ML20237E498

Notice of Violation from Insp on 980628-0808.Violation Noted:As of 980810,util Had Not Corrected Known Deficiency in Verifying MSIV Full Closed During Springs Only Full Stroke Closing Tests

ML20237E498
Person / Time
Site:	Hope Creek
Issue date:	08/25/1998
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20237E496	List: IR 05000354/1998007 ML20237E494 ML20237E498
References
50-354-98-07, 50-354-98-7, NUDOCS 9809010007
Download: ML20237E498 (2)

Text

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j APPENDIX A i

NOTICE OF VIOLATION Public Service Electric and Gas Company Docket No: 50-354-l Hope Creek Generating Station License No: NPF-57 1

During an NRC inspection conducted netween' June 28,1998, and August 8,1998, a violation of NRC requirements was identified. In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," NUREG-1600, Revision 1, the violation is listed below:

10 CFR 50, Appendix B, Criterion XVI, requires in part that measures shall be established to ensure that conditions adverse to quality, such as deficiencies, are J promptly identified and corrected. i l

Contrary to the above, as of August 10,1998, PSE&G had not corrected a known i deficiency in verifying main steam isolation valves full closed during " springs-only" full stroke closing tests. Specifically, on about March 1,1989, PSE&G was made aware by General Electric Service Information Letter No. 477, dated December 13, 1988, that main steam isolation valves should be locally verified to be closed using stem travel measurements during " springs-only" full stroke closing tests. PSE&G recognized its' existing method for verifying main steam isolation valves closed was deficient, but failed to implement changes to testing methodology to correct this deficiency.

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

The NRC has concluded that information regarding the reason for the violation, the 1 corrective actions taken and planned to correct the violation and prevent recurrence and

. the date when full compliance will be achieved is already adequately addressed on the ,

docket in the enclosed inspection Report No. 50-354/98-07. 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 1 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.

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 i

9809010007 990825

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PDR ADOCK 05000354 G PDR

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

Dated at King of Prussia, Pennsylvania this 25th day of August 1998 i

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