ML20128K647
| ML20128K647 | |
| Person / Time | |
|---|---|
| Issue date: | 02/09/1993 |
| From: | Chaffee A Office of Nuclear Reactor Regulation |
| To: | Grimes B Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9302180233 | |
| Download: ML20128K647 (15) | |
Text
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FEB 0 91993 MEMORA!1DUM FOR:
Brian K. Grimos, Director Division of Operating Reactor Support FROM:
Alfred E. Chaffee, Chief Events Assessment Branch Division of Operating Reactor Support
SUBJECT:
OPERATIllG REACTORS EVEllTS DRIEFING FEBRUARY 3, 1993 - BRIEFIl1G 93-04 On February 3, 1993, we conducted an Operating Reactors Events Briefing (93-04) to inform senior managers from officos of the Commission, OE, EDO, ACRS, SECY, RES, AEOD, llRR, and regional officos of selected events that occurred since our last briefing on January 27, 1993.
Attachment i lists the attendocs. presents the significant clomonts of the discussed events. contains reactor scram statistics for the w'eok onding January 31, 1993.
One significant event was identified for input into the 11RC performance indicator program (Attachment 4).
/5/
Alfred E.
Chaffee, Chlof Events Assessment Branch Division of Operating Reactor Support Attachments:
As stated DISTRIBUTIOll:
Centra 11Filess cc w/ attachments:
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ORTRAliS.KAG (G:KAG) 93021eo233 930209
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Cet T. Muricy, NRR (12G18)
A. Dromerick, (PDI-4) f F. Miraglia, NRR (12G18)
J. Stolz, (PDI-4) l F. Gillespie, NRR (12G18)
N. Conicella, (PDI-1) j J.
Partlow,-liRR (12G18)
R. Capra, (PDI-1)
S. Varga, NRR (14E4) l J.
Calvo, 11RR (14A4) l G., Lainas, llRR (14H3)
J.
Roe, NRR (13E4) i J.
Zwolinski, 11RR (13H04)
M. Virgilio, NRR (13E4)
W. Russell, NRR (12G18)
J. Richardson, llRR (7D26)
A. Thadani, llRR (8E2)
S. Rosenborg, llRR (10E4) j C.
Rossi, llRR (9A2)
B. Boger, 11RR (10H3) i P. Congal, flRR (10E2)
D.
Crutchfield, NRR (11H21)
W.
Travers, llRR (11B19)
D. Coe, ACRS (P-315)
E. Jordan, AEOD (Mil-3701)
.i T. !!ovak, AEOD (Mll-9112)
L. Spessard, AEOD'(M11-3701)
K. Brockman, AEOD (Mil-3206)
S. Rubin,'AEOD (Mil-5219)
M. Harper, AEOD (M11-9112)
J. Grant, EDO (17G21)
R.
!!ewlin, GPA (2GS)
E.
A. Bates, SECY1(16G15)'
G.
Ramm1'ing, OCM (16G15)
T. Martin, Region I W. Kane, Region I
- c. Hohl, Region I
~S.
Ebneter, Region II E. Merschoff,-Region II B.. Davis, Region III E.
Greenman, Region-III J. Milhoan, Region IV B.
Beach, Region IV J.B. Martin, Region V K. Perkins,-Region V j
bcc Mr. Sam Newton Manager Events Analysis Department Institute of 11uclear Power. Operations 1100 circle 75 Parkway, Suite'1500
-Atlanta,: GA 30339-3064~
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I ATTACllMEllT 1
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LIST OF ATTEliDEES OPERATI!1G REACTORS EVEllTS FULL BRIETI!1G (93-04)
FEBRUARY 3, 3993 i
11AME QTJ1CI
]!! mig OPFICl; i
B. GRIMES IIRR L. BETTE!111AUSEll llRR A. CllAFFEC 11RR J.
STOLZ llRR J.
CARTER 11RR R. GALLO 11RR C.
ORSI!11
.11RR T. MURLEY 11RR K. GRAY 11RR F. MIRAGLIA flRR G.
MARCUS flRR S.
VARGA flRR R. DEllllIG llRR J.
BALL llRR C.
DEARDSLEE IIRR -
J. CALVO llRR -
E. GOODWILL 11RR R. JollES tlRR J.
ZIMMERMA!1 liRR J. SCARDOROUGli OCM/KR R. II E Rll All flRR V. MCCREE OEDO G.
WEST, JR.
lIRR W. TROSKOSKI OE M. PollIDA liRR D. COE ACRS R.
