ML20205G955

Summary of Operating Reactors Events Meeting 86-28 on 860811 Re Briefing of Ofc Director,Div Directors & Representatives on Events Discussed at 860804 Meeting.List of Attendees & Viewgraphs Encl

ML20205G955
Person / Time
Site:	Palo Verde, Fermi, Catawba, Grand Gulf, 05000000
Issue date:	08/13/1986
From:	Holahan G Office of Nuclear Reactor Regulation
To:	Harold Denton Office of Nuclear Reactor Regulation
References
NUDOCS 8608190665
Download: ML20205G955 (16)

Text

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AUG 13 516 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 AUGUST 11, 1986 - MEETING 86-28 On August 11, 1986, an Operating Reactor Events meeting (86-28) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on August 4,1986. 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.

Af/

Gary M. Holahan, Director Operating Reactors Assessment Staff

Enclosures:

As Stated cc w/ Encl.:

See Next Page DISTRIBUTION Central File .

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. AUG 13 NE6 Harold R. Denton 1 cc: R. Vollmer M. Licitra l J. Taylor H. Bailey C. Heltemes G. Knighton D. Ross L. Kintner T. Murley, Reg. I W. Butler J. Nelson Grace, Reg. II K. Jabbour J. Keppler, Reg. III D. Lynch R. D. Martin, Reg. IV B. J. Youngblood J. B. Martin, Reg. V E. Adensam 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

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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 P. Baranowsky l

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ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (86-28)

AUGUST 11, 1986 NAME DIVISION NAME DIVISION G. Holahan ORAS/NRR M. Caruso ORAS/NRR J. Jackson NRR/DSR0 R. Benedict NRR/B-F0B S. Massaro AE0D/PTB W. Regan NRR/PWRB D. Muller NRR/ DBL J. Clifford NRR/PRAS C. Miller NRR/PRAS G. Murphy ORNL/NOAC M. Lynch NRR/ DBL S. Rubin AE0D V. Benaroya NRR/PAF0 G. Klingler IE/DI J. Stone IE/DQAVT E. Weiss IE/DEPER N. Trehan NRR/ DBL D. Crutchfield NRR/PWRB W. Paulson NRR/PWRB K. Jabbour NRR/PWRA J. Rosenthal IE/EAB E. Jordan IE/DEPER R. Starostecki IE R. Baer IE/EGCB E. Rossi NRR/PWRA F. Schroeder NRR/DPLB F. Miraglia NRR/DPLB M. Virgilio ORAS/NRR W. Swenson ORAS/NRR J. T. Beard ORAS/NRR D. Tarnoff ORAS/NRR

ENCLOSURE 2 OPERATING REACTOR EVENTS BRIEFING 86-28 AUGUST 11, 1986 PALO VERDE 1 8 2 CLASS 1E ELECTRICAL POWER DEGRADATION IN TWO UNITS DUE .

TO NON-1E ELECTRIC FAULT GRAND GULF 1 CONTROL R0D WITHDRAWAL PROBLEM FERMI 2 FIRE IN MOTOR CONTROL CENTER PANEL OTHER EVENTS OF INTEREST CATAWBA 1 REACTOR COOLANT PUMP SEAL FAILURE

PALO VERDE 1 & 2 - CLASS 1E ELECTRICAL POWER DEGRADATION IN TWO UNITS DUE TO NON-1E ELECTRIC FAULT AUGUST 6, 1986 (H. BAILEY, IE) l l

PROBLEM: DUAL UNIT TRIP DUE TO LOSS OF A STARTUP TRANSFORMER CAUSED BY WATER IN A NON-1E 480V MCC SIGNIFICANCE:

CHALLENGE TO 1E POWER SYSTEM CAUSED BY SYSTEMS INTERACTION FAILURE IN NON-CLASS 1E ELECTRICAL SYSTEM CAUSED LOSS OF CLASS 1E DIVISION IN EACH QF TWO. UNITS DESCRIPTION OF CIRCUMSTANCES:

HOUSE LOADS (NON-1E) ON STARTUP (SU) TRANSFORMERS DUE TO PREVIOUS PROBLEMS WITH FAST TRANSFER UNIT 2 TURBINE TRIP FROM 50% POWER LED TO MFW VENT VALVE LEAKAGE VENT VALVE LEAKED ONTO NON-1E 480V MCC AND SHORTED OUT HIGH VOLTAGE (13,8 KV) SIDE IMPROPER BREAKER COORDINATION CAUSED SU TRANSFORMER DIFFERENTIAL CURRENT RELAY TO LOCK OUT SU TRANSFORMER (SU-X03)

