| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
08/10/2007 - 08/13/2007 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 43554 | Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: INTEGRITY INSPECTION SOLUTIONS
Region: 4
City: LAFAYETTE State: LA
County:
License #: LA-11357-L01
Agreement: Y
Docket:
NRC Notified By: RICHARD PENROD
HQ OPS Officer: JEFF ROTTON | Notification Date: 08/08/2007
Notification Time: 09:55 [ET]
Event Date: 08/01/2007
Event Time: [CDT]
Last Update Date: 08/08/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
LINDA SMITH (R4)
RON ZELAC (FSME)
| Event Text RADIOGRAPHIC CAMERA SOURCE CONNECTOR ASSEMBLY MALFUNCTION
The following information was provided by the State via facsimile:
"On 8/1/07, one of Integrity Inspection Solutions crews was setting up for radiographic operations at a temporary job site. While connecting the crankout to the exposure device, the source connector assembly broke. Due to this happening before the first exposure on the job, there was no source disconnect. Another crankout was available and the job was completed. The crankout manufacturer could not be determined. The crankout will be sent to an authorized agent for repair. The crankout was used with a SPEC 150 camera."
LA Event Report ID No.: LA070023 |
| General Information or Other | Event Number: 43557 | Rep Org: NC DIV OF RADIATION PROTECTION
Licensee: PIEDMONT CARDIOLOGY ASSOCIATES
Region: 1
City: LENOIR State: NC
County:
License #: 014-1144-2
Agreement: Y
Docket:
NRC Notified By: JAMES ALBRIGHT
HQ OPS Officer: JEFF ROTTON | Notification Date: 08/08/2007
Notification Time: 17:36 [ET]
Event Date: 08/06/2007
Event Time: [EDT]
Last Update Date: 08/08/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
ROBERT SUMMERS (R1)
KEITH McCONNELL (FSME)
| Event Text NORTH CAROLINA AGREEMENT STATE - NUCLEAR MEDICINE TECHNOLOGIST SELF ADMINISTERED SPARE RADIONUCLIDES
The State provided the following information via facsimile:
"Incident description as reported to NCRP [North Carolina Radiation Protection]: Nuclear Medicine Technologist (NMT) working in the Lenoir, NC office of the Licensee performed a diagnostic cardiac imaging exam on himself. He administered himself with 39.4mCi Tc-99m Myoview for a stress test and followed it up with 11.6 mCi Tc-99m Myoview for the rest test. Both administrations occurred on 8/6/07 and were done without the Licensee's or an Authorized User's knowledge or consent; using a dose intended for a patient that did not show-up for their scheduled diagnostic cardiac imaging exam. The NMT 'read' the resulting diagnostic images and observed a cardiac problem, then apparently called the Licensee's office in Hickory to get a second opinion. The Nuc Med Supervisor (Located in the Hickory Office) was made aware of the administration at approximately 1530 on 8/6/07, and the RSO was notified at approximately 1800 on 8/7/07.
"The Licensee reported that the Lenoir office is attended by a single NMT assisted by a Nurse. The rest of the Lenoir office is a non-nuclear cardiology practice although there is an Authorized User (an MD) at that location. At the time of the administration the Authorized User was attending non-nuclear study patients and was not aware of the activities being performed by the NMT on himself. The NMT performed the stress part of this diagnostic administration with Nursing assistance. The licensee reported that the Nurse felt that the NMT was doing something wrong but assisted the treadmill portion of the stress test for safety reasons. Sometime during this span of time the Authorized User at the Lenoir office went to the Hickory office to attend patients and was at that office when the NMT called and reported what he had done.
"NCRPS actions:
(1) requested a complete written report with statements from all individuals involved from the Licensee, which will be evaluated;
(2) report to NRC Op Center in case this turns out to be immediately reportable;
(3) consider follow-up inspection/incident investigation;
(4) possible escalated enforcement actions to be determined."
NC Incident # 07-41 |
| Power Reactor | Event Number: 43560 | Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: TIM BOLAND
HQ OPS Officer: JOHN KNOKE | Notification Date: 08/11/2007
Notification Time: 21:25 [ET]
Event Date: 08/11/2007
Event Time: 17:51 [CDT]
Last Update Date: 08/11/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
RANDY MUSSER (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | A/R | Y | 100 | Power Operation | 0 | Hot Shutdown | Event Text AUTOMATIC SCRAM DUE TO NEUTRON MONITORING TRIP SIGNAL
"On 08/11/2007 at 1751 CDT, Browns Ferry Unit 1 received an Automatic SCRAM due to a Neutron Monitoring (APRM) Trip Signal . Preliminary investigation indicates the trip signal was caused by a Recirculation System Flow Transmitter sensing line becoming separated giving an indicated low flow signal to the neutron monitoring system. With the indicated low flow and high (100%) power, the neutron monitoring system initiated an APRM Simulated Thermal Power Flow Biased Reactor Scram. All control rods inserted and all systems responded as required to the automatic SCRAM signal. No Emergency Core Cooling System (ECCS) initiations occurred as a result of the SCRAM. Reactor water level lowered below Level 3 (+2") (lowest indicated level reached -33") as a result of the SCRAM and was recovered to the normal level band by the Reactor Feed Pumps (RFPs). The expected Primary Containment Isolation System (PCIS) Groups 2, 3, 6, and 8 isolations were received due to Reactor Water Level lowering below Level 3 (+2") (lowest indicated level reached -33") with all systems isolating as required. Reactor pressure is being controlled using Main Steam Bypass Valves. Reactor Level is being maintained in band using Reactor Feed Pumps. Plant to remain in Mode 3 and initiate repairs to the failed sensing line. Investigation into the event is proceeding.
"This event is reportable under 10CFR50.72(b)(2)(iv)(B), any event or condition that results in a valid actuation of the Reactor Protection System; 10CFR50.72(b)(3)(iv)(A), any event that results in an actuation of the specified systems. This event also requires a 60 day written report in accordance with 10CFR50.73(a)(2)(iv)(A).
"The NRC Senior Resident Inspector has been informed of this event."
The sensing line had a flow limiter on it and the line was isolated locally. Amount of leakage not known at this time. | |