| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
04/04/2006 - 04/05/2006 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 42446 | Facility: MCGUIRE
Region: 2 State: NC
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: FRED KIRK
HQ OPS Officer: STEVE SANDIN | Notification Date: 03/23/2006
Notification Time: 18:20 [ET]
Event Date: 03/23/2006
Event Time: 12:50 [EST]
Last Update Date: 04/04/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
| Person (Organization):
CAROLYN EVANS (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 99 | Power Operation | | 2 | N | Y | 100 | Power Operation | 99 | Power Operation | Event Text 24-HOUR CONDITION OF LICENSE REPORT DUE TO THERMAL POWER POTENTIALLY EXCEEDING LICENSED LIMIT
"McGuire Unit 1 and Unit 2 may have been operating greater than design thermal power limits of 3411 MW [Megawatt] by approximately 0.08% due to discovery of non-conservative thermal power calculations. Preliminary evaluation of Steam Generator Blow Down inputs into the thermal power calorimetric indicates a non-conservative error resulting in indicated total thermal power being approximately 0.08% lower than actual. Additional evaluations to confirm indicated power are ongoing. Power was reduced as soon as the on duty shift was made aware of the error and both Unit 1 and Unit 2 indicated thermal power is being limited to less than 99.85% to ensure actual reactor power remains less than 3411 MW.
"This notification is being made pursuant to the McGuire Facility Operating License Condition 2.C.(1) Maximum Power Level."
The licensee will inform the NRC Resident Inspector.
* * * UPDATE AT 09:17 ON 4/4/2006 FROM REZA DJALI TO ABRAMOVITZ * * *
"McGuire Nuclear Station is retracting event number 42446 which was reported to the NRC Operations Center on 3/23/06 at 1820. This event is now determined to be not reportable because further analyses of plant parameters, engineering margins, and actual plant power operation history indicated that neither Unit 1 nor Unit 2 exceeded 3411 megawatt thermal. The analyses and the bases for this retraction can be found under the plant corrective action program."
Notified the R2DO (Bonser). The licensee notified the NRC Resident Inspector. |
| General Information or Other | Event Number: 42460 | Rep Org: UTAH DIVISION OF RADIATION CONTROL
Licensee: ALPHA TESTING LABS, LC
Region: 4
City: SANDY State: UT
County:
License #: UT 1800485
Agreement: Y
Docket:
NRC Notified By: JULIE FELICE
HQ OPS Officer: JEFF ROTTON | Notification Date: 03/31/2006
Notification Time: 16:27 [ET]
Event Date: 02/23/2006
Event Time: 09:15 [MST]
Last Update Date: 03/31/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
DALE POWERS (R4)
LAWRENCE KOKAJKO (NMSS)
| Event Text AGREEMENT STATE REPORT - MALFUNCTIONING RADIOGRAPHY CAMERA
The State provided the following information via facsimile:
"This event involved a crank cable for a Source Production & Equipment Company radiographic exposure device (model SPEC 150, serial number 876; with sealed source model SPEC G-60, serial number ML0608). The activity contained in the radiographic exposure device at the time of the incident was 2.66 terabecquerels (72 Ci). A crimped fitting on the crank cable housing came loose when a radiographer was moving the radiographic exposure device. The source was in the shielded position at all times when it was being moved. No source disconnect occurred. The cause of this incident is not known since the equipment had been functioning until this incident. The licensee believes it to be a manufacturing problem. When the incident occurred, radiographic operations were immediately stopped. And the radiography crew (radiographer, radiographer's assistant, and Radiation Safety Officer) returned to the licensee's Utah facilities. The control cable was tagged out of operation until a new housing could be obtained from the manufacturer.
"The Utah Division of Radiation Control was notified by the licensee in a letter dated March 23, 2006 (received on March 29, 2006).
"The licensee notified the manufacturer and the malfunctioning equipment was returned. It was immediately replaced with a new cable housing.
