ML19312D125
| ML19312D125 | |
| Person / Time | |
|---|---|
| Issue date: | 02/13/1980 |
| From: | Souder J NRC OFFICE OF ADMINISTRATION (ADM) |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NUDOCS 8003210131 | |
| Download: ML19312D125 (35) | |
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UNITC STATES tt NUCLEAR REGULATORY COMMis$lON :
p
. _j WASHINGTON, D. C. M
- POWER REACTOR - BIWEEKLY 4
/
TA P
II phi REPORTA83LE OCCURRENCE-COMPUTER PRINT 0UT~ FOLDER
'A-IS-80 NOTE T0:
Librarians of all Local Public Document-Rooms /
Regional Public Infonnation Offices /and Directors of the Office of Inspection and Enforcement,
. Regional' 0ffices, Region I, II III, IV, and V.-
Please file the' attached computer.. printout concerning
" Reportable Occurrence Reports" recejved jfrom all poyer T
reactor facilities-for the' period 1AJ31; 79 thru I J 13, la I
I u
o If you have any questions,- please feel free to wrjte or call (301).492-7536.-
N bna L. Sou er, Chief thcal Public Document Room Branch Division of Rules & Records Office of Administration V
Enclosure:
_ Computer Printout'for all Reportable Occurrence Reports received from reactor facilities iNhlY7h
/0$7hb ru pages _ '
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PAGE'1-LER DUTPUT ON REPORTS' RECEIVED-FROM 12/31/79 ~ THRU 01/13/80 1"'
FEB 07s-19801
.0UTPUT SORTED:BY FACILITY AND EVENT DATE' FACILITY / SYSTEM /1 DOCKET-MO./ EVENT DATE/:.
EVENT ~ DESCRIPTION /?
COMPONENT / COMPONENT SUBCODE/1 CAUSE/CAUSE SUBCODE/',
LER NO./=
. REPORT DATE/
-CAUSE DESCRIPTION'
. CONTROL NO.-REPORT TYPE
-COMPONENT MANUFACTURERf DURING PLANT HEATUP TO'HditSHdTDdWN CONDITIONS, THE OPERATIONAL' TEST!
~
WAS~NOT P 05000313-111979 1106.06) OF-THE TURBINE DRIVEN EMERGENCY FEEDWATER' PUMP:(P7 ARKANSAS-1 1
79-022/03L-0"1121879
- FEEDWATER. SYSTEMS + CONTROLS ERFORMED.. HOWEVER, ISFACTORILY WHILE IN COLD SHUTDOWN CONDITIONS ON, 11-12-79.
ON-11-20-791' 027712~ ' 30-DAY-4' LPUMPS-
- THERE HAVE'
-DTHER:
'THE P7A EMERGENCY FEEDWATER PUMP WAS SATISFACTORILY TESTED.
DEFECTIVE PROCEDURES
'BEEN HO SIMILAR OCCURRENCES. REPORTABLE PER.T.S.'6.12.3.2(B).
NOT~ APPLICABLE 1106.06-DUE TO A-
' ITEM NOT APPLICABLE.
.THE P7A' EMERGENCY.FEEDWATER PUMP WAS NOT TESTED PER OP SCHEDULING MISTAKE WHICH WAS NOT COVERED BY THE STARTUP PROCED ANY FUTURE SIMIL AR OCCURR'WAS ADDED TO THE ST ETHEREFORE,'A STEP 2.
ENCES.
DURING' MODE 2 OPERATION THE CONTAINMENT BUILDING SUMP LEVEL IND THE REDUNDANT LEVEL INDIC'
- 05000368
112879 ARKANSAS 2 79-097/03L 122879 LI-5646-2) WAS. DISCOVERED TO BE READING 0.0%.-THIS OCCURRENCE.TS.SIM SAFETY RELATED DISPLAY INSTR-
. INSTRUMENTATION + CONTROLS-027806 30-DAY ATOR-(2LI-5646-1) REMAINED OPERABLE 50-368/79-079.
REPORTABLE PER T.S. v.9.1.9.5..
POWER SUPPLY
-COMPONENT FAILURE ELECTRICAL-
-POWER SUPPL.
OTHERu
. INVESTIGATION' REVEALED A FAULTY-CONVERT 0R AND POWER SUPPLY.
THE UNIT WAS CALIBRATED AMD RETURMED:TO Y-AND CONVERT 0R WERE REPLACED.
SERVICE WITHIN 48. HOURS MEETING REQUIREMENTS OF ACTION -STATEM A-DPERATION, THE CHANNEL "B" PRES $URIZER PRESSURE VARIABLE S:
.DURING MODE 1
-ETPOINT OSCILLATED BETWEEN O AND 1000' PSIA CAUSING A-LOW 05000368 120779
- ARKANSAS SSURE TRIP ON CHANNEL."B"..~THE AFFECTED. CHANNEL WAS BYPASSED AND
-REACTOR TRIP SYSTEMS 79-094/03L-0 010480 HER THREE CHANNELS REMAINED OPERATIONAL. THIS OCCURRENCE IS SIMIL INSTRUMENTATION + CONTROLS 027807 30-DAY
~
~
COMPUTATION MODULE
'LER 50-368/79-023.
REPORTABLE PER T.S. 6.9.1.9.5.
2
-COMPONENT FAILURE ELECTRONIC.
ELECTRO-MECHANICS INVESTIGATION AND CHECK 0UT' REVEALED-THE FAILURE WAS'DUE TO A POWER THE CARD WAS REPLACED AND:THE CHANNEL W Y FAILURE OH THE BISTABLE CARD.
AS TESTED AHD-RETURNED TO SERVICE WITHIN TWO HOURS PER T.S. TABLE.3.3 FUNCTIONAL UNIT 5 ACTION STATEMENT 2.A.
DURING MODE 1: 0PERATION, BATTERY CHARGER 2D32 WAS DISCOVERED TO HAVE A L ARKANSAS-2 05000368 121179 OW OUTPUT VOLTAGE,' RENDERING THE "B" DC BUS INDPERABLE PER T.S. 3.8.2.3.
DC ONSITE POWER SYS + CONTR0*.S 79-095/03L-0 010480 BATTERY CHARGER 2D32 WAS RETURNED TOL THE "A" DC BUS REMAINED OPERABLE.
THIS.
BATTERIES + CHARGERS 027808 30-DAY SERVICE'WITHIN'ONE HOUR MEETING REQUIREMENTS OF'T.S. 3.8.2.3(8).
1 SUBCOM?ONENT NOT APPLICABLE OCCURREHCE IS SIMILAR TO LER 50-368/79-065.
REPORTABLE PER T.S'.
6.9.1.9'
)
COMPONENT FAILURE
.B.
~~
l' ELECTRICAL INVESTIGATION REVEALED THE CHARGER AC BREAKER TRIPPED DUE TO'A POWER' CONVERSION PRODUCTS,'INC URGE WHILE READJUSTING OUTPUT-VOLTAGE WHEN THE CHARGER WAS SHIFTED THE AC BREAKER WAS RESET-AND 2D32 WA3 RETURNED TO'S EQUALIZED TO FLOAT.
INSTRUCTIONS WILL BE POSTED LOCALLY GIVING CAUTIONS NEEDED T0 =
j-
'ERVICE.
VOID REOCCURRENCE.
3
T
+
.w s
p I
on s
.FEB.07,'1980 LER DUTPUT ON REPORTS RECEIVED'FROM. 12/31/79'THRU 01/13/80
.,PAGE 2--
s OUTPUT SORTED BY FACILITY AND EVENT =DATE FACILITY / SYSTEM /
COMPONENT / COMPONENT SUSCODE/
DOCKET NO./ EVENT-DATE/
CAUSE/CAUSE SUBCODE/.
LER NO./
REPORT DATE/
EVENT. DESCRIPTION /
COMPONENT MANUFACTURER CONTROL.HO REPORT TYPE
.CAUSE DESCRIPTION-05000368 121179 DURING MODE 1 OPERATION THE "C" CORE PROTECTION'C' LCULATOR FAILED CAUSIN
~
A ARKANSAS-2 79-096/03L-0 ;010480 G LOW DNBR AND HIGH LPD TRIPS IN THE "C" PPS.
ALL' REMAINING CPC CHANNELT REACTOR TRIP SYSTEMS 5 : REMAINED OPERABLE. THE "C" CPC -TRIPS WERE BYPASSED PL ACING THE REACTO -
- INSTRUMENTATION + CONTROLS 027809 '
30-DAY '
COMPUTATION MODULE R TRIP LOGIC IN A ~ 2 OUT OF 3 CONDITION. OTHER 0CCURRENCES INVOLVING CPC'
'S ARE LER'S 50-368/79-0063 79-0073.79-011: 79-012;79-015; 79-0453 79-8:
^ COMPONENT FAILURJ INSTRUMENT 71; 79-074: 79-075.
REPORTABLE PER T.S. 6.9.1.9.8..
COMBUSTION ENGINEERING, INC.
INVESTIGATION: REVEALED CAUSE OF CPC FAILURE TO BE A NATA LINK FAILURE BE-TWEEN THE CPC AND THE CPC'S.0PERATORS CONSOLE. SY! EM WAS-RESTARTED AND RESTORED TO OPERATIDHAL STATUS. THE REQUIREMENTS OF ACTION STATEMENT T
.S.
TABLE _3.3-1, 82 WERE MET.
05000435' 021279
. PROC 2ESSIVE CRACKING OF HEAT' AFFECTED ZONE' 0F STUD ANCHORS IN FLEXIBLE P BELLEFONTE-l 79-
/02X.
070379 LATE CONNECTIONS.HAS DCCURRED IN TVA RESEARCH TESTS.
. SYSTEM CODE NOT APPLICABLE OTHER-COMPONENTS-027733 OTHER SUBCOMPONENT NOT. APPLICABLE DESIGN / FABRICATION ERROR CAUSE'SUBCODE NOT PROVIDED ITEM NOT APPLICABLE TVA.IS EVALUATING DATA FROM THE TESTS TO DETERMINE PROPER CORRECTIVE ' ACT '
ION.
BELLEFONTE-1' 05000438 081779 LINES' LEADING FROM THE PRESSURIZER SAFETY STEAM VENT. AND RELIEF VALVES Si
-MAIN STEAM SYSTEMS + CONTROLS
'79-
/02L-091379 HOULD.HAVE BEEH DESIGHED TO WITHSTAND ANTICIPATED TRANSIENT WITHOUT TRIP PIPES, FITTINGS
~
027875 30-DAY EVENTS AND WERE NOT.
THE FAILURE OF THE LINES DURING AN EXPECTED 'TRANS.
NO SUBCOMPONENT PROVIDED IENT WOULD INCREASE THE RISKS TO THE PUBLIC DURING SUCH A TRANSIENT.
DESIGH/ FABRICATION ERROR CAUSE SUBCODE NOT PROVIDED ITEM POT APPLICABLE
^ TVA WILL'MO.
THE EFFICIENCY WAS CAUSED BY AN INADVERTENT DESIGNER ERdOR.
DIFY THE LINES TO WITHSTAND THESE LOADS.
BROWNS FERRY-1 05000259-111279 DURING HORMAL OPERATION, THE DRYWELL AIR SAMPLING MONITOR, RM 90-256 WAS-
' AIRBORNE RADIDACT MONITOR SYS 79-031/03L-0 121279 OBSERVED' ALARMING DOWHSCALE (T.S. 3.6.C.2).
THE' INSTRUMENT HAD INDICAT
. INSTRUMENTATION + CONTROLS 027790 30-DAY
.ED ERRATIC RECORDING PRIOR TO THE EVENT. THE CHEMICAL LABORATORY WAS'HO-TIFIED TO BEGIN A SAMPLING PROGRAM WHILE THE INSTRUMENT WAS OUT-OF SERVI; OTHER i ~~ -COMPCNENT FAILURE' CE. 'THERE ARE NO REDUNDANT SYSTEMS. THERE WAS HO HAZARD TO THE PUBLIC
' INSTRUMENT hs0LTH.OR SAFETY.
THE,RE HAVE BEEN.HO PREVIOUS - EVENTS 0F THIS HATURE.
OTHER RAECO MODEL-1017 24-VOLT TRANSFORMER HAD FAILED.
THE TRANSFORMER WAS' RE:
PLACED, AND THE SYSTEM FUNCTIONALLY' TESTED AND RETURNED TO SERVICE'IH SE.
VEN HCURS.
NO RECURRENCE COHTROL ACTION IS PLAHHED SINCE THE FAILURE AP PEARS TO BELRANDOM IN HATURE.
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l-i FEB'B7, 1980'
- LER OUTPUT ON REPORTS" RECEIVED FROM'12/31/79 THRU 01/.13/80L
- PAGE!41 0UTPUT SORTED BY FACILITY-AND EVENT DATE.
. FACILITY / SYSTEM /
COMPONENT / COMP 0HENT SUBCODE/.- 1 DOCKET MO./. EVENT DATE/-
.CAUSE/CAUSE SUBCODE/-
' LER HD./
REPORT.DATE/
EVENT DESCRIPTION /
COMPONENT MANUFACTURERc CONTROL NO. REPORT TYPE CAUSE DESCRIPTION
'05000296 120279
- DURING PERFORMANCE OF THE DIESEL GENERATOR EMERGENCY LOAD ACCEPTANCE TES
'BROWHS. FERRY-3
.79-023/03L-1 123179-
.T -DIESEL-GENERATOR 3C TRIPPED FOLLOWING THE START OF -THE RHR PUMP 35 CO:
EMERG GENERATOR SYS.+ CONTROLS -
COMPONENT. CODE NOT APPLICABLE.'
027161
' 30-DAY
.HTRARY'TO T.S. 3.9 A.
THERE WERE NO SIGHIFICANT RESULTING EVENTS. THER SUBCOMPONENT NOT: APPLICABLE LE WAS NO DANGER TO HEALTH OR SAFETY OF THE PUBLIC. NO PREVIOUS DCCURREN' 4
DIESEL GENERATORS 3A, 38, AND 3DLWERE.AVAILABLE.
' HOT. APPLICABLE ITEM:NOT APPLICABLE; VOLTAGE OUTPUT.0F FREQUENCY' GENERATOR WAS TOO HIGH RESULTING IN THE DIES
.EL GENERATOR TYING IN AT A LOWER SPEED AND VOLTAGE. THE FREGUENCY GENER;'
ATOR VOLTAGE OUTPUT WAS CORRECTED, AND.THE SPEED SENSING PANELS WERE-CAL IBRATED.. THE HIGHER QUTPUT WAS DUE TO COMPONENT DRIFT. 'ALL U-3 D/G'S W ERE, CHECKED, & U-1 8 U-2 D/G WILL BE1 CHECKED.DURING REFUELING OUTAGE.'
BROWHS FERRY'3 05000296 120779 DURING UNIT 3 REFUELING OUTAGE RCIC FAILED TO REACH RATED' FLOW AS PER T.
REAC CORE ISOL COOL SYS + CONT:
79-026/03L-0 010480 S.,3.5.F.1.(1).
THERE'WAS'HO DANGER.TO HEALTH OR SAFETY OF PUBLICzAND NJ
-INSTRUMENTATION.+ CONTROLS 027833-30-DAY 0 SIGNIFICANT RESULTING EVENTS..NO PREVIOUS' OCCURRENCES.< HPCI WAS VERI CONTROLLER FIED OPERABLE.
COMPONENT-FAILURE-NATURAL END OF LIFE
+
' WOODWARD GOVERNOR CO.
. THE EGM BOX W -
THE RCIC EGM BOX HAD A DEFECTIVE HIGH TRIM POTENTIOMETER.
AS; REPLACED.. TYPE EGMt. MODEL 8270-849.
NO RECURRENCE CONTROL REQUIRED.
BROWHS FERRY-3 05000296' 120879
-WITH UNIT 3 AT 200 MWE FOLLOWING UNIT: RETURN'~TO SERVICE AFTER REFUELING-
. REACTOR CONTAIMMENT SYSTEMS 79-024/03L-0 010780 OUTAGE-EXCESSIVE LOCAL. LEAKAGE WAS DETECTED AT THE SOUTH EACH DRYWELL Et COMPONENT-CODE NOT APPLICABLE
'027842-30-DAY
.UIPMENT HATCH DOOR.'
THE PLANT WAS OPERATED'UNDER CONDITIONS PERMITTED R SUBCOMP0HEHT NOT APPLICABLE Y TECHNICAL SPECIFICATION 4.7.A.2.H.(2). -THERE WAS HD DANGER TO HEALTH PERSONNEL ERROR OR SAFETY OF THE PUBLIC;. NO PREVIOUS OCCURRENCES.
. MAINTENANCE & REPAIR PERSONNEL ITEM HOT APPLICABLE EAST DRYWELL EQUIPMENT HATCH DOOR WAS LEAKING DUE TO UNEVENLY TIGHTENED -
BOLTS. BOLTS WERE RETIGHTENED AND HATCH PASSED LLRT.
ADMINISTRATIVE C0 i
HTROLS ARE BEING DEVELOPED TO INCORPORATE ADDITIONAL-VERIFICATIONS AND T.
l 0 USE A LOCK THAT WILL INSURE'THAT THE HATCH IS HOT DISTURBED WITHOUT PR:
OPER APPROVAL.
79-22 DISCUSSES SAME EVENT.
BROWNS FERRY-3 05000296 120879 WITH UNIT 3 AT 200 MWE FOLLOWING UNIT.RETURH TO SERVICELAFTER' REFUELING-REACTOR CONTAIHMENT SYSTEMS 79-022/03L-0 010480 OUTAGE THE DRYWELL TO SUPPRESSIDH CHAMBER DIFFERENTIAL PRESSURE COULD H-COMPONENT CODE NOT APPLICABLE 027843 30-DAY OT BE MAINTAINED AT OR ABOVE 1.3 PSID PER-TECHNICAL SPECIFICATION 3.7.A.
4 SUBCOMPONENT HOT APPLICABLE 6.A.
AH ORDERLY' SHUTDOWN OF UNIT 3 WAS INITIATED. 'THERE WAS NO DANGER PERSONNEL-ERROR:
TO THE HEALTH OR SAFETY OF THE PUBLIC; H0 PREVIOUS ~ SIMILAR OCCURRENCES.
MAINTENANCE & REPAIR PERSONNEL REDUNDANCE IS NOT, APPLICABLE.
ITEM HOT APPLICABLE EAST DRYWELL. EQUIPMENT HATCH DOOR WAS LEAKING DUE TO UNEVENLY TIGHTENED.
BOLTS. BOLTS WERE RETIGHTEHED AND HATCH PASSED LLRT.. ADMINISTRATIVE CO.
HTROLS ARE BEING DEVELOPED TO INCORPORATE ADDITIDHAL VERIFICATIONS AHD T.
HE USE OF A LOCK TO ENSURE THAT THE HATCH IS HOT MOVED WITHOUT PROPER AP. :
e PROVAL.
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~
FEB 07,N'1980
, LER:00TPUTION REPORTS RECEIVED FROM-12/31/79;THRU'01/13/80
- PAGEl5' U'
- 0UTPUT, SORTED BY;FACILITYsAND. EVENT DATE.
+
' FACILITY / SYSTEM /~
DOCKET NO./. EVENT DATE/..
- COMPONENT / COMPONENT SUBCODE/
CAUSE/CAUSE SUBCODE/
.LER NO./
REPORT DATE/
. EVENT. DESCRIPTION /r
, COMPONENT. MANUFACTURER:
- CDHTROL NO. REPORT! TYPE CAUSE: DESCRIPTION' BRUNSWICK-1/,
05000325'
'111579 DURING A~ NORMAL' REACTOR STARTUP, T'HE' " FULL IN" I DICATING LIGHTS ' REMAINE'
,-REACTIVITYLCONTROLlSYSTEMSE
-.7 9-0 9 9/ 0 3L-0 120779
'D LIT ON-CONTROL RODS 18-11 AND 26-11 WHEN THE RODS WERE' REMOVED FROM TM'
.INSTRUMENTATIONL+ CONTROLS:
'027787 130-DAY!
E " FULL IN" PGSITION. - " FULL'OUT" INDICATION TO RSCS 1 ROD. SEQUENCE CONTRf
'OL SYSTEM) WAS NOT-SEING RECEIVED FROM CONTROL ROD 18-31r TECHNICAL.SPE a..
- -OTHER..
.CIFICATIONS; 3.1.3.7, 6.9.1.98.
LCOMPONENT FAILURE /
ELECTRONIC.
' GENERAL ELECTRICfCO.-
THE PROBLEM WITH.26-11 WAS A SHORT ON:Q16'ON THE PROBE BUFFER. CARD,.AND' THE PROBLEM WITHL 18-11 WAS A ' DEFECTIVE GATE ON Q33 ON THE PROBE BUFFER C ARD. - BOTH-916 1-933 WERE REPLACED. AN OPTICAL ISOLATOR WAS FOUND'DEFEC-TIVE ON THE 18-31 CIRCUITRY & WAS REPLACCD. 'THESE ARE CONSIDERED _ISOLATi ED EVENTS, AND.M0 FURTHER ACTION.IS REQUIRED.
05000325 111679 DURING NORMAL PLANT OPERATION, A BROKEN DRIVE BELT WAS FOUND ON'THE CONT
< BRUNSWICK-1 79-094/03L-0 =121479 AIMMENT' ATMOSPHERIC MONITOR CAC-AQH-1259.
TECHNICAL SPECIFICATIONS-3.3t CNTNMNT'COMBUS GAS CONTROL;SYS
- 0THER COMPONENTS
,'027783 30-DAY 5.3, 6.9.1.98.-
.SUBCOMPONENT NOT APPLICABLE COMPONENT FAILURE--
.OTHER-BROWNING'CO.
THE BELT BROKE DUE TO NORMAL WEAR.. TO DETECT' WORM BELTS ^IN THE FUTURE'B EFORE THEY BREAK, THE BELT HAS BEEN ADDED TO THE. PERIODIC MAINTENANCE PR' DGRAM INCORPORATED IN MAINTENANCE INSTRUCTION.10-501A. THIS IS CONSIDER:
ED AN ISOLATED EVENT,1AND NO FURTHER ACTION IS REQUIRED.
[ BRUNSWICK-11 05000325 111979 DURING. NORMAL" PLANT'0PERATION, THE,0PERATOR. NOTICED THAT.THE CONTAINMENT-CNTNMNT COMBUS GAS-CONTROL SYS ~
79-086/03L-O' -121179 ATMOSPHERIC M3NITOR, CAC-AQH-1263, HAD FAILED DOWNSCALE OH THE OXYGEN.C-LINSTRUMENTATION'+ CONTROLS:
027792
~30-DAY.
.HANNEL.
TECHNICAL SPECIFICATION 3.6.6.4, 6.9.1.98.
OTHER' COMPONENT FAILURE
. ELECTRONIC BECKMAN INSTRUMENTS, INC.
THE' OXYGEN ANALYZER HAD DRIFTED OUT OF CALIBRATION FOR HO KNOWN REASON.
-THE INSTRUMENT WAS RECALIBRATED AND RETURNED'TO SERVICE SATISFACTORILY.'
ENGINEERING ISL NOW INVESTIGATING.0THER MONITORING SYSTEMS TO DETERMINE ~
THE POSSIBILITIES FOR REPLACEMENT.
05000325 120579 WHILE PERFORMING PT 2.1.7PC,- HPCI EXHAUST DIAPHRAGM HIGH PRESSURE CALIBR.
'BRUNSWIC'K-1 79-101/03L-0 122879 ATIONi PRESSURE SWITCH 1E41-PS-H012A WOULD NOT ACTUATE AT ANY: APPLIED PR EMERG CORE COOLING SYS + CONT
" INSTRUMENTATION + CONTROLS 027835' 30-DAY ES5URE UP TO 30 PSIG. -THE DESIRED SETPOINT IS 7 +/-L0.7 PSIG INCREASING-AND THE REPORT LIMIT IS > 10 PSIG.
TECHNICAL SPECIFICATIONS 3.3.2,'6.9
'I
. SWITCH COMPONENT' FAILURE-,~
1.98.
-ELECTRONIC
'BARKSDALE COMPANY INTERMITTENT ACTUATION OF THE INTERNAL MICR0 SWITCH WAS ~ DETERMINED THE. C.
1 AUSE FOR SWITCH FAILURE.
THE SWITCH WAS REPL ACED AND-THE CALIBRATION PT -
WAS COMPLETED.SUCCESSFULLY. THIS IS CONSIDERED AN ISOLATED EVENT.AND N0?
l FURTHER ACTION IS REQUIRED.
't i
$ ' )
y c41 d5 FEB 07,[198'0-
.LER 0UTP'UT'ON REPORTS RECEIVED FROM 12/31/79 TH'RU.01/13/80'
- PAGE 6s
~
- 0UTPUT; SORTED BY.FA.IllTY;AND EVENT DATEL, 4
, FACILITY / SYSTEM /o
-COMPONENT / COMPONENT SUBCODE/, : DOCKET NO./. EVENT DATE/
1CAUSE/CAUSE.SURCODE/
LER.NO./.
. REPORT DATE/
. EVENT: DESCRIPTION /_
. COMPONENT MANUFACTURER CONTROL HO. REPORT TYPE CAUSE DESCRIPTION
?
05000325
.120679; L WHILE PERFORMING PT 9.5, HPCI-10008 FLOW RATE TEST,. THE HPCI SYSTEM ISOL:
BRUNSWICK-1
'79-104/03L-0 -122879-cATED DUE TO A HIGH SUCTION PRESSURE SIGNAL FROM;1E41-PSH-NO31..TECHNICA EMERG CORE COOLING SYS + CONT
' INSTRUMENTATION + CONTROLS
' 027838 30-DAY.
L SPECIFICATIONS 3.5.1, ' 6.9.1.98.
SENSOR / DETECTOR /EL EMENT -
.CDMPONENT FAILURE.
MECHANICAL
'BARKSDALE COMPANY THE DIAPHRAGM ON 1E41-PSH-NO31 WAS FOUND?TO BE LEAKINGP.THUS-PROVIDING AC, FALSE HIGH PRESSURE SIGNAL. THE DIAPHRAGM WAS' REPLACED'AND RETURNED.TO' SERVICE SATISFACTORILY. THIS SWITCH IS CHECKED ON A QUARTERLY' BASIS'PER'
-THE CALIBRATION PROGRAM..THIS IS. CONSIDERED AN ISOLATED EVENT AND NO F URTHER ACTION IS REQUIRED.
~ BRUNSWICK '
305000325 121179-DURING HORMAL, PLANT OPERATION, THE CONTROL' OPERATOR HOTICED.THAT THE DRY-REACTOR CONTAIHMENT SYSTEMS' 79-108/03L-0 010380 WELL PRESSURE : INDICATOR CAC-PI-3341 WAS READING '3 PSIG WITH ' A NORMAL. DRY-
. INSTRUMENTATION + CONTROLS'
.l 02784 0 '
_30-DAY WELL-PRESSURE.0F 0.5 PSIG. ' TECHNICAL. SPECIFICATIONS:3.3.5.2, 6.9.1.98.
