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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217C5661991-07-0101 July 1991 Forwards Rev Updating Fnmcp.Encl Withheld (Ref 10CFR2.790) NRC-91-3569, Forwards Proprietary SER Re Preliminary Design of Std Nuclear Steam Supply Ref Sys RESAR SP/90. Encl Withheld1991-02-12012 February 1991 Forwards Proprietary SER Re Preliminary Design of Std Nuclear Steam Supply Ref Sys RESAR SP/90. Encl Withheld ML20012E9261990-03-20020 March 1990 Forwards SP/90 Position on Severe Accident Policy Issues Presented by NRC During 900209 ACRS Full Committee Meeting NRC-89-3461, Forwards Proprietary & Nonproprietary Amend 3 to RESAR-SP/90 Pda Module 2, Regulatory Conformance1989-10-0303 October 1989 Forwards Proprietary & Nonproprietary Amend 3 to RESAR-SP/90 Pda Module 2, Regulatory Conformance ML20248H8461989-10-0303 October 1989 Requests That Proprietary Amend 3 to RESAR-SP/90 Pda Module 2, Regulatory Conformance, Be Withheld from Public Disclosure (Ref 10CFR2.790).Affidavit Encl ML20247H2791989-09-12012 September 1989 Grants Request for Withholding of Response to NRC Draft SER Open Issues 1-41 Re Review of RESAR SP/90 Pda Application, Per 10CFR2.790(b)(5) NRC-89-3453, Forwards Proprietary & Nonproprietary Responses to NRC Draft SER Open Issues 82-107 in Review of RESAR-SP/90 Pda. Responses Include Associated Text Changes That Will Be Made in Final Submittal to Draft Ser.Proprietary Rept Withheld1989-08-31031 August 1989 Forwards Proprietary & Nonproprietary Responses to NRC Draft SER Open Issues 82-107 in Review of RESAR-SP/90 Pda. Responses Include Associated Text Changes That Will Be Made in Final Submittal to Draft Ser.Proprietary Rept Withheld ML20247G2581989-08-31031 August 1989 Requests That Response to Draft SER Open Issue 82-107 Re RESAR-SP/90 Pda Be Withheld from Public Disclosure (Ref 10CFR2.790) NRC-89-3448, Forwards Westinghouse SP/90 Position on Selected Severe Accident Issues to Be Discussed During 890714 Meeting W/Nrc in Rockville,Md.Issue Topics Include Fire Protection, Intersys Loca,Midloop Operation & ATWS1989-07-11011 July 1989 Forwards Westinghouse SP/90 Position on Selected Severe Accident Issues to Be Discussed During 890714 Meeting W/Nrc in Rockville,Md.Issue Topics Include Fire Protection, Intersys Loca,Midloop Operation & ATWS ML20246H2151989-07-0606 July 1989 Approves Request to Withhold Amends 1a & 2 to Westinghouse Advanced PWR RESAR SP/90 Preliminary Design Approval Module 7, Structural/Equipment Design, (Ref 10CFR2.790) ML20245J8861989-06-28028 June 1989 Requests That Response to Draft SER Open Issues 1-41 Re RESAR-SP/90 Pda Be Withheld from Public Disclosure (Ref 10CFR2.790) ML20245J8821989-06-28028 June 1989 Forwards Proprietary & Nonproprietary Responses to NRC Draft SER Open Issues 1-41 Re RESAR-SP/90 Pda.Proprietary Response Withheld (Ref 10CFR2.790) NRC-89-3438, Forwards Nonproprietary Draft Responses to Open Issues 42-81 of Draft SER Re RESAR-SP/90 Preliminary Design Application1989-06-0909 June 1989 Forwards Nonproprietary Draft Responses to Open Issues 42-81 of Draft SER Re RESAR-SP/90 Preliminary Design Application NRC-89-3419, Forwards Draft Response to NRC Questions 730.1 - 730.4 Re RESAR-SP/90 Pda,Module 2, Regulatory Conformance1989-03-15015 March 1989 Forwards Draft Response to NRC Questions 730.1 - 730.4 Re RESAR-SP/90 Pda,Module 2, Regulatory Conformance ML20236B3751989-03-0909 March 1989 Forwards to Wj Johnson,Forwarding NRC Draft SER Re RESAR SP/90 on Listed Technical Areas.Ltrs Provided to ACRS Members of Progress in Reviewing Pda Application ML20236B3571989-03-0909 March 1989 Forwards Proprietary Draft SER Re Status of Review of Pda Application for RESAR SP/90.Encl Withheld (Ref 10CFR2.790) NRC-89-3400, Forwards Nonproprietary & Proprietary Amends 1a & 2 to Wapwr RESAR-SP/90 Module 7, Structure Equipment Design1989-02-14014 February 1989 Forwards Nonproprietary & Proprietary Amends 1a & 2 to Wapwr RESAR-SP/90 Module 7, Structure Equipment Design ML20235N4451989-02-14014 February 1989 Application for Withholding Proprietary Amends 1a & 2 to Wapwr RESAR-SP/90 Pda Module 7, Structural/Equipment Design, from Public Disclosure ML20195H1161988-11-22022 November 1988 Provides Guidance Re Scope of Design & NRC Review of RESAR SP/90 Design.Westinghouse Intends to Apply for Design Certification for RESAR SP/90 Design Currently Inhouse for Preliminary Design Approval Review ML20206F8681988-11-0808 November 1988 Requests Withholding Proprietary Rept from Public Disclosure Per 10CFR2.790 NRC-88-3382, Forwards Proprietary & Nonproprietary Amend 4 to RESAR-SP/90 Pda Module 5, Reactor Sys. Proprietary Rept Withheld (Ref 10CFR2.790)1988-11-0808 November 1988 Forwards Proprietary & Nonproprietary Amend 4 to RESAR-SP/90 Pda Module 5, Reactor Sys. Proprietary Rept Withheld (Ref 10CFR2.790) NRC-88-3365, Discusses Design Approval & Certification Programs for AP-600 & SP-90 Designs for Std Nuclear plants.SP-90 Plant Currently Being Evaluated by NRC & Completion of Safety Review & Receipt of SER Anticipated First Quarter 19891988-11-0101 November 1988 Discusses Design Approval & Certification Programs for AP-600 & SP-90 Designs for Std Nuclear plants.SP-90 Plant Currently Being Evaluated by NRC & Completion of Safety Review & Receipt of SER Anticipated First Quarter 1989 ML20195C7871988-10-26026 October 1988 Requests Withholding of Amend 2 to Westinghouse Advanced PWR RESAR-SP/90 Pda Module 4, RCS from Public Disclosure (Ref 10CFR2.790) NRC-88-3379, Forwards Proprietary & Nonproprietary Amend 2 to Westinghouse Advanced PWR RESAR-SP/90 Pda Module 4, Rcs. Proprietary Amend Withheld (Ref 10CFR2.790)1988-10-26026 October 1988 Forwards Proprietary & Nonproprietary Amend 2 to Westinghouse Advanced PWR RESAR-SP/90 Pda Module 4, Rcs. Proprietary Amend Withheld (Ref 10CFR2.790) NRC-88-3374, Forwards Response to NRC 880414 Questions 260.1-260.33 Re QA Program for RESAR-SP/90 Pda.Responses Reflect Discussions Between NRC & Westinghouse During Telcons & 880616 Meeting1988-10-25025 October 1988 Forwards Response to NRC 880414 Questions 260.1-260.33 Re QA Program for RESAR-SP/90 Pda.Responses Reflect Discussions Between NRC & Westinghouse During Telcons & 880616 Meeting ML20207J9441988-09-19019 September 1988 Requests Withholding of Proprietary Version of Amend 4 to RESAR-SP/90 Pda Module 1, Primary Side Safeguards Sys (Ref 10CFR2.790) NRC-88-3371, Forwards Proprietary & Nonproprietary Amend 4 to RESAR-SP/90 Pda Module 1, Primary Side Safeguards Sys. Application for Withholding & Affidavit Also Encl. Proprietary Amend 4 Withheld (Ref 10CFR2.790)1988-09-19019 September 1988 Forwards Proprietary & Nonproprietary Amend 4 to RESAR-SP/90 Pda Module 1, Primary Side Safeguards Sys. Application for Withholding & Affidavit Also Encl. Proprietary Amend 4 Withheld (Ref 10CFR2.790) NRC-88-3368, Forwards Proprietary & Nonproprietary