ML19332D282

Summary of Operating Reactors Events Meeting 89-040 on 891115

ML19332D282
Person / Time
Site:	Point Beach, Zion, 05000000
Issue date:	11/16/1989
From:	Haughney C Office of Nuclear Reactor Regulation
To:	Rossi C Office of Nuclear Reactor Regulation
References
OREM-89-040, OREM-89-40, NUDOCS 8911300263
Download: ML19332D282 (15)

Text

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November 16, 19891

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-Charles'E. Rossi, Director MEMORANDUM FOR:

Division of Operational Events Assessment FROM:

Charles J. Haughney, Chief 4

2 Events Assessment Branch Division of Operational Events Assessment

SUBJECT:

.THE OPERATING REACTORS EVENTS MEETING November 15,-1989 - MEETING 89-40 s

On November 15; 1989, we conducted an Operating Reactors Events meeting (89 40).to brief senior managers from NRR, AE0D,'ACRS, Commission staff, and_ regional offices on selected events that occurred since our last meeting on November 8,1989. - Enclosure 1 lists the attendees.

Enclosure.2 presents the significant elements of the discussed events. contains a sumary of reactor. scrams for the weeks ending 11/05/89 and 11/12/89. Welidentified five significant events for input into the NRC performance indicator program.critdr:1:Za6d W t ChrRL J. HaldLW p

Charles J. Haughney, Chief.

Events Assessment Branch Division of Operational Events Assessment J

Enclosures:

-As-stated cc w/ Encl.:-

-See Next Page.

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November 16, 1989-

'MEMORA'DUM FOR:

Charles ~E. Rossi, Director N

Division of Operational Events Assessment f

FROM:

Charles J. Haughney, Chief Events Assessment Branch Division of Operational Events Assessment

?

SUBJECT:

THE OPERATING REACTORS EVENTS MEETING November 15 1989 --MEETING 89-40 i

On November 15, 1989, we conducted an Operating Reactors Events meeting (89-40)tobriefseniormanagersfromNRR,AEOD,ACRS,Commissionstaff, and regioral offices on selected events that occurred since.our last meeting on November 8, 1989. lists the attendees.

' presents.the significant elements'of the discussed events. contains:a summary of reactor scrams for the weeks ending 11/05/89 and 11/12/89. We identified five significant events for' input-

.into the NRC performance indicator program.

(

f Events Assa" at h,d (..

Charles'J. H hney, Chie g

Division of Operational Events Assessment

Enclosures:

As stated cc w/ Encl.:

See-Next Page i

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,7 ENCLOSURE 1-1 tjc-j

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.[151 0F' ATTENDEES

-H OPERATIt1G' REACTORS EVENTS BRIEFING (89-40)

)

November 15, 1989 p

o NAME ORGANIZATION NAME-ORGANI2ATION:

0.:Trimble.

OCM/JC E. Rossi ilRR/DOEA

C.-Patel' ilRR/DRSP P. Bobe AE0D/DSP..

C. haughney NRR/E0EA R. Borchardt-OEDO '

W.-Troskoski OE L. Plisco NRR/DONRR R. Aulock-tsRP,/TVA

'L. Norrholm OCM/KC R. Kursch NRR/DOEA' P. Barcoowsky HRR/DOEA s

R. Perfetti OE H. Alderman ACRS W, Swenson:

NRR/PD3-3 R. Hermann NRR/ ENTE t

R. Ber. edict-NRR/00EA-A. Gilbert NRR/D0EA.

C. Thon.as NRR/DLPQ-J. Partlow hRR/ADP f,. F.ischer NRR/00EA M. Reardon-NRR/DOEA R. Kendall-

-NRR/DOEA D. Brinkman NRR/PD1-1

.lb Hum-NRR/EMCC

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a OPERATING REACTORS EVENTS BRIEFING 89-40

-EVENTS ASSESSMENT BRANCH.