-INDICATOR-J COMPONENT: FAILURE ELECTRONIC' INTERNATL INSTRUMENTS, INC.
THE INDICATOR "ZER0" WAS OUT OFJTOLERANCE' CAUSING THE INDICATOR TO BE OUT T OF CALIBRATION. THE INDICATOR WAS RECALIBRATED AND RETURNED TO SERVIC=
E; SATISFACTORILY. THIS IS CONSIDERED AH ISOLATED EVENT AS THE INDICATOR-
-IS CALIBRATED QUARTERLY AND IT DOES NOT HAVE A' HISTORY OF "ZER0" SHIFTS
~
05000324 111579
-WHILE PERFORMING PT 3.1.14PC, REACTOR LOW PRESSURE CHANNEL CALIBRATION A i-LBRUNSWICK-2.
79-096/03L-0 120779 HD FUNCTION TEST,'$ WITCHES'1 AND~2 0F 2-B21-PS-H021D WERE OUT'0F TOLERAN 1EMERG CORE COOLING SYS +' CONT INSTRUMENTATION + CONTROLS
-027784 30-DAY-CE.
SWITCH 1, WITH A REQUIREMENT OF 335 +/- 15 PSIG, WAS FOUND AT'315 P OTHER:
SIG, AND SWITCH 2,-WITH A REQUIREMENT OF'435 +/- 15 PSIG, WAS FOUND AT '
COMPONENT FAILURE 80 PSIG.
TECHNICAL SPECIFICATIONS 3.3.3, 6.9.1.98.
MECHANICALL BARTON--INSTRU CO., DIV 0F ITT THE ACTUATING CAM WAS FOUND TO BE LOOSE CAUSING THE INDICATION'AND SWITC' HES TO.BE OUT OF TOLERANCE. THE CAM SET SCREW WAS TIGHTENED, THE INSTRU' MENT WAS CALIBRATED, AND THE-INSTRUMENT WAS RETURNED TO SERVICE SATISFACL TORILY. THIS IS'AH ISCLATED EVENT AND HD FURTHER ACTION IS REQUIRED.
05000324 112079 DURING A HORMAL REACTOR STARTUP, " FULL OUT" INDICATION WAS NOT:BEING REC-
< - BRUNSWICK-2..
79-100/03L-0 121379 EIVED BY RSCS (ROD SEQUENCE COH1ROL SYSTEM) FROM CONTROL ROD 06-27. 'THEr REACTIVITY CONTROL SYSTEMS INSTRUMENTATION + CONTROLS 027785 30-DAY ROD WAS BYPASSED " FULL OUT" WHEH ' ALL OTHER INDICATIONS SHOWED THE ROD A '
0THER
-T NOTCH 48.
TECHNICAL SPEDIFICATIONS 3.1.3'7, 6.9.1.-9B.
"~
COMPONENT FAILURE ELECTRONIC GENERAL ELECTRIC CO.
~THE PROBLEM WAS FOUND TO BE A DEFECTIVE OPTICAL ISOLATOR WHICH WAS REPLA' CED FROM STOCK.
THE UNIT WAS TESTED TO ENSURE PROPER SIGNAL TRANSFER AN' D RETURNED TO-SERVICE.
THIS IS' CONSIDERED AH ISOLATED EVENT,.AND H0 FUR THER ACTIOH'IS REQUIRED.
W 4
4 jz b.
4
~
. PAGE 77 - ?
FEB107,11980 LER OUTPUT ON REPORTS 2 RECEIVED FROM 12/31/79_THRU 01/13/80
~
0UTPUT. SORTED BY FACILITY _AND EVENT'DATE4
^
FA'CILITY/ SYSTEM /
K COMPONENT / COMPONENT ' SUBCODE/
DOCKET NO./-EVENT DATE/c
. EVENT DESCRIPTION /:
~CAUSE/CAUSE SUBCODE/-
LLER HO./>.
-REPORT DATE/
n COMPONENT; MANUFACTURER.
CONTROL NO. REPORTiTYPE- '
CAUSE DESCRIPTION-26 1 BRUNSWICK-2. -
05000324 112079~
uAT 085510N NOVEMBER-19,~1979,' UNIT NO. 215 CRAMMED ~FOLLOWING'APPROXIMATEL1
- + PROCESS SAMPLING SYSTEMS:
.79-099/03L-0 120679z Y TWO MONTHS OF HIGH POWER OPERATION. 'DURING THE SUBSEQUENT STARTUP,'TH OTHER COMPONENTS ~.
-027786
'30-DAYc E REACTOR' SCRAMMED AGAIM AT:0425 ON NOVEMBER 20. 1979. COOLANT. IODINE A-SUBCOMPONENT NOT-APPLICABLE, CTIVITY, ' ALREADY INCREASING AFTER THE FIRST -SCRAM,' EXCEEDED THE TECHNICA '
0THER.
' L: SPECIFICATION LIMIT OF.O.2 UCI/GM I-131 DOSE EQUIVALENT. -THE. MAXIMUM 1
NOT APPLICABLE'
- IODINE ACTIVITY WAS 0.414'UCI/GM.
TECHNICAL SPECIFICATIONS 3.4.5,.6.9.1:
. ITEM NOT APPLICABLE-
.98.
REACTOR POWER HELD TO <10% UNTIL IODINE ACTIVITY RETURNED WITHIN SPECIFIf
+
CATIONS. HIGH COOLANT ACTIVITY CAUSED BY. 2 REACTOR SCRAMS & SUBSEGUENT LINCREASE IN FISSIDH; PRODUCT INVENTORY IN COOLANT' COMING FROM' LEAKING FUE L ELEMENT. UNIT 82 FUEL BUNDLES'WILL BE' SIPPED DURING HEXT' REFUELING OU--
.TAGE AHD THE LEAKING BUNDLES REMOVED FROM THE CORE.
~ BRUNSWICK-2 05000324
. 120679 DURING HORMAL. PL ANT OPERATION, 2B REACTOR RECIRCUL ATION PUMP TRIPPED. 0; COOLANT'RECIRC SYSi+-CONTROLS 79-088/03L-0 122879-N DECEMBER 13, 1979 THE PUMP TRIPPED AGAIN FOR~APPARENTLY THE SAME.REAS
- GENERATORS-1027769.
30-DAY ON.. TECHNICAL SPECIFICATIONS 3.4.1.1,' 6.9.1.98.
' GENERATOR' COMPONENT. FAILURE ELECTRICAL-l GENERAL ELECTRIC'CO.
'IH BOTH CASES,' FUSES F18 S'F19 IM-VOLTAGE FEEDBACK CIRCUITRY FOR VOLTAGE'-
REGULATOR FOUND BLOWN.
IT.IS BELIEVED THAT SHORT BRUSHES'ON EXCITER C0 2
LLECTOR RINGS-COULD HAVE CAUSED DEGRADED EXCITATION FOR GENERATOR FIELD.
CAUSING BLOWN FUSES PROBLEM. BRUSHES & FUSES REPLACED &-PUMP SUCCESSFUL LY RESTARTED. ' PREVENTIVE MAINTENANCE INSTRUCT-MI 10-2M WILL BE REVISED..
BRUNSWICK-2'.
05000324 121479 WHIL E. PERFORMING PT - 2.3.1, DRYWELL TO TORUS VACUUM BREAKER OPERABILITY C l'
.CNTHMNT ISOLATION'SYS + CONT 79-102/03L-0 ~010380 HECK,' THE "CLOSE" INDICATION FOR X18H WOULD NOT DE-ENERGIZE WHEN 'THE VAL -
-INSTRUMENTATION'+ CONTROLS' 027844-30-DAY VE WAS OPEN.
TECHNICAL SPECIFICATIONS 3.6.4.1, 6.9.1.98.
. SWITCH-i
~ COMPONENT FAILURE-ELECTRICAL
- THE "CLOSE" LIMIT SWITCH WAS DISCONNECTED AND THE INSTALLED SPARE SWITCH '
. CONNECTED IN ITS PLACE.
THE. ORIGINAL SWITCH WILL'BE REPAIRED OR REPLAC' ED DURING THE NEXT OUTAGE.0F-SUFFICIENT' LENGTH. THIS IS CONSIDERED AN,I 1
SOLATED: EVENT.
4 BRUNSWICK-2 05000324
.121579 DURING MORMAL PLANT 0PERATION, THE CONTROL OPERATOR. NOTICED THAT THE CON CNTHMNT.COMBUS GAS' CONTROL SYS. 106/03L-0 010380 TAINMENT. ATMOSPHERIC MONITOR.CAC-AT-1259 WOULD HOT RUN DUE TO LOW FLOW.
PUMPS '
027839 30-DAY TECHNICAL SPECIFICATIONS 3.3.5.3, 6.9.1.98.
RECIPROCATING
~~
COMPONENT. FAILURE-MECHANICAL 9
. BECKMAN INSTRUMENTS,:INC.
.THE VACUUM PUMP DRIVE BELT WAS'FOUND BROKEN AND WAS REPLACED. THIS BELT IS INSPECTED MONTHLY PER MAINTENANCE' INSTRUCTION 10-3A.
ENGINEERING IS EVALUATING OTHER MONITORING SYSTEMS TO DETERMINE A-QUALIFIED REPL ACEMENT
{
FOR.THE MONITORS NOW IN USE.
1 i
.m g,
l l
- lY
- FEB 07,E1940 LER OUTPUT ON' REPORTS RECLIVED FROM 12/31/79 THRU 01/13/80' '
.PAGE 8 S
. OUTPUT SORTED BY FACILITY.AND EVENT DATE 4
- FACILITY / SYSTEM /t COMPONENT / COMPONENT 15UBCODE/ ' : DOCKET' NO./ EVENT DATE/
s
- CAUSE/CAUSE SURCODE/ -
.LER MO./. ' REPORT. DAT E/ -
- EVENT DESCRIPTION /"
- COMPONENT, MANUFACTURER
' CONTROL NO. REPORT TYPE CAUSE. DESCRIPTION AT 1800 THE CON' TROL ROOM'0PERATOR'WHILE TAKING' LOG' READINGS D'ISCOVERED R 2
CALVERT CLIFFS-11 05000317 112279 o
= REACTOR TRIP SYSTEMS)
'79-070/03L-0~ 122079 EACTOR'PROTECTIDH SYSTEM' CHANNEL'"C" CONTAINMENT PRESSURE,$1GNAL~HAD DEVl INSTRUMENTATION +-CONTROLS-027798
<30-DAY IATED BY GREATER-THAM,0.1 VOLTS FROM.TH0 0THER CHANNELS. ~THE CHANNEL WA>
' SENSOR / DETECTOR / ELEMENT-1 S BYPASSED IN ACCORDANCE, WITH T.S.~ 3.3.1.1 TO - ACCOMMODATE REPAIRS. E T H E <.'
' COMPONENT FAILURE-THREE REUJMDANT CHANNELS REMAINED OPERABLE DURING THE EVENT.. CHANNEL "C:
IZSTRUMENT
- CONTAINMENT PRESSURE.WAS RETURNED TO SERVICE AT'1310 OH.11/23/79.' THI.
- TRA%SMATION,. INC.
5 IS A REPETITIVE OCCURRENCE FOR THIS TYPE OF INSTRUMENT. ' 1..
FOUND ISOLATOR 1-E/E-5313C TO HAVE A LOW OUTPUT'FOR ITS IMPUT: SIGNAL-LEV-EL. -THE INSTRUMENT COULD HOT BE CALIBRATED AND WAS REPLACED WITH A STOC KED SPARE. 'THE INSTRUMENT IS A'TRANSMATION MODEL:230T' ISOLATING TRANSMIJ TTER.
RECENT TRANSMATION CORRESPONDENCE HAS' SUGGESTED THE USE OF' MIL. 5-PEC. CAPACITORS TO DECPEASE FAILURE RATE OF THIS.MODEL.-
05000317 112679 DURING STEADY STATE OPERATIONS, ~ SEVERAL SPURIOUS. TRIPS ' ON CHANNEL "A" HI:
'CALVERT CLIFFS-1
.79-067/03L-0 122075 GH. POWER OCCURRED.
AT-0040' CHANNEL "A" HIGH POWER, THERMAL MARGIN / LOW P'
- REACTOR. TRIP SYSTEMS-027799
'3C-DAY RESSURE AND AXI AL FLUX OFFSET -TRIP UNITS WERE BYPASSED PER T.S. 3.3.1.1,1 INSTRUMENTATION + CONTROLS SENSOR / DETECTOR / ELEMENT
. ACTION 2, ALL OTHER RPS TRIP UNITS REMAINED OPERABLE: THROUGHOUT'THE EVE -
-COMPONENT FAILURE HT.. CHANNEL "A" HIGH POWER.TM/LP, AND AXI AL > FLUX OFFSET -TRIPS WERE RETU INSTRUMENT
.'R EVENT.
J DESCRIBES A.SIMILA RNED T0. SERVICE AT 22OO ON 11/26/79..LER 79-62 (U-1):
COS EMOUNT, - INC.~
~
FOUND INTERMITTENT SPIKES-ON ONE T-COLD TEMPERATURE' INPUT!(TCL).. TO CHANN L EL... APPARENT CAUSE IS FAULTY RESISTANCE TEMPERATURE' DETECTOR OR FIELD T
- ERMINATIONS. THE PROBLEM HAS CONTINUED TO BE INTERMITTENT. FURTHER TROL U$LESH00 TING AND REPAIR WILL BE ACCOMPLISHED DURING THE NEXT PLANT COLD:
SHUTDOWN.
05000317 112779 DURING NORMAL STEADY' STATE OPERATION. 812 EMERGENCY DIESEL' GENERATOR'WAS
. CALVERT CLIFFS-1
. 068/03L-0 121379 PLACED OUT 0F SERVICE AT 1020~-TO REPLACE AN AUTOMATIC VENT VALVE-OH THE:
STATION SERV WATER SYS + CONT VALVES 027803 30-DAY.
SERVICE-WATER RETURN:LINE.. THE REMAINING' DIESELS AND POWER SOURCES' WERE OTHER VERIFIED OPERABLE PER' TECHNICAL SPECIFICATI0H 3.8.1.1 AT 1140 #12 DIE:
COMPONENT FAILURE SEL GENERATOR WAS RETURNED TO SERVICE. _.THIS IS NOT.A REPETITIVE EVENT.
MECHANICAL INTERNATIONA-TEL.f4 TELEGRAPH THE "HOFFMAN AIR VENT" FLOAT VALVE FAILED DUE TO NORMAL WEAR ON THE VALV E SEAT.
THE VENT WAS REMOVED (THREADED PIPE FITTING) AND REPLACED WITH -
ONE FROM STOCK.
05000317
.112779 DURING STEADY STATE OPERATID'N 811 DIESEL GENERATOR WAS REMOVED FROM SERV
' CALVERT CLIFFS.
79-069/03L-0 121379 ICE AT.1420 TO REPAIR A FUEL OIL LINE LEAK.
THE REMAINING DIESELS AND P J EMERG GENERATOR SYS + CONTROLS ENGINESiINTERNAL COMBUSTION 027804 30-DAY OWER SOURCES WERE VERIFIED OPERABLE PER" TECHNICAL SPECIFICATION 3.8.1.1.
SUBCCMPONENT NOT APPLICABLE AT 2135 811 DIESEL GENERATOR WAS RETURNED'TO SERVICE. THIS IS NOT A RE.
"". COMPONENT. FAILURE' PETITIVE EVENT.
METALLURGICAL FAIRBANKS: MORSE THE DIESEL WAS TAKEN OUT OF. SERVICE FOR AN' ATTEMPTED REPAIR ON'THE FUEL:
OIL IHJECTOR SUPPLY LINE.
THE 18" PIECE.0F.62S" COPPER TUBING WAS REMO VED 1. TESTED FOR LEAKS,'BUT NOME COULD BE FOUND. LINE REPLACED & DIESEL RETURNED TO. SERVICE. LEAK WAS THEN LOCATED.S MARKED FOR FUTURE REFEREN CE.
A FOLLCW-UP REPORT WILL BE ISSUED AT~A LATER DATE.
e 9
. r
.s
~. - _
^V, rd'^
h' r
a
- se i
- LER OUTPUT'0H REPORTS RECEIVED:FROM [12/31/79 THRU 01/13/80'
- PAGE19,:a, f
JFEB 07,J1980.','
0UTPUT SORTED BY-FACILITY.AND EV N :E T DATE^
i e
- FAC LITY/ SYSTEM /E
. DOCKET -NO./; EVENT. DATE/.
- EVENT DESCRIPTION /.
COMPONENT / COMPONENT SUBCODE/.
LER NO./'
. REPORT.DATE/-
CAUSE/CAUSE. SUSCODE/.
s
- CDMPONENT-MANUFACTURER-CONTROL.NO.: REPORT TYPE'
'CAUSE DESCRIPTION, i
05000317 112979(
AT 0020 WHILE PERFORMING'A RINSE OF 812 MAKE-UP. TRAIN RESIN THEtSERVICE:
.CALVERT' CLIFFS -. -
'.7 9-0 75/ 04T-O ' s t2137 9 BUILDING 0PERATOR DISCOVERED THAT 012 ' WASTE NEUTRALIZING-TANK.(hMT) W4S;
,DEMIN WATER MAKE-UP.
c0VERFLOWING TO THE GROUND,.RESULTING-IN AN UNMONITORED DISCHARGE OF THE~
> COMPONENT CODE NOTfAPPLICABLE 2027802
_2-WEEK
..SUBCOMPONENT-MOT APPLICABLEr'
~
.WNT WHICH IS NOT ALLOWED ~BY ENVIRONMENTAL-T.S.-2.2.1..~NO ENVIRONMENTALL
. PERSONNEL ERROR <1-
~
- IMPACT IS EXPECTED.DUE TO.THE-SMALL~ AMOUNT OF PARTIALLY -EXHAUSTED REGEME1 RANT. CHEMICALS' DISCHARGED'AS' COMPARED TO THE DILUTION FLOW RATE. ' UNIT 2J
-N0HLIC. OPERATIONS PERSONNEL WAS IN MODE'5.
THIS'IS NOT.A REPETITIVE OCCURRENCE. -
. ITEM NOT APPLICABLE THE CAUSE,WAS APPARENTLY'AN 0PERATOR ERROR IN READING THE' TANK, LEVEL AND
- APPARENT-DISREGARD TO EVENTS WHILE PERFORMING A REGENERATION. IMMEDIAT:
E CORRECTIVE ACTION WAS TO ' REVISE.THE PROCEDURES ' TO REQUIRE THE T'
TO RECORD WNT LEVEL. HOURLY WHILE WNT'S ARE:IN USE. :FURTHER MEASURES TO'
' PREVENT RECURRENCE ARE'BEING CONSIDERED.
oCALVERT2 CLIFFS-1' 05000317 120479'
-DURING STEADY STATE OPERATICH, 912 DIESEL GENERATOR WAS' PL ACED OUT' OF. SE.
EMERG GENERATOR SYS + CONTROLS' f79-074/03L-0 122079 RVICE-AT.0650 FOR' REPAIR OF VARIOUS FUEL OIL LEAKS.~ WHILE:812 DIESEL WA
- ENGINES, INTERNAL COMBUSTION.
027812 30-DAY' S INOPERABLE THE REMAINING A.C.' POWER' SOURCES WERE TESTED:IN ACCORDANCE SUBCOMPONENT1 NOT APPLICABLE
-WITH T.S.
3.8.1.1.-
'812 DIESEL GENERATOR WAS RETURNED'TO SERVICE ATi1150
' COMPONENT FAILURE' UNIT 2:WAS:IN MODE 2.
LER 77-122.(U-1) DESCRIBES A;SIMILAR EVENT.
METALLURGICAL
.FAIRBANKS MORSE' VARIOUS FLARE AND-FERRULE FITTINGS LOOSE FROM VIBRATION"0F DIESEL'WERE T-
'IGHTENED TO STOP LEAKS. ONE 4" PIECE OF 1/4" COPPER TUBING WAS' REPLACED DUE-TD A CRACK.,THESE SMALL LEAKS DO NOT: DEGRADE SERVICE OF-THE DIESEL-
- USUALLY THEY ARE DETECTED AND ELIMINATED BY BI-WEEKLY P.
M. PROCEDURE
S 1 1.8 2-24-M-2W-1..
05000317 120479 AFTER COMPLETION OF WEEKLY TESTING ON 911 DIESEL' GENERATOR, IT WAS'0BSER-CALVERT CLIFFS-1 79-073/03L-0 010480 VED:THAT THE ASSOCIATED " SEQUENCE INITIATE"' ALARM DID HOT CLEAR.' AT 132 EMERG GENERATOR SYS'+ CONTROLS l
.; CIRCUIT CLOSERS / INTERRUPTERS
'027813:
~30-DAY-
- 3. THE DIESEL GENERATOR WAS REMOVED FROM SERVICE <TO INVESTIGATE THE PROB
- SWITCH -(OTHER THAN. SENSOR)
LEM AND EFFECT REPAIRS ON THE OUTPUT BREAKER. THE BREAKER' AUXILIARY,5WI TCH WAS FOUND TO BE BINDING AND WOULD NOT RETURN Til THE OPEN POSITION.
COMP 3 MENT FAILURE.
ELECTRICAL
-GENERAL ELECTRIC CO.
THE FAULTY SWITCH WAS REPLACED, L(MODEL #S3M TYPE 10 AX 01263). 'THE PROP ER OPERATIDH OF THIS SWITCH CAN BE.0BSERVED DURING THE WEEKLY FUNCTIONAL TEST OF THE DIESEL GENERATORS. ADDITIONALLY, THE BREAKER AND ITS AUXIL-i IARY SWITCHES ARE PERIODICALLY INSPECTED UNDER THE PREVENTIVE MAINTENANC 4
E PROGRAM.
~05000318 112779 1AT - 1130 CHANNEL ZG ' PRESSURIZER ' PRESSURE TRANSMITTER OF THE ENGINEERED S A -
.CALVERT' CLIFFS-2
.. 042/03L-0 122079 FIRE PROTECTION SYS + CONT FETY FEATURES SYSTEM WAS-PLACED OUT OF SERVICE IN ACCORDANCE WITH T.S.-3',
j.
. HANGERS SUPPORTS, SHOCK SUPPRSS 027797 30-DAY
.3.2.1 FOR REPAIR OF'A CONDUIT,AND CORRECT'A TRANSMITTER ZERO SHIFT. TH DESIGN / FABRICATION > ERROR'.
.E THREE REDUNDANT CHANNELS REMAINED OPERABLE DURING THE EVENT..THE TRAN" HANGERS.
SMITTER WAS RETURNED TO SERVICE LT 1615.
THIS IS NOT A REPETITIVE OCCUR' a
?
" CONSTRUCTION / INSTALLATION-RENCE.
t i
ITT'GRINNELL FOUND TRANSMITTER 2-PT-102D OUT OF CALIBRATIOH; IT HAD ZERO-SHIFTED TO A l'
SIGNAL LEVEL APPROXIMATELY 28 PSI HIGH.- THE TRANSMITTER WAS RECALIBRAT ED AND ITS CONDUIT REPAIRED. THF CAUSE WAS THE CLOSE PROXIMITY'0F THE C-ONDUIT TO A FIRE-SYSTEM WATER LlnE. HANGER. MOVEMENT OF. PIPE SYSTEM' CAUS -
[
ED HANGER'TO CONTACT CONDUIT ON THE TRANSMITTER BASE.
l~"
4.
e de~
.FE8l07,-1980 LER 0UTPUT ON REPORTS RECEIVED,FROM 12/31/79 THRU.01/13/80' lPAGE'10 OUTPUT SORTED.BY FACILITY AMD' EVENT-DATE_
FACILITY / SYSTEM /-
- COMPONENT / COMPONENT SUBCODE/- DOCKET HO./ EVENT DATE/
JCAUSE/CAUSE SUBCODE/
LER N0./-. - REI ORT DATE/
EVENT. DESCRIPTION /.
. COMPONENT MANUFACTURER CONTROL HO., REPORT TYPE-CAUSE,DESCRIPTIDH CALVERT CLIFFS-2.
05000318
'120479 AT 1520 WHILE PERFORMING A POST REFUELING LOW POWER' PHYSICS TEST. TAVE D-MAIN. STEAM SUPPLY-SYS +-CONT 79-047/03L-0 2010480 R0PPED BELOW 515 DEG. F.. CONTRARY ' TO THE REQUIREMENTS OF T.S. -3.1.1.5.
, COMPONENT CODE NOT APPLICABLE
.027816.
30-DAY THE'0PERATOR IMMEDIATELY TRIPPED THE REACTOR AND PLACED IT-IN-HOT STANDBL
-SUBCOMPONENT' HOT APPLICABLE-Y, SINCE IN HIS JUDGMENT TAVE COULD HOT BE RESTORED TO GREATER THAN 515 PERSONNEL ERROR
'DEG. F. WITHIN.15 MINUTES.
LER.76-11 DESCRIBES-A SIMILAR. EVENT.
LICEhSED & SENIOR 0PERATORS' ITEM HOT _ APPLICABLE L OF TURBINE. BYPASS VALVES BECAUSE OF LOW STEAM FLOW.
THE COMBINED EVEN.'
TS CAUSED TAVE TO RAPIDLY DECREASE. SINCE. REACTOR OPERATION WITH A PTC.
IS LIMITED.TO BRIEF PERIODS, H0 CORRECTIVE ACTION LIS DEEMED HECESSARY.
CALVERT CLIFFS 05000318 121279 AT'0705 CHANNEL.A WIDE RANGE HUCLEAR INSTRUMENT.(WRNI).WAS DISCOVERED T?
REACTOR TRIP SYSTEMS-79-043/03L-0 010380 0 BE MALFUNCTIONING. THE INSTRUMENT WAS.PLACED 0UT OF SERVICE'IH ACCORD-INSTRUMENTATION + CONTROLS 027817'.
30-DAY
.ANCE WITH T.S. 3.3.1.1
'THE-THREE REDUNDANT WRNI CHANNELS REMAINED ~0PER-
- SENSOR / DETECT OR/ EL EMENT ABLE DURING THE EVENT. ' CHAHHEL A WRNI WAS RETURHED TO SERVICE AT.1630. -
COMP 0HENT FAILURE THIS IS NOT.A REPETITIVE OCCURRENCE. '
MECHANICAL WESTINGHOUSE ELECTRIC CORP.
.THE PROBLEM WAS FOUND TO BE A LACK OF FISSIDH CHAMBER CURRENT FROM-THE'C'.
HANNEL A WIDE RANGE DETECTOR. THIS WAS CUASED BY THE CENTER'PIM-IN'A C0 NHECTOR HAVING PARTED FROM THE FISSIDH CHAMBER EXTENDER CABLE CONDUCTOR.
LACK OF-FISSIDH CHAMBER CURRENT CAUSED ERRATIC INDICATION.
