ML20042B376
| ML20042B376 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 01/28/1982 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20042B364 | List: |
| References | |
| 50-321-81-34, 50-366-81-34, NUDOCS 8203250260 | |
| Download: ML20042B376 (2) | |
Text
-
APPENDIX A NOTICE OF VIOLATION Georgia Power Company Docket Nos. 50-321 and 50-366 Hdtch 1 and 2 License Nos. OPR-57 and NPF-5 As a result of the inspection conducted on November 21 - December 20, 1981, and in accordance with the Interim Enforcement Policy, 45 FR 66754 (October 7,1980),
the following violations were identified.
A.
10 CFR 50 Appendix B, Criterion V requires that written procedures be implemented and Criterion XVI as implemented by Hatch Quality Assurance llanual, section 16, paragraph 16.1, requires that measures be established to assure that, for significant conditions adverse to quality, corrective action is taken to preclude repetition.
Contrary to the above, written procedures were not implemented and effective corrective action not taken in that on four different occasions within the past three years, the licensee has lost, misplaced or improperly documented transfer of special nuclear material (incore detectors) controlled by procedure HNP-1/2-9600 Special Nuclear Material Inventory and Transfer Control.
The four instances were reported in Licensee Event Reports 50-321/79-54, 50-366/79-112, 50-321/80-117, and 50-366/81-99.
This is a Severity Level V Violation (Supplement I.E.).
B.
10 CFR 50, Appendix B, Criterion V requires that activities affecting quality shall be prescribed by documented procedures which shall contain appropriate acceptance criteria for detennining that important activities have been satisfactorily accomplished. The accepted QA program for Unit 2, FSAR Section 17.2.5, also requires appropriate acceptance criteria in procedures.
Contrary to the above, appropriate acceptance criteria were not contained in plant procedure HNP-1/2-3160, Residual Heat Removal Pump Operability.
The surveillance procedure did not require individual verification of the room cooler auto start feature for each of the two Residual Heat Removal (RHR) pumps in the room.
This procedural deficiency was reported by the licensee in LER 50-321/81-105 as a result of the failure of the Unit 1 cooler to continue to run when one of the RHR pumps was stopped during a maintenance outage. A loose wire to a relay in the cooler actuation circuitr caused the malfunction. The wire had been loose, undetected by required rveil-lance, since 1975.
This is a Severity Level V Violation (Supplement I.E.).
C.
Technical Specification 6.9.1.f. requires that personnel error or procedural inadequacy which prevents or could prevent, by itself, the fulfillment of the functior.al requirements of systems required to cope with accidents 8203250260 B20317 PDR ADOCK 05000321 0
c__m Georgio Power Company 2
Docket Nos. 50-321 & 50-366 Notice of Violation License Nos. DPR-57 & NPF-5 analyzed in the SARs be reported witnin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the NRC regional office with a written report within 14 days.
Contrary to the above, when in September,1981, it was discovered that the dred rofA1 Cooler for 2E Pasidual Heat Removal (RHR) pump would not auto start as required by Technical Specification 3.5.K and described in FSAR Section 10.18, the licensee failed to make the required 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> oral and 14 day written reports to the NRC.
The licensee did, however, subnit a 30 day report (LER 50-321/81-105) describing the incident.
The area roaa cooler would not automatic start due to failure to tenninate a wire during a design change conpleted in 1975 and an inadequate surveillance procedure which prevented its detection.
This violation is applied to Unit 1 only.
This is a Severity level V Violation (Supplement I.E.).
D.
Technical Specification 3.7.6.1.b. requires that with the fire suppression water system inoperable, a special report shall be sutnitted by telephone within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the NRC Regional Of fice.
Contrary to the above, following a fire main rupture at 02:30 a.m. on December 15, 1931, the Regional Office was not notified of the event until 3:40 p.m. on December 16, 1981.
This violation is applicable to Unit 2 only.
This is a Severity Level V Violation (Supplement I.E.).
Pursuant to the provisions of 10 CFR 2.201, you are hereby required to subait to this of fice within thirty days of the date of this Notice, a written statement or explanation in reply, including:
(1) adatssion or denial of the alleged viola-tions; (2) the reasons for the violations if admitted; (3) the corrective steps which have been taken and the results achieved; (4) corrective steps which will be taken to avoid further violations; and (5) the date when full canpliance will be achieved.
Consideration nay be given to extending your response time for good Cause shown.
!jnder the authority of Section 182 of the Atomic Energy Act of 1954, as amended, this response shall be sutunitted under oath or offirnation.
Da te :_JAN a R 1992