ML19031A819

LER 1978-029-01 for Salem Unit 1 Inoperability of Two Power Range Channels During Training Startups

ML19031A819
Person / Time
Site:	Salem
Issue date:	06/21/1978
From:	Librizzi F Public Service Electric & Gas Co
To:	Grier B NRC/IE, NRC Region 1
References
LER 1978-029-01
Download: ML19031A819 (4)

Text

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p Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 Phone 201 /622-7000 o

June 21, 19 7 8 f~:.~i::-i

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Mr. Boyce H. Grier Director of USNRC Off ice of Inspections and Enforcements Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406

Dear Mr. Grier:

LICENSE NO. DPR-70 DOCKET NO. 50-272 REPORTABLE OCCURRENCE 78-29/0lT Pursuant to* the requirements of Salem Generating Station Unit No. 1 Technical Specifications, Section 6.9.1.8.b, we are submitting Licensee Event Report for Reportable Occurrence 78-29/0lT. This report is required within fourteen (14) days of the occurrence.

Sincerely yours, F. P. Librizzi General Manager -

Electric Production CC: Director, Office of Inspection and Enforcement (40 copies)

Director, Office of Management Information and Program Control (3 copies)

/

The Energy People i_ 95-2001 300M 1 C

. Report Number: tit 78-29/0lT Report Date: 6/21/78 Occurrence Date: 6/10/78 Facility: Salem Generating Station Public Service Electric & Gas Company Hancocks Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:

Inoperability of Power Range Channels N41 and N42 Loss of both Source Range Channels in Mode 3 CONDITIONS PRIOR TO OCCURRENCE:

Startup Mode 2 -*Reactor startups for training being conducted.

Maximum power - Sxlo-6 amp. Intermediate Range DESCRIPTION OF OCCURRENCE:

On June 9, 1978, instrumentation personnel were directed to remove the signal input and high voltage leads from power range channel N42 and to connect these leads through a pico-arnpmeter to the reactivity computer. This was done so that physics data could be obtained during the training startup and shutdown evolutions that were scheduled to be performed the following day. ,on June 10, 1978, seven reactor startups and shutdowns were performed for training.

During this period, noise was encountered on the reactivity com-puter. Instrumentation personnel were called to investigate the noise. Investigation revealed that although channel N42 bistables had been placed in the tripped condition, the signal input and high voltage leads had been removed from channel N41. These actions resulted in two (2) effectively inoperable power range channels.

These conditions being in excess of those allowed by Technical Speci-fication 3.3.1.1. Action Statement No. 2 required reliance on Technical Specification 3.0.3. Immediately upon identifying these conditions, the unit was taken sub-critical and the reactor trip breakers were opened.

While attempting to restore power range channels N41 and N42 to their desired configuration (N41 - Normal, N42 - To Reactivity Computer), the. 118 VAC Instrument Power Fuses were removed from channel N41. When the first of these two fuses was removed, a reactor trip signal was initiated. Also, the resultant surge ener-gized the P-10 permissive which automatically de-energized the High Voltage from both Source Range channels causing both channels to be inoperable. Both Source Range channels were immediately re-energized.

Source range inoperability was less than 1 minute. Power Range channel N41 was returned to normal and Technical Specification 3.0.3 requirements were terminated.

LER 78-29/0lT DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:

The cause of this occurrence was personnel error. The instrument supervisor identified the wrong leads to be removed and connected to the reactivity computer.

Loss of source range was due to personnel error in that instrument fuse was removed with existing reactor trip signal.

ANALYSIS OF OCCURRENCE:

Technical Specification 3.0.3 states that "in the event a Limiting Condition for Operation and/or Associated Action requirements cannot be satisfied because of circumstances in excess of those addressed in the specification, the facility shall be placed in Hot Standby within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and in Cold Shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> unless corrective measures are completed that permit operation under the permissible action statements for the specified time interval as measured £rom initial discovery".

Immediately upon identification of the two (2) inoperable power range channels, the unit was placed in Hot Standby and Power Range channel N41 was returned to operable status. Seven reactor startups were performed in violation o.f Technical Specification 3. 3 .1.1.

Maximum reactor power during critical.operation was Sxlo-6 amps.

CORRECTIVE ACTION:

Power Range channel N41 was returned to normal. Power Range channel N42 was properly connected to the reactivity computer.

To prevent further occurrences of this type, this*event will be thoroughly reviewed with all instrumentation personnel with particular emphasis on proper equipment identification.

FAILURE DATA:

N/A Prepared by T. L. Spencer

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Manager - Salem Generating Stat' SORC Meeting No. 37-78

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NRC FORM 366 LAT UR Y COMl'JriSSION '

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7 U 60 61 COCl<E7 lliUMBER 68 69 EVENT CATE 74 75 REPORT CATE 80 EVENT DESCRIPTION ANO PROBABLE CONSEQUENCES(@)

• I During training startups, two inoperable power range channels were ITIIJ I identified. Wrong leads had been disconnected for reactivity computer.!

[§ID Unit immediately placed in Mode 3. Power Range channel N41 returned to!

[))I) operable status. Channel N43 and N44 were operable throughout this

[:mJ event. Seven startups conducted in violation of T.S. 3.3.1.1.

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OJ:§] I The cause of this event was personnel error in that the instrument supet-visor failed to identify the proper leads for removal. Instrument per- I

• sonnel will review this incident with particular emphasis on proper OJI] I equipment identification.

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