ML20212N272

Summary of Operating Reactor Events Meeting 87-005 on 870302.List of Attendees & Viewgraphs Encl

ML20212N272
Person / Time
Site:	Indian Point, Vogtle, Rancho Seco, 05000000
Issue date:	03/05/1987
From:	Holahan G Office of Nuclear Reactor Regulation
To:	Harold Denton Office of Nuclear Reactor Regulation
References
OREM-87-005, OREM-87-5, NUDOCS 8703120426
Download: ML20212N272 (16)

Text

MAR 0 51987

. MEMORANDUM FOR: Harold R. Dent:n, Director

/

Office of Nuclear Reactor Regulation FROM:

Gary M. Holahan, Director Operating Reactors Assessment Staff

SUBJECT:

SUPMARY.0F THE OPERATING REACTORS EVENTS MEETING ON MARCH 2,1987 - MEETING 87-05 On Monday, March 2,1987, an Operating Reactor Events meeting (87-M) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on February 9,1987. The list of attendees is included as Enclosure 1.

The events discussed and the significant elements of these events are presented in Enclosure 2. provides a sunnary of those presented events that will be input to NRC's performance indicator program as significant events.

Af/

Gary M. Holahan, Director Operating Reactors Assessment Staff

Enclosures:

As stated cc w/ Encl.:

See Next Page DISTRIBUTION,

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NRC PDR ORAS Rdg Tarnoff Rdg w/o Enclosure ORAS Members P

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0703120426 870305 PDR ORG PERC

v.

Harolo'R. Denton cc:

R. Vollmer M. Slosson J. Taylor M. Miller C. Heltemes S. Varga R. Starostecki G. Kalman-D. Ross S. Miner-

~ T. Murley, Reg. I J. Stolz J. Nelson Grace, Reg. II B. Youngblood J. Keppler, Reg. III R. D. Martin, Reg. IV J. B. Martin, Reg. V W. Kane 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 E. Rossi G. Lainas V. Benaraya W. Regan D. Vassallo E. Jordan J. Rosenthal R. Baer E. Weiss R. Hernan S. Showe S. Rubin G. Arlotto 1

64..

4

-EhCLOSURE I LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (87-05)

MARCH 2, 1987 NAME DIVISION NAME DIVISI0h G. Holahan NRR K. Eccleston NRR

'M. Virgilio NRR S. Aggarwal RES/ DES D. Tondi NRR M. Slosson NRR M. Miller NRR V. Benaroya NRR-J. Wermiel NRR R. Emch NRR J. Clifford NRR B. Boger NRR

'B. Clayton

.NRR'

13. Murphy.

ORNL-W. Regan NRR R. Weller NRR S. Miner NRR-G. Kalmar NRR G. Klingler.

IE M. Chiramal AEOD E. Weiss IE E. Jordan IE R. Baer IE J. Rosenthal IE T. Novak NRR S. Varga NRR J. Stolz NRR C. Rossi NRR F. Miraglia NRR F. Schroeder NRR R. Bernero NRR D. Basdekas RES/RAB W. Swenson-NRR K. Kniel NRR

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Ef! CLOSURE 2 y/.

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OPERATING REACTORS EVENTS BRIEFING:87-05 MARCH 2, 1987?

-INDIAN' POINT 2 iREACTOR MANUAL ~ TRIP-WITH COMPLICATIONS RANCHO SECO CABLE ROUTING ERRORS OTHER EVENT OF INTEREST V0GTLE HYDROGEN LEAK IN AUXILIARY BUILDING

3/2/87 INDIAN POINT 2 - REACTOR MANUAL TRIP WITH COMPLICATI0f!S FEBRUARY 10, 1987 - (M. SLOSSON, NRR)

PROBLEM:

OPERATOR INADVERTENTLY MANUALLY TRIPPED THE UNIT TIE BREAKER FAILED TO TRANSFER NON-SAFEGUARDS EUS TO 0FFSITE POWER OPERATOR INADVERTENTLY OPENED SECOND TIE BREAKER CAUSE:

