ML20059G701

Summary of Operating Reactors Events Meeting 90-22 on 900905.List of Attendees & Scram Statistics Encl

ML20059G701
Person / Time
Site:	Calvert Cliffs, Pilgrim
Issue date:	09/06/1990
From:	Baranowsky P Office of Nuclear Reactor Regulation
To:	Rossi C Office of Nuclear Reactor Regulation
References
OREM-90-022, OREM-90-22, NUDOCS 9009130076
Download: ML20059G701 (1)

Text

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.I SQptember 6,1_. 'O q

,$, .x MEMORANDUM FOR: . ChirlesE.Rossi, Director Division of Operational Events: Assess;nent FROM: Patrick W.: Baranowsky; Acting Chief Events Assessment Branch ,

Division'of Operational. Events Assessment.

SUBJECT:

THE'0PERATING' REACTORS EVENTS MEETING SEPTEMBER 5, 1990 - MEETING 90 22 ,

l On.S ptember 5, 19903 we conducted an Operating-Reactors Events meeting (90-22) '

to inform senior nanagers from NRR, ACRS,: AE00, Comission staff, and regional offices.of selected events that occurred since our last briefing on :

Augusc 22, 1990. Enclosure 1 lists the attendees. Enclosure 2 presente the:

significant elements of the discussed events.

Enclosurc'3 contains reactor scram statistics for the week ending 09/02/90.

Origiria' signed by i

Patrick W. BIranowsky, Acting Chief:

Events Assessment Branch j

' Division of 0perational Events' Assessment'

Enclosures:

As stated cc ' . ic1.: 1 See.Next Page DISTRIBUTION s'5Centrah File & S*

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/ DOCUMENT NAME: TRANSMITTAL LETTER 09/05/90 ,

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T.> Hurley, NRR D.' Mcdonald?-Jr. NRR F. Miraglia, NRR R. Capra,'NRR? '

W. Russell, NRR R. Eaton,'NRR!

F. Gillespie, NRR R. Wessman,.NRR= +

J. Partlow, NRR l S.:Varga,- NRR' l :R.Wessman, NRR. .

L G. Lainas,'NRR . .

L D. Crutchfield, NRR -

i H- .J.- Zwolinski, NRR .

B. Boger, NRR-W. Travers, NRR J. Richardson, NRR  ?!

A. Thadani, NRR i F. Rosa ~, NRR t B. Grimes, NRR t

F. Congel, NRR L

J. Roe, NRR T. Martin, RI ,

W. Kane, RI.

C. Hehl,.RI' S. Ebneter, RII "

l-L. Reyes, RII B. Davis, RIII E. Greenman, RIII .

S. Collins, RIV R.D, Martin, RIV  :

J.B. Martin, RV R. Zinnerman, RV P. Boehnert, ACRS E.-Jordan,'AE0D ,

T. Novak, AEOD L. Spessart AE00 E. Weiss, AEO S. Rubin, AEOD .

M. Harper, AEOD '

J. Dyer, EDO '

R. Newlin, GPA J. Cowan, INP0 ll E. Beck,jord, RES A. Bates, SECY "

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e ENCLOSURE.1 .

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LIST OF ATTENDEES a l :.

OPERATING REACTORS' EVENTS BRIEFING (90-22).

Sep'temb'er 5, 1990- .

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NAME ORGANIZATION NAME; ORGANIZATION' j P; Boehnert' .ACRS N. Kadambi. NRR/DOEA R. Karsch NRR/DOEA J. Thompson: .NRR/DOEA- i P. Baranowsky - NRR/DOEA' D. Fischer NRR/DOEA' ',

C. Rossi _ NRR/DOEA W. Haass NRR/DRIS A. Fitzgerald NRR/DRIS L. Norrholm- OCM/KC: l M. ' Ca se ._ .DLPQ R. VanHouten. ESECY l, V. .Benaroya AE0D/DSP; J. Capra NRR/PDI-li J. Scarborough - OCH/KC- R. Gallo EDO 'I r

D. La,arge NRR/PDI-1 ,

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. 1 NOTES- .

