Event Notification Report for June 26, 2011
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
06/25/2011 - 06/26/2011
EVENT NUMBERS
46994469874698846989469904699146992
Agreement State
Event Number: 46994
Rep Org: NEW YORK STATE DEPT. OF HEALTH
Licensee: FAIRWAY TESTING
Region: 1
City: STONY POINT State: NY
County:
License #: NYS C2322
Agreement: Y
Docket:
NRC Notified By: ROBERT SNYDER
HQ OPS Officer: PETE SNYDER
Licensee: FAIRWAY TESTING
Region: 1
City: STONY POINT State: NY
County:
License #: NYS C2322
Agreement: Y
Docket:
NRC Notified By: ROBERT SNYDER
HQ OPS Officer: PETE SNYDER
Notification Date: 06/27/2011
Notification Time: 15:50 [ET]
Event Date: 06/26/2011
Event Time: 00:00 [EDT]
Last Update Date: 07/20/2011
Notification Time: 15:50 [ET]
Event Date: 06/26/2011
Event Time: 00:00 [EDT]
Last Update Date: 07/20/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
BLAKE WELLING (R1DO)
JIM LUEHMAN (FSME)
CANADA (FAX)
BLAKE WELLING (R1DO)
JIM LUEHMAN (FSME)
CANADA (FAX)
AGREEMENT STATE REPORT - STOLEN PORTABLE MOISTURE DENSITY GAUGE
The following was received via fax:
"Fairway Testing Co. license no. C2322, called 6/27/11 to report that a Troxler model 3411 s/n 4363 portable density gauge was stolen from a company vehicle on Sunday, June 26. The device contained 8 mCi Cesium 137 and 40 mCi of Americium 241/Beryllium.
"The employee worked late on Friday, June 24 and did not have access to the permanent storage location since the building is locked after 5:00 p.m. The driver took the vehicle to his residence on Brookside Drive in Stony Point, Rockland County and parked it in his driveway. The device was in its transport container, which was doubly chained to the bed of the pickup truck.
"On Sunday morning, the employee observed that the container was still in the bed of the pickup before he left his residence for the day in a family vehicle. When he came home that night he did not check the vehicle.
"On Monday morning, he realized that both chains were cut and the transport box along with the device was stolen. Other items were also stolen from the vehicle which leads to speculation that the perpetrators were not specifically after the density gauge.
"The local police were notified and a police report has been initiated. The licensee has thirty days to send a written response and to notify the NYS DOH (New York State Department of Health) of any substantial development in the case."
NY State Event #: NY-11-11
* * * * UPDATED AT 1431 EDT ON 7/20/11 BY S. SANDIN * * * *
The following update was received from NY DOH via fax:
"On 7/5/11, DOH was notified via fax that a load of scrap metal tripped the alarm at Gerdau Ameristeel in Sayreville, NJ. The load was returned to the originator (Teplitz in Nanuet, NY) and then to Orange County Metal recycling (OCMR) in Middletown, NY. OCMR staff identified, isolated and secured the source of the trip and contracted Co-Physics to characterize. In cooperation with DOH, Co-Physics contacted Troxler with model and serial numbers from the item and identified it as the cesium source from the stolen gauge. Fairway Testing and Stony Point Police have been notified.
"Fairway Testing is aware of its responsibility for proper disposition of the source.
"The Am-Be source is still unaccounted for. A search of Teplitz is underway.
"No Reward offered. No Press Release issued."
Notified R1DO (Dentel), FSME (White) and Canada via fax.
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
The following was received via fax:
"Fairway Testing Co. license no. C2322, called 6/27/11 to report that a Troxler model 3411 s/n 4363 portable density gauge was stolen from a company vehicle on Sunday, June 26. The device contained 8 mCi Cesium 137 and 40 mCi of Americium 241/Beryllium.
"The employee worked late on Friday, June 24 and did not have access to the permanent storage location since the building is locked after 5:00 p.m. The driver took the vehicle to his residence on Brookside Drive in Stony Point, Rockland County and parked it in his driveway. The device was in its transport container, which was doubly chained to the bed of the pickup truck.
