U.S. Nuclear Regulatory Commission Operations Center Event Reports For 09/01/95 - 09/05/95 ** EVENT NUMBERS ** 29265 29268 29269 29270 29271 29272 29273 29274 29275 29276 29277 29278 29279 29280 29281 29282 29283 29284 29285 29286 29287 29288 29289 29290 29291 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29265 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 08/31/95 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 13:36 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 08/31/95 | +------------------------------------------------+EVENT TIME: 10:15[EDT]| |NRC NOTIFIED BY: ROGER WEST |LAST UPDATE DATE: 09/02/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PATRICK HILAND 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 N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | IMPROPER INSTALLATION OF THE SEAL ASSEMBLIES ON ELECTRICAL CONNECTIONS TO | | TWO REACTOR VESSEL HEAD VENT SOLENOID VALVES. | | | | THE LICENSEE DISCOVERED THAT SEAL ASSEMBLIES ON ELECTRICAL CONNECTIONS TO | | TWO UNIT 1 REACTOR VESSEL HEAD VENT SOLENOID VALVES HAD BEEN IMPROPERLY | | INSTALLED. THIS RESULTED IN THE LACK OF A MOISTURE BARRIER SUCH THAT BOTH | | VALVES COULD HAVE FAILED UNDER ACCIDENT CONDITIONS. EACH OF TWO REACTOR | | VESSEL HEAD VENT FLOW PATHS CONTAINS ONE OF THE AFFECTED VALVES. FAILURE | | OF BOTH VALVES WOULD RENDER THE REACTOR VESSEL HEAD VENT UNAVAILABLE FOR | | ACCIDENT MITIGATION. | | | | THE ROOT CAUSE OF THE INSTALLATION ERRORS IS CURRENTLY UNDETERMINED, AND | | THE LICENSEE IS CONTINUING TO INVESTIGATE THE STATUS OF OTHER CONNECTIONS | | IN THE REACTOR VESSEL HEAD VENT SYSTEM AND IN THE PRESSURIZER HEAD VENT | | SYSTEM. THIS IS AN ENVIRONMENTAL QUALIFICATION ISSUE. AT THE TIME OF THIS | | NOTIFICATION, THE LICENSEE DID NOT KNOW WHEN THE IMPROPER INSTALLATIONS | | OCCURRED, AND UNIT 1 WAS NOT IN ANY TECHNICAL SPECIFICATION LIMITING | | CONDITIONS FOR OPERATION. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | | | | * * * 20:05 AUGUST 31, 1995, UPDATE FROM WEST RECEIVED BY SCARFO * * * | | | | THE FOLLOWING IS THE TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "BASED UPON FURTHER EVALUATION OF THE STATUS OF THE SEAL ASSEMBLIES ON | | ELECTRICAL CONNECTIONS TO REACTOR VESSEL HEAD VENT SOLENOID VALVES AND | | PRESSURIZER VENT SOLENOID VALVES, IT HAS BEEN DETERMINED THAT THE | | ASSEMBLIES FOR ALL VENT SOLENOID VALVES ON BOTH UNITS WERE IMPROPERLY | | INSTALLED, THEREBY INVALIDATING THE ENVIRONMENTAL QUALIFICATION BASIS. ON | | UNIT 2, WHICH IS CURRENTLY IN MODE 3, DECLARATION OF VALVE INOPERABILITY | | HAS RESULTED IN ENTRY INTO A 72-HOUR ACTION STATEMENT. UNIT 1 IS IN A MODE | | IN WHICH THE VENT VALVE TECHNICAL SPECIFICATION DOES NOT APPLY. ACTIVITIES | | CONTINUE TO CORRECT THE SEAL ASSEMBLY INSTALLATION AND RESTORE THE VENT | | VALVES TO OPERABLE STATUS. | | | | APPLICABLE TECHNICAL SPECIFICATIONS IN UNIT 2 ARE 3.4.12.1 "REACTOR VESSEL | | HEAT VENTS", AND 3.4.12.2 "PRESSURIZER STEAM SPACE VENTS". ACTIONS | | STATEMENTS (b) OF BOTH SPECIFICATIONS ALLOW 72 HOURS TO RESTORE OPERABILITY | | (FOLLOWING REMOVAL OF POWER FROM THE VALVE ACTUATORS)." | | | | END OF TEXT. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR, AND THE NRC OPERATIONS | | CENTER NOTIFIED THE R3DO (HILAND). | | | | * * * 13:57 SEPTEMBER 1, 1995, UPDATE FROM PTACEK RECEIVED BY TROCINE * * * | | | | IN ORDER TO FACILITATE REPAIRS ON UNIT 2, THE LICENSEE COMMENCED A COOLDOWN | | AT 12:45 ON SEPTEMBER 1, 1995, AND PLANS TO COOL THE UNIT DOWN FROM MODE 3 | | TO MODE 5 FOR PERSONNEL SAFETY REASONS. UNIT 2 REACTOR COOLANT TEMPERATURE | | IS CURRENTLY AT 530øF, AND IT IS BEING COOLED DOWN AT A RATE OF 25øF PER | | HOUR. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR, AND THE NRC OPERATIONS | | CENTER NOTIFIED THE R3DO (MILLER). | | | | * * * 18:02 SEPTEMBER 2, 1995, UPDATE FROM KARNES RECEIVED BY TROCINE * * * | | | | UNIT 2 ENTERED MODE 5 AT 09:02 ON SEPTEMBER 2, 1995, AND THE LICENSEE HAS | | SINCE COMPLETED THE REPAIRS TO THE VENT SOLENOID VALVES. HOWEVER, | | ADDITIONAL INSPECTIONS REVEALED THAT THE PRESSURIZER PORV LIMIT SWITCH | | INDICATION CABLE AND THE PORV ACOUSTIC MONITORING SYSTEM ENVIRONMENTALLY | | QUALIFIED CONNECTIONS WERE ALSO IMPROPERLY INSTALLED. THIS EQUIPMENT IS | | REQUIRED TO BE OPERABLE DURING MODES 1, 2, AND 3, BUT THE LICENSEE PLANS TO | | KEEP UNIT 2 IN HOT SHUTDOWN UNTIL ALL OF THESE ISSUES HAVE BEEN CORRECTED. | | | | THE LICENSEE WILL NOTIFY THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | CENTER NOTIFIED THE R3DO (HILAND). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29268 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 08/31/95 | |UNIT: [1] [2] [3] STATE: SC |NOTIFICATION TIME: 23:10 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 08/31/95 | +------------------------------------------------+EVENT TIME: 23:01[EDT]| |NRC NOTIFIED BY: ROY SMITH |LAST UPDATE DATE: 09/01/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GEORGE AL BELISLE RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION REQUIRED SHUTDOWN BECAUSE A 72-HOUR LIMITING | | CONDITION FOR OPERATION FOR AN INOPERABLE BACKUP POWER SUPPLY WAS EXCEEDED. | | | | AT 22:01, THE LICENSEE EXCEEDED A LIMITING CONDITION FOR OPERATION TIME | | LIMIT BECAUSE 1 OF 2 BACKUP POWER SUPPLIES (THE OVERHEAD KEOWEE BACKUP | | POWER SUPPLY) WAS INOPERABLE FOR MORE THAN 72 HOURS. AS A RESULT, THE | | APPLICABLE TECHNICAL SPECIFICATION ACTION STATEMENT REQUIRES THE AFFECTED | | UNITS (ALL 3 UNITS) TO BE IN HOT SHUTDOWN WITHIN 12 HOURS AND COLD SHUTDOWN | | WITHIN THE FOLLOWING 48 HOURS. ACCORDINGLY, THE LICENSEE COMMENCED A | | SHUTDOWN OF UNIT 3 AT 23:01, AND THE LICENSEE CURRENTLY PLANS TO STAGGER | | THE UNIT SHUTDOWNS. UNIT 3 WILL BE SHUT DOWN FIRST FOLLOWED BY UNITS 1 AND | | 2, RESPECTIVELY. THERE HAD BEEN NO ENGINEERING SAFEGUARDS FEATURES | | ACTUATIONS OR REACTOR PROTECTIVE SYSTEM ACTUATIONS AS OF THE TIME OF THIS | | NOTIFICATION. | | | | PRIOR TO COMMENCEMENT OF THE UNIT 3 SHUTDOWN, THE LICENSEE WAS IMPLEMENTING | | A NUCLEAR STATION MODIFICATION TO THE OVERHEAD KEOWEE BACKUP POWER SUPPLY | | AND WAS NOT ABLE TO COMPLETE THE MODIFICATION WITHIN THE 72-HOUR ALLOTTED | | TIME FRAME. AS A RESULT, THE LICENSEE BACKED OUT OF THE MODIFICATION AND | | WAS REQUIRED TO TEST THE BACKUP POWER SUPPLY BEFORE RETURNING IT TO | | OPERABLE STATUS. TESTING IS CURRENTLY IN PROGRESS TO RETURN THE INOPERABLE | | BACKUP POWER SUPPLY TO AN OPERABLE STATUS. | | | | THE LICENSEE HAS NOTIFIED THE NRC RESIDENT INSPECTOR. | | | | * * * 00:17 SEPTEMBER 1, 1995, UPDATE FROM SMITH RECEIVED BY GOULD * * * | | | | AT 23:30 ON AUGUST 31, 1995, THE NRC REGION II OFFICE GRANTED A NOTICE OF | | ENFORCEMENT DISCRETION TO THE LICENSEE TO ALLOW 24 HOURS (IN LIEU OF 12 | | HOURS) TO SEQUENTIALLY BRING ALL 3 UNITS TO HOT SHUTDOWN. TESTING OF THE | | BACKUP POWER SUPPLY IS CURRENTLY ONGOING, AND THE UNIT 3 POWER REDUCTION IS | | STILL IN PROGRESS. UNIT 3 IS CURRENTLY OPERATING AT 90% REACTOR POWER, AND | | UNITS 1 AND 2 ARE BOTH CURRENTLY OPERATING AT 100% REACTOR POWER. