Event Notification Report for October 24, 2012
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
10/23/2012 - 10/24/2012
EVENT NUMBERS
4843948440484364843748557
Power Reactor
Event Number: 48439
Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: DAVID NOYES
HQ OPS Officer: PETE SNYDER
Region: 1 State: MA
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: DAVID NOYES
HQ OPS Officer: PETE SNYDER
Notification Date: 10/24/2012
Notification Time: 19:23 [ET]
Event Date: 10/24/2012
Event Time: 19:20 [EDT]
Last Update Date: 10/24/2012
Notification Time: 19:23 [ET]
Event Date: 10/24/2012
Event Time: 19:20 [EDT]
Last Update Date: 10/24/2012
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):
JOHN CARUSO (R1DO)
JOHN CARUSO (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 |
PRESS RELEASE REGARDING STATUS OF ONGOING LABOR NEGOTIATIONS
"On October 24, 2012, at 1920 EDT hours with the reactor at 100% core thermal power the following press release is being issued by Entergy Nuclear regarding the status of the ongoing labor negotiations.
"ENTERGY NUCLEAR STATEMENT - ENTERGY AND UWUA LOCAL 369 AGREE TO TENTATIVE CONTRACT
"October 24, 2012
"Plymouth, Mass. - Entergy Nuclear and the Utility Workers Union of America (UWUA) reached a tentative agreement today on a new four-year labor contract for Local 369 technical employees at Pilgrim Station, pending a ratification vote by Union membership.
"Additionally, the parties have agreed to a 21-day extension that will expire at midnight on Nov. 14. The previous contract for the approximately 67 workers affected by this union contract will remain in effect during the extension. The original contract was set to expire at midnight Oct. 24.
"Pilgrim's Site Vice President Robert Smith said, 'We appreciate the hard work of both parties to come to a successful outcome to this negotiation process. We believe the new proposal represents fair and equitable terms both for our employees and the Company.'
"END
"The Resident Inspector staff has been informed of this press release and notification.
"This notification is being made in accordance with 10 CFR 50.72(b)(2)(xi)."
"On October 24, 2012, at 1920 EDT hours with the reactor at 100% core thermal power the following press release is being issued by Entergy Nuclear regarding the status of the ongoing labor negotiations.
"ENTERGY NUCLEAR STATEMENT - ENTERGY AND UWUA LOCAL 369 AGREE TO TENTATIVE CONTRACT
"October 24, 2012
"Plymouth, Mass. - Entergy Nuclear and the Utility Workers Union of America (UWUA) reached a tentative agreement today on a new four-year labor contract for Local 369 technical employees at Pilgrim Station, pending a ratification vote by Union membership.
"Additionally, the parties have agreed to a 21-day extension that will expire at midnight on Nov. 14. The previous contract for the approximately 67 workers affected by this union contract will remain in effect during the extension. The original contract was set to expire at midnight Oct. 24.
"Pilgrim's Site Vice President Robert Smith said, 'We appreciate the hard work of both parties to come to a successful outcome to this negotiation process. We believe the new proposal represents fair and equitable terms both for our employees and the Company.'
"END
"The Resident Inspector staff has been informed of this press release and notification.
"This notification is being made in accordance with 10 CFR 50.72(b)(2)(xi)."
Power Reactor
Event Number: 48440
Facility: HARRIS
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: RYAN MacNAIL
HQ OPS Officer: STEVE SANDIN
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: RYAN MacNAIL
HQ OPS Officer: STEVE SANDIN
Notification Date: 10/24/2012
Notification Time: 20:09 [ET]
Event Date: 10/24/2012
Event Time: 15:30 [EDT]
Last Update Date: 10/24/2012
Notification Time: 20:09 [ET]
Event Date: 10/24/2012
Event Time: 15:30 [EDT]
Last Update Date: 10/24/2012
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):
RANDY MUSSER (R2DO)
RANDY MUSSER (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 |
TECHNICAL SUPPORT CENTER VENTILATION SUPPORT SYSTEM NON-FUNCTIONAL
"At 3:30 PM EDT on October 24, 2012, Harris Operations discovered that the Technical Support Center (TSC) outside differential pressure controller (PDC-4011) was not working. This pressure controller makes the TSC non-functional due to the ventilation system not being capable of maintaining a positive pressure with respect to outside. Procedural guidance exists for the Radiation Protection staff to perform continuous air monitoring of the TSC atmosphere to determine habitability conditions. Actions are being taken to expeditiously restore the system.
