ML20247D233

Requests Meeting to Review Current Status of Combustible Gas Control at Plant,Per 10CFR50.44,due to Inadequate Info Provided by Util.Proposed Agenda Encl

ML20247D233
Person / Time
Site:	Oyster Creek
Issue date:	05/01/1989
From:	Varga S Office of Nuclear Reactor Regulation
To:	Fitzpatrick E GENERAL PUBLIC UTILITIES CORP.
References
GL-84-09, GL-84-9, TAC-62980, NUDOCS 8905250260
Download: ML20247D233 (5)

Text

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May 1, 1989 2.R

'DocketNo.50-)tf .

DISTRIBUTION

Docket J11e> EJordan Mr. E. E. Fitzpatrick NRC Local PDRs BGrimes Vice President and Director Plant File ACRS(10)

Oyster Creek Nuclear Generating Station SVarga Post Office Box 388 BBoger Post Office Box 388 .

SNorris l Forked River, New Jersey 08731 ADromerick OGC

SUBJECT:

10 CFR 50.44, ACTIVE COMBUSTIBLE GAS CONTROL SYSTEM - OYSTER CREEK NUCLEAR GENERATING STATION (TAC NO. 62980)

The staff has determined that information previously supplied by you in submittals or at meetings is not adequate to resolve the outstanding issue of containment air dilution related to combustible gas control (10 CFR 50.44) at Oyster. Creek. I have directed my staff to give this issue high priority so that we may reach resolution as soon as possible. In order to accomplish a speedy resolution, I am requesting that we arrange a meeting, at your earliest convenience, to review the current status of combustible gas control at Oyster Creek. A proposed agenda for this meeting is enclosed. It is our intention to resolve this issue and, if found acceptable,.to issue.a safety evaluation accepting the Oyster Creek design or planned modifications, or to issue an order requiring compliance with 10 CFR 50.44 It should be noted that i the other affected licensees with BWR Mark I containments are also being requested to meet with the NRC.

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I I, along with the project manager and staff from the Plant Systems Branch, will contact you by telephone to make final arrangements for the meeting and to discuss the proposed agenda. If you have an matter, please feel free to contact me at (301)y492-1403, questionsorregarding this the project manager, Alexander Dromerick at (301) 492-1301.

Sincerely,

/s/

Steven A. Varga, Director Division of Reactor Projects I/II Office of Nuclear Reactor Regulation

Enclosure:

As stated cc w/ enclosure:

See next page s,

[ TAC 62980]

• See previous concurrence LA:PDI-4 PM:PDI-4 PD:PDI-4 ADR1 .

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lL t N DocketNo.50-% DISTRIBUTION

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Docket File EJordan Mr. E. E. Fitzpatrick NRC Local PDRs BGrimes Vice President and Director Plant File ACRS(10)

Oyster Creek Nuclear Generating Station SVarga Post Office Box 388 BBoger Post Office Box 388 SNorris Forked River, New Jersey 08731 ADromerick OGC

SUBJECT:

10 CFR 50.44, ACTIVE COMBUSTIBLE GAS CONTROL SYSTEM - OYSTER CREEK NUCLEAR GENERATING STATION (TAC N0. 62980)

The staff has determined that information previously supplied by you in submittals or at meetings is not adequate to resolie the outstanding issue of ,

containment air dilution related to combustible gr.s control (10 CFR 50.44) at '

Oyster Creek. I have directed my staff to give tiiis issue high priority so that we may reach resolution as soon as possible. In order to accomplish a speedy resolution, I am requesting that we arrange a meeting, at your earliest convenience, to review the current status of combustible gas control at Oyster Creek. A proposed agenda for this meeting is enclosed. It is our intention to resolve this issue and to issue a safety evaluation accepting the Oyster Creek design or planned modifications, or to issue an order requiring compliance with 10 CFR 50.44 It should be noted that the other affected licensees with BWR Mark I containments are also being requested to meet with the NRC.

I, along with the project manager and staff from the Plant Systems Branch,

! will contact you by telephone to make final arrangements for the meeting and l to discuss the proposed agendc. If you have an matter, please feel free to contact me at (301)y 492-1403, questions orregarding this the project manager, Alexander Dromerick at (301) 492-1301.

