ML20211P136

Summary of 860707 Operating Reactor Events Meeting 86-23 W/ Div Directors & Representatives Re Events Since Last Meeting on 860630.Notification of Inability to Meet Assigned Target Completion Dates for Actions Requested.Viewgraphs Encl

ML20211P136
Person / Time
Site:	Perry, Wolf Creek, Hope Creek, Vermont Yankee, Diablo Canyon, Waterford, Farley, Big Rock Point, Fort Calhoun, FitzPatrick, 05000000, 05000115
Issue date:	07/16/1986
From:	Holahan G Office of Nuclear Reactor Regulation
To:	Harold Denton Office of Nuclear Reactor Regulation
References
NUDOCS 8607230012
Download: ML20211P136 (14)

Text

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JUL 16 1l186 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 JULY 7, 1986 - MEETING 86-23 On July 7, 1986, an Operating Reactor Events meeting (86-23) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on June 30, 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 followup 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 ORAS (D. Tarnoff, X27864) if the target completion date cannot be met.

M/

Gary M. Holahan, Director Operating Reactors Assessment Staff

Enclosures:

As Stated cc w/ Encl.:

See Next Page

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R. Vollmer W. Long J. Taylor D. Muller.

C. Heltemes J. Zwolinski T. Murley, Reg. I D. Mcdonald J. Nelson Grace, Reg. II H. Bailey J. Keppler, Eeg. III L. Rubenstein R. D. Martin, Reg. IV J. Stefano J. B. Martin, Reg. V W. Butler R. Starostecki, Reg. I V. Rooney S. Ebneter, Reg. I P. Leech R. Walker, Reg. II D. Clark C. Norelius, Reg. III M. Grotenhuis E. Johnson. Reg. IV J. Hopkins D. Kirsch, Reg. V E. Sylvester H. Thompson G. Gears F. Miraglia T. Colburn R. Bernero T. Speis W. Russell T. Novak F. Schroeder W. Houston B. Sheron F. Rowsome D. Crutchfield G. Lainas V. Benaroya W. Regan D. Vassallo E. Jordan E. Rossi R. Baer E. Weiss R. Hernan S. Showe S. Rubin H. Alderman

JUL 16 ses ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (86-23)

JULY 7, 1986 NAME DIVISION NAME DIVISION H. R. Denton NRR B. D. Liaw NRR/ DBL G. M. Holahan NRR/0 RAS D. Muller NRR/ DBL M. Virgilio NRR/0 RAS R. Benedict NRR/ DBL E. Weinkam NRR/DPLA V. Benaroya NRR/PWRA C. Berlinger NRR/PWRA W. Paulson NRR/PWRB R. Hermann NRR/ DBL A. Dromerick IE/DEPER G. Klingler IE/DI J. Stone IE/QAVT H. Ornstein AE0D/R0AB E. Brown AE0D/R0AB E. Jordan IE/DEPER T. Novak NRR/PWRA R. Houston NRR/ DBL D. Humenansky OCM F. Schroeder NRR/PWRB F. Rowsome NRR/DHFT J. Hopkins NRR/DPLA V. Rooney NRR/ DBL W. Regan NRR/PWRB D. Tarnoff NRR/0 RAS

ENCLOSURE 2 OPERATING REACTOR EVENTS BRIEFING 86-23 JULY 7, 1986 PERRY FIRE IN OFFGAS CHARC0AL BEDS BWRs-RESIbUALHEATREMOVALPUMP/WEARRING FAILURES - FOLLOWUP PWRs - INADEQUATE DESIGN OF ECCS PUMP MINIMUM FLOW PATHS OTHER EVENT OF INTEREST VERMONT YANKEE PROBLEMS WITH SCRAM SOLEN 0ID VALVES - UPDATE I

PERRY - FIRE IN OFFGAS CHARC0AL BEDS JULY 6, 1986 (H. BAILEY, IE)

PROBLEM:

FIRE IN CONDENSER OFFGAS BEDS SIGNIFICANCE:

RECURRENCE OF JUNE 20, 1986 FIRE FIRE IN CHARC0AL BEDS WOULD CAUSE UNCONTROLLED RELEASE IF 1

PLANT HAD OPERATED FOR EXTENDED PERIOD NO WATER DELUGE SYSTEM IS AVAILABLE TO SUPPRESS A FIRE IN THESE CHARC0AL BEDS CIRCUMSTANCES:

UNIT IN COLD SHUTDOWN.