CALVERT CLIFFS-2 05000318 121779 DURING TH'E PERFORMANCE OF A SURVEILLANCE 1 TEST IT WAS DISCOVERED THAT-822 CNTHMNT AIR.PURIJ+ CLEANUP SYS 79-048/03L-0 010480 IODIHE FILTER WOULD HEITHER START OH A CIS SIGNAL, HOR START _WITH-THE H CIRCUIT CLOSERS / INTERRUPTERS
_027815 30-DAY AHDSWITCH.- THE IODINE FILTER WAS OUT OF SERVICE FROM 1125 TO'1345 ON DE-OTHER' CEMBER 17, 1979.
IODINE FILTERS #21 AND 923 REMAINED OPERABLE DURING TH.
COMPONENT-FAILURE
.IS PERIOD. THIS IS N07 A. REPETITIVE 0CCURRENCE.
(T.S.l3.6.3.1).
MECHAHICAL WESTINGHOUSE. ELECTRIC CORP.
L IT WAS FOUND THAT CIRCUIT BREAKER'S (DS-206) MOVING CONTACT PIVOT' ARM WA S NOT ROTATING AS FREELY AS SHOULD BE EXPECTED, THE PIVOT POINT WAS RELU-
.BRICATED AND THE BREAKER TESTED.
IT IS FELT THAT CUR PREVENTIVE MAINTEN ANCE PROGRAM & FTE-53. THAT RELATES'TO WESTINGHOUSE INSTRUCTIDH 33-790-1 B SECTION 9.3.2, IS SUFFICIENT TO MINIMIZE THE ABOVE PROBLEM.
l-05000298 110979
. TECHNICAL-SPECIFICATION 4.5.F.'1 WAS HDT MET. IN THAT OH HOVEMBER 9.
1979-
'C00PER-1 79-033/03L-0' 30-DAY PERFORMED OH #1 DIESEL GENERATOR FOR 82 DIESEL GENERATOR BEING IHOPERABL.
EMERG GENERATOR SYS + CONTROLS 12C679 SURVEILLANCE PROCEDURE 6.3.12.1, DIESEL GENERATOR OPERABILITY, WAS NOT-ENGINES. INTERNAL' COMBUSTION 027805
~ THIS OCCURREHCE PRESENTED HO ADVERSE CONSEQUENCES FROM THE STANDPOIN.
SUSCOMPONENT NOT APPLICABLE E.
PERSONNEL ERROR T.0F.PUBLIC HEALTH AND SAFETY.
~ ~ ~
LICENSED 1 SENIOR OPERATORS COOPER ENERGY SERVICES 0800-1600 SHIFT FAILED TO PERFORM THE< REQUIRED OPERABILITY TEST FOR 91 D l-G BEING UNDER THE IMPRESSIGH #2 DG WOULD BE MADE OPERABLE. FOLLOWING DA.
Y, UPON ASSUMING WATCH THEY REALIZED REQUIRE 3 OPERABILITY TEST HAD NOT B EEN PERFORMED FOR #1 DG AND IMMEDIATELY PERFORMED THE REQUIRED TEST SATI-SFACTORILY. OCCURRENCE BEING DISCUSSED WITH OPERATIDHS PERSONNEL.
l
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- FEB'07,J1980_
+
,.LER'0UTPUT'ON REPORTS RECEIVED FROML12/31/79 THRU.01/13/80a OUTPUT' SORTED BY FACILITY;AND:EVENTJDATE-
'PAGE 11'c.;
1 :
e q
t FACILITY / SYSTEM /L
.... : DOCKET: NO./i EVENT' DATE/.
' COMPONENT / COMPONENT.SUSCODE/-
E
- COMPONENT MANUFACTURER!
CONTROLz NO. REPORT-TYPE ~
~ EVENT. DESCRIPTION /
. CAUSE/CAUS E :SUSCODE/ : -.
, LER NO./ -.. REPORT DATE/'
!CAUSE DESCRIPTION:
n-
., 1:..
~05000302' 112079 AT 0050.FOLLOWING ROUTI. E' SAMPLING OF THE PRESSURIZER DISCOVERED. CHEMICAL
.. CRYSTAL' RIVER-3
~
L ;CNTNMNTKISOLATION!SYSi+ CONT 5 79-107/03L-0 121279
,L ADDITION ISOLATION VALVE CAV-2 WOULD NOT.CLOSE CONTRARY TO TECN. SPEC.i
- VALVESL 027855' 30-DAY
?3.6.3.1.
CAV-2 WAS' CLOSED MANUALLY AND THE VALVE OPERATOR WAS DISABLED L. ? GLOBE 1
.. ~ -..
.m FIFTH OCCURRENCE REPORTED.FOR.CAV-2.. REFERENCE.LER 77-36,178-14, 79-
- DESIGN / FABRICATION ERROR' 37, AMD.79-105.
-DESIGN.
I-
- ROCKWELL MANUFACTURING.CO.
ATTRIBUTED TD INADEQUATE DESIGN.. ENGINEERING EVALUATION RESULTED~IN IMS~
i i
TALLATION OF A' MODIFICATION WHICH PROVIDES PHEUMATIC ASSIST DURING-VALVE 1
-CLOSING. ' MODIFICATION COMPLETED.AND CAV-2 RETURNED TO SERVICE.AT-1715=
ON.12/4/7 9'.
~
05000302
- 120179
- AT 0050, DURING ROUTINE POWER 0PERATION,EIT WAS: REPORTED THAT EMERGENCY-
-CRYSTAL RIVER-3'.
79-108/03L-0 122179 DIESEL-GENERATOR 18 STANDBY COOLING PUMP DJP-4'HAD FAILED' CONTRARY TO TE.
+
- EMERG GENERATOR SYS + CONTROLS, "
027856 30-DAY CN. SPEC. 3.8.1.1.
REMAINING AC SOURCES WERE VERIFIED OPERABLE. THIS I
- EN3INES, INTERNAL COMBUSTION S.TNE FIRST OCCURRENCE OF' THIS TYPE REPORTED.-
~
~
-SUBCOMPONENT NOT. APPLICABLE
-CIMPONENT FAILURE)
-NATURAL END'0F' LIFE-
> FAIRBANKS MORSE-BEARING FAILURE 10N1 STANDBY CCOLING PUMP. ' REPAIRED STANDBY COOLING PUMP,
j'.,-.
. AND: EMERGENCY DIESEL' GENERATOR 1-5. RETURNED T0 - SERVICE ' AT 0730. - SUBSEGU:
ENT INSPECTION OF EMERGENCY DIESEL' GENERATOR 1-A RESULTEDlIN BEARING REP LACEMENT ON DJP-3.
"D.1C.
05000315 120179~
DURING 'THE INVESTIGATION OF A HIGH : STEAM ' GENERATOR LEVEL 1 INDICATION, FOR
~, REACTOR TRIP SYSTEMS 79-064/03L-0 122779
' CHANNEL--I-LOOP 4, TRANSMITTER BLP 141 WAS FOUND TO ben 13 PERCENT.OUT 0F I'
. INSTRUMENTATION + CONTROLS
.027763 30-DAY.
SPECIFICATION HIGH. THIS CONDITION WAS NON-CONSERVATIVE ~WITH RESPECT T" TRANSMITTER O T.S.1 TABLE 2.2-1 ITEM 13 AND TABLE 3.5-1 ITEM.14.. ACTION REQUIREMENTS '-
- COMPONENT. FAILURE' 0F T.S. TABLE 2.2-1 ITEM 13'AND-TABLE 3.5-1 ITEM 14 WERE FULFILLED.'
4
' INSTRUMENT (BARTONLINSTRU'CO., DIV 0F ITT THE-TRANSMITTER:(BLP-141) COULD NOT BE BROUGHT.BACK'INTO' SPECIFICATION'A.
I ND WAS' REPLACED. THE DEFECTIVE-TRANSMITTER WAS SENT TO BARTON FOR EVALU' ATION OF CAUSE OF THE FAILURE AND. REPAIR. ~THIS INVESTIGATION WILL.REMAI 4
N OPEN.AHD A. SUPPLEMENTAL LER WILL BE SUBMITTED WHEN AN ANSWER'IS'RECEIV2 ED FROM BARTON.'
lD. C. C00K-2 05000316 110279 DURING SURVEILLANCE INSPECTION PER T.S. 4.6.5.9, THE -ICE CONDENSER DIVID CNTHMHT HEAT REMOV SYS +' CONT' 79-043/03X-1 122479 ER BARRIER SEAL WAS:FOUND TO HAVE CRACKS IN THE. RUBBER. IN SOME AREAS,'...
OTHER COMPONENTS.
027492.
OTHER.
-THE CRACKS DID PENETRATE THE SEAL. HOWEVER.THE MAJOR PORTION OF1THE' SEA
^.-SUDCOMPONENT. HOT APPLICABLE-L: INTEGRITY REMAINED INTACT. THE EVENT DID NOT' JEOPARDIZE PUBLIC HEALTHL
. UNIROYAL,'INC.
. 0503.15.
79-029/03L-0, DOCKET N0' i "" DESIGN / FABRICATION ERROR AND SAFETY. A SIMILAR EVENT'WAS REPORTED AS RO ~
~
-CONSTRUCTION / INSTALLATION'
~
{
THE CRACKING OF'THE SEAL MATERIAL WAS DUE TO EXCESSIVE COMPRESSION'0F TH E-MATERIAL DURING INSTALLATION. REINSTALLATION OF THE SEAL RING WAS PER~
FORMED IN A MANNER WHICH' LIMITED THE COMPRESSION OF 'THE MATERIAL-DURING.
e THE BOLTING PROCEDURE.
i l
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/
1FEB 87, 1980.
'LER 0UTPUT DN REPORTS RECEIVED ~FROM:12/31/795THRU'01/13/80' PAGE"12E -
. 0UTPUT. SORTED BY. FACILITY AND EVENT DATES ~
tFACILITY/ SYSTEM /E COMPONENT /CDMPONENT.SUSCODE/-
DOCKET'NO./ EVENT DATE/.
YE
' CAUSE/CAUSE SUBCODE/ :.
LER NO./-.
. REPORT,DATE/'
~
- EVENT DESCRIPTION /.-
1 COMPONENT, MANUFACTURER CONTROL.MO. REPORT TYPE.
CAUSE DESCRIPTION'
- ENGNRD SAFETY -FEATR INSTR. SYS -
, 05000316J. 111979
.WITN REFUELING IN: PROGRESS SOURCE RANGE' NEUTRON. FLUX MONITOR (N-31)$5ECA
^
D..C. C00K -.. -...
- 79-046/03L-0,121979-
- MEsERRATIC AND WAS DECLARED INOPERABLE.LTHIS.IS' MON-CONSERVATIVE IN RESP. ^
INSTRUMENTATION += CONTROLS 1027762
30-DAY ECT-TO T.S."3.9.2. ALL CORE ALTERATIONS'WERE> TERMINATED AS REQUIRED BY TT HE ACTION REQUIREMENT. -PREVIOUS OCCURRENCES INCLUDE R0-950-315/77-393;7 1 OTHER'
.8-55;'R0-350-316/78-81, 91.
4 COMPONENT / FAILURE 3
~ Es
-ELECTRICAL ~
- WESTINGHOUSEiELECTRIC: CORP.
CAUSE' WAS DETERMINED T3 BE EXCESSIVE' MOISTURE.IN ' DETECTOR ' WELLS.." BOTH S OURCE. RANGE DETECTORS 8 THEIR-SPARES MERE FOUND-.TO BE SOAKED.. MOISTURE-
.WAS ALSO FOUNDsIN: CABLES FOR N-32.
2 NEW DETECTORS ~WERE INSTALLED,'ALL' DETECTORS WERE CLEANED,, DRIED & WATERPR00 FED PRIOR TD. REASSEMBLY. TEMPO' RARY CABLES.USED DURING REFUELING 4 LATER REPLACED BY'PERMANENTcCABLES.
D. C. E C00K-2 '
05000316 112479 DURING THE CALIBRATION 0F GRID DEGRADED VOLTAGE" RELAYS,JRELAY-NUMBER 27,
~.ENGNRD' SAFETY FEATR INSTR'SYS
. 79-047/03L-0 121979 1-201-AB-DROPPED 0UT AT:A VALUE CORRESPONDING TO 21.9 KV. <THIS.IS-NON-C.
. INSTRUMENTATION + CONTROLS-
' '027761 30-DAY
- ONSERVATIVE.IN. RESPECT. 70 T.S. c TABLE 3.5-5. ITEM. S.B' REQUIREMENTS..
, SWITCH ^'
COMPONENT FAILURE ELECTRONIC.
. GENERAL: ELECTRIC ~CO.
INVESTIGATION. REVEALED THAT A.ZENER' DIODE HAD FAILED IN THE AFFECTED RELL AY,3 MANUFACTURED'BY GE-MGV13A11A. THE ZENER DIODE WAS REPLACED AND TME1.
RELAY WAS CALIBRATED TD THE: PROPER,SETPOINTS. NO FURTHER ACTIONS ARE'RE'
? QUIRED AS A RESULT 10F THIS EVENT.
D. C. C00K -
05000316 120179 WHILE-INEMODE f,'WITH. REFUELING' COMPLETE,-THE CONTAINMENT' AIR PARTICULAT i.
AIRBORNE RADI0ACT MONITOR' SYS -
79-048/03L-0 122779 E AND AIR GASEOUS SAMPLE PUMP TRIPPED WITH.A CONTAINMENT PURGE IN PROGRE:
- VALVES
' 027760-
~30-DAY SS. 'THE: CONTAINMENT PURGE-AND EXHAUST-WAS ISOLATED AS REQUIRED BY T.S.2
'~ GLOBE TABLE _3.3-6 ACTION REQUIREMENTS 20'AND 22, AND T.S. 3.9.9.
OTHER i
NOT APPLICABLE 1
' WESTINGHOUSE ELECTRIC ~ CORP.
~
INVESTIGATION ~ REVEALED THAT S AMPLE PUMP-BYPASS VALVE WAS FOUN1*
- CLOSED,1 C..
l REATING HIGH FLOW CONDITION 4' TRIPPED SAMPLE PUMP- ~ PUMP WAS. RESTARTED-1
~
BYPASS VLV WAS ADJUSTED FOR PROPER FLOW.
CAUSE FOR VLV BEING SHUT HAS.
i I
NOT BEEN DETERMINED. ' HO FURTHER. ACTION -IS PL ANNED SINCE A: T.S. CHANGE Wi oAS-SUBMITTED:TO'NRC ON~ 12-28-78 TO CHANGE APPLICABILITY OF.T.S. 3.9.9.
D.' C. C00K-2 05000316 121879 DURING: INSPECTION-IN RESPONSE TO IE BULLETIN 79-14, A SIGNIFICANT DISCRE--
-CHEM,'VOL CONT + LIQ'POISN SYS.
79-049/01T-0 '123179 PANCY;WAS NOTED IN.THE AS-BUILT CONDITION OF Art" DIAMETER AUXILIARY PIP 1 COM70NENT CODE; HOT-4PPLICABLE 027768 2-WEEK E-(CONNECTED BETWEEN REACTOR COOLANT PIPING AT DISCHARGE N0ZZLE OF-REACT SUBCOMPONENT NOT APPLICABLE-OR COOLANT PUMP AND EXCESS LETDOWN HEAT-EXCHANGER)'
CAUSE WAS THAT "AS-:
DESIGN / FABRICATION ERROR BUILT"-LENGTH OF PIPE WAS ABOUT 3 FEET LONGER THAN THAT SPECIFIED.IN THE.
CONSTRUCTION / INSTALLATION MATHEMATICAL MODEL.
ITEM NOT APPLICABLE PIPE CONNECTION WOULD BE OVERSTRESSED DURING BOTH OBE AND DBE SEISMIC EV ENTS.
TW0' ADDITIONAL -RESTRAINTS WERE INSTALLED WHICH CORRECTED THE PROB LEM.
o
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9 LER'0UTPUT ON' REPORTS RECEIVED FROM 12/31/79 THRU ' 01/13/80.
'/PAGEE13; '..,
(FEB 07 1,980';
1
~
0UTPUT SORTED BY. FACILITY AND EVENTiDATE l
're 1 FA'CILITY/SYST EM/ '
. : DOCKET NO./ ' EVENT DATE/-
~
CCOMPONENT/ COMPONENT-SUBCODE/? _
s
.LER MO./
REPORT /DATE/
- EVENTLDESCRIPTION/S 5
ECAUSE/CAUSE;5UBCODE/
+
c.
s JCOMPONENT' MANUFACTURER 3
-CONTROL'HO. REPORTaTYPE
-CAUSEEDESCRIPTION?
" ^
' m
~l
- AC ONSITE-POWER
- SYS + CONTROLS..
05000346 110579 AT 1320 HOURS THE UNIT < EXPERIENCED A LOSS.0F ' ESSENTIAL' INSTRUMENTATION D
- DAVIS-BESSE-1'9:..,~...
.. J79-107/03L-1 :120479 ISTRIBUTION. PANEL Y2.
BEING 'IN MODE 5, THE UNIT DID NOT ENTER THE ACTIO 7 1
>SUBCOMPONENT NOT'APPLICABLEi 30-DAY
.N STATEMENT - OF TECHNICAL. SPECIFICATION 3.8.2.2,~ AS IT. ONLY : REQUIRES THRE '
EELECTRICAL' CONDUCTORS 027478
-E OF THE 120-VOLT AC ESSENTIAL BUSES OPERABLE..THIS OCCURRENCE'IS BEINGL REPORTED TO DOCUMENT A COMPONENT FAILURE. i(NP-33-79-122)..
.t:
VCOMPONENT'FAILUREc 1
U
--ELECTRICAL' CYBEREX INC.
. THE : LOSS OF Y2 WAS FOUND TO BE' CAUSED BY. AN OPEN RESISTORLIN,THE2 LOGIC :V :
OLTAGE SUPPLY TO THE SILICON CONTROLLED RECTIFIERS (SCRS)..THE OPEN RESK 1
S ISTOR RESULTED 'IN 'SHORT CIRCUITING THE DC BUS DUE T0 tTHE FIRING OF.TNE. 5 -
h CRS.
THE. INVERTER:WAS REPAIRED, AND ON NOVEMBER 8,'1979, THE INVERVER W:
AS. TESTED AND RETURNED TO SERVICE.
?
J... DAVIS-BESSE.
'05000346 L110979 AT!1400'DURING REVIEW OF HRC-IRE BULLETIN 79-21 RESPONSE DISCOVERED'STE-FEEDWATER SYSTEMS.+ CONTROLS
?79-105/01T-1 112179 AM GENERATOR LOW LEVEL TRIP SETPOINTS TO-STEAM AND FEEDWATER RUPTUREICON?
INSTRUMENTATION + CONTROLS'
,027423 2-WEEK
. TROL SYSTEM CHANNELSu1 AND 2 WERE LESS CONSERVATIVE' THAM LIMITS OF T.S.
s i
SENSOR / DETECTOR / ELEMENT L3.3.2.2.. REPORTED IN ' ACCORDAME WITH T.S. 6.9.1.8.N.
MODE 3iRESTRAINT.P-
= DESIGN / FABRICATION.ERRCR-LACED 0N L THE UNIT UNTIL-NEW VALUES WERE DETERMINED AND ADJUSTMENTS MADE.
. DESIGN
'A SAFETY ANALYSIS IS BEING MADE AND WILL BE FORWARDED-AS-A REVISION.';(-
- COSMODYMEs
'NP-32-79-12)
~
ERROR IN METHOD USED IN DETERMINING STEAM GENERATOR LOW LEVEL ~ BISTABLE S ETPOINTS WHICN. FAILED TO-TAKE.INTO ACCOUNT ACTUAL PRESSURES AMD TEMPERAT' URES SEEN BY'$ TEAM GENERATOR LEVEL TRANSMITTER.
ON'.11/12/79 ADJUSTMENTS a
i MADE, AND TEST SUCCESSFULLY ' PERFORMED.'
b. DAVIS-BESSE-1 79-121/03L-0 122879.
- THAN THE GROUP AVERAGE. PLACING UNIT IH ACTION STATEMENT-OF:T.S.'3.1.3.2=
05000346 113079 AT 0620 WHILE MOVING. GROUP 8 RODS, ROD 8-1 WAS INDICAT'ING ABOUT.8% LOWER:
- . 0T HR ' INST " SYS ' REQD.. FOR ' S A FETY; INSTRUMENTATION +~ CONTROLS-027915 30-DAY WHILE RESTORING ROD 8-1 TO WITHIN 6.5% OF THE GROUP
- AVERAGE, THE POSI,
. INDIC ATOR ' '
TION INDICATION JUMPED: BACK UP TD - AGREE: WITH THE GROUP AVERAGE. CONTROL:
COMPONENT. FAILURE' ROD NEVER DEVIATED FROM ITS INTENDED POSITION. ONLY.THE POSITION INDIC L
. INSTRUMENT.
ATION WAS-FAULTY.
(HP-33-79-138).-
1 DIAMOND POWER SPECIALTY CORP.
THE CAUSE OF 'THIS OCCURRENCE WAS A FAULTY METER MOVEMENT.FOR THE ROD POS '
ITION INDICATION.ON CONTROL ROD 8-1.
AFTER'THE REACTOR: SHUTDOWN'ON DECE<
MBER 2, 1979,.THE' METER-MOVEMENT FOR' ROD 8-1' POSITION INDICATION WAS-REM.
OVED AND A NEW' METER WAS' INSTALLED.
LEDWIN Ii HATCH-1
'05000321 112679
'DURING NORMAL PLANT OPERATION' DISCOVERED-SURVEILLANCE PROCEDURE HNP-1-37.
- h
,DC_0NSITE POWER SYS-+5 CONTROLS 79-095/03L-0 121479 52, BATTERY INDIVIDUAL CELL SURVEILLANCE, NOT-PERFORMED ON REQUIRED DATE-
" BATTERIES'+ CHARGERS 027782 30-DAY 11/26/79. AS SPECIFIED BY T.S. 4.9.A.3.
B. PROCEDURE
HHP-1-3752 PERFORM.
2 -
SUBCOMPONENT.NOT APPLICABLE
-ED 11/27/79. 8 ALL BATTERY CELL FOUND SATISFACTORY. NO EFFECT ON SAFE P-j ' 'LPERSONNEL' ERROR-LANT OPERATIONS. PUBLIC HEALTH OR SAFETY NOT AFFECTED BY INCIDENT.
SIM' MAINTENANCE 8: REPAIR PERSONNEL ILAR OCCURRENCE, CONCERNING A MISSED. BATTERY < SURVEILLANCE, WAS REPORTED' ITEM NOT: APPLICABLE =
OH REPORTABLE.0CCURRENCE-REPORT' 50-366/1979-89.
t MONTHLY SURVEILLANCE, HNP-1-3752, NOT PERFORMED ON REQUIRED DATE DUE TO:
PERSONNEL-0VERSIGHT. ON DISCOVERY.' MISSED SURVEILLANCE IMMEDIATELY-PERF ORMED 8 FOUND SATISFACTORY ON' 11/27/79. METHOD OF NOTIFYING RESPONSIBLE i
' PERSONNEL THAT SURVEILLANCE IS DUE HAS.BEEN REVISED & RESPONSIBLE PERSO 2
HNEL CAUTIONED AS TO IMPORTANCE OF? SURVEILLANCE.
~~
4 h
M
-se_
FEB.07,619801 LER.0UTPUT ON. REPORTS' RECEIVED FROM: 12/31/79 THRU 01/13/80 PAGE.14l 4
,0UTPUT SORTED BY-' FACILITY.AND EVENT DATE-FACILITY / SYSTEM /
. COMPONENT / COMP 0HENT SUBCODE/
DOCKET NO./. EVENT DATE/
CAUSE/CAUSE SUBCODE/ r
~LER NO./.
REPORT DATE/
EVENT DESCRIPTION /
COMPONENT MANUFACTURER CONTROL NO. REPORT TYPE CAUSE DESCRIPTION LEDWIN'I. HATCH-1 05000321 1120679 WITH REACTOR IN RUN MODE, WHILE PERFORMING PROCEDURE HNP-1-3605 '0FF-GAS GAS RADI0ACT.WSTE MANAGMNT SYS-79-099/03L-0 122779-SYS AUTO ISOLATION VALVE OPERABILITY, STACK-INLET VALVE, 1N62-F527,: FAI.
- VALVE-OPERATORS.-
027777-
~.30-DAY
-LED IN CLOSED POSITION. ENVIRON TECH SPEC 2.1.3.D REQUIRES THIS. VALVE B:
ELECTRIC MOTOR - AC E OPERABLE-IH AUTO MODE.
REACTOR POWER REDUCED FROM,2430 MWT TD 2144 MW
- COMPONENT FAILURE
~
T DUE TO SLIGHT BACK PRESSURE DEVELOPING IM OFF-GAS SYSTEM.
1N62-F527 VJ ELECTRICAL'..
'ALVE MANUALLY OPERATED TO RELIEVE PRESSURE. THIS WAS NOT A REPETITIVE 0:
LIMITORQUE CORP.'
-CCURRENCE AND THERE WERE NO EFFECTS TO PUBLIC HEALTH AND SAFETY.
THE FAILURE OF THE 1N62-F527. VALVE TO OPEN WAS DUE TO A LIMIT' SWITCH IN THE CONTROL CIRCUIT NOT2 MAKING PROPER CONTACT. -THE LIMIT SWITCH WAS API USTED AND PROCEDURE HHP-1-3605 PERFORMED SATISFACTORILY ON. DECEMBER 6, l'
979.
'EDWIN:I. HATCH-1 05000321 121079 FAILURE TO CONSIDER RCIC SYSTEM IHOPERABLE AFTER A TRIP ON HIGH TURBINE
-REAC CORE ISOL1C00L SYS + CONT 79-098/01T-0 121979
. EXHAUST PRESSURE OH 12-8-79.
THEREFORE, THE ::PCI SYSTEM WAS-NOT PROVEN TPUMPS
~
027818
~ 2-WEEK OPERABLE AS REQUIRED BY.T/S 4.5.E.2.
ALSO, T/S SECTION 3.5.E.3 WAS NOT
. CENTRIFUGAL COMPLIED WITH.
A PREVIOUS EVENT OF THIS NATURE WAS REPORTED ON LER 50 ' PERSONNEL ERROR
-21/79-066.
RCIC TRIP OCCURRED WHILE IN USE FOR FEED DURING STARTUP. TR LICENSED & SENIOR OPERATORS' IP WAS DUE TO MANUAL STOP CHECK VALVE E51-F001 BEING CLOSED.
IT'APPEARE' ITEM NOT APPLICABLE.
D TO HAVE VIBRATED-SHUT =AFTER A LOCK OH.THE HANDWHEEL BROKE.
CAUSE OF' EVENT WAS DUE TO AN OVERSIGHT"BY OPERATING PERSONNEL ON SHIFT T 0 DECLARE RCIC SYSTEM INOPERABLE WHEN SYSTEM -TRIPPED ON HIGH TURBINE' EXH AUST PRESSURE. PERSONNEL INVOLVED IN OCCURRENCE WERE ADMINISTRATIVELY R>
ELIEVED OF THEIR LICENSED. DUTIES AND WERE EVALUATED AT THE COMPLETION OF-A. TRAINING AND SELF-STUDY PROGRAM.
