Event Notification Report for October 29, 2012
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
10/28/2012 - 10/29/2012
EVENT NUMBERS
48523484564845048451484524845348454
Non-Agreement State
Event Number: 48523
Rep Org: U. S. ARMY
Licensee: U.S. ARMY
Region: 3
City: WARREN State: MI
County:
License #: 21-328-38-01
Agreement: N
Docket:
NRC Notified By: THOMAS GIZICKI
HQ OPS Officer: VINCE KLCO
Licensee: U.S. ARMY
Region: 3
City: WARREN State: MI
County:
License #: 21-328-38-01
Agreement: N
Docket:
NRC Notified By: THOMAS GIZICKI
HQ OPS Officer: VINCE KLCO
Notification Date: 11/20/2012
Notification Time: 11:41 [ET]
Event Date: 10/29/2012
Event Time: 00:00 [EST]
Last Update Date: 11/20/2012
Notification Time: 11:41 [ET]
Event Date: 10/29/2012
Event Time: 00:00 [EST]
Last Update Date: 11/20/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
Person (Organization):
BILLY DICKSON (R3DO)
FSME EVENTS (EMAI)
RAY KELLAR (R4DO)
BILLY DICKSON (R3DO)
FSME EVENTS (EMAI)
RAY KELLAR (R4DO)
MISSING IMPROVED CHEMICAL AGENT MONITOR
An ICAM (Improved Chemical Agent Monitor) is missing at Fort Riley, KS. The ICAM contains a 10 mCi Nickel-63 source. The licensee has initiated a formal investigation and notified NRC Region 3 Inspector (McGraw).
THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL
Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf
An ICAM (Improved Chemical Agent Monitor) is missing at Fort Riley, KS. The ICAM contains a 10 mCi Nickel-63 source. The licensee has initiated a formal investigation and notified NRC Region 3 Inspector (McGraw).
THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL
Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf
Power Reactor
Event Number: 48456
Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [] [2] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: MARK GREER
HQ OPS Officer: ERIC SIMPSON
Region: 1 State: NY
Unit: [] [2] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: MARK GREER
HQ OPS Officer: ERIC SIMPSON
Notification Date: 10/30/2012
Notification Time: 03:35 [ET]
Event Date: 10/29/2012
Event Time: 21:00 [EDT]
Last Update Date: 10/30/2012
Notification Time: 03:35 [ET]
Event Date: 10/29/2012
Event Time: 21:00 [EDT]
Last Update Date: 10/30/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
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 | N | Y | 100 | Power Operation | 100 | Power Operation |
AUTOMATIC INITIATION OF EMERGENCY DIESEL GENERATOR DUE TO LOSS OF ONE OFF-SITE POWER SOURCE
"On October 29, 2012 at 2100 EDT, Nine Mile Point Unit 2 experienced an automatic initiation of the Division 1 Emergency Diesel Generator due to a loss of line 5. Line 5 is one of the 115KV offsite power sources. Line 5 was lost due to a lightening arrestor falling onto electrical components in the Scriba switchyard during high winds.
"During the electrical transient, Nine Mile Point Unit 2 also experienced a feedwater level control lockup, requiring manual control. No Emergency Core Cooling Systems actuated and feedwater level control was returned to automatic. Nine Mile Point Unit 2 remained at 100% power during the loss of line 5.
"The off-site power source, line 5, was restored on October 30, 2012 at 0326 EDT."
The licensee notified the NRC Resident Inspector.
"On October 29, 2012 at 2100 EDT, Nine Mile Point Unit 2 experienced an automatic initiation of the Division 1 Emergency Diesel Generator due to a loss of line 5. Line 5 is one of the 115KV offsite power sources. Line 5 was lost due to a lightening arrestor falling onto electrical components in the Scriba switchyard during high winds.
"During the electrical transient, Nine Mile Point Unit 2 also experienced a feedwater level control lockup, requiring manual control. No Emergency Core Cooling Systems actuated and feedwater level control was returned to automatic. Nine Mile Point Unit 2 remained at 100% power during the loss of line 5.
"The off-site power source, line 5, was restored on October 30, 2012 at 0326 EDT."
