Event Notification Report for May 15, 2013
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
05/14/2013 - 05/15/2013
EVENT NUMBERS
4903449036490384904049041
Power Reactor
Event Number: 49034
Facility: MILLSTONE
Region: 1 State: CT
Unit: [] [] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: GERALD BAKER
HQ OPS Officer: PETE SNYDER
Region: 1 State: CT
Unit: [] [] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: GERALD BAKER
HQ OPS Officer: PETE SNYDER
Notification Date: 05/15/2013
Notification Time: 11:55 [ET]
Event Date: 05/15/2013
Event Time: 04:00 [EDT]
Last Update Date: 05/15/2013
Notification Time: 11:55 [ET]
Event Date: 05/15/2013
Event Time: 04:00 [EDT]
Last Update Date: 05/15/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
DAN SCHROEDER (R1DO)
DAN SCHROEDER (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | N | 0 | Hot Shutdown | 0 | Hot Standby |
LEAKING CONTAINMENT AIR LOCK EQUALIZING VALVE
"On May 15, 2013, at 0400 EDT, it was discovered that an equalizing valve for the outer containment air lock was leaking by its seat rendering the outer containment air lock inoperable. This condition was discovered by maintenance personnel as they were exiting containment through the inner containment air lock.
"The containment inner door was open for transit, which resulted in the Loss of Containment Integrity.
"With both containment air lock doors open at the time of discovery of the leaking equalizing valve, this condition is reportable pursuant to 10 CFR 50.72(b)(3)(v). The inner air lock door was immediately closed and has remained closed since.
"Technical Specification 3.6.1.1 Primary Containment Integrity is applicable in Modes 1,2,3, and 4. Since Primary Containment Integrity was rendered inoperable, Dominion is reporting that this condition could have prevented the fulfillment of the safety function to control the release of radioactive material.
"The NRC Senior Resident Inspector has been notified."
"On May 15, 2013, at 0400 EDT, it was discovered that an equalizing valve for the outer containment air lock was leaking by its seat rendering the outer containment air lock inoperable. This condition was discovered by maintenance personnel as they were exiting containment through the inner containment air lock.
"The containment inner door was open for transit, which resulted in the Loss of Containment Integrity.
"With both containment air lock doors open at the time of discovery of the leaking equalizing valve, this condition is reportable pursuant to 10 CFR 50.72(b)(3)(v). The inner air lock door was immediately closed and has remained closed since.
"Technical Specification 3.6.1.1 Primary Containment Integrity is applicable in Modes 1,2,3, and 4. Since Primary Containment Integrity was rendered inoperable, Dominion is reporting that this condition could have prevented the fulfillment of the safety function to control the release of radioactive material.
"The NRC Senior Resident Inspector has been notified."
Power Reactor
Event Number: 49036
Facility: CATAWBA
Region: 2 State: SC
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: AARON MICHALSKI
HQ OPS Officer: VINCE KLCO
Region: 2 State: SC
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: AARON MICHALSKI
HQ OPS Officer: VINCE KLCO
Notification Date: 05/15/2013
Notification Time: 15:00 [ET]
Event Date: 05/15/2013
Event Time: 00:00 [EDT]
Last Update Date: 05/15/2013
Notification Time: 15:00 [ET]
Event Date: 05/15/2013
Event Time: 00:00 [EDT]
Last Update Date: 05/15/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(ii) - LOST/STOLEN LNM>10X
10 CFR Section:
20.2201(a)(1)(ii) - LOST/STOLEN LNM>10X
Person (Organization):
JONATHAN BARTLEY (R2DO)
FSME RESOURCES (EMAI)
HAROLD CHERNOFF (NRR)
JONATHAN BARTLEY (R2DO)
FSME RESOURCES (EMAI)
HAROLD CHERNOFF (NRR)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
MISSING LICENSED MATERIAL
This is a non-emergency 30 day notification for missing licensed material. This event is reportable in accordance with 10CFR20.2201(a)(1)(ii).
