U.S. Nuclear Regulatory Commission Operations Center Event Reports For 11/21/97 - 11/24/97 ** EVENT NUMBERS ** 33255 33296 33297 33298 33299 33300 33301 33302 33303 33304 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33255 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 11/13/97 | |UNIT: [ ] [2] [ ] STATE: NY |NOTIFICATION TIME: 13:07 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 11/13/97 | +------------------------------------------------+EVENT TIME: 09:07[EST]| |NRC NOTIFIED BY: BRIAN WEAVER |LAST UPDATE DATE: 11/21/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JACK DURR 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 Y 82 POWER OPERATION | 82 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | RCIC SYSTEM INOPERABLE DUE TO CLOSED INSTRUMENT ROOT VALVE | | | | "DURING A PLANT WALKDOWN BY A MEMBER OF THE INDEPENDENT SAFETY ENGINEERING | | GROUP, THE INSTRUMENT ROOT VALVE FOR 2ICS*PT105 WAS FOUND SHUT. THIS | | PRESSURE TRANSMITTER, IN ADDITION TO PROVIDING REACTOR CORE ISOLATION | | COOLING (RCIC) SUCTION PRESSURE AND LOW SUCTION PRESSURE ANNUNCIATION, | | PROVIDES A RCIC TURBINE TRIP SIGNAL TO PREVENT DAMAGE TO THE TURBINE OR | | TURBINE PUMP DUE TO LOSS OF COOLING WATER. RCIC WAS INOPERABLE WITH THIS | | ROOT VALVE SHUT. | | | | THE INSTRUMENT ROOT VALVE WAS LAST OPERATED ON APRIL 22, 1997 DURING | | ROUTINE MAINTENANCE ON THE RCIC SYSTEM. INSTRUMENTATION ON THE SUCTION | | HEADER TO RCIC WAS VENTED AFTER THIS MAINTENANCE AND THE ROOT VALVE WAS NOT | | OPENED AS REQUIRED BY THE WORK ORDER. INVESTIGATION IS CONTINUING. | | | | THE ROOT VALVE FOR 2ICS*PT105 WAS OPENED AT 0907 THIS MORNING, 11/13/97, | | AND RCIC IS PRESENTLY OPERABLE." | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | | | | * * * UPDATE AT 1245 ON 11/21/97 BY M. CONWAY TAKEN BY FANGIE JONES * * * | | | | SUBSEQUENT ENGINEERING REVIEW INDICATES THAT EVEN WITH THE PRESSURE | | TRANSMITTER (2ICS*PT105) ISOLATED, THE RCIC SYSTEM WOULD HAVE MET ITS | | DESIGN REQUIREMENTS. THE PRESSURE TRANSMITTER PROVIDES ALARM AND TRIP | | SIGNALS FOR EQUIPMENT PROTECTIONS AND DOES NOT PERFORM ANY SAFETY RELATED | | FUNCTION. | | | | THE RCIC SYSTEM, WITH THE PRESSURE TRANSMITTER ISOLATED WOULD HAVE: | | 1. INITIATED AND OPERATED ON DEMAND AS PER DESIGN AS SYSTEM STARTUP | | CONTROLS WERE UNAFFECTED. | | 2. DELIVERED THE DESIGN FLOW TO THE REACTOR VESSEL AS FLOW CONTROL SIGNAL | | WAS UNAFFECTED. | | 3. CHANGED OVER THE WATER SUPPLY SOURCE FROM CONDENSATE STORAGE TANK TO | | SUPPRESSION POOL IN CASE OF LOW WATER LEVEL AS CONTROLS WERE UNAFFECTED. | | 4. CONTINUED TO DELIVER DESIGN FLOW TO THE REACTOR VESSEL AS PER DESIGN | | BECAUSE ALL INSTRUMENTS AND CONTROLS (OTHER THAN THE LOW SUCTION PRESSURE | | TRIP) WERE OPERATIONAL. | | | | THEREFORE NOTIFICATION OF THE EVENT IS BEING RETRACTED. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | THE HEADQUARTERS OPERATION NOTIFIED R1DO (JACK MCFADDEN) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33296 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 11/20/97 | |UNIT: [ ] [2] [ ] STATE: GA |NOTIFICATION TIME: 22:49 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 11/20/97 | +------------------------------------------------+EVENT TIME: 20:52[EST]| |NRC NOTIFIED BY: R. MUSGROVE |LAST UPDATE DATE: 11/21/97 | |HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JACK MCFADDEN RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | M/R Y 71 POWER OPERATION | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ESF ACTUATION FOLLOWING PLANNED SCRAM FOR SHUTDOWN. | | | | FOLLOWING A PREPLANNED SHUTDOWN FROM POWER, BY MANUAL SCRAM, DUE TO A | | PROBLEM WITH SUCTION PIPING ON THE 2A CONDENSATE BOOSTER PUMP, REACTOR | | WATER LEVEL DROPPED TO -45 INCHES RESULTING IN A GROUP 2 AND GROUP 5 | | PRIMARY CONTAINMENT ISOLATION. HIGH PRESSURE COOLANT INJECTION (HPCI) AND | | REACTOR CORE ISOLATION COOLING (RCIC) INITIATED, BUT THEY ARE NOT BELIEVED | | TO HAVE INJECTED. ALL CONTROL RODS FULLY INSERTED EXCEPT ROD 30-35, WHICH | | STOPPED AT THE 02 POSITION AND WAS DRIVEN TO FULL IN, THE 00 POSITION. | | REACTOR WATER LEVEL HAS BEEN RESTORED TO NORMAL. FURTHER INVESTIGATION IS | | BEING CONDUCTED. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | *** UPDATE BY MUSGROVE ON 11/21/97 @ 0042 EST TAKEN BY MACKINNON *** | | | | ON FURTHER REVIEW OF PLANT DATA IT WAS DETERMINED THAT NEITHER HPCI OR RCIC | | INJECTED INTO THE REACTOR VESSEL. R2DO (AL BELISLE) NOTIFIED. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | | THE REASON WHY THE LICENSEE SCRAMMED FROM 71% REACTOR POWER LEVEL: | | | | THE DISCHARGE CHECK VALVE ON CONDENSATE BOOSTER PUMP "2A" WAS LEAKING AND | | EARLIER IN THE DAY IT CAUSED THE PUMP TO ROTATE BACKWARDS WHEN THE LICENSEE | | WAS TRYING TO TAKE IT OUT OF SERVICE FOR MAINTENANCE. THE LICENSEE SHUT THE | | SUCTION VALVE OF THE CONDENSATE BOOSTER PUMP TO PREVENT THE PUMP FROM | | ROTATING BACKWARDS. WHEN THE SUCTION VALVE WAS CLOSED IT CAUSED THE SUCTION | | BELLOWS (FLEX JOINT ON THE SUCTION SIDE PIPING OF THE BOOSTER PUMP WHICH IS | | MADE OF VERY THIN METAL) TO EXPAND BECAUSE IT WAS OVERPRESSURIZED. THE | | LICENSEE'S EFFORTS TO PREVENT THE SUCTION BELLOWS FROM BEING | | OVERPRESSURIZED WAS UNSUCCESSFUL. AS REACTOR POWER/PRESSURE DECREASED THE | | CONDENSATE BOOSTER PUMP DISCHARGE PRESSURE INCREASED WHICH WAS SENSED BY | | THE SUCTION BELLOWS. THE SUCTION BELLOWS IS RATED AT 300 psig. THE LICENSEE | | HAD 440 psig ON THE BELLOWS AND AS REACTOR POWER DECREASED THE CONDENSATE | | BOOSTER PUMP PRESSURE CONTINUED TO INCREASE. WHEN THE SUCTION BELLOWS | | REACHED 475 psig THE LICENSEE'S AE SAID NOT TO FURTHER INCREASE THE | | PRESSURE ON THE SUCTION BELLOWS. THEREFORE THE LICENSEE MANUALLY SCRAMMED | | THE PLANT FROM 71% REACTOR POWER LEVEL INSTEAD OF NORMALLY GOING DOWN TO | | APPROXIMATELY 20% POWER AND THEN MANUALLY SCRAM THE PLANT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 33297 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 11/21/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 00:58 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 11/10/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 10:50[CST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 