ML20207M077

Summary of Operating Reactors Events Meeting 88-39 on 881004.List of Attendees & Viewgraphs Encl

ML20207M077
Person / Time
Site:	Oyster Creek, Surry, Vermont Yankee, 05000000
Issue date:	10/05/1988
From:	Jaudon J Office of Nuclear Reactor Regulation
To:	Rossi C Office of Nuclear Reactor Regulation
References
OREM-88-039, OREM-88-39, NUDOCS 8810180093
Download: ML20207M077 (16)

Text

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OCT e g q MEMORANDUM FOR: Charles E. Rossi, Director Division of Operational Events Assessment FROM: Johns P. Jaudon. Acting Chief Events Assessment Branch Division of Operational Events Assessment

SUBJECT:

THE OPERA 11NG REACTORS EVENTS MEETING October 4, 1988 - MEETING 88-39 On October 4, 1988, an Operating Reactors Etents meeting (88 39) was held to brief senior managers from HRR, OSP, AE00, RES, Commission Staff, and Regional Offices on events which occurred since our last meeting on September 27, 1988.

The list of attendees is included as Enclosure 1.

The events discussed and the significant elements of these events are presented in Enclosure 2. Enclosure 3 presents a report-to-date of long-term followup assignments and a summary of reactor scrams. One significant event was identi.

fied for input to NRC's performance indicator program. One event was suggesteo for long. term f ollowup.

Johns P. Jaudon, Acting Chief Events Assessment Branch Division of Operational Events Assessment

Enclosures:

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ogi t1 W MEMORANDUM FOR: Charles E. Rossi, Director Division of Operational Events Assessment FROM: Johns P. Jaudon, Acting Chief Events Assessment Branch Division of Operational Events Assessment

SUBJECT:

THE OPERATING REACTORS EVENTS MEETING October 4, 1988- MEETING 88-39 On October 4, 1988, an Operating Reactors Events meeting (68-39) was held to brief senior managers from NRR, OSP, AE00, RES, Commission Staff, and Regional Offices on events which occurred since our last meeting on Septerrber 27, 1988.

The list of attendees is included as Enclosure 1.

The events discussed and the significant elemerits of these events are presented in Enclosure 2. Enclosure 3 presents a report-to-date of long-term followup assignments and a sunnary of reactor scrams. One significant event was identi-fied for input to NRC's performance indicator program. One event was suggested for long-term followup.

M M Johns P. 6J n, Acting Chief Events Assessment Branch i

Division of Operational Events Assessment

Enclosures:

As stated I

4 cc w/ Encl.:

See Next Page

. ENCLOSURE 1 L

LIST OF ATTENDEES OPERATINGREACTORSEVENTSBRIEFING(88-39}

October 4, 1988 NAME ORGANIZATION NAME ORGANIZATION J.P. Jaudon NRR/00EA C.S. Schulten NRR/00EA D. Fischer NRR/00EA T. Greena NRR/00EA i P. Baranowsky NRR/00EA C.E. Rossi NRR/00EA J. Sniezek NRR/00NRR S. Varga NRR/DRP G. Lainas NRR/ADR2 L. Norrholm NRR/RSIB '

4 W. Troskoski E00 H.N. Berkow NRR/PD22 '

J. Donohen 05P b.A. Boger NRR/ADR1 S. Juergens SECY l

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. NOTES

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1. PLANT SPECIFIC DATA BASED ON INITIAL REVIEW 0F 50.72 REPORTS FOR THE WEEK OF INTEREST. PERIOD IS MIONIGHT SUNDAY THROUGH i MIONIGHT SUNDAY. SCRAMS ARE DEFINED AS REACTOR PROTECTIVE '

ACTUATIONS WHICH RESULT IN R00 NOTION, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE WITH A PLANT PROCEDURE. THERE ARE 109 REACTORS HOL0thG 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 DEFICIENCIES, AND MAh0AL STEAM GENERATOR LEVEL CONTROL PROBLEMS.

4. "0THER" !NCLUDES AUTOMATIC SCRAltS ATTRIBUTED TO ENVIRONNEhTAL CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.  ;

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OPERATiliG REACTORS EVENTS BRIEFING 88-39.

EVENTS ASSESSMEllT BRANCH LOCATI0lh 12-B-11 WHITE FLil1T IUESDAY, OCTOBER 4, 1988, 11:00 A.M.