Sincerely, Steven A. Varga, Director Division of Reactor Projects I/II Office of Nuclear Reactor Regulation

Enclosure:

As stated cc w/ enclosure:

See next page

[ TAC 62980]

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L_ _ _ - - - _ - _ _-

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• I Mr. E. E. Fitzpatrick Oyster Creek Nuclear Oyster Creek Nuclear Generating Station Generating Station cc:

Ernest L. Blake, Jr. Resident Inspector Shaw, Pittman, Potts and Trowbridge c/o U.S. NRC 2300 N Street, NW Post Office Box 445 Washington, D.C. 20037 Forked River, New Jersey 08731 J.B. Liberman, Esquire Connissioner Bishop, Liberman, Cook, et al. New Jersey Department of Energy 1155 Avenue of the Americas 101 Connerce Street New York, New York 10036 Newark, New Jersey 07102 Jennifer Moon, Acting Chief Regional Administrator, Region I New Jersey Department of Environmental U.S. Nuclear Regulatory Connission Protection 475 Allendale Road Bureau of Nuclear Engineering King of Prussia, Pennsylvania 19406 CN 415 Trenton, New Jersey 08625 BWR Licensing Manager GPU Nuclear Corporation i Upper Pond Road Parsippany, New Jersey 07054 Deputy Attorney General State of New Jersey Department of Law and Public Safety 36 West State Street - CN 112 Trenton, New Jersey 08625 Mayor Lacey Township 818 West Lacey Road Forked River, New Jersey 08731 Licensing Manager Oyster Creek Nuclear Generating Station l Mail Stop: Site Emergency Bldg.

P. O. Box 388 Forked River, New Jersey 08731 j

l 5 ". .'

MEETING AGENDA FOR 4 DISCUSSION OF PLANT SPECIFIC DESIGN OF ACTIVE COMBUSTIBLE GAS CONTROL SYSTEM I. INTRODUCTION BY NRC STAFF II. MEETING OBJECTIVE To provide sufficient design details of the Nitrogen Injection Capability for each plant to determine if the provisions are adequate to meet the intent of 10 CFR 50.44

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III. AIR-CAD SYSTEM /

NRC staff will provide the basis for concluding that the system should not be used for combustible gas control.

. Represents an air source per GL 84-09 guidence

. Potential misuse of system i

. Impact of deinerting on course of the accident IV. LICENSING BASIS AND BWR EPG'S .,

Reconcile any conflicts between original licrising basis and Rev. 4 to the EWR EFG's.

. When will CAD be used (under what system conditions)

. Is the E0P consistent with FSAR assumptions V. PLANT SPECIFIC DESCRIPTION OF INERTING SYSTEM The objective is to identify all essential components, design conditions, instrumentation, and power supply for the normal inerting system to determine under what post LOCA conditions the system could be expected to function as a combustible gas control system.

A. System / component description l

All components required to operate under post LOCA conditions should l

, be described.

. Design specification (i.e. seismic, redundancy, quality group, i

etc) for a parameter where the component has not been designed for, such as seismic, but is expected to survive, provide the basis

. Location

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. Design pressure and temperature Maximum containment conditions for component operability should also be noted

. Design flow rate as a function of containment pressure B. System Instrumentation Instrumentation necessary to operate the system post LOCA should be identified. ,e

. Identify each sensor, number and location -

. Location of instrument readout If outside control room, determine accessability post LOCA

. System use of sensor output What is sensor used for (automatic valve operation? or not) if operator information only, indicate what type of action is anticipated (flow change, system shutoff, etc)

P C. Operational requirements post LOCA Identify those actions that will be required to initiate system operation and those necessary for monitoring operation. For each action, identify whether it is from the control room or at a remote site.

. Instrumentation needed for startup

. Instrumentation needed for operation

. Power supply (off site and diesel?)

D. Nitrogen capacity (onsite and time to get added supply)

E. Identification of deviations from GDC 41,42, and 43 F. Modifications to eliminate deviations from (e)

~ G. Operational, maintenance, and surveillance history objective is to obtain some basis for determining system availability l

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