NPL-98-0672, Informs NRC of Util Intention to Inspect & Replace Baffle Former Bolts During Next Point Beach Nuclear Plant,Unit 2 Refueling Outage.Outage Presently Scheduled to Begin in Dec 1998

Informs NRC of Util Intention to Inspect & Replace Baffle Former Bolts During Next Point Beach Nuclear Plant,Unit 2 Refueling Outage.Outage Presently Scheduled to Begin in Dec 1998

ML20237B595
Person / Time
Site:	Point Beach
Issue date:	08/14/1998
From:	Kaminskas V WISCONSIN ELECTRIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NPL-98-0672, NPL-98-672, NUDOCS 9808190093
Download: ML20237B595 (2)

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Wisconsin

. Electnc POWER COMPANY Point Beach Nuclear Plant (920) 755-2321 661o Nuclear Rd., Two Rivers. WI 54241 NPL 98-0672 10 CFR 50.4 August 14,1998 Document Control Desk US Nuclear Regulatory Commission l Mail Station Pl-137 Washington, DC 20555 Ladies / Gentlemen: '

DOCKET 50-301 BAFFI E FORMER BOLT INSPECTION AND REPLACEMFEI POINT BEACH NUCLEAR PLANT. UNIT 2 This letter is to inform you of Wisconsin Electric's intention to inspect and replace bame former bolts during the next Point Beach Unit 2 refueling outage. This outage is presently scheduled to begin in December 1998. Our current plans are to inspect all baffle former bolts to ensure the baffle plates are capable of performing their intended safety functions. It is also our intention to replace bolts in an adequate bolting configuration to ensure that all design basis functionality requirements of the bame plates are met. The number of bolts actually replaced will be contingent on various aspects of the replacement program, such as equipment reliability, personnel radiation exposure, and schedule. Included in our schedule are considerations to avoid a conflict with the next scheduled use of the bame former bolt replacement equipment at another nuclear power plant in the Spring of1999.

We will perform an evaluation to determine bolting configurations that are acceptable to ensure the design basis functionality requirements of the baffle plates are fulfilled. It is our intention to utilize WCAP-14748," Justification for Increasing Postulated Break Opening Times in Westinghouse Pressurized Water Reactors," and WCAP-15029. " Westinghouse Methodology for Evaluating the Acceptability of Baffle-Former-Barrel Bolting Distribution Under Faulted Load Conditions," in this evaluation. Therefore, review of these two WCAPs by the NRC Staffis requested. These WCAPs were previously submitted to the NRC Staff by the Westinghouse Owner's Group.

\~U The current schedule for equipment qualification, crew training, and Point Beach Unit 2 outage

activities is provided below. These dates are subject to change and should be confirmed if NRC L Staff plans to attend any of these activities.

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"NPL 98-0672 August 14,1998 l Page 2 Point Beach Unit 2 Baffle Former Bolt Activities Activity Location Date (all in 1998)

Removal and installation tooling Framatome Technologies, August 3 - 28 qualification Lynchburg, VA Ultrasonic testing equipment Framatome Technologies, August 24 - 28 qualification Lynchburg, VA Training of crews for onsite work Framatome Technologies, September 14 -

Lynchburg, VA October 23 Point Beach Unit 2 outage begins Two Creeks, WI December 5 ,

Baffle former bolt inspection begins Two Creeks, WI December 18 Baffle former bolt replacement begins Two Creeks, WI December 25 If you have any questions or desire additional information, please contact our Project Manager for this effort, James Pfefferle, at (414) 221-4678.

Sincerely, t- hd44q -

Vito A. Kaminskas Manager, Regulatory Services & Licensing JG/dms cc: NRC Resident Inspector NRC Regional Administrator PSCW INPO Support Services i

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