CHARC0AL BED TEMPERATURES INDICATED ABOUT 80F, NITROGEN HAD BEEN MAINTAINED IN BEDS FOR 14 DAYS FOLLOWING THE FIRE ON JUNE 20, 1986.

REC 0VERY PLAN DEVELOPED FOLLOWING 6/20/86 FIRE THAT INCLUDES SAMPLING AND ANALYSIS PROGRAM FOR CHARC0AL ABSORBER AND FUNCTIONAL TEST OF THE SYSTEM.

6/26/86 INITIAL SAMPLES DRAWN FROM FILTER VAULT "14B".

ANALYSIS CURRENTLY BEING PERFORMED PERFORMING AIR PURGE OF THE CHARC0AL BEDS TO EQUALIZE TEMPER-ATURES PRIOR TO VAULT REFRIGERATION TEST.

N0 HEATERS WERE IN THE VAULT.

S00N AFTER AIR PURGE BEGAN, THE FILTER VAULT 14A AND 14B MIDDLE TEMPERATURES INDICATED 656F AND 578F RESPECTIVELY.

DECLARED UNUSUAL EVENT AIR PURGE WAS STOPPED AND A NITROGEN PURGE WAS STARTED.

1 MIDDLE TEMPERATURES DECREASING.

BOTTOM TEMPERATURES G0ING UP.

i FOLLOWUP:

CHARC0AL VENDOR REPORTS THAT IGNITION TEMPERATURE IS LOWERED BY PREVIOUS FIRE.

IGNITION TEMPERATURE MAY BE AS LOW AS 300F, LICENSEE BELIEVES THE VERY LOW THERMAL CONDUCTIVITY OF BEDS MAY HAVE LEFT HOT SPOTS DURING PREVIOUS NITROGEN PURGE.

LICENSEE PLANS TO CONTINUE NITROGEN PURGE AND DEVELOP A PLAN TO REPLACE THE CHARC0AL IN 14A AND 14B BEDS.

1

BWRs-RESIDUAL HEAT REMOVAL PUMP / WEAR RING FAILURES - FOLLOWUP (R

HERMANN, NRR)

PROBLEM:

IGSCC 0F LOWER IMPELLER WEAR RING RESULTING IN THE P0TENTIAL FOR PUMP PERFORMANCE DEGRADATION OR FAILURE 410 MARTENSITIC STAINLESS STEEL HIGHLY HARDENED CONDITION IS SUSCEPTIBLE TO IGSCC SIGNIFICANCE:

LOSS OF LHSI AND LONG TERM COOLING FOLLOWING A DBA CIRCUMSTANCES:

BROWNS FERRY UNIT 2 (LER 86-06 RECEIVED 6/6/86)

CRACKING IDENTIFIED IN PUMPS 2A & 2D METALL0 GRAPHIC ANALYSIS OF 2D LOWER WEAR RING CONFIRMED IGSCC ADDITIONAL INFORMATION - TELECONS WITH BROWNS FERRY - 7/1 & 2/86 CRACKING IDENTIFIED IN LOWER WEAR RINGS IN PUMPS 2B & 2C LOWER WEAR RINGS REMAINED IN PLACE IN ALL CASES OTHER AFFECTED PLANTS PILGRIM COOPER VERMONT YANKEE FOLLOW-UP NRR RECOMMENDATIONS RHR PUMPS BE INSPECTED AND REPAIRED AS NECESSARY PUMP INSPECTIONS BE PERFORMED WITH UNIT AT POWER (1 PUMP OUT OF 4 AT A TIME)

