| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
12/17/2013 - 12/18/2013 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 49621 | Rep Org: NE DIV OF RADIOACTIVE MATERIALS
Licensee: SHOPKO STORES
Region: 4
City: State: NE
County:
License #: GL
Agreement: Y
Docket:
NRC Notified By: TRUDY HILL
HQ OPS Officer: VINCE KLCO | Notification Date: 12/10/2013
Notification Time: 16:43 [ET]
Event Date: 12/10/2013
Event Time: 12:00 [CST]
Last Update Date: 12/13/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
GREG WERNER (R4DO)
FSME RESOURCES (EMAI)
ILTAB (EMAI)
|
| This material event contains a "Less than Cat 3 " level of radioactive material. | Event Text AGREEMENT STATE REPORT - COMPOSITE LISTING OF MISSING TRITIUM EXIT SIGNS
The following forty eight (48) lost licensee tritium signs were submitted by the State of Nebraska via email:
1. ShopKo Store #47 located in Lincoln, NE;
(1) SRB Technologies; Model Safety-10; S/N ST18770; H-3; 21 Ci.
(10) Safety Light; Model #2040; S/N A44267, A44269, A44272 thru A44274, A44276, A42278 thru A44281; H-3; 11.5 Ci each.
Nebraska Event - NE130006.
2. ShopKo Store #48 located in Norfolk, NE;
(6) Safety Light Model #2040; S/N Unknown; H-3; 11.5 Ci.
Nebraska Event - NE130007.
3. ShopKo Store #56 located in Omaha, NE;
(29) SRB Technologies; Model Safety-10; S/N 24303 thru 24318, 24327 thru 24333, 24398, 24299, 24400, 24401, 24399H-3; 21 Ci each.
(2) Safety Light Model #2040; S/N AON845, AON847; H-3; 12 Ci each.
Nebraska Event - NE130008.
* * * UPDATE ON 12/13/13 AT 0921 EST FROM TRUDY HILL TO DONG PARK * * *
The following thirteen (13) lost licensee tritium signs were submitted by the State of Nebraska via email:
1. ShopKo Store #53 located in North Platte, NE;
(13) Safety Light Model #2040; S/N Unknown; H-3; 11.5 Ci.
Nebraska Event - NE130009.
Notified R4DO (Walker), FSME Events Resource and ILTAB via email.
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 |
| Agreement State | Event Number: 49622 | Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: CORNERSTONE EARTH GROUP
Region: 4
City: WALNUT CREEK State: CA
County:
License #: CA 7619-43
Agreement: Y
Docket:
NRC Notified By: KENT PRENDERGAST
HQ OPS Officer: JOHN SHOEMAKER | Notification Date: 12/10/2013
Notification Time: 18:37 [ET]
Event Date: 12/10/2013
Event Time: 05:20 [PST]
Last Update Date: 12/10/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
GREG WERNER (R4DO)
ROBERT BUNCH (ILTA)
FSME EVENTS RESOURCE (EMAI)
MEXICO (EMAI)
|
| This material event contains a "Less than Cat 3 " level of radioactive material. | Event Text AGREEMENT STATE REPORT - STOLEN MOISTURE DENSITY GAUGE
The California Radiologic Health Branch reported a stolen moisture density gauge from a licensee in Walnut Creek, CA. The gauge was recovered in about 4 hours, in Lafayette, CA, after being abandoned by the thieves. The state assisted local law enforcement in Walnut Creek and Lafayette, CA with the gauge recovery. The gauge was recovered in good condition and there are no known exposures or spread of contamination. The gauge has been returned to the licensee for storage in a secure location. The gauge is a Instro Tek, model 3500 Explorer, Serial #1644, containing 10 mCi Cs-137 and 40 mCi Am/Be-241 sources.
California State Report #121013 and Lafayette, CA police report #13-21268.
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: 49637 | Facility: FARLEY
Region: 2 State: AL
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: DARRIN GARD
HQ OPS Officer: DANIEL MILLS | Notification Date: 12/16/2013
Notification Time: 21:37 [ET]
Event Date: 12/16/2013
Event Time: 14:54 [CST]
Last Update Date: 12/17/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
STEVE ROSE (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 | Event Text LOSS OF CONTAINMENT SMOKE DETECTION CAPABILITY
"At 1454 CST on December 16, 2013, the Unit 1 pyro panel (smoke detection panel) was declared non-functional due to an unexpected failure. Viable compensatory measures have been established for all affected areas except the Unit 1 Containment Building. Since a fire in Containment is an entry condition for the site's Emergency Plan, this is considered a loss of emergency assessment capability and is being reported per 10CFR50.72(b)(3)(xiii). Containment temperatures are being monitored while the pyro panel is out of service, however, this is not considered a satisfactory compensatory measure for maintaining effective assessment capability."
