ML20059B733

Summary of Operating Reactors Events Meeting 90-21 on 900822.Reactor Scram Statistics Encl

ML20059B733
Person / Time
Site:	Brunswick, Haddam Neck  File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	08/23/1990
From:	Baranowsky P Office of Nuclear Reactor Regulation
To:	Rossi C Office of Nuclear Reactor Regulation
References
OREM-90-021, OREM-90-21, NUDOCS 9008300034
Download: ML20059B733 (16)

Text

{{#Wiki_filter:, l August 23, 1990 l 'J' MEMORANDUM FOR: Charles E. Rossi, Director Division of Operational Events Assessment FROM: Patrick W. Baranowsky, Acting Chief Events Assessment Branch Division of Operational Events Assessment

SUBJECT:

THE OPERATING REACTORS EVENTS MEETING AUGUST 22, 1990 - MEETING 90-21 On August 22, 1990, we conducted an Operating Reactors Events meeting (90 21) l to -inform senior managers from NRR, ACRS, AE00, Comiiiisiion :taff, and regional offices of selected events that occurred since our hst briefing on August 8, 1990. lists the attendees. presents the significant elements of the discussed events. . contains reactor scram statistics for the weeks ending 08/12/90 and 08/19/90. tabulates one significant event which was. identified for input into the NRC performance indicator program and one event identified for long-term followup. Original signed by Patrick W. Baranowsky, Acting Chief Events Assessment Branch Division of Operational Events Assessment

Enclosures:

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? August 23, 1990 MEMORANDUM FOR: Charles E. Rossi, Director Division of Operational Events Assessment FROM: Patrick W. Baranowsky, Acting Chief Events Assessment Branch 1 Division of Operational Events Assessment

SUBJECT:

THE OPERATING REACTORS EVENTS MEETING AUGUST 22, 1990 - MEETING 90 21 On August 22, 1990, we conducted an Operating Reactors Events meeting (90 21) to inform senior managers from NRR, ACRS, AE00, Comission staff, and regional offices of selected events that occurred since our last briefing on August 8, 1990. Enclosure 1 lists the attendees. presents the significant elements of the discussed events. contains reactor scram stat 9 tics for the weeks ending 08/12/90 ) and 08/19/90. tabulates one sipificant event which was identified for input into the NRC performance indicator program and one event identified for long-term followup. Original signed by Patrick W. Baranowsky, Acting Chief Events Assessment Branch Division of Operational Events Assessment I

Enclosures:

As stated cc w/ Encl.: See Next Page DISTRIBUTION Central Fits EAB Reading File Circulating Copy, EAB Staff l MLReardon, EAB LKilgore, SECY 'LPDR V I l1 ) 0FC *EAB/DOEA' AC EAB ...... :...... /..... ::...: l.y uu t. A : NAME:MLRea/ don

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l ./ OFFICIAL RECORD COPY [ DOCUMENT NAME: TRANSMITTAL LETTER 08/22/90 l

1, CC* T.-Murley, NRR N. Le, NRR F. Miraglia, NRR E. Adensam, NRR W. Russell, NRR A. Wa.1g, NRR F.'Gillespie, NRR J. Stolz, NRR J. Partlow, NRR

5. Varga, NRR i

R. Wessman, NRR G. Laines, NRR D. Crutchfield, NRR J. Zwolinski, NRR i B. Boger, NRR . W. Travers, NRR J. Richardson, NRR A. Thadani, NRR j F. Rosa, NRR B. Grires, NRR F. Congel, NRR J. Roe, NRR T. Martin, RI 1 W. Kane, RI J C. Hehl, RI . S. Ebneter, RII L. Reyes, RI! B. Davis, RIII E. Greenman, RIII S. Collins, RIV R.D. Martin, RIV J.B.' Martin, RV R. Zimmerman, RV P. Boehnert, ACRS E. Jordan, AE00 T. Novak,~ AEOD L. Spessard, AE00 E. Weiss, AEOD S. Rubin, AEOD l M. Harper, AEOD s J. Dyer, EDO R. Newlin, GPA J. Cowan, INPO E. Beckjord, RES A. Bates, SECY l

