ML18041A135

LER 86-004-00:on 860601,heater Drain Tank Level Control Channel Failed & Both Heater Drain Pumps Tripped.Caused by Severe Lightning Storm.Heater Drain Tank Level Control Channel Power Supply replaced.W/860701 Ltr

ML18041A135
Person / Time
Site:	Yankee Rowe
Issue date:	07/01/1986
From:	Boutwell L, St Laurent N YANKEE ATOMIC ELECTRIC CO.
To:	NRC OFFICE OF ADMINISTRATION (ADM)
References
LER-86-004, LER-86-4, NUDOCS 8607100426
Download: ML18041A135 (354)

Text

0 FORM 1 LER SCSS DATA 08-30-91,

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DOCKFT YEAR LER NUMBER REVISION DCS NUMBER NSIC iVENT DATE 029 1986 004 0 8607100426 199889 06/01/86 DOCKET:029 YANKiE ROWE TYPE:PWR e REGION: 1 NSSS:WE ARCHITECTURAL ENGINEER: SMXX FACILITY OPERATOR: YANKEE ATONIC ELECTRIC CO ~

SYMBOL: YAE COHNENTS STEP 2: NODEL 2AX-PS9A STEP 16: COMP HEI-CONCENTRATOR EFF DX-UNSPECIFIED DAMAGE REPORTABILITY CODES FOR THIS LER ARE:

13 10 CFR 50 ~ 73(a) (2) (iv): ESF actuations REFERENCE LERS:

029/83-022 ABSTRACT POWER LEVEL 101 X ~ WHILE OPERATING AT 100X POWER IN HODE 1 ON JUNE 1 r 1986r A SEVERE LIGHTNING STORM CAUSED A DISTURBANCE ON THE PLANT'S 120 VOLT A C ~ H-G SET DISTRIBUTION PANEL ~ THE RESULTING VOLTAGE SURGE CAUSED THE FAILURE OF THE HEATER DRAIN TANK LEVEL CONTROL CHANNELr WHICH TRIPPED BOTH HEATER DRAIN PUMPS THE LOSS OF THE HEATER DRAIN PUMPS TRIPPEO THE THREE BOILER- FEFD PUMPS ON LOW SUCTION PRESSURE WITH A RESULTING LOSS OF FEEDMATER ATTENPTS TO RESTART THE PUNPS FAILED AND THE REACTOR SCRAMMED AT 2034 HOURS ON LOW STEAN GENERATOR LEVEL ~

ALL AUTOMATIC SAFETY SYSTEMS FUNCTIONED AS REQUIRED OR WERE AVAILABLE FOR OPERATION EXCEPT FOR PANALARNS N A34r N A35r N A36r N A40r N A41r N A42r N A46r N A47r N A48r T C79r T CBOr AND T C90 THROUGH T CI02 ~

THE HEATER DRAIN TANK LEVEL CONTROL CHANNEL POWER SUPPLY WAS FOUND DAMAGED AND WAS REPLACED THERE WAS NO ADVERSE AFFECT ON THE HEALTH OR SAFETY OF THE PUBLIC AS A RESULT OF THIS EVENT ~ THIS IS THE FIRST EVENT OF THIS NATURE ~ 'HE PLANT 'WAS RETURNED TO POWER ON JUNE 3r 1986 ~

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FORM LER SCSS DATA 08-30-91 DOCKET YEAR LER NUtlBER REVISION DCS NUNBER NSIC EVENT DATE 029 1989 002 0 8902170016 213101 01/11/89

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e DOCKET:029 YANKEE ROME REGION: 1.

TYPE:PWR NSSS:ME ARCHITECTURAL ENGINEER: SWXX FACILITY OPERATOR. YANKEE ATONIC ELECTRIC CO SYMBOL: YAE g CONNENTS STEPS 4 5: EFF IX - VOLTAGE FLUCTUATIONS y WATCH-LIST CODES 40 PROCEDURAL FOR THIS DEFXCXENCY l ER ARE:

REPORTABILITY CODES FOR THIS LER ARE:

DOOZY'N 13 10 CFR 50 73(a) (2) (iv): ESF actuations.

ABSTRACT POMER LEVEL 1/11/89r AT 1937 HOURSr WITH THE PLANT XN NODE 3r WHILE CONDUCTING CONTROL ROD DROP TIME MEASUREHENTS FOLLOWING A REFUELXNG OUTAGEr. TH REACTOR PROTECTION SYSTEM AUTONATICALLY ACTUATED'T THE TINE OF THE EVENT THE NO ~ 1 VITAL BUS XNVERTER WAS OUT OF SERVICE FOR HAXNTENANCEr WITH THE VITAL BUS XNVERTER POWER SUPPLY IN BYPASS IN THIS CONFIGURATION POWER TO THE VITAL BUS WAS SUPPLIED FROM EHERGENCY HCC-5. THE REACTOR MAS SUBCRITICAL AND THE GROUP A CONTROL RODS MERE AT 82 INCHESr BEING WITHDRAWN TO 90 INCHES ~

THE ROOT CAUSE OF THIS EVENT IS ATTRIBUTED'TO A VOLTAGE FLUCTUATION ON THE VITAL BUS WHICH INDUCED A FALSE HIGH STARTUP RATE SCRAM SIGNALr OPENING THE SCRAH BREAKERSr BK 1 AND BK 2 ~ THE UNPLANNED OPENING OF BK-1 AND 2 CONSTITUTES AN ACTUATION OF THE RPS ~ THE VOLTAGE FLUCTUATION OCCURRED WHEN THE NO 1 BOILER FEED PUMP MAS STARTED NORHALLYr THE VITAL BUS INVERTER WOULD HAVE PREVENTED THE VOLTAGE FLUCTUATION ON THE EMERGENCY MCC-5 FROl~i AFFECTING THE RPS THE OPERATORS TOOK ACTION TO PRECLUDE THE STARTING OF HEAVY LOADS WHILE THE VITAL BUS INVERTER WAS XN BYPASS ~ TO PREVENT A RECURRENCE OF THIS EVENT CONDXTIONAL PRECAUTIONS WILL BE ADDED TO THE APPROPRIATE Pl ANT OPERATING PROCEDURES ~ THIS IS THE FIRST OCCURRENCE OF THIS NATURE ~ 'O FURTHER CORRECTIVE ACTIONS ARE DEENEO NECESSARY ~ THE RPS FUNCTIONED AS DESIGNED

0 FORH 3 LER SCSS DATA 08-30-91 DOCKET YEAR LER NUMBER REVISION OCS NUMBER NSIC EVENT DATE 206 1989 002 0 8902280475 213086 01/23/89

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y DOCKET:206 SAN ONOFRE REGION:

1 5

TYPE:PMR NSSS ME ARCHITECTURAL ENGINEER: BECH FACILITY OPERATOR: SOUTHERN CALIFORNIA EDISON CO SYHBOL: SCE WATCH-LIST CODES FOR THIS LER ARE:

32 COHHUNICATION PROBLEM 35 HUMAN ERROR REPORTABILITY CODES FOR THIS LER. ARE:

10 10 CFR 50.73(a) (2) (i): Shutdowns or technical specification violations.

ABSTRACT POWER LEVEL 000% FROH 0400 TO 2300'N 1/23/89r FOLLOWING REFUELING WITH THE REACTOR VESSEL HEAD REMOVED> REACTOR REFUELING CAVITY WATER LEVEL WAS BEING REDUCED AND THE CAVITY SURFACES WERE DECONTAHINATED WITH APPROX ~ 440 GALLONS OF UNBORATED WATER ~ THIS PROCESS REDUCED THE BORON CONCENTRATION OF THE REACTOR COOLANT FROH APPROX 2663 PPH TO 2626 PPH ~ THIS REACTXVITY ADDITION MAS CONTRARY TO THE REQUIREMENTS OF TECH SPECS 3~7 AND 3 ~ Bi DUE TO AN INOPERABLE VITAL BUS AND INOPERABLE SOURCE RANGE HONXTORSr RESPECTXVELY THcRE WAS NO SAFETY SIGNIFXCANCE TO THIS EVENT SINCE THE iNXNINUN REQUIRED SHUTDOWN NARGIN OF 5% (EQUXVAI ENT TO 1900 PPN BORON CONCENTRATION) MAS NOT APPROACHED DUE TO A thXSAPPLICATION OF GUXOANCE INVOLVING THE ACCEPTABILITY OF POSITIVE REACTIVITY ADDITION FROM THE USE OF UNBORATED MAT'ER XN THE SPENT FUEL POOLr OPERATIONS AUTHORIZED A SHALL AMOUNT OF UNBORATED WATER TO BE USED WITHIN THE REACTOR REFUELING CAVITY DURING THE PROCESS'URTHERMORE~ AS A RESULT OF MISUNDERSTANDINGS BETWEEN OPERATIONS AND DECONTAHINATXON PERSONNELr THE EVOLUTION INVOLVED AN ADDITIONAL QUANTITY OF WATERs AND OCCURRED OVER A LONGER PERIOD OF TXHE (3 SHIFTS)r THAN WHAT MAS INTENDED TO BE AUTHORlZED~ THIS EVENT HAS BEEN REVIEWED WITH APPROPRIATE DECONTAHINATXON AND OPERATIONS PE RSONNEL

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FORM 4 LER SCSS DATA 08-30-91 DOCKET YEAR LER NUNBER REVISION DCS NUMBER NSIC EVENT DATE 219 1984 017 1 8501080531 194562 06/27/84

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~ DOCKET:219 OYSTER CREEK REGION:

TYPE:BMR NSSS:GE ARCHITECTURAL ENGINEER: BNRO FACILITY OPERATOR: GENERAL PUBLIC UTILITIES CORP SYMBOL: GPU g COHHENTS WATCH LIST 975 - POTENTIAL GENERIC FAULT IN CONTAINHENT ISOLATION CONTROL CIRCUIT DESXGN ~

MATCH-LIST CODES FOR THIS LER ARE:

975 POSSIBLE SIGNIFICANT EVENT REPORTABILXTY CODES FOR THXS LER ARE:

11 10 CFR 50 73(a) (2) (ii): Unanalyzed 14 10 CFR 50.73(a) (2) (v): Event that conditions could have prevented fulfillment of a safety function.

15 10 CFR 50.73(a) (2) (vii): Single failur e criteria ABSTRACT POMER LEVEL OOOX A HODIFICATION MAS IN PROGRESS MHICH INVOLVED PLANT CONPUTER SYSTEM TIE-INS ~ DURING THE PERFORMANCE OF A PROCEDURE WHICH INVOLVED THE TXE-IN OF COMPUTER WIRING TO EXISTING PLANT CIRCUITRY' NEUTRAL ELECTRICAL LEAD WAS REQUIRED TO BE LIFTED ~ THIS ACTION CAUSED 15 PRIHARY CONTAINMENT ISOLATION VALVES~ INCLUDING ALL 4 HSIV'Si TO REPOSITION THE PLANT ALSO EXPERIENCED A HALF SCRAH AT APPROX THE SAYiE TINE THAT THESE VALVES CYCLED ~ THE PREVIOUSLY LIFTED NEUTRAL ELECTRICAL LEAD AND. A FUSE PREVIOUSLY REMOVED WERE RE-INSTALLED~ THE PRIMARY CONTAINMENT ISOLATION VALVES WHICH ACTION 'N

-REPOSITIONEO MERE THEN PLACED IN THEIR PROPER POSITIONS BY OPERATOR INTERYiEDIATE RANGE MONITOR BELIEVED TO HAVE CAUSED THE HALF SCRAH WAS RANGED UP SCALEr AND THE NEUTRAL ELECTRICAL LEAD MAS ONCE AGAIN LIFTED'HE RESULTS MERE THE SANE AS BEFOREr EXCEPT THAT NO HALF-SCRAH OCCURRED ~ PLANT CONDITIONS MERE RESTORED TO NORNAL. NO VIOLATION OF THE TECH SPECS OCCURRED SINCE PRIt1ARY CONTAINMENT XNTEGRITY WAS NOT REQUIRED AT THE TIME OF THE INCXDENT~ THE VALVES REPOSITIONED DUE TO AN ABNORNAL CURRENT FLOWPATH MHICH WAS ESTABLISHED THROUGH THEIR SOLENOIDS WHEN. THE NEUTRAL LEAD MAS LIFTED THIS ABNORNAL FLOW PATH HAS SEEN VERXFIEO THROUGH PERFORNANCE OF ADDITIONAL TESTING ON THE CONTAINMENT XSOLATXON VALVE CONTROL CIRCUITRY

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FORM 5 LER SCSS DATA 08-30-91 e ****************%*************A*************A***********************

DOCKET YEAR LER NUMBER REVISION DCS NUMBER NSIC EVENT DATE 237 1 987 024 0 8709250294 206326 08/21/87 DOCKET:237 DRESDEN 2 TYPE:BWR

@ REGXON: 3 NSSS:GE ARCHXTECTURAL ENGINEER SLXX FACILITY OPERATOR: COHNONWEALTH EDISON CO ~

SYNBOL: C'WE COtdHENTS STEP 3: MODEL NO P-200-12 STEP 10: CAUSE IX AUTOMATIC TRANSFER OF POWERr EFF IH MOMENTARY LOSS OF POWER ~ STEP 20- CAUSE LX LIMITED MEMORY STEP 21: COHP OR - COVER MATCH-LIST CODES FOR THIS LER ARE:

20 EQUIPNENT FAILURE REPORTABILITY CODES FOR THIS LER ARE:

13 10 CFR 50 73(a) (2) (iv): ESF actuations REFERENCE LERS:

1 237/84-009 2 237/87-016 3 237/87-023 4 249/84-010 5 249/87-012 ABSTRACT POWER LEVEL 093% ~ ON AUGUST 21r 1987 AT 1755 HOURS WITH UNIT 2 AT APPROXIMATELY 2350 NW THERMAL (93% POWER),THE REACTOR SCRANt'lED ON A LOW REACTOR MATER LEVEL SIGNAL OF +8 INCHES THE ROOT CAUSE OF THE EVENT WAS THE FAXLURE OF THE 2A FEEDWATER REGULATING VALVE (FMRV)

THE STEH AND PLUG ASSEMBLY OF THE 2A FMRV SEPARATED DUE TO A FATIGUE CRACK CORRECTIVE ACTXONS ENTAILED REPLACEHENT OF THE STEH/PLUG ASSEMBLY METH A NEW WELDED STEM/PLUG ~ ALSO TO PREVENT RECURRENCE A NEM TRXN PACKAGE INCORPORATING A= LIGHTER PLUG THAT IS LESS SUSCEPTIBLE TO FATIGUE CRACKXNG MILL BE CONSXDERED AS REPLACEMENT PARTS IN THE FUTURE ~ THIS DECISION MILL BE HADE FOLLOWING THE TESTING BEING PERFORMED ON UNIT 3 AS A RESULT OF THE 8/7/87 UNXT 3 SCRAM DUE TO e f EEDWATER SYSTEH OSCXLl ATING ~ THE SAFETY SIGNIFICANCE MAS MINIMAL SINCE ALL EHERGENCY CORE COOLING SYSTEMS 'WERE AVAILABIEr HOMEVERr NO ACTUATXON MAS NECESSAPY THE FEEDWATER LEVEL CONTROL SYSTEH RENAINED CAPABLE OF MANUAL CONTROL OF REACTOR LEVEL AT ALl TINES AND THE REACTOR SCRAMHEO .AT THE SPECIFIED CONSERVATIVE SETPOXNT FIVE (5)

PREVIOUS OCCURRENCES MERE REPORTED BY LICENSEE EVENT REPORTS 487-12 AND 484 10 ON DOCKET 050249 AND 084 23r '8? 16r 484 9 ON DOCKET 050237

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FORM LER SCSS DATA 08-30-91 e ********************************************************************

DOCKET YEAR LER NUMBER REVISION DCS NUMiBER NSIC EVENT DATE 244 1988 005 . 0 8807080142 209704 06/01/88

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e DOCKET:244 GINNA REGION: 1 TYPE:PWR NSSS:WE ARCHITECTURAL ENGINEER: GLBT FACILITY OPERATOR: ROCHESTER GAS 5 ELECTRIC CORP S YM BOL: RGE COMMENTS STEP 1 BUSSMAN STYI E MDL 1/10 AMPr 125 VOLT FUSE ~ STEP 8, CAUSE HX SHRINK EFFECT MATCH 914 - SEE NRC INSPECTXON REPORT 50-244/88-11 FOR DETAILS OF STEPS 32 - 37. $ E/E/1 WATCH-LIST CODES FOR THXS LER ARE:

20 EQUIPMENT FAILURE 914 INADEQUACIES OF INFORMATXON REPORTABILITY CODES FOR THIS LER ARE:

13 10 CFR. 50.73(a) (2) (iv): ESF actuations.

ABSTRACT POWER LEVEL 098% OiN JUNE 1r 1988 AT 1932 EDST WITH THE REACTOR POWER AT APPROXIMATELY 98%r A REACTOR TRIP OCCURRED:-DUE TO LOM LEVEL IN THE "B" STEAM GENERATOR COINCXDENT MITH STEAM FLOW FEEDMATER FLOW MISMATCH FOLLOWED IN APPROXIMATELY 3 MINUTES BY A SAFETY INJECTION INXTIATION FROM PRESSURIZER LOW PRESSU/E ~ THE TMO REACTOR TRIP BREAKERS OPENED AS REQUIRED ANO ALL SHUTDOWN AND CONTROL RODS INSERTED AS DESIGNED ALL SAFEGUAROS EQUIPMENT OPERATED AS DESXGNEO WITH THE EXCEPTION OF TWO VALVES THE UNDERLYING CAUSE OF THE REACTOR TRIP WAS A TRANSIENT CAUSED BY A BLOWN FUSE IN THE "B"- STEAM GENERATOR CONTROLLING FEEDWATER FLOW CHANNEL POWER SUPPLY THE UNDERLYING CAUSE OF- THE SAFETY INJECTION INXTIATION MAS A REACTOR COOLANT SY'TEM COOLDOMN CAUSED BY OVERFEEDXNG THE STEAM GENERATORS IMMEDEATE CORRECTIVE ACTXON MAS TO STABILIZE THE PLANT PER THE EMERGENCY OPERATING PROCEDURES FOR REACTOR TRIP ANO SAFETY XNJECTION ~ ACTION TAKEN TO PREVENT RECURRENCE MAS TO INVESTIGATE ANO REPLACE ALL FEEDWATER FLOM CHANNEL POWER SUPPLY FUSES AND TO REPLACE THE POWER SUPPLY ON THE EFFECTED CHANNELS

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FORM 7 LER SCSS DATA 08-30-91

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DOCKET YEAR LER NUNBER REVISION DCS NUMBER NSIC EVENT DATE 247 1988 009 0 8808310153 210252 07/25/88 INDIAN POINT

~ DOCKET:247 REGION:

2 1 .

TYPE:PMR NSSS:ME ARCHXTECTURAL ENGXNEER: UECX FACILITY OPERATOR: CONSOLIDATED EDISON CO ~

SYNBOL: CEC, MATCH-LEST CODES FOR THIS LER ARE:

34 DESIGN ERROR OR INADEQUACY REPORTABILITY CODES FOR THIS LER ARE:

10 10 CFR 50 ~ 73(a) (2) (i): Shutdowns or technical specification violations.

REFERENCE LERS:

1 247/84-003 ABSTRACT POMER LEVEL 100X AT APPROXIMATELY 1345 HOURS AND 1815 HOURS ON JULY 25'988> A DEFECTIVE REGULATOR BOARD ON THE SOLA TRANSFORMER THAT PROVXDES A REGULATED SOURCE OF POWER FOR THE ROD POSXTION INDICATION SYSTEH CAUSED ALL ROD POSITIONS TO INDICATE HIGH LOSS OF ALL ROD POSITION INDICATION IS A CONDITION NOT COVERED BY A TECHNICAL SPECIFICATION LIMITING CONDITION fOR OPERATION ANDr THEREFOREr ENTRY INTO TECHNICAL SPECIFICATION 3 ~ 0 ~ 1 WAS REQUIRED ON BOTH OCCASIONS ADJUSTMENT OF THE POTENTIOMETER APPEARED TO CORRECT THE CONDITION AFTER THE FIRST OCCURRENCE THE REGULATOR BOARD ON THE TRANSFORNER WAS REPLACED AFTER THE SECOND OCCURR NCEr WHICH ULTIMATELY CORRECTED THE HIGH VOLTAGE CONDITION ~ THE HEALTH ANO SAFETY OF THE PUBLIC MERE NOT AFFECTED BY THIS EVENT.

i' FORM 8 LER SCSS DATA 08-30"91

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DOCKET YEAR LER NUMBER REVISION DCS NUHBER NSIC EVENT DATE 249 1986 019 0 8612160138 202112 11/13/86 DOCKET:249 DRESDEN 3 TYPE:BWR e REGION: 3 NSSS:GE ARCHITECTURAL ENGINEER: SLXX FACILITY OPERATOR: CONlriQNMEALTH EDISON CO ~

SYMBOL: CME REPORTABILITY CODES FOR THIS LER ARE:

13 10 CFR 50.73(a) (2) (iv): ESF actuations.

REFERENCE LERS:

1 237/86-019 2 249/86-021

~ ABSTRACT POWER LEVEL 092X ON 11-13-86 POWER UNDER NORMAL CONDITIONS A SCRAM OCCURRED THE CAUSE OF THE SCRAM WAS THE SINULTANEOUS OCCURRENCE OF 2 UNRELATED HALF- SCRANS THE FIRST HALF-SCRAM WAS CAUSED BY PERSONNEL ERRORS ABOUT 1 WEEK PRIOR TO THE EVENTr AN ELECTRXCAL MAINTENANCE FOREMAN (EHF) MAS PERFORMING WORK ON THE UNINTERRUPTIBLE POMER SUPPLY (UPS) ~ THE ESSENTIAL. SERVICE BUS (ESB) WHICH IS NORNALLY POWERED BY THE UPSr WAS BEING POWERED BY XTS RESERVE POllER SOURCE ~ THE El'IF LEFT FOR VACATION MITHOUT COY<PLETING HIS WORK ON THE UPS DURING HIS ABSENCEr A REACTOR SCRAM OCCURRED DURING STARTUP FOLLOWING THE SCRAHr THE OPERATORS SMITCHED THE ESB POWERS SOUPCE FROM ITS RESERVE POWER SOURCE TO ITS NORMAL PO'MER SOURCE WHEN THE EHF RETURNED FROM HIS VACATION ON THE DAY OF THE EVENTr HE ASKED IF ANY WORK HAD BEEN PERFORMED ON THE UPS AND MAS TOLD THAT NO WORK MAS PERFORHED THE ENF THEN PREPARED TO CONTINUE HIS WORK ON THE UPSr WHICH INCLUDED INFORtlING OPERATIONS PERSONNEL OF HXS INTENT THE ENF WAS STILL UNAMARE THAT THE POWER SOURCE TO THE ESB WAS SMXTCHED'TO THE NORMAL POWER SOURCE ~ AT 1058 HOURSr THE EflF OPENED A BREAKER WHICH CAUSED A HOHENTARY LOSS OF POMER TO THE ESB AND A HALF-SCRAM MAS INITIATED FROM THE HAIN STEAN LINE RADIATION HONITORS ~ BEFORE OPERATORS COULD RESET THE HALF-SCRAHr ANOTHER HALF-SCRAH OCCURRED'HE SECOND HALF-SCRAM MAS PROBABLY CAUSED BY A DIRTY CONNECTION IN A FLOW-BIASED APRN

FORM LER SCSS DATA 08-30-91 e ********************************************************************

DOCKET YEAR LER NUMBER REVISION DCS NUthBER NSIC EVENT DATE 250 1984 015 0 8406180289 190302 05/14/84

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DOCKET: 250 TURKEY POINT 3 TYPE:PWR REGION: 2 NSSS WE ARCHITECTURAL ENGItlEER: SECH FACILITY OPERATOR: FLORIDA POWER tt LXGHT CO ~

SYMBOL: FPL i REPORTABILITY CODES FOR THIS LER ARE:

13 10 CFR 50 73(a) (2) (iv): ESF actuations.

i REFERENCE 1

LERS.

250/84-009 2 250/84-013 ABSTRACT POWER LEVEL - 100K ON MAY 14 1984 A TURBINE RUNBACK OCCURRED'HE ROOT CAUSE WAS DETERMINED TO STEM FROM AN INSTRUMENT POWER SUPPLY FAILURE IN THE NUCLEAR INSTRUMENTATION SYSTEM (NIS) THAT RESULTED IN AN 'NIS ROD DROP'IGNAL (NXS CHANNEL N-41) WHICH GENERATED THE TURBINE RUNBACK ALL EQUIPMENT FUNCTIONED AS DESIGNED IMMEDIATE CORRECTIVE ACTIONS INCLUDED PROMPT IDENTIFICATION OF THE CAUSE OF THE RUNBACK AND RESTORATXON OF FULL POWER OPERATION~ TRIPPING THE ASSOCIATED REACTOR TRIP BXSTABLES FOR THE NIS CHANNELS REMOVED FROM SERVICEr ISOLATION OF THE FAILED POWFR SUPPLY'ND RETURN TO SERVICE OF NIS CHANNEL N-41 SXMILAR OCCURRENCES: LER 250-84-009 AND LER 250-84-013

o a e o o e e o e e e e o e e e o e e 4 l

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0 0 0 0 0 0 0 1 0 0 1

FORM 10 LER SCSS DATA 08-30" 91

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DOCKET YEAR LER NUl'1BER REVISION DCS NUMBER NSIC EVENT DATE 250 1985 018 0 8508190627 195293 07/16/85

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DOCKET:250 TURKEY POINT 3 TYPE:PWR REGION- 2 NSSS:ME ARCHITECTURAL ENGINEER: SECH FACILITY OPERATOR: FLORIDA POWER 5 LIGHT CO ~

SYHBOL: FPL.

REPORTABILITY CODES FOR THIS LER ARE:

13 10 CFR 50 ~ 73(a) (2) (iv): ESF actuations.

REFERENCE LERS:

. 1 250/84-003 2 250/84-014 3 250/84-026 4 251/84-011 5 251/84-021 6 251/84-022 7 251/85-012 8 251/85-013 9 251/85-017 ABSTRACT POWER LEVEL 000'N 7 16 85r UNIT 3 EXPERIENCED A REACTOR TRIP FROM HOT STANDBY CONDITIONS THE 3C INVERTER THAT blAS IN SERVICE SUPPLYING POWER TO 120V VITAL INSTRUMENT PANEL 3P06r TRIPPED ~ LOSS OF POWER TO 3P06 RESULTED IN A LOSS OF POWER TO THE NUCLEAR INSTRUMENTATION SYSTEM (NIS) SOURCE RANGE CHANNEL N-31 THE LOSS OF POWER TO CHANNEL N-31 GENERATED A SOURCE RANGE HX FLUX REACTOR TRIP SIGNAL WHXCH OPENED BOTH REACTOR TRIP BREAKERS RESULTING IN BOTH SHUTDOWN BANKS FALLING I!lTO THE CORE ~ THE CONTROL ROD BANKS WERE ALREADY IN THE CORE AT THE TINE OF THE EVENT ~ INVESTIGATIONS INTO THE LOSS OF THE 3C INVERTER COULD NOT REVEAL ANY APPARENT ROOT CAUSE ~

CORRECTIVE ACTIONS: POMER TO THE VITAL INSTRUMENT BUS FOR PANEL 3P06 WAS RE-ESTABLISHED AND THE AFFECTED EQUIPNENT WAS RETURNcD TO NORMAL LXNEUP ~ THE 3C INVERTER WAS INSPECTED AND CHECKED AS PER MAINTENANCE INSTRUCTIONS'USE F6 MAS FOUND BLOWN AND REPLACED'HE BLOWN FUSE WAS A RESULT AND NOT THE CAUSE OF THE LOSS OF THE 3C INVERTER. NO OTHER SIGNIFICANT PROBLEMS MERE FOUND ~ THE ON-GOIllG CORRECTIVE ACTION IS TO REPLACE THE INVERTERS WITH A MODEL OF A DXFFERENT blANUFACTURER THE 3C INVERTER WAS REHOVED FROM SERVICE FOR THIS REPLACEHENT ON 7 19 85 ~ SIMILAR OCCURRENCES 250/84-003r 250/84-014r 250/84-026r 251/84 011 r 251/84-021r 251/84 022r 251/85 012r 251/85 013r, AND 251/85-01 7

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FORM 11 LER SCSS DATA 08"30-91

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DOCKET YEAR LER NUMBER REVISION DCS NUMBER NSIC EVENT DATE 251 984 021 8504080577 96658 09/20/84

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1 1 1 4.

~ DOCKET:251 TURKEY POINT REGION: 2 TYPE:PWR NSSS:WE ARCHITCCTURAL ENGINEER: SECH FACILITY OPERATOR: FLORIDA POWER 5 LIGHT CO SYNBOL: FPL REPORTABILITY CODES FOR THIS LER ARE:

13 10 CFR 50.73(a) (2) (iv): ESF actuations REFERENCE LERS:

1 251/84-011 ABSTRACT POWER LEVEL 100X ~ ON SEPTENBER 20r 1984' TURBINE RUNBACK AND SUBSEQUENT REACTOR TRIP OCCURRED DURING AN INVESTIGATION FOR A GROUND IN THE 3A DC BUSr THE "NORMAL" (4A) STATIC INVERTER (4Y01)

TRIPPED DUE TO A BLOWN FUSE ~ THE 4A INVERTER WAS IN, SERVICE SUPPLYING POWER TO A VITAl 1 20 VOLT (A C ) XNSTRUHENT BUS (PANEL 4P07) THE 4A INVERTER FAILURE RESULTED IN A LOSS OF POWER TO VITAL PANEL 4P07 WHICH CAUSED NUCLEAR INSTRUHENTATION SYST" N (NIS) CHANNEL N-42 TO GENERATE AN "NIS ROD DROP" SIGNAL CAUSING A TURBINE RUNBACK TO 70X POMER ~ FOLLOWING THE TURBINE RUNBACK~ A REACTOR TRIP OCCURRED WHEN THE REACTOR PROTECTION LOGIC OF STEAi'l FLOW GREATER THAN FEED FLOWi COINCIDENT WITH STEAM GENERATOR LOW LEVEL FOR THE "8" STEAN GENERATOR MAS t<ADE UP INNEDIATE CORRECTIVE ACTIONS INCLUDED STABILIZING THE UNIT AND RE-ENERGIZING VITAL PANEL 4P07 ~ LONG TERN CORRECTIVE ACTION IS TO REPLACE THE INVERTERS TO ENSURE A NORE RELIABLE POWER SUPPLY ALL EQUXPh1ENT FUNCTIONED AS DESIGNED ON INITIATXON OF 'THE ENGINEER ED SAFETY r EATURE ACTUATION SIGNAL (ESFAS) GENERATED IN THE REACTOR PROTECTION SYSTEM SIMILAR OCCURRENCES: LER 251-84-011

0 0 0 0 0 ~ 0 0 0 0 0 0 0 0 0 o 0 0 Ir I

0 0 0 0 0 0 0 0 0 0 0 0 0

FORM 12 LER SCSS DATA 08-30-91 DOCKET YEAR LER NUHBER REVISION DCS NUHBER NSIC EVENT DATE 251 - 1985 012 0 8507150257 194932 05/30/85

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g DOCKET:251 TURKEY POINT 4 REGION: 2 TYPE:PMR NSSS:ME ARCHITECTURAL ENGIhlEER: SECH FACILITY OPERATOR: FLORIDA POWER 8 LIGHT CO SYMBOL: FPL REPORTABILITY CODES FOR THIS LER ARE:

13 10 CFR- 50.73(a) (2) (iv): ESF actuations.

LERS:

~ REFERENCE

1. 250/84-003 2 250/84-014 3 250/84-026 4 251 /84-011 5 251/84-021 6 251/84-022 ABSTRACT POWER LEVEL 100X ~ ON HAY 30' REACTOR TRIP OCCURRED DUE TO THE LOSS OF POWER FROM THE AS INVERTER TO THE 120 VAC VITAL INSTRUNENT BUS FOR THE PANEL 4P07 THE LOSS OF VOLTAGE ON THE VITAL BUS RESULTED IN THE "B" STEAM GENERATOR LEVEL CHANNEL II FAILING LOWr AND THE STEAN GENERATOR FEEDMATFR CONTROL STATION TRANSFERRING -TO HANUAL. WHILE HANUALLY CONTROLLING FEEDWATER- FLOWr A REACTOR TRIP OCCURRED WHEN THE REACTOR PROTECTION LOGIC OF STEAN GENERATOR LOM LEVEL COINCIDENT MXTH STEAM FLOW GREATER THAN FEEDMATER FLOM ON THE 4B STEAN GENERATOR WAS COMPLETED OUE TO A FEEDWATER FLOW TRANSIENT CAUSED BY A TURBINE RUNBACK THE UNXT MAS STABILIZED IN A HOT SHUTDOWN CONDITION SIHILAR OCCURRENCES LERS 250/84 003r 250/84 014r 250/84 026'51/84 011r 251/84 021r AND 251/84 022 ~ THE LOSS OF POWER TO THE VITAL INSTRUHENT BUS SERVING THE 4P07 PANEL RESULTED FROYi A BLOWN FUSE ON THE AS SPARE INVERTED ALTHOUGH A FULL SET OF TESTS MERE PERFORMED ON THE INVERTER MHICH DEMONSTRATED THAT IT NET THE h'IANUFACTURER'S SPECIFICATIONS'HE EXACT CAUSE OF THE BLOWN FUSE COULD NOT BE DETERHINED ~ IN THE PAST~ BOTH PLANTS HAVE EXPERIENCED SIHII AR EVENTS DUE TO THE'LOSS OF POWER FROM THESE INVERTERS

FORM 13 LER SCSS DATA 08-30-91

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • 0'OCKET YEAR LER NUMBER REVISION DCS NUMBER NSIC EVENT DATE 251 1985 017 0 8508010723 1 9? 71 7 06/20/85

• • • • • • • • • • • • • • • • • • 4*************************************************

~ DOCKET:251 TURKEY POINT 4 REGION: 2 TYPE:PMR NSSS:WE ARCHITECTURAL ENGXNEER BECH FACXLXTY OPEPATOR: FLORIDA POWER 8 LXGHT CO SYMBOL: FPl

~ COMMENTS WATCH 990 " INTERACTION BETWEEN UNIT 3 AND UNIT 4 EQUIPMENT.

WATCH-LIST CODES FOR THIS LER ARE:

990 COMPLEX EVENT REPORTABILITY CODES FOR THIS LER ARE:

13 10 CFR 50.73(a) (2) (iv): ESF actuations.

REFERENCE LERS:

1 250/84-003 2 250/84-014 3 250/84-026 4 251/84-011 5 251/84-021 6 251/84-022 7 251/85-012 8 251/85-013 ABSTRACT POWER LEVEL 100X ON 6-20-85 UNIT 4 EXPERIENCED A REACTOR TRiP THE 4C INVERTER THAT MAS IN SERVICE SUPPLYING POWER TO THE 120V VITAL INSTRUMENT PANEL 4P05r TRIPPED ~ LOSS OF 4P06 DE-ENcRGIZED LEVEL CONTROLLER LC-460C AND THE PRESSURIZER SPRAY VALVE CONTROLLERS (CAUSING THE SPRAY VALVES TO REMAIN AT THEIR LAST DcMAND POSITION) ~

DE-ENERGXZING OF LC-460C GENERATED A FALSE INDICATION OF LOM PRESSURIZER LEVEL WHICH DE-ENERGIZED THE PRESSURIZER HEATERS AND INITIATED LETDOWN ISOLATION LOSS OF 4P06 ALSO RESULTED IN THE LOSS OF AUTOMATIC OPERATION OF PORVr PCV 4 455C ~ PORV PCV 4 456 WAS AVAILABLE WITH ITS ASSOCIATED;BLOCK VALVEr MOV 4 535 CLOSED DUE TO SLIGHT LEAKAGE THROUGH PCV 4 456 ~ THESE CONDITIONSr ALONG WITH A TURBINE RUNBACK DUE TO LOSS OF POWER TO NUCLEAR XNSTRUMENTATXON SYSTEM CHANNEL N 41 r RESULTED IN THE RCS PRESSURE INCREASING UNTIL IT REACHcD THE PRESSURIZER HIGH PRESSURE REACTOR TRIP SETPOINT OF 2370 PSXG RESULTING IN A REACTOR TRIP THE LOSS OF THE 4C XNVERTER OCCURRED WHILE ATTEMPTING TO CNERGIZE THE 3C INVERTER ONTO THE 38 120V DC BUS THE PROCEDURAL REQUIREMENTS FOR THIS EVOLUTION REQUIRE CHARGING THE 3C XNVFRTER'S CHARGING CAPACITORS PRIOR TO ENERGIZING THE INVERTER ONTO THE BUS ~ THIS STEP WAS NOT EXECUTED CAUSING THE LOSS OF THE 3C INVERTER WHICH RESULTED IN A DC BUS TRANSIENT WHXCH IN TURN CAUSED A LOSS OF THE 4C INVERTER ~ CORRECTXVE ACTIONS MERE TAKEN~

0 e e a o e e e o e e e e o e e o e o % 0 V

0 0 0 0 0 0 0 0 0 0 0 0 0 0

FORM 14 LER SCSS DATA 08-30-91,

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • k****A*******A*******A****

DOCKET YEAR LER NUtlBER REVISION DCS NUtlBER NSIC EVENT DATE 251. 1988 005 0 8806020092 209378 04/25/88 DOCKET.251 TURKEY POINT 4 .TYPE:PWR REGION: 2 NSSS:WE ARCHXTECTURAL ENGINEER: SECH FACILITY OPERATOR: FLORIDA POMER 8 LIGHT CO ~

SYtl BOL: FPL

~ COMMENTS

$ MP/ET/3 y WATCH-LIST CODES FOR 35 HUMAN ERROR THIS LER ARE:

CODcS FOR THIS

~ REPORTABILITY 10 10 CFR 50.73(a) (2) (i):

LER ARE:

Shutdowns or technical specification violations.

REFERENCE LERS:

1 250/86-011 2 250/86-013 3 250/86-020 4 250/86-027 5 250/87-013 6 250/87-028 7 250/88-005 ABSTRACT POMER LEVEL 100X. THE NUCLEAR INSTRUMENTATION SYSTEM (NIS) POMER

~ RANGE DETECTORS ARE CALIBRATED BY PERFORMING A CALORIMETRIC MEASUREMENT AND COMPARING THE RESULTS WITH THE NXS INDXCATEO POWER THIS IS USUALLY PERFORMED AUTOMATICALLY BY THE DIGITAL DATA,PROCESSING SYSTEM (OOPS) ~ IT WAS LAST PERFORMED ON 4/24/88r AT 0730 DUE TO MALFUNCTIONSr THE DDPS WAS DECLAREO OUT OF SERVICE (OOS) AT 2108r 4/24~ EFFORTS TO RETURN THE OOPS TO SERVXCE MERE INITIATED IMMEDIATELYr HOWEVER A PLANT- WORK ORDER (PWO) TO REPAIR THE DOPS WAS GENERATED AT APPROXIMATELY 0730 WHEN ET BECAME APPARENT THAT INSTRUMENTATION AND CONTROLS (ERC) MAINTENANCE HELP WAS REQUIRED UNTIL ABOUT 1030r'HE EMPHASES WAS PLACED UPON FIXING THE OOPS ANO IT WAS BELIEVED THAT A MANUAL CALCULATION MOULD NOT BE NEEOEO ~ AT APPROXIMATELY 1100r EFFORTS TO PERFORM THE CALCULATION MANUALLY MERE INITIATEDr HOWEVER THE CALCULATION MAS NOT COMPLETED UNTXL 1358 ~ AS DECLARED OOSr AND THE UNIT ENTEREO TS 3 'T THE GRACE PERIOD EXPIRED AT 1330r THE POWER RANGE DETECTORS MERE MERE RETURNED TO SERVICE ANO THE UNXT EXITED TS 3 Oo1 ~

1358r THE DETECTORS THE CAUSE OF THE LATE SURVEXLLANCE MAS PERSONNEL ERROR THE DDPS MAS REPAIRED THE GROUP RESPONSIBLE FOR THE PERFORMANCE OF THIS SURVEILLANCE DISCUSSED THIS EVENT IN ORDER TO PREVENT RECURRENCE BY ASSURXNG THAT ADEQUATE TIME IS ALLOTTED TO PERFORM THE SURVEILLANCE MANUALLY

0 e ~ e e o a o o e o o e e e o e e e o e E

0 0 e e o e o e o e e e e e e e o o o o a

FORH 15 LER SCSS DATA 08"30-91

• • • • k*****k****k k*******k** k *k*k********* k********************k*****

DOCKET YEAR l ER NUHBER REVISION DCS NUNBER NSIC EVENT DATE 255 1986 013 0 8604020224 198707 02/25/86

• • • • k*****kk*****k***k*k*k******k**********************k***********k DOCKET: 255 PALISADES TYPE:PWR REGION: 3 NSSS:CE ARCHITECTURAL ENGINEER: BECH FACXLXTY OPERATOR: CONSUMERS POWER CO SYHBOL: CPC REPORTABXLITY CODES FOR THIS LER ARE-13 10 CFR 50.73(a) (2) (iv): ESF actuations.

REFERENCE LERS:

1 255/85-013 2 255/86-011 ABSTRACT POWER LEVEL OOOX ~ 'N 2 25 86'ITH THE PLANT IN HOT SHUTDOWNr A REACTOR PROTECTION SYSTEN (RPS) ACTUATION OCCURRED FROM A SPIKE IN A NUCLEAR INSTRUMENT CHANNEL THE SPIKE WAS CAUSED BY THE RE-ENERGIZATION OF A PREFERRED AC BUS DURING A NANUAI TRANSFER OF POWER SUPPLIES NO ROD HOTION OCCURRED XN THIS EVENT THE RPS ACTUATION CAUSED THE TURBINE GENERATOR TRXP CIRCUIT TO INITIATE AN AUTOMATIC START OF BOTH DIESEL GENERATORS ~ THE DIESEL GENERATORS MERE NOT LOADED ONTO ANY BUS. THE SPIKE IS A NORHAL OCCURRENCE DURING THE HANUAL TRANSFER OF POWER SUPPLXES TO THE PREFERRED BUS THE RPS ACTUATION HAY BE PREVENTED BY PLACING A HIGH RATE TRIP CHANNEL IN BYPASS PRIOR TO THE BUS TRANSFER THXS REQUIREHENT HAS BEEN ADDED TO OPERATING PROCEDURES ALL EQUIPMENT OPERATED PROPERLY IN THIS EVENT THE ACTUATION MAS NOT REQUIRED TO MITIGATE ANY ABNORHAL PLANT CONDXTIONS<<FOR SIHXl AR OCCURRENCEr REFERENCE LERS 85 13 AND 86 11 ~

i 0 0 0 0 0 0 0 0 0 0 0 0 4 0 0 ~ 0 0 5 i

0 0 0 0 0 0 0 0 0 0 0 0 0

FORM 16 LER SCSS DATA 08-30-91

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • +*********************

DOCKET YEAR LER NUbtBER REVXSXON DCS NUNBER NSIC EVENT DATE 260 1989 021 1 9002220042 216872 07/10/89

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • A**

~ DOCKET:260 BROWNS FERRY.2 REGlON: 2 TYPE:BMR NSSS:GE ARCHITECTURAL ENGINEER: TVAX FACILITY OPERATOR: TENNESSEi VALLEY AUTHORITY SYHBOL: TVA COMMENTS OTHER REPORTABXLITY - VOLUNTARY STEP 3: COHP ZZZ INTERNAL PANEL COHPONENTS ~

WATCH-LEST CODES FOR THIS LER ARE:

35 HUMAN ERROR REPORTABILXTY CODES FOR THIS LER ARE:

21 OTHER: Voluntary- repor etc.

ti special repor tr Par t 21 repor tr ABSTRACT POWER LEVEL 000% ~ ON JULY 10/ 1989r INSTRUMENT TECHNICIANS MERE PERFORHXNG ROUTINE NEUTRON HONXTORING SYSTEH TESTXNG IN ACCORDANCE WITH A SURVEILLANCE INSTRUCTION (SX) AS A RESULT OF ACTIONS DURING THIS TESTING~ XT WAS ORIGINALLY BELIEVED THAT AN OPERATION PROHIBITEO BY TECHNICAL SPECIFICATXONS HAD OCCURRED AND THIS EVENT WAS REPORTED IN REVXSION "0" OF THIS LER ~ FOLLOWING THE SUBHXTTAL OF THAT LERr ADDXTIONAL REVIEW OF THIS EVENT HAS OETERHINED THAT THIS EVENT WAS NOT REPORTABLE AS AN LER ~ THIS REVISION CHANGES THIS LER TO A VOLUNTARY REPORT ~ DURING SX TESTING/ THE NUl'iBER OF OPERABLE INTERMEDIATE RANGE HONITOR (IRH) CHANNiLS MAS LCSS THAN REQUIRED BY TECHNICAL SPECIFICATION 3>>1r TABLE 3 ~ 1 ~ A>> HOWEVER< THROUGHOUT THXS EVENTs UNIT 2 MAS IN COLO SHUTDOWN WITH ALL CONTROL RODS INSERTED AND NO CORE ALTERATIONS IN PROGRESS MITH THESi CONDITIONS'HE APPLXCABLE ACTION FOR TECHNICAL SPECIFICATION 3 ~ 1r TABLE 3 ~ 1 ~ A MAS IIEET DURING THIS EVENT ~ ADDXTIONALLYr THE TIHE WITH LESS THAN THE MINIHUYi REQUIRED OPERABLE XRH CHANNELS DURING THIS EVENT DID NOT EXCEED THi FOUR HOURS ALLOMEO BY TECHNICAL SPECXFICATION 3 1 FOR REQUIRED SURVEILLANCE TESTING ~ DUE TO AN OPERATED FUSE THE ELAPSED TINE MXTH LESS THAN THE MXNIMUN REQUIRED OPERABLE IRN CHANNELS MAS APPROXXHATELY ONE HOUR

~ e e e o o e o e e o e o e e e e o e o e 0 FORM 17 LER SCSS DATA 08-30-91

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • 4*********

DOCKET YEAR LER NUNBER REVISION DCS NUMBER NSIC EVENT DATE 261 1985 021 0 8510180532 196272 09/17/85 DOCKET:261 ROBINSON 2 TYPE:PMR REGION: 2 NSSS:ME ARCHITECTURAL ENGINEER: EBAS FACILITY OPERATOR: CAROLINA POWER 8 LIGHT CO SYNBOL: CPL COHHENTS STEPS 3 8 6: EFFECT IX - VOLTAGE SPIKE REPORTABIl ITY CODES FOR THIS LER ARE:

13 10 CFR 50 73(a) (2) (iv): ESF actuations.

ABSTRACT POWER LEVEL 100X ~ ON 9-17-85 THE REACTOR WAS AT 100X POWER AT 1259 HRSr A REACTOR TRIP OCCURRED DUE TO A FALSE LOM REACTOR COOLANT FLOW SIGNAL TESTING ON THE LOOP 1 REACTOR COOLANT FLOW PROTECTION CXRCU TRY MAS IN PROGRESS ONE OF THE THREE BISTABLES FOR 'LOOP 1 WAS TRIPPED FOR TESTING ~ AN INSTRUHENT BUS 42 VOLTAGE SPIKE OCCURRED GENERATING A FALSE SECOND LOOP 1 LOW FLOW SIGNAL THIS PROVIDED THE NECESSARY 2 OUT OF 3 SIGNALS REQUIRED FOR THE 1 LOOP LOM FLOM REACTOR TRIP ~ AN EXTENSIVE MALKDOMN OF IB 02 MAS PERFORHEDr 'AND NO SPECIFIC CAUSE FOR THE VOLTAGE SPIKi MAS XDENTIFIED~ A SPECIAL PLANT NUCLEAR SAFETY COMHITTEE (PNSC) MEETING MAS HiLD TO REVIEM THE EVENT ~ THE PNSC DETERHINED THAT THE INVESTIGATION HAD BEEN THOROUGHr THAT NO OTHER ACTION COULD BE TAKEN TO DETERMINE THE CAUSE OF THE VOLTAGE SPIKEr AND THAT IT WAS SAFE TO RESTART THE UNIT ~ AS OF 10 8 85r VOLTAGE SPIKES ON IB02 HAVi NOT REOCCURRED

~ ~

FORM 18 LER SCSS DATA 08-30-91 DOCKET YEAR LER NUNBER REVISION DCS NUNBER NSIC EVENT DATE 261 1986 005 2 861 2010229 201 984 01/28/86

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • +*********************

~ DOCKET:261.

ROBINSON 2 TYPE:PWR REGION: 2 NSSS:WE ARCH!TECT URAL ENGINEER: EBAS FACILITY OPERATOR: CAROLINA LIGHT CO.

e S YlhBOL: CPL POWER Jt COHt1ENTS STEP 2: CAUSE AX-FOR UPGRADE WATCH 975-LOSS OF OFF-SITE POWER OCCURRED METH ONE DG OUT OF SERVICE STEPS 4r 5 COMP HEX FUSE HOLDER ~

WATCH-LIST CODES FOR THIS LER ARE:

942 UNUSUAL EVENT 975 POSSIBLE SXGiVIFICANT EVENT REPORTABILITY CODES FOR THIS LER ARE:

13 10 CFR 50.73(a) (2) (iv): ESF actuations.

ABSTRACT POWER LEVEL. 080X ON 1 28 86 WITH UNIT 2 AT BOX POWERr EMERGENCY BUSS E-2 WAS LOSTr RESULTING IN A HXGH PRESSURIZER PRESSURE REACTOR TRIP ~ UNIT AUXILIARIES THEN SHXFTED TO THE STARTUP (S/U) TRANSFORHER BUT A WEST 115 KV BUSS LOCKOUT OE ENERGIZED THE TRANSFORHERr CAUSING LOSS OF OFFSITE AC POWERS EMERGENCY BUSS E-1 MAS ENERGIZED SX AND NSXV CLOSURE SIGNALS WERE RECEXVED FROGS A HIGH STEAM LINE FLOW COINCIDENT WITH LOW TAVEr AND AN 'UNUSUAL EVENT MAS DECLAREO POWER MAS RESTORED TO E-2 BUT A SECOND SI SIGNAL MAS RECEIVED FROM A STEAtk LINE HIGH DIFFERENTIAL PRESSURE OFFSXTE AC POWER WAS THEN RESTORED AND THE UNUSUAL EVEN WAS TERHINATED~ ON 3-6-86r DURING REFUELING SHUTDOWNr TMO STATION SERVICE TRANSFORMERS MERE TAKEN OUT-OF-SERVICE FOR MAINTENANCE ON THEIR CONMON SUPPLY BREAKER ~ MHILE ENERGIZING E-2 FROM EMERGENCY BUSS - 1r THE SUPPLY BREAKER OPENED DUF TO DEGRADED VOLTAGE RELAY ACTUATION~ INVESTIGATION FOUND THE LOSS OF E-2 AND LOSS OF OFFSXTE AC POWER APPARENTLY RESULTED FROH TWO SEPARATEr INDEPENDENT CONDITIONS - SUSCEPTXBXLITY OF THE S/U TRANSFORNER PRIHARY SIDE CURRENT TRANSFORHERS (CTS) TO DC SATURATIOtJ AND VULNERABILITY TO A RANDOM BLOMN FUSE IN THE EHERGENCY BUSS UNDERVOLTAGE RELAYS. HARDMARE CHAt<GES HAVE BEEN HADEr AND INSTALLATION OF AN INPROVED FUSE HOLDER DESIGN HAS BEEN PLANNED."

0 o o e e e o e o a o e o o e o o e e o e 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 4

FORM 19 LER SCSS DATA 08-30-91

• • • • • • • • • • • • • • • +*A**************************************************

DOCKET YEAR LER NUMBER REVISION DCS NUMBER NSIC EVENT DATE 261 1990 001 0 9002220270 216883 01/10/90

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • 4*****************************

DOCKET: 261 ROBINSON 2 TYPE:PWR REGION: 2 NSSS:ME ARCHITECTURAL ENGINEER: EBAS FACILITY OPERATOR: CAROLINA POWER 8 LIGHT CO S YMBOL: CPL COMMENTS STEP 1: COMP MSC - BUS RECEPTACLE CODES FOR THIS

~ WATCH-LXST 20 EQUIPMENT FAILURE LER ARE:

~ REPORTABILITY CODES FOR THXS 10 10 CFR 50 73(a) (2) (i):

LER ARE:

Shutdowns or technical specification violations.

ABSTRACT POWER LEVEL 100'N JANUARY 10r 1990r AT 0908 HOURSr POMER WAS LOST TO THE ROD POSITION INDICATION (RPI) SYSTEM WHICH RESULTED IN THE ACTUATION OF AN AUTOMATIC TURBINE RUNBACK FROM 100X POWER THE UNXT MAS STABILIZED AT APPROXIMATELY 46X POWER FOLLOWING THE TRANSIENT WITH THE RPI SYSTEM DE ENERGIZEDr THE ROD POSITION DEVIATION MONITORING FUNCTION MAS UNAVAILABLE THIS FUNCTION IS PROVIDED BY THE PLANT PROCESS COMPUTER USING INPUT DATA RECEIVED FROM THE RPI SYSTEMr AND IS OthE PART Of T'HC CONTROL ROD MISAI IGNMENT MONITOR AS REQUIRED BY TECHNICAL SPEClFICATION TABLE 3 ~ 5-2r ITEM 15 ~ THE TECHNICAL SPECIFICATIONS ALSO REQUIRE THAT THE CONTROL ROOM ANALOG RPI BE MONITORFD IF THE MINIMUM REQUIRED CHANNELS OF THE ROD POSITION DEVIATION MONITOR ARE NOT OPERABLE ~ HOWEVERr THE LOSS OF POMER TO THE RPI SYSTEM ALSO CAUSED THE CONTROL ROOM ANALOG RPI TO BE UNAVAILABLE THEREFOREr IMPLEMENTATION OF TECHNICAL SPECIFICATION 3 ~ 0 MAS REQUIRED ~ THE CAUSE OF THE EVENT MAS THE FAILURE OF A TMO POLEr SINGLE PHASEr 120 VOLT AC CIRCUIT BREAKER MHICH SUPPLIES THE RPI SYSTEM ~

THE REQUIRED REPAIRS AND POST MAINTENANCE TESTING WERE COMPLETEOr AND THE RPI SYSTEM WAS RETURNED TO SERVICE AT 1540 HOURS ON JANUARY 10r 1990 THIS LICENSEE EVENT REPORT IS SUBMITTED PURSUANT TO 10CFR50. 73(A) (2) (I) (B).

0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 N 0 t

II

~0 It 0 O O e o e e e e e e e o e o O e e e e o-e

FORM 20 LER SCSS DATA 08-30-91 e ********************************************************************

DOCKET YEAR LER NUMBER REVISION DCS NUMBER NSIC EVENT DATE 263 1 984 015 0 8405010038 1 89599 03/25/84

• • • • • • • • • • • • • • • • • • • • • • • • • k******************************************

DOCKET:263 MONTICELl 0 TYPE:BWR e REGION: 3 NSSS:GE ARCHITECTURAL ENGINEER:

OPERATOR: NORTHERN STATES POWER CO BECH'ACILITY SYMBOL: NSP g COMMENTS STEP 2: COMPONENT CODE MSC CONNECTING STAB OF BREAKER SHELF TO MOTOR CONTROL. CENTER BUS BARS TRIP UNIT CAT NO TFK236T150 REPORTABILITY CODES FOR THIS LER ARE:

13 10 CFR 50.73(a) (2) (iv): ESF actuations.

ABSTRACT POWER LEVEL - OOOO THE MOTOR SOURCE BREAKER FOR THE REACTOR PROTECTION SYSTEM POWER SUPPLY MOTOR GENERATOR SET TRIPPED WHICH ISOLATED RPS BUS A LOADS'HESE LOADS CONSIST OF POWER RANGE NEUTRON MONITORS'CRAM, SOLENOID LOGXC CHANNEL Ai STEAM LINE AND OFF-GAS RADIATION MONITORS ~ LOSS OF 120V AC POWER TO RADIATION MONITORS INITIATED A PRIMARY CONTAINMENT STANDBY GAS TREATMENT SYSTEM GROUP II ISOLATION AND START OF POWER WAS RESTORED TO RPS BUS A FROM ALTERl'IATE SOURCE AND THE SYSTEM WAS RESET AND RETURNED TO NORMAL WHILE REPAXRS WERE MADE AND.EQUIPMENT TESTED THE MG SET WAS RETURNED TO SERVICE 8 DAYS AFTER THE EVENT ~

0 i 0 0 0 0 0 0 4 0 0 0 0 0 0 0 4 4 0 0 0 0 0 0 0 0 0 0 0

FORM 21 LER SCSS DATA 08-30-91

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • +*********A'*************************

DOCKET YEAR LER NUMBER REVISION DCS NUMBCR NSZC EVENT DATE 265 1984 001 0 8402070303 189034 01/03/84

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • +*A********************************k CITIES

~ DOCKET:265 QUAD REGION:

2 3

TYPE:BWR NSSS:GE ARCHITECTURAL ENGINEER: SLXX FACZl ITY OPERATOR:, COMMONWEALTH EDISON CO ~

SYMBOL: CWE COMMENTS STEPS 3r9: EFFECT XX = DEFECTIVi CABLE REPORTABXLITY CODES FOR THIS LER ARE 13 10 CFR 50 ~ 73(a) (2) (iv): ESF actuations.