"This event is reportable per 10 CFR 50.72(b)(3)(xiii) due to the Technical Support Center ventilation support system being non-functional. The on call Site Emergency Coordinator and Emergency Response Manager have been notified.
"The NRC Senior Resident Inspector has been informed."
"At 3:30 PM EDT on October 24, 2012, Harris Operations discovered that the Technical Support Center (TSC) outside differential pressure controller (PDC-4011) was not working. This pressure controller makes the TSC non-functional due to the ventilation system not being capable of maintaining a positive pressure with respect to outside. Procedural guidance exists for the Radiation Protection staff to perform continuous air monitoring of the TSC atmosphere to determine habitability conditions. Actions are being taken to expeditiously restore the system.
"This event is reportable per 10 CFR 50.72(b)(3)(xiii) due to the Technical Support Center ventilation support system being non-functional. The on call Site Emergency Coordinator and Emergency Response Manager have been notified.
"The NRC Senior Resident Inspector has been informed."
Power Reactor
Event Number: 48436
Facility: NORTH ANNA
Region: 2 State: VA
Unit: [] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP,[3] M-4-LP
NRC Notified By: JONATHAN ALLEN
HQ OPS Officer: BILL HUFFMAN
Region: 2 State: VA
Unit: [] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP,[3] M-4-LP
NRC Notified By: JONATHAN ALLEN
HQ OPS Officer: BILL HUFFMAN
Notification Date: 10/24/2012
Notification Time: 02:40 [ET]
Event Date: 10/24/2012
Event Time: 01:47 [EDT]
Last Update Date: 10/24/2012
Notification Time: 02:40 [ET]
Event Date: 10/24/2012
Event Time: 01:47 [EDT]
Last Update Date: 10/24/2012
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):
RANDY MUSSER (R2DO)
MICHELE EVANS (NRR)
JANE MARSHALL (IRD)
RANDY MUSSER (R2DO)
MICHELE EVANS (NRR)
JANE MARSHALL (IRD)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A/R | Y | 99 | Power Operation | 0 | Hot Standby |
AUTOMATIC REACTOR TRIP ON LOW STEAM GENERATOR WATER LEVEL
"On 10/24/12 at 0147, North Anna Unit 2 reactor tripped automatically. The reactor first out is the 'C' steam generator lo-lo level. The turbine first out is reactor tripped, turbine trip. The event was apparently initiated by a loss of load on the secondary side. The cause of the loss of load is still being investigated. All systems responded as expected. This event is reportable per 10 CFR 50.72(b)(2)(iv)(B) due to actuation of the Reactor Protection System.
"The Auxiliary Feedwater pumps received an automatic start signal due to low-low level in all steam generators at the time of the trip, Steam generator levels have been restored to normal operating level. The Auxiliary Feedwater System operated as designed with no abnormalities noted. This event is reportable per 10 CFR 50.72(b)(3)(iv)(A) due to actuation of an ESF system.
"All control rods inserted into the core at the time of the trip and decay heat is being removed via the main condenser steam dumps. Several secondary [feedwater] relief valves lifted and reseated during the event. North Anna Unit 2 is currently stable at no load temperature and pressure in mode 3.
"At 0147 EDT, the Unit 2 Pressurizer Power Operated Relief Valve (PORV) , 2-RC-PCV-2455C, opened during an automatic reactor trip of Unit 2. The valve indicated open for less than 1 second. During this time, the identified leakage threshold for EAL SU6.1 [25 gpm] was exceeded."