ENCLOSURE 1 I LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (90-21) August 22, 1990 NAME ORGANIZATION NAME ORGANIZATION P. Boehnert ACRS N. Kadambi NRR/DOEA W. Haass NRR/RVIB R. Kendall NRR/00EA R, VanHouten SECY M. Case NRR/DLPQ D. Kern RI/DRP P. Baranowsky NRR/DOEA S. Yarth DRP R. Wessman DRP N. Wagner DST /CDLB E. Rossi NRR/DOEA R. Woodruff NRR/DOEA A. Wang NRR/DRPI B. Borchardt OEDO H. Berkow NRR/D8P + D. Becker NRR/DRP R. Pederson OE L. Norrholm OCM/KC D. Trimble OCM/JC V. Berearsya AEOD/DSP R. Lo PD 11-1 J. Partlow NRR/ADPR F d

NOTES 1. - PLANT SPECIPIC DATA BASED ON INITIAL REVIEW 0F 50.72 REPORTS FOR THE WEEK OF INTEREST. PERIOD IS MIDNIGHT SUNDAY THROUGH MIDNIGHT SUNDAY. SCRAMS ARE DEFINED AS REACTOR PROTECTIVE ACTUAT10t!S WHICH RESULT IN ROD MOTION, AND EXCLUDE PLANNED TESTS OR SCRA!!S AS PART OF PLANNED SHUTDOWN IN ACCORDANCE WITH A PLANT PROCEbuRE. THERE ARE 111 REACTORS HOLDING AN OPERATING LICENSE. 2. COMPLICATIONS: RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAUSE OF SCRAt!. 3. PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS. 4

• 0THER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONtENTAL CAUSES(LIGHTNING),SYSTEMDESIGN,ORUNKNOWNCAUSE.

OEAB SCRAll Of.TA Manual and Autonatic Scrans for 1986 ------------------ 461 Manual and Automatic Scrams for 1987 ------------------ 439 Manual and Automatic Scrams for 1988 ------------------ 287 Manual and Automatic Scrams for 1989 ------------------ 244 ManualandAutomaticScramsfor1990(YTD08/19/90)---127 t J ,7 a

- g - -.- 't; q 79 1 v. l- .L ~ ll -q - i.h,7 t OPERATING REACTORS EVENTS' BRIEFING 90-21 EVENTS ASSESSMENT BRANCH. LOCATION: 10B-11, WHITE FLINT W . EDNESDAY, AUGUST 22, 1990, 11:00 A,M. BRUNSWl(K UNIT!2 MSIV CLOSURE AT FULL P0,WER c3 (AIT) l HADDAM l'iCK-AUXIL'ARY FEEDWATER SYSTEM CONCERNS 1 + I

^ r 90-21 g1 j m 1 BRUNSWICK 2 0 -MSly CLOSURE AT FULL POWER (AITF AUGUST 19, 1990 LI -PROBLEM' SCRAM WITH DEGRADED PERFORMANCE OF SEVERAL VALVES ~(SRVs, RCIC,. 9 LFW), CAUSE VIOLATION OF PLANT PROCEDURE LED TO REACTOR TRIP. CAUSE OF VALVE FAILURES IS BEING INVESTIGATED, SAFETY SIGNIFICANCE THE NATURE OF THE PROBLEM MAY BE INDI:ATIVE OF A BREAKDOWN IN THE WORK CONTROL PROCESS, DISCUSSION o' ON 8/19/9G,-THE REACTOR WAS INADVERTENTLY SCRAMMED FROM 100%

