ML20210C421

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Summary of Operating Reactors Events Meeting 86-31 on 860908.Lists of Attendees,Events & Significant Elements & Assignments Encl
ML20210C421
Person / Time
Site: Salem, Palisades, Perry, LaSalle, 05000000
Issue date: 09/11/1986
From: Holahan G
Office of Nuclear Reactor Regulation
To: Harold Denton
Office of Nuclear Reactor Regulation
References
REF-GTECI-A-44, REF-GTECI-EL, TASK-A-44, TASK-OR NUDOCS 8609180330
Download: ML20210C421 (21)
v • d • e


Text

...

.t f SEP 111996 MEMORANDUM FOR: Harold R. Denton, Director Office of Nuclear' Reactor Regulation FROM:

Gary M. Holahan, Director Operating Reactors Assessment Staff

SUBJECT:

SUMMARY

OF THE OPERATING REACTORS EVENTS MEETING ON SEPTEMBER 8, 1986 - MEETING 86-31 On-September 8,1986, an Operating Reactor Events meeting (86-31) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on August 25, 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 r.esponsibilities.

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.

OrigiMI M D Gary M. Holahan, Director Operating Reactors Assessment Staff

Enclosures:

As Stated cc w/ Encl.:

See Next Page DISTRIBUTION

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SEP 1.1986 MEMORANDUM FOR: Harold R. Denton, Director Office of Nuclear Reactor Regulation FROM:

Gary H. Holahan, Director Operating Reactors Assessment Staff

SUBJECT:

SUMMARY

OF THE OPERATING REACTORS EVENTS MEETING ON SEPTEMBER 8, 1986 - MEETING 86-31 On September 8, 1986, an Operating Reactor Events meeting (86-31) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on August 25, 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.

l}

Gary M. Holahan, Director Operating Reactors Assessment Staff i

Enclosures:

As Stated cc w/ Encl.:

See Next Page i

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- !iarold R. Denton cc:

R. Vollmer D. Fischer J. Taylor S. Varga C. Heltemes T. Wambach D. Ross A. Thadani T. Murley, Reg. I J. Stefano J. Nelson Grace, Reg. II W. Butler J. Keppler, Reg. III A. Bournia R. D. Martin, Reg. IV E. Adensam J. B. Martin, Reg. V R. Starostecki, 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 G. Lainas V. Benaroya W. Regan D. Vassallo E. Jordan E. Rossi R. Baer E. Weiss R. Hernan S. Showe S. Rubin P. Baranowsky l

ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (86-31)

SEPTEMBER 8, 1986 NAME DIVISION NAME DIVISION G. Holahan ORAS/NRR J. Hickman IE/DEPER T. Wambach' PWRB/NRR J. Stefano BWD4/NRR W. Swenson ORAS/NRR J. Knight PWRA/NRR G. Rivenbark BPD2/NRR V. Benaroya PAF0/NRR A. Siller PPAS/NRR R. Perfetti DPLB/NRR A. Thadani DPLB/NRR D. Crutchfield PWRB/NRR B. Clayton PWRA/NRR D. Vassallo DBL /NRR R. Baer IE/DEPER G. Murphy ORNL/N0AC J. Hannon KHFT/NRR H. Bailey IE/EAB E. Adensam DBL /NRR E. Weiss IE/EAB D. Basdekas RES/RAB G. Klingler IE/0RPB J. Stone IE/DQAVTP M. Chiramal AE0D A. Dromerick IE/EGCB A. Bournia DBL /NRR R. Hernan PPAS/NRR J. Knox DBL /NRR W. Regan PBF0/NRR J. T. Beard ORAS/NRR M. Virgilio ORAS/NRR R. Frahm DSR0/NRR F. Miraglia PWRB/NRR F. Schroeder PWRB/NRR S. Varga PWRA/NRR J. Norris PWRA/NRR C. Rossi PWRA/NRR G. Lear PWRA/NRR B. Sheron DSR0/NRR J. Rosenthal IE/EAB E. Jordan IE R. Houston DBL /NRR R. Woodruff IE/EAB D. Tarnoff ORAS/NRR

