ML20005D812

Summary of Operating Reactors Events Meeting 89-044 on 891213.List of Attendees & Viewgraphs Encl

ML20005D812
Person / Time
Site:	Oyster Creek, Arkansas Nuclear, River Bend, 05000000
Issue date:	12/18/1989
From:	Haughney C Office of Nuclear Reactor Regulation
To:	Rossi C Office of Nuclear Reactor Regulation
References
OREM-89-044, OREM-89-44, NUDOCS 8912290161
Download: ML20005D812 (14)

Text

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December 18, 1989 MEMORANDUM FOR:

Charles E. Rossi Director Division of Operational Events Assessment i

FROM:

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

SUBJECT:

THE OPERATING REACTORS EVENTS MEETING December 13, 1989 - MEETING 89 44 On December 13, 1989, we conducted an Operating Reactors Events meeting (89-44).to brief senior managers from NRR, AE0D, ACRS, RES, Comission staff, and regional offices on selected events that occurred since our last meeting on December 6, 1989. lists the attendees. presents the significant elements of the discussed events. contains a sumary of reactor scrams for the week ending 12/10/89.

No significant events were identified for input into the NRC performance indicator program.

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h hrieo J. Ft4 tf Charles J. Haughney, Chief Events Assessment Branch Division of Operational Events Assessment

Enclosures:

As stated cc w/ Encl.:

See Next Page l

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T. Nurley, NRR C. Harbuck. NRR F. Miraglia, Nkt F. Hebdon, NRR

'J. Sniezek,_ liRR A. Cromerick, llRR -

J.:Partlow, NRR J. Stolz, NRR E. Jordan, AEOD' W. Paulson,liRR J. laylor, EDO E. BeckJord, RES-W. Russell, R1 S. Ebneter, Ril B. Davis, Rlll R.D.11artin RIV J.D. l'artin, RV W. Kane, R1

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Zimmerman, RV S. Varga, NRR B. Boger, NRR G. Lainas, l'RR T. Congel, NRR E. L'eiss, AE00 B.'Clayton, EDO J. _ Liebernian, OE J. Guttmann, SECY

-A. Thadani, NRR J. Richardson, !!RR

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December 18, 1989 EEMORANDUli FOR:

Charles E. Rossi, Director Division of Operational Events Assessment FROM:

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

SUBJECT:

THE OPERATING FEACTORS EVENTS MEETING Eecember 15, 1989 - MEETING 89-44 On December 13, 1989, we conducted an Operating Reactors Events nieeting (89-44) to brief senior managers from NRR, AE0D, ACRS, RES, Commission staff, and regional offices on selected events that occurred since our last meeting on December 6, 1989. lists the attendees. presents the significant elements of the discussed events. contains a summary of reactor scrams for the week ending 12/10/.89, ho significant events were identified for input into the '

performance indicator prograni.

C1:

1 AA Charles J. Hau h y Chief l

Events Assessm anch Divisi erationalEMsAssessment

!~

Enclosures:

As stated l

cc w/ Encl.:

See Next Page l

l l

l

i-d' ENCLOSURE 1 LISTOfATTENCEM OPERATit!G REACTORS EVENTS BRIEflNG (89-44)

December 13, 1989 tit.!!E ORGANIZATION NAME ORGANIZAT10h T. Murley I;RR/D0hRR F. Miraglia' i:RR/ADT

[

J. Dyer OEDO F. Witt i:RR/EMED C. Sellers-NRR/E!!CB W. Paulson NRR/PD-4 P. Baratiowsky liRR/DOEA P. Prescott NRR/LFEB

f. Hebdon I:RR/PD-4 C. Vandenburg NRR/RSIB r

L. Lois NRR/SRXB H. Aldern'.an ACRS R. Perfetti OE C. Poslusny NRR/PC-4 M. Case NRR/PQED P. Cortland NRR/TVAP

f. Cherny RES/EIB J. Stolz NRR/PDI-4

-U. Troskoski OE H. Shaw NRR/EMEB T. Sullivan NRR/EMEB J. Thompson NRR/00EA P. Reardon NRR/DOEA R. Jones NRR/SRXB S. Varga NRR/DRF D. Fischer NPA/DOEA H. Ornstein AE0D/DSP

