05000219/LER-1981-040, Forwards LER 81-040/03L-0.Detailed Event Analysis Encl

Forwards LER 81-040/03L-0.Detailed Event Analysis Encl

ML20010F190
Person / Time
Site:	Oyster Creek
Issue date:	09/01/1981
From:	Carroll J JERSEY CENTRAL POWER & LIGHT CO.
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20010F191	List: 05000219/LER-1981-040, Forwards LER 81-040/03L-0.Detailed Event Analysis Encl 05000219/LER-1981-040-03, /03L-0:on 810815,electromatic Relief Valve High Pressure Switches IA83B & IA83C Found to Trip Higher than Tech Spec Limit.Caused by Instrument Repeatability.Pressure Sensors Reset to Trip within Required Limits
References
NUDOCS 8109090478
Download: ML20010F190 (3)

LER-1981-040, Forwards LER 81-040/03L-0.Detailed Event Analysis Encl

Event date:
Report date:
2191981040R00 - NRC Website

text

M

.m OYSTER CREEK NUCLEAR GENERATING STATION TX,q,?l'j,'$.C 'J,7l' (609)693-6000 P.O BOX 388

• FORKED RIVER

• NEW JERSEY

• 08731 c enux um.~. sv. n Septaber 1, 1981 d

I y-Mt. Boyce H. Grier, Director J

Office of Inspection and Enforement

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9. ! 'r _ 0319815 -12 Region I United States Nuclear Regulatory Cm mission

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631 Park Avenue

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Dear Mr. Grier:

SUBJECT: Oyster Creek Nuclear Generating Station Docket No. 50-219 Licensee Event Rep]rt Reportable Occurrence No. 50-219/81-40/3L This letter fonrards three copies of a Licensee Event Report to report Reportable Occurrence No. 50-219/81-40/3L in cmpliance with paragraph ti.9.2.b(1) of the Technical Specifications.

Very truly yours, f

Adt/ W

/ J. T. Carroll, Jr.

Acting Director ter Creek JDC:dh Enclosures cc: Director (40 copies)

Office of Inspection and Enforcement United States Nuclear Regulatory Ca mission Washington, D.C.

20555 Director (3)

Office of Managment Information and Program Control United States Nuclear Regulatory Cmmission Washington, D. C. 20555 MRC Resident Inspector (1)

Oyster Creek Nuclear Generating Station f

Forked River, N. J.

[f 81090997 ;

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OYSTER CREEK NUCLEAR GENERATING STATION Forked River, New Jersey- 08731-Licensee Event Report Reportable Occurrence No. 50-219/81-40/3L Report Date Septmber 1, 1981 Occurrence Date August 15, 1981 Identification of Occurrence Electrcanatic Relief Valve High Pressure Sensors IA83B and IA83C were found to exceed the limiting safety systen actuation setpoint, Technical Specification 2.3.4.

This event 1s' considered to be a reportable occurrenca as defined in the Technical l

Specifications, paragraph 6.9.2.b(1).

Conditions Prior to Occurrence l

The plant was shutdown.

Description of Occurrence On Saturday, August 15, 1981, during perfonnance of the Electromatic Relief Valve Pressure Sensor Test and Calibration (Plant Procedure 602.3.004) pressure switches IA83B and IA83C were found to trip at a setting les.= conservative than the Technical Specification limit of <1070 psig. Surveillance test data was as follows:

j Sensor

• Tech. Spec. Limit (psig)

• As Found Trip (psig)

IA83A 1079.15 1055 IA83B 1084.5 1104 + 19.5 IA83C 1076.8 1083 + 6.2 IA83D 1082.2 1069 IA83E 1082.2 1082 I

• Includ,, head corrections Apparen; Cause of Occurrence The cause of the occurrence is attributed to instrunent repeatability.

Reportable Occurrence Page 2 Report No. 50-219/81-40/3L Analysis of Occurrence Primary systen relief valves are provided to ratove sufficient energy from the primary systen to prevent the safety valves frun lifting during the most severe transients that include a scram. An analysis of turbine trip frun full power with a failure of bypass to function has shown with a relief valve setpoint of 1125 psig the D4RV's are capable of limiting the peak pressure below the sotpoint of the first group of safety valves and well below the fuel design pressure limits and reactor coolant systan pressure safety limit.

The relief valve Technical Specification limit of 1070 psig (not including head correction) was chosen to maintain an adoquate margin between peak pressure and the setpoint of the first group of safety valves. Since the relief valves were still functional and tripped only slightly higher than the desired setpoint the safety significance is considered minimal.

Corrective Action

The sensors were reset to trip within 'Ibchnical Specification limits.

'A Technical Specification change was previously subnitted to raise the setpoint of the Electronatic Relief Valves. In addition, theses sensors are scheduled to be replaced during the next refueling outage with an inproved design.

Failure Data Barksdale Pressure Switch l

bbdel #D2SH12SS Range 0-3000 psig