ML20029C112

Summary of Operating Reactors Events Meeting 91-03 on 910213 in Rockville,Md Re Selected Events That Occurred Since 910130 Briefing.List of Attendees & Elements Discussed Encl

ML20029C112
Person / Time
Site:	Dresden, Mcguire, Quad Cities, McGuire
Issue date:	02/25/1991
From:	Chaffee A Office of Nuclear Reactor Regulation
To:	Rossi C Office of Nuclear Reactor Regulation
References
OREM-91-003, OREM-91-3, NUDOCS 9103250372
Download: ML20029C112 (19)

Text

..

l February 25, 1991 MEMORANDUM FOR:

Charles E. Rossi, Director Division of Operational Events Assessment FROM:

Alfred E. Chaffee, Chief Events Assessment Branch Division of Operational Events Assessment

SUBJECT:

THE OPERATING REACTORS EVENTS MEETING FEBRUARY 13, 1991 - MEETING 91 03 On February 13, 1991, w<s conducted an Operating Reactors Events meeting (91 03) to inform senior managers from the Commission staff, NRR, ACRS. EDO, AEOD, OE, i

RES and regional offices of selected events that occurred since our last briefing on-January 30, 1991. lists the attendees. presents the significant elements of the discussed events. contains reactor scram statistics for the weeks ending 02/03/91 and 02/10/91. tabulates one significant event which was identified for input into the NRC performance indicator program.

ORIGINAL SIGNED BY:

Alfred E. Chaffee, Chief Events Assessment Branch Division of Operational Events Assessment

Enclosures:

As stated cc w/ Encl.:

See Next Page DISTRIBUTION:

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N F. Miragl NRR B. Siegel, NRR (Dresden) e W. Russell, NRR R. Barrett, NRR F. Gillespie, NRR T. Reed, NRR (McGuire)

J. Partlow NRR D. Matthews, NRR S. Yarga, NRR R. Wessman, NRR G. Lainas, NRR D. Crutchfield, NRR J. Zwolinski, NRR B. Boger,-NRR W. Travers NRR

_.J. Richardson, NRR A. Thadani NRR F. Rosa, NRR

- B. Grimes, NRR F. Congel NRR J. Roe, NRR T. Martin, RI

- W. Kane, RI C. Hehl, RI S. Ebneter, RII-L. Reyes, RII B. Davis, RIII E. Greenman, RIII R.D. Martin,=RIV' S. Collins,.RIV J.B. Martin, RV R. Zimerman,- RV P. Boehnert, ACRS-E. Jordan, AEOD T. Novak.. AEOD -

L. Spessard, AEDD G. Zech, AE00 E. Weiss S. Rubin, AE00

, -AEOD M. Harper,.AEOD-W. Bateman, EDO R. Newlin, GPA-J..Cowan,'INPO E.. Beckjord, RES-A. Bates, SECY Y

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j February 25, 1991 l

I MEMORANDLN FOR:

Charles 6. Rossi, Director Division of Operational Events Assessment FROM:

Alfred E. Chnffee, Chief Events Assestment Branch Division of Operational Events Assessment

SUBJECT:

THE OPERATING REACT 0lls EVENTS MEETING FEBRUARY 13, 1991 - NIETING 91-03 On February 13, 1991, weconductedanOperatingReactorsEventsmeeting(91-03) to inform senior managers from the Commission staff, NRR, ACRS, E00, AE00, OE, RES and regional offices of selected events that occurred since our last briefing on January 30, 1991. Enclosure i lists the attendees. Enclosure 2 presents the significant elements of the discussed events.

Ecciosure'3 contains reactor scram statistic; for the weeks end ng 02/03/91 and 02/10/91. Enclosure 4 tabulates ore significant event which wa) identiffed for input ihto the NRC performance indicator program.

