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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217B3331999-10-0707 October 1999
Responds to 990825 Telephone Call Re Presense of Polychlorinated Biphenyl Wastes at Plant,Unit 1
ML20216J0681999-09-29029 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
ML20212F4481999-09-17017 September 1999
Forwards NRC Form 536 Containing Currently Proposed Site Specific Operator Licensing Exam Schedule & Estimates of Number of Applicants for Generic Fundamentals Exams Through Cy 2003
ML20212F7051999-09-14014 September 1999
Forwards Rev 19 to Ipn,Units 1 & 2 Physical Security Plan. Plan Withheld,Per 10CFR2.790(d) & 73.21
ML20211N0681999-09-0202 September 1999
Informs That Commission Requested Publication of Notice of Consideration of Issuance of Amend to Fol,Proposed NSHC Determination & Opportunity for Hearing. Amend Changes Senior Reactor License Requirement for Operations Manager
ML20211H6291999-08-26026 August 1999
Forwards NPDES Discharge Monitoring Rept for July 1999 for Indian Point,Units 1,2 & 3. Rept of Noncompliance Is Attached for Noncompliance Which Occurred at Unit 3
ML20211H6051999-08-18018 August 1999
Forwards Rev 8 to Security Force Training & Qualification Plan, for Indian Point 3 Nuclear Power Plant.Rev Facilitates Transition of Duty Weapons Carried by Security Force Members from Revolvers to Semiautomatic Pistols
ML20211E1531999-08-18018 August 1999
Forwards Semi Annual fitness-for-duty Program Performance Data for 990101-990630,IAW 10CFR26.71(d)
ML20211A9241999-08-11011 August 1999
Informs That IPS Currently Estimates,That Approx Two Licensing Actions Will Be Submitted to NRC During Remainder of 1999 NRC Fiscal Yr & Approx Ten Will Be Submitted During 2000 NRC Fiscal Yr
ML20210M7251999-07-26026 July 1999
Forwards Projection of Ability to Pay Retrospective Premium Adjustment for Period of Aug 1999 to 000731, Which Demonstrates That Ceny Will Have Sufficient Cash Flow &/Or Cash Reserve Available Throughout Period to Pay Premium
ML20210G8911999-07-20020 July 1999
Forwards Application for Amend to License DPR-5 for Proposed New TS 3.2.1.i,revising Senior Reactor License Requirement for Operations Manager
ML20209B6611999-06-29029 June 1999
Returns Recently Submitted Renewal Applications,Nrc Form 398,for Three Reactor Operators,As They Are Not Completed Properly.List of Docket Numbers & Block Numbers That Contain Incorrect Info & Block Numbers Not Completed.Without Encls
ML20196A6371999-06-15015 June 1999
Forwards Rev 19 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(d) & 73.21
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
ML20207D1861999-05-27027 May 1999
Informs That Effective 990328,NRC Office of NRR Underwent Reorganization.Mt Masnik Section Chief for Indian Point Station,Unit 1.JL Minns Remains Primary Contact for All Routine Licensing & Administrative Matters.Chart Encl
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
ML20205R1981999-04-15015 April 1999
Requests That Dept of Environ Conservation Modify SPDES Permit for IPS IAW Proposed Rev Attached & Described as Listed
ML20205R2961999-04-15015 April 1999
Forwards Copy of Proposed Change to Indian Point SPDES Permit NY0004472.Proposed Change Requests Permission to Add Permitted Outfall to Plant as Well as Change Character of Existing Outfall.Without Encl
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
ML20196K8111999-03-31031 March 1999
Forwards Decommissioning Funding Status Rept for Indian Point,Units 1 & 2 Through 981231
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
ML20205F9711999-03-25025 March 1999
Informs That Under Separate Cover,Licensee Transmitted to Ofc of Nuclear Regulatory Research Annual Rept of Results of Individual Monitoring at Indian Point,Units 1 & 2,for CY98
ML20204F7931999-03-17017 March 1999
Forwards Table Outlining Nuclear Property Insurance Which Has Been Placed on Behalf of Consolidated Edison Co of Ny, Inc.Insurance Covers Indian Point,Units 1 & 2
ML20204J9971999-03-0909 March 1999
Forwards Insp Rept 50-003/98-19 on 981130-990222.No Violations Noted
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
ML20203B9001999-02-0808 February 1999
