ML20128C748

Summary of Operating Reactors Events Meeting 93-03 on 930127.List of Attendees & Elements Discussed Encl

ML20128C748
Person / Time
Site:	Summer, Seabrook
Issue date:	01/28/1993
From:	Chaffee A Office of Nuclear Reactor Regulation
To:	Grimes B Office of Nuclear Reactor Regulation
References
OREM-93-003, OREM-93-3, NUDOCS 9302040110
Download: ML20128C748 (16)

Text

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• JAN2bbe MEMORANDUM FOR: Brian K. Grimes, Director Division of Operating Reactor Support FROM: Alfrecl E. Chaffee, Chief Events Assessment Branch Division of Operating Reactor Support

SUBJECT:

OPERATING REACTORS EVENTS BRIEFING JANUARY 27, 1993 - BRIEFING 93-03 On January 27, 1993, we conducted an Operating Reactors Events Briefing (93-03) to inform senior managers from offices of the Commiscion, OE, EDO, ACRS, RES, AEOD, NRR, and regional offices of selected events that occurred since our last briefing on January 13, 1992. Attachment 1 lists the attendees.

Attachment 2 presents the significant elements of the discussed events.

Attachment 3 contains reactor scram statistics for the weeks ending January 17 and January 24, 1993. Two significant events were identified for input into the NRC performance indicator program (Attachment 4).

original signed by Edward F. Goodwin for Alfred E. Chaffee, Chief Events Assessment Branch Division of Operating Reactor Support

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Attachments: As stated p_ISTRIBUTION:

'CentraliF11est cc w/ attachments: PDR See next page EAB R/F KGray EBenner Corsini LKilgore, SECY b/D EA /QORS EAB/ DORS EAB/ DORS KGray RDennig EGoodwin AChaffee ( ,)

01/43/93 I /,2 ? / 93 / g/93 / g/93 -

i OFFICIAL RECORD COPY ~

DCCUMENT NAME: CRTRANS.KAC (G:KAG) _ __ ,

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9302040110 930120~ '7 p'V ~c"

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'T. Murley, NRR (12G18) A. De Agazio,'(PDI-4)1 F._Miraglia, NRR (12G18). J. Stolz,-(PDI-4)-

F. Gillet. pie, NRR (12G18) (. Wunder,_(PDII-1)

J.-Partlow, NRR (12G18) E. lAdensam, c (PDII-1) -

S. Varga, NRR ,-(14 E4 )

J. Calvo, NRR (14A4)

G. Lainas, NRR (14H3) '

J. Roe, NRR (13E4)

J. Zwolinski, NRR (13H24)-

M. Virgilio,-NRR (13E4)

W. Russell, NRR (12G18)

J. Ricterdson, NRR (7D26)

A. Thadani, NRR (8E2)

S. Rosenberg, NRR (10E4)

C. Rossi, NRR (9A2)

B. Boger, NRR (10H3)

F. Congel, NRR (10E2)

D._Crutchfield, NRR (11H21)

W. Travers, NRR (11B19)~

D. Coe, ACRS.(P-315) -

E. Jordan, AEOD (MN-3701)

T. Novak, AEOD (MN-9112)

L. Spessard, AEOD-(MN-3701)

K. nrockman, AEOD (MN-3206)

S. Rubin, AEOD (MN-5219)

M. Harper,-AEOD (MN-9112)

J. Grant, EDO (17G21)

R. Newlin, GPA (2GS)

E. Beckjord, RES (NLS-007)

A. Bates, SECY (16G15)

G._Rammling, OCM (16G15)

T. Martin, Region I W. Kane, Region I C. Hehl, Region I S. Ebneter, Region II E. Merschoff, Region II B.-Davis,-Region.III E. Greenman, Region _III J. Milhoan, Region-IV B. Beach, Region IV '

J.B. Martin, Region V-K. Perkins, Region _V bec: Mr. Sam-Newton, Manager Events. Analysis _ Department Institute of_ Nuclear Power Operations 1100 - Circle 75 Parkway,-_. Suite 1500 Atlanta, GA 30339-3064

