Event Notification Report for April 22, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
04/21/1999 - 04/22/1999
** EVENT NUMBERS **
35494 35611 35612 35613 35614 35615 35616 35617
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35494 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 03/20/1999|
| UNIT: [1] [] [] STATE: MA |NOTIFICATION TIME: 20:20[EST]|
| RXTYPE: [1] GE-3 |EVENT DATE: 03/20/1999|
+------------------------------------------------+EVENT TIME: 18:57[EST]|
| NRC NOTIFIED BY: ERIC OLSON |LAST UPDATE DATE: 04/21/1999|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JACK MCFADDEN R1 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
|NLCO TECH SPEC LCO A/S | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| RCIC INOPERABLE |
| |
| The licensee declared Reactor Core Isolation Cooling (RCIC) inoperable |
| because of a problem found during a surveillance. Relay 13A-k30 contacts 1 |
| - 7 were found to have a high resistance. These contacts close to provide |
| the 'A' channel input to the RCIC high level shutdown. A high resistance |
| across these contacts may prevent the actuating relay (13A-k38) from |
| energizing, and thereby prevent a shutdown of RCIC on a high reactor vessel |
| water level. The RCIC high water level shutdown requires both channels 'A' |
| and 'B' signals be present to occur. |
| |
| The licensee entered a 14 day LCO because of this condition. Repair |
| efforts are in progress. RCIC remains available for use in the event of an |
| emergency. |
| |
| The licensee will inform the NRC resident inspector. |
| |
| * * * UPDATE at 1903 on 04/21/99 by MIKE ENGLAND to JOLLIFFE * * * |
| |
| After further evaluation of this event, the licensee determined that the |
| as-found condition of the RCIC System did not affect its operability since |
| the last surveillance test. NUREG-1022, Rev 1, Section 3.2.2, Item 3, |
| discusses this instance. Therefore, the RCIC System was not inoperable due |
| to the above problem. Thus, the licensee desires to retract this report. |
| |
| The licensee notified the NRC Resident Inspector. The NRC Operations |
| Officer notified the R1DO MOHAMED SHANBAKY. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35611 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 04/20/1999|
| UNIT: [1] [] [] STATE: PA |NOTIFICATION TIME: 19:21[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 04/20/1999|
+------------------------------------------------+EVENT TIME: 18:32[EDT]|
| NRC NOTIFIED BY: RAY McKINLEY |LAST UPDATE DATE: 04/22/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MOHAMED SHANBAKY R1 |
|10 CFR SECTION: |CURT COWGILL R1 |
|ACCS 50.72(b)(1)(iv) ECCS INJECTION |R. BLOUGH/D. FLOREK R1 |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION |ART BURRITT SRI |
|AESF 50.72(b)(2)(ii) ESF ACTUATION |WILLIAM BATEMAN NRR |
| |CHARLES MILLER IRO |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 A/R Y 100 Power Operation |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - AUTO REACTOR SCRAM FROM 100% POWER DUE TO LOSS OF MAIN FEEDWATER; ECCS |