LOCATION:

~16B-11=, WHITE FLINT I

WEDNESDAY, NOVEMBER 15, 1989, 11:00 A.M..

l, POINT BEACil UNITS 1 s 2 125 VDC SYSTEM CIRCUIT BREAKER DESIGN PROBLEM-

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ZION = UNIT 41 STEAM' GENERATOR CRACKING IN TRANSITION CONE TO UPPER 9

SHELL GIRTH WELD l

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89-40 e

t POINT BEACH UNITS 1 8 2 125-VDC SYSTEM CIRCUIT BREAKER DESIGN PROBLEM NOVEMBER 7, 1989 PROBLEM 125 VDC SYSTEM LOAD FAULTS COULD CAUSE DAMAGE TO STATION BATTERIES, j

CAUSE-CIRCulT BREAKERS.D0 NOT HAVE INSTANTANE0US TRIP DEVICES TO PROVIDE o

CIRCUlT PROTECTION AGAINST HIGH AMPERAGE SHORT DURATION FAULTS, 3

SAFETY SIGNIFICANCE--

INABILITY TO CLEAR OR ISOLATE FAULTS CAN RESULT IN DEGRADATION OF MULTIPLE SAFETY RELATED CIRCUITS / EQUIPMENT, FAULTS IN NON-SAFETY.

d RELATED CIRCUITS CAUSED BY A SEISMIC EVENT'COULD POTENTIALLY AFFECT REDUNDANT SAFETY RELATED EQUIPMENT.

DISCUSSION

-o.

FOUR' BATTERIES ARE SHARED BETWEEN TWO UNITS, o

TW6 BATTERIES (D105 8 D106) ARE DEDICATED TO "TMI LOADS",

THE REMAINING TWO BATTERIES (DOS 8 D06) PROVIDE POWER USED FOR i

-ACTUATION LOGICS AND CIRCUIT BREAKER CONTROL.

3 o

LICENSEE DISCOVERED THAT INSTANTANE0US (MAGNETIC OVERLOAD)

PROTECTION WAS-MISSING FROM THE BREAKERS ASSOCIATED.WITH 005 AND D06 DURING THEIR SELF-INITIATED SSFI 0F THE ELECTRICAL SYSTEM.

o THE-PLANT DESIGN BASIS REQUIRES'THAT EITHER BATTERY DOS OR D06 BE CAPABLE OF SUPPLYING ACCIDENT LOADS IN EITHER UNIT AND SHUTDOWN LOADS-IN THE OTHER UNIT, o

BATTERIES-DOS AND D06 SUPPLY NON-SAFETY AS WELL AS SAFETY RELATED LOADS.

THE LICENSEE BECAME CONCERNED THAT A SEISMIC

~

EVENT COULD GENERATE FAULTS IN THE NON-SAFETY LOADS THAT COULD

. ADVERSELY AFFECT BOTH BATTERIES (CABLE TRAYS FOR NON-SAFETY CABLES ARE NOT SEISMICALLY SUPPORTED),

CONTACT:

R. KENDALL SIGEVENT:

YES

REFERENCES:

10 CFR 50.72 # 17036

y 3

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- POINT BEACH UNITS 1 8-2

. 89-40

'iL o

CIRCUIT BREAKERS.FOR NON-SAFETY RELATED LOADS WERE REPLACED WITH BREAKERS HAVING INSTANTANE0US TRIP DEVICES, OR THE LOADS

-WERE DISCONNECTED FROM THE BATTERIES.

HOWEVER, CONCERNS 1

REMAIN REGARDING THE LACK 0F INSTANTANE0US TRIP DE/ ICES IN BREAKERS THAT-SUPPLY POWER TO SAFETY RELATED LOADS.

o NRC HAS-REQUESTED-THE LICENSEE TO CONFIRM THROUGH ANALYS1S i

THAT FOR ACCIDENT CONDITIONS AT EITHER UNIT (INCLUDING-THOSE INVOLVING LOSS OF 0FFSITE POWER) AND FOR STATION BLACK 0UT, THAT EITHER DOS OR D06 CAN SUPPLY THE NECESSARY ACCIDENT AND SHUTDOWN LOADS GIVEN A SINGLE FAILURE OF Tile OTHER BATTERY.

o ALL FOUR BATTERIES'ARE NEW.

