PNO-I-93-006, on 930125,licensee Notified NRC That Reactor Vessel Core Temp Exceeded 212 Degrees F During Shutdown Cooling Operations.No Core Damage or Radioactive Release Occurred.Inspectors Reviewing Event.State of Nj Notified

PNO-I-93-006:on 930125,licensee Notified NRC That Reactor Vessel Core Temp Exceeded 212 Degrees F During Shutdown Cooling Operations.No Core Damage or Radioactive Release Occurred.Inspectors Reviewing Event.State of Nj Notified

ML20127N953
Person / Time
Site:	Oyster Creek
Issue date:	01/26/1993
From:	Blough R, Rogge J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
References
PNO-I-93-006, PNO-I-93-6, NUDOCS 9302010132
Download: ML20127N953 (2)

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'i> DCS No: 50219930125'

- Date: January 26,1993 PRiil#HMAIO' NOTE [CM!ON OF EVENT OR UNUSUAL OCCURRENCE PN1-9306 This preliminary notiGeation constitutes EARLY' notice of events of POSSIBLE safety or public interest

significance. The infonnation is as initially received without verincation or evaluation, and is basically -

all that is known by the Region I staff on this date.

Fscility: Licensee Emergency Classification:

- GPU Nuclear Corp. Notification of Unusual Event Oyster Creek 1 _ Alen Forked River, New Jersey Site Area Emergency General Emergency X Not Applicable Docket No. 50 219 License No.' DPR 16 Event No. 24943 Event Location Code: POW

Subject:

AUGhiENTED INSPECTION TEAM DISPATCIIED TO OYSTER CREEK NRC Region I is dispatching an Augmented Inspection Team to review an event involving degmded shutdown cooling at Oyster Creek. The AIT will include representatives from Region I, NRR, and AEOD.

On January 25,1993, at approximately 10:07 p.m., the licensee notified the NRC IIcadquarters Operations Officer that the reactor vessel core temperature had exceeded 212 degrees F during shutdown cooling operations. -The licensee had been conducting inboard Main' Steam Isolation Valve (MSIV) leak rate testing, for which they had implemented a modified shutdown cooling (SDC) lineup. In the modiGed configuration, enough of the SDC 00w bypassed the core to cause temperature stratification in-the mactor vessel. At approximately 4:30 p.m. on January 25, the licensee observed that the thermcouple for the reactor vessel head temperature indicated greater than 212 degrees F, the Teclinical SpeciGcation limit for their plant conditions. Realizing they had stratification, the licensee placed three SDC pumps in service, increasing SDC flow to the reactor vessel core and also increased reactor vessel water level to between 190" and 200" This promptly restored nonnal cooling. _The licensee also?

reestablished primary containment, The reactor vessel pressure during this time was approximately 35 psig (pressurized init.iallyjvith air for the MSIV testing). The licensee calculated that reactor vessel core temperature may have reached 280 degrees F. No core damage or radioactive release occurred.

The resident inspecior was informed of the event on the evening of January 25. Two resident and two specialist inspectors are reviewing the event onsite until the AIT arrives.

The State of New Jersey was notified of the AIT; a representative of the State will observe the

-inspection. Region I Public Affairs is prepared to respond to media inquiries. This' notification is-current as of 2:00 p.m. on January 26,1993.

~ CONTACT: John Rogge Randy Blough g g-(215) 337-5146 (215) 337-5219 9302010132 930126 PDR I&E ~

PNO-I-93-OO6 PDR ..

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b DCS No: . 50219930125 ,

Date: January 26,1993 PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE PN1-9306 -

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- DISTRIBUTION:

OWFN- MNBB - Idt. EL Mail: ADM:DMB Chairman Selin AEOD** PDR' RES DOT:Tmns only**

- Comm. Rogers IRM Conun. Cuniss OIG *

• NRC Ops Ctr** -

Connu. Remick .

INPO * * <3> ; -

Conun. de Planque OCAA. NSAC'* 3, * ,l $ /",w i OIP Phillips OCA EDO ACRS *

• OGC NMSS OPA NRR** (Phone Verif: A, Byrdsong 964-1168 or 9641166)

OE OSP Regional Offices RI Resident. Office ),' ') O ,/<w i tww OIG Licensee:

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.) g'4 (Reactor Licensees)

'* Ocneral Int for tendmg PN4 by FAX Region 1 Form 83 (Rev. November 1992) k k-s'

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