ML14138A118
| ML14138A118 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 02/01/1983 |
| From: | Paulson W Office of Nuclear Reactor Regulation |
| To: | Dietch R Southern California Edison Co |
| References | |
| TASK-06-07.A3, TASK-6-7.A3, TASK-RR LSO5-83-02-004, LSO5-83-2-4, NUDOCS 8302070612 | |
| Download: ML14138A118 (4) | |
Text
February 1, 1983 Docket No. 50-206 LS05-83-02-004 Mr. R. Dietch, Vice President Nuclear Engineering and Operations Southern California Edison Company 2244 Walnut Grove Avenue Post Office Box 800 Rosemead, California 91770
Dear Mr. Dietch:
SUBJECT:
SEP TOPIC VI-7.A.3, ECCS ACTUATION SYSTEM FINAL SAFETY EVALUATION REPORT FOR THE SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 1 The enclosed safety evaluation report is based on a technical evaluation that was provided to you in a letter from D. M. Crutchfield to R. Dietch dated November 18, 198), and comments provided in a letter from, R. W. Krieger to D. M. Crutchfield dated January 20, 1983.
With regard to the referenced topic, the staff has concluded that your facilit jmeets current licensing criteria for testing the electrical portions of the emergency core cooling system.
Sincerely,
Origival signed byi Walter A. Paulson, Project Manager Operating Reactors Branch No. 5 Division of Licensing
Enclosure:
As stated cc w/enclosure:
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Mr. R. Dietch, Vice Pres@)nt Docket No. 50206 Nuclear Engineering and Operations San Onofre 1 Southern California Edison Company 2244 Walnut Grove Avenue Post Office Box 800 Rosemead, California 91770 cc Charles R. Kocher, Assistant General Counsel James Beoletto, Esquire Southern California Edison Company Post Office Box 800 Rosemead, California 91770 David R. Pigott Orrick, Herrington & Sutcliffe 600 Montgomery Street San Francisco, California 94111 Harry B. Stoehr San Diego Gas & Electric Company Post Office Box 1831 San Diego, California 92112 Resident Inspector/ San Onofre NPS c/o U.S. Nuclear Regulatory Commission Post Office Box 4329 San Clemente, California 92672 Mayor City of San Clemente San Clemente, California 92672 Chairman Board of Supervisors County of San Diego San Diego, California 92101 California Department of Health ATTN:
Chief, Environmental Radiation Control Unit Radiological Health Section 714 P Street, Room 498 Sacramento, California 95814 U.S. Environmental Protection Agency Region IX Office ATTN:
Regional Radiation Representative 215 Freemont Street San Francisco, California 94111 Robert H. Engelken, Regional Administrator U.S. Nuclear Regulatory Commission, Region V 1450 Maria Lane Walnut Creek, California 94596
SYSTEMATIC EVALUATION PROGRAM TOPIC VI-7.A.3 SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 1 TOPIC: VI-7.A.3, ECCS Actuation System I.
INTRODUCTION The ECCS actuation system was reviewed with respect to the testability of operability and performance of individual active components of the system and of the entire system as a whole under conditions as close to the design condition as practical.
The purpose of the reviews was to assure that all ECCS components (e.g., valves and pumps) are included in the component and system test and to assure that the scope of the periodic testing is adequate and meets the requirements of GDC 37. The technical specifications were also audited for large differences between the present test requirements and those in the Standard Technical Specifications.
II. REVIEW CRITERIA The current licensing criteria are identified in Section 2 of EG&G Report 0546J, "ECCS Actuation System."
III.
RELATED SAFETY TOPICS AND INTERFACES The scope of review for this topic was limited to avoid duplicatton of effort since some aspects of the review were performed under related topics. The related topics and the subject matter are identified below.
Each of the related topic reports contain the acceptance criteria and review guidance for its subject matter.
Topic VI-3 Containment Pressure and Heat Removal Capability Topic VI-4 Containment Isolation System Topic VI-7 Emergency Core Cooling System Topic VI-7.C ECCS Single Failure Criterion and Requirements for Locking Out Power to Valves, IncludngTndependence of Interlocks on ECCS Valves Topic VI-9 Main Steam Isolation Topic VI-10.A Testing of Reactor Trip System and Engineered Safety Features, Including Response Time Testing Only Topic VI-10.A is dependent on the present topic information for completion. Response time testing is addressed in Topic VI-10.A
-2 IV. REVIEW GUIDELINES The review guidelines are presented in Sectionsi3-and 4 of Report 0546J.
V.
EVALUATION Report 0546J describes the extent to which our contractor determined that the ECCS actton system ts tested,.except for the question of response time testing. In summary, neither the safety injection system nor the recircu lation system meet the review criterta. A subsequent letter from R. W.
Krieger to D. M. Crutchfield, pointed out that the technical evaluation was based on outdated information.
The ECCS logic is a part of the diesel generator sequencers. The testing of these sequencers is addressed in SEP Topics VI-4 and VIII-2. The testing of the recirculation heat exchanger and/or protection against its failure is addressed in SEP Topic V-10.A.
Full flow systems tests of the ECCS at power is not possible, since the loss of the feedwater to the steam generators would cause a reactor trip. The staff's review of the technical specifications through Amendment 62, indicated an acceptable design.
VI.
CONCLUSION Based upon our review of our contractor's evaluation and the technical spectfications, the staff concludes that San Onofre Unit 1 conforms to current licensing criteria.