Versions of Amend 3 to Wapwr RESAR-SP/90 Pda Module 3, Introduction & Site. Proprietary Version Withheld (Ref 10CFR2.790)1988-08-25025 August 1988 Forwards Proprietary & Nonproprietary Versions of Amend 3 to Wapwr RESAR-SP/90 Pda Module 3, Introduction & Site. Proprietary Version Withheld (Ref 10CFR2.790) ML20153F7131988-08-25025 August 1988 Requests Withholding of Amend 3 to Wapwr RESAR-SP/90 Pda Module 3, Radiation Protection (Ref 10CFR2.790) NRC-88-3364, Forwards Proprietary & Nonproprietary Amend 4 to Westinghouse Advanced PWR RESAR-SP/90 Pda Module 13, Auxiliary Sys. Proprietary Rept Withheld (10CFR2.790)1988-08-0505 August 1988 Forwards Proprietary & Nonproprietary Amend 4 to Westinghouse Advanced PWR RESAR-SP/90 Pda Module 13, Auxiliary Sys. Proprietary Rept Withheld (10CFR2.790) ML20151T8611988-08-0505 August 1988 Requests That Proprietary Amend 4 to Westinghouse Advanced PWR RESAR-SP/90 Pda Module 13, Auxiliary Sys Be Withheld from Public Disclosure (10CFR2.790) ML20207E1421988-07-29029 July 1988 Forwards Proprietary BNL Repts Re Probability Safety Study for RESAR SP/90.Repts Withheld (Ref 10CFR2.740) NUREG/CR-5177, Forwards Proprietary Vols 1 & 2 to NUREG/CR-5177 Re Review of Westinghouse Advanced PWR Probabilistic Safety Study,For Review.Repts Withheld (Ref 10CFR2.790)1988-07-29029 July 1988 Forwards Proprietary Vols 1 & 2 to NUREG/CR-5177 Re Review of Westinghouse Advanced PWR Probabilistic Safety Study,For Review.Repts Withheld (Ref 10CFR2.790) NRC-88-3360, Forwards Amend 2 to Proprietary & Nonproprietary RESAR-SP/90 Pda Module 11, Radiation Protection & RESAR-SP/90 Pda Module 12, Waste Mgt. Proprietary Repts Withheld (Ref 10CFR2.790)1988-07-27027 July 1988 Forwards Amend 2 to Proprietary & Nonproprietary RESAR-SP/90 Pda Module 11, Radiation Protection & RESAR-SP/90 Pda Module 12, Waste Mgt. Proprietary Repts Withheld (Ref 10CFR2.790) ML20151N4281988-07-27027 July 1988 Requests That Proprietary Amend 2 to Westinghouse Advanced PWR RESAR-SP/90 Pda Module 11, Radiation Protection & Amend 2 to RESAR-SP/90 Pda Module 12, Waste Mgt, Be Withheld from Public Disclosure (Ref 10CFR2.790) ML20150C9011988-06-23023 June 1988 Requests Withholding of Addendum 10 to Wapwr RESAR-SP-90 Pda Re Westinghouse Response to NRC Outstanding SEB Questions from Public Disclosure (Ref 10CFR2.790) NRC-88-3349, Forwards Addendum 10 to Wapwr RESAR-SP/90 Pda Re Westinghouse Response to Outstanding SEB Questions. Affidavit for Withholding Addendum (Ref 10CFR2.790) Encl1988-06-23023 June 1988 Forwards Addendum 10 to Wapwr RESAR-SP/90 Pda Re Westinghouse Response to Outstanding SEB Questions. Affidavit for Withholding Addendum (Ref 10CFR2.790) Encl NRC-88-3345, Forwards Addendum 9 to Wapwr RESAR-SP/90 Pda,To Complete Westinghouse Response to NRC Questions Documented in Tj Kenyon to Wj Johnson1988-06-14014 June 1988 Forwards Addendum 9 to Wapwr RESAR-SP/90 Pda,To Complete Westinghouse Response to NRC Questions Documented in Tj Kenyon to Wj Johnson ML20195H1131988-06-14014 June 1988 Requests That Westinghouse Submittal Re Response to Outstanding NRC Questions Be Treated as Proprietary Info Per 10CFR2.790(a) ML20155C2591988-05-27027 May 1988 Submittal of Westinghouse Response to Staff Questions 470.1 to 470.2 in Review of Wapwr RESAR-SP/90 Pda & Application for Withholding Proprietary Info from Public Disclosure NRC-88-3344, Forwards Proprietary Addendum 8 to Wapwr RESAR-SP/90 Pda & Application for withholding,AW-88-054 (non-proprietary),per 880414 & 880425 Requests1988-05-27027 May 1988 Forwards Proprietary Addendum 8 to Wapwr RESAR-SP/90 Pda & Application for withholding,AW-88-054 (non-proprietary),per 880414 & 880425 Requests ML20154J8091988-05-23023 May 1988 Requests That Proprietary Addendum 7 to RESAR-SP/90,PDA Module 2, Regulatory Conformance, Including Responses to Outstanding Safety Issues,Be Withheld from Public Disclosure (Ref 10CFR2.790) NRC-88-3343, Forwards Proprietary Addendum 7 to RESAR-SP/90 Pda Module 2, Regulatory Conformance, Including Responses to Outstanding Safety Issues.Info Constitutes First Step in Updating Module 2.Proprietary Rept Withheld1988-05-23023 May 1988 Forwards Proprietary Addendum 7 to RESAR-SP/90 Pda Module 2, Regulatory Conformance, Including Responses to Outstanding Safety Issues.Info Constitutes First Step in Updating Module 2.Proprietary Rept Withheld ML20154F0511988-05-13013 May 1988 Requests That Amends 1a & 3 to Proprietary Wapwr RESAR-SP/90 Pda Module 1, Primary Side Safeguards Sys Be Withheld from Public Disclosure (Ref 10CFR2.790) NRC-88-3340, Forwards Proprietary & Nonproprietary Amend 3 to RESAR-SP/90 Pda Module 13, Auxiliary Sys. Proprietary Amend Withheld (Ref 10CFR2.790)1988-05-13013 May 1988 Forwards Proprietary & Nonproprietary Amend 3 to RESAR-SP/90 Pda Module 13, Auxiliary Sys. Proprietary Amend Withheld (Ref 10CFR2.790) NRC-88-3335, Forwards Amends 1a & 3 to Proprietary & Nonproprietary Wapwr RESAR-SP/90 Module 1, Primary Side Safeguards Sys. Application for Withholding Proprietary Info from Public Disclosure & Affidavit Encl1988-05-13013 May 1988 Forwards Amends 1a & 3 to Proprietary & Nonproprietary Wapwr RESAR-SP/90 Module 1, Primary Side Safeguards Sys. Application for Withholding Proprietary Info from Public Disclosure & Affidavit Encl NRC-88-3339, Requests Withdrawal of All Copies & Attachments of Licensee Ltr NS-NRC-88-3325 to L Rubenstein Re Amend 2 to Wapwr RESAR-SP/90 Pda Module 13, Auxiliary Sys. Request for Withdrawal Necessary to Correct Amend Number1988-05-13013 May 1988 Requests Withdrawal of All Copies & Attachments of Licensee Ltr NS-NRC-88-3325 to L Rubenstein Re Amend 2 to Wapwr RESAR-SP/90 Pda Module 13, Auxiliary Sys. Request for Withdrawal Necessary to Correct Amend Number ML20154K8841988-05-13013 May 1988 Requests That Proprietary Addendum 4 to RESAR-SP/90, Request for Addl Info Be Withheld from Public Disclosure Per 10CFR2.790(a) NRC-88-3337, Forwards Proprietary & Nonproprietary Amend 1 to Wapwr RESAR-SP/90 PDR Module 4, Rcs1988-05-13013 May 1988 Forwards Proprietary & Nonproprietary Amend 1 to Wapwr RESAR-SP/90 PDR Module 4, Rcs NRC-88-3336, Forwards Proprietary & Nonproprietary Amend 1a to RESAR-SP/90 Pda Module 3, Introduction & Site. Proprietary Amend Withheld (Ref 10CFR2.790)1988-05-13013 May 1988 Forwards Proprietary & Nonproprietary Amend 1a to RESAR-SP/90 Pda Module 3, Introduction & Site. Proprietary Amend Withheld (Ref 10CFR2.790) 1991-07-01