| INJECTION - |
| |
| AT 1832 ON 04/20/99, WITH UNIT 1 AT 100% POWER, ALL EIGHT CONDENSATE SYSTEM |
| DEEP BED DEMINERALIZER OUTLET MOTOR OPERATED VALVES FAILED CLOSED POSSIBLY |
| DUE TO A COMPUTER MALFUNCTION. THE DEMINERALIZER BYPASS VALVES TRIPPED DUE |
| TO THERMAL OVERLOADS AND FAILED TO OPEN, CAUSING ALL THREE STEAM DRIVEN MAIN |
| FEEDWATER PUMPS TO TRIP. THE REACTOR VESSEL WATER LEVEL DROPPED FROM A |
| NORMAL LEVEL OF +35 INCHES TO +12.5 INCHES, CAUSING THE REACTOR TO |
| AUTOMATICALLY SCRAM FROM 100% POWER DUE TO LOW REACTOR VESSEL WATER LEVEL. |
| ALL CONTROL RODS INSERTED COMPLETELY; HOWEVER, ROD #30-39 INSERTED SLOWLY. |
| NO SAFETY/RELIEF VALVES LIFTED. STEAM IS BEING DUMPED TO THE MAIN |
| CONDENSER. |
| |
| REACTOR VESSEL WATER LEVEL FURTHER DROPPED TO -38 INCHES, CAUSING THE HIGH |
| PRESSURE COOLANT INJECTION (HPCI) AND THE REACTOR CORE ISOLATION COOLING |
| (RCIC) SYSTEMS TO ACTUATE AND INJECT INTO THE REACTOR VESSEL. THE REDUNDANT |
| REACTIVITY CONTROL SYSTEM INITIATED TO TRIP THE CIRCUIT BREAKERS FOR THE |
| REACTOR RECIRCULATION PUMPS. PRIMARY CONTAINMENT ISOLATION SYSTEM GROUPS |
| 1B, 2A, 2B, 2C, 3, 6A, 6B, 6C, 7B, AND 8B ISOLATED. THE DIVISION 'A' |
| ATWS/RPT CIRCUIT BREAKER FOR THE 'A' RECIRC MOTOR GENERATOR SET FAILED TO |
| TRIP, AS REQUIRED. SMOKE WAS OBSERVED TO BE COMING FROM THE BREAKER. THE |
| BREAKER WAS MANUALLY TRIPPED FROM THE CONTROL ROOM AND THE SMOKING STOPPED. |
| THE 'A' AND 'B' RECIRC MOTOR GENERATOR SET DRIVE MOTOR CIRCUIT BREAKERS ALSO |
| FAILED TO TRIP ON THE 13 kV BUS FAST TRANSFER. THE BREAKERS WERE MANUALLY |
| TRIPPED. |
| |
| REACTOR VESSEL WATER LEVEL DROPPED TO A LOW LEVEL OF -75 INCHES ABOUT 40 |
| SECONDS INTO THE EVENT (TOP OF ACTIVE FUEL IS -161 INCHES). THE HPCI AND |
| RCIC SYSTEMS RECOVERED REACTOR VESSEL WATER LEVEL TO +25 INCHES, AT WHICH |
| TIME CONTROL ROOM OPERATORS MANUALLY SECURED THE HPCI SYSTEM. THE RCIC |
| SYSTEM IS MAINTAINING REACTOR VESSEL WATER LEVEL AT +25 INCHES WITH REACTOR |
| PRESSURE AT 875 PSIG AT AN INJECTION RATE OF 300 GPM. |
| |
| PLANT OPERATORS ENCOUNTERED A PROBLEM WITH THE AUXILIARY STEAM SYSTEM AND |
| THE MECHANICAL VACUUM PUMP. THEY MANUALLY CLOSED THE MAIN STEAM ISOLATION |
| VALVES. THEY ARE CONTROLLING REACTOR VESSEL WATER LEVEL WITH THE RCIC |
| SYSTEM AND REACTOR COOLANT SYSTEM PRESSURE WITH THE HPCI SYSTEM. |
| |
| UNIT 1 IS STABLE IN OPERATIONAL CONDITION 3 (HOT SHUTDOWN) AND COOLING DOWN |
| TO COLD SHUTDOWN. PRIMARY CONTAINMENT PARAMETERS ARE NORMAL. THERE WAS NO |
| RELEASE OF RADIOACTIVE MATERIAL. RELEASE RATES ARE NORMAL. THIS EVENT HAD |
| NO IMPACT ON UNIT 2 WHICH IS IN OPERATIONAL CONDITION 5 IN A REFUELING |
| OUTAGE. |
| |
| THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND IS INVESTIGATING THIS |
| EVENT. THEY PLAN TO ISSUE A PRESS RELEASE. |
| |
| *** UPDATE ON 4/21/99 @ 0418 BY HUNTER TO GOULD *** |
| |
| THE REACTOR IS IN OPCON 3 AT 350 PSIG CONTINUING TO COLD SHUTDOWN. |
