ML17054D559

Informs That Responses to Generic Ltr 83-28,Items 2.1,2.2.2, 4.5.2 & 4.5.3 Incomplete.Request for Addl Info Encl. Responses Requested within 60 Days for Items 2.1 & 2.2.2 & within 90 Days for Items 4.5.2 & 4.5.3

ML17054D559
Person / Time
Site:	Cooper
Issue date:	04/23/1985
From:	Vassallo D Office of Nuclear Reactor Regulation
To:	Pilant J NEBRASKA PUBLIC POWER DISTRICT
References
GL-83-28, NUDOCS 8505030132
Download: ML17054D559 (10)

Text

April 23, 1985 Docket No. 50-298 Mr. J.

M. Pilant, Technical Staff Manager Nuclear Power Group Nebraska Public Power District Post Office Box 499

Columbus, Nebraska 68601

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOLLOWING PRELIMINARY STAFF REVIEW OF LICENSEE RESPONSES TO GENERIC LETTER 83-28 Re:

Cooper Nuclear Station The staff has completed a preliminary review to assess the completeness and adequacy of licensee responses to Generic Letter 83-28 Items 2.1, 2.2,

3. 1.3, 3.2.3, 4.4 and 4.5.

For Cooper Nuclear Station, your response dated November 4, 1983 was found to be incomplete for Items 2. 1, 2.2.2, 4.5.2 and 4.5.3.

Brief descriptions of the deficiencies are given as guidelines for corrective action in the enclosed Request for Additional Information.

Efforts by Owners

Groups, INPO and NSSS vendors have been or are being made to produce generic responses that may be useful in meeting the requirements of Generic Letter 83-28 Items 2. 1, 2.2.2, 4.5.2 and 4.5.3.

You may wish to contact your Owners Group or INPO regarding the applicability of such generic responses to Cooper.

In order to preserve our present review schedule, the staff needs to have the supplementary information within 60 days of receipt of this letter for Items 2. 1 and 2.2.2 and within 90 days for Item 4.5.2 and 4.5.3. If you intend to formally endorse the BWR Owners Group response to Item 4.5.3 (NEDC-30844),: the staff should be advised within 60 days.

Your plant-specific response to Item 4.5.3 should then be provided within 90 days after NRC completes its, review of NEDC-30844 and issues its evaluation.

We request your cooperation "in meeting this schedule.

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Mr. J.

M. Pilant This Request for Additional Information was approved by the Office of Management and Budget under clearance number 3150-0011 which expires April 30, 1985.

Comments on burden and dupl,ication may be directed to the Office of Management and Budget, Reports Management Room 3208, New Executive Office Building, Washington, D,. G...20503.

Sincerely, Original signed by/

Domenic B. Vassallo, Chief Operating Reactors Branch ¹2 Division of Licensing

Enclosures:

1.

Request for Additional Information 2.

Ltr dtd March 20,

1985, H. Thompson (NRC) to S.

Rosen

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Mr. J.

M. Pilant Nebraska Public Power District Cooper Nuclear Station CC:

Mr. G.

D. Watson, General Counsel Nebraska Public Power District Post Office Box 499

Columbus, Nebraska 68601 Mr. Arthur C. Gehr, Attorney Snell 5 Wi lmer 3100 Valley Center Phoenix, Arizona 85073 Cooper Nuclear Station ATTN:

Mr. Paul Thomason, Division Manager of Nuclear Operations Post Office Box 98 Brownville, Nebraska 68321 Director Nebraska Dept. of Environmental Control Post Office Box 94877 State House Station Lincoln, Nebraska 68509 Mr. William Siebert, Commissioner Nemaha County Board of Commissioners Nemaha County Courthouse Auburn, Nebraska 68305 Mr. Dennis DuBois U. S. Nuclear Regulatory Commission Resident Inspector Post Office Box 218 Brownville, Nebraska 68321 John T. Collins Regional Administrator Region IV Office U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 H. Ellis Simmons, Director Division of Radiological Health Department of Health 301 Centennial Mall, South Post Office Box 95007 Lincoln, Nebraska 68509

ENCLOSURE 1

RE/VEST FOR ADDITIONAL INFORMATION COOPER NUCLEAR STATION Item 2.1, Equipment Classification and Vendor Interface (Reactor Trip System Components)

Your response to Part 1 is incomplete.

You are requested to confirm that the review of the Reactor Trip System (RTS) classification program is complete and that it verifies that RTS components are classified as safety-related and are identified as such on all documents and in information handling systems.

b.

Your response to Part 2 is also incomplete.

You are requested to verify that periodic contact is made with all vendors of RTS components and describe how the division of responsibility between nuclear and non-nuclear divisions of vendors and the Nebraska Public Power District (NPPD) is handled.

Verify that lists of vendor technical information and the information itself is available at the reactor site for audit.

Item 2.2, Equipment Classification and Vendor Interface (Programs for All Safety-Related Components) a

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Your response to Part 2 fails to describe the interface between all vendors of safety-related equipment and the division of responsibility between NPPD and the divisions of its vendors.

Actions to be taken by vendors and NPPD to ensure that current vendor technical information is obtained and incorporated as appropriate into plant procedures and maintenance instructions are not described.

You are requested to supplement your response to address this lack of information.

Item 4.5, Reactor Trip System Reliability (System Functional Testing) a ~

b.

Your response to Part 2 is incomplete.

You are requested to verify that all components needed to perform reactor trip (RTS components) can be tested on-line (backup scram valves excepted).

The results of the BWROG and GE reviews of current functional testing of backup scram valves promised for March 1, 1984 should be included for review.

Your response to Part 3 is incomplete.

You are requested to provide the results of a review of existing or proposed intervals for on-line testing of the reactor trip system that considers the concerns expressed in Items 4.5.3. 1 to 4.5.3.5 of Generic Letter 83-28, shows how the selected intervals result in high reactor trip system availability, and presents and provides any needed Technical Specifications for staff review.

The staff finds that modifications are not required to permit on-line testing of the backup scram valves.

However, the staff concludes that testing of the backup scram valves (including initiating circuitry) at a

refueling outage frequency, in lieu of on-line testing, is appropriate and should be included in the Technical Specification surveillance requirements.

The licensee needs to address this conclusion.

The staff has just received the BWR Owners Group response to Item 4.5.3 (NEDC-30844).

If the licensee intends to formally endorse the Owners Group

response, the 1'icensee should delay his plant-specific response to Item 4.5.3 until after the staff completes its review of the Owners Group response.