View source for PNO-III-86-154, on 861222,reactor Tripped from 15% Power During Testing of Integrated Control Sys.Caused by Decrease in Steam Generator Water Level Due to Feedwater Sys Control Valve Closure.Licensee Investigating Cause of Valve Closure

{{Adams
| number = ML20212F858
| issue date = 12/23/1986
| title = PNO-III-86-154:on 861222,reactor Tripped from 15% Power During Testing of Integrated Control Sys.Caused by Decrease in Steam Generator Water Level Due to Feedwater Sys Control Valve Closure.Licensee Investigating Cause of Valve Closure
| author name = Defayette R, Guldemond W
| author affiliation = NRC OFFICE OF INSPECTION &amp; ENFORCEMENT (IE REGION III)
| addressee name = 
| addressee affiliation = 
| docket = 05000346
| license number = 
| contact person = 
| document report number = PNO-III-86-154, NUDOCS 8701120194
| document type = PRELIMINARY NOTIFICATION OF EVENT OR OCCURRENCE (PNO,, TEXT-INSPECTION &amp; AUDIT &amp; I&amp;E CIRCULARS
| page count = 1
}}
{{#Wiki_filter:: PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE--PNO-III-86-154 Date December 23, 1986 This preliminary notification constitutes EARLY notice of events of POSSIBLE safety or public interest significance. The information is as initially received without ~           hyh v;rification or evaluation, and is basically all that is known by the Region III staff on this date.
Facility: Toledo Edison Company                    Licensee Emergency Classification:
Davis-Besse Nuclear Plant                  Notification 'of an Unusual Event Oak Harbor, OH 43449                       Alert Site Area Emergency Docket No. 50-346 X  GeneralEmergencyh Not Applicable

==Subject:==
REACTOR TRIP At 10:15 p.m. (EST), on December 22, 1986, the reactor tripped from 15 percent power during testing of the Integrated Control System. The startup feedwater system control valve closed during a test that was intended to demonstrate that the startup feedwater system would control steam generator level. Steam generator water level decreased, causing the reactor trip.
An NRC inspector was in the control room during the incident and determined that all safety systems functioned as expected. Operator response was good.
The licensee is investigating the cause of the control valve closure. Once the cause is identified and corrected, the licensee plans to take the plant to a level not exceed 40 percent power and stabilize the plant at that point through the Christmas holiday. The augmented inspection team is on site and monitoring the licensee's evaluation of the reactor trip.
The State of Ohio will be notified.
R:gion III (Chicago) was notified of the reactor trip about 11:15 p.m. (EST), December 22, 1986, by the Headquarters Duty Officer. This information is current as of 10 a.m. (EST),
December 23, 1986.
fh y CONTACT: R.DeFayetke f&k./hwn                  ~
W. G. Guldemond FTS 388-576/              FTS 388-5574 1  DTSTRIBUTION:
l  H. St.                      EDO       NRR        E/W        Willste       Mail:  ADM:DMB l  Chairman Zech               PA                   IE          NMSS                00T:Trans only l  Com. Roberts                ELD                  OIA         RES Com. Asselstine                                  AE00                     NRC Ops Ctr   / /,' k ?
Conn. Bernthal Com. Carr                   SP M 27 7 Regional Offices ACRS SECY CA INP0 )[,*/).
RIII Edsident OffLct NSAC //,/4                                   M3h PDR                         Licensee:     ///.L3 ,(Corp. Office - Reactor Lic. Only) 3 87011ho194861223                                                  Region III ggggbe6-154PDR                                                   Rev. November 1986}}

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