PNO-II-86-045, on 860627,four PORVs Opened,Dropping Primary Sys Pressure from 2,235 Psi to 702 Psi & Temp from 550 F to 450 F in 6 Minutes.Cause Under Investigation.Valves Closed & Safety Injection Initiated: Difference between revisions

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{{Adams
#REDIRECT [[PNO-II-86-045B, on 860628-0701,augmented Insp Team Sent to Plant.Corrective Action Documented in 860630 Confirmatory Action Ltr Being Monitored by NRC Resident Inspectors.Plant at 6% Power]]
| number = ML20212A253
| issue date = 06/27/1986
| title = PNO-II-86-045:on 860627,four PORVs Opened,Dropping Primary Sys Pressure from 2,235 Psi to 702 Psi & Temp from 550 F to 450 F in 6 Minutes.Cause Under Investigation.Valves Closed & Safety Injection Initiated
| author name = Burger C, Sinkule M
| author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
| addressee name =
| addressee affiliation =
| docket = 05000414
| license number =
| contact person =
| document report number = PNO-II-86-045, PNO-II-86-45, NUDOCS 8607280147
| document type = PRELIMINARY NOTIFICATION OF EVENT OR OCCURRENCE (PNO,, TEXT-INSPECTION & AUDIT & I&E CIRCULARS
| page count = 1
}}
{{#Wiki_filter:June 27, 1986 PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE PNO-II-86-45 This preliminary notification constitutes EARLY notice of events of POSSIBLE safety or public interest significance. The information is as initially received without verifi-cation or evaluation, and is basically all that is known by the Region II staff on this date.
FACILITY: Duke Power Company                          Licensee Emergency Classification:
Catawba Unit 2                              X Notification of Unusual Event Docket No. 50-414                              Alert Rock Hill, South Carolina                      Site Area Emergency General Emergency Not Applicable
 
==SUBJECT:==
UNEXPECTED REACTOR DEPRESSURIZATION AND C00LDOWN During performance of a scheduled Loss of Control Room Test the four steam system Pressure Operated Relief Valves (PORV) opened at 9:40 a.m., and primary system pressure dropped from 2235 psi to 702 psi and primary sytem temperature dropped from 550 F to 450 F in approximately six minutes. The transient was initiated shortly after the reactor was manually tripped from 25 percent power and control was switched to the auxiliary shutdown panel as prescribed by the test. The event was terminated in approximately 13 minutes when control was transferred back to the control room and the PORVs were closed and safety injected was initiated. The reactor is in mode 3.
The licensee is investigating the cause of the event.        Resident inspectors were on site witnessing the Test. An Augmented Inspection Team has been dispatched to the site from the            ,
Regional Office to investigate the event. The licensee management has agreed not to                  l restart the reactor without NRC concurrence.
The State of South Carolina has been notified. The licensee has informed the press through            l their regularly scheduled Weekly Generation Report.
l This information is current as of 1:00 p.m. (EDT) on June 27.                                        !
 
==Contact:==
C. Burger, 242-4198                              M. Sinkule, 242-5506 4
DISTRIBUTION:
H. Street T2I        MNBB ypPhillips p.g fE/W  g 25 Willste prt MAIL:
Chairman Palladino EDO        NRR          IE-      NMSS        ADM:DMB Comm. Roberts        PA                    OIA      RES        DOT: Trans Only Comm. Asselstine      MPA                  AEOD                  Applicable State Comm. Bernthal        ELO Comm. Zech            Air Rights            INP0 1 0 "
SECY                        SP              NSAC ACRS                                                    y      g l, R                        Regions:  _T    72E Licensee: A'/ O                                                          l (Reactor Licensees)                                                      !
Applicable Resident Site $ 3 7g 8607200147 e60627 PDR                                                        pAA C.
        %.th6-045                                                                                    1 L C 3 R o/i
                                                                                              . .. --}}
 
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