POWER, l

'o A SINGLE TECHNICIAN WAS TESTING THE PRIMARY CONTAINMENT ISOLATION SYSTEM.ALTHOUGH TWO TECHNICIANS WERE REQUIRED, SUBSEQUENTLY, ANOTHER TECHNICIAN PROVIDED FALSE VERIFICATION .0F THE WORK, o CHANNEL B2 WAS TRIPPED BY THE TECHNICIAN BEFORE CHANNEL A2 WAS RESET,BY THE OPERATOR CAUSING THE MSIVs-TO CLOSE AND THE REACTOR TO SCRAM, i o REACTOR PRESSURE REACHED 1133 PSIG. HIGH PRESSURE AND LOW LEVEL SCRAM-SIGNALS WERE GENERATED, o LOW LEVEL ALSO CAUSED AN ATWS SIGNAL WHICH TRIPPED THE RECIRC PUMPS, o FIVE.SRVs' FAILED TO OPEN AND ONE FAILED TO INDICATE OPEN, .THREE WERE OUTSIDE THE 1% PRESSURE BAND, l AIT: YES l CONTACT: AL BELISLE, RII; R0GER WOODRUFF, NRR SIGEVENT: YES

REFERENCES:

10 CRS 50.72#s 19158 AND 19163. =

u- '~,..., BRUNSWICK 2 i2-90-21 o THE FEEDWATER STARTUP LEVEL CONTROL VALVE STUCK CLOSED ~ ~ RESULTING IN LOW REACTOR VESSEL WATER LEVEL, -o RCIC AND HPCI WERE USED TO CONTROL WATER LEVEL.. o ~THE RCIC THROTTLE VALVE WAS OPENED AND CLOSED SEVERAL TIMES AND FAILED ON THERMAL'0VERL0AD, o THE REACTOR VESSEL MAXIMUM C00LDOWN RATE IN THE BOTTOM HEAD AREA WAS 140 F/HR FOR APPROXIMATELY ONE-HOUR, 0 THE REACTOR WAS IN HOT SHUTDOWN TUESDAY A.M. (8/21/90), o SHUTDOWN COOLING WAS LOST FOR 20-MIN, WHEN AN AUXILIARY OPERATOR TRIPPED THE WRONG MG SET, o ADDIT 10tlAL RECENT CONCERNS: - FOLLOWING THE SCRAM 0F 8/16/90, REACTOR-LEVEL CONTROL PROBLEMS-WERE ENC 0UNTERED, TWO RHR VALVES FAILED ON-THERMAL OVERLOAD, THE MAXIMUM HEATUP RATE WAS 170.F/HR,' AND THE MAXIMUM C00LDOWN RATE WAS 140 F/HR, - THE REACTOR VESSEL DRAIN LINE IS PARTIALLY CLOGGED, - WATER HAS BEEN FOUND IN HPCI PUMP LUBE OIL, - THE PROCEDURE FOR SHUTDOWN COOLING HAS NEVER COVERED THE . CASE WHERE THE RECIRCULATION PUMPS ARE NOT RUNNING, - THREE MONTHS AG0,'0PERATORS FAILED'TO REQUAllFY, FOLLOWUP o THE'llCENSEE PLACED-THE TECHNICIANS ON ADMINISTRATIVE LEAVE AND FORMEP A SCRAM INVESTIGATION TEAM, o-THE REGICL DISPATCHED AN AIT, 1

90-21 a 1 HADDAM NECK AUXILIARY FEEDWATER SYSTEM CONCERNS AUGUST 20, 1990 t PEEEM o SEISMIC EVENT COULD POTENTIALLY RESULT IN LOSS OF ALL AUXILIARY FEEDWATER (AFW), o MANUAL.0PERATOR ACTION REQUIRED FOLLOWING AUTOMATIC INITIATION OF AFW TO ENSURE MINIMUM FLOW REQUIREMENTS ARE MET, CAUSE o THE TURBINE DRIVEN AFW PUMP STEAM ADMISSION VALVES OPEN T00 FAST,' CAUSING PUMP TRIP ON OVERSPEED, o FLOW CONTROLLER SETTING NECESSARY TO ACHIEVE MINIMUM REQUIRED FLOWRATE RESULTS IN TRIP 0F AFW PUMP TURBINES ON.0VERSPEED, 4 SAFETY SIGNIFICANCE o SEISMIC' EVENT COULD LEAD TO A LOSS OF ALL FEEDWATER (MAIN .FEEDWATER AND AUXILIARY FEEDWATER), o SIGNIFICANCE OF-LOW-FLOWRATE APPEARS MINIMAL; STILL BEING

