Event Notification Report for April 30, 2001
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 04/27/2001 - 04/30/2001 ** EVENT NUMBERS ** 37948 37949 37950 37951 37952 37953 +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 37948 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 04/27/2001| | UNIT: [] [] [3] STATE: IL |NOTIFICATION TIME: 17:13[EDT]| | RXTYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 04/27/2001| +------------------------------------------------+EVENT TIME: 14:51[CDT]| | NRC NOTIFIED BY: MIKE MCDONALD |LAST UPDATE DATE: 04/27/2001| | HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |THOMAS KOZAK R3 | |10 CFR SECTION: | | |*RPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | |3 A/R Y 100 Power Operation |0 Hot Shutdown | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR SCRAM | | | | UNIT 3 scrammed on low reactor water level (+8") due to flow and power | | oscillations from 3B reactor recirculation pump. The 3B recirculation | | motor generator set could not be tripped from the main control room and was | | tripped locally. All rods fully inserted during the scram. The unit is | | currently stable in mode 3. There were no ECCS injections nor did any SRVs | | lift. | | | | The licensee notified the NRC resident inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Other Nuclear Material |Event Number: 37949 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: MONTANA DEPT OF TRANSPORTATION |NOTIFICATION DATE: 04/27/2001| |LICENSEE: MONTANA DEPT OF TRANSPORTATION |NOTIFICATION TIME: 22:50[EDT]| | CITY: PLENTYWOOD REGION: 4 |EVENT DATE: 04/27/2001| | COUNTY: STATE: MT |EVENT TIME: 12:00[MDT]| |LICENSE#: 25-11498-01 AGREEMENT: N |LAST UPDATE DATE: 04/27/2001| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |BILL JONES R4 | | |E. WILLIAM BRACH NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: REX HOY | | | HQ OPS OFFICER: DOUG WEAVER | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DAMAGED TROXLER GAUGE | | | | A Troxler moisture/density gauge model 3440 was run over on a construction | | site. The gauge contains 8 mCi of Cs-137 and 40 mCi of Am-241. The serial | | number of the gauge is 20993. The gauge was not seriously damaged. The | | gauge was surveyed for contaminated and none was found. The gauge has been | | removed from the job site and placed in storage pending further action. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 37950 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 04/28/2001| | UNIT: [] [2] [] STATE: SC |NOTIFICATION TIME: 21:10[EDT]| | RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-L|EVENT DATE: 04/28/2001| +------------------------------------------------+EVENT TIME: 16:00[EDT]| | NRC NOTIFIED BY: JAMES WEAST |LAST UPDATE DATE: 04/28/2001| | HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |PAUL FREDRICKSON R2 | |10 CFR SECTION: | | |*UNA 50.72(b)(3)(ii)(B) UNANALYZED COND OP | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | UNANALYZED CONDITION - BORON RESIDUE ON REACTOR VESSEL HEAD PENETRATIONS | | | | Preliminary reactor head visual inspection indicates a small amount of boron | | residue surrounding four control rod drive mechanism head penetrations. | | These indications are similar to those previously reported for unit one and | | unit three. Additional inspection will be performed to determine the cause | | of identified boron accumulation. | | | | The licensee notified the NRC resident inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 37951 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 04/29/2001| | UNIT: [1] [] [] STATE: OH |NOTIFICATION TIME: 03:18[EDT]| | RXTYPE: [1] GE-6 |EVENT DATE: 04/29/2001| +------------------------------------------------+EVENT TIME: 00:50[EDT]| | NRC NOTIFIED BY: ROBERT KIDDER |LAST UPDATE DATE: 04/29/2001| | HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |THOMAS KOZAK R3 | |10 CFR SECTION: | | |*RPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| | |*ESF 50.72(b)(3)(iv)(A) VALID SPECIF SYS ACTUAT| | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 M/R Y 16 Power Operation |0 Hot Standby | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL SCRAM DUE TO DEGRADING VACUUM CONDITIONS | | | | The licensee had reduced power to 16% and removed the main generator from | | service due to a stator water leak on the generator exciter causing a | | ground. After the main generator was off line vacuum started deteriorating | | and the reactor was manually scrammed. All rods fully inserted and all | | systems functioned normally. The plant is presently using the reactor core | | isolation cooling (RCIC) system for makeup and the safety relief valves to | | the suppression pool for decay heat removal. | | | | The cause of the deteriorating vacuum condition is under investigation. | | | | The licensee notified the NRC Resident Inspector. | | | | * * * UPDATE AT 0526 EDT ON 4/29/01 BY TOM VEITCH TO FANGIE JONES * * * | | | | The plant is using RCIC for pressure control and the motor driven feedpump | | for makeup to the reactor coolant system. Also, at 0116 EDT there was an | | automatic main steam valve isolation due to the deteriorating vacuum | | condition, an expected action. This is reportable under 10 CFR | | 50.72(b)(3)(iv)(B) as an 8 hour report. | | | | The licensee