ML13333A457

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Forwards Revisions to Util 790913 Commitments Re Compliance w/short-term TMI Lessons Learned Task Force Requirements Per NUREG-0578
ML13333A457
Person / Time
Site: San Onofre 
Issue date: 12/14/1979
From: Baskin K
Southern California Edison Co
To: Eisenhut D
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0578, RTR-NUREG-578, TAC-44128 NUDOCS 7912270504
Download: ML13333A457 (2)


Text

Southern California Edison Company P. 0. BOX 800 2244 WALNUT GROVE AVENUE ROSEMEAD, CALIFORNIA 91770 K. P. BASKIN TELEPHONE

MANAGER, GENERATION ENGINEERING December 14, 1979 213-572-1401 Director, Office of Nuclear Reactor Regulation Attention:

Mr. D. G. Eisenhut, Acting Director Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Gentlemen:

Subject:

Docket No. 50-206 Implementation of NRC Short-Term TMI Requirements San Onofre Nuclear Generating Station Unit 1 The purpose of this letter is to clarify and revise our previous commitments with respect to compliance with the short-term TMI requirements established in NUREG 0578 as provided to us by your letter of September 13, 1979 as clarified by your letter of October 30, 1979 and numerous telephone discussions with representatives of the Regulatory Staff. Specifically:

1.

With respect to Lessons Learned Item 2.1.4, Containment Isolation, we intend to eliminate reliance on administrative controls to ensure that all automatically actuated containment isolation valves are closed prior to overriding the containment isolation signal.

Electrical interlocks will be provided such that the containment isolation signal cannot be overridden unless all automatically actuated containment isolation valves are closed.

This modification will be completed during the special January, 1980 outage.

2.

Also with respect to Lessons Learned Item 2.1.4, Containment Isola tion, we intend to provide the capability to open automatically actuated containment isolation valves individually following the overriding of the containment isolation signal; overriding the containment isolation signal will be possible only after containment pressure drops below the 2 psig containment isolation setpoint.

Based on conceptual engineering and estimating, it is believed that it may not be possible to complete this modification prior to the Fall, 1981 refueling outage based on an estimated procurement lead time of 18 months for containment electrical penetrations. We will continue efforts to improve this conceptual implementation schedule and advise you of any ability to complete this modification sooner than the Fall, 1981 outage.

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3.

With respect to Lessons Learned Item 2.1.8.a, improved Post-Accident Sampling Capability, we intend to comply with the informational submittal and procedure implementation requirements (without adherence to dose and time criteria for sampling and analysis) by January 1, 1980.

It is our understanding, based on discussions with representatives of the Regulatory Staff, that the above commitments together with our commitments contained in our letters of October 17, 1979 and Novemeber 21, 1979 represent compliance with all technical requirements established by the NRC as short-term TMI requirements with the possible exception of Lessons Learned Item 2.1.7.a.,

Automatic Initiation of Auxiliary Feedwater Systems for PWRS, which continues to be under consideration by the NRC at this time. If additional clarification of the above is required at this time, please let me know.

Sincerely,