Event Notification Report for April 10, 2011
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
04/09/2011 - 04/10/2011
Power Reactor
Event Number: 46744
Facility: BEAVER VALLEY
Region: 1 State: PA
Unit: [] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: DAN SCHWER
HQ OPS Officer: VINCE KLCO
Region: 1 State: PA
Unit: [] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: DAN SCHWER
HQ OPS Officer: VINCE KLCO
Notification Date: 04/10/2011
Notification Time: 06:40 [ET]
Event Date: 04/10/2011
Event Time: 03:45 [EDT]
Last Update Date: 04/10/2011
Notification Time: 06:40 [ET]
Event Date: 04/10/2011
Event Time: 03:45 [EDT]
Last Update Date: 04/10/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(ii)(A) - DEGRADED CONDITION 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(ii)(A) - DEGRADED CONDITION 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
JOHN CARUSO (R1DO)
JOHN CARUSO (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | M/R | Y | 12 | Power Operation | 0 | Hot Standby |
MANUAL REACTOR TRIP WHILE PERFORMING A TECHNICAL SPECIFICATION REQUIRED SHUTDOWN
"On April 09, 2011, at 2349 [EDT], Beaver Valley Power Station [BVPS] Unit No. 2 was operating at 15% power while preparing to synchronize the main unit generator to the grid. At that time, the 'A' Auxiliary Feedwater Injection Header was declared inoperable due to a water leak identified from a vent valve fillet weld between the inside and outside Containment Isolation Valves (outside of containment) for containment penetration X-79.
"In accordance with Technical Specification 3.7.5, Auxiliary Feedwater (AFW) System, Condition D, at 0345 [EDT], April 10, 2011, BVPS Unit 2 commenced a Reactor Shutdown to Mode 3. Required action is to be in Mode 3 within 6 hours. This event is being reported as a Technical Specification required shutdown pursuant to 10CFR50.72(b)(2)(i), 4 hour notification. Repairs are in progress. The following additional shutdown actions may be required from the time the Injection Header/Containment Penetration was declared inoperable: Technical Specification 3.7.5, Condition D, Mode 4 in 18 hours and Technical Specification 3.6.1, Condition A, Mode 5 within 37 hours. This event is also being reported as a degraded condition for Containment pursuant to 10CFR50.72(b)(3)(ii)(A), 8 hour notification.
"Additionally, at 0357 [EDT], during the Reactor Shutdown, at 4.6% Reactor Power, the BVPS Unit 2 Reactor was manually tripped due to reaching a pre-established manual trip criteria of 25% Steam Generator Level for the 21A Steam Generator. This was conservative criteria set above automatic actuation setpoint of 20.5% level. This event is being reported as a RPS Actuation pursuant to 10CFR50.72(b)(2)(iv)(B), 4 hour notification.
"Control room personnel entered Emergency Operating Procedure E-0, 'Response to Reactor Trip and Safety Injection.' Safety systems and equipment functioned as designed following the manual reactor trip.
"Due to the cooldown and subsequent shrink of level in the 21A Steam Generator, an automatic start of the Steam Driven Auxiliary Feedwater Pump [2FWE-P22] occurred at 20.5%. This event is being reported as an Auxiliary Feedwater System Actuation pursuant to 10CFR50.72(b)(3)(iv)(A), 8 hour notification."
All control rods fully inserted into the core. The plant electrical system is aligned to normal offsite power sources. Decay heat from the reactor coolant pumps is being directed to atmospheric dump valve. There is no primary to secondary leakage. There was no impact on Unit 1. The licensee notified the NRC Resident Inspector.
"On April 09, 2011, at 2349 [EDT], Beaver Valley Power Station [BVPS] Unit No. 2 was operating at 15% power while preparing to synchronize the main unit generator to the grid. At that time, the 'A' Auxiliary Feedwater Injection Header was declared inoperable due to a water leak identified from a vent valve fillet weld between the inside and outside Containment Isolation Valves (outside of containment) for containment penetration X-79.
