ML13330B353
| ML13330B353 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 07/15/1988 |
| From: | Medford M Southern California Edison Co |
| To: | NRC Office of Administration & Resources Management (ARM) |
| References | |
| NUDOCS 8807220100 | |
| Download: ML13330B353 (2) | |
Text
Southem California Edison Company P. 0. BOX Boo 2244 WALNUT GROVE AVENUE ROSEMEAD, CALIFORNIA 91770 M.O.MEDFORD TELEPHONE MANAGER OF NUCLEAR ENGINEERING (818) 302-1749 AND LICENSING July 15, 1988 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Gentlemen:
Subject:
Docket No. 50-206 Steam Generator Inspection Technical Specification Reporting Requirements San Onofre Nuclear Generating Station Unit 1
Reference:
Letter, C. M. Trammell, NRC, to Kenneth P. Baskin, SCE, Steam Generator Inspection Report, April 15, 1988 The referenced letter took exception to Southern California Edison's (SCE's) position that NRC approval of steam generator inspection reports, submitted in accordance with the provisions of Technical Specification 4.16.E.4, is not required prior to resumption of power operation. The referenced letter requested that SCE resolve this issue within 60 days of receipt of the letter. Accordingly, the following information is provided to resolve this issue for San Onofre Unit 1.
A review of the reporting requirements delineated in the standard technical specifications provides the basis for the conclusion that NRC "approval" is not required prior to resumption of power operation. NUREG-0452, "Standard Technical Specifications for Westinghouse Pressurized Water Reactors, Revision 4 (STS)", indicates that when C-3 results are obtained, a reportable occurrence report shall be made in accordance with Specification 6.9.1.
This has since been revised, by the not yet issued Revision 5, to require NRC prompt notification in accordance with 10 CFR 50.72 and detailed reporting in a Special Report pursuant to Specification 6.9.2., filed prior to resumption of power operation. C-3 results are equivalent to the results described in San Onofre Unit 1 Technical Specification 4.16.E.4. The requirements of either of these reporting guidelines specify that the licensee should report the occurrence or condition and specify corrective actions taken to mitigate the condition. There is no discussion of any NRC approval of the report or approval prior to resumption of plant operation. Accordingly, it is determined that SCE should be reporting steam generator inspection results that meet the criteria described in Technical Specification 4.16.E.4, along with a technical discussion of any corrective actions and the appropriateness of these actions, prior to resumption of power operation.
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Document Control Desk July 15, 1988 SCE Proposed Change No. 176, currently under NRC review, proposes to revise the reporting requirements of Technical Specification 4.16.E.4 to require a report and NRC approval under the special report provisions of Technical Specification 6.9.2.
Based upon the previous discussion, Technical Specification 6.9.2 is an appropriate reporting requirement and the specification of NRC approval goes beyond the STS requirements. The report will be submitted identifying the date for return to power and allowing sufficient time for NRC review and decision regarding the corrective actions.
Based on discussions above, Proposed Change No. 176 will satisfactorily resolve this matter. If you have any questions, please let me know.
Very truly yours, cc: J. B. Martin, Regional Administrator, NRC Region V F. R. Huey, NRC Senior Resident Inspector, San Onofre Units 1, 2 and 3