Event Notification Report for June 12, 2013
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
06/11/2013 - 06/12/2013
EVENT NUMBERS
49111491094910852000
Agreement State
Event Number: 49111
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: NRG TEXAS POWER LLC
Region: 4
City: THOMPSONS State: TX
County:
License #: 02063
Agreement: Y
Docket:
NRC Notified By: CHRIS MOORE
HQ OPS Officer: NESTOR MAKRIS
Licensee: NRG TEXAS POWER LLC
Region: 4
City: THOMPSONS State: TX
County:
License #: 02063
Agreement: Y
Docket:
NRC Notified By: CHRIS MOORE
HQ OPS Officer: NESTOR MAKRIS
Notification Date: 06/13/2013
Notification Time: 16:26 [ET]
Event Date: 06/12/2013
Event Time: 00:00 [CDT]
Last Update Date: 06/13/2013
Notification Time: 16:26 [ET]
Event Date: 06/12/2013
Event Time: 00:00 [CDT]
Last Update Date: 06/13/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
HEATHER GEPFORD (R4DO)
FSME EVENTS RESOURCE (EMAI)
HEATHER GEPFORD (R4DO)
FSME EVENTS RESOURCE (EMAI)
AGREEMENT STATE REPORT - FAILURE OF GAUGE SHUTTERS TO OPERATE
"On June 13, 2013, the licensee notified the Agency [State of Texas] that after completing maintenance on cables on Hoppers that one of the retest was to operate shutters on all nuclear gauges. The failures were identified on June 12, 2013. Eight gauge shutters failed to operate. The shutters are on Thermo Fisher Model #5197 gauges each containing 100 mCi of Cesium-137. The licensee stated that open is the normal operating position for the shutter and the gauge does not pose an exposure risk to any individual. The sources are not accessible to the general public or workers in the area. The licensee stated that a service provider will most likely remove and possible replace the gauges. The gauges have been in operation for approximately 30 years. Additional information will be provided as it is received in accordance with SA 300."
Texas Incident # I-9091
"On June 13, 2013, the licensee notified the Agency [State of Texas] that after completing maintenance on cables on Hoppers that one of the retest was to operate shutters on all nuclear gauges. The failures were identified on June 12, 2013. Eight gauge shutters failed to operate. The shutters are on Thermo Fisher Model #5197 gauges each containing 100 mCi of Cesium-137. The licensee stated that open is the normal operating position for the shutter and the gauge does not pose an exposure risk to any individual. The sources are not accessible to the general public or workers in the area. The licensee stated that a service provider will most likely remove and possible replace the gauges. The gauges have been in operation for approximately 30 years. Additional information will be provided as it is received in accordance with SA 300."
Texas Incident # I-9091
Power Reactor
Event Number: 49109
Facility: VERMONT YANKEE
Region: 1 State: VT
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: MICHAEL PLETCHER
HQ OPS Officer: MARK ABRAMOVITZ
Region: 1 State: VT
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: MICHAEL PLETCHER
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 06/12/2013
Notification Time: 21:36 [ET]
Event Date: 06/12/2013
Event Time: 16:38 [EDT]
Last Update Date: 06/13/2013
Notification Time: 21:36 [ET]
Event Date: 06/12/2013
Event Time: 16:38 [EDT]
Last Update Date: 06/13/2013
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):
GLENN DENTEL (R1DO)
GLENN DENTEL (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
TONE ALERT SYSTEM FAILURE
"Vermont Yankee Control Room was notified by E-Plan personnel at 1638 [EDT] that the tone test initiated by the National Weather Service from Albany, NY, failed to activate tone alert radios via the Ames Hill NOAA transmitter and would be out for greater than one hour. At 1712 [EDT] the tone alert radios were functionally tested from the backup transmitter link (WTSA Radio Studio) satisfactorily verifying the ability to activate tone alert radios is available."
The licensee suspects a phone service change was not sufficiently tested.
The licensee notified the NRC Resident Inspector.
* * * UPDATE FROM MIKE FRENCH TO NESTOR MAKRIS ON 6/13/13 AT 1207 EDT * * *
On 6/13/13 at 1045 EDT, the Ames Hill transmitter was returned to service after restoration of the transmission link between Ames Hill and the National Weather Service.
