| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
07/19/2005 - 07/20/2005 ** EVENT NUMBERS ** |
 | Power Reactor | Event Number: 41851 | Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [3] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: STEPHEN PRUSSMAN
HQ OPS Officer: PETE SNYDER | Notification Date: 07/19/2005
Notification Time: 09:42 [ET]
Event Date: 07/19/2005
Event Time: 02:00 [EDT]
Last Update Date: 07/19/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
RICHARD CONTE (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text LOSS OF EMERGENCY SIREN POWER
On July 19, 2005, at approximately 0650 hours, it was determined that of all of the Indian Point Energy Center emergency sirens were out of service and had been out of service since approximately 0200 on July 19, 2005. This results in a degraded emergency siren notification system which is reportable under 10 CFR 50.72(b)(3)(xiii). Both Units 2 and 3 were at 100 percent power and remain at 100 percent power. The loss of sirens was caused by a loss of power to the main radio transmitter. The loss of normal power is still under investigation. The loss of emergency backup occurred when the non-safety related backup diesel tripped. The transmitter remained operable on the backup battery supply until it was expended. Immediate corrective action was completed at approximately 0745 by restoring backup battery power and verification of system operability, (two sirens remain inoperable). Availability of battery power will be assured until corrective action to restore normal power is complete. The loss of the [non-safety related backup] diesel is being investigated.
The emergency plan has route alerting and public radio announcements available as necessary to notify the public in lieu of the non-operational sirens. The counties and state were notified of the loss of sirens and restoration.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 41852 | Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: MARK SHAFFER
HQ OPS Officer: PETE SNYDER | Notification Date: 07/19/2005
Notification Time: 10:53 [ET]
Event Date: 07/19/2005
Event Time: 03:45 [EDT]
Last Update Date: 07/19/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
RICHARD CONTE (R1)
|
| 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 HIGH PRESSURE COOLANT INJECTION SYSTEM INOPERABLE
"On 7/19/05 at 0345, maintenance technicians were performing a voltage check during an I&C surveillance when a lead slipped, making inadvertent contact within the panel. This resulted in shorting of a power connection and blowing a fuse. This fuse supplied initiation and trip logic components associated with the High Pressure Coolant Injection (HPCI) system, the 'A' Core Spray system, and the 'A' Residual Heat Removal (RHR) system. Loss of the HPCI system is reportable under 10 CFR 50.72(b)(3)(v) as a loss of a single train safety system required to mitigate the consequences of an accident.
"Hope Creek entered Technical Specification (TS) 3.0.3 for HPCI inoperability with one Core Spray and one RHR system inoperable. Actions to replace the fuse and restore operability of the HPCI system were completed at 0909 on 7/19/05, allowing exit from TS 3.0.3. Actions to commence staffing for a shutdown and implement required procedures were implemented, however a power reduction was not initiated based on successful restoration.
"The remaining retest activities associated with fuse restoration were completed for the 'A' Core Spray Loop and the 'A' RHR system at 0923 on 7/19/05, clearing the remaining Limiting Conditions for Operation associated with the fuse failure. No additional Emergency Core Cooling Systems or safety related equipment was inoperable during this time period."
The licensee notified the NRC Resident Inspector and Lower Alloways Creek Township. |
| Hospital | Event Number: 41853 | Rep Org: RAPID CITY REGIONAL HOSPITAL
Licensee: RAPID CITY REGIONAL HOSPITAL
Region: 4
City: RAPID CITY State: SD
County:
License #: 40-00238-04
Agreement: N
Docket:
NRC Notified By: ED CYTACKI
HQ OPS Officer: BILL HUFFMAN | Notification Date: 07/19/2005
Notification Time: 11:00 [ET]
Event Date: 01/06/2005
Event Time: 07:00 [MDT]
Last Update Date: 07/19/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
| Person (Organization):
LINDA SMITH (R4)
RICHARD CONTE (R1)
MIKE ERNSTES (R2)
PATRICK LOUDEN (R3)
GREG MORELL (NMSS)
TOM ESSIG VIA E-MAIL (NMSS)
MICHELE BURGESS (NMSS)
| Event Text PART 21 NOTIFICATION CONCERNING MALFUNCTION OF A HIGH DOSE RATE BRACHYTHERAPY REMOTE AFTERLOADER DEVICE
The RSO at the Rapid City Regional Hospital reported a malfunction of a high dose rate brachytherapy remote afterloader manufactured by Nucletron - Old Delft (Headquarters in Maryland). The unit was a Microselect V-2 with 18 channels. While treating a patient, the source had been deployed successfully through 16 channels. When attempting to deploy the source into the 17th channel, an alarm was received indicating a problem and locked-out the source in its safe shielded position. Attempts to correct the problem were unsuccessful and the treatment was terminated. No excess exposure resulted from the problem.
A service representative from Nucletron serviced and repaired the device on January 7, 2005. The "Flag" wire on the device was determined to be broken and the "V" block was replaced. The device flag is a component that monitors the position of the source and will lock out the device when it does not respond properly. It was noted by the RSO that the device had been in service for about 5 years without any problem of this nature.
This problem was discussed with NRC Region 4 inspector (Rick Munoz) on 7/13/05 during a routine inspection of the hospital. Additional discussions were conducted with NRC HQ (Greg Morell) on 7/19/05.
The hospital RSO will followup this verbal notification with a written report. |
| Other Nuclear Material | Event Number: 41855 | Rep Org: DEPARTMENT OF VETERANS AFFAIRS
Licensee: DEPARTMENT OF VETERANS AFFAIRS
Region: 1
City: BILOXI State: MS
County:
License #: 03-23853-01VA
Agreement: Y
Docket:
NRC Notified By: MICHAEL SIMMONS
HQ OPS Officer: MIKE RIPLEY | Notification Date: 07/19/2005
Notification Time: 18:22 [ET]
Event Date: 07/19/2005
Event Time: [CDT]
Last Update Date: 07/19/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
20.1906(d)(1) - SURFACE CONTAM LEVELS > LIMITS
| Person (Organization):
RICHARD CONTE (R1)
PATRICK LOUDEN (R3)
DANIEL GILLEN (NMSS)
| Event Text RADIOACTIVE PACKAGE WITH REMOVABLE SURFACE CONTAMINATION EXCEEDING A LIMIT
"Licensee: Department of Veterans Affairs, National Health Physics Program License # 03-23853-01VA
"Permittee: VA Gulf Coast Veterans Health Care System, Biloxi, Mississippi
"Date of event: July 19, 2005, about 1000 CDT
"Date and Time NHPP notified: July 19, 2005, 1700 CDT
"A radioactive package was received from the commercial radiopharmacy at about 1000 hours CDT. The nuclear medicine technologist followed routine procedures for opening radioactive packages and performed a wipe test on the outside of the package. The wipe test results were 13,000 dpm / 300 cm2. Slight contamination was located on the inside of the package. The technologist immediately notified the radiopharmacy of the contamination. The radiopharmacy is Cox Nuclear Pharmacy in Biloxi, MS.
"NHPP representatives will follow-up with the permittee on July 20, 2005. A copy of this text has been sent to Kevin Null, NRC Region III
"Event Number: 41855" | |