Event Notification Report for March 14, 2013
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/13/2013 - 03/14/2013
Power Reactor
Event Number: 48822
Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: BILL BALL
HQ OPS Officer: STEVE SANDIN
Region: 2 State: AL
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: BILL BALL
HQ OPS Officer: STEVE SANDIN
Notification Date: 03/14/2013
Notification Time: 09:50 [ET]
Event Date: 03/14/2013
Event Time: 08:00 [CDT]
Last Update Date: 03/14/2013
Notification Time: 09:50 [ET]
Event Date: 03/14/2013
Event Time: 08:00 [CDT]
Last Update Date: 03/14/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
KATHLEEN O'DONOHUE (R2DO)
KATHLEEN O'DONOHUE (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 85 | Power Operation | 80 | Power Operation |
UNIT 2 SHUTDOWN REQUIRED BY TECHNICAL SPECIFICATIONS DUE TO INOPERABLE RCIC
"At 0300 [CDT] on 3/02/2013, radiography results for the U2 [Unit 2] RCIC [Reactor Core Isolation Cooling] system stop-check valve 2-HCV-71-14 showed this valve to be in the fully open position thus, not meeting the acceptance criteria of 2-SI-3.2.3 (Testing ASME Section XI Check Valves). This valve is the RCIC turbine exhaust stop-check valve. It is one of two PCIVs [Primary Containment Isolation Valves] connecting RCIC directly to primary containment. TS [Technical Specification] 3.6.1.3 (PCIVs) Condition 'A' was entered. In order to comply with TS 3.6.1.3 Condition 'A', the RCIC system was required to be isolated to prevent flow through the RCIC turbine exhaust check valve 2-CKV-71-0580. This valve is the upstream RCIC turbine exhaust line PCIV. 2-FCV-71-003, RCIC Steam Line Outboard Isolation valve, was closed and deactivated to meet TS 3.6.1.3 (PCIV) Condition 'A' at 0525 [CDT] on 03/02/2013. This resulted in RCIC being unable to auto initiate and required U2 to enter TS 3.5.3 (RCIC System) Condition 'A', which requires RCIC to be returned to service within 14 days. Because valve 2-HCV-71-14 is unisolable to primary containment, a unit S/D [Shutdown] is required to perform repairs. The RCIC TS LCO [Limiting Condition for Operation] 3.5.3 requires that U2 be in MODE 3 by 1725 [CDT] on 03/16/2013 and <150psig by 1725 [CDT] on 03/17/2013.
"Action to initiate Reactor S/D was taken on 03/14/2013 at 0800 [CDT]."
The licensee informed the NRC Resident Inspector.
"At 0300 [CDT] on 3/02/2013, radiography results for the U2 [Unit 2] RCIC [Reactor Core Isolation Cooling] system stop-check valve 2-HCV-71-14 showed this valve to be in the fully open position thus, not meeting the acceptance criteria of 2-SI-3.2.3 (Testing ASME Section XI Check Valves). This valve is the RCIC turbine exhaust stop-check valve. It is one of two PCIVs [Primary Containment Isolation Valves] connecting RCIC directly to primary containment. TS [Technical Specification] 3.6.1.3 (PCIVs) Condition 'A' was entered. In order to comply with TS 3.6.1.3 Condition 'A', the RCIC system was required to be isolated to prevent flow through the RCIC turbine exhaust check valve 2-CKV-71-0580. This valve is the upstream RCIC turbine exhaust line PCIV. 2-FCV-71-003, RCIC Steam Line Outboard Isolation valve, was closed and deactivated to meet TS 3.6.1.3 (PCIV) Condition 'A' at 0525 [CDT] on 03/02/2013. This resulted in RCIC being unable to auto initiate and required U2 to enter TS 3.5.3 (RCIC System) Condition 'A', which requires RCIC to be returned to service within 14 days. Because valve 2-HCV-71-14 is unisolable to primary containment, a unit S/D [Shutdown] is required to perform repairs. The RCIC TS LCO [Limiting Condition for Operation] 3.5.3 requires that U2 be in MODE 3 by 1725 [CDT] on 03/16/2013 and <150psig by 1725 [CDT] on 03/17/2013.