ABSTRACT POWER LEVEL OOOX ON JANE 3 AND 5r 1984r REACTOR SCRAMS OCCURRED WHILE THE 'O'- REACTOR PROTECTION SYSTEM (RPS) WAS OUT OF SERVXCi FOR CIRCUIT BREAKER MAINTENANCE~ IN BOTH CASESr THE UNIT WAS SHUTDOWN FOR.A REFUELING OUTAGE NO ANNUNCIATORS OR COMPUTER ALARMS CAME UP TO EXPLAIN THE RiASON FOR THE 'B'PS CHANNEL TRXP AND RESULTANT SCRAM THROUGHOUT THE TIME SPAN OF THE EVENTSr XNTERMEDXATE RANGE MONITOR (IRM) 18 HAD BEEN SPIKXNG SPURXOUSLY DUE TO A FAULTY DETECTOR CABLE ~

XT IS POSTUI ATED THAT THE SPIKING IRtl HAD CAUSED THE e Be RPS CHANNEL TRIPr ALTHOUGH NO ALARMS WERE PRESENT TO VERIFY IT ~ THE DETECTOR CABLE FOR IRM 18 WAS REPLACiD PREVENTATIVE MAINTENANCE ON RPS BUSES IS NOT ROUTINELY ACCOMPLISHED DURXNG POWER OPERATION THE CONDITIONS SURROUNDING THIS EVENT WOULD NOT EXIST DURING OPERATIONr THEREFOREr NO FURTHER CORRiCTXVE ACTION XS DEEMED APPROPRIATE AT THIS TIME

e o e e a e o e o e e e e o e e o o o 0 4 V

~~

~ 8 ~L bI

~ ~ l P 0 0 0 0 0 0 0 0 0 0 0 0 0 0

FORM 22 LER SCSS DATA 08-30-91 .

DOCKET YEAR LER NUNBER REVISION DCS NUMBER NSIC EVENT DATE 265 1 990 007 0 9007090056 21 8698 05/31/90 DOCKET:265 QUAD CITIES 2 TYPE:BMR REGION: 3 NSSS:GE ARCHITECTURAL ENGINEER: SLXX FACILITY OPERATOR: COMMONWEALTH EDISON CO SYMBOL: CME COHHENTS STEP 2 30 AMP'USS MIN 30 FUSE i

~

WATCH-LIST CODES FOR- THIS LER ARE:

20 EQUIPHENT F AILURE REPORTABILITY CODES FOR THIS LER ARE:

10 10 CFR 50.73(a) (2) (i): Shutdowns or technical specification violations.

REFERENCE LERS:

1 254/85"021.

a POWER LEVEL - 100K ON HAY 31 ~ 1990 AT 1615 HOUPS UNIT TMO WAS XN THE RUN t40DE AT 100 PERCENT OF RATED CORE THER) lAL POWER ~ AT THIS TXHEr THE FOLLOWING ALARMS WERE RECEXVED ON THE 902 5 PANEL A 3x ROO DRIFTS B 3i ROD MORTH HXN ~ BLOCKi E 3r ROD OVERTRAVELS AND G-5i RPIS INOPERATIVE ~ ROO POSITION INDICATION (RPIS) HAD BEEN LOST ON THE LOWEP. HALF OF THE FULL CORE DISPLAY AND 4 ROD DISPLAYS AN EQUXPHENT OPERATOR (EO) WAS DISPATCHED TO THE 902-27 ANO 28 PANELS TO INVESTIGATE THL= CAUSE OF THE EVENT 'MAS FOUND TO BE OUE TO A BLOWN POWER SUPPLY FUSE XN THc 902-27 PANEL IMMEDIATE CORRECTIVE ACTION INVOLVED THE UNIT OPERATOR NONITORXNG AVERAGE ANO LOCAL POWER RANGE HONITORS (APRM) (LPRH) TO ENSURE STEADY STATE POWER.LEVELS WERE MAINTAINED THE BLOWN FUSE WAS REPLACED AT 1643 HOURS WHICH RESTORED FULL ROD POSITION INDICATION FURTHER CORRECTIVE ACTION. MILL XNCI UDE SUBHITTING A TECHNICAL SPECIFICATION CHANGE ANO UPGRADING AND EXISTING PROCEDURE THIS REPORT IS BEING SUBMITTED IN ACCORDANCE WITH 10 CFR 50 ~ 73(A) (2) (I) (B)

0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 8 0 0 0 r

k' h

0 0 0 0 0' 0 0 0 0 0 0 0 0

FORM 23 I ER SCSS DATA 08-30-91 DOCKET YEAR LER NUNBER REVISION DCS NUNBER NSIC- EVENT DATE 266 1985 003 0 8508080469 195786 06/26/85 DOCKET: 266 POINT BEACH 1 TYPE:PWR REGION: 3 NSSS:ME ARCHITECTURAL ENGINEER: BECH FACILITY OPERATOR: WISCONSXN ELECTRIC POWER CO S YH BOL: WEP COHNENTS STEP 12: TURBINE RUNBACK (OCCURRED ON 7/03/85 AFTER RETURNING TO POWER) ~

REPORTABILITY CODES FOR THIS LER ARE 13 10 CFR 50 73(a) (2) (iv): ESF actuations.

ABSTRACT POWER LEVEL 088'T 0723 HRS ON 6-26-85r UNIT 1 TRIPPED FROM 88X POMER BECAUSE OF THE FAILURE OF AN INVERTER FOR THE MHITE INSTRUMENT BUS THE FUSE IN THE INVERTER OPENED BECAUSE OF THE FAILURE OF AN INTEGRATED CIRCUIT WHICH CONTROLLED THE FIRING OF A SERIcS OF SILICON CONTROLLED RECTIFIERS (SCR'S) ~ THIS INSTRUHENT BUS FAILURE CAUSED SEVERAL INSTRUMENTATION SIGNA S TO FAXL TO ZERO ~ ONE SIGNALr THE TURBINE FIRST STAGE PRESSURE (MHITE CHANNEL) INPUT INTO THE SG LEVEL CONTROL SYSTEM CAUSED FEEDMATER FLOM TO BE REDUCED WXTHOUT A CORRESPONDING REDUCTION IN STEAN FLOWr CREATING A STEAN Fl.OW FEED FLOM MISMATCH INPUT TO THE RPS ~ ANOTHER SIGNALr SG LEVEL (WHITE CHANNEL)

CAUSED A LOW LEVEL INPUT INTO THE RPS THE STEAN FLOW FEED FLOW MISMATCH COXNCIDENT MITH THE LOM SG LEVEL RESULTED IN A REACTOR TRIP ALL EQUIPMENT RESPONDED AS DESIGNED ~

L%

l P 4 1

4 0

0 4 7 a '4 ls a as,p reap@ a s.

C 4 '. I . I

FORM 24 LER SCSS DATA 08-30-91 DOCKET 266 YEAR 1 985 '04 LER NUNBER REVISION 0

DCS NUYiBER 8509030084 NSIC 196527 EVENT DATE

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • +******************

07/25/85 e DOCKET:266 POINT BEACH 1 REGION:

TYPE:PMR NSSS ME ARCHITECTURAL ENGINEER: SECH FACILITY OPERATOR: WISCONSIN ELECTRIC POWER CO SYMBOL: MEP g COMMENTS STEPS 2 AND 3: CONP HEI - PRESSURE TRIP DEVICE g MATCH-LIST CODES FOR 913 UPDATE NEEDED THIS LER ARE:

942 UNUSUAL EVENT REPORTABILITY CODES FOR THIS LER ARE:

13 10 CFR 50 73(a) (2) (iv): ESF actuations.

ABSTRACT POWER LEVEL NG % ~ AT 0604 HRS ON 7-25-85r A 20X RUNBACK MAS INITIATED FROM A ROD POSXTXON INDiCATOR (RPI) ROD BOTTOM BISTABLE ON UNIT 1 ~ THIS BISTABLE PROVIDED A RUNBACK SIGNAL BECAUSE OF A NOHENTARY LOSS OF POWER TO 1Y06 WHXCH FEEDS THE RPI SYSTEM THE CAUSE OF THE POWER FAILURE MAS DUE TO A LOCKOUT OF THE 1X04 LOM'OLTAGE STATION TRANSFORNER THIS LOCKOUT WAS CAUSED BY A SUDDEN PRESSURE TRIP DEVICE ACTUATION THE LOCKOUT OF 1X04 CAUSED A LOSS OF POWER ON THE 4 16 KV BUSES 1A03/1A04 AND THE SAFEGUARDS 4 16 KV BUSES 1A05/1A06 THE 1A05/1A06 BUSES AND ASSOCIATED LOADS WERE PICKED UP BY AN AUTO START OF THE DG'S G01 AND G02 ~ DUE TO THE SUSTAINED LOSS OF OFFSITE AC TO THE SAFEGUARDS BUSES FOR GREATER THAN 15 HINSr AN UNUSUAL EVENT MAS DECLARED AT 0625 HRS A SHUTDOWN WAS COMMENCED AS REQUIRED BY TECH SPECS'T 0849 HRSr THE TRANSFORMER MAS RETURNED TO SERVICE ~ THE UNUSUAL EVENT WAS TERMINATED AT 0857 HRS AFTER 1X04 WAS RETURNED TO SERVICE ~ THE UNIT WAS STARTED BACK UP TO FULL POWER OPERATION AT 1/2X PER NXNUTE AT 0858 HRS.

FORH 25 LER SCSS DATA 08-30-91

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DOCKET YEAR LER NUMBER REVISION DCS NUNBER NSIC -

EVENT DATE 266 1 985 006 0 851 01 001 2 8 1 96108 09/03/85

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • 4***************

DOCKET:266- POINT BEACH 1 TYPE:PMR REGION: 3 NSSS:ME ARCHITECTURAL ENGINEER: SECH FACILITY OPERATOR: WISCONSIN ELECTRIC POWER CO ~

SYYiBOL: MEP COHHENTS STEP 1 8 2: EFFECT IX NEGATIVE VOLTAGE SPIKE REPORTABILITY CODES FOR THIS LER ARE:

13 10 CFR 50.73(a) (2) (iv): ESF actuations ~

ABSTRACT POWER LEVEL 100X AT 1453 HRS ON 9-3-85 UNIT 1 EXPERIENCED A TURBINE RUNBACK FROM- 100K TO 80Ã POWER THIS RUNBACK MAS DUE TO A NOMENTARY DOMNWARD SPIKE ON THE NUCLEAR INSTRUHENTATION SYSTEM CAUSED BY A VOLTAGE SPIKE ON THE RED INSTRUMENT BUS ~ ALL SYSTEMS OPERATED AS DESIGNED A RETURN TO 100% POWER WAS COMMENCED AT 1456 HOURS

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J f ~

3

FORM 26 LER SCSS DATA 0 8-30-91 kkkkkkk**kkk*k*kkk*kkkk**kkk***kk*k*k**kkkk*k**kkk*k**k**k*kk***kkkk DOCKET YEAR LER NUHBER REVISION DCS NUNBER NSIC EVENT DATE 266 1985 007 0 8510220439 196274 09/11/85 kkkk*k*kkkkkkkkkkkk*kkkkkkk*kk*kk**kk*kkkkkkkkkkkkk**kkkkk*kkkkkkkkk e DOCKET:266 POINT BEACH 1 REGION: 3 TYPE:PWR NSSS:ME" ARCHITECTURAL ENGINEER: BECH FACILITY OPERATOR: WISCONSIN ELECTRIC POWER CO SYMBOL: WEP CONNENTS STEP 1: COMP ISL FIRE BARRIER PACK FOR CONDUITS CODES FOR THIS LER ARE:

y REPORTABILITY 13 10 CFR 50 73(a) (2) (iv): ESF actuations.

g ABSTRACT POWER LEVEL- 100% AT 1315 HRS ON 9-11 85r UNXT 1 EXPERIENCED A TURBINE RUNBACK FROH 100% TO APPROX 80% POWER ~ THIS MAS DUE TO A MOMENTARY NEGATIVE DOWNWARD SPiKE ON THE NUCLEAR INSTRUMENTATION SYSTEM (NIS) CAUSED BY A VOLTAGE SPIKE ON THE YELLOW INSTRUMENT BUS FEEDING NXS CHANNEL 44 THE VOLTAGE SPIKE WAS CAUSED BY A CONTRACTOR PACKING FIRE BARRIER NATERIAL INTO AN ELECTRICAL CONDUIT CONTAINING THE POWER SUPPl Y TO THE INVERTER SUPPLYXNG THE YELLOW INSTRUMENT BUS ~

THE PLANT WAS RETURNED TO 100% POMER A SHORT TINE AFTER THE EVENT Al L RESPONSE TO THE TURBINE RUNBACK WAS NORHAI ~

FORM 27 LER SCSS DATA 08-30-91 DOCKET YEAR LER NUMBER REVISION DCS NUMBER NSIC EVENT DATE 266 1985 010 0 8601290256 197681 12/20185

~ DOCKET:266 POINT BEACH 1 REGION: 3 TYPE:PMR NSSS:WE ARCHITECTURAL ENGINEER SECH FACILITY OPERATOR: WISCONSIN ELECTRIC POWER CO SYNBOL: MEP

~ REPORTABILITY CODES FOR THIS LER ARE:

13 10 CFR 50 73(a) (2) (iv): ESF actuations ABSTRACT POWER LEVEL 100K ~ AT 0520 HRS ON 12-20-85 UNIT 1 EXPERIENCED A TURBINE RUNBACK TO APPROX 80X POWER THIS WAS DUE TO A FAILURE IN THE YELLOW INSTRUMENT BUS WHICH CAUSED A NEGATIVE RATE RUNBACK SIGNAL FROM CHANNEL 44 OF THE NUCLEAR INSTRUMENTATION SYSTEN ~ THE FAILURE OF THE INSTRUNENT BUS WAS DUE TO THE FAILURE OF A CAPACITOR IN THE ISOLATION TRANSFORMER IN THE INSTRUMENTATION BUS CIRCUITRY ~ THE PLANT

~ MAS RETURNED TO 100X POWER SHORTLY AFTER THE EVENT ALL PLANT RESPONSE TO THE TURBINE RUNBACK MAS NORMAL

f>

FORM 28 LER SCSS DATA 08-30-91

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DOCKET YEAR LER NUMBER REViSION DCS NUHBER NSIC EVENT DATE 266 1986 003 0 8607090090 199975 06/03/86

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • 4**************************

e DOCKET:266 POINT BEACH 1 REGION: 3 TYPE:PMR NSSS:WE ARCHITECTURAL ENGINEER: BECH FACILITY OPERATOR: WISCONSIN ELECTRIC POMER CO SYMBOL: MEP y COMMENTS STEPS 38-43: COMPLETE DESCRIPTION OF UNIT 2 EVENT GIVEN IN LER 301/86-003.

MATCH 975 TRANSIENT INITIATED ON BOTH UNITS DUE TO SINGLE FAILURE WATCH-LIST CODES FOR THIS LER ARE:

975 POSSIBLE SIGNIFICANT EVENT REPORTABILITY CODES FOR THIS LER ARE:

13 10 CFR 50.73(a) (2) (iv): ESF actuations.

REFERENCE LERS:

1 301/86-003 ABSTRACT POWER. LEVEL '00X ~ ON 6 3 86'NIT 1 AT POINT BEACH NUCLEAR PLANT EXPERIENCED A REACTOR TRIP OUE TO THE LOSS OF POMER ON THE WHITE INSTRUMENT BUS THE POWER LOSS MAS DUE TO THE TRIP OF THE MHITE INVERTER (1DY03) OUTPUT BREAKER FEEDING THE WHITE INSTRUHENT BUS ~ THE BREAKER TRIP MAS CAUSED WHEN'FTER HAXNTENANCEr THE SWING INVERTER (DYOC) MAS INCORRECTLY RESTORED TO OPERATXON ON THE DC BUS FEEDING THE WHITE INVERTERS TO BOTH UNIT 1 ANO UNIT 2 (1DY03 AND 2DY03 RESPECTIVELY) ~ THE WHITE INSTRUMENT, BUS SUPPLIES A CHANNEL OF POWER RANGE NUCI EAR INST RUHENTATXON~ WHEN POWER MAS IiVTERRUPTEDr THIS INSTRUMENTATION GENERATED A 20X LOAD REFEPENCE TURBINE RUNBACK FROM ITS DROPPED ROD DETECTXOiV CIRCUITRY THE STEP DECREASE IN POWER CAUSED THE STEAN DUMP SYSTEH TO ARM BECAUSE THE MHXTE BUS ALSO SUPPLIES POWER TO THE TREF INSTRUHENTr TREF FAXLED LOW GENERATING A TEYiPERATUR DEVIATION SIGNAL MHICH CAUSED THE STEAN DUMPS TO GO FULL OPEN AND CONTROL RODS TO STEP IN AT YiAXIHUH SPEED ~ THESE EVENTS CREATEO A PRIHARY SYSTEM COOLDOMN WHICH CAUSED PRIMARY SYSTEH PRESSURE TO DcCRESE BELOW THE REACTOR TRIP SETPOINT THE REACTOR TRIPPED ~

THE PRIMARY SYSTEi4 CONTINUED TO COOL DOWN AFTER THE REACTOR TRIP WHEN THE AUXILIARY FEEDWATER SYSTEM AUTOHATICALLY STARTED THXS COOLDOMN RESULTEO XN ACTUATION OF THE SAFETY INJECTION SYSTEM. ALI SAFETY SYSTEMS FUNCTIONED AS DESIGN PLANT SYSTEMS WERE STABILIZED AND SAFEGUARDS CIRCUITS RESET

FORM 29 LER, SCSS DATA 08-30 "91

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DOCKET YEAR LER NUNBER REVISION DCS NUHBER NSIC EVENT DATE 266 1986 005 0 8612240042 202117 11/17/86

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • A*******************%***************

DOCKET: 266 POINT B EACH 1 TYPE:PMR REGION: 3 NSSS:ME ARCHiTECTURAL ENGINEER: SECH FACILITY OPERATOR: WISCONSIN ELECTRIC POMER CO ~

SYNBOL: WEP REPORTABILITY CODES FOR THIS LER ARE:

13 10 CFR 50 73(a) (2) (iv): ESF actuations.

REFERENCE LERS:

1 266/85-003 ABSTRACT POMER LEVEL 100X ~ ON NOVENBER 17r 1986r AT 1808 HOURSr THE UNIT 1 REACTOR TRIPPED DUE TO A LOSS OF POWER ON THE RED INSTRUHENT BUS WHEN A CONTROL CIRCUIT DIODE XN THE BUS INVERTER FAILED~ THE LOSS OF POWER RESULTED IN AN INDXCATED LOM LEVEL ALARM IN THE "B" STEAN. GENERATOR AND CREATED A STEAN FLOM/FEED FLOW i4lXSHATCH CONDXTXON THE COINCIDENCE OF STEAN FLOW/FEED FLOM NISHATCH ANO LOM LEVEL TRIPPED THE REACTOR ~ POWER MAS RESTORED TO THE BUS APPROXIHATELY THREE MINUTES AFTER IT WAS LOST ~ WHILE THE REO INSTRUMENT BUS, WAS DEENERGIZEDr MANUAL CONTROL OF PRESSURXZER PRESSURE AND THE "A" ELECTRIC NOTOR-DRIVEN AUXILXARY FEEDWATER PUMP DISCHARGE PRESSURE CONTROL VALVE MAS NECESSARY TO HAINTAIN THE DESIRED PLANT CONDITIONS ~ ONE SOURCE RANGE AND AN XNTERHEDXATE RANGE NUCLEAR FLUX INSTRUMENT'AILEO AS DID THE OTHER INTERMEDIATE RANGE WHICH IS POMERED FRON THE BUS ~ ONE OF THE INTERMEDIATE RANGE INSTRUHENTS MAS RETURNED TO SERVICE PRIOR TO STARTUP OF THE UNIT ~

L4 0

I

FORM 30 LER SCSS DATA 08-30-91

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DOCKET YEAR LER NUHBER REVXSXON DCS NUNBER NSXC EVENT DATE 266 1986 006 0 '612300366 202333 11/28/86 e DOCKET:266 POINT BEACH 1 REGION: 3 TYPE:PWR NSSS:WE ARCHITECTURAL ENGINEER: SECH FACILITY OPERATOR: WISCONSXN ELECTRIC POWER CO S YH BOL: MEP CONMENTS STEP 4: NODEL 253-1-103 REPORTABILITY CODES FOR THIS LER ARE:

13 10 CFR 50 73(a) (2) (iv): ESF actuations.

LERS:

~ REFERENCE 1 266/86-001 2 266/86-003 3 301/86-003 y ABSTRACTLEVEL 100X POWER AT 0752 HOURS ON NOVEHBER 28r 1986 WHII E UNIT 1 WAS OPERATING AT 100X POWERr A 2 5 SECOND TURBINE" RUNBACK TO APPROXIMATELY 95K POWER MAS EXPERXENCED ~ THE RUNBACK MAS DUE TO A i4!ONENTARY LOSS OF POWER ON THE WHITE INSTRUMENT BUS WHICH OCCURRED WHILE THE XNSTRUHENT BUS NORNAL POWER SUPPLY INVERTER WAS BEING TRANSFERRED TO THE SPARE INVERTER ~ THE REACTOR MAS RETURNED TO 100X

~ POWER AT 0800 HOURS ~ AN EVALUATION IS BEING PERFORNED TO DETERHINE-THE FEASIBXLXTY OF PROVIDXNG A BUFFER BETWEEN THE INVERTER AND NEW COMPUTER" LOADS WHICH ARE CAUSING VOLTAGE HARMONICS ON THE INSTRUMENT BUS THE HARMONICS ARE CAUSING THE INVERTER PROTECTIVE CIRCUITS TO NOHENTARILY XNTERRUPT OUTPUT POWER WHEN TRANSFERS OF THIS TYPE ARE HADE ~

FORM 31 LER SCSS DATA 08-30-91 DOCKET YEAR LER NUMBER -.

REVISION DCS NUthBER NSIC EVENT DATE 266 1987 004 1 8711300155 207319 05/15/87

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DOCKET:266 POINT- BLACH TYPE:PMR g REGION: 3 1

NSSS:WE ARCHITECTURAL ENGINEER: BECH FACILITY OPERATOR: WISCONSIN ELECTRIC POMER- CO SYMBOL: MEP IJ CONHENTS STEP 2: TYPE LC-25 'TEP 6: STYLE NUNBER 130RF-400 STEP 1: CAUSE AX MODIFICATION WORK TO UPGRADE AN APPENDIX R SRN TO NEET REG GUXDE 1 97 STEPS 8i14r19 tlOOEI NUNBER 125CTT 10 KVA WATCH-l XST CODES FOR THIS LER ARE:

34 DESIGN ERROR OR INADEQUACY REPORTABZLITY CODES FOR THIS LER ARE:

13 10 CFR 50.73(a) (2) (iv): ESF ac'tuations ABSTRACT e POWER LEVEL 000Xe OiV NAY 15'987'ITH UNIT 1 AND UNIT 2 'SHUT DOWNr THE STATION BATTERY (005), BREAKER WAS OPENED TO ISOLATE THE STATION BATTERY FOR CELL REPLACEMENT 'HEN THE BATTERY (D05) BREAKER MAS OPENED/ THE BATTERY CHARGER (007) CAUSED A VOLTAGE SPIKE ON THE DC BUS (D01) THE VOLTAGE SPIKE AFFECTED THE ASSOCIATED INSTRUMENT BUS POWER SUPPLY INVERTERS (1DY01 ANO 2DY01) FOR BOTH UNITS AND THE STANDBY (SWING) INVERTER DYOA ~ THXS INITIATED A REACTOR PROTECTION SYSTEH ACTUATION IN BOTH UNITS THE VOLTAGE OSCILLATION MAS CLEARED WITHIN 10 SECONDS BY MANUAL'RECLOSURE OF THE BATTERY BREAKER THE LOSS OF VOLTAGE ON THL UNIT 1 RED INSTRUMENT BUS R SULTED IN A 2/4 POWER RANGE REACTOR TRIP SIGNAL FROM CHANNElS N41 AND N43 N41 TRIPPED WHEN ITS POWER SUPPLY MAS DEENERGZZED. N43 MAS IN TRIP DUE TO MODIFICATION WORK IT Al SO RESULTED IN A 1/2 INTERMEDIATE RANGE REACTOR TRIP SIGNAL THE VOLTAGE PERTURBATION ON THE UNIT 2 RED INSTRUHENT BUS RESULTED IN A 1/2 ZR N35 REACTOR TRIP SIGNAL AS MELL. AS A 1/2 SOURCE RANGE N31 REACTOR TRIP SIGNAL ALL REACTOR. PROTECTION SYSTEM CIRCUXTRY FUNCTIONED AS DESIGNED DURING THIS EVENT AN INVESTIGATION INTO THE CIRCUMSTANCES OF THIS EVENT HAS REVEALED THAT MITHOUT THE FILTERXNG EFFECT OF THE BATTERYr THE BATTERY CHARGES WILL PRODUCE VOI.TAGE PERTURBATIONS ON THEIR RESPECTIVE LOADS (THE INSTRUMENT BUSES)

yn 0 4 3 IC

FORM 32 LER SCSS DATA 08-30-91 e ***************4****************************************************

DOCKET YEAR LER NUMBER REVISION DCS NUMBER NSIC EVENT DATE 269 1986 004 0 8604230170 198909 03/12/86

~ DOCKET:269 OCONEE 1, REGION: 2 TYPE:PMR NSSS:BM ARCHITECTURAL ENGINEER: DKBE FACELITY OPERATOR: DUKE POWER CO SYMBOL: DPC y COMMENTS STEP 2: EFF EX - POWER TRANSIENT STEP 5: OPERATOR MOVED FUEL WITH ONE SOURCE RANGE DETECTOR INOPERABLE ~ OTHER REPORTABILXTY 50 ~ 73(A) (2) (I) (B) ~

REPORTABXLITY CODES FOR THIS LER ARE:

21 OTHER: Voluntary reportr special repor tr Part 21 reportr 0 etc.

ABSTRACT POWER LEVEL OOOX ~ ON MARCH 12r 1986r AT 1330 HOURSr WITH UNIT 1 SHUTDOMN AND REFUELING ACTIVITIES EN PROGRESSr THE REFUELING SENIOR REACTOR OPERATOR DISCOVERED THAT THE NUCLEAR INSTRUHENTATEON CHANNEL NI-1 WAS NOT OPERATING ~ THIS EVENTr WHICH BEGAN AT 1115 HOURSr CONSTITUTES A VIOLATION OF TECHNICAL SPECXFXCATION 3 ~ 8 2r WHICH REQUIRES CONTINUAL MONITORXNG OF CORE SUBCRITICAL NEUTRON FLUX BY AT LEAST TMO NEUTRON FLUX MONITORS WHENEVER CORE GEOMETRY IS BEING CHANGED ~ CONTRARY TO THIS REQUIREHENTr EIGHT FUEL ASSEMBLIES WERE INSERTED ENTO THE CORE MHILE NE-1 WAS INOPERABLE UPON THE DISCOVERY OF THE LOSS OF SIGNAL FROM NI-1 REFUELING ACTIVITIES MERE IMHEDXATELY STOPPED SUBSEQUENT CORRECTXVE ACTIONS INCLUDED AN ASSESSMENT OF CORE GEOMETRY CHANGES WHILE NE-1 WAS INOPERABLEr A DETERMINATION OF THE CAUSE OF THE LOSS OF NI 1 SIGNAI r AND ACTION TO RETURN NE 1 TO SERVXCE REFUELING ACTEVXTEES MERE RESUHED AFTER THE REFUELING REACTOR OPERATOR HAD BEEN REINSTRUCTED ON PROPER ADHERENCE TO THE REFUELING PROCEDURE REQUXREMENTS. THE CAUSE OF THIS EVENT WAS DETERMINED AS PERSONNEL ERROR BECAUSE THE REFUELING REACTOR OPERATOR FAILED TO HAENTAXN FULL REQUXREHENTS OF THE REFUELING PROCEDURE WHILE INSTRUCTXNG THE EXECUTION OF FUEL MOVEMENT PROCEDURE STEPS'HE HEALTH AND SAFETY OF THE PUBLIC WERE NOT AFFECTED BY THIS XNCIDENT ~

0 FORM 33 LER SCSS DATA 08-30 "91 e ********************************************************************

DOCKET YEAR LER NUMBER REVISION DCS NUllB E R NSIC F VENT DATE 271 1980 004 0 8002080489 154604 01/09/80 DOCKET 271. VERHONT YANKEE TYPE:BWR REGION: 1 NSSS:GE ARCHITECTURAl ENGINEER: EBAS FACILITY OPERATOR: VERHONT YANKEE NUCLEAR POWER CORP SYMBOL: VYC COHHENTS STEP 2:MODEL L5R6-70-OVST4626 ABSTRACT POWER LEVEL 095% CAUSE POWER SUPPLY FAN FAILURE~ DURING NORMAL OPERATIONs ALL ROD POSITION INDICATION WAS LOSTr ACCONPANIEO BY RPIS INOP ALARM/ ALL ROD DRIFT ALARNSr RWH ROO BLOCK ANO OVERTRAVEL ALARMS POSITXON XNDXCATION RETURNED FIVE HINUTES LATER THIS SEQUENCE WAS REPEATED SIX MORE TiilES AT FIVE AT SIX NXNUT INTERVALSr WITH EACH OCCURRENCE LASTING FIVE TO SEVEN HINUTES THE COOLING FAN IN THE POWER SUPPLY HAO FAILED CAUSING THE POWER SUPPLY TO OVERHEAT AND FAIL. WHEN THE POWER SUPPLY COOLEOw iT WOULD RE ENERGIZE ~ THE INHEDXATE SOl UTION WAS TO SLIDE THE POWER SUPPLY OUT OF THE PANEL ANO REMOVE THE TOP COVER ~ ATMOSPHERE COOLING-WAS SUFFICIENT TO PREVENT TRIPPING THE FAN WAS SUBSEQUENTLY REPLACED

i i4 e

1

FORM 34 LER SCSS DATA 08-30-91

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DOCKET YEAR LER NUMBER REVISION DCS NUMBER NSIC EVENT DATE 271 1984 018 0 8409170568 191249 08/01/84

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e DOCKET:271 VERMONT YANKEE REGION: 1 TYPE:BWR NSSS: GE ARCHITECTURAL ENGINEER EBAS FACILITY OPERATOR: VERMONT YANKEE NUClEAR POWER CORP SYMBOL: VYC y COMMENTS STEP 3: CAUSE SE RETURNING LENS TO NORMAL SUPPLY CODES FOR THIS LER ARE:

g REPORTABILITY 13 10 CFR 50 73(a) (2) (iv): ESF actuations

~ ABSTRACT POWER LEVEL OOOX ~ ON 8 1 84r WITH THE REACTOR SHUT DOWN AND WHILE SHXFTING 480V VITAL BUSESr A VOLTAGE TRANSIENT CAUSED AN INADVERTENT HI-HI TRIP FROM APRM 'C' WHICH RESULTED IN A REACTOR SCRAM AFTER VERIFYING THE CAUSEr THE SCRAM WAS RESET ~

FORM 35 LER SCSS DATA 08-30-91 DOCKET YEAR LER NUNBER REVXSIO'N DCS NUNBER NSIC EVENT DATE 271 1986 011 0 8607140396 200211 06/10/86

• • • • • %****************************A*********************************

DOCKET:271 VERHONT YANKEE TYPE:BMR REGXON: 1 NSSS:GE ARCHXTECTURAL ENGINEER: EBAS FACILITY OPERATOR: VERNONT YANKEE NUCLEAR POWER CORP.

SYMBOL: VYC COMMENTS STEP 1: CAUSE AX - MAINTENANCE ON RPS BUS B NORMAL POWER SUPPLY REPORTABXLITY CODES FOR THIS LER ARE:

13 10 CFR 50.73(a) (2) (iv): ESF actuations.

ABSTRACT POWER LEVEL 000/ ~ ON 6-10-86 AT 2041 HOURS WHILE THE PLANT MAS SHUTDOWN AND PERFORHING RECIRCULATION PUMP TESTING THE REACTOR PROTECTIVE SYSTEM (RPS) ALTERNATE POWER SUPPLY TRIPPED CAUSING A HALF SCRAM ON THE '-'B" CHANNEL CONCURRENT WITH THXS AN AUTO SCRAH SIGNAL MAS RECEiVED ON THE "A" CHANNEL AS A RESULT OF A NEUTRON MONITORING SYSTEN A-1 TRIP ~ THE A TRIP IS ATTRIBUTED TO AN XRM GOING "HI-HI" DUE TO NOISE IN THE CIRCUXT THIS ADDITIONAL HALF SCRAN RESULTED IN A FULL SCRAH SIGNAL BEING RECEIVED THcRE MERE NO ADVERSE SAFETY CONSEQUENCES AS A RESULT OF THIS EVENT AND ALL SYSTENS MERE RETURNED TO THEIR NORNAL CONDXTIONS ~ ALTERNATE RPS SUPPLY VOLTAGE STABILITY HAS BEEN DETERMINED TO BE THE ROOT CAUS= OF THIS EVENT

5 w v c

FORM 36 LER SCSS DATA 0 8-30-91 DOCKET YEAR LER NUHBER REVISION DCS NUMBER NSIC EVENT DATE 271 1987. 014 0 8710140034 206713 09/08/87

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • It**************

DOCKET:271 VERMONT YANKEE TYPE:BMR e REGXON: 1 NSSS:GE ARCHITECTURAL ENGINEER: EBAS OPERATOR: VERtlONT YANKEE. NUCLEAR POWER CORP.-

'ACXLITY SYHBOL: VYC COHHENTS STEP 4 CAUSE VX HAINTENANCE~ STEPS 6r12 CAUSE SX INADEQUATE TRAINING ~

y WATCH-LEST CODES FOR THIS LER ARE:

36 It<ADEQUATE TRAINiNG 13 '0 CFR 50.73(a) (2) (iv): ESF actuations.

y REPORTABILITY CODES FOR THIS LER ARE:

(

ABSTRACT g POWER LEViL OOOX EVENT 1: AT 2050 HOURS ON 09/08/87- WITH THE REACTOR IN THE COLD SHUTDOWN CONDITIONs THE FEEDER BREAKER (BU*) FOR 480 VAC BUS 8 (SMGR*) WAS OPENEDr TO RETURN BUS 8 TO ITS NORHAL SOURCE OF POMERr AND A FULL REACTOR SCRAH OCCURRED BUS 8 SUPPLIES POMER TO HOTOR CONTROL CENTER 8A (NCC) (SMGR*).WHICH XS THE POWER SOURCE FOR A", REACTOR PROTECTION SYSTEH (RPS) (JE*) HG (*ilG) SET AND IN TURN POWERS "A" RPS LOSS OF POWER TO EITHER RPS (A OR B) MILL CAUSE A HALF SCRAH ~ AT 2053r THE SCRAH MAS RESET AND SYSTEMS WERE RETURNED TO NORMAL EVENT 2: AT 0257 HOURS ON 09/10/87 WITH THE REACTOR IN THE COLO SHUTDOWN CONDITION THE FEEDER BREAKER (BU*) FOR HOTOR CONTROL CENTER 8B(HCC) (SMGR*) WAS OPENEDr TO FACILXTATE TESTING THE BREAKERr AND A FULL REACTOR SCRAH OCCURRED~ DURXNG THIS EViNTr THE "A*'PS WAS POWERED FROM ITS ALTERNATi POMER SUPPLY MCC 88 ~ AT 0307 THE SCRAM MAS RESET AND SYSTEMS MERE RETURNED TO NORHAL BOTH EVENTS: FOR BOTH PLANNED EVOLUTIONSr OPERATIONS INTENTIONALLY RENOVED POWER FROM "A" RPS AND THE EXPECTED HALF-SCRAN OCCURRED ~ THE FULL SCRAH MAS UNANTICIPATED OPERATXONS INVESTIGATIONr FOLLOWING THE EVENT ON 09/10/87 REVEALED THAT THE AVERAGE POMER RANGE NONITOR SYSTEH (APRi4l)(*JE) CHANNEl S A AND C ALSO SHARE THEIR LOCAL POWER RANGE MONITOR (LPRtl) (DETI) INPUTS MITH CHANNELS D AND F ~

FORM 37 LER SCSS DATA

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • 4***********

DOCKET YEAR LER NUNBiR REVISION DCS NUNBER NSIC EVENT DATE 272 1981 100 0 8112010515 170100 10/19/81

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • k************************

DOCKET:272 SALEM 1 TYPE:PMR REGION: 1 NSSS:ME ARCHITECTURAL ENGINEER: PSEG FACILITY OPERATOR: PUBLIC SERVICE ELECTRIC 5 GAS CO ~

SYNBOL:- PEG ABSTRACT WHILE PREPARING FOR A STARTUPr WITH THE TRIP BREAKERS CLOSEOr THE NEUTRON LEVEL AND STARTUP RATE METERS FOR THE INTERMEDIATE RANGE NUCI EAR INSTRUNENTATIONr CHANNEL 1r MiRE OBSERVED SPIKING FRON 0 TO

~ FULL SCALE ~ THE CHANNEL WAS DECLARED INOPERABLE THE CAUSE OF THE SPIKING WAS A FAILED HIGH-VOI TAGE POMER SUPPLY ~ ALL CABLES AND CONNECTORS WERE TESTED SATISFACTORILY AND THE TRIP BREAKERS WERE OPENED ~ SUBSEQUENTLYr THE HIGH VOLTAGE POWER SUPPLY MAS REPLACEOr PROPERLY CALIBRATEDr AND TESTED SATISFACTORILY~

0-FOR N 38 LER SCSS DATA 08-30-91 DOCKET YEAR LER NUMBER REVISION DCS NUNBER NSIC EViNT DATE 272 1981 103 0 8112010490 170252 10/25/81 y DOCKET.272 SALEM 1 REGION: 1 TYPE:PWR NSSS:WE ARCHITECTURAL ENGINEER- PSEG FACILITY OPERATOR: PUBLIC SERVICE ELECTRIC 5 GAS CO ~

SYMBOL: PEG ABSTRACT THE CONTROL OPERATOR NOTICED THAT THE INTERMEDIATE RANGE DETECTOR N-36 HAD FAILED~ THE LEVEL TRIP SMITCH FOR THIS CHANNEL MAS PLACED IN THE BYPASS POSITION ~ THE CAUSE WAS A FAILURE OF THE DETECTOR HIGH VOLTAGE POWER SUPPLY ~ THE POWER SUPPLY MAS. REPLACED AND TESTED SATISFACTORILY

0 FORM 39 LER'SCSS DATA OS-30-91.

• • • • • • • • • • • • • • • • • • • • • • • • • • Br*****************************************

DOCKET YEAR LER NUtlBER REVISION OCS NUMBER NSIC EVENT DATE 272 1991 008 0 9103200417 221220 02/17/91 DOCKET:272 SALEM 1 TYPE:PWR REGION: 1 NSSS:ME ARCHITECTURAL ENGINEER: PSEG FACILITY OPERATOR: PUBLIC SERVICE ELECTRIC ltd GAS CO ~

SYNBOL: PEG WATCH-LIST CODES FOR THIS LER ARE:

35 HUMAN ERROR 941 REPORT ASSOCIATED ltITH 10 CFR 50 72 REPORTABILITY CODES FOR THIS LER ARE:

13 10 CFR 50.73(a) (2) (iv): ESF actuations.

ABSTRACT POWER LEVEL OOOX ~ ON 2/17/91 AT 0530 HOURSr A REACTOR PROTECTION SYSTEM (RPS) SIGNAL FROM THE NUCLEAR INSTRUMENTATXON SYSTEM (NIS) WAS RECEIVED ~ THE OVERHEAD ANNUNCIATIONr INDXCATING THE CAUSE OF THE RPS SIGNALr MAS "IR FLUX HIGH" THE UNIT WAS IN COLD SHUTDOWN (NODE 5) IN SUPPORT OF ITS NINTH REFUELXNG OUTAGE THE ROOT CAUSE OF THIS EVENT IS PERSONNEL ERROR AS ATTRIBUTED" TO INATTENTION TO DETAIL AT THE TINE OF THE EVFNTr THE 1N3'2 SOURCE RANGE NIS CHANNEL CABLE REPLACEMENT MAS IN PROGRESS ~, IN SUPPORT OF THIS WORKr THE SUB JECT CHAtlN L S RPS FUNCTIONS ARE BLOCKEO AND THEN THE CHANNEL IS DEENERGIZED BY REMOVING XTS FUSES ~ THE MAINTENANCE ILC TECHNICIANr PERFORMING THIS MORKr HAD INADVERTENTLY PULLED THE FUSE FOR THE 1N36 INTERMEDIATE RANGE NXS CHANNEL INSTEAD OF THE 1N32 FUSc ~ THIS RESULTEO IN THE RPS ACTUATION BY SATISFYING THE 1 OUT OF 2 SOLID STATE PROTECTION SYSTEM (SSPS)

LOGIC WHEN THE HIGH FL'UX BISTABLE FAILEO TO ITS SAFE POSITION ON LOSS OF POWER THE TECHNICIAN XNVOLVED DID NOT APPLY GOOD WORK PRACTICES HE DID NOT PERFORtl A "SELF CHECK" TO ENSURE THAT HE MOULD REMOVE THE CORRECT FUSE ~ THE 1N32 CHANNEL DRAWER IS l OCATED APPROXIMATELY 6'-

ABOVE THE FLOORr DIRECTLY ABOVE THE 1N36 CHANNEL ORAMER ~ THE FUSES OF EACH CHANtlEL ARE LOCATEO ON THE DRAWER OUTSIDE FACE IN THc LOWER LEFT ScCTXON ~ 'HIS EVENT HAS BEEN REVIEMEO BY MAINTENAtlCE DEPARTMENT MANAGEMENT

rg FORM 40 LER SCSS DATA 08-30"91 DOCKET YEAR LER NUfdBER REVISION DCS NUMBER NSIC EVENT DATE 275 1983 010 0 8306210078 183398 05/14/83

~DOCKET:275 DIABLO CANYON 1 TYPE:PWR REGION: 5 NSSS:WE ARCHITECTURAL ENGINEER: PGEC FACILITY OPERATOR: PACIFIC GAS ff ELECTRIC CO SYMBOL: PGE COMMENTS STEP 3 COMP ~ XA = RADIATION t'lONXTOR ALARMSr SEISMIC ALARMS'ND FIRE 0ETECTXON ALARf'lS 7 ISYS ZY IN IG IF REFERENCE LERS.

1 275/83-008 ABSTRACT PRIOR TO FUEL LOADr POWER TO ALL MAIN CONTROl ROOM ANNUtfCXATORS WAS LOST DURING CONSTRUCTION ACTIVITY IN THE ANNUNCIATOR CABXNETS

~ RESULTr ALARM STATUS FOR VARIOUS RADIATION MONITORSr SEISMIC AS A MONITORXNG INSTRUf'IENTATION AND FIRE DETECTION INSTRUMENTATION WAS LOST FOR A PERIOD OF 32 MINUTES ~ ALL APPLXCABLE TECHNICAL SPECIFICATION ACTION STATEMENTS WERE SATISFIED AS LISTED XN SUPPLEMENTAL INFORMATXON REPORTABLE PER TECH SPECS SECTION 6 ~ 9 1 13 ~ B CONSTRUCTION ELECTRICIAN INADVERTENTLY TOUCHED HOT WIRE TO GROUNDS SHORT CIRCUITING THE PANEL POWER WAS RESTORED AND THE ANNUNCIATOR RETURNED TO SERVICE ~ THE WORKER INVOLVED WAS ADMONISHED REGARDING THE POSSIBLE CONSEQUENCES OF HIS ACTIONS AND TO PAY MORE CAREFUL ATTENTION TO HIS WORK ACTIVITIES CONSTRUCTION WORKERS ON VITAL PLANT EQUIPMENT WILL RECEIVE ADDITIONAL TRAINXNG PRIOR TO WORK.

0

~ ~ 5 4 4

FOR H 41 LER SCSS DATA 0 8-30-91 DOCKET YEAR LER NUYiBER REVISXON DCS NUNBER NSIC EVENT DATE 275 1983 0?4 0 8311220228 187412 10/07/83 DOCKET:275 DIABLO CANYON 1 TYPE:PMR REGION: 5 NSSS:ME ARCHXTECTURAL ENGINEER: PGEC FACILITY OPERATOR: PACIFIC GAS 5 ELECTRIC CO SYMBOL: PGE COHNENTS STEP 3: XSYS SM = UNKNOWN AREAS' REFERENCE LERS:

1 275/83"010 ABSTRACT PRIOR TO FUEL LOADS POWER TO Al L HAIN CONTROL ROON ANNUNCIATORSr MAS LOST DURING CONSTRUCTION ACTIVITY IN THE ANNUNCIATOR CABINETS AS A RESULTS ALARM STATUS FOR VARIOUS RADIATXON NONXTORSi SEISMIC MONITORXNGr AND FIRE DETECTION INSTRUHENTATXON WAS LOST FOR A PERIOD OF APPROXIHATELY 5 NINUTcS ~ ALL APPLICABLE TECH SPEC ACTION STATEHENTS MERE SATISFIED AS LISTED XN SUPPLEHENTAL INFORMATION A SIMILAR EVENT MAS REPORTED. IN LER 83-010 'EPORTABLc PER TECH SPEC SECTION 6 ~ 9 1 13B ~ CONSTRUCTION ELECTRICIAN INADVERTENTLY GROUNDED THE HOT MIRE SHORT-CIRCUITING THE PANEL POWER WAS RESTORED AND THE ANNUNCIATOR RETURNED TO SERVICE PERSONNEL INVOLVED IN ANNUNCIATOR CABINET WORK WILL RECEIVE TRAINING IN THE INPORTANCE OF PREVENTING RECURRENCE OF THIS EVENT

0 FORM 42 LER SCSS DATA 08-30-91 6 ********************************************************************

DOCKET YEAR LFR NUMBER REVISION DCS NUMBiR NSIC iVENT DATE 275 1985 - 033 0 8512100697 197543 10/25/85 DOCKET:275 DIABLO CANYON 1 TYPE:PWR REGION: 5 NSSS:WE ARCHITECTURAL ENGINEER: PGEC FACXLITY OPERATOR: PACIFIC GAS 8 ELECTRIC CO ~

SYMBOL: PGE g COMMENTS STEP 4: COMP MEX - COMPARATOR STYLE 4111082-001r STEPS 758: COMP RLX RELAY MONITORING RCP BREAKER POSITION ~

REPORTABILITY CODES FOR THIS LER ARF-13 10 CFR 50 73(a) (2) (iv): ESF actuations.

REFERENCE LERS 1 275/85"012 2 275/85-015 ABSTRACT POWER LEVEL 1 00% ~ AT 1 321 POTr 1 0 25 85 WHILE IN MODE 1 AT 100%

POWERr AUTOMATIC REACTOR AND TURBINc TRIPS OCCURRED TWO PLANT TECHNICIANS WERc RESTORING THE BORIC ACXD STORAGE TANK LEVEL INDICATING/ALARMCIRCUIT WHEN A FUSE WAS BEING INSTAI LEO WHILE RETURNING THE CIRCUIT TO OPERATIONr A SHORTED CAPACITOR IN A COMPARATOR MODULE CREATED.A MOMENTARY SHORT IN A 120V POWER SUPPLY BUS CIRCUIT THE RESULTANT REDUCTXON IN INVERTER VOLTAGE OUTPUT CAUSED A RELAY IN THE SOLID STATE PROTECTION RACKSr WHICH MONITORS RCP BREAKER POSXTIONr TO MOMENTARILY DROP OUT SINCE THE UNIT WAS ABOVE P 8r ONLY 1 RCP BREAKER OPEN SIGNAL WAS RcQUXRED TO INITIATc A REACTOR TRIP THE COMPARATOR MODULE WAS REPLACED AND THE UNIT WAS RETURNED TO POWER IN ACCORDANCE WITH PROCEDURES ~ TO PREVENT RECURRiNCEr PGSE XS SEEKING EXPEDXTXOUS NRC APPROVAL OF A LICENSE AMENDMENT REQUEST TO CHANGE THE RCP BREAKER POSITION TRIP LOGIC THIS WILL PREVENT A SINGLE FAILUREs SUCH AS THE FAILEO COMPARATOR IN THIS CASEr FROM PUTTING THE PLANT THROUGH AN UNNECESSARY TRANSXENT

~

FORN 43 LER SCSS DATA 08-30-91 DOCKET -

YEAR LER NUHBER REVISION DCS NUMBER NSIC EVENT DATE 2.77 1 987 011 0 8708170111 205725 07/10/87

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • +*************+**********

OOCKET:277 PEACH"BOTTOM 2 TYPE:BMR REGION: 1- NSSS:GE ARCHITECTURAL ENGINEER: BECH FACILITY OPERATOR: PHIl ADELPHIA ELECTRIC CO S YHBOL: PcC MATCH-LIST CODES FOR THIS LER ARE:

20 'QUIPHENT FAILURE REPORTABILITY CODES FOR THIS LER ARE:

13 10 CFR 50.73(a) (2) (iv): ESF actuations ABSTRACT POWER LEVcL'00'N JUl Y 10r 1987~ AT 0905 HOURSr A PRIMARY CONTAINMENT ISOLATION SYSTEM (PCIS) GROUP IIB ISOLATION OCCURRED WHILE OPERATING THE RCSIDUAL HEAT REMOVAL SYSTEH IN THE SHUTDOMN COOLING NODE THIS ACTION OCCURRED. AS THE RESULT. OF A BLOMN FUSE (10A-F2B)

WHICH CAUSED A LOSS-OF-POWER TO THE SYSTEH IXB RESIDUAL HEAT REMOVAL SYSTEH LOGIC BUS THE LOSS-OF-POWER RESULTED IN Di-ENERGIZATION OF RELAY 10-K114B AND SUBSEQUENT, CLOSURE OF THE SHUTDOMN COOLING NODE SUCTION VALVES THERE WERE NO ADVERSE CONSiQUENCES AS A RESULT OF THIS EViNT WHICH MOULD HAVE AFFECTED PLANT SAFETY THERE MAS NO OBSERVABLi CHANGE IN REACTOR COOLANT TEHPERATURE THE ROOT CAUSE FOR THE BLOWN FUSE MAS NOT DETERHINED ~ AS CORRECTIVE ACTIONSr THE FUSE MAS REPLACED AN THE ALARMS AND PCIS ISOLATXON SIGNAL MERE RESET THE SHUTDOMN COOLING ODE MAS REESTABLISHED BY0930 HOURS ~

re f

p k + g g h

FORM 44 LER SCSS DATA 08-30-91

• • • • • • • • • • • • 4*******************************************************

DOCKET YEAR LER NUMBER REVISXON OCS NUMBER NSIC EVENT DATE 277 1987 032 0 88031 40361 208490 11/1 0/87 g,DOCKET:277 PEACH BOTTOM 2 TYPE:BWR REGION: 1 NSSS:GE ARCHITECTURAL ENGINEER: BECH FACILITY OPERATOR: PHII ADELPHIA ELECTRIC CO ~

SYMBOL: PEC COMMENTS STEP 42: COMP XS TRANSFERR SWITCH' MATCH-LIST CODES FOR THIS LER ARE:

34 DESIGN ERROR OR INADEQUACY CODES FOR THIS g REPORTABILXTY 14" 10 CFR 50.73(a) (2) (v):

LER ARE:

Event that could have prevented fulfillment of a safety function REFERENCE LERS:

1 277/85-023 ABSTRACT POWER LEVEL.- - 000K ON= 11/10/87. WITH UNIT 2 IN'HE COI D SHUTDOWN CONDITION IT WAS DETERMXNED THAT ELECTRICAL'ABLES INSTALLED IN THE CABLE SPREADING ROOM AS THE RESULT OF A PLANT MODIFICATION DID NOT CONFORM TO THE SEPARATION CRITERIA AS IDENTIFIED XN THE PEACH BOTTOM ATOMIC POWER STATION UPDATED FSAR SECTXONS 7 ' 6 ' ANO 8 4 ~ THE MODIFICATION INVOLVED THE REMOVAL OF THE YARWAY TEMPERATURE COMPENSATEO REFERENCE COLUMNr- REROUTING OF THE ASSOCIATED REACTOR LEVEL MEASUREMENT INSTRUMENT SENSING LINES AND THE ADDITION OF REACTOR PRESSURc COMPENSATION TO THE REACTOR WATER LEVEL MEASUREMENT AT PBAPS UNIT 2 THERE WERE THREE CAUSES OF THIS EVENT: 1)

ENGINEERING DESIGN PERSONNEL FAILED TO PROVXOE AN ADEQUATE DESIGN TO CONSTRUCTION PERSONNEL') DESIGN DOCUMENTS WERE INADEQUATE FOR FXELO INSTALLATION PERSONNEI AND 3) QUALITY CONTROL FAILEO TO IDENTIFY THE NONCONFORMING CONDITION AS CORRECTIVE ACTIONS~ THE CABLES HAVE BEEN REROUTED OR WRAPPED WITH A FIRE RETARDANT BARRIER ~ AS ACTIONS TO PREVENT RECURRENCE'RAINING WAS HELD FOR THE PECO ENGINEERING DESIGN GROUP PECO PBAPS QUALITY CONTROL GROUP AND THE PECO PBAPS CONSTRUCTION GROUP WHXCH REXNFORCEO THE ROUTING AND SEPARATXON CRITERIA WHICH MUST BE INCLUDED IN THE APPLICABLF DESIGN AND INSTALLATIONS IF THXS DEFICIENCY HAD REMAINED UNCORRECTEDr AN INTERNALLY GENERATED ELECTRICAL FAULT IN THE AFFECTED CABLES OPERATIONS OF SEVERAL PLANT SYSTEMS MAY'FFECT

s ~ 0 k C

FORM 45 LER SCSS DATA 08-30-91

• • • • • • • • • • • • • • • • • • • • • • 4********************************************%'OCKET YEAR LER NUMBER REVISION DCS NUMBER NSXC EVENT DATE 277 1988 020 0 8809010336 210285 07/29/88 DOCKET:277 PEACH'BOTTOM 2 TYPE:BWR g REGION: 1 NSSS:GE ARCHITECTURAL ENGXNEER: BECH FACILITY OPERATOR: PHILADELPHIA ELECTRXC CO SYMBOL: PEC COMMENTS STEP 7: MODEL NO ~ AM-4 16-250 CODES FOR THIS LER ARE:

'ATCH-LIST 20 EQUIPMENT FAILURi

.. 'g.,941. REPORT ASSOCIATED WITH 10 CFR 50 72

'REPORTABILITY CODES FOR THIS l ER ARE:

13 10 CFR 50 73(a) (2) (iv): ESF actuations

. REFERENCE LERS:

1 277/86-010 ABSTRACT POWER LEViL OOOO~ ON JULY 29'988 AT 1858-HOURS> THE CAPACXTORS

'WHICH CONNECT THE 500KV 0'1 BUS TIE LINE TO THE A PHASE POTENTIAL TRANSFORMER FAILED~ THIS FAILURE RESULTED XN A FIRE OF THE POTENTXAL TRANSFORMER AT THE NORTH SUBSTATION AND A VOLTAGE DISTURBANCE WHICH ULTXMATELY RESULTED IN SEVERAL ENGXNEERED SAFETY FEATURE ACTUATIONS ON UNITS 2 AND 3 AND A PARTIAL LOSS OF TELEPHONE COMMUNXCATIONS AT

. PBAPS THE EVENT IS REPORTABLE UNDER 50 '3(A)(2)(IV) ~ THE CAUSE OF THE CAPACITORS TO FAIL WAS DUE TO NORMAL WEAR ~ Al L SYSTEMS WERE RETURNED TO NORMAL BY 2103 HOURS THE POTENTIAL TRANSFORMER WAS REPLACED AND RETURNED TO SERVICE ON AUGUST 2 1988. THE DURATION OF THE EVENT WAS 125 MINUTES ~ THERE WERE NO ADVERSE CONSEQUENCES OF THIS EVENT WHICH. WOULD HAVE AFFECTED PLANT SAFETY ALL UNIT 2 AND 3 RPS AND PCIS LOGICS FUNCTIONED AS EXPECTED. DURING THE MONTH PRIOR TO THE EVENTr THE POTENTXAL TRANSFORMER HAD BEEN IDENTIFXEO AS GXVING ERRONEOUS READINGS ~ DUE TO THE HIGH LOAD DEMANDS THE TRANSFORMER UNXTS WERE NOT TAKEN OUT OF SERVICE FOR INSPECTION ~ THEREFORE'O ACTION TO PREVENT RECURRENCE WILL BE TAKiN~

p

'4 4

FORN 46 l ER SCSS DATA e ********************************************************************

I DOCKET YEAR LER NUHBER REVXSION OCS NUMBER NSXC EVENT DATE

~

280 1984 001 1 8504290512 196193 01/06/84

• • • • • • • • • • • 4******+*************************************************

e DOCKET:280'URRYREGION:1 2

TYPE:PWR NSSS: ME ARCHITECTURAL ENGINEER: SWXX FACILXTY OPERATOR: VIRGINIA ELECTRXC POWER CO SYMBOL: VEP COHNENTS STEP 4: CAUSE CODE IX -- POWER SURGES STEP 9: CAUSE CODE LX UNDERCOHPEiNSATED L REPORTABXLITY CODES FOR THIS LER ARE:

13 10 CFR 50 73(a) (2) (iv): ESF actuations.