'EDWIN I. HATCH-1 05000321 121179
-DURING STEADY STATE POWER OPERATION, CBSERVATIDH OF RHR "B" LOOP HE*T EX RESIDUAL HEAT REMOV SYS + CONT 79-100/03L-0 122079 CHANGER PRESSURE INDICATOR E11-R606B BY LICENSED OPERATOR IN CONTROL R00
, VALVES-;
~.
0277:o 30-DAY M SHOWED HEAT EXCHANGER BEING PRESSURIZED. INVEST. SHOWED IF LPCI DUTBO' GATE '
ARD IHJECTION VALVE E11-F017B WAS CLOSED, PRESSURIZATION OF. HEAT EXCHANG COMPONENT FAILURE ER WOULD CEASE. -THUS, LPCI CONTAINMENT ISOLATION VALVE E11-F015B WAS DE MECHANICAL
.TERMINED TO BE LEAKING. SIMILAR EVENT DCC ON THE RHR "A" LOOP: REFER T CHAPMAN DIV 0F CRANE CO.
O RD-REPORT HO. 50-321/1979-012.
NO EFFECTS CH PUBLIC HEALTH OR SAFETY.
IHITIAL CORRECTIVE ACTION WAS TO CLOSE Ell-F017B VALVE & DECLARE RHR "B" LOOP'INOP. 'LATER, WAS DECIDED IT WAS1 PERMISSIBLE TO OPERATE WITH E11-F-017B VALVE CLOSED 8 STILL BE ABLE TO CONSIDER "B" LOOP OPERABLE:
E11-F0.
ISB VALVE.WAS TO BE REPAIRED HEXT COLD SHUTDOWN. OH 12/15/79 UNIT PLACE D IN COLD SHUTDOWN DUE TJ GROUND PROB IN MAIH GENERATOR, VLV REP STARTED EDWIN I. HATCH-1 05000321 121279 WITH REACTOR'IH RUN MODE, 12/12/79 & AGAIH 12/13/79,
'C' DIESEL GENERATO EMERG GENERATOR SYS +. CONTROLS 79-101/03L-0 010380 R,
IR43-5001C, FAILED TO START WITHIN 7 SECONDS WHILE PERFORMING PROCEDU-ENGINES, INTERNAL COMBUSTION 027772 30-DAY RE HNP-1-3801, D/G MANUAL START.
'C' DIESEL WAS'BEING RUN TO COMPLY WIT SU3 COMPONENT NOT APPLICABLE H TECH SPECS 4.5.B'2 3 4.5.J.2.
THIS DIESEL ALSO FAILED OH.12/16/79 WIT COMPONENT FAILURE.
H REACTOR IN COLD SHUTDOWN.
'C' DIESEL DECLARED' INOPERABLE AFTER EACH I-
-~
MECHANICAL HCIDENT 4. PREPARATIONS MADE TO COMPLY WITH TECH SPECS 3.5.B.3 & 3.5.J.2.
FAIRBANKS MORSE AFTER THE.FIRST 2 INCIDENTS. LER-366/1978-60 IS SIMILAR EVENT.
AFTER START FAILURE OH 12/12/79. DIESEL WAS STARTED FROM LOCAL STATION W HICH BYPASSES.THE 7 SECOND CONTROL CIRCUIT. AFTER 1R43-S001C WAS SHUTDO.
WH, IT WAS SUCCESSFULLY RESTARTED FROM REMOTE STATION & HNP-1-3801 PERF0 RMEP SATIS. WHEN DIESEL FAILED 12/13/79, THE GOVERHOR BOOSTER SERVO WAS
- DISASSEMBLED,. CLEANED & REINSTALLED. AFTER 3RD FAILURE, SERVO REPLACED 7
i
\\,g.
'LER OUTPUT ON REPORTS-RECEIVED FROM 12/31/79 THRU-01/13/80 lPAGE 15j i J
!FEB 07,'1980 OUTPUT SORTED BY. FACILITY AND EVENT DATE' FACILITY / SYSTEM /
COMPONENT / COMP 0HENT SUBCODE/
DOCKET NO./ EVENT DATE/-
CAUSE/CAUSE SUBCODE/
LER HO./
REPORT DATE/
EVENT'DESCRIPTIOM/.
/ COMPONENT MANUFACTURER CONTROL HO. REPORT TYPE CAUSE DESCRIPTION' lt s
EDWIN I. HATCH-1 05000321 121679 WITH THE REACTOR IN THE SHUTDOWN MODE, WHILE PERFORMING PROCEDURE HHP..
STATION. SERV. WATER SYS + CONT-79-104/03L-0 -010280
-3801 DIESEL GENERATOR MANUAL START, 2P41-C002,~ STANDBY DIESEL SERVICE W PUMPS 027773 30-DAY ATER PUMP. TRIPPED. ~ TECHNICAL SPECIFICATION 3.5.J.2 WAS NOT REQUIRED DU CENTRIFUGAL".
E TO THE PL ANT BEING SHUTDOWN FOR MAINTENANCE. PUBLIC HEALTH AND SAFETY-I'
-COMPONENT FAILURE WERE NOT AFFECTED BY THIS INCIDENT. THIS WAS NOT A REPETITIVE OCCURREM METALLURGICAL CE.
'JOHNSTON PUMP CO.
~
OVERLOAD. ON INVESTIGAT'
- CAUSE OF'2P41-C002 MOTOR TRIP DUE TO MECHANICAL l '
IDH OF PROBLEM, DISCOVERED A HUMBER OF BOLTS USED TO ASSEMBLE SUCTIDH BE LL, INTERMEDI ATE BOWLS & DISCHARGE CASE OF PUMP HAD DETERIORATED & BROKE i
L H LODSE CAUSING MISALIGHMENT OF PUMP. SHAFT.
THERE WAS ALSO EVIDEHCE.0F WEAR TO SEAL RINGS, BOWL BEARINGS & PUMP. SHAFT.- REPAIRS MADE.
IDWIN'I. HATCH-1 05000321 122879 OH 12-18-79, WITH UNIT 1 REACTOR IN COLD SHUTDOWH, A VISUAL INSPECTION O REACTOR CONTAINMENT SYSTEMS
.79-105/OlT 010480 F TORUS INTERNALS WAS PERFORMED. POSSIBILITY OF A DEVIATION FROM DESIGN 6
HANGERS, SUPPORTS, SHOCK SUPPRSS
-027846-2-WEEK WAS NOTED BY CONTRACT PERSOHHEL & REPORTED TO ARCHITECT ENG. ON 12-23-79 23 PLANT PERSONNEL VERIFIED BRACE BETWEEN LEGS OF VENT LINE DOWNCOMER HE -
OTHER AR MAIN STEAM RELIEF VLV DISCHARGE LINE *L" WAS MISSING. ' 0H 12-26-79, IT l0THER NOT. APPLICABLE WAS DETERMINED THAT THIS SITUATION WAS REPORTABLE. 12-27-79 IT WAS DETE-CHICAGO BRIDGE & IRON COMPANY RMINED 4 OTHER VENT LINE DOWHCOMERS WHICH.HAD MOD BRACES WERE IMADEQUATE CAUSE OF THIS EVENT IS UHKHOWN AT PRESENT. MODIFIED BRACES HAVE BEEN IN STALLED IN ALL LOCATIDHS WHERE A' BRACE WAS MISSING OR WAS. DEEMED INADEQU ATE.
THE LACK OF ADEQUATE BRACES ON THE DOWHCOMERS COULD HAVE CAUSED FA ILURE OF.THE DOWHCCMERS IH EVENT ON A DESIGN BASIS ACCIDENT.
05000366 060279 WHILE PERFORMING HORMAL SURV. ON B DIESEL GEN. IT WAS' DISCOVERED THAT'80 EDWIN I.. HATCH-2 79-047/03X-1 010780 TH STRAINERS WERE ISOLATED ON-STANDBY PSW PUMP THEREBY ISOLATING PSW TO STATION SERV WATER SYS + CONT VALVES 026151
'OTHER B DIESEL GEN. COOLING SYSTEM. THIS CONDITIDH EXISTED FROM 5-26-79 WHEN S, YS VALVE LINEUP WAS PERFORMED UNTIL 6-2-79 WHEN CONDITION WAS NOTED & CO BUTTERFLY RRECTED. B D/G WAS THEREBY RENDERED IHOPERABLE 102 THIS PERIOD OF TIME..'
DESIGH/ FABRICATION ERROR CONSTRUCTIOH/ INSTALLATION ORIGIHAL LER (DATED 6-18-79) DID HOT REPORT THAT D/G WAS IHOPERABLE BETW PRAVT, HENRY CO.
EEN 5-26-79 8 6-2-79.
THERE ARE'2 ISOLATION VALVES FOR EACH OF THESE STRAINERS. 1 0F THE STRAI-i HER ISOLATION VALVES CLOSES IN CLOCKWISE DIRECTIDH & OPENS IN CCW DIRECT.
IDH WHILE OTHER STRAINER ISOLATI0H VALVES OPERATE JUST THE OPPOSITE'. THI 5 LED OPERATOR THAT WAS LIMING UP VALVES TO BELIEVE VALVES THAT OPERATED IN OPPOSITE DIRECTIDH WERE OPEN WHEN THEY INDICATED CLOSED.
EDWIH I. HATCH-2 05000366 111479 OH 11/14/79,.DURING A ROUTIHE REVIEW 0F PREVIOUS LIQUID RADWASTE DISCHAR LIQ RADIDACT.WSTE MAHAGMNT SYS 79-125/04L-0 121279
.GES, DISCOVERED THAT, OH 11/7/79. WHILE'AT 0 MWT POWER, MINIMUM RECIRC T
-PUMPS 027794 30-DAY INE PRIOR TO SAMPLING & ANALYSIS AS REQ BY E.T.S. - SECT. - 2.1.2.C, NOT MET '
0THER OH UNIT II CHEMICAL WASTE SAMPLE TAHK A.
5548 GAL OF THIS' TANK WAS SUB 1
COM?0HENT FAILURC SEQUENTLY DISCHARGED TO ALTAMAHA RIVER. SIMILAR EVENT OCC OH THIS TAHK MECHANICAL-DURING POWER OPER AT 2399 AT 2399 MWT 11/21/79 1 70 GAL WAS: DISCHARGED T 4
CRAHE DEMING PUMPS 0 RIVER. NO SIGNIFICANT DISCHARGES TOOK PLACE.
IN BOTH EVENTS INSPECTION OF PUMP USED FOR BOTH RECIRC & DISCHARGE, REVE I
ALED THE IHLET STRAINER HAD BECOME CLOGGED WITH SMALL BITS OF PAPER WHIC 4
H REDUCED THE FLOW CAPACITY OF THE PUMP.
THE STRAIHER WAS CLEAHED AND T HE PUMP RETURHED - TO SERVICE. THE PUMP IS HOW IN FULL COMPLIANCE WITH-TH E REQUIREMENTS AND HO FURTHER REPORTING IS REQUIRED.
t
s
~:
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~
,' 'FEB 07,t1980_~
-LER 0UTPUT ON REPORTS RECEIVED FROM. 12/31/79 THRU 01/13/80' PAGEi16.
OUTPUT SORTED.BY FACILITY AND EVENT DATE FACILITY / SYSTEM /
. COMPONENT / COMPONENT SUBCODE/. ' DOCKET NO./ EVENT DATE/.--
^
CAUSE/CAUSE SUBCODE/..
LER HO./
REPORT DATE/ -
. EVENT DESCRIPTION /
- COMPONENT MANUFACTURER -
CONTROL-NO. REPORT TYPE CAUSE DESCRIPTION
~
.EDWIM-I. HATCH-2 05000366 112179-WITH REACTOR IN RUN. MODE,.WHILE PERFORMING PL ANT SERVICE WATER PUMP OPER STATION. SERV. WATER SYS + CONT
'79-126/03L-0 121479 ABILITY TEST, HNP-2-3182, PLANT' SERVICE WATER PUMP 2P41-C001D WOULD NOTI.
- 7 UMP S -
027780-
.30-DAY.
MEET -THE ASME SECTION II REQUIREMENTS AS REQUIRED BY TECH SPECS. 'SECTION 0THER' 4.0.5.
THE PUMP WAS DECLARED IMOPERABLE AHD. A LIMITING CONDITION FOR 0 0THER PERATION ESTABLISHED PERLT.S. SECTION 3.7.1.2.-
A PREVIOUS FAILURE OF A
.NOT APPLICABLE PLANT SERVICE WATER PUMP WAS REPORTED ON LER 79-123.-
PUBLIC HEALTH AND-J0MMSTON PUMP CO.
SAFETY WERE NOT AFFECTED BY THIS' INCIDENT.
FAILURE OF PUMP TO MEET ITS REQUIRED ACCEPTANCE CRITERIA WAS DUE TO A PI' ECE OF METAL BEING DRAWN UP INTO' SUCTION BELL OF PUMP. 'AT THIS POINT TH' E PIECE OF-METAL WAS STRUCK BY 1ST STAGE IMPELLER CAUSING DISTORTION 0F.
IMP EL L ER.' DURING INSPC, DISCOVERED IMPELLER SEAL RINGS:8 PUMP SHAFT BEA' RINGS WORN & HEEDED REPLACING. PUMP REBUILT 8 PLACED BACK IN SERVICE.-
-EDWIN I. HATCH-2 05000366' 112979
.WITH THE REACTOR IN THE RUN MODE,. WHILE PERFORMING PROCEDURE-HNP-2-3303,-
RESIDUAL HEAT REMOV SYS + CONT' 79-129/03L-0 121479 HPCI' PUMP RATED FLOW, THE THERMAL OVERLOADS OF THE HPCI AUXILIARY OIL P PUMPS
~
~
027781
' 30-DAY' UMP BREAKER TRIPPED WHILE THE HPCI TURBINE SPEED WAS BEING DECREASED.
-T GEAR-
~HE HPCI SYSTEM.WAS-DECLARED INOPERABLE AND THE REQUIREMENTS OF TECHNICAL PERSONNEL ERROR
' SPECIFICATION 3.5.1 WERE. COMPLIED WITH...THIS WAS NOT A REPETITIVE OCCU'
' LICENSED & SENIOR OPERATORS RRENCE. PUBLIC HEALTH AND SAFETY WERE NOT AFFECTED BY THIS INCIDENT.=
i' TUTHILL PUMP CO.
FAILURE OF HPCI AUX OIL 1 PUMP DUE TO PERSONNEL ERROR AS HPCI' TURBINE WAS~
HOT TRIPPED AT 2100 RPM AS REQUIRED BY PROCEDURE HHP-2-3303, BUT WAS GRA DUALLY BROUGHT DOWN BY MANUAL CONTROL T10 APPROX 1000 RPM.
THIS CAUSED A:
UX OIL PUMP'TO CYCLE RAPIDLY UNTIL-THERMAL'0VERLOADS IN BREAKER TRIPPED.
AUX OIL PUMP & MOTOR CHECKED FOR DAMAGE & THERMAL OVERLOADS RESET.
EDWIN-I. HATCH-2 05000366 120579 WHILE PERFORMING REACTOR WATER LEVEL (ADS) INSTRUMENT FUNCTIONAL TEST AN-ENGNRD SAFETY FEATR INSTR SYS 79-130/03L-0 122679 D CALIBRATION, HHP-2-3251, 2B21-H042A WAS FOUND TO BE OUT-0F TECH SPECS INSTRUMENTATION + CONTROLS 027776 30-DAY-LIMIT.
THE SWITCH ACTUATED AT 10.2" H2O REACTOR LEVEL;' TECH SPECS LIMIT SWITCH IS:=/> 12.5" H20.
THE SWITCH, 2B21-N042B, IH THE REDUNDANT CHANNEL WAS COMPONENT FAILURE OPERABLE AND WITHIH TOLERANCE. THERE WAS NO EFFECT ON THE ENVIRONS..T.'
INSTRUMENT HIS IS A HDH-REPETITIVE EVENT FOR THIS.IHSTRUMENT. '
GENERAL' ELECTRIC CO.
THE CAUSE OF THE OCCURREHCE'HAS BEEN ATTRIBUTED TO INSTRUMENT DRIFT. TH E. INSTRUMENT WAS CALIBRATED AND A FUNCTIONAL TEST WAS PERFORMED SATISFAC.
TORILY.
EDWIH I. HATCH-2 05030366 120679 WITH REACTOR IN RUN MODE OH 12/6/79. THE TORUS WATER LEVEL WIDE RANGE RE REACTOR TRIP. SYSTEMS 79-131/03L-0 122879 CORDER, 2T48-R607A, FAILED UPSCALE INDICATING A HIGH WATER LEVEL IN TORU VALVES 027774 30-DAY S.
SAME~ EVENT ALSO OCCURRED ON 12/7/79.
DURING BOTH OCCURRENCES REDUND OTHER ANT HARROW RANGE LEVEL RECORDER,.2T48-R607B, INDICATED HORMAL~ LEVEL AS D COMPONENT FAILURE ID THE TWO HARROW RANGE -INDICA 10RS.. THIS WAS NOT A REPETITIVE OCCURRENC' METALLURGICAL
'E IN THAT IT HAD HOT MAPPEHED PRIOR TO DECENBER 6, 1979.
PUBLIC HEALTH.
DRAGON, VALVE, INC.
AND SAFETY WERE HOT EFFECTED BY THIS INCIDENT.
2T48-R607A RECORDER FAILED UPSCALE DUE TO REFEREHCE LEG ON LEVE!
lAHSMI-TTER, 2T48-H021A, HAVING DRAINED. THIS CAUSED OUTPUT TO IHCREASt 8 GIVE-A FALSE HIGH LEVEL INDICATION. OH 12/6/79. THE REFERENCE LEG WAS REFIL LED WHICH CORRECTED THE PROBLEM. 0H 12/7/79. WHEN THE PROBLEM RECURRED, VENT PLUG ON THE MAHIFOLD BLOCK VALVE WAS LEAKING.
LEAK WAS CORRECTED.*
i 4.
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4 s
'4 p'
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7 s
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' LER 0UTPUT'ON REPORTS = RECEIVED FROM 12/31/79;THRU 01/13/80 '
PAGEit7'
. i FEB' 97, :19801 OUTPUT. SORTED.BY FACILITY AND EVENT.DATE -
n
.' FACILITY / SYSTEM /t
~ '
L COMPONENT / COMPONENT -- SUBCODE/ f. DOCKET NO./ EVENT DATE/'
1CAUSE/CAUSE SUBCODE/-
.LER MO./.
fREPORT DATE/-
EVENT: DESCRIPTION /-
?
CCOMPONENT MANUFACTURER; ECONTROL NO.-REPORT 4 TYPE
'CAUSE DESCRIPTION 1 j
t
'05000366" - 121'179
- DURING MORMAL:0PERATION ON 12-6-79,'W/ REACTOR POWER'.AT'2438:MW'T,'NPCI S
- 5
~
EDWIN I'.[NATCH-2 79-133/03L-8? 122779:
~ STEM ISOLATED ON~HPCI EQUIPMENT ROOM VENT AIR DELTA' TEMPERATURE. rTHERE' ~
7
.EMERG'CORELCOOLING.SYS + CONT
' ' '30-DAYJ
' IS NOT ANY -T.S.
SECTION APPLICABLE.T0 ISOL ATION - ACTUATION 'INSTRUMENTATIO f: ' ; INSTRUMENTATION +. CONTROLS 027832'
~
N FOR'HPCI EQUIPMENT ROOM VENTJAIR. DELTA T.-
WEATHER WAS CDLD AT' TIME OF;
-SWITCH-OCCURRENCE 8 SYS-ISOLATED. SYS ISOLATION SETPOINT.IS 40 DEGREES DELTA
- 0THER
- . -.-
T;FOR ISOLATION INSTRUMENTATION 2E41-N601A&B. 'SE R0' REPORT 850-321/1979 NOT' APPLICABLE"
-023 FOR U-1~FOR EVENT OF SIMILAR. NATURE.= REDUNDANT SYS WERE OPERABLE.
- TRANSMATION, INC.
' HPCI SYSTEM ISOLATED IN EQUIP. ROOM VENT; AIR DELTA TEMP. ~SETPOINT FOR I.
l 50LATION INSTRUMENTATION 15.40 DEGREES. / COLD. WEATHER' EXISTING AT TIME 0-IF OCCURRENCE 4 SYS ISOLATED PER DESIGN DUE-TO VEN AIR INLET /0UTLET TEMP.
+
' DIFFERENCE IN: EXCESS 40 DEG.'UPON ISOLATION OF SYS, PLT-OPERATOR TURNED.
ON HPCI ROOM EQUIP. COOLERS & 5YS RETURNED TO NORM. DESIGN CHNG MADE.-
. 05000366'
.121479 WITH THE: REACTOR AT-99% STEADY STATE POWER,'WHILE PERFORMING FISSION PR04
- EDWIN.I. HATCH.
79-134/03L-0 :122879 DUCT INSTRUMENT FUNCTIONAL TEST,: HHP-2-3057, 2D11-K633. FAILED TO GIVE AN AIRBORNE RADIDACT MONITOR SYS-
' 027771 30-DAY INOPERABLE RESPONSE WHEN ITS MODE 5 WITCH WAS TAKEN OUT OF OPERATION. T INSTRUMENTATION + CONTROLS HE OTHER FISSIDH MONITORS,-PARTICULATE AND IODINE, WERE OPERABLE. LTHERE-oCOMPUTATION MODULE-WAS NO EFFECT ON_THE ENVIRONS. THIS WAS A-NON-REPETITIVE EVENT.S~
COMPONENT FAILURE.
s
+
INSTRUMENT- -.
GENERALzELECTRIC CD.
-THE CAUSE OF THE OCCURRENCE HAS BEEN ATTRIBUTED TO A BAD WIRING'CONNECTIS ON IN MONITOR 2D11-K633..THE INSTRUMENT WAS REPLACED'AND SATISFACTORILYs
- tc
. TESTED.
05000366 "121679 WITH REACTOR IN RUN MODE.-WHILE PERFORMING FUNCTIONAL TEST.AFTER MAINTEN:
' EDWIN?I. HATCH-2.
REACTOR CONTAINMENT SYSTEMS 79-136/03L-0 010880
.ANCE ON TORUS' VACUUM BREAKER, 2T48-F323H, TORUS'TO DRYWELL' VACUUM BREAKE-
-VALVES 027847 30-DAY' R, CONTROL LIGHTS FAILED TO GIVE OPEN INDICATION. AT LOCAL PANEL OR' CONTR 1
- 0L ROOM PANEL. REQUIRED SURVEILLANCE ON OPERABLE VACUUM BREAKER VALVES W 0THER' je
. COMPONENT. FAILURE FFECT OH SAFE PLANT OPERATION. PUBLIC HEALTH 4' SAFETY.WERE NOT EFFECTED.
AS IMMED. PERFORMED PER:T/S 3.6.4.1' ACTION A. THERE WAS NO SIGNIFICANT E' l
1 1 MECHANICAL.
.BY THIS INCIDENT. SIMILAR EVENT 0CCURRED ON 11/20/79 AT E..I.
HATCHi U 2; 1
GPE CONTROLS CAUSE OF OCCURRENCE.IS UNKNOWN AT THIS TIME DUE TO INACCESSIBILITY OF VA.
1
}
LVE. FAILURE IS NOT RELATED TO PRIOR MAINTENANCE. IMOPERABLE VACUUM BREA
.KER VALVE WILL BE INSPECTED & REPAIRED AS NECESSARY DURING NEXT REACTOR COLD: SHUTDOWN. TESTING-OF-OPERABLE VACUUM BREAKER VALVES EVERY 15 DAYS.W
.ILL BE CONTINUED PER T/S 3.6.1.4 ACTION A UNTIL NEXT RX COLD SHUTDOWN. '
l EDWIN'I.-HATCH-2
'05000366.
121979 WHILE OPERATING AT STEADY' STATE POWER ON 12/19/79, THEJ'A' POWER SUPPLY
~ENGNRD SAFETY FEATR INSTR-SYS 79-135/03L-0 010880 FOR: RCIC STEAM LEAK.-DETECTION SYSTEM FAILED. REDUNDANT SYSTEM CHANNEL' WA GENERATORS-027848 30-DAY-S.0PERABLE. ON 12/20/79, AT STEADY STATE POWER,.THE
'B' POWER SUPPLY F0 R THE. RCIC -STEAM. LEAK DETECTION SYSTEM' FAILED. THE
'A' SYSTEM HAD BEEN-5 l'
. INUERTER,...
'RETURHED TO SERVICE AND WAS OPERABLE. OTHERE WAS NO EFFECT ON.THE ENVIRO t
f "~ ' ' COMPONENT FAILURE i
j ELECTRONIC,
NS. - THIS IS'A NON-REPETITIVE EVENT.
F TOPAZ ELECTRONICS-CAUSE OF BOTH EVENTS WAS. ATTRIBUTED TO EXCESS CURRENT ON 125 V DC INPUT -
l
.TO POWER SUPPLIES. EXCESS CURRENT CAUSED FUSES F7A AND F7B TO BLOW DISAS
>BLING POWER SUPPLIES. FUSES WERE' REPLACED AND CAUSE FOR EXCESS CURRENT
-IS UNDER INVESTIGATION..RESULTS OF INVESTIGATION WILL BE SUBMITTED IN A FOLLOWUP REPORT.
i. --
i
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i
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~
r pe 4
'FEB.07. 1980-
'LER 0UTPUT ON REPORTS RECEIVED FROM-12/31/79 THRU 01/13/80:
PAGE 18 0UTPUT SORTED BY FACILITYEAND EVENT DATE
' FACILITY / SYSTEM /
cCOMPONENT/ COMPONENT SUBCODE/
DOCKET-NO./-EVENT DATE/
CAUSE/CAUSE SUBCODE/
LER NO./.
- REPORT-DATE/.
. EVENT DESCRIPTIOM/
COMPONENT MANUFACTURER..
. CONTROL ND. REPORT 1 TYPEL CAUSE DESCRIPTION I
- 122479 WHILE PERFORMING PROCEDURE HNP-2-1050, ' SURVEILL ANCE' CHECKS, DURING STEAD
.EDWIN I.' HATCH-2 05000366.-. 010880 Y-STATE OPERATION, PLANT-OPERATORS OBSERVED-THE DRYWELL AND TORUS TEMPER' REACTOR CONTAINMENT' SYSTEMS' 179-137/03L 027849 30-DAYE ATURE RECORDER, 2T47-R626, PRINTING ERRATIC TEMPERATURES. ALL.0THER DRY ~
INSTRUMENTATION + CONTROLS
. RECORDER-
'WELL-AND TORUS TEMPERATURE INDICATIONS APPEARED NORMAL. 'THERE WAS NO.EF-
~ DESIGN / FABRICATION ERROR JFECT ON THE ENVIRIGHS. :THIS IS A'NON-REPETITIVE EVENT.
