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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20216J0681999-09-29029 September 1999 Forwards Rev 3 of AP600 Design Control Document, Incorporating Documentation Changes Resulting from Final Review Performed to Check Consistency of Implementation of Approved Design Change Proposals.With Summary of Changes ML20207G5411999-06-0808 June 1999 Discusses Request Made by Westinghouse on 981109 That Proprietary WCAP-14252,Rev 1,be Withheld from Public Disclosure.Determined Info to Be Proprietary & Will Be Withheld from Public Disclosure ML20195D5201999-06-0404 June 1999 Discusses Westinghouse Request That Change Pages Submitted on 980921 to WCAP-14292 Be Withheld from Public Disclosure. Determined Info to Be Proprietary & Will Be Withheld from Public Disclosure ML20196G2431999-05-21021 May 1999 Informs That USNRC Has Published in Fr Encl Notice of Proposed Rulemaking Re AP600 Design Certification Rule. Rulemaking Allows Applicants or Licensees to Construct AP600 Std Plant Design by Referencing Design Certification Rule ML20206G5411999-05-0505 May 1999 Forwards Draft Environ Assessment Re Proposed Certification of AP600 Std Plant Design.Environ Assessment Will Be Used as Basis for NRC Finding of No Significant Environ Impact Resulting from Certification of AP600 Design ML20205J3351999-04-0707 April 1999 Informs That USNRC Staff Has Completed Review of Rev 2 of AP600 Design Control Document,Verified That All of Changes in Rev 2 Are Acceptable & Determined That AP600 Dcd,Rev 2, Can Now Be Used in Proposed Design Certification Rule NSD-NRC-99-5827, Forwards Rev 2 to AP600 Design Control Document.Attachment 1 Provides Summary of Changes Made as Part of Mar 1999 Rev to AP600 Design Control Document1999-03-31031 March 1999 Forwards Rev 2 to AP600 Design Control Document.Attachment 1 Provides Summary of Changes Made as Part of Mar 1999 Rev to AP600 Design Control Document ML20205D3051999-03-25025 March 1999 Requests Amend to 920626 Application for Design Certification of AP600,including AP600 Ssar & AP600 Dcd,To Reflect Sale of CBS Commercial Nuclear Business to W ML20203C5481999-02-10010 February 1999 Forwards Rev 1 to AP600 Design Control Document (DCD) for Docket File.Dcd Provides Reference Basis for AP600 Design Certification ML20199H8671999-01-20020 January 1999 Forwards Comments on AP600 Design Control Document,Submitted by Westinghouse ML20199B1121999-01-0707 January 1999 Advises That Info Contained in NSRA-APSL-92-0268 & Containing Presentation Matl Used in 921209-10 Meeting,Marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA ML20198B4601998-12-14014 December 1998 Discusses W Ltr NTD-NRC-95-4556,dtd 950918,provided as Status Rept on Proprietary Matl Submitted to NRC to Support AP600 Design Review Effort.Proprietary Info in Encl Have Been Removed from AP600 Docket File & Being Returned ML20197G3501998-11-30030 November 1998 Forwards AP600 Design Control Document, Vols 1-12 for Docket File.Submittal Closes Confirmatory Items 1.5-1 & 1.5-2 from Sept 1998 Final SER Re Certification of AP600 Std Design ML20195E9331998-11-0909 November 1998 Requests That Rev 1 to WCAP-14252, AP600 Low-Pressure Integral Sys Test at or State Univ Final Data Rept, Vols I- Iv,Be Withheld (Ref 10CFR2.790) NSD-NRC-98-5806, Forwards non-proprietary Rev 1 to WCAP-14253 & Proprietary Rev 1 to WCAP-14252, AP600 Low-Pressure Integral Sys Test at or State Univ Final Data Rept. Proprietary Rept Includes Vols 1-4.Proprietary Info Withheld,Per 10CFR2.7901998-11-0909 November 1998 Forwards non-proprietary Rev 1 to WCAP-14253 & Proprietary Rev 1 to WCAP-14252, AP600 Low-Pressure Integral Sys Test at or State Univ Final Data Rept. Proprietary Rept Includes Vols 1-4.Proprietary Info Withheld,Per 10CFR2.790 ML20155G9021998-11-0303 November 1998 Advises That Info Contained in 981012 ltr,NSD-NRC-98-5795, Will Be Withheld from Public Disclosure,Per 10CFR2.790(b) (5) & Section 103(b) of AEA of 1954,as Amended ML20155G9271998-11-0202 November 1998 Forwards Copy of NRC Staff FSER for Westinghouse AP600 Design.Staff Completed Review of Design & Issued Final Design Approval & FSER on 980903.Without Encl ML20155G7591998-11-0202 November 1998 Forwards Copy of NRC Staff FSER for Westinghouse AP600 Design,Per Discussion at Sept 1997 Meeting.Staff Completed & Issued Final Design Approval of FSER on 980903.Without Encl NSD-NRC-98-5795, Informs That Figures from Rev 0 & Rev 3 of PRA Which Indicate Location of H Igniters Should Be Considered Proprietary.Nonproprietary Versions of AP600 General Arrangement Drawings Were Provided in Rev 7 of Ssar1998-10-12012 October 1998 Informs That Figures from Rev 0 & Rev 3 of PRA Which Indicate Location of H Igniters Should Be Considered Proprietary.Nonproprietary Versions of AP600 General Arrangement Drawings Were Provided in Rev 7 of Ssar ML20154A4091998-09-29029 September 1998 Advises That Certain Info Contained in Westinghouse Ltr NTD-NRC-95-4506,dtd 950713,submitting WCAP-14425,will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5).Figure 3-1 Will Be Placed Into Public Record ML20153G2521998-09-25025 September 1998 Advises That Proprietary Matl Discovered by NRC in NSD-NRC-97-4966 & Proprietary Matl Noted by W in NSD-NRC-98-5772 Will Be Withhheld from Public Disclosure Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 ML20153C1001998-09-15015 September 1998 Advises That Matls Re AP600 Notrump Final Validation Rept, WCAP-14807,marked Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended NSD-NRC-98-5788, Forwards Formal Transmittal of Correspondence Previously Sent Informally Over Period of 980702-0826.Index of Encl Matl Provided1998-09-15015 September 1998 Forwards Formal Transmittal of Correspondence Previously Sent Informally Over Period of 980702-0826.Index of Encl Matl Provided ML20151X4381998-09-15015 September 1998 Informs That Staff Has Decided to Accept Claim That Info in WCAP-14135,Rev 1 Is Proprietary & Will Be Withheld from Public Disclosure,Per W 980821 & 26 Ltrs ML20151X4041998-09-11011 September 1998 Discusses Revised Tier 2 Info for AP600 Design.Staff Revised Decision on Whether Fire Protection Should Expire at First Full Power Encl ML20151V1711998-09-0808 September 1998 Advises That Info Re Westinghouse AP600 Std Safety Analysis Rept Through Rev 4 & PRA Through Rev 5 Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5).Disposition of Ssar & PRA Proprietary Info Encl ML20151V2231998-09-0808 