ML18130A487
| ML18130A487 | |
| Person / Time | |
|---|---|
| Site: | Surry |
| Issue date: | 06/11/1979 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18130A481 | List: |
| References | |
| 50-281-79-38, NUDOCS 7908240162 | |
| Download: ML18130A487 (1) | |
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APPENDIX A NOTICE OF VIOLATION Virginia Electric and Power Company Surry Power Station, Unit No. 2 License No. DPR-37 Based on the NRC inspection May 22-25, certain of your activities were apparently not conducted in full compliance with NRC requirements as indicated below.
These items have been categorized as described in correspondence to you dated December 31, 1974.
As required by 10 CFR, Part 50, Appendix B, Criterion Vas implemented by VEPCO's licensing submittal (Steam Generator Project, Surry Power Station, Unit Nos. 1 and 2-Revision 9), "Activities affecting quality shall be prescribed by documented instructions, procedures, or drawings of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures or drawings.
Instructions, procedures or drawings shall include appropriate quanti-tative or qualitative acceptance criteria for determining that important activi-ties have been satisfactorily accomplished.
VEPCO's Nuclear Power Station Quality Assurance Manual, Section 3S, Revision O, Paragraph 2.0 states that, in part, "The Steam Generator Replacement Project is a single design change.
Because of the magnitude of the project, it is subdivided into engineering task assignments (ETA)... " and Section 5S, Revision O, Paragraph 2.3 states, in part,
"... procedure revisions shall be considered 'field changes'".
Contrary to the above, on May 23, 1979, the licensee was replacing helicoils in the new steam generator lower assembly support feet by the use of a speed letter with attached instructions.
The instructions being used for helicoil replace-ment were issued by the cognizant responsible engineer with stated Westinghouse approval.
Even though the instructions were technically satisfactory, the instructions were not issued nor approved as specified by VEPCO's Nuclear Power Station Quality Assura?ce Manual.
This is a deficiency.
7908240 (ll2-