05000219/LER-1980-023-03, /03L-0:on 800523,prior to Inservice Insp Reactor Vessel Hydro,Testing Revealed That Electromatic Relief Valve High Pressure Sensor IA83B Exceeded Tech Spec Setpoint. on 800531,sensor IA83F Found to Exceed Setpoint

/03L-0:on 800523,prior to Inservice Insp Reactor Vessel Hydro,Testing Revealed That Electromatic Relief Valve High Pressure Sensor IA83B Exceeded Tech Spec Setpoint. on 800531,sensor IA83F Found to Exceed Setpoint

ML19318C054
Person / Time
Site:	Oyster Creek
Issue date:	06/23/1980
From:	Ross D JERSEY CENTRAL POWER & LIGHT CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19318C045	List: 05000219/LER-1980-023, Forwards LER 80-023/03L-0 05000219/LER-1980-023-03, /03L-0:on 800523,prior to Inservice Insp Reactor Vessel Hydro,Testing Revealed That Electromatic Relief Valve High Pressure Sensor IA83B Exceeded Tech Spec Setpoint. on 800531,sensor IA83F Found to Exceed Setpoint
References
LER-80-023-03L, LER-80-23-3L, NUDOCS 8006300482
Download: ML19318C054 (3)

LER-1980-023, /03L-0:on 800523,prior to Inservice Insp Reactor Vessel Hydro,Testing Revealed That Electromatic Relief Valve High Pressure Sensor IA83B Exceeded Tech Spec Setpoint. on 800531,sensor IA83F Found to Exceed Setpoint

Event date:
Report date:
2191980023R03 - NRC Website

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E% E*4f DESCRIPTION AND PRCBASLE CONSECUENCES h 101:1l On May 23. 1980. orior to the commencement nf the In<ervice Inenerefnn I

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(201)455-8203 OYSTER CREEK NUCLEAR GENERATING STATION Forked River, New Jersey 08731 Licensee Event Report Reportable Occurrence No. 50-219/80-23/3L Report Date

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June 23, 1980 Date of Occurrence May 23, 1980 and May 31, 1980 identification of Occurrence Exceeding a limiting condition for operation as per Technical Specifications, paragraph 2.3.4, when the electromatic relief valve high pressure actuation setpoint was found to be higher than the limiting safety system setting.

This event is considered to be a reportable occurrence as defined in the Tech-nical Specifications, paragraph 6.9.2.b.

Conditions Prior to Occurrence The plant was shutdown for refueling and maintenance.

Description of Occurrence On May 23, 1980, prior to the commencement of the Inservice Inspection reactor vessel hydrostatic test, the electromatic relief valve high pressure actuation pressure sensors were tested.

IA838 was found to exceed the Tech Spec setpoint.

The as-found setpoints were as follows:

Sensor As-Found (psig)

Tech Spec Setpoint (psig)*

IA83A 1065 1079.15 lA838 1086 1084.5 lA83C 1076 1076.8 1A83D 1070 1082.2 lA83E Was not tested at this time

• Including head correction After testing was completed, the setpoints were increased above the operating cechnical specifica~ ion limit to the reactor vessel hydro overpressure protection limit with the exception of sensor "E".

"E" electromatic relief valve's high pressure actuation was bypassed from the cont rol room during the hydro.

i Jersey Central Power & Light Company is a Member of the General Pubhc Utihties System

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e Reportable Occurrence No. 50-219/80-23/3L Page 2 June 23, 1980 Af ter completion of the hydro on May 31, 1980, the setpoints of the sensors for A, B, C, & D valves were set at less than the tech spec limit. The sensor for "E" valve was found to be set at 1085 psig (2.8 psig above the corrected tech spec setpoint 1082.2 psig).

Apparent Cause of Occurrence 4

Both instruments of concern exhibited drift characteristics well within the total accuracy of the instrument.

Analysis of Occurrence i

i Electromatic relief valve actuation at high reactor pressure serves to limit the peak reactor pressure. Although the high pressure actuation setpoints of two of the controllers were above the tech spec limit, electromatic relief valve function on high pressure was still operable and capable of limiting reactor pressure to a value less than the lowest safety valve actuation point.

Peak reactor pressure would be higher, but would still be limited from reaching the safety limit of 1375 psig by actuation of the safety valves. The failure of the sensors to trip at their prescribed setpoint had no effect on the health and safety of the public.

Corrective Action

Both pressure sensors were reset to trip points meeting or conservative to the Technical Specifications.

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