ML20136C514

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Summary of Operating Reactors Event Meeting 85-21 on 851028.List of Attendees,Events Discussed & Completion Dates Assigned Encl
ML20136C514
Person / Time
Site: Palo Verde, Perry, Susquehanna, North Anna, La Crosse, 05000000, Trojan, Crane
Issue date: 11/11/1985
From: Crutchfield D
Office of Nuclear Reactor Regulation
To: Thompson H
Office of Nuclear Reactor Regulation
References
OREM-85-021, OREM-85-21, NUDOCS 8511210104
Download: ML20136C514 (24)
v • d • e


Text

m, NOV 111985 MEMORANDUM FOR:

Hugh L. Thompson, Jr., Director Division of Licensing FROM:

Dennis M. Crutchfield, Assistant Director for Safety Assessment, DL

SUBJECT:

SUMMARY

OF THE OPERATING REACTORS EVENTS MEETING ON OCTOBER 28, 1985 - MEETING 85-21 On October 28, 1985, an Operating Reactor Events meeting (85-21) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on October 21, 1985. 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 assignees are approaching the due date. Please be responsive and advise ORAB (D. Tarnoff, x29526) if the target completion date cannot be met.

Dennis M. Crutchfield, Assistant Director for Safety Assessment, DL

Enclosures:

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NOV 111985 MEMORANDUM FOR:

Hugh L. Thompson, Jr., Director Division of Licensing FROM:

Dennis M. Crutchfield, Assistant Director for Safety Assessment, DL

SUBJECT:

SUMMARY

OF THE OPERATING REACTORS EVENTS MEETING ON OCTOBER 28, 1985 - MEETING 85-21 On October 28, 1985, an Operating Reactor Events meeting (85-21) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on October 21, 1985. 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 assignees are approaching the due date. Please be responsive and advise ORAB (D. Tarnoff, x29526) if the target completion date cannot be met.

Dennis M. Crutchfield, sistant Director for Safety Asses ment, DL

Enclosures:

As stated cc w/ encl:

See next page

i, l

Hugh L. Thompson, Jr. cc:

H. Denton R. Hernan

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R. Bernero F. Schroeder J. Knight D. Silver T. Speis J. Lyons C. Heltemes D. Brinkman T. Novak E. Weiss W. Russell R. Baer J. Taylor J. Stang E. Jordan J. Zwo11nski F. Rowsome R. Dudley W. Minners M. Licitra L. Shao G. Knighton T. Ippolito M. J. Campagnone G. Lainas W. Butler E. Sullivan H. Bailey D. Beckham J. Thoma G. Edison E. Tourigny K. Seyfrit E. Butcher T. Murley, R-I J. Stolz J. Nelson Grace, R-II L. Engle J. Keppler, R-III J. Stefano R. D. Martin, R-IV B. J. Youngblood J. B. Martin, R-V J. Wermiel R. Starostecki, R-I R. Walker, R-II' C. Norelius, R-III E. Rossi, IE P. Baranowski D. Kirsch, R-V R. Denise, R-IV

ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (85-21)

OCTOBER 28, 1985 Name Division Name Division D. Eisenhut NRR W. Regan NRR/DAFS E. Licitra NRR/DL/LB3 R. Freeman AE0D

' W. Haas IE/VPB S. Rubin AE0D E. Butcher NRR/DL/0RB3 T. Speis NRR/DSI C. Miller NRR/DL/ADSA E. Rossi IE/DEPER/EAB S. Long IE/DEPER/EAB M. Ley NRR/DL/LB3 R. Singh IE/DEPER/EAB F. Schroeder NRR/ DST G. Knighton NRR/DL/LB3 F. Miraglia

$RR/DL E. J. Weinkam NRR/DL/ADL G. Holahan NRR/DL M. Chiramal AEOD/ROAB R. Wessman NRR/DL M. Campagnone NRR/DL/LB2 W. Butler NRR/DL/LB2 J. Thoma NRR/DL/0RB4 T. Wambaugh NRR/DL/0RB5 E. Weiss IE/DEPER R. Wright NRR/DE J. Stang NRR/DL/ ORB 5 R. Hernan NRR/PPAS E. Tourigny NRR/DL/0RB3 J. Beard NRR/DL/0RAB T. Rotella NRR/DL/0RB5 M. Caruso NRR/0RAB W. Johnston NRR/DE G. Lainas NRR/DL W. Minners DST R. Bernero DSI J. Zwolinski NRR/DL/0RABS L. Engle NRR/DL/0RB3 D. Tarnoff NRR/DL/0RAB D. Humenansky OCM/ZECH