ABSTRACT POWER LEVEL 100X~ ON 1 6r A REACTOR TRIP OCCURRED AS A RESULT OF AN OVER TEHPERATURE DEITA-T (OT DELTA T) SIGNALS PLANT PARAHETERS OXD NOT INDICATE A VALID OT DELTA T CONDITION AT THE TINE OF THE EVENTr INSTRUHENT TECHNICIANS MERE PERFORMING A PERIODIC TEST WHICH REQUIRED THE CH IX OT DELTA T BISTABLES TO BE IN= THE TRIP NODEr AND MAINTENANCE WAS BEING PERFORHEO ON THE PLANT GAITRONXCS (P A ) SYSTEM>>

THE GAITRONXCS SYSTEM IS POMERED FRON THE UNIT I VITAL BUS I WHEN THE GAITRONICS WAS RE ENERGXZEDr AN APPARENT POWER SURGE OCCURRED XN THE GAITRONICS SYSTEN THE POMER SURGE IS BELIEVED TO HAVE INDUCED A VOLTAGE TRANSIENT XN VITAL BUS I WHICH RESULTEO IN TRIPPING THE RELAYS FOR OT DELTA T REACTOR TRIP CH I. SINCE CH XX MAS IN TRIP AT THE

'TINE IN ORDER TO SUPPORT PERFORHANCE OF P ~ T 2 ~ 1r THE 2/3 MATRIX WAS COMPLETED AND AS A RESULT A REACTOR TRXP OCCURRED AN ANALYSIS HAS BEEN COHPLETEO TO EVALUATE THE EFFECTS OF THE GAXTRONICS SYSTEM ON THE VXTAL INSTRUMENT BUS ~ HAINTENANCE PROCEDURES HAVE BEEN DEVELOPED AND HARDWARE HODIFICATIONS ARE BEING EVALUATED

0 FORH 47 LER SCSS DATA'8-30"91

• • • • • • • • • • • • • • • • • • • • • 4**********************************************

DOCKET YEAR LER NUHBER REVISION DCS NUHBER NSXC EVENT DATE

~

280 1984- 002 0 8402220435 189161 01/18/84

• • • • • 4**************************************************************

DOCKET:280 SURRY 1 TYPE:PWR REGION: 2 NSSS:ME ARCHITECTURAL ENGINEER: SWXX FACILXTY OPERATOR: VIRGINIA ELECTRIC POMER CO S Ytl BOL VEP COHHENTS STEP 8. COHPONENT COD" HSC CROMBAR CIRCUIT REPORTABILITY CODES FOR THIS LER ARE:

13 10 CFR 50 73(a) (2) (iv): ESF actuations.

ABSTRACT POWER LEVEL 100X. THE UNIT MAS AT FULL POWER ON 1-18-84. AT 0834 HOURS'HEN NUMEROUS CONTROL ROOH INDICATIONS ANO ANNUNCIATORS STARTED BEHAVING ERRATICALLY IT MAS OETERHINEO THAT A VOLTAGE SPIKE =WAS IN PROGRESS ANO THE UNIT. WAS HANUALLY TRIPPED TO PLACE IT IN A SAFE CONDITION "

DURING CABI E REHOVAL FROHi A NO'ONGER USED HEAT TRACING BREAKER FOR A DESIGN CHANGEr A CABL'E FELL OUT OF AN ADJACENT BREAKER BECAUSE OF AN APPARENT LOOSE SCREW ~ THIS ADJACENT BREAKER WAS THE FEEDER FOR THE SEHI VXTAL BUS ~ THE LOOSE CABLE BEGAN ARCING~ AND THIS

-MAS THE CAUSE OF THE ERRATIC INDICATIONS. THE SEHI VXTAL BUS BREAKER MAS OPENED FOR ABOUT ONE HXNUTE SO THE LOOSE CABLE COULD BE RECONNECTED

o e o e a e e o e e a e e o o e o e o % 0 0 o ~ o o o e e o e e e e o e o e e e e o 0

FORM 48 LER SCSS DATA 08-30-91 4'**************************************************************4****

DOCKET YEAR LER NUMBER REVISXON DCS NUMBER NSXC EVENT DATE 281 1982 022 0" 8206010218 173687 04/13/82

• • • • • • • • • • • • • • • • • • • • • +**********************************************

'I e DOCKET:281 P

SURRY 2 REGION: 2 TYPE:PWR NSSS:WE ARCHITECTURAL ENGINEER: SWXX FACILITY OPERATOR: VIRGINIA ELECTRIC POMER CO SYMBOL: VEP ABSTRACT THE NUCLEAR POMER RANGE INSTRUMENT 44 (N44) PANEL WAS AUTONATICALlY

.DE ENERGIZED BY IT'- PROTECTION CIRCUIT PLANT OPERATION WAS

=CONTINUED AS PER TECH SPEC TABLE 3 7 1 ' THXS EVENT XS REPORTABLE PER

-TECH SPEC 6 6 GAB(2) A VOLTAGE SURGE ON. VITAL BUS 4 CAUSED BY LIGHTNING ARRESTOR FAILURE AND DXFFERENTIAL LOCKOUT OF 42 AUTO-TXE TRANSFORMERr RESULTED IN THE DE ENERGXZATION OF THE N44 POMER SUPPLY ~

THE POWER SUPPLY MAS RESTORED'ND N 44 WAS RETURNED TO SERVICE AS

=PER PT 1 ' 'HE 02 AUTO-TIE TRANSFORNER WAS RETURNED TO SERVXCE FOLLOWING REPLACEMENT OF THE FAILED LXGHTNING ARRESTOR

0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 FORM 49 LER SCSS DATA- 08-30-91 e ****************************+***************************************

DOCKET YEAR LER NUMBER REVISION DCS NUMBER NSXC EVENT DATE 281 1984 009 0 8405210244 189706 04/15/84

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • %******+***********

DOCKET:281 SURRY 2 TYPE:PMR REGION: 2 NSSS:WE ARCHITECTURAL ENGXNE ER: SM XX FACILITY OPERATOR: VIRGINIA ELECTRIC POMER CO ~

S YblBOL: VEP COMMENTS STEP 2 COMPONENT CODE HEI NULTXHETERr SYSTEM ZX=TEST EOUXPHENT REPORTABILXTY CODES FOR THIS LER ARE:

13 10 CFR 50 73(a) (2) (iv): ESF actuations ABSTRACT POMER LEVEL 002K AT 1607 ON 4-15-84 FOLLOWING A HAXNTENANCE 2 MAS AT 2X'EACTOR POWER WHEN A REACTOR TRIP OCCURRED AS A OUTAGE'NIT RESUI T OF AN INTERHEDIATE RANGE (NI-35) HIGH FLUX TRIP PLANT PARAM TERS DID NOT INDICATE A VALID HIGH FLUX TRIP -

AN ELECTRICXAN WAS CHECKING FOR CONTINUITY ACROSS THE SWITCH FOR TV-SS-201A WHEN AN ARC OCCURRED RESULTING IN A SPIKE ON VITAL BUS 1 MHICH CAUSED THE SPIKE ON NI-35 THE HULTXHETER WAS SELECTED TO RESISTANCE INSTEAD OF VOLTAGE

0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Oj OONOOOOOOON'NO@0 0 0

FORM 50 LER SCSS DATA 08-30-91

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • %**A***************************

DOCKET YEAR, LER NUMBER REVXSION DCS NUHBER NSIC EVENT DATE 281 1985 010 1 .8602140213 198478 08/13/85

• • • • • • • • • %*A***********9r********************************************

g DOCKET:281 SURRY 2 REGION: 2 TYPE:PWR NSSS:WE ARCHITECTURAL ENGINEER: SMXX FACILITY OPERATOR: VIRGINIA ELECTRIC POMER CO SYNBOL: VEP y REPORTABILXTY CODES FOR THXS 10 10 CFR 50.73(a) (2) (i):

LER ARE:

Shutdoens or technical specification violations.

ABSTRACT POWER LEVEL'99'N AUGUST 13r 1985 MXTH POWER STABLE AT 99 '% AND NO HA JOR Pl 'ANT EVOLUTIONS XN P ROGR ESSs UNIT 2 EXP ERXENC ED A TURBINE RUNBACK TO APPROXIMATELY 48% POMER ~ THIS EVENT WAS INITIATEO FROM THE LOSS OF VITAL BUS 2 Ir WHICH RESULTED IN A NUCLEAR INSTRUHENT SYSTEH (NIS) DROPPED ROD TURBINE RUNBACK XN ORDER TO RESTORE POWERr VITAL BUS 2-I MAS CROSSTIEO WITH ENERGIZED VITAL BUS 2-XII FOLLOWING THE EVENTs FEEDER BREAKER 24H11 FOR BUS 2H 1 AND THE FEEDER BREAKER TO VITAL BUS 2- I SOLA TRANSFORHER (4B) WERE FOUND TRIPPED ~ BOTH BUSES WERE EXAHXNED FOR ELECTRICAL FAIl URES AND NONE MERE FOUND ~ DURING THE UNIT 2 OUTAGE THAT FOLLOMEO THIS EVENTr BREAKERS 24H11 ANO 4B MERE REPLACED ~ IN ADDITIONr BREAKERS 24H11 AND 24H16 WERE TESTEO SATISFACTORILY AND SETTINGS MERE FOUND TO BE WITHIN SPECIFICATIONS BREAKER 4B MAS EXAHINEO AND NO PROBLEMS MERE FOUND

0 o o e e e a o e e o e e o e o o e o ~ o JE 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

FORM LER SCSS DATA 08-30-91

• • • • 4'***********dr*********************************************+4****

DOCKET YEAR LER NUMBER REVISION DCS NUMBER NSIC EVENT DATE 281 1 986 001 1 860611071 6 199705 01/02/86 DOCKET:281 SURRY 2 TYPE:PWR REGION: 2 NSSS:WE ARCHITECTURAL ENGINEER: SMXX FACILXTY OPERATOR: VIRGXNIA ELECTRXC POMER CO SYNBOL: VEP COHHENTS STEP 9: COMP XFHR RESERVE STATXON SERVICE TRANSFORHER ~

REPORTABILITY CODES FOR THIS LER ARE:

13 10 CFR 50.73(a) (2) (iv): ESF actuations ABSTRACT POWER LEVEL 100K. ON- 1-2-86. AT 1458 HOURS'OLLOMING AN AUTOVATIC TURBINE RUNBACKr NO ~ 2- EMERGENCY DIESEL- GENERATOR (NO ~ 2 EDG) STARTED AS DESIGNED. ON A LOSS OF "E" TRANSFER BUS ~ UNIT 2 EXPERIENCED A LOSS OF "E" TRANSFER BUS WHEN BREAKER 15E1 OPENED ON A PILOT MIRE DIFFERENTXAL LOCKOUT FRON "B" RESERVE STATION SERVICE TRANSFORHER THIS WAS INXTIATED DUE TO A FAILED STRESS CONE CONNECTION ON FEEDER BREAKER "252" WHICH SHORTED A CABLE TO GROUND AN INVESTIGATION HAS FOUND IHPROPER INSTALLATION AS THE CAUSE OF THE STRESS CONE FAILURE ~

0 0 0 0 0 0 0 0 O.O 0 0 0 0 0 0 0 N 0 1 I P

0 e e e e e o e o e o o o e e o e o.e e o

FORM 52 LER SCSS DATA 08-30-91

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • 4******************

DOCKET YEAR I ER NUMBER RcVISION DCS NUMBER NSIC EVENT DATE 281 1988 004 0 8805030238 209130 03/27/88

• • • • • • • • • • • • • • • • • • • • • 4**********************************************

y DOCKET:281 SURRY 2 RcGION: 2 TYPE:PMR NSSS:ME ARCHITECTURAL ENGXNEER: SMXX FACILITY OPERATOR: VIRGXNIA ELECTRIC POMER CO ~

SYHBOL: VEP CONHENTS STEP 1: COt1P NSC INDUCTOR STEP 2: MODEL 120G10000FE STEP 17: NO IDENTIFABLc CAUSE FOR LOM AUX FEED FLOW STEP 22: MODEL 3 INCH-S350W-DD

$ N/DP MATCH-LXST CODES FOR THXS LER ARE:

20 EQUXPNENT FAILURE REPORTABILITY CODES FOR THIS LLR ARE:

13 10 CFR 50.73(a) (2) (iv): ESF actuations ABSTRACT POWER LFVEL 100K ON'ARCH 27r 1 988 AT 1 621 HOURSr WITH UNIT 2 AT 1007>> REACTOR POMERr VITAL BUS (VB) (EIIS ED) 2 XII WAS DE ENERGIZED DUE TO THE LOSS OF 2-III INVERTER (EIIS-INVT) A TURBINE RUNBACK WAS AUTOMATICALLY INXTIATED DUE TO THE LOSS OF POMER TO THE POWER RANGE NUCLEAR INSTRUMENT NI-43 (EIXS-IG) WHICH IS POMERED FROM VB 2-III III ABNORMAL PROCEDURE AP 10 2r "LOSS OF VITAL BUS 1 OR 2 XIX"r WAS ENTERED ANO AS REQUIRED BY THE PROCEDUREr THE REACTOR (EIIS-RCT) AND A REACTOR COOLANT PUMP (RCP) (EIIS P)r 'MERE HANUALLY TRIPPED AT 1622 HOURS>> APPROXIHATELY 30 SECONDS LATERr A HIGH STEAN FLOW/LOW REACTOR COOLANT SYSTEN (RCS) (EIXS-AB) TAVG SAFETY INJECTION (SI) (EIIS-BQ)

OCCURRED OPERATORS FOLLOWED APPROPRIATE Pl ANT PROCEDURES AND QUICKLY STABILIZED THE UNIT FOLLOMING THE REACTOR'RIP/SAFETY INJECTION ~ AN ENGXNEERXNG EVALUATION OF THE INVERTER DETERMINED THAT AN INTERNAL INDUCTOR FAILED DUE TO AGEr THUS CAUSXNG A CURRENT SURGE WHICH BLEW THE FUSE AND TRIPPED THE AC OUTPUT BREAKER ONE OF TMO OF THE STATION VITAL BUS INVERTERS PER UNIT HAVE BEEN REPLACED MXTH AN UNINTERRUPTIBLE POMER SUPPLY ~ THE REMAINING TWO VITAL BUS XNVERTERS (2-IXI AND 1-III) WILL BE RcPl ACED WITH UNINTERRUPTXBLE POMER SUPPLIES DURING THE UPCOMING REFUELING OUTAGES

0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 a

FORM 53 LiR SCSS DATA 0 8-30-91

• • • • • • • • • • • • • • • • • • • • k***********************************************

DOCKET YEAR LER NUMBER REVISION DCS NUMBER NSXC EVENT DATE 282 1 980 009 1 8006300499 156030 03/10/80 k*k*k****kkkkk**k****kk**kkk***kkk******k*kkk**k***kkk***kk****k*k**

DOCKET:282 PRAIRIE ISLAND 1 TYPE:PMR REGION: 3 NSSS:ME ARCHITECTURAL, ENGINEER: FLPR FACILXTY OPERATOR: NORTHERN STATES POWER CO SYN BO!: NSP ABSTRACT POMER LEVEL' 100X CAUSE" SPIKE ON INSTRUNENT BUS DURING NORMAL OPERATIONr NUCLEAR POWER,RANGE CHANNEL 1N44 MAS INOPERABLE FOR A FEM MINUTES ~ INHEDIATELY AFTER LOSS OF THE CHANNELr - ITS BI STABLES 'W ERE P UT IN TRIP REDUNDANT CHANNELS MERE OPERABLE THE HIGH VOLTAGi POWER SUPPLY FOR THE DETECTOR "LATCHED UP" DUE TO A SPIKE ON THE YELLOW INSTRUHENT BUS THIS IS CHARACTERISTIC OF THESE POWER SUPPLIES

~ REHOVAL AND REINSERTION OF THE POWER SUPPLY FUSES ALLOWED THE CIRCUITRY TO RESET ~

e ~ o a e o e o e o e e e o e e e o o e N 0 a

I hL II

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FORM 54 LER SCSS DATA 08-30-91

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • 4**************************

DOCKET YEAR LER NUMBER REVISION DCS NUMBER NSIC EVENT DATE 285 1980 023 0 8010140447 160075 09/08/80 DOCKET:285 FT CAl HOUN 1 TYPE:PMR REGION: 4 NSSS CE ARCHITECTURAL ENGINEER: GIBB FACXLITY OPERATOR: OMAHA PUBLIC POWER DISTRICT SYMBOL: OPP CONHENTS STEP 5: COMP RLX SUPERVISORY REl AY ABSTRACT POWER LEVEL 100K CAUSE - CRUD ON CONTACTS DURING ROUTINE POMER OPERATIONSr THE "CPHS A1 AUTO STANDBY" ANNUNCIATOR MENT INTO ALARH AND THE AMBER/SUPERVISORY LIGHT ASSOCIATED MXTH THE 86A1/CPHS (CONTAINMENT PRESSURE HIGH SIGNAL) HAD EXTINGUISHEOr THUS SIGNIFYING THAT POWER TO THE 86A1/CPHS LOCKOUT RELAY COIL HAO BEEN XNTERRUPTEO A NORNALLY CLOSED SET OF CONTACTS (3-3T) OF THE CHANNEL "A" DERIVEO SIGNAL CUTOFF SMITCH <CS/SPA) HAD ELECTRICALLY OPENED AND INTERRUPTED=

THE POMER FEED TO THE 86A1/CPHS RELAYr ITS ASSOCXATEO SUPERVISORY LIGHT AND THE 86A1/CPHSS SUPERVISORY RELAY THE CONTACTS MERE CLEANED ANO BURNISHED ANO THE PROBLEN MAS RESOLVED

0 0 0 0 0 0 0 0 0 0 0 0 0 0 ~ 0 0 0 III 4

0 e o e e e o e e e e 'e e o o e o o e e e e

FORM 55 LER SCSS DATA 0 8-30-91 .

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • 4**************************************

DOCKET YEAR LER NUMBER REVISION OCS NUMBER NSXC EVENT DATE 293 1987 010 0 8711 3001 63 2071 95 07/02/87

• • • • • • • • • • • • • • • • • • +**********************************4'**************

y DOCKET:293 PILGRIM 1 REGXON: 1.

TYPE:BWR NSSS:GE ARCHITECTURAL ENGINEER: SECH FACILXTY OPERATOR: BOSTON EDISON CO SYMBOL: BEC COMMENTS STEP 3: CAUSE VX MAINTENANCE MATCH-LIST CODES FOR THIS LER ARE:

14 ELECTROMAGNETXC INTERFERENCE REPORTABILITY CODES FOR THIS LER ARE:

13 10 CFR 50 73(a) (2) (iv): ESF actuations.

ABSTRACT POWER LEVEL - OOOO ON JULY 2r 1987r AT 0530 HOURSr AN AUTOMATIC ACTUATION OF THE REACTOR PROTECTXON SYSTEM (RPS) OCCURRED OUE TO ERRATXC OPERATION AND SUBSEQUENT SPURXOUS TRIP OF- AVERAGE POWER RANGE MONITOR (APRM) "E" THE PLANT WAS XN A COLO CONDITION WITH THE REACTOR MODE SWITCH IN REFUEL ANO ALL FUEL ASSEMBLIES REMOVED FROM THE REACTOR VESSEL NO CONTROL RODS WERE WITHDRAWN AND THE REACTOR VESSEL HEAD WAS REMOVED THE SPURIOUS TRIP OF APRM "E" INSERTED A HALF-SCRAM SIGNAL INTO CHANNEL A" OF THE RPS THE CHANNEL'A" HAl F-SCRAM SIGNAL.'OINCIDENT WITH AN EXISTXNG CHANNEL "B HALF-SCRAM RESUI TED IN A FULL RPS REACTOR SCRAM TRIP SIGNAL ~ THE CAUSE OF THXS EVENT XS ATTRIBUTEO TO A SPURXOUS.TRXP OF APRM "E" ALTHOUGH THE CAUSE OF THE SPURIOUS TRIP COULD NOT BE ESTABLISHED WITH CERTAINTY'T IS BELIEVED TO HAVE RESULTED FROM DISTURBANCE OF THE APRM CABLING AND CONNECTORS DURING EXTENSIVE UNDERVESSEL WORK THAT WAS XN PROGRESS AT THE TXMc OF THIS EVENT>> FOLLOWING THIS EVENTr IMMEDIATE ACTION WAS TAKEN TO PLACE APRM "E" IN BYPASS AND RESET THE RPS SCRAM SXGNAL ~

TESTING OF APRM "E" DXO NOT IDENTIFY COMPONENT MALFUNCTION*OR FAXLURC~

THE UNDERVESSEL WORK HAS NOW BEEN COMiPLETED AND NO FURTHER OCCURRENCES OF SPURXOUS TRXPS OF APRM "E" HAVE BEEN OBSERVED

P k

h

FORM 56 LER SCSS DATA 08-30-91 e ********************************************************************

DOCKET YEAR LEQ NUNBER REVISXON DCS NUMBER NSIC EVENT DATE 295 1987 004 0 8703170276 203532 02/12/87

• • • • • • • • • • • • • • • • • 4**************************************************

DOCKET:295 ZION TYPE: PMR e 1 REGION: 3 NSSS:ME ARCHITECTURAL ENGINEER: SLXX FACILITY OPERATOR: COMMONWEALTH EDISON CO SYHBOL: CWE COHHENTS STEP 1: CAUSE AY - LOM NOISE PREAMPLIFIER UPGRADE REPLACEMENT ACTIVITY g MATCH-LXST CODES FOR 35 HUMAN ERROR THIS LER ARE:

i REPORTABILITY CODES FOR THI S LER ARE.

13 10 CFR 50.73(a) (2) (iv): ESF actuations.

lERS:

g REFERENCE 1 295/85-01 9 ABSTRACT POWER LEVEL .OOOX>> ON FEBRUARY 12'987 AT 1520 HOURS WHILE TROUBLESHOOTXNG SOURCE RANGE NUCLEAR INSTRUMENTATION CHANNEL 1N31s THE INSTRUMENT POWER FUSES MERE RENOVEO WITH THE lEVEl TRIP SWITCH IN THE NORHAL POSITIONr RESULTING IN A REACTOR TRIP SIGNAL~ SINCE THE REACTOR TRIP BRFAKERS MERE CLOSED AT THE TINEr A REACTOR TRIP OCCURRED ~ THE ROOT CAUSE WAS DETERMINED TO BE A COHBINATION OF ERRORS IN THAT THF INITXAL CONDXTXONS OF THE PROCEDURE XN USE MERE NOT RE VERIFIED EACH TIN THE MORK MAS RESTARTEDr THERE MAS MISCOMMUNICATION OF THE PLANT STATUS (I ~ E RX TRIP BREAKERS C1 OSED)

AND INATTENTION TO THE EXPECTED RESUlTS OF ACTIONS BEING TAKEN ~

THROUGHOUT THE EVENTS THE UNIT 'MAS IN COLO SHUTDOWN WITH ALL,. RODS FULLY INSERTED ~ THE IMPORTANCE OF THE STEPS TAKEN IN REGARDS TO TROUBLESHOOTING PLANT SYSTEMS AND RE-VERIFYING INITIAt CONDITIONS PRIOR TO RESUMING MORK WAS DISCUSSED MITH THE ENGINEER INVOLVED A PREVIOUS OCCURRENCE OF THIS EVENT IS OOCUHENTEO IN lER 295/85-019

0 e e e o o o e e a o e o o ~ o o e o o e I

I P

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4 l

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FORM 57 LER SCSS DATA 08-30-91 e ********************************************************************

DOCKET YEAR LER NUNBER REVISION DCS NUMBER NSIC EVENT DATE 295 1988 005 0 8806070261 209455 02/24/88

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • 4*****************

DOCKET:295 ZXON 1 TYPE.PMR

~ REGION: 3 NSSS ME ARCHITECTURAL ENGINEER: SLXX FACILXTY OPERATOR: COMHONMEALTH EDISON CO ~

SYNBOL: CWE COMMENTS STEP 1: FAIl EO TO REPORT SLUGGISHNESS OF VALVE 1LCV-FW-520 ~ STEP 7: ISYS SW UNKNOWN, STRUCTURAL AREA ~ STEP 9: CAUSE XX - PEl'l FAILED TO INK~ STEP 10-TYPE 2625 SNL/EPT/1 ~ REH: OPERATORS DISCOVERED SLUGGISH VALVE RESPONSE BUT DID NOT INITIATE CORRECTIVE ACTION WATCH-LIST CODES FOR THIS LER ARE 20 EQUIPMENT FAILURE REPORTABILITY CODES FOR THXS LER ARE:

13 10 CFR 50 ~ 73(a) (2) (iv): ESF actuations LERS:

y REFERENCE 1 295/85-005 2 295/88-004 ABSTRACT POMER LEVEL 049%~ AT APPROXXt'lATELY 1000 HOURS ON FEBRUARY 24'988r ZION UNIT 1 TRIPPEO FROM 49% POWER THE TECHNICAL STAFF HAD BEEN PERFORMING l OW PRESSURE STEAH POPPET TESTXNG ON 1B FEEDMATER (FW) PUHP PER TECH STAFF SPECIAL PROCEDURE (TSSP) 87-29 THE IMMEDIATE CAUSE OF THE TRIP MAS HIGH STEAN GENERATOR LEVEL CAUSED BY Sl OM RESPONSE OF THE 1C FEED REGULATING VALVE AND ITS INABXLITY TO FOLLOW THE SMING IN FM HEADER PRESSURE WHEN 18 F'W PUMP MAS TRIPPED OFF AS PART OF THE POPPET. TEST CONTRIBUTING FACTORS MERE FAILURE OF TSSP 81-29 TO ANTICIPATE THE MAGNITUDE OF THE EFFECT OF FM PUHP SPEED ON FM FLOW TO THE STEAN GENERATORSr FALSE ALARHS ON THE ANNUNCIATOR PANEl DUE TO A SHORT CIRCUITWHICH DIVERTED THE OPERATOR'S ATTENTION FROM THE RISING S/G LEVELS AND FAILURE OF THE CHART RECORDER FOR CONTROL ROOM S/G LEVEL DURING THE EVENT ~ THE REACTOR PROTECTXON SYSTEM FUNCTIONED PROPERLY IN TRIPPING THE UNITr MINIMIZING SAFETY SIGNIFICANCE ~

CORRECTIVE ACTIONS INCLUDE REPAIRS TO THE FW REGULATING VALVE AND REVISIONS TO FW PUMP POPPET TESTING PROCEDURES

0 e e a e o e e a o o a e o o o e e e o a

~W

)g 0 0 0 0 0 0 0 0 0 0 0 0 0

FORM 58 LER SCSS DATA 08-30"91

• • • • • • • • • • • • • • • • • • • • • • • • • k ************.4 *****************************

DOCKET YEAR LER NUMBER REVISION DCS NUMBER NSIC EVENT DATE 295 1989 004 1 8911080061 215790 03/08/89

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • 4********************

DOCKET:295 ZION 1 TYPE:PMR REGION: 3 NSSS.WE ARCHITECTURAL ENGINE ER: SLXX FACILITY OPERATOR: COMMONWEALTH EDISON CO S Yhi BOL: CME COMMENTS STEP 4 MODEI NO ~ 31 16 250'ART NO '/N- OK10

~ HATCH-LIST CODES FOR THIS 20 EQUIPMENT FAILURE LER ARE:

g REPORTABILITY CODES FOR THIS 10 10 CFR 50.73(a) (2) (i):

LER ARE:

Shutdowns or technical speci f ication viol ations.

REFERENCE LERS:

1 304/86-024 ABSTRACT POWER LEVEL 099K ON 3/8/89'LL UNIT 1 ROD POSITION INDICATORS DROPPED TO A READING OF APPROXXHATELY 220 STEPS IT WAS FOUND THAT A LINE VOLTAGE REGULATORr IN SERIES MITH THE POWER SOURCE FOR THE ROD POSITION XiVDICATION SYSTEN~ HAO FAILED~ ALL INDICATOR CHANNELS WERE DECLARED INOPERABLE'NO OPERATORS PREPARED TO RAHP THE UNIT DOWN AS REQUIRED BY TECH SPECS BECAUSE OF THE UNCERTAINTY OF ACTUAL ROD POSITIONr AND THE CONCERN FOR MAINTAINING ADEQUATE SHUTOOMN thARGINr THE UNIT OPERATOR WAS INSTRUCTED TO RAMP DOWN IN POWER USING ONLY CHEHICAL SHIH AT ONE POINT IN THE SHUTDOMNr DUE TO THE DIFFICULTIES INHERENT XN USING ONLY BORON TO CONTROL REACTIVITY< REACTOR POMER DROPPED BELOM TURBINE POMER ENOUGH TO CAUSE COOLANT PRESSURE TO FALL BELOW THE DNB OPERATING- LIHIT DEFINED IN PLANT TECH SPECS THE FAILED REGULATOR WAS REPLACED WITH' NEW ONEi THE OLD REGULATOR WAS RETURNED TO THE HANUFACTURER AND ANALYZED FOR THE CAUSE OF THE FAILURE THIS MAS DETERMINED TO BE A . AILED CAPACITOR AND ZENER DIODE

0 o e e e e o e e e e e e o o o o o e o e O.

0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

FORM 59 LER SCSS DATA 08-30-91

• • • • • • • • • 4*********A************************************************

DOCKET YEAR LER NUMBER REVISION DCS NUNBER NSXC EVENT DATE 301 1980 001 0 8003170421 155338 02/21/80

• • • • • • • • • • • • • • • • A*************+*************************************

DOCKET:301 POiNT BEACH 2 TYPE:PMR REGION: 3 NSSS M ARCHITECTURAL ENGINEER: BECH FACILITY OPERATOR: MISCONSIN ELECTRXC POWER CO SYMBOL: MEP COMMENTS STEP 6: EFFECT KX TURBINE RUNBACK' REFERENCE LERS 1 301/78-018 ABSTRACT POWER LEVEL" 1O0r.. CAUSE FAULTY POWER SUPPLY CAPACITOR DURING NORMAL FULL POWER OPERATION AT 1831 HOURS' HONENTARY LOSS OF THE REO INSTRUMENT BUS WAS EXPERXENCEO THIS MOMENTARY NEGATIVE SPXKE CAUSED POWER RANGE CHANNEL N41 TO FAIL LOW~ RESULTING IN A TURBXNE RUNBACK ~

FAILURE OF CHANNEL N41 RESULTEO IN A l OSS OF REDUNDANCY UNTIL THE BISTABLE WAS PLACED IN THE TRIPPED NODE AT 1842 'HE NEGATIVE POWER SPXKE MHICH BLEW THE CHANiNEL N41 FUSES WAS CAUSED BY A FAULTY CAPACXTOR XN THE 2DY01POMER SUPPLY THE CHANNEL N41 FUSES WERE REPLACED THE RED INSTRUMENT BUS SHIFTED TO THE ALTERNATE POMER SUPPLY AND ALL BXSTABLES RLTURNED TO NORMAL AT 1858 THE CAPACITOR MAS REPLACED AND THE NORMAL POWER SUPPLY RESTORED AT 1043 ON 2-22-80

i 0 0 0 0 0 0 0 0 0 0 o e e e e e e %-0 0 0 i 0 0 1 0 0 0 0 0 0 i 0 0 0

FORM 60 LER SCSS DATA 08-30-91.

• • • • • • • • • • • • • • 9r *****************************************************

DOCKET YEAR- LER NUiRBER REVXSXON DCS NUMBER NSIC EVENT DATE 301 1 985 001 0 8506270001 194989 05/16/85 DOCKET:301 POINT BEACH 2 TYPE:PWR REGION: 3 NSSS:WE ARCHITECTURAL ENGXNEER: BECH FACILITY OPERATOR: WISCONSIN ELECTRIC'OMER CO ~

SYN BOL: WEP g COMMENTS STEP 5: COHP BUS - HYDROGEN ANALYZER XN UNIT 1 POMERED FROM SAllE BUS AS UNIT 2 POWER RANGE NUCLEAR INSTRUMENT CHANNEL ~

REPORTABILITY CODES FOR THIS LER ARE:

13 10 CFR 50.73(a) (2) (iv): ESF actuations.

ABSTRACT POWER'EVEL 100%>> AT 1 406 HOURS ON ilAY 1 6r 1 985r UNIT 2 EXPERIENCED A 20X RUNBACK FROH 100X POWERS THE POWER RANGE NUCLEAR INSTRUHENTATION SENSED. A VOLTAGE SPIKE AND REACTEO BY ACTIVATING THE DROPPED ROD TURBINE RUNBACK THE VOLTAGE SPIKE OCCURRED AFTER A JUMPER WAS INADVERTENTLY GROUNDED DURING INSTRUHENT CALIBRATION ON THE INSTRUMENT BUS FEEDING THE POMER RANGE NUCLEAR INSTRUMENTATION~ ALL EQUIPMENT R ESPONDED AS DESIGNED ~

0 o e'a o o e e o o e e e o e o e o o o o 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

FORM 61 LER SCSS DATA 08-30-91

• • • • • • • A************************************************************

DOCKET YEAR LER NUMBER REVISION DCS NUMBER NSIC EVENT DATE 301 1986 003 0 8607090083 199907 06/03/86

~ ************************************************4*******************

DOCKET:301 POXNT BEACH 2 TYPE:PWR REGION: 3 .NSSS:ME ARCHXTECTURAl ENGINEER: BECH FACILITY OPERATOR: WISCONSIN ELECTRIC POWER CO SYMBOL: WEP e COMMENTS WATCH 975 TRANSXENTS INITIATED IN TWO UNITS AS THE RESULT OF A SINGLE FAILURE STEPS 25-37: COMPLETE DESCRXPTION OF UNIT 1 EVENT (WHICH XNClUOEO A SCRAM) IS DESCRIBED XN LER 266/86-003 MATCH-LIST CODES FOR THIS LER ARE:

975 POSSIBLE SIGNIFICANT EVENT REPORTABILITY CODES FOR THIS LER ARE:

13 10 CFR 50.73(a) (2) (iv): ESF actuations REFERENCE LERS:

1 266/86-003 2 301/85-003 ABSTRACT POWER LEVEL 100% ~ ON JUNE 3r 1986r UNIT 2 AT POINT BEACH NUCLEAR Pl ANT EXPERXENCED A 6 TO 8% TURBINE RUNBACK OUE TO THE LOSS OF POWER ON THE WHITE INSTRUMENT BUS THE POWER LOSS" WAS OUE TO THE TRXP OF THE WHITE INVERTER (2OY03) OUTPUT'REAKER FEEDING THE MHXTE INSTRUMENT BUS THE BREAKER TRIP MAS CAUSED WHEN THE SMING XNVERTER (DYOC) WAS INCORRECTLY RESTORED TO OPERATION ON THE OC BUS FEEDING THE WHITE INVERTERS TO BOTH UNXT 1 AND UNIT 2 (1DY03 AND 2DY03 RESPECTIVELY)

THE WHITE INSTRUMENT BUS SUPPLIES POMER TO A CHANNEl OF NUCLEAR INSTRUHENTATXON~ WHEN THE POMER WAS XNTERRUPTEDr THXS INSTRUHENTATION GENERATEO A LOAD REFERENCE AND A LOAD LXHIT TURBINE RUNBACK FROH ITS DROPPED ROD DETECTION CIRCUITRY THE WHITE BUS ALSO SUPPLIES POWER TO A FIRST-.STAGE PRESSURE XNSTRUHENT CHANNEL THAT ENABLES THE LOAD LIMIT RUNBACKr THEREFOREr WHEN POMER WAS XNTERRUPTEDr- THE lOAD LXHIT RUNBACK MAS DEFEATED DUE TO AN APPARENT MISMATCH BETWEEN LOAD REFERENCE AND ACTUAL FIRST STAGE PRESSUREr THE TURBINE CONTROL SYSTEM SHIFTED TO MANUAL AND STOPPED THE RUNBACK AT 6 TO 8% RATHER THAN THE EXPECTED 20% THE UNIT. STABILIZED AT APPROXIMATELY 94% POWER ~ THE MHITE XNVERTER FOR UNIT= 2 MAS RESTORED TO SERVICE AND THE UNIT WAS RETURNED TO 100% POWER. THE DC BUS TRANSIENT ALSO CAUSED THE OUTPUT BREAKER OF THE UNXT 1 WHITE INVERTER (LDY03) TO TRIPr RESULTING IN A RUNBACK AND REACTOR TRIP ON UNIT 1 (SEE LER 86 003 00r UNIT 1 ) ~

0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 8 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

FORN 62 LER SCSS DATA 08-30-91

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • 4**********************************

DOCKET YEAR LER NUMBER REVISION DCS NUHBER NSIC EVENT DATE 301 1986 006 0 8611120322 201874 10/02/85

• • • • • • • • • • • • • • • • • • 4*************************************************

~ DOCKET-301 POINT BEACH REGION:

2 3

TYPE:PWR NSSS:ME ARCHITECTURAL ENGINEER: SECH FACILITY OPERATOR: MXSCONSIhl ELECTRIC POWER CO S Ytl BOL: MEP CONhlENTS STEP 1 EFF IX UNKNOWN TYPE OF FAILURES STEPS 20r21 EFF IX VOLTAGE Fl UCTUATIONS ~

WATCH-LIST CODES FOR THIS LER ARE:

941, REPORT ASSOCIATED MITH 10 CFR 50 72 REPORTABILITY CODES FOR THIS LER ARE:

13 10 CFR 50.73(a) (2) (iv): ESF aetuations.

ABSTRACT POWER LEVEL OOOO ~ WITH UNIT 2 IN A REFUELING SHUTDOMN CONDITION AND REACTOR TRIP BREAKERS OPLNr REACTOR TRIP SIGNALS WERE GENERATED ON THREE OCCASIONS AS A RESULT OF WORK ACTXVITIES OR INSTRUMENT BUS VOLTAGE FLUCTUATIONS ~ - OM'CTOBER 2r 1986r A REACTOR TRIP SIGNAL MAS GENERATED WHEN A FUSE BLEW WHILE REtlOVING POWER FROhl A DC hlOTOR OPERATED VALVE THIS CAUSED AN INSTRUhlENT BUS VOLTAGE FLUCTUATION RESULTING IN A SOURCE RANGE REACTOR TRIP ~ ON OCTOBER 4r 1986r DURING A HEGGAR TEST OF A NEM APPENDIX "R" NEUTRON FLUX DETECTOR SIGNAL CABLEr A REACTOR TRIP SIGNAL, WAS G ENERATED WHEN THE hlEGGAR TEST INDUCED AN ERRONEOUS VOLTAGE ON A NEARBY SIGNAL CABLE RESULTING IN A SOURCE RANGE REACTOR TRXP SIGNAL BEING GENERATED ~ OCTOBER 8r 1986 A VOLTAGE FLUCTUATION ON THE INSTRUMENT BUS CAUS D THE P7 LOGIC CIRCUITRY TO .UNBLOCK RESULTXNG IN THE GENERATION OF A REACTOR TRIP SXGNAL ~ IN EACH OF THESE EVENTSr THE CAUSE WAS ATTRIBUTED TO EITHER AN OUTAGE RELATED MORK ACTIVITY OR ERRATIC OPERATION OF AN XNSTRUHENT BUS INVERTER (WHICH WAS SUBSEQUENTLY REPAIRED) ~ PROCEDURES HAVE BEEN CHANGED AND DISCUSSIONS MXLL BE HELD WITH OPERATIONS PERSONNELr DUTY AND CALL SUPERINTENDENTSr AND DTA S TO EHPHASIZE THE CORRECT INTERPRETATION OF REPORTING REQUIREHENTS AND THE IhlPORTANCE OF ANTICIPATXNG ACTUATION SIGNALS CAUSED BY WORK ACTIVITIES DURING Ahl OUTAGE

0 0 0 0 0 0 O*O 0 0 0 0 0 0 0 0 0 0 0 0 0 l'

e o o e e e e o e e e o e e o e o e e e e

FORN 63 LER SCSS DATA 08"30-91,

• • • • • • • • • • • • • • • • • • • • • • • • • A******************************************

DOCKET YEAR LER NUMBER REVISXON DCS NUHBER NSIC "VENT DATE 301 1988 001 0 8805240310 211631 04/07/88

~ ***********************************************+********************

DOCKET:301 POiNT BEACH 2 TYPE:PWR REGION:" 3 NSSS-WE ARCHITECTURAL ENGINEER: BECH FACILXTY OPERATOR: WISCONSIN ELECTRIC POWER CO SYYiBOL: WEP COMMENTS STEP 4: PART NO HEK-3DT1 STEP 6: EFF IX VOLTAGE OSCILLATIONS MATCH LIST CODES FOR THIS LER ARE 33 CONSTRUCTION ERROR OR INADEQUACY 35 HUMAN ERROR 40 PROCEDURAL DEFICIENCY REPORTABILITY CODES FOR THIS LER ARE:

13 10 CFR 50.73(a) (2) (iv): ESF actuations.

REFERENCE LERS:

1 266/85-006 2 266/86-005 3 266/87-004 ABSTRACT POWER LEVEL 100X ~ AT 0904 HOURS ON 4/7/88r A REACTOR TRXP OCCURRED FROM 100% POWERS THF TRXP MAS CAUSED BY A LOW PRESSURIZER PRESSURE SIGNAl SAFETY INJECTION ALSO INITIATED DUE TO A LOM PRESSURIZER PRESSURE SIGNAL ~ THESE AND OTHER ANOMALIES WERE CAUSED BY RED INSTRUMENT BUS VOLTAGE FLUCTUATIONS RESULTING FROH THE PRXHARY AND ALTERNATE INVERTERS FEEDING THE RED INSTRUMENT BUS WITH THE INVERTERS CONNECTED IN PARALLEL~ THE INVERTER PARALLEL OPERATION OCCURRED DU

<<TO THE FAILURE OF THE HECHANICAL INTERLOCKr WHICH IS DESIGNED TO PREVENT THE SIMULTANEOUS CONNECTION OF THE INVERTERS TO THE LOAD DURING THE RECOVERYr WITH PRIMARY PRESSURE NEAR THE SAFETY INJECTION SET POINT AND SAF TY INJECTION RESETr SAFETY INJECTION OCCURRED A SECOND TINE DUE TO COOLING OF THE PRIMARY COOLANT SYSTEH WHEN STEAN MAS RESTORED TO THE TURBXNE HALL~ ALL SYSTEMS OPERATED AS EXPECTED DURING THE TRANSIENT MITH THE EXCEPTION OF ONE OF THE TMO SOURCE RANGE NUCLEAR INSTRUMENTATION CHANNELS THIS CHANNEL FAILED TO ENERGIZE AFTER THE TRIP THIS CHANNEL REHAXNS OUT OF SERVICE AND WAS PLACED XN THE TRIP BLOCKED CONDITION AS ALLOWED BY POINT BEACH TECH SPECS IMMEDIATE CORRECTIVE ACTION INCLUDED THE POSTING OF AN OPERATOR AID AT THE LOCATION OF THE INSTRUHENT BUS BREAKER CABINETS~ MHICH PROVIDES INSTRUCTIONS TO REDUCE THE PROBABILITY OF THIS TYPE OF OCCURRENCE IN THE FUTURE

0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 f

0 o o o e e e o e e e e e e e o e e e e o

FOR H 64 LER SCSS DATA 08-30-91

• • • • • • • • • • • A********************************************************

DOCKET YEAR LER NUMBER REVISION DCS NUf'1BER NSIC EVENT DATE 301 1989 008 0 8912130112 216072 11/03/89 DOCKET: 301 POINT B EACH 2 TYPE:PMR REGION: 3 NSSS:ME ARCHITECTURAL ENGINEER: BECH FACILITY OPERATOR". MXSCONSIN ELECTRIC POWER CO ~

SYNBOL: 'MiP

~ COl1NENTS STEP 1: CAUSE SO thISLABELED POWER SUPPLY LEADS STEP 8 COMP HEI COMPUTER VIDEO NONITORS.

WATCH-LIST CODES FOR THIS LER ARE:

35 HUMAN'RROR REPORTABILITY CODES FOR THIS LER ARE:

13 10 CFR 50 73(a) (2) (iv): ESF actuations.

REFERENCE LERS:

1 266/87-004 2 301/89-002 3 301/89-006 ABSTRACT POWER LEVEL 000X ON NOVEMBER 3r 1 989r DURING RE FUELING OPERATIONSr CONTRACT~OR PERSONNEL GENERATED A FALSE TRIP SiGNAL WHILE INVESTIGATING A MIRING DISCREPANCY IN THE REACTOR PROTECTION SYSTEM INSTRUMENT RACKS THE REACTOR MAS DEFUELEO AND THE REACTOR TRIP BREAKERS WERE OPEN ~ THEREFOREr NO SAFETY RELATiD EQUIPHENT STARTED ~

AN ORIGINAL MIRE LABELXNG ERROR MAS CONSIDERED THE ROOT CAUSE OF THE EVENT ~ FURTHER ANALYSIS INOICATEO TMO REDUNDANT CHANNEl S OF BORIC ACID STORAGE TANK T-6C LEVEL INSTRUMENTATION (2 OF 3 LOGIC) HAD COMMON INSTRUMENT BUS POMER SUPPLIES ~ CORRECTIVE ACTION XNCI UOEO CHANGXNG THE BORIC ACXO STORAGE TANK LEViL XNSTRUtlENT POWER SUPPLY AND RELABELING OF THE CABLE CONDUCTORS THIS EVENT IS REPORTABLE PURSUANT TO 10 CFR 50 73(A) (2) (XV) ~

0 o e e e e a a a e o e e o e e e o o o ~ ol 0 O ~ l 4

~ c 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

FORM 65 LER SCSS DATA 08-3 0-91 e ********************************************************************

DOCKET YEAR LER NUHBER REVISION DCS NUMBER NSXC EVENT DATE 302 1985 - 023 0 8512050381 197969 10/26/85

• 4'******************************************************************

DOCKET: 302 CRYSTAL RIVER 3 TYPE:PMR REGION: 2 NSSS:BM ARCHITECTURAL ENGINEER: GLBT FACILiTY OPERATOR: Fl ORIDA POWER CORPORATION SYHBOL: FPC CONNENTS SIX PREVIOUS INSTANCES WHERE LOSS OF A VXTAL BAR OCCURRED: DURING NODE 1 OPERATION RFPORTABILXTY CODES FOR THIS LER ARE:

13 10 CFR 50.73(a) (2) (iv): ESF actuations.

REFERENCE LERS:

1 302/85-020 ABSTRACT POWER LEVEL 095/ ON OCTOBER 26r 1985r AT 1404r A TURBINE/REACTOR TRIP OCCURRED FOLLOWING A 120 VAC VITAL XNVERTER FAILURE THE INVERTER FAIl URE CAUSED SEVERAL ALARMS AS MEl L AS LOSS OF RPS POWERED INSTRUMENT INDICATIONS~ INSTRUNENT FAXLURES CAUSE A HAIN FEED PUMP TO TRXP AND AN AUTOHATIC RUNBACK NUHEROUS ALARHS SOUNDED AND SMOKE MAS OBSERVED IN THE CONTROL ROON'URING THE RUNBACK'NE OF THE OPERATORS OBSERVED THE CONTROL ROO DRIVE POSITION XNDICATORS SHOMXNG ALL RODS "FULLY INSERTED" THIS AND OTHER ERRONEOUS INFORMATION INDICATED THAT THE REACTOR HAD TRIPPED ANO Hf ANNOUNCED XT. A SECOND CONTROL BOARD OPERATORr NOTICING THAT THE TURBINE CONTROL VALVES MERE NOT CLOSED'ANUALLY TRXPPEO THE HAIN TURBINE ~ THIS RESULTED IN AN ACTUAL ANTICIPATORY REACTOR TRIP APPROXIMATELY 14 HINUTES AFTER THE REACTOR TRXPs THE "A" XNVERTER FAILEO TO ZERO VOLTAGE AND VITAL BUS DISTRIBUTION 'PANEL VBDP-3 SWITCHED TO THE ALTERNATE POWER SOURCE ~ THE INVERTER HAO BEEN IN- AN UNOERVOLTAGE CONDITION PRXOR TO FAILURE AND CAUSED ERRONEOUS INDICATIONS ON THE MAIN CONTROl BOARD WHICH LED THE CONTROL BOARD OPERATOR TO TRIP THE HAIN TURBINES THOUGH TAKEN PREMATURELY THE ACTIONS TAKEN BY THE OPERATORS WERE CONSERVATIVE FOR THE INDICATIONS WHICH THEY SAM AND THE CONDITIONS WHICH MERE ANNOUNCED INVESTIGATIVE MAINTENANCE OETERNINEO THAT A DEFECTIVE OSCXLLATOR BOARD CAUSED THE LOM VOLTAGF FAILURE AND IT WAS REPLACED'

0 e a 0 a o e a e e o e o a e e o e a 0 P I

~ '

I Il 0 a o e e e e e e 0 a a e e o a a e o a

FOR H 66 LER SCSS DATA 0 8-30-91

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • 0************************

DOCKET YEAR LER NUMBER REVISION DCS NUMBER NSIC EVENT DATE 302 1987 025 0 8712240085 207506 10/16/87 e DOCKET:302 CRYSTAL RIVER 3 REGION: 2 TYPC:PWR NSSS:BM ARCHITECTURAI ENGXNEER: GLBT FACILITY OPERATOR: FLORIDA POWER CORPORATION SYHBOL: FPC

~ CONMENTS STEP 7: CAUSE AX TO PERHIT TESTING OF BATTERIES STEP 20: COMP XR EVENTS RECORDER.

WATCH-LIST CODES FOR THIS LER ARE:

31 ACCIDENTAL ACTION 943 ALERT REPORTABIl ITY CODES FOR THIS LER ARE:

13 10 CFR 50.73(a) (2) (iv): ESF actuations REFERENCE LERS:

1 302/87-021 ABSTRACT POWER LEVEL 000% ~ ON OCTOBER 16'987r CRYSTAL RIVER UNIT 3 MAS SHUT OOMN IN A REFUELING OUTAGE+ AT 2119~ PERSONNEL MORKING IN THE VICXNXTY OF THE UNIT STARTUP TRANSFORMER RAISEO A NETAL POLE AND MADE ELECTRXCAL CONTACT WITH A 230 KV FEEDER INTERRUPTING THE PLANT OFFSITE POWER SUPPLY THE FOLLOMXNG SIGNIFICANT EVENTS RESULTED: THE ENGINEEREO SAF EGUARDS SYSTEN ACTUATEOr THE "8" DIESEL GENERATOR STARTED: AND LOADED/ NORHAL POWER WAS'LOST TO THE SECURITY SYSTENSr ANO THE REACTOR BUILDXNG PURGE ISOLATED ~ ADDITXONALLYr POWER TO THc FOLLOWING MAS LOST. ONE NEUTRON NONXTORXNG CHANNELs THE AUXILIARY-BUXLDING VENTILATION SYSTEN EXHAUST FANSr THE CONTROL BOARD ANNUNCIATOR AND EVENT RECORDERs AND THE EHERGENCY NOTIFICATION SYSTEH PHONE THIS EVENT MAS CAUSED BY ACCIDENTAL GROUNDING OF THE UNIT STARTUP TRANSFORMER 230 KV FEEDER RESULTING IN INTERRUPTION OF THE OFFSITE POWER SUPPLY ELECTRICAl DISTRIBUTION SYSTEM LINEUPS MERE RESTORED TO THEIR PRE-EVENT STATUS ANO THE DAHAGED 230 KV FEEDER MAS REPAIRED MORK ACTIVITIES IN THE VICINXTY OF THE UNIT STARTUP TRANS FORMER HA VE B EEN DISCONTINUED ~

0 e 0 e a a 0- 0 a a a 0 0 0 0 a a 0 0 0 0 ~ 0 0 0 0 0 0 t 0 0 0 0 0 0

FORM 67 LER SCSS DATA 08-30-91

• • • • • • • • • • • • • • • • • • • • • • A'*********************************************

DOCKET YEAR LER NUMBER REVISION DCS NUMBER NSIC EVENT DATE 304 1985 001 0 8602060332 198307 01/03/86

• • • • • • • • • • • • • • • • • • • • • • • • • 0******************************************

DOCKET:304 ZION 2 TYPE:PWR REGION: 3 NSSS:WE ARCHITECTURAL ENGINEER: SLXX FACILITY OPERATOR: COMMONWEALTH EDISON CO SYMBOL: CWE

'OMMENTS OTHER REPORTABIl ITY- TECH SPEC 6 6~3 H STEP 1: EFF XX- POWER FLUCTATION REPORTABILXTY CODES FOR THIS LER ARE:

21 OTHER."Voluntary repor tr special reports Part 21 reports etc.

ABSTRACT POWER LEVEL 000'T 1547 ON 1- 3 86 UNIT 2 WAS SHUT DOWN FOR A REFUELING OUTAGE AND THE RCS WAS FILLED SOLID WITH NO BUBBLE IN THE PRESSURIZER' MOMENTARY FLUCTUATION OF OUTPUT OF INVERTER POWER SUPPLY BUS 213 (CAUSE UNKNOWN) CAUSED THE CHARGING Fl OW CONTROL VALVEr 2VC-FCV121 TO FAIL TO THE 20X DEMAND POSITION AND ALSO CAUSED 2MOV-RH8701 THE RHR PUMP SUCTION ISOLATION VALVE TO FAIL CLOSED ~ THIS XNCREASED CHARGING FLOW FROM 39 TO 190 GPMr AND ISOLATED LETDOWN Fl OW RESUl TING XN LIFTING OF THE PRESSURIZER POWER OPERATED RELXEF VALVES (PORV S) ~ WHILE INVESTIGATING THE CAUSEr BUS 213 WAS AGAXN AND THE PORV S AGAIN LXFTED THE CAUSE OF THE BUS OUTPUT 'EENERGIZED FLUCTUATXON IS CURRENTLY UNKNOWN THIS EVENT IS REPORTABLE SINCE TECH SPEC 6 ~ 6 3~H REQUIRES A 30 DAY WRITTEN REPORT ON ACTUATION OF THE OVERPRESSURE PROTECTION. SYSTEM

0 o e e e o e e e o e e e e e o e e e o N 0 o o e a e e o e e o a o o e o e o e e o

FORM 68 LER SCSS DATA 08-30-91 e ******4*************************************************************

DOCKET YEAR LER NUHBER REVISION DCS NUMBER NSIC EVENT DATE 304 1986 007 0 8602270366 198544 01/23/86 DDCKET:304 ZION 2 TYPE-PMR g REGION: NSSS:ME' ARCHITECTURAL ENGINEER: SLXX FACILITY OPERATOR: COMMONWEALTH EDISON CO SYHBOL: CME COMMENTS STEP 2 SMITCHXNG POWER SOURCES MHILE SCRAH BREAKERS CLOSEDr STEPS 3&4:

CAUSE IX - NOHENTARY INTERRUPTION IN AeC ~ POMER REPORTABILITY CODES FOR THIS LER ARE:

13 10 CFR 50.73(a) (2) (iv): ESF actuations.

REFERENCE LERS:

1 295/85-021 ABSTRACT POWER LEVEL 000/ ON JANUARY 23r 1986r AT 0830r THE UNIT WAS IN HOT SHUTDOWN AND THE REACTOR TRIP BREAKERS WERE CLOSED FOR CONTROL ROD TESTING ~ INSTRUHENT INVERTER 211r WHICH SUPPLIES REGULATED A ~ C ~ POWER TO NUCLEAR INSTRUMENTATION SYSTEH (NIS) CHANNELS N31 AND N35r MAS OUT OF SERVICE AND THOSE CHANNEI S MERE SUPPLIED MITH NONREGULATED POWER CONTROL ROON PERSONNEL WERE PREPARING TO SMITCH BACK FROM NONREGULATED POMER TO THE XNVERTER ~ THE PROCEDURE MARNED THAT THIS MOULD CAUSE A HOHENTARY INTERRUPTION IN POWER TO THE NIS CHANNELSr CAUSING A REACTOR TRiP SIGNAL AFTER SENDING AN EQUIPHENT OPERATOR TO SMITCH POMER SUPPLIESr THE SHIFT SUPERVISOR DECIDED TO HAVE THE TRIP BREAKERS OP NED MANUALLY~ BEFORE HE COULD DO THISr THE POWER SUPPLY MAS SWITCHED AND THE AUTOMATIC TRIP OCCURRED ~ TO PREVENT RECURRENCEr ALL LICENSED SHIFT SUPERVISORS WILL BE TRAINED AND A STANDXNG ORDER Wil L CLARIF Y THE PROPER ACTION TO TAKE WHEN AUTOMATIC ACTUATION OF AN ENGINEERED SAFETY FEATURE OR THE REACTOR PROTECTION SYSTEH IS EXPECTED

0 0 0 0 0 0 0 0 0 N 0 0 0 0 0 0 0 0 tl 4 p 0 0 0 0 0 0 0 0 0 0 0 0 0

FORM 69 LER SCSS DATA 08-30 "91

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • 4********

DOCKET YEAR I ER NUHBER REVXSIOll DCS NUMBER NSXC ~ EVENT DATE 305 1983 035 0 8401160278 188403 12/10/83

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • A********************

DOCKET:305 KEMAUNEE TYPE". PMR REGION: 3 NSSS:ME ARCHITECTURAL ENGINEER: FLPR FACILITY OPERATOR: WISCONSIN PUBLIC SERVICE CORP ~

SYMBOL: MPS CONMENTS STEPS 1. AND 2: EFFECT CODE XX = HIGH RESISTANCE CAUSING LOW 'UTPUT VOLTAGE g ABSTRACT WITH THE REACTOR AT 100'OWER OPERATION ALL RODS OUT ANO IN NANUAL THE OPERATORS NOTICED THAT ALL ROD POSITION INDICATORS (RPI) MERE GRADUALLY DRIFTING DOWNWARDS THE COHHON DRIFTING OF ALL RPI WAS DUE TO A VOLTAGE REGULTOR FAILUREr THUS THE RPI SYSTEM MAS AT NO TIHE DECLARED INOPERABLE>> BASED ON EXCORE INDICATIONSr WHICH REMAINED NORNAL THE ENTIRE TIHEr AND NO CHANGE IN 'ANK DEHAND POSITIONr THERE WAS NO ROO iNIS ALIGNUGENT 8 ECAUSF. OF- THE POTENTIAL SAFETY SIGNIFICANCE INVOLVED WE FEEL<<THIS INCIDENT IS WORTHY OF A 30 OAY REPORT DRIFTING RPI WAS BECAUSE THE CONTACT POINT IN THE VOLTAGE REGULATOR WAS TARNISHED DUE TO AGE AND WEAR CAUSING A LOWER OUTPUT VOLTAGE THE VOLTAGE ADJUST POT 'WAS WIPED THROUGH THE BAD'POTr THE VOLTAGE READJUSTEDr AND ALL RPI RETURNED TO NORMAL'ONG TERH ACTIONS INCLUDE ADDING THE OUTPUT VOLTAGE READINGS TO THE ANNUAL SURVEILLANCE TEST ANO REPLACING THE POMER SUPPLY ONCE A NEM ONE CAN BE PURCHASED NO

'URTHER ACTION IS REQUIRED AT THIS TINE ~

e e a ~ e e e e o.e e e e e e e o e e N 0 FORhl 70 LER SCSS DATA 08-30-9'l DOCKET YEAR LER NUhlBER RiVISION DCS NUt<BER NSXC EVENT DATE 306 1990 009 0 9011130187 220038 10/07/90

• • • • • • • • • • A**********************************************A**********

DOCKET:306 PRAIRIE ISLAND 2 TYPE:PMR e REGION: 3 NSSS:ME ARCHITECTURAL ENGINEER: FLPR FACILiTY OPERATOR: NORTHERN STATES POWER CO SYflBOL: NSP y MATCH-LIST CODES FOR 35 HUhlAN ERROR THIS LER ARE:

O REPORTABILITY CODES FOR THXS LER ARE:

13 10 CFR 50.73(a) (2) (iv): ESF actuations.

