ML19210E846
| ML19210E846 | |
| Person / Time | |
|---|---|
| Issue date: | 11/13/1979 |
| From: | Boyle E NRC OFFICE OF MANAGEMENT AND PROGRAM ANALYSIS (MPA) |
| To: | |
| References | |
| NUDOCS 7912130083 | |
| Download: ML19210E846 (84) | |
Text
j e arco UNITED STATES
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NUCLEAR REGULATORY COMMisSK v f ' Q( #
WASHINGTON, D. C. 20555
- di '"' j' ROV 131979 os, y
+....
LER M0fiTHLY REPORT The enclosed computer listing, as identified on the attached sheet, provides information concerning Licensee Event Reports (LERs) entered into the data base during the month of October.
If you desire additional information or special searches, please feel free.to contact me on 301/492-7724.
Sincerely,
/
s. %o a m
Eugenia L. Boyle Licensee Operations Evaluation Branch, DTS Office of Management and Program Analysis
Enclosures:
As Stated 1543 022 7912130 Q?3
PAGE 1 NOV 08, 1979 LER MONTHLY REPORT SORTED BY FACILITY PROCESSED DURING CCTOBER, 1979 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
DOCKET NO./
EVENT DATE/
COMPONENT SUBCODE/CAUSE CODE / LER NO./
REPORT DATE/
EVENT DESCRIPTION /
CAUSE-SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION ARKANSAS-1 05000313 021679 DURING STEADY STATE OPERATION, 4 CIRC. WATER PUMPS RUNNING, MAX. DIFFERE CIRCULATING WATER SYS + COH 79-001/04L-0 031679 NTIAL TEMP. ACROSS THE CONDENSER EXCEEDED ETS 15 DEG.
F. LIMIT.
EVENT L COMPONENT CODE NOT APPLICABLE 026766 30-DAY ASTED 2.5 HRS WITH MAX. RISE OF 15.26 DEG.
F.
COMPUTER LOG REVIEW INDIC SUBCOMP0HENT NOT APPLICABLE ATED ANOTHER ETS VIOLATION OCC'jRRED FOR APPROX. 49 HRS OH 2/9-2/11/79 WI PERSONNEL ERROR TH A MAX. TEMP. RISE OF 15.45 DEG.
F.
NO IMPACT FROM THERMAL STRESS EXP LICENSED & SENIOR OPERATORS ECTED ON ENVIRONMENT.
ITEM HOT APPLICABLE EXCESSIVE IMPINGEMENT OF THREADFISH SHAD ON CIRC. WATER INTAKE SCREENS P LUGGED INLET TUBE SHEETS, RESTRICTING CCOLING WATER FLOW.
IHLET WATER B OX VALVES WERE CYCLED TO CLEANSE SHEETS.
MONITORING OF CONDENSER 8 DIFF TEMP. IMPROVED BY USE OF COMPUTER TREHD RECORDER.
ARKANSAS-1 05000313 042579 AT 0100 HOURS OH 4/25/79 WITH REACTOR IN COLD SHUTDOWN, A LEAK WAS DISCO RESIDUAL HEAT REMOV SYS + CONT 79-003/04T-0 042679 VERED IH "B" DECAY HEAT LOOP DISCHARGE LOCATED IN REACTOR BLDG. (IHSERT PIPES FITTINGS 026312 2-WEEK A) DUE TO PLANT CONDITION AND SMALL MAGHITUDE OF LEAK.
THERE WAS NO HAZ LESS THAN 4 INCHES ARD TO HEALTH AND SAFETY OF PUBLIC.
((A)
LEAK WAS IN A 1 INCH DRAIN LI COMPONENT FAILURE HE SOCKET WELD TO AN 8 INCH CROSS CONNECT LINE TO THE "A" DECAY HEAT LOO OTHER P.)
ITEM NOT APPLICABLE THE 1 INCH DRAIN LINE WILL BE REPLACED. CAUSE FOR THE EnILURE IS UHKNOW H AT THIS TIME.
ARKANSAS-1 05000313 080879 DURING HORMAL COLD SHUTDOWN OPERATION, DELAY HEAT BORGN CONCENTRATION WA RESIDUAL HEAT REMOV SYS + CONT 79-013/03L-0 082879 5 NOT MONITORED DURING PRESCRIBED INTERVAL AS REQUIRED BY T.S.4.16, TABL COMPONENT CODE NOT APPLICABLE 026695 30-DAY E 4.1-3, ITEM IF.
INSERVICE DECAY HEAT LOOP WAS SWITCHED WITHOUT SWITCH SUBCOMPONENT NOT APPLICABLE ING SAMPLE LINEUP, RESULTING IN SAMPLING OF OUT OF SERVICE LOOP.
THERE HAVE BEEN HO SIMILAR OCCURREHCES. THIS OCCURRENCE IS REPORTABLE PER T.S PERSOHNEL ERROR
.S.12.3.28.
OTHER ITEM NOT APPLICABLE CAUSE WAS A BREAKDOWN IN COMMUNICATIONS BETWEEN OPERATION: 8 RADIOCHEMIS TRY DEPARTMENTS. RADI0 CHEMISTS WERE INSTRUCTED TO VERIFY SAMPLE LINEUP THROUGH OPERATIONS. A DESIGN CHANGE IS BEING EVALUATED TO ADD CHECK VAL VES IN SAMPLE LINES TO PREVENT IHADVERTANT SAMPLING OF OUT OF SERVICE LO OP.
ARKANSAS-1 05000313 080979 DURING A HRC PERFORMANCE APPRAISAL TEAM INTERVIEW, IT WAS DISCOVERED THA REACTOR VES. + APPURTENANCES 79-011/01T-0 082379 T PRESSURIZER SAFETY RELIEF VALVE, PSV-1002, WAS NOT PROPERLY TESTED IN COMPONENT CODE NOT APPLICABLE 026699 2-WEEK MAR, 1978.
DOCUMENTATION REVEALED ACCEPTANCE CRITERIA 0F PROCEDURE 401.
SUBCOMPONENT HOT APPLICABLE 03, REQUIRING TWO CONSECUTIVE LIFTS AT 2500 +/- 1% PSI, WAS NOT MET.
AH PERSONNEL ERROR 0 PLANT SAFETY COMMITTEE (PSC) RULED TEST WAS NOT PERFORMED SATISFACTORI MAINTENANCE & REPAIR PERSOHHEL LY.
THERE HAVE BEEN HO SIMILAR OCCURRENCES. THIS CCCURREHCE REPORTABLE ITEM NOT APPLICABLE PER T.S.
6.12.3.1.F.
TEST ACCEPTABILITY WAS INITIALLY JUSTIFIED BASED ON HIGH PRESSURE GAGE I HDICATION DUE TO EXCEEDINGLY HOT AMBIENT TEMPERATURE. VALVE WAS RETESTE D ON 8/12/79, SUCCESSFULLY, WITH HO ADJUSTMENT HECESSARY.
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NOV 08, 1979 LER MONTHLY REPORT SORTED BY FACILITY PAGE 2 PROCESSED DURING OCTOBER, 1979 FOR POWE7 REACTORS FACILITY / SYSTEM / COMPONENT /
DOCKET HO./
EVENT DATE/
COMPONENT SUBCODE/CAUSE CODE / LER NO./
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUSCODE/ MANUFACTURER CONTRO' HO.
REPORT TYPE CAUSE DESCRIPTION ARKANSAS-1 05000313 081079 DURING COLD SHUTDOWN OPERATICH, LEAK RATE TESTING OF REACTOR BUILDING PE OTHER AUX SYSTEMS + C0r?kOLS 79-012/03L-0 083179 HETRATION V-1, PER PROCEDURE 1304.23, REVEALED A LEAK RATE IN EXCESS OF VALVES 026900 30-DAY 50,000 CC/ MIN.
IT WAS DETERMIHED TO BE CAUSED BY THE OUTSIDE ISOLATION GATE VALVE, CV-7402.
THE INSIDE ISOLATION VALVE, CV-7404, DID NOT LEAK.
THI COMPONENT FAILURE S OCCURRENCE IS SIMILAR TO LER 50-313/79-005 AND 77-15.
REPORTABLE PER MECHANICAL T.S.
6.12.3.2B.
PRATT, HENRY CD.
INVESTIGATIOH REVEALED THAT THE VALVE REQUIRED AN ADJUSTMENT OF ITS SHIN 5 DN THE VALVE SEAT TO MATCH THE SURFACE OF THE BUTTERFLY. ADJUSTMENTS WERE MADE AFD THE LEAK RATE RETESTED, MEETING THE 60% LA REQUIREMENT OF T.S.
4.4.1.2.3.
TEST FREQUENCY INCREASED FROM QUARTERLY TO AFTER EVERY R.B.
PURGE.
ARKANSAS-1 05000313 081379 WHILE INCREASING POWER, AT APPROXIMATELY 75% REACTOR POWER, SWITCHYARD R REACTOR TRIP SYSTEMS 79-014/99X-0 091279 ELAY, 2121, FAILED, CAUSING A TURBINE TRIP.
TURBINE LOCK-0UT RELAY, 286 RELAYS 026910 OTHER
-T, FAILED TO OPERATE, DEFEAYING THE GENERATOR LOCK-0UT & THE RECENTLY A SWITCHGEAR, PROTECTIVE DDED " REACTOR TRIP.0H TURBINE TRIP"-
THE DEGRADED FREQUENCY DURING COAS COMP 0HENT FAILURE TDOWN RESULTED IN BUSES A2 AND H1 UNDERVOLTAGE, CAUSING SLOW AUXILIARY P ELECTRICAL OWER TRAHSFER WHEN GENERATOR LOCK-0UT WAS RECEIVED FROM REACTOR TRIP (OH WESTINGHOUSE ELECTRIC CORP.
HIGH RC PRESSURE).
INVESTIGATION REVEALED THAT THE TURBINE LOCK-0UT RELAY. 286-T, HAD LOOSE TERMINALS ON THE LEADS TO THE TURBIHE, WITH ONE LUG FAILED.
THE FAILED LUG WAS REPLACED AND THE TERMINALS WERE TIGHTENED.
THE TURBINE LOCK-0U T AHD " REACTOR TRIP ON TURBINE TRIP INTERLOCKS WERE TESTED WITH SATISFAC TORf RESULTS.
ARKANSAS-1 05000313 081779 AS A RESULT OF THE AHALYSIS OF SEISMIC CATEGORY I PIPE SUPPORTS FOR BASE OTHER SYSTEMS 79-015/99X-0 091479 PLATE FLEXIBILITY AS REQUESTED IN NRC IE BULLETIH 79-02, THIRTY-SEVEN RE HANGERS. SUPPORTS, SHOCK SUPPRSS 026893 OTHER STRAINTS HAVE BEEN IDENTIFIED AS HAVING A SAFETY FACTOR OF LESS THAN TWO HANGERS REFER TO THE RESPONSE TO IE BULLETIH 79-02 FOR IDENTIFICATION. THERE DESIGN / FABRICATION ERROR HAVE BEEN HD SIMILAR OCCURRENCES. REPORTABLE PER T.S.
6.12.
CONSTRUCTION / INSTALLATION BECHTEL CORP.
ALL PIPE SUPPORTS WITH A SAFETY FACTOR OF LESS THAN TWO HAVE BEEH MODIFI ED.
REFER TO THE RESPONSE TO THE IE BULLETIN 79-02 FOR DETAILS.
ARKANSAS-1 05000313 082779 DURING THE MONTHLY SURVEILLANCE OPERATIONAL TEST, DIESEL GENERATOR 32 TR EMERG GENERATOR SYS + CONTROLS 79-016/03L-0 091479 IPPED ON LOW OIL PRESSURE AFTER APPROXIMATELY THREE MINUTES OF OPERATION ENGINES.INTERHAL COMBUSTION 026894 30-DAY DIESEL GENERATOR 31 WAS DEMONSTRATED OPERABLE IMMEDIATELY PER SURVEIL SUBCOMP0HENT NOT APPLICABLE LANCE PROCEDURE 1104.36 SUPPLEMENT I.
UNIT POWER OPERATION W%S CONTINUE COMP 0HENT FAILURE D BASED OH MEETING THE REQUIREMENTS OF T.S. 3.7.1C. LER 50-313/75-009 IN MECHANICAL VOLVED THE LUPE OIL COOLER, BUT WAS NOT SIMILAR IH NATURE.
REPORTABLE P STEWART 4 STEVENSON SERV INC.
ER T.S.
6.12.3.2B.
THE DIESEL LUBE OIL COOLER WAS LEAKING ALLOWING WATER TO ENTER THE OIL S YSTEM.
THE WATER VAPORIZED CH UNIT OPERATICH CAUSING A HIGH CRANKCASE P RESSURE, WHICH ULTIMATELY CAUSED THE OIL SWITCHES TO TRIP THE ENGINE.
T HE OIL COOLER WAS REPLACED AND THE DIESEL GENERATOR SUCCESSFULLY TESTZD L.M WITHIN THE 7 DAYS ALLOWED BY T.S.
3.7.1C.
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HOV 08, 1979 LER MONTHLY REPORT SORTED BY FACILITY PAGE 3 PROCESSED DURING OCT0 DER, 1979 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
DOCKET HO./
EVENT DATE/
COMPONENT SUBCODE/CAUSE CODE / LER NO./
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL H0.
REPORT TYPE CAUSE DESCRIPTION ARKANSAS-2 05000368 081278 DURING MODE 2 OPERATION, EMERGENCY FEEDWATER FLOW CONTROL VALVE, 2CV-102 COOL SYS FOR REAC AUX + CONT 78-068/03L-0 090579 5-1, FROM THE ELECTRIC DRIVEN EFW PUMP, 2P7B, TO THE "A"
STEAM GENERATOR VALVE OPERATORS 026703 30-DAY FAILED TO FULLY CLOSE FROM A CONTROL ROOM DEMAND SIGNAL.
THE REDUNDAN ELECTRIC MOTOR - AC T EFW VALVES WERE SUCCESSFULLY STROKED FROM THE CONTROL ROOM.
THIS OCCU COMPONENT FAILURE RRENCE IS SIMILAR TO LER 50-368/79-051,79-043, 79-035, AND 78-28.
REPO MECHANICAL RTABLE PER T.S.
6.9.1.98.
WESTON HYDRAULICS DIV.
INVESTIGAITON REVEALED THAT THE LIMIT STOP SWITCH WAS OUT OF ALIGNMENT.
REALIGNMENT WAS MADE AND THE VALVE WAS SUCCESSFULLY STROKE TESTED.
THE VALVE WAS DECL*, RED OPERABLE WITHIN 7 HOURS, MEETING THE REQUIREMENT OF A CTICH STATEMENT T.S.
3.7.1.2.
ARKANSAS-2 05000368 072479 AS A RESULT OF THE ANALYSIS OF SEISMIC CATEGORY I PIPE SUPPORTS FOR BASE OTHER SYSTEMS 79-058/03X-1 052079 PLATE FLEXIBILITY AS REQUESTED IN NRC IE BULLETIN 79-02, HINE RESTRAINTS HANGERS, SUPPORTS, SHOCK SUPPRSS 026702 OTdER HAVE BEEN IDENTIFIED AS HAVING A SAFETY FACTOR OF < 2.
REFER TO RESPON HANGERS SE OF IE BULLETIN 79-02 FOR IDENTIFICATI0H.
IT UAS REQUIRED TO DECLARE DESIGN / FABRICATION ERROR THE R.B.
SUMP DRAIN, OUTSIDE CONTAINMENT ISOLATION VALVE, 2CV-2061, IHOP CONSTRUCTION / INSTALLATION ERABLE DUE TO THE INADEQUATE PIPE RESTRAINTS.
THERE HAVE BEEN SIMILAR 0 BECHTEL CORP.
CCURRENCES. REPORTABLE PER T.S.
6.9.1.9B.
AlL PIPE SUPPORTS WITH A SAFETY FACTOR OF LESS THAN TWO HAVE BEEN MODIFI ED.
RFFER TO THE RESPONSE TO THE IE BULLETIH 79-02 FOR DETAILS.
ARKANSAS-2 05000368 073079 DURING MODE 1 OPERATION, CONTROL ROOM RADIATION MONITOR, 2RITS-8750-1, P AREA MONITORING SYSTEMS 79-059/03L-0 082879 OWER SUPPLY FAILED, RESULTING IN A FALSE HIGH INDICATION, CAUSING ISOLAT IHSTRUMENTATION + CONTROLS 026694 30-DAY ION OF CONTROL ROOM VENTILATION.
THERE WERE NO HIGH RADIATION EVENTS; T SENSOR / DETECTOR / ELEMENT HEREFORE, P'JB L IC & OPERATING PERSONNEL SAFETY WAS NOT ENDANGERED.
OTHER COMPONENT FAILURE OCCURREHCE1 INVOLVING RADIATION MONITORS ARE: LER 50-368/79-047 & 79-0 INSTRUMENT 57.
THIS L'CC'JRREHCE REPORT ABLE PER T.S.6.9.1.9B.
WESTINGHOUSE ELECTRIC CORP.
INVESTIGATI3:! d6(EALED +/- 15 VOLT POWER SUPPLY INOPERABILITY WAS DUE TO A CIRCUITRY FAILURE.
POWER SUPPLY WAS REPAIRED, OPERATIONALLY CHECKED,
& RADIATION MOHITOR WAS RETURHED TO SERVICE.
CONTROL ROON EMERGENCY VE HTILATION SYSTEM WAS PUT IN SERVICE WHILE MONITOR WAS OUT OF SERVICE.
ARKANSAS-2 05000368 080479 DURING MODE 1,
POWER ESCALATION IESTING, IT WAS DISCOVERED THAT FULL LEN REACTIVITY CONTROL SYSTEMS 79-062/03L-0 083079 GTH CEA #39 WOULD HOT MOVE.
WITH THE CEA IHOPERABLE DUE TO CAUSES OTHER COHTROL ROD DRIVE MECHAHISMS 026891 30-DAY THAN THAT CAUSING MECHANICAL INTERFEREHCE, AND BEING WITHIN ITS ALIGNME SUBCOMPONENT NOT APPLICABLE NT REQUIREMENTS, OPERATION IN MODE 1 CONTINUED PER T.S.
3.1.3.1.C.
THER COMPONENT FAILURE E HAVE BEEN H0 SIMILAR OCCURRENCES. REPORTABLE PER T.S.
6.9.1.9B.
INSTRUMENT COMBUSTION ENGINEERING, INC.
INVESTIGATION REVEALED A FAILED CEA EHABLE CARD.
THE CARD WAS REPLACED AND CEA #39 WAS SUCCESSFULLY STROKE TESTED.
THE CEA WAS DECLARED OPERAB LE WITHIN APPROXIMATELY ONE HOUR OF THE FAILURE DETECTION, 4
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NOV 08, 1979 LER MONTHLY REPORT SORTED BY FACILITY PAGE 4 PROCESSED DURING OCTOBER, 1979 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
DOCKET HO./
EVENT DATE/
COMPONENT SUBCODE/CAUSE CODE / LER t.0./
REPORT DATE/
EVENT DESCRIPTIOH/
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION ARKANSAS-2 05000368 080679 DURING MODE 1 OPERATION, THE CONTAIHMENT ATMOSPHERE SAMPLE REACTOR BUILD CNTHMNT ISOLATION SYS + CONT 79-063/03L-0 083179 ING PEHEIRATION OUTSIDE ISOLATION VALVE, 2SV-8263-2, UGULD HOT INDICATE VALVE OPERAT6RS 026905 30-DAY CLOSED DUIRNG A STROKE TEST.
THE INSIDE VALVE, 2SV-8265-AT PENETRATI SOLEHOID - AC OH 2P58, WAS VERIFIED GPERaBLE.
THIS OCCURREHCE IS SIMILAR TO LER 50-36 COMP 0HEhT FAILURE 8/79-044,79-060, AND 79-061 OCCURRENCE IS REPORTABLE PER T.S.
6.9.1.9 MECHANICAL
.B.
TARGET ROCK CORPORATION INVESTIGATION REVEALED THAT THE LIMIT SWITCH WAS OUT OF ADJUSTMENT.
THE LIMIT WAS ADJUSTED AND THE VALVE WAS PROVEN OPERABLE PER T.S.
4.6.3.1.1 TALLE 3.6-1 THE VALVE WAS RETURHED TO SERVICE IN LESS THAN TWO HOURS MEETING THE REQUIREMENT OF ACTION STATEMENT T.S.
3.6.1A.
ARKANSAS-2 05000368 080779 DURING MODE 1 OPERATION, THE CPC TRIPS IN "D" PPS WERE PLACED IN BYPASS REACTOR TRIP SYSTEMS 79-064/03L-0 090579 TO INVESTIGATE OSCILLATIONS IN THE " DELTA-T" POWER INDICATION. POWER OP INSTRUMENTATION + CONTROLS 026705 30-DAY ERATION WAS CONTINUEU BASED ON MEETING THE REQUIREMENIS OF ACTION STATEM COMPUTATION MODULE ENT #2 0F T.S.
TABLE 3.3.-1 THIS OCCURRENCE IS SIMILAR TO LER 50-36S/7 COMPONENT FAILURE 9-015.
REPORTABLE PER T.S.
6.9.1.9B.
INSTRUMEHT COMBUSTION ENGINEERING, INC.
THE " DELTA-T" POWER CALCULATION OSCILLATION WAS DUE TO A COLD LEG TEMPER ATURE INDICATICH OSCILLATION. AN UNRELATED PLANT TRIP OCCURRED DURING T HE INVESTIGATICH. THE INVESTIGATION CONTINUED DURING THE OUlAGIL ALL R ELATED SIGNAL CONNECTIONS WERE TIGHTENED AND THE CONDITION DID HOT REAPP EAR.
ARKANSAS-2 05000368 080879 DURING MODE 1 OPERATIOH, THE AUXILIARY BUILDING RADWASTE AREA RADIATION PRCSS + EFF RADIOL MONITOR SYS 79-067/04L-0 090579 MONITOR, 2RE-E542, SAMPLE PUMP WAS FOUND WITH A BROKEN COUPLING. GASE00 INSTRUMENTATION + CONTROLS 026704 30-DAY S RELEASES WHICH UTILIZE THE SUBJECT MONITCR WERE SAMPLED AND ANALYZED W SENSOR / DETECTOR / ELEMENT ITH LESS THAN MINIMUM DETECTABLE RESULTS.
THIS OCCURRENCE IS SIMILAR TO COMPONENT FAILURE LER 50-368/79-057.
REPORTABLE PER E.T.S.
5.6.2B.
MECHANICAL WESTINGHOUSE ELECTRIC CORP.
APPROPRIATE GRAB SAMPLES WERE TAKEN WHILE THE MONITOR WAS OUT OF SERVICE
, ONCE PER SHIFT, AS REQUIRED BY E.T.S.
2.2.2.7.
THE PLASTIC COUPLING W AS REPLACED WITH A METAL COUPLING.
ARKAHSAS-2 05000368 080979 DURING MODE 1 OPERATION, FOLLOWING ROUTINE DRAINING OPERATION OF THE REA PROCESS SAMPLING SYSTEMS 79-066/03L-0 083179 CTOR DRAIN TANK, CONTAIHMENT ISOLATION VALVE, 2CV-2201-2, WOULD NOT FULL VALVES 026903 30-DAY Y CLOSE.
THE AFFECTED PENETRATICH WAS ISOLATED WITHIN ONE HOUR BY DEACT BALL IVATING 2CV-2202-1 IN THE CLOSED POSITION, MEETING THE REQUIREMENTS OF A COMPONENT FAILURE CTION STATEMENT T.S.
3.6.3.1B.
OTHER OCCURRENCES ON CONTAINMENT PENETRA MECHANICAL TIONS ARE 50-368/79-063,79-061, 79-060,79-044, 3 78-19.
RE.' ORT ABL E PE E.
B.
V.
SYSTEMS, IHC.
R T.S.
6.9.1.9B.
INVESTIGATICH REVEALED FOREIGH MATERIAL HAD DAMAGED SEATS AND BALL CAUSI HG VALVE TO LEAK THROUGH.
THE VALVE WAS DISASSEMBLED, CLEAHED AND REASS EMBLED.
HD REPLACEMENT PARTS WERE AVAILABLE, THE INSIDE CONTAINMENT ISO LATION VALVE, 2CV-2201-1 REMAINS DEACTIVATED IN THE CLOSED POSITION.
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NOV 08i.1979 LER MONTHLY REPORT SORTED BY FACILITY PAGE 5 x-PROCESSED DURING OCTOBER, 1979 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
DOCKET NO./
EVENT DATE/
COMPONENT SUBCODE/CAUSE CODE / LER NO./
REPORT DATE/
EVENT DESCRIPTION /
CAUSE'SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION ARKANSAS-2 05000368 080979 DURING MODE 1 OPERATION, BATTERY CHARGER, 2D31, FAILED RENDERING THE "A"
DC ONSITE POWER SYS + CONTROLS 79-065/03L-0 083179 DC BUS IHOPERABLE PER T.S.
3.8.2.3B.
BATTERY CHARGER, 2D32, REMAINED 0 BATTERIES + CHARGERS 026904 30-DAY PEPABLE AND 2034 WAS PLACED IN SERVICE, RESTORING THE "A" BUS TO AN OFER SUBC0"PONENT NOT APPLICABLE ABLE STATUS WITHIN 10 MINUTES UF THE FAILURE DETECTION PER T.S.
3.8.2.3B COMPONENT FAILURE THERE HAVE BEEN HO SIMILAR OCCURRENCES. REPORTABLE PER T.S.
6.9.1.9B ELECTRICAL POWER CONVERSION PRODUCTS, INC INVESTIGATION REVEALED THE D.C.
OUTPUT LAMP SOCKET BURNED UP, CAUSING TH L OUTPUT BREAKER TO TRIP.
THE FAILURE WAS CAUSED BY HIGHER VOLTACE DUE TO HEAT AND INCREASED RESISTANCE IN LAMP CIRCUIT.
DUST IN THE UNIT WAS HAMPERING ITS VENTILATION.
THE UNIT WAS CLEANED AND REPAIRED.
ARKANSAS-2 05000368 081479 DURING MODE 2 CPERATION, FOLLOWING THE COMPLETION OF THE SURVEILLANCE TE EMERG GENERATOR SYS + CONTROLS 79-069/03L-0 090579 ST RUN ON DIESEL GENERATOR 82. THE DIESEL COULD HOT BE STOPPED FROM THE CIRCUIT CLOSERS / INTERRUPTERS 026706 30-DAY CONTROL POOM HANDSWITCH, 2HS-2829-2.
THE DIESEL WAS STOPPED FROM THE LO SWITCH (OTHER THAN SENSOR)
CAL HANDSWITCH.
COMPONENT FAILURE ELECTRICAL GENERAL ELECTRIC CO.
INVESTIGATION REVEALED THAT THE INTERNAL SPRING ON THE HANDSWITCH CONTAC T WAS GUT OF ADJUSTMENT.
THE SPRING AND SWITCH CONTACTS WERE ADJUSTED A ND TESTED SATISFACTORILY. THE SURVEILLANCE TEST WAS COMPLETED AND THE D IESEL GENERATOR DECLARED OPERABLE MEETING REQUIREMENTS OF ACTION STATEME NT T.S.
3.8.1.1A.
ARKANSAS-2 05000368 081679 DURING M3DE 1 OPERATION, BATTERY ELIMINATOR, 2D35. FAILED, CAUSING REACT ONSITE POWER SYSTEM + CONTROL 79-070/03L-0 091279 OR TRIP BREAKERS, TCB3 AND TCB7, TO CPEN, RENDERING ONE CHANNEL IMOPERAB RELAYS 026911 30-DAY LE PER T.S.
3.3.1.1 TABLE 3.3-1 ITEM #14.
THIS PUT THE BREAKERS IN THE OTHER TRIPPED CONDITION AS REQUIRED BY ACTION STATEMENT T.S.
TABLE 3.3-1 ACTIO COMPONENT FAILURE N #4.
ALL OTHER REACTOR TRIP BREAKERS REMAINED C'_0 SED AND OPERABLE.
TH ELECTRICAL (RE HAVE BEEN NO SIMILAR OCCURRENCES. REPGRTABLE PER T.S.
6.9.1.93.
WESTINGHOUSE ELECTRIC CORP.
INVESTIGATION REVEALED THAT 2D35 HAD A RELAY COIL FAILED DUE TO A STICKI NG PLUNGER.
THE REACTOR TRIP EREAKERS OPENED OH UNDERVOLTAGE.
THE RELA Y WAS REPLACED AND THE BREAKERS WERE RECLOSED WITHIN FOUR HOURS OF THE F AILURE DETECTION.
ARKANSAS-2 05000368 081879 DURING MODE 1 OPERATION, THE "B" CORE PROTECTION CALCULATOR FAILED CAUSI REACTOR TRIP SYSTEMS 79-071/03L-0 091279 NG LOW DNPR AND HIGH LPD TRIPS IN THE "B" PPS.
ALL REMAINING CPC CHANNE INSTRUMENTATION + CONTROLS 026912 30-DAY LS REMAINED OPERABLE.
THE DNBR AND LPD TRIPS IN THE "B" PPS WERE BYPASS COMPUTATICH MODULE ED, PLACING THE REACTOR TRIP LOGIC IN A 2 OUT OF 3 CONDITION.
THIS OCCU COMPONENT FAILURE RRENCE IS SIMILAR TO LER 50-368/79-052.
REPORTABLE PER T.S.
6.9.1.9B.
INSTRUMENT SYSTEMS ENGINEER. LASS., INC.
INVESTIGATION REVEALED A MEMORY FAILURE.
THE MEMORY MODULE WAS REPLACED SOFTWARE LOADED, CPC FUNCTIONALLY TESTED, AND RETURNED TO SERVICE WITH IN 7 HOURS MEETING ACTION STATEMENT T.S.
TABLE 3.3-1 ACTIb.* 2A.
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NOV 08, 1979 LER MONTHLY REPORT SORTED BY FACILITY PAGE 6 PROCESSED DURING OCTOBER, 1979 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
DOCKET NO./
EVENT DATE/
COMPONENT SUBCODE/CAUSE CODE / LER NO./
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ mat;UFACTURER CONTROL HO.
REPORT TYPE CAUSE DESCRIPTION ARKANSAS-2 05000368 081879 IMMEDIATELY FOLLOWING A PLANT TRIP, THE EMERGENCY FEEDWATER PUMP TURBINE COOL SYS FOR REAC AUX + C0hT 79-072/03L-0 091279 DRIVER, 2K3, FOR PUMP 2P7A TRIPPED OH OVERSPEED UPON RECEIPT OF EFAS SI TURBINES 026913 30-DAY GNAL.
THE ELECTRIC DRIVEN PUMP. 2P7B, WAS STARTED MANUALLY AT APPROXIMA SUBCCMP0HEHT NOT APPLICABLE TELY THE SAME TIME AS THE ACTUATION SYSTEM, RATHER THAN DELAYED AS PROGR OTHER AMMED WITH AUTO ACTUATION.
THIS OCCURRENCE IS SIMILAR TO LER 50-368/79-NOT APPLICABLE 055.
REPORTABLE PER T.S.
6.9.1.9B.
TERRY STEAM TURBINE CO'1PANY THE APPARENT CAUSE WAS STICKY LINKAGE ON THE TURBINE GOVERHOR; AND THE S IMULTAHEOUS START OF 2P7B DROPPING THE SUCTION PRESSURE, THUS REDUCING T HE PUMPING RESISTANCE.
PROCEDURE CHANGED TO CAUTION AGAINST SIMULTAHEOU S STARTS.
ARKANSAS-2 05000368 08207)
DURING MODE 1 OPERATION, ALL CEA CALCULATOR INPUTS TO THE CPC'S WERE PLA REACTIVITY CONTROL SYSTEMS 79-073/03L-0 091271 CED IN THE IHOP FOR DIAGNOSTIC TESTING OF CEAC OUTPUTS FOLLOWING SPURIOU INSTRUMENTATION + CONTROLS 026914 3 0 - D A't S PEHALTY FACTOR OUTPUTS WHICH CAUSED A REACTOR TRIP.
CONTINUATION OF M COMPUTATION MODULE ODE 1 OPERATION WAS ALLOWED BY MEETING THE REQUIREMENTS OF T.S.
ACTION S COMPONENT FAILURE TATEMENT T.S.
TABLE 3.5-1.
ACTION'5B.
THERE HAVE BEEN NO SIMILAR OCCURR INSTRUMENT ENCES.
THIS OCCURRENCE IS REPORTABLE PER T.S. 6.9.1.9B.
SYSTEMS ENGINEER. LABS., INC.
REPORTING OF MAINTENANCE ACTIVITY CAUSED BY HECESSITY OF ENTERING A T.S.
ACTION STATEMENT.
THE HIGH CEAC PEHALTY FACTORS WERE CAUSED BY DIRTY I NPUT CARD CONTACTS.
THE EDGE CONNECTOR WAS CLEAHED AND CEAC'S VERIFIED OPERABLE PER PROCEDURES 2304.108 AND 2304.109.
ARKAHSAS-2 05000368 OP?t79 DLRING MODE 1 OPERATION, THE CONTROL ROOM EMERGENCY AIR CONDITIONING UNI AIR COND. HEAT, COOL,VEHT SYSTEM 79-076/03L-0 Oi2079 T 2VE1B, FAILED TO START OH DEMAND FROM THE CONTROL ROOM.
THE REDUNDANT HEAT EXCHANGERS 026897 30-DAY EMERGENCY AIR CONDITIONING SYSTEM WAS VERIFIED OPERABLE.
OTHER OCCURRE COOLER NCES INVOLVING THE EMERGEHCY CONTROL AIR CONDITIONING ARE LER 50-368/79-COMPONENT FAILURE 050.
THIS OCCURRENCE IS REPORTABLE PER T.S.
6.9.1.9B.
MECHANICAL CVI CORP.
IMMEDIATE CORRECTIVE ACTION WAS TO RESET THE LOW DISCHARGE OIL PRESSURE SWITCH AND PROVE OPERABLE PER PROCEDURE 2104.34.
INVESTIGATION REVEALED A CRANKCASE OIL LEAK.
THE LEAK WAS REPAIRED, OIL AND FREON WERE ADDED, AND THE UNIT WAS OPERATIONAL CHECKED OUT.
ARKANSAS-2 05000368 382179 DURING MODE 1 OPERATION, THE "A" CPC TRIPS WERE BYPASSED TO ALLOW THE CH OTHR INST SYS REQD FOR SAFETY 79-074/03L-0 091279 ANGE OUT OF THE RSPT PCWER SUPPLIES WHICH WERE CAUSING ERROHEOUS POSITIO INSTRUMENTATION + CONTROLS 026907 30-DAY N INDICATION INPUTS TO THE CPC.
THE PULSE CCUHTER FRCM CEAC 32 AND THE POWER SUPPLY UPPER ELECTRICAL LIMITS WLRE AVAILABLE FCR CEA POSITION INDICATIONS. TH COMP 0HENT FAILURE ERE HAVE BEEN NO SIMILAR PCCURRENCES.
THIS OCCURREHCE IS RELATED TO.ER INSTRUMENT 50-368/79-073.
REPORTABLE PER T.S.
6.9.1.9B.
LAMBDA ELECTRONICS THE "A" CPC WAS TAKEN OUT OF SERVICE AS A PRECAUTIONARY STEP DURING THE MAINTENANCE ACTIVITY IN THE CPC CABIHET.
THE RSPT POWER SUPPLIES WERE C HAHGED OUT AND THE "A" CPC WAS RETURNED TO SERVICE WITHIH THREE HOURS ME ETING THE REQUIREMENTS OF ACTION STATEMENT T.S. TABLE 3.3-1 ACTIOH 2A.
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REPORT TYPE CAUSE DESCRIPTION ARKANSAS-2 05000368 082279 DURING MODE 1 OPERATION, THE DATA LINK FROM CEAC 51 TO THE "B" CPC DROPP REACTOR TRIP SYSTEMS 79-075/03L-0 091279 ED A BIT CAUSING AN INACCURATE OUTPUT INDICATION, RESULTING IN THE "B"
C INSTRUMENTATION + CONTROLS 026906 30-DAY PC CHANNEL TRIPPING. THE DATA LINK FAYLED IN THE CONSERVATIVE DIRECTION COMPUTATION MODULE AND THE REMAINING CEAC DATA LINKS WERE OPERABLE.
THERE HAVE BEEN NO SI COMPONENT FAILURE MILAR OCCURRENCES. REPORTABLE PER T.S.
6.9.1.98.
INSTRUMENT OTHER THE DATA LINK OUTPUT ERROR WAS CAUSED BY A FAILED OPTICAL AMPLIFIER.
TH E DATA LINK WAS REPAIRED AND THE "B" CPC RETURNED TO SERVICE WITHIN ONE HOUR MEETING THE REQUIREMENTS OF ACTION STATEMENT T.S.
TABLE 3.3-1 ACTID H 2A.
ARKANSAS-2 05000368 082679 DURING MODE 1 OPERATION, THE "D" SAFETY INJECTION TANK, 2T2D, LEVEL COUL EMERG CORE COOLING SYS + CONT 79-077/03L-0 092079 D NOT BE MAINTAINED ABOVE THE 80.1% INDICATED LEVEL AS RECUIRED BY T.S.
VALVE OPERATORS 026896 30-DAY 3.5.1B DUE TO MAKEUP VALVE, 2CV-5064 FAILING TO OPEN ON COMMAND.
THE O ELECTRIC MOTOR - AC THER SAFETY INJECTION TANKS REMAINED OPERATIONAL.
AN OCCURRENCE INVOLVI COMPONENT FAILURE NG SAFETY INJECTION TANKS IS LER 50-368/79-16; HOWEVER, IT IS NOT SIMILA ELECTRICAL R.
THIS OCCURRENCE IS REPORTABLE PER T.S. 6.9.1.9B.
E P G (DIV 0F GULF-W)
SAFETY INJECTION TANK MAKEUP VALVE, 2CV-5064, UAS MANU ALLY CPENED AND LE VEL WAS RETURNED TO NORMAL IN LESS THAN TWO HOURS. MEETING THE REQUIREME NT OF ACTION STATEMENT T.S.
3.5.1 ACTION A.
THE SPRING TENSION WAS ADJU STED ON THE VALVE OPERATOR GATE AND IT WAS RETURNED TO CPERATICNAL STATU S.
BEAVER VALLEY-1 05000334 042478 AT 1020 HOURS. THE LOOP B DELTA T-TAVG INDICATION FAILED DCUNSCALE. AT REACTOR TRIP SYSTEMS 78-034/03L-0 091879 1046 HOURS. THE INSTRUMENT LOOP BISTABLES WERE PLACED IN THE TRIPPED CCN INSTRUMENTATION + CONTROLS 026843 30-DAY DITION.
REDUNDANT INSTRUMENTATION REMAINED AVAILABLE UNTIL THE INSTRUME POWER SUPPLY NT LOOP WAS RETURNED TO SERVICE AT 1940 HOURS ON 4/25/78.
COMPONENT FAILURE INSTRUMENT WESTINGHOUSE ELECTRIC CORP.
THE INCIDENT RESULTED FROM THE FAILURE OF A CAPACITOR IN LCW LEVEL AMPLI FIER [TM-RC-422H] FOR LOOP B HOT LEG TEMPERATURE.
THE CAPACITCR WAS REP LACED AND THE LOOP WAS TESTED AND RETURNED TO OPERATION.
BEAVER VALLEY-1 05000334 010479 PLANT SHUTDOWN WITH ALL COOLING TOWER PUMPS SECURED. ON 1/4/79, CHLORIN STATION SERV WATER SYS + CONT 79-001/047-0 011979 ATION WAS PERFORMED IN RIVER WATER SYSTEMS AND EDTH CONDENSER SECTIONS.
COMPONENT CODE NOT APPLICABLE 026810 2-WEEK AT 1520 HRS, HIGH ALARM ON THE CHLORINE ANALYZER AT THE OUTFALL STRUCTU SUBCOMPONENT NOT APPLICABLE RE WAS RECEIVED. AT 1530 HRS, FREE CHLORINE RESIDUALS REACHED A MAXIMUM PERSONNEL ERROR OF 2.0 PPM, 3.
AT 1610 HRS, RETURNED TO <0.5 PPM.
AT 1745 HRS. HIGH AL OTHER ARM WAS AGAIN RECEIVED 2 MAXIMUM FREE CHLORINE RESIDUAL WAS 0.6S PPM.
A ITEM NOT APPLICABLE T 1815 HOURS, IT FETURNED TO LESS THAN 0.5 PPM.
WITH NO COOLING TOWER PUMPS OPERATING, FLOW THROUGH CONDENSER IS REVERSE D DUE TO OPERATION tc PLANT RIVER WATER SYSTEMS.
THEREFORE, ANY CHLORIN
~~*
E ADDITIONS INTENDED FOR CONDENSER ARE BACKWASHED TO RIVER WITUGUT PASSI (J7 NG THROUGH THE CONnFNSER.
PERSONNEL HAVE BEEN INSTRUCTED TO CHLORINATE 45, ONLY WITH AT LEAST ONE COOLING TOWER PUMP IN OPERATION.
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REPORT TYPE CAUSE DESCRIPTION BEAVER VALLEY-1 05000334 062479 DURING A RECORDS REVIEW ON 7/24/79, IT WAS DISCOVERED THAT THE RESULTS 0 REACTOR TRIP SYSTEMS 79-025/03L-0 082379 F A SURVEILLANCE TEST PERFORMED ON 6/24/79 WERE UNSATISFACTCRY. THE BIA INSTRUMENTATION + CONTROLS 026970 30-DAY SING CIRCUIT FCR THE CHANNEL 2 DELTA T-TAVG SIGNAL SUMMATOR WAS PRCCUCIN COMPUTATICH MODULE G AN OUTPUT SIGNAL SETPOINT APPROXIMATELY 25 DEGREES LESS THAN REQUIRED.
COMPONENT FAILURE THIS FAILURE WAS IN THE CONSERVATIVE DIRECTICH AND WOULD HAVE RESULTED INSTRUMENT IN THE CHANNEL TRIPPING SCONER THAN REQUIRED.
WESTINGHOUSE ELECTRIC CORP.
THE INCIDENT RESULTED FROM A FAILURE OF THE INSTRUMENT LOOP SIGNAL SUMMA TOR.
THE SUMMATOR WAS REPLACED AND THE LOOP WAS CALIERATED SUCCESSFULLY BEAVER VALLEY-1 05000334 072279 ON JULY 2,1979, ROCKWELL INTERHATIONAL INFORMED BVPS OF A POTENTIAL FOR CNTHMNT COMBUS GAS CCHTROL SYS 79-022/03L-0 081779 FAILURE OF THE INTERCONNECTING POWER CABLES ON THE CONTAIN"ENT HYCROGEN ELECTRICAL CONDUCTORS 026995 30-DAY RECOMBINERS. AT ANOTHER SITE, ONE OF THE POWER CONDUCTORS IN THE PCWER C SUBCOMP0HENT NOT APPLICABLE ABLE MELTED AT THE CONNECTOR WHICH PLUGS INTO THE RECOMBINER JUNCTICN BC PERSONNEL ERROR X.
WHILE DISASSEMBLING MAIN POWER CONNECTOR ON 1A RECOMBINER AT BVPS FCR OTHER INSPECTION, 3 0F THE 4 WIRES WERE LOGSE & PULLED CUT OF THE CONNECTCR.
ATOMICS INTERNATIONAL THERE WAS NO EVIDENCE OF OVERHEATING.
INCIDENT RESULTED FRCM INSUFFICIENT SETSCREW TORQUE CN THE UIRES IN THE PINS OF THE POWER CONNECTOR. THE WIRES WERE REINSTALLED WITH THE CORRECT SETSCREW TCRQUE AND SATISFACTGRILY TESTED.
THE FOUR WIRES IN THE CONNE CTOR OF THE IB RECOMBINER WERE INSPECTED AND VERIFIED TO HAVE BEEN INSTA LLED CORRECTLY.
BEAVER VALLEY-1 05000334 072379 AS A RESULT OF A REVIEW OF SIS CABLE USED IN CONTAINMENT, IT WAS DETERMI OTHR INST SYS REQD FOR SAFETY 79-019/01X-1 081779 NED WIRE FROM FOUR MANUFACTURFRS MAY HAVE BEEN INSTALLED.
THREE OF THE ELECTRICAL CONDUCTORS 026373 OTHER FCUR VENDORS HAVE SUPPLIED DOCUMENTATION INDICATING THEIR PRODUCTION RUN SUBCOMP0HENT NOT APPLICABLE S COVERING THE TIME PERICD THAT THE SIS WIRE WAS PURCHASED AND INSTALLED DESIGN / FABRICATION ERROR WOULD HAVE QUALIFIED FOR THE HOSTILE POST LOCA CONTAINMENT ENVIRONMENT.
DESIGN ITEM NOT APPLICABLE REVIEW OF AFFECTED EQUIPMENT IN CONTAINMENT BY ONSITE SAFETY COMMITTEE H AS DETERMINED THAT 4 VALVES REQUIPE WIRE REPLACEMENT PRIOR TO STARTUP.
REMAINING VLVS THAT DO NOT HAVE QUALIFIED SIS WIRE CLOSE ON CIB & WOULD NOT BE REQ. TO BE REOPEHED TO MITIGATE CONSEQUENCES OF AN ACCIDENT. CAB LE FOR SAFETY RELATED EQUIP. IN CONTAINMENT TO BE REPL DURING REFUELING.
BEAVER VALLEY-1 05000334 072479 AT 0315 HOURS DURING PERFORMANCE OF A SURVEILLANCE TEST. THE NO. 1 DIESE EMERG GENERATOR SYS + CONTROLS 79-023/03L-0 082379 L GENERATOR OUTPUT EREAKER FAILED TO CLOSE WHEN THE CONTROL SWITCH UAS A COMPONENT CODE NOT APPLICABLE 026971 30-DAY CTUATED.
IN ADDITION, AN ALARM WAS RECEIVED INDICATING A FAILURE OF THE SUBCOMP0HENT NOT APPLICABLE NO. 1 AIR START MOTORS TO START THE DIESEL GENERATCR.
THE DIESEL START OTHER ED ON THE NO. 2 AIR START MOTORS.
THE NO. 2 EMERGENCY DIESEL GENERATOR NOT APPLICABLF.
REMAINED OPERABLE THROUGHOUT THE PERIOD.
ITEM NOT APPLICABLE AIR START MOTOR FAILURE RESULTED FRCM A STICKING PINION ON AIR MOTCR.
P INION ASSEMBLY WAS CLEANED, EXERCISED, 1 SATISFACTORILY TESTED.
TEST CI RCUIT INSTALLED TO MONITUR BREAKER CONTROL CIRCUITRY INDICATED FAILURE O CCURRED IN MANUAL START RELAYS.
REPEATED CYCLING OF RELAYS DID NOT PROD CJ7 UCE ANY FAILURES. DLC ENGINEERING IS INVESTIGATING REPLACEMENT OF RELAYS 5%
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REPORT TYPE CAUSE DESCRIPTION BEAVER VALLEY-1 05000334 072c79 AS A RESULT OF REVIEW OF ASCO SOLENOID VALVES PER IE BULLETIN 79-01A, IT REACTOR CONTAINMENT SYSTEMS 79-024/017-1 081~79 HAS BEEN DETERMINED THAT THERE ARE 44 ASCO VALVES INSTALLED IN THE REAC VALVE OPERATORS 026501 2-W.EK TOR CONTAINMENT WHICH HAVE DEFICIENCIES IN ENVIRONMENTAL CUALIFICATIONS.
SOLEHOID - DC SEVERAL OF THESE VALVES HAVE CLASS HT OR HB HIGH TEMPERATURE COILS BUT DESIGN / FABRICATION ERROR HONE OF THE VALVES ARE OF THE NEW HDCLEAR CRADE TYPE NF-1.
THE PLANT SA DESIGN FETY COMMITTEE HAS DETERMINED THERE IS NO HAZARD TO THE GENERAL PUBLIC D ASCO URING THE INTERIM OPERATING PERIOD.
INADEQUATE DESIGN RESULTED IN INSTALLATION OF SUBJECT SOLENOID VALVES.
44 SOLENOID VALVES WILL BE REPLACED WITH TYPE NP-1 VALVES OR OTHER CUALI FIED VALVES DURING FALL REFUELING UUTAGE.
SOLFNOID VALVES ON A PRESSURI ZER PORV & 2 COMPONENT COOLING WATER ISOLATION VLVS TO EXCESS LETDCWN HE AT EXCHANGER HAVE BEEN REBUILT W/HI TEMP COILS & RENEWED INTERNAL PARTS.
BEAVER VALLEY-1 05000334 081679 AT 0635 HOURS, THE 1C CHARGING PUMP WAS STARTED FOR AN OPERABILITY VERI EMERG CORE COOLING SYS + CONT 79-029/03L-0 091479 FICATION FOLLOWING MAINTENANCE. AT 0738 HOURS, A HIGH TEMPERATURE ALARM VALVES 026841 30-DAY WAS RECEIVED FOR THE 1C CHARGING PUMP THRUST BEARING.
THE 1C CHARCING GATE PUMP WAS SHUTDOWN AT 0742 HOURS.
AN INVESTIGATION REVEALED A RIVER WATE PERSONNEL ERROR R SUPPLY VALVE TO THE CHARblNG PUMP SPEED INCREASER HAD BEEN INADVERTENT MAINTENANCE & REPAIR PERSONNEL LY LEFT SHUT FOLLOWING MAINTENANCE.
ITEM NOT APPLICABLE THE INCIDENT RESULTED FROM A FAILURE OF MAINTENANCE AND OPERATIONS PERSO NNEL TO INSURE THE CHARGING PUMP WAS RETURNED TO SERVICE SATISFACTCRILY FOLLOWING MAINTENANCE ACTIVITIES.
THE PERSONNEL INVOLVED RECEIVED WRITT EN REPRIMANDS COR THEIR ACTIONS.
ALL MAINTENANCE AND OPERATIONS PERSONN EL WERE APPRISED OF THE INCIDENT AND ITS CONSEQUENCES.
BEAVER VALLEY-1 05000334 082779 DURING A LOAD INCREASE, AT 99 PERCENT POWER, THE CHANNEL 3 OVERPOWER DEL REACTOR TRIP SYSTEMS 79-026/03L-0 092779 TA TEMPERATURE ALARM WAS RECEIVED.
AT 1830 HOURS, THE LOOP BISTABLES WE INSTRUMENTATION + CONTROLS 026972 30-DAY RE TRIPPED.
THE LOOP WAS CALIBRATED AND RETURNED TO SERVICE AT 1630 HOU POWER SUPPLY RS ON 8/29/79.
THE HEALTH AND SAFETY OF THE GENERAL PUBLIC WERE NOT JE0 DEFECTIVE PROCEDURES PARDIZED AS REDUNDANT INSTRUMENT LOOPS WERE AVAILABLE AND THE LOOP WAS P NOT APPLICABLE ROTECTING IN THE CONSERVATIVE DIRECTION.
WESTINGHOUSE ELECTRIC CORP.
INSTRUMENT LOOP WAS MISCALIBRATED AS RESULT 0.7 NOT HAVING CURRENT RTD CA LIBRATION DATA IN SURVEILLANCE TEST.
HOT LEG RTD WAS REPL ACED DURING PR EVIOUS OUTAGE & NEW CALIBRATION DATA WAS OBTAINED.
HOWEVER, NEW DATA WA S NOT INCLUDED IN LOOP CALIBRATION PROCEDURE. MAINTENANCE PROCEDURES WI LL BE REVISED TO INSURE REVISIONS PLACED IN CONTROLLED PROCEDURE FILE.
BIG ROCK POINT 05000155 061679 A CONTROL ROOM OPERATOR NOTED THAT STATIC INVERTER POWER SUPPLY FCR ONE OTHER ENGNRD SAFETY FEATR SYS 79-021/03L-0 071379 CONTAINMENT VACUUM RELIEF LOOP WAS DE-ENERGIZED & A BLOWN INPUT FUSE WAS INSTRUMENTATION + CONTROLS 026880 30-DAY FOUND. FUSE WAS REPLACED & UNIT RFSTORED TO OPERABILITY ON 6/16/79. BENC POWER SUPPLY H CHECKING COMPLETED ON 7/10/79 LID NOT REVEAL ANY OTHER DEFECT. REDUNDA DESIGN /FABRICATIGN ERROR NT LOOP WAS OPERABLE & NO HAZARD CCCURRED. PREVIOUS FAILURES REPORTED IN DESIGN R0-78-40 & R0-79-15. REPORTABLE PER TECHNICAL SPECIFICATION 6.9.2.B.(2)
TOPAZ ELECTRONICS BASED ON PREVIOUS EXPERIENCE WITH SAME TYPE INVERTER, IT IS HYPOTHESIZED
~~^
THAT LIGHTLY LOADED INVERTER SHOULD HAVE A DUMMY LOAD TO PRECLUDE FAILU (J7 RE ON INPUT VOLTAGE TRANSIENTS. EQUIPMENT IS BEING CHECKED ROUTINELY UNT 43, IL THIS MODIFICATION IS COMPLETED. LOAD ADDITION IS PLANNED PRICR TO PLA NT STARTUP.
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CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION BIG ROCK POINT 05000155 082279 DESIGN REVIEW OF REACTOR VESSEL LEVEL INSTRUMENT SYSTEM, LE RE09 3 LS RE EMERG CORE COOLING SYS + CONT 79-022/01T-0 090579 09 REVEALED THAT DURING POSTULATED LOSS OF COOLANT ACCIDENT CONDITIONS, INSTRUMENTATION + CONTROLS 026881 2-WEEK AUTOMATIC INITIATION OF REACTOR SCRAM, CONTAINMENT ISOLATION, & CORE SPR SENSOR / DETECTOR / ELEMENT AY ACTUATIONS THAT ARE INITIATED BY THIS SYSTEM MIGHT NOT FUNCTION DUE T DESIGN / FABRICATION ERROR 0 FLASHING THAT COULD OCCUR IN REFERENCE LINE DURING RAPID DEPRESSURIZAT DESIGN ION OF PRIMARY SYSTEM. REPORTABLE PER TECH. SPEC. 6.9.2.A (9).
YARWAY CORP.
THIS ITEM REPRESENTS A GENERIC DESIGN SHORTCOMING THAT WAS IDENTIFIED BY THE N.S.S.S.
VENDOR.
THE RESOLUTION IS STILL UNDER STUDY TO DETERMINE CORRECTIVE ACTION PRIOR TO PLANT START-UP.
BIG ROCK POINT 05000155 091179 DURING ROUTINE LEAK RATE TESTS OF AUTOMATIC ISOLATION VALVES IN REACTOR CNTHMNT ISOLATION SYS + CONT 79-023/03L-0 101079 3 FUEL PIT DRAIN LINE, VALVE CV/4027 EXHIBITED LEAKAGE OF 30 MILLILITER VALVES 027093 30-DAY PER MIN. WHICH IS IN EXCESS OF LIMIT DEFINED IN TECH SPEC 3.7(B).
REDUM GATE DANT VALVE CV/4117 UAS OPERABLE & THUS CONTAINMENT INTEGRITY WAS MAINTAI COMPONENT FAILURE HED.
SIMILAR LEAKAGE OF THIS VALVE HAS BEEN REPORTED IF R0-78-33 & A0-1 MECHANICAL 5-75 DATED 6/10/75.
BLACK-SIVALS-BRYSON INVESTIGATION REVEALED THAT SEATING SURFACE NEEDED TO BE MACHINED TO RED UCE DISC CONTACT AREA TO PROVIDE TIGHT SHUT-OFF CAPABILITY. NEW SEATS W ILL BE INSTALLED ON BOTH VALVES DURING A FUTURE OUTAGE.
SEAT UAS MACHIN ED & A VALVE RETEST WAS SATISFACTORY. REPORTABILITY IS BASED ON TECH SP EC 6.9.2BC2).
BIG ROCK POINT 05000155 091379 DURING ROUTINE TESTING OF REACTOR DEPRESSURIZING SYSTEM PUMP DISCHARGE P CTHER ENGNRD SAFETY FEATR SYS 79-024/03L-0 101079 RESSURE SWITCHES PS789, PS790, PS791, & PS792, SET POINTS UERE FOUND TO INSTRUMENTATION + CONTROLS 027092 30-DAY BE BETWEEN 1.0 8 3.5 PSI BELOW TECH SPEC REQUIREMENT OF >/: 100 PSI IN T SWITCH ABLE 3.5.2H.
