Event Notification Report for December 02, 2012
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
12/01/2012 - 12/02/2012
Power Reactor
Event Number: 48550
Facility: MCGUIRE
Region: 2 State: NC
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ADAM EASTRIDGE
HQ OPS Officer: VINCE KLCO
Region: 2 State: NC
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ADAM EASTRIDGE
HQ OPS Officer: VINCE KLCO
Notification Date: 12/02/2012
Notification Time: 14:06 [ET]
Event Date: 12/02/2012
Event Time: 11:42 [EST]
Last Update Date: 12/12/2012
Notification Time: 14:06 [ET]
Event Date: 12/02/2012
Event Time: 11:42 [EST]
Last Update Date: 12/12/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
MIKE ERNSTES (R2DO)
MIKE ERNSTES (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 15 | Power Operation | 15 | Power Operation |
60-DAY REPORT - INVALID AUXILIARY FEEDWATER AND NUCLEAR SERVICE WATER PUMP ACTUATION
"The Unit-2 AMSAC (Anticipated Transient Without Scram Mitigation Actuation Circuitry) actuation generated a Unit-2 turbine trip signal. The Unit-2 turbine was already tripped, but the 2A and 2B Auxiliary Feedwater and 2B Nuclear Service Water pump started. AMSAC actuation occurred during calibration of AMSAC actuation pressure switches."
The licensee notified the NRC Resident Inspector.
* * * UPDATE FROM TIM JOHNSON TO VINCE KLCO ON 12/11/12 AT 1550 EST * * *
"This notification retracts an eight (8) hour notification per 10CFR50.72(b)(3)(iv)(A) which was made December 2, 2012 and documented as NRC Event Notification (EN) # 48550. The December 2, 2012 actuation of the Auxiliary Feedwater System was initially reported under 10CFR 50.72(b)(3)(iv)(A), valid actuation of the Auxiliary Feedwater system as listed in paragraph 10CFR50.72(b)(3)(iv)(B)(6). McGuire Nuclear Station (MNS) has subsequently determined that the actuation signal, which was caused by a test signal during calibration of the AMSAC (Anticipated Transient Without Scram Mitigation Actuation Circuitry) actuation pressure switches, constitutes an invalid actuation as described in Revision 2 of NUREG-1022 (Event Reporting Guidelines 10CFR50.72 and 50.73). Specifically, valid actuations result from signals initiated in response to actual plant conditions or parameters satisfying the requirements for initiation of the safety function of the system. A test signal is not representative of an actual plant condition and was therefore an invalid actuation signal and does not meet the NRC 8-hour reporting criteria under paragraph 10 CFR50.72(b)(3)(iv)(B)(6).
"In addition to retracting the 10CFR50.72(b)(3)(iv)(B)(6) notification, MNS is notifying the NRC Operations Center that the December 2, 2012 event met the reporting criteria specified in 10CFR50.73(a)(2)(iv)(A). Specifically, an invalid actuation of the auxiliary feed water system occurred while the systems was in service. The event did not involve an actuation of the reactor protection system (RPS) when the reactor was critical; therefore, MNS is opting to notify the NRC Operations Center within 60 days in lieu of a 60 day written licensee Event Report (LER), as allowed by 10CFR 50.73(a)(1) and 10CFR50.73(a)(2)(iv)(A).
"This notification satisfies 10CFR50.73(a)(2)(iv)(A) reporting requirements in lieu of a written LER. The 2A and 2B trains of the auxiliary feed water were actuated by an invalid signal. Each train's actuation was complete and systems operated as designed."
The licensee notified the NRC Resident Inspector.
Notified the R2DO (Sykes).
"The Unit-2 AMSAC (Anticipated Transient Without Scram Mitigation Actuation Circuitry) actuation generated a Unit-2 turbine trip signal. The Unit-2 turbine was already tripped, but the 2A and 2B Auxiliary Feedwater and 2B Nuclear Service Water pump started. AMSAC actuation occurred during calibration of AMSAC actuation pressure switches."