notified the NRC Resident Inspector. The R3DO (Thomas Kozak) | | was notified. | | | | * * * UPDATE AT 1641 ON 4/29/01 BY TODD HENDERSON TO DOUG WEAVER * * * | | | | At approximately 0215 on 04/29/2001, the Main Steam Isolation Valves closed | | automatically as a result of the continued loss of vacuum. In a 0530 update | | to the original notification, this isolation was reported as a specified | | system actuation in accordance with 10 CFR 50.72 (b)(3)(iv)(A). In that | | update, the time of the actuation was originally reported as 0116 on | | 04/29/2001. At approximately the same time, Reactor Core Isolation Cooling | | (RCIC) was started to assist with pressure control. At 0227, main condenser | | vacuum was broken. At 0247, a Safety Relief Valve (SRV) was opened and | | closed to control pressure, with the motor driven feed pump supplying | | feedwater. | | | | Approximately 2 minutes after the first SRV was cycled, a High Pressure Core | | Spray (HPCS) RPV Level 2 (130" above the top of active fuel) initiation | | signal was received which started the HPCS pump and Division 3 emergency | | diesel generator. No injection to the RPV occurred (or should have | | occurred) because reactor level was above the level where injection was | | required (Level 8 219" above the top of active fuel). A Division 2 Balance | | of Plant isolation signal and Redundant Reactivity Control System Level 2 | | also occurred at this time (with expected plant response including the | | tripping of both Recirculation pumps). The source of this signal has not | | yet been determined. | | | | At approximately 0430, a Reactor Pressure High/Drain Temperature Low alarm | | was received, indicating thermal stratification in the reactor pressure | | vessel due to the loss of reactor recirculation. This originally delayed | | placing shutdown cooling in operation, but the condition has been cleared | | allowing progress toward initiating shutdown cooling. | | | | The plant is currently in mode 3, with reactor level and pressure being | | maintained with periodic cycling of Safety Relief Valves and operation of | | RCIC. Residual heat removal (RHR) train 'B' is being used for suppression | | pool cooling. Actions are in progress to place RHR train 'A' in shutdown | | cooling, and bring the plant to Mode 4. | | | | The Senior Resident Inspector has been informed of the event. The | | operations center notified the R3DO (Kozak). | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 37952 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 04/29/2001| | UNIT: [] [2] [] STATE: CT |NOTIFICATION TIME: 12:19[EDT]| | RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 04/29/2001| +------------------------------------------------+EVENT TIME: 11:28[EDT]| | NRC NOTIFIED BY: JOSEPH FRANKS |LAST UPDATE DATE: 04/29/2001| | HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |DAVID SILK R1 | |10 CFR SECTION: | | |*RPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| | |*ESF 50.72(b)(3)(iv)(A) VALID SPECIF SYS ACTUAT| | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | |2 A/R Y 97 Power Operation |0 Hot Standby | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TURBINE TRIP - REACTOR TRIP | | | | The loss of a circulating water pumped led to a turbine trip and reactor | | trip. All rods inserted after the trip and the plant is stable in mode 3. | | Reactor coolant pumps are running and the steam generators are being fed | | with the mainfeed system. The main condenser is available for decay heat | | removal. One steam generator safety valve may have lifted during the | | transient, but is closed now. | | | | The cause of the circulating water pump trip is unknown. | | | | The licensee informed the NRC resident inspector as well as State and local | | governments. | | | | | | * * * UPDATE AT 1715 ON 4/29/01 BY FRANKS RECEIVED BY WEAVER * * * | | | | This update corrects the time of the event from 1151 to 1128. There was | | also a specified system actuation after the trip. Two auxiliary feedwater | | pumps started after the trip on low steam generator level. Once level was | | restored the pumps were secured. The licensee notified the NRC resident | | inspector. The operations center notified R1DO (Silk). | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 37953 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: GRAND GULF REGION: 4 |NOTIFICATION DATE: 04/30/2001| | UNIT: [1] [] [] STATE: MS |NOTIFICATION TIME: 02:24[EDT]| | RXTYPE: [1] GE-6 |EVENT DATE: 04/29/2001| +------------------------------------------------+EVENT TIME: 22:50[CDT]| | NRC NOTIFIED BY: DAVE HANKS |LAST UPDATE DATE: 04/30/2001| | HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |BILL JONES R4 | |10 CFR SECTION: | | |*COM 50.72(b)(3)(xiii) LOSS COMM/ASMT/RESPONSE| | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N N 0 Refueling |0 Refueling | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | EXPECTED LOSS OF SPDS FOR GREATER THAN 8 HOURS | | | | Planned maintenance removed safety parameters display system (SPDS) from | | service for greater than 8 hours. This requires a notification per 10 CFR | | 50.72(b)(3)(xiii) for loss of assessment capabilities. | | | | The licensee notified the NRC Resident Inspector. | +------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021