~

e ENCLOSURE 2

' 0PERATING REACTOR EVENTS BRIEFING 86-31 SEPTEMBER 8, 1986

. SALEM 2 REACTOR TRIP AND SAFETY INJECTION WITH COMPLICATIONS PALISADES DESIGN DISCREPANCY ESF DEFICIENCIES PERRY RHR ISOLATIONS l

OTHER EVENT OF INTEREST LASALLE STATIC-0-RING SWITCH TEST RESULTS - UPDATE i

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SALEM 2'- REACTOR TRIP AND SAFETY INJECTION WITH COMPLICATIONS AUGUST 26, 1986 (R. WOODRUFF, IE)

PROBLEM:

STATION BLACK 0UT SIGNAL WITHOUT BLACK 0UT

~

t SIGNIFICANCE:

L LOSS OF FORCED COOLING 0F CORE-LOSS OF COOLING.T0 REACTOR. COOLANT PUMP SEALS AND MOTOR CIRCUMSTANCES:

LAST TRANSIENT ANALYSIS OF STATION TRANSFORMER (SXF) LOADS WAS PERFORMED'IN 1981 IN RESPONSE TO NRC' DEGRADED GRID CONCERNS 8 KVA WAS SUBSEQUENTLY ADDED TO SXF "21" AND 2 KVA TO SXF "22" A UNIT 1 CONDENSATE PUMP WAS TEMPORARILY CONNECTED TO UNIT 2 SXF

'EDG."B" WAS OUT OF SERVICE.FOR MAINTENANCE r

i

' AUGUST 26, 1986 i

.- TECHNICIAN INADVERTENTLY GROUNDED VITAL INSTRUMENT BUS "C" CAUSI_NG FALSE LOW RCS FLOW AND SG PRESSURE SIGNALS i

- NORMAL REACTOR / TURBINE TRIP FROM-100%, STEAM DUMP, AND~SI

- TRANSIENT-STATION BLACK 0UT SIGNAL DURING TRANSFER OF GROUP BUSES TO SXF

- VITAL BUS TRANSFERRED FROM ONE SXF TO THE OTHER, BACK AGAIN, AND THEN TO EDGs

- VITAL BUSES STRIPPED THEIR LOADS, EDGs "A" AND "C" STARTED, j

AND LOADS WERE SEQUENCED TO THEIR BUSES

[

- WITH SI AND STATION BLACK 0UT SIGNAL, CCW PUMPS ARE NOT i

f SEQUENCED (AS DESIGNED, SINCE SENSED CONDITION SHOULD HAVE RESULTED IN RCP TRIP)

- RCPs WERE MANUALLY TRIPPED, NATURAL CIRCULATION WAS l

ESTABLISHED, AND A PRESSURIZER PORV OPENED SEVERAL TIMES

- CCW PUMPS AND RCPs WERE RESTARTED AND VITAL BUSES WERE

[.

TRANSFERRED TO SXF l

- PLANT CONDITIONS STABILIZED (EVENT LASTED APPR0X, 26 MINUTES)

I i

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SALEM 2 - REACTOR TRIP AND SAFETY INJECTION WITH COMPLICATIONS CIRCUMSTANCES, (CON'T.)

LICENSEE HAS REDUCED SXF LOADS.

BOTH UNITS RESTARTED AT DERATED POWER, OPERATING PROCEDURES WERE REVISED BASED ON REDUCTION IN AVAILABLE EQUIPMENT GROUP BUSES WHICH WERE ON AUXILIARY TRANSFORMER ARE NOW POWERED FROM SXFs FOLLOWUP:

SXF TRANSIENTS WILL BE REANALYZED BY LICENSEE 4

TRANSFER AND BLACK 0UT RELAYING OF BUSES WILL BE ANALYZED BY LICENSEE TO FIND CAUSE OF MULTIPLE TRANSFERS OF VITAL BUS REGION WILL REVIEW MONTHLY STATUS REPORTS WHICH WILL INCLUDE INTERIM RESULTS OF ANALYSES REGION CONSIDERING A TIA FOR ASSISTANCE IN REVIEW 0F LICENSEE'S ANALYSES IE WILL ISSUE AN INFORMATION NOTICE IE WILL CONSIDER A TI i