"On Sunday morning, the employee observed that the container was still in the bed of the pickup before he left his residence for the day in a family vehicle. When he came home that night he did not check the vehicle.
"On Monday morning, he realized that both chains were cut and the transport box along with the device was stolen. Other items were also stolen from the vehicle which leads to speculation that the perpetrators were not specifically after the density gauge.
"The local police were notified and a police report has been initiated. The licensee has thirty days to send a written response and to notify the NYS DOH (New York State Department of Health) of any substantial development in the case."
NY State Event #: NY-11-11
* * * * UPDATED AT 1431 EDT ON 7/20/11 BY S. SANDIN * * * *
The following update was received from NY DOH via fax:
"On 7/5/11, DOH was notified via fax that a load of scrap metal tripped the alarm at Gerdau Ameristeel in Sayreville, NJ. The load was returned to the originator (Teplitz in Nanuet, NY) and then to Orange County Metal recycling (OCMR) in Middletown, NY. OCMR staff identified, isolated and secured the source of the trip and contracted Co-Physics to characterize. In cooperation with DOH, Co-Physics contacted Troxler with model and serial numbers from the item and identified it as the cesium source from the stolen gauge. Fairway Testing and Stony Point Police have been notified.
"Fairway Testing is aware of its responsibility for proper disposition of the source.
"The Am-Be source is still unaccounted for. A search of Teplitz is underway.
"No Reward offered. No Press Release issued."
Notified R1DO (Dentel), FSME (White) and Canada via fax.
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
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 46987
Facility: PEACH BOTTOM
Region: 1 State: PA
Unit: [] [3] []
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: ROY GLACKIN
HQ OPS Officer: PETE SNYDER
Region: 1 State: PA
Unit: [] [3] []
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: ROY GLACKIN
HQ OPS Officer: PETE SNYDER
Notification Date: 06/26/2011
Notification Time: 05:25 [ET]
Event Date: 06/26/2011
Event Time: 00:30 [EDT]
Last Update Date: 08/08/2011
Notification Time: 05:25 [ET]
Event Date: 06/26/2011
Event Time: 00:30 [EDT]
Last Update Date: 08/08/2011
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):
CHRISTOPHER CAHILL (R1DO)
CHRISTOPHER CAHILL (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | Y | 100 | Power Operation | 100 | Power Operation |
PIPING LEAK ISOLATED ON HIGH PRESSURE COOLANT INJECTION
"On 06/26/11, at 0030 [hrs. EDT], Peach Bottom Atomic Power Station Unit 3 declared the High Pressure Coolant Injection [HPCI] system inoperable for an ASME class 2 exempt piping leak found during operator rounds. Piping on the steam line pressure indication sensing line downstream of a sensing line root valve had an approximate 5 drop per minute leak. The leak has been isolated and the Unit 3 HPCI system was restored to an operable condition as of 0347 on 06/26/11.
"This report is being submitted pursuant to 10CFR 50.72(b)(3)(v)(D)."
The licensee notified the NRC Resident Inspector.
* * * RETRACTION ON 08/08/2011 AT 1432 EDT FROM DAVE FOSS TO RYAN ALEXANDER * * *
"The purpose of this notification is to retract a previous report made on 06/26/11 at 0525 [EDT] (EN# 46987). Notification of this event to the NRC was initially made as a result of declaring the Unit 3 High Pressure Coolant Injection (HPCI) system inoperable on 06/26/11 at 0030 [EDT] when a small leak on an instrument sensing line was found during performance of routine operator rounds. Specifically, it was observed that the 1/2 inch instrument piping for the non-safety related HPCI steam supply pressure indicator was leaking at approximately 5 drops per minute. The location of the leak was downstream of the instrument line root valve. The leak was isolated and the Unit 3 HPCI system was considered operable at approximately 0347 [EDT] on 06/26/11. The ENS report on 06/26/11 was originally submitted to report a potential loss of safety function involving the Unit 3 HPCI system due to this leak.
"Since the initial report, engineering has determined that HPCI was capable of performing its safety function at the time the instrument sensing line was leaking. The evaluation determined that the small sensing line leak would not have resulted in any significant equipment qualification, internal flooding or other equipment concerns that could have affected the HPCI system capability during any postulated design basis events. The pressure indicating instrument supplied by the sensing line is not safety related and is not required for any HPCI function or HPCI operability. Therefore, HPCI was determined to have maintained its operability during the time period that the HPCI sensing line was leaking.
