ML20024C312

LER 83-069/03L-0:on 830523,during Attempt to Reenergize Div II Motor Operated Valves,Shutdown Cooling Mode of RHR Sys & Reactor Water Cleanup Sys Isolated.Caused by Failure to Install Power Fuses.Fuses installed.W/830622 Ltr

ML20024C312
Person / Time
Site:	Grand Gulf
Issue date:	06/22/1983
From:	Mcgaughy J, Rohrer M MISSISSIPPI POWER & LIGHT CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
AECM-83-0360, AECM-83-360, LER-83-069-03L, LER-83-69-3L, NUDOCS 8307120509
Download: ML20024C312 (3)

Text

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REPORT oATE 80 EVENT DESCRIPTION ANOPPOSAaLE CONSEQUGNCES h o lDD_May 23. 1983. the shutdown cooline mode of the RHR system and the j o IRWCU system isolated when an attempt was made to reenergize the Divisionf n 4 [II MOVs of these systems (valves were blocked open during Div II i o s toutage). T.S.3.4.9.2 requires two loops of shutdown cooling be 1 o a loo er abl e. therefore, this is beina reported pursuant to Technical J o 7 lSDecification 6.9.1.13.b. The event had no affect on the health and I o e Isafety of the public and did not constitute a threat to plant safety. l so 7 eo

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44 47 CAUSE 9ESCRIPTION ANDCORRECTIVE ACTIOrJS h i o iAt this time, it is believed the cause was due to power fuses to the l i i lisolation logic being omitted following completion of a design change 1

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Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission Region II 101 Marietta St. , N.W. , Suite 2900 Atlanta, Georgia 30303 Attention: Mr. J. P. O'Reilly, Regional Administrator

SUBJECT:

Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-13 File 0260/L-835.0 Shutdown Cooling Mode of the RHR System and the RWCU System Inoperable LER 83-069/03 L-0 AECM-83/0360 On May 23, 1983, the shutdown cooling mode of the RHR system and the RWCU system isolated when an attempt was made to reenergize the Division II motor operated valves for these systems. These valves had been blocked open while deenergized during a planned Division II electrical outage. Technical Specification 3.4.9.2 requires two loops of shutdown cooling be operable, therefore, this is being reported pursuant to Technical Specification 6.9.1.13.b. Attached is LER 83-069/03 L-0 with Supplementary Information.

Yours truly,

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cc: Mr. J. B. Richard (w/a)

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

Mr. T. B. Conner (w/o)

Mr. G. B. Taylor (w/o)

Mr. Richard C. DeYoung, Director (w/a)

Office of Inspection & Enforcement U. S. Nuclear Regulatory Cor: mission Washington, D. C. 20555 Document Control Desk (w/a)

U. S. Nuclear Regulatory Commission Washington, D. C. 20555 FICIAL COP" Member Middle South Utilities System

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'e AECM-83/0360 Page 2 of 2 t SUPPLEMENTARY INFORMATION TO LER 83-069/03 L-0 Mississippi Power & Light Company Grand.Culf Nuclear Station - Unit 1 Docket No. 50-416

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Technical Specification Involved: 3.4 9.2 Reported Under Technical Specification: 6.9.1.13.b Event Narrative:

On May 23, 1983, while attempting to reenergire some RWCU system and RHR shutdown. cooling MOVs following a planned Division II electrical outage the valves isolated (during the outage the valves were blocked open per a temporary directive for the Division II electrical outage). The valves isolated as a result of an isolation signal from the MOV's isolation logic.

The isolation logic relays deenergize to produce an isolation signal. At this time, it'is believed this signal was present due to power fuses not being installed after completion of hardware changes brought about by an approved design change package. Since the fuses were not in place, this removed voltage from the isolation logic relays and placed the logic in the actuated state. The and result of this event was that both shutdown cooling loops and the RWCU system were-isolated, therefore, decay heat removal / coolant circulation capability was lost for a very short time (less than one (1) hour).

Immediate actions were to manually override the closed valve. signal and place both systems back in operation. Power fuses were installed and-normal system operation was attained. Investigation is continuing to determine exact cause and further corrective actions. This is an interim report. An update report is expected to be submitted by July 30, 1983.

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