The licensee notified the NRC Resident Inspector.
Notified R1DO (Dentel).
"Vermont Yankee Control Room was notified by E-Plan personnel at 1638 [EDT] that the tone test initiated by the National Weather Service from Albany, NY, failed to activate tone alert radios via the Ames Hill NOAA transmitter and would be out for greater than one hour. At 1712 [EDT] the tone alert radios were functionally tested from the backup transmitter link (WTSA Radio Studio) satisfactorily verifying the ability to activate tone alert radios is available."
The licensee suspects a phone service change was not sufficiently tested.
The licensee notified the NRC Resident Inspector.
* * * UPDATE FROM MIKE FRENCH TO NESTOR MAKRIS ON 6/13/13 AT 1207 EDT * * *
On 6/13/13 at 1045 EDT, the Ames Hill transmitter was returned to service after restoration of the transmission link between Ames Hill and the National Weather Service.
The licensee notified the NRC Resident Inspector.
Notified R1DO (Dentel).
Power Reactor
Event Number: 49108
Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: JAMES PRIEST
HQ OPS Officer: PETE SNYDER
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: JAMES PRIEST
HQ OPS Officer: PETE SNYDER
Notification Date: 06/12/2013
Notification Time: 16:59 [ET]
Event Date: 06/12/2013
Event Time: 13:33 [EDT]
Last Update Date: 06/12/2013
Notification Time: 16:59 [ET]
Event Date: 06/12/2013
Event Time: 13:33 [EDT]
Last Update Date: 06/12/2013
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):
GLENN DENTEL (R1DO)
GLENN DENTEL (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | M/R | Y | 100 | Power Operation | 0 | Hot Shutdown |
CIRCULATING WATER PUMP TRIP LEADS TO REACTOR SCRAM
"This is a report of a manual RPS actuation and manual RCIC actuation per 10CFR50.72(b)(2)(iv)(B) and 10CFR50.72(b)(3)(iv)(A).
"At 1332 [EDT], on 6/12/13, the 'B' Circulating Water Pump tripped with a stuck open discharge valve resulting in a vacuum transient. Operators lowered reactor power from 100% in an effort to stabilize condenser vacuum. When vacuum reached 6.5 inches, the operators inserted a manual reactor scram at 1333 [EDT]. All control rods inserted as required. No automatic ECCS or RCIC initiations occurred. No primary or secondary containment isolations occurred. The plant is stable in OP CON 3 HOT SHUTDOWN with the condensate pumps in service. The Reactor Recirculation Pumps are in service.
"At the time of the event, a RCIC surveillance was in progress, but did not contribute to the event. The RCIC pump was secured and subsequently placed in service for inventory control. The only safety-related equipment out of service at the time of the scram was the C Service Water Pump, which was tagged for scheduled maintenance.
"No personnel injuries occurred. No radiation releases occurred. The NRC Resident Inspector has been informed."
"This is a report of a manual RPS actuation and manual RCIC actuation per 10CFR50.72(b)(2)(iv)(B) and 10CFR50.72(b)(3)(iv)(A).
"At 1332 [EDT], on 6/12/13, the 'B' Circulating Water Pump tripped with a stuck open discharge valve resulting in a vacuum transient. Operators lowered reactor power from 100% in an effort to stabilize condenser vacuum. When vacuum reached 6.5 inches, the operators inserted a manual reactor scram at 1333 [EDT]. All control rods inserted as required. No automatic ECCS or RCIC initiations occurred. No primary or secondary containment isolations occurred. The plant is stable in OP CON 3 HOT SHUTDOWN with the condensate pumps in service. The Reactor Recirculation Pumps are in service.
"At the time of the event, a RCIC surveillance was in progress, but did not contribute to the event. The RCIC pump was secured and subsequently placed in service for inventory control. The only safety-related equipment out of service at the time of the scram was the C Service Water Pump, which was tagged for scheduled maintenance.
"No personnel injuries occurred. No radiation releases occurred. The NRC Resident Inspector has been informed."