| CONDENSER VACUUM IS BEING REESTABLISHED IN ORDER TO RE-OPEN THE MSIVs AND |
| SECURE HPCI FROM PRESSURE CONTROL MODE. FEEDWATER SYSTEM IS BEING |
| REPRESSURIZED TO REESTABLISH NORMAL FEED AND SECURE RCIC FROM LEVEL CONTROL |
| MODE. |
| |
| ALSO THE "1A" AND "1B" MG SET DRIVE MOTOR BREAKERS DID NOT TRIP DURING THE |
| TRANSIENT SINCE PLANT LOADS WERE PREVIOUSLY TRANSFERRED BY A REACTOR |
| OPERATOR PRIOR TO THE TURBINE TRIP. THE BREAKERS, THEREFORE, OPERATED AS |
| DESIGNED. |
| |
| THE RESIDENT INSPECTOR WAS NOTIFIED. |
| |
| THE REG 1 RDO(SHANBAKY) WAS NOTIFIED. |
| |
| *** UPDATE ON 4/22/99 @ 0220 BY HUNTER TO GOULD *** |
| |
| THE UNIT IS IN COLD SHUTDOWN AS OF 2214 ON 4/21/99. RESOLUTION OF |
| EQUIPMENT PROBLEMS WHICH RESULTED IN THE SHUTDOWN ARE IN PROGRESS. |
| ACTIVITIES ARE ALSO IN PROGRESS FOR PLANT STARTUP. |
| |
| ALL CONTROL RODS INCLUDING 30-39 WENT FULL IN WITHIN THE REQUIRED TECHNICAL |
| SPECIFICATION TIME. ROD 30-39 POSITION INDICATION WAS LOST FOR |
| APPROXIMATELY TWO MINUTES AFTER THE SCRAM, THEN THE "00" FULL IN POSITION |
| INDICATION BECAME AVAILABLE AND REMAINED AVAILABLE THROUGHOUT THE SHUTDOWN. |
| |
| THE RESIDENT INSPECTOR WILL BE INFORMED. THE REG 1 RDO(SHANBAKY) WAS |
| INFORMED. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 35612 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: MA DEPT OF PUBLIC HEALTH RCP |NOTIFICATION DATE: 04/21/1999|
|LICENSEE: AEA TECHNOLOGIES QSA, INC |NOTIFICATION TIME: 15:00[EDT]|
| CITY: BURLINGTON REGION: 1 |EVENT DATE: 04/21/1999|
| COUNTY: STATE: MA |EVENT TIME: 14:00[EDT]|
|LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 04/21/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |MOHAMED SHANBAKY R1 |
| |FREDERICK COMBS NMSS |
+------------------------------------------------+JOSEPH GIITTER IRO |
| NRC NOTIFIED BY: KEN TRAEGDE |DONNA MARIE PEREZ IP |
| HQ OPS OFFICER: DICK JOLLIFFE |LEN WERT R2 |
+------------------------------------------------+DALE POWERS R4 |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - SHIPMENT OF 8 Ir-192 SOURCES (866 CURIES TOTAL) FROM BURLINGTON, MA, |
| OVERDUE IN MEXICO - |
| |
| AT 1500 EDT ON 04/21/99, KEN TRAEGDE, MA DEPARTMENT OF PUBLIC HEALTH |
| RADIATION CONTROL PROGRAM (RCP), BOSTON, MA, REPORTED THAT ON 04/16/99, AEA |
| TECHNOLOGY QSA, INC, BURLINGTON, MA, SHIPPED A MODEL #855 SOURCE CHANGER |
| LOADED WITH EIGHT Ir-192 SOURCES (TOTALING 866 CURIES) VIA FEDERAL EXPRESS |
| TO VICONT SA DE CV, TALUCA, MEXICO. THE UNDAMAGED PACKAGE HAS A TRANSPORT |
| INDEX OF 1.4 (NORMAL READINGS OF 1.4 MR/HR AT ONE METER AND 55 MR/HR AT THE |
| SURFACE) AT THE TIME OF SHIPMENT. |
| |
| THE SHIPMENT WAS SCHEDULED TO ARRIVE IN MEXICO ON 04/17/99. AS OF 1400 EDT |
| ON 04/21/99, THE RECEIVER HAD RECEIVED THE SHIPPING PAPERS BUT NOT THE |
| CONTAINER. THE SHIPPER AND FEDERAL EXPRESS HAVE LAUNCHED A FULL SEARCH FOR |
| THE PACKAGE. THE FEDEX HAZARDS MATERIAL INVESTIGATION TEAM HAS CONDUCTED A |
| PHYSICAL SEARCH OF EXPRESS DEPOS IN BOSTON, MEMPHIS, LOS ANGELES, AND |
| MEXICO. |
