ML13316B985
| ML13316B985 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 02/10/1989 |
| From: | Kirsch D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML13316B984 | List: |
| References | |
| 50-206-89-03, 50-206-89-3, NUDOCS 8902280026 | |
| Download: ML13316B985 (2) | |
Text
APPENDIX A NOTICE OF VIOLATION Southern California Edison Company Docket No. 50-206 P. 0. Box 800 License No. DPR-13 2244 Walnut Grove Avenue Rosemead, California 91770 During an NRC inspection conducted during the period January 9-20, 1989, a violation of NRC requirements was identified.
In accordance with the "General Statement Policy and Procedure for NRC Enforcement Actions", 10 CFR Part 2, Appendix C (1988), the violation is listed below:
10 CFR Part 50 Appendix B, Criterion V, is implemented by section 17.2.5 of the Southern California Edison Company Quality Assurance Program SCE-1-A, Amendment 11, which states in part:
"Activities affecting quality are prescribed by, and accomplished in accordance with appropriate instructions, procedures, and drawings."
General Procedure S0123-XV-5, Revision 2, TCN 2-7, titled "Nonconforming Material, Parts or Components", paragraph 6.2.1.3, requires that items found in use in the plant that are not in accordance with drawings or other design disclosure documents, are to be documented on a nonconformance report. A note under paragraph 6.2.2 of the same procedure states in part:
"Validation of an NCR should normally occur within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />...."
Contrary to the above:
As of January 11, 1989 a nonconformance report (NCR) had not been prepared to identify that a January 3, 1989 ultrasonic (UT) examination of eight inch diameter residual heat removal (RHR) piping adjacent to weld joint no. 5002-7, indicated the existing wall thickness was less than design requirements. The unanalyzed nonconforming wall thickness condition was first identified by the Westinghouse ISI group on January 3, 1989. After the Westinghouse ISI group reverified the UT wall thickness measurements on January 4, 1989, a sketch was prepared on that date, and provided to the licensee. The UT wall thickness measurements indicated eight inch diameter schedule 120 piping was installed during construction of the plant, instead of the schedule 160 piping identified in the applicable design drawings and documents.
This is a Severity Level IV violation (Supplement I).
PDC Fruf:
0
- -2 Pursuant to the provisions of 10 CFR 2.201, Southern California Edison Company is hereby required to submit a written statement of 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, 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) 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 Dated a Walnut Creek, California this L0_day of February 1989 D. F. Kirscfi, Chief Reactor Safety Branch 0II