ML20141F409

Summary of Operating Reactors Events Meeting 86-10 W/Ofc Director,Div Directors & Representatives Re Events Since 860324.Viewgraphs & Supporting Documentation Encl

ML20141F409
Person / Time
Site:	Oconee, Palisades, Oyster Creek, Braidwood, Brunswick, North Anna, Haddam Neck, Diablo Canyon, Robinson, San Onofre, Zion, 05000000
Issue date:	04/10/1986
From:	Holahan G Office of Nuclear Reactor Regulation
To:	Harold Denton Office of Nuclear Reactor Regulation
References
NUDOCS 8604230018
Download: ML20141F409 (20)

Text

W APR 10 SE MEMORANDUM FOR:

Harold R. Denton, Director Office of Nuclear Reactor Regulation FROM:

Gary M. Holahan, Director Operating Reactors Assessment Staff

SUMMARY

OF THE OPERATING REACTORS EVENTS MEETING ON March 31, 1986 - MEETING.86-10 On March 31, 1986, an Operating Reactor Events meeting (86-10) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on March 24, 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.

In addition, the assignment of follow-up review responsibility was discussed. The assignments made during this meeting and the status of previous assignments are presented in Enclosure 3.

Completion dates have been assigned for items in Enclosure 3.

Each assignee should review Enclosure 3 with regard to their respective responsibilities.

Note that several assignments are approaching the due date.

Please be responsive and advise ORAB (D. Tarnoff, x29526) if the target completion date cannot be met.

/v/

Gary M. Holahan, Director Operating Reactors Assessment Staff

Enclosures:

As stated cc w/ encl:

See next page

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ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (86-10)

MARCH 31, 1986 NAME DIVISION NAME DIVISION H. Denton NRR L. Engle PWR/NRR W. Regan PWRB/NRR J. Stone IE/VPB H. Rood PWRB/NRR E. Eranagan PWRB/NRR D. Ziemann DHFT V. Benaroya PWRA/NRR C. Miller PWRB/NRR C. Grimes ISAP0/NRR G. Knighton DLB/NRR R. Hernan PPAS/NRR N. Trehan DBL /NRR E. Leeds AE00/R0AB G. Murphy ORNL/N0AC E. Weinkam PWRA/NRR S. Rubin AE00/ROAB R. Jones PWRB/NRR H. Bailey IE/EAB H. Ornstein AE0D/R0AB D. Allison IE/EAB J. Giftter IE/EAB V. Hodge IE/EGCB E. Weiss IE/EAB A. Dromerick IE/EGCB

0. Parr PWRB/NRR F. Akstulewicz PWRB/NRR M. Virgilio ORAS/NRR J. T. Beard ORAS/NRR J. Zwolinski DBL /NRR R. Houston DBL /NRR F. Schroeder DPLB/NRR S. Varga PWRA/NRR E. Rossi PWRA/NRR T. Speis DSR0/NRR E. Jordan IE R. Auluck DBL /NRR L. Olshan PWRA/NRR I

D. Tarnoff ORAS/NRR J. Donohew DBL /NRR i

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ENCLOSURE 2 OPERATING REACTORS EVENTS BRIEFING 86-10 MARCH 31, 1986 NORTH ANNA UNIT 1 SPURIOUS MSIV CLOSURE AT FULL POWER WITH COMPLICATIONS SAN ONOFRE UNIT 2 COMMON MODE FAILURE OF BOTH SHUTDOWN COOLING TRAINS HADDAM NECK NEW SMALL BREAK LOCA RESULTS BRAIDWOOD UNIT 1 WATER HAMMER IN MAIN STEAM LINE OYSTER CREEK LEVEL SWITCH SETPOINT DRIFT 4

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g,%bb NORTH ANNA 1 - SPURIOUS MSIV CLOSURE AT FULL POWER WITH COMPLICATIONS MARCH 26, 1986 (J. GIITTER, IE)

PROBLEM:

A SINGLE MAINSTEAM TRIP VALVE (I.E. MSIV) INADVERTENTLY CLOSED WHILE THE UNIT WAS OPERATING AT 100% POWER.