LCO's BE ADJUSTED, IF REQUIRED, TO BE CONSISTENT WITH PUMP REINSPECTION AND REPAIR TIME PILGRIM COMMITTED TO INSPECT 2 RHR PUMPS COOPER & VERMONT YANKEE CONTACTED LICENSEES PROPOSED ACTION PLAN DUE BY 7/11/86

Attachm:nt 1 IN 86-39 May 20, 1986

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Lower Impeller Wear Ring FIGURE 1 - Typical CVIC RHR Pump Sectional Assembly

PWRs - INADEQUATE DESIGN OF ECCS PUMP MINIMUM FLOW PATHS JUNE 25, 1986 (J. HOPKINS, NRR)

PROBLEM:

LOSS OF ECCS PUMP MINIMUM FLOW PATH DUE TO INADEQUATE DESIGN RESULTING IN SINGLE FAILURE VULNERABILITY SIGNIFICANCE:

POTENTIAL LOSS OF ECCS PUMPS DURING A SMALL BREAK LOCA DISCUSSION:

1984 AND 1985, BRUNSWICK, PEACH BOTTOM, AND POINT BEACH IDENTIFIED POTENTIAL FOR LOSS OF ECCS PUMP MINIMUM FLOW PATHS IE NOTICE 85-94 ISSUED DECEMBER 13, 1985 GE IDENTIFIED POTENTIAL FOR LOSS OF MINIMUM FLOWPATHS AT SEVERAL BWRs IE BULLETIN 86-01 ISSUED MAY 23, 1986 FOR GE BWRs ONLY JUNE 25, 1986 - TURKEY POINT IDENTIFIES POTENTIAL FOR LOSS OF MINIMUM FLOW PATHS DUE TO LOSS OF INSTRUMENT AIR MINIMUM FLOW RECIRCULATION VALVES BLOCKED OPEN ADMINISTRATIVE CONTROLS IN PLACE FOR CLOSURE OF VALVES WHEN NECESSARY FOLLOWUP:

IE BULLETIN TO ADDRESS PWRs UNDER DEVELOPMENT

OTHER EVENT OF INTEREST VT, YANKEE - PROBLEMS WITH SCRAM S0LEN0ID VALVES (UPDATE)

JUNE 14, 1986 (ERIC WEISS, IE)

PROBLEM:

1 R0D FAILED TO MOVE AND 5 RODS HESITATED 5 SECONDS BEFORE MOVING BECAUSE OF PROBLEMS WITH SCRAM SOLEN 0 IDS SIGNIFICANCE:

LICENSEE WENT CRITICAL WITH IN0PERABLE RODS MANUFACURING DEFECTS OF REBUILD KITS-MAY AFFECT OTHER PLANTS INADEQUATE POST-MAINTENANCE TESTING OF SCRAM S0LEN0 IDS CORE DAMAGE POSSIBLE IF TWO STUCK RODS ARE ADJACENT CIRCUMSTANCES:

SCRAM TIME TESTS PERFORMED FOLLOWING A SYSTEM HYDR 0 AFTER IN-SEQUENCE CRITICAL TEST AND S/D MARGIN TESTS ALL SCRAM S0LEN0 IDS HAD BEEN REBUILT FOR NORMAL PREVENTATIVE MAINTENANCE (0NCE EVERY 5 YEARS)

R0D CONDITION CAUSE 06-23 N0 SCRAM SPRING ON PLUNGER OUT OF PLACE 38-23 5 SEC DELAY DIAPHRAGM INSTALLED BACKWARDS 10-23 DIMENSIONS OF CONE ON PLUNGER 18-11 26-23 22-35 VT. YANKEE HAD 200 0F REBUILD KITS FROM LOT OF 3000 DISTRIBUTED BY GE WHICH HAS ONLY 200 KITS LEFT APPLICABLE TO BWR 2, 3, 4, AND SOME Ss SPRINGS IN REBUILD KITS HAVE OUT-0F-TOLERANCE INNER DIAMETER PLUNGER LAND HAS OUT-0F-TOLERANCE OUTER DIAMETER S