ABSTRACT POWER LEVEL 000X ~ ON OCTOBER 7r 1990 UNIT 2 WAS CRITICAL AT ZERO POWER AFTER REFUELING ~ ZERO POWER PHYSICS TESTING HAO JUST BEEN COhlPLETED THE PEACTIVITY CONPUTER USED FOR PHYSICS TESTING WAS TO BE DISCONNECTED FROH NUCLEAR XNSTRUYiENTATXON (NIS) POWER RANGE CHANNEL N41 ~ AN INSTRUhl ENT AND CONTROL TECHNICIANr WHEN ASKED TO DO THE MORKr REVIEMED THE PROCEDURE ANO THE LOGIC DIAGRAMS TO DETERt'lINE WHAT HXS ACTIONS SHOULD BE ~ WXTH PROCEDURE XN HANDr HE PROCEEDED TO REhlOVE THE CONTROL POWER AND INSTRUhlENT POWER FUSES FROM THE FRONT PANEL OF THE NXS DRAWERr CAUSING A UNIT 2 REACTOR TRIP AT 1712 BECAUSE HE HAD INADVERTENTLY REHOVED THE FUSES FROhl NIS INT RHEOXATE RANGE CHANNEL N35 INSTEAD OF POMER RANGE CHANNEL N41 THE TRiP AND RECOV RY FROhl THE TRIP MERE UNEVENTFUL CAUSE OF THE EVENT WAS PERSONNEL ERROR IN REHOVING FUSES FRON THE WRONG NXS CHANNEL DRAWER CHANNEL N35 IS IMMEDIATELY ABOVE CHANNEL N41 ON THE NIS RACK THE TECHNXCIAN FAXLEO TO USE SELF-CHECKING WHiN REMOVING THE FUSES ~

0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 N )

4 0 0 0 0 0 0 0 0 0 0 ~ 0 0 0 0 0 0 0

FOR H 71 LER SCSS DATA 08-30-91 DOCKET YEAR LER NUMBER REVISION DCS NUMBER NSXC EVENT DATE 311 1982 145 1 8301250373 181466 11/29/82

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • 4******************

DOCKET:311 SAI EM 2 TYPE:PMR REGION: 1 NSSS:ME ARCHITECTURAL ENGINEER: PSEG FACXLITY OPERATOR: PUBLIC SERVICE ELECTRIC tt GAS CO ~

SYHBOL: PEG ABSTRACT ON NOVEHBER 29r 1982r FOLLOWING A SHIFT OF NO ~ 28 VITAL BUS POWER SOURCE IN PREPARATION FOR PLANNED tlAINTENANCE ON NO ~ 1 STATION POWER TRANSFORt1ERi THE CONTROL ROON OPERATOR OBSERVED THAT THE P-250 COMPUTER HAD SHUT DOMN SINCE IT UTILIZES THE COMPUTER DATA AND tlEtlORYr THE REACTOR COOLANT SYSTEM (RCS) SUBCOOLING ."lONITOR WAS RENDERED INOPERABLE'ND ACTXON STATEMENT 3 ~ 3 3 ~ 7A MAS ENTERED ~

REDUNDANT MXDE RANGE RCS PRESSURE AND TEHPERATURE XNDXCATION AND STEAN TABLES WERE AVAILABLE'NO THE EVENT CONSTITUTED OPERATION IN A DEGRADED NODE XN ACCORDANCE WITH TECH SPEC 6 ~ 9 1 9 B INVESTIGATION REVEAlEO THAT THE COMPUTER HAD SHUT DOWN DUE TO FAILURE OF THE INVERTER POMER SUPPLY'HE POMER SUPPLY PROBLEtl RESULTED FROH A FAILED OSCIL! ATOR CIRCUIT BOARD THE BOARD MAS REPLACEDr THE COHPUTER WAS RESTORED TO OPERATION ANO THE ACTXON STATEMENT WAS TERMINATED~

0 e e e e o o e o e e e e o e e e o e o 0 t

I 4 U I ~0 0 o e o o e o e o e o e e o e e o e e e o 0

FORN 72 LER SCSS DATA 08-30"91

• • • • • • • • • • • • • • • • • • • • • • • • • • 4'*******************4'*********************

DOCKET YEAR LER NUMBER REVISION DCS NUMBER iNSIC EVENT DATE 311 1983 019 0 8306030188 182916 04/30/83 e DOCKET:311 SALEH 2 REGION. 1, TYPE:PWR NSSS:ME ARCHITECTURAL ENGXNEER: PSEG FACXLITY OPERATOR: PUBLXC SERVICE ELECTRIC 5 GAS CO ~

SYNBOL: PEG g COMMENTS STEP 1: CAUSE AX FOR CALIBRATION

~ ABSTRACT ON APRXL 30r 1983r DURING ROUTINE SHUTDOMN OPERATIONS'HE NO ~ 2D VITAL INSTRUMENT BUS WAS DE-ENERGIZED AND TAGGED OUT FOR MAINTENANCE DE-ENERGIZATION OF THE BUS RESULTED IN A LOSS OF THE NO N-44 POMER RANGE CHANNELS THE NO N-42 CHANNEL MAS ALREADY DE-ENERGIZED FOR A CHANNEL CALIBRATION LOSS OF TWO POWER-RANGE CHANNELS IN TURN DE-ENERGIZED THE SOURCE RANGE CHANNELS (DUE TO PERMISSIVE P 10)

~ SHUTDOWN MARGIN MAS IHMEDXATELY PERFORNENO AND WAS SATISFACTORY A

THE EVENT CONSTITUTEO OPERATION XN A DEGRADED NODE IN ACCORDANCE WITH TECH SPEC 6 9 1 98 ~ INVESTIGATiON REVEALEO THAT XN ACCORDANCE -WITH ACCEPTED PRACTICE IT MAS POSSIBLE FOR A SENXOR SHIFT SUPERVISOR TO SE UNAWARE OF THE DE-ENERGXZATXON OF A- NUCLEAR INSTRUMENT SYSTEM (NXS)-

CHANNEL FOR CALIBRATION A NEW METHOD OF TRACKING NIS STATUS MAS INITIATED ANO OPERATING SHIFTS MERE INFORHED OF THE INCIDENT~

~ ~

FORM 73 LER SCSS DATA 08-30-91

• • • • • • • • • • • A******************A****A********************************

DOCKET YEAR 'ER NUMBER 'EVISION DCS NUMBER NSIC EVENT DATE 311 1983 022 0 8306170362 183365 05/30/83

• • • • • • • • • • • • • • • • • A**********%***************************************

DOCKET:311 SAI EH 2 TYPE:PMR REGION: 1 NSSS:WE ARCHITECTURAL ENGINEER: PSEG FACILITY OPERATOR: PUBLIC SERVICE ELECTRIC 8 GAS CO ~

SYNBOL: PEG COMMENTS STEP 2: IX- INVERTER CHATTERINGr STEP 4: XA UNKNOWN ALARM TYPES STEP 7:

HEI- SPRXNKLERS ANO FIRE HOSE STATIONS REFERENCE LERS:

1 311/83-021 ABSTRACT ON NAY 30r 1983r DURING ROUTINE SHUTDOWN OPERATIONr THE NO~ 2C VITAL

~

INSTRUNENT INVERTER FAILEDr RENDERING THE ASSOCIATED ELECTRICAL BUS TRAIN INOPERABLE SINCE NO 2A DIESEL GENERATOR WAS ALSO INOPERABLE AT THE TIHEr ACTION STATEHENT 3 ~ 8 ~ 2 2 MAS ENTEREO ~ CONTAINMENT INTEGRITY WAS ESTABLISHED WITHIN 8 HOURS AS REQUIRED BY THE ACTION STATEHENT OUE TO OPERATION LESS CONSERVATIVE THAN THE LEAST CONSERVATIVE ASPECT OF A LIMITING CONDITION FOR OPE RATIONr THE EVENT IS REPORTABLE IN ACCORDANCE WITH TiCH SPiC 6 9 ~ 1 ~ 88 ~ THE FACT THAT ONE SURVEILLANCE TEST NECESSARY TO ESTABLISH CONTAXNHENT INTEGRITY MAS EXPIREO MAS OVERLOOKED UNTIL INSUFFICIENT TXHE REMAINEO TO COMPLETE THE TEST~ A REVIEM OF APPLICABLE PROCiDURES AND TECH SPECS MILL BE PERFORHED TO IDENTIFY IHPROVENENTS WHICH MXLL PREVENT RECURRENCE ~ THE INVERTER MAS ~

REPAIRED ANO THE ACTION STATEMENT WAS TERMINATED~-

e o e e e o o e e o e e e o o e e o e e N FORM 74 LER SCSS DATA 08-30-91

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • +***************

DOCKET YEAR LER NUMBER REVISION DCS NUMBER NSXC EVENT DATE 311. 1984 006 0 8404240215 189305 03/18/84

• • • • • • • • • • • • • • • • • • • • • +**********************************************

g DOCKET:311 SALEM 2 REGION:

TYPE:PWR NSSS:WE ARCHITECTURAL ENGINEER PSEG FACIl ITY OPERATOR: PUBLIC SERVXCE ELECTRIC 8 GAS CO S Y<~1 BOL: PEG COMMENTS OTHER REPORTABXLITY - SURVEILLANCE REQUIREMENT CODES FOR THIS y REPORTABXLITY 10 10 CFR 50 73(a) (2) (i):

LER ARE.

Shutdo<<<ns or technical specif ication violations.

21 OTHER: Voluntary reports special etc r epor ti Part 21. r eportr

~ ABSTRACT POWER LEVEL 100% ~ AT 0213 HRSi MAR 18r 1984r DURING ROUTINE SURVEILLANCE TESTING~ A LOSS OF 2B 4KV VITAL BUS OCCURRED WHILE PARALLELING 28 EMERGENCY DG WITH THE GRID THE BUS DIFFERENTIAL PROTECTION RELAY ACTUATED MHXCH IN TURNr ACTUATED THE MULTI-TRIP RELAY AND TRIPPED 2B EMERGENCY DG BREAKER AND THE 4KV VITAL BUS INFEED BREAKER ~ THE PLANT WAS VERIFIEO TO BE IN STABLE CONDITION. ALTHOUGH

~ THE INDXVIDUAL ROD POSITION XNDICATION FAILED AT IEROr AND THE ROD BOTTOM LIGHTS ILLUHINATEDr REACTOR POWER LEVEL REMAINED STEADY AT 100% THE Pl ANT MAS MAINTAINED STABLE WHILE THE IRPI AND ROD-BOTTOM INDICATXON WERE RESTORED ~ AT 0610 HRSr A UNIT SHUTDOWN MAS COHHENCED PER TECH SPECS'UE TO THE INOPERABILITY'F 3 CONTAINMENT- ISOLATION VALVES THE EVENT MAS ATTRIBUTED TO PARALLELXNG THE GENERATOR OUT OF PHASE TESTING VERIFIED THAT THE BUSr BREAKERSr RELAYS AND ALL EQUIPHENT WERE UNAFFECTED BY THE TRANSIENT THE BUS WAS REENERGIZED AT 1123 HRS THE CONTAINNENT XSOLATXON VALVES MERE RESTORED TO AN OPERABLE STRTUSr AND THE REACTOR SHUTDOWN WAS TERMINATED~ THIS REPORT IS SUBMITTED XN ACCORDANCE WITH 1 0 CFR 50 ~ 73 (A) (2) (I) AND SURVEILLANCE REQUIREHENT 4 8.1 ~ 1 4 ~

~

0 o ~ e e o e e o e o e o o ~ a o o o e e 0 k

I

, N f

'P I

/

4 0 0 0 0 0 0 0 0 0 0 0 0 0

FORM 75 LER SCSS DATA 08-30-91.

DOCKET YEAR LER NUMBER REVISXON DCS NUMBER NSXC EVENT DATE 311 1 990 .043 0 9101280159 220723 12/20/90

• • • • • • • • • • • • • • • • • • • • • • • • • • 4*****************************************

y DOCKET:311 SALEM 2 REGION: 1 TYPE:PWR NSSS:WE ARCHITECTURAL ENGINEER: PSEG FACILITY OPERATOR: PUBLIC SERVICE ELECTRIC 8 GAS CO SYMBOL: PEG

~ WATCH-LIST CODES FOR THIS 20 EQUIPMENT FAILURE LER ARE:

941 REPORT ASSOCIATEO WXTH 10 CFR 50 72 REPORTABXLITY CODES FOR THIS LER ARE:

10 10 CFR 50.73(a) (2) (i): Shutdowns or technical specification violations.

ABSTRACT POWER LEVEL 100X ON 12/20/90 AT 0154 HOURSr DURING FULL POWER OPERATXONr ALL CONTROL ROOM ANALOG ROD POSITION INDICATOR (ARPX)

INDICATION WAS LOST SUBSEQUENTLY TECH ~ SPEC 3 ~ 1 ~ 3 2 1. WAS REVIEWED THE ACTION STATEMENTS DO NOT ADDRESS INOPERABILITY OF MORc THAN ONE ARPIJ THEREFORE'ECH SPEC ACTION STATEMENT 3 0 ~ 3 WAS ENTERED'EVERAL OVERHEAD ALARMS WERE RECEIVED XN THE CONTROL ROOM WHEN THIS EVENT OCCURRED ~ THE ROOT CAUSE OF THIS EVENT IS EQUIPMENT FAILURE~ A CHART RECORDER'S RIBBON CABLE INSULATION WORE THROUGH TO XTS WIREr SUBSEQUENTLY SHORTING THE EXPOSED WIRE TO GROUND ~ THIS RESULTED IN THE OPENING OF THE BREAKER (NO CB-1 A 2 AMP BREAKER)

WHICH REMOVED POWER TO THE ARPI INDICATORS AT THE TIME OF THE EVENTr A MAINTENANCE-ILC TECHNXCIAN WAS INSERTING THE CHART RECORDER (LOCATED ON'HE CONTROL ROOM CONSOLE) INTO XTS CHASSIS THE CUT CABLE SUPPl IES POWER FROM THE NO 21 MISCELLANEOUS AC (MAC) 115 VAC DISTRIBUTION CABINET NO 34 BREAKER (15 AMPS) TO THE RECORDER WHEN THE SHORT OCCURREOr THE'O 34 BREAKER DID NOT TRIP OPENS HOWEVERS THE CB 1 BREAKERr LOCATED IN THE ARPI CABINET 87r TRIPPED OPEN RESULTING IN THE LOSS OF ALL" ARPI INDICATION THE POWER SOURCE TO THE CB-1 ~

BREAKER COMES FROM BREAKER NO ~ 41 (15 AMPS) ALSO LOCATED IN THE NO 21 MAC CABINETS THE CB-1 BREAKER WAS RESET AND CLOSED TO RESTORE POWER TO THE ARPI INDICATORS AND TECH SPEC ACTION STATEMENT 3 0 3 WAS THEN EXITED ~

0 e o e e o e e e o e e e e e o o e e e ~

rs y~

4 e u ID 0 o e e a e o o e e o e e e o a e o o o 0

FORM 76 LER SCSS DATA 08-30-91.

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • +**************

DOCKET YEAR LER NUMBER REVISION DCS NUMBER NSIC EVENT DATE 315 1985 057 1 8602100448 198498 10/25/85

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • 4*********************************

DOCKET:315 COOK TYPE:PMR e 1 REGION: 3 NSSS:WE ARCHITECTURAL ENGINEER: AEPS FACILITY OPERATOR: INDIANA 8 MICHIGAN ELECTRIC CO ~

S YPl BOL: IME REPORTABILXTY CODES FOR THIS LER ARE:

13 10 CFR 50 73(a) (2) (iv): FSF actuations.

ABSTRACT POWER LEVEL OOOX THIS I ER IS BEING RESUBHITTED TO CORRECT THE DESCRIPTION OF THE SEQUENCE OF EVENTS LEADING TO THE REACTOR TRIP ~ ON OCTOBER 25r 1985r AT 0850 HOURS WITH THE UNIT IN HOT SHUTDOWN TWO OF FOUR POWER RANGE INSTRUMENTS MERE TAKEN FROH SERVICE BY RENOVING THE FUSES (XEEE/FU) TO ALl OW FOR INSTALLATION OF AN APPROVEO DESIGN CHANGE THIS SATISFIED THE 2/4 COINCXDENCE REQUXRED TO DE-ENERGIZE THE DETECTOR HIGH VOLTAGE IN BOTH SOURCE RANGE CHANNELS THUS RENDERING THEN INOPERABLE ~ TECHNICAL SPECIFICATION 3 ~ 3~1~1 TABLE 3 ~ 3 1, ITEM 6 ~ B REQUIRES AT LEAST ONE CHANNEL OPERABLE COMPLIANCE MITH SHUTDOWN MARGIN REQUIREMENTS MAS VERIFIED PER THE ASSOCIATEO ACTION STATEHENT ~

WITH 2/4 POWER RANGE CHANNELS INOPERABLEr A REACTOR TRIP SIGNAL WAS GENERATED ALTHOUGH THE REACTOR TRIP BREAKERS MERE OPEN AND NO EQUIPMENT MAS ACTUATED~ AT 0852 HOURSr THE FUSES WERE RE INSTALLED IN THE POWER RANGE DRAWERS AND BOTH SOURCE RANGE CHANNEL DETECTOR HIGH VOLTAGES WERE RE-ENERGIZED THE INCIDENT MAS DUE TO PERSONNEL ERROR ON THE PART OF THE TECHNICIANS AND THE UNIT SUPERVISOR TO PREVENT RECURRENCEr ALL OF THE PERSONNEL XNVOLVED HAVE BEEN COUNSELED ON THE IMPORTANCE OF THOROUGHLY RESEARCHING ALL POSSIBLE CONSEQUENCES OF THEIR ACTIONS THE HEALTH AND SAFETY OF THE PUBLIC, WERE NOT AFFECTED

0 0 0 ~ 0 0 0 0 0 0 0 0 0 0 0 S ~ 0 0 0 y

0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 ~

FOR H 77 LER SCSS DATA 08-30"91 6 ***********A**********A******************************************A**

DOCKET YEAR LER NUMBER REVXSXON OCS NUHBER NSIC EVENT DATE 315 1988 011 0 8900000000 213655 10/19/88 DOCKET:315 COOK 1 TYPE:PWR REGION: 3 NSSS:ME ARCHITECTURAL ENGXNEER: AEPS FACILITY OPERATOR: INDIANA 8 MICHIGAN ELECTRIC CO ~

SYMBOL: INE COHHENTS STEP 1: COHP XI SSPS INSTRUMENT BUS 01 POWER AVAXLABILITYINDICATOR BULB AND SOCKET ASSEMBLY) MODEL 37-1362-0335-216>>

MATCH-LIST CODES FOR THIS LCR ARE:

20 EQUIPMENT FAILURE REPORTABIl XTY CODES FOR THIS LER ARE:

13 10 CFR 50 73(a) (2) (iv): ESF actuations.

REFERENCE LERS:

1 315/88-013 ABSTRACT POWER LEVEL - 000X ON 10/19/88 AT 1522 HOURS UNIT ONE EXPERIENCED AN ENGINEERED SAFETY FEATURES ACTUATION (REACTOR TRIP) FROM THE LOSS OF REACTOR FLOW LOGIC CXRCUIT OF THE PLANT PROTECTION SYSTEMS ALTHOUGH NO ACTUAL LOSS OF REDUCTION OF REACTOR COOLANT FLOW EXISTED THE REACTOR TRiP SIGNAL. MAS THE ULTIMATE RESULT OF THE FAILURE OF AN INDICATING LIGHT ASSEMBLY, CONNECTED DIRECTLY 'TO ONE OF THE CLASS 1-E INSTRUMENT AND UNINTERRUPTABLE POWER SOURCES WHICH FEED THE SOLID STATE PROTECTION SYSTEM (SSPS) THE FAILURE CREATEO A SHORT CIRCUITr RESULTING IN EXCESSIVE CURRENT DEMAND ON THE POWER SOURCE THE INLINE PROTECTIVE FUSE OPENED AS REQUIRED~ RESULTING IN LOSS OF POWER IN ONE SSPS INPUTBAY>> THE RELAYS WITHXN THE AFFECTED INPUT BAY THEN OE-ENERGIZED TO THE FAIL-SAFE POSITION ONE OF THESE RELAYS IS ASSOCIATED METH THE REACTOR COOLANT PUMP (RCP) BREAKER POSITION LOGIC CIRCUIT ~ BECAUSE THIS CIRCUIT HAS A ONE OUT OF FOUR COINCID NCE WHEN REACTOR POWER.XS ABOVE 50Xr A REACTOR TRIP RESULTED'HE FAULTEO LAHP AND SOCKET ASSEMBLY WAS REPLACED AND UNIT STARTUP MAS ACCOHPLISHED ~

a e e o e o e e o o e e o e o e o W 0 f 7 s ~

I r

~ o o e e e e o e e e o e o o e e e o e 0

FORM 78 LER SCSS DATA 08-30-91 e ********************************************************************

DOCKET YEAR LER NUNBER REVISION DCS NUMBER NSIC EVENT DATE 316 1986 008 0 8600000000 202548 03/11/86 kkkkkkkkkkkkkk*kkkkkk*kkkkkkkkkkkkk*kkkkkkkkkkkkkkkkkkkkkkkkkkkkkkkk DOCKET:316 COOK 2 TYPE:PMR REGION: 3 NSSS:WE ARCHITECTURAL ENGINEER: AEPS FACILITY<<OPERATOR: INDIANA 8 MICHIGAN ELECTRIC CO SYHBOL: IME REPORTABXLITY CODES FOR THIS LER ARE:

13 10 CFR 50.73(a) (2) (iv): ESF actvations.

ABSTRACT POWER LEVE 000X. ON 3-11-.86 AT 1305 HOURS WITH UNIT 2 IN MODE 5 (COLD SHUTDOWN) r AN ESF REACTOR TRIP SIGNAL MAS RECEIVED CAUSED BY CONTROL POWER MIRES PULLING FREE FROM A POWER RANGE NUCLEAR INSTRUMENT (NI) DRAWER ANO SHORTING OUT DURING PREVENTIVE MAINTENANCE ESF SIGNALS WERE ALSO GENERATED WHEN THE SHORTED WIRES MERE DISCONNECTED AT 1317 HOURS AND WHEN RESTORING POWER AT 1355 HOURS'H WRONG BREAKER MAS CYCLED THERE WAS NO AUTOi4lATXC ACTUATION OF PLANT EQUIPMENT AS THE SIGNALS ARE BLOCKED MHEN XN NODE 5 ~ IT MOULD HAVE BEEN POSSIBLE FOR THIS EVENT TO HAVE OCCURRED DURING POWER OPERATIONS AS THE NI DRAWERS MERE PULLED OUT ON OCCASION ~ THIS WOULD HAVE RESULTED IN A REACTOR TRIP THE CAUSE MAS DUE TO A FAULTY ELECTRICAL CONNECTOR (IEEE/CON) ANO HISLABELED POWER SUPPLY DOORS (DOORS MERE INTERCHANGED) THE ELECTRICAL CONNECTOR HAS BEEN REPAIRED AND THE CABINETS LABELED PROPERLY AND PAINTED DIFFERENT COLORS TO PREVENT INTERCHANGING DOORS

0 e e e e e a o e a o o o e o o o e ~ o o 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

FORM 79 LER SCSS DATA 08-30-91 DOCKET YEAR LER NUMBER REVISION DCS NUMBER NSXC EVENT DATE 316 1986 016 0 8605290252 199418 04/29/86

• • • • • • • • • m******A***************************************************

DOCKET:316 COOK 2 TYPE:PMR REGXON: 3 NSSS:ME ARCHITECTURAL ENGINEER: AEPS FACXlITY OPERATOR: INDIANA 5 HICHIGAN ELECTRIC CO S YN BOL: I tlE COMMENTS STEP 2: COHP CON - 3 PIN 120 V AC CONNECTORJ STEP 6: EFF ID - MOMENTARY POMER LOSS DURXNG

- AUTOttATIC SMITCH TO BACKUP POMER REPORTABILITY CODES FOR THIS LER ARE:

13 10 CFR SO 73(a) (2) (iv): ESF actuations.

REFERENCE LERS:

1 316/86-008 ABSTRACT POWER LEVEL - OOOO ON 4 29 86r AT 0229 HOURS WITH UNXT 2 IN NODE 6 (REFUELING) WITH THE CORE UNLOADEDr ESF AND REACTOR TRIP SIGNALS WERE RECEIVED CAUSED BY SHORTED CONTROL POMER MXRES TO POWER RANGE NUCLEAR INSTRUMENT (NX) DRAWER N"41B THE WIRES SHORTED OUT MHILE A TECHNICXAN WAS PULLING THE NI DRAWER OUT FOR A SURVEILLANCE TEST AN ELECTRICAL CONNECTOR FAILED ALLOWXI'jG THE WIRES TO PUl L FREE THERE MAS NO WATER INJECTED INTO THE REACTOR COOLANT SYSTEN OR ACTUATION OF PLANT EQUIPMENT AS THE SIGNAlS ARE BLOCKED WHILE IN NODE 6 XT WOUl D HAVE BEEN POSSIBlE FOR THIS EVENT TO HAVE OCCURRED DURING POWER OPERATIONS WHXCH COULD HAVE RESULTED IN A REACTOR TRXP AND SAFETY INJECTION ~ TO PR VENT RECURRENCEr INSPECTIONS ARE BEING CONDUCTED OF ALL ELECTRICAL CONNECTORS IN THE NUCLEAR INSTRUMENT CABINETS "(BOTH UNIT 1 AND 2) ~ THE PURPOSE IS TO REPAIR OR REPLACE CONNECTORS AS REQUIRED AND ARRANGE THE CABLES TO ENSURE FREE HOVEt'tENT ~ THESE ACTIONS WILL BE COMPLETED BY 6-1-86m PREVIOUS SIMILAR EVENTS 316/86-008

e o a e o e e o o o e o a o o e o e e N 0 t

,0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

FORM 80 LER SCSS DATA 08-30-91

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • 4*************************************

DOCKET YEAR 'LER NUMBER REVISION DCS NUMBER NSXC EVENT DATE 316 1989 014 -0 8909220109 21 5257 08/14/89

• • • • • • • • • • • A'****************************************************A***

y DOCKET:316 COOK 2 REGXON: 3 TYPE;PWR NSSS:WE ARCHITECTURAL ENGINEER: AEPS FACILITY OPERATOR: INDIANA 5 MICHIGAN ELECTRIC CO SYMBOl: MEI g COMMENTS STEPS 2s8 MODEL NO ~ SV25075 (7 ' KVA) ~ STEP 5 EFF AM AUTO TRANSFERRED TO ALTERNATE POWER SOURCE STEP 7: EFF AM - TRANSFERRED BACK TO CLASS 1E POWER SOURCE STEPS 41 42 43 45 66 67 68 CHANNEL X - 10 11 12 13 14 15 16 RESPECTIVELY

'g WATCH-LIST CODES fOR THIS LER ARE:

20 EQUIPMENT FAiLURE CODES FOR THIS LER ARi:

y REPORTABILXTY 13 10 CFR 50 73(a) (2) (iv): ESF actuations e ABSTRACT POWER LEViL 100X ~ ON 8/14/89 AT 1601 HOURSr A REACTOR PROTECTION SYSTEM (RPS) ACTUATION (REACTOR TRIP) OCCURRED WHEN OPERATORS TRANSFERRiD THE CONTROL ROOM INSTRUMENTATION DISTRIBUTION (GRID) iV (VITAL BUS) INVERTER TO ITS NORMAl CLASS 1 E POWER SUPPLY AND THE INVERTER FAIl ED ~ WHEN" THi GRID IV INVERTER FAILED' REACTOR TRIP SIGNAL WAS INITIATED DUE TO THE REACTOR COOLANT PUMP (RCP) CIRCUIT BREAKER POSITION INDICATION OPEN (FED FROM CRID IV) PRIOR TO THE TRIP (AT APPROXIMATELY 1540 HOURS) r THE GRID INVERTER HAD TRANSFERRED TO ITS ALTERNATE NON-CLASS 1E POWER SUPPLY AT THE SAME TIME THAT A CONTROL POWER FUSE HAD BLOWN ON POWER RANGE NUCLEAR INSTRUMENTATION SYSTEM (NIS) CHANNEL IV (N-44) SUBSEQUENT INVESTIGATION DETERMINED THAT THE GRID INVERTER FAXLURE WAS DUE TO A FAILED SXLXCON CONTROLLED

~ RECTIFIER (SCR) IN THE STATXC TRANSFER SWITCH THIS AlSO RESULTEO IN THE FAILURE OF FUSES AND POWER SUPPLiES IN VARIOUS COMPONENTS FED FROM THE CRID ~ THE FAULTED SCR'S WERE REPLACED AND THE CRID INVERTER DECLARED OPERABLE'Ll .COMPONENTS FED FROM THE CRID WERE XNSPECTED ANDr WHERE NECESSARYr FUSES AND/OR POWER SUPPLXiS WERE REPLACED'

0 o o e e o e e o o e o e e o e e o e e o 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

FORM 81 LER SCSS DATA 08-30-91

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • 4******************************

DOCKET YEAR LER NUMBER REVISION DCS NUMBER NSIC EVENT DATE 317 1983 036 1 8402080353 188612 06/18/83

• • • • • • • • • • • • • • • • • • • • • • A*****A***************************************

DOCKET:317 CALVERT CLIFFS 1 TYPE:PMR REGION: 1 NSSS: CE ARCHITECTURAL ENGINEER: BECH FACILITY OPERATOR: BAl TXMORE GAS 5 ELECTRIC CO SYMBOL: BGE LERS:

~ REFERENCE 1 317/83-008 2 318/82-022 g ABSTRACT DURING STEADY STATE OPERATION AT 83X POWERS REED SWITCH POSITION INDICATION (RSPX) WAS LOST FOR ALL CONTROL- ELEMENT ASSEMBLIES (CEA)

(TECH SPiC 3 ~ 1 ~ 3 ~ 3) ACTXON WAS TAKEN TO Pl ACE REACTOR IN MiODE 3 PER TECH SPEC 3 0 ~ 3 ~ TROUBLESHOOTING INDICATED A SHORT ON CEA 56 REED STACK ~ LiADS TO CEA 56 WERE LIFTEDr RESTORING PROPER INDXCATION ON THE

~

OTHER REED STACK CHANNELS ALL CEA PULSE COUNTING POSITION CHANNELS AND UPPER ELECTRICAL'IMIT SWITCHES REMAINiD OPFRABLE THROUGHOUT EVENT ~ SIMILAR EVENTS 83 08r 50 31 8/82 22 THE RSPI POWER SUPPLY MAS OVERLOADED WHEN CEA 56 ~ S REED STACK POSITION TRANSMITTER (RSPT)

( El CCTRO MECHANICS< PART PN9027r R EV ~ 1 ) SHORTED ~ THE CMI FEATUR E WAS RETAINED VIA A TEMPORARY MODIFICATION UNTIL THE RSPT WAS REPLACED DURING THE UNIT'S REFUELING OUTAGE ~ THE FAXLED RSPT MAS REPAIRED FOLLOWING THE VENDOR'S ROOT CAUSE INSPECTION

0 0 0 0 0 0 0 e 0 0 0 0 0 a 0 e 0 0 0

~ ~ 0 0 0 ~ ~ ~ 0 0 0 ~ ~ ~ 0 0 0 0 0 0 0

FORM 82 LER SCSS DATA 08-30-91 DOCKET YEAR LER NUMBER REVISION OCS NUMBER NSIC EVENT DATE 322 1989 002 0 8904140508 213574 03/09/89

• • • • • • • • • • • A*********A****************************************%'4****

e DOCKET:322 SHOREHAH REGION: 1 TYPE.BWR NSSS:GE ARCHITECTURAL ENGINEER: SWXX FACIl XTY OPERATOR: LONG ISLAND l XGHTX NG CO SYNBOL: LIL g COHMENTS'TEP 1: CAUSE AX - TESTING THIS LER ARE:

g MATCH-LEST 35 HUHAN ERROR CODES FOR 941 REPORT ASSOCIATEO WITH 10 CFR 50 72 REPORTABILITY CODES FOR THIS LCR ARE:

13 10 CFR 50.73(a) (2) (iv): ESF actuations.

ABSTRACT POWER LEVEL OOOO ON 3/9/89 AT 2037r A FULI RPS ACTUATION OCCURRED WHILE ATTEMPTING TO RESTORE POMER TO THE "8" RPS BUS DURING THE PERFORMANCE OF AN OPERATIONS SURVEILLANCE TEST THE PLANT MAS IN OPERATIONAL CONDITION 4 (COLO SHUTDOWN) MXTH THE MODE SIMTCH IN SHUTDOMN AND ALL RODS INSERTED IN THE CORE AFTER EMERGENCY BUS 102 WAS DEENERGIZEO. DURING A SIHULATED LOSS OF OFFSITE POWER (LOOP) BY PROCEDURE SP (24 307 02) ANO REENERGIZED BY ITS ASSOCIATEO DIESEL (EDG 102) r OPFRATORS ATTEHPTEO TO REENERGIZE THE "B" RPS BUS ~ THE BUS DEENERGIZATXON MAS AN EXPECTED RESPONSEw RESULTING IN A 1/2 REACTOR TRIP SIGNAL~ HOWEVERS THE "B" RPS HG SET OUTPUT BREAKER WOULD NOT RESET AND REHAIN CLOSED DURING THE COURSE OF TROUBLESHOOTING~ THE MATCH ENGINEER INADVERTENTLY DOMNPOMERED AN APRH INVERTER ON THE "A" SIDEr THEN REPOWEREO IT CAUSING A FALSE HXGH FLUX SIGNAL RESULTING IN AN "A" SIDE REACTOR TRIP ~ SINCE THE "B" SIDE REACTOR TRIP SIGNAL MAS ALREADY PRESENT DURING THE TROUBLESHOOTINGs A FULI REACTOR TRIP OCCURRED+ PLANT MANAGEMENT MAS NOTIFIED AND THE NRC MAS NOTIFXED AT 2215 PER 10CFR50 ~ 72 ~ INVESTIGATION REVEALED THAT TRANSIENTS RESULTING FROM THE LOADING OF THE "B" RPS BUS CAUSED A PEAK VOLTAGE OF 135 VAC ~

THE OVERVOLTAGE TRIP SETPOINT OF THE MG SET OUTPUT BREAKER WAS SET AT 129 3 VAC ADJUSTHENTS WERE HADE TO THE VOLTAGE REGULATOR ANO THE OUTPUT BREAKER WITH SATXSF ACTORY RESULTS ~

0 o e o e o o e e o o o o a o o o o e o o 0

~ 1

FORM 83 LER SCSS DATA 08-30-91

• • • • • • • • • • • %*********************A**********************************

DOCKET YEAR LcR NUMBER - REVISION DCS NUHBER NSIC EVENT DATE 323 1988 020 0 8901040394 212250 11/28/88

~ *******************************0**************+*********************

DOCKET:323 DIABLO CANYON 2 TYPE:PMR RFGXON: 5 NSSS:ME ARCHITECTURAL ENGXNEER: PGEC FACILXTY OPERATOR: PACIFIC GAS 8 ELECTRIC CO SYMBOL: PGE MATCH-LIST CODES FOR THIS LER ARE:

941, 60 REPORT ASSOCXATEO WITH 10 CFR 50 SPURIOUS/ UNKNOMN CAUSE

'2 REPORTABILITY- CODES FOR THIS LER ARE:

13 10 CFR 50 ~ 73(a) (2)

. (iv): ESF actuations.

REFERENCE LERS:

1 275/86-014 2 275/88-006 ABSTRACT POWER LEVEL 000% ~ ON 11/28/88 AT 2008 PSTs A CONTAINMENT VENTILATION ISOLATION OCCURRED AND THE FUEL HANDLING BUILDING VENTXLATXON SYSTEN SHIFTED TO THE XODINE RENOVAL'ODE THIS RESULTEO FROM A TEMPORARY LOSS OF POWER IN VITAL INSTRUMENT AC DISTRIBUTION PANEL PY-2Z TO THE RADIATION MONITORS WHXCH CAUSED THE ESF ACTUATXONS WHEN THE AFFECTED RADIATION ilONITORS SMXTCHEO TO ALARM UPON LOSS OF POMER ~ XN ADDITXON TO'HE ESF ACTUATXONSr SYSTEHS RESPONSES INCLUOEO: HAIN STEAN =

ISOLATION SIGNAL (NO VALVES CLOSED BECAUSE THE SIGNAL MAS OF INSUFFXCIENT DURATiON) LETDOWN ISOLATION PRESSURXZER HEATERS TRIPPEO STEAN DUMPS CLOSED FCV-128 STARTED TO FAIL OPEN (5% DEMAND TO 25% DEMAND) w RN 2BA" PUMP TRIPPEDJ FCV 111 A FAILEO CLOSED FLUX RATE TRIP ON-POWER RANGE N42s AND NUHEROUS OTHER ALARHS THE FOUR HOUR NONEMERGENCY REPORT REQUIRED BY 10 CFR 50 72 MAS COMPLETED BY 2227 PST ~ '

REVIEW OF'LANT RECORDS INDICATES THAT NO EVOLUTION MAS IN PROGRESS THAT MOULD HAVE PRODUCED A VOLTAGE TRANSIENT OF SUFFICIENT HAGNITUDE TO HAVE CAUSED. THIS EVENT

0 o e a o e e e o e o a e a o e e o o e N 0 l

IJ I

~ ~

F I

lf i

0 0 0 0 0 0 0 0 0 0 0 0 0 P 0 0

FORM 84 LER SCSS DATA 08-30-91 DOCKET'EAR LcR NUHBER REVISION DCS NUtlBER NSXC EVENT DATc 323 1990 003 0 9005080252 218123 04/04/90

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • %*****************A*****************

DOCKiT:323 DIABLO CANYON 2 TYPE:PMR e REGION: 5 NSSS:WE ARCHITECTURAL ENGINEER: PGEC FACXLITY OPERATOR: PACIFIC GAS 8 ELECTRIC CO SYNBOL: PGE COMMENTS STEP 3: EFF IX -'LECTRXCAL TRANSIENT MATCH-LIST CODES FOR THIS LER ARE:

941 REPORT ASSOCXATED WITH 10 CFR 50 72 60 SPURIOUS/ UNKNOWN CAUSE REPORTABILITY CODES FOR THIS LcR ARE 13 10 CFR 50.73(a) (2) (iv): ESF actuations.

REFERENCE LERS:

1 275/86-014 2 323/86-010 3 323/88-020 ABSTRACT POMER LEVEL OOOX ~ ON 4/4/90r AT 1258 PDTr WITH UNIT 2 IN HODE 5 (COLO SHUTDOWN) r A CONTROL'OOM VENTILATION SYSTEH TRANSFER FROM NODE 1 (NORHAL) TO NODE 4 (PRESSURIZATION) OCCURRED AflD A FUEL HANDLING BUILDING VENTILATXON SYSTEtl TRANSFER TO THE IODINE REMOVAL NODE OCCURRED ~ THiSE ARi'NGINEERED SAFETY FEATURE ACTUATIONSr AND MERE CAUSED BY AN ELECTRICAL TRANSIENT IN VITAL INSTRUMENT AC DISTRIBUTION PANEL PY-21 A WHICH SUPPLIES A NUHBER OF VITAL LOADSr INCLUDING T'WO RADIATXON HONITOR SYSTEM RACKS ANO THE CONTROL ROOM VENTILATION SYSTEM ISOLATION AUXILIARY RELAYS ~ A FOUR HOURr NON EMERGENCY REPORT blAS HADE IN ACCORDANCE WITH 10 CFR '50 72(B) (2) (XI) ON 4/4/90r AT 1535 PDT ~

A REVIEW OF THE UNiT 2 OUTAGE WORK IN PROGRESS AT THE TXHE OF THE EVENT INDICATED THAT MANY" OF THE WORK ACTIVITIES COULD HAVE PRODUCED AN ELECTRXCAL TRANSIENT OF SUFFICXENT MAGNITUDE TO HAVE CAUSED THIS EVENT+ HOMEVERr XNT'ERVXEMS WITH THE MORK FOREitEN AND AN INVESTIGATION OF THE EVENT DID NOT IDENTIFY A ROOT CAUSE FOR THE EVcNT THUSr NO SPECIFIC CORRECTIVE ACTIONS TO PREVENT RECURRENCE MERE DETERMINED FOR THXS EVENT ~

0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

~ '

0 0 4 0 0 0 e 0 0 0 0 0 0

FORH 85 LER SCSS DATA 08-30-91 DOCKET YEAR LER NUMBER REVISION OCS NUMBER NSIC EVENT DATE 324 1981 1 09 0 81111 0041 4 1 69624 1 0/07/81

• • • • • • • • • irk*********************************************************

DOCKET:324 BRUNSWICK 2 TYPE:BWR REGION: 2 NSSS:GE ARCHITECTURAL ENGINEER: UECX FACILITY OPERATOR: CAROlINA POWER 5 LIGHT CO SYNBOL: CPL CONHENTS STEP 1: COHPONENT BX SWITCH HOUSING ~

ABSTRACT HPCI SYSTEH STEAN LEAK DETECTION AHBIENT TEMPERATURE HIGH ANO HPCI LOGIC POWER FAILURE ANNUNCIATORS MERE RECEIVED AN IMMEDIATE INVESTIGATION REVEAI EO THE HPCI SYSTEY ISOLATION LOGIC POWER SUPPLY FUSEr LOCATED IN'ISTRIBUTION PANEL P614w MAS BLOWN ~ THE HPCI SYSTEH MAS THEN O'ECLAREO INOPERABlE ANO WAS ISOLATEO ELECTRICAL SHORTING TO GROUND OF HPCI STEANLINE TUNNEL TEMPERATURE SMITCHi 2-E41=TS-3314r HOOEL NO 170002 40r OUE TO NOISTURE ACCUNULATION IN THE SWITCH HOUSING RESULTING FROH CORROSION OF THE SMITCH HOUSING CAUSED THE EVENT ~ A NEW TEMPERATURE SMITCH AND LOGIC POWER SUPPLY FUSE WERE INSTALLED MHICH RETURNED THE HPCI LEAK DETECTION SYSTEM TO NORMAL~

THE HPCI SYSTEN WAS OECLAREO OPERABLE

0 ~ 0 0 0 0 0 0 0 0 0 0 0 N 0 0 0 0 %

FORM 86 LE R SCSS DATA 08-30-91 DOCKET YEAR LER NUHBER REVISlON DCS NUMBER NSIC EVENT DATE 324 1987 004 0 8704170194 204119 03/11/87

• • • • • • • A********A**********A*************************************A**

g DOCKET:324 BRUNSWICK 2 REGION: 2 TYPE:BMR NSSS: GE ARCHITECTURAL ENGINEER:

OPERATOR: CAROLINA POWER. 8 LIGHT CO UECX'ACILITY SYMBOL: CPL COHHENTS STEP 34: CAUSE HX REVERSE FLOW.

y WATCH-LIST CODES FOR THIS 20 EQUIPHENT FAILURE LER ARE:

35 HUHAN ERROR REPORTABILITY CODES FOR. THXS LER ARE:

13 10 CFR 50.73(a) (2) (iv): ESF actuations.

14 10 CFR, 50;73(a) (2) (v): Event that could have pr evented fulfillment of a sa ety unction f f ABSTRACT PO'WER LEVEL. 100'T 0307 ON 3/11/87r A UNIT 2 REACTOR SCRAM OCCURRED DUE TO A LOM LEVEL IN THE REACTOR VESSEL THE LOM VESSEL LEVEL MAS CAUSED BY LOSS OF THE UNINTERRUPTIBLE POWER SUPPLY (UPS)

WHICH CAUSED THE SIGNAL TO THE FEED PUNP CONTROL SYSTEM TO RAMP BACK TO HINIHUH SPEED OF APPROXXNATELY 2800 RPH ~ AT THIS SPEEDi THE PUMPS MERE NOT ABLE TO NAINTAIN AN ADEQUATE FLOW RATE INTO THE VESSELr THUS CREATING THE LOM. LEVEL CONDITION>> FOLLOWING THE SCRAM RECOVERY~

DURING A SUBSEQUENT HPCX SYSTEM LINEUP VERIFICATIONS IT MAS ALSO NOTED THAT THE HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM MAS INOPERABLE THE HPCI SYSTEM OID PERFORN AS REQUIRED DURING THE SCRAH.

AT THE TINE'F THIS EVENTr UNIT 2 MAS AT 100% POMER THE LOSS OF THE UPS SYSTEH STEMMED FRON FAILURE TO FOLLOW- PROCEDURES MHXLE ATTEMPTING TO TRANSFER INPUT POWER TO UPS FROM.,THE RESERVE BUS TO THE STANDBY INVERTED THE HPCI SYSTEM INOPERABILXTY MAS DUE TO A FAXLED MOTOR ON THE HPCI (E41) PUMP DISCHARGE VAI VE E41 F007- WITH THE VALVE IN THE CLOSED POSITION THE MOTOR WAS REPLACED PRIOR TO STARTUP AND THE HPCI SYSTEH RETURNED TO OPERABLE. STATUS

0 e o e e e a e o o e e o e e o o e o o o 0 I

SO IA t

0 0 0 0 0 0 0 0 0 0 0 0 0 0

FORM 87 LER SCSS DATA 08-30-91

• • • • • • • A************************+**********+********************i***

DOCKET YEAR LER NUMBER REVISION DCS NUMBER NSIC EVENT DATE 1988 018 0 8812210111 -211569 11/16/88 '24

~ *********************+**********************************************

DOCKET:324 BRUNSWICK 2 TYPE:BMR REGION: 2 NSSS GE ARCHITECTURAL ENGINEER: UECX FACILITY OPERATOR: CAROI XNA POWER 5 LIGHT CO ~

SYMBOL: CPl MATCH-LIST CODES FOR THXS LER ARE:

20 EQUIPMENT FAXLURE REPORTABXLXTY CODES FOR THIS LER ARE:

13 10 CFR 50 73(a)(2)(iv): ESF actuations ABSTRACT POWER LEVEL 100X AT 1026 HOURS ON NOVEHBER 16r 1988r THE UNIT 2

~

REACTOR SCRAHHEO DUE TO TURBINE CONTROL VALVE FAST CLOSURE ON A HIGH LEVEL TURBINE. TRIP ~ THE UNIT MAS OPERATING AT 100X POWER ~ THE EMERGENCY CORE COOLING SYSTEMS MERE OPERABLE AND IN STANDBY READINESS ~

DURING THE EVENTr GROUPS 1r 2r 3r 6r AND 8 XSOLATIONS MERE RECEIVED ~

THE D OUTBOARD HAIN STEAN LINE ISOLATION VALVE (NSIV) EXHXBITEO DUAL POSITION INDXCATXON HPCI AND RCIC RECEIVED INITIATION SIGNALS AND THE RCXC SYSTEM XNJECTEOr HOMEVERr THE HPCI SYSTEM RECEIVED A TRIP SIGNAL ANO THE INJECTION VALVE IMMEDIATELY CLOSED UPON REACHING FULL OPEN THE OPERATOR MANUALLY OPENED THE HPCI INJECTION VALVE AND RESTORED LEVELS REACTOR PRESSURE MAS CONTROI LED BY AUTO ANO MANUAL SAFETY RELIEF VALVE ACTUATION BY 1052 HOURS THE OPERATOR HAD RESET THE GROUP 1 AND 3 ISOLATXONSr AND REESTABLISHED.THE CONDENSER-AS A HEAT SINK THE HIGH REACTOR LEVEL MAS DUi TO A FEEDMATER LOGXC CONTROL TOPAZ INVERTER TRIPPING ON HIGH INPUT VOLTAGES THE HSXV DUAL INDICATION MAS DUE TO A LIMIT SMITCH PROBLEM HPCI XS BELIEVED TO HAVE TRIPPED ON LOM SUCTION PRESSURE (LSP) ~ 'HE XNVERTER,. HAS BEcN RECALIBRATEOr THE NSIV LIMIT SMITCH HAS BEEN READJUSTED AND THE HPCI LSP TRIP HAS BEEN DISABLED THIS EVENT HAD HINIHAL SAFETY SIGNIFICANCE

~~

FORH 88 LER SCSS DATA 08-30-.91

• • • • • • • • • • • • • • • • • • • • • • 4*********************************************

DOCKET YEAR LER NUMBER REVISIOI'I DCS NUMBER NSIC EVENT DATE 325 1988 023 0 8811290031 213662 10/21/88 DOCKET:325 BRUNSWICK 1 TYPE:BMR O REGION: 2 NSSS:GE ARCHITECTURAL ENGINEER: UECX FACILITY OPERATOR: CAROLINA POWER 8 LIGHT CO SYMBOL: CPL COHHENTS STEPS 3r4 PART NO 11500 100 STEP 8 EFF ED HIGH CONDUCTIVITY~ STEP 11 PART NO 112C3144 STEP 12: PART NO 175A9746P001 STEP 14: PART NO ~ 885D7 01G006 ~ STEP 15: PART NO ~ 209A5034P003 ~ STEP 16".PART NO 112C2346P002 ~

STEPS 21r22 TYPE CR120 STEP 29 HODEL NO MIN 1 y MATCH-LIST CODES FOR THIS 20 EQUIPMEttT FAILURE LER ARE:

g REPORTABILITY CODES FOR THIS LER ARE:

13 10 CFR 50.73(a) (2) (iv): ESF actuations ABSTRACT POWER LEVEL 027X ~ "'AT 1243 HOURS ON 10/21/88 UNIT 1 AUTOMATICALLY SCRAMHEDr WHILE AT APPROXIMATELY 27X POMERr DUE TO A MAIN TURBINE TRIP/TURBINE STOP VALVE CLOSURE CAUSED BY A HIGH REACTOR LEVEL OF </

208 INCHES THIS OCCURRED AFTER SHIFTING FROM THREE-ELEMENT TO ONE-ELEMENT FEEOWATER CONTROL DURING A PLANNED POWER REDUCTION FOR A ORYWEI L ENTRY TO REPAIR REACTOR WATER CLEANUP (RMCU) SYSTEM (G31)

INBOARD PRXHARY CONTAINMENT ISOLATION VALVE G31-F001 NO PRXMARY CONTAXNHENT ISOLATIONS OCCURRED AND THC HIGH PRESSURE COOLANT INJECTION SYSTEHr AUTOMATIC DEPRESSURIZATION SYSTEHr RESIDUAL HEAT REMOVAL/LOM PRESSURE COOLANT INJECTION SYSTEHr THE A AND 8 CORE SPRAY SUBSYSTEHSr AND THE REACTOR CORE ISOLATION COOLING SYSTEM REMAINED IN STANDBY READINESS THIS EVENT HAO MINIMAL IIIPACT ON PLANT SAFETY THE HIGH LEVEL RESULTEO FROM A FALSE l.OM LEVEL SIGNAL TO FEEDMATER (C32) MASTER LEVEL CONTROLLERr C32 R600r WHICH INCREASED FEEDWATER FLOW TO THE REACTOR ~ THE FALSE LOM LEVEL SIGNAL RESULTED FROM HIGH ELECTRICAL RESISTANCE ACROSS CONTACTS 3 ANO 4 OF THE FEEDWATER CONTROI THREE ELEMENT TO ONE EI EMENT CONTROL TRANSFER RELAYr C32 K3 THE FAILURE HECHANISM OF K3 WILL BE FURTHER INVESTIGATED BY 3/15/89 K3 MAS REPLACED AND THE FEEDWATER CONTROL SYSTEM WAS RETURNED TO SERVICE G31-F001 MAS REPAIRED AND THE RMCU SYSTEM WAS RETURNED TO SERVICE AT 1218 HOURS ON 10/23/88.

0 o e e o e e o o a o e e o e o o e o o o 0 N

~~

I P

I 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

FORM 89 LER SCSS DATA 08-30-91 DOCKET YEAR LER NUNBER REVXSION OCS NUMBER NSXC EVENT DATE 327 1980 005 0 80041 50533 1 561 24 03/11/80

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • 4****

DOCKET:327 SEQUOYAH 1 TYPE:PWR REGION: 2 ENGINEER TVAX NSSS:WE'RCHITECTURAL FACILITY OPERATOR: TENNESSEE VALLEY AUTHORITY S YNBOL: TVA ABSTRACT POWER LEVEL 000% CAUSE MAINTENANCE ERROR ~ MHILE PERFORMING SI-247~ 605 (RESPONSE TIHE SI ON SAFEGUARDS RELAY K605) r THE REACTOR SOLID STATE PROTECTION SYSTEH WAS PLACED IN THE "INPUT INHIBIT""NODE

~ THIS REHOVEO THE HIGH VOLTAGE FROH THE SOURCE RANGE CHANNEL N31 ~ ONLY ONE SOURCE RANGE CHANNEL MAS THEN IN SERVICE ~ UNIT MAS IN MODE 6 BUT NO CORE ALTERATIONS MERE TAKING PLACE THE SOURCE RANGE HXGH VOLTAGE MAS REHOVED BECAUSE OF TH ABNORHAL STATUS OF A SOURCE RANGE VOLTAGE CUT OUT RELAY ~ FUSES L19 AND L20 HAD BEEN REMOVED WHICH PREVENTEO OPERATION OF THIS RELAY THE FUSES MERE REPLACED

o e a e o e e e e o e e o e e e e e o N 0 s

I 0 o e a a 0 o o e e e e o ~ e o o o e e e 0

FORN 90'ER SCSS DATA I

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • 4*************

08-30-91 DOCKET YEAR LER NUHBER REVISION DCS NUMBER NSXC EVENT DATE 327 1982 050 0 8205180393 173358 04/13/82

• • • • • • • • • • • • • • • i<****************************************************

DOCKET:327 SEQUOYAH. TYPE:PMR e 1 REGION: 2 NSSS:WE ARCHITECTURAL ENGINEER: TVAX FACILXTY OPERATOR: TENNESS EE VALLEY AUTHORITY

@ SYMBOL: TVA g COMMENTS STEP 2: COMPONENT XA ANNUNCIATOR HORN ABSTRACT AT 0040 ON 04/13/82r WITH UNIT 1 IN NODE 1r DIESEL GENERATOR (0/G) 1A-A WAS DECLARED. INOPERABLE WHEN POWER FUSES BLEW IN THE CONTROL CIRCUITRY THE ACTION STATEMENT OF*LCD 3 ~ 8 ~ 1 ~ 1 MAS COMPLIED WITH ~

INVESTIGATION REVEALED A BROKEN LEAD ON THE ANNUNCXATOR HORN HAD SHORTED TO THE CASEi CAUSING THE FUSES TO BLOW~ THE HORN WAS REPLACED AND THE D/G MAS DECLARED OPERABLE AT 0716 ON 04/13/82 THE PRESENT SURVEILLANCE FREQUENCY IS EVERY 31 DAYS

J ~

~~

P'

FORM 91 LER SCSS DATA 08-30"91.

• • • • • • • • 4'***A*****************************%*************************

DOCKET YEAR LER NUMBER REVISION DCS NUMBER NSXC EVENT DATE 327 1983 009 0 8302240266 189874 01/31/83 DOCKET:327 SEQUOYAH 1 TYPE:PWR

~ REGION: 2 NSSS".WE ARCHITECTURAl ENGINEER: TVAX FACILXTY OPERATOR: TENNESSEE VALLEY AUTHORITY SYMBOL: TVA COMMENTS STEP 2 AND 3: EFFECT IX - REDUCED VOLTAGE ABSTRACT UNIT 1 IN MODE 1 AT 100X POWER AT 1?26 HRS DURXNG THE PERFORMANCE OF SPECIAL'EST INSTRUCTION 82 06'HE CONTROL ROO POSITION INDICATION SYSTEM WAS INOPERABLE WHEN THE INDICATED POSITION FOR ALL RODS OEVIATEO GREATER THAN 12 STEPS FROM ACTUAL ROD POSITION THIS EVENT CAUSED ENTRY INTO LCOS 3.1.3 ~ 2 AND 3.0 3. SPECIAL TEST INSTRUCTION 82-06 WAS BEING RUN UNDER DEGRADED VOLTAGE CONDITIONS WHEN THE 480 V SHUTDOWN BOARD VOLTAGE WAS REDUCED TO 410 VOLTS'HIS CAUSED THE ROD POSITION INDICATION SYSTEM TO INDICATE ERRONEOUS POSITIONS ~ AT 1228 HRSr 480 V BOARD VOLTAGE WAS RAISED AND AL'L ROO POSITXONS INDICATED 0 NORMAL~ 'MPHASIS WAS PLACED ON A MORE DETAILED EVALUATION OF DEGRADED VOLTAGE TESTS'F REQUIREDr IN THE FUTURE~

0 e e e o e o e o o e e o.e e o e e o e N 0 I ~ 4~

I3 CI I

4 t

I-0 e o e e e e e e o o e e e e o e e e o a 0

FORM 92 LER-SCSS DATA 08-30-91

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • 4***********************************

DOCKET YEAR l ER NUMBER REVISl'ON OCS NUMBER NSIC EVENT DATE 327 1985 009 0 8503070005 193361 01/28/85

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • 4**********************************

DOCKET:327 SEQUOYAH 1. TYPE:PWR REGION: 2 NSSS:WE ARCHITECTURAL ENGINEER: TVAX FACILITY OPERATOR: TENNESSEE VALLEY AUTHORITY SYMBOL:, TVA y REPORTABXLITY CODES FOR THIS 10 10" CFR 50.73(a) (2) (i):

LER ARE:

Shutdoens or technical specification violations.