HUMAN ERROR EQUIPMENT FAILURE SIGNIFICANCE:

EQUIPMENT FAILURE AND KULTIPLE OPERATOR ERROR DISCUSSION:

PLANT AT 100%

EMERGENCY DIESEL GENERATOR (EDG #22) OUT FOR SERVICE OPERATOR ATTEMPTING TO RE-ENERGIZE D.C. POWER TO EDG #22 BY SWITCHING D.C. CONTROL BREAKER IN CONTROL ROOM OPERATOR INADVERTENTLY THREW REACTOR TRIP BREAKER TRAIN B RESULTING IN REACTOR TRIP FOUR 6.9 KV BUSES TRANSFER FROM ONSITE TO 0FFSITE POWEP BUS 2 DID NOT TRANSFER WITH EDG #22 OUT THIS RESULTED IN SAFEGUARDS BUS 2A OUT TIE BREAKER RACKED IN AND OUT TRANSFER MADE ON BUS 2 OPERATOR " MATCHING FLAGS" IN CONTROL ROOM TIE BREAKER 3 OPENED DURING MATCHING WITH DIESEL QUT THIS RESULTED IN LOSS OF SAFEGUARDS BUS 3A 2-5 BREAKER FAILED 3 0F 26 CHALLENGES FOLLOW-UE:

LICENSEE FOLLOWING UP WITH OPERATOR

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e 3/3/87 PANCHO SEC0 - CABLE ROUTING ERRORS (G. KALMAN, NRR)

PROBLEM:

LERs, ALLEGATIONS, AND CABLE ROUTING INSPECTIONS HAVE IDENTIFIED CABLE-ROUTING ERRORS AT RANCHO SEC0

CAUSE:

CABLE ROUTING CRITERI A NOT FOLLOWED, MISREPRESEtiTED RECORDS SIGNIFICANCE:

RANCHO SECO DESIGNED SAFETY FEATURES MAY BE COMPPOMISED.

PROGRAMMATIC DEFICIENCY IN PLANT MODIFICATION PROCEDURES.

DISCUSSION PLANT IN EXTENDED SHUTDOWN.

AUGUST 8 AND ON AUGUST 14, 1985, DECAY HEAT SYSTEM BLOCK VALVE CLOSED INADVERTENTLY ON HIGH RCS PRESSURE.

INCIDENT CAUSED BY SIGNAL INTERFERENCE BETWEEN INSTRUMENT AND POWER CABLES.

MAY 22, 1986, FIRE PROTECTED CONDUIT DESIGNED TO HOLD 7 SAFE SHUTDOWN INDICATION CIRCUITS WAS FOUND EMPTY.

SAFE SHUTDOWN CIRCUITS FOUND UNPROTECTED IN SINGLE SWITCHGEAR ROOM.

SMUD INITIATED CABLE ROUTING VERIFICATION PROGRAM 95/95 SAMPLE INSPECTION.

VERIFICATION IDENTIFIED 2 ADDITIONAL MISROUTED CABLES.

PROBLEM TRACED TO 1 ENGINEERING CHANGE NOTICE (ECN), 14 0F 22 CABLES MISROUTED.

2000 LESS SIGNIFICANT DISCREPANCIES IDENTIFIED, 118 CABLES TRACED, 237 CABLES IN INITIAL SAMPLE SET ASSUMING NO ADDITIONAL PROBLEM, CORRECTIVE ACTIONS COMPLETE IN APRIL.

FOLLOW-UP:

REGION V INSPECTION IN PROGRESS.

NRR RESTART EVALUATION IN PROGRESS.

