ML20154C993

Summary of Operating Reactors Event Meeting 86-04 on 860210.List of Attendees,Briefing & Reactor Scram Summaries Encl

ML20154C993
Person / Time
Site:	Beaver Valley, Millstone, Hatch, Calvert Cliffs, Dresden, Peach Bottom, Salem, Oconee, Mcguire, Palo Verde, Perry, Saint Lucie, Byron, Arkansas Nuclear, Three Mile Island, Summer, Brunswick, Surry, Turkey Point, River Bend, Vermont Yankee, Farley, Robinson, Cook, McGuire, 05000000, Trojan
Issue date:	02/24/1986
From:	Holahan G Office of Nuclear Reactor Regulation
To:	Harold Denton Office of Nuclear Reactor Regulation
References
OREM-86-004, OREM-86-4, NUDOCS 8603050427
Download: ML20154C993 (22)

Text

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FEB 2 41986 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 February 10, 1986 - MEETING 86-04 On February 10, W86, an Operating Reactor Events meeting (86-04) was held to brief the Office Director, the Division Directors and their representatives on events which ocarred since our last meeting on January 27, 1986. The list of attendees is included as Enclosure 1.

The z.-ents 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 recpective 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.

Gary M. Holahan, Director Operating Reactors Assessment Staff

Enclosures:

DISTRIBUTION As stated Central File NRC PDR cc w/ encl: ORAS Rdg See next page DTa rnoff RWessman GHolahan 0 [

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res s 4 as 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 February 10, 1986 - MEETING 86-04 On February 10, 1986, an Operating Reactor Events meeting (86-04) was held to brief the Office Director, the Division Directors and their representatives on (;

events which occurred since our last meeting nn January 27, 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 ORAS (D. Tarnoff, x27864) if the target completion date cannot be met.

Y pl - -

Gary Holahan, Director Operating Reactors Assessment Staff -

Enclosures:

As stated cc w/ enc 1:

See next page

(

Harold R. Denton cc: D. Eisenhut R. Gilbert J. Taylor R. Bevan C. Heltemes J. Zwolinski T. Murley, Reg. I G. Requa J. Nelson Grace, Reg. II L. Rubenstein J. Keppler, Reg. III J. Stefano R. D. Martin, Reg. IV W. Butler J. B. Martin, Reg. V V. Rooney R. Starostecki, Reg. I D. Muller R. Walker, Reg. II S. Stern C. Norelius, Reg. III R. Singh E. Johnson, Reg. IV E. Reeves D. Kirsch, Reg. V H. Nicolaras H. Thompson D. Sells F. Miraglia A. Thadani R. Bernero T. Speis W. Russell T. Novak F. Schroeder W. Houston B. Sheron D. Ziemann J. Knight g D. Crutchfield G. Lainas V. Benaroya W. Regan D. Vassallo E. Jordan E. Rossi R. Baer E. Weiss R. Hernan K. Seyfrit M*-

i

ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (86-04)

FEBRUARY 10, 1986 NAME OFFICE NAME OFFICE H. R. Denton NRR E. Weiss IE/DEPER G. M. Holahan NRR/0 RAS M. Chiramal AE00 D. Ziemann NRR/DHFT 5. Krill IE/DEPER W. Hazelton NRR/ DBL R. Keppeler IE/DEPER R. Emch NRR/TOSB R. Gilbert NRR/ DBL V. Rooney NRR/ DBL T. Rotella NRR/ DBL D. Crutchfield NRR/PWR-B E. Jordan IE D. Tarnoff NRR/ORAS T. Novak NRR/PWR-A R. Singh IE/DEPER C. Rossi NRR/PWR-A J. Stone IE/DEPER F. Schroeder NRR/PWR-B V. Benaroya NRR/F0B-A R. Houston NRR/ DBL W. Swenson NRR/0 RAS F. Miraglia NRR/PWR-B F. Witt NRR/ DBL G. Requa NRR/PWR-A J. Stang NRR/ DBL J. Zwolinski NRR/ DBL S. Newberry NRR/0 RAS C. Miller NRR/PWR-B E. Weinkam NRR/PWR-A L. Rubenstein NRR/ PAD-2 D. Muller NRR/ DBL W. Regan NRR/PWR-B R. Perfetti NRR/PWR-B L. Kelly NRR/ORAS G. Murphy ORNL/NOAC J. Buchanan ORNL/NOAC R. Baer IE/DEPER A. Rubin NRR/DSR0 R. Hernan NRR/PPAS 0. Allison IE/EAB R. Bosnak NRR/DSR0 D. Zukor NRC/AE00 K. Seyfrit NRC/AE0D

