Event Notification Report for January 8, 2001
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
01/05/2001 - 01/08/2001
** EVENT NUMBERS **
37637 37646 37647 37648 37649 37650 37651 37652
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37637 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 12/28/2000|
| UNIT: [1] [] [] STATE: NE |NOTIFICATION TIME: 12:21[EST]|
| RXTYPE: [1] GE-4 |EVENT DATE: 12/28/2000|
+------------------------------------------------+EVENT TIME: 07:41[CST]|
| NRC NOTIFIED BY: STEVE WHEELER |LAST UPDATE DATE: 01/05/2001|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CHARLES MARSCHALL R4 |
|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 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| CONTROL BUILDING VENTILATION ISOLATION |
| |
| "At 0741 CST the Control Building Emergency Filtration System automatically |
| initiated on a Control Building Intake Gas High Activity alarm. The cause of |
| the Gas High Activity alarm is under investigation." |
| |
| The NRC resident inspector has been informed of this event by the licensee. |
| |
| * * * UPDATE ON 12/29/00, 0024 ET BY MYERS TAKEN BY MACKINNON * * * |
| |
| During the day, trouble shooting was performed to determine the source of |
| the actuation at 0741 CST today. Surveillance Procedure 6.PRM.317, CONTROL |
| ROOM AIR SAMPLING SYSTEM ELECTRONIC CALIBRATION, was performed, and all |
| indications were within specification. A source check of the gaseous |
| channel was also performed per Instrument Operating Procedure 4.17, and the |
| response of the monitor was normal. Air sampling was conducted, and no |
| indications of abnormal radiation were identified. The Control Room |
| Emergency Filtration System was returned to the standby lineup. |
| |
| At 1933, the Control Room Emergency Filtration System again initiated on a |
| high gaseous activity signal. All equipment functioned as required. The |
| Control Building Ventilation Radiation Monitor has been declared inoperable, |
| and the Control Room Emergency Filtration System remains in service, aligned |
| in the accident mode. |
| |
| The NRC Resident Inspector was notified. |
| |
| Note: The Control Building Ventilation Radiation Monitor consists of three |
| channels, with two required to be operable. The Iodine channel is also |
| presently inoperable. The actuation logic requires only one channel of the |
| three to initiate Control Room Isolation and start the Emergency Booster |
| (pressurization) fan. |
| |
| Noble gas sample was taken at 2142 CST. All readings were normal. NRC |
| R4DO (C. Marschall) notified. |
| |
| * * * UPDATE ON 1/5/01 @ 1113 BY VAN DER KAMP TO GOULD * * * RETRACTION |
| |
| Event Number 37637 reported a condition at Cooper Nuclear Station (CNS) |
| where the Control Room Emergency Filtration System (CREPS) automatically |
| initiated on a Control Building Intake Gas High Activity alarm. Surveillance |
| testing found no abnormalities with the system and air sampling found no |
| indications of abnormal radiation levels. A subsequent identical event |
| occurred later the same day and was reported to the NRC Operations Center in |
| an update. |
| |
| Subsequent troubleshooting has found a solder connection, that connects gas |
| monitor components to ground, had come apart. Discussions with the |
| manufacturer of the monitor confirm that the loss of ground can cause |
| spiking in the displayed background reading. |
| |
| CNS investigation has found that the initiation of the CREPS was due to an |
| invalid signal, i.e., not due to an actual elevated radioactive |
| concentration. Per 10CFR50.72(b)(2)(ii), invalid actuations of CREFS are |
| not required to be reported and EN 37637 is retracted. |
| |
| The NRC Resident Inspector will be notified of this event by the licensee. |
| |
| The Reg 4 RDO(Johnson) was notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 37646 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: HOLTEC INTERNATIONAL |NOTIFICATION DATE: 01/04/2001|