-J. Carter NRR/D0EA R. Karsch NRR/00EA C. Haughney NRR/00EA E. Rossi NRR/DOEA A. Dromerick

!!RR/PDI-4

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ENCLOSURE 2

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OPERATING REACTORS EVENTS BRIEFING 89-44 EVENTS ASSESSMENT BRANCH LOCATION:

16D-13, WHITE FLINT WEDNESDAY, DECEMBER 13, 1989, 11:00 A.M.

0YSTER CREEK AIT STATUS REPORT RIVER EEND RECURRENCE OF MULTIPLE MSIV FAILURES:

GENERIC S0LEN0ID OPERATED VALVE PROBLEf1 ARKANSAS 1 LEAKING CRDM FLANGES CAUSES 1

SEVERE CORROSION TO THE FLANGE NUT COMPRESSION RING I

l

n

,1 L,

89-44 c..

+

0YSTER CREEK AIT STATUS REPORT DECEMBER 7, 1989 PROBLEM OPERATIONAL CONCERNS SURROUNDING A PARTIAL LOSS OF CONDENSER

VACUUN, CAUSE OPERATOR ERROR DURING HOTWELL BACKWASH, SAFETY SIGNIFICANCE MINIMAL SAFETY SIGNIFICANCE: A REACTOR TRIP ON LOW CONDENSER VACUUM IS IN ANTICIPATION OF TURBINE TRIP, DISCUSSION o ON DECEMBER 7, 1989, 0YSTER CREEK WAS OPERATING AT 100% POWER WITH ONE SECTION OF THE "B" CONDENSER ISOLATED BECAUSE OF SALT WATER-LEAKAGE, OPERATORS LOST VACUUM IN THE OTHER SECTION OF THE "B" CONDENSER DUE TO AN IMPROPERLY EXECUTED BACKWASH _

j PROCEDURE, o LOW VACUUM ALARMS WERE RECEIVED BY THE CONTROL ROOM OPERATORS.

o THE OPERATOR CONSIDERED A MANUAL SCRAM WHEN THE AUTOMATIC TRIP DID NOT ACTUATE, BUT WHILE HE WAS VERIFYING THE NECESSITY FOR A TRIP THE CONDENSER VACUUM REC 0VERED AB0VE THE ALARM POINT, l

L o OPERATORS REDUCED POWER TO 85% UNTIL VACUUM WAS COMPLETELY RESTORED AND THEN RESUMED OPERATION AT 100% POWER.

FOLLOWUP-l AIT WAS DISPATCHED TO OYSTER CREEK ON DECEMBER 8, 1989 TO DETERMINE THE FOLLOWING:

o DID THE REACTOR PROTECTIVE SYSTEM FUNCTION PROPERLY DURING THE EVENT?

AIT:

YES CONTACT:

R. KARSCH SIGEVENT:

NO

REFERENCES:

10 CFR 50.72 # 17280 AND PRELIMINARY REPORT PN0-1-89-97

Fp.

QYSTER CREEK 89-44 EpllOWUP (CONT 1tlVED) t o DlD THE OPERATOR TAKE THE PROPER ACTION LY NOT MANUALLY TRIPPING L

THE PLANT?

o DlD THE LICENSEE ACT PRUDENTLY IN RETURNING TO 100% POWER BEFORE COMPLETING AN ANALYSIS OF THE EVENT?

Ali FINDINGS:

o THE REACTOR PROTECTIVE SYSTEM FUNCTIONED PROPERLY, BUT THE TRIP SETP0lNT WAS NOT REACHED BY THE TRIP SENSORS BECAUSL THE SENSORS HAD DRIFTED HIGH 'NONCONSERVATIVE).