First Partial Response to FOIA Request for Documents. Forwards Documents Listed in App a Already Available in PDR, Documents in App B Released in Entirety & Documents in App C Being Withheld in Part (Ref Exemption 6)
ML20202J6171999-02-0505 February 1999
Forwards Transcript from 990120 Public Meeting Held in Peekskill,Ny Re Decommissioning
ML20199H8671999-01-20020 January 1999
Forwards Comments on AP600 Design Control Document,Submitted by Westinghouse
ML20199H3731999-01-11011 January 1999
Informs That T Schmeiser,Con Ed Plant Manager for Plant Is Retiring,Effective 990111.AA Blind Will Assume Duties & Responsibilities of Plant Manager Until Replacement Named
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
ML20198E9561998-12-21021 December 1998
Forwards Order Prohibiting Involvement in NRC Licensed Activities Re Deliberate Misconduct in Violation of Regulation When False Info Was Provided to Two NRC Licensees
ML20198C2371998-12-15015 December 1998
Ltr Contract:Task Order 237, Review & Evaluation of Indian Point 3 Nuclear Power Plant Application for Conversion to Improved TS, Under Contract NRC-03-95-026
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
ML20198C4911998-12-11011 December 1998
Forwards Rev 18 to Physical Security Plan,Reflecting Organizational Changes & Incorporating Administrative Corrections & Clarifications.Encl Withheld
ML20198C3251998-12-11011 December 1998
Responds to ,Responding to NRC Ltr Re Concerns Raised About Potential Chilling Effect from Temp Denial of Site Access to Employee Raising Safety Issues to Util Senior Mgt
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
ML20155H2901998-11-0303 November 1998
Responds to to Lj Callan Expressing Concern About Continued Operation of Indian Point Nuclear Generating Station.Explanation Why NRC Do Not Think Revoking OLs for Indian Point Units 2 & 3 Justified,Provided
ML20155G7591998-11-0202 November 1998
Forwards Copy of NRC Staff FSER for Westinghouse AP600 Design,Per Discussion at Sept 1997 Meeting.Staff Completed & Issued Final Design Approval of FSER on 980903.Without Encl
ML20155G9271998-11-0202 November 1998
Forwards Copy of NRC Staff FSER for Westinghouse AP600 Design.Staff Completed Review of Design & Issued Final Design Approval & FSER on 980903.Without Encl
ML20155F9181998-10-28028 October 1998
Forwards Changes to SPDES Permit,Removing Requirement to Monitor Svc Boiler Blowdown for Phosphates,Eliminate Redundant Sampling of Oil or Grease Entering Flow Tributary to Floor Drains,Per Ts,App B,Section 3.2
ML20155D2791998-10-23023 October 1998
Forwards Corrected Pages for Indian Point Annual Radiological Environ Operating Rept for 1997
ML20154Q1761998-10-21021 October 1998
Second Final Response to FOIA Request for Documents. Documents Listed in App C Being Withheld in Part (Ref FOIA Exemption 7)
ML20154L8031998-10-16016 October 1998
Ack Receipt of & Payment in Amount of $55,000 in Electronic Funds for Civil Penalty Proposed by NRC in .Corrective Actions Will Be Examined During Future Insp
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
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
ML20212F4481999-09-17017 September 1999
Forwards NRC Form 536 Containing Currently Proposed Site Specific Operator Licensing Exam Schedule & Estimates of Number of Applicants for Generic Fundamentals Exams Through Cy 2003
ML20212F7051999-09-14014 September 1999
Forwards Rev 19 to Ipn,Units 1 & 2 Physical Security Plan. Plan Withheld,Per 10CFR2.790(d) & 73.21
ML20211H6051999-08-18018 August 1999
Forwards Rev 8 to Security Force Training & Qualification Plan, for Indian Point 3 Nuclear Power Plant.Rev Facilitates Transition of Duty Weapons Carried by Security Force Members from Revolvers to Semiautomatic Pistols
ML20211E1531999-08-18018 August 1999
Forwards Semi Annual fitness-for-duty Program Performance Data for 990101-990630,IAW 10CFR26.71(d)
ML20211A9241999-08-11011 August 1999
Informs That IPS Currently Estimates,That Approx Two Licensing Actions Will Be Submitted to NRC During Remainder of 1999 NRC Fiscal Yr & Approx Ten Will Be Submitted During 2000 NRC Fiscal Yr
ML20210M7251999-07-26026 July 1999