| |
| LICENSE NUMBERS ARE: SU-1485, 12-8361, 52-0243, 54-0237, 58-0242. |
| |
| CONTACT THE NRC OPERATIONS OFFICER FOR TELEPHONE NUMBERS. |
| |
| THE NRC OPERATIONS OFFICER NOTIFIED THE DOT NATIONAL RESPONSE CENTER |
| (GAUTHIER), REPORT NUMBER 481132. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35613 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 04/21/1999|
| UNIT: [1] [2] [] STATE: TX |NOTIFICATION TIME: 18:03[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/21/1999|
+------------------------------------------------+EVENT TIME: 10:15[CDT]|
| NRC NOTIFIED BY: KLAY KLIMPLE |LAST UPDATE DATE: 04/21/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |DALE POWERS R4 |
|10 CFR SECTION: | |
|HFIT 26.73 FITNESS FOR DUTY | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - FITNESS FOR DUTY REPORT - |
| |
| AT 1015 CDT ON 04/21/99, A PLANT EMPLOYEE WAS DETERMINED TO BE UNDER THE |
| INFLUENCE OF ALCOHOL DURING A RANDOM TEST. THE EMPLOYEE'S ACCESS |
| AUTHORIZATION TO THE PLANT HAS BEEN TERMINATED. REFER TO THE HOO LOG FOR |
| ADDITIONAL DETAILS. |
| |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35614 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 04/21/1999|
| UNIT: [2] [] [] STATE: NY |NOTIFICATION TIME: 22:16[EDT]|
| RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 04/21/1999|
+------------------------------------------------+EVENT TIME: 21:17[EDT]|
| NRC NOTIFIED BY: PHIL SANTINI |LAST UPDATE DATE: 04/21/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MOHAMED SHANBAKY R1 |
|10 CFR SECTION: | |
|AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2 N Y 99 Power Operation |99 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - UNIT 2 OUTSIDE ITS PLANT DESIGN BASIS FOR 30 SECONDS DUE TO A FAILED |
| TRANSFER SWITCH - |
| |
| DURING A SURVEILLANCE TEST, DC CONTROL POWER TRANSFER SWITCH #EDD-2 FAILED |
| TO TRANSFER TO THE EMERGENCY POWER SUPPLY FOR 480-VOLT BUS 2A.. PLANT |
| OPERATORS RESTORED DC CONTROL POWER TO 480-VOLT BUS 2A FROM ITS NORMAL POWER |
| SUPPLY IN APPROXIMATELY 30 SECONDS. |
| |
| THIS LOSS OF DC CONTROL POWER TO 480-VOLT BUS 2A PLACED UNIT 2 OUTSIDE ITS |
| PLANT DESIGN BASIS FOR 30 SECONDS. |
| |
| THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35615 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GINNA REGION: 1 |NOTIFICATION DATE: 04/21/1999|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 22:30[EDT]|
| RXTYPE: [1] W-2-LP |EVENT DATE: 04/21/1999|
+------------------------------------------------+EVENT TIME: 20:00[EDT]|
| NRC NOTIFIED BY: DOUG PETERSON |LAST UPDATE DATE: 04/21/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MOHAMED SHANBAKY R1 |
|10 CFR SECTION: | |
|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 2 Startup |2 Startup |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - INADVERTENT TDAFW PUMP START DURING A MOVATS TEST - |
| |
| During the restoration of motor operated valve #MOV-3505A from Motor |
| Operated Valve Analysis and Test System (MOVATS) test #M-64.1.2, the turbine |
