Event Notification Report for July 31, 2013
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
07/30/2013 - 07/31/2013
Power Reactor
Event Number: 49228
Facility: HARRIS
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: RICHARD DAVIS
HQ OPS Officer: NESTOR MAKRIS
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: RICHARD DAVIS
HQ OPS Officer: NESTOR MAKRIS
Notification Date: 07/31/2013
Notification Time: 11:40 [ET]
Event Date: 07/31/2013
Event Time: 05:10 [EDT]
Last Update Date: 07/31/2013
Notification Time: 11:40 [ET]
Event Date: 07/31/2013
Event Time: 05:10 [EDT]
Last Update Date: 07/31/2013
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):
MICHAEL F. KING (R2DO)
MICHAEL F. KING (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 |
EMERGENCY RESPONSE FACILITY PREPLANNED MAINTENANCE
"This condition does not affect the health and safety of the public or the operation of the facility. At 0510 [EDT] on July 31, 2013, preplanned maintenance commenced which affects the Technical Support Center (TSC) ventilation and radiation monitoring systems. The scope of the maintenance is to inspect and perform functional checks on various TSC ventilation system fans and the outside air intake radiation monitor. This maintenance is scheduled to be performed and completed within approximately 20 hours.
"TSC functionality requires all occupied areas of the TSC be maintained between 60.8 degrees F and 82.4 degrees F. Actual TSC temperatures have been verified to be less than 78 degrees F. If an emergency should occur, the ventilation system will be restored, but potentially not within the time required for activation of the TSC. If the facility were activated with full staff, temperatures could rise above the 82.4 degree F limit. Consideration will be given to relocating the TSC to the alternate emergency facility in accordance with PEP-240. The alternate TSC has been verified to have electrical power, ventilation, and communication capability. The Technical Support Center - Site Emergency Coordinator has been notified.
"The NRC Resident Inspector has been notified."
* * * UPDATE AT 1620 EDT ON 07/31/13 FROM RICHARD DAVIS TO S. SANDIN * * *
Preplanned maintenance was completed at 1540 EDT on 7/31/13. The licensee informed the NRC Resident Inspector.
Notified R2DO (King).
"This condition does not affect the health and safety of the public or the operation of the facility. At 0510 [EDT] on July 31, 2013, preplanned maintenance commenced which affects the Technical Support Center (TSC) ventilation and radiation monitoring systems. The scope of the maintenance is to inspect and perform functional checks on various TSC ventilation system fans and the outside air intake radiation monitor. This maintenance is scheduled to be performed and completed within approximately 20 hours.
"TSC functionality requires all occupied areas of the TSC be maintained between 60.8 degrees F and 82.4 degrees F. Actual TSC temperatures have been verified to be less than 78 degrees F. If an emergency should occur, the ventilation system will be restored, but potentially not within the time required for activation of the TSC. If the facility were activated with full staff, temperatures could rise above the 82.4 degree F limit. Consideration will be given to relocating the TSC to the alternate emergency facility in accordance with PEP-240. The alternate TSC has been verified to have electrical power, ventilation, and communication capability. The Technical Support Center - Site Emergency Coordinator has been notified.
"The NRC Resident Inspector has been notified."
* * * UPDATE AT 1620 EDT ON 07/31/13 FROM RICHARD DAVIS TO S. SANDIN * * *
Preplanned maintenance was completed at 1540 EDT on 7/31/13. The licensee informed the NRC Resident Inspector.
Notified R2DO (King).
Non-Agreement State
Event Number: 49229
Rep Org: VETERANS HEALTH ADMINISTRATION
Licensee: VA SOUTHERN NEVADA HEALTHCARE SYSTEM
Region: 4
City: NORTH LAS VEGAS State: NV
County:
License #: 03-23853-01VA
Agreement: Y
Docket:
NRC Notified By: DAVID BURKETT
HQ OPS Officer: DONALD NORWOOD
Licensee: VA SOUTHERN NEVADA HEALTHCARE SYSTEM
Region: 4
City: NORTH LAS VEGAS State: NV
County:
License #: 03-23853-01VA
Agreement: Y
Docket:
NRC Notified By: DAVID BURKETT
HQ OPS Officer: DONALD NORWOOD
Notification Date: 07/31/2013
Notification Time: 16:03 [ET]
Event Date: 07/31/2013
Event Time: 08:15 [PDT]
Last Update Date: 07/31/2013
Notification Time: 16:03 [ET]
Event Date: 07/31/2013
Event Time: 08:15 [PDT]
Last Update Date: 07/31/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
20.1906(d)(2) - EXTERNAL RAD LEVELS > LIMITS
10 CFR Section:
20.1906(d)(2) - EXTERNAL RAD LEVELS > LIMITS
Person (Organization):
STEVE ORTH (R3DO)
THOMAS FARNHOLTZ (R4DO)
FSME EVENTS RESOURCE (EMAI)
STEVE ORTH (R3DO)
THOMAS FARNHOLTZ (R4DO)
FSME EVENTS RESOURCE (EMAI)
PACKAGE RECEIVED EXCEEDING EXTERNAL RADIATION LIMITS
"Per 10 CFR 20.1906(d)(2), the Veterans Health Administration (VHA) reported receipt of a package of radioactive material with external radiation levels exceeding NRC reporting limits (as referenced in 10 CFR 71.47).
