IR 07100130/2012011

Notice of Violation from Insp on 871130-1211.Violations Noted:Adequate Testing Not Performed to Ensure Valve Would Isolate on High Differential Flow Isolation Actuation Signal

ML20155G957
Person / Time
Site:	Hatch, 07100130
Issue date:	05/31/1988
From:	Julian C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20155G955	List: IR 07100130/2012011 ML20155G952
References
50-321-87-31, 50-366-87-31, NUDOCS 8806200154
Download: ML20155G957 (2)

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ENCLOSURE

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NOTICE OF VIOLATION Georgia Power Company Docket Nos. 50-321 and 50-366 Hatch License Nos.-DPR-57, NPF-5

During the Nuclear Regulatory Commission (NRC) inspection conducted on November 30 - December 11, 1987, violations of NRC requirements were identi-fled. -In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1988), the violations are listed below:

A.

10 CFR 50.59(b)(1) states that the licensee shall maintain records of changes in the facility and that these records must include a written safety evaluation which provides the bases for the determination that the change does not involve an unreviewed safety determination, Contrary to the above, the safety evaluation for Design Change Request

DCR 85-007, Revision 1 did not adequately detail the bases for determining that the addition of 'a 45-second delay timer relay to the Reactor Water Cleanup System (RWCV) values 2G31-F001 and 2G31-F004 was not an unreviewed safety question.

The determination did not consider the original design basis for the actuation or various failure mades, nor did it document any design basis' accidents that were reviewed for impact, or other systems and components that could have been affected by the change.

Additionally, this change made these valves exceed the Technical Specification (TS) Table 3.3.2-3, required response time of 13 seconds.

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

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B.

10 CFR 50, Appendix B, Criterion XI; and the licenseo's accepted Quality Assurance program, Final Safety Analysis Report (FSAR) Section 17.2.11, collectively require that apprcpriate tests be performed and documented to assure satisfactory performance of structures, svstems and components.

The FSAR, Appendix A, cormits to Regulatory Guide 1.33, Quality Assurance Program Requirements (Operations), which endorses /cerican National Standards Institute (ANSI) N18.7-1976, Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants.

Section 5.2.7 of this Standard requires that a suitable level of confi-dence in structures, systems, or components on which maintenance or modifications have been performed shall be ettained by performance testing.

Contrary to the 3bove, after maintenance was performed on RWCU System inboard isolation valve 1G31-F001 on December 25, 1984, adequate testing was not performed to ensure the valve would isolate on c high differential flow isolation actuation signal as required by TS in that, on January 5 and 10, 1985, the valve failed to close upon receiving this signal.

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addition, post-modification testing was not performed after installing a 45-second time delay relay in the RWCU system after performing Maintenance Work Order.'-85-401.

0906200154 880531 i

PDR ADOCK 05000321 Q

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Georgia Power Company

Docket Nos.30-321 and 50-366 Hatch License Not DPR-57, NPF-5 Pursuant to the provisions of 10 CFR 2.201, Georg.:, wer Company is hereby required to submit a written statement or explanatiw Nuclear Regulatory

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Commission, ATTN:

Document Control Desk, Washington,

^ 2 555, with a copy t

NRC Psesident to the -Regional Administrator, Region II, and a copy t Inspector, Hatch, within 30 days of the date of the let'

.ransmitting this Notice.

This reply should be clearly marked as a "Rt to a Notica of

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Violation" and should include [for each violation]:

(1) admission or denial of the violation, (2) the reason for the violation i# admitted, (3) the corrective steps which have bee; 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 wili be given to extending the response time.

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

FOR THE Nbu EAR REGULATORY COMMISSION

/N k-h& h Caudie A. Julian, Chief Operations Branch Division of Reactor Safety Dated at Atlanta, Georgia this 31th day of M3y 1988 s

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