November 1998 Forwards Copy of NRC Staff FSER for Westinghouse AP600 Design.Staff Completed Review of Design & Issued Final Design Approval & FSER on 980903.Without Encl ML20155G7591998-11-0202 November 1998 Forwards Copy of NRC Staff FSER for Westinghouse AP600 Design,Per Discussion at Sept 1997 Meeting.Staff Completed & Issued Final Design Approval of FSER on 980903.Without Encl NSD-NRC-98-5795, Informs That Figures from Rev 0 & Rev 3 of PRA Which Indicate Location of H Igniters Should Be Considered Proprietary.Nonproprietary Versions of AP600 General Arrangement Drawings Were Provided in Rev 7 of Ssar1998-10-12012 October 1998 Informs That Figures from Rev 0 & Rev 3 of PRA Which Indicate Location of H Igniters Should Be Considered Proprietary.Nonproprietary Versions of AP600 General Arrangement Drawings Were Provided in Rev 7 of Ssar ML20154A4091998-09-29029 September 1998 Advises That Certain Info Contained in Westinghouse Ltr NTD-NRC-95-4506,dtd 950713,submitting WCAP-14425,will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5).Figure 3-1 Will Be Placed Into Public Record ML20153G2521998-09-25025 September 1998 Advises That Proprietary Matl Discovered by NRC in NSD-NRC-97-4966 & Proprietary Matl Noted by W in NSD-NRC-98-5772 Will Be Withhheld from Public Disclosure Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 ML20153C1001998-09-15015 September 1998 Advises That Matls Re AP600 Notrump Final Validation Rept, WCAP-14807,marked Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended NSD-NRC-98-5788, Forwards Formal Transmittal of Correspondence Previously Sent Informally Over Period of 980702-0826.Index of Encl Matl Provided1998-09-15015 September 1998 Forwards Formal Transmittal of Correspondence Previously Sent Informally Over Period of 980702-0826.Index of Encl Matl Provided ML20151X4381998-09-15015 September 1998 Informs That Staff Has Decided to Accept Claim That Info in WCAP-14135,Rev 1 Is Proprietary & Will Be Withheld from Public Disclosure,Per W 980821 & 26 Ltrs ML20151X4041998-09-11011 September 1998 Discusses Revised Tier 2 Info for AP600 Design.Staff Revised Decision on Whether Fire Protection Should Expire at First Full Power Encl ML20151V1711998-09-0808 September 1998 Advises That Info Re Westinghouse AP600 Std Safety Analysis Rept Through Rev 4 & PRA Through Rev 5 Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5).Disposition of Ssar & PRA Proprietary Info Encl ML20151V2231998-09-0808 September 1998 Informs That NRC Determined That WCAP-14132 Encl in Westinghouse Ltr NTD-NRC-94-4244,dtd 940729 & Marked as Proprietary,Will Be Withheld from Public Disclosure,Per to 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 ML20151S9181998-09-0303 September 1998 Advises That Info Marked as Proprietary Re Westinghouse AP600 Design Ltrs Concerning Pxs Scaling & Pirt Closure Rept WCAP-14727,will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) ML20239A1481998-09-0303 September 1998 Forwards Notice of Issuance of Final Design Approval & Final SER for AP600.FDA Allows AP600 Design to Be Referenced in Application for Construction Permit or Operating License Under 10CFR50 or Application for Combined License ML20239A3111998-09-0303 September 1998 Forwards Final SER Which Summarizes Staff Safety Review of AP600 Design Against Requirements of Subpart B of 10CF5R52 & Delineates Scope of Technical Details Considered in Evaluating Proposed Design ML20151V8521998-09-0101 September 1998 Extends Invitation to Attend Ceremony on 980911,where NRC Will Present Final Design Approval for AP600 Std Nuclear Reactor Design to Westinghouse NSD-NRC-98-5781, Informs That W Determined That AP600 FSER Contains No Proprietary Info1998-09-0101 September 1998 Informs That W Determined That AP600 FSER Contains No Proprietary Info ML20151V2201998-08-31031 August 1998 Informs That EPRI Documents, GOTHIC Containment Analysis Package Qualification Rept, GOTHIC Containment Analysis Qualification Manual, & Listed Documents Dtd Sept 1993 Will Be Withheld from Public Disclosure ML20151V8431998-08-31031 August 1998 Extends Invitation to Attend Ceremony on 980911,where NRC Will Present Final Design Approval for AP600 Std Nuclear Reactor Design to Westinghouse ML20238F3241998-08-31031 August 1998 Advises That AP600 RAI Responses Encl in Westinghouse Ltrs NTD-NRC-95-4598,dtd 951117,as Modified by NSD-NRC-98-5776, Dtd 980826,marked Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) ML20238F5991998-08-31031 August 1998 Refers to W 980821 Revised Response to Insp Rept 99900404/97-01 That Contained All Substantive Info Provided w/DCP/NRC-1074 Ltr.Nrc Will Destroy DCP/NRC-1074,as Requested NSD-NRC-98-5783, Forwards non-proprietary Rev 2 to WCAP-14989, Accident Specification & Phenomena Evaluation for AP600 Passive Containment Cooling Sys1998-08-28028 August 1998 Forwards non-proprietary Rev 2 to WCAP-14989, Accident Specification & Phenomena Evaluation for AP600 Passive Containment Cooling Sys NSD-NRC-98-5782, Forwards Corrected Pages 4-28 Through 4-32 to Be Inserted in Rev 2 to non-proprietary WCAP-14953, AP600 Pxs Scaling & Pirt Closure Rept. Pages Were Originally Submitted W/Incorrect Header Which Stated 'W Proprietary Class 2.'1998-08-28028 August 1998 Forwards Corrected Pages 4-28 Through 4-32 to Be Inserted in Rev 2 to non-proprietary WCAP-14953, AP600 Pxs Scaling & Pirt Closure Rept. Pages Were Originally Submitted W/Incorrect Header Which Stated 'W Proprietary Class 2.' NSD-NRC-98-5778, Provides Commitment to Include Requested Changes Into AP600 Design Control Document.Discussion W/Vijuk on 980825 Re Disposition of Ltrs DCP/NRC1074,dtd 971016 & DCP/NRC1324,dtd 980403,formalized1998-08-27027 August 1998 Provides Commitment to Include Requested Changes Into AP600 Design Control Document.Discussion W/Vijuk on 980825 Re Disposition of Ltrs DCP/NRC1074,dtd 971016 & DCP/NRC1324,dtd 980403,formalized ML20237E4421998-08-27027 August 1998 Advises That Info Contained in Ltr DCP/NRC-0985,dtd 970821, Sought to Be Withheld,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended NSD-NRC-98-5777, Provides Revised Response to NRC Ltr Re W Requests for Withholding Info Re AP600 PCS Final Data rept,WCAP-14135 & WCAP-141381998-08-26026 August 1998 Provides Revised Response to NRC Ltr Re W Requests for Withholding Info Re AP600 PCS Final Data rept,WCAP-14135 & WCAP-14138 NSD-NRC-98-5776, Forwards Proprietary Revised Response to Ref NRC Ltr Re W Requests for Withholding Info Re AP600 Design Certification Test Program,Notrump Computer Code,Wcobra/Trac Computer Code & Loftran Computer Code.Proprietary Info Withheld1998-08-26026 August 1998 Forwards Proprietary Revised Response to Ref NRC Ltr Re W Requests for Withholding Info Re AP600 Design Certification Test Program,Notrump Computer Code,Wcobra/Trac Computer Code & Loftran Computer Code.Proprietary Info Withheld ML20237E0731998-08-26026 August 1998 Advises That Info in WCAP-14812,revs 1 & 2, Accident Spec & Phenomena Evaluation for AP600 PCS, Will Be Withheld from Public Disclosure ML20238F8031998-08-26026 August 1998 Requests That Proprietary W Revised Response to NRC Ltrs Re Requests for Withholding Info,Be Withheld from Public Disclosure IAW 10CFR2.790 NSD-NRC-98-5774, Informs That W Faxed Last Response Re Afser Open Item 1.1-1 to NRC on 980821.Last of Attachments Supporting Several of Responses Faxed to NRC Over Past Several Days Were Express Mailed to NRC on 980821.Responses Close Subject Open It1998-08-24024 August 1998 Informs That W Faxed Last Response Re Afser Open Item 1.1-1 to NRC on 980821.Last of Attachments Supporting Several of Responses Faxed to NRC Over Past Several Days Were Express Mailed to NRC on 980821.Responses Close Subject Open Item NSD-NRC-98-5773, Responds to Questions Raised in NRC 971022 & s Re Proprietary Info Contained in 970930 Summary of Meeting Held on 970804-15 Concerning Structural Design of AP600.Figure 12-24 of WCAP-14407 Still Considered Proprietary by W1998-08-21021 August 1998 Responds to Questions Raised in NRC 971022 & s Re Proprietary Info Contained in 970930 Summary of Meeting Held on 970804-15 Concerning Structural Design of AP600.Figure 12-24 of WCAP-14407 Still Considered Proprietary by W ML20237E7991998-08-21021 August 1998 Forwards non-proprietary Results of AP600 Design Assurance Review (Dar) That Was Commitment in W Response to NRC Insp Rept 99900404/97-02.Info Should Assist in Closing Nonconformances & Unresolved Item Identified in Insp Rept NSD-NRC-98-5771, Forwards non-proprietary Rev 2 to WCAP-14138, Final Data Rept for PCS Large-Scale Tests,Phase 2 & Phase 3. Submittal Satisfies Verbal Commitment to Revise non-proprietary Version of PCS Final Data Rept Made by W1998-08-21021 August 1998 Forwards non-proprietary Rev 2 to WCAP-14138, Final Data Rept for PCS Large-Scale Tests,Phase 2 & Phase 3. Submittal Satisfies Verbal Commitment to Revise non-proprietary Version of PCS Final Data Rept Made by W NSD-NRC-98-5769, Responds to NRC Ref Ltrs Re W Requests for Withholding Info. Info Provided as Proprietary in Ref 1 Has Either Been Moved from Ssar to Ref 3,which Includes non-proprietary Version of Rept or Made non-proprietary in Current Version of1998-08-21021 August 1998 Responds to NRC Ref Ltrs Re W Requests for Withholding Info. Info Provided as Proprietary in Ref 1 Has Either Been Moved from Ssar to Ref 3,which Includes non-proprietary Version of Rept or Made non-proprietary in Current Version of Ssar NSD-NRC-98-5772, Forwards non-proprietary & Proprietary Info in Response to NRC Ltrs Re W Requests for Withholding Info.Separate Ltr & Affidavit Justifying Proprietary Nature of Info,Encl. Proprietary Info Withheld,Per 10CFR2.7901998-08-21021 August 1998 Forwards non-proprietary & Proprietary Info in Response to NRC Ltrs Re W Requests for Withholding Info.Separate Ltr & Affidavit Justifying Proprietary Nature of Info,Encl. Proprietary Info Withheld,Per 10CFR2.790 1999-09-29