EVALUATED, i

DISCUSSION o HADDAM NECK AFW SYSTEM DESIGN IS UNIQUE; TWO SAFETY-RELATED TURBINE. DRIVEN AFW PUMPS AND ONE NON-SAFETY MOTOR DRIVEN-PUMP, o THE AIR SUPPLY LINES TO THE TURBINE DRIVE AFW PUMP STEAM ADMISSION VALVES ARE NOT SEISMICALLY QUALIFIED, o GROSS FAILURE OF 12-INCH SECTION OF THE STEAM ADMISSION VALVE-CONTROL AIR LINE (DOWNSTREAM 0F Tile AIR PRESSURE REGULATOR) CAUSES VALVE TO OPEN IN LESS THAN 2-SECONDS. THIS RESULTS IN AFW PUMP TURBINE OVERSPEED TRIP, BOTH TURBINE DRIVEN PUMPS ARE AFFECTED, i o PLANT WILL REMAIN BELOW 10% REACTOR POWER PENDING NRR APPROVAL OF CORRECTIVE ACTIONS TO RESOLVE PROBLEM, CONTACT: RICK KENDALL, NRR SIGEVENT: TBD

REFERENCES:

10 CFR 50,72 #19162

t a } o HADDAM'NECKL -90-21 01 NO APPARENT GENERIC IMPLICATIONS, o 'THE MAXIMUM FLOW RATE ACHIEVABLE ON AUTOMATIC INITIATION WITHOUT RESULTING IN POTENTIAL OVERSPEED TRIP 0F-THE AFW PUMP TURBINES'IS 240 GPM: MINIMUM REQUIRED FLOW IS 268 GPM, AFW FLOW CONTROLLER MUST BE ADJUSTED BY OPERATORS FOLLOWING INITIATION TO ATTAIN DESIRED FLOW, FOLLOWUP REGION 1.AND NRR (PROJECT MANAGER, PLANT SYSTEMS BRANCH, HUMAN FACTORS ENGINEERING BRANCH) ARE MONITORING-THE LICENSEES RESPONSE AND WILL EVALUATE FINAL CORRECTIVE ACTIONS, 3 f \\ j l l l

4, <[* .'HADDAM NECK- . 3 90-21;- 4 -,q '7.2 TUR8INE DRIVEN A N PUMP STEAM supply l I -i 1 M t4 () g sep : p,- kNW%N ~; Qe' + Mb / it jj <%. i - N s o-- _o v.t.. ! s. __ g /- ms tui.iu a m., m wY-I%'k MS-W qp 19 eft db g ms-w Wl#% Pat %C () h 'I* ' "th afjuv = .s., m -s v ius. t tT44s eh g, t ) -i 't

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L' REACTOR OCRM BUMMRY NEEKEN01E)08/19190 1.PLANTSPECIFitDATA .= / 9 ATE $1TE. UNIT PONER $16NAL CAUSE COMPLI-YTD Yil YTD / CA110NS AB0VE DELON TOTAL 151 151 08/11/90'HADDM NECK 1 0M EQUIPMENT NO 0 1 1 08/13/90210N. 1 95A PERSONNEL NO 2 0 2 08/14/90 PALD VERM 1 ' 65 A EDUIPMENT le 1 0 1 06/16/90BRUN5 NICK 2 100 A EDUlPMENT NO 1 1 2 -08/1T/90 SALEM-1 26 A EQUIPMENT NO 2 1 3 08/19/90 SYRf"~ 76A EDUlPMENT NO 2 0 2 08/19190 NINL !LE POINT 1 22 M EDU! PENT NO 2 0 2 08/19/90 BRUNSNICK 2 100 A EQUIPENT NO 2 1 3 + / REACTOR SCRM

