ML20245H995

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Requests Meeting Between Util & NRC to Discuss Current Status of Combustible Gas Control at Facility.Proposed Agenda Encl
ML20245H995
Person / Time
Site: Millstone 
Issue date: 05/01/1989
From: Varga S
Office of Nuclear Reactor Regulation
To: Mroczka E
NORTHEAST NUCLEAR ENERGY CO.
References
TAC-65067, NUDOCS 8905030605
Download: ML20245H995 (5)


Text

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n May 1, 1989 9

Docket No. 50-245 DISTRIBUTION

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Ecket Filei EJordan Mr. Edward J. Mroczka NRC" Local PDRs BGrimes

' Senior Vice President Plant File ACR$(10)

Nuclear Engineering and Operations SVarga i

Northeast Nuclear Energy Company BBoger P. O. Box 270 SNorris Hartford, Connecticut 06141-0270 MBoyle OGC

Dear Mr. Mroczka:

SUBJECT:

10 CFR 50.44, ACTIVE COMBUSTIBLE GAS CONTROL SYSTEM - MILLSTONE j

NUCLEAR POWER STATION UNIT N0. 1 (TAC NO. CSC67)

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 4

Miilstone 1.

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 Millstone 1.

A proposed agenda for this meeting is enclosed.

It is our intention to resolve this issue and, if found acceptable., to issue a safety evaluatior accepting the Millstone 1 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, w'ill contact you by telephone to make final arrangements for the meeting and to discuss the proposed ogenda.

If yau have an matter, please feel free to contact me at (301)y questions regarding this 492-1403, or the project manager, Michael Bcyle, at (301) 492-1308.

Sincerely,

/s/

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

Enclosure:

As stated cc w/ enclosure:

See next page

[ TAC 65067)

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s' Docket No. 50-245 DISTRIBUTION Docket FiTe-EJordan Mr. Edward J. Mroczka NRC Local PDRs BGrimes j

Senior Vice President Plant File ACRS(10)

Nuclear Engineering and Operations SVarga Northeast Nuclear Energy Company BBoger j

P. O. Box 270 SNorris

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m Hartford, Connecticut 06141-0270 MBoyle OGC j

Dear Mr. Mroczka:

1

SUBJECT:

10 CFR 50.44, ACTIVE COMBUSTIBLE GAS CONTROL SYSTEM - MILLSTONE 1

HUCLEAR POWER STATION UNIT No. 1 (TAC N0. 65067)

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

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containment air dilution related to combustible gas control (10 CFR 50.44) at Millstons 1.

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 Millstone 1.

A proposed agenda for this meeting is enclosed.

It is our intention to resolve this issue and to issue a safety evaluation accepting the Millstone 1 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 to discuss the proposed agenda.

If you have an matter, please feel free to contact me at (301)y questions regarding this 492-1403, or the project manager, Michael Boyle, at (301) 492-1308.

Sincerely,

i j

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

Enclosure:

As stated 1

cc w/ enclosure-See next page

[ TAC 65067]

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__._________.________________m

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J' Mr. Edward'J. Mroczka Millstone Nuclear' Power Station' Northeast Nuclear. Energy Company Unit No. l' cc:

Gerald Garfield, Esquire R. M. Kacich, Manager Day, Berry and Howard Generation Facilities Licensing Counselors at Law Northeast Utilities Service Company City Place Post Office Box 270 Hartford, Conne'cticut 06103-3499 Hartford,. Connecticut 06141-0270 W. D. Ronberg, Vice President D. 0. Nordquist Nuclear Operations Manager of Ouality Assurance Northeast Utilities Seryice Company Northeast Nuclear Energy Company Post Office Box 270 Post Office Box 270 Hartford, Connecticut 06141-0270 Hartford, Connecticut 06141-0270 Kevin McCarthy, Director Regional Administrator Radiation Contro1~ Unit Region I i

Department of Environmental Protection U. S. Nuclear Regulatory Commission State Office Building 475 Allendale Road Hartford, Connecticut 06106 King of Prussia, Pennsylvania 19406 i

Bradford S. Chase, Under Secretary First Selectmen Energy Division Town of,Waterford Office of Policy and Management Hall of Records 80 Washington Street 200 Boston Post Road Hartford, Connecticut 06106 Waterford, Connecticut 06385 S. E. Scace, Station Superintendent W. J. Raymond, Resident Inspector Millstone Nuclear Power Station Millstone Nuclear Power Station Northeast Nuclear Energy Company c/o U. S. Nuclear Regulatory Commission Post Office Box 128 Post Office Box 811 Waterford, Connecticut 06385 Niantic, Connecticut 06357 J. P. Stetz, Unit Superintendent Millstone Unit No. 1 Northeast Nuclear Energy Company Post Office Box 128 Waterford, Connecticut 06385

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MEETING 1.GuiDA FOR 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 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 i

Potential misuse of' system Impact of deinerting on course of the accident IV. ' LICENSING BASIS AND BWR EPG'S Reconcile any conflicts between original licensing basis and Rev. 4 to the EWR EFG's.

WhenwillCADbeused(underwhatsystemconditions)

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 combt.stible gas control system.

A.

System / component description All components required to operate under post LOCA conditions should be described.

l Design specification (i.e. seismic, redundancy, quality group, etc) for a parameter where the component has not been designed for, such as seismic, but is expected to survive, provide the I

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2-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 recessary to operate the system post LOCA should be identified.

,e Identify each sensor, number and location Location of instrument readeut If outside control room, determine accessability post LOCA System use of s nsor output What is sensor used for (automatic valve operation? ornot)if operator information only, indicate what type of action is anticipated (flow change, system ' shutoff, etc)

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?)

i D.

Nitrogen capacity (onsite and time to get addeo supply)

E.

Identification of deviations from GDC 41,42, and 43 F.

Modificationstoeliminatedeviationsfrom(e)

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Operational, maintenance, and surveillance history objective is to obtain some basis for determining system availability 1

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