The cause of the loss of secondary load, which is believed to have caused the low steam generator water level and the lifting of the pressurizer PORV, is still under investigation. The licensee is focusing on the high pressure to low pressure turbine intercept valves or reheat valves going shut for reasons unknown at this time. The licensee's data shows that a pressurizer PORV opened momentarily. The instantaneous leak rate exceeded the unusual event threshold leak rate of 25 gpm. The PORV reseated and no ongoing leakage occurred during the transient. The rest of the transient was characterized as uncomplicated. The unit is in a normal post-trip electrical configuration. All systems functioned as required. There was no impact on Unit 1.
The licensee has notified the NRC Resident Inspector.
* * * UPDATE AT 1346 EDT ON 10/24/12 FROM PAGE KEMP TO S. SANDIN * * *
The licensee is updating their report to RETRACT the portion related to the after-the-fact entry into EAL SU6.
"At 0147 hours EDT on 10-24-12, a Unit 2 Pressurizer Power Operated Relief Valve, 2-RC-PCV-2455C, opened during automatic reactor trip. The valve indicated open for less than 1 second. 2-RC-PCV-2455C opened as designed in response to the plant trip and allowed a small amount of water to transfer to the Pressurizer Relief Tank, as designed. The Pressurizer Power Operated Relief Valve subsequently re-closed and remains available for automatic operation, if needed. Initially, this issue was reported to the NRC at 0240 hours on 10-24-12 as an After-The-Fact Unusual Event for EAL SU6.1. Subsequent review has determined that the Pressurizer Power Operated Relief Valve functioned as designed and the small amount of inventory was transferred to the Pressurizer Relief Tank as designed and therefore does not meet the criteria for an Unusual Event and this notification is being retracted.
"NEI 99-01, Rev. 5 provides additional guidance that relief valve normal operation should be excluded from this Initiating Condition. However, a relief valve that operates and fails to close per design should be considered applicable to this Initiating Condition if the relief valve cannot be isolated. In this case, the Pressurizer Power Operated Relief Valve operated as designed and returned to automatic operation."
The licensee informed state and local agencies and the NRC Resident Inspector. Notified R2DO (Musser).
"On 10/24/12 at 0147, North Anna Unit 2 reactor tripped automatically. The reactor first out is the 'C' steam generator lo-lo level. The turbine first out is reactor tripped, turbine trip. The event was apparently initiated by a loss of load on the secondary side. The cause of the loss of load is still being investigated. All systems responded as expected. This event is reportable per 10 CFR 50.72(b)(2)(iv)(B) due to actuation of the Reactor Protection System.
"The Auxiliary Feedwater pumps received an automatic start signal due to low-low level in all steam generators at the time of the trip, Steam generator levels have been restored to normal operating level. The Auxiliary Feedwater System operated as designed with no abnormalities noted. This event is reportable per 10 CFR 50.72(b)(3)(iv)(A) due to actuation of an ESF system.
"All control rods inserted into the core at the time of the trip and decay heat is being removed via the main condenser steam dumps. Several secondary [feedwater] relief valves lifted and reseated during the event. North Anna Unit 2 is currently stable at no load temperature and pressure in mode 3.
"At 0147 EDT, the Unit 2 Pressurizer Power Operated Relief Valve (PORV) , 2-RC-PCV-2455C, opened during an automatic reactor trip of Unit 2. The valve indicated open for less than 1 second. During this time, the identified leakage threshold for EAL SU6.1 [25 gpm] was exceeded."
The cause of the loss of secondary load, which is believed to have caused the low steam generator water level and the lifting of the pressurizer PORV, is still under investigation. The licensee is focusing on the high pressure to low pressure turbine intercept valves or reheat valves going shut for reasons unknown at this time. The licensee's data shows that a pressurizer PORV opened momentarily. The instantaneous leak rate exceeded the unusual event threshold leak rate of 25 gpm. The PORV reseated and no ongoing leakage occurred during the transient. The rest of the transient was characterized as uncomplicated. The unit is in a normal post-trip electrical configuration. All systems functioned as required. There was no impact on Unit 1.
