ML13333A365

Forwards Topics Deleted from Systematic Evaluation Program Review of Facilities.Requests Review & Identification of Errors within 30 Days from Receipt of Ltr

ML13333A365
Person / Time
Site:	San Onofre
Issue date:	04/16/1979
From:	Ziemann D Office of Nuclear Reactor Regulation
To:	James Drake SOUTHERN CALIFORNIA EDISON CO.
References
NUDOCS 7905090020
Download: ML13333A365 (7)

Text

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Local PDR ORB. #2 Reading Docket No. 50-206 NRR Reading VStello DEisenhut BGrimes RVcllmer Mr.Jams H Drke PR 6 1979 TJCarter

.James H. Drake WRussell Vice President QELD Southern California Edison Company OI&E (3) 2244 Walnut Grove Avenue DLZiemann Post Office Box 800 Rosemead, California 91770 HSmith DKDavis Dear Mr. Drake.

JRBuchanan This letter is to advise you of topics which have been deleted from the Systematic Evaluation-Program (SEP) review of your facility. Enclosure 1 is a list of topics b.eing deleted because the same safety issues are being reviewed as part of ongoing -generic issues. As indicated at the onset of the SEP many generic issues would not be evaluated in the SEP; however, the staff will consider any criteria resulting from the completion of the evaluation of a generic issue prior to the integrated assessment of your facility. is a list of topics that have been deleted from the review of your plant because they are not applicable to your facility or site.

Please review and identify any errors in these lists and provide your comments within 30 days of the date you receive this letter. If no response is received within that time, we will assume that you have no comments or corrections.

Sincerely,

Original ciped by Dennis L. Ziemann, -Chief Operating Reactors Branch 02 Division of Operating Reactors

Enclosures:

As Stated cc w/enclosures:

See next page

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NRC FORM 318 (9-76) NRCH 0240 U.S. GOVERNMENT PRINTING OFICEE: 1978 -

85 - 769

Mr.

James H. Drake 2

cc w/enclosures:

Charles R. Kocher, Assistant General Counsel Southern California Edison Company Post Office Box 800 Rosemead, California 91770 David R. Pigott Samuel B. Casey Chickering & Gregory Three Embarcadero Center Twenty-Third Floor San Francisco, California 94111 Jack E. Thomas Harry B. Stoehr San Diego Gas & Electric Company P. 0. Box 1831 San Diego, California 92112 U. S. Nuclear Regulatory Commission ATTN:

Robert J. Pate P. 0. Box 4167 San Clemente, California 92672 Mission Viejo Branch Library 24851 Chrisanta Drive Mission Viejo, California 92676 K M C, Inc.

ATTN:

Jack McEwen 1747 Pennsylvania Avenue, N. W.

Suite 1050 Washington, D. C. 20006.

CLOSURE 1 SAN ONOFRE 1 SEP TOPICS NOT REQUIRING REVIEW DUE TO ONGOING GENERIC LICENSING ACTIVITIES TOPIC V-1:

COMPLIANCE WITH CODES AND STANDARDS COMMENTS:

The Engineering Branch, DOR, is performing a review of all plants for compliance with inspection require ments of 10 CFR 50.55a(g).

TOPIC V-3:

OVERPRESSURE PROTECTION COMMENTS:

Listed as TASK A-26 in NUREG-0371, "TASK ACTION PLANS FOR GENERIC ACTIVITIES", Published date November 1978.

Generic letters issued to PWR facilities in August 1976.

Specific criteria has been identified to be used in the design of modifications intended to preclude exceeding the limits of 10 CFR 50, Appendix G.

TOPIC V-7:

REACTOR COOLANT PUMP OVERSPEED COMMENTS:

Listed as TASK B-68 in NUREG-0371, dated November 1978.

At this time no criteria has been developed for this task.

TOPIC V-8:

STEAM GENERATOR INTEGRITY COMMENTS:

Listed'as TASK A-3, 4, 5 of NUREG-0317, dated November 1978.

The TASK ACTION PLAN completely envelopes the scope of this topic review.

TOPIC V-13:

WATER HAMMER COMMENTS:

Listed as TASK A-2 in NUREG-0371, "TASK ACTION PLANS FOR GENERIC ACTIVITIES", Published date November 1978.

Generic letters sent to this facility May 1975.

TOPIC VI-2-B:

SUBCOMPARTMENT ANALYSIS COMMENTS:

Listed as TASK A-2 in NUREG-0371, "TASK ACTION PLANS FOR GENERIC ACTIVITIES", Published dated November 1978.

