ML20247R016

Summary of Operating Reactors Events Meeting 89-34 on 890920 to Brief Senior Managers & Regional Offices on Selected Events That Occured Since Last Meeting

ML20247R016
Person / Time
Site:	Palo Verde, Arkansas Nuclear, Farley, 05000000
Issue date:	09/21/1989
From:	Haughney C Office of Nuclear Reactor Regulation
To:	Rossi C Office of Nuclear Reactor Regulation
References
OREM-89-034, OREM-89-34, OREM-YY-XXX, NUDOCS 8909290147
Download: ML20247R016 (15)

Text

.

4 September 21, 1989

e. s MEMORANDUM FOR: Charles E. Rossi, Director Division of Operational Events Assessment FROM: Charles J. Haughney, Chief Events Assessment Branch Division of Operational Events Assessment

SUBJECT:

THE OPERATING REACTORS EVENTS MEETING September 20, 1989 - MEETING 89-34 On September 20, 1989, we conducted an Operating Reactors Events meeting (89-34) to brief senior managers from NRR, ACRS, AE00, RES, Commission staff, and regional offices on selected events that occurred since our last meeting on September 13, 1989. Enclosure 1 lists the attendees.

Enclosure 2 presents the significant elements of the discussed events.

Enclosure 3 contains a summary of reactor scrams for the week ending 09/17/89.

We identified two significant events for input into the NRC performance indicator program.

/r/

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

Enclosures:

As stated cc w/ Encl.:

See Next Page DISTRIBUTION Central File 4 EAB Reading File  !

Circulating Copy, EAB Staff MLReardon, EAB BBenedict. EAB LKilgore, SECY o.PDR; ,

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DATE :09/2 / /89 :09/ Al/89  :  :  :  :  :

OFFICIAL RECORD COPY 8909290147 890921 PDR ORG NRRD

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T. Murley. NRR C. Poslusny 'NRR l F. Miraglia, NRR F..Hebdon, NRR' i

'J. 'Sniezek, NRR E. Reeves, NRR J. Partlow, NRR. E. Adensam, NRR F. Jordan, AEOD T. Chan. NRR-J. Taylor. EDO G. Knighton, NRR E. BeckJord, RES-p W. Russell, RI.

i S. Ebneter, RII-B.' Davis, RIII R.D. Martin, RIV J.B. Martin..RV-

'W. Kane. RI L. Reyes, RII E. Greenman. RIII J. Milhoan, RIV R. Zimmerman, RV-S. Varga,.NRR B. Boger, NRR G. Lainas. NRR

0. Holahan. NRR F. Congel, NRR E. Weiss, AE00 T. Martin, EDO J. Lieberman, OE

'J. Guttrann, SECY A. Thadani, NRR J. Richardson. NRR

5. Rubin, AEOD J. Forsyth, IhF0

-R. Barrett, NRR fi. Harper.-AE00 R. Newlin, GFA J. Roe, NRR I! . Alderman. ACRS

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September 21, 1989 -

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. MEMORANDUM FOR: Charles E. Rossi, Director .{

Division of Operational Events Assessment 1 FROM: Charles J. Haughney, Chief Events Assessment Branch j Division of Operational Events Assessment l

1

SUBJECT:

THE OPERATING REACTORS EVENTS MEETING September 20, 1989 - MEETING 89-34 On September 20, 1989, we cor. ducted an Operating Reactors Events meeting (89-34) to brief senior managers f rom NRR, ACRS, AE0D, RES, Comission staff, and regional offices on selected events that occurred since our last meeting on September 13, 1969. Enclosure 1 lists the attendees.

Enclosure 2 presents the significant elements of the discussed events.

Enclosure 3 contains a summary of reactor scrams for the week ending 09/17/89.

We identified two significant ever.ts for input into the NPC performance indicator program.

j [, b .t ' bo ' -  %

Charles J. Haughney. Chief Events Assessment Branch Division cf Operational Events Assessment

Enclosures:

As stated cc w/ Encl.:

See Next Page

ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (89-34)

Sep't ember 20. 1989-NAME ORGANIZATION NAME ORGANIZATION D. Trimble. OCM/JC W. Troskoski OE R. Nease NRR/DLPQ N. Trehan NRR/ DST T. Chan NRR/PD-5 R. Benedict NPR/00EA.

