ML17250A930

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Advises That 890707 & 0724 Responses to NRC Bulletin 88-004, Re Potential safety-related Pump Loss,Confirmed That Activities Required to Address Issues Discussed in Bulletin Will Be Fully Implemented by 900701.TAC 69918 Closed
ML17250A930
Person / Time
Site: Ginna Constellation icon.png
Issue date: 08/16/1989
From: Andrea Johnson
Office of Nuclear Reactor Regulation
To: Mecredy R
ROCHESTER GAS & ELECTRIC CORP.
References
IEB-88-004, IEB-88-4, TAC-69918, NUDOCS 8908220102
Download: ML17250A930 (4)


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Docket No. 50-244 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 August 16, 1989 Dr. Robert C. Mecredy, General Manager Nuclear'roduction Rochester Gas 5 Electric Corporation 89 East Avenue Rochester, New York 14649

Dear Dr. Mecredy:

SUBJECT:

NRC BULLETIN 88-04:

POTENTIAL SAFETY-RELATED PUMP LOSS (TAC NO. 69918)

By letter dated July 7, 1988 and July 24, 1989, RG&E responded to NRC Bulletin 88-04, May 5, 1988, Potential Safety-Related Pump Loss.

In your response you considered

1) whether conditions may exist which could potentially cause safety-related pump damage due to parallel operation; and 2) the adequacy of the minimum recirculation flow during operation, testing, and accident conditions.

The two plant modifications which RG8E committed to perform as a result of NRC Bulletin 88-04 involved redesign of the minimum flow. recirculation systems for the High Head Safety Injection (SI) and Residual Heat Removal (RHR) systems.

The redesign of the SI recirculation system consisted of installation of larger diameter piping sized for 25 percent of best efficiency point flow, and replacement of two series air operator valves with motor operator valves in the common return line to the refueling water storage tank.

This modification and functional testing was accomplished during the 1989 refue'ling outage and was completed as established by the Design Criteria as of June 24, 1989.

The redesign of the RHR recirculation system involves new piping, valves, and flow, pressure and temperature instruments in order to provide an independent recirculation system for each pump train.

An interim modification was accomplished, using larger fixed orifice sizes as well as larger recirculation lines, during the 1989 refueling outage as an interim measure to remove any concern expressed in NRC Bulletin 88-04 regarding the dead heading of one RHR pump.

Completion of the full scope of the modification is targeted for July 1990 following the cycle 20 1990 refueling outage.

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Dr. Robert C. Hecredy August 1 6, 1 989 By letters dated July 7, 1988 (with attachments) and July 24, 1989 RGSE has satisfactorily responded to NRC Bulletin 88-04.

In these responses RG&E has confirmed that activities required to address the issues discussed in Bulletin 88-04 will be fully implemented by July I, 1990.

TAC No. 69918 is hereby, closed.

S incere ly,

'.Q<ginal signd >J:

Allen Johnson, Project tlanager Project Directorate I'-'3 Division of Reactors Projects I/II Office of Nuclear Reactor Regulation cc:

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Harry H. Voigt, Esquire

LeBoeuf, Lamb, Leiby and tlacRae 1333 New Hampshire
Avenue, N.W.

Suite 1100 Washington, D.C.

20036 Resident Inspector R.E. Ginna Plant U.S. Nuclear Regulatory Commission 1503 Lake Road

Ontario, New York 14519 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allenda le Road King of Prussia, Pennsylvania 19406 Hs.

Donna Ross Division of Policy Analysis 5 Planning New York State Energy Office Agency Building 2 Empire State Plaza

Albany, New York 12223 Nr. Bruce A. Snow, Superientendent Nuclear Production Rochester Gas 5 Electric Corporation 89 East Avenue Rochester, New York 14649-0001 Charlie Donaldson, Esq.

Assistant Attorney General New York Department of Law 120 Broadway New York, New York 10271