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PAllSADES - DESIGN DISCREPANCY AUGUST 26, 1986 (T. WAMBACH, NRR)

PROBLEM:

POSTULATED DC BUS FAILURE WOULD CAUSE PREMATURE

' AUTOMATIC SWITCH 0VER TO SUMP RECIRCULATION SIGNIFICANCE:

LOSS OF ALL SAFETY INJECTION AND CONTAINMENT SPRAY POTENTIAL DAMAGE TO HPSI, LPSI, AND CS PUMPS VIOLATION OF PART 50 APPENDIX A GDC 35'ON SINGLE FAILURE POSSIBLE GENERIC IMPLICATIONS

. DISCUSSION:

FOUR SAFETY INJECTION AND REFUELING WATER TANK L0 LEVEL SENSORS (3' FROM BOTTOM) 2 OUT OF 4 LOGIC FOR ACTUATION OF SUCTION TRANSFER TO DRY CONTAINMENT SUMP DE-ENERGIZE TO ACTUATE (FAIL SAFE?)

LOSS OF 1 0F 2 DC BUSSES DE-ENERGlZES 2 CHANNELS CAUSING SWITCH 0VER WITH P0TENTIAL FOR PUMP DAMAGE SINGLE FAILURE ALSO RESULTS IN RTS ACTUATION AND PARTIAL ESF ACTUATION AND LOSS OF CONTROL POWER TO ONE DIVISION FOLLOWUP:

LICENSEE CHANGING LOGIC T0 "0NE OUT OF TWO TAKEN TWICE" NRR CHECKING GENERIC IMPLICATIONS NEED FOR IE NOTICE OR COMPLI ANCE BULLETIN TO BE DETERMINED

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t PALISADES _ESF DEFICIENCIES AUGUST 1986 (T, WASACH, NRR).

PROBLfl:

FLOW RATES LESS THAN FSAR ACCIDENT ANALYSIS FOR LPSI, CCW, AND AIR COOLERS SIGNIFICANCE:

FSAR ANALYSES MAY NOT BE BOUNDING llISCUSSION:

DEFICIENCIES IN TESTING (POST-MAINTENANCE AND SURVE.II. LANCE)

LPSI

- 8/86 - PULLED IMPELLER TO REPLACE GA$KET

- POST MAINTENANCE TEST 2700 GPM VS, 3000 GPM (FSAk VALUE)

- REVIEW 0F RECORDS FOUND THAT IN 1983, REPl. ACED IMPELLER WITH SPt.RE

-SPARE NOT MODIFIED AS REQUIRED TO MEET FLOW REQUIREMENTS BUT POST-MAINTENANCE AND' PERIODIC TESTING INADEQUATE TO DISCOVER FLOW DEFICIENCY

- NEW MODIFIED IMPELLER BEING INSTALLED i

i CCW

- LO FLOW ALARM TO RCP SEALS IN THIS CYCLE

- FLOW BALANCE TEST 5800 GPM VS, 8000 GPM (FSAR) FOR SHUTDOWN COOLING HEAT EXCHANGER

- REVIEW 0F RECORDS FOUND THAT IN 1971, VALVE.S THROTTLED TO MEET 16.5 PSID LIMIT PER VEllDOR

- SUBSEQUENT TESTING INADEQUATE TO DISCOVER FLOW DEFICIENCY

- REVISED TESTS DETERMINED 7950 GPM AT 19 PSID VALVES OPEN

- CE REANALYZING REQUIRED FLOW

- MAY AUTOMATE THR0TTLED VALVES TO OPEN FULLY ON ACCIDENT-OPERATION ONLY AIR COOLERS

- 1 FAN MOTOR BURNED OUT

- INVESTIGATION DISCOVERED CHEGK DAMPER LOST COUNTER WEIGHT

- CHECKED OTHER FANS I

- FOUND ACCESS COVER OFF AND LOOSE BOLTG AND MOT 0F BEARING FR0ZFN ON ONE FAN -- l.!CENSEE BELIEVES VIBRATIONS FROM BEARII;G LOOSENED BOLTS