ABSTRACT POWER LEVEL 100X ~ ALL ROD POSITION INDICATION SIMULTANEOUSLY LOWEREO APPROX 20 STEPS RESULTING IN MISALIGNMENT FROM THE STEP COUNTER OF GREATER THAN 12 STEPS ALLOWED BY TECH SPECS ~ ALL POWER PARAMETERS REMAINED UNCHANGED INDICATING FALSE ROD POSITION XNOICATXON READINGS ~

ALL ROD POSITION INDICATORS GRADUALLY RETURNED TO NORMAL IN =9 MINS IT WAS DETERMINED THAT THE ONLY FAIi.URE WHICH COULD CAUSE ALL OF THE RPI'S TO FAXL WOUI D BE AN. INTERRUPTION OR REDUCTION IN 120V AC POWER AFTER IT WAS DETERMINED THAT NO BREAKER SWITCHING HAD OCCURREDr A CHECK WAS MADE OF THE SOLATRON LINE VOLTAGE REGULATOR IN THE CABLE SPREADING ROOM THIS CHECK REVEALED SMAI L (2-3 INCH DIAMETER) PUDDLES OF WATER BENEATH THE SOLATRON ~ THE MOST LIKE! Y SEQUENCE OF EVENTS WAS WETTING OF THE SOLATRON INDUCTION CIRCUITRY RESULTING IN VOLTAGE REDUCTION ~ AS THE MOISTURE DISSIPATED OUE TO THE HEAT GENERATEO BY THE UNITr THE NORMAL VOLTAGE WAS REESTABLISHEDr AND THE RPX S GRADUALLY RETURNED. TO NORMAL'O DAMAGE TO THE SOLATRON WAS NOTED'HE ACTUAL MEANS OF WATER ENTERING THE SOLATRON COULD NOT BE DETERMINED ~

0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 II

FORM 93 LER SCSS DATA 08-30-91 0 ********************************************************************

DOCKET YEAR LER NUMBER REVXSION DCS NUMBER NSXC EVENT DATE 327 1987 061 8803040223 208435 08/31/87

~ ***********************************************************4********

1 DOCKET:327 SEQUOYAH TYPE:PWR g REGION: 2 NSSS:WE ARCHITECTURAL 'EPIGXNEER: TVAX FACILITY OPERATOR: TENNESSEE VALLEY AUTHORITY SYNBOL: TVA MATCH-LIST CODES FOR THIS LER ARE:

34 DESIGN ERROR OR INADEQUACY REPORTABILITY CODES FOR THIS LFR ARE:

11 10 CFR 50.73(a) (2) (ii): Unanalyzed conditions LERS:

~ REFERENCE 1 327/84-046 2 327/84-049 3 327/84-051 4 327/84-057 5 327/84-059 o 327/84-063 7 327/84-067 8 327/84-074 9 327/85-002 ABSTRACT POWER LEVEL 000% THIS LER IS BEING REVISED. IN- ITS ENTIRETY TO PROVIDE ADDITIONAL XNFORHATION RELATING TO PRiVIOUSLY REPORTED 10 CFR 50 APPENDIX R OEFICIENCIESr TO UPDATE THE .CORRECTIVE ACTIONS TAKEN BY TVAr ANO TO CLARIFY THE CONTROLS THAT ARE CURRENTLY IN PLACE TO PREVENT THE RECURRENCE OF THXS EVENT ON 8/31/87'ITH UNITS 1 AND 2 IN MODE 5 (COLO SHUTDOWN) ~ XT WAS DETERMINED THAT A FAULT IN APPENDIX R, ASSOCXATEO CIRCUITS COULD HAVE CAUSED A REQUIRED CIRCUIT ON THE 125-VOLT DC ViTAL BATTERY BOARDS AND/OR THE 480-VOLT SHUTDOMN BOARDS TO BE INTERRUPTED'HE CONDXTXONS ON THE 125-VOLT BATTERY BOARDS MERE CAUSED BY iNADEQUATE DESIGN PROCiOURES WHILE THE CONDITIONS ON THE SHUTDOWN BOARDS WERE CAUSiD BY AN INADEQUATE DESIGN CHANGE CONTROL PROCESS THE DESIGN PROCEDURES THAT MERE USED TO CALCULATE SELECTIVE COORDINATION BETWEEN FUSE AND BREAKER COMBINATIONS IN CIRCUITS POWEREO BY THE 125-VOLT BATTERY BOARDS OIO NOT REQUIRE ACTUAL CONSTRUCTED CABLE LENGTHS TO BE USED'HE DESIGN CHANGE CONTROL PROCESS THAT WAS FOLLOWED WHEN MODIFICATIONS MERi 5lAOE TO THE CIRCUITS POWERED BY THE 480-VOLT SHUTDOWN BOARDS OID NOT REQUIRE SELECTIVE COORDINATION CALCULATIONS TO BE PERFORHEO ~ THE IDENTIFIED CIRCUITS HAVE BiEN EVALUATEDr ANO CORRECTIVE ACTXONS TO OBTAIN PROPCR SELECTIVE COORDINATION (OR DELETE THE REQUIREMENT FOR SANE) HAS BEEN COMPLETED ~

0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 %

l 4 0 0 0 0 0 0 0 0 0 0 0 0 N 0 0 0 0 0

FOR H* 94 LER SCSS DATA 08-30-91 DOCKET'EAR LER NUMBER REVISION DCS NUMBER NSXC EVENT DATE 327 1988 002 0 8802080125 208231 01/05/88 g DOCKET:327 SEQUOYAH REGION:

1 2

TYPE:PWR NSSS:ME ARCHITECTURAL ENGINEER: TVAX FACII ITY OPERATOR: TENNESSEE VALLEY AUTHORITY SYNBOL: TVA COMMENTS STEP 4 COYiP RA INSTRUMENT NAl FUNCT ION ALARM~ STEP 8 F AILURE TO SAHPi F SERVICE MATER TRAXN B MHXLE BOTH MONITORS MERE INOPERABLE'A/PT MATCH-LIST CODES FOR THIS LER ARE:

40 PROCEDURAL DEFICXENCY REPORTABXLITY CODES FOR THIS LER ARE:

10 10 CFR 50.73(a) (2) (i): Shutdouns or technical 0 specif ication violations.

'BSTRACT POWER LEVEL. 000% ~ ON" JANUARY 5 1 988'ITH UNITS 1 AND 2 XN NODE 5 (0 PERCENT POMERr 4 PSIG> 120 DEGREES F AND 0 PERCENT POWERr 100 PSXGr 128 DEGREES Fr RESPECTIVELY) r AT APPROXIHATELY 1730 EST XT WAS DISCOVERED THAT A LXNITING CONDITION FOR OPERATXON (LCO) MAS NOT COHPLIEO WITH. AS REQUIRED BY SEQUOYAH NUGAE EAR PLANT (SQN) TECH SPECS ON JANUARY 4 1988 AT APPROXIMATELY 1630 EST OPERATIONS PERSONNEL

=

DECLARED RADIATION HONXTORS (RHS) 0-RH-90-134 At/0 0-RN-90-141 INOPERABLE'OMEVERr OPERATIONS PERSONNEL OID NOT COHPLY WITH ACTION STATEMENT 32 OF LCO 3 ~ 3 3 9 FOR AN INTERVAL OF APPROXXHATELY 13 HOURS ~

AN INVESTIGATION INTO THiS EVENT CONCLUDED THAT A SUFFICIENT DESCRIPTION TO DETERMINE THE HXNXNUM CHANNELS OF MONITORING REQUXR'ED TO ENSURE COHPLXANCE FOR THE LCO DXD NOT EXIST THIS RFSULTEO XN OPERATIONS PERSONNEL INCORRECTLY INTERPRETING THE REQUIREMENTS FOR CONPLIANCE OF - THE LCO"' AS A RESULTS THE ACTION OF THE LCO WAS NOT ENTERED AS IMMEDIATE CORRECTIVE ACTION UPON DISCOVERY OF THE NONCOHPLIANC Ex OPERATIONS NOTX FIED CHEYiIST RY TO INITIATE THE LC 0 ACTION STATEHENT TO PREVENT RECURRENCE A TECH SPEC INTERPRETATION XS BEING ISSUED TO STATE THAT ONE CHANNEL FOR EACH ERC'M EFFLUENT LINE DISCHARGE HEADER IS REQUIRED TO BE OPERABLE DURING RELEASE THROUGH THESE PATH WAYS

0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

~v

<. I

~ i

FORH 95 LER SCSS DATA 08-30-91 e ********************************************************************

DOCKET YEAR LER NUMBER REVISION DCS NUMBER NSXC EVENT DATE 327 1989 005 1 8906270186 214406 02/10/89

• • • • • • • • • 4'*************************************************4********

y DOCKET:327 SEQUOYAH 1 REGXON: 2 TYPE:PWR NSSS:ME ARCHITECTURAL ENGINEER: TVAX FACILXTY OPERATOR: TENNESSEE VALLEY AUTHORITY SYMBOL: TVA COHHENTS STEP 12: COHP XA TURBINE OVERSPEED FIRST-OUT ANNUNCIATOR STEP 15: COMP HSC - POSITIONER FEEDBACK RRH MATCH-LEST'- CODES FOR THIS LER ARE:

35 HUHAN ERROR 942 UNUSUAL EVENT REPORTABXLITY CODES FOR THIS LER ARE:

13 10 CFR 50.73(a) (2) (iv): ESF actuations.

REFERENCE l ERS:

1 327/84-054 2 327/88-036 3 328/88-023 4 328/88-027 ABSTRACT POWER LEVEL 100X ~ ON 2/10/89 MITH UNIT 1 IN NODE 1r A REACTOR TRIP OCCURRED AT 2036: EST ~ THE TRIP SXGNAL WAS A RESULT OF A STEAH GENERATOR (SG) STEAH FLOW TO FEEDMATER FLOW i4ISHATCH OF GREATER THAN 40X OF THE NOMINAL'ALUE OF STEAN FLOW AT FULL POWER COINCIDENT WITH A LOM SG LEVEL (25X) SIGNAL ON SG LOOP 3 ~ TMO INSTRUMENT HAXNTENANCE (IH) TECHNICIANS MERE IMPLEMENTING WORK REQUEST (MR)-B238429 ON FLOW RECORDER (FR)-2-200/201 "CONDENSER BYPASS/HAKEUP FLOW " THE RECORDER PEN NEEDED TO BE RESTRUNG WHICH REQUIRED IT: TO BE REMOVED FROM THE CASE ~ THE TECHNICIANS FULLY REMOVED THE RECORDER IN ITS CASc WHICH REQUIRED LXFTING- THE POWER SUPPLY LEADS ~ AFTER REXNSTALLATIONr THE TECHNICIANS RETERYiINATED THE POWER SUPPLY LEADSr AT WHICH TINE ONE TECHNICIAN DETERMINED THE TERHINATING LEADS WERE TOO CLOSE TO EACH OTHER THE,TECHNZCIAN INADVERTENTLY SHORTED A SCREWDRIVER BETMEEN THE TERHXNALSr TRIPPING OPEN- BREAKER NO ~ 39 ON 1 20 VAC VITAL INSTRUMENT BOARD I-II WHICH IS THE POWER SUPPLY TO A PLUG HOLD SUPPLYING THE RECORDER THE PLUG HOLD IS ALSO THE COHHON POWER SUPPLY TO THE FLOM INDICATING CONTROl l ERS (FIC) 3 35r 90r AND 103 WHICH CONTROL HAIN FEEDWATER REGULATING VALVES (MFMRVS) FCV-3 35r 90r AND 103 FOR SG LOOPS 1r 3r ANO 4 ~ ROOT CAUSE OF THE REACTOR TRIP SXGNAL 'WAS PERSONNEL ERRORr IN THATr APPROPRIATE PRECAUTIONS McRE NOT TAKEN .IN PERFORMING TERHXNATIONS OF ENERGIZED EQUI PHENT

i FOR H 96 LER SCSS DATA 0 8-3 0-91 .

e ****4'***********************A***********************************A'***

DOCKET YEAR LER NUHBER REVISXON DCS NUMBER NSIC EVENT DATE 327 1990 021 0 9010230284 219736 09/14/90 DOCKET:327 SEQUOYAH TYPE:PMR e 1 REGION: 2 NSSS:ME ARCHITECTURAL ENGXNEER: TVAX FACILITY OPERATOR: TENNESSEE VALLEY AUTHORITY SYMBOL: TVA COMMENTS STEP 28: COYiP MSC INERTIA LATCH~

g WATCH-LIST CODES FOR THIS 20 EQUIPMENT FAILURE LER ARE:

913 UPDATE NEEDEO REPORTABILITY CODES FOR THIS LER ARE:

13 10 CFR 50 73(a) (2) (iv): ESF actuations.

ABSTRACT POWER LEVEL 098K ~ ON SEPTENBER 14/ 1990r*MXTH UNIT 1 IN MODE 1r A REACTOR TRXP OCCURRED, AT 1613 EASTERN DAYLIGHT TINE ~ THE TRIP WAS GENERATED: FROH A LOW-.LOW STEAN GENERATOR MATER 'LEVEL SIGNAL IN LOOP 2 THE LOW LEVEL'AS THE" RESULT OF A FEEDMATER TRANSXENT, XNITIATEO BY THE FAILURE OF A VITAL INVERTER~ THE INVERTER FAII URE OCCURRED AFTER THE COMPLETION OF MAINTENANCE ACTIVITIES ON THE INVCRTER AND DURXNG THE TRANSFER OF THE INVERTER FROM XTS HAINTENANCE POWER SUPPLY TO ITS NORMAL POMER SUPPLY ~ DURING THE TRANSFERs THE XNVERTER OUTPUT VOLTAGE DROPPED TO ZERO BECAUSE OF THE RANDOM FAILURE OF THE INVERTER'S SILICON-CONTROLLED R'ECTIFIERS ~ THIS OEENERGIZEO THE 1-XI VITAL INSTRU4lENT POWER BOARD THE LOSS OF POWER RESULTEO IN THE HAIN FEEDMATER REGULATOR VALVES CLOSING AND THE HAIN FEEDMATER PUMPS DROPPING TO'-MINIMUM SPEED ~ THIS REDUCED FEEDWATER FLOW TO ALL FOUR STEAth GENERATORS PLANT SYSTEHS RESPONDED PROPERLY AND THE SHUTDOWN POSED NO DANGER TO PLANT EMPLOYEES OR THE GENERAL PUBLIC THE UNIT MAS STABILIZED IN, ACCORDANCE WITH PLANT PROCEDURES THE VITAl INVERTER WAS REPAIRED AND RETURNED TO SERVICE ON SEPTENBER 15'990 ~

0 0 0 0 0 0 0 0 0 0 0 0 ~ 0 ~ 0 0 1 ~

0 0 0 0 0 0 0 0 0 0 e N 0

FORM 97 LER SCSS DATA 08-30-91 6 ***********A****A********k******************************************

'DOCKET YEAR LER NUHBER REVISXON OCS NUMBER NSIC EVENT DATE 331 1985 024 1 8509040038 1 97927 07/07/85

• • • • • • • • • • • • • • • • • • • • • • 4**************************************+******

DOCKET-331- ARNOLD TYPE:BMR REGION: 3 NSSS:GE .

ARCHITECTURAL ENGINEER. BECH FACII ITY OPERATOR: IOWA ELECTRIC LIGHT 8 POWER CO SYNBOL: IEL CONHENTS STEP 2: COt1P HSC - DAMPING SPRINGER STEP 3: MODEL - ITE TYPE OD - 4r REFERENCE LER DESCRIBES APRN SPiKING PROBLEHS SIMILAR TO STEPS 8 AND 14 REPORTABXLITY CODES FOR THIS LER ARE:

13 10 CFR 50.73(a) (2) (iv): ESF actuations REFERENCE LERS:

1 331/85-034 ABSTRACT POWER LEVEL 000X ~ ON JULY 7r 1985 TWO REACTOR PROTECTION SYSTEN (RPS) TRIPS OCCURRED DUE TO AN UNATTACHED TRIP COIL INSIDE DANPING SPRING ON AN ESSENTXAL BUS BREAKER AT 1142 HOURSr MITH THE REACTOR IN COLO SHUTDOWN HOOE AND REFUELEO WXTH ALL CONTROL RODS FULLY INSERTEDULL REACTOR PROTECTION SYSTEH TRIP OCCURRED ~ THE RECENTLY NODIFIED (DURXNG THE CURRENT REFUELXNG OUTAGE) FEEDER BREAKER FOR ESSENTIAL BUS iB42 WHICH POMERS THE "B" RPS MOTOR-GENERATOR SET TRIPPED OPEN WHILE BEING LOADEDr- AND A CONCURRENT "E" AVERAGE POWER RANGE HONITOR (APRH) HOHENTARY UPSCALE SIGNAL OCCURRED ~ BOTH STANDBY FILTER UNITS INITIATEO AS DESIGNED ~ THE STANDBY GAS TREATNENT SYSTEH ANO GROUP II THROUGH V ISOLATIONS HAO PREVIOUSLY BEEN INITIATED~

1B42 FEEDER BREAKER WAS FOUND TO HAVE A LOW SUSTAINED CURRENT TRIP THE SETTING WHICH WAS THEN ADJUSTED AT 2230 HOURSr THE 1842 FEEDER BREAKER AGAIN TRIPPED OPEN DURING LOADINGr AND THE "A" RPS lOGXC TRIPPED ON TOO FEW INPUTS TO THE "A". APRHw AS PER DESIGN ~ THE FEEDER BREAKER WAS FURTHER EXAMINED AND FOUND TO HAVE AN UNATTACHED TRIP COil INSIDE DAMPING SPRING ~ THXS MAS DETERMINED TO HAVE BEEN THE CAUSE OF BOTH RPS TRIPS ~ THE SPRING WAS REATTACHED AND OTHER BREAKERS INSPECTEO FOR SIHILAR PROBLEMS THE "E" APRH CIRCUITRY WAS INSPECTED ANO MINOR ADJUSTNENTS COMPLETED

~ 0 0 0 ~ 0 0 0 0 0 0 0 0 0 0 0 0 0 0 r'

0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

FOR H 98 LER SCSS DATA 0 8-3 0-91 .

DOCKET YEAR LER NUMBER REVISION OCS NUMBER- NSIC EVENT DATE 331 1985 031 0 8509040369 196080 08/02/85 DOCKET-331 ARNOLD TYPE.BMR g REGION: 3 NSSS:GE ARCHITECTURAL ENGINEER: BECH FACILITY OPERATOR: IOWA ELECTRIC LIGHT 8 POWER CO SYHBOL: IEL COMMENTS STEP 1: OIL- LEAKEO FROH A CAPACXTOR XNSIOE AN INVERTER STEP 2: MODEL 125 GW 125 60 115'OO R~

REPORTABILITY CODES FOR THIS LER ARE:

14 10 CFR 50 73(a) (2) (v): Event that could have prevented fulfillment of a safety function ABSTRACT POWER LEVEL 093K ~ AT 1108 HRS ON 8-2 THE RCIC TURBINE/PUMP INITXATXON AND CONTROL POWER STATiC XNVERTER MAS REMOVED FROH SERVICEi RENDERING THE RCIC SYSTEN INOPERABLE ~ PER TECH SPEC 3 ~ 5 ~ E ~ 2s A 7 DAY LCO MAS ENTERED~ CONTINGENT UPON THE OPERABILITY OF THE HPCI> THE HPCI SYSTEM SATISFACTORILY COHPLETED ITS OPERABlLXTY TEST ON 8-2-85 THE RCIC SYSTEH STATIC INVERTER PROVIDES 115V. AC POWER TO THE RCIC TURBINE/PUMP INITIATION AND CONTROL INSTRUHENTATXON~ IT RECEIVES ITS XNPUT POWER FROH 125V DC SYSTEN I ~ ON 8-2i THE '125V OC SYSTEM I TROUBLE Al ARM MAS RECEIVED IN THE CONTROL ROOHr FOLLOWED. A FEM SECONDS LATER BY THE CONTROL ROON PANEL 1C04 SMOKE ALARH ANO AN INDICATXON ON THE CONTROL ROON FIRE SYSTEM ANNUNCIATOR PANEL. AN OPERATOR QUICKLY INVESTIGATEDr AND FOUND THE RCIC STATIC INVERTER MAS EMITTING SMOKE ~ A REACTOR LEVEL INDXCATOR POWERED OFF THE INVERTERr FAILEO DOWNSCALE WHEN THE INVERTER POMER WAS SECURED THE SOURCE OF THE SMOKE MITHXN THE RCIC STATIC INVERTER MAS OIL WHICH HAD LEAKED FROM A CAPACXTOR THE INVERTER IS A TOPAZ ELECTRONICS MODEL 125-GW-125-60-115~ MOD ~ R~ THE XNVERTER WAS REPLACED ANO THE RCIC SYSTEM RETURNED TO SERVICE ON 8 2 85 AT 1 825 HRSr ENDING THE 7 OAY LCO A PREVENTXVE MAINTENANCE PROCEDURE IS BEING DEVELOPED AND WXLL BE SCHEDULED ONCE PER REFUEI OUTAGE

0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 v"

J 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

FORM 99 LER SCSS DATA 0 8-30-91 e ***********A**k*****4k'************A*********************************

DOCKET YEAR LER NUMBER REVXSION DCS NUMBER NSIC EVENT DATE 331 1987 013 0 8706150125 204857 05/08/87

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • +*******************************

DOCKET:331 ARNOLD TYPE:BWR REGION: NSSS:GE ARCHITECTURAL ENGINEER: SECH FACILITY OPERATOR:, IOMA El ECTRIC LIGHT L POMER CO ~

SYMBOL: IEL COHHEHTS STEP 9: TYPE CR120A ~

WATCH-LIST CODES FOR THIS lER ARE:

35 HUHAN ERROR REPORTABILITY CODES FOR THIS LcR ARE:

13 10 CFR 50.73(a) (2) (iv): ESF actuations REFERENCE LERS:

1 331/84-008 2 331/85-024 ABSTRACT POWER LEVEL 000'N HAY 8 ANO 9r 198?r WITH ALL FUEL REHOVEO FROM THE VESSEL~ TWO FULL RcACTOR PROTECTION SYSTEH (RPS) TRiPS MERE RECEIVED AN INTERMEDIATE CAUSE OF EACH EVENT IS TOO FEW INPUTS TO THE AVERAGE POWER RANGE MONITORING (APRM) SUBSYSTEM ~ ON=- MAY Br 198?r A FULL RPS TRIP OCCURRED WHEN HOTOR CONTROL CENTER 1B42 MAS DE-ENERGIZED FOR PREPLANNED MAINTENANCE~ PO'WER WAS LOST TO THE '8' RPS LOGIC AS EXPECTED (RESULTING IN A 'B'PS TRIP) ~ HOWEVERS DUE TO OTHER PREPLANNED HAINTENANCE ON THE LOCAL POMER RANGE MONITORING SYSTEH (LPRN)i TOO FEW. INPUTS WERE AVAILABLE TO APRH C ANO AN APRH INOP" TRIP OCCURRED IN THE ~ A~ RPS AS A CORRECTIVE ACTIONr 1842 MAS RE-ENERGIZED AND THE FULL RPS TRIP MAS'ESET THE ROOT CAUSE OF THE EVENT WAS INADEQUATE PRE-WORK REVIEW OF THE CURRENT SYSTEM STATUS ~ ON HAY 9i 1987< A FULL RPS TRIP OCCURRED WHEN THE A RPS MOTOR GENERATOR (NG) SET TRIPPED DUE TO A FAULTY RElAY AND TOO FEW INPUTS WERE AVAILABLE TO APRH D BECAUSE OF LPRH HAXNTENANCE AS A CORRECTIVE ACTIONr THE RELAY MAS REPLACED ON NAY 1 2r 1987 THE ROOT CAUSE OF THE RELAY FAILURE IS UNKNOMN XN BOTH EVENTS THE CONTROL ROD DRIVE HYDRAULIC CONTROL UNITS MERE ELECTRICALLY DISABLED AND NO CONTROL ROD NOTION OCCURRED THERE MAS NO AFFECT ON THE HEALTH ANO SAFETY OF THE PUBLIC THESE EVENTS ARE BEING REPORTED PURSUANT TO 10 CFR 50 ?3 (A) (2) (IV) ~

0 o e e e a e e a e o e e o e e e e o o 0 I

h C'

o e e e e e o e e o o e e e e e e e o 0

FORM- 100 l ER SCSS DATA 08-30-91 DOCKET YcAR LcR NUMBER REVISION OCS NUMBER NSIC EVENT DATE 333 1989 01 6 0 8910250321 215682 09/18/89

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • +

FITZPATRICK e DOCKET:333 REGION: 1 TYPE:BMR NSSS:GE ARCHITECTURAL ENGINEER: SWXX FACILITY OPERATOR: POWER AUTHORITY OF THE STATE OF NY SYMBOL: PNY y COMMENTS STEPS 2s7 FF IX TRANSFER FROH NORMAL TO ALTERNATE POWER SUPPLY'ATCH-LIST CODES FOR THIS LER ARE:

35 HUHAN ERROR 40 PROCEDURAL DEFICIENCY REPORTABILITY CODES FOR THIS LER ARE:

13 10 CFR 50.73(a) (2) (iv): ESF actuations.

REFERENCE LERS.

1 333/84-004 3 333/86-004 4 333/87-006 5 333/87-021 ABSTRACT POMER l EVEI- 000'N SEPTEHBER 1 8r 1 989 WITH THE Pl ANT SHUTDOWN FOR A PLANNED HAINTENANCE OUTAGEr THE POWER SUPPLY FOR THE REACTOR PROTECTION SYSTEN (RPS) (VC) BUS MAS TRANSFERRED FROil NORHAL POWER SUPPLY FROM THE RPS HOTOR GENERATOR SETS (HG) (HG) TO THE ALTERNATE POMER SUPPLY IN ACCORDANCE WITH AN APPROVED PROCEDURE THE TRANSFER MAS NECESSARY TO PERMIT PLANNED MAINTENANCE WORK ON THE RPS HG SETS ALTHOUGH THE CONTROL RODS MERE ALREADY FULLY INSERTEDr A SCRAM SIGNAL WAS AUTOMATICALLY INITIATED DURING THE BUS TRANSFER. THE PROCEDURE PROVIDES FOR TRANSFcR OF THE A RPS POMER WHICH GENERATES A HALF SCRAN OUE TO THE MOMENTARY LOSS OF POMER THIS IS FOLLOWED BY HANUAL RESET OF THE A SIDE HALF SCRAM AND THEN TRANSFER OF THE B RPS POWER FOLLOWED BY MANUAL RESETTING OF THE RESULTANT B SIDE HALF SCRAM THE PROCEDURE DIO NOT PROVIDE GUIDANCE ON THE TINE INTERVAL TO BE ALLOWED BETMEEN BUS TRANSFER ~ 'HE RESET OF THE A SIDE MAS COMPLETED MITHIN FOUR SECONDS OF THE TRANSFER IN THE NEXT FOUR SECONDS THE B SIDE MAS TRANSFERRED ANO A FULL SCRAH RESULTEO ~ THE HAIN STEAN LINE RADIATION MONITOR POWERED FROH THE A RPS BUS WAS NOT YET STABILIZED FOl LOWING THE TRANSFER AND INITIATEO A FALSE HALF SCRAM SIGNAL LESS THAN A TENTH OF A SECOND BEFORE THE 8 SIDE MAS TRANSFERREO THE COHBINATION OF SCRAH SIG!'lALS ON BOTH THE A AND B RPS CHANNELS RESULTED IN FULL SCRAN.

0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 II l 1

)l '

l t

d y

FORM 101 LER SCSS DATA 08-30-91 DOCKET YEAR LER NUHBER REVISION OCS NUHBER NSIC EVENT DATE 334 1980 043 0'007090338 158678 06/05180

• • • • • • • • • • 4k********************************************************

DOCKET:334 BEAVER VALLEY 1 TYPE:PMR RFGION: 1 NSSS.ME ARCHITECTURAL ENGINEER: SMXX FACILITY OPERATOR: DUQUESNE LIGHT CO SYMBOL: OUQ ABSTRACT POWER LEVEL - 000'AUSE - FAILEO POWER SUPPLY ONE SOURCE RANGE CHANNEL MAS LOST DUE TO FAILED HIGH VOLTAGE POWER SUPPLY A NEM POWER SUPPLY MAS INSTALLED AND THE SOURCE RANGE CHANNEL MAS TESTED SUCCESSFULLY BOTH SOURCE RANGE AND INTERHEOIATE RANGE POWER SUPPLIES HAVE FAILEO PREVIOUSLY

o e o e o o e e o o a o a o o e o e o N 0 W

v r ir

'I I

I

[

e o o.e o e o e e o o ~ e o e e e o e e e

FORM 102 LER SCSS DATA 08-30-91

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • 4*****

DOCKET YEAR LLR NUMBER REVXSXON OCS NUMBER NSIC EVENT DATE 334 1980 085 0 8012120535 161838 11/24/80

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • A***********

DOCKET:334 BEAVcR VALLEY 1 TYPE:PMR REGION: 1 NSSS:WE ARCHITECTURAL ENGXNEER: SMXX FACILITY OPERATOR: OUQUESNE LIGHT CO ~

S YM BOL: OUQ g ABSTRACT POMER LEVEL 000K CAUSE NOT OETERHINEO ~ TWO OUT OF FOUR NUCLEAR POWER RANGE INSTRUMENTS WERE INDICATING ZERO PERCENT POWER IT MAS FOUND THAT THE HIGH VOLTAGE PROTECTION CIRCUIT HAD ACTUATED OEENERGIZING THE DETECTORS CONSIDERING THAT THE CIRCUIT IS FOR HIGH VOLTAGE PROTECTIONr THERE HAD TO HAVE BEEN A VOLTAGE SPIKE TO ACTUATE THE CIRCUIT THERE XS NO TRACEABLE XNFORYiATXON TO INDICATE A VOLTAGE INCREASE A CHANGE MAS HADE TO THE SHIFT TURNOVER CHECKLIST TO ADDRESS CHECKING THE INSTRUMENTS EVERY SHIFT ~

0 e e e e o o e e o e e o e e o o o e o e 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

FORM 103 LER SCSS DATA 08-30-91

• • • • fr*****************+**%*%*****%**********************************

DOCKET YEAR LER NUMBER REVISION DCS NUMBER NSIC EVENT DATE 334 1980 096 8012230538 161 841 11/21/80

• • • • • • • • %*********A*************%******************************+****

DOCKET:334 BEAVER VAl LEY 1 TYPE:PMR REGION: NSSS:WE ARCHITECTURAL ENGINEER: SMXX FACILITY OPERATOR: DUQUESNE LXGHT CO ~

SYHBOL: DUQ ABSTRACT POWER LEVEL 020K CAUSE CONTROL SYSTEM FAILURE DURING A POWER INCREASE FROH REACTOR CRITXCAl ITYr A CONTROL PROBLEM WITH THE BYPASS AND MAIN FEED REGULATING VALVES CAUSED A TRANSIENT IN THE REACTOR COOLANT SYSTEH (RCS) THAT COULD NOT BE CONTROLLED WITHIN LIMITS WITH THE PRESSURIZER PRESSURE CONTROL IN MANUAL AUTO CONTROL MAS INOPERABLE PRES SURI ZER PRESSURE MAS BELOW THE T'ECH SPEC LIMIT OF 2220 PSIA FOR ABOUT EIGHT MINUTES AND RCS TAVG WAS LESS THAN THE TECH SPEC LXNIT OF 541F FOR ABOUT TMO HINUTcS NcW CONTROL MODIFICATION FOR FEED BYPASS VALVES MAS NOT PROPERLY TUNED A BAD POWER SUPPLY FUSE CONNECTOR FOR FEED Fl OM XNPUT TO THE 1B STEAtl GENERATOR LEVcL CONTROLLER CAUSED MAIN FEED VALVE TO FULLY OPEN IN AUTO AUTO-MANUAL STATION'OR THE "B" PRESSURIZER SPRAY VALVE FAILED ~ CONNECTIONS AT THE AUTO-MANUAL STATION FOR THE "A" PRESSUPIZER SPRAY VALVE WERE DIRTY CONTROL SYSTEt'lS WERE REPAIRED< TUNED ~

0 e e e e o e o e o e e e e e o e o e o % 0 1'

0 ~ o e e e o ~ ~ ~ ~ o ~ o o o ~ e o o o oJ

FORM 104 LER SCSS DATA 08-30-91 DOCKET YEAR LER'NUMBER REVXSXON'CS NUHBER NSIC EVENT DATE 334 1985- 017 1 8704060198 203808 09/26/85 DOCKET:334 BEAVER VALLEY 1 TYPE PWR REGION: 1, NSSS:WE ARCHITECTURAL ENGINEER: SWXX FACILITY OPERATOR: DUQUESNE LXGHT CO SYMBOL: OUQ COHNENTS STEP 1: MODEL POW01 STEP 2: iFFECT-LX CALIBRATION HOOF FAXLUREr HOOEL AIN 00 'TEPS 7r8 HOOEL 1140 REPORTABILITY CODES FOR THIS LER ARE:

10 10 CFR 50 ~ 73(a) (2) (i): Shutdowns or technical specif ication violations 0

ABSTRACT POMER LEVEL 100% ~ ON 9/26/85- AT 1023 HOURSr WHILE OPERATXNG AT 100%

POWERr THE PLANT VARIABI E COMPUTER (PVC) WAS RETURNED TO SERVICE AFTER HAVING A POWER SUPPLY REPLACED (BAILEY MODEL= NUHBER POW01) XN DATA INPUT NODE (DIN) 3a AT THIS TXHEr THE DELTA FLUX OUT OF BAND ALARM CANE IN THIS WAS DUE TO A FAULT WITHIN THE PVC CAUSING THE NUCLEAR INSTRUMENTATION SYSTEN (NIS) CHANNELS N42 ANO N43 DATA INPUTS TO THE PLANT'S P250 COMPUTER TO READ APPROXIMATELY 20% LOW THE COMPUTER ENGINEER IMMEDIATELY BEGAN TROUBLESHOOTING ANOr AT 111 5 HOURSr DETERMINED THE PROBLEM TO BE IN THE ANALOG INPUT HODULE (BAILCY MODEL AIM 00) IN SI OT 12 OF OXN 3 ~ AT 1120 HOURSr THi OPERATORS ALSO DISCOVERED THAT CONTROL'ANKS C ANO 0 ANALOG ROD POSITION INDICATORS (RPX'S MERE INDICATING INCORRECT ROD POSITION (200 STEPS INDXCATEO AS OPPOSEO TO 228 AND 225 STEPS ACTUAL) THE COMPUTER ENGINEER IHNEOXATEI Y OEENERGIEEO OIN 3 AT 1125 HOURS ~ THIS CAUSED THE RPX'S ANO THE NIS DATA TO THE P250 TO RETURN TO NORHAL THE FAULTED MODULE WAS REPLACED'ND THE DIN RETURNED TO SERVICE ~ IT MAS DETERMINED -THAT MHILE THE PVC IS XSOLATEO FROM SAFETY RELATED EQUIPMENT/PROTECTXON INSTRUHENTATXONr IT IS NOT ISOLATCD FROM SOME NON SAFETY RELATED BUT

~

TECH SPEC REQUIRED EQUIPMENT AN INVESTIGATXON HAS IDENTIFIED WHICH STATION COMPONENTS COULD. BE AFFECTED BY A PVC FAULT CORRECTIVE ACTION HAS BiEN INITIATED"TO PREVENT A WORST CASE PVC FAULT FROM AFFECTING REQUXRCD. COMPONENTS

0 e e e o o e e e a o a e o e o o o e a o 0 1f II 0

'e>

1 i ~ ~ i i i i ~

0 FORM 105 LER SCSS DATA 08-30-91

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • 4***********************

DOCKET YEAR LER NUMBER REVISION DCS NUMBER NSIC EVENT DATE 334 1985 018 0 8511180511 198231 10/04/85

• • • • • • • • • • • • • • • A****************A****************+******************

DOCKET:334 BEAVER VALLEY 1 TYPE:PMR REGION: 1 NSSS:ME ARCHITECTURAL ENGINEER: SMXX FACILXTY OPERATOR: DUQUESNE LIGHT CO ~

5YNBOL: DUQ COMMENTS STEP 2: PSYS HF NORMAL SMITCHGEAR ROON'TEP 5: EFFECT KX XHPROPER FIRING SEQUENCES STEP 1 4 COHP XA PROTECTION CHANEL III BISTABLE LIGHTS REPORTABILITY- CODES FOR THIS LER ARE:

13 10 CFR 50.73(a) (2) (iv): ESF actuations ABSTRACT POWER LEVEL 040X ~ ON 10-4-85 AT 1402 HRSr NUHEROUS ALARMS ANNUNCIATEDr INCLUDING SEVERAl FIRST OUT ANNUNCIATORS AND A VITAL BUS III INVERTER TROUBLE ALARH AT THIS TIt'1Er THE REACTOR HAD NOT TRIPPED AND THE OPERATORSr CHECKING THE CONTROL BOARD INDICATIONSr VE)IFIED THAT VITAl BUS III HAD FAILED PRIOR TO THE VITAL BUS FAILUREr ALL SG LEVEl= CONTROLLERS MERE XN AUTO THE 'A'TEAN GENERATOR LEVEL CONTROLLER REfdAINED IN AUTO AND WENT FULL. OPEN IN RESPONSE TO THE LEVEL ERROR SIGNAL THE WBe SG LEVEL'CONTROLLER WENT INTO MANUAL IN RESPONSE TO THE LOSS OF POWER TO THE CONTROLl ER ~ THE 'C'G l EVEL CONTROLLER WENT INTO THE AUTO-HOLD NODE DUE TO A LOSS OF POMER TO THE AUTO/MANUAL STATION ~ THE VALVE POSITIONS OF THE B AND C SG'S DID NOT CHANGE ~ WHILE ATTEHPTING TO RESTORE SG LEVELSr THE A SG REACHED THE HI HI LEVEL SETPOINT CAUSING A TURBINE TRIPr REACTOR TRXPr AND A FEEDMATER ISOLATION~ THE OPERATORS FOLLOWED THE EHERGENCY PROCEDURES AND STABILIZED THE PLANT . THE VITAL BUS MAS LOST MHEN THE INPUT FUSE TO THE P3 INVERTER FAILED IT HAS BEEN DETERMINED THAT THE FUSE FAILED AS THE'ESULT OF A NISFIRING SILICON CONTROL RECTIFIER THE RECTIFIER WAS NISFIRING BECAUSE OF HIGH ANBIENT TEMPERATURES PRESENT THAT DAY DUE TO AN OFF-NORMAL VENTILATION ARRANGEHENT XN THE SWITCHGEAR ROOHS

0 ~ e a e o e e e o e o e o e o e o ~ o a 0 A~ b I

U 0 0 0 0 0 0 0 0 0 O-N 0 0 0 0 0

FORM. 106 LER SCSS DATA 08-30-91 e ***********/********************************************************

DOCKET YEAR LER NUMBER REVISION DCS NUHBER NSIC EVENT DATE 334 1986 001 0 8603170525 199192 02/10/86 e DOCKET:334 BEAVER VALl EY REGION: 1 1 TYPE:PMR NSSS. WE ARCHITECTURAL ENGINEER: SWXX FACILITY OPERATOR: DUQUESNE LXGHT CO SYMBOL: DUQ COMHENTS STEP 1: COMP RK- INVERTER CABINET STEP 2: CONTROL NODULE CARO 9549-51 STEP 4: EFF IX- MISFIRING ~

MATCH-LIST CODES FOR THIS LER ARE."

941 REPORT ASSOCIATED WITH 10 CFR 50 72 REPORTABILITY CODES FOR THIS LER ARE:

13-. 10 CFR 50 73(a) (2) (iv): ESF actuations ABSTRACT POWER LEVEL OE-ENERGIZED ~

-100% ON THE, l OSS 2/10/86r OF THE AT 1926 HOURSr. 120 VAC VITAL BUS VITAL BUS CAUSED THE 'A'TEAN III GENERATOR CONTROLLER TO OVERFEEDr RESULTING IN A HIGH-HIGH STEAN GENERATOR (75%) TURBINE TRIPr REACTOR TRIPr AND FEEDMATER ISOLATION AT 1927 HOURS ~ THE PLANT WAS STABILIZED IN HOT STANDBY BY 1950 HOURS THE CAUSE OF THE VITAL BUS LOSS WAS A FAILED INPUT FUSE TO THE INVERTER THE VENDOR BELIEVES THE FAILURE TO HAVE-BEEN CAUSED BY A HISFIRING SILICON RECTIFIER CARO EXPOSED TO HIGH TEMPERATURE FOLLOWING THE TRIPr SOURCE RANGE DETECTOR N 31 FAILED AND WAS OECLAREO INOPERABLE'" DURING REPLACENENTr THE INTERMEDIATE RANGE DETECTOR N 35 WAS PLACED ON CLEARANCE'HILE REHOVING THE INSTRUNENT FUSESr THE OPERATORS FAII EO TO BYPASS THE HIGH FLUX TRIP SXGNAL ANO THE REACTOR TRIPPED AT 1727 HOURS ON 2/11/86 PROCEDURES MILL BE CHANGED TO PERNIT A NORE RAPID CHANGE TO VITAL BUS ALTERNATE SUPPLYr- AND CAUTION TAGS MILL. BE POSTED ON FLUX -DETECTORS TO RENIND OPERATORS OF THE TRIP LOGXC ~ THE REACTOR RETURNED TO CRITICALITY AT 1430 HOURS ON 2/12/86

0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 ~ 0 0 0 FORM 107 LER SCSS DATA 0 8-30-91 e ********************************************************************

DOCKET YEAR LER NUMBER REVISION DCS NUHBER NSIC EVENT DATE 334 1987 007 0 8705150325 204407 04/09/87

• • • • 4'**********4****************************************************

DOCKET:334 BEAVER VALLEY TYPE:PWR e REGION: 1 1

NSSS:ME ARCHITECTURAL ENGINEER: SMXX FACILITY OPERATOR: DUQUESNE LIGHT= CO ~

S YH BOL: OUQ CONMENTS STEP 5: COMP XA EVACUATION Al ARH y MATCH-LIST 35 HUHAN CODES ERROR FOR THIS LER ARE:

941 REPORT ASSOCIATED MXTH 10 CFR 50 '2 REPORTABILITY CODES FOR THIS LCR ARE:

13 10 CFR 50 73(a) (2) (iv): ESF actuations.

ABSTRACT POWER LEVEL 100K ON 4/9/87 AT 0940 HOURS DURING NORMAL FULL POMER OPERATIONS A l'1AIN FILTER BANK ACTUATION OCCURRED ~ MHILE PERFORNING MAINTENANCE ON A HULTXPOINT RADIATION RECORDERr A METER AND CONTROL REPAIRMAN (MCR) MOMENTARILY SHORTED THE RECORDER POWcR SUPPLY CAUSING A 120VAC VITAL BUS 2 SPIKE ~ THiS CAUSED A SPIKE ON THE ~ A'RAIN AUXILIARY BUILDING VENTXLATION RADIATION ilONTORr INITIATING Fl OM THROUGH- THE HAIN FXl TER. BANK THE VENTILATION OPERATORS REScT THE RADIATION MONITOR.- ANO INITIATED ACTIONS TO RETURN THE SYSTEH TO NORMAL OPERATION ~ THE CAUSE FOR THIS EVENT WAS PERSONNEL ERROR 8 "CAUSE BOTH INSTRUHENT AND CONTROL (ISC) AND OPERATIONS PERSONNEL FAILFD TO REALIZE THAT RECORDER DEENERGIZATION COULD HAVE BEEN EASILY ACCOMPLISHED PRIOR TO HAINTENANCE XNXTXATION THIS cVENT XS REPORTABLE IN ACCORDANCE MITH 10 CFR 50 ~ 72 8 2. XI ANO 10 CFR 50 73 A ~ 2 IV~ TO

'PREVENT FUTURE OCCURRENCES OF THIS TYPES'OTH IRC AND OPERATIONS PERSONNEL'ILL BE TRAINED ON THE PROPER USE OF THE TERMINAL BLOCK POWER DISCONNECT PINS AVAILABLE FOR RECORDER DEENERGXZATION TERMINAL BLOCK POMER DISCONNECT PIN LOCATIONS MILL ALSO BE POSTED AT THE REAR OF THE RADXATION MONITOR RACKS CONTAINING THE .RECORDERS THERE MERE NO SAFETY INPLICATIONS TO THE PUBLIC BECAUSE THE SYSTEH FUNCTIONED AS DESIGNED UPON RECEIPT OF A HIGH-HXGH RADIATION SIGNAL FOR THE AUXILIARY BUILDING VENTILATION SYSTEM

It 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 i 0 lt e e e e o e e e e e o e e o e o o o e e 0

FORM 108 LER SCSS DATA 08-30-91 e **********************0******+**************************************

DOCKET YEAR LER NUHBER REVISION OCS NUMBER NSXC EVENT DATE 334 1987 018 1 8712010026 207264 10/22/87

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • Bred**********A******************A DOCKET:334 BEAVER VALLEY 1 TYPE:PWR REGION: 1 NSSS:WE ARCHITECTURAL ENGINEER: SMXX FACXLXTY OPERATOR: DUQUESNE LIGHT CO ~

SYNBOL: OUQ COHHENTS STEP 3: CAUSE AX CHART PAPER REPLACEHENT ACTIVITY FOR THE MATT RECORDERS COMP HSC CHART PAPER DRIVE UNIT ELECTRICAL POMER CORD PLUG STEP 4:=MODEL KF-44 ~

MATCH-LIST CODES FOR THIS LER ARE:

34 DESIGN ERROR OR INADEQUACY 31 ACCXDENTAL ACTION CODES f OR. THIS LER ARE:

g REPORTABILITY 13 10 CFR 50.73(a) (2) (iv): ESF actuations y ABSTRACTLEVEL POWER 100% ON 10/22/87 AT 0457 HOURSr DURING NORNAL FULL POWER OPERATIONr A iIAIN FXLTER BANK AND CONTROL ROON PRESSURIZATION ACTUATION'CCURRED>> MHILE CHANGING THE GENERATOR WATT RECORDER CHART PAPERr THE REACTOR OPERATOR HOMENTARXLY SHORTED THE RECORDERS POWER SUPPLY CAUSING -A 120 VAC VITAL BUS 2 SPIKE ~ THIS CAUSED A SPIKE ON THE "A" TRAXN AUXILIARY BUXLDING VENTILATION RADIATION NONITOR INITIATING FLOW THROUGH THE HAIN FILTER BANK AND A SPIKE ON THE "B" CONTROL ROON RADIATION HONITOR INITIATING CONTROL ROON PRESSURIZATION ~

THE OPERATORS RESET THE RADIATION HONITORS ANO INITIATEO ACTIONS TO RETURN THE SYSTENS TO NORNAL OPERATION THIS EVENT MAS CAUSED BY THE DESIGN OF THE RECORDERS ~, PAPER DRIVE PLUG WHICH HAS INSUFFXCIENT PROTECTION AGAINST THE PLUG CONTACT TOUCHXNG GROUND THERE MERE NO SAFETY IMPLICATIONS RESULTING FROM THIS EVENT SINCE THE SYSTENS FUNCTIONEO AS DESiGNED ON RECEIPT OF A HIGH-HIGH RADXATION SIGNAL

0 e o e e o e e o o o e o o o e o e e o e 0 j R, 0 0 '0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

FORM 109 LER SCSS DATA 08-30-91 e ***********I********************************************************

DOCKET YEAR LER NUMBER REVISiON= DCS NUHBER NSIC EVENT DATE 335 -1980 058 0 8012020567 161710 10/19/80

• • • • • • • • • • • • • 4 ***********************************************+******

LUCIE

~ DOCKET:335 ST 1 REGION: 2 TYPE.PMR NSSS:CE ARCHITECTURAL; ENGINEER. EBAS FACILITY OPERATOR: FLORIDA. POWER 8 LIGHT COMPANY SYMBOL: FPL ABSTRACT POWER LEVEL, 100% CAUSE - OPEN BREAKER- DUE TO BACKFIT MORK ERRORS TARGET A-16 ALARMED (DG 1B FAILURE TO START) THE PYROMETER THAT GIVES THE ALARN MAS FOUND DEENERGIZED ~ DURING INVESTIGATION~ THE OG LOCKOUT A1 ARN WAS INADVERTENTLY ACTUATED THE LOCKOUT ALARM MAS RESET ANO THE DIESEL MAS STARTED TO VERXFY OPERABILITY. MHILE TROUBLESHOOTING THE PYROMETER POWER LOSSr THE FEEDER BREAKER FROM NCC 1 B7 WAS FOUND OP EN HCC-iB7 SUPPLIES POWER PANEL 112 WHICH SUPPLIES POWER TO VARIOUS COMPONENTS THE FEEDER BREAKER MAS CLOSED THE OPEN FECDER BREAKER TO PP-112 HAS BEEN ATTRXBUTED TO BACKFXT WORK BEING PERFORMED IN THE VICINXTY OF THE BREAKER

0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 @

FORM 110 LER SCSS DATA 08-30-91

• • • • • • • • • • • A********************************************************

DOCKET YEAR LER NUMBER REVXSION DCS NUHBER NSXC EVENT DATE 338 1980 047 0 8006090361 158645 05/23/80

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • 4*****

DOCKET:338 NORTH ANNA 1, TYPE:PWR e REGION: 2 NSSS:ME ARCHITECTURAL ENGINEER: SWXX FACILITY OPERATOR: VIRGXNXA ELECTRIC POMER CO S YMBOL: VEP COMMENTS STEP 2: CAUSE XX NORMAL OPERATIONS STEP 7: CAUSE XX - REQUIRED FOR TESTING ABSTRACT POWER LEVEL - 000X ~ CAUSE LOSS OF VITAL BUS ~ AT 0146'ITH THE UNIT AT HOT STANDBYr ACTUATION Or THE EMERGENCY CORE COOLING SYSTEH MAS INXTIATED ON HIGH STEAN LINE FLOW SIGNAL COINCXDENT MITH LO-LO T-AVE THIS MAS AN INADVERTENT, ACTUATION (EQUIPMENT PERFORHED THE INTENDED INJECTION FUNCTION) ANO. THE REACTOR MAS ALREADY SHUTDOMN THE HIGH STEAN FLOW SIGNAL RESULTED FROM A LOSS OF VITAL BUS 1-IXI THE LO-LO T-AVE SIGNAL RESULTEO FROM THE TRIPPING OF AL'L THREE REACTOR COOLANT PUMPS WHICH MAS'EQUXRED OUE TO THE LOSS OF VITAL BUS 1-IXI~

CORRECTIVE ACTION MAS FOR THE CONTROL'OON OPERATORS TO PERFORN THE APPLICABLE EHERGENCY PROCEDURE AND RETURN- THE PLANT TO STABLE CONDITIONS

0 e e4 e o o o o e e e e o o a o o e e o e 0 I

f 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

FOR N 111 08-30-91 .

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • 4*******************************

DOCKET YEAR LER. NUMBER REVISION DCS NUMBER NSIC EVENT DATE 338 1980 078 1 8010140436 163519 09/08/80

• • • • • • • • • • • • • 4'******************************************************

DOCKET:338 NORTH ANNA 1 TYPE:PMR REGION: 2 NSSS:WE ARCHITECTURAL ENGINEER: SWXX FACILITY OPERATOR: VIRGINIA ELECTRIC POWER CO SYNBOL: VEP COMMENTS STEP 7: ISYS SW UNKNOWN STRUCTURESJ COMP HEI FLOW ORIFICE REFERENCE LER 338/80-080 DESCRIBES EVENTS RELATED TO INVERTER FAIlURE ~

REFERENCE I ERS:

1 338/80-080 ABSTRACT POWER LEVEL OOOX CAUSE - .INCORRECT GOVERNOR SETTING THE GOVERNOR VALVE FOR THE STEAN DRIVEN AUXILIARY FEEDWATER PUHP MAS FOUND TO BE IN THE TRIPPED CONDITION RENDERING THE PUHP INOPERABLE THE GOVERNOR VALVE. APPARENTLY TRIPPED DUE TO PUMP OVERSPEED FOLLOWING A UNIT TRIP THE CAUSE OF THE OVERSPEEO WAS APPARENTLY AN INCORRECT GOVERNOR SETTING ~ THE GOVERNOR VALVE MAS RESETr THE GOVERNOR VALVE SETTING ADJUSTED TO ITS PROPER SETTING AND THE PERIODIC TEST ON THE AUXILIARY FEEOMATER PUMP WAS COHPLETELY SATISFACTORILY ~

e a o o e e e o e e e e o o o o e e o 4 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

FORH 112 LER SCSS DATA 08-30-91

• • • • • • • • • • • A*************A******************************************

DOCKET YEAR LER NUHBER REVISION DCS NUHBER NSIC EVENT DATE 338 1980 080' , 8010140423 163521 09/08/80

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • A'*

DOCKET:338 NORTH ANNA TYPE:PMR e REGION: 2 1

NSSS.ME ARCHITECTURAL ENGINEER: SWXX FACILITY OPERATOR: VIRGINIA ELECTRIC POWER CO SYi~1BOL: VEP g COHHENTS REFERENCE LER 338/80-078 DESCRIBES EVENTS SUBSEQUENT TO THE SCRAH LERS:

y REFERENCE 1.- 338/80-078 ABSTRACT POMER LEVEL - 100K CAUSE UNKNOWN POWER TO THE 120 VOLT ABC VITAL BUS 1-IV WAS LOST CONTRARY TO TECH SPEC ~ THE SUPPLY BREAKER FOR THE INVERTER WHICH SUPPLIES POWER TO VITAL BUS IV. MAS FOUND IN THE OPEN POSITION HOW THE BREAKER BECAME OPEN COULD NOT BE DETERMINED POWEP.

TO THE VITAL BUS MAS RESTORED VIA THE INSTALLED TRANSFORMER ~ POWER SUPPLY TO THE VITAL BUS WAS LATER SWITCHED TO THE INVERTER

0 o e e e o e o o o o e o o e a o o o o o 0 FORM 113 LER SCSS DATA 08-30-91

• • • • • • • • • • • • • • • • • • • • • • • • • • • • 4***************************************

DOCKET YEAR LER NUNBER REVISION DCS NUMBER NSIC EVENT DATE 338 1 986 009 0 8606250041 1 99801 05/31 /86

• • • • • • • • • • • • • • • • • • • • • 4**********************************************

DOCKET:338 NORTH ANNA 1 TYPE:PMR REGXON: 2 NSSS:ME ARCHITECTURAL ENGINEER: SMXX FACILITY OPERATOR: VIRGINIA ELECTRIC POWER CO ~

SYNBOL: VEP COMMENTS STEP 1: EFF IX-VOLTAGE AND CURRENT FLUCTUATIONS STEP 10: CAUSE LX-UNOERCOMPENSATXON STEP 4: COHP RLX-RELAY WHICH SENSES BREAKER POSITION (F OR RCS PUMP)

REPORTABILXTY CODES FOR THIS LER ARE:

13 10 CFR 50 ~ 73(a) (2) (iv): ESF actuations.

ABSTRACT POWER LEVEL 100% ~ AT 21 31 HOURS ON HAY 31r 1 986r UNIT 1 TRIPPED FROM 100% POWER (HOOE 1) AS A RESULT OF A LOSS OF POWER TO THE 120 VAC VITAL BUS (VB) 1-1 ~ VITAL BUS 1-1 POWERS THE RELAY WHICH SENSES THE BREAKER POSXTION-.OF ~A'EACTOR COOLANT PUMP (RCP) ~ WHEN THIS RELAY WAS O'E ENERGIZEDr A REACTOR 'TRIP SIGNAL MAS GENERATED AS A RESUI T OF

~

THE REACTOR PROTECTION SYSTEM SENSING THE 'A'CP BREAKER OPEN COINCIDENT MITHREACTOR POWER GREATER THAN 30% (P-8) ~ REACTOR COOLANT PUHP 'A'IO NOT ACTUALLY TRIP DURING THIS EVENT. TMO PARALLEL 480/120 VAC TRANSFORNERS MERE BEING USED AS AN ALTERNATE POWER SUPPLY TO VB 1-1 DUE TO VOLTAGE ANO CURRENT FLUCTUATXONS ON THE BATTERY CHARGER VITAL. BUS 1-1 MAS DE-ENERGIZED WHEN ONE OF THE 480/120 VAC TRANSFORMERS FAILED~ POMER WAS RESTORED TO VB. 1-I BY TRANSFERRING BACK TO THE NORMAL POWER SUPPLY (INVERTER) THE REACTOR MAS RETURNED TO CRITICALITY AT 0743 HOURS ON JUNE 1r 1986 AND Pl ACED ON LINE AT 0432 HOURS ON JUNE 2r 1986 THIS EVENT IS REPORTABLE PURSUANT 10CFR50 73(A) (2) (IV).

0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 i 0 III P N

M I

,0 o o o a e e o e o o e o e o o e e o o e 0

FORM 114 LER SCSS DATA 08-30-91

• • • • • • • • • • • • • • • • • • • • • • • • A**A**************A'*************************

DOCKET YEAR LER NUMBER REVISION DCS NUMBER NSIC EVENT DATE 339 1 983 036 0 8305250384 183213 04/29/83 e DOCKET:339 NORTH ANNA 2 REGXON: 2 TYPE:PWR NSSS:WE ARCHITECTURAL ENGItiEER: SWXX FACILXTY OPERATOR: VIRGINXA ELECTRIC POWER CO.