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | CENTER NOTIFIED THE R2DO (BELISLE). | | | | * * * UPDATE AT 02:44 ON SEPTEMBER 1, 1995, BY SNOWDEN TO GOULD * * * | | | | THE BACKUP EMERGENCY POWER SUPPLY WAS RETURNED TO SERVICE, AND THE LIMITING | | CONDITION FOR OPERATION WAS EXITED AT 02:30. UNITS 1 AND 2 ARE CURRENTLY | | AT 100% REACTOR POWER, AND UNIT 3 IS CURRENTLY AT 75% REACTOR POWER. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29269 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 09/01/95 | |UNIT: [ ] [2] [ ] STATE: NY |NOTIFICATION TIME: 06:37 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 09/01/95 | +------------------------------------------------+EVENT TIME: 05:04[EDT]| |NRC NOTIFIED BY: RESTUCCIO |LAST UPDATE DATE: 09/01/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOHAMED SHANBAKY RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | M/R Y 26 POWER OPERATION | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT HAD A MANUAL REACTOR SCRAM FROM 26% POWER. | | | | THIS SCRAM OCCURRED DURING A PLANT SHUTDOWN ON A FORCED OUTAGE WHEN | | VIBRATION ON MAIN TURBINE BEARING #6 INCREASED TO 11.6 MILS. (AN AUTOMATIC | | TURBINE TRIP OCCURS AT A BEARING VIBRATION OF 12 MILS.) THE REACTOR | | RECIRCULATION PUMPS WERE IN SLOW SPEED. AT THIS TIME, A MANUAL REACTOR | | SCRAM WAS ORDERED IN ANTICIPATION OF AN AUTOMATIC TURBINE TRIP AND THE | | SUBSEQUENT AUTOMATIC REACTOR SCRAM (WITH REACTOR POWER AT 26%). SPECIAL | | OPERATING PROCEDURES FOR THE TURBINE TRIP AND REACTOR SCRAM WERE | | IMPLEMENTED IN PARALLEL WITH THE EMERGENCY OPERATING PROCEDURE. POST-SCRAM | | REACTOR WATER LEVEL LOWERED TO 154 INCHES AND WAS SUBSEQUENTLY RECOVERED TO | | A NORMAL LEVEL OF 183 INCHES WITH REACTOR FEEDWATER. ALL CONTROL RODS | | FULLY INSERTED WITH THE EXCEPTION OF ROD 26-19. AT 05:09, ROD 26-19 WAS | | FOUND AT POSITION "00" WHICH IS FULLY INSERTED. INITIAL POSITION OF ROD | | 26-19 WAS REPORTED AS UNKNOWN, AND THE LICENSEE IS CONTINUING TO | | INVESTIGATE THIS. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29270 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ZION REGION: 3 |NOTIFICATION DATE: 09/01/95 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 08:52 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/01/95 | +------------------------------------------------+EVENT TIME: 04:56[CDT]| |NRC NOTIFIED BY: WENNERHOLM |LAST UPDATE DATE: 09/01/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PAT HILAND RDO | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 99 POWER OPERATION | 99 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 1 ENTERED TECHNICAL SPECIFICATION 3.0.3 DUE TO LOW AIR PRESSURE ON | | ZONE 4 ISOLATION VALVE SEAL WATER TANK. | | | | THE CONTROL ROOM RECEIVED AN ISOLATION VALVE SEAL WATER TANK (USED TO | | SUPPLY PRESSURIZATION AIR TO PENETRATION AREA CONTAINMENT ISOLATION VALVES) | | LOW PRESSURE ANNUNCIATOR ALARM. AN OPERATOR WAS SENT TO THE ISOLATION | | WATER TANK AND DISCOVERED THAT THE TANKS PRESSURE WAS 32 psig. (THE | | TECHNICAL SPECIFICATION 3.9 LIMIT IS ò68 psig.) THE LICENSEE ENTERED | | TECHNICAL SPECIFICATION 3.0.3 (4 HOURS TO HOT SHUTDOWN CONDITION). AFTER | | 29 MINUTES, THE ISOLATION VALVE SEAL WATER TANK PRESSURE WAS INCREASED TO | | ò68 psig AT WHICH TIME THE LICENSEE EXITED TECHNICAL SPECIFICATION 3.0.3 AT | | 0525 CDT. UPON INVESTIGATION, THE LICENSEE FOUND THAT WHEN THE ISOLATION | | VALVE SEAL WATER TANK RECEIVER WAS TAKEN OUT OF SERVICE FOR PERIODIC | | TESTING OF ITS RELIEF VALVES PER PROCEDURE SOI-BD, THE PROCEDURE OMITTED | | OPENING NITROGEN ISOLATION VALVE 1PPO199 WHICH WOULD HAVE PRESSURIZED THE | | ISOLATION WATER TANK TO ò68 psig WHILE ITS RECEIVER WAS ISOLATED FOR | | TESTING. THE LICENSEE WILL PERFORM A ROOT CAUSE ANALYSIS OF THIS EVENT AND | | WILL REVISE THE PROCEDURE. THE LICENSEE SAID THAT IT HAD PERFORMED THIS | | SAME PROCEDURE IN THE PAST WITHOUT ANY PROBLEMS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29271 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 09/01/95 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 08:52 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 09/01/95 | +------------------------------------------------+EVENT TIME: 06:49[EDT]| |NRC NOTIFIED BY: MICHAEL DAMMANN |LAST UPDATE DATE: 09/01/95 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PATRICK HILAND 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 N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNPLANNED REACTOR CORE ISOLATION COOLING (RCIC) INITIATION SIGNAL DURING | | RESTORATION OF DIVISION 2 POWER SUPPLY. | | | | DURING RE-ENERGIZATION OF DIVISION 2 TOPAZ INVERTER POWER SUPPLY, THE UNIT | | RECEIVED A RCIC INITIATION SIGNAL. RCIC WAS ISOLATED PRIOR TO THE | | INITIATION SIGNAL AND DID NOT INITIATE. EMERGENCY CLOSED COOLING (ECC) | | PUMP "A" AUTOMATICALLY STARTED IN RESPONSE TO THE RCIC INITIATION SIGNAL. | | THE ECC PUMP "A" WAS RETURNED TO STANDBY BY 06:55 EST. THE LICENSEE | | ATTRIBUTES THE CAUSE TO PERSONNEL ERROR AND A WORK ORDER INADEQUACY IN NOT | | RECOGNIZING RCIC ACTUATION WHEN RE-ENERGIZING THE DIVISION 2 POWER SUPPLY. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | SEE EVENT #29264 FOR RELATED INFORMATION. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29272 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 09/01/95 | |UNIT: [ ] [3] [ ] STATE: NY |NOTIFICATION TIME: 14:15 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 09/01/95 | +------------------------------------------------+EVENT TIME: 11:50[EDT]| |NRC NOTIFIED BY: TOM WOOLEY |LAST UPDATE DATE: 09/01/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOHAMED SHANBAKY RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 3 | N Y 100 POWER OPERATION | 95 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT SHUTDOWN AS A RESULT OF A LOSS OF THE CAPABILITY TO INITIATE A | | FEEDWATER ISOLATION SIGNAL FROM A REACTOR TRIP WITH A LOW REACTOR COOLANT | | SYSTEM TEMPERATURE CONDITION DUE TO A FAILED RELAY | | | | AT 11:50, THE LICENSEE DISCOVERED THE FAILURE OF RELAY RTX1 DURING THE | | PERFORMANCE OF PROCEDURE 3PT-M14A, SAFETY INJECTION SYSTEM LOGIC FUNCTIONAL | | TRAIN 'A' TEST. THIS CAUSED THE TRAIN 'A' FEEDWATER ISOLATION CIRCUITRY TO | | BE INOPERABLE. AT 13:18, THE LICENSEE COMMENCED A UNIT SHUTDOWN FROM 100% | | REACTOR POWER TO HOT SHUTDOWN AT A RATE OF 20% PER HOUR. THIS WAS THE | | RESULT OF THE