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20216J0681999-09-29029 September 1999 Forwards Rev 3 of AP600 Design Control Document, Incorporating Documentation Changes Resulting from Final Review Performed to Check Consistency of Implementation of Approved Design Change Proposals.With Summary of Changes NSD-NRC-99-5827, Forwards Rev 2 to AP600 Design Control Document.Attachment 1 Provides Summary of Changes Made as Part of Mar 1999 Rev to AP600 Design Control Document1999-03-31031 March 1999 Forwards Rev 2 to AP600 Design Control Document.Attachment 1 Provides Summary of Changes Made as Part of Mar 1999 Rev to AP600 Design Control Document ML20205D3051999-03-25025 March 1999 Requests Amend to 920626 Application for Design Certification of AP600,including AP600 Ssar & AP600 Dcd,To Reflect Sale of CBS Commercial Nuclear Business to W ML20203C5481999-02-10010 February 1999 Forwards Rev 1 to AP600 Design Control Document (DCD) for Docket File.Dcd Provides Reference Basis for AP600 Design Certification ML20197G3501998-11-30030 November 1998 Forwards AP600 Design Control Document, Vols 1-12 for Docket File.Submittal Closes Confirmatory Items 1.5-1 & 1.5-2 from Sept 1998 Final SER Re Certification of AP600 Std Design NSD-NRC-98-5806, Forwards non-proprietary Rev 1 to WCAP-14253 & Proprietary Rev 1 to WCAP-14252, AP600 Low-Pressure Integral Sys Test at or State Univ Final Data Rept. Proprietary Rept Includes Vols 1-4.Proprietary Info Withheld,Per 10CFR2.7901998-11-0909 November 1998 Forwards non-proprietary Rev 1 to WCAP-14253 & Proprietary Rev 1 to WCAP-14252, AP600 Low-Pressure Integral Sys Test at or State Univ Final Data Rept. Proprietary Rept Includes Vols 1-4.Proprietary Info Withheld,Per 10CFR2.790 ML20195E9331998-11-0909 November 1998 Requests That Rev 1 to WCAP-14252, AP600 Low-Pressure Integral Sys Test at or State Univ Final Data Rept, Vols I- Iv,Be Withheld (Ref 10CFR2.790) NSD-NRC-98-5795, Informs That Figures from Rev 0 & Rev 3 of PRA Which Indicate Location of H Igniters Should Be Considered Proprietary.Nonproprietary Versions of AP600 General Arrangement Drawings Were Provided in Rev 7 of Ssar1998-10-12012 October 1998 Informs That Figures from Rev 0 & Rev 3 of PRA Which Indicate Location of H Igniters Should Be Considered Proprietary.Nonproprietary Versions of AP600 General Arrangement Drawings Were Provided in Rev 7 of Ssar NSD-NRC-98-5788, Forwards Formal Transmittal of Correspondence Previously Sent Informally Over Period of 980702-0826.Index of Encl Matl Provided1998-09-15015 September 1998 Forwards Formal Transmittal of Correspondence Previously Sent Informally Over Period of 980702-0826.Index of Encl Matl Provided NSD-NRC-98-5781, Informs That W Determined That AP600 FSER Contains No Proprietary Info1998-09-0101 September 1998 Informs That W Determined That AP600 FSER Contains No Proprietary Info NSD-NRC-98-5782, Forwards Corrected Pages 4-28 Through 4-32 to Be Inserted in Rev 2 to non-proprietary WCAP-14953, AP600 Pxs Scaling & Pirt Closure Rept. Pages Were Originally Submitted W/Incorrect Header Which Stated 'W Proprietary Class 2.'1998-08-28028 August 1998 Forwards Corrected Pages 4-28 Through 4-32 to Be Inserted in Rev 2 to non-proprietary WCAP-14953, AP600 Pxs Scaling & Pirt Closure Rept. Pages Were Originally Submitted W/Incorrect Header Which Stated 'W Proprietary Class 2.' NSD-NRC-98-5783, Forwards non-proprietary Rev 2 to WCAP-14989, Accident Specification & Phenomena Evaluation for AP600 Passive Containment Cooling Sys1998-08-28028 August 1998 Forwards non-proprietary Rev 2 to WCAP-14989, Accident Specification & Phenomena Evaluation for AP600 Passive Containment Cooling Sys NSD-NRC-98-5778, Provides Commitment to Include Requested Changes Into AP600 Design Control Document.Discussion W/Vijuk on 980825 Re Disposition of Ltrs DCP/NRC1074,dtd 971016 & DCP/NRC1324,dtd 980403,formalized1998-08-27027 August 1998 Provides Commitment to Include Requested Changes Into AP600 Design Control Document.Discussion W/Vijuk on 980825 Re Disposition of Ltrs DCP/NRC1074,dtd 971016 & DCP/NRC1324,dtd 980403,formalized ML20238F8031998-08-26026 August 1998 Requests That Proprietary W Revised Response to NRC Ltrs Re Requests for Withholding Info,Be Withheld from Public Disclosure IAW 10CFR2.790 NSD-NRC-98-5776, Forwards Proprietary Revised Response to Ref NRC Ltr Re W Requests for Withholding Info Re AP600 Design Certification Test Program,Notrump Computer Code,Wcobra/Trac Computer Code & Loftran Computer Code.Proprietary Info Withheld1998-08-26026 August 1998 Forwards Proprietary Revised Response to Ref NRC Ltr Re W Requests for Withholding Info Re AP600 Design Certification Test Program,Notrump Computer Code,Wcobra/Trac Computer Code & Loftran Computer Code.Proprietary