SIGNIFICANCE:

FAILURE OF SINGLE VALVE INITIATES TRANSIENT WHICH RESULTS IN REACTOR SCRAM AND SAFETY INJECTION.

DISCUSSION:

AT 7:51 A.M. AN INADVERTENT CLOSURE OF THE "B" LOOP MAINSTEAM TRIP VALVE CAUSED STEAM FLOW TO BE DIVERTED TO THE OTHER TWO STEAMLINES.

STEAMLINE HIGH FLOW IN CONJUNCTION WITH LOW STEAMLINE PRESSURE RESULTED IN ESF ACTUATION SIGNAL.

ABOUT 900 GALLONS OF B0 RATED WATER INJECTED.

REACTOR SCRAM, EDG AUTO-START, AUX FEED AUTO-START, TRIP VALVES (MSIVs) CLOSURE, FW ISOLATION AND ALL OTHER ESF ACTUATIONS INITIATED AS DESIGNED.

ALL THREE CENTRIFUGAL CHARGING PUMPS AUTO-STARTED ON ESF SIGNAL BUT THIRD CHARGING PUMP DID NOT STOP.

FOLLOWING STEAM GENERATOR ISOLATION, STEAM PRESSURE ROSE TO PORV SETPOINT BUT PORVs DID NOT OPEN AUTOMATICALLY.

AFTER SAFETIES LIFTED, OPERATORS MANUALLY OPENED PORVs'.

DISCREPANCY BETWEEN IRM CHANNEL READINGS.

SOURCE RANGE CHANNEL (N-31) FAILED TO ENERGIZE.

UNUSUAL EVENT DECLARED.

OPERATIONS CENTER NOTIFIED AT 8:15 A.M.

UNUSUAL EVENT TERMINATED AT 8:48 A.M.

FOLLOW-UP:

LICENSEE CURRENTLY INVESTIGATING CAUSE OF THE MAINSTEAM TRIP VALVE CLOSURE AND THE RPS INSTRUMENTATION ANOMALY.

INADVERTENT CLOSURE OF AN MSIV AT A 4-LOOP WESTINGHOUSE PLANT DOES NOT RESULT IN A SAFETY INJECTION.

VEPC0 MAY RUN THE TRANSIENT ON THEIR SIMULATOR.

NORMAL SRI, REGIONAL FOLLOWUP

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gg'h SAN ONOFRE 2 - COMMON MODE FAILURE OF BOTH SHUTDOWN COOLING TRAINS MARCH 26, 1986 (H. ROOD, NRR)

PROBLEM:

LOSS OF BOTH LPSI PUMPS DUE TO AIR IN SUCTION LINES SIGNIFICANCE:

COMMON MODE FAILURE OF REDUNDANT SAFETY SYSTEMS GENERIC APPLICABILITY.

DISCUSSION:

PLANT IN COLD SHUTDOWN, FOR REFUELING RCS WATER LEVEL BEING REDUCED TO CENTER LINE OF HOT LEG TO FACILITATE RCP SEAL CHANGE 2 OUT OF 3 WATER LEVEL INSTRUMENTS NOT PROPERLY CALIBRATED; TYGON TUBE AND WIDE RANGE ELECTRIC CHANNEL BOTH READ HIGH.

NARROW RANGE ELECTRIC CHANNEL READ PROPERLY.

WATER LEVEL GOT T00 LOW.

VORTEXING AND AIR ENTRAINMENT LJCURRED: NOT FULLY RECOGNIZED BY OPERATORS OPERATORS SWITCHED BACK AND Ft.aH BETWEEN LPSI PUMPS.

