ML20215D063
| ML20215D063 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Perry, Indian Point, Point Beach, Oyster Creek, Haddam Neck, Ginna, Rancho Seco, 05000000 |
| Issue date: | 12/11/1986 |
| From: | Holahan G Office of Nuclear Reactor Regulation |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8612160189 | |
| Download: ML20215D063 (14) | |
Text
{{#Wiki_filter:-- - _ _ _ _ _ __ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ DEC 111986 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 k HEETING ON DECEMBER 1,1986 - MEETING 86-42 On December 1, 1986 an Operating Reactor Events meeting (86-42) was held to btief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on November 24, 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. Enclosure 3 provides a suninary of those presente6 events that will be input to NRC's performance indicator program as significant events. 41/ ( Gary M. Holahan, Director Operating Reactors Assessment Staff
Enclosures:
As stated cc w/ Encl.: See Next Page DISTRIBUTION r Central-File' ' - NRC PDR ORAS Rdg ORAS Members W l 0 AS DTARH0FF
.C:PWR:0 RAS DTONDI C:BWR:0RASNM MJVIRGILIO D:0 RAS M@
GMHOLAHAN J.[/f/86 p g /86 o/it/86 sA/si/86 t 1DM-5 -l Ops &P 8612160189 861211 PDR ORG NRRC
. DEC 111986 Harold R. Denton cc: R. Vollmer J. Zwolinski l J. Taylor J. Stolz i C. Heltemes G. Kalman '
R. Starostecki S. Miner D. Ross J. Donohew T. Murley, Reg. I R. Hermann. J. Nelson Grace, Reg. II M. Slosson J. Keppler, Reg. III S. Varga 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. Benaroya W. Regan D. Vassallo E. Jordan J. Rosenthal R. Baer E. Weiss R. Hernan S. Showe S. Rubin G. Arlotto p - - - - - . . - -- . - - - - . . - - , . , - - . . , , - - , - - - , , - . . ._----,,,-..---_,n ------,,..n. ---- -
DEC 111986 ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (86-42) I DECEMBER 1, 1986 NAME DIVISION NAME DIVISION G. Holahan ORAS/NRR K. Wolley IE/EAB D. Tondi ORAS/NRR M. Chiramal AE00 R. Scholl ORAS/NRR P. Basdekas RES M. Slosson PAD 3/NRR G. Cwalina DHFT/NRR D. Crutchfield PWRB/NRR J. Clifford NRR B. Clayton PWRA/NRR G. Plumlee PF0B/NRR W. Regan PBF0/NRR D. Allison IE/EAB V. Benaroya PAF0/NRR D. Vassallo DBL /NRR G. Kalman PWRB/NRR G. Edison PWRB/NRR G. Murphy NOAC/0RNL A. Dromerick IE/EGCB W. Haass IE/VPB G. Klingler IE/0RPB B. Boger DHFT/NRR G. Lanik IE/DEPER L. Marsh PBEB/NRR C. Cheng PBEB/NRR j T. Rotella BWD1/NRR E. Weiss IE/DEPER E. Jordan IE T. Novak PWRA/NRR i R. Baer IE/DEPER K. Kniel DSR0 J. Stolz PWRB/NRR D. Humenansky OCM C. Ader OCM/TMR F. Schroeder PWRB/NRR F. Miraglia PWRB/NRR W. Swenson ORAS/NRR K. Eccleston TOSB/NRR M. Caruso ORAS/NRR J. Donohew BWD1/NRR D. Tarnoff ORAS/NRR _ . , _ _ . . , - - - - _ , - _ . . ~ . . . . _ .._,.. - -.. --- . . _ _ _ . _ - - - - _ _ _ _ _ _ . . _ - - _ _ _ - - . _ -
ENCLOSURE 2 i OPERATING REACTORS EVENTS BRIEFING 86-42 DECEMBER 1, 1986 SIGNIFICANT EVENTS OYSTER CREEK - DRYWELL SHELL CORROSION RANCHO SEC0 - PRESSURIZER HEATER DAMAGED OTHER EVENT OF INTEREST INDIAN POINT 2 - FAILED SAFETY INJECTION PUMP
