ML13323A567
| ML13323A567 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 11/13/1978 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML13323A566 | List: |
| References | |
| 50-206-78-14, NUDOCS 7812210376 | |
| Download: ML13323A567 (2) | |
Text
APPENDIX A Southern California Edison Company P. 0. Box 800 2244 Walnut Grove Avenue Rosemead, California 91770 Docket No. 50-206 License No. DPR-13 Notice of Violation Based on the results of NRC inspections on October 10-13 and October 24-27, 1978, it appears that one of your activities was not in
'full compliance with conditions of your NRC Facility License No. DPR-13 as indicated below. This is an infraction.
10 CFR Part 50, Section 50.55a, "Codes and Standards," states in paragraph (g)(4)(ii) that, "The inservice examinations conducted during successive 40-month periods throughout the service life of the facility thereafter shall comply with those requirements in editions of the code and addenda in effect no more than 6 months prior to the start of each 40-month period."
The San Onofre Nuclear Generating Station proposed inservice inspection program submitted to the NRC on September 28, 1977, and authorized for implementation of the requirements of 10 CFR 50.55a(g) for the 40-month period beginning on January 1, 1978, states, in part, in Engineering Procedure S-V-2.10, that, '...the next forty (40) month inspection period for Class 1, 2 and 3 com ponents... must comply with Section XI of ASME Code through and including the Summer, 1975 Addenda...."
Paragraph IWA-2232 of the above code states, in part, for ultrasonic examinations where Appendix I is not applicable, that, "...the provisions of Article 5 of Section V shall apply..." and Tables IWB-2500 and IWB-2600 of the above code specify a volumetric and surface examination of reactor vessel closure studs and nuts, including threads in base material.
Contrary to the above, on October 12, 1978, the following examinations were not performed in accordance with the above code requirements and the examination methods used were not shown to provide results of demonstrated equivalence or superi ority to those specified in the code.
Appendix A (Con't.)
-2
- 1. Straight beam, axial scan, ultrasonic examination of reactor vessel closure studs 1-14, Class 1 components, utilized a back reflection technique for calibration rather than a calibration block equipped with reflec tors and establishment of a distance amplitude curve for evaluating indications as required by paragraph.T-525.2 of Article 5 of Section V.
- 2. Surface examinations of the reactor vessel closure'nuts 1-14, Class 1 components, did not include threads in the base material.