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U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
03/19/2004 - 03/22/2004
** EVENT NUMBERS **
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| General Information or Other |
Event Number: 40594 |
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: LOMA LINDA MEDICAL CENTER
Region: 4
City: LOMA LINDA State: CA
County:
License #: 0060-36
Agreement: Y
Docket:
NRC Notified By: C. J. SALGADO
HQ OPS Officer: MIKE RIPLEY |
Notification Date: 03/17/2004
Notification Time: 16:37 [ET]
Event Date: 03/16/2004
Event Time: [PST]
Last Update Date: 03/17/2004 |
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE |
Person (Organization):
JEFFERY CLARK (R4)
HAROLD GRAY (R1)
TOM ESSIG (NMSS) |
Event Text
AGREEMENT STATE REPORT - MISSING SR-90 EYE APPLICATOR SOURCE
"Licensee reported to Radiologic Health Branch-Granada Hills (RHB-GH) that it had discovered one of its Sr-90 eye applicator sources (Model Manning #357, SIN pending) missing yesterday [03/16/04] from its sealed source storage C-container where it had been stored for the last ten years. The actual eye applicator was kept in its own box provided by the manufacturer. The discovery was made when the RSO was conducting a routine check for leak test/inventory purposes. This source was reportedly last accounted for about July 2003. The original assay date for the source was 8/22/79 at 31.7 millicuries (Reported to be about 17 millicuries now).
"The source was stored in a locked and alarmed C-container used exclusively for radioactive material storage. A fence around it is also locked. There was no sign of a break-in. However, the licensee reported that in May 2002 there was a break-in to this storage container. The same source was at that time removed from the C-container by the intruder apparently and was later found in an outside barrel so it was recovered. Incidentally, some uranyl nitrate (or acetate?) in microcurie quantities was stolen then, too.
"The licensee will continue searching to determine the likely disposition of the missing source. RHB-GH suggested they notify their security people. The licensee will be providing a written report." |
| Power Reactor |
Event Number: 40598 |
Facility: PERRY
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: DAVID ODONNELL
HQ OPS Officer: RICH LAURA |
Notification Date: 03/19/2004
Notification Time: 16:17 [ET]
Event Date: 02/22/2004
Event Time: 10:16 [EST]
Last Update Date: 03/19/2004 |
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION |
Person (Organization):
KENNETH O'BRIEN (R3) |
| Unit |
SCRAM Code |
RX CRIT |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
| 1 |
N |
Y |
100 |
Power Operation |
100 |
Power Operation |
Event Text
PARTIAL RPS ACTUATION DURING TESTING AT PERRY
"This report is being made in accordance with 10CFR50.73 (a)(1), which states, in part, "in the case of an, invalid actuation reported under 10 CFR50.73(a)(2)(iv), other than actuation of the reactor protection system (RPS) when the reactor is critical, the licensee may, at its option, provide a telephone notification to the NRC Operations Center within 60 days after discovery of the event instead of submitting a written LER." These invalid actuations are being reported under 10CFR50.73(a)(2)(iv)(A).
"On February 22, 2004, at 1016 hours, while operating at 100 percent power, the reactor protection system manual scram channel functional test was performed. When a division 1 manual scram pushbutton was depressed, in addition to the expected half scram, the reactor protection system (RPS) A motor-generator electrical protection assembly circuit breakers tripped open. Loss of power from the RPS A motor-generator caused the loss of electrical power to the RPS instrumentation. This resulted in the invalid actuation of the logic that is powered by RPS A. The actuations resulted in isolation signals that closed one or more valves in each of the following division 1 subsystems: main steam line drains, containment and drywell radiation monitors, reactor water cleanup, fuel pool cooling, suppression pool cleanup, containment and drywell radwaste sumps and containment chilled water. All systems and components responded as designed for the signals that resulted from the loss of RPS A buss. This is considered a partial actuation since only division 1 components were effected. Following restoration of power to the RIPS A buss, the actuation logic was reset, and the equipment/systems were returned to the status required by plant conditions.
