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U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
01/12/2004 - 01/13/2004
** EVENT NUMBERS **
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| General Information or Other |
Event Number: 40430 |
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: THE METHODIST HOSPITAL
Region: 4
City: HOUSTON State: TX
County:
License #: L00457-000
Agreement: Y
Docket:
NRC Notified By: JAMES H. OGDEN
HQ OPS Officer: JOHN MacKINNON |
Notification Date: 01/07/2004
Notification Time: 16:43 [ET]
Event Date: 01/05/2004
Event Time: 08:16 [CST]
Last Update Date: 01/07/2004 |
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE |
Person (Organization):
MIKE RUNYAN (R4)
JOSEPH GIITTER (NMSS) |
Event Text
AGREEMENT STATE REPORT: NOVOSTE STRONTIUM-90 INTRAVASULAR BRACHYTHERAPY (IVB) SOURCE DISCOVERED MISSING.
"Novoste Strontium-90 Intravascular brachytherapy (IVB) source (remote afterloader) was discovered missing on January 5, 2004. Source was last seen but not used on December 17, 2003. Reported by phone by RSO. Source is a small handlheld device - Manufacturer: Novoste, Model: BethCath, Serial No. 92607; Source train Serial No. ZB-520; Original Activity 55.62 millicuries; current activity (date of discovery) 54.64 millicuries; Calibration date: 04/11/2003; Last leak test 10/29/2003. Received at the hospital on November 4, 2003. Last used in a patient on December 5, 2003 (first and last use). Last seen on during a functional test on December 17, 2003 in the Fondren Building, Room F1099 (near cath lab) at the Licensee's main site 6565 Fannin Street, Houston, Texas. The source was not used that day. Two other sources of different activity and length remain in storage. The room and cath lab have been search 4 times by the Licensee's staff. Trash has been surveyed. Hospital staff has been notified of the missing equipment.."
Texas Incident No.: I-8089. |
| Power Reactor |
Event Number: 40437 |
Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: ART BREADY
HQ OPS Officer: JEFF ROTTON |
Notification Date: 01/12/2004
Notification Time: 12:30 [ET]
Event Date: 01/12/2004
Event Time: 10:48 [EST]
Last Update Date: 01/12/2004 |
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL |
Person (Organization):
DANIEL HOLODY (R1) |
| Unit |
SCRAM Code |
RX CRIT |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
| 1 |
M/R |
Y |
68 |
Power Operation |
0 |
Hot Shutdown |
Event Text
MANUAL SCRAM FOLLOWING INVALID CONTAINMENT ISOLATION SIGNAL
"On 01/12/04 at 1048 hours, the Hope Creek Generating Station reactor was manually scrammed following an invalid containment isolation signal on Reactor Building High-High Radiation. The invalid signal was caused by the combination of a scheduled sensor calibration on channel 'C', coincident with an emergent failure on channel 'A.' This combination of trip signals made up the two out of three trip logic for the Reactor Building High-High Radiation containment isolation signal. While recovering from the spurious isolation signal, the operating crew observed two of the inboard MSIV's drifting closed from a loss of pneumatic pressure as a result of the isolation signal. In response to this condition, the operating crew manually scrammed the reactor. A low reactor water level scram signal was received at 12.5 inches as expected, and reactor level was subsequently returned to the normal band using the reactor feedpumps. At the time of this event, the 'A' Control Room Ventilation Train was inoperable but available pending emergent corrective maintenance. The 'C' channel Reactor Building Radiation monitor has been returned to service and is operable, and the 'A' channel remains failed in the tripped condition. All other systems functioned as expected, and a post-transient review team is being assembled to investigate the event."
Decay heat is being removed via steam to the main condenser using the bypass valves. The condensate and feedwater system is in operation maintaining reactor vessel water level. No SRVs lifted during the transient and the electrical system is stable in a normal lineup.
The licensee notified the NRC Resident Inspector and will be notifying the LAC Township. |
| Fuel Cycle Facility |
Event Number: 40438 |
Facility: PADUCAH GASEOUS DIFFUSION PLANT
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
6903 ROCKLEDGE DRIVE
BETHESDA, MD 20817 (301)564-3200
Region: 2
City: PADUCAH State: KY
County: McCRACKEN
License #: GDP-1
Agreement: Y
Docket: 0707001
NRC Notified By: CALVIN PITTMAN
HQ OPS Officer: JEFF ROTTON |
Notification Date: 01/12/2004
Notification Time: 14:17 [ET]
Event Date: 01/11/2004
Event Time: 18:00 [CST]
Last Update Date: 01/12/2004 |
Emergency Class: NON EMERGENCY
10 CFR Section:
76.120(c)(2) - SAFETY EQUIPMENT FAILURE |
Person (Organization):
PAUL FREDRICKSON (R2)
JOHN HICKEY (NMSS)
SUSAN FRANT (IRO) |
Event Text
SAFETY EQUIPMENT FAILS TO FUNCTION
"At 1810 [CST] on 01-11-04 the Plant Shift Superintendent (PSS) was notified of a failure of the C-360 #4 Autoclave High Pressure Isolation System. Water was observed leaking from the autoclave head-to-shell interface near the six o'clock position shortly after initiating a cylinder heat cycle. At the time of discovery, the autoclave was in TSR mode 5 and the High Pressure Isolation System was required to be operable while in this mode. This system is designed to provide containment of the autoclave and prevent an external release of UF6 during a system breach while heating a UF6 cylinder. The PSS declared the system inoperable and TSR LCO 2.1.3.1 .C1 actions were implemented to remove the autoclave from service and place it in Mode 2, 'Out of Service.' The event is reportable as a 24 hour event, as required by 10 CFR 76.120©(2)(i); An event in which equipment is disabled or fails to function as designed when the equipment is required by a TSR to prevent releases, prevent exposures to radiation and radioactive materials exceeding specified limits, mitigate the consequences of an accident, or restore this facility to a preestablished safe condition after an accident. The equipment was required by TSR to be available and operable and no redundant equipment was available to perform the required safety function."
"PGDP Problem Report No. ATR-04-0095; PGDP Event Report No. PAD-2004-02; Event Worksheet Responsible Division; Operations"
Operations has notified the Senior NRC Resident Inspector. |
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