ML20236U639

Summary of Operating Reactors Events Meeting 87-041 on 871124.List of Attendees,Summary of Reactor Scrams & Comparison of Wk Statistics W/Industry Averages Encl

ML20236U639
Person / Time
Site:	Beaver Valley
Issue date:	11/25/1987
From:	Lanning W Office of Nuclear Reactor Regulation
To:	Rossi C Office of Nuclear Reactor Regulation
References
OREM-87-041, OREM-87-41, NUDOCS 8712030231
Download: ML20236U639 (13)

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UNITED STATES j\ )g[g r,

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NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555  ;

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.NOV 15 I MEMORANDUM FOR: Charle's E. Rossi Director Director of Operational Events Assessment FROM: Wayne Lanning, Chief Events Assessment Branch Division of Operational Events Assessment j

SUBJECT:

THE OPERATING REACTORS EVENTS MEETING NOVEMBER 24, 1987 - MEETING 87-41 j i

On November 24, 1987 an Operating Reactors Events meeting (87-41) was held to.

brief senior managers from NRR, RES, AEOD and Regional Offices on events which occurred since our last meeting on November 17, 1987. The list of attendees is included as Enclosure 1.

The events discussed and the significant elements of these events are presented  !

l in Enclosure 2. The Enclosure 3 provides a summary of reactor scrams and a  ;

comparison of this week's statistics with industry averages. One significant l event was identified for input to NRC's perfor ce indicator program.

I ay Lanning, Chief Events Assessment ch Division of Operational Events Assessment

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Enclosures:

As stated cc w/ Encl.:

See Next Page i

8712030231 871125 /

PDR ORG NRRB h p$s4 V

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' MEMORANDUM FOR:

Charles E. Rossi, Director Director of Operational Events Assessment FROM: Wayne Lanning, Chief Ivents Assessment Branch O'avision of Operational Events Assessnent

SUBJECT:

THE OPERATING REACTORS EVENTS MEETING NOVEMBER 24, 1987 - MEETING 87-41 i On November 24, 1987 an Operating Reactors Events meeting (87-41) was held to brief senior managers from NRR, RES, AEOD and Regional Offices on events which occurred since our last meeting on November 17, 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. The Enclosure 3 provides a summary of reactor scrams and a comparison of this week's statistics with industry averages. One significant event was identified for input to NRC's performance indicator program.

Wayne Lanning, Chief Events Assessment Branch Division of Operational Events Assessment

Enclosures:

As stated cc w/ Encl.:

See Next Page DISTRIBUTION

' Central File EAB Reading File Circulating Copy EAB Staff MLReardon, EAB LKilgore, SECY, PDR hNA' 0FC :EAB/NRR :C:EAB/NRN  :  :  :  :  : :

. . . . . : . . . . . . . . . . . . : . 3_,. ...___:....________:.______..___:._____......:.___..........__........

NAME :HLReardon :W m i  :  :  :  :  :

DATE :11/ 25'/87 :11/)('/87: :  :  :  :

i 0FFICIAL RECORD COPY m-

cc: .

T. Murley J. Sniezek F. Miraglia G. Gears E. Jordan J. Stefano J. Taylor D. Wessmann E. Beckjord V. Rooney.

W. Russell, RI M. Virgilio J. Nelson Grace, RII J. Stang B. Davis, RIII P. Tam -

R. U. Martin, RIV. J. Stoltz J. B. Martin, RV W. Kane, RI L. Reyes, RII C. Nore11us, RIII J. Callan, RIV D. Kirsch, RV S. Varga D. Crutchfield B. Boger G. Lainas G. Holahan l L. Shao.

J. Partlow B. Grimes F. Congel l

E. Weiss S. Black.

T. Martin J. Stone R. Hernan H. Bailey J. Guttmann A. Thadani 0

ENCLOSURE 1 LIST OF ATTENDEES _

, OPERATING REACTORS EVENTS BRIEFING (87-41) -

. November 24, 1987 1

[AME ORGANIZATION NAME ORGANIZATION W. Lanning NRR/DOEA T. Murley NRR/DONRR C.E. Rossi NRR/DOEA R. Scholl NRR/D0EA  !