LOSS OF THE CAPABILITY TO INITIATE A FEEDWATER ISOLATION | | SIGNAL FROM A REACTOR TRIP WITH A LOW REACTOR COOLANT SYSTEM TEMPERATURE | | CONDITION. | | | | THIS SHUTDOWN WAS IN ACCORDANCE WITH THE LICENSEE'S OPERATIONS POLICY | | (MOTHERHOOD STATEMENT) FOR NOT HAVING AN ACTION TIME REQUIREMENT OR | | TECHNICAL SPECIFICATION LIMITING CONDITION FOR OPERATION FOR THE SPECIFIC | | CONDITION. THIS OPERATIONS POLICY STATES THAT IN THE EVENT THAT THE | | LICENSEE IS IN A CONDITION OUTSIDE OF THE TECHNICAL SPECIFICATIONS, THEN | | THE LICENSEE HAS ONE HOUR TO AFFECT REPAIRS AND MAKE PREPARATIONS AND | | ANOTHER SIX HOURS TO PLACE THE UNIT IN HOT SHUTDOWN. | | | | AT 13:51, THE AFFECTED RELAY COIL WAS REPLACED, TESTED SATISFACTORILY, AND | | DECLARED OPERABLE. AS A RESULT, THE LICENSEE TERMINATED THE SHUTDOWN WITH | | THE UNIT AT 95% REACTOR POWER. THE LICENSEE PLANS TO MAINTAIN THE UNIT AT | | 95% REACTOR POWER PENDING A MANAGEMENT DECISION TO ESCALATE POWER. THE | | CAUSE OF THE RELAY FAILURE IS UNKNOWN AT THIS TIME. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29273 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HARRIS REGION: 2 |NOTIFICATION DATE: 09/01/95 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 15:04 [ET]| |RX TYPE: [1] W-3-LP |EVENT DATE: 09/01/95 | +------------------------------------------------+EVENT TIME: 13:35[EDT]| |NRC NOTIFIED BY: BRYCE MILLER |LAST UPDATE DATE: 09/01/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GEORGE AL BELISLE 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 75 POWER OPERATION | 75 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNPLANNED AUXILIARY FEEDWATER ACTUATION DURING TESTING DUE TO A PROCEDURAL | | PROBLEM | | | | DURING THE PERFORMANCE OF ELECTRICAL SURVEILLANCE TEST PROCEDURE MST-E0034, | | THE 'A' TRAIN STEAM SUPPLY VALVE (IMS-70) TO THE TURBINE-DRIVEN AUXILIARY | | PUMP WAS INADVERTENTLY OPENED. THE TEST DID NOT ADDRESS THE FACT THAT | | VALVE IMS-70 WOULD OPEN, AND THEREFORE, IT WAS NOT EXPECTED TO OCCUR. THE | | LICENSEE RECLOSED THE VALVE WITHIN 2 MINUTES, AND NO ADVERSE EFFECTS | | OCCURRED. A SIMILAR OPERATIONS SURVEILLANCE TEST REQUIRES THIS VALVE TO BE | | DE-ENERGIZED TO PREVENT THIS TYPE OF ACTUATION, BUT THIS ELECTRICAL TEST | | DID NOT. IN ADDITION, LICENSEE PERSONNEL DID NOT RECOGNIZED THAT THE VALVE | | WOULD OPEN BEFORE THE TEST WAS RUN. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29274 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ARKANSAS NUCLEAR REGION: 4 |NOTIFICATION DATE: 09/01/95 | |UNIT: [ ] [2] [ ] STATE: AR |NOTIFICATION TIME: 15:07 [ET]| |RX TYPE: [1] B&W-L-LP,[2] CE |EVENT DATE: 09/01/95 | +------------------------------------------------+EVENT TIME: 11:30[CDT]| |NRC NOTIFIED BY: BILL HINTON |LAST UPDATE DATE: 09/01/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PHIL HARRELL RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | A/R Y 98 POWER OPERATION | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR TRIP ON HIGH STEAM GENERATOR LEVEL DUE TO THE INCREASE IN FEEDWATER | | PUMP SPEED WHEN A PAINTER INADVERTENTLY VENTED THE 'B' MAIN FEEDWATER | | HEADER FLOW TRANSMITTER | | | | A CONTRACTOR PAINTER INADVERTENTLY VENTED THE 'B' MAIN FEEDWATER HEADER | | FLOW TRANSMITTER, AND THIS IN TURN CAUSED BOTH MAIN FEEDWATER PUMPS TO | | INCREASE SPEED. HIGH STEAM GENERATOR LEVEL WAS REACHED ON THE 'B' STEAM | | GENERATOR, AND THE REACTOR AUTOMATICALLY TRIPPED FROM 98% REACTOR POWER. | | ALL SYSTEMS RESPONDED AS EXPECTED FOLLOWING THE REACTOR TRIP. ALL RODS | | FULLY INSERTED, EMERGENCY FEEDWATER ACTUATED (AS EXPECTED), AND NO SAFETY | | VALVES LIFTED. | | | | STEAM GENERATOR LEVELS ARE CURRENTLY BEING MAINTAINED WITHIN THE NORMAL | | RANGE VIA THE USE OF EMERGENCY FEEDWATER, AND THE GENERATORS ARE STEAMING | | TO THE CONDENSER. (EMERGENCY FEEDWATER ACTUATED AS EXPECTED AS A RESULT OF | | THE REACTOR TRIP.) PRIMARY INVENTORY AND PRESSURE CONTROL IS CURRENTLY | | BEING MAINTAINED VIA THE USE OF NORMAL CHARGING AND LETDOWN. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. IN ADDITION, A COURTESY | | NOTIFICATION WAS MADE TO THE ARKANSAS STATE DEPARTMENT OF HEALTH AT 13:05. | | A PRESS RELEASE MAY BE ISSUED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 29275 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BABCOCK & WILCOX CO. |NOTIFICATION DATE: 09/01/95 | | RXTYPE: URANIUM FUEL FABRICATION |NOTIFICATION TIME: 15:44 [ET]| |COMMENTS: HEU FABRICATION & SCRAP RECOVERY |EVENT DATE: 08/29/95 | | NAVAL REACTOR FUEL |EVENT TIME: 22:00[EDT]| | |LAST UPDATE DATE: 09/01/95 | | CITY: LYNCHBURG REGION: 2 +-----------------------------+ | COUNTY: CAMPBELL STATE: VA |PERSON ORGANIZATION| |LICENSE#: SNM-42 AGREEMENT: N |GEORGE AL BELISLE RDO | | DOCKET: 07000027 |COMBS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: OLSEN | | |HQ OPS OFFICER: GREG SCARFO | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE AMOUNT OF URANIUM-235 STORED IN A UNIT OF A STORAGE RACK ASSOCIATED | | WITH THE SCRAP MATERIAL RECOVERY OPERATION AT B&W NAVAL NUCLEAR FUEL | | FABRICATION FACILITY IN LYNCHBURG, VIRGINIA, EXCEEDED THE ADMINISTRATIVE | | LIMIT OF 350 GRAMS AS STIPULATED IN GENERIC LETTER 91-01. | | | | THE FOLLOWING IS THE TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | "AT ABOUT 10:00PM ON TUESDAY, AUGUST 29, 1995, AN OPERATOR DISCOVERED A | | POTENTIALLY UNSAFE CONDITION IN THAT A STORAGE UNIT WITH A POSTED LIMIT OF | | 350 GRAMS U-235 HAD AN ACTUAL AMOUNT OF 783.82 GRAMS OF U-235. THE | | OPERATOR IMMEDIATELY NOTIFIED THE FOREMAN OVER THE AREA. IMMEDIATE | | CORRECTIVE ACTION WAS TAKEN, AND EXCESS U-235 WAS REMOVED FROM THE UNIT | | SUCH THAT ALL UNITS HAD LESS THAN THE POSTED LIMIT OF 350 GRAMS U-235. | | | | THE UNIT WAS ONE OF 12 UNITS OF AN SNM STORAGE RACK LOCATED IN THE DRUM | | COUNT AREA. IN ADDITION TO THE IMMEDIATE CORRECTIVE ACTION TAKEN TO ASSURE | | THAT THE UNIT'S MASS LIMIT WAS BEING MET, ALL STORAGE UNITS AND LOCATIONS | | IN THE AREA HAVE BEEN CHECKED TO ENSURE THAT THERE ARE NO OTHER UNITS IN | | VIOLATION OF THEIR POSTED LIMIT. | | | | AS SET OF CONSERVATIVE PHYSICS CALCULATIONS HAVE BEEN MADE AND Q.A. | | REVIEWED. THE 783.82 GRAMS WAS DRY, FULLY ENRICHED UO2. THE CALCULATIONS | | DEMONSTRATE THAT IF ALL 12 UNITS OF THE RACK, INSTEAD OF JUST ONE, HAD BEEN | | OVERLOADED TO 800 GRAMS OF THIS TYPE OF MATERIAL, THE KEFF WOULD STILL HAVE | | BEEN LESS THAN THE LICENSE LIMIT FOR NORMAL OPERATIONS, 0.85. THE ACTUAL | | EXISTING CONDITION, THEREFORE, DID NOT EXCEED ANY NNFD LICENSE LIMIT. | | | | A PRELIMINARY INVESTIGATION HAS BEEN MADE. IT IS BELIEVED THAT THE UNIT | | WAS IN A STATE OF OVERLOAD FOR ABOUT 8 TO 11 HOURS BEFORE BEING DISCOVERED. | | AT THIS TIME, THERE ARE NO EXPLANATIONS OF