CAPRA liRR K. IIART SECY M. WILLIAMS 11RR W. MI!111ERS RES.
P. LOESER l4RR V.
BEllAROYA AEOD TELEPilollE ATTE!1DAllCE (AT ROLL CALL)
Renions Resident' Inspectors Region I l
Region III Region IV Region V I
AIT Team Loadern Misc.
James E. Beall (Oyster Crook) a
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ATTACHMENT 2 OPERATING REACTORS EVENTS BRIEFING 93-04 LOCATION:
10 Bil, WHITE FLINT WEDNESDAY, FEBRUARY 3, 1993, 11:00 A.M.
0YSTER CREEK DEGRADED CORE COOLING WITH SHUTDOWN COOLING SYSTEM.IN OPERATION (AIT)
INDIAN POINT, UNIT 3 ATWS MITIGATION SYSTEM ACTUATI0h CIRCUITRY (AMSAC)
FAILURE PRESENTED BY:
EVENTS ASSESSMENT BRANCH DIVISION OF OPERATING REACTOR SUPPORT, NRR i
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93-04 OYSTER CREEK DEGRADED CORE COOLING WITH SHUTDOWN COOLING SYSTEM IN OPERATION (AIT)
JANUARY 25, 1993 P_ROBLEM WHILE SHUTDOWN AND RUNNIllG A TEST, A SPECIAL OPERATING CONFIGURATION LED TO AN UNKNOWN DEGRADATION OF COOLANT CIRCULATION THROUGH THE CORE AND INCREASED CORE TEMPERATURES.
CAUSE FAILURE TO PROPERLY TRAt1 SLATE REQUIREMENTS IN TECHNICAL ANALYSIS INTO A TEMPORARY PROCEDURE.
SAEETY SI_GRIEIIARCE INADEQUATE PROCEDURES AND MONITORING 0F REACTOR VESSEL TEMPERATURES TO PROMPTLY ALERT THE OPERATORS OF AN INCREASE IN TEMPERATURE.
THE OPERATING FLOW THAT WAS REQUIRED FOR THE SPECIAL CONFIGURATION WAS NOT ESTABLISHED, AS A RESULT, THE UNEXPECTED DECREASE IN CORE COOLING WENT UNDETECTED FOR ABOUT 2 DAYS.
DISIUSS10B e
THE REACTOR HEAD WAS IN PLACE AND BOLTED.
CONTACTS:
J. CARTER, NRR/ DORS AIT:
YES_
J. BEALL, RI SIGEVENT:
TBA_
REFERENCE:
10 CFR 50.72 #24942 i
0YSTER CREEK 93-04 e
DECAY HEAT WAS BEING REMOVED VIA TWO SHUTDOWN COOLING LOOPS.
REACTOR VESSEL WATER LEVEL WAS ABOVE 185" THE TOTAL FLOW RATE THROUGH THE LOOPS WAS ABOUT 3100 GPM e
A PROCEDURE TO PERMIT MSIV LEAK TESTING WAS INITIATED.
TWO SHUTDOWN COOLING PUMPS WERE TO BE OPERATING REACTOR WATER LEVEL WAS REDUCED TO 165" TWO SHUTDOWN COOLING PUMPS-WERE T0-DELIVER 6000 GPM ONLY ABOUT 3200 GPM EXISTED ONE RECIRCULATION LOOP ("A") HAD BOTH INLET AND OUTLET VALVES OPEN A TECHNICAL SPECIFICATION REQUIREMENT o
SHUTDOWN COOLING SYSTEM FLOW GOING THROUGH LOOP "A" BYPASSES CORE, AND REDUCES FLOW TO THE CORE.
FLOW DELIVERED BY THE SHUTDOWN COOLING LOOPS-WAS-INADEQUATE TO SUPPLY BOTH THE REQUIRED FLOW TO THE CORE (UP THROUGH THE CORE AND OVER THE-CC... SHROUD) AND THE COMMENSURATE FLOW TO LOOP'"A".
CONDITION ESTABLISHED 01/24/93 010200 HRS e
OPERATORS BEGAN TO INCREASE SYSTEM PRESSURE FOR' TEST 01/25/93 0 0124 HRS.
PRESSURIZATION T0. ABOUT 42 T0-45 PSIG ACHIEVED' BY AIR COMPRESSOR e LTEST COMPLETED AND BEGAN VENTING AT 1630 HRS.
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s 0YSTER CREEK 93-04 e
REACTOR VESSEL HEAD WAS IDENTIFIED AS BEING AB0VE 212*F.