SYMBOL: VFP g ABSTRACT ON APRIL 29m 1 983r WXTH UNIT 2 IN MODE 6r A LOSS OF VITAL BUS 2 1

~

RESULTED XN LOSING RESIDUAL HEAT REMOVAL (RHR) FLOW FOR LESS THAN ONE MINUTE WHEN. ONE OF TWO XN SERIES RHR SUCTION VALVES (MOV-2?00) CLOSED IN ADOITIONr ONE OF TWO SOURCE RANGE CHANNELS (N 31) AND THE CONTAXNMENT PARTICULATE ANO GASEOUS RADIATION MONITORS (RM-259 AND 260) WERE DE-ENERGXZED SINCE THE VITAL BUS WAS PROMPTLY REENERGXZEO AND THE DE ENERGIZED. EQUIPMENT PROilPTLY RESTORED ~ THIS EVENT XS REPORTABLE PURSUANT TO TECH SPEC 6 9 1 9 B THIS EVENT OCCURRED AS MAINTENANCE PERSONNELWERE PERFORMING A GROUND ISOLATXON PROCEDURE FOR 125 VOLT D C ~ BUS W-I AND SHORTEO THE TEST LEADS AS LOADS WERE BEXNG TRANSFERRED TO ANOTHER 0 C BUS THIS EVENT CAUSED THE INPUT-BREAKER TO 2-1 120 VOLT A C VITAL. BUS TO OPEN AND DE-ENERGIZED THE ABOVE LISTED EQUIPMENT THE VITAL BUS. AND DE-ENERGIZED EQUIPMENT WERE RESTORED AND NORMAL OPERATION RESUMED

0 e 0 0 0 0 0 0 0 0 0 0 0 0 0 0 l

~ ~

r 1 f' 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

,FORM 11 5 LER SCSS DATA 08-30-91

• k******k*kk*k*kkk*kk*k*k***k*kkk****k***kkk**kk*k***kkk**kkkk*kkkkk DOCKET YEAR LER NUMBER REVISION DCS NUMBER NSIC EVENT DATE 341 1987 048 9 8812200285 211 535 10/08/S7

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • kk**

Y DOCKET:341 FERMI 2 TYPE:BMR e REGXON: 3 NSSS:GE ARCHITECTURAL ENGliVEER: SI XX FACILITY OPERATOR: DETROIT EDISON CO SYMBOL: DEC COMMENTS STEP 38: DI X - 10 STEP 44: DI X-11 ~ STEP 4 8: DI X 12 ~ STEP 49: COMP XI LOOSE PARTS MONITOR STEP 51: DE X-13 STEP 54: OX X - 14 ~ STEP 58: OI X 15 ~ STEP 62: Dl X - 16 STEP 64: DI X 17

~

MATCH-LIST CODES FOR THIS LER ARE:

40 PROCEDURAL DEFICIENCY 942 UNUSUAL EVENT 913 UPDATE'EEOEO REPORTABXLXTY CODES FOR THIS LER ARE:

10 10 CFR 50 ~ 73(a) (2) (i): Shvtdowns or technical specification violations.

REFERENCE LERS:

1 341/85-01S 2 341/85-036 3 341/85-037 4 341/85-040 5 341/86-004 6 341/86-008 7 341/86-010 8 341/86-022 9 341/86-039 10 341/87-029 11 341/87-044 ABSTRACT POWER LEVEL OOOX DETROIT EDISON COMMITTED TO PERFORM A REVIEW OF TECH SPEC SURVEELLANCES AS PART OF ITS TECH SPEC XMPPOVEMENT PROGRAM LER 87-048 DESCRIBES THE REPORTABLE FINDXNGS OF THXS ONGOING PROGRAM WHICH CONSTITUTE VIOLATIONS OF THE TECH SPECS THIS LER ES UPDATED ON AN AS REQUERED BASIS XT MAS DETERMINED THAT THE LOM PRcSSURE COOLANT XNJECTION (LPCI) LOGXC FUNCTXONAL TEST SURVEILLANCE PROCEDURE OID NOT SPECIFY TESTING OF EIGHT TINE DELAY RELAYS THE RELAYS WERE RECALIBRATEO AND ROUTINE CALEBRATION OF THESE RELAYS EN ACCOROAI'ICE WITH THE PREVENTIVE NAXNTENANCE PROGRAM Wil L BE ESTABLESHEO BY DECEMBER 31r 1988 ET WAS DETERMINED THAT THE SERVICEr TURBINE ANO RADMASTE BUILDING VENTXLATXON RADIATION MONITORXNG SYSTEMS CHANNEL FUNCTIONAL TEST SURVEiLLANCE PROCEDURES DEO NOT SPECIFY TESTING OF NON-RUNNING SUPPLY AND EXHAUST FANS THE SYSTEMS MERE SUCCESSFULLY TESTED ANO SURVEILLANCE PROCEDURES MERE REVISEO IT MAS DETCRMENED

~ THAT AN ELECTRICALLY SUPERVISED FIRE DOOR AND THE ALARM SET POINTS FOR THE OFF-GAS RADIATION MONITORS MERE NOT,ADDRESSED IN THEIR ASSOCIATED SURVEILLANCE PROCEDURES THE ABOVE EQUIPMENT MAS RETESTEO ANO ASSOCIATED SURVEILLANCE PROCEDURES MELL BE REVISEO BY DECEMBER 31r 1988

a e e e o e o e o e e e e .o o o e e e e N 0 k

I~

0 e e o e o e e e e o e e e e o o o e o 0

FORM 116 LER SCSS DATA 08-30-91

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • A*************************

DOCKET YEAR LER NUMBER REVISION DCS NUMBER NSIC EVENT DATE 346 1 980 013 0 8003110685 155444 02/08/80

• • • • • 4'*******************4******************************************

DAVIS-BESSE e DOCKET:346 REGION:

1 3

TYPE:PMR NSSS:BW ARCHITECTURAL ENGXNEER: BECH FACILITY OPERATOR: TOt FDO EDISON CO SYMBOL: TEC ABSTRACT

' POWER LEVEL - OOOX CAUSE BLOWN FUSE AT 2300 HOURS METH A REACTOR STARTUP IN PROGRESSr XT WAS NOTED THAT CONTROL ROD 5 11!S ABSOLUTE POSITION XNDICATION (API) WAS NOT RESPONDING THE REACTOR STARTUP MAS TERMINATED AND ALL GROUP 5 CONTROL RODS MERE DRIVEN IN THE REACTOR STARTUP MAS TERMINATED BECAUSE THE UNIT COULD NOT NEET THE LIHITING CONDITIONS OF T S ~ THE CONTROL ROD NEVER DEVIATED FROM ITS INTENDED POSITION iN THE GROUPS ONLY THE API MAS FAULTY FUSE F14 IN THE POSXTION REFERENCE PANEL FOR CONTROL ROD 5-11'S VAC API SUPPLY MAS BLOMN FUSE F14 MAS REPLACED AND THE API NODULE VOLTAGES WERE CHECKED SATISFACTORILY CONTROL ROO 5-11 MAS WITHDRAWN TO VERXFIY THE APX MAS TRACKING~ THE API MAS DECLAREO OPERABLE ANO THE REACTOR STARTUP MAS COMMENCED

~ ~

FORM 117 LER SCSS DATA 08-30-91, DOCKET YEAR LER NUMBER REVISION DCS NUMBER NSIC EVENT DATE 346 1980 029 0 8005060178 158860 04/19/80 DOCKET:346 DAVIS-BESSE 1 TYPE:PWR REGION: 3 NSSS:BW ARCHITECTURAL ENGXNEER: BECH FACXLITY OPERATOR: TOLEDO EDISON CO SYMBOL: TEC COMMENTS WATCH 975 - RHR PUMP SUCTION TRANSFERRED TO EMERGENCY SUMP DURING SAFETY INJECTION ~ THIS LED TO AIR BINDING OF PUMP ALSO GRAVITY FEED OF RWST WATER TO SUMP OCCURR ED

~

MATCH-LIST CODES FOR THIS LER ARE:

975 POSSIBLE SIGNIFICANT EVENT REFERENCE LERS:

1 346/79-005 ABSTRACT POWER LEVEL - 000Ã ~ CAUSE BREAKER OPENS DUE TO HIGH VIBRATION~

BREAKER HBBF2 WAS OPENED BY A GROUND FAULT RELAY WHICH PROBABLY ACTUATED FROM MECHANICAL VIBRATXON DUE TO CONSTRUCTION PERSONNEL IN THE ROOM TWO ESSENTXAL BUSES WERE LOST DUE TO THE ELECTRICAL LINEUP FOR MAINTENANCE SAFETY FEATURES ACTUATION RESULTED THE DECAY HEAT PUMP HAD TO BE'HUTDOWN TO STOP THE INJECTXON AIR IN THE PXPING DELAYED THE PUMP RESTART+ REACTOR. COOLANT TEMPERATURE ROSE ABOVE THE 140F SPECIFXCATXON ~ THE DECAY HEAT PUMP WAS V NTED AND RESTARTED AT A MAXIMUM REACTOR COOLANT SYSTEM TEMPERATURE OF 170F ~

0 0 0 0 0 0 0 0 0 0 0 0 0 W N

,0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

FORM 118 LER SCSS DATA 08-30-91

• • • A****%'**A'****A******************************************A**%*****

DOCKET YEAR LER NUMBER REVISION OCS NUMBER NSXC EVENT DATE 346 1980 064 1 8012120512 160365 08/22/80 DOCKET:346 DAVIS-BESSE 1 TYPE PWR g REGION: 3 NSSS:BW ARCHITECTURAL ENGINEER: SECH FACILITY OPERATOR: TOLEDO EDISON CO SYMBOL: TEC COMMENTS SUBSEQUENT EVENT OCCURRED 08/23/80 LERS:

g REFERENCE 1 346/79-009 2 346/80-056 y ABSTRACTLEVEL POWER OOOO CAUSE FUSE FAILURES ON 8/22/80 AT 1446 HOURS AND ON 8/23/80 AT 0922 HOURS> THE STATION EXPERIENCED A LOSS OF ESSENTIAL INSTRUMENT AC PANEL Y2 THE P.ESULT WAS THE DE-ENERGIZATXON OF SAFETY FEATURES ACTUATION SYSTEM (SFAS) CHANNEL '2r REACTOR PROTECTXON SYSTEM (RPS) CHANNEL 2 ANO STEAMi AND FEEOWATER RUPTURE CONTROL- SYSTEMi (SFRCS) CHANiNEL 2 WHICH CAUSED THE CONTAINMENT RADIATION STRING FOR SFAS CHANNEL 2 TO FAIL" THE CAUSE WAS THE FAILURE OF THE YV 2 XNVERTER OUTPUT FUSEr HOWEVER/ THE EXACT CAUSE OF THE FUSE FAILURE HAS NOT BEEN DETERMXNEO

0 0

FORM 119 LER SCSS DATA 08-30-91 e ********************************************************************

DOCKET YEAR LER NUMBER REVXSION DCS NUMBER NSIC EVENT DATE 346 1982 029 0 8207190259 175395 06/08/82

• • • • • • • • • • A******************************************A**********A***

DOCKET:346 DAVIS-BESSE 1 TYPE:PWR REGION: 3 NSSS:BW ARCHITECTURAL ENGINEER: SECH FACXLITY OPERATOR: TOLEDO EDXSON CO ~

SYMBOL: TEC ABSTRACT THE ESSENTIAL XNVERTER YV2 FAILEO WHICH DEENERGIZED 120VAC ESSENTIAL BUS 'Y2 AND SUBSEQUENTLY SOURCE RANGE DETECTOR NI-1 SINCE NI-2 HAD ALREADY BEEN DEENERGIZEO FOR DETECTOR REPLACEMENTr THE STATXON WAS LEFT WITHOUT AN OPERABLc SOURCE RANGE DETECTOR THE STATION ENTEREO THE ACTION STATEMENT OF TECH SPEC 3 ~ 3 1 THE SHUTDOWN MARGIN WAS CALCULATED AND FOUND TO STILL Bc WITHIN ACCEPTABLE LIMITS~ THE CAUSE OF THE OCCURRENCE WAS A COMPONENT FAILURE WITHIN THE REGULATED RECTIFIER YRF2 WHXCH NORMALLY SUPPLIES DC POWER TO INVERTER YV2 Y2 WAS ENERGIZED FROM ITS ALTERNATE SOURCE AND NI1 WAS RETURNED TO OPERABILITY BY 1500 HOURS'ORK REVEALED THAT THE VOLTAGE CONTROL MODULE YRF2 HAD FAILED IN SUCH A WAY THAT THE REC) XFIER COULD ONLY CARRY THE LOADED INVERTER WITH THE AID OF THE ALTERNATE DC SUPPLY

rg 0

FORM 120 LER SCSS DATA 08-30-91 e *********A***A**********************************************k*******

DOCKET YEAR LER NUHBER REVISXON OCS NUMBER NSXC EVENT DATE 346 1982 046 1 8301240081 178922 09/09/82

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • 4*****+***********

DOCKET:346 DAVIS-BESSE 1. TYPE: PWR REGION. 3 NSSS:BW ARCHITECTURAL ENGINEER: BECH FACILiTY OPERATOR: TOLEDO EDISON CO SYMBOL: TEC y REFERENCE 1

LERS:

346/81-.011 . 2 346/81-027 ABSTRACT OPERATORS RECEXVED A HXGH DECAY HEAT (OH) FLOW ALARM THE DH FLOM INDICATOR FOR DH PUMP 2 READ GREATER. THAN 4200 GPH IT MAS VERIFIED THAT DH PUMP 2 MAS NOT,. RUNNING ~ HIGH PRESSURE INJECTION (HPI) FLOW INDICATION. FOR HPI PUMP 2 ALSO SHOWED HIGH FLOW WITH NO PUHP RUNNING HPI AND LPI/OH FLOW INDXCATION FOR TRAIN 2 WAS DECl ARED XNOPERABLEr AND THE STATION ENTERED. THE ACTION STATEMENT OF TECH SPECS 3 5 2 ~ THE

'-24 VDC POWER SUPPLY FOR THE BUFFER CARDS FAILED CAUSXNG THE INDICATION TO FAIL HIGH ~ THE CAUSE OF THE'OWER SUPPLY FAXl URE IS UNKNOWN AT THIS TIME~ THE POWER SUPPI Y WAS REPl ACED UNDER MMO IC-414-82 HPI AND LPI TRAIN '

FLOW XNDXCATXON MAS DECLARED OPERABLE AT 1 544 HOURS ON 9/9/82r REHOVING THE STATION FROM THE ACTION STATEMENT THE POWER SUPPLY WXLL BE RETURNED TO THE MANUFACTURER FOR FAILURE ANALYSIS~ '

e

~ 4 J

c lk 7 0'Asm'-;-.Vw~x~ ~ 44%4

FOR hl 1 21 LER SCSS DATA 08-30-91

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • 4**************************

DOCKET YEAR LER NUhlBER REVISION'CS NUNBER NSIC EVENT DATE 346 1983 045 1 85071 201 54 195425 08/27/83

• • • • • • • • k *******************************P *********** 4***************

DOCKET:346 DAVIS-BESSE 1 TYPE:PMR g REGION: 3 NSSS:BM ARCHITECTURAL ENGINEER: BECH FACILiTY OPERATOR: TOLEDO EDISON CO SYtlBOL: TEC REFERENCE LERS:

1 346/80-056 ABSTRACT ON 8 27 83 AT 0955 HRSr MHILE HOOKING UP LEADS FOR ST 5030 ~ 09r RPS RESPONSE TihlE TESTei AN INC TECHNICIAtJ SHORTED TEST LEADS TOGETHER CAUSING AN ESSENTIAL BUS FUSE TO BLOMr DEENERGXZING 120V AC ESSENTIAl Y1: BUS ~

THIS HADE SOURCE RANGE FLUX HONXTOR NT. 2 XNOPERABLEr PLACING THE UNIT IN THE ACTION'TATEhlENT OF TECH SPEC 3 9 12 REDUNDANT hlONITOR NI-1 MAS OPERABLE THROUGHOUT THIS OCCURRENCE ~ DUE TO THE CLOSE CONFXNENENT OF THE TERilINAL BOARD LOCATIONS'HE INC TECHNICIAN INADVERTENTLY SHORTED THE TEST LEADS TOGETHER NX-2 MAS DECLARED OPERABLE AT 1250 HRS ON 8-27-83 ~ DESIGN hlODIFXCATIONS HAD PREVIOUSLY BEEN HADE TO THESE TERNINALS TO PRECLUDE RECURRENCE A PROCEDURE HODXFICATION MAS MADE TO ST 5030 09 TO t<AKE ISC TECHNXCIANS hlORE CONSCIOUS OF THE POTENTIAL OF SHORTING OUT ESSENTIAL BUSES

3 4 lt ~ '

I E'

FORM 122 LER SCSS DATA 08-30-91

• • • • • • • • • • • A'********************************************************

DOCKET YEAR LER NUMBER REVXSION DCS NUMBER NSXC EVENT DATE 348 1980 029 0 8006050036 158641 04/30/80

• • • • • • • • • • • • • +*********************A********************************

DOCKET:348 FARLEY TYPE:PWR e 1 REGION: 2 NSSS WE ARCHITECTURAL ENGINEER: BESS FACILiTY OPERATOR: ALABAMA POWER CO S YMBOL: AP C ABSTRACT POWER LEVEL 100% CAUSE LOOSE CIRCUIT BREAKER TERMINAL SCREW AT 1546r INTERMEDIATE RANGE NIS CHANNEL N-35 WAS DECLARED INOPERABLE DUE TO LOSS OF POWER ~ WHILE PERFORMING A WIRING VERIFICATIONs POWER TO N-35 WAS INADVERTENTLY INTERRUPTED DUE TO A LOOSE TERMINAL SCREW ON A 120 VOLT VITAL AC PANEL 1A MOLDED CASE BREAKER. THE WIRE WAS RECONNECTED AND N-35 WAS RETURNED TO SERVICE AT 1551 CONNECTIONS IN THE PANEL 'WERE VERIFXED SECURE ~

'LL OTHER

E

~ < E C

FORM 123 LER SCSS DATA 08-30-91

• • • • • • • • • • • A***********A********************************************

DOCKET YEAR LER NUMBER REVISION DCS NUNBER NSXC EVENT DATE 348 1 983 021 0 8306100270 183268 05/06/83 DOCKET:348 FARLCY 1. TYPE:PMR REGION: 2 NSSS:ME ARCHITECTURAL ENGINEER: BESS FACILITY OPERATOR: ALABANA POWER CO>>

SYMBOL APC ABSTRACT AT 0739 ON 5/6/83r THE DIGITAL ROO POSITION INDICATION (DRPI) SYSTEM MAS DECLARED INOPERABLE MHEN POWER SUPPLY BREAKCR HBI 7R OPENED ~ TECH SPEC 3>>1>>3 ~ 2i XiV PART~ REQUIRES THE DRPI SYSTEM TO BE OPERABLE ~ TECH SPEC ACTION STATEMENT R QUIRENENTS MERi HCT NO DEFINITIVE CAUSE COULD BE DETERMINED ~ THE BREAKER t1AY HAVE BEEN INADVERTENTLY TRIPPED BY PERSONNEL OPENING A ClOTHING LOCKER IN CLOSE PROXIMITY TO THE BREAKER ~ FOLLOMING A SHIFT TO AN ALTERNATE POWER SUPPLY~ THE DIGITAL ROD POSITION INDICATION WAS RESTORED AT 0747 ON 5/6/83 THE LOCKER WAS MOVED TO AN AREA NOT IN PROXIMITY TO THE SUBJECT BREAKER THE INCIDENT WAS DXSCUSSED WITH PERSONNEL MHO MERE ASSIGNED DUTIES IN THE VICINITY OF THE BREAKER AT THE TINE OF OCCURRENCE AN INSPECTION OF OTHER AREAS'N THE PLANT FOR SITUATIONS WHERE A SIMILAR EVENT COULD OCCUR REVEALCD NO POTiNTIAL PROBLENS

e a a e o e o o o o e e e e e e e o o %

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FORM 124 LER SCSS DATA 08-30-91 m

DOCKET YEAP, LER NUi4IBER REVISION DCS NUHBEP, NSIC EVENT DATE 348 1987 004 0 8702260585 202834 01/22/87

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • %*********%***+**********************

DOCKET:348 FARl EY 1. TYPE:PWR REGiON: 2 NSSS:WE ARCHITECTURAL ENGINEER: BESS FACILITY OPERATOR: ALABAMA POWER CO+

S YH BOL: APC g COHHENTS STEP 1: CAUSE AX CALIBRATION AND FUNCTIONAL TESTING OPERATIONS STEP 7:

NOOEL -.5 KVAr 60 HZ WATCH-LIST CODES FOR THIS LER ARE:

20 EQUIPMENT FAILUR 40 PROCEDURAL DEFICIENCY REPORTABILITY CODES FOR THXS LER ARE:

13 10 CFR 50.73(a) (2) (iv): ESF actuations.

REFERENCE LERS:

1 364/85-012 ABSTRACT POMER LEVEL 100X~ AT 1218 ON 1:22 87r WITH, THE UNIT OPERATING AT

~

1001i POWERr A REACTOR TRXP OCCURRED DUE TO HIGH FLUX RATES INDICATED BY POWER RANGE NUCLEAR INSTRUHENTATION CHANNELS N-41 AND N-42 ~ THE HIGH FLUX RATE ON N-42 MAS DUE TO TESTING WHICH WAS IN PROGRESS AT THE TINE ~ THE HIGH FLUX RATs ON N-41 MAS CAUSED BY THE" FAILURE OF THE 1A INVERTER MHICH SUPPLIES POWER TO N-41 ~ TESTING OF N-42 MAS COMPLETED AND N-42 WAS RETURNED TO SERVICE THE BACKUP POWER SUPPLY FOR N-41.

WAS PLACED INTO SERVICE THE UNIT RETURNED TO POWER OPERATION ON 1-23-87 SUBSEQUENTLYr THE 1A INVERTER WAS TESTEO AND FOUR Bl OWN FUSES WERE REPLACED ~ NO CAUSE FOR THE BLOMN FUSES COULD BE FOUND ~

THE INVERTER WAS RETURNED TO SERVICE

0 FORM 125 LER SCSS DATA 08-30-91

• • • • • • +*************************************************************

DOCKET YEAR LER NUMBER REVXSION DCS NUMBER NSIC EVENT DATE 348 1987 007 0 8704290331 204233 04/05/87

• • • • • • • • • • • k%*******************************************************

~ DOCKET:348 FARLEY 1 REGION: 2 TYPE:PMR NSSS:ME ARCHITECTURAL ENGXNEER: BESS FACILITY OPERATOR: ALABANA POWER CO SYMBOL: APC 0 COHHENTS STEP 5: PART NO. WL23706 WATCH-LIST CODES FOR THXS LER ARE:

?0 EQUIPMENT FAILURE REPORTABILITY CODES FOR THIS LER ARE:

13 10'FR 50.73(a) (2) (iv): ESF'ctuations ABSTRACT POWER LEVEL - OOOX>> AT 2238 ON 4-5-87'ETH THE UNIT XN NODE 3 (HOT STANDBY) AND TH'2 FULL LENGTH CONTROL RODS INSERTED+ A REACTOR TRIP SIGNAL MAS GENERATEO WHEN SOURCE RANGE NUCLEAR INSTRUMENT N-31 FAILED HIGH ~ THE SHUTDOWN BANKS XNSERTED ON THE REACTOR TRIP SiGNAL ~ UPON INVESTXGATXONr IT MAS FOUND THAT THE DETECTOR FOR N 31 HAO FAILED~

THE DETECTOR WAS REPLACED ANDr FOLLOWING TESTXNGr N 31 MAS RETURNED TO SERVICE

i%

R 4

FORM 126 LER. SCSS DATA 08-30-91,

/

DOCKET YEAR l.ER NUMBER REVISION DCS NUMBER NSIC EVENT DATE 352 1984 039 0 8502010074 192700 1 2/21 /84

• • • • • • • • • • • A'******************************************************A'*

DOCKET:352 LIHERXCK TYPE:BMR e 1 REGXON: 1 NSSS:GE ARCHITECTURAl ENGXNEER: SECH FACXLXTY OPERATOR: PHIl.ADELPHIA ELECTRIC CO SYNBOL: PiC COMMENTS STEP 1: CAUSE AX FOR TESTING CODES FOR THIS LER ARE:

g REPORTABILXTY 13 10 CFR 50 73(a) (2) (iv): iS"; actuations.

LERS:

g REFERENCE

1. 352/84-005

~ ABSTRACT POWER LEVEl OOOX ON 12 21 84r A TEHPORARY LOSS OF POMER TO AN UNINTERRUPTIBLE AC ELECTRICAL PANEL CAUSED THE REACTOR MATER CLEANUP SYSTEM AND THE REACTOR ENCLOSURE AND REFUEL FLOOR VENTXLATXON SYSTEMS TO ISOLATE ~ THE LOSS OF POWER ('B'PS LOGIC)i COHBINED WITH CONCURRENT SURVEILLANCE TESTING ON THE ~ A~ RPS LOGXCr Al SO RESULTED IN THE GENERATION OF A FULL SCRAH SIGNAL~ THE CAUSE OF THE EVENT MAS AN OVERVOI TAGE CONDITION FROM THE 'B'PS STATIC INVERTER AFTER THE EVENTr THE SCRAH SIGNAL WAS RESET AND ALL AFFECTED SYSTEMS WERE RETURNED TO NORNAL OPERATION

0 FORM 127 LER SCSS DATA 08-30-91 DOCKET YEAR LEP. NUMBER REVISION DCS NUMBER NSXC EVENT DATE 353 1991 003 0 9104250285 221862 03/24/91

• • • • • • • • • • • • • • • • • • • A********************************************A***

DOCKET:353 LXMERICK' TYPE:BWR REGION 1 NSSS:GE ARCHITECT URAl ENGINEER,: BECH FACILITY OPiRATOR: PHILADELPHIA ELECTRIC CO SYMBOL: PEC COMMENTS STEP 4. COMP 1XZ REDUNDANT REACTIVITY CONTROL SYSTEM SELF TFST SYSTEM ~

STEP 5: COMP XA - RRCS OUT OF SERVICE AND CHANNEL ACTIVATED ANNUNCIATORS.

MATCH-LXST CODES FOR THIS LER ARE:

35 HUMAN ERROR 40 PROCEDURAL DEFICIENCY 32 COMMUNICATION PROBLEM 941 REPORT ASSOCIATED METH 10 CFR 50 72 REPORTABILITY CODES FOR THIS LER ARE:

13 10 Cf R 50 73(a) (2) (iv): ESF actuations O REFERENCE LERS:

1 352/84-002 2 352/85-046 3 352/86-011 4 352/86-020 5 352/90-026 ABSTRACT POWER LEVEL OOOO ON 3/24/91r AN INADVERTENT REDUNDANT REACTIVXTY CONTROL SYSTEM (RRCS) ALTERNATE ROD INSFRTXON (ARI) ACTUATION MAS I

INITIATcD FROM DIVISION LOGIC DURING THE APPLICATION OF A TEMPORARY CIRCUIT ALTERATION (TCA) TO SUPPORT UNIT 2 OUTAGE WORK ON DIVISION

'HE I AND IIX INSTRUMENTATION ARX XNXTXATION CAUSED THE SCRAM INLET AND OUTLET VALVES TO OPEN AND CAUSED THE SCRAM DISCHARGE VOLUME (SDV)

VENT ANO DRAXN VALVES TO CLOSE ~ REPOSITIONING OF THESE VALVES CAUSED LEVEL IN THE SDV TO INCREASE TO XTS HIGH LEVcL TRIP SETPOXNTr CAUSING A REACTOR PROT'ECTION SYSTEM (RPS) FULL SCRAM ACTUATION~ THERE WAS NO CONTROL ROD MOTION DURING THIS EVENT SINCE ALL CONTROL. RODS MERc FULLY INSERTED PRIOR TO THE EVENTS THE ARI AND THE RPS ACTUATcD AS DESIGNED DURING THIS EVENT ~ THE CAUSE OF THIS EVENT MAS PERSONNEL ERROR RESULTING IN LESS THAN ADEQUATE COMMUNICATION DURING INSTALLATION OF THE TCAr AN RRCS RESET MAS REQUESTED WHEN BOTH RRCS AND ARI RESiTS MERE REQUIRED ~ -

PROCEDURAL GUIDANCE MILL BE OEVELOPiD TO ENSURE BOTH RRCS AND ARX RESETS ARE PERFORMED FOR THESE ROUTINE DIVISIONAL TCAS THAT ARE APPLIED DURING OUTAGES THE LXCENSEO OPERATOR REQUALXFICATION TRAXNING MODULE FOR RRCS WILL BE REVXSEO TO INCLUDE MORi DETAILED XNFORMATION ON RRCS AND ARX LOGIC RESETS

i' FORM 128 LER SCSS DATA 08-30-91 e ********************************************************************

DOCKET YEAR LER NUHBER 'EVISION DCS NUMBER NSIC EVENT DATE 354 1986 025 0 8607080014 199997 05/30/86 DOCKET:354 HOPE CREEK TYPE:BWR e REGXON: 1 NSSS:GE ARCHITECTURAL ENGINEER: SECH FACILITY OPERATOR: PUBl IC SERVICE ELECTRIC & GAS CO S Yb'I BOL: P E G COMMENTS STEP 1: EFFECT IX- UNSPECIFIED ELECTRICAL- FAILURE ~

REPORTABILITY CODES FOR THIS LER ARE:

13 10 CFR 50.73(a) (2) (iv): ESF actuations ~

ABSTRACT POWER LEVEL 000'N 5-30-86 AT 0525 THE CONTROL ROON CONSOLE INDICATION FOR THE IN SERVXCE "A" SERVICE WATER PUHPr "A" SAFETY AUXILIARY COOLING (SACS) PUMP AND THE "A" ENERGENCY DIESEL GENERATOR WAS LOST ~ IN ADDITXON THE "A" SACS LOOP TRIPPED ON AN ERRONEOUS EXPANSION TANK LOM LEVEL SIGNAL AND THE "A" TECHNICAL SUPPORT CENTER (TSC) CHILLER'HE "A" CONTROL ROON CHILLER AND THE "C" TURBINE y BUILDING CHXLLER TRIPPED ON LOW COOLXNG MATER FLOM ~ THIS RESULTED IN THE AUTO START OF THE "8" TSC CHILLER AND "8"'ONTROL ROON CHIl LER ~

THE ROOT CAUSE OF. THE EVENT WAS A HUMAN FACTORS DESXGN DEFICIENCY INVOLVING THE ELECTRICAL CABINET WHICH HELD COMPONENTS THAT CONTROLLED CONSOLE AND EXPANSION TANK LEVEL INDICATIONS AT THE TIME OF THE INCIDENTr 2 X&C TECHNICIANS MERE INSTALLXNG A NEW POWER SUPPLY DIRECTLY ABOVE AN XN-SERVICE SUPPLY ALTHOUGH CARE WAS TAKEN TO AVOID GROUNDING OR "BUHPING" OF SUPPLIES' TECHNICXAN HEARD A BREAKER TRIP AND SAW THE LED EXTINGUISH ON THE XN-SERVICE SUPPLY THE XHHEDIATE RESPONSE BY THE OPERATORS WAS TO STABILIZE THE ASSOCIATED EQUXPHENT ~

CORRECTIVE ACTIONS WILL INCI UDE THE REVXEW OF WORK PRACTICES AND THE CONSIDERATION OF A DESIGN CHANGc TO THE ELECTRXCAL CABINETS

0 0

FORM 129 LER SCSS DATA 08-30-91

• • • • • • • • • • • • • • • • • • • • • • • • • • A*****************************************

DOCKET YEAR LER NUMBER REVISION OCS NUHBER NSXC EVENT DATE 354 1987 015 8710020168 206510 02/13/87

~ ********************************************************************

1 DOCKET:354 HOPE CREEK 1 TYPE:BMR REGION: 1 NSSS:GE.

ARCHXTECTURAL ENGXNEER: BECH FACILiTY OPERATOR: PUBLIC SERVICE ELECTRIC 5 GAS CO SYMBOL: PEG V

COHHENTS STEP 4: COMP XA - EXCESSIVE PUMP OPERATING TIME ALARM~

MATCH-LIST CODES FOR THIS lER ARE:

60 SPURIOUS/ UNKNOWN CAUSE REPORTABILITY CODES FOR THXS LER ARE:

13 10 CFR 50 73(a) (2) (iv): ESF actuations.

REFERENCE LERS:

1 354/86-012 2 354/ 86-01 6 3 354/86-017 4 354/86-047 5 354/86-074 6 354/86-075 ABSTRACT POMER LEVEL 000K AN AUTO-ISOLATION OF THE CONTROl ROOH VENTILATION (CRV) SYSTEM OCCURRED MHEN A SPURIOUS CHANNEL D HIGH RADIATION SIGNAL WAS RECEXVEO MHEN CRV XSOLATEOr THE "B" CONTROL ROOM EMERGENCY FILTRATION (CREF) UNIT AUTO-STARTED A CHECK OF THE RADIATION MONITORING SYSTEM (RMS) DETERMINED THAT RADIATION lEVCLS HERE NORMAL AT THE TIHE THE SIGNAL WAS GENERATED ~ AS A RESULT THE SIGNAL WAS CONSIDERED SPURXOUS AND THE CRV SYSTEM MAS RETURNCD TO SERVICE AND "B" CREF UNIT =HAS STOPPED ~ SUBSEQUENT INVESTXGATIOiV REVEALED THAT AN ISC FUNCTIONAL TEST (FT) MAS BEING PERFORMED ON THE DRYMELL LEAK DETECTION HONITORING SYSTEM AT THE TIME THE ISOLATION OCCURRED AND THAT THE ISOLATION PROBABLY RESULTED FROH A VOLTAGE SPIKE GENERATED DURING THE PERFORMANCE OF THE FT ~ ATTEMPTS TO REPCAT THE CIRCUMSTANCES MHXCH CAUSED THE CRV RADIATION MONITOR TO ALARM HAVE PROVEN UNSUCCESSFUL'ND AS A RESULTS NO DEFINITE CORRECTXVE ACTIONS CAN BE ASSIGNED ~

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FORM 130 LER SCSS DATA 0 8-30-91 DOCKET YEAR LER NUMBER REYISXON DCS NUMBER NSIC EVENT DATE 361 1 986 029 3 8909120059 215156 12/10/86

• • • • • • • • • • • • • • • • • +**********A*************W*************************

I DOCKET:361 SAN ONOFRL 2 REGION:

ARCHITECTURAL ENGXNEER: BECH 5

TYPE:PWR NSSS:CE FACILITY OPERATOR: SOUTHERN CALIFORNIA EDISON CO ~

SYMBOL: SCE y COMMENTS STEP 2: COMP XS STATIC TRANSFER SMiTCH STEP 8: MODEL NO. 140718 ~ STEP 1 5: GAMMA-METRICS NO 8?

REPORTABILITY CODES FOR THIS LER ARE:

13 10 CFR 50 73(a) (2) (iv): ESF actuations ABSTRACT POWER LEVEL 100% ON 12/10/86 AT. 1037r WITH UNIT 2 AT 93X POWERr THE TURBINE TRIPPEO DURING A POWER INTERRUPTION TO THE TURBINE GOVERNOR CONTROL SYSTEM (TGCS)r CAUSING A REACTOR TRXP ~ THE STEAM BYPASS CONTROL SYSTEM (SBCS) DID NOT INITIALLY ACTUATE AND A MAIN STEAM SAFETY VALVE BRIEFLY ACTUATED THE TRIP RECOVERY PROCEEDEO NORMALLY ALTHOUGH START UP CHANNEL B FAILEDr ANO PLANT PROTECTXON SYSTEM (PPS) CHANNEL I A'" DID NOT TRIP ALL OTHER REQUIRED SAFETY RELATED EQUIPMENT FUNCTIONED AS DESXGNEO AND THERE WERE NO SAFETY NON-1E 120'VAC LOAD MAS BEING TRANSFERREO FROM THE

'ONSEQUENCES'HE NON-1E UNXNTERRUPTIBLE POWER SUPPLY (UPS) It)VERTER TO THE ALTERNATE SOURCE A PROCEDURAL STEP TO DEFEAT THE AUTOMATIC RETRANSFER CIRCUIT WAS NOT PERFORMEDr CAUSING THE LOAD TO TRANSFER BACK TO THE PRXMARY SOURCE ~ MHEN THE UPS INVERTER WAS DISCONNECTED UNDER LOAD THE AUTOMATIC TRANSFER TO THE ALTERNATE SOURCE DID NOT OCCUR IN TIME TO PREVENT THE TRIP 'HE UPS IS EQUIPPED WITH AN AUTOMATIC TRANSFER SWITCH MHICH AUTOMATICALLY TRANSFERS THE LOAD TO THE ALTERNATE SOURCE ON LOSS OF INVERTER OUTPUT VOLTAGE THE TRANSFER SMITCH MAS FOUND TO OPERATE CORRECTLYr HOWEVERr THE ENSUING TRANSIENT IS BELIEVED TO HAVE CAUSED. THE TRIP THE EVENT RESULTED FROM THE FAILURE TO FOLLOW THE PROCEDUREr ADDITIONALIYr THE JOB DIO NOT RECEIVE THE CORRECT LEVEL OF ATTENTION BY OPERATIONS PERSONNEL ~

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FORM 131 LER SCSS DATA 08-30-91

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DOCKET YEAR LER NUMBER REVXSION OCS NUMBER NSXC EVENT DATE 362 1982 003 0 8301170367 181744 11/27/82

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • A*****i'e***********

DOCKET:362 SAN ONOFRE 3 TYPE.PWR REGION: 5 NSSS:CE ARCHITECTURAL ENGINEER: SECH FACILITY OPERATOR: SOUTHERN CALIFORNIA EDISON CO ~

SYMBOL: SCE ABSTRACT WITH THE PLANT IN MODE 6r CHANNEL 2 STARTUP MONITOR 3JI 006 WAS OBSERVED TO HAVE LOST VISUAL INDICATION AND. WAS DECLARED INOPERABLE ~

THE REDUNDANT MONITOR REMAINED OPERABLE ANO NO CORE ALTERATIONS OR POSXTIVE REACTIVITY CHANGES TOOK PLACE DURING THXS EVENT ~ THE MONITOR INOPERABILITY WAS ATTRIBUTABLE TO LOSS OF POWER WHEN MOTOR CONTROL CENTER (MCC) 3BNr WAS TAKEN OUT OF SERVXCE THE MCC AND THE MONITOR WERE RETURNED TO SERVICE ON NOVEMBER 27r 1982 ~ RESPONSIBLE OPERATXONS PERSONNEL HAVE BEEN DIRECTED TO'ERFORM A MORE DETAILED REVIEW OF THE IMPACT OF DE-ENERGIZING MCC'S ~ AOOITIONALLYi THE INFORMATION SUCH AS LOAD LISTS FOR MCC'S WILL BE REVIEWED FOR ADEQUACY OF DETAIL AND REVISEO XF NECESSARY

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FORM 132 LER .SCSS DATA 08" 30-91 DOCKET YEAR LER NUMBER REVISION DCS NUMBER NSIC EVENT DATE

. 362 1985 026 2 8703060082 202871 10/16/85 DOCKET:362 SAN ONOFRE 3 TYPE:PWR O REGION: 5 NSSS: CE ARCHXTECTURAL ENGINEER: BECH FACILXTY OPERATOR: SOUTHERN CALIFORNIA EDXSON CO ~

SYMBOL: SCE g COMMENTS STEP 1: CAUSE AX - CALIBRATION AND. MODIFICATIONS~ STEP 8: D-COL N CALIFORNIA OFFXCE OF EMERGENCY SERVICES RECEIVED AN ALARMr "EMERGENCY COOLING SYSTEM" AND NOTIFIED PLANT OPERATORS ~ STEPS 13r27: COHP XA - STATUS ALARMS FOR RADIATION MONITORS.

CODES FOR THIS LER ARE:

g REPORTABXLiTY 9 10 CFR 50 36(c) (2): Limiting conditions for oper ation.

10 10 CFR 50 73(a) (2) (i): Shutdouns or technical specification violations ABSTRACT POWER LEVEL OOOX 'N 10/16/85 AT APPROXIHATELY 1104 - WITH UNIT 3 IN MODE 6 AND A CONTAINMENT PURGE IN PROGRESSr CONTAINMENT PURGE ISOLATION SYSTEM (CPIS) TRAIN 'A4 HONITOR 3RE-7804 MAS ISOLATED FROM THE CONTAINHENT SY CLOSURE OF THE SAMPLE XSOI ATION VALVES TO THE MONITOR~ THIS CLOSURE MAS CAUSED BY DE-ENERGIZATXON OF THE POWER SUPPLY TO THE ENGINEERED SAFETY FEATURE ACTUATION SYSTEH (ESFAS)r TRAIN 'A'UXILiARY RELAYS TECHNICAL SPECIFICATIONS REQUIRE THE

~ MONITOR TO BE XN SERVICE DURING CONTAINMENT PURGE AND ONE TRAIN OF CPIS TO* BE OPERABLE DURING REFUELING OPERATIONS IN THE CONTAINMENT~

DUE TO THE ISOLATION OF 3RE 7804r A PORTION OF CPXS TRAIN A MAS NOT IN SERVICE FROM 1104 UNTXL 1345 MHEN POWER MAS RESTORED TO THE RELAYS ~

NORMALLY TMO DC POWER SUPPLIES ARE OPERATED IN PARALI EL AND SUPPLY POWER TO HALF OF THE ESFAS TRAIN A AUXILIARY RELAYSr ONLY ONE OF THE TMO SUPPLICS IS REQUIRED FOR OPERATION IT IS POSTUI ATED ONE OF THE POWER SUPPLIES HAD BEEN DE ENERGIZED DURING MODIFICATION WORKr WHEN WORK MAS LATER CONTINUED ON 10/16/85r THE REMAXNING POWER SUPPLY MAS DE-ENERGIZED CAUSING A LOSS OF POMER TO THE AUXILIARY RELAYS'NE HALF OF THE TRAIN A ESFAS AUXILIARY RELAYS DE ENERGIZEDr ACTUATING THOSE COMPONENTS WHICH HAD NOT BEEN REMOVED FROM SERVICE FOR THE OUTAGE ~

FORM 133 LER SCSS DATA 08-30-91 e *********** k ********************************************************

DOCKET YEAR LER NUMBER REVISION OCS NUMBER NSXC EVENT DATE 362 1987 011 .2 8806100192 209515 06/21/87

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • +*********

DOCKET:362 SAN ONOFRE 3 TYPE:PWR REGION: 5 NSSS: CE ARCHITECT UR Al ENGINEER: BECH FACILITY OPERATOR: SOUTHERN CALIFORNIA EDISON CO SYMBOL: SCE COMMENTS WATCH 975 - BECAUSE OF THE LOW PRESSURIIER LEVEL AND THE LOW RCS TEMPERATURE/PRESSUREr A SMAl L STEAM BUBBLE MAY HAVE EXISTED IN THE RPV HEAD FOR ABOUT 30 SECONDS'TEPS 4r5 COMP XA REACTOR TRIP OVERRIDE ALARMS STEP 33: MODEL NE13DH l"ATCH LIST CODES FOR THIS LER AR 20 EQUIPMENT FAILURE 35 HUMAN ERROR 975 POSSIBLE SIGNIFICANT EVENT REPORTABILITY CODES FOR THIS LER ARE:

13 10 CFR 50.73(a) (2) (iv): ESF actuations.

REFERENCE LERS:

1 361/85-049 2 362/85-006 ABSTRACT POWER LEVEL 100% ~ ON JUNE 21r 1987 AT 0258r WITH UNIT 3 IN MODE 1 AT 100% POWER THE REACTOR AUTOMATICALLY TRIPPEO ON LOW STEAM GENERATOR

- (SG) WATER-LEVEL THE LOW SG- WATER LEVEL WAS CAUSED BY AN INTERMITTENT LOSS OF POWER IN ONE PHASE OF A. 120 VAC NON-1E INSTRUMENT BUS WHICH RESULTED IN THE INABILITY TO CONTROL MAIN FEEDWATER AND THE CONSEQUENT REDUCTION IN SG WATER LEVELS LEVEL CONTXNUEO TO DECREASE TO THE LOW LEVEL REACTOR TRIP AND EMERGENCY FEEOWATER ACTUATION SET POINT ~

FOLLOWING THE REACTOR TRXPr 120 VAC NON 1 E POWER RETURNED AND MAIN FEEDWATER FLOW RESUMED THE CWATER LEVEL IN SG E088 INCREASED FROM THE LOW LEVEL TRXP SET POINT TO ABOVE THE HIGH LEVEL Al ARM SET POINT AS e OPERATORS WERE IMPl EMENTXNG THEIR IMMEDIATE POST-TRIP ACTIONS IN ACCORDANCE WITH EMERGENCY OPERATING XNSTRUCTIONS (EOIS) THIS RESULTEO IN COOLING DOWN OF THE REACTOR COOLANT SYSTEM (RCS) TO BELOW THE SAF TY INJECTXON ACTUATION SIGNAL (SIAS) SET POINT ~ THE 120 VAC POWER MALFUNCTION WAS DETERMINED TO BE DUE TO A LOOSE BOLT CONNECTING THE "B" PHASE OF INSTRUMENT BUS 01 TO THE MAIN BUS BARS OF THE NON-1E UNINTERRUPTABLE POWER SUPPLY (UPS) MAIN DISTRIBUTION SWITCHBOARDr WHICH RESULTED IN INTERMITTENT 'LOSS OF CIRCUIT CONTINUITY THIS WAS EVIDENCED BY ARCING AND PITTING AT THE CONNECTIONr ANO CONFIRMED BY SUBSEQUENT DUPLICATION OF POWER INTERRUPTIONS WHEN THE ASSEMBLY WAS MANUAlLY MOVED

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FORH 134 LER SCSS DATA 08-30-91 e ***********4********************************************************

DOCKET YEAR LER NUMBER REVISION OCS NUMBER NSIC EVENT DATE 362 1989 001 ~

3 8912260017 216246 01/06/89 DOCKET:362 SAN ONOFRE 3 TYPE:PMR REGION: 5 NSSS:CE ARCHITECTURAL ENGINEER: BECH FACILITY OPERATOR: SOUTHERN CALXFORNIA EDISON CO SYMBOL: SCE a

COMMENTS STEP 6 ITEN NO ~ TX801r PART NO ~ 312744 ~ STEP 16 CAUSE AX FOR TESTING ~

STEP 7: PART NUHBER 23778 STEP 5: COMP HSC - IRON CORE MATCH-LIST CODES FOR THIS LER ARE:

20 EQUIPMENT F'AILURE 35 HUMAN ERROR REPORTABILITY CODES FOR THIS LER ARE:

13 10 CFR 50 ~ 73(a) (2) (iv): ESF actuations REFERENCE LFRS:

1. 361/87-004 2 362/87-011 ABSTRACT POWER LEVEL 100' AT 2335 ON 1/6/89 WITH UNIT 3 AT 98X POMERr REACTOR TRIPPED ON LOM SG LEVEL AFTER A PARTIAL l OSS OF NON-1E UiNINTERRUPTIBLE POWER SUPPLY (UPS) POWER OCCURRED WHICH CAUSED FEEOWATER REGULATING VALVES.TO REDUCE FLOM TO SG E089 ANO.RESULTED IN

~ ACTUATION OF EHERGENCY FEEDWATER TO SG E089 ~ EHERGENCY FEEDWATER TO SG E088 ALSO ACTUATED DUE TO THE RESULTING LEVEL "SHRXNK" XN SG E088r MHICH IS EXPECTED FOLLOMXNG A TRIP FRON HIGH POWER ~ SINCE STEAM HEAT REHOVAL FROM THE SGS WAS GREATER THAN NORMAL 'T BYPASS CONTROL SYSTEN MAS IN HANUAl TO PERFORH TURBINE VALVE TESTINGr RESULT OF LOMER SG TEHPFRATUREr RCS PRESSURE DECREASED BELOW SIAS 2336r AS A SETPOINT (1806 PSXA) r ~ RESULTING XN AN SXAS ACTUATION~ THERE MAS NO SAFETY XNJECTXON FLOW INTO RCS SINCE RCS PRESSURE REMAINED ABOVE SHUTOFF HEAD OF INJECTION PUMPS ~ 2 OF 3 NON-1E UPS 'HASES WERE LOST BECAUSE OF A COHHON FAULT IN THE ASSOCIATED INVERTER'S'ONSTANT VOLTAGE TRANSFORHER (CVT) OUTPUT MINOXNGS ~ A TEHPORARY JUMPERr MHXCH.

HAD NOT BEEN PROPERLY REYiOVED DURING PREVIOUS HAINTENANCEr WAS FOUND BETWEEN UPS UNGROUNDED NEUTRAL AND GROUNDS THERE MERE 2 PRIOR FAILURES OF A CVT IN THE SAHE INVERTER AFTER INSTALLATION OF THE TEMPORARY JUHPERr BUT NEITHER RESUl TEO IN A SAFETY SYSTEM ACTUATION~

CAUSE OF TRANSFORMER FAXLURE WAS THE BREAKDOWN OF INSULATXON BETMEEN ENERGIZED MINDINGS AND GROUNDED IRON CORE ~

FOR H 135 LER SCSS DATA 08-30-91

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DOCKET YEAR LER NUHBER REVISION DCS NUHBER NSIC EVENT DATE 364 1981., 004 0 8104200314 165203 03/14/81

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DOCKET:364 FARLEY 2 TYPE:PWR REGION- 2 NSSS:WE ARCHITECTURAL ENGINEER: BESS FACILITY OPERATOR: ALABAHA POMER APC CO'YHBOL:

ABSTRACT AUDIBLE COUNT RATE IN THE CONTAINHENT WAS LOST AS A RESULT OF A BLOMN FUSE IN THE 2D XNVERTER ~ THE 120 VOLT VITAL INSTRUHENT PANEL 2D MAS TRANSFERRED TO AN ALTERNATE SUPPLY AND THE BLOWN INVERTER FUSE MAS REPLACED

La 0

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FORM 136 LER SCSS DATA 08-30-91 DOCKET YEAR l ER NUMBER REVISION DCS NUMBER NSIC EVENT DATE 366 1 984 030 3 85071 60039 1 96055 1 1/1 5/8 4

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • A*******it*********************+**

DOCKET:366 HATCH 2 TYPE:BWR REGION: 2 NSSS:GE ARCHITECTURAL EtlGINEER: SECH FACILITY= OPERATOR: GEORGIA POWER CO ~

SYMBOL: GPC REPORTABXLITY CODES FOR THIS LER ARE:

g 10 10 CFR 50 ~ 73(a) (2) (i): Shutdowns or technical specification violations ABSTRACT POWER LEVEL 099X ON 11-15-84 THE PLANT'S SURVEILLANCE COOROXNATOR DETERMIl'lED THAT THE MONTHLY CHANNEl FUNCTIONAL TEST HAD NOT. BEEN PERFORMED ON THE MAIN STEAtl LXNE XNSTRUMENTATION FOR THE tlONTHS OF SEPT ANO OCT THXS MONTHLY.TcST IS REQUIRED BY TECH SPECS TABLE 4~ 3~2 1 i ITEM D ~ r AS WELL AS THE MAIN STEAt'l l INE TUNNEL TEMPERATURE INSTRUMeNT FTSC'ROCEDURE (HNP-2-3107) THIS TEST WAS PREVIOUSLY REQUXRED EVERY 18 MONTHSr HOWEVERr TECH SPECS AMENDMENT NUMBER 39 CHANGED THE 18 MONTH INTERVAL TO A 30 OAY INTERVAL THE PLANT~S SURVEILLANCE COORDINATOR DID NOT ADJUST THE SURVEILLANCE THXS EVENT IS THE RESULT OF PERSONNEL ERROR ~ ON 11 29. 84 FREQUENCY'ONSEQUENTLYr DURING A QA AUDITS PLANT PERSONNEL DETERMINED THAT REACTOR VESSEL PRESSURE INSTRUMENTATION ANO REACTOR VESSEL SHROUD WATER LEVEL INSTRUMENTATXON WERE NOT RECEIVING MONTHLY CHANNEL CHECKS AND QUARTERLY CHANNEL CALIBRATIONS PER TFCH SPECS TABLE 4 3 AND 4 ~ 3 ~ 6 ~ 4 1w ITEM 2r RESPECTIVELY~

' '-1i ON 3 13 85 IT WAS DETERMINED ITEM 1 THAT THE 'RIMARY CONTAXNMENT HYDROGEN RECOMBINER FUNCTIONAL TEST (HEATUP TO 1200 OEG F) SURVEILLANCE PROCEDURE DID NOT MEET THE ACCEPTANCE CRITERIA OF TECH SPECS SECTION 4 ~ 6 6 ~ 2 B 4 REFER TO THE NARRATIVE FOR ADDITIONAL ITEMS ADDED VIA REV 3

0 4

0 4 J 0

FORM 137 LER SCSS DATA 08-30-91 DOCKET YEAR LER NUHBER REVISION DCS NUHBER NSIC EVENT DATE 368 1 980 088 1 8407260034 1 62054 1 2/01/80

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • 4***

DOCKET:368 ARKANSAS NUCLEAR, 2 TYPE:PWR REGION: 4 NSSS:CE ARCHITECTURAL ENGINEER: BECH FACILITY OPERATOR: ARKANSAS POWER ANO LIGHT CO SYNBOL: APL COMMENTS STEP 3:NODEL NO 9262 ABSTRACT POMER LLVEL - 060/ CAUSE MAINTENANCE PERSONNEL SHORTED POWER SUPPLIES CPC A ANO, CEAC 01 FAILEO ISC MAINTENANCE'ERSONNEL WERE WORKING ON 2F1-8229-1 IN CABINET 2C33 THE ISC PERSONNEL SHORTEO THE SIGNA FLOW INDICATOR POMER SUPPLY LEADS TOGETHER TRIPPING BREAKER 12 ON 2RS1 AND CAUSING A VOLTAGE TRANSIENT ON 2Y11 AND 2Y13. CPC A FAILEO ON LOW SUPPLY VOLTAGE ANO CEAC NO 1 FAILED BECAUSE OF THE LOSS OF REED SMITCH POSITIVE INDICATION~ THE A ~ C POWER TO SIGNA INDICATOR 2FI-8229-1. AND OTHER INSTRUMENTS IN 2C33 CANNOT BE FEASIBLY DE-ENERGIZED THE INSTRUMENTS CANNOT BE REHOVEO WITHOUT 0 SCONNECTING THE POWER SUPPLY L ADSr MAKING IT NECESSARY TO PERFORH HAINTENANCE

~

WITH THE SYSTEN ENERGIZED SIGNA INDICATORS ARE SCHEDULED TO BE REPLACED WITH ANOTHER TYPE ~

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II ~

FORM 138 LER SCSS DATA 08-30-91

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • 4**********************************

DOCKET YEAR LER NUMBER REVISION DCS NUMBER NSIC EVENT DATE 368 1989 024 0 9002080162 216686 12/31/89

• • • • • • • • • • • 4************+*******************************************

e DOCKET:368 ARKANSAS NUCLEAR 2 'YPE:PMR REGION: 4 NSSS:CE ARCHITECTURAL ENGINE ER: BECH FACILITY OPERATOR: ARKANSAS POWER AND LIGHT CO SYHBOL: APL WATCH-LIST CODES FOR THIS LER ARE:

941 REPORT ASSOCIATED WITH 10 CFR 50 72 35 HUMAN ERROR REPORTABILITY CODES FOR THIS LER ARE:

13 10 CFR 50 73(a) (2) (iv): ESF actuations ABSTRACT POWER LEVEL 100/ ~ ON 12/31/89r A REACTOR TRIP OCCURRED FROM 100% OF RATED THERHAL POWER WHEN '8'TEAN GENERATOR (SG) MATER LEVEL REACHED A HIGH LEVEL SETPOINT AND THE REACTOR PROTECTION SYSTEM GENERATED A REACTOR TRIP SXGNAL DURING THE TRANSIENT ONE OF THE RUNNING CONDENSATE PUHPS WHICH WAS EXPECTED TO TRIP DID NOT TRIP>>:- OTHERWISEr THE PLANT RESPONDED PROPERLY MHEN THE REACTOR TRIP OCCURRED. THE OPERATIONS STAFF RESPONDED APPROPRXATELY AND IN A TIHELY HANNER TO THE REACTOR TRIP. OF PRIHARY CONCERN WAS THE POTENTXAL FOR REACTOR COOLANT SYSTEM OVERCOOLING OR A SG OVERFILL EVENTr HOWEVERS- PROPER SYSTEH OPERATION P REVENTED EITHER FROYi OCCURRING ~ NO SIGNIFICANT SAFETY CONCERNS MERE XDENTIFIED THE ROOT CAUSE OF THIS EVENT IS BELIEVED TO BE A LOOSE TERHINAL ON AN ELECTRICAL MODULE IN THE CONTROL SYSTEM (FMCS) CABINET THE TERHINAL MAS NOT 'B'EEDMATER PROPE RLY RETERNINATED WHEN MAINTENANCE ACTIVITIES WERE PERFORNED DURING 2R7 REFUELING OUTAGE ~ THE LOOSE T RHINAL WAS ON AN" ELECTRICAL NODULE IN THE 'B'AIN FEEDMATER (HFM) FLOW LOOP TO THE 'B'MCS TO VERIFY THAT THE LOOSE TERMINAL COULD CAUSE A TRANSIENT SIllILAR TO THIS EVENTr SIilULATEO SIGNALS FOR 100% POWER CONDITIONS FOR THE INPUTS TO THE 'B'MCS MERE INPUT AND THE CONNECTXON ON THE'TERHXNAL LOOSENED' VERY SIMILAR RESPONSE TO THE TRANSIENT WHICH INITIATED THE REACTOR TRIP OCCURRED

0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 I

4

FORM 139 LER SCSS DATA 08-30-91 DOCKET YEAR LER NUMBER REVISION DCS NUMBER NSIC EVENT DATE 369 1981 1 54 0 811 01 90252 1 59954 0 9/08/81 DOCKET: 369 HCGUIRE 1 TYPE:PMR REGION% 2 NSSS:ME ARCHITECTURAL ENGINEER: DUKE FACILITY OPERATOR: DUKE POWER CO SYMBOL: DPC COHMENTS STEP 5: MODEL NO ~ AA840A STEP 6: HODEL NO ~ 02T-H1855 ABSTRACT AN INSTRUMENTATION AND CONTROL POWER BREAKER WAS TAGGED OUT TO All OM MORK TO BE DONE ON THE GAG ACTUATOR ON A UHI BLOCK VAl.VE~ THIS RESULTED IN THE INSIDE CONTAINMENT ISOLATiON VALVES FOR (EFFLUENT MONITORING CHANNELS) EHF S 38r 39r AND 40 FAILING CLOSED ~ THE THREE EHF S WERE DECI ARED INOPERABLE ~ THE VALVE'S FAILING CLOSED MENT UNDETECTED BECAUSE A VACUUM RELIEF VALVE (GAST PAA840A) APPARENTLY OPENED BEFORE THE "LOSS OF SAHPLE FLOW" aLARM SETPOINT MAS REACHFD.

