ML20207P627

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Summary of Operating Reactor Events Meeting 86-46 on 861229.List of Attendees,Events Discussed & Summary of Presented Events That Will Be Input to NRC Performance Indicator Program Encl
ML20207P627
Person / Time
Site: Palo Verde, Surry, LaSalle, 05000000
Issue date: 01/12/1987
From: Holahan G
Office of Nuclear Reactor Regulation
To: Harold Denton
Office of Nuclear Reactor Regulation
References
OREM-86-046, OREM-86-46, NUDOCS 8701160336
Download: ML20207P627 (13)


Text

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, JAN 12 1997

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MEMORANDUM FOR: Harold R. D nton, Director Office of Nuclear Reactor Regulation FROM: Gary M. Holahan, Director Operating Reactors Assessment Staff

SUBJECT:

SUMMARY

OF THE OPERATING REACTORS EVENTS MEETING ON DECEMBER 29, 1986 - MEETING 86-46 On December 29, 1986, an Operating Reactor Events meeting (86-46) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on December 22, 1986. 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 provides a sumary of those presented events that will be input to NRC's performance indicator program as significant events.

AJ/

Gary M. Holahan, Director Operating Reactors Assessment Staff

Enclosures:

As stated cc w/ Encl.:

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'JAN 12 1997 Harold R. Denton cc: R. Vollmer C. Patel J. Taylor L. Rubenstein C. Heltemes E. Licitra R. Starostecki G. Knighton D. Ross A. Bournia T. Murley, Reg. I E. Adensam J. Nelson Grace, Reg. II J. Keppler, Reg. III R. D. Martin, Reg. IV J. B. Martin, Reg. V W. Kane Reg. I S. Ebneter, Reg. I R. Walker, Reg. II C. Norelius, Reg. III E. Johnson. Reg. IV D. Kirsch, Reg. V H. Thompson F. Miraglia R. Bernero

< T. Speis W. Russell T. Novak F. Schroeder W. Houston B. Sheron B. Boger D. Crutchfield E. Rossi G. Lainas V. Benaroya W. Regan D. Vassallo

,, ,E. Jordan

~J. Rosenthal R. Baer E. Weiss R. Hernan S. Showe S. Rubin G. Arlotto l

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JAN 19 1937 ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (86-46)

DECEMBER 29, 1986 NAME DIVISION NAME DIVISION G. Holahan ORAS/NRR K. Wolley EPER~

C. Patel DPLA/NRR D. Basdekas RES E. Adensam DBL /NRR E. Murphy ORAS/NRR E. Tomlinson DPLB/NRR J. Calvo DPLB/NRR W. Regan DPLB/NRR D. Muller DBL /NRR l J. Kauffman AE00 R. Emch PPAS/NRR G. Dick DPLB/NRR D. Crutchfield PWRB/NRR B. Boger PHFT V. Benaroya PAF0/NRR J. Stolz BWRB/NRR H. Bailey IE/EAB M. Chiramal AEOD G. Klingler IE/0RPB J. Stone IE/VPB K. Eccleston TOSB/NRR J. Rosenthal IE/EAB R. Baer IE/DEPER C. Rossi PWRA/NRR F. Schroeder PWRB/NRR R. Houston DBL /NRR R. Scholl ORAS/NRR M. Caruso ORAS/NRR M. Licitra NRR D. Tarnoff ORAS/NRR l

ENCLOSURE 2 3

OPERATING REACTORS EVENTS BRIEFING 86-46 DECEMBER 29, 1986-i PALO VERDE UNIT 3 DAMAGED ENGINE IN EMERGENCY DIESEL GENERATOR SURRY UNIT 2 FAILURE OF MAIN FEEDWATER PIPE -

UPDATE .

LASALLE UNITS I a 2 FAILURES OF SOR DIFFERENTIAL PRESSURE SWITCHES f

. . , . . - - . , , . . - - , - - _ _ , . . . , - , .__.._.n.,_..._...__ .

