U.S. Nuclear Regulatory Commission Operations Center Event Reports For 10/12/95 - 10/13/95 ** EVENT NUMBERS ** 29443 29444 29445 29446 29447 29448 29449 29450 29451 29452 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29443 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HARRIS REGION: 2 |NOTIFICATION DATE: 10/12/95 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 04:13 [ET]| |RX TYPE: [1] W-3-LP |EVENT DATE: 10/12/95 | +------------------------------------------------+EVENT TIME: 02:23[EDT]| |NRC NOTIFIED BY: ANDY BARBEE |LAST UPDATE DATE: 10/12/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS PEEBLES RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A/R Y 5 STARTUP | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TURBINE TRIP/REACTOR TRIP DURING TURBINE OVERSPEED TESTING DUE TO THE | | INADVERTENT MISPOSITIONING OF A SWITCH | | | | WITH REACTOR POWER AT APPROXIMATELY 5.3%, OPERATORS WERE ROLLING THE | | TURBINE AT 1,800 RPM, AND PROCEDURE OPT-1075 (TURBINE OVERSPEED TRIP TEST - | | 18-MONTH INTERVAL MODES 1-2) WAS IN PROGRESS. STEP 15 OF THIS PROCEDURE | | DIRECTED OPERATORS TO PLACE THE 'OVERSPEED TRIP' KEY SWITCH IN THE | | 'OVERSPEED TEST PERMISSIVE' POSITION; HOWEVER, THE 'OVERSPEED TRIP' KEY | | SWITCH WAS INADVERTENTLY PLACED IN THE 'OPC TEST' POSITION. THE OPC | | (OVERSPEED PROTECTION CONTROLLER) CAUSED THE TURBINE GOVERNOR AND | | INTERCEPTOR VALVES TO CLOSE, AND TURBINE SPEED REDUCED TO 1,690 RPM. THE | | SWITCH MISPOSITIONING WAS REALIZED BY THE BALANCE-OF-PLANT OPERATOR, AND | | THE DECISION WAS MADE TO RESTORE THE SWITCH TO THE 'IN SERVICE' POSITION. | | THE TURBINE IMMEDIATELY ATTEMPTED TO RETURN TO 1,800 RPM CAUSING AN | | INCREASE IN STEAM FLOW TO THE TURBINE. THE EXCESSIVE STEAM FLOW CAUSED | | STEAM GENERATOR LEVELS TO SWELL, AND PERMISSIVE P-14 (STEAM GENERATOR | | HIGH-HIGH LEVEL) WAS RECEIVED ON THE 'B' STEAM GENERATOR. SENSED TURBINE | | POWER INCREASED ABOVE 10% TURBINE LOAD WHICH REMOVED THE 'LOW POWER TRIPS | | BLOCKED P-7.' | | | | THE P-14 SIGNAL GENERATED A TURBINE TRIP WHICH IN TURN GENERATED A REACTOR | | TRIP SIGNAL. FEEDWATER ISOLATION, WHICH WAS ALSO INITIATED BY P-14, CLOSED | | ALL FEEDWATER ISOLATION VALVES AND PROVIDED A TRIP SIGNAL TO THE 'B' MAIN | | FEEDWATER PUMP. THE TRIP OF THE MAIN FEEDWATER PUMP (TRIP OF THE LAST | | RUNNING FEEDWATER PUMP) GENERATED AN AUXILIARY FEEDWATER START SIGNAL TO | | BOTH MOTOR-DRIVEN AUXILIARY FEEDWATER PUMPS. ALL RODS INSERTED ON THE | | REACTOR TRIP, AND ALL SYSTEMS FUNCTIONED AS REQUIRED. THE PLANT WAS | | STABILIZED USING THE EMERGENCY OPERATING PROCEDURES. THE LICENSEE IS | | CURRENTLY UTILIZING NORMAL CHARGING FOR PRIMARY INVENTORY CONTROL, THE | | REACTOR COOLANT PUMPS FOR PRIMARY TRANSPORT CONTROL, MAIN FEEDWATER FOR | | STEAM GENERATOR INVENTORY CONTROL, AND THE CONDENSER FOR HEAT SINK CONTROL. | | | | THE LICENSEE