|LICENSEE: HOLTEC INTERNATIONAL |NOTIFICATION TIME: 15:59[EST]|
| CITY: MARLTON REGION: 1 |EVENT DATE: 10/18/2000|
| COUNTY: STATE: NJ |EVENT TIME: 12:00[EST]|
|LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 01/05/2001|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |MELVYN LEACH R3 |
| |VERN HODGE, FAX NRR |
+------------------------------------------------+ |
| NRC NOTIFIED BY: BRIAN GUTHERMAN | |
| HQ OPS OFFICER: JOHN MacKINNON | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|CCCC 21.21 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 10 CFR PART 21 NOTIFICATION FOR DISCREPANT WEIGHT OF SPENT FUEL RACKS |
| |
| Spent fuel racks removed from Byron Nuclear Power Plant were discovered to |
| have as-found weights ranging from approximately 8,200 to 10,500 lbs more |
| than the weights used in the analyses supporting the original design and |
| licensing of these racks and in the design of the lifting equipment used to |
| lift the racks. The analyses related to seismic loadings, bearing pad |
| design, spent fuel pool liner fatigue, and possibly others used to design |
| and license these racks may no longer be conservative when the additional |
| weight is considered. The actual impact on these analyses has not, to our |
| knowledge, been evaluated. The impact on the design of the lifting |
| equipment is that the design safety factors for the lifting equipment, while |
| still above 1.0, may not meet the minimum safety factors in NUREG-0612 and |
| associated reference documents. |
| |
| Braidwood Nuclear Station has four similarly designed racks provided by the |
| same supplier. |
| |
| |
| * * * UPDATE ON 1/5/01 @ 0946 BY GUTHERMAN TO GOULD * * * |
| |
| The manufacturer of the spent fuel racks reported in the initial reports was |
| Joseph Oat Co of Camden, NJ. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37647 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: THREE MILE ISLAND REGION: 1 |NOTIFICATION DATE: 01/05/2001|
| UNIT: [1] [] [] STATE: PA |NOTIFICATION TIME: 06:38[EST]|
| RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP |EVENT DATE: 01/05/2001|
+------------------------------------------------+EVENT TIME: 06:20[EST]|
| NRC NOTIFIED BY: SCHORK |LAST UPDATE DATE: 01/05/2001|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JAMES NOGGLE 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| THE MOTOR FOR MS-V-1C HAS BEEN DECLARED INOPERABLE |
| |
| TMI identified a condition that is outside the design basis of the facility |
| at 0620 hours on January 5, 2001. The condition is that MS-V-1C may not be |
| capable of being closed within 120 seconds as described in the bases for |
| Technical Specification 4.8.2 and FSAR Section 10.3. The bases for TS 4.8.2 |
| and FSAR Section 10.3 both state that the valve is capable of being remotely |
| closed within 120 seconds from the Control Room. With the motor inoperable, |
| the valve cannot be remotely closed within 120 seconds. The condition was |
| found during routine surveillance testing and subsequent evaluation. During |
| the surveillance testing the valve is stroke closed 10% and then returned to |
| its normal operation position of full open. The valve stroke closed to the |
| 10% closed position without incident. During the return of the valve to the |
| full open position sparks were observed and a burning odor was present. |
| However, the sparking ceased and the motor successfully traveled to the fail |
| open position (verified by visual observation of the valve stern position). |
| Subsequent visual inspection of the valve and motor, interviews with the |
| technicians, the system engineer and the Electrical Foreman resulted in the |
| declaration of the inoperability of the motor for MS-V-1C. |
| |
| This deficient condition has been documented in the TMI Corrective Action |
| program. Troubleshooting of the motor for MS-V-1C is in progress. Interim |