MANUFACTURING-LEEDS &'NORTHRUP CO.
. INVESTIGATION REVEALED.A COLD SOLDER-JOINT ON A' TRANSISTOR LEAD' CAUSING' THE PEN'To BE ERRATIC. THE-TRANSISTOR PINS WERE RE50LDERED1TO.THE CARD WHICH ELIMINATED THE PROBLEM, AND THE RECORDER WAS RETURNED T0' SERVICE.
05000366 122879-
.WHILE PERFORMING HPCI STEAMLINE. DELTA PRESSURE FUNCTIONAL' TEST PROCEDURE EDWIN I. HA'TCH -..
79-138/01T-0 123179
, HHP-2-3307, AND CALIBRATION PROCEDURE, HNP-2-5202, INSTRUMENTS 2E41-NO-
.SYS REQRD FOR SAFE'SHUTDOWH' 027770 2-WEEK 04 AND.2E41-H005 WERE.FOUND OUT OF TECH SPEC LIMITS.
2E41-H004' ACTUATED INSTRUMENTATION + CONTROLS SENSOR / DETECTOR / ELEMENT 20 AT -222 IN. H2O AND +198 IN. H20. -THE ACCEPTANCE CRITERIA.IS-:/>-196 0THER IM. H20:AND =/<+196 IN. H20.
2E41-N005 ACTUATED AT. +197 IN. H20.
THE.
NOT APPLICABLE.
ACCEPTANCE CRITERI A IS :/<+196 IN. H20. THERE WERE-HO EFFECTS UPON PUBLI BARTON INSTRU CO.,..DIV 0F ITT C HEALTH AND' SAFETY.
THE CAUSE OF THE OCCURRENCE HAS BEEN ATTRIBUTED TO INSTRUMENT DRIFT. TH E INSTRUMENTS WERE CALIBRATED AND HPCI STEAMLINE DELTA PRESSURE FUNCTION AL TEST PROCEDURE, HHP-2-3307 SUCCESSFULLY. PERFORMED.
P 05000333 111879
.DURING TEST'F-ST-11 (MAIN STEAM ISOLATION VALVE LIMIT' SWITCH INSTRUMENT' FITZ'ATRICK-1 79-106/03L-0 121779
' FUNCTIONAL TEST), MSIV 29-A0V-80A DID HOT PROVIDE A HALF SCRAM SIGNAL AT-REACTOR TRIP SYSTEMS COMPONENT: CODE NOT APPLICABLE-027822 30-DAY EQUAL TO OR-LESS THAN 10% CLOSURE AS REQUIRED. INSTRUMENT CHANNEL RELA-SUBCOMPONENT NOT APPLICABLE YS WERE PLACED IN TRIPPED CONDITION. THE OTHER CHANNELS WERE SHOWN' TO B '
OTHER
~
E FULLY OPERABLE.
' HOT-APPLICABtE l
. ITEM NJT APPLIC.1BLE L
SINCE THE LIMIT SWITCHES.ARE LOCATED INSIDE PRIMARY CONTAIMMENT, THE PRE-l CISE NATURE OF THE FAILURE CAN NOT BE DETERMINED AT THIS TIME.- WHEN PLA I
HT CONDITIONS PERMIT, REPAIR WILL BE COMPLETED AND A' FOLLOWUP. REPORT'SUB L
MITTED.
FITZPATRICK-1' 05000333'
'120379 FOLLOWING A POWER INTERRUPTION TO PRIMARY CONTAINMENT OXYGEN ANALYZER "A
, THE INSTRUMENT INDICATED GREATER THAN 10% OXYGEN CONCENTRATION.
ANAL-OTHR INST SYS REQD FOR SAFETY 79-107/02L-0 1226/9 l
.INSTRUMENTATIDH + CONTROLS
~027819
.30-DAY YZER "B" WAS ALSO QUT OF. SERVICE. A SAMPLE OF PRIMARY CONTAINMENT ATMOS-I '~
INDICATOR PHERE WAS OBTAINED AND ANALYZED WHICH INDICATED AN OXYGEN CONCENTRATI0H COMPONENT FAILURE LESS THAN TECHNICAL SPECIFICATI0H LIMITS.
. ELECTRONIC BECKMAN INSTRUMENTS, INC.
THE INSTRUMENT'WAS CALIBRATED USING TEST PROCEDURE F-1SP-31 AND RETURNED TO SERVICE ON THE FOLLOWING DAY.
FOLLOWING RECALIBRATION, THE INDICATE
~
D OXYGEN CONCENTRATION WAS 2.6%' COMPARED TO T.S. LIMIT OF 4%.
em W
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~ -
u 1
3:g.
+
4 5
/
I
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i PAGE 19
- FEB}07,ft980'
- LER'0UTPUT ON REPORTS RECEIVED'FROM'12/3'1/79 THRU.01/13/80
~2>
^
00TPUT,50RTED BY.-FACILITY AND EVENT 1DATE.
1 FACILITY / SYSTEM /-
' !! COMPONENT / COMPONENT ' SUBCODE/.
DOCKET NO./: EVENT'DATE/.-
5-
~
4
.CAUSE/CAUSE SUBCODE/'
' LER NO./-
. REPORT.. DAT E/ L
~ EVENT DESCRIPTION /1
. COMPONENT MANUFACTURER _
' CONTROL {.NO. REPORT TYPE JCAUSE DESCRIPTION-
,.FITZPATRICK-1 1
~
05000333
~ 120579 ARCHITECT - ENGINEER
- NOTIFIED! LICENSEE 'THAT PIPE HANGER N10-539 :( AS$0 CIA.,
OTHER SYSTEMS.-E
' 79-193/01T-O 121779 TED WITH,THE RHR SYSTEM STEAM CONDENSING MODE MON-CONDENSIBLE GAS VENT'L.5-HANIERS. SUPPORTS, SHOCK:SUPPRSS:
L027820
' 2-WEEK 1 INE - BETWEEN RHR. HEAT. EXCHANGER AND. TORUS) WAS CONSIDERED INOPERABLE DUE '
T HANGERS
.TO THERMAL GROW H.
DESIGN /FABRICATIONJERROR;
. DESIGN 4
^
STONE 4 WEBSTER ENG.' CORP.
MODIFICATION OF THE HANGER BY REMOVING HOLD-DOWN CLIPS AND GUIDES WHICM
- RESTRAINED MOVEMENT OF THE PIPE, RETURNED THE HANGER T0 A FULLY OPERABLE.-
STATUS ON THE FOLLOWING DAY.
IFITZPATRICK-1 2
, 05000333
.120679-THE RCIC SYSTEM WAS DECLARED I'NOPERABLE T01 PERMIT ' INSPECTION OF THE-SYST REAC CORE'ISOL' COOL SYS +, CONT 79-108-03L-0.010380-EM'S TURBINE BEARINGS. THE HPIC SYSTEM WAS DEMONSTRATED' OPERABLE IMMEDI TURBINES 027766 30-DAY ATELY:AND DAILY.UNTIL THE RCIC WAS RETURNED TO: SERVICE.
SUSCOMPONENT' HOT APPLICABLE OTHER NOT-APPLICABLE"..
. TERRY STEAM TURBINE COMPANY MO PROBLEM MAS FOUND. : SYSTEM.WAS REASSEMBLED, TESTED, AND-DECLARED FULL.
. Y-OPERABLE. THE OPERATOR APPARENTLY ERROMEOUSLY SUSPECTED THE EXISTENCE
.0F-BEARING OVERHEATING.
- FITZPATRICK-1 05000333
.121379 DURING TEST F-ISP-27' (DRYWELL AND SUPPRESSION POOL' TEMP. INSTRUMENT 'CALI.
REACTOR CONTAIMMEHf SYSTEMS 79-109/03L-0 -010880-BRATION). SUPPRESSION CHAMBER TEMP. ' RECORDER '27-TA-182 'WAS FOUND OUT OF-
. INSTRUMENTATION + CONTROLS O27828(
30-DAY CALIBRATION IN THE MON-CONSERVATIVE DIRECTION. - REDUNDANT: INSTRUMENT WAS'
-COMPUTATION MODULE VERIFIED OPERABLE.
COMPONENT FAILURE
' ELECTRONIC' OTHER FAILED PRINTED CIRCUIT BOARD. BOARD WAS REPLACED AND INSTRUMENT *VERIFIE D OPERABLE BY SATISFACTORY COMPLETION OF TEST F-ISP-27.
i l 'FITZPATRICK-1 05000333 121479 HPCI SYSTEM STEAM SUPPLY INBOARD ISOLATION VALVE (23 MOV-15) CLOSED AS~A'
[.
- CNTNMNT ISOLATION SYS + CONT 79-110/03L-0 010880 RESULT OF A SPURIOUS ISOLATION SIGNAL. 'THIS RENDERED THE HPCI SYSTEM I I-COMPONENT CODE.NOT. APPLICABLE 027829 DAY NOPERABLE AT A TIME'ITS REQUIRED TO BE OPERABLE.- ISOLATION SIGNAL WAS R
-SUBCOMPONENT NOT APPLICABLE.
ESET, VALVE REOPENED. AND HPCI SYSTEM RESTORED TO OPFRABLE STA1US.
~~
[
' OTHER NOT APPLICABLE i
ITEM NOT APPLICABLE
~
NO CAUSE FOR SPURICUS SIGNAL COULD BE FOUND AND CONDITION COULD NOT BE D r
l-UPLICATED.
[.
" ~. -
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l
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/--
" m -
3 '
~
4 lk*
9' W-t e_ s h '
~
bj
+
s
'~
e
..LER OUTPUT 0N REPORTS RECEIVED'FROMs 12/31/79 THRU 01'/13/80;
~
. PAGE'20 IFESGN:liSS I F
.0UTPUT SORTED BY-FACILITY AND EVENT'DATE.
. y7'
', J fNAh!LITY/ SYSTEM /'
?:
..~DOCKETiMO./. EVENT DATE/'
1 COMPONENT / COMPONENT SUBCODE/F
-;W CAUSE/CAUSE SUBCODE/
-!LER NO./
. REPORT DATE/-
EVENT DESCRIPTION / :
TCOMPONENT MANUFACTURER '
. CONTROL'. MO. REPORT. TYPE -
CAUSEl DESCRIPTION:
z.
05000333 121475-DURING TEST'F-ISP-9-(STEAM LINE MIGN' FLOW-NPCI RCIC) 'ONE OF FOUR NION F-2
'IFITZPATRICK-1 J
'iCNTNMNT-tISOLATION'SYS'+ CONT' 79-111/03L-0 011080-.- LOW INSTRUMENTS WAS FOUND TO HAVE DRIFTED IM.TME NON-CONSERVATIVE DIRECT
+
INSTRUMENTATION-:+ CONTROLSE
'027830' ~
30-DAY ION.
THE OTHER THREE INSTRUMENTS WERE FOUND TO BE WITHIN TECHNICAL SPEC ~
~
IFICATION LIMITS.
n;[ SWITCHE COMPONENT FAILURE?
s o
p OTNER -..
. t
~ BARTONLINSTRU.CO.,'DIV.0FJITT INSTRUMENT WAS -RECALIBRATED AND RETURNED TO OPERABLE STATUS..~ SAME INSTR UMENT WAS AGAIN CHECKED A WEEK LATER AND WAS FOUND TO BE SATISFACTORY.a w
{
g;;
4
'05000333~
121679 DURING TEST F-ST-76J 19 :CSMOKE. AMD. NEAT DETECTOR TEST). FIRE DOORS DG-272
,FITZPATRICK-1 79-112/03L-0 011180
-2 AND:DG-272-3 DID NOT CLOSE WHEN TRIPPED BY ACTUATION OF-TME CARD 0X SY' FIRE PROTECTION.SYS + CON 1 BOTM DOORS WERE THEN CLOSED 8 VERIFIED ' CLOSED EACM SMIFT UNTIL-RE.
> COMPONENT COLi MOTfAPPLICa.blE-027831 30-DAY STEM.
.SURCOMPONENT NOT. APPLICABLE-
-PAIR OF THE DOORS.COULD BE COMPLETED.'
' ' ^
~
OTHER NOT APPLICABLE ~- -
= ITEM' MOT' APPLICABLE IMPROPER. ALIGNMENT OF.THE-DOORS. DOORS WERE REALIGNED AND LUBRICATED AM-D SATISFACTORY. OPERATION DEMONSTRATED BY SUCCESSFULLCOMPLETION OF:F-ST. +
6J 19..
l i
F. FT ST.'(VRAIN-1 05000267-120179 WITN REACTOR SHTUDOWN FOR SCHEDULED MAINTENANCE. ~ THREE' MOSITURE MONI)0R -
' REACTOR TRIP SYSTEMS-79-062/03L-S 122879 FLOW TRANSMITTERS WERE FOUND OUT OF TOLERANCE DURING ROUTIME SURVEILL ANC' 4
l:
l INSTRUMENTATION'+ CONTROLS
.'027851 30-DAY E TESTING. SAMPLE FLOW REQUIREMENTS OF LC0 ~ 4.4.1 NOTE (T) COULD NOT BE..,
i -
SENSOR /DETECTCR/ ELEMENT VERIFIED. REPORT ABLE PER AC 7.5.2(831 AMD 7.S.2(B)2..NO EFFECT ON PUBL.'
7
.NOT' APPLICABLE-~
HASTINGS RAYDISTL CAUSE OF FLOW TRAN*.,MITTERS BEING OUT OF TOLERANCE WAS INSTRUMENT CALIBRA TION DRIFT. THE TRANSMITTERS WERE RECALIBRATED AND THE SURVEILLANCE TES
- t T SUCCESSFULLY. COMPLETED. N0'FURTHER CORRECTIVE ACTION IS ANTICIPATED Ol
'{
R REQUIRED.
FT.lST. VRAIN-1 05000267 120579
'WntILE REACTOR WAS SHTUDOWN FOR. SCHEDULED MAINTENANCE.-SURVEILLANCE TEST.
~ MAIN STEAM SYSTEMS.+ ClaTROLS 79-064/03L-0 010280 ON CLASS I HYDRAULIC SNUBBERS IDENTIFIED THREE INOPERABLE SNUBBERS.- REA" HANGERS. SUPPORTS. SHOCK SUPPRSS 027850 30-DAY CTOR OPERATION HADtTAKEN' PLACE DURING SURVEILLANCE' INTERVAL. INTERPRETE, e'
D AS OPERATION UNDER A DEGRADED MODE PERMITTED BY LCO 4.3.10,AND REPORTA1
- SNU5BERS BLE PER TECHNICAL SPECIFICATION AC 7.5.2(B)2.
NO. ACCOMPANYING OCCURRANC.
DESIGN / FABRICATION ERROR
. CONSTRUCTION / INSTALLATION E.
NO.EFFECT ON PUBLI,C HEA.LTH OR-SAFETY.
'ITTcGRINNELL' '
'4
. FIGURE 200 AND' 201 SNUBBERS IMOPERABLE. DNE PISTON WA.
~
THREE ITT GRINNEL S-0UT'0F TOLERANCE DUE TO THERMAL MOVEMENT. TWO INSTALLED WITH INCORREC.
i T ORIENTATION OF DIL RESERVOIR / SNUBBER VALVE.
ADJUSTED TO BRING PISTON.
IN TOLERANCE. RE-INSTALLED WITH CORRECT ORIENTATION. MAINTENANCE PROCE-DURE REVISED TO PROVIDE ORIENTATION VERIFICATION.
l 1,_, -
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. PAGE=21;
<LERl OUTPUT'ON REPORTS RECEIVED FROM 12/31/79 THRU 01/13/80 m
OUTPUTx 50RTED BY FACILITY: AND EVENT'DATE 4
g.
[ FACILITY / SYSTEM /..."...
~
?
sCOMPONENT/ COMPONENT SUSCODE/
-DOCKET.NO./ EVENT-DATE/
' CAUSE/CAUSE: SURCODE/ --
LER.NO./
JREPORT DATE/
. EVENT-DESCRIPTION /.
n " COMPONENT MANUFACTURER' CONTROL NO.LREPORT TYPE
CAUSE DESCRIPTION
.t
+3
^
05000213' 192877-JTNE!TLD. DOSIMETER OF A WORKER AT NADDAM MECK NUCLEAR ' POWER PLANT INDICAT-NADDAM' NECK-l' o :
77-001/13L 012279-
' ED A SKIN. DOSE OF 23' 50. REMS DURING THE PERIOD 10/15/77 -TO - 10/28/77.
NO-
'; iSYSTEM CODE NOT/ APPLICABLE!
2
~
~ COMPONENT:CCDE NOT APPLICABLE ' '
'023648-
'30-DAY WEVER, THE TLD WAS; CONTAMINATED, AND THE WORKER'S ACTUAL SKIN DOSE WAS B.
'SUSCOMPONENT NOT. APPLICABLE ELIEVED TO BE 2.71 REMS AS DETERMINED BY HIS FILM BADGE. FOR PURPOSES 10-F MAINTAINING THE WORKER'S RECORD CONSERVATIVELY, THE-TLD READING WILL 3.
- UNKN0kNJ. -..
MOT APPLICABLE ~-.--
E USED.
(REPORT FILED IN RADIATION RECORDS.)-
~
~
YTEM NOT-APPLICABLE-T 4,
A WORKER'S'TLD BECAME CONTAMINATED AND INDICATED A'23.50 REM SKIN DOSE.. '
THE' PLANT CHANGED TLD VENDORS AND TOOK ACTIBMS.TO REINFORCE, STRICT ADNEC
' ~ *, J RENCE TO GOOD HEALTH PHYSICS PRACTICES.
?~
. 05000213 031679-
.AT.THE HADDAM NECK PLANT,-6 WORKERS RECEIVED DOSES' EXCEEDING 1.25 ' REMS I 1HADDAM HECK-11 s
79-001/13L-0 031679
- N A. 0UARTER BEFORE THEIR PREVIOUS DOSE HISTORY HAD BEEM COMPLETED 'ON AN
- $YSTEM CODE NOT APPLICABLE'.
3 COMPONENT CODE'NOT APPLICABLE;.
- 327874 ~
30-DAY-NRC. FORM-4.
AT THE TIME OF DISCOVERY,7 THEIR WHOLE BODY DOSES WERE ESTIM s
J~SUSCOMPONENT NOT' APPLICABLE
'ATED.TO BE 1.445.-1.34,1 1.315, 1.94' 1.89.AND;1.35' REMS.
(REPORT. FILED
- PERSONNEL ERROR;
.IN RADIATION RECORDS.).'
' RADIATION PROTECTION PERSONNEL cITEM NOTsAPPLICABLE ALL MISSING EXPOSURE RECORDS WERE OBTAINED FOR THESE INDIVIDUALS AND THE s RECORDS TECHNICIANS'WERE INSTRUCTED IN THE PROPER-PROCEDURES FOR.COMPLE TING FORM-4'S.
RECORDS WILL BE CHECKED CLOSER BEFORE. ALLOWING.INDIVIDUA-i i.
LS TO EXCEED 1.25. rut $ PER GUARTER.
i L
t
~
05000518' 060679 THE DRYulLL VENT STRUCTURE AND REACTOR. PRESSURE. VESSEL PEDESTAL.WITH BUT-L HARTSVILLE-A1 79-
/02L-0 070579<
TERED EDGES WERE-TOO POROUS TO BE USED. HAD THESE DEFICIENCIES GONE UND.
. REACTOR VES. + >PPURTENANCES<
~ ' V ESS EL S, PR ES$UEc- '
'027879 30-DAY ETECTED THE STRUCTURES COULD HAVE BEEN JEOPARDIZED.DURING AM EARTNGUAKE '
.cNO SUSCOMPONENT PROVIDED OR LOSS'0F COOLANT ACCIDENT.
j
' DESIGN / FABRICATION ERROR s
-CAUSE.SUBCODE NOT PROVIDED l:
-LAKESIDE BRIDGE & STEEL CD.
THE BUTTERING' DEFICIENCIES WERE CAUSED BY - A DISAGREEMENT BETWEEN THE MAN F
UFACTURER AND THE TECHNICAL ENGINEER ABOUT-THE CLASSIFICATION OF BUTTERI MG AS A REPAIR OR MOT.
TVA WILL REINSPECT-STRUCTURE' SEGMENTS SENT BYsTN-I 1
.E MANUFACTURER AND REPAIR, AS PFR : INSTRUCTIONS BY THE. TECHNICAL ENG. -
n 05000247 033178-CONSOLIDATED EDISONlCO. OF N.Y.,
INC. (IMDIAN PT. 2).
A WORKER'S FILM 3-
' INDIAN POINT-2 78-001/13L-0 080878 ADGE INDICATED A DOSE OF 3.11 REMS FOR 3/9-31/78.. HIS SELF-READING DOSI-i sSYSTEM CODE NOT' APPLICABLE-
'~ COMPONENT CODE' HOT APPLICABLE 023649 30-DAY METER SHOWED-0.340 REMS.
TWO OTHER WORKERS ALSO HAD HIGHER' THAM NORMAL'
- SUBCCMPONENT1NOT APPLICABLE.
FILM BADGE READINGS & LARGE DISCREPANCIES-BETWEEN SRD & FB-READINGS. AL;
-i e
['""KUNKNCMN L 3 WORKED ON THE SAND BOX COVER PLATES, CLOSE TO THE' CAVITY SEAL PLATE i.
NOTmAPPLICABLE.
WHICH HAD LOCALIZED AREAS 1DF CONTAMINATION. WCRKER WAS ASSIGNED DOSE YI ITEM NOT:. APPLICABLE ELDING A TOTAL DOSE OF 4~.48-FOR THE QTR. (REPORT IN RADIATION. RECORDS.)
~
A LARGE DISCREPANCY BETWEEN A WORKER'S SELF-READING DOSIMETER AND HIS FI:
l LM BADGE RESULTS (3.110 REMS VS. 0.340 REMS) WAS FOUND FOR'3/9-3/31/78.
NO DEFINITIVE CAUSE OF THE ANCMALY OR'INFORMATION THAT PRECLUDED THE FI t
LM BADGE READING WAS FOUND.
i x
~
~
4-
m
- o(.
EB.' 07,t 198 0 -
-LER OUTPUT OH REPORTS RECEIVED FROM 12/31/79 THRU 01/13/80 PAGE[?2-OUTPUT SORTED BY FACILITY AND EVENT DATE FACILITY / SYSTEM /
TCOMPONENT/ COMPONENT SUBCODE/
DOCKET NO./-EVENT DATE/
CAUSE/CAUSE'SUBCODE/
LER NO./
REPORT DATE/
EVENT DESCRIPTION /
- COMPONENT MANUFACTURER CONTROL NO. REPORT TYPE CAUSE DESCRIPTION lIIDIAN POINT-2 78-001/13L-0 022779 G DOSIMETER INDICATED 1.295 REMS IN NOVEMBER 1978.
THE-DOSE RATES IN TN 05000247-111378 A-WORKER'S FILM BADGE INDICATED A DOSE OF 3.3 REMS WHILE HIS SELF-READIN-
- SYSTEM CODE NOT APPLICABLE-
. COMPONENT CODE NOT APPLICABLE.
.023650-30-DAY E RADWASTE AREA WHERE NE WORKED FOR 2 WEEKS ARE THE ONLY ONES IN WHICH H.
SUBCOMPONENT NOT APPLICABLE E WORKED THAT ARE HIGH ENOUGH TO PRODUCE SUCH A DOSE. THIS WAS THE FIFT-UNKNOWN H TIME IN 9 MONTHS IN WHICH A WORKER'S F.B. RESULTS WERE SIGNIFICANTLY D NOT APPLICABLE IFFERENT FROM HIS SRD RESULTS. SIMILAR TO EVENT REPORTED 8/8/78.
(REPO,
. ITEM NOT APPLICABLE RT IN RAD 7ATION RECORDS.)
A LARGE DISCREPANCY-BETWEEN A WORKER'S SELF-READING DOSIMETER AND HIS FI LM BADGE RESULTS (3.30 VS. 1.295) WAS FOUND FOR NOV. 1978.
OTHER WORKER S IN THE SAME AREA SHOWED NO UNUSUAL EXPOSURES. NO DEFINITIVE CAUSE WAS FOUND, BUT A PROGRAM TO CHECK THE ABILITY OF A WORKER.TO PROPERLY READ HIS SRD MAY BE INSTITUTED.
JOSEPH M. FARLEY-1.
05000348
.110879 AT 2210 MAKEUP TO REACTOR COOLANT SYSTEM DURING A ROUTINE PLANT C00LDOWN REACTIVITY CONTROL SYSTEMS 79-055/03L-0 120779 FOR MAINTENANCE RESULTED IN DECREASING AVAILABLE BORATED WATER VOLUME I COMP 0HENT CODE NOT APPLICABLE 027640-30-DAY N BORIC ACID STORAGE TANK 442 GAL BELOW T.S. 3.1.2.8.A.f LIMIT OF 14,336
-SUBCOMPONENT NOT APPLICABLE
' GAL.
ADDITIONAL 6000 GALLONS OF 8234 PPM BORIC ACID SOLUTION AVAILABLE PERSONNEL. ERROR BUT COULD NOT BE CONSIDERED IN MEETING THE TECH. SPEC. MINIMUM DUE TO U
. MAINTENANCE & REPAIR PERSONNEL PPER LIMIT OF 7700 PPM.
TECH.. SPEC. 3.1.2.8 ACTION. STATEMENT REQUIREMEN ITEM NOT APPLICABLE TS MET.
MA'EUP TO RCS 11/8/79 DECREASED B BAT LEVEL FROM 54% TO 50%.
52% IS ret UIRJ7 TO MEET T.S. LIMIT OF 11.336 GAL PER BAT TANK.
BAT A UNAVAILABLE DUE.TO CONTENTS BEING ABOVE 7700 PPM FROM BATCHING IN PROGRESS.. BAT A L.
ESS THAN 7700 PPM BY 1050 ON 11/9/79.
JOSEPH M.
FARLEY-1 05000348 t>2179 AS A RESULT OF AN INADVERTENT SAFETY INJECTION, THE BIT WAS DECLARED IMO CHEM, VOL CONT + LIQ POISN SYS 79-058/03L-0 121979 PERABLE AT 0730 DUE TO BORON CONCENTRATION DECREASING TO APPROXIMATEL" 1 COMPONENT CODE NOT APPLICABLE 027853 30-DAY 8,232 PPM.
TECN. SPEC.
3.5.4.1,. IN PART, REQUIRES BIT TO BE OPERABLE WI SUBCOMPONENT NOT APPLICABLE TH A BORON CONCENTRATION BETWEEN 20,000 AND-22,500 PPM.
TECH. SPEC. 3.5
-0THER-
.4.1 ACTION STATEMENT REQUIREMENTS WERE NET.
BIT WAS RETURNED TO SERVIC NOT APPLICABLE E AT 1745 WHEN BORON CONCENTRATION WAS INCREASED TO 20,504 PPM BY BATCHI ITEM NOT APPLICABLE HG.