S. Long ACRS G. Hammer NRR/DET-S. tiatthews NRR/DRIS A. Vietti-Cook 0CM/KC R. Perfetti OE . F. Cherny RES/EID M. Wegner AEOD/R0AB M. Chiramal AEOD/ROAG P. Baranowsky NRR/00EA M. Davis NRR/PD-5 C. Posiusny NRR/PD-4 G. Knighton NRR/FD-5 F. Hebdon NRR/PD-4 A. Howell RIV L. Plisco NRR/LPEB E. Butcher NRR/ILPB R. Lo NRR-PD2-1 J. Donohew NRR/ADSP M. Reardon NRR/00EA B. Clayton OED0 W. Minners RES/DSIR E. Reeves NER/PD2-1 A. Gilbert NRR/DOEA N. Fields NRR/00EA P. Bobe AEOD/DSP k. Lobel NRR/00EA J. Carter NRR/DOEA R. Karsch NRR/00EA l

ENOLOSURE 2 OPERATING REACTORS EVENTS BRIEFING 89-34 EVENTS ASSESSMENT BRANCH LDCATION: 1EE-11, WHITE FLINT WEDNESDAY, SEPTEMBER 20, 1989, 11:00 A.M.

ARKANSAS UtilTS 3 8 2 DISCREPANCIES BETWEEN ELECTRICAL DIAGRAl'S AND AS-BulLT CONFIGURATION

- FARLEY ADECUACY OF SERVICE ktTER FLOWS PA.LO VERDE UNIT 2 MAIN STEAM SAFETY VALVES -

IMPRCPER BLOWDOWN RING SETTlf4S 1*

t' it..mm_._,.. . .. . . . . .

89-34 ARKANSAS UNITS 1 & 2 DISCREPANCIES BETWEEN ELECTRICAL DIAGRAMS AND AS-BUILT CONFIGURATION SEPTEMBER 13, 1989 PROBLEB

. DISCREPANCIES WERE FOUNL BETWEEN ELECTRICAL LIAGRAMS'Ahr THE AS-BUILT CONFIGURATION OF THE INITIATION CIRCulTRY FOR TWO OUT .

OF THREE SERVICE WATER PUMPS. -

LAUSE LACK OF APECUATE QUALITY CONTROL OF CIRCUIT MODIFICATIONS DURING CONSTRUCTION AND STARTUP, SAFETY SIGNIFICANCE o DIFFICULlY IN PREDICTING lHE EFFECTIVENESS OF CIRCUIT MODIFICATIONS.

c UhEXPECTED PLANT RESPONSE TO A SET OF CONDITIONS.

ILLSLLSSJE 0 AEOD DIAGNOSTIC EVALUATION TEAM FOUND SEVERAL DISCREPANCIES BEThEEN ELECTRICAL CONNECTich DRAWINGS AND THE AS-BU1LT C0hFIGURATION CF INITIATION CIRCUITRY FOR UNIT 1 SERVICE WATER PUMPS "A" ANL "C" (THE "E" PUMP WAS UNAFFECTEL).

0 LICENSEE LETERMINED THAT THE TWO SERVICE WATER PUMPS WERE lECllN1CALLY INOPERABLE DUE TO A LOGIC ERROR. ThE LOGIC ERROR HAD BEEN LISCOVERED PREVIOUSLY AT THE COMPLET10N OF UNIT CONSTRUCTION IN LATE 1974.

o ON A REACTOR TRIP COINCIDENT WITH AN ESF ACTUATION, PUMPS "A" ALD "C" WOULD FAIL TO RESTART ON A SLOW (10 CYCLE TO 1 SEC)

TRANSFER FROM THE AUX XFMR TO THE STARluP XFMR LUE TO THE ACTICh 0F THE ANTI-PUMP CIRCulTLY. (NRC INFORMATION NOTICE EL-75, AS SUPPLEMENTED, EESCRIBES EVENTS LURING kHICH ANTI-PUMP CIRCUITRY PREVENTED THE DESIREL CLOSURE OF CIRCUIT BREAKERS).

