Event Notification Report for April 23, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
04/22/1999 - 04/23/1999
** EVENT NUMBERS **
35600 35611 35612 35617 35618 35619 35620 35621 35622
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35600 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 04/17/1999|
| UNIT: [] [] [3] STATE: IL |NOTIFICATION TIME: 11:58[EDT]|
| RXTYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 04/17/1999|
+------------------------------------------------+EVENT TIME: 09:59[CDT]|
| NRC NOTIFIED BY: DAVE SLAGER |LAST UPDATE DATE: 04/23/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN JACOBSON R3 |
|10 CFR SECTION: | |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
| | |
|3 N Y 99 Power Operation |99 Power Operation |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| FAILURE OF A PRIMARY CONTAINMENT AIR SAMPLE RETURN ISOLATION VALVE TO MEET |
| MAXIMUM INSERVICE TEST STROKE-TIME REQUIREMENTS |
| |
| While performing quarterly valve stroke-time testing on Unit 3, a primary |
| containment air sample return isolation valve exceeded its specified maximum |
| stroke-time limit. The sample return line was isolated in accordance with |
| Technical Specification 3.7.D for primary containment isolation valves, and |
| this action satisfied the 4-hour limiting condition for operation action |
| statement requirements. The second in-line primary containment isolation |
| system valve remains operable. |
| |
| The licensee stated that no other valves failed to meet the maximum |
| stroke-time limits. The licensee also stated that, during a test that was |
| performed last month, the valve in question was identified as being in the |
| 'Alert' time range for inservice test timing requirements and that it was |
| being tested per the required increased testing frequency. Corrective |
| actions are being initiated, and troubleshooting activities are in |
| progress. |
| |
| The licensee plans to notify the NRC resident inspector. |
| |
| *** UPDATE ON 4/23/99 @ 0443 BY GADBOIS TO GOULD *** RETRACTION |
| |
| UPON FURTHER REVIEW, IT WAS DETERMINED THAT THIS EVENT DID NOT CONSTITUTE A |
| REPORTABLE CONDITION SINCE THE PENETRATION HAD A OPERABLE REDUNDANT VALVE |
| WHICH COULD HAVE ISOLATED THE CONTAINMENT PENETRATION. THEREFORE, THEY ARE |
| RETRACTING THIS EVENT. |
| |
| THE RESIDENT INSPECTOR WILL BE NOTIFIED. |
| |
| THE REG 3 RDO(LEACH) WAS NOTIFIED. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|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: 04/22/1999|
| 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 | |
|NOCM COMM ASST BRIEF | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
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 OF THE MA DEPARTMENT OF PUBLIC HEALTH |
| RADIATION CONTROL PROGRAM (RCP) LOCATED IN BOSTON, MA, REPORTED THAT ON |
| 04/16/99, AEA TECHNOLOGY QSA, INC., LOCATED IN BURLINGTON, MA, SHIPPED A |
| MODEL #855 SOURCE CHANGER LOADED WITH 8 Ir-192 SOURCES (TOTALING 866 CURIES) |
| VIA FEDERAL EXPRESS TO VICONT S.A. DE C.V. LOCATED IN TOLUCA, MEXICO. THE |
| UNDAMAGED PACKAGE HAD A TRANSPORT INDEX OF 1.4 (NORMAL READINGS OF 1.4 mR/HR |
| AT 1 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 RECIPIENT (VICONT S.A. DE C.V.) HAD RECEIVED THE SHIPPING |
| PAPERS BUT NOT THE CONTAINER. THE SHIPPER AND FEDERAL EXPRESS HAVE LAUNCHED |
| A FULL SEARCH FOR THE PACKAGE. THE FEDERAL EXPRESS HAZARDS MATERIAL |
| INVESTIGATION TEAM HAS CONDUCTED A PHYSICAL SEARCH OF EXPRESS DEPOTS IN |
| BOSTON, MEMPHIS, LOS ANGELES, AND MEXICO. |
| |
| THE LICENSE NUMBERS ARE: SU-1485, 12-8361, 52-0243, 54-0237, AND 58-0242. |
| |
| CONTACT THE NRC OPERATIONS OFFICER FOR APPLICABLE TELEPHONE NUMBERS. |
| |
| THE NRC OPERATIONS OFFICER NOTIFIED THE DOT NATIONAL RESPONSE CENTER |
| (GAUTHIER); REPORT NUMBER 481132. |
| |
| *********************************** UPDATE AT 1345 ON 04/22/99 BY JONES |
| *********************************** |
| |