| action has been taken to provide for the expeditious manual closure of the |
| valve and those actions are contained in an approved plant procedure. |
| |
| The Resident Inspector will be informed. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 37648 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: COLORADO DEPARTMENT OF HEALTH |NOTIFICATION DATE: 01/05/2001|
|LICENSEE: SAN LUIS VALLEY REGIONAL MED CENTER |NOTIFICATION TIME: 10:02[EST]|
| CITY: ALAMOSA REGION: 4 |EVENT DATE: 01/05/2001|
| COUNTY: STATE: CO |EVENT TIME: 08:00[MST]|
|LICENSE#: 14202 AGREEMENT: Y |LAST UPDATE DATE: 01/05/2001|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |WILLIAM JOHNSON R4 |
| |BRIAN SMITH NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: PENTECOST | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT - MOLYBDENUM-99/TECHNETIUM-99m GENERATOR LOST WHILE |
| IN SHIPMENT |
| |
| DUPONT PHARMACEUTICALS SHIPPED A 750 MILLICURIE MOLYBDENUM/TECHNETIUM |
| GENERATOR VIA FEDEX TO THE SAN LUIS VALLEY REGIONAL MEDICAL CENTER IN |
| ALAMOSA, CO ON 12/28/00. AS OF THIS DATE THE SHIPMENT HAS NOT BEEN |
| RECEIVED. THERE WAS NO FEDEX TRACKING NUMBER AND DUPONT COULD NOT GIVE THE |
| STATE ANY INFORMATION BECAUSE THEIR COMPUTERS WERE DOWN. |
| |
| * * * UPDATE ON 1/5/01 @ 1037 BY PENTECOST TO GOULD * * * |
| |
| THE GENERATOR WAS LOCATED @ 0830MST AT THE FEDEX DENVER FACILITY AND IT IS |
| IN TRANSIT TO THE MEDICAL FACILITY. |
| |
| NOTIFIED REG 4 RDO(JOHNSON) AND NMSS(SMITH) WERE NOTIFIED |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 37649 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: CALIFORNIA RADIATION CONTROL PRGM |NOTIFICATION DATE: 01/05/2001|
|LICENSEE: PACIFIC SOILS ENGINEERING |NOTIFICATION TIME: 11:22[EST]|
| CITY: OCEANSIDE REGION: 4 |EVENT DATE: 01/02/2001|
| COUNTY: STATE: CA |EVENT TIME: [PST]|
|LICENSE#: 3142 AGREEMENT: Y |LAST UPDATE DATE: 01/05/2001|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |WILLIAM JOHNSON R4 |
| |JOHN HICKEY NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: GREGER | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| STOLEN NUCLEAR MOISTURE DENSITY GAUGE |
| |
| The licensee reported that a Campbell Pacific Nuclear moisture density gauge |
| was stolen from a storage unit in Oceanside, Ca between 1530 on 12/29/00 and |
| noon on 12/30/00. Model # of the gauge was MC-3 and its serial # is |
| M380504284. The gauge contained approximately 8 millicuries of cesium-137 |
| and 40 millicuries of americium/beryllium. The licensee will offer a |
| reward. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37650 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: ARKANSAS NUCLEAR REGION: 4 |NOTIFICATION DATE: 01/05/2001|
| UNIT: [1] [] [] STATE: AR |NOTIFICATION TIME: 12:25[EST]|
| RXTYPE: [1] B&W-L-LP,[2] CE |EVENT DATE: 01/05/2001|
+------------------------------------------------+EVENT TIME: 08:48[CST]|
| NRC NOTIFIED BY: JAMES PORTER |LAST UPDATE DATE: 01/05/2001|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |WILLIAM JOHNSON R4 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
|APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 M/R Y 100 Power Operation |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| REACTOR MANUALLY TRIPPED FROM 80% POWER LEVEL DUE TO EXCESSIVE MAIN TURBINE |
| GENERATOR HYDROGEN LEAK. |
| |
| "At 0848 CT on 01/05/01 ANO Unit 1 reactor was manually tripped due to |
| excessive hydrogen leakage on the main turbine generator. Reactor power was |
| reduced from 100% to 80% prior to the manual reactor trip. No ESF actuations |
| occurred following the trip. The unit is currently stable at Hot Shutdown |
| conditions." |
| |
| Hydrogen leak on the main turbine generator was first noticed around 2100 |
| hours CT on 01/04/01. Normal hydrogen pressure in the main turbine |
| generator is 70 psi. The licensee stated that they were losing |
| approximately 3 psi per hour. The licensee evacuated the Turbine Building |
