ML20005E179

Forwards Changes to 891030 Rev 1 to Inservice Test Program. Encl Revised Relief Request V-49 Indicates That Full Stroke Exercising of Each Valve Will Be Performed During First Refueling Outage But No Longer than June 1990

ML20005E179
Person / Time
Site:	Seabrook
Issue date:	12/27/1989
From:	Feigenbaum T PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NYN-89175, NUDOCS 9001040028
Download: ML20005E179 (5)

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l lNew H'ampshire<

Ted C. F:'_ ' ::

Senior Vice President and Chief Operating Officer '

NYN 89175 December 27, 1989 j

United States Nuclear Regulatory Conunission Washington, DC 20555

. Attention: Document Control Desk

References:

(s)

Facility Operating License NPF-67, Docket No. 50-443 (b)'

NHY Letter NYN-89131,. dated October 30, 1989, ' Inservice.

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Test Program (IST), Revision 1, Change," T. C. Feigenbaum to v

USNRC

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Subject:

Inservice Test Program (IST), Revision 1, Changes Gentlemen:.

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-New Hampshire Yankee (NHY) submitted in Reference (b), proposed changes Lto-its Inservice Test Program, Revision 1.

Included in Reference (b), was a i

.one-time' relief request, numbered V-49, which applied to eight Safety

-Injection System check valves which were disassembled, repaired and

reassembled subsequent to low power testing.

These check valves serve as Reactor Coolant System pressure boundary isolation-valves.

A post-maintenance full stroke exercise of these valves in accordance with the ASME Boiler and Pressure Vessel Code is currently impractical.

In order to provide the plant configuration necessary for a full stroke exercise of these check-valves the reactor vessel head would have to be removed. A Safety Injection Pump could then be utilized to demonstrate full flow capability through the eight check' valves.

The enclosed revised relief request V-49 proposes to stroke exercise the Safety Injection System check valves utilizing partial flow capability, for each of the eight valves, in lieu of a full flow stroke exercise. The proposed. test method is expected to achieve 10-25 gpm through each check valve under parallel flow conditions. This amount of flow is sufficient to verify an' adequate partial stroke given that the test instrumentation to be utilized

-is-capable of detecting flow in excess of 0.5 gpm.

Additionally, the revised relief request indicates that each of the eight check valves was satisfactorily inspected during its disassembly or repair for loose or corroded partc, and manually exercised to assure proper operation.

Each valve ~is also being radiographed to verify proper orientation of valve internals. Radiography will be complete before entry into Mode 4.

The revised relief request (V-49) also indicates that full-stroke exercising of each valve will be performed during the first refueling outage but in no case later than June, 1992.

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-9001040028 891227 0f f 3

'PDR ADOCK 05000443 P

PDC New Hampshire Yonkee Division of Public Service Company of New Hompshire

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P.O. Box 300

• Seabrook, NH 03874

• Telephone (603) 474-9521

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-l United States Nuclear Regulatory Commission December. 27,-1989 Attention: Document Control ~ Desk ~

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• p If you have any questions regarding this letter please contact Mr. Terry L. Harpster, Director of Licensing Services at_(605) 474-9521, extension'2765.

Very_truly yours, j~

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$/ W Ted C. Feigenbaum-Enclosure y

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cci~ Mr. William T. Russell n.['

Regional-Administrator United States' Nuclear Regulatory Commission Region I 475 Allendale Road

. King of Prussia,-PA 19406 Mr. Victor Nerses, Project Manager Project Directorate I-3 United States Nuclear Regulatory Commission Division.of Reactor Projects Washington, DC 20555 Mr. Antone'C. Carne NRC Senior Resident Inspector P.O. Box 1149 Seabrook, NH 03874 i-l i

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,p New Hampshire Yankee

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December 27, 1989 fl i

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ENCLOSURE 1 TO NYN-89175' INSERVICE TEST PROGRAM (IST)

-REVISION 1 CHANGES j

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5 Relief Recocat V-49 E

. Valves:

SI-V81, SI-V86, SI-V106. SI-V118, SI-V122, SI-V126, SI-V130 Category: AC Code Class:

2 Functions (Active) Reactor Coolant Pressure Boundary Isolation Valves Test Reouirements:

IWV-3200, IWV-3520 Basis for Relief:

During the Low Power Test Program, leakage was observed through the above' listed Safety Injection System check valves.

Subsequently, these valves were repaired and/or replaced.

IWV-3200 requires that when a valve has been replaced, repaired or has undergone maintenance that could affect its performance, and prior to the time it is returned to

'j service, it must be tested to demonstrate that the performance parameters which could be affected by the l

replacement, repair or maintenance are within acceptable l.

limits.

q l-Full-stroke exercising of these check valves during the l

present cold shutdown condition is impractical since it would require operation of a safety injection pump to flow to the reactor coolant system, which is prohibited by present Seabrook Station Technical Specifications.

To comply with Seabrook Station Technical Specifications, it would require removal of the reactor vessel head to flow a Safety Injection pump to the RCS. Full-stroke exercising of these check valves during plant heatup is not practical due to the potential for low temperature overpressurization of the RCS. Full-stroke exercising of these check valves during plant operation is not possible because the RCS pressure is greater than the shutoff head of the Safety Injection pumps.

In lieu of full-stroke exercising, these valves can be l

partially-stroked during the present plant shutdown using L~

RHR pump flow connected to the Safety Injection System.

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In addition to partial flow exercising, during disassembly and/or replacement, these valves were satisfactorily inspected for loose or corroded parts, and manually exercised to assure that no binding exists that would interfere with valve operation. The design of these valves I

is simple (lift check valve) and incorporates the use of only two moving parts (plug and spring) so there is a high assurance after reassembly of proper valve operation.

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Basis for Relief:

Additionally, a search of available industry records (continued).

through the Nuclear Plant Reliability Data System (NPRDS) of comparable check valves was conducted and indicated.that

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there have been no known instences of failure of similar l

check valves to open when required.

Future testing will be performed in accordance with the approved IST Program Plan.

Alternate Testinn Each check valve during disassembly or repair was inspected j

for loose or corroded parts and manually exercised to assure proper operation of the valve.

Following' reassembly, radiographs are being performed to verify proper orientation-of valve interaals.

Partial-stroke exercising will be performed on each valve during the present plant shutdown using RHR pump flow cross connected to the Safety-Injection System.

Flow through individual valves will be verified and quantified, and records maintained for future use.

Full-stroke exercising of these valves will be performed during the first scheduled refueling outage but in no case later than June, 1992.

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