THE LICENSEE HAS RECENTLY~ COMPLETED A LOAD ANALYSIS WHICH THEY BELIEVE DEMONSTRATES ADEQUATE CAPACITY OF THE-BATTERIES.

- o PROBLEM APPEARS T0'BE PLANT SPECIFIC, F0LLOWUP..

THE LICENSEE IS INVESTIGATING TO DETERMINE (1) THE BASIS FOR INSTALLING. BREAKERS'WITHOUT MAGNETIC OVERLOAD TRIP DEVICES,.AND (2).WHAT DESIGN CHANGES MAY BE NECESSARY TO PROVIDE ADEQUATE FAULT PROTECTION.

DESIGN CHANGES WILL BE REVIEWED BY THE ELECTRICAL SYSTEMS BRANCH.

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89-40 ZION UNIT 1

. STEAM GENERATOR CRACKING IN TRANSITION l CONE TO UPPER SHELL GIRTH WELD

^

OCTOBER 22, 1989

' PROBLEM:

t SURFACE:AND SUBSURFACE CRACK INDICATIONS WERE FOUND.BY ULTRASONIC TESTING (UT)'0F THE TRANSITION CONE TO Tile UPPER SHELL GIRTH WELD

'a (GIRTH WELD) 0F THE STEAM GENERATOR.

CAUSE UNKNOWtl SAFETY SIGNIFICAN'CE SIGNIFICANT STEAM GENERATOR (SG) SHELL CRACKING IS OF PARTICULAR~

CONCERN SINCE AlSG-BREAK IS AN UNANALYZED EVENT.

ALSO, THIS IS THE SECOND FINDING OF SIGNIFICANT SG CRACKING IN THE LAST 6 MONTHS.

DACKGROUND

o-ON APRIL 15, 1989, WHILE IN REFUELING, THE LICENSEE FOR INDIAN f

. POINT:2 DISCOVERED A TOTAL:0F-ABOUT 290 CRACKS IN THE INNER.

CIRCUMFERENCE OF TiiE SG GIRTH. WELD.

THESE CRACKS WERE UP T0-1,42 INCHES DEEP.

(THE SG WALL IS 3.5 INCHES THICK.)

o INTHEMOSTSEVERELYAFFECTED$G(SG"22"),THELICENSEESETA L

. MAXIMUM GRIND 00T DEPTH 0F 0.75 INCHES.

THEREFORE, GRIND 0VT L

DEPTtiS EXCEEDING 0.75 INCHES IN SG "22" UNDERWENT WELD-BUILDUP

~AND-POST-WELD-HEAT TREATMENT, Lo INDIAN POINT 2 HAS GROUND-0UT ALL THE CRACKS IN ALL 4 SGs AND THE UNIT RESTARTED IN: JULY 1989.

NO SG REPLACEMENT IS SCHEDULED

.AT THIS TIME.

o 0THER FINDINGS OF SG CRACKING INCLUDE SG LEAKAGE (THROUGH-WALL L

CRACKING) AT INDIAN POINT 3 IN 1982, AND SEVERE SG CRACKING o

-AT SURRY-1 AND 2 IN ]985.

-CONTACT:

A. P. GILDERT SIGEVENT YES

REFERENCE:

MORNING REPORT DATED 11/14/89

/s

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" ZION UNIT 1 89-40

.+

DISCUSSION.

l o

IN OCTOBER 1989, THE LICENSEE FOR ZION 1 PERFORMED UT OF THE GIRTH WELD AND DISCOVERED CRACK INDICATIONS IN ALL 4 SGs, THE' i

gL MOST SEVERE CASE BEING SG "1D."

o SURFACE AND: SUBSURFACE INDICATIONS WERE IDENTIFIED IN THE INNER

= i CIRCUMFERENCE 0F THE GIRTH WELDS.-

i 0-THE LICENSEE HAS GROUND-0VT THE SURFACE INDICATIONS WITHOUT WELD BUILDUP SINCE THE CRACK DEPTHS DID NOT EXCEED THE MINIMUM 1

i SG WALL THICKNESS.

THE GROUND-0UT AREAS WERE-UP TO 0.50 INCHES

- l DEEP.AND ABOUT 6-INCHES LONG.

o-THE LICENSEE IS INVESTIGATING THE NATURE AND EXTENT OF THE CRACK INDICATIONS.