WATER LEVEL INCREASED, AIR VENTED, S/D COOLING RESTORED WITHIN 1 HOUR 15 MINUTES RCS AVERAGE TEMPERATURE ROSE FROM 115* TO 180*F FOLLOW-UP:

NORMAL SRI, REGIONAL FOLLOW-UP

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HADDAM NECK - NEW SMALL BREAK LOCA RESULTS MARCH 2, 1986 (F AKSTULEWICZ, NRR)

PROBLEM:

THE LICENSEE IDENTIFIED A RANGE OF SMALL LINE BREAKS IN RCS LOOP 2 FOR WHICH SAFETY INJECTION FLOW WOULD BE INSUFFICIENT TO PREVENT CORE UNC0VERY.

SAFETY SIGNIFICANCE:

THE SPECIFIC BREAKS IN THE CHARGING LINE WOULD HAVE INADEQUATE LONG-TERM CORE COOLING FOLLOWING A LOSS-0F-COOLANT ACCIDENT AND COULD RESULT IN CORE DAMAGE, DISCUSSION:

SCENERIO - PROBLEM OCCURS DURING HI-PRESSURE RECIRCULATION MODE OF ECCS.

LOCA ANALYSIS FOR ISAP PROBABILISTIC STUDY SMALL BREAKS (0.02 FT

- 0,0l45 FT ) IN THE 3" DISCHARGE LINE OF INECTbNPOINTINTOTHERCSTHROUGHTHELOOP2 CO SING E LEG; BELIEVED TO BE PLANT-UNIQUE FEATURE.

PIPE BREAK SCENARIOS HAVE A PROBABILITY OF 8 x 10-5/YR ANALYSES TO DATE HAVE USED "BEST-ESTIMATE" VALUES; SINGLE FAILURES NOT INCLUDED, ANALYSES CARRIED OUT BEYOND REFLOODING FOLLOW-UP:

LICENSEE EVALUATING ALTERNATE MEANS OF PROVIDING HIGH PRESSURE RECIRCULATION CORE COOLING FOR THIS SCENARIO E.G., PIGGYBACK OF HPSI ONTO RHR LICENSEE WILL SUBMIT LER DESCRIBING THE ANALYTICAL DETAILS AND PROPOSED CORRECTIVE ACTIONS THIS WEEK, NRR WILL REVIEW TO ASSURE THE CORRECTIVE ACTIONS ARE ADEQUATE PRIOR TO RESTART, NRR WILL ASSESS THE POTENTIAL FOR GENERIC APPLICABILITY,

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PROBLEM:

DAMAGE TO MAIN STEAM PIPE SUPPORTS IN STEAM TUNNEL SIGNIFICANCE:

SEQUENCE CAUSED WATER HAMMER IN NON-SAFETY PART OF SYSTEM.

SEISMIC ANALYSIS REMAINS VALID.

DISCUSSION:

EVENT SEQUENCE:

HEATING SYSTEM, 2ND STAGE REHEATER DRAIN TANK LEAKED.

OPERATORS CLOSED MSIV BYPASS VALVES AND OPENED ALL 12 STEAM DUMP VALVES; GOT LOUD BANG.

DISTORTED 2 HANGERS IN UNANALYZED DIRECTION; STEAM LINE DROPPED 7 IN ; 3 SNUBBERS LOCKED UP LICENSEE REPLACED AND IMPOUNDED DAMAGED SUPPORTS, RESUMED TESTING PROGRAM.

CAUSE BELIEVED TO BE CONDENSATE ACCUMULATION IN PIPING LOW POINTS.

BYRON (SISTER PLANT IN OPERATION) CONSIDERING ADDITIONAL LOW POINT.

DRAINS FOLLOWUP:

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0YSTER CREEK - LEVEL SWITCH SETPOINT DRIFT 1/

MARCH 26, 1986 (J DON 0 HEW, ORPM, NRR)

IhU PROBLEM:

RCS WATER LEVEL SWITCHES INSTALLED IN SPECIAL OUTAGE TO MEET EQ RULE HAVE SIGNIFICANT DRIFT IN SETPOINT OUTSIDE OF TECHNICAL SPECIFICATIONS LIMITS, SIGNIFICANCE:

POTENTIAL GENERIC APPLICABILITY FOR PLANTS USING SAME SWITCH, DISCUSSION:

" STATIC 0-RING" SWITCHES PLACED IN RE-02 POSITION (LOW-LOW LEVEL ESF ACTUATION) AND RE-05 POSITION (LOW LEVEL REACTOR SCRAM);

ORIGINALLY BELIEVED TO BE "SIMILAR".

