View source for PNO-IV-89-028, on 890418,reactor Trip Due to Main Turbine Trip Occurred.Cause Unknown.Pump Reset & Restarted & Both Turbine Driven & Motor Driven Emergency Feedwater Pumps Operated to Maintain Steam Generator Water Level

{{Adams
| number = ML20245C578
| issue date = 04/18/1989
| title = PNO-IV-89-028:on 890418,reactor Trip Due to Main Turbine Trip Occurred.Cause Unknown.Pump Reset & Restarted & Both Turbine Driven & Motor Driven Emergency Feedwater Pumps Operated to Maintain Steam Generator Water Level
| author name = Howell A
| author affiliation = NRC OFFICE OF INSPECTION &amp; ENFORCEMENT (IE REGION IV)
| addressee name = 
| addressee affiliation = 
| docket = 05000368
| license number = 
| contact person = 
| document report number = PNO-IV-89-028, PNO-IV-89-28, NUDOCS 8904270252
| document type = PRELIMINARY NOTIFICATION OF EVENT OR OCCURRENCE (PNO,, TEXT-INSPECTION &amp; AUDIT &amp; I&amp;E CIRCULARS
| page count = 2
}}
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April 18, 1989 jg
        - PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE -- PN0-IV-89-28                                                                      )
This preliminary notification constitutes EARLY notice of events of POSSIBLE safety or public interest significance. The-information is as initially received                                                             1 without verification or evaluation, and is basically all that is known by the Region IV staff on this date.
FACILITY: Arkansas Power & Light Company            Licensee Emergency Classification:
Arkansas Nuclear One, Unit 2                                                Notification of Unusual Event Docket No.: 50-368                                                          Alert Site Area Emergency General Emergency X                              Not Applicable

==SUBJECT:==
SHUTDOWN GREATER THAN 48 HOURS At approximately 9:41 a.m. (CDT), Arkansas Nuclear One (ANO), Unit 2, tripped from 100 percent reactor power because of a trip of the main turbine. The
          'orbine trip was caused by the automatic tripping of the electrohydraulic wntrol system (EHC) trip valve. Although the cause of the tripping of the EHC trip valve is not known, the licensee suspects that it was tripped on high turbine hood temperature. High hood temperature is suspected to have been caused by steam f rom a leak in a high energy steam extraction line. This steam leak occurred from an approximately 180 degree " fishmouth" pipe wall rupture (approximately 3-4 inches wide) below the weld that joins a 14-inch diameter steam extraction line to the high pressure turbine. The steam extraction line rupture was apparently caused by erosion of the pipe wall. Some piping insulation was blown off the pipe as a result of the leak and steam was observed in the overhead of the turbine building. Apparently, no personnel were injured or any other equipment was damaged.
No automatic actuation of the engineered safety features (ESF) equipment occurred; however, as part of the initial operator response, main feedwater supply was isolated to the steam generators (SGs) because it was not known whether the type of leak was steam or feedwater. After isolating main feedwater, the licensee manually started the emergency feedwater (EFW) pumps to maintain SG water level. The turbine driven EFW pump (2P7A), however, tripped on overspeed following manual start. The cause of the overspeed is not known. The pump was reset and restarted and both the turbine driven and motor driven EFW pumps were operated to maintain SG water level.
No other complications were noted following the reactor trip. Currently, the plant is in Mode 3 (hot standby) and the plant is being cooled down to cold shutdown by use of the atmospheric dump valves (ADVs). The NRC resident inspector and two Region IV based inspectors, who were already onsite, are monitoring licensee actions. A Region-based specialist is being dispatched to the site to investigate the steam pipe rupture. The region will assess additional NRC response as deemed appropriate.
The licensee is issuing a statement about the Unit 2 shutdown.                                                           Region IV is prepared to respond to redia inquiries.
The s ate of Arkansas hps been informed.
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PNO-IV-89-28 g
    -     Region IV' received notification of this occurrence by telephone from the                                                            l resident ~ inspector at 10:45 a.m. on April 18, 1989.- Region IV has informed NRR and the office of the EDO.
This information has been confirmed with a licensee representative.
        ' CONTACT:                                                  A. Howell, 728-8180
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Comm. Roberts CA-                                                         NRR        ARM Comm. Carr                                                     OGC-       OIA        OGC        FAX:     (5520:-       89 @ I    '
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Conn. Rogers - GPA                                                        01                    TNF0             egions & HQ)        l Comm. Curtiss PA                                                          SLITP      H-St       PDR ACRS                                                           ED0        OE.       W           NSAC EW-W       RRI 75 IIP      NRC Ops Ctr Licensee (Reactor)
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NRCRM, AE0D                                                          AE0D (Patty Wilson NRCRM, BROWN                                                         ARM (Karen Brown) )
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NRCRMP, OIDW                                                         Investigations (Displaywriter/PC)
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INRC0304, NMSSPN                                                     Nuclear Material Safety & Safeguards Pat Graaf)
INRC0506, NMSSPN                                                     Nuclear Material' Safety & Safeguards CathyJenkins)
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