SURRY 2 UPDATE- THINN1f1G OF MAlh FEEDWATER PIPING VERfioliT YANKEE 1 FIRE SUPPRESSION SYSTEM INOPERAEILITY OYSTER CREEK LOSS OF SHUTLOWfi COOLING EVEliTS e

88-39

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.SURRY 2 UPDATE-THINNING OF MAIN FEEDWATER PIPING SEPTEMBER 26, 1988 PROELEM THIfit; LNG 0F PIPING IN THE SECONDARY SYSTEM IS OCCURRING MORE RAPIDLY THAN EXPECTED AT SOME LOCATIONS fAU.Sf EROSION / CORROSION ,

l SIGNIFICANCE FAILURE OF PIPING BETWEEN THE STEAM GENERATOR fiO22LE AllD THE

JUNCTIOh 0F AUXILIARY AliD MAIN FEEDWATER PIP! fig WOULD CAUSE LOSS OF i

SAFETY-RELATED AUXILIARY FEEDWATER ,

DISCUSS.L0li c ON SEPTEMBER 26, 1988, THE REGION ISSUED A PN STATING THAT Oft  ;

OR AbCUT THAT DATE, THINNihG WAS DETECTED DURING AN INSPECTION o 8 COMP 0NENTS RECulRED REPLACEMENT (3 WERE NEW IN 87) o 3 0F THE COMP 0flEtiTS HAL WALL THICKNESSES THAT WERE LESS THAf; MlhlMUM CODE ALLOWABLE. 2 WERE IN TiiE LOOP SEAL TO STEAM GEf;ERATOR B. 1 WAS Ili THu C0flDENSATE RECIRCULATION PIPlfiG.

i o 5 COMPONENTS HAD THINillNG RATES GREATER thall EXPECTED, BUT WALL THICKNESSES WERE GREATER THAN MINIMUM CODE ALLOWABLE. THESE l COMPONENTS WERE If; THE LOOP SEAL TO STEAM GEf1ERATOR A, ON THE

SUCTION SIDE OF EOTH MAIN FEEDWATER PUMPS, 'll THE FEEDWATER DRAlli PIPING, AND IN A MAIN STEAM PIPE.

j o THERE ARE 4 ELB0WS !!4 EACH STEAM GENERATOR LOOP SEAL. 3 0F .12 l THINNED MORE RAPIDLY THAN EXPECTED. THE REMAINDER THINNED AT THE RATE EXPECTED.

i o A CHROME MOLY TEST ELBOW IS BEING INSTALLED IN A LOCATION WITil A HIGH THINNiliG RATE.

0 EROSION WAS ALSO FOUND IN Tile SWIRL VANE SEPARATORS OF THE ONE j STEAM GEliERATOR TH/.T WAS INSPECTED.

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88 39 2

o THE LICENSEE PUT A PRELlhlNARY NOTICE Off THE INP0 NETWORK RE ACCELERATED THINNING o THE LICENSEE DOES liOT CONSIDER THINNIfiG OF THE MAIN FEEDWATER LitiE BETWEEN THE STEAM GENERATOR fiOZZLE AND THE JUNCTION OF THE AUXILIARY FEEDWATER LINE TO BE REPORTABLE UfiDER 50.72 EDLLDSUE NRR IS C0flSIDERING THE fiEED T0 ISSUE A SUPPLEMENT TO PREVIOUS GEf1ERIC COMMutilCATIONS. THE REG 10ft IS REVIEWIi!G THE REPORTABILITY CUEST10fl.

CONTACT: R. WOODRUFF (301) 492-1180 REFEREliCE: Pf:0-Ril-88-61, 9/26/66

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- VERMONT YANKEE 1 FIRE SUPPRESSION SYSTEM IN0PERABILITY "

SEPTEMBER 28, 1988 PROBLEM BOTH CARBON DIOXIDE (CARD 0X) FIRE SUPPRESSION SYSTEMS FOR THE SAFETY RELATED SWITCHGEAR P00M AND THE CABLE VAULT WERE IN0PERABLE l t

fAllSE BOTH DETECTION AND ACTUAT10fl CIRCulTS CONNECTED TO COMFON POWER

~ SOURCES SAFCT_YJJ GNIFIC ANCE ,

PLANT Ill AN UNANALYZED CONDITION WITH NO AUTOMATIC FIRE SUPPRESSION i SYSTEM FOR SWITCHGEAR ROOM AND CABLE VAULT l

])JSCUSSION j o PART OF THE DETECTION SYSTEM CONSISTS OF THE FIRE PROTECTIVE PANEL, WHICH IS DESIGNED FOR 4 AMP. THE POWER SUPPLY CIRCUlT 5

