ML20207E832
| ML20207E832 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek, Susquehanna, Surry, 05000000 |
| Issue date: | 12/29/1986 |
| From: | Holahan G Office of Nuclear Reactor Regulation |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| OREM-86-044, OREM-86-44, NUDOCS 8701050155 | |
| Download: ML20207E832 (19) | |
Text
,
DEC 2 91986 O
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 DECEMBER 15, 1986 - MEETING 86-44 On December 15, 1986, an Operating Reactor Events meeting (86-44) was held to 4
brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on December 8,1986. The list of attendees is included as Enclosure 1.
The events discussed and the significant elements of these events are presented in Enclosure 2. provides a sumary of those presented events that will be input to NRC's performance indicator program as significant events and a sunmary of the scram with complications not formally presented in the Operating Reactor Events meeting.
Af/
Gary M. Holahan, Director Operating Reactors Assessment Staff
Enclosures:
As stated cc w/ Encl.:
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J. Taylor L. Rubenstein C. Heltemes R. Hermann R. Starostecki J. Donohew D. Ross J. Zwolinski T. Murley, Reg. I M. Thadani J. Nelson Grace, Reg. II E. Adensam J. Keppler, Reg. III T. Rotella R. D. Martin, Reg. IV J. Stang J. B. Martin, Reg. V R. Gilbert 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. Itouston B. Sheron B. Boger D. Crutchfield E. Rossi G. Lainas V. Benaroya W. Regan D. Vassallo E. Jordan J. Rosenthal R. Baer E. Weiss l
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DEC 2 91986 ENCLOSURE 1 1-LIST OF ATTENDEES i
OPERATING REACTORS EVENTS BRIEFING (86-44)
DECEMBER 15, 1986 NAME DIVISION NAME DIVISION G. Holahan ORAS/NRR M. Virgilio ORAS/NRR D. Tondi ORAS/NRR M. Thadani BWR/NRR D. Vassallo BWR/NRR E. Merschoff DQAVT/IE S. Black PPAS/NRR D. Tarnoff ORAS/NRR J. Giitter IE/DEPER J. Schiffgens F0BA/NRR M. Caruso ORAS/NRR G. Dick PWR-B/NRR D. Basdekas RAB/RES R. Bosnak DSR0/NRR V. Benaroya PAF0/NRR D. Muller BWR/NRR D. Notley BWR/NRR R. Anand BWR/NRR J. Jacobson DQAVTT/IE J. Carter ORAS/NRR P. Milano DQAVTT/IE P. Baranowsky AE0D J. Kauffman AE00 B. Boger DHFT/NRR G. Murphy ORNL/NOAC J. Rosenthal EAB/IE R. Vollmer NRR R. Hermann NRR R. Hernan PPAS/NRR R. Auluck BWR/NRR D. Becker BWR/NRR M. Chiramal AE0D K. Kniel DSR0/NRR G. Klingler DI/IE L. Rubenstein PWR-A/NRR E. Weiss DEPER/IE j
J. Henderson DEPER/IE J. Stolz PWR-B/NRR W. Regan PWR-B/NRR D. Allison EAB/IE F. Miraglia PWR-B/NRR F. Schroeder PWR-B/NRR R. Houston BWR/NRR D. Humenansky OCM/LZ S. Rubin AEOD C. Rossi PWR-A/NRR T. Novak PWR-A/NRR R. Wilson IE i
