05000311/LER-1982-142, Forwards LER 82-142/03L-0.Detailed Event Analysis Encl

Forwards LER 82-142/03L-0.Detailed Event Analysis Encl

ML20070G561
Person / Time
Site:	Salem
Issue date:	12/08/1982
From:	Midura H Public Service Enterprise Group
To:	Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20070G570	List: 05000311/LER-1982-142, Forwards LER 82-142/03L-0.Detailed Event Analysis Encl
References
NUDOCS 8212220381
Download: ML20070G561 (3)

LER-2082-142, Forwards LER 82-142/03L-0.Detailed Event Analysis Encl

Event date:
Report date:
3112082142R00 - NRC Website

text

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1PSEG Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station December 8, 1982 Mr. R. C. Haynes Regional Administrator USNBC Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406

Dear Mr. Haynes:

LICENSE NO. DP R-7 5 DOCKET NO. 50-311 REPORTABLE OCCURRENCE 82-142/03L Pursuant to the requirements of Salem Generating Station Unit No. 2, Technical Specifications, Section 6.9.1.9.b, we are submitting Licensee Event Report for Reportable Occurrence 82-142/03L. This report is required within thirty (30) days of the occurrence.

Sincerely yours, l , h lYlv&

H. J. Midura General Manager -

Salem Operations RF:ks CC: Distribution 8212220381 821200 PDR ADOCK 05000311 S PM The Energy People  %*

% 2189 t20'O 1181

Report Number: 82-142/03L Report Date: 12-08-82 Occurrence Date: 11-23-82 Facility: Salem Generating Station Unit 2 Public Service Electric & Gas Company Hancock's Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:

Reactor Trip and Engineered Safety Feature Actuation System Instrumentation - No. 21 Steam Generator Level Channel IV -

Inoperable.

This report was initiated by Incident Report 32-483.

CONDITIONS PRIOR TO OCCURRENCE:

Mode 1 - RX Power 81 % - Unit Load 890 MWe.

DESCRIPTION OF OCCURRENCE:

At 1640 hours0.019 days <br />0.456 hours <br />0.00271 weeks <br />6.2402e-4 months <br />, November 23, 1982, during r0 cts.a- operation, the Control Room Operator observed that No. 21 Steam Gcnotau r Level Channel IV indication was reading 4% higher than the of.hr c..Innels. Due to the excessive difference, Channel IV was declarr 1, a. arable, and Limiting conditions for Operation 3.3.1 Action 7 and 3.3 < .'ation 14 were entered. All bistables associated with the che.nnc. were placed in the tripped conditon at 1652 hours0.0191 days <br />0.459 hours <br />0.00273 weeks <br />6.28586e-4 months <br />, November 23, 1982. Tbc redundant steam generator level channels were operable throughe.;t the occurrence.

APPARENT CAUSE OF OCCURRENCE:

Attempts at recalibrating the channel level transmitter were unsuccessful, and the problem was attributed to failure of the transmitter. No other problems with the channel were evident, and no recent failures of this type were noted. The occurrence was therefore assumed to be of an isolated nature.

ANALYSIS OF OCCURRENCE:

The steam generator level instruments are utilized in the Reactor Trip and Engineered Safety Feature Actuation Systems. A reactor trip on low steam generator level insures a minimum DNBR of 1.30 during normal operation and anticipated transients. Automatic initiation of auxiliary feedwater flow insures that the Reactor Coolant System can be cooled down to less than 350 F in the event of a total loss of offsite power.

Due to the operability of the redundant channels, the event involved no risk to the health and safety of the public. The occurrence constituted operation in a degraded mode permitted by a limiting l

l

LER 82-142/93L ANALYSIS OF OCCURRENCE: (cont'd) condition for operation. As such, the incident is reportable in accordance with Technical Specification 6.9.1.9b.

Limiting Conditions for Operation 3.3.1 Action 7 and 3.3.2 Action 14 require:

With the number of operable channels one less than the total number of channels, power operation may proceed until performance of the next required channel functional test, provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

CORRECTIVE ACTION:

As noted, the bistables associated with the channel were placed in the tripped condition as required by the action statements. The failed transmitter was replaced and the new transmitter calibrated. No. 21 Steam Generator Level Channel IV was satisfactorily tested, the channel was declared operable, and at 1835 hours0.0212 days <br />0.51 hours <br />0.00303 weeks <br />6.982175e-4 months <br />, November 24, 1982, Limiting Conditions for Operation 3.3.1 Action 7 and 3.3.2 Action 14 was terminated. In view of the nature of the occurrence, no further action was deemed necessary.

FAILURE DATA:

ITT-Barton Corp.

Differential Pressure Transmitter Model 764 Prepared By R. Frahm b[E Gendral Manager -

SORC Meeting No.82-109

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