- REPAIRING WELDS ON COUNTER NF.IGHTS

- REPLACING FAN MOTOR BEARING i

EQLt,0WUP:

CONFIRMATORY ACTION LETTER ISSUED BY REGION III THAT ADDRESSES NAINTENANCE AND TESTING LICENSEE TESTING ALL SAFETY-RELATED FLUID SYSTEMS WITH UPGRADED TESTS PRIOR TO RESTART REGION III TO REVIEW PROGRAM AND RESULTS

l FERR'Y + RHR ISOLATIONS_

(J _STE?AND JRR)

-fLREB_LE_51 REPETITIVE INADVERTENT SHUTD0h!N C001.1NG SYSEM ISOLATIONS AT PERP.Y SIGNIFICANCE; AF?ARENT THADILITY ON PART OF LICENSEE TO IDENTIFY ROOT CAUSE!S)

ADE00ACY AND EFFECTIVENESS OF L!CENSEE OVERSIG!!T TRAJNihG PROGRAM POTENTI AL LOSS OF SilVTDOWN COOLING CAPABIllTY RISC_l)SSION t a

EIGHT OCCURRENC,ES OF INAD','ERTENT SHUTDOWN COOLING SYSTEM ISOLAT10N FROM JUNE 26,1985 TO PRESENT BREAKDOWN OF CAUSES e

- 4 0FERATOR/TECilNICIAM ERROR (PERSONNEL)

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- 3 PROCEDURAL PROBLEMS

- 1 EQUIPMENT PROBLEM THFEE PROCEDURAL ERRORS At_L JNVOLVE SURVEILLANCE IllSTP,UCTICN PROBLEMS FOUR PERSONNEL PRO,BLEMS NOT DIRECTLY PELATED

+

+ OPERATORS PERFORMED G'JRVEILLANCE INSTRUCTION STEPS OUT OF SEQUENCE

- TECHNICIAN DID NOT FOLLOW WORK ORDER PROPERLY

~

- TECHNICI AN IMPROPERLY INSTALLED THE CONNECTION CETWEEN TERillNAL-AND JUMPER

- OPERATOR INCORRECTLY IDENTIFIED POWER SUPPLY BREAKER FOLLOW UPt

  • REGION 111 FOLLOWING tJP ON ALL EVENTS TO ENSURE CORRECTIVE ACTION IS

[

ADEQUATE

  • LICENSEE

- INCREASING TRAINING TO ENSURE PERSONNEL PROBLEMC ARE MlHIMIZED

- INITI ATED PROSPAM TO REVIEil DECIGN CONTROL PACKAGES AND WORK C0ilTROL PROCESSES

- REVISED Ali.18 MONTH FurlCTI0flAL TESTS AND CALIBRATIONS

- INITIATED REVIEW 0F ALL SURVEILLANCE INSTRUCTIONS

  • NRP. STAFF

- PROJECT MfRAGER ACTIVATING J0lflT NRR/IE/ REGION Ill 0VERSIGHT GROUP T0 l'.CNITOR PERRY PERFORMANCE THROUGH BALANCE OF Fi8ST FUEL CYCLE l

OYMER EVENT OF INTEREST LASALLE_ _ STATIC-0-RING SWITCH TEST RESULTS - UPDATE-JUNE 1, 198_6 (A, BOURNIA, NRR)

PROBLEM:

LO REACTOR WATER LEVEL SCRAM SWITCHES (3 0F 4) DID NOT TRIP SIGNIFICANCE::

POTENTI AL COMMON M0DE ' FAILURES GENERIC APPLICASILITY TO SEVERAL BWRs AND PWRs BACKGROUND:

6/1/86 - LASALLE UNIT 2 FEEDWATER TRANSIENT WITHOUT REACTOR SCRAM PRECURSOR EVEf TS AT OYSTER CREEK AND LASALLE AUGMENTED' INSPECTION TEAM DISPATCHED INFORf1AT10N NOTICE ISSUED (86-47)

INFORMATJON LULLETIN. ISSUED (86-02)

