Event Notification Report for March 23, 2012
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/22/2012 - 03/23/2012
Power Reactor
Event Number: 47766
Facility: SALEM
Region: 1 State: NJ
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOHN OSBORNE
HQ OPS Officer: PETE SNYDER
Region: 1 State: NJ
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOHN OSBORNE
HQ OPS Officer: PETE SNYDER
Notification Date: 03/23/2012
Notification Time: 17:00 [ET]
Event Date: 03/23/2012
Event Time: 14:28 [EDT]
Last Update Date: 03/23/2012
Notification Time: 17:00 [ET]
Event Date: 03/23/2012
Event Time: 14:28 [EDT]
Last Update Date: 03/23/2012
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):
WAYNE SCHMIDT (R1DO)
WAYNE SCHMIDT (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 |
TURBINE TRIP FOLLOWED BY AUTOMATIC REACTOR TRIP
"Salem Unit 2 has experienced an automatic reactor trip at 1428 hours on 3/23/12.
"Salem Unit 2 tripped due to a turbine trip above [permissive] P-9. All shutdown and control rods fully inserted on the reactor trip.
"At the time of the trip 22 station power transformer [SPT], the 2F and 2G 4KV group buses were not energized causing a loss of 23 and 24 reactor coolant pumps. The auxiliary feedwater (AFW) system auto-started to provide feed to the steam generators.
"The crew entered EOP-TRIP-1, then transitioned to the EOP-TRIP-2 and stabilized the plant. Salem Unit 2 is currently in Mode 3 at normal operating temperature and pressure with 21 and 22 reactor coolant pumps in service.
"There are no shutdown technical specifications in effect. All ECCS and ESF systems are available. Decay heat removal is being provided by 21 and 22 AFW pumps and the main steam dump system. The plant is aligned with a normal electrical line-up from offsite power sources with the exception of 22 SPT. Restoration of the 22 SPT and 2F and 2G 4KV group buses is in progress.
"There were no personnel injuries associated with this event.
"This event is reportable per 10 CFR 50.72 (b)(3)(iv)(A) due to the auto-start of the auxiliary feed water pumps."
The licensee notified the NRC Resident Inspector. The licensee will notify Lower Alloways Creek Township and the States of New Jersey and Delaware. The licensee anticipates making a press release.
* * * UPDATE FROM WILLIAM MUFFLEY TO PETE SNYDER AT 2127 EDT ON 3/23/12 * * *
"During the post trip review ... two additional AFW pump start signals were identified. At 1429 hrs. EDT with RCPs 23 and 24 tripped the 21 and 22 steam generators (SG) dipped below the lo-lo level setpoints and caused an AFW actuation to occur. At 1457 hrs. EDT 23 turbine driven AFW pump was stopped in accordance with operating procedures. At 1509 hrs. EDT the 21 SG cleared the low level setpoint and at 1513 hrs. EDT the 22 SG cleared the low level setpoint. At 1523 hrs. EDT the 22 SG dipped below the lo-lo level setpoint and caused an AFW actuation to occur. The two motor drive AFW pumps continued to run throughout this event.
"The licensee notified the NRC Resident Inspector and will notify Lower Alloways Creek Township and the States of New Jersey and Delaware."
Notified R1DO (Schmidt).
"Salem Unit 2 has experienced an automatic reactor trip at 1428 hours on 3/23/12.
"Salem Unit 2 tripped due to a turbine trip above [permissive] P-9. All shutdown and control rods fully inserted on the reactor trip.
"At the time of the trip 22 station power transformer [SPT], the 2F and 2G 4KV group buses were not energized causing a loss of 23 and 24 reactor coolant pumps. The auxiliary feedwater (AFW) system auto-started to provide feed to the steam generators.
"The crew entered EOP-TRIP-1, then transitioned to the EOP-TRIP-2 and stabilized the plant. Salem Unit 2 is currently in Mode 3 at normal operating temperature and pressure with 21 and 22 reactor coolant pumps in service.
"There are no shutdown technical specifications in effect. All ECCS and ESF systems are available. Decay heat removal is being provided by 21 and 22 AFW pumps and the main steam dump system. The plant is aligned with a normal electrical line-up from offsite power sources with the exception of 22 SPT. Restoration of the 22 SPT and 2F and 2G 4KV group buses is in progress.
"There were no personnel injuries associated with this event.