September 1998 Informs That NRC Determined That WCAP-14132 Encl in Westinghouse Ltr NTD-NRC-94-4244,dtd 940729 & Marked as Proprietary,Will Be Withheld from Public Disclosure,Per to 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 ML20151S9181998-09-0303 September 1998 Advises That Info Marked as Proprietary Re Westinghouse AP600 Design Ltrs Concerning Pxs Scaling & Pirt Closure Rept WCAP-14727,will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) ML20239A1481998-09-0303 September 1998 Forwards Notice of Issuance of Final Design Approval & Final SER for AP600.FDA Allows AP600 Design to Be Referenced in Application for Construction Permit or Operating License Under 10CFR50 or Application for Combined License ML20239A3111998-09-0303 September 1998 Forwards Final SER Which Summarizes Staff Safety Review of AP600 Design Against Requirements of Subpart B of 10CF5R52 & Delineates Scope of Technical Details Considered in Evaluating Proposed Design ML20151V8521998-09-0101 September 1998 Extends Invitation to Attend Ceremony on 980911,where NRC Will Present Final Design Approval for AP600 Std Nuclear Reactor Design to Westinghouse NSD-NRC-98-5781, Informs That W Determined That AP600 FSER Contains No Proprietary Info1998-09-0101 September 1998 Informs That W Determined That AP600 FSER Contains No Proprietary Info ML20151V2201998-08-31031 August 1998 Informs That EPRI Documents, GOTHIC Containment Analysis Package Qualification Rept, GOTHIC Containment Analysis Qualification Manual, & Listed Documents Dtd Sept 1993 Will Be Withheld from Public Disclosure ML20151V8431998-08-31031 August 1998 Extends Invitation to Attend Ceremony on 980911,where NRC Will Present Final Design Approval for AP600 Std Nuclear Reactor Design to Westinghouse ML20238F3241998-08-31031 August 1998 Advises That AP600 RAI Responses Encl in Westinghouse Ltrs NTD-NRC-95-4598,dtd 951117,as Modified by NSD-NRC-98-5776, Dtd 980826,marked Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) ML20238F5991998-08-31031 August 1998 Refers to W 980821 Revised Response to Insp Rept 99900404/97-01 That Contained All Substantive Info Provided w/DCP/NRC-1074 Ltr.Nrc Will Destroy DCP/NRC-1074,as Requested NSD-NRC-98-5783, Forwards non-proprietary Rev 2 to WCAP-14989, Accident Specification & Phenomena Evaluation for AP600 Passive Containment Cooling Sys1998-08-28028 August 1998 Forwards non-proprietary Rev 2 to WCAP-14989, Accident Specification & Phenomena Evaluation for AP600 Passive Containment Cooling Sys NSD-NRC-98-5782, Forwards Corrected Pages 4-28 Through 4-32 to Be Inserted in Rev 2 to non-proprietary WCAP-14953, AP600 Pxs Scaling & Pirt Closure Rept. Pages Were Originally Submitted W/Incorrect Header Which Stated 'W Proprietary Class 2.'1998-08-28028 August 1998 Forwards Corrected Pages 4-28 Through 4-32 to Be Inserted in Rev 2 to non-proprietary WCAP-14953, AP600 Pxs Scaling & Pirt Closure Rept. Pages Were Originally Submitted W/Incorrect Header Which Stated 'W Proprietary Class 2.' NSD-NRC-98-5778, Provides Commitment to Include Requested Changes Into AP600 Design Control Document.Discussion W/Vijuk on 980825 Re Disposition of Ltrs DCP/NRC1074,dtd 971016 & DCP/NRC1324,dtd 980403,formalized1998-08-27027 August 1998 Provides Commitment to Include Requested Changes Into AP600 Design Control Document.Discussion W/Vijuk on 980825 Re Disposition of Ltrs DCP/NRC1074,dtd 971016 & DCP/NRC1324,dtd 980403,formalized ML20237E4421998-08-27027 August 1998 Advises That Info Contained in Ltr DCP/NRC-0985,dtd 970821, Sought to Be Withheld,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended NSD-NRC-98-5777, Provides Revised Response to NRC Ltr Re W Requests for Withholding Info Re AP600 PCS Final Data rept,WCAP-14135 & WCAP-141381998-08-26026 August 1998 Provides Revised Response to NRC Ltr Re W Requests for Withholding Info Re AP600 PCS Final Data rept,WCAP-14135 & WCAP-14138 NSD-NRC-98-5776, Forwards Proprietary Revised Response to Ref NRC Ltr Re W Requests for Withholding Info Re AP600 Design Certification Test Program,Notrump Computer Code,Wcobra/Trac Computer Code & Loftran Computer Code.Proprietary Info Withheld1998-08-26026 August 1998 Forwards Proprietary Revised Response to Ref NRC Ltr Re W Requests for Withholding Info Re AP600 Design Certification Test Program,Notrump Computer Code,Wcobra/Trac Computer Code & Loftran Computer Code.Proprietary Info Withheld ML20237E0731998-08-26026 August 1998 Advises That Info in WCAP-14812,revs 1 & 2, Accident Spec & Phenomena Evaluation for AP600 PCS, Will Be Withheld from Public Disclosure ML20238F8031998-08-26026 August 1998 Requests That Proprietary W Revised Response to NRC Ltrs Re Requests for Withholding Info,Be Withheld from Public Disclosure IAW 10CFR2.790 NSD-NRC-98-5774, Informs That W Faxed Last Response Re Afser Open Item 1.1-1 to NRC on 980821.Last of Attachments Supporting Several of Responses Faxed to NRC Over Past Several Days Were Express Mailed to NRC on 980821.Responses Close Subject Open It1998-08-24024 August 1998 Informs That W Faxed Last Response Re Afser Open Item 1.1-1 to NRC on 980821.Last of Attachments Supporting Several of Responses Faxed to NRC Over Past Several Days Were Express Mailed to NRC on 980821.Responses Close Subject Open Item NSD-NRC-98-5773, Responds to Questions Raised in NRC 971022 & s Re Proprietary Info Contained in 970930 Summary of Meeting Held on 970804-15 Concerning Structural Design of AP600.Figure 12-24 of WCAP-14407 Still Considered Proprietary by W1998-08-21021 August 1998 Responds to Questions Raised in NRC 971022 & s Re Proprietary Info Contained in 970930 Summary of Meeting Held on 970804-15 Concerning Structural Design of AP600.Figure 12-24 of WCAP-14407 Still Considered Proprietary by W ML20237E7991998-08-21021 August 1998 Forwards non-proprietary Results of AP600 Design Assurance Review (Dar) That Was Commitment in W Response to NRC Insp Rept 99900404/97-02.Info Should Assist in Closing Nonconformances & Unresolved Item Identified in Insp Rept NSD-NRC-98-5771, Forwards non-proprietary Rev 2 to WCAP-14138, Final Data Rept for PCS Large-Scale Tests,Phase 2 & Phase 3. Submittal Satisfies Verbal Commitment to Revise non-proprietary Version of PCS Final Data Rept Made by W1998-08-21021 August 1998 Forwards non-proprietary Rev 2 to WCAP-14138, Final Data Rept for PCS Large-Scale Tests,Phase 2 & Phase 3. Submittal Satisfies Verbal Commitment to Revise non-proprietary Version of PCS Final Data Rept