"Event Location: Structural Steel & Plate Fabrication, 555 N. Main, North Salt Lake, Utah 84054"
Utah Event Report ID No. : UT-06-0001 |
| General Information or Other | Event Number: 42464 | Rep Org: MARYLAND DEPT OF THE ENVIRONMENT
Licensee: GEOTECH LAB INC
Region: 1
City: COLUMBIA State: MD
County:
License #: MD-27-075-01
Agreement: Y
Docket:
NRC Notified By: BOB NELSON
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 04/01/2006
Notification Time: 00:12 [ET]
Event Date: 03/31/2006
Event Time: 16:00 [EST]
Last Update Date: 04/01/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
LAWRENCE KOKAJKO (NMSS)
WILLIAM COOK (R1)
| Event Text AGREEMENT STATE REPORT: DAMAGED TROXLER
A Troxler moisture density gauge was left unattended at a site in Clinton, Maryland and was run over by a bulldozer. The Troxler was broken in two parts. No external contamination was detected and the source was in the shielded position. Troxler Model 3430, serial #23881.
Sources:
8 milliCurie Cs-137
40 milliCurie Am-241:Be |
| Hospital | Event Number: 42469 | Rep Org: INDIANA UNIVERSITY MEDICAL CENTER
Licensee: INDIANA UNIVERSITY MEDICAL CENTER
Region: 3
City: INDIANAPOLIS State: IN
County:
License #: 13-02752-03
Agreement: N
Docket:
NRC Notified By: JEFFREY MASON
HQ OPS Officer: STEVE SANDIN | Notification Date: 04/03/2006
Notification Time: 12:56 [ET]
Event Date: 01/17/2005
Event Time: 12:00 [CST]
Last Update Date: 04/04/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
35.3045(a)(1) - DOSE <> PRESCRIBED DOSAGE
| Person (Organization):
ANNE MARIE STONE (R3)
GREG MORELL (NMSS)
| Event Text MEDICAL EVENT INVOLVING DELIVERED DOSE LESS THAN THE PRESCRIBED DOSE
During a review of patient's records, the licensee identified a patient who received a delivered dose of 6,885 Centigray vice the prescribed dose of 8,196 Centigray using an ovoid applicator. The incident occurred on 1/17/05 and was discovered following a similar incident reported on 03/30/06 (see EN #42453). Both the referring physician and patient have been informed. There is indication or requirement for additional treatment at this time. The licensee discussed this incident with R3 (Gattone).
* * * UPDATE AT 11:44 ON 4/4/2006 FROM JEFF MASON TO ABRAMOVITZ * * *
The doses are being revised by the System RSO as:
prescribed: 2500 centigray
actual dose: 1203 centigray
Notified NMSS (Morell) and the R3DO (Stone). |
| Power Reactor | Event Number: 42471 | Facility: HATCH
Region: 2 State: GA
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: BARRY COLEMAN
HQ OPS Officer: BILL HUFFMAN | Notification Date: 04/05/2006
Notification Time: 02:22 [ET]
Event Date: 04/05/2006
Event Time: 00:16 [EDT]
Last Update Date: 04/05/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(2)(iv)(A) - ECCS INJECTION
| Person (Organization):
BRIAN BONSER (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | A/R | Y | 100 | Power Operation | 0 | Hot Shutdown | Event Text REACTOR SCRAM FOLLOWING MAIN TURBINE CONTROL VALVE FAST CLOSURE
"Two I & C technicians were performing a 24 month calibration on 2S32R017, Megavar & Voltmeter Recorder in accordance with 57CP-CAL-010-2, Esterline Angus Megavar & KV Recorder. This activity was being performed on Work Order 2042825001. At the approximate time the recorder was being removed from service the shift received a RPS trip from a MTCV [Main Turbine Control Valve] Fast Closure. The control valve fast closure scram was caused by a power load imbalance. Both RFP's [Reactor Feed Pumps] tripped on high reactor water level and RCIC and HPCI were used (for 7 and 2 minutes respectively) to control RWL [Reactor Water Level]. Eight SRV's [Safety Relief Valves] opened momentarily on high reactor pressure. The highest reactor pressure indicated was 1120 psig and the lowest RWL indicated was +7 inches. A main condenser vacuum transient due to loss of seals required use of HPCI and RCIC."
The licensee characterized the scram as uncomplicated. All systems functioned as required and nothing unusual or not understood besides what caused the initial power load unbalance signal and resulting MTCV fast closure. All rods fully inserted. The unit is currently at normal pressure and water level for Mode 3. MSIVs remained opened and decay heat is being discharged to the main condenser. The scram had no impact on Unit 1 and offsite on onsite electrical conditions remained normal. The licensee was not in any significant LCOs at the time of the event.
The licensee notified the NRC Resident Inspector. | |