Alfred E. Chaffee, Chief L

Events Assessment Branch bisisiw of Operational Eventt Assessment

Enclosures:

-As stated L;-

.cc w/ Encl.:

See Next Page ji i

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ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS FULL BRIEFING (91-03)

February 13, 1991 NAME ORGANIZATION NAME ORGANIZATION D oung NRR/DOEA D aass IMR/RVIB P. Baranowsky NRR/00EA R. Pedersen OE D. Fischer NRR/DOEA A. Almond OE J. Carter NRR/DOEA A. Hend m b OCH R. Benedict NRR/DOEA E. Murphy HRR/EMCB K. Baumann NRR/00EA T. Reed NRR/PDII-3 N. Fields NRR/DOEA U. Carter NRR S. Sanders NRR/00EA R. Elliott NRR/PDill-2 B. Grimes NRR/DRIS L. 01shan NRR/PDill-2 H. Alderman ACRS J. Lee NRR/PRPB J. Knight NRR/SELB K. Connaughton OCM/JC I

C. Thomas NRR/SELB J. Tatum NRR/SPLB C

W. Minners RES R. Lobel EDO M. Caruso NRR/SRXB H. Balukjian NRR/SRXB G. Imbro NRR/RSIB E. Rossi NRR/DOEA F. Miraglia NRR S. Jones NRR/SPLB V. Benaroya AE0D/DSP R. Hauber GPA/IP 3

1

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. 0PERATING: REACTORS EVENTS-BRIEFING 91-03 1

?;;y.

EVENTS ASSESSMENT BRANCH LLOCATION:. -10B-11, WHITE FLINT cWEDNESDAY,-FEBRUARY'13; 1991, 11i00:A.M.

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QUADICITIES.118 2

. STANDBY. LIQUID CONTROL -SYSTEM

-DRESDENj248: 3.

-POTENTIALLYTIN0PERABLE DUE TO

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34 A

INADEQUATE 1:NPSH

,h.

m, MCGulRE-UNIT:2-i.0SS OF 350 GALLONS 10F REACTOR.-

C00LANTTFROM CVCS.

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,LOSSLOF10FESITEdPOWER WITH. SAFETYL I

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.-INJECTION..

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1 n m 91-03 QUAD CITIES, UNITS 1 & 2 DRESDEN, UNITS 2 & 3

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STAN P LIQUID CONTROL SYSTEM POTENTIALLY lh0PERABLE DUE T0 INADEQUATE NPSH FEBRUARY 11, 1991 4

PROBLEM-a STANDBY-LIQUID CONTROL SYSTEM MAY NOT BE ABLE TO DELIVER SPECIFIED FLOW

' SATISFY ATWS REQUIREMENT-86 GPM.

t EAuSE:-

PREVIOUS DESIGN ANALYSIS AND TESTING FAILED TO RESOLVE, ADEQUACY

-0F.;NPSH-WHEN BOTH STANDBY LIQUID CONTROL PUMPS ARE OPE 3ATING.

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1

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SAFETY-SIGNIFIC ANCE:--

CONTAINMENT OVERPRESSURIZATION COULD OCCUR WITH--REuuCED-RATE OF-1 BORON. INJECTION INTO THE RE!iCTOR SYSTEM FOLLOWING-ATWd.

3 DISCUSSION:;

DUAL PUMP;0PERATION IS REQUIRED FvR-A M MlTIGATION 3 N0l FLOW. TEST-HAS: BEEN PERFORMED IN-TRt>E CONFIGURATION

• 'DURINGLA TEST =AT QUAD CITIES-USING THE TEST: TANK-920" LEVEL,

A S!NGLE OPERATING SBLC PUMP 5 STARTED TO' CAVITATE.WHEN THE WATER 1

TEMPERATURE WAS:= INCREASED T0ill3 F3

• =-.THE" SINGLE-PUMP DEllVERED 43--GPM AT. LOWER-TEMPERATURES WITHOUT-

-CAVITATION-

• ~PUMPScARE' TRIPLEX POSITIVE DISPLACEMENT TYPE

=

=' LMARGINAL SINGLE PUMP OPERABILITY' BELIEVED DUE TO FLUID ACCELERATION LOSSES CAUSEDLBY-POSITIVE DISPLACEMENT PUMr1 nPERATION 0

g CONTACTi: JERRY: CARTER

-AIT:

