05000219/LER-1981-051, Forwards LER 81-051/03L-0.Detailed Event Analysis Encl

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Forwards LER 81-051/03L-0.Detailed Event Analysis Encl
ML20033C978
Person / Time
Site: Oyster Creek
Issue date: 11/18/1981
From: Carroll J
JERSEY CENTRAL POWER & LIGHT CO.
To: Haynes R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20033C979 List:
References
NUDOCS 8112040558
Download: ML20033C978 (3)


LER-1981-051, Forwards LER 81-051/03L-0.Detailed Event Analysis Encl
Event date:
Report date:
2191981051R00 - NRC Website

text

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OYSTER CREEK NUCLEAR GENERATING STATION L

Cllf'";'lJE'.7CA n7 (609)693-6000 P.O BOX 388

  • FORKED RIVER
  • 08731 v~,1 %u Novenber 18, 1981 f//Q Mr. Ronald Haynes, Director Office of Inspection and Enforcamnt oI

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Region I

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United States Nuclear Regulatory Conmission 81; 631 Park Avenu

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DEC3 1981~

l King of Prussia, Pennsylvania 19406 cl yg ver u s.

Dear Mr. Haynes:

SUBJECT: Oyster Creek Nuclear Generating Station

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Docket No. 50-219 Licensee Event Report Reportable Occurrence No. 50-219/81-51/3L This letter forwards three copies of a Licensee Event Report to report Reportable Occurrence No. 50-219/81-51/3L in empliance with paragraph 6.9.2.b(1) of the Technical Specifications.

Very truly yours,

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L.

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. T. Carroll, J cting Director ter Creek JIC:dh Enclosures cc: Director (40 crpies)

Office of Inspection and Enforcment United States Nuclear Regulatory Conmission Washington, D.C.

20555 Director (3)

Office of Managemnt Information and Program Control United States Nuclear Regulatory Comtission Washington, D. C. 20555 NRC Resident Inspector (1)

Oyster Creek Nuclear Generating Station Forked River, N. J.

8112040558 811119 N

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l OYSTER CREEK NUCLEAR GDERATING STATION Forked River, New Jersey 08731 Licensee Event Report Reportable Occurrence No. 50-219/81-51/3L Report Date Novs ber 18, 1981 Occurrence Date October 17, 1981 Identification of Occurrence Electrantic Relief Valve (DIRV) High Pressure Sensor IA83E was found to exceed the limiting safety systen actuation setpoint, Technical Specification 2.3.4.

This event is considered to be a reportable occurrence as defined in the Technical Specifications, paragraph 6.9.2.b(1).

Conditions Prior to Occurrence The plant was shutdown with reactor coolant taperature less than 212 F.

Description of Occurrence on Sunday, October 17, 1981, during perfonnance of the Electrmatic Relief Valve Pressure Sensor Test and calibration (Plant Procedure 602.3.004) high pressure switch IA83E was found to trip at a setting less conservative than the Technical Specification limit of <1070 psig. Surveillance test data on high pressure switches was as follows:

Sensor

  • Tech. Spec. Lunit (psig)
  • As Ebund Trip (psig)

IA83A 1079.15 1059 IA83B 1084.5 1084 IA83C 1076.8 1075 IA83D 1082.2 1070 IA83E 1082.2' 1086

  • Includes head corrections Apparent Cause of Occur:sco The cause of the occurrence is attributed to set point drift.

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Reportable Occurrence Page 2 Report No. 50-219/81-51/3L Analysis of Occurrence Purpose of the DW's is to limit the primary systen pressure. The D4RV's are the first line of defense to maintain the primary systen integrity whose design pressure is 1250 psig.

The DRV's technical specification limit of 1070 psig (not including head correction) was chosen to maintain adequate margin between the electromatic relief setpoint and that of the first group of the code safety valves (whose limiting technical specification setpoint is 1212 + 12 psig). Since the affected HW (NR108E) was still functional and tripped at slightly higher pressure than the desired setpoint, the safety significance is considered minimal.

Corrective Action

'Ihe switch was reset to trip within the required Technical Specification setpoint.

Failure Data Barksdale Pressure Switch Model #B2SH12SS Range 50-1200 psig/ proof 1500 psig l

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