Event Notification Report for May 01, 2014
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
04/30/2014 - 05/01/2014
EVENT NUMBERS
50077500785007950080
Power Reactor
Event Number: 50077
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: JOHN LAUDENBACH
HQ OPS Officer: CHARLES TEAL
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: JOHN LAUDENBACH
HQ OPS Officer: CHARLES TEAL
Notification Date: 05/01/2014
Notification Time: 09:54 [ET]
Event Date: 05/01/2014
Event Time: 08:40 [CDT]
Last Update Date: 05/01/2014
Notification Time: 09:54 [ET]
Event Date: 05/01/2014
Event Time: 08:40 [CDT]
Last Update Date: 05/01/2014
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):
LAURA KOZAK (R3DO)
LAURA KOZAK (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 89 | Power Operation | 89 | Power Operation |
SERVICE WATER RADIATION MONITOR TAKEN OUT OF SERVICE FOR PLANNED MAINTENANCE
"The Service Water Radiation Monitor will be removed from service to facilitate planned preventative maintenance. As a result, this represents a loss of emergency assessment capability under NUREG 1022 revision 3 specific to RU 1.2 and RA 1.2. The planned maintenance is expected to last 7 hours. During this time, the site Chemistry Department will perform sampling every thirty minutes per procedure. As a result of the sampling, reasonable assurance exists to monitor and detect rising radiation levels in order to protect the health and safety of the public.
"The NRC Resident Inspector has been informed."
"The Service Water Radiation Monitor will be removed from service to facilitate planned preventative maintenance. As a result, this represents a loss of emergency assessment capability under NUREG 1022 revision 3 specific to RU 1.2 and RA 1.2. The planned maintenance is expected to last 7 hours. During this time, the site Chemistry Department will perform sampling every thirty minutes per procedure. As a result of the sampling, reasonable assurance exists to monitor and detect rising radiation levels in order to protect the health and safety of the public.
"The NRC Resident Inspector has been informed."
Power Reactor
Event Number: 50078
Facility: CALVERT CLIFFS
Region: 1 State: MD
Unit: [1] [] []
RX Type: [1] CE,[2] CE
NRC Notified By: BOB MARTIN
HQ OPS Officer: JEFF ROTTON
Region: 1 State: MD
Unit: [1] [] []
RX Type: [1] CE,[2] CE
NRC Notified By: BOB MARTIN
HQ OPS Officer: JEFF ROTTON
Notification Date: 05/01/2014
Notification Time: 11:50 [ET]
Event Date: 05/01/2014
Event Time: 10:16 [EDT]
Last Update Date: 05/01/2014
Notification Time: 11:50 [ET]
Event Date: 05/01/2014
Event Time: 10:16 [EDT]
Last Update Date: 05/01/2014
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
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
WILLIAM COOK (R1DO)
WILLIAM COOK (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
AUTOMATIC REACTOR TRIP
"At 1016 [EDT] CCNPP [Calvert Cliffs Nuclear Power Plant] Unit 1 automatically tripped due to an RPS actuation. Cause is under investigation. All safety functions are met with normal heat removal. Electric plant is in a normal lineup. No ESFAS [Engineered Safety Feature Actuation System] actuations have occurred."
Steam Generator atmospheric dump valves momentarily opened and then closed. There is no known steam generator tube leakage. All control rods fully inserted on the trip.
There was no impact on Unit 2 from this event.
The licensee notified the NRC Resident Inspector and provided a courtesy notification to the Calvert County Control Center.
"At 1016 [EDT] CCNPP [Calvert Cliffs Nuclear Power Plant] Unit 1 automatically tripped due to an RPS actuation. Cause is under investigation. All safety functions are met with normal heat removal. Electric plant is in a normal lineup. No ESFAS [Engineered Safety Feature Actuation System] actuations have occurred."
Steam Generator atmospheric dump valves momentarily opened and then closed. There is no known steam generator tube leakage. All control rods fully inserted on the trip.
There was no impact on Unit 2 from this event.
The licensee notified the NRC Resident Inspector and provided a courtesy notification to the Calvert County Control Center.
Power Reactor
Event Number: 50079
Facility: BEAVER VALLEY
Region: 1 State: PA
Unit: [] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: MATT ENOS
HQ OPS Officer: JEFF ROTTON
Region: 1 State: PA
Unit: [] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: MATT ENOS
HQ OPS Officer: JEFF ROTTON
Notification Date: 05/01/2014
Notification Time: 18:12 [ET]
Event Date: 05/01/2014
Event Time: 16:10 [EDT]
Last Update Date: 05/01/2014
Notification Time: 18:12 [ET]
Event Date: 05/01/2014
Event Time: 16:10 [EDT]
Last Update Date: 05/01/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
WILLIAM COOK (R1DO)
WILLIAM COOK (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Defueled | 0 | Defueled |
DEGRADED CONDITION DISCOVERED ON REACTOR VESSEL HEAD CONTROL ROD DRIVE PENETRATION
"On 5/01/2014 during the Beaver Valley Power Station Unit No. 2 (BVPS-2) refueling outage, it was determined that the results of planned ultrasonic (UT) examinations performed on one of the 66 penetrations of the reactor vessel head would not meet the applicable acceptance criteria. This penetration will require repair prior to returning the vessel head to service. The indication was not through wall and there was no evidence of leakage based on inspections performed on the top of the reactor vessel head. The examinations were being performed to meet the requirements of 10CFR50.55a(g)(6)(ii)(D) and ASME Code Case N-729-1, to find potential flaws/indications well before they grow to a size that could potentially jeopardize the structural integrity of the reactor vessel head pressure boundary. Currently 52 of 66 penetrations have been examined, with 51 satisfactory. All of the penetrations will be examined during the current refueling outage.
