ML19332C559

LER 89-008-00:on 891016,control Room Alarms Received Indicating Fire Pump Had Started & Deluge Valve Had Opened. Caused by Actuation of Manual Pull Station.Deluge Sys Restored to Normal & Personnel interviewed.W/891115 Ltr

ML19332C559
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	11/15/1989
From:	Notaro J, Danni Smith LONG ISLAND LIGHTING CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-89-008, LER-89-8, PM-89-202, NUDOCS 8911280273
Download: ML19332C559 (6)

Text

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4,g LONG ISLAND LIGHTING COMPANY SHOREHAM NUCLEAR POWER STATION

• P.O. BOX 628

• WADING RIVER. NEW YORK 11792 TEL.15.8) 929 8300 November 15, 1989 PM 89-202 U.S. Nuc} ear Regulatory Commission Docuinent Control Desk Washington, D.C. 20556 Dear Sir In accordance with 10CFR50.73, enc]osed is Shoreham Nuclear Power Station's Licensee Event Report (LER 89-008).

Sincerely yours,

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Jack A. Notaro Plant Manager JN/RP/jp Enclosure ec: Wil31am T. Russell, Regiona) Administrator Frank Crescenzo, Senior Resident Inspector Institute of Nuclear Power Operations, Records Center American Nuclear Insurers SR.A21.U200 8911280273 891115 PDR ADOCK 05000322 S PDC

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On 10/16/89, at 0845, during normal defueled conditions, Control ,

Room. alarms were received indicating a fire pump had started and a "

deluge valve had opened. This was followed shortly by an intraplant phone report of a pipe break on elevation 8' of the Reactor Building. The operator, after inspecting the area, found no evidence.of a fire and isolated the fire header in the Reactor Building. A subsequent walkdown of the affected area determined

.that a manual pull station had been actuated. This indicated that a person or persons may.have deliberately initiated the deluge system.

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An Unusual Event (attempted sabotage / tampering) was declared.

Actions required under the declaration of an Unusual Event were performed. The NRC was notified of the situation at 1016 per 10 CFR 73, Appendix G, I f.a) (3). Security obtained a computer printout of people in the Reactor Building at the time of the incident. At 1025, the deluge system was restored to nornal and the Unusual Event was terminated. A second walkdown of the area was then performed to check for equipment damage. The seven personnel in the area at the time of the event were interviewed. Water that was found inside electrical ju:ction boxes was wiped up.

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-ELAHI AND_SYSIEM_.lDENTIFICAIlON General Electric Boiling Water Reactor l- Energy.; Industry Identification System (EIIS) codes ~are identified L 11n the text as [xx).

, IDENIIEICAI1QH OF THE EVENT

j. Unauthorized. Actuation of Deluge System  :

Event Date: 10/16/89 i t

Report Date: 11/15/89

'GGHDITIONS_.ERIQR TO THE_EYENI Reactor Defueled - All fuel assemblies stored in the Spent Fuel Pool' Mode Switch - Shutdown a RPV Pressure O psig RPV Temperature =.98 Degrees F-POWER LEVEL - 0 All rods inserted in the core ,

DESCEIPTIQH_QE THE_EYEHI On 10/16/89 at 0845, with.the plant in its normal shutdown and

-defueled condition, alarms were received in the Control Room which indicated that the electric motor-driven fire pump (1M43-P-59) had started'and a fire suppression deluge valve (1M43-02-0430) [KP] had-opened. This particular deluge valve supplies water to nossles that spray-the vertical cable trays [FA) on elevation 8' of the' Reactor Building [NG]. (Elevation 8 is where the emergency core cooling system pumps [BJ, BM, BN, BO] ace located.) Shortly after the

alarms, the Control Room received an intraplant phone report from a

. person in the Reactor Building stating that e pipe break had occurred. (This was later found to be the deluge spray water and not a pipe break). The actions required by Alarm Response Procedures for the vertical cable tray deluge valvo actuation were s

executed. An equipment operator was sent to check the area. After finding no evidence of a fire the Reactor Building fire header was isolated. A further investigation and system walkdown determined that the manual pull g,o.. u.. . .u s cro i.e.+.u us m

