ML18093A746

LER 88-003-00:on 880224,reactor Trip Occurred on False intermediate-range High Flux Signal.Caused by Personnel Error.Maint Mgt Completed Review of Circumstances Surrounding Event.Individual counseled.W/880316 Ltr

ML18093A746
Person / Time
Site:	Salem
Issue date:	03/16/1988
From:	Pollack M, Zupko J Public Service Enterprise Group
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
LER-88-003-02, LER-88-3-2, NUDOCS 8803230073
Download: ML18093A746 (4)

Text

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Public Service Electr-ic and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station March 16, 1988 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Dear Sir:

SALEM GENERATING STATION LICENSE NO. DPR-70 DOCKET NO. 50-272 UNIT N0.-1 LICENSEE EVENT REPORT 88-003-00 This Licensee Event Report is being submitted pursuant to the requirements of 10CFR 50.73(a) (2) (iv). This report is required within thirty (30) days of the event.

Sincerely yours,

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General Manager-Salern Operations MJP:pc Distribution 95-2189 (11 Ml 12-8C

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l'ACILITY NAME 111 Salem Generating Station - Unit 1 0 I 5 I 0 I 0 I 0 I 2 I 7 ,2 I 1 OF 0 I 3 TITLE 141 Rx. Trip on a False Intermediate Range - High Flux Signal Due To Personnel Error DATI Ill Liii Nuroi.Ell 111 llEPOllT DATE 171 OTHEll FACILITIEI INVOLVED Ill FACILITY NAMES DOCKET NUMllERISI O I I0 I 0 I0 I I I oh 214 s s s Is - oIo I 3 * - o b o13 1 I6 a ls

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- ID.7111111211.UlllAI I0.73C.llllllUI - 111.nc.1121111111111 lo.nc.1121Cal LICENIEE CONTACT FOii THll-LEll 1111 NAME TELEl'HONE NUMIER AREA CODE M. J. Pollack - LER Coordinator COMPLETE ONE LINE FOii EACH COWONENT FAILUllE DEIClllllD IN THll lllPOllT 11~1 MANUFAC MANUFAC CAUSE SYSTEM COMPONENT TUR ER SYSTEM COMPONENT TUR ER I I I I I I I I I I I I I I I I I I I I I I I I I I I I IUl'PLEMENTAL llEPOllT EXl'ICTl!D 1141 MONTH DAY Y~AR EXPECTED SUBMISSION DATE 1161

- - , YES (If Y*. t:amp- EXPECTED SUllM1$SION DA TEJ I I I On February 24, 1988 at 0436 hours0.00505 days <br />0.121 hours <br />7.208995e-4 weeks <br />1.65898e-4 months <br />, a reactor trip occurred from 4%

power.* The "first out" annunciation, indicating the cause of the trip, was "IR High Flux". The Unit was involved in a reactor startup following the completion of a refueling outage. The root cause of this trip has been attributed to personnel ~rror. A Maintenance-I&C te~hnician after successful completion 6f N35 Interm~diate R~~ge channel adjustment was requested by Operations personnel to repeat the procedure to determine if a correlation between a No. 13 Tavg channel spike and the N35 channel adjustment existed. Upon repeating the procedure, the technician performed the procedure out of sequence. The output trip signal was not bypassed prior to pulling the channel fuses. The technician involved in this event was counseled. A Human Performance Evaluation System (HPES) review of this event will be conducted to preclude future occurrences. In_

addition~ this event and the results of the HPES recommendations will be evaluated by the PSE&G Nuclear Training Center for incorporation into appropriate training programs. '

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I LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 1 5000272 88-003-00 2 of 3 PLANT AND SYSTEM IDENTIFICATION:

Westinghouse - Pressurized Water Reactor Energy Industry Identification System (EIIS) codes are identified in the text as {xxJ IDENTIFICATION OF OCCURRENCE:

Reactor Trip on a False Intermediate Range - High Flux Signal Due to Personnel Error Event Date: 02/24/88 Report Date: 03/16/88 This report was initiated by Incident Report No.88-068.

CONDITIONS PRIOR TO OCCURRENCE:

Mode 2 Reactor Power 4% - Unit Load 0 MWe DESCRIPTION OF OCCURRENCE:

On February 24, 1988 at 0436 hours0.00505 days <br />0.121 hours <br />7.208995e-4 weeks <br />1.65898e-4 months <br />, a reactor trip occurred from 4%

power. The first out" annunciation, indicating the cause of the trip, was "IR High Flux". The Unit was involved in a reactor startup following the completion of a refueling outage.

The Unit was stabilized in Mode 3 (Hot Standby), and in accordance with the requirements of the Code of Federal Regulations, 10CFR 50.72(b) (2) (ii), the Nuclear Regulatory commission was notified of the automatic actuation of the Reactor Pr6tection System {JC}.

APPARENT CAUSE OF OCCURRENCE:

The root cause of this trip has been*attributed to personnel error.

On February 24, 1988 at 0230 hours0.00266 days <br />0.0639 hours <br />3.80291e-4 weeks <br />8.7515e-5 months <br />, during post refueling outage low power testing, Reactor Engineering requested Maintenance-I&C personnel to adjust the 1N35 Intermediate Range Channel setpoint to 25% (using procedure lPD-16.4.034 - "Intermediate Range 1N35 Bistable Adjustment"). During the refueling outage, the 1N35 intermediate range detector was replaced.

• When the 1N35 channel setpoint adjustment was performed, the No. 13 Reactor Coolant Loop Tavg channel spiked. Operations contacted the technician and request~d the technician to. repeat the procedure to determine if a correlation between the spike and the equipment being checked by the procedure existed. When the technician returned to the racks to do as requested, he performed the procedure out of sequence.

The technician had removed the channel fuses prior to bypassing the.

output trip signal. Therefore, the logic was satisfied to cause the reactor to trip on Intermediate Range (IR) - High Flux.

I LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 1 -5000272 88-003-00 3 of 3 ANALYSIS OF OCCURRENCE:

The IR - High Flux trip provides reactor core protection during reactor startup. It provides redundant protection to the low setpoint trip of the Power Range, Neutron Flux channels. The IR - High Flux trip is set to cause a reactor trip at a current level proportional to approximately 25% of rated thermal power unless manually blocked. No credit is taken for operation of this trip in the accident analysis for the Unit.

• The Reactor Protection System functioned as designed to_ trip the reactor upon sensing the IR - High Flux logic signal. This event involved no undue risk to the health or safety of the public. Due to the- operation of the Reactor Protection System, this event is reportable to the Nuclear Regulatory Commission in accordance with Code of Federal Regulations 10CFR 50.73(a) (2) (IV).

CORRECTIVE ACTION:

Maintenance management has completed a review of the circumstances surrounding this event. The Maintenance-I&C individual involved was counseled. The need to follow procedures was stressed.

A Human Performance Evaluation System (HPES) investigation has been initiated.

Investigation into the No. 13 Tavg channel indicated the spike was caused by a defective RTD. The spare RTD is now in use and the defective RTD will be replaced during a future outage of sufficient duration. The channel spike was coincidental with the N35 channel setpoint adjustment.

This event and the results of the HPES evaluation will be reviewed by the PSE&G Nuclear Training Center for incorporation into applicable training programs.

Ge~~9-Salem Operations MJP:pc SORC Mtg.88-022