View source for PNO-V-87-042, on 870604,reactor Trip Occurred Due to Low Steam Generator Level.Caused by Malfunction in Automatic Feedwater Control Sys During Sys Troubleshooting/Testing. Investigation Into Cause of Malfunction Ongoing

{{Adams
| number = ML20214W709
| issue date = 06/04/1987
| title = PNO-V-87-042:on 870604,reactor Trip Occurred Due to Low Steam Generator Level.Caused by Malfunction in Automatic Feedwater Control Sys During Sys Troubleshooting/Testing. Investigation Into Cause of Malfunction Ongoing
| author name = Richards S, Zimmerman R
| author affiliation = NRC OFFICE OF INSPECTION &amp; ENFORCEMENT (IE REGION V)
| addressee name = 
| addressee affiliation = 
| docket = 05000529
| license number = 
| contact person = 
| document report number = PNO-V-87-042, PNO-V-87-42, NUDOCS 8706160143
| document type = PRELIMINARY NOTIFICATION OF EVENT OR OCCURRENCE (PNO,, TEXT-INSPECTION &amp; AUDIT &amp; I&amp;E CIRCULARS
| page count = 1
}}
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1 PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE--PNO-V-87-42                        Date: 06/04/87 This preliminary notification constitutes EARLY notice of POSSIBLE safety or public interest i  significance. The information presented is as initially received without verification or i   evaluation and is basically all that is known by Region V staff on this date.
]   FACILITY: Arizona Nuclear Power Project                 Emergancy Classified Palo Verde Unit 2                               X Notification of Unusual Event
,              Docket No. 50-529                            ~- ~X1ert Site Area Emergency General Emergency Not Applicable

==SUBJECT:==
REACTOR TRIP AND SAFETY INJECTION ACTUATION - UNIT 2.                                                        ;
On June 4,1987, at 12:59PM (MST), Unit 2 reactor tripped from 100% power as a result of low
 ,  steam generator level. The low steam generator level was caused by a malfunction in the automatic feedwater control system during system troubleshooting / testing. A subsequent overcooling (42 drop) of the reactor coolant system (RCS) resulted in low pressurizer pressure causing a safety injection and containment isolation actuation. The RCS pressure; i  however, did not fall below the shut off head of the high pressure safety injection pumps, i therefore no injection into the RCS occurred. The licensee declared an Unusual Event at A:05 PM (MST), and secured from the event at 1:11PM. All safety related equipment appeared
]   to function as designed following the reactor trip. The licensee's investigation into the i   cause of the feedwater control malfunction is ongoing. The resident inspectors are                                    2 j   following the licensee's action. The unit is currently in Mode 3.
 !  The licensee has notified local media, i
This information is current as of 3:15 PM (MST) June 4,1987.
CONTACT:   S. Richards                                                              R. Zimmerman FTS 463-3853                                                             (602)386-5260 4
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:   Comm. Roberts        PA                         OIA       RES                             D0T:Trans Only i   Comm. Asselstine     MPA                        AE00 i   Comm. Bernthal       ELD l   Comm. Carr           Regions:
SECY                          - TNP0_.//oy NSAC 2l67 ACRS                             Licensee:
CA                               (ReactorI.icensees)                       REGION V: FORM 211
,   PDR                              Resident Inspector # F [                   (Revised 3/14/83) l l195^ OMdma cas agN 2:oy j
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