Guidance letters issued to PWR licensees October 1975.

Aprile16, 1979

0 0

SAN ONOFRE

-2 TOPIC VII-l-B:

TRIP UNCERTAINTY COMMENTS:

Staff evaluations, issued August 1978, state that review is being pursued independent of SEP to determine impact of instrument error and drift upon safety margins of trip setpoints, and that appropriate actions will be taken to assure that adequate safety margins are maintained.

TOPIC VII-4:

FAILURES OF NON-SAFETY SYSTEMS AND SELECTED ESF'S COMMENTS:

The scope of this topic is contained in TASK A-17 of NUREG-0371, November 1978. The staff is

.developing a method of review. Criteria has not been established for implementation.

TOPIC VII-5:

INSTRUMENTS FOR MONITORING ACCIDENTS COMMENTS:

TASK A-34 of NUREG-0371, November 1978.

Criteria under development.

TOPIC VII-6:

FREQUENCY DECAY COMMENTS:

The scope of this topic is completely addressed in TASK A-35 (2.C-10) of NUREG-0371, November 1978.

TOPIC VIII-1-A:

EFFECTS OF DEGRADED GRID VOLTAGE COMMENTS:

The scope of this topic is contained in TASK A-35 (C-2, 3, 4, and 5) of NUREG-0371, November 1978.

Initial letters sent to licensee August 1976.

SAN ONOFRE

-3 TOPIC IX-6:

FIRE PROTECTION COMMENTS:

This topic is being reviewed outside the SEPB as part of the ongoing licensing review implemented as a result of the Browns Ferry incident.

TOPIC XI-1:

APPENDIX I COMMENTS:

This topic is part of an ongoing licensing review for all facilities to implement the limits of the Appendix I to 10 CFR 50.

TOPIC XI-2:

RADIOLOGICAL MONITORING SYSTEMS COMMENTS:

Listed in NUREG-0371, November 1978, as TASK B-67, criteria and scope of review under development.

TOPIC XIII-2:

SAFEGUARDS/INDUSTRIAL SECURITY COMMENTS:

Ongoing licensing review to implement the require ments of 10 CFR 73.55.

TOPIC XV-22:

ANTICIPATED TRANSIENTS WITHOUT SCRAM COMMENTS:

TASK A-9 of NUREG-0371, November 1978, criteria for implementation under development.

TOPIC XV-23:

STEAM GENERATOR MULTIPLE TUBE FAILURES

-COMMENTS:'

This topic is being considered in conjunction with TASK A-2, 3, 4 of NUREG-0371.

No criteria has been established on this topic.

ENCLOSURE SAN.ONOFRE 1 SEP TOPICS NOT APPLICABLE TO SAN ONOFRE 1 TOPIC NO.

TITLE COMMENTS II-4-E Dam Integrity N/A to this unit site III-7-C Delamination of Prestressed Concrete N/A to this unit containment Containment design III-10-C Surveillance Requirements on BWR N/A BWR Safety Topic Recirculation Pumps IV-3 BWR Jet Pump Operating Indications N/A BWR Safety Topic V-2 Applicability of Code Cases N/A at this time. To be reviewed for any future modifications using references to Code Cases.

V-9 Reactor Core Isolation Cooling N/A BWR Safety Topic System V-12-A Water Purity of BWR Primary Coolant N/A BWR Safety Topic VI-2-A Pressure-Suppression BWR Containments N/A BWR Safety Topic VI-2-C Ice Condenser Containment N/A to this unit containment design VI-7-A-2 Upper Plenum Injection N/A to this unit design VI-7-A-4 Core Spray Nozzle Effectiveness N/A BWR Safety Topic VI-7.D Long Term Cooling Passives Failures N/A No current criteria VI-9-A Main Steam Line Isolation Seal N/A BWR Safety Topic System VI-10-B Shared Engineered Safety Features N/A to this unit site VII-7 Acceptability of Swing Bus Design N/A BWR Safety Topic on BWR-4 Plant XV-11 Fuel Assembly Misloading Reviewed on a routine basis as part of reload

-2 SAN ONOFRE 1 (CONTINUED)

TOPIC NO.

TITLE COMMENTS XV-13 Rod Drop Accidents N/A BWR Safety Topic Group I (BWR)

All N/A BWR DBE Review DBE Group VI DBE Topic XV-13 (Only) Uncontrolled N/A BWR DBE Review Rod Assembly Withdrawal at Power, at Low Power Startup, Rod Drop Accident