ML20199L647
| ML20199L647 | |
| Person / Time | |
|---|---|
| Site: | Monticello, Perry, Cooper, Turkey Point, Vermont Yankee, 05000000 |
| Issue date: | 06/26/1986 |
| From: | Holahan G Office of Nuclear Reactor Regulation |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| OREM-86-021, OREM-86-21, TAC-61787, NUDOCS 8607090515 | |
| Download: ML20199L647 (19) | |
Text
1 J1512 8 SE 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 JUNE 23, 1986 - MEETING 86-21 On June 23, 1986, an Operating Reactor Events meeting (86-21) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on June 16, 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.
M/
Gary M. Holahan, Director Operating Reactors Assessment Staff
Enclosures:
As Stated cc w/ Encl.:
See Next Page
. DISTRIBUTION Central. File,
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C. Heltemes R. Auluck T. Murley, Reg. I J. Zwolinski J. Nelson Grace, Reg. II D. Mcdonald J. Keppler, Reg. III H. Bailey R. D. Martin, Reg. IV L. Rubenstein J. B. Martin, Reg. V J. Stefano R. Starostecki, Reg. I W. Butler S. Ebneter, Reg. I V. Rooney 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 F. Rowsome D. Crutchfield G. Lainas V. Benaroya W. Regan D. Vassallo E. Jordan E. Rossi R. Baer E. Weiss R. Hernan S. Showe S. Rubin H. Alderman
ASI 2 8 IW6 ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (86-21)
JUNE 23, 1986 NAME DIVISION NAME DIVISION R. Vollmer NRR G. Klingler 0IE/DE G. Holahan NRR/0 RAS W. Swenson NRR/0 RAS W. Long NRR/BWD2 F. Rooney NRR/BWD2 R. Auluck NRR/BWD1 R. Pierson IE V. Hodge IE/EGCB A. Rubin NRR/DSR0 C. Ader OCM/TR M. Clausen OCM J. Clifford NRR S. Black NRR/PPAS E. Weinkam NRR/PWRA C. Miller NRR/PWRB V. Thomas IE/DEPER V. Benaroya NRR/PWRA D. Vassallo NRR/ DBL G. Murphy ORNL/NOAC H. Bailey IE/DEPER W. Butler NRR/ DBL M. Srinivasan NRR/ DBL L. Kintner NRR/ DBL W. Regan NRR/PWRB D. Crutchfield NRR/PWRB W. Paulson NRR/PWRB P. Koutanicezi IE/DEPER E. Weiss IE/DEPER S. Stern NRR/ DBL J. Stone IE/DUQAT J. Rosenthal NRR/DSR0 D. Notley NRR/BWPS R. Houston NRR/ DBL F. Schroeder NRR/PWRB F. Miraglia NRR/PWRB D. Allison IE/EAB E. Rossi NRR/PWRA K. Kniel NRR/DSR0 B. Sheron NRR/DSR0 T. Novak NRR/PWRA S. Rubin AE0D M. Chiramal AEOD D. Tarnoff NRR/0 RAS
ENCLOSURE 2 OPERATING REACTORS EVENTS BRIEFING 86-21 JUNE 23, 1986 COOPER NUCLEAR REACTOR COOLANT SYSTEM LEAKAGE STATION MONTICELLO INTERMEDIATE RANGE MONITOR SYSTEM IN0PERABLE TURKEY POINT POTENTIAL FAILURE OF ALL EMERGENCY UNITS 3 & 4 DIESEL GENERATORS PERRY FIRE IN CHARC0AL OFFGAS BEDS VERMONT YANKEE PROBLEMS WITH SCRAM SOLEN 0ID VALVES i
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COOPER NUCLEAR STATION - REACTOR COOLANT SYSTEM LEAKAGE JUNE 16, 1986 (W. LONG, NRR)
PROBLEM:
UNIDENTIFIED REACTOR COOLANT SYSTEM (RCS) LEAKAGE-SIGNIFICANCE:
POWER OPERATION WHILE DEINERTED WITH UNIDENTIFIED REACTOR COOLANT SYSTEM LEAKAGE CIRCUMSTANCES:
TECH, SPEC. LIMIT FOR UNIDENTIFIED RCS LEAKAGE IS 5 GPM.