EN0lD B SE B SSEMB ES ARE OUT 0 -R0 ND COULD PREVENT FREE TRAVEL OF PLUNGER i

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. VERMONT YANKEE CIRCUMSTANCES: CONTINUED SOME TESTS SHOW PROBLEM AFTER A FEW CYCLES SOME TESTS SHOW NO PROBLEM AFTER REASSEMBLY BACKUP SCRAM VALVE WILL CAUSE SCRAM KITS USED TO BE DISTRIBUTED AS " COMMERCIAL GRADE" GE HAS EXAMINED 200 REBUILD 1:ITS FOR VERMONT YANKEE - IDENTIFIED NUMEROUS PROBLEMS GE HAS ISSUED A RAPID INFORMATION COMMUNICATION SERVICES INFORMATION LETTER (RICSIL)

FOLLOWUP:

IE INFORMATION NOTICE IS'UNDER DEVELOPMENT IE VENDOR INSPECTION IS PLANNED f

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REACTOR SCRAM

SUMMARY

WEEK ENDING 07/06/86 I.

PLANT SPECIFIC DATA t-I DATE SITE UNIT POWER RPS CAUSE COMPLI-YTD CATIONS TOTAL 06/30/86 WATERFORD 3

100 A EQUIP / INST. FAIL NO 3

06/30/86 WOLF CREEK 1

100 A EQUIPMENT NO 3

06/30/86 HOPE CREEK 1

1M EQUIP /Rx CONTRO NO 2

06/30/86 VERMONT YANKEE 1

OA EQUIP / INST.

NO 1

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07/01/86 WOLF CREEK 1

20 A PERSONNEL NO 4

7 07/01/86 BIG ROCK POINT 1

'90 A EQUIP / ELECT.

NO 1

07/02/86 FORT CALHOUN 1

100 A EQUIP / ELECT.

NO 1

07/02/86 FARLEY 1

99 A EQUIP / CTRL ROD NO 4

07/03/86 FITZPATRICK 1

100 A EQUIP / ELECT.

NO 2

07/03/86 DIABLO CANYON 2

7A EQUIPMENT YES 8

07/04/86 HOPE CREEK 1

1A EQUIP / ELECT.

NO 3

07/05/86 DIABLO CANYON 2

20 A EQUIP /MFW NO 9

SUMMARY

OF COMPLICATIONS SITE UNIT COMPLICATIONS DIABLO CANYON 2 SI INJECTION ON HIGH STEAM FLOW SIGNAL 4

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i-II. COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES SCRAMS FOR WEEK ENDING 07/06/86 SCRAM CAUSE POWER NUMBER 1986 1985 OF WEEKLY WEEKLY SCRAMS (5)

AVERAGE AVERAGE YTD (3) (4) i

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• • POWER >15%

EQUIP. RELATED

>15%

7 4.4 5.4 (68%)

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PERS. RELATED(6) >15%

1 2.1 2.0 (25%)

OTHER(7)

>15%

O O.2 0.6 ( 7%)

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• • Subtotal **

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6.7 8.0

• • POWER <15%

T EQUIP. RELATED

<15%

4 1.6 1.3 (54%)

PERS. RELATED

<15%

0 1.1 0.9 (38%)

OTHER

<15%

0 0.1 0.2 ( 8%)

• • Subtotal **

4 2.8 2.4

• • • Total ***

12 9.5 10.4 MANUAL VS AUTO SCRAMS TYPE NUMBER 1986 1985 OF WEEKLY WEEKLY SCRAMS AVERAGE AVERAGE YTD MANUAL SCRAMS 1

0.8 1.0 AUTOMATIC SCRAMS 11 8.7 9.4

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PLANT SPECIFIC DATA BASED ON INITIAL REVIEW OF 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 ROD MOTION, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE WITH A PLANT PROCEDURE, 2.

RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAUSE 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 AND DIVIDING BY 52 WEEKS / YEAR.

4.

IN 1985, THERE WERE AN ESTIMATED TOTAL OF 5til AUTOMATIC AND MANUAL UNPLANNED REACTOR TRIPS AT 93 REACTORS (HOLDING FULL POWER LICENSES).

THIS YIELDS AN AVERAGE RATE OF 5.8 TRIPS PER REACTOR PER YEAR AND AN AVERAGE RATE OF 10.4 TRIPS PER WEEK l

FOR ALL REACTORS.

l 5.

BASED ON 97' REACTORS HOLDING A FULL POWER LICENSE *.

6.

PERSONNEL RELATED PROBLEMS 1.NCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.

7.

"0THER" 1NCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.

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9 ENCLOSURE 3 Pa;e No.

1 07/14!96 05ERATINS REACTORS EVENTS MEETINS FOLLOW'jP ITEMS AS OF NEETINS 26-23 CN JULY 7, IC96 (INASCENDINGMEETINSDATE,NSSSVEOCR,FACILITYORDER)

"EETINS FACILITY REEF:NS!!LE TASK IESCRIPTION SCHEDULE CLOSEDCATE CCMMENTS NUx!EP/

hiss VE9 0R/

IIVISICN/

CCMPLET., EY DOC'.NENT, MEEi:NS EVENT OESCRIP.

IK!VIDUAL DATE(S)

• EETINS,ETC.

DATE S1-10 CfSTES CREEK NRR /0 USTON W RES3LVE THE QUESi!CN Cc THE 10/!0/66 OPEN

/ /

FOLLOWUP AC"!0N TO 0 /!!/E6 SE / '.EVEL

/

ACCEPTABILITY OF BLIND SWITCHES

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EE !!:0RFCRATED IN Sd!!CH SETFO!NT A W DELET!0N Of ta!LY CH MNEL

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REVIEW 0F TJNE RIFT CFECK 1,1926 EVENT AT LASSALLE E6-21

'/EMCNT YANFEE NER /FDLAHAN 6.

DETERMINE STATUS AND 08/20/86 CPEN

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06/2!/!6 GE / 'RCELEMS

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EFFECTIVENESS OF STAFF AND

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WITN SCRAM LICEMSEE ACT!0N ON

/ /

SQLENSIDVALVES POST-MAINTENANCE TESTINS (SL 23-28).tEVELCDRECGM9ENDATICNS FOR FURTHER ACTION Ee-2:

TU9EY FSINT NSR / ROSA F.

CCNS!:ERREVIEW!h3ELECTRitAL 02/!0l96 CFEM

/ /

06/23/56 W /FOTE".TIAL

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SYSTEM OF PL 4 T WITH SIMILAR

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FAIL';RE OF ALL SWING BUS IESISN

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EMERGEN;VDIEEEL SENEFATCRS 96-23 PERiY N'R /H0;STCN W.

09?AIN AND REVIEW INFCRMATION 09/29/86 C;EN

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07/07/!6 SE / FIFE IN

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RELATEDTCRE:tiRFENCEOFFIRE

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OFF313 CH:RC 4L AC INVESTIEATE PR:80 SED

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25-23 MU'.i!

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IETEoPINEA:FF0PPIATE 09/!0/96 C*EN

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RES'1LAi0cY REQU!FE*ENTS SA!!D

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fi'!-RES!!UAL CN RE 0M?.EEATI:15 DISCL53ED AT / /

FEai FEMOVAL ERIEFINS F "F/WEA' RINS FaILL*ES -

'2LLNJ i6-23 MU'.TI NRR /BE9 LINGER C.

A?3tFENRRAND!ECC:5DINATILN 09/!0/96 CPEN

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