i ENCLOSURE 2 OPERATING REACTORS EVENTS BRIEFING 86-04 FEBRUARY 10, 1986 DRESDEN UNIT 3 FIRE IN DRYWELL EXPANSION GAP ROBINSON UNIT 2 REACTOR TRIP WITH LOSS OF 0FFSITE POWER PERRY UNIT 1 AND 2 EARTHOUAKE VERMONT YANKEE FAILURE OF STANDBY LIQUID CONTROL SYSTEM RIVER BEND STARTUP PROBLEMS l RECENT SAFETY PERFORMANCE OF FARLEY,

' OCONEE AND ST, LUCIE PLANTS 1

OTHER EVENT OF INTEREST SHROUD BOLT CRACKS AT BWRs i

1

i-l DRESDEN 3 - FIRE IN DRYWELL EXPANSION GAP JANUARY 20, 1986 (R. GILBERT, NRR) ,

PROBLEM FIRE IN DRYWELL EXPANSION GAP

SAFETY SIGNIFICANCE P0TENTIAL GENERIC NON-COMPLIANCE WITH APPENDIX R i

CIRCUMSTANCES WHILE THE UNIT WAS SHUTDOWN a DEFUELED, WELDERS WERE CUTTING i

PIPE (PIPE REPLACEMENT PROGRAM).

DURING CUTTING JUST OUTSIDE A PENETRATION, POLYURETHANE IN THE i

DRYWELL WALL WAS IGNITED AT APPR0X 9 A.M. CST.

j WHEN SM0KE APPEARED, WORKERS IN BUILDING WERE EVACUATED. NO INJURIES.

l *

, FIRE WATCH PERSON USED A DRY CHEMICAL EXTINGUISHER SPRAYING l INTO PENETRATION Ut'TIL THE FIRE APPEARED TO BE OUT.

THE FIRE WAS EXTINGUISHED AFTER SEVERAL HOURS BY WATER FLOODING THROUGH FIVE PENETRATIONS

! REGION Ill BEGAN AN ASSESSMENT AND HAS SINCE TRANSFERRED j LEAD TO HRR NRR STAFF AND CONSULTANT VISITED THE SITE ON 2/6/86.

! PHOT 0S TAKEN FOLLOW-UP

{ THE LICENSEE HAS DRAFTED A PROJECT PLAN FOR EVALUATING THE

EFFECTS OF THE FIRE FROM A STRUCTURAL STANDPOINT LICENSEE IS DRYING OUT DRYWELL AREA l

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! NRR EVALUATING DRESDEN RESTART ISSUES AND GENERIC ASPECTS.

j SIMILAR UNITS ALSO HAVE THIS CONSTRUCTION i

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t H. B ROBINSON UNIT 2 - REACTOR TRIP WITH LOSS OF 0FFSITE POWER JANUARY 28, 1986 (G. REQUA, NRR)

PROBLEM LOSS OF 0FFSITE POWER (LOOP) WITH "B" EDG OUT OF SERVICE SAFETY SIGNIFICANCE PRECURSOR TO STATION BLACK 0UT DISCUSSION 09:17 WITH "B" EDG OUT OF SERVICE, FAULT ON EMERGENCY BUS E-2 CAUSED SPIKED ON INSTRUMENT BUS #4. FALSE RCD DROP SIGNAL CAUSED TURBINE RUNBACK. REACTOR TRIPPED ON HIGH PRESSURIZER PRESSURE, 09:18 LOSS OF 0FFSITE POWER COINCIDED WITH FAST TRANSFER TO START UP TRANSFORMER. "A" EDG STARTS 8 LOADS ON BUS E-1.

RCP's TRIPPED. NATURAL CIRCULATION ESTABLISHED.

