ML19345C525

Requests Info Resulting from Review of Application Re Inservice Insp of Pressure Isolation Valves.Requests List of Pressure Isolation Valves Included in Testing Program W/Four Sets of Piping & Instrumentation Diagrams

ML19345C525
Person / Time
Site:	Perry
Issue date:	11/17/1980
From:	Tedesco R Office of Nuclear Reactor Regulation
To:	Davidson D CLEVELAND ELECTRIC ILLUMINATING CO.
References
NUDOCS 8012050425
Download: ML19345C525 (4)

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't r. Dalwyn R. Davidson y

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Vice President, Engineering g

M e.3 The Cleveland Electric Iluminating Company

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P. O. Box 5000 Cleveland, Ohio 44101

SUBJECT:

INSERVICE IfiSpECTIO?i 0F FRESSURE ISCLATION VALVES (Perry Muclear Power Plant, Unit Nos.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 testinq program with fcur (4) sets of piping and instrumen-tation abgrams which clearly show the reacter coolant system isolation alves. Also, discuss in detail how your leak test-ing progran confoms to the staff position (see enclosure).

It is requested that this infomation be provided within 15 days of receipt of this letter. This position has previously been provided to your staff.

Sincerely, Original signed by Robert L. Tedesco, Assistant Director l

for Licensing Division of Licensing

Enclosure:

Staff Position -

Inservice Inspection of Pressure Isolation Valves, l

i September 22, 1980 8 012050 W5 SEE ATTACHED LIST FOR DISTRIBUTION j_

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Mr. Dalwyn R. Davidsen Vice President, Engineering The Cleveland Electric Illuminating Company P. O. Box 5000 Clevelano, Ohio 44101 cc: Gerald Charnoff, Esq.

Shaw, Pittman, Potts 1 Trewbridge 1800 '1 Street, N. W.

Mashington, D. C.

20036 Donald H. Hauser Esq.

Cleveland Electric Illuminating Company P. O. Box 5000 Cleveland, Ohio a4101 U. S. Nuclear Regulatory Ccmmission Resident Inspector's Office

?armly at Cantar Road Perry, Ohio 44081

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210.0 MECHANICAL ENGiftEERING BRANCH There are several safety systems connected to the reactor coolant pressure bcundary that have design pressure below the rated reactor coolant system (RCS) pressure. There are also some systems whicn are rated at full reactor pressure on the discharge side of pumps but nave pump suction below RCS pressure.

!n order to protect these systems fr:m RCS pressure, two or more isolation valves are placed ir 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 recuired to be category A or AC cer IW-2000 and to meet the appropriate recuirements of IW-3*20 of Section XI of the ASME Code except as discussed below.

Limiting Conditions for Operation (LCO) are recuired to be added to the technical specifications which will require corrective action f.e., shutcown or system isolation unen the final approved leakage limits are not met. Also surveillance requirements, unich will state the acceptable leak rate testing frequency, shall be pr: viced in the technical specifications.

Periodic leak testing of each pressure isolation valve is required to ce performed at least once per each refueling outage, after valve maintenance criar to return to service, anc for systems rated at less than 50" of RCS design pressure each time the valve has moved from its fully closed position unless j"stification is given.

The testing interval should average to be approximately one year. Leak testing should also be performed after all disturbances to ne valves are com::lete, prior to reaching 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 er less than 1 gallon per minute for each valve (GPM) to ensure the integrity of tne valve, demonstrate the adequacy of the redundant pressure isolation function and give an indicaticn of valve degradaticn over a finite period of time. Significant increases over this limiting valve would be an indication of valve degradation from one test to anothar.

Leak rates higher tnan 1 GPM will be considered if the leak rate changes are below 1 GPM above the previous test leak rate or system design precluces measuring 1 GPM with sufficient accuracy. These items will be reviewed on a case 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 pressure isolation is provided by two valves, both will be inde-pendently leak tested. When three or more valves provide isolation, only two of tne valves need to be leak tested.

Provide a list of all pressure isolation valves included in your testing program along with four sets of Piping and Instrument Diagrams which cescribe your reactor coolant system pressure isolation valves. Also discuss in detail how your leak testing program will conform to the above staff position.

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