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ATTACRMENT 1

~ LIST OF ATTENDEES OPERATING REACTORS EVENTS FULL BRIEF::NG (93-03) 4 JANUARY 27, 1993 NAME OFFICE UM1E OFFICE

- B. .' GRIMES NRR M. CARUSO- NRR E. GOODWIN NRR R. GALLO NRR-E. BENNER NRR C. ROSSI .NRR K. GRAY NRR G. LAINAS NRR C. ORSINI NRR S. VARGA NRR Ce BEARDSLEE NRR J. CALVO -NRR-R. DENNIG NRR R.. JONES NRR.

G. WLEDER NRR J. MITCHELL .OEDO A. DE AGAZIO NRR T. SHEDLOSKY OCM/ISl T. ALFXION NRR D. SPAULDING OE D. FISCHER NRR W. TROSKOSKI OE S. ROSENBERG NRR L. PLISCO 'OEDO T. LE NRR D. COE ~ACRS.

S. LONG NRR W. HINNERS RES M. DAVIS . NRR V, DENAROYA AEOD E. ADENSAM NRR ,

4 TELEPHONE ATTENDANCE (AT ROLL CALL)

Recions Resident-Insocctors i

Region I Seabrook Region.-II -

Summer Region III

' Region V AIT Team Leaders . Mi s c .-

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ATTACHMENT 2 l

i OPERATING REACTORS EVENTS BRIEFING 93-03 LOCATION: 10 Bil, WilfTE FLINT WEDNESDAY, JANUARY 27, 1993, 11:00 A.M.

p SEABROOK, UNIT 1 POTENTIAL-TO AIR BIND RESIDUAL ~ HEAT REMOVAL AND CONTAINMENT BUILDING SPRAY l PUMPS-l SIMMER REACTOR TRIP-AND LOSS OF.

BALANCE OF PLANT- (BOP)

POWER l-PRESENTED BY: EVENTS ASSESSMENT BRANCH DIVISION OF OPERATING REACTOR SUPPORT, NRR-

• 93-03 SEABROOK, UNIT 1 POTENTIAL TO AIR BIND RESIDUAL HEAT REMOVAL AND CONTAINHENT BUILDING SPRAY PUMPS JANUARY 7, 1993 EILQB1EM INITIATION OF A SAFETY INJECTION (SI) SIGNAL DURING A REFUELING WATER STORAGE TANK (RWST) LEVEL TRANSMITTER TEST COULD AIR BIND THE RESIDUAL HEAT REMOVAL (RHR) AND CONTAINMENT BUILDING SPRAY (CBS) PUMPS.

.CAUlE PERFORMANCE 9F A RWST LEVEL TRANSMITTER TEST CREATES A FALSE LOW LEVEL SIGNAL. IN CONJUNCTION WITH AH SI SIGNAL, THIS REALIGHS RHR AND CBS SUCTIONS TO THE CONTAINMENT SUMP.

SAEETY SIGNIFICANCE AIR BINDING OF THE RHR AND CBS PUMPS WOULD PREVENT MITIGATION OF A LARGE BREAK LOCA.

DISCUSSION o DURING PERFORMANCE OF RWST LEVEL CALIBRATION, A SECOND LEVEL TRANSMITTER IS PLACED IN TEST TO VERIFY OPERATION OF THE SOLID STATE PROTECTION SYSTEM (SSPS) INPUT RELAYS BY SATISFYING THE 2 0F 4 COINCIDENCE LOGIC.

• PROCEDURE IS NORMALLY PERFORMED EVERY 18 MONTHS, BUT THERE IS N0 MODE RESTRICTION ON WHEN THE PROCEDURE MAY BE PERFORMED.