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217C5661991-07-0101 July 1991 Forwards Rev Updating Fnmcp.Encl Withheld (Ref 10CFR2.790) NRC-91-3569, Forwards Proprietary SER Re Preliminary Design of Std Nuclear Steam Supply Ref Sys RESAR SP/90. Encl Withheld1991-02-12012 February 1991 Forwards Proprietary SER Re Preliminary Design of Std Nuclear Steam Supply Ref Sys RESAR SP/90. Encl Withheld ML20012E9261990-03-20020 March 1990 Forwards SP/90 Position on Severe Accident Policy Issues Presented by NRC During 900209 ACRS Full Committee Meeting ML20248H8461989-10-0303 October 1989 Requests That Proprietary Amend 3 to RESAR-SP/90 Pda Module 2, Regulatory Conformance, Be Withheld from Public Disclosure (Ref 10CFR2.790).Affidavit Encl NRC-89-3461, Forwards Proprietary & Nonproprietary Amend 3 to RESAR-SP/90 Pda Module 2, Regulatory Conformance1989-10-0303 October 1989 Forwards Proprietary & Nonproprietary Amend 3 to RESAR-SP/90 Pda Module 2, Regulatory Conformance ML20247G2581989-08-31031 August 1989 Requests That Response to Draft SER Open Issue 82-107 Re RESAR-SP/90 Pda Be Withheld from Public Disclosure (Ref 10CFR2.790) NRC-89-3453, Forwards Proprietary & Nonproprietary Responses to NRC Draft SER Open Issues 82-107 in Review of RESAR-SP/90 Pda. Responses Include Associated Text Changes That Will Be Made in Final Submittal to Draft Ser.Proprietary Rept Withheld1989-08-31031 August 1989 Forwards Proprietary & Nonproprietary Responses to NRC Draft SER Open Issues 82-107 in Review of RESAR-SP/90 Pda. Responses Include Associated Text Changes That Will Be Made in Final Submittal to Draft Ser.Proprietary Rept Withheld NRC-89-3448, Forwards Westinghouse SP/90 Position on Selected Severe Accident Issues to Be Discussed During 890714 Meeting W/Nrc in Rockville,Md.Issue Topics Include Fire Protection, Intersys Loca,Midloop Operation & ATWS1989-07-11011 July 1989 Forwards Westinghouse SP/90 Position on Selected Severe Accident Issues to Be Discussed During 890714 Meeting W/Nrc in Rockville,Md.Issue Topics Include Fire Protection, Intersys Loca,Midloop Operation & ATWS ML20245J8861989-06-28028 June 1989 Requests That Response to Draft SER Open Issues 1-41 Re RESAR-SP/90 Pda Be Withheld from Public Disclosure (Ref 10CFR2.790) ML20245J8821989-06-28028 June 1989 Forwards Proprietary & Nonproprietary Responses to NRC Draft SER Open Issues 1-41 Re RESAR-SP/90 Pda.Proprietary Response Withheld (Ref 10CFR2.790) NRC-89-3438, Forwards Nonproprietary Draft Responses to Open Issues 42-81 of Draft SER Re RESAR-SP/90 Preliminary Design Application1989-06-0909 June 1989 Forwards Nonproprietary Draft Responses to Open Issues 42-81 of Draft SER Re RESAR-SP/90 Preliminary Design Application NRC-89-3419, Forwards Draft Response to NRC Questions 730.1 - 730.4 Re RESAR-SP/90 Pda,Module 2, Regulatory Conformance1989-03-15015 March 1989 Forwards Draft Response to NRC Questions 730.1 - 730.4 Re RESAR-SP/90 Pda,Module 2, Regulatory Conformance ML20235N4451989-02-14014 February 1989 Application for Withholding Proprietary Amends 1a & 2 to Wapwr RESAR-SP/90 Pda Module 7, Structural/Equipment Design, from Public Disclosure NRC-89-3400, Forwards Nonproprietary & Proprietary Amends 1a & 2 to Wapwr RESAR-SP/90 Module 7, Structure Equipment Design1989-02-14014 February 1989 Forwards Nonproprietary & Proprietary Amends 1a & 2 to Wapwr RESAR-SP/90 Module 7, Structure Equipment Design NRC-88-3382, Forwards Proprietary & Nonproprietary Amend 4 to RESAR-SP/90 Pda Module 5, Reactor Sys. Proprietary Rept Withheld (Ref 10CFR2.790)1988-11-0808 November 1988 Forwards Proprietary & Nonproprietary Amend 4 to RESAR-SP/90 Pda Module 5, Reactor Sys. Proprietary Rept Withheld (Ref 10CFR2.790) ML20206F8681988-11-0808 November 1988 Requests Withholding Proprietary Rept from Public Disclosure Per 10CFR2.790 NRC-88-3365, Discusses Design Approval & Certification Programs for AP-600 & SP-90 Designs for Std Nuclear plants.SP-90 Plant Currently Being Evaluated by NRC & Completion of Safety Review & Receipt of SER Anticipated First Quarter 19891988-11-0101 November 1988 Discusses Design Approval & Certification Programs for AP-600 & SP-90 Designs for Std Nuclear plants.SP-90 Plant Currently Being Evaluated by NRC & Completion of Safety Review & Receipt of SER Anticipated First Quarter 1989 NRC-88-3379, Forwards Proprietary & Nonproprietary Amend 2 to Westinghouse Advanced PWR RESAR-SP/90 Pda Module 4, Rcs. Proprietary Amend Withheld (Ref 10CFR2.790)1988-10-26026 October 1988 Forwards Proprietary & Nonproprietary Amend 2 to Westinghouse Advanced PWR RESAR-SP/90 Pda Module 4, Rcs. Proprietary Amend Withheld (Ref 10CFR2.790) ML20195C7871988-10-26026 October 1988 Requests Withholding of Amend 2 to Westinghouse Advanced PWR RESAR-SP/90 Pda Module 4, RCS from Public Disclosure (Ref 10CFR2.790) NRC-88-3374, Forwards Response to NRC 880414 Questions 260.1-260.33 Re QA Program for RESAR-SP/90 Pda.Responses Reflect Discussions Between NRC & Westinghouse During Telcons & 880616 Meeting1988-10-25025 October 1988 Forwards Response to NRC 880414 Questions 260.1-260.33 Re QA Program for RESAR-SP/90 Pda.Responses Reflect Discussions Between NRC & Westinghouse During Telcons & 880616 Meeting ML20207J9441988-09-19019 September 1988 Requests Withholding of Proprietary Version of Amend 4 to RESAR-SP/90 Pda Module 1, Primary Side Safeguards Sys (Ref 10CFR2.790) NRC-88-3371, Forwards Proprietary & Nonproprietary Amend 4 to RESAR-SP/90 Pda Module 1, Primary Side Safeguards Sys. Application for Withholding & Affidavit Also Encl. Proprietary Amend 4 Withheld (Ref 10CFR2.790)1988-09-19019 September 1988 Forwards Proprietary & Nonproprietary Amend 4 to RESAR-SP/90 Pda Module 1, Primary Side Safeguards Sys. Application for Withholding & Affidavit Also Encl. Proprietary Amend 4 Withheld (Ref 10CFR2.790) NRC-88-3368, Forwards Proprietary & Nonproprietary Versions of Amend 3 to Wapwr RESAR-SP/90 Pda Module 3, Introduction & Site. Proprietary Version Withheld (Ref 10CFR2.790)1988-08-25025 August 1988 Forwards Proprietary & Nonproprietary Versions of Amend 3 to Wapwr RESAR-SP/90 Pda Module 3, Introduction & Site. Proprietary Version Withheld (Ref 10CFR2.790) ML20153F7131988-08-25025 August 1988 Requests Withholding of Amend 3 to Wapwr RESAR-SP/90 Pda Module 3, Radiation Protection (Ref 10CFR2.790) NRC-88-3364, Forwards Proprietary & Nonproprietary Amend 4 to Westinghouse Advanced PWR RESAR-SP/90 Pda Module 13, Auxiliary Sys. Proprietary Rept Withheld (10CFR2.790)1988-08-0505 August 1988 Forwards Proprietary & Nonproprietary Amend 4 to Westinghouse Advanced PWR RESAR-SP/90 Pda Module 13, Auxiliary Sys. Proprietary Rept Withheld (10CFR2.790) ML20151T8611988-08-0505 August 1988 Requests That Proprietary Amend 4 to Westinghouse Advanced PWR RESAR-SP/90 Pda Module 13, Auxiliary Sys Be Withheld from Public Disclosure (10CFR2.790) NRC-88-3360, Forwards Amend 2 to Proprietary & Nonproprietary RESAR-SP/90 Pda Module 11, Radiation Protection & RESAR-SP/90 Pda Module 12, Waste Mgt. Proprietary Repts Withheld (Ref 10CFR2.790)1988-07-27027 July 1988 Forwards Amend 2 to Proprietary & Nonproprietary RESAR-SP/90 Pda Module 11, Radiation Protection & RESAR-SP/90 Pda Module 12, Waste Mgt. Proprietary Repts Withheld (Ref 10CFR2.790) ML20151N4281988-07-27027 July 1988 Requests That Proprietary Amend 2 to Westinghouse Advanced PWR RESAR-SP/90 