"Discussion of the causes and corrective actions associated with this event are documented in the corrective action program in condition report 04-00901. The resident inspector has been notified." |
| Fuel Cycle Facility |
Event Number: 40599 |
Facility: PORTSMOUTH GASEOUS DIFFUSION PLANT
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
6903 ROCKLEDGE DRIVE
BETHESDA, MD 20817 (301)564-3200
Region: 2
City: PIKETON State: OH
County: PIKE
License #: GDP-2
Agreement: N
Docket: 0707002
NRC Notified By: RON CRABTREE
HQ OPS Officer: RICH LAURA |
Notification Date: 03/19/2004
Notification Time: 17:45 [ET]
Event Date: 03/19/2004
Event Time: 09:10 [EST]
Last Update Date: 03/19/2004 |
Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT |
Person (Organization):
ANNE BOLAND (R2)
M. WAYNE HODGES (NMSS) |
Event Text
SAFETY SYSTEM ACTUATION AT PORTSMOUTH GDP
"On 03/19/04 at 0910 hours, Autoclave #5 in the X-343 Facility experienced a Steam Shutdown due to high condensate level alarms (A) and (B) actuating. The autoclave was in an applicable TSR mode (Mode II, Heating) at the time of the alarm actuations. The autoclave was placed in Mode VII (Shutdown) and declared INOPERABLE by the Plant Shift Superintendent (PSS). An investigation is underway to determine the cause of the actuations. No release of radioactive material occurred as a result of this incident. This event is being reported in accordance with UE2-RA-RE1030, Appendix D. J. 2. Safety System Actuations." |
| Power Reactor |
Event Number: 40600 |
Facility: LIMERICK
Region: 1 State: PA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: DAN SEMETER
HQ OPS Officer: RICH LAURA |
Notification Date: 03/19/2004
Notification Time: 21:00 [ET]
Event Date: 03/19/2004
Event Time: 14:08 [EST]
Last Update Date: 03/19/2004 |
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION |
Person (Organization):
HAROLD GRAY (R1) |
| Unit |
SCRAM Code |
RX CRIT |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
| 1 |
N |
Y |
15 |
Power Operation |
15 |
Power Operation |
Event Text
HPCI SYSTEM DECLARED INOPERABLE AT LIMERICK 1 DUE TO A BROKEN HAND SWITCH
"On 3/19/04 at 14:08 PM EST, the Unit-1. HPCI system was declared inoperable due to a hand-switch failure, which prevented main control room operation of the HV-055-1F0O1 HPCI steam admission valve. The system had just successfully completed its functional surveillance test and the switch broke resulting in the operators using an, alternate means to shutdown the HPCI system. The steam admission valve is not a PCIV. The valve was open all the time; the system was shutdown using an alternate procedure. The system is now blocked for hand-switch replacement. This report is being made pursuant to 10CFR50.72(b)(3)(v) for failure of a single train accident mitigation system."
The NRC Resident inspector was notified. Operators entered the unit into a 14 day LCO for declaring HPCI system inoperable. |
| Power Reactor |
Event Number: 40601 |
Facility: CALVERT CLIFFS
Region: 1 State: MD
Unit: [1] [ ] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: KEVIN UMPHREY
HQ OPS Officer: RICH LAURA |
Notification Date: 03/20/2004
Notification Time: 15:25 [ET]
Event Date: 03/20/2004
Event Time: 13:40 [EST]
Last Update Date: 03/20/2004 |
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL |
Person (Organization):
HAROLD GRAY (R1) |
| Unit |
SCRAM Code |
RX CRIT |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
| 1 |
A/R |
Y |
100 |
Power Operation |
0 |
Hot Standby |
Event Text
AUTOMATIC REACTOR TRIP AT CALVERT CLIFFS UNIT 1 DUE TO A LOSS OF FEEDWATER
"At 1340 on 3/20/2004, Calvert Cliffs Unit 1 Reactor automatically shutdown due to low Steam Generator Water Level. The low water level was caused by a loss of at least one Steam Generator Feed Pump. The loss was initially caused by a short or ground from Chart Recorder maintenance in Panel 1C29. 1C29 is a control panel in the control room. The chart recorder was a 500KV Bus Voltage Monitor.
"The post trip primary indications responded normally. The auto steam dump operation responded normally until the quick open signal was cleared at which time the Turbine Bypass Valves failed shut. It is unclear at this time why they failed shut. Steam dump continues through the use of the Atmospheric dump valves and feedwater is supplied via the Auxiliary Feedwater System with the use of 11 (Steam Driven Pump) & 13 AFW Pump (electric driven pump). Lowest Steam Generator Level was -210" in 11 S/G and -115" in 12 S/G level.
"Current Conditions are RCS pressure is 2250 PSIA and temperature is 532°F."
All control rods properly inserted into the reactor core. The NRC Resident Inspector was notified. |
| Power Reactor |
Event Number: 40602 |
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: RONALD FRY
HQ OPS Officer: CHAUNCEY GOULD |
Notification Date: 03/21/2004
Notification Time: 16:03 [ET]
Event Date: 03/21/2004
Event Time: 12:32 [EST]
Last Update Date: 03/21/2004 |
Emergency Class: NON EMERGENCY
10 CFR Section:
INFORMATION ONLY |
Person (Organization):
HAROLD GRAY (R1) |
| Unit |
SCRAM Code |
RX CRIT |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
| 1 |
N |
N |
0 |
Refueling |
0 |
Refueling |
| 2 |
N |
Y |
100 |
Power Operation |
100 |
Power Operation |
Event Text
THREE INJURIED NONCONTAMINATED CONTRACTORS WERE TRANSPORTED TO THE HOSPITAL.
"On 3/21/04 at 12:32 hrs a bucket truck working at the Unit 1 Cooling Tower came in contact with a 230KV transmission line causing the loss of one off site power supply to the plant. The 500 KV offsite circuit remained energized during the event. A contract employee at the base of the truck was thrown due to the electrical short. A contract employee in the bucket of the truck was able to lower the bucket to the ground. A first aid crew was dispatched to the location and an Ambulance was requested. The Ambulance entered the site at 12:50 and at 13:02 the individuals were transported to the local hospital. Due to the electrical transient in the plant, a contract employee performing grinding activities lost control of the grinder and injured his middle finger. This individual received first aid and was transported to the local hospital by his supervisor. The individual injured in the plant was surveyed by Health Physics prior to leaving the site and no contamination was found. The Local Law Enforcement Agency was notified of the Emergency vehicle being dispatched to the site. The State Emergency Operations Center will be notified of the Emergency vehicle entering the site."
The NRC Resident Inspector and local agencies were notified and the state will be notified. |
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