THE TRIP POINT WAS AT A HIGHER ABSOLUTE CONDENSER PRESSURE THAN THE ALARK POINT, o THE OPE.RATOR WAS NOT ABLE TO CONF 1RM THE NEED TO TRIP (POSSIBLY DUE TO A PROCEDURAL WEAKNESS) AND ACTED PRUDENTLY IN AVO! DING INDUCING A TRANSIENT, o RETURNING TO POWER FOLLOWING THE EVENT WAS A REASONADLE ACTION

~

UNDER THE CIRCUMSTANCES, THE LICENSEE UNDERTOOK SUBSTANTIAL SYSTEM CHECKS INCLUDING A SHUTDOWN TO CONFIRM OPERABILITY OF THE VACUUM SENSORS INSIDE THC CONDENSER

HOTWELL, LICENSEE CORRECTIVE ACTIONS L

o MAKE OPERATORS SENSITIVE TO THIS EVENT, o INSTRUMENTS ARE BEING RESET AT 24 " 0F MERCURY.

o REVIEW THE ADE0VACY OF THE TECH SPECS, L

LONGTERM CORRECTIVE ACTIONS o IMPROVE DESCRIPTIONS IN THE TECH SPEC TABLES, 0 UPDATE PLANT DRAWINGS TO REFLECT AS BUILT CONFIGURATION, l

o OPERATOR RETRAINING, m.

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F.*

I.

I J

89-44 RIVER BEND RFCURRENCE OF MULTIPLE MSIV FAILURES:

A GENERIC SOLEN 0ID OPERATED VALVE PROBLEM DECEMBER 2, 1989 PROBLEM SECOND INSTANCE OF MULTIPLE MAIN STEAM ISOLATION VALVE (MSIV)

+

FAILURES AT RIVER BEND OCCURRED AFTER TAKING CORRECTIVE ACTION.

CAUSE MSIV SOLEN 0ID VALVES FAILED TO RELEASE.

SEVERAL ROOT CAUSES SUSPECTED (E.G., VALVE SEAT MATERIALS, LUBRICANTS, OPERATING TEMPERATURE, AIR QUALITY).

SAFETY SIGNIFICANCE.

PECURRING COMMON CAUSE FAILURES OF MSIVs REPRESENT DEGRADATION OF CONTAINMENT INTEGRITY AND REACTOR ISOLATION FUNCTION.

DISCUSSION o AFTER REACTOR SCRAF FROM 97% POWER AND WHILE IN MODE 4 ON DECEMBER 2, 1989, LICENSEE BEGAN TO SLOW CLOSE MSIVs.

o TWO OUTB0ARD MSIVs FAILED TO REMAIN CLOSED UPON RELEASING TEST PUSH BUTTON WHEN POSITION SWITCH WAS IN THE CLOSED POSITION.

MSIVs CLOSED BY DEPRESSURIZING ACCUMULATORS.

o ONE OPERABLE INB0ARD AND BOTH INOPERABLE OUTB0ARD MSIV S0LEN0ID VALVES WERE REMOVED FOR INSPECTION.

L A SMALL AMOUNT OF LUBRICANT BETWEEN CORE AND PLUG NUT ASSEMBL APPEARED AS A DISCOLORED RING BETWEEN MATING SURFACES ON OUTBOARD VALVE.

LESSER AMOUNT OF LUBRICANT OBSERVED ON INB0ARD VALVE.

o LICENSEE USES ASCO DUAL C0ll SOLEN 0ID VALVES (NP8323E) WITH EPDM SEAT MATERIAL, CONTACT:

J. CARTER SIGEVENT:

YES

REFERENCES:

10 CFR 50.72 # 17245

R!VER~ BEND-89-44 4

DISCUSSION (CONTINUED) o A SIMILAR PRODLEh OCCURRED WITH TWO INBOARD MSIVs AT RIVER BEND IN SEPTEMBER 1988.