' NO -

REFERENCE:

1 :10 -.'R :50.'72: #20424 SIGEVENI;_T3D

.AND:#20425

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QUAD CITIES /DRESDEN 91-la DUAL PUMP OPERATION INDETERMINATE PIPING CONFIGURATION HAS DUAL LINES FROM SBLC TANK TO HEADER AND FROM HEADER TO SBLC PUMPS ADVERSE INTERACTION MAY BE CAUSED BY THE TWO PUMPS OPERATING IN PARALLEL BOTH-0UAD CITIES UNITS AND DRESDEN UNITS HAVE SIMILAR PROBLEM

PROBLEM BELIEVED GENERIC TO OTHER BWRs FOLLOWUPr GE IS-PERFORMING AN ANALYSIS FOR THE LICENSEE TO DETERMINE THE AVAILABLE hPSH REGION 111 IS CLOSELY FOLLOWING THE LICENSEE'S EVALVATION REGION 111 IS. DRAFTING A GENERIC COMMUNICATION REACTOR SYSTEMS BRANCH REVIEWING-CALCULATIONS TO ASSIST REGION.

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MCGUIRE, UNIT 2

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LEAKAGE FROM CVCS 4

FEBRUARY 5, 1991 1

PROBLEM LOSS 10F 350. GALLONS OF REACTOR COOLANT FROM C'/CS,

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1

'CAUSEu

LEAKY DIAPHRAGMS lN RESIN:SLUTCE VALVES AND SPURIOUS PARTIAL r

CLOSURE OF VALVE-NV-347.

y SAFETY SIGNIFICANCE

• LLEAKAGE:0F; PRIriMY COOLANT:0UTSIDE; CONTAINMENT:

• 1 LEAK -WAS-ISOLAi".' FROM REACTOR 'C00LANT' SYSTEM -

i LEAKAGELWAS EXTERNAli:NOTcTO-ANOTHER FLUID SYSTEM.

s t*- ' LEAK WASLT00lSMALLET0LBE NOTICEABLE FROM RCr PARAMETERS,

AND WAS SMALLER THAN: CHARGING AND MAKEUP-SYSTEMS':

i

CAPABILITIES.

n CVCS LEAR IS~ BOUNDED BY'SMALL-BREAK LOCA ANALYSIS.

DISCUSSION

"* TSAMPLING5 PROCEDURE UNDERWAY IN'BTRS RELJ1 RED'"F0OLING" i

m LVALVE V-347: INT 0VREMAINING.:<0 PEN.

4

='~ :;V-347! PARTI ALLY! CLOSED (REASON-UNKNOWN L,--INCREASING lUPSTREAM.

!PRESSORE.

OPERATOR. HEARD' MAKEUP PUMP-START UP CHECKED VCT, SAh LEVEL-lh'ASi: DOWN.

• 20PERATOR:SAW:NV-3477NOT OPEN, OPENED 21T.

L." IVCTs:iLEVELiRETURNED(T0;NORMALL

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JCONTACT:: ;R? BENEDICT AIT:

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REFERENCE:

EVENTTSO.72:N0.320388-

SIGEVENT

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. MCOUlRF'UNITJ2 91-03 DISCUSSiOL (CONTINUED)~

SCENARIO ESTIMATED FROM PLANT RECORDS:

L

• iDIAPHRAGMS:IN VALVES NV-350 AND 349 LEAKED, ALLOWING APPR0XIMATELY 350 GALLONS,0F CVCS WATER-T0 SPILL INTO

~ VALVE PIT.

- WHEN NV-347 WAS OPENED,-UPSTREAM PRESSURE DROPPED T0

NORMAL AND LEAK RATE DROPPED TO NORMAL ()/2 GPM UNIDENTIFIED) i

- *'! LICENSEE PLANS TO REPLACE VALVES NV-350 AND 349, AND REMOVEL NY-347.