Pda Module 11, Radiation Protection & Amend 2 to RESAR-SP/90 Pda Module 12, Waste Mgt, Be Withheld from Public Disclosure (Ref 10CFR2.790) NRC-88-3349, Forwards Addendum 10 to Wapwr RESAR-SP/90 Pda Re Westinghouse Response to Outstanding SEB Questions. Affidavit for Withholding Addendum (Ref 10CFR2.790) Encl1988-06-23023 June 1988 Forwards Addendum 10 to Wapwr RESAR-SP/90 Pda Re Westinghouse Response to Outstanding SEB Questions. Affidavit for Withholding Addendum (Ref 10CFR2.790) Encl ML20150C9011988-06-23023 June 1988 Requests Withholding of Addendum 10 to Wapwr RESAR-SP-90 Pda Re Westinghouse Response to NRC Outstanding SEB Questions from Public Disclosure (Ref 10CFR2.790) NRC-88-3345, Forwards Addendum 9 to Wapwr RESAR-SP/90 Pda,To Complete Westinghouse Response to NRC Questions Documented in Tj Kenyon to Wj Johnson1988-06-14014 June 1988 Forwards Addendum 9 to Wapwr RESAR-SP/90 Pda,To Complete Westinghouse Response to NRC Questions Documented in Tj Kenyon to Wj Johnson ML20195H1131988-06-14014 June 1988 Requests That Westinghouse Submittal Re Response to Outstanding NRC Questions Be Treated as Proprietary Info Per 10CFR2.790(a) NRC-88-3344, Forwards Proprietary Addendum 8 to Wapwr RESAR-SP/90 Pda & Application for withholding,AW-88-054 (non-proprietary),per 880414 & 880425 Requests1988-05-27027 May 1988 Forwards Proprietary Addendum 8 to Wapwr RESAR-SP/90 Pda & Application for withholding,AW-88-054 (non-proprietary),per 880414 & 880425 Requests ML20155C2591988-05-27027 May 1988 Submittal of Westinghouse Response to Staff Questions 470.1 to 470.2 in Review of Wapwr RESAR-SP/90 Pda & Application for Withholding Proprietary Info from Public Disclosure NRC-88-3343, Forwards Proprietary Addendum 7 to RESAR-SP/90 Pda Module 2, Regulatory Conformance, Including Responses to Outstanding Safety Issues.Info Constitutes First Step in Updating Module 2.Proprietary Rept Withheld1988-05-23023 May 1988 Forwards Proprietary Addendum 7 to RESAR-SP/90 Pda Module 2, Regulatory Conformance, Including Responses to Outstanding Safety Issues.Info Constitutes First Step in Updating Module 2.Proprietary Rept Withheld ML20154J8091988-05-23023 May 1988 Requests That Proprietary Addendum 7 to RESAR-SP/90,PDA Module 2, Regulatory Conformance, Including Responses to Outstanding Safety Issues,Be Withheld from Public Disclosure (Ref 10CFR2.790) NRC-88-3340, Forwards Proprietary & Nonproprietary Amend 3 to RESAR-SP/90 Pda Module 13, Auxiliary Sys. Proprietary Amend Withheld (Ref 10CFR2.790)1988-05-13013 May 1988 Forwards Proprietary & Nonproprietary Amend 3 to RESAR-SP/90 Pda Module 13, Auxiliary Sys. Proprietary Amend Withheld (Ref 10CFR2.790) NRC-88-3335, Forwards Amends 1a & 3 to Proprietary & Nonproprietary Wapwr RESAR-SP/90 Module 1, Primary Side Safeguards Sys. Application for Withholding Proprietary Info from Public Disclosure & Affidavit Encl1988-05-13013 May 1988 Forwards Amends 1a & 3 to Proprietary & Nonproprietary Wapwr RESAR-SP/90 Module 1, Primary Side Safeguards Sys. Application for Withholding Proprietary Info from Public Disclosure & Affidavit Encl NRC-88-3339, Requests Withdrawal of All Copies & Attachments of Licensee Ltr NS-NRC-88-3325 to L Rubenstein Re Amend 2 to Wapwr RESAR-SP/90 Pda Module 13, Auxiliary Sys. Request for Withdrawal Necessary to Correct Amend Number1988-05-13013 May 1988 Requests Withdrawal of All Copies & Attachments of Licensee Ltr NS-NRC-88-3325 to L Rubenstein Re Amend 2 to Wapwr RESAR-SP/90 Pda Module 13, Auxiliary Sys. Request for Withdrawal Necessary to Correct Amend Number NRC-88-3337, Forwards Proprietary & Nonproprietary Amend 1 to Wapwr RESAR-SP/90 PDR Module 4, Rcs1988-05-13013 May 1988 Forwards Proprietary & Nonproprietary Amend 1 to Wapwr RESAR-SP/90 PDR Module 4, Rcs NRC-88-3336, Forwards Proprietary & Nonproprietary Amend 1a to RESAR-SP/90 Pda Module 3, Introduction & Site. Proprietary Amend Withheld (Ref 10CFR2.790)1988-05-13013 May 1988 Forwards Proprietary & Nonproprietary Amend 1a to RESAR-SP/90 Pda Module 3, Introduction & Site. Proprietary Amend Withheld (Ref 10CFR2.790) ML20154K8841988-05-13013 May 1988 Requests That Proprietary Addendum 4 to RESAR-SP/90, Request for Addl Info Be Withheld from Public Disclosure Per 10CFR2.790(a) ML20154H6561988-05-13013 May 1988 Requests That Proprietary Amend 1a to RESAR-SP/90 Pda Module 3, Introduction & Site, Be Withheld from Public Disclosure (Ref 10CFR2.790) ML20154F0511988-05-13013 May 1988 Requests That Amends 1a & 3 to Proprietary Wapwr RESAR-SP/90 Pda Module 1, Primary Side Safeguards Sys Be Withheld from Public Disclosure (Ref 10CFR2.790) ML20154E9471988-05-13013 May 1988 Requests That Proprietary Amend 3 to RESAR-SP/90 Pda Module 13, Auxiliary Sys, Be Withheld from Public Disclosure (Ref 10CFR2.790) ML20154H4941988-05-13013 May 1988 Requests Withholding of Proprietary Version of Amend 1 to Wapwr RESAR-SP/90 Pda Module 4, RCS, Per 10CFR2.790 NRC-88-3325, Forwards Nonproprietary & Proprietary Amend 2 to Westinghouse RESAR-SP/90 Pda Module 13, Auxiliary Sys. Affidavit Encl.Proprietary Amend 2 Withheld (Ref 10CFR2.790)1988-04-20020 April 1988 Forwards Nonproprietary & Proprietary Amend 2 to Westinghouse RESAR-SP/90 Pda Module 13, Auxiliary Sys. Affidavit Encl.Proprietary Amend 2 Withheld (Ref 10CFR2.790) ML20151Y0061988-04-20020 April 1988 Requests That Amend 2 to RESAR-SP/90 Pda Module 13, Auxiliary Sys, Be Withheld from Public Disclosure (Ref 10CFR2.790) ML20151L9261988-04-0404 April 1988 Requests Withholding Proprietary Version of Westinghouse 880406 Presentation of SP/90 PRA to ACRS Subcommittee on Westinghouse Advanced Plants (Ref 10CFR2.790(b)(1)). Affidavit & Nonproprietary Version of Presentation Encl NRC-88-3323, Forwards Proprietary & Nonproprietary Versions of 880406 Presentation of RESAR-SP/90 Pda Probabilistic Safety Study (Module 16)1988-04-0404 April 1988 Forwards Proprietary & Nonproprietary Versions of 880406 Presentation of RESAR-SP/90 Pda Probabilistic Safety Study (Module 16) 1991-07-01
[Table view] Category:VENDOR/MANUFACTURER TO NRC