The licensee notified the NRC Resident Inspector.
* * * UPDATE FROM TIM JOHNSON TO VINCE KLCO ON 12/11/12 AT 1550 EST * * *
"This notification retracts an eight (8) hour notification per 10CFR50.72(b)(3)(iv)(A) which was made December 2, 2012 and documented as NRC Event Notification (EN) # 48550. The December 2, 2012 actuation of the Auxiliary Feedwater System was initially reported under 10CFR 50.72(b)(3)(iv)(A), valid actuation of the Auxiliary Feedwater system as listed in paragraph 10CFR50.72(b)(3)(iv)(B)(6). McGuire Nuclear Station (MNS) has subsequently determined that the actuation signal, which was caused by a test signal during calibration of the AMSAC (Anticipated Transient Without Scram Mitigation Actuation Circuitry) actuation pressure switches, constitutes an invalid actuation as described in Revision 2 of NUREG-1022 (Event Reporting Guidelines 10CFR50.72 and 50.73). Specifically, valid actuations result from signals initiated in response to actual plant conditions or parameters satisfying the requirements for initiation of the safety function of the system. A test signal is not representative of an actual plant condition and was therefore an invalid actuation signal and does not meet the NRC 8-hour reporting criteria under paragraph 10 CFR50.72(b)(3)(iv)(B)(6).
"In addition to retracting the 10CFR50.72(b)(3)(iv)(B)(6) notification, MNS is notifying the NRC Operations Center that the December 2, 2012 event met the reporting criteria specified in 10CFR50.73(a)(2)(iv)(A). Specifically, an invalid actuation of the auxiliary feed water system occurred while the systems was in service. The event did not involve an actuation of the reactor protection system (RPS) when the reactor was critical; therefore, MNS is opting to notify the NRC Operations Center within 60 days in lieu of a 60 day written licensee Event Report (LER), as allowed by 10CFR 50.73(a)(1) and 10CFR50.73(a)(2)(iv)(A).
"This notification satisfies 10CFR50.73(a)(2)(iv)(A) reporting requirements in lieu of a written LER. The 2A and 2B trains of the auxiliary feed water were actuated by an invalid signal. Each train's actuation was complete and systems operated as designed."
The licensee notified the NRC Resident Inspector.
Notified the R2DO (Sykes).
Power Reactor
Event Number: 48551
Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [] []
RX Type: (1) CE
NRC Notified By: KLINT KUDLACEK
HQ OPS Officer: VINCE KLCO
Region: 4 State: NE
Unit: [1] [] []
RX Type: (1) CE
NRC Notified By: KLINT KUDLACEK
HQ OPS Officer: VINCE KLCO
Notification Date: 12/02/2012
Notification Time: 17:28 [ET]
Event Date: 12/02/2012
Event Time: 15:30 [CST]
Last Update Date: 12/02/2012
Notification Time: 17:28 [ET]
Event Date: 12/02/2012
Event Time: 15:30 [CST]
Last Update Date: 12/02/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
Person (Organization):
JACK WHITTEN (R4DO)
JACK WHITTEN (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Defueled | 0 | Defueled |
INADEQUATE RAW WATER PUMP ANCHOR EMBEDMENT
"The raw water pumps (AC-10A/B/C/D) base plate support anchors were discovered by Fort Calhoun Station personnel to have inadequate embedment to support existing analysis. Plant drawing specify a j-bolt type of anchor with a required 16 inch embedment. Actual plant configuration was found to be a j-bolt type anchor with a 9 inch embedment. Plant design analysis requirements are not being met for the existing configuration. Existing analysis requires a minimum embedment of 60 inch for a j-bolt type anchor. There are a total of 4 anchors for each raw water pump, totaling 16 anchors. The as found condition renders all four raw water pumps inoperable.