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ENCLOSURE 2 OKRATING EACTORS EVENTS BRIEFING 86-M DECEMBER 15, 1986 SURRY UNIT 2 FAILUE OF MAIN FEEDWATER PIE 0YSTER CREEK DRYWELL SHELL CORROSION - UPDATE filLTIPLANT CABLE SPLICES UNQUALIFIED - UPDATE OTER EVENT OF INitHEST SUSQUEHANNA UNIT 2 ItPROPER VALVE POSITIONING PRIEDURE n
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12/15/86 SURRY UNIT 2 - FAILURE OF MAIN FEEDWATER PIE DECEMBER 9, 1986 (C. PATEL, NRR)
PROBLEM: AN 18-INCH MAIN FEEDWATER PIE ON THE SUCTION SIDE OF FEEDWATER PLNP "A" FAILED CATASTROPHICALLY CAUSE:
PRELIMINARY INFORMATION ATTRIBUTES CAUSE OF PIPING FAILURE TO EROSION OF PIE WALL AND A PPESSURE TRANSIENT WHICH OVERLOADED THE EINNED WALL SECTION SIGNIFICANCE:
6 WORKERS INJURED (2 DIED, 4 IN CRITICAL OR SERIOUS CONDITION)
DISCUSSION:
AT 2:20 P.M. ON 12/9/86, THE REACTOR WAS OPERATING AT 100% POWER MAIN STEAM ISOLATION VALVE (MSIV) "C" CLOSED INADVERTENTLY "A" AND "B" MISVs CLOSED REACTOR TRIPPED ON LOW LOW LEVEL IN STEAM GENEPATOR "C" AN 18" MAIN FEEDWATER PIW ON TE SUCTION SIDE OF FEEDWATER PTP "A" FAILED CATASTROPHICALLY RELEASING STEAM TO THE TURBINE "UILDING OPERATORS TURNED OFF ALL SECONDARY SIDE PLMPS, ISOLATED FEEDWATER ISOLATION VALVES AND OTHER LINES G0ING TO THE AFFECTED APEA lHE LICENSEE DECLARED AN ALERT STEAM GENERATOR LEVELS WERE MAINTAINED WITH AUXILIARY FEEDWATER AND STEAM WAS DT1 PED TO ATMDSPHERE FIRE PROTECTION SYSTEM INITIATED AND DT1 PED HALON AND CO IN EERGENCY 2
SWITCHGEAR ROOM AND CABLE SPREADING ROOM AT 2 A.M., THE RESIDUAL HEAT REMOVAL SYSBl WAS PUT IN SERVICE UNIT REACHED COLD SHUTDOWN DURING THE f0RNING OF 12/10/86 TE REGION DISPATCHED AN AUGENTED INSKCTION TEAM LICENSEE EXAMINED "A" FEEDWATER PLMP DISCHARGE CHECK VALVE AND FOUND DAMAGED INTERNALS THE LICENSEE SHUT DOWN UNIT 1 FOR EXAMINATION AND FOUND PIK THINNING IN SAE PIK FOLLOWUP:
LICB4SEE CONTINUING IT'S EVALUATION OF TRANSIENT AND PIK FAILURE LICENSEE TO EXAMINE ADDITIONAL UNIT 1 PIPING AND BASED ON TEST RESULTS ESTABLISH A PLAN OF ACTION AIT CONTINUING INVESTIGATION OF EVENT IE TO ISSUE INFORMATION NOTICE
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12/18/86 0YSTER CREEK - DRYWELL SHELL CORROSION - UPDATE NOVEMBER 20, 1986 (R. HERMANN, NRR) PROBLEM: LOCAL CIRCUMFERENTIAL WASTAGE OF DRYWELL SHELL OUTSIDE THICKNESS, SAND P0CKET REGION CAUSE: WASTAGE THOUGHT TO BE RELATED TO MOISTURE ENTRAINED IN SAND. POSTULATED MECHANISM - UNIFORM CORROSION OF STEEL IN AN AQUE0US ENVIRONMENT ACCELERATED BY CONTAMINANTS / MICRO-0RGANISMS. SIGNIFIC/bC_El DEGRADED SHELL MAKES CONTAINMENT INTEGRITY UNCERTAIN. DISCUSSION: MEETING HELD WITH LICENSEE - DECEMBER 12, 1986 SEVEN CORES (SAMPLES) REMOVED FROM DRYWELL WALL AND SAND GENERAL WASTAGE VERIFIED - BAYS 17-19, BAY 11 (LOCAL AVERAGE - 0.841", MIN. 0.741") LOCAL SMALL LAMINATIONS IN PLATES - BAY 5 ULTRASONIC MEASUREMENTS VERIFIED SHELL THINNING TO 0.700 INCHES ANALYZED - LOCAL SHELL DISCONTINUITY INFORMATION NOTICE 86-99 ISSUED DEC. 8, 1986 FOLLOWUP MEETING TO BE SCHEDULED WITH THE LICENSEE (GPU NUCLEAR) NRR TO SUPPLEMENT BY SURVEY INFORMATION RECEIVED FROM BWROG STAFF TO EVALUATE NEED FOR FURTHER REGULATORY ACTION
