IR 05000522/2007026
| ML13323B003 | |
| Person / Time | |
|---|---|
| Site: | San Onofre, Skagit  |
| Issue date: | 08/06/1985 |
| From: | Johnson P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML13323B002 | List: |
| References | |
| 50-206-85-20, NUDOCS 8508210196 | |
| Download: ML13323B003 (2) | |
Text
APPENDIX A NOTICE OF VIOLATION Southern California Edison Company Docket.No. 50-206 2244 Walnut Grove Avenue License No. DPR-13 Rosemead, California 91770 As a result of the inspection conducted during the period of May 22 through July 26, 1985, and in accordance with NRC Enforcement Policy (10 CFR Part 2, Appendix C) the following violation was identified:
Technical Specification 6.8.1 requires, in part, that:
"Written procedures and administrative policies shall be established, implemented and maintained that meet or exceed the requirements and recommendations of ANSI N18.7-1976, Administrative Controls for Nuclear Power Plants; Appendix "A" of USNRC Regulatory Guide 1.33, Rev. 1, Quality Assurance Program Requirements (Operation)...."
Paragraph 8.b of Regulatory Guide 1.33, Revision 1, states in part that
"...implementing procedures are required for each surveillance test...listed in the technical specifications."
Paragraph 5.3 of ANSI Standard N18.7-1976 states, in part that:
"Activities affecting safety at nuclear power plants shall be described by written procedures of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions and procedures."
San Onofre Nuclear Generating Station Surveillance Procedure S01-12.3-2, Hot Operational Test of the Safety Injection and Containment Spray Systems, provides detailed instructions for performing Technical Specification required operability tests on the safety injection and refueling water pumps. Section 2.5.8 of this test procedure requires independent verification that the north refueling water pump discharge valve (CRS-306) is locked open before isolating the south refueling water pump by shutting its discharge valve (CRS-307).
Contrary to the above requirements on June 10, 1985, Unit 1 operations personnel performing this surveillance test did not perform independent verification that valve CRS-306 was locked open prior to shutting valve CRS-30 This is a Severity Level IV Violation (Supplement I) applicable to Unit PDR ADOCK 05000206 PDR
-2 Pursuant to the provisions of 10 CFR 2.201, Southern California Edison Company is hereby required to submit to this office 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 will be taken to avoid further items of noncompliance; and (3) the date when full compliance will be achieve Dated P. H. Johnson, Chief Reactor Projects Section 3