ML13310A950
| ML13310A950 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 09/07/1983 |
| From: | Krieger R Southern California Edison Co |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML13310A952 | List: |
| References | |
| NUDOCS 8309120436 | |
| Download: ML13310A950 (2) | |
Text
Southern California Edison Company P. 0. BOX 800 2244 WALNUT GROVE AVENUE ROSEMEAD. CALIFORNIA 91770 September 7, 1983 Director, Office of Nuclear Reactor Regulation Attention:
Mr. H. R. Denton U. S. Nuclear Regulatory Commission Washington, D.C.
20555 Gentlemen:
Subject:
Docket No. 50-206 Amendment No. 112 San Onofre Nuclear Generating Station Unit 1 Amendment No. 112, submitted by letter dated July 20, 1983, consists of Proposed Change No. 120 to the Technical Specifications incorporated into Provisional Operating License No. DPR-13 as Appendices A and B. Subsequent to this submittal, discussions with members of the Regulatory Staff indicated the need to incorporate additional information into the proposed change in order that the submittal stand as a more comprehensive document. This need resulted from recent changes to 10 CFR Parts 2 and 50 concerning significant hazards consideration and requirements for prior notice to the general public and to state officials. In reference to Proposed Change No. 120, this entailed including in the Proposed Change the existing Technical Specifications which would be revised and elaborating on the information contained in the Safety Analysis of the Proposed Change.
For this reason, please find enclosed copies of revised Proposed Change No. 120.
The information contained in the revised Proposed Change supercedes the original Proposed Change No. 120. Change bars are used to indicate the areas where additional information has been included or previous information has been revised.
It should also be noted that upon inspection of the Proposed Change a discrepancy between proposed Technical Specification 3.8.A.4 and the corresponding basis was discovered. Specifically, the Proposed Technical Specification establishes a requirement that a minimum shutdown margin of 5% A1 K/K be maintained during refueling while the corresponding basis states that during refueling the reactor coolant system is filled with borated water to a minimum boron concentration of 2900 ppm.
In order to be consistent with the proposed Technical Specification, the corresponding basis has been changed and is reflected in the enclosed revised Proposed Change.
8309120436 830907 PDR ADOCK 05000206 PDR ts
Mr. H.
September 7, 1983 SCE considers the revised Proposed Change to be sufficiently comprehensive to satisfy the requirements of 10 CFR Parts 2 and 50 concerning significant hazards consideration and prior notice to the general public and state officials.
If you have any questions or desire additional information, please contact me.
Very truly yours, R. W. Kriege Supervising Engineer San Onofre Unit 1 Licensing Enclosure cc: J. B. Martin, Regional Administrator, NRC Region V J. 0. Ward, Chief, Radiological Health Branch, State Department of Health Services