FOLLOWUP

o THE LICENSEE HAS PROVIDED A TEST SPECIMEN FOR METALLURGICAL 4

ANALYSIS.

ONCE THE' LICENSEE HAS DETERMINED THE MECHANISM FOR CRACKING, THE MATERIALS >8 CHEMICAL ENGINEERING BRANCH (MTCB)

WILL BE ABLE TO DETERMINE GENERIC APPLICABILITY BASED ON THE LICENSEE'S FINDINGS.

WESTINGHOUSE HAS IDENTIFIED A ROOT CAUSE FOR THE INDIAN POINT 2 CRACKING.-' STRESSES APPLIED BY STANDING i

WATER-TRAPPED BETWEEN THE. DIFFUSER PLATE AND THE GIRTH WELD -

WHICH MAY APPLY TO ZION 1.

a o

IN THE WCAP-12293 ON THE INDIAN POINT 2 GIRTH WELD CRACKING, i

WESTINGHOUSE IDENTIFIED OTHER PLANTS'THAT HAVE A SIMILAR CONFIGURATION TO THE INDI AN P0lNT 2 SG AND COULD BE SUSCEPTIBLE TO GIRTH WELD CRACKING.

.o TWO INFORMATION NOTICES HAVE BEEN PUT OUT ON THIS

SUBJECT:

INFORMATION NOTICE 82-37 ON THE INDIAN POINT 3 GIRTH WELD LEAK AND INFORMATION NOTICE 85-65 ON THE SURRY GIRTH WELD CRACKING.

THE EVENTS ASSESSMENT BRANCH IS WORKING WITH MTCB TO PUT OUT AN INFORMATION NOTICE ON THE POTENTIAL SUSCEPTIBILITY OF PWRs T0 i

' GIRTH WELD CRACKING.

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_ ZION UNIT i:

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[ P0$1TIVE ENTRAINMEN STEAM DRYERS.

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SECONDARY MANWat y

swlRL VANE-UPPER SHELL Mol5TURE SEPARATOR $

c, V-i FEE 0 WATER N0ZZLE

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,1L 11/16/89 *

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, ENCLOSURE 3 PERFDRMANCEINDICATORS$16NIFICANTEVENTS o.

PLANT NAME' EVENT EVENT N SCRIPi!DN' GTR SIGNIFICANCE

^

- MTE b. CDMANCHE PEAK 1-

07/02/89 LEAKIN6' AIR BLOC 4 VALVES AND AIR START VALVES COULD CAUSE 0 PDTENilAL FOR OR ACTUAL DEGRALATION CADSE HMA6E TO DIESEL SENERATOR$; PROBLEM APPEARS 10 BE LOF SAFEff RELATED EDUlPMENT.

L BENERIC 10191 DIESELS.

iHESDEN21 10/23/99 LEAKABE OF FEELNATER INTO THE NPCI SYSTER THRU THE 0 PDTENiiAL FOR OR ACTUAL DE6RADAT10N i.

4 INJEti10N VALVES RESULTED IN HATER HAMMER AND THE OF SAFETY RELATED E00lPMENT.

FDIENTIAL OF THERMAL STRATIFICAi!DN AND STEAM IINDIN6.

P0lN1 RACH 1 & 2-11/bh39f;RCuliDREAKERSDONOTHAVE1KSTANTANFOUSTRIPDEVICES 0 P0fENilAL FOR OR ACTUAL DEBRADAtlok-10 PROVIDE CIRCUlT PROTEtilDN AGAINST HIGH AMPERA6E SHORT l,F SAFETY RELATED EQUIPMENT.

DURA 110N FAULTS. SElSMit EVENT COULD CREATE FAULT

.CDND}T10NS THAT COULD PDTENilALLY HMA6E REDUNMNT i

. BATTERIES.

- 00AD C111ES 1 & 2

' M/09/89 JNCORRECT VALVES & VALVES INSTALLED BACKNARDS ON O PDTENTIAL FOR OR ACTUAL DE6RADATION

~.