R. Lobel NRR/r0EA J. Stang OSP 1 M.L. Reardon NRR/JOEA G. Klingler NRR/PMAS G. Gears OSP J. Partlow NRR/DRIS l B. Clayton DEDRO l

L. Plisco NRR/DLPQ l C. Schulten NRR/DOEA l E. Wright _NRR/DRSP W. Jensen NRR/DOEA P. Tam NRR/PDI-4 K. Naidu NRR/DRIS S. Mackay NRR/DOEA J. Guillen NRR/DOEA 1

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- _ _ - _ _ _ _ _ - . _ _ _ _ - - _ _ _ _ - _ _ . _ - - - _ . - . _ _ .e. _ . - - _ _ - - - - - __ __---

Enclosure 2 OPERATING REACTORS EVENTS BRIEFING 87-41 TUESDAY NOVEMBER 24, 1987, 11 A.M.

THE AGENDA INFORMATION MAY ALSO BE OBTAINED BY DIALING EXTENSION 27174.

I BEAVER VALLEY 2 SCRA.M WIlH COMPLICATIONS BROWNS FERRY FIRE (UPDATE)

I PILGRIM AIT (UPDATE) l GENERIC ISSUE HFA RELAYS

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BEAVER VALLEY llNIT 2 LOSS OF OFFSITE POWER NOVEMBER 17, 1987

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PROBLEM LOSS OF 0FFSITE POWER WITH COMPLICATIONS, SIGNIFICANCE ONE OFFSITE POWER CIRCUIT RESIORED IN APPROX, 17 SECONDS, BUT MALFUNCTION OF AUTO TRANSFER FROM UNIT TO 0FFSITE POWER IDENTIFIED POTENTIALLY SERIOUS PROBLEM.

DISCUSSION I o INADVERTENT TRIP BY TECHNICIAM OF TURBINE ROTOR POSITION DRAWER, o TECHNICIAN RE-ENERGIZED DRAWER GENERATING MOMENTARY THRUST BEARING FAILURE SIGNAL, l 0 TURBINE TRIP, REACTOR TRIP FROM FULL POWER, IMMEDIATE AUTO TRANSFER

! FROM UNIT TO 0FFSITE POWER.

I o

MALFUNCTION OF AUTO TRANSFER PARALLELED THE TRIPPED GENERA. TOR WIT THE OFFSITE SOURCES THRU THE 4 KV. BUSES AND UNIT AUXILIARY AND OFFSIIE SERVICE TRANSFORMERS, o BREAKER OPERATIONS ISOLATE 4 KV BUSES.

o DG(S) START AND LOAD ON EMERGENCY BUSES.

o ONE 138 KV 0FFSITE CIRCUll (IRIPPED ON PHASE UNBALANCE) RESTORED TO TWO 4 KV BUSES IN APPR0X. 17 SECONDS, ONE RCP STARTED IN APPROX.

4 MINU1ES.

o ONE EMERGENCY BUS RECONNECTED TO 0FFSITE POWER (DG SECURED) IN APPROX. ONE HOUR, o

TRANSFORMER ON SECOND OFFSITE CIRCUIT (TRIPPED ON OC) CHECKED OUT AND RECONNECTED TO REMAINING TWO 4 KV BUSES IN APPROX, 8 HOURS, o SECOND EMERGENCY BUS RECONNECTED TO 0FFSilE POWER (DG SECURED),

CORRECTIVE ACTIONS TAKEN o

THE EVENT RECORDER AND THE STRIP CHARI RECORDER TRACES OF MAIN GENERATOR CURRENT AND 4 KV BUS VOLTAGES EVALUAIED.

o TESTS PERFORMED TO VERIFY AUTO TRANSFER MALFUNCTION, CONTACT: F. ROSA I

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l o PROPOSED CHANGES: .