WHY THE RACK'S POSTED LIMITS | | WERE VIOLATED. AN INVESTIGATION TEAM IS BEING FORMED TO CONDUCT A DETAILED | | REVIEW OF THE INCIDENT TO DETERMINE ROOT CAUSES AND RECOMMEND CORRECTIVE | | ACTIONS TO PREVENT RECURRENCE. | | | | GIVEN THAT SPACING, REFLECTOR, AND MODERATION CONTROLS REMAINED INTACT, IT | | IS POSSIBLE THAT DOUBLE CONTINGENCY WAS NOT LOST. CALCULATIONS ARE BEING | | PERFORMED TO CONFIRM THIS. HOWEVER, THEY WILL NOT BE COMPLETE WITHIN 24 | | HOURS OF THE OCCURRENCE; THEREFORE, THIS REPORT IS BEING SUBMITTED. IF IT | | CAN BE CONFIRMED THAT DOUBLE CONTINGENCY WAS NOT LOST, THIS REPORT WILL BE | | WITHDRAWN. | | | | THE NRC RESIDENT HAS BEEN NOTIFIED. REGION II AND NRC STAFF HAVE ALSO BEEN | | ADVISED. THE GENERAL MANAGER HAVE BEEN BRIEFED." | | END OF TEXT. | | | | IN THE SCRAP MATERIAL RECOVERY PORTION OF THE FACILITY, A STORAGE RACK | | CONTAINS 12 STORAGE UNITS. EACH LOCATION CAN HOLD EIGHT 2.5 LITER BOTTLES | | OF SCRAP U-235. THE ADMINISTRATIVE LIMIT ON U-235 FOR EACH STORAGE UNIT IS | | 350 GRAMS. EACH BOTTLE IS MARKED WITH THE AMOUNT OF U-235 IT CONTAINS | | PRIOR TO STORAGE BY AN OPERATOR. AN OPERATOR INCORRECTLY STORED FIVE | | BOTTLES RANGING IN AMOUNTS FROM 90 GRAMS OF U-235 TO 250 GRAMS OF U-235 IN | | A PARTICULAR STORAGE UNIT. THIS EXCEEDED ITS 350 GRAM U-235 LIMIT. | | SUBSEQUENTLY, ANOTHER OPERATOR DISCOVERED THIS CONDITION AND IMMEDIATELY | | RECONFIGURED THE BOTTLES TO REDUCE THE U-235 INVENTORY IN THE STORAGE UNIT | | BELOW THE 350 GRAM LIMIT. | | | | AN INVESTIGATION IS ONGOING TO DETERMINED THE CAUSE OF THIS CONDITION. THE | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR, REGION II PERSONNEL, AND HQ | | PERSONNEL. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 29276 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: N/A |NOTIFICATION DATE: 09/01/95 | | CITY: ST. PETERSBURG REGION: 2 |NOTIFICATION TIME: 16:42 [ET]| | COUNTY: STATE: FL |EVENT DATE: 09/01/95 | |LICENSE#: N/A AGREEMENT: Y |EVENT TIME: 14:35[EDT]| | DOCKET: |LAST UPDATE DATE: 09/01/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | |GEORGE AL BELISLE RDO | | |JOHN HICKEY EO | +------------------------------------------------+ | |NRC NOTIFIED BY: WILLIAM LENSMYER |ED SENSINTAFFAR EPA | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | RESOURCE RECYCLING (A SCRAP METAL PROCESSING BUSINESS) OF ST. PETERSBURG, | | FLORIDA, IDENTIFIED AND CONTAINED A RADIOACTIVE SOURCE IN EXCESS OF FIVE | | MICRO-ROENTGENS PER HOUR ON CONTACT | | | | A RADIOACTIVE SOURCE WAS DISCOVERED IN A LOAD OF SCRAP METAL THAT RESOURCE | | RECYCLING HAD SENT TO MISSISSIPPI STEEL (A STEEL MILL). MISSISSIPPI STEEL | | DETECTED VERY LOW LEVELS OF RADIOACTIVITY AND RETURNED THE ENTIRE LOAD OF | | SCRAP METAL TO RESOURCE RECYCLING. RESOURCE RECYCLING THEN INSPECTED THE | | LOAD OF SCRAP METAL AND IDENTIFIED A 12-INCH LONG, 8-INCH DIAMETER, | | RADIOACTIVE CYLINDER WITH NO IDENTIFIABLE MAKINGS. THERE WAS NO OBVIOUS | | DAMAGE TO THE CYLINDER. SURVEY READINGS OF THE CYLINDER WERE IN EXCESS OF | | 5,000 MICRO-ROENTGENS PER HOUR ON CONTACT. THESE SURVEY READINGS DECREASED | | RAPIDLY WITH INCREASING DISTANCE. THE ISOTOPE HAS NOT YET BEEN IDENTIFIED. | | | | THE RADIOACTIVE CYLINDER IS CURRENTLY CONTAINED IN A 55-GALLON DRUM, AND | | THE SURVEY READINGS OUTSIDE THE DRUM ARE LESS THAN 1,000 MICRO-ROENTGENS | | PER HOUR. RESOURCE RECYCLING ALSO CHECKED ALL OF THE SURROUNDING AREA AND | | MATERIAL, AND NO RESIDUALS WERE IDENTIFIED. | | | | RESOURCE RECYCLING HAS CONTACTED A CONSULTANT WHO WILL ARRIVE NEXT WEEK TO | | TRY TO DETERMINE WHERE THE CYLINDER CAME FROM AND TO DETERMINE WHAT TO DO | | WITH IT. RESOURCE RECYCLING ALSO NOTIFIED THE STATE OF FLORIDA DEPARTMENT | | OF ENVIRONMENTAL PROTECTION. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 29277 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: NORTH STAR STEEL COMPANY |NOTIFICATION DATE: 09/01/95 | | CITY: YOUNGSTOWN REGION: 3 |NOTIFICATION TIME: 18:10 [ET]| | COUNTY: STATE: OH |EVENT DATE: 08/27/95 | |LICENSE#: AGREEMENT: N |EVENT TIME: 01:00[EDT]| | DOCKET: |LAST UPDATE DATE: 09/01/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | |PATRICK HILAND RDO | | |JOHN HICKEY EO | +------------------------------------------------+ | |NRC NOTIFIED BY: RALPH GRAF | | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |IBDB 30.50(b)(4)(ii) DAMAGED LNM/CONTAINER | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | NORTH STAR STEEL COMPANY OF YOUNGSTOWN, OHIO, ACCIDENTALLY POURED LIQUID | | STEEL OVER THE TOP OF A 1,000 MILLICURIE CESIUM-137 SOURCE | | | | AT 01:00 ON AUGUST 27, 1995, LIQUID STEEL WAS ACCIDENTALLY POURED OVER THE | | TOP OF A 1,000 MILLICURIE CESIUM-137 SOURCE THAT WAS USED FOR MONITORING | | AND CONTROLLING THE LIQUID STEEL LEVEL IN THE LICENSEE'S MOLDS. AS A | | RESULT, THE ENCASING LEAD MELTED, AND THE ENCAPSULATED CESIUM-137 SOURCE | | FLOATED TO THE TOP OF THE LEAD. SURVEYS INDICATED THAT THE SOURCE WAS | | STILL INTACT. SURVEY READINGS WERE ABOUT 830 MILLIREM AT THE SOURCE ON | | CONTACT, AND THE HOTTEST SPOT 3 FEET AWAY FROM THE SOURCE WAS APPROXIMATELY | | 50 MILLIREM. | | | | ON THE MORNING OF AUGUST 27, 1995, THE LICENSEE REMOVED THE SOURCE FROM THE | | PLANT SITE OPERATIONS AREA AND PLACED IT IN A SECURED AREA THAT WAS ROPED | | OFF BY A FIELD SURVEY TO LESS THAN 2 MILLIREM. THE INDIVIDUAL WHO | | PERFORMED THIS TASK RECEIVED A DOSE OF 3 MILLIREM. | | | | ON AUGUST 31, 1995, THE SOURCE WAS PHYSICALLY CUT OFF AND PLACED IN A | | 55-GALLON BARREL WITH SAND. THIS REDUCED THE FIELD TO APPROXIMATELY ONE | | HALF. THE SOURCE WAS THEN PLACED IN A LOCKED AND LABELLED ROOM AT | | APPROXIMATELY 15:30 ON AUGUST 31, 1995. THE SAME INDIVIDUAL PERFORMED THIS | | TASK AND RECEIVED ANOTHER 25 MILLIREM. | | | | THE LICENSEE NOTIFIED THE NRC REGION 3 OFFICE (SLAWINSKI). REPRESENTATIVES | | FROM THE NRC REGION 3 OFFICE AND FROM A LICENSED WASTE DISPOSAL COMPANY ARE | | EXPECTED TO GO TO THE SITE ON SEPTEMBER 5, 1995. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29278 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 09/01/95 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 19:05 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/01/95 | +------------------------------------------------+EVENT TIME: 17:29[CDT]| |NRC NOTIFIED BY: MIKE DEBOARD |LAST UPDATE DATE: 09/01/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PATRICK HILAND RDO | |ADEG 50.72(b)(1)(ii) DEGRAD COND DURING OP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | POTENTIAL DEGRADED CONDITION FOR THE SAFETY INJECTION SYSTEM DUE TO | | CONFLICTING OPERABILITY DETERMINATIONS | | | | AT 23:10 CDT ON AUGUST 27, 1995, THE 1A SAFETY INJECTION PUMP WAS TAKEN OUT | | OF SERVICE FOR SCHEDULED MAINTENANCE WORK, AND THE 1A SAFETY INJECTION PUMP | | SUCTION VALVE (1SI8923A) WAS ISOLATED AND DE-ENERGIZED IN THE CLOSED | | POSITION. AN OPERABILITY DETERMINATION PERFORMED IN 1992 ADDRESSED THIS | | CONDITION AND DETERMINED THAT THERE WAS NO OPERABILITY EFFECT ON THE 'B' | | TRAIN OF EMERGENCY CORE COOLING SYSTEM EQUIPMENT. VALVE 1SI8923A WAS | | RESTORED AT 03:02 CDT ON AUGUST 30, 1995. | | | | SUBSEQUENT TO THE RESTORATION OF THE 1A SAFETY INJECTION TRAIN, ANOTHER | | OPERABILITY DETERMINATION WAS DISCOVERED WHICH PLACED A RESTRICTION OF 1 | | HOUR ON THE TIME THAT VALVE 1SI8923A COULD BE CLOSED AND INCAPABLE OF BEING | | OPENED. THERE APPEARS TO BE A CONFLICT BETWEEN THE TWO OPERABILITY | | DETERMINATIONS. THE EXACT PLANT CONFIGURATION THAT EXISTED AT THE TIME OF | | THE SECOND EVALUATION IS UNKNOWN AT THIS TIME. | | | | IF SUBSEQUENT RESEARCH INDICATES THAT THE LATER OPERABILITY EVALUATION IS | | APPLICABLE TO THE PLANT CONFIGURATION THAT EXISTED FROM AUGUST 27 TO 30, | | THEN THIS EVENT IS REPORTABLE AS A DEGRADED CONDITION AND IS BEING | | CONSERVATIVELY REPORTED AT THIS TIME. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29279 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 09/01/95 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 19:46 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/01/95 | +------------------------------------------------+EVENT TIME: 18:52[EDT]| |NRC NOTIFIED BY: RUSSELL MUNOS |LAST UPDATE DATE: 09/01/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |MOHAMED SHANBAKY RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |JACK ROE EO | | |AL AUSTIN FEMA | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNUSUAL EVENT DECLARED DUE TO THE TRANSPORT OF A POTENTIALLY CONTAMINATED | | INDIVIDUAL OFFSITE TO AN OFFSITE MEDICAL FACILITY | | | | AT APPROXIMATELY 18:30, AN INDIVIDUAL FELL FROM A STEAM GENERATOR PLATFORM | | ONTO TWO OTHER INDIVIDUALS. THE INDIVIDUAL THAT FELL AND ONE OF THE TWO | | INDIVIDUALS THAT BROKE THE FALL WERE INJURED (NOT SEVERELY) AND WERE NOT | | CONTAMINATED. THE OTHER INDIVIDUAL ON THE GROUND COMPLAINED OF NUMBNESS ON | | ONE SHOULDER AND WAS PLACED ON A STRETCHER. AT 18:52, THE LICENSEE MADE | | THE DECISION TO TRANSPORT THIS POTENTIALLY CONTAMINATED INDIVIDUAL TO AN | | OFFSITE MEDICAL FACILITY VIA AN AMBULANCE, AND AN UNUSUAL EVENT WAS | | DECLARED IN ACCORDANCE WITH EMERGENCY CLASSIFICATION GUIDELINE SECTION 7, | | CONDITION 'A'. THE INDIVIDUAL WAS TRANSPORTED OFFSITE AT APPROXIMATELY | | 19:07, AND THE AMBULANCE REACHED THE HOSPITAL AT 19:30. | | | | THERE WAS NO RADIOLOGICAL RELEASE IN PROGRESS, AND NO PROTECTIVE ACTIONS | | ARE RECOMMENDED AT THIS TIME. THE UNUSUAL EVENT WILL BE TERMINATED IF | | LICENSEE HEALTH PHYSICS PERSONNEL LOCATED AT THE HOSPITAL DETERMINE THAT | | THE INJURED INDIVIDUAL IS NOT CONTAMINATED. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR, THE LOWER ALLOWAYS CREEK | | TOWNSHIP, AND THE STATES OF NEW JERSEY AND DELAWARE. | | | | * * * 20:06 SEPTEMBER 1, 1995, UPDATE FROM MUNOS RECEIVED BY TROCINE * * * | | | | A SURVEY OF THE POTENTIALLY CONTAMINATED INDIVIDUAL DETERMINED THAT HE WAS | | NOT CONTAMINATED. AS A RESULT, THE LICENSEE TERMINATED THE UNUSUAL EVENT | | AT 20:00. THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR, THE | | LOWER ALLOWAYS CREEK TOWNSHIP, AND THE STATES OF NEW JERSEY AND DELAWARE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29280 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 09/01/95 | |UNIT: [ ] [ ] [3] STATE: AL |NOTIFICATION TIME: 21:35 [ET]| |RX TYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 09/01/95 | +------------------------------------------------+EVENT TIME: 18:34[CDT]| |NRC NOTIFIED BY: A. T. ROGERS |LAST UPDATE DATE: 09/01/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GEORGE AL BELISLE RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N N 0 REFUELING | 0 REFUELING | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INADVERTENT AUTOMATIC START OF ALL UNIT 3 EMERGENCY DIESEL GENERATORS WHILE | | BOOTING A RELAY CONTACT DURING SCHEDULED SURVEILLANCE TESTING | | | | AT 18:34 CDT, A BOOT WAS BEING INSTALLED AS SPECIFIED ON RELAY 14AK35a | | DURING THE PERFORMANCE OF SURVEILLANCE PROCEDURE 1/2-SI-4.9.A.3.a, COMMON | | ACCIDENT SIGNAL LOGIC, AND IT APPEARED THAT THE CONTACT WAS MADE UP. THIS | | IN TURN CAUSED ALL FOUR OF THE UNIT'S EMERGENCY DIESEL GENERATORS TO | | AUTOMATICALLY START AND COME UP TO RATED SPEED. THE EMERGENCY DIESEL | | GENERATORS DID NOT LOAD. ALL SYSTEMS RESPONDED AS EXPECTED. | | | | THE TEST WAS HALTED, AND THE EMERGENCY DIESEL GENERATORS WERE STOPPED AND | | RETURNED TO STANDBY READINESS AT 19:01 CDT. THE LICENSEE PLANS TO CONDUCT | | FURTHER TESTING ONCE THE PROCEDURE IS REVISED TO PROVIDE AN EASIER METHOD | | OF DISABLING THE RELAY CONTACT. | | | | THE LICENSEE WILL NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29281 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ARKANSAS NUCLEAR REGION: 4 |NOTIFICATION DATE: 09/01/95 | |UNIT: [1] [ ] [ ] STATE: AR |NOTIFICATION TIME: 23:36 [ET]| |RX TYPE: [1] B&W-L-LP,[2] CE |EVENT DATE: 09/01/95 | +------------------------------------------------+EVENT TIME: 19:30[CDT]| |NRC NOTIFIED BY: BRIAN DUNGAN |LAST UPDATE DATE: 09/01/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PHIL HARRELL 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 +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATIONS OF POTENTIAL FUEL OIL IN THE DISCHARGE CANAL. (REFER | | TO EVENT NUMBER 29285.) | | | | AT 19:30 CDT, A REPORT WAS MADE TO THE CONTROL ROOM OF A POTENTIAL FUEL OIL | | LEAK IN THE DISCHARGE CANAL. SMALL PATCHES OF AN OILY SUBSTANCE | | APPROXIMATELY ONE FOOT IN DIAMETER APPEARED TO BE COMING FROM THE EAST | | FLUME OF THE DISCHARGE CANAL. THESE PATCHES WERE REPORTED TO SMELL LIKE | | FUEL OIL. AS A RESULT, THE LICENSEE IMPLEMENTED ITS NO SPILL PREVENTION | | CONTROL AND COUNTER MEASURE PLAN, AND PERSONNEL WERE DISPATCHED THROUGHOUT | | THE PLANT TO TRY TO IDENTIFY THE SOURCE OF THE LEAKAGE. NO ABNORMAL LEAKS | | OR CONDITIONS WERE DISCOVERED. THE LEAKAGE OF OIL TO THE DISCHARGE CANAL | | IS ESTIMATED AT LESS THAN FIVE GALLONS, AND IT STOPPED AT 20:10 CDT. THERE | | WAS NO EFFECT ON THE PLANT, AND ACTIONS ARE CURRENTLY UNDER WAY TO | | DETERMINE THE SOURCE OF THE LEAKAGE. AT THE TIME OF THIS NOTIFICATION, | | THERE WAS NO CONFIRMED SOURCE OF THE LEAKAGE. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR, THE ARKANSAS DEPARTMENT | | OF HEALTH, THE STATE DEPARTMENT OF POLLUTION CONTROL AND ECOLOGY, THE ARMY | | CORPS OF ENGINEERS, AND THE U.S. COAST GUARD NATIONAL RESPONSE CENTER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29282 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 09/02/95 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 08:18 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 09/02/95 | +------------------------------------------------+EVENT TIME: 07:43[EDT]| |NRC NOTIFIED BY: STAN GAMBLE |LAST UPDATE DATE: 09/02/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOHAMED SHANBAKY RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 21 POWER OPERATION | 19 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT COMMENCED SHUTDOWN IN ACCORDANCE WITH PLANT TECHNICAL SPECIFICATIONS. | | | | THE LICENSEE ENTERED TECHNICAL SPECIFICATION 3.0.3 AND COMMENCED A UNIT | | SHUTDOWN WHEN BOTH POST-LOCA HYDROGEN RECOMBINERS WERE DECLARED INOPERABLE. | | DURING PERFORMANCE OF CONTAINMENT ATMOSPHERE CONTROL VALVE TEST | | ST6-057200-1, THE 1A AND 1B POST-LOCA RECOMBINER COOLING WATER VALVES | | (HV-57-110A AND B) FAILED TO OPERATE AS DESIGNED. THE 1A AND 1B POST-LOCA | | RECOMBINERS WERE DECLARED INOPERABLE AT 07:15, AND TECHNICAL SPECIFICATION | | 3.0.3 WAS ENTERED DUE TO THE LICENSEE'S INABILITY TO MEET TECHNICAL | | SPECIFICATION 3.6.6.1. | | | | ALTHOUGH THE LICENSEE HAS BEGUN REDUCING UNIT REACTOR POWER, THE LICENSEE | | STATED THAT IT DID NOT EXPECT THE UNIT TO BE COMPLETELY SHUT DOWN BEFORE | | THE VALVES WERE REPAIRED. THE LICENSEE STATED THAT THE PROBLEM APPEARED TO | | BE DUE TO A MODIFICATION WHICH WAS PERFORMED TO THE RECORDER INSTALLED ON | | BOTH RECOMBINERS. SPECIFICALLY, A CONTACT DOES NOT APPEAR TO BE CLOSING, | | THUS PREVENTING THE VALVES FROM STROKING. THE NRC RESIDENT INSPECTOR WILL | | BE INFORMED BY THE LICENSEE. | | | | * * * 21:37 SEPTEMBER 2, 1995, UPDATE FROM NEFF RECEIVED BY TROCINE * * * | | | | REPAIRS AND TESTING OF THE 1B RECOMBINER WERE SATISFACTORILY COMPLETED AT | | 19:50, AND FOLLOWING MANAGEMENT REVIEW OF THE CORRECTIVE ACTIONS AND | | TESTING METHODS, THE 1B RECOMBINER WAS DECLARED OPERABLE. REPAIRS AND | | TESTING OF THE 1A RECOMBINER WERE COMPLETED AT 20:55, AND IT WAS DECLARED | | OPERABLE. UNIT 1 IS CURRENTLY AT 7% REACTOR POWER WITH THE TURBINE OFF | | LINE. POWER ASCENSION IS UNDERWAY. THE LICENSEE NOTIFIED THE NRC RESIDENT | | INSPECTOR. THE NRC OPERATIONS CENTER NOTIFIED THE R1DO (SHANBAKY). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29283 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 09/02/95 | |UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 12:28 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 09/02/95 | +------------------------------------------------+EVENT TIME: 11:45[EDT]| |NRC NOTIFIED BY: STAN GAMBLE |LAST UPDATE DATE: 09/02/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOHAMED SHANBAKY RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 90 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO INOPERABILITY OF A | | POST-LOCA HYDROGEN RECOMBINER FOR MORE THAN 30 DAYS. | | | | AT 07:15 ON SEPTEMBER 2, 1995, THE 2A POST-LOCA HYDROGEN RECOMBINER WAS | | DETERMINED TO BE INOPERABLE DUE TO A PREVIOUSLY PERFORMED SYSTEM | | MODIFICATION. UPON REVIEW OF PLANT RECORDS, THE LICENSEE DETERMINED THAT | | THE 2A POST-LOCA HYDROGEN RECOMBINER HAD BEEN INOPERABLE SINCE JULY 19, | | 1995. AT 11:25 ON SEPTEMBER 2, 1995, THE LICENSEE DETERMINED THAT THE | | ACTION STATEMENT FOR TECHNICAL SPECIFICATION 3.6.6.1 (A 30-DAY LIMITING | | CONDITION FOR OPERATION) HAD NOT BEEN MET AND THAT ENTRY INTO TECHNICAL | | SPECIFICATION 3.0.3 WAS REQUIRED. ACCORDINGLY, A UNIT 2 SHUTDOWN PER | | TECHNICAL SPECIFICATION 3.0.3 WAS COMMENCED AT 11:45. NO EMERGENCY | | CLASSIFICATION WAS DECLARED. | | | | THE INOPERABILITY OF THE 2A POST-LOCA HYDROGEN RECOMBINER APPEARED TO BE | | THE RESULT OF A RECORDER PROBLEM. APPARENTLY, A RECORDER HAD BEEN | | INSTALLED WHICH AFFECTED THE LOGIC OF THE EQUIPMENT. THE LICENSEE | | ANTICIPATES RESOLUTION OF THIS ISSUE WITHIN APPROXIMATELY THREE HOURS. | | RE-PROGRAMING OF THE RECORDER IS CURRENTLY ONGOING. FOLLOWING COMPLETION, | | THE LICENSEE PLANS TO TEST THE EQUIPMENT, RESTORE IT TO OPERABILITY, EXIT | | THE ACTION STATEMENT OF TECHNICAL SPECIFICATION 3.0.3, AND RESUME POWER | | ASCENSION. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | | | | * * * 21:37 SEPTEMBER 2, 1995, UPDATE FROM NEFF RECEIVED BY TROCINE * * * | | | | REPAIRS AND TESTING OF THE 2A RECOMBINER WERE SATISFACTORILY COMPLETED AT | | 18:23, AND FOLLOWING MANAGEMENT REVIEW OF THE CORRECTIVE ACTIONS AND | | TESTING METHODS, THE 2A RECOMBINER WAS DECLARED OPERABLE. THE UNIT 2 | | SHUTDOWN WAS THEN TERMINATED WITH REACTOR POWER AT 34%, AND POWER ASCENSION | | WAS RECOMMENCED. THE UNIT IS CURRENTLY AT 51% REACTOR POWER. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | CENTER NOTIFIED THE R1DO (SHANBAKY). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 29284 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WESTINGHOUSE ELECTRIC CORPORATION |NOTIFICATION DATE: 09/02/95 | | RXTYPE: URANIUM FUEL FABRICATION |NOTIFICATION TIME: 14:12 [ET]| |COMMENTS: LEU CONVERSION (UF6 to UO2) |EVENT DATE: 09/01/95 | | COMMERCIAL LWR FUEL |EVENT TIME: 16:45[EDT]| | |LAST UPDATE DATE: 09/02/95 | | CITY: COLUMBIA REGION: 2 +-----------------------------+ | COUNTY: RICHLAND STATE: SC |PERSON ORGANIZATION| |LICENSE#: SNM-1107 AGREEMENT: Y |GEORGE AL BELISLE RDO | | DOCKET: 07001151 |JOHN HICKEY EO | +------------------------------------------------+ | |NRC NOTIFIED BY: WILBER GOODWIN/JIM HEATH | | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |KBDB 70.50(b)(4)(ii) DAMAGED LNM/CONTAINER | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DAMAGED URANIUM DIOXIDE POLYPACK CONTAINER DUE TO A MINOR FIRE. | | | | WHILE IN THE PROCESS OF SHUTTING DOWN CONVERSION OPERATIONS, AN OPERATOR | | NOTICED THAT A POLYPACK CONTAINER (A 6-INCH HIGH, 8-INCH DIAMETER, PLASTIC | | CONTAINER THAT HOLDS URANIUM DIOXIDE POWDER) ON CONVERSION LINE 2 WAS | | SMOLDERING IN THE FITZMILL PRODUCT HOOD AS THE POWDER WAS BEING DISCHARGED. | | SHORTLY AFTER, ANOTHER OPERATOR NOTICED A SMALL FLAME UP. THE OPERATORS | | USED SOME CLEANING RAGS THAT WERE IN THE VICINITY TO SMOTHER THE MINOR | | FIRE. PRIOR TO THE EVENT, THE URANIUM HEXAFLUORIDE FEED MATERIAL HAD BEEN | | SHUT OFF BECAUSE THE LINE WAS BEING SHUT DOWN IN PREPARATIONS FOR THE LONG | | HOLIDAY WEEKEND. ABOUT THE TIME THAT THE OPERATORS NOTICED THE SMOLDERING | | POWDER IN THE SMALL CONTAINER, THE STEAM AND HYDROGEN SUPPLIES TO THE LINE | | WERE SHUT OFF. AT THIS POINT, NOTHING COULD POSSIBLY FLOW INTO THE PRODUCT | | HOOD WHICH CONTAINED THE SMOLDERING URANIUM DIOXIDE POWDER. THE OPERATORS | | CONTINUED TO MONITOR AND EXTINGUISH THE FLAME UPS UNTIL THE POWDER COOLED | | OFF IN THE HOOD. THE SMOLDERING AND MINOR FLAME UPS WERE COMPLETELY | | EXTINGUISHED WITHIN APPROXIMATELY 15 MINUTES. AFTER THE