Made by W NSD-NRC-98-5769, Responds to NRC Ref Ltrs Re W Requests for Withholding Info. Info Provided as Proprietary in Ref 1 Has Either Been Moved from Ssar to Ref 3,which Includes non-proprietary Version of Rept or Made non-proprietary in Current Version of1998-08-21021 August 1998 Responds to NRC Ref Ltrs Re W Requests for Withholding Info. Info Provided as Proprietary in Ref 1 Has Either Been Moved from Ssar to Ref 3,which Includes non-proprietary Version of Rept or Made non-proprietary in Current Version of Ssar NSD-NRC-98-5772, Forwards non-proprietary & Proprietary Info in Response to NRC Ltrs Re W Requests for Withholding Info.Separate Ltr & Affidavit Justifying Proprietary Nature of Info,Encl. Proprietary Info Withheld,Per 10CFR2.7901998-08-21021 August 1998 Forwards non-proprietary & Proprietary Info in Response to NRC Ltrs Re W Requests for Withholding Info.Separate Ltr & Affidavit Justifying Proprietary Nature of Info,Encl. Proprietary Info Withheld,Per 10CFR2.790 1999-09-29
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20216J0681999-09-29029 September 1999 Forwards Rev 3 of AP600 Design Control Document, Incorporating Documentation Changes Resulting from Final Review Performed to Check Consistency of Implementation of Approved Design Change Proposals.With Summary of Changes NSD-NRC-99-5827, Forwards Rev 2 to AP600 Design Control Document.Attachment 1 Provides Summary of Changes Made as Part of Mar 1999 Rev to AP600 Design Control Document1999-03-31031 March 1999 Forwards Rev 2 to AP600 Design Control Document.Attachment 1 Provides Summary of Changes Made as Part of Mar 1999 Rev to AP600 Design Control Document ML20205D3051999-03-25025 March 1999 Requests Amend to 920626 Application for Design Certification of AP600,including AP600 Ssar & AP600 Dcd,To Reflect Sale of CBS Commercial Nuclear Business to W ML20203C5481999-02-10010 February 1999 Forwards Rev 1 to AP600 Design Control Document (DCD) for Docket File.Dcd Provides Reference Basis for AP600 Design Certification ML20197G3501998-11-30030 November 1998 Forwards AP600 Design Control Document, Vols 1-12 for Docket File.Submittal Closes Confirmatory Items 1.5-1 & 1.5-2 from Sept 1998 Final SER Re Certification of AP600 Std Design NSD-NRC-98-5806, Forwards non-proprietary Rev 1 to WCAP-14253 & Proprietary Rev 1 to WCAP-14252, AP600 Low-Pressure Integral Sys Test at or State Univ Final Data Rept. Proprietary Rept Includes Vols 1-4.Proprietary Info Withheld,Per 10CFR2.7901998-11-0909 November 1998 Forwards non-proprietary Rev 1 to WCAP-14253 & Proprietary Rev 1 to WCAP-14252, AP600 Low-Pressure Integral Sys Test at or State Univ Final Data Rept. Proprietary Rept Includes Vols 1-4.Proprietary Info Withheld,Per 10CFR2.790 ML20195E9331998-11-0909 November 1998 Requests That Rev 1 to WCAP-14252, AP600 Low-Pressure Integral Sys Test at or State Univ Final Data Rept, Vols I- Iv,Be Withheld (Ref 10CFR2.790) NSD-NRC-98-5795, Informs That Figures from Rev 0 & Rev 3 of PRA Which Indicate Location of H Igniters Should Be Considered Proprietary.Nonproprietary Versions of AP600 General Arrangement Drawings Were Provided in Rev 7 of Ssar1998-10-12012 October 1998 Informs That Figures from Rev 0 & Rev 3 of PRA Which Indicate Location of H Igniters Should Be Considered Proprietary.Nonproprietary Versions of AP600 General Arrangement Drawings Were Provided in Rev 7 of Ssar NSD-NRC-98-5788, Forwards Formal Transmittal of Correspondence Previously Sent Informally Over Period of 980702-0826.Index of Encl Matl Provided1998-09-15015 September 1998 Forwards Formal Transmittal of Correspondence Previously Sent Informally Over Period of 980702-0826.Index of Encl Matl Provided NSD-NRC-98-5781, Informs That W Determined That AP600 FSER Contains No Proprietary Info1998-09-0101 September 1998 Informs That W Determined That AP600 FSER Contains No Proprietary Info NSD-NRC-98-5782, Forwards Corrected Pages 4-28 Through 4-32 to Be Inserted in Rev 2 to non-proprietary WCAP-14953, AP600 Pxs Scaling & Pirt Closure Rept. Pages Were Originally Submitted W/Incorrect Header Which Stated 'W Proprietary Class 2.'1998-08-28028 August 1998 Forwards Corrected Pages 4-28 Through 4-32 to Be Inserted in Rev 2 to non-proprietary WCAP-14953, AP600 Pxs Scaling & Pirt Closure Rept. Pages Were Originally Submitted W/Incorrect Header Which Stated 'W Proprietary Class 2.' NSD-NRC-98-5783, Forwards non-proprietary Rev 2 to WCAP-14989, Accident Specification & Phenomena Evaluation for AP600 Passive Containment Cooling Sys1998-08-28028 August 1998 Forwards non-proprietary Rev 2 to WCAP-14989, Accident Specification & Phenomena Evaluation for AP600 Passive Containment Cooling Sys NSD-NRC-98-5778, Provides Commitment to Include Requested Changes Into AP600 Design Control Document.Discussion W/Vijuk on 980825 Re Disposition of Ltrs DCP/NRC1074,dtd 971016 & DCP/NRC1324,dtd 980403,formalized1998-08-27027 August 1998 Provides Commitment to Include Requested Changes Into AP600 Design Control Document.Discussion W/Vijuk on 980825 Re Disposition of Ltrs DCP/NRC1074,dtd 971016 & DCP/NRC1324,dtd 980403,formalized ML20238F8031998-08-26026 August 1998 Requests That Proprietary W Revised Response to NRC Ltrs Re Requests for Withholding Info,Be Withheld from Public Disclosure IAW 10CFR2.790 NSD-NRC-98-5776, Forwards Proprietary Revised Response to Ref NRC Ltr Re W Requests for Withholding Info Re AP600 Design Certification Test Program,Notrump Computer Code,Wcobra/Trac Computer Code & Loftran Computer Code.Proprietary Info Withheld1998-08-26026 August 1998 Forwards Proprietary Revised Response to Ref NRC Ltr Re W Requests for Withholding Info Re AP600 Design Certification Test Program,Notrump Computer Code,Wcobra/Trac Computer Code & Loftran Computer Code.Proprietary Info Withheld NSD-NRC-98-5777, Provides Revised Response to NRC Ltr Re W Requests for Withholding Info Re AP600 PCS Final Data rept,WCAP-14135 & WCAP-141381998-08-26026 August 1998 Provides Revised Response to NRC Ltr Re W Requests for Withholding Info Re AP600 PCS Final Data rept,WCAP-14135 & WCAP-14138 NSD-NRC-98-5774, Informs That W Faxed Last Response Re Afser Open Item 1.1-1 to NRC on 980821.Last of Attachments Supporting Several of Responses Faxed to NRC Over Past Several Days Were Express Mailed to NRC on 980821.Responses Close Subject Open It1998-08-24024 August 1998 Informs That W Faxed Last Response Re Afser Open Item 1.1-1 to NRC on 980821.Last of Attachments Supporting Several of Responses