ML20136C089

Notice of Violation from Insp on 961217-970203.Violation Noted:Diesel Generator Fuel Oil Storage Tank Level Was Below TS Value & Required Actions for Inoperable Diesel Generator Was Not Performed

ML20136C089
Person / Time
Site:	Limerick
Issue date:	03/06/1997
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20136C086	List: ML20136C081 ML20136C089 ML20136C095
References
50-352-96-10, 50-353-96-10, NUDOCS 9703110258
Download: ML20136C089 (2)

Text

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l NOTICE OF VIOLATION PECO Energy Docket Nos. 50-352;50-353 Limerick Nuclear Generating Station License Nos. NPF-39; NPF-85 Units 1 & 2 During an NRC inspection conducted on December 17,1996, through February 3,1997, violations of NRC requirements were identified. In accordance with the " General i Statement of Policy and Procedure for NRC Enforcement Actions," NUREG-1600, the I violations are listed below:

A. Unit 1 Technical Specification (TS) 3.8.1.1 requires, in part, that each diesel l

generator be operable with a fuel storage system containing a minimum of 33,500 '

gallons of fuel. With one diesel generator inoperable, Technical Specification 3.8.1.1 requires the performance of a surveillance requirement within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, by verifying correct breaker alignments and indicated power availability, and demonstrating the operability of the remaining diesel generators.

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l Contrary to the above, when on December 31,1997, operators identified that the '

Unit 1 D14 diesel generator fuel oil storage tank level had been below the minimum technical specification value since November 1996. The required actions for an ,

inoperable diesel generator had not been performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. l This is a Severity Level IV violation applicable to Unit 1 (Supplement 1).

B. Unit 2 Technical Specification (TS) Table 3.6.3-1, Note 32, requires specific primary containment isolation valves to be " sealed closed" whenever the reactor is critical  ;

and above a reactor pressure of 600 psig. The Standard Review Plan 6.2.4, 1 Containment Isolation System, Section ll.6.F defines " sealed closed," in part, as a '

barrier used in place of an automatic isolation valve, administratively controlled, by preventing power from being supplied to the valve operator.

Contrary to the above, from December 13 through December 16,1996, two Unit 2 prirnary containment isolation valves listed in TS Table 3.6.31 were not sealed closed when the reactor was critical and above a reactor pressure of 600 psig.

Power to the valve motor operators was not deenergized as required by administrative controls.

This is a Severity Level IV violation applicable to Unit 2 (Supplement I).

The NRC has concluded that information regarding the reason for the violation, the corrective actions taken and planned to correct the violation and prevent recurrence and the date when full compliance was achieved is adequately addressed in inspection Report No. 50-352, 353/96-10. However, you are required to submit a written statement or evManation 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 9703110258 970306 PDR ADOCK 05000352 G PDR

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1 2 I 20555 with a copy to the Regional Administrator, Region I, and a copy to the NRC I 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). l 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 l 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 j 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 l 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 financialinformation). 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 6th day of March,1997