OPERATING REACTOR EVENTS BRIEFING (85-21)

OCTOBER 28, 1985 LA CROSSE LOSS OF 0FFSITE POWER APPARENT FAILURE TO SCRAM i

PALO VERDE 1 UNPLANNED REACTOR TRIP DURING TESTING SUSQUEHANNA 1 CONDENSATE RESIN SPILL TROJAN INCORRECT SETPOINTS FOR TRIP 0F AFW PUMPS ON LOW SUCTION PRESSURE I

TMI 1 START UP STATUS REPORT NORTH ANNA 1 LOSS OF CCW TO RCP MOTOR MAIN BEARINGS PERRY 1 TEST RETURN LINE PIPING OVERPRESSURIZATION 4

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il LA CROSSE - LOSS OF 0FFSITE POWER OCTOBER 22,1985 (R, DUDLEY, NRR)_

PROBLEM:

LOSS OF 0FFSITE POWER SIGNIFICANCE:

UNIQUE PLANT DESIGN HAS ONLY ONE OFFSITE POWER SOURCE, BUT PLANT IS CAPABLE OF C00LDOWN WITH-OUT ANY AC POWER CIRCUMSTANCES:

MAINTENANCE (WINTERIZATION) BEING PERFORMED ON SWITCHYARD BREAKER TO GRID

" BUMPING" 0F BREAKER TRIP BAR CAUSED IT TO OPEN; GENERATOR LOST 80% LOAD, PLANT TRIPPED ON HI FLUX DUE TO PRESSURE SPIKE CAUSED BY TURBINE INLET VALVES CLOSING EDGs STARTED AND POWERED ALL REQUIRED LOADS 1 HOUR REQUIRED TO REFILL AIR RECEIVER WITH AIR COMPRESSOR AND RE-CLOSE BREAKER FOLLOWUP:

NRR/PM INVESTIGATING TIME REQUIRED TO RE-CLOSE BREAKER TO ENSURE THAT SEP REVIEW 0F 0FF-SITE POWER IS ADEQUATE.

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f LA CROSSE - APPARENT FAILURE TO SCRAM OCTOBER 23, 1985 - (R DVDLEY, NRR) 1 PROBLEM:

APPARENT FAILURE OF REACTOR PROTECTION SYSTEM TO SCRAM UPON RECEIPT OF HIGH FLUX SIGNAL SIGNIFICANCE:

i HIGH-INTEREST OCCURRENCE HIGH SAFETY SIGNIFICANCE IF SAFETY LIMITS EXCEEDED W/0 SCRAM UNIQUE PLANT DESIGN; N0 GENERIC APPLICATIONS i

CIRCUMSTANCES:

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OPERATOR PULLING RODS AT 10-5% POWER AND FAILED TO UPSCALE INSTRUMENTATION "CH,6 HI-FLUX" ALARM RECEIVED i'

1 0F 2 LOGIC WAS SATISFIED BUT NO SCRAM OCCURRED I

RODS MANUALLY INSERTED l

FOLLOW UP:

REG, III ISSUED CONFIRMATORY ACTION LETTER REQUIRING PERMISSION BEFORE RESTART, SRI AND REG, III TEAM INVESTIGATED CONCLUDED THAT ALARM RELAY ACTUATED EARLY AT 112% OF SCALE; TRIF RELAY SETPOINT OF 115% NOT REACHED (VALID TRIP SIGNAL i

NOT GENERATED) j TESTING WAS ABLE TO REPRODUCE CIRCUMSTANCES OF THIS EVENT s

ENTIRE INSTRUMENT DRAWER REPLACED l

TRIP SYSTEM SUCCESSFULLY TESTED l

PERMISSION GIVEN TO RESTART ON OCTOBER 24, 1985 i

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PALO VERDE 1 - UNPLANNED REACTOR TRIP DURING TESTING OCTOBER 24, 1985 (E. A LICITRA, NRR)

PROBLEM:

UNPLANNED REACTOR TRIP, C00LDOWN TRANSIENT AND SAFETY INJECTION SAFETY SIGNIFICANCE:

PLANT PERFORMANCE NOT AS EXPECTED BY UTILITY DISCUSSION:

PLANT AT 80% POWER WITH ALL PLANT LOADS ON STARTUP TRANSFORMER AS PART OF A PLANNED TEST, TURBINE MANUALLY TRIPPED TO SIMULATE LOAD REJECTION AND TEST REACTOR CUTBACK LOGIC TURBINE THROTTLE VALVES CLOSING CAUSED UNEXPECTED

