ML20246H832

Advises That plant-specific Reactor Coolant Pump Trip Setpoint Development,Per TMI Action Plan Item II.K.3.5 Acceptable,Based on NRC Approval of Westinghouse Owners Group Methodology Per Generic Ltr 85-12

ML20246H832
Person / Time
Site:	Byron
Issue date:	08/28/1989
From:	Olshan L Office of Nuclear Reactor Regulation
To:	Kovach T COMMONWEALTH EDISON CO.
References
TASK-2.K.3.05, TASK-TM GL-85-12, TAC-60889, TAC-63262, NUDOCS 8909010383
Download: ML20246H832 (3)

Text

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-C f"*%, . i UMTED STATES A 8 -

j NUCLE A,3 REGULATORY COMMISSION

, y :E WASHINGTON, D. C. 20555 k ....+ , August 28, 1989 Docket Nos. 50-454 and 50-455 Mr. Thomas J. Kovach Nuclear Licensing Manager Commonwealth Edison Company Post Office Box 767 Chicago, Illinois 60690

SUBJECT:

REACTOR COOLANT PUMP TRIP FOR BYRON STATION, UNITS 1 AND 2 (TACN05.60889AND63262)

For the reactor coolant pump (RCP) trip issue defined in TMI Action Plan Item II.K.3.5 (Multiplant Action G-01), the staff generically approved the Westinghouse Owners Group (WOG) methodology in the Generic Letter 85-12 with the condition that plant-specific information needs to be addressed. Our review of the Byron plant-specific information has progressed to a degree that we can conclude that the WOG methodology has significantly improved the reactor _ safety,~ and there are no major safety-significant concerns for the plant-specific information.

Accordingly, we have completed our review of your plant-specific RCP trip setpoint development and find it acceptable. This issue may be the subject of on-site verification.

f2M Leonard N. 01shan, Project Manager Project Directorate III-2 Division of Reactor Projects III, IV, Y, and Special Projects cc: See next page O i ib 8909010383 890828 PDR ADOCK 05000454 P puu

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5 Mr. Thomas J. Kovach Byron Station Commonwealth Edison Company Units 1 and 2 CC:'

Mr. Jack Tain Regional Administrator Atomic Power Distribution U. S. Nuclear Regulatory Westinghouse Electric Corporation Commission Post Office Box 355 799 Roosevelt Road, Bldg. f4 Pittsburgh, Pen.,sylvania 15230 Glen Ellyn, Illinois 60137 Mich6el Miller, Esq.- Illinois Department of Sidley and Austin Nuclear Safety One First National Plaza Office of Nuclear Facility Safety Chicago, Illinois 60603 -

1035 Outer Park Drive Springfield, Illinois, 62704 Mrs. Phillip B. Johnson Joseph Gallo, Esq.

1907 Stratford Lane Hopkins and Sutter Rockford, Illinois 61107 1050 Connecticut Avenue, N.W.

Suite 1250 Ms. Lorraine Creek Rt. 1, Box 182 Douglass Cassel, Esq.

Manteno, Illinois 60950 109 N. Dearborn Street Suite 1300 l Dr. Bruce von Zellen Chicago, Illinois 60602 Department of Biological Sciences Northern Illinois University Ms. Pat Morrison

! DeKalb, Illinois 61107 913 N Main Street #707

[ Rockford, Illinois 61103-7058 Mr. Edward R. Crass Nuclear Safeguards & Licensing Attorney General I. Serger,t & Lundy Engineers 500 South 2nd Street 1 55 East Monroe Street Springfield, Illinois 62701 l Chicago, Illinois 60603 I

Chairman, Ogle County Board U. S. Nuclear Regulatory Commission Post Office Box 357 Byron / Resident Inspectors Offices Oregon, Illinois 61061 4448 North German Church Road Byron, Illinois 61010 EIS Review Coordinator Environmental Protection Agency Region V 230 S. Dearborn Street Chicago, Illinois 60604 1

Conraonwealth Edison Company Eyron Station Kanager 4450 North German Church Road Byron, Illinois 61010

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DISTRIBUTION

. Docket Nos. 50-454 and 50-455~ '

Docket t n e NRC & Local PDR PDIII-2 r/f' -PShemanski MVirgilio LLuther L01shan EJordan-Mr.' Thomas J. Kovach. .. BGrimes- ACRS (10)-

Nuclear Licensing Manager

. Commonwealth' Edison Company-Post Office Box 767' Chicago -Illinois 60690

Dear Mr. Kovach:

E

SUBJECT:

REACTOR COOLANT PUMP TRIP FOR BYRON STATION, UNITS 1 AND 2~

(TACNOS.60889AND63262)' ~

l ~Forthereactor.coolantpump(RCP)tripissuedefinedinTMIActionPlanItem'

~II.K.3.5 (Multiplant Action G-01), the staff generically approved the Westinghouse Owners Group (WOG) methodology in the Generic Letter.85-12.with the condition that plant-specific'information needs to be addressed. Our review of the Byron plant-specific information has progressed to a degree that we can conclude that the WOG methodology has significantly improved the reactor safety, ara there are no major safety-significant concerns for the plant-specific . information.

Accordingly, we have completed our review of your plant-specific RCP trip setpoint development and find it acceptable. This issue may be the subject of' on-site verification.

Leonard N. 01shan, Project Manager Project Directorate III-2 Division of Reactor Projects III, IV, V, and Special Projects cc: See next page

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