Faxed to NRC Over Past Several Days Were Express Mailed to NRC on 980821.Responses Close Subject Open Item ML20237E7991998-08-21021 August 1998 Forwards non-proprietary Results of AP600 Design Assurance Review (Dar) That Was Commitment in W Response to NRC Insp Rept 99900404/97-02.Info Should Assist in Closing Nonconformances & Unresolved Item Identified in Insp Rept ML20237D3161998-08-21021 August 1998 Requests That W Response to NRC Ltrs Re Requests for Withholding Info Be Withheld from Public Disclosure,Per 10CFR2.790 NSD-NRC-98-5773, Responds to Questions Raised in NRC 971022 & s Re Proprietary Info Contained in 970930 Summary of Meeting Held on 970804-15 Concerning Structural Design of AP600.Figure 12-24 of WCAP-14407 Still Considered Proprietary by W1998-08-21021 August 1998 Responds to Questions Raised in NRC 971022 & s Re Proprietary Info Contained in 970930 Summary of Meeting Held on 970804-15 Concerning Structural Design of AP600.Figure 12-24 of WCAP-14407 Still Considered Proprietary by W NSD-NRC-97-5370, Transmits Results of AP600 Foake Design Assurance Review as Requested in NRC .Info Is Being Provided to Close Unresolved Item Identified in Insp Rept 99900404/97-011998-08-21021 August 1998 Transmits Results of AP600 Foake Design Assurance Review as Requested in NRC .Info Is Being Provided to Close Unresolved Item Identified in Insp Rept 99900404/97-01 NSD-NRC-98-5763, Responds to NRC Ltrs Re W Claim for Treatment of Proprietary Info Submitted in .As Discussed W/Nrc on 980821, Info Contained in W Is self-critical Analysis of W QA Program & Therefore Falls Under Items of Affidavit1998-08-21021 August 1998 Responds to NRC Ltrs Re W Claim for Treatment of Proprietary Info Submitted in .As Discussed W/Nrc on 980821, Info Contained in W Is self-critical Analysis of W QA Program & Therefore Falls Under Items of Affidavit NSD-NRC-98-5772, Forwards non-proprietary & Proprietary Info in Response to NRC Ltrs Re W Requests for Withholding Info.Separate Ltr & Affidavit Justifying Proprietary Nature of Info,Encl. Proprietary Info Withheld,Per 10CFR2.7901998-08-21021 August 1998 Forwards non-proprietary & Proprietary Info in Response to NRC Ltrs Re W Requests for Withholding Info.Separate Ltr & Affidavit Justifying Proprietary Nature of Info,Encl. Proprietary Info Withheld,Per 10CFR2.790 NSD-NRC-98-5769, Responds to NRC Ref Ltrs Re W Requests for Withholding Info. Info Provided as Proprietary in Ref 1 Has Either Been Moved from Ssar to Ref 3,which Includes non-proprietary Version of Rept or Made non-proprietary in Current Version of1998-08-21021 August 1998 Responds to NRC Ref Ltrs Re W Requests for Withholding Info. Info Provided as Proprietary in Ref 1 Has Either Been Moved from Ssar to Ref 3,which Includes non-proprietary Version of Rept or Made non-proprietary in Current Version of Ssar NSD-NRC-98-5771, Forwards non-proprietary Rev 2 to WCAP-14138, Final Data Rept for PCS Large-Scale Tests,Phase 2 & Phase 3. Submittal Satisfies Verbal Commitment to Revise non-proprietary Version of PCS Final Data Rept Made by W1998-08-21021 August 1998 Forwards non-proprietary Rev 2 to WCAP-14138, Final Data Rept for PCS Large-Scale Tests,Phase 2 & Phase 3. Submittal Satisfies Verbal Commitment to Revise non-proprietary Version of PCS Final Data Rept Made by W ML20237D3551998-08-20020 August 1998 Requests That Proprietary Info Re W Response to NRC Ltrs Re Requests for Withholding Info Concerning AP600 Pxs Scaling & Pirt Closure Rept, WCAP-14727 Be Withheld from Public Disclosure IAW 10CFR2.790 NSD-NRC-98-5762, Forwards Proprietary Change Pages for Chapters 7 & 8,for Inclusion as Rev 2 of TR WCAP-14727,in Response to NRC Ltr Dtd 980714.Non-proprietary Rev 2 to TR WCAP-14953 Re AP600 Scaling & Pirt Closure Encl.Proprietary Info Withheld1998-08-20020 August 1998 Forwards Proprietary Change Pages for Chapters 7 & 8,for Inclusion as Rev 2 of TR WCAP-14727,in Response to NRC Ltr Dtd 980714.Non-proprietary Rev 2 to TR WCAP-14953 Re AP600 Scaling & Pirt Closure Encl.Proprietary Info Withheld NSD-NRC-98-5764, Responds to NRC Ltrs Re Requests for Withholding Info from Public Disclosure for W AP600 Design Ltr of 951117,dtd 960229.W Considers Matl Proprietary Since Matl Discusses Approach Used by W to Develop Analysis Models of Cctf Test1998-08-20020 August 1998 Responds to NRC Ltrs Re Requests for Withholding Info from Public Disclosure for W AP600 Design Ltr of 951117,dtd 960229.W Considers Matl Proprietary Since Matl Discusses Approach Used by W to Develop Analysis Models of Cctf Test NSD-NRC-98-5768, Responds to NRC Ref Ltrs Re W Requests for Withholding Info. Specific Info Considered non-proprietary or Proprietary Discussed1998-08-20020 August 1998 Responds to NRC Ref Ltrs Re W Requests for Withholding Info. Specific Info Considered non-proprietary or Proprietary Discussed NSD-NRC-98-5766, Provides Summary of 980813 Telcon W/Nrc Re W Explanation of Rationale Which Was Used to Determine What Info Was Considered to Be Proprietary in TR WCAP-148121998-08-20020 August 1998 Provides Summary of 980813 Telcon W/Nrc Re W Explanation of Rationale Which Was Used to Determine What Info Was Considered to Be Proprietary in TR WCAP-14812 NSD-NRC-98-5770, Responds to NRC Ltrs Re W Requests for Withholding Info.W Withdraws AP600 Rept Entitled, Wcobra/Trac Core Makeup Tank Preliminary Validation Rept, Since Rept Was Not Required by NRC to Make Safety Determination of AP6001998-08-20020 August 1998 Responds to NRC Ltrs Re W Requests for Withholding Info.W Withdraws AP600 Rept Entitled, Wcobra/Trac Core Makeup Tank Preliminary Validation Rept, Since Rept Was Not Required by NRC to Make Safety Determination of AP600 NSD-NRC-98-5760, Forwards Rev 25 to GW-GL-021, AP600 Ssar, Vols 1-11. Revised Tables of Contents,Change Page Instructions,List of Effective Pages,Document Cover Sheet & Change Roadmap Outlining Changes in Each Section Also Encl1998-08-19019 August 1998 Forwards Rev 25 to GW-GL-021, AP600 Ssar, Vols 1-11. Revised Tables of Contents,Change Page Instructions,List of Effective Pages,Document Cover Sheet & Change Roadmap Outlining Changes in Each Section Also Encl NSD-NRC-98-5761, Provides Written Confirmation That Identified Figure Is Not Considered Proprietary by W.Refs 1-5,discussed1998-08-19019 August 1998 Provides Written Confirmation That Identified Figure Is Not Considered Proprietary by W.Refs 1-5,discussed ML20237D2681998-08-18018 August 1998 Requests That Proprietary Informal