LICENSEE ~PEFFORMED DETAIL TEST FOR ALL APPLICATIONS OF SWITCHES DISCUSSION:

SHORT-TERM-ACTIONS

- SUEMIT FINAL REPORT OF SOR INVESTIGATION

- CAllBRATE ALL SOR SWITCHES AT ATMOSPHERIC PRESSURE PLUS ALLOWANCE FOR SETPOINT SHIFT DUE TO OPERATING PRESSURE

- INCREASE SURVEILLANCE FREQUENCY (INITIAL 2-WEEK CALIBRATION OF LEVEL 3 SWITCHES) AND EVERY 3 MONTHS FOR ALL OTHER SWITCHES

- NEW CALIBRAYION PROCEDURE TO THE "AS FOUND" CONDITION

- HEW " ACTION" AND " REJECT" LIMITS ESTABLISHED

- PERFORM REACTOR WATER LEVEL DROP TEST OF LEVEL 3 SWITCHES AT STARTUP AND SHUTDOWN AT 0, 500 AND 900 PSIG LONG-TERM ACTIONS

- SOR LONG-TERM TEST

- EVALUATE SOR SWITCH IMPROVEMENTS

- EVALUATE CALIBRATION AT OPERATING CONDITIONS

- DECISION CONCERNING ALTERNATIVE LEVEL SENSING EQUIPMENT

~

STAFF AGREED TO SHORT-TERM ACTIONS BEFORE RESTART OF UNIT 2 ON AUGUST 7, 1986 IN VIEW 0F REFUELING OUTAGE SCHEDULED FOR DECEMEER 1985 FOLLOWUP:

NRR CONTINUING TO EVALUATE INFORMATION RECEIVED FROM LASALLE 2 NRR REVIEW TO DETERMINE LASALLE 1 RESTART

)

LA SALLE 2 LEVEI. 3 50R SWITCHES LEVEL MATER DROP TEST RESULTS SCRAM SWITCHES 7/31/86-0PSIG 8/10/86-950PSIG 8/10/06-500PSIG N024 A 19.5 IN 16.5 IN 2).7 IN N024 B 19.0 IN 16.3 IN 19.0 IN N024 C 19.0 IN 17.3 IN 24.5 IN 16.7 IN 24,0 IN N024 D 20.5.IN,

l ADS LOW LEVEL PERMISSIVE SWITCHES NO38 A 20.0 IN 10.5 IN 21.9 IN NO38 B 19,5 IN 14.8 IN 20.6 IN CALIBRATION AT 19.4 IN RIII AllTHORIZED UNIT 2 STARTUP - 8/7/86 UNIT 2 PULLED CONTROL RODS

- 8/8/86 UNIT 2 WENT CRITICAL 8:20 A.M. - 8/11/86 i

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t IASA1,1.8 37 ] 12 VEL 3 SWrXh SbidEMJM8 setroint: 54.9 inches w.c.

Calibratim Tolerance. 53.4 to 59.4 inches 4?.c.

Less than 36.1 inches u.c.

1 Action 1.init:

pksre than 61.7 inchea w.c.

Reject:

1.5.0 inches w.c. or less 61.8 inenes w.c. or mole b

Tech Spec LCO:

64 84 inchas w.c.

al inghes Wicatled As Left Asr Four4 kgt.gh 7/30/66 g,etpoint G.g.t.e Set 24L 53.9 58.3 8/18 59.3 9/1 24*a 58.9 59.15 8/18 gg,g gjj 2tc 58.9 58.85 i6/18 50.5 9/1 2to

!9.0 56.9 6/18 58.75 9 /1 30 58.9 59.55 8/19 50.05 9/2 368 58.9 59.2 8/13 59.4 9/t 2011K

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LOIG YEM TESTS -981T01 "A5 F8Wpt" T!tir/IIESET V4 LUES SHtTOtf IW!!!AL*

+24 Mntats

+ 2 IEIKi 4 4 lesEKS

+ 814Re.K CAL!shATIGN

_ 7/3/95 7/9/95 7/11/96 7/14/06 7#M/05 7/72 E 7/p/st 7/29/06 9/6/66 Dolly "#"