"The plant is currently shutdown and in a mode undefined [Defueled] and the reactor vessel head is not currently installed. Repairs are currently being planned and will be completed prior to startup.
"This is reportable pursuant to 10CFR50.72(b)(3)(ii)(A) since the as found indications did not meet the applicable acceptance criteria referenced in ASME Code Case N-729-1 to remain in-service without repair.
"The NRC Resident Inspector has been notified."
"On 5/01/2014 during the Beaver Valley Power Station Unit No. 2 (BVPS-2) refueling outage, it was determined that the results of planned ultrasonic (UT) examinations performed on one of the 66 penetrations of the reactor vessel head would not meet the applicable acceptance criteria. This penetration will require repair prior to returning the vessel head to service. The indication was not through wall and there was no evidence of leakage based on inspections performed on the top of the reactor vessel head. The examinations were being performed to meet the requirements of 10CFR50.55a(g)(6)(ii)(D) and ASME Code Case N-729-1, to find potential flaws/indications well before they grow to a size that could potentially jeopardize the structural integrity of the reactor vessel head pressure boundary. Currently 52 of 66 penetrations have been examined, with 51 satisfactory. All of the penetrations will be examined during the current refueling outage.
"The plant is currently shutdown and in a mode undefined [Defueled] and the reactor vessel head is not currently installed. Repairs are currently being planned and will be completed prior to startup.
"This is reportable pursuant to 10CFR50.72(b)(3)(ii)(A) since the as found indications did not meet the applicable acceptance criteria referenced in ASME Code Case N-729-1 to remain in-service without repair.
"The NRC Resident Inspector has been notified."
Power Reactor
Event Number: 50080
Facility: HATCH
Region: 2 State: GA
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: JOHN SELLERS
HQ OPS Officer: JEFF ROTTON
Region: 2 State: GA
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: JOHN SELLERS
HQ OPS Officer: JEFF ROTTON
Notification Date: 05/01/2014
Notification Time: 22:33 [ET]
Event Date: 05/01/2014
Event Time: 20:45 [EDT]
Last Update Date: 05/02/2014
Notification Time: 22:33 [ET]
Event Date: 05/01/2014
Event Time: 20:45 [EDT]
Last Update Date: 05/02/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
DAVID AYRES (R2DO)
DAVID AYRES (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 |
LOSS OF HPCI OPERABILITY DUE TO WATER ACCUMULATION IN THE HPCI TURBINE
"While investigating a Unit 1 high pressure coolant injection (HPCI) room instrument sump level high alarm, condensation was observed dripping out around the HPCI turbine shaft gland seals. A steady stream of water was also observed coming out of the governor end gland seal along with a slight leak coming from the coupling end. Observation revealed that leakage through the 'closed' steam admission valve (1E41-F001) was apparently resulting in water accumulation in the HPCI turbine. A blown fuse that prevented the associated HPCI exhaust drain pot from draining in conjunction with the leakage by the steam admission valve was determined to be sufficient to impact HPCI operability. Required actions were taken in accordance with the Technical Specifications.
"Efforts are underway to determine the actions needed to restore the HPCI system to operable status."
The licensee has notified the NRC Resident Inspector.
* * * UPDATE FROM JOHN SELLERS TO CHARLES TEAL AT 0154 EDT ON 5/2/14 * * *
"HPCI has been restored to an Operable but degraded nonconforming condition. Fuses replaced and automatic functions restored. Leakage confirmed to not be excessive for this condition. Compensatory actions established. Restoration time 2345 EDT 5/1/14."
The licensee will notify the NRC Resident Inspector.
Notified R2DO (Ayers).
"While investigating a Unit 1 high pressure coolant injection (HPCI) room instrument sump level high alarm, condensation was observed dripping out around the HPCI turbine shaft gland seals. A steady stream of water was also observed coming out of the governor end gland seal along with a slight leak coming from the coupling end. Observation revealed that leakage through the 'closed' steam admission valve (1E41-F001) was apparently resulting in water accumulation in the HPCI turbine. A blown fuse that prevented the associated HPCI exhaust drain pot from draining in conjunction with the leakage by the steam admission valve was determined to be sufficient to impact HPCI operability. Required actions were taken in accordance with the Technical Specifications.
"Efforts are underway to determine the actions needed to restore the HPCI system to operable status."
The licensee has notified the NRC Resident Inspector.
* * * UPDATE FROM JOHN SELLERS TO CHARLES TEAL AT 0154 EDT ON 5/2/14 * * *
"HPCI has been restored to an Operable but degraded nonconforming condition. Fuses replaced and automatic functions restored. Leakage confirmed to not be excessive for this condition. Compensatory actions established. Restoration time 2345 EDT 5/1/14."
The licensee will notify the NRC Resident Inspector.
Notified R2DO (Ayers).