CONTACT: E. BENNER, NRR/ DORS AIT: _H0_

10 CFR 50.72 #24849 SIGEVENT: TBD ,

REFERENCE:

SEABROOK, UNIT 1 93-03 o THE PROCEDURE NOTES THAT LOW LEVEL IN 2 0F 4 CHANNELS IN COMBINATION WITH AN SI SIGNAL WILL GENERATE AN "ECCS/ CONT SPRAY RECIRC SIGNAL" WHICH ALIGNS.THE RHR AND CBS SUCTION TO THE CONTAINMENT SUMP, o PRECAUTIONS EXIST IN THE PROCEDURE TO NOT TEST THE RERAINING TWO LEVEL TRANSMITTERS AND TO RETURN THE CHANNEL TO OPERABLE STATUS IF A BISTABLE TRIP OCCURS IN EITHER OF THE TWO REMAINING LEVEL TRANSMITTERS. THESE PRECAUTIONS APPLY ONLY IN MODES 1, 2, 3, AND 4.

EQLLOWUP EVENTS ASSESSMENT, PROJECTS, AND THE REGION ARE CURRENTLY EVALUATING THE EVENT, ITS GENERIC IMPLICATIONS, AND THE LICENSEE'S CORRECTIVE ACTIONS.

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- 93-03 SUMMER REACTOR TRIP AND LOSS OF B0P POWER JANUARY 12, 1993 PROBLEM REACTOR TRIP AND LOSS OF BALANCE OF PLANT (B0P) POWER RESULTING IN NATURAL CIRCULATION AND DUMPING STEAM TO ATH0 SPHERE.

CAUSE LOSS OF LOAD DUE TO SPURIOUS OVERCURRENT RELAY ACTUATION CAUSING THE MAIN TRANSFORMER TIE BREAKER TO OPEN.

SAFETY SIGNIFICANCE o NATURAL CIRCULATION.

o LOSS OF CONDENSER AS HEAT SINK.

SEQUENCE OF EVENTS TIME o (08:54) TIE BREAKER BETWEEN MAIN TRANSFORMER AND SWITCHYARD GPENED, APPARENTLY DUE TO A FAULTY RELAY.

POWER RANGE HI FLUX RATE REACTOR TRIP DUE TO INCREASED REACTOR COOLANT PUMP (RCP)

SPEED.

CONTACTS: G. WUNDER, NRR/PDII-1 AIT: 1K)

C. ORSINI, NRR/ DORS SIGEVENT: TRQ

REFERENCES:

10 CFR 50.72 #24862 MORNING REPORT DATED 01/14/93

m/4755EEvP SUMMER 93-03 o 30 SEC MAIN GENERATOR OUTPUT BREAKER OPENED, RESULTING IN A LOSS OF POWER TO B0P BUSSES INCLUDING THE RCPs AND CIRCULATING WATER PUMPS. LOGIC PREVENTED AUTO SWAPOVER TO EMERGENCY AUXILIARY TRANSFORMER (EAX) .

- START OF NATURAL CIRCULATION o 40 SEC EMERGENCY FEEDWATER INITIATED.

o 4 MIN CONDENSER STEAM DUMP VALVES CLOSE.

e 1 HR 9 MIN CONDENSER VACUUM LOST.

e 1 HR 45 MIN B0P POWER RESTORED VIA EAX.

e 2 HRS 19 MIN STARTED 'A' RCP.

- END OF NATURAL CIRCULATION e 2 HRS 28 MIN 'A' MAIN STEAM POWER-0PERATED RELIEF VALVE (PORV) OPENED FOR THE FIRST TIME, BEGAN CONTROLLING PRIMARY TEMP. BY DUMPING 'A' STEAM GENERATOR (SG) TO ATMOSPHERE VIA PORV.

e 33 HRS CONDENSER RETURNED TO SERVICE. SECURED DUMPING STEAM TO ATMOSPHERE.

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SUMMER 93-03 EISCUSSION o NORMAL ELECTRICAL LINEUP POWERS THE B0P BUSSES (INCLUDING THE RCPs) THROUGH A UNIT AUXILIARY TRANSFORMER.

