ML13330A458

Forwards Request for Addl Info Re Generic Ltr 83-28,Items 4.2.1 & 4.2.2, Required Actions Based on Generic Implications of Salem ATWS Events. Response Requested within 60 Days

ML13330A458
Person / Time
Site:	San Onofre
Issue date:	11/28/1984
From:	Zwolinski J Office of Nuclear Reactor Regulation
To:	Baskin K Southern California Edison Co
References
GL-83-028 LSO5-84-11-030, LSO5-84-11-30, NUDOCS 8411290462
Download: ML13330A458 (5)

Text

November K;8', 1984 Docket No. 50-206 LS05-84-11-030 Mr. Kenneth P. Baskin, Vice President Nuclear Engineering Licensing and-Safety Department Southern California Edison Company 2244 Walnut Grove Avenue Post Office Rox 800 Rosemead, California 91770

SUBJECT:

REQUIRED ACTIONS BASED ON GENERIC IMPLICATIONS OF SALEM ATWS EVENTS (GENERIC LETTER 83-28)

Re:

San Onofre Unit No. 1 The NRC staff has reviewed (1) your November 28, 1983 response to Items 4.2.1 and.4.2.2 of Generic Letter 83-28, and (2) the additional infor mation regarding Item 4.2.1 contained in your April 27, 1984 letter. To complete our review of these items we find that we need the additional information identified in the enclosure.

Please provide your response within 60 days of the receipt of this letter in order to expedite our review process.

This request for information was approved by the Office of Management and Budget under clearance number 3150-0011 which expires April 30, 1985.

Sincerely, John A. Zwolinski, Chief Operating Reactors.Branch #5 Division of Licensing DISTRIBUTION Docket PM NRC PDR OELD Local PDR ELlordan ORB Reading PFMcKee1 NSIC ACRS(10 JZwolinski SEPB Clamerson CMiles, OPA DL:ORB#5 DL R#5.

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-0,/84 8411290462 841128 PDR ADOCK 050002O6 P

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0 Mr. Kenneth P. Baskin. November 28, 1984 cc Charles R. Kocher, Assistant Joseph.0. Ward, Chief General Counsel Radiological Health Branch Jap-es Beoletto, Esquire State Department of Health Southern California Edison Company Services Post Office Box 800 714 P Street, Office Bldg. 8 Rosemead, California 91770 Sacramento, California 95814 David R. Pigott Orrick, Herrington & Sutcliffe 600 Montgomery Street San Francisco, California 94111 Dr.

Lou Bernath:

San Diego Gas & Electric Company P. 0. Box 1831 San Diego, California 92112 Resident Inspector/San Onofre NPS c/o U.S. NRC P. 0. Rox 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 Director Energy Facilities Siting Division Energy Resources Conservation &

Development Commission 1516 - 9th Street Sacramento, California 95814 U.S. Environmental Protection Agency Region IX Office ATTN:

Regional Radiation Representative 215 Freemont Street San Francisco, California 94105 John B. Martin,.Regional Administrator Nuclear Regulatory Commission, Region V 1450 Maria Lane Walnut Creek, California 94596

SAN ONOFRE NUCLEAR GENERATING STATION UNIT 1 REOUEST FOR ADDITIONAL INFORMATION GL 83-28, ITEMS 4.2.1 AND 4.2.2

1. Item 4.2.1 -

Periodic Maintenance Program for Reactor Trip Breakers.

1.1 Criteria for Evaluating Compliance with Item 4.2.1 The San Onfore Trip System utilizes Westinghouse DB-25 circuit breakers with DB-50 Undervoltage Trip Attachment (UVTA).

The primary criteria identified for an acceptable maintenance program for this-breaker is contained in the Westinghouse Maintenance Program for DB-50 Trip Switchgear, Revision 0, October 14, 1983. The NRC Staff, Equipment Qualification Branch, has reviewed and endorsed the Westinghouse Maintenance Program for DB-50 Switchgear.: Specifically, the criteria used to evaluate compliance include those items.in the Westinghouse program that relate to the safety function of the breaker supplemented by those measures that must be taken to accumulate data for trending.

1.2 Issues Relating to Item 4.2.1 The licensee's November 28, 1983 submittal indicates that the San Onofre Preventative Maintenance Procedure, for the Reactor Trip Switchgear, deviates from the Westinghouse program. The licensee states that the preventative maintenance is performed on each breaker on a one-year interval.

The licensee maintenance program for reactor trip breakers should include, on a six month basis:

1. Verification of trip bar freedom;

2. Retaining ring verification, 33 places;

3. Verification of nut and bolt tightness;

4. Verification of pole bases physical condition;

5. Verification of insulating link's physical condition;

6. Verification of wiring insulation and termination physical condition;

7. Verification of arc chutes physical condition;

.8. Verification of operation of auxiliary switches;

9. Verification of shunt trip attachment (STA) operation.

This program should include, on a six months basis and using pro cedure outlined in Westinghouse Maintenance Program:

1. Verification of operating mechanism alignment and freedom;.

2. Verification of arcing and main contacts physical condition;

3. Undervoltage Trip Attachment (UVTA) dropout oltage test and lubrication;

4. Inspection of positioning lever condition;

5. Functional test of the breaker prior to returning it to service.

The licensee's preventative maintenance program for the reactor trip breakers should also include on a refueling interva basis:

1. Verification of cell interlock operation;

2. Examination and cleaning of breaker enclosure;

3. Measurement of trip force required, using the procedure identified in the Westinghouse program;

4. Breaker response time for undervoltage trip;

5. Functional test of the breaker prior to returning it to service, using the procedure identified in the Westinghouse program.

The licensee should confirm that these nineteen items are in cluded in their preventative maintenance procedure for the Reactor Trip Switchgear and being performed on the frequencies.

described above, or that they will be included.

2. Item 4.2.2 - Trending of Reactor Trip Breaker Parameters to Forecast Degradation of Operability.

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g 2.1 Criteria for Evaluating Compliance with Item 4.2.2 Four parameters have been identified as trendable and are in cluded in the criteria for evaluation. These are (1)

.under voltage trip attachment dropout voltage, (2) trip force, (3) breaker response time for undervoltage trip, and (4) breaRer insulation resistance.

2.2 Issues Relating to Item 4.2.2 The licensee submittal states that "Data taken during the annual inspection" will be recorded and analyzed. "Trending data will be examined by the Maintenance Field Engineer and the Supervisor of Plant Maintenance.

Any abnormal trend will cause immediate action to be taken to investigate and correct the abnormality."

The licensee should provide a discussion of the technical criteria to be used for evaluating trend data.

Also identify how often the analyses will be performed and how the information derived from the analyses will be used to affect their periodic maintenance.

The licensee should also commito include the four parameters listed above, in the Criteria for Evaluating Compliance with Item 4.2.2, as trending parameters.

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