RE-05 SWITCHES SHOWED SIGNIFICANT SETPOINT DRIFT - SEE ATTACHED TABLE; RE-02s DID NOT, ON 4 OCCASIONS, AN RE-05 WAS DECLARED INOPERABLE AND REPLACED -

NO RE-02s REPLACED.

RUST FROM SWITCH INTERNALS FOUND IN ONE REPLACED RE-05 (2/27/86)

RE-02s HAVE SNAP-ACTION SWITCHES, RE-05s DO NOT, PLANT VOLUNTARILY SHUT DOWN (3/27/85) TO REPLACE ALL RE-05s WITH RE-02-TYPE SWITCH, PLANT TESTS ON 3/28 - 3/30/86 0F SPARE RE-02s AT RE-05-SETP0lNT SHOWED THAT SETPOINT VALUE (-60 IN VS. -90 INCHES) NOT A FACTOR.

PLANT RESTARTED 3/31/86.

FOLLOWUP:

NRR/PM WILL FOLLOW SURVEILLANCE RESULTS OF RE-02s/RE-05s, INCLUDING POSSIBLE EFFECT OF RUST, NRR/PM WILL DOCUMENT THE DIFFERENCES BETWEEN SWITCHES.

IE INF0, NOTICE WILL BE PROPOSED BY NRR, IF APPROPRIATE.

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REACTOR SCRAM

SUMMARY

WEEK ENDING 03/30/86 I.

PLANT SPECIFIC DATA DATE SITE UNIT POWER RPS CAUSE COMPLI-YTD CATIONS TOTAL gY 03/24/86 ZION

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2 99 A PERSONNEL YES 1

03/24/86 ROBINSON h0 bi 2

10 A EQUIP / TURBINE NO 6

T O,7 9

03/25/86 MCGUIRE 1

100 A EQUIP /FD RG VLV NO 2

03/26/86 NORTH ANNA 6E 1

100 A EQUIP /MSTV YES 3

03/26/86 BRUNSWICKGO' i

100 A EQUIP /TURB PEN YES 1

PALISADES G2', fqt) 1 03/26/86 60 4 EQUIP /TURB GEN NO 1

DIABLO CANYON 9 2

20 M EDUIP/ CONDENSER YES S

03/30/96

SUMMARY

OF COMPLICATIONS FITE UNIT COMPLICATIONS ZION 2 1 BUS DID NOT AUTO TRANSFER NORTH ANNA 1 SI ON ANTICIPATED TRANSIENT BRUNSWICK 1 HPCI/RCIC GRP1,GRP6 ISO GRV LIFT DIABLO CANYON 2 SI ACTUATION nI

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II. COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES SCRAMS FOR WEEK EllDING 03/30/86 SCRAM CAUSE POWER NUMBER NUMBER 1985 OF NORMALIZED (6)

WEEKLY j

SCRAMS (5)

TO 1985 AVERAGE (3)(4)

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• POWER >15%

EQUIP. RELATED

>15%

5 5.0 5.4 (68%)

PERS. RELATED(7) >15%

1 1.0 2.0 (25%)'

OTHER(8)

>15%

0 0.0 0.6 ( 7%)

• • Subtotal **

6 6.0 8.0

• • POWER <15%

EQUIP. RELATED

<15%

1 1.0 1.3 (54%)

PERS. RELATED

<15%

0 0.0

0. 9 (38%)

OTHER

<15%

0 O.O O.2 ( 8%)

• • Subtotal $3 1

1.0 2.4

• • • Total ***

7 7.0 10.4 MANUAL VS AUTO ECRAMS TYPE NUMBER NUMBER 1985 OF NORMALIZED WEEKLY SCRAMS TO 1985 AVERAGE MANUAL SCRAMS 1

1.0 1.0 AUTOMATIC SCRAMS 6

6.0 9.4

O NOTES 1.

