ML20079F415

Provides Summary of Results of Containment Isolation Valves Review,Including Existing Conditions,Proposed Mods & Justifications,Per Conformance to Reg Guide 1.97.Schedule for Installation of Recorders Is 15R Refueling Outage

ML20079F415
Person / Time
Site:	Oyster Creek
Issue date:	09/19/1991
From:	J. J. Barton GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RTR-NUREG-0737, RTR-NUREG-737, RTR-REGGD-01.097, RTR-REGGD-1.097 C321-91-2220, NUDOCS 9110080149
Download: ML20079F415 (4)

Text

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e a' 3 GPU Nuclear Corporation 6 Nuclear sForked n River,

= 38' New Jersey 087310388 609 971 4000 Writer's 0 roct Dial Number.

Setember 19, 1991 C321-91-2220 l

U S. Nuclear Regulatory Commission '

Attention: Document Control Desk j Washington, DC 20555 i i

Gantlemen:

Subject:

Oyster Creek Nuclear Generating Station (OCNGS)

Docket No. 50-2.9 Conformance to Regulatory Guide 1.97 - )

Containment Isolation Valve Position Indication i On February 19, 1991 your latter entitled Emergency Response Capability - I Conformance to Regulatory Guide 1.97, Revision 3, transmitted the NRC staff's Safety Evaluation (SE). As discussed in the SE, the Staff found the l

instrumentation provided by GPU Nuclear for meeting the recommendations of R. G.

1.97, Revision 3, acceptable except for the variables relating to neutron flux, reactor coolant level, reactor coolant system pressure, containment isolation valve position indication, and primary system safety relief valve position ir.dication.

GPUN letter dated May 1, 1991 provided our response to those variables listed

! above except containment isolation valve position indicators for which GPUN l requested additional time to respond.

GPUN topical t eport TR 028 which was transmitted to you by our letter dated July 23, 1990, classified all containment isolation valves except the Main Steam, Emergency Condenser and Reactor Clean Up System Valves as Category 2 type B vari abl es . -- Based on this classification it was determined that redundancy /

o separation. requirements are not applicable to the position indication circuits

! ~ o' of these valves. The Staff, however, concluded in the above mentinned SE that

' 3S$ "the licensee should provide separate Class lE power sources for the containment l- ~$8 isolation valve position-instrumentation "

tn In light of the Staff's conclusion we reviewed containment isolation valves which

! .$ - were classified as Category 2 variables in the Topical Report 028.

-o

! SS LIn the review, availability of the redundancy and/or diversity in the valve

8 . position indication circuits for the inboard and outboard isolation valves were

- -x determined. A summary of the results of this review, including existing ESa_ condo. inns, proposed modification and justifications (if applicable) are provided ,

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-C321-91-2220 Page 2 1.0 Instrument Air line Condition: Existing condition meets the requirements of Regulatory Guide 1.97 Proposed Modification: Not applicable 2.0 Reactor Buildina C1)std Coolina Watar Line - Containment Inlet and Outlet Fl_qw Condition: Existing condition meets the requirements for Regulatory Guide ;.97.

Proposed Modification: Not applicable 3.0 Emeroency Condensqr NE01-A and NE01-B Vent Lines Condition: Position inoication circuits of both inboard and outboard isolation valves for these lines are powered by the same Class IE power supply.

Proposed Modification: Position indicating circuit of one valve will be modified to be powered from a redundant Class IE power source.

4.0 Drywell Eauinment Drain Tank line Inboard and Outboard Isolation Drywell Sumn line Inboard and Outboard . Isolation Vaives Drvwell and Torus Atmos 9here Control Lines Inboard and Outboard Isolation Valves Condition: Position indication circuits of all inboard and outboard isolation valves are powered by the same Class 1E power supply.

' Proposed Modification: Position indicating circuit of one valve in each line will be modified to be powered by a redundant Class IE power source.

.y C321-91 1220 Page 3 5.0 IDIRS to Reactor Buildina Vacuum Relief lines Inhnard and Outboard Isolation Valves.

Condition' . Outboard isolation valves are check valves for which position indication is not available. Position indicating circdit of inboard isolation valves is powered by a Class IE power source. However, both valves have only one set of common red and green indicating linhts in the control room.

Proposed Modification: Position indication is not required for check valves in accordance with Table ? of Regulatory Guide 1.97.

ilowever, one set of red and green indicating lights will be provided for each of the inboard valves.

6.0 Shutdown Coolina Inlet and Outlet line Inboard and Outboard Isolation Valves.

Condition: Position indicating circuits of all valves powered by the same Class IE power supply.

Justification: All isolation valves are kept closed during normal operation. The shutdown cooling system is not required to mitigate the consequences of an accilent. Hence, the position indication of these valves do not prcvide useful information to the operator for accident mitigation.

Propcsed Modification: None

' . 0 liitin Steamline "B" Inboard and Outboard Isolation Valves Condition

Position indication circuits of both inboard and outboard isolation valves are powered by the same Class lE power supply. (Topical Report TR 028 has not identified this deficiency.

This was identified during the detailed review for the proposed modifications.)

. ~t C321-91-1220 Page 4 Proposed Modification: Position indication circuit of one valve will be modified to be powered by a redundant Class IE power source.

The schedule for the implementation of the proposed modifications will be provided in Oyster Creek Integrated Schedule.

It must be noted that our May 1,1991 letter contained an error. The latter stated that wide range reactor pressure recorders which meet Reg, Guide 1.97 Category 1 criteria are currently scheduled to be installed during the next refueling outage (14R). H3 wever, the correct schedule for installation is 15R outage. The correct schedule was provided in our recent Oyster Creek Integrated Schedule which was submitted on June 13, 1991. The Integrated Schedule was approved by your letter dated June 28, 1991.

Should you have any questions regarding this submittal, please contact Mr.

Michael Laggart, Manager, Corporate Nuclear Licensing at (201) 316-7968.

Vc tr ly yours, /

v.

ob i J. Barto

/Vi 2 Presiden d Director OCNGS JJB/YN/ pip cc: Administrator, Region 1 Senior NRC Resident inspector Oyster Creek NRC Project Manager

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