ALSO LIMITED BY 1983 ORDER LIMITING LEAKAGE INCREASES TO 2 GPM OVER 24-HOUR PERIOD MONDAY, (6/16/86) - PLANT INITIALLY AT 90% POWER, UNIDENTIFIED LEAKAGE (12-4 P.M.) 1.78 GPM, 24 HR. AVG. = 1.01 GPM 6 P.M. - DRYWELL HUMIDITY, RADIATION, PRESSURE SHOWING SLIGHT INCREASE 8 P.M. - UNIDENTIFIED LEAKAGE CALCULATION SHOWS 3.69 GPM (4-HR. AVG.)
9:20 P.M. - LICENSEE COMMENCES SHUTDOWN AND BEGINS DEINERTING FOR DRYWELL ENTRY.
0XYGEN AT 4% AT 10:15 P.M.
TUESDAY, (6/17/86) 8 A.M. HR. NOTIFICATION TO NRC, ENTER LC0 ACTION STATEMENT REQUIRED BY 2 GPM INCREASE WITHIN 24 HOURS 12:29 P.M. - WITH PLANT AT 17% POWER PERSONNEL ENTER DRYWELL AND IDENTIFY LEAKAGE AS COMING FROM RECIRCULATION PUMP DISCHARGE VALVE PACKING.
(VALVE GLANDS MODIFIED LAST OUTAGE PER ANCHOR DARLING RECOMMENDATION - CHANGED FROM 3-STAGE TO 2-STAGE) START 24-HR CLOCK TO REINERT 6 P.M. - DRYWELL SECURED, AIRLOCK TESTED 6:30 P.M. - REINERTING COMMENCES, BEGIN POWER ASCENSION TO 30%
11 P.M. - COMMENCE SINGLE-LOOP OPERATION FOR STR0KE-TIME SURVEILLANCE ON VALVE 12 P.M. - RETURN TO 2-LOOP OPERATION, RESUME POWER ASCENSION WEDNESDAY, (6/18/86) 11:05 A.M. - REINERTED FOLLOWUP:
REGION IV WILL SEND TIA CONCERNING RELATIVE RISK OF OPERATIONS WHILE NOT INERTED
MONTICELLO - INTERMEDIATE RANGE MONITOR SYSTEM INOPERABLE JUNE 14, 1986 - (R, AULUCK, NRR)
PROBLEM:
LOSS OF INTERMEDIATE RANGE MONITOR (IRM) TRIP FUNCTION WITHOUT ANNUNCIATION SIGNIFICANCE:
SAFETY GRADE SYSTEM TRIP FUNCTIONS TERMINATE POWER INCREASES FOR FUEL BARRIER PROTECTION MAY HAVE GENERIC APPLICABILITY TO BWRs DISCUSSION:
PLANT IN SHUTDOWN CONDITION SINCE APRIL 30, 1986 FOR REFUELING AND MAINTENANCE SWITCHING 0F 480 VOLT BUSES RESULTED IN SUDDEN POWER SURGE WHICH BLEW THE FUSES ON 24V DC POWER SUPPLY REPLACED FUSES ON THE POSITIVE SIDE OF IRM CIRCUIT.
ALL ANNUNCIATORS CLEARED AND INDICATION RETURNED ON THE IRMs DURING PERIODIC FUNCTIONAL TESTS, CIRCUITS WOULD NOT GENERATE A REACTOR TRIP SIGNAL AND C. R. INSTRUMENTATION DID NOT RESPOND PROPERLY TO TESTING.
