ML20246K501

Summary of Operating Reactors Events Meeting 89-25 on 890705 to Discuss Manual Reactor Trip W/Complications

ML20246K501
Person / Time
Site:	Seabrook
Issue date:	07/07/1989
From:	Haughney C Office of Nuclear Reactor Regulation
To:	Rossi C Office of Nuclear Reactor Regulation
References
OREM-89-025, OREM-89-25, NUDOCS 8907180191
Download: ML20246K501 (11)

Text

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.!'.(;71;,3 MEMORANDUM FOR: Charles E. Rossi, Director .

Divisien of Operational Events Assessment i FROM: Charles J. Haughney, Chief Events Assessment Branch Division of Operational Events Assessment

SUBJECT:

THE OPERATIllG REACTORS EVENTS MEETING J July 5, 1989 - MEETING 89-25 On July 5, 1989, an Operating Reactors Events meetinc (89 25) was held to brief senior managers from NRR, AE00, RES, Commisdon Staff, and Regional '

Offices on events which occurred since our la % meeting on June 21, 1989.

The list of attendees is included as Enclosure 1.

ine events discussed and the significant elements of these events are presented in Enclosure 2. Sunearies of reactor scrams for the weeks ending 06/25/89 and 07/02/89 are presented in Enclosure 3.- One significant event was identified for input into the NRC performance indicator program.

Charles J. Haughney, Chief Events Assessment Branch Division of Operational Events Assessment

Enclosures:

As stated cc w/ Encl.:

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1/.EMORANDUM FOR: Charles E. Rossi. Direr, tor Division of Operationr.1 Events Assessment FROM: Charles J. Haughney, Chief Events Assessment Branch Division of Operational Events Assessment i

SUBJECT:

THE OPERATING REACTORS EVENTS MEETING July 5, 1989 - MEETING 89-25 On July 5,1989, an Operating Reactors Events meeting (89-25) was held to brief senior inanagers from NRR, AEOD, RES, Commission Staff, and Regional Offices on events which occurred since our last meeting on June 21, 1989.

The list of attendees is included as Enclosure 1.

The events discussed and the significant elements of these events are ; ecented in Enclosure 2. Summaries of reactor scrams for the weeks ending 06/25/89 and 07/02/89 are presented in Enclosure 3. One significant event was identified for input into the NRC performance indicator program.

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Charles J. H. hney, Chief Events Assesstent Branch Division of Operational Events Assessment

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Enclosures:

As stated ,

cc w/Ent.1.: )

See Next Page l l

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y, CC:. .

.T. Ilurley,' NRR.~ V. lierses,'hRR

, F. Miraglia, NRR- S. Black NRR L

-J. Sniczek, NRR ~

t-E. Jordan AE00 t J. Taylor, E00'

> E. Beckjord RES-W. Russe 11', R1

5. Ebneter, RII

.B. Davis, EIll

'R. D. Martin, RIV-J.~B. Martin, RY.

W..Kane, RI L'. Reyes, RII E. Greenman, RIII L. Callan, RIV P. Zimmerman, RV S. Varga, IGR B. Boger, NRR G.'Lainas NRR-L. Shao, NRR B.. Grimes NRR

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F. Congel,.NRR.-

E. Weiss,'AE00

'T. Martin,~EDO.

J., Lieberman,.OE J. Cuttmann, SECY-A.'Thadani, NRR S. Rabin, AE0D J. Forsyth, INPO R. Barrett, NRR-M. Harper, AE00 R. Newlin, GPA l

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ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING'(89-25).

July 5, 1989 hAME ORGANIZATION NAME ORGANIZATION J. Sniezek HRR/DONRR J. Partlow NRR/ADP J. Dyer OEDO C. Morris NRR/SELB.

R. Fulsifer NRR/FD3-1 C. Della Penna NPR/DOEA P. Bobe AE00/DSP C. Ader OCM/TR W. Butler NRR/DRP J. Konklin NRR/DRIS W. Johnson RI K. Connaughton OCM/JC G. Constable RIV P. Cortland NRR/TVA R. Wessman NRR/PD1-3 C. Rossi NRR/DOEA S. Varga URR/DRP W. Minners RES/DSIR P. Baranowsky HRR/DOEA R. Kendall NRR/00EA M. Reardon NRE/DOEA

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ENCLOSURE 2 i

f CPERATil!G-REACTORS EVENTS BRIEFING 89 EVENTS ASSESMjEl1T BRANCH 1DCAT10ll: 12B-11, WHITE FLINT WEDNESDAY, JULY 5, 1989, 11:00 A.M.

SEAbROOK UNIT.I MANUAL REACTOR TRIP WITH COMPLICATIONS (AIT) i

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89-25 SEABROOK' UNIT J MANUAL REACTOR TRIP WITH COMPLICATIONS (AIT)

JUNE 22, 1989 PROBLEM A. MINOR TRANSIENT'0CCURRED WHILE CONDUCTING THE NATURAL CIRCULATION STARTUP TEST. THE REACTOR WAS MANUALLY TRIPPED FROM ABOUT 3% POWER.

EMlBE A STEAM DUMP VALVE (SDV) TO THE MAIN CONDENSER FAILED TO CLOSE ON

' DEMAND (MANUALLY FROM THE C0hTROL ROOM), RESblTING IN A PRIMARY

' SYSTEM PERTURBATION.

fif[IX_SJENIFICANCE REACTCR OPERATION OCCURRED OUTSIDE THE BOUNDARY CONDITIONS SPECIFIED IN THE TEST PROCEDURE.