Correspondence Be Withheld from Public Disclosure,Per 10CFR2.790 NSD-NRC-97-5046, Submits Rev 1 of W Ltr Originally Submitted 970917,which Transmitted Proprietary & non-proprietary Informal Correspondence.Rev Includes Notarized Affidavit as Part of Application for Withholding Info.Proprietary Info Withheld1998-08-18018 August 1998 Submits Rev 1 of W Ltr Originally Submitted 970917,which Transmitted Proprietary & non-proprietary Informal Correspondence.Rev Includes Notarized Affidavit as Part of Application for Withholding Info.Proprietary Info Withheld NSD-NRC-98-5759, Submits Response to NRC Ltrs Re Request for Withholding Info.Figure 8-19 Will No Longer Be Considered Proprietary by W1998-08-17017 August 1998 Submits Response to NRC Ltrs Re Request for Withholding Info.Figure 8-19 Will No Longer Be Considered Proprietary by W NSD-NRC-98-5756, Responds to NRC 980714 & 21 Ltrs Re Request for Withholding Proprietary Info That Was Not Clearly Identified Other than Being Marked W Proprietary Class 21998-08-14014 August 1998 Responds to NRC 980714 & 21 Ltrs Re Request for Withholding Proprietary Info That Was Not Clearly Identified Other than Being Marked W Proprietary Class 2 NSD-NRC-98-5757, Responds to Ref NRC Ltrs Re Request for Withholding Proprietary Info Re W AP600 Ltr.Per 980708 Telcon,W Has Reviewed TRs WCAP-13288 & WCAP-13289 & Considers None of Info to Be Proprietary1998-08-14014 August 1998 Responds to Ref NRC Ltrs Re Request for Withholding Proprietary Info Re W AP600 Ltr.Per 980708 Telcon,W Has Reviewed TRs WCAP-13288 & WCAP-13289 & Considers None of Info to Be Proprietary ML20151Z0971998-08-13013 August 1998 Requests That Proprietary Rev 5 to WCAP-14807, Notrump Final Validation Rept, Be Withheld from Public Disclosure, Per 10CFR2.790 NSD-NRC-98-5754, Forwards non-proprietary Versions of Revs 3-5 to WCAP-14808 & Proprietary Version of Rev 5 to WCAP-14807, Notrump Final Validation Rept for AP600, in Form of Replacement Pages. Proprietary Encl Withheld1998-08-13013 August 1998 Forwards non-proprietary Versions of Revs 3-5 to WCAP-14808 & Proprietary Version of Rev 5 to WCAP-14807, Notrump Final Validation Rept for AP600, in Form of Replacement Pages. Proprietary Encl Withheld NSD-NRC-98-5749, Forwards Rev 13 to AP600 PRA for Simplified Passive Advanced LWR Plant Program. Rev Represents Final Version of AP600 Pra.All NRC Comments Related to Rev 12 of AP600 PRA Have Been Resolved1998-08-13013 August 1998 Forwards Rev 13 to AP600 PRA for Simplified Passive Advanced LWR Plant Program. Rev Represents Final Version of AP600 Pra.All NRC Comments Related to Rev 12 of AP600 PRA Have Been Resolved NSD-NRC-98-5753, Responds to Ref NRC Ltrs & W Ltr Re Request for Withholding Proprietary Info Re AP600 Design Ltrs1998-08-13013 August 1998 Responds to Ref NRC Ltrs & W Ltr Re Request for Withholding Proprietary Info Re AP600 Design Ltrs NSD-NRC-98-5752, Responds to Open Item 1.1-2 Contained in 980501 Advance Final SER for AP600 Requesting Update of Comparison of AP600 to NRC Reviewed Version of Alwr Util Requirements Document. Changes Resulting from NRC Comments Re Plant Design,List1998-08-13013 August 1998 Responds to Open Item 1.1-2 Contained in 980501 Advance Final SER for AP600 Requesting Update of Comparison of AP600 to NRC Reviewed Version of Alwr Util Requirements Document. Changes Resulting from NRC Comments Re Plant Design,Listed NSD-NRC-98-5755, Forwards Rev 7 to Simplified Passive Advance Light Water Reactor Plant Program AP600 Tier 1 Matl, Incorporating Comments Received from NRC Technical Staff,As of 980812.Encl Closes Open Item 14.3-1 from Advanced Final SER1998-08-13013 August 1998 Forwards Rev 7 to Simplified Passive Advance Light Water Reactor Plant Program AP600 Tier 1 Matl, Incorporating Comments Received from NRC Technical Staff,As of 980812.Encl Closes Open Item 14.3-1 from Advanced Final SER ML20153D9491998-08-12012 August 1998 Submits Response to NRC Ltrs Re Requests for Withholding Info.Info Does Not Have Commercial Value & No Longer Considered to Be Proprietary by W NSD-NRC-98-5751, Submits Response to NRC Ltrs Re Requests for Withholding Info.Info Does Not Have Commercial Value & Is No Longer Considered Proprietary by W1998-08-12012 August 1998 Submits Response to NRC Ltrs Re Requests for Withholding Info.Info Does Not Have Commercial Value & Is No Longer Considered Proprietary by W NSD-NRC-98-5748, Forwards Rev 24 of AP600 Ssar.Revised Tables of Contents, Change Page Instructions,List of Effective Pages,Document Cover Sheet & Change Roadmap Outlining Changes in Each Section Also Encl.Rev Submitted Under Encl Oath1998-08-0707 August 1998 Forwards Rev 24 of AP600 Ssar.Revised Tables of Contents, Change Page Instructions,List of Effective Pages,Document Cover Sheet & Change Roadmap Outlining Changes in Each Section Also Encl.Rev Submitted Under Encl Oath NSD-NRC-98-5743, Forwards Table Which Compares Combined License (COL) Info Items Identified in AP600 Design Certification Application W/Col Action Items Identified in AP600 Advance Final SER Provided to W by NRC on 9805061998-07-31031 July 1998 Forwards Table Which Compares Combined License (COL) Info Items Identified in AP600 Design Certification Application W/Col Action Items Identified in AP600 Advance Final SER Provided to W by NRC on 980506 NSD-NRC-98-5733, Forwards Rev 6 to GW-GL-030, Simplified Passive Advance LWR Plant Program,AP600 Tier 1 Matl, Which Incorporates Comments Received from NRC Technical Staff as of 9807221998-07-27027 July 1998 Forwards Rev 6 to GW-GL-030, Simplified Passive Advance LWR Plant Program,AP600 Tier 1 Matl, Which Incorporates Comments Received from NRC Technical Staff as of 980722 NSD-NRC-98-5742, Forwards Rev 12 to AP600 PRA Rept. All NRC Open Items Related to AP600 PRA Have Been Resolved1998-07-24024 July 1998 Forwards Rev 12 to AP600 PRA Rept. All NRC Open Items Related to AP600 PRA Have Been Resolved 1999-09-29
[Table view] |
Text
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- Westinghouse Energy Systems Ba 355 Pmsbu@ Pemsylvania 15230-0355 Electric Corporation DCP/NRC1043 NSD-NRC-97 5334 Docket No.: 52 003 September 23,1997 l
Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: T. R. QUAY
- UBJECT: CilANGES TO SSAR CHAPTER 18 TO RESOLVE NRC COMMENTS
Reference:
Letter from NRC to Westinghouse (Roe to Liparulo), "lluman Factors Engineering issues Related to'AP600 Operator Workstations and Computerized Procedure System,"
dated September 16,1997.