Info Withheld NSD-NRC-98-5777, Provides Revised Response to NRC Ltr Re W Requests for Withholding Info Re AP600 PCS Final Data rept,WCAP-14135 & WCAP-141381998-08-26026 August 1998 Provides Revised Response to NRC Ltr Re W Requests for Withholding Info Re AP600 PCS Final Data rept,WCAP-14135 & WCAP-14138 NSD-NRC-98-5774, Informs That W Faxed Last Response Re Afser Open Item 1.1-1 to NRC on 980821.Last of Attachments Supporting Several of Responses Faxed to NRC Over Past Several Days Were Express Mailed to NRC on 980821.Responses Close Subject Open It1998-08-24024 August 1998 Informs That W Faxed Last Response Re Afser Open Item 1.1-1 to NRC on 980821.Last of Attachments Supporting Several of Responses Faxed to NRC Over Past Several Days Were Express Mailed to NRC on 980821.Responses Close Subject Open Item ML20237E7991998-08-21021 August 1998 Forwards non-proprietary Results of AP600 Design Assurance Review (Dar) That Was Commitment in W Response to NRC Insp Rept 99900404/97-02.Info Should Assist in Closing Nonconformances & Unresolved Item Identified in Insp Rept ML20237D3161998-08-21021 August 1998 Requests That W Response to NRC Ltrs Re Requests for Withholding Info Be Withheld from Public Disclosure,Per 10CFR2.790 NSD-NRC-98-5773, Responds to Questions Raised in NRC 971022 & s Re Proprietary Info Contained in 970930 Summary of Meeting Held on 970804-15 Concerning Structural Design of AP600.Figure 12-24 of WCAP-14407 Still Considered Proprietary by W1998-08-21021 August 1998 Responds to Questions Raised in NRC 971022 & s Re Proprietary Info Contained in 970930 Summary of Meeting Held on 970804-15 Concerning Structural Design of AP600.Figure 12-24 of WCAP-14407 Still Considered Proprietary by W NSD-NRC-97-5370, Transmits Results of AP600 Foake Design Assurance Review as Requested in NRC .Info Is Being Provided to Close Unresolved Item Identified in Insp Rept 99900404/97-011998-08-21021 August 1998 Transmits Results of AP600 Foake Design Assurance Review as Requested in NRC .Info Is Being Provided to Close Unresolved Item Identified in Insp Rept 99900404/97-01 NSD-NRC-98-5763, Responds to NRC Ltrs Re W Claim for Treatment of Proprietary Info Submitted in .As Discussed W/Nrc on 980821, Info Contained in W Is self-critical Analysis of W QA Program & Therefore Falls Under Items of Affidavit1998-08-21021 August 1998 Responds to NRC Ltrs Re W Claim for Treatment of Proprietary Info Submitted in .As Discussed W/Nrc on 980821, Info Contained in W Is self-critical Analysis of W QA Program & Therefore Falls Under Items of Affidavit NSD-NRC-98-5772, Forwards non-proprietary & Proprietary Info in Response to NRC Ltrs Re W Requests for Withholding Info.Separate Ltr & Affidavit Justifying Proprietary Nature of Info,Encl. Proprietary Info Withheld,Per 10CFR2.7901998-08-21021 August 1998 Forwards non-proprietary & Proprietary Info in Response to NRC Ltrs Re W Requests for Withholding Info.Separate Ltr & Affidavit Justifying Proprietary Nature of Info,Encl. Proprietary Info Withheld,Per 10CFR2.790 NSD-NRC-98-5769, Responds to NRC Ref Ltrs Re W Requests for Withholding Info. Info Provided as Proprietary in Ref 1 Has Either Been Moved from Ssar to Ref 3,which Includes non-proprietary Version of Rept or Made non-proprietary in Current Version of1998-08-21021 August 1998 Responds to NRC Ref Ltrs Re W Requests for Withholding Info. Info Provided as Proprietary in Ref 1 Has Either Been Moved from Ssar to Ref 3,which Includes non-proprietary Version of Rept or Made non-proprietary in Current Version of Ssar NSD-NRC-98-5771, Forwards non-proprietary Rev 2 to WCAP-14138, Final Data Rept for PCS Large-Scale Tests,Phase 2 & Phase 3. Submittal Satisfies Verbal Commitment to Revise non-proprietary Version of PCS Final Data Rept Made by W1998-08-21021 August 1998 Forwards non-proprietary Rev 2 to WCAP-14138, Final Data Rept for PCS Large-Scale Tests,Phase 2 & Phase 3. Submittal Satisfies Verbal Commitment to Revise non-proprietary Version of PCS Final Data Rept Made by W ML20237D3551998-08-20020 August 1998 Requests That Proprietary Info Re W Response to NRC Ltrs Re Requests for Withholding Info Concerning AP600 Pxs Scaling & Pirt Closure Rept, WCAP-14727 Be Withheld from Public Disclosure IAW 10CFR2.790 NSD-NRC-98-5762, Forwards Proprietary Change Pages for Chapters 7 & 8,for Inclusion as Rev 2 of TR WCAP-14727,in Response to NRC Ltr Dtd 980714.Non-proprietary Rev 2 to TR WCAP-14953 Re AP600 Scaling & Pirt Closure Encl.Proprietary Info Withheld1998-08-20020 August 1998 Forwards Proprietary Change Pages for Chapters 7 & 8,for Inclusion as Rev 2 of TR WCAP-14727,in Response to NRC Ltr Dtd 980714.Non-proprietary Rev 2 to TR WCAP-14953 Re AP600 Scaling & Pirt Closure Encl.Proprietary Info Withheld NSD-NRC-98-5764, Responds to NRC Ltrs Re Requests for Withholding Info from Public Disclosure for W AP600 Design Ltr of 951117,dtd 960229.W Considers