THIS DEFECT W3ULD NOT PREVENT ADEQUATE OPERATION OF SYSTEM COMPONENT FAILURE
& NO HAZARD TO PUBLIC EXISTED.
INCIDENT IS NOT REPETITIVE. REPORTABLE OTHER BASED ON TECH SPEC 6.9.2.B(1).
STATIC-0-RING EXACT CAUSE OF INSTRUMENT DRIFT IS NOT KNOWN.
A TRENDING HISTORY WILL B E ESTABLISHED FOR THIS SWITCH.
THE PRESSURE SWITCHES WERE RESET TO TRIP AT 105 PSIG.
SWITCH IS MADE BY STATIC-0-RING AND IS MODEL GNN-G5-M2CIS SX.
BROWNS FERRY-1 05000259 072379 WITH UNIT 1 AT 1035 MWE, UNIT 2 AT 1095 MUE, & UNIT 3 IN OUTAGE, TVA'S F SYSTEM CODE NOT APPLICABLE 79-013/01X-1 091279 IELD INSPECTION & EVALUATION PROGRAM OF SELF-DRILLING EXPANSION ANCHORS COMPONENT CODE NOT APPLICABLE 026456 OTHER IS CONTINUING IN ACCORD WITH IE EULLETIN 79-02, 79-02 Rt, 1 79-02 R1 SUP SUBCOMPONENT NOT APPLICABLE PL 1 TO DATE 875 ANCHORS HAVE BEEN INSPECTED IN SAFETY-RELATED PIPING PERSONNEL ERROR SYS.
71 DEVIATIONS FOUND.
ON NOM-SAFETY-RELATED PIPING, 18 BOLT ANCHOR CONSTRUCTION PERSONNEL S PULL-TESTED, 2 SLIPPED, 4 2 PULLED OUT.
NO EFFECT TO HEALTH OR SAFETY ITEM NOT APPLICABLE OF PUBLIC.
EVENT REPORTED UNDER T.S.
6.7.2.A.(9).
DEVIATIONS DURING INSTALLATION DUE TO REBAR INTERFERENCE SHORTBOLTS 8 IM PROPERLY SEATED ANCHORS. ANCHORAGES WITH DEVIATIONS BEING EVALUATED BY T VA'S DIVISION OF ENG. DESIGN AS FOUND.
DIV 0F ENG DESIGN CONTINUING TO (y1 EVALUATE RESULTS OF ONGOING INSPECTION PROGRAM.
REPAIR PROG TO IMMED CO RRECT IMPROPERLY INSTALLED ANCHORS IS ONGOING WITH THE INSPECTION EFFORT 43, U
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CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION BROWNS FERRY-1 05000259 080479 DURING NORMAL OPERATION BREAKER CLOSURE SPRING FOR START BUS "1B" NORMAL AC ONSITE POWER SYS + CONTROLS 79-016/03L-0 083179 FEEDER BREAKER WAS FOUND TO BE DISCHARGED. THIS MADE THE BREAKER IHOPE CIRCUIT CLOSERS / INTERRUPTERS 026741 30-DAY RABLE FOR CLOSURE WHICH PLACED START BUS "1B" IN AN ABNORMAL CONDITICN C SWITCHGEAR ONTRARY TO T.S.
3.9.B.
THE DIESEL GENERATORS WERE VERIFIED CPERABLE.
T COMPONENT FAILURE HERE WAS NO EFFECT ON PUBLIC HEALTH AND SAFETY.
THERE HAVE BEEN NO PREV ELECTRICAL IOUS OCCURRENCES.
GENERAL ELECTRIC CO.
THE START BUS "1B" NORMAL FEEDER BREAKER SPRING CHARGING MOTOR CCMMUTATO R HAD A HOLE BURNED IN IT.
THIS CAUSED THE CLOSE CIRCUIT CONTROL FUSES TO BLOW AND ALSO LEFT THE CLL'URE SPRING IN A DISCHARGE CONDITION.
THE MOTOR, G.E.
105C9393 P3, WAS REPLACED AND THE BREAKER RETURNED TO SERVIC E.
BROWNS FERRY-1 05000259 080579 DURING NORMAL OPERATION A SMOKE DETECTOR FOR THE AUXILIARY INSTRUMENT RO FIRE PROTECTION SYS + CONT 79-015/03L-0 09b479 OM ALARMED AND WOULD NOT CLEAR.
THE ALARi1 MOULD HAVE MASKED SIGNALS FR0 INSTRUMENTATION + CONTROLS 026742 30-DAY M DETECTORS WHICH ARE REQUIRED TO DE OPERATIONAL BY T.S.
3.11.C.1 THER SEN3OR/ DETECTOR / ELEMENT E WEPE NO EFFECTS CH PUBLIC HEALTH OR SAFETY.
THERE ARE NO REDUNDANT SY COMPGNENT FAILURE STEMS.
SIMILAR EVENTS:
296/77-2, 259/73-01, 259/73-09, 296/78-09, 296/
NATURAL END OF LIFE 78-17, 296/78-23, 296/78-26, 296/78-23.
KIODE, WALTER & CO THE SMOKE DETECTOR WENT INTO ALARM STATE DUE TO INCREASED DETECTOR SENSI TIVITY.
THE KIDDE FT-200 DETECTOR WAS REPLACED. A FIRE WATCH WAS ESTAB LISHED UNTIL REPAIRS WERE MADE.
BROWNS FERRY-1 05000259 080979 DUE TO G.E. REEVALUATION OF POST-LOCA CONDITIONS, GE SIL 299. HIGH DRYWE REACTOR TRIP SYSTEMS 79-017/03L-0 090779 LL TEM *ERATURE EFFECT ON REACTOR VESSEL WATER LEVEL INSTRUMENTATION, THE COMPONENT CODE NOT APPLICABLE 026740 30-DAY REACTOR WATER LEVEL INDICATIONS CAN BE 29 INCHES LESS THAN INDICATED BT SUBCOMPONENT NOT APPLICABLE PRESENT PROCEDURES.
THERE WAS NO HAZARD TO THE PUBLIC HEALTH CR SAFETY.
OTHER THERE HAVE BEEN NO PREVIOUS OCCURRENCES. REDUNDANT SYSTEMS ARE NOT APPL NOT APPLICABLE ICABLE.
GENERAL ELECTRIC CO.
THE REEVALUATION OF HIGH DRYWELL TEMPERATURE EFFECTS ON THE REACTOR VESS EL WATER LEVEL INSTRUMENTATION HAS RESULTED IN A DESIGN CHANGE REQUEST 1 875 SUBMITTED REQUESTING A SETPOINT CHANGE FOR LIS-3-53A-D.
BRCWNS FERRY-1 05000259 082379 WITH UNIT IN NORMAL OPERATION AT 9 5 ?. PCWER. INSPECTIONS UERE MADE IN ACC DEMIN WATER MAKE-UP 79-018/01T-0 090679 ORDANCE WITH I E BU'.L ET IN 7 9-14.
N' RING THIS INSPECTION IT WAS FOUND THA HANGERS, SUPPORTS, SHOCK SUPPRSS 026778 2-WEEK T RESTRAINTS ON CERTAIN CSSC SYSTE.15 WERE INOPERABLE IN THAT THEIR CONFI OTHER GURATION DID NOT CONFORM TO THE DESIGN SPECIFICATIONS. THERE WERE NO RE OTHER SULTING SIGNIFICANT OCCURRENCES, NO PREVIOUS sit 1ILAR EVENTS AND HO DANGE NOT APPLICABLE R TO HEALTH OR SAFETY OF THE PUBLIC.
THIS EVENT WAS REPORTED UNDER T.S.
TENNESSEE VALLEY AUTHORITY 6.7.2.A.9.
PIPE VIBRATION AND/OR IMPROPER INSTALLATION DURING CONSTRUCTION CAUSED T HE INOPERABILITY. SIMILAR RESTRAINTS IN UNITS 1, 2. AND 3 ARE BEING INS CJ7 PECTED AND A FOLLOWUP REPORT WILL BE ISSUED.
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NOV 08, 1979 LER MONTHLY REPORT SORTED BY FACILITY PAGE 12 PROCESSED DURING OCTOBER. 1979 FOR PCWER REACTORS FACIL TY/ SYSTEM / COMPONENT /
DOCKET NO./
EVENT DATE/
COMPONENT SUBCODE/CAUSE CODE / LER NO./
REPORT DATE/
EVENT DESCRIPTION /
CAUSE-SUSCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION BROWNS FERRY-1 05000259 083179 DURING NORMAL OPERATION, CONTAINMENT OXYGEN CONCENTRATION EXCEEDED 4% (T REACTOR CONTAINMENT SYSTEMS 79-020/03L-0 092879
.S.
3.7.A.5.A) AND DRYWELL-SUPPRESSION CHAMBER DIFFERENTIAL PRESSURE DEC COMPONENT CODE NOT APPLICABLE 026943 30-DAY REASED BELOW 1.0 PSID (T.S.
3.7.A.6).
THERE ARE NO REDUNDANT SYSTEMS.
SUBCOMPONENT NOT APPLICABLE THERE WAS N0 HAZARD TO THE PUBLIC HEALTH OR SAFETY, AND THERE WERE NO PR OTHER EVIOUS OCCURRENCES.
NOT APPLICABLE ITEM NOT APPLICABLE THE PRIMARY CONTAINMENT OXYGEN CONCENTRATION HAD BEEN INCREASED AND DRYU ELL-SUPPRESSION CHAMBER DIFFERENTIAL PRESSURE DECREASED IN PREPARATION F OR A PLANNED REACTOR SHUTDOWN.
THE SHUTDOWN WAS DEFERRED DUE TO A FORCE D SHUTDOWN OF UNIT 2.
CONTAINMENT REINERTED & DIFFERENTIAL PRESS REESTA BLISHED WITHIN 24 HRS.
NO RECURRENCE CONTROL ACTION IS REQUIRED.
BROWNS FERRY-1 05000259 090279 WITH UNIT IN HOT STANDBY AT LESS THAN 25 PSIG CCNTAINMENT ISCLATICH VALV REAC CORE ISOL COOL SYS + CONT 79-021/03L-0 100179 E FCV-71-3 WOULD NOT CLOSE AND WAS I N O P E R A B '. E. CONTRARY TO TECHNICAL SP VALVE OPERATORS 026954 30-DAY ECIFICATION 3.7.D.1, FCV 71-2 IN THE SAME LINE WAS CLOSED TO PROVIDE ISO ELECTRIC MOTOR - DC LATION.
THERE WAS NO HAZARD TO THE PUDLIC'S HEALTH OR SAFETY.
THERE WE COMPONENT FAILURE RE NO PREVIOUS OCCURRENCES.
ELECTRICAL OTHER PEERLESS ELECTRIC MOTOR, S/N GV 79985 HAD A MOTOR FAILURE. THE CAUSE OF THE PROBLEM IS NOT KNOWN.
THE MOTOR WAS REPLACED. THE OPERATING LIMIT S OF THE VALVE WERE RESET AND THE VALVE WAS OPERATIONALLY TESTED.
THE F AILURE WAS RANDCM AND NO RECURPENCE CONTROL IS NECESSARY.
BROWNS FERRY-2 05000260 053079 WITH REACTOR AT RATED TEMPERATURE AND PRESSURE, THE RCIC TRIPPED OH OVER REAC CORE ISOL COOL SYS + CONT 79-013/03L-1 092479 SPEED DURING FLOW TEST.
DURING THE INVESTIGATION, THERE WAS A LOSS OF S MECHANICAL FUNCTION UNITS 026166 30-DAY PEED SIGNAL IN THE CONTROL ROOM.
THERE WERE NO SIGNIFICANT RESULTING EV SUBCOMPONENT NOT APPLICABLE ENTS AND HO DANGER TO HEALTH OR SAFETY OF THE PUBLIC. PREVIOUS CCCURREN PERSONNEL ERROR CES: BFR0 50-296/78-32, BFR0 50-259/76-15. TECHNICAL SPECIFICATION 3.5.F OTHER WAS INVOLVED.
WOODWARD GOVERNOR CD.
IMPROPER INITIAL ASSEMBLY ALLOWED TURBINE WHEEL NUT TO LOOSEN DESTROYING THREADS AND CAUSING AXIAL LOADING OF BEARINGS. BEARING WEAR ALLOWED SH AFT TO STRIKE PICK-UP CAUSING SPEED CONTROL MALFUNCTION, THUS THROTTLE V ALVE REMAINED GPEN.
WHEEL NUT, BEARINGS, AND ACTUATOR REPLACED. WOOCWA RD GOVERNOR, SH 968510.
TEkRY TURBINE, MODEL A8250 TYPE GS-1.
BROWNS FERRY-3 05000296 081579 DURING NORMAL OPERATION WHILE PERFORMING SI 4.1.A-14. TURBINE FIRST STAG REACTOR TRIP SYSTEMS 79-012/03L-0 091479 E PRESSURE PERMISSIVE. PRESSURE SWITCH 1-81A SETPOINT WAS FOUND TO EXCEE INSTRUMENTATION + CCNTROLS 026776 30-DAY D THE T.S. LIMIT SPECIFIED IN TABLE 3.1.A.
BY 8 PSIG.
THERE WAS NO HAZA OTHER RD TO THE PUBLIC HEALTH CR SAFETY.
THERE ARE NO REDUNDANT SYSTEMS.
PRE OTHER VIOUS OCCURRENCES:
259/79-8, 259/78-16, 260/79-16 AND 296/79-7.
NOT APPLICABLE BARKSDALE VALVE COMPANY THE MODEL B2TA12Sb SETPOINT HAD CRIFTED OUT OF THE SPECIFIED LIMIT.
THE SUITCH WAS RECALIrtATED AND SATISFACTORILY FUNCTIONALLY TESTED.
THE FR EQUENCY OF TESTING HAS BEEN INCREASED TO TRY TO DETERMINE THE CAUSE OF T (J7 HE SETPOINT DRIFT.
THESE WILL BE REPLACED WITH ANALOG TRIP UNITS IN THE siiTuor (A
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NOV 08, 1979 LER MONTHLY REPORT SORTED BY FACILITY PAGE 13 r,
PROCESSED DURING OCTOBER, 1979 IOR POWER REACTORS FACILITY / SYSTEM /CCMPONENT/
DOCXET NO./
EVENT DATE/
COMPONENT SUECODE/C/JSE CODE / LER NO./
REPCRT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION BROWNS FERRY-3 05000296 031679 DURING HORMAL OPERATION WHILE CORE DRILLING IN THE U-3 DIESEL GENERATOR FIRE PROTECTION SYS + CONT 79-013/03L-0 091479 EUILDING THE CARBON DIDXIDE PILOT VALVE LINE FOR FCV-39-36 AND FCV-39-27 COMPONENT CODE NOT APPLICABLE 026774 30-DAY WAS CUT.
THE CARBON DIDXIDE SYSTEM FOR BOARD ROOMS 3EA AND 3EB WAS MAD SUBCOMPONENT NOT APPLICABLE E INOPERABLE T.S.
3.11.B.1 THERE WAS NO HAZARD TO THE PUBLIC HEALTH OR
'ESIGN/ FABRICATION ERROR SAFETY.
THERE HAVE BEEN NO PREVIOUS OCCURRENCES. THERE ARE NO REDUNDA uGNSTRUCTION/ INSTALLATION NT SYSTEMS.
ATEM NOT APPLICABLE THE Ef1 BEDDED PIPING DRAWING WAS IN ERROR.
THE EMBEDDED PIPE DID NOT APP EAR ON THE DRAWING.
THE SAFETY ENGINEER UAS NOTIFIED AND A FIRE WATCH E STABLISHED WHILE THE SYSTEM WAS INOPERABLE.
THE DAMAGED PIPE WAS REPAIR ED.
THE DRAWING WILL BE CORRECTED TO PREVENT RECURRENCE.
BROWNS FERRY-3 05000296 083179 DURING REFUELING UHILE PERFORMING LOCAL LEAK RATE TESTING, 5 MSIV'S EXCE MAIN STEAM ISOL SYS + CONTROLS 79-C14/03L-0 092777 EDED LEAKAGE LIMITS CF 11.5 SCFH CONTRARY TO T.S.
4.7.A.2.I.
REDUNDANT VALVES 026942 30-D
SYSTEMS WERE NOT APPLICABLE SINCE REACTOR WAS IN REFUELING MODE.
THERE GLOBE WAS NO SIGNIFICANT RESULTING CHAIN OF EVENTS AND NO DANGER TO HEALTH OR COMPCMENT FAILURE SAFETY OF THE PUBLIC.
PREVIOUS OCCURRENCES BFRO-50-296/78-25, 259/78-3, MECHANICAL 4 259/77-23, 259/79-03, 260/79-13, 260/79-7, 260/78-9.
ATUOOD & MCRRILL CO.,
INC.
EVENT WAS CAUSED BY AGE AND USE OF SEATING SURFACES. VALVE SEATING SURF ACES UILL BE REPAIRED AND MSIV'S RETESTED TO MEET TECHNICAL SPECIFICATI0 NS PRIOR TO RETURN TO UNIT STARTUP.
ATWOOD AND MORRILL 26-INCH GLOBE, V ALVE MODEL 20851 H.
1250 PSIG.
BRUNSWICK-1 05000325 060979 WHILE PERFORMING A NORMAL REACTOR STARTUP, CONTROL ROD 18-23 HAD NO INDI SAFETY RELATED DISPLAY INSTR 79-043/03X-1 092379 CATION AT NOTCH 30.
TECHNICAL SPECIFICATION 3.1.3.7, 6.9.1.9B.
INSTRUMENTATICN + CONTROLS 026160 OIHER SUITCH COMPONENT FAILURE ELECTRICAL GENERAL ELECTRIC CO.
THE REED SUITCH FOR NOTCH 30 INDICATION WAS FOUND DEFECTIVE AND REPLACED THE SYSTEM WAS TESTED AND RETURNED TO SERVICE SATTSFACTORILY. DUE TO AN INCREASING NUMBER OF INDICATIMG PROBLEMS, AN Et,GINEERING UORK REQUES T HAS BEEN WRITTEN TO DETERMINE IF THERE IS A GENERIC PROBLEM WITH THE P OSITION INDICATING SYSTEF.
BRUNSUICK-1 05000325 072879 DURING A NO Rf1 A L REACTOR STARTUP, ROD 26-15 HAD NO POSITION INDICATION AT SAFETY RELATED DISPLAY INSTR 79-052/03X-1 092879 NOTCH 38 AND ROD 18-23 HAD NO POSITION INDICATION AT NOTCH 30.
TECHNIC INSTRUMENTATION + CONTROLS 026517 OTHER AL SPECIFTCATION 3.1.3.7, 6.9.1.98.
SWITCH COM?ONENT FAILURE ELECTRICAL GENERAL ELECTRIC CO.
BOTH ROD POSITIONS HAD DEFECTIVE REED SWITCHES WHICH WERE REPLACED. BOT H INDICATING SYSTEMS WERE TESTED AND RETURNED TO SERVICE SATISFACTORILY.
(ya DUE TO THE INCREASING MUMBER OF INDICtTING PROBLEMS, AN ENGINEERING WDR K REQUEST HAS CEEN URITTEN TO DETERMINE IF THE POSITION INDICATING SYSTE 4D*
M FA7 LURES ARE GENERIC.
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UCV 08, 1979 LER MONTHLY REPORT SORTED BY FACILITY PAGE 14 PROCESSED DURING CCTOBER, 1979 FOR POWER REACTORS FACILITY / SYSTEM /CCMPONENT/
DOCKET NO./
EVENT DATE/
COM"GNENT SUSCODE/CAUSE CODE / LER NO./
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SU3 CODE / MANUFACTURER CONTROL NO.
REPORT TYPE CAUEE DESCRIPTION BRUNSWICK-1 05000325 030879 WHILE PERFORMING PT 1.1.13P, HIGH STEAMLINE RADIATION CHANNEL ALIGNMENT PRCSS + EFF RADIOL MONITOR SYS 79-056/03L-0 090679 AND FUNCTION TEST, MAIN STEAM LINE HI RAD MONITOR "B" WAS FOUND TO BE AC INSTRUMENTATION + CONTROLS 026739 30-DAY TUATING AT 3.95 X BACKGROUND WHILE THE ALLOWABLE LIMIT IS </: 3.5 X BACK CCMPUTATION MODULE GROUNO.
TECHNICAL SPECIFICATIONS 2.2.1, 6.9.1.9A.
OTEER NOT APPLICA3LE GENERAL ELECTRIC CD.
QUT OF TOLERtNCE READING WAS ATTRIBUTED TO INSTRUMENT DRIFT. MONITOR WAS RECALIBRATED 8 RETURNED TO SERVICE. GENERAL ELECTRIC UILL BE REQUESTED TO PROVIDE TECHNICAL ASSISTANCE IN DETERMINING CAUSE OF INSTRUMENT DRIFT
& DETERMINING CORRECTIVE ACTION. A SUPPLEMENT REPORT WILL BE ISSUED UHE N REQUIRED CORRECTIVE ACTION HAS BEEN DETERMINED.
ERUNSMICK-1 05000325 032079 CURING A NORMAL STARTUP AND FOLLCUING POWER INCREASE. THE OPERATOR NOTIC SAFETY RELATED DISPLAY INSTR 79-C51/03L-0 091779 ED THAT POSITION 12 ON ROD 06-43 WAS NOT INDICATING. TECHNICAL SPECIFIC INSTRUMEHTATION + CONTROLS 026022 30-DAY ATIONS 3.1.3.7, 6.9.1.93.
SENSOR / DETECTOR / ELEMENT COMPCNEHT FAILURE ELECTRICAL GENERAL ELECTR?.C CO.
A6 INVESTIGATION DETERMINED THAT THE PROBLEM UAS PROBABLY A SHORT IN THE PIP PROBE OF THE NOTCH 12 REED SWITCH.
THIS PROBLEM WILL BE CORRECTED DURING THE FIRST CUTAGE OF SUFFICIENT LENGTH TO ENTER THE DRYWELL.
B RUN S!!!C K-1 05000325 002479 AFTER REACHING 99% POWER FOLLOWING REDUCED POWER OPERATION DUE TO CONDEN REACIOR CORE 79-063/03L-0 092079 SER BACK PRESSURE, A DAILY CORE PARAMETER CHECK REVEALED THAT THE LHGR W CCMPONENT COEE NOT APPLICAELE 026823 30-DAY AS 13.59 KW/FT., OR GREATER THAN THE MLHGR OF 13.4 KU/FT THE NUCLEAR EN SU200M?ONEN~ NOT APPLICABLE GINEER HAD ESTIMATED AT 967 POUER THAT SUFFICIENT MARGIN EXISTED IN LHGR DEFECTIV: TRUCEDURES TO ALLOW FULL POWER OPERATIONS. POWER WAS IMMEDIATELY REDUCED AND LHGR NOT APPLICABLE RETURNED WITHIN SPECIFICATIONS. TECHNICAL SPECIFICATIONS 3.2.4, 6.9.1.
ITEM NOT APPLICABLE SB.
THE CAUSE OF THIS EVENT WAS OPERATING WITHOUT A MARGIN TO THE MLHGR AND NOT MONITORING THE APPROACH TO THE MLHCR LIMIT WHILE INCREASING REACTOR
- POWER, TiiIS UAS CAUSED BY NOT HAVING COMPLETED ALL PREVENTATIVE MEASURE S OF LER 1-79-022, DATED 8-21-79.
OPERATING RESTRICTIONS WERE PLACED IN THE DAILY INSTRUCTIONS AND AT THE NUCLEAR ENGINEER'S DESK.
ORUNSWICK-1 05000325 032379 DURING A REk?EU OF UNIT 1 CORE LOAD VIDEOTAPES. IT WAS DISCOVERED THAT B REACTCR CORE 7!-062/01T-0 091179 UNPLE 29-10, SERIAL NUMBER LJO 197. HAD BEEN PLACED IN CORE 130 DEG FROM FUEL ELEMENTS 02673S 2-W2EK RLyUIRED ORIENTATION.
THIS WAS VERIFIED BY CHANNEL FASTENER LOCATION 3 SUSCOMPONENT NOT APPLICABLE SER'tL NUMBER ALIGNMENT. PRELIMINARY ANALYSIS BY G.E.
INDICATED THAT C PERSCHNEL ERROR OHTle.JED GPERATION OF THE UNIT CAN BE SUPPORTED WITH THIS CONDITION. TEC OTHER ENICAL SPECIFICATION 6.9.1.3I.
GENERAL ELECTRIC CD.
A REVIEW OF REFUELING RECORDS INDICATED THAT BUNDLE LJO 197 WAS MOVED DU RING 1979 REFUELING CUTAGE FROM POSITION 33-02 TO POSITION 29-10 WITH N3 kJI CHANGE IN ORIENTATION REGUIRED. AN EVALUATION OF FUEL MOVEMENT PLAN IND J2*
ICATES NO APPARENT CAUSE FOR THE SUNDLE ROTATION. CORE VERIFICATION BY A (ja SPD, A NUCLEAR ENG, 1 A Q.A.
TECHNICIAN FAILED TO DETECT ROTATED BUNDLE C3 Cr4 Ch
NOV 08, 1979 LER MONTHLY REPORT SORTED BY FACILITY PAGE 15 PROCESSED DURING OCTOBER, 1979 FOR PCWER REACTORS FACILITY / SYSTEM / COMP 0HENT/
DOCKET NO./
EVENT DATE/
COMPONENT SUBCODE/CAUSE CODE / LER NO./
REPCRT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION BRUNSWICK-1 05000325 090479 DURING HORMAL PLANT OPERATION, THE CPERATOR NOTICED THAT THE CRYWELL OXY CNTNMNT COMBUS GAS CONTROL EYS 79-050/03L-0 100179 GEN / HYDROGEN MONITCR, CAC-1263. MADE A STEP INCREASE FOR NO APPARENT REA INSTRUMENTATION + CONTROLS 026941 30-DAY SON.
DRYWELL OXYGEN CONCENTRATION DID NOT EXCEED 4%.
TECHNICAL SPECIFI COMPUTATION MODULE CATIONS 3.6.6.4, 6.9.1.93.
COMPONENT FAILURE ELECTRONIC BECKMAN INSTRUMENT 3, INC.
CALIBRATION CHECK FCUn7 INSTRUMENT "ZER0" SHIFTED APPRCX 40% FOR NO APPA RENT REASCN, GIVING AB0vI A 2% SHIFT IN MONITOR.
INSTRUMENT RECALIBRtTE D3 RETURNED TO SERVICE SATIS.
AS THIS IS FIRST TIME INSTRUMENT HAS CEE N CUT OF CALILRATION SINCE GCING TO A SIUEEKLY CALIBRATION, THIS IS CONS IDERED AN ISOLATED EVENT AND NO FURTHER /CTION IS RE^UIRED.
B RI'N SWIC K-1 05000325 090579 DURING A ROUTINE SURVEILLANCE OF THE CONTROL PANEL, THE CPERATCR NOTICED FMERG CORE COOLING SYS + CONT 79-038/03L-0 100279 THAT HE DID DDT HAVE ANY INDICATION OF THE VALVE POSITION FCR E41-F006, AELAYS 026950 30-DAY HPCI INJECTIJN VALVE, CN THE RTGB OR AT THE LCCAL MOTCP CCNTROL CENTER.
CONTROL, GENERAL PURPOSC THE HPCI SYSTEM WAS DECLARED INOPERABLE.
TECHNICAL SPECIFICATICNS 3.5.
COMPONENT FAILURE
- i. 6.9.1.98.
ELECTRICAL GENERAL ELECTRIC CD.
THE CONTROL POWER FUSE WAS FOUND BLOWN DUE TO A SHORTED RELAY COIL.
THE FUSE AND THE RELAY COIL UERE REPLACED.
A REASON COULD NOT BE DETERMIHE D FOR THE SHORTED COIL.
AS THIS IS A FIRST TIME OCCURRENCE, THIS IS CCN SIDERED AN ISOLATED EVENT AND NO FURTHER ACTION IS REQUIRED.
BRUNSWICK-1 05000325 090879 WHILE PERFORMING PT 14.1, CONTROL RCD GPERABILITY CHECK, RCD 02-35 HAD N SAFETY RELATED DISPLAY INSTR 79-064/03L-0 100179 0 POSITION INDICATION AT NOTCH 46 UUEN THE ROD MAS DRIVEN IN.
NO PRCOLE INSTRUMENTATION + CONTROLS 026940 30-DAY M WAS EXPERIENCED AT THE NCFMAL RCD PGSITION, NOTCH 43.
TECHNICAL SPECI INDICATOR
~
FICATION 3.1.3.7.
6.9.1.9B.
OTHER NOT APPLICABLE GENERAL ELECTRIC CD.
AN OPERATIONAL CHECK OF ROD 02-35 AND A CHECK OF THE CIRCUITRY REVEALED NO PROBLEM.
PT 14.1 WAS RUN AGAIN ON 9/17/79 UITH NORMAL INDICATICN AT NOTCH 46 ON ROD 02-35.
THE POSITICN INDICATION OF ALL ROD 3 UILL DE CONT INUALLY MONITORED DURING OPERATION AND DURING RCD MOVING PT'S.
BRUNSWICK-1 05000325 091679 WHILE PERFORMING PT 55.9 PC, SHUTCCUN PANEL RHR SERVICE WATER D/P CALIER STATION SERV WATER SYS
- CONT 79-060/03L-0 100270 ATION, DIFFERENTIAL PRESSURE TRtNSMITTER 1E11-PDT-N0023X FAILED TO RESPD INSTRUMENTATION + CONTRO:S 026955 30-DAY ND 10 A TEST SIGNAL.
TECHNICAL SPECIFICATIONS 3.3.5.2, 6.9.1.53.
TRANSMITTER COMPONENT FAILURE ELECTRONIC ROSEMOUNT, INC.
THE TRANSMITTER CAPSULE FAILED CAUSING NO CUTPUT SIGNAL FCR THE INDICATO R.
A NEW TRAN5MITTER HAS BEEN GCDERED AND IS TO ARRIVE LY OCTC'ER 10, (yq 979.
WHEN THE TRAN MITTER IS RECEIVED, IT UILL LE INSTALLED, LALISPSTED 45" AND RETURNED TO SERVICE.
AS THIS IS THE FIRST FAILUCE CF THIS INSTRUM
(/4 ENT, THIS IS CONSIDERED AN ISCLATED EVENT.
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NOV 08, 1979 LER MONTHLY REPORT SORTED BY FACILITY PAGE 16 PROCESSED DURING OCTOBER, 1979 FOR POWER REACTORS FACILITY / SYSTEM /CCMPONENT/
DOCKET NO./
EVENT DATE/
COMPONENT SUBCODE/CAUSE CODE / LER NO./
REPORT DATE/
EVENT DESCRIPTICN/
CAUSE'SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION BRUNSWICK-1 05000325 091679 DURING'A NORMAL REACTOR STARTUP, THE 0'ERATOR NOTICED THAT ROD 26-15 DID SAFETY RELATED DISPLAY INSTR 79-067/03L-0 100379 NOT HAVE POSITION INDICATION AT NOTCHES 30, 31, 34. AND 35.
ALL OTHER INSTRUMENTATION + CONTROLS 026956 30-DAY INDICATIONS RERE NORMAL.
TECHNICAL SPECIFICATIONS 3.1.3.7, 6.9.1.9C.
SWITCH COMPONENT FAILURE ELECTRICAL GENERAL ELECTRIC CO.
TROUBLESHOOTING ROD 26-15 DETERMINED THAT THE PROBLEM EXISTED IN THE PIP PROBE LOCATED IN THE DRYWELL.
THIS PROBf Fil W'LL BE CORRECTED DURING TH E NEXT GUTAGE OF SUFFICIENT LENGTH.
DUE Th. INCREASING NC; DER OF ROD POSITION INDICATION PROBLEMS, AN ENGINEERING UORK REQUEST HAS BEEN SUZ ITTED TO INVESTIGATE THE PROBLEM.
BRUNSWICK-1 05000325 091779 WHILE PERFORMING PT 19.6.0.2, VISUAL INSF_CTION OF ACCE 3IBLE SNUBBERS 0 OTHER ENGNRD SAFETY FEATR SYS 79-061/03L-0 100379 H SAFETY RELATED SYSTEMS, THE FOLLOWING WLRE FOUND INOFtRABLE:
- 1) 15u-1 HANGERS SUPPORTS, SHOCK SUPPRSS 026957 30-DAY 73SS175, SERVICE WATER TO DISCHARGE CANAL; 2) 1 E 11 - 11. S 3 4 7. LINE RUR HEAT SNUBBERS EXCHANGER TO VESSEL; 3) IC41-95S27, LINE FROM SLC
'MP S 'O VESSEL; 4) 1 COMPONENT FAILURE G41-1SS22. FUEL POOL COOLING LINE TO RHR: 5) 1G4t 20SS76. FUEL ? COL CCOL MECHANICAL ING RECIRCULATION LINE.
TECHNICAL SPECIFICAT MNS 3.7.5, 6.9.1.33.
BERGEN-PATTERSON PIPE SUPPORT SNUBBERS 15U-1735S175, AND 1 E 11-18 S S 47 HA-LUat #LUID LEVEL.
THESE SMU BBERS WERE RE3UILT WITH NEW SEALS AND FUNC.
HALLi TESTED.
SI:UB3ERS 1C4 1-9SS27, AND 1541-15S22, AND 1G41-20SS76 HA.
'.COSE PI5E CLAM?S UHICH ALL
'OMED SNUBSERS TO SLIP CN THEIR PIPES.
SNUBBERS UERE POSITICNED PER PLAN T DRAWINGS 3 TIGHTENED. TESTING OF SNUBSERS WILL t" 'INUE PER TECH SPEC BRUNSWICK-1 05000325 092179 REVIEW OF REACTOR VESSEL UATER LEVEL INSTRUMENTATIG
'OLLOUING RECEIPT 0 ENGNRD SAFETY FEATR INSTR SYS 79-070/03L-0 100379 F GENERAL ELECTRIC SERVICE INFO LETTER 299 RESULTt
'N IDENTIFICATION INSTRUMENTATION + CONTROLS 026958 30-DAY OF POTENTIAL INACCURACY WHICH COULD OCCUD UNDER ! dM CCNDITION OF VER SENSOR / DETECTOR / ELEMENT Y HI DRYWELL TEMP. CHARACTERIZED BY ACCIDENT COND. TIC 3.
EFFECT OF IMACC DESIGN / FABRICATION ERROR URACY IS ACCEPTABLE FROM A SAFETY STAND POINT, BUT
- COULD RESULT IN RE DESIGN DUCTION IN REDUNDANCY OF INITIATING SIGNALS OF SF cMERG. CCRE COOLING YARWAY CORP.
SYS 1 LEAD TO MISINTERPRETATION OF ACTUAL VESSEL LEVEL LY OPERATCR.
LARGE INCREASES IN DRYMELL TEMP., SUCH AS THOSE THAT COULD OCCUR CURING A PIFE RUPTURE TN DRfuELL, WOULD CAUSE REF. LEG OF YARUAY LEVEL INDICATI ONS TO HEAT UP. AS REF. LEG TEMP. INCREASES, ITS DENSITY WILL DECREASE C AUSING A DECREASING D/P. THIS CECREASING D/P UCULD REGISTER AS AN INCREA SING VESSEL LEVEL ON D/P CELL INDICATOR E REMOTE INDICATION.
BRUNSWICK-1 05000325 G92779 DURING REVIEU OF ECCS DIVISICH SEPARATION, DETERMINED THAT DIVISICN II C EMERG CORE COOLING SYS + CONT 79-058/01T-0 100979 ABLES FOR HPCI INBOARD ISOLATIDH VLV (G41-F002), DIV. II VLV, RUN IN SFC ELECTRICAL CONDUCTORS 026949 2-UEEK TICNS OF CABLE TRAY CONTAINING DIV. II ADS SYS CABLES.
SUBSEQUENT ANALY SUBCOMPONENT NOT APPLICABLE SIS OF CABLES REVEALED IF ISCLATION VLV WAS IN URONG POSITION, A FAILURE DESIGN / FABRICATION ERROR AT A TRAY SECT CONTAINING THESE CABLES MICHT RESUL1 IN C0"BINATION OF C DESIGN ADLE FAILURES WHICH COULD IMPAIR OPER OF HPCI (DIV. I) 1 ADS (DIVISION I GENERAL ELECTRIC CO.
I) SYSTEMS.
THIS IS CCMMON TO BOTH UNITS.
TECH SPEC 6.9.1 CI.
UNITED ENG 8 CONSTRUCTORS PREPARING PL ANT MOD TO "SP ARE" '
LES 3 INSTAL L NEW CALLES IN ISOLATED CONDUIT TO PROVIDE SUFFICIENT IS.
ION.
REVIE W OF ECCS 3 THEIR PRIMARY CONTAINMENT ISOLATION VLVS EEING PERFORMED TO VERIFY THAT NO OTHER CALLE SEPARATICN PROC. EXISTED.
CAJLE SEPARATICN C RITERION FOR HPCI & ADS SYS WILL LE REDEFINED IN APPRCP CADLE SEP SPECS.
(D>
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1T NOV 08, 1979 LER MONTHLY REPORT SORTED BY FACILITY PAGE 17 PROCESSED DURING OCTOBER, 1979 FOR PCWER REACTORS IF'ACILITY/ SYSTEM /CCMPONENT/
DOCKET NO./
EVENT DATE/
COMPONENT SUBCODE/CAUSE CODE / LER NO./
REPGRT DATE/
EVENT DESCRIPTION /
-CAUSE SUSCODE/ MANUFACTURER CONTROL NO.
REPCRT TYPE CAUSE DESCRIPTION BRUNSWICK-2 05000324 080879 WHILE PERFORMING PT 8.2.4, RHRSW OPERATIONAL COMPONENT TEST, RHRSW PUMP CNTMMNT HEAT REMOV SYS + CCNT 79-071/03L-0 090679 2D HAD A VIBRATION OF 12.5 MILS.
THE MAXIMUM ALLOWAELE VALUE IS </: 3.6 PU"PS 026736 30-DAY MILS.
TECHNICAL SPECIFICATIONS 3.7.1.1, 6.9.1.9B.
CENTRIFUGAL COMPONENT FAILURE MECHANICAL INGERSOLL-RAND CO AN INVESTIGATION OF PUMP REVEALED A PART OF A SPRING LODGED IN VANE OF I MPELLER. THIS WAS REMOVED, PUMP WAS INSPECTED, TESTED, & RETURNED TO SER VICE. IT IS BELIEVED THAT THIS PARTIAL SPRING CAME FROM A Ch :CK VA!VE DI SK ASSEMBLY ON DISCHARGE OF NUCLEAR 1/OR CONVENTIONAL SERVICE WATER PUMP S.
BRUN5 WICK-2 05000324 081079 WHILE PERFORMING PT 1.1.13P, HIGH STEAMLINE RADIATION CHANNEL ALIGNMENT PRCSS + EFF RADIOL MONITOR SYS 79-069/03L-0 090779 AND FUNCTION TEST, MAIN STEAMLINE HI RAD MONITOR "D" WAS FOUND TO BE ACT INSTRUMENTATION + CONTROLS 026737 30-DAY UATING AT 3.66 X BACKGROUND WHILE THE ALLOWABLE LIMIT IS </: 3.S X BACKG COMPUTATION MODULE ROUND.
TECHNICAL SPECIFICATIONS 2.2.1, 6.9.1.9A.
OTHER HOT APPLICABLE GENERAL ELECTRIC CO.
DUT OF TOLERANCE READING WAS ATTRIBUTED TO ?ue'"C..uns DRIFT. MONITOR WAS RECALIBRATED & RETURNED TO SERVICE. GENERAL ELECTRIC IS BEING REQUESTED TO PROVIDE TECHNICAL ASSISTANCE IN DETERMINING THE CAUSE OF INSTRUMENT DRIFTING & DETERf1INING CORRECTIVE ACTION. A SUPPLEMENT REPORT WILL BE IS SUED WHEN REQUIRED CORRECTIVE ACTION HAS BEEN DETERMINED.
BRUNSWICK-2 0S000324 031279 DURING NORMAL PLANT OPERATION, VESSEL CONDUCTIVITY EXCEEDED 2,UMHOS FOR REAC COOL CLEANUP SYS + CONT 79-072/03L-0 091179 APPROXIMATELY 33 HOURS.
POWER WAS REDUCED TO LIMIT CONDUCTIVITY BUILD HEAT EXCHANGERS 026735 30-DAY UP.
TECHNICAL SPECIFICATIONS 3.4.4, 6.9.1.9B.
COOLER C0"PONENT FAILURE OTHER PERFEX, INC.
REASON FOR EXCEEDING 2,UMHOS WAS IHOPERABILITY OF RWCU SYSTEM. DUE TO L EAKS ON "B"
RUCU HEAT EXCHANGER, SYSTEM WOULD ISOLATE ON "HI ROOM TEMPER ATURE" OR "HI HI LEAK DIFFERENTIAL" GROUP ISOLATION. HEAT EXCHANGER WAS SEALED WITH FURMANITE & RETURNED TO SERVICE, AT WHICH TIME CONDUCTIVITY SLOWLY DECREASED TO 2,UMHOS. MOD WILL BE PERF ON ALL RWCU HEAT EXCHANGE BRUNSWICK-2 05000324 081379 WHILE ATTEMPTING TO PLACE "B" LOOP OF RHRSW UNDER CLEARANCE FOR MAINT, OTHER ENGNRD SAFETY FEATR SYS 79-073/03L-0 091179 2A" RHRSW PUMP BREAKER WAS RACKED OUT BY MISTAKE, MAKING BOTH LOOPS OF R CIRCUIT CLOSERS / INTERRUPTERS 026734 30-DAY HRSW INOPERABLE.
"2A" PUMP WAS OUT OF OPERATION FOR APPROX 15 MINS.
ER SWITCHGEAR ROR WAS DISCOVERED QUICKLY AFTER IT OCCURRED, AS A RESULT OF NORMAL CLEA PERSONNEL ERROR RANCE PROCESS WHEN AUX OPERATOR UHO HUNG TAG RETURNED TO CONTROL ROOM TO LICENSED 3 SENIOR OPERATORS SIGN TAG SHEET 3 OBSERVED THAT IT DID NOT REFLECT ACTUAL EQUIPMENT CLEA GENERAL ELECTRIC CD.
RED.
TECHNICAL SPECIFICATIONS 3.7.1.1, 6.9.1.9C.
"2" RHRSW PUMP WAS IMMEDIATELY RACKED IN. TAG 2 TAG-0UT SHEET HAD BEEN P REPARED INCORRECTLY BY CONTROL OPERATOR IN THAT "2" PUMP WAS DESIGNATED TO BE RACKED OUT VICE "2B" PUMP. THE FOLLOWING CORRECTIVE ACTION WERE OR WILL DE TAKEN: 1) AN IMMEDIATE MEETING 3 COUNSELING SESSION WAS HELD WI TH CONTROL OP INVOLVED, SHIFT FOREMAN, ACTING OP SUPV. & SUPERINTENDENT.
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NOV 08, 1979 LER MONTHLY REPORT SORTED BY FACILITY PAGE 13 PROCESSED DURING OCTOBER, 1979 FOR POWER REACTORS FACILITY / SYSTEM /CCMPONENT/
DOCKET NO./
EVENT DATE/
CGMPONENT SUBCODE/CAUSE CCDE/ LER NO./
REPCRT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL HO.
REPORT TYPE CAUSE DESCRIPTION BRUNSWICK-2 05000324 081579 WHILE PERFORMING PT 3.1.14PC, REACTOR LCW PRESSURE CHAHHEL CALIBRATION A EMERG CORE COOLING SYS + CONT 79-074/03L-0 091179 ND FUNCTION TEST, B21-PS-N021D WAS FOUND TO BE OPERATING IN AN OUT OF TO INSTRUMENTATION + CONTROLS 026733 30-DAY LERANCE CONDITION.
THE ALLOWABLE RANGE FOR THIS INSTRUMENT IS 435 + 15 COMPUTATION MODULE PSIG AND THE AS-F3UND CONDITION WAS 395 PSIG. TECHNICAL SPECIFICATION 3.
OTHER 3.3, 6.9.1.9D.
NOT APPLICABLE BARTON INSTRU CC., DIV 0F ITT THE INSTRUMENT WAS RECALIBRATED AND RETURNED TO SERVICE. THE INSTRUMENT WAS OUT OF CALIBRATION DUE TO INSTRUMENT CRIFT.
DUE TO THIS INSTRUMENT S PAST RELIABILITY AND PERFORMANCE AND BECAUSE IT IS CHECKED MONTHLY, TH IS IS CONSIDERED AN ISOLATED EVENT AND NO FURTHER ACTION IS REQUIRED.
BRUNSWICX-2 05000324 081879 DURING NCRMAL CPERAIUR SURVEILLANCE CF THE CONTROL PANELS, THE OPERATOR CNTHMNT CCM3US GAS CONTROL SYS 79-075/03L-0 091379 NOTICED A LOW FLOW INDICATED ON 2-CAC-1263.
THE ALARM WOULD NOT CLEAR A INSTRUMENTATION + CONTROLS 026771 30-DAY ND THE MONITOR COULD NOT BE STARTED.
TECHNICAL SPECIFICATION 3.6.6.4.
6 S EN S C R/ D ET EC T O R/ E L E:1EN T
.9.1.9B.
OTHER HOT APPLICABLE DWYER AN AUXILIARY OPERATOR WAS SENT TO THE -1263 PANEL TO DETERMINE THE PROBL EM & HONE WAS FOUND.
AHOTHER ATTEMPT WAS MADE TO CLEAR THE ALARM 8 STAR T THE UNIT AT THE END OF THE SHIFT.
THE UNIT STARTED HORMALLY, 4 RAN SA TISFACTORILY. NO CAUSE COULD BE FOUND FOR THE FLOW FAILURE; THEREFORE.
THE UNIT WILL BE CLOSELY MONITORED TO TRY 2 DETECT A DEVELOPING PROBLEM.
BRUNSWICK-2 05000324 083079 DURING NORTIAL PLANT OPERATION, PRIMARY COHTAINMENT AMBIENT TEMP EXCEEDED CNTHMNT HEAT REMOV SYS + CONT 79-080/03L-0 092579 135 DEG. F (135.176 DEG. F). TEMPS. OVER PREVIOUS SEVERAL DAYS HAD BEEN VALVES 026850 30-DAY 133-134 DEG. F WITH ALL AVAILALLE DRYWELL COOLERS OPERATING. DRYWELL LE CHECK AKAGE HAD INCREASED TO APPROX. 2 GPM & AIRECRNE PARTICULATE ACTIVITY WAS COMPONENT FAILURE HIGHER THAN NORMAL. INDICATING A SMALL STEAM LEAK. HEAT LOAD ON RSCCW S MECHANICAL YS WAS HI DUE TO HI SERVICE WATER INJECTION TEMP. RMCU REJECTING TO HOTW ANCHOR / DARLING INDUSTRIES ELL, 8 SUPPLYING 20 GPM CONCENTRATOR IN RADWASTE. T/S 3.6.1.6, 6.9.1.9B.
RWCU REJECT TO HOTWELL WAS DECREASED FROM 130 GPM TO 100 GPM & SERVICE W ATER FLOW TO RBCCW HEAT EXCHANGERS WAS INCREASED. THIS LOWERED RBCCW OUT LET TEMP FRCM 99 DEG. F TO 89 DEG. F & DRYWELL AMBIENT TEMP WAS LOWERED FROM 135.176 DEG. F TO 134 DEG.
F.
DURING RECENT GUTAGE. A LEAK IN KING PIN COVER ON FEEDWATER CHECK VALVE B21-F010B WAS REPAIRED.
BRUNSWICK-2 05000324 083179 WHILE REMOVING RWCV A " LEAK HI HI" ALARM WAS RECEIVED WHICH ISCLATES THE REAC COOL CLEANUP SYS + CONT 79-078/03L-0 092579 RWCV SYSTEM.
THE OPERATOR HOTICED THAT THE SUCTION OUTBOARD VALVE SHUT VALVE OPERATCRS 026849 30-DAY AS REQUIRED BUT THE SUCTION INBOARD VALVE F001 FAILED IN THE MID-POSITI ELECTRIC MOTOR - AC OH.
TECHNICAL SPECIFIACTION 3.6.3, 6.9.1.9B.
COMPONENT FAILURE MECHANICAL LIMITORQUE CORP.
AN INVESTIGATION REVEALED THAT THE TORQUE LIMIT SWITCH HAD OPENED, CAUSI NG THE MOTOR TO STOP.
THE VALVE WAS MANUALLY SHUT THEN CYCLED FOUR TIME S ELECTRICALLY AND THE PROBLEM COULD NOT BE MADE TO RECUR.
THIS IS CONS IDERED AN ISOLATED EVENT AND NO FURTHER ACTION IS REQUIRED.
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NOV 08, 1979 LER MONTHLY REPORT SORTED BY FACILITY PAGE 19 PROCESSED DURING OCTOBER, 1979 FOR PCUER REACTORS
' FACILITY /SYST EM/ COMPONENT /-
DOCKET NO./
EVENT DATE/
COMPONENT SUBCODE/CAUSE CODE / LER NO./
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION BRUNSWICK-2 05000324 083179 DURING HORMAL PLANT OPEATION. THE OPERATOR NOTICED THAT THE DRYWELL OXYG CNTNMNT COMBUS GAS CONTROL SYS 79-079/03L-0 092579 EN/ HYDROGEN MONITOR. CPC-1263, HAD A LOW FLOM CONDITICN AND WAS NOT INDI AIR DRYERS 026851 30-DAY CATING HORMALLY.
DRYWELL OXYGEN CONCENTRATION WAS MAINTAINED LESS THAN SUBCOMPONENT NOT APPLICABLE 4% BY THE CAC-1259 INSTRUMENT.
TECHNICAL SPECIFICATIONS 3.6.6.4, 6.9.1.
COMPONENT FAILURE 9B.
OTHER HANKISON CORP.
AN INVESTICATICH FUUND THAT AIR DRYER HAD FROZEN. BLOCKING SAMPLE AID FL s
OU.
DRYER WAS DEENERGIZED & ALLCWED TO THAU, 2 A DRY NITROGEN PURGE WAS USED TO BLOW OUT MOISTURE & DRY COILS. CRYER WAS INSPECTED BY A CCNTRAC T HEATING & AIR-CONDITIONING CO. 1 NO PROBLLM COULD BE FOUND WITH DRYER.
SYSTEM WAS RETURNED TO SERVICE 4 MONITORED FOR SEVERAL DAYS.
BRUNSWICK-2 05000324 090879 DURING A NORMAL REACTOR STARTUP, THE OPERATOR NOTICED THAT RCD 26-07 HAD SAFETY RELATED DISPLAY INSTR 79-076/03L-0 100179 NO POSITION INDICATION AT NOTCH 43.
ALL OTHER INDICATIONS WERE NORMAL.
INSTRUMENTATION + CONTROLS 026945 33-DAY TECHNICAL SPECIFICATION 3.1.3.7, 6.9.1.9B.
INDICATOR COMPONENT FAILURE ELECTRICAL GENERAL ELECTRIC CO.
ROD 26-07 OPERATIONALLY TESTED 8 NO PROBLEM FOUNJ WITH POSITION INDICATI NG PROBE.
ROD WAS NOTCHED IN TO NOTCH 46 8 BACK TO NOTCH 43 3 NORMAL IN DICATION RETURNED.
AN ENGINEERING WCRK REQUEST HAD BEEN WRITTEN TO INVE STIGATE THE POSITION INDICATING SYSTEM DUE TO THE NUMBER OF POSITI2N IND ICATING FAILURES WE HAVE BEEN EXPERIENCING.
BRUNSWICK-2 05000324 091079 WHILE PERFORMING PT 1.2.4.
APRM HIGH FtUX AND DCWNSCALE TEST, THE DOWNSC REArTIVITY CONTROL SYSTEMS 79-068/03L-0 100379 ALE ALARM FOR APRM "F" ACTUATED AT 2% VICE THE REGUIRED 3%.
APRM "B" WA INS 4RUMENTATION + CONTROLS 026953 30-DAY S ALSO 00T OF SERVICE DUE TO A DETECTOR CPEN SIGNAL LEAD.
TECHNICAL SPE COMPUTATION MODULE CIFICATION 3.3.1, 6.9.1.9A.
COMPONENT FAILURE ELECTRONIC GENERAL ELECTRIC CO.
APRM "F" UAS OUT OF CALIBRATICN DUE TO INSTRUMENT DRIFT.
THE INSTRUMENT WAS CALIBRATED AND RETURNED TO SERVICE SATISFACTORILY. APRM "D" WILL B E REPLACED DURING THE NEXT GUTAGE OF SUFFICIENT LENGTH.
AS THIS IS THE FIRST APRM CALIBRATION PROBLEM, THIS IS CONSIDERED AN ISOLATED EVENT AND NO FURTHER ACTION IS REQUIRED.
CALVERT CLIFFS-1 05000317 122178 OYSTER SAMPLES COLLECTED 12/5/78 FROM CAMP CANDY LOCATION AND ANALYZED P SYSTEM CODE NOT APPLICABLE 78-056/04T-0 010479 ER ETS 3.2, APPENDIX B, SHOWED AG-110M AT 81 +/- 11% PCI/KG.
BACKGROUND COMPONENT CODE NOT APPLICABLE 023644 2-WEEK LOCATION SHOWED AG-110M AT < 7 PCI/KG.
BASED CH OBSERVED L EVELS, AVERA SUBCOMPONENT NOT APPLICABLE GE INCIVIDUAL DOSES TO GI TRACT AND WHGLE BODY ARE VERY SMALL FRACTIONS OTHER OF ALLOWABLE DOSES TO MEMBERS OF GENERAL PUBLIC (40CFR PART 190) AND ARE NOT APPLICABLE OF NO CONSEQUENCE TO PUBLIC HEALTH AND SAFETY.
ITEM NOT APPLICABLE INTRODUCTION OF MORE SENSITIVE TECHNIQUE HAS REDUCED 1HE MDL VALUE FOR A G110M AT < 7 PCI/KG, LOWER THAN PREVIOUS AVERAGE MDL VALUE OF < 40 PCI/K G.
DECEMBER CAMP CAN0Y SAMPLES EXCEEDED NEW BACKGROUND VALUE BY > FACTO kJl R OF 10 WHILE SHOMING CONTINUED TREND OF DECREASING AG-110:1 ACTIVITY IN 45m OYSTERS.
NO CORRECTIVE ACTION IS REQUIRED.
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NOV'08, 1979 LER MONTHLY REPORT SORTED BY FACILITY PAGE 20 PROCESSED DURING OCTOBER, 1979 FOR PCWER REACTORS
' FACILITY / SYSTEM / COMPONENT /
DOCKET NO./
EVENT DATE/
COMPONENT SUBCODE/CAUSE CODE / LER NO./
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION CALVERT CLIFFS-1 05000317 022879 DURING NORMAL OPERATIlNS A WATCHSTANDER OBSERVED WHAT APPEARED TO BE ACI DEMIN WATER MAKE-UP 79-007/04T-0 0 31'e 7 9 D ON GROUND NEAR THE SULFURIC ACID STORAGE TANK.
ACID LINES IN THE AREA PIPES, FITTINGS 026799 2-WEEK WERE ISOLATED AND THE FLOW OF LIQUID ARRESTED.
CHEMICAL ANALYSEE WERE LESS THAN 4 INCHES PERFORMED ON SUSPECT MATERIAL WHICH WAS VERIFIED TO BE ACID.
LESS THAN COMPONENT FAILURE 5 GALLONS OF SULFURIC ACID WAS DISCH/RGED TO THE BAY VIA THE STCRM DR4IN CORROSION S.
NO ENVIRONMENTAL IMPACT IS EXPECTED DUE TO SMALL AMOUNT OF ACIO RELE OTHER ASED.
CAUSE HAS BEEN DETERMINED TO BE FAILURE OF A PIPE WELD.
IMMEDIATE CORRE CTIVE ACTION CONSISTED OF ISOLATING AND CONTAINING THE SPILL. SU3SECUEN T CORRECTIVE ACTION CONSISTED OF LOCATING AND SEALINr. THE LEAK BY WELDIN G.