" PRESSURE PULSE" IN STEAM GENERATORS; FALSE S/G LOW LEVEL CAUSED SCRAM TURBINE BYPASS VALVES FAILED TO CONTROL STEAM GENERATOR HEAT REMOVAL; ONE VALVE FAILED OPEN AND OTHER VALVES REOPENED CAUSING C00LDOWN TRANSIENT MSIVs CLOSED AND SAFETY INJECTION INITIATED ON LOW PRESSURE RCS PRESSURE DROPPED TO 1774 PSIG; T-AVE DROPPED TO 546*; PRESSURIZER LEVEL DROPPED TO 10% BEFORE PLANT STABILIZED FOLLOWUP:

PLANT IN MODE 3 LICENSEE AND COMBUSTION ENGINEERING INVESTIGA1.NG

" PRESSURE PULSE" PHENOMENON INCORRECT SETPOINT FOUND ON TURBINE BYPASS CONTROL CARD; ALL OTHER CARDS BEING CHECKED REGION V FOLLOWING LICENSEE FORECASTS RESTART ON OCTOBER 29, 1985

SUSQUEHANNA UNIT 1 - CONDENSATE RESIN SPILL I

OCTOBER 26,1985-(M.J. CAMPAGNONE, NRR) t PROBLEM:

FAILURE IN FLANGE GASKET RESULTED IN RESIN SPILL AND CONTAMINATION OF PORTION OF TURBINE BUILDING SAFETY SIGNIFICANCE:

POTENTIAL FOR UNCONTROLLED RELEASE j

i DISCUSSION:

PRIOR TO THE INCIDENT, THE "B" CONDENSATE DEMIN, WAS I

TAKEN OUT OF SERVICE FOR MAINTENANCE l

GASKET ON FLANGE TO 11" VENT LINE AT TOP 0F THE DEMIN, j,

VESSEL " LEAKED" 12,000 GALLONS OF CONTAMINATED CONDENSATE LEAKED ONTO THE FLOOR OF THE DEMIN. ROOM AND INTO THE PASSAGEWAY OF 1

THE TURBINE BUILDING (3000 SQ FT. AREA WAS CONTAMINATED)

CONTACT RADIATION:

100 MR/HR GAMMA, 500 MRAD /HR BETA I

NO AIRBORNE CONTAMINATION OR CONTAMINATION TO PERSONNEL i

FOLLOWUP:

i LICENSEE IS INVESTIGATING THE TYPE OF MAINTENANCE PERFORMED PRIOR TO THE SPILL

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TROJAN - INCORRECT SETP0INTS FOR TRIP 0F AFW PUMPS ON LOW SUCTION PRESSURE OCTOBER 17, 1985 (M. CARUS 0, NRR) 1 PROBLEM INCORRECT SETPOINT FOR AUTOMATIC TRIP OF AUXILIARY FEEDWATER (AFW) PUMPS ON LOW SUCTION PRESSURE (WAS BELOW ATMOSPHERIC PRESSURE BY.5 PSI SINCE INSTALLATION)

SIGNIFICANCE POTENTIAL FOR DAMAGE TO TWO 0F THREE AFW PUMPS ON LOSS OF NON-SAFETY GRADE SUCTION SOURCE DISCUSSION:

PRESSURE TRANSMITTERS INSTALLED (APPR0X. 1981) AS PART OF TMI ITEM ll.E.1.1.

PRESSURE TRANSMITTER CAllBRAliON ERROR; ONE FOOT ELEVATION DIFFERENCE BETWEEN SUCTION PIPE AND TRANSMITTER NOT ACCOUNTED FOR (TRANSMITTER IS BELOW PIPE) l CORRECTIVE ACTION SETPOINTS ADJUSTED TO CORRECT ERROR CST LEVEL INCREASED BY 10%

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TMI 1 - START UP STATUS REPORT OCTOBER 28, 1985 (J. THOMA, NRR)

START-UP SE0VENCE DATE COMPLETED FINAL HEATUP AND SURVEILLANCE TESTING 10/3/85

  • REGION APPROVAL TO APPROACH CRITICALITY 10/3/85 ZERO AND LOW POWER PHYSICS TESTING 10/5/85 3% POWER TESTING 10/8/85
  • REGION APPROVAL TO PROCEED 10/8/85 15% POWER TESTING 10/9/85 25% POWER TESTING 10/15/85 40% POWER TESTING 10/21/85 l

