05000219/LER-1982-001, Forwards LER 82-001/03L-0.Detailed Event Analysis Encl

Forwards LER 82-001/03L-0.Detailed Event Analysis Encl

ML20040F524
Person / Time
Site:	Oyster Creek
Issue date:	02/01/1982
From:	Fiedler P GENERAL PUBLIC UTILITIES CORP.
To:	Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20040F525	List: 05000219/LER-1982-001, Forwards LER 82-001/03L-0.Detailed Event Analysis Encl 05000219/LER-1982-001-03, /03L-0:on 820128,during Testing,Containment Spray High Drywell Pressure Indicating Switches IP15A,IP15B & IP15C Found to Trip at Values Greater than Tech Spec Limits. Caused by Instrument Repeatability.Switches Reset
References
NUDOCS 8202090298
Download: ML20040F524 (3)

LER-1982-001, Forwards LER 82-001/03L-0.Detailed Event Analysis Encl

Event date:
Report date:
2191982001R00 - NRC Website

text

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GPU Nuclear g

gf P.O. Box 388 Forked River, New Jersey 08731 609-693-6000 Writer's Direct Dial Number:

February 1, 1982 Mr. Ronald C. Haynes, Administrator

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a, Region I jy e,

U.S. Nuclear Regulatory Commission y

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,s 631 Park Avenue l

,f 6h r3 King of Prussia, PA 19406

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Dear Mr. Haynes:

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Subject:

Oyster Creek Nuclear Generating Station

's 10 Docket No. 50-219

'N]Y Licensee Event Report Reportable Occurrence No. 50-219/82-01/3L This letter forwards three copies of a Licensee Event Report to report Reportable Occurrence No. 50-219/82-01/3L in compliance with paragraph 6 9 2.b.1 of the Technical Specifications.

Very truly yours, (b

4 A

eter B. Fiedler ice President & Dire r

Oyster Creek JTC:lse Encl % ares cc:

Director (40 copies)

Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.

20555 Director (3)

Office of Management Information and Program Control U.S. Nuclear Regulatory Commission Washington, D.C.

20555 NRC Resident Inspector (1)

Oyster Creek Nuclear Generating Station Forked River, NJ 08731 F20:090298 820201 PDR ADOCK 05000219 G

PDR GPU Nuclear is a part of the General Pubhc Utihties System

' OYSTER CREEK NUCLEAR GENERATING STATION Forked River, New Jersey : 08731' Licensee Event -Report Reportable Occurrence 50-219/82-01/3L Report Date February 1,'1982 Occurrence Date January 2,1982 Identification of' Occurrence During surveillance testing, the Containment Spray High Drywell Pressure Indicating Switches IP-15A, IP-15B, and IP-150 tripped at values greater than those given in the Technical Specifications, Table 3.1.1, Item E.1. -

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 in the refuel mode with reactor temperaturo less than 2120F.

- Description of Occurrence.

During performance of the " Containment Spray System Automatic Actuation Test" (Surveillance Procedure 607.3 002) on January 2,1982, the IP-15A, IP-15B, and IP-150 trip points were found to exceed the Technical Specification desired setpoint. Testing of the four sensors yielded the following data:

Switch Designation Desired Setpoint As Found (psig)

As Left (psig)

IP-15A

<2.0 psig 2.05 1 90-IP-15B

]).0 psig.

2.12 1 97 IP-150

<2.0 psig 2.09 1.94 IP-15D

<2.0 psig 1.97 1.97-Apparent Cause of Occurrence The cause of the occurrence was instrument. repeatability. The switches were previously set as follows: IP-15A at 198, IP-15B at 1.94, and IP-150 at 1.92.

They tripped at 2.05, 2.12, and 2.09, respectively.

The range for repeatability is 2-3% of full range, which in the case of the IP-15 switch is 0.2-0 3 psig. The differences between the setpoints and the actual trip points, 0.07 for IP-15A, 0.18 for IP-15B, and 0.17 for IP-150 clearly falls within the range of instrument repeatability.

4 Reportable Occurrence Page 2 Report No. 50-219/82-01/3L Analysis of Occurrence The Containment Spray System consists of two independent cooling loops, each of which is capable of removing heat from the primary containment in the event of a loss of coolant accident. The Containment Spray System will be initiated upon receipt of both a high drywell pressure signal and a reactor low-low water level signal.

Although switches IP-15A, IP-15B, and IP-15C would have tripped at a slightly higher pressure than the desired setpoint, their actuation would have been delayed by only a fraction of a second. Also, the reactor low-low level setpoint is not reached until approximately 4 seconds after the setpoint for high drywell pressure is reached.

Furthermore, the fourth switch, IP-15D, would have actuated :t the required setpoint; and theref ore, the safety significance of the occurrence is considered minimal.

Corrective Action

Pressure switches IP-15A, IP-15B, and IP-15C were reset to trip within the Technical Specifications limit of 2.0 psig (as shown.in the "As Lef t" values in the Description of Occurrence). Setpoint changes to ellow for instrument repeatability are being incorporated into surveillance rocedures.

For the IP-15 switches, the setpoint will be changed from 2.0 + to 1.85 +.10 in order to reduce the frequency of exceeding the Technica Specification limit.

In addition, it has been recommended that these type of snap-action switches be replaced with an improved model, and it is planned to replace them during a future refueling outage.

Failure Data (Same for all three switches)

Manufacturer:

ITT Barton Model:

1. 288A Pressure Indication Switch Range:

0-10 psig