MATERIAL COOLED, | | THE OPERATORS REMOVED IT, REPACKAGED IT INTO DIFFERENT POLYPACK CONTAINERS, | | AND CONTINUED TO SHUTDOWN THE LINE. | | | | AN AREA APPROXIMATELY TWO INCHES WIDE WAS MELTED OUT OF THE SIDE OF THE | | POLYPACK CONTAINER. AS A RESULT, SOME OF THE URANIUM DIOXIDE POWDER | | SPILLED OUT OF THE CONTAINER ONTO THE FLOOR OF THE HOOD. THE HOOD WAS NOT | | DAMAGED AND REMAINED FUNCTIONAL DURING THIS EVENT. THE LEVEL PROBE TO THE | | CONTAINER AND ALL OF THE SAFETY SYSTEMS ALSO REMAINED FUNCTIONAL. IN | | ADDITION, THERE WERE NO PERSONNEL INJURIES OR EXPOSURES AS A RESULT OF THIS | | EVENT. THIS EVENT ALSO INVOLVED APPROXIMATELY 25 KILOGRAMS OF URANIUM | | DIOXIDE POWER WITH AN ENRICHMENT OF 4.95 WEIGHT PERCENT. THIS WAS LESS | | THAN AN UNSAFE MASS AND WAS, THEREFORE, NOT A CRITICALITY CONCERN. | | | | THE URANIUM DIOXIDE POWDER WAS FIRST PRODUCED IN A CALCINER (A HEATED KILN) | | AND THEN IT WAS SENT TO THE FITZMILL (A CRUSHER THAT GRINDS THE POWDER TO | | PRODUCE UNIFORM PARTICLE SIZES). AFTER THE MILLING AND GRINDING PROCESSES, | | A CHUTE WAS CONNECTED TO THE POLYPACK CONTAINER. THE URANIUM DIOXIDE | | MATERIAL HAS A LARGE SURFACE AREA, AND BECAUSE THIS MATERIAL IS PYROPHORIC, | | IT TENDS TO OXIDIZE VERY RAPIDLY ESPECIALLY WHEN IT IS HOT AND SUBJECTED TO | | OXYGEN. IT ALSO GENERATES HEAT WHEN IT IS OXIDIZED. THEREFORE, THE | | LICENSEE'S INITIAL INVESTIGATION CONCLUDED THAT A POSSIBLE CAUSE OF THE | | MINOR FIRE COULD HAVE BEEN A FAILED SEAL WHICH PERMITTED OXYGEN TO ENTER | | THE POLYPACK CONTAINING THE HOT URANIUM DIOXIDE POWDER. | | | | THE LICENSEE PLANS TO INVESTIGATE THIS EVENT FURTHER AND TO NOTIFY THE NRC | | REGION 2 OFFICE NEXT WEEK. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29285 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ARKANSAS NUCLEAR REGION: 4 |NOTIFICATION DATE: 09/02/95 | |UNIT: [1] [ ] [ ] STATE: AR |NOTIFICATION TIME: 14:14 [ET]| |RX TYPE: [1] B&W-L-LP,[2] CE |EVENT DATE: 09/02/95 | +------------------------------------------------+EVENT TIME: 12:25[CDT]| |NRC NOTIFIED BY: DAVID THOMPSON |LAST UPDATE DATE: 09/02/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PHIL HARRELL 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 +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATIONS OF FUEL OIL IN THE DISCHARGE CANAL. (REFER TO EVENT | | NUMBER 29281.) | | | | AT 12:25 CDT, THE LICENSEE IDENTIFIED A SMALL OIL LEAK INTO THE DISCHARGE | | CANAL THAT WAS THOUGHT TO BE ISOLATED LAST NIGHT. THE LICENSEE IS | | CURRENTLY TRYING TO IDENTIFY THE SOURCE OF THE LEAK SO THAT IT CAN BE | | ISOLATED. A BOOM IS BEING USED TO CONTAIN THE OIL SO THAT IT DOES NOT | | REACH THE LAKE DOWNSTREAM. | | | | AS A RESULT, THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR, THE ARKANSAS | | DEPARTMENT OF HEALTH, THE STATE DEPARTMENT OF POLLUTION CONTROL AND | | ECOLOGY, THE ARMY CORPS OF ENGINEERS, AND THE U.S. COAST GUARD NATIONAL | | RESPONSE CENTER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29286 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 09/02/95 | |UNIT: [ ] [2] [ ] STATE: NY |NOTIFICATION TIME: 14:17 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 09/02/95 | +------------------------------------------------+EVENT TIME: 10:13[EDT]| |NRC NOTIFIED BY: ROY GREEN |LAST UPDATE DATE: 09/02/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOHAMED SHANBAKY 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A WOODEN PEG WAS FOUND TO BE LODGED IN THE SUCTION PIPE FOR THE DIVISION 1 | | HYDROGEN/OXYGEN RECOMBINER. | | | | AT 21:30 ON AUGUST 28, 1995, THE DIVISION 1 HYDROGEN/OXYGEN RECOMBINER WAS | | DECLARED INOPERABLE DUE TO A FAILED SURVEILLANCE TEST WHEN THE RECOMBINER | | WAS UNABLE TO ACHIEVE THE REQUIRED FLOW. AT 10:13 ON SEPTEMBER 2, 1995, | | THE INVESTIGATION OF THIS FAILURE IDENTIFIED A WOODEN PLUG THAT WAS LODGED | | IN THE SUCTION PIPE FROM THE SUPPRESSION CHAMBER. THIS IS A 3-INCH | | DIAMETER LINE. THE PLUG APPEARED TO HAVE BEEN LEFT IN THE PIPE FROM | | INITIAL CONSTRUCTION AND APPEARED TO HAVE RECENTLY MIGRATED TO A POSITION | | WITHIN THE PIPE TO OBSTRUCT SYSTEM FLOW. ALL PREVIOUS SURVEILLANCE TESTS | | HAD BEEN COMPLETED SATISFACTORILY. | | | | THE LICENSEE CUT OUT THE AFFECTED PORTION OF PIPING, REMOVED THE PLYWOOD | | PLUG, AND IS IN THE PROCESS OF WELDING A PIPE BACK IN. THE RECOMBINER WAS | | NOT DAMAGED. THE UNIT IS NOT IN ANY TECHNICAL SPECIFICATION LIMITING | | CONDITIONS FOR OPERATION BECAUSE IT IS CURRENTLY IN MODE 4. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29287 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 09/02/95 | |UNIT: [ ] [2] [ ] STATE: GA |NOTIFICATION TIME: 16:59 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 09/02/95 | +------------------------------------------------+EVENT TIME: 15:14[CDT]| |NRC NOTIFIED BY: EDWEN URQUHART |LAST UPDATE DATE: 09/02/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GEORGE AL BELISLE RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | M/R Y 33 POWER OPERATION | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR SCRAM AND TURBINE TRIP DUE TO DECREASING CONDENSER VACUUM. | | | | AT 12:20 EDT, THE LICENSEE OBSERVED VACUUM ON THE 'A' CONDENSER SLOWLY | | DECREASING AND COMMENCED A POWER REDUCTION FROM 64%. DUE TO THE CONTINUED | | DECREASE IN CONDENSER VACUUM, THE LICENSEE INITIATED BOTH A MANUAL REACTOR | | SCRAM FROM 33% POWER AND A MANUAL TURBINE TRIP AT 15:14 EDT. MAIN | | CONDENSER VACUUM INDICATIONS RETURNED TO NORMAL WHEN THE MAIN TURBINE WAS | | TRIPPED, AND REACTOR VESSEL WATER LEVEL WAS MAINTAINED WITH USE OF THE | | REACTOR FEEDWATER PUMP TURBINES. THE LOWEST WATER LEVEL WAS +8 INCHES. ALL | | RODS FULLY INSERTED, AND ALL SYSTEMS FUNCTIONED AS REQUIRED. | | | | THE UNIT IS CURRENTLY STABLE IN HOT SHUTDOWN, AND REACTOR VESSEL LEVEL AND | | PRESSURE CONTROL ARE BEING MAINTAINED BY THE USE OF NORMAL MAKEUP (REACTOR | | FEEDWATER PUMP TURBINES), THE MAIN TURBINE, AND THE STEAM SEALS. THE HEAT | | SINK IS STILL THE MAIN CONDENSER. THE LICENSEE IS CURRENTLY INVESTIGATING | | THE CAUSE OF THE LOSS OF CONDENSER VACUUM. | | | | THE LICENSEE HAS NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29288 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 09/02/95 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 18:23 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 09/02/95 | +------------------------------------------------+EVENT TIME: 17:35[EDT]| |NRC NOTIFIED BY: RUSS KEARNEY |LAST UPDATE DATE: 09/02/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PATRICK HILAND RDO | |ACCS 50.72(b)(1)(iv) ECCS INJECTION | | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A/R Y 15 STARTUP | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC REACTOR