| The NRC entered the Monitoring Phase of Normal Mode at 1345 on 04/22/99. |
| The NRC operations officer notified, the R1DO (Shanbaky), Region 1 (Miller), |
| IRO (Congel and Giitter), NMSS (Paperiello), RCT (Weinstein), PAO (Gagner), |
| EDO's office (name unknown), and Chairman's office (Holian). The RCT |
| notified FEMA (Dan Rishe), DOE (Thomas Yates), EPA (Ms. Reddy), USDA (Bob |
| Conley), HHS/CDC (James Raab), and DOT (Rick Boyle). |
| |
| |
| |
| *********************************** UPDATE AT 1600 ON 04/22/99 BY JONES |
| *********************************** |
| |
| A Commissioner's Assistants Briefing was conducted at 1600 on 04/22/99. The |
| following notifications were made (* office did not participate): IRO (Joe |
| Giitter, Erick Weinstein), Chairman Jackson (Dan Gillen), Commissioner Dicus |
| (Joel Lubenau), Commissioner Diaz (Patrick Castleman), Commissioner |
| McGaffigan (Janet Schlueter), Commissioner Merrifield (JohnThoma), EDO (*), |
| DEDE (*), NMSS (Don Cool, Carl Paperiello), NMSS EO (Fred Combs), R1DO |
| (Mohamed Shanbaky), PAO (Joe Gilland), CAO (Thomas Madden), SECY (Andrew |
| Bates), SP (Paul Lohaus), IP (Ron Hauber), R1 (Felicia Hinson, Jim Wiggins, |
| etc), and R2 (Doug Collins, Chuck Hosey, Rich Woodruff). The briefer was |
| Fred Combs of NMSS. |
| |
| 1610 Played back tape of briefing for EDO (Dan Martin) and DEDE (Jocelyn |
| Mitchell). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|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. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35618 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 04/22/1999|
| UNIT: [1] [] [] STATE: MN |NOTIFICATION TIME: 06:32[EDT]|
| RXTYPE: [1] GE-3 |EVENT DATE: 04/22/1999|
+------------------------------------------------+EVENT TIME: 01:45[CDT]|
| NRC NOTIFIED BY: WELLER |LAST UPDATE DATE: 04/22/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MELVYN LEACH R3 |
|10 CFR SECTION: | |
|AINB 50.72(b)(2)(iii)(B) POT RHR INOP | |
|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 N 0 Hot Shutdown |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| THE LICENSEE DECLARED HPCI INOPERABLE AND ENTERED AN LCO ACTION STATEMENT. |
| |
| THE HPCI SYSTEM WAS DECLARED INOPERABLE FROM 0145 TO 0236 DUE TO MOISTURE IN |
| THE TURBINE STEAM INLET LINE. A HPCI TURBINE INLET HIGH DRAIN POT LEVEL |
| ANNUNCIATION WAS RECEIVED AT 0145. RCIC WAS VERIFIED OPERABLE. THE |
| STEAMLINE MANUAL DRAIN VALVE WAS OPENED AND THE DRAIN LINE ANNUNCIATOR |
| CLEARED AT 0236. HPCI WAS DECLARED OPERABLE AND PLACED IN STANDBY. |
| |
| THE RESIDENT INSPECTOR WAS NOTIFIED. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35619 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CALVERT CLIFFS REGION: 1 |NOTIFICATION DATE: 04/22/1999|
| UNIT: [1] [2] [] STATE: MD |NOTIFICATION TIME: 14:36[EDT]|
| RXTYPE: [1] CE,[2] CE |EVENT DATE: 04/21/1999|
+------------------------------------------------+EVENT TIME: [EDT]|
| NRC NOTIFIED BY: BRUCE MONTGOMERY |LAST UPDATE DATE: 04/22/1999|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MOHAMED SHANBAKY R1 |
|10 CFR SECTION: | |
|NINF INFORMATION ONLY | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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 N 0 Refueling |0 Refueling |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - VOLUNTARY FITNESS-FOR-DUTY REPORT - |
| |
| A licensed operator was determined to be just below the limit by random |
| test. The employee's access to the plant was terminated. Refer to the HOO |
| Log for additional details. |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Other Nuclear Material |Event Number: 35620 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: U.S. ARMY (ACALA) |NOTIFICATION DATE: 04/22/1999|
|LICENSEE: U.S. ARMY (ACALA) |NOTIFICATION TIME: 17:22[EDT]|
| CITY: ROCK ISLAND REGION: 3 |EVENT DATE: 04/22/1999|
| COUNTY: STATE: IL |EVENT TIME: [CDT]|