Forwards Projection of Ability to Pay Retrospective Premium Adjustment for Period of Aug 1999 to 000731, Which Demonstrates That Ceny Will Have Sufficient Cash Flow &/Or Cash Reserve Available Throughout Period to Pay Premium
ML20210G8911999-07-20020 July 1999
Forwards Application for Amend to License DPR-5 for Proposed New TS 3.2.1.i,revising Senior Reactor License Requirement for Operations Manager
ML20196A6371999-06-15015 June 1999
Forwards Rev 19 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(d) & 73.21
ML20205R2961999-04-15015 April 1999
Forwards Copy of Proposed Change to Indian Point SPDES Permit NY0004472.Proposed Change Requests Permission to Add Permitted Outfall to Plant as Well as Change Character of Existing Outfall.Without Encl
ML20196K8111999-03-31031 March 1999
Forwards Decommissioning Funding Status Rept for Indian Point,Units 1 & 2 Through 981231
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
ML20205F9711999-03-25025 March 1999
Informs That Under Separate Cover,Licensee Transmitted to Ofc of Nuclear Regulatory Research Annual Rept of Results of Individual Monitoring at Indian Point,Units 1 & 2,for CY98
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
ML20204F7931999-03-17017 March 1999
Forwards Table Outlining Nuclear Property Insurance Which Has Been Placed on Behalf of Consolidated Edison Co of Ny, Inc.Insurance Covers Indian Point,Units 1 & 2
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
ML20199H3731999-01-11011 January 1999
Informs That T Schmeiser,Con Ed Plant Manager for Plant Is Retiring,Effective 990111.AA Blind Will Assume Duties & Responsibilities of Plant Manager Until Replacement Named
ML20198C4911998-12-11011 December 1998
Forwards Rev 18 to Physical Security Plan,Reflecting Organizational Changes & Incorporating Administrative Corrections & Clarifications.Encl Withheld
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
ML20155F9181998-10-28028 October 1998
Forwards Changes to SPDES Permit,Removing Requirement to Monitor Svc Boiler Blowdown for Phosphates,Eliminate Redundant Sampling of Oil or Grease Entering Flow Tributary to Floor Drains,Per Ts,App B,Section 3.2
ML20155D2791998-10-23023 October 1998
Forwards Corrected Pages for Indian Point Annual Radiological Environ Operating Rept for 1997
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
ML20155H3021998-09-24024 September 1998
Urges NRC to Revoke Operating Licenses for Indian Point Nuclear Generating Station,Units 2 & 3 & Not Renew OL for Unit 1
ML20154A1391998-09-22022 September 1998
Informs That Effective 980724,AA Blind Assumed Position of Vice President,Nuclear Power & Ja Baumstark Assumed Position of Vice President,Nuclear Power Engineering,Effective 980813
ML20153F0661998-09-18018 September 1998
Provides Response to Violations Noted in Insp Rept 50-286/98-05 & Proposed Imposition of Civil Penalty Dtd 980819.Corrective Actions:Existing Drawings for Spare Switchgear Cubicles Have Been Revised
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
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
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
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-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
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
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-98-5770, 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-98-5766, 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
1999-09-29
[Table view] |
Text
, . -._ _ - . .-. . . - - - ,- . -
i'
( h j
-Westinghouse - Energy Systems Box 35h Pittsburgh Pennsylvania 15230 0355
__ Electric Corporation DCP/NRC1064 NSD NRC-97-5359 l Docket No.i 52-003 <
- October 2,1997 Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: T.R. QUAY
SUBJECT:
RESPONSE '10 RAls RELATED TO GENERIC COMMUNICATIONS De, r Mr, Quay:
1 2 Attached are the responses for RAls 650.1 through 650.8 (OITS # 5758 through f 765). These RAls
[ are related to generic issues and generic communications on valve testing and valve quali6 cation. The Westinghouse status for these issues will be ConGrm W pending revision to the SSAR and WCAP-13559. The SSAR changes will be included in Revision 17.
ii Please contact Donald A. Lindgren at (412) 374-4856 if you ha've any questions.