DECEMBER 4, 1986 0YSTER CREEK - DRYWELL SHELL CORROSION NOVEMBER 20, 1986 (J. DON 0 HEW, NRR) l PROBLEM: SIGNIFICANT REDUCTION OF OUTSIDE OF DRYWELL SHELL THICKNESS, AROUND CIRCUMFERENCE AT FLOOR OF DRYWELL CAUSE: LICENSEE SPECULATES CAUSE OF CORROSION IS DUE TO M0ISTURE ENTRAINED IN SAND IN SMALL CAVITY AROUND CIRCUMFERENCE, SIGNIFICANCE: DEGRADED CARBON STEEL CONTAINMENT SHELL MAKES INTEGRITY UNCERTAIN. DISCUSSION: WATER LEAKED THROUGH BELLOWS SEAL BETWEEN OUTSIDE SHELL AND BIOLOGICAL SHIELD WHEN REFUELING CAVITY FLOODED FOR REFUELING (CYCLES 9R AND 10R) LEAKAGE COLLECTED FROM DRAINAGE CHANNEL BELOW DOWNCOMERS. WATER QUALITY INDICATED THIS WAS REACTOR GRADE WATER, SEAL BETWEEN SHELL AND CONCRETE FIXED IN CYCLE 11R OUTAGE. WATER DRAINED DOWN OUTSIDE OF SHELL TO CAVITY, FILLED WITH SAND, AND OUT DRAINAGE CHANNEL, SAND USED IN CAVITY IS SAME AS SAND USED IN MAKING CONCRETE AT OYSTER CREEK UT USED TO MEASURE SHELL THICKNESS. MEASUREMENTS RANGE FROM 0.38" TO 1.09", AVERAGE READING IS 0.92", NOMINAL WALL THICKNESS IS 1.15 " FOLLOWUP: MEETING WITH GPU NUCLEAR ON DECEMBER 1, 1986, 0YSTER CREEK RESTART FROM CYCLE 11R OUTAGE DELAYED, LICENSEE MAY REMOVE UP TO 12 CORES FROM SHELL IN CORRODED AREAS TO DETERMINE DEGREF. OF DEGRADATION GENERIC IMPLICATIONS FOR MARK I CONTAINMENTS,
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DECEMBER 4, 1986 RANCHO SEC0 - PRESSURIZER HEATER DAMAGED NOVEMBER 21, 1985 - (G. KALMAN, NRR) PROBLEM: PRESSURIZER UPPER HEATER BUNDLE BURNED OUT (1 0F 3 HEATER BUNDLES) CAUSE: MULTIPLE PERSONNEL ERRORS SIGNIFICANCE: CREDIBILITY OF SMUD PERFORMANCE IMPROVEMENT PROGRAM COMPROMISED SETBACK TO RANCHO SECO PLANNED RESTART DISCUSSION: NOVEMBER 20, 1986, OPERATORS BEGAN FILLING AND VENTIllG PRIMARY SYSTEM IN PREPARATION FOR DECAY HEAT SYSTEM OUTAGE.
"B" AND "C" PRESSURIZER LEVEL INDICATORS WERE TAGGED OUT.
"A" INDICATOR BELIEVED TO BE IN SERVICE DUE TO COMMUNICATION GAP BETWEEN OPERATORS AND MAINTENANCE PERSONNEL. "A" INDICATOR REFERENCE LEG ONLY PARTIALLY FULL. -
3:10 A.M., NOVEMBER 21, 1986, INEXPERIENCED SHIFT CREW ENERGIZED PRESSURIZER HEATERS TO RAISE STEAM BUBBLE. 3:12 A.M., CIRCUIT BREAKERS FOR TOP HEATER BUNDLE BEGAN TRIPPING. OPERATORS REPEATEDLY RESET BREAKERS AND CONTINUED ATTEMPTS TO RAISE BUBBLE. AT APPR0XIMATELY 10:00 A.M., RESISTANCE MEASUREMENTS INDICATED THAT 33 0F 39 HEATER ELEMENTS IN THE UPPER BUNDLE WERE BURNED OUT. SHEATHING AROUND HEATER IS DEFORMED (PART OF PRESSURE BOUNDARY) FOLLOWUP: CHEMICAL ANALYSIS, VIDEO INSPECTION OF PRESSURIZER REVIEW PROCEDURES FOR OPERATIONAL ACTIVITIES. ESTABLISH COMMUNICATION GUIDELINES FOR MAINTENANCE /0PERATIONS INTERFACE REVIEW OPERATOR QUALIFICATIONS / SUPERVISORY REQUIREMENTS EVALUATE CONTAINMENT PENETRATIONS FOR OVERHEAT DAMAGE REGION V AND NRR FOLLOWING LICENSEE ACTIONS
DECEMBER 4, 1986 L OTHER EVENT OF INTEREST INDIANPOINT2-FAILEDSAFETYINJECTIONPUMf NOVEMBER 13, 1986 - (M. SLOSSON, NRR) ! ERQHLEM: SAFETY INJECTION PUMP (NUMBER 22) SEIZED WHILE ATTEMPTING MANUAL START CAUSE: B0UND IMPELLER - ROOT CAUSE UNKNOWN SIGNIFICANCE: DEGRADATION OF SAFETY INJECTION SYSTEM DISCUSSION: 3 - 50% SI PUMPS PUMP SEIZED WHILE ATTEMPTING TO REFILL THE ACCUMULATORS 24 HOUR LC0 ENTERED PLANT PLACED IN HOT SHUTDOWN 48 HOUR LC0 ENTERED PLANT COMMENCED COLD SHUTDOWN PROCEDURES UNWOUND SPRING FOUND IN PUMP PUMP INTERNALS REPLACED, PUMP OPERABILITY DEMONSTRATED, SHUTDOWN DISCONTINUED PUMP MANUFACTURER'S REPRESENTATIVE ON SITE (PACIFIC PUMP) TECH SPECS DO NOT REQUIRE TESTING 0F REDUNDANT PUMPS FOLLOWUP: LICENSEE TO DISASSEMBLE JAMMED IMPELLER RESIDENT INSPECTOR FOLLOWING LICENSEE ACTIONS