CALVERT CLIFFS-1 05000317 032279 SECTION 4.6.2.C OF THE ENVIRONMENTAL TECHNICAL SPECIFICATIDHS REOUIRES A LIQ RADIDACT WSTE MANAGMNT SYS 79-012/04L-0 042079 REPORT WHEN THE SITE'S RADI0 ACTIVE LIQUID WASTE RELEASE RATE EXCEEDS 1 COMPONENT CODE NOT APPLICABLE 026800 30-DAY 25 CURIES PER QUARTER.
THIS VALUE WAS EXCEEDED ON MARCH 22, 1979.
LER' SUBCOMPCHENT NOT APPLICABLE 5 78-46, 78-50 DESCRIBE SIMILAR EVENTS.
OTHER HOT APPLICABLE ITEM NOT APPLICABLE ENVIRONMENTAL TECH. SPEO. CHANGE WAS SUBMITTED TO MODIFY SECTION S.6.2.C TO AGREE WITH SECTION 2.3.A.7.
CURING THIS PERIOD, MISCELLANEGUS WASTE ION EXCHANGER WAS RENDERED USELESS DUE TO A SALT WATER LEAK.
THE ION E XCHANGER WAS REPLACED AND WILL SIGNIFICANTLY HELP TO RFDUCE RELEASE RATE OF RADIDACTIVE LIQUID EFFLUENTS.
CALVERT CLIFFS-1 05000317 080679 AT 0845,#12 CHARGING PUMP PLACED OUT OF SERVICE BECAUSE OF PUMP TRIPS DU CHEM, VOL CONT + LIQ FOISN SYS 79-032/03L-0 083179 E TO LOW SUCTION FRESSURE & UNSUCCESSFUL ATTEMPTS TO RESTART PUMPS 8 MAI INSTRUMENTATION + CONTROLS 026718 30-DAY NTAIN IT IN OPERATION. PLACING PUMP OUT OF SERVICE REDUCED NUMBER CPERAB SENSOR / DETECTOR / ELEMENT LE CHARGING PUMPS TO 1 (#11 CHARGING PUMP WAS ISOLATED BECAUSE OF PACKIN COMPONENT FAILURE G LEAK). #11 CHARGING PUMP WAS REPAIRED 4 PLACED BACK IN SERVICE AT 1530 NATURAL END OF LIFE ON 8/6/79, BRINGING NUMSER OF OPERABLE PUMPS TO 2 AS REQ BY TS 3.'.2.4.
ASHCROFT GAUGE
- 13 CHARGING PUMP REMAINED OPE 7ABLE DURING EVENT. NOT REPETITIVE OCCUR.
- 12 CHARGING PUMP LOW SUCTION PRESSURE TRIPS WERE CAUSED BY A FAULTY PRE SSUPE INDICATING SWITCH:
1-PC-224Y.
THIS ASHCROFT MODEL 1379 TAXEF WAS REPAIRED BY REPLACEMENT OF GAUGE INTERNALS WHICH WERE WORN.
THIS IS BE ING CONSIDERED AS AN 'SOLATED FAILURE AND NO FURTHER CORRECTIVE ACTION I S TO BE TAKEN.
CALVE CLIFFS-1 05000317 081179 AT 0130 THE CONTR0i ROCM OPERATOR NOTICED THAT THE CONTAIbMENT AIR PARTI AIRB0kNE RADIDACT MONITOR SYS 79-035/03L-0 091079 CULATE MONITOR HAD FAILED.
THE MONITOR WAS DECLARED INOPERABLE PER T.S.
INSTRUMENTATION + CONTROLS d26783 30-DAY 3.4.6.1 THE CONTAINMENT PARTICULATE MCNITOR WAS RETURNED TO SERVICE A SEhSOR/ DETECT 3R/ ELEMENT T 1345.
THE CONTAINMENT GASEOUS MONITOR AND CCNTAIhMENT SUMP LEVEL ALAR COMPONENT FAILURE M REMAINED OPERABLE DURING THE EVENT.
LER 78-28 (U-2) DESCRIBES A SIMIL ELECTRONIC AR EVENT.
WESTINGHOUSE ELECTRIC CORP.
CAUSE OF THE LOW INDICATION WAS DUE TO THE DETECTOR TUBE GIVING LOW RESP DNSE (WESTINGHOUSE P/N 2372A80-H01).
TUBE FAILURE WAS PROBABLY CAUSED B Y DIRT ON ITS SOCKET ASSEM3LY, WHICH WAS CLEANED.
THE DETECTOR WAS REPL ACED.
NO PREVENTIVE ACTION IS NECESSARY. HEAVY WORK IN CONTAINMENT DUR ING REFUELING CAUSED SAMPLER TO DRAW IN UNUSUAL AMOUNT OF DUST AND DIRT.
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N5V 08, 1979 LER MONTHLY REPORT SORTED BY FACILITY PAGE 21 PROCESSED DURING OCTOBER, 1979 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
DOCKET NO./
EVENT DATE/
__' COMPONENT SUECODE/CAUSE CODE / LER NO./
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUSCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAU3E DESCRIPTION CALVERT CLIFFS-1 05000317 081279 AT 0105 WHILE PERFORMING A SURVEILLANCE TEST IT WAS DISCOVERED THAT WIDE REACTOR TRIP SYSTEMS 79-036/03L-0 091179 RANGE NUCLEAR INSTRUMENT (WRNI) CHANNEL D WOULD NOT INDICATE PROPERLY W OTHER COMPONENTS 026784 30-DAY HILE IN CALIBRATION.10DE.
WRNI CHANNEL D WAS DEULARED INOPERABLE PER T.
SUBCOMPONENT NOT APPLICABLE S.
3.3.1.1 ACTION 2.
WRNI CHANNEL D WAS RETURNED TO SERVICE AT Of20.
T COMPONENT FAILURE HE THREE REDUNDANT WRNI CHANNELS REMAINED GPERABLE DURING THE EVENT.
TH ELECTRICAL IS IS NOT A REPETITIVE OCCURRENCE.
ITEM NOT APPLICABLE DISCONNECTED " TEST" AND " POWER" CABLES ON DRAWER.
CHECKED CALIBRATION P ULSES.
SIGNALL WERE NORMAL.
RECONNECTED CABLES AND DRAWER FUCTIONED PR CPERLY.
APPARENT CAUSE WAS BAD CONNECTION. CABLE CONNECTORS WERE INSPE CTED, FOUND TO BE IN GOOD CONDITION. NO PREVENTIVE ACTION IS NECESSARY.
CALVERT CLIFFS-1 05000317 081379 AT 0030 WHILE PERFORMING ROUTINE SURVEILLANCE TESTING. IT WAS DISCOVERED REACTIVITY CONTROL SYSTEMS 79-034/03L-0 091379 THAT CONTROL ELEMENT ASSEMBLY DEVIATION OF GREATER THAN 7.5 INCHES WAS INSTRUMENTATION + CONTROLS 026865 30-DAY REQUIRED TO INITIATE CEA MOTION INHIBIT. CEA DRIVE SYSTEM WAS PLACED IN INDICATOR "0FF" AND ALL CEAS WERE FULLY WITHDRAWN AS REQUIRED BY T.S. 3.1.3.1 UNT COMPONENT FAILURE IL CORRECTIVE ACTION WAS COMPLETED. CMI WAS RESTORED ON 8-21-79. THIS I INSTRUMENT S NOT A REPETITIVE EVENT FOR UNIT 1.
SEE UNIT 2 LERS 79-13, 79-25, 79-3 METRA INSTRUMENTS 0.
REPLACED FAULTY CEA #4 OPERATIONAL AMPLIFIER, CEA GRP. 84 OUT OF SEQUENC E CIRCUIT A-25, 8 DEVIATION OUTPUT CIRCUITS FOR GRPS.
A, B,C, 3,
4.
AND 5.
EITHER OF THE FIRST TWO CIRCUITS, IN FAILING WITH HIGH CONDUCTION, I S 3ELIEVED TO HAVE AFFECTED THE FAILURE OF !dE OTHER STAGES. THE DEVIAT ION OUTPUT STAGES FAILED TO..ONDUCT SUFFICIENTLY TO INITIATE A CMI.
CALVERT CLIFFS-1 05000317 082879 AT 0600 DURING PERFORMANCE OF SURVEILLANCE TEST, 0"ERATOR DISCOVERED THA EMERG CORE COOLING SYS + CONT 79-037/01T-0 090679 T SI ' 14 5-MOV (12 HEADER CONT AINMENT SUMP SUCTION VALVE) WAS OPEN & SI-4 VALVES 026785 2-WEEK 143-MOV (12 HEADER RWT SUCTION VALVE) WAS SHUT, CAUSING ONE ECCS 8 ONE C GATE ONTAINMENT SPRAY SYSTEM TO BECOME INOPERABLE (T.S. 3.5.2 & 3.6.2.1).
UP PERSONNEL ERROR ON DISCOVERY, OPERATOR IMMEDIATELY REPOSITIONED VALVES TO THEIR PROPER P LICENSED & SENIOR OPERATORS OSITION.
REDUNDANT CONTAINMENT SPRAY 3 ECCS SYSTEMS REMAINED OPERABLE D VELAN VALVE CORP.
URING THE EVENT.
THIS IS NOT A REPETITIVE OCCURRENCE.
ON 3-27-79, CONTROL ROOM OPERATOR INADVERTENTLY SHUT SI-4143-MOV WHILE R ETURNING ECCS SYSTEM TO NORMAL FOLLOWING SURVEILLANCE TESTING OF SI-4145
-MOV & OPEN SI-4143-MOV.
FURTHER CORRECTIVE ACTION WILL BE TO INITIATE A COLOR SIGNALING SYSTEM TO AID OPERATORS IN VERIFYING PROPER POSITION O F ECCS VALVES AND PLACE POSITION ANNUNCIATORS ON RWT SUCTION VALVES.
CALVERT CLIFFS-1 05000317 082979 WHILE PERFORMING A ROUTINE SURVEILLANCE TEST, IT WAS DISCOVERED TNAT THE CNTHMNT COMBUS GAS CONTROL SYS 79-038/03L-0 092879 115 VOLT POWER SUPPLY TO HYDROGEN ANALYZER 0-AE-6527 WAS INOPERATIVE (T INSTRUMENTATION + CONTROLS 026960 30-DAY
.S.
3.6.5.1).
HYDROGEN ANALYZER 0-AE-6527 WAS REPAIRED AND RETURNED TO POWER SUPPLY SERVICE ON 8/31/79.
THE REDUNDANT HYDROGEN ANALYZER REMAINED IN OPERATI CCMPONENT FAILURE ON THROUGHOUT THIS EVENT.
THIS HAS NOT BEEN A REPETITIVE EVENT.
ELECTRICAL DELPHI INDUSTRIES TROUBLESHOOTING DISCLOSED THE DELPHI MODEL B1B POWER TRANSFORMER T-1 HAD A SHORTED SECONDARY WINDING.
THERE WAS NO OTHER FAILED COMPONENT WHICH MAY HAVE BEEN A PRIMARY CAUSE FOR TRANSFORMER FAILURE. THE OCCURRENCE
~~"
IS CONSIDERED TO BE AN END-OF-LIFE FAILURE; NO PREVENTIVE ACTION IS NECE (J7 SSARY.
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PROCESSED DURING OCTOBER, 1979 FOR POWER REACTORS FACILITY / SYSTEM /CCMPONENT/
DOCKET NO./
EVENT DATE/
-COM?ONENT SUCCCDE/CAUSE CODE / LER NO./
REPCRT DATE/
EVENT DESCRIPTION /
CAUSE SUSCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION CALVERT CLIFFS-1 05000317 083179 AT 0830 THE OPERATOR NOTICED THAT 1-CC-3830-CV (12 SHUTDOWN COOLING HEAT COOL SYS FOR REAC AUX + CONT 79-045/03L-0 092879 EXCHANGER OUTLET VALVE) WAS INDICATING INTERMEDIATE. SUBSEQUENT INVEST VALVE CPERATCRS 026965 30-DAY IGATION REVEALED THAT THE VALVE OPERATOR HAD BECOME DISCONNECTED FROM TH PNEUMATIC /DIAFHRAGM/ CYLINDER E VALVE STEM (T.S.
3.6.2.1).
THE VALVE WAS REPAIRED AND RETURNED TO SER CCMPCNENT FAILURE VICE AT 1445.
THIS IS NOT A REPETITIVE OCCURRENCE.
MECHANICAL MASONEILAN INTERNATIONAL, INC.
THE PIVOT LOCKING PLATE FAILED, DISCONNECTING THE ACTUATOR (MASONEILAN M ODEL 71-34312) FROM THE VALVE STEM.
FCR 79-60 WAS INITIATED ALLOWING FA BRICATION AND INSTALLATION OF NEW PLATE FROM STRONGER MATERIAL. THE ACT UATOR WAS REPAIRED AND RETURNED TO SERVICE.
CALVERT CLIFFS-2 05000318 080379 DURING A TURBINE ROLL WITH THE REACTOR AT 3% PWR CONTAINMENT PARTICULATE PRCSS + EFF RADIOL MONITCR SYS 79-029/03L-0 083179 AND GASECUS MONITOR WAS RENDERED INOPERABLE SY A BLOWN FUSE.
THE PLANT CIRCUIT CLOSERS / INTERRUPTERS 026713 30-DAY START-UP WAS STCPPED AND PCWER WAS REDUCED TO HCT STANDBY AT 0750 (MODE OTHER 3).
THE PARTICULATE AND GASECUS MONITCR SYSTEN WAS RETURNED TO SERVICE OTHER AT 0853 ON 8/3/79.
THE CONTAINMENT SUMP LEVEL ALARM REMAINED IN SERVIC NOT APPLICABLE E THROUGHOUT THIS EVENT (T.S.
3.4.6.1.).
THIS IS NOT A REPETITIVE OCCUR WESTINGHOUSE ELECTRIC CORP.
RENCE.
THE INITIAL CAUSE OF EVENT WAS A BLPWN HEUTRAL PHASE FUSE FOR THE AFFECT ED CASINET'S CONTROL POWER.
DURING REPLACEMENT, A FUSE BROKE IN THE HDL DER.
EFFORTS TO REMOVE A FUSE END CAP DAMAGED THE HOLDER SUCH THAT HGLD ER WAS SHORTED TO GROUND.
HOLDER WAS JUMPERED AND CCNTROL POWER RESTORE D.
A REPLACEMENT HOLDER IS ON ORDER.
CALVERT CLIFFS-2 05000318 090279 AT 0043 WHILE PERFORMING A SURVEILLANCE TEST, CONTROL ELEMENT ASSEMBLY (
REACTIVITY CONTEPL SYSTEMS 79-028/03L-0 091379 CEA) 43 SLIPPED TO 100 INCHES.
REACTCR POWER WAS REDUCED TO LESS THAN 7 CONTROL ROD DRIVE MECHANISMS 006852 30-DAY 0 PERCENT AT 0140 IN ACCORDANCE WITH T.S.
3.1.3.1 CEA 43 WAS WITHORAWN SUBCOMPONENT NOT APPLICABLE AND LEVELED WITH ITS GROUP AT 0143.
LER'S 78-48 (U-1) AND 79-24 (U-2)
CCM?CNENT FAILURE DESCRIBE SIMILAR EVENTS.
ELECTRICAL POWER-MATE THE SLIPPED CEA IS ASSUMED TO BE THE RESULT OF A VOLTAGE FLUCTUATION IN THE IS VOLT PCWER SUPPLY.
A DESIGN MODIFICATION TO IMPROVE THE RELIABIL ITY OF THE SYSTEM BY INSTALLING DUAL PCWER SUPPLIES (FCR 78-72) IS TO BE INSTALLED DURING THE NEXT REFUELING OUTAGE.
CALVERT CLIFFS-2 05000318 090379 WHILE OPERATING AT STEADY STATE POWER, SPURIOUS TRIPS ON RPS CHANNEL "C"
REACTOR TRIP SYSTEMS 79-031/03L-0 100179 HI POWER TRIP UNITS DCCURRED CN THE FOLLOWING DATES 9-3-79, 9-21-79 AND INSTRUMENTATION + CONTROLS 026961 30-DAY 9-22-79.
IN LACH CASE, CHANNEL "C" HIGH POWER, TM/LP AND AXIAL FLUX OF SWITCH FSETS WERE BYPASSED PER T.S.
3.3.1.1, ACTION 2.
ALL OTHER RPS TRIP UNIT CCMPCNENT FAILURE S REMAINED IN SERVICE THROUGHOUT THE EVENT.
LER 79-27 U-2 DESCRIBES A 5 INSTRUMENT IMILAR EVENT.
COMBUSTION ENGINEERING. INC.
REPLACED TEMPERATURE ELEMENT 2-TE-122 HC UNDER MAINTENANCE REQUEST 0 3'"4 ON 9/11/ 7 9.
THIS PLANNED MAINTENANCE WAS REPORTED UNDER LER 79-27.
THE CHANNEL AGAIN EXHIBITED SIMILAR SYMPTCMS OF A FAILING ELEMENT ON 9/
21/79 AND 9/22/79.
MR NO. 0-79-2911 IS BEING HELD FOR FURTHER WORK DURI NG THE HEXT COLD SHUTDCWN.
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EVENT DESCRI? TION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION CALVERT CLIFFS-2 05000318 091479 DURING INSPECTICH OF 12 AND 21 DIESEL GENERATOR PIPE HANGERS PER IE BULL EMERG GENERATOR SYS + CONTROLS 79-034/01T-0 092879 ETIN 79-14, DISCCVERED THAT iHE AIR START SYSTEM HANGERS WERE NOT LUILT HANGERS SUPPORTS, SHOCK SUPPRSS 026964 2-WEEK TO MEET SEISMIC REQUIREMENTS.
IN ORDER TO MEET T.S.
3.8.1.1 D/G'S WERE HANGERS STARTED WITHIN ONE HOUR AND RAN CONTINUOUSLY.
THIS ACTION ELIMINATED TH DESIGN /FABRICATIDH ERROR E RELIANCE ON THE AIR START SYSTEM FOR OPERABILITY. THIS IS NOT A REPET DESIGN ITIVE OCCURRENCE.
OTHER THE INSTALLATION OF SEISMIC PIPE SUPPORTS UPCRADED THE DIESEL STARTING A IR SYSTEM TO MEET SEISMIC REQUIREMENTS. THESE SUPPORTS HAD NOT BEEN PRE VIOUSLY INSTALLED DUE TO AN ERROR THAT CLASSIFIED THESE LINES AS NON-SEI SMIC.
DIESELS UERE ELECTRICALLY LOADED FOR ONE HOUR OF EVERY EIGHT HOUR S DURING THEIR CONTINUGUS RCH IO PRECLUDE EXCESSIVE CAR 3ON LUILD-UP.
C00PER-1 05000298 052578 AFTER REACTOR SCRAMMED ON APRM dI UPSCALE, BREAKER 1AS FAILED TO CLOSE A ONSI1E POWER SYSTEM + CONTROL 78-015/03X-1 080179 UTCMATICALLY.
THE BREAKER WAS THEN CLOSED SY ITS CONTROL SUITCH.
CREAK CIRCUIT CLOSERS / INTERRUPTERS 026291 GTHER ER 1AS TIES 4160V BUS 1A TO THE STARTUP TRANSFORMER WHEN THE GENERATOR T SWITCH (OTHER THAN SENSOR)
RIPS.
BREAKER 1FA FAILED TO TRIP AUTOMATICALLY AND WHEN ITS CONTRGL !WI DESIGN / FABRICATION ERROR TCH WAS OPERATED TO TRIP.
THIS BREAKER IS ONE OF TWO LREAKERS CONNECTED MANUFACTURING IN SERIES WHICH TIES 4160V BUS 1F TO BUS 1A.
REDUNDANT SYSTEMS MERE AV GENERAL ELECTRIC CO.
AILABLE.
BREAKER IFA FAILURE TO TRIP IS REPETITIVE (79-8).
BREAKER 1AS APPARENTLY FAILED TO CLOSE BECAUSE OF IMPROPER OPERATION OF SWITCH 52 IN BREAKER 1AN.
GE HAS BEEh REQUESTED TO EVALUATE.
SW!TCH CO NTACTS WERE CLEANED AND TESTED SATISFACTORILY. BREAKER 1FA FAILED TO TR IP BECAUSE MISALIGNMENT OF THE TRIP COIL AND.THE TRIP ARMATURE. LREAKER S ARE GE MAGNA BLAST TYPE AMH 4.76-250.
C00FER-1 05000298 021679 DURING NORMAL OPERATION, REACTOR RECIRCULATION MOTOR GENERATOR SET "A" T
ENGNRD SAFETY FEATR INSTR SYS 79-005/03X-1 080279 PIPPED DUE TO FAILURE OF LEVEL SWITCH NBI-LIS-58A.
TECHNICAL SPECIFICAT INSTRUMENTATION + CONTROLS 025608 OTHER ION 3.6.F.3 ALLOWS OPERATION OF UP TO 24 HOURS WITH ONE RECIRC. LOOP OUT SWITCH OF SERVICE.
THERE WAS NO SIGNIFICANT OCCURRENCE AS A RESULT OF THIS EV COMPONENT FAILURE ENT.
THERE WAS NO ADVERSE AFFECTS TO PUBLIC HEALTH AND SAFETY.
THIS EV INSTRUMENT ENT 'S REPETITIVE. (REFERENCE LER 76-48).
(UPDATE OF LER DATED 3-12-79 YARWAY CORP.
).
TRIP OF "A" RRMG SET WAS CAUSED BY LEVEL SWITCH NBI-LIS-58A.
CORROSIDH BUILDUP IN SWITCH CAUSED IT TO ACTUATE.
NDI-LIS-58A IS A YARWAY MODEL 3 318C LEVEL INDICATING SWITCH. ALL CORROSION WAS CLEANED FROM INSIDE SWI TCH CASE & SWITCH REPLACED. OTHER YARRAY INDICATORS OF THIS TYPE UERE I HSPECTED & ALL AREAS WHERE MOISTURE COULD ENTER CASE HAVE BEEN SEALED.
C00PER-1 05000298 070679 DURING ROUTINE TESTING, REACTOR VESSEL LEVEL INDICATING SWITCH NCI-LIS-5 MAIN STEAM ISOL SYS + CONTROLS 79-018/03L-0 080379 8A SWITCH NUMBER ONE WAS FOUND WITh A TRIP POINT LESS CONSERVATIVE THAN INSTRUMENTATION + CONTROLS 026693 30-DAY ALLOWED Ih T.S.
TABLE 3.2.A.
THERE WAS NO SIGNIFICANT OCCURRENCE AS A R SWITCH ESULT OF THIS EVENT.
THE REDUNDANT LEVEL SWITCH NBI-LIS-57A WAS OPERABL OTHER E.
THERE WERE NO ADVERSE AFFECTS TO FU3LIC HEALTH & SAFETY.
THIS EVENT NOT APPLICABLE IS REPETITIVE. REFERENCE LER 79-5, 77-12.
YARWAY CORP.
A YARWAY MODEL 4418C LEVEL INDICATING SWITCH FAILED TO ACTUATE WITHIN TO LERANCE.
INVESTIGATION DISCLOSED THAT SEDIMENT CCNSISTING OF DUST & MOI STURE IN AUXILIARY SWITCH MECHANISM HAD CAUSED SWITCH TO HANG-UP.
SWITC H WAS CLEANED & AFTER CLEANING TESTED SATISFACTORILY. A NEW MECHANICAL CAM ACTUATED SOLID STATE SWITCH MODULE IS UNDER EVALUATION.
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CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION C00PER-1 05000298 080979 WHILE PERFORMING SURVEILLANCE PROCEDURE (S.P. 6.2.2.2.5) ON THE RELIEF V OTHR INST SYS NOT REQD FR SFTY 79-020/03L-0 090579 ALVE BELLOWS MONITORING SYSTEM AS REQUIRED BY TECH. SPEC.
4.6.D.4, PRESS INSTRUMENTATION + COHTROLS 026895 30-DAY URE SWITCH MS-PS-71G FAILED TO ACTUATE.
THE PRESSURE SWITCHES ON ALL TH SENSOR / DETECTOR / ELEMENT E OTHER RELIEF VALVES WERE OPERABLE.
THERE WERE NO SIGNIFICANT OCCURREN DISIGN/ FABRICATION ERROR CES AS A RESULT OF THE EVENT.
SIMILAR EVENT WAS UE 75-1 THERE WERE NO MANUFACTURING ADVERSE AFFECTS TO PUBLIC HEALTH AND SAFETY.
ITEM NOT APPLICABLE A PRESSURE SWITCH, MODEL A 17-1, MANUFACTURED BY PRESSURE CONTROLS, INC.
FAILED TO ACTUATE.
PRESSURE SUITCH WAS REPLACED 3 SURVEILLANCE TESTING PERFORMED SATISFACTORILY. REMOVED PRESSURE SWITCH WAS RETURNED TO MANU FACTURER WHOSE ANALYSIS SHOWED THAT IT HAD BEEN IMPROPERLY ASSEMBLED. M ANUFACTURER STATED THIS WAS A UNICUE OCCURRENCE & NO FURTHER ACTION REQ.
C00PER-1 05000298 030979 WHILE PERFORMING ROUTINE SURVEILLANCE PROCEDURE 6.2.1.4.2, MS-DPIS-119B MAIN STEAM ISOL SYS CONTROLS 79-023/03L-0 090779 WAS FOUND WITH A SETPOINT IN EXCESS OF THAT ALLOWED IN TECHNICAL SPECIFI INSTRUMENTATION + CONTROLS 026899 30-DAY CATIONS TA3LE 3.2.A.
ALL REDUNDANT DIFFERENTIAL PRESSURE SWITCHES WERE SWITCH FUNCTIONING PROPERLY AND WERE WITHIN SPECIFICATION. THERE WERE NO SIGNI COMPONEHT FAILURE FICANT OCCURRENCES AS A RESULT OF THIS EVENT AND THERE WERE NO ADVERSE E MECHANICAL FFECTS TO PUBLIC HEALTH AND SAFETY.
THIS EVENT IS N0f REPETITIVE.
BARTON INSTRU CO., DIV 0F ITT MS-SPIS-119B IS A BARTON MODEL 288 DIFFERENTIAL PRESSURE INDICATING SW'T CH.
THE CAUSE OF THE SETPOINT DRIFT IS ATTRIBUTED TO A FAULTY MICROSWIf CH.
ASSEMBLY WAS REPLACED.
C00PER-1 05000298 080979 UPON RECEIPT OF AN AUTO START SIGNAL, THE HPCI (HIGH PRESSURE COOLANT IN EMERG CORE COOLING SYS + CONT 79-019/01T-0 082079 JECTIDH) PUMP DID HOT INITIALLY START.
HOWEVER, A SHORT TIME LATER THE VALVE OPERATORS 026930 2-WEEK PUMP STARTED AND WAS USED TO INCREASE REACTOR LEVEL.
THE RCIC SYSTEM WA HYDRAULIC S OPERABLE AND STARTED AS REQUIRED, AS WERE ALL LOW PRESSURE INJECTION S COMPONENT FAILURE YSTEMS.
THE EVENT IS NOT REPETITIVE.
NATURAL END OF LIFE MILLER FLUID POWER CO.
THE PISTON RINGS IN THE VALVE ACTUATOR FOR THE TURBINE STOP VALVE HAD DE TERIORATED AND WERE ALLOWING OIL TO FLOW AROUND THE PISTON.
THE RINGS U LRE REPLACED AND A SIMULATED AUTO ACTUATION TEST (S.P. 6.3.3.3) WAS PERF ORMED SATISFACTORILY. THE PREVENTIVE MAINTENANCE PROGRAM REVISED TO REP LACE RINGS AND CHECK FOR RING LEAKAGE.
C00PER-1 05000298 081179 THE PLANT WAS AT STEADY STATE OPERATION WHEN THE CCHTROL ROOM RECEIVED A FIRE PROTECTIDH SYS + CONT 79-021/03L-0 09f779 N ACTUATION ALARM FOR THE DELUGE SYSTEM ON THE STANDBY GAS TREATMENT SYS INSTRUMENTATION + CONTROLS 026926 30-DAY TEM "B" CARBON ADSORBER. THF CARBON ADSORBER IN STANDBY GAS TREATMENT S SENSOR / DETECTOR / ELEMENT YSTEM "B" WAS WETTED WITH WATER AND RENDERED INOPERACLE PER RTS 3.7.B.3.
DESIGN /FABRICATICH ERROR THERE WERE NO ADVERSE EFFECTS ON PUBLIC HEALTH AND SAFETY.
REDUNDANT S CONSTRUCTION / INSTALLATION YSTEM WAS AVAILABLE.
AUTO SPRINKLER CORP CAUSE OF THIS EVENT IS ATTRIEUTED TO IMPROPER INSTALLATION OF BASEPLATE OF FIRE DETECTION UNIT (PYROTRONICS MODEL DGS-3). INTERMITTENT ACTUATION OF FIRE PROTECTION SYS WAS CAUSED BY LEAD WIRE BEING " PINCHED" BETWEEN (ja BASEPLATE 4 A METAL FITTING ATTACHING A PIECE OF FLEXILLE CONDUIT. CAEB0 N ACSORBER WAS DRIED & NEW BASEPLATE INSTALLED ENSURING WIRE NOT PINCHED 4,
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CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION C00PER-1 05000298 081279 DURING NORMAL OPERATIONS, WATER WAS OBSERVED CCMING FROM THE CAREON ADSO FIRE PROTECTION SYS + CONT 79-022/03L-0 090779 RBER HOUSING OF STANDBY GAS TREATMENT SYSTEM "A".
THE DELUGE SYSTEM HAD VALVES 026898 30-DAY NOT BEEN INITIATED AND THE VALVE WAS FOUND CLCSED.
THE CARBCN ADSORSER CHECK TRAYS WERE SPRAYED WITH WATER AND RENDERED INOPERABLE PER RTS 3.7.B.3.
COMPONENT FAILURE THERE WERE NO ADVERSE EFFECTS ON PUBLIC HEALTH AND SAFETY.
REDUNDANT SY MECHANICAL STEM WAS AVAILABLE. THE EVENT IS REPETITIVE, SEE LER 79-21.
AUTO SPRINKLER CORP THE CAUSE OF THIS EVENT IS ATTRIBUTED TO INADEQUATE SEATING AREA BETWEEN VALVE CLAPPER AND LATCH, SYSTEM 22 AUTOMATIC SPRINKLER CORP. OF AMERICA N DELUGE VALVE.
THE CLAPPER WAS REPLACED AMD ADJUSTED TO PROVIDE CUFFIC IENT SEATING AREA.
THE CARDON ADSORDER WAS DRIED OUT AND THE SYSTEM RET URNED TO NORMAL.
CRYSTAL RIVER-3 05000302 012379 CONTRARY TO ETS 3.1.5 WATER SAMPLES WERE NOT OBTAINED FOR JANUARY F P 21 T SYSTEM CODE NOT APPLICABLE 79-013/04L-0 022779 EST WELLS 1,
32 4.
THE DISCHARGE CANAL DIRECTLY NORTH OF THE PON05. &
COMPONENT CODE NOT APPLICABLE J26795 30-DAY THE CHEMICAL-INDUSTRIAL WASTE WATER PONDS WITHIN 1 MONTH (+25%) 0F T ri E 1 SUBCOMPONENT NOT APPLICABLE 2/13/79 SAMPLES.
PERSONNEL ERROR OTHER ITEM NOT APPLICABLE NEW LAB DIRECTOR WAS NOT PROPERLY INFORMED OF PROCEDURE. NEW DIRECTOR W AS INFORMED OF PROPER TIME RESTRAINT AND WILL BE FULLY RESPONSIBLE FOR T HE PROCEDURE.
CRYSTAL RIVER-3 05000302 031579 A DIFFERENCE OF >2 STANDARD DEVIATIONS EXISTED BETUEEN PREOP.
STUDY AND SYSTEM CODE NOT APPLICABLE 79-021/04L-0 040379 CPERATIONAL STUDY IN METAB0LIC FUNCTIONS FOR 2 AQUATIC ECOSYSTEMS IN DI COMPONENT CODE NOT APPLICABLE 026794 30-DAY SCHARGE SALT MARSHES:
(1) SPARTI'4A, DEAD BIOMASS-SUMMER QTR. AND (2) JU SUBCOMPONENT NOT APPLICABLE NCUS, LIVE BIOMASS-WINTER, SPRING. SUMMER, FALL QTRS; DEAD BIOMASS SUMME OTHER R,
FALL QTRS: GROSS PRODUCTIVITY-SUMMER QTR. ECOSYSTEMS ARE STILL REORGA NOT APPLICABLE NIZING TO OPERATIONAL CONDITIDHS.
ITEM NOT APPLICABLE NATURAL OR SEASONAL CHANGES AND/OR INCREASED THERMAL CUTPUT FROM FLANT S ITE COULD HAVE CAUSED CHANGE.
OPERATIONAL STUDY WILL BE CONTINUED AND H OPEFULLY WILL CLARIFY CAUSE OF THIS EVENT.
CRYSTAL RIVER-3 05000302 033079 CONTRARY TO ETS 3.1.4.D.
FIRST QUARTER 1979 SAMPLES OF NUMBERS OF ORGANI SYSTEM CODE NOT APPLICABLE 79-027/04X-0 040679 SMS WITH A REEF QUADRATE WERE NOT COLLECTED ON THE MARCH 1979 FIELD TRIP COMPONENT CODE NOT APPLICABLE 026872 OTHER SUBCOMPONENT NOT APPLICABLE EXTERNAL CAUSE NOT APPLICABLE ITEM NOT APPLICABLE UNUSUALLY HIGH TIDES AND SEVERE WEATHER CONDITIONS RESULTED IN THESE REE FS NOT BEING EXPOSED DURING FIELD OPERATION. BECAUSE ALL OYSTER REEF CA TA ARE BASED ON SAMPLES TAKEN ON EXPOSED REEFS, DECIDED NOT TO CHANGE ME (J7 THODOLOGY. LESSER NUMBER WILL BE USED AND 50 INDICATED IN THE ANNUAL RE g
PORT.
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CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION CRYSTAL-RIVER-3 0S000302 042679 A DIFFERENCE OF MORE THAN 2 STANDARD DEVIATIONS EXISTED BETWEEN PRECPERA SYSTEM CODE NOT APPLICABLE 79-039/04L-0 050179 TIONAL AND OPERATICHAL STUDIES IN lHE METABOLIC FUNCTICNS OF THE ACUATIC COMPONENT CODE NOT APPLICABLE 026796 30-DAY SYSTEM IDEhTIFIED AS DISCHARGE S LT MARSHES (JUNCUS) FOR 20TH LIVE DICM SUBCOMPONENT NOT APPLICABLE ASS AND DEAD BIOMASS DURING UINTER QTR. REPETITIVE. ECOSYSTEM STILL ADA OTHER PTING TO NEW CPERATIONAL CONDITIONS.
NOT APPLICABLE ITEM NOT APPLICABLE CAUSE COULD BE NATURAL GR SEASONAL VARIATIONS IN CCNJUNCsION UITH SITE T HERMAL DISCHARGE. PERIOD OF ADJUSTMENT BY ECOSYSTEM UAS EXPECTED CCNCUR RENT WITH UNIT 3'S INITIAL OPERATICN.
PRESENT ENVIRCNMENTAL MONITORING PROGRAM WILL CONTINUE. CHANGES IN UNIT OPERATION NOT REOUIRED AT THIS T If1E.
CRYSTAL RIVER-3 0S000302 051179 ENVIRONMENTAL SAMPLES WERE NOT ANALYZED USING PROCEDURES WHICH PROVIDED SYSTEM CODE NOT APPLICABLE 79-016/04L-0 051579 LLD'S EQUAL TO GR GREATER THAN ETS REQUIREMENTS.
LLD'S WERE GREATER THA COMPONENT CODE NOT APPLI0ABLE 026793 30-DAY N REQUIRED FOR 1 SEtWATER SAMPLE IN JANUARY, 2 CRAB SAMPLES IN IST HALF, SUBCOMPONENT NOT APPLICABLE AND 1 HERBIVCROUS FISH SAMPLE IN IST HALF YEAR.
ACTIVITY ASSCCIATED UI DTHER TH ZN-6S WAS NON-DETECTABLE FOR THE IST HALF OF THE YEAR FOR THESE SAMPL NOT APPI.ICABLE ES.
ITEM NOT /PPLICABLE INADEQUATE SAMPLE TIME.
ANALYSES ARE PERFORMED TO ACHIEVE LLD'S UNDED R OUTINE CONDITIONS. BACKGROUND FLUX, UNAVOIDABLE SMALL SAMPLE SIZE, PRES ENCE OF INTERFERIhG NUC IDES OR OTHER UNCONTROLLABLE FACTORS MAY RENDER LLD'S UNACHIEVABLE. NO CORRECTIVE ACTION PROPOSED.
D. C. C00K-1 0S00031S 020179 ON FEBRUARY 1 IT WAS DISCOVERED THAT AFTER SWITCHING APCMS DETECTCRS GN ENGNRD SAFETY FEATR INSTR SYS 79-043/03L-0 091379 JANUARY 22, THE APCMS DETECTCR F(Z) ALARM SETPOINT WAS SET AT THE T S.
INSTRUMENTATION + CONTROLS 026820 30-DAY VALUE.
UPON DISCOVERY THE ALARM SETPOINT VALUE WAS RESET TO THE PRCPER SWITCH VALUE.
THIS IS NCN-CCHSERVATIVE IN RESPECT TO A PREVICUS COMMITMENT STA PERSONNEL ERROR TED IN R0-316/78-68 AND R0-31S/75-SS.
THIS EVENT IS NCN-CONSERVATIVE IN OTHER RESPECT TO T.S.
3.3.3.6.B.
WESTINGHOUSE ELECTRIC CORP.
THIS CCNDITION EXISTED FROM JANUARY 22, WHEN AN APCMS DETECTOR WAS SWIIC HED AND THE T.S.
VALUE WAS USED FCR THE POWER LEVEL F'Z) ALARM SETPOINT.
THE TRACES CURING THIS OCCURRENCE HAVE BEEN REVIEUED AND THERE WAS SUFF ICIENT MARGIN SO THAT THERE WOULD HAVE BEEN NO F(Z) VIOLATIGNS. SETPOIN TS NCW POSTED AT APCMS.
D. C. C00K-1 0S00031S 081479 CURING NORMAL OPERATION, A GROUND WAS DISCOVERED ON THE BORON INJECTION EMERG CORE COOLING SYS + CONT 79-041/03L-C 091279 TANK TRAIN B HEATERS.
THE met.TER T7AIN WAS REMOVED FRCM SERVICE AND THE HEATERS. ELECTRIC 026769 30-DAY REQUIRED ACTION ITEMS OF TECH. SPEC. 3.5.4.2 WERE FOLLCWED. No rREVICU SUBCOMPONENT NOT APPLICABLE S EVENTS OF THIS NATURE.
PUBLIC HEALTH AND SAFETY WERE HOT JECPARCIZED.
COMPONENT FAILURE ELECTRICAL CHROMALOX ONE CHRCMALOX TH-13 HEATER WAS REPLACED AND THE TRAIN B HEATER WAS VERIF IED TO BE OPERABLE.
BOTH HEATER TRAINS ARE NCW CLEAR OF GRCUNDS.
THE C AUSE OF THE HEATER FAILURE HAS BEEN ATTRIBUTED TO NATURAL END OF LIFE.
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REPORT TYPE CAUSE DESCRIPTION D.
C. C00K-1 05000315 081479 ON AUGUST 14 WHILE ISOLATING A PRESSURIZER LEVEL TRANSMITTER (NLP-152)
REACTOR TRIP SYSTEMS 79-042/03L-0 091379 THE ASSOCIATED PRESSURIZER PRESSURE TRANSMITTER (NPP-152) WAS ISOLATED.
INSTRUMENTATION + CONTROLS 026818 30-DAY WHEN NPP-152 WAS VALVED BACK IH, INDICATION DIFFERED FROM THE OTHER PRE TRANSMITTER SSURIZER PRESSURE CHANNELS.
NPP-152 OUTPUT WAS ADJUSTED FOR PROPER CUTP PERSUNNEL ERROR UT.
ON AUGUST 22. IT WAS DISCOVERED THAT THERE WAS A 30 PSI DIFFERENCE MAINTENANCE & REPAIR PERSONNEL BETWEEN THE PRESSURIZER PRESSURE INDICATION AND A HEISE GAUGE.
GAUGES W BARTCN INSTRU CO.,
DIV 0F ITT ERE RE-CALIBRATED.
THESE PRESSURIZER PRESSURE TRANSMITTERS WERE INSTALLED DURING THE LAST R EFUELING OUTAGE EECAUSE THEY ARE ENVIRONMENTALLY QUALIFIED FOR USE UNDER POST ACCIDENT CONDITIONS. AS OF THIS TIME, IT IS NOT KNOWN WHAT CAUSED ALL OF THESE TRANSMITTERS TO DRIFT.
HCWEVER, THE INVESTIGATION IS STIL L OPEN.
SURVEILLANCE IS PERIODIC.
D. C. C00K-1 05000315 083179 DURING A ROUTINE TOUR ON 8-31-79, ONE ICE CONDENSER INTERMEDIATE DECK DO REACTOR CONTAINMENT SYSTEMS 79-045/03L-0 100179 OR WAS FOUND TO BE FROZEN SHUT CONTRARY TO THE REQUIREMENTS OF T.S.
3.6.
HEAT EXCHANGERS 026967 30-DAY 5.3.
A SIMILAR SITUATION WAS DISCOVERED 9-17-79 WHEN SIX DCORS WERE FCU CONDENSER ND FROZEN.
IN BOTH CASES, THE ICE WAS CHIPPED AUAY AND THE DOORS WERE F EXTERNAL CAUSE REED.
THIS EVENT DID NOT AFFECT PUBLIC HEALTH AND SAFETY.
A SIMILAR OC NOT APPLICABLE CURRENCE WAS REPORTED AS 379-036/03L-0.
WESTINGHOUSE ELECTRIC CORP.
THE ICE BUILDUPS APPEAR TO HAVE BEEN CAUSED BY CONDENSATION. PRIOR TO E ACH OCCURRENCE, THE ICE BED TEMPERATURE WAS DECREASING RESULTING IN INCR EASED INFLUX OF HUMID AIR.
THIS WITH THE HIGHER HUMIDITY IN THE SUMMER MONTHS RESULTED IN THE CONDENSATION WHICH FROZE STICKING THE DOORS SHUT.
DAILY INSPECTIONS HAVE NOT INDICATED ANY FURTHER PROBLEMS.
D.
C.
C00K-1 05000315 090579 WHILE CONDUCTING A FULL LENGTH CONTROL ROD CPERABILITY TEST, AN URGENT F REACTIVITY CONTROL SYSTEMS 79-046/03L-0 100579 AILURE ALARM FROM POWER CABINET 2 AC WAS RECEIVED ON ROD CCNTRCL.
ONLY CONTROL RODS 026999 30-DAY SHUTDOWN DANK-A WOULD MOVE.
THE OTHER CONTROL BANKS COULD NOT BE MOVED SUBCOMPONENT NOT APPLICABLE EVEN IN MANUAL CONTROL.
THIS EVENT IS NON-CONSERVATIVE IN RESPECT TO T.
OTHER S.
3.1.3.1.
THE REQUIREMENTS OF ACTION ITEM B UERE MET AS THE CONTROL R NOT APPLICABLE ODS WERE RETURNED TO OPERATION IN LESS THAN 6 HOURS.
ITEM NOT APPLICABLE INVESTIGATION FAILED TO REVEAL ANY EQUIPMENT FAILURE OR MALFUNCTION. TH E POWER SUPPLY WAS RESET AND THE FULL LENGTH CONTROL ROD OPERABILITY TES T WAS SATISFACTORILY CCMPLETED. NO OTHER PROBLEMS HAVE BEEN ENCOUNTERED SINCE THIS EVENT.
NO FURTHER ACTIDHS ARE PLANNED AT THIS TIME.
D.
C.
C00K-2 05000316 071579 ON JULY 15. IT WAS DISCOVERED THAT AFTER COMPLETING REPAIRS TO THE APDMS ENGNRD SAFETY FEATR INSTR SYS 79-029/03L-0 091379 ON JULY 13, AN APDMS DETECTCR F(Z) LIMT' SETPOINT WAS SET AT THE T.S.
V INSTRUMENTATION + CONTROLS 026819 30-DAY ALUE.
THIS WAS RESET TO THE PROPER VALL.
THIS IS NON-CONSERVATIVE IN SWITCH RESPECT TO A PREVIOUS COMMITMENT STATED IN R0-316/78-63.
THIS EVENT IS PERSONNEL ERROR NON-CONSERVATIVE IN RESPECT TO T.S.
3.3.3.7.B.
MAINTENANCE 3 REPAIR FERSONNEL
_ JSTINGHOUSE ELECTRIC CORP.
W THIS CONDITION EXISTED SINCE JULY 13. WHEN REPAIRS WERE COMPLETED TO THE (J7 APDMS.
THE REPAIR TECHNICIAM UAS GIVEN THE CORRECT SETPCINT VALUES.
H OWEVER, AS A SHIFT CHANGE OCCURRED. THE NEW INDIVIDUAL DID NOT RECEIVE T 4:3 HESE VALUES.
THE TRACES DURING THIS EVENT HAVE LEEN REVIEUED AND THERE l#
WERE NO VIOLATIONS. SETPOINTS NOW POSTED AT APDMS.
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CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION e
D. C. C00K-2 05000316 081079 WHILE PERc0RMING THE DAILY SURVEILLANCE TESTS, IT WAS DISCOVERED THAT ON 0THR INST SYS REQD FOR SAFETY 79-028/03L-0 082979 E OF THE THREE SPECIFIED LOWER CONTAINMENT TEMP READINGS HAD NOT BEEN RE
'CCMPONENT CODE NOT APPLICABLE 026714 30-DAY CORDED ON DATA SHEETS DUE TO FAILURE OF THAT TEMP MEASURING POINT.
THE
~~'SUBCOMPONENT NOT APPLICABLE THREE POINTS ON THE DATA SHEET ARE CHOSEN FRO *1 A TOTAL OF 8 POINTS WHICH DEFECTIVE PROCEDURES MEET LOCATION REQUIREMENTS IN T.S.
4.6.1.5.1.
THE REMAINING 7 POINTS W NOT APPLICABLE ERE ALL OPERABLE 4 WERE RECORDING READINGS BELOW THE ALLCWADLE AVERAGE T ITEM NOT APPLICABLE EMPERATURE.
TME REQUIREMENTS OF T.S. 4.6.1.5.3 WERE NOT MET.
THE ERROR WAS CAUSED BY THE FACT THAT THE DATA SHEET DID NOT SPECIFICALL Y INDICATE THAT THREE READINGS WERE REGUIRED, AND ALSO THAT IT DID NOT I NDICATE THAT OTHER MEASURING POINTS COULD CE SUBSTITUTED FOR THESE POINT S.
THE DATA SHEET HAS BEEN CORRECTED TO PREVENT A REOCCURRENCE.
DAVIS-BESSE-1 05000346 010279 REVIEW OF PREVIOUS RADIATION MONITOR FAILURES DETERMINED THAT STATICN VE PRCSS + EFF RADIOL MONITOR SYS 79-001/04L-0 013079 HTILATION RADIATION MONITORS RE2024 AND RE2025 WERE BOTH IMOPERAELE ON 8 INSTRUMENTATION + CONTROLS 026807 30-DAY
/29/77 8 12/14/77. VIOLATING ETS 2.4-3.
G7AB SAMPLES WERE WITHIN LIMITS SENSOR / DETECTOR / ELEMENT DURING EACH PERIOD.
CONDENSER air EJECTOR MONITORS RE 1003A AND B WERE CCMPONENT FAILURE NOT OPERABLE DURING THIS TIME AS REQUIRED DY ETS.
INSTRUMENT ITEM NOT APPLICABLE COMPONENT FAILURE. ALERT SETPOINT DN RE 2025 WAS RESET AhD SETPOINTS ON BOTH MONITORS WERE RECALIBRATED. PERSONNEL REINSTRUCTED CN REPORTABILI TY OF MONITOR FAILURES.
ETS CURRENTLY UNDER REVISION. MCDIFICATIONS TO SURVEILLANCE TESTS ST 5032.01 4 ST 5032.02 MADE TO CLARIFY REPCRTIdG RE QUIREMENTS.
DAVIS-BESSE-1 05000346 010479 MCHTHLY FUNCTIONAL TEST OF RADIATION MONITORING SYSTEM DETERMINED THAT R LIQ RADIDACT WSTE MANAGMNT SYS 79-002/04L-0 020179 EC432, SERVICE WATER SYS. HEADER OUTFLCU RADIATION M3NITOR HAD LCW FLOW COMPONENT CODE NOT APPLICABLE 026808 30-DAY LIGHT AND WAS INCPERALLE (ETS 2.4-3).
NO DANGER TO PU3LIC HEALTH 8 SAFE SUBCOMPONENT NOT APPLICABLE TY.
RE1412 AND RE1413 IN COMPONENT CCCLING LINES 1 &
2.
RESPECTIVELY, A DESIGN / FABRICATION ERROR RE UPSTREAM FROM RE8432 AND WOULD HAVE INDICATED ACTIVITY IF PRESENT.
N DESIGN EITHER RE1412, RE1413, NOR WEEKLY GRAB SAMPLES INDICA 12D ANY LEAKS.
ITEM NOT APPLICABLE COMPONENT DEFICIENCIES DUE TO DESIGN ERROR.
NOT ENOUGH PRESSURE DIFFERE NTIAL TO MAINTAIN CCRRECT SAM?LE FLOW IN ALL OPERATION MODES OF SERVICE WATER SYSTEM.
FLCU SWITCH STICKS WITHOUT ENOUGH FLCM.
FLCU SWITCH WAS REPLACED WITHOUT SUCCESS.
FACILITY CHANGE REOUEST INITIATED TO CCRRECT FLOW PROBLEM.
DAVIS-BESSE-1 05000346 012679 ON 01/22/79 STATION VENT MONITOR RE 2024 WAS DECLARED INOPERAELE. CN 2/
GAS RADI0ACT WSTE MANAGMNT SYS 79-004/04L-0 022179 26/79. THE PUMP FOR MONITOR RE 2025 SEIZED AND WAS DECLARED INCPERA3LE, PUMPS 026809 30-DAY VIOLATING ETS 2.4.4 WHICH REQUIRES A MINIMUM OF 1 OPERABLE MONITOR FCR T VANE TYPE HE STATION VENT. NO GASEGUS RELEASES WERE MADE WHILE BOTH MCNITCRS WERE COMPONENT FAILURE OUT.
RE 2024 WAS RETURNED TO SERVICE LATER ON 2/26/79.
NO DANGER TO PU HATURAL END OF LIFE BLIC HEALTH AND SAFETY.
ITEM NOT APPLICADLE RE 2024 FAILED DUE TO NORMAL VANE WEAR.
RE 2025 FAILURE PROBABLY DUE TO EXCESSIVELY LOM FLCW CONDITIONS DURING TESTING. PUMPS WERE REPLACED IN BOTH MONITORS AND OPERATIONALLY TESTED. PREVENTIVE MAINTENANCE PROGRAM MODIFIED.
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- CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION DUANE ARNOLD 05000331 061778 DURING WEEKLY CONTROL VALVE TESTING AN AUTOMATIC REACTOR SCRAM CCCURRED.
REACTOR TRIP SYSTEMS 78-031/01X-1 092079 PLANT TRIPPED WHEN 7 REACTOR PROTECTION SYSTEM RELAY AUXILIARY SWITCHES RELAYS 021862 OTHER FAILED IN THE CLOSED POSITICN LEADING TO ACTUATICN OF THE EACK-UP SCRAM CONTROL, GENERAL PURPOSE VALVE SOLENOIDS.
THE PLANT REMAINED SNUTDOWN FOR REPAIRS. OPERATION O DESIGN / FABRICATION ERROR F THE REACTOR PROTECTION SYSTEM MAIN RELAYS WAS NOT AFFECTED LY THE AUXI CONSTRUCTION / INSTALLATION LIARY SWITCH MALFUNCTIONS.
GENERAL ELECTRIC CO.
THE CAUSE OF THE SWITCH PROBLEMS WAS TRACED TO THE SCREW WHICH RETAINS T HE OPERATING ARM OF THE AUXILIARY SWITCH EECOMING LOOSE AND BACKING OUT.
THIS CAUSED MISOPERATION AND IN ONE CASE ALLOWED THE ARM TO FALL OFF.
THE RETAINING SCREWS AND OPERATING ARMS WERE REINSTALLED AND PRCPERLY TI GHTENED.
SWITCH VENDOR RECOMMENDED NO FURTHER CCR. ACTION BE TAKEN.
DUANE ARNOLD 05000331 012879 WHILE OPERATING RECIRCULATICH SYSTEM IN PREPARATION FOR A HYDROSTATIC T COOLANT RECIRC SYS + CONTROLS 79-001/03X-1 092079 EST. NO FLOW INDICATION WAS NOTED FOR NUMBER 3 & 4 JET PUMPS. FLCW INSTR PIPES, FITTINGS 025714 OTHER UMENTATION WAS IMMEDIATELY TESTED C FOUND OPERABLE. ADDITIONAL TESTING 6 TO 10 INCHES WAS THEN PERFORMED WHICH CONFIRMED BLOCKAGE EXISTED IN EITHER N2B RISER PERSONNEL ERROR OR IN ASSOCIATED JET PUMPS NUMBERS 31 4.
PLANNING WAS BEGUN FOR INVESTI CONTRACT. & CONSULT. PERSONNEL GATING NATURE AND POSITION OF BLOCVAGE AND FOR ITS REMOVAL.
A REVIEW OF CHICAGO BRIDGE & IRON COMPANY REPAIR PROCEDURES WAS BEGUN.
(SEE LER 78-030).
INVESIIGATION REVEALED CONSULTANT PERSONNEL MANAGING REPL ACEMENT OF ALL RECIRC SYSTEM INLET N0ZZLE SAFE-ENDS HAD NOT FOLLOWED PROCEDURES PROPERL Y AND HAD APPARENTLY NOT ENSURED A LEAD SHIELD PLUG 2 CANNISTER WAS REMD VED FROM N2B N0ZZLE. CONTRIBUTING CAUSE LACK OF OUALITY VERIFICATION THA T PIPE WAS CLEAR PRIOR TO CLOSURE. LEAD PLUG WAS REMOVED.
DUANE ARNOLD 05000331 030679 DURING A DESIGN REVIEW OF CONTAINMENT PURGING EQUIPMENT 1 CONTROLS IT WA CNTNMNT COMBUS GAS CONTROL SYS 79-002/0fX-1 092079 5 DEIERMINED THAT CONTAIMMENT PURGE VALVES CV4300, 4301, 4302, 4303, 430 VALVES 025713 OTHER 6,
4307 AND 4308 WERE NOT DESIGNED TO CLOSE FROM FULL OPEN POSITION AGAI BUTTERFLY NST DIFFERENTIAL PRESSURE RESULTING FROM A DESIGN BASIS LOCA. VALVE VEND DESIGN / FABRICATION ERROR 01 INDICATED VALVES WOULD CLCSE AGAINST LOCA FCRCES IF LIMITED TO CPENIN DESIGN G NO MORE THAN 30 DEGREES. VALVES WERE ALL PLACED IN CLOSED POSITICH UNT FISHER CONTROLS CO.
Il MODIFICATIONS COULD BE COMPLETED.
VALVE VENDOR DID NOT SUPPLY VALVES ACCORDING TO ARCHITECT ENGINEERS SPEC IFICATIONS. SPECS REFLECTED PROPER DIFFERENTIAL PRESSURE UNDER WHICH VA LVE WOULD HAVE TO OPERATE. THIS PRESSURE (46 PSID) IS BASED CN TIME DEPE NDENT CONTAINMENT PRESSURE AFTER LOCA. ALL 7 VALVES HAVE BEEN MOD TO LIM IT CPENING TO 30 DEGREES. NO FURTHER ACTION PLANNED.
