ML19256A970

LER 78-020/03L-1 on 780917:intermidiate Range Monitor (IRM) Channel 17 Failed Downscale While Channel 16 Was Already Inoperable.Caused by Repairman Inadvertently Pulling IRM 17 Wiring Out of Its Connector

ML19256A970
Person / Time
Site:	Oyster Creek
Issue date:	01/10/1979
From:	Ross D JERSEY CENTRAL POWER & LIGHT CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19256A964	List: ML19256A963 ML19256A970
References
LER-78-020-03L, LER-78-20-3L, NUDOCS 7901170205
Download: ML19256A970 (3)

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LICENSEE EVENT REPORT UPLATE REPORT - PREVIOUS REPORT DATE 100578 CONTROL BLOCK: l \ j l l l (PLEAsE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6 o i NlJ 0lC Pl1 @!0 0 l- l 0 0 0 0 10 l- 0 l0 @l411 11 l111 j@l57 CAT 58l@

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REPORT C ATE 7 8 60 61 DOCKETNuvBER 6a 63 EVENT DATE EVENT DESCRIPTION AND PROB ABLE CONSEQUENCES h o 2 While performing control rod timing tests with the reactor in the refuel l o 3 l mode, Technical Specification Table 3.1.1.A.9 was violated when IRM l n 4 l Channel 17 feiled downscale at a time when IRM Channel 16 was already in- l

!oi3, ; operable. Control rod 30-43 which was withdrawn a: the time was imme- l di tely inserted and the administrative rod block was placed in service oK L l until the problem was corrected.

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L 04 J 42 /3 CAUSE DESCRIPTION AND CORRECTIVE ACTloNs 3 o;} Maintenance personnel, working under the vessel on removal of TIP tubing, i jij l inaOventently pulled the wiring for IRM 17 out of its connector. The i

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wiring was repai red and an operabil i ty test was pe rformed orior to re- [ (1 3 3 turning the channel to service. An evaluation wi11 be made to determine l

, 4 if more effective controls can be implemented. l 7 8 9 83 ST T S *, POWER OTHER ST ATUS DISCO RY DISCOVERY DESCRl8 TION 7

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gsaga Weekly press release - October 11, ic78

n Y'@l l 68 " So4 9 1F70205 Donald A. Ross -

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Jersey Central Power & Light Company

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{-) Mad: son Avenue at Punch Bowl Road 6 a_ _ __- ' ~ s_ 'e_E_/ "

Mornstown, New Jersey :'060 (201) 455-82N OYSTER CREEK NUCLEAR GENERATING STATION Forked River, New Jersey 08731 Licensee Event Report Reportable Occurrence No. 50-219/78-20/3L-1 Report Date January 10, 1979 (Previous report dated October 5,1978)

Occurrence Date September 17, 1978 Identification of Occurrence Violat ion of the Technical Specifications, Table 3.1.1. A.9, when Intermediate Range Monitor (IRM) Channel 17 became inoperable in addition to IRM Channel 16, which was al ready 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 the 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 per-formed. Controi rod 30-43 was in a withdrawn position, in the process of being timed. The operator at the controls immediately inserted the withdrawn control 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 underway in preparatica for CRD removal.

Personnel involved with this activity inadvertently pulled the wiring for the IRM out of its connector.

Jersey Centra! Pov er & Lyt Company is a Member of the Gre a Put: c U:nt es S, stem

- P.eportable Occurrence No. 50-219/78-20/3L-1 Page 2 January 10, 1979 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 made, no nore 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 oeer. highly improbable. Additionally, two other channels in the trip system were available to scram the reactor had a high neutron flux condition occurred. The safety significance of this event is, therefore, considered to be minimal.

Corrective Action The wiring for IRM Channel 17 was repaired and an operability check was performed prior to returning the instrument to service. Additionally, (1 the PORC feels that all the required precautions and limitations are already in the appropriate procedures and that difficult working conditions (bubble suits, respirator requirements, etc.) in che area and inef fective supervision are the causes of this recurrent problem. An evaluation will be made to determire if more effective controls can be implemented (PORC Action item 104-78-2) to prevent this type of occurrence.

PORC Action item 104-78-2 will be completed prior to the next refueling outage. It is tne PORC's position that by elaboration on me e effective administrative controls that the potential for this type >f occurrence will be minimized.

Failure Data Similar events occurred in F,eportable Occurrences No. 50-219/~.'7-15/lT and (1 No. 50-219/78-23/3L.