09:35 UNUSUAL EVENT DECLARED - OPEN TELEPHONE LINE ESTABLISHED BETWEEN NRC OPERATIONS CENTER AND ROBINSON SITE 09:46 "B" DIESEL GENERATOR RESTORED 10:52 PRESSURIZER HEATERS RtSTORED 12:55 E-1 BUS CONNECTED TO 0FFSITE POWER 16:03 E-2 BUS CONNECTED TO 0FFSITE POWER. REALIGNMENT OF '

0FFSITE POWER DELAYED BY

1. TWO SI SIGNALS - IST SIGNAL CAUSED BY CLOSURE OF MS!Vs; SECOND SIGNAL CAUSED BY STUCK OPEN S/G PORV

2. ADDITIONAL BREAKER PROBLEM BETWEEN #3 BUS 8 E-2 -

3. OPERATOR DECISION TO PROCEED WITH CAUTION IN RESTORING ELECTRICAL CONFIGURATION PLANT WAS TAKEN TO HOT SHUTDOWN. CP8L DECIDED TO SHUTDOWN FOR REFUELING ONE WEEK EARLY FOLLOWUE PLANT IN 45 DAY REFUELING OUTAGE; LICENSEE INVESTIGATING CAUSE OF LOOP; REGION 11 WILL REVIEW PRIOR TO RESTART LICENSEE 8 INPO TEAM FORMED TO INVESTIGATE HIGH FREQUENCY OF REACTOR SCRAMS AT ROBINSON: REGION 11 TO EVALUATE RESULTS PRIOR TO RESTART

PERRY 1 AND 2 - EARTHOUAKE JANUARY 31, 1986 (J. STEFANO, NRR)

PROBLEM EARTHOUAKE MEASURING 5.0 ON RICHTER SCALE WITH EPICENTER APPROXIMATELY 10 MILES FROM SITE.

SIGNIFICANCE EVENT MAY BE OUTSIDE DESIGN ENVELOPE CIRCUMSTANCES l PLANT CONSTRUCTION COMPLETE-WAS UNDERG0ING SYSTEM SURVEILLANCE /

OPERATIONAL READINESS TESTS FOR LICENSING. (NUMEROUS SAFETY SYSTEMS WERE IN OPERATION).

SEISMIC INSTRUMENTS WERE BEING CAllBRATED AT TIME OF EVENT.

TWO NON-SAFETY EQUIP. TRIPPED ON PROTECTIVE SIGNAL AS DESIGNED; SOME HAIRLINE CONCRETE CRACKS OBSERVED IN AUX., INTERMED. AND RADWASTE TREATMENi BLDGS. PIPE FLANGE ON WATER TANK IN RADWASTE BLDG. LEAKING.

PRELIM. DATA SEEMS T0 INDICATE SHORT DURATION (41 SEC) SEISMIC MOT!0N MAINLY FALLS WITHIN OBE/SSE DESIGN SPECTRUM EXCEPT POSSIBLY AT HIGH FREQUENCY RANGE (>15Hz)

FOLLOWUP NRR/ REG.Ill TEAM VISIT TO SITE TO LOOK FOR DAMAGE 8 OBTAIN

SEISMIC DATA ON 2/1/86 - 2/2/86 NRR/ REG.ll! FOLLOWUP VISIT TO SITE ON 2/5/86 - 2/7/86 CEI ANALYSIS UNDERWAY TO DETERMINE TO WHAT EXTENT PLANT STRUCTURE / COMPONENT DESIGN WAS EXCEEDED.

PLANT LICENSING DECISION PENDING NRC STAFF EVALUATION AND ,

DETERMINATIONS RE EVENT.

4 0

I VERMONT YANKEE - FAILURE OF STANDBY LIQUID CONTROL SYSTEM FEBRlfARY 8, 1986 (V. ROONEY, NRR)

PROBLEM SLCS SoulB VALVE FAILED TO FIRE DURING ANNUAL TEST I

SIGNIFICANCE STANDBY LIQUID C0flTROL SYSTEM UNAVAILABLE CIRCUMSTAflCES REACTOR IS DEFUELED WITH RECIRCULATION PIPIllG REPLACEMENT UNDERWAY BOTH SOUlB VALVES SATISFACTORILY TESTED 7/11/84 CAUSE OF FAILURE FOUND TO BE WIRES CROSS CONNECTED INSPECTION REVEALED SIMILAR CROSS CONNECTION Oil REDullDANT SCU!B VALVE FOLLOW-UE 4