ALL SOLEN 0ID VALVES WERE REPLACED, METAL PARTS WIPED WITH ACETONE, SILICON LUBRICANT APPLIED TO ELASTOMERIC 0-RINGS, o ALL EIGHT ASCO SOLEN 0ID VALVES REPLACED AFTER RECENT FAILURES, METAL PARTS CLEANED BOTH BY ACETONE WIPE AND ULTRASONIC BATH, ALL ELASTOMERIC MATERIALS WIPED WITH ACETONE, TEST FREGUENCY INCREASED TO QUARTERLY, GENERIC C0hSIDERAT10NS o SOLEN 0ID VALVES WIDELY USED IN MANY SAFETY-RELATED SYSTEMS, o COMMON MODE FAILURE MECHANISMS IDENTIFIED FOR ASCO MODEL NP8323.

FOREIGN MATERIAL ELASTOMER DEGRADATION STICKING INTERNALS o BOTH BWPs AND PWRs HAVE ASCO DUAL COIL SOLEN 0ID VALVES, o MANY GENERIC COMMUNICATIONS ISSUED, MOST RECENTLY:

INFORMATION NOTICES 88-43 AND 89-66, AND GE SIL 481, l

o DUAL COIL HEATUP DATA ISSUED BY ASCO IN OCTOBER 1989, l

' SEAT TEMPERATURE ABOUT 100 F ABOVE AMBIENT, o ASCO TO TERMINATE AVAILABILITY OF NP8323.

FOLLOWUP o REGION IV ASSEMBLED INFORMATION ON SOLEN 0ID VALVE TESTING i

FREQUENCY, l

0 AE0D IS COMPLETING A CASE STUDY ON SOLEN 0ID VALVE FAILURES, o OEAB IS CONSIDERING THE NEED FOR A BULLETIN - REQUIRES AE0D CASE STUDY INPUT,

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RIVER BEND FIGURE 1 Solenoid A r

I Plunger Coil U

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w J

Return Spring

. Seal' Mat'l

_y Inlet Port y g Cylinder Port J -(

Seal Material

-,k YM Balance Spring 5?)}

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Solenoid B

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.w mw Energized De-Energized Schematic of the ASCO Dual Solenoid Valve l

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I 89-44 ARKANSAS 1 LEAKING CRDM FLANGES CAUSES SEVERE CORROSTON TO THE FLANGE NUT COMPRESSION RING DECEMBER 5, 1989 INFORMATION PROVIDED FOR 89-44 BRIEFING AND SUBMITTED FOR EDO HIGHLIGHTS ON 12/05/89, THE LICENSEE IDENTIFIED 6 CRDMs THAT HAD MINOR FLANGE SEAL LEAKAGE.

THE LICENSEE OBSERVED SLIGHT BORIC ACID CRYSTAL BUILDUP ON THE FLANGES.

N0' CORROSION WAS IDENTIFIED AT THE TIME.

ON 12/13/89, THE LICENSEE IDENTIFIED SEVERE BORIC ACID CORROSION OF A' CARBON STEEL 1 1/4" NUT RING USED TO SEAL ONE OF THE CRDM

. HOUSINGS.

THE CORROSION WAS SEVERE EN0 UGH TO CAUSE TWO 0F THE I

EIGHT BOLTS ON THE CRDM TO BECOME LOOSE.

B8W IS CURRENTLY PERFORMING AN ANALYSIS OF THIS EVENT TO DETERMINE THE EXTENT OF THE PROBLEM AND RCS BOUNDARY DETERIORATION.

ALL OTHER NUT RINGS WERE INSPECTED WITH NO SIGNIFICANT CORROSION FOUND.

BOLTS, NUT RINGS, AND GASKETS ON ALL LEAKING CRDMs WERE REPLACED.

CONTACT:

J. THOMPSON

REFERENCE:

10 CFR 50.72 #17332 AND MORNING REPORTS 12/05, 12/13, AND 12/14/89

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BEACTORBCRAM$UMMARY ENCLOSURE 3 pf,;

WEEKENDIN612/10/09 y

1

1. PLANT SPECIFIC DATA DATE SlfE llNii POWER S!6NAL CAUSE COMPLI - YTD Vip yip -

CATIONS AB0VE BELOW TOTAL 1

151 151 12/05/09 NORil, ANNA l'

7A EOUIPMENT NO 2

1 3'

c.