. 1. PLANT SPECIFIC DATA BASED ON INITIAL REVIEW 0F 50.72 REPORTS I. FOR THE WEEK OF INTEREST.: PERIOD IS MIDNIGHT SUNDAY-THROUGH l

, MIDNIGHT SUNDAY. SCRAMS ARE DEFINED AS REACTOR PROTECTIVE.

ACTUATIONS WHICH RESULT IN ROD MOTION, AND EXCLUDE PLANNED

TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN'IN ACCORDANCE- o WITH A PLANT PROCEDURE. THERE~ARE 111. REACTORS HOLDING'AN-OPERATING LICENSE.u &

-t L ' 2. 00HPLICATIONS: RECOVERY COMPLICATED BY EQUIPMENT FAILURES'OR PERSONNEL ERRORS UNRELATED TO CAUSE OF SCRAM.'

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i 3. -PERSONNEL RELATED. PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL' a L DEFICIENCIES, AND= MANUAL STEAM GENERATOR" LEVEL CONTROL p PROBLEMS.

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4. "0THER" INCL'UDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL a l CAUSES(LIGHTNING),SYSTEMDESIGN,ORUNKNOWN_CAU'E.. l OEAB SCRAM. DATA Manual and Automatic Scrams for 1986 ------------------ 461 Manua11 and Automatic Scrams for 1987 ----------------- '439 Hanual and Automatic Scrams for 1988'------------------ 287

• Manual and Automatic Scrams for 1989 ------------------ 244 Manual and Automatic Scrams for 1990 (YTD 09/02/90) --- 139 4

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.0PERATING REACTORS, EVENTS BRIEFINGt90-22 h EVENTS ASSESSMENT BRANCH-  ;

LOCATION- 10B-11', WHITE 2 FLINT' WEDNESDAY,. SEPTEMBER 5, 1990,ill:00 A.M.

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CALVERT. CLIFFS UNIT 1 REACTOR VESSEL LEVEL-CONCE %  !'

WHILElDRAININGiRCS1

PILGRIM MALFUNCTION OF THE FEEDWATER REGULATING SYSTEM AND RCIC FAILURE s

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NOTE

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THE FULL BRIEFING ON OR/F:/90 WILL BE HELD IN 10B-11 AT 11:00 A.M.

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, CALVERT CLIFFS UNIT 1  ;

.-  : REACTOR VESSEL LEVEL CONCERN'WHILE DRAINING RCS  ;

AUGUST 30,J1990 1 q

PROBLEM o WHILE ATTEMPTING TO.. DRAIN DOWN THE RCS'IN PREPARATION FOR RCP- R SEAL REPLACEMENT,.TWO CHANNELS.OF REACTOR VESSEL LEVEL 1

INDICATION SYSTEM (RVLIST ALARMS WERE-RECEIVED.. l CAUSE o -UNDER-INVESTIGATION.

SAFETY SIGNIFICANCE 0: POSSIBLE VOID FORMATION IN VESSEL. ,

o PROCEDURE ADHERENCE CONCERNS RAISED.

DISCUSSION o ON AUGUST 30, 1990, WITH THE REACTOR IN MODE 5,~WHILE DRAINING DOWN THE RCS IN PREPARATION-FOR MID~-LOOP RCP SEAL REPLACEMENT, THE OPERATORS RECEIVED RVLIS LOW LEVEL ALARMS.

o OPERATORS VERIFIED THE PZR LEVEL INSTRUMENTATION STILL INDICATED PZR LEVEL WELL AB0VE THE BOTTOM 0F THE PZR.

o THE OPERA 10RS CONTINUED THE DRAIN DOWN WHILE CONFIRMING'THE-RVLIS ALARMS.