11/21/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |JOHN MADERA RDO | | DOCKET: 0707001 |JOE HOLONICH EO | +------------------------------------------------+ | |NRC NOTIFIED BY: RANDY BOSHELL | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HOLDING DRUMS TEMPERATURE NOT MAINTAINED ABOVE 105 DEGREES F (IF | | TEMPERATURE DROPS BELOW 105 F THE URANIUM HEXAFLUORIDE COULD HAVE | | SOLIDIFIED) BECAUSE THE NCSA DID NOT SPECIFY LOWER TEMPERATURE LIMIT. | | | | THIS EVENT WAS CALLED IN AS A 4 HOUR NOTIFICATION UNDER NRC BULLETIN 91-01. | | | | ON 11/10/97 A PROBLEM REPORT AND CRITICALITY SAFETY INCIDENT REPORT WERE | | ISSUED REPORTING THAT THE C-335 HOLDING DRUM TEMPERATURE WAS DISCOVERED TO | | BE 100 DEGREES F (ONLY 4 DRUMS INVOLVED AND THIS IS THE ONLY BUILDING WITH | | THESE TYPE OF HOLDING DRUMS). THIS INCIDENT REPORT STATED THAT THE | | CONDITIONS PRESENT IN THE DRUMS DID NOT ALLOW FOR URANIUM HEXAFLUORIDE TO | | SOLIDIFY, i.e. URANIUM HEXAFLUORIDE WAS BEING MAINTAINED IN A GASEOUS | | STATE, OR FOR THE HF TO CONDENSE (IF THE TEMPERATURE DROPS LOW ENOUGH AND | | THE PRESSURE INCREASES THE URANIUM HEXAFLUORIDE IN THE DRUM COULD SOLIDIFY | | AND IF MOISTURE LEAKED INTO THE DRUM WHICH CONTAINS GREATER THAN 1% WEIGHT | | PERCENT URANIUM-235 YOU COULD HAVE A POTENTIAL FOR A CRITICALITY. THE DRUMS | | ARE AIR TIGHT). THE INCIDENT REPORT FURTHER CONCLUDED THAT THIS WAS A LEVEL | | 4 INCIDENT (LEVELS USED IN PLANT ONLY AND LEVEL 4 IS THE LOWEST LEVEL FOR A | | CRITICALITY) DUE TO THE LOSS OF AN NUCLEAR CRITICALITY SAFETY APPROVAL | | (NCSA) REQUIREMENT THAT DOES NOT VIOLATE THE DOUBLE CONTINGENCY PRINCIPLE. | | GIVEN THIS, AN EVENT NOTIFICATION WAS NOT MADE TO THE NRC. | | | | ON 11/19/97, NCS PERSONNEL FILED A PROBLEM REPORT STATING THAT THE C-335 | | URANIUM HEXAFLUORIDE DRUMS CONTAIN FISSILE MATERIAL, POTENTIALLY GREATER | | THAN 1 WEIGHT PERCENT URANIUM-235, WITHOUT AN IMPLEMENTED NCSA. THE | | CURRENTLY IMPLEMENTED NCSA FOR THE URANIUM HEXAFLUORIDE/R-114 SEPARATION | | SYSTEM DOES NOT SPECIFY REQUIREMENTS FOR THE URANIUM HEXAFLUORIDE HOLDING | | DRUMS. | | | | RECENTLY APPROVED, BUT NOT YET IMPLEMENTED, NCSA 3971-05, REQUEST 1873, | | SPECIFIES THE CONTROLS NECESSARY TO MAINTAIN THE URANIUM HEXAFLUORIDE IN | | THE HOLDING DRUMS IN THE DESIRED GASEOUS STATE. THESE CONTROLS INCLUDE | | MAINTAINING THE TEMPERATURE OF THE DRUM ROOM AT OR ABOVE 105 DEGREES F, AND | | SHOULD THE TEMPERATURE DROP BELOW 105 DEGREES F THAT ACTION SHOULD BE TAKEN | | TO ENSURE THAT THE TEMPERATURE AND PRESSURE OF THE DRUMS IS MAINTAINING THE | | URANIUM HEXAFLUORIDE IN A GASEOUS STATE, THUS PRECLUDING A CRITICALITY | | CONCERN. | | | | SAFETY SIGNIFICANCE OF EVENT: | | | | AT THE TIME OF DISCOVERY, THE URANIUM HEXAFLUORIDE WAS IN A GASEOUS STATE | | AND, THEREFORE, DID NOT PRESENT A CRITICALITY CONCERN. ACTIONS WERE | | INITIATED TO RAISE THE TEMPERATURE AND THE TEMPERATURE WAS 142 DEGREES F AT | | 2050 CST ON 11/11/97. | | | | POTENTIAL CRITICALITY PATHWAYS INVOLVED OF HOW CRITICALITY COULD OCCUR: | | | | THE PRIMARY POTENTIAL PATHWAY IS THE LOSS OF TEMPERATURE AND PRESSURE | | CONTROLS TO ALLOW