SAMPLING OF THE CONTAINNENT ATHOSPHERE WAS PERFORNEDr AND A PERIODIC TEST MAS HODIFIED TO INCLUDE VERIFICATION OF THE ISOLATION VALVES POSITION DUKE POMER CO ~ WILL CONTINUE TO TROUBLESHOOT THE EHF ~ S TO ENSURE RELIABl E OPERATION ~

a e e o o e e e e o e o e ~ e e o s o o 0

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0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

FORM 140 LER SCSS DATA 08-30"91 DOCKET'EAR LER. NUMBER PEVXSION OCS NUMBER NSIC EVENT DATE 369 1984 024 0 8412010048 192511 08/21/84

• • • • • • • • • • • 4********************************************************

y DOCKET:369 MCGUIRE REGION: 2 TYPE:PWR NSSS:ME ARCHITECTURAL ENGINEFR: DUKE FACILITY OPERATOR: DUKE POWER CO SYMBOL: DPC COMMENTS STEP 16: CAUSE XX VOLTAGE SPIKE STEP 6: COMP RLX - CONTROL OUTPUT RELAY ~

g MATCH-LIST CODES FOR THIS LER ARE:

975 POSSIBLE SIGNIFICANT. EVENT REPORTABILITY CODES FOR THIS LER ARE:

14 10 CFR 50.73(a) (2) (v): Event that could have prevented fulfillment of a safety function.

ABSTRACT POWER LEVEL 100X~ AT 2400 ON 8 20 84r THE MCGUIRE SMITCHYARO COMPUTER MAS REPORTED INOPERABLE ~ ON 8-21-84r COMPUTER ANO INVERTER MAINTENANCE PERSONNEL PERFORMED CORRECTIVE MAINTENANCE ON THE SMITCHYARD COMPUTER ANO STATIC INVERTER ~ AT 2114r THE SWITCHYARD COMPUTER WAS RE STARTEOr CHECKED FOR OPERABILITYr AND RETUPNEO TO SERVICE AT 2148r WHEN THE SMXTCHYARD OPERATOR RE-ENABLED THE COMPUTER CONTROL. OUTPUTSr 30 POWER CIRCUIT BREAKERS (PCBS) AND ASSOCIATEO DISCONNECTS OPENEOr RESULTING XN MCGUIRE UNIT 1 REACTOR TRIP AND TURBINE TRIPr LOSS OF UNIT 1 OFFSITE AC POWERr AND STARTUP OF UNIT 1 DGS A AND B ~ UNIT 1 WAS XN MODE 1 AT 100/i POMER AT THE TIME THIS INCXDENT IS CLASSIFIED AS A COMPONENT MALFUNCTION/FAILURE BEC'AUSE THE CONTROL CIRCUITS WERE CHANGED TO AN UNDESIRABLE STATE WITHOUT A COMMAND FROM THE COMPUTERr OURXNG COMPUTER ANO INVERTER MAINTENANCE DESIGN DEFICIENCY ALSO CONTRIBUTED BECAUSE THE COMPUTER PROGRAM OXD NOT INCLUDE A FUNCTION TO RESET THE COMPUTER OUTPUT CONTROL CIRCUITS TO A PREDETERMINED STATE WHEN THE COMPUTER IS RESTARTED THE BEHAVIOR ANO CONTROL OF THE TRANSIENT WHICH RESULTED FROM THE REACTOR ANO TURBINE TRIP MERE AS COULD BE EXPECTED'

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FORM 141 LER SCSS DATA 08-30-91 6 *******%*A'**********************************************************

DOCKET YEAR l ER NUMBER REVISION DCS NUHBER ttSIC EVENT DATE 370 1984 034 0 8502010483 192823 12/21/84

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • +*******

370 TYPE:PMR 0 DOCKET HCGUXRE 2 REGION: 2 NSSS:WE ARCHITECTURAL ENGINEER: DUKE FACILITY OPERATOR: DUKE POMER CO ~

~

SYMBOL: DPC COMMENTS STEP 1: HAINTENANCE PERSONNEL HXSTOOK UNIT 2 EQUIPtlENT FOR UNIT 1 EQUIPMENT REPORTABILXTY CODES FOR THIS LER ARE-13 10 CFR 50 73(a) (2) (iv): .ESF actuations ABSTRACT POWER LEVEL 100Fo ~ ON 1 2 21 85r UNIT 2 TRIPPED FROM 1 OOX POWER WHEN PREVENTIVE MAINTENANCE ON UNIT 1 125V AC VITAL INC POMER RESULTED IN A UNIT 2 XNVERTER BEING ERRONEOUSLY REHOVED FROH SERVICEr INSTEAD OF THE ADJACENT UNIT 1 INVERTER THE RESULTING LOSS OF POWER TO THE ANALOG CONTROLLERS FOR SG LEVELr FEEOMATER FLOWr AND STEAM FLOW

=

RESULTED it< A FEEDWATER TRANSXEiNTr WHICH WAS CORRECTED BY SMXTCHING TO HANUAl CONTROL AiNO TRANSFERRING THE CONTROLLERS TO ANOTHER CHANNEL ~

HOMEVERr THE TRANSFER TO ANOTHER CHANNEL WAS DONE INCOHPLETELYr IN THAT 1 OF 13 CONTROLt ER S'WXTCHES WAS NOT MOVED TO THE At. TERNATE CHANNELS WHEN CONTROL MAS RETURNED TO THE AUTOHATIC HODEr THE CONTRIBUTION OF THIS INOPERABLE INPUT TO AUTOHATXC CONTROL CAUSED THE LEVEL IN SG C TO FALL TO THE LOW-LOM TRIP SETPOINT ~ THE CAUSE OF THE EVENT MAS PERSONNEL ERROR BECAUSE AN OPERATOR AND AN XNDEPENDENT VERIFIER FAXlED TO IDENTIFY PROPERLY THE EQUIPMENT TO BE REHOVED FROM SERVICE ~ IN ADDXTIONr THE TRANSFER OF THE SG PROGRAH TO AN. ALTERNATE CHANNEL MAS PERFORMED INCORRECTLY CORRECTIVE ACTION MILl INCLUDE A RE EMPHASIS MITH OPERATORS ON THE IHPORTANCE OF FOLLOWING PROCEDURESr AND VERIFICATION~ ALSOr THE SG LOW LOW LEVEL TRIP SETPOINT MILL BE lOMERED TO ALLOM OPERATORS MORE TIHE TO DIAGNOSE AND COMPENSATE FOR SG LEVEL TRANSXENTS

0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0

~ J

~e 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

FORM 142 LER SCSS DATA 08-30-91

• • • • • • • • • • • • • • • • • • • • +***********************************************

DOCKET YEAR LER NUHBER REVISION DCS NUMBER NSIC EVENT DATE 370 1985 026 0 8512100425 197373 10/24/83

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • Br++*********

e DOCKET:370 MCGUIRE 2 REGION: 2 TYPE:PMR NSSS:ME ARCHITECTURAL ENGINEER: DUKE FACILXTY OPERATOR: DUKE POWER CO SYMBOL: DPC CODES FOR THIS LER ARE-g REPORTABILITY 13 10 CFR 50 73(a) (2) (iv): ESF actuations.

LERS:

g REFERENCE 1 370/84-034 ABSTRACT POWER LEVEL 100K ~ ON OCTOBER 24 1985 A REACTOR TRIP OCCURRED AS A RESULT OF LOM LFVEL IN STEAN GENERATOR (S/G) "C" THE INADVERTENT OPENING OF THE OUTPUT BREAKER ON THE CHANNEL II VITAL INSTRUMENTATION ANO CONTROL INVERTER INITIATED THE EVENT THE ANALOG CONTROLLERS FOR THE S/G'S AND PRESSURIZER MERE BEING SUPPLIED BY CHANNEL I POMER SUPPLY ANO MERE UNAFFECTED BY THE LOSS OF POWER THE S/G LEVEL PROGRAM SEl ECTOR SWITCH FOR THE NUCLEAR POWER CONTRIBUTION MAS IN THE N41 N42 (CHANNEL Xr CHANNEL XI) POSITION AT THE TINE OF THE INCIDENT THE N42 CHANNEL HAD FAII EO DUE TO THE LOSS OF POMER ANO MAS CAUSING AN ERRONEOUS S/G LEVEL SIGNAL WHICH WAS CLOSING THE FEEDWATER CONTROL VALVES FOR S/G'S "B" AND "C". THE DECREASING S/G LEVELS MERE NOT NOTICED BY THE OPERATORS UNTIL THE LOM LEVEL ALERT 'WAS RECEIVED AT APPROXIHATELY 45 PERCENT LEVELS ATTEHPTS TO MANUALLY RECOVER LEVFL MERE UNSUCCESSFUL ANO REACTOR TRIP FROM 100 PERCENT POWER OCCURRED THIS INCIDENT'S ATTRIBUTED TO PERSONNEL ERROR DUE TO THE UNXNTENTIONAl TRIPPING OF THE INVERTER BREAKER SYSTENS RESPONDED AS EXPECTED FOR THE TRANSIENT ~ MODIFICATIONS ARE BEING CONSIDERED TO Al LOM OPERATORS NORE TIiNE TO CORRECT OR PREVENT THXS TYPE OF TRANSIENT

0 0 0 0 0 0 0 0 0 0 0 0 0 0 ~ 0 0 4~

Ul Id ~

n P

FORhl 143 LER SCSS DATA 08-30-91 e ********************************************************************

DOCKET YEAR LER NUhlBER REVISION-'CS NUMBER NSIC EVENT DATE 373 1989 009 1 8907110299 214561 03/02/89 DOCKET:373 LA SALLE 1 TYPE:BMR REGION: NSSS:GF.

ARCHITECTURAL ENGINEER: SLXX FACILITY OPERATOR: CONtlONMEALTH EDISON CO SYMBOL: CME COhlHENTS STEPS 2r3 HOOEL NOa 9l 11NHA264 ~

~ MATCH-LIST CODES FOR 942 UNUSUAL EVENT THXS LER ARE:

20 EQUIPMENT FAILURE REPORTABILITY CODES FOR THIS LER ARE:

13 10 CFR 50.73(a) (2) (iv): ESF actuations.

REFERENCE LERS:

1 373/87-003 2 3?3/87-014 3 374/84-020 ABSTRACT POMER LEVEL' 086X ~ ON 3/2/89 AT 2302 HRS A PHASE TO GROUND FAULT OCCURRED AT "C" PHASE LIGHTNING ARRESTOR ON THE PRIMARY SIDE OF THE UNIT 2 SYSTEH AUX ~ TRANSFORHER ~ FAULT MAS AUTONATICALlY ISOI ATED BY THE TRIPPING OF SMITCHYARD OIL CIRCUIT BREAKERS (OCB) 4-6 AND 6-1, AND UNIT 2 FEcOER BREAKERS ~ ALL LOADS BEING FED FRON THE SAT TRANSFERRED TO UNIT 2 UNIT AUX TRANSFORhlER EXCEPT FOR BUS 243 MHICH MAS SUPPLIED BY 28 DIESEL GENERATOR MHXCH SATISFACTORILY AUTO-STARTED ON UNDERVOLTAGE UNIT 2 REtCAINED ON-LINE AFTER THE INCXDENT ~ AS A RESULT OF TRANSIENT ON THE 345 KV SYSTEhlr UNIT 1 GENERATOR PROTECTIVE RELAYING SENSED A HIGH GENERATOR DIFFERENTIAL CURRENT ON PHASE A AND ISOLATED UNIT 1 GENERATOR ~ UNIT 1 TURBINE TRIPPED ON -LOAD REJECTION RESULTING IN A REACTOR SCRAtl FROH TURBINE CONTROL VALVE FAST CLOSURE UNIT 1 PROCEEDED INTO NORMAL POST-SCRAM CONDITIONS MITH THE EXCEPTION OF TEMPORARY LOSS OF THE SERVICE AIR COMPRESSOR AND PLANT PROCESS COMPUTER PROBLEMS MERE AI SO ENCOUNTERED MXTH THE RESETTING OF THE SCRAM LOGIC CAUSE OF THIS EVENT MAS THE PHASE TO GROUND FAULT THAT OCCURRED FROM THE I XGHTNING ARRESTOR TOP CAP TO A SPARGER HEAD ON THE TRANSFORMER DELUGE SYSTEM ~ THIS MAS EVIDENT FROM ARC BURNING IDENTXFXEO AT TOP OF LIGHTNING ARRESTOR ANO AT SPARGER HEAD. FAULT WAS'AUSED BY. DEBRIS THAT HAD BLOMN ONTO THE LIGHTNING ARRESTOR LEAD

0 0 0 ~ 0 0 0 0 0 0 0 0 0 0 8 0 0 0 0

(

0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

FORM 144 LER SCSS DATA 08-30-91

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • 4'****************

DOCKET YEAR LER NUMBER REVISXON DCS NUMBER NSIC EVENT DATE 382 1 985 042 0 8511070012 197229 10/02/85

• • • • • • • • • • • • • • • • 4***************************************************

e DOCKET:382 WATERFORD 3 REGION:

ARCHITECTURAL'NGINEER:

4 EBAS

'SSS: TYPE:PWR CE FACILITY OPERATOR: LOUISIANA POWER 8 LXGHT CO ~

SYMBOL: LPL y COMMENTS STEP 1: COMP MOT DIESEL. GENERATOR AIR DRYER MOTOR STEP 2: EFFECT IX VOLTAGE SPIKE REPORTABILITY CODES FOR THIS LER ARE:

13 10'FR 50.73(a) (2) (iv): ESF actuations.

ABSTRACT POWER LEVEL'03X~ AT 2032 HRS ON 10 2 85'HE WATER LEVEL XN SG 02 INCREASED TO THE HXGH LEVEL REACTOP. TRXP SETPOINT JUST PRIOR TO THE TRIP CONTROL ROOM OPERATORS RECEIVED NUMEROUS ALARMiS/ANNUNCIATIONS WHEN A SHORT IiN THE EMERGENCY DG AXR DRYER MOTOR (NON-SAFETY) CAUSED A SPIKE ON THE STATIC UNINTERRUPTIBLE POWER SUPPLY 'A'SAFETY) SINCE THE FEEDWATER CONTROL SYSTEM WAS IN THE MANUAL MODE OF OPERATION 'HE ALARMS/ANNUNCIATIONS DISTRACTED THE CONTROL BOARD OPERATOR'S ATTENTION LONG ENOUGH FOR THE WATER LEVEL IN SG 02 TO INCREASE TO THE REACTOR TRIP SETPOINT ~ THE AIR DRYER MOTOR HAS BEEN REPLACED ~ A STATION MODIFICATION HAS BEEN INITIATED TO CHANGE'HE POWER SUPPLY FOR ALL 4 EMERGENCY DG AIR DRYERS ~ UNTIL THIS MODIFICATION IS COMPLETE POWER. FOR ALL 4 AIR DRYERS IS BEING TEMPORARILY SUPPI IED FROMi A NON-SAFETY SOURCES

0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 lI N

~ 1

~ lk 0 0 0 0 0 0 0 0 0 0 0 0 0

FORM 145 LER SCSS DATA 08-30-91 O ***********i********************************************************

DOCKET YEAR LER NUMBER REVISION DCS NUMBER NSIC EVENT DATE 387 1985 009 0 85041 905 22 1 93981 03/1 0/85 DOCKET:387 SUSQUEHANNA 1 TYPE:BMR REGION. 1 NSSS:GE ARCHITECTURAL ENGINEER: BECH FACILITY OPERATOR: PENNSYLVAiNIA POMER 8 LIGHT CO ~

SYMBOL: PPL COMMENTS STEPS 2r12r17 CAUSE LD MELDING WORK ~ STEPS 10r15 HALF SCRAM SIGNAL PRESENT FOR MODIFICATION WORK XN PROGRESS REPORTABILITY CODES FOR THXS LER ARE:

13 10 CFR 50.73(a) (2) (iv): ESF actuations ABSTRACT POMER LEVEL 000%>> ON 3 10r 3 11r AND 3 28 85r INADVERTENT ESF ACTUATIONS OCCURRED ~ ON 3 1 Or THE CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY SYSTEMr A COMMON SYSTEM FOR UNIT 1 AND 2r STARTED UNEXPECTEDLY ON A HIGH-HIGH RADIATXON DETECTION SYSTEM SPIKE ~ NO ACTUAL HIGH RADIATION CONDITION EXISTED ~ ON 3 11r WITH THE ~ Bs RPS CHANNEL SCRAM PRESENT DUE TO MODIFICATION MORKr A NOXSE SPIKE ON INTERMEDIATE RANGE MONITOR s Cs -'CAUSED A SCRAM SIGNAL ON THE 'A'PS CHANNEL RESULTING IN AN RPS ACTUATiON ON 3-28 WITH THE 'A'PS CHANNEL SCRAM SIGNAL PRESENT DUE TO MODIFICATION WORKr A NOISE SPIKE ON XRM sDs CAUSED A SCRAM SIGNAL ON THE 'O'PS CHANNEL RESULTING IN AN RPS ACTUATION~

THERE MAS NO CONTROL ROD MOVEMENT ON EXTHER RPS ACTUATION AS THE REACTOR WAS SHUTDOWN AND DEFUELED AT THE TIME OF THE INCXDENTS ~ ALL 3 INCIDENTS HAVE BEEN ATTRIBUTED TO MELDING XN THE VICINITY OF THE DETECTORS INDUCXNG NOISE IN THE INSTRUMENTATION~

0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 II II

~0 i

FORM 146 LER SCSS DATA 08-30-91 e **********************A*********************************************

DOCKET YEAR l ER NUMBER REVXSXON DCS NUMBER NSXC EVENT DATE 395 1987 015 0 8707150475 205259 06/16/87

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • 4******

-e DOCKET-395 SUtdHER 1 TYPE:PWR REGION: 2 NSSS:ME ARCHITECTURAL ENGINEER: GLBT FACILXTY OPERATOR: SOUTH CAROLINA ELECTRIC 8 GAS CO ~

S YNBOL: SCC g WATCH-LIST CODES FOR THIS 20 EQUIPMENT FAILURE LER ARE:

~ REPORTABILITY CODES FOR THXS LER ARE:

13 10 CFR 50 73(a) (2) (iv): ESF actuations g ABSTRACT.

POWER LEVEL 100%. ON JUNE 16 1987 AT 2003 HOURS A REACTOR TRIP OCCURRED FROM 100! POWER THE FAILURE OF A CAPACITOR XN 'CONVERTER XXT 5904 CAUSED AN OUTPUT FUSE TO BLOW WHICH RESULTiD IN THE LOSS OF POWER RANGE NUCLEAR INSTRUMENT (NX),44 THE LOSS OF NX- 44 CAUSED THE STEAt< GENERATOR (SG) PROGRAH LEVEL CONTROL SIGNAL TO DECRFASE FROH FULL LOAD TO NO LOAD (38%) THE FEEDWATER REGULATING VALVES (FMRVS)

REDUCED FLOW TO DECREASE ACTUAL LEVEL TO NEET THE PROGRAMMED LEVELS WHEN THE OPERATOR PLACED THE FMRV CONTROLS TO MANUAL AND DEHANDED AN OPEN SIGNALr THE ADDXTXON OF COOLER FEEDMATER (IN CONJUNCTION WITH THE ALREADY DECREASED LEVEL) CAUSED "B" STEAH GENERATOR l EVEL TO SHRINK BELOW THE LOM-LOM LEVEL REACTOR TRIP SETPOXNT THE PLANT RESPONDED TO THE REACTOR TRIP WITH NO ABNORMALITIES NOTOR DRIVEN EMERGENCY FEEDWATER PUMP "A" AND THE TURBINE DRIVEN EMERGENCY FEEDMATER PUMP STARTED TO SUPPLY FEEDMATER TO THE SGS IN RESPONSE TO THE -SG LOW-LOW LEVEL REACTOR TRXP ~ DUE TO A PREVIOUS STEAN GENERATOR TUBE LEAKr THE STEAN REI EASED FROM THE tdAIN STEAt< POWER OPERATEO RELIEF VALVES ANO THE TURBINE DRIVEN iHiRGiNCY FEEOMATER PUNP EXHAUST TO ATMOSPHERE MAS CONSERVATIVELY CALCULATED TO BE A SHALL. FRACTION OF THE ALLOWABLE RELEASE LX NIT

0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 I'

1l

FORM 147 LER SCSS DATA 08-30-91 DOCKET YEAR LER NUMBER REVISION DCS NUMBER NSIC EVENT DATE 395 1987 028 0 8712040158 207343 10/30/87

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • dr*********************A********

DOCKET:395 SUNMER 1 TYPE:PWR REGION: 2 NSSS:ME ARCHITECTURAL ENGINEER: GLBT FACILITY OPERATOR: SOUTH CAROLINA ELECTRIC & GAS CO SYMBOL: SCC COHHENTS STEP 2: COMP XI - LIGHT BULBS FOR POWER STATUS ~

HATCH-LIST CODES FOR THIS LER ARE:

941 REPORT ASSOCXATED WITH 10 CFR 50 72 35 HUMAN ERROR REPORTABILITY CODES FOR THXS LER ARE:

13 10 CFR 50 ~ 73(a) (2) (iv): ESF actuations.

ABSTRACT POWER LEVEL 0007o ~ ON OCTOBER 30r 1987r AT 0903 HOURS WITH THE PLANT IN NODE 3 AND THE SHUTDOWN BANKS WITHDRAWN' REACTOR TRXP OCCURRED AND BOTH SETS OF SHUTDOWN BANKS INSERTED DUE TO THE LOSS OF POWER TO A SOURCE RANGE NUCLEAR INSTRUH NTATXON DRAWERS THXS LOSS OF POWER OCCURRED WHEN THE MRONG TYPE OF LIGHT BULBS MERE INSERTED XN BOTH THE INSTRUMENT AND CONTROL POWER STATUS INDICATING LIGHTS IN ONE OF THE SOURCE RANGE DRAMERS IN THE CONTROL ROON THE INCORRECT lXGHT BULBS CAUSED BOTH THE INSTRUMENT AND CONTROL POWER FUS"S TO BLOW WHEN THE LXGHT BULB HOLDER ASSEHBLY MAS REINSERTED SUBSEQUENT INVESTIGATXONS DETERMINED THAT THE ORXGINAL BULBS WERE NEON TYPE BULBS WITH AN XNFINITE RESISTANCEr WHXLE THE BULBS USED AS REPLACEMENTS

~ THOUGH SIMILAR lOOKING MERE XNCANDES CENT TYPE BULBS WITH AN OHHXC VALUE OF APPROXIMATELY 176 OHHS ~ TO PREVENT RECURRENCE'HE LICENSEE IS DEVELOPING A PROGRAM TO ADDRESS CHANGEOUT OF LIGHT BULBS XN THE CONTROL ROON ~

-0 C

0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 I

t 41 '

~ e o e e e o e e o.e e e o o e e e o o 0

FORH 148 LER SCSS DATA 0 8-30-91 DOCKET YEAR LER NUHBER REVISION DCS NUMBER NSIC EVENT DATE 397 1985 006 0 8502250773 193436 01/1?/85 DOCKET:397'PPSS 2 TYPE:BMR REGXON: 5. NSSS:GE ARCHITECTURAL ENGINEER: BNRO FACILITY OPERATOR: WASHINGTON PUBLIC POMER SUPPI Y SYSTEH SYHBOL: MPP COMMENTS OTHER REPORTABXLITY 50 ~ 72(B) (2) (II)

WATCH-LIST CODES FOR THIS LER ARE 941 REPORT ASSOCIATED SIXTH 10 CFR 50 72 CODES FOR THIS LER ARE:

y REPORTABXLITY 13 10 CFR 50 73(a) (2) (iv): ESF actuations

21. OTHER: Voluntary reports special r eportr Part 21 reports etcr ABSTRACT POWER LEVEL 100% ~ ON-1-17-85 AN EQUIPNENT OPERATOR MAS RACKING IN 480V BREAKER ROA-FN-1A ON SMITCHGEAR SL-73 ~ WHILE DOING SO IT APPEARED THAT THE TRIPPING BAR MAS EXTENDED FURTHER THAN NORMAL VERIFY THIS'E OPENED THE DOOR TO THE BREAKER BELOW (FEEDER BREAKER

'O TO 480 V HOTOR CONTROL CENTER "1C-7A) SO AS TO COYiPARE THE TWO BREAKER CONFIGURATIONS IN THE PROCESS OF THE CHECK THE TRIPPING BAR FOR THE HC ?A BREAKER WAS INADVERTENTLY MOVED SLIGHTLY INWARDS THEREBY CAUSING THE BREAKER TO TRIP THE HC-7A TRIP CAUSED THE A RPS HOTOR-GENERATOR SET TO LOSE POWER AND DEENERGXZE ITS RESPECTXVE BUS ~ ALTHOUGH THE TRIP OF NC 7A MAS NOT XN ITSELF CAPABLE OF GENERATING A FULL SCRAM' PLANT TRIP OCCURRED BECAUSE A= COINCIDENT TRIP CONDITION EXXSTEQ ON THE OPPOSITE RPS 'CHANNEL DUE TO A BLOWN FUSE ON THE APRYi D POMER SUPPLY ~ THE BLOMN FUSE MAS THE RESULT OF HAINTENANCE ACTIVITIES ASSOCIATED WITH APRN eDe AND MAS IN THE PROCESS OF BEING REPLACED WHEN THE SCRAM OCCURRED

0 e e e e o e e o o o e e o o o e e o a o 0 f,

t 5

4 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

FORM 149 LER SCSS DATA 08-30-91

• • • • • • • • • • • • • • • • • • • • • • • • • A *'*********************4 **************** 4**

DOCKET YEAR LER NUMBER REVXSXON DCS NUMBER NSIC EVENT DATE 397 1985 059 0 8512180073 197590 11/13/85

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • 4**************************************

DOCKET:397 MPPSS 2 TYPE-BMR REGION: 5 NSSS:GE ARCHITECTURAL ENGINEER: BNRO FACILITY OPERATOR: MASHXNGTON PUBLIC POMER SUPPLY SYSTEM SYMBOL: MPP COHHENTS STEP 1: COHPONENT HSC - UNSPECIFIED SUBCONPONENTS STEP 2: HODEL INV 203-101 J STEP 14: COMPONENT CBL-TEST JUMPER ~

REPORTABILITY CODES FOR THIS LER ARE:

13 10 CFR 50 ~ 73(a) (2) (iv): ESF actoations ~

ABSTRACT POWER LEVEL 050X~ ON 11. 13 85m AT APPROXXHATELY 0600 HRSr A REACTOR SCRAM OCCURRED DUE TO FAILURE OF POMER TO THE CONTROLLING REACTOR FEEDMATER (RFW) SYSTEM REACTOR PRESSUR VESSCL (RPV) LEVEI INSTRUJ'JENT CHANNEL LOSS OF POWER CAUSED DOMNSCALE RPV LEVEL INDICATION ON THE CONTROLLING CHANNEL. "A""WHICH CAUSED THE RFW SYSTEi4l TO RESPOND BY INCREASING RPV LEVEL UNTIL THE CHANNiLS "B" AND "C" QPV HIGH LEVEL

~TURBINE TRIP SETPOINT WAS RiACHED THE POMER FAILURE TO THE RFW CHANNEL. "A". INSTRUMENTATION MAS CAUSED BY COMPONENT FAILURi OF CRITICAL INSTRUMENT POWER INVERTER IN-3 THIS RESULTED XN THE FAILURE OF THE UNIT TO SUPPLY POWER TO ONE OF TMO CRXTXCAl INSTRUMENT BUSES WHICH W" RE SUPPLYING POWER TO THE RFM LEVEL INSTRUNENTATXON~ AT APPROXIMATE 0845'HILE TROUBLESHOOTING INVCRTiR IN 3w THE INVERTER WAS INADVERTENTLY SHUTDOWN WHEN THE NORMAL OPERATING PROCEDURE WAS USED TO TRANSFER INVERTER POWER SUPPLIES THE INVERTER SHUTDOWN SYSTEM AND A PARTIAL'ONTAINMENT ISOLATION 'T-CAUSED AN INADVERTENT START OF THE CONTROL ROOM EHERGENCY FILTRATION APPROXIHATELY 1435 HRSs WHILE CONTINUING TO TROUBLESHOOT XNVERTER IN 3r A TEST LEAD MAS ACCIDENTLY SHORTED TO GROUND WHICH CAUSED O'USE IN THE POWER SUPPLY TO THE PP-7A-A CRITICAL INSTRUJ'IENT BUS TO BLOM ~ THIS CAUSED A SECOND AUTOMATIC START OF THiS ESF SYSTEM AND A PARTIAl CONTAINMENT ISOLATION

0 e a e o e e e e o e o o e e o e e e o % 0 t 0 ~

III Il

~ e e o o e o e e e e e o e o e e e e e o

FORM 150 I ER SCSS DATA 08-30-91.

6 *****4**********************************+***************************

REVISION DOCKET 409 YEAR 1 986 LER NUMBER 016 0 '6061 DCS NUHiBER 60266 1 NSIC 99849 EVENT DATE 05/1 0/86 DOCKET:409 LACROSSE TYPE:BMR O REGION: 3 NSSS:AC ARCHITECTURAL ENGINEER- SLXX FACILITY OPERATOR: DAIRYLAND POWER COOPERATIVE SYH BOL: OLP g COMMENTS WATCH LIST 231 - UNEXPECTED INTERACTION OF EMERGENCY TELEPHONE SYSTEM WITH EHERGENCY BUS ~ WATCH LIST 932 - IE INFORMATION NOTICE 85-77 STEPS 1r20:

VENDOR- ADVANCE CONY'ERSION DEVICES COHPANY HOOEL- A66-1/118 STEP 8: ALL ESF SXGNALS MERE NOT BYPASSED BEFORE MAINTENANCE STEP 9: CAUSE AX-REPLACEHENT OF FAILED INVERTER STEP 16: CAUSE SX- POWER SOURCE FOR EMERGENCY TELEPHONES HAD BEEN SWITCHED TO A VXTAL BUS DURING A RECENT REFUEl ING OUTAGE XN RESPONSE TO IE NOTICE 85-77. STEP 23: MODEL- T/613.

STEP 29 COHPONENT HSC FUSE HOLDERr EFFECT DX- UNSPECIFXEO DAHAGE ~

WATCH-LIST CODES FOR THIS LER ARE:

231 UNEXPECTED SYSTEM ACTION OR RESPONSE 932 RESULT OF IE BULLETXNSr ORDERSr ETC (IEB ~ 81-7)

REPORTABILXTY CODES FOR THIS LER ARE:

10 10 CFR 50.73(a) (2) (i): Shutdowns or technical specification violations.

13 10 CFR 50.73(a) (2) (iv): SF actuations ABSTRACT POWER LEVEL 000X ~ ON HAY 10r WITH THE REACTOR XN HOT SHUTDOWNr= THE 1A STATIC INVERTER FAILEO AND TRANSFERREO THE 1A NONINTERRUPTXBLE BUS TO XTS ALTERNATE SOURCE ~ DURING THE TRANSFERr REACTOR MATER I EVEL SAFETY CHANNEL NO 2r CAUSED BOTH HIGH PRESSURE CORE SPRAY PUMPS AND BOTH EMERGENCY DIESEL GENERATORS TO START AND CONTAINHiENT BUILDING TO ISOLATE THE XNVERTER MAS REPLACED WITH A SPARE ~ ON ltAY 13r 1A STATIC INVERTER AGAIN- FAILED ANO THE 1A NONINTERRUPTXBLE BUS TRANSFERREO TO ITS ALTERNATE SOURCE THE REACTOR SCRAMMED FROM LOM POWERr BOTH HPCS PUHPS AND EMERGENCY DIESEL GEiVERATORS STARTEDr CONTAINMENT BUILDING ISOLATED AND THE SHUTDOWN CONDENSER XNITIATEO ALSOr 1C STATIC INVERTER SHIFTEO TO ITS ALTERNATE SOURCE ANO THE FUSE

'HICH SUPPLIES EMERGENCY'HONE CIRCUITS FROM THE 1C NONINTERRUPTXBLE BUS MAS FOUND BLOMN THE 1A STATXC XNVERTER FAILURE WAS OUE TO AN OVERHEATED RESISTOR OiV A CIRCUIT BOARD INSTALLED BY THE MANUFACTURER IN 1977 TROUBLESHOOTING DETERHINFD THAT'HE INTERACTION BETWEEN 1A ANO 1C NONINTERRUPTIBLE BUSES S"EHED ASSOCIATED WITH THE EMERGENCY PHONE CIRCUITr WHICH HAD RECENTLY HAD XTS POWER SUPPLY CHANGED TO 1C BUS ~ THE EMERGENCY PHONE CIRCUIT MAS REMIREO TO ITS ORIGIiVAL POWER SUPPLY

0 0 0 0 0 0 0 0 0 0 0 0 0 0 4 0 0 ~

4'

FORM- 1 51 LER SCSS DATA 08-30-91

• • • • • • • • • • • 0****A*************A*************************************

DOCKET YEAR LER NUMBER REVXSION OCS NUMBER NSIC EVENT DATE 409 1986 021 0 8608190726 200725 07/16/86

~ ********************************************************************

DOCKET:409 LACROSSE TYPE: BWR g REGION: 3 NSSS:AC ARCHITECTURAL ENGINEER: SLXX FACILITY OPERATOR: DAlRYLAND POWER COOPERATIVE SYMBOL: DLP COMMENTS STEP 3: COMP RLX-MECHANICAL TRANSFER RELAY STEP 4: ADVANCE CONVERSION DEVICES CO MODEL A66-1/118 REPORTABILITY CODES FOR THlS LER ARE:

10 10 CFR 50 73(a) (2) (i): Shutdowns or technical specification violations 13 10 CFR 50.73(a) (2) (iv): ESF- actuations.

LERS:

g REFERENCE 1 409/74-003 2 409/79-017 3 409/80-011 4 409/83-007 5 409/86-016 ABSTRACT POWER LEVEL 098X REACTOR SCRAMMED WHEN 1A STATIC INVERTER TRANSFERREO TO ITS ALTERNATE SOURCEr MOMENTARILY DE ENERGIZING ONE OF THE SCRAM TRAINS AFTER INVERTER WAS CHECKEOr THE 1A NON INTERRUPTIBLE BUS WAS TRANSFERREO BACK TO THE INVERTED LATERr THE INVERTER LOAD TRANSFERR D AGAIN AND TWO FUSES BLEWr DE ENERGIZING SOME INSTRUMENTATION~ HIGH PRESSURE CORE SPRAY (HPCS) PUMPS STARTEDr THE 1A SHUTDOWN CONDENSER (SDC) TRAIN INITIATED ANO CONTAINMENT BUILDING XSOLATED ~ THE HPCS PUMPS CONTROL SWITCHES WERE PLACED IN "PULLOUT" TO PREVENT THE PUMPS FROM RUNNING'HE 1A SOC STEAM INLET VAI VE WAS MANUALLY ISOLATED THE FUSES WERE REPLACED AND EQUIPMENT RETURNED TO NORMAL WHILE THE SDC WAS IN SERVICE~ THE REACTOR VESSEL COOLED DOWN AT A RATE IN EXCESS OF THE TECHNICAL SPECIFICATION LIMIT THE STRESSES EXPERIENCED WERE NOT XN EXCESS OF ALI OWABLE LIMITS

,I 0 0 0 0 0 0 0 0 0 0 0 0 0' 0 0 I

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'h 1

4 ao I I 0 e o o o e o e e o e o e e e o e e e o o

FORM 152 LER SCSS DATA 08-30-91 DOCKET YEAR LER NUMBER REVISION DCS NUMBER NSIC EVENT DATE 410 1986 015 0 8612300319 202301 12/03/86

• • • • • • • • • • • • • • • • • • • • • A ************************ **********************

NINE MILE POINT 2 e DOCKET:410 REGION: 1 TYPE:BMR NSSS:GE ARCHITECTURAL ENGINEER: SMXX FACILITY OPERATOR: NIAGARA MOHAWK POWER CORPORATION SYMBOL: NHP g COHHENTS STEP 1- LOGIC CIRCUITS DESXGNED BY GENERAL ELECTRIC (G080) STEPS 3r4 COMP CBL TEMPORARY JUMPER ~ ST P 4 CAUSE AX JUNPER REMOVED ~ STcPS 7r8 IE CROSS CONNECTED MXTH POWER SUPPLXES OUT OF PHASE ~ STEPS 5r6 P COL TR HSIVS LOGIC CIRCUiTS DESIGN WAS CHANGED ~

MATCH-LIST CODES FOR THIS LER ARE:

942 UNUSUAL EVENT REPORTABILITY CODES FOR THIS lER ARE:

13 10 CFR 50 73(a) (2) (iv): ESF actuations.

LERS:

g REFERENCE 1 410/86-014 ABSTRACT POWER LEVEL - OOOX ON DECEMBER 3 1986 WITH THE REACTOR AT OX POWER AND THE NODE SMITCH IN "SHUTDOWN"r NINE NILE POINT UNIT 2 FXPERIENCED A SCRAH DUE TO THE LOSS OF POWER TO BOTH REACTOR PROTECTION SYSTEH (RPS) CHANNEI S THE RPS POMER SUPPLIES MERc INADVERTENTLY CROSS CONNECTEDr RESULTING IN THE lOSS OF ALL RPS POWER COINCIDENT WITH THIS EVENT MAS A CONTAINMENT ISOLATION AND A STANDBY GAS SYSTEH AUTOMATIC INITIATION~ NO REACTOR TRANSIENTS MERE EXPERXENCED DURING THIS EVENT CORRECTIVE ACTIONS TAKEN: 1 A DESXGN CHANGE HAS BEEN BUILT INTO THE HAIN STEAH ISOLATION VALVE (NSIV) LOGIC CIRCUITS THAT MXLL AVOID CROSS CONNECTXNG RPS CHANNELS A AND 8 AS DESCRIBED IN THIS REPORT~ 2~' FURTHER XNVESTIGATION XS BEING CONDUCTED ON THE LOSS OF ALL ANNUNCIATORS

I I

E I'

f 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

FORM 153 LER SCSS DATA 08-30-91 kkkkk*kk*k*kkkkkk**k*kkkk***k*k***kkk**kkkkkk*k*kk*k*kkkk*kkkkk**kkk DOCKET YEAR LER NUMBER REVISION OCS NUMBER NSIC EVENT DATE 412 1987 001 0 8707300525 205543 06/28/87

~ ********************************k*********************************k*

I DOCKET:412 BEAVER VALLEY ?

REGION:

ARCHITECTURAL ENGINEER: SMXX 1

TYPE:PMR NSSS:WE FACILITY OPERATOR: OUQUESNE LIGHT CO ~

S YH BOL. DUQ COMMENTS STEP 2: ITE MODEL K-1600 '

MATCH-LIST CODES FOR THIS LER ARE:

60 SPURIOUS/ UNKNOWN CAUSE REPORTABILITY CODES FOR THIS LER ARE:

13 10 CFR 50.73(a) (2) (iv): ESF actuations y REFERENCE 1

LERS:

412/8?-003 ABSTRACT.

POWER 'LEVEL 000X ~ AT 1647 HOURS ON 6/28/87r WITH THE UNIT IN COLD SHUTDOMNr A BREAKER SUPPLYXNG A 480 VAC EHERGENCY MOTOR CONTROL CENTER (MCC) TRIPPED ON OVERCURRENTr THUS DE-ENERGIZING THE BREAiYER ~ THE NO ~ 1 120 VAC VITAL BUS WAS BEING SUPPLXED FROM THE HCC AT THE TIME BECAUSE ITS NORMAL UNXNTERRUPTIBLE POWER SUPPLY (UPS) WAS OUT OF SERVICE FOR MAINTENANCE~ THFREFOREr THE LOSS OF THE HCC RESULTED IN THE LOSS OF THE VXTAL BUSr WHICH DE-ENERGIZED SOURCE RANGE NEUTRON FLUX DETECTOR N-31 AND CAUSED A REACTOR TRIP ON HIGH SOURCE RANGE Fl UX ~ A TRIP SIGNAL MAS ALSO G NERATED ON LOM-LOM 'C'TEAH GENERATOR (SG) LEVEL THIS TRIP SIGNAL RESULTED FROM THE LOSS OF THE 'C'G CHANNEL 1 LEVEL- TRANSMITTER (WHICH MAS BEING SUPPLIED WITH AN ARTIFICXALLY HIGH LEVEL. SIGNAL TO PERMiIT REACTOR TRIP BREAKER CLOSURE FOR CONTROL ROD TESTING) IN COINCIDENCE MITH AN ACTUAL LOM LEVEL SIGNAL ON CHANNEL- 3 ~ NO SAFETY IHPLXCATIONS RESULTED BECAUSE THE UNIT WAS ALREADY IN COLD SHUTDOWN WITH AN ADEQUATF. HARGXN OF NEGATIVE REACTIVXTY THE OVERCURRENT CONDITION WAS CLEARED AND THE SUPPLY BREAKER CLOSED AT 1657 HOURS ON 6/28/87 ~ THE UPS MAS RETURNED TO SERVICE ON ?/2/87r THUS RESTORING THE NORMAL POWER SUPPLY CONFIGURATXON FOR THE VITAL BUS

I 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 ] 0 c V K

0 e e e o e e e e e e e e e e e e e e o 0

FORM 154 LER SCSS DATA 08"30"91

• • • • • • • • • • • A'*********%***A******************************************

DOCKET YEAR LER NUMBER REVISION DCS NUMBER NSIC EVENT DATE 413 1 988 004 0 8802230102 208355 01/1 6/88

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • A'**

~ DOCKET:413 CATAWBA 1 REGION: 2 TYPE:PMR NSSS:ME ARCHXTECTURAL ENGINEER: DUKE FACILITY OPERATOR: DUKE POWiR CO ~

SYMBOL: DPC COMMENTS STEP 4: CAUSE XX NORMAL RCS TEMPERATURE fOR HODE OTHER REPORTABILXTY 50 ~ 72 (B) (2) (II) $ E/E A/EP MATCH-LIST CODES FOR THIS LER ARE:

20 EQUIPMENT FAILURE 942 UNUSUAL EVENT 18 TEMPERATURE REPORTABILITY CODFS FOR THIS LER ARE:

13 10 CFR 50 ~ 73(a) (2) (iv): ESF actuations 21 OTHER: Voluntar y r eportr special repor etc%

ti Part 21 r eportr REFERENCE LERS:

1 413/86-025 2 413/87-013 3 413/87-034 4 413/88-003 5 414/86-015 6 414/86-051 7 414/87-003 8 414/87-019 9 414/87-029 ABSTRACT POWER LEVEL. OOOX ON 1/1 6/88r THE UNIT WAS IN THE PROCESS OF BEING SHUTDOWN ~ WHEN REACTOP, POWER REACHED 10E-10 AHPS ON THE INTERMEDIATE RANGE (I/R) r THE CONTROL POWER FUSE FAILED IN I/R CHANNEL N36r CAUSING THE LOW POWER HIGH FLUX RiACTOR TRIP BISTABLE TO ACTUATE THE REACTOR TRXP BREAKERS OPENED AND ALL OF THE UNINSERTED RODS DROPPED INTO THi CORE ~ (KEFF WAS < ~ 99 AT THE TINE OF THE ACTUATION ) THE OPiN REACTOR TRIP BREAKERS COINCIDENT WITH AVERAGE REACTOR COOLANT TEMPERATURE BELOW 564 DEGREES F RESULTED IN A FEEDWATER ISOLATION THE UNIT WAS IN NODE 3r HOT STANDBYr AT THi TINE OF THIS INCIDENT~

SUBSEQUENT TO- THIS EVENTS All OPERATIONS NUCLEAR EQUIPMENT OPERATOR (NEO) WAS SENT TO THE UNIT 1 COOLING TOWERS TO XNSPECT THEN FOR ICE ~

DURING THE INSPECTXONr HE FOUND THAT A FRACTURE OF THE CONDENSER CIRCULATING WATER (RC) PIPING HAD OCCURRED ~ THE FEEDMATER ISOLATION SIGNAL MAS RESET AND THE AFFECTED VALVES WER'E RETURNED TO THEIR PREVIOUS ALIGNHENT WORK REQUESTS MERE XSSUED TO INVESTIGATi AND REPAIR I/R CHANNEL N36 AND PERFORM TESTXNG ON CHANNEL N36. THE RC PIPING WAS REPAIREDr AND THE UNIT WAS RETURNED TO POWER ~ ALSO THE SHUTDOWN PROCEDURE WAS REVISED TO RAISE THE LOll LIHXT RC TENPERATURE TO PRiVENT FURTHER BRITTLE FRACTURE PROBLEMS WITH THE RC SYSTEH

0 o e o o e e o o a e o e a e e e e e e o 0 tl I

FORM 155 LER SCSS DATA 08-30-91

• • • • • • • • • • 4 k ********************** 4 *********************************

DOCKET YEAR LER NUMBER REVISION OCS NUMBER NSIC EVENT DATE 414 1986 006 0 86052901 0 5 1 99576 04/1 7/86

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • +*******

g DOCKET:414 CATAWBA 2 REGXON: 2 TYPE:PWR NSSS:WE ARCHITECTURAL ENGINEER: DUKE FACILITY OPE RATOR: OUK E POMER CO ~

SYMBOL: OPC

,COMMENTS OTHER REPORTABILITY-50 72(B) (2) (IX) ~ STEP 1: COMP HSC-INOUCTOR STEP 2:

MODEL 5V1 21 00/TSMB WATCH-LEST CODES FOR THIS LER ARE:

941. REPORT ASSOCIATED METH 10 CFR 50 72 REPORTABILXTY CODES FOR THIS LER ARE:

13 10 CFR 50.73(a) (2) (iv): ESF actuations 21 OTHER: Voluntar y reports special reportr Par t 21 report~

etc LERS:

y REFERENCE 1 413/85-012 ABSTRACT POMER LEVEL OOOX ~ ON APRIL 17/ 1986~ AT APPROXIHATELY 1617 120 VAC VITAL INSTRUMENTATION ANO CONTROL POMER (EPG) SYSTEH HOURS'HE, INVERTER 2EIB HALFUNCTIONEOr RESULTING IN THE LOSS OF CHANNEL B CONTROL POMER THIS RESULTEO IN A LOM LEVEL INDICATION ON CHANNEL 2 FOR ALL FOUR STEAM GENERATORS (S/GS) THE LOW LEVEL INDICATION CAUSED THE FEEOWATER CONTROL BYPASS VALVES FOR S/GS Ar Cr ANO Dr WHICH WERE XN THE AUTO POSITIONS TO OPEN AND FEED THE S/GS ~ AT 1620 10 HOURSr FEEOWATER ISOLATION INITXATED ON S/G A HIGH-HIGH LEVEL ~ THE S/G LEVELS MERE RETURNED TO NORHAL AND THE FEEOMATER ISOLATION SIGNAL MAS RESET FEEDWATER VALVES WERE THEN REALIGNED TO THE S/GS ~ THE UNIT MAS IN NODE 4r HOT SHUTDOWNS AT THE TIME OF THXS INCIDENT~ THIS INCIDENT IS ASSIGNED CAUSE CODE Xr OTHER/ DUE TO AN EQUIPHENT FAILURE~

AN INDUCTOR IN INVERTER 2EXB HAO BURNED OUT ~ THiS INCXOENT IS REPORTABLE PURSUANT TO LO CFR 50 73'ECTION (A) (2) (XV) AND LO CFR 50 ~ 72'ECTION (B) (2) (IX) .

4 LI ~

e FORM 156 LER SCSS DATA 08-30-91

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • 4**********************************

DOCKET Y AR LER NUHBER REVXSXON OCS NUNBER NSIC EVENT DATE 414 1986 036 0 8609150178 200921 08/07/86 g DOCKET:414 CATAWBA 2 REGION: 2 TYPE=PWR NSSS:WE ARCHITECTURAL ENGINEER: DUKE FACILITY OPERATOR: DUKE POMER CO ~

SY/1BOL: DPC COHNENTS OTHER REPORTABILITY - 50 72(B) (2) (II)

WATCH- IST CODES FOR THIS LER ARE:

941 REPORT ASSOCIATEO WITH 10 CFR 50 72 6

CODES FOR THIS g REPORTABILITY 10 10 CFR 50.73(a) (2) (i):

LER ARE:

Shutdowns or +echnical specification violations.

21 OTHER: Voluntary reportr special r eporti Part 21 repor tr 73(a)(2)(iv): actuations etc'3 10 CFR 50 ESF REFERENCE LERS:

1 413/85-001 2 413/85-019 3 414/86-007 ABSTRACT POWER LEVEL - OOOX ON AUGUST 7 1986 AT APPROXIHAT LY 1230 HOURS TECHNICIANS MERE ADJUSTING THE OUTPUT FREQUENCY ON A 125 VDC/120 VAC VITAL INVERTER WHEN THEY INADVERTENTLY CAUSED THE INVERTER TO TRIP ~

THIS RESULTED IN REACTOR TRIP SIGNALS B" ING GENERATED BECAUSL- OF LOSS OF POWER TO THE SOURCE AND INTERNEDIATE RANGE EXCORE NEUTRON DETECTORS ~ THE REACTOR TRIP SIGNALS RESULTED IN A TURBINE TRIP SIGNAL ANO MAIN FEEOMATER ISOLATION ALSOr LETDOWN ISOLATION OCCURRED DUE TO LOSS OF POWER TO A PRESSURIZER LEVEL INSTRUNENT CHANNEL LETDOWN ANO FEcOMATER FLOWS MERE QUICKLY RE-ESTABLISHED ~ THE INVERTER WAS RETURNED TO SERVICE AT 1312 07 HOURS ~ THE UNIT MAS IN NODE 3r HOT STANDBYr AT THE TINE OF THIS INCIDENT~ THIS INCIDENT IS ASSIGNED CAUSE CODE Ar PERSONNEL ERROR THE RESPONSIBLE SUPERVISOR FAILEO TO ADEQUATELY INSTRUCT THE TECHNICIANS TO PROPERLY INVESTIGATE ANO REVIEW THE PROBLEH WITH THE INVERTER BEFORE PERFORMING CORRECTIVE NAINTENANCE ALSO THE TECHNICIANS FAILED TO RECOGNIZE THAT THE INSTRUCTIONS THEY HAO RECEIVED MERE INCORRECT FOR THE CONDITIONS THEY HAO OBSERVED ~ THIS INCIDENT IS REPORTABLE PURSUANT TO 10 CFR 50 ~ 73r SECTION (A) (2) (IV) AND 10 CFR 50 72 SECTION (B) (2) (II)

0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 e 0 0 0 J

1 If 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 9

FORM 157 LER SCSS DATA 08-30-91

• • • • • • • • • • • • 9>*******************************************************

DOCKET YEAR LER NUMBER REVISION DCS NUMBER t'JSIC cVENT DATE 414 1988 019 8809290344 2't0568 05/27/88

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • +

DOCKET:414 CATAMBA 2 TYPE:PWR REGION: 2 NSSS:WE ARCHITECTURAL ENGXNE ER: DUKE FACILXTY OPERATOR: DUKE POWER CO SYMBOL: DPC HATCH-LIST CODES FOR THIS LER ARE:

34 DESIGN ERROR OR INADEQUACY 36 INADEQUATE TRAINING REPORTABXLXTY CODES FOR THIS LER ARE:

13 10 CFR 50 73(a) (2) (iv): ESF actuations.

REFERENCE LERS:

1 413/87-006 2 414/86-022 3 414/87-007 ABSTRACT POMER lEVEL 000'N MAY 27i 1988r AT 1403 21: HOURS> AN UNDERVOLTAGE CONDITION OCCURRED ON THE 240/120 VAC AUXILXARY CONTROL POWER SYSTEt<

DISTRIBUTION PANEL 2KXPB ~ THIS UNDERVOLTAGE CONDITION OCCURRED WHILE CYCLING THE ALTERNATE SOURCE TO KXPB BREAKER IN AN ATTEMPT TO Ct EAR AN INDICATED ALTERNATE SOURCE UNDERVOLTAGE THE INDICATED UNDERVOLTAGE CONDITION MAS NOTICED WHILE ISOLATING THE 2KXPB INVERTER FOR CORRECTIVE MAINTENANCE THE PANEL'S POWER SUPPLY HAD PREVIOUSLY BEEN SWAPPED TO THE ALTERNATE SOURCE TO KXPB SUPPLY FROM REGULATED AC POWER SOURCEr 2RDB ~ UPON NOTICING THE LOM ALTERNATE SOURCE VOLTAGE; INDICATION ON THE MANUAL BYPASS SWITCHr 'KXMBr* THE INVOl VED NUCLEAR OPERATIONS SPECIALIST (NOS) REQUcSTED ASSISTANCE FROM CONTROL ROOM PERSONNEL A CONTROL ROOM OPERATOR (CRO) UTILIZED THE OPERATOR AID COMPUTER (OAC) GRAPHICS TO VERIFY THAT A LOM VOLTAGE WAS INDICATED'HE CRO RECOMMENDED THAT THE NOS CYCLE THE ALTERNATc SOURCE TO KXPB BREAKER TO CLEAR THE UNDERVOlTAGE CONDITION~ CYCLING THE BREAKER CAUSED AN APPROXIMATE 5 SECOND LOSS 0. POWER TO THE LOADS SUPPLIED BY THE KXPB DISTRIBUTION PANELr ONE OF WHICH WAS THE CONTROL POMER TO MAIN FEEDWATER PUMP TURBINE (CFPT) 2B ~ THIS RESULTED IN A DECREASE XN CFPT 2B SPEEDr LOM STEAM GENERATOR LEVELSr AND A SUBSEQUENT AUTOMATIC REACTOR TRIP" THE UNIT WAS AT 100X POWER AT THE TIME OF THIS INCXDENT

0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 N

~ ~

o 0 e e e o o a o o a a o e o o e e e e e 0

FORM 158 LER SCSS DATA 08-30-91.

e ********************************************************************

DOCKET YEAR LER NUMBER REVISION DCS NUMBER NSIC EVENT DATE 414 1988 024 1 8906060078 214077 06/22/88

• • • • • • • • • • • • • • • A**************A******************Br******************

e DOCKET:414 CATAWBA 2 REGION: 2 TYPE:PWR NSSS:ME ARCHXTECTURAL ENGINEER: DUKE FACILITY OPERATOR: DUKE POWER CO SYHBOL: OPC COHMENTS STEP 2: COHP RLX - LATCHING TRANSFER RELAY ~

g WATCH-LIST CODES 40 PROCEDURAL FOR THIS LER ARE:

DEFXCIENCY CODES FOR THIS LER ARE:

g REPORTABILITY 13 10 CFR 50.73(a) (2) (iv): ESF actuations.

y REFERENCE 1

LERS:

414/87-009

~ ABSTRACT POWER LEVEL 098X~ ON 6/22/88~ AT 0120 HOURS'HE UNIT 2 TURBINE DRIVEN AUX - FEEDWATER PUHP (CAPT) AUTOMATICALLY STARTED AND SUPPLIED FLOW TO STEAH GENERATORS (S/GS) B ANO C ~ IN ADDITIONw CONTROL ROOM XNDICATXON WAS LOST FOR 600V BLACKOUT LOAD CENTER 2LXI AND PRESSURIZER HEATER A ~ THIS INCIDENT OCCURRED MHEN INSTRUNENTATION AND ELECTRICAL (XAE) PERSONNEL DISCONNECTED THE CABLE SUPPLYING ALTERNATE 125 VDC TERMINALS 'T CONTROL POWER FROM THE ALTERNATE BATTERY (2DPB) XN ORDER TO CLEAN ITS WAS UNKNOWN TO IAE AND OPERATIONS P RSONNEL THAT 125 VDC CONTROL POWER HAD PREVIOUSLY BEEN AUTOMATICALLY TRANSFERRED FROH THE NORNAL SUPPLY (OISTRXBUTXON CENTER 2CDA) TO THE ALTERNATE SUPPLY (2DPB). THE CONTROL ROON OPERATOR (CRO) STABILIZED THE INCREASING LEVELS If< S/GS 8 AND Cr AND SUBSEQUENTLY SECURED THE CAPT'HE UNIT SUPERVISOR RESET THE RELAY WHICH TRANSFERS 125 VDC CONTROL POWERr RESTORING THc NORMAL POMER SUPPLY TO THE AFFECTED LOADS UNIT 2 WAS AT 98fi POWERS AT THE TINE~ THE CAUSE OF THE SWAP OF 125 VDC CONTROL POWER FROM THE NORMAL TO ALTERNATE SUPPLY COULD NOT BE DETERMINED THE CONTROL ROOtd STATUS INDICATXON LiGHT MAS OFF'NDXCATXNG THAT 125 VDC BLACKOUT CONTROL POMER MAS BEING SUPPLIED BY THE NORMAL SUPPLY'VEN THOUGH XT WAS BEING SUPPLIED BY THE ALTERNATE SUPPLY ~ THIS XNCIDENT HAY HAVE BEEN PREVENTED BY NORE THOROUGH PROCEDURES

0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

~ I C

li

~,~

0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 4I

FORH 159 LER SCSS DATA 08-30-91

• • A******************************4*******************************i'**

DOCKET YEAR LER NUHBER REVISION DCS NUHBER NSIC EVENT DATE 425 1990 004 0 9005160032 218185 04/11/90

~ ********************************************************************

DOCKET:425 VOGTLE 2 TYPE:PWR REGION: 2 NSSS:WE ARCHITECTURAL LNGXNEER: BESS FACILITY OPERATOR: GEORGIA POMER CO ~

SYMBOL: GPC

~ WATCH-LIST CODES FOR 35 HUMAN ERROR THIS LER ARE CODES FOR THIS

~ REPORTABILITY 10 10 CFR 50.73(a) (2) (i):

LER ARE:

Shutdowns or technical speci f ication violations REFERENCE LERS:

1 424/87-046 2 424/87-077 3 424/87-080 ABSTRACT POWER LEVEL 100% ~ ON APRIL 11r 1990r THE UNIT SHIFT SUPERVISOR r (USS) FOR THE ONCOHING NIGHT SHIFT MAS REVIEMING THE UNIT SHIFT SUPERVISOR S LOG ~ AT 1615 COTr HE NOTICED THAT THE POWER RANGE CALORIMETRIC CHANNEL CALIBRATION HAD NOT BEEN PERFORNED SINCE 1045 CDT ON APRIL 10r 1990 ~ TECHNICAL SPECIFICATION (TS) 4 ~ 3 ~ 1 ~ 1~ TABI E 4 ~ 3 1r ITEM'Ar REQUIRES THAT THIS CALIBRATION BE PERFORMED DAILY FOR TH'E POWER RANGE NEUTRON FLUX HIGH SETPOINT THE USS ON DUTY MAS ADVISED AND PERSONNEL BEGAN TO PERFORN THE NECESSARY CALIBRATION THE SURVEILLANCE INTERVAL PLUS THE 25/ GRACE PERIOD (24 HOURS PLUS 6 HOURS) EXPXRED AT 1645 CDT AND THE UNIT ENTERED OPERATION UNDER TS 3 0~3 BY 1736 CDT THE CALORINETRIC CALIBRATION WAS SATXSFACTORII Y COHPLETED WITH NO AOJUSTHENTS REQUIREOr AND THE UNIT EXITED OPERATION UNDER TS 3 0 3 ~ THE CAUSE OF THIS EVENT MAS A COGNITIVE PERSONNEL ERROR BY THF USS ON DUTY/ RESULTING IN A FAILURE TO COHPLY WITH PROCEDURE 14000-Cr "OPERATIONS SHXFT AND DAILY SURVEILLANCE LOGS ~" TH USS WAS COUNSELED REGARDING THE IMPORTANCE OF CONPLXANCE MXTH TS REQUIREMENTS

0 0 0 0 0 0 0 0 0 0 0 4 0 0 0 0 0 ~4 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

FORH 160 LER SCSS DATA 08-30-91

• • • • 4***************************************************************

DOCKET YEAR LER NUMBER REVISION DCS NUt<BER NSIC EVENT DATE 440 1987 042 0 8707240079 205486 06/17/87 e DOCKET:440 PERRY 1 REGION: 3 TYPE:BMR NSSS:GE ARCHITECTURAL ENGINEER: GLBT FACXLITY OPERATOR: CLEVELAND ELECTRIC XLl UHXNATZNG CO ~

SYMBOL: CEZ COMMENTS STEP 1: PART NO 169C8671-P013 WATCH-LIST CODES FOR THIS LER ARE:

20 EQUIPMENT FAILURE 34 DESIGN cRROR OR INADEQUACY REPORTABILITY CODES FOR THIS LER ARE:

13 10 CFR 50 ~ 73(a) (2) (iv): ESF actuations.

