ML16340D507
| ML16340D507 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 06/17/1983 |
| From: | Kirsch D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML16340D506 | List: |
| References | |
| 50-275-83-20, NUDOCS 8306270344 | |
| Download: ML16340D507 (4) | |
Text
1 APPENDIX A NOTICE OP VIOLATION Pacific Gas and Electric Company P. 0.
Box 7442 San Francisco, California 94120 Docket No-50-275 Licensee No. DPR-76 As a result of the inspection conducted on May 23-June 3,
- 1983, and in accordance with NRC Enforcement, Policy, 10 CFR Part 2, Appendix C, the following violation was identified:
Technical Specification 6.9.1.11 states, in part, that "The REPORTABLE OCCURRENCES of Specifications 6.9,1,12 and 6.9.1.13 below, including corrective actions and measures to preveat recurrence, shall be reported to the HRC-
~."
Technical Specification 6.9.1.12 lists the types of events which shall be reported by telephone within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Director of the Regional Office, or his designate, aad confirmed by telegram, mailgram or facsimile no later than the first, working day following the event, with a written followup report within 14 days.
Technical Specification 6.9.1.12.i describes a type of eveat which shall be reported pursuant to Technical Specification 6.9.1.12 and states as follows:
1 "Performance of structures,
- systems, or components that requires remedial action or corrective measures to prevent. operation in a manner lese conservative than assumed in the accident analyses in the safety analysis report or Technical Specifications bases; or discovery during unit life of conditions aot specifically coasidered in the safety analysis report or Technical Specifications that require remedial action or corrective measures to prevent the existence or development of aa unsafe condition."
~ I Contrary to the above requirements, oa December 17, 1982 the licensee identified that certain areas of Veld No. VIB-RC-2-17 were less than. the minimum wall thickness specified by design and the applicable
- codes, Weld No. WIH-RC-2-17 is in Loop No.
2 of the Reactor Coolant System.
This condition was not reported to the NRC until May 10, 1983.
This is a Severity Level IV Violation (Supplement I).
PDR ADOCK 05000275 9
Purusant to the provisions of 10 CFR 2.201, Pacific Gas and Electric Company is hereby required t.o submit.
l.o this of.ic within thirty days of the date of this notice, a written statement or explanation in reply, including:
(1) the corrective steps which have been taken and the results achieved; (2) corrective steps which wil.l be taken to avoid further items of noncompliance; and (3) the date when full compliance will be achieved.
Consideration may be given to ext.ending your response time for good cause shown.
"U> ( 7',983 Date D. F. Kirsch, Chief Reactor Projects Section No.
3