HAS NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29444 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 10/12/95 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 12:57 [ET]| |RX TYPE: [1] CE |EVENT DATE: 10/12/95 | +------------------------------------------------+EVENT TIME: 10:10[CDT]| |NRC NOTIFIED BY: T. REISDORFF |LAST UPDATE DATE: 10/12/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ELMO COLLINS RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE NOTIFIED THE NEBRASKA DEPARTMENT OF ENVIRONMENTAL QUALITY THAT | | TWO PLANT EMPLOYEES WERE BURNED BY SULFURIC ACID. | | | | AT 08:35 CDT, 452 POUNDS OF SULFURIC ACID SPILLED WHEN MAINTENANCE WAS | | BEING PERFORMED ON PIPING DOWNSTREAM OF A SULFURIC ACID TANK. (AN | | ISOLATION VALVE FAILED.) A MAINTENANCE WORKER THAT HAD BEEN SPRAYED ON THE | | NECK AND ARMS WAS TAKEN BY THE LOCAL BLAIR CLINIC RESCUE SQUAD TO BLAIR | | CLINIC AND WAS LATER TRANSFERRED TO A HOSPITAL LOCATED IN OMAHA. AN | | EQUIPMENT OPERATOR RECEIVED MINOR BURNS ON HIS ARM AND WAS TAKEN BY SITE | | PERSONNEL TO THE BLAIR CLINIC. DOCTORS AT BLAIR CLINIC ATTENDED HIS MINOR | | BURNS AND THEN RELEASED HIM. THE SULFURIC ACID SPILL WAS CONTAINED AND | | CLEANED UP. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29445 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 10/12/95 | |UNIT: [1] [ ] [ ] STATE: MN |NOTIFICATION TIME: 13:09 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 10/12/95 | +------------------------------------------------+EVENT TIME: 11:20[CDT]| |NRC NOTIFIED BY: DALE COX |LAST UPDATE DATE: 10/12/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |B J HOLT RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | BOTH LOOPS OF DRYWELL SPRAY WERE OUT OF SERVICE FROM OCTOBER 3 THROUGH 5, | | 1995. | | | | IT WAS DISCOVERED TODAY THAT LOOP 'B' OF DRYWELL SPRAY HAD BEEN VALVED OUT | | SINCE OCTOBER 18, 1995. THIS WAS DISCOVERED DURING ITS ANNUAL ROUTINE | | MAINTENANCE. DRYWELL LOOP 'B' MANUAL ISOLATION VALVE (RHR74-2) WAS FOUND | | CLOSED. THE LICENSEE THINKS THAT THIS VALVE HAS BEEN IN THE CLOSED | | POSITION SINCE ITS LAST MAINTENANCE OUTAGE AND IS INVESTIGATING THIS | | POSSIBILITY. DURING THE PERIOD OF OCTOBER 3 THROUGH 5, 1995, WHEN LOOP 'A' | | OF DRYWELL WAS OUT OF SERVICE FOR ITS ANNUAL MAINTENANCE, BOTH LOOPS OF | | DRYWELL SPRAY WERE OUT OF SERVICE AT THE SAME TIME. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 29446 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: WYOMING MEDICAL CENTER |NOTIFICATION DATE: 10/12/95 | | CITY: CASPER REGION: 4 |NOTIFICATION TIME: 15:48 [ET]| | COUNTY: NATRONA STATE: WY |EVENT DATE: 09/15/95 | |LICENSE#: 49-00152-02 AGREEMENT: N |EVENT TIME: 00:00[MDT]| | DOCKET: |LAST UPDATE DATE: 10/12/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | |ELMO COLLINS RDO | | |BOB BEAR EO | +------------------------------------------------+ | |NRC NOTIFIED BY: TOM CHEREWICK | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAB2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A 1.29-MILLICURIE PALLADIUM-103 SEED WAS LOST AT THE CASPER WYOMING MEDICAL | | CENTER. | | | | WHILE LOADING SOURCES INTO A MICK APPLICATOR (USED FOR INSERTING SEEDS INTO | | THE PROSTATE), THE SPRING LOADED MAGAZINE CONTAINING THE SEEDS CAME LOOSE | | FROM THE PERSON HOLDING THE MAGAZINE IN HIS LEAD LINED GLOVES, AND THREE | | SEEDS CAME OUT OF THE MAGAZINE. TWO OF THE THREE SEEDS WERE FOUND USING A | | GEIGER COUNTER. THE THIRD SEED HAS NOT BEEN FOUND. THIS SEED IS LOCATED | | SOMEWHERE INSIDE THE ISOTOPE STORAGE ROOM OF THE MEDICAL CENTER. THE SEED | | WAS LOST ON SEPTEMBER 15, 1995. THE SEED IS 4.5 MILLIMETERS IN LENGTH AND | | 0.8 MILLIMETERS IN DIAMETER. NO PERSON HAS RECEIVED ANY EXPOSURE FROM THE | | MISSING SEED. | | | | THE LICENSEE WILL INFORM REGION 4 OF THIS REPORT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29447 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 10/12/95 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 15:50 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/12/95 | +------------------------------------------------+EVENT TIME: 14:25[CDT]| |NRC NOTIFIED BY: MIKE DEBOARD |LAST UPDATE DATE: 10/12/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |B. J. HOLT RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 1 AND 2 MISCELLANEOUS EQUIPMENT ROOM VENTILATION SUPPLY FANS MAY | | BECOME INOPERABLE AS A RESULT OF A FIRE IN ZONES 11.5-0 AND 11.6-0. | | | | THE FOLLOWING IS FROM THE FACSIMILE SENT BY THE LICENSEE. | | | | "ON OCTOBER 6, 1995, A REVIEW OF THE FIRE PROTECTION REPORT (FPR) SAFE | | SHUTDOWN ANALYSIS REVEALED THAT ANALYSIS CONCLUSIONS REGARDING THE | | AVAILABILITY OF UNIT 1 & UNIT 2 MISCELLANEOUS EQUIPMENT ROOM VENTILATION | | SUPPLY FANS 1VE01C AND 2VE01C MAY BE INCORRECT. THE ERROR WAS IDENTIFIED | | AS A RESULT OF ONGOING ANALYSES TO RESOLVE THERMO-LAG FIRE BARRIER ISSUES | | AT BRAIDWOOD AND BYRON STATIONS. AT 1425 CDST ON OCT. 12, 1995, IT WAS | | DETERMINED THAT THE EXISTING CONFIGURATION WAS NOT IN COMPLIANCE WITH | | 10CFR50, APP R. | | | | THE EXISTING [FPR] DISCUSSION INCORRECTLY STATES THAT THE SUPPLY FANS WILL | | BE AVAILABLE AFTER A FIRE IN FIRE ZONES 11.5-0 & 11.6-0 MOTOR CONTROL | | CENTERS (MCCs) 132X4 & 232X4, WHICH POWER FANS 1VE01C AND 2VE01C COULD BE | | UNAVAILABLE AS A RESULT OF A FIRE IN ZONES 11.5-0 & 11.6-0. THESE MCCs ARE | | AFFECTED BECAUSE THEY ARE FED FROM COMMON SOURCE BREAKERS WITH MCCs 132X5 | | AND 232X5. THEREFORE, A FIRE INDUCED FAULT ON MCCs 132X5 & 232X5 OR THEIR | | ASSOCIATED FEED CABLES WILL RENDER THE POWER SOURCE FOR THE SUBJECT FANS, | | MCCs 132X4 & 232X4, UNAVAILABLE. | | | | THE SUPPLY FANS ARE SUPPORT EQUIPMENT FOR THE DIVISION 12 AND 22 125 Vdc | | ESF BUSES AND INSTRUMENT POWER BUSES 112, 114, 212, & 214. | | | | COMPENSATORY ACTIONS IN THE FORM OF HOURLY FIRE WATCHES HAVE BEEN IN PLACE | | IN THESE ZONES SINCE INITIAL PLANT START-UP DUE TO THERMO-LAG DEFICIENCIES | | AND OTHER FIRE PROTECTION REASONS. DESIGN MODIFICATIONS ASSOCIATED WITH | | THERMO-LAG RESOLUTION ARE CURRENTLY IN PROGRESS TO RE-POWER THE AFFECTED | | MCCs FROM NEW SOURCE BREAKERS." END OF TEXT. (SEE BYRON EVENT NUMBER | | 29449 FOR A SIMILAR EVENT.) | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29448 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 10/12/95 | |UNIT: [1] [2] [ ] STATE: NJ |NOTIFICATION TIME: 15:59 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/12/95 | +------------------------------------------------+EVENT TIME: 14:00[EDT]| |NRC NOTIFIED BY: B. HAMILTON |LAST UPDATE DATE: 10/12/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GENE KELLY RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | IT WAS FOUND THAT TWO SERVICE WATER (SW) PUMPS COULD POTENTIALLY | | RUNOUT/CAVITATE DURING THE RECIRCULATION PHASE OF A LOCA. | | | | THE FOLLOWING IS THE TEXT FROM A FACSIMILE SENT BY THE LICENSEE. | | | | "AS A RESULT OF AN ONGOING REVIEW OF 3 PROBLEM REPORTS [PR's] ASSOCIATED | | WITH THE SW SYSTEM, IT WAS DETERMINED THAT THE CONDITIONS DESCRIBED IN | | THESE PR's COULD HAVE POTENTIALLY AFFECTED THE ABILITY OF THE SYSTEMS TO | | PERFORM/COMPLETE ITS DESIGN FUNCTION. THE CURRENT SALEM DESIGN BASIS FOR | | THE SW SYSTEM IS THAT IT WILL BE ABLE TO SUPPLY ALL SAFETY RELATED LOADS | | WITH ONLY 2 SW PUMPS POWERED FROM DIFFERENT 1E BUSES. | | | | THE SPECIFIC CONDITIONS DESCRIBED IN THESE PR's (I.E., SINGLE FAILURES) | | COULD HAVE RESULTED IN AN ALIGNMENT WHERE THE ASSUMED 2 SW PUMPS COULD | | POTENTIALLY RUNOUT/CAVITATE DURING THE RECIRCULATION PHASE OF THE LOCA. | | SPECIFICALLY, THE ORIGINAL SW SYSTEM DESIGN ASSUMED THAT WITH ONLY 2 SW | | PUMPS AVAILABLE, ONLY ONE CCHX [HEAT EXCHANGER] WOULD BE ALIGNED FOR | | COOLING. THIS CONDITION WAS NOT PROPERLY ADDRESSED BY PROCEDURES. | | | | IN THE INTERIM, THESE CONDITIONS HAVE BEEN ADDRESSED BY PROCEDURAL CHANGES | | AND DESIGN MODIFICATIONS SO THAT THE ABILITY OF THE SW SYSTEM TO ACCOMPLISH | | AND COMPLETE ITS DESIGN FUNCTION IS BEING MAINTAINED. I.E., WITH ONLY 2 SW | | PUMPS AVAILABLE CCHX FLOW IS ADJUSTED SUCH THAT TOTAL SYSTEM FLOW IS | | COMPATIBLE WITH ORIGINAL ASSUMPTIONS. LONG TERM CORRECTIVE ACTIONS ARE | | BEING DEVELOPED BY A DEDICATED TEAM AND WILL BE IMPLEMENTED PRIOR TO UNIT | | RESTART. | | | | THESE ISSUES WERE SELF DISCOVERED BY PSE&G AS A PART OF THE DESIGN BASIS | | AND SWSOPI RECONSTITUTION EFFORTS. | | | | HOWEVER, ITS PAST EXISTENCE - PRIOR TO THE CORRECTIVE ACTIONS - IS BEING | | REPORTED IN ACCORDANCE WITH 10CFR50.72. THESE CONDITIONS AND CORRECTIVE | | (INTERIM) ACTIONS WERE IDENTIFIED AND COMPLETED