ML13322A720

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Forwards Application for Amend 89 to License DPR-13 Consisting of Proposed Change 89 to Tech Specs 3.5, Instrumentation & Control, & 4.1, Operational Safety Items. Westinghouse Evaluation Withheld (Ref 10CFR2.790)
ML13322A720
Person / Time
Site: San Onofre Southern California Edison icon.png
Issue date: 03/31/1980
From: Dietch R
Southern California Edison Co
To: Harold Denton
Office of Nuclear Reactor Regulation
Shared Package
ML13322A721 List:
References
NUDOCS 8004030140
Download: ML13322A720 (3)


Text

DOCKET NO._

DATE: 4/7/aO NOTE TO NRC AND/OR LOCAL PUBLIC DOCUMENT ROOMS The following item submitted with letter dated

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.s being withheld from public disclosure in accordance with Section 2.790.

PROPRIETARY INFORMATION

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Distribution Service's Branch

Southern California Edison Company P. 0. BOX 800 2244 WALNUT GROVE AVENUE ROBERT DIETCH ROSEMEAD, CALIFORNIA 91770 VICE PRESIDENT TELE8HON1 March 31, 1980 Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Gentlemen:

Subject:

Docket No. 50-206 Amendment No. 89 San Onofre Nuclear Generating Station Unit 1 Enclosed are three executed and thirty-seven conformed copies of Amendment No. 89 in Docket No. 50-206.

Amendment No. 89 consists of Proposed Change No. 89 to the Technical Specifications incorporated into Provisional Operating License No. DPR-13 as Appendices A and B.

Proposed Change No. 89 is a request to revise Technical Specification Sections 3.5, "Instrumentation and Control" and 4.1, "Operational Safety Items", of the Appendix A Technical Specifications. These revisions are in response to NRC Staff review of LER's and Technical Specification requirements related to Control Rod Position Indication Systems (RPI) at Westinghouse PWR's and are necessary to assure compliance in accordance with our letters dated January 4, 1980 and February 14, 1980.

In order to comply with Proposed Technical Specification 3.5.4, Rod Position Indicating System, item C.l.a., a method of determining the position of a control rod using the movable incore detectors is required. Results k

obtained at equilibruim conditions indicate that a corre lation exists between axial offset in core power, and rod position. Data at non-equilibruim conditions will have to be obtained during the startup following refueling.

We therefore request that the effective date for this Technical Specification be deferred until 60 days after startup, scheduled to commence on June 1, 1980, in order to allow for the development of a procedure for the im plementation of this portion of the Technical Specifications.

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AAsC

Mr. H. R. Denton, Director March 31, 1980 Also enclosed is Southern California Edison Company's Check No. T016444 dated March 31, 1980, in the amount of $4,000.00 as required by 10CFR170.22.

Very truly yours, Enclosures