ML20199H562

Notice of Violation from Insp on 981121-990104.Violations Noted:As of 981015,adequate VT-2 Visual Exam of Pressure Retaining Boundary of Sfsp Common to Units 1 & 2 Not Performed During Each Code Insp Period

ML20199H562
Person / Time
Site:	Point Beach
Issue date:	01/15/1999
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20199H555	List: IR 05000266/1998021 ML20199H549 ML20199H562
References
50-266-98-21, 50-301-98-21, NUDOCS 9901250238
Download: ML20199H562 (2)

Text

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NOTICE OF VIOLATION Wisconsin Electric Power Company Docket Nos.: 50-266;50-301 Point Beach Nuclear Plant License Nos.: DPR-24; DPR-27 ,

. Units 1 and 2 During an NRC inspection conducted from November 21,1998, through January 4,1999, a violation of NRC requirements was identified. In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," NUREG-1600, the violation is listed below.

Technical Specification 15.4.2.B.1 requires, in part, that inservice inspection of American Society of Mechanical Engineers (ASME) Code Class 1, Class 2, and Class 3 components be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda.

a. ASME Code,1986 Edition,Section XI, Table IWD-2500-1, Category D-C, requires a VT-2 visualinspection of the pressure retaining boundary of the spent fuel storage pool (SFSP) each inservice inspection period. ASME Code,1986 Edition,Section XI, paragraph IWA-5243, " Components With Leakage Collection Systems," requires, in part, that where leakages from components are normally expected and collected, a VT-2 visual examination be conducted by verifying that the leakage collection system is operative.

Contrary to the above, as of October 15,1998, an adequate VT-2 visual l examination of the pressure retaining boundary of the SFSP common to Units 1 and 2 was not performed during each Code inspection period. Specifically, the VT-2 visual examination performed failed to verify the absence of leakage from the SFSP liner, an ASME Code Class 3 pressure retaining boundary, as monitored and collected by the SFSP leakage collection system. Further, the VT-2 visual examination was conducted and the leakage collection system was not verified to be operative.

b. ASME Code,1986 Edition,Section XI, Paragraph IWA-2430 " Inspection Intervals," requires, in part, that system pressure tests be completed during each of the inservice inspection intervals for the service lifetime of the power unit.

Contrary to the above, as of November 13,1998, system pressure tests were not completed during each of the inservice inspection intervals for certain Unit 1 systems. Specifically, system pressure tests were not completed during the second inspection period, which ended on July 31,1997, for portions of the piping outside the Unit 1 containment for the main steam, component cooling water, and chemical and volume control systems.

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

9901250238 990115 PDR ADOCK 05000266 e PM

Notice of Violation '

l The NRC has concluded that information regarding the reason for the violation, the corrective l actions taken and planned to correct the violation and prevent recurrence, and the date when l full compliance will be achieved is already adequately addressed on the docket in Inspection  !

Report 50-266/98019(DRP); 50-301/98019(DRP), Licensee Event Report 50-266/98028, and l the enclosed report. 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

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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, DC 20555 with a copy to the Regional '

Administrator, Region ill, and a copy to the NRC Resident inspector at the facility that is the subject of this Notice of Violation (Notice), within 30 days of the date of the letter transmitting this Notice.

l 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.

If you choose to respond, your response will be placed in the NRC Public Document Room (PDR), to the extent possible, the response should not include any personal privacy, proprietary, or safeguards information so that it can be placed in the PDR without redaction.

In accordance with 10 CFR 19.11, you may be required to post this Notice within 2 working days.

Dated this 15* day of January 1999 I

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