ML13330B265

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Forwards Request for Addl Info Re Generic Ltr 83-28,Item 4.2,Parts 1 & 2,concerning Response Time Testing for Reactor Trip Breakers.Response Requested within 60 Days of Receipt of Ltr
ML13330B265
Person / Time
Site: San Onofre Southern California Edison icon.png
Issue date: 03/15/1988
From: Trammell C
Office of Nuclear Reactor Regulation
To: Baskin K
Southern California Edison Co
References
GL-83-028, TAC-53148 NUDOCS 8803210449
Download: ML13330B265 (3)


Text

March 15, 1988 Docket No.: 50-206 DISTRIBUTION Docket File

-NRC & LPDRs Mr. Kenneth P. Baskin CTrammell Vice President GHolahan Southern California Edison Company JLee 2244 Walnut Grove Avenue OGC White Flint Post Office Box 800 PD5 Plant File Rosemead, California 91770 EJordan JPartlow JBradfute

Dear Mr. Baskin:

ACRS 10 A. Toalston

SUBJECT:

ITEM 4.2 OF GENERIC LETTER 83 SAN ONOFRE UNIT 1 (TAC NO. 53148)

In reviewing your letter of June 3, 1987 relating to response time testing of the reactor trip breakers, we have determined that the additional information identified in the enclosure is needed to continue our review. In order to maintain our review schedule, your response is requested within 60 days of your receipt of this letter.

The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.

Please contact us if you should have any questions regarding this request.

Sincerely, original signed by Charles M. Trammell, Project Manager Project Directorate V Division of Reactor Projects -

III, IV, V and Special Projects

Enclosure:

Request for Additional Information cc w/enclosure:

See next page

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3/p/ 88 OFFICIAL RECORD COPY 860321044 880315 PDR ADOCK 05000206 P

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Mr. Kenneth P. Baskin San Onofre Nuclear Generating Southern California Edison Company Station, Unit No. 1 cc Charles R. Kocher, Assistant Mr. Jack McGurk, Acting Chief General Counsel Radiological Health Branch James 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 Mr. Hans Kaspar, Executive Director Orrick, Herrington & Sutcliffe Marine Review Committee, Inc.

600 Montgomery Street 531 Encinitas Boulevard, Suite 105 San Francisco, California 94111 Encinitas, California 92024 Mr. Robert G. Lacy Mr. Dennis M. Smith, Chief Manager, Nuclear Radiological Programs Division San Diego Gas & Electric Company Governor's Office of Emergency Svcs.

P. 0. Box 1831 State of California San Diego, California 92112 2800 Meadowylew Road Sacramento, California 95832 Resident Inspector/San Onofre NPS U.S. NRC P. 0. 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 Director Energy Facilities Siting Division Energy Resources Conservation &

Development Commission 1516 - 9th Street Sacramento, California 95814 Regional Administrator, Region V U.S. Nuclear Regulatory Commission 1450 Maria Lane, Suite 210 Walnut Creek, California 94596

ENCLOSURE REQUEST FOR AflTIONAL INFORMATION ITEM 4.2, PART 1 AND 2, OF GENERIC LETTER 83-28 SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 1 DOCKET NO. 50-206 By letter to the NRC dated June 3, 1987, Southern California Edison gave their position that response time testing and trending of the undervoltage trip attachment of the reactor trip breakers (RTBs) at San Onofre 1 is not needed.

At San Onofre 1, the undervoltage (UV) and shunt trip attachments of the RTBs are actuated simultaneously by the protection system as well as by manual actuation. The present design does not allow on-line testing of the RTBs or the trip attachments. Although the trip attachments are independently tested in place during refueling outages, this occurs after the breaker has been tripped. Thus, the "as-found" response of the UV trip attachment cannot be determined. Although the breakers have never failed to trip on demand, there is no assurance that the breaker could be tripped, in particular if power were lost to the shunt trip attachment.

The licensee states that implementation of on-line testing of the RTBs would require installation of two additional bypass breakers, and that such an addition is complicated by space limitations. The staff is currently considering under Item 4.5.2 of Generic Letter 83-28 the safety implications of such changes versus the benefits of on-line testing.

The licensee has not addressed the possibility of design changes that would permit response time testing of the reactor trip breakers using only the UV trip attachment in the "as-found" condition during pre-planned shutdowns of the unit, where the advance notice of the shutdown is sufficient to set up necessary equipment. The licensee is requested to submit a plan for NRC staff evaluation that would permit such testing.