INSTRUMENTAIRLINE. THE S!! IB' BUTTERFLY VALVES NOULD OF CONTAINMENT OR SAFETY-RELATED NOT CLOSE 1F INSTRUMENT AIR NAS LOST NHILE DRYNELL NAS STRUCTURES.

BEIN6 PUR6ED. CONTAINMENT INTE6R!iY COULD NOT BE INSURED.

310 NIM 10/22/89 SURFACE AND SUBSURFACE CRACK INDICA 110NS NERE FOUND BY 0 PDTENTIAL FOR OR ACTUAL M6RADAT!DN UNTRASONIC.TESilN6(UT)DFTHETRANSITIONCONEUPPER OF SAFETY-RELATED EQUIPMENT.

BIRTH NELD (61RTH NELD) 0F THE STEAM SENERATOR.

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REACf0R SCRAM

SUMMARY

WEEK E' DIN 611/12/99

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1. PLANT SPECIFIC DATA'-

ei DATE Sl1E:

Wii PONER $16NAL CAUSE.-

COMPL1 YTD ' YTD

- Y1D 4

CATIONSiAB0VEBELDW. TOTAL--

i,-

151 151a

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u,

., 100 A EDUlPMENT N0 3,

0; 3

11/07/89 BRAND. SULF

,1;

.s f2 11/10/89 LIMERICK-2 2l ' 99 A E90!PMENT; YES.

- 1.

0 1

!11/10/09 ARKANSAS 1

'1

~ 74 A.-

PER$0NNEL-NO-

-3

- 01 3-11/12/B9 FARLEY l 1: L34 A EQUIPMENT.

ND 1

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' 11/12/B9Fli2FATRICK l'

11 A EDU1PMENT.

ND-

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2 l

2

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SUMMARY

OFCOMPLICATIONS n

$1TE' UNii

~3 o

COMPLICAi!0NS LIMERICK

. 2 HPCI STARTED AND TRIPPED S!! TIMES IN DNE MINUTE FOLLONIN6 SCRAM' 7

RELAYS SET TOO LOW AND HFCI TURBlNE OVERSPEEDED DUE TO NO LOAD.

'i 3

REACTOR SCRAM

SUMMARY

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NEEKENDIN611/05/89.

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1.PLANTSPECIFltDATA

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DATE/

SITE:

UNIT PONER S!6NAL CAUSE COMPLI-, YTD YTD YTD.

p*

CATIONS A80VE BELOW TOIAL '

L 151 -151 H,

a 1

L 10/31/E9 PALD VERSE-2 66 A EQUIPMENT N0 3

0 3

11/05/09 VDBILE 2 100 M PERSONNEL NO 5

1 6

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' J1/05/89 F111FAIRlCK

-1 100 A EDUlPMENT ND 1

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W O p: l EIN ; COhF:_ARISDN; Di: WEEKLY STATISTICS;WITH INDUSTRY AVERAGES

'. + :,

D

v f6/' YT SCRAMS FOR WEEK ENDING 11/12/89 y,

W BL 4SCRAMjCAUSE POWER NUMBER

~1989L 1988i 1987.

'1986 1985-

. -(

OF-

LWEEKLY, WEEKLY WEEKLY. WEEKLY WEEKLY M

-SCRAMS (5):

AVERAGE AVERAGE AVERAGE l AVERAGE AVERAGE'

(

YTD.

(3)(4)~.(8)(9)-

M **LPOWERt>15%t i!EifEDOIP. RELATED L>15%.

3 3.0 3.1-3.9 ~

4.1-5.4 I)PERS. RELATED(6)T>15%-

1 1.1

-1.O' 1.3 1.B' 2.0

[@f0THER(7)=

' >15%

O O ~.1 0.5 1.2

0. 4, 0.6

! * * :: Sub to ta l.: *

• yy 4

4 '. 2

-4. 6 6.4 16. 5

'B.0-fWu5 Ti** POWER:<15%

F 1 EQUIP. RELATEDf

.<15%

1 0.4 0.5 1.2 1.4; 1.3

PERS.JRELATEDi

<15%-

0-0.3 O '. 3 0.6 0.8

-0.9

" OTHER..