• SWITCHGEAR LOGIC PREVENTS AUTOMATIC TRANSFER TO EMERGENCY AUXILIARY TRANSFORMER WHEN BUS IS POTENTIALLY FAULTED.

o ENTRY INTO NATURAL CIRCULATION PER SE DOES NOT QUALIFY AS AN UNUSUAL EVENT (UE).

o MOST EVENTS RESULTING IN NATURAL CIRCULATION QUALIFY AS UEs SINCE THEY ARE INITIATED BY A LOSS OF 0FFSITE POWER.

RADIOLQ_GICAL ASPECTS o LICENSEE SAMPLED "B" SG BLOWDOWN AND PERFORMED ISOTOPIC ANALYSIS 4 TIMES FOLLOWING THE TRIP.

o "B" SG WAS CHOSEN AS " WORST CASE" SINCE IT HAD SHOWN THE GREATEST PRIMARY TO SECONDARY LEAKAGE (9-11 GALLONS PER DAY (GPD)) HISTORICALLY.

• LEAKAGE REMAINED RELATIVELY CONSTANT THROUGHOUT EVENT AT 3-6 GPD FROM 'B' SG.

• INTERMITTENT VENTING TO ATMOSPHERE CONTINUED FOR APPR0XIRATELY 32 HOURS BECAUSE THE CONDENSER WAS UNAVAILABLE.

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SUMMER - 4- 93-03 j STEPS TO RECOVER CONDENSER:  ;

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- FILL AND VENT CIRCULATING WATER SYSTEM. -

- SAMPLE _HOTWELLS TO DETERMINE IF TUBE LEAKAGE OCCURRED.

- REPAIR HOTWELL LEVEL CONTROL.

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- DUMP HOTWELLS TO TURBINE BUILDING SUMP.  :

- PUMP TURBINE BUILDING SUMP.

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' ATTAC'iMENT 3 REAttot SCLAN Reporting Parlod 01/11/93 to 01/2&/93 YTD YiB ABOVE 81 LOW TfD f.261 lifki CM}1 P

GM.i!CM10W5 111 13 19]AL till P.LAWL $3M11 No 1 0 1 01/12/73 D M'!R 1 100 1A twissent f atture 0 2 SEA 8800K 1 100 SA twignent f ailure NO 2 01/1&/93 raternet No 1 0 1 1AW OWOFRt 3 75 sa 01/16/93 SM tept;nent ialture WO 0 1 1 1AltM 1 13 01/16/93 Equitment felture No 1 0 1 DRttDru 3 83 sM 01/16/93 operating trror No 1 0 1 100 SA 01/18/73 COMAWCHE PEAK 1 1 0 1 01/21/93 WA$NING10N N'JCLEAR 2 100 SA Detten or instatisti Wo twipient f alture No 1 0 1 01/23/93 $0J1W itKAS 2 100 SA Equipnent f atture ho 2 0 2 01/26/73 COMANCHE PEAK 1 100 SA -

V Wotet Year lo Date (YTC) Totals trienAe Events Within the Calerder Year Indicated By the End Date of 1he Specified Reporting Perlo Page:1 01/23/9 E15 10

l Co@ARit0N of WttRLY SCRAM st A11$1lCn WITN INDU51RY AVtR ACES a

i PERICO ENDlWG 01/18/93 to 01/24/93 1992* 1991* 1990* 1989*

kuustt 1993 WittLT WitKLY WEIKLY WEELLY OF WEKLT Ayt R ACE Ayt tt GE Ay[ RAGE AytRAGE stRAMg AytRAGE 1[f44 CAU$t (T10)

POWtR CitAttR THAN OR tDUAL 10 15%

2 2.6 2.6 2.9 3.4 3.1 EQUIPMENT fAILutt' -

DEllCN/lW$1AttA110N tRROR* 1 0.3 -

1 0.3 0.8 0.6 0.5 1.0 OPERATING tRROR*

MAlWithANCE tRROR* 0 0.3 -

tritRNAL* 0 0.3 -

• O 0.0 - - - 0.1 01HER*

4 3.8 3.4 3.5 3.9 4.2 54 total POUCR Lit $ INAN iS1 0 0.3 0.4 0.3 0.4 0.3 EQUIPMENT fAltutt' DtllCN/lW11ALLA110N tRROR* 0 0.0 - -

0 0.0 0.2 0.2 0.1 0.3 OPERAllWG tRROR*

• - 6 MAlW1ENAkCE (RROR* 0 0.0 .