4ff Brian A. McIntyre, Manager W
- Advanced Plant Safety and Licensing jmi- Y
---U Attachment
/V ec: J. M. Sebrosky, NRC (w/ Attachment)
N. J.- Lipurato, (w/o Attachment)
. \\
9710070126 971002 "f PDR ADOCK 052000031 A PDR f 3414e wp
- c
NRC REQUEST FOR ADDITIONAL INFORMATION sp Question 650.1-Issue ll.D.l: Performance Testing of PWR Safety and Relief Valves As discussed in NUREG-0933, Issue II.D.1, addressed the requirements in NUREG-0737 for qualifi-cation testing of RCS safety, relief, and block valves under expected operating conditions for design-basis transients nd accidents, including ATWS. This issue was resolved by requiring licensees to conduct testing to qualify reactor coolant relief valves, safety valves, block valves, and associated discharge piping.
A safety and relief valve test program was conducted by the EPRI for a group of PWR licensees to respond to the staff recommendations in NUREG-0587 and as clarified in NUREG 0737. De purpose of the program was to develop sufficient documentation and test data so that the participating licensees could demonstmte compliance with the II.D.1 requirements. De results were documented in the EPRI repon, EPRI NP2628 SR, "EPRI PWR Safety and Relief Valve Test Report," December 1982. EPRI l also published a guide on how to apply the test results to the evaluation of plant specific valves. De
! staff used the test results documented in EPRI NP 2628 SR as a part of its acceptance criteria in its evaluations of the resolution of issue II.D.I for all current operating plants.
In Section 1.9.3 of the SSAR, item (2)(x), Westinghouse states that the AP600 design does not include power-operated relief valves and their associated block valves on the RCS He safety valve and discharge piping used will either be of similar design as those valves tested and documented in EPRI Repon NP 2770-LD_("EPRI/CE PWR Safety Valve Test Repon," December 1982), or will be tested in accordance with the guidelines of Issue II.D.1 in NUREG-0737.
In DSER Open Item 20.411, the staff requested that Westinghouse clarify an apparent inconsistency in the references to the EPRI test data in Sections 1.9.3 and 1.9.7 of the SSAR.- ne reference in both of these sections should be EPRI NP-2628-SR, which is the latest report that documents the EPRI test data. Westinghouse has not yet responded to this request through Revision 12 of the SSAR, -Here-fore, Issue II.D.I is not resolved t~or the AP600 design.
Response
The DSER write-up for the response to 10 CFR34.f.(2)(x) (NUREG-0737 Item II.D.1) in Section 20.4 states that reference to NP 2770-LD is acceptable. EPRI Report NP 2770-LD documents the specific test results of a number of valves from different valve manufacturers. Included in these reports is an identification of the valve designs tests. His is an appropriate reference for the commitment in the SSAR. A reference for the repon will be provided in the SSAR. EPRI repon NP2628-SR is more of a summary of the program.
650.M T Westinghouse
NRC REQUEST FOR ADDITIONAL INFORMATION
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SSAR Resision:
Revise the ikst paragraph of the response for (2)(x)in subsection 1.9.3 as follows:
The AP600 reactor coolant system design does not include power operated relief valves and their associated block valves. However, the safety valve and discharge piping used in the AP600 design will be either of design similar to those items tested by EPRI and documented in EPRI Report EPRI NP.
I 2770-LD (Reference 2) or will be tested in accordance with the guidelines of Item [lI.D.1] or l NUREG.0737.
l Revise Reference 2 in subsection 1.9.6 as follows:
1 2. Report NP 2770-LD, "EPRl/CE PWR Safety =d Rc!!cf-Valve Test Pregra n Safc:y =d Rc!!cf l Valw-Test Report," December 1982. !r.:c:i- Report, Apri! 1982, l
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- NRC REQUEST FOR ADDITIONAL INFORMATION ar 9.
Question 650.2 GL.87-06: Periodic verification of leak tight integrity of pressure isola' ion valves.
