ML20236X866

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Notice of Violation from Insp on 980426-0627.Violation Noted:From 1988 to Sept 1997,licensee Routinely Vented Units 1 & 2 HHSI Piping Prior to Surveillance Testing W/O Proper Controls to Evaluate Amount of Gas.No Response Required
ML20236X866
Person / Time
Site: Beaver Valley
Issue date: 08/05/1998
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20236X857 List:
References
50-334-98-03-01, 50-334-98-3-1, 50-412-98-03, 50-412-98-3, EA-98-359, NUDOCS 9808100331
Download: ML20236X866 (2)


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! ENCLOSURE 2 NOTICE OF VIOLATION WITH NO RESPONSE REQUIRED Duquesne Light Company Docket Nos. 50-334,50-412 Beaver Valley Power Station 1 & 2 License Nos. DPR-66, NPF-73 EA No.98-359 During an NRC inspection conducted from April 26, to June 27,1998, 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 listed below l

10 CFR 50, Appendix B, Criterion XI, " Test Control," requires, in part, that "... the test is performed under suitable environmental conditions." Suitable environmental conditions include conditions representative of the expected conditions when the equipment is required to perform its safety function. )

Contrary to the above, from 1988 to September 1997, the licensee routinely vented the Unit 1 and Unit 2 high head safety injection piping prior to surveillance testing without proper controls to evaluate the amount of gas vented and the effects of the gas on the system. As a result, the test environment was altered such that pre-existing adverse conditions could not be detected and the operability of the pump could not be determined.

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

The NRC has concluded that information regarding the reason for this violation, the corrective actions taken and planned to correct the violation and prevent recurrence and the date when full compliance was achieved is already adequately addressed as stated in this inspection report. Therefore, no response to this violation is required. However, you are required to submit a written statement or explanation pursuant to 10 CFR 2.201 if the description therein does not accurately reflect your corrective actions or your position, in that case, or if you choose to respond, clearly mark your response as a " Reply to a Notice of Violation," and send it 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 !nspector at the facility that is the subject of this Notice, within 30 days of the date of the lettar transmitting this Notice of Violation (Notice).

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 respor se, 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 9808100331 900805 -

gDR ADOCK 05000334 PDR ,

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withholding of such material, you must specifically identify the portions of your response that you seek to have withheld and provide 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 August 1998

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