| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
03/09/2012 - 03/12/2012 ** EVENT NUMBERS ** |
 | Non-Agreement State | Event Number: 47719 | Rep Org: CAMDEN CLARK MEMORIAL HOSPITAL
Licensee: CAMDEN CLARK MEMORIAL HOSPITAL
Region: 1
City: PARKERSBURG State: WV
County: WOOD
License #: 47-09772-02
Agreement: N
Docket:
NRC Notified By: DAN BERKLEY
HQ OPS Officer: ERIC SIMPSON | Notification Date: 03/05/2012
Notification Time: 16:17 [ET]
Event Date: 02/25/2011
Event Time: 12:00 [EST]
Last Update Date: 03/05/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
35.3045(a)(1) - DOSE <> PRESCRIBED DOSAGE
| Person (Organization):
LAWRENCE DOERFLEIN (R1DO)
KEVIN O'SULLIVAN (FSME)
| Event Text DOSE RECEIVED BY PROSTATE LESS THAN PRESCRIBED
At the request of NRC Region I, Camden-Clark Memorial Hospital reassessed records from a prostate radioactive seed implantation procedure that had been performed on February 25, 2011. The record review indicated that the patient had received roughly 80 percent of the prescribed dose.
"The effect on the patient has been minimal as the desired response was achieved. The long term effect will be under constant follow-up.
"The entire implant process will be reviewed with special attention to real time seed placement and subsequent thirty day image evaluation with respect to NRC regulatory guidelines.
"The attending physician, based on medical judgment, felt that notifying the patient would be harmful. The patient is under the care of oncologic physicians and will be followed appropriately as per his disease type."
A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient. |
| Power Reactor | Event Number: 47728 | Facility: DIABLO CANYON
Region: 4 State: CA
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DAVID BAHNER
HQ OPS Officer: BILL HUFFMAN | Notification Date: 03/09/2012
Notification Time: 19:17 [ET]
Event Date: 03/08/2012
Event Time: 18:50 [PST]
Last Update Date: 03/09/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
INFORMATION ONLY
| Person (Organization):
JACK WHITTEN (R4DO)
PART 21 GROUP ()
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text INOPERABLE STEAM GENERATOR NARROW RANGE LEVEL TRANSMITTERS DUE TO PART 21 CONCERN
"Pacific Gas and Electric (PG&E) is supplying this information as a voluntary report. On March 8, 2012, at 1850 PST, Diablo Canyon Power Plant (DCPP), Unit 1, declared the steam generator (SG) 1-1 narrow-range, low-low, water level channels for level transmitters LT-517 and LT-519 inoperable. This resulted from DCPP determining that the low-low setpoints were non-conservative as a result of its evaluation of the Rosemount Nuclear's 10 CFR Part 21 notification titled 'Notification Under 10 CFR Part 21 on Certain Rosemount Model 1154 Series H Pressure Transmitters,' dated March 2, 2012.
"PG&E determined that the following SG narrow-range level transmitters having reactor protection and emergency safeguards actuation functions are affected:
Unit 1:
- two channels on SG 1-1
- one channel each on SGs 1-2 and 1-4
Unit 2:
- one channel each on SGs 2-1, 2-2, 2-3 and 2-4
"The Part 21 notification identified that the high temperature/pressure accuracy specification changed for certain transmitters which have higher impedance resistors installed in their temperature compensation circuitry. PG&E's evaluation concluded that narrow range SG low-low level setpoint uncertainty increased by as much as 2 percent of span due to the revised specification. Under the most limiting conditions, this deficiency could result in a short delay in relay actuation.
"At 1953 PST, DCPP personnel declared the LT-517 and LT-519 water level low-low channels for SG 1-1 to be operable after adjusting the low-low setpoints from 15 percent to 17 percent on SG 1-1. DCPP also changed the low-low setpoints on SG 1-2 and SG 1-4 on March 8, 2012, and is changing this setpoint on all four of the Unit 2 SGs.
"PG&E plans to submit a Licensee Event Report on this issue.
"Plant personnel notified the NRC Resident Inspector." |
| Power Reactor | Event Number: 47729 | Facility: HARRIS
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: NEIL MACARTHUR
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 03/09/2012
Notification Time: 19:48 [ET]
Event Date: 03/09/2012
Event Time: 14:00 [EST]
Last Update Date: 03/09/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
GEORGE HOPPER (R2DO)
|
| 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 FAILURE OF A TECHNICAL SUPPORT CENTER AIR HANDLING UNIT
"At approximately 14:00 on March 9, 2012, with the Harris Nuclear Plant operating at 100% power in mode 1, Air Handler 17 was discovered not operating. Air Handler 17 provides ventilation supporting environmental habitability to the Technical Support Center (TSC) to keep ambient temperatures comfortable for personnel and to ensure communications and assessment equipment remain functional. This degrades the heating and cooling capacity of the TSC by approximately a third. Due to the cool weather in the forecast, the remaining cooling systems will be operating more efficiently than they would in the hot summer months, which mitigates the impact of the degraded ventilation system. The system will be repaired expeditiously. The cause of the equipment failure is not yet known but will be investigated in the site corrective action program. This report is being made in accordance with 10 CFR 50.72, criterion (b)(3)(xiii) as a condition that may impair the functionality of an Emergency Response Facility. The plant continues to operate at 100%. Other equipment functioned as expected. The on call Emergency Response Manager and Site Emergency Coordinator (TSC) have been notified and the alternate TSC is available."
The licensee notified the NRC Resident Inspector. | |