Dear Mr. Quay:
Attached is a markp of SSAR Chapter 18 page changes resulting primarily from resolution of NRC lluman Factors Engineering (HFE) lYAAC review comments discussed during a telecon on August 25, 1997. Also, there are two changes in addition to those resulting from ITAAC review comment resolution:
- 1. Based on NRC feedback received during a telecon today, the text suggested to NRC by telefax on September 9,1997, is modif'ied as marked on the attached SSAR pages 18.8-2 and 13-2. This text clarifies that the computerized procedure system is not part of t'ae AP600 design scope that the NRC is being asked to approve.
- 2. On page 18.8-18, reference to a " single-step" safety system actuation is deleted to reflect ongoing resolution of fire protection issues.
With this submittal, the Westinghouse status for Open item Tracking System (OITS) item 5752 is
" Confirm-W" for Westinghouse to confinn incorporation of the attached SSAR changes into Revision j 17 of the SSAR. /
While not affecting SSAR Chapter 18, there are two remaining actions related to life: ,
)
I. During the telecon today, NRC requested that Westinghouse provide a formal response to the referenced letter; that response is forthcoming and is assigned OITS number 5790, p.D
-- - 2. NRC has the action to advise Westinghouse if changes related to the computerized procedure _
system, as discussed above, as required in SSAR Chapter 1.8. This is assigned OITS number
'5791.
~
9710010142 970923
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- . NSD-NRC-97 5334:- 2 September 23,1997 1
If you have any questions regarding this transmittal, please contact Robin K. Nydes at 412-374-4125.
A/s9kanager Brian A. McIntyre, h
, Advanced Plant Safety and Licensing
- jml Attachment
- cc
- J. M. Sebrosky, NRC (w/ Attachment) 4 J. P. Bongarra, NRC (w/ Attachment) i N. J. Liparulo, Westinghouse (w/o Attachment) i S. Rubin, NRC (w/ Attachment) ~
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- 18. H: man Fact:rs Engineerizg Figure 18.2 3 provides an overview of the Westinghouse human factors engineering process.
The figure summarizes the major activities of the human factors engineering program, their relative order, and the inputs and outputs for the major activities. The boxes in the diagram indicate major human factors engineering activities. The activities are presented in approximate chronological order, with the outputs of each activity ser ing as inputs to subsequent activities. The items listed below the activity boxes are the document outputs 1 J
from that human factors engineering activity. The human factors engineering process includes iterations considering the outcomes of subsequent analysis and design activities, design reviews, and testing. In this approach, design issues are addressed and resolved through the iterative stages of the human factors engineering process. Potential points of iteration are indicated in Figure 18.2-3. Further details on the activities, inputs, and output documents l
associated with the vnious elements of the human factors engineering program are provided in the sections corresponding to each human factors engineering element. ,
Figure 18.2 3 provides a program milestone schedule of human factors engineering tasks showing relationships between human factors engineering elements and activities, products, and reviews. Internal design reviews are performed at various points throughout the design process.
18.2.6 Combined License Information l The Combined License applicant referencing the AP600 certified design is responsible for the i execution of the NRC approved human factors engineering program as presented by I Section 18.2.
The Combined License applicant referencing the AP600 certified design is responsible for i designing the emergency operations facility, including specification of the location, in I accordance with the AP600 human factors engineering program.
18.2,7 References
- 1. NUREG-0711. " Human Factors Engineering Program Review Model," U.S. NRC,
- 2. WCAP 14645, " Human Factors Engineering Operating Experience Review Report For The AP600 Nuclear Power Plant." Med54n f 4 neder /ff6,
- 3. WCAP-.14694, " Designers Input to Determination of the AP600 Main Control Room Staffing Level." DAM ( M j (, ,
- 4. WCAP-14644, "AP600 Functional Requirements Analysis and Allocation."y Re554 j d Seff & er l11b,
- 5. Reason, J.T., " Human Error," Cambridge, U.K., Cambridge University Press,1990.
- 6. WCAP-14822, "AP600 Quality Assurance Procedures Supporting NRC Review of AP600 SSAR Sections 18.2 and 18.8," Revision 0, February 1997.
l Revision: 13
[ W85tillgh0US8 18.2-19 May 30,1997
, 18. Human Factors EEgineering
+
The process " state identification" activity, which aids the user in understanding the abnormal conditions and provides corrective action guidance. It guides the operating crew into the information display system.
He plant information system presents plant process information for use by the operators. The plant information system provides dynamic display of plant parameters and alarm information so that an understanding of current plant conditions and status is readily ascertained. He plant information system uses color graphic video display units located on the operations and control centers workstations to display plant process data. These displays provide information important to monitoring, planning, and controlling the operation of plant systems and obtaining feedback on control actions.
he computerized procedure system has a mission to assist plam operators in monitoring and controlling the execution of plant procedures. He computerized procedures system is a software system. It runs on the hardware selected for the operations control centers. The computerized procedure system is accessible from the operator workstations in the main control room. Procedure development, as stated in Section 13.5 and 18.9,is the responsibility of the Combined License applicant. A procedure writer's guide is developed as part of the human system interface design implementation plan for the computerized procedure system.
He writeri guide is the design guidelines document for the computerized procedure system.
Information on the writer's guide and on the computerized procedure system is found in Reference 31. Man-in-the-loop concept tests (Reference 9) are planned as part of the human syrtem interface design implementation plan. Rese tests determine how effectively computerized procedures handle plant situations and whether computer-based procedures adequately support operator performance, he design of a backup to the computerized procedure system, to handle the unlikely event of a loss of the computerized procedure system, is developed as part of the human system interface design process. Design options include the use of a paper backup. The acceptability of the backup is evaluated through concept testing or by executing a walk through using the full scale mockup of the AP600 main control room.-na-sor=W' pad = symm i its balup - s Loui es pc.:
of.the integrated system validation phase-oRL. ir- iactuu mA.ew rd =M@ -
, y (Refee24)-
he mission of the controls in the main control room is to allow the operator to operate the plant safely under normal conditions, and to maintain it in a safe condition under accident j conditions. The types of controls in the main control room include both discrete (dedicated) control switches and soft controls. The discrete control switches are controls dedicated to a
/ single function, with each switch having a single action. As shown in Figure 18.;-1, the soft
/ control units are control devices whose resulting actions are selectable by the operator. De instrumentation and control architecture uses both discrete control switches and soft control units. De soft control units are used to provide a compact altemative to the traditional control board switches by substituting virtual switches in the place of the discrete switches.
De final configuration of these elements is dependent upon the results of the human system interface design process described in subsection 18.8.1 below.