1/5/87 PALO VERDE UNIT 3 - DAMAGED ENGINE IN EMERGENCY DIESEL GENERATOR DECEMBER 23, 1986 - (E. LICITRA,-NRR) '

PROBLEM: "B" EMERGENCY DIESEL GENERATOR (EDG) FAILED DURING TEST DUE TO BROKEN PARTS (COOPER ENGINE)

CAUSE: UNKNOWN AT THIS~ TIME SIGNIFICANCE:

MAY AFFECT SCHEDULED MARCH 1987 FUEL LOAD DATE ON UNIT 3 MAY HAVE' GENERIC IMPLICATIONS FOR FACILITIES USING SIMILAR ENGINES l DISCUSSION:

i ON 12/23/86 IN 3RD HOUR OF 24-H0VR TEST, "B" EDG " THREW" '

TWO RODS AND PISTONS FROM N0, 9 BANK OF THE ENGINE THROUGH INSPECTION PORTS l' ENGINE CONTINUED TO RUN FOR ABOUT ONE HOUR AFTER FUEL AND AIR WERE SECURED (PROBABLY DUE TO LEAKING LUBE OIL)

ENGINE STOPPED BY INJECTING FIRE PROTECTION FOAM INTO ENGINE BLOCK

! BROKEN P' ARTS GATHERED FOR EXAMINATION, SAMPLES TO BE SENT OUT FOR METALLURGICAL ANALYSIS.

! CRANKCASE DRAINED i

CURRENTLY PULLING HEADS OFF CYLINDER BLOCK NO, 9 (AFFECTED BLOCK) AND ADJACENT BLOCKS

!. FOLLOW-UP:

COOPER AND 18E REPRESENTATIVES TO ARRIVE ONSITE TOMORROW

-NRR, 18E, AND REGION V CONTINUING TO FOLLOW THE EVENT i

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SURRY UNIT 2 - FAILURE OF MAIN FEEDWATER PIPE - UPDATE 1 DECEMBER 9, 1986 - (C. PATEL, NRR)

PROBLEM: AN 18-INCH MAIN FEEDWATER PIPE ON THE SUCTION SIDE OF FEEDWATER PUMP "A" FAILED CATASTROPHICALLY CAUSE: PRELIMINARY INFORMATION ATTRIBUTES CAUSE OF PIPING FAILURE TO EROSION OF PIPE WALL AND A PRESSURE TRANSIENT WHICH OVERLOADED THE THINNED WALL SECTION SIGNIFICANCE:

6 WORKERS INJURED (4 DIED, 2 IN SERIOUS OR STABLE CONDITION)

DISCUSSION:

ERROR IN MAINTENANCE OF MAIN STEAM TRIP VALVE (MSTV) BELIEVED TO BE A CAUSE OF SPURIOUS MSTV CLOSURE EROSION / CORROSION CONTRIBUTED TO FAILURE OF PIPE GEOMETRY, 0XYGEN CONTENT, AND WATER TEMPERATURE AB0VE APPROX.

250*F CONTRIBUTE TO EROSION CORROSION PITTING EXISTS, CORR 0SION PATTERN SIMILAR TO S.G.

J TUBE PROBLEMS LICENSEE PLANS TO DO ANALYSIS TO DETERMINE THE METALLURGICAL DETAILS OF THE FAILURE -

, LICENSEE INSPECTED UNIT 1 MFW SUCTION AND DISCHARGE PIPING.

THINNING BELOW THE CODE MINIMUM FOUND AT ADDITIONAL LOCATIONS.

LICENSEE PLANS TO INSPECT OTHER SYSTEM PIPING AND VISUALLY l INSPECT INSIDE OF MAIN STEAM LINES l

FOLLOW-UP:

i LICENSEE CONTINUING ITS EVALUATION OF TRANSIENT AND PIPE i FAILURE AIT PREPARING THE REPORT NRR, REGION II AND LICENSEE MEETING SCHEDULED FOR 1/12/87 IE INFORMATION NOTICE ISSUED ON DECEMBER 16, 1986 SURRY UNITS 1 & 2 WILL REMAIN SHUTDOWN FOR FIVE TO SEVEN WEEKS INSPECTION RESULTS AT NORTH ANNA FOUND TO BE ACCEPTABLE BY LICENSEE

l 12/29/86 LASALLE UNITS 1 & 2 - FAILURES OF SOR DIFFERENTIAL PRESSURE SWITCHES DECEMBER 18, 1986 - (G. HOLAHAN, NRR)

PROBLEM: 5 FAILURES OF SOR DIFFERENTIAL PRESSURE SWITCHES AT LASALLE UNITS 1 8 2 OVER A 14-MONTH PERIOD SAFETY SIGNIFICANCE:

DIFFERENTIAL PRESSURE SWITCHES IN SEVERAL SAFETY-RELATED APPLICATIONS hAVE FAILED OVER A SHORT PERIOD OF TIME RAISING RELIABILITY AND DESIGN CONCERNS DISCUSSION:

12/18/86 - COMMONWEALTH EDISON REPORTED THAT 5 SOR SWITCH FAILURES HAD OCCURRED SINCE OCTOBER 1985 ALL 5 FAILURES WERE RELATED TO FAILURES OF THE DIAPHRAGM (PIN-HOLE LEAKS OR TEARS)

FAILURES PRIOR TO JUNE 1986 WERE FOUND DURING NORMAL SURVEILLANCE TESTING FAILURES AFTER JUNE 1986 HAVE BEEN FOUND DURING THE AUGMENTED TEST PROGRAM FAILURES HAVE INVOLVED:

- UNIT 2 ADS PERMISSIVE (LEVEL 3)

- UNIT 2 RCIC LINE BREAK PROTECTOR

- UNIT 1 RHR MINI-FLOW ALARM PRIOR TO 12/18/86 LASALLE CONSIDERED THE FAILURES TO BE

" RAND 0M FAILURES" CAUSE OF THE DIAPHRAGM FAILURES IS STILL UNDER INVESTIGATION BY LASALLE AND SOR FOLLOW-UE:

NRR, 18E, AND REGION III ARE CONTINUING TO REVIEW THE FAILURES AND CORRECTIVE ACTION MEETING PLANNED FOR JANUARY 22, 1987 ADDITIONAL INFORMATION ON DIAPHRAGM FAILURES TO BE SUBMITTED l BY CECO ON JANUARY 1, 1987 1

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REACTOR SCRAM

SUMMARY

WEEK ENDING 12/28/86 I. PLANT SPECIFIC DATA DATE SITE UNIT POWER RPS CAUSE COMPLI- YTD YTD YTD CATIONS ABOVE BELOW TOTAL 15% 15%.

12/22/86 WOLF CREEK 1 30 A EQUIP / ELECT NO 5 2 7 12/22/86 ROBINSON 2 100 A EQUIP / ELECT NO 8 2 10 12/22/86 DAVIS BESSE -1 15 A EQUIP / MECHAN. NO O 1 1 12/23/86 MILLSTONE 2 50 A EQUIP / ELECT. NO 4 0 4 12/23/86 SALEM 2 9A EQUIP /LO COND V NO 5 0 8 12/24/86 OYSTER CREEK 1 2A EQUIPMENT NO 1 1 2 12/24/86 PALO VERDE 2 100 A EQUIPMENT YES G 2 10 12/26/86 RIVER BEND 1 100 A EQUIPMENT NO 16 2 18 12/27/86 TURKEY POINT 3 100 M EQUIPMENT YES 6 1 7 12/28/86 SALEM 2 77 A EQUIP /FD REG VL NO 6 3 9 12/20/86 DIABLO CANYON 1 6A EQUIPMENT NO 2 1 3 1

SUMMARY

OF COMPLICATIONS

~~TE, UNIT COMPLICATIONS

.)

TURVEY POINT 3 PRESSURIZER PORV DID NOT RESET -

PALO VERDE 2 SI PUMPS DEADHEADED l

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t II. COMPARISDN OF WEEKLY STA"ISTICS WITH INDUSTRY AVERAGES -

SCRAMS FOR WEEK ENDING 11/28/06 ,

CCRAM CAUSE POWER NUMBER 1986 1985 OF WEEKLY WEEKLY

, SCRAMS (5) AVERAGE -

AVERAGE YTD (3) (4)

\

00 POWER >15%

EQUIP. RELATED >15% 7 '

4.3 5.4 (68%)

PERS. RELATED(6) >15% 0 1.8 OTHER(7) >15%

2.0 (25%)

0 0.4 0.6 ( 7%)

oo Subtotal **

7 6.5 B.O C0 POWER <15%

EQUIP. RELATED <15% 4 PERS. RELATED <15% -

0 1.4 1.3 (54%)

0.8 0.9 (38%)

OTHER <15% 0 0.2 0.2 ( 8%)

00 Subtotal **

4 2.4 2.4 000 Total ***

11 8.9 10.4 r

NANUAL VS AUTO SCRANS TYPE NUMBER 1'996 1985 0F WEEKLY WEEKLY SCRAMS AVERAGE AVERAGE YTD MANUAL SCRAMS 1 0.9 AUTOMATIC SCRAMS 1.0 10 7.9 9.4 r

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_ NOTES 1.' '

PLANT SPECIFIC DATA BASED ON INITIAL REVIEW OF 50.72 REPOR 4

FOR THE WEEK OF INTEREST. PERIOD IS MIDNIGHT SUNDAY THRO HIDNIGHT SUNDAY SCRAMS ARE DEFINED AS REACTOR PROTECTIVE

.ACTUATIONS WHICH RESULT IN ROD MOTION, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCORD WITH A PLANT PROCEDURE. -

l. 2.

