| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
05/28/2013 - 05/29/2013 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 48886 | Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: KELLEY BELENKY
HQ OPS Officer: PETE SNYDER | Notification Date: 04/03/2013
Notification Time: 16:51 [ET]
Event Date: 04/03/2013
Event Time: 10:53 [EDT]
Last Update Date: 05/28/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
ROBERT DALEY (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 65 | Power Operation | 65 | Power Operation | Event Text COOLING WATER MAKEUP PUMP FAILED TO START DURING A SURVEILLANCE TEST
"At 1053 [EDT] on April 3, 2013, during the performance of a surveillance test on the Division 2 Emergency Equipment Cooling Water (EECW) system the EECW system was declared inoperable due to the Division 2 EECW makeup pump failing to start during the surveillance. The EECW system cools various safety related components, including the High Pressure Coolant Injection (HPCI) room cooler.
"A 14 day Limiting Condition for Operation (LCO) was entered for HPCI via [Technical Specification] LCO 3.5.1. Investigation into why the makeup pump did not start is currently in progress.
"This report is being made pursuant to 10 CFR 50.72 (b)(3)(v)(D) as a condition that at the time of discovery could have prevented the fulfillment of a safety function needed to mitigate the consequences of an accident, based on a loss of a single train safety system.
"The NRC Resident Inspector has been notified."
* * * UPDATE FROM BRETT JEBBIA TO VINCE KLCO ON 5/28/13 AT 1613 EDT * * *
"An evaluation of Event 48886 has determined that the Division 2 Emergency Cooling Water (EECW) system was capable of supporting HPCI Room Cooler and HPCI operation for a period of time in excess of that required to perform the required safety functions as assumed in the accident analysis. Therefore, this event is retracted."
The licensee notified the NRC Resident Inspector. Notified the R3DO (Orth). |
| Power Reactor | Event Number: 49073 | Facility: MILLSTONE
Region: 1 State: CT
Unit: [1] [2] [ ]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: STEPHAN LAMBERT
HQ OPS Officer: BILL HUFFMAN | Notification Date: 05/28/2013
Notification Time: 10:32 [ET]
Event Date: 05/28/2013
Event Time: 10:06 [EDT]
Last Update Date: 05/28/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
DANIEL HOLODY (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Decommissioned | 0 | Decommissioned | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text RADIATION MONITORS OUT OF SERVICE FOR PLANNED MAINTENANCE
The Station Stack Radiation Monitor, RM-8169, and the Unit 1 Spent Fuel Pool Island Rad Monitor have been removed from service for preplanned maintenance for filter change out. During this time period, the licensee will not have normal assessment capability for radiation releases via these pathways. Compensatory monitoring methods are in place for the duration of the maintenance activity.
The radiation monitors will be restored upon completion of the filter change-out. The expected completion time is before the end of day shift on 5/28/13.
The licensee has notified the NRC Resident Inspector along with state and local authorities. |
| Power Reactor | Event Number: 49074 | Facility: HARRIS
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: RAYMOND MOORE
HQ OPS Officer: JOHN SHOEMAKER | Notification Date: 05/28/2013
Notification Time: 11:36 [ET]
Event Date: 05/28/2013
Event Time: 10:52 [EDT]
Last Update Date: 05/28/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
| Person (Organization):
ALAN BLAMEY (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text LOSS OF REDUNDANT ASSESSMENT CAPABILITY
"Loss of one of two National Weather Service (NOAA) Tone Alert Radio Transmitters.
"This is a non-emergency notification.
"At 10:52 AM EDT on May 28, 2013, the National Weather Service reported that they plan to remove the National Weather Service (NOAA) Tone Alert Radio Transmitter, WXL-58 located in Chapel Hill, NC., serving the northeast piedmont on 162.550 MHZ, from service maintenance. The maintenance is expected to last 4 hours. The purpose of the National Weather Service (NOAA) Tone Alert Radio transmitters is a redundant means to the 83 Harris Nuclear Plant Emergency Sirens to warn the public within the 5 mile radius of the plant of an actual event. The 83 Harris Nuclear Plant Emergency Sirens are in service and fully functional to alert the public within the 5 mile radius of the plant of an actual event should an event occur.
"There is no impact to public health and safety due to this condition.
"The NRC Resident has been notified."
* * * UPDATE FROM RAYMOND MOORE TO CHARLES TEAL AT 1420 EDT ON 5/28/13 * * *
At 1415 EDT on 5/28/13 the Tone Alert Radio Transmitter WXL-58 was returned to service.
The licensee will notify the NRC Resident Inspector. Notified R2DO (Bonser). |
| Power Reactor | Event Number: 49075 | Facility: NORTH ANNA
Region: 2 State: VA
Unit: [ ] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP,[3] M-4-LP
NRC Notified By: PAGE KEMP
HQ OPS Officer: VINCE KLCO | Notification Date: 05/28/2013
Notification Time: 18:09 [ET]
Event Date: 05/28/2013
Event Time: 15:07 [EDT]
Last Update Date: 05/28/2013 | 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):
BRIAN BONSER (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | M/R | Y | 98 | Power Operation | 0 | Hot Standby | Event Text MANUAL REACTOR TRIP DUE TO A FEEDWATER TRANSIENT
"On May 28, 2013, at 1507 [EDT], Unit 2 was manually tripped from approximately 98 percent power due to decreasing steam generator levels as a result of a main feedwater system transient. The main feedwater system transient was initiated when the 'C' Main Feedwater Pump Discharge Motor-Operated Valve, 2-FW-MOV-250C, spuriously closed. The cause of the spurious closure of 2-FW-MOV-250C is unknown at this time.
"The Operations crew entered the reactor trip procedure and stabilized Unit 2 in Mode 3 at normal operating temperature and pressure. All control rods fully inserted into the core following the reactor trip. The reactor protection system actuation is reportable per 10CFR50.72(b)(2)(iv)(B). The Auxiliary Feedwater (AFW) pumps actuated as designed as a result of the reactor trip and provided makeup flow to the steam generators. The automatic start of the AFW system is reportable per 10CFR50.72 (b)(3)(iv)(A) for a valid actuation of an ESF system. The AFW pumps were subsequently secured and returned to automatic. Decay heat is being removed by the condenser steam dump system. Unit 2 is in the normal shutdown electrical line-up.
"Unit 1 was not affected by this event."
The licensee notified the NRC Resident Inspector. | |