I i
The computerized procedure system is not part of the AP600 design scope that the Nuclear Regulatory Commission is being asked to approve. The acceptability of the computerized procedure system, and its backup, for application to the AP600 design will be d :rmined during the implementation of the AP600 verification and validation program (Reference 24) and reviewed as a part of an application for a combined license.
nghouse
[D}. 1884
- 18. H; man Factors Engineering room supports the operator's decision making process, and promotes the interaction with other plant personnel, while preventing distractions by non-operating personnel. De main control room provides the interfacing resources between the operation of the plant and the maintenance of the plant. Its areas include the main control area, the switching and tagging area, the shift supervisor's office, the shift supervisor's clerk's office, and the operations staff's area (see Figure 1.2 8). Habitability systems are described in Sections 6.4 and 9.4 18.8.3.2 Main Control Area Mission and Major Tasks ne mission of the main control area is to provide the support facilities necessary for the operators to monitor and control the AP600 efficiently and reliably. Figure 6.41 provides a view of the main control area. The main control area includes the reactor operator I workstations, the supervisort workstation, the dedicated safety panel and the wall panel 1
information system. De layout, size and ergonomics of the operator workstations and the wall panel information system depicted in this figure does not reflect the results of :he human system interface design implementation plan described in subsection 18.8.1, De actual size, shape, ergonomics and layout of the operator workstations and the wall panel information system is an output of the implementation plan.
He major task of the main control area is to provide the human system interface resources that determine the plant state and implement the desired changes to the plant state during both normal and emergency plant operations. De main control area provides alarms to alert the operator to the need for further investigation. Plant process data displays permit the operatur to observe abnormal conditions and identify the plant state. De controls enable the operator to execute actions. De process data displays and the alarms provide feedback to enable the operator to observe the effects of the control actions.
l Each reactor operator workstation contains the displays and controls to start up the plant, maneuver the plant, and shut down the plant. Reference 44 presents input from the designer to the Combined License applicant for the determination of the staffing level of the operating crew in the main control room. Each workstation is designed to be manned by one operator.
Here is sufficient space and operator interface devices for two operators. The physical 1- makeup of the# reactor operator workstations is identical. De human system interface resources available at each workstation are:
Plant information system displays a
Control displays (soft controls)
Alarm system support displays Computerized procedure displays
. Screen and component selector controls I ne supervisor workstation is identical to the reactor operator workstations, except that its controls are lockedeut. The supervisor workstation contains both intemal plant and extemal plant communications systems.
Revision: 13
{ Westinghouse 18.8-17 May 30,1997 l
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- 18. Husman Factors Engineering 4
l Upon failure of a reactor operator workstation, the failed workstation is locked out, and the supervisor workstation controls are unlocked. This modified wortstation configuration maintains independent, redundant workstations.
A dedicated safety panel is located in the main control area. De qualified data processing system visual display units and the dedicated safety system controls are provided in this panel.
4 Dese visual display ur.its are the only monitoring display devices in the main control room j tat are seismically qualified and provide the post. accident mot.itoring capabilities in accordance with Regulatory Guide 1.97. Dedicated system. level safety system control switches are located on the dedicated safety panel to provide the operators with' ;!: q -
' safety system actuation capabilities. A minimum inventory of these de e' sted displays and controls are presented in Section 18.12.
Deri is storage space for supplies, protective clothing and some spare parts. Cabinets are provided for necessary documents, and a drawing laydown area is providui for the operators' use, Restroom and kitchen facilities are provided for the main control room operations crew.
18.8.3.3 Switching and Tagging Area Mission and Major Tasks De mission of the switching and tagging sea is to provide an interface between plant maintenance and plant operations personnel. Figures 1.2 8 and 6.41 provide the layout of the switching and tagging area. De operations staff monitors and approves the state of systems, major components, and equipment. De maintenance snff is informed of
, maintenance required by the operations staff. De means for initiating, tracking, and logging maintenance work orders is provided.
De major task of the switching and tagging area is to ease the management and -
implementation of the switching and tagging operations. The switching and tagging area generates notifications that equipment is not available due to testing, maintenance, or equipment failure. Dese notifications alert plant operating personnel to the unavailability of equipment. Notifications are provided to plant maintenance personnel, alerting them that operating personnel are aware of the equipment status. De switching and tagging area facihtates a systematic and organized approach to removing equipment from senice as well as returning it to service.
18.8.3.4 Remote Shutdown Workstation Mission and Major Tasks De mission of the remote shutdown workstation is to prcvide the resources to bring the plant to a safe shutdown condition after an evacurion of the main control room. De remote shutdown workstation resources are based on an assumed evacuation of the main control room without an opportunity to accomplish tasks involved in the shutdown except reactor trip.
Subsection 7.4.3 discusses safe shutdown using the remote shutdown workstation, including design bases infermation.
Revision: 13 May 30,1997 18.8 18 T Westinghouse
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- 18. Iluman Fact:rs Engineering 18.8.3.7 Radwaste Control Area Mission and Major Tasks The mission of the radwaste control area is to provide a habitable area and the appropriate resources for the operation of the radwaste processing systems. These resources include alanns, displays, controls, and procedures. Dese resources are located in a control area outside of the main control room.
I 18.8.3.8 Local Control Mission and Major Taske gskhh D
. I The mission of local controlhs to provide the resources, outside of the main control room the remote shutdown room, and the radwaste control area for operations personnel to perform I monitoring and control activities. De capability to access displays and controls (controls as I
assigned by the main control room operaton) for local control and monitoring, from selected I
locations throughout the plant, is provided. Activities that are implemented through local contro are reviewed to verify that their removal from the main control room is consistent with the o. rator staffing and performance considerations. Human system interface locations are provi ed for single task operations such as the operation of a manual valve.
i 18.8.3.9 h tknd Emergency uperations Facility l
I As stated in subsection 18.2.6, the Combined License applicant is responsible for designing 1 the emerpncy operations facility, including specification of the location, in accordance with I the AP600 human factors engineering program.
18.8.4 Human Factors Design for the Non. Human System Interface Portion of the Plant 18.8.4.1 General Plant Layout and Design ne AP600 design process incorpo ates a human engineering approach to operations ar<t maintenance. Maintainability design guidelines and human factors and as low as reasonably-achievable (ALARA) checklists are used to meet the requirements of a human engineered environment. The design objectives include reducing worker exposure and eliminating unnecessary inspection and maintenance tasks.
18.8.4.1.1 Maintainability Design features such as component selection, layout and standardization increase the probability that targeted repair times are achieved. nese features coupled with a preventative maintenance prognm help the AP600 meet its objectives for operation and maintenance.
Design requirements from the utility industry and industry design pixtices establish criteria for layout, changeout, and replacement for parts and components; access for major pieces of equipment; and vehicle passage.
Critical path outage models are prepared for the AP600. A typical refueling and maintenance outage schedule is used by design engineen. The modelindicates maintenance windows for Revisiont 13 May 30,1997 18.8 20 3 W85tingh00S8
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- 18. II: man Factors Enginnring 18.8.6 References
- 1. American National Standards Institute, ANSI HFS-1001988, "American Standard for Human Factors Engineerins of Visual Display Terminal Workstations," Santa Monica.
Califomia.1988.
- 2. CEl/IEC 964, Design for Control Rooms of Nuclear Power Plants," Intemational Electrotechnical Commission, Geneva, Switzerland,1989.
- 3. NUREG 0899, " Guidelines for the Preparation of Emergency Operating Procedures,"
U.S. Nuclear Regulator Commission, Washington, D.C., August 1982.
- 4. NUREG 1358, " Lessons Learned from the Special Inspection Program for Emergency "
U.S. Nuclear Regulatory Commission, Washington, D.C., April 1989.