| driven auxiliary feedwater (TDAFW) pump inadvertently started. A system |
| engineer standing near the TDAFW pump called the control room and reported |
| that the pump was running. The control operator isolated the TDAFW system |
| discharge to the steam generators with the discharge air operated valves, |
| and the control room foreman directed the auxiliary operator to close the |
| manual isolation valve which secured the steam to the TDAFW pump. |
| |
| This resulted in a 2�F cooldown of the reactor coolant system (RCS) during |
| the approximate 1 minute run of the TDAFW pump. |
| |
| The licensee informed the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35616 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 04/21/1999|
| UNIT: [] [2] [] STATE: PA |NOTIFICATION TIME: 23:19[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 04/21/1999|
+------------------------------------------------+EVENT TIME: 20:25[EDT]|
| NRC NOTIFIED BY: CURT WOLTON |LAST UPDATE DATE: 04/22/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MOHAMED SHANBAKY R1 |
|10 CFR SECTION: | |
|AMED 50.72(b)(2)(v) OFFSITE MEDICAL | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N N 0 Refueling |0 Refueling |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - POTENTIALLY CONTAMINATED INDIVIDUAL TRANSPORTED TO OFFSITE MEDICAL |
| FACILITY - |
| |
| AT 2025 ON 04/21/99, A WORKER RECEIVED AN INJURY TO HIS HAND. THE INJURY |
| WAS SERIOUS ENOUGH THAT THE EMERGENCY MEDICAL TECHNICIAN AND HEALTH PHYSICS |
| TECHNICIAN DID NOT REMOVE THE WORKERS GLOVE BEFORE TRANSPORTING HIM TO THE |
| POTTSTOWN HOSPITAL FOR TREATMENT. THE HEALTH PHYSICS TECHNICIAN |
| SUBSEQUENTLY DETERMINED THAT THE INDIVIDUAL WAS NOT CONTAMINATED. |
| |
| THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35617 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 04/22/1999|
| UNIT: [1] [] [] STATE: MN |NOTIFICATION TIME: 03:00[EDT]|
| RXTYPE: [1] GE-3 |EVENT DATE: 04/22/1999|
+------------------------------------------------+EVENT TIME: 01:31[CDT]|
| NRC NOTIFIED BY: PFEFFER |LAST UPDATE DATE: 04/22/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MELVYN LEACH R3 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 A/R Y 100 Power Operation |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| THE PLANT HAD A REACTOR SCRAM ON LOW REACTOR WATER LEVEL. |
| |
| THE PLANT HAD A REACTOR SCRAM FROM 100% POWER DUE TO A LOW REACTOR WATER |
| LEVEL. CAUSE OF THE LOW REACTOR WASTER LEVEL IS UNKNOWN AND BEING |
| INVESTIGATED. ALL RODS FULLY INSERTED, NO ECCS INJECTION OCCURRED, AND NO |
| SAFETY RELIEF VALVES LIFTED. PLANT DID HAVE GROUP 2 AND GROUP 3 ISOLATIONS. |
| THE GROUP 3 ISOLATION HAS BEEN RESET, AND PRESENTLY THEY ARE IN PROGRESS |
| OF RESETTING THE GROUP 2 ISOLATION. THE MAIN CONDENSER IS THE HEAT SINK. |
| |
| THE RESIDENT INSPECTOR WILL BE INFORMED. |
+------------------------------------------------------------------------------+
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