ML19321A847
| ML19321A847 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 05/19/1980 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19321A829 | List: |
| References | |
| 50-321-80-17, 50-366-80-17, NUDOCS 8007240285 | |
| Download: ML19321A847 (2) | |
Text
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APPENDIX A NOTICE OF VIOLATION Georgia Power Company License Nos. DPR-57 and NPF-5 Hatch Nuclear Plant Units 1 and 2 Based on the NRC inspection March 8 through April 11, 1980, 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 correspon-dence to you dated December 31, 1974.
A.
As required by Technical Specification 3.7.C.1, the integrity of the secon-dary containment shall be maintained.
10 CFR 50, Appendix B, Criterion XVI, implemented by Hatch Quality Assurance Manual, Section 16, paragraph 16.1, states in part that measures shall be established to assure that conditions adverse to quality are promptly identified and corrected, and in any case of significant conditions adverse to quality, the measures shall assure that the cause of the condition is determined and corrective action taken to preclude repetition.
Contrary to the above, secondary containment integrity has been compromised sixteen times in the past year as reported in Licensee Event Report (LER) 50-321/80-28. The failure to correct this long-term problem constitutes ineffective corrective action and was the subject of an identical citation in NRC Report 50-321/79-11 and 50-366/79-15 dated May 18, 1979.
This is an infraction. A similar item was brought to your attention in our letter dated May 18, 1979.
B.
As required by Technical Specification 6.9.1.8.i, performance of systems that require remedial action or corrective measures to prevent operation in a manner less con e vative than assumed in the accident analyses shall be reported to the NRC sithin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Technical Specification 6.9.1.9.b requires that conditions leading to operation in a degraded mode permitted by a limiting condition for operation be reported within 30 days.
Contrary to the above:
1.
A report was not made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the seismic design deficiency discovered on the Unit 2 residual heat removal system which required corrective action to assure that a portion of the system would not fail when subjected to a design, seismic event. This event was docu-mented in LER No. 50-366/80-12.
2.
AreportwasnotmadetotheNRC'within30daysofthe# failure of the Unit 1 "10" diesel generator manual voltage regulato: on February 26, 1980.
This was documented in plant deviation report No. 1-80-101.
A 8007240M6
- 9 Georgia Power Company Appendix A Hatch Nuclear Plant Units 1 and 2
' Notice of Violation 3.
A report was not made to the NRC within 30 days of the failure of the Unit I standby PSW Pump during surveillance (HNP-1-3801) performed on January 30, 1930 which was documented in plant deviation report No.
1-80-56.
These events constitute an infraction.
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