ML20008D967

Requests Addl Info Re Inservice Insp of Pressure Isolation Valves.Forwards Position

ML20008D967
Person / Time
Site:	McGuire, Mcguire
Issue date:	10/06/1980
From:	Tedesco R Office of Nuclear Reactor Regulation
To:	Parker W DUKE POWER CO.
References
NUDOCS 8010240006
Download: ML20008D967 (4)

Text

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NUCLEAR REGULATORY COMMISSION g

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Docket Nos.: 50-369 OCT 061980 and 50-370 Duke Power Ccmpany ATTN: Mr.141111am 0. Parker, Jr.

Vice President - Steam Production P. O. Box 33189 422 South Church Street Charlotte, N. C.

28242

SUBJECT:

INSERVICE INSPECTION OF PRESSURE ISOLATION VALVES (McGuire Nuclear Station, Units 1 and 2)

As a result of our review of your application regarding inservice inspection of pressure isolation valves, we require the following information:

Provide a list of pressure isolation valves included in your testing program with four (4) sets of piping and instrumentation diagrams which clearly show the reactor coolant system iso-lation valves. Also discuss in detail how your leak testing program conforms to the staff position (see enclosure).

It is requestad that this information be provided by October 6,1980.

This positio's has previously been provided to your staff.

Sincerely,

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Robert L. Tedesco, Assistant Director for Licensing Division of Licensing

Enclosure:

Staff Position -

Inservice Inspection of Pressure Isolation Valves, September 22, 1980 l

1 8010240

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0-ENCEOSURE 9/22/80 Staff Position Inservice Inspection of Pressure Isolation Valves There are several safety systems connected to the reactor coolant pressure boundary that have design pressure below the rated reactor coolant system (RCS) pressure. There are also some systems which are rated at full reactor pressure on the discharge side of pumps but have pump suction belt.,w RCS pressure. In order to protect these systems from RCS pressure, two or more isolation valves are placed in series to form the interface between the high pressure RCS and the low pressure systems. The leak tight integrity of these valves must be ensured by periodic leak testing to prevent exceeding the design pressure of the low pressure systems thus causing an inter-system LOCA.

Pressure isolation valves are required to be Category A or AC per IWV-2000 and to meet the appropriate requirements of IWV-3420 of Section XI of the ASME code except as discussed below.

s Limiting Conditions for Operation (LCO) are required to be adden to the technical specifications which will require corrective action f.e., shutdown or system isolation when the final approved leakage limits are not met.

Also surveillance requirements, wiiich will state the acceptable leak rate testing frequency, shall be provided in the technical specifications.

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Periodic leak testing of each pressure isolation valve is required to be performed at. lea,st once,per each refueling outage, after valve maintenar.:e prior to return tojservice and each time the valve has moved from its i

fully closed position unless justification is given. The testing interval I

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. should average to be approximatel*. one year. Leak testing should also be performed'after all disturbance to the valves are complete, prior to reachin power operation following a refueling outage maintenance and etc.

The staff's present position on leak rate limiting conditions for operation must be equal to or less than 1 gallon per minute to ensure the integrity of the valve, demonstrate the adequacy of the redundant pressure isolation function and give an indication of valve degradation over a finite period of time.

Significant increases over this limiting value would be an indication of valve degradation from one test to another.

Leak rates higher than 1 GPM will be considered if the leak rate changes are below 1 GPM above the previous test leak rate or system design precludes measuring 1 GPM with sufficient accuracy. These items will be reviewed on a ease-by-case basis.

The Class 1 to ' Class 2 boundary will be considered the isolation point which must be protected by redundant isolation valves.

In cases where pressum isolation if provided by two valves, both will be s

independently leak tested. When three or more valves provide isolation, only t.

two of the valves need to be leak tested.

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Mr. William O. Darker, Jr.

Vice Presid.ent, Steam Production Duke Power Company P. O. Box 2178 422 South Church Street Charlotte, florth Carolina 28242 cc: Mr. W. L. Porter David, Flesichaker, Esq.

Duke Power Company 1735 ' Eye Street, N. W.

P. C. Box 2178 Suite 709 422 South Church Street Washinaton, D. C.

20006 l

Charlotte, North Carolina 28242 Richard P. Wilson, Esq.

Mr. R. S. Howard Assistant Attorney Geneal Power Systems Division State of South Carol N Westinghouse Electric Corporation 2600 Cull Street P. O. Box 355 Columbia, South Carolina 29201 Pittsburgh, Pennsylvania 15230 Mr. E. J. Keith Office of Intergovernmental Relations 116 West Jones Street EDS Nuclear Incorporated Raleigh, North Carolina 27603 220 Montgomery Street San Francisco, California 94104 County Manager of Mecklenburg County 720 East Fourth Street Mr. J. E. Houghtaling Charlotte, North Carolina 28202 NUS Corporation 2536 Countryside Boulevard U. S. Environmental Protection Agency Clearwater, Florida 33515 ATTN: EIS Coordinator Region IV Office Mr. Jesse L. Riley, President 345 Courtland Street, N. W.

The Carolina Environmental Study Group 854 Henley Place Atlanta, Georgia 30308 Charlotte, North Carolina 28207 Mr. Tom Donai-Resident Inscector McGuire NPS J. Michael McGarry, III, Esq.

c/o USNRC Debevoise & Liberman Post Office Box 216 1200 Seventeenth Street, N. W.

Cornelius, North Carolina 28031 Washington, D. C.

20036 Rober t M. Lazo, Esq., Chairman Atomic Safety and Licensing Board U. S. Nuclear Regulatory Comission Washington, D. C.

2055:5 br. Emmeth A. Luebke Atomic Safety and Licensing Board

u. S. Nuclear Regulatory Comission

-ashington, D. C.

20555 Or. Cadet H. Hand, Jr., Director Bodega Marine Lab of California P. O. Box 247 Bodega Bay, California 94923

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