-o THE OPERATORS CHECKED THE RVLIS THERM 0 COUPLES LOCATED OUTSIDE THE CONTROL ROOM AND FOUND THE MAGNITUDE'0F THE DELTA-T '

INDICATION WAS APPROPRIATE'T0 INDICATE A VALID ALARM FOR A V0ID IN THE VESSEL.

o OPERATORS ATTEMPTED TO VENT THE VESSEL HEAD TO A QUENCH TANK, BUT DID NOT GET WATER OR GAS FLOW.

o OPERATORS PROCEEDED TO PERFORM A STEAM GENERATOR BLOWDOWN IN RESPONSE TO EXPECTED V0IDING IN VESSEL HEAD. i o

SUBSEQUENT VENTING RESULTED IN A MIXTURE OF WATER AND GAS SEEN IN TYG0N TUBING, POSSIbtY RELATED TO THE BLOWDOWN.

o NO ABNORMAL RADIATION INDICATIONS WERE OBSERVED.

o THE DRAIN E0WN WAS THEN RESUMED.

CONTACT: N. FIELDS SIGEVENT:

REFERENCE:

MORNING REPPM 8-30-90

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v x . ' '- 'CALVERTLCLIFFS UNIT 1 90-22

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p FOLLOWUP .

o' THE LICENSEE IS EVALUATING THIS EVENTtT0. DETERMINE THE ROOTL

• CAUSE-0F:THE Rx VESSEL BUBBLE,- "

o - AiSPECIAl INSPECTION TEAM'FROM THE REGION AND.NRR IS~AT THE-SITE T0-CONDUCT AN INDEPENDENT EVALUATION 0F THE ROOT CAUSE OF THIS EVENT INCLUDING THE REASON:THE u,J"' DOWN PROCEDURE  !

WAS CONTINUED INSPITE OF OPERATORS'HAVING RECEIVED-THE'RVL!S- t ALARMS, h

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PILGRIM

. MALFUNCTION OF THE-FEEDWATER REGULATING SYSTEM AND RCIC FAILURE.

. SEPTEMBER 2, 1990 PROBLEM' FEEDWATER CONTROL WAS. LOST, THE PLANT MANUALLY TRIPPED AND RCIC FAILED T0 START.

CONCERNS AROSE REGARDING THE SUITABILITY OF OPERATOR RESPONSE, y$ CAUSE L o A' HIGHLY CORRODED AIR PRESSURE SWITCH COMMON T0 BOTH FEEljWATER-REGULATING VALVES FAILED, A BLOWN FUSELIN THE CONTROL SYSTEM-PREVENTED VALVE LOCKUP S0 THE VALVES OPENED FULLY, 1

-SAFETY SIGNIFICANCE i o FAILURE OF THE FEEDWATER SYSTEM IN CONJUNCTION WITH' FAILURE OR .

-MALFUNCTION OF SEVERAL BACKUP SYSTEMS.

I DISCUSSION o THE REACTOR WAS AT 100% POWER DURING THIS EVENT (UNTIL'IT WAS MANUALLY TRIPPED AT 99% POWER).

o PEP, PROCEDURE THE-FEEDWATER REGULATING VALVES'WERE PLACED IN -

MANUAL CONTROL. MINIMAL RESPONSE TO REMOTE / MANUAL CONTROL WAS NOTED BY OPERATORS. IN ADDITION SOME FLOW'WAS DIVERTEDJTO -

THE CONDENSER, o LATER ON THE OPERATORS TRIPPED 0NE OF THREE MAIN FEED PUMPS ON HIGH LEVEL, WHEN LEVEL DECREASED TO 24" T0 26" THE.0PERATORS TRIPPED THE REACTOR, o THE PLANT WAS OPERATED FOR 20 TO 30 MINUTES BETWEEN THE TIME OF THE INITIAL HIGH LEVEL ALARM UNTIL THE MANUAL TRIP, o AFTER THE TRIP, PER A PROCEDURE WHICH HAD-NEVER BEEN USED BEFORE, THE OPERATORS MANUALLY INITIATED RCIC. THE RCIC l TURBINE SUBSEQUENTLY TRIPPED ON OVERSPEED BECAUSE TH

E. PROCEDURE

IS INCORRECT, CONTACT: 'RUDY KARSCH SIGEVENT: _TJLD

REFERENCE:

EVENT 19270 m .. -

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., PILGRIM. 90-22 .