SUMMARY

NEEKEEING 08/12/90

1. PL MT SPECIFIC HTA Hit -

$1TE UNIT PONER SISNAL CAUSE COMPLI-YTD Y10 YTD CA110NS AB0VE 9ELON TOTAL 151 151 08/06/90 NINE MILE POINT 1 20M EQUIPMENT NO 1 0 1 Hl08/90 COMMCHE PEAK 1 17A EDUIPENT . N0 3 1 4 08/09/90 TROJM 1 100A PERSouEL NO 1 0 1 08/12/90 IURKEY POINT 4 100 A EDUlPENT NO 2 1 3

II. COMPARISON OF WEEKLY STATISTICS.WITH INDUSTRY AVERAGEE SCRAMS FOR WEEK ENDING~ o ,4 a 08/19/90' SCRAM.CAUSEL POWER NUMBER 1990 1989: '1988 19871 1986 OF WEEKLYf WEEKLY. WEEKLY.~ WEEKLY' WEEKLY-SCRAMS (5)- AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE YTD- -(3)(4)

• • LPOWER >15%

EQUIP. RELATED' >15% 6 3.2 2.9 3.1 3.9' 4.3 PERS. RELATED(6) >15% i O.5 1.0 1.0 1.3 1.8 ? OTHER(7) >15% 0 0.0 0.1 0.5 1.2-O.4-

• • Subtotal **

7 3.7 4.0 4.6 6.4 6.5 Jet POWER <15%' EQUIP.'RELATED <15% 1 0.4 0.4 0.5 1.2 -1.4' PERS. RELATED <15% 0 0.1

0. 'c O.3 0.6 0.G

'OTHER <15% 0. 0.0 0.7' O.1 0.3 0.2-

• • Subtotal **

1 0.5

1. 4' O.9 2.1

'2. 4, ' *** Total *** 8 4.2 5.4 5.5 9.5 '8.9 [ MANUAL VS AUTO SCRAMS 1 TYPE NUMBER -1990 1989 1988 1987 1986 OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAh5 AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE .YTD MANUAL SCRAMS 2 1.1 0.9 1.0 - 1. 4 1.0- . AUTOMATIC SCRAMS-6 3.1 3.8 4.5 7.0 7.9 l t

~ ^ W 4,. 9 II4 COMPARICON!OF WEEKLY-STATISTICS WITH INDUSTRY: AVERAGES 9-1 E SCRAMS FOR WEEK ENDING. 5 08/12/90'- . p. 4- -CCRAM~CAUSE. POWER. NUMBER 1990 1989 1988-1987 1986-i

r. ~,i OF-WEEKLY WEEKLY ~. WEEKLY.- WEEKLY-WEEKLY-l SCRAM 9f5)-

AVERAGE. AVERAGE-AVERAGE AVERAGE AVERAGE. ~t YTD (3)(4) I ] >4* POWER >15%

EQUIP. RELATED

->15%- 3 3.1 2.9 3.1 3.9 4.3. .PERS. RELATED(6) >15% 1~ O.5-1.0 1.0 1.3

1. B.'

• ~OTHER(7)

>15% 0 0.0 0.1 0.5 1~.2 0.4

• • Subtotal **-

5> c-4 3.6 4.0 4.6 6.4 6.5 - ** POWER ~<15% .EQUIPLRELATED <15% 0 0.4 0.4 _ O. 5 1.2 1.4 ~ -FERS.sRELATED. <15% 0 0.1 - 0.3 0.3 0.6 -0.8 OTHER. . <15% 0-0.0 0.7 0.1 0.3 0.2 [~ **cSubtotal ** O O.5-1.4 0.9 2.1 2.4

• • • Total-***

4 4.1 5.4 5.5-8 '. 5 8.9. i \\ MANUAL-VS AUTO SCRAMS TYPE NUMBER 1990 1989-- 1988 1987 1986 OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE YTD MANUAL' SCRAMS 1 1.1 0.9 1.O 1.4. 1.O

AUTOMATIC SCRAMS 3

3.0-3.8 4.5 7.0 7.9-I a I n

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