ML19294A348

LER#78-020/03L-0 on 780917:Tech Specs Table 3.1.1,A,9 Violated When Intermediate Range Monitor Channel 17 Became Inoper in Addition to IRM Channel 16 Which Was Already Inoper Due to Maint Activities Performed Under React Vessel

ML19294A348
Person / Time
Site:	Oyster Creek
Issue date:	10/05/1978
From:	Ross D JERSEY CENTRAL POWER & LIGHT CO.
To:
Shared Package
ML19294A344	List: ML19294A343 ML19294A348
References
LER-78-020-03L, LER-78-20-3L, NUDOCS 7810120076
Download: ML19294A348 (3)

Text

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LICENSEE EVENT REPORT

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3$n"CE 60 lLl@l015 61 0DOCKET 01012l119l@l01911 NUYBER 68 63 171718l@ll EVENT DATE 74 10 75 10 15 17 1880 @

REPORT DATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h o 2 l whiin nerfnrninn enntrol rod timino tests with the reactor in the refuel 0 3 I mnde. Technical Soecification Table 3.1.1.A.9 was violated when IRM l 0 4 I channe1 17 failed downscale at a time when IRM Channel 16 was already in- l o 5 I nnerable. Control rod 30-43 which was withdrawn at the time was immed- l 0 6 I iately inserted and the administrative rod block was placed in service l 10 7 I until the problem was corrected. l 0 8 l 80 7 8 9 SYSTEM CAUSE CAUSE COY P. VALV E CODE CODE SUSCODE COMPONENT CODE SUSCODE SUBCODE O 9 lI l Aj@ 10 A l@ l C l@ l1 lN l5 lT lR lU l@ 18 19 E l@ 20 Z[@

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Q' Mad: son Avenue at Punch Bow' Road Mornstown. New Jersey 07960 (201)455-8200 OYSTER CREEK NUCLEAR 3ENERATING S'ATION Forked River, New Jersey 0d731 Licensee Event Report Reportable Occurrence No. 50-219/78/20-3L-0 Report Date October 5, 1978 Occurrence Date September 17, 1978 Identification of Occurrence Violation of the Technical Specifications, fable 3.1.1,A,9 when I n t e rmed ia te Range Monitor Channel 17 became inoperable in addition to IRM Channel 16, which was already inoperable.

This event is considered to be a reportable occurrence as defined in the Technical Specifications, paragraph 6.9.2,b,2.

Conditions Prior to Occurrence The event occurred during refueling shutdown.

Description of Occurrence On Sunday, September 17, 1978, at approximately 1345 hours0.0156 days <br />0.374 hours <br />0.00222 weeks <br />5.117725e-4 months <br />, IRM Channel 17 failed downscale during the time control rod timing tests were being performed.

Control rod 30-43 was in a withdrawn position, in the process of being timed.

The operator at the controls immediately inserted the withdrawn cont rol rod and placed the administrative rod block in service until the problem was corrected.

Apparent Cause of Occurrence The failure of IRM 17 was attributed to the maintenance activities that were being performed under the reactor vessel at the time of the occurrence. Removal of the TIP tubing was underv.ay in preparation for CRD removal. Personnel in-volved with this activity inadvertantly pulled the wiring for the iRM sut of its connector.

Jersey Central Power & Lignt Company is a Member of the Genera Pubhc Utit.es System

Reportable Occurrence No. 50-219/78/20-3L-0 Page 2 October 5, 1978 Analysis of Occurrence The IRM system provides the automatic features required for knowledgeable and efficient reactor operations in the intermediate power range. High level trips, actuated by the outputs from the IRM channels, are used to trigger a reactor scram with certain coincident trip requirements. At the time of the occurrence, the reactor was in the refuel mode. In this mode, no more than one control rod can be in the withdrawn position at one time. Since this protective function was in effect, a reactivity excursion would have been highly improbable. Additionally, two (2) other channels in the trip system were available to scram the reactor had a high neu: ^n flux condition occurred.

The safety significance of this event is therefore considered to be minimal.

Correct ive Action The wiring for IRM Channel 17 was repaired and an operability check was performed prior to returning the instrument to service.

Failure Data Not applicable.

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