"In accordance with Technical Specification 3.7.5, Auxiliary Feedwater (AFW) System, Condition D, at 0345 [EDT], April 10, 2011, BVPS Unit 2 commenced a Reactor Shutdown to Mode 3. Required action is to be in Mode 3 within 6 hours. This event is being reported as a Technical Specification required shutdown pursuant to 10CFR50.72(b)(2)(i), 4 hour notification. Repairs are in progress. The following additional shutdown actions may be required from the time the Injection Header/Containment Penetration was declared inoperable: Technical Specification 3.7.5, Condition D, Mode 4 in 18 hours and Technical Specification 3.6.1, Condition A, Mode 5 within 37 hours. This event is also being reported as a degraded condition for Containment pursuant to 10CFR50.72(b)(3)(ii)(A), 8 hour notification.
"Additionally, at 0357 [EDT], during the Reactor Shutdown, at 4.6% Reactor Power, the BVPS Unit 2 Reactor was manually tripped due to reaching a pre-established manual trip criteria of 25% Steam Generator Level for the 21A Steam Generator. This was conservative criteria set above automatic actuation setpoint of 20.5% level. This event is being reported as a RPS Actuation pursuant to 10CFR50.72(b)(2)(iv)(B), 4 hour notification.
"Control room personnel entered Emergency Operating Procedure E-0, 'Response to Reactor Trip and Safety Injection.' Safety systems and equipment functioned as designed following the manual reactor trip.
"Due to the cooldown and subsequent shrink of level in the 21A Steam Generator, an automatic start of the Steam Driven Auxiliary Feedwater Pump [2FWE-P22] occurred at 20.5%. This event is being reported as an Auxiliary Feedwater System Actuation pursuant to 10CFR50.72(b)(3)(iv)(A), 8 hour notification."
All control rods fully inserted into the core. The plant electrical system is aligned to normal offsite power sources. Decay heat from the reactor coolant pumps is being directed to atmospheric dump valve. There is no primary to secondary leakage. There was no impact on Unit 1. The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 46745
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: FRANK KICH
HQ OPS Officer: MARK ABRAMOVITZ
Region: 1 State: NY
Unit: [2] [] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: FRANK KICH
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 04/10/2011
Notification Time: 10:42 [ET]
Event Date: 04/10/2011
Event Time: 08:40 [EDT]
Last Update Date: 04/10/2011
Notification Time: 10:42 [ET]
Event Date: 04/10/2011
Event Time: 08:40 [EDT]
Last Update Date: 04/10/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
JOHN CARUSO (R1DO)
RONNIE (DOE)
PALAZZOLO (EPA)
RUSSELL (USDA)
HOSKINS (HHS)
JOHN CARUSO (R1DO)
RONNIE (DOE)
PALAZZOLO (EPA)
RUSSELL (USDA)
HOSKINS (HHS)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
OFFSITE NOTIFICATION OF AN OIL SHEEN IN THE DISCHARGE CANAL
"Report has been made to the New York State Department of Environmental Conservation and the Westchester County Department of Health related to a visible oil sheen identified on the discharge canal. NRC report required per 10CFR50.72(b)(2)(xi) due to notification of other government agencies."
Initially, the National Response Center was not notified as it does not appear that the oil had reached the Hudson River from this occurrence. After further discussion with the Indian Point Environmental Supervisor, the National Response Center and the Coast Guard were notified concerning this event.
The licensee will notify the NRC Resident Inspector.
"Report has been made to the New York State Department of Environmental Conservation and the Westchester County Department of Health related to a visible oil sheen identified on the discharge canal. NRC report required per 10CFR50.72(b)(2)(xi) due to notification of other government agencies."
Initially, the National Response Center was not notified as it does not appear that the oil had reached the Hudson River from this occurrence. After further discussion with the Indian Point Environmental Supervisor, the National Response Center and the Coast Guard were notified concerning this event.
The licensee will notify the NRC Resident Inspector.