- 5. NUREG 0700, " Human System Interface Design Review Guideline," Rev.1. U.S.
Nuclear Regulatory Commission, Washington, D.C., February 1995. (Draft Report)
- 6. NUREG/CR 5908, " Advanced Human System Interface Design Guidelines," U.S.
Nuclear Regulatory Commission, Washington, D.C., July 1994.
- 7. NUREG/CR 6105, " Human Factors Engineering Guidelines for the Review of Advanced Alarm Systems," U.S. Nuclear Regulatory Commission, Washington, D.C., September 1994.
- 8. U.S. Department of Defense, ' Human Engineering Guidelines for Management Information Systems," DOD HDBK 761A, Office of Management and Budget, Washington, D.C.,1990.
- 9. WCAP 14396, " Man in The Loop Test Plan Description," Revision 2, January 1997,
- 10. AP600 Document Number OCS J1-008, " Effects of Control Lag and Interaction Mode on Operators' Use of Soft Controls," Sperb S,17.4.- Mfs g s,@cr $qq
- 11. Hoecker, D.G. and Roth, E. M., " Man-Machine Design and Analysis System (MIDAS)
Applied to a Computer Based Procedure Aiding System," Westinghouse STC Report ISW5- CHICR P2, May 25,1994; also in " Proceedings of the Human Factors and Ergonomics Society 35th Annual Meeting," October 1995.
- 12. Hoecker, D.G. and Roth, E. M., " MIDAS in the Control Room: Applying a Flight Deck Cognitive Modeling Tool to Another Doinain," Westinghouse STC Report ISWS-CHICR P3, September 26, 1994: also in RAF Institute of Research and Development, " Proceedings of the Third Intemational Workshop on Human-Computer Teamwork " Cambridge, UK, September 26,1994.
Revision: 13 May 30,1997 18.8 24 3 Westinghouse
is, iluman Facion Engineering
- 42. U.S. Department of Defense,1989. "htilitary Standard 1472D; Human Engineenng Design Cntena for hiilitary Systems, Equipment and Facilities," (Washington, D.C., U.S.
Department of Defense).
- 43. American National Stand'.rds institute,1988 " ANSI /HF 100-1988 Amencan National Standard for Human Fa: tors Engineering of Visual Display Terminal Workstations,"
(Sants hionica. CA. Human Factors Society, American National Standards Institute).
- 44. WCAP 14694, "D,ejigner's input To Determination of the AP600 hiain Control Room Staffing Level"y Kf 49iq ()j Ji /f16,
- 45. WCAP 14701, " Methodology and Results of Defining Evaluation issues for the AP600 I
Human System Interface Design Test Program." Revision 1 May 1997.
- 46. Reid. O. B. and Nygren T. E.,1988, "He Subjective Workload Assessment Technique:
A Scaling Procedure for Measuring Mental Workload," also in Hancock, P. A., and Meshkati. N., (eds.), " Human Mental Workload," (Amsterdam, Nonh Holland).
- 47. Hart, S. O., and Stavel nd, L. E.,1988, " Development of NASA TLX: Results of Empirical and neoretict Research," also in Hancock, P. A., and Meshkati, N., (eds.),
" Human Mental Workload," (Amsterdam, North Holland).
Revision: 13 3 Westinghouse 18.8 2; May 30,1997
, _U
"1'4:$mt
, 18. Human Facton Engineering Table 18.12.21 (Sheet 1 of 2) htINIhtUh1 INVENTORY h
- xse.hf_ficH x *.. . Control Display Alarram Neutron flus x x Neutron flux doubling x
Startup rate x x RCS pressure x x Wide range iT, x Wide range Tg x x RCS cooldown rate compared to the limit x x based on RCS pressure Wide range Tcold compared to the limit x x ba.ted on RCS pressure Change of RCS temperature by more than x
5'F in the last 10 minutes Containment water lesel x x Containment pressure x x Pressurizer water level x x Pressurizer water level trend x Pressurizer reference leg temperature x Reactor venel . Hot leg water level x x Pressuriter pressure x Core exit temperature x x RCS subcooling x x RCS cold overpressure limit x x
, IRWST water level x x PRHR flow x x PRHR outlet temperature .t x PCS storage tank water level x PCS cooli.,g flow x IRWST to RNS suction valve status x x Remotely op33ted containment isolation x valve status Containment area high range radiation level x x Containment nressure (extended range) x Containment nydrogen concentration x CMT levelm x
Revision: 13
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I
. 18. Iluman Factors Engineering Table 18.12.21 (Sheet 2 of 2) i MINIMUM INVENTORY Orseffhien \
- Prr :u.- Control Display Alarm
- Manual safeguards actuation x Manual CMT actuation x Manual main control room emergency x habitability system actuation
- I Manual ADS actuation (13 and 4) x Manual PRHR actuation x Manual containment cooling actuation x Manual IRWST injection actuation x Manual containment recirculation actuation x Manual containment isolation x Manual main steamline isolation x Manual feedwater isolation x M?mual containment hydrogen igr. iter x (nonsafety related) d21SE
- 1. Although this parameter does not satisfy any of the selection criteria of subsection 18.12.2 its importance to manual actuation of ADS justifies its placement on this list.
- 2. These parameters are used to generate visual alerts (safety related displays for the main control room; nonsafety-related displays for the remote shutdown workstation) that identify challenges to the critical safety functions.
- 3. "Ihese instruments are not required after 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. (Subsection 7.5.4 includes more information on the class IE valve position indication signals, specified as part of the post accident monitoring instrumentation.)
- 4. This manual actuation capability is not needed at the remote shutdown workstation.
Revision: 13 May 30,1997 18.12 10 Y Westinghouse
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- 13. Conduct of Operation for the high level requirements for the technical suppon center and the operauonal suppon center. See Section 7.5 for identification of plant variables that are provided for interface to the emergency planning areas.
Communication interfaces among the main control room, the technical suppon center and de l
emergency planning centers are the responsibility of the Combined License applicant.
13.3.1 Combined License Inforrr.ation item j l
Combined License applicants referenting the AP600 certified design will address emergency !
1 planning including post.72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> hetions and its communication interface.
13.4 Operational Review This section is the responsibility of the Combined License applicant.
13.4.1 Combined License Information item Combined License applicants referencing the AP600 certified design will address each operational review.
13.5 Plant Procedures Plant procedures are the responsibility of the Combined License applicant. References to applicable combined license information are included in Section 1.8. This includes, for example, reference to guidelines on inservice inspection in Chapters 3 and 6, and initial testing in Chapter 14.
Reference 2 provides input to the Combined License applicant for the development of plant operating procedures, including information on the development and design of the AP600 emergency response guidelines and emergency operating procedures. Also included in Reference 2 is information on the computerir.ed procedure system, which is the human system interface that allows the operators to execute the plant procedures.
13.5.1 Combined Lkense Information Item ,
Combmed License applicants referencing the AP600 cenified design will address plant procedures including the following: .
- Emergency opersion ne computerized procedure system is not part of the AP600 design scope that the Nuclear Regulator)
Commission is tving asked to approve. De acceptability of the computerized procedure system, and its backup, for appheation to the AP600 design will be determined during the implementation of the AP600 verification and validation program (see SSAR Section 18.8) and reviewed as a past of an g pplication for a combined license.
August 8,1997 13 2 3 W85tingh00S4