ML20214V026

Notice of Violation from Insp on 861005-09

ML20214V026
Person / Time
Site:	Hatch
Issue date:	12/01/1986
From:	Walker R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20214V005	List: IR 05000321/1986030 ML20214V001 ML20214V026
References
50-321-86-30, 50-366-86-30, NUDOCS 8612090502
Download: ML20214V026 (2)

Text

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ENCLOSURE 1 NOTICE OF VIOLATION

' Docket Nos. 50-321 and 50-366 Georgia Power Company License Nos. DPR-57 and NPF-5 Hatch iDuring the Nuclear Regulatory Comission (NRC) inspection conducted on The  !

October 5-9, 1986, violations of NRC requirements were identified.

In accordance with the " General

. violations involved maintenance activities.

' Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix.C (1986), the violations are listed below:

'A. Technical Specification 6.8.1.a requires the licensee to establish, imple-ment and maintain. written procedures covering the applicable activitiesAppendixin"A" Appendix A of Regulatory Guide 1.33, Revision 2, February.1978.

of Regulatory Guide 1.33 recommends establishment of procedures to control contamination and for the performance of safety-related maintenance.

Technical Specification 6.8.1.c requires the licensee to establish and

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implement procedures for the conduct of surveillance and test activities of safety related equipment.

Plant Procedure 62RP-RAD-017-0, Release Surveys for Trash and Materials Leaving Operating Buildings, requires that the Health Physics Technician at C-52 is responsible for ensuring that all persons exiting the control building use the monitors upon exit.

Preventive Maintenance Procedure 52PM-MNT-005-05, Revision 3. Limitorque Valve Operator Inspection, step 7.6.6.13, states in part, perform limit switch adjustment in accordance with 52GM-MNT-017-05, ' Limitorque Valve Operator Setup and Test. Procedure 52GM-MNT-017-OS was replaced by 52GM-MEL-022-0S contains the Procedure 52GM-MEL-022-0S on February 1986.

limit switch adjustment instruction.

Contrary to the above,

-1. The licensee failed to provide adequate procedures to control test i

activities on the 2C emergency diesel . generator on Monday, October 6 and Wednesday, October 8, 1986.

2. The requirement that personnel use the monitors when exiting the i

control building and that the HP technician ensure this is accomplished

! was not met in that on October 9,1986, a contractor was observed exiting l the RCA at Control Point C-52 without using the monitor, f

T 0

Georgia Power Company 2 Docket Nos. 50-321 and 50-366 Hatch License Nos. DPR-57 and NPF-5

3. In August 1986, for Maintenance Work Orders, 2-86-2136, 2-86-2137 and 2-86-54 the licensee failed to perform the required limit switch adjustments in accordance with Preventive Maintenance Procedure 52PM-MNT-005-0S.

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

B. Unit 1 Technical Specifications 3.7.D.1 and 4.7.D.1 and Unit 2 Technical Specifications 3.6.3 and 4.6.3.3 require that primary containment isolation valves listed be operable, and that the isolation times shall be demon-strated to be within the required limits.

Unit 2 Technical Specification 4.0.5 require that inservice testing of ASME Code Class 1, 2, and 3 valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code except where specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g)(6)(i). ASME Section XI defines stroke time as the time interval from initiation of the actuating signal to the end of the actuating cycle.

The E. I. Hatch Pump and Valve Test Plan also defines full-stroke time as that time interval from initiation of the actuating signal to the end of the actuating cycle.

Contrary to the above, the licensee does not stroke time test power operated valves from initiation of the actuating signal to the end of the actuating cycle as required by Technical Specifications and ASME Section XI and the licensee has not received specific written relief from the requirements of the ASME code that requires stroke time testing from initiation of the actuating signal to the end of the actuating cycle.

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

Pursuant to the provisions of 10 CFR 2.201, Georgia Power Company is hereby required to submit to this Office within 30 days of the date of the letter transmitting this Notice a written statement or explanation in reply including (for each violation): (1) admission or denial of the violation, (2) the reason for the violation if admitted, (3) the corrective steps which have been taken and the results achieved (4) the corrective steps which will be taken to avoid further violations, and (5) the date when full compliance will be achieved.

Where good cause is shown, consideration will be given to extending the response time.

FOR THE NUCLEAR REGULATORY COMMISSION

. k Roger D. Walker, Director Division of Reactor Projects Dated at Atlanta, Georgia this 1st day of December 1986