ML13316B863
| ML13316B863 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 02/26/1988 |
| From: | Zimmerman R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML13316B862 | List: |
| References | |
| 50-361-87-31, 50-362-87-31, NUDOCS 8803140200 | |
| Download: ML13316B863 (2) | |
Text
APPENDIX A NOTICE OF VIOLATION Southern California Edison Company Docket No. 50-361 50-362 San Onofre Unit 2/3 License No. NPF-10 NPR-15 During an NRC inspection conducted during the period of November 22, 1987 through January 20, 1988, a violation of NRC requirements was identified. In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1987), the violation is listed below:
A.
10 CFR 50.73(a)(1) states in part:
"The holder of an operating license for a nuclear power plant (licensee) shall submit a Licensee Event Report (LER) for any event of the type described in this paragraph within 30 days after the discovery of the event."
10 CFR 50.73(a)(2) states that the licensee shall report any operation or condition prohibited by the plant's Technical Specifications.
Contrary to the above requirements, the licensee did not report the following conditions:
- 1. In February, 1987, the licensee identified that the Unit 2 steam generator code safety valves had been improperly adjusted in March, 1986, during the Cycle III refueling outage. During this period, the unit operated in a condition prohibited by Technical Specification Limiting Condition for Operation (L.C.O.)
3.7.1.1, in that 14 safety valves failed to satisfy the operability requirements of the Technical Specifications.
- 2. In March, 1987, the licensee identified that the Unit 3 steam generator code safety valves had been improperly adjusted in September, 1985, during the Cycle II refueling outage. During this period, the unit operated in a condition prohibited by Technical Specification L.C.O. 3.7.1.1, in that 15 safety valves failed to satisfy the operability requirements of the Technical Specifications.
This is a Severity Level IV violation (Supplement I).
Pursuant to the provisions of 10 CFR 2.201, Southern California Edison Company is hereby required to submit a written statement or explanation to the U.S.
Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, DC 20555 with a copy to the Regional Administrator, Region V, and a copy to the NRC Senior Resident Inspector, San Onofre, within 30 days of the date of the letter transmitting this Notice. This reply should be clearly marked as a "Reply to a Notice of Violation" and should include for each violation:
(1) 8803140200 880226 PDR ADIC:K::: 05000206.
EC:E
-2 the reason for the violation if admitted, (2) the corrective steps that have been taken and the results achieved, (3) the corrective steps that will be taken to avoid further violations, and (4) the date when full compliance will be achieved. If an adequate reply is not received within the time specified in this Notice, an order may be issued to show cause why the license should not be modified, suspended, or revoked or why such other action as may be proper should not be taken. Consideration may be given to extending the response time for good cause shown.
FOR THE NUCLEAR REGULATORY COMMISSION R. P. Zimme n, Chief Reactor Pro ects Branch Dated at Walnut Creek, California this,96-day of 1988