"The NRC resident has been informed of the retraction."
Notified R1DO (Powell).
"On 06/26/11, at 0030 [hrs. EDT], Peach Bottom Atomic Power Station Unit 3 declared the High Pressure Coolant Injection [HPCI] system inoperable for an ASME class 2 exempt piping leak found during operator rounds. Piping on the steam line pressure indication sensing line downstream of a sensing line root valve had an approximate 5 drop per minute leak. The leak has been isolated and the Unit 3 HPCI system was restored to an operable condition as of 0347 on 06/26/11.
"This report is being submitted pursuant to 10CFR 50.72(b)(3)(v)(D)."
The licensee notified the NRC Resident Inspector.
* * * RETRACTION ON 08/08/2011 AT 1432 EDT FROM DAVE FOSS TO RYAN ALEXANDER * * *
"The purpose of this notification is to retract a previous report made on 06/26/11 at 0525 [EDT] (EN# 46987). Notification of this event to the NRC was initially made as a result of declaring the Unit 3 High Pressure Coolant Injection (HPCI) system inoperable on 06/26/11 at 0030 [EDT] when a small leak on an instrument sensing line was found during performance of routine operator rounds. Specifically, it was observed that the 1/2 inch instrument piping for the non-safety related HPCI steam supply pressure indicator was leaking at approximately 5 drops per minute. The location of the leak was downstream of the instrument line root valve. The leak was isolated and the Unit 3 HPCI system was considered operable at approximately 0347 [EDT] on 06/26/11. The ENS report on 06/26/11 was originally submitted to report a potential loss of safety function involving the Unit 3 HPCI system due to this leak.
"Since the initial report, engineering has determined that HPCI was capable of performing its safety function at the time the instrument sensing line was leaking. The evaluation determined that the small sensing line leak would not have resulted in any significant equipment qualification, internal flooding or other equipment concerns that could have affected the HPCI system capability during any postulated design basis events. The pressure indicating instrument supplied by the sensing line is not safety related and is not required for any HPCI function or HPCI operability. Therefore, HPCI was determined to have maintained its operability during the time period that the HPCI sensing line was leaking.
"The NRC resident has been informed of the retraction."
Notified R1DO (Powell).
Power Reactor
Event Number: 46988
Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [] []
RX Type: (1) CE
NRC Notified By: AMY BURKHART
HQ OPS Officer: HOWIE CROUCH
Region: 4 State: NE
Unit: [1] [] []
RX Type: (1) CE
NRC Notified By: AMY BURKHART
HQ OPS Officer: HOWIE CROUCH
Notification Date: 06/26/2011
Notification Time: 07:58 [ET]
Event Date: 06/26/2011
Event Time: 00:00 [CDT]
Last Update Date: 06/26/2011
Notification Time: 07:58 [ET]
Event Date: 06/26/2011
Event Time: 00:00 [CDT]
Last Update Date: 06/26/2011
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):
R4IRC (WALKER) (R4)
RICK DEESE (R4DO)
R4IRC (WALKER) (R4)
RICK DEESE (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
BOTH EMERGENCY DIESEL GENERATORS SUPPLYING PLANT EMERGENCY BUSES PER PLANT PROCEDURE
"At approximately 0125 [hrs. CDT], the AquaDam providing enhanced flood protection for FCS [Ft. Calhoun Station] Unit 1 failed. At 0221, as a precautionary measure, DG-2 [Diesel Generator] was automatically started per plant procedure to divorce bus 1A4 from offsite power. At 0250, DG-1 was automatically started to divorce bus 1A3. Both Emergency Diesel Generators loaded on buses as designed. 345KV and 161KV offsite power remain available.
"This is reportable pursuant to 10CFR50.72(b)(3)(iv)(A), 'System Actuation of the Emergency Diesel Generators'. All safety related flood protection barriers remain in place.
"Current river level is 1006.5' MSL and stable. FCS remains in a NOUE [Notification of Unusual Event] due to high river level.