Matl Proprietary Since Matl Discusses Approach Used by W to Develop Analysis Models of Cctf Test1998-08-20020 August 1998 Responds to NRC Ltrs Re Requests for Withholding Info from Public Disclosure for W AP600 Design Ltr of 951117,dtd 960229.W Considers Matl Proprietary Since Matl Discusses Approach Used by W to Develop Analysis Models of Cctf Test NSD-NRC-98-5768, Responds to NRC Ref Ltrs Re W Requests for Withholding Info. Specific Info Considered non-proprietary or Proprietary Discussed1998-08-20020 August 1998 Responds to NRC Ref Ltrs Re W Requests for Withholding Info. Specific Info Considered non-proprietary or Proprietary Discussed NSD-NRC-98-5766, Provides Summary of 980813 Telcon W/Nrc Re W Explanation of Rationale Which Was Used to Determine What Info Was Considered to Be Proprietary in TR WCAP-148121998-08-20020 August 1998 Provides Summary of 980813 Telcon W/Nrc Re W Explanation of Rationale Which Was Used to Determine What Info Was Considered to Be Proprietary in TR WCAP-14812 NSD-NRC-98-5770, Responds to NRC Ltrs Re W Requests for Withholding Info.W Withdraws AP600 Rept Entitled, Wcobra/Trac Core Makeup Tank Preliminary Validation Rept, Since Rept Was Not Required by NRC to Make Safety Determination of AP6001998-08-20020 August 1998 Responds to NRC Ltrs Re W Requests for Withholding Info.W Withdraws AP600 Rept Entitled, Wcobra/Trac Core Makeup Tank Preliminary Validation Rept, Since Rept Was Not Required by NRC to Make Safety Determination of AP600 NSD-NRC-98-5760, Forwards Rev 25 to GW-GL-021, AP600 Ssar, Vols 1-11. Revised Tables of Contents,Change Page Instructions,List of Effective Pages,Document Cover Sheet & Change Roadmap Outlining Changes in Each Section Also Encl1998-08-19019 August 1998 Forwards Rev 25 to GW-GL-021, AP600 Ssar, Vols 1-11. Revised Tables of Contents,Change Page Instructions,List of Effective Pages,Document Cover Sheet & Change Roadmap Outlining Changes in Each Section Also Encl NSD-NRC-98-5761, Provides Written Confirmation That Identified Figure Is Not Considered Proprietary by W.Refs 1-5,discussed1998-08-19019 August 1998 Provides Written Confirmation That Identified Figure Is Not Considered Proprietary by W.Refs 1-5,discussed ML20237D2681998-08-18018 August 1998 Requests That Proprietary Informal Correspondence Be Withheld from Public Disclosure,Per 10CFR2.790 NSD-NRC-97-5046, Submits Rev 1 of W Ltr Originally Submitted 970917,which Transmitted Proprietary & non-proprietary Informal Correspondence.Rev Includes Notarized Affidavit as Part of Application for Withholding Info.Proprietary Info Withheld1998-08-18018 August 1998 Submits Rev 1 of W Ltr Originally Submitted 970917,which Transmitted Proprietary & non-proprietary Informal Correspondence.Rev Includes Notarized Affidavit as Part of Application for Withholding Info.Proprietary Info Withheld NSD-NRC-98-5759, Submits Response to NRC Ltrs Re Request for Withholding Info.Figure 8-19 Will No Longer Be Considered Proprietary by W1998-08-17017 August 1998 Submits Response to NRC Ltrs Re Request for Withholding Info.Figure 8-19 Will No Longer Be Considered Proprietary by W NSD-NRC-98-5756, Responds to NRC 980714 & 21 Ltrs Re Request for Withholding Proprietary Info That Was Not Clearly Identified Other than Being Marked W Proprietary Class 21998-08-14014 August 1998 Responds to NRC 980714 & 21 Ltrs Re Request for Withholding Proprietary Info That Was Not Clearly Identified Other than Being Marked W Proprietary Class 2 NSD-NRC-98-5757, Responds to Ref NRC Ltrs Re Request for Withholding Proprietary Info Re W AP600 Ltr.Per 980708 Telcon,W Has Reviewed TRs WCAP-13288 & WCAP-13289 & Considers None of Info to Be Proprietary1998-08-14014 August 1998 Responds to Ref NRC Ltrs Re Request for Withholding Proprietary Info Re W AP600 Ltr.Per 980708 Telcon,W Has Reviewed TRs WCAP-13288 & WCAP-13289 & Considers None of Info to Be Proprietary ML20151Z0971998-08-13013 August 1998 Requests That Proprietary Rev 5 to WCAP-14807, Notrump Final Validation Rept, Be Withheld from Public Disclosure, Per 10CFR2.790 NSD-NRC-98-5754, Forwards non-proprietary Versions of Revs 3-5 to WCAP-14808 & Proprietary Version of Rev 5 to WCAP-14807, Notrump Final Validation Rept for AP600, in Form of Replacement Pages. Proprietary Encl Withheld1998-08-13013 August 1998 Forwards non-proprietary Versions of Revs 3-5 to WCAP-14808 & Proprietary Version of Rev 5 to WCAP-14807, Notrump Final Validation Rept for AP600, in Form of Replacement Pages. Proprietary Encl Withheld NSD-NRC-98-5749, Forwards Rev 13 to AP600 PRA for Simplified Passive Advanced LWR Plant Program. Rev Represents Final Version of AP600 Pra.All NRC Comments Related to Rev 12 of AP600 PRA Have Been Resolved1998-08-13013 August 1998 Forwards Rev 13 to AP600 PRA for Simplified Passive Advanced LWR Plant Program. Rev Represents Final Version of AP600 Pra.All NRC Comments Related to Rev 12 of AP600 PRA