OTHER EVENT OF' INTEREST o

3/2/07 V0GTLE - HYDROGEN LEAK IN AUXILIARY BUILDING FEBRUARY 20,1987- (E. WEISS, IE) j)

PROBLEM:

VALVE PACKING ON SMALL HYDROGEN LINE LEAKED INSIDE AUX BLDG

~

SIGNIFICANCE:

I HYDR 0 GEN LEAKAGE FROM LINES IN SAFETY RELATED AREAS OUTSIDE CONTAINMENT MAY BE A GENERIC CONCERN NO INSTALLED HYDROGEN DETECTION, SO SLOW LEAKS MAY GO UNDETECTED (EXCESS FLOW CHECK VALVES PREVENT LARGE LEAKS)

CAUSES:

PACKING LEAK ON SMALL GLOBE VALVE AREA NEAR LEAK HAS LITTLE VENTILATION (HVAC FLOW BALANCING PROELEMS)

CIRCUMSTANCES:

UNIT IN COLD SHUTDOWN (UNIT HAS NOT G0NE CRITICAL)

HYDROGEN VALVE REPOSITIONED 1/26/87 CHLORINE DETECTORS TRIP 2/20/87 NO T0XIC GAS FOUND, SO SHIFT SUP DIRECTS FURTHER SAMPLING 0309 HPs DISCOVERED HYDR 0 GEN IN VERTICAL PIPE CHASE NEAR CENTER OF AUX BLDG CONCENTRATION 20% OF LOWER FLAMMABILITY LIMIT (LFL) ROOM A-24 1,2% H BY VOLUME 2

CURRENT ESTIMATE IS 500 TO 1000 SCF HYDROGEN 0319 ISOLATED HYDROGEN SKID 0325 SOURCE OF LEAK IDENTIFIED (VALVE PACKING ON 1 INCH SCHEDULE 80 CARBON STEEL LINE TO VOLUME CONTROL TANK)

LINE IS FROM LIQUID HYDROGEN SKID OUTSIDE TURBINE BUILDING (CAPACITY IS 335,000 SCF)

SKID IS USED TO SUPPLY HYDR 0 GEN T0:

1.

MAIN GENERATOR 2.

VCT 3.

HYDROGEN RECOMBINERS IN WASTE GAS SYSTEM 0337 VENTING 0F HYDROGEN HEADER TO TURBINE BUILDING ROOF 0341 UNUSUAL EVENT DECLARED, DOORS TO AUX BUILDING PROPPED OPEN 0404 N0 HYDR 0 GEN REPORTED 0536 UNUSUAL EVENT TERMINATED FOLLOWUP:

LICENSEE EXAMINING:

- USE OF DIAPHRAGM VALVES IN THIS APPLICATION

- BASIS FOR EXCESS FLOW CHECK VALVE SETPOINT IE CONSIDERING AN INF0 NOTICE

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REACTCR SCEAM

SUMMARY

WEEK ENDING O2/15/97 I.'FLANT SPECIFIC' DATA

.DATE 3 I TE '.

UtilT 1 POWER -- RF S CAUSE COMPLI-YTD YTD.

YTD CATIONS AEOVE BELOW TOTAL.

.15%

15.

- 02/10/G7 INDIAN POINT'

-2 100'M.

FER50fiNEL YES 1

0 1

. 02/11/E7 INDIAN POINT

'O 100 A EQUIP / ELECT.

NO 2

2

" 02/11/87 HOFE. CREEK

-1 1~ M EQUIP / LEAK NO

. f.i 1

1 lO2/10/G7 PERRY-~

1 4A FERSONNEL NO-0 1

1 02/14/07.BYRCN 2'

OA FER50NNEL NO O

v

--02/14/57-OvSTER. CREEK

-1 98 A

EQUIP /t'ECH.

