ML20084K401

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Forwards List of Safety & Relief Valve Failures & Challenges for 1982-83,per NUREG-0737,Item II.K.3.3
ML20084K401
Person / Time
Site: FitzPatrick 
Issue date: 05/07/1984
From: Bayne J
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To: Vassallo D
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.3.03, TASK-TM JPN-84-31, NUDOCS 8405140015
Download: ML20084K401 (5)


Text

123 Main Street Whee hains, New Yek 10001 e-914 681.6200

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May 7, 1984 JPN-84-31 Director of Nuclear Reactor Regulation U.

S.

Nuclear Regulatory Commission Washington, D.

C.

20555 Attention:

Mr. Domenic B. Vassallo Operating Reactors Branch No. 2 Division of Licensing

Subject:

James A.

FitzPatrick Nuclear Power Plant Docket No. 50-333 NUREG-0737 Item II.K.3.3 Safety and Relief Valve Failures and Challenges

Dear Sir:

NUREG-0737 Item II.K.3.3 requires that challenges to safety and relief valves (SRVs) be reported on an annual basis. to this letter provides a report of challenges occurring between January 1, 1983 and December 31, 1983. provides a report of challenges occurring between January 1, 1982 and December 31, 1982.

This report was inadvertently not transmitted previously.

If you have any further questions, please do not hesitate to contact us.

Very truly yours, g

J.

P.

Bayne Executive Vice President l

Nuclear Generation cc:

Office of the Resident Inspector U. S. Nuclear Regulatory Commission P. O. Box 136 Lycoming, New York 13093 t

8405140015 840507 k

PDR ADOCK 05000333 P

PDR g

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i JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 May 7, 1984 JPN-04-31

SAFETY RELIEF VALVE FAILURES AND CHALLENGES 1983 D7to Valve Challenges

  • Failure Remarks 1/05/83 02-RV-71K None Yes

- Valve serial No. 1047

- Set-point 1105 (11%) psig

- Test at Wyle Laboratory revealed lift pressure of 1216 psig

- Pilot disc and seat were refurbished, and tested satisfactorily at setpoint of 1140 (I l% ) psig.

)l/17/83 02-RV-71A 1 (operator)

No 02-RV-71G 1 (pressure)

No 02-RV-71H 2 (pressure)

No 02-RV-71J l (operator)

No 02-RV-71L 1 (pressure)

No 02-RV-71K 1 (pressure)

Incon-Valve Serial No 1056 clusive - Set point 1090 (

1%) psig

- Examination of post trip log printout indicates peak reactor pressure of 1120 psig.

- Subsequent test at Wyle Laboratory did not reveal any problem.

)9/03/83 02-RV-71H None Yes

- Valve serial No. 1053

- Setpoint 1140 (

1%) psig

- Valve solenoid failed to operate from remote SRV panel during surveillance test due to a ground fault in the DC control circuit.

Valve, however, was fully operable from the control room, from ADS logic circuits and with respect to reactor pressure demand.

Operated normally from remote SRV panel following correction of ground fault.

operator - challenge caused by operator action pressure - challenge caused by system pressure o

F e

JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 May 7, 1984 JPN-84-31 2 -

SAFETY RELIEF VALVE FAILURES AND CHALLENGES 1982 Dnte Valve Challenges

  • Failure Remarks 10/18/82 02-RV-71D None Yes

- Valve serial No 1080

- Set point 1140 (i 1%) psig

- Test at Wyle Laboratory revealed lift pressure of 1204 psig.

It was found that there was gross pilot leakage and pilot disc and seat were steam cut.

Valve was refurbished and retested with satisfactory results with a setpoint of 1105 (f l% ) psig.

12/16/82 02-RV-71A 1 (pressure)

No 02-RV-71J l (pressure)

No 02-RV-71J l (operator)

No 1

02-RV-71L 1 (pressure)

No o

operator - challenge caused by operator action pressure - challenge caused by system pressure 1

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