Have Been Resolved NSD-NRC-98-5753, Responds to Ref NRC Ltrs & W Ltr Re Request for Withholding Proprietary Info Re AP600 Design Ltrs1998-08-13013 August 1998 Responds to Ref NRC Ltrs & W Ltr Re Request for Withholding Proprietary Info Re AP600 Design Ltrs NSD-NRC-98-5752, Responds to Open Item 1.1-2 Contained in 980501 Advance Final SER for AP600 Requesting Update of Comparison of AP600 to NRC Reviewed Version of Alwr Util Requirements Document. Changes Resulting from NRC Comments Re Plant Design,List1998-08-13013 August 1998 Responds to Open Item 1.1-2 Contained in 980501 Advance Final SER for AP600 Requesting Update of Comparison of AP600 to NRC Reviewed Version of Alwr Util Requirements Document. Changes Resulting from NRC Comments Re Plant Design,Listed NSD-NRC-98-5755, Forwards Rev 7 to Simplified Passive Advance Light Water Reactor Plant Program AP600 Tier 1 Matl, Incorporating Comments Received from NRC Technical Staff,As of 980812.Encl Closes Open Item 14.3-1 from Advanced Final SER1998-08-13013 August 1998 Forwards Rev 7 to Simplified Passive Advance Light Water Reactor Plant Program AP600 Tier 1 Matl, Incorporating Comments Received from NRC Technical Staff,As of 980812.Encl Closes Open Item 14.3-1 from Advanced Final SER ML20153D9491998-08-12012 August 1998 Submits Response to NRC Ltrs Re Requests for Withholding Info.Info Does Not Have Commercial Value & No Longer Considered to Be Proprietary by W NSD-NRC-98-5751, Submits Response to NRC Ltrs Re Requests for Withholding Info.Info Does Not Have Commercial Value & Is No Longer Considered Proprietary by W1998-08-12012 August 1998 Submits Response to NRC Ltrs Re Requests for Withholding Info.Info Does Not Have Commercial Value & Is No Longer Considered Proprietary by W NSD-NRC-98-5748, Forwards Rev 24 of AP600 Ssar.Revised Tables of Contents, Change Page Instructions,List of Effective Pages,Document Cover Sheet & Change Roadmap Outlining Changes in Each Section Also Encl.Rev Submitted Under Encl Oath1998-08-0707 August 1998 Forwards Rev 24 of AP600 Ssar.Revised Tables of Contents, Change Page Instructions,List of Effective Pages,Document Cover Sheet & Change Roadmap Outlining Changes in Each Section Also Encl.Rev Submitted Under Encl Oath NSD-NRC-98-5743, Forwards Table Which Compares Combined License (COL) Info Items Identified in AP600 Design Certification Application W/Col Action Items Identified in AP600 Advance Final SER Provided to W by NRC on 9805061998-07-31031 July 1998 Forwards Table Which Compares Combined License (COL) Info Items Identified in AP600 Design Certification Application W/Col Action Items Identified in AP600 Advance Final SER Provided to W by NRC on 980506 NSD-NRC-98-5733, Forwards Rev 6 to GW-GL-030, Simplified Passive Advance LWR Plant Program,AP600 Tier 1 Matl, Which Incorporates Comments Received from NRC Technical Staff as of 9807221998-07-27027 July 1998 Forwards Rev 6 to GW-GL-030, Simplified Passive Advance LWR Plant Program,AP600 Tier 1 Matl, Which Incorporates Comments Received from NRC Technical Staff as of 980722 NSD-NRC-98-5742, Forwards Rev 12 to AP600 PRA Rept. All NRC Open Items Related to AP600 PRA Have Been Resolved1998-07-24024 July 1998 Forwards Rev 12 to AP600 PRA Rept. All NRC Open Items Related to AP600 PRA Have Been Resolved 1999-09-29
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. '. / rrAck HfNr Z O i NTD NRC-95-4474 Westingtiouse Energy Systems weu tunneiotv asion Electric Corporation e n 333 Pmsburgh Pennsylvania 15230 0355 -
June 2,1995
- l. 5,tr. John C. Hoyle Secretary (J.S. Nuclear Regulatory Commission Washington, DC 20555-0001 j 1
I Attention: Docketing a;id Service Branch i
Dear Mr. Hoyle:
Subject:
Comments on Proposed Rule - 10 CFR Parts 50,52, and 100, " Reactor Site Criteria '
Including Seismic and Earthquake Engineering Criteria for Nuclear Plants" (60 Federal Register 10810 - February 28,1995)
We believe that the proposed rulemaking, associated regulatory guides, and standard review plans should contain unambiguous language, and clear and consistent technical guidance to establish a stable licensing basis for the siting of future nuclear power plants. And, we further believe that a stable licensing basis will create the environment for a successful rebirth of nuclear power plant construction.
l As a major NSSS vendor who has a major stake in the success of nuclear power industry, Westinghouse personnel over the past four years have participated in industry advisory committees and task forces associated with NRC's proposed rulemaking referenced above.~ Through this participation, many Westinghouse concerns regarding the proposed rulemaking have been addressed.
Specitically, the concerns were captured in the letter from the Nuclear Energy Institute (W.H. Rasin to J.C. Hoyle) dated May 12,1995 and in the letter from EPRI ALWR Programs (A. Machiels to l J.C. Hoyle) dated May 12, 1995.