50.1/51.4 60.7/51.8 60.0/57.0 60.9/52.1 61.t/51.5 61.3.32.2 51.4/52.3 G1.6/52.5 1

2 leret "A*

54.C/48.7 60.0/52.4 6G.4/52.9 L

i a thek *A" 30.6/5?.5 61.3/52.9 67.3/53.4 j

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  • Readl9gs taben at 1000 psig, at ilse T = 0 hmers, after hasing been cycled toetain destred setpnist.
    • The too-meet ssitclues kill nett be cycis=* at a later date to ehtain longer laterval confineston data.

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  • REACTOR SCKAM

SUMMARY

WEEK ENDING 06/31/96

1. PLANT' SPECIFIC DATA COMPLI-YTD YTD YTD UNIT PCWER RPS CAUSE CATIONS ABOVE BELOW TOTAL DATE SITE 15%

15%

1 30 M E3UIP/ MECHAN.

NO 5

1 6

6 2

8 08/25/96 CALLAWAY F>ERS/OVERBORAT. NO 09/25/86 ROBINSON 2

100 A 4

2 6

08/25/86 PALO VERDE 2

80 A EQUIP /ELEC.

NO 08/25/86 BRAND GULF 1

7# A EQUIP /TURB.VLV NO 4

2 6

2 100 A PERS3NNEL YES 4

2 6

08/26/86 BEAVER VALLEY 1

3M EQUIP / ELECT.

NO 1

3 4

09/26/86 SALEM 2

100 M EQUIP / ELECT.

NO 4

2 6

5 2

-7 09/27/96 MCGUIRC 1

100 N EQUIP /TURB.VIB. NO 2

SO A EQUIP / ELECT.*

NO 5

2 7

08/27/96 NORTH AhNA 4

1 5

08/29/86 PALO VERDE 2

62 A PERSONNEL NO 08/29/06 DIABLO CANYON 1

53 A EQUIP / ELECT.

NO 2

0 2

08/29/96 HATCH 2

4A PERSONNEL NO O

1 1

9 0

9 09/29/06 FERtj!

09/20/96 PALO UERDE I

100 A - EQUIP / SPUR. SIGN NO 08/30/06 HADDAM NECK 1

100 M EQUIP /MFWP NO 3

3 6

00/31/86 RIVER PEND 1

100 A EQUIP / ELECT.

NO 14.

2 16 09/31/86 bOPE CREEK 1

5A UNKNOWN NO O

8 8

SUMMARY

OF COMPLICATIONS COMPLICATIONS SITE UNIT

'B' VITAL BUS 2 1. BLACKOUT SIGNAL, LOSS OF SALEM 2.10 GPM LEAK ON CONTAINMENT FAN COOLER 4

1 6

0 I

I*.

COMPARISON OF WEEMLY STATISTICS WITH INDUSTRY AVERAGES SCRAMS FOR WEEK ENDING 08/31/86 3 CRAM CAUSE POWER NUMBER 1986 1985 OF WEEKLY WEEKLY SCRAMS (5)

AVERAGE AVERAGE YTD (3) (4) mi POWER >15%

EQUIP. HELATED

>15%

10 4.6 5.4 (60%)

PERS. RELATED(6) >15%

3 2.0 2.0 (25%)

OTHER(7)

>15%

0 0.6 0.6 ( 7%)

    • Subtotal **

13 7.2 8.0

~~

~

    • POWER <15%

EQUIP. RELATED

<15%

1 1.5 1.3 (54%)

PERS. RELATED

<15%

1 1.0 0.9 (38%)

OTHER

<15%

1 0.2 0.2 ( 8%)

