05000219/LER-1981-054, Forwards LER 81-054/03L-0.Detailed Event Analysis Encl

Forwards LER 81-054/03L-0.Detailed Event Analysis Encl

ML20038B470
Person / Time
Site:	Oyster Creek
Issue date:	11/30/1981
From:	Carroll J JERSEY CENTRAL POWER & LIGHT CO.
To:	Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20038B471	List: 05000219/LER-1981-054, Forwards LER 81-054/03L-0.Detailed Event Analysis Encl 05000219/LER-1981-054-03, /03L-0:on 811028,trip Setpoint on Main Steam Low Pressure Sensor RE23 Found Below Tech Spec Limit.Caused by Instrument Repeatability.Trip Setpoint Reset
References
NUDOCS 8112080315
Download: ML20038B470 (3)

LER-1981-054, Forwards LER 81-054/03L-0.Detailed Event Analysis Encl

Event date:
Report date:
2191981054R00 - NRC Website

text

,

OYSTER CREEK NUCLEAR GENERATING STATION

$'Q,2,2f S.Z:,j f' (609)693-6000 P O BOX 388

• FORKED RIVER

• NEW JERSEY

• 08731 s.w w, m,w,

November 30, 1981 Mr. Ronald Haynes, Director Office of Inspection and Enforcement Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406

Dear Mr. Haynes:

Subject: Oyster Creek Nuclear Generating Station Docket No. 50-219 Licensee Event Report Reportable Occurrence No. 50-219/81-54/3L This letter forwards three copies of a Licensee Event Report describing Reportable Occurrence No. 50-219/81-54/3L in compliance with paragraph 6.9.2.b.1 of the Technical Specifications.

Very truly yours, l

AMdh J. T. Carroll, Jr.

Acting Director -

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cc: Director (40 copies)

Office of Inspection and Enforcerent

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U.S. Nuclear Regulatory Commission

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Oyster Creek Nuclear Generating Station lh Forked River, NJ 08731 j//

8112080315 811130 PDR ADOCK 05000219 S

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0YSTER CREEK NUCLEAR GENERATING STATION Forked River, New Jersey 08731 Licensee Event Report Reportable Occurrence No. 50-219/81-54/3L Report Dat e November 30, 1981 Occurrence Date October 28, 1981 Identification of Occurrence During surveillance testing, Main Steam Line Low Pressure Sensor RE23D tripped at a pressure lower than the limit specified in Technical Specification Table 3.1.1, Item B.S.

This event is considered to be a reportable occurrence as defined in Technical Specification paragraph 6.9.2.b.l.

Conditions Prior to Occurrence The reactor was operating at steady state power.

Major Plant Pa rameters :

Powe.:

Reactor 1837 MWt Generat or 648 MWe 4

Flow:

Recirculation 14.9 x 10 gpm Feedwat e r 6.9 x 106 lbs /hr Description of Occurrence On Wednesday, October 28, 1981, while perf orming the " Low Pressure Main Steam Line Functional and Calibration Test While Operating" (Surveillance Procedure 619.3.008), Low Main Steam Line Pressure Sensor RE23D tripped at a value less than the corrected Technical Specification limit of 3,834.6 psig. The as found trip setpoint was 830 psig. The limit of >834.6 psig is determined by the Technical Specification limit of >825 (Section 2.3) plus associated head cor rections.

pparent Cause of Occurrence The cause of the occurrence was attributed to instrument repeatability. The as found trip point was 330 psig which is within the design range of instrument repeatability.

s

r 9

Reportable Occurrence

.Fage 2 Report No. 50-219 /81-54/3L Analysis of Occurrence The purpose of the Main Steam Low Pressure trip is to initiate the closure of the Main Eteam Isolation Valves, thereby causing a reactor scram, in order to protect against-rapid reactor depressurization and the resulting high cooldown rate of the vessel. The safety limit ' setting with respect to this condition is 825 psig as per Section 2.3 of the Technical Specifications; however, in order to account for instrument. head correction, an Oyster Creek Standing Order requires a setpoint of >834.6 psig.

Although one (1) Main Steam Low Pressure Sensor (RE23D) would have tripped below the setpoint limit of greater than or equal to 835 psig, the remaining three (3) sensors (RE23A through C).would have actuated above this limit. ' The tus found' trip points of these sensors were 842 psig, 840 psig, 842 psig, re spectively. Therefore, in the event of a main steam low pressure condition, a closure signal to the Main Steam Line Isolation Valves would have been initiated.

Since the Main Steam Isolation Valve closure signal would have been initiated by redundant sensors and since the sensor in question (RE23D) would have actuated at slightly less than the safety limit setting (825 psig), the safety significance of this event is considered minimal.

Corrective Action

The Main Steam Low Pressure Sensor RE23D setpoint was reset to 853 psig.

Additionally, due to the repeatability problem, these sensors (RE23A through D) will be replaced during the next refueling outage.

Failure Data Manufacturer: Mele tro n Model:

372 Ra nge :

20-1400 psig

=

A