CONCLUDED WITH REACTOR TRIP 10/21/85

  • REGION APPROVAL TO PROCEED 10/23/85 48% POWER - 30 DAYS OPERATOR TRAINING
  • REGION APPROVAL TO PROCEED 75% POWER - 35 DAYS OF TESTING 8 TRAINING
  • REGION APPROVAL TO PROCEED l

100% POWER - 5 DAYS OF TESTING CONCLUDED WITH REACTOR TRIP

  • REGION APPROVAL TO PROCEED REC 0VERY TO 100% OPERATION START-UP PROBLEMS THERE HAVE BEEN NO MAJOR PROBLEMS OF SAFETY SIGNIFICANCE ENC 0UNTERED IN THE START-UP, THE REGION HAS MONITORED ALL PROBLEMS ENC 0UNTERED TO DATE.

SOME OF THE PROBLEMS ENCOUNTERED INCLUDE:

STEAM LEAKS ON THE MAIN TURBINE THROTTLE DRAIN LINES l

SAFETY VALVES ON EFW TURBINE STEAM SUPPLY LIFTED & RESET l

OTSG PRESSURE CONTROL PROBLEMS ON THE TRIP L

NORTH ANNA UNIT 1, LOSS OF CCW TO RCP MOTOR MAIN BEARINGS OCTOBER 24, 1985 - (L. B, ENGLE, NRR)

PROBLEM:

LOSS OF CCW TO RCP MOTOR UPPER 8 LOWER MAIN BEARINGS AND STATOR COOLERS REQUIRED REACTOR-TURBINE 8 RCP TRIP SIGNIFICANCE:

POTENTIAL SYSTEMS INTERACTION CIRCUMSTANCES:

AT 0330 HOURS ON OCTOBER 24, 1985, LOSS OF THE 1-J-1 BUS FROM BREAKER FAILURE IN A BATTERY ROOM EXHAUST FAN RESULTED IN LOSS OF A SEMI-VITAL PANEL LOSS OF BUS CLOSED VALVES THAT SUPPLY CCW TO RCPs A, B, a C MAIN BEARINGS AND STATOR, UNIT COMMENCED RAMP DOWN FROM 100% POWER AND'RCP MOTOR TEMPERATURES WERE TRENDED FOR RISE IN TEMPERATURE, RCP MOTOR BEARING TEMPERATURE RISE TO 195'F WHEN MANUAL REACTOR-TURBINE TRIP INITIATED AT 87% AND RCPs WERE DE-ENERGIZED, UNIT WAS PLACED IN NATURAL CIRCULATION FOR ABOUT 3 HOURS.

1-J-1 BUS REPAIRED AND RE-ENERGIZED: CCW RESTORED TO RCP MOTOR BEARINGS AND RCP "A" RESTARTED, UNIT STABLE IN MODE 3.

FOLLOW UP:

POST-TRIP REVIEW AND ASSESSMENT BY LICENSEE EXHAUST FAN BREAKER FAILURE UNDER INVESTIGATION BY LICENSEE AFTER REPAIRS TO BREAKER AND RE-ENERGIZING 1-J-1 BUS, UNIT WENT CRITICAL AT 1901 HOURS ON OCTOBER 25, 1985.

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PERRY 1 - TEST RETURN LINE PIPING OVERPRESSURIZATION OCTOBER 23, 1985 (HENRY BAILEY, IE)

PROBLEM:

OVERPRESSURIZATION OF HPCS RECIRCULATION PIPING DURING PRE-0PERATIONAL TESTING SAFETY SIGNIFICANCE:

P0TENTIAL BREAKDOWN IN TEST PROGRAM MANAGEMENT AND/0R INADEQUATE TEST PROCEDURES DISCUSSION:

PLANT STATUS - COLD, UNFUELED RUNNING VIBRATION TEST ON CORE SPRAY PIPING BOTH TEST RETURN VALVES TO CST AND HOTWELL WERE LEFT CLOSED DUE TO IMPROPERLY SPECIFIED VALVE LINEUP IN PROCEDURE i

NO DISCHARGE PATH FOR HPCS PUMP DIAPHRAGM ON TWO LIQUID RADWAST ALTERilATE RETURN LINES RUPTURED

'::S PUMP DISCHARGE PRESSURE WAS 1250 PSIG AND TEST RETURN LINES ARE 150 PSIG PIPING HPCS FLOW 0F APPROX. 2000 GPH LEAKED TO RADWASTE BUILDING SUMP FOLLOWUP:

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