! RECOVERY C0f1 PLICATED BY EQUIPHENT FAILURES OR PERS UNRELA.TED TO CAUSE OF SCRAM.

3.

1985 INFORMATION DERIVED FROM RECENT ORAS PRELIMINAR UNPLANNED REACTOR TRIPS IN 1985. WEEKLY DATA DETERMINE TAKING TOTAL TRIPS IN A GIVEN CATEGORY AND DIVIDING BY 52 WEEK $/ YEAR.

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,. 4.

IN 1985. TNERE WERE AN ESTIMATED TOTAL OF 541 AUTOMATIC A j

MANUAL UNPLANNED REACTOR TRIPS AT S3 REACTOR $ (NOLDING POWER LICENSES). TNIS YIELDS AN AVERAGE RATE OF 5.B TRIPS REACTOR PER YEAR AND AN AVERAGE RATE OF 10.4 TRIPS ' PER WE FOR ALL REACTORS.

l 5.

l BASED ON 100 REACTORS NOLDING A FULL POWER LICENSE.

l 6.

PERSONNEL RELATED PROBLEMS INCLUDE NUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.

7.

'OTHER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIR I

CAUSES(L1GHTNING),5YSTEMDESIGN,ORUNKNOWNCAU$E.

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01/M/67 SIBNIFICANT EVENTS FFE9 EN:Y FEFI:F SNCE INDICATOR N:. 3 FLAN! NA"E EVENT EVE \T IES RIPi!0N S GNIFICANCE CIR DATE LASALLE : 12/19/86 FAILERES vF 5 9 D!rFEFENTIAL FFE35'JFE SWITC"ES FUTEt;TIAL FOR OR ACTUAL DE5?ADATICh C: 1

-THE FIVE FAILURES UNCOVERD Ai LASALLE OVER A SAFETY-RELATED E0V!FFENT 14-M] NTH FER:0D WERE FELATE; TO FAILUFES OF TvE DIAFHRAM (FIN 4CLE3 LEAR 1 CR TEMS)

Ui3ALLE 2 12/19/Ss FAILUREE OF SCF DIcFEFENTai FFESSURE SiliCHES - F0iEN'!at FCR CR A:T' J AL DEEWATION 0: 1 THE FIVE FAILUPES L%CCVERED DVER A 14-t] NTH SAFETY 4 ELATE 3 ECUIFFENT FERICS WERE FELATED TO FA! LURES OF TFE DIAFFR G (F:N-t0LES LERS 0; TEM 3)

FALO VEF:E 2 1:! 4/26 cA!LLEE 0: ik0 CF FOUR FFS LC31C P N E9 EUFLIES SCRAM KITH C0"FLICATICN3 1 FES'JLTED IN 14A7.ERTENT FEA TCP SCFM EITH MAIN STEAM ISO.ATION,$AFETY INJECTION ACTUAT!CN,FECIRC:1.ATICN ACTUAi!04 SYSTEM ACTUATION PAL 3 VER;E 3 1:!23/96 tJRIN3 TESTIN3,FAILUFE OF 'B'EI3.Th0 FISics F0 TENT:AL FOR 09 ACTUAL DIEU DA* ION CF 1 F:35 PROFE AND CA*E THFOUGH TwE SIDE OF TFE Sa'ETY-FELATED ECUIFMENT EN3:NE WHICH CONTIN"E2 TO RUN FUELED BV O!L IN CRAnCA!E TUDEYF0!NT; 1:/27/i! LC35 CF TUFBINE GI.EFNOR CCNTROL DIL FRE55URE - SCFA" WITH COMFLICATION3 1 CUR:NSL:AL FELUCTICN THE A'JTC"ATIC F:D INEERTICN FEATU'E OF THE F:D CONTROL SYSTEM FAILED TO IN!ERT R:03 - AFTER THE SCSA" F:EESCRIIER F RV Fa! LED TO FESET