ML20128B315

Requests Addl Info Following Preliminary Review of Licensee 831107 Response to Generic Ltr 83-28,Item 1.1 Re post-trip Review.Supplementary Info Requested within 90 Days

ML20128B315
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	07/01/1985
From:	Zwolinski J Office of Nuclear Reactor Regulation
To:	Vandewalle D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
References
GL-83-28, LSO5-85-06-036, LSO5-85-6-36, NUDOCS 8507030189
Download: ML20128B315 (1)

Text

r-Docket No. 50-155 July 1,1985 LS05-85-06-036 Mr. David J. VandeWalle Director, Nuclear Licensing Consumers Power Company 1945 W. Parnall Road Jackson, Michigan 49201

Dear Mr. VandeWalle:

SilBJECT: REQUEST FOR ADDITIONAL INFORMATION FOLLOWING PRELIMINARY STAFF DEVIEW 0F LICENSEE RESPONSES TO GENERIC LETTER 83-28, ITEM 1.1 (FOST-TRIP REVIEW)

Pe: Big Rock Point Plant The staff has completed a prelininary review to assess the completeness and adequacy of your response to Generic Letter 83-28, Item 1.1 (Post-TripReview)fortheBigRockPointPlant. Your response, provided via letter dated November 7,1983, was found to be incomplete for this item.

Brief descriptions of the deficiencies have been provided for your use as I guidelines for corrective action, and are depicted in the enclosed request for additional information.

In order to preserve our present review schedule, the staff needs to have the supplementary information within 90 days. We request your cooperation in meeting this schedule.

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

t Sincerely, l Original signed by l John A. Zwolinski, Chief i Operating Reactors Branch #5 Division of Licensing

Enclosure:

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% ,,, g # July 1,1985 Docket No. 50-155 LS05-85-06-036 Mr. David J. VandeWalle Director, Nuclear Licensing Consuners Power Company 1945 W. Parnall Road Jackson, Michigan 49201

SUBJECT:

REQUEST FOR AD'JITIONAL INF0PMATION FOLLOWING PRELIMINAP,Y STAFF REVIEW 0F LICENSEE RESPONSFS TO GENERIC LETTER 83-28, ITEM 1.1 (POST-TRIP REVIEW)

Re: Big Rock Point Plant 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 Big Rock Point Plant. Your response, provided via letter dated November 7,1983, 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.

In order to preserve our present review schedule, the staff needs to have the supplementary information within 90 days. We request your cooperation in meeting this schedule.

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

a Since ly, O Lg t.w ,

John A. Zwolinski, Chief Operating Reactors Branch #5 Division of Licensing

Enclosure:

Request for Additional Information cc w/ enclosure:

See next page i

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Mr. David J. VandeWalle Big Rock Point Plant Consumers Power Company I

cc Mr. Thomas A. McNish, Secretary Cnnsumers Power Company

?l? Past Michiaan Avenue -

Jackson, Michigan 49201 Judd L. Bacon, Esquire Consumers Power Cmpany 212 West Michigan Avenue

.lackson, Michigan 49201 Pio Rock Point Plant ATTN: Mr. Dave Foffman Plant Superintendent Charlevoix, Michigen 497PO Mr. I. Lee Moerland Chaiman, Board of Commissioners P. O. Box 218 Charlevoix, Michigan 49720 Of# ice of the Governor Donm 1 - Capitol Building Lansing, Michigan 48013 Regional Administrator Nuclear Regulatory Comission, Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 Nuclear Facilities and Environmental Monitoring Section Office Division of Radiological Health P. O. Box 30035 Lansing, Michigan 48909 Resident Inspector Big Rock Point Plant c/o IJ.S. NRC P.P #3, Pnx 600 Charlevoix, Michigan 49720

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ENCLOSL'PE pF0l'EST FOR ADDITIONAL INFORMATION BIG ROCK POINT PLANT DOCKET NO. 50-155 Item 1.1 - Incomplete

1. The licensee needs to submit information clearly defining the responsibilities and authorities of the personnel who will perform the post-trip review and analysis. We recommend that the post-trip review team include a member of plant management at the Shift Supervisor level or above who holds or has held a license et the Senior Operator level on the plant (the Shift Supervisor who was on shift at the time of the event would be acceptable) and 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 an STA or an engineer who has had special transient analysis trainina. These two people should have a joint responsibility to concur on a decision / recommendation to restart the plant.

P. 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 data provided in the FHSR to verify proper operation of the systems or equipment. Where possible, comparisons with previous sinflar events should be made.

3. .. The licensee has indicated that if the cause of the trip cannot be determined, the 08M Superintendent or the On-Duty Superintendent prescribes which portions of the precritical check list must be performed prior to requesting that the Plant Superintendent obtain General Office authorization for restart. We find that this ec, tion to be taken by the licensee is not sufficient to ensure safe play. operation. We recommend that if any of the restart criteria listed ttlow are not met, ai, independent assessnent of the event should be performed by the Plant Review Cormittee or a group with simile authority ard experience. In addition, the licensee should have procedures to ensure that all physical evidence necessary for an independent assessment is preserved.

Recomended restart criteria:

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

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

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c. The post-trip review team has performed an analysis and determined 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 frecuency significantly larger than expected).

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

Recommended guidelines:

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

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

c. The methods and criteria for determining whether plant parameters and system responses were within the limits provided in the FHSR.

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

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