Event Notification Report for September 07, 2008
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
09/06/2008 - 09/07/2008
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 44470
Facility: DRESDEN
Region: 3 State: IL
Unit: [] [2] []
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: GLEN MORROW
HQ OPS Officer: STEVE SANDIN
Region: 3 State: IL
Unit: [] [2] []
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: GLEN MORROW
HQ OPS Officer: STEVE SANDIN
Notification Date: 09/07/2008
Notification Time: 14:45 [ET]
Event Date: 09/07/2008
Event Time: 08:05 [CDT]
Last Update Date: 10/31/2008
Notification Time: 14:45 [ET]
Event Date: 09/07/2008
Event Time: 08:05 [CDT]
Last Update Date: 10/31/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
Person (Organization):
RICHARD SKOKOWSKI (R3)
RICHARD SKOKOWSKI (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 67 | Power Operation | 67 | Power Operation |
ISOLATION CONDENSER DECLARED INOPERABLE FOLLOWING SURVEILLANCE TESTING
"Unit 2 Isolation Condenser did not meet acceptance criteria per DOS 1300-01 Isolation Condenser 5 year heat removal capability test. This is a single train system and cannot fulfill its safety function. The Isolation Condenser is a single train system. The function of the IC System is to respond to main steam SAFETY ANALYSES line isolation events by providing core cooling to the reactor. The IC System is an Engineered Safety Feature System, and credit is taken in the loss of feedwater transient analysis for IC System operation."
Unit 2 entered a 14-day TS LCO A/S 3.5.3 at 0249 CDT on 09/07/08 after declaring the IC System Inoperable. The Action Statement (A/S) requires restoration of the IC System to Operable status within 14 days or place the unit in hot shutdown within 12 hrs followed by entry into cold shutdown in the following 24 hrs. The licensee is performing maintenance to adjust the cooling flow valve stroke time in order to re-test and exit the LCO A/S.
The licensee informed the NRC Resident Inspector.
* * * UPDATE AT 1318 EDT ON 10/31/08 FROM SCOTT BRILEY TO S. SANDIN * * *
The licensee is retracting this report based on the following:
"The purpose of this notification is to retract ENS notification 44470 made on September 7, 2008 for Dresden Nuclear Power Station. After further evaluation, Dresden has determined that the Isolation Condenser did successfully pass its 5-year heat removal test on September 7, 2008. The evaluation corrected the steam flow rate based on a more accurate instrument and calculated the heat removal rate by multiplying the mass flow rate through the Isolation Condenser times the difference in enthalpy between the steam going to the condenser and the condensate leaving the condenser. Therefore, the Isolation Condenser was capable of performing its safety function and the ENS report is being retracted."
The licensee informed the NRC Resident Inspector. Notified R3DO (Kozak).
"Unit 2 Isolation Condenser did not meet acceptance criteria per DOS 1300-01 Isolation Condenser 5 year heat removal capability test. This is a single train system and cannot fulfill its safety function. The Isolation Condenser is a single train system. The function of the IC System is to respond to main steam SAFETY ANALYSES line isolation events by providing core cooling to the reactor. The IC System is an Engineered Safety Feature System, and credit is taken in the loss of feedwater transient analysis for IC System operation."
Unit 2 entered a 14-day TS LCO A/S 3.5.3 at 0249 CDT on 09/07/08 after declaring the IC System Inoperable. The Action Statement (A/S) requires restoration of the IC System to Operable status within 14 days or place the unit in hot shutdown within 12 hrs followed by entry into cold shutdown in the following 24 hrs. The licensee is performing maintenance to adjust the cooling flow valve stroke time in order to re-test and exit the LCO A/S.
The licensee informed the NRC Resident Inspector.
* * * UPDATE AT 1318 EDT ON 10/31/08 FROM SCOTT BRILEY TO S. SANDIN * * *
The licensee is retracting this report based on the following:
"The purpose of this notification is to retract ENS notification 44470 made on September 7, 2008 for Dresden Nuclear Power Station. After further evaluation, Dresden has determined that the Isolation Condenser did successfully pass its 5-year heat removal test on September 7, 2008. The evaluation corrected the steam flow rate based on a more accurate instrument and calculated the heat removal rate by multiplying the mass flow rate through the Isolation Condenser times the difference in enthalpy between the steam going to the condenser and the condensate leaving the condenser. Therefore, the Isolation Condenser was capable of performing its safety function and the ENS report is being retracted."
The licensee informed the NRC Resident Inspector. Notified R3DO (Kozak).
Power Reactor
Event Number: 44471
Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [1] [2] [3]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: TIM BOLAND
HQ OPS Officer: STEVE SANDIN
Region: 2 State: AL
Unit: [1] [2] [3]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: TIM BOLAND
HQ OPS Officer: STEVE SANDIN
Notification Date: 09/07/2008
Notification Time: 23:12 [ET]
Event Date: 09/07/2008
Event Time: 17:20 [CDT]
Last Update Date: 09/07/2008
Notification Time: 23:12 [ET]
Event Date: 09/07/2008
Event Time: 17:20 [CDT]
Last Update Date: 09/07/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
REBECCA NEASE (R2)
REBECCA NEASE (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
| 3 | N | Y | 100 | Power Operation | 100 | Power Operation |
PARTIAL LOSS OF OFFSITE COMMUNICATION CAPABILITY CAUSED BY AN UNPLANNED POWER OUTAGE
"On 09/07/2008 at 1720 CDT, Browns Ferry Nuclear Plant experienced a partial loss of offsite communication to include the Emergency Notification System to the NRC, normal phone communication to offsite, the Operations Duty Specialist ring down phone to Chattanooga and the satellite phone to offsite located in the control room. This loss of communications was the result of an unplanned electrical power outage due to loss of temporary diesel generator supplying power to the communications network. The control room indications and assessment capability were not affected. Cell phones and the Health Physics Radio Network were available to be used onsite to communicate offsite. The plant radio system and sound powered phones were unaffected and plant staff communication capability was available.
"Communication capability was restored at 1758 CDT 09/07/2008.
"Operation of Unit 1, Unit 2 and Unit 3 was not affected by the event.
"The NRC Sr. Resident Inspector has been notified.
"This event is reportable under 10CFR50.72(b)(3)(xiii), 'Any event that results in a major loss of emergency assessment capability, offsite response capability, or offsite communications capability (e.g., significant portion of control room indication, Emergency Notification System or offsite notification system.'"
"On 09/07/2008 at 1720 CDT, Browns Ferry Nuclear Plant experienced a partial loss of offsite communication to include the Emergency Notification System to the NRC, normal phone communication to offsite, the Operations Duty Specialist ring down phone to Chattanooga and the satellite phone to offsite located in the control room. This loss of communications was the result of an unplanned electrical power outage due to loss of temporary diesel generator supplying power to the communications network. The control room indications and assessment capability were not affected. Cell phones and the Health Physics Radio Network were available to be used onsite to communicate offsite. The plant radio system and sound powered phones were unaffected and plant staff communication capability was available.
"Communication capability was restored at 1758 CDT 09/07/2008.
"Operation of Unit 1, Unit 2 and Unit 3 was not affected by the event.
"The NRC Sr. Resident Inspector has been notified.
"This event is reportable under 10CFR50.72(b)(3)(xiii), 'Any event that results in a major loss of emergency assessment capability, offsite response capability, or offsite communications capability (e.g., significant portion of control room indication, Emergency Notification System or offsite notification system.'"