LOSS OF SU TRANSFORMER CAUSED LOSS OF TWO RCP IN EACH UNIT, RESULTING IN DUAL UNIT TRIP ROOT CAUSE APPEARS TO BE EITHER DIFFERENTIAL RELAY PROBLEM OR BREAKER C0 ORDINATION PROBLEM FOLLOWUP:

LICENSEE PLANS TO RETURN NON-1E HOUSE LOADS TO UNIT AUX TRANSFORMER AFTER TESTING TROUBLESHOOTING THIS (AND OTHER) TRANSFORMER DIFFERENTIAL RELAYS REEVALVATING BREAKER COORDINATION

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GRAND GULF UNIT 1 - CONTROL ROD WITHDRAWAL PROBLEM JULY 30, 1986 (ERIC WEISS, IE)

PROBLEM: CONTROL R0D MOVED TO FULL OUT POSITION DESPITE R0D BLOCK WHEN OPERATOR ATTEMPTED TO MOVE R0D FROM NOTCH 8 TO NOTCH 10.

SIGNIFICANCE:

EVENT GOES BEYOND FSAR ANALYSIS (50.72 REQUIRES REPORT)

CONTRARY TO FSAR, R0D BLOCK DEFEATED BY SINGLE FAILURE OF DIRECTION CONTROL VALVE OPERATOR PROCEDURES CHANGED TO COVER THIS EXACT EVENT (50,72 REPORT REQUIRED IF PROCEDURES DID NOT COVER THIS EVENT)

GE 8/6/86 LETTER SAYS EVENT IS "NOT A PROBLEM" CIRCUMSTANCES:

PLANT AT 69% POWER OPERATOR ATTEMPTS.T0 MOVE CONTROL R0D 20-45 0UT FROM NOTCH 8 TO NOTCH 10 CONTROL R0D MOVES SLOWLY TO NOTCH 48 DURING THIS UNREQUESTED WITHDRAWAL OPERATORS REDUCES PLANT POWER TO ABOUT 60%

OPERATORS ATTEMPT NORMAL NOTCH-IN OF R0D 20-45 BUT THAT FAILS AFTER R0D 20-45 IS FULLY WITHDRAWN:

OPERATORS CHECK RCIS BY NOTCHING OTHER RODS - RCIS 0,K.

OPERATORS DRIVE IN R0D 20-45 TO NOTCH 46, AND R0D LATCHES OPERATORS DRIVE OUT SYMETRICAL RODS OPERATORS DRIVE R0D 20-45 AND SYMETRICAL RODS FULL IN DRIVE WATER ISOLATION VALVES ON HCU LOCKED CLOSED FOR R0D 20-45 CHANGE OUT DIRECTION CONTROL VALVE 422 (WITHDRAWAL PRESSURE)

N0 THERMAL LIMITS APPARENTLY EXCEEDED N0 SAFETY EQUIPMENT FAILED N0 50,72 REPORT MADE BUT RESIDENT INSPECTOR WAS INFORMED VISUAL INSPECTION OF DIR CONTRL VALVE 422 SHOWS NOTHING BENCH TEST OF DIR CONTROL VALVE 422 SHOWS NOTHING WRONG SUSPECT CRUD UNDER VALVE SEAT WAS CAUSE SIMILAR EVENTS AT BRUNSWICK, 0YSTER CREEK, PILGRIM, & PEACH BOTTOM PROBLEM MENTIONED IN GE SIL 292 SUP 1 (7/80)

FOLLOW-UP IE PREPARING INF0 NOTICE IE EXAMINING ROOT CAUSE WITH ASSISTANCE OF REGION, LICENSEE, AND GE GE EXAMINING SAFETY CONSEQUENCES

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FERMI 2 - FIRE IN MOTOR CONTROL CENTER PANEL AUGUST 6, 1986 (D. LYNCH, NRR)

PROBLEM: IRE IN A DC MOTOR CONTROL CENTER PANEL SIGNIFICANCE:

POTENTIAL FIRE SOURCE BREAKER ACTUATION REQUIRED FOR MINIMUM FLOW HPCI BYPASS LINE CIRCUMSTANCES:

TESTING HPCI TURBINE OVERSPEED TRIP TWO SUCCESSFUL TURBINE TRIPS & TWO FAILURES IN ABOUT 4 HOUR PERIOD; ABOUT 15 BYPASS VALVE ACTUATIONS DIV II ITE BREAKER AT 130 VDC TWO-PHASE OPERATION; AUXILIARY CONTACTOR LIFTED IN MILLISECONDS AT ABOUT 400W (37 OHMS) WHILE FUNCTION COMPLETED AT ABOUT 10 W (1700 OHMS)

P0TENTIAL ROOT CAUSES BAD CONNECTION FAILURE OF AUXILIARY SWITCH STICKING CONTACTOR BREAK OR SHORT IN C0ll FUSED AT 30 AMPS; FAULT CURRENT APPR0X, 3 AMPS.

