ML13323A618
| ML13323A618 | |
| Person / Time | |
|---|---|
| Site: | San Onofre |
| Issue date: | 09/21/1979 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML13323A615 | List: |
| References | |
| 50-206-79-12, NUDOCS 7911090157 | |
| Download: ML13323A618 (2) | |
Text
APPENDIX A Southern California Edison Company P. 0. Box 800 2244 Walnut Grove Avenue Rosemead, California 91770 Docket No. 50-206 Nctice of Vioatlon Based on the results of the NRC inspection conducted on July 31
- August 2, 1979, it appears that certain of your activities were not conducted in full compliance with the conditions of NRC License No. DPR-13 as indicated below.
A. Technical Specification 6.8.1 states, "Written procedures and administrative policies shall be established, implemented, and maintained that meet or exceed the requirements and recommendations of Sections 5.1 and 5.3 of ANSI N18.7-1976.".
ANSI N18.7-1976, "Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Plants," Section 5.3.7, requires that "Procedures shall also be provided for periodic calibration of measuring and test equipment used in activities affecting the quality of (safety-related) systems."
In response to Section 5.3.7, San Onofre Station Order S-E-115, "Requirements for the Calibration and Control of Measuring and Test Instrumentation," requires that "Type A instruments shall be calibrated at intervals not to exceed six months."
Contrary to the above, four (4) Type A Roylyn pressure gages, serial numbers 16878, 762310, 750147 and 762519, used as prime standards for safety-related equipment, were last calibrated prior to February 1, 1978.
This is an infraction.
B. Criterion II of 10 CFR Part 50, Appendix B, states in part, "The Quality Assurance Program shall provide control over activities affecting the quality of identified structures, systems and components, to an extent consistent with their importance to safety."
Section D.2 of Appendix D of the Final Safety Analysis Report for the San Onofre Nuclear Generating Station, Unit No. 1, reads in part, "The policies established by the 7911090
-2 Quality Assurance Program specify that corporate poTicies established shall meet regulatory requirements. This program is applicable to activities, including an ECP, which are related to plant equipment listed in Table D.."
Table D.1 shows that the boric acid transfer pump motors, refueling water pump motors, and recirculation pumps and motors are equipment subject to control under the station Quality Assurance Program.
Contrary to the above requirements, the Station Quality Assurance Program, Station Order S-A-112, does not identify the boric acid transfer pump motors, refueling water pump motors or the recirculation pumps and motors as equipment subject to the Quality AssuranCe Program requreen4 s.
This is a deficiency.