TESTS SHOWED THAT FUSES ON THE NEGATIVE SIDE OF EACH IRM CIRCUIT HAD ALSO BLOWN TESTS DEMONSTRATED NO IRM TRIP FUNCTION ACTUATION WITH NEGATIVE 24V DC POWER INTERRUPTED AND IRMs WOULD NOT RESPOND TO ACTUAL FLUX SIGNAL NOT A PROBLEM IN SRM OR PRM INSTRUMENTATION APPEARS TO BE AN IRM CIRCUIT DESIGN PROBLEM F0LLOW-UP:
CORRECTIVE ACTIONS ARE BEING EVALUATED BY THE LICENSEE REGION III SENDING TEAM TO REVIEW CORRECTIVE ACTIONS AND CONSIDER GENERIC IMPLICATIONS IE PLANNING TO ISSUE INFORMATION NOTICE GE TO FOLLOW THE GENERIC ASPECT
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9 TURKEY POINT UNITS 3 8 4 - POTENTIAL FAILURE OF ALL EMERGENCY DIESEL GENERATORS JUNE 10, 1986 (H. BAILEY, IE)
PROBLEM:
POTENTIAL FAILURE OF BOTH EDGs DUE TO MULTIPLE DESIGN DEFICIENCIES IN THE ELECTRICAL DISTRIBUTION SYSTEM SIGNIFICANCE:
l POTENTIAL STATION BLACK 0UT IN THE EVENT OF A LOSS OF 0FFSITE POWER DISCUSSION:
JUNE 10, 1986, FPal REPORTED RESULTS OF FAILURE MODES AND EFFECTS ANALYSIS IN ACCORDANCE WITH 10 CFR 21 MOTOR CONTROL CENTER "D" SWING BUS WITH NON-SAFETY RELATED STUB BUS HAS ONLY SINGLE BREAKER ISOLATION.
COULD RESULT IN OVERLOADING 0F BOTH EDGs.
SINGLE FAILURE OF 4A BATTERY OR 4A LOAD SEQUENCER RESULTS IN FAILURE OF 4A 4160V BUS.
EDG "B" AUXILIARIES POWERED FROM MCC 4A COULD RESULT IN FAILURE OF EDG "B" IN ABOUT 1 HOUR.
THIS RESULTS IN LOSS OF 3 0F 4 HIGH HEAD SI PUMP AND CONTROL ROOM AIR-CONDITIONING.
5 ADDITIONAL DEFICIENCIES IDENTIFIED THAT COULD CONTRIBUTE TO OVERLOADING OF BOTH EDGs.
MOST OF THESE DEFICIENCIES DO NOT REQUIRE A SINGLE FAILURE TO CONTRIBUTE TO OVERLOADING.
POST-TMI EMERGENCY OPERATING PROCEDURES REQUIRE ADDITIONAL CHARGING PUMP AND HIGH HEAD SI PUMP IN 1-30 AND 30-60 MIN.
LOADING INTERVALS RESPECTIVELY ACTUAL COOLING WATER PUMP (CCW AND ICW) LOADS HIGHER THAN EXPECTED.
SOME INCREASE DUE TO ONLY ONE TRAIN IN OPERATION.
EQ EVALUATIONS ASSUME CONTAINMENT COOLERS OPERATE LONGER THAN BEFORE TRANSFORMER LOSSES NOT ADEQUATELY ACCOUNTED FOR IN PREVIOUS EVALUATIONS AUT0-START OF NON-SAFETY LOADS WHEN SI RESET I
FOLLOWUP:
SWING BUSES DISABLED AND DEDICATED OPERATOR USED TO MANIPULATE BREAKERS EDG LOADS REDUCED, LOADING SEQUENCES CHANGED AND PLANT PROCEDURES REVISED REGION II HAS REVIEWED JUSTIFICATION FOR CONTINUED OPERATION OF UNIT 3.
UNIT 4 IN COLD SHUTDOWN.
NRR AND REGION II ARE REVIEWING JUSTIFICATION FOR OPERATION OF UNIT 4 AND FURTHER MODIFICATIONS ARE LIKELY PRIOR TO STARTUP 0F UNIT 4
TURKEY POINT - UNITS 3 & 4 4
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PERRY - FIRE IN CHARC0AL 0FFGAS BEDS JUNE 20, 1986 (E. WEISS, IE)
PROBLEM:
FIRE IN CONDENSER OFFGAS BEDS SIGNIFICANCE:
FIRE IN CHARC0AL BEDS WOULD CAUSE UNCONTROLLED RELEASE IF PLANT HAD OPERATED FOR EXTENDED PERIOD NO WATER DELUGE SYSTEM IS AVAILABLE TO STOP FIRE IN BEDS CIRCUMSTANCES:
TEST OF ROOM CHILLERS FOR RECHAR SYSTEM BEGAN PREVIOUS DAY PORTABLE ELECTRIC HEATERS PLACED IN FILTER VAULTS SUSTAINED ELEVATED TEMPERATURES IN BEDS CAUSES PLANT PERSONNEL TO CONCLUDE FIRE WAS PRESENT UNUSUAL EVENT DECLARED AT 11:45 A.M.
