ML20217F588

Notice of Violations from Insp on 980208-0321.Violations Noted:Conditions Adverse to Quality Were Not Promptly Corrected from Nov 1993 to March 1998,util Failed to Correct Known Unit 1 & 2 TS Deficiency in Timely Manner

ML20217F588
Person / Time
Site:	Beaver Valley
Issue date:	04/22/1998
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20217F568	List: ML20217F564 ML20217F588 ML20217F595
References
50-334-98-01, 50-334-98-1, 50-412-98-01, 50-412-98-1, NUDOCS 9804280197
Download: ML20217F588 (2)

Text

. 1 ENCLOSURE 1 NOTICE OF VIOLATION Duquesne Light Company Docket Nos. 50-334,50-412 Beaver Valley Power Station 1&2 License Nos. DPR-66, NPF-73 During an NRC inspection conducted from February 8 to March 21 two violations of NRC requirements were identiksd. in accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," NUREG-1600, the violations are listed below:

A. 10 CFR 50, Appendix B, Criterion XVI (Corrective Action), requires, in part, that measures shall be established to assure that conditions adverse to quality, such as failures, deviations, defective material and equipment, and nonconformances are promptly identified and corrected.

Contrary to the above, conditions adverse to quality were not promptly corrected in that from November 1993 to March 1998, Duquesne Light Co. failed to correct a '

known Unit 1 and Unit 2 Technical Specification (TS) deficiency (TS degraded voltage setpoints) in a timely manner. The TS degraded voltage setpoints were non-conservative in that the setpoints were not sufficient to maintain minimum voltage requirements for safety-related equipment. The licensee failed to submit a TS amendment request to correct the setpoints. In addition, station procedures were not properly revised to assure that the emergency diesel generator would )

receive an automatic start signal at or above the bus voltage required by design.

Specifically,1) the reference in the procedure identified the TS values (which were non-conservative) and not the determined design basis values; 2) the procedure did not have explicit acceptance criteria that the setpoints would be within the design basis values as listed in a procedural attachment: 3) the step to notify the shift supervisor that the relay was below allowable values identified the non-conservative TS value rather than the design basis value.

This is a Severity Level IV violation (Supplement 1).

B. 10 CFR 50, Appendix B, Criterion ill (Design Control), requires, in part that design changes shall be subject to design control measures commensurate with those applied to the original design.

Contrary to the above, on February 18,1998, design control measures for a modification to the Unit 2 emergency diesel generators (EDGs) ground overcurrent trip isolation feature were inadequate. Specifically, the failure mode analysis for this design change did not fully evaluate failures of the quality assurance category 2 ground switch and resistor. The failure mode analysis also did not identify or evaluate an additional failure mode which had the potential to damage the EDG during surveillance testing if a fault occurred on the 4 kV line.

This is a Severity Level IV violation (Supplement 1).

Pursuant to the provisions of 10 CFR 2.201, Duquesne Light Company is hereby required to submit a written statement or explanation to the U.S. Nuclear Regulatory Commission, 9804280197 900422 PDR G

ADOCK 05000334 PDR  ;

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Enclosure 1 2 l

ATTN: Document Control Desk, Washington, D.C. 20555 with a copy to the Regional Administrator, Region 1, and a copy to the NRC Resident inspector at the facility that is the subject of this Notice, within 30 days of the date of the letter transmitting this Notice of Violation (Notice). This reply should be clearly marked as a " Reply to a Notice of l Violation" and should include for each violation: (1) the reason for the violation, or, if t

contested, the basis for disputing the violation or severity level, (2) the corrective steps that have been taken and the results achieved, (3) the corrective steps that will be taken to avoid further violations, and (4) the date when full compliance will be achieved. Your

! response may reference or include previous docketed correspondence, if the correspondence adequately addresses the required response if an adequate reply is not received within the time specified in this Notice, an order or a Demand for information may be issued as to why the license should not be modified, suspended, or revoked, or why l~

such other action as may be proper should not be taken. Where good cause is shown, consideration will be given to extending the response time.

If you contest this enforcement action, you should also provide a copy of your response to the Director, Office of Enforce nent, United States Nuclear Regulatory Commission, Washington, DC 20555-0001.

Because your response will be placed in the NRC Public Document Room (PDR), to the

[ extent possible, it should not include any personal privacy, proprietary, or safeguards information so that it can be placed in the PDR without redaction. If personal privacy or proprietary information is necessary to provide an acceptable response, then please provide a bracketed copy of your response that identifies the information that should be protected and a redacted copy of your response that deletes such information. If you request withholding of such material, you mMA.t specifically identify the portions of your response that you seek to have withheld and provide in detail the bases for your claim of withhold-ing (e.g., explain why the disclosure of information will create an unwarranted invasion of personal privacy or provide the information required by 10 CFR 2.790(b) to support a ,

request for withholding confidential commercial or financial information). If safeguards j e

information is necessary to provide an acceptable response, please provide the level of 1 protection described in 10 CFR 73.21.

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~ Dated at King of Prussia, PA this 22nd day of April 1998.

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