DUANE ARNOLD 05000331 061479 DURING DAILY SURVEILLANCE TESTING, RR 4379A & PR 4379B, DRYWELL GASECUS REAC COOL PRES BOUN LEAK DETEC 79-013/03L-0 071379 RADIATION MONITORS, WERE FOUND TO BE INDICATING DCUNSCALE. PARTICULATE 1 INSTRUMENTATION + CONTROLS 026873 30-DAY IODINE MONITORING FUNCTIONS OF RECORDERS WERE OPERAELE. TECH SPEC SECTI RECORDER ON 3.6.C REQUIRES BOTH SUMP & AIR SAMPLING SYSTEMS TO BE OPERABLE DURING COMPONENT FAILURE REACTCR OPERATION. A SEVEN DAY LIMITING CONDITION FOR OPERATION WAS ENT ELECTRONIC ERED. THERE HAD BEEN 2 PREVIOUS OCCURRENCES INVOLVING THESE RECORDERS (S HONEYWELL CORPORATION EE LERS 77-3 AND 77-4).
AN AMPLIFIER CARD IN RR 4379B WAS REPAIRED & RECORDER TESTED E FOUND OPE RABLE. THIS ACTION WAS COMPLETED APPROXIMATELY 25 HRS AFTER RECORDERS WE RE FCUND COWNSCALE. THIS CANCELLED 7 DAY LCO. RE0102A WAS REPLACED
- RR 4379A IS AWAITING OPERABILITY TESTING. BOTH RECORDERS ARE HONEYWELL MODE L 37303.
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CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORY TYPE CAUSE DESCRIPTICN DUANE ARNDLD 05000331 070379 AS A RESULT OF NRC BULLETIN 79-02, A SPECIAL TESTING PROGRAM MAS DEVELOP SYSTEM CODE NOT APPLICABLE 79-014/01T-0 071779 ED 8 IMPLEMENTED TO TEST PIPE SUPPORT BASE PLATE DESIGNS USING CONCRETE HANGERS, SUPPORTS,$ HOCK SUPPRSS 026876 2-WEEK EXPANSION ANCHOR BOLTS. RESULTS OF TESTING INDICATED A POTENTIAL GENERIC SUPPORTS PROBELM EXISTED WITH ANCHOR LOLTS NOT MEETING SEISMIC DESIGN CRITERIA.
DESIGN /FABRICATIDH ERROR ANALYSIS BY ARCHITECT ENGINEER CONCLUDED FAILURE RATE SUFFICIENTLY LCW CONSTRUCTION / INSTALLATION SO AS TO NOT COMPRot1ISE ECCS OPERABILITY IN EVENT OF A DESIGN BASIS EART RED HEAD /PHILLIPS DRILL CO.
HQUAKE.
ECCS DETERMINED THEREFORE TO BE CPERABLE.
CAUSE DETERMINED TO BE PRIMARILY FAULTY INSTALLATION WITH A CONTRIBUTING CAUSE OF INADECUATE DESIGN. MAJORITY OF INSTALLED ANCHGR BOLTS WERE MAD E BY PHILLIPS DRILL CD. AT THE PRESENT TIME AN ANCHOR BOLT REPLACEMENT P ROGRAM IS IN PROGRESS. REPLACEMENT ANCHOR BOLTS OF AN IMPROVED DESIGN MA DE BY HILTI ARE BEING INSTALLED.
DUANE ARNOLD 05000331 070579 DURING AN ANNUAL REVIEW OF SURVEILLANCE PROGRAM IT MAS DETERMINED THE RE EMERG CORE COOLING SYS + CONT 79-015/03L-0 080379 QUIREMENT ON TECH SPEC PAGE 3.2-15, NOTE 6.
TO MEASURE RELAY DROPOUT VOL COMPONENT CODE NOT APPLICABLE 026874 30-DAY TAGE HAD NOT BEEN INCORPORATED INTO SURVEILLANCE TEST WHICH TESTS HPCI, SUBCOMPONENT NOT APPLICABLE RCIC, LPCI. ADS & CCRE SPRAY TRIP SYSTEM BUS PCUER MONITOR RELAYS. THE S DEFECTIVE PROCEDURES URVEILLANCE TEST IN QUESTION DID PROVIDE FOR A FUNCTIONAL TEST OF THE RE NOT APPLICABLE LAYS WHICH VERIFIED GPERABILITY. ECCS OPERABlLITY NOT AFFECTED.
ITEM NOT APPLICABLE DEFECTIVE PROCEDUPE. A SURVEILLANCE TEST PROCECURE (STP) MEASURING RELAY DROPCUT VOLTAGE WAS APPARENTLY DELETED FOLLCWING CHANGE 15 TO T.S. WITH OUT INCCRPORATING THIS 'EST REQUIREMENT INTO ANOTHER STP. A NEW STF 15 C URRENTLY BEING DEVELOPED WHICH WILL SATISFY CURRENT T.S.
TESTING REQUIRE MENTS. THIS TEST WILL BE PEPFORMED WHEN REVIEW & APPROVAL IS CCMPLETED.
DUANE ARNOLD 05000331 072579 DURING NORMAL OPERATION IT WAS DETERMINED THAT PLANT HEAT RATES 1 EFFICI FEEDWATER SYSTEMS + CONTROLS 79-016/01T-0 080879 ENCIES WERE BETTER THAN NORMALLY EXPECTED. AN INVESTIGATION WAS BEGUN WH VALVES 026875 2-WEEK ICH CENTERED ON FEEDWATER FLOW INSTRUMENTATION. FOLLOWING A PLANT GUTAGE SINGLE BLADE ON 7/21/79, DURING WHICH F/W FLOW INSTRUMENT MANIFOLD VALVES WERE REPAI COMPONENT FAILURE RED, HEAT RATES & EFFICIENCIES WERE CLOSE TO EXPECTED VALUES. IT HAS SIN MECHANICAL CE BEEN CALCULATED THAT LICENSED THERMAL PCUER LIMIT WAS EXCEEDED. IT CA HEX INDUSTRIES, INC.
N AL50 BE CONCLUDED MAPLHGR, LHGR 8 MCPR LIMITS WERE EXCEEDED.
EQUALIZING VALVES ON VALVE MANIFOLDS FOR FLCW TRANSMITTERS FOR EDTH FEED WATER TRAINS WERE SLIGHTLY STEAM CUT, WHICH ALLOWED BYPASS FLGW S GAVE L OW F/W FLOW INDICATION. THIS CAUSED CORE THERMAL POWER CALCULATION TO EE NON-CONSERVATIVE. VALVES LAPPED. MANIFOLD MADE BY HEX INDUSTRIES WILL B E REPLACED. REDUNDANT INDICATICN WILL BE ADDED.
DUANE ARNOLD 05000331 072679 DURING SURVEILLANCE TESTING PRESSURF DIFFERENTIAL SWITCHES WHICH CGNTROL REACTOR CONTAINMENT SYSTEMS 79-018/03L-0 052479 SUPPRESSION CHAMBER TO REACTOR ELDG VACUUM LREAKERS TRIPPED AT GUT OF S INSTRUMENTATION + CONTROLS 026878 30-DAY PECIFICATION VALUES. PDS 4304 HAD NOT TRIPPED BY TIME UPPER LIMIT (3.5 P SWITCH SID) 0F TEST INSTRUMENT UAS REACHED & PDS 4305 TRIPPED AT.64 PSID. SETP COMPONENT FAILURE OINT REQUIRED BY TECH SPEC 3.7.A.3 IS
.5 PSID. SWITCHES WERE RECALIBRATE ELECTRICAL D& FUNCTIONALLY TESTED. THERE WERE 3 PREVIOUS SIMILAR OCCURRENCES (SEE BARTGN INSTRU CO., DIV 0F ITT LERS 75-33, 77-55 AND 78-32).
PDS 4305 WAS OUT OF TOLERANCE DUE TO INSTRUMENT DRIFT. CAUSE OF PDS 4304 NOT TRIPPING IS UNKNOWN. BOTH SWITCHES ARE CARTON MODEL 2CEA PRESSURE D IFFERENTIAL SWITCHES. SWITCHES WERE CALIERATED 4 FUNCTICHALLY TESTED WIT H SATISFACTORY RESULTS. A DESIGN REVIEW IS CURRENTLY IN PROGRESS TO DETE RMINE ADEQUACY OF THIS INSTRUMENT APPLICATION.
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REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION DUANE ARNOLD 05000331 072879 FOLLOWING A POWER INCREASE IN ACCORDANCE WITH APPROVED PROCEDURES, CPR W REACTIVITY CONTROL SYSTEMS 79-019/03L-0 082779 AS FOUND TO BE AT FLOW ADJUSTED 1.364 T.S.
LIMIT. IN CRDER TO GAIN MARGI OTHE2 COMPONENTS 026879 30-DAY N CORE FLOW WAS DECREASED FPCM 62% TO 48% IN PREPARATION FOR DRIVING CON SUSCOMPONENT NOT APPLICABLE TROL RODS. CDR WAS AGAIN CHECKED 4 FOUND TO BE 1.430, BELOW FLOW ADJUSTE OTHER D 1.436 T.S.
LIMIT. FOUR CCNTROL RODS WERE INSERTED FROM POSITION 18 TO NOT APPLICABLE POSITION 12 WITHIN 6 MINUTES. CPR WAS AGAIN CHECKED E FOUND TO BE 1.588, ITEM NOT APPLICABLE WELL ABOVE THE 1.436 T.S.
LIMIT.
THIS OCCURRENCE WAS RESULT OF A XENON TRANSIENT CAUSING THERMAL POWER TO INCREASE. CORRECTIVE ACTIONS TO INCREASE CPR WERE PROPER AND WELL WITHI N TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS PARAGRAPH 3.12.C. PL ANT HAS BEEN AND WILL CONTINUE TO BE OPERATED IN A MANNER WHICH WILL MIN IMIZE THIS TYPE OF OCCURRENCE.
DUANE ARHOLD 05000331 081079 DURING HORMAL OPERATION OPERATIONS PERSONNEL NOTED SUPPRESSION CHAMBER W SAFETY RELATED DISPLAY INSTR 79-017/03L-0 090679 ATER LEVEL INDICATION ON LR 4385 WAS DRIFTING D0kNSCALE WHILE REDUNDANT INSTRUMENTATION + CONTROLS 026877 30-DAY INDICATION ON LR 4384 WAS STABLE. TECHNICAL SPECIFICATIONS TABLE 3.2-F R TRANSMITTER EQUIRES TWO SUPPORESSION CHAMBER WATER LEVEL IND]CATORS BE CPERABLE. THE COMPONENT FAILURE RE HAVE BEEN NO PREVIOUS SIMILAR OCCURRENCES.
ELECTRONIC GENERAL ELECTRIC CO.
COMP 0HENT FAILURE. LEVEL TRANSMITTER, LT 2325, ASSOCIATED WITH LR4385 WA S FOUND TO HAVE A FAULTY AMPLIFIER CARD. LT 2325 IS A GE-MAC MODEL 555 L IQUID LEVEL TRANSMITTER. AMPLIFIER CARD WAS REPLACED WITH A LIKE-FOR-LIK E SPARE & TRANSMITTER CALIBRATED 8 FUNCTIONALLY TESTED WITH SATISFACTORY RESULTS. NO FURTHER CORRECTIVE ACTION PLANNED.
DUANE ARNOLD 05000331 091779 DURING SURVEILLANCE TESTING CONTROL BUILDING STAND 3Y FILTER UNTT (SBFU)
CONT ROOM HABITBLTY SYS + CONT 79-023/03L-0 101179 IV-SFU-30B DID NOT START WHEN INITIATED. REDUNDANT STANDBY FILTER UNIT INSTRUMENTATION + CONTROLS 027094 30-DAY IV-SFU-30A WAS OPERABLE. OPERABILIi. REQUIREMENTS ARE LISTED IN TECHNIC TRANSMITTER AL SPECIFICATIONS SECTION 3.10.1.
A 7 DAY LCO WAS ENTERED AS PER TECH.
CCMPCNENT FAILURE SPEC. PARAGRAPH 3.10.A.3.
THERE HAS BEEN ONE PREVIOUS SIMIL AR OCCURRENC INSTRUMENT E (SEE R0 REPORT 77-082).
GEHERAL ELECTRIC CO.
FT7320B WAS DRIFTED SUFFICIENTLY UPSCALE TO PREVENT THE PERMISSIVE START SIGNAL FOR THE "B" SBFU.
FT7320D IS A GE MODEL 552 FLOW TRANSMITTER.
FT7 320B WAS RECALIBRATED 8 SBFU SURVEILLANCE TESY COMPLETED WITH SAT. R ESULTS ENDING 7 DAY LCO.
DESIGN REVIEW TO BE INITIATED. CALIBRATIDH OF FT7320B TO BE CHECKED WEEKLY PENDING DESIGN REVIEW RESULTS.
EDWIN I. HATCH-1 05000321 032079 DURING STEADY STATE POWER OPERATION AT 2384 MWT, 2 CHEMICAL RADIATION TE SYSTEM CODE NOT APPLICABLE 79-021/04L-0 032679 CHNICIANS 03 SERVED WATER BUBBLING OUT OF GROUND WHILE OBTAINING A WATER COMPONENT CODE NOT APPLICABLE 026797 30-DAY SAMPLE FRCM PIEZGMETER WELL P17B HEAR DIESEL GENERATOR BLDG.
ANALYSIS 0 SUBCOMPONENT NOT APPLICASLE F WATER 3 SOIL REVEALED SMALL AMOUNTS OF RADI0 ACTIVITY AS FOUND IN REACT PERSONNEL ERROR OR STEAM SAMPLES. NO SIGNIFICANT IMPACTS ON PUBLIC HEALTH & SAFETY BECAU CONSTRUCTION PERSONNEL SE EVENT CCCURRED IN PROTECTED AREA 0F SITE, ACTIVITY RELEASED WAS SMALL ITEM NOT APPLICABLE
& ACTIVITY (EXCLUDING TRITIUM) WAS CONFINED TO IMMED POINT OF DISCHAR.
DURING CONSTRUCTIDH A 1/2 INCH LINE WAS INSTALLED TO CARRY INERTING NITR OGEN TO FEEDWATER HEATERS FROM A TANK IN YARD.
CPEN LINE NOT REMOVED A (37 FTER UNIT STARTUP. VALUE DISCOVERED PARTI ALLY 0; EN ON THIS LINE NEAR FE 45m EDWATER HEATER WAS IMMEDIATELY CLOSED. LINE WAS CAPPED INSIDE TURBINE B (jg UILDING TO PREVENT RECURRENCE.
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C,AUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION EDWIN I. HATCH-1 05000321 06t279 DURING THE 1979 REFUELING OUIAGE A GENERAL ELECTRIC REVIEW OF CLASS IE D MAIN STEAM ISOL SYS + CONTROLS 79-037/01T-1 072379 RYWELL EQUIPMENT IN RESPONSE TO IEB 79-01 INDICATED THAT THE LIMIT SWIT VALVES 026153 2-WEEK CHES ON MAIN STEAM ISOLATICN VALVES B21-F022A, B,
C, 4 D DID NOT HAVE A GLOBE CCMPLETE TEMPERATURE & RADIATION CUALIFICATION TEST REPORT DOCUMENT TO Q DESIGN / FABRICATION ERROR UALIFY IT TO PERFORM UNDER AN ACCIDENT CONDITION. NO SIGNIFICANT EFFECT DESIGN ON PLANT SAFETY FROM EVENT SINCE WORST CASE FAILURE OF THESE LIMIT SWIT NAMCO CONTROLS CHES WOULD ONLY RESULT IN A LOSS OF VALVE POSITION INDICATION.
AT TIME OF INSTALLATION, NAMCO MODEL SL3-B2U LIMIT SWITCHES WERE NOT REQ UIRED TO HAVE ENVI"'NMENTALLY QUALIFIED TEST REPORT DOCUMENTS. LATER IM PLEMENTED IEB 79-O' REQUIRED ALL IE EQUIPMENT IN DRYWELL MEET TEST QUALI FICATIONS FOR ACCIDENT CONDITIONS. NEW NAMCO MODEL EA-740-5000 LIMIT SW ITCH IS ORDERED 3 UILL BE INSTALLED AT FIRST SCHEDULED COLD SHUTDCWN.
EDWIN I. HATCH-1 05000321 072579 WITH THE REACTOR IN THE SHUTDouN COOLING MODE, THE 1C RHR PUMP (E11-C002 RESIDUAL HEAT REMOV SYS + CONT 79-050/01X-1 090579 C) WAS FOUND TO HAVE AN EXCESSIVE L EAK AT THE MECHANICAL SEAL.
k" TEN THE PUMPS 026419 OTHER 1C RHR PUMP UAS REMOVED FROM SERVICE TO REPAIR THE SEAL, THE REALTOR UN CENTRIFUGAL IT WAS NOT IN COMPLIANCE WITH TECHNICAL SPECIFICATION 3.5.B.1.A BECAUSE COMPONENT FAILURE THE RHR PUMPS IN THE B LOOP WERE ALREADY OUT OF SERVICE FOR HANGER REPAI MECHANICAL RS.
PUBLIC HEALTH AND SAFETY WERE NOT AFFECTED SY THIS INCIDENT.
BYRON JACKSON PUMPS, INC.
THE EXCESSIVE LEAKAGE WAS CAUSED BY THE MECHANICAL SEAL BEING RUPTURED.
THE SEAL WAS REPLACED AND THE 1C RHR PUMP RETURNED TO SERVICE OH JULY 2 7,
1979.
EDWIN I.
HATCH-1 05000321 081279 WITH REACTOR IN COLD SHUTDCWN, WHILE PERFORMING RHR SERVICE WATER PUMP O RESIDUAL HEAT REMOV SYS + CONT 79-063/03L-0 083179 PERABILITY TEST, RHR SERVICE WATER PUMPS WERE FOUND INCAPABLE OF DELIVER PUMPS C26732 30-DAY ING A RATED FLCW FROM EACH PUMP OF 4000 GPM AT 384 PSI AS REQUIRED BY T.
CENTRIFUGAL S.
4.5.C.1.B.
THE PUMPS & FAILURE DATES ARE:
E11-C001B 3 E11-C001D ON COMPONENT FAILURE AUGUST 12, 1979, E11-C001A ON AUGUST 16, 1979, 3 Ell-C001D ON AUGUST 20, MECHANICAL 1979.
PUBLIC HEALTH AND SAFETY WERE NOT AFFECTED BY THIS INCIDENT.
JOHNSTON PUMP CO.
PUMPS FAILED TO DELIVER RATED FLOW DUE TO NORMAL WEAR ON THE IMPELLER WE AR RINGS AND THE BUSHINGS.
THESE PUMPS ARE DESIGNED TO DELIVER RATED FL OW UNDER FACTORY CONDITIONS WITH NO ALLOWANCES MADE FOR WEAR.
THE PUMPS WERE REBUILT AND REINSTALLED. THE LAST PUMP TO BE TESTED, E11-C001C W AS FOUND SATISFACTORY ON AUGUST 24, 1979.
EDWIN I. HATCH-1 05000321 081679 ON 3-16-79. AT 1000 CST IT WAS DISCOVERED THAT FUNCTIONAL TESTS FOR THE SYSTEM CODE NOT APPLICABLE 79-067/03L-0 083179 CABLE SPREADING ROOM CO2 SYSTEM 8 130' EL.
CONTROL BUILDING CORRIDOR SP CCMPONENT CODE NOT APPLICABLE 026729 30-DAY RINKLER SYSTEM HAD NOT BEEN SUBMITTED FOR PLANT REVIEW BOARD APPROVAL OF SUBCOMPONENT NOT APPLICABLE TEMPORARY CHANGES MADE ON 7-30-79, & 7-31-79, BEFORE 14 DAY LIMIT SPECI PERSONNEL ERROR FIED IN HMP-818 SECTION B.3.
OPERABILITY OF FIRE PROTECTION SYSTEMS 1 P MAINTENANCE & REPAIR PERSONNEL LANT SAFETY WERE NOT ADVERSELY AFFECTED. THIS IS A REPETITIVE OCCURRENC ITEM NOT APPLICABLE E - SEE LER 2-79-91.
COORDINATING ENG FAILED TO SUBMIT TEMP CHANCES TO PRB WITHIN 14 DAY LIMI 4T. ADEQUATE TRACKING OF SUCH CHANGES WILL BE PROVIDED ADMINISTRATIVELY BY A REVISION TO PROCEDURE HNP-818 (TEMPORARY PROCEDURE CHANGE APPROVED 18-24-79, WHICH REQUIRES ALL TEMPCRARY PROCEDURE CHANGE TO BE LOGGED & T LJ7 RACKED BY APPRO DEPT HEAD. FULL COMPLIANCE WILL BE ACHIEVED BY 9-1-79.
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REPORT TYPE CAUSE DESCRIPTION EDWIN I. HATCH-1 05000321 082279 WHILE PERFORMING PROCEDURE HNP-1-3357, (SPRAY / SPRINKLER VALVE CHECKS) IN FIRE PROTECTION SYS + CONT 79-069/03L-0 090579 SAFETY RELATED AREAS, A LINK IN THE ELECTRIC FIRE PUMP START CIRCUIT WA COMPONENT CODE NOT APPLICABLE 026777 30-DAY S OPENED PER PROCEDURE REQUIREMENTS MAKING THE ELECTRIC FIRE PUMP INOPER SUBCCMPONENT NOT APPLICABLE ABLE.
NUMDER 3 DIESEL FIRE PUMP HAD BEEN TAGGED INOPERABLE FOR MAINTENA DEFECTIVE PROCEDURES NCE THEREBY LEAVING ONLY ONE FIRE PUMP READY IN VIOLATION OF TECH. SPEC.
NOT APPLICABLE 3.13.2.
ITEM NOT APPLICABLE EVENT CAUSED BY INADEQUACY OF PROCEDURE HNP-1-3357 IN MAKING PLANT PERSO NNEL AWARE THE ELECTRIC FIRE PUMP WOULD BE INOPERABLE WHILE PROCEDURE WA S CEING PERFORME
D. PROCEDURE
HNP-1-3357 HAD BEEN REVISED SO THAT IT WIL L NOT TIAKE ELECTRIC FIRE PUMP INOP 8 50 PLANT PERSGNNEL WILL BE AWARE OF ELECTRIC FIRE PUMP STATUS WHILE THIS PROCEDURE IS BEING PERFORMED.
EDWIN I.
HATCH-1 05000321 082379 WHILE SHUTDOWN FOR REFUELING 8 PERFORMING HANGER SURV IN RESPONSE TO IE COMPRESSED AIR SYSTEMS + CONT 79-065/01T-0 083179 BULLETIN 79-14 IT WAS DISCOVERED THAT A SECTION OF PIPING IN PLANT INST HANGERS SUPPORTS, SHOCK SUPPRSS 026731 2-WEEK RUMENT AIR SYSTEM (PS2) WAS NOT SEISMICALLY SUPPORTED PER ORIGINAL DESIG HANGERS N.
FURTHER ANALYSIS BY ARCHITECT ENG HAS REVEALED THAT SINCE CONTROLLING DESIGN / FABRICATION ERROR LOAD FCP SUPPORT WAS FOR SEISMIC CONCERNS ONLY 8 SINCE NO SEISMIC EVENT CONSTRUCTION / INSTALLATION HAS DCCURRED, PIPING WAS NOT DEGRADED. THIS IS A REPETITIVE OCCURRENCE.
BECHTEL CORP.
SEE LER 50-366/1978-02.
CURING INITIAL INSTALLATION OF THE PIPING AND ITS ASSOCIATED HANGERS, T HE AFOREMENTIONED HANGER WAS INADVERTENTLY LEFT OFF.
THE PROBLEM WAS C ORRECTED BY INSTALLING A PIPE HANGER AS CALLED FOR BY ORIGINAL DESIGN.
ECWIN I.
HATCH-1 05000321 082579 WITH REACTOR IN STARTUP 4 HOT STANDBY MODE, WHILE PERFORMING PROCEDURE H REAC CORE ISOL COOL SYS + CONT 79-082/03L-0 091279 HP-1-3405, RCIC PUMP CPERABILITY, ON AUGUST 25, 1979, TURBINE WOULD NOT VALVES 026825 30-DAY TRIP WITH TURBINE TRIP PUSHBUTTON 8 ON AUGUST 27, 1979 TURDINE TRIP 4 TH GATE ROTTLE VALVE WOULO NOT CLOSE WITH EITHER CONTROL SWITCH CR TURBINE TRIP CCMPONENT FAILURE PUSHBUTTON.
RCIC SYSTEM WAS DECLARED INOPERABLE, AS A RESULT OF LATER I MECHANICAL NCIDENT, 8 REQUIRt'MENTS OF TECHNICAL SPECIFICATICN 4.5.E.2 COMPILED WITH TERRY STEAM TURDINE COMPANY THERE WERE NO EFFECTS TO PUBLIC HEALTH 8 SAFETY AS RESULT OF INCIDENT FAILURE OF TURBINE-TO TRIP WITH PUSHBUTTON ON AUGUST 25, 1979 WAS DUE TO TURBINE TRIP ACTLATOR HAVING BURNED COILS.
ACTUATCR PLUNGER 8 COIL HOU SING WERE CLEANED 8 BURNED COILS REPLACE
D. PROCEDURE
HNP-1-3405 WAS THE N PERFORMED SATISFACTORILY. ON AUGUST 27, 1979, FAILURE WAS CAUSED BY S PRING CYLINDER ASSEMBLY OF VLV BINDING AFTER TURBINE TRIP COIL ACTUATED.
ECWIN I. HATCH-1 05000321 082779 DURING STEADY STATE OPERATICH AT LOW POUER FOR STARTUP TESTING FOLLOWING REACTOR VESSEL INTERNALS 79-066/01T-0 090479 REFUELING OUTAGE, RCUTINE SURV REVIEW REVEALED THAT HNP-1-9400 (JET PUM COMPONENT CODE NOT APPLICABLE 026730 2-WEEK P INTEGRITY) HAD BOT BEEN PERFORMED SATISFACTORILY CN 8-26-79. PROCEDURE SUBCOMPONENT NOT APPLICABLE HAD BEEN PERFORMED, BUT WAS UNACCEPTABLE. TEST SHOP BEGAN CALIBRATION O PERSONNEL ERROR F INSTRUMENTS SO THAT PROCEDURE COULD BE PERFORMED AGAIN TO ENSURE ACCUR LICENSED 8 SENIOR OPERATCRS ATE READINGS. T/S 3.6.I REQUIRES PLANT TO BE IN COLD SHUTDOWN MODE WITHI ITEM NOT APPLICABLE N 24 HRS. FAILURE TO COMPLY WITH SHUTDOWN REQ WAS NOT RECOGNIZED.
PLANT PERSCNNEL FJILED TO RECOGNIZE THAT LCO EXISTED. INSTRUMENT CALIBRA (yg TION WAS SUSPECTED 4 PROCEDURE WAS EXPECTED TO BE ACCEPTABLE WHEN INSTRU N*
MENT CALIBRATION UAS CCMPLETE. IMMEDIATELY UPON DISCOVERY PROCEDURE HNP-1-9400 WAS PERFORMED 4 WAS ACCEPTABLE. BALANCING OF RECIRC LOOP FLOW HAD
(/4 PLACED PROCEDURE IN ACCEPTABLE STATUS. JET PUMP INTEGRITY DID EXIST.
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EVENT DESCRIPTION /
CAUSE SUSCODE/MANUFACT"RER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION EDWIN I.
HATCH-1 050CD321 082779 DURING STARTUP OPERATIONS AT A30sT 80 MWT. HYDROGEN GAS CONCENTRATICN. M GAS RADI0ACT WSTE MANAGMNT SYS 79-070/03L-0 091479 EASURED DOWNSTREAM OF RECOMBINERS. EXCEEDED T.S. APPENDIX B SECTION 2.1.
RECOMBINERS 026826 30-DAY 3.H LIMIT OF 4%
HYDROGEN LEVEL WAS GREATER THAN 4% FOR APPROXIMATELY 3 SUBCOMPONENT NOT APPLICABLE D MINUTES BEFORE RETURNING TO NORMAL.
ANOTHER EVENT OF THIS TYPE OCCURR PERSONNEL E7ROR ED ON 9-11-79 AT 1586 MMT (494 MWE).
HYDROGEN LEVEL FOR THIS EVENT WAS LICENSED. SENIOR OPERATCRS GREATER THAN 4% FOR APPROXIMATELY 15 MINUTES BEFORE RETURNING TO NORMAL.
CATALYTIC INC.
THERE WERE NO EFFECTS ON PUBLIC HEALTH AND SAFETY DUE TO THESE EVENTS.
PROBABLE CAUSE FOR EVENT ON 8-27-79 WAS THAT. WHILE TRYING TO PLACE 1 B SJAE IN SERVICE. WATER IN OFF GAS PIPING ENTERED RECOMBINERS, THUS REDUC ING THEIR RECOMBINING CAPABILITY. PROBABLE CAUSE FOR EVENT ON 9-11-79 W AS THAT A SLUG OF WATER IN OFF GAS SYSTEM REDUCED THE TEMPERATURE IN PRE HEATER AND RECOMBINER. THUS REDUCING THE RECOMSINING CAPABILITY.
EDWIN I. HATCH-1
.05000321 082779 ON 3-27-79. AT 1530 CST. WHILE PERFORMING MONTHLY SUR
V. PROCEDURE
HNP FIRE PROTECTION SYS + CONT 79-072/03L-0 092179 3353 FIRE EQUIPMENT INSPECTION. IT WAS DISCOVERED THAT PLANT SERVICE WAT VALVES 026855 30-DAY ER SUPPLY ISOLATION VALVES FOR STANDBY GAS TREATMENT CHARCOAL FILTER FIR GATE E PROTECTION DELUGE VAL"ES WERE IN CLOSED POSITION WHICH PREVENTED SATIS DESIGN / FABRICATION ERROR FACTORY COMPLETION OF HNP-1-3353. FIRE PROTECTION FOR FILTER TRAINS T46-DESIGN D001 A & B WAS AVAILABLE MANUALLY AND BY AREA SPRINKLER SYSTEM.
OTHER VALVES HAD BEEN CLOSED TO PREVENT SPURIOUS TRIPS OF SYSTEMS CAUSED BY LO W PSW PRESSURE & DELUGE VALVES OVERLY SENSITIVE TO PRESSURE. VALVES WIL L BE MAINTAINED IN MANUAL MODE WITH BREAKAWAY LOCKS: REVISED ANNUNCIATOR RESPONSE & SURVEILLANCE PROCEDURES WILL ASSURE QUICK 8 PROPER ACTION IN EVENT OF A FIRE UNTIL A DESIGN REVIEW IS COMPLETED 3 IMPLEMENTED.
EDWIN I. HATCH-1 05000321 082779 ON 8-27-79. AT 1330 CST. WHILE PERFORMING MONTHLY FIRE PROTECTION EQUIPM FIRE PROTECTION SYS + CONT 79-073/03L-0 092179 ENT INSPECTION PROCEDURE HNP-1-3353. IT WAS DISCOVERED THAT THE SUPPtY F PIPES. FITTINGS 026857 30-DAY OR CONTROL ROOM CHARCOAL FILTER FIRE PROTECTION DELUGE SYS DOES NOT MEET LESS THAN 4 INCHES SEISMIC & RCDUNDANCE REQUIREMENTS PER REG. GUIDE 1.52. A DESIGN CHANGE.
DESIGN / FABRICATION ERROR DCR 76-209. WAS IMPLEMENTED WllICH CHANGED SUPPLY FROM PLANT SERVICE WAT DESIGN ER TO FIRE PROTECTION WATER FOR RELIABLE DELUGE VALVE OPERATION WITH HIG OTHER HER FIRE PROTECTION H2O PRESS. SYS WOULD HAVE OPERATED IN EVENT OF FIRE.
LOW PLANT SERVICE WATER PRESSURE HAD CAUSED PROBLEMS WITH SPURIOUS TRIPS 1 LEAKAGE SO SUPPLY PIPING WAS REROUTED TO FIRE PROTECTION WATER; AE'S RECOMMENDATION NOT TO DO SO WAS RECEIVED AFTER COMPLETION. A LESIGN STUD Y IS UNDERWAY TO DETERMINE AN APPRCPRIATE SOLUTION SUCH AS A DELUGE-VALV E LESS SENSITIVE TO LOW SUPPLY PRESSURE.
EDWIN I HATCH-1 05000321 082979 DURING INITIAL CYCLE 4 STARTUP. THE REACTOR WAS OPERATED AT > 1% POWER I REACT 0k CORE 79-077/03L-0 091379 N THE RUN MODE FOR MORE THAN 24 HOURS WITHOUT A MAXIMUM TOTAL PEAKING FA INSTRU.1ENTATION + CCHTROLS 026824 30-DAY CTOR BEING CALCULATED AS REQUIRED BY TECHNICAL SPECIFICATTON 4.1.B.
THE OTHER RE WERE NO CONSEQUENCES TO THE HEALTH AND SAFETY OF THE PUBLIC. THIS IS OTHER A REPETITIVE OCCURRENCE - SEE LER 79-06.
NOT APPLICABLE ITEM NOT APPLICABLE AT APPROX 28% OF RATED THERMAL PWR., MALFUNCTION OF TRAVERSING INCORE PR OBE PREVENTED UPDATING PROCESS COMPUTER TO FACILITATE CALCULATION OF THE RMAL HYDRAULIC PARAMETERS. MAINTENANCE PERSONNEL WERE CALLED TO REPAIR
--a MALFUNCTIONING TIP MACHINE; HOWEVER. REPAIRS NOT COMPLETED PRIOR TO EXP IRATION OF 24 HR LIMIT.
FOLLCWING REPAIR OF TIP MACHINE, MPF CALCULATED A
LeJ CD Ln Ch
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EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT. TYPE CAUSE DESCRIPTION EDWIN I.
HATCH-1 05000321 083179 WHILE IN STEADY STATE OPrRATION AT LCW POWER FOR TESTS AFTER STARTUP, TH SYSTEM CODE NOT APPLICABLE 79-071/03L-0 091079 E TORUS LEVEL MAS EEING LOWERED.
PLANT PERSONNEL ALLONED TORUS LEVEL TO COMPONENT CODE NOT APPLICABLE 026779 30-DAY DP.0P TO 12 FEET.
MINIMUM LEVEL PER TECH SPECS. 3.7.A.1.A IS 12 FEET 2 SUBCOMPONENT NOT APPLICABLE INCHES.
LEVEL WAS IMMEDIATELY RESTORED TO NORMAL LIMITS.
THIS DID NOT PERSONNEL EEROR CAUSE ANY SIGNIFICANT OCCURRENCE OR HAVE ANY EFFECT ON PUBLIC HEALTH GR LICENSED & SENIOR OPERATORS SAFETY.
ITEM NOT APPLICALLE TORUS LEVEL WAS BEING LOWERED BY NORMAL PROCEDURE. PLANT PERSONNEL PERF ORMING PROCEDURE FAILED TO ADEQUATELY MONITOR LEVEL DECREASE. AFTER DIS COVERY, LEVEL WAS IMMEDIATELY RETURNED TO WITHIN HORMAL LIMITS. PLANT P ERSONNEL HAVE BEEN REINSTRUCTED TO PREVENT REOCCURRENCE.
EDWIN I.
HATCH-1 05000321 090279 THE NSSS SUPPLIER CONTACTED PLANT MANAGEMENT AEOUT POSSIBLE CABLE SEPARA EMERG CORE COOLING SYS + CONT 79-076/01T-0 091179 TION IRREGULARITIES WITHIN THE HPCI SYSTEM AFTER DISCOVERING A SIMILAR P ELECTRICAL CONDUCTORS 026328 2-WEEK ROBLEM AT ANOTHER DUR PLANT.
AT 1800 HOURS ON 9-2-79 WITH REACTOR OF UN SUBCOMPONENT NOT APPLICABLE IT 1 AT STEADY STATE POWER OF 1892 MMT, PLANT ENGINEERING PERSONNEL CONF DESIGN / FABRICATION ERROR IRMED NSSS SUPPLIER'S COMMENTS REGARDING HPCI.
PLANT ENGINEERING PERSON DESIGN HEL REVIEWED WIRING DIAGRAMS AND CONFIRMED A PROBLEM WITH HPCI CABLE SEP ITEM NOT APPLICABLE ARATION DID EXIST.
THIS IS A NON-REFETITIVE OCCURRENCE.
IT WAS DISCOVERED CONTROL CIRCUITS FOR HATCH UNIT 1 DIV. 1 E41-F002 HPCI STEAM ISOLATION VLV WAS ROUTED W/ ADS SYS CONTROL CABLES. SEPARATION CRI TERIA PER DESIGN NOTES WAS NOT MET. DESIGN ERROR DETERMINED TO BE CAUSE OF GCCURRENCE. ARCHITECT-ENGINEER UAS NOTIFIED OF HPCI/ ADS CABLE SEPARA TICN PROBLEM. CURRENTLY IN PROCESS OF FORMULATING PROPOSED DESIGN CHANGE EDWIN I.
HATCH-1 05000321 090479 RBM
'B' UAS OUT OF SERVICE FOR GREATER THAN 24 HOURS.
'B' WAS REMOV OTHR INST SYS REQD FOR SAFETY 79-080/03L-0 092579 ED FROM SERVICE AT 0500 ON SEPTEM3ER 3, 1979 AND RETURNED TO SERVICE AT INSTRUMENTATION + CONTROLS 026947 30-DAY 1505 ON SEPTEMLER 4, 1979.
A SIMILAR OCCURRENCE WAS REPORTED ON LER 75-COMPUTATION MODULE 54.
THERE WERE NO EFFECTS ON THE ENVIRONS.
COMPCNENT.AILURE INSTRUMENT GENERAL ELECTRIC CD.
THE RBM WAS CEMOVED FROM SERVICE TO REPAIR CIRCUITS WHICH WERE MALFUNCTI ONING.
THE RCM HAD FAILED IN A CONSERVATIVE MODE BY NOT ALLOWING SPECIF IC RODS TO EE WITHDRAWN AT CONDITIONS WHICH WOULD HAVE ALLOWED THEIR WIT HDRAWAL.
THE RBM WAS RETURNED TO SERVICE FOLLOWING REPAIRS.
EDWIN I.
HATCH-1 05000321 090579 DURING HORMAL OPERATION PLANT PERSONNEL DISCOVERED ISOLATION VALVE TO RE SYSTEM CODE NOT APPLICABLE 79-078/03L-0 091479 ACTOR BUILDING HVAC ROCM SPRAY SYSTEM CLOSED.
SYSTEM WAS REQUIRED TO BE COMPONENT CODE NOT APPLICABLE 026827 30-DAY OPERABLE PER TECHNICAL SPECIFICATIONS 3.13.3.
SYSTEM WAS IMMEDIATELY R SUBCOMPONENT NOT APPLICABLE ESTORED TO SERVICE.
THERE WERE NO SIGNIFICANT OCCURRENCES THAT TOOK PLA PERSONNEL ERROR CE AS A RESULT OF THE EVENT.
THIS IS NOT A REPETITIVE OCCURRENCE.
LICENSED 2 SENIOR OPERATCRS ITEM NOT APPLICABLE REACTOR DLDG HVAC ROOM SPRAY SYSTEM ISOLATION VALVE WAS CLOSED DURING OU TAGE BECAUSE OF WELDING IN AREA.
ISCLATION VLV WAS NOT OPENED AT CONCLU SION OF UELDING.
AFTER DISCOVERY, VLV WAS OPENED 2 SYS WAS RETURNED TO (j,
SERVICE.
PLANT PERSONNEL HAVE BEEN REINSTRUCTED 2 PROCEDURES WILL BE RE VISED TO PREVENT RECURRENC
E. PROCEDURE
HNP-1-3588 REVISED BY 10-11-79.
4, LN CD Ln N
'NOV 08, 1979 LER MONTHLY REPORT SORTED BY FACILITY PAGE 36 C'
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- - CAUSE SU3 CODE / MANUFACTURER CONTROL HO.
REPORT TYPE CAUSE DESCRIPTICN
-EDWIN I.
HATCH-1 05000321 090779 WITH THE UNIT 1 AT 2304 MEGAWATTS, THE RHR SERVICE WATER PUMPS "A",
"C" RESIDUAL HEAT REMOV SYS + CONT 79-075/01T-0 091879 1
"D" W7ULD NOT PUMP RATED FLOW AT RATED DISCHARGE PRESSURE AS PER HNP-1 PUMPS 026939 2-WEEK
-3167, "RHR SERVICE WATER PUMP OPERABILITY AND RATED FLCW" TEST.
- LATER, ROTARY THE "B" PUMP UAS ALSO DIAGNOSED TO HAVE THE SAME PROBLEM. SINCE THE RH DEFECTIVE PROCEDURES R SERVICE WATER SYSTEM WAS IHOPERABLE, THE REACTOR WAS TAKEN TO COLD SHU NOT APPLICABLE TDOWN AS PER THE TECH SPECS SECTION 3.S.C.
THE OTHER EMERGEHCY CORE C00 JOHNSTON PUMP CO.
LING SYSTEMS WERE AVAILABLE AND GPERABLE. THIS IS REPETITIVE (79-63).
RHR SERVICE H2O PUMP OPERABILITY TEST CONTAINED FORMULAS FOR CALCULATING IHLET PRESS & DISCHARGE PRESS UHICH WERE DETERMINED TO BE INCORRECT. A RCHITECT ENG CONSULTED ABOUT EQUATIONS, THEIR SUGGESTIONS THEN IMPLEMENT ED IN REVISION TO HNP-1-3167 4 DOCUMENT CHANGE TO T.S.
LIMIT ON PUMP TOT ALY. DYNAMIC HEAD SUBMITTED 8 APPROVED BY NRR. PUMP TESTED SUCCESSFULLY.
ECWIN I. HATCH-1 05000321 090979 UHILE IN SHUTDOWN, IT WAS DISCOVERED THAT THE REACTOR WATER LEVEL (ADS)
ENGNRD SAFETY FEATR INSTR SYS 79-079/03L-0 092479 SURVEILLANCE TEST (HNP-1-3251) GRACE PERIOD HAD BEEN EXCEEDED. THE TEST INSTRUMENTATION + CONTROLS 026948 30-DAY WAS COMPLETED TEN (10) HOURS LATER THAN THE GRACE PERIOD A; LOWS.
WHEN SWITCH THE SURVEILLANCE TEST WAS PERFORMED, THE LEVEL SWITCHES WERE "OUND TO BE PERSONNEL ERROR OPERATING SATISFACTORY.
MAINTENANCE & REPAIR PERSONNEL ITEM NOT APPLICABLE THE CAUSE WAS PERSONNEL ERROR.
THE LIMIT OF THE GRACE PERIOD WAS OVERLO OKED.
THE SURVEILLANCE TEST WAS PERFORMED SATISFACTORILY. PERSONNEL WE RE COUNSELED ON THE IMPORTANCE OF COMPLETING SURVEILLANCE TESTS WITHIN T HEIR GRACE PERIODS.
EDWIN I. HATCH-1 05000321 091079 WITH UNIT 1 IN RUN & UNIT 2 IN SHUTDOWN, A POTENTIAL FAILURE MODE FOR SE CNTHMNT COMBUS GAS CONTROL SYS 79-031/01T-0 092079 VERAL PRIMARY CONTAINMENT PURGE & INERTING VALVES WAS DISCOVERED BY ARCH VALVES 026856 2-WEEK ITECT-ENGINEER AND VALVE VENDOR.
IT WAS POSTULATED THAT, IF A LOCA OCCU BUTTERFLY RRED WHILE VALVES WERE OPEN, STEAM PRESSURE COULD CAUSE THESE VALVES TO DESIGN /FABRICATIDH ERROR OVERTRAVEL AND LOSE SEATING CAPABILITY. THIS WOULD ALLOW LEAKAGE OF CON DESIGN TAMINATION TO REACTOR BUILDING. THIS FAILURE MODE APPLIES TO BOTH UNITS FISHER CONTINENTAL 1 & 2: IT IS A NON-REPETITIVE OCCURRENCE.
THIS SITUATION IS A RESULT OF DESIGN DEFICIENCIES. A DESIGN CHANGE TO P REVENT THE VALVES FROM OPENING MORE THAN 30 DEGREES IS BEING INVESTIGATE D.
NOTE THAT FACILITY STATUS APPLIES TO UNIT 1 OHLY.
UNIT 2 WAS SHUTD0 WN AT THE TIME.
EDWIN I. HATCH-2 05000366 082777 THE COOLING WATER TO RHR SERVICE WATER PUMPS 2B AND 2D WAS FOUND TO BE L RESIDUAL HEAT REMOV SYS + CONT 77-097/03L-0 091279 ESS THAN THE AMOUNT HEEDED TO COOL THE BEARINGS PROPERLY.
THERE WAS HO INSTRUMENTATION + CONTROLS 026832 30-DAY EFFECT ON THE ENVIRONS. THERE HAVE BEEH NO SIMILAR OCCURRENCES OF THIS CONTROLLER TYPE.
COMPONENT FAILURE INSTRUMENT FISHER CONTROLS CO.
THE PRESSURE CONTROLLER FOR VALVE 2E11-F126B, COOLING WATER FLOW CONTROL VALVE, WAS NOT CONTROLLING THE VALVE POSITIDH PROPERLY. THE CONTROLLER WAS TUNED TO ALLOW THE PROPER COOLING WATER FLOW.
2E11-F126A WAS CHECK ED AND FOUND TO BE OPERATING PROPERLY.
4 U
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.CAUSE SUSCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION E D' I I.
HATCH-2 05000366 062879 AT 1220 CDT, MSIV FAST CLOSURE STARTUP TEST FOR UNIT 2 INITIATED. REACT REAC CORE ISOL COOL SYS + CONT 79-059/01T-1 091479 OP SCRAMMED AS A RESULT OF MSIV CLOSURE.
DURING RESULTING TRANSIENT, RC INSTRUMENTATION + CONIROLS 026321 2-WEEK IC 3 HPCI BOTH ISOLATED ON STEAM LINE HIGH DIFFERENTIAL PRESSURE.
T.S.
SWITCH 3/4.7.3.B & 3/4.5.1 ACTION A WERE MET FOR EDTH RCIC & HPCI RESPECTIVELY.
OTHER ADS SYSTEM WAS OPERABLE. BOTH RCIC & HPCI SYSTEMS WERE SUCCESSFULLY ST NOT APPLICABLE ARTED MANUALLY.
AT TIME OF GCCdRRENCE UNIT 1 WAS IN COLD SHUTDOWN CONDI BARTON INSTRU CO.,
DIV 0F ITT TION FOR MAINTENANCE, HANGER MODIFICATIONS, AND REFUELING.
RCIC 2 HPCI SYSTEMS ISOLATED ON STEAM LINE HIGH DIFFERENTIAL PRESSURE.
AS SYSTEMS ISOLATED. THEY WERE MANUALLY STARTED 8 LATER SECURED UPON COM PLETION OF MSIV FAST CLOSURE STARTUP TEST.
TEST SHOP PERSONNEL WERE INS TRUCTED TO CHECK CALIBRATION OF SWITCHES 2E51-N017 & N018 (RCIC) & 2E41-N004 & N005 (HPCI). INSTRUMENT LINES REDESIGNED & TESTING WAS SUCCESSFUL EDWIN I. HATCH-2 05000366 081379 WHILE PERFCRMING ROUTINE SURVEILLANCE PROCEDURE HHP-2-3005, MAIN STEAM L MAIN STEAM SYSTEMS + CONTROLS 79-092/03L-0 082979 INE RADIATION MONITOR FUNCTIONAL TEST AND CALIBRATION, INSTRUMENT 2D11-K INSTRUMENTATION + CONTROLS 026728 30-DAY 603B SETPOI1T WAS FOUND TO BE 2700 MR/HR.
THE TECH. SPEC. ACCEPTANCE CR SUITCH ITERIA REQUIRES A SETPOINT OF 2175 +/- 10% MR/HR.
THERE WAS NO EFFECT 0 CCMPONENT FAILURE N THE ENVIRONS.
A SIMILAR OCCURRENCE WAS REPORTED ON LER-2-79-053.
INSTRUMENT GENERAL ELECTRIC CD.
INSTRUMENT DRIFT WAS ATTRIBUTED AS THE CAUSE FOR THE PROBLEM.
THE INSTR UMENT WAS RECALIBRATED PER HNP-2-5100 AND RETURNED TO SERVICE.
EDWIN I. HATCH-2 05000366 081879 WHILE PERF0FMING NORMAL SURVEILLANCE PROCEDURE HNP-2-3105, FOR MAIN STEA MAIN STEAM SYSTEMS + CONTROLS 79-093/03L-0 082979 M LINE PRESSURE INSTRUMENT FUNCTIONAL TEST AND CALIBRATION, 2B21-N015A W INSTRUMENTATION + CONTROLS 026727 30-DAY AS FOUND TO HAVE A SETPOINT OF 835 PSIG DECREASING. THE TECH. SPEC. ACC SWITCH EPTANCE CRITERIA REQUIRES A SETPOINT OF GREATER THAN CR EQUAL TO 825 PSI CCMPONENT FAILURE G PLUS 15 PSIG HEAD CORRECTION. THERE WAS NO EFFECT ON THE ENVIRONS. H INSTRUMENT 0 PREVIOUS CCCURRENCES OF THIS TYPE HAVE BEEN REPORTED.
DARKSDALE COMPANY THE PROBLEM WAS ATTRIBUTED TO SETPOINT DRIFT.
THE INSTRUMENT WAS RECALI BRATED PER HNP-2-5279 AND RETURNED TO SERVICE.
EDWIN I.
HATCH-2 05000366 082279 WHILE PERFORMING PROCEDURE HHP-2-3357, (SPRAY / SPRINKLER VALVE CHECKS) IN FIRE PROTECTION SYS + CONT 79-094/03L-0 090779 SAFETY RELATED AREAS. A LINK IN THE ELECTRIC FIRE PUMP START CIRCUIT WAS COMPONENT CODE NOT APPLICABLE 026780 30-DAY OPENED PER PROCEDURE REQUIREMENTS MAKING THE ELECTRIC FIRE PUMP IN0PERA SUCCC"PONENT NOT APPLICABLE BLE.
NUMBER 3 DIESEL FIRE PUMP HAD DEEN TAGGED INOPERABLE FOR MAINTENAN DEFECTIVE FROCEDURES CE THEREBY LEAVING ONLY ONE FIRE PUMP READY IN VIOLATIGN OF TECH. SPEC.
NOT APPLICABLE 3.7.6.1.
ITEM NOT APPLICABLE EVENT CAUSED BY INADEQUACY OF PROCEDURE HHP-2-3357 IN MAKING PLANT PERSO
~~~
NNEL AWARE THAT ELECTRIC FIRE PUMP WOULD BE IHOP WHILE PROCEDURE WAS EEI (J7 NG PERFORMED.
PROCEDURE HNP-2-3357 HAS BEEN REVISED SO IT WILL NOT MAKE 43, THE ELECTRIC FIRE PUMP INOP & SO PLANT PERSONNEL WILL BE AWARE OF THE E LECTRIC FIRE PUMP STATUS WHILE THIS PROCEDURE IS BEING PERFORMED.
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CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION ECUIN I. HATCH-2 05000366 082979 WHILE PERFORMING ROUTINE SURVEILLANCE PROCEDURE HNP-2-3309, HPCI TURBINE EMERG CORE COOLING SYS + CONT 79-099/03L-0 090779 EXHAUST DIAPHRAGM PRESSURE SWITCH FUNCTIONAL TEST AND CALIBRATION, INST INSTRUMENTATION + CONTROLS 326775 30-DAY RUMENT 2E41-N012C FAILED TO HOLD PRESSURE.
INSTRUMENTS 2E41-N012 A, B,
SWITCH AND D WERE OPERABLE.
THERE WAS NO EFFECT ON THE ENVIRONS. THERE HAVE B COMPONENT FAILURE EEN NO SIMILAR OCCURRENCES REPORTED PREVIOUSLY.
INSTRLMENT BARKSDALE COMPANY A CRACK WAS DISCOVERED IN THE DIAPHRAGM OF THE SWITCH.
THE INSTRUMENT W AS REPLACED AND THE NEW SWITCH CALIBRATED PER HNP-2-5279.
THE OTHER TUR BINE EXHAUST SWITCHES (2E41-N012A, B AND D) WERE CHECKED AND WERE ABLE T 0 HOLD PRESSURE.
EDWIN I. HATCH-2 05000366 090279 THE NSSS SUPPLIER CONTACTED PLANT MANAGEMENT ABOUT POSSIBLE CABLE SEPARA EMERG CORE COOLING SYS + CONT 79-098/01T-0 091179 TION IRREGULARITIES WITHIN THE HPCI SYSTEM AFTER DISCOVERING A SIMILAR P ELECTRICAL CONDUCTORS 026829 2-WEEK ROBLEM AT ANOTHER EWR PLANT.
AT 1800 HOURS ON 9-2-79, WITH UNIT 2 REACT SUBCCMPONENT NOT APPLICABLE OR AT STEADY STATE POWER OF 2350 MWT, PLANT ENGINEERING PERSONNEL REVIEW DESIGN / FABRICATION ERROR r0 WIRING DIAGRAMS AND CONFIRf1ED A PROBLEf1 WITH HPCI CABLE SEPARATION DI DESIGN D TXIST.
THIS IS A NON-REPETITIVE OCCURRENCE.
ITEM NOT APPLICABLE IT WAS DISCOVERED THAT CONTROL CIRCUITS FOR HATCH UNIT 2 DIV. I 2E41-F00 2 HPCI STEM 1 ISOL ATION VLV WAS ROUTED WITH ADS SYSTEM CONTROL CABLES. S EPARATION CRITERIA PER DESIGN NOTES WAS NOT MET.
DESIGN ERPOR WAS CAUSE OF OCCURRENCE.
ARCHTECT-ENGINEER WAS NOTIFIED OF HPCI/ ADS CABLE SEPARAT ION PROBLEft.
A/E IN PROCESS OF FORi1UL ATING PROPOSED DESIGN CHANGE.
EDWIN I. HATCH-2 05000366 090379 WHILE PERFORt1ING ROUTINE CALIBRATION PROCEDURE HNP-2-5202, BARTON MODELS EMERG CORE COOLING SYS + CONT 79-101/03L-0 091779 288A AND 239A DIFFERENTIAL PRESSURE INDICATING SWITCH, THE HIGH LEVEL S INSTRUMENTATION + CONTROLS 026830 30-DAY WITCHES OF 2B21-N017B AND 2B21-N017D WERE FOUND TO EXCEED THE TECH SPEC SWITCH LIMIT BY APPROXIMATELY 0.5 INCHES.
THESE SWITCHES ISOLATE HPCI AT +58 I COMPONENT FAILURE NCHES OF REACTOR WATER LEVEL.
THERE WAS NO EFFECT ON THE ENVIRONS. AS INSTRUMENT If1ILAR OCCURRENCE WAS REPORTED FOR 2B21-N017C ON LER 2-78-67.
BARTON INSTRU CO.,
DIV 0F ITT SETPOINT 3 RIFT WAS DETERMINED TO BE THE CAUSE OF THE FAILURE. THE INSTR UTIENTS WERE RECALIBRATED AND RETURNED TO SERVICE.
EDWIN I. HATCH-2 05000366 090579 WHILE AT APPROX. 89% POWER DURING A LOAD INCREASE, CMPF WAS FOUND TO BE REACTOR CORE 79-100/03L-0 091779 2.570. LIMIT IS 2.38. FLOW INCREASED & A COMPUTER UPDATE CERFORMED TO RE CCMPONENT CODE NOT APPLICABLE 026831 30-DAY DUCE CMPF. AFTER 2 HRS, POWER HAD NOT DROPPED SIGNIFICANTLY 8 APRMS HAD SUBCCMPONENT NOT APPLICABLE NOT BEEN ADJUSTED IN VIOLATION OF T/S 3.2.2.
FGLLOWING 2 HRS, ROD PATTER PERSONNEL ERROR N WAS ADJUSTED & ANOTHER COMPUTER UPDATE WAS PERFORMED. CMPF DROPPED TO OTHER W.105. THIS IS A REPETITIVE OCCURRENCE, SEE LER 2-79-58. THERE WERE NO C ITEM NOT APPLICABLE ONSEQUENCES TO THE HEALTH AND SAFETY OF THE PUBLIC.
FOLLOWING MOVEMENT OF CONTROL RODS, CMPF WAS FOUND TO EXCEED ITS LIMIT.