WCAP 13559, Revision 1. states that this generic letter is addressed in LCOs 3.4.8 and 3.4.9 of the plant TS in SSAR Chapter 16. Amendment 0 of SSAR Chapter 16 delded LCO 3.4.8. "RCS Pressure Isolation Valve (PlV) Leakage." LCO 3.4.9 is not applicable to PlV leakage. The staff has determined that the resolution of GL 87-006 will ultimately depend upon the resolution of issues identified in a May 28,1997, letter to Westinghouse entitled " Comment on the AP600 Technical Specifications related to pressure isolation valves".
Response
Letter DCP/NRC1009 dated August 29,1997 provided the response to the May 28,1997 NRC letter.
LCO 3.4.16 has been added in SSAR Revision 16 to provide for testing of pressure isolation valves PlVs in the technical specifications. Subsection 3.9.6.2.2 of the SSAR identifies that there is no '
maximum leakage requirement for AP600 PlVs. The AP600 includes design features to preclude a rupture in connecting systems due to pressurization through a closed isolation valve.
SSAR Revision: NONE WCAP 13559 Revision:
Revise the Comment for Generic Letter 87-M as follows:
I SSAR Chapter 16, LCO 3.4.16 3.4.8 r.d 3.4.9 -
T Westinghouse
NRC REQUEST FOR ADDITIONAL INFORMATION Question 650.3 GL-95-07: Pressure locking and thermal binding of safety related power operated gate valves.
WCAP 13559, Revision I states that this GL is not applicable because it is a procurement / surveillance issue. The staff does not agree. Although this GL was addressed to licensees of operating plants and plants under construction, the staff's position is that the concerns in this GL should also be addressed during the design stage. Therefore, the staff requests that if the AP600 design contains any safety-related power-operated gate valves, Westinghouse should add a discussion in the SSAR and WCAP-l'4559 to explain how the Requested Actions in GL-95-007 will be implemented.
Response
l SSAR Subsections 5.4.8.1.2 and 5.4.8.2 identify design provisions and qualification requirements to address pressure locking and thermal binding in gate valves. For example, solid wedge designs are
( not used and provisions for venting of heated, trapped fluid are provided when overpressurization of gate valves can result.
SSAR Resisiont NONE l WCAP 13559 Pevision:
l l Revise the Comment for Generic Letter 95-07 a* follows:
1 Net-AppheaNe-Procuitment S=ci!!=ce Issue SSAR Subsections 5.4.8.1.2 and 5.4.8.2 3-94-3 3 Westinghouse
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e NRC REQUEST FOR ADDITIONAL INFORMATION-jit "if Question 650.4 GL 96-05: Periodic verification of design-basis capability of safety related motor-operated valves.
This GL is not addressed in WCAP 13559 Revision 1. Since the staff has included GL 96-05 as a part of its evaluation of the AP600 inservice testing program, this GL should be added to WCAP.
13559, in a letter dated March 19,1997, in response to RAI 210.229, Westinghouse agreed to revise
- WCAP 13559 to add GL-96-05. Updating of WCAP 13559 is also tied to the resolution of DSER Open item 20.71.
Response
The inservice test plan for AP600 is outlined in subsection 3.9 ..d the requirements for preoperational testing is outlined in subsection 5.4.8.5 SSAR Revision: None WCAP 13559 Revision:
Add an entry for Generic Letter 96-05 as follows:
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Number Title Comment I 96 Periodic Verification of Design Basis SSAR subsections 3.9.6.2 and 5.4.8.5 i Capability of Safety-related Motor operated i Valves I
e T Westinghouse
- 1 NRC REQUEST FOR ADDITIONAL INFORI AATION i
Question 650.5 BL 81-02: Failure of gate-type valves to close against differeatal pressure.
In WCAP 13559 Revision 1. Westinghouse states that this bulletin is not applicable to the AP600 design because the issues involved procurement. The staff agrees that this bulletin was addressed to operating plants and plants under construction in 1981. However, since the subject of this bulletin led, in part, to the issuance of Generic Letter (GL) 89-10. " Safety-Related Motor Operated Valve Testing and Surveillance," the staff's position is that the basis for disposition of this issue should be the information in SSAR Section 3.9.6 relative to GL-8910. The staff has concluded that the commit-ments in SSAR Section 3.9.6 r.lative to inservice and qualification testing of motor-operated valves provides an acceptable basis to resolve this issue. Therefore, the Comment for Bulletin 81-02 in WCAP-13559 should be revised to reference the commitments to GL 8910 in SSAR Section 3.9.6.
