ML20087H550

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Forwards Rev 0 to Seismic Evaluation Rept & Rev 0 to Relay Evaluation Rept for Resolution of USI A-46,per GL 87-02
ML20087H550
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 06/30/1995
From: Link B
WISCONSIN ELECTRIC POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20087H553 List:
References
REF-GTECI-A-46, REF-GTECI-SC, TASK-A-46, TASK-OR GL-87-02, GL-87-2, VPNPD-95-055, VPNPD-95-55, NUDOCS 9508180141
Download: ML20087H550 (4)


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Wisconstir Electnc POWER COMPANY 231 W Mchgon. PO Box 2046. Mdwoukee. WI 53201-2046 (414) 221-2345 r

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VPNPD-95-055 June 30, 1995 Document Control Desk U.S. NUCLEAR REGULATORY ' C',MMISSION Mail Station P1-137 Washington, DC 20555 Gentlemen:

DOCKETS 50-266 AND 50-301 GENERIC LETTER 87-02

SUMMARY

REPORT FOR RESOLUTION OF UNRESOLVED SAFETY ISSUE A-46 POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 r

INTRODUCTION 3

In Generic Letter (GL) 87-0?

the NRC Staff set forth.the process for resolution of "'

A-46 and encouraged the affected nuclear power plant licer

o participate in a generic program.

In Supplement 1 to GL 87-02,* the Staff required a response to include a commitment to the Generic Implementation Procedure (GIP)8 prepared by the seismic. Qualification Utility Group (SQUG), a schedule for the implementation of the GIP, and submission of a report summarizing the results of the USI A-46 program.

By letter

" Verification Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors, Unresolved Safety Issue (USI) A-46 (Generic Letter 87-02)," dated February 19, 1987, U.S. Nuclear Regulatory Commission.

2

" Supplement No.

1 to Generic Letter (GL) 87-02 that Transmits Supplemental Safety Evaluation Report No. 2 (SSER No. 2) on SQUG Generic Implementation Procedure, Revision 2, As Corrected on February 14, 1992, (GIP-2),"

dated May 22, 1992, U.S. Regulatory Commission.

8

" Generic Implementation Procedure (GIP) for Seismic Verification of Nuclear Plant Equipment," Revision 2,

Corrected 2/14/92, Seismic Qualification Utility Group L

(SQUG).

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Documen,t Control Desk June 30, 1995 Page 2 to the NRC Staff dated September 21, 1992,'

Wisconsin Electric committed to implement the GIP, including the clarifications, 2

interpretations, and exceptions in SSER-2, and to communicate to the NRC Staff any significant or programmatic deviations from the GIP guidance.

Wisconsin Electric agreed to submit the results of the USI A-46 evaluation by June 1995.

This letter forwards the results of the USI A-46 evaluation for 1

the Point Beach Nuclear Plant Units 1 and 2.

This letter also confirms that no significant or programmatic deviations from the GIP guidance were made during the USI A-46 resolution process.

USI A-46 REPORTS Section I.2.2.8 of the GIP requires that a plant-specific Summary Report be submitted to the NRC Staff, including a proposed schedule for future modifications and replacements, if appropriate, of those outliers which are yet to be resolved.

Further, GIP Section II.9 provides for a Safe Shutdown Equipment List (SSEL) Report, a Relay Evaluation Report, a Seismic Evaluation Report, and a Completion Letter.

This letter constitutes the Summary Report.

includes the Seismic Evaluation Report and Attachment 2 includes the Relay Evaluation Report.

As permitted in Section II.9.2 of the GIP, the pertinent results from the SSEL Report are included in the attached Seismic Evaluation and Relay Evaluation Reports.

As required in Section II.9.5 of the GIP, the Completion Letter will be submitted when all the planned actions for resolution of USI A-46 have been completed.

OUTLIERS Outliers, defined in the GIP as those items of equipment which do not comply with all of the screening guidelines provided in the GIP, were identified during the seismic and relay reviews.

These outliers are described in detail in the attached reports.

Each outlier identified during the implementation of the USI A-46 program was evaluated against the current Point Beach licensing and design bases for equipment seismic qualification.

Wisconsin Electric Letter, VPNPD-92-313, " Response to Generic Letter 87-02, Supplement 1 on SQUG Resolution of USI A-46, Point Beach Nuclear Plant, Units 1 and 2,"

September 21, 1992.

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-Document Cohtrol Desk June-30, 1995 Page 3 3

1 Seismic Evaluation Outliers I

For the resolution of USI A-46, a total of 814 individual plant components were seismically evaluated in accordance with the GIP.

Of these, 66 components were

. identified as outliers for not meeting one or more of i

the GIP screening guidelines.

The attached Seismic Evaluation Report provides a complete description as j

to why the component is considered an outlier.

The following six (6) components of the 66 identified as i

outliers were determined to deviate from the Point Beach l

licensing and design basis.

Two (2) Point Beach Unit 1 Cavity Cooling Fan Units (1W-4A and 1W-4B), located in Unit 1 containment, were found unanchored during Unit 1 Refueling Outage 21.

These are required to be Seismic Class 1.

The units were anchored during the same refueling outage.

Four (4) air operated valves, (2SI-839A, 2SI-839B, 2SI-839C, 2SI-839D) located in Unit 2 containment, were found to need operator supports during Unit 2 Refueling Outage 19.

Operator supports were installed during the same Unit 2 refueling outage.

Relav Evaluation Outliers i

For the resolution of USI A-46, a total of 1455 relays were identified as " essential" requiring relay specific seismic capacity analysis.

Of those relays, 132 were identified as outliers.

The attached Relay Evaluation Report provides a complete listing of the relays and why they are considered outliers.

Eight (8) of the 132 relays are " low ruggedness" relays, and 124 relays have an unknown seismic capacity. At this point, the i

124 relays _are considered to be seismically adequate for their application.

If the seismic qualification information obtained during the outlier resolution process indicates that the relays have insufficient seismic capacity, the condition will be identified and the significance evaluated in accordance with the appropriate plant procedures.

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Document Cehtrol Desk June 30; 1995 Page 4 The schedule for resolution, future modification or replacement of those outliers which have not yet been resolved is provided in the attached reports.

We would be pleased to answer any questions you may have regarding the results of our USI A-46 study or the enclosed report.

Sincerely, Boo Link i

Vice President Nuclear Power TJD/jj Attachments cc:

NRC Resident Inspector NRC Regional Administrator 1

Subscribed and sworn to before me this 36' A day of (T, s2.

, 1995.

Gr40tbE4 6%

40%3rgPublic, State of Wisconsin M1 Commission expires 10-J?-96 g_

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