ML20206U314

Notice of Violation from Insp on 981116-1217.Violation Noted:On or Before 981217,design Control Measures Were Not Established to Ensure That Design Basis Closing Voltage Requirements of Circuit Breakers Were Met & Verified

ML20206U314
Person / Time
Site:	Beaver Valley
Issue date:	02/05/1999
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20206U307	List: IR 05000334/1998009 ML20206U301 ML20206U314
References
50-334-98-09, 50-334-98-9, 50-412-98-09, 50-412-98-9, NUDOCS 9902120314
Download: ML20206U314 (2)

Text

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NOTICE OF VIOLATION Duquesne Light Company Docket No. 50-412 Beaver Valley Power Station 2 License No. NPF-73 During an NRC inspection conducted from November 16 to December 17,1998, a violation of NRC requirements was identified. In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," NUREG-1600, Rev.1, the violation is listri below:

10 CFR 50, Appendix B, Criterion Ill, " Design Control," requires, in part, that: " Measures be established to assure that applicable regulatory requirements and the design basis ...

, for structures, systems, and components ... are correctly translated into specifications, drawings, procedures, and instructions .... The design control measures shall provide for verifying or checking the adequacy of design ...."

DC voltage drop Calculation No.10080-E-202, Revision 1, daied July 30,1998, is part of I the set of calculations that support the design performance criteria specified in Section 8.3.2 of the UFSAR for the de power system. This calculation stated that, (1) the minimum required (design) voltage at the closing coils of the safety-related 4160V air circuit breakers was 90Vde, and that, between steps 2 and 6 of the emergency diesel generator loading sequence, the voltage at the DC bus was 129.2Vde, i.e., the same voltage available from the battery charger during normal power plant operation.

Contrary to the above, on and before December 17,1998, design control measures were not established to ensure that the design basis closing voltage requirements of the circuit breakers were met and verified, in that the licensee failed to recognize that, between the specified emergency diesel generator loading steps, the battery charger loading exceeded its rating and, therefore, would not be capable of supplying voltage at the same level as during normal operation. As a result, ten breakers were identified as having calculated voltages below the minimum required by design.

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, ATTN:

Document Control Desk, Washington, D.C. 20555 with a copy to the Regional Administrator, Region I, 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 Violation" and should include for each violation: (1) the reason for the violation, or, if 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 l

compliance will be achieved. Your response may reference or include previous docketed correspor>dence,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 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.

9902120314 990205 PDR ADOCK 05000334 G PDR I

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, 1 Notice of Violation 2 If you contest this enforcement action, you should also provide a copy of your response to the Director, Office of Enforcement, 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 must specifically identify the portions of your response that you seek to have withheld and provicle in detail the bases for your claim of withholding (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 information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21.

Dated at King of Prussia, PA this 5th day of February,1999.