On April 16, 2013, while performing the required semi-annual source leak check and inventory, Radiation Protection personnel could not locate the source label tag or cable for source RMC-0169 on radiation monitor 1EMF44H (This monitor has not been in use since 1995). The monitor's pre-amplifier box had been removed as well. 1EMH44H was inspected and the source was not found within the housing. A search was conducted for this missing source, however it could not be located. During the previous source leak check and inventory on October 4, 2012, the source was in its expected location.
Source RMC-0169 is a 200 milligram depleted uranium source. The total original activity of the source was 9.998E-02 microCuries (3.03E-02 micro curies; U-234; 1.98E-03 microCuries; U-235, 6.77E-02 microCuries; U-238). The reportable limit for U-234 (the shortest-lived isotope in the source is U-234 with a half-live of 2.46E+05 years) is 0.01 microCuries per 10CFR20, Appendix C. Based on the activity of U-234 present in the source of 0.03 microCuries, this 30 day phone notification to the NRC is being provided pursuant to 10CFR22.2201(a)(1)(ii).
The external dose to an individual from this source is negligible due to the small quantity and the type of material involved. Therefore, this event has no adverse effect upon the health and safety of employees or the public.
The required written report pursuant to 10CFR20.2201(b)(1) will be provided to the NRC within 30 days of the telephone notification.
The NRC Resident Inspector has been notified.
The licensee with notify State and local authorities.
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 is a non-emergency 30 day notification for missing licensed material. This event is reportable in accordance with 10CFR20.2201(a)(1)(ii).
On April 16, 2013, while performing the required semi-annual source leak check and inventory, Radiation Protection personnel could not locate the source label tag or cable for source RMC-0169 on radiation monitor 1EMF44H (This monitor has not been in use since 1995). The monitor's pre-amplifier box had been removed as well. 1EMH44H was inspected and the source was not found within the housing. A search was conducted for this missing source, however it could not be located. During the previous source leak check and inventory on October 4, 2012, the source was in its expected location.
Source RMC-0169 is a 200 milligram depleted uranium source. The total original activity of the source was 9.998E-02 microCuries (3.03E-02 micro curies; U-234; 1.98E-03 microCuries; U-235, 6.77E-02 microCuries; U-238). The reportable limit for U-234 (the shortest-lived isotope in the source is U-234 with a half-live of 2.46E+05 years) is 0.01 microCuries per 10CFR20, Appendix C. Based on the activity of U-234 present in the source of 0.03 microCuries, this 30 day phone notification to the NRC is being provided pursuant to 10CFR22.2201(a)(1)(ii).
The external dose to an individual from this source is negligible due to the small quantity and the type of material involved. Therefore, this event has no adverse effect upon the health and safety of employees or the public.
The required written report pursuant to 10CFR20.2201(b)(1) will be provided to the NRC within 30 days of the telephone notification.
The NRC Resident Inspector has been notified.
The licensee with notify State and local authorities.
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: 49038
Facility: HARRIS
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: ARTHUR PAN
HQ OPS Officer: PETE SNYDER
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: ARTHUR PAN
HQ OPS Officer: PETE SNYDER
Notification Date: 05/15/2013
Notification Time: 19:55 [ET]
Event Date: 05/15/2013
Event Time: 06:49 [EDT]
Last Update Date: 05/15/2013
Notification Time: 19:55 [ET]
Event Date: 05/15/2013
Event Time: 06:49 [EDT]
Last Update Date: 05/15/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS 50.72(b)(3)(ii)(A) - DEGRADED CONDITION 50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS 50.72(b)(3)(ii)(A) - DEGRADED CONDITION 50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
JONATHAN BARTLEY (R2DO)
JONATHAN BARTLEY (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 SPECIFICATION REQUIRED SHUTDOWN DUE TO DISCOVERY OF AN UNACCEPTABLE FLAW DURING DATA REVIEW
"On May 13, 2013, during a secondary review of ultrasonic data of the reactor vessel head penetrations performed during Harris Nuclear Plant spring 2012 refueling outage, it was determined that the results for one of the penetrations appeared to not meet the applicable acceptance criteria. Further evaluation completed on May 15, 2013, characterized the flaw as a 0.26 inch flaw on nozzle 49 that overlaps the J-grove weld and exhibits characteristics of primary water stress corrosion cracking. The original examinations were performed per NRC requirements.