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12/18/86 MULTIPLANT-CABLE SPLICES UNOUALIFIED - UPDATE DECEMBER 5, 1986 --(J. JACOBSON, IE) PROBLEM: UNOUALIFIED BUTT SPLICE CONNECTORS WERE SUPPLIED BY GE TO VARIOUS LICENSEES AS PART OF A QUALIFIED PENETRATION ENCLOSURE ASSEMBLY TESTING PERFORMED BY WYLE LABORATORIES ON DEC. 4-5, 1986 HAS SHOWN THESE CONNECTORS WILL LIKELY SHORT TO GROUND IN A LOW TEMPERATURE STEAM ENVIRONMENT CAUSE: INCOMPLETE REVIEW 0F QUALIFICATION PACKAGE BY LICENSEE QUESTIONABLE TEST DATA PROVIDED BY GE IN ORIGINAL PENETRATION ENCLOSURE QUALIFICATION PACKAGE i SIGNIFICANCE: POTENTIAL FOR LOSS OF ELECTRICAL EQUIPMENT AND INSTRUMENTATION ROUTED INTO DRYWELL THROUGH PENETRATION ENCLOSURES DISCUSSION: GE SUPPLIED SPLICES MANUFACTURED BY AMP, HOLLINGSWORTH, AND THOMAS AND BETTS ALONG WITH QUALIFIED TYPE F101 PENETRATION ENCLOSURES FOUR SAMPLES TESTED AT WYLE WHICH WERE REMOVED FROM QUAD CITIES AFTER 12 YEARS AS INSTALLED SPARES SAMPLES WERE ENERGIZED WITH 528 AND 132 VAC AND EXHIBITED EXCESSIVE j LEAKAGE CURRENTS TO GROUND FIRST FAILURE OCCURRED DURING PREHEAT AT 150*F FAILURE MODE IS SUCH THAT NEW CONNECTORS COULD ALSO EXPERIENCE FAILURE 1 AMP HAS SOLD SIMILAR QUALIFIED CONNECTORS WHOSE QUAliFICl,il0N IS ALSO IN QUESTION FOLLOWUP: IE INFORMATION NOTICE TO BE ISSUED IE INSPECTION OF AMP QUALIFICATION REPORTS SCHEDULED FOR WEEK OF 12/15/86 THUS FAR, FOUR NUCLEAR UNITS AFFECTED BY THIS PROBLEM QUAD CITIES 1 8 2 SHUTDOWN AND TAPED CONNECTIONS ^ DRESDEN 3 SHUTDOWN AND TAPED CONNECTIONS DUANE ARNOLD SHUTDOWN AND TAPING CONNECTIONS \\1 ,.w--
12/15/86 OTER EVENT OF INTEEST SUSOUEHANNA UNIT 2 - IPPROPER VALVE POSITIONING PROCEDURE OCTOBER 24,1986 (M THADANI, NPR) PROBLEM: OPERATING PROCEDURES SECIFYING ALIGNTNT OF TE EERGENCY SWITCHGEAR R00M COOLERS INADVERTENTLY PLACED THE FLOW CONTROL VALVES IN TE CLOSED POSITION, RENDERING SWITCHGEAR ROOM COOLER INOPERABLE CAUSE: VALVE CONTROLLER MISLEADING (VALVE OPENED AT 0% POSITION, CLOSED AT 100% POSITION) SIGNIFICANCE: IN A LOCA, INOPERABLE E E RGENCY SWITCHGEAR ROOM 000LER COULD RESULT IN LOSS OF LPCI AND COE SPRAY SYSTEMS, DISCUSSION: ON OCTOBER 24, 1986, DURING A QUARTERLY SERVICE WATER FLOW TEST, TE E E RGENCY SWITCHGEAR ROOM COOLER WAS DETERMINED TO BE INOPERABLE DUE TO LACK 0F COOLING WATER FLOW, THE EERGENCY SWITCHGEAR ROOM COOLER IS INTENDED TO MAINTAIN THE SWITCHGEAR ROOM TElPERA11JRE BELOW 104*F, THE MAXItUi QUALIFIED ELECTRICAL COPPONENTS TEPPERATUE, TE PROCEDURE FOR OPERATION OF COOLER CALLED FOR FLOW REGULATING VALVES HV-27203 A & B TO