DAMAGED COMP 0NENTS REPLACED FOLLOWUP:

PLANT RESTARTED AT 8 P.M. 8/10/86 FAAA INVESTIGATING

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PROBLEM: REACTOR COOLANT PUMP EXPERIENCED A SEAL FAILURE RESULTING IN A MAXIMUM LEAK OF ABOUT 60 GPM TO THE REACTOR COOLANT DRAIN TANK SIGNIFICANCE:

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CIRCUMSTANCES:

PLANT IN MODE 3 APPROX. 60 GPM EXPERIENCED IN "B" RCP; PUMP SECURED IMMEDIATELY LEAK IS TO REACTOR COOLANT DRAIN TANK AND THEN TO PRESSURIZER RELIEF TANK LEAK REDUCED TO APPROX. 8 GPM AS RCS IS COOLED & DEPRESSURIZED COLD SHUTDOWN ACHIEVED EARLY MORNING, AUGUST 10, 1986 FOLLOWUP:

REGION II AND NRR FOLLOWING LICENSEE'S EVALUATION OF ROOT CAUSE

REACTOR SCRAM

SUMMARY

WEEK ENDING 08/10/06 I. PLANT SPECIFIC DATA COMPLI- YTD YTD YTD DATE SITE UNIT POWER RPS CAUSE CATIONS ABOVE BELOW TOTAL

. 15% 15%

2 49 M PERSONNEL / TEST NO 3 2 5 08/04/06 CATAWBA 2 1 3 08/04/06 FARLEY 2 99 A UNKNOWN /SURV.T. NO 100 A EQUIP /LO SG LVL NO 7 1 B 08/05/86 SALEM 1 NO 1 1 2 08/05/86 CAN ONOFRE 1 87 A UNKNOWN 100 A EQUIP / ELECT. NO 3 0 3 09/05/06 TROJAN '

1 5 0 5 08/05/86 FARLEY 1 99 A EQUIP /FD REG VL NO 1 100 A EQUIP / ELECT. NO 7 0 7 CB/06/96 PALO VERDE NO 3 2 5 08/06/06 PALO VERDE 2 6A EQUIP / ELECT.

36 A EQUIPMENT NO 8 1 9 C8/07/06 SALEM 1 6 2 8 08/09/B6 CATAWBA 1 . 70 A PERSONNEL / TEST NO 4

100 A EQUIP / ELECT. NO 4 0 08/10/06 MAINE, YANKEE 1 O

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5.4 (68%)

PERS. RELATED(6) >15% 2 2.1 2.0 (25%)

OTHER(7) >15% 2 0.5 0.6 ( 7%)

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10 7.1 8.O ,

• • POWER <15%

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

PERS. RELATED <15% 0 1.0 0.9 (38%)

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, <15% 0 0.2 0.2 ( 0%)

• • Subtotal **

1 2.7 2.4

• • • Total ***

11 9.8 10.4 MANUAL VS AUTO SCRAMS -

TYPE NUMBER 1986 1985 OF WEEKLY WEEKLY SCRAMS AVERAGE AVERAGE YTD -

MANUAL SCRAMS 1 0.8 1.0 AUTOMATIC SCRAMS 10 9.0 9.4 t

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NOTES

1. PLANT SPECIFIC DATA BASED ON INITIAL REVIEW OF 50.72 REPORTS FOR THE WEEK 0F INTEREST. PERIOD IS MIDNIGHT SUNDAY THROUGH MIDNIGHT SUNDAY SCRAMS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN R0D 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.

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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 MANUALUNPLANNEDREACTORTRIPSAT93 REACTORS (HOLDINGFULL POWERLICENSES). THIS YIELDS 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 97 REACTORS HOLDING A FULL POWER LICENSE.

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

7. "0THER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES(LIGHTNING),SYSTEMDESIGN,ORUNKNOWNCAUSE.