' AUXILIARY BUILDING VENTILATION EXHAUST SWITCHED AUTOMATICALLY.

FROM. UNFILTERED.-0PERATION TO FILTERED DUE TO INCREASED AIR ACTIVITYulNLTHE UNIT-VENT.

sSWITCH0VER.IN EXHAUST WAS NOT INITIATED BY-ENGINEERED SAFETY

)

DFEATURE ACTUATION.

• !NON-ESF:c STACK MONITOR-AREA MONITOR ESF:

.LOCA BLACK 0UT t

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BTRS CHARGING VCT SPEHT PUMPS RESIN TAMK 3

MCCUIRE CVCS

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91-03 MCGUIRE UNIT 1 LOSS OF.OFFSITE POWER (LOOP) AND SAFETY INJECTION 3

FEBRUARY 11, 1991

-PROBLEM:

UNUSUAL EVENT DECLARED DUE TO LOOP AND SUBSE0 VENT SAFETY INJECTION AT MCGUIRE UNIT 1

'CAUSE:

LOOP RESULTED FROM COMBINATION OF INADEQUATE POST MAINTENANCE TEST PROCEDURE AND AN EXISTING FAILURE OF A PROTECTIVE RELAY IN A REMOTE SWITCHYARD SAFETY SIGNIFICANCE:

LOOP IS A POTENTIAL PRECURSOR TO LOSS OF ALL STATION AC POWER POTENTIAL FOR A STUCK OPEN PORV DISCUSSION:

o ON FEBRUARY 11, 1991, AN UE WAS DECLARED AT MCGulRE UNIT 1 DUE TO A LOOP, A SUBSEQUENT REACTOR TRIP, AND A SAFETY INJECTION (SI) 0.THE LOOP'0CCURRED AS'A RESULT OF (1) AN INADEQUATE POST MODIFICATION TEST PROCEDURE FOR A RECENTLY INSTALLED OVERPRESSURE DEVICE AND (2) THE PASSIVE FAILURE OF A DISTANCE / DIRECTIONAL

' RELAY o BOTH EDG STARTED AND LOADED PROPERLY o AT.APPR0XIMATELY 2:13 PM UNIT 1 REACTOR /TdRBINE TRIPPED ON

~

SPURIOUS:HIGH RATE OF CHANGE OF NEUTRON FLUX SIGNAL INITIATED BY A VOLTAGE SPIKE WHICH FOLLOWED THE LOOP.

ALL RCPS WERE DEENERGlZED.

UNIT 2 WAS' UNAFFECTED BY THE TRANSIENT.

CONTACT:

NICK FIELDS AIT:

NO

REFERENCE:

10 CFR 50,72 #20421 SIGEVENT: YES-

I.

MCGUlRE, UNIT 1 91-03 o THE MOTOR OPERATED MSR HEADER INLET VAu!L LOST MOTIVE POWER WHEN THE LOOP OCCURRED AND THEREFORE COULD NOT BE CLOSED FROM THE CONTROL ROOM.

MAIN STEAM DRAIN VALVES FAILED OPEN AS DESIGNED.

AS A RESULT OF THESE OPEN VALVES, MAIN STEAM PRESSURE DECREASED TO 585 PSI, THE SETPOINT FOR SI AND MSIV ACTUATION.

