Letter Sequence Request |
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MONTHYEARML13330A3911981-08-28028 August 1981
Forwards Contractor Draft Technical Evaluation & NRC Safety Evaluation of SEP Topic VI-10.A Re Testing of Reactor Trip Sys & Esf.Proposes Mods to Tech Specs & Equipment to Implement Response Testing Program
Project stage: Draft Approval
ML13317A7411981-11-17017 November 1981
Forwards Draft Technical & Safety Evaluations of SEP Topic VII-2, ESF Sys Control Logic & Design. Requests Sufficient Info within 30 Days to Complete Safety Evaluation
Project stage: Draft Approval
ML13317A7351981-11-18018 November 1981
Forwards Eg&G Draft Technical Evaluation on SEP Topic VII-3, Electrical,Instrumentation & Control Feature of Sys Required for Safe Shutdown, & NRC Draft Safety Evaluation. Facility Meets Current Licensing Criteria
Project stage: Draft Approval
ML13310A2431982-04-30030 April 1982
Failure Modes & Effects Analysis for San Onofre Nuclear Generating Station Unit 1 Rod Control Sys
Project stage: Request
ML13317A1541982-06-0404 June 1982
Forwards Final Safety Evaluation Re SEP Topic VII-03, Sys Required for Safe Shutdown. Conclusions Have Been Modified. Basis for Revision Is Discovery That Component Cooling Water Surge Tank Level Indication Does Not Satisfy Criterion
Project stage: Approval
ML13310A7531983-01-0303 January 1983
Forwards Revised SER on SEP Topic IV-2, Reactivity Control Sys, Reflecting Comments Contained in .Results Will Be Used in Reviewing Licensee Rept of SEP Topic XV-8
Project stage: Other
ML13317A5161983-02-10010 February 1983
Forwards Final Technical Evaluation Rept of SEP Topic VII-1.A, Isolation of Reactor Protection Sys from Non-Safety Sys,Including Qualification of Isolation Devices. Present Isolation Schemes Need Justification
Project stage: Other
ML13317A5621983-03-30030 March 1983
Forwards Final SER for SEP Topic VII-2, ESF Control Logic & Design. Topic Complete.Topic Assessment May Be Revised If Facility Design Changed or Criteria Modified
Project stage: Approval
ML13317A1461983-04-28028 April 1983
Forwards Final SER Re SEP Topic VI-10.A Concerning Testing of Reactor Trip Sys & ESF & Including response-time Testing. Mods to Tech Specs & Equipment to Implement response-time Testing Recommended
Project stage: Approval
ML13310B2561984-02-24024 February 1984
Forwards Addl Info,Plans & Schedules to Perform Analyses for SEP Topics II-1.C,II-3.A,II-3.B,III-2,III-3.A,III-4.A, IV-2,V-5,VI-7.B,VI-7.C.2,VII-1.A & IX-5.W/three Oversize Figures.Aperture Cards Are Available in PDR
Project stage: Request
ML13310B3161984-03-30030 March 1984
Forwards Responses to Listed SEP Open Items,Per Util 840119, 0224 & 0304 Ltrs.Final Program in Response to SEP Topic III-3.C Re Inservice Insp of Water Control Structures Will Be Delayed Until 840420 Due to Incomplete Formal Review
Project stage: Other
1983-01-03
[Table View] |
Forwards Addl Info,Plans & Schedules to Perform Analyses for SEP Topics II-1.C,II-3.A,II-3.B,III-2,III-3.A,III-4.A, IV-2,V-5,VI-7.B,VI-7.C.2,VII-1.A & IX-5.W/three Oversize Figures.Aperture Cards Are Available in PDR| ML13310B256 |
| Person / Time |
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| Site: |
San Onofre  |
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| Issue date: |
02/24/1984 |
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| From: |
Medford M
Southern California Edison Co |
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| To: |
Crutchfield D
Office of Nuclear Reactor Regulation |
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| References |
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| TASK-02-01.C, TASK-02-03.A, TASK-02-03.B, TASK-03-02, TASK-03-03.A, TASK-03-04.A, TASK-04-02, TASK-05-05, TASK-06-07.B, TASK-06-07.C2, TASK-07-01.A, TASK-09-05, TASK-2-1.C, TASK-2-3.A, TASK-2-3.B, TASK-3-2, TASK-3-3.A, TASK-3-4.A, TASK-4-2, TASK-5-5, TASK-6-7.B, TASK-6-7.C2, TASK-7-1.A, TASK-9-5, TASK-RR NUDOCS 8402280276 |
| Download: ML13310B256 (2) |
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Text
Southern California Edison Company P. 0.
BOX BOO 2244WALNUTGROVEAVENUE ROSEMEAD. CALIFORNIA 91770 M.O. MEDFORD TELEPHONE MANAGER, NUCLEAR LICENSING February 24, 1984 (213) 572-1749 Director, Office of Nuclear Reactor Regulation Attention:
- 0. M. Crutchfield, Chief Operating Reactors Branch No. 5 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C.
20555 Gentlemen:
Subject:
Docket No. 50-206 Systematic Evaluation Program Integrated Assessment San Onofre Nuclear Generating Station Unit 1
Reference:
Letter, M. 0. Medford, SCE, to D. M. Crutchfield, NRC, dated January 19, 1984 The referenced letter provided responses to all of the Open Items resulting from the Systematic Evaluation Program Review. In that response, it was indicated that additional information, plans and schedules to perform the indicated analyses for selected topics would be provided by February 17, 1984. The enclosure provides these responses for the following topics:
Topic Title II-l.C Potential Hazards or Changes in Potential Hazards Due to Transportation, Institutional, Industrial and Military Facilities II.3.A Hydrologic Description II-3.B Flooding Potential and Protection Requirements 111-2 Wind and Tornado Loadings III-3.A Effects of High Water Level on Structures III-4.A Tornado Missiles IV-2 Reactivity Control System Including Functional Design and Protection Against Single Failures V-S Reactor Coolant Pressure Boundary Leakage Detection VI-7.B ESF Switchover from Injection to Recirculation Mode (Automatic ECCS Realignment) 8402280276 840224 PDR ADOCK 05000206 P
-PDR
Mr. D.
February 24, 1984 VI-1.-C.2 Failure Mode Analysis ECCS VII-l.A Potential Equipment Failures Associated with a Degraded Grid Voltage IX-5 Ventilation Systems If you have any questions or require additional information, please let me know.
Very truly yours, Enclosures