ML13324A733

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Informs of Plans to Submit Proposed Tech Spec Change to Require Operation of All Reactor Coolant Pumps in Mode 3 W/Reactor Trip Breakers Closed
ML13324A733
Person / Time
Site: San Onofre 
Issue date: 10/17/1985
From: Medford M
SOUTHERN CALIFORNIA EDISON CO.
To: Zwolinski J
Office of Nuclear Reactor Regulation
References
TAC-65271, NUDOCS 8510210024
Download: ML13324A733 (1)


Text

Southern California Edison Company P. 0.

BOX 800 2244 WALNUT GROVE AVENUE ROSEMEAD, CALIFORNIA 91770 M. 0. MEDFORD TELEPHONE MANAGER. NUCLEAR LICENSING (818) 302-1749 October 17, 1985 Director, Office of Nuclear Reactor Regulation Attention:

Mr. 3. A. Zwolinski, Chief Operating Reactors Branch No. 5 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C.

20555 Gentlemen:

Subject:

Docket No. 50-206 Technical Specification 3.1.2 San Onofre Nuclear Generating Station Unit 1

Reference:

Letter M. 0. Medford (SCE) to J. A. Zwolinski (NRC), Technical Specification 3.1.2, dated August 30, 1985 By the referenced letter, Southern California Edison (SCE) informed you of a potential discrepancy between the San Onofre Unit 1 Technical Specifications and the plant's safety analysis assumptions.

Our letter stated that for the control rod bank withdrawal from subcritical accident in Mode 3, the DNB design basis may not be met with only one reactor coolant pump in operation, even though the Unit 1 Technical Specifications clearly permit this.

Our letter further stated that SCE was reviewing this problem with Westinghouse and, depending on the results of this review, a proposed change to the Unit 1 Technical Specifications would be submitted for NRC approval.

This letter is to inform you that SCE plans to submit a proposed Technical Specification change requiring operation of all three reactor coolant pumps in Mode 3 with reactor trip breakers closed. Since, as pointed out in the referenced letter, the potential for bank withdrawal is not present when the reactor trip breakers are in an open position, the Technical Specifications dealing with this case will remain the same as at present.

Until the new Technical Specifications become effective, the interim procedures described in the reference will continue to be implemented.

If you have any questions, please call me.

Very truly yours, 8510210024 851017 PDR ADOCK 05000206 4

P PDR cc: R. Dudley, NRC/NRR San Onofre Unit 1 Project Manager F. R. Huey, NRC Senior Resident Inspector, Units 1, 2 and 3