DISfUSSION o ON JUNE 22, 1989, THE LICENSEE WAS PREPARING TO CONDUCT THE NATURAL CIRCULATION TEST FOR UNIT 1.

o THE PLANT WAS STABILIZED AT LOW POWER (3% PWR); CONTROLLERS WERE PLACED IN MANUAL CONTROL AS REQUIRED BY THE TEST PROCEDURE.

o INITIATION OF THE TEST REQUIRED TRIPPING OF THE REACTOR COOLANT PUMPS; THE RESULTING TRANSIENT WAS EXPECTED TO LAST APPROX ,

10 TO 50 MINUTES. -

0 SHORTLY AFTER TRIPPING THE RCPs, RCS TEMPERATURE AND PRESSURIZER i LEVEL DECREASED.

o TEMPERATURE AND LEVEL FURTHER DECREASED BECAUSE OF A FAILED OPEN SDV.

c THE TEST PROCEDURE CALLS FOR A MANUAL REACTOR TRIP IF PRESSURIZER LEVEL DECREASES TO 17%. PRESSURIZER LEVEL DECREASED BELOW 17%  ;

FOR 4 TO 5 MINUTES, BUT THE f,EACTOR WAS h0T TRIPPED.

o ThE OPERATORS SUBSECLENTLY TRIPPED THE REACTOR AFTER PRESSURIZER  ;

PRESSURE AND LEVEL HAD BEEN RESTORED AND WERE RAPIDLY INCREASING.

CONTACT: J. THOMPSON SIGEVENT: NO

REFERENCE:

10 CFR 50.72 #15933 AND PNC-I-89-48 (DATED 06/22/89) l

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-SEAER00K UNITL1- ~89-25 o .0N JUNE 23,.1989, RE61GN I ISSUED A' CAL (89-11) T0.BEVIEW THE:

. JUNE'21' EVENT AND TO DETERMINE ANY LONG TERM CORRECTIVE ACTIONS-

.TO'BE COMPLETED LEFORE RESTART.

0 ON JUNE 27,1989,. AN AIT WAS FORMED AND SENT T0-THE SITE (JUNE 28).

TO. REVIEW TliE SAFETY IMPLICATIONS AND ROOT CAUSE FOR THE- EVENT,

0 THE PLANT RESPONSE TO THE TRANSIENT WAS AS EXPECTED GIVEN THE SDV FAILURE.

o THERE APPEARS TO BE NO GENERIC IMPLICATIONS REGARDING ADEQUACY.

OF PROCEDURES OR EQUIPMENT PERFORMANCE FROM THE EVENT.

FOLLOWUP

. THE PRELIMINARY INVESTIGATION AT THE SITE BY THE AIT IS COMPLETE. A.

DETAILED ANALYSIS ON THE EVENT IS STILL ONGOING.

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hye,No. , 1 04/22/S9 T EF.F05.".AN:E I C:CATDR3 $1BNIFICANT EVENTS  : ENCLOSURE 3 GTR SIGNIF;0 ACE i FLANTNAME- ELINT ' EdNi lESCRif!!CN l IATE 1'

! DCENTE1,2,3 M107/89 UMNALYIED PLANT : CIT 13h THAT COUL!) 1.E3 ULT IN LDSS OF 0 FDTEWi AL FDR OR ACTUAL DEGRADATION L ALL AC POWER ID 5AFETY-REL4TED LDADS. DF 3AFET ERELATED EGJ!? MENT-l u

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FIR 19R SCR49 SUWFW

' NEEK ENDIN6 06/25/B9 y

1. PLANT SPECIFIC DATA e <

!!TE UNIT PDWER !!6NAL CAUSE CDMPL!- YTD YTD YTD

'DATE CAT!DNS ABDVE BELOW TDTAL 1h ;L

! $2 A EDU!Pr.ENT ND 1 0 -1 06/19/B9 MDNTICELLD.

06/19/89 SALEM 1' 45 A EDUIPMENT ND 2 l' 3 06/22/89 SEAPRDDt 'l 3M EDUIPMENT ND 0 1 1 06/25/B9 DYSTER CREEK '1 98 A EDUIPMENT WD 2' 1 3 6

9 BEACTORSCRAESCHElif NEELINDING07/02/69 1.Platt!PICIPicDatl DAf! Slf! B51fPOWIISIGIALCADSI COBPLI- ifD IfD ffD Caf10lS AB0i! EILOW 7076L 151 151 1

06/26/69C&fAWil 1 1009 IQUIPlilt 10 2 0 PilS0HIL ID 1 0 1 06/27/89SAlltLUCit 2 221 1 3 06/28/89CLitf05 1 100& 'IQDIPliff 50 2 10 2 0 2 06/29/69Wi? .2 24& PERSOMEL 50 2 1 3

. 06/29/89QD&DCl!!!S 1 94 1 IQUIPEllt m

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f.0TES

1. PLANTSPECIFICDATABASEDONINITIALREVIEW0F'50.72kEPORTS FOR THE WEEK OF INTEREST. PERIOD IS MIDNIGHT SUNDAY THROUGH aL MIDNIGHT' SUNDAY. SCRANS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN' ROD MOTION, AND EXCLUDE PLANNED '

TEDTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN /CCORDANCE

.WITH A PLANT PROCEDURE. THERE ARE-111' REACTORS HOLDING AN-OPERATING LICENSE..

2.- COMPLICATIONS: RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAUSE OF SCRAM.

3. PERSONNEL.RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL I DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.

4 .~ "0THER" 1NCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.

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