DISCOVERED 01/25/93 0 1800 HRS e
RECOGNITION iHAT ADEQUATE CIRCULATION THROUGH THE CORE HAD NOT BEEN MAINTAINED.
ALL THREE SHUTDOWN COOLING PUMPS WERE PLACED IN SERVICE.
FLOW RATE WAS INCREASED TO 7200 GPM e
REACTOR VESSEL WATER LEVEL WAS INCREASED TO AB0VE 185".
WATER LEVEL IS AB0VE TOP 0F SHROUD e
SUBSTANTIAL FLOW RATE THROUGH THE CORE IS ESTABLISHED.
IHLET TEMPERATURE PEAKED AT ABOUT 170*F, UP FROM 120 F e
A RECIRCULATION PUMP WAS STARTED AND LOOP FLOW WAS ESTABLISHED 0 2023 HRS.
LICENSEE REPORTED EVENT TO OPERATIONS CENTER 01/25/93 0 2207 HRS.
E01LORllE e
AIT WAS ASSEMBLED 01/26/93.
AN INFORMATION NOTICE MAY BE ISSUED.
BRIEflNG 93-04 e
0YSTER CREEK steamflow 4
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Figure 4-1 : SCS flow with recirculation loop open I
93-04 INDIAN POINT, UNIT 3 ATWS MITIGATION SYSTEM ACTUATION CIRCUITRY (AMSAC) FAILURE DECEMBER 31, 1992 P_R0BLEM 1
ATWS MITIGATION SYSTEM ACTUATION CIRCUITRY (AMSAC) LOGIC FAILED TO OPERATE DUE T0 QUALITY ASSURANCE DEFICIENCIES INVOLVING SOFTWARE.
CAUSE LACK 0F CONFIGURATION MANAGEMENT AND INADEQUATE RE-TEST PROCEDURES.
SAEETY SIGNIFICANCE AMSAC LOGIC DEFICIENCY WOULD HAVE PREVENTED THE AUTOMATIC INITIATION OF AUXILIARY FEEDWATER (AFW) DURING AN ATWS EVENT.
S.XSTEM DESCRIPTION AMSAC BECOMES ACTIVE AT 40% POWER.
INITIATES AN ACTUATION SIGNAL WHEN 3 0F 4 CHANNELS INDICATE 21% OR LESS MAIN FEEDWATER FLOW FOR A PREDETERMINED TIME DELAY.
TIME DELAY VARIES FROM 300 SEC AT 40% POWER TO 25 SEC e
AT 100% POWER.
ACTUATION SIGNAL IS LOCKED-IN FOR 40 SEC.
CONTACT:
C. ORSINI, NRR/DDRS AIT:
NO
REFERENCE:
10 CFR 50.72 #24952 SIGEVENT:
TBD_
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INDIAN POINT, 93-04 UNIT 3 e
MOTOR DRIVEN AFW AUTO-START 28 SEC AFTER ACTUATION.
DISfUSSION e
AMSAC CONFIGURATION IS MAINTAINED ON A HARD DRIVE, NOT NEEDED ONCE THE SYSTEM IS POWERED UP BECAUSE IT IS LOADED INTO MEMORY DURING BOOT-UP.
DURING SURVEILLANCE ON MAY 12, 1992, THE HARD DISC FAILED TO REBOOT.
(THIS WAS DURING A REFUELING OUTAGE WHICH ENDED ON AUGUST 3, 1992.)
NYPA (NEW YORK POWER AUTHORITY) CALLED THE VENDOR (FOXBOR0) FOR ASSISTANCE, ON JULY 8, 1992, VENDOR INSTALLED HARD DRIVE AND e
PERFORMED SURVEILLANCE.
NYPA HAD FAILED TO MAINTAIN BACK-UP CONFIGURATION FILES ON FLOPPY DISC PREVIOUSLY PROVIDED BY VENDOR.
TECHNICIAH ATTEMPTED TO REBUILD THE CONFIGURATION FILES.
GL 85-06, " QUALITY ASSURANCE GUIDANCE FOR ATWS EQUIPMENT THAT IS NOT SAFETY RELATED," RECOMMENDS THE APPLICATION OF QUALITY CONTROLS COMPARABLE TO SELECTED PORTIONS OF THEIR APPENDIX B PROGRAM.
AMSAC FAILED. SURVEILLANCE DUE TO TIME DELAY NOT WORKING.
VENDOR MODIFIED PROGRAM.