CONTACT: N. FIELDS SIGEVENT: _YES_

REFERENCE:

10 CFR SC.71 #16583 thI MORNINC REPORTS OF SEPTEMBER 13 ANI 14,1989

ARKANSAS UNITS 1 t. 1 --

89-34 o WHEN THE ERROR WAS DISCOVERED (1974), LICENSEE ALTERED SCHEMATIC DIAGRAMSLTO REFLECT THE CORRECTION IN CIRCulT LOGIC. HOWEVER, TilE ACTUAL AS-BUILT' CONFIGURATION WAS NOT CHANGED FOR PUMPS "A" AND "C".

o TO DATE, LICENSEE HAS DETERMINED TilAT THE HARDWARE WAS POSSIELY.

NOT CCREECTED TO CCNFORM TO THE ALTERED SCHEMATIC BECAUSE THE LOCATIONS OF THE CIRCulT CONNECTIONS FOR THE RELAY CONTACTS WERE o

DIFFERENT FROM,THOSE INDICATED ON THE APPLICABLE CIRCull CCNNECTIO!! DI AGRAMS MISLEADING Tile CRAFTSPERSON INTO BELIEVING g THAT THE CONNECTIONS DID NOT-EXIST.

o CTHER PROBLElis FOUND INCLULED-SEVERAL UNATTACHED, UNLABELED WIRES l WITH TERMlHAL LUGS: AFFIXED, INDICATIONS THAT CABLES LOCATED ON  !

i Tl:E CABINET FLOOR ARE IJECESSARILY TREAD UPON BY CRAFTSPEOPLE IN PERFCRMING CERTAIN TASKS-INSIDE CABINET, RELAY DUST COVERS MISSINC, AND CABLE FIRE WRAP DAMAGE.

EDLLDEE '

o LICENSEE HAS BEGUN AN lhSFECTIOh 0F A COMPREHENSIVE SAfiPLING OF SAFETY RELATED ELECTf.lCAL COMFCNENTS AND ECulFMENT Al UNITS 3 f t:T 2 . f o THERE IS A SPECIAL INSPECTION TEAM COMPOSED CF REGIONAL AND HEADQUARTERS PERSCNNEL AT THE SITE.

- m _________ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ . _ . _ _ _ _ _ _ _ _ . _ _

89-34 EhBLEX ALEGUhfY OF SERVICE WATER fl01S SEPTEMBER 14, 1989 EED31EB Ut'CERTAIM SERV!CE WATER FLOW RATE TO SAFETY RELATED COMPONENTS F0LLOWING A POSTULATED SEISMIC EVENT.

CAUSE COMPRESSED AIR SYS1EM NOT CONSIDERED NECESSARY F0f, SAFE SHUTDOWN.

SAFETY S10f.'IFICANCE THERE MAY LE INADECUATE COOLING WATER FLOW TO THE EMERGEf4CY DIESEL GENERATORS; INTERIM COMPENSATORY MEASbEES INVOLVE OPERATOR ACTION.

DlBLDSSlDb o LICENSEE INITIATED SAFETY SYSTEM ASSESSMENT OF SERVICE WATER SYSTEM IfJ MAY 1929.

O POSTULATED SEISMIC EVENT MAY CAUSE LOSS OF AIR SYSTEM.

SEISMIC CATEGORY 11 DESICN VS PLANT SSE OF 0.1 C AIR OPERATED VALVES IN SERVICE WATER SYSTEM.

FSAR STATES THAT SAFETY RELATEC VALVES FAIL TO " SAFE" POSITION.

c ASSESSMENT EETERMINED TlitT WITH A LOSS CF AIR SYSTEF., NOT ALL NCN-ESSEt:TITL C00LINC WATER LOADS WCULD EE ISCLATED.

- SOME VALVES T0 f:0N-ESSENTIAL LOADS FAIL OPEN, o MAY h0l HAVE ADECUATE FLOW TO SAFETY RELATEC LOADS.

PARTICULAR CONCERN IS DIESEL COOLING.

~

o ANALYSIS OF SERVICE WATER SYSTEM SCHEDULED FOR COMPLETI0f' IN FEBRUARY 199C.

0 /S INTERIM "FIX", LICENSEE HAS MODIFIED PROCEDURES.

0FErl. TORS TO SHUT OTHER VALVES (MOTOR) FROM CONTRCL E00M.

ONLY A FEW VALVES f.EED 10 BE CLOSED.