LICENSEE UTILIZED NITROGEN TO PURGE SYSTEM AND EXTINGUISH FIRE SEVERAL TRUCKLOADS OF NITROGEN USED THUS FAR MAX TEMPERATURES DROP SLOWLY DAY TIME TRAIN "A" TRAIN "B" 6/20 1345 1348'F 1146*F 1800 1108 1119 MIDNGHT 1040 1065 6/21 0900 948 973 1800 832 855 MIDNGHT 626 680 6/22 0900 164 548 MIDNGHT 82 420 6/23 0900 32 304 LICENSEE PLANS TO COOL BEDS UNTIL MAX TEMP IS LESS THAN 150*F FOLLOWUP:
REGIONAL REACTIVE RESPONSE TIA PLANNED FOR LONGER TERM NRR FOLLOWUP
VERMONT YANKEE - PROBLEMS WITH SCRAM S0LEN0ID VALVES JUNE 14, 1986 (E. WEISS, IE)
PROBLEM:
1 R0D FAILED TO MOVE AND 5 RODS HESITATED 5 SECONDS BEFORE MOVING BECAUSE OF PROBLEMS WITH SCRAM S0LEN0 IDS SIGNIFICANCE:
PLANT CRITICAL WITH INOPERABLE RODS MANUFACTURING DEFECTS IN REBUILD KITS MAY AFFECT OTHER PLANTS INADEQUATE POST-MAINTENANCE TESTING OF SCRAM S0LEN0 IDS CIRCUMSTANCES:
ALL SCRAM S0LEN0 IDS HAD BEEN REBUILT FOR NORMAL PREVENTATIVE MAINTENANCE (ONCE EVERY 5 YEARS)
SCRAM TIME TESTS PERFORMED FOLLOWING A SYSTEM HYDR 0 AFTER IN-SEQUENCE CRITICAL TEST AND S/D MARGIN TESTS FOLLOWING DEFICIENCIES WERE NOTED:
R0D CONDITION CAUSE C6-23 N0 SCRAM SPRING ON PLUNGER OUT OF PLACE 38-23 5 SEC DELAY DIAPHRAGM INSTALLED BACKWARDS 10-23 DIMENSIONS OF CONE ON PLUNGER 18-11 26-23 22-35 LICENSEE PLANS TO SAMPLE PARTS KITS FOR BAD SPRINGS FOLLOWUP:
ASCO MAY FILE PART 21 IE INFORMATION NOTICE IS UNDER DEVELOPMENT
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REACTOR SCRAM
SUMMARY
WEEK ENDING 06/22/86 I.
PLANT SPECIFIC DATA DATE SITE UNIT POWER RPS CAUSE COMPLI-YTD CATIONS TOTAL 06/17/86 HADDAM NECK 1
100 M EQUIP /MFW HTR NO 3
06/17/86 SURRY 2
28 M EQUIP /MFW VLV NO 3
06/17/86 PALO VERDE 1
100 A PERSONNEL / PROC NO 5
06/18/86 NINE MILE POINT 1
OA PERSONNEL NO 1
06/18/86 BRUNSWICK 2
54 A EQUIP /MFW VLV NO 1
06/19/86 HADDAM NECK 1
OA EQUIP / INSTR NO 4
1 06/19/86 TROJAN 1
25 A PERSONNEL / TEST NO 2
06/19/86 NINE MILE POINT 1
OA EQUIP / ELECT NO 2
06/19/86 SAN ONOFRE 2
83 A EQUIP /ELEC NO 4
06/20/86 ROBINSON 2
98 A EQUIP /ELEC NO 7
06/21/86 CALLAWAY 1
99 A UNKNOWN NO 4
06/22/96 HADDAM NECK 1
10 A PERSONNEL /MAINT NO 5
06/22/86 LACROSSE
'l 99 A EQUIP / INSTR YES 7
SUMMARY
OF COMPLICATIONS
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SITE UNIT COMPLICATIONS LACROSSE 1 INSTRUMENT LINE BREAK VESSEL LEVEL READINGS CONFLICTING t
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II. COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES SCRAMS FOR WEEK ENDING 06/22/86 SCRAM CAUSE POWER NUMBER 1986
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1985 OF WEEKLY WEEKLY SCRAMS (5)
AVERAGE AVERAGE YTD (3) (4)
- POWER >15%
EQUIP. RELATED
>15%
6 4.2 5.4 (68%)
PERS. RELATED(6) >15%
2 2.2 2.0 (25%)
OTHER(7)
>15%
1 0.2 0.6 ( 7%)
- Subtotal **
9 6.6 8.0
- POWER <15%
EQUIP. RELATED
<15%
2 1.5 1.3 (54%)
PERS. RELATED
<15%
2 1.2 0.9 (38%)
OTHER
<15%
0 0.1 0.2 ( 8%)
- Subtotal **
4 2.8 2.4
- Total ***
13 9.4 10.4 MANUAL VS AUTO SCRAMS TYPE NUMBER 1986 1985 OF WEEKLY WEEKLY SCRAMS AVERAGE AVERAGE YTD MANUAL SCRAMS 2
0.0 1.0 AUTOMATIC SCRAMS 11 8.6 9.4 2
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NOTES 1.