CONTAINS A 2 AMP FUSE. l

o THE ACTUATI0ft CIRCulT REQUIRES ABOUT 5 AMPS TO ACTIVATE DAMPER IN VENTILAT10li SYSTEM AND TO OPEN VALVES IN CARD 0X SYSTEM o FIRE SUPPRESSION SYSTEM BECAME Ifl0PERABLE WHEN THE 2 AMP FUSE BLEW DURING SURVEILLANCE TESTlfiG BECAUSE BOTH DETECTION AND ACTUATION CIRCUlTS WERE CONilECTED TO COMMON POWER SOURCE o SYSTEM HAS WORKED IN PAST, HOWEVER, SOMETIMES THE 2 AMP FUSE I' BLEW AFTER VALVES WERE OPEN

o LICENSEE IMMEDIATELY ESTABLISHED A CONTINUOUS FIRE WATCH

, o LICENSEE MODIFIED SYSTEM BY ESTABLISHING SEPARATED POWER SUP' PLIES FOR DETECTION CIRCUlT AllD ACTUAT10f1 CIRCulT l 0 F_LLOWUE i o EAB WILL CONTINUE TO FOLLOWUP TO DETERMINE At1Y GENERIC IMPLICAT10flS j CONTACT: T. GREEhE (301) 497-1176

REFERENCE:

Eli 13566 AND MR SEPTEMBER 29, 1986

88-39

. OYSTER CREEK (BWR/2, MARK 1)

LOSS OF SHUTDOWN COOLING EVENTS SEPTEMBER 29, 1988, OCTOBER 2, 1988 .

PROBLEM Oli SEPTEMBER 29, THE PLAliT WAS SHUTDOWil AND AN UtiUSUAL EVENT DECLARED AS A RESULT OF BOTH THE "A" AfiD "B" ISOLAT1011 CONDENSERS BEING DECLARED INOPERABLE ON OCTOBER 2, A FAULTED BUS RESULTED 111 THE LOSS OF HALF 0F ALL ECCS AliD SHUTDOWN C00LiliG WITH REACTOR IN SPHTDOWN AT ll48'F Ch1\SE 1 Ol4 SEPTEMBER 29, WATER "1.0WED FROM THE "B" ISOLATION CONDENSER STEAM

, VENT LINE INTO THE "A" ISOLAT10h CONDENSER VEllT LINE VI A A PATHWAY THAT IS NOT FULLY UNDERSTOOD. ON OCTOBER 2, A DIESEL GENERATOR CABLE FAULTED.

hAFETY SIGNIFICANCE SEPTEMBER 29, 1988 THIS COULD RESULT lh A TUBE RUPTURE IN THE ISOLATION CONLENSERS IF ISOLATION SHUTDChN C00LIh6 WERE REQUIRED. WITHOUT THE ISOLATIGh 3

C0hDENSERS, SilVTLOWri COOLING WOULD RE0VIRE USE OF Tile ADS SYSTEM AllD THE CORE SPRAY SYSTEM TAKING SUCTION ON THE CST PR SUPPRESSION P00L.

OCTOBER 2, 1988 THE CABLE FAULT HAMPERED SHUTDOWN C00LillG OPERAT10flS BECAUSE 2

OUT OF 3 RHR LOOPS WERE WITHOUT POWER. RCS TEMPERATURE INCREASED 9'F j

TO 159'F. LOSS OF OliLY OliE PUMP (ESW, CCW OR SHUTDOWN COOLING) WOULD LOSE ONLY AVAILABLE SHUTDOWN COOLING LOOP.

RISDJSSIDE l SEPTEMBER 29, 1988 0 DURING Ah AUTO ISOLATION SURVEILLAliCE CAllBRAT10!i (9/26) 0F THE "A" l

!' ISOLATION CONDEllSER OPERATORS NOTED THAT THE "A" ISOLATION CONDENSER WAS STEAMlhG SLIGHTLY AND TilAT SHELL TEMP AND TUBE DIFFEREtiTIAL TEMPERATUkES WERE ELEVATED. "B" ISCLATION

! CONDENSER HAS BEEli STEAMING SlhCE AUGUST 28TH.