REFERENCE LERS:

1 440/86-044 ABSTRACT POWER LEVEL 023K ~ ON JUNE 17r 1987 AT 1139r A REACTOR PROTECTION SYSTEH (RPS) ELECTRICAL PROTECTXON ASSEMBLY (EPA) BREAKER TRIPPEDr RESULTXNG IN DEENERGIZATION OF RPS BUS A AND CLOSURE OF THE OUTBOARD HAIN STEAN ISOLATION VALVES (NSIV) - CLOSURE OF THE i4ISXVS RESULTED ZN A REACTOR SCRAM LOSS OF THE RPS BUS ALSO RESULTEO IN A NUCLEAR STEAM SUPPLY SHUTOFF SYSTEM (NSSSS) ISOLATION SIGNAL AND CLOSURE OF THE ASSOCIATED CONTAXNNENT ISOLATION VALVES~ THE ROOT CAUSE OF THE CONTAINHENT ISOLATION MAS A FAILED COMPONENT OF AN EPA. LOGIC CARO WHICH PRODUCED SPURIOUS OUTPUT VOLTAGE PULSES AND RESULTANT TRIPPING OF THE EPA BREAKERS THE CAUSE OF THE NSIV CLOSURE AND RESULTANT SCRAH MAS THE DESIGN OF THE POWER SUPPLIES TO THE MSXV PILOT VALVE SOLENOZDS BOTH OF THE THE'SOLENOIDS FOR EACH OUTBOARD HSIV MERE POWERED FROH THE SANE RPS BUSr THEREFOREr MSXV CLOSURE RESULTED WHEN NORMAL RPS POMER MAS LOST TO BOTH SOLENOIDS THE LOGIC CARDS FOR THE RPS BUS A EPAS MERE REPLACEOr CHANGES MERE llADE TO THE APPROPRIATE PLANT OPERATING INSTRUCTZONSr AND SURVEILL'ANCE TESTING OF THE NORMAL RPS POWER SUPPLY OUTPUT BREAKERS MAS CONPLETED ON JUNE 20 THE EPA CARDS FOR THE NORMAL RPS B POMER SUPPLY MERE REPLACED AND.THE POWER SUPPLY CONFIGURATION TO THE INBOARD AND OUTBOARD HSXV SOLENOXDS WAS MODIFIED DURING THE CURRENT PLANT OUTAGE

0 0 0 0 0 0 0 ~ 0 0 0 0 0 0 0 J

1 I r 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

FORM 161 LER SCSS DATA 08-30"91 e *******************************+************************************

OOC KET YEAR L ER NUi4lB ER REVISION DCS NUMBER NSXC EVENT DATE 440 1987 070 1 8807210080 209915 10/24/87

• • • • • • • • • • • • • • • • • • • • • • • • • 4****************************************+*

DOCKET:440 PERRY 1 TYPE:BMR REGION: 3 NSSS:GE ARCHITECTURAL'NGINEER: GLBT FACILITY OPERATOR: CLEVELAND ELECTRIC ILLUNINATING CO ~

SYNBOL: CEX MATCH-LXST CODES FOR THXS LER ARE:

20 EQUIPNENT FAILURE CODES FOR THIS LER ARE:

~ REPORTABILXTY 13 10 CFR 50.73(a) (2) (iv): ESF actuations y REFERENCE 1

LERS:

440/86-004 2 440/86-050 3 440/86-071 4 440/86-072 5 440/86-091 6 440/87-042 7'440/88-006 ABSTRACT POWER LEVEL 100X ON OCTOBER 24'987 AT 0101r A REACTOR PROTECTION SYSTEM (UPS) EL"CTRICAL PROTECTION ASSEMBLY'(EPA) BREAKER TRXPPEO OUE

. TO AN OVERVOLTAGE CONDITION RESULTXNG IN DEENERGXZATION OF RPS BUS A AND A NUCLEAR STEAM SUPPLY SHUTOFF SYSTEM (NSSSS) DIVISION 1 BALANCE OF PLANT (BOP) ISOLATION AFFECTED SYSTEHS AND COMPONENTS WERE RESTORED BY 0215 THE ROOT CAUSE OF THIS EVENT IS INDETERMINATE~

INVESTIGATION HAS DETERMINED THAT THE EPA BREAKERS DIO TRIP ON A HXGH RPS MOTOR GENcRATOR (HG) SET OUTPUT VOLTAGE~ HOWEVERr EXTENSIVE TROUBLESHOOTING XOENTXFIED NO EVIDENT CAUSE FOR THE MG SET OUTPUT VOLTAGE DRIFTING HIGH THE POTENTXAL CAUSE OF THIS EVENT WAS ISOLATED TO THE VOLTAGE REGULATOR ANO/OR RHEOSTAT THEREFOREr BOTH WERE REPLACED AND SENT TO THE VENDOR FOR ADDITIONAL EVALUATION THE VENDOR ANAI YSIS DXD NOT IDENTIFY ANY INDIVIDUAL FAILURES OR OPERATIONAL ANOHALIES OF THESE COMPONENTS. THE EXXSTING REPETITIVE TASK WHICH IS PERIODICALLY PERFORNED ON THE RPS HG SETS AND THE ASSOCIATED CONTROL CIRCUITRY'AS BEEN REVISED TO ENSURE THAT THE OUTPUT VOLTAGE RHEOSTAT IS PROPERLY ADJUSTED ANO SECURED IT ALSO REQUIRES CLEANING OF THE e RHEOSTAT MXPER AND MINOXNGS APD TESTING FOR DEAD SPOTS THROUGHOUT THE FULL RANGE OF RESISTANCE

0 0 0 ~ 0 0 0 0 0 0 0 0 0 0 0 0 0 4 J

), I 0 e o e o e o o e e e e o e o o e e e o o 0

FORM 162 LER SCSS DATA 08-30-91

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • 4*********************************

DOCKET YEAR LER NUMBER REVISION DCS NUMBER NSIC EVENT DATE 440 1988 012 0 8806020232 209479 04/27/88

• • • • • • • • • • • 4********************************************************

e OOCKCT:440 PERRY 1 REGION 3 TYPE:BWR NSSS:GE ARCHITECTURAL ENGXNEER: GLBT FACILITY OPERATOR: CLEVELAND ELECTRIC ILl UMINATING CO SYMBOL: CEI y COMMENTS

$ PA/CTP/2 REM: SCRAM ON LOSS OF FEEDWATER HPCS UNAVAILABLE' WATCH-I IST CODES FOR THIS LER ARE:

35 HUMAN ERROR 40 PROCEDURAL, DEFICIENCY REPORTABILITY CODES FOR THIS LER ARE:

13 10 CFR 50 73(a) (2) (iv): ESF actuations ABSTRACT POWER LEVEL 100X ON APRIL 27 1988 AT 2209 AN AUTOMATIC REACTOR SCRAM OCCURRED DUC 'TO A REACTOR WATER LEVEL OF LESS THAN LEVEL 3

(+177 7 XNCHES ABOVE THE TOP OF ACTIVE FUEI ) ~ THE LOW WATER LEVEL OCCURRED AFTER AN IMPROPER TRANSFER OF DC POWER SUPPLIES RESULTING XN A TEMPORARY LOSS OF AC CONTROL POWER FOR THE HOT SURGE TANK LEViL CONTROL VAl VES AND A SUBSEQUENT TRIP OF ALL OPiRATING FEEDWATER PUMPS THi CAUSES OF THE EVENT ARE PERSONNEL ERROR AND PROCEDURAL-INAOEQUACY A MISINTERPRETATION OF THE INSTRUCTION DESCRIBING OC POWER SUPPLY TRANSFERS PLACED THE DC ELECTRICAL SYSTEM XN A NON-RECOMMENDED LINiUP LEADING TO THE LOSS OF VITAL 120 VAC POWER FED FROM THE DC BUS VIA AN INVERTER THE INSTRUCTION WAS CONFUSING AND DIFFICULT TO XMPLEMENT CORRECTIVE ACTIONS TO PREVENT RECURRENCE INCLUDEr COUNSiLING OF THE OPERATORS INVOLVED REGARDXNG THEIR RESPONSIBILITIES TOWARDS FAIMILARITY WITH. INSTRUCTIONS AND PROCEDURAL COMPLIANCEr TRAINXNG FOR ALL OPERATORS REGARDING THE SEQUENCE OF EVENTSr AND REVISING THE APPROPRIATE SYSTEt'f OP'ERATING INSTRUCTIONS TO PROVIDE GREATER EASE OF USE BY THE OPERATOR ~

0 e o o e o o o o o ~ e e o e e o e e e o 0 4 I, t

Pl g

FORH 163 LER SCSS DATA 08"30-91 DOCKET YEAR LER NUMBER REVISION DCS NUHBER NSIC EVENT DATE 445 1990 002 0 9004170049 217600 03/05/90 DOCKET:445 COHANCHE 1 TYPE:PWR REGION: 4 NSSS:ME ARCHITECTURAL ENGINE ER: GI BB FACILITY OPERATOR: TEXAS UTILITIES GENERATING CO SYN BOL: TUG COHHENTS STEP 3 COMP XPWT FERRORESONANT TRANSFORMERS STEPS 5r12 MODEL NO ~

ESELIVr 7a5 KVA~ STEP 10: COHP LX CONTAINHENT ISOLATION AND SWAP OF CHARGING PUMP SUCTION FROID THE VCT TO THE RWST MATCH- IST CODES FOR THIS LEP. ARE:

20 EQUIPMENT FAILURE 941 REPORT ASSOCIATED MXTH 10 CFR 50 72 REPORTABILITY CODES FOR THIS LER ARE:

13 10 CFR 50.73(a) (2) (iv): ESF actuations.

REFERENCE LERS:

1 445/90-001 2 498/89-008 ABSTRACT POWER LEVEL 000% AT 0155 CST ON 3/5/90r WHILE CONDUCTING COLO ROD DROP TESTXNGr A BLOWN FUSE IN INVERTER IV1PC1 RESULTED IN A REACTOR TRIP AND A SOURCE RANGE FlUX DOUBLING (SRFD) SiGNAL THE DISTRIBUTION PANELBOARD MAS RE-ENERGIZED ON ALTERNATE POMER ~ THIS RE-ENERGIZATION CAUSED A HOHENTARY SPIK ON A MXDE RANGE REACTOR COOLANT SYSTEM (RCS)

PRESSURE CHANNEL WHICH CLOSED THE RESIDUAL HEAT REHOVAL (RHR) HOT LEG SUCTION VALVE RESULTING IN THE TEHPORARY LOSS OF SHUTDOMN COOLING ~

SHUTDOMN COOLING MAS RESTORED AT 0228 CST ON 3/5/90 ~ AT APPROXIMATELY 0248 CSTr AFTER VERIFYING THAT INDICATXON MAS APPROPRIATE FOR PLANT CONDXTIONSr THE SRFD SIGNAL WAS RESET AND AFFECTED COMPONENTS RESTORED TO THEXR ORIGINAL POSITION ~ THE ROOT CAUSE FOR THE FUSE FAILURE HAS NOT BEEN DETERMINED ~ THE POSSXBLE CAUSES IDENTIFIED INCLUDE FAILURE OF THE FERRO RESONANT TRANSFORHERr AND LOOSE CONNECTIONS IN THE GATING CZRCUIT CORRECTIV ACTiONS INCLUDED THE REPlACEMENT OF THE FERRO-RESONANT TRANSFORHER AND A REWORK OF ALL LOOSE, CONNECTIONS IN THE INVERTER ~ A DETAILED VXSUAL XNSPECTXON OF THE THREE OTHER SIMILAR INVERTERS MILL BE PERFORHED DURING THE NEXT COLO SHUTDOWN OF SUFFICIENT DURATION THIS INSPECTXON MILL INCLUDE THE VERIFICATION OF ALL.BOLTED AND SOLDERED CONNECTIONS IN THE INVERTERS

e e o e e e o o e e e e e a o o e e e % 0 4

I 0 e e e o o e o o e e e e e o o o o e o e

FORM 164 LER SCSS DATA 08-30-91 DOCKET YEAR LER NUHBER REVISION DCS NUtlBER NSXC EVENT DATE 455 1987 007 1 8709080017 206288 05/04/87

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • %*************A***********

e,DOCKET:455 BYRON 2 TYPE:PWR REGION: 3 NSSS: WE ARCHITECTUR Al ENGINEER: SLXX FACILITY OPERATOR: COHNONMEALTH EDISON CO SYMBOL: CWE

~ COHtlENTS STEP 2: PART NUMBER 1815A70H23 STEP 3: PART NUHBER 1538A73H10 STEP 1:

CAUSE AX - CAI IBRATION

~

WATCH-LEST CODES FOR THXS LER ARE:

20 EQUIPNENT FAILURE REPORTABILITY CODES FOR THIS LFR ARE:

13 10'- CFR 50 73(a) (2) (iv): ESF actuations.

ABSTRACT POWER LEVEL 088K~ ON YiAY 4x 1987r AT 0644< THE UNIT 2 REACTOR TRXPPEO DURING THE PERFORMANCE OF THE QUARTERLY POWER RANGE CALIBRATION SURViXLLANCE ON CHANNEL NI-43 UNIT 2 WAS IN HOOE 1 POMER OPERATIONS AT 88K POWER ~ AS A REQUXREtlENT OF THE SURVEILLANCE~

THE POWER RANGE CHANNEL ~ S BXSTABLES WcRc TRIPPED ~ DURING THE CONDUCT OF THE SURVEXLLANCEr THE INSTRUMENT BUS 211, BREAKER TRIPPED ~ THIS DE-ENERGIZED CHANNEL N41 ANO TRIPPED XTS BISTABLES THIS SATXSFXCO THE 2 OUT OF 4 LOGIC COINCIDENCE FOR HIGH NEUTRON FLUX REACTOR TRXP ~

AS A NORMAL RESULTS THE STEAt< GENERATOR LEViL RiACHED THE LOM LEVcL AUTOMATIC AUXILIARY FEEDMATER (AF) PUHP START SETPOINT ~ THE 2B DIESEL DRIVEN AF PUMP STARTED~ AS EXPECTED. THE 2A AF PUNP DXO NOT START AS A RESULT OF THE INSTRUMENT BUS 211 TRIP THE UNIT WAS RECOVERED CONSISTENT WITH EMERGENCY PROCEDURES WITHOUT INCIDENT THE CAUSE OF THE INSTRUHENT BUS 211 TRIP IS OUE TO A FAILURE OF A SILICON CONTROLLED RECTIFIER AND A CAPACITOR IN THE INVERTER ~ THE CAPACITOR FAILURE CAUSED THE RiCTIFIER FAILURE THE FAILURE t<ECHANXStl OF THE CAPACXTOR COULD NOT BE OETERHINED AND IS ATTRIBUTABLE TO NORNAL WEAROUT THE COMPONENTS WERE REPLACED AND THE BUS RE-ENERGIZED'HERE MERE NO ADVERSE SAFETY CONSEQUENCES'

e v

~ v

~ a

FORM 165 LER SCSS DATA 08-30-91

• • • • • • • • • • • • • • • • • • • • • • A***************A*****************************

DOCKET YEAR LER NUtlBER REVXSION DCS NUMBER NSIC EVENT DATE 455 1990 006 0 9010150142 219766 09/03/90 DOCKET:455 BYRON ? TYPE:PWR REG!OiN: 3 NSSS:WE ARCHITECTURAL ENGIttEER: SLXX FACII ITY OPERATOR: COHNONMEALTH EDISON CO SYMBOL: CME COMMENTS STEP 11: PART NO 443A322H17 STEP 12: PART NO A501950 STEP 17: CAUSE AX PLANNED LOSS DURING SURVEILLANCE MATCH-LIST CODES FOR THIS LER ARE:

32 COMMUNICATION PROBLEtl 40 PROCEDURAL DEFICIENCY 913 UPDATE NEEDEO 941. REPORT ASSOCIATEO WITH 10 CFR 50 72 REPORTABXLITY CODES FOR THIS LER ARE:

13 10 CFR 50.73(a) (2) (iv): ESF actuations.

REFERENCE LERS:

454/90-001 2 454/90-009 ABSTRACT POWER LEVEL 000% ~ ON 9/3/90 AT APPROXItlATELY 0805r WITH UNIT 2 IN MODE 5 (COLD SHUTDOWN) 2BOS 3>>2 ~ 1>>1 ~ A 1r "UNIT TMO TRAIN A MANUAL SAFETY INJECTION XNITIATXON AND HANUAL PHASE A INITIATION SURVEILLANCE " WAS BEING PERFORMED PER THE REFUELING OUTAGE SCHEDULE AFTER PERFORHING THE NORMAL SAFETY INJECTION (SI) (JE)

THAT THE 2C REACTOR CONTAINMENT FAN COOLER (RCFC) LOM SPEED FAN i IT MAS NOTED BREAKER DID NOT CLOSE ATTEMPTS TO Cl OSE THE BREAKER MERE UNSUCCESSFUL'T 08?Or THE 480 VOLT BUS THAT FEEDS THE BREAKER WAS DE-ENERGIZED TO ALLOW REMOVAL OF THE BREAKER AT 0850 WHILE STRIPPING THE BUS OF XTS ALTERNATING CURRENT LOAD~ INSTRUMENT XNVERTERS 211 AND 213 MERE DE-ENERGIZED DUE TO A COtlHUNICATIONS BREAKDOWNS MHEN THE INSTRUMENT BUSES MERE DE ENERGIZEDr THE PRESSURIZER PRESSURE LOM SI AND STEAHLINE PRESSURE LOM SI BLOCKS MERE LOST ON TRAIN A ~ THE UNIT REACTOR OPERATOR WAS UNAWARE THAT THE BLOCKS HAD BEEN LOST AND THE SURVEILLANCE DIO NOT CONTAIN AN EHERGENCY EXIT SECTION TO PROVIDE RESTORATION GUIDANCE ~ AT 090?r THE TRAIN A REACTOR TRIP BREAKER MAS CLOSED PER THE SURVEILLANCE AND A SAFETY INJECTION SIGNAL RESULTED DUE TO A LOSS OF THE REACTOR TRIP INTERLOCK (P-4) WHILE CYCLING THE REACTOR TRIP BREAKER ~ CORRECTIVE ACTIONS INCLUDE A PROCEDURE REVISION TO THE MANUAL SX SURVEILLANCE TO INCLUDE AN EMERGENCY EXIT SECTXON," THXS EVENT MILL ALSO BE INCLUDED IN OPERATOR REQUIRED LISTENING

0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 J

~ s I'y4 N

~ I 0 o e a o o o o e o o e o o o e e e o o o

FORH 166 LER SCSS DATA 08-30-91 DOCKET YEAR LER NUMBER REVISION OCS NUMBER NSIC EVENT DATE 456 1987 010 0 87031 70197 203537 02/09/87

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • %***A*************+************

DOCKET:456 BRAXOMOOD TYPE:PWR e REGION: 3 1

NSSS:ME ARCHITECTURAL ENGINEER: SLXX FACILXTY OPERATOR: COt1HONWEALTH EDISON CO ~

S YH BOL: CME

~ WATCH-LIST CODES FOR 35 HUMAN ERROR THIS LER ARE:

~ REPORTABILITY CODES FOR THIS LER ARE:

13 10 CFR 50.73(a) (2) (iv): ESF -actuations LERS:

~ REFERENCE 456/86-005 2 456/86-011 3.456/87-002 y ABSTRACTLEVEL POWER OOOX AT 1351 ON FEBRUARY. 9 1987 THE OUTPUT BREAKER TO THE INVERTER FEEDING INSTRUMENT BUS 111 MAS INADVERTENTLY TRIPPED ~

THIS CAUSED A LOSS OF CONTROL POWER TO SOURCE RANGE N-31 AND INTERMEDIATE RANGE N-35 GENERATING A REACTOR TRIP SIGNAL ~ THE BREAKER WAS RESET WXTHIN .ONE MINUTE AND FOUR SECONDS>> ALLOWING THE REACTOR TRIP SIGNAL, TO CLEAR ~ THE CAUSE WAS ATTRXBUTED TO PERSONNEL ERROR BY CONTRACTORS WORKING IN THE AREA A BAG WAS BEING LOMERED IN FRONT OF THE CABINET WHICH HOUSES THE BREAKER THAT FEEDS BUS 111 INVERTER AS THE BAG WAS LOWERED IT CANE IN CONTACT WITH THE HANDLE OF THE BREAKERr TRXPPXNG THE BREAK'ERr CAUSING A LOSS OF POWER TO INSTRUMENT BUS 111r ANO A LOSS OF POWER TO SOURCE AND INTERHEDIATE RANGE MONITORS ~ THIS'N'URNr CAUSED A REACTOR TRIP SXGNAL ~ THE ELECTRICAL LINEUP .TO INSTRUMENT BUS 111 WAS VERIFIED THE CONSTRUCTION CRAFT IN THE AREA WERE ORAI LY INSTRUCTED ON THE ACTIONS TO TAKE WHEN EQUIPMENT HAS BEEN XHPACTED THESE CONCERNS HAVE BEEN HIGHLIGHTED TO CONSTRUCTION.MANAGEMENT< ANO-INCREASED ATTENTION IS BEING GIVEN TO CONSTRUCTION IMPACT ON UNIT 1 'PERAS'XON THIS IS EVIDENCED BY THE WORKING OF OVER 900r000 HANHOURS SINCE THE LAST EVENT OF A SIHILAR NATURE

0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 ~ 0 0 0 1

~ '

~'

4 L

k

~ ~

r; v

t' e e e o e o e e e e e e o o e o e a

FORM 167 LER SCSS DATA 08-30-91

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • k*********************A'********

DOCKET YEAR- LER NUNBER .REViSION DCS NUHBER NSIC EVENT DATE 456 1989. 001 1 8903290371 213395 02/06/89

• • • • • • • • • • • • • • %**************%****+************************A********

g DOCKET:456 BRAIDMOOD REGION:

1 3

TYPE:PWR NSSS:WE ARCHITECTURAL ENGINEER: SLXX FACILITY OPERATOR. CONHONWEALTH EDISON ~

BOL:

CO'YH CME WATCH-LIST CODES FOR THIS LER ARE:

20 EQUIPMENT FAXLURE 941 'EPORT-ASSOCXATEO MXTH 10 CFR,50 72 REPORTABILITY CODES FOR THIS LER ARE:

13 10 CFR 50.73(a) (2) (iv): ESF actuations.

ABSTRACT POWER LEVEL OOOO AT 1322 ON 2/16/89 UNIT 1 MAS XN NODE 3 WITH ALL THE CONTROL RODS INScRTED AND THE REACTOR TRIP BREAKERS CLOSED' NOHENTARY LOSS'OF OUTPUT VOLTAGE ON INSTRUMENT INVERTER 112 CAUSED A REACTOR TRIP SIGNAL DUE TO INTERMEDIATE RANGE HIGH FLUX BISTABLE FROM CHANNEL N36 REVERTING TO ITS ESF SAFE CONFIGURATION~ THE OPENING OF THE REACTOR TRIP BREAKERS COINCIDENT WITH RCS AVERAGE TEMPERATURE LESS THAN 364F CAUSED A FEEDWATER ISOLATION SIGNAL 'AT 1323 THE FEEDMATER ISOI ATION SIGNAL WAS RESET AND NORHAL FEEDMATER FLOW WAS ESTABLISHED PERSONNEl IN THc AREA AT THE TINE OF THE EVENT WERE INDEPENDENTLY INTERVIEMEOr 'HEIR ACTIVITIES DID NOT PLACc THEN IN CONTACT WITH

~ INSTRUMENT INVERTER 112 PHYSICALLY OR ELECTRICALLY THE HOHENTARY LOSS OF INSTRUHENT XNVERTER OUTPUT VOLTAGE XS STILL.'UNDER INVESTIGATION THE UNIT 1 INSTRUMENT INVERTERS ARE SCHEDULED FOR AN INSPECTION DURING THE NEXT OUTAGE OF OPPORTUNITY THIS REPORT MILL. BE SUPPLEMENTED SHOULD THE ROOT CAUSE BE DETERMINED'HERE HAVE BEEN PREVIOUS OCCURRENCES OF REACTOR- TRIPS -INVOLVING INSTRUMENT XNVERTERSr

~ ~

HOMEVER THE PREVIOUS EVENTS MERE NOT THE RESULT OF SPURIOUS PERTURBATIONS ON THE INVERTER ~ THE CORRECTIVE ACTIONS FOR THOS EVENTS MERE IMPLEMENTED ADDRESSING BOTH- ROOT AND CONTRIBUTING CAUSES PREVIOUS CORRECTIVE ACTIONS ARE NOT APPLICABLE TO THIS EVENT

0 ~ ~ 0 0 0 0 0 0 0 0 P 0 O'0 0 0 hl IE

'J

~ I

~ j v

0 0 0 0 0 0 0 0 0 ~ 0 i 0 0 0 0 0 0 0

FORH 168 LER SCSS DATA 08-30"91 DOCKET YEAR LER NUMBER REVISION OCS NUNBER NSIC EVENT DATE 456 1989 005 0 8905250462 214012 04/23/89 DOCKET:456 BRAIDMOOO 1. TYPE:PMR REGION: 3 NSSS:WE ARCHITECTURAL ENGINEER: SLXX FACILITY OPERATOR: COHHONMEALTH EDXSON CO SYMBOL: CWE COHHENTS STEP 1 HODEL NO ~ "20 MFDr- 600Vr PART NO ~ 1589A93H23

~ MATCH-LIST CODES FOR THIS 20 EQUIPHENT FAILURE LER ARE:

942 UNUSUAL EVENT REPORTABILITY CODES FOR THIS LER ARE:

10 10 CFR 50 ~ 73(a) (2) (i): Shutdowns or technical specif ication violations.

REFERENCE LERS:

1 456/87-010 2 456/89-001.

ABSTRACT POWER LEVEL 088X ~ AT 1349 ON 4/22/89 INSTRUHENT XNVERTER 111 TRIPPED ~ AT 1409 INSTRUHENT BUS 111 WAS RE-ENERGIZED FROM ITS ASSOCIATED CONSTANT VOLTAGE TRANSFORMER (CVT) AT 1800 MAINTENANCE BEGAN TROUBLESHOOTXNG,THE INVERTER THE XNVERTER WAS NOT REPAIRED WITHIN THE 24 HOURS PROVIDED FOR IN THE TECH SPECS ~ A PLANT SHUTDOWN WAS REQUIRED

'T AT 1248 ON 4/23 A REACTOR SHUTDOWN MAS INITIATED 'N UNUSUAL EVENT WAS DECLARED 1259 THE APPROPRIATE NRC NOTIFICATION MAS HADE ~ AT 1 820 UNIT 1 ENTEREO NODE 3r HOT STANDBY ~ AT 1 500 ON 4/24 A SHORTED CAPACITOR WAS FOUND ~ 'Hc CAPACITOR WAS REPLACED AND THE INVERTER WAS SUCCESSFULLY STARTED AT 0221 ON 4/25 THE INSTRUHENT BUS 111 WAS TRANSFERRED FROM. THE CVT TO THE INVERTER ~ AT 1030 THE INVERTER MAS DECLARED OPERABLE THE CAUSE OF THIS EVENT WAS THE SHORTED CAPACITOR ~ THIS MAS ATTRXBUTED TO NORHAL WEAR ~ THE CORRECTIVE ACTIONS MERE TO RE-ENERGIZE INSTRUMENT. BUS 111 FROH THE CVT ANO REPAIR THE INVERTER A CLEANING AND XNSPECTION PROGRAM MITH A FREQUENCY OF 18 MONTHS MILL BE IHPLENENTED CAPACITOR MILL BE REPLACED WITH A FREQUENCY OF 3 YEARS STARTING WITH THE 9/89 REFUELING OUTAGE'HERE HAVE BEEN PREVIOUS OCCURRENCES OF LOSS OF INVERTER OUTPUT VOLTAGE. PREVIOUS CORRECTIVE ACTIONS ARE NOT APPLICABLE TO THIS EVENT ~

0 0 0 0 0 0 0 0 0 0 0 0 d 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 ~ 0 0 0 0 0 0

FORM 169 LER SCSS DATA 08-30-91

• • • • • • • • • • • • • • • • • • • • • • /*A'*******************************************

DOCKET YEAR LER NUMBER REVISION OCS NUMBER NSXC EVENT DATE 456 1990 003 0 9005020091 218060 03/26/90

~ ********************************************************************

DOCKET:456 BRAIOWOOD 1. TYPE:PMR REGION: 3 NSSS:WE ARCHITECTURAL ENGXNEER: SLXX FACILITY OPERATOR: COHt<ONMEALTH EDISON CO SYMBOL: CME COHMENTS STEP 1: CAUSE AX - TESTING ~

THIS LER ARE:

y WATCH-LXST CODES FOR 35 HUMAN ERROR CODES FOR THIS g REPORTABILITY 10 10 CFR 50.73(a) (2) (i):

LER ARE:

Shutdowns or technical specification violations ABSTRACT POWER LEVEL 093% .AT 0048 ON 3/26/90 POMER RANGE NUCLEAR INSTRUMENT CHANNEL N-41 (PR 41) QUARTERLY CALIBRATION WAS INITIATED THE ACTION STATEHENT OF TECH SPEC 3 ~ 3 ~ 1 REQUIRED THE BISTABLES FOR PR-41. TO BE PLACED IN THE TRIPPED CONOXTION WITHIN 6 HOURS THE INSTRUMENT TECHNICAN (CST) MAS 'INFORHED BY THE CONTROL- ROON SUPERVISOR (SCRE)

THAT THE CALIBRATXON MUST BE CONPLETED WITHIN 6 HOURS OR THE CHANNEL WOULD HAVE TO BE PLACED IN A TRIPPEO CONDITION~ THIS IS ACCOMPLISHED BY REHOVING THE CONTROL POWER FUSES AT 0130 AND 0400 THE CST AND THE INSTRUMENT MAINTENANCE (IH) SUPERVISOR INFORHED THE SCRE THAT THE CALIBRATION WOULD NOT BE CONPLETED WITHIN 6 HOURS THE SCRE PERCEIVEO THAT THE FUSES MERE NEEDED TO PERFORM PORTIONS OF THE CALIBRATION AND ASSUMED THAT THE CST MOULD RENOVE THEN WHEN THEY WERE NO LONGER REQUIRED PRIOR TO TURNOVER THE SCRE GLANCED AT THE PR-41 DRAMER ANO OBSERVED THAT BISTABLE LIGHTS WERE ILLUHXNATEO AND ASSUMED THAT THE FUSES MERE REHOVEDr HOWEVER THIS WAS A RESULT OF THE CALIBRATION AT 0717 IT MAS RECOGNIZEO THAT THE FUSES HAD NOT BEEN REHOVEO AT 0719 THE CONTROL POWER FUSES WERE REMOVED THE CAUSE OF THIS 'EVENT MAS PERSONNEL ERROR TRAINING MILL BE CONDUCTEO FOR OPERATING PERSONNEL NUCLEAR INSTRUMENT PROCEDURES THAT REQUIRE COMPONENTS POSITIONED DIFFERENT FROM THE ACTION STATEMENT MILL BE REVISEO TO PROVXDE FOR SCRE NOTIFICATION~

0 0 0 0 0 0 - 0 0 0 0 0 0 0 0 0 0 i 0 s 1 IU P

'I i t

1 ~

0 0 0 0 0 0 i 0 0 0 0 0 0 0 0 0

FORM 170 LER SCSS DATA 08-30-91

• • • • • • • • • • • 4********************************************************

DOCKET YEAR LER NUMBER REVISION DCS NUNBER NSIC EVENT DATE 457 1988 003 0 8803040343 208574 01/31/88 y DOCKET:457 BRAIDWOOD 2 RsGIONi 3 TYPE:PWR NSSS:ME ARCHITECTURAL ENGINEER: SLXX FACILITY OPERATOR: COMHONWEALTH EDISON CO SYMBOL: CME COMMENTS STEP 3: VENDOR CARBONEJ ROUND FIBERGLASS FUSE NO 773E4040 STEP 2: VENDOR FERRAZ SNP/E WATCH-LIST CODES FOR THIS LER ARE:

35 HUMAN ERROR 941 REPORT ASSOCIATED METH 10 CFR 50 72 REPORTABILITY CODES FOR THIS l ER ARE:

13 10 CFR 50 ~ 73(a) (2) (iv): ESF actuations.

REFERENCE LERS:

1 457/86-005 3 457/87-002 4 457/87-010 ABSTRACT POWER LEVEL OOOX AT 1052 ON JANUARY 31' 988r A REACTOR TRIP SIGNAl

'WAS RECEIVED AS A RESULT OF THE DE-ENERGIZATION OF INSTRUMENT BUS 212 THE DE-ENERGIZATXON MAS CAUSED BY CONTRACTOR. PERSONNEL MORKXNG IN THE AREA ~ THE CONTRACTORS WERE PREPARING THE INVERTER CABINET FOR BUS 212 FOR PAINTING THE BUS WAS RE-ENERGIZED FROM ITS ASSOCXATEO CONSTANT VOLTAGE TRANSFORHERr THE PAINTERS WERE TOLD TO DISCONTINUE WORK ON THE INVERTER CABINETr AND A FUSE WHICH WAS BLOWN AS' RESULT OF IMPROPER DE-ENERGIZATION OF THE BUS WAS REPLACED ~ THERE HAVE BEEN FOUR PREVIOUS OCCURRENCES

IS

\ S S

0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

FORM 171 LER SCSS DATA 08-30-91 DOCKET YEAR LER NUMBER REVISION DCS NUMBER NSIC EVENT DATE 457 1988 008 1 8806170151 209680 02/20/88 DOCKET:457 B RAID WOOD 2 TYPE:PWR REGION: 3 NSSS WE ARCHITECTURAL'NGINEER: SLXX FACILITY OPERATOR: COMMONWEALTH EDISON CO ~

SYMBOL: CWE COMMENTS STEP 4: MODEL'NO ~ '70B36i PART NO~ 23L6066 ~ SD/E/1 ~

WATCH-LIST CODES FOR THIS LER ARE:

37 MANUFACTURING ERROR OR INADEQUACY 941 REPORT ASSOCIATED WITH 10 CFR 50 72 REPORTABILITY CODES FOR THIS LER ARE:

13 10 CFR 50.73(a) (2) (iv): ESF actuatians.

ABSTRACT POWER LEVEL OOOO "AT 0626 ON FEBRUARY 20/. 1988'DURING THE PERFORMANCE OF STARTUP TEST BWSU RD-70 THERE WAS A LOSS OF POWER TO INSTRUMENT BUS 212. THXS RESULTED IN A REACTOR TRIP SIGNAL BEING GENERATED~ AND CAUSED THE REACTOR TRIP BREAKERS TO OPENS THIS LOSS OF POWER ALSO CAUSED A BORON DILUTION PROTECTION SYSTEM ACTUATION AN-EQUIPMENT OPERATOR WAS SENT TO THE BUS AND HE RE-ENERGIZED IT FROM ITS CONSTANT VOLTAGE TRANSFORMER ACTION TO PREVENT RECURRENCE WILL BE TO CONDUCT AN INSPECTION OF'.ALL "FAST-ON-CONNECTORS" FOR HEAT DAMAGE TO THE SAME CONNECTIONS FOR EACH.INVERTER-. ON BOTH UNITS ~ THERE HAVE BEEN NO PREVIOUS. OCCURRENCES

0 0 0 0 0 0 0 t 0 ~ 0 0 0 0 0 5 1'>

0 o e o e e e e o e e e e e e e e e e e 0

FORH 172 LER SCSS DATA 08-30-91

• • • • • • • • • • • • • • • • A***************************************************

DOCKET YEAR LER NUMBER REVISION DCS NUi4lBER NSIC . EVENT DATE 458 1987 015 0 8708120414 205670 06/21/87

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • k*******************************

DOCKET:458 RIVERBEND TYPE:BWR REGION: 4 NSSS:GE ARCHITECTURAL ENGINEER: SMXX FACILITY OPERATOR: GULF STATES UTILITIES SYMBOL: GSU COMMENTS STEP 3: SWITCHOVER FROM NORMAL TO ALTERNATE POWER SUPPLY' WATCH LIST CODES FOR THIS LER ARE:

60 SPURXOUS/ UNKNOWN CAUSE REPORTABIl XTY CODES FOR THXS LER ARE:

13 10 CFR 50 '3(a)(2)(iv): FSF actuations.

REFERENCE LiRS:

1 458/86-024 g ABSTRACT POWER LEVEL'00X~ AT 1015 ON JUNE 21r 1987 WITH THE UNIT IN COLD SHUTDOMt< (tlODE 4) r' REACTOR PROTECTION SYSTEM (RPS) ACTUATION OCCURRED WITH THE CONTROL RODS ALREADY INSERTED ~ INTERNEDIATE RANGE MONITOR (IRH) CHANNEL E SPIKiD CAUSING A HALF SCRAM ON RPS DIVISION A AT THE SAME TIHEr OPERATIONS MAS PLACING RPS DIVISION B ON THE ALTERNATE POWER SUPPLY'OMENTARILY DE-ENERGIXING THE B DIVISION

~

CAUSING A HALF SCRAM Otk THE RPS DIVISION B THE ONLY OTHER ENGINEERED SAFETY FEATURE ACTUATIONS WHICH OCCURRED MERL ANTICIPATED AS A RESULT OF THE RPS POMiR SUPPLY SWAP. OPERATIONS MAS PERFORHING THE SWAP FROM THE RPS NORNAL POWiR SUPPLY, TO ALTERNATE POWER SUPPLY TO SUPPORT ELECTRICAL MAINTENANCE TO, COMPLETE A HODIFICATIOtl AS A RESULT OF LER 86-024 THE "A" RPS BUS HAD BEEN SWAPPED FROM NORHAL TO ALTERNATE POWER SUPPLY EARLIER MITH NO PROBLEMS OCCURRING..MAINTENANCE WORK REQUEST (NMR) 106034 MAS GENERATED TO INVESTIGATE THE SPIKING PROBLEH ON IRM CHANNEL E 'lWR 106034 IS CURRENTLY IN THE PLANNING PHASE AND IS AWAITING A PLANT OUTAGE FOR MORK THERE WAS NO IMPACT ON THE SAFE OPERATION OF THE PLANT OR TO THE HEALTH AND SAFETY OF THE PUBLIC AS A RESULT OF THXS EVENT e THE PLANT WAS IN COLO SHUTDOWN AND ALL CONTROL qRODS WERE ALREADY INSERTED RTED

0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Oi U

~~

Ih 4 0 e e e e e e e e o o e e e o o o e e e o

FOR H 173 LER SCSS DATA 08-30-91

• • • • • • • • • • • • • • • • • • • • • • • • • A******************************************

DOCKET YEAR LER NUMBER REVISION DCS NUMBER NSIC EVENT DATE 458 1 988 018 4 9002120339 216666 08/25/88

• • • • • • • • • • • 4********************************************************

DOCKET:458 RIVERBEND 1 TYPE:BMR g REGION: 4 NSSS:GE ARCHITECTURAL ENGINEER: SMXX FACXLITY OPERATOR: GULF STATES UTILITIES SYi4lBOL: GSU COMMENTS MATCH 975 - REVERSE FLOW IN HPCS INJECTION LINE DUE TO CHECK VALVE FAILURES POTENTIAL FOR LOCA ~ STEP 2: COMP HSC BRUSHESr EFF IX - LOSS OF EXCITER FIELD VOLTAGE STEP 7: COMP X SRV LIFT STEP 25: TYPE 1154 CAUSE LX LACK OF ELECTRONIC DAMPENING STEP 30: EFF HX - REVERSE FLOW IN HPCS INJECTION LINE ~

WATCH-LIST CODES FOR THIS LER ARE:

942 UNUSUAL EVENT 40 PROCEDURAL DEFICIENCY.

975 POSSIBLE SIGNXFICANT. EVENT REPORTABILITY CODES FOR THIS LER ARE:

13 10 CFR 50 73(a) (2) (iv): ESF actuations..

REFERENCE LERS:

1 458/88-004 2 458/88-021.

ABSTRACT POMER LEVEL - 100K AT 1232 ON 8/25/88 WITH THE UNIT AT 100X POWER (OPERATIONAL CONDITION 1) r THE REACTOR AUTOHATXCALLY SCRAMMED DUE TO A TURBINE CONTROL VALVE FAST CLOSURE CAUSED BY A LOSS OF HAINGENERATOR FIELD EXCITATION RESULTING IN AUTOMATIC HAIN GENERATOR ANO TURBINE TRIPS ~ INMEDXATELY FOLLOWING THE SCRAYir REACTOR PRESSURE SPIKED TO A PEAK BETWEEN 1100 AND 1117 PSIG.CAUSING THF 5 LOW-LOM SET SAFETY

~ RELIEF VALVES TO CYCLE PER DESIGN ~ THE TURBINE BYPASS VALVES OPENED AS REQUIRED ANO THE REACTOR RECIRCULATION PUHPS TRANSFERRED TO SLOM SPEED PER DESIGN REACTOR WATER LEVEL INITIALLY DECREASED TO +4 INCHES AS INDICATED BY THE WIDE RANGE INSTRUMENTS DUE TO THE REACTOR PRESSURE SPIKE THE HIGH PRESSURE CORE SPRAY (HPCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEMS INJFCTEO AS A RESULT OF A SPURIOUS LOM REACTOR MATER LEVEL 2 SIGNAL CAUSED BY A HYDRAULIC PERTURBATION IN THE REACTOR WATER l EVEL INSTRUMENT REFERENCE LINES AS A RESULT OF THE FEEDWATER FLOW CONTINUING (DUE TO THE "A" FEEOWATER CONTROL VAl VE BFING IN THE t1ANUAL; NODE AT 50K OPEN) IN CONJUNCTION WITH THE HPCS AND RCIC INJECTXONSr REACTOR WATER LEVEL RAPXDLY INCREASED TO LEVEL" 8 CAUSING THE HPCS INJECTION VALVE AND THE RCIC STEAM SUPPLY VALVE TO CLOSE AND THE REACTOR FEEDMATER PUMPS TO TRIP PER DESIGN.

THERE WAS NO SIGNIFXCANT ADVERSE IMPACT ON THE SAFE OPERATION OF THE PLANT

~ 0 0 0 0 0 0 0 0 '0 0 0 0 0 0 0 0 0 0 a ~ "I 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

FORM 174 LER SCSS DATA 08-30-91

• • • • • • • • • 4'********************************************************4*

DOCKET YEAR LER NUMBER REVISION DCS NUMBER NSIC EVENT DATE 458 1990 026 0 9009190263 219518= 08/10/90 DOCKET:458 RIVERBEND 1 TYPE".BMR REGION: 4- NSSS:GE ARCHITECTURAL ENGINEER: SWXX FACILITY OPERATOR: GUlF STATES UTILITIES SYMBOl: GSU "'

WATCH-lEST CODES IFOR THIS LER ARE 31 ACCIDENTAL ACTION 38 POOR ERGONOMICS OR HUHAN ENVIRONMENT REPORTABILITY CODES FOR THIS l ER ARE:

13 10 CFR 50.73(a) (2) (iv): ESF actuations.

REFERENCE LERS:

1- 458/85-019' 458/85-020 458/85-022 4 458/85-023 5'58/86-010 ABSTRACT POWER LEVEL 100K ~ AT APPROXIMATELY 0202 ON 08/10/90 MITH THE UNIT AT FULL POWER IN OPERATIONAL'ONDITION 1r THE REACTOR WATER CLEANUP SYSTEM -(RWCU) ISOLATED MAINTENANCE WAS INSTALLING JUMPERS TO ALLOW REPLACEMENT OF- A FAULTY OPTICAl ISOLATOR CARD WHEN A SHORT CIRCUIT OCCURRED ~ THIS SHORT CAUSED TMO FUSES TO BLOMr RESULTING IN A LOSS OF POWER TO SEVERAL BALANCE-OF-PLANT (BOP) OPTICAL XSOLATOR CARDS LOSS OF THESE ISOLATOR CARDS OE-ENERGIZED NORMALLY ENERGIZED RELAYS FOR THE HVAC - COOLING MATcR- SYSTEM (HVN) ~ - THIS CAUSED AN ISOLATION OF THE COOLING WATER TO THE CONTAINMENT UNIT COOLERS MITH COOLING WATER ISOLATEDr AREAS IN THE CONTAINMENT- SERVED BY THESE UNITS BEGAN TO HEAT UP ~ WHEN THE RMCU HEAT EXCHANGER ROOH AMBIENT TEMPERATURE REACHED THE ISOLATION SETPOINTr 'N ISOLATION OF THE SYSTEM OCCURRED ~

THEREFORE THIS EVENT IS REPORTABLE PURSUANT TO 10CFR50 73(A) (2) (IV) AS ESF ACTUATION A SHORT CIRCUIT OURXNG JUMPER HANIPUI ATXON RESULTED IN THE RMCU ISOLATION~ INSTALLATION OF JUHPERS ON THE OPTICAL ISOLATOR CARDS IS COMPLICATED BY- THE REI ATXVE LOCATIONS OF THE POSITIVE AND NEGATIVE TCRHXNALS MHICH APPROXIMATELY 1/4" APART WITH NO BARRXERS BETWEEN ~ AS CORRECTIVE ACTIONr THIS, REPORT WILL BE

~

REQUIRED READING FOR APPLICABLE MAINTENANCE PERSONNEL BY 10/31/90 SINCE ALL PLANT SYSTEMS PERFORHED AS OESIGNEOr THIS EVENT DID NOT ADVERSELY AFFECT THE HEALTH AND SAFETY OF THE PUBLIC

0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

FORM 175 LER SCSS DATA 08-30-91

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DOCKET YEAR LER NUMBER REVISION DCS NUMBER NSIC EVENT DATE 483 1986 010 8610280571 201560 04/16/86

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1 I

DOCKET:483 CALLAWAY TYPE:PWR g REGION:

1 3 NSSS:WE ARCHITECTURAL ENGINEER: BECH FACILITY OPERATOR: UNION El ECTRIC CO ~

S YMBOL: UEC COMMENTS STEP 1: CAUSE AX-FOR CORE TESTING .STEP 6: COMP XFMR-FERRO- RESONANT OUTPUT TRANSFORMER REPORTABILITY'ODES FOR THIS l.ER ARE:

13 10 CFR 50.73(a) (2) (iv): ESF actuations.

ABSTRACT POWER LEVEL OOOX ON 4/16/86 AT 1424 CST A REACTOR TRIP ANO A FEEDWATER ISOLATION (FWIS) OCCURRED AS A RESULT OF A POWER RANGE HIGH SETPOINT HIGH FLUX (PRHSHF) SIGNAL. AT THE TIME OF THE TRIP THE REACTOR WAS'N MODE 2r STARTUPr AT OX OF RATED THERMAL POWER AND NORMAL OPERATING TEMPERATURE AND PRESSURE. THE PRHSHF TRIP OCCURRED DUE TO LOSS OF 120 VAC POWER SUPPLYING POWER RANGE NUCI EAR INSTRUMENTATXON (PRNI) CHANNEL 41 LOSS OF.120 VAC POWER TO PRNX CHANNEL 41 WAS CAUSED BY FAILURF OF THE NN-11 INVERTER TRANSFORMER THAT SUPPLXES POWER TO BUS NN-01 ~ PREVIOUS TO THE TRIP+ PRNI CHANNEL 44 WAS PLACED OUT OF SERVXCE (XN TRIPPED CONDITION) TO FACXLITATE CORE PHYSICS TESTXNG ~ SINCE PRNI CHANNEL" 44 WAS ALREADY IN THE TRIPPEO CONDITIONr FAILURE OF THE POWER SUPPLY TO PRNI CHANNEL 41 SATISFIED THE 2 OF 4 l OGIC NECESSARY TO INITIATE THE REACTOR TRIP. THE OTHER FOUR INVERTER TRANSFORMERS AS WELL AS THE REPLACEMENT TRANSFORMER WERE TESTEOr PER WESTINGHOUSE TECHNICAL BULLETIN 84-11 AS A PRECAUTIONARY MEASUREs WITH SATISFACTORY RESULTS ~ BASED UPON A GENERAL ELECTRIC FAULT ANALYSIS OF THE DEFECTIVE TRANSFORMERr WESTINGHOUSE CONCLUDED IT FAILEO WHEN THE MAIN AND REACTOR TRANSFORMERS SHORTED TO GROUND THE CAUSE OF THE FAILURE COULD NOT BE DETERMINED THE FAILURE IS CONSIDERED AN ISOLATED EVENT ALL ENGINEERED SAFETY FEATURES ACTUATED AS DESIGNED ~ AT NO TIME OID THIS EVENT ENDANGER THE PUBLIC HEALTH OR SAFETY 0

e a o e o e a e e e o o e o e e e e 0 e4 il 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

FORM 176 LER SCSS DATA 08-30-91

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DOCKET YEAR LER NUHBER REVISiON DCS NUMBER NSXC EVENT DATE 483 1990 005 0 9006010187 218374 05/01/90

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DOCKET:483 CALLAWAY 1 TYPE PMR REGION: 3 NSSS:ME ARCHITECTURAL'NGINEER: SECH FACXLITY OPERATOR: UNION ELECT RIC CO S YHBOL: UEC

~ MATCH-LIST 20 CODES FOR THIS FAILURE LER ARE:

EQUIPNENT CODES FOR THIS LER ARE:

~ REPORTABILXTY 13 10 CFR 50.73(a) (2) (iv): ESF actuations.

y ABSTRACTLEVEL POWER 100K ~ ON=5/1/90 AT 1331. CDTr A REACTOR TRIPr AND AUXILIARY FEEDWATER ACTUATIONr AND A FEEDWATER ISOLATION OCCURRED OUE TO A TURBINE TRIP ON A LOSS OF HAIN GENERATOR STATOR COOLING MATER.

(SCM) INSTRUNENTATIONa THE PLANT. MAS IN MODE 1 POWER OPERATIONSr 100 PERCENT REACTOR POWERr- AT NORMAL OPERATING PRESSURE AND TEMPERATURE ~ THE SCM LOM FLOW TURBINE TRIP SIGNAL AND SUBSEQUENT REACTOR TRIP SIGNAL MERE RECEIVED DURING THE CALIBRATION OF THE SCM INLET CONDUCTIVITY METER DURING RESTORATION OF POWER TO THE CONOUCTXVITY NETERr A CONDUCTIVE FOREIGN PARTICLE CREATED A DEAD SHORT ACROSS THE POMER SUPPLY LEADS OF THE H TER ASSEMBLY'HE SUBSEQUENT TRANSIENT CAUSED THE FAILURE OF A 10 AMP FUSE RESULTING IN A LOSS OF

~

t~iAIN GENERATOR SCM INSTRUMENTATION POWER ~ THE LOSS OF INSTRUMENTATION POWER INITIATED A'URBINE RUNBACK AT 1328 MITH THE "LOSS'F SCW FLOW" SIGNAL STILL PRESENTr THE HAIN GENERATOR PROTECTION CIRCUXTRY INITIATED. A TURBINE TRIP AT 1331 SEVERAL GENERATOR PROTECTION SCM RUNBACK HODIFICATIONS ARE BEING IMPLEMENTED TO ALLEVIATE FALSE ACTIVATIONS AND ENHANCE 'THE RELIABILITY OF THE SYSTEH

0 o e e e o o e o o o o o o e o e e o e o 0 I

W t

I'

'0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

FORM 177 LER SCSS DATA 08-30-91

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DOCKET YEAR LiR NUMBER REVISION DCS NUHBER NSIC EVENT DATE 529 1986 023 8703160089 203416 12/24/86

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1 DOCKET:529 PALO VERDi 2 TYPE:PWR REGION: 5 NSSS: CE ARCHITECTURAL ENGINEER: BECH FACILITY OPERATOR: ARIZONA PUBLIC SERVICi CO SYMBOL: APS CONNENTS STEP 2: COMP HEI INDICATION BULB STEP 17: MODEL OSM12-75 REPORTABILITY CODES FOR THIS LER ARE 13 10 CFR 50 73(a) (2) (iv): ESF actuations.

ABSTRACT POWER lEVEL 100K ~ AT ABOUT 2010 HST ON 12-24-86'NIT 2 MAS -IN RODE 1 (POWER OPERATION) AT 100% POMiR MHEN THE AUTOMATIC ACTUATION"OF THE PLANT PROTECTION SYSTEM (PPS)(JC) INITIATED A REACTOR (RCT) TRIP. THE REACTOR TRIP MAS ANNUNCIATED (ANN) AND RESPONDED- TO BY UTILITY LICENSED OPERATORS IN THE CONTROL'OOH (CR) ALL SAFETY SYSTEMS AND COMPONENTS OPERATED AS DESIGNED THE CAUSE OF THE EVENT MAS'ETERNXNED TO BE AN INTERMITTENT GROUND ON THE 125 VOLT, DC BUS (H42) CAUSING A DESIGNED "0"= OUTPUT VOLTAGE RESPONSE FROH THE INVERTERr CONCURRENT WXTH AN "OUT OF-SYNC" CONDXTION BETWEEN THE INVERTER AND VOLTAGE REGULATOR (ALTERNATE POWER) THIS PROHIBITEO A TRANSFER OF THE 120 VOLT AC BUS (D26) TO THE VOLTAGE REGULATOR RESULTING IN A'OSS OF POWER TO D26 THE LOSS OF POWER TO D-26 RESULTED IN THE'OSS OF PPS CHANNEL "B" THIS LOSS COMBINED WITH A DEGRADED VOLTAGE CONDITION ON A PPS CHANNEL "A" POWER SUPPLYr RESULTED IN THE REACTOR TRIP ~ AS CORRECTIVE ACTIONr THE GROUND WAS, REMOVED AND THE POWER SUPPLY WAS REPLACED ~ FURTHER EVALUATIONS ARE CURRENTLY IN PROGRESS TO DETERMINE THE ROOT CAUSE OF THE DEGRADED VOLTAGE CONDITION EXPERIENCED BY THE PPS POWER SUPPLY THIS SESSION HAS USED 8 83 SECONDS OF CPU TINE AND HAS BEEN ACTIVE FOR 109 95 SECONDS THE ESTINATED COST OF THE RUN IS 8 2 68