ML20092N635

Special Rept 84-01:on 840606,post-indicating Valve V-9-12 Branching Off 14-inch Fire Water Main Damaged by Maint Vehicle,Resulting in Loss of Fire Suppression Water Sys. Caused by Lack of Protection Against Physical Damage

ML20092N635
Person / Time
Site:	Oyster Creek
Issue date:	06/15/1984
From:	Fiedler P GENERAL PUBLIC UTILITIES CORP.
To:	Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
84-01, 84-1, NUDOCS 8407030362
Download: ML20092N635 (3)

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-OYSTER CREEK NUCLEAR GENERATING STATION ,

Forked River, New Jerrr.y 08731 Special Report 84-01 I

Report Date. ,

t June 15, 1984 Occurrence Date June 6,1984 ~ ,

Identification of Occurrence

- Fire suppression water system inoperable. This event is considered to be reportable as defined in the Technical Specifications, paragraph 3.12.B.3.

Conditions Prior to Occurrence l

' The plant is shutdown with fuel in the reactor vessel. A refueling / maintenance outage is in progress.

. Description of Occurrence

' On June 6 - 1984 at 'l:30 P.M., post indicating valve Y-9-12, branching off the .

14" fire water main was: damaged by a' maintenance vehicle resulting in a loss

- r of the fire suppression water system (main water feed to underground loop from fi re punip 1-1 and 'l-<.). Subsequently, the 14" fire water main was isolated in the area of the damaged post indicating valve (V-9-12) and the redundant fire ,

protection water supply / pump was tested for operability and aligned to the .

fire suppression header.-

' Apparent Cause of Occurrence

< The cause for loss of the fire suppression water system was attributed to extremely soft soil and a lack of protection against physical damage in the i area surrounding the post in'dicating valve in question. This condition

- rcsulted in the . soil giving way causing the maintenance vehicle to slide into and damage post indicating valve V-9-12. In order to perform maintenance on V-9-12, the 14" fire water main had to be isolated and drained, rendering fire pump :1-1 and 1-2 inoperable.

8407030362 840615 PDR ADOCK 05000219 S PDR

. -. Sp;cial Rep 3rt 84-02 Page 2 nh. i r

Corrective Action Immediate corrective action to repair post indicating valve V-9-12 and restore the fire suppression water system (14" main from fire pump 1-1 and 1-2) to  :

operable status was completed at 11:00 P.M. on June 6,1984. -

As a result of the above incident'all post indicating valves in similar areas were inspected for potential damage due to a lack of physical protection. All  !

post indicating valves were adequately protected except for the post

- indicating valve in question (V-9-12), which has been temporarily barricaded off. and will be permanently protected with guard posts. ,

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e o To: Dr. Thomas E. Murley Administrator, Region I U.S. Nuclear Regulatory Commission ,

631 Park Avenue King of Prussia, PA 19406 From: GPU Nuclear Oyster Creek Nuclear Generating Station Docket No. 50-219 Forked River, NJ 08731

Subject:

Special Report to the Commission The following is a preliminary report submitted in compliance with the Technical Specifications, paragraph 3.12.B.3. ,

Report Date: June 15, 1984 '

Notification of the event described herein was made to '

Mr. W. M. Burton of the U.S. Nuclear Regulatory Commission, Region I on June 6,1984 at 1:55 P.M. by Mr. W. V. Stewart, Operations Control Manager.

Preliminary Approval:

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KV VZ = ^121 Peter B.Mer Vice President and Director Oyster Creek:

P8F: dam cc: Director (2)

Office of Management Infonnation and i Program Control U.S. Nuclear Regulatory Commission Washington, DC 20555 NRC Resident Inspector Oyster Creek Nuclear Generating Station Forked River, NJ 08731

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