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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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)NS-EPR-2607 SED-SA-00052 Nucleariechnology Division Westinghouse Water Reactof Electric Corporation Divisions sc,333 PittsburghPennsyIyania15230 (412) 373-4868 May 27, 1982 1
Mr. Themis P. Speis, Assistant Director l Reactor Safety
- Office of Nuclear Regulatory Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Speis:
i
Subject:
RESAR-3S Data Acquisition via NRC to INEL In his letter of April 5,1982, Roger Mattson requested that additional data for the RESAR-3S NSSS be provided and requested that a meeting be held involving Westinghouse, NRC and INEL personnel. Such a meeting was conducted at Bethesda, Maryland, On April 13, 1982. The attendees were as follows:
from Westinghouse, R. P. Vijuk, R. ii. Kemper and P. A. Loftus; from NRC, J. Guttman, J. T. Han, D. Wheeler and N. Lauben; from INEL, A. Peterson, C. Dobbe and J. M. Cozzuol. A discussion of best-estimate core operational parameters was presented by Westinghouse at the subject meeting, and the additional information needs of NRC/INEL were also discussed.
Attachment 1 to this letter provides the additional data for RESAR-3S plants which NRC/INEL attendees identified as being necessary at the subject meeting. Attachment 2 documents the Westinghouse presentation of core power shape and peaking factor information as well as other information transferred at the meeting concerning two-phase reactor coolant pump performance, accumu-lator tanks, pressurizer heater rods, and reactor coolant system flow and loop layout parameters. This letter will serve to document that Westinghouse proprietary information was provided at the April 13 meeting.
The information provided at the meeting and repeated in Attachment 2 is to be treated as proprietary information. Likewise, the material in Attachment 1 is also to be treated as proprietary information. Since the material is not intended for docket at this time, a separate submittal for docket would be pre-pared as necessary if a specific licensing application to docket is intended at a later time.
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f000 8207010321 820527 PDR ADOCK 05000545 A PDR
SED-SA-00052 May 27, 1982 Correspondence with respect to proprietary aspects of this submittal should reference AW-82-30 and should be addressed to R. A. Wiesemann, Manager, Regulatory and Legislative Affairs, Westinghouse Electric Corporation, P.O. Box 355, Pittsburgh, Pennsylvania 15230.
Very truly yours, E. P. Rahe, M n ger Nuclear Safety epartment EPR/RMK/imj Attachments
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