|LICENSE#: 12-00722-06 AGREEMENT: Y |LAST UPDATE DATE: 04/22/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |MOHAMED SHANBAKY R1 |
| |MELVYN LEACH R3 |
+------------------------------------------------+FREDERICK COMBS NMSS |
| NRC NOTIFIED BY: GAVIN ZIGLER | |
| HQ OPS OFFICER: FANGIE JONES | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|IBAC 30.50(b)(1)(i) ACCESS DENIED >24 HRS | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| DAMAGED VIAL CONTAINING 0.8 CURIES OF TRITIUM |
| |
| During repair activities at Fort Drum, New York, in the arms room, an M224 |
| range indicator was apparently damaged. The illuminator was checked working |
| prior to the maintenance and noted not to be working later. The contained |
| vial of tritium, 0.8 Ci, used in the illuminator is assumed to be broken. |
| The device has been double bagged and the area secured until the results of |
| surveys are obtained. Survey results were sent off site as lab facilities |
| are not available on site. Investigation of the event is ongoing, and no |
| further information is available at this time. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35621 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 04/22/1999|
| UNIT: [3] [] [] STATE: FL |NOTIFICATION TIME: 19:02[EDT]|
| RXTYPE: [3] B&W-L-LP |EVENT DATE: 04/22/1999|
+------------------------------------------------+EVENT TIME: 18:08[EDT]|
| NRC NOTIFIED BY: BILL BANDHAUGER |LAST UPDATE DATE: 04/22/1999|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |LEN WERT R2 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| POSSIBLE OVERLOAD OF ESF TRANSFORMER IN AN ABNORMAL OPERATING PROCEDURE |
| FOUND |
| |
| While investigating a previous LER concerned with backfeed the following was |
| discovered: |
| |
| "During a scenario involving a Loss of Off-Site Power resulting from a loss |
| of the BEST and Startup transformers, the Crystal River Unit 3 abnormal |
| operating procedures could have caused an overload of the safety-related |
| Engineered Safeguards 4160V to 480V transformer. Assuming a single failure |
| of the 'B' side diesel generator, power could have been unavailable to both |
| trains of 480V Engineered safeguards loads. |
| |
| "This condition is considered reportable per 10 CFR 50.72(b)(l)(ii)(B) and |
| 10 CFR 50.73(a)(2)(ii)(B) as a condition outside of the design basis of the |
| plant. |
| |
| "Loads have been identified which can be administratively maintained off |
| during this scenario to avoid the overload condition, and therefore, the |
| transformer is operable." |
| |
| This is under investigation, and further actions will be forthcoming. |
| |
| The licensee intends to notify the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35622 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 04/23/1999|
| UNIT: [1] [] [] STATE: MN |NOTIFICATION TIME: 04:33[EDT]|
| RXTYPE: [1] GE-3 |EVENT DATE: 04/23/1999|
+------------------------------------------------+EVENT TIME: 02:14[CDT]|
| NRC NOTIFIED BY: WELLER |LAST UPDATE DATE: 04/23/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MELVYN LEACH R3 |
|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 N 0 Hot Shutdown |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| HPCI SYSTEM DECLARED INOPERABLE AND PLANT ENTERED LCO ACTION STATEMENT |
| |
| THE HPCI SYSTEM WAS DECLARED INOPERABLE FROM 0214 TO 0220 DUE TO MOISTURE IN |
| THE TURBINE STEAM INLET LINE. A 14-DAY LCO ACTION STATEMENT WAS ENTERED, |
| AND RCIC WAS VERIFIED OPERABLE. HPCI TURBINE INLET HIGH DRAIN POT LEVEL |
| ANNUNCIATION WAS RECEIVED DUE TO STROKING MO-2036 (TURBINE STEAM SUPPLY |
| VALVE) AS PART OF THE REACTOR SHUTDOWN PROCEDURE AT REACTOR PRESSURE OF 500 |
| PSIG. THE STEAM LINE MANUAL DRAIN VALVE WAS OPENED, AND THE ANNUNCIATOR |
| CLEARED AT 0220. HPCI DECLARED OPERABLE AND IN STANDBY. THE 14-DAY LCO |
| ACTION STATEMENT WAS ALSO EXITED AT 0220. |
| |
| THE RESIDENT INSPECTOR WILL BE NOTIFIED. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021