DILUTION RESULTED FROM-INADVERTENT SAFETY INJECTION. BIT BORON CONCENTR ATION WAS INCREASED BY BATCHING. A SIMILAR OCCURRENCE WAS REPORTED IN L' ER 78-039/03L-0.
A SPECIAL REPORT WILL BE SUEMITTED FOR THE SAFETY INJE-CTION AS REQUIRED BY TECH. SPEC. 6.9.2.A.
JOSEPH M.
FARLEY-1 05000348 112279 AT 1130 STEAM GENERATOR B LEVEL CHANNEL 486 DECLARED INOPERABLE DUE TO R Rr CTOR TRIP SYSTEMS 7.9-057/03L-0 121979 EADING APPROXIMATELY EIGHT PERCENT HIGHER THAN OTHER TWO STEAM GENERATO VALVES 027852
'30-DAY R B LEVEL TRANSMITTERS.
TECH. SPEC. 3. 3.1.1, IN PART, REQUIRES STREAM G DIAPHRAGM ENERATOR B LEVEL CHANNEL 486 TO.BE OPERABLE.
TECH. SPEC. 3.3.1.1 ACTION-
"~
OTHER-STATEMENT REQUIREMENTS MET.
NOT APPLICABLE KER0 TEST MANUFACTURING CORP.
CAUSED BY INSTRUMENTS EQUALIZING VALVE LEAKING; SUBSEQUENTLY, VALVE WAS TIGHTENED.AND CHANNEL RETURNED TO QPERATION AT 0200 DN 11/23/79 FOLLOWIN G COMPLETICN OF SURVEILLANCE TEST FHP-0-STP-213.6.
~
W N
1 i
~
l48 y,
FEB 07s[19801
~
~ I LER OUTPUT ON REPORTS RECEIVED FROM.12/31/79 THRU 01/13/80~
PAGE 23 I
~
~
OUTPUT SORTED BY. FACILITY,AND. EVENT DATE SFACILITY/ SYSTEM}..
J i ':
. COMPONENT / COMPONENT SUBCODE/.
DOCKET NO./ EVENT DATE/
LER MO./
REPORT DATE/
EVENT DESCRIPTION /
M ' 1 CAUSE/CAUSE ^ 5UBCODE/ :
~
.CONTROLLMO.' REPORT TYPE.
CAUSE DESCRIPTION, r
COMPONENT MANUFACTURER 05000348 113079 AT 0858 FLOW PATH FROM BAT B WAS DECLARED INOPERABLE DUE:TO ITS-0UTLET.V:
JJOSEPN'M. FARLEY-1
- REACTIVITY CONTROL ^5YSTEMS-79-059/03L-0.123179 ALVE BEING CLOSED. BAT A WAS IN THE RECIRCULATION MODE AT THE TIME OF T-VALVES l 1 027910 '
30-DAY ME INCIDENT. TECHNICAL SPECIFICATION 3.1.2.2.'IN PARTI-REGUIRES THE FLO DDIAPHRAGM
.TO BE OPERABLE.'
UPON DISCOVERY THE VALVE WAS OPENED AND TNE SYSTEM WAS:
W PATH FROM EITHER BAT TO THE-RCS VIA-A TRANSFER PURP AND CHARGING PUMP-
' PERSONNEL ERROR.
RETURNED TO OPERATION.
LMONLIC. 0PERATIONS. PERSONNEL l
'{GRINNELL. CORP.
AS A RESULT OF A AND B BAT VALVE MANIPULATIONS MADE IN
=
4
.0PERATOR ERROR.
ORDER TO RECEIVE EFFLUENT FROM THE BATCHING TANK ON 11/29/79,.THE B BAT'-
OUTLET VALVE WAS ERRONEOUSLY LEFT CLOSED.. PERSONNEL TNVOLVED IN THIS-IN
'CIDENT HAVE RECEIVED INDOCTRINATION IN THE CORRECT USE OF TNE.CVCS BORIC ACID SYSTEM OPERATING PROCEDURE.
05000348 120279' AT 0400'TAKING UNIT FROM MODE 1 TO MODE 2.1 REACTOR OPERATOR NOTICED CONT'-
JJOSEPH M. FARLEY-1 ECNTNMNT HEAT REMOV SYS + CONT
.79-060/03L-0 122879' AIMMENT PRESSURE HI-1 AND HI-2-TRIP STATUS LIGHTS FOR ONE CHANNEL-ENERGI 1 INSTRUMENTATION +~ CONTROLS 027854 30-DAY, ZED.ON MCB WIYd NORMAL. READINGS ON.ALL FOUR. CONTAINMENT PRES 5URE IMDICAT iL JINTEGRATOR-(TOTALIZER)
ORS.
T.S. 3.3.2.1, REQUIRES TWO OPERABLE CONTAINMENT PRES 5URE CHANNELS-
!?
. COMPONENT FAILURE'-
.FOR CONTAIHMENT PRESSURE HI-1 AND TH2EE OPERABLE CONTAIMMENT PRESSURE CH ANNELS FOR.CONTAIMMENT PRES 5URE HI-2.
T.S. 3.3.2.1 ACTION-STATEMENT ret i-ELECTRONIC.
QUIREMENTS WERE MET.
NO SIMILAR OCCURRENCES RE."0RTED.
WESTINGHOUSE ELECTRIC CORP.
COMPARATOR CARD IN THE 7300 RACKS FOR CONTAINMENT PRESSURE BI5 TABLES *C9 525-1 AND PC9528-2 FAILED. CARD REPLACED AND CALIBRATED PER FNP-1-STP-2 :
20.3.
CONTAINMENT PRESSURE CHANNEL RESTORED TO OPERABLE 5TATUS AT 1115; UPON VERIFYING BI5 TABLES PC9525-1 AND PC9528-2 CLEARED.
I fJO$EPH M?-FARLEY-t 05000348-120279 AT 0345 CONDUCTING CHANGE FROM MODE 1 TO 2 AND SECURING THE SECONDARY ST',
MAIN STEAM SYSTEMS + CONTROLS 79-061/03L-0 010280 EAM LOADS, THE C ATMOSPHERIC RELIEF VALVE FAILED OPEN CAUSING A REDUCTIO
[.
VALVES-
'027911 30-DAY N IN RCS TAVG T0 531 DEG. F.
TECHNICAL SPECIFICATION 3.1.1.5 REQUIRES R PHERIC RELIEF VALVE WAS MANUALLY ISOLATED AND TAVG RESTO CS LOWEST OPERATING LOOP TAVG TO.BE 541 DEG. F. OR GREATER.- 'THE C f
CHECK TER T.
COMPONENT FAILURE' CORROSION HAN 541 DEG. F.
ACTIDH STATEMENT REQUIREMENTS OF TECHNICAL SPECIFICATIO.
i FISHER CONTROLS CO.
N 3.1.1.5 WERE MET.
TAVG DECREASE 0CCURRED BECAUSE C ATMOSPHERIC RELIEF VALVE FAILED OPEN DU j
E TO A BROKEN POSITIONING ARM.
IMMEDIATE CORRECTIVE ACTION WAS TO MANUA-a
' LLY ISOL ATE C ATMOSPHERIC. RELIEF VALVE WHICH ' AI LOWED RCi TAVG TO BE REST.
l.
ORED'ABOVE 541 DEG. F. BY 08a5 ON 12/2/79.
THE POSITIONING ARM WAS REPL ACED AND THE C ATMOSPHERIC PE.IEF VALVE'WAS-RETURNED TO SERVICE.
05000348 120479 AT 1400. FLOW-PATH FROM B AT A WAS. DECLARED. IMOPERABLE DUE.TO IT5 OUTLET-V
- j. ' JOSEPH:M. FARLEY-1.
79-063/03L-0 010480 ALVE BEING CLOSED. BAT B WAS IN THE RECIRCULATION MODE AT'THE TIME.- TE-4
-REACTIVITY CONTROL SYSTEMS
' VALVES 027913 30-DAY CH. SPECS. 3.1.2.2, IN PART, REQUIRES,THE FLOW PATH FROM EITHER BAT-TO T.
DIAPHRAGM HE~ RCS~ VI A A TRANSFER-PUMP - AND CHARGING PUMP TO BE OPERABLE.
UPON DISC r
3 "~- PERSONNEL ERROR
, DVERY, WHILE PERFORMING DOUBLE VALVE VERIFICATION, THE VALVE WAS OPENED'
.NDHLIC. OPERATIONS. PERSONNEL AND THE SYSTEM RETURNED TO OPERATION. A SIMILAR' OCCURRENCE WAS REPORTED GRINNELL CORP.
IN LER 79-059/03L-0.
OPERATOR ERROR AND PROCEDURAL' DEFICIENCIES. AS A RESULT OF A AND B BAT 1-VALVE MANIPULATIONS THAT WERE MADE IN ORDER TO PERFORM BORON CONCENTRATI1 1.
ON ANALYSIS A BAT OUTLET VALVE WAS' ERR 0NEOUSLY LEFT CLOSE
D. PROCEDURE
C HANGES, WHICH ENHANCE THE CLARITY. WILL BE COMPLETED BY 1/4/80.
INFORMA TION AND RETRAINING-REGARDING 'THESE CHANGES WILL BE PROVIDED.
!~~
1, 4
9 7:
7eh 34
' c.
- F EB[4 7',~ i t'980 ~
- LER OUTPUT ON REPORTS RECEIVED FROM 12/31/79 THRU 01/13/80
'PAGE 24
~
OUTPUT SORTED BY, FACILITY AND EVENT DATEL FAC'IL'ITY/ SYSTEM / :
" COMPONENT / COMPONENT.SUBCODE/.. DOCKET NO./ EVENT DATE/.
~
m CAUSE/CAUSE SUBCODE/.
LER NO./
REPORT DATE/
' EVENT DESCRIPTION / '
sCOMPONENT MANUFACTURER _ ~
CONTROL NO. REPORT TYPE CAUSE' DESCRIPTION.
k e
l ; JOSEPH M. FARLEY-1..
79-064/03L 011180 E SAFETY INJECTION INITI ATION SIGNAL' COMPARATOR PB,446B -TRIPPED AT A VAL '
05000348 121379-DURING PERFORMANCE OF FNP-1-STP-213,125, STEAM LINE DIFFERENTIAL-PRESSUR-lENGNRD SAFETY.FEATR: INSTR SYS 1 INSTRUMENTATION,+ CONTROLS 027912f 30-DAY UE LESS CONSERVATIVE THAN TECN. SPEC. 3.3.2.1' UPPER
- LIMIT OF 112 PSID...
0THER -
PROTECTION CHANNEL.IV PRESSURE.ON STEAM HEADERS 1 AND 2 WAS DECLARED.INO
,. COMPONENT FAILURE PERABLE.AT 2000.
TECH. SPECS.-'3.3.2.1 ACTION STATEMENT. REQUIREMENTS-WER.
. ELECTRONIC
.E MET.- THE PROTECTIVE FUNCTION WOULD HAVE BEEN INITIATED IF: THE SETPOIN - -
. WESTINGHOUSE ELECTRIC CORP.
T OF ONE OF THE REMAINING TWO OPERABLE CHANNELS WAS EXCEEDED.
THE MAL CARD.USED FOR PB 486B CUULD NOT BE-ADJUSTED TO GIVE THE PROPER B i
ISTABLE TRIP VALUE. A NEW CARD WAS INSTALLED AND CALIBRATED PER FMP-1-5 TP-213.128.
THE. CHANNEL' WAS DECL ARED,0PERABLE AT 2210. 0N -~ 12/13/79. '
? JOSEPN M. FARLEY 05000348 122079 AT 1032 WHILE PERFORMING SURVEILLANCE-TEST FHP-1-STP-220?tt, ONE CONTAIN!
REACTOR-CONTAINMENT' SYSTEMS-79-066/03L-0 011680 MENT PRESSURE CHANNEL,(PT950)'WAS DECLARED INOPERABLE DUE TO A: FAULTY CD ELECTRICAL CONDUCTORS 027914' 30-0AY NNECTION IN "B" TRAIN $$PS INPUT CABINET 1.'
TECHNICAL SPECIFICATION 3.3 SUBCOMPONENT NOT APPLICABLE
.2.1 IN PART, REQUIRES 4 CONTAINMENT PRESSURE CHANNELS TO BE:0PERABLE.
OTHER.
TECHNICAL SPECIFICATION 3.3.2.1~ ACTION STATEMENT, REQUIREMENTS WERE MET.
NOT APPLICABLE: -
THE PROTECTIVE FUNCTION, IF REQUIRED. WOULD HAVE BEEN INITIATED FROM TN WESTINGHOUSE ELECTRIC CORP.'
E "A" TRAIN'SSPS..
~~
FAULTY CONNECTION IS ATTRIBUTABLE'TO A CONTACT FILM BUILD-UP.
THE FILM WAS REMOVED, THE STP RE-PERFORMED, AND THE CHANNEL WAS RETURNED TO SERVI L CE AT,1100 ON 12/20/79. THE STP WILL BE REVISED TO REQUIRE USING A HIGN ER CURRENT-RESISTANCE MEASUREMENT DEVICE WHICH WILL. ELIMINATE THE CONTAC
~
T FILM BUILD-UP.
^
120779
.WHILE INSPECTING SAFETY-RELATED LINES FOR SEISMIC QUALIFICATION AS-REQ B KEWAUNEE-1 05000305
'OTHER ENGNRD SAFE 1Y FEATR SYS
'79-028/03L-0 010780 Y IE BUL 79-14, 3 HORIZONTAL PIPE RESTRAINTS -DISCOVERED MISSING ON 16" S-
' HANGERS, SUPPORTS, SHOCK.SUPPRSS 027827 30-DAY ERVICE H2O HEADER. SEISMIC REAHALYSIS REVEALED MOVEMENT GREAT ENOUGH TO-
. OTHER INCREASE PROBABILITY OF FAILURE OF 2, 4" BRANCH LINES. FAILURE OF^ BRAN'
' DESIGN / FABRICATION ERROR CH LINES COULD RESULT IN INOP OF 2 AUX FEEDWATER PUMPS. FUNCTION OF.A 3 DESIGN RD~ AUX FEEDWATER PUMP WOULD BE MAINTAINED. ONE PUMP IS' SUFFICIENT TO CD
' ITEM NOT APPLICABLE PE WITH' TRANSIENTS DESCRIBED IN THE KEWAUNEE FSAR.
l ORIGINAL SEISMIC ANALYSIS REQ INSTALLATION.0F THESE'3 RESTRAINTS. DUE T-l 0 APPARENT OVERSIGHT BETWEEN SEISMIC ANALYSIS & HANGER DESIGN TEAMS, RES TRAINTS WERE NEVER DESIGNED OR INSTALLED. A DESIGN FOR THESE HANGERS PE' RFORMED, APPROVED & HANGERS INSTALLED. NO FURTHER ACTION HELESSARY ON"T-
.HIS CONCERN.
EVALUATIONS' CONTINUING UNDER IE BULLETIN-79-14.
MCGUIRE.
05000369 062279 WESTINGHOUSE NOTIFIED DUKE POWER THAT THE STEAM GENERATOR SECONDARY-SIDE-3 MAIN STEAM' SUPPLY SYS + CONT 79-
/02L-0 082479 WATER LEVEL INSTRUMENTATION CDULD BECOME HEATED DURING A HIGH ENERGY LI i.
1 INSTRUMENTATION + CONTROLS
'027878 30-DAY NE BREAK IN THE CONTAINMENT. THIS WOULD DELAY S/G LOW-LOW SIGNAL TO.TRI.
' N0' SUBCOMPONENT PROVIDED P THE REACTOR, THEREFORE ADVERSELY AFFECTING PLANT SAFETY.
~~
DESIGN / FABRICATION ERRCR
.-CAUSE SUBCODE NOT PROVIDED U
ITEM NOT APPLICABLE THE DEFICIENCY WAS CAUSED BY A DESIGN OVERSIGHT. WESTINGHOUSE IS INVEST IGATING THE POSSIBLE EFFECTS ON THE MCGUIRE NUCLEAR STATION AND WILL INF ORM DUKE POWER AND THE HRC OF ANY NEEDED MODIFICATIONS.
~
n i
j nn-
Ien:
'A
~ b
~
IFEB07,[1980)
.LER OUTPUT ON REPORTS RECEIVED FROM 12/31/79' THRU 91/13/80 ;
PAGE 25 c,.
OUTPUT SORTED BY FACILITY'AND EVENT DATE s
4 FACILITY / SYSTEM / '
' COMPONENT / COMPONENT SUBCODE/ - DOCKET NO./ EVENT DATE/-
_CAUSE/CAUSE:SUBCODE/
- LER NO./
REPORT - DAT E/
EVENT DESCRIPTION /
4
' COMPONENT. MANUFACTURER.
CONTROL NO. REPORT TYPE CAUSE' DESCRIPTION-MIDLAND-1' 05000329
'072779-THE RACK-TENSION. CLAMP OF THE WIRE SHEAR WAS NOT FUNCTIONING DURING THE -
OTHER SYSTEMS' 79- - /02L-0 092879 MAKING OF TENDON 432-240. RESULTING IN-THE RECALL OF ALL SIMILAR TENDONS HANGERS. SUPPORTS. SHOCK SUPPRSS-027876 30-DAY PRODUCED'AT THAT-FACILITY. ~ THE USE OF THE TENDONS WOULD HAVE REDUCED T NO SUBCOMPONENT PROVIDED '
HE SAFETY MARGIN OF THE STRUCTURE THEY SUPPORT,1THE CONTAINMENT.-
DESIGN / FABRICATION ERROR CAUSE SUBCODE NOT:PROVIDED:
INLAND-RYERSON CONST. PROD.~ CO' THE DEFICIENCIES IN THE MANUFACTURING PROCESS WERE ELIMINATED.. TME TEND DNS WERE REPLACED.
MILLSTONE-1 05000245 120479 ON DECEMBER 4.
1979, AT 1030 HOURS, WHILE PERFORMING THE ROUTIME MONTHLY CNTHMNT. ISOLATION SYS + CONT 79-035/03L-0 122079 MAIN STEAM LINE LOW PRESSURE FUNCTIONAL SURVEILLANCE ONE OF THE FOUR P INSTRUMENTATION + CONTROLS 027779 30-DAY RESSURE SWITCHES RESPONSIBLE FOR INITIATION OF GROUP-I ISOLATION WAS FOU SWITCH.
HD TO TRIP OUTSIDE THE TECH. SPEC. ALLOWED PRES $URE BAND.-
THE SUBJECT L4 ECOMPONENT FAILURE WITCH OPERATED AT 877 PSIG VS. 880 PSIG. THIS WOULD HOT HAVE SIGNIFICAN INSTRUMENT.
TLY REDUCED THE MARGIN OF SAFETY, BARKSDALE COMPANY T
IT APPEARS THAT INSTRUMENT DRIFT WAS RESPONSIBLE FOR THIS OCCURRENCE.
HE SUBJECT SWITCH WAS READJUSTED AND TESTED SATISFACTORILY.
CURRENTLY,'
A SETPOINT CHANGE IS UNDER REVIEW. ANALOG REPLACEMENT INSTRUMENTS ARE A LSO BEING EVALUATED. SIMILAR OCCURRENCES RO-53-245/77-11/3L, RD-50-245/
'78-1/3L, R0-50-245/79-03/3L.
MONTICELLO-1 05000263
.111979 DURING MORMAL OPERATION, EVALUATION OF IE BULLETIN 79-02 INSPECTION RESU RESIDUAL HEAT REMOV SYS-+ CONT. 79-021/03L-0 121979 LTS REVEALED SHUBBER 55-31 BASE PLATE EXPAMSION ANCHOR BOLT SAFETY FACTC-4 LHANGERS, SUPPORTS, SHOCK SUPPRSS 027755 30-DAY R LESS THAN 1 SS-31 DECLARED INOPERABLE. CONSTITUTES OPERATION IN DE SUPPORTS.
GRADED MODE PERMITTED BY T.S. 3.6.H.2.
NO EFFECT ON PUBLIC HEALTH OR SA DESIGN / FABRICATION ERROR FETY. ANALYSIS SHOWED PIPE STRESS WITHIH CODE ALLOWABLE WITHOUT SS-31 D 1
-DESIGN, URING SSE.
REDUNDANT SYSTEM OPERABLE DURING EVENT. NOT A REPETITIVE OC BECHTEL CORP.
CURRENCE.
i REAHALYSIS INDICATED THAT ' BASE PLATE AND EXPAHSION ANCHOR BOLTS ASSOCIAT L
ED WITH SS-31 WERE INADEQUATE. THE SUPPORT WAS MODIFIED TO INCREASE SAF ETY FACTOR TO AT LEAST 2 WITHIN 72 HOURS OF EVENT IDENTIFICATION.. A SAF i-ETY FACTOR-MEETING THE LONG TERM REQUIREMENTS OF IE BULLETIN 79-02'WILL BE ASSURED.
MONTICELLO-1 05000263 121479 EVALUATION OF FUEL ASSEMBLY EXPOSURES FOP NEXT CYCLE LED TO THE DISCOVER REACTOR CORE:
79-023/01X-1 010380 Y THAT CURRENT CYCLE EXPOSURE OF SEVERAL NODES FOR ONE FUEL TYPE EXREEDE i
FUEL ELEMENTS ~
027810 OTHER D THE EXPOSURE VALUES FOR WHICH MAPLHGR LIMITS ARE SPECIFIED IN TECt SPE.
SUDCOMPONENT NOT APPLICABLE C TABLE-3.11-1, MAPLHGR VS. EXPOSURE. ACTUAL KW/FT. VALUES WERE 8 Co...i i ~~ PERSONNEL ERROR NUE TO BE CONSERVATIVELY BELOW APPROPRIATE ALLOWABLE MAXIMUM VALUES. AL OTHER 50, FOR FUEL TYPE 8DB219L PROCESS COMPUTER WAS INCORRECTLY APPLYING A MA ITEM NOT APPLICABLE PLHGR FOR 25.000 MWD /ST WHILE ACTUAL FUEL: EXPOSURE 27.000 MWD /ST.
OCCURRENCE CAUSED BY INADEQUATE INTERNAL AND EXTERNAL REVIEW. CORRECTIV-E ACTIONS INCLUDE CHANGES IN PROCESS COMPUTER CONSTANTS. DETERMINATION T i
HAT FUTURE ANALYSIS REVIEW METHODS PREVENT RECURRENCE. AND PROCEDURAL CH-ANGES TO. INCREASE NODAL EXPOSURE MONITORING AT THE PLANT.
'W l
I i
g
,~-. __
~
' PAGE 26 ^
- FES
- 07,j1980i
~LER QUTPUT ON REPORTS RECEIVED FROM 12/31/79 THRU 01/13/80 00TPUT'50RTED BY FACILITY AND EVENT DATE.
- FACILITY / SYSTEM /-
. COMPONENT / COMPONENT:SUBCODE/ -DOCKET NO./ EVENT DATE/
- CAUSE/CAUSE SUBCODE/-
'LER NO./
REPORT.DATE/'
EVENT DESCRIPTION /
COMPONENT MANUFACTURER.
CONTROL NO. RFPORT TYPE CAUSE DESCRIPTION-05000220' 051479 DURING REFUELING OUTAGE, AFTER AN EVALUATION OF TLD & FILM BADGE. IT WAS, NINE MILE POINT-1 79-011/13X 061579 DISCOVERED THAT.A RADIOGRAPHER RECEIVED A TECHNICAL OVEREXPOSURE OF 379-
- SYSTEM CODE NOT APPLICABLE. -
~
JCOMPONENT CODE NOT APPLICABLE 026071-OTHER 0 MILLIREM FOR THE 2ND QTR OF 1979.
RADIOGRAPHER-HAD BEEN CONDUCTING IN-
~5UBCOMP0HENT NOT APPLICABLE-
-SERVICE INSPECTION OPERATIONS..SOME OF WHICH WERE IN' AREAS WITM RADIATI-PERSONNEL ERROR ON LEVELS UP TO 2 REMS PER HOUR.
HE SOMETIMES FAILED TO TURN IN HIS TLD CONTRACT.'8 CONSULT. PERSONNEL S & RADIATION WORK PERMITS, & A LARGE DISCREPANCY BETWEEN THE READINGS O
~ ITEM NOT APPLICABLE F HIS DOSIMETER & TLD DEVELOPED.
(REPORT FILED IN RADIATION RECORDS.).
THE RADIOGRAPHER'S INABILITY TO ADHERE -TO RWP & ~ PROCEDURE REQUIREMENTS C OMTRIBUTED TO THE OVEREXPOSURE.~ THE. COMPUTER DOSIMETRY-SYSTEM WILL BE M.
ODIFIED TO FLAG LARGE DISCREPANCIES BETWEEN TLD & SELF-READING DOSIMETEit 8 SOME. RADIOGRAPHY P'PS WILL REQUIRE MORE FREQUENT READING OF.>
- RESULTS, s
TLDS.
OCONEE-1 05000269 120579 ON DECEMBER 5, 1979 AREA PADIATION MONITOR RIA-6.IN THE SPENT FUEL POOL
' AREA MONITORING SYSTEMS 79-035/03L-0 010480 AREA WAS' DISCOVERFD TO PE IHOPERABLE DURING ROUTINE VERIFICATION OF 'INIT INSTRUMENTATION + CONTROLS'
'027823 30-DAY I AL CONDITIONS FOR REF'sELING. REFUELING OPERATIONS HAD COMMENCED ON DEC SENSOR / DETECTOR / ELEMENT EMBER.3, 1979.
FUEL, HANDLING IN THE SPENT FUEL POOL WAS SUSPENDED UNTIL PERSONNEL ERROR.
A PORTABLE-MONITOR EQUIVALENT TO RIA-6 WAS PROVIDED. THE VENTILATION A
~ LICENSED & SENIOR' OPERATORS IR MONITOR WOULD HAVE ALERTED THE CONTROL. ROOM TO HIGH RADIATION LEVELS.
ITEM NOT: APPLICABLE DURING THE VERIFICATION OF INITIAL CONDITIONS FOR REFUELING PRIOR TO COM MENCING REFUELING OPERATIDHS, THE INOPERABILITY OF RIA-6 MISTAKENLY FAIL-ED TO BE NOTED. THE RESPONSIBLE PERSONNEL HAVE BEEN COUNSELED REGARDING THE INCIDENT, AND STEPS HAVE BEEN TAKEN TO ASSURE REPAIR OF THE MONITOR 05000270 120979 DURING ANNUAL PREVENTIVE MAINTENANCE OF ES VALVES.-THE HPI SUCTION VALVE OCONEE.
