ML20150B587

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Notice of Violation from Insp on 871202-04.Violations Noted: Valve Testing Not Performed in Accordance W/Approved Test Procedure & Licensee Failed to Provide Instructions for Fill & Vent of Portion of RHR Train a Piping
ML20150B587
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 02/19/1988
From: Julian C
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20150B585 List:
References
50-364-87-35, NUDOCS 8803170068
Download: ML20150B587 (2)


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ENCLOSURE 1 NOTICE-0F VIOLATION Alabata Power Company Docket No. 50-364 Farley Unit 2 License No. NPF-8 During the Nuclear Regulatory Comission (NRC) inspection conducted on December 2 - 4, 1987, a violation of NRC requirements was identified.

In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1987), the violation is listed below:

Technical Specification 6.8.1 requires that written procedures be implemented covering the activities recommended in Appendix A of Regulatory Guide 1.33, Revision 2,

1978.

Regulatory Guide 1.33, Appendix A includes administrative procedures for procedural. adherence and maintanance procedures.

FNP-0-AP-6, Procedure Adherence, and FNP-0-AP-16, Conduct of Operations, require adherence to all plant procedures except under emergency conditions, where adherence to the procedures will create an undue hazard to personnel, equipment, or public health and safety, or under a temporary procedure change.

FNP-0-AP-57, Preservice and Inservice Inspections, and FNP-0-AP-5, Surveillance Program Administrative Control, require tests to be performed in accordance with plant procedures.

FNP-0-AP-52, Equipment Status Control and Maintenance Authorization, and FNP-0-AP-5, Surveillance Program Administrative Control, require that directions be provided for the restoration of equipment and systems to service.

Contrary to the above, on November 27, 1987:

Operations personnel marked initial condition 3.2 of surveillance test procedure (STP) FNP-2-STP-11.6, Residual Heat Removal (RHR)

Inservice Test, as not applicable (NA).

The licensee departed from the test procedure initial condition which would have required taking "A" RHR train out of service and closing the "A" RHR pump suction isolation valves.

This departure occurred under non-emergency plant conditions and was not processed as a temporary procedure change.

As a result of the NA on initial cocdition 3.2, the valve testing was not performed in accordance with the approved test procedure.

Additionally, the licensee failed to. provide instructions for the fill and vent of' that portion of the RHR "A" train piping between valves 8811A and 8812A prior to its return to service.

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

8803170068 880219 PDR ADOCK 05000348 O

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Alabama Power Company 2

Docket No. 50-364 Farley Unit 2 License No. NPF-8 Pursuant to the provisions of 10 CFR 2.201, Alabama Power Company is hereby required to submit a written statement or explanation to the Nuclear Regulatory Commission, ATTN:

Document Control Desk, Washington, DC 20555, with a copy to the Regional Administrator, Region II, and a copy to the NRC Resident Inspector, Farley, within 30 days of the date of the letter transmitting this Notice.

This reply should be clearly marked as a "Reply to a Notice of Violation" and should include [for each violation]:

(1) admission or denia' of the violation, (2) the reason for the violation if admitted, (3) the correc;ive 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.

If an adequate reply is not received within the tima specified in this Notice, an order may be issued to show cause why the license should not be modified, suspended, or revoked or why such other action as may be proper should not be taken.

FOR THE NUCLEAR REGULATORY COMMISSION k'

Yi Caudle A. Julian, Chief Operations Branch Division of Reactor Safety Dated at Atlanta, Georgia this 19th day of February 1988 9

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