"Initial evaluation indicates that the flaw is not through wall and there is no evidence of leakage based on inspections performed on the top of the reactor vessel head during the spring 2012 refueling outage. Operators are shutting down the unit to make the necessary repairs. There is no impact to the health and safety of employees or the public.
"The NRC resident inspector has been informed.
"This report is being made in accordance with 10 CFR 50.72(b)(3)(ii)(A), discovery of a degraded condition, 10 CFR 50.72(b)(2)(i), plant shutdown required by technical specifications, and 10 CFR 50.72(b)(3)(v)(C), a condition which could have prevented the fulfillment of a safety function to control the release of radioactive material."
"On May 13, 2013, during a secondary review of ultrasonic data of the reactor vessel head penetrations performed during Harris Nuclear Plant spring 2012 refueling outage, it was determined that the results for one of the penetrations appeared to not meet the applicable acceptance criteria. Further evaluation completed on May 15, 2013, characterized the flaw as a 0.26 inch flaw on nozzle 49 that overlaps the J-grove weld and exhibits characteristics of primary water stress corrosion cracking. The original examinations were performed per NRC requirements.
"Initial evaluation indicates that the flaw is not through wall and there is no evidence of leakage based on inspections performed on the top of the reactor vessel head during the spring 2012 refueling outage. Operators are shutting down the unit to make the necessary repairs. There is no impact to the health and safety of employees or the public.
"The NRC resident inspector has been informed.
"This report is being made in accordance with 10 CFR 50.72(b)(3)(ii)(A), discovery of a degraded condition, 10 CFR 50.72(b)(2)(i), plant shutdown required by technical specifications, and 10 CFR 50.72(b)(3)(v)(C), a condition which could have prevented the fulfillment of a safety function to control the release of radioactive material."
Agreement State
Event Number: 49040
Rep Org: VIRGINIA RAD MATERIALS PROGRAM
Licensee: HONEYWELL RESINS & CHEMICALS LLC
Region: 1
City: CHESTER State: VA
County:
License #: 041-344-2
Agreement: Y
Docket:
NRC Notified By: ASFAW FENTA
HQ OPS Officer: DONALD NORWOOD
Licensee: HONEYWELL RESINS & CHEMICALS LLC
Region: 1
City: CHESTER State: VA
County:
License #: 041-344-2
Agreement: Y
Docket:
NRC Notified By: ASFAW FENTA
HQ OPS Officer: DONALD NORWOOD
Notification Date: 05/16/2013
Notification Time: 10:28 [ET]
Event Date: 05/15/2013
Event Time: 00:00 [EDT]
Last Update Date: 05/16/2013
Notification Time: 10:28 [ET]
Event Date: 05/15/2013
Event Time: 00:00 [EDT]
Last Update Date: 05/16/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
DAN SCHROEDER (R1DO)
FSME EVENTS RESOURCE (E-MA)
DAN SCHROEDER (R1DO)
FSME EVENTS RESOURCE (E-MA)
FIXED GAUGE SHUTTER HARD TO OPEN
The following information was submitted by the Commonwealth of Virginia via fax:
"On May 15, 2013, the licensee reported that the shutter of one of its fixed gauges was not 'functioning per the design.' The problem was detected during the periodic shutter checks on May 15, 2013. The shutter could be closed but needed strong force to open it. The gauge is a Ronan Engineering Company, Model SA1-F37, Serial number M-2232. The gauge contains 50 mCi of Cs-137 as of the manufacturing date (remaining activity as of the incident date is 34.3 mCi).
"Ronan Engineering Company was contacted and a schedule has been arranged for shutter repair.
"A radiation survey was performed by the licensee and found to be within design parameters and regulatory limits. There are no public health or safety issues involved. The Virginia Radioactive Material Program will follow up with the licensee."
