05000311/LER-1981-131, Forwards LER 81-131/03L-0.Detailed Event Analysis Encl

Forwards LER 81-131/03L-0.Detailed Event Analysis Encl

ML20040C676
Person / Time
Site:	Salem
Issue date:	01/15/1982
From:	Midura H Public Service Enterprise Group
To:	Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20040C677	List: 05000311/LER-1981-131, Forwards LER 81-131/03L-0.Detailed Event Analysis Encl 05000311/LER-1981-131-03, /03L-0:on 811228,low Reading Noticed on 24 Reactor Coolant Loop Flow Channel 2.Channel Declared Inoperable. Caused by Failure of Flow Transmitter.Flow Transmitter Replaced & Calibr Satisfactorily
References
NUDOCS 8201290144
Download: ML20040C676 (3)

LER-1981-131, Forwards LER 81-131/03L-0.Detailed Event Analysis Encl

Event date:
Report date:
3111981131R00 - NRC Website

text

{{#Wiki_filter:_ l O PSEG ^ ' Public Service Electric and Gas Company P.O. Box 168 Hancocks Bridge, New Jersey 08038 Salem Generating Station January 15, 1982 4 Mr. R. C.' Haynes 9 m Director of USNRC g Office of Inspection and Enforcement d'

- Region 1 631 Park Avenue rj?

SpgEIVED ) s King of Prussia, Pennsylvania 19406-{Mte'l/ INS 7198g ~ b kfp j

Dear Mr. Haynes:

g . LICENSE NO. DPR-75 8 DOCKET NO 50-311 %l m REPORTABLE OCCURRENCE 81-131/03L Pursuant to the requirements of Salem Generating Station Unit N6'.,2, Technical Specifications, Section 6.9.1.9.b, we are submitting Licensee Event Report for Reportable Occurrence 81-131/03L. This report is required within thirty,(30) days of the occurrence. Sincerely yours, //. } %e O W J H. J. Midura General Manager - Salem Operations ^ FD: al CC: Distribution b. f 4-N \\ 9201290144 820115 The Energy People PDR ADOCK 05000311 g'>2m o2 so im 9 W S PDR

Report Number: 81-131/03L Report Date: 01-15-82 Occurrence Date: 12-28-81 Facility: Salem Generating Station, Unit 2 Public Service Electric & Gas Company Hancocks Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE: No. 24 Reactor Coolant Loop Flow Channel 2 - Inoperable. This report was initiated by Incident Report 81-514. CONDITIONS PRIOR TO OCCURRENCE: Mode ' - Rx Power 99% - Unit Load 1110 MWe DESCRIPTION OF OCCURRENCE: On December 28, 1981 the Control Room Operator noticed a low reading on No. 24 Reactor Coolant Loop Flow Channel 2. The channel was de-clared inoperable at 1530 hours and Action Statement 3.3.1 Action 7 was entered. This occurrence constituted operation in a degraded node in accordance with Technical Specification 6.9.1.9.b. DE_.iGNATION OF APPARENT CAUSE OF OCCURRENCE: The cause of the low flow indication was failure of the flow transmitter. ANALYSIS OF OCCURRENCE: Technical Specification 3.3.1 Action 7 requires: With the number of operable channels one less than the total number of channels, startup and/or power operation may proceed until performance of the next required channel functional test provided the inoperable channel is placed in the tripped con-dition within 1 hour.

LER 81-131/03L ~

CORRECTIVE ACTION

The channel bistables were placed in the tripped condition within 1 hour. The flow transmitter was replaced and calibrated satisfac-torily. The No. 24 Reactor Coolant Loop Flow Channel 2 was tested satisfactorily and declared operable. At 1546 hours, December 29, 1981 Action Statement 3. 3.1 Action 7 was terminated. FAILURE DATA: Fischer and Porter Co. Differential Pressure Flow Transmitter Model 10B2496 Prepared by F. Dickey //(/ h j[ sed Gendral Manager - Salem Operations SORC Meeting No. 82-08 l l i 1 l }}