1

ENCLOSURE 3

• Page CD. 1 C~/12/96 OPERAT!% REACTORS EVENTS MEEi!N6 FOLLOWUP ITEMS AS OF MEETING B6-28 ON AU6UST !!,1986 (IN ASCENDING MEEi!N6 LATE, NSSS VENDOR, FACILITY ORDER)

MEET!1~) FACILITY RESPONSIBLE TASK DESCRIPTION SCHEDULE CLOSEDDATE COMMENTS NUMBER / NSSS VENDOR / DIVISION / COMPLET. BY DOCU.iENT, MEET!] EVENT DESCRIP. INDIVIDUAL CATE(S) MEETING,ETC.

DATE 86-10 OVSTERCREEK NRR / HOUSTON W RESOLVE THE QL'ESTION OF THE 10/30/86 OPEN / / FOLLOWUP ACTION TO 01/31/86 6E / LEVEL / ACCEPTABILITY OF ELIND SWITCHES / / BE INCORPORATED IN SWITCH SETPOINT AND DELET!0N OF DA!LY CHANNEL // REVIEW OF JUNE DRIFT CHECK 1,1986 EVENT AT LASSALLE 86-21 VERMONT YANKEE NRR /HOLAHAN 6. DETERMINE STATUS AND 08/20/96 DPEN / /

06/23/86 6E / PROBLEMS / EFFECTIVENESS OF STAFF AND / /

WITH SCRAM LICENSEE ACT!DN ON / /

SOLEN 0!D VALVES POST-MAINTENANCE TESTING (6L

, 83-28). DEVELOP RECOMMENDAil0NS FOR FURTHER ACTION 86-21 TURKEYPOINT NR / ROSA F. CONSIDER REVIEWIN6 ELECTRICAL 08/30/86 OPEN / /

06/23/86 W /PDTENTIAL / SYSTEM OF PLANT WITH SIMILAR / /

! FAILURE OF ALL SWING BUS DESIGN //

EMERGENCY DIESEL GENERATORS 86-23 PERRY NRR / HOUSTON W. OBTAIN AND REVIEW INFORMATION 08/29/96 OPEN / /

07/07/96 GE / FIRE IN / RELATEDTORECURRENCEOFFIRE / /

OFF6AS CHARC0AL AND INVESTI6 ATE PROPOSED //

BEDS ACTIONS 86-23 MULT! NRR / HOUSTON W. DETERMINE APPROPRIATE 09/30/86 OPEN / /

07/07/86 NA / / RESULATORY REQUIREMENTS BASED //

BWRS-RESIDUAL ON RECOMMENDAi!0NS DISCUSSED AT / /

HEAT REMOVAL BRIEFIN6 PUMP / WEAR RING FAILURES -

FOLLOWUP 86-23 MULT! NRR / BERLIN 6ER C. ASSURE NRR AND IE C00RDINAi!0N 08/30/06 OPEN / /

07/07/96 NA / / TO DETERMINE THE NEED FOR AN IE / /

PWRS-!NADEGUATE BULLEi!N / /

DESIGN OF ECCS PUMP MINIMUM FLOW PATHS B6 26 RANCHO SECO 1 NRR /RE6AN W. FIND OUT IF PUMPS ARE USED IN 08/30/86 OPEN / /

07/28/86 BW / BOTH IRAINS / OTHER SYSTEMS AT RANCHO SECO / /

OF DECAY HEAT //

REM 0'/AL DECLARED TECHNICALLY INOPERABLE

,Page No. 2 C^/12/86 OPERATING REACIDRS EVENTS MEETING FOLLONUP ITEMS AS OF MEETING 86-28 DN AU6UST 11,1986 (IN ASCENDIN6 MEETING DATE, NSSS VENDOR, FACILITY ORDER)

MEETING FACILITY RESPONSIBLE TASK DESCRIPil0N SCHEDULE CLOSED DATE COMMENTS NUMBER / NSSS VENDOR / DIVISION / COMPLET. BY DOCUMENT, MEETING EVENTDESCRIP. INDIVIDUAL DATE(S) MEETIN6,ETC.

DATE B6-26 RANCHO SECO 1 NRR /REGAN N. FOLLONUP DN USE OF FERMINITE IN 08/30/86 OPEN / /

07/28/06 H / BOTH TRAINS / PUMPS DRAIN LINE / /

OF DECAY HEAT //

REMOVAL DECLARED TECHNICALLY INOFERABLE B6-28 BRAND GULF IE / JORDAN E. ASSESSPOTENTIALFORSENERIC 09/30/06 OPEN / /

08/11/06 GE / CONTROL R0D / APPLICABILITY / /

NITHDRANAL / /

, PROBLEM k

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