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L REACTOR SCRAM EUMMARY WEEK ENDING 11/23/06
- 1. PLANT EFECIFIC DATA DATE SITE f UNIT POWER RPS CAU3E COMPLI-{ YTD YTD YTD CATIONS
- ABOVE LELCW TOTAL 15% 15%
11/26/86 PERRY 1 2A PERSONNEL NO O s # 11/28/86 POINT EEACH 2 1A EQUIP / MECH. NO 11/05/86 GINNA 1 1 2 1 100 A PERSONNEL NO 4 0 4 11/30/86 HADDAM NECK 1 100 A EQUIP / ELECT NO 4 3 11/30/86 MILLSTONE 7 1 100 A EQUIP / ELECT NO 2 1 0
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O e 6 5 O 0 7 4 0 $ e e e me - -
n - - II. COMPARICON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES SCRAMS FOR WEEK ENDING 11/23/86 SCRAM CAUSE , POWER NUMBER 1986 19E3' 0F WEEKLY l WEEKLY' SCRAM 3(5) AVERAGE AVERAGE YTD !(3) (4)
** POWER >15%
ECUIP. RELATED- >15% 2 4.4 5.4 (68%) PERS. RELATED(6) >15% 1 1.9 0.0 (C5%) OTHER(7) >15% 0 0.5 0.6 ( 7%)
** Subtotal **
3 6. 9 - C.0
** POWER <15'/.
- EQUIP. RELATED <15% 1 1.4 1.3 (54%)
< 15'/. 1 0.8 -0.9 (38%)
PERS. RELATED OTHER <15% 0 0.2 0.2 ( 8%) ,
** Subtotal **
2 2.4 2.4
*** Total ***
5 9.2 10.4 MANUAL VS AUTO SCRAMS NUMBER 1986 1985 TYPE 0F WEEKLY WEEKLY SCRAMS AVERAGE AVERAGE YTD 0 1.0 1.0 MANUAL SCRAMS 5 ' O.2 9.4 AUTOMATIC GCRAMS o S 4 0 e 9 e
, - _ ~ -.. - . - -
f.e (. .. g i. NDTES 1." ' PLANT SPECIFIC DATA BASED ON INITIAL REVIEW OF 50.72 REPORTS FOR THE WEEK OF INTEREST. PERIOD IS MIDNIGHT SUNDAY THROUGil MIDNIGHT SUNDAY 3 CRAMS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN R0D MOTION AND EXCLUDE PLANNED TESTS OR SCRAM 5 A5 PART OF PLANNED SHUTDOWN IN ACCORDANCE WITH A PLANT PROCEDURE. - 2. RECOVERY C011 PLICATED SY EQUIPllENT FAILURES OR PERSONNEL ERRO
, UNRELA,TED 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 WEEK 5/ YEAR.
, . 4.
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 PER YEAR AND AN AVERAGE RATE OF 10.4 TRIPS PER WEEK FOR ALL REACTOR $.
. 5. SASED ON 100 REACTORS HOLDING A FULL POWER LICENSE.
6. PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR PROCEDURAL DEFICIENCIES AND MANUAL STEAM GENERAT0k LEVEL CONTROL PROBLEMS. 7.
*0THER" 1NCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENYlRONMENTAL l CAUSES (LIGHTNING) SYSTEM DESIGN, OR UNKNOWN CAUSE.
. , 12/01/06 SIGNIFICANT EVENTS FREQUENCY PERFOM ANCE INDICATOR Ns 3 PLANTNAME EVENT EVENT.DESCRIFi!DN SISNIFICANCE '
GTR DATE OfSTERCREER ! 11/20'86 THICKNESS OF LRYNELL NALL REDUCED IN SOME AREAS POTENTIAL FOR OR ACTU FROM !.!!* (NOMINAL) TO 0.38'-AVERA6E C0hiA!hMENTORSAFETY4ELATEDSTRutitFES 0.92'-LICENSEETHEORIZESCAUSEISCORROS!0NDUE ! TO MOISTURE ENTRAINED IN SAND IN SMALL CAVliY AROUNDCIRCURFERENCE RANCHO SECO !!/21/06 PEES $URl!ER UFFER HEATER BAhK BU.NED QUT (1 C: 3 FOTENTIAL FOR OR ACTUAL EREAKC0hN 1% MMSE i FEATER BAhrS) NMEN HEATERS WERE EhER6tlED OR ACMINISTFAtlVE CONTROLE (E.6. TFAixlu
' ulTHOUT SUFFICIENT NATER. TN0 PRESSUR!!ER LEVEL PROCEDU8.ES, FROE*A'S1 lhDICATORSNERETAGEED037.THETHIRDLEVEL i lhD!CATOR HAD REFEREN: ELE 6DNLYFART!ALLYFAL
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