REVISE BREAKER CONTROL CIRCUIT TO DEFEAT AUTO TRANSFER FROM 0FFSITE POWER TO UNIT TRANSFORMERS. -

REVISE TURBINE IRIP CIRCUIT TO LOCK IN IHL TP,IP SIGNAL, TESTS PERFORMED TO VERIFY PROPOSED CHANGE WOULD CORRECl AUTO TRANSFER PROBLEM.

UNIT 1 ACIIONS o NONE AT PRESENI - THE UNIT WILL COME DOWN ON DECEMBER 11, 1987.

l 0 UNIT ONE HAS A " HYDRAULIC-TYPE" THRUSl BEARING POSITION TRIP WHICH HAS INHERENT SEAL IN FEATURE, FOLLOWUP o SPECIAL INSPECTION - NRR AND RI PARTICIPATION WAS PROVIDED.

o LICENSEE ANALYSIS OF EVENT AND PROPOSED CORRECTIVE ACTIONS WERE EVALUATED. ~

O PROPOSED. CIRCUIT CHANGES WERE FOUND ACCEPTABLE. I o NRR SHOULD CONSIDER ISSUANCE OF AN INFORMATION NOTICE ON POSSIBLE PROBLEM WITH TWO-WAY AUTO TRANSFER LOGIC, i

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1 GE HFA-TYPE LATCHING RELAYS MAY MALFUNCTION l PROBLEM ALL HFA 151B, HFA 154B, AND HFA 154E TYPE LATCHING RELAYS MAY FAIL TO LATCH DUE TO INADEQUATE SPRING TENSION.

CAUSE DESIGN DEFICIENCY. THE RELAYS WERE QUALIFIED TO IEEE-323 AND IEEE-344.

SIGNIFICANCE o AFFECTS SAFETY RELATED APPLICATIONS SUCH AS 4.16KV BUS LOAD SHEDDING PRIOR TO ACCEPTING'DG SOURCE.

o NON-SAFETY RELATED APPLICATIONS INCLUDE ANNUNCIATION AND DISPLAY, DISCUSSION BRUNSWICK TESTED A HFA 154E RELAY IN STORAGE (WAREHOUSE) PRIOR TO REPLACING AN EXISTING RELAY. THE RELAY FAILED TO LATCH. GE SAN JOSE WAS NOTIFIED. GE SAN JOSE NOTIFIED THE METER AND CONTROL l BUSINESS DEPARTMENT (MCBD). MCBD TESTED HFA lYPE LATCHING RELAY AND DETERMINED THAT:

o THE DISTANCE BETWEEN THE TOP OF THE MOLDED CONTACT CARRIER AND THE TOP OF THE RELAY ARMATURE WAS NOT A MINIMUM 0F 1/32 INCH AS REQUIRED.

o THERE WAS INSUFFICIENT TENSION BY THE LEAF SPRING THAT ROTATES THE LATCH TO ITS FULLY ENGAGED POSITION.

o A LATCHING RELAY, WHEN ENERGIZED OPERATES A MECHANISM WHICH CHANGES THE STATE OF NORMALLY CLOSED AND NORMALLY OPEN CONTACTS AND HOLDS LIT IN THAT STATE AFTER THE RELAY IS DE-ENERGIZED. THE RELAY HAS TO BE ELECTRICALLY OR MECHANICALLY RESET TO RETURN THE CONTACTS TO THE ORIGINAL STATE.

FOLLOWUP VIB IS DRAFTING AN IE BULLETIN.

CONTACT: J. STONE

-_._ .____.mm. _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . _ _ _ _ _ _ .___ _. _ _

AEACTOR SCRAM SUMARY Enclosure 3L q l NEEKENSING11/22fB7-1 c .;

1. PLANT SPECIFIC DATA 1 .

DATE SITE ' UNIT PDNER SIGNAL CAUSE COMPL1- ?fTD YTD YTD CAT 10NSl E0VE BELOW ' WTAL 151 151 r.

f

!!/16/87 MILLSTONE 2 100 A EQUIPMENT' ' YES '5- i' 5-11/17/87 BEAVER VALLEY 2 98 A FERSDhhEL YES 12 5 17 ,

11/21/B7 FDINT BEACH 1 100 A EQUIP / MECH. ND 1 1 2 6 1

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11/22/B7 CALVERT CLIFFS 2 100 M PERSONNEL' NO '4 1 5 '/ i 11/22187 PALD VERDE 2 7A EQUIPMENT NO 2 1 3, l ./

