Letter Sequence Request |
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MONTHYEARML13319A7181980-08-0808 August 1980
Summary of 800710 Meeting W/Util in Bethesda,Md Re Results of Steam Generator Insps & Corrective Actions
Project stage: Meeting
ML13330A1541980-11-19019 November 1980
Immediate Action Ltr,Confirming 801119 Telcon Re Steam Generator Repairs.Util Will Not Proceed W/Production Insertion Phase W/O Prior NRC Review & Approval
Project stage: Other
ML13330A1801980-11-28028 November 1980
Forwards Ofc of Nuclear Reactor Regulation Interim Assessment Re Sleeving of San Onofre,Unit 1 Steam Generator Tubes. Util May Proceed W/Production Insertion Phase of Steam Generator Tube Repairs
Project stage: Other
ML13330B1001980-11-28028 November 1980
Forwards Eia Re Sleeving Project
Project stage: Other
ML13330B1021980-11-28028 November 1980
Eia Supporting Proposed Mods Re Sleeving Project
Project stage: Other
ML13330A1821980-11-30030 November 1980
Interim Assessment of Sleeving of San Onofre,Unit 1 Steam Generator Tubes
Project stage: Other
ML13316A5201980-12-10010 December 1980
Forwards Application to Amend App a Tech Specs,Sections 2.1,3.5.2 & 3.11.Westinghouse Rept & Certificate of Svc Encl
Project stage: Request
ML13330A2361981-03-0505 March 1981
Forwards Proprietary & Nonproprietary Versions of Westinghouse rept,NS-MFSE-81-054, Technical Evaluation Rept for Hybrid Sleeve. Affidavit Also Encl.Proprietary Version Withheld (Ref 10CFR2.790)
Project stage: Other
ML13331B4381981-03-31031 March 1981
Nonproprietary Version of Technical Evaluation Rept for Hybrid Sleeve
Project stage: Other
IR 05000261/19810101981-04-10010 April 1981
IE Safety Insp Rept 50-261/81-10 on 810302-04.Noncompliance Noted:Failure to Perform Adequate Survey or Evaluation & Preserve Survey Records
Project stage: Request
ML13311B1191981-05-0505 May 1981
Forwards Endorsement 70 to Maelu Policy MF-38, & Endorsements 5 to Maelu & ANI Draft Master Policy Binders XB-10 & EB-10
Project stage: Request
ML13317A6321981-06-0808 June 1981
Safety Evaluation Supporting Amend 55 to License DPR-13
Project stage: Approval
ML13317A6301981-06-0808 June 1981
Forwards Amend 55 to License DPR-13,safety Evaluation,Eia & Notice of Issuance & Availability.Amend Authorizes Changes to App a Tech Specs to Allow Facility to Resume Cycle 8 Power Operation
Project stage: Approval
ML14133A4591981-06-0808 June 1981
Amend 55 to License DPR-13,authorizing Changes to App a Tech Specs & Bases to Allow Facility to Resume Power Operation for Cycle 8
Project stage: Other
ML13317A6341981-06-0808 June 1981
Notice of Issuance & Negative Declaration of Amend 55 to License DPR-13
Project stage: Approval
ML13317A6331981-06-0808 June 1981
Eia Supporting Amend 55 to License DPR-13
Project stage: Other
ML13308A8241983-01-19019 January 1983
Requests Info Re Steam Generator Leaks & Generator Tube Degradation.Congressman Unable to Attend 821213 Subcommittee Hearing Where Info Was Presented
Project stage: Other
1981-03-31
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Text
0p Southern California Edison Company P. O. BOX 800 2244 WALNUT GROVE AVENUE ROBERT DIETCH ROSEMEAD, CALIFORNIA 91770 T-'LEPHONE vcses December 10, 1980 e
C~gg VICE PRE5IDENT Deebr101980 213-572-4144$
CZ.
Mr. H. R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Gentlemen:
Subject:
Docket No. 50-206 Amendment No. 95 San Onofre Nuclear Generating Station Unit 1 Enclosed are three executed and thirty-seven conformed copies of Amendment No. 95 in Docket No. 50-206. Amendment No. 95 consists of Proposed Change No. 100 to the Technical Specifications incorporated into Provisional Operating License No. DPR-13 as Appendix A.
Proposed Change No. 100 is a request to revise Appendix A Technical Specifications 2.1, "REACTOR CORE - Limiting Combination of Power, Pressure, and Temperature," 3.5.2, "Control Group Insertion Limits," and 3.11, "Continuous Power Distribution Monitoring," to allow San Onofre Unit 1 to be operated as described in the supporting report, "Reload Safety Evaluation, San Onofre Nuclear Generating Station, Unit 1, Cycle 8, Revision 1," dated October, 1980. This revision to the Reload Safety Evaluation is provided to consider the impact of the core flow reduction resulting from the steam generator modifications now underway at San Onofre Unit 1.
Accordingly, it is respectfully requested that the NRC promptly review and take appropriate action on the enclosed Proposed Change No. 100 to the Technical Specifications, and the supporting report prior to resumption of power operation which is scheduled to commence in the first quarter of 1981.
Also enclosed is Southern California Edison Company's Check No. T019756 dated December 4, 1980, in the amount-of $4,000.00 as required by 10 CFR 170.22.
Very truly yours, Enclosures
'9 GP