MONTHYEARML20012E9261990-03-20020 March 1990 Forwards SP/90 Position on Severe Accident Policy Issues Presented by NRC During 900209 ACRS Full Committee Meeting ML20248H8461989-10-0303 October 1989 Requests That Proprietary Amend 3 to RESAR-SP/90 Pda Module 2, Regulatory Conformance, Be Withheld from Public Disclosure (Ref 10CFR2.790).Affidavit Encl NRC-89-3461, Forwards Proprietary & Nonproprietary Amend 3 to RESAR-SP/90 Pda Module 2, Regulatory Conformance1989-10-0303 October 1989 Forwards Proprietary & Nonproprietary Amend 3 to RESAR-SP/90 Pda Module 2, Regulatory Conformance NRC-89-3453, Forwards Proprietary & Nonproprietary Responses to NRC Draft SER Open Issues 82-107 in Review of RESAR-SP/90 Pda. Responses Include Associated Text Changes That Will Be Made in Final Submittal to Draft Ser.Proprietary Rept Withheld1989-08-31031 August 1989 Forwards Proprietary & Nonproprietary Responses to NRC Draft SER Open Issues 82-107 in Review of RESAR-SP/90 Pda. Responses Include Associated Text Changes That Will Be Made in Final Submittal to Draft Ser.Proprietary Rept Withheld ML20247G2581989-08-31031 August 1989 Requests That Response to Draft SER Open Issue 82-107 Re RESAR-SP/90 Pda Be Withheld from Public Disclosure (Ref 10CFR2.790) NRC-89-3448, Forwards Westinghouse SP/90 Position on Selected Severe Accident Issues to Be Discussed During 890714 Meeting W/Nrc in Rockville,Md.Issue Topics Include Fire Protection, Intersys Loca,Midloop Operation & ATWS1989-07-11011 July 1989 Forwards Westinghouse SP/90 Position on Selected Severe Accident Issues to Be Discussed During 890714 Meeting W/Nrc in Rockville,Md.Issue Topics Include Fire Protection, Intersys Loca,Midloop Operation & ATWS ML20245J8821989-06-28028 June 1989 Forwards Proprietary & Nonproprietary Responses to NRC Draft SER Open Issues 1-41 Re RESAR-SP/90 Pda.Proprietary Response Withheld (Ref 10CFR2.790) ML20245J8861989-06-28028 June 1989 Requests That Response to Draft SER Open Issues 1-41 Re RESAR-SP/90 Pda Be Withheld from Public Disclosure (Ref 10CFR2.790) NRC-89-3438, Forwards Nonproprietary Draft Responses to Open Issues 42-81 of Draft SER Re RESAR-SP/90 Preliminary Design Application1989-06-0909 June 1989 Forwards Nonproprietary Draft Responses to Open Issues 42-81 of Draft SER Re RESAR-SP/90 Preliminary Design Application NRC-89-3419, Forwards Draft Response to NRC Questions 730.1 - 730.4 Re RESAR-SP/90 Pda,Module 2, Regulatory Conformance1989-03-15015 March 1989 Forwards Draft Response to NRC Questions 730.1 - 730.4 Re RESAR-SP/90 Pda,Module 2, Regulatory Conformance NRC-89-3400, Forwards Nonproprietary & Proprietary Amends 1a & 2 to Wapwr RESAR-SP/90 Module 7, Structure Equipment Design1989-02-14014 February 1989 Forwards Nonproprietary & Proprietary Amends 1a & 2 to Wapwr RESAR-SP/90 Module 7, Structure Equipment Design ML20235N4451989-02-14014 February 1989 Application for Withholding Proprietary Amends 1a & 2 to Wapwr RESAR-SP/90 Pda Module 7, Structural/Equipment Design, from Public Disclosure NRC-88-3382, Forwards Proprietary & Nonproprietary Amend 4 to RESAR-SP/90 Pda Module 5, Reactor Sys. Proprietary Rept Withheld (Ref 10CFR2.790)1988-11-0808 November 1988 Forwards Proprietary & Nonproprietary Amend 4 to RESAR-SP/90 Pda Module 5, Reactor Sys. Proprietary Rept Withheld (Ref 10CFR2.790) ML20206F8681988-11-0808 November 1988 Requests Withholding Proprietary Rept from Public Disclosure Per 10CFR2.790 NRC-88-3365, Discusses Design Approval & Certification Programs for AP-600 & SP-90 Designs for Std Nuclear plants.SP-90 Plant Currently Being Evaluated by NRC & Completion of Safety Review & Receipt of SER Anticipated First Quarter 19891988-11-0101 November 1988 Discusses Design Approval & Certification Programs for AP-600 & SP-90 Designs for Std Nuclear plants.SP-90 Plant Currently Being Evaluated by NRC & Completion of Safety Review & Receipt of SER Anticipated First Quarter 1989 NRC-88-3379, Forwards Proprietary & Nonproprietary Amend 2 to Westinghouse Advanced PWR RESAR-SP/90 Pda Module 4, Rcs. Proprietary Amend Withheld (Ref 10CFR2.790)1988-10-26026 October 1988 Forwards Proprietary & Nonproprietary Amend 2 to Westinghouse Advanced PWR RESAR-SP/90 Pda Module 4, Rcs. Proprietary Amend Withheld (Ref 10CFR2.790) ML20195C7871988-10-26026 October 1988 Requests Withholding of Amend 2 to Westinghouse Advanced PWR RESAR-SP/90 Pda Module 4, RCS from Public Disclosure (Ref 10CFR2.790) NRC-88-3374, Forwards Response to NRC 880414 Questions 260.1-260.33 Re QA Program for RESAR-SP/90 Pda.Responses Reflect Discussions Between NRC & Westinghouse During Telcons & 880616 Meeting1988-10-25025 October 1988 Forwards Response to NRC 880414 Questions 260.1-260.33 Re QA Program for RESAR-SP/90 Pda.Responses Reflect Discussions Between NRC & Westinghouse During Telcons & 880616 Meeting NRC-88-3371, Forwards Proprietary & Nonproprietary Amend 4 to RESAR-SP/90 Pda Module 1, Primary Side Safeguards Sys. Application for Withholding & Affidavit Also Encl. Proprietary Amend 4 Withheld (Ref 10CFR2.790)1988-09-19019 September 1988 Forwards Proprietary & Nonproprietary Amend 4 to RESAR-SP/90 Pda Module 1, Primary Side Safeguards Sys. Application for Withholding & Affidavit Also Encl. Proprietary Amend 4 Withheld (Ref 10CFR2.790) ML20207J9441988-09-19019 September 1988 Requests Withholding of Proprietary Version of Amend 4 to RESAR-SP/90 Pda Module 1, Primary Side Safeguards Sys (Ref 10CFR2.790) NRC-88-3368, Forwards Proprietary & Nonproprietary Versions of Amend 3 to Wapwr RESAR-SP/90 Pda Module 3, Introduction & Site. Proprietary Version Withheld (Ref 10CFR2.790)1988-08-25025 August 1988 Forwards Proprietary & Nonproprietary Versions of Amend 3 to Wapwr RESAR-SP/90 Pda Module 3, Introduction & Site. Proprietary Version Withheld (Ref 10CFR2.790) ML20153F7131988-08-25025 August 1988 Requests Withholding of Amend 3 to Wapwr RESAR-SP/90 Pda Module 3, Radiation Protection (Ref 10CFR2.790) NRC-88-3364, Forwards Proprietary & Nonproprietary Amend 4 to Westinghouse Advanced PWR RESAR-SP/90 Pda Module 13, Auxiliary Sys. Proprietary Rept Withheld (10CFR2.790)1988-08-0505 August 1988 Forwards Proprietary & Nonproprietary Amend 4 to Westinghouse Advanced PWR RESAR-SP/90 Pda Module 13, Auxiliary Sys. Proprietary Rept Withheld (10CFR2.790) ML20151T8611988-08-0505 August 1988 Requests That Proprietary Amend 4 to Westinghouse Advanced PWR RESAR-SP/90 Pda Module 13, Auxiliary Sys Be Withheld from Public Disclosure (10CFR2.790) NRC-88-3360, Forwards Amend 2 to Proprietary & Nonproprietary RESAR-SP/90 Pda Module 11, Radiation Protection & RESAR-SP/90 Pda Module 12, Waste Mgt. Proprietary Repts Withheld (Ref 10CFR2.790)1988-07-27027 July 1988 Forwards Amend 2 to Proprietary & Nonproprietary RESAR-SP/90 Pda Module 11, Radiation Protection & RESAR-SP/90 Pda Module 12, Waste Mgt. Proprietary Repts Withheld (Ref 10CFR2.790) ML20151N4281988-07-27027 July 1988 Requests That Proprietary Amend 2 to Westinghouse Advanced PWR RESAR-SP/90 Pda Module 11, Radiation Protection & Amend 2 to RESAR-SP/90 Pda Module 12, Waste Mgt, Be Withheld from Public Disclosure (Ref 10CFR2.790) NRC-88-3349, Forwards Addendum 10 to Wapwr RESAR-SP/90 Pda Re Westinghouse Response to Outstanding SEB Questions. Affidavit for Withholding Addendum (Ref 10CFR2.790) Encl1988-06-23023 June 1988 Forwards Addendum 10 to Wapwr RESAR-SP/90 Pda Re Westinghouse Response to Outstanding SEB Questions. Affidavit for Withholding Addendum (Ref 10CFR2.790) Encl ML20150C9011988-06-23023 June 1988 Requests Withholding of Addendum 10 to Wapwr RESAR-SP-90 Pda Re Westinghouse Response to NRC Outstanding SEB Questions from Public Disclosure (Ref 10CFR2.790) NRC-88-3345, Forwards Addendum 9 to Wapwr RESAR-SP/90 Pda,To Complete Westinghouse Response