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 48450
Facility: OYSTER CREEK
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-2
NRC Notified By: JOHN CLARK
HQ OPS Officer: DAN LIVERMORE
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-2
NRC Notified By: JOHN CLARK
HQ OPS Officer: DAN LIVERMORE
Notification Date: 10/29/2012
Notification Time: 16:15 [ET]
Event Date: 10/29/2012
Event Time: 15:00 [EDT]
Last Update Date: 10/30/2012
Notification Time: 16:15 [ET]
Event Date: 10/29/2012
Event Time: 15:00 [EDT]
Last Update Date: 10/30/2012
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):
JOHN CARUSO (R1DO)
JANE MARSHALL (IRD)
JOHN CARUSO (R1DO)
JANE MARSHALL (IRD)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
LOSS OF 21 EMERGENCY NOTIFICATION SIRENS
On October 29, 2012, at approximately 1500 EDT, ANS, the licensee's provider of siren maintenance, reported a loss of 12 out of 43 sirens in the Oyster Creek Emergency Planning Zone, which exceeded the licensee's reporting threshold of 25 percent or more sirens out of service.
At 1600 EDT, ANS, updated that the number of sirens out of service was 21 out of 43 sirens. ANS and the licensee continues to work to rectify the issue.
The NRC Resident Inspector will be notified.
* * * UPDATE ON 10/30/12 AT 0428 EDT FROM JOHN CLARK TO RYAN ALEXANDER * * *
As of 0320 EDT on 10/30/12, it was determined that 36 of the 43 Emergency Planning Zone sirens were out of service, and the licensee continues work to rectify the issue.
The NRC Resident Inspector will be notified. Notified R1DO (Caruso) and IRD (Marshall).
On October 29, 2012, at approximately 1500 EDT, ANS, the licensee's provider of siren maintenance, reported a loss of 12 out of 43 sirens in the Oyster Creek Emergency Planning Zone, which exceeded the licensee's reporting threshold of 25 percent or more sirens out of service.
At 1600 EDT, ANS, updated that the number of sirens out of service was 21 out of 43 sirens. ANS and the licensee continues to work to rectify the issue.
The NRC Resident Inspector will be notified.
* * * UPDATE ON 10/30/12 AT 0428 EDT FROM JOHN CLARK TO RYAN ALEXANDER * * *
As of 0320 EDT on 10/30/12, it was determined that 36 of the 43 Emergency Planning Zone sirens were out of service, and the licensee continues work to rectify the issue.
The NRC Resident Inspector will be notified. Notified R1DO (Caruso) and IRD (Marshall).
Power Reactor
Event Number: 48451
Facility: FERMI
Region: 3 State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: BRETT JEBBIA
HQ OPS Officer: DAN LIVERMORE
Region: 3 State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: BRETT JEBBIA
HQ OPS Officer: DAN LIVERMORE
Notification Date: 10/29/2012
Notification Time: 18:15 [ET]
Event Date: 10/29/2012
Event Time: 17:00 [EDT]
Last Update Date: 11/09/2012
Notification Time: 18:15 [ET]
Event Date: 10/29/2012
Event Time: 17:00 [EDT]
Last Update Date: 11/09/2012
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 |
|---|---|---|---|---|---|---|
| 2 | N | Y | 68 | Power Operation | 68 | Power Operation |
ERDS LOST DUE TO PROCESS COMPUTER SYSTEM DATA SERVER FAILURE
"At 1700 EDT on October 29, 2012, Fermi 2 discovered a failure occurred with a data server within the Process Computer system at 0115 EDT on October 28, 2012. The failure of the data server affects data input to the server providing information to the Emergency Response Data System (ERDS). ERDS is currently not receiving updated information from Fermi data systems. This loss in capability is being reported as a loss of assessment capability in accordance with 10 CFR 50.72(b)(3)(xiii).
