| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
07/24/2009 - 07/27/2009 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 45213 | Rep Org: OHIO BUREAU OF RADIATION PROTECTION
Licensee: PETROCHEM INSPECTION SERVICES
Region: 3
City: OREGON State: OH
County:
License #: 03320990001
Agreement: Y
Docket:
NRC Notified By: STEPHEN JAMES
HQ OPS Officer: CHARLES TEAL | Notification Date: 07/21/2009
Notification Time: 08:57 [ET]
Event Date: 06/19/2009
Event Time: [EDT]
Last Update Date: 07/21/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
DAVID HILLS (R3DO)
GLENDA VILLAMAR (FSME)
| Event Text AGREEMENT STATE REPORT - DIFFICULTY RETRIEIVING RADIOGRAPHY SOURCE
The following report was received via email:
"On 6/19/09 at approximately 11:30 a.m., the licensee was unable to retract an industrial radiography source. [The] cause was due to a magnetic positioning device used during operations which fell onto the guide tube, crimping the tube and preventing the source to be retracted to the fully shielded position. [The] device was a QSA Model 660, S/N B2692, with a 91 Curie Ir-192 source, QSA S/N 53932B. No over exposure to personnel or [the] public was reported. [The] source was retrieved into [the] camera by trained personnel within approximately 1/2 hour. [The] licensee revised procedures and conducted refresher training to help prevent similar accidents in the future. ODH [Ohio Department of Health] conducted [an] inspection of [the] job site on 7/1/09. [The] licensee provided [a] written report within [the] 30-day required timeframe. [The] licensee originally thought that this event required a 30-day notice. [The] licensee has been instructed as to the need for 24-hour notification for these events."
Ohio report number: OH090007 |
| General Information or Other | Event Number: 45222 | Rep Org: WISCONSIN RADIATION PROTECTION
Licensee: WHEATON FRANCISCAN HEALTHCARE - ALL SAINTS
Region: 3
City: RACINE State: WI
County:
License #: 101-1299-01
Agreement: Y
Docket:
NRC Notified By: CHRIS TIMMERMAN
HQ OPS Officer: DONALD NORWOOD | Notification Date: 07/22/2009
Notification Time: 16:29 [ET]
Event Date: 07/16/2009
Event Time: [CDT]
Last Update Date: 07/22/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
DAVID HILLS (R3DO)
PATRICE BUBAR (FSME)
| Event Text AGREEMENT STATE REPORT - MULTIPLE EQUIPMENT ISSUES ASSOCIATED WITH HDR BRACHYTHERAPY UNIT
The following is a summary of information received via fax from the State of Wisconsin. For more details contact the Headquarters Operations Officer.
On July 16, 2009, DHS [Department of Health Services] performed a reciprocity inspection at Wheaton Franciscan Healthcare - All Saints for a source exchange of a 10 Ci, Ir-192 source and routine maintenance of a Nucletron Micro Selectron HDR [High Dose Rate] classic remote afterloader brachytherapy device. During the inspection, three items were identified during testing of the HDR unit: 1) HDR control panel did not operate as designed; 2) the HDR/Linac switch was not wired correctly; and 3) Radiation area monitor was operating sporadically.
On July 16, 2009, DHS informed the licensee that they would not be able to use the HDR unit for patient treatments until all areas of concerns were corrected. The licensee informed DHS that the HDR unit has NOT been used for any patient treatments since the Department authorized the licensee the HDR unit on August 8, 2008.
On July 21, 2009, DHS issued the licensee a Confirmatory Action Letter effective July 17, 2009, that the licensee is not allowed to use the HDR unit for patient treatments until the listed items were corrected
The licensee has committed to address all equipment malfunctions prior to treating patients using the Nucleation HDR unit. DHS plans to conduct an inspection prior to patient treatment.
The State does not anticipate any media attention. |
| Power Reactor | Event Number: 45227 | Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: TIMOTHY D. BOLAND
HQ OPS Officer: DONALD NORWOOD | Notification Date: 07/24/2009
Notification Time: 18:50 [ET]
Event Date: 07/24/2009
Event Time: 14:15 [CDT]
Last Update Date: 07/24/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
STEVEN VIAS (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 HPCI INOPERABLE DUE TO OIL LEAK IN MECHANICAL TRIP HOLD VALVE
"During performance of surveillance 1-SR-3.5.1.7, HPCI Main and Booster Pump Set Developed Head and Flow Rate Test at Rated Reactor Pressure, the HPCI Turbine Stop Valve Mechanical Trip Hold Valve, 1-PCV-73-18C, developed an oil leak of approximately 0.25 gpm. HPCI was INOPERABLE at the time of discovery due to performance of SR and continued to be INOPERABLE due to the oil leak that developed.
"This event is reportable within 8 hours in accordance with 10CFR 50.72(b)(3)(v) as an event or condition that at the time of discovery could have prevented the fulfillment of a safety function. It also requires a 60 day written report in accordance with 10CFR 50.73(a)(2)(vii)."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 45228 | Facility: COOK
Region: 3 State: MI
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: SCOTT RICHARDSON
HQ OPS Officer: DONALD NORWOOD | Notification Date: 07/26/2009
Notification Time: 18:44 [ET]
Event Date: 07/26/2009
Event Time: 15:06 [EDT]
Last Update Date: 07/26/2009 | 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):
DAVID HILLS (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | M/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text MANUAL REACTOR TRIP DUE TO A REACTOR COOLANT PUMP SEAL MALFUNCTION
"At 1506 on Sunday, July 26, 2009, the Cook Nuclear Plant (CNP) Unit 2 reactor was manually tripped after the control room staff concluded that the #22 Reactor Coolant Pump (RCP) needed to be promptly secured due to a RCP seal malfunction as indicated by lowering #1 seal leakoff flows and rising #1 seal return and pump radial bearing temperature. This requires a 4-hour report under 10CFR50.72(b)(2)(iv)(B).
"Both motor-driven Auxiliary Feedwater pumps automatically started due to the reactor trip and trip of both Main Feedwater Pumps. The Turbine-Driven Auxiliary Feedwater Pump (TDAFP) started automatically due to low-low water levels in at least two steam generators, which is expected for a reactor trip from approximately full power. The automatic actuation of the reactor protection system and the TDAFP require an 8-hour report under 10CFR50.72(b)(3)(iv)(A).
"All systems functioned as expected after the trip, and no major components were out of service at the time except for the Moisture Separator Reheaters which were not in service since the beginning of the current power cycle.
"The licensee has notified the NRC Senior Resident Inspector."
All control rods fully inserted as required. Electrical system is in normal post-trip lineup. Plant cooldown is via Condenser Steam Dumps using Auxiliary Feedwater pumps. Plant cooldown will continue to Mode 5 (cold shutdown). | |