to NRC Questions Documented in Tj Kenyon to Wj Johnson1988-06-14014 June 1988 Forwards Addendum 9 to Wapwr RESAR-SP/90 Pda,To Complete Westinghouse Response to NRC Questions Documented in Tj Kenyon to Wj Johnson ML20195H1131988-06-14014 June 1988 Requests That Westinghouse Submittal Re Response to Outstanding NRC Questions Be Treated as Proprietary Info Per 10CFR2.790(a) NRC-88-3344, Forwards Proprietary Addendum 8 to Wapwr RESAR-SP/90 Pda & Application for withholding,AW-88-054 (non-proprietary),per 880414 & 880425 Requests1988-05-27027 May 1988 Forwards Proprietary Addendum 8 to Wapwr RESAR-SP/90 Pda & Application for withholding,AW-88-054 (non-proprietary),per 880414 & 880425 Requests ML20155C2591988-05-27027 May 1988 Submittal of Westinghouse Response to Staff Questions 470.1 to 470.2 in Review of Wapwr RESAR-SP/90 Pda & Application for Withholding Proprietary Info from Public Disclosure ML20154J8091988-05-23023 May 1988 Requests That Proprietary Addendum 7 to RESAR-SP/90,PDA Module 2, Regulatory Conformance, Including Responses to Outstanding Safety Issues,Be Withheld from Public Disclosure (Ref 10CFR2.790) NRC-88-3343, Forwards Proprietary Addendum 7 to RESAR-SP/90 Pda Module 2, Regulatory Conformance, Including Responses to Outstanding Safety Issues.Info Constitutes First Step in Updating Module 2.Proprietary Rept Withheld1988-05-23023 May 1988 Forwards Proprietary Addendum 7 to RESAR-SP/90 Pda Module 2, Regulatory Conformance, Including Responses to Outstanding Safety Issues.Info Constitutes First Step in Updating Module 2.Proprietary Rept Withheld NRC-88-3340, Forwards Proprietary & Nonproprietary Amend 3 to RESAR-SP/90 Pda Module 13, Auxiliary Sys. Proprietary Amend Withheld (Ref 10CFR2.790)1988-05-13013 May 1988 Forwards Proprietary & Nonproprietary Amend 3 to RESAR-SP/90 Pda Module 13, Auxiliary Sys. Proprietary Amend Withheld (Ref 10CFR2.790) NRC-88-3336, Forwards Proprietary & Nonproprietary Amend 1a to RESAR-SP/90 Pda Module 3, Introduction & Site. Proprietary Amend Withheld (Ref 10CFR2.790)1988-05-13013 May 1988 Forwards Proprietary & Nonproprietary Amend 1a to RESAR-SP/90 Pda Module 3, Introduction & Site. Proprietary Amend Withheld (Ref 10CFR2.790) NRC-88-3337, Forwards Proprietary & Nonproprietary Amend 1 to Wapwr RESAR-SP/90 PDR Module 4, Rcs1988-05-13013 May 1988 Forwards Proprietary & Nonproprietary Amend 1 to Wapwr RESAR-SP/90 PDR Module 4, Rcs NRC-88-3339, Requests Withdrawal of All Copies & Attachments of Licensee Ltr NS-NRC-88-3325 to L Rubenstein Re Amend 2 to Wapwr RESAR-SP/90 Pda Module 13, Auxiliary Sys. Request for Withdrawal Necessary to Correct Amend Number1988-05-13013 May 1988 Requests Withdrawal of All Copies & Attachments of Licensee Ltr NS-NRC-88-3325 to L Rubenstein Re Amend 2 to Wapwr RESAR-SP/90 Pda Module 13, Auxiliary Sys. Request for Withdrawal Necessary to Correct Amend Number NRC-88-3335, Forwards Amends 1a & 3 to Proprietary & Nonproprietary Wapwr RESAR-SP/90 Module 1, Primary Side Safeguards Sys. Application for Withholding Proprietary Info from Public Disclosure & Affidavit Encl1988-05-13013 May 1988 Forwards Amends 1a & 3 to Proprietary & Nonproprietary Wapwr RESAR-SP/90 Module 1, Primary Side Safeguards Sys. Application for Withholding Proprietary Info from Public Disclosure & Affidavit Encl ML20154E9471988-05-13013 May 1988 Requests That Proprietary Amend 3 to RESAR-SP/90 Pda Module 13, Auxiliary Sys, Be Withheld from Public Disclosure (Ref 10CFR2.790) ML20154F0511988-05-13013 May 1988 Requests That Amends 1a & 3 to Proprietary Wapwr RESAR-SP/90 Pda Module 1, Primary Side Safeguards Sys Be Withheld from Public Disclosure (Ref 10CFR2.790) ML20154H4941988-05-13013 May 1988 Requests Withholding of Proprietary Version of Amend 1 to Wapwr RESAR-SP/90 Pda Module 4, RCS, Per 10CFR2.790 ML20154H6561988-05-13013 May 1988 Requests That Proprietary Amend 1a to RESAR-SP/90 Pda Module 3, Introduction & Site, Be Withheld from Public Disclosure (Ref 10CFR2.790) ML20154K8841988-05-13013 May 1988 Requests That Proprietary Addendum 4 to RESAR-SP/90, Request for Addl Info Be Withheld from Public Disclosure Per 10CFR2.790(a) NRC-88-3325, Forwards Nonproprietary & Proprietary Amend 2 to Westinghouse RESAR-SP/90 Pda Module 13, Auxiliary Sys. Affidavit Encl.Proprietary Amend 2 Withheld (Ref 10CFR2.790)1988-04-20020 April 1988 Forwards Nonproprietary & Proprietary Amend 2 to Westinghouse RESAR-SP/90 Pda Module 13, Auxiliary Sys. Affidavit Encl.Proprietary Amend 2 Withheld (Ref 10CFR2.790) ML20151Y0061988-04-20020 April 1988 Requests That Amend 2 to RESAR-SP/90 Pda Module 13, Auxiliary Sys, Be Withheld from Public Disclosure (Ref 10CFR2.790) ML20151L9261988-04-0404 April 1988 Requests Withholding Proprietary Version of Westinghouse 880406 Presentation of SP/90 PRA to ACRS Subcommittee on Westinghouse Advanced Plants (Ref 10CFR2.790(b)(1)). Affidavit & Nonproprietary Version of Presentation Encl NRC-88-3323, Forwards Proprietary & Nonproprietary Versions of 880406 Presentation of RESAR-SP/90 Pda Probabilistic Safety Study (Module 16)1988-04-0404 April 1988 Forwards Proprietary & Nonproprietary Versions of 880406 Presentation of RESAR-SP/90 Pda Probabilistic Safety Study (Module 16) ML20148N6871988-03-24024 March 1988 Requests That Encl Proprietary Amend 2 to RESAR-SP/90 Pda Module 13, Auxiliary Sys, Be Withheld (Ref 10CFR2.790) ML20150E6121988-03-23023 March 1988 Requests That Proprietary Amend 2 to RESAR-SP/90 Pda Module 2, Regulatory Conformance Be Withheld from Public Disclosure (Ref 10CFR2.790) 1990-03-20
[Table view] |
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4= w Westinghouse Energy Systems y,jeagay99,qnjea Electric Corporation Box 355 Pmsburgh Pennsylvania 15230-0355
, March 15, 1989 NS-NRC-89-3419 Docket No. STN 50-601 Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Charles L. Miller, Director Standardization and Non-Power Reactor Project Directorate
Subject:
Submittal of Westinghouse Draft Response to Staff Questions 730.1 - 730.4 in Review of WAPWR RESAR-SP/90 PDA.
Ref(s) 1. T. J. Kenyon (NRC) letter to W. J. Johnson (Westinghouse),
dated February 2, 1989.
l 2. Letter No. NS-NRC-88-3343_(Addendum 7 to SP/90), Johnson l
(Westinghouse) to Rubenstiin (NRC) dated May 23, 1988.
I
Dear Mr. Miller:
Enclosed are ten (10) non-Proprietary copies of the Westinghouse draft response to NRC questions 730.1 - 730.4 (Reference 1) in the Staff's review of the Westinghouse response to " Outstanding" Safety Issues (Reference 2) as applied to MAPWR RESAR-SP/90. The responses include H commitments to modify our original resolution of the subje::t issues, and these modifications will be included in our soon to be submitted update of RESAR-SP/90 PDA Module 2, " Regulatory Confromance" Note that the enclosed package is n9_t to be inserted in the RESAR-SP/90 PDA document, but, as noted above, will be part of our next amendment to Module 2.