"This event is reportable per 10 CFR 50.72 (b)(3)(iv)(A) due to the auto-start of the auxiliary feed water pumps."
The licensee notified the NRC Resident Inspector. The licensee will notify Lower Alloways Creek Township and the States of New Jersey and Delaware. The licensee anticipates making a press release.
* * * UPDATE FROM WILLIAM MUFFLEY TO PETE SNYDER AT 2127 EDT ON 3/23/12 * * *
"During the post trip review ... two additional AFW pump start signals were identified. At 1429 hrs. EDT with RCPs 23 and 24 tripped the 21 and 22 steam generators (SG) dipped below the lo-lo level setpoints and caused an AFW actuation to occur. At 1457 hrs. EDT 23 turbine driven AFW pump was stopped in accordance with operating procedures. At 1509 hrs. EDT the 21 SG cleared the low level setpoint and at 1513 hrs. EDT the 22 SG cleared the low level setpoint. At 1523 hrs. EDT the 22 SG dipped below the lo-lo level setpoint and caused an AFW actuation to occur. The two motor drive AFW pumps continued to run throughout this event.
"The licensee notified the NRC Resident Inspector and will notify Lower Alloways Creek Township and the States of New Jersey and Delaware."
Notified R1DO (Schmidt).
Agreement State
Event Number: 47943
Rep Org: COLORADO DEPT OF HEALTH
Licensee: PUBLIC SERVICE COMPANY OF COLORADO
Region: 4
City: HAYDEN State: CO
County:
License #: 032-01
Agreement: Y
Docket:
NRC Notified By: MEGAN BROWN
HQ OPS Officer: DONG HWA PARK
Licensee: PUBLIC SERVICE COMPANY OF COLORADO
Region: 4
City: HAYDEN State: CO
County:
License #: 032-01
Agreement: Y
Docket:
NRC Notified By: MEGAN BROWN
HQ OPS Officer: DONG HWA PARK
Notification Date: 05/22/2012
Notification Time: 13:02 [ET]
Event Date: 03/23/2012
Event Time: 00:00 [MDT]
Last Update Date: 05/22/2012
Notification Time: 13:02 [ET]
Event Date: 03/23/2012
Event Time: 00:00 [MDT]
Last Update Date: 05/22/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
BLAIR SPITZBERG (R4DO)
ANGELA MCINTOSH (FSME)
BLAIR SPITZBERG (R4DO)
ANGELA MCINTOSH (FSME)
AGREEMENT STATE REPORT - POTENTIAL OVER EXPOSURE DURING GAUGE REMOVAL
The following information was received via email from the State of Colorado:
"On May 21, 2012, the Colorado Department of Public Health and Environment was notified of an incident which occurred at Public Service Company of Colorado, Colorado License 032-01. The event occurred at the Hayden Station located in Hayden, CO on March 23, 2012. During boiler repairs, two contract workers removed six radiation level detector fixed gauges from an ash hopper without authorization. The gauges were discovered the following day by plant personnel, and it was noted that the shutters were in the open position. Each gauge, Texas Nuclear Model 5197, contained 100 mCi of Cesium-137. Based on dose reconstruction estimates provided by the licensee, it is likely that at least one of the contract workers received an exposure in excess of 2.0 mrem in one hour and up to 6.0 mrem in one hour. No other details are available at this time.
"Event Report ID No.: CO12-I12-09"
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
Note: This device is assigned an IAEA Category 3 value based on the actual radioactivity of the source, not on the device type. (Reference IAEA RG-G-1.9)
The following information was received via email from the State of Colorado:
"On May 21, 2012, the Colorado Department of Public Health and Environment was notified of an incident which occurred at Public Service Company of Colorado, Colorado License 032-01. The event occurred at the Hayden Station located in Hayden, CO on March 23, 2012. During boiler repairs, two contract workers removed six radiation level detector fixed gauges from an ash hopper without authorization. The gauges were discovered the following day by plant personnel, and it was noted that the shutters were in the open position. Each gauge, Texas Nuclear Model 5197, contained 100 mCi of Cesium-137. Based on dose reconstruction estimates provided by the licensee, it is likely that at least one of the contract workers received an exposure in excess of 2.0 mrem in one hour and up to 6.0 mrem in one hour. No other details are available at this time.
"Event Report ID No.: CO12-I12-09"
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
Note: This device is assigned an IAEA Category 3 value based on the actual radioactivity of the source, not on the device type. (Reference IAEA RG-G-1.9)