THE URANIUM HEXAFLUORIDE TO SOLIDIFY AND TO THEN BECOME | | MODERATED BY CONDENSATION OF HF OR BY WET AIR INLEAKAGE. | | | | CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC.): | | | | THE PRIMARY CONTROL IS MAINTAINING THE URANIUM HEXAFLUORIDE CONTAINED IN | | THE DRUMS IN A GASEOUS PHASE WHILE ALSO MAINTAINING MODERATION CONTROL | | THROUGH TEMPERATURE AND PRESSURE AND SYSTEM INTEGRITY. | | | | ESTIMATE AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL: | | | | ALTHOUGH NOT SAMPLED, DUE TO PAST OPERATIONS, THE POTENTIAL EXISTS FOR | | THESE DRUMS TO CONTAIN GREATER THAN 1 WEIGHT PERCENT URANIUM-235 ENRICHED | | MATERIAL IN THE GASEOUS URANIUM HEXAFLUORIDE FORM. | | | | NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION | | OF THE FAILURES OR DEFICIENCIES: | | | | THE NCSE/A FOR THE URANIUM HEXAFLUORIDE/R-114 SEPARATION SYSTEM DID NOT | | ESTABLISH CONTROLS FOR OPERATION OF THE HOLDING DRUMS ASSOCIATED WITH THE | | SYSTEM. THE PROCEDURES NECESSARY TO IMPLEMENT THE APPROVAL NCSA HAVE NOT | | BEEN COMPLETED AND APPROVED FOR USE. | | | | CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEM AND WHEN EACH WAS IMPLEMENTED: | | | | AN NCSA WAS APPROVED AND APPLICABLE PROCEDURES ARE BEING WRITTEN TO | | IMPLEMENT THIS NEW NCSA. THE HOLDING DRUM ROOM TEMPERATURE WAS RAISED TO | | 142 DEGREES F AT 2050 CST ON 11/11/97. A LONG TERM ORDER WAS ISSUED ON | | 11/19/97 TO MONITOR THE HOLDING DRUM ROOM TEMPERATURE ONCE PER SHIFT AND | | TAKE ACTION TO ENSURE THE URANIUM HEXAFLUORIDE IS MAINTAINED IN A GASEOUS | | STATE IF THE TEMPERATURE DROPS BELOW 105 DEGREES F. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED BY THE LICENSEE OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33298 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 11/21/97 | |UNIT: [ ] [2] [ ] STATE: TX |NOTIFICATION TIME: 06:22 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/21/97 | +------------------------------------------------+EVENT TIME: 02:13[CST]| |NRC NOTIFIED BY: ANDY DUNLAP |LAST UPDATE DATE: 11/21/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOE TAPIA 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 100 POWER OPERATION | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR MANUALLY TRIPPED DUE TO THE PRIMARY 120 VAC TO 24 VDC POWER SUPPLY | | IN THE CUBICLE DEENERGIZING (FOR UNKNOWN REASON) AND THE ALTERNATE CUBICLE | | POWER SUPPLY NOT PICKING UP AND SUPPLYING ELECTRICAL POWER. THIS CAUSED A | | LOSS OF ELECTRICAL POWER TO A PROCESS CABINET WHICH RESULTED IN STEAM | | GENERATOR "2D" FEEDWATER REGULATING VALVE (FRV) CLOSING. | | | | THE PRIMARY 120 VAC TO 24 VDC POWER SUPPLY TO PROCESS CABINET PANEL 8 | | CIRCUIT BREAKER OPENED FOR UNKNOWN REASON. THE ALTERNATE 120 VAC TO 24 VDC | | POWER SUPPLY TO PROCESS CABINET PANEL 8 DID NOT PICK UP AS EXPECTED. THE | | LOSS OF POWER TO THE PROCESS CABINET CAUSED A LOSS OF ELECTRICAL POWER TO | | STEAM GENERATOR "2D" FRV (WHICH FAILS CLOSED), LOSS OF POWER TO THE | | CHARGING PUMP FLOW CONTROL VALVES (FAIL OPEN), LOSS OF POWER TO THE LETDOWN | | PRESSURE CONTROL VALVE, LOSS PERMISSIVE SIGNAL TO THE STEAM DUMPS, LOSS