The licensee has notified the NRC Resident Inspector.
* * * UPDATE AT 1346 EDT ON 10/24/12 FROM PAGE KEMP TO S. SANDIN * * *
The licensee is updating their report to RETRACT the portion related to the after-the-fact entry into EAL SU6.
"At 0147 hours EDT on 10-24-12, a Unit 2 Pressurizer Power Operated Relief Valve, 2-RC-PCV-2455C, opened during automatic reactor trip. The valve indicated open for less than 1 second. 2-RC-PCV-2455C opened as designed in response to the plant trip and allowed a small amount of water to transfer to the Pressurizer Relief Tank, as designed. The Pressurizer Power Operated Relief Valve subsequently re-closed and remains available for automatic operation, if needed. Initially, this issue was reported to the NRC at 0240 hours on 10-24-12 as an After-The-Fact Unusual Event for EAL SU6.1. Subsequent review has determined that the Pressurizer Power Operated Relief Valve functioned as designed and the small amount of inventory was transferred to the Pressurizer Relief Tank as designed and therefore does not meet the criteria for an Unusual Event and this notification is being retracted.
"NEI 99-01, Rev. 5 provides additional guidance that relief valve normal operation should be excluded from this Initiating Condition. However, a relief valve that operates and fails to close per design should be considered applicable to this Initiating Condition if the relief valve cannot be isolated. In this case, the Pressurizer Power Operated Relief Valve operated as designed and returned to automatic operation."
The licensee informed state and local agencies and the NRC Resident Inspector. Notified R2DO (Musser).
Power Reactor
Event Number: 48437
Facility: LASALLE
Region: 3 State: IL
Unit: [1] [2] []
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: CHRISTOPHER SMITH
HQ OPS Officer: BILL HUFFMAN
Region: 3 State: IL
Unit: [1] [2] []
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: CHRISTOPHER SMITH
HQ OPS Officer: BILL HUFFMAN
Notification Date: 10/24/2012
Notification Time: 09:31 [ET]
Event Date: 10/24/2012
Event Time: 08:25 [CDT]
Last Update Date: 10/24/2012
Notification Time: 09:31 [ET]
Event Date: 10/24/2012
Event Time: 08:25 [CDT]
Last Update Date: 10/24/2012
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):
PATTY PELKE (R3DO)
PATTY PELKE (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
TECHNICAL SUPPORT CENTER VENTILATION REMOVED FROM SERVICE FOR PLANNED MAINTENANCE
"On October 24, 2012, at approximately 08:25 hrs [CDT], the Exelon LaSalle Station Technical Support Center (TSC) Ventilation system was removed from service for planned TSC ventilation system maintenance.
"The removal of the ventilation system potentially affects the TSC habitability during a declared emergency requiring activation. The Emergency Response Organization (ERO) team has been notified of the maintenance and the possible need to relocate during an emergency. If an emergency is declared and the TSC ERO activation is required, the TSC will be staffed and activated unless the TSC becomes uninhabitable due to ambient temperatures, radiological, or other conditions. If relocation of the TSC staff becomes necessary, the Station Emergency Director will relocate the staff to an alternate TSC location in accordance with applicable site procedures.
"The ventilation system is expected to be out of service for approximately 21 hours.
"This telephone notification is provided in accordance with Exelon Reportability Manual SAF 1.10, 'Major Loss of Emergency Preparedness Capabilities', and 10CFR50.72(b)(3)(xiii)."
The licensee has notified the Senior Resident Inspector of the issue.
"On October 24, 2012, at approximately 08:25 hrs [CDT], the Exelon LaSalle Station Technical Support Center (TSC) Ventilation system was removed from service for planned TSC ventilation system maintenance.