PLANT SPECIFIC DATA BASED ON INITIAL REVIEW 0F 50.72 REPORTS FOR THE WEEK OF INTEREST.
PERIOD IS MIDNIGHT SUN. THROUGH MIDNIGHT SUN. 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.
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 MANUAL UNPLANNED REACTOR TRIPS AT 93 REACTORS (HOLDING FULL POWER LICENSES).
THIS YlELDS AN AVERAGE RATE OF 5.8 TRIPS PER j
REACTOR PER YEAR AND AN AVERAGE RATE OF 10.4 TRIPS PER WEEK FOR ALL REACTORS.
5.
BASED ON 95 REACTORS HOLDING A FULL POWER LICENSE'.
6.
PERSONNEL RELATED PROBLEMS I.NCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.
7.
"0THER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.
l l
o ENCLOSURE 3 6e 0FERATINS REA; TORS EVENTS MEETINS FOLL0btP ITEMS AS CF MEETING E6-21 04 JUNE 23, 1926 (IN ASCENDINS MEETINS DATE, NSSS VENDOR, FACILITY ORDER)
MEETING FACILITY RESFCNSIELE TASK DESCRIFil0N SCHEDULE CLOSEDDATE
' COMMENTS NWKR/
NiSS VENDOR /-
[IVIE!0N!
COMPLET.
BY DOCUMENT, PEETINI EVENT IE!CRIP, INDIVIDUAL DATE(S)
MEETING,ETC.
DATE Bi-10 CYSTE9 CREEK N:.c. /HCUETON W RESOLVE THE QUESTION OF THE 06/30/06 OPEN
//
FOLLCWUP ACT10N TO 03/31/66 EE / LEVEL
/
ACCEPTABILITY OF ELIND SWITCHES
/ /
EE INCORFORATED IN EWITCHSETFDINT AND DELETION Or DAILY CHANNEL
/ /
REVIEW OF JUNE IEIFT CHECK 1,1926 EVENT AT LASSALLE E6-10 15A!EWCDD 1 N'iR INOCNAN V REQUEST FEFCRT OF EVENT FROM 06/30/26 CLOSED 06/20/26 03/31/B6 W / WATER
'ICENSEE 05/30156 REPORT HASER IN MAIN 05/01/86 456/26-007-01 STEAM Lit!
85-13 RIVER BEND IE IJ0EDAN E CETEFMINE HEED FOR VENDCP 06/25/E6 CLOSED 06/23/96 04/21/96 W / QA CCNCERNS
/
INSFECTICN 05/30/86 MD NEED FOR INVOLVINS
/ /
VENDOR AFCHITECT INSPECTION ENSINEER 85-21 VERMONT YANKEE NRR /HOLAHAN G.
DETERMINE STATUS AND 08/20/26 CPEN
//
05/23/26 EE / FROPLEMS
/
EFFECTIVENESS OF STAFF AND
/ /
WITH SCRAM LICENSEE Atil0N ON
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SOLEN 010 VALVES POST-MAINTENANCE TESTINS (6L 83-28). DEVELOP FECOMMENDATIONS FOR FURTHER ACTION 86-21 TUFKEY POINT NRR / ROSA F.
CONSIDER REVIEWINS ELECTRICAL 08/30/86 OPEN
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06/23/86 W / PDTENTIAL
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SYSTEM OF PLANT WITH SIMILAR
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FAILUPE OF ALL SWINS BUS DESIGN
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EMERSENCY DIESEL SENEPATCRS l
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