CONTAINMENT ISOLATION G; CURRED AND AUXILIARY FEEDWATER STARTED AS DESIGNED o PRESSURIZER LEVEL INCREASED TO 87 PERCENT,

'"E PRESSURE PEAKED AT

-2385 PSI, PRESSURIZER PORV LIFTED AND RESEATED PROPERLY o THE PLANT WAS STABILIZED IN NATURAL CIRCULATION o AN OPEN ICE CONDENSER DOOR COUPLED WITH THE LOSS OF CONTAINMENT HVAC CONTRIBUTED TO AN INLPEASE IN HUMIDITY AND PRESSURE INSIDE CONTAINMENT o 0FFSITE POWER WAS REC 0VERED BY 3:06 PM AND BY 3:30 PM, OPERATORS BEGAN RESTORING 0FFSITE POWER TO THE VITAL AND NONVITAL BUSES o BY 4:05, ONE OF THE VITAL BUSES WAS BEING SUPPLIED BY OFFSITE POWER WITH THE OTHER CONTINUING TO BE SUPPLIED BY THE EDG, ONE RCP HAD BEEN STARTED AND THE "B" SG WAS BEING FED BY AUXILIARY FEEDWATER USING THE SG PORV TO MAINTAIN PROPER RCS TEMPERATURE AND PRESSURE o THE UE WAS TERM:.'iATED AT 4:43 PM o A CONTAINMENT ENTRY AND SYSTEM WALK-DOWN INDICATED NO EQUIPMENT DAnU E AS A RESULT OF THE TRANSIENT.

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$iMCGUIRErUNITil- -

91-034 7p'

? OLLOWUP:

F

- 0. REGION:Il'. MANNED THElR; INCIDENT RESPONSE CENTER l

0:THE LICENSEE-MANNED.THEIR TECHNICAL SUPPORT CENTER" e

'o THE COMMISSIONER'S ASSISTANTS WERE BRIEFED BY.THE REGION' m

0: THE' LICENSEE BRIEFED THE REGION AND HEADQUARTERS ON LESSONS

' LEARNED: PRIOR T0: UNIT STARTUP o N0 ADDITIONAL--F0LLOWUP-IS CONTEMPLATED I'

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ENCLOSURE 3L 4EACTORSCRAMSUMMART o--L WEEKENDING 02/03/91 1

't. PLANT SPECIFIC MTA ( }

(3)

.,P-

-Mit -

$1TE UNil PON(R 516NAL CAUSE COMPL1-Yip Yib fig i

Call 0NS A90VE DELOW TOTAL 151 151

-01/28/91 SiLUCIE 1

0A PERSONNEL NO 0

1 1

02/01/91 DIABLOCANYON 1

90 A PER50hN!L NO 1

0 1-02/01/91 ARKANSAS 2

88 A EQUIPMENT

1. 3 1

0 1

.7-6-

+

1 1

1EAC10RSCRAM

SUMMARY

NEEK ENDlW6 02/10/91 Il }

], PLANT SPECIFIC MTA (3)

^

pt"- :

Site' UN]f PONER 516NAL CAUSE

- COMPL1 - YTD YTD Yif

.CA110NS A00VE DELON 101AL 151 151

. 02/10/91 CDMAN:Hi PEA '

,1 ' 100 A -

EDVIPMEN1 N0 i

0 2

02/09/91 DUANE ARN0(D 0

2

- 4

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80 A

-PERSONNEL NO 2

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II.: COMPARISON 0F WEEKLY STATISTICS WITH INDUSTRY AVERAGES' SCRAMS FOR' WEEK ENDING 02/03/91

+

NUMBER 1991-1990 1989 1988 1987 I

0F-

. WEEKLY -

WEEKLY WEEKLY WEEKLY WEEKLY SCRAM CAUSE>

SCRAMS AVERAGE AVERASE AVERAGE

. AVERAGE ' AVERAGE

• s (YTD)

, POWER GREATER THAN 15%-

EQUIPMENT 1RELATED.

1 1.6 3.4 3.1-3.0 t.9-PERSONNEL :;' LATED (2):

1 0.6-0.5 1.0

-1.0 1.3 1

OTHER(4):

0 0.0 0.0 0.1

0. 4 '

1.1 j.

1 35ubtotalt 2

2.3*

3.9-4.2 4 6.3 y

1 POWER:LESS.THAN.15%

9

" _ ~

EEQUIPMENT:RELATED...

