05000416/LER-1987-006, Corrected LER 87-006-00:on 870501,isolation Valve in Steam Supply Piping to RCIC Sys Turbine Inadvertently Isolated. Caused by Personnel Error.Personnel Counseled

Corrected LER 87-006-00:on 870501,isolation Valve in Steam Supply Piping to RCIC Sys Turbine Inadvertently Isolated. Caused by Personnel Error.Personnel Counseled

ML20214W670
Person / Time
Site:	Grand Gulf
Issue date:	05/29/1987
From:	Byrd R, Kingsley O SYSTEM ENERGY RESOURCES, INC.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
LER-87-006-01, LER-87-6-1, NUDOCS 8706160126
Download: ML20214W670 (4)

LER-2087-006, Corrected LER 87-006-00:on 870501,isolation Valve in Steam Supply Piping to RCIC Sys Turbine Inadvertently Isolated. Caused by Personnel Error.Personnel Counseled

Event date:
Report date:
4162087006R00 - NRC Website

text

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LICENSEE EVENT REPORT (LER)

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On May 1, 1987 at 2240 an isolation valve in the steam supply piping to the Reacter Core Isolation Cooling (RCIC) system turbine received an isolation signal while technicians were filling and venting an associated transmitter reference leg.

The isolation signal was cleared and the valve reopened by 2245.

Prior to and during the transmitter reference leg fill and vent evolution, the technicians placed the transmitter's associated trip unit in the calibration mode and applied a specified current input to the trip. unit to simulate normal conditions. This action is performed to prevent a spurious trip which could occur during the reference leg fill and vent evolution. Prior to returning the system to service, an I&C technician connected a digital volt meter to the trip unit to check the readings. However, the meter was in the current mode rather than the voltage mode, which caused the signal voltage to drop and actuate the trip unit.

The technician immediately recognized his error and notified Control Room operators. This task is considered to be within the knowledge and skills of the Maintenance Instrumentation and Controls (I&C) technicians and does not need to be included in a detailed work instruction. The technician was counseled concerning the error, gl 8706160126 870529 ,. I PDR ADOCK 05000416 S PDR J19AECM87052201 - 3

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A. REPORTABLE OCCURRENCE  !

On May 1, 1987 an isolation valve in the steam supply piping to the Reactor Core Isolation Cooling (RCIC) system turbine inadvertently ,

isolated while technicians were filling and venting an associated transmitter reference leg. The isolation is part of the Containment and Reactor Vessel Isolation Control System (CRVICS) function and is considered to be an ESF actuation reportable pursuant to 10CFR50.73(a)(2)(iv).  ;

B. INITIAL CONDITIONS The plant was operating at 100 percent power at the time of the isolation.

C. DESCRIPTION OF OCCURRENCE On May 1, 1987 Instrumentation and Controls (I&C) technicians were filling and venting a reference leg associated with transmitter N084B ,

(GG-1JM-PDT-N0848). This transmitter and its trip unit provide a leak detection / containment isolation function by isolating inboard isolation valve F063 (GG-1BN-ISV-F063) on an RHR/RCIC steam line high flow signal.

Prior to and during the fill and vent evolution, the technicians placed the transmitter's associated trip unit in the calibrate mode and applied a specified current to the input of the trip unit to simulate normal conditions. This action was performed in accordance with approved instructions to prevent a spurious trip which could occur during the reference leg fill and vent evolution. Prior to restoring the trip unit to service, the I&C technician connected a digital volt meter (DVM) to the test jacks of the trip unit to check the readings. However, the DVM was in the current mode rather than in the voltage mode which caused the signal voltage to drop and actuate the trip unit.. Valve F063 isolated at 2240. The isolation signal was cleared and the valve was reopened by 2245.

D. APPARENT CAUSE ,

The cause of the isolation was personnel error. The I&C technician incorrectly left the DVM in the current mode rather than placing it in the voltage mode when he plugged the DVM test leads into the test jacks of the trip unit. The technician immediately recognized his error and '

notified operators in the Control Room. This task is considered to be within the knowledge and skills of the Maintenance Instrumentation and  !

Controls (I&C) technician and does not need to be included in a detailed I work instruction.

J19AECM87052201 - 4

Attachment to AECM-87/0105 meC foran 304A . U S. NUCLtA3 E EIutifi/AY COMMissiCN LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Anaovia ows No siso m4 EXPIRES 8/31/8B 8 AClLITT NAME III DOCKET NUMSER (2) LER huMSER 468 PACE 131 saa "R!R.-- "O.*J:

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01016 0l0 0l3 013 rw w - m . m .. m nac w ma mm E.- SUPPLEMENTAL CORRECTIVE ACTIONS The individual involved was counseled regarding the error. The Plant ,

Management Review Board consisting of Manager of Maintenance, Manager of Support and Acting Manager of Operations conducted a review of the incident which determined that no additional action was required. Also a review was conducted to determine if there were any general weaknesses in the training program for the proper use of a DVM and no weakness was found. , ,

F. SAFETY ASSESSMENT There were no safety consequences as a result of this event. The RCIC system was unavailable for approximately 5 minutes; however, the high pressure core spray (HPCS) system, the Automatic Depressurization System and low pressure ECCS systems were available. The plant Technical Specification allow the RCIC system to be inoperable for up to 14 days provided the HPCS system is operable.

J19AECM87052201 - 5

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, CORRECTED COPY: To correct event date on the first page of the LER form from 05/18/87 to 05/01/87.

EVETEM ENERGY REEDtJRCEE. INC.

O;S VTGE :: D

@li?Lj~ .3 3 May 29, 1987 U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Document Control Desk Gentlemen:

SUBJECT:

Grand Gulf Nuclear Station Unit 1

• Docket No. 50-416 License No. NPF-29 Inadvertent Reactor Core Isolation Cooling System Isolation Due to Personnel Error LER 87-006-00 AECM-87/0105 Attached is Licensee Event Report (LER) 87-006-00 which is final report.

Yours ruly,

/

/

ODK:baa .

Attachment cc: Mr. T. H. Cloninger (w/a)

Mr. R. B. McGehee (w/a)

Mr. N. S. Reynolds (w/a)

Mr. H. L. Thomes (w/o)

Mr. R. C. Butcher (w/a)

Dr. J. Nelson Grace, Regional Administrator (w/a)

U. S. Nuclear Regulatory Commission Region II 101 Marietta St., N. W., Suite 2900 Atlanta, Georgia 30323 Yh\

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