LICENSEE AND RESIDENT INSPECTOR INVESTIGATION IS IN PROGRESS I

• llRR FOLLOWillG UP POTENTIAL ABNORMAL OCCURRENCE i

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RIVER BEND UNIT 1 - START-UP PROBLEMS E,ECEMBER 1985 - JANUARY 1986 (S. STERN, NRR)

PROBLEM ABNORMAL NUMBER OF PROBLEMS REPORTED DURING START-UP SIGNIFICANCE FREQUENCY OF CHALLENGES AND EQUIPMENT PROBLEMS MAY INDICATE HIGHER RISK CIRCUMSTANCES HIGH FREQUENCY OF REPORTABLE EVENTS LOSS OF 0FFSITE POWER EVENT CHRONIC FEEDWATER SYSTEM PROBLEMS FOLLOW-UP LICENSEE - MANAGEMENT TEAM ESTABLISHED TO ADDRESS PROBLEM NRC - NRR/IE/ REGION IV SITE VISIT IE NOTICES ON RlLEY TEMPERATURE SWITCHES: TONE SYSTEMS; VALVE OPERATORS ADVISE CLINTON, PERRY, OTHER BWR APPLICANTS TO REVIEW l

LESSONS LEARNED FROM RIVER BEND 1

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4 RECENT SAFETY PERFORMANCE OF FARLEY, OCONEE AND ST, LUCIE PLANTS (R. SINGH, IE)

, OBJECTIVE: ASSESSMENT OF PLANT SAFETY PERFORMANCE FOR INPUT TO INSPECTION PROGRAMS OVERALL RESULIS: FARLEY AND ST, LUCIE PLANTS ARE WELL MANAGED,  ;

OCONEE PLANTS ALSO WELL MANAGED EXCEPT THEIR '

MAINTENANCE PROGRAM MAY BE SOMEWHAT WEAK, ANALYSIS METHOD:

ANALYZE OPERATING REACTOR EVENTS DATA FOR THE 6-MONTH l PERIOD ENDING DE.CEMBER 1985 ,

. REV!EW: 50,72 REPORTS I

Ri! MORNING REPORTS INSPECTION REPORTS EVENT FOLLOW-UP NOTES GRAY BOCKS IDENTIFY SICNIFICANT EVENTS:

SCRAMS ESF ACTUATIONS SAFETY SYSTEM / COMPONENT FAILURES OTHERS AFFECTING SAFETY IDENTIFY BASIC CAUSES/ AREAS OF WEAKNESS ASSOCIATED WITH THE EVENTS:

9AND0M EQUIPMENT FAILURE PROCEDURE  :

MAINTENANCE PERSONNEL ERROR ,

! ADMINISTRATIVE CONTROL

! EVENT DATA PLACED ON A COMPUTERIZED DATA BASE RE10klS FARLEY 1: 1 SCRAM DUE TO PERSONNEL ERROR FARLEY 2: 3 SCRAMS - RESPECTIVELY DUE TO PERSONNEL ERROR DURING S/U, WEAK MAINTENANCE AND LIGHTNING 2

ONE ESF ACTUATION-EDG START DUE TO PERSONNEL ERROR l SOME MINOR VIOLATIONS i 1

OCONEE 1: NO SCRAMS, ONE FORCED OUTAGE DUE TO SG TUBE LEAK i OCONEE 2: 1 SCRAM - PERSONNEL ERROR, 2 FORCED SHUTDOWNS -

ONE DUE TO RCS LEAKAGE FROM VALVE PACKING, THE OTHER DUE TO RCP SEAL FAILURE i OCONEE 3: 2 SCRAMS - ONE DUE TO PERSONNEL ERROR DURING S/U, THE OTHER DUE TO ICS COMP. FAILURE, THREE FORCED SHUTDOWNS - LOW RCP MOTOR Oil LEVEL, RCS LEAKAGE, LPI VALVE REPAIR VIOLATIONS INVOLVED RTB MAINTENANCE ST, LUCIE 1: NO SCRAMS OR FORCED SHUTDOWNS ONE SIGNIFICANT EVENT (LIFTING BOLT PROBLEM)

