05000483/LER-1986-001, :on 860119,at 100% Power,Esf Actuation Occurred.Caused by Restoration of Power to Containment Purge Radiation Monitor Due to Failure to Place Monitor in Bypass.Technicians Counseled

:on 860119,at 100% Power,Esf Actuation Occurred.Caused by Restoration of Power to Containment Purge Radiation Monitor Due to Failure to Place Monitor in Bypass.Technicians Counseled

ML20153D493
Person / Time
Site:	Callaway
Issue date:	02/14/1986
From:	Randolph C, Robinson W UNION ELECTRIC CO.
To:	NRC OFFICE OF ADMINISTRATION (ADM)
References
LER-86-001, LER-86-1, ULNRC-1257, NUDOCS 8602240160
Download: ML20153D493 (4)

LER-1986-001, on 860119,at 100% Power,Esf Actuation Occurred.Caused by Restoration of Power to Containment Purge Radiation Monitor Due to Failure to Place Monitor in Bypass.Technicians Counseled

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(iv), System Actuation
4831986001R00 - NRC Website

text

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On 1/19/86 at 2217 CST, a Control Room Ventilation Isolation (CRVI) and a Containment Purge Isolation Signal (CPIS) occurred when power was restored to Containment Purge Radiation Monitor GT-RE-33 without the monitor being in " bypass." At the time of the incident the plant was in Mode 1, Power Operation, at 100% power and normal operating temperature and pressures The Shift Supervisor had directed I&C technicians to investigate j

GT-RE-33 when its sample pump failed to start. Due to miscommunication, I

the I&C technicians went to troubleshoot the problem instead of just investigating, and in so doing, caused the CRVI and CPIS since GT-RE-33 was not in " bypass."

To prevent recurrence, the I&C technicians were reminded of the proper documentation requirements associated with troubleshootings control Room personnel are aware of the necessity to place Radiation Monitors in

" bypass" before removing power.

Since the redundant Containment Purge Radiation Monitor was operable and the event was not caused by actual radiation levels, the public health and safety was not endangered.

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, C - n7, On 1/19/86 at 2217 CST, a Control Room Ventilation Isolation (CRVI) occurred and a Containment Purge Isolation Signal (CPIS) was received.

The alarn printer (RM-ll) indicated that the radiation levels had not exceeded the setpoint of the Containment Purge Radiation Monitors.

Further investigation revealed the cause to be powering up of a Containment Purge Radiation Monitor without the monitor being in " bypass."

At the time of the incident the plant was in Mode 1, Power Operation, at 100% power and normal operating temperature and pressure.

On1/19/86atappyyximately2022 CST,ContainmentPurgeRadiation Monitor GT-RE-33 was declared inoperable because the Reactor Operators could not get GT-RE-33's sample pump started from the RM-ll or RM-23 computers. Health Physics investigated the problem but was unsuccessful at starting the sample pump at approximately 2045 CST. The Shift Supervisor directed I&C technicians to investigate GT-RE-33 to see what was wrong. The I&C technicians interpreted his direction to be a troubleshooting request and they proceeded to do what was necessary to determine the cause of the problem. The Shift Supervisor did not intend for the I&C technicians to troubleshoot the monitor because it needed to be in " bypass" to troubleshoot.

Due to miscommunication, the I6C technicians powered down the monitor to troubleshoot and then powered it back up.

In doing so, an electronic spike was initiated which ccused the CRVI and CPIS at approximately 2217 CST. After determination that the CRVI and CPIS were inadvertent, GT-RE-33 was placed in " bypass" at approximately 2225 CST. Troubleshooting was completed and GT-RE-33 was made operable at approximately 0133 CST on 1/20/86.

To prevent recurrence, I&C technicians have been reminded of the procedural requirements associated with proper documentation to guide them in troubleshooting problems such as this. The Control Room personnel are aware of the necessity to place Radiation Monitors in

" bypass" before having I&C technicians troubleshoot them.

There was no damage to plant equipment or release of radioactivity as a result of this event.

Purging of containment was not in progress at the time of this event and the redundant Containment Purge Radiation Monitor, GT-RE-22, was operable.

Based on thin and the fact that the event was not caused by actual radiation levels, the public health and safety was not endangered.

Previous occurrences

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', t.'5 LNON ELECTRIC COIMANY February 14, 1986 U. S. Nuclear Regulatory Consnission Document Control Desk Washington,'DC 20555 ULNRC-1257 l

Gentlemen:

DOCKET NUMBER 50-483 CALLAWAY PLANT UNIT 1 FACILITY OPERATING LICENSE NPF-30 LICENSEE EVENT REPORT 86-001-00 INADVERTENT ENGINEERED SAFETY FEATURES-ACTUATION The enclosed Licensee Event Report is submitted pursuant to 10 CFR 50.73(a)(2)(iv) concerning an unplanned Control Room Ventilation Isolation.

i G. L. Randol Manager, Callaway Plant M M&UIR6 MET /WRR/WRB/dra Enclosure cc:. Distribution attached 4

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- cc distribution for ULNRC-1257 Mr. James G. Keppler Regicnal Administrator Office of Inspection & Enforcement U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137 American Nuclear Insurers c/o Dottie Sherman, Library The Exchange Suite 245 270 Farmington Avenue Farmington, CT 06032 Records Center Institute of Nuclear Power Operations Suite 1500 1100 Circle 75 Parkway Atlanta, GA 30339 Mr. Nicholas A. Petrick Executive Director, SNUPPS 5 Choke Cherry Road Rockville, Maryland 20850 Mr. J. H. Smith Bechtel Power Corporation SNUPPS Project 15740 Shady Grove Road Gaithersburg, Maryland 20877-1454 NRC Resident Inspector D. F. Schnell J. F. McLaughlin J. E. Davis (Z40LER)

D. W. Capone /R. P. Wendling F. D. Field A. P. Neuhalfen A. C. Passwater/D. E. Shafer/D. J. Walker G. A. Ilughes Z40.01 (QA Record)

J. M. Price W. R. Robinson R. A. McAleenan S. L. Auston (470)(NSRB)

J. D. Schnack l

Merlin Williams, Wolf Creek GLR Chrono 3456-0021.6 3456-0260 Z40ULNRC C56.37 N. Date M. E._ Taylor