~

    • Subtotal **

3 27 2.4

      • Total ***

16 9.,9 10.4 MANUAL VS AUTO SCRAMS TYPE NUMBER 1986 1985 OF WEEKLY WEEKLY SCRAMS AVERAGE AVERAGE YTD MANUAL SCRAMS 5

0.9 1.0 AUTOMATIC SCRAMS 11 8.9 9.4

l I

I REACTOR SCRAM

SUMMARY

hEEK ENDING 09/07/86 j

I. PLANT SPECIFIC DATA DATE SITE UNIT POWER RPS CAUSE COMPLI-YTD YTD YTD CATIONS ABOVE BELOW TOTAL 15%

15%

09/01/86 OUAD CITIES 1

55 A PERSONNEL / TEST. NO 1

1 2

09/02/86 DRESDEN 3

22 M EQUIP / MECH.

NO 1

0 1

09/02/06 PALO VERDE 1

100 A EQUIP / ELECT.

NO 10 0

10 09/02/86 PERRY 1

3A EQUIPMENT NO O

1 1

09/02/86 RIVER DEND 1

90 A EQUIP / ELECT.

NO 15 2

17 09/03/86 HATCH 2

49 A EQUIPMENT NO 5

1 6

09/03/86 DEAVER VALLEY 1

100 A PERSONNEL / TEST. NO 2

3 5

k 09/03/86 MILLSTONE 2

100 A EQUIPMENT NO 3

0 3

09/03/86 WNP h

100 A EQUIP / MECH.

NO 4

2 6

09/04/06 HATCH 2

%A EQUIPMENT NO 5

2 7

09/04/06 SAN ONOFRE 3

90 A EQUIP / ELECT.

YES 4

1 5

I 09/05/86 INDIAN POINT 3

6A EQUIP / ELECT.

NO 5

2 7

09/05/86 CALVERT CLIFFS 2

A EQUIP / ELECT.

NO 4

0 4

09/06/06 HOPE CREEK 1

4( A UNKNOWN NO 1

8 9

09/06/06 TURKEY POINT 4

OO A EQUIP / ELECT.

NO 1

1 2

09/06/06 MILLSTONE 3

70 A EQUIPMENT NO 5

8 13

SUMMARY

OF COMPLICATIONS i

SITE UNIT COMPLICATIONS l

SAN ONOFRE 3 AFW AUTO ACTUATION-DISCHARCE VALVE ON STEAM DRIVEN AFW DID NOT OPEN i

l l

II. COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES SCRAMS FOR WEEK ENDING 09/07/86 SCRAM CAUSE POWER NUMBER 1906 1965 OF WEEKLY WEEKLY SCRAMS (5)

AVERAGE AVERAGE YTD (3) (4) o* POWER >15%

EQUIP. RELATED

>15%

11 4.8 5.4 ( 60*. )

PERS. RELATED(6) >15%

2 2.0 2.0 (25%)

OTHER(7)

>15%

i O.6 0.6 ( 7 ". )

o* Subtotal **

14 7.4 B.O o* POWER <15%

EQUIP. RELATED

<15%

2 1.5 1.3 (54%)

PERS. RELATED

< 15'/.

O 1.0 0.9 (38%)

OTHER

<15%

0 0.2 0.2 ( 8%)

c* Subtotal **

2 2.7 2.4 o** Total ***

16 10.1 10.4 MANUAL VS AUTO SCRAMS TYPE NUMPER 1906 1965 OF WEEKLY WEEKLY SCRAMS AVERAGE AVERAGE YTD MANUAL SCRAMS 1

0.9 1.0 AUTOMATIC SCRAMS 15 9.0 9.4

NOTES 1

PLANT SPECIFIC DATA BASED ON INITIAL REVIEW 0F 50.72 REPORTS FOR THE WEEK OF INTEREST. PERIOD IS MIDNIGHT SUNDAY THROUGH MIDNIGHT 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 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 541 AUTOMATIC AND MANUAL UNPLANNED REACTOR TRIPS AT 93 REACTORS (HOLDING FULL POWERLICENSES). THIS YIELDS AN AVERAGE RATE OF 5.8 TRIPS PER REACTOR PER YEAR AND AN AVERAGE RATE OF 10.4 TRIPS PER WELK FOR ALL REACTORS.

5.

BASED ON 100 REACTORS HOLDING A FULL POWER LICENSE.

6.

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

7.

"0THER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES(LIGHTNING),SYSTEMDESIGN,ORUNKNOWNCAUSE.

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