"NRC personnel stationed onsite for flood monitoring have been informed."
"At approximately 0125 [hrs. CDT], the AquaDam providing enhanced flood protection for FCS [Ft. Calhoun Station] Unit 1 failed. At 0221, as a precautionary measure, DG-2 [Diesel Generator] was automatically started per plant procedure to divorce bus 1A4 from offsite power. At 0250, DG-1 was automatically started to divorce bus 1A3. Both Emergency Diesel Generators loaded on buses as designed. 345KV and 161KV offsite power remain available.
"This is reportable pursuant to 10CFR50.72(b)(3)(iv)(A), 'System Actuation of the Emergency Diesel Generators'. All safety related flood protection barriers remain in place.
"Current river level is 1006.5' MSL and stable. FCS remains in a NOUE [Notification of Unusual Event] due to high river level.
"NRC personnel stationed onsite for flood monitoring have been informed."
Power Reactor
Event Number: 46989
Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [] []
RX Type: (1) CE
NRC Notified By: NATHAN SEID
HQ OPS Officer: DONALD NORWOOD
Region: 4 State: NE
Unit: [1] [] []
RX Type: (1) CE
NRC Notified By: NATHAN SEID
HQ OPS Officer: DONALD NORWOOD
Notification Date: 06/26/2011
Notification Time: 12:22 [ET]
Event Date: 06/26/2011
Event Time: 10:45 [CDT]
Last Update Date: 06/26/2011
Notification Time: 12:22 [ET]
Event Date: 06/26/2011
Event Time: 10:45 [CDT]
Last Update Date: 06/26/2011
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):
RICK DEESE (R4DO)
RICK DEESE (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
OFFSITE NOTIFICATION DUE TO PETROLEUM RELEASE TO THE MISSOURI RIVER
"At approximately 0125 CDT, the AquaDam providing enhanced flood protection for Fort Calhoun Station Unit 1 failed. This resulted in approximately 100 gallons of petroleum being released into the river after a protective barrier was breached and many fuel containers were washed out to the river. The fuel/oil containers were staged around the facility to supply fuel for pumps which remove water within the flood containment barriers. The spill was reported to the State of Nebraska at 10:45 AM CDT on 6/26/2011.
"This condition is being reported pursuant to 10 CFR 50.72(b)(2)(xi) for News Release or Notification of Other Government Agency. Applicable governmental agencies have been notified per plant procedures."
The licensee notified the NRC Resident Inspector.
"At approximately 0125 CDT, the AquaDam providing enhanced flood protection for Fort Calhoun Station Unit 1 failed. This resulted in approximately 100 gallons of petroleum being released into the river after a protective barrier was breached and many fuel containers were washed out to the river. The fuel/oil containers were staged around the facility to supply fuel for pumps which remove water within the flood containment barriers. The spill was reported to the State of Nebraska at 10:45 AM CDT on 6/26/2011.
"This condition is being reported pursuant to 10 CFR 50.72(b)(2)(xi) for News Release or Notification of Other Government Agency. Applicable governmental agencies have been notified per plant procedures."
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 46990
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: MARCY BLOW
HQ OPS Officer: DONALD NORWOOD
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: MARCY BLOW
HQ OPS Officer: DONALD NORWOOD
Notification Date: 06/26/2011
Notification Time: 18:00 [ET]
Event Date: 06/26/2011
Event Time: 16:09 [CDT]
Last Update Date: 06/26/2011
Notification Time: 18:00 [ET]
Event Date: 06/26/2011
Event Time: 16:09 [CDT]
Last Update Date: 06/26/2011
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):
RICK DEESE (R4DO)
RICK DEESE (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | M/R | Y | 82 | Power Operation | 0 | Hot Standby |
REACTOR MANUAL TRIP DUE TO MAIN FEED PUMP TRIP
"6/26/11 at 1609 CDT, the reactor was manually tripped due to the trip of the 'B' Main Feed Pump while operating in Mode 1 at approximately 82% reactor power. The unit was increasing power to 95% after the current refuel outage. The cause of the trip of the 'B' Main Feed Pump is not known at this time. All equipment functioned normally as expected. The investigation into the cause of the 'B' Main Feed Pump trip is ongoing at this time.