Since the proposed rule revision will have an enormous impact on the future of nuclear power, we are augmenting the comments provided by the industry associations with our own comments. Our l
comments are provided in Enclosure 1.
i, We want to commend the NRC for addressing industry concerns in a very professional manner j' through the previous round of comments on this proposed rule. We hope that the Staff will do an I
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eq'ntly diligentjob in addressing the concerns of the industry through this round. Westinghouse would be pleased to meet with the Staff to discuss any comments offered in this letter.
i Very truly yoers,
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fff N. J. Liparuto, h anal;er Nuclear Safety Regulatory and Licensi1g Activities Enclosure i l
l ec: James S. Taylor, NRC j William T. Russell, NRC l i
David L. Morrison, NRC Leonard Soffer, NRC Andrew J Murphy, NRC i
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a ENCLOSURE 1 l i
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- Comments on Proposed Rule - 10 CFR Parts 50,52, and 100, " Reactor Site Criteria Including ,
Seismic and Earthquake Engineering Criteria for Nuclear Plants"
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NON-SEISMIC
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j' Comments on the proposed revision (59 Federal Register 52255, October 17,1994) to paragraph !
(a)(1) of part 50.34 of the Code of Federal Regulations.
i 1.1 Comments on the identification of the two hour interval to be used for calculating the dose at
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- 'the Exclusion Area Boundary 1
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j The proposed time period for calculating the Exclusion Area Boundary (EAB) dose is "any 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ,
j period following the onset of the postulated fission product release." Since the dose calculated over ,
i the time interval has value only relative to the potential for an individual to be exposed, the dose interval should bear a relationship to the presence of a population in the vicinity to the plant.
j Presently, EAB doses are calculated based on the assumption that the people in the low population .
zone are at the site boundary for a two hour period at the beginning of the accident, thus conservatively calculating the potential dose during the two hour interval over which evacuation of. ;
l this zone is assumed to take place. I j.
- With the implementation of the shurce term described in NUREG-1465, " Accident Source Terms for .
Light-Water Nuclear Power Plants," February 1995, the release of activity from the core is modeled - ;
i as occurring over a period of time instead of the instantaneous release assumed in Regulatory Guides .
1.3 and 1.4. This creates the likelihood that the calculation of the dose over the 0 to 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> time ,
! interval will not result in the most conservative determination. Additionally, the development of !
l passive plant designs has demonstrated that it is feasible to design plants to substantially delay the
, onset of core damage in the event of an accident. Instead of core damage initiating at the very i i beginning of the postulated large break Loss-of-Coolant Accident, it has been shown that the core
- 1. damage will be delayed for approximately an hour. This is a substantial improvement in plant safety t relative to currently operating plants. Theoretically, it would be possible to design a plant such that
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the onset of core damage would be more than two hours after accident initiation in this instance, a two hour dose calculated from the beginning of the accident would not be significant since the only '
radioactive material that would be available for release would be the activity from the reactor coolant
- which would enter the containment building as a result of the accident.
i
! With the " sliding dose window" concept, the interval over which doses would be calculated is not 4 linked to any specific occurrence, not to the beginning of the accident, not to the onset of the gap a release phase, and not to the onset of the core melt phase. Specifying that the interval for the EAB dose determination should be the two hours over which the highest doses would be accumulated is j conservative but, since there is no direct link to any particular aspect of the accident sequence, there
! is a sense of the arbitrary that detracts from the technical authority that should be present in this i document. The " sliding dose window" ignores the dose that would oe accumulated during the time
] period between the accident initiation and the two hour interval of highest dose. It could, of course, j be argued that the population in the vicinity of the plant leaves but that other members of the public i initially at a far distance from the plant site choose to approach the plant during the time of the site j emergency and at the precise time interval when they will accumulate the maximum dose. While E ' theoretically ponible, this is not'an appropriate model.
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A more reasonable approach would be to modify the use of the two hour dose concept, replacing it )
with a time interval of two hours starting at the onset of core damage plus the time interval between . :
accident initiation and the onset of core damage. This has the advantage that it is linked to the - i beginning of the accident and thus has a rational connection with the concept of notification of the public and their evacuation ~ ' It does not ignore the dose accumulation that would occur prior to core damage. It also has the regulatory advantage in that the EAB dose calculation is not susceptible to !!.
being made trivial due to an extensive delay in reaching the beginning of core degradation.
ne proposed use of a " sliding dose window" attempts to address the issue of evaluating the t capabilities of the containment and other safety features to limit release of activity to the environment - ,
but, as discussed above, in its attempt to capture the period of greatest activity release, it introduces . 1 distortions into the determination of potential dose to the public. The evaluation of the ability of the :
plant to limit accident releases to the environment should encompass a sufficient portion of the accident duration to be said to characterize the event. For the postulated large break LOCA with core' ;
melt, an appropriate time interval would be 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> since, after this point, the accident is essentially l complete. There would be continuing minor releases of activity to the environment but these would - l not be significant when compared to the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.- The releases over this 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period would .
have to be demonstrated as being within some bounding value. One approach would be to specify that the EAB dose over the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> not exceed twice the identified dose limit for the "two hour" l EAB dose. The calculation of a 24 dose at the EAB should not be construed as the consideration of the presence of any person at the EAB for that period; the determination of dose is only 'a surrogate ;
used for evaluating the ability of the containment and other safety features to appropriately limit the '
release of activity to the environment. :
1.2 Comments on the TEDE (Total Effective Dose Eauivalent) dose limit The proposed revision specities a dose limit of 25 rem TEDE. From SECY-94-194, the approach I used in determining this limit is based on starting with the current dose criteria of 300 rem thyroid ,
and 25 rem whole body and determining the risk of latent cancer fatality associated with these - !
combined doses. The resultant risk of latent cancer fatality is 2.7 x 10- (2.5 x 10 2 from the whole body dose and 2.0 x 10-3 from the thyroid dose). It is noted that this risk determination neglects the ;
dose contribution from the remainder of the source term identified in TID-14844. ' That source term j includes, in addition to the iodines and noble gases, one percent of the solids in the tission product inventory. This portion of the source term was not taken into consideration in the calculation of whole body doses or thyroid doses because the contribution is not significant but it has been included ;
in the evaluation of in-containment radiation environment following the postulated accident. If these "other nuclides" are taken into consideration, the risk associated with the current dose methodology and source term is greater than the 2.7 x 10-2 that was determined and would lead to higher TEDE dose limits, in addition to assuming a risk factor of 2.7 x 10 2, SECY-94-194 also assumes that the dose is quickly ~
accumulated over the designated two hour interval, thus justifying the risk coefficient of 10-3 per rem instead of the risk coefficient of 5 x 10 dper rem that is associated with dose accumulation over the longer term (i.e., a period of days or more). Using this approach, the dose limit was calculated to be 27 rem but was reduced to 25 rem.