Response
Bulletin 81-02 was written in response to results of tests of valves used as power operated relief valve block valves. The AP600 does not have power operated relief valves or associated block valves.
SSAR Subsections 5.4.8.1.2 and SA8.2 identify design provisions and qualification requiren.ents for safety related valves. These valves are shown by test, analysis or combination of both to operate over the range of design conditions. This includes opening or closing against pressure or flow as applicable. Schsection 3.9.6.2 outlines the inservice test plan requirements for valves.
In some cases the system design also minimizes the loads on the gate valves during closing. For example, as noted in subsection 6.3.2.2.8.5, the isolation valve in each pair of valves in the first three stages of the automatic depressurization system is sequenced to open before the control valve opens so that the gate valve does not open against full flow conditions. The control valve in each pair is not a gate valve.
SSAR' Revision: None WCAP.13559 Revision:
Revise the Comment for Bulletin 8102 as follows:
I Net-AppheuW-Procurement and Surveillance issue SSAR Subsections 3.9.6.2, 5.4.8.1.2 and 5.4.8.2 f3 Westinghouse
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NRC REQUEST FOR ADDITIONAL INFORMATION l
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Question 650.6 BL-88-08: Thermal stresses in piping connected to reactor cooling systems.
WCAP-13559 states that this bulletin is addressed in Sections 3.9.3.1.2 and 5.4.10.1 of the SSAR.
Sec: ion 5.4.10.1 does not contain this information and should be deleted from the " Comment" column for BL 88-003 in WCAP 13559. However, the staff has concluded that the information in SSAR Section 3.9.31.2 provides an acceptable basis for resolving BL 88-008 for the AP600.
Response
Section 3.9.3.1.2 includes a discussion of the issues raised in Bulletin 88-08 and the Supplements to Bulletin 83-08.
SSAR Revision: None WCAP.13559 Revision:
Rev the Comment for Bulletin 88 08 as follows:
I SSAR Subsection 5.4.10. ! , 3.9.3.1.2 Revise the Comment for Bulletin 88-08 supplements 1,2, and 3 as follows:
I SSAR Subsection 4-44043.9.3.1.2 T Westinghouse
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.s NRC REQUEST FOR ADDITIONAL INFORMATION Question 650.7 GL-89-G4: Guidance on developing acceptable inservice testing programs.
Westinghouse states that this generic letter is addressed in Sections 5.2.4 and 6.6 of the SSAR. The staffi evaluation and acceptance of the AP600 inservice testing program tvas based on the information in SSAR 3.9.6, Therefore, GL-89-004 is resolved for the AP600. SSAR Section 3.9.6 should be added in the " Comment" under GL 89-004 in WCAP 13559.
Response
The AP600 inservice testing program requirements are outlined in subsection 3.9.6 SSAR Revision: None WCAP 13559 Revision:
Revise the Comment for Generic Letter 89-004 as follows:
I SSAR Subsections 3.9.6.25.2.4,6.6
W wesineouse
.l NRC REQUEST FOR ADDITIONAL INFORMATION
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Question 650.8 GL 8910: Safety related motor operated valve testing and surveillance Westinghouse states that this generic letter is not applicable to the AP600 design because it involves procurement and surveillance issues: however, the generic letter is addressed in Section 3.9.6.2 of the SSAR. The staff's position is that this generic letter is applicable to the AP600. Therefore, the state-ment in the Comment" under GL-8910 should be revised. The staff's evaluation of the information
-in SSAR 3.9.6 relative to motor-operated valve testing and surveillance provides the basis for the staff to conclude that GL-8910 is resolved for the AP600.
Response: ,
! The AP600 inservice testing program requirements are outlined in subsection 3.9.6 I SSAR Revision: None l
WCAP 13559 Revision:
Revise the Comment for Generic Letter 89-010 as follows:
1 Nc: Applienb!c P:ceure:nc.: Testing and Surveillance Issue SSAR Subsection 3.9.6.2 T Westinghouse i
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