of TWO ATTEMPTS WERE MADE TO RESTART RCIC. THE TURBINE COULD.NOT >

BE

KEPT RUNNING;BECAUSE OF DAMAGE TO THE STEAM INLET THROTTLE--

VALVE, POSSIBLY CAUSED-BY THE-OVERSPEED TRIPL 4 o RCIC WAS THEN CONSIDERED FAILED. THE=STARTUP FEED SYSTEM HAD i ALSO FAILED DUE TO A BLOWN GASKET IN THE AIR'0PERATED-CONTROLLER.

o VESSEL LEVEL WAS CONTROLLED BY FEEDING-THROUGH A, HEATER STRING BLOCK VALVE'AND: CYCLING THE MAIN FEED PUMPS.

c' A: GROUP 3.lSOLAT10N OCCURRED 47 MINUTES AFTER THE REACTOR-TRIP DUE TO HIGH VESSEL LEVEL. '

p AFTER THE ISOLATION, HPCI WAS RUN-IN TEST MODE-TO CONTROL l PRESSURE. THE OPERATORS DID.NOT WANT-TO FEED THE VESSEL WITH-' i L HPCI FEARING 0VERFEED-AND WERE RELUCTANT TO CYCLE HPCI,

-o HPC1' EVENTUALLY TRIPPED ON HIGH LEVEL SO SRVs WERE USED TO

-CONTROL PRESSURE UNTIL HPCI COULD BE RESTARTED.

o THE LEVEL WAS LATER CONTROLLED USINGLTHE CONDENSATE PUMPS OR CONTROL R0D DRIVE. PUMPS.

o RHR WAS ISOLATED BRIEFLY.DUE T0-SUCTION SIDE PRESSURE SPIKES DURING LINEUP 0F SHUTDOWN COOLING.

• FOLLOW UP

! o CONCERNS ARE RAISED REGARDING;0PERATOR ACTIONS AND: PROCEDURE.

L ADEQUACY.

o REGION I DISPATCHED A SPECIAL INSPECTION TEAM TO'lHVESTIGATE THIS EVENT AND WILL BE ON SITE 09/05/90 -

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.. lII.' COMPARISON OF' WEEKLY STATISTICS WITH-INDUSTRY AVERAGES SCRAMS FOR' WEEK _ENDING l 09/02/90 1

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SCRAM.CAUSEL POWER HUMBER -1990 1989J 1988- 1987 !1986; 1 OF. 1 WEEKLY WEEKLY = l WEEKLY- NF.dKLYr WEEKLY- 1 SCRAMS (5) AVERAGE AVERAGE- AVERAGE AVERAGEiAVERAGE'  !

? 'YTD _( 3)(4) j 1- l L

• • POWER'>15%

l EQUIP. RELATED- 1>15%- 6 3.3 2.9 '3 .1 '3. 9 :4.3-I PERS. RELATED(6) >15%- 1 .0. 5 1.0 - 1'. 0 L 1.'3 - 1.8 OTHER(7) >15% 0 0.01 0.1- 0.5 1.2 0.4-

-** Subtotal **. .

7; 3.8- 4.0~ 4.6. 6.4 !6.5-  :

• • POWER <15% '

• EQUIP. RELATED <15% 1 0.4  : 0,4: 0.5 1.2: ' 1. 4 .

PERS. RELATED <15%. -0 0 '.1 0-3

, 0.3 .06 . 0.8 OTHER. <15%- 0 '0.0 0.7 0.1 0.3 0.2

• • -Subtotal ** .,

1 0. 5 - 1.4 0.91 2.1' 2.4 l

• • • Total *** .

8 4.3 5.4 5.5 8.5 8.9 I

i MANUAL VS AUTO' SCRAMS ,

I TYPE NUMBER 1990' 1989 '1988. 1987 1986 .;

0F WEEKLY . WEEKLY WEEELY . WEEKLY WEEKLY SCRAMS AVERAGE AVERAGE AVERAGE-AVERAGE AVERAGE

'YTD 1

MANUAL SCRAMS,. 4 1.2 0.9 1.0 1.4 1.0; AUTOMATIC SCRAMS 4 3.1 3.8 4.5 7.0 -7.9 i

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