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MONTHYEARML20235Z4081987-10-16016 October 1987
Summary of Operating Reactors Events Meeting 87-35 on 871013.List of Attendees,Events Discussed,Significant Elements of Events & Summary of Reactor Scrams & Comparison of Wk Statistics W/Industry Averages Encl
Project stage: Meeting
ML13319A7911987-10-16016 October 1987
Forwards Description of ESF Single Failure Analysis,Per NRC 860923 Request,Resulting from 860730 Failure of PT-59 Which Identified Single Failure Susceptibility of Reactor Protection Sys.Final Rept Will Be Submitted by 871106
Project stage: Other
ML13336A0441987-10-20020 October 1987
Summary of 871009 Meeting W/Util in Bethesda,Md Re Licensee Identified Possible Failure in ESF Equipment.List of Attendees & Slides Used by Licensee Encl
Project stage: Meeting
ML13333A5941987-12-0101 December 1987
Forwards Revised Better Estimate Analysis for Cases 5 & 6 to Support Justification for Continued Operation for Remainder of Cycle.Better Estimate Analysis for Core Response During Main Steam Line Break (Cases 5 & 6) Also Encl
Project stage: Other
ML13333A6031987-12-0202 December 1987
Forwards Safety Evaluation Accepting Util 871016 Single Failures Analysis for Esf,Per 871009 Meeting.Justification for Interim Plant Operation Acceptable Until 871214,pending Further Analysis
Project stage: Approval
ML13333A6081987-12-0202 December 1987
Safety Evaluation Re Single Electrical Failures Affecting safety-related Function of Esfs.Util 871016 Justification for Continued Plant Operation Acceptable Until 871214. Operation Beyond 871214 Must Be Supported by Addl Analyses
Project stage: Approval
ML13333A6001987-12-0808 December 1987
Provides Addl Info Re ESF Single Failure Analysis,Including Discussion of Method Used to Determine Min Acceptable DNBR Applicable for Macbeth Correlation at Sys Pressures Established by Analysis,Per 871204 Request.Graph Also Encl
Project stage: Other
ML13333A6141987-12-0909 December 1987
Forwards Proprietary ESF Single Failure Analysis Re Min Value of Dnbr.Proprietary Calculation of DNBR & Supporting Affidavit Withheld (Ref 10CFR2.790)
Project stage: Other
ML13333A6321987-12-11011 December 1987
Safety Evaluation Supporting Util Justification for Interim Plant Operation Re ESF Single Failure Vulnerability
Project stage: Approval
ML13333A6271987-12-11011 December 1987
Forwards Safety Evaluation Re Util 871016 Submittal of ESFs Single Failure Analyses & 871201,08 & 09 Submittals of Analyses Justifying Operation of Plant for Remainder of Current Operating Cycle.Justification Acceptable
Project stage: Approval
ML13331B0101988-02-19019 February 1988
Forwards Fee for 871016 Application for Review of Justification for ESFs Single Failure Analysis,Per 880127 Request
Project stage: Request
ML13331B0581988-07-19019 July 1988
Advises That Calculation CAW-87-130 Will Be Withheld from Public Disclosure Per 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act of 1954,per 871209 Request
Project stage: Other
ML13336A0991988-07-27027 July 1988
Confirms Discussions on Closeout of Event 10237 Re Newly Discovered ESF Single Failure Vulnerability Reported on 871007.Final Review of Longer Term Corrective Action Being Conducted Under Tac 66624
Project stage: Approval
1987-12-02
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70 Southern California Edison Company P. 0.
BOX 800 2244 WALNUT GROVE AVENUE ROSEMEAD, CALIFORNIA 91770 M.O.MEDFORD TELEPHONE MANAGER OF NUCLEAR ENGINEERING December 9, 1987 (818) 302-1749 AND LICENSING U. S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, D.C. 20555 Gentlemen:
Subject:
Docket No. 50-206 Engineered Safety Features Single Failure Analysis San Onofre Nuclear Generating Station Unit 1 By letter dated December 8, 1987, SCE provided additional information regarding the better estimate end of life analysis of the core response during a main steam line break to support justification for continued operation. This information was provided in response to NRC Staff questions on the better estimate analysis submitted by letter dated December 1, 1987. SCE, at the request of NRC Staff, also committed to provide the minimum value of DNBR resulting from this transient analysis.
The purpose of this letter is to provide this value.
Provided as Enclosure 1 is the calculation of DNBR for the better estimate end of life steamline break for San Onofre Unit 1. As this enclosure contains information proprietary to Westinghouse Electric Corporation, it is supported by an affidavit (Enclosure 2) signed by Westinghouse, the owner of the information.
The affidavit sets forth the basis on which the information may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed in paragraph (b) (4) of Section 2.790 of the Commission's regulations. Accordingly, it is respectfully requested that the information which is proprietary to Westinghouse be withheld from public disclosure in accordance with 10CFR Section 2.790 of the Commission's regulations.
If you have any questions regarding this submittal, please contact me.
Very truly yours, cc: J. 0. Bradfute, NRR Project Manager, San Onofre Unit 1
- 3. B. Martin, Regional Administrator, NRC Region V F. R. Huey, NRC Senior Resident Inspector, San Onofre Units 1, 2 and 3 8712140275 871209 P
ADocK 05000206 PDR