79-009/01T-0 122179 S FROM THE BORATED WATER STORAGE TANK FOR OCONEE 2 WERE INADVERTENTLY RE
.EMERG CORE COOLING.SYS + CONT VALVE OPERATORS 027795 2-WEEK NDERED INOPERABLE. ONLY ONE VALVE-WAS OUT OF SERVICE AT A TIME. SO THE ELECTRIC MOTOR - AC BWST WAS ALWAYS AVAILABLE TO SUPPLY THE HPI PUMPS IF REQUIRED. IN ADDIT PERSONNEL' ERROR ION. THE LETDOWN STORAGE TANK WAS AVAIL ABLE AS A SOURCE OF WATER. THERE MAINTENANCE & REPAIR PERSONNEL FORE, INCIDENT IS CONSIDERED TO BE OF N0' SIGNIFICANCE WITH RESPECT TO.SA LIMITORQUE CORP.
FE.0PERATION, 2 HEALTH & SAFETY OF THE PUBLIC WERE NOT AFFECTED.
LIMIT SWITCHES FOR EQUIVALENT OCONEE 1 VALVES WERE TO HAVE BEEN CLEANED.
BUT LIMIT SWITCH ASSEMBLIES FOR NEARBY OCONEE 2 VALVES WERE INADVERTENT-LY REMOVED 8 CLEANED. VALVES TESTED TO VERIFY-OPERABILITY. 3 RESPONSIBLE.
PERSONNEL COUNSELLED & DISCIPLINE
D. PROCEDURE
S WILL BE REVISED TO INCLU DE PLACING TAGS ON COMPONENTS WHOSE ELECTRICAL BREAKERS HAVE TAGGED 0UT.
PEACH BOTTOM-2 05000277 112779 PURSUANT TO NRC INFORMATION HOTICE 79-28.'
ENGINEERING ANALYZED FOUR CON l
OTHER SYSTEMS 79-052/01T-0 121179 CRETE BLOCK WALLS LOCATED NORTH AND SOUTH OF NORTH AND SOUTH ISOLATION V:
HANGERS. SUPPORTS, SHOCK SUPPRSS O27793 2-WEEK ALVE ROOMS RESPECTIVELY. IN BOTH REACTOR BUILDINGS. ANALYSIS OF THE SE OVHER ISMIC CAPABILITIES OF THE SUBJECT WELLS INDICATED THAT USING PRESENT DAY DESIGN / FABRICATION ERROR CALCULATIONAL METHODS THE SAFETY FACTORS OF THE CONCRETE EXPAHSION BOLT
~~
DESIGN S ASSOCIATED WITH THE CHANNELS WHICH SUPPORT THE ABOVE WALLS ARE GREATER BERGEN-PATTERSON PIPE SUPPORT THAN 2.
BUT LESS THAN THE DESIRED SAFETY FACTOR OF 4.
THIS NON-CONSERVATIVE CONDITION WAS CAUSED BY DEFICIENT ENGINEERING DESI GN.
MODIFICATIONS TO CONCRETE BLOCK WALLS INCLUDE ADDITION OF 18" CHANN EL TO BE BOLTED OR WELDED TO EXISTING CHANNELS OR BEAMS, RESPECTIVELY, T 0 RAISE BOLT SAFETY FACTORS TO MINIMUM OF 4 CORRECTIVE ACTION FOR UNIT*
3 WALLS SCHEDULED TO BE COMPLETE 12/15/79 AND UNIT 2 BYL1/1/80.
1
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- scR CITPUT ON REPORTS RECEIVED FROM 12/31/79 THRU 01/13/80 PAGE'27.'-[
i
(
.0UTPUT SORTED BYsFACILITY.AND EVENT: DATES (FACILITY / SYSTEM 1
" COMPONENT / COMPONENT SUBCODE/'.... DOCKET NO./ EVENT DATE/
lE
^
LER NO./'. - REPORT DATE/-
EVENT.DESCRIPTIOW/
~
i CA%SE/CAUSE SUSCODE/-
s J COMPONENT;MANUFACTURERE,
CONTROL.MO. REPORT. TYPE.
CAUSE DESCRIPTION /
S, s-s
.~....
05000277 1120779 DURING OPERATION ON.5/20/79 THE.RECIRCUL ATION SYSTEM SAMFLE ' ISOLATION VA ;
" PEACH BOTTOM-2J....-
- 79-053/01T-0 122179 LVE,-A0-2-2-40, FAILED TO OPEN..'A JUMPER WAS INSTALLED TO RESTORE MANUA iCNTNMNT^ ISOLATION SYS'+1 CONT:
' COMPONENT CODE NOTuAPPLICABLE.
E027841:
'2-WEEK' L OPERATION. ON 12/7/79 IT WAS RECOGNIZED'THAT'THE: JUMPER-INNIBITED AUT:
OMATIC ISOLATION. S AFETY SIGNIFICANCE IS SMALL. BECAUSE.TNE REDUNDANT lIN V T'SUBCOMPONENTfNOTiAPPLICABLE
' PERSONNEL. ERROR' NER VALVE WAS OPERABLE.
OTNERJ.
s cITEM NOT APPLICABLE.
TECHNICAL PER50NNEL ERROR. ' FAILED TO IDENTIFY ALLJACTIONS CAUSED BY INS-l-
_~.
TALLATION OF-JUMPER.
IMPORTANCE OF-PROPERLY: IDENTIFYING JUMPER. ACTION W:
AS STRESSED. JUMPER WAS REMOVED. BOTH INNER AND. OUTER VALVES WERE SUCC; JC ESSFULLY TESTED FOR OPERATION. REVIEW OF JUMPER LOG ENTRIES ON.RPS.ECC S.-AND'PCIS WAS CONDUCTED AND NO ABNORMALITIES WERE FOUND....
PEACH BUTTOM 3 05000278 063079
'DURING SURVEILLANCE TESTING, MAIN STEAM SAMPLE LINE INBOARD ISOLATION.VA' ~ O E
JCNTNMNT/ ISOLATION SYS'+_ CONT-79-021/03X-1 010480:
LVE, A0-3-2-316 FAILED-TO CLOSE.
IN ACCORDANCE WITHtTECH. SPECS. 3.7.D.'
. VALVE OPERATORS
'026411 OTHER.
2,' THE REDUNDANT. 0UTBOARD ISOL ATION VALVE WAS OPERABLE < AND CLOSED. 'THE a
~
- ' PNEUMATIC / DIAPHRAGM / CYLINDER DAILY-SURVEILLANCE. REQUIREMENTS-FOR-THE REDUNDANT ISOLATION VALVE WERE P.
ERFORMED UNTIL THE FAILED VALVE COULD BE CHECKED DURING.THE RECENT UNIT.
4 0THER : -
3 REFUELING OUTAGE.
/NOT APPLICABLE BLACK,$IVALLS:4-BRYSON,~INC.
IT OPERATED-($TROK-THE VALVE WAS INSPECTED DURING THE REFUELING'0UTAGE.
ED) SATISFACTORILY. MOST PROBABLE CAUSE OF VALVE FAILURE TO 'CLOSE WAS.V ALVE PACKING BINDING OR SOLENOID VALVE STICKING-WHEN THE VALVE WAS-AT IN -
GH TEMPERATURE. AS PRECAUTIONARY MEASURE PACKING AND SOLEN 0ID WERE REPL-
, PEACH. BOTTOM-3<
^05000278 - 111379 SUR kILLANCE. TESTING ON THE RSCS (ROD. SEQUENCE CONTROL--SYSTEM) PRIOR T01 ENGNRD SAFETY-FEATR ' INSTR SYS 79-037/03L-0 121379 ROD WITHDRAWAL REVEALED THAT WITH THE RSCS MODE SWITCH AND THE GROUP NOT,.
iH SELECT SWITCH IN." NORMAL *'ANY' ROD GROUP COULD PE SELECTED..TO SELECT' INSTRUMENTATION + CONTROLS 027788 DAY C
~ COMPUTATION MODULE
' A ROD WITH'BOTH SWITCHES-AS STATED ABOVE, OPPOSITE ROD GROUPS SHOULD BE-FULL CUT (IE. TO SELECT A12, ALL B12 AND B34 RODS MUST BE FULL CUT). ' TN 1 COMPONENT FAILURE '
.IS MADE THE " SEQUENCE" MODE OF RSCS INOPERABLE AS REQUIRED BY. TECH SPEC
.. ELECTRONIC GENERAL ELECTRIC CO.
4.3.B.3.w.
THE MALFUNCTION WAS CAUSED.BY A FAILURE IN AN INTEGRATED CIRCUIT " CHIP"-
ON THE SEQUENCE. LOGIC-BOARD. THE INTEGRATED CIRCUIT CHIP, GE PART,NUM8E R 176A1664P945. WAS REPLACED. THE RSCS WAS TESTED SATISFACTORILY AND OP.
ERABLE IN LESS TMAN 12 HOURS. ROD WITHDRAWAL DID NOT-COMMENCE UNTIL THE.
FAILURE WAS CORRECTED.
05000278 112079 REVIEW OF A SURVEILLANCh TEST COMPLETED ON 11/19/79 REVEALED THAT THE 2
' PEACH BOTTOM-3,
79-038/01T-0 120679 MSIV'S IN THE "A" STEAMLINF CLOSED IN TIMES SHORTER THAN SPECIFIED IN TE-
' MAIN ^ STEAM ISOL'SYS + CONTROLS
-VALVE OPERATORS 027789 2-WEEK CH SPECS 3.7.D.3.
FASTER CLOSURE-.THAN SPECIFIED INCREASES THE PRESSURE.
t
- t 1 HYDRAULIC REACHED DURING A MAIN STEAMLINE ISOLATION. THE AVERAGE ISOLATION TIME F-
PERSONNEL ERROR-OR ALL 4' LINES WAS MORE THAN 2.8 SECONDS. THE TRANSIENT ANAiYSIS SHCWS.
LICENSED 8-SENIOR OPERATORS NO SIGNIFICANT.' EFFECTS FOR A'3.SECOND. ISOLATION, THEREFORE IT'IS BELIEVE-HYDRO.LINE MFG., COMPANY D 2.8 SECONDS WOULD BE WITHIN THE CONSERVATISM OF THE ANALYSIS.
THE OPERATOR-PERFORMING THE TEST DID NOT RECOGNIZE-THAT THE CLOSURE TIME-
- FOR THE "A" MSIV'S WAS TOO FAST.
UPON DISCOVERY OF THE RESULTS, REACTO PJ POWER WAS' REDUCED TO 75% AND THE "A" STEAMLINE ISOLATION VALVES WERE C LOSED. THE IMPORTANCE OF THE EVENT HAS BEEN. STRESSED 'TO THE OPERATOR AN -
D THE APPLICABLE PROCEDURE HAS BEEN REVISED'TO PREVENT RECURRENCE.
m-m,-w-
s e
os; FEB;07,91980 LER CUTPUT ON REPORTS' RECEIVED FROM 12/31/79 THRU 01/13/80-PAGE~28:
OUTPUT SORTED.BY FACILITY AND EVENT.DATE
- FACILITY / SYSTEM / -
COMPONENT / COMPONENT.SUBCODE/ -DOCKET NO./ EVENT DATE/
CAUSE/CAUSE SUBCODE/
,LER MO./
REPORT DATE/
EVENT DESCRIPTION /
COMPCNENT MANUFACTURER-CONTROL NO. REPORT TYPE CAUSE DESCRIPTIDH
'05000278' 120679 DURING ROUTINE SURVEILLANCE TESTING, THE "C" CORE SPRAY P' UMP DISCHARGE P
~
PEACH BOTTOM-3
.-... CONT 79-040/03L-0 010380 RESSURE SWITCH PSE-14-44C WA% FOUND TO BE 9.0 PSIG ABOVE THE LIMITS IN T.
EMERG CORE COOLING SYS 4 INSTRUMENTATION + CONTROLS 827836 30-DAY HE TECHNICAL SPECIFICATIONS (180 +/- 10 PSIG). THE INSTRUMENT,'WHICN PR 0VIDES A PUMP RUNNING SIGNAL TO THE ADS LOGIC, WAS CALIBRATED AND RESTOR
. SWITCH
' COMPONENT FAILURE :
ED TO SERVICE WITHIN 15 MINUTES.-. REDUNDANT INSTRUMENTAITON WAS OPERABLE' INSTRUMENT STATIC-0-RING.-
THE~ INSTRUMENT, STATIC-0-RING MODEL SM-AA3 PRESSURE SWITCH, WAS DUT OF C
?1 ALIBRATION DUE TO SETPOINT DRIFT.
THE INSTRUMENT WAS RECALIBRATED, ' '!T
.ED SATISFACTORILY AND RETURNED TO SERVICE..
PEACH BOTTOM-3 05000278 121079 WHILE SHUTD0'4N FOR MAINTENANCE FEEDWATER FLUSH VALVE M03-2-38A FAILED T
~
CNTHMNT ISOLATICN.SYS + CONT.
79-041/03L-O 010980 0.CLOSE DURING PERFORMANCE OF ST 1.3-1 (PCIS LOGIC SYSTEM FUNCTIONAL TES
. VALVE OPERATORS..
'027837 30-DAY T) MAKING IT AN INOPERABLE ISOLATION VALVE PER TECH SPEC 3.7.D.1 AND. TAB
. ELECTRIC MOTOR - AC LE 3.7.1 THIS VALVE IS CLOSED DURING POWER OPERATION AND IS USED ONLY COMPONENT FAILURE DURING SHUTDOWN CONDITIONS. ALSO.THE INNER. ISOLATION CHECK VALVE WAS.0P
,MECNAMICAL ERABLE.
.LIMITORQUE CORP.
FAILURE'0F THE VALVE TO CLOSE WAS CAUSED BY IMPROPER OPERATION OF A LIMI.
T SWITCH IN THE AUTOMATIC CLOSURE LOJIC OF THE VALVE. THE LIMIT SWITCH (LS-7) WAS CLEANED AND ADJUSTED. THE VALVE WAS PROVEN OPERABLE 0? 12/10
/79 BEFORE THE PLANT WAS RESTARTED.
. PILGRIM-l 05000293 081279 ON AUGUST 12 '1979, THE POSITION' 0F ASSISTANT STATION MANAGER, AS PROPOS 0THER SYSTEMS 79-046/03;-o 121479 ED IN A LETTER TO THE COMMISSION DATED SEPTEMBER 27, 1979. WAS FILLED.
COMPONENT CODE NOT APPLICABLE
' 027831 30-DAY THIS PROPOSAL NECESSITATED A CHANGE TO THE STATION ORGANIZATIONAL CHART.
SUBCOMPONENT NOT APPLICABLE (FIGURE 6.2.2 IN THE TECHNICAL SPECIFICATIONS). THE OPERATIONS REVIEW OTHER COMMITTEE COMPOSITION (SECTICH 6.S.A.2) HAS ALSO BEEN CHANGED.TO INCLUDE NOT APPLICABLE A "VICE-CHAIRMAN".
ITEM NOT APPLICABLE THIS POSITION WAS MADE NECESSARY DUE TO THE GREATLY INCREASED WORK LOAD -
ON THE STATION MANAGER.
IN ADDITION, REPORTING ASSIGNMENTS HA*/E BEEN AD, JUSTED TO ACCCMMODATE THIS CHANGE.
PILG2IM-1 05000293 111479 ON HOVEMBER 14, 1979 AFTER HPCI VALVE 2301-4 WAS BACKSEATED TO PREVENT'I REACTCR CONTAINMENT SYSTEMS 79-045/03L-0 021179 TS LEAKAGE INTO THE DRYWELL, THE DIFFERENTIAL PRESSURE sETWEEN THE DRYWE
. VALVES 027796 30-DAY LL'AND SUPPRESSION CHAM 3ER DECREASED TO LESS THAN 1.50 PSID. THIS IS CD:
GATE NTRARY TO SECTICH 3.7.A.1.I 0F TECHNICAL SPECIFICATIONS.
'ERSCSNEL' ERROR LICESSED 1 SENIOR OPERATORS ITEM NOT APPLICABLE DECREASING THE 2301-4 VALVE LEAKAGE-TO THE-DRYWELL CAUSED THE CRYWELL PR ESSURE TO DECREASE THEREBY CAUSING THE DRYWELL'TO SUPPRESSION CHAMBER DI FFERENTIAL PRESSURE TO DECREASE. NITROGEH MAS ADDED TO THE DRYWELL.AND RBCCW TEMPERATURE WAS INCREASED..THIS ACTICH INCREASED THE DRYWELL TO $
UPPRESSION CHAMBER DIFFERENTIAL PRESSURE TO 1.50.
7
~
i no
. PAGE 29 LER'0UTPUT ON REPORTS RECEIVED FROM 12/31/79 THRU 01/13/80
!FEB'07, 1980' OUTPUT SORTED BY FACILITY AND EVENT DATE
' FACILITY / SYSTEM /
DOCKET NO./ EVENT DATE/
EVENT DESCRIPTION /.
COMPONENT / COMPONENT SUBCODE/J CAUSE/CAUSE SUBCODE/-
LER HO./-
REPORT DATE/
CAUSE DESCRIPTION COMPONENT MANUFACTURER CONTROL HO. REPORT TYPE ON HOVEMBER 17 AND AGAIN OH HOVEMBER'20, 1979. THE FIRE BRIGADE WAS REDU 05000293 111779-CED TO LESS THAN THAT REQUIRED BY TECHNICAL SPECIFICATIONS 6.2.B.6 FOR A'
' PILGRIM-1'...
'79-047/03L-0 121779 PERIOD OF APPROXIMATELY FOUR HOURS. THE FIRE BRIGADE WAS NOT REQUIRE
. SYSTEM CODE NOT APPLICABLE COMP 0HEHT CODE HOT. APPLICABLE 027800 30-DAY DURING THIS TIME, THEREFORE, THE HEALTH AHD SAFETY OF 'THE PUBLIC WERE NO SUBCOMPONENT NOT APPLICABLE
'T AFFECTED.
. PERSONNEL-ERROR CONTRACT.'1 CONSULT.-PERSOHHEL~
ITEM NOT'APPLICAFLE THE CAUSE OF THIS' EVENT WAS SECURITY SHIFT SUPERVISORY PERSONNEL CNAN G PRIORITIES OF ASSIGHED TASKS AND CONTRADICTIFG DIRECTIVES ISSUED BY TH E CHIEF OF SECURITY. THE REQUIREMENTS TO MAINTAIN FIRE BRIGADE REQUIREM ENTS H AVE BEEN RE-EMPHASIZED.
1979 BOSTON-EDISDN WAS NOTIFIED BY YANKEE ATOMIC ENVIROH 05000293 111979 OH NOVEMBER 19, COMPOSITE SAMPLE OF AIR PA MENTAL LAB THAT A QUARTERLY (6/26 TO 9/24/79)
. PILGRIM-1
'OTHER SYSTEMS 79-04f/04T-1 121879 RTICULATES TAKEN AT THE OVERLOOK AREA CONTAINED A LEVEL OF CO-60 IN EX COMPONENT CODE NOT APPLICABLE-027708 2-WEEK THE SAMPLE INDICATED 1012 E-5
'SS OF 10 TIMES THE CONTROL STATION LEVEL.
THIS WOULD RESULT IN A D-
.SUBCOMPONENT NOT APPLICABLE PCI/M5. COMPARED TO 90E-SPCI/M3 AT THE CONTROL.
OSE OF ABOUT 2E-2 MREM TO ANY ORGAN OF A MAXIMUM EXPOSED INDIVIDUAL DU OTHER NOT APPLICABLE NG THE QUARTER.
ITEM HOT APPLICABLE IMPROVED ANALYTICAL TECHNIQUES HAVE RESULTED IN SENSITIVITIES FOR ISOTO ES WHICH ARE BELOW DETECTIDH CAPACILITIES.SPECIFIED IN TECHNICAL 5PEC CATIDH TABLE 4.8.4.
COMPARISONS AT THESE LOW LEVELS RESULTED IN A RATIO ~
GREATER THAN 10 WHICH.HECESSITATED THIS REPORT.
05000293 112979 ON HOVEMBER 29, 1979, AFTER COMPLETING ROUTINE SURVEILLANCE TESTING OF "
THE AUX. TRIP RELAY AHHUNCIATOR DID HOT CLEAR.
INV PILGRIM-1 A" DIESEL GENERATOR, EMERG GENERATOR SYS + CONTROLS 79-049/03L-0 122879 ESTIGATION OF THE DIESEL GENERATOR 0UTPUT BREAKER REVEALED A DIFFERENT 027811 30-DAY L RELAY PHASE "A" TARGET WAS DROPPED AND THE DIFFERENTIAL LOCKOUT TRIPPE RELAYS SWITCHGEAR, AUXILIARY THE DIESEL GENERATOR WAS DECLARED IHOPERABLE AND REDUNDANT TESTING C D.
PUBLIC HEA OTHER ONDUCTED IN ACCORDANCE WITH TECHNICAL SPECIFICATION 3.9.B.4.
HOT APPLICABLE LTH AND SAFETY WERE HOT AFFECTED.
ELECTRIC PRODUCTS ELECTRIC LAB PERSONNEL INVEST 1 GATED POSSIBLE CAUSES FOR THIS EVENT AN THE PHASE "A" TARGET AND DIFF ERE UNABLE TO FIND ANY ELECTRICAL FAULTS.
ERENTIAL LOCKOUT WERE RESET AND DIESEL GENERATOR OPERABILITY TEST PER MED WITH NO RECURRENCE OF THE TRIP.
POINT BEACH-1 05000266 121179 DURING HORMAL POWER OPERATION OH 12-11-79, INCREASING STEAM GENERATCR PR i
COOLANT RECIRC SYS + CONTROLS 79-021/01T-0 122279 IMARY-TO-SECONDARY LEAKAGE WAS NOTED. SECONDARY WATER SAMPLES INDICATED
]
HEAT EXCHANGERS 027821 2-WEEK A LEAK RATE OF APPROX. 250 GPD, OF WHICH APPROX. 200 GPD WAS CALCULATED TO BE FROM "B" STEAM GENERATOR. SHUTDOWN OF UNIT BEGAN AT 1713 HRS ON 12 i
STEAM-GENERATOR
/11/79. THIS EVENT IS. REPORTABLE PER TS 15.6.9.2.A.3 AND SIMILAR TO PREV l
C "" COMPONENT FAILURE IOUS LER'S 78-001/01T-0, 78'-010/01T-1, 79-003/01T-0, 79-012/01T-0, 79-08 CORROSION 3/01T-0. AND 79-017/01'T-0.'
^
WESTINGHOU$E ELECTRIC CORP.
AH 800 PSI SECONDARY SIDE LEAK TEST WAS PERFORMED IN BOTH STEAM GENERAT NO LEAKS WERE OBSERVED IN "A".
ONE LEAKING TU3E WAS FO RS ON 12-14-79.
TOGETHER WITH DRIPS IN ONE EXPLOSIVE PLUG AND ONE WELDED PLU l
UND IN "B",
G.
LEAKING TUBE WAS MECHANICALLY PLUGGED ON 12/15/79 AHO THE PLUGS WER l
WELD-REPAIRED ON 12/17/79.
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- FES 07,E1980; LER DUTPUT ON REPORTS' RECEIVED'FROM 12/31/79 THRU.01/13/80
-PAGE 38 OUTPUT SORTED BY FACILITY AND EVENT DATE FACILITY / SYSTEM /
1 iCOMPONENT/ COMPONENT SUBCODE/.
DOCKET NO./ EVENT DATE/'
m, t CAUSE/CAUSE SURCODE/-
- LER HD./
. REPORT DATE/
EVENT DESCRIPTION /~
1 COMPONENT. MANUFACTURER-CONTROL NO.. REPORT TYPE.
CAUSE DESCRIPTION-IPOINT BEACH-2' _ '
~05000301 121079 AT 2230 P.M. ON-12-10-79 DURING NORMAL OPERATION OF UNIT 2, THE UNIT 2'"
L CHEM,rVOL; CONT-+ LIQ:POISN/SYS: c79-008/03L-0. 122779 A" CHARGING. PUMP'WAS TAKEN OUT-OF-SERVICE DUE TO OBSERVED LEAKAGE:IM THE DISCHARGE MANIFOLD AREA.
"C": PUMP WAS OUT-CF-SERVICE FOR' MAINTENANCE Al PUMPS
~
027765
~ 30-DAY' T TIME.
"C" PUMP WAS RETURNED TO OPERATION AT 4:08 P.M. DN-12-10-79.,M
' RECIPROCATING.
COMPONENT FAILURE INIMAL LIQUID LEAKAGE TO RADWASTE-SYSTEM & NO MEASURABLE NOBLE GAS' RELEA.
. NATURAL END UF LIFE' SE.
"B" CHARGING PUMP OPERABLE DURING PERIOD. <MO EFFECT ON PUBLIC HEAL
'AJAX-IRON WORKS
' TH OR SAFETY. REPORTABLE PER T.S. ' 15.6.9.2.5.2 AND 15.6.9c2.B.4.
VALVE' SEAT (AJAX PART NO.~P-5717-C-2;'316-55) ON DISCHARGE'CNECK VALVE O-6 F'THE UNIT 2 "A" CHARGING PUMP WAS LEAKING. -POSSIBLE CAUSE OF VALVE SEAL
.T FAILURE'IS NORMAL FATIGUE. 'THE VALVE SEAT.WAS REPLACED.
"A" CHARGING; o
PUMP IS VARI ABLE LAPACITY,. AJAX IRON WORKS ' TYPE T-125. RECIPROCATING PI STON, THREE CYLINDER MODEL.
tr
'05000312 123178 DURING:THE 4TH CUARTER OF 1978. AN ENGINEER. RECEIVED A WHOLE BODY DOSE O RANCHO SECO-1.
78-001/13L-0 011579' F 3.45-REMS DURING-REFUELING ACTIVITIES. THE RECORD OF-THE DOSE RECEIVE.
SYSTEM CODE NOT APPLICABLE-COMPONENT. CODE NOT APPLICABLE '
'023647
.30-DAY' D DURING HIS FIRST WEEK OF WORK IN NOV. WAS MISPLACED AND WAS NOT TRANSF SUBCOMPONENT NOT~ APPLICABLE ^
ERRED.TO HIS' ACCUMULATED RADIATION TOTALS CARD.
THE ERROR WAS NOT FOUND'
' PERSONNEL.ERPOR UNTIL' DEC. 28 WHEN THE LICENSEE OBTAINED THE FILM BADGE RESULTS & BEGAN
' CONTRACT. 8 CONSULT. PERSONNEL INVESTIGATING THE. DISCREPANCY IM.THE INDIVIDUAL'S DOSIMETER AND FILM BA'
- ITEM'NGT' APPLICABLE-DGE READINGS FOR NOV.-(REPORT IN RADIATION RECORDS.)
~
DUE TO' A CLERICAL ERROR, THE ENGINEER'S ACCUMULATIVE-DOSIMETER. CARD WASE NOT' CORRECT. THE CONTROLLING PROCEDURES, FLOW OF EXPOSURE DATA, AND 'THE AUDITING OF EXPOSURE RECORDS WILL BE REVIEWED. ANOTHER RAPID READING D OSIMETRY: SYSTEM MAY BE MADE AVAILABLE TO WORKERS-EXPECTED TO GET DOSES E-XCEEDING 100 MREM PER DAY.