NO 2

0 2

02/15/37 TURREY. POINT 5

10 A FEFSONNEL NO 1

1 C'

~

SUMMARY

OF'COMFLICATIONS

' SITE UNIT COMFLICATIONS INDI AN. F OINT C LREAFER FAILURE CFEFATOR INADVERTENTLY OPENED ANOTHER LREALER

II. CO'!PARIGON OF WEEKLY STATISTICS WITH IMOU3TR'( AVERAGES SCRAMS FOR NEEK ENDING O2/15/G7 SCRAM CAUEE FCWER NUMEER.

1987 1956 1985 OF-WEEKLY WEEVLY WEEKLY GCRAMS(C)

AVERAGE AVERAGE AVERAGE YTD (2) (4)

(6)(9).

e+

POWER :: 15%

COUIP. RELATED

/15%

2 3.5 4.3 5.4 FERS. RELATED(6) 215%

1 1.5 1.a

2. 0 OfHER(7)

>15%

0 0.8 0.4 0.6

• + Subtotal

-e +

3 5.8 6.5 0.0

• + POWER +'15%

ECUIF. RELATED

15%

1 0.9 1.4 1.3 FERS. RELATED

15%

3 1.2 0.9 0.9 OTHER

15%

0 0.O O.2 O.2 I

• • Subtotal

++

4 2.1

2. 4 2.4

+ + ' + Tot al ***

7 7.9 0.0 10.4 MANUAL V3 AUTO SCRAM 3 TYRE NUMDEF:

1997 1996 1955 OF WEEF:LY WEEKLY WEENLY SCRAMS AVERAGE AVERAGE AERAGE YTD Mi,NUAL SCFAMS 2

1.1 1.O 1.O AUTOMATIC SCRAN5 5

6.8 7.c

7. 4

r FEACTOF ECFAM

SUMMARY

WEEl. ENDING O2/22/57 I.

PLANT EPECIFIC CATA DA E CITE UNIT F owe F. RF5 CAUEE' COMPLI-YTD T:

CATIONS ABCVE EE:CW TCTk

.e-.,

1,..

4 02/le/57 MCNTICELLO 1

100 A EOUIFMENT NO 2

0 2

02/16 E7 LACC.055E 1

95 M EDU!FMENT NO O2,l'-37 EPAIDWO:D 1

0M ECUIe/ ELECT.

N3 0

1 1

02'15/E7 r Ar# EE F:CWE 1

99 A EOUIFMENT NO 1

0 1

02 13/E7 COCFER 1

50 A FERSONNEL IJO 3

1 Q:/IE/S7 !: P A I LWOOD 1

0M EOL'I P / EL E CT.

rJO O

2 02/19/97 MCGUIRE 1

100 A EQUIF/ ELECT.

NO 1

1 02.22/57 LIABLO CANVON 1

30 A EQUIPMENT NO O

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2 O

O II. COMFARISCt CF WEEt:LY STATISTICS WITH INDUETR( M'ER AG EE

+

SCPAMS FOR WEEF. ENDING 02/

/87 ECT AM CAUSE POWER ULIME EP 1987 1986 1955 OF WEEFLY WEEKLY WEEELv' SCRAME(5)

AVERAGE AVERAGE AVERAGE YTD (3) (4)

(G)(9)

++ FCWER 15's.

EDUIP. RELATED 15%

5

3. 7 4.3 5.4 PERS. RELATED(o)

' 15 .

1 1.4 1.9 2.0 GTHER P) 1 T.

O O7

9. 4 0.e

++ Subtotal

• +

o 5.5 e.5 9.'

+* POWER <15%

EDUIP. RELATED

~15%

2 1.1 1.4 1.2 FERS. RELATED 15%

0 1.1 0.8 0.9 OTHER

~ 151.

0

0. O O.2 O.

Subtotal 2

2.2 2.4 2.4

• • • Total *++

8

0. 0 S.9 10.4 MANUAL VS AUTO SCRAMS TYPE NUMEER 1987 1986 1985 OF WEEFLY WEEtLY WEEt:LY SCRAMS AVERAGE AVERAGE AVERAGE YTD MANUAL SCRAMS 3

1.3 1.O 1.O 4.UTCMATIC ECRAMS 5

6.6 7.9 9.4 t

f.

