ML20238C930

Forwards Request for Addl Info Re Licensee 831108,840316 & 860513 Responses to Generic Ltr 83-28,Item 4.2 (Parts 3 & 4).Responses Inadequate Due to Reliance on WCAP-10835.Response Requested within 30 Days

ML20238C930
Person / Time
Site:	Millstone
Issue date:	09/03/1987
From:	Ferguson R Office of Nuclear Reactor Regulation
To:	Mroczka E NORTHEAST NUCLEAR ENERGY CO.
References
GL-83-28, TAC-60398, NUDOCS 8709100455
Download: ML20238C930 (4)

Text

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Docket No. 50-4?3

)f September 3, 1987 Q kb Mr. Edward J. Mroczka Senior Vice President Nuclear Engineering and Operations Northeast Nuclear Energy Company P. O. Box '*70 Hartford, Conr.ecticut 00141-0270

SUBJECT:

GENERIC LETTER 83-28 SALEM ATWS ITEM 4.2 (PARTS 3 AND 4)

(TAC NO. 60398) i

Re: Millstone Nuclear Power Station, Unit Nc 3 l Tha Northeast Nuclear Energy Company-(NNECo) responded to Generic Letter 83-28 Salem ATM5 Item 4.2 (Parts 3 & 4) in letters dated November 8,1983, March 16,

) 1984, and May 13, 1986. This response relied on WCAP-10835, " Report of the DS-416 Reactor Trip)

Tests" (Proprietary . Breaker Undervoltage and Shunt Trip Attachments Life Cycle Ve have reviewed WCAP-10835 and havt found that it does not provide an adequate response to GL 83-28 Item 4.2 parts 3 and 4.. Enclosure 1 explains our concerns, suggests alternatives and requests additional infomation to resolve this issue.

If you cannot respond to this letter within 30 days, let us know the date you will respond.

This request for adoitional information affects fewer than ten respondents; therefore, OMP clearance is not required under P.L.96-511.

Sincerely, ISI Robert L. Ferguson, Proiect Manager Project Directorate I-4 l Division of Reactor Projects I/II

Enclosure:

Request for Additional Information I cc w/ enclosure:

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Pr. E. J. Mroczka Millstone Nuclear Power Station Northeast huclear Energy Company Unit No. 3 Cc' Gerald Garfield, Esq. Ms. Jane Spector Day, Bercy & Howard Federal Energy Regulatory Commission City Place 825 N. Cepitol Street, NE Hartford, Connecticut 06103-3499 Room 8608C Washingten, D.C. 20426 Mr. Maurice R, Scully, Executive Director Mr. Kevin McCarthy, Director Connecticut Municipal Electric Radiation Control Unit Energy Cooperative Department of Environmental Protection 263 Thomas Road State Office Building Groten, Connecticut 06340 Hartford, Connecticut 06115 Robert W. Bishop Esq. Burlington Electric Department Corporate Secretary c/o Robert E. Fletcher, Esq.

Northeast Utilities 271 South Union Street j Post Office Box 270 Burlington, Vermont 05402 j Hartford, Connecticut 06141 j Mr. William J. Raymond Senior Resident inspector Office U. S. Nuclear Regulatory Commission Millstone III I P. O. Box 811 Niantic, Connecticut 06357-08 l Mr. Michael L. Jones, Manager Project Management Department Massachusetts Municipal Wholesale Electric Company i Post Office Box 426 l Ludlow, Massachusetts 01056 Regional Administrator i U. S. NRC, Region I 631 Park Avenue f King of Prussia, Pennsylvania 19406 l

Hr. Karl Abraham Public Affairs Office, Region I U. S. Nuclear Regulatory Commission, i King of Prussia, Pennsylvania 19406 l 1

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PE0 VEST FOR ADDITIONAL INFORMATION ITEM T.2 (PARTE 3&4 ) 0F GENERIC LETTER 83-28 {

MILLSTONF NUCLEAR STATION, UNIT 3 l

Item 4.2 of Generic Letter 83-28 requires licensees or applicants to describe their preventive maintenance and surveillance program for ensuring reliable reactor trip breaker operation. Part 3 of Item 4.2 requires life testing of i an acceptable sample size of the breakers, and Part 4 of Iter d.2 requires periodic replacement o# the breakers or components consistent with demonstrated ,

life cycles.

By letter dated November 8,1983, NNEco stated they had contracted with the Westinghouse Owner's Group (WOG) to perform a life cycle testing program evi- i to define the life cycle of the reactor trip breakers. NNECo also commitv )

to ensure that periodic breaker / component replacement is accomplished at the required intervals. By letter dated March 16, 1984, NNECo informed the staff that WOG had elected to use actual life cycle testing. By letter dated May 13, 1986, NNECo informed the staff that Millstone 3 used Model D5-416 breakers.

This letter also stated that the WOG program for these breakers was complete and the results reported to the staf# by letter L. D. Butterfield, WOG, to I R. J. Wright, NRC, dated December 9, 1985. In part, the WOG letter transmitted a copy of WCAP-10835, " Report of the DS-416 Reactor Trip Rreaker Undervoltage and Shunt Trip Attachrnents Life Cycle Tests" (Proprietary).

We have reviewed WCAP-10835 and have found that it does not provide an edequate response to GL 83-28 Item 4.2. parts 3 and 4. It neither addresses life qualification of the reactor tri performance-degrading phenomena,(e.g.p aging)breakers norattachments.

for the trip noneyclic life-limiting or To meet the requirements of GL 83-28 Item 4.2 parts 3 and 4, the staf#

suggests the following alternatives:

Alternative 1 l l 4.2 Part 3: Actual life testing of the reactor trip breakers, including aging, on an acceptable size.

4.2 Part 4: A replacement program for the reactor trip breakers / components

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Alternative 2 4.2 Part 3: Cyclic testing of.the reactor trip breakers, excluding aging, on an acceptable sample size plus an ongoing life testing program to demonstrate the qualified life is longer than the accumulated service through the next refueling outage.

4.2 Part 4: A replacement program for the reactor trip breakers / components i plus a description of how the results o# the ongoing life  ;

testing will be reflected into the replacement program.

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2 0* scribe th? 31:ernative you intend to use to resolve GL 83-28. Item 4.2 Farts 3 7.no 4. r,r the alternative selected, provide the appropriate information as follows:

Alternative 1 Provide s description of the life testino and the results of

'such testing.

Provide the *eplacement program for the reactor trip breaker / components.

Alternative ? Provide a description of the cyclic testing and the resJlts of such testing.

Provide a description of the ongoing life testing program including an estinate of RTB demands between refueling outages, a definit 1cn of end-of-life failure modes, an identification of possible failure modes, a categorization of them as end-of-life or not, the methodology for categorizing future failure modes, and the actions to be taken if a failure occurs.

Provide the replacement program for the reactor trip breaker / components based on the cyclic testing.

Describe how the results of the ongqing life testing will be used to verify or modify the reolecement program.

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