"Indications of related plant variables are available in the Main Control Room. The Visual Annunciator System (VAS) and other portions of the Process Computer system remain functional. Meteorological and process effluent radiological monitor indications are available and dose assessment capability is available. Fermi 2 personnel will use normal phone communications to update NRC Operations Center in the case of an event declaration. Information normally provided by ERDS can be transmitted via the notification system as described in the Radiological Emergency Response Preparedness Plan. Fermi 2 will notify the NRC when ERDS is returned to service."
The licensee has notified the NRC Resident Inspector.
* * * UPDATE ON 11/9/12 AT 2056 EST FROM BRETT JEBBIA TO DONG PARK * * *
"This is a follow up to EN #48468 & EN #48451.
"On October 29, 2012, Fermi experienced a failure of a data server within the process computer system which feeds data to Emergency Response Data System (ERDS), and EN #48451 was made to the NRC.
"On November 1, 2012, planned maintenance for Cyber Security Modification began which removed ERDS, SPDS, and IPCS from service, and EN #48468 was made to the NRC.
"On November 9, 2012, planned maintenance on ERDS, SPDS, and IPCS is complete, restoring full emergency assessment capabilities to all onsite emergency response facilities (EN #48468). The maintenance also repaired the data server within the process computer system which feeds data to ERDS (EN #48451)."
The licensee has notified the NRC Resident Inspector. Notified R3DO (Lipa).
"At 1700 EDT on October 29, 2012, Fermi 2 discovered a failure occurred with a data server within the Process Computer system at 0115 EDT on October 28, 2012. The failure of the data server affects data input to the server providing information to the Emergency Response Data System (ERDS). ERDS is currently not receiving updated information from Fermi data systems. This loss in capability is being reported as a loss of assessment capability in accordance with 10 CFR 50.72(b)(3)(xiii).
"Indications of related plant variables are available in the Main Control Room. The Visual Annunciator System (VAS) and other portions of the Process Computer system remain functional. Meteorological and process effluent radiological monitor indications are available and dose assessment capability is available. Fermi 2 personnel will use normal phone communications to update NRC Operations Center in the case of an event declaration. Information normally provided by ERDS can be transmitted via the notification system as described in the Radiological Emergency Response Preparedness Plan. Fermi 2 will notify the NRC when ERDS is returned to service."
The licensee has notified the NRC Resident Inspector.
* * * UPDATE ON 11/9/12 AT 2056 EST FROM BRETT JEBBIA TO DONG PARK * * *
"This is a follow up to EN #48468 & EN #48451.
"On October 29, 2012, Fermi experienced a failure of a data server within the process computer system which feeds data to Emergency Response Data System (ERDS), and EN #48451 was made to the NRC.
"On November 1, 2012, planned maintenance for Cyber Security Modification began which removed ERDS, SPDS, and IPCS from service, and EN #48468 was made to the NRC.
"On November 9, 2012, planned maintenance on ERDS, SPDS, and IPCS is complete, restoring full emergency assessment capabilities to all onsite emergency response facilities (EN #48468). The maintenance also repaired the data server within the process computer system which feeds data to ERDS (EN #48451)."
The licensee has notified the NRC Resident Inspector. Notified R3DO (Lipa).
Power Reactor
Event Number: 48452
Facility: OYSTER CREEK
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-2
NRC Notified By: STEVE SERPE
HQ OPS Officer: RYAN ALEXANDER
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-2
NRC Notified By: STEVE SERPE
HQ OPS Officer: RYAN ALEXANDER
Notification Date: 10/29/2012
Notification Time: 19:18 [ET]
Event Date: 10/29/2012
Event Time: 18:55 [EDT]
Last Update Date: 10/31/2012
Notification Time: 19:18 [ET]
Event Date: 10/29/2012
Event Time: 18:55 [EDT]
Last Update Date: 10/31/2012
Emergency Class: ALERT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION 50.72(b)(3)(v)(B) - POT RHR INOP
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION 50.72(b)(3)(v)(B) - POT RHR INOP
Person (Organization):
JOHN CARUSO (R1DO)
WILLIAM DEAN (R1 R)
ERIC LEEDS (NRR)
MICHELE EVANS (NRR)
JANE MARSHALL (IRD)
JOHN CARUSO (R1DO)
WILLIAM DEAN (R1 R)
ERIC LEEDS (NRR)
MICHELE EVANS (NRR)
JANE MARSHALL (IRD)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
NOTICE OF UNUSUAL EVENT DECLARED DUE TO HIGH INTAKE STRUCTURE WATER LEVEL
At 1855 EDT on 10/29/2012, the licensee declared a Notice of Unusual Event (NOUE) per criteria HU4 for high water level in the station intake structure of greater than 4.5 feet. At the time of the notification, water level in the intake structure was approximate 4.8 feet and slowly rising. The cause of the increased water level was due to storm surge associated with Hurricane Sandy. No other station impacts were reported at the time. The licensee continues to monitor the intake levels and ocean tides.