ST. LUCIE 2: 2 AUTO SCRAMS (0NE DUE TO PROCEDURE, ONE DUE TO WEAK MAINTENANCE),

2 MANUAL SCRAMS AND A FORCED SHUTDOWN

DUE TO RCP V!BRATION, NO VIOLATIONS AT EITHER PLANT

SUMMARY

SCRAM FREQUENCY OF ALL SEVEN PLANTS AT OR BELOW INDUSTRY AVERAGE j ALL WELL MANAGED EXCEPT OCONEE MAINTENANCE PROGRAM MAY BE SOMEWHAT WEAK ELauS -

, ASSESSMENTS BEING PLANNED FOR SEVERAL OTHER PLANTS 1

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t SHROUD BOLT CRACKS AT BWRS (D. TARN 0FF, NRR)

PROBLEM BWR SHROUD BOLT CRACKS DISCOVERED AT OTHER PLANTS SIGNIFICANCE EXCESSIVE FAILURE OF BOLTS COULD ULTIMATELY LEAD TO STEAM SEPARATOR LIFTING 4

i CIRCUMSTANCES HISTORY 11/26/85-SHROUD BOLT CRACKS DISCOVERED AT PEACH BOTTOM l -

MATERIALS EXAMINATION INDICATES IGSCC ALL BWR0 EXCEPT BWR-6s HAVE SAME SHROUD BOLTS

, GE ISSUED CUSTOMER INFORMATION BULLETIN RECOMMENDING INSPECTION OF ALL BWRs IN OUTAGE ULTRAS 0filC PROCESS USED 1/29/86 GE RESULTS OF OllGOING INSPECTION ARE AS FOLLOWS:

J ELMIX TOTAL NO. OF BOLTS NO. INSPECTED fl0. CRACKED HATCH 1 36 35 4 l BROWNS FERRY l 48 48 3 BROWflS FERRY 2 48 47 14

PEACH BOTTOM 3 48 21 15 DRESDEll 3 48 48 7 BRUflSWICK 2 36 36 15 l l

l EDLLOW-UE GE PREPARiflG SIL

REPLACEl1ENT OF CRACKED BOLTS Ill PROGRESS i

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REACTOR SCRAM

SUMMARY

WEEK ENDING 02/0 /86 I. FLANT SPECIFIC DATA '

i DATE SITE UNIT F0WER RFS CAUSE .' C'OMPL!- YTD

] CATIONS TOTAL l

01/ G/06 ROE'INSON O 00 A EDU!P/ELEC YES 4 01/29/06 DYRON 1 98 A EQUIP /MS!V NO 2 j 01/01/06'OCON'EE 65 A EQUIP / FLOW TRNS NO 1 1 01/01/86 GALEM 1 100 A EDU!F/FD RG VLV YES  : ,

01/01/06 OCONEE  : 100 A FERSONNEL/ TEST NO 1  ;

} 01/01/06 OCONEE 1 100 A EQUIP /ELEC NO 1 i 02/01/06 COOL 2 BG A EQUIP /ELEC FIRE NO 1

! 02/02/Go SUMMER 1 100 A FERSONNEL/MAINT NO 1

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SUMMARY

OF COMPLICATIONS i

I EITE UNIT COMF LIC ATIONS ROFINCON O LOST OFFSITE F0WER WITH 1 EDG 005 FOLLOWING SCRAM

SALEM 1 T.FANSFORMER 00S.O OF 4 RCPS TRIFFED FOLLOWIN3 SCRAM i

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!!. COMPARISON OF WEELLY STATISTICS WITH INDUSTRY AVERAGES SCRAMS FOR WEEV ENDING O2/02/06

. ECRAM CAUSE F'OWER NUMDER NUMBER 1905 l OF NORMALIZED (6) WCD Ly BCRAMS(5) TD 1995 AVERAGE C) t4) ee FOWER $15%

EOU!F. RELATED >15% 6 6.0 5.4 (60%)

FERS. RELATED(7) >15%  : 2.0 2.0 (25%)

i OTHER(0) >15% 0 0.0 0.6 ( 7%) l l 84 Eubtotal as O 0.0 0.0

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8s FOWER <15% I EOUIF. RELATED s 15'/. O O.0 1.0 (54%)

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• FERS. RELATED 15% 0 0.0 0.9 ( O E *'. )

g OTHER '15%

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0 0.0 2.4

• • • Total ***

O U.0 10.4 l .