"In the current plant Mode 5 (De-fueled), Shutdown Condition, the raw water pumps are considered available per the station's Shutdown Operations Protection Plan. Raw water pumps AC-10B and AC - 10D are in service providing cooling to the Component Cooling Water System. The core is offloaded and the Component Cooling Water System is maintaining Spent Fuel Pool temperature."
The licensee notified the NRC Resident Inspector.
"The raw water pumps (AC-10A/B/C/D) base plate support anchors were discovered by Fort Calhoun Station personnel to have inadequate embedment to support existing analysis. Plant drawing specify a j-bolt type of anchor with a required 16 inch embedment. Actual plant configuration was found to be a j-bolt type anchor with a 9 inch embedment. Plant design analysis requirements are not being met for the existing configuration. Existing analysis requires a minimum embedment of 60 inch for a j-bolt type anchor. There are a total of 4 anchors for each raw water pump, totaling 16 anchors. The as found condition renders all four raw water pumps inoperable.
"In the current plant Mode 5 (De-fueled), Shutdown Condition, the raw water pumps are considered available per the station's Shutdown Operations Protection Plan. Raw water pumps AC-10B and AC - 10D are in service providing cooling to the Component Cooling Water System. The core is offloaded and the Component Cooling Water System is maintaining Spent Fuel Pool temperature."
The licensee notified the NRC Resident Inspector.
Agreement State
Event Number: 48895
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: AMERICAN SOIL TESTING
Region: 4
City: SAN JOSE State: CA
County:
License #: 5059
Agreement: Y
Docket:
NRC Notified By: GENE FORRER
HQ OPS Officer: STEVE SANDIN
Licensee: AMERICAN SOIL TESTING
Region: 4
City: SAN JOSE State: CA
County:
License #: 5059
Agreement: Y
Docket:
NRC Notified By: GENE FORRER
HQ OPS Officer: STEVE SANDIN
Notification Date: 04/08/2013
Notification Time: 14:00 [ET]
Event Date: 12/02/2012
Event Time: 00:00 [PDT]
Last Update Date: 04/08/2013
Notification Time: 14:00 [ET]
Event Date: 12/02/2012
Event Time: 00:00 [PDT]
Last Update Date: 04/08/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
RICK DEESE (R4DO)
FSME EVENTS RESOURCE (EMAI)
MEXICO (FAX)
RICK DEESE (R4DO)
FSME EVENTS RESOURCE (EMAI)
MEXICO (FAX)
AGREEMENT STATE REPORT - STOLEN MOISTURE DENSITY GAUGES
The State of California provided the following information via email:
"On December 5, 2012, . . . American Soil Testing notified RHB [California Radiologic Health Branch] that his storage facility had been broken into and two CPN Moisture Density gauges (Serial numbers MD00405615 & M17031878) had been stolen. The licensee was advised to post a notice and reward in the local newspapers and on Craigslist and to notify local law enforcement.
"Note: Miscommunication resulted in the NRC not being notified until 4/8/13."
CA 5010 Number: 120512
These CPN Moisture Density gauges contain two (2) sources each, i.e., 10 mCi Cs-137 and 50 mCi Am-241/Be.
HOO Note: See EN #48867 - Report from Nevada concerning recovery of M17031878 gauge.
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 State of California provided the following information via email:
"On December 5, 2012, . . . American Soil Testing notified RHB [California Radiologic Health Branch] that his storage facility had been broken into and two CPN Moisture Density gauges (Serial numbers MD00405615 & M17031878) had been stolen. The licensee was advised to post a notice and reward in the local newspapers and on Craigslist and to notify local law enforcement.
"Note: Miscommunication resulted in the NRC not being notified until 4/8/13."
CA 5010 Number: 120512
These CPN Moisture Density gauges contain two (2) sources each, i.e., 10 mCi Cs-137 and 50 mCi Am-241/Be.
HOO Note: See EN #48867 - Report from Nevada concerning recovery of M17031878 gauge.
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