The licensee has notified the NRC Resident Inspector and the State of New Jersey.
* * * ALERT UPDATE ON 10/29/2012 AT 2141 EDT FROM STEVE SERPE TO RYAN ALEXANDER * * *
At 2044 EDT on 10/29/2012, the licensee escalated its emergency declaration to an Alert per criteria HA4 for high water level in the station intake structure of greater than 6.0 feet. At the time of the notification, water level in the intake structure was approximately 6.6 feet. The site also experienced a loss of offsite power event concurrent with the additional water level increase. Both emergency diesel generators started and are supplying power to the emergency electrical busses. Shutdown cooling and spent fuel pool cooling have been restored. Reactor pressure vessel level is steady at 584.7 inches. Intake levels continues to rise slowly and the licensee is monitoring.
The licensee has notified the NRC Resident Inspector and the State of New Jersey.
Notified DHS SWO, FEMA Ops Center, USDA Ops Center, HHS Ops Center, DOE Ops Center, DHS NICC Watch Officer, EPA EOC, and NuclearSSA via e-mail.
* * * UPDATE on 10/30/12 at 0414 EDT FROM GILBERT DEVRIES TO RYAN ALEXANDER * * *
The licensee updated this report with an 8-hour non-emergency notification of emergency diesel generator auto-actuation due to the actual loss of off-site power event [which occurred at 2018 EDT on 10/29/2012]. This event caused a valid RPS actuation with automatic containment isolations that resulted in a temporary loss of shut-down cooling to the reactor. Shutdown cooling was subsequently restored with power provided by the emergency diesel generators.
The licensee has notified the NRC Resident Inspector. Notified R1DO (Caruso).
* * * UPDATE AT 0357 EDT ON 10/31/12 FROM GILBERT A. DeVRIES TO S. SANDIN * * *
"Termination of Alert.
"The Oyster Creek Station has terminated the Alert that was declared at 2044 [EDT] on 10/29/12 due to Intake Structure high water level greater than 6.0 ft. MSL (EAL HA4).
"Intake water level has returned to normal and is now below the Unusual Event EAL threshold (4.5 ft. MSL) and continues to lower."
The licensee informed state and local agencies and the NRC Resident Inspector. Notified Region I IRC (Clifford), NRR (Evans), and IRD (Marshall).
Notified DHS SWO, FEMA Ops Center, USDA Ops Center, HHS Ops Center, DOE Ops Center, DHS NICC Watch Officer, EPA EOC, and NuclearSSA via e-mail.
At 1855 EDT on 10/29/2012, the licensee declared a Notice of Unusual Event (NOUE) per criteria HU4 for high water level in the station intake structure of greater than 4.5 feet. At the time of the notification, water level in the intake structure was approximate 4.8 feet and slowly rising. The cause of the increased water level was due to storm surge associated with Hurricane Sandy. No other station impacts were reported at the time. The licensee continues to monitor the intake levels and ocean tides.
The licensee has notified the NRC Resident Inspector and the State of New Jersey.
* * * ALERT UPDATE ON 10/29/2012 AT 2141 EDT FROM STEVE SERPE TO RYAN ALEXANDER * * *
At 2044 EDT on 10/29/2012, the licensee escalated its emergency declaration to an Alert per criteria HA4 for high water level in the station intake structure of greater than 6.0 feet. At the time of the notification, water level in the intake structure was approximately 6.6 feet. The site also experienced a loss of offsite power event concurrent with the additional water level increase. Both emergency diesel generators started and are supplying power to the emergency electrical busses. Shutdown cooling and spent fuel pool cooling have been restored. Reactor pressure vessel level is steady at 584.7 inches. Intake levels continues to rise slowly and the licensee is monitoring.