The calculation of 27 rem TEDE is based on the inappropriate assumption that the dose accumulation occurs over a short time. For the postulated two hour exposure interval, most of the anticipated dose wou'd be as a result of long term dose accumulation from the nuclide body burden. Only a small fraction of the total dose would be acute dose from the irimersion in the cloud of activity. This is especially true when taking into account the new sourn term set forth in NUREG-1465. Instead of basing the TEDE dose limit on the risk associated with short term dose accumulation, it should be _
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< 1 based on an appropriate combination of short and long term dose accumulation. . it is appropriate to assume that the acute dose is substantially below this value - say 10 rem. Based on studies for the :
AP600 plant, the acute dose is expected to be well below this value. This 10 rem gamma body dose '
translates to a 1 x 10-2 risk for latent cancer fatality and corresponds to 10 rem TEDE. Using a risk coefficient of 5 x 10 4per rem, the additional allowable TEDE dose that could accumulate over the !
long term without exceeding a risk of 2.7 x 10 2 would be 34 rem. The total is thus 44 rem TEDE. 1 i
However, this approach still does not accurately reflect the dose limit that is associated with the -
identified level of risk. . As indicated in SECY-94-194. in the original determination of the level of . j risk, the risk identified for the 300 rem thyroid dose is 2 x 10t Since 300 rem thyroid translates to 4
9 rem TEDE, the risk coefficient associated with this exposure is 2.2 x 17 per rem. For the postulated LOCA with core melt, more than half of the accumulated TEDE dose is expected to be I from dose to the thyroid. If it is conservatively assumed that only 25% of the non-acute dose is from. i thyroid dose (and thus,25% of the risk of 1.7 x 10 2 allocated for the non-acute dose is associated -
with the thyroid dose), this results in 19.3 rem TEDE associated with the thyroid dose and 25.5 rem TEDE associated with the remaining organ contributors. The resulting total of 55 rem TEDE could l be rounded down to 50 rem. This would be a more appropriate TEDE dose limit the 6: 21 rem ;
i specified in the proposed revision to 10 CFR 50. i 1.3 . Comments on the concent of " cans" for soecific orean doses ]
The idea of " caps" on the fraction of TEDE dose limit that could be associated with any specific organ is presented for discussion in SEC-94194. This concept of having specific organ dose limits in addition to the overall TEDE dose limit adds to the complexity of the approach and implies that the methodology used in generating the TEDE dose limit is not viewed as valid.. The TEDE dose limit is based on an identified level'of risk. If the basis for the TEDE dose limit is valid, there is no need for i
caps on specific organ doses. The use of limits on specific organ doses in addition to the overall TEDE dose limit would result in an unnecessary complication to the rule and would not reduce the risk to the public.
t SEISMIC Westinghouse supports NRC's decision to move guidance material from the proposed rule to the proposed regulatory guides. We also support NRC's decision to eliminate the " dual" deterministic and probabilistic analyses from the proposed rule. We, however, are concerned that retaining deterministic evaluations in SRP 2.5.2 will lead to confusion as to whether future licensees will also need to perform a deterministic analysis even though such an analysis is only recommended for NRC staff to perform as a " sanity" check. This additional deterministic analysis will add to instability in the licensing process and increase a future license applicant's seismic analysis costs (in defending its probabilistic analyses) without any additional benefit to public health and safety. We recommend that references to deterministic analyses be removed from all documentation associated with the proposed rule revision.
Westinghouse shares NEl's concern with respect to the type of analyses needed to construct a new plant on an existing approved site, using the proposed rule and associated proposed regulatory guides.
We also believe that site characterization analysis for existing sites should be contirmatory in nature and of " limited scope," rather than " full scope" as required for new sites.
There are several phrases that are used in the proposed rule that should be modified to make the rule more stable from a licensing point of view. Since these phrases nre used in several places, only the eewo o.cm 3
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! , phrase and not the location, are identified below. We suggest that these phrases and others that are similar in nature be modified as well.
- 1. "...certain structures, systems, and components" should read: "certain structures, systems, ;
and components as identified in Regulatory Guides xxx." By referencing the regtlatory guides, ,
the vagueness of the statement is eliminated from the rule and the description of the structures, ,
systems and components can be changed, if necessary, via changes to the regulatory guides. _
- 2. ". .without loss of capability to perform their safety functions" should read: ",;.without loss of ,
capability to perform their safety intended functions."_ .The components perform a function and not a " safety" function - components may be a part of a safety system or a non-safety system. l There are other sentences which have similar phraseology -- for example, item 3 below. These sentences should be similarly modified. l
- 3. "The required safety functions of structures, systems, and components must be assured..." I should read: "The required -setesy- functions of structures, systems, and components must be - l assured oer the ruidance orovided in Rerulatory Guide xxx..." The underlined phrase shows that the regulatory guide contains guidance as to how a future license applicant can provide l
" assurance."
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