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LINDIAN POINT, 93-04
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SURVEILLANCE TEST PERFORMED SATISFACTORILY, EXCEPT SYSTEM REBOOT CAUSED REACTOR TRIP SIGNAL, VENDOR MODIFIED. PROGRAM AGAIN, INCLUDING CHANGE OF THE TIME DELAY BLOCK IN LOGIC.
SURVEILLANCE NOT RE-PERFORMED, ONLY REBOOT CHECK WHICH PERFORMED CORRECTLY.
e ON DECEMBER 31, 1992 DURING-ROUTINE SURVEILLANCE TESTING, THE TIME DELAY WAS FOUND INOPERABLE.
AUT0-START OF AFW IN0PERABLE FROM JULY 8,1992 TO JANUARY 12, 1993 (STARTUP IN AUGUST).
ALL-0THER REQUIRED ALARMS AND' AUTOMATIC _ FUNCTIONS, TRIPPING MAIN TURBINE, ISOLATING STEAM GENERATOR BLOWDOWN-AND SAMPLE VALVES, WOULDLHAVEcFUNCTIONED.
FOLLOWUP _
REGION T0 DETERMINE NEED FOR ENFORCEMENT ACTION; INFORMATION NOTICE ON SOFTWARE ISSUES 1IN PREPARATION.-
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I'RIrr JTy; 93_o1 If!D IAT F'O i!!T !!*il i 3 T URBINE FtRST STA6E PRESSURE LOW FEEDWATER FLOW LOOP 1 LOOPZ LOOP 3 LOOP 4 1
I40%
I 40 %
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UU UU 3/4 180-420 SEC l
1 '
y TIME DELAY OM 300 - 25 SEC.
U TIME DELAY ON M
C-20 PER MtSSIVE DE-EMER6tZING EMERG1ZlM6 FOR I
U' I POWER LEVELS OF 40 */o TO 100 %
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MAMUAL RESET i<6r>
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3 n4tTATE AUXtt.1 ARY FEEDWATEft FLOW l
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ATTACHMENT 3-ttAC10R SCRAM seporting Period: 01/25/93 to 01/31/93 YTD YTD ABOVE SELOW YTD cal [
PLANT & UNIT Eqb_Q M
[A2 COMPLicAfl0Nl ,1}} }}} Ipf,Al 01/26/93 LAsALLt 1 20 SM Melntenance Error. No 1 0 1 01/26/93 k!NE MILT Polwi 1 100 SA maintenance Error WO 1 0 1 01/26/93 Oc0Ntt 3 100 SA Melntenance Error WO 1 0 1 01/28/93 sAttM 2 100 SM twirrent f ailure WO 1 1 2 01/28/93 KtWAUWit i 100 SA Equipment f ailure WO 1 0 1 01/29/93 OUAD Clfits 2 100 $A Melntenance trror NO 2 0 2 01/29/93 KtWAUNtt i 5 SA operating Error No 1 1 2 01/29/93 OCONtt 1 0 SA Operating Error No 1 1 2 01/30/93 stAVER VALLEY 2 92 SA twipment f ailure NO 1 0 1 01/30/93 PALO VERDE 1 96 $M Melntenance Error NO 1 0 1 01/30/93 DIABLO tsWYOW 2 100 SA Operating Error NO 1 0 1 NOTES PLAN 1 SPECIFIC DATA BASED ON INITIAL REVIEW OF 50,72 REPORTS FOR PERIOD OF INTEREST. SCRAMS ARE DEFINED AS REACTOR PROTECTION SYSTEM ACTUATIONS WHICH RESULT IN R00 MOTION, AND EXCLUDE THOSE FROM PLANNEO TESTS OR AS PART OF PLANNED SHUTDOWN IN ACCORDANCE WITH A PLANT PROCEDURE.- COMPLICATIONS: REC 0VERY COMPLICATED BY EQUIPMENT FAILURES OR_ PERSONNEL ERRORS UNRELATED TO CAUSE OF SCRAM, SA - SCRAM AUTOMATIC; SM - SCRAM MANUAL Q1AS SCRAM DATA Manual and Automatic Scrams for 1987 ------------------ 435 Manual and Automatic Scrams for 1988 ----------- ------ 291 Manual and Automatic Scrams for 1989 ------------------ - 252 Manual and Automat ic Scrams for -1990 ------------------ 226 Manual and Automatic Scrams for 1991 -------------------206 Manual and Automatic Scrams for' 1992 ------------------ 212 Manual and Automatic Scrams for '1993 --(YTD 01/31/93)-- 025 hote: Year To Date (YTD) Totals Include Fvents Within The calender Year Indicated By The End Date of the speelfled Reporting Perlo _ ITs 10 Page:1 02/08/93 s