' 12/06/B9PIL6 RIM 95 A EDUlPMENT ND 4

~ 0 4

12/10/B9 SEQUDYAN 1

99 A EDU1PMENT ND 2

0 2

0 1

I i

OEAB SCRAt1 DATA Manual & Automatic Scrams for 1986 ------------------- 461 j

Manual & Automatic Scrams for 1987 ------------------- 439 l

Manual & Automatic Scrams for 1988 ------------------- 287 Manual & Automatic Scrams for 1989 (YTD 12/10/89) ---- 228

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'If tCOMPARISON OF: WEEKLY-l STATISTICS WITH; INDUSTRY: AVERAGES L

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-SCRAMS FOR. WEEK"ENDING N+

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'12/10/e9 i

h'IS RAM CAUSEl POWER:

. NUMBER

'1989 1988:

-1987 1986--

.198 0 OF?

WEEKLY WEEKLY. ' ' WEEKLY., WEEKLYJ -WEEKLY!

w SCRAMS (5)

-AVERAGEE -AVERAGE AVERAGE AVERAGE. AVERAGE -

E-l

'YTD' (3)(4)

.(O)(9)E

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p,

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in?,

g -*lt4cPOWER '>15%-

E m EQUIP.fRELATED-

>15%3

2:

2., 9 '

- 3.1 =

3.9

-4. 3 5.4 h

? PERS.'RELATED(6) >1b%

0 1.0

1. 0 -

=.1. 3 21 ;8

< 2. 0 -;

F

'OTHER(7)t.

>15%-

- O~

0.1

-0.5 1.2

= 0. 4 ~-

' 0 ; 6' h

'**jSubtotal'*4-2=

4.0=

4.6?

6.4 6.5

0. 0:

2

_p F **' POWER <15%

19.. EGUIP. RELATED

<15%=

1

,0.4 0.5

' 1. 2 1.4

' a.~ 3

-' P E R S.a R E L A T E D L

< 15% :

-O-0;3 0.3

- 0. 6 :-

O. G'

'C.9' N OTHERf

<15%

'O 0.0-0.1;

'O.3 O.2; O.2' f ) * *i. Subtotal 14 4 '

1 0.7 C.9.

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2. 4 '

2. A -

(***4 Total ***

3 4' 7 5.5 B.5 0.9-

<10.4 E--

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^ MANUAL VS-AUTO SCRAMS' a

. TYPE:

NUMBER 1989 1988 1907-1986-21985-OF-WEEKLY-WEEKLY WEEKLY' WEEKLY WEEKLY;

[

YTD;

" ^

SCRAMS AVERAGE ' AVERAGE AVERAGE. AVERAGE AVERAGE 1

s w.

N

' MANUAL SCRAMS.

O'

.O.8 1.0 1.4 1.0 1.0 p

AUTOMATIC _. SCRAMS 3

3.8-4.5 7.0 79-9. 4 -.

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i NOTES 1.

PLANT SPEClfl0 DATA BASEC ON INITIAL REVIEW OF 50.72 REPORTS FOR THE WEEK Of INTEREST.

PERIOD 15 MIDNIGHT SUNDAY THROUGH MIDNIGHT SUNDAY.

SCRAliS ARE DEfiltED AS REACTOR PROTECTIVE ACTUAT10lis WHICH RESULT 111 ROD MOTI0ll, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE WITH A PLAllT PROCECURL. THERE ARE 111 REACTORS HOLDlhG All OPERATING LICENSE.

2.

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

S.

PERSONNEL RELATED FRCBLEMS IliCLULE HUKAll ERRCR, PROCEDURAL DEFICIEliCIES, AND MAllVAL STEAM GEhERATOR LEVEL C0llTROL PROBLEllS.

4.

"0THER INCLUDES AUT0KATIC SCRIES ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNil4G), SYSTEl DESIGN, OR Ul;KNOWii CAUSE.

+

i 1

.