INITIAL CORRECTIVE ACTION TAKEN DID NOT SIGNIFICANTLY REDUCE CMPF & 2 HR TIME LIf1IT HAD ELAPSED BEFORE FURTHER ACTION WAS COMPLETED. ROD PATTERN WAS ADJUSTED & A COMPUTER UPDATE WAS PERFORMED WHICH CORRECTED PEAKING (J7 PROBLEM. PERSONNEL INVOLVED HAVE BEEN ADVISED THAT ACTION WAS INADEGUATE
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REPORT DATE/
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CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION EDWIN I. HATCH-2 05000366 090779 DURING NORMAL POWER OPERATION DRYWELL AVERAGE AIR TEMPERATURE WAS INCREA CNTNMNT HEAT REMOV SYS + CONT 79-103/03L-0 091979 SING BECAUSE OF A SUSPECTED STEAM LEAK.
WHILE MAINTENANCE PERSONHEL WER COMPONENT CODE NOT APPLICABLE 026854 30-DAY E ADJUSTING FLOU THE AVERAGE DRYWELL TEMPERATURE REACHED 145.8 DEG. F.
S SUBCOMPONENT NOT APPLICABLE YSTEM FLOW WAS READJUSTED AHD TEMPERATURE WAS RETURNED TO T.S. 3.6.1.7.
PERSONNEL ERROR LIMITS.
THE SAME CONDITION OCCURRED ON 9-8-79 WHEN CHILLER UNITS WERE B MAINTENANCE & REPAIR PERSONNEL EING SWAPPED.
THIS IS A REPETITIVE OCCURREHCE AS NOTED IN LER 79-81 ITEM NOT APPLICABLE MAINTENANCE PERSONNEL WERE ADJUSTING CHILLED WATER FLCU THROUGH REACTOR BLDG CHILLER COOLER TO ACHIEVE LESS FLCU AT A LOWER TEMP TO LOUER DRYWEL L TEMP. THIS CAUSED DRYWELL TEMP TO INCREASE TO 14 5.8 DEG.
F.
FLOW WAS R EADJUSTED TO REDUCE DRYWELL AVERAGE TEMP. OH 9-8-79 PLANT PERSONNEL UERE SWAPPING CHILLER UNITS & 2ND UNIT DID HOT START.
EDWIN I. HATCH-2 05000366 091279 DURING STARTUP OPERATIONS, HYDROGEN GAS CONCENTRATION INCREASED GREATER CNTHMNT COMBUS GAS CONTROL SYS 79-095/03L-0 091979 THAN T.
S. APPENDIX B SECTIDH 2.1.3.H LIMIT OF 4%.
HYDROGEN CONCENTRATI RECOMBINERS 026852 30-DAY ON EXCEEDED 4% FOR APPROXIMATELY IS MINUTES. ON 9-15-79 AT 1391 MUE PRE SUBCOMPONENT NOT APPLICABLE HEATER PROBLEMS CAUSED HYDROGEN TO EXCEED 4% FOR APPROXIMATELY 30 MINUTE DESIGN / FABRICATION ERROR S.
THIS IS A REPETITIVE OCCURRENCE AS REPORTED OH LER 79-78.
THERE WER DESIGN E NO EFFECTS UPON THE PUBLIC HEALTH AND SAFETY DUE TO THESE EVENTS.
CATALYTIC INC.
PROBABLE CAUSE FOR EVENT ON 9-12-79 IS THAT WHILE PREHEATING OFFGAS LINE S MOISTURE ENTERED RECOMBINER THUS REDUCING ITS RECOMBINING CAPASILITY.
PROBABLE CAUSE FOR EVENT ON 79 IS THAT PREHEATER TEMPERATURE WAS N OT SUFFICIENT TO PREVENT MOIS.URE FRCM ENTERING RECOM3INER & REDUCED ITS RECOMBINING CAPABILITY. SWAPPED PREHEATERS & RECOMBINERS TO CORR. PROBL EDWIN I. HATCH-2 05000366 091279 THE HPCI FLOW CONTROL LOOP WAS FOUND TO BE INOPERATIVE. THIS DEFICIENCY EMERG CORE COOLING SYS + CONT 79-096/03L-0 091979 WOULD HOT ALLOW THE SYSTEM TO PERFORM ITS DESIGNED FUNCTION IN MANUAL 0 INSTRUMENTATION + CONTROLS 026853 30-DAY R AUTO.
THERE WAS NO AFFECT ON THE ENVIRONS. THERE HAVE BEEN NO PREVIO CONTROLLER US REPORTS OF SIMILAR OCCURRENCES.
COMPONENT FAILURE INSTRUMENT WOODWARD GOVERNOR CO.
INVESTIGATIONS REVEALED A BAD RAMP GENERATOR IN TURBINE CONTROL LOOP.
R AMP GENERATOR WAS REPLACED AND CONTROL LOOP FUNCTIONALLY TESTED TO ENSUR E PROPER OPERATION. MODE OF FAILURE OF RAMP GENERATOR UOUL D HAVE BEEN D ETECTED DURING ROUTINE OPERABILITY TESTING DUE TO INABILITY TO MOVE TURB INE CONTROL VALVE TO POSITIONS GREATER THAN 40% CPEN.
EDWIN I.
HATCH-2 05000366 091579 THE OXYGEN BOTTLE PROVIDING THE SOURCE OF REAGENT GAS FOR THE HYDROGEN A CNTNMNT COMBUS GAS CONTROL SYS 79-104/03L-0 100379 NALYZERS (2P33-P001A AND 2P33-P001B) WAS FOUND TO BE EMPTY.
THE EMPTY B INSTRUMENTATION + CONTROLS 026951 30-DAY OTTLE RESULTED IN THE ANALYZERS BEING INOPERATIVE. THERE WAS HO EFFECT OTHER ON THE ENVIRONS. THERE HAVE BEEH NO SIMILAR OCCURRENCES OF THIS TYPE.
OTHER HOT APPLICABLE DELPHI INDUSTRIES ANALYZERS WERE INOP BECAUSE THEY HAD NO REAGENT GAS FLOW TO HYDROGEN CEL LS.
NEW BOTTLE OF GAS INSTALLED & ANALYZERS RETURMED TO OPERABLE STATUS STANDING ORDER HAS BEEN WRITTEN TO SURVEY USAGE OF REAGENT GASES TO D (J7 ETERMINE FREQUENCY NEEDED FOR REPLACING GAS BOTTLES.
PROCEDURE HNP-2-10 a3g 60, DAILY ROUNDS WILL BE REVISED TO INCLUDE FREQ. CHECKS OF GAS PRESSURE W
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FACILITY / SYSTEM / COMPONENT /
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CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTIDH EDWIN~I. HATCH-2 05000366 091879 WHILE PERFORMIf:S ROUTINE SURVEILLANCE PROCEDURE HNP-2-3106, MAIN STEAM L CNTHMNT ISOLATION SYS + CONT 79-102/03L-0 092579 INE FLOW INSTRUMENT FUNCTIONAL TEST AND CALICRATION. INSTRUMENT SETPOINT INSTRUMENTATION + CONTROLS 026946 30-DAY S FOR 2B21-N006A, 2B21-H006B, 2B21-N006D AND 2B21-N007A UERE FOUHD TO EX SWITCH CEED THE TECH. SPEC. LIMIT.
2B21-N006A, 2B21-H007B-D, 2D21-H008A-D AND COMPONENT FAILURE 2B21-N009A-D WERE OPERABLE WITH SETPOINTS WITHIH THE TECH. SPEC. LIMIT.
INSTRUMENT THERE WAS NO EFFECT ON THE ENVIRONS.
THERE HAVE LEEN NO PREVIOUS OCCUR BARTON INSTRU CO., DIV 0F ITT RENCES OF THIS TYPE.
SETPOINT DRIFT DETERMINED TO BE CAUSE OF EVENT.
INSTRUMENTS WERE RECALI BRATED & RETURNED TO SERVIC
E. PROCEDURE
S FOR SURVEILLANCE 2 CALIBRATION REVIEWED FOR FACTORS WHICH UQULD ATTRIBUTE TO MULTIPLE DRIFTS BUT NONE FOUND.
SETFOINT WAS CONSIDERED TO NEED MOVING TO A MCRE CONSERVATIVE PO INT.
SETPOINT WILL BE CHANGED ON HEXT REGULAR SURVEILLANCE TEST.
FITZPATRICK-1 05000333 012479 AN APPARENT EXCESSIVE SOLUTE RELEASE FROM THE MAKEUP UATER TREATMLUT WAS DEMIN WATER MAKE-UP 79-005/04L-0 021479 TE NEUTRALIZER TANKS TO THE CIRCULATING WATER DISCHARGE TUNNEL WAS DETEC COMPONENT CODE NOT APPLICABLE 026805 30-DAY TED DURING 01/79 24-HOUR COMPOSITE SAMPLE ANALYSIS. CONCENTRATION OF SU SUBCOMPONENT NOT APPLICABLE LFATE WAS GREATER THAN 5% ABOVE LAKE ONTARIO AM3IENT (INTAKE) CONC.
DEFECTIVE PROCEDURES NOT APPLICABLE ITEM NOT APPLICABLE CALCULATIONS INDICATE THAT ETS COULD HOT HAVE BEEN EXCEEDED. COMPOSITE SAMPLING OF CIRC. WATER SYSTEM DISCHARGE TUNNEL AND METHOD OF DETERMININ G SOLUTE CONC AND TOTAL DISSOLVED SOLIDS ARE UNSOUND. TECHNICAL SPECIFI CATION AMENDMENT REGUEST INITIATED.
FITZPATRICK-1
'05000333 021479 DURING NORMAL OPERATION, DRYWELL ATMOSPHERE SAMPLE ISOLATION VALVE 27-S0 REACTOR CONTAINMENT SYSTEMS 79-011/03X-1 091179 V-123B DID NOT INDICATE OPEH.
INSPECTION SHOMED A BLOWN FUSE DUE TO A 5 VALVES 025348 OTHER HORTED VALVE SOLENDID. SOLENDID WAS REPLACED BUT AGAIN SHORTED.
GLOBE COMPONENT FAILURE OTHER ATK0MATIC VALVE CO.,
INC.
APPARENTLY A FLUX WASHER WAS MISSING IN PREVIOUS VALVE SOLENDID ASSEMBLI ES.
A NEW SOLENDID COIL AND FLUX WASHER WAS INSTALLED WHICH HAS SOLVED THE PROBLEM.
FITZPATRICK-1 0S000333 031579 DURING A LOAD REDUCTIDH TO A COLD SHUTDOWN CONDITION, THE ROD SEQUENCE C OTHR INST SYS REQD FOR SAFETY 79-015/03X-1 091179 ONTROL SYSTEt1 FAILED TO PASS TEST F-ST-23A.
THERE UAS ILSUFFICIENT TIME INSTRUMENTATIDH + CONTROLS 025542 OTHER TO REPAIR THE SYSTEM (DUE TO TIME LIMITATIUNS TO COLD SHUIDOWN IMPOSED OTHER IN A 3/13/79 NRC SHOW CAUSE ORDER) 50 REACTOR WAS MANUALLY SCRAMMED FROM COMPONENT FAILURE ABOUT 21% OF RATED POWER.
ELECTRONIC GENERAL ELECTRIC CO.
RSCS WAS REPAIRED BY REPLACING CERTAIN PRINTED CIRCUIT BOARDS AND PROPER OPERATION WAS DEMONSTRATED BY SUCCESSFUL COMPLETI0H OF TES7 F-ST-23A ON 8/24/79.
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REPORT DATE/
EVENT DESCRIPTION /
,CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION
-FITZPATRICK-1 05000333 052479 DURING A REVIEW IN RESPONSE TO NRC BULLETIN 79-02. IT WAS FOUND THAT THE COOL SYS FOR REAC AUX + CONT 79-033/03X-1 091179 REACTOR BUILDING COOLING SYSTEM SUPPLY AND RETURN LINES TO DRYWELL EQUI COMPONENT CODE NOT APPLICABLE 026073 OTHER PMENT DRAIN SUMP DID HOT HAVE A SEISMIC STRESS ANALYSIS PERFORMED. PLAN SUBCOMPONENT NOT APPLICABLE T IS IN COLD SHUTDOWN CONDITICN.
OTHER HOT APPLICABLE ITEM NOT APPLICABLE REANALYSIS IS COMPLETE AND REVEALED THAT THE EXISTING DESIGN CONFIGURATI ON IS ACCEPTADLE WITHOUT MODIFICATION TO EITHER THE LINES OR SUPPGRTS.
THEREFORE, THE EVENT DID NOT REPRESENT ANY HAZARD TO PU2LIC HEALTH OR SA FETY.
FITZPATRICK-1 05000333 081079 DURING ANNUAL FIRE PUMP PERFORMANCE TESTING, THE OPERATION OF THE DIESEL FIRE PROTECTION SYS + CONT 79-047/03L-0 090679 DRIVEN FIRE PUMP RELIEF VALVE, WHILE SATISFACTORY, APPEARED TO CE SLUGG VALVES 026758 30-DAY ISH IN NATURE.
THE REDUNDANT ELECTRIC MOTOR DRIVEN FIRE PUMP WAS OPERAB CHECK LE.
COMPONENT FAILURE MECHANICAL LONERGAN THE RELIEF VALVE SPRING AND STEM ASSEMBLY WAS REPLACED, VALVE REASSEMBLE D AND TESTED SATISFACTORY.
FITZPATRICK-1 05000333 081579 IT WAS FOUND THAT THE TRIP POINTS FOR THE L.0W-LOW-LOW WATER LEVEL INSTRU OTHER COOLANT SUBSYS + CONTROL 79-048/03L-0 090779 MENTS SHOULD BE READJUSTED TO A MORE CONSERVATIVE SET POINT IN ORDER TO INSTRUMENTATION + CONTROLS 026757 30-DAY PRECLUDE POSSIBLE INSTRUMENT ERRORS AS A RESULT OF CERTAIN HYFOTHETICAL SENSOR / DETECTOR / ELEMENT CONDITIONS.
OTHER NOT APPLICABLE YARWAY CORP.
INSTRUMENT SET POINTS WERE RECALCULATED. THE CALCULATIONS WERE REVIEWED AND VERIFIED FOR ACCURACY BY GENERAL ELECTRIC.
FITZPATRICK-1 05000333 081979 CONTROL ROD 22-07 C0b: n NOT BE POSITIVELY SHOUN 10 BE COUPLED TO THE DRI REACTIVITY CONTROL SYSTEMS 79-049/03L-0 091879 VE DURING ROD DRIVE VENT & TIMING TEST.
ATTEMPT TO RECCUPLE ACCORDING T OTHER COMPONENTS 026860 30-DAY 0 PLANT PROCEDURES DID NOT RESULT IN POSITIVE COUPLING INDICATION. REAC SUBCOMPONENT NOT APPLICABLE TOR WAS IN REFUEL MODE AT TIME.
NO OTHER RODS WITHDRAWH.
OTHER NOT APPLICABLE GENERAL ELECTRIC CO.
CONTROL ROD DRIVE WAS REMOVED AND REPLACED. OLD DRIVE WILL BE INSPECTED TO DETERMINE POSSIBLE CAUSE. WHEN WORK IS COMPLETE, FOLLOW UP REPORT U ILL BE SUBMITTED.
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EVENT DESCRIPTIOH/
CAUSE SUBCCDE/ MANUFACTURER CONTROL HO.
REPORT TYPE CAUSE DESCRIPTION FITZPATRICK-1 05000333 082879 WHILE CONDUCTING SURVEILLANCE TEST F-ST-11 THE OFF GAS PROCESS RADIATION PRCSS + EFF RADIOL MONITOR SYS 79-050/03L-0 092079 MOHITOR, THE RECORDER (17-RR-152) DID NOT CCRRESPOND TO THE READING ON INSTRUMENTATION + CONTROLS 026861 30-DAY THE "A" CHANNEL MONITOR. REDUNDANT INSTRUMENT WAS OPERABLE.
RECORDER COMPONENT FAILURE ELECTRONIC GEHERAL ELECTRIC CO.
RECORDER WAS RECALIBRATED AND PROPER OPERATION WAS VERIFIED BY SUCCESSFU L COMPLETION OF TEST.
FITZPATRICK-1 05000333 082979 THE ACTIVITY LEVEL OF MN-54 IN MOLLUSK SAMPLES ON-SITE WAS FOUND TO BE G SYSTEM CODE NOT APPLICABLE 79-051/04T-0 091979 REATER THAN 10 TIMES THE CONTROL LOCATIONS OFF-SITE FOR THE SAME St.MPLE COMPONENT CODE NOT APPLICABLE 026918 2-WEEK PERIOD.
A POSSIBLE EXPLAHATION COULD BE THE VERY HIGH BI0 ACCUMULATION F SUBCOMPONENT NOT APPLICABLE ACTOR OF MANGANESE IN FRESH WATER MOLLUSKS ONE INDIGENDUS TO THE OFF-SHO OTHER RE AREA 0F THE SITE.
NOT APPLICABLE ITEM NOT APPLICABLE THE FRESH WATER MOLLUSKS ARE NOT CONSUMED BY HUMANS.
EVEN IF THEY WERE, BASED ON AVERAGE HUMAN CONSUMPTION OF SEAFOOD, THE DOSE WOULD BE ONLY 0
.0005 MREM /YR AND 0.0074 MREM /YR TO THE WHOLE BODY AND GASTR 0 INTESTINAL TRACTS, RESPECTIVELY.
FITZPATRICK-1 05000333 083079 A/E NOTIFIED PLANT MANAGEMENT ABOUT POSSIBLE CABLE SEPARATION IRREGULARI EMERG CORE COOLING SYS + CONT 79-046/03T-0 091279 TIES WITHIH HPCI AFTER DISCOVERY AT OTHER BMR.
CABLE FOR HPCI STEAM SUP ELECTRICAL CONDUCTORS 026846 2-WEEK PLY ISOLATIDH VALVE AND APS CABLES WERE ROUTED IN SAME CABLE TRAYS.
THI SUBCOMPONENT HOT APPLICABLE S DOES NOT MEET DESIGN SPEC. FOR SEPARATION OF DIVISION I AND DIVISION I DESIGN / FABRICATION ERROR I EQUIPMENT.
CONSTRUCTION / INSTALLATION ITEM NOT APPLICABLE DESIGN ERROR WAS CAUSE OF OCCURRENCE. PLANT MODIFICATION WAS IMPLEMENTE D AND CABLES REROUTED ERROR TO PLANT STARTUP.
FITZPATRICK-1 05000333 083079 DURING CONDUCT OF " CIRCULATING WATER SYSTEM WATER TEMP. RTD'S" THE CALCU CIRCULATING WATER SYS + CON 79-052/04L-0 092579 LATIONS FOR IHLET TEMP AND DISCHARGE DIFFERENTIAL TEMP WERE OUT OF CALIB INSTRUMENTATION + CONTROLS 026847 30-DAY RATION.
ACCURACY WAS NOT WITHIN 0.5 DEGREES F AS REOUIRED BY T.S.
DRIF OTHER T WAS IN CONSERVATIVE DIRECTION.
COMPONENT FAILURE ELECTRONIC GENERAL ELECTRIC CO.
INSTRUMENTS WERE RECALIBRATED TO WITHIN T.S. LIMITS AND CALCULATIONS PER FORMED AND VERIFIED TO BE SATISFACTORY.
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CAUSE SUBCODE/t1ANUFACTURER CCNTROL NO.
REPCRT TYPE CAUSE DESCRIPTION FITZPATRICK-1 05000333 090179 PEHETRATICN SLEEVE NOT SEALED.
FIRE WATCH MAINTAINED DURING TIME SLEEVE FIRE PROTECTION SYS + CONT 79-053/03L-0 092579 WAS NOT SEALED.
SLEEVE WAS REMOVED TO ALLOW PULLING OF HEW CABLES.
OTHER COMPONENTS 026848 30-DAY SUBCOMPONENT NOT APPLICABLE OTHER NOT APPLICABLE ITEM NOT APPLICABLE SEAL MATERIAL RECEIVED AND PENETRATION SEALED ON 9-17-79.
FITZPATRICK-1 05000333 090279 DURING SURVEILLANCE TEST F-ST-12D (RADWASTE BUILDING EXHAUST MONITOR INS T1AIN STEAM ISOL SYS + CONTROLS 79-055/03L-0 092679 TRUMENT FUNCTIONAL TEST), THE " A" R ADWAST E BUILDING EXH AUST MONITOR ( 17-INSTRUMENTATION + CONTROLS 026919 30-DAY RIS-458A) UAS FOUND OUT OF CALIBRATION. THE REDUNDANT INSTRUMENT (17-RI OTHER S-450B) WAS VERIFIED OPERABLE.
COMPONENT FAILURE ELECTRCHIC NUCLEAR MLASUREMENTS CORP.
THE INSTRUMENT WAS REPAIRED, RECALIBRATED AND SATISFACTORY OPERATION WAS DEMONSTRATED BY THE SUCCESSFUL COMPLETION OF F-ST-12D.
FITZPATRICK-1 05000333 090279 DURING SURVEILLANCE TEST F-ST-12B (REACTOR BUILDING EXHAUST MONITOR FUNC MAIN STEAM ISOL SYS + CONTROLS 79-054/03L-0 092679 TIONAL TEST). THE "B" REACTOR BUILDING EXHAUST MONITOR (17-RIS-452B) WAS INSTRUMENTATION + CONTROLS 026920 30-DAY FOUND OUT OF CALIBRATION. THE REDUNDANT INSTRUl1ENT (17-RIS-452A) WAS V OTHER ERIFIED OPERABLE.
CCMPONENT FAILURE ELECTRONIC NUCLEAR MEASUREMENTS CORP.
THE INSTRUMENT WAS RECALIBRATED AND SATISFACTORY OPERATION WAS DEMONSTRA TED BY THE SUCCESSFUL COMPLETI0H OF F-ST-12B.
FITZPATRICK-1 05000333 090379 THE HPCI SYSTEM TURBINE WAS INTENTIONALLY UNCOUPLED FROM THE PUMP TO AL EMERG CORE C00LIiG SYS + CONT 79-058/03L-0 100179 LOW OVER SPEED TESTING OF THE TURBINE IN ACCORDANCE WITH F-ST-4K (HPCI T PUMPS 026921 30-DAY URBINE OVER SPEED TESTING).
THIS ACTICH WAS REQUIRED BY THE INSURANCE U CENTRIFUGAL HDERWRITERS.
THE DISABLING WAS DONE AT A PRESSURE OF LESS THAN 150 PSIG OTHER 50 THERE WAS HO SAFETY HAZARD.
NOT APPLICABLE TERRY STEAM TURBINE COMPANY THE TEST WAS SATISFACTORY. AFTER THE TEST, THE PUMP AND TURBINE WERE RE COUPLED AND THE SYSTEM DEMONSTRATED OPERABLE.
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CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION FITZPATRICK-1 05000333 090479 A LEAKING CELL WAS NOTED IN STATION BATTERY "B"-
THE CELL WAS INTENTION DC ONSITE POWER SYS + CONTROLS 79-059/03L-0 100279 ALLY JUMPERED UNTIL A REPLACEMENT COULD BE OBTAINED. JUMPERING OF THE C GTHER COMPONENTS 026922 30-DAY ELL CAUSES THE BATTERY TO BE OPEN-CIRCUITED FOR A SHORT TIME PERIOD AND SUBCOMPONENT NOT APPLICABLE THEREFORE MAKES THE ENTIRE BATTERY IHOPERABLE. THE OTHER BATTERY, AND I COMPONENT FAILURE TS ASSOCIATED EQUIPMENT WERE VERIFIED OPERABLE.
ELECTRICAL GOULD-NATIONAL BATT WHEN A REPLACEMENT CELL IS AVAILABLE AND PLANT CONDITIONS PERMIT, THE CE LL WILL BE REPLACED.
FITZPATRICK-1 05000333 090479 DURING REVIEW OF UPDATED FUEL PARAMETERS, A CHANGE IN THE VALUE OF THE T SYSTEM CODE NOT APPLICABLE 79-060/03L-0 100379 EMPERATURE COEFFICIENT OF REACTIVITY WAS NOTED.
REVIEW OF SHUT DOWN MAR COMPONENT ; DE NOT APPLICABLE 026923 30-DAY GIN DEMONSTRATION USING THE NEW VALUE SHOWED THE REACTIVITY INSERTION NE SUCCOMPONENT NOT APPLICABLE EDED TO DEMONSTRATE THE SHUTDOWN VALUE WAS ABOUT 0.05% DELTA K LARGER TH OTHER AN VALUE ACTUALLY USED DURING DEMONSTRATION PERFORMED AT BEGINNING OF TH NOT APPLICABLE E CURRENT FUEL CYCLE.
ITEM NOT APPLICABLE RECALCULATION SHOWED THAT THE SHUT DOWN MARGIN CAPABILITY AT BEGINNING 0 F THE CYCLE WAS GREATER THAN 1% COMPARED TO VALUE OF R+ 0.38% REQUIRED B Y
T.S.,
THEREFORE, THERE WAS NO SIGHIFICANT SAFETY HAZARD.
FITZPATRICK-1 05000333 090579 DURING HPCI SUB-SYSTEM LOGIC FUNCTIONAL TEST. IT WAS NOTED THAT SWITCH N EMERG CORE COOLING SYS + CONT 7 9-0 61/ 0 3 L -0 100379 0.
3 ASSOCIATED WITH LEVEL INSTRUMENT 02-3-LIS-72D DID NOT PROPERLY PICK INSTRUMENTATION + CONTROLS 026924 30-DAY UP ITS FOLLOWER RELAY WHEN THE STATE OF SWITCH NO. 3 WAS CHANGED AS PAR SWITCH T OF THE TEST.
THE OTHER 3 SUITCHES (INCLUDING THE REDUNDANT CHANNEL) A DEFECTIVE PROCEDURES SSOCIATED WITH THE SAME PARAMETER WERE VERIFIED OPERABLE.
NOT APPLICABLE YARWAY CORP.
CAUSE DUE TO A WIRING ERROR DURING INSTALLATION OF A NEW SWITCH IN JUNE, 1979.
THE WIRING ERROR WAS CORRECTED AND PROPER OPERATION DEMONSTRATED THE TEST HAS BEEN REVISED TO REQUIRE VERIFICATION OF PROPER OPERATION OF THE FOLLOWER RELAY.
FITZPATRICK-1 05000333 090579 DURING TEST F-ST-4E (HPCI SUB-SYSTEM LOGIC FUNCTIONAL TEST) IT WAS NOTED EMERG CORE COOLING SYS + CONT 79-062/03L-0 100I79 THAT A PLUG IN INSTRUMENT 02-3-LIS-72A WAS LEAKING.
THE OTHER INSTRUME INSTRUMENTATION + CONTROLS 026925 30-DAY NTS MONITORING THE SAME PARAMETER WERE VERIFIED OPERABLE BEFORE ANY ATTE SWITCH MPT TO REPAIR THE LEAKING PLUG WAS MADE.
PERSONNEL ERROR NONLIC. OPERATIONS PERSONNEL YARWAY CORP.
THE REPAIR OF THE INSTRUMENT WAS COMPLETED ON THE SAME DAY AS THE DISCOV ERY.
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CAUSE SUBCODE/ MANUFACTURER CONTROL HO.
REPORT TYPE CAUSE DESCRIPTION FITZPATRICK-1 05000333 090679 DURING TEST (HPCI SUB-SYSTEM LOGIC FUNCTIONAL TEST), THE MOTOR ON THE SY EMERG CORE COOLING SYS + CONT 79-064/03L-0 100379 STEMS CONDENSATE STORAGE TANK SUCTION VALVE FAILED.
DURING REPAIRS, DUE COMPONENT CODE NOT APPLICABLE 027006 30-DAY TO A VALVE BEING IN A CLOSED POSITION, THE TORUS WAS NOT AUTOMATICALLY SUBCOMPONENT HOT APPLICABLE AVAILABLE TO THE HPCI SYSTEM FOR ABOUT 5 HOURS.
OTHER NOT APPLICABLE ITEM NOT APPLICABLE INADEQUATE COMMUNICATION BETWEEN PLANT MANAGEMENT AND OPERATIONS PERSOHN EL.
VALVE PLACED IN OPEN POSITIOH, MOTOR REPLACED, AND PROPER GPERATION DEMONSTRATED.
FITZPATRICK-1 05000333 090779 DURING TEST (FLOW BIAS FUNCTIONAL TEST). AVER AGE POWER RANGE F10NITOR ( AP OTHR INST SYS REQD FOR SAFETY 79-066/03L-0 100479 RM) CHANNELS A, D,
AND F TRIPPED AT A VALUE OF 120.5 COMPARED TO T.S. VA INSTRUMENTATIOH + CONTROLS 027004 30-DAY LUE 120% OF RATED POWER.
COMPUTATION MODULE PERSONNEL ERROR LICENSED 2 SENIOR OPERATORS GENERAL ELECTRIC CO.
INVESTIGATION COULD HOT REPRODUCE THE OUT OF TOLERANCE TRIP VALUES AND R ETEST OF THE INSTRUMENTS SHOWED THE TRIP POINTS TO BE WITHIN T.S.
LIMITS
. THEREFORE, THE APRM SYSTEM WAS RESTORED TO HORMAL.
FITZPATRICK-1 05000333 090779 THE ROD SEQUENCE CONTROL SYSTEM FAILED IN SUCH A MAHHER AS TO NOT ALLOW REACTIVITY CONTROL SYSTEMS 79-065/03L-0 100479 NORMAL CONTROL ROD INSERTION OR WITHDRAUAL.
THE SCRAM FUNCTION FOR CONT INSTRUMENTATION + CONTROLS 027005 30-DAY ROL RODS REMAINED UNAFFECTED. THE SYSTEM DID MAINTAIN CONTROL OF THE WI OTHER THDRAWAL SEQUENCE.
COMPONENT FAILURE INSTRUMENT GENERAL ELECTRIC CO.
FAILED RELAY ON ONE OF THE PRINTED CIRCUIT BOARDS ASSOCIATED WITH CONTRO L ROD GROUP 3.
THE RELAY WAS REPLACED.
FITZPATRICK-1 05000333 090879 WHILE ESTABLISHING DRYWELL TO TORUS DIFFERENTIAL PRESSURE REOUIRED BY T.
OTHER ENGNRD SAFETY FEATR SYS 79-068/03L-0 100479 S.
THE TORUS WATER LEVEL EXCEEDED THE MAXIr1Uf1 VENT PIPE SUBMERGENCE LIrlI COMPONENT CODE NOT APPLICABLE 026968 30-DAY TATIONS AS CONTAINED IN THE T.S.
MAXIMUM LEVEL WAS 0.33" ABOVE ALLOWED SUBCOMP0HENT NOT APPLICABLE FOR A PERIOD OF 9 MINUTES.
PERSONNEL ERROR LICENSED 8 SENIOR OPERATORS ITEM HOT APPLICABLE THE TORUS WAS IMMEDIATELY PUMPED DOWN TO RETURN THE LEVEL TO NORMAL.
AL SO, OPERATIONS PERSCHHEL WERE COUNSELED IN IMPORTANCE OF CONFORMING TO T
.S.
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REPORT TYPE CAUSE DESCRIPTION FITZPATRICK-1 05000333 090879 ON 9/10/79, 9/13/79. AHD 9/14/79. ROD BLOCK MONITOR "B" FAILED IN AN IHO REACTIVITY CONTROL SYSTEMS 79-059/03L-0 100579 PERABLE CONDITION.
IN EACH CASE, ROD BLOCK MONITOR "A" WAS DEMONSTRATED INSTRUMENTATION + CONTROLS 027002 30-DAY OPERABLE.
COMPUTATION MODULE COMP 0HENT FAILURE HATURAL END OF LIFE GENERAL ELECTRIC CO.
REPLACEMENT OF THE RELAY CARD ASSOCIATED WITH ROD BLOCK MOHITOR B ELIMIN ATED THE REPEATED FAILURES, AND PROPER OPERATIDH WAS DEMONSTRATED.
FITZPATRICK-1 05000333 090879 THE REQUIRED DIFFERENTIAL PRESSURE BETWEEN THE DRYWELL AND TORUS WAS NOT OTHER ENGNRD SAFETY FEATR SYS 79-067/03L-0 100479 ESTABLISHED WITHIN THE SPECIFIED TIME REQUIREMENTS (24 HOURS) 0F PLACIN COMPONENT CODE NOT APPLICABLE 027003 30-DAY G THE MODE SWITCH IN THE RUN POSITION.
THE DIFFERENTIAL PRESSURE WAS C0 SUBCOMPONENT NOT APPLICABLE MPLETED WITHIN 24 HOURS AND 15 MINUTZS.
PERSONNEL ERROR LICENSED 8 SENIOR OPERATORS ITEM NOT APPLICABLE OPERATIONS PERSONNEL WERE COUNSELED IN THE PROPER PROCEDURES.
FITZPATRICK-1 05000333 090979 IMPROPER INPUTS WERE NOTED AT THE "A" AND "C" LEVELS TO ROD BLOCK MONITO REACTIVITY CONTROL SYSTEMS 79-070/03L-0 100579 R
"A"-
THE INSTRUMENT WAS DECLARED IHOPERABLE AND THE REDUNDANT CHANNEL INSTRUMENTATION + CONTROLS 027001 30-DAY (ROD BLOCK MONITOR "B") WAS VERIFIED OPERABLE.
COMPUTATION MODULE COMPONENT FAILURE ELECTRONIC GEHERAL ELECTRIC CO.
FAILED INTEGRATED CIRCUIT. CIRCUIT WAS REPL ACED AND THE INSTRUf1ENT RECA LIBRATED AND RETURNED TO SERVICE.
FITZPATRICK-1 05000333 092279 THE PLANT STAFF WAS NOTIFIED BY THE ARCHITECT ENGINEER THAT A PIPE SUPPO COOL SYS FOR REAC AUX + CONT 79-074/01T-0 100579 RT ASSOCIATED WITH THE SERVICE WA(ER SYSTEM RETURN LINE FROM THE REACTOR HANGERS, SUPPORTS, SHOCK SUPPRSS 027000 2-WEEK BUILDING COOLING SYSTEM WAS CONSIDERED INOPERABLE IN ACCORDANCE WITH RE SUPPORTS QUIREMENTS OF THE 8/14/79 HRC LETTER LIFTING THE SHOW CAUSE ORDER OF 3/1 DESIGN / FABRICATION ERROR 3/79.
CONSTRUCTION / INSTALLATION STONE 8 WEBSTER ENG. CORP.
REPAIR AND MODIFICATIONS OF THE PIPE SUPPORT WERE COMPLETED WITHIH THE P RESCRIBED TIME FRAME AND THE PIPE SUPPORT IS t:0W CONSIDERED FULLY GPERAB LE.
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CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION FT. ST. VRAIN-1 05000267 072079 DURING PERFORMANCE OF SURVEILLANCE REQUIREMENT SR NR 2.1, ECOLOGICAL MON SYSTEM CODE NOT APPLICABLE 79-022/03L-0 091779 ITORING. AQUATIC MACR 0 INVERTEBRATE SAMPLES WERE NOT COLLECTED FROM THE S COMPONENT CODE NOT APPLICABLE 026892 30-DAY T.
VRAIN RIVER.
REVIEW OF PAST SAMPLE ANALYSIS INDICATES NO SIGNIFICANT SUBCOMP0HENT NOT APPLICABLE CHANGES WOULD HAVE BEEN EVPECTED.
REPORTABLE PER TECHNICAL SPECIFICATI PERSONNEL ERROR ON AC 7.5.2(B)3.
NO ACCOMPANYING OCCURRENCE OR PROBABLE CONSEQUENCES.
CONTRACT. & CONSULT. PERSONNEL NO EFFECT OH PUBLIC HEALTH OR SAFETY.
ITEM NOT APPLICA3LE AN OVERSIGHT ON THE PART OF CONTRACT AGENT SAMPLING PERSCHNEL RESULTED I N FAILURE TO COLLECT THE REQUIRED SAMPLES.
SAMPLING WAS RESUMED AND WIL L CONTINUE ON A BI-WEEKLY BASIS BEGINHING JULY, 1979.
FT. ST. VRAIN-1 05000267 080479 ON THREE OCCASIDHS DURING PERIOD AUG 4, 1979, THROUGH AUG 16, 1979, TOTA COOLANT RECIRC SYS + CONTROLS 79-024/03L-0 083179 L PRIMARY COOLANT OXIDANTS (SUM OF WATER, CARBON MONOXIDE, 8 CARBON DIOX COMPONENT CODE NOT APPLICA5LE 026698 30-DAY IDE) EXCEEDED 10 PPM WITH CORE AVERAGE OUTLET TEMPERATURE GREATER THAN 1 SUBCOMP0HENT NOT APPLICABLE
,200 DEG F.
THIS CONSTITUTES OPERATION UNDER A DEGRADED MODE PERMITTED OTHER BY LCO 4.2.10 & IS REPORTABLE PER T.S.
AC 7.5.2(B)2.
NOT APPLICABLE ITEM N3T APPLICABLE LCO 4.2.10 PRIMARY COOLANT IMPURITY LIMITS WERE EXCEEDED DURING DRYING 0 UT OPERATIONS FOLLOWING FIRST REFUELING. A PREVIOUS DRYER BYPASS RESULT ING IN WATER INGRESS TO CORE
- BREAKTHROUGH OF PURIFICATION TRAIN CONTRI BUTED TO INCREASED OXIDANT LEVELS OBSERVED.
FT. ST. VRAIN-1 05000267 080679 DN AUG 6, 1979, DURING STEADY STATE OPERATIONS AT 45% THERMAL POWER & 14 ONSITE POWER SYSTEM + CONTROL 79-025/03X-0 033179 5 MW ELECTRICAL POWER, "A" EMERGENCY DIESEL GENERATOR WAS FOUND IN A DEG RELAYS 026697 OTHER RADED MODE PER FT ST VRAIN T.S.
THIS IS REPORTABLE PER FT ST OTHER VRAIN T.S.
AC 7.5.2(3)2.
WHEN "A" DIESEL ENGIHE DECLUTCHED "B" DIESEL COMP 0HENT FAILURE ENGINE ALSO DECLUTCHED. REDUNDANT EQUIPMENT WAS OPERABLE & AVAILABLE. T NATURAL END OF LIFE HERE WAS HO EFFECT OH PUBLIC HEALTH OR SAFETY.
ITEM HOT APPLICABLE A RELAY FAILED DUE TO NORMAL END OF LIFE.
THE UNIT HAD BEEN TESTED SATI SFACTORILY THE PREVIOUS MONTH.
THE RELAY WAS REPLACED AND TESTED AND TH E SURVEILLANCE SUCCESSFULLY COMPLETED.
FT. ST. VRAIN-1 05000267 080779 WITH REACTOR OPERATING AT APPROXIMATELY 65% POWER, BEARING WATER MAKEUP COOLANT RECIRC SYS + CONTROLS 79-026/03L-0 033179 PUMP P-2105 WAS REMOVED FRCM SERVICE TO PERFORM A LINE REPAIR.
REPORTAB PIPES, FITTINGS 026696 30-DAY LE PER T.S.
AC 7.5.2(B)2 OPERATION UNDER DEGRADED MODE PERMITTED BY LCO LESS THAN 4 INCHES 4.2.2.
NO ACCOMPANYING OCCURRENCE OR PROBABLE CONSEQUEHCES. NO AFFECT COMPONENT FAILURE ON PUBLIC HEALTH OR SAFETY.
MECHANICAL CTHER A HOLE IN THE RECIRCULATION LINE TO THE PUMP REQUIRED THAT THE PUMP BE T AKEN OUT OF SERVICE FOR REPAIR.
THE LlHE WAS REPAIRED, INSPECTED, AND T HE PUMP RETURNED TO SERVICE.
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C AySE SUBCODE/MANUF ACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION FT. ST. VRAIN-1 05000267 081779 DURING NORMAL PLANT OPERATION WHILE COHHECTING A HEW INSTRUMENT, PLANT P DNSITE POWER SYSTEM + CONTROL 79-028/01T-0 083179 ERSOHHEL GROUNDED AN INSTRUMENT PANEL, BLOWING THE PANEL'S FUSES AND CAU COMPONENT CODE NOT APPLICABLE 026691 2-WEEK SING A VOLTAGE PERTURBATION ON INSTRUMENT BUS 2.
THIS EVENT RESULTED IN SUSCOM?0HENT NOT APPLICABLE A LOOP 1 SHUTDOWN, REACTOR SCRAM, AND A LOSS OF FORCED CIRCULATION FOR PERSONNEL ERROR APPROXIMATELY 3 MINUTES.
SIMILAR EVENTS WERE REPORTED IN RO 76-01, 77-1 MAINTENANCE 3 REPAIR PERSONNEL 4,
AND 79-17.
THERE WAS NO EFFECT ON PUBLIC HEALTH OR SAFETY.
ITEM NOT APPLICABLE THE GROUND WAS CAUSED BY PERSONAL ERROR OF A NON-LICENSED MAINTENANCE PE RSONNEL.
THE GROUHD WAS CORRECTED, POWER RESTORED TO THE INSTRUMENT PAN EL AND ACTION TAKEN TO RETURH THE PLANT TO NORMAL CONDITIONS. THE EFFEC TS OF THE UPSET ARE BEING ANALYZED.
FT. ST. VRAIN-1 05000267 081779 ON AUGUST 17, 1979. WHILE OPERATING AT APPROXIMATELY SD% OF RATED POWER COOLAHT RECIRC SYS + CONTROLS 79-027/01T-0 083179 IT WAS DETERMINED THAT A RECENT PIPE HANGER INSTALLATION ON PCRV COOLING HANGER 3, SUPPORTS, SHOCK SUPPRSS 026888 2-WEEK WATER LINES WOULD HAVE PREVENTED PROPER INSTALLATION OF PIPE SPOOLS TO HAMGERS HIGH TEMPERATURE FILTER ADSORBER COOLERS.
THESE ARE REQUIRED TO BE INST DESIGN / FABRICATION ERROR ALLED & OPERABLE WITii1N 1 t/2 HRS OF AN EXTENDED LOSS OF FORCED CIRCULAT CONSTRUCTICN/ INSTALLATION ION. THIS DOES NOT MEET REQUIREMENTS OF FORT ST. VRAIN TECHNICAL SPECIFI GENERAL ATOMIC CO.
CATIONS LCO 4.2.18 AND IS REPORTABLE PER AC 7.S.2(A)S.
HANGER ADDITIONS TO SYSTEM PIPING CAUSED PIPE ENDS TO CHANGE ALIGNMENT 8 MADE SPOOL PIECES INOPERABLE. SPOOL PIECES WERE MODIFIED TO FIT ON THE AVAILABLE PURIFICATIDH TRAIN AND WILL BE MODIFIED ON THE OTHER TRAIN AF TER IT IS REMOVED FROM SERVICE. THERE WAS NO EFFECT OH PUBLIC SAFETY OR HEALTH.
FT. ST. VRAIN-1 05000267 081979 DURING PLANT STARTUP WHILE "C" INSTRUMENT AIR COMPRESSOR WAS REMOVED FR0 COMPRESSED AIR SYSTEMS + CONT 79-029/03L-0 091779 M SERVICE FOR SCHEDULED INSPECTIOH, "B"
INSTRUMENT AIR COMPRESSOR BECAME VALVES 026927 30-DAY INOPERABLE. OPERATICH OF THE PLANT AT POWER WITH ONLY OHE INSTRUMENT A CHECK IR COMPRESSOR OPERABLE IS CONTRARY TO LCO 4.3.6.
THERE WAS NO EFFECT UP COMPONENT FAILURE ON THE HEALTH OR SAFETY OF THE PUBLIC.
BACKUP TO THE INSTRUMENT AIR SYS NATURAL END OF LIFE TEM WAS AVAILABLE FROM THE SERVICE AIR SYSTEM.
GARDNER-DENVER THE CAUSE OF IHOPERABILITY FOR "B" INSTRUMENT AIR COMPRESSOR WAS FAILURE OF THE DISCHARGE FEATHER VALVE.
ALL DISCHARGE VALVES ON THE COMPRESSOR WERE REPLACED. RETURNING THE INSTRUMENT AIR SYSTEM TO OPERABILITY WAS ACCOMPLISHED BY RETURNING "C" INSTRUMENT AIR COMPRESSOR TO SERVICE.
FT. ST. VRAIN-1 05000267 082179 ON SIX OCCASIONS DURING THE PERIOD AUGUST 21, 1979, THROUGH SEPTEMBER 1 COOLANT RECIRC SYS + CONTROLS 79-030/03L-0 092079 1979, TOTAL PRIMARY COOLANT OXIDAPTS (SUM OF WATER, CARBON MONOXIDE. AN CCMPONENT CODE NOT APPLICASL E 026909 30-DAY D CARBCH DIOXIDE) EXCEEDED TO PPM aiTH AVERAGE CORE OUTLET TEMPERATURE G SUBCCMP0hENT NOT APPLICABLE REATER THAN 1,200 DEG.
F.
THIS CONSTITUTES OPERATION UNDER A DEGRADED M OTHER ODE PERMITTED BY LCO 4.2.10 AND IS REPORTABLE PER TECHNICAL SPECIFICATI0 NOT APPLICABLE N AC 7.S.2(B)2.
NO EFFECT ON PUBLIC HEALTH OR SAFETY.
ITEM NOT APPLICABLE PRIMARY COOLANT IMPURITY LIMITS WERE EXCEEDED DURING THIS PERIOD AS A RE SULT OF DRYING OUT OPERATIONS AND AN EXTENDED REGENERATION PERIOD ON THE OFF-LINE HELIUM DRYER.
AT ANY TIME OXIDANTS DID HOT DECREASE IN TIME T 0 MAINTAIN LCO COMPLIANCE, CORE OUTLET TEMPERATURES WERE REDUCED.
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.CAUSE SUSCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION FT ST. VRAIN-1 05000267 082179 ON AUGUST 21, 1979, AND ON AUGUST 30, 1979, PLANT WAS OPERATED WITH REAC COOLANT RECIRC SYS + CONTROLS 79-031/03L-0 092079 TOR DEWPOINT GUTSIDE THE LIMITS OF LCO 4.2.11, FIGURE 4.2.11-1.
NO ACCO RELAYS 026932 30-DAY MPANYING EVENTS OR PROBABLE CCHSEGUEHCES. NO EFFECT OH PUBLIC HEALTH OR TIME DELAY, PNEUMATIC SAFETY.
REPORTABLE PER TECHNICAL SPECIFICATION AC 7.5.2(B)2.
SIMILAR COMPONENT FAILURE EVENTS HAVE BEEH REPORTED IN REPORTABLE OCCURRENCE REPORTS 76-06, 77-02, ELECTRICAL 77-13, 78-16, AND 78-39.
AGASTAT RELAY CO.
NO CAUSE FOR AUGUST 21, 1979, EVENT TRACEABLE TO PLANT OPERATION. EVENT OF AUGUST 30, 1979, WAS RESULT OF HELIUM DRYER BYPASS DUE TO FAULTY TIM E DELAY RELAY.
RELAY WAS REPLACED AND TESTED, AND THE DRYER RETURHED TO SERVICE.
FT. ST. VRAIH-1 05000267 082879 DURING HORMAL OPERATION WHILE ATTEMPTING TO NAKE AH AUTHORIZED RELEASE F SYSTEM CODE NOT APPLICABLE 79-033/03L-0 092079 ROM THE 1B GAS WASTE SURGE TANK, AN UNAUTHORIZED RELEASF WAS MADE FROM T VALVES 026908 30-DAY HE TA GAS WASTE SURG: TANK.
ON DISCOVERY OF THIS OCC. RELEASE WAS TERMI CLOLE HATED & VALVE LINEUP CORRECTED.
1A GAS WASTE SURGE TANK WAS SAMPLED 8 A PERSCNNEL ERROR NALYZED & RELEASE FOUND TO BE SELOW LIMITS OF LCO 4.8.1.
RELEASE OF RAD NONLIC. OPERATIONS PERSONNEL I0 ACTIVE GAS WASTE WITHOUT PRIOR SAMPLE 8 ANALYSIS IS CONTRARY TO LCO 4.
ITEM NOT APPLICABLE 8.1.
RO 78-22 SIMILAR. HD EFFECT ON HEALTH OR SAFETY OF THE PHBLIC.
THE WRONG VALVE LINEUP WAS MADE.
THE VALVES WERE POSITIONED FOR RELEASE FROM THE 1A GAS WASTE SURGE TAHK UHEN RELEASE FROM 1B WAS AUTHORIZED.
THE VALVE CHECK 0cF SHEETS WERE REVISED TO REQUIRE OPERATOR INITIALS FOR EACH INDIVIDUAL VALVE.
PERSOHNEL INVOLVED WERE ADMONISHED.
FT. ST. VRAIN-1 05030267 083179 A FIELD AUDIT AND PRELIMIHARY ENGINEERING ANALYSIS OF A RANDOM SAMPLE OF SYSTEM CODE NOT APPLICABLE 79-035/01T-0 091379 AS-BUILT SAFETY RELATED PIPING DRAWINGS SHOWED THAT SEVERAL HANGERS HAV HANGERS. SUPPORTS, SHOCK SUPPRSS 026902 2-WEEK E INCONSISTFHCIES THAT MAY JEOPARDIZE THE OPERABILITY OF THE ASSOCIATED HANGERS SYSTEMS IN THE EVENT OF A DESIGN BASIS EARTHOUAKE. BECAUSE OF THESE INC DESIGN / FABRICATION ERROR ONSISTENCIES THE FORT ST. VRAIN UNIT WAS SHUTDOWN OH SEPTEMBER 1,
1979.
DESIGN THIS APPEARS TO BE REPORTABLE PER FORT ST. URAIN TECHNICAL SPECIFICATION ITEM NOT APPLICABLE AC 7.5.2(A)9.
THERE WAS H0 EFFECT ON PUPt.IC HEALTH UR SAFETY.
THE CAUSE OF THIS PROBLEM IS DESIGH/ INSTALLATION INCONSISTENCIES WHICH C OULD JEOPARDIZE THE SYSTEMS INVOLVED.
THE EXACT EXTENT OF THE PROBLEM I S NOT YET CERTAIN AND AH INVESTIGATION IS CONTINUING. WHEN THE EXACT CA USE IS DETERMINED THE CORRECTIVE ACTION WILL EE DECIDED AND A REVISED LI CENSEE EVENT REPORT SUBMITTED.
H.
B.
ROBINSON-2 05000261 072479 CN JULY 24, 1979, BETWEEN 0000 8 0800. HOURLY FIRE PATROLS WERE NOT PERF FIRE PROTECTION SYS + CONT 79-024/03L-0 082379 ORMED AS REQUIRED UHEN PORTIONS OF FIRE DETECTION SYSTEM WERE INOPERABLE COMPONENT CODE NOT APPLICABLE 0?6701 30-DAY THESE PATROLS ARE REQUIRED BY." PROPOSED" T.S.
3.14.1.2.B, WHICH WE ARE SUBCOMP0HENT NOT APPLICABLE CONSIDERED TO BE IN EFFECT.
THEREFORE, THIS IS BEING REPORTED PER T.S.
PERSONNEL ERROR 6.9.2.3.
CONTRACT. 2 CONSULT. PERSONNEL ITEM NOT APPLICA3LE MIDHIGHT SHIFT FIRE PATROL FAILED TO REPORT FOR WORK DUE TO CAR TROUBLE.
EVENING SHIFT FIRE PATROL LEFT AT MIDNIGHT W/0 INFORMING SHIFT FOREMAN THAT HE HAD NOT BEEN RELIEVED. FIRE PATROLS WERE RESUMED BY DAY SHIFT FI RE PATROL AT 0800. ALL FIRE PATROLS WERE INSTRUCTED TO INFORM SHIFT FORE MAN IF THEIR RELIEF IS NOT PRESENT & HOT TO LEAVE TIL THEY ARE RELIEVED.
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CAUSE SUBCODE/MANUF%CTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION H.
B.
ROBINS 0H-2 05000261 073079 DN JULY 30, 1979, BETWEEN 0800 3 1000, HOURLY FIRE PATROLS WERE NOT PERF FIRE PROTECTION SYS + CCNT 79-025/03L-0 032379 ORMED AS REQUIRED WHEN PORTIONS OF FIRE DETECTION SYSTEM WERE INOPERABLE COMPONENT CODE NOT APPLICABLE 026700 30-DAY THESE PATROLS ARE REQUIRED BY " PROPOSED" T.S.
3.14.1.2.B.
THIS CONSTI SUBCOMP0HENT HOT APPLICABLE TUTES A REPORTABLE OCCURRENCE PER T.S.
6.9.2.B.
PERSONNEL ERROR CONTRACT. & CONSULT. PERSONNEL ITEM NOT APPLICABLE DAY SHIFT FIRE PATROL FAILED TO REPORT FOR WORK.
MIDNIGHT SHIFT FIRE PA TROL LEFT PLANT AT 0800 W/0 INFORMING SHIFT FOREMAN THAT HE HAD NOT BEEN RELIEVED.
FIRE PATROL INSPECTIONS WERE RESUMED AT 1100 HRS THAT DAY BY AH AUX. OPERATOR. PERSON WHO FAILED TO REPORT TO WORK WILL BE REPLACED CCHTRACTOR THAT LEFT HAS BEEN STERNLY COUNSELLED ON RESPONSIBILITIES.
H.
B.
ROBINS 0H-2 05000261 080279 WHILE PERFORMING REFUELING PERIODIC TEST ON 5/24/79, WHICH DEALS WITH HY REAC COOL CLEANUP SYS + CONT 79-026/03L-0 083179 DRAULIC SHOCK SUPPRESSORS (PT-31.0), OHE BLAW KNOX UNIT FAILED FUNCTIDHA HANGERS. SUPPORTS. SHOCK SUPPRSS 026692 30-DAY L TEST PORTION DUE TO BROKEN SHAFT WHICH OCCURRED DURING TEST.
$NUBBER SNUBSERS HAD BEEN INSTALLED CH CVCS PIPING 2 IS REQUIRED SY T.S.
3.13.1.
ON AUGU COM?CNENT FAILURE ST 2, 1979, AS A RESULT OF METALLURGICAL ANALYSIS PERFORMED ON FAILED SH OTHER AFT, IT WAS DETERMINED THAT THIS TYPE OF FAILURE COULD HAVE OCCURRED WHI TnMKINS-JOHNSON LE SNUBBER WAS IN SERVICE, THUS RENDERING IT IHOPERABLE.
THE FAILED SHUBBER WAS REPLACED BY A SPARE OF SIMILAR SIZE AND RATING.
THE FAILURE WAS CAUSED BY (1) INCORRECT SHAFl MATERIAL AS DETERMINED BY A METALLURGICAL ANALYSIS OF THE FAILED PART, AND (?' 00!SIBLE SIDE LOADI NGS IMPOSED ON THE SNUBBER DURING THE TEST SINCE ". FAILED SHAFT WAS SL IGHTLY BEHT.
H.
B.
ROBINSOH-2 05000261 080979 DURING NORMAL CPERATIONS ON 8/9/79, AT 1106 HRS VALVE SI-355 MECHANICALL CNTNMNT ISOLATION SYS + CONT 79-028/03L-0 091079 Y STUCK IN MID-TRAVEL AFTER ADDING HITROGEN TO ACCUMULATORS. VALVE IS A VALVES 026773 30-DAY CONTAINMENT AUTO ISOLATION 1 RIP VALVE & ITS FAILURE IS REPORTABLE UNDER GLOBE T.S.
6.9.2.BC2).
PEHETRATION WAS ISOLATED BY LOCKING CLOSED MANUAL VAL COMPONENT FAILURE VES WITHIN THE 4 HRS AS REQUIRED BY TECH. SPEC.
3.6.3.C.
THIS IS A CLOS MECHANICAL ED SYSTEM WITHIH CCHTAINMENT 8 THEREFORE WAS NOT A THREAT TO THE PUBLIC BLAW-KNOX COMPANY HEALTH CR SAFETY.
THE BLAW KNOX, ONE IHCH, GLOBE, AIR OPERATED, FAIL CLOSE, CARBON STEEL, 1500 POUND VALVE FAILED TO CLOSE DUE TO MECHANICAL BINDING. THE PARALLE L VALVES IN THE LINE DCWHSTREAM FROM CONTAIHMENT WERE LOCKED CLOSED TO S ATISFY CONTAINMENT ISOLATION CRITERIA. WHEN PLANT CCHDITIONS PERMIT, TH E BINDING IN VALVE 855 WILL BE CORRECTED.