"Current plant status is Mode 3. The NRC Senior Resident has been contacted."
All rods fully inserted upon reactor trip. The unit is stable with Auxiliary Feedwater supplying the Steam Generators. Decay heat is being removed to the Main Condenser via steam dumps. The electrical system is in a normal post-trip alignment. The licensee characterized the reactor trip as uncomplicated.
* * * UPDATE FROM MARCY BLOW TO DONALD NORWOOD AT 1923 EDT ON 6/26/2011 * * *
"A valid Auxiliary Feed[water] actuation signal [occurred] due to trip of both of the Main Feed pumps from a turbine trip and low steam generator levels. This is reportable under 10CFR50.72 (b)(3)(iv)(A), 8-hour report. All auxiliary feed pumps started and operated as expected."
The licensee will notify the NRC Resident Inspector.
Notified R4DO (Deese).
"6/26/11 at 1609 CDT, the reactor was manually tripped due to the trip of the 'B' Main Feed Pump while operating in Mode 1 at approximately 82% reactor power. The unit was increasing power to 95% after the current refuel outage. The cause of the trip of the 'B' Main Feed Pump is not known at this time. All equipment functioned normally as expected. The investigation into the cause of the 'B' Main Feed Pump trip is ongoing at this time.
"Current plant status is Mode 3. The NRC Senior Resident has been contacted."
All rods fully inserted upon reactor trip. The unit is stable with Auxiliary Feedwater supplying the Steam Generators. Decay heat is being removed to the Main Condenser via steam dumps. The electrical system is in a normal post-trip alignment. The licensee characterized the reactor trip as uncomplicated.
* * * UPDATE FROM MARCY BLOW TO DONALD NORWOOD AT 1923 EDT ON 6/26/2011 * * *
"A valid Auxiliary Feed[water] actuation signal [occurred] due to trip of both of the Main Feed pumps from a turbine trip and low steam generator levels. This is reportable under 10CFR50.72 (b)(3)(iv)(A), 8-hour report. All auxiliary feed pumps started and operated as expected."
The licensee will notify the NRC Resident Inspector.
Notified R4DO (Deese).
Power Reactor
Event Number: 46991
Facility: SEQUOYAH
Region: 2 State: TN
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JEFF EPPERSON
HQ OPS Officer: CHARLES TEAL
Region: 2 State: TN
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JEFF EPPERSON
HQ OPS Officer: CHARLES TEAL
Notification Date: 06/26/2011
Notification Time: 19:39 [ET]
Event Date: 06/26/2011
Event Time: 16:14 [EDT]
Last Update Date: 06/26/2011
Notification Time: 19:39 [ET]
Event Date: 06/26/2011
Event Time: 16:14 [EDT]
Last Update Date: 06/26/2011
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):
GERALD MCCOY (R2DO)
GERALD MCCOY (R2DO)
| 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 DUE TO TURBINE TRIP
"At 1614 EDT on 6/26/2011, Unit 1 reactor automatically tripped following a turbine trip from greater than 50% rated thermal power (P-9 interlock).
"Following the reactor trip, all safety-related equipment operated as designed. Auxiliary Feedwater automatically actuated as expected on loss of the operating main feedwater pumps.
"Initially, the steam dump system functioned as expected (all valves opened). Subsequently, the steam dump system was manually turned off when 3 of the valves did not close when expected. Consequently, decay heat removal is via the Steam Generators' atmospheric relief valves.
"No primary or secondary safety valves opened during or after this trip.
"Unit 1 is currently being maintained in Mode 3 at NOT/NOP, approximately 548 degrees F and 2235 psig, with auxiliary feedwater supplying the steam generators."
There is no indications of any primary to secondary leakage. All control and shutdown rods are inserted. The electrical alignment is normal, supplied from off-site power. There was no impact to Unit 2. Unit 2 is operating at 100% power / Mode 1"
The NRC Resident Inspector has been notified.
"At 1614 EDT on 6/26/2011, Unit 1 reactor automatically tripped following a turbine trip from greater than 50% rated thermal power (P-9 interlock).
"Following the reactor trip, all safety-related equipment operated as designed. Auxiliary Feedwater automatically actuated as expected on loss of the operating main feedwater pumps.