"The package was received today (July 31, 2013) around 0815 PDT by the VA Southern Nevada Healthcare System, North Las Vegas, Nevada. This medical center holds permit number 27-00593-01 under the VHA master materials license.
"The package was surveyed by the VA facility nuclear medicine technologist with a pressurized ionization chamber. Readings were 160 mR/hr on the top surface of the shipping container and 32 mR/hr at 1 meter away from the top of the container (i.e., Transport Index = 32, which exceeded the NRC reporting limit of 10). Removable radioactivity tests of the external package surfaces were within regulatory limits.
"The shipping container lacked proper shielding on the top and bottom. The package contained 2 lead pigs each containing F-18 (half-life 110 minutes). One source was assayed at 0929 PDT on 7/31/2013 at 350 mCi. The other source was calibrated for 12 mCi at 1100 PDT.
"The VA facility Nuclear Medicine Technologist immediately notified, by telephone, Cardinal Health in Las Vegas, NV, who was the package shipper and final delivery carrier, regarding the high readings from the package. The vendor contact person acknowledged that the incorrect shipping box was used and the source should have been shipped later in the day.
"As corrective actions, the VA facility technologist isolated the package in the VA medical center hot lab, and additional lead shielding was placed on the top of the package.
"VHA has also notified NRC Region III (Null) by telephone of this event."
"Per 10 CFR 20.1906(d)(2), the Veterans Health Administration (VHA) reported receipt of a package of radioactive material with external radiation levels exceeding NRC reporting limits (as referenced in 10 CFR 71.47).
"The package was received today (July 31, 2013) around 0815 PDT by the VA Southern Nevada Healthcare System, North Las Vegas, Nevada. This medical center holds permit number 27-00593-01 under the VHA master materials license.
"The package was surveyed by the VA facility nuclear medicine technologist with a pressurized ionization chamber. Readings were 160 mR/hr on the top surface of the shipping container and 32 mR/hr at 1 meter away from the top of the container (i.e., Transport Index = 32, which exceeded the NRC reporting limit of 10). Removable radioactivity tests of the external package surfaces were within regulatory limits.
"The shipping container lacked proper shielding on the top and bottom. The package contained 2 lead pigs each containing F-18 (half-life 110 minutes). One source was assayed at 0929 PDT on 7/31/2013 at 350 mCi. The other source was calibrated for 12 mCi at 1100 PDT.
"The VA facility Nuclear Medicine Technologist immediately notified, by telephone, Cardinal Health in Las Vegas, NV, who was the package shipper and final delivery carrier, regarding the high readings from the package. The vendor contact person acknowledged that the incorrect shipping box was used and the source should have been shipped later in the day.
"As corrective actions, the VA facility technologist isolated the package in the VA medical center hot lab, and additional lead shielding was placed on the top of the package.
"VHA has also notified NRC Region III (Null) by telephone of this event."
Part 21
Event Number: 49230
Rep Org: ABB INC.
Licensee: ABB INC.
Region: 1
City: FLORENCE State: SC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: JAY LAVRINC
HQ OPS Officer: DONALD NORWOOD
Licensee: ABB INC.
Region: 1
City: FLORENCE State: SC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: JAY LAVRINC
HQ OPS Officer: DONALD NORWOOD
Notification Date: 07/31/2013
Notification Time: 17:45 [ET]
Event Date: 07/31/2013
Event Time: 00:00 [EDT]
Last Update Date: 04/08/2015
Notification Time: 17:45 [ET]
Event Date: 07/31/2013
Event Time: 00:00 [EDT]
Last Update Date: 04/08/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
Person (Organization):
GORDON HUNEGS (R1DO)
MICHAEL F. KING (R2DO)
STEVE ORTH (R3DO)
THOMAS FARNHOLTZ (R4DO)
PART 21 REACTORS (EMAI)
GORDON HUNEGS (R1DO)
MICHAEL F. KING (R2DO)
STEVE ORTH (R3DO)
THOMAS FARNHOLTZ (R4DO)
PART 21 REACTORS (EMAI)
PART 21 REPORT - DEVIATION OF HK CIRCUIT BREAKER CLOSE LATCH SPRING
ABB identified a deviation with close latch springs provided since 1/20/2010 used in medium voltage HK circuit breakers. These close latch springs are used on new legacy HK circuit breakers, replaced during HK circuit breaker refurbishment activities, and provided in HK refurbishment kits and as component items. The ABB part number for the close latch spring is: 162374A00. The nature of the deviation is a reduced spring force. There is a potential for an aged HK circuit breaker with hardening grease and this reduced spring force not to close.