| as a precaution. After reactor power had been reduced to 80% power the |
| hydrogen leak increased at which point the licensee manually tripped the |
| reactor. All rods fully inserted into the core. Once Through Steam |
| Generator atmospheric valves operated properly. The licensee stated that |
| they have a 0.17 gallon per day primary leak to secondary system leak. All |
| Emergency Core Cooling Systems and the Emergency Generators are fully |
| operable if needed. Once Through Steam Generator water levels are being |
| maintained using main feedwater, one main feedwater pump operating. At the |
| time of the notification the licensee had not located the source of the |
| hydrogen leak. |
| |
| The licensee notified Arkansas Department of Health. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
| |
| * * * UPDATE ON 01/05/01 AT 1734 ET BY REX KNIGHT TAKEN BY MACKINNON * * * |
| |
| When the reactor was tripped, discharge canal temperature dropped from 52 |
| degrees F to 37 degrees F. This caused a large number of Thread Fin Shad to |
| die. A member of the public called the Arkansas Game and Fish (AG&F) |
| Commission about the Shad. ANO has contacted the AG&F Commission and |
| explained the situation. A Press Release is not planned at this time. NRC |
| R4DO (Bill Johnson) notified. |
| |
| The NRC Resident Inspector was notified of the event update by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37651 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 01/06/2001|
| UNIT: [1] [] [] STATE: MN |NOTIFICATION TIME: 20:50[EST]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 01/06/2001|
+------------------------------------------------+EVENT TIME: 18:30[CST]|
| NRC NOTIFIED BY: LES ANDERSON |LAST UPDATE DATE: 01/06/2001|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: |MELVYN LEACH R3 |
|10 CFR SECTION: | |
|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 90 Power Operation |90 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| COURTESY CALL TO THE NATIONAL RESPONSE CENTER (NRC) MADE AFTER SPILLING |
| APPROXIMATELY 25 GALLONS OF SULFURIC ACID. |
| |
| A courtesy call was made to the National Response Center that was made to |
| report a sulfuric acid spill at the plant water treatment area. The |
| Corporate Environmental and Regulatory Affairs Department, which the |
| licensee calls ERAD, was notified. ERAD, in turn, notified the Minnesota |
| State Pollution Control Agency. The Minnesota State Pollution Control |
| Agency suggested a courtesy call to the National Response Center. |
| |
| Approximately 25 gallons of sulfuric acid was spilled (reportable quantity |
| is 65 gallons of greater). A small amount, less than 10 gallons, of acid |
| drained to their Turbine Building Sump of which a very small amount may have |
| been released. |
| |
| The NRC Resident Inspector was notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37652 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 01/07/2001|
| UNIT: [] [2] [3] STATE: CT |NOTIFICATION TIME: 09:50[EST]|
| RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 01/07/2001|
+------------------------------------------------+EVENT TIME: 06:00[EST]|
| NRC NOTIFIED BY: ROBERT SMITH |LAST UPDATE DATE: 01/07/2001|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JAMES NOGGLE R1 |
|10 CFR SECTION: | |
|DDDD 73.71 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |100 Power Operation |
|3 N Y 90 Power Operation |90 Power Operation |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| SECURITY REPORT |
| |
| Safeguard system degradation related to area boundary. Immediate |
| compensatory measures taken upon discovery. The licensee notified the NRC |
| Resident Inspector. |
| |
| Refer to HOO Log for additional details. |
+------------------------------------------------------------------------------+
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Page Last Reviewed/Updated Thursday, March 25, 2021