"Action to initiate Reactor S/D was taken on 03/14/2013 at 0800 [CDT]."
The licensee informed the NRC Resident Inspector.
Power Reactor
Event Number: 48823
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 TAYLOR
HQ OPS Officer: VINCE KLCO
Region: 2 State: AL
Unit: [1] [2] [3]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: TIM TAYLOR
HQ OPS Officer: VINCE KLCO
Notification Date: 03/15/2013
Notification Time: 01:48 [ET]
Event Date: 03/14/2013
Event Time: 18:00 [CDT]
Last Update Date: 03/15/2013
Notification Time: 01:48 [ET]
Event Date: 03/14/2013
Event Time: 18:00 [CDT]
Last Update Date: 03/15/2013
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):
KATHLEEN O'DONOHUE (R2DO)
KATHLEEN O'DONOHUE (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 |
| 2 | N | Y | 23 | Power Operation | 23 | Power Operation |
| 3 | N | Y | 100 | Power Operation | 100 | Power Operation |
PARTIAL LOSS OF OFFSITE COMMUNICATIONS
"On 03/14/2013 at 1800 CDT, Browns Ferry Nuclear Plant experienced a partial loss of offsite communication to include the Emergency Notification System to the NRC and normal phone communication to offsite. This loss of communications appears to be the result of an unplanned degraded voltage condition on the 48VDC Telephone Battery supplying power to the communications network. Main Control Room indications and assessment capability were not affected. The Nextel cellular phone system, the satellite phones in the Control Rooms, and the Health Physics Radio Network were available onsite to communicate offsite. The plant radio system was also unaffected. Required corrective maintenance is being evaluated. Communication capability is being periodically restored during maintenance troubleshooting, but has not yet been permanently corrected. Operation of Unit 1, Unit 2, and Unit 3 was not affected by the event.
"At 2145 CDT, the NRC Operations Center was notified of alternate contact numbers for [Browns Ferry] until the Telephone Battery is fully restored.
"The NRC Senior Resident Inspector has been notified.
"This event is reportable under 10CFR50.72(b)(3)(xiii)."
* * * UPDATE FROM CHRISTMAN TO KLCO ON 3/15/13 AT 0330EDT * * *
A spare battery charger was aligned to the 48 VDC Telephone Battery and offsite communications was restored.
The licensee notified the NRC Resident Inspector. Notified the R2DO (O'Donohue).
"On 03/14/2013 at 1800 CDT, Browns Ferry Nuclear Plant experienced a partial loss of offsite communication to include the Emergency Notification System to the NRC and normal phone communication to offsite. This loss of communications appears to be the result of an unplanned degraded voltage condition on the 48VDC Telephone Battery supplying power to the communications network. Main Control Room indications and assessment capability were not affected. The Nextel cellular phone system, the satellite phones in the Control Rooms, and the Health Physics Radio Network were available onsite to communicate offsite. The plant radio system was also unaffected. Required corrective maintenance is being evaluated. Communication capability is being periodically restored during maintenance troubleshooting, but has not yet been permanently corrected. Operation of Unit 1, Unit 2, and Unit 3 was not affected by the event.
"At 2145 CDT, the NRC Operations Center was notified of alternate contact numbers for [Browns Ferry] until the Telephone Battery is fully restored.
"The NRC Senior Resident Inspector has been notified.
"This event is reportable under 10CFR50.72(b)(3)(xiii)."
* * * UPDATE FROM CHRISTMAN TO KLCO ON 3/15/13 AT 0330EDT * * *
A spare battery charger was aligned to the 48 VDC Telephone Battery and offsite communications was restored.
The licensee notified the NRC Resident Inspector. Notified the R2DO (O'Donohue).