05000206 101079 DURING A QA AUDIT, IT WAS DISCOVERED THAT THERE WERE TWO CASES WHERE THE; LSAN ONOFRE-1.
79-023/03L-0 121179 VARIABLE LOW PRESSURE TRIP SAFETY SETTING ON ONE OF THE THREE PRESSURIZ REACTOR TRIP SYSTEMS INSTRUMENTATION:+ CONTROLS 027654 30-DAY ER PRESSURE CHANNELS WAS NOT EQUAL-TO OR GREATER THAN THE PRESCRIBED COM
' 0 tiler t PUTED VALUE FOR THE TRIP.'
THE MAXIMUM DEVIATION NOTED WAS EQUALS TO 1 PS DEFECTIVE PROCEDURES' I.
THIS CONDITION IS CONTRARY TO TECHNICAL SPECIFICATION 2.1. TABLE 2.1 NOT. APPLICABLE
. REDUNDANT SYSTEMS WERE AVAILABLE. THERE WAS NO EFFECT ON PUBLIC HEAL ITEM NOT APPLICABLE TH AND SAFETY AS A RESULT OF THIS EVENT.
THE SECTION OF THE' TEST PROCEDURE WHERE.THE ACTUAL TRIP SET POINT IS DE TERMINED DID NOT CONTAIN SPECIFIC ACCEPTANCE CRITERIA. THE TEST PROCEDU RE HAS BEEN REVISED TO INCLUDE THE ACCEPTANCE CRITERI A A1 THE DATA RECOR DING' POINT.
.SEQUOYAH-1.
05000327 062979 WESTINGHOUSE NOTIFIED TVA THAT THE STEAM GENERATOR SECONDARY SIDE WATER MAIN' STEAM SUPPLY SYS'+ CONT 79 -
/02L-072079 LEVEL INSTRUMENTATION COULD BECOME HEATED DURING A HIGH ENERGY LINE BREA
. INSTRUMENTATION + CONTROLS 027881 30-DAY K IN THE CONTAINMENT. THIS WOULD DEL AY S/G LOW-LOW SIGNAL TO TRIP THE R NO SUBCOMPONENT PROVIDED EACTOR, THEREFORE ADVERSELY AFFECTING PLANT. SAFETY.
""~ CESIGN/ FABRICATION ERROR' CAUSE SUBCODE NOT'PROVIDED ITEM NOT APPLICABLE THE DEFICIENCY WAS CAUSED.BY A DESIGN OVERSIGHT. DUE TO ICE CONDENSOR C.
ONTAINMENT DESIGN. THIS FAULT IS MINIMIZED AT SEQUOYAH. WESTINGHOUSE IS INVESTIGATING AND WILL REPORT IF ANY MODIFICATIONS ARE HEEDED.
M'
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'FEB 074J1980-LER OUTPUT ON REPORTS RECEIVED FROM 12/31/79 THRU 01/13/80 PAGE 31 OUTPUT SORTED BY FACILITY AND EVENT DATE
. FACILITY / SYSTEM /
COMPONENT / COMPONENT SUBCODE/
DOCKET NO./ EVENT DATE/
LER NO./-
REPORT DATE/
EVENT DESCRIPTION /.
CAUSE/CAUSE SUSCODE/.
CONTROL NO. REPORT TYPE CAUSE DESCRIPTION COMPONENT. MANUFACTURER 05000335 050779-DURING A REFUELING OUTAGE, SURVEILLANCE INSPECTION OF RCS' BORON CONCENTR ST.'LUCIE-t.
79-015/03L-1 102279 ATION INDICATED THE RCS BELOW THE 1720 PPM LIMIT OF T.S. 3.9.1 (1698 PPM MAIN STEAM SUPPLY SYS + CONT HEAT EXCHANGERS
~026191
' 30-DAY
).
THE BORON CONCENTRATION IN THE RCS WAS RESTORED TO PROPER-CONCENTRAT
- STEAM GENERATOR IDH IN 135 MIN.-
NO CORE ALTERATIONS OR POSITIVE REACTIVITY-CHANGES WERE :
~
DESIGN / FABRICATION ERROR OCCURRING DURING THE LOW BORON CONCENTRATION-CONDITION. MORE THAN ADE9 CONSTRUCTION / INSTALLATION UATE SHUTDOWN MARGIN WAS MAINTAINED (KEFF <0.95) THROUGHOUT THIS PERIOD.
COMBUSTION ENGINEERING -INC.
THIS IS THE FIRST OCCURRENCE OF'THIS TYPE.
EARLIER IN THE OUTAGE, TWO SC TUBES IN'1B SG WERE UNKNOWINGLY CUT BY VEN DDR WORKERS DURING SG RIM CUT MODIFICATIONS. WHEN 1B SG WAS PLACED IN W ET LAY-UP, FEEDWATER PASSED THRU THE DAMAGED TUBES INTO THE RCS AND DILU TED THE RCS BORON CONCENTRATION. THE SG AND AFFECTED RC LOOP WERE DRAIN ED'AND THE SG TUBES WERE PLUGGED PER APPROVED INSTRUCTIONS.
SURRY-1'
-05000280 12*479 WITH UNIT 1 AT STEADY STATE OPERATION. TWO MANUAL ISOLATION VALVES'FOR T.
e 0480 HE RWST CHEMICAL ADDITION-TANK (CAT) DUTLET VALVE M05-CS-102B WERE FOUND' CNTHMNT HEAT REMOV SYS + CONT 79-038/03L-0 s
30-DAY TO BE CLOSED. SUBSEQUENT TO THE DISCOVERY OF THIS CONDITION. A TEST ES VALVES; 027759 ~
GATE TABLISHED THE OPERABILITY OF THE REDUNDANT CAT GUTLET VALVE. THEREFORE T PERSONNEL. ERROR HE HEALTH AND SAFETY OF THE GENERAL PUBLIC WERE NOT AFFECTED. THE EVENT NONLIC. 0PERATIONS PERSONNEL.
IS REPORTABLE IN ACCORDANCE WITH TECH. SPEC. 6.6.2.B.3.
THE VALVES WER
' ITEM NOT APPLICABLE.
E CLOSED FOR ABOUT 38 HOURS.
THE DISCREPANCY IN VALVE ALIGNMENT WAS CAUSED BY AN OPERATOR FAILING TO FOLLOW A PROCEDURE THAT REQUIRED THE REDPENING OF MANUAL ISOLATION VALVE S FOR MOV-CS-102B FOLLOWING COMPLETION OF A TEST. OPERATORS HAVE BEEN E XPLICITLY REINSTRUCTED ON THE IMPORTANCE OF PERFORMING A PERIODIC TEST I N COMPLETE CONFORMANCE WITH THE TEST DOCUMENT.
SURRY.
05000280 121979 DURING POWER OPERATION, A-REACTOR TRIP, FOLLOWED BY SAFETY INJECTION, OC
~ COOLANT.RECIRC SYS + CONTROLS'
'79-041/21X 010280 CURRED AS A RESULT OF LOW REACTOR COOLANT FLOW IN LOOP "A".
ALL SYSTEMS MOTORS-
-027758' OTHER RESPONDED AS DESIGNED AND THE HEALTH AND SAFETY OF THE GENERAL PUBLIC W -
SUSCOMPONENT NOT APPLICABLE.
ERE NOT AFFECTED. 1AT APPROXIMATELY 3 MINUTES AFTER THE TRIP, THE SAFETY C0flPONENT FAILURE INJECTION AUTOMATICALLY INITI ATED ON A LOW STEAM LINE HEADER DIFFERENTI ELECTRICAL AL ON LOOP A.
, WESTINGHOUSE ELECTRIC' CORP.
THE REACTOR TRIP OCCURRED AS A RESULT 0F A GROUND FAULT WITHIN "1A" REAC TOR COOLANT PUMP MOTOR. THE FAILURE OF THE MOTOR WINDING'S INSULATION R ESULTED IN THE GROUNDING OF 1-RC-P-1A'S MOTOR. THE MOTOR HAS BEEN REPLA CED.
ALL EMERGENCY PROCEDURES WERE PERFORMED AS REQUIRED.
SURRY-1' 05000280 122079 WHILE AT A COLD SHUTDOWN CONDITION, RADIATION' RECORDER RR-175 STOPPED PR AREA MONITORING SYSTEMS-79-043/03L-0 011680 INTING. THIS IS CONTRARY TO TECH. SPECS. 3.11.A.5 & 3.11.B.4. AND IS RE INSTRUMENTATION + CONTROLS 027938-30-DAY PORTABLE PURSUANT TO TECHNICAL SPECIFICATI0H 6.6.2.B.(2).
THE MONITORIN RECORDER G INSTRUMENTS. INCLUDING ALARM AND TRIP FUNCTIONS REMAINED OPERABLE AND COMPONENT FAILURE-RELEASES WERE WELL WITHIN ALLOWABLE LIMITS. THEREFORE. THE HEALTH AND S
. MECHANICAL' AFETY OF THE PUBLIC WERE NOT AFFECTED.
.VICTOREEN INSTRUMENT DIV.
-THE RECORDER 3ECAME INOPERATIVE WHEN THE CONTROL STRING DISENGAGED FROM THE DRIVE WHEEL.
THE STRING WAS REPLACED AND THE RECORDER CONTINUED OPE RATING NORMALLY.
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'LER OUTPUT ON: REPORTS RECEIVED FROM 12/31/79 THRU 01/13/80 -
' PAGE 32i 1
s
. 0UTPUTiSORTED BY FACILITY.AND. EVENT DATE-
' TL 2
< FACILITY / SYSTEM /.
$ COMPONENT / COMPONENT -SUBCODE/ i DOCKET NO./f EVENT DATE/
14
-CAUSE/CAUSE-SUBCODE/s
- LER NO./
REPORT-DATE/
EVENT DESCRIPTION /
TCOMPONENT MANUFACTURER.,
CONTROL ~NO..REPORTETYPE.
.CAUSE' DESCRIPTION 05000387.
120177 DIMENSIONALLY UNDERSIZED WELDS ON SAFETY RELATED PIPE NANGERS WERE DISCO G iSUSQUEHANNA-ti..
it
.;0TNER SYSTEMS' 77-7
/02X -
040679
- VERED BY THE. LICENSEE..HOWEVER. ANALYSISsBY THE VENDOR SHOWED THAT. TME '
'4 AMAN!ERS, SUPPORTS.SH0CK"SUPPRSS 1027880' 0THER' CONDITION DOES NOT REPRESENT A SAFETY' HAZARD SINCE NO WELD WAS OVERSTRES-ENO SUBCOMPONENT PROVIDED-1 SED.
1 DESIGN /FABRICATI'N ERROR-O
,CAUSE-SUBCODE'NOT PROVIDED-
'ITTEGRINNELL' INVESTIGATION OF THE PROBLEM REVEALED THAT THE SPECIFICATION OF HANGER M' A-
. ANUFACTURER LACKED CRITERIA FOR THE ACCEPTANCE OR REJECTION OF MELDS. J A
-LL SIMIL AR WELDS WERE RE-INSPECTED;" HOWEVER: NOME WERE FOUND WITN STRESSE S EXCEEDING THE ALLOWABLE AMOUNT.
s
.JTHREE; MILE ISLAND..
'05000289' 110879-DURING INSPECTIONS REQUIRED BY I~.E.sBULLETIN 79-14.. SIZE OF SUPPORT BOLT ^
ON; RESIDUAL > HEAT-REMOV SYS'+1 CONT. :.79-017/01T-1 121179 ING FOR RIGID ANCHOR DHH-127A FOUND INADEQUATE.IN BOTH-DESIGN AND INSTAL ~
. HANGERS. SUPPORTS, SHOCK ~SUPPRSS.
027484 2-WEEK' LATION. UNDER SEISMIC CONDITIONS, < AFFECTED DECAY HEAT REMOVAL COOLING P -
SUPPORTS-IPING MAY EXCEED CODE ALLOWABLE' STRESSES.- TNIScIS REPORTABLE BYeT.S.
6...
6
-DESIGN / FABRICATION ERROR.
9.2.A(9).
CONDITION DISCOVERED'BY' ARCHITECT ENGINEER WITN PLANT.SNUTDOW
,B' DESIGN -
N. '
c ASIC ENGINEERS BOLTS'FOUND'DURING-INSPECTION WERE'5/8 INCH DIAMETER CONTRARY TO'3/4 INC:
- H DESIGN REQUIREMENT. FURTHER EVALUATION REVEALED 3/4 INCN DIAMETER BOL, TS WOULD NOT HAVE PROVIDED REQUIRED SAFETY MARGIN. REDESIGNED SUPPORT. F OR DHH-127A WILL BE INSTALLED PRIOR'TO STARTUP. SIMILAR DESIGN-. SUPPORTS IN DECAY HEAT A BLDG SPRAY' VAULTS WILL BE EVAL PRIOR TO STARTUP.
05000271 111079 CONTROL ROOM INDICATORS LI 16-19-46 A/B SHOWED INCREASING -TORUS WATER LEV--
DVERMONT YANKEE-1.
' ENGNRD' S AFETY: FEATR INSTR SYS 79-030/03L-0 121079 EL. 'AT INDICATED LEVEL'0F 1.26 FT ORDERLY SHUTDOWN-COMMENCED. BYPASS V:
,.. V ALV ES 027704 30-DAY ALVE FOR' TORUS LEVEL TRANSMITTERS HAD LEAKED AND SLOWLY DRAINED COMMON R S;
1.
J OTHER i EFERENCE LEG CAUSING ERkONEOUS READINGS. PROPER INDICATION RESTORED WIT
? PERSONNEL' ERROR.
HIN 6 HOURS ALLOWED BY TECH SPEC TABLE:3.2.6 AND PLANT POWER OPERATION C CONTRACT. S CONSULT. PERSONNEL ONTINUED.
THE-PACKING. LEAK WAS REPAIRED, THE REFERENCE LEG REFILLED. AND -THE INSTR '
i UMENTS RETURNED TO OPERATION.
'A SIMILAR OCCURRENCE WAS REPORTED AS RO 7 9-24.
I VERMONT YANKEE-1' 7.9-032/03L-0 010280 AL SPECIFICATION 3.6.I.1 REQUIRES THAT ALL SEISMIC HANGERS BE OPERABLE D-05000271 120479 SEISMIC CLASS I HANGER' CST-HD 195 FOUND DAMAGED AND' INOPERABLE.
-T ECHNIC,
EMERG CORE COOLING <SYS + CONT-
~ -027814.
30-DAY-URING POWER OPERATION.
HANGERS,5UPPORTS, SHOCK SUPPR$$
L
, SUPPORTS-
"" DESIGN / FABRICATION ERROR DESIGN-ITT.GRINNELL.
CAUSE UNDER INVESTIGATION.
ALTHOUGH NOT-CONCLUSIVE. FAILURE' IS ATTRIBUT ED TO WATER HAMMER DEVELOPED DURING FULL FLOW SURV ILLANCE TESTING OF AS.
50CIATED SAFETY SYSTEMS.
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"?FEB 07, 1980!
LER DUTPUT'ON REPORTS RECEIVED FROM 12/31/79'THRU 01/13/80 PAGE 33 OUTPUT. SORTED.BY FACILITY AND EVENT DATE FACILITY / SYSTEM /
.CAUSE/CAUSE.SUBCODE/
DOCKET NO./ EVENT DATE/
COMPONENT / COMPONENT SUBCODE/
LER'K3./
. REPORT DATE/.
EVENT DESCRIPTION /.
COMPONENT MANUFACTURER
' CONTROL'HO.. REPORT TYPE CAUSE DESCRIPTION
' VERMONT YANKEE-1 05000271-120579 REVIEW PER NRC BULLETIN 79-14 SHOWED THAT CERTAIN PIPE SUPPORTS HAD THE OTHER SYSTEMS-79-033/01T-0 121979 POTENTIAL TO EXCEED CODE ALLGWABLE STRESS IN THE EVENT OF A DESIGN BASIS
- HANGERS,5UPPORTS. SHOCK SUPPRSS 027756 2-WEEK EARTHQUAKE. MODIFICATIONS: SUPPORTS CS-HD555, CS-HD85D, RSW-H231 RSW
-HD141C, RSW-HD2318 RHR-HD205A, RHR-H119, RSW-HD254, RSW-HD39 RSW-HD17
,20THER 7B AND RHR-HD205C MODIFIED TO PROVIDE VERTICAL LOAD CAPABILITY: NEW SUPP DESIGN / FABRICATION ERROR ORTS ASCP-HD-228 AND RHR-HD-187C ADDED FOR VERTICAL LOAD CAPABILITY; BAS DESIGN ITT GRINNELL EPLATE FOR RHR-HD200E STIFFENED.
THE REPORTABLE OCCURRENCE-INCLUDES ALL SUPPORT DEFICIENCIES DISCOVERED I N THE SEISMIC ANALYSIS-REQUIRED BY NRC BULLETIN 79-14.
' WATTS'BAR-1' 05000390 040579 TVA HAS RECEIVED GENERIC INFORMATION FROM-THE VENDOR CONCERNING DEFICIEN SPEl*T FUEL STORAGE FACILITIES 79.
/02X-071079 CIES IN DOCUMENTATION OF THE DESIGN, MATERIAL AND FABRICATION OF THE SPE 0THER COMPONENTS-027722 OTHER NT FUEL RACKS.
SUBCOMPONENT.NOT APPLICABLE
' DESIGN / FABRICATION ERROR CAUSE SUBCODE NOT PROVIDED ITEM NOT APPLICABLE TVA WILL ASSESS THE INFORMATION TO DETERMINE.THE ACCEPTABILITY-OF.THE RA CKS.
WATTS BAR-1 05000390 061379 STEAM GENERATOR LEVEL INDICATORS HAVE SHOWN SIGNS OF BEING AFFECiED BY H MAIN STEAM SUPPLY SYS + CONT:
'79-
/02X-0 092179 IGH TEMPERATURE. DUE TO POSSIBLE INACCURACIES IN THE LEVEL INDICATOR RE INSTRUMENTATION + CONTROLS
'027877
,0THER ACTOR TRIP BASED ON LOW-LOW LEVEL IN S/G MAY BE DELAYED, WHICH COULD AFF ECT ADVERSELY PLANT SAFETY.' THIS DEFICIENCY ALSO APPLIES TO SEQUDYAH NU HO SUBCPMPONENT PROVIDED DESIGN /F4BRICATION ERROR CLEAR STATION.
CAUSE SUBCODE-NOT PROVIDED
. ITEM NOT. APPLICABLE THE BARTON COMPANY (WHICH FOUND THE' DEFICIENCY). THE INDICATORS WERE RE TURHED TO BARTON FOR MODIFICATION.
05000029 113079 DURING HORMAL OPERATION IN MODE 1 THE NO.' 3 STEAM GENERATOR BLOWDOWN MON YANKEE'ROWE 79-031/03L-0 122879 ITOR WAS ISOLATED TO REPAIR A LEAKING VALVE.
T.S. TABLE 3.3.4 REQUIRES PRCSS + EFF RADIOL' MONITOR SYS VALVES 027764 30-DAY THE MOHITOR TO BE OPERATIONAL IN MODE 1.
THIS IS THE FIRST INCIDENT OF GLOBE THIS NATURE. BLOWDOWN OF THE STEAM GEHERATOR WAS $ECURED DURING THE REP COMPONENT FAILURE AIR AND THE AIR EJECTOR MONITOR WAS OPERATIONAL. THEREFORE, THERE WERE
.HATURAL END'0F' LIFE NO ADVERSE EFFECTS TD (HE PUBLIC. HEALTH OR. SAFETY.
PACIFIC VALVES INC.
THE ROOT CAUSE OF THIS EVENT WAS A LEAKING MONITOR ISOLATION VALVE.
THE-MONITOR AND VALVE WERE TAKEN OUT OF SERVICE IN ORDER TO REPAIR THE VALV -
E.
THE VAttE IS A 3/4 IN. PACIFIC 600 PSI-GLOBE VALVE. THE BODY TO BON HET GASKET WAS REPLACED AND THE MONITOR WAS RETURHED TO SERVICE.
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.ect FES.07,D1980' LLER OUTPUT ON REPORTS RECEIVED FROM' 12/31/79'THRU'01/13/80
- PAGE'34 OUTPUT SORTED BY FACILITY AND EVENTfDATE FACIL' ITY/ SYSTEM /I 1 COMPONFMT/ COMPONENT SUBCODE/'
DOCKET HO./ EVENT DATE/
LCAUSEJCAUSE:SUBCODE/
LER N0'/
REPORT DATE/
EVENT DESCRIPTION /
COMPONENT MANUFACTURER-CONTROL NO.' REPORT TYPE CAUSE DESCRIPTION IT WAS NOIED THAT THE PRIMARY' VENT' STACK P 05000029-121179-DURING MORMAL OPERATION, LYANKEE"RDWE
. 79-032/03L-0 011080' ULATE RADIATION MONITOR HAD FAILED. TECHNICAL SPECIFICATIONS 3.3.3.1 RE-
. AIRBORNC RADIDACT MONITOR,SYS
( MOT!RS-027767.
30-DAY QUIRES THIS CHANNEL TO BE OPERABLE AT ALL TIMES. PUMP-MOTOR FAILURE IS-
~
' SUBCOMP0 KENT NOT' APPLICABLE' THE FIRST OCCURRENCE OF THIS' NATURE AT THI$' FACILITY. NO RELEASES OCCUR RED AND. FIXED PARTICULATE GRAB SAMPLES WERE TAKEN WHILE THE MONITOR WAS
. COMPONENT 1.'ILURE '.
'0UT OF SERVICE. BASED ON THE ABOVE,'THERE WAS NO ADVERSE EFFECTS TO THE.
NATURAL END MF LIFE.
WESTINGHOUSE ELECTRIC CORP' PUBLIC AS A RESULT OF THIS OCCURRENCE.
' THE ROOT CAUSE OF THIS OCCURRENCE WAS THE NATURAL END' 0F LIFE OF ONE OF THE PUMP-MOTOR BEARINGS.~ THE PUMP-MOTOR IS A SER-EL73; TYPE FJ; 1 HP; F-RAME H56; CODE K; -1725 RPM; SINGLE PHASE UNIT MANUFACTURED BY WESTINGHOU-SE CORP.
THE PUMP-MOTOR WAS REPLACED IN KIND. NO FURTHER ACTIONS ARE D EEMED NECESSARY AT THIS TIME..
' ZION-1.
/
'05000295 120679 DURING REFUELING OPERATION THE GAS DECAY TANK' RAD MONITOR ORT-PR02BLALAR
..PRCSS + EFF RADIOL MONITOR SYS 79-092/03L-0 010480 MED WHEN - THE INDICATOR NEEDLE READ BELOW THE ALARM SETPOINT..THE MONITOL INSTRUMENTATION +. CONTROLS 027825 30-DAY R WOULD NOT RESET. IT WAS T AKEN 0.0.S. AND SHIFTLY GRAB SAMPLES WERE TA INDICATOR KEN AS REQUIRED BY T.S. 3.14.1.C.
'THERE WERE NO SAFETY IMPLICATIONS AMD.
. COMPONENT FAILURE THE HEALTH AND SAFETY OF THE GENERAL PUBLIC WERE NOT AFFECTED.
NATURAL..END OF LIFE OTHERr THE INDICATOR NEEDLE OF THE MONITGR BECAME DISLODGED FROM ITS' JEWEL BEAR ING.
THIS WAS CAUSED BY ACCIDENT AL -J ARRING OF THE MODULE. THE METER' WA S REPLACED (DIXSON P/M 330) AND AN INTERMITTENT CONTACT ON THE ALARM CAR ^
D WAS REPAIRED. THIS IS THE FIRST OCCURRENCE OF-THIS EVENT. NO FURTHER CORRECTIVE ACTION IS HECESSARY.
05000295 120779 DURING DUT OF-SERVICE SURVEILLANCE REQUIREMENTS (T.S. 3.14.1.C) FOR THE'-
~ ZION-1 79-091/03L-0 010380 GAS DECAY TANK CUBICLE RAD MONITOR, ORT-PR02B, ONE SHIFTLY GRAB SAMPLE W'
. SYSTEM CODE NOT APPLICABLE COMPONENT CODE NOT APPLICABLE 027824 30-DAY AS NOT TAKEN. THIS IS A VIOLATION UNDER T.S. 6.6.E.A.(2).
THE CUBICLE
-SUBCOMPONENT NOT APPLICABLE WAS UNOCCUPIED DURING THE SHIFT AND GRAB SAMPLES FOR THE PRECEEDING AND PERSONNEL'ERPOR FOLLOWING SHIFTS SHOWED MINIMAL ACTIVITY. THUS THERE WERE NO SAFETY ' IMP RADIATION PROTECTION PERSONNEL LICATIONS AND THE HEALTH AND SAFETY OF THE GENERAL PUBLIC WERE NOT AFFEC
~-ITEM NOT APPLICABLE' TED.
AN INVESTIGATION REVEALED THAT RAD PROTECTION WAS'HEGLIGENT IN FAILING T 0 OBTAIN A SAMPLE AND OPERATING WAS. NEGLIGENT IN FAILING TO NOTIFY RP T0f 0BTAIN A SAMPLE. BOTH GROUPS WERE RE-INSTRUCTED ON THE IMPORTANCE OF 'O 05 SURVEILLANCE AND COMPLIANCE WITH THE TECH. SPECS. HQ FURTHER ACTION-IS NECESSARY.
ZION-1 05000295 122879 THE PH OF ALL EFFLUENTS DISCHARGING INTO THE CONDENSER COOLING WATER SH DEMIN WATER MAKE-UP 79-094/04T-0 010780 ALL BE IN THE' RANGE OF 6-8 ACCORDING TO APPENDIX B, SECTION 1.3 0F THE Z.
PUMPS 027826 2-WEEK ION TECHNICAL SPECIFICATI0HS. THE PH OF THE EFFLUENT FRGM THE WASTE WAT CENTRIFUGAL ER TREATMENT FACILITY WAS MEASURED TO BE IN THE 4.1 TO 4.77 RANGE FROM D
-COMPONENT FAILURE EC. 27 TO DEC. 29.
A. TOTAL OF 5760 GALLONS OF' ACID SOLUTION WAS DISCHAR MECHANICAL.
GED TO CONDENSER COOLING WATER, WHERE IT WAS THEN FURTHER* DILUTED BY A F INGERSOLL-RAND CO ACTOR OF 184,000 TO 1.
HAD AN ACIDIC SOLUTION LEAK WHICH DR THE WASTE NEUTRALIZATION TANK (WHT)
AINED VIA BAD PACKING GLANDS (WNT PUMPS) TO THE WASTE WATER TREATMENT FA CILITY.
IMMEDI ATE CORRECTIVE ACTION WAS NEUTRALIZING AND DISCHARGING WN T.
A WORK REQUEST HAS BEEN WRITTEN TO REPAIR PUMP PACKINC GLANDS.
FREF NOW ON LARGE AMOUNTS OF ACIDIC SOLUTION WILL NOT BE TRANSFERRED TO WNT.
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