BE PLACED IN 100% POSITION (ASSIM D OPEN POSITION), 100% POSITION CLOSES THE VALVE INSTEAD OF OPENIfE IT, COOLING WATER FLOW WAS LOST - COOLING OF TE EERGENCY SWITCHGEAR ROOM WAS LOST. IF TE BERGENCY SWITCHGEAR ROOM TEMPERATURE EXCEEDS 104*F, LPCI AND CS SYSTEFS COULD FAIL ON DEMAND, OPERATORS SET TE VALVE POSITION TO 0% - THE VALVE OPENED, COOLING WAS RESTORED PROCEDIJRE HAS BEEN REVISED - OPERATORS HAVE BEEN ALERTED, LABCLS WERE INSTALLED SHOWING VALVES OPENED AT 0% AND CLOSED AT 100%, FOLLOWUP: NRR-FM FOLLOWUP TO DETERMINE EXTENT OF THIS VALVE CONTROLLER SCALItE SODE AND TE APPROPRIATENESS OF CHANGING PROCEDURES IN LIEU OF K)DIFYING VALVE CONTROLLER SCALES.
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REACTOR SCRAM
SUMMARY
WEEK ENDING 12/14/86 I. PLANT SPECIFIC DATA DATE SITE UNIT POWER RPS CAUSE COMPLI-YTD YTD YTD CATIONS ABOVE BELOW TOTAL 15% 15% s 12/09/86 LACROSSE 1 98 M EQUIPMENT NO 7 10 17 12/09/86 SURRY 2 100 A EQUIP / MECH. YES 4 0 4 12/09/86 QUAD CITIES 1 15 A EQUIP /COND. LEAK NO 2 2 4 12/10/86 DUANE ARNOLD 1 OA QUIP / ELECT. NO O 2 2 12/10/86 SAN ONOFRE 2 93 A EQUIP / ELECT. YES 7 2 9 12/11/86 DRESDEN 3 85 A EQUIP / MECH. NO 6 0 6 12/12/86 PRAIRIE ISLAND 1 99 A EQUIP / MECH NO 1 1 2
SUMMARY
OF COMPLICATIONS SITE UNIT COMPLICATIONS SURRY 2 RUPTURE OF AN EIGHTEEN INCH MFW LINE SAN ONOFRE 2 LOSS OF STEAM BYPASS CONTROL SYSTEM SECONDARY STEAM SAFETY VA LVE OPENED f e 9 ~
II. COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES SCRAMS FOR WEEK ENDING 12/14/86 SCRAM CAUSE POWER NUMBER 1986 1985 OF WEEKLY WEEKLY SCRAMS (5) AVERAGE AVERAGE YTD (3) (4) no POWER >15% EQUIP. RELATED >15% 5 4.3 5.4 (68%) PERS. RELATED(6) >15% 0 1.9 2.0 (25%) OTHER(7) >15% 0 0.4 0.6 ( 7%) on Subtotal ** 5 6.6 8.0 no POWER <15% EQUIP. RELATED <15% 1 1.3 1.3 (54%) PERS. RELATED <15% 0 0.8 0.9 (38%) OTHER <15% 1 0.2 0.2 ( 8%)
- Subtotal **
2 2.3 2.4 con Total *** 7 8.9 10.4 MANUAL VS AUTO SCRAMS TYPE NUMBER 1986 1985 OF WEEKLY WEEKLY SCRAMS AVERAGE AVERAGE YTD MANUAL SCRAMS 1 1.0 1.0 AUTOMATIC SCRAMS 6 8.0 9.4
i.. I.... 7 NOTES 1 -- PLANT SPECIFIC DATA BASED ON INITIAL REVIEW OF 50.72 REPORTS FOR THE NEEK OF INTEREST. PERIOD IS MIDNIGHT SUNDAY THROUGH ) MIDNIGHT SUNDAY SCRAMS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RE5iiLT IN ROD MOTION, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE WITH A PLANT PROCEDURE. 2. REC]VERY COMPLICATED BY EQUIPHENT 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.- 1 I 4. IN 1985, THERE WERE AN ESTIMATED TOTAL 0F 541 AUTOMATIC AND e MANUAL UNPLANNED REACTOR TRIPS AT 93 REACTORS (HOLDING FULL i-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 100 REACTORS HOLDING A FULL POWER LICENSE. 6. PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDlIRAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS. 7.