OF | | POWER TO SEVERAL ANNUNCIATORS AND LOSS OF POWER TO SEVERAL ITEMS. THE LOSS | | OF CONTROL POWER TO THE STEAM GENERATOR "2D" FCV CAUSED THE VALVE TO CLOSE. | | THE REACTOR OPERATOR MANUALLY TRIPPED THE PLANT BECAUSE STEAM GENERATOR | | "2D" WATER LEVEL WAS DECREASING. ALL RODS FULLY INSERTED INTO THE CORE. | | TWO STEAM GENERATOR ATMOSPHERIC VALVES WERE OPENED TO CONTROL REACTOR | | COOLANT TEMPERATURE AT A Tave NO LOAD CONDITION OF 567 DEGREES F (VERY | | SMALL PRIMARY TO SECONDARY LEAKAGE RATE, NO RELEASE OF RADIOACTIVITY TO | | OFFSITE). AN EXPECTED FEEDWATER ISOLATION OCCURRED WITH LOW Tave IN | | COINCIDENCE WITH REACTOR TRIP. ALL THREE MOTOR DRIVEN AUXILIARY FEEDWATER | | PUMPS AND THE TURBINE AUXILIARY FEEDWATER PUMP AUTOMATICALLY STARTED ON | | STEAM GENERATOR LOW LOW WATER LEVEL. AUXILIARY FEEDWATER PUMPS WERE | | FEEDING THE STEAM GENERATORS FOR BETWEEN 1 HOUR AND 1.5 HOURS BEFORE THEY | | WERE SECURED (MAIN FEEDWATER WAS RESTORED TO SERVICE BEFORE AUXILIARY | | FEEDWATER WAS SECURED). STEAM DUMP BYPASS CONTROL SYSTEM WAS RESTORED TO | | SERVICE AFTER THE ALTERNATE 120 VAC TO 24 VDC POWER SUPPLY TO PROCESS | | CABINET PANEL 8 WAS PLACED IN SERVICE. | | | | INVESTIGATION AS TO WHY THE ALTERNATE 120 VAC TO 24 VDC POWER DID NOT | | AUTOMATICALLY SWITCH OVER HAS FOUND THAT ITS BREAKER WAS OPEN (LIGHT | | SWITCH). THE BREAKER SHOULD HAVE BEEN CLOSED. THE LICENSEE IS | | INVESTIGATING WHY THE BREAKER WAS OPEN. | | | | NRC RESIDENT INSPECTOR WAS NOTIFIED BY THE LICENSEE OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33299 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 11/21/97 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 06:42 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 11/21/97 | +------------------------------------------------+EVENT TIME: 04:45[CST]| |NRC NOTIFIED BY: DAVE GEEVER |LAST UPDATE DATE: 11/21/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN MADERA 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 +------------------------------------------------------------------------------+ | BOTH STANDBY LIQUID CONTROL PUMPS DECLARED INOPERABLE. | | | | ON NOVEMBER 20, 1997, AT 1100 HOURS, BOTH "A" AND "B" STANDBY LIQUID | | CONTROL PUMPS WERE DECLARED INOPERABLE TO UNIT TWO. THE PERFORMANCE OF QCOS | | 1100-07, QUARTERLY STANDBY LIQUID CONTROL PUMP FLOW RATE TEST, RESULTED IN | | BOTH STANDBY LIQUID CONTROL PUMPS IN THE REQUIRED ACTION RANGE FOR FLOW | | RATE. ALTHOUGH BOTH PUMPS MET THE TECH SPEC REQUIRED MINIMUM FLOW RATE OF | | 40 gpm, THE PUMPS ARE INOPERABLE PER THE IST PROGRAM. BECAUSE UNIT TWO IS | | CURRENTLY IN MODE 4, NO LOCs WERE ENTERED. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33300 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 11/21/97 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 16:21 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 11/21/97 | +------------------------------------------------+EVENT TIME: 13:31[CST]| |NRC NOTIFIED BY: DARYL NOHR |LAST UPDATE DATE: 11/21/97 | |HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN MADERA RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | LOSS