ML20098E015

Requests Extension of Submittal Date to Respond to Generic Ltr 88-20 Re Individual Plant Exam for Severe Accident Vulnerabilities,Per 920507 Meeting W/Nrc.Response Expected to Be Completed by June 1993

ML20098E015
Person / Time
Site:	Point Beach
Issue date:	05/27/1992
From:	Link B WISCONSIN ELECTRIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
CON-NRC-92-054, CON-NRC-92-54 GL-88-20, TAC-M74452, TAC-M74453, VPNPD-92-195, NUDOCS 9206010185
Download: ML20098E015 (2)

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?OWER COMPAtN 231 W Mchgan. PO Box 2046. Mawoukee, wt 53201 (414)221-2345 VPNPD - 195 NRC-92 054 May 27, 1992 Document Control Desk U.S. NUCLEAR REGULATORY COMMISSION Mall Station P1-137 Washington, D.C.

20555 Gentlemen:

DOCKETS 50-266 AND 50-301 GENERIC LETTER 88-20 (TAC NOS. 74452_hpD 74453)

REVISED SCHEDULE FOR SUBMITTAL OF IPE

-PGINT-BEACH NUCLEAR PLANT UNITS 1 AND 2 ROn May 7, 1992, Wisconsin Electric Power Company personnel attended a meeting in Rockville, Maryland, with members of the NRC staff to discuss the progress on our programs to complete the Individual Plant L

Examination (IPE) _for severe accident vulnerabilities required by l

Generic-Letter 88-20.

During the meeting, we discussed the backgroundfof'PRA activities at Wisconsin Electric, our recent switch in contractors and software supporting the project, and the current' status and schedule forLsubmitting an IPE Summary Report to the NRC.

Our1 emphasis to the.NRC staff was that our project-changes were-l

_necessary to_ improve the plant-specific detail.in our models and to l

more-thorotm.ly address several technical details such as the two--

unit interface and the human reliability analysis.

We noted that we are planning to go well beyond the min. mum requirements for backend analysis by conducting our own severe accident thermal-hydraulic l

' analysis:using the MAAP code.

Our goal has-been to do more than just meetothe minimum requirements of the generic letter-for an IPE l

< submittal.

We plan to build a living PRA model which can'be used as aimanagement tool for plant decision making affecting modifications,.

Loperations, maintenurc e. safety evaluations, and possible plant life extension.-

In our letter dated September 28, 1990, we had discussed our schedule for the IPE submittal and proposed a submittal date of December 31, 1992.

InLMr..Samworth's letter _ dated March 18, 1991, this schedule was approved.

As' detailed in the May 7 meeting, we believe it is necessary-for us to request a revised IPE submittal date of no later than June 1993.

Although the majority of the work involved in the

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Level 1 and Level 2 PRA evaluations should be completed before the

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Document Control Desk Mar 27, 1992 Page 2 end of this year, we believe it is necessary to request this schedule extension-in order to provide our staff sufficient time to conduct

~the accond phase of independent review, evaluate the results of these analyses, and to plan and schedule any modifications or procedural changes which may be appropriate to addreas significant core damage sequences identified by-the PRA.

If the results of the PRA quantification demonstrate that only minimal changes to plant operations and procedures are required, it is likely that we would be able to submit our response to Generic Letter 88-20 well before LJune 1993.

If we identify any significant severc accident vulnerability during the PRA quantification process, we shall communicate these results to the NRC staff-before our formal submittal and initiate appropriate steps to address such a vulnerability on an expedited basis.

As suggested by the NRC staff, we agree that an additional meeting witt. NRC personnel some time in November 1992 is appropriate to discuss the results of the Level 1 and Level 2 PRA assessments.

We shall contact you in fall to establish a firm date for that meeting.

We appreciated this opportunity to meet with the NRC staff and discuss our IPE progress.

Should you have any outstanding questions as.a result of the meeting or this letter, please let us know.

Sincerely,

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-S6b Link i

_vice President Nuclear Power Copy-to:

NRC Regional Administrator, Region III NRC Resident Inspector i

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