JAFP-95-0900, Submits Plant Annual Rept Re SRV Challenges & Failures

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Submits Plant Annual Rept Re SRV Challenges & Failures
ML20079A718
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 02/23/1995
From: Harry Salmon
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
JAFP-95-0900, JAFP-95-900, NUDOCS 9503010351
Download: ML20079A718 (2)


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Harry P. Salmon, Jr.

f Resident Manager February 23, 1995 JAFP-95-0090 a.

United States Nuclear Regulatory Commission Document Control Desk Mail Station P1-137 Washington, D.C.

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SUBJECT:

James A.

FitzPatrick Nuclear Power Plant Docket No. 50-333 Annual Report Safety Relief Valve Challenges and Failures

Dear Sir:

FitzPatrick Plant Technical Specification 6.9.A.2.b requires that challenges to and failures of Safety Relief Valves (SRVs) be reported annually.

During calendar year, 1994, no challenges to Safety Relief Valves (SRVs) from automatic control circuits or due to pressure transients occurred.

During calendar year, 1994, a total of 23 operator demand challenges occurred to satisfy required Technical Specification surveillance or post maintenance operability demonstrations.

No failures occurred on any of the 23 operator demand challenges.

During a maintenance outage in November, 1993, SRV pilot valve assemblies (02RV-71E and 02RV-71K) were removed and replaced with pilot valve assemblies that had been refurbished and certified as having an actual lift pressure within 1% of the setpoint.

Both of the pilot valve assemblies that had been removed in November, 1993, were subsequently tested in February, 1994, and both failed to lift within 1% of the setpoint.

Refer to LER-94-002 for additional details.

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United _Stotco Nuclocr ROgulatcry Cosmiccion Annual Report safety Relief Valve Challenges and Failures Page 2 During a maintenance outage in April, 1994, the pilot valve assemblies for SRVs 02RV-71E and 02RV-71J were removed and replaced with pilot valve assemblies that had been refurbished and certified as having an actual lift pressure within 1% of the setpoint.

In June, 1994, the test facility determined that both pilot assemblies removed in April, 1994, had an as-found lift pressure in excess of the required 1% tolerance.

Refer to LER-94-005 for additional details.

No additional SRV failures due to pressure demand,'cn lift setpoint testing occurred in 1994.

During the 1994/1995 refuel outage six SRV pilot valve assemblies were removed in December, 1994, for replacement with refurbished and racertified pilot valve assemblies.

On January 6, 1995,,the test laboratory performing the tests on the pilot valve assemblies informed the New York Power Authority that five of the pilot valves had not lifted within 1% of the setpoint.

Refer to LER-95-001 for additional details.

If you have any questions concerning this report, please contact Mr. A. Zaremba.

Very truly yours, 4

Y P. SALMON, JR.

RESIDENT MANAGER

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Regional Administrator USNRC Resident Inspector M. Colomb R. Barrett D. Lindsey c

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