Virginia Event Report ID: VA-13-005
The following information was submitted by the Commonwealth of Virginia via fax:
"On May 15, 2013, the licensee reported that the shutter of one of its fixed gauges was not 'functioning per the design.' The problem was detected during the periodic shutter checks on May 15, 2013. The shutter could be closed but needed strong force to open it. The gauge is a Ronan Engineering Company, Model SA1-F37, Serial number M-2232. The gauge contains 50 mCi of Cs-137 as of the manufacturing date (remaining activity as of the incident date is 34.3 mCi).
"Ronan Engineering Company was contacted and a schedule has been arranged for shutter repair.
"A radiation survey was performed by the licensee and found to be within design parameters and regulatory limits. There are no public health or safety issues involved. The Virginia Radioactive Material Program will follow up with the licensee."
Virginia Event Report ID: VA-13-005
Agreement State
Event Number: 49041
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: NON-DESTRUCTIVE INSPECTION CORPORATION
Region: 4
City: LAKE JACKSON State: TX
County:
License #: 02712
Agreement: Y
Docket:
NRC Notified By: KAREN BLANCHARD
HQ OPS Officer: HOWIE CROUCH
Licensee: NON-DESTRUCTIVE INSPECTION CORPORATION
Region: 4
City: LAKE JACKSON State: TX
County:
License #: 02712
Agreement: Y
Docket:
NRC Notified By: KAREN BLANCHARD
HQ OPS Officer: HOWIE CROUCH
Notification Date: 05/16/2013
Notification Time: 12:50 [ET]
Event Date: 05/15/2013
Event Time: 00:00 [CDT]
Last Update Date: 05/16/2013
Notification Time: 12:50 [ET]
Event Date: 05/15/2013
Event Time: 00:00 [CDT]
Last Update Date: 05/16/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
WAYNE WALKER (R4DO)
FSME EVENTS RESOURCE (EMAI)
WAYNE WALKER (R4DO)
FSME EVENTS RESOURCE (EMAI)
TEXAS AGREEMENT STATE REPORT - BROKEN RADIOGRAPHY CAMERA DRIVE CABLE
The following information was obtained from the State of Texas via email:
"On May 15, 2013, the licensee reported that one of its radiography teams had been unable to retract an iridium-192 source back into a QSA Model 880 radiography camera at a temporary field site in Galena Park, Texas. The licensee's RSO and a supervisor responded to the site.
"The RSO covered the collimator containing the source with lead shot bags then an individual authorized to perform source retrieval responded and secured the source. The pocket dosimeter readings for the three were: RSO received 60 millirem; the supervisor received 50 millirem; and the individual performing source retrieval received 40 millirem.
"The licensee reported that the drive cable had broken right behind the ball. No member of the public received any exposure as a result of this event. The source, camera, and equipment will be taken to the licensee's facility and the licensee will contact the manufacturer.
"Further information will be provided as it is obtained in accordance with SA-300.
"Radiography camera: QSA Model 880, SN: 2735. Source SN: 91360B"
Texas Incident # I-9078
The following information was obtained from the State of Texas via email:
"On May 15, 2013, the licensee reported that one of its radiography teams had been unable to retract an iridium-192 source back into a QSA Model 880 radiography camera at a temporary field site in Galena Park, Texas. The licensee's RSO and a supervisor responded to the site.
"The RSO covered the collimator containing the source with lead shot bags then an individual authorized to perform source retrieval responded and secured the source. The pocket dosimeter readings for the three were: RSO received 60 millirem; the supervisor received 50 millirem; and the individual performing source retrieval received 40 millirem.
"The licensee reported that the drive cable had broken right behind the ball. No member of the public received any exposure as a result of this event. The source, camera, and equipment will be taken to the licensee's facility and the licensee will contact the manufacturer.
"Further information will be provided as it is obtained in accordance with SA-300.
"Radiography camera: QSA Model 880, SN: 2735. Source SN: 91360B"
Texas Incident # I-9078