"Initially, the steam dump system functioned as expected (all valves opened). Subsequently, the steam dump system was manually turned off when 3 of the valves did not close when expected. Consequently, decay heat removal is via the Steam Generators' atmospheric relief valves.
"No primary or secondary safety valves opened during or after this trip.
"Unit 1 is currently being maintained in Mode 3 at NOT/NOP, approximately 548 degrees F and 2235 psig, with auxiliary feedwater supplying the steam generators."
There is no indications of any primary to secondary leakage. All control and shutdown rods are inserted. The electrical alignment is normal, supplied from off-site power. There was no impact to Unit 2. Unit 2 is operating at 100% power / Mode 1"
The NRC Resident Inspector has been notified.
Power Reactor
Event Number: 46992
Facility: SALEM
Region: 1 State: NJ
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOHN KONOVALCHICK
HQ OPS Officer: CHARLES TEAL
Region: 1 State: NJ
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOHN KONOVALCHICK
HQ OPS Officer: CHARLES TEAL
Notification Date: 06/26/2011
Notification Time: 22:08 [ET]
Event Date: 06/26/2011
Event Time: 18:00 [EDT]
Last Update Date: 06/26/2011
Notification Time: 22:08 [ET]
Event Date: 06/26/2011
Event Time: 18:00 [EDT]
Last Update Date: 06/26/2011
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):
CHRISTOPHER CAHILL (R1DO)
CHRISTOPHER CAHILL (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
AUTOMATIC REACTOR TRIP DUE TO LOSS OF REACTOR COOLANT PUMP
"This notification is being made to report that Salem Unit 2 has experienced an automatic reactor trip. The trip was caused by 23 Reactor Coolant (RC) loop low flow and P-8 caused by 23 reactor coolant pump trip. The cause of the 23 Reactor Coolant Pump trip is under post reactor trip investigation. Main Feedwater to the Steam Generators was isolated due to the 'Feed Water Interlock' which is expected on a reactor trip. The Auxiliary Feed Water (AFW) system auto started on low Steam Generator levels. This is also expected on a reactor trip. 21, 22 and 23 AFW pumps all automatically started and fed the Steam Generators. 23 AFW pump has been shutdown by procedure and is available.
"The crew entered EOP-TRIP-1, and then transitioned to EOP-TRIP-2 and stabilized the plant at no load conditions. Salem Unit 2 is currently in Mode 3. Reactor Coolant System temperature is 547 degrees F with pressure at 2235 psig NOP/NOT. 21, 22, and 24 Reactor Coolant Pumps are in service.
"Decay heat removal is being provided by 21 and 22 AFW pumps via the Main Steam Dump System. All shutdown and control rods fully inserted on the reactor trip. The plant is aligned with normal electrical lineup from offsite power sources.
"There were no personnel injuries associated with this event."
The NRC Resident Inspector has been informed.
"This notification is being made to report that Salem Unit 2 has experienced an automatic reactor trip. The trip was caused by 23 Reactor Coolant (RC) loop low flow and P-8 caused by 23 reactor coolant pump trip. The cause of the 23 Reactor Coolant Pump trip is under post reactor trip investigation. Main Feedwater to the Steam Generators was isolated due to the 'Feed Water Interlock' which is expected on a reactor trip. The Auxiliary Feed Water (AFW) system auto started on low Steam Generator levels. This is also expected on a reactor trip. 21, 22 and 23 AFW pumps all automatically started and fed the Steam Generators. 23 AFW pump has been shutdown by procedure and is available.
"The crew entered EOP-TRIP-1, and then transitioned to EOP-TRIP-2 and stabilized the plant at no load conditions. Salem Unit 2 is currently in Mode 3. Reactor Coolant System temperature is 547 degrees F with pressure at 2235 psig NOP/NOT. 21, 22, and 24 Reactor Coolant Pumps are in service.
"Decay heat removal is being provided by 21 and 22 AFW pumps via the Main Steam Dump System. All shutdown and control rods fully inserted on the reactor trip. The plant is aligned with normal electrical lineup from offsite power sources.
"There were no personnel injuries associated with this event."
The NRC Resident Inspector has been informed.