Power Reactor
Event Number: 52000
Facility: MILLSTONE
Region: 1 State: CT
Unit: [] [] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: WALTER ORF
HQ OPS Officer: DANIEL MILLS
Region: 1 State: CT
Unit: [] [] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: WALTER ORF
HQ OPS Officer: DANIEL MILLS
Notification Date: 06/12/2013
Notification Time: 23:51 [ET]
Event Date: 06/12/2013
Event Time: 20:13 [EDT]
Last Update Date: 06/13/2016
Notification Time: 23:51 [ET]
Event Date: 06/12/2013
Event Time: 20:13 [EDT]
Last Update Date: 06/13/2016
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)(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)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
FRANK ARNER (R1DO)
CHRIS MILLER (NRR)
BERNARD STAPLETON (IRD)
FRANK ARNER (R1DO)
CHRIS MILLER (NRR)
BERNARD STAPLETON (IRD)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | M/R | Y | 100 | Power Operation | 0 | Hot Standby |
TECHNICAL SPECIFICATION REQUIRED SHUTDOWN AND REACTOR TRIP
At 2013 EDT on 6/12/16, Millstone Unit 3 commenced a Technical Specification (TS) required shutdown due to excessive Reactor Coolant System leakage from the "A" Reactor Coolant Pump (RCP) third stage seal. The leakage from the third stage seal was approximately two gpm which is greater than the Technical Specification (TS) limit of less than one gpm.
During the shutdown, oscillations developed in the Main Feedwater which required the operator to initiate a manual reactor trip. Unit 3 is currently stable in Mode 3. Decay heat is being released via the Steam Dumps to the Main Condenser. Normal offsite power is available and the unit is in a normal shutdown electrical line-up. The cause of the Main Feedwater oscillations is being investigated.
The licensee notified the NRC Resident Inspector. The licensee notified State and local government agencies.
* * * UPDATE FROM WALTER ORF TO DONALD NORWOOD AT 0129 EDT ON 6/13/2016 * * *
The following clarifies Feedwater isolation vs. Feedwater oscillation:
"At 2337 EDT on 6/12/16, a manual reactor trip was initiated on Unit 3 following feedwater isolation. As expected, Aux Feedwater system (AFW) initiated on the reactor trip. The trip was uncomplicated and the plant is currently in Mode 3 with a normal electric line-up and decay heat is being removed via steam dumps to the condenser. This is reportable under 10 CFR 50.72(b)(2)(iv)(B) - RPS Actuation - Critical and 10 CFR 50.72(b)(3)(iv)(A) - Valid Specific System Actuation."
"The Feedwater isolation occurred due to high Steam Generator water level."
The licensee notified the NRC Resident Inspector.
Notified R1DO (Arner).
At 2013 EDT on 6/12/16, Millstone Unit 3 commenced a Technical Specification (TS) required shutdown due to excessive Reactor Coolant System leakage from the "A" Reactor Coolant Pump (RCP) third stage seal. The leakage from the third stage seal was approximately two gpm which is greater than the Technical Specification (TS) limit of less than one gpm.
During the shutdown, oscillations developed in the Main Feedwater which required the operator to initiate a manual reactor trip. Unit 3 is currently stable in Mode 3. Decay heat is being released via the Steam Dumps to the Main Condenser. Normal offsite power is available and the unit is in a normal shutdown electrical line-up. The cause of the Main Feedwater oscillations is being investigated.
The licensee notified the NRC Resident Inspector. The licensee notified State and local government agencies.
* * * UPDATE FROM WALTER ORF TO DONALD NORWOOD AT 0129 EDT ON 6/13/2016 * * *
The following clarifies Feedwater isolation vs. Feedwater oscillation:
"At 2337 EDT on 6/12/16, a manual reactor trip was initiated on Unit 3 following feedwater isolation. As expected, Aux Feedwater system (AFW) initiated on the reactor trip. The trip was uncomplicated and the plant is currently in Mode 3 with a normal electric line-up and decay heat is being removed via steam dumps to the condenser. This is reportable under 10 CFR 50.72(b)(2)(iv)(B) - RPS Actuation - Critical and 10 CFR 50.72(b)(3)(iv)(A) - Valid Specific System Actuation."
"The Feedwater isolation occurred due to high Steam Generator water level."
The licensee notified the NRC Resident Inspector.
Notified R1DO (Arner).