"The removal of the ventilation system potentially affects the TSC habitability during a declared emergency requiring activation. The Emergency Response Organization (ERO) team has been notified of the maintenance and the possible need to relocate during an emergency. If an emergency is declared and the TSC ERO activation is required, the TSC will be staffed and activated unless the TSC becomes uninhabitable due to ambient temperatures, radiological, or other conditions. If relocation of the TSC staff becomes necessary, the Station Emergency Director will relocate the staff to an alternate TSC location in accordance with applicable site procedures.
"The ventilation system is expected to be out of service for approximately 21 hours.
"This telephone notification is provided in accordance with Exelon Reportability Manual SAF 1.10, 'Major Loss of Emergency Preparedness Capabilities', and 10CFR50.72(b)(3)(xiii)."
The licensee has notified the Senior Resident Inspector of the issue.
Agreement State
Event Number: 48557
Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: WINFIELD ALLOY, INC.
Region: 1
City: LAWRENCE State: MA
County:
License #: NONE
Agreement: Y
Docket:
NRC Notified By: BRUCE PACKARD
HQ OPS Officer: STEVE SANDIN
Licensee: WINFIELD ALLOY, INC.
Region: 1
City: LAWRENCE State: MA
County:
License #: NONE
Agreement: Y
Docket:
NRC Notified By: BRUCE PACKARD
HQ OPS Officer: STEVE SANDIN
Notification Date: 12/04/2012
Notification Time: 15:59 [ET]
Event Date: 10/24/2012
Event Time: 00:00 [EST]
Last Update Date: 12/06/2012
Notification Time: 15:59 [ET]
Event Date: 10/24/2012
Event Time: 00:00 [EST]
Last Update Date: 12/06/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
DON JACKSON (R1DO)
FSME EVENTS RESOURCE (EMAI)
DON JACKSON (R1DO)
FSME EVENTS RESOURCE (EMAI)
AGREEMENT STATE REPORT - RADIUM DIAL COMPASS REJECTED AT RECYCLING FACILITY
The following information was received from the Commonwealth of Massachusetts via fax:
"Abstract:
"10/24/12 - Metal load rejected at recycling facility. Reported to CRCPD. [Conference of Radiation Control Program Directors]
"11/7/12 - Compass with suspected Ra dial was recovered from trash load.
"12/4/12 - Compass was identified as 13.8 microCuries Ra-226. Compass was worn on wrist and was labeled Sperio Magneto Company."
* * * UPDATE VIA FAX FROM JOSH DAEHLER TO DONALD NORWOOD AT 1534 EST ON 12/6/12 * * *
"The compass source is now stored in Rockland, MA, pending disposal, in accordance with Atlantic Nuclear's specific radioactive materials license No. 56-0477. The compass source is reported by Atlantic Nuclear to have passed a leak test; be of excellent condition; and to exhibit a dose rate of approximately 8 to 10 microrem/hr at one meter from the source, as measured by a calibrated ion chamber. The compass source appears to be of type that was designed to have been worn on a wrist or attached by hook to a belt or lanyard."
Notified R1DO (Jackson). Notified FSME Events Resource via E-mail.
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 information was received from the Commonwealth of Massachusetts via fax:
"Abstract:
"10/24/12 - Metal load rejected at recycling facility. Reported to CRCPD. [Conference of Radiation Control Program Directors]
"11/7/12 - Compass with suspected Ra dial was recovered from trash load.
"12/4/12 - Compass was identified as 13.8 microCuries Ra-226. Compass was worn on wrist and was labeled Sperio Magneto Company."
* * * UPDATE VIA FAX FROM JOSH DAEHLER TO DONALD NORWOOD AT 1534 EST ON 12/6/12 * * *
"The compass source is now stored in Rockland, MA, pending disposal, in accordance with Atlantic Nuclear's specific radioactive materials license No. 56-0477. The compass source is reported by Atlantic Nuclear to have passed a leak test; be of excellent condition; and to exhibit a dose rate of approximately 8 to 10 microrem/hr at one meter from the source, as measured by a calibrated ion chamber. The compass source appears to be of type that was designed to have been worn on a wrist or attached by hook to a belt or lanyard."
Notified R1DO (Jackson). Notified FSME Events Resource via E-mail.
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