ML20154C909

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Notice of Violation from Insp on 851226-27
ML20154C909
Person / Time
Site: Hatch Southern Nuclear icon.png
Issue date: 02/14/1986
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20154C896 List:
References
50-321-85-39, NUDOCS 8603050342
Download: ML20154C909 (2)


Text

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E_N_ CLOSURE 1 NOTICE OF VIOLATION i

Georgia Power Company Docket No. 50-321 Edwin I. Hatch, Unit 1 License No. DPR-57 i The following violation was identified during an inspection conducted on December 26 - 27, 1985. The Severity Level was assigned in accordance with the NRC Enforcement Policy (10 CFR Part 2, Appendix C).

Technical Specification 6.8.1 requires, in part, that " written procedures shall be established, implemented and maintained covering the applicable procedures recommended in Appendix 'A' of Regulatory Guide 1.33, Revision 2, February 1978 and covering surveillance and test activities of safety-related equipment."

Appendix A of Regulatory Guide 1.33, Revision 2, February 1978, recommended that equipment control (e.g. locking and tagging) be covered by written procedures.

Section 8.8.4 of Hatch Procedure 30AC-0PS-001-01, Revision 0, dated October 22, 1985 requires the shift supervisor to review the boundaries for adequacy and set additional clearance, if required.

Contrary to the above, the licensee failed to properly implement the procedure for tagging equipment for the situation described below:

a. On December 17, 1985, while issuing clearance 1-85-1675 of the repair of M0V 1E11-F004A under Maintenance Work Order 1-85-7120, Procedure

. 30AC-0PS-001-01 was not followed in that A0V 1E11-F065A was inadequately isolated.

(1) The Control Switch was tagged to the closed position.

(2) No gagging device was placed upon the air actuator.

(3) Repair work was allowed to commence which affected a penetration t

of the Residual Heat Removal System at MOV IE11-F004A, this being downstream of A0V 1E11 F065A.

b. On December 21, 1985, while conducting a Loss of Off-Site' Power test on electrical bus IE, the inadequate isolation of M0V 1E11-F004A resulted in an excess of 40,000 gallons of water being transferred, without control, from the suppression pool to the southeast corner room of the drywell reactor building.

This is a Severity Level IV violation (Supplement I).

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Georgia Power Company 2 Docket No. 50-321 Edwin I. Hatch, Unit 1 License No. DPR-57 i

l Pursuant to 10 CFR 2.201, you are required to submit to this office within 30 days of the date of this Notice, a written statement or explanation in reply,

. Including: (1) admission or denial of the alleged violation; (2) the reasons I

for the' violation if admitted; (3) the corrective steps which have been taken and the results achieved; (4) corrective steps which will be taken to avoid j

further violations; and (5) the date when full compliance will be achieved.

Security .cr safeguards information should be submitted as an enclosure to ,

facilitate withholding it from public disclosure as required by 10 CFR 2.790(d) i 3

or 10 CFR 73.21.

Date: Febuary 14. 1986 i

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