The licensee has notified the NRC Resident Inspector and the State of New Jersey.
Notified DHS SWO, FEMA Ops Center, USDA Ops Center, HHS Ops Center, DOE Ops Center, DHS NICC Watch Officer, EPA EOC, and NuclearSSA via e-mail.
* * * UPDATE on 10/30/12 at 0414 EDT FROM GILBERT DEVRIES TO RYAN ALEXANDER * * *
The licensee updated this report with an 8-hour non-emergency notification of emergency diesel generator auto-actuation due to the actual loss of off-site power event [which occurred at 2018 EDT on 10/29/2012]. This event caused a valid RPS actuation with automatic containment isolations that resulted in a temporary loss of shut-down cooling to the reactor. Shutdown cooling was subsequently restored with power provided by the emergency diesel generators.
The licensee has notified the NRC Resident Inspector. Notified R1DO (Caruso).
* * * UPDATE AT 0357 EDT ON 10/31/12 FROM GILBERT A. DeVRIES TO S. SANDIN * * *
"Termination of Alert.
"The Oyster Creek Station has terminated the Alert that was declared at 2044 [EDT] on 10/29/12 due to Intake Structure high water level greater than 6.0 ft. MSL (EAL HA4).
"Intake water level has returned to normal and is now below the Unusual Event EAL threshold (4.5 ft. MSL) and continues to lower."
The licensee informed state and local agencies and the NRC Resident Inspector. Notified Region I IRC (Clifford), NRR (Evans), and IRD (Marshall).
Notified DHS SWO, FEMA Ops Center, USDA Ops Center, HHS Ops Center, DOE Ops Center, DHS NICC Watch Officer, EPA EOC, and NuclearSSA via e-mail.
Power Reactor
Event Number: 48453
Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: KEVIN MATTESSICH
HQ OPS Officer: ERIC SIMPSON
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: KEVIN MATTESSICH
HQ OPS Officer: ERIC SIMPSON
Notification Date: 10/29/2012
Notification Time: 21:58 [ET]
Event Date: 10/29/2012
Event Time: 00:00 [EDT]
Last Update Date: 10/29/2012
Notification Time: 21:58 [ET]
Event Date: 10/29/2012
Event Time: 00:00 [EDT]
Last Update Date: 10/29/2012
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):
JOHN CARUSO (R1DO)
JOHN CARUSO (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 Shutdown |
RPS ACTUATION WHILE CRITICAL DUE TO GENERATOR LOAD REJECT
On October 29, 2012 at 2100 EDT, Nine Mile Point Unit 1 experienced an automatic reactor scram due to a generator load reject. The cause of the load reject is currently under investigation. All control rods fully inserted and all plant systems responded per design following the scram.
Following the automatic scram, the High Pressure Coolant Injection (HPCI) System automatically initiated as expected. At Nine Mile Point Unit 1, a HPCI System actuation signal on low Reactor Pressure Vessel (RPV) level is normally received following a reactor scram, due to level shrink. HPCI is a flow control mode of the normal feedwater systems, and is not an Emergency Core Cooling System. At 2101 EDT, RPV level was restored above the HPCI System low level actuation set point and the HPCI System initiation signal was reset. Pressure control was established on the Turbine Bypass Valves, the preferred system. Three Electromatic Relief Valves actuated due to this scram and re-closed automatically.
Nine Mile Point Unit 1 is currently in Hot Shutdown, with reactor water level and pressure maintained within normal bands. Decay heat is being removed via steam to the main condenser using bypass valves. Both Reserve Station Transformers are in service and being supplied by their normal power sources. Both Emergency Diesel Generators are operable and in standby.
The unit is currently implementing post scram recovery procedures.
The licensee has notified the NRC Resident Inspector.
