PNO-I-88-034, on 880323,outlet Flow Control Valve for Common Fuel Pool Cooling Filter/Demineralizer Failed Open Causing Excessive Flow & High Differential Pressure.Reactor Currently Defueled.Commonwealth of PA Informed

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PNO-I-88-034:on 880323,outlet Flow Control Valve for Common Fuel Pool Cooling Filter/Demineralizer Failed Open Causing Excessive Flow & High Differential Pressure.Reactor Currently Defueled.Commonwealth of PA Informed
ML17156A465
Person / Time
Site: Susquehanna 
Issue date: 03/24/1988
From: Blough R, Young F
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
References
PNO-I-88-034, PNO-I-88-34, NUDOCS 8803290216
Download: ML17156A465 (3)


ACCELERATED UTION DEMONS+4"N SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:8803290216 DOC.DATE: 88/03/24 NOTARIZED: NO DOCKET g

FACIL:50-388 Susquehanna Steam Electric Station, Unit 2, Pennsylva 05000388 AUTH.NAME AUTHOR AFFILIATXON YOUNG,F.

Region 1, Ofc of the Director BLOUGH,R.

Region 1, Ofc of the Director RECIP.NAME RECIPIENT AFFILIATION R

g I

DXSTRIBUTION CODE:

ZE34D COPIES RECEIVED:LTR (9 ENCL SIZE:

TXTLE: Preliminary Notification-Occurrence/Non-Routine Event/Sa

SUBJECT:

PNO-I-88-034:on 880323,increased radiation levels in reactor bldg.

NOTES:LPDR 2 cys Transcripts.

05000388 8

RECXPIENT ID CODE/NAME INTERNAL: AEOD/DSP/TPAB NRR/DOEA/EAB11E NRR/DRIS/SIB9D4 OE LIEBERMAN,J RES BROOKS,B RES FILE RES/DE/EX B RES/DRAA RES/PMPDAS EXTERNAL: DOE BARBER EV34 NRC PDR NOTES:

COPXES LTTR ENCL 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 2

2 RECIPIENT ID CODE/NAME NRC OP CNTR NRR/DRIS/SGB9A1 NRRQ&3fh ILRB12 G-02 S

DEPY RES/DE RES/DRA RES/DRPS RGN1 FILE 01 LPDR NSIC COPIES LTTR ENCL 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 2

2 1

1 R

I S

'A TOTAL NUMBER OF COPIES REQUIRED:

LTTR

/i ENCL 25

DCS No: ~38~323 Date:

~rch~,

1988 PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE--PNO-I-88-34 This preliminary notification constitutes EARLY notice of events of POSSIBLE safety or public interest significance.

The information is as initially received without verification or evaluation, and is basically all that is known by the Region I staff on this date.

Facility:

Pennsylvania Power

& Light Co.

Susquehanna Unit 2 Berwick, Pa.

D/N 50-388 Licensee Emergency Classification:

Notification of Unusual Event Alert Site Area Emergency General Emergency X

Not Applicable

Subject:

INCREASED RADIATION LEVELS IN REACTOR BUILDING At 9:25 p.m.

on March 23 while shutting down the Unit 2 fuel pool cooling system, the outlet flow control valve for the common fuel pool cooling filter/demineralizer failed open causing excessive flow and high differential pressure across the demineralizer.

As a result, some resin fines and crud were flushed into the spent fuel pool letdown line directing water to the Condensate Storage Tank (CST).

Increased radiation levels throughout the reactor building along the letdown line path and hot spots in low flow points were detected.

Contact readings along the pipeline ranged from 5R/hr to 45R/hr with general area levels increasing to between 20 mr/hr and 130 mr/hr.

Leakage through the return valve to the CST had caused radiation levels to fluctuate during the afternoon of 3/24 until further isolation was achieved.

The licensee has stopped work in the reactor building and removed workers until a solution can be implemented.

Levels at the CST inlet are 200 mr/hr on contact and 50 mr/hr at 18 inches.

No overexposures or releases have occurred as a result of this event.

The licensee has staffed their Technical Support Center in order to assemble the necessary technical resources to resolve issues.

The reactor is currently defueled while the plant is in its second refueling outage.

Unit 1 is operating at 50K power and continuing with the plant startup.

The Commonwealth of Pennsylvania was informed.

This Preliminary Notification was issued for information only and no further action by the NRC is anticipated.

The resident -inspectors are following up on this event and Region I is sending additional inspectors to the site.

CONTACT:

F.

Young '-",,"

8-717-542.-2134 R. Blough 346"5146'803290216 880324 PDR I~cE PNO-1-88-034 DCD

DISTRIBUTION:

H. St.

Cj Chairman Zech Comm.

Roberts Comm. Bernthal Comm. Carr Comm.

Rogers ACRS SECY CA PDR OGC-H GPA Region I Form 83 (Rev.

March 1988)

PA OGC AE00 ARM 0

wF NMSS NRR OIA OI SLITP Regional Offices NL RES.

Ma A

MB DOT:Trans only NRC Ops Ctr INPO--

NSAC-"

TMI Resident Section RI Resident Office Licensee:

Reactor Licensees)