Very truly yours, iw W. M J hnson, Manager Nu ha Safety Department l -
l l Enclosure (s)
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cc: Thomas J. Kenyon - NRC (MS 11H3)
Trevor Pratt - Brookhaven National Lab I
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.. .. i WESTINGHOUSE CLASS 3 {
I DRAFT RESPONSE TO NRC OVESTIONS 730.1 - 730.4 RESAR-SP/90 MODULE 2
" REGULATORY CONFORMANCE"
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ATTACHMENT RE0 VEST FOR ADDITIONAL INFORMATION hh h l
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730.1 For future PWRs, the staff has recently concluded that PORVs'and l (GSI-70) block valves and associated controls for.these components should be ;
constructed' to safety grade standards. This includes having a I minimum of two sets of PORYs and block valves including redundant and diverse control systems, being designed to Seismic Category I requirements, being environmentally qualified, having increased Technical Specifications surveillance requirements and inservice i testing requirements, and inclusion within the scope of a quality l assurance program that is in compliance with 10 CFR 50, Appendix l'
B. In addition, the requirements should include those improvements.
that were imposed subsequent to the TMI-2 accident, such as requirements to be powered from Class IE buses, and to have valve position indication in the control room.
By letter dated May 23, 1988, Westinghouse provided its resolution of GSI-70 as it applies to the RESAR-SP/B0 design. In addition to this information, the staff requires Westinghouse to provide a commitment to providing safety grade PORVs and block valves, and associated controls which include, 'as a minimum, the following features.
o There must be a minimum of two PORVs and block valves, including associated redundant and diverse control systems, o The equipment must be designed to Seismic Category 1 l requirements.
o The equipment must be environmentally qualified.
l o Increased inservice testing must be provided in accordance with applicable ASME Section XI rules.
o The equipment .must be included within the scope of a quality assurance program that is in compliance with 10 CFR- 50, Appendix B. That is, "PORVs and block valves will be included in the safety related 0 List".
o Increased Technical Specifications surveillance requirements must be provided to insure PORV and block valve operability.
RESPONSE
l l The commitments requested by Staff are, for the most part, currently reflected in the RESAR-SP/90 PDA document. For example, WAPWR-RC 730-1 MARCH, 1989 8751e:1d
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'*%o e D see Subsection 5.4.7 and Question / Response 140.Q, / .. %am 82 m ofq RE'5&R',Sl g90 PDA Module 1, " Primary Side Safeguards , abjub Bon 5.4.13 of 'RESAR-SP/90 PDA Module 4, " Reactor. Coolant System."
However, the Westinghouse response to GSI-70, "PORV and Block Valve Reliability," will be revised for our update of RESAR-SP/90 PDA Module 2 " Regulatory Conformance," to provide the following commitments:
o There will 'eb a minimum of two PORVs and block valves including redundant and diverse control systems.
o The PORVs and block valves will be designed to Safety Grade, Seismic Category I requirements..
o The design will allow .for environmental qualification of the PORVs and block valves.
o The design of the PORVs and block valves will allow inservice testing in accordance with Article IWV-3400 of ASME Section'XI.
o The PORVs and block valves will be included in the final safety related 0-list of Table 3.2-1 of RESAR-SP/90 PDA Module 7,
" Structural / Equipment Design."
4 o Surveillance requirements will be included in the FDA Standard Technical Specifications to ensure PORV and block -valve operability.
1 (730.2 In response to the staff's Question 210.71 relative to periodic
((GSI-105) leak testing of pressure isolation valves, Westinghouse referenced its response *; Question 210.38. In that response, a commitment is.
I made to perform periodic leak testing of all pressure isolation
, valves in accordance with the requirements in the Westinghouse Standard Technical Specifications. The staff concludes that this is an acceptable commitment regarding Generic Issue 105 for the PDA i Phase of RESAR-SP/90. The response to this issue in the May 23, 1988 Letter on USIs/GSIs should be revised to reflect this eommitment. J l WAPWR-RC 730-2 MARCH, 1989 s7si..le l
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.. . ',if In addition. the Westinghouse response to Gener' s s that the ISS interconnections to the RCS are ei er vent irec y back to the in containment EWST or consist of 2000 PSIG design pressure piping. Are there any other low pressure systems which are connected to the RCS that do not have either of these features?
RESPONSE
A commitment to perform periodic leak testing of all pressure isolation valves, in accordance with the requirements in the Westinghouse Standard Technical Specifications, will be added to our response to GSI-105, " Interfacing Systems LOCA at LWRs", in our update of RESAR-SP/90 PDA Module 2, " Regulatory Conformance."
In response to the second part of this question, there are other low pressure systems which are connected to the RCS. These connections are such that leak testing similar to that performed on ECCS check valves is not required. A brief description of these connections is provided below:
o RCS drain and vent connections, and the ISS emergency letdown lines are provided with redundant closed isolation valves.
Since these lines do not penetrate the containment, the failure of both isolation valves would not only be a low probability event, but would not result in an "intersystem LOCA."
o Sampling system lines both penetrate the containment and may be open during normal operation. These piping connections are provided with a 3/8-inch flow restrictor such that failure would not require safety system actuation. These lines contain redundant and automatic containment isolation valves.
o The CVCS letdown line is normally open during plant operation.
This line contains redundant valves (normally open) which will automatically close on low pressurizer level, and redundant and automatic containment isolation valves.
- '2 WAPWR-RC 730-3 MARCH, 1989 87sle.1d
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o The CVCS alternate letdown line conta s closed isolation valves, redundant a fn fu a on 11y ent isolation valves, an operator controlled throttle valve and a temperature sensor, o The CVCS charging line contains multiple chack valves and redundant isolation valves.
All piping connections up to and including their isolation valves are designed for full RCS prersure and temperature conditions.
730.3 By letter dated May 23, 1988, Westinghouse stated that it has (GSI-113) assured high reliability of its snubbers by use of stringent requirements in its equipment specifications to resolve GSI-113.
Westinghouse further stated that for the design of the RESAR-SP/90, it advocates the implementation of -environmental and dynamic qualification of its snubbers as well as inservice testing (to the extent that state of the art testing equipment is adequate) and surveillance. Before the staff can complete its evaluation of the applicant's response on this issue, provide the following additional information:
- 1. Clarify how the use of stringent requirements in equipment specifications has assured high reliability of large bore hydraulic snubbers. Describe what reliability is assumed for LBHSs in the analyses of applicable systems.
- 2. Clarify your statement regarding the advocation of the implementation of environmental and dynamic qualification, and inservice testing and surveillance of snubbers. Provide more detailed information explaining how these actions will resolve this 1ssue.
RESPONSE
730.3, ITEM 1 Westinghouse equipment specifications help assure LBHS reliability.
by defining a complete set of fabrication and functional testing requirements. The Westinghouse equipment specifications define the l snubber design requirements, environmental requirements, operability requirements, functional requirements, and establish a process that ensures Westinghouse engineering controls and reviews WAPWR-RC 730-4 MARCH, 1989 87sle.1d
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'q r gy, 49 all vendor procedures and processes us he ring cycle. Each step of the fabrication an shop assembly of the 3 snubber, including the review and approval of all procedures, fabrication sequences and test results, is closely monitored by Westinghouse engineering and quality assurance personnel to insure all requirements and testing criteria are adhered to.
Additionally, each snubber must pass numerous performance qualification tests (i.e., control valve lockup, piston bleed ;
rates, load rating, spring rates, piston drag, etc.) prior to its acceptance and release for shipment.
The Westinghouse equipment specifications also require the vendor to provide functionality analyses, design reports, fluid / seal compatibility analyses, environmental qualification data for " soft j parts", installation procedures, spare parts lists, and recommended l l 1 l maintenance practices. Westinghouse's attention to detail and j l
complete definition of snubber design, function, operability, and j l maintenance requirements help assure a high reliability in LBHSs.
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The steam generator LBHSs are assumed to perform their intended function for the 40 year opert. ting life of the plant. The snubbers are required to provide minimum resistance against normal reactor coolant loop thermal expansion (drag less than or equal to 5000 l lbs. per snubber) and to " lockup" at velocities greater than or equal to 6 inches per minute. In the locked. condition the snubbers are required to bleed at 0.15 to 0.25 inches per minute at full faulted rated load. In addition, the snubbers are to remain fully functional when exposed to a radiation level of 25 RAD /hr, 70%
hum;dity, and 120 degrees Fahrenheit long term operation and 300 !
degrees Fahrenheit short term operation.
Westinghouse has been defining the requirements for and procuring steam generator LBHSs for over twenty years. The technical and material advances in LBHS technology that have taken place have 4
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l been evaluated and adopted into the Westinghouse requirements for LBHSs. This knowledge will,be implemented in the SP/90.
