05000333/LER-1980-046-03, Surveillance Testing Revealed Shutdown Cooling Permissive Switches Set in Excess of 75 Psig Limit.Caused by Procedural Error.Instruments Recalibr & Returned to Svc

Surveillance Testing Revealed Shutdown Cooling Permissive Switches Set in Excess of 75 Psig Limit.Caused by Procedural Error.Instruments Recalibr & Returned to Svc

ML19320B513
Person / Time
Site:	FitzPatrick
Issue date:	07/07/1980
From:	W. Verne Childs POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19320B508	List: 05000333/LER-1980-046, Forwards Updated LER 80-046/03X-1 05000333/LER-1980-046-03, Surveillance Testing Revealed Shutdown Cooling Permissive Switches Set in Excess of 75 Psig Limit.Caused by Procedural Error.Instruments Recalibr & Returned to Svc
References
LER-80-046-03X, LER-80-46-3X, NUDOCS 8007140394
Download: ML19320B513 (2)

LER-1980-046, Surveillance Testing Revealed Shutdown Cooling Permissive Switches Set in Excess of 75 Psig Limit.Caused by Procedural Error.Instruments Recalibr & Returned to Svc

Event date:
Report date:
3331980046R03 - NRC Website

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POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT 00CKET NO.50-333 ATTACHMENT TO LER 80- 046/03X-1 Page 1

of 1

During normal operations on April 30, 1980, surveillance testing to satisfy the requirements of Technical Specifications Table 4.2-1 revealed two (2) of four (4) shutdown cooling permissive switches set in excess of the 75 psig limit in Technical Specifications Table 3.2-1.

Shutdown cooling permissive switch 02-PS-128A and B each operate two switches and follower relays which are part of the shutdown cooling permissive circuitry which only allows the initiation of shutdown cooling when the reactor vessel dome pressure has decreased to less than 75 psig. Correspondingly, an increase in the reactor vessel dome pressure above 75 psig, while shutdown cooling is in service, isolates the shutdown cooling system from the reactor vessel to protect low pressure piping from overpressurization.

During the surveillance testing, switches No. I and No. 2 associated with 02-PS-128A were found set higher than allowed. Switch No. I was set 17 psig high and switch No. 2 was set 9 psig high.

Both switches associated with 02-PS-128B were found set within the Technical Specifi-cation limit. The improper set point was attributed to Instrument drif t at that time.

Instrument 02-PS-128A was recalibrated and the surveillance interval was increased from monthly to weekly to monitor performance of the switches. Five weeks later on June 7,1980 switch No. I associated with 02-PS-128A were again found set above the Technical Specification limit my approximately 40 psig.

Investigation revealed that the procedure was confusing and could be misinterpreted resulting in adjustment of 02-PS-128A in order to bring'one of the switches (No. I or No. 2) Into calibration and simultaneously place the other switch out of calibration.

A similar misadjustment of 02-PS-128B was also possible but had not occurred.

As a result of this finding, Instrument Surveillance Procedure F-ISP-5-1 titled " Reactor High Pressure (Shutdown Cooling Permissive)" was revised and the instruments were recalibrated and returned to service in a fully operable status.

No additional action is required. The ever.t did not represent a significant hazard to the public health and safety.

NOTE:

This followup report is submitted to correct the cause of failure and to report the out of specification test results on June 7, 1980.