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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20054K2421982-05-27027 May 1982
Requests Withholding,Per 10CFR2.790,of Info Transmitted by EP Rahe to Tp Speis
ML20054K2341982-05-27027 May 1982
Forwards Addl Data,Per 820413 Meeting W/Westinghouse,Nrc & Inel Re Fuel Rod Design & Info Re two-phase Reactor Coolant Pump Performance.Encls Withheld (Ref 10CFR2.790)
ML20054B5731982-04-0707 April 1982
Responds to NRC 811006 Ltr Requesting Transient Analysis Data for Use in Calculations Performed for Reactor Sys Branch.Info Will Be Transmitted Via Westinghouse
ML20039F6161981-12-29029 December 1981
Requests 2-yr Extension of RESAR-3S Preliminary Design Approval (PDA-7) to Allow for Continued Review of Significant New Safety Issues Raised Since TMI-2
ML19211A6641979-12-18018 December 1979
Forwards Amend 15 to RESAR-3S,in Response to NRC 791213 Request for Addl Info
ML19249D8121979-08-11011 August 1979
Opposes Sale of Reactor to Philippines by Westinghouse. Other Ltrs & Petitions in Opposition Encl
ML19208B6401979-08-0606 August 1979
Requests Issuance of Export License by Us.Full CP Issued After Review of PSAR & Topics Raised by 1978 IAEA Safety Mission
ML19269C9021979-02-0202 February 1979
Responds to NRC Inquiry Re Choice of Custom Rather than Standardized Design for NSSS & Balance of Plant.Reliability Was Primary Goal for Turbine Generators
ML20150E4121978-12-15015 December 1978
Forwards Copy of Amend 14 to RESAR-3S Documenting the Westinghouse 3411 Mwt Nuc Steam Supply Sys as Appl for 2-yr Extension of Preliminary Design Approval(PDA-7) for RESAR- 3S.None of Existing Matl in RESAR-3S Has Been Modified
ML20244A4211977-10-24024 October 1977
Forwards Topical Rept Re Fuel Rod Bow Penalties.Application & Affidavit for Withholding Rept Also Encl.Rept Provides Basis for near-term Rev to Fuel Rod Bow Penalties
1982-05-27
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARML20054K2421982-05-27027 May 1982
Requests Withholding,Per 10CFR2.790,of Info Transmitted by EP Rahe to Tp Speis
ML20054K2341982-05-27027 May 1982
Forwards Addl Data,Per 820413 Meeting W/Westinghouse,Nrc & Inel Re Fuel Rod Design & Info Re two-phase Reactor Coolant Pump Performance.Encls Withheld (Ref 10CFR2.790)
ML20054B5731982-04-0707 April 1982
Responds to NRC 811006 Ltr Requesting Transient Analysis Data for Use in Calculations Performed for Reactor Sys Branch.Info Will Be Transmitted Via Westinghouse
ML20039F6161981-12-29029 December 1981
Requests 2-yr Extension of RESAR-3S Preliminary Design Approval (PDA-7) to Allow for Continued Review of Significant New Safety Issues Raised Since TMI-2
ML19211A6641979-12-18018 December 1979
Forwards Amend 15 to RESAR-3S,in Response to NRC 791213 Request for Addl Info
ML19249D8121979-08-11011 August 1979
Opposes Sale of Reactor to Philippines by Westinghouse. Other Ltrs & Petitions in Opposition Encl
ML19208B6401979-08-0606 August 1979
Requests Issuance of Export License by Us.Full CP Issued After Review of PSAR & Topics Raised by 1978 IAEA Safety Mission
ML19269C9021979-02-0202 February 1979
Responds to NRC Inquiry Re Choice of Custom Rather than Standardized Design for NSSS & Balance of Plant.Reliability Was Primary Goal for Turbine Generators
ML20150E4121978-12-15015 December 1978
Forwards Copy of Amend 14 to RESAR-3S Documenting the Westinghouse 3411 Mwt Nuc Steam Supply Sys as Appl for 2-yr Extension of Preliminary Design Approval(PDA-7) for RESAR- 3S.None of Existing Matl in RESAR-3S Has Been Modified
ML20244A4211977-10-24024 October 1977
Forwards Topical Rept Re Fuel Rod Bow Penalties.Application & Affidavit for Withholding Rept Also Encl.Rept Provides Basis for near-term Rev to Fuel Rod Bow Penalties
1982-05-27
[Table view]
Category:VENDOR/MANUFACTURER TO NRC
MONTHYEARML20054K2421982-05-27027 May 1982
Requests Withholding,Per 10CFR2.790,of Info Transmitted by EP Rahe to Tp Speis
ML20054K2341982-05-27027 May 1982
Forwards Addl Data,Per 820413 Meeting W/Westinghouse,Nrc & Inel Re Fuel Rod Design & Info Re two-phase Reactor Coolant Pump Performance.Encls Withheld (Ref 10CFR2.790)
ML20039F6161981-12-29029 December 1981
Requests 2-yr Extension of RESAR-3S Preliminary Design Approval (PDA-7) to Allow for Continued Review of Significant New Safety Issues Raised Since TMI-2
ML19211A6641979-12-18018 December 1979
Forwards Amend 15 to RESAR-3S,in Response to NRC 791213 Request for Addl Info
ML20150E4121978-12-15015 December 1978
Forwards Copy of Amend 14 to RESAR-3S Documenting the Westinghouse 3411 Mwt Nuc Steam Supply Sys as Appl for 2-yr Extension of Preliminary Design Approval(PDA-7) for RESAR- 3S.None of Existing Matl in RESAR-3S Has Been Modified
1982-05-27
[Table view] |
Text
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U Water Reactor Nucien TechnologyDivision Westinghouse Electric Corporation Divisions # D sacss Pittsburgh Pennsylvania 1523J 3 F.ECEIVED g 5 JAN111982* h December 29, 1981 7/ a munnumetamma t)
N888 7 " NS-EPR-2537
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-- 16 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulations U.S. Nuclear Regulatory Com:nission 7920 Norfolk Avenue Bethesda, Maryland 20014
SUBJECT:
Request for Extension of the RESAR-3S Preliminary Design Approval
Dear Mr. Denton:
With regard to RESAR-3S, the Reference Safety Analysis Report for the Westing-house 3411 MWt Nuclear Steam Supply System, Westinghouse had submitted addi-tional information for a two-year extension of PDA-7 with letter NS-TMA-2179 dated December 18, 1979. This two-year extension will end this December 31, 1981. Because of the continued interest in a standardization program for the nuclear power industry, Westinghouse would like to keep the RESAR-3S PDA-7 administrative 1y active and not be allowed to expire.
Although this PDA does not directly address current licensing requirements for new applications (e.g., TMI Action Plan), there do exist significant aspects and technical areas that would not require re-review or change. The resultant benefits in both resource and time required by a regulatory review and Westinghouse'are significant.
It is requested that the Nuclear Regulatory Commission therefore provide an additional two-year administrative extension to PDA-7. Referencing this PDA would be' contingent upon addressing significant new safety issues raised since the TMI-2 accident.
Very truly yours,
--m p . . Rahe, Jr., Manager Nuclear Safety Department
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