ML20202G171

Summary of Operating Reactor Events Meeting 86-22 on 860630 W/Ofc Director,Div Directors & Representatives to Discuss Events Occurring Since 860623.List of Attendees & Viewgraphs Encl

ML20202G171
Person / Time
Site:	Fermi, Catawba, Vermont Yankee, 05000000
Issue date:	07/08/1986
From:	Holahan G Office of Nuclear Reactor Regulation
To:	Harold Denton Office of Nuclear Reactor Regulation
References
IEB-86-001, IEB-86-1, IEB-86-13, IEIN-85-094, IEIN-85-94, IEIN-86-053, IEIN-86-53, NUDOCS 8607150318
Download: ML20202G171 (17)

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• 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 JUNE 30, 1986 - MEETING 86-22 On June 30, 1986, anOperatingReactorEventsmeeting(86-22)washeldto brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on June 23, 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.

AU Gary M. Holahan, Director Operating Reactors Assessment Staff

Enclosures:

As Stated cc w/ Encl.:

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July 8,1986 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 JUNE 30, 1986 - MEETING 86-22 On June 30, 1986, an Operating Reactor Events meeting (86-22) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on June 23, 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 dr.te. Please be responsive and advise ORAS (D. Tarnoff, X27864) if the target completion date cannot be met.

N Gary . Ho ahan, Director Operating Reactors Assessment Staff

Enclosures:

i As Stated '

cc w/ Encl.:

See Next Page

K 08 M Harold R. Denton cc: R. Vollmer K. Jabbour J. Taylor B. J. Youngblood C. Heltemes D. Lynch T. Murley, Reg. I E. Adensam J. Nelson Grace, Reg. II V. Rooney J. Keppler, Reg. III D. Mcdonald R. D. Martin, Reg. IV J. Hopkins J. B. Martin, Reg. V L. Rubenstein R. Starostecki, Reg. I D. Muller 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 D. Ziemann D. Crutchfield G. Lainas V. Benaroya W. Regan '

D. Vassallo E. Jordan E. Rossi R. Baer E. Weiss R. Hernan S. Showe S. Rubin l

1 i

ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (86-22)

JUNE 30, 1986 NAME DIVISION NAME DIVISION L. Vaughan IE/VPB W. Haass IE/VPB D. Crutchfield NRR/PWR-B W. Regan NRR/PWR-B D. Vassallo NRR/ DBL K. Eccleston NRR/PPAS B. Clayton NRR/PWR-A J. Hopkins NRR/ PAD-2 J. Smith IE/0RPB G. Murphy ORNL/N0AC V. Thomas IE/EGCB A. Dromerick IE/DEPER/EGCB F. Rosa NRR/DPLA/EICSB S. Weiss NRR/DPLA/EICSB W. Paulson NRR/PWR-B E. Weiss IE/DEPER/EAB M. Chiramal AE0D S. Rubin AE0D F. Rowsome NRR/DHFT T. Novak NRR/PWR-A G. Holahan NRR/0 RAS M. Virgilio NRR/0 RAS

. J. Rosenthal IE/EAB F. Miraglia NRR/PWR-B F. Schroeder NRR/PWR-B G. Lainas NRR/ DBL ,

E. Rossi NRR/PWR-A R. Baer IE/DEPER J. Beard NRR/0 RAS t

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ENCLOSURE 2 OPERATING REACTORS EVENTS BRIEFING 86-22 JUNE 30, 1986 CATAWBA 1 DEGRADATION OF AUXILIARY FEEDWATER SYSTEM DUE TO FUSE FAILURE CATAWBA 2 MULTIPLE DEFICIENCY IN REMOTE SHUTDOWN CAPABILITY CAUSE DEPRESSURIZATION AND C00LDOWN TRANSIENT IMPROPER INSTALLATION OF HEAT SHRINKABLE TUBING ON ELECTRICAL CABLE SPLICES - UPDATE FERMI 2 MSIV SPRING FAILURE - UPDATE VERMONT YANKEE PROBLEMS WITH SCRAM S0LEN0ID VALVES - UPDATE ,

PWRs INADEQUATE DESIGN OF ECCS PUMP MINIMUM FLOW PATHS COMPARIS0N OF FIRST SIX MONTHS 1986 TRIP RATE DATA

CATAWBA UNIT 1 - DEGRADATION OF AUXILIARY FEEDWATER SYSTEM DUE TO FUSE FAILURE JUNE 22, 1986 (K. JABBOUR, NRR)