APPROXIMATELY 1 YEAR AGO, | | BUT THE REPORTABILITY WAS NOT IMMEDIATELY RECOGNIZED." END OF TEXT. | | | | THE LICENSEE NOTIFIED LOWER ALLOWAYS CREEK TOWNSHIP AND THE NRC RESIDENT | | INSPECTOR OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29449 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BYRON REGION: 3 |NOTIFICATION DATE: 10/12/95 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 16:10 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/12/95 | +------------------------------------------------+EVENT TIME: 14:25[CDT]| |NRC NOTIFIED BY: D. FLOWERS |LAST UPDATE DATE: 10/12/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |B J HOLT RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 99 POWER OPERATION | 99 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 1 AND 2 MISCELLANEOUS EQUIPMENT ROOM VENTILATION SUPPLY FANS MAY | | BECOME INOPERABLE AS A RESULT OF A FIRE IN ZONE 11.6-0. | | | | THE FOLLOWING TEXT IS FROM A FACSIMILE SENT BY THE LICENSEE. | | | | "ON OCTOBER 9, 1995, BRAIDWOOD STATION NOTIFIED BYRON STATION THAT A REVIEW | | OF THE FIRE PROTECTION REPORT (FPR) SAFE SHUTDOWN ANALYSIS REVEALED THAT | | ANALYSIS CONCLUSIONS REGARDING THE AVAILABILITY OF UNIT 1 AND UNIT 2 | | MISCELLANEOUS EQUIPMENT ROOM VENTILATION SUPPLY FANS 1VE01C AND 2VE01C MAY | | BE INCORRECT. THE ERROR WAS IDENTIFIED AS A RESULT OF ONGOING ANALYSES TO | | RESOLVE THERMO-LAG BARRIER ISSUES AT BRAIDWOOD AND BYRON STATIONS. AT 1425 | | [CDT] ON OCT. 12, 1995, IT WAS DETERMINED THAT THE EXISTING CONFIGURATION | | WAS NOT IN COMPLIANCE WITH 10CFR50, APP R. | | | | THE EXISTING FPR DISCUSSION INCORRECTLY STATES THAT THE SUPPLY FANS WILL BE | | AVAILABLE AFTER A FIRE IN FIRE ZONES 11.6-0. MOTOR CONTROL CENTERS (MCCs) | | 132X4 & 232X4 WHICH POWER FANS 1VE01C AND 2VE01C COULD BE UNAVAILABLE AS A | | RESULT OF A FIRE IN ZONE 11.6-0. THESE MCCs ARE AFFECTED BECAUSE THEY ARE | | FED FROM COMMON SOURCE BREAKERS WITH MCCs 132X5 AND 232X5. THEREFORE, A | | FIRE INDUCED FAULT ON MCCs 132X5 & 232X5 OR THEIR ASSOCIATED FEED CABLES | | WILL RENDER THE POWER SOURCE FOR THE SUPPLY FANS, MCCs 132X4 & 232X4, | | UNAVAILABLE. | | | | THE SUPPLY FANS ARE SUPPORT EQUIPMENT FOR THE DIVISION 12 AND 22 125 Vdc | | ESF BUSES AND INSTRUMENT POWER BUSES 112, 114, 212, & 214. | | | | COMPENSATORY ACTIONS IN THE FORM OF HOURLY FIRE WATCHES HAVE BEEN IN PLACE | | IN THIS ZONE SINCE LATE 1992 DUE TO THERMO-LAG DEFICIENCIES. HOURLY FIRE | | WATCHES EXISTED IN THIS ZONE PRIOR TO 1992 FOR OTHER REASONS. DESIGN | | MODIFICATIONS ARE CURRENTLY BEING PROCESSED TO PERMANENTLY CORRECT THE | | WIRING CONFIGURATION TO ASSURE THE SUBJECT FANS WILL BE AVAILABLE FOLLOWING | | A FIRE IN ZONE 11.6-0." END OF TEXT. (SEE EVENT NUMBER 29447 FROM | | BRAIDWOOD FOR A SIMILAR EVENT.) | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29450 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: THREE MILE ISLAND REGION: 1 |NOTIFICATION DATE: 10/12/95 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 17:45 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP |EVENT DATE: 10/12/95 | +------------------------------------------------+EVENT TIME: 15:05[EDT]| |NRC NOTIFIED BY: NELSON |LAST UPDATE DATE: 10/12/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GENE KELLY RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 1 STARTUP | 1 STARTUP | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | STARTUP FEEDWATER ISOLATION VALVE CLOSED DURING STARTUP. | | | | INSTRUMENT TECHNICIANS WERE WORKING ON TRAIN 'A' HEAT SINK PROTECTION | | SYSTEM (HSPS) FOR THE 'B' ONCE-THROUGH STEAM GENERATOR (OTSG). THE | | TECHNICIANS WERE WORKING ON THE LOW PRESSURE MODULE (GIVES A MAIN FEEDWATER | | ISOLATION). THE LICENSEE DOES NOT BELIEVE THAT WORK IN THIS CABINET HAD | | ANYTHING TO DO WITH THE HSPS ACTUATION THAT WAS RECEIVED AS DESCRIBED IN | | THE FOLLOWING PARAGRAPH. | | | | AT 15:05 EDT, THE LICENSEE RECEIVED AN ALARM INDICATING THAT 'B' OTSG | | STARTUP FEEDWATER ISOLATION VALVE, 92B, HAD CLOSED. OPERATORS WENT TO | | DEFEAT ON HIGH-HIGH OTSG 'B' WATER LEVEL. THIS CLEARED THE SIGNAL AND | | ALLOWED THE OPERATORS TO REOPEN STARTUP FEEDWATER ISOLATION VALVE 92B. THE | | LICENSEE THEN OPENED THE BREAKER ON THE 'B' TRAIN OF HSPS TO PREVENT ANY | | FURTHER ACTIONS. THE 'B' OTSG STARTUP FEEDWATER ISOLATION VALVE, 92B, | | RECEIVES ITS CLOSING SIGNAL FROM TRAIN 'B' FOR THE HSPS AND NOT FROM THE | | TRAIN 'A' SIDE OF THE HSPS (WHICH WAS BEING WORKED ON). OTSG 'B' WATER | | LEVEL DECREASED ONLY SIX INCHES DURING THIS EVENT. THE LICENSEE RESTORED | | TRAIN 'B' OF HSPS AT 16:40 EDT. THEREFORE, BOTH TRAINS OF HSPS FOR OTSG | | 'B' WERE INOPERABLE FOR 1.5 HOURS. PER TECHNICAL SPECIFICATION 3.5.1.9.1, | | THE LICENSEE HAS 1 HOUR TO RESTORE ONE TRAIN OF THE HSPS OR SHUT DOWN IN | | THE FOLLOWING 6 HOURS. THE UNIT WAS AT 10E-8 AMPS (LOW POWER LEVEL), AND | | THE LICENSEE DID NOT START TO SHUT DOWN THE UNIT AFTER THE TECHNICAL | | SPECIFICATION 3.5.1.9.1 1-HOUR LIMIT HAD BEEN EXCEEDED. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29451 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 10/12/95 | |UNIT: [ ] [ ] [3] STATE: IL |NOTIFICATION TIME: 20:56 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 10/12/95 | +------------------------------------------------+EVENT TIME: 17:22[CDT]| |NRC NOTIFIED BY: BRILEY |LAST UPDATE DATE: 10/12/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |B. J. HOLT RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N Y 20 POWER OPERATION | 20 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HIGH PRESSURE CORE INJECTION (HPCI) DECLARED INOPERABLE DURING ITS MONTHLY | | SURVEILLANCE TEST. | | | | DURING HPCI MONTHLY SURVEILLANCE TESTING, A HPCI EXHAUST DRAIN POT