Letter Sequence Request |
|---|
|
|
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
[Table View] |
Text
REGULA@.Y INFORMATION DISTRIBUTICS8YSTEM (RIDS)
ACCESSION NBR:8802250027 DOC.DATE: 88/02/19 NOTARIZED: NO DOCKET #
FACIL:50-206 San Onofre Nuclear Station, Unit 1, Southern Californ 05000206 AUTH.NAME AUTHOR AFFILIATION MEDFORDM.O.
Southern California Edison Co.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Forwards fee for 871016 application for review of justification for engineered safety features single failure analysisaper 880127 request.
DISTRIBUTION CODE: AO1D COPIES RECEIVED:LTR _
ENCL SIZE:
TITLE: OR Submittal: General Distribution NOTES:License Exp date in accordance with 10CFR2,2.109.
05000206 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 LA 1
PD5 PD 5
TRAMMELL,C 1
INTERNAL: ACRS 6
ARM/DAF/LFMB 1
NRR/DEST/ADS7E4 1
NRR/DEST/CEB8H7 1
1 NRR/DEST/MTB 9H 1
NRR/DEST/RSB BE 1
1 NRR/DOEA/TSB11F 1
_-NRRA--MAS/ILRB12 1
1 OGC 15-B-18 1
REG FIL 01 1
1 RES/DE/EIB 1
EXTERNAL: LPDR 1
NRC PDR 1
NSIC 1
TOTAL NUMBER OF COPIES REQUIRED: LTTR 26 ENCL
0 0
Southern California Edison Company P. 0. BOX 800 2244 WALNUT GROVE AVENUE ROSEMEAD. CALIFORNIA 91770 M. 0. MEDFORD TELEPHONE MANAGER OF NUCLEAR ENGINEERING (818) 302-1749 AND LICENSING February 19, 1988 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
References:
- 1. Letter, Reba M. Diggs, NRC to Kenneth P. Baskin, SCE, January 27, 1988
- 2. Letter, M. 0. Medford, SCE to NRC, Engineered Safety Features Single Failure Analysis, dated October 16, 1987 Reference 1 requested that SCE remit an application fee of $150 for the Office of Nuclear Reactor Regulation (ONRR) review of the justification for continued operation for San Onofre Unit 1 submitted by Reference 2. This request was based upon the NRC's determination that the ONRR review of the Reference 2 submittal is subject to the fee provisions of 10 CFR 170.
In response to that request, enclosed is SCE's check in the amount of $150 in accordance with 10 CFR 170.12(c) and 170.21.
If you have any questions, please let me know.
Very truly yours, Enclosure cc:
J. B. Martin, Regional Administrator, NRC Region V F. R. Huey, NRC Senior Resident Inspector, San Onofre Units 1, 2 and 3 R. M. Diggs, Facilities Program Coordinator A00 8602250027 860219 C e PDR ADOCK 05000206 0
P PDR 4t A. -qm