The NRC Resident Inspector has been notified.
* * * UPDATE AT 2046 EST ON 12/17/13 FROM DARRIN GARD TO DANIEL MILLS * * *
The Unit 1 pyro panel has been returned to service as of 1554 CST on 12/17/13, which restores Unit 1 containment fire detection capability.
The NRC Resident Inspector has been notified.
Notified R2DO (Freeman). |
| Power Reactor | Event Number: 49641 | Facility: HATCH
Region: 2 State: GA
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: J D SELLERS
HQ OPS Officer: JOHN SHOEMAKER | Notification Date: 12/17/2013
Notification Time: 13:07 [ET]
Event Date: 10/21/2013
Event Time: 04:19 [EST]
Last Update Date: 12/17/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
| Person (Organization):
SCOTT FREEMAN (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text 60 OPTIONAL REPORT - INVALID PARTIAL REACTOR PROTECTION SYSTEM ACTUATION
"Invalid partial Reactor Protection System (RPS) actuation results in; Closure of Containment Isolation Valves (CIVs) in multiple systems, including isolation of the Reactor Water Clean-Up (RWCU) System.
"On October 21, 2013, at 0419 EST, Unit 2 received a Reactor Auto SCRAM System 'B' trip signal in the main control room. Initial investigations at the local RPS Motor-Generator (MG) set room discovered breaker 52-3D tripped in cabinet 2C71-P003D. This resulted in a half-scram and the closure of CIVs in multiple systems, including closure of the RWCU system outboard isolation valve, 2G31-F004. These trips are normal responses to the loss of the 'B' RPS. The operating crew entered abnormal operating procedures, including those for loss of RPS and for loss of the RWCU system, and confirmed that all isolations and trips occurred as expected. Additionally, the crew restored the 'B' RPS bus from its alternate source, reset the half scram, returned the CIVs to their normal positions, and placed RWCU in service.
"Upon investigation, the determination was made that the trip and reset setpoints for under-voltage relay 2C71 -K752D had drifted. Consequently, once the drift reached the trip setpoints during the event, breaker 52-3D tripped, resulting in the loss of the 'B' RPS bus. Because a malfunctioning subcomponent caused the partial RPS trip rather than a valid CIV actuation signal, the resulting isolation is considered an invalid actuation.
"Further evaluation into the cause of the drift revealed solder joint cracks in the relay circuit board and an inadequate previous refurbishment of the subject relay. The drifting relay was removed and a refurbished relay was installed in location 2C71-K752D. Plans are to replace both units' RPS Power Monitoring relays with a different design. Until that design change is implemented, the frequency of calibration for these relays is being increased from every 182 days to every 91 days."
The licensee has notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 49642 | Facility: MILLSTONE
Region: 1 State: CT
Unit: [ ] [2] [ ]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: ANGELO LEONE
HQ OPS Officer: DANIEL MILLS | Notification Date: 12/17/2013
Notification Time: 13:38 [ET]
Event Date: 12/17/2013
Event Time: 10:15 [EST]
Last Update Date: 12/17/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
ANTHONY DIMITRIADIS (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text STACK RADIATION MONITOR REMOVED FROM SERVICE FOR PREPLANNED MAINTENANCE
At 1015 EST on 12/17/13, the Unit 2 high range stack radiation monitor RM-8168 was removed from service for preplanned maintenance. The maintenance was completed and the radiation monitor returned to service at 1300 EST.