H.
B.
ROBINSON-2 05000261 081479 ON AUGUST 14, 1979. BETWEEN 0100 AND 0530, THE HOURLY FIRE PATROLS WERE FIRE PROTECTION SYS + CONT 79-029/03L-0 091379 NOT CONDUCTED AS REQUIRED WHEN PORTIONS OF THE FIRE DETECTION SYSTEM WER COMPCHENT CODE NOT APPLICABLE 026901 30-DAY E INOPERABLE. THE PATROLS ARE REQUIRED BY " PROPOSED" TECHHICAL SPECIFIC SUBCOMPONENT NOT APPLICABLE ATION 3.14.1.2.B.
THIS WOULD CONSTITUTE A REPORTABLE OCCURRENCE PER TEC PERSONNEL ERROR HNICAL SPECIFICATION 6.9.2.B.
CONTRACT. & CONSULT. PERSONNEL ITEM NOT APPLICABLE THE MIDHIGHT SHIFT FIRE PATROLMAN FAILED TO CONDUCT HOURLY PATROLS BETWE EH 0100 4 0530.
WHEN ASKED, HE INFORMED SHIFT FOREMAN THAT HE WAS ILL D URING THIS TIME PERIOD.
HE WAS STRICTLY INSTRUCTED AGAIH ON IMPORTANCE lll 0F HOURLY PATROLS & HIS RESPONSIBLITIES. FIRE PATROLS WERE RESUMED AT T 425 HIS TIME 2 WERE PERFORMED PROPERLY THROUGHOUT REMAINDER OF THE SHIFT.
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REPORT TYPE CAUSE DESCRIPTION H. B. ROBIHSOH-2 05000261 052979 ON 8/29/79 AT 1119 HRS DURING HORMAL OPERATION AT 100% POWER, EDTH SWEP' STATION SERV WATER SYS + CONT 79-030/01T-0 091279 S RENDERED 00S WHEN "B" SUBP WAS SECURED &
"A" SWBP TRIPPED: HEITHER PUM PUMPS 026931 2-WEEK P COULD BE RESTARTED IMMED.
DURING THIS PERIOD, "D" SW P' IMP WAS 005 FCR CENTRIFUGAL ROUTINE MAINTENANCE.
THIS IS CONTRARY TO PARAGRAPH 3.2..
' 0F T.S.
3 C OTHER ONSTITUTES A REPORTABLE OCCURRENCE UNDER PARAGRAPH 6.9.2.A.
POWER RED NOT APPLICABLE UCTION WAS IMMEDIATELY COMNENCED. NO ADVERSE EFFECTS TO THL PLANT OR TO WORTHIHGTON CORP.
THE PUBLIC HEALTH OR SAFETY UCCURRED FROM THIS EVENT.
THE STARTING & STOPPING OF "B" SWBP APPAREHTLY CAUSED PRESSURE FLUCTUATI ONS WHICH TRIPPED "A" SWBP OH LOW SUCTIDH PRESSURC. BOTH PUMPS FAILED T 0 RESTART APPARENTLY BECAUSE OF LOW SERVICE WATER SYSTEM PRESSURE.
"D" SERVICE WATER PUMP WAS OUT OF SERVICE (005) FOR ROUTINE MAINTENANCE. A CHANGE IN DESIGN OF THE TRIPPING LOGIC FOR SUBP'S IS BEING CONSIDERED.
HADDAM HECK-1 05000213 012779 OH 01/27/79 WHILE PLANT WAS IN PROCESS OF SHUTTING DOWN FOR ROUTINE REFU CIRCULATING WATER SYS + CON 79-002/04L-0 021279 ELING, THE PLANT COMPUTER ALARMED, INDICATING A DISCHARGE TEMPERATURE RA COMPONENT CODE NOT APPLICABLE 026870 30-DAY TE OF CHANGE GREATER THAN THE ETS LIMIT OF 8 DEGREES F PER HOUR.
NO ENV SUBCOMPONENT NOT APPLICABLE IRONMENTAL IMPACT EXPECTED.
OTHER NOT APPLICABLE ITEM NOT APPLICABLE NO CORRECTIVE ACTION TAKEN.
HADDAM NECK-1 05000213 013179 AN ESTIMATED 279 SPOTTAIL SHINERS (HOTCRPIS HUDSONIUS)
>6" WERE IMPINGED CIPCULATING WATER SYS + CON 79-001/04L-0 020279 AS OF 01/31/79 EXCEEDING EIS LIMITS OF 25.
SPOTTAIL SHINERS ARE 2HD M0 COMPONENT CODE NOT APPLICABLE 026765 30-DAY ST ABUNDANT FISH IN CONNECTICUT RIVER AND ARE UNIMPORTANT COMMERCIALLY A SUBCOMPONENT NOT APPLICABLE ND FOR SPORT.
OTHER HOT APPLICABLE ITEM NOT APPLICABLE NO APPARENT CAUSE RELATED TO PLANT OPERATION. SEASCHAL TEMPERATURE CHAN GES APPARENTLY CONTRIBUTE TO INCREASED IMPINGEMENT DURING THE WINTER MON THS.
HADDAM NECK-1 05000213 021579 DIESEL FIRE PUMP WAS TO BE TESTED BEFORE REMOVING IT FROM SERVICE FOR IN FIRE PROTECTION SYS + CONT 79-003/03X-1 091179 SPECTION. WHEN UNIT WAS GIVEN START SIGNAL IT FAILED TO START.
INVESTI ENGINES, INTERNAL COMBUSTION 025479 OTHER GATIONS SHOWED THAT ONE COIL OF STARTER MOTOR BURNED OPEN.
THIS EVENT I SUBCOMP0HENT NOT APPLICABLE S REPORTABLE UNDER T.S.
6.9.2.BC2).
OPJRATING IN DEGRADED MODE PERMITTE COMPONENT FAILURE D BY LIMITING CONDITIONS FOR OPERATICN.
T.S.
3.22 REQUIRES A 30-DAY REP ELECTRICAL ORT IF IHOPERABLE UNIT IS NOT RETURNED TO SERVICE WITHIN 7 DAYS.
dMIT W DEkCO CO.
AS RETURNED TO SERVICE AFTER 12 DAYS.
REDUNDANT FIRE PUMP WAS OPLCA3LE.
AS DESCRIBED IN ORIGINAL LER. PUMP SHAFT WAS FROZEN IN BLOCK OF ICE.
(;q PREVENT THIS FROM HAPPEHING IN FUTURE, PLANT DESIGN CHANGE HAS EEEN APP 425 ROVED WHICH UILL ALLCW IHSTALLATION OF 1/2" LINE COMIHG OFF SERVICE H2O
(/4 HEADER TO BE RUH TO BOTH PUMP DISCHARGE COLUMNS TO PREVENT H2O If, COLUMH S FROM BECOMING STAGHANT. MODIFICATI0H INSTALLED PRIOR TO COLD UEATHER.
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_CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION HADDAM HECK-1 05000213 080379 WHI8.E PERFORMING A VISUAL INSPECTION OF CATEGORY I PIPING SYSTEM SUPPORT RESIDUAL HEAT REMOV SYS + CONT 79-008/01T-0 081479 S. AS PART OF IE BULLETIN 79-02, REV. 01, A SEISMIC TYPE PIPE SUPPORT WA HANGERS SUPPORTS, SHOCK SUPPRSS 026996 2-WEEK S FOUND TO BE MISSING (AC-ER-31), ON THE RESIDUAL HEAT REMOVAL PIPING (R SUPPORTS WL-152-7) SYSTE:1. INITIAL INVESTIGATION SHOWED THAT THE EXISTING SURROUN DESIGH/ FABRICATION ERROR DING SUPPORTS MIGHT NOT PROVIDE THE LOAD SUPPORT CAPABILITY SPECIFIED ON CONSTRUCTIOH/IHSTALLATION THE PIPING DRAWING. NO EFFECT ON THE HEALTH AND SAFETY OF THE FU3LIC WA STONE 1 WEBSTER EHG. CORP.
S EXPERIENCED.
THE PIPING DRAWING WAS REVISED, DURING CONSTRUCTION OF PLANT, TO ADD A S EISMIC TYPE PIPING RESTRAINT. HOWEVER, THE SEISMIC SUPPORT WAS NOT ADDED IN THE FIELD. THE SUPPORT WAS INSTALLED AT THE LOCATICH SHOW:4 ON THE PI PING DRAWING WITHIN 72 HOURS.
HADDAM NECK-1 OSC00213 083179 MANUFACTURER OF PL^NT EMERGENCY DIESEL CENERATORS HAS IDENTIFIED A POTEN EMERG GENERATOR SYS + CONTROLS 79-009/01T-0 091279 TIAL PROBLEM HITH TURBOCHARGER THRUST BEARING LUBRICATION. IF THE ENGINE ENGINE 5, INTERNAL COMBUSTION 026994 2-WEEK IS RESTARTEL WITHIH 15 TO 180 MINUTES OF A FREVIOUS HDT RUN, SCME EMEAR SUBCOMPONENT NOT APPLICABLE ING OF BEARING METAL MAY OCCUR. CUMULATIVE CAMAGE FROM SEVERAL SIMILAR S DESIGN /FAERICATION ERROR TARTS COULD RESULT IN TURD 0 CHARGER FAILURE. CERTAIN CHECKS OH LUBE OIL S MANUFAC10 RING YSTEM AFTER MAINTENANCE, TO EHSURE PROPER LUBRICATION, ARE ALSO NECESSAR ELECTRO - MOTIVE DIV. OF G. M.
Y.
NO EFFECT ON HEALTH & SAFETY OF PULLIC WAS EXPERIENCED.
DAMAGE TO TURE0 CHARGER THRUST BEARING COULD OCCUR LECAUSE MAIN LUBE OIL SYSTEM PUMP " PRIME" MAY NOT BE f1AINTAINED DURING THIS PERIOD. ALMINISTRA TIVE CCHTROLS HAVE BEEN INSTITUTED TO AVOID THESE TYPE CF STARTS 3 EH3UR E THAT AT LEAST ONE DIESEL IS AVAILABLE AT ALL TIMES. MANUFACTURER IS DE VELOPING MODIFICATION TO LUBRICATION SYSTEM.
INDIAN POINT-2 05000247 042878 TELEDYNE ISOTOPES, OUR CONTRACTING LAB, INFORMED CON EDISDN THAT THE ACT OTHER SYSTEMS 78-020/04T-0 060978 IVITY OF A WATER SAMPLE TAKEN FROM CA"? FIELD RESEVOIR ON 03/27/78 EXCEE COMPONENT CODE NOT AFPLICABLE 023643 2-WEEK DED 10 TIMES THE HISTORICAL LEVEL AT THIS LOCATION.
THIS EVENT DOES NOT SUBCOMPONENT NOT APPLICABLE HAVE ANY SIGNIFICANT ENVIRONMEN'#L CONSECUENCES, SINCE THE SAMPLE WA3 N EXTERNAL CAUSE CH-REPRESENTATIVE, AND THE VALIDITY OF THE RESULTS IS THEREFORE QUESTION NOT APPLICABLE ABLE.
ITEM NOT APPLICABLE THIS ANOMOLOUS SAMPLE ACTIVITY WAS CONSIDERED TO BE CAUSED BY NON-REPRES ENTATIVE SAMPLING TECHNIQUE IN CONJUNCTION WITH ADVERSE METEORLOGICAL CO HDITIONS ON THE DAY THE SAMPLE WAS TAKEN.
SAMPLING PROCECURES ARE BEING REVIEWED AND UPGRADED WHERE NECESSARY TO PREVENT A RECURRENCE OF THIS E VENT.
INDIAN POINT-2 05000247 010879 TELEDYNE ISOTOPES, OUR CONTRACTING LA30RATORY, PROVIDED CON EDISCN WITH OTHER SYSTEMS 79-002/04X-0 041879 A REPORT OH JANUARY 8, 1979 THAT THE ACTIVITY OF OUR PRECIPITATICH SAMPL COMPONENT CODE NOT APPLICABLE 026790 OTHER E TAKEN FROM EASTVIEW CN HOVEMSER 30, 1978 EXCEEDED TEN TIMES THE CONTRO SUBCOMPONENT NOT APPLICABLE L STATION LEVEL.
THIS E'!ENT DID NOT HAVE ANY EUVIRONMENTAL CCNSEQUENCES OTHER ATTRIBUTABLE TO PLANT OPERATIONS AT INDIAN POINT.
NOT APPLICABLE ITEM NOT APPLICABLE THE ANOMALOUS SAMPLE ACTIVITY WAS DETERMINED TO BE CAUSED BY TRITIUM REL L37 EASES FROM A SOURCE OTHER THAN INDIAN POINT.
THE NEW YORK STATE DEPARTM ENT OF ENVIRONMENTAL CCHSERVATION INVESTIGATED A MANUFACTURER IN THE VIC 45 INITY OF EASTVIEW STATION, WHICH hAS SINCE MODIFIED THEIR INSTALLATION T (ja O PREVENT A RECURRENCE OF THIS PROBLEM.
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[ FACILITY / SYSTEM / COMPONENT /
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EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL HD.
REPORT TYPE CAUSE DESCRIPTION INDIAN POINT-2 05000247 021379 TELEDYNE ISOTOPES, THE CONTRACTING LABORATORY, PROVIDED CON EDISON WITH OTHER SYSTEMS 79-012/04T-0 031479 A REPORT ON 2/13/79, THAT THE ACTIVITY OF THE PRECIPITATION SAMPLE TAKEN COMPONENT CODE NOT APPLICABLE 026804 2-WEEK FRCM EASTVIEW OH 1/2/79 EXCEEDED TEN TIMES THE CONTROL STATION LEVEL.
SUBCOMPONENT NOT APPLICABLE THIS EVENT DID NOT HAVE ANY ENVIRON!1 ENTAL CONSEQUENCES ATTRIEUTABLE TO P OTHER LANT OPERATIONS AT INDIAN POINT.
NOT APPLICABLE ITEM NOT APPLICABLE THE AHOMALOUS SAMPLE ACTIVITY WAS CAUSED BY TRITIUM RELEASED FROM A SOUR CE OTHER THAN INDIAH POINT.
THE NEW YORK STATE DEPARTMENT OF ENVIRONMEN TAL CONSERVATION INVESTIGATED A MANUFACTURER IN THE VICINITY OF EASTVIEW STATIGH, UHICH HAS SINCE MODIFIED THEIR INSTALLATION TO PREVENT A RECUR RENCE OF THIS PROBLEM.
INDIAN POINT-2 05000247 081779 LHILE SHUTDOWN FOR REFUELING, A REVIEW OF THE RESULTS OF SURVEILLANCE TE MAIN STEAM SYSTEMS + CONTROLS 79-021/03L-0 091479 ST /I-V1 (A) INDICATED THAT THE RESERVOIR ASSOCIATED WITH THE SHU3EER BA HANGERS, SUPPORTS. SHOCK SUPPRSS 026834 30-DAY HK LOCATED AT THE TOP OF THE SUPPORT STRUCTURE FOR HO. 24 STEAM GEHERATO SHUBBERS R HAD LESS THAN THE REQUIRED FLUID LEVEL - TECHHICAL SPECIFICATION 3.12.
COMPONENT FAILURE MECHANICAL GRIHNELL CORP.
TUBING FITTING LEAKAGE RESULTED IN FLUID LOSS FROM THE GRIHHEL 8" BORE, 5" STROKE, SHUBBER OIL RESERVOIR. FITTINGS WERE TIGHTEMED AND RESERVOIR REFILLED TO THE REQUIRED LEVEL.
TO PROVIDE FURTHER ASSURANCE THAT THE PROPER OIL LEVEL WILL BE MAINTAINED INCREASED SURVEILLANCE OF RESERVOIR FLUID LEVEL WILL BE PERFORMED.
INDIAN POINT-3 05000286 082379 WHILE OPERATING AT 85 PERCENT POWER, THE CONDENSATE STORAGE TANK LEVEL D CONDENSATE STORAGE FACILITIES 79-010/03L-0 092179 ROPPED BELOW THE 360,000 GALLON LIMIT DESIGHATED BY TECHNICAL SPECIFICAT COMPONENT CODE NOT APPLICABLE 026838 30-DAY ION 3.4.A(3) TO A LEVEL OF 342,000 GALLONS.
OUR USUAL DEMINERALIZED UAT SUBCOMPONENT NOT APPLICABLE ER SOURCE AT CONSOLIDATED EDISON (INDIAH POINT UNIT 1) UAS OUT OF SERVIC EXTERNAL CAUSE E FOR REPAIRS AT THE TIME.
SIMILAR EVENTS WERE REPORTED ON SEPTEMBER 2, HOT APPLICABLE 1978, SEPTEMBER 7, 1978, AND MARCH 27, 1979.
ITEM NOT APPLICABLE THE INCIDENT WAS CAUSED BY HORMAL USE OF THE STEAM GEHERATOR BLOWDCXN SY STEM, COMPOUNDED BY THE UNAVAILADILITY OF OUR STANDARD WATER SOURCE AT C ONSOLIDATED EDISON. WATER WAS SUPPLIED FROM AN ALTERNATE SOURCE AT THE INDIAH POINT 2 HOT WELL, AND THE CCHDENSATE STORAGE TANK LEVEL WAS RETUR HED TO SPECIFICATION WITHIN THE DESIGNATED 43-HOUR LIMIT.
INDIAN POINT-3 05000286 090279 WHILE IN HOT SHUTDOWH, THE CONDENSATE STORAGE TANK LEVEL DROPPED BELOW T CONDENSATE STORAGE FACILITIES 79-011/03L-0 092479 HE 360,000 GALLON LIMIT DESIGNATED BY TECHNICAL SPECIFICATION 3.4.A(3) T COMPONENT CODE NOT APPLICABLE 026839 30-DAY 0 A LEVEL OF 310,000 GALLONS.
THE WATER SUPPLIED FRCM CUR EXTERNAL SUPP SUBCOMPONENT NOT APPLICABLE ORT FACILITY AT CONSOLIDATED EDISON (INDIAN POINT UNIT 1) WAS AT REDUCED OTHER CAPACITY DUE TO MAINTENANCE. SIMILAR EVENTS OCCURRED ON SEPTE1BER 2, 1
NOT APPLICABLE 978, SEPTEMBER 7, 1978, MARCH 27, 1979, AND AUGUST 23, 9979.
ITEM N3T APPLICABLE THE INCIDENT WAS CAUSED BY HORMAL LOSSES DUE TO THE STEAM GENERATOR BLOW DCWH SYSTEMS AND ATMOSPHERE STE/.M DUMPS, COMPOUNDED DY THE IHABILITY OF EXTERNAL SCURCE TO MAKE UP SUFFICIENT AMOUNT OF WATER.
ENOUGH WATER WAS EVENTUALLY SUPPLIED TO RETURH THE CONDENSATE STORAGE TAHK TO AH ACCEPTA kJ7 BLE LEVEL WITHIN THE DESIGHATED 48-HOUR LIMIT.
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REPORT DATE/
EVENT DESCRIPTIOH/
CAUSE SUBCODE/ MANUFACTURER CONTROL HO.
REPORT TYPE CAUSE DESCRIPTION INDIAN POINT-3 05000286 091479 WHILE AT 79 PERCENT POWER IN THE COURSE OF A ROUTINE SHUTDOWN FOR REFUEL CONDENSATE STORAGE FACILITIES 79-012/03L-0 100979 ING, THE CONDENSATE STCRAGE TANK LEVEL DROPPED BELOW THE 360,000 GALLON COMPONENT CODE NOT APPLICABLE 026981 30-DAY LIMIT DESIGNATED BY TECHNICAL SPECIFICATIGH 3.4.A(3).
THE USUAL DEMINER SUBCOMPONENT NOT APPLICABLE ALIZED WATER SOURCE WAS OPERATING AT REDUCED CAPACITY AT THE TIME.
SIMI OTHER LAR EVENTS OCCURRED ON SEPTEMBER 2, 1978, SEPTEMBEJ 7, 1978, MARCH 27, 1 NOT APPLICABLE 979, AUGUST 23, 1979 AND SEPTEftBER 2,1979.
ITEM HOT APPLICABLE THE INCIDENT WAS CAUSED BY NORMAL USE OF THE STEAM GENERATOR BLOWDOWN SY STEM, CCMBINED WITH LIMITED MAKEUP WATER FROM ThE EXTERNAL WATER FACTORY THEREFORE, THE PLANT CCNTINUED ITS DESCENT TO SHUTDOWN BELOW 350 DEG.
F.
JOSEPH M.
FARLEY-1 05000348 062779 AT 1335 FUEL STORAGE POOL AREA RADIATICH MONITOR R-5 DECLARED INOPERABLE AREA MONITORING SYSTEMS 79-028/03L-0 072679 DUE TO A LOSS OF POWER TO R-5.
T.S. SECTION 3.3.3.1 TABLE 3.3-6 REQUIR INSTRUMENTATION + CONTROLS 026716 30-DAY E5 R-5 OPERABLE WHEN FUEL IS IN THE STORAGE FOOL.
T.S.
3.3.3.1 ACTION S OTHER TATEMENT REQUIREMENTS MET.
R-5 RETURNED TO OPERATION AT 1425.
OTHER HOT APPLICABLE VICTOREEN INSTRUMENT DIV.
THE FEED BREAKER TO R-5 WAS FOUHD OPEN.
AN INVESTIGATION FAILED TO DETE RMINE THE CAUSE FOR THE BREAKER BEING CPEN.
THE BREAKER WAS CLOSED AND R-5 DECLARED OPERABLE AT 1425 ON 6/27/79.
JOSEPH M.
FARLEY-1 05000348 071679 135 SHUBBERS WERE FOUND HOT TO MEET SURVEILLANCE TEST REOUIREMENTS.
T.S SYSTEM CODE NOT APPLICABLE 79-026/03L-0 072679 3.7.9.1 REQUIRES ALL HYDRAULIC SNUBBERS LISTED IN TABLE 3.7-4 TO BE OP HANGERS. SUPPORTS SHOCK SUPPRSS 026715 30-DAY ERABLE IN MODES 1 THROUGH 4.
THE PLANT HAS BEEN IN MODE 5 OP 6 SINCE PR SHUBBERS IOR TO INITIATION OF SNUBBER FUNCTIONAL TESTING.
T.S.
ACTION STATEMENT COMPONENT FAILURE REQUIREMENTS MET.
OTHER ITT GRINNELL ATTRIBUTED TO LOSS OF OIL DUE TO SEAL LEAKAGE AND FAILURE TO MEET LOCKUP AND BLEED ACCEPTANCE CRITERIA DURING FUNCTIONAL TEST.
AS OF 7/16/79 AL L 135 SHUBBERS HAD BEEN REPAIRED AND RETESTED SATISFACTORILY, I.E.,
THE SHUBBERS PASSED THE FUNCTIONAL TEST.
JOSEPH M.
FARLEY-1 05000348 073079 DIESEL GENERATORS 1C AND 2C (EMERGENCY POWER SOURCE FOR RIVER WATER PUMP EMERG GENERATOR SYS + CONTROLS 79-032/03L-0 082879 S,
2850 KW D.G.) OUTPUT BREAKERS WERE RACKED CUT.
AT LEAST ONE 4075 KW CIRCUIT CLOSERS / INTERRUPTERS 026719 30-DAY D.G.
FOR BACKUP EMERGENCY POWER FOR REMAINING ESF EQUIPMENT WAS AVAILABL CIRCUIT BREAKER E.
T.S.
3.8.1.2 RECUIRES ONE 4075 KW D.G. AND ONE 2850 KW D.G.
CPERABLE PERSONNEL ERROR T.S.
3.8.1.2 ACTION ST ATEf1ENT REQUIREMENTS MET.
RIVER WATER PUf;PS NO HOHLIC. OPERATIOHS PERSONNEL T REQUIRED IN MODES 5 OR 6 AND STORAGE POND WAS AVAILABLE FOR BACKUP SUP ITEM NOT APPLICABLE PLY FOR SERVICE WATER.
PERSONNEL ERROR.
BREAKERS HAD BEEN RACKED OUT AND NOT PROPERLY RESTCRED TO OPERATION DURING PERFORMANCE OF SURVEILLANCE TESTS FHP-1-STP-40.1 AN D FNP-1-STP-40.2 (DIESEL GENERATOR SEQUENCER LOAD SHEDDING TESTS).
IMME
_-+
DIATELY UPON DISCOVERY, BREAKERS WERE RACKED IN AND CONTROL POWER RESTOR g
ED.
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CAUSE SUBCODE/ MANUFACTURER CONTROL N0.
REPORT TYPE CAUSE DESCRIPTION KEWAUNEE-1 05000305 080879 DURING POWER ASSUMPTIOH PHASE OF PLANT STARTUP, SP125 DATA. SHIFT INSTRU OTHR IHST SYS REQD FOR SAFETY 79-022/03L-0 090779 MENT CHAHHEL CHECKS, WERE NOT RECORDED AS REQUIRED BY TS 4.1. A DURING 1 COMP 0HEHT CODE NOT APPLICABLE 026744 30-DAY SHIFT. SP125 DATA TAKEN BEFORE & AFTER THIS EVENT INDICATE HORMAL INSTRU SUBCOMPONENT NOT APPLICABLE MENT CHAHHEL OPERATICNS. THEREFORE, THIS EVENT HAD HO SAFETY SIGNIFICANC PERSONNEL ERROR E.
NO EFFECT OH PLANT OPERATION OR PUBLIC SAFETY. SP 125 IS PERFORMED EA LICENSED 2 SENICR OPERATORS CH SHIFT WHILE OPERATING TO ASSURE ACCEPTABLE OPERABILITY OF EACH INSTRU ITEM HOT APPLICABLE NEHT CHAHHEL BY COMPARISOH OF CHAHNEL WITH OTHER INDEP. IHST. CHANNELS.
BECAUSE OF INVOLVEMENT IN PLANT STARTUP ACTIVITIES OPER OVERLOOKED REQ.
TO PERFORM SP125. AS MUCH DATA AS POSSIBLE WAS OBTAINED FROM COMPUTER LO GS. INVOLVED OPER WERE INSTRUCTED ON IMPORTANCE OF ASSURING THAT ALL SP REQUIREMENTS ARE SATISFIED. DURIHC ROUTIHE SHIFT TURHOVER, OPER REVIEW P LANT INDICATIONS & INFORMALLY VERIFY INDICATI045 AGREE WITH PLANT STATUS KEWAUNEE-t 05000305 081979 WHILE AT FULL POWER OPERATION A SAFETY VALVE DISCHARGE LINE HIGH TEMP AL COOLANT RECIRC SYS + CONTROLS 79-023/03L-0 091879 ARM WAS ACTUATED.
CALCULATED RCS LEAKRATE WAS GREATER THAH THE TS 3.1.D VALVES 026817 30-DAY 1 LIMIT.
PLANT WAS TAKEN TO HOT SHUTDOWN CONDITION FOR INVESTIGATION O GLOBE F LEAKAGE.
SOURCE OF THE LEAKAGE WAS IDENTIFIED AND C,0RRECTED.
THE SAF OTHER ETY VALVE WAS NOT LEAKING.
THE PLANT WAS RETURHED TO OPERATION WITHIH 8 HOT APPLICABLE HOURS.
NO EFFECT ON PUBLIC HEALTH OR SAFETY.
THIS REPORT SUBMITTED UN ED'JARDS CO DER TS 6.9.2.6.2 REQUIREMENT FOR REPORTING OPERATION WITHIH AH LCO.
2 VALVES IN SAFETY VALVE LOOP SEAL DRAIN LINE & 2 RCS DRAIN VALVES (WHIC H WERE HOT OPERATED DURING REFUELING EHUTDOWH) FOUND LEAKING.
AFTER TOR QUING THESE VALVES SHUT; CALCULATED LEAKRATE WAS BELOW THE T.S.
LIMIT.
THEPMAL CYCLING DURING PLANT STARTUPS AND SHUTDOWHS IS BELIEVED TO BE TH E CAUSE OF THIS VALVE LEAKAGE.
LA CROSSE BWR 05000409 070279 DURING REACTOR OPERATION, A ROUTINE SURVEILLANCE TEST REVEALED 1A DIESEL EMERG CCRE COOLING SYS + CONT 79-012/03L-0 072779 ENGIHE DRIVEN PUMP FAILED TO START UP0H MANUAL ACTUATION OF CONTROL R00 EHGINES,IHT"RHAL COMBUSTION 026884 30-DAY M CONTROL SWITCH.
SUBCCMPONENT NOT APPLICABLE OTHER HOT APPLICABLE ITEM NOT APPLICABLE ELECTRICAL SHORT IN STARTING FUEL SOLEHOID VALVE CIRCUIT CAUSED TWO ELEC TRICAL DIODES TO BURHOUT AND FUEL VALVE TO REMAIN CLOSED DURING START CY CLE OF DIESEL ENGINE.
REPLACED DIODES AND REIHSULATED SHORTED WIRE.
SA iISFACTORY ENGIHE OPERATION WAS ACHIEVED.
LA CRUSSE 2WR 05000409 070479 DURING REACTOR POWER ESCALATION, A FAILURE OF A PISTON ROD SEAL OCCURRED TURBINE BYPASS SYS + CONT 79-013/03L-0 072579 ON THE TURBINE MAIN STEAM BYPASS VALVE OPERATING CYLINDER RESULTING IN VALVE OPERATORS 026883 30-DAY A LOSS OF HYDRAULIC OIL AND THE VALFE POTENTIALLY HOT BEING ABLE TO PERF HYDRAULIC ORM ITS INTENDED FUNCTION IN ACCORDANCE WITH T.S.
4.2.5.7.
NOTIFICATION COMPONENT FAILURE IS MADE IN ACCORDANCE WITH T.S.
3.9.2.B.(2).
MECHANICAL VICKERS, INC REACTOR PLANT SHUTDOWN WAG PROMPTLY INITIATED. FOLLOWING SHUTDOWN, REPAI RS WERE EFFECTED INCLUDING REPLACEMENT OF THE FAULTY SEAL AHD OTHER SEAL LJ7 S AND 0-RINGS PRESENT a REPLENISHMENT OF HYDRAULIC OIL.
SEAL FAILURE IS 42m ATTRIBUTED TO HORMAL WEAR.
A REPLACEMTH SEAL OF A DIFFERENT MATERIAL I S BEING INVESTIGATED TO PROBLING SERVICE LIFE.
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CAUSE SUBCODE/ MANUFACTURER CONTROL HD.
REPORT TYPE CAUSE DESCRIPTION LA CROSSE BWR 05000409 070879 DURING POWER ESCALATION OH JULY 8, 1979, CONTROL ROD 10 WAS INADVERTANTL REACTIVITY CONTROL SYSTEMS 79-014/03L-0 072779 Y PARTIALLY WITHDRAWN INSTEAD OF CONTROL ROD 12 WHICH PLACED THE CONTROL CCNTROL RODS 026882 30-DAY RODS IN AN OUT SEQUENCE CONDITION WITH REGARD TO THE REQUIREMENTS FOR M SUBCCMPONENT NOT APPLICABLE INIMUM CRITICAL POWER RATIO (MCPR) AS ADDRESSED IN T.S. 4.2.4.2.3.
PERSONNEL ERROR LICENSED & SENIOR OPERATORS HUCLEAR COMPONENTS, INC.
ACTION REQUIREMENTS T.S.
4.2.4.23 WERE COMPLETED SUCH THAT THE CONTROL R ODS WERE RETURNED TO THE REQUIRED PATTERN WITHIN 30 MINUTES. SUBSEQUENTL Y,
THERMAL-HYDRAULIC CALCULATIONS SHOWED THAT THE LIMITING MCPR WAS NOT VIOLATED. IMPORTANCE OF COMPLIANCE WITH THE CONTROL ROD PROGRAM WILL BE EMPHASIZED TO ALL OPERATIONS PERSONNEL.
MAINE YANKEE 05000309 022379 DURING ROUTIHE OPERATIONS, CONTROL ROOM OPERATORS NOTICED THAT THE CH. C REACTGR TRIP SYSTEMS 79-004/03L-0 031379 MCB INDICATION FOR INCORE TILT AND THE POSITIVE AND HEGATIVE SOTC TRIP INSTRUMENTATION + CONTROLS 026840 30-DAY LIMITS WERE READING MORE NEGATIVE THAN THE OTHER THREE CHAHHELS.
INVEST POWER SUPPLY IGATION BY THE I& C DEPT. DETERMINED THE CAUSE TO BE A FAILED +/- 18 VD COMP 0HENT FAILURE C POWER SUPPLY AND REPLACED SAME.
BECAUSE ONLY ONE OUT OF FOUR CHANNELS ELECTRICAL WERE AFFECTED, THE MINIMUM DEGREE OF REDUNDANCY WAS MAINTAINED AND THER LAMBDA ELECTRONICS E WAS NO EFFECT ON THE PUBLIC HEALTH OR SAFETY.
THE INVESTIGATION REVEALED THE POWER SUPPLY'S + 18 VDC OUTPUT HAD DECREA SED TO A VALUE OF APPROX. + 12 VDC CAUSING ALL INDICATIONS TO BECOME MOR E NEGATIVE.
THE UNIT WAS REPLACED IN KIND AND THE FAILED UNIT RETURHED TO THE VENDOR FOR FAILURE ANALYSIS.
MAINE YANKEE 05000309 091079 A ROUTINE REVIEW OF RADIOLOGICAL LIQUID WASTE DISCHARGE PERMITS, FOR DIS LIQ RADICACT WSTE MANAGMNT SYS 79-020/03L-0 100979 CHARGES MADE DURING THE PERIOD SEPT.
10, 1979 THROUGH SEPT 16.
1979 INDI INSTRUMENTATION + CONTROLS 027009 30-DAY CATED THAT THE WASTE LIQUID RADIATION MONITOR HAD NOT RESP 0HDED AS EXPEC SENSOR / DETECTOR / ELEMENT TED DURING THE RELEASES. SUBSEQUENT IHVESTIGATION HAS SHOUH THAT THE WA COMPONENT FAILURE STE LIQUID RADIATION MONITOR WAS OUT OF CALIBRATION. DOWNSTREAM SERVICE ELECTRICAL WATER RADIATION MONITOR REMAINED IN SERVICE.
HARSHAW CHEMICAL CO.
THE INSTALLED CHECK SOURCE WAS TOO SMALL TO PROVIDE A DEFINIT 7VE MEASURE OF CHANNEL CALIBRATION.
THE PLAHT IS CURRENTLY INVESTIGATING THE AVAIL ABILITY OF LARGER CHECK SOURCES.
IN THE INTERIM, THE OPERATORS HAVE BEE N INSTRUCTED TO BE ESPECIALLY COHGNIZANT OF EXPECTED CHANNEL RESPONSE DU RING RADIOLOGICAL RELEASES.
MAINE YANKEE 05000309 092579 DURING ROUTINE PREPARATION FOR PLANT HEATUP FOLLOWING A SCHEDULED MAINTE RESIDUAL HEAT REMOV SYS + CONT 79-018/01T-0 100379 NANCE OUTAGE, THE RHR SYSTEM WAS SECURED WITHOUT A STEAM GENERATOR BEING COMP 0HEHT CODE NOT APPLICABLE 026976 2-WEEK OPERABLE AS DEFINED BY TECH. SPEC. #3.8.
STEAM GENERATOR WATER LEVEL W SUBCGMP0HENT NOT APPLICABLE AS AT 300" INSTEAD OF 346" WHICH IS THE TOP OF THE TUBE BUNDLE.
BECAUSE PERSOHHEL ERROR A HEAT SIHK FOR CORE DECAY HEAT REMOVAL WAS AVAILABLE BUT NOT EXACTLY A LICENSED & SENIOR OPERATORS S SPECIFIED BY THE TECH. SPECS., THERE WAS HO EFFECT ON THE PUBLIC HEALT ITEM NOT APPLICABLE H OR SAFETY.
THE OPERATOR FAILED TO REALIZE THAT THE 300" LEVEL IN ALL 3 S/G'S WAS NO T ABOVE THE TOP OF THE BUNDLES AS SPECIFIED IN THE TECH. SPECS.
UPON R ECOGNIZIHG THE ERROR, LEVEL WAS RAISED IN ALL S/G'S TO THE HORMAL OPERAT (y3 ING LEVEL.
THE INCIDENT HAS BEEN DISCUSSED WITH THE OPERATORS INVOLVED.
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NOV 08, 1979 LER MONTHLY REPORT SORTED BY FACILITY PAGE 57 PROCESSED DURING OCTOBER, 1979 FOR POWER REACTORS FACILITY / SYSTEM / COMP 0HEHT/
DOCKET NO./
EVENT DATE/
COMPONENT SUBCODE/CAUSE CODE / LER NO./
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL HO.
REPORT TYPE CAUSE DESCRIPTION
' MAINE YANKEE 05000309 092579 DURING A REVIEW OF OUTSTANDING PROCEDURE CHANGE REPORTS (PCR), IT WAS DE SYSTEM CODE NOT APPLICABLE 79-019/03L-0 100379 TERMINED THAT ONE PCR HAD NOT BEEH REVIEWED BY THE PORC WITHIN 14 DAYS 0 COMPONENT CODE HOT APPLICABLE 026977 30-DAY F BEING GENERATED AS REQUIRED LY T.S.
- 5.8.3.C.
A MEETING OF THE PORC W SUBCOMPONENT NOT APPLICABLE AS HELD AND THE PCR WAS REVIEWED AND APPROVED.
BECAUSE THE PCR REVIEW W PERSONNEL ERROR AS CHLY SIX DAYS LATE FOR REVIEW AND WAS ULTIMATELY APPROVED, THERE WAS OTHER HO EFFECT ON THE PUBLIC HEALTH OR SAFETY.
ITEM HOT APPLICABLE FAILURE TO REVIEW THE PCR WITHIN 14 DAYS BY THE PORC WAS DUE TO THE PCR BEING MISPLACED IN ITS ROUTING FOR REVIEW AND APPROVAL. A MEMO TO ALL PL ANT PERSONHEL DESCRIDIHG THE PCR PROCEDURE AND REVIEW PROCESS HAS BEEN P REPARED TO REMIND ALL INDIVIDUALS ABOUT THE CORRECT METHOD OF UTILIZING PCR'S.
MILLSTONE-1 05000245 073179 OH JULY 31, 1979, AT 1300 HOURS, WHILE PERFORMING ROUTINE SURVEILLANCE, CNTHMNT AIR PURI + CLEANUP SYS 79-024/03L-0 083079 IT WAS DISCOVERED THAT CHANNEL 1 0F THE REFUEL FLOOR HICH RADIATION fl0HI INSTRUMENTATION + CONTROLS 026726 30-DAY TOR WAS TRIPPING OUTSIDE THE TECH. SPEC. ALLOMADLE BAHD.
THE OTHER CHAN POWER SUPPLY HEL WAS WITHIH SPECIFICATI0H AND WOULD HAVE PROVIDED THE ISOLATICH IHITI COMPONENT FAILURE ATION SIGNAL BY ITSELF.
ELECTRONIC GENERAL ELECTRIC CO.
THE CAUSE WAS BELIEVED TO BE IHSTRUMENT DRIFT.
THE CHANNEL WAS RECALIER ATED, TESTED, AND RETURHED TO SERVICE.
THE SURVEILLANCE WILL BE MONITOR ED FOR TREND DEVELOPMENT.
MILLSTONE-1 05000245 082779 OH AUGUST 27, 1979. AT 0900 HOURS, IT WAS DISCOVERED THAT THE SEMIANNUAL FIRE PROTECTION SYS + CONT 79-027/03L-0 092479 FUNCTIONAL TEST OF THE CABLE VAULT SMOKE DETECTION SYSTEM HAD BEEN INAD INSTRUMENTATION + CONTROLS 026859 30-DAY VERTENTLY OVERLOOKED.
H0 CONSEQUENCES.
SENSOR / DETECTOR / ELEMENT PERSONNEL ERROR MAINTENANCE & REPAIR PERSONNEL ITEM HOT APPLICABLE THE SUBJECT SURVEILLANCE WAS INADVERTENTLY OVERLOOKED BECAUSE IT WAS NOT LISTED ON EITHER
..tE VENDOR COMPUTER SCHEDULE OR THE UNIT'S SURVEILLANC E SCHEDULE.
THE SURVEILLANCE WAS ACCOMPLISHED AND ADDED TO THE SURVEILL ANCE SCHEDULES.
MILLSTONE-1 05000245 082879 OH AUGUST 28, 1979, AT 1045 HOURS, AFTER VENTING THE PRESSURE SUPPRESSIO CNTHMHT ISOLATION SYS + CONT 79-028/03L-0 092579 H CHAMBER, THE VENT BYPASS VALVE (1-AC-12) FAILED TO CLCSE.
THE REQUIRE VALVES 026933 30-DAY D SURVEILLANCE FOR AN IHOPERABLE CCHTAIHMENT ISOLATION VALVE WAS PERFORM PLUG ED.
NO CONSEQUENCES, THE DOWNSTREAM VALVE WAS CLOSED.
OTHER HOT APPLICABLE DEZURIK DISASSEMBLY OF THE MAIN VALVE REVEALED RUST SCALE CONTAMINATION IN THE A (J7 REA 0F THE PIVOT MECHANISM, APPARENTLY SUFFICIENT TO PREVENT THE VALVE P 45m LUG FROM ROTATING COMPLETELY CLOSED.
THE VALVE WAS CLEAHED, REASSEMBLED AND TESTED.
THIS OCCURRENCE IS SIMILAR IN HATURE TO LER-79-22/3L AND 7
(,4 9-23/3L.
C3 NW
HOV 08, 1979 LER NOHTHLY REPORT SORTED BY FACILITY PAGE 58 PROCESSED DURING OCTOBER, 1979 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
DOCKET NO./
EVENT DATE/
COMPONENT SUBCODE/CAUSE CODE / LER NO./
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUSCODE/ MANUFACTURER CCHTROL HO.
REPORT TYPE CAUSE DESCRIPTION MILLSTOHE-1 05000245 090479 ON SEPTEMBER 4, 1979, AT 1000 HOURS, WHILE PERFORMING SURVEILLANCE ON CO RESIDUAL HEAT REMOV SYS + CONT 79-029/03L-0 100479 NTAIHMENT ISOLATION VALVES, THE ISOLATION CONDENSER INBOARD STEAM SUPPLY INSTRUMENTATION + CONTROLS 026952 30-DAY
- VALVE, 1-IC-1 FAILED TO GO CLOSED UPJH RECEIPT OF THE ISCLATION SIGNAL.
SWITCH NO CONSEQUENCES, THE DOWHSTREAM VALVE WAS DEMONSTRATED TO BE OPERABLE.
COMPONENT FAILURE ELECTRICAL MICR0 SWITCH A FAULTY MICRO-SWITCH ON THE CLOSING TORQUE SWITCH HAS IDENTIFIED AS THE CAUSE OF OCCURRENCE.
THE MICRO-SWITCHES ON THE CLOSING AND OPEHING TOR QUE SWITCHE5 WERE REPLACED, ADJUSTED AHD TESTED.
THIS OCCURRENCE IS SIM ILAR TO LER 76-42/3L.
MILLSTONE-1 05000245 091379 ON SEPTEMBER 13, 1979, AT 1600 HOURS, IT BECAME APPARENT THAT THE TOTAL REACTOR CORE 79-025/01T-0 092579 PEAKING FACTOR LIMIT FOR THE CURRENT RELOAD FUEL (8X8R) WAS MORE CONSERV COMP 0HEHT CODE NOT APPLICABLE 026935 2-WEEK ATIVE THAN THE TECHNICAL SPECIFICATION LIMIT FOR THE STANDARD 8X8 FUEL T SUBCOMPONENT NOT APPLICABLE YPE.
NO PROBABLE CONSEQUENCES. REVIEW OF TPF SURVEILLANCES ILLUSTRATED PERSONNEL ERROR ADEQUATE MARGIH BETWEEN OPERATING VALUE AND THIS LIMIT.
OTHER ITEM NOT APPLICABLE THE INADVERTENT OMISSION OF THIS NEW TOTAL PEAKING FACTOR LIMIT WAS AN A PPARENT OVERSIGHT.
THE OPERATING PROCEDURE WAS MODIFIED TO IHCLUDE THE NEW LIMIT FOR 8X8R TYPE FUEL AND A TECHNICAL SPECIFICATION CHANGE WAS IN ITIATED TO INCLUDE THIS VALUE.
MILLSTONE-1 05000245 091479 ON SEPTEMBER 14, 1979, AT 1430 HOURS. IT WAS DISCOVERED THAT UNDER A CER EMERG CORE COOLING SYS + COHT 79-026/01T-0 092779 TAIN ELECTRICAL DISTRIBUTION ARRANGEMENT, A LOSS OF POWER COULD OCCUR TO COMPONENT CODE HOT APPLICABLE 026934 2-WEEK THE SUPPLY FOR THE E.C.C.S.
ELECTRICAL BUSES WITHOUT THE LOSS OF NORMAL SUBCOMPONENT NOT APPLICABLE POWER (LHP) INITIATION LOGIC BEIHG ABLE TO SENSE THIS LOSS.
DESIGN / FABRICATION ERROR DESIGH ITEM NOT APPLICA3LE THE CAUSE OF THIS OCCURRENCE IS ATTRIBUTABLE TO A DESIGN OVERSIGHT.
THE LOGIC WAS CHANGED TO ELIMINATE THIS POSSIBILITY.
MILLSTONE-2 05000336 011679 SURVEILLANCE TESTING DURING REACTOR STARTUP REVEALED CEA MOTIOH INHIBIT OTHR INST SYS NOT REQD FR SFTY 79-002/04L-0 020879 (CMI) INTERLOCK DID HOT FUNCTION PROPERLY.
FOLLOWING A RETURH TO SUB-CR INSTRUMENTATIDH + CONTROLS 026871 30-DAY ITICAL CONDITIONS INVESTIGATIONS SHOWED FAULTY POSITIF4 INDICATION FOR C OTHER EA 64, INDICATING ABOUT 6 STEPS HIGH, EXCEEDING THE LIMITS OF TECHNICAL COMPONENT FAILURE SPECIFICATIONS SECTION 3.1.3.3.
WITH THE POSITION INDICATICH FOR CEA 63 OTHER CORRECTED AND THE CMI FUNCTIONING PROPERLY, THE REACTOR STARTUP WAS RES ROCHESTER INSTRU. SYSTEMS INC.
UMED.
THE CEA 63 POSITION INDICATI0H UNIT HAD DRIFTED GIVING INCORRECT POSITIO N INDICATION. THE UNIT, AH RIS, MODEL SC1370, RESISTANCE-TO-VOLTAGE CON y
VERTER WAS RECALIBRATED AND CORRECT INDICATION RESTORED.
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NOV 08, 1979 LER MONTHLY REPORT SORTED BY FACILITY PAGE 60 PROCESSED DURING OCTOBER, 1979 FOR POWER REACTORS FACILITY / SYSTEM / COMP 0HEHT/
DOCKET HO./
EVENT DATE/
CCMPONENT'SUBCODE/CAUSE CODE / LER HO./
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION MILLSTONE-2 05000336 090679 DURING STEADY STATE POWER OPERATION, A FLUCTUATION IN INDICATED LEVEL IN EMERG CORE COOLING SYS + CONT 79-026/03L-0 092179 MUMBER 3 SAFETY INJECTION TANK WAS NOTED WITH NO CONCURRENT PLANT EVOLUT INSTRUMENTATIDH + CONTROLS 026973 30-DAY ION OR CHANGE IN TANK PRESSURE. THIS RESULTED IN AN INDICATED LEVEL READ TRANSMITTER ING OF 58.4%, WHICH EXCEEDS THE LIMIT OF %8.% A S STATED IN SECTION 3.5.1 COMPONLo, FAILURE B 0F THE TECHNICAL SPECIFICATIONS. LEVEL IN SAFETY INJECTION TAHK WAS DE INSTRUMEh' CREASED AND THE LEVEL TRANSMITTER SUBSEQUENTLY REPLACED. SIMILAR EVENT GENERAL EL CTRIC CO.
LER 77-48 SUBMITTED ON 11/2/77.
CAUSE OF ERRAliC TRANSMITTER OPERATION WAS NOT DETERMINED. FOLLOWING INI TIAL HIGH LEVEL INDICATION, LEVEL IN NUMBER 3 SAFETY INJECTION TANK WAS LOWERED AND A LONTAINMENT ENTRY MADE TO CHECK THE TRANSMITTER CALIBRATIO N.
AS A RESULT OF THIS CHECK THE TANK LEVEL HAD TO BE LOWERED FURTHER. T RANSMITTER WAS THEN REPLACED THE FOLLOWING 9AY.
MONTiCELLO-1 05000263 080679 DURING A ROUTIHE OPERATOR INSPECTION, A STEAM LEAK WAS OBSERVED ON THE 1 FEEDWATER SYSTEMS + CONTROLS 79-017/03L-0 083179 5A FEEDWATER EXTRACTION STEAM LINE DRAIN.
THE LEAK APPEARED TO BE DUE T OTHER COMPONENTS 026710 30-DAY 0 STEAM EROSIDH THROUGH THE WALL OF THE STEAM TRAP ON THIS LINE.
THIS C SUDCOMPONEHT HOT APPLICABLE CHSTITUTES AN ABNORMAL DEGRADATION OF A SYSTEM DESIGNED TO CONTAIN RADIO COMPONENT FAILURE ACTIVE MATERIAL AS REQUIRED BY TECHNICAL SPECIFICATION 6.7.B.2.D.
THERE OTHER WERE NO PREVIOUS SIMILAR OCCURRENCES.
YARWAY CORP.
THROUGH WALL EROSION DUE TO INSUFFICIENT AMOUNT OF MAINTENANCE FOR TRAP REPAIRS.
EROSION MAY BE CONSIDERED NORMAL END OF LIFE FOR COMPONENT UND ER THESE CONDITIONS. STEAM TRAP WAS YARWAY 3/4" 600# CARB0H STEEL BODY BUCKET TYPE TRAP.
TRAP WAS ISOLATED PENDING REPAIR OR REPLACEMENT AT NE XT APPROPRIATE OUTAGE.
STEAM TRAP MAINTENANCE PROGRAM WILL BE EXPANDED.
NINE MILE POINT-1 05000220 052579 DURING REFUELIHG OUTAGE, IT WAS NOTED THAT THE SITE OPERATIONS REVIEW C0 SYSTEM CODE NOT APPLICABLE 79-013/03X-1 092779 MMITTEE FAILED TO REVIEW TEMPORARY CHANGES TO 3 INSTRUMENT SURVEILLANCE COMPONENT CODE NOT APPLICABLE 026043 OTHER PROCEDURES WITHIN THE 7 DAYS AS REQUIRED BY T.S.
SINCE NO VIOLATIONS OF SUBCOMPONENT NOT APPLICABLE PERSONNEL ERROR APPROVED OPERATING PROCEDURES WERE INVOLVED AND KHOWLEDGABLE PERSOHNEL WERE CONSULTED IN EACH CASE, THERE WERE MINIMAL SAFETY IMPLICATIONS.
HONLIC. OPERATIONS PERSONNEL ITEM NOT APPLICABLE SUBSEQUENT APPROVALS OF THE PROCEDURES HAVE BEEN MADE.
REGULAR PROCEDUR E CHANGES HAVE BEEN REVIEWED BY THE SITE OPERATIONS REVIEW COMMITTEE AND APPROVED BY THE GENERAL SUPERINTENDENT NUCLEAR GENERATION.
HIHE MILE POINT-1 05000220 081679 A ROUTINE MAHAGEMENT REVIEW DISCLOSED THAT 5 MONTHLY SURVEILLANCE TESTS SYSTEM CODE NOT APPLICABLE 79-019/03L-0 091079 HAD NOT BEEN COMPLETED ON SCHEDULE.
THERE WERE MINIMAL SAFETY If1PLICATI COMPONENT CODE NOT APPLICABLC 026768 30-DAY ONS SINCE ALL TESTS WERE SUCCESSFULLY COMPLETED AND THEREFORE, THE SYSTE SUBCOMP0HENT NOT APPLICABLE MS INVOLVED WOULD HAVE OPERATED PROPERLY IF REQUIRED.
PERSONNEL ERROR LICENSED 2 SENIOR OPERATORS ITEM NOT APPLICABLE MANAGEMENT REVIEW REVEALED A FAILURE TO PERFORM FIVE SURVEILLANCE TESTS ON SCHEDULE.
THESE TESTS WERE IMMEDIATELY PERFORMED AND CCMPLETED. APP RDPRIATE PERSONNEL HAVE BEEN REINSTRUCTED TO FOLLOW THE PUBLISHED SURVEI LLANCE TEST SCHEDULE.
LD
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T HOV 08, 1979 LER MONTHLY REPORT SORTED BY FACILITY PAGE 61
~
PROCESSED DURING OCTOBER, 1979 FOR POWER REACTORS FACILITY / SYSTEM / COMP 9HENT/
DOCKET NO./
EVENT DATE/
COMP 0HENT SUBCODE/CAUSE CCDFe LER NO./
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/MANUFACTUREP CONTROL NO.
REPCRT TYPE CAUSE DESCRIPTION HINE MILE POINT-1 05000220 090179 DURING STEADY STATE OPERATION, #14 DRYWELL COOLER TRIPPED 1 DRYWELL LEAK CNTHMNT HEAT REMOV SYS + C0iT 79-020/03L-0 091079 AGE INCREASED TO ABOVE 5 GPM.
SINCE DRYWELL COOLERS ARE SUPPLIED BY REA HEAT EXCHANGERS 026767 30-DAY CTOR BLDG CLOSED LOOP COOLING, IT WAS APPARENT THAT THE UNIDENTIFIED LEA
' COOLER KAGE WAS PROBABLY HOT REACTOR COOLANT, HOWEVER, UNIT SHUTDOWN WAS COMMEN COMPONENT FAILURE CED PER TECH. SPEC. PARAGRAPH 3.2.5.
THE COOLER WAS THEN ISOLATED AND U OTHER HIDENTIFIED LEAKAGE RETURNED TO BELOW FIVE GPM. THUS THIS EVENT RESULTED BUFFALO FORGE IN MINIMAL SAFETY IMPLICATIONS.
IT IS ASSUMED THAT UNIDENTIFIED LEAKAGE INCREASED DUE TO A TUBE LEAK IN NO. 14 DRYWELL COOLER.
THIS IS BASED ON THE FACT THAT OHCE THE COOLER W AS ISOLATED, UNIDENTIFIED LEAKAGE DROPPED TO 1.2 GPM.
AFTER THIS CORREC TIVE ACTION RETURHED LEAKAGE TO AN ACCEPTABLE LEVEL, THE SHUTDOWN WAS TE RMINATED.
NINE MILL ?OINT-1 05000220 090579 DURING REFUELING OUTAGE, AH ONSITE SAMPLE INDICATED THAT THE CONCENTRATI SYSTEM CODE NOT APPLICABLE 79-021/04T-0 090779 ON OF THREE (3) HUCLIDES WAS GREATER THAH TEH TIMES THE CONTROL VALUE AN COMPONENT CODE NOT APPLICABLE 026772 2-WEEK D ALSO THERE WAS A FAILURE TO COMPLETE THE COHFIRMATORY ANALYSIS WITHIH SU3 COMP 0HENT NOT APPLICABLE THIRTY DAYS.
THIS RESULTED IN MINIMAL SAFETY IMPLICATIONS.
OTHER HOT APPLICABLE ITEll NOT APPLICABLE INITIAL DATA WAS REPORTED LATE BY CONTRACTOR AND SUBSEQUENT RECOUNT WAS LATE DUE TO HIGH INFLUX OF SAMPLES.
CONTRACTOR HAS INCREASED ITS STAFF AND IS ADDING ADDITIONAL PERSOHNEL TO TAKE CARE OF SAMPLE BACKLOG.
HINE MILE POINT-1 05000220 091879 FOUND ONE SEISMIC CONSTRAINT ON CONTAIHMENT SPRAY SYSTEM OUTSIDE THE PRI REACTOR CONTAINMENT SYSTEMS 79-022/01T-0 100179 MARY CONTAIHMENT WAS HOT INSTALLED AS REQUIRED BY CONSTRUCTION DRAWINGS.