PLANT SPECIFIC DATA BASED ON INITIAL REVIEW 0F 50.72 REPORTS FOR THE WEEK OF INTEREST.

PERIOD IS MIDNIGHT SUN THROUGH MIDNIGHT SUN. SCRAMS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN R0D MOTION, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE WITH A PLANT PROCEDURE.

2.

REC 0VERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAU.SE OF SCRAM 3.

1985 INFORMATION DERIVED FROM RECENT ORAS PRELIMINARY STUDY OF UNPLANNED REACTOR TRIPS IN 1985.

WEEKLY DATA DETERMINED BY TAKING TOTAL TRIPS IN A GIVEN CATEGORY & DIVIDING BY 52 WEEKS / YEAR 4.

IN 1985, THERE WERE AN ESTIMATED TOTAL OF 541 AUTOMATIC &

MANUAL UNPLANNED REACTOR TRIPS AT 93 REACTORS (HOLDING FULL POWER LICENSES).

THIS YlELDS AN AVERAGE RATE OF 5.8 TRIPS PER REACTOR PER YEAR & AN AVERAGE RATE OF 10.4 TRIPS PER WEEK FOR ALL REACTORS.

5.

BASED ON 93 REACTORS HOLDING A FULL POWER LICENSE, AS OF 2/1/86 6.

NORMAllZED VALUES ALLOW COMPARIS0N TO 1985 DATA BY MULTIPLYING ACTUAL 1986 VALUE BY:

93 REACTORS IN 1985 NUMBER OF REACTORS REPORTING 7.

PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS 8.

"0THER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.

ENCLOSURE 3 PagiNo.

1 04/08/96 OFERATINS REACTORS EVENTS MEET!hG F0!c.0WUP ITEMS AS OF MEETINS 26-10 CN MARCH 31. 1996 (IN ASCEN !NS MEETINE DATE, NSSS VENDER. FACILITY GRDERI MEETING FACILITY RESPONSIPLE TASA DE5CRIPTION SCHEDULE CLOSEDCATE COMMENTS NURSER /

NSES VENDOR /

DIVISICN/

CGMPLET.

BY DOCUMENT, FEETINS EVENT IESCRIP.

INDIVIDUAL DATE(S)

MEETINS. ETC.

DATE E5-13 TURKEY FOINT 3 PS2 /M!LH0AN J.

REvlEW ADEQUACY CF S0?ER'.0R 04/22/06 0 FEN

//

02/13/E5 W / FOST-TRIP

/

DESIGN CN TURPINE ERIVEN AFh 01/05/66 LOSS OF AFW PL?FS 10/13/55 E6-01 AS)AhSAS 1 IE /JORfAN E 1 ENTIFY WHAT IS ACTUAL IESIGN 04/20/E6 CFEN

//

01/27/36 18 / CESIE1

/

IN ElW FLANTS 03/!!/26 DEFICIENCY IN EMERSENCY FEEDWATER SYSTEM

$6-03 I"! I h;c /HOLAH N S CONS!:Ec SUSFLE" ENTAL IE NOTICE 03/!1/E6 CLOSED 01/31/26 01/27/26 IW / FARTIAL IE /J.M AN E CN FECEC it!P E;EA6E FF0ELESS IE NOTICE PE!NG LOSS OF NN1

/ /

ERAFTED 8H3 MCEUIRE l65/IIEMANN D FEVIEW NOVE*iER !.1985 M:SUIFE 04/30/E6 0CEN

//

01/27/S6 W / START-UD

/

EVENT /ND DETEFMINE IF FAILURE

/ /

WITH IESCAIED TO REFAIF VALVE MOTCR OFERATC5:

