| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
03/13/2009 - 03/16/2009 ** EVENT NUMBERS ** |
 | Power Reactor | Event Number: 44905 | Facility: PERRY
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: TOM MORSE
HQ OPS Officer: VINCE KLCO | Notification Date: 03/13/2009
Notification Time: 00:42 [ET]
Event Date: 03/13/2009
Event Time: 00:25 [EDT]
Last Update Date: 03/14/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
JULIO LARA (R3)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text PARTIAL LOSS OF PLANT COMPUTER FOR SCHEDULED MAINTENANCE TAKING ERDS OOS
"The Perry Nuclear Power Plant has taken a portion of the Plant Computer out of service for scheduled maintenance. This has resulted in a portion of ERDS being out of service. From 0025 hours EDT on March 13, 2009 for approximately 36 hours, personnel will be performing maintenance activities which result in a partial loss of the Plant Computer. During this planned maintenance, portions of the Safety Parameter Display System (SPDS) and the automatic mode calculation of the Computer Aided Dose Assessment Program (CADAP) will be unavailable.
"In the event of an emergency, plant parameter data will be orally transmitted to the facilities through the Status Board Ring Down circuit with back-up by the Private Branch Exchange, Off Premise Exchange, and various redundant intra-facility circuits throughout the emergency facilities. The dose assessment function will be maintained during the out of service time period by manual input of data into CADAP and, if required, by manual calculation. The ability to open and maintain an 'open line' using the Emergency Notification System will not be affected and will be the primary means of transferring plant data to the NRC as a contingency until the ERDS can be returned to service during the period of unavailability.
"This event is being reported in accordance with 10CFR50.72(b)(3)(xiii), as a condition that results in a major loss of offsite communication capability. A follow-up notification will be made when the maintenance activities are completed and the equipment is restored."
The licensee notified the NRC Resident Inspector.
* * * UPDATE AT 1132 ON 3/14/2009 FROM TONY JARDINE TO MARK ABRAMOVITZ * * *
The plant has extended the expected plant computer outage time by 60 hours (ending 3/16/2009 at 2400).
Notified the R3DO (Lara). |
| Power Reactor | Event Number: 44906 | Facility: ARKANSAS NUCLEAR
Region: 4 State: AR
Unit: [ ] [2] [ ]
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: REX KNIGHT
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 03/14/2009
Notification Time: 02:03 [ET]
Event Date: 03/13/2009
Event Time: 21:51 [CDT]
Last Update Date: 03/14/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
THOMAS FARNHOLTZ (R4)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | M/R | Y | 84 | Power Operation | 0 | Hot Standby | Event Text FEEDWATER REGULATING VALVE FAILURE LEADS TO MANUAL REACTOR TRIP
"At 2151 CDT on 3/13/2009 with plant power at 84% following securing of the 2P-1A Main Feedwater Pump at 1934 due to bearing degradation, Unit 2 experienced a failure of the 'B' Main Feedwater Regulating Valve 2CV-0740 which caused 2E-24B Steam Generator level to lower. At 2151, with 2E-24B Steam Generator level at approximately 25% control room staff manually tripped the reactor anticipating an automatic trip at 22% steam generator level. Emergency Feedwater Actuation System automatically actuated at 22% steam generator level and responded to restore level to the normal post-trip levels. All Control Element Assemblies (rods) Inserted on the reactor trip."
No safeties or relief valves opened after the trip. The plant is in its normal shutdown electrical line-up. Steam generator level is being maintained with emergency feedwater and decay heat is being dumped to the main condenser.
The licensee notified the State of Arkansas and the NRC Resident Inspector. | |