OTHER COMP 0HENTS 026997 2-WEEK SUBCOMPONENT NOT APPLICABLE DESIGN / FABRICATION ERROR CONSTRUCTIOH/ INSTALLATION ITEM NOT APPLICABLE NOT INSTALLED AT CONSTRUCTION. INITIATED DESIGN AND ORDER TO INSTALL CD HSTRAINT.
DECLARED APPLICABLE CONTAIHMENT SPRAY LOOP IHOPERABLE. PERF0 RMING REDUNDANT LOOP OPERABILITY TEST AS REQUIRED BY TECHNICAL SPECIFICA TIONS.
NORTH AHHA-1 05000338 043079 DURING STARTUP OPERATIONS, AT 2% POWER, TEMPERATURE INDICATOR TI-RS-100A OTHER ENGNRD SAFETY FEATR SYS 79-061/03X-1 100879 ON CASING COOLING TANK (1-RS-TK-1) WAS READING OUT OF SPECIFICATIONS AT HEAT EXCHANGERS 025861 OTHER GREATER THAN 50 DEG.
F.
THIS IS REPORTABLE PURSUANT TO T.S.
6.9.1.9.B.
COOLER THIS EVENT DID NOT AFFECT THE HEALTH AND SAFETY OF THE GC.HERAL PUBLIC.
COMPONENT FAILURE MECHANICAL DUNHAM BUSH THE TEMPERATURE ROSE ABOVE ITS LIMIT DUE TO A SLIPPING BELT ON THE MECHA NICAL REFRIGERATION UNIT.
THE BELT DRIVE WAS TIGHTENED, MAKING THE SYST EM OPERABLE.
4=
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NOV 08, 1979 LER MONTHLY REPORT SORTED BY FACILITY PAGE 62 PROCESSED DURING OCTOBER. 1979 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
DOCKET NO./
EVENT DATE/
,'. COMPONENT SUBCODE/CAUSE CODE / LER NO./
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL HO.
REPORT TYPE CAUSE DESCRIPTION OCONEE-1 05000269 070479 OH JUL 4,
1979, A SLIGHT LEAK IN LPI COOLER A ALLOWED APPROXIMATELY 456 EMERG CORE COOLING SYS + C0HT 79-021/01X-1 092479 MICR0 CURIES OF CORROSION & FISSION PRODUCTS TO BE RELEASED TO LAKE KE0WE HEAT EXCHANGERS 026472 OTHER E.
SINCE THE RELEASE WAS VERY SMALL & SINCE THE OTHER LPI COOLER WAS AV COOLER AILABLE TO REMOVE DECAY HEAT IF REQUIRED, THE LEAKAGE IS CONSIDERED TO 8 PER$0HNEL ERROR E OF NO SIGNIFICANCE WITH RESPECT TO SAFE OPERATION & THE HEALTH & SAFET OTHER T OF THE PdBLIC WERE NOT AFFECTED.
BABCOCK & WILCOX COMPANY THE LPI COOLER LEAK IS THE RESULT OF OVERPRESSURIZATION OF THE COOLER DU E TO LEAKAGE PAST THE COOLER INLET VALVES & AH IMPORTANT RELIEF VALVE SE TPOINT.
FIVE TUBES WHICH SHOWED THROUGH-WALL DEGRADATION GREATER THAN 4 0% WERE PLUGGED.
ADMINISTRATIVE ACTIONS WILL BE TAKEN TO PRECLUDE OVERP RESSURIZATION IN THE FUTURE.
OCONEE-1 05000269 080279 WHILE UNITS 1 & 3 WERE AT COLD SHUTDOWN & UNIT 2 WAS AT 100% FULL POWER, EMERG GENERATOR SYS + CONTROLS 79-026/03L-0 083179 POWER CIRCUIT BREAKER (PCB) 9 WAS OPEHED, MAKING KECWEE HYDRO UNIT 1 UN CIRCUIT CLOSERS / INTERRUPTERS 026712 30-DAY AVAILABLE TO PROVIDE EMERGENCY POWER BY WAY OF THE OVERHEAD FEEDER.
THE CIRCUIT BREAKER BREAKER WAS OPENED ONLY MOMENTARILY.
IN ADDITION, THE UNDERGROUND FEED DEFECTIVE PiOCEDURES ER WAS AVAILABLE TO SUPPLY EMERGEHCY POWER IF REQUIRED.
THEREFORE, THIS NOT APPLICABLE INCIDENT IS CONSIDERED NOT TO BE SIGNIFICANT WITH RESPECT TO SAFE OPERA WESTINGHOUSE ELECTRIC CORP.
TION, AND THE HEALTH & SAFETY OF THE PUBLIC WERE NOT AFFECTED.
PCB 9 WAS OPEHED BY CIRCUIT PROTECTIVE EQUIPMENT AS A RESULT OF A DECREA SE IN AIR PRESSURE DUE TO CYCLING AIR CIRCUIT BREAKER (ACB) 4 SEVERAL TI MES RAPIDLY. PCB 9 WAS RECLOSED ALMOST IMMEDIATELY. OPERATOR TRAINING i
AND PROCEDURES WILL BE REVISED TO INCLUDE CAUTIONS AGAIHST REPEATEDLY CY CLING THE ACB'S TOO QUICKLY.
OCONEE-1 05000269 080579 AT 0455 ON AUGUST 5,
1979, UNIT 1 WAS AT HOT SHUTDOWN WHEH ONE OF THE TW AC ONSITE POWER SYS + CONTROLS 79-027/03L-0 090479 0 4160 VOLT MAIH FEEDER BUSES FROM THE STARTUP TRANSFORMER WAS ISOLATED CIRCUIT CLOSERS / INTERRUPTERS 026786 30-DAY
- ' A RESUtT OF A BREAKER TRIPPING FOR H0 APPARENT REASON.
ONE FEEDER BU CIRCUIT BREAKER S TJ PERMITTED TO BE IHOPERABLE FOR UP TO 24 HOURS, AND THE SECOND BUS R OTHER EiaINED ENERGIZED. THEREFORE. THIS INCIDENT IS CONSIDEPED TO BE OF N0'S NOT APPLICABLE IGNIFICANCE WITH RESPECT TO SAFE OPERATIOH, AND THE HEALTH AND SAFETY OF WESTINGHOUSE ELECTRIC CORP.
THE PUBLIC WERE NOT AFFECTED.
ALTHOUGH THE EXACT CAUSE OF THE OCCURRENCE COULD NOT BE DETERMINED, AT T HE TIME THE BREAKER TRIPPED PROBLEMS WERE BEING EXPERIENCED WITH A DC PO WER BUS GROUND UHICH MAY HAVE AFFECTED THE BREAKER'S DC OPERATED TRIP CO IL.
THE BREAKER WAS TESTED, DETERMINED TO BE OPERATING PROPERLY, AND RE SET.
OYSTER CREEK-1 05000219 080379 FIFTY TO ONE HUNDRED DEAD FISH WERE OBSERVED IN BARNEGOT BAY, SOUTH OF T SYSTEM CODE NOT APPLICABLE 79-005/04T-0 091079 HE MOUTH OF OYSTER CREEK, FLOATING ALONG THE SHORE.
THIS REPORT CONFORM COMPONENT CODE NOT APPLICABLE 026369 2-WEEK S WITH CONDITION 4.5 0F THE ENVIRONMENTAL TECHNICAL SPECIFICATIONS. LO SUBCOMPONENT NOT APPLICABLE SS OF THESE FISH SHOULD NOT ADVERSELY AFFECT THE POPULATION OF THE FOUR EXTERNAL CAUSE SPECIES IDENTIFIED IN APPENDIX I.
NOT APPLICABLE ITEM NOT APPLICABLE EXACT CAUSE UFCERTAIN.
TWO POSSIBILITIES ARE HIGH WATER TEMPERATURE AND LOW DISSOLVEU UXYGEN.
LOAD REDUCTION OF THE PLANT HAD BEEN MADE DURING
~~^
AUGUST 2.
SIX SPECIMENS WERE SENT TO RADIATION MANAGEMENT CORPORATION FOR IDENTIFICATI0H, LENGTH AND WEIGHT MEASUREMENTS.
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NOV 08, 1979 LER MONTHLY REPORT SORTED BY FACIL;TY PAGE 63 PROCESSED DURING OCT03ER, 1979 FOR PCWER REACTORS FACILITY / SYSTEM / COMPONENT /
DOCKET NO./
EVENT DATE/
COMPONENT SUBCODE/CAUSE CODE / LER NO./
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION OYSTER CREEK-1 05000219 080779 ON AUGUST 7,
1979. DURING AN INSPECTION OF SEISMIC RESTRAINTS ASSOCIATED EMERG CORE COOLING SYS + CONT 79-027/01T-0 082179 WITH CORE SPRAY SYSTEM II, P 'UR SEISMIC RESTRAINTS, NZ-2-RS, NZ-2-R7, N HANGERS. SUPPORTS SHOCK SUPPRSS 026708 2-WEEK Z-2-R8, AND NZ-2-R9, WERE DIStlVERED IN POSITIOis OTHER THIN FEQUIRED BY SUPPORTS CRIGINAL DESIGN OR HAD FAILED.
ON AUGUST 6, 1979 TW3 MORE RESTRAIPTS, DESICN/ FABRICATION ERROR NZ-2-R6, AND NZ-2-R6A, WERE FOUPD TO BE IN CONDITION NOT REPRESENTATIVE CONSTRUCTION / INSTALLATION OF THE ORIGINAL DESIGN CRITERIA.
CORE SPRAY SYSTEM II WAS CONSIDEREL IN ITEM NOT APPLICABLE OPERABLE FOR A TIME UNTIL ANALYSE: WERE MADE AND CONDITICMS CCRRECTED.
FOUR OF THE RESTRAINTS WERE FOUND PO BE INSTALLED CONTRARY TO ORIGINAL D ESIGN CRITERIA AND BECAUSE OF THIS TWO OTHERS WERE DAMAGED DUE TO UNREST RAINED PIPE MOVEMENT IN OTHER SECTIONS OF THE PIPING.
FOUR CF THE RESTR AINTS WERE RESTORED TO THEIR DESIGNED CONDITION.
NZ-2-D7 DESICH WAS MOD IFIED.
NZ-2-R6 WILL BE RESTORED TO CRIGINAL DESIGN OR RELOCATED.
OYSTER CREEK-1 05000219 080779 ON AUGUST 7, 1979. DURING ROUTINE SURVEILLANCE OF CORE SPRAY SY5TEtt I, P EMERG CORE COOLING SYS + CONT 79-028/03L-0 090679 ARALLEL ISOLATICH VALVE V-20-15 BECAME INOPERABLE IN THE OPEN POSITION.
VALVE OPERATORS 026709 30-DAY THE CIRCUIT BREAKER FOR THE MOTOR CPERATOR TRIPPED WHEN THE ACTUATION PR ELECTRIC MOTOR - AC ESSURE SENSCR WAS RESET.
A PARALLEL VALVE V-20-40, WHICH IS ACTUATED BY OTHER THE SAME PRESSURE SENSOR, OPERATED NORf1 ALLY.
VALVE STROKING CURRENTS W NOT APPLICABLE ERE READ WITH THE BREAKER RESET AND F3UND TO BE NORMAL.
THE VALVE WAS S GENERAL ELECTRIC CO.
TROKED TO DETERMINE OPERABILITY AND RESURVEILLED WITHOUT INCIDENT.
THE APPARENT CAUSE OF THE OCCURRENCE WAS THE HIGH MOTOR CURRENT DRAWN WH EN A VALVE CLOSE SIGNAL WAS INADVERTENTLY INITIATED DLRING THE PEPICD WN EN THE VALVE WAS STILL STRGKING OPEN.
ALL ASSOCIATED ELECTRICAL CCMPONE NTS WERE FUNCTIONALLY TESTED AND FOUND SATI!'ACTORY. THE SURVEILLANCE PR OCEDURE WAS REVISED.
MOTOR CURRENT TESTS WERE *ERFORMED.
OYSTER CREEK-1 05000219 080779 DURING NORMAL OPERATION, WHILE EXCAVATING TO EFF ST R[ FAIRS CN THE EQUIP LIQ RADI0ACT WSTE MANAGMNT SYS 79-026/03L-0 090679 MENT DRAIN TANK LINE. A LEAK UAS DISCOVERED IN T : LAUNORY TANK DISCHARG PIPES, FITTINGS 026762 30-DAY E PIPE.
FLCW RATE OF THE LEAK WAS APPROXIMATED BE 1/2 GPM UHILE WATE LESS THAN 4 INCHES R WAS BEING PUMPED TO RADWASTE.
SAMPLES WERE ANALYZED AND REVEALED LEVE COMPONENT FAILURE LS OC C0(60) AND MN(54).
THE EXTENT OF 20NTAMINATION DUE TO THIS LEAK C CORROSION ANNOT BE DISTINGUISHED FRGM THE LEAK IN THE EQUIPMENT DRAIN TANK LINE (R ITEM NOT APPLICABLE O S0-219/79-10).
ISOTCPIC ANALYSIS PERFORMED ON THE SOIL AND RESICUAL WATER PEVEALED LEVE LS OF MN(54) & C0(60).
IrMEDIATE ACTION WAS TO ISOL ATE THE LINE a T AG T HE LAUNDRY TANK PUMP "OUT OF SERVICE *- THE LINE HAS BEEN TEttPORARILY RE ROUTED UNTIL REPAIRS CAN BE MADE & AN ENCLOSLURE CAN BE LUILT ARGUND THE SE PIPE RUNS.
SUPPLEMENTAL INFO WILL BE SENT UPON FURTHER ANALYSIS.
OYSTER CREEK-1 05000219 081279 DURING NORMAL OPERATION, "A"
CRD PUMP UAS REMOVED FRC 1 SERVICE DUE TO EX REACTIVITY CONTROL SYSTEMS 79-030/03L-0 091279 CESSIVE LEAKAGE FROM THE PUMP VENT PIPING.
THE PIPING WAS FOUND TO BE C PIPES, FITTINGS 026782 30-DAY RACKED AT THE BUSHING WHERE IT ENTERS THE PUMP CASING.
THE SAFETY SIGNI LESS THAN 4 INCHES FICANCE OF THIS EVENT IS CONSIDERED MINIMAL LECAUSE OF THE AVAILABILITY PERSONNEL ERROR OF REDUNDANT PUMP.
OTHER ITEM NOT APPLICABLE THE CRACKING APPEARS TO BE CAUSED BY AN OPERATCR USING THE VENT LINE AS A FOOT SUPPORT.
THE AFFECTED BUSHING AND A SHORT PIPE NIPPLE IN THE LIN
~~'
E WERE REPLACED AND THE PUMP RETURNED TO SERVICE.
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NOV 08, 1979 LER MONTHLY REPORT SCRTED BY FACILITY PAGE 65 PROCESSED CURING OCTOBER, 1979 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
DOCKET HO./
EVENT DATE/
COMPONENT SUB00DE/CAUSE CODE / LER HO./
REPGRT DATE/
EVENT DESCRIPTION /
]CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION PALISADES-1 05000255 090579 DURING A RELEASE OF CONTENTS OF WASTE GAS DECAY TANK T-68B, WASTE GAS MO GAS RADI0ACT WSTE MANAGMNT SYS 79-035/01T-0 091479 HITOR ALARMED 3 TERMINATED RELEASE. INVESTIGATION REVEALED THAT T-638 HA COMPONENT CODE NOT APPLICABLE 026864 2-WEEK D BEEN INCORRECTLY ASSIGNED AS TANK TO BE RELEASED. AS A RESULT, PARTIAL SUBCOMPONENT N3T APPLICABLE RELEASE OF T-68B OCCURRED WITHOUT HAVING FIRST MET SAMPLING & HOLDUP RE PERSONNEL ERROR QUIREMENTS OF TS 3.9.3 AND 3.9.17. NO RELEASE LIMITS WERE EXCEEDED: RELE RADIATION FROTECTION PERSONNEL ASE RATE WAS 0.464 PERCEHT OF ANNUAL AVERAGE LIMIT. NO THREAT TO PUBLIC ITEM NOT APPLICABLE HEALTH RESULTED.
A PERSONNEL ERROR IN TRANSCRIBING THE ID NUMBER OF THE TANK TO BE RELEAS ED FROM THE SAMPLE / CALCULATION SHEET TO THE BATCH RELEASE FORM RESULTED IN THE WRONG TAHK BEING RELEASED.
TO PREVENT RECURRENCE, A REVIEW STEP WILL BE ACDED TO THE PELEASL FORM.
PEACH BOTTOM-2 05000277 041879 ROUTINE PH ANALYSIS OF SEWAGE PLANT EFFLUENT IDENTIFIED A PH OF 5.3 WHIC POTABLE + SAN WATER SYS + CONT 79-017/04T-0 042779 H EXCEEDED THE TECH SPEC RANCE OF 6.0 TO 9.0.
PH OF THE EFFLUENT WAS BE COMPONENT CODE NOT APPLICABLE 026764 2-WEEK LOW 6.0 FOR LESS THAN 4 HOURS AFTER DISCOVERY. PH OF THE WATER ENTERING SUBCOMPONENT NOT APPLICABLE CONOWINGO POND FROM THE DISCHARGE CANAL WAS HOT AFFECTED DUE TO LARGE D OTHER ILUTION FACTOR.
ENVIRONM:hTAL IMPACT WAS INSIGNIFICANT.
NOT APPLICABLE ITEM HOT APPLICABLE SOURCE OF LOW PH WATER COULD NOT BE DETERMINED. AERATION TAHK WAS NEUTR ALIZED TO BRING EFFLUENT PH WITHIN LIMITS. MODIFICATION TO THE SEWAGE T REATMENT PLANT TO PROVIDE AUTOMATIC PH CONTROL IS PRESENTLY UNDER INVEST ICATION.
PEACH BOTTOM-2 05000277 051579 ROUTIHE PH ANALYSIS OF SEWAGE PLANT EFFLUENT IDENTIFIED A PH OF 5.8 WHIC POTABLE + SAN WATER SYS + COHT 79-023/04T-0 052579 H EXCEEDED THE TECH SPEC RANGE OF 6.0 TO 9.0.
THE PH OF THE EFFLUENT WA BLOWERS 026845 2-WEEK S BELOW 6.0 FOR LESS THAN 4 HOURS AFTER DISCOVERY. THE PH OF THE WATER SUBCOMPONENT NOT APPLICABLE ENTERING CONOWINGO POND FROM THE DISCHARGE CANAL WAS NOT AFFECTED DUE TO COMPONENT FAILURE THE LARGE DILUTION FACTOR.
THE ENVIRONMENTAL IMPACT WAS INSIGNIFICANT.
MECHANICAL HOFFMAN AIR-FILT., DIV. CLARKS FAILURE OF AIR BLOWERS ALLOWED THE DISSOLVED OXYGEN LEVEL TO DROP TO ZER 0.
THIS CAUSED THE AERATICH TANK TO GO TO AN AEROBIC CONDITION WHICH DR OPS PH.
AERATION TANK WAS NEUTRALIZED AND AIR TEMPORARILY SUPPLIED TO B RING PH WITHIN LIMITS.
BLOWERS WERE REPAIRED. MODIFICATION TO PROVIDE AUTOMATIC PH CONTROL IS PRESENTLY UNDER INVESTIGATION.
PEACH BOTTOM-2 05000277 081279 WHILE AT POWER, TORUS HIGH VACUUM ALARM WAS RECEIVED IN THE CONTROL ROOM REACTCR CONTAINMENT SYSTEMS 79-038/03L-0 090779
. OPERATORS REDUCED VACUUM IN TORUS WITH THE CONTAIHMENT ATMOSPHERIC DI VALVE OPERATORS 026724 30-DAY LUTION SYSTEM.
SUBSEQUENTLY OPERATORS TESTED THE VACUUM BREAKER AIR OPE PNEUMATIC / DIAPHRAGM / CYLINDER RATE" VALVES.
VALVE A0-2502A FAILED TO CPEN AND WAS DECLARED INOPERABLE COMPONENT FAILURE THE REDUNDANT VALVE A0-2502B WAS PROVEN CPERABLE.
SINCE THE REDUNDAN MECHANICAL T VALVE WOULD HAVE OPERATED PROPERLY AND OPERATORS WERE ALERTED TO THE I FISHER GOVERNOR HCREASE IN TORUS VACUUM THE SAFETY SIGNIFICANCE IS MINIMAL.
THE HEEDLE VALVE WHICH BLEEDS AIR TO CLOSE VALVE A0-2502A WAS FOUND CLOG GED.
MANUAL OPERATION OF THE HEEDLE VALVE RELIEVED THE CLOGGING AND BLE ED RATE ADJUSTED.
VALVE A0-2502A WAS TESTED FOR PROPER OPERABILITY AND
~~*
RETURNED TO SERVICE ON 8/13/79.
( 71
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NOV 08, 1979 LER MONTHLY REPORT SCRTED BY FACILITY PAGE 66 PROCESSED DURING OCTOBER, 1979 FOR POWER REACTORS FACILITY / SYSTEM /CCMPONEHT/
DOCKET HO./
EVENT DATE/
CCMPONENT SUBCODE/CAUSE CODE / LER HO./
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION PEACH BOTTOM-2 05000277 081279 AT POWER DURING A ROUTINE SURVEILLANCE TEST THE A AND B CONTROL ROOM INT AIRBORNE RADIDACT MONITOR SYS 79-037/03L-0 091179 AKE AIR RADIATION MOHITORS FAILED DOWHSCALE.
THE SYSTEM GPERATED CORREC INSTRUMENTATION + CONTROLS 026725 30-DAY TLY TO ISOLATE CONTROL ROOM VENTILATIDH.
THE EMERGENCY VENTILATION SYST SENSOR / DETECTOR / ELEMENT EM WAS PLACED IN OPERATIGH.
BOTH MOHITORS WERE RESTORED TO SERVICE WITH COMPONENT FAILURE IN 24 HOURS.
THERE WAS MINIMAL SAFETY SIGNIFICANCE SINCE ALL APPROPRIAT ELECTRONIC E SYSTEMS FUNCTIONED CORRECTLY AND NO RADIATION HAZARD EXISTED.
LFE CORP.
FAILURE OF TRANSISTOR CIRCUITS WITHIN THE A AND B RADIATION MOHITORS OCC URRED.
THE A MONITOR WAS REPLACED.
THE B MONITOR WAS REPAIRED.
BOTH M ONITORS WERE SATISFACTORILY TESTED AND RETURHED TO SERVICE.
PEACH BOTTOM-2 05000277 082179 CONTRACT PERSCHNEL WORKING IN THE E2 DIESEL ROOM DISARMED THE CO2 SYSTEM FIRE PROTECTION SYS + CONT 79-040/01T-0 090579 AND ESTABLISHED A FIRE WATCH IN ACCORDANCE WITH PROCEDURE.
UPON COMPLE COMP 0HENT CODE NOT APPLICABLE 026722 2-WEEK TION OF WORK, THE CO2 SYSTEM WAS NOT RESTORED TO NORMAL AND THE AREA WAS SUBCOMPONENT NOT APPLICABLE WITHOUT A FIRE WATCH FOR ABOUT 10 MINUTES.
CONSEQUENCES ARE MINIMAL DU PERSOHNEL ERROR E TO THE SHORT TIME INTERVAL IHVOLVED AND ALSO THE FACT THAT HO WORK WAS CONSTRUCTIDH PERSONNEL BEING PERFORMED IN THE DIESEL GENERATOR DAY WHEN THE FIRE WATCH WAS ABS ITEM HOT APPLICAELE ENT.
PERSONNEL THOUGHT SECOND GROUP WORKING IN THE CARD 0X ROOM OF THE DIESEL BUILDING REQUIRED THE CO2 SYSTEM TO BE DISARMED. C02 SYSTEM WAS RESTORE D TO NORMAL WITHIH 10 MINUTES.
ALL PERSONNEL INVOLVED RECEIVED INSTRUCT ION OH WORK REQUIREMENTS WHERE A FIRE WATCH IS POSTED.
PEACH BOTTOM-2 05000277 082879 INADVERTENTLY OPEHED DRAIN VALVE CAUSED IHOPERABILITY OF -B-CHANNEL OF MAIN STEAM ISOL SYS + CONTROLS 79-039/03L-0 092779 THE -D-MAIN STEAM LINE HIGH FLOW ISOLATION SIGNAL.
REDUNDANT CHANHELS COMPONENT CODE NOT APPLICABLE 026936 30-DAY REMAINED OPERABLE; SAFETY SIGHIFICANCE IS MINIMAL.
SUBCOMPONENT NOT APPLICABLE PERSONNEL ERROR CONTRACT. & CONSULT. PERSONHEL ITEM NOT APPLICABLE DRAIN VALVE LOCATED ON INSTRUMENT RACK OPEHED PARTIALLY WHEN STRUCK BY S CAFFOLDING BEING TRANSPORTED THROUGH THE AREA.
VALVE WAS RECLOSED WITHI N 10 MINUTES AND THE INSTRUMENT RETURNED TO SERVICE.
TEMPORARY BARRIER INSTALLED TO PRECLUDE SIMILAR EVENT.
INSTRUCTIONS GIVEN TO CONTRACTOR P ERSONNEL TC EXERCISE MORE CARE.
PEACH BOTTOM-2 05000277 090579 WHILE AT PCWER AN IHADVERTENTLY OPEHED 440 VOLT BREAKER SWITCH MADE THE EMERG CORE COOLIHG SYS + COHT 79-041/03L-0 100579
'A' RHR LOOP IHJECTION VALVE (MD-?5A) INOPERABLE FOR APPROXIMATELY 10 MI COMPONENT CODE NOT APPLICABLE 026944 30-DAY NUTES.
DURING THIS INTERVAL, ALL OTHER ECCS SYSTEMS IHCLUDING THE
'B' R
SUBCOMPONENT NOT APPLICABLE HR LOOP WERE OPERABLE. SAFETY SIGNIFICANCE IS MINIMAL DUE TO SHORT DURA PERSONMEL ERROR TION OF THE EVENT AND AVAILABILITY OF REDUNDANT SYSTEMS.
CONTRACT. & CONSULT. PERSONHEL ITEM NOT APPLICABLE THE BREAKER SWITCH WAS HIT BY SCAFFOLDING BEING TRANSPORTED THROUGH THE AREA.
FOLLOWING INVESTIGATION, THE BREAKER SWITCH WAS RECLOSED.
INSTRU CTIONS WERE GIVFH TO CONTRACTOR PERSOHNEL TO EXERCISE MORE CARE.
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REPORT DATEe EVENT DESCRIPTION /
CAUSE SUBCODE/MAHUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTICH PEACH BOTTOM-2 05000277 090679 THE INSPECTION PP0 GRAM PERFORMED IN RESPONSE TO IE BULLETIN 79-02 IDENTI OTHER ENGNRD SAFETY FEATR SYS 79-043/01T-0 092079 FIED TWO ANCHORS IN ONE SUPPCRT WHICH HAD CCHTACT BETWEEN THE BOLT SHELL HANGERS, SUPPORTS, SHOCK SUPPRSS 026821 2-WEEK S AND THE SUPPCRT PLATE.
THESE ANCHORS ARE ASSOCIATED UITH THE HIGH PRE HANGERS SSURE SERVICE MATER CHPSW) SYSTEM LINE IN THE UNIT 2 A RHR RCOM.
EVEN T DESIGH/ FABRICATION ERROR HOUGH FAILURE OF THE PIPE DURING A SEISMIC EVENT WOULD AFFECT TUG HPSM C CONSTRUCTION / INSTALLATION OHTAIHMENT COOLING SUBSYSTEMS THE SAFETY SIGNIFICANCE IS CONSIDERED MINI I.T.T. PHILLIPS DRILL DIVISION MAL BECAUSE LPCI AND REDUNDANT RHR SU3 SYSTEMS ARE AVAILABLE.
CONTACT BETWEEN THE BOLT SHELLS AND SUPPORT PLATE MtS CAUSED BY IMPROPER INSTALLATION OF THE BOLT ANCHOR SHELLS.
THE DEFECTIVE BOLT SHELLS HAVE BEEN REMOVED AND REPLACED BY WEDGE TYPE AHCHOR EOLTS AND HAVE BEEN SUCC ESSFULLY TORQUE TESTED.
THE RESULTING ANCHOR BOLT SAFETY FACTOR ATTAINE D IS GREATER THAN 5.
PEACH BOTTOM-2 05000277 090679 SEISMIC AHD REDdHDANCY DESIGN DEFICIENCIES INVOLVING ELECTRICAL FEEDS DI CNTHMNT COMBUS GAS CONTROL SYS 79-042/01T-0 092079 SCOVERED ON CAD SYSTEM VALVES AND INSTRUMENTATION. SAFETY SIGNIFICANCE INSTRUMENTATION + CONTROLS 026938 2-WEEK MINIMIZED BY THE AVAILABILITY OF ALTERNATE METHODS OF EhSURING SYSTEM OP POWER SUPPLY ERABILITY.
DESIGN / FABRICATION ERROR DESIGN OTHER DEFICIENCIES RESULTED FRCM INADEQUATE DESIGN BY ARCHITECT-ENGINEER.
COR RECTIVE ACTION IN PROGRESS TO INSTALL AND RELOCATE THE CAD SYSTEtt PCWER AND CONTROL CABLES.
PEACH BOTTOM-2 05000277 090779 INSPECTION PROGRAM PERFORMED IN RESPONSE TO BULLETIN 79-02 IDENTIFIED A OTHER ENGHPD SAFETY FEATR SYS 79-044/01T-0 092179 FAILURE OF ONE SUPPORT ASSOCIATED WITH EMERGENCY SE4VICE WATER SYSTEM PI HANGERS. SUPPORTS SHOCK SUPPRSS 026858 2-WEEK PING IN UNIT 2 REACTOR BLDG. CLOSED COOLING WATER ROOM. 2 BOLTS WERE CGN HANGERS SIDERED FAILED BECAUSE OF EXCESSIVE SHELL PROJECTION FROM WALL. BECAUSE DESIGN / FABRICATION ERROR 3 0F THE 4 BOLTS ACHIEVED THE REQUIRED TORQUE AND SAFETY FACTCR LtS 2.88 CONSTRUCTION / INSTALLATION
, POSSIBILITY OF FAILURE OF RELATED PIPING SYSTEMS DURING A SEISMIC EVEN I.T.T. PHILLIPS DRILL DIVISION T WAS MINIMAL.
IMPROPER INSTALLATION IS MOST PROBABLE CAUSE OF TEST FAILURE. FOLLOWING NOTIFICATICH OF TEST FAILED ANCHOR BOLTS, E5W LINE WAS ISOLATED BY MANUA LLY CLOSING VALVE 0-517 & SHUTDOWN WAS IHITIATED.
FAILED BCLTS WERE REP LACED WITH 1"X9" HILTI KWIK BOLTS.
REPLACEMENT BOLTS WERE SUCCESSFULLY TORQUE TESTED.
THE RESULTANT SAFETY FACTOR WAS 5.33.
PEACH BOTTOM-3 0$000278 010879 ROOF VENT STACK INSTANTANEOUS RELEASE RATE ABOVE TECH. SPEC. LIMIT. DURI GAS RADI0ACT WSTE MANAGMNT SYS 79-002/04T-0 012279 NG A MAINTENANCE OUTAGE COOLANT VAPCR LEAKED FROM REACTOR THRU CPEN & PA VALVE OPERATORS 026763 2-WEEK RTIALLY DISMANTLED RCIC ISOLATION VALVES VIA THE MSIV ROOM TO THE VENT S ELECTRIC MOTOR - DC TACK.
WORK CN LOTH VALVES WAS PERMISSIBLE SINCE UNIT WAS IN COLD SHUTCO COMPONENT FAILURE WN.
TOTAL RELEASE WAS 1.5 HRS LCNG WITH RATE EXCEEDING TECH. SPEC. FOR MECHANICAL APPROX. 15 MIN. (PEAK 270% OF LIMIT).
CONSEQUENCES MINIMAL EECAUSE OF S LIMITORQUE CORP.
HORT DURATION AND CCNTENT OF RELEASE (NOBLE GASES).
VALVE OPERATGR FAILURE (M016A) CAUSED LOSS OF INSERVICE RHR LCCP, RISE I N COOLANT TEMP, 4 GASEOUS RELEASE VIA RCIC VALVES UNDERGCING MAINTENANCE SHUTDOWN COOLING RE-ESTABLISHED. REACTOR COOLANT TEMP. REDUCED. THUS ENDING RELEASE.
OPEPATING PERSONNEL INSTRUCTED TO LIMIT COOLANT TEMP. T O 170 F WHEN RELEASE FLOW PATH EXIST
S. PROCEDURE
MCDS PROVIDE GUIDANCE.
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DOCKET NO./
EVENT DATE/
COMPONENT SUBCODE/CAUSE CODE / LER NO./
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION PEACH BOTTOM-3 05000278 081579 INSPECTION PROGRAM PERFORMED IN RESPONSE TO IE BULLETIN 79-02 IDENTIFIED EMERG CGRE COOLING SYS + CONT 79-024/01T-0 082979 3 0F 4 ANCHOR BOLTS TESTED IN ONE SUPPORT ON THE 3D RHR PUMP SUCTION PI HANGERS,5UPPORTS,$ HOCK SUPPRSS 026723 2-WEEK PING FAILED.
DURING A SEISMIC EVENT THE ANCH00 SUPPORT PIPING SYSTEM C0 SUPPORTS ULD POSSIBLY FAIL AND CAUSE FLOODING IN ONE OF FOUR RHR ROCMs.
BECAUSE DESIGN / FABRICATION ERROR REDUNDANT RHR PU;tPS AND DACKUP CORE SPRAY SYSTEM ARE AVAILABLE, SAFETY S CONSTRUCTION / INSTALLATION IGNIFICANCE IS CONSIDERED MINIMAL.
I.T.T. PHILLIPS DRILL DIVISION THE MOST PROBABLE CAUSE OF FAILURE WAS IMPROPER INSTALLATION. THE THREE TEST FAILED ANCHOR BOLTS WERE REPLACED WITH WEDGE TYPE ANCHORS AND SUCC ESSFULLY TORQUE TESTED.
PEACH BOTTOM-3 05000278 082979 WHILE AT POWER AND DURING A SURVEILLANCE TEST OF REACTOR VESSEL LEVEL IN EMERG CORE COOLING SYS + CONT 79-025/03L-0 092879 STRUMENTATION (LSLL3-2-3-72B), RELAY (2E-K18) FAILED TO MAKE CONTACT.
T RELAYS 026937 30-DAY HIS RELAY PROVIDES REACTOR VESSEL LCW LEVEL TRIP (-130 IN.) TO ADS INITI CONTROL, GENERAL PURPOSE ATION LOGIC.
SAFETY CONSEQUENCES WERE MINIMAL SINCE THE REDUNDANT LOGIC COMPONENT FAILURE CHANNEL WAS OPERABLE.
ELECTRICAL GENERAL ELECTRIC CO.
THE CAUSE OF THIS OCCURRENCE WAS A WORN CONTACT ON A GE HFA RELAY.
THE LOGIC HAS BEEN PLACED IN THE TRIPPED CONDITION AND THE RELAY WILL BE REP L ACED DURING THE CURRENT REFUELING AND MAINTENANCE OUT AGE.
PEACH BOTTOM-3 05000278 090479 ANCHOR 3-23-DDN-525 WAS IDENTIFIED AS A FAILURE AND REPAIRED IN CONJUNCT EMERG CORE COOLING SYS + CONT 79-026/01T-C 091379 ION WITH THE SEISMIC SUPPORT PROGRAM REQUIRED BY NRC BULLETIN 79-02.
TH HANGERS,$UPPORTS, SHOCK SUPPRSS 026833 2-WEEK IS SUPPORT GUIDES A SECTION OF THE PIPING BETWEEN THE HPCI PUMP DISCHARG OTHER E AND MO-20 VALVE.
BECAUSE THE FAILURE OF THIS ANCHOR MAY NOT HAVE RESU DESIGN / FABRICATION ERROR LTED IN FAILURE OF THE SUPPORTED PIPING SYSTEM DURING A SEISMIC EVENT, A CONSTRUCTION / INSTALLATION ND BECAUSE REDUNDANT ECCS SYSTEMS WERE SATISFACTORILY TESTED FOR OPERABI I.T.T. PHILLIPS DRILL DIVISION LITY, THE SAFETY SIGNIFICANCE OF THIS FAILURE WAS MINIMAL.
THE MOST PROBABLE CAUSE OF FAILURE WAS IMPROPER INSTALLATICN. THE ORIGI HAL ANCHOR PLATES WERE ATTACHED TO NEW PLATES BY MEANS OF FILLET WELDS.
THE LARGER PLATES WERE BOLTED TO THE WALL USING 7" X 3/4" HILTI K!JIK EOL TS.
THIS REPAIR RAISED THE CALCULATED SAFETY FACTOR TO 6.5.
ANCHOR BOL TS WERE SUCCESSFULLY TOROUE-TESTED.
PILGRIM-1 05000293 061279 DURING AN IE INSPECTION IT WAS DISCOVERED THAT ON JUNE 12, 1979 WHILE PE EMERG CORE COOLING SYS + CONT 79-029/017-0 082479 RFORMING REPAIRS ON THE "A" CORE SPRAY SYSTEM MINIMUM FLOW LINE, A DEGRA VALVES 026759 2-WEEK DATION OF PRIMARY CONTAINMENT OCCURRED. WHEN THE MINIMUM FLOW LINE CHEC CHECK K VALVE WAS REMOVED, THE TORUS WAS OPENED TO ATMOSPHERE.
PERSONNEL ERROR LICENSED 3 SENIOR OPERATORS VELAN VALVE CORP.
THIS EVENT WAS CAUSED BY INADEQUATE REVIEW OF PLANNED MAINTENANCE ACTIVI TIES.
THIS INCIDENT WILL BE REVIEWED, ADDITIONAL TRAINING CONDUCTED AND PROCEDURES REVISED TO STRENGTHEN BOTH PROCEDURAL AND MANAGEMENT CCNTROL S.
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NOV OS, 1979 LER MONTHLY REPORT SORTED BY FACILITY PAGE 69 PROCESSED DURING OCTOBER, 1979 FOR PCWER REACTORS FACILITY / SYSTEM / COMPONENT /
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REPORT DATE/
EVENT GESCRIPTION/
CAUSE SUBCODE/ MANUFACTURER CCHTROL NO.
REPORT TYPE CAUSE DESCRIPTION PILGRIM-1 05000293 072579 OH JULY 25, 1979 WHILE PLACING THE "B" RHR LOOP IN SUPPRESSION POOL COOL RESIDUAL HEAT REMOV SYS + CONT 79-030/03L-0 081679 ING, MOV-1001-36B WAS GIVEN A SIGNAL TO OPEN AND ITS MOTOR CONTROL CENTE VALVES 026760 30-DAY R BREAKER TRIPPED ON OVERLOAD.
SURVEILLANCE TESTING WAS CONDUCTED FOR 0 CLOBE NE CONTAINMENT COOLING SUBSYSTEM INOPERABLE AND THE BREAKER OVERLOAD TRI COMPONENT FAILURE P WAS INVESTIGATED. IT WAS DISCOVERED THAT THE VALVE STEM GUIDE KEY HAD OTHER SHEARED.
THIS WAS THE 4TH SUCH FAILURE SINCE JULY, 1974 FOR MOVS 1001-ANCHOR / DARLING VALVE CO.
36A & B.
VALVE STEM GUIDE KEY FOUND TO BE OF MARGINAL DESIGN FOR THE APPLICATION.
STEM CLAMPS PREVIUUSLY HELD IN PLACE USING THIS KEY WILL BE MODIFIED TO USE SET SCREWS.
PILGRIM-1 05000293 081679 DURING A SEISMIC EVENT WITH OR WITHOUT LOCA, THE UNIT AUXILIARY TRANSFOR ENERG GENERATOR SYS + CONTROLS 7 9- 0 31/ 01 T- 0 082879 MER BREAKERS A505 AND A605 MAY NOT BE TRIPPED OPEN AUTOMATICALLY BY THE COMPONENT CODE NOT APPLICABLE 026761 2-WEEK EXISTING TRIP SIGNALS BECAUSE THESE TRIP SIGNALS COME FROM HON SEISMICAL SUBCOMPONENT NOT APPLICABLE LY QUALIFIED SOURCES.
HENCE THE EMERGENCY DIESEL GENERATOR BREAKERS A50 DESIGH/ FABRICATION ERROR 9 AND A609 COULD HOT CLOSE ALTGMATICALLY SIHCE THE UNIT AUXILIARY BREAKE DESIGN RS ARE NOT TRIFPED.
ITEM NOT APPLICABLE AUX. TRIP RELAYS ASSOCIATED WITH TRIP LOGIC FOR UNIT AUX. BREAKERS WERE NOT ORIGINALLY SPECIFIED TO BE SEISMICALLY QUALIFIED. UNIT AUX. TRANSFO C5)
RMER BREAKER CONTROL CIRCUITS MODIFIED SO A TRIP WILL OCCUR FROM AN UNDE RVOLTAGE AT A5
- A6 BUSES SY UTILIZING SPARE CONTACTS OF SEISMICALLY QUA LIFIED UNDERVOLTAGE RELAYS.
TRIPS ARE BACKUP TO ORIGINAL TRIP CIRCUITS.
PILGRIM-1 05000293 082179 AT 2200 OH AUCUST 21, 1979 WHILE PERFORMING SURVEILLANCE TEST 8.M.1-16 R ENGNRD SAFETY FEATR INSTR SYS 79-034/03L-0 083079 EACTOR PRESSURE PERMISSIVE IT WAS OBSERVED THAT PRESSURE SWITCHES 263-51 INSTRUMENTATION + CONTROLS 026711 30-DAY B AND 263-51D ACTUATED AT PRESSURES BEYOND THE TECH. SPEC. LIMIT OF 613 SWITCH PSI.
CGMPONENT FAILURE ELECTRICAL BARKSDALE COMPANY CALIBRATIDH CHECKS REVEALED THAT P.S. 263-51B ACTUATED AT 625 PSI AND P.
S. 263-51D ACTUATED AT 615 PSI.
THESE INSTRUMENTS HAD EXPERIENCED A SET POINT DRIFT.
THEY WERE RECALIBRATED, SATISFACTORILY TESTED AND RETURHED TO SERVICE.
PILGRIM-1 05000293 082679 ON AUGUST 26, 1979 AT 0912 THE DRIVE BELT ON THE REACTOR COOLANT LEAK DE REAC COOL PRES BOUN LEAK DETEC 79-035/03L-0 091479 TECTION AIR SAMPLING SYSTEM (PANEL C-19) WAS FOUND BROKEN.
OTHER COMPONENTS 026866 30-DAY SUBCCMPONENT NOT APPLICABLE COMPONENT FAILURE OTHER HUCLEAR MEASUREMENTS CORP.
THE DRIVE SYSTEM SHEAVES WERE FOUND MISALIGNED. THIS CAUSED THE DRIVE B ELT TO WEAR AND EVENTUALLY BREAK.
THE SHEAVES WERE REALIGNED, A NEW BEL T WAS INSTALLED AND THE SYSTEM RETURHED TO MORMAL ON AUGUST 28, 1979.
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REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CCHTROL NO.
REPORT TYPE CAUSE DESCRIPTION PILGRIM-1 05000293 082879 ON AUGUST 18, 1979 AT 0030 HRS, A REACTOR SCRAM OCCURRED AS A RESULT OF OFFSITE POWER SYSTEMS + CCNTRL 79-033/01T-0 091179 A LOSS OF Att OFF-SITE POWER.
THE EMERGENCY DIESEL GENERATORS FUNCTIONE COMPONENT CODE NOT APPLICABLE 026781 2-WEEK D AS REQUIRED AND ASSUMED EMERGENCY LOADS.
A RELIEF VALVE WAS MANUALLY SUBCOMPOSENT N01 APPLICABLE ACTUATED TO CONTROL PRESSURE AND MANEUVER THE REACTOR TO A SAFE SHUTDOWN EXTERNAL CAUSE HOT APPLICABLE ITEM NOT APPLICABLE THE CAUSE OF THIS EVENT WAS LIGHTNING STRIKING THE STATION SWITCHYARD CA USING A HIGH SPEED RELAY OPERATION FOR A LINE TO GROUND FAULT.
PCWER WA S RESTORED TO THE STARTUP TRANSFORMER AHD STATION LOADS RETURHED TO NORM AL AFTER APPROXIMATELY 30 MINUTES.
PILGRIM-1 05000293 082879 DURING EVALUATION PERFORMED IN RESPONSE TO IE BULLETIN 79-01, DRYWELL SU CNTHMNT ISOLATION SYS 4 CONT 79-032/01T-0 091179 MP CONTAINMENT ISCLATION VALVES A0-7011A&B AND A0-7017A38 WERE DETERMINE VALVE OPERATORS 026863 2-WEEK D TO BE UNQUALIFIED'FOR SERVICE. POSTULATED FAILURE CONSIDERED IS UNDET SOLENDID - AC ECTED CARRYOVER (SYPHON) 0F DRYWELL SUMP CONTAMINATED WATER DUE TO CONCU DESIGN / FABRICATION ERROR RRENT HIGH DRYWELL PRESSURE AND HIGH RADIATION EXPOSURE IN THE TORUS COM MANUFACTURING PARTMENT FOLLOWING LOCA.
ASCO FAILURE IDENTIFIED IS VIA HIGH RADIATION EXPOSURE TO SOLEHOID VALVE INTE RNALS, SYNTHETIC MATERIALS, FOLLOWING LOCA. FORMAL LICENSED OPERATOR TRA INING IS BEING CONDUCTED CONC 2HTRATING ON SYMPTOM RECOGNITION AND CORREC TIVE RESPONSES. APPLICABLE EMERGENCY PROCEDURES ARE BEING REVISED TO ASS URE OP ACTION. QUALIFIED REPLACEMENT SOLEHOID VLVS WILL BE INSTALLED.
POINT BEACH-1 05000266 080479 AT 0615 HRS, 8-3-79, LHILE PROCEEDING TO A COLD SHUTDOWN CONDITION WITH REACTOR CCHTAINMENT SYSTEMS 79-011/01T-0 081479 REACTOR COOLANT SYSTEM AT 393 PSIG & 343 DEG, CONTAINMENT INTEGRITY WAS MECHANICAL FUNCTION UNITS 026743 2-WEEK BRIEFLY VIOLATED.
VIOLATION OCCURRED WHEN THE INSIDE CONTAINMENT DOOR W SUBCOMPONENT NOT APPLICABLE AS OPEHED WITH THE OUTSIDE DOOR ALREADY OPEH.
CONTAINMENT INTEGRITY WAS COMPONENT FAILURE QUICKLY REESTABLISHED BY SHUTTING INSIDE DOOR.
TS 15.3.6.A.A REQUIRES MECHANICAL THAT CONTAINMENT INTEGRITY NOT BE VIOLATED UNLESS THE REACTOR IS IN A CO PITTSBURGH-DES MOINES STEEL CO LD SHUTDOWN CONDITION.
ORDINARILY INSIDE & UUTSIDE DOORS ARE PREVENTED FRCM BEING OPEHED SIMULT ANEOUSLY BY A MECHANICAL INTERLOCK.
IN THIS INSTANCE THE INTERLOCK FAIL ED DUE TO A ROLL PIN FALLING OUT OF A CONNECTING ROD IN THE MECHANISM.
THE INTERLOCK WAS REPAIRED AND SATISFACTORILY TESTED ALONG WITH A QUALIF YING AIR TEST OF THE PERSONNEL HATCH BY 2045 HOURS, 8-4-79.
POINT BEACH-1 05000266 083079 AT 1158 HRS, 8/29/79, UNIT 1 WAS TAKEN OFF LINE FOR REPAIR OF 324 GALLON COOLANT RECIRC SYS + CONTROLS 79-013/01T-0 091479 S PER DAY STFAM GENERATOR PRIMARY-TO-SECONDARY LEAKAGE.
THE LEAKAGE HAD HEAT EXCHANGERS 026917 2-WEEK INCREASED GRADUALLY FROM A 150 GALLON PER DAY RATE WHICH WAS DISCOVERED STEAM GENERATOR AFTER THE UNIT HAD RECOVERED FROM A PREVIOUS STEAM GENERATOR REPAIR OUT COMPONENT FAILURE AGE OH 8/18/79.
THIS EVENT IS REPORTABLE PER T.S.
15.6.9.2.A.3 AND SIMI MECHANICAL LAR TO LER'S 78-001/01T-0, 78 -010 / 01 T-1, 79-003/01T-0 AND 79-012/01T-0.
WESTINGHOUSE ELE ( RIC CORP.
LEAK TESTING REVEALED CNE LEAKING TUBE AT R20C37 IN THE "A" STEAM GENERA TOR INLET.
REANALYSIS OF EDDY CURRENT TESTING DATA TAKEN DURING THE PRE VIOUS STEAM GENERATOR REPAIR OUTAGE REVEALED INDICATIONS OF AM 88 PERCEN T DEFECT LOCATED JUST BELOW THE TOP OF THE TUBESHEET BURIED IN A NOISY S IGNAL.
THE TUBE WAS MECHANICALLY PLUGGED.
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NOV 08, 1979 LER MONTHLY REPORT SORTED BY FACILITY PAGE 72 PROCESSED DURING OCTOBER, 1979 FOR PCWER REACTORS FACILITY / SYSTEM / COMPONENT /
DOCKET NO./
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EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTIDH PRAIRIE ISLAND-2 05000306 091979 DURING A POWER REDUCTION TO BELOW 90% FOR AXIAL OFFSET CALIBRATION, AXIA REACTOR CORE 79-026/01T-0 100379 L FLUX DIFFERENCE WAS ALLOWED TO LEAVE THE TARGET BAFD WHILE REACTOR POW COMPONENT CODE NOT APPLICABLE 026975 2-WEEK ER WAS STILL ABOVE 90%
PCUER WAS REDUCED TO BELOW 9C% IN HALF AH HOUR.
SUBCOMPONENT NOT APPLICABLE SUBSEQUENT FLUX MAPS SHOWED THAT THE SAME FLUX DISTRIBUTION AT 10C% POW PERSONNEL ERROR ER WOULD NOT HAVE PRODUCE 0 UNACCEPTABLE PEAKING FACTORS.
NO EFFECT ON P LICENSED 8 SENIOR OPERATORS UBLIC HEALTH OR SAFETY.
ITEM NOT APPLICABLE PERSONMEL ERROR.
POWER WAS REDUCED TO BELOW 90%.
THE EVENT WAS DISCUSS ED WITH INVOLVED PERSONNEL.
ALL LICENSED OPERATORS AND LICENSE CANDIDAT ES WILL REVIEW THE LVENT REPORT.
RANCHO SECO-1 05000312 052979 WHILE SHUTDOWN IN MAY OF 1979, A REVIEW OF EFFLUENT MONITORING CHARTS IN OTHER AUX WATER SYS + CONTROLS 79/001/04T-0 061379 DICATED THE PLANT LIQUID EFFLUENT PH EXCEEDED THE 8.5 LIMIT ESTABLISHED INSTRUMENTATION + CONTROLS 026816 2-WEEK BY TECHNICAL SPECIFICATIONS, APPENDIX B.
SECTION 2.4 ON ONE OCCASION.
T SENSOR / DETECTOR / ELEMENT HIS OCCURRED MAY 29 AND LASTED FOR APPROXIMATELY 5 HOURS.
MAXIMUM PLANT CGMPONENT FAILURE WATER DISCHARGE FH WAS 8.9.
OTHER ITEM NOT AFPLICABLE SUSPECTED CAUSE BEING THE ERRCR BAND ASSOCIATED WITH THE PH ALARM SETPOI HT.
DISTRICl IS INVESTIGATING FEASIBILITY OF REDUCING ERROR BAND ON THI S INSTRUMENT.
IN ADDITION, UTILIZING INDIVIDUAL ALARMS RATHER THAN A C0 MMON ALARM ON EFFLUENT PARAMETERS IS BEING CONSIDERED.
RANCHO SECO-1 05000312 071979 WHIL6 PERFORMING MONTHLY DHR PUMP SURVEILLANCE (SP 203.05G) ON "B" DHR P RESIDUAL HEAT REMOV SYS + CONT 79-008/03L-0 080979 UMP, LEAKAGE IN EXCESS OF 0.63GPH ALLOWABLE PER T.S.
SECTION 4.5.3.1 WAS PUMPS 026886 30-DAY OBSERVED AT THE PUi1P SEAL. SYSTEM WAS DECLARED INOPERABLE AND ITS REDUN CENTRIFUGAL DANT SYSTEM TESTED SATISFACTORY. SIMILAR EVENTS OCCURRED WITH THIS PUMP CONPONENT FAILURE ON 10-18-76 AND 6-22-78. THESE WERE REPORTED TO YOUR OFFICE AS LER'S NO.
MECHANICAL
'S 76-13 AND 78-07.
BABCOCK 4 WILCOX CANADA LTD.
THE LEAKING SEAL WAS REPLACED AND THE SYSTEM TESTED PER APPLICABLE SURVE ILLANCE TESTS.
THE TEST RESULTS WERE ACCEPTABLE AND THE SYSTEM WAS DECL ARED OPERABLE.
RANCHO SECO-1 05000312 081479 ON AUGUST 14, 1979, CONTRARY TO TECH. SPEC. SECTION 3.3.1, THE BORATED W CHEM, VOL CONT + LIQ POISH SYS 79-009/03L-0 090679 ATER STORAGE TANK (BWST) HAD LESS THAN 1800 PPM BORON CONCENTRATION.
RE COMPONENT CODE NOT APPLICABLE 026915 30-DAY ACTOR SHUTDCWN WAS COMMENCED SIMULTANEOUSLY WITH ADDITION OF CONCENTRATE SUBCOMPONENT NOT APPLICABLE D BORIC ACID TO THE TANK.
UPON ACHIEVING >1800 PPMB, THE SHUTDOWN WAS T PERSONNEL ERROR ERMINATED.
LICENSED 8 SENIOR OPERATORS ITEM NOT APPLICABLE PREVIOUS DAYS SAMPLE SHOWED LESS THAN HORMAL, BUT ABOVE TECH SPEC LIMIT.
OPERATIONS PERSONNEL RECIRCULATED THE TANK.
THIS WAS INEFFECTIVE. WHE gy3 N INFORMED OF LESS THAN 1800 PPMB, ADDED CONCENTRATED BORIC ACID TO BRIN G CONCENTRATION BACK ABOVE THE 1800 PPMB LIMIT.
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REPORT DATE/
EVENT DESCRIPTIOH/
CAUSE SUBCODE/ MANUFACTURER CONTROL HO.
REPORT TYPL CAUSE DESCRIPTION RANCHO SECO-1 0S000312 082979 DURING ROUTINE PLANT OPERATIONS, IT WAS HOTICED THAT THE BLPB's.FOR THE ONSITE POWER SYSTEM + CONTROL 79-010/03L-0 091279 HSCW PUMP P-482B WERE NOT LIT.
AFTER CHANGING LIGHT BULBS WITH NO CHAHG CIRCUIT CLOSERS / INTERRUPTERS 026929 30-DAY E THE BREAXER CUBICLE WAS CHECKED.
IT WAS DISCOVERED THAT THE D.C.
CONT CIRCUIT BREAKER ROL POWER BREAKER WAS IN THE OFF POSITION CONTRARY TO T.S.
SECTION 3.3.1 PERSONNEL ERROR
.D.1.
ONLY OHE HSCW PUMP COULD BE CONSIDERED GPERABLE AT THAT TIME.
MAINTENANCE & REPAIR PERSOHNEL I-T-E CIRCUIT BREAKER SINCE BREAKER MAINTENANCE HAD BEEN IN PROGRESS FOR SEVERAL DAYS, IT IS F ELT THE CREAKER WAS INADVERTENTLY SHUT OFF WHILE PERFORMING MAIHTEHANCE ON A BREAKER IN THE SAME CUBICLE.
THE D.C.
CONTROL POWER WAS RESTORED A ND THE UNIT SUCCESSFULLY TESTED PRIOR TO BEING DECLARED OPERABLE.