SCRAM ON LOW REACTOR VESSEL WATER LEVEL. | | | | DURING ACTIVITIES INVOLVED IN A REACTOR RESTART AND POWER INCREASE, A FULL | | SCRAM SIGNAL WAS GENERATED BY A LOW REACTOR WATER LEVEL. THIS ACTUATION | | OCCURRED AT 178 INCHES (LEVEL 3) BY NARROW RANGE INSTRUMENTS. ALL RODS | | FULLY INSERTED, AND ALL SYSTEMS FUNCTIONED AS REQUIRED. THE MAIN TURBINE | | AUTOMATICALLY TRIPPED ON REVERSE POWER AFTER THE SCRAM AS DESIGNED. | | | | AT THE TIME OF THE EVENT, THE MOTOR-DRIVEN FEEDWATER PUMP WAS IN SERVICE, | | AND THE FEEDWATER CONTROLLER WAS IN AUTOMATIC ON THE STARTUP LEVEL | | CONTROLLER. PREPARATIONS WERE ALSO IN PROCESS TO START THE 'A' REACTOR | | FEEDWATER PUMP TURBINE WHICH WAS RUNNING AT 1,100 RPM. FOR REASONS UNKNOWN | | AT THIS TIME, REACTOR WATER LEVEL DECREASED TO A LEVEL ABOVE LEVEL 2 WHICH | | IS SET FOR 130 INCHES. | | | | FOLLOWING THE REACTOR SCRAM, REACTOR PRESSURE VESSEL LEVEL WAS RETURNED TO | | NORMAL VIA OPERATOR ACTION WHEN THE HIGH PRESSURE CORE SPRAY PUMP WAS | | MANUALLY STARTED BY OPERATION OF THE PUMP CONTROL SWITCH (NOT THROUGH THE | | MANUAL ECCS INITIATION METHOD). DUE TO THESE ACTIONS, REACTOR VESSEL LEVEL | | DID NOT REACH A LEVEL WHERE AUTOMATIC ACTIONS WOULD HAVE OCCURRED. | | THEREFORE, THERE WERE NO CONTAINMENT ISOLATION SIGNALS, NO REACTOR | | RECIRCULATION PUMP TRIPS, NO DIVISION 3 AUTOMATIC START SIGNALS, AND NO | | HIGH PRESSURE CORE SPRAY OR REACTOR CORE ISOLATION COOLING SYSTEM AUTOMATIC | | INITIATION SIGNALS. DUE TO THE MANUAL INITIATION OF HIGH PRESSURE CORE | | SPRAY, WATER LEVEL INCREASED TO LEVEL 8 AND CAUSED THE MOTOR-DRIVEN | | FEEDWATER PUMP TO AUTOMATICALLY TRIP DURING THE PLANT RECOVERY. THIS PUMP | | WAS SUBSEQUENTLY RESTARTED WHEN NEEDED. REACTOR WATER LEVEL WAS RETURNED | | TO NORMAL APPROXIMATELY 1-1/2 MINUTES FOLLOWING THE SCRAM. | | | | THE PLANT IS CURRENTLY STABLE IN MODE 3 AT APPROXIMATELY 500 PSI. REACTOR | | VESSEL LEVEL AND PRESSURE ARE BEING CONTROLLED BY THE USE OF THE | | MOTOR-DRIVEN FEEDWATER PUMP AND THE NORMAL STEAM BYPASS AND PRESSURE | | CONTROL SYSTEM WITH THE MAIN CONDENSER AVAILABLE. | | | | THE LICENSEE INVESTIGATION IS ONGOING. AT THIS TIME, IT APPEARS THAT THE | | DECREASE IN REACTOR VESSEL WATER LEVEL MAY HAVE BEEN DUE TO EITHER AN | | ELECTRONIC PROBLEM IN THE FEEDWATER CONTROL SYSTEM OR ASSOCIATED WITH THE | | ACTIVITIES INVOLVED WITH THE STARTUP OF THE 'A' REACTOR FEEDWATER PUMP | | TURBINE. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND PLANS TO ISSUE A PRESS | | RELEASE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29289 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ARKANSAS NUCLEAR REGION: 4 |NOTIFICATION DATE: 09/02/95 | |UNIT: [ ] [2] [ ] STATE: AR |NOTIFICATION TIME: 21:05 [ET]| |RX TYPE: [1] B&W-L-LP,[2] CE |EVENT DATE: 09/02/95 | +------------------------------------------------+EVENT TIME: 19:27[CDT]| |NRC NOTIFIED BY: MICHEAL AZAMI |LAST UPDATE DATE: 09/02/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PHIL HARRELL RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | A/R Y 10 STARTUP | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC REACTOR TRIP POSSIBLY DUE TO A CORE PROTECTION CALCULATOR TRIP. | | | | PRIOR TO THIS EVENT, THE REACTOR WAS AT 10% POWER, THE TURBINE WAS OFF | | LINE, AND ONE FEEDWATER PUMP WAS RUNNING TO FEED THE STEAM GENERATORS. FOR | | REASONS NOT KNOWN AT THIS TIME, AN AUTOMATIC REACTOR TRIP OCCURRED. ALL | | RODS FULLY INSERTED, AND ALL SYSTEMS FUNCTIONED AS REQUIRED. THERE WERE NO | | ENGINEERED SAFETY FEATURES ACTUATIONS. THE UNIT IS CURRENTLY STABLE IN HOT | | SHUTDOWN. THE LICENSEE IS USING NORMAL CHARGING AND LETDOWN FOR PRIMARY | | INVENTORY CONTROL, AND BOTH STEAM GENERATORS ARE AVAILABLE AS A HEAT SINK. | | | | THE LICENSEE CURRENTLY BELIEVES THAT THE TRIP WAS CAUSED BY THE CORE | | PROTECTION CALCULATOR WHICH LOOKS AT THE AXIAL SHAPING INDEX. THERE ARE NO | | KNOWN FAILURES, AND THERE WERE NO MAINTENANCE ACTIVITIES OCCURRING AT THE | | TIME OF THE TRIP. | | | | THE LICENSEE NOTIFIED THE ARKANSAS DEPARTMENT OF HEALTH AND PLANS TO NOTIFY | | THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29290 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SURRY REGION: 2 |NOTIFICATION DATE: 09/05/95 | |UNIT: [ ] [2] [ ] STATE: VA |NOTIFICATION TIME: 02:53 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 09/05/95 | +------------------------------------------------+EVENT TIME: 02:02[EDT]| |NRC NOTIFIED BY: HARTKA |LAST UPDATE DATE: 09/05/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BELISLE RDO | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 2 SAFETY PARAMETER DISPLAY SYSTEM (SPDS) INOPERABLE. | | | | AT 0102, THE UNIT 2 SPDS BECAME INOPERABLE WHEN ONE OF EIGHT DATA LINKS TO | | THE MASTER RECEIVER FAILED. THE BACKUP MASTER RECEIVER HAD A PREVIOUSLY | | EXISTING HARDWARE FAILURE IN ONE OF ITS EIGHT DATA LINKS. THE SPDS WAS NOT | | RESTORED TO OPERABLE STATUS WITHIN ONE HOUR, CONSTITUTING A MAJOR LOSS OF | | EMERGENCY ASSESSMENT CAPABILITY. NO CONTROL ROOM ANNUNCIATORS OR | | INDICATION ARE AFFECTED BY THE FAILURE OF THE SPDS. | | | | THE LICENSEE STATED THAT THE CAUSE OF THE HARDWARE FAILURE IS CURRENTLY | | UNKNOWN, AND THEREFORE NO ESTIMATE OF REPAIR TIME IS AVAILABLE. THE UNIT 2 | | SPDS COULD BE PLACED INTO SERVICE USING ANOTHER BACKUP MASTER RECEIVER, BUT | | THIS WOULD RENDER THE UNIT 1 SPDS INOPERABLE. THE LICENSEE IS | | INVESTIGATING THE CAUSE OF THE FAILURE. THE NRC RESIDENT INSPECTOR WILL BE | | INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29291 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 09/05/95 | |UNIT: [1] [ ] [ ] STATE: LA |NOTIFICATION TIME: 03:54 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 09/05/95 | +------------------------------------------------+EVENT TIME: 00:30[CDT]| |NRC NOTIFIED BY: CARLSON |LAST UPDATE DATE: 09/05/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |HARRELL RDO | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | HIGH PRESSURE CORE SPRAY SYSTEM DECLARED INOPERABLE. | | | | THE HIGH PRESSURE CORE SPRAY (HPCS) SYSTEM WAS DECLARED INOPERABLE WHEN | | AUXILIARY BUILDING UNICOOLER NO. 5, WHICH SUPPLIES VENTILATION TO THE HPCS | | PUMP ROOM, FAILED CATASTROPHICALLY. THE LICENSEE REPORTED THAT THE FAN | | RIPPED LOOSE FROM ITS HOUSING AND FELL TO THE BOTTOM OF THE UNICOOLER. ALL | | OTHER ECCS EQUIPMENT IS CURRENTLY AVAILABLE. | | | | THE LICENSEE IS CURRENTLY ASSESSING THE EXTENT OF DAMAGE TO THE FAN AND | | UNICOOLER, AND NOTED THAT NEITHER A SPARE FAN NOR MOTOR IS NOT AVAILABLE | | ONSITE. THE INOPERABILITY OF THE HPCS SYSTEM PLACES THE UNIT IN A 14-DAY | | LIMITING CONDITION FOR OPERATION. THE NRC RESIDENT INSPECTOR HAS BEEN | | INFORMED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+