COMPAR150N OF WEEKLY SCRAM IfkillTICS W11H INDUSTRY AVERACES PER100 ENDING 01/25/93 to 01/31/93 WUMBER 1993 1992* 1991* 1990* 1989* OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAM CAU$E SCRAMS AVERACE AVERACE AVERACE AVE RACE AVE R ACE (YTD) POWER CREA1ER THAN OR EQUAL 1015% EQUlPMEN1 FAILURE
- 3 2.7 2.6 2.9 3.4 3.1 CESICN/ INSTALLATION ERROR
- 0 0.2 OPERATING ERROR
- 1 0.5 0.8 0.6 0.5 1.0 MAINTEhANCE ERROR
- 5 1.4 EXTERNAL
- 0 0.2 OTHER*
0 0.0 0.1 SWtotat 9 5.0 3.4 3.5 3.9 4.2 POWER LE$$ THAN 151 EQUIPMENT FAILURE' 0 0.2 0.4 0.3 0.4 0.3 OESIGN/thSTALLAT10N ERROR
- O
'.0 OPERAfikG ERROR
- 2 0.5 0.2 0.2 0.1 0.3 MAlWTEhANCE ERROR
- 0 0.0 EXTERNAL
- O 0.0 OTHER*
0 0.0 Subtotal 2 0.7 0.6 0.5 0.5 0.6 TOTAL 11 5.7 4.0 4.0 4.4 4.8 1993 1992 1991 1990 1989 NO OF WEEKLY WEEKLY WEEKLY WEEKLY WEEK 1.Y scram int SCRAMS AvtRACE AVERACE AVERACE AVERAGE AVERACE (YTD) TOTAL AUTOMAftC SCRAM 5-8 4.3 3.0 3.3 3.2 3.9 TOTAL MANUAL SCRAMS 3 1.4 1.0 0.7 1.2 0.9
- Detailedbreakdownnotindatabasefor19(andearlier EXTERNAL cause included in EQUlPMENT FAILURE MAINTENANCE ERROR and OE51CN/lNSTALLAT10N ERROR causes included in OPERATING ERROR
- OTHER cause included in EQUIPMENT FAILURE 1991 and 1990 EXTERNAL CAUSE INCLUDES SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (EG LIGHTNING, LOSS OF 0FFSITE POWER)
i il 1! I 39 3 / 0/20 4 7 3 T 3 0 i e 0 0 f 6 E 2 3 9 9 4 E
- H R
R C F F E E A T TA R RE T T C T N I E D T S E M E N S R E 0 3 P B 1 9/3 G 2 N / 1 6 6 F 0 1 0 1 2 S a I 9 9 R T B N e f L t E a uA E C V D YI E t E R m u T e F C t o OE s T e L y N s E E S o R A UN g l O n T I i C C A T I N Z l R o F 3 GR o O I 9 N E C P I V7 d E / N 7 R ( s e R 2 R G e/ C C N ! a E USC t 1 R I t k E R S l 0 a A R EE e O B D = C CD R T MM y A I t F S n RCE t C e E T e e 4 I T vt C P DS f a N E T N Y a D D S OA S S N A 1 t I L u e T o g P R E a OS e C P s T N R o MA ST O M l O C F 1 T R I N 4 O TC .E UF D F R S WF O SE G X EI L A U O T O F 1 S A R P-R R E E P S T i E R e MWI S N p E OR DO O P y T PT ER C T S K C G T T GC C N N t S S NI T C I n OI PL I e N LS L F v O U8A O D T E PA2 J E A N MC W Y I O L ,&A F T R Y I P M I R T DA P U UEF A IL I E E A DE2S T B Q T EP sW A N O CF I G R E T A R DS E N NT EU k D E EE B L I W V C V R E UI O .F L R T ) S Y F E DCT E E L O D - A A R S R E UD U N T OR ( R L U O N T I I O I E 0 .R H A I e MT F T T f DF P R V I E .E 1 ,1 E E R V ) F S L.- C D T F . D T GS R S A A I X AI 4 C P E M SR UON 1 C I ( T A LU $ E D R 9 5 8 7 0 6 8 0 3 2 2 1 2 9 9 / / 4 1 6 2 0 / / 3 7 0 0 T I 2 NU E N O 1 2 T 1 T S N N L A O L S T P Z I E t I M .}}