OF THE B CHANNEL OF RPS LED TO A PARTIAL ISOLATION FROM ESF SIGNAL. | | | | THE 2AB-2 RESERVE FEED ELECTRICAL PROTECTION ASSEMBLY (EPA) TRIPPED ON | | UNDERVOLTAGE CAUSING A LOSS OF THE "B" CHANNEL OF REACTOR PROTECTION SYSTEM | | (RPS). ENGINEERED SAFETY FEATURES (ESF) ACTUATIONS WERE RECEIVED INCLUDING | | PARTIAL GROUP 2 AND 3 ISOLATIONS. WITH SHUTDOWN COOLING NOT INSERVICE, | | DECAY HEAT REMOVAL WAS BY THE REACTOR WATER CLEANUP SYSTEM, WHICH ISOLATED | | DUE TO THE PARTIAL GROUP 3 ISOLATION SIGNAL. AFTER INVESTIGATION, THE EPA | | WAS RESET AT 1431 CST AND THE "B" RPS WAS RESTORED. REACTOR WATER CLEANUP | | SYSTEM WAS RESTARTED AND SHUTDOWN COOLING BECAME AVAILABLE. THERE WILL BE | | CONTINUED INVESTIGATION INTO THE CAUSE OF THE UNDERVOLTAGE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33301 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 11/22/97 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 15:51 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 11/22/97 | +------------------------------------------------+EVENT TIME: 13:35[EST]| |NRC NOTIFIED BY: D. PRICE |LAST UPDATE DATE: 11/22/97 | |HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JACK MCFADDEN 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CHECK VALVES FAILURE WOULD PREVENT PERFORMANCE OF DESIGN SAFETY FUNCTION. | | | | ON 11/12/97 THE LICENSEE IDENTIFIED THE LACK OF LEAK RATE TESTING ON THE | | TWO CHECK VALVES SEPARATING THE CLASS 1E AND NONCLASS 1E PORTION OF THE | | INSTRUMENT AIR SYSTEM SUPPLYING THE REACTOR BUILDING TO TORUS VACUUM | | BREAKER ISOLATION VALVES. ON 11/21/97 THE LEAK RATE TEST WAS PERFORMED AND | | BOTH VALVES FAILED. ON 11/22/97 THE LICENSEE DETERMINED THAT THE EXCESSIVE | | CHECK VALVE LEAKAGE WOULD PREVENT THE REACTOR BUILDING TO TORUS VACUUM | | BREAKERS FROM BEING ABLE TO PERFORM THEIR DESIGNATED SAFETY FUNCTION UNDER | | CERTAIN CONDITIONS, THAT IS TO VENT THE REACTOR BUILDING TO THE TORUS. | | ALSO, INVESTIGATION IDENTIFIED THAT OPERATOR ACTION TO PLACE THE BACKUP | | PNEUMATIC SUPPLY IN SERVICE TO SUPPORT VACUUM BREAKER OPERATION (ASSUMED TO | | OCCUR WITHIN 2 HOURS OF AN INITIATING EVENT) HAD NOT BEEN PROCEDURALIZED. | | | | THIS IS BEING REPORTED AS A CONDITION THAT ALONE COULD HAVE PREVENTED THE | | FULFILLMENT OF A SAFETY FUNCTION THAT IS NEEDED TO MITIGATE THE | | CONSEQUENCES OF AN ACCIDENT. REPAIR OF THE CHECK VALVES IS IN PROGRESS AND | | PROCEDURAL REVISIONS TO INCORPORATE ACTIONS TO INITIATE THE BACKUP | | PNEUMATIC SUPPLY ARE PLANNED. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR AND LOCAL AUTHORITIES. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33302 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GRAND GULF REGION: 4 |NOTIFICATION DATE: 11/22/97 | |UNIT: [1] [ ] [ ] STATE: MS |NOTIFICATION TIME: 22:04 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 11/22/97 | +------------------------------------------------+EVENT TIME: 20:00[CST]| |NRC NOTIFIED BY: T. McINTYRE |LAST UPDATE DATE: 11/22/97 | |HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOSEPH TAPIA 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 +------------------------------------------------------------------------------+ | A PORTION OF THE CIVIL DEFENSE SIRENS ACTIVATED. | | | | AT 2000 ON 11/22/97, CIVIL DEFENSE SIRENS ACTIVATED ALONG STATE HIGHWAY 547 | | FOR AN UNKNOWN REASON. CLAIBORNE COUNTY RESPONDED AND TURNED THEM OFF. THE | | ACTIVATION IS BEING INVESTIGATED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AND LOCAL AUTHORITIES. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33303 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 11/23/97 | |UNIT: [1] [ ] [ ] STATE: MA |NOTIFICATION TIME: 04:33 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 11/23/97 | +------------------------------------------------+EVENT TIME: 04:01[EST]| |NRC NOTIFIED BY: TOM TREPANIER |LAST UPDATE DATE: 11/23/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JACK MCFADDEN 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 50 POWER OPERATION | 50 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PLANT SHUTDOWN DUE TO MSIV CLOSURE ANOMALIES | | | | WHILE PERFORMING A SURVEILLANCE TEST OF THE MAIN STEAM ISOLATION VALVES, | | THE LICENSEE IDENTIFIED CLOSURE ANOMALIES WITH TWO OF THE VALVES. THE | | LICENSEE REPORTED THAT ALL VALVES FUNCTIONED PROPERLY WHEN CLOSED UNDER | | SPRING PLUS PNEUMATIC PRESSURE; HOWEVER, TWO VALVES DID NOT APPEAR TO CLOSE | | PROPERLY UNDER SPRING PRESSURE ALONE. ONE INBOARD MSIV APPEARS TO HAVE A | | LIMIT SWITCH PROBLEM, WHILE ONE OUTBOARD MSIV FAILED TO COMPLETE ITS LAST | | 3/4" OF STROKE. | | | | THE FINAL SAFETY EVALUATION REPORT (FSAR) TAKES CREDIT FOR THE VALVES | | CLOSING USING EITHER SPRING OF PNEUMATIC FORCE. THEREFORE, THE LICENSEE HAS | | DECIDED TO SHUT DOWN THE UNIT TO REPAIR THE MSIVs. THE NRC RESIDENT | | INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33304 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 11/23/97 | |UNIT: [ ] [2] [ ] STATE: MI |NOTIFICATION TIME: 18:29 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/23/97 | +------------------------------------------------+EVENT TIME: 16:05[EST]| |NRC NOTIFIED BY: S. CZUK |LAST UPDATE DATE: 11/23/97 | |HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN MADERA RDO | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | |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 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | VIOLATION OF CONTAINMENT INTEGRITY DURING REFUELING | | | | AN APPARENT VIOLATION OF CONTAINMENT INTEGRITY OCCURRED AT APPROXIMATELY | | 1400 (THE EXACT TIME IS UNKNOWN). AT 1605, IT WAS DISCOVERED THAT WORK WAS | | BEING PERFORMED TO REMOVE THE SPOOL PIECE USED FOR ADDING ICE TO THE ICE | | CONDENSERS IN CONTAINMENT. IT IS REMOVED AND TWO BLANK FLANGES HAVE BEEN | | INSTALLED TO REESTABLISH CONTAINMENT INTEGRITY. ICE ADDITION HAD BEEN | | COMPLETED FOR THE PRESENT REFUELING OUTAGE AND THE PENETRATIONS WERE BEING | | ALIGNED FOR THEIR AT-POWER CONFIGURATION. | | | | REFUELING OPERATIONS WERE IMMEDIATELY STOPPED AND CONTAINMENT PENETRATION | | ALIGNMENT WAS VERIFIED. REFUELING RESUMED AT 1640. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+