RANCHO SECO-1 05000312 083079 DURING ROUTINE OPERATION AN OPERATOR OBSERVED THE SPRING CHARGING DISCON ONSITE POWER SYSTEM + CONTROL 79-011/03L-0 091379 HECT SWITCH ON BREAKER S23A14 IN THE OFF POSITION. UPON PLACING THE SWI CIRCUIT CLOSERS / INTERRUPTERS 026928 30-DAY TCH IN THE ON POSITION THE CHARGING MOTOR STARTED AND CHARGED THE SPRING SWITCH (OTHER THAH SENSOR) 5.
THIS INDICATED THAT THE SPRINGS WERE UNCHARGED AND UP UNTIL THEN THE PERSONNEL ERROR BREAKER WOULD HAVE TO BE CONSIDERED IHOPERABLE.
THE BREAKER SUPPLIES T NOHLIC. OPERATIONS PERSONNEL HE RX BLDG. EMERG. COOLER A-500C.
IHOPERABILITY OF THIS UNIT IS CONTRAR I-T-E CIRCUIT BREAKER Y TO T.S.
SECTION 3.3.1.C.3.
IT IS FELT THAT IHADVERTENT REPOSITIONING OF THE DISCOHHECT SWITCH WAS T HE CAUSE.
TO MINIMIZE RECURRENCE, LOG SHEETS HAVE BEEN INITIATED WHICH WILL VERIFY THE SWITCHES IN THE PROPER POSITION ON ALL NUCLEAR SERVICE B USES ONCE EACH SHIFT.
ROBERT E.
GINNA-1 05000244 040679 DURING MAINTENANCE OH BORIC ACID, FLOW CONTROL VALVE LEAK WAS NOTED ON V CHEM, VOL CONT + LIQ POISH SYS 79-008/04L-0 050779 ALVE OUTLET 1" N!PPLE.
(T.S. 6.9.2.D.(4)) TWO FLOW PATHS FROM BORIC ACI PIPES, FITTINGS 026806 30-DAY D TANKS TO RCS WERE VERIFIED.
LESS THAN 4 INCHES COMPONENT FAILURE METALLURGICAL ITEM NOT APPLICABLE IHTERNAL WELD FLOWTHROUGH DEFECTS AND DEEP EXTERNAL PITTING.
THE 1" NIP PLE IS 3 1/2" LONG SCH 10 STAINLESS.
IT IS HEAT TRACED. AND NORMAL OPER ATING PRESSURE IS 100 PSIG.
THE HIPPLE WAS REPLACED WITH A SCH 40 NIPPL E.
LATER MAINTENANCE IN THIS SECTION OF PIPING RESULTED IN REPLACEMENT OF NIPPLES, CHECK VLV 4 COUPLING FROM FLOW COHTROL VLV TO THE COUPLING.
ROBERT E.
GINHA-1 05000244 040679 DURING MAINTENANCE ON EORIC ACID FLOW CONTROL VALVE LEAKS WERE NOTED OH CHEM, VOL COHT + LIQ POISN SYS 79-008/03X-1 082179 VALVE OUTLET 1" HIPPLE.
(T.S. 6.9.2.B.(4).
TWO FLOW PATHS FROM BORIC A PIPES, FITTINGS 027001 OTHER CID TANKS TO RCS WERE VERIFIED. NIPPLE WAS REPLACED WITH SCH 40 NIPPLE.
LESS THAN 4 INCHES LATER, NIPPLES, CHECK VALVE AND COUPLING FROM CONTROL VALVE TO COUPLING COMPONENT FAILURE WERE REPLACED.
METALLURGICAL ITEM NOT APPLICABLE SEVERE EXTERNAL CAUSTIC PITTING PROBABLY STARTED PROCESS CAUSING LEAKS.
METALLURGICAL ANALYSIS IDENTIFIED THIS COMBINED WITH THROUGHWALL CHLORID E STRESS CORROSION CRACKING.
1" HIPPLE IS 3 1/2" LONG SCH 10 SS, HEAT T RACED, NORMAL OPERATING PRESSURE 100 PSIG. OTHER HEAT TRACED PIPIHG AREA S INVOLVING SIMILAR CONDITIONS EXAMINED; NO PROBLEMS FOUND.
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REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL HO.
REPORT TYPE CAUSE DESCRIPTION SALEM-1 05000272 031279 A PROGRAM BEING RUN ON THE PLANT COMPUTER TO CALIBRATE A CONTROL ROOM RE CIRCULATING WATER SYS + CON 79-023/04L-0 041279 CORDER DISRUPTED HORMAL CONDENSER TEMPERATUPF INDICATION IN THE CONTROL CCMPONENT CODE NOT APPLICABLE 026885 30-DAY ROOM. LOCAL TEMPERATURE READINGS WERE NOT MONITORED PER ETS 2.1.1.A, 2.1 SUBCOMPONENT NOT APPLICABLE
,1.B.
2.1.2 &
2.1.3.
PLANT WAS OPERATING AT 65% POWER WHILE COND5NSER W PERSCHNEL ERROR ATER BOXES WERE CLEANED. EVENT LASTED 2 HOURS 32 MINUTES. HD DANGER TO P OTHER UBLIC HEALTH AND SAFETY.
ITEM NOT APPLICABLE COMPUTER OPERATOR DEVELOPING THE CALIBRATION PROCEDURE DID NOT OBSERVE N ECESSARY PRECAUTIONS TO INSURE THAT MONITORING REQUIREMENTS WERE NET. CA LIBRATION PROCEDURE FUR CONDENSER CIRCULATING WATER TEMPERATURE RECORDER HAS BEEN PROPERLY WRITTEN, REVIEWED AND APPE0VED AND WILL INSURE MONITO RING CONTINUITY DURING SUCH PROCEDURES.
SALEM-1 05000272 082479 DURING FIRST REFUELING OUTAGE, AS FOLLCW-UP TO NRC INSPECTION 50-311/79-FEEDWATER SYSTEMS + CONTROLS 79-054/01T-0 090779 19, THREE SNUBDERS ON NO.
14 MAIN FEEDWATER LIHE WTRE FOUND TO HAVE FAIL HANGERS SUPPORTS SHOCK SUPPRSS 026978 2-WEEK ED IN PLACE.
THESE SHUBBERS WERE INCLUDED IN STRESS CALCULATIONS FOR SE SHUBBER3 ISMIC SAFETY ANALYSIS OF NUCLEAR PORTION OF MAIN FEEDWATER PIPING.
PUBL CCMPONENT FAILURE IC SERVICE ENGINEERING DEPARTMENT IS PERFORMING A SAFETY ANALYSIS OF THI MECHANICAL S OCCURRENCE WHICH WILL BE SUBMITTED IN A SUPPLEMENTAL REPORT.
THIS IS PACIFIC SCIENTIFIC CO.
THE FIRST OCCURRENCE OF THIS TYPE.
THE THREE FAILED SNUBBERS WERE REPLACED IN KIND.
SHUBBERS CH NO.
11, 12 AHD 13 MAIN FEEDWATER SYSTEMS WERE CHECKED SATISFACTORY.
THE CAUSE OF THE FAILURE IS BEING INVESTIGATED AHD WILL BE REPORTED IN A SUPPLEMENTAL REPORT.
SALEM-1 05000272 083079 IN RESPONSE TO A HRC QUESTION CONCERNING OPERATION OF CONTAINMENT VENTIL CHThMNT ISOLATION SYS + COHT 79-055/01T-0 091379 ATION ISOLATION VALVES, A REVIEW OF THE OPERATING CHARACTERISTICS OF VAL VALVE OPERATORS 026993 2-WEEK VES IN THE 10 INCH & 36 INCH CONTAINMENT PENETRATION LINES SHOWED THAT U PHEUMATIC/ DIAPHRAGM / CYLINDER NDER CERTAIH ACCIDENT CONDITIONS THE VALVE ACTUATORS MAY HAVE INSUFFICIE OTHER HT TORQUE TO FULLY CLOSE THE VALVES FROM THE FULLY OPEN POSITION. THIS I HOT APPLICABLE S THE FIRST UCCURRENCE OF THIS TYPE.
OTHER THIS OCCURRENCE IS UNDER INVESTIGATION BY THE ENGINEERING DEPARTMENT. WH EN THE EVALUATION IS COMPLETE. THE CAUSE, CORRECTIVE ACTION AND SAFETY A NALYSIS WILL BE SUBMITTED IN A SUPPLEMENTAL REPORT.
SALEM-1 05000272 083179 IN RESPONSE TO A HRC QUESTION ON SALEM UNIT 2 REGARDING RHR PUMP NPSH DU RESIDUAL HEAT REMOV SYS + CONT 79-056/01T-0 091479 RING POST LOCA OPERATION, TESTS PERFORMED ON UNIT 2 RHR SYSTEM INDICATED CCMPONENT CODE NOT APPLICABLE 026992 2-WEEK RHR PUMP FLOW EXCEEDED DESIGN RUNOUT FLOW. SINCE UNIT 1 HAS AN IDENTICA SUBCOMPONENT NOT APPLICABLE L CONFIGURATION AS UNIT 2, THIS UNACCEPTABLE CONDITION EXISTS ON UNIT 1.
DESIGN / FABRICATION ERROR ENGINEERING DEPARTMENT IS EVALUATING THIS CONDITION & A SUPPLEMENTAL RE DESIGN PORT WILL BE SUBMITTED. THIS IS THE FIRST OCCURRENCE OF THIS TYPE.
ITEM NOT APPLICABLE IT IS EVIDENT BY TEST RESULTS THAT THE RHR SYSTEM FLOW RESISTANCE IS LCW A DESIGN CHANGE TO INCREASE FLOW RESISTANCE BY RESIZING THE ORIFICES I N THE FLOW ELEMENTS UPSTREAM AND DOWNSTREAM OF THE HEAT EXCHANGER IS IN PREPARATION. ESTIMATED TIME TO COMPLETE THIS CHANGE IS THREE WEEKS.
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REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL HO.
REPORT TYPE CAUSE DESCRIPTION SALEM-1 05000272 090779 DURING INSPECTION OF PIPE HANGERS ON SEISMIC I SYSTEMS IN ACCORDANCE WIT SYSTEM CODE NOT APPLICABLE 79-057/01T-0 092079 H NRC BULLETIN 79-14, THREE HANGERS ON THE SI AND CVC SYSTEMS WERE FOUND HANGERS, SUPPORTS, SHOCK SUPPRSS 026835 2-WEEK TO HAVE A CROKEN WELD, BROKEN BOLT AND A BROKEN PIPE GUIDE.
FURTHER IN HANGERS VESTIGATION IS PRESENTLY UNDERWAY.
THIS IS THE FIRST OCCURRENCE OF THIS OTHER TYPE.
HOT APPLICABLE OTHER WORK ORDERS ARE 2EING INITIATED BY MAINTENANCE DEPARTMENT TO REPAIR THE DEFECTIVE HANGERS AS THEY ARE IDENTIFIED. RESULTS CF THE INSPECTION, CA USE AND SAFCTY ANALYSIS WILL BE SUBMITTED IN A SUPPLEMENTAL REPORT.
SALEM-1 05000272 090779 WESTINGHOUSE HAS NOTIFIED US THAT A REVIEW OF THE ENVIORHMENTAL QUALIFIC SYS REQRD FOR SAFE SHUTDOWN 79-058/01T-0 092079 ATIDH OF HSSS EQUIPMENT HAS IDENTIFIED THAT CONDITIONS ASSOCIATED WITH H COMP 0HENT CODE NOT APPLICABLE 026836 2-WEEK IGH ENERGY LINE BREAKS INSIDE OR OUTSIDE CONTAINMENT AND THEIR IMPACT ON SUBCOMPONENT NOT APPLICABLE N0d-SAFETY CONTROL SYSTEMS MAY CONSTITUTE AN UNREVIEWED SAFETY QUESTION OTHER THIS IS THE SECOND OCCURRENCE OF THIS TYPE (79-52).
NOT APPLICABLE WESTINGHOUSE ELECTRIC CORP.
PUBLIC SERVICE ENGINEERING DEPARTMENT IS EVALUATING THE SALEM CCHTROL SY STEMS IDENTIFIED BY WESTINGHOUSE. THE RESULTS OF THE INVESTIGATION WILL BE REPORTED AT A LATER DATE.
SALEM-1 05000272 090779 DURING PERFORMANCE OF 18 MONTH SURVEILLANCE OF SAFEGUARDS SYSTEMS AND RM DC ONSITE POWER SYS + CONTROLS 79-060/03L-0 100579 S CONTAINMENT ISOLATICH FUNCTIONAL TEST, SEVERAL SAFEGUARD SYSTEMS COULD CIRCUIT CLOSERS /INTERRU"TERS 026969 30-DAY NOT BE RESET DUE TO THE 28 VOLT DC C0HTROL POWER BREAKERS BEING TRIPPED CIRCUIT BREAKER PERFORMANCE DEPARTMENT INVESTIGATED THE PROBLEM AND INITIATED CORRECT DESIGN / FABRICATION ERRSA IVE ACTION.
FUNCTIONAL TESTS OF THE SAFEGUARD SYSTEM DURING NORMAL OPER DESIGN ATION HAVE BEEN PERFORMED SATISFACTORILY TO VERIFY SYSTEM OPERABILITY.
HEINEMAHN ELECTRIC CO.
THIS IS THE FIRST OCCURRENCE OF THIS TYPE.
THE CAUSE OF THIS OCCURRENCE WAS THE 28 VOLT DC EREAKER WHICH IS A 1 AMP LOAD BREAKER WHILE POSSIBLE CIRCUIT LOAD IS APPROXIMATELY 2 AMPS.
THE BREAKERS ARE BEING REPLACED UNDER DCR IPD-0153 WITH 2 AMP BREAKERS.
THE DCR WILL BE IMPLEMENTED PRIOR TO ENTRY INTO MODE 4.
SALEM-1 05000272 091079 DURING THE Q.A.
SURVEILLANCE OF THE AUXILIARY BUILDING, TWO (2) FOUR INC SYSTEM CODE NOT APPLICABLE 79-061/03L-0 100979 H CONDUITS PENETRATING THE E1 84 FLOOR WERE FOUND NOT SEALED OR CAPPED COMPONENT CODE NOT APPLICABLE 027008 30-DAY AND H0 FIRE WATCH WAS POSTED.
THE SENIOR SHIFT SUPERVISOR AND ThE MAINT SUBCOMP0HENT NOT APPLICABLE ENANCE CONTRACTOR WERE NOTIFIED.
THE CONDUITS WERE PROPERLY SEALED BY 1 PERSONNEL ERROR 120 HOURS'.
THE PENETRATIONS HAD BEEN OPEN WITH NO FIRE WATCH FOR APPROX CONTRACT.
- CONSULT. PERSOHHEL IMATELY 96 HOURS.
ITEM NOT APPLICABLE THIS INCIDENT WAS DUE TO A MISINTERPRETATION OF THE REQUIREMENTS OF MAIN TENANCE PROCEDURE M3Y.
A MEMORAhDUM HAS BEEN ISSUED TO CLARIFY THE PROC EDURE AND ALL SUPERVISORS AND CRAFT FOREMEN. WHO MAY BECOME INVOLVED IN BREAKING FIRE BARRIERS. HAVE BEEN RETHSTRUCTED IN THE REQUIREMENTS OF TH LJ1 E FIRE AND FLOOD BARRIER PROCEDbRE.
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REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/MAHUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION SAN ONOFRE-1 05000206 010979 ANNUAL AUDIT OF THE ENVIRONMENTAL TECHNICAL SPECIFICATIONS DETERMINED TH SYSTEM CODE NOT APPLICABLE 79-004/04L-0 041979 AT ON TWO SEPARATE OCCASIONS 30 DAY WRITTEN REPORTS WERE NOT SUEMITTED P COMPONEHT CODE NOT APPLICABLE 026813 30-DAY ER ETS 5.6.3.B(3) REPORTING THE LOSS OF QUARTERLY BENTHIC SURVEY DATA.
SUBC0f1P0HENT NOT A?PLICABLE DURING THE 1ST AND 2ND QUARTERLY BENTHIC SURVEYS IN 1978, DATA COULD OHL PERSONNEL ERROR Y BE COLLECTED FROM ONE OF ELEVEN AND FIVE OF ELEVEN BENTHIC STATIONS. R OTHER ESPECTIVELY. NO EFFECT ON THE ENVIRONMENT CR PLANT SAFETY.
ITEM HOT APPLICABLE PERSONNEL RESPONSIBLE FOR IMPLEMENTATION OF ETS FAILED TO REALIZE HECESS ITY OF REPORTING OCCURRENCES.
THIS EVENT AND REPORTING REQUIREf1ENTS HAV E BEEN REVIEWED WITH COGNIZANT PERSONNEL STRESSING THE HEED FOR RECOGNIZ ING REPORTABLE OCCURREHCES.
SAN ONOFRE-1 05000206 040279 SEA TEMPERATURE DATA FROM THREE SENSORS WERE HDT OBTAINED FOR THE FOLLOW SYSTEM CODE NOT APPLICABLE 79-005/04L-0 050179 ING TIME PERIODS: STATION C25, SURFACE TEMP-, 9/28-10/10/78; STATION C2 INSTRUMENTATION + CONTROLS 026814 30-DAY 25, SURFACE TEMP., 1/10-2/8/79; STATION C225, MID-DEPTH TEMP.. 2/8-3/12/
RECORDER 79.
THESE SENSORS PROVIDE TEMPERATURE DATA FOR DEFINING THE DISCHARGE P COMPONENT FAILURE LUME AS REQUIRED BY ETS 3.1.1 A(5).
LOSS OF DATA FOR THE ABOVE STATIONS MECHANICAL AND TIME PERIODS HAD NO EFFECT ON THE ENVIRONMENT OR PLANT SAFETY.
OTHER STATION C2S SURFACE TEMP.
DOUBLE FILM IMAGE ON CARTRIDGE PROHIBITED AC CURATE DATA RETRIEVAL. STATION C225 SURFACE TEMP.
JAMMED FILM CARTRID GE.
STATION C22S MID-DEPTH TEMP.
TORN FROM ANCHORAGE.
ALL UNITS HAVE BEEN REPAIRED OR REPLACED.
DUPLICATE BACKUP SYSTEf15 TO IMPROVE RELIABI LITY ARE UNDER INVESTIGATION.
SAN ONOFRE-1 05000206 080579 DURING A CIP,CULATING WATER SYSTEM HEAT TREATMENT, WITH THE UNIT AT REDUC SYSTEM CODE NOT APPLICABLE 79-012/03L-0 083079 ED LOAD, IT WAS NOTED THAT FISH IMPINGEMENT DATA, WHICH INCLUDES NUM3ER, COMP 0HENT CODE NOT APPLICABLE 026890 30-DAY SIZE, WEIGHT, COHDITION AND REPRODUCTIVE STATE OF ALL FISH SPECIES. WAS SUBCOMPONENT NOT APPLICABLE NOT COLLECTED AS REQUIRED BY ETS 3.1.2 A(2)A.
THERE WAS NO EFFECT ON T PERSONNEL ERROR HE ENVIRONME"T OR PLANT SAFETY.
OTHER ITEM HOT APPLICABLE PERSONNEL RESPONSIBLE FOR THE ACTIVITY WERE NOT NOTIFIED OF THE HEAT TRE ATMENT NOR WAS THEIR PRESENCE ON SITE VERIFIED.
APPROPRIATE PROCEDURES ARE BEING REVISED OR PREPARED, AS APPLICABLE, TO NOTIFY AND VERIFY THAT THE PROPER PERSONNEL ARE PRESENT TO COLLECT THE DATA.
THIS SAME INFORMA TION HAS BEEN REVIEWED AND STRESSED WITH CONGIZANT PERSONNEL.
SAN ONOFRE-1 05000206 080679 ROUTINE MONTHLY DRINKING WAIER SAMPLES FOR TRI-CITIES MUNICIPAL WATER DI AREA MOHITORING SYSTEMS 7 9-011/ 0 3 L-0 083179 STRICT FOR THE MONTH OF MAY, 1979 WAS LOST.
LOSS OF DATA HAS NO EFFECT COMPONENT CODE NOT APPLICABLE 026887 30-DAY OH THE ENVIRONMENT OR PLANT SAFETY.
SUBCOMPONENT NOT APPLICABLE PERSONNEL ERROR RADIATION PROTECTION PERSONNEL ITEM NOT APPLICABLE REPLACEMENT OF LOST DATA WAS DUE TO PERSONNEL ERROR IN CONJUNCTION WITH LACK OF ADMINISTRATIVE CONTROLS.
APPROPRIATE PROCEDURES HAVE BEEN REVIS
~~*
ED AND COGNIZANT PERSONNEL HAVE BEEN MADE AWARE OF THE REQUIREMENTS AND (J7 ADMINISTRATIVE CONTROLS HAVE BEEN ESTABLISHED.
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REP 0;T DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTICH SEQUOYAH-1 05000327 062179 DEFICIENCY OCCURS WHEN A DIESEL CENERATOR IS BROUCHT TO OPERATING TEMPER EMERG GENERATOR SYS + CONTROLS 79-
/02L-072079 ATURE, SHUTDOWN FOR LESS THAN 3 HRS. THEN RESTxRTED. D3 MAGE CAN THEN OCC GENERATORS 026720 30-DAY UR TO THE TURBOCHARGER THRUST BEARING. LEADING TO A DISEL GENERATOR FAIL NO SUBCOMPONENT PROVIDED URE. THIS FAILURE COULD RECUCE RELIABILITY AhD AVAILABILITY OF EMERGENCY DESIGN / FABRICATION ERROR ONSITE POWER SOURCE THAT IS REQUIRED FOR THE PLANT TO ACHIEVE SAFE SHUT CAUSE SUBCODE NOT PROVIDED DOWN.
ELECTRO - MOTIVE DIV. OF G. M.
CAUSE OF THE DEFICIENCY IS THE "50AKBACK" PUMP, WHICH, DUE TO LUBE OIL V ISCOSITY, 15 UNABLE TO KEEP THE ACCESGRY LUB. OIL SYSTEM PRIMED. PROCEDU RES ARE IN EFFECT TO PREVENT RESTART DAMAGES WHILE MODIFICATIONS TO THE PUMP ARE BEING PLANNED.
ST. LUCIE-1 05000335 080179 WHILE PERFORMING A NORMAL MONTHLY FUNCTIONAL TEST IN ACCORDANCE WITH I2C REACTOR TRIP SYSTEMS 79-026/03L-0 083179 PROCEDURE 1400050, THE MINUS 1C VOLT POWER SUPPLY PS-1 IN CHANNEL A RPS INSTRUMENTATION + CONTROLS 026867 30-DAY CPC-2 (CORE PROTECTION CALCULATOR) WAS FOUND TO DE AT APPROXIt1ATELY MIN POWER SUPPLY US 13 VOLTS. ACTION IN ACCORDANCE WITH T.S.
3.3.1.1 WAS INITIATED, & PLA COMPONENT FAILURE ER SUPPLY WAS REPLACED. CPC CHANNEL MAS RESTORED TO OPERABLE STATUS WITH ELECTRICAL IN TIME lit 1IT SPECIFIED. NO ADVERSE EFFECTS RESULTED FRCM THIS OCCURENC LAMBDA ELECTRONICS E.
SPECIFIC ROOT CAUSE OF POWER SUPPLY FAILURE IS NOT KNOWN.
IT IS MOST LI KELY THAT A HORMAL END OF LIFE FAILURE OF AN ELECTRONIC COMF0HENT WAS TH E CAUSE. A NEW POWER SUPPLY WAS INSTALLED. NO ADDITIONAL ACTICH IS REQUI RED. THIS WAS THE SECOND OCCURRENCE OF A FAILED POWER SUPPLY IN THE CPC.
(REFER TO LER 335-79-25).
SURRY-1 05000280 082979 WITH BOTH UNITS AT COLD SHUTDOWN, WESTINGHOUSE NOTIFIED VEPCO THAT A GEN SYSTEM CODE NOT APPLICABLE 79-026/01T-0 091379 ERIC REVIEW INDICATES THE POSSIBILITY THAT LERTAIN BALANCE OF PLANT EQUI COMPONENT CODE HOT APPLICABLE 026844 2-WEEK PMENT, WHEN SU3JECTED TO AN ADVERSE ENVIRONMENT, COULD LEAD TO CONTROL 5 SUBCOMP0HEHT NOT APPLICABLE YSTEM OPERATIONS WHICH MAY IMPACT PROTECTIVE FUNCTIONS.
OTHER NOT APPLICABLE ITEM NOT APPLICABLE A REVIEW HAS BEEN INITIATED AND RESULTS WILL FOLLOW IN A SUPPLEMENTARY R EPORT.
THREE MILE ISLAND-2 05000320 030779 ON 3/7/79 A SAMPLE TAKEN FROM THE INDUSTRIAL WASTE FILTER SYSTEM (IMFS)
POTABLE + SAN WATER SYS + CONT 79-001/04T-0 031579 DISCHARGE YIELDED AN OIL AND GREASE CONC. OF 153 NG/ LITER, EXCEEDING THE COMPONENT CODE NOT APPLICABLE 026811 2-WEEK ETS LIMIT OF 20 MG/L.
APPROXIt1ATELY 5,000 GALLONS UERE DISCHARCED.
DU SUBCOMPONENT NOT APPLICABLE E TO RELATIVELY SMALL AMOUNT OF FLOW, TOTAL AMOUNT OF OIL AND GREASE PEL PERSONNEL ERROR EASED WILL NOT HAVE A SIGNIFICANT ADVERSE IMPACT.
NONLIC. OPERATIONS PERSOHHEL ITEM NOT APPLICABLE OPERATOR LEFT SLUDGE FROTH TANK DRAIN VALVES OPEN, ALLOWING OIL AND GREA SE FROM IWTS TO DRAIN TO IWFS WITH THE SLUDGE.
DRAIN VALVE OPERATION WI LL BE RE-EMPHASIZED TO OPERATORS.
AUTCMATIC DRAIN VALVES WILL BE INSTAL (yg LED.
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REPORT DATE/
EVENT DESCRIPTION /
C AUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION
_ TROJAN-1 05000344 080779 CURING AN IHSPECTION OF THE PL ANT, A SEISMIC RESTRAINT ON THE CONT AINMEN CNTHMNT AIR PURI + CLEANUP SYS 79-013/03L-0 090679 T SPRAY SUCTION PIPING WAS FOUND TO BE NONFUNCTIONAL WHICH COULD HAVE RE HANGERS, SUPPORTS, SHOCK SUPPRSS 026889 30-DAY SULTED IN FAILURE OF THAT SECTIGN OF LINE.
SUPPORTS OTHER HOT APPLICABLE BERGEH-PATTERSON PIPE SUPPORT THE BASE PLATE OF THE PEDESTAL SUPPORT SLID OFF THE GRAPHITE PLATE AND C RACKED THE GRAPHITE PLATE.
THE SUPPORT HAS BEEN REDESIGNED, REPAIRED, A HD RETURHED TO SERVICE.
AN ADJACENT SUPPORT WAS ALSO REDESIGHED AND REP AIRED.
VERMONT YANKEE-1 05000271 080279 NCPR WAS BELCW TECH SPEC LIMITS ON TWO OCCASIONS.
SIMILAR OCCURRENCES W REACTOR C3RE 79-018/03L-0 083079 ERE REPORTED AS RO 78-17 AND RO 78-28.
FUEL ELEMENTS 026788 30-DAY SUBCOMP0HENT NOT APPLICABLE OTHER HOT APPLICABLE ITEM NOT APPLICABLE ATTRIBUTED TO XENON TRANSIENT. BOTH EVENTS FOLLOWED PCWER CHANGES.
IN BOTH CASES ACTION WAS TAKEN TO INCREASE MCPR BY INSERTING CONTROL RODS A ND/OR INCREASING CORE FLOW.
VERMONT YANKEE-1 05000271 080279 ANCHOR BOLTS ASSOCIATED WITH SEISMIC HANGER MS-H-A10 WERE FCUND PULLED F EMERG CORE COOLING SYS + CONT 79-015/031-0 083079 ROM THE WALL.
THIS HANGER IS ON THE HPCI TURBINE STEAM LIHE.
TECH. SPE HANGERS, SUPPORTS, SHOCK SUPPRSS 026789 30-DAY C.
3.6.I.1 REQUIRES ALL SAFETY RELATED SNUBDERS TO BE CPERA3LE AT PCWER.
SUPPORTS COMPONENT FAILURE MECHANICAL ITT GRINNELL HANGER WAS REPAIRED WITHIN 72 HOURS AS ALLOWED BY TECH. SPEC. 3.6.I.2.
A REVIEW OF SEISMIC CLASS I SYSTEMS IS UNDERWAY AND ANY APPROPRIATE MODS TO THIS HANGER WILL BE MADE FOLLOWING THIS REVIEW.
VERMONT YANKEE-1 05000271 080679 HO AIR PARTICULATE AND RADICIODINE SAMPLES WERE COLLECTED AT THE HINSDAL SYSTEM CODE NOT APPLICABLE 79-019/03L-0 090579 E SUBSTATION FROM JULY 30 TO AUGUST 6 EECAUSE THE SAMPLING PUMP WAS OFF.
RELAYS 026787 30-DAY T.S.
TABLE 3.9.1 REQUIRES CONTINUGUS AIR SAMPLING.
PREVIOUS EVENTS INV SWGEAR, PROTECT., SLOW ACTING OLVING MISSED ENVIRGhMENTAL SURVIELLANCE WERE REPORTED AS LERS 76-39, 78 PERSONNEL ERROR
~18, AHD 78-1 RADIATION PROTECTION PERSONNEL ITEM NOT APPLICABLE A TECHNICIAN DID NOT SWITCH THE AIR SAMPLING PUMP DN FOLLOWING A SERVICE VISIT TO THE STATION.
THE TECHNICIAN HAS BEEN REINSTRUCTED.
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DOCKET NO./
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REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL HD.
REPORT TYPE CAUSE DESCRIPTION VERMONT YANKEE-1 05000271 081579 DURING ROUTINE SURVEILLANCE TESTING. INBOARD MSIV V2-80A WOULD NOT COME MAIN STEAM ISOL SYS + CONTROLS 79-020/03L-0 091379 FULL OPEN FOLLOWING CLOSURE. MAIN STEAM FLOW AND VALVE POSITION LIGHTS VALVE OPERATORS 026868 30-DAY GAVE CONFLICTING INFORMATION OH VALVE STATUS WHEN THE VALVE WAS AGAIH CL PHEUMATIC/ DIAPHRAGM / CYLINDER OSED.
SIMILAR EVENT REPORTED IN LER 79-11/3L.
COMPONENT FAILURE MECHANICAL ROCKWELL-INTERNATIONAL VALVE OP. SPRING PLATE WAS BINDING ON CUIDE SHAFTS. SURFACES OF GUIDE SH AFTS WERE SMOOTHED AND THE VALVE STROKED SEVERAL TIMES.
WHILE V2-80A WA 5 IHOP. THE OTBD MSIV V2-86A WAS MAINTAINED CLOSED PER T.S.
3.7.D.E.
MSI VS WILL BE INSPECTED AND REPAIRED AS NECESSARY DURING REFUELING.
VERMONT YANKEE-1 05000271 081679 DURING SURVEILLANCE TESTING FOUND BOTH TORUS LEVEL TRANSMITTERS HAD UNDE ENGNRO SAFETY FEATR INSTR SYS 79-021/CIL-0 091779 RGONE A ZERO SHIFT AND WERE INDICATING TOR' S LEVEL HIGHER THAN ACTUAL. A J
INSTRUMENTATION + CONTROLS 026959 30-DAY CTUAL LEVEL WAS BELOW TECH. SPEC. MINIMUM.
TRANSMITTER OTHFR N0( APPLICABLE RPdERTSHAW CONTROLS CD.
TRANSMITTERS SHOWED A ZERO DRIFT AND THE COMMON REFEREHCE LEG FOR THE TR AHSMITTERS WAS NOT COMPLETELY FILLED. REFERENCE LEG WILL BE CHECKED ON A WEEKLY BASIS.
INVESTIGATION IS UNDERWAY TO IMPROVE LEVEL SYSTEM RELI AB
- ILITY, TLHKEE ROWE 05000029 081379 DURING TESTING, WHILE PERFORMING LEAK RATE SURVEILLANCE CH VD-TV-202, LE OHTHMNT ISOLATION SYS + CONT 79-020/03L-0 091279 AKAGE PAST THE UPSTREAM ISOLATION VALVES RESULTED IN ABANDONMENT OF THE VALVES 026770 33-DAY TESTING.
IT HAS BEEN MORE THAN 24 MONTHS SINCE A LEAK TEST HAS BEEN COM GLOBE PLETED OH THE VALVE AS REQUIRED BY T.S.
4.6.1.2.D.
THIS IS THE FIRST EV CGMPONEHT FAILURE ENT OF THIS NATURE ASSOCIATED WITH THIS TEST.
THIS EVENT DID NOT AFFECT MECHANICAL THE ABILITY OF Tile TRIP VALVE TO PERFORM ITS INTENDED FUNCTIOH, THEREF0 MASONEILAN INTERNATIONAL, INC.
RE, H0 AD9ERSE EFFECT UPON THE PUBLIC HEALTH OR SAFETY RESULTED.
ROOT CAUSE OF THIS EVENT IS LEAKAGE BY THE SEAT OF ONE OR MORE OF THE UP STREAM ISOLATION VALVES.
THE TRIP VALVE WILL BE TESTED DURING A SHUTDOW H SCHEDUttD FOR 9/8/79 WHEN THE PRESSURE ACROSS THE ISOLATION VALVES IS LOWER.
FJTURE LEAK TESTING WILL BE SCHEDULED FOR REFUELING OUTAGES WHIC H IS WELL WITHIN THE 2'+ MONTH TIME INTERVALS REGUIRED BY T.S.
YANKEE ROWE 05000029 090379 DURING A SCHEDULED SHUTDOWN, WHILE PERFORMING SECONDARY PLANT CHEMISTRY, FEEDWATER SYSTEMS + CONTROLS 79-022/03L-0 100879 STEAM GENERATORS' 3& 4 CHLORIDE CONCENTRATIDH WAS > 0.5 PPM.
TECH. SP HEAT EXCHANGERS 026998 30-DAY EC. SECTION 3.7.1.6, LIMITS CHLORIDE CONCENTRATION TO </: 0.5 PPM DURING STEAM GENERATOR MODES 1-3.
SIMILAR OCCURRENCES WERE REPORTED AS LER 79-7, 3,
78-36, 27, OTHER 24, 20, 77-22, 13, 17, AND 13.
SECONDARY WATER CHEMISTRY REMAINED OPTI NOT APPLICABLE MUM FOR INHIBITION OF CHLORIDE REDUCED STRESS CORROSION, THUS THERE WAS WESTINGHOUSE ELECTRIC CORP.
NO ADVERSE EFFECTS TO THE HEALTH OR SAFETY OF THE PUBLIC.
THE ROOT CAUSE OF THIS EVENT IS STEAM GENERATOR'S CHEMICAL HIDEOUT. STEA N GENERATOR BLOUDOWN RATE WAS INCREASED AND THE STEAM GENERATORS DRAINED AHD REFILLED WHICH INDUCED THE CHLORIDE CONCENTRATION TO < 0.5 PPM.
IN THAT THIS IS A NORMAL PLANT CHARACTERISTIC NO FURTHER ACTIONS ARE PLANN L37 ED AT THIS TIME.
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DOCKET NO./
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COMPONENT SUSCCDE/CAUSE CODE / LER h0./
REPCRT DATE/
EVENT DESCRIPTION /
CAUSE SUBC00E/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTICN ZION-1 05000295 031479 ESTIMATED 20RCH USAGE LISTED IN APPENDIX B, TABLE B.4 0F THE ZION TECHNI SYSTEM CODE NOT APPLICABLE 79-017/04T-0 032279 CAL SPECIFICATION IS 1000 LBS/ YEAR.
THIS AMOUNT WAS EXCEEDED BETWEEN MA CCMPONENT CODE NOT APPLICABLE 026798 2-WEEK RCH 10 AND MARCH 14, 1979.
DURING THIS PERIOD, 2100 LBS OF BORIC ACID W SUBCC"PONENT NOT APPLICABLE ERE USED.
PREVIOUS LER:
50-295/78-76.
OTHER NOT APPLICABLE ITEM NOT APPLICABLE BORIC ACID USAGE IS DUE TO DRUMMED Rt.DIDACTIVE WASTE CONSISTING OF BORAT ED WATER.
THE BORIC ACID USAGE HAS NO BEARING CN PURPOSE OR INTENT OF T HE WATER QUALITY PROGRAM IN APPENDIX B 0F THE TECHNICAL SPECIFICATIONS.
ZION-1 05000295 052379 AT 1323 HRS. ON 5/23/79, WHILE PERFORMING SAFEQUARDS LOGIC TESTING AT 98 EMERG CCRE COOLING SYS + CONT 79-042/99X-C 082079
. POWER, AN INADVERTANT RX. TRIP AND SAFETY INJECTION WAS INITIATED ON U COMPONENT CODE NOT APPLICABLE 026756 OTHER NIT 1 TECH. SPEC. 3.3.2.F.3 REQUIRES A 90 DAY REPORT.
VISUAL INSPECTI SUBCC"PCNENT NOT APPLICABLE ONS INDICATED THAT NO DAMAGE OCCURRED AS A RESULT OF THE SAFETY INJECTIO PERSONNEL ERROR N.
THE HEALTH AND SAFETY OF THE PUBLIC WERE NOT AFFECTED.
LICENSED & SENIOR OPERATORS ITEM NOT APPLICABLE AN OPERATCR ERROR IN TESTING TRAIN "A" SAFEGUARDS LOGIC CIRCUITS SIMULAT ED HIGH STEAM FLCW SIGNALS CONCURRENT WITH LOW STEAM PRESSURE.
THIS COI NCIDENCE INITIATED MAIN STEAM ISOLATION. WHEN 1B MAIN STEAM ISOL. VLV.
FAILED TO CLOSE, STEAMLINE DIFF PRESSURE REACHED 100PSID AND SI INITIATE D.
OPERATOR WAS REINSTRUCTED.
ZION-1 05000295 071379 WHILE PERFORMINS MAINTEN ANCE ACTIVITIES, INSTRUMENT MECHANICS DISCOVERED REACTOR TRIP SYSTEMS 79-053/03L-0 081079 THAT IL-518 HAD DRIFTED HIGH BY 2.6% (2% IS OVERALL LGOP TCLERANCE).
T INSTRUMENTATION + CONTROLS 326755 30-DAY HIS IS NON-CONSERVATIVE FCR LO-LO S/G LEVEL AND STEAM / FEED FLCW MISMATCH TRANSMITTER COINCIDENT W!TH LOW S/G LEVEL RX TRIPS (T.S.
3.1-1.17 AND 18).
AS REDU CCMPONENT FAILURE NDANT PROTECTION WAS AVAILABLE, THE HEALTH AND SAFETY OF THE PUBLIC WERE INSTRUMENT NOT AFFECIED.
FISCHER-PORTER TRAhSMITTERS HAVE HAD A LONG HISTORY OF D FISCHER & PORTER CO.
RIFTING.
CAUSE WAS INSTRUMENT DRIFT.
MECHANICS ADJUSTED TRANSMITTER ZERO.
MISAL IGNMENT OF OSCILLATOR-AMPLIFIER HAS BEEN IDENTIFIED AS A CAUSE OF ZERO 5 HIFT, AND MECHANICS ARE BEING TRAINED HCW TO QUICKLY IDENTIFY IF THIS SI TUATION EXISTS.
T.S.
CHANGE TO GIVE 1.5% TRANS. AND 3% LOOP TOL. WILL B E SUBMITTED.
ZION-1 05000295 080179 WHILE REVIEWING ISE BULLETIN 79-01, IT WAS DISCOVERED THAT THE REACTOR C REACTOR VES. + APPURTENANCES 79-056/01T-0 082079 00LANT ISOLATICH VALVES HAVE D2400X LIMIT SWITCHES, USED IN TRAIN B REAC INSTRUMENTATION + CONTROLS 026753 2-WEEK TCR PROTECTICH CIRCUITS.
THESE SWITCHES IF FAILED WOULD BE BACKED UP BY SWITCH TRAIN A INTERNAL GEAR DRIVEN LIMIT SWITCHES. THEREFORE THE HEALTH AND DESICN/FAERICATION ERROR SAFETY OF THE PUBLIC WAS NOT AFFECTED.
DESIGN NAMCO CONTROLS NAMCO D2400X LIMIT SWITCHES ARE NOT SUITABLE FOR POST LOCA ENVIRONMENT.
THEY WILL RE REPLACED WITH QUALIFIED EA180-14302 AND EA180-15302 LIMIT S WITCHES DURING NEXT 00TAGES ON BOTH UNITS.
- _cm, U
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REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CCNTROL NO.
REPORT TYPE CAUSE DESCRIPTION ZION-1 05000295 030579 DURING NORMAL OPERATION, OPERATORS NOTICED THAT STEAM FLOW 1FI-523 READ REACTOR TRIP SYSTEMS 79-055/03L-0 033079 200K 1B/HR LOWER THAN THE OTHER CHANNEL.
(LIMIT 189K 1B/HR)
THIS IS NO INSTRUMENTATION + CONTROLS 026754 30-DAY N-CONSERVATIVE FOR STEAM / FEED FLOW MISMATCH COIHCIDENT WITH LOW S/G LEVE TRANSMITTER L (REF. TS TABLE 3.1-1.17).
AS THE ALTERNATE INSTRUMENTS WERE OPERABLE, CCMPONENT FAILURE THE HEALTH AND SAFETY OF THE PUBLIC WAS NOT AFFECTED. BISTABLES WERE T INSTRUMENT RIPPED PER AOP-9.
FISCHER & PORTER CD.
MECHANICS DISCOVERED THAT FISCHER-PORTER MODEL 10B2491 S/N 6904A4355A36 HAD DRIFTED.
A 2% ZERO ADJUSTMENT WAS MADE.
MECHANICS ARE BEING TRAINE D IN AN IMPROVED CALIBRATION TECHNIQUE ON THESE TRANSMITTERS WHICH WILL REDUCE THE RATE OF ZERO DRIFT.
ZION-1 05000295 081179 DURING NORMAL OPERATION, INSTRUMENT INVERTER 114 FAILED AT 0615 HOURS.
ONSITE POWER SYSTEM + CONTROL 79-057/03L-0 090679 DG "0" WAS 005 FOR MAINTENANCE. AH IMMEDIATE PROCESSION TO HOT SHUTDOWN GENERATORS 026916 30-DAY WAS STARTED AS REQUIRED BY T.S.
3.15.2.H.
REDUNDANT COMPONENTS WERE AV INVERTER AILABLE TO PERFORM ANY REQUIRED SAFETY FUNCTIOHS SO THE HEALTH AHD SAFET COMPCMENT FAILURE Y WERE NOT AFFECTED.
(REF LER #50-295-79-4)
ELECTRICAL WESTINGHCUSE ELECTRIC CORP.
THE SKVA TRANSFORMER IN THE MASTER UNIT OF THE INVERTER CAT #23-25-250 WA S FOUND DEFECTIVE AND WAS REPLACED WITHIN 4 HOURS 50 THERE WAS NO NEED T 0 GO TO HOT SHUTDOWN.
DUE TO LOW FREQUENCY OF OCCURRENCE NO FURTHER ACT IDH IS CONSIDERED HECESSARY.
ZIOH-1 05000295 081379 DURING A 50% PUWER INCREASE, OPERATORS OBSERVED FEEDWATER FLOW 1FI-520 R REACTOR TRIP SYSTEMS 79-058/03L-0 083079 EAD 190K LB/HR HIGHER THAN THE OTHER CHANNEL (LIMIT IS 189K LB/HR).
AFT INSTRUMENTATION + CONTROLS 026752 30-DAY ER THE RAMP TO 100% POWER, CHANHEL WAS IN TOLERANCE, 50 BISTABLES WERE R OTHER ESET.
REDUNDANT PROTECTION WAS AVAILABLE, 50 THE PUBLIC'S HEALTH AND SA COMPONENT FAILURE FETY WERE HOT AFFECTED.
REF.
T.S.
3.1-1.17 STEAM /FEEDFLOW MISMATCH WITH OTHER LOW S/C LEVEL.
BISTABLES WERE TRIPPED PER AOP-9.
FISCHER & PORTER CO.
THE TRANS. SIGNAL GOES TO A SQUARE ROOT EXTRACTOR WHICH MAGNIFIES ANY TR ANS. ERROR BELCW 50% FULL FLOW RANGE.
MECHANICS ADJUSTED TRANS. ZERO 0.
8% AT 100% POWER.
IMPROVED TRANS. CALIBRATION TECHNIQUE SHOULD REDUCE T HE RATE OF DRIFT.
T.S.
CHANGES WILL BE SUBMITTED TO INCREASE ALLOWABLE TRANS. DRIFT FROM.5 TO 1.5%
ZION-1 05000295 081679 ON 8/15/79 AT 1900 HRS WHILE PERFORT11NG S AFEGUARD TEST PT-10A, CONTAINME CNTNMNT ISOLATION SYS + COHT 79-063/03L-0 083079 NT ISOL. VLV:
1A0V-PR21B, FAILED TO CLOSE.
REDUNDANT VLV PR-21A, WAS 0 VALVES 026751 30-DAY PERABLE BUT WAS NOT IMMEDIATELY SECURED IN CLOSED POSITION (VIOLATING CO PLUG NT. INTEGRITY TECH. SPEC.
3.9.5).
VALVE WAS SECURED 12 HOURS LATER BY N PERSOHNEL ERROR EXT SHIFT.
PUBLIC HEALTH AND SAFETY WAS NOT AFFECTED.
LICENSED & SENIOR OPERATORS MASONEILAN INTERNATIONAL, INC.
FAILURE TO PROMPTLY SECURE 1FCV-PR21A IN THE CLOSED POSITION WAS DUE TO PERSOHNEL ERROR.
OPERATORS HAVE BEEN INSTRUCTED TO TAKE PROMPT ACTION A ND PROVIDE CLEAR HOTIFICATION OF FAILURES TO SHIFT SUPERVISOR.
IFCV-PR2 1A WAS SECURED BY HEXT SHIFT AND TAKEH OUT OF SERVICE.
1FCV-PR21B FAILU RE IS UNDER INVESTIGATION.
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DOCKET NO./
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COMPONENT SUSCODE/CAUSE CODE / LER NO./
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL HO.
REPORT TYPE CAUSE DESCRIPTION ZION-1 05000295 083179 FOLLCWIHG UNIT TRIP, OPERATOR FOUND S/G LEVEL CHANNEL IL-538 INDICATING REACTOR TRIP SYSTEMS 79-065/03L-0 092879 HIGHER THAN HORMAL, CHANNEL WAS DECLARED INCPERABLE, PUTTING THE PLANT INSTRUMENTATION + CONTROLS 027010 30-DAY IN A MODE OF OPERATING AT AH LCO PERMITTED BY T.S.
TABLE 3.1-1.
REDUNDA TRANSMITTER NT EQUIPMENT WAS OPERABLE AND AVAILABLE, AND THE HEALTH AND SAFETY OF TH CCMPONEHT FAILURE E PUBLIC WERE NOT AFFECTED.
INSTRUMENT FISCHER & PORTER CO.
THE XMTR WAS MECHANICALLY STICKING. NAINTENANCE ADJUSTED TO ZERO.
XMTR WILL BE MECHANICALLY REALIGNED AT UNIT REFUELING OUTAGE.
HQ FURTHER AC TION REQUIRED.
ZION-2 05000304 071879 WHILE PERFORMING PERIODIC TESTING, RECIRC. SUMP TO RHR PUMP SUCTION VALV EMERG CORE COOLING SYS + CONT 79-038/03L-0 081479 E 2MOV-SI5811A FAIL ED TO STROKE OPEN.
THIS WOULD HAVE RESULTED IN THE V VALVES 026750 30-DAY ALVE BEING IN THE WRONG POSITION FOR THE RECIRCULATION PHASE OF LOCA.
(
GATE T.S.
3.8.3.B).
HOWEVER, THE VALVE FOR THE OTHER TRAIN WAS OPERABLE AND COMPCHENT FAILURE AVAILABLE, 50 THE HEALTH AND SAFETY OF THE PUBLIC WAS NOT AFFECTED.
MECHANICAL DARLING VALVE & MFTG. CO.
VALVE 8811A FAILED TO STROKE DUE TO FAILURE OF STEM MOUNTED LIMIT SWITCH INTERLOCK CONTACT ON VALVE 2MOV-RH8700A TO MAKE UP.
LIMIT SWITCH FAILE D DUE TO LOOSE SIEM NUT.
VALVE IS A 14 INCH SS DARLING VALVE MODEL D323 3A.
A SECOND LOCKHUT AND LOCKWASHER WILL BE INSTALLED ON THESE VALVE ST EMS, ON BOTH ZION UNITS.
NO FURTHER ACTION IS CONSIDERED NECESSARY.
ZION-2 05000304 072379 DURING NORMAL OPERATIONS, THE UNIT 2 CONT. PURGE PARTICULATE MONITOR, 2R PRCSS + EFF RADIOL MONITOR SYS 79-039/03L-0 082379 T-PR09C WAS TAKEN 005 FOR REPAIR.
DURING THE TWO DAYS THE MONITOR WAS 0 COMPONENT CODE NOT APPLICABLE 026749 30-DAY 05, THE UHIT 2 CONT. WAS VENTED ONCE.
THIS IS A TECH SPEC VIOLATION AS SUBCOMPONENT NOT APPLICABLE INDIC A TED PER TECH SPEC 3.12.1C.1 THERE WAS NO UNPLANNED RELEASE OF RA DEFECTIVE PROCEDURES DI0 ACTIVITY BECAUSE GRAB SAMPLES OF THE CONT. ATMOSPHERE WERE ANALYZED B NOT APPLICABLE EFORE THE RELEASE.
HOWEVER, THE 00S MONITOR WAS ABLE TO BE USED TO QUAN ITEM EDT APPLICABLE TIFY THE RELEASE PATH.
THE HEALTH & SAFETY OF PUBLIC WAS NOT AFFECTED.
THIS EVENT OCCURRED BECAUSE THE OPERATING PROCEDURE USED FOR VENTING THE CONT. DID NOT INDICATE WHAT MONITORS MUST BE OPERABLE.
THIS PROCEDURE "4% BEEN REVISED TO INCLUDE THE MONITORS.
ALSO, THE CHEMISTRY PROCEDURE FOR VENTING HAS BEEN CHANSED TO REFERENCE THE APPLICABLE VENTING PROCED URE.
NO FURTHER ACTICH IS REQUIRED.
ZION-2 05000304 080379 DURING NORMAL OPERATION, PZR LEVEL CHANNEL 2L-4S9 WAS INDICATING LOWER T REACTOR TRIP SYSTEMS 79-044/03L-0 090479 HAH THE OTHER LEVEL CHANNELS.
THIS PUT THE PLANT IN A MODE OPERATING AT INSTRUMENTATION + CONTR0!S 026745 30-DAY AN LCO AS DEFINED IN T.S.
TABLE 3.1-1.
REDUNDANT EQUIPMENT WAS OPERABL TRANSMITTER E AND AVAILABLE, 50 NO SAFETY IMPLICATIONS WERE IHVOLVED.
THE HEALTH AH COMPONENT FAILURE D SAFETY OF THE PUBLIC WAS HOT AFFECTED. PREVIOUS LER:
50-295/79-29.
INSTRUMENT BART0H INSTRU CO.,
DIV 0F ITT CAUSE OF THE CHANNEL OUT OF TOLERANCE WAS CAUSED BY XMTR ZERO SHIFT.
TH E TRANSMITTER ZERO WAS ADJUSTED AND THE CHANNEL RETURNED TO SERVICE. AC
--a (jg TION TO CORRECT THE PRESSURIZER LEVEL CHANNELS WAS IDENTIFIED IN THE REF ERLHCED LER.
NO FURTHER ACTION IS REQUIRED.
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DOCKET NO./
EVENT DATE/
COMPONENT SUBCODE/CAUSE CODE / LER NO./
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION ZION-2 05000304 080579 DURING MONTHLY CONTAINMENT ISOLATION VALVE OPERABILITY TEST (TT-300), 2A CNTNMNT ISOLATION SYS + CONT 79-062/03L-0 083179 OV-SS$354B FAILED TO CLOSE FROM CONTROL ROOM SWITCH. VALVE WOULD CLOSE W VALVES 026747 30-DAY ITH MANUAL ASSISTANCE. THIS PLACED CONTAINMENT ISOLATION SYSTEM IN A DEG GLOBE RADED MODE (T.S.
3.9.3.A).
THERE WEPE NO PREVIOUS SIMILAR FAILURES.
TH CCMPONENT FAILURE E HEALTH AND SAFETY OF THE PUBLIC WERE NOT AFFECTED BECAUSE THE REDUNDAN MECHANICAL T ISOLATION VALVE WAS OPERABLE AND CLOSED AS REQUIRED.
THE ffANUAL DCWHS MASONEILAN INTERNATIONAL, INC.
TREAM ISCLATION VALVE WAS ALSO CLOSED.
CAUSE OF FAILURE WAS STICKING VALVE STEM.
THE VALVE WAS CLOSED WITH MAN UAL ASSISTANCE IMMEDIATELY AFTER THE FAILURE.
LATER, THE VALVE STEM WAS CLEANED, LUERICATED, AND THE PACKING WAS ADJUSTED.
THE VALVE THEN STRO KED SUCCESSFULLY AND WAS PROVEN OPERABLE.
NO FURTHER CORRECTIVE ACTION IS REQUIRED DUE TO THE LOW FREQUENCY OF OCCURRENCE.
ZION-2 05000304 080679 WHILE ATTEMPTING DIESEL CENERATOR LOADING TEST (PT-11) ON 2B DG, ENGINE EMERG GENERATOR SYS + CONTROLS 79-043/03L-0 083079 FAILED TO STAY RUNNING.
THIS FAILURE CONSTITUTED A CONDITION OF CPERATI ENGINES INTERNAL COMBUSTION 026746 30-DAY ON IN A DEGRADED f0DE PERMITTED BY A LIMITING CONDITION FOR OPERATICN.
SUBCOMPONENT NOT APPLICABLE (TECH. SPEC. 3.15.2.C).
THE HEALTH AND SAFETY OF THE PUBLIC WERE NOT AF OTHER FECTED BECAUSE REDUNDANT EQUIPMENT WAS VERIFIED OPERABLE BY REQUIRED TES NOT APPLICABLE TING.
COOPER PENJAX ACTUAL CAUSE UNKNOWN. PROBABLE CAUSE OVERSPEED TRIP.
PREVIOUS LOW OIL LEVEL IN GOVERNOR COULD HAVE INTRCDUCED AIR INTO C0f1PENSATING PISTON, AL LOWING DG TO OVERSPEED ON START.
GOVERNCR EXERCISED TO BLEED AIR FRCN P ISTON AND DG DEMONSTRATED OPERABLE.
PROCEDURE CHANGED TO CHECK GOVERNOR OIL LEVEL DAILY.
NO FURTHER CORRECTIVE ACTION WARRANTED.
ZION-2 05000304 080679 OPERATORS DISCOVERED THAT S/G LEVEL 2LI-538 READ OVER 4% HICHER (2% PER REACTOR TRIP SYSTEMS 7 9 - 0 41/ 0 3 L -0 083079 CHANNEL LIMIT) THAN OTHER CHANNELS.
THIS IS NON-CONSERVATIVE FOR LOW-LO INSTRUMENTATION + CONTROLS 026748 30-DAY W S/G TRIP AND LOW S/G COINCIDEHT WITH STEAM / FEED FLOW (REF TS TABLE 3.1 POWER SUPPLY
-1.17 AND 18).
BISTABLES WERE TRIPPED PER AOP-9.
AS REDUNDANT PROTECTI CCt1P ON EN T FAILURE ON WAS AVAILABLE AND OPERATIONAL, THE HEALTH AND SAFETY OF THE PUBLIC WE ELECTRICAL RE NOT AFFECTED.
HAGAN CONTROLS MECHANICS DISCOVERED THAT HAGAN POWER SUPPLY MODEL 4111085-G01 S.N.
M058 4 DRIFTED FROM 46V TO 49V; EXCEEDING THE TRANSMITTER MANUFACTURER'S RECO MMENDATIONS.
THE POWER SUPPLY WAS REPLACED AND THE LOOP RETURNED TO NOR MAL.
SINCE THIS IS NOT A RECURRING PROBLEM, NO FURTHER ACTION IS PLANNE D.
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