On October 29, 2012 at 2100 EDT, Nine Mile Point Unit 1 experienced an automatic reactor scram due to a generator load reject. The cause of the load reject is currently under investigation. All control rods fully inserted and all plant systems responded per design following the scram.
Following the automatic scram, the High Pressure Coolant Injection (HPCI) System automatically initiated as expected. At Nine Mile Point Unit 1, a HPCI System actuation signal on low Reactor Pressure Vessel (RPV) level is normally received following a reactor scram, due to level shrink. HPCI is a flow control mode of the normal feedwater systems, and is not an Emergency Core Cooling System. At 2101 EDT, RPV level was restored above the HPCI System low level actuation set point and the HPCI System initiation signal was reset. Pressure control was established on the Turbine Bypass Valves, the preferred system. Three Electromatic Relief Valves actuated due to this scram and re-closed automatically.
Nine Mile Point Unit 1 is currently in Hot Shutdown, with reactor water level and pressure maintained within normal bands. Decay heat is being removed via steam to the main condenser using bypass valves. Both Reserve Station Transformers are in service and being supplied by their normal power sources. Both Emergency Diesel Generators are operable and in standby.
The unit is currently implementing post scram recovery procedures.
The licensee has notified the NRC Resident Inspector.
Power Reactor
Event Number: 48454
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [] [3] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: CHUCK GUALDONI
HQ OPS Officer: ERIC SIMPSON
Region: 1 State: NY
Unit: [] [3] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: CHUCK GUALDONI
HQ OPS Officer: ERIC SIMPSON
Notification Date: 10/30/2012
Notification Time: 00:30 [ET]
Event Date: 10/29/2012
Event Time: 22:41 [EDT]
Last Update Date: 10/30/2012
Notification Time: 00:30 [ET]
Event Date: 10/29/2012
Event Time: 22:41 [EDT]
Last Update Date: 10/30/2012
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):
JOHN CARUSO (R1DO)
JOHN CARUSO (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
AUTOMATIC RPS ACTUATION ON GENERATOR TRIP
"On October 29, 2012, at 2241EDT, the Reactor Protection System automatically actuated at 100% reactor power due to a direct electrical trip to the Unit 3 Main Turbine Generator. The generator trip resulted in a turbine/reactor trip. All control rods fully inserted on the reactor trip. All plant equipment responded normally to the unit trip. This is reportable under 10 CFR 50.72(b)(2)(iv)(B). The plant is stable in Mode 3 at this time.
"The Auxiliary Feedwater System actuated following the automatic trip as expected. This is reportable under 10 CFR 50.72(b)(3)(iv)(A). The Emergency Diesel Generators did not start as offsite power remained available and stable. The unit remains on offsite power and all electrical loads are stable. No primary or secondary relief valves lifted. The plant is in Hot Standby at normal operating temperature and pressure with decay heat removal using auxiliary feedwater to the steam generators and normal heat removal through the condenser via condenser steam
dumps. There was no radiation released.
"Indian Point Unit 2 was not affected by this event and remains at 100% power.
"A post trip investigation is in progress."
The licensee notified the NRC Resident Inspector.
"On October 29, 2012, at 2241EDT, the Reactor Protection System automatically actuated at 100% reactor power due to a direct electrical trip to the Unit 3 Main Turbine Generator. The generator trip resulted in a turbine/reactor trip. All control rods fully inserted on the reactor trip. All plant equipment responded normally to the unit trip. This is reportable under 10 CFR 50.72(b)(2)(iv)(B). The plant is stable in Mode 3 at this time.
"The Auxiliary Feedwater System actuated following the automatic trip as expected. This is reportable under 10 CFR 50.72(b)(3)(iv)(A). The Emergency Diesel Generators did not start as offsite power remained available and stable. The unit remains on offsite power and all electrical loads are stable. No primary or secondary relief valves lifted. The plant is in Hot Standby at normal operating temperature and pressure with decay heat removal using auxiliary feedwater to the steam generators and normal heat removal through the condenser via condenser steam
dumps. There was no radiation released.
"Indian Point Unit 2 was not affected by this event and remains at 100% power.
"A post trip investigation is in progress."
The licensee notified the NRC Resident Inspector.