ML20010E872

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Requests Presence at 810909 Meeting in Bethesda,Md to Discuss Causes of Variations in Jet Pump Flow & Related Parameters at Browns Ferry Unit 1 During Single Loop Operation
ML20010E872
Person / Time
Site: Millstone Dominion icon.png
Issue date: 08/24/1981
From: Crutchfield D
Office of Nuclear Reactor Regulation
To: Counsil W
NORTHEAST NUCLEAR ENERGY CO.
References
LSO5-81-08-048, LSO5-81-8-48, NUDOCS 8109080419
Download: ML20010E872 (3)


Text

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$t August 24, 1981 i \\j$,s LS05-81 048 s7of.h,)N(Y Docket No. 50-245

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si SEP 011981* 3 Mr. V. G. Counsil, Vice President Huclear Engineering and Operations 3 "*S7 Northeast Hucicar Energy Company P. O. Box 270 B

Hartford, Connecticut 06161 RE: MILuSTONE NUCLEAR POWER STATION, UNIT H0. 1

Dear Mr. Counsil:

On July 2,1981, we sent a letter to all licensees who have requested approval to operate on a continuing basis at power levels above 50% with only one recirculation loop in the event the other loop is inoperative. You and other B'.!R licensees received a copy of one of these letters since we expect rtost BWR facilities would like to have this flexibility.

In the letter we proposed a meting to obtain a better understanding of what might have caused variations in jet pump flow and related pararreters at Browns Ferry Unit No.1 during sing'.e loop operation and how this incident should affect approval of single loop operation at other fact'litics.

You have indicated to your MRC project manager that you are interested in attending the proposed neeting. The meeting will be held at 9:00 A.M.,

Wednnsday, Septenhor 9,1981 in room P-118, Phillips Building, 7920 Horfolk Avenue, Bethesda, Maryland. You are requested to advise your project manager of the people who will be attending this meeting from your organization.

Si ncarely.

ORIGINAL SIGNED BY i

l Dennis Crutchfield, Chief Operating Reactors Granch f5 Division of Licensing

Enclosure:

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Mr. W. G. Counsil. August 24, 1981 cc William H. Cuddy, Esquire Connecticut Energy Agency Day. Berry & Howard ATTN: Assistant Director Counselors at Law Research and Policy One Constitution Plaza Development Hartford, Connecticut 06103 Department of Planning and Energy Policy Natural Resources Defense Council 20 Grand Street 91715th Street, N. W.

Hartfqrd, Connecticut 06106 rashington, D. C.

20005 Northeast Nuclear Energy Company ATTN: Superintendent Millstone Plant P. O. Box 128 Waterford, Connecticut 06385 Mr. Richard T. Laudenat Manager, Seneration Facilities Licensing Northeast Utilities Service Company.

P. O. Box 270 Hartford, Connecticut 06101 Resident Inspector c/o U. S. NRC P. O. Box Drawer KK Niantic, Connecticut 06357 Waterford Public Library Rope Ferry Road, Route 156 Waterford, Connecticut 06385 First Selectman of the Town of Waterford Hall of Records 200 Boston Post Road Waterford, Connecticut 06385 John F. Opeka Systems Superintendent s

Northeast Utilities Service Company P. O. Box 270 Hartford, Connecticut 06101 U. S. Environmental Protection Agency Region I Office ATTN: EIS COORDINATOR JFK Federal Building Boston, Massachusetts 02203

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r Proposed Meeting with Bi.'R Applicants and Licensees on Sirigle. Loop Operation Purpose of Meeting:

1.

To determine what may have caused the jet pump flow and other variations experienced by Browns Ferry Unit I during single loop operation and 2.

Evaluate whether the Browns Ferry' experience 'should result in' power limits for other BWRs operating on a single loop.

I' Agenda:

1.

Discussion of what may have caused the unexpected variations in operating parameters when Browns Ferry Unit 1 exceeded about 60 percent rated power while operating t ith only onc recirculation loop.

2.

Discussion of parameters affected at Browns Ferry 1 (i.e., jet pump flow, neutron flux, core flow, core pressuredrop,etc.)

3.

Discussion of whetFer the Browns Ferry 1 experience l.

would be expected at other BWRs operating on one recirculation loop.

If so3_are safety limits.likely to be violated or cause complications with respect to core L

stability,' core flow symnetry, pump cavitation or damage to the jet pumps and reactor vessel internals.

4.

Discussion of the benefits vs. potential problems and cost of testing single loop operation in another BWR that is instrumented to detect what parameters are affected.

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5.

' Evaluation of whether single loop operation at p:wer l

levels about 50 to 55 percent is a safe and prudent means of reactor operation.

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