ML20207Q475

Forwards Revised Response to Item E of IE Bulletin 85-003, Motor Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings. Review & Corrective Action Will Be Completed by 871115

ML20207Q475
Person / Time
Site:	Oyster Creek
Issue date:	12/23/1986
From:	Wilson R GENERAL PUBLIC UTILITIES CORP.
To:	Kane W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
5000-86-1118, IEB-85-003, IEB-85-3, NUDOCS 8701270406
Download: ML20207Q475 (5)

Text

GPU Nuclear Corporation

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Nuclear

g = 388 Forked River.New Jersey 08731-0388 609 971-4000 Writer's Direct Dial Number:

December 23, 1986 5000-86-1118 Mr. William F. Kane, Director Division of Reactor Projects Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406

Subject:

Oyster Creek Nuclear Generating Station Docket No. 50-219 IE Bulletin 85-03 Motor Operated Valves Your letter of October 28, 1986 evaluated GPU Nuclear's response to IE Bulletin 85-03 " Motor Operating Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings", and requested additional information. An extension of the due date to December 23, 1986 was granted by Mr. R. Conte of the NRC on December 16, 1986.

Attachment I provides the revised response to item "e" of IE Bulletia 85-03. The maximum differential pressure values are for safety related Motor Operated. Valves in both the Core Spray and Isolation Condenser Systems at Oyster Creek. They result from GPUN's review of all normal and abnormal operating conditions to which the valve could be subjected. These values will form the basis of the analytical work to determine valve opening and closing thrust requirements and appropriate switch settings.

In accordance with your letter of October 28, 1986, the evaluation of this concern, including the implementation of the torque switch settings and any resultant corrective actions (items "b" through "d" of IE Bulletin 85-03), is projected for completion by November 15, 1987. The final report on this project will be submitted to the NRC by January 14, 1987.

8701270406 B61223 PDR ADOCK 05000219 P

PDR 1;&: ((

GPU Nuclear Corporation is a subsidiary of the General Pubhc Utihties Corporahon

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.Sillia2 F. Kane, Director Divisicn cf R:act:r Projects - USNRC:

Page 2 If any further information is required, please contact Mr. John Rogers of my staff at -(609)971-4893.

Very truly yours,

/2 F G.bL A esf R. F. Wilson Vice Pres.Jent Technical Functions RFW:JJR: dam (0183A)

Attachment cc: Mr. Jack N. Donohew, Jr.

U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue, Phillips Bldg.

Bethesda, MD 20014 Mail Stop No. 314 NRC Resident Inspector Oyster Creek Nuclear Generating Station

INLET MAX.

MAX.

PRESS.,

OPENING CLOSING VALVE PSIC DELTA P DELTA P TAG NO FUNCTION PSI BASIS PSI BASIS V-14-30,33 ISO Cond.

1250 1250 The highest RCS pressure 1250 The highest RCS pressure steamside based on highest set based on highest set pres-inboard pressure of safety valves, sure of safety valves, 1239!

isolation 1239 12 psig, 12 psig (Ref. T.S.2.3) as (Ref.T.S.2.3) as inlet inlet pressure. HELB causes pressure.

atm. pressure downstream.

Assume closure of MSIV due to a transient, causing no downstream pressure.

Valve is opened after completion of IST.

V-14-31,32 ISO Cond.

1250 1250 Same as above 1250 Same as above.

steamside out board isolation V-14-36,37 ISO Cond.

1250 1250 Same as above 1250 Same as above condensate inboard isolation V-14-34,35 ISO Cond.

1250 0

Valves are normally 1250 If valves are open for Condensate closed, and not expected initiation, HELB will outboard to be open after a HELB require closure, isolation j

i t

7164d

INLET MAX.

MAX.

PRESS., OPENING CLOSING VALVE PSIG DELTA P DELTA P TAG NO FUNCTION PSI BASIS PSI BASIS V-20-3, 4 Core Spray 5

10 Valves normally open to 35 Valve is closed:

32,33 Suction torus which is at atmos-

1) During normal OPS as Isolation pheric pressure during part of surveillance Valves operation. Valve is cycled

2) As a result of a leak only during surveillance in the C.S. Piping testing. Max pressure

3) #2 concurrent with a is static head during blowdown (Pmax=30 psia) surveillance.(This assumes Case (3) is the max pressure that a DBA does not case. Closing AP is based occur concurrently with on (3) surveillance testing.)

V-20-12,18 Core Spray 350 350 Valves Normally open 350 Valve is closed:

Test during operation, cycled 1)During Surveillance Isolation during monthly testing.

Testing Valves Max. differential is pump 2)If containment ISO shut off head valves leak back, the test ISO valves can be closed.

While a leak of the isolation valves would result in reactor pressure in the CS piping, the pressure rise would be limited by the relief valves which are set at 350 psig.

7164d

INLET MAX.

MAX.

PRESS.,

OPENING CLOSING VALVE PSIG DELTA P DELTA P TAC NO FUNCTION PSI BASIS PSI BASIS h

V-20-15,21 Outside DW 350 350 Valves are interlocked to 1250 RCS Design Pressure 40,41 Isolation open at paes1285. Pumps Valves will be operating on min.

recire @ close to shutoff head (350 psig) when valves go open.

V-20-26,27 Core Spray 350 Valves are cycled during 350 Valves normally closed Test Valves monthly pump tests. Max during plant operation.

If pressure will be pump open during an event, the shutoff head (350 psig).

valves will go closed against max. pump head (350 psig).

7164d

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