HIGH | | LEVEL ALARM WAS RECEIVED, AND THE ALARM WOULD NOT CLEAR. THE HPCI TURBINE | | WAS MANUALLY TRIPPED, AND HPCI WAS DECLARED INOPERABLE. TECHNICAL | | SPECIFICATION 3.5.C.1 WAS ENTERED WHICH REQUIRES THE LICENSEE TO RESTORE | | HPCI TO SERVICE WITHIN 7 DAYS OR SHUT DOWN. THE LICENSEE THINKS THAT THE | | HPCI EXHAUST DRAIN POT LEVEL SWITCH IS NOT OPERATING PROPERLY. ALL OTHER | | EMERGENCY CORE COOLING SYSTEMS AND THE EMERGENCY DIESEL GENERATORS ARE | | FULLY OPERABLE. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29452 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 10/12/95 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 21:27 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 10/12/95 | +------------------------------------------------+EVENT TIME: 19:05[CDT]| |NRC NOTIFIED BY: DOUG HITZEL |LAST UPDATE DATE: 10/12/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ELMO COLLINS RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 85 POWER OPERATION | 85 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HOOKUP OF TRAIN "A" OF THE STANDBY NITROGEN INJECTION SYSTEM (SBNI) ENTAILS | | POTENTIALLY BREACHING SECONDARY CONTAINMENT. | | | | THE FOLLOWING TEXT WAS TAKEN FROM A FACSIMILE SENT BY THE LICENSEE. | | | | "ON 10/12/95 AT 1905, A CONDITION WAS IDENTIFIED THAT COULD HAVE PREVENTED | | THE FULFILLMENT OF THE SAFETY FUNCTION OF A SYSTEM NEEDED TO MITIGATE THE | | CONSEQUENCES OF AN ACCIDENT. IT WAS DETERMINED THAT THE PROCEDURE FOR USE | | OF TRAIN "A" OF THE CNS STANDBY NITROGEN INJECTION (SBNI) SYSTEM, DIRECTS | | PERSONNEL TO PENETRATE A BARRIER WHICH FORMS PART OF THE CNS SECONDARY | | CONTAINMENT BOUNDARY. THE SBNI SYSTEM WAS INSTALLED TO MEET THE | | REQUIREMENTS OF 10CFR50.44, "STANDARDS FOR COMBUSTIBLE GAS CONTROL SYSTEM | | IN LIGHT-WATER-COOLED POWER REACTORS". THIS SYSTEM IS A TWO TRAIN, | | NON-ESSENTIAL SYSTEM WHICH PROVIDES A BACKUP TO THE INERTED CONTAINMENT AND | | THE NORMAL AUTOMATIC NITROGEN MAKEUP SYSTEM. FOR THE "A" SBNI TRAIN, | | MANUAL OPERATOR ACTION IS REQUIRED TO HOOK UP A FLEXIBLE HOSE FROM THE | | SUPPLY PIPING LOCATED OUTSIDE THE REACTOR BUILDING TO THE DISTRIBUTION | | PIPING LOCATED INSIDE A VESTIBULE BETWEEN TWO REACTOR BUILDING DOORS. THIS | | ACTIVITY IS CREDITED WITH BEING ACCOMPLISHED WITHIN 10 HOURS OF A LOCA. IT | | WAS RECOGNIZED THAT THIS HOOKUP ENTAILS POTENTIALLY BREACHING SECONDARY | | CONTAINMENT TO ACCOMMODATE THE FLEXIBLE HOSE. THIS EVENT HAS MINIMAL | | SAFETY SIGNIFICANCE DUE TO THE UNLIKELY SEQUENCE OF EVENTS THAT WOULD | | REQUIRE SBNI USE, AND THAT TRAIN "B" OF THE SBNI SYSTEM CAN BE USED WITHOUT | | SIMILAR CONSEQUENCES. HOWEVER, DUE TO THE POTENTIAL TO BREECH SECONDARY | | CONTAINMENT DURING A DESIGN BASIS ACCIDENT, THIS CONDITION IS REPORTABLE | | UNDER 10CFR50.72(b)(2)(iii)." END OF TEXT. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+