<15%

0 0.0 0.1 0.3

.O.2

'O.2 ct*cSubtotal:-**;

~1 0.7 0.9 2.1 2.4 2.4 j**'*4 Total

• • 4i 5'

4.9 5.5 8.5 8.9' 10.4 m

s

. MANUAL-VS AUTO SCRAMS j :y TYPEi NUMBER 1989 1988 1987 1986' 1985 3

OF WEEKLY'

-WEEKLY WEEKLY WEEKLY-WEEKLY SCRAMS ' AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE-YTD 4

n

~

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r 4MANUALESCRAMS' O

O.9 1.0

'1. 4 1.0

'1.0-LAUTOMATIC SCRAMS-5 3.9

'4.5 7.0 7.9 9.4~

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II. COMPARISON OF-~ WEEKLY STATISTICS WITHLINDUSTRY: AVERAGES l

e q:

u

~

mJ SCRAMS'-FOR WEEK ENDING 11/05/89

')

.i zSCRAM'CAUSE, POWER-NUMBER 1989 1988 1987 1986 "1985',

OF WEEXLY:

WEEKLY WEEKLY. WEEKLY

-i WEEKLY c

SCRAMS (5)

. AVERAGE: AVERAGE-AVERAGE AVERAGE ' AVERAGE -

'YTD' (3)(4)-

(8)(9)

• • l POWER >15%-

-EQUIP.:RELATED-

>15%

2-3.O' 3.1 3.9-4.3.

5.4-PERS. RELATED(6)J)15%L 1

1.1~

1.0-1.3

.1.8

.2.01

-0THER(7)l

>15%-

O O.1

'O.5' 1.2 10.4 0.6L

/**:Subtotalo**l c3 4.2

-4.6 6.4 6.5 8.0

!**LPOWER-<15%-

' EQUIP. RELATED

<15%"

O 0.4 0.5

=1.2 1 '.' 4 '

1. '3

,3 PERS. RELATED-(15%-

O.

O.3 0.3 0.6 0.8.

.O.9

-**JSubtotal'**.

<15%

0

.O.0-0.1 0.3

0. 2.

.O.2' i

'OTHER.

~

O O.7 0.9 2.1 2.4

-2.4L

• • • ITotal;***>

3 4.9 5.5 8.5 8.9 10.4-a L

' MANUAL VS AUTO' SCRAMS l

TYPE.

NUMBER 1989 1988

-1987 1986 1985

,c

. OF

' WEEKLY-WEEKLY WEEKL Y ' WEEKLY' WEEKLY l

. SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE

' I ll

' YTD. L f

i

' h.

- 1 '. O 1,

l':.

3 t1 A N U A L: SCRAMS 1

0.9 1.0 1.4.

-1.0 I

AUTOMATIC: SCRAMS-2 3.9

-4.5 7.0 7.9 9.4 P

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i NOTE,S O

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PL4I;TL SPECIFIC DATA BASED ON IlilTIAL-REVIEW.0F 50.72 REFCRTS.

FOR-THE WEEK OF IFTEREST. ' PERIOD IS MIDNICHT SUNDAY THROUGH "r

' MIDNIGHT SUNDAY.. SCRAMS ARE DEFINED AS REACTOR: PROTECTIVE AC1VATIONS WHICH RESULT Ih' ROD HOTION, Al.D EXCLUDE PLANNEDL 4

TESTS' OR SCRAMS AS PART OF PLA!;i:ED SHUTDOWl' IN ACCORDANCE PL WITH A PLANT PROCEDURE. THERE ARE 111 REACTORS HOLDING AN-OPERATIllG LICENSE.

e-N 2.

COMPLICATI0tS: RECOVERY: COMPLICATED BY EQUIPMENT FAILURES OR

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PERSONNEL RELATEL PROBLEHSLIt.'CLUDE HUMAN ERROR, PROCEDURAL-DEFICIEliCIES. AND MANUAL STEA!! GENERATOR LEVEL CONTROL PROBLEMS.-

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c"OTHER"' INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LICHTHIttG), SYSTEM DESIGft, OR UNKNOUll CAUSE.

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