ExitRNAl* O 0.0 - -

OTHER* 0 0.0 - -

0.3 0.6 0.5 0.5 0.6 54 total 0 4 4.1 4.0 4.0 4.4 4.8 TOTAL 1993 1792 1991 1990 1989 WEEKLY WEEKLY Wo. OF WtittY WEEKLY WEEKLY AVERAGE AVERACE AVERACE AVERAGE AVERACE SCRAW TYPE SCRAMS (T10) 4 3.2 3.0 3.3 3.2 3.9 TOTAL AUTOMAtlC SCRAxt 0 0.9 1.0 0.7 1.2 0.9 TOTAL MANUAL 5 TRAMS

• Detalledbreekdownretindatabasefor199Aandearlier ExilRNAL cause. included in (OUIPMENT FAILUtt MAINTENANtt (RROR and OtSIGN/ Inst ALLA110N ERROR causer, included in OPCRA11NG tEROR

• DIMER tause included in (OUIPMENT FAILURE 1o91 ard 1990 l

CcwARI$0W ol WttKLY $ CRAM SI Af tstit$ W11M IwoustRY AVtRAGE$

e Ptkloo (W0lWG 01/11s93 to 01/17/93

- 1993 1992* 1991* 1990* 1989*

WuMett OF WitKLY WitKLY WitKLY VitKLT WitKLY AVf R ALI AVERAGE AvtRAGE AVIRACE g(RAM _teg1[ SCRAM 5 AvtRAGE (Y1D)

POWER GREAftR IMAN OR (QUAL 10 15%

3 2.9 2.6 2.9 3.4 3.1 toulPMtWT FAILURt* *

• OtllGW/IN$1ALLAfl04 ERROR

• O 0.0 -

0 0.0 0.6 0.6 0.5 1.0 CPIRAllWG tRROR*

KAIWirkANet (RROR* O 0.4 -

ExitRNAL* i 0.4 -

0 0.0 - *

• 0.1 OTHER*

4 3.7 3.4 3.5 3.9 4.2

$ubtotet POWER LES$ THAN 1$%

1 0.4 0.4 0.3 0.4 0.3 EDVIPMENT FAILutt*

Dt$1GN/lW$fALLAflDN ERROR

• O 0.0 *

• 0 0.0 0.2 0.2 0.1 0.3 OrtRAfikG ERROR

• MAlWitWANCE (RROR* 0 0.0 -

EXTikNAL* 0 0.0 - -

OTHER* O 0.0 .

0.4 0.6 0.5 0.5 0.6 Subtotal 1 5 4,1 4.0 4.0 4.4 4.8 TOTAL l

1992 1991 1990 1989 1993 Wo. Of WEEKLY WttKLY WttLLY VttKLT WEEKLY AVfRAGE AVERAct AVERAGE AVERAGE SCRAM YYPE SCRAM $ AVERAGE (yid) 3 2.9 3.0 3.3 3.2 3.9 l TOTAL AUTOHATIC SCRAMS l 2 1.2 1.0 0.7 1.2 0.9 TOTAL MANUAL SCRAM 1 i

• Ottelled breakdown not in database for 194 and earlier ExitRNAL r.ause _ Included in (OUIPME"i F AILURE KAIN1tNANCE tRROR and DE$1GN/th11ALLATIDW (RRDR causes included in OPERA 11NG ERROR

+ 01 Hit cause included in (GUIPMENT FAlltlRE 1991 and 1990 t

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