Event Notification Report for November 22, 2010
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
11/21/2010 - 11/22/2010
Power Reactor
Event Number: 46431
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: DAVID BARNETT
HQ OPS Officer: DONALD NORWOOD
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: DAVID BARNETT
HQ OPS Officer: DONALD NORWOOD
Notification Date: 11/22/2010
Notification Time: 23:32 [ET]
Event Date: 11/22/2010
Event Time: 17:47 [CST]
Last Update Date: 11/22/2010
Notification Time: 23:32 [ET]
Event Date: 11/22/2010
Event Time: 17:47 [CST]
Last Update Date: 11/22/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
BILLY DICKSON (R3DO)
BILLY DICKSON (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Startup | 0 | Startup |
VALVES IDENTIFIED OPEN IN MODE 2 THAT SHOULD HAVE BEEN CLOSED
"At 1547 CST, November 22, 2010, the reactor mode was changed from Mode 4 to Mode 2 with the main steam drain valves, which are primary containment isolation valves, tagged open with power removed from their respective breakers. The valves were tagged to comply with S/D [Shutdown] operating procedure requirements. The valves should have been restored prior to making the mode change. The main steam line drain isolation valves MO-2373 and MO-2374 were restored at 1747 CST and verified at 1755 CST. Startup was held for determination of further actions needed. Reactor startup recommenced at 2200 CST. Currently the reactor is not critical."
The licensee notified the NRC Resident Inspector. The licensee notified the Minnesota State Duty Officer.
"At 1547 CST, November 22, 2010, the reactor mode was changed from Mode 4 to Mode 2 with the main steam drain valves, which are primary containment isolation valves, tagged open with power removed from their respective breakers. The valves were tagged to comply with S/D [Shutdown] operating procedure requirements. The valves should have been restored prior to making the mode change. The main steam line drain isolation valves MO-2373 and MO-2374 were restored at 1747 CST and verified at 1755 CST. Startup was held for determination of further actions needed. Reactor startup recommenced at 2200 CST. Currently the reactor is not critical."
The licensee notified the NRC Resident Inspector. The licensee notified the Minnesota State Duty Officer.
General Information
Event Number: 46449
Rep Org: ROSEMOUNT NUCLEAR
Licensee: ROSEMOUNT NUCLEAR
Region: 3
City: CHANHASSEN State: MN
County:
License #:
Agreement: Y
Docket:
NRC Notified By: MARC BUMGARNER
HQ OPS Officer: JOE O'HARA
Licensee: ROSEMOUNT NUCLEAR
Region: 3
City: CHANHASSEN State: MN
County:
License #:
Agreement: Y
Docket:
NRC Notified By: MARC BUMGARNER
HQ OPS Officer: JOE O'HARA
Notification Date: 12/02/2010
Notification Time: 20:15 [ET]
Event Date: 11/22/2010
Event Time: 00:00 [CST]
Last Update Date: 12/02/2010
Notification Time: 20:15 [ET]
Event Date: 11/22/2010
Event Time: 00:00 [CST]
Last Update Date: 12/02/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
Person (Organization):
WAYNE SCHMIDT (R1DO)
SCOTT SHAEFFER (R2DO)
MARK RING (R3DO)
DALE POWERS (R4DO)
PART 21 GRP
WAYNE SCHMIDT (R1DO)
SCOTT SHAEFFER (R2DO)
MARK RING (R3DO)
DALE POWERS (R4DO)
PART 21 GRP
ANOLMALY DISCOVERED ON ROSEMOUNT MODEL 1152 DIFFERENTIAL PRESSURE TRANSMITTERS WITH OUTPUT CODE "L" 10-50 mA ELECTRONICS
The following was received via fax:
Rosemount Nuclear discovered an anomaly in Model 1152 differential pressure transmitters while troubleshooting a separate, unrelated issue. The anomaly is related to the pressure transmitters response during a overpressure condition. Normally, under a low side overpressure condition, the output will go off-scale and remain off scale for conditions less than 10 mA. Rosemount has discovered that some detectors may go off-scale and then return to on-scale between 10mA and 50 mA, rather than remain off scale under 10mA. This is caused by a change made to operational amplifier components in March 2001. Rosemount recommends all customers evaluate the safety impact of this anomaly on their plants. No field failures have been reported to date.
The following sites are affected: Browns Ferry, Brunswick, Cook, Dresden, Duane Arnold, Fermi, Fort Calhoun, Ginna, Hatch, Indian Point, Kewaunee, Millstone, Nine Mile Point, Oyster Creek, Palisades, Pilgrim, Quad Cities, Sequoyah, Vermont Yankee, and Watts Bar.
The following was received via fax:
Rosemount Nuclear discovered an anomaly in Model 1152 differential pressure transmitters while troubleshooting a separate, unrelated issue. The anomaly is related to the pressure transmitters response during a overpressure condition. Normally, under a low side overpressure condition, the output will go off-scale and remain off scale for conditions less than 10 mA. Rosemount has discovered that some detectors may go off-scale and then return to on-scale between 10mA and 50 mA, rather than remain off scale under 10mA. This is caused by a change made to operational amplifier components in March 2001. Rosemount recommends all customers evaluate the safety impact of this anomaly on their plants. No field failures have been reported to date.
The following sites are affected: Browns Ferry, Brunswick, Cook, Dresden, Duane Arnold, Fermi, Fort Calhoun, Ginna, Hatch, Indian Point, Kewaunee, Millstone, Nine Mile Point, Oyster Creek, Palisades, Pilgrim, Quad Cities, Sequoyah, Vermont Yankee, and Watts Bar.