0:

'0.0' O.4 -

0.3

-04 L2

-PERSONNELRELATED'.(2) 1 0.2 0.1 0.3 0.4

'O. 6

.'0_THER:(AP 0'

O.0 0.0 0.0-0.2 0.3-f

Subtotal.

I' O.2 0.5 0.6

- 1.2 -

2.1

}

TOTAL:

- -3 '

2.5

-4.4 4.8' 5.6 8.4

~

MANUAL VS AUTO SCRAMS' 1991 1990' 1989-1988-1987 N0; 0F -

' WEEKLY' WEEKLY; WEEKLY:

WEEKLY WEEKLY;

.' SCRAMS'

- AVERAGE. AVERAGE-~

AVERAGE AVERAGE' -AVERAGE-i STYPE (YTD) i IMANUALSCRAMS:

i 0-10.4 1.' 2 '

O9 1.'1 1.4L

-AUTOMATICLSCRAMS'

- 3 2.1 3.2 3.9-4.5

- 7.0

'.- m 3.*CorrectedLto accommodate rounding-off L

A at

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y ammy - -,

mm

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II.:. COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES SCRAMS FOR WEEK ENDING 02/10/91 NUMBER 1991-1990-1989 1988 1987:

OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY JSCRAM CAUSE SCHAMS AVERAGE AVERAGE AVERAGE AVERAGE' AVERAGE (YTD)

POWER GREATER THAN 15%

l EQUIPMENT-RELATED-1 1.5 3.4 3.1 3.0 3.9 r

PERSONNEL RELATED (2) 1 0.7 0.5 1.0 1.0 1.3

!0THER-(4) 0-0.0-0.0 0.1 0.4 1.1

~ Subtotal-

_2 2.2 3.9 4.2 4.4 6.3

. POWER lESS THAN 15%

EQUIPMENT RELATED 0

0.0

-0.4 0.3 0.6 1.2

-PERSONNEL RELt.TED (2) 0-22 0.1 0.3 0.4 0.6

~0THER(4)!

0F 0.0 0.0 0.0 0.2 0.3 Subtotal' 0

0.2 0.5 0.6 1.2 2.1

' TOTAL 2

2.4 4.4 4.8 5.6 18.4 7

MANUAL VS AUTO SCRAMS 1991 1990 1989

=1988 1987 N0.- OF

-WEEKLY WEEKLY WEEKLY WEEKLY

-WEEKLY

' TYPE

-SCRAMS.

' AVERAGE' AVERAGE AVERAGE-. AVERAGE AVERAGE (YTD)

-, MANUAL: SCRAMS 0

0.3 1.2 0.9 1.1 1.4 AUTOMATIC: SCRAMS 2

2.1*

3.2 3.9 4.5 7.0

'9Correctedtoaccommodaterounding-off 4

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.~.. -. -. -

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NOTES 1.

PLANT SPECIFIC DATA BAS.D ON INITIAL REVIEW OF 50.72 REPORTS FOR THE PEEK OF INTEREST.

PERIOD lb MIDNIGHT SUNDAY THROUGH MIDNIGHT SUNDAY. SCRAMS

'ARE DEFINED AS REACT 0k PROTECTIVE ACTUATIONS WHICH RESULT IN R00 MOTION, AND EXCLUDE PLANNED TESTS OR SCRAMS %S-PART OF PLANNED SHUTDOWN IN ACCORDANCE WITH A PLANT-PROCEDURE. THERE ARE 111 REACTORS HOLDING AN OPERATING LICENSE.

2.

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

4 3.

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

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

OEAB SCRAM DATA Manuo I and Automatic Scrams for 1987 ------------------ 435 Manca and Automatic Scrams for 1988 ------------------ 291 Manut. and Automatic Scrats for 1989 ------------------ 252 Manual und Automatic Scrams for 1990 ------------------ 226 Manual and Automatic Scrams for 1991---(YTD 02/10/91)-- 014 I

2 w r,.w 4

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ENCLOSURE 4

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