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88-39

. 2 o IT WAS REPORTED THAT STEAM HAD CONDENSED, SUCKING WATER INTO THE "B" ISO CONDENSER FOLLOWlh6 MAINTENANCE. THIS LINE CONNECTS TO THE STEAM VENT LINE OF THE "A" ISO CONDENSER BEFORE EMPTYING lhTC THE MAlU STEAM LINE. APPARENTLY, DURING SURVEILLANCE OF THE "A" ISOLATION CONEENSER ISOLATION FUNCTION, WATER FROM THE "B" ISOLATION CONDENSER FLOWED INTO THE "A" ISOLATION CONDENSER VIA STEAM VENT LINE.

o BOTH THE "A" AND "B" ISOLATION CONDENSERS WERE DECLARED OUT-0F-

SERVICE (9/29) 0 REACTOR C00LlHG FOLLOWING A REACTOR SCRAM AND ISOLATION i IS kORMALLY ACCOMPLISHED USING AN ISOLATION CONDENSER o ISO CONDENSERS ARE BACKED UP BY 5 ADS VALVES AND TWO LOOPS OF CORE SPRAY, OCTOBER 2, 1988 o FAULT ON THE "B" 4100 VOLT EMERCENCY BUS CAUSED THE LOSS OF ALL "B" VITAL POWER

! c THE "B" ENERGENCY DIESEL GENERATOR FAILED TO START. RCS TEMP INCREASED 9 DEGREES F TO 159 DEGREES IN ONE hCUR DUE TO THE i 1 0F 2 NON-SAFETY SHUTDOWN COOLING LOOPS BEING WITHOUT POWER.

O RCS COOLED OFF TO 156 DEGREES F AND MAINTAINED WITH ONE I.00P l

, o CYSTER CREEK TECHNICAL SPECIFICt.TIONS DO NO REQUIRE ONS'.TE l GENERATION CAPAEILITY DURING SHUTDOWN [

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88-39 FOLLOWUP o THE REG 1011 SECTION CHIEF, RESIDEtiT INSPECTOR, REG 10ti I INSPECTION SPECI ALIST AfiD AN f1RR ENG! FLEER ARE O!1 SITE REVIEWillG THE CAUSE AND POTEllTIAL CONSEQUEliCES OF THE FLOODED STEAM VENT LINE o PROJECT EflGINEER OBSERVED LICEf; SEES TROUBLE SHOOTING 8 RESTORATION OF THE "B" 4100 VOLT BUS o REGION WILL REVIEW LICEtiSEE EVALUATI0t' :.F THE CABLE FAULT CONTACT: C. SCHULTEli (301) 492-1192

REFERENCE:

50.72 #13576, Pfl0-I-88-99 313603

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II. COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES SCRAMS fos WEEK ENDING 10/02/88 L ' ' SCRAM CAUSE

• POWER NUMBER 1988 1987 1986 1985 f

OF WEEKLY WEEKLY WEEKLY WEEKLY SCR!.MS( 5 ) AVERAGE AVERAGE AVERAGE AVERAGE YTD (3)(4) (8)(9) oc DOWER >15%

EQUIP. RFI,ATED >15% 0 3.0 3.9 4.3 5.4 PERS. RELATED(6) >iS4 2 1.0 1.3 1.8 2.0 OTHER(7) >154 0 0.7 1.2 0.4 0.6 C* Subtotal **

2 4.7 6.4 6.5 8.0 c4 POWER <15%

EQUIP. RELATED <15% 1 0.7 1.2 1.4 1.3 PERS. RELATED <15% 0 0.4 0.6 0.8 0.9 OTHER <15% 0 0.2 0.3 0.2 0.2 00 Subtotal **

1 1.3 2.1 2.4 2.4 o*o Total ***

3 6.0 8.5 6.9 10.4 .

MAdUAL VS AUTO SCRt.

TYPE HUMBER 1988 1987 1986 1985 0F WEEKLY WEEKLY WEEKLY WEEKLY SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE '

YTD MANUAL SCRAMS 2 1.0 1.4 1.0 1.0 AUTOMATIC SCRAMS 1 5.0 7.0 7.9 9.4 l

1110f08SClil50EE111 IIIIIID!l310/0!/18 1.FLilt$PIClfl0!!!!

ffD ffD Cit! $lt! tilfPCVil$1GiltCALSI CCIPLl- if0 Cifl013 11011 IILCW f0 fit lil !!!

19/11/88I!!CI 1 15I IQO!!Ilif 10 4 1 5 11,29/18 Citival . 40I FilSCillL TIS 1 1 C 68/29/11111111000 2 18i Fil50llik 10 1 ( 11 1

$C1111fOfC0tiLICifl0ll lift Cilf C0tfLICifl015 Cit!W !Fillf'll 111011DfaFIflClfitIlliGil.Stif01C00LilfFIEFC195110iLOW5fif01 000Liitfil55C01).VilCItilfilfl0ifDillitllillCIfl01131POVilTO411P0til.

Fu C01'30L FinlLIIS ItQDillD E110lt fil? (1970 lliCf01 fIlf 18 ILOCIID llLOV lit K4Ils .

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