PROBLEM: FUSE FAILURES RESULTED IN DEGRADATION OF BOTH TRAINS OF ELECTRIC MOTOR DRIVEN AUXILIARY FEEDWATER SYSTEMS SIGNIFICANCE:

POTENTIAL FOR COMMON MODE FAILURE IN PROTECTION SYSTEMS LOGIC CIRCUITS GENERIC IMPLICATION FOR OTHER PLANTS USING THE SAME FUSES CIRCUMSTANCES:

JUNE 22, 1986 - PLANT IN MODE 4 (H0T SHUTDOWN)

LOSS OF MAIN FEED PUMPS AND MAIN FEEDWATER ISOLATION PROVIDED DEMAND SIGNAL FOR AUXILIARY FEEDWATER SYSTEM "A" AUXILIARY FEEDWATER PUMP DID NOT START, SOME TRAIN "A" VALVES FAILED TO RE-POSITION, TRAIN "B" PUMP STARTED BUT "B" RUN0VT PROTECTION VALVE FAILED TO CLOSE (SYSTEM DESIGNED TO CLOSE VALVE ON HIGH FLOW)

OPERATORS SECURED AUXILIARY FEEDWATER AND ESTABLISHED LEVEL CONTROL USING MAIN FEEDWATER SYSTEM LICENSEE EVALUATION OF FAILURE DETERMINED BOTH TRAIN "A" AND -

TRAIN "B" AUXILIARY FEEDWATER PROBLEMS WERE AS A RESULT OF FUSE FAILURES BUSSMANN (DIVISION OF MCGRAW EDISON) FNA TYPE FUSES DETERMINED TO HAVE FAILED MECHANICALLY AT SOLDER POINTS REVIEW 0F RECORDS SHOW BOTH TRAINS OF AUXILIARY FEEDWATER SYSTEM FUNCTIONED PROPERLY ON MAY 17, 1986 SIMILAR FAILURES OCCURRED AT MCGUIRE IN 1981 AND NOVEMBER 1985 RESULTING IN REACTOR SCRAMS DUKE HAS IN EFFECT, A PROGRAM TO REPLACE THESE FUSES AT BOTH CATAWBA AND MCGUIRE FOLLOWUP:

REGION II AND NRR FOLLOWUP ON PLANT-SPECIFIC AND GENERIC ASPECTS OF THIS EVENT

CATAWBA UNIT 2 - MULTIPLE DEFICIENCIES IN REMOTE SHUTDOWN CAPABILITY CAUSE DEPRESSURIZATION AND C00LDOWN TRANSIENT JUNE 27, 1986 (K. JABBOUR, NRR)

PROBLEM: INADEQUATE PROCEDURES AND TRAINING AND MISLABELED CONTROLS RESULTED IN A SEVERE TRANSIENT DURING A TEST OF THE REMOTE SHUTDOWN PANEL SIGNIFICANCE:

INADEQUATE REMOTE SHUTDOWN CAPABILITY RAPID C00LDOWN AND DEPRESSURIZATION OF PRIMARY SYSTEM DISCUSSION:

UNIT 2 WAS AT 24% POWER LOSS OF CONTROL ROOM TEST WAS BEING PERFORMED FOLLOWING TRANSFER TO REMOTE SHUTDOWN PANEL, THREE REQUALIFICATION OPERATORS LEFT CONTROL ROOM AND ESTABLISHED CONTROL FROM THE REMOTE SHUTDOWN PANEL REMOTE SHUTDOWN PANEL HAS INDICATORS FOR STEAM GENERATOR PRESSURE AND STEAM SIDE PORVs PRESSURE SETPOINTS OPERATOR WAS INSTRUCTED BY PROCEDURE TO SET PRESSURE; HOWEVER, IN EFFECT, OPERATOR WAS OPENING THE FOUR PORVs PRESSURIZER LEVEL DROPPED; PRESSURE WENT DOWN FROM 2250 PSIG TO 702 PSIG AND TEMPERATURE WENT DOWN FROM 550*F TO 455'F IN 6 MINUTES AFTER APPROXIMATELY 6 MINUTES, CONTROL ROOM OPERATORS RECOGNIZED TRANSIENT, REQUESTED TRANSFER BACK TO THE CONTROL ROOM AND TERMINATED HE T'1T UPON TRANSFER OF CONTROL DURING THE TRANSEcNT, THERE EXISTED A VALID SAFETY INJECTION DEMAND SIGNAL. HOWEVER, SIGNAL IS BLOCKED (BY DESIGN) WHEN TRANSFER TO REMOTE SHUTDOWN IS PERFORMED. UHI WAS MANUALLY ISOLATED THROUGHOUT THE EVENT UNIT WAS SUBSEQUENTLY BROUGHT TO MODE 3 CONDITIONS FROM THE CONTROL ROOM AIT DISPATCHED 'O THE SITE FOLLOWUP: I NRR EVALUATING ACCEPTABILITY OF DESIGN OF REMOTE SHUTDOWN PANEL AIT SCHEDULED TO EXIT SITE JULY 1, 1986