The following is a list of affected customers:
Detroit Edison Fermi 2
Dominion VA
DTE
Duke Catawba
Duke Energy - Seneca
Duke Energy - Cataw
Duke Huntersville
Duke McGuire
Duke Oconee
Entergy River Bend
Exelon Limerick
Exelon Nuclear
Exelon Peach Bottom
Exelon Point Beach
First Energy Beaver Valley
Georgia Power Plant Vogtle
Nextera Point Beach
Nextera Seabrook
Prairie Island Nuclear
Progress Energy Brunswick
Progress Energy Crystal River
PSEG Alloway Creek
Southern Cal Edison
STP Nuclear
TVA Sequoyah.
* * * UPDATE AT 1715 EDT ON 04/08/15 FROM DAVID C. BROWN TO S. SANDIN * * *
The following information is excerpted from a fax/email submitted by ABB, Inc.:
"This letter amends the previous 10CFR Part 21 Notification of 31 July 2013 to encompass a wider time period during which the close latch spring (P/N: 162374A00) was sold for use in medium voltage HK circuit breakers. The initial time period of concern reported was January 2010 to July 2013. Revision 7 to the print was issued in January 2010 and it was determined during the initial investigation that this was the start of the deviation because the free angle was incorrectly shown. Our [ABB, Inc.] corrective actions in 2013 corrected this mistake.
"In February 2015, a licensee notified us [ABB, Inc.] of springs from 2007 that have the same improper free angle. The order of springs received just prior to it had the proper free angle. We [ABB, Inc.] have narrowed the start time of this issue to the lone batch of springs purchased in 2007 as they were received shortly before the order identified by the licensee was released."
Notified R1DO (Ferdas), R2DO (Heisserer), R3DO (Skokowski), R4DO (Azua) and NRR Part 21 via email.
ABB identified a deviation with close latch springs provided since 1/20/2010 used in medium voltage HK circuit breakers. These close latch springs are used on new legacy HK circuit breakers, replaced during HK circuit breaker refurbishment activities, and provided in HK refurbishment kits and as component items. The ABB part number for the close latch spring is: 162374A00. The nature of the deviation is a reduced spring force. There is a potential for an aged HK circuit breaker with hardening grease and this reduced spring force not to close.
The following is a list of affected customers:
Detroit Edison Fermi 2
Dominion VA
DTE
Duke Catawba
Duke Energy - Seneca
Duke Energy - Cataw
Duke Huntersville
Duke McGuire
Duke Oconee
Entergy River Bend
Exelon Limerick
Exelon Nuclear
Exelon Peach Bottom
Exelon Point Beach
First Energy Beaver Valley
Georgia Power Plant Vogtle
Nextera Point Beach
Nextera Seabrook
Prairie Island Nuclear
Progress Energy Brunswick
Progress Energy Crystal River
PSEG Alloway Creek
Southern Cal Edison
STP Nuclear
TVA Sequoyah.
* * * UPDATE AT 1715 EDT ON 04/08/15 FROM DAVID C. BROWN TO S. SANDIN * * *
The following information is excerpted from a fax/email submitted by ABB, Inc.:
"This letter amends the previous 10CFR Part 21 Notification of 31 July 2013 to encompass a wider time period during which the close latch spring (P/N: 162374A00) was sold for use in medium voltage HK circuit breakers. The initial time period of concern reported was January 2010 to July 2013. Revision 7 to the print was issued in January 2010 and it was determined during the initial investigation that this was the start of the deviation because the free angle was incorrectly shown. Our [ABB, Inc.] corrective actions in 2013 corrected this mistake.
"In February 2015, a licensee notified us [ABB, Inc.] of springs from 2007 that have the same improper free angle. The order of springs received just prior to it had the proper free angle. We [ABB, Inc.] have narrowed the start time of this issue to the lone batch of springs purchased in 2007 as they were received shortly before the order identified by the licensee was released."
Notified R1DO (Ferdas), R2DO (Heisserer), R3DO (Skokowski), R4DO (Azua) and NRR Part 21 via email.