ML20132C424

Forwards Request for Addl Info Re 831025 Response to Generic Ltr 83-28,Item 1.1 Concerning post-trip Review.Info Requested within 90 Days

ML20132C424
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	07/26/1985
From:	Zwolinski J, Zwonlinski J Office of Nuclear Reactor Regulation
To:	Taylor J DAIRYLAND POWER COOPERATIVE
References
GL-83-28, LSO5-85-07-039, LSO5-85-7-39, NUDOCS 8507300267
Download: ML20132C424 (5)

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- July 26, 1985 Docket No. 50-409 LS05-85-07-039 fir. James W. Taylor General Menager Dairyland Power Cooperative 2615 East Avenue South La Crosse, Wisconsin 54601

SUBJECT:

REQUEST FOR ADDITI0flAL INF0PMATION FOLLOWING PRELIMIflARY STAFF REVIEW 0F LICENSEE RESPONSES TO GEf'ERIC LETTER 83-28, ITEM 1.1 (POST-TRIP REVIEW)

Re: La Crosse Boiling Water Reactor The staff has completed a preliminary review to assess the completeness and adequacy of your response to Generic Letter 83-28, Item 1.1 (Post-Trip Review) for the La Crosse Plant. Your. response, provided via letter dated October 25, 1983, was found to be incomplete for this item. Brief descriptions of the deficiencies have been provided for your use as guidelines for corrective action, and are depicted in the enclosed request for additional information.

To preserve our present review schedule, the staff request that you provide the supplementary information within 90 days. We request your cooperation in meeting this schedule.

The reporting and/or record keeping requirements contained in this letter affect fewer than ten respondents, therefore OMB clearance is not required under P.L.96-511.

Sincerely, W sbmed by John A. Zwolinski, Chief i

f Operating Reactors Branch No. 5 i

Division of Licensing

Enclosure:

l Request for Additional Information cc w/ enclosure:

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%.,,,,*' July 26, 1985 Docket No. 50-409 LS05-85-07-039 Mr. James W. Taylor General Manager Dairyland Power Cooperative P615 East Avenue South La Crosse, Wisconsin 54601

Dear Mr. Taylor:

SIIR. LECT: RE0 VEST FOR ADDITIONAL INFORMATION FOLLOWING PRELIMINARY STAFF REVIEW 0F LICENSEE RESPONSES TO GENERIC LETTER 83-28, ITEM 1.1 (POST-TRIP PEVIEW)

Re: La Crosse Boiling Water Reactor The staff has completed a preliminary review to assess the completeness and adequacy of your response to Generic Letter 83-28, Item 1.1 (Post-Trip Review) for the Le Crosse Plant. Your response, provided via letter dated October 25, 1983, was found to be incomplete for this item. Brief descriptions of the deficiencies have been provided for your use as guidelines for corrective action, and are depicted in the enclosed request for additional in#ormation.

To preserve our present review schedule, the staff requests that you provide -

the supplementary infomation within 90 days. We request your cooperation in meeting this schedule.

The reporting and/or record keeping requirements contained in this letter affect fewer than ten respondents, therefore OMB clearance is not required under P.L.96-511 Sincerely, John A. Zwolinski, Chief Opere ing Reactors Branch No. 5 Division of Licensing

Enclosure:

Recuest for Additional Infoma tion cc w/ enclosure:

See next page

Mr. James W. Taylor Dairyland Power Cooperative La Crosse Boiling Water Reactor cc:

Fritz Schubert, Escuire Clarence Riederer, Chief Engineer Staff Attorney Wisconsin Public Service Dairyland Power Cooperative Commission 2615 East Avenue South Post Office Box 7854 La Crosse, Wisconsin 54601 Madison, Wisconsin 53707

0. S. Heistand, Jr., Esquire Morgan, Lewis & Bockius 1800 M Street, N.W.

Washington, D.C. 20036 Mr. John Parkyn, Plant Manager La Crosse Boiling Water Reactor Dairyland Power Cooperative P. O. Box 275 Genoa, Wisconsin 54632 U.S. Nuclear Regulatory Commission Resident Inspectors Office Rural Route #1, Box 276 Genoa, Wisconsin 54632 Town Chairman Town of Genoa Route 1 Genoa, Wisconsin 54632 Chairman, Public Service Commission -

of Wisconsin Hill Farms State Office Building Madison, Wisconsin 53702 Regional Administrator, Region III

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U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 ,

ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION LA CROSSE BOILING WATER REACTOR (LACBWR)

DOCKET NO. 50-409 Item 1.1 - Incomplete

1. The licensee needs to submit infomation clearly defining the responsibilities and authorities of the personnel who will perfom the pcst-trip review and analysis. We recomend that the post-trip review team include a member of plant management at the Shift Supervisor level on the plant end who has the responsibility and authority to obtain all necessary personnel and data to ensure a thorough and complete post-trip review. In addition, the post-trip review team should include a Shift Technical Advisor or an engineer who has had special transient analysis training. These two people should have a joint responsibility to concur on a decision / recommendation to restart the plant.

2. The licensee needs to address the methods and criteria comparing the event information with known or expected plant behavior. We recommend ,

that the pertinent data obtained during the post-trip review be '

compared to the applicable deta provided in the LACBWR Safeguards Report to verify proper operation of the systems or equipnent. Where -

possible, comparisons with previous similar events should be made.

3. The licensee needs to address the criteria for oetermining (1) the acceptability of restart for any unscheduled reactor trip, and (2) the need for independent assessment of an event. Ve recomend that if any of the restart criteria listed below are not met, an independent assessment of the event should be performed by the Operations Review Comittee or a group with similar authority and experience. In addition, the licensee should have procedures to ensure that all physical evidence necessary for an independent assessment is preserved.

Recommended restart criteria:

a. The post-trip review team has determined the root cause and sequence of events resulting in the plant trip.

b. Near term corrective actions have been taken to remedy the cause of the the trip.  ;

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c. The post-trip review team has performed an analysis and detemined that the major safety systems responded to the event within specified limits.

d. The post-trip review has not resulted in the discovery of a potential safety concern (e.g., the root cause of the event occurs with a frequency significantly larger than expected).

4. The licensee has not provided, for our review, a systematic safety assessment program to assess unscheduled reactor trips. We recommend that the licensee develop a systematic safety assessment program in accordance with the guidelines previded below.

Recommended guidelines:

a. The criteria for determining the acceptability of a restart of the plant.

b. The qualifications, responsibilities, and authorities of key personnel in the post-trip review process.

c. The methods and criteria for determinino whether plant paraneters and system responses were within the limits provided in the LACBWR Safeguards Report.

d. The criteria for determining the need for an independent review.

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