l IMPROPER INSTALLATION OF HEAT SHRINKABLE TUBING ON ELECTRICAL CABLE SPLICES - UPDATE (J. T. BEARD, NRR)

PROBLEM:

IMPROPER INRTALLATION DUE TO LACK OF PLANT ENGINEERING INVOLVEMENT AND/0R UNDERSTANDING INADEQUATE QUALITY CONTROL INSPECTION LACK OF CLEAR ACCEPTANCE CRITERIA WIDE, BUT UNDEFINED, APPLICABILITY -

SIGNIFICANCE:

COMMON MODE FAILURE MECHANISM AFFECTING REDUNDANT PORTIONS OF MULTIPLE SAFETY SYSTEMS AND CONTROL SYSTEMS GENERIC APPLICABILITY DISCUSSION:

IE INFORMATION NOTICE 86-53 ISSUED WHICH DESCRIBES PROBLEM AND IDENTIFIES ~SEVERAL PLANTS AFFECTED NATURE OF DISCREPANCIES:

BARE COPPER WIRES EXPOSED IMPROPER TUBING DIAMETER USED CAUSI'R EXCESSIVE STRESS, INADEQUATE ELECTRICAL INSULATION IMPROPER OVERLAP ONTO CABLE JACKET; INADEQUATE WATER SEAL APPLIED OVER BRAIDED / FABRIC JACKET C0VERINGS - M0ISTURE INGRESS EXCESSIVE BENDING 0F SPLICES, BEFORE COOLED

~

LACK OF INDIVIDUAL WIRES BEING SEALED IN BREAK 0UTS MANY INSTALLATIONS INVALIDATE EQUIPMENT QUALIFICATION NRC TRAINING AT RAYCHEM JUNE 26 - 27, 1986 RAYCHEM SELLS BULK TUBING AND PRE-ENGINEERED KITS RAYCHEM ASSUMES THAT USE OF BULK TUBING IS SPECIFIED BY PLANT ENGINEERS WHO HAVE ADEQUATE INFORMATION ON HOW TO SELECT TUBING FOR EACH TYPE APPLICATION INSTALLERS APPARENTLY FREQUENTLY DO NOT APPRECIATE ENGINEERING CONSIDERATIONS REPAIR ACTIONS MAY BE WRONG F0LLOWUP:

CLEAR ACCEPTANCE CRITERIA NEED TO BE SPECIFIED BY RAYCHEM ACCEPTABLE REPAIR ACTIONS NEED TO BE DEVELOPED RAYCHEM CONSIDERING REGIONAL TRAINING SEMINARS FOR ENGINEERS, QUALITY CONTROLLERS, INSTALLERS, NRC INSPECTORS IE BULLETIN MAY BE NEEDED TO REQUIRE LICENSEES TO INSPECT AND REPAIR

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FERMI UNIT 2 - MSIV SPRING FAILURE UPDATE JUNE 6, 1986 (L. D. VAUGHAN, IE)

PROBLEM: IN MAY 1986, FERMI 2 REPORTED FINDING SOME MSIV SPRINGS CRACKED AND BROKEN, IT WAS LATER DETERMINED TO BE A GENERIC PROBLEM APPLICABLE TO SEVERAL BWRs AND PWRs SIGNIFICANCE:

IN BWRs, SLOWER CLOSING SPEED COULD OCCUR AND VALVE MAY NOT REMAIN FULLY SEATED FOLLOWING CLOSURE IN PWRs, CLOSURE OF THE REVERSE FLOW VALVE (WHICH IS SPRING-CLOSED) WOULD BE AFFECTED DISCUSSION:

TWO DIFFERENT RECOMMENDED FOLLOWUP ACTIONS j GE's RECOMMENDATIONS:

FOR PLANTS UNDER CONSTRUCTION VISUAL INSPECTION IF CRACKED OR BROKEN PERFORM 5% OVERLOAD TEST ON ALL REMAINING SPRINGS REPLACE ALL CRACKED OR BROKEN SPRINGS WITH NEW SPRINGS PASSING THE 5% OVERLOAD TEST RE-INSPECT AT END OF FIRST OPERATING CYCLE VALVE DISASSEMBLY NOT NECESSARY FOR OPERATING PLANTS VISUAL INSPECTION AT NEXT SCHEDULED OUTAGE REPLACE CRACKED OR BROKEN SPRINGS WITH NEW SPRINGS PASSING 5% OVERLOAD TEST VALVE DISASSEMBLY NOT NECESSARY FOR ALL NEW PURCHASES PASS 5% OVERLOAD TEST PRIOR TO USAGE ATWOOD 8 MORRILL RECOMMENDATION:

CLEAN SPRING BY BLASTING PERFORM MAGNETIC PARTICLE INSPECTION VALVE DISASSEMBLY IS REQUIRED FOLLOWUP: IE NOTICE BEING DEVELOPED

VT, YANKEE - PROBLEMS WITH SCRAM SOLEN 0ID 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 INOPERABLE RODS

MANUFACURING DEFECTS OF REBUILD KITS MAY AFFECT OTHER PLANTS l 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 i

• AFTER IN-SEQUENCE CRITICAL TEST AND S/D MARGIN TESTS

. ALL SCRAM SOLEN 0 IDS HAD BEEN REBUILT FOR NORMAL

! PREVENTATIVE MAINTENANCE (ONCE EVERY 5 YEARS) 4 R0D CONDITION CAUSE 06-23 NO 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 i 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 l SPRINGS IN REBUILD KITS HAVE OUT-0F-TOLERANCE INNER DIAMETER PLUNGER LAND HAS OUT-0F-TOLERANCE OUTER DIAMETER CONES (CORE NEEDLE) LARGE BECAUSE THEY ARE FOR ANOTHER VALVE

. S0LEN0ID BASE SUBASSEMBLIES ARE OUT-0F-ROUND -

, COULD PREVENT FREE TRAVEL OF PLUNGER 4

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 KITS 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

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 1

SIGNIFICANCE: P0TENTIAL 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 BLOW RECIRCULATION VALVES BLOCKED OPEN ADMINISTRATIVE CONTROLS IN PLACE FOR CLOSURE OF VALVES WHEN NECESSARY FOLLOWUP:

IE BULLETIN TO ADDRESS PWRs UNDER DEVELOPMENT l

6 COMPARISON OF FIRST SIX MONTHS 1986 TRIP RATE DATA D. TARN 0FF, (NRR)

NO OF TRIP RATES PER YEAR YEAR PLANTS AUTOMATIC MANUAL TOTAL 1983 77 5.6 0.9 6.5 1984 83 5.2 0.7 5.9 1985 92 5.3 0.6 S.9 1986* 97 4.5 0.4 4.9

FIRST SIX MONTHS DATA EXTRAPOLATED TO YEARLY RATE FOR COMPARISON PURPOSES 1

OTHER FIRST SIX MONTHS RESULTS

1. 14% OF PLANTS HAD 40% OF TRIPS

2. 9 PLANTS HAD 6 OR MORE TRIPS

3. AUTOMATIC SCRAMS JUMPED FROM 3.9 IN FIRST QUARTER TO 5.2 IN SECOND OVARTER OF 1986 ASSESSMENT a

1. THE TOTAL TRIP RATE (TRIPS / PLANT) APPEARS TO BE DECREASING EACH YEAR.

2. WHILE THE RESULTS FOR FIRST SIX MONTHS 1986 ARE ENCOURAGING, THE CAUSES HAVE NOT YET BEEN ASSESSED. " TRIPS /1000-HRS. OPERATION FOR MATURE PLANTS" MAY BE A BETTER INDICATOR THAN TRIPS PER CALENDAR YEAR

e REACTOR SCRAM

SUMMARY

WEEK ENDING 06/29/86 I PLANT SPECIFIC DATA DATE SITE UNIT POWER RPS CAUSE COMPLI- YTD CATIONS TOTAL 06/25/86 MCGUIRE' 2 O AUT EQUIP / BREAKER NO 3 06/25/86 INDIAN POINT 2 43 AUT UNKNOWN NO 5 06/27/86 ZION 2 68 A EQUIP / LIGHTNING NO '

3 06/27/86 DIABLO CANYON 2 100 A EQUIPMENT NO 7 06/27/86 TURKEY POINT 3 100 A ~ PERSONNEL NO 4 06/27/86 LACROSSE 1 80 A EQUIP /LVL CONT. NO 8 06/28/86 HATCH 2 27 A EQUIPMENT NO 4 06/29/86 NORTH ANNA 2 100 A EQUIP / ELECT. NO 4 06/29/86 SUMMER 1 90 A EQUIP /FW IS VLV NO 5 06/29/86 HOPE CREEK 1 OA PERSONNEL NO 1 l

,- -.- _ - , . , . , - - - - _ , , , , ,n , , - - - , - . . - , . + - , . . a - ,-,--.--,,,.

II. COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES

~

SCRAMS FOR WEEK ENDING 7

06/29/86 SCRAM CAUSE i POWER f NUMBER 1986 1985

. OF WEEKLY WEEKLY SCRAMS (5) AVERAGE AVERAGE YTD (3) (4)

• • POWER >15%

EQUIP. RELATED >15% 6 4.3 5.4 (68%)

PERS. RELATED(6) >15% 1 2.2 2.0 (25%)

OTHER(7) >15% 1 0.2 0.6 ( 7%)

• • Subtotal **

8 6.7 8.0

• • POWER <15%

EQUIP. RELATED <15% 1 1.5 1.3 (54%)

PERS. RELATED <15% 1 1.2 0.9 (3,8%)

OTHER <15% 0 0.1 0.2 ( 8%)

• • Subtotal **

2 2.8 2.4

• • • Total ***

10 9.5 10.4 MANUAL VS AUTO SCRAMS TYPE NUMBER 1986 1985 OF WEEKLY WEEKLY SCRAMS AVERAGE AVERAGE -

YTD MANUAL SCRAM 5 O O.8 1.0 AUTOMATIC SCRAMS ,

10 B.7 9.4

i. ,

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NOTES ,

1. 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. REC 0VERY 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.

i 4 IN 1985, THERE WERE AN ESTIMATED TOTAL OF 541 AUTOMATIC AND MANUAL UNPLANNED REACTOR TRIPS AT 93 REACTORS (HOLDING FULL POWER LICENSES). THIS YlELDS AN AVERAGE RATE OF 5.8 TRIPS PER REACTOR PER YEAR AND AN AVERAGE RATE OF 10.4 TRIPS PER WEEK FOR ALL REACTORS.

5. BASED ON 95 REACTORS HOLDING A FULL POWER LICENSE ~.

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

7. "0THER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.

i i

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ENCLOSURE 3 Page No.  !

. 07/01/86 OPERATING REACTORS EVENTS MEETIN6 FOLLOWUP ITEMS AS OF MEETING B6-22 DN Jt*E 30, 1986 (IN ASCENDING IEETIN6 DATE, NSSS VENDOR, FACILITY ORDER)

SCHEDULE CLOSED DATE COMMENTS IEEilD FACILITY RESPONSIBLE TASK DESCRIPTION COMPLET. BY DOCUMENT, WMBER/ NSSS VENDOR / DIVIS10N/

DATE:S) MEETIN6,ETC.

IEETING EVENT DESCRIP. INDIVIDUAL BATE NRR / HOUSTON N RESOLVE THE QUESTION OF THE 06/30/B6 OPEN / / FOLLOWUP ACTIDN TO 86-10 DYSTER CREEK

/ / BE INCORPORATED IN 03/31/86 SE / LEVEL / ACCEPTABILITY OF BLIND SWITCHES

/ / REVIEW OF JUNE SWITCH SETPOINT AND DELETION OF DAILY CHANNEL 1,1986 EVENT AT DRIFT CHECK LASSALLE NRR /HOLAHAN 6. DETERMINE STATUS AND 08/20/B6 OPEN / /

B6-21 VERMCNT YANKEE

/ EFFECTIVENESS OF STAFF AND / /

06/23/B6 6E / PROBLEMS WITH SCRAM LICENSEE ACTION ON / /

SDLEN0!D VALVES POST-MAINTENANCE TESTING (6L B3-2Bl. DEVELOP RECOMMENDATIONS FOR FusihER ACT10N NRR /RDSA F. CONSIDER REVIEWING ELECTRICAL 08/30/86 0 FEN / /

B6-21 TURKEY POINT 06/23/B6 W / PDTENTIAL / SYSTEM 0F PLANT WITH SIMILAR / /

FAILURE OF ALL SWING BUS DESIGN / /

EMER5ENCY DIESEL 6ENERATDRS File has been deleted.

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