- 0THER"
- INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES(LIGHTNING),SYSTEMDESIGN,ORUNKNOWNCAUSE.
O P O 9 ~- e
ENCLOSURE 3 ' Page No. 1 12416/B6 SIGNIFICANT EVENTS FREQUENCY PERFORMANCE INDICATOR Wo. 3 PLANT NAME EVENT EVENT DESCRIPTION SIGNIFICANCE DTR DATE CU ME ARNOLD 12/09/86 PROBLEM WITH EQ OF AMP SPLICES ENTERING PDTENTIAL FOR OR ACTUAL DEGRADATION OF 1 DRYWELL.MDST EQUIPMENT SERVED BY THESE CABLES IS SAFETY-RELATED EDUIPMENT SAFETY RELATED SAN DNOFRE 2 12/10/86 SCRAR COMPLICATED BY LOSS OF STEAM BYFASS SCRAM WITH COMPLICAT!DNS 1 CONTROL SYSTEM. SECONDARY STEAM SAFETY VALVE GPENED.0PERATORS USED ATMOSPHERIC DUMP VALVES FOR ABOUT 20 MINUTES UNTIL STEAM BYFASS WAS RESTORED SUPRY 2 12/09/86 INADVERTENT MSIV CLOSURE. REACTOR TRIP DN LOW SCRAM WITH COMPLICATIONS 1 LOW S/6 LEVEL'. SHORTLY AFTER AN 18 INCH MAIN FEEDWATER PIPE ON SUCTION SIDE OF FEEDWATER PUMP FAILED CATASTROPHICALLY i a 1 ll 1 a, D I f .,n..
12/15/86 SAN ONOFRE UNIT 2 - SCPAM WITH COMPLICATIONS DECEMBER 10, 1986 - (H ROOD, NRR) PROBLEM: OPERATOR ERROR CAUSES REACTOR TRIP; RECOVERY C0FPLICARD BY EQUIPPDfT MALFUNCTION CAUSE: OPERATOR DID NOT FOLLOW PROCEDURES DURING TRANSFER OF BUS TO ALTERNATE POWER SOURE BAD CIRCUIT CARD PREVENTED STEAM BYPASS SYSTEM FROM FUNCTIONING PROPERLY SIGNIFICANCE:- SCRAM WITH COPPLICATIONS CHALLENGED SECONDARY SAFETY VALVES DISCUSSION: POWER TO NON-1E INSTRLPENT BUS INTERRUPTED DURING TRANSFER TO ALTERNATE TOER SOURE. LOSS OF BUS F0WER CAUSED TURBINE STOP VAL \\ES TO CLOSE RESULTING IN RJRBINE/ REACTOR TRIP FROM 93% POWER STEAM BYPASS VALVES FAILED TO OPEN DUE TO CIRCUIT CARD FAILURE STEAM SAFEIY VALVES LIFTED, OPERATORS OPENED ADVs RECONSTRUCTION OF TRIP SEQUENE HINDERED BECAUSE PLANT MONITORING COPPLTIER WAS OLIT OF SERVIE OE OF 4 PPS CHANNELS DID NOT INDICATE LOSS OF LOAD TRIP NO ESF ACTUATION ALL SAFETY SYSTEMS FUNCTIONED PROPERLY FOLLOWUP: LICENSEE COUNSELLED OPERATORS REGARDING NEED TO FOLLOW PROCEDURES BAD CIRCUIT CARD REPLACED 6}}