/ /

FFS! SYSTEM FRICR TO START-UP WAS IN VIOLATICN 0F TECH SFECS FEQ"IFEPEkT EH4 DRESIEN 3 NFR /IERNERO F DISCUSS WITH EkRS ChNEFS GFOUF 0!/II/E6 CLOSEC 03/31/E6 02/10/E6 GE / FIFE IN

/

THE FRCDEILITY OF FOLVORETFAnE

/ /

TASr EEINS IRYhELL ISNITINS ItFING OFEFATION AND

/ /

ACCOMPLISHED EUANSION GAP AFFENDII R COMPLIANCE ISSUE UN:ER TA: NO 60907 06-06 W PLANTS IE /JCPDANE FEVIEW REFCRTABILIT'! CF ITEMS 04/20/06 0 FEN

//

(3/03/86 W / SINSLE

/

SUCH AS SINGLE FAILUCE OF P-10 03/!!/06 FAILtFE CF INTE;LCD

/ /

NUCLEAR INSTFLMENTATICN INTEFLOCr F-10 86-10 SAN CNGFrf 2 IE /J0FDAN E CEVIEW ACEQUACY 0F rec 0RTINS CF 05/01/26 0 FEN

//

0;i31/26 CE / COMM2N MOLE

/

THIS EVENT

/ /

FAILUCE OF POTH

/ /

SHUTDChN CCCLING TRAINS 96-10 SAN ONCFFE 2 IE /J3FEAN E EVALUATE HEED F09 !E NOT!CE 05/01/86 0 FEN

//

0!/31/06 CE / C0950N MOLE

/

/ /

FAILURE OF POTH

/ /

SHUIDCWN COOLING TRAINS

r Pagp'No.

2

,04/03/S6 0FERATIh6 REACTORS EVENTS MEETINS FOLLOWUP ITEMS AS OF MEETING 86-10 DN MARCH 31, 1966 (IN ASCENDING BEEriNS DATE. NSSS VEND 0R, FACILITY ORDER)

MEET!h5 FACILITY RESPONSIBLE TASK DESCRIPTICN SCHEDULE CLOSED DATE COMMENTS N' SEER /

NSSS VEN 0R/

DIVISION /

CCMFLET.

Bf DOCUMENT, RETING EVENT DESCRIP.

INDIVIDUAL DATEfS)

MEETING,ETC.

DATE E6-10 OYSTER CSEEK NRR /MIRASLIA F CHECK ON TMI FOR USE OF SIMILAP 05/01/56 OPEN

/ /

03/31/26 EE / LEVEL

/

!alTCHES

/ /

SWITCH SETF0 INT

/ /

LRIFT E6-10 DYSTER CREEK hFR / HOUSTON W FESOLVE THE QUESTION CF ihE 06/30/26 0 FEN

/ /

03/31/86 SE / LEVEL

/

ACCEPTABILITY CF EL!hD SWITCHES

/ /

SWITCH SETFOINT ANL CELETICN OF OAILY CHANNEL

/ /

ERIFT LHECK 66-10 99AIDWD00 1 NRR /;CSSI E FEQUEST SEFC I Or EVENT FR0F C/01!!6 CTE%

/ /

03/;1/26 W / kATER

/

LICENSEE

/ /

HA*MER IN MAIN

/ /

STEAM LINE 86-10 ERAIDWDCD !

IE /J06 DAN E EVALUATE NEED FCR IE NOTICE C5/01/E6 0FE%

/ /

03/31/26 W / WATER

/

/ /

HAM"ER IN MAIN

/ /

STEAM LINE 96-10 F400AM NECF hER /SFEIS T ASSESS THE P0 TENT AL FOR M/30/06 0 FEN

/ /

03/31/26 W / NEW SMALL

/

GENERICAFFLICA5ILITY

/ /

IFEAK LOCA

/ /

FESULTS 86-10 WA;DA9 NECV NRR /RDSSI E ASSURE THAT TkE C0FFECTivE 05/01/86 CFEN

/ /

03/31/E6 W / NEW SMALL

/

ACT10NS A;E A: EQUATE PRICR TO

/ /

BREAK LOCA RESTART

/ /

FESULTS