EDLLDEDE REG 10h TO IChlTOR LICENSEE'S ASSESSMENT CONCLUSIONS. ,

IIT: f.0- I CONTACT: J. CARTER SIGEVEf!T : _NO

REFERENCES:

]C CFF 50.71 #10591 I

89-34 PALO VERDE UNIT _2 ULIN STEAM SAFETY VALVES - IMPROPER ELOWDOWN RING SETTINGS SEPTEMBER 1, 1989 EEDELEB

'PALO VERDE UNIT 3 MAIN STEAM SAFETY VALVES (MSSVs), SUPPLIED BY CONSOLIDATED VALVE CORP / DRESSER, HAD IMPROPER BLOWDOWh RING SE1 TINGS WHICH COULD AFFECT VALVE CHATTER, VALVE BLOWDOWN TIME, AND VALVE RELIEF CAPACITY.

'fAUSE STILL UNDER INVESTIGATION.

I SAFETY SIGNIFICANCE IMPROPER SETTINGS ON BLOWDOWN RINGS (GUIDE RING AND N0ZZLE RING)

COULD RESULT IN MAIN STEAM REllEF WITH EXTENDED BL0hDOWN AND INSUFFICIENT STEAh RELIEF, BOTH OF WHICH ARE OUTSIDE OF THE DESIGN BASIS.

DISCUSSION o Oh AUGUST 31, 1559, PALO VERDE RECEIVED RESULTS OF TESTS DONE AT WYLE LAES ON UNIT 3 MSSVs WHICH lhDICATED IMPRCPER BLOWDOWN

l. RING SETTlh6S (BOTH, CUIDE AND N0ZZLE RING SETTINGS). THE LICENSEE RECOGNIZED THE PROLLEM ON SEPTEMEER 1. ON SEPTEMBER 6,

AFTER C0hSULTING WITH DRESSER THE LICENSEE IMMEDIATELY SHUTDOWN UNIT 2 (UNIT 1 WAS.ALREADY SHUTDOWN) TO INVESTIGATE MSSV RINC SETTINGS ON OTHER UNITS.

O fslNG SETTINGS V/RIED IN BOTH THE HIGH DIRECTION AND LOW DIRECTION.

THE NOMINAL SETTING WAS +100 AND -8 FOR THE TWO RINCS, SETTINGS WERE FOUNE AS hlGH AS +371 AND +2, AND AS LOW AS +136 AND -28.

ALL VALVES TESTED WERE FCLI.D TO BE IMPROFERLY SET.

c lhE TESTS CONE AT WYLE INDICATE THAT THESE WERE THE AS-FOUND SETTINGS OF THE UNll 3 MSSVs. THIS WAS THE FIRST GUTAGE FOR UNIT 3. THEFEFORE, THE VALVES MAY HAVE EEEN INITIALLY SUPPLIED  !

WITH IMPROPER RING SETTINGS.

00hlACT: A. f. CILBERT SILEVENT: __TEL J

REFERENCE:

30 CFR 50.71 #16513

o SS '

.PALO VERDE UNIT-2

. i o UNIT 2 MSSVs ARE NOW EEING CHECKEDs STAR 1LP UNIT 2 IS SCHEDULED FOR LATER THIS WEEK. THE OTHER TWO UNITS' MSSVs WILL BE TESTED PR10R TO THEIR RESPECTIVE-STARTUPS.

c GENERIC COMMUNICATION!!S:

INFORMATION NOTICE 86-05: MAIN STEAM SAFETY VALVE TEST.

FAILURE AND RING SETTING ADJUSTMENTS WAS= ISSUED OF JANUARY 31, 1986 IN- RESPONSE TO IMPROPER RING SETTINGS AFTER

- TESTING AT WYLE LABS.

PROPOSED 50.54(F) LETTER ON INADECUATE FLOW CAPACITY OF MAIN .

STEAM CODE SAFETY VALVES WAS TRANSMITTED FOR CRGR REVIEW ON AUGUST- 31, 1987, EUT WAS NEVEF. ISSUED.