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S l0 0h 0F n lq Tur , . me war.nm station on elevation 8' for the vertical cable trays had been actuated. The station's handle had been pulled out, breaking a seal, and then pushed back in, which indicates that the action may not have been accidental. In accordance with Standing Order #37,

" Operational Response to Events Concerning Deliberate Acts Directed Against Plant Equipment", Security and management personnel were notified and the applicable portion of the Emergency Plan was executed. Thus, an Unusual Event-12 was declared based upon attempted sabotage / tampering. The NRC was notified per 10 CFR 73, Appendix G, I (a) (3). Seven people were in the Reactor Building at i the time of the incident as determined from the security computer.

The operators reset the manual pull station and restored the deluge system and fire header to their normal lineups. When the fire header was repressurized a gasket blew out on a fire hose station on elevation 175' of the Reactor Building. This caused additional equipment to be sprayed with water and required that 2 fire hose stations on elevation 175' be isolated. Finally, in accordance with Standing Order #37, a general field check vf equipment in the Reactor Building was conducted using SP 22.000.02, "Non Technical Specification-Equipment Readings", to determine if any equipment irregularities existed. No equipment irregularities were found.  ;

The Unusual Event was terminated at 1025.

The electrical panels and junction boxes sprayed by the deluge system were subsequently inspected for water damage by Quality Control and Maintenance personnel. Any water found was removed by hand toweling and the equipment covers were left open overnight to ,

assist in evaporating the moisture. Additionally, a review was  !

performed to determine if environmental qualification standards were maintained during this event. The equipment affected by the deluge valve-actuation is operating normally. The leaking gasket on the

-fire hose ~ station on elevation 175' was repaired and the two fire j hose stations were returned to service.

l The people in the Reactor Building at the time of the event were interviewed by Site Security and a member of the Plant Staff.

Corporate Security personnel checked the pull station for fingerprints and along with Site Security conducted a second round of interviews. All of the above information was inconclusive.

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0p 0g or 0 15 texm . wanc a asuunn CAUSE_DE_IHE_EYEHI Based upon the available evidence, i.e., investigations by plant staff and security personnel, a check for fingerprints, interviews and past experience with the fire suppression deluge system, no definite conclusion as to the cause of the activation of the manual pull station has been made. This event is not considered to be a case of sabotage. It could be an isolated incident where a person tampered with a piece of equipment without realising the consequences of his actions.

AHALYSIS_0E_IHE_EYENI 1 The actuation of the manual pull station caused the opening of the l deluge valve and spraying of fire water onto the vertical cable trays on elevation 8' in the Reactor Building and also started the electric motor-driven fire pump.

The plant had been shutdown and defueled prior to this event. There was no fire and this event had no safety consequences. Even if the plant had been operating at power the safety consequences would have- t only been minor. The fire protection system performed as designed and the operators took the appropriate corrective actions.

COBEECIIYE_ACIl0HS During a meeting with site employees, the Plant Manager discussed the seriousness and consequences of this event. He emphasized the extent that the company went in investigating this event including the involvement of security personnel, the check for fingerprints and the company's intention to prosecute people who tamper with <

plant-equipment. This is being followed up'by a memorandum from the Plant Manager to site employees which emphasises that even though the plant is shutdown, the plant still contains operable and energized equipment and serious consequences can result from persons operating or tampering with this equipment.

The problem with water accumulating in certain electrical junction boxes has been referred to the Engineering Department for further I investigation.

The cause of the blown gasket is believed to be the pressure surge resulting from repressurising the fire header. This is still being investigated and if necessary, procedure changes will be made in order to prevent this from reoccurring.

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