MANUAL VS AUTO SCRAML

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. TYFE NUMEER NUMDER 1905 OF NORMALI2ED WEElLY

. SCRAMG TO 1905 AVERAGE l MANUAL SCRAMS O O.0 1.O f AUTOMATIC SCRAM 3 0 0.0 9.1 l i 1

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SUMMARY

! WEEL ENDING O2/09/06 I

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!. FLANT SFECIFIC DATA DATE SITE UNIT POWER RFS CAUSE COMPLI- YTD CATIONS TOTAL L

02/05/86 SUMMER 1 9A EDUIP/EHC NO 2 02'00/Bo FALQ VERDE 1 60 A EOUIP/MFW NO 2 02/04/06 MILLSTONC 0 14 A EQUIP /MFW NO 1 02/04/06 CALVERT CLIFFS 2 100 A EQUIP / INST NO 1 0;/04/06 OCONEC 0 100 A FERSONNEL/ TEST NO 2 02/05/86 MILLSTONE 1 70 A EQUIP /FRESS REG YES 1 02/06/06 SAINT LUCIE 1 100 A FERSONNEL/ TEST NO 1 02/07/Oc MILLSTONE 3 14 A EDUIP/STM/ FEED NO 2

i. 02/07/06 FALO VERDE - 1 18 A FERSONNEL/SU NO . 7 02/08/06 TROJAN 1 100 A EQUIP /TURB TRP NO 1 02/08/06 SURRY 1 14 A FERSONNEL/SU NO

SUMMARY

OF COMPLICATIONS SITE *

• UNIT COMFLICATIONS MILLSTONE 1 F,EDUNDANT MS!V FA! LURE I

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!!. COMFARISON OF WEELLY STATISTICS WITH INDUCTRY AVERAGES SCRAMS FOR WEEF ENDING O2/09/06 SCRAM CAUSE F0WER NUMBER NUMBER '

19 E *.,

OF NORMAL 12ED(6) WEEtLN SCRAMG(5) TO 1985 AVERAGE (2)(4) e$ F0WER F 157.

COUIP. RELATED >15% 4 4.0 5.4 (60%)

FERS. RELATED(7) >15% 0 0.0 1.0 (25*.)

OTHER(0) >15% 0 0.0 0.6 ( 7%)

• • Subtetal **

7 7.0 0.0

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I $$ F 0WER /15.

. EOU!F. RELATED <15% 5 5,o g,7 (543)

! . FERS. FELATED < 15's. 1 3,o n,9 g g.,, )

, O'HER <15% o o,o g,7 g gg3

• • Subtotal **

ees Total ***

11 11.0 10.4 1

< i MANUAL VS AUTO GCRAMS i

. TYFC NUMLER NUMLER 190s '

OF NORMALI2ED WEEl L Y SCRAMC TO 1985 AVERAGE MANUAL CCRAMC O O.0 1.0 i AUTOMATIC SCRAMS 11 11.0 t 9.4

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NOTES  !

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! 1. PLANT SPECIFIC DATA BASED ON INITIAL REVIEW 0F 50.72 REPORTS  !

I FOR THE WEEK 0F INTEREST. PERIOD IS MIDNIGHT SUN THROUGH

! MIDNIGHT SUN SCRAMS ARE DEFINED AS REACTOR PROTECTIVE f

ACTUATIONS WHICH RESULT IN R0D MOTION, AND EXCLUDE PLANNED l

TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE WITH A l l PLANT PROCEDURE.  !

j

2. REC 0VERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAUSE OF SCRAM j l

l  !

3, 1985 INFORMATION DERIVED FROM RECENT ORAS PRELIMINARY STUDY OF i I UNPLANNED REACTOR TRIPS IN 1985. WEEKLY DATA DETERMINED BY [

] TAKING TOTAL TRIPS IN A GIVEN CATEGORY & DIVIDING BY l

! 52 WEEKS / YEAR i l ,

! 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 l PER REACTOR PER YEAR & AN AVERAGE RATE OF 10.4 TRIPS PER WEEK l FOR ALL REACTORS.

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

6. NORMALIZED VALUES ALLOW COMPARISON TO 1985 DATA BY MULTIPLYING ACTUAL 1986 VALUE BY: 93 REACTORS IN 1985 NUMBER OF REACTORS REPORTING .

I

7. PER5ONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL l DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS l l

8.  ;

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