SUMARY OF COMPLICATI0k'S -

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SITE UNIT COMPLICATIONS

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n!LLSTCNE '2 DNE OF TND MOTOR OPERATED AUX FEED PUMP FAILED TO START BEAVER VALLEY 2 COMPLETE LOSS OF 0FFSITE FONER FOR 17 MINUTES P

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I 11' COMPAR2 SON OF WEdKLY STATIS12CG WITM INDUSTRY AVERAGE SCRAMS FOR WEEX ENDING 11/22/F7 l

f SCRAM CAUSE POWER 'I NUMBER 1987 1986 1985

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OF WEEKLY WEEKLY WEEKLY  !

SCRAMS (5) AVERARE AVERAGE AVERAGE J YTD (3) (4) (B) (9) i 1

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• • POWER >15% ., 2 i

EQUIP. RELATED

>pS% 2 4.0 4.3 5.4 l PERS. RELATED(6) );*. 3% 2 1.3 1.8 2. 0 OTHER<7) {

>1S% '

.e 0 1.2 0.4 0.6 I

• • Subtotal **

4 6.5 6.5 8.0 1

• • POWER <15%

EQUIP. RELATED <15% 1 1.2 1.4 1.3 f1 PERS. RELATED < 15%- 0 0.6 0.8 0.9  !

6THER <15% C O.3 0.2 0.2

• • Subtotal **

, 1 2.1 2.4 2.4

• ** Total *** ' '

5 8.6 8. 9 10.4 MANUAL VS AUTO SCRAMS

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TYPE l NUMBER

' 1987 1986 1985 OF WEEKLY WEEKLY WEEKLY f SCRAMS AVERAGE AVERAGE AVERAGE l YTD MANUAL SCRAMS 1 1.4 g 1.0 .

1.0 AUTOMATIC SCRAMo 4 7.3 7.9 9.4 l

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. NOTES

1. PLANT SPECIFIC DATA BASED ON INITIAL REVIEW OF 50.72 REPORTS I FOR THE WEEK OF INTEREST. PERIOD IS MIDNIGHT SUNDAY THROUGH *, 1 MIDNIGHT SUNDAY SCRAMS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN POD MOTION, AND EXCLUDE PLANNED-TESTS OR SCRAM 5 AS PART OF PLANNED SHUTDOWN IN ACCORDANCE I WITH A PLANT PROCEDURE. 1

2. RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNREL ATED TO CAU5E OF SCRAll.

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.

I

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

S. BASED ON 107 REACTORS HOLDING AN OPERATING LICENSE.

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

7. "0THER" INCLUDES AUT0fMTIC SQtAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.

8. 1985 INFORMATION DERIVED FROM AN ORAS STUDY OF. UNPLANNED REACTOR TRIPS IN 19E5. WEEKLY DATA DETERMINED BY TAKING TOTAL TRIPS IN A GIVEN CATEGORY AND DIVIDING SY 52 WEEX5/ YEAR.

S. IN 1985, THERE WERE AN EST1t%TED TOTAL OF 541 AUTOMATIC AND MANUAL

' UNPLANNED REACTOR 7 RIPS AT 93 REACTORS (HOLDING FULL POWER LICENSES). THIS YIELDS AN AVERAGE RATE OF S.8 TRIPS PER REACTOR YEAR AMD AN AVERAGE RATE OF 10.8 TRIPS PER WEEK FOR ALL REACTORS.

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FERIU CANCE INDICAT0*E SIGNIFICANT EVENTS a.>

EVENT EVENT IEECRIPTION I'f' 'i' lh. DATE QTR SIGNIFICANCE IEEIEE VA' LEY 2

!!/17/67 FERSONNEL IK U:n Tyge!NE TRIP CONCGREC W mtp~ r 0' LIESIICN3 AUTD-TRANErER EEEgtTED IN REACTOR ECRAM VITH Lnce

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