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MONTHYEARML13311A2341979-05-31031 May 1979
Analysis of Capsule F,Reactor Vessel Radiation Surveillance Program
Project stage: Other
ML13330A0341980-04-24024 April 1980
Forwards Analysis of Capsule F,Reactor Vessel Radiation Surveillance Program, & Tech Specs 3.1.3 for Combined Heatup,Cooldown & Pressure Limitations.Proposed Change to Tech Specs Will Be Submitted by 801231
Project stage: Request
ML13330A0351980-04-24024 April 1980
Tech Spec 3.1.3 for Combined Heatup,Cooldown & Pressure Limitations,Figures 3.1.3a-3.1.3d & Table 3.1.3.1 for Reactor Vessel Toughness Data (Unirradiated)
Project stage: Other
ML13302B0031981-03-0606 March 1981
Notification of 810309 Meeting W/Util in Bethesda,Md to Discuss Facility Emergency Plan
Project stage: Request
ML13317A6591981-06-0202 June 1981
Safety Evaluation Re Environ Qualification of safety-related Electrical Equipment Finding No Outstanding Items That Require Immediate Corrective Action.Deficient Items Replaced.Equipment Qualified for Low Probability Events
Project stage: Request
ML13323A2601981-10-31031 October 1981
Operating Instructions for SSH-3/FBA-13 Seismic Scram & Trip Sys
Project stage: Request
ML13309A0791981-11-0404 November 1981
Forwards Responses to Safety Evaluation of Environ Qualification of safety-related Electrical Equipment,Addl Info Not Addressed in Safety Evaluation & Revised Pages to
Project stage: Request
ML13317A8361982-01-25025 January 1982
Forwards Util 150-day Response to 810821 Request for Addl Info Re Pressurizer Thermal shock.Plant-specific Analyses Indicate That Vessel Integrity Will Be Maintained,Therefore Remedial Actions Not Warranted
Project stage: Request
ML13310B0841983-11-22022 November 1983
Requests Mod to Tech Spec 3.1.3, Combined Heatup,Cooldown & Pressure Limitations, Requiring License Amend Application to Update Figures Providing Limits for Reactor Pressure & Heatup/Cooldown of RCS
Project stage: Other
ML13310B1991984-02-0707 February 1984
Advises That Extension of Time Required Until 840229 to Respond to 840106 Request for Addl Info Re Transamerica Delaval Emergency Diesel Generators
Project stage: Request
ML13330A4361984-05-17017 May 1984
Application for Amend to License DPR-13,consisting of Proposed Changes 127,137 & 138.Changes Revise Limiting Conditions for Operation & Surveillance Requirements for Auxiliary Feedwater Sys
Project stage: Request
ML13310B4061984-05-17017 May 1984
Forwards Response to NRC Request for Addl Info on SEP Topic II-4.F Re Settlement of Foundations & Buried Equipment,Per NRC 840208 & 09 Meetings
Project stage: Request
ML13331A7791985-01-31031 January 1985
Forwards Evaluation & Request for Addl Info Re Util 840517 Tech Spec Change Request Re Combined Heatup,Cooldown & Pressure Limitations.Info Re Safety Margins for Closure Flange Region Requested 6 Months Prior to Start of Cycle 9
Project stage: RAI
ML13331A7811985-01-31031 January 1985
Evaluation of Util 840517 Proposed Tech Spec Change 137 Re Combined Heatup,Cooldown & Pressure Limitation.Clarification of Method for Determining That Beltline Region More Limiting than Closure Flange Region Requested
Project stage: Approval
ML13324A7941986-01-23023 January 1986
Forwards Assessment of Reactor Vessel Beltline Matls,Listing Current Values & Values at OL Expiration Date of RT Pressurized Thermal Shock,Required by 10CFR50.61(b)(1).No Further Action Required
Project stage: Other
ML13324A8161986-03-17017 March 1986
Forwards Revised Heatup & Cooldown Curves to Resolve Concerns W/Margins Associated W/Closure Flange Region,Per 840517 Amend Application 118.Addl Info Requested in Encl 2 to Ja Zwolinski to Kp Baskin Unnecessary
Project stage: Other
ML13316A9021986-05-21021 May 1986
Safety Evaluation Supporting Amend 92 to License DPR-13
Project stage: Approval
ML13316A8971986-05-21021 May 1986
Forwards Amend 92 to License DPR-13 & Safety Evaluation. Amend Modifies Tech Specs to Incorporate Updated RCS pressure-temp Limits
Project stage: Approval
ML13316A8991986-05-21021 May 1986
Amend 92 to License DPR-13,updating Tech Specs to Include Revised RCS pressure-temp Limits
Project stage: Other
ML13330B1521987-02-0202 February 1987
Forwards Safety Evaluation Re Projected Values of Matl Properties for Fracture Toughness Requirements for Protection Against PTS Events
Project stage: Approval
ML13330B1541987-02-0202 February 1987
Safety Evaluation Re Projected Values of Matl Properties for Fracture Toughness Requirements for Protection Against PTS Events.Issue Acceptably Resolved
Project stage: Approval
1983-11-22
[Table View] |
Text
Southern California Edison Company P. 0. BOX 800 2244 WALNUT GROVE AVENUE ROSEMEAD. CALIFORNIA 91770 K. P. BASKIN TELEPHONE MANAGER, NUCLEAR ENGINEERING (213) 572-1401 AND LICENSING April 18, 1980 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 Heatup and Cooldown Curves San Onofre Nuclear Generating Station Unit 1 Technical Specification 4.9, "Reactor Vessel Surveillance Program," for San Onofre Unit 1 requires that reactor pressure vessel material surveillance capsules be removed and the specimens analyzed to monitor the effects of neutron exposure on the vessel materials in the core region. Accordingly, Capsule F was removed in December, 1978 after approximately 10 calendar years (approximately 8 EFPY)) of station operation. The Westinghouse report entitled "Analysis of Capsule F from the Southern Cali fornia Edison Company, San Onofre Reactor Vessel Radiation Surveillance Program, May 1979, WCAP-9520", presents the results of the examination of Capsule F, twenty copies of which accompany this letter. The enclosed report is submitted for your information as required by Technical Specification 6.9.3.b.
The analysis presented in the enclosed report has resulted in a need to update the heatup and cool down curves of Figures 3.1.3a and 3.1.3b as specified in Technical Specification 3.1.3, "Combined Heatup, Cool down and Pressure Limitations".
In addition, due to changes in the methods used and additional data obtained, Figure 3.1.3d and Table 3.1.3.1 have been modified.
There fore.the entire Technical Specification 3.1.3 has been updated as required by Technical Specification 3.1.3B and
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Technical Specification 4.9.
The updated Technical Speci fication is included for your information as Enclosure 1, twenty copies of which also accompany this letter. The changes in wording of Technical Specification 3.1.3 were 0, u required to make it consistent with the new figures and the table.
80042 40
Mr. H.
April 18, 1980 As discussed with Mr. A. Burger of your staff by telephone on April 14, 1980 we will provide a Proposed Change to the Technical Specifications for San Onofre Unit 1, to require that in the future, updates to the Heatup and Cooldown Curves will be submitted for review and ap proval by the NRC as an amendment to the operating license.
We will use the Standard Technical Specifications for guidance in preparing the new Technical Specification.
It is expected that the Proposed Change to the Technical Specifications will be submitted by December 31, 1980 which provides sufficient time for implementation since the next surveillance capsule is not scheduled to be removed until after 14 EFPY.
If you require any additional information please contact me.
Very truly yours, Enclosures