WAPWR-RC 730-5 MARCH, 1989 87sle.1d t
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The majority of LBHS procured by Westinghouse
! see es n l
l and manufactured by Paul-Munroe Hydraulics. aul-Munroe steam generator LBHS has implemented design features which help ensure the reliability of the snubber. Features such as a self cleaning bleed orifice end a corrosion resistant chrome lined carbon steel cylinder contribute to the reliability of the snubber. Additional information on the reliability of Paul-Munroe steam generator LBHSs is provided in Attachment-A 730.33 ITEM 2 Currently dynamic testing of production scale steam generator snubbers is not performed. As such, Westinghouse requires a rigorous series of static function,a1 tests (drag, lockup, bleed) to be performed on each snubber. These tests, although not dynamic, verify the operability of the snubbers at their rated load capacity. Until recently, the means of dynamically testing these snubbers was not available. However, Paul-Munroe has performed a limited number of dynamic tests of steam generator snubbers. A drop weight test with an equivalent loading exceeding the rated load has been performed. Small scale dynamic testing has been performed including tests for a cyclic force of 90 kips applied at up to 16 Hz. and a cyclic force of 450 kips applied at up to 11 Hz. These tests represent the approximate limits of current testing facilities. The results of these tests demonstrated that the Paul-Munroe snubbers performed as predicted during dynamic loading conditions.
Due to limits on the capacity of the available testing facilities, dynamic tests of steam generator snubbers for the full rated load and a full range of frequencies (1-33 Hz.) is not possible.
Westinghouse however, does support the future development of such facilities that will permit this type of testing and qualification of the steam generator snubbers.
Currently, inservice inspection requirements of steam generator snubbers is defined by individual plant technical specifications. I WAPWR-RC 730-6 MARCH,1989 87sle.1d
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j Many of these technical specifications r e 1 e a st requirements of ASME's OM4 inservice et n s ng-criteria. Westinghouse believes that a certain amount of inservice surveillance (leakage and fluid level checks) is required to provide added assurance that the snubber will continue to function as intended during plant operation.
730.4 By letter dated May 23, 1988, Westinghouse provided a discussion (GSI-135) on GSI-135 which concluded that its steam generator overfill !
protection system is designed to divert flow to the Emergency Water Storage Tank if the high steam generator water level setpoint is ,
reached. Although this system feature will reduce the probability !
of the occurrence of a steam line overfill, the current staff position is that a part of the basis for evaluating plant spe:ific j responses to this issue is a commitment from each applicant or- '
licensee that it has evaluated th'e structural adequacy of the main '
steam lines and associated supports under water-filled conditions !
as a result of steam generator tube rupture. The RESAR-SP/90 i response to Generic Issue 135 should be revised to provide such a commitment. .
l RESPONSE 1
The Westinghouse response to Generic Issue 135 will be revised in I l our update of RESAR-SP/90 PDA Module 2, " Regulatory Conformance,"
as shown below, to provide a commitment to evaluate the structural adequacy of the main steam lines and associated supports: j i
"Although the features described above will reduce the probability of the occurrence of a steam line overfill, Westinghouse will evaluate the structural adequacy of the main steam lines and associated supports under water filled conditions as a result of steam generator tube rupture. This evaluation will assume that the main steam line is water filled from the steam generator out and the first isolation valves are at main steam system design pressure and temperature. This load condition will be evaluated against Service Level D Allowables".
WAPWR-RC 730-7 MARCH, 1989 8751e:1d
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Attachment-A (730.3)
Hydraulic Snubber Reliability l fg,'
The Paul-Munroe hydraulic snubbers used for steam generator upper lateral supports are reliable. The reliability of the Paul-Munroe hydraulic snubbers has been demonstrated by their effective performance over 1900 snubber years without impact to plant operation.
Westinghouse has primarily used Paul-Munroe hydraulic snubbers in the Westinghouse reactor coolant loop support system. To date, Westinghouse has accumulated over 1000 snubber years of trouble-free operating experience of Paul-Munroe snubbers in Westinghouse designed reactor coolant loop support systems. Throughout this operating service life, Westinghouse is not knowledgeable of any instance in which a Paul-Munroe steam generator hydraulic snubber was found to be inoperable or cause for a plant shutdown.
Inoperability is defined as the snubber'not being able to perform the minimum plant specific functional requirements of locking-up and bleeding (translating under load). To update and confirm Westinghouse knowledge of Paul-Munroe snubber operating experience, Westinghouse recently conducted a limited survey of domestic operating plants with a Westinghouse reactor coolant loop support design and Paul-Munroe steam generator snubbers. In every case the Paul-Munroe snubbers were reported to have experienced no operational problems.
In addition, a domestic utility independently contacted INPO to perform a sort on the INP0 Licensing Event Report, LER, data base to identify all reported failures of Paul-Munroe hydraulic snubbers. The INPO report identified only three LERs referencing Paul-Munroe hydraulic snubbers, j
- 1. Diablo Canyon Unit 1 - On 9/13/86 with Unit 1 in mode 5, during inservice inspection one steam generator snubber was found to be unpinned at the blind end. All other snubbers were found to be 1 l functional. The cause of the pin movement is unknown. A design change which provided the pins with locking devices was implemented to prevent repetition.
The SP/90 steam generator snubbers will be provided with pins which feature a positive locking device, cotter pins.
- 2. Calloway Unit 1 - On 3/8/86, during inservice testing of one steam I generator snubber, one hydraulic control valve failed causing the snubber to lock-up. The cause of the failure was attributed to the in plhee test equipment creating an unnatural high rate of cycling on the control valve and thereby causing the valve stem to shear. The snubber was replaced and sent to Paul-Munroe for refurbishment. .
Paul-Munroe has isolated the problem that caused the control valve failure and have modified their in place test equipment to prevent any
( reoccurrence. The control valve failure at Calloway is unique to the inservice testing performed on that snubber using original Paul-Munroe test equipment and is no indication of any generic service life problem with the control valve.
WAPWR-RC 730-8 MARCH,1989 B7sle.1d
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- 3. Arkansas Nuclear One Unit 1 -
On 11/9f%, t shutdown, a 200 kip capacity reactor coolant pu d tul sn I was found to be leaking fluid. Examination of the snubber revealed arc strikes on the piston rod. These appeared to have been the result of the snubber being used as a ground for a welding machine. The cause of the leak were scratches on the TEF2EL piston rod seal !
apparently caused by the arc strikes. The snubber was disassembled, i cleaned, inspected, damaged parts were rebuilt by Paul-Munroe and the snubber was reassembled with new seals.
1 The SP/90 steam generator snubbers will also use TEFZEL seals.
However, the installation, maintenance, and inspection procedures at i SP/90 will preclude misuse of the snubbers and identify any abnormal l snubber leakage.
As additional confirmation on the reliability of Paul-Munroe hydraulic snubbers, Paul-Munroe Hydraulics was contacted and requested to provide a summary of their knowledge of the operating service life of Paul-Munroe ,
hydraulic snubbers similar in load capacity to the steam generator snubbers.
Paul-Munroe entered into the snubber production of large bore (250 to 2000 kip capacity) snubbers in 1969. Since that time, Paul-Munroe has become the major manufacturer of large bore snubbers worldwide with over 1400 snubbers supplied. In addition, Paul-Munroe has been the main supplier of steam generator snubbers for both Westinghouse and Combustion Engineering reactor coolant support systems.
Paul-Munroe has used advanced technology in its snubber seal, pc'ppet-style control valve design, and in pirce testing capability. The Paul-Munroe TEF2EL seal has been an extremely reliable design and is fully qualified for 40 year life performance. The poppet-style control valve provides consistent ;-
performance and is not subject to the problems experienced by conventional '
control valves. The poppet-style control valve has the bleed orifice in-line with the poppet thus eliminating silting or clogging conditions by r.ature of this self cleaning design. The control valves are set in the factory and are i not subject to field tampering. The in place testing capability allows the '
snubbers to be tested for operability in place. The SP/90 steam generator hydraulic snubbers incorporate all these advanced design features.
Paul-Munroe large bore snubbers have provided nuclear facilities with a total, I effective performance of over 1,900 snubber years of operating service without impact to plant operation. Paul-Munroe has over 390 snubbers that have been in operating service for over 4 years.
Paul-Munroe's statements are supported by EPRI's " Snubber Reliability Improvement Study", EPRI NP-2297, which states that " ..no generic problems have been reported for their (Paul-Munroe) snubbers due to storage, installation, field adjustment, deterioration in service, inspection, or maintenance.". inservice In conclusion, the 1900 plus snubber years of operating experience with no reports of inoperability demonstrate the reliability of the Paul-Munroe steam generator hydraulic snubbers.
WAPWR-RC 730-9 MARCH, 1989 8751e:1d a______-__