The licensee notified the NRC Resident Inspector and the State and Local Governments. |
| Power Reactor | Event Number: 49644 | Facility: LIMERICK
Region: 1 State: PA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: CHRIS GIAMBRONE
HQ OPS Officer: HOWIE CROUCH | Notification Date: 12/17/2013
Notification Time: 15:11 [ET]
Event Date: 12/16/2013
Event Time: 20:00 [EST]
Last Update Date: 12/17/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
| Person (Organization):
ANTHONY DIMITRIADIS (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 | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text FITNESS FOR DUTY REPORT - LICENSED OPERATOR TESTED POSITIVE FOR ALCOHOL
A licensed operator had a confirmed positive for alcohol during a random fitness for duty test. The employee's access to the plant has been restricted. The licensee has notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 49645 | Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: JASON LOVEGREN
HQ OPS Officer: JOHN SHOEMAKER | Notification Date: 12/17/2013
Notification Time: 15:25 [ET]
Event Date: 12/17/2013
Event Time: 11:33 [PST]
Last Update Date: 12/17/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
RYAN LANTZ (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text REACTOR BUILDING STACK RADIATION MONITOR INOPERABLE DUE TO SCHEDULED MAINTENANCE ON SUPPORTING EQUIPMENT
"At 1133 PST on December 17, 2013, the Reactor Building Stack Radiation Monitor - Intermediate Range detector was declared non-functional due to scheduled maintenance on supporting equipment. Preplanned compensatory actions have been initiated.
"This event is being reported as a loss of emergency assessment capability in accordance with 10 CFR 50.72(b)(3)(xiii). A follow up notification will be made when the equipment has been returned to service.
"The licensee has notified the NRC Resident Inspector." |
| Power Reactor | Event Number: 49646 | Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [4] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: ROBERT STRUSINSKI
HQ OPS Officer: DANIEL MILLS | Notification Date: 12/17/2013
Notification Time: 17:25 [ET]
Event Date: 12/17/2013
Event Time: 10:50 [EST]
Last Update Date: 12/17/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
SCOTT FREEMAN (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | | 4 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text TECHNICAL SUPPORT CENTER DEGRADED DUE TO LOSS OF AIR FILTRATION
"At approximately 1050 EST on December 17, 2013, during a check of facility equipment, the Technical Support Center (TSC) was found to be degraded due to the loss of the air filtration system. The air filtration system was restored and the TSC made fully functional at approximately 1300 the same day.
"The emergency assessment function could have been performed in the control room as addressed in emergency response procedures. This event is reported in accordance with 10 CFR 50.72(b)(3)(xiii)."
The NRC Resident Inspector has been notified. |
| Power Reactor | Event Number: 49647 | Facility: GRAND GULF
Region: 4 State: MS
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: ROGER BUTLER
HQ OPS Officer: DANIEL MILLS | Notification Date: 12/17/2013
Notification Time: 22:13 [ET]
Event Date: 12/17/2013
Event Time: 13:32 [CST]
Last Update Date: 12/17/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
RYAN LANTZ (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text LOSS OF CONTAINMENT ISOLATION CAPABILITY DUE TO SURVEILLANCE PROCEDURE ERROR
"During performance of 06-IC-1E31-Q-1016-02 RCIC Steam Supply Pressure Low, the RCIC Containment Isolation Valve 1E51F063, RCIC STM SPLY DRWL INBD ISOL, closed. The procedure for this surveillance (which had recently been revised) should have directed the opening of the breakers for isolation valves 1E51F063 and 1E51F076, RCIC STM LINE WARMUP VLV, which are the division two inboard containment isolation valves for the RCIC system. The procedure incorrectly directed the breakers to be opened for the 1E51F064, RCIC STM SPLY DRWL OTBD ISOL, and 1E51F076. The 1E51F076 is a division two valve and the 1E51F064 is a division one valve. Both the 1E51F076 and 1E51F064 were open at the time their breakers were opened, which resulted in the loss of isolation capability for this containment penetration."
The NRC Resident Inspector has been notified. |
| Power Reactor | Event Number: 49648 | Facility: OYSTER CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-2
NRC Notified By: STEVEN JOHNSTON
HQ OPS Officer: VINCE KLCO | Notification Date: 12/18/2013
Notification Time: 03:41 [ET]
Event Date: 12/17/2013
Event Time: 19:57 [EST]
Last Update Date: 12/18/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
ANTHONY DIMITRIADIS (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Hot Shutdown | 0 | Hot Shutdown | Event Text REACTOR PROTECTION SYSTEM (RPS) ACTUATION WITH THE REACTOR IN HOT SHUTDOWN
"Pursuant to 10CFR50.72(b)(3)(iv)(A), notifications are being performed for a valid actuation of the reactor protection system resulting in a full scram. The actuation was a result of the reactor mode switch being placed from the refuel position to the shutdown position without the scram bypass jumpers installed. The reactor was subcritical with all rods inserted at the time of the actuation. All systems functioned as designed."
The licensee notified the NRC Resident Inspector. | |