9 REACTOR SCRAM

SUMMARY

WEEK ENDING 03/01/87 I.

PLANT SPECIFIC DATA DATE SITE UNIT POWER RPS CAUSE COMPLI-YTD YTD

't ' D CATIONS ABO'/E BELCW TOTAL 15%

15*.

02/24/87 HOPE CREEK 1

100 A PERSONNEL NO 1

1 2

02/24/87 CATAWBA 2

100 A EQUIP / ELECT.

NO 2

0 02/24/87 IEWAUNEE 1

OA EQUIP / ELECT.

NO O

1 1

02/26/87 FERMI 2

29 A EQUIPMENT NO 1

O l'

02/27/87 HARRIS 1

50 M EQUIPMENT NO 2

2 4

02/28/87 FARLEY 2

100 A EQUIP / ELECT.

NO 1

0 1

.02/28/87 CALVERT CLIFFS 2

95 A EQUIP / ELECT.

NO 1

0 1

O!/01/87 FERMI 2

18 A PEPSONNEL NO 2

0 2

V h

II. COMFARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES SCRAMS FOR WEEK ENDING 03/01/87 SCRAM CAUSE POWER NUMBER 1987 1986 1985 OF WEEKLY WEEVLY WEEELY SCRAMS (5)

AVERAGE AVERAGE AVERAGE YTD (3)(4)

(S) (9)

++ FOWER > 15%

EQUIP. RELATED 2157.

5 3.8 4.3 5.4 PERS. RELATED(6) 215%

2 1.5 1.8 2.0 OTHER(7) t15%

0 0.6 0.4 0.6

• + Subtotal **

7 5.9 6.5 8.0

• • POWER <15%

EQUIP. RELATED

<: 15%

1 1.0 1.4 1.3 PERS. RELATED

<15%

0 0.9 0.8 0.9 g

OTHER

<15%

0 0.0 0.2 0.2

• • Subtotal **

1 1.9 2.4 2.4

• • • Total *++

8 7.8 8.9 10.4 MANUAL VS AUTO SCRAMS TYPE NUMBER 1987 1986 1985 OF WEEKLY WEELLY WEELLY SCRAMS AVERAGE AVERAGE AVERAGE YTD MArlUAL SCRAMS 1

1.0 1.0 1.0 AUTOMATIC SCPAMS 7

6.6 7.9 9.4

......-.-..........--..J

9.

^

i NOTES 1.

PLANT SPECIFIC DATA BASED ON IN!TIAL 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 R00 MOTION, AND EXCLUDE PLANNED TESTS OP SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE WITH A PLANT PROCEDURE.

2.

REC 0VERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERROPS UNRELATED TO CAUSE OF SCRAM.

3.

1986 INFORMATION DERIVED FROM ORAS STUDY OF UNPLANNED REACTOR TRIPS IN 1986. WEEKLY DATA DETERMINED BY TAKING TOTAL TRIPS IN A GIVEN CATEGORY AND DIVIDING BY 52 WEEKS / YEAR.

4.

IN 1986, THERE WERE AN ESTIMATED TOTAL OF 461 AUTOMATIC AND MANUAL UNPLANNED REACTOR TRIPS AT 104 REACTORS (HOLDING OPERATINGLICENSES). THIS YIELDS AN AVERAGE RATE OF 4.4 TRIPS PER REACTOR PER YEAR AND AN AVERACE RATE OF 8.8 TRIPS PER WEEK FOR ALL REACTORS.

5.

BASED ON 104 REACTORS HOLDING AN OPERATING LICENSE.

6.

PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ER30R, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS 7.

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

8.

1985 INF0PMATION DERIVED FROM AN ORAS STUDY OF UNPLANNED REACTOR TRIPS IN 1985. WEEKLY DATA DETERMINED BY TAKING TOTAL TRIPS IN A GIVEN CATEGORY AND DIVIDING BY 52 WEEKS / YEAR.

9.

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

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