FOLLOWUP THE' LICENSEE IS INVESTIGATING THE ROOT CAUSE FOR THE IMPROPER RING SE111NCS . REGION V IS FOLLOWING THIS EVENT AND ASSOCIATED ACTIVITY CLOSELY. AEOD ANC EMEB WILL CONTINUE TO FOLLOW FOR POTENTIAL GENERIC IMPLICATIONS AND/0R A NEEL FOR A PART 21 SUBMITTAL, A

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J PA O VERDE UNIT 2 TYPICAL PMIN STEAM SAFETY VALVE I

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ggf39;g9 ENCLOSURE 3 j

. FERFDRMANLE INDICATDRS SIGNIFICANT EVENTS {

PLANT NAME EVENT EVENT DESCRIFT]DN GTR SIGNIFICANCE l DATE ARrAN5AS 1 1 2 09/13/B9 A DISCREPANCY hAS FDUND BETWEEN PLANT ELECTRICAL LEAWINSS 1 UNEIFECTED PLANT RESFDNSE TD A SET AND AS-BUILD ELECTRICAL CCMFDNENTS/EDUlF' MENT. DF CDNDITIDNS GCSUIF.E 2 09/05/P9 DVERPREESURIIATION DF iHE CONTAINMENT SPEAY SYSTEM 1 FDTENTIAL FDR DR ACTUAL DESEADATIDN RESULTED IN LEAK DF REACTOR CDDLANT AND REFUELING WATER. DF FRIP.ARY CDDLANT FRESSURE EDUCARY l

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FEACTDRSCRAM

SUMMARY

1

. WEEK ENDING 09/17/E9

1. PLANT SPECIFIC DATA DATE $1TE Uhli POWER 516hAL CAUSE COMPLI- Y1D YTD YTD CAllDNS ABDVE PELOW TDTAL 151 151 09/13/69 ST LU:IE 1 100 A ~ PEP.SDNNEL ND 1 0 1 09/15/69 TUF: LEY PDIKT 4 100 M EDUIPMENT ND 1 0 1 09/16/09 $Uf:RY 2 0M EQUIPMENT ND 0 1 1 l

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1 I- II. COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES i

l SCRAMS FOR WEEK ENDING l .

09/17/89 SCRAM CAUSE POWER NUMBER 1989 1988 1987 1986 1985 OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAMS (5) AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE YTD (3)(4) (B)(9) l

• • POWER >15%

EQUIP. RELATED >1b% 1 3.1 3.1 3.9 4.3 5.4 PERS. RELATED(6) >15% 1 1.1 1.0 1.3 1.8 2.0 OTHER(7) >15% 0 O<1 0.5 1.2 0.4 0.6

~*t Subtotal **

2 4.3 4.6 6.4 6.5 0.0

• POWER <15%

EQUIP. RELATED <15% 1 0.4 0.5 1.2 1.4 1.3 PERS. RELATED <15% 0 0.3 0.3 0.6 0.8 0.9 OTHER <15% O O.O O.1 0.3 0.2 0.2

• Subtotel **

1 0.7 0.9 2.1 2.4 2.4

• • • Total 444 3 5.0 5.5 8.5 8.9 10.4 MANUAL VS AUTO SCRAMS 7YPE NUMPER 1989 1988 1987 1986 1985 OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE YTD MANUAL SCRAMS 2 0.9 1.0 1.4 1.0 1.0 AUTOMATIC SCRAMS 1 4.1 4.5 7.0 7.9 9.4

,_- rx. ._.x-_.___. - . - _ _ _ _ - _ _ . . _ _ _ _ _ . _

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(~' NOTES

. 1. PLANT SPECITIC DATA BASED ON INITIAL PEVIEW OF EC.72 REPORTS FOR THE WEEr,OF INTEREST. PERIOD IS MIDNIGHT SUNDAY THROUGH MIDNIGHT SUNDAY. SCPAMS ARE DEFINED AS REACTOR FRO *. IVE ACTUATIONS WHICH RESULT IN RCD MOTICN, AND EXCLUDE PL dNE0 TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE Wild A PLANT-PROCEDURE. THERE APE 111 REACTORS HOLDING AN OPERATING LICENSE.

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

3. FERSONNEL RELATED PROELEMS INCLUCE HUMAN EPRCR, PROCEDURAL DEffr7?CIES, AND MANUAL STEAM GENEPATOR LEVEL CONTROL P RGt!,1"'.3.

4 "0THER" INCLUDES AUTOMATIC SCEAMS ATTRIBUTED TO ENVIP.0hMENTAL CAUSES (LIGHTNING), SYSTEl' DESIGN, OR UllKNOWN CAUSE.

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