Event Notification Report for January 09, 2014
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
01/08/2014 - 01/09/2014
EVENT NUMBERS
497034970449705497064970749708497094971049711
Power Reactor
Event Number: 49703
Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [] []
RX Type: (1) CE
NRC Notified By: SCOTT MOECK
HQ OPS Officer: DAN LIVERMORE
Region: 4 State: NE
Unit: [1] [] []
RX Type: (1) CE
NRC Notified By: SCOTT MOECK
HQ OPS Officer: DAN LIVERMORE
Notification Date: 01/09/2014
Notification Time: 06:42 [ET]
Event Date: 01/09/2014
Event Time: 03:15 [CST]
Last Update Date: 01/09/2014
Notification Time: 06:42 [ET]
Event Date: 01/09/2014
Event Time: 03:15 [CST]
Last Update Date: 01/09/2014
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):
BOB HAGAR (R4DO)
BOB HAGAR (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 99 | Power Operation | 96 | Power Operation |
INTAKE STRUCTURE SLUICE GATE INOPERABLE
" At 2230 CST on 1/8/14 during operator rounds it was self identified there was a block of ice formed on the shaft and top of one of the intake structure sluice gates. This has bent the sluice gate operating shaft. At 0315 CST on 1/9/14 it was verified this gate could not be closed.
"There are six intake sluice gates that are required to be able to close to act as flood barriers. The other 5 sluice gates are not affected by this condition."
The licensee informed the NRC Resident Inspector.
" At 2230 CST on 1/8/14 during operator rounds it was self identified there was a block of ice formed on the shaft and top of one of the intake structure sluice gates. This has bent the sluice gate operating shaft. At 0315 CST on 1/9/14 it was verified this gate could not be closed.
"There are six intake sluice gates that are required to be able to close to act as flood barriers. The other 5 sluice gates are not affected by this condition."
The licensee informed the NRC Resident Inspector.
Power Reactor
Event Number: 49704
Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [] []
RX Type: (1) CE
NRC Notified By: SCOTT MOECK
HQ OPS Officer: DAN LIVERMORE
Region: 4 State: NE
Unit: [1] [] []
RX Type: (1) CE
NRC Notified By: SCOTT MOECK
HQ OPS Officer: DAN LIVERMORE
Notification Date: 01/09/2014
Notification Time: 06:42 [ET]
Event Date: 01/09/2014
Event Time: 05:18 [CST]
Last Update Date: 01/09/2014
Notification Time: 06:42 [ET]
Event Date: 01/09/2014
Event Time: 05:18 [CST]
Last Update Date: 01/09/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
BOB HAGAR (R4DO)
BOB HAGAR (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 99 | Power Operation | 0 | Hot Shutdown |
TECH SPEC REQUIRED SHUTDOWN DUE TO INOPERABLE RAW WATER PUMPS.
"At 0315 CST T.S. 2.0.1 was entered for all four Raw Water pumps being declared inoperable. The pumps were declared inoperable due to inability to close one of the sluice gates. There are six sluice gates and one is not functional.
"At 0518 the technical specification required shutdown commenced."
The licensee notified the NRC Resident Inspector.
* * * UPDATE FROM AMY BURKHART TO NESTOR MAKRIS ON 01/09/14 AT 1915 EST * * *
"At 0900 CST 1/9/14 Fort Calhoun Station Unit 1 was manually tripped and entered Mode 3. Reactor Coolant System (RCS) cooldown to less than 300 deg F was commenced at time 1030 CST 1/9/14. The RCS temperature was less than 300 deg F at time 1433 CST. A press release has been issued."
The licensee informed the NRC Resident Inspector.
Notified R4DO [Hagar]
"At 0315 CST T.S. 2.0.1 was entered for all four Raw Water pumps being declared inoperable. The pumps were declared inoperable due to inability to close one of the sluice gates. There are six sluice gates and one is not functional.
"At 0518 the technical specification required shutdown commenced."
The licensee notified the NRC Resident Inspector.
* * * UPDATE FROM AMY BURKHART TO NESTOR MAKRIS ON 01/09/14 AT 1915 EST * * *
"At 0900 CST 1/9/14 Fort Calhoun Station Unit 1 was manually tripped and entered Mode 3. Reactor Coolant System (RCS) cooldown to less than 300 deg F was commenced at time 1030 CST 1/9/14. The RCS temperature was less than 300 deg F at time 1433 CST. A press release has been issued."
The licensee informed the NRC Resident Inspector.
Notified R4DO [Hagar]
Power Reactor
Event Number: 49705
Facility: RIVER BEND
Region: 4 State: LA
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: DAN PIPKIN
HQ OPS Officer: NESTOR MAKRIS
Region: 4 State: LA
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: DAN PIPKIN
HQ OPS Officer: NESTOR MAKRIS
Notification Date: 01/09/2014
Notification Time: 15:29 [ET]
Event Date: 01/09/2014
Event Time: 00:00 [CST]
Last Update Date: 01/09/2014
Notification Time: 15:29 [ET]
Event Date: 01/09/2014
Event Time: 00:00 [CST]
Last Update Date: 01/09/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
BOB HAGAR (R4DO)
BOB HAGAR (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 |
UNANALYZED CONDITION IDENTIFIED FROM OPERATING EXPERIENCE REVIEW
"A review of industry operating experience regarding the impact of unfused [safety-related] direct current ammeter circuits in the main control room has determined the described condition [having the ammeters installed] to be applicable to River Bend Station, resulting in a potentially unanalyzed condition with respect to 10 CFR 50 Appendix R analysis requirements. River Bend Station does have unfused ammeter leads. This normally is not a concern, since two failures are required to cause the problem described in the document referenced above; an ammeter lead must short to ground, and another lead of the opposite polarity must also short to ground. Either of these events by itself will set an alarm, but not cause equipment damage. This allows for locating and repairing the problem before the second failure occurs. However, during a fire, there is a greater chance that these two failures could happen simultaneously, or before a single failure can be repaired.
"This condition is being reported in accordance with 10 CFR 50.72(b)(3)(ii)(B). Interim compensatory measures have been implemented."
The NRC Resident Inspector has been notified.
"A review of industry operating experience regarding the impact of unfused [safety-related] direct current ammeter circuits in the main control room has determined the described condition [having the ammeters installed] to be applicable to River Bend Station, resulting in a potentially unanalyzed condition with respect to 10 CFR 50 Appendix R analysis requirements. River Bend Station does have unfused ammeter leads. This normally is not a concern, since two failures are required to cause the problem described in the document referenced above; an ammeter lead must short to ground, and another lead of the opposite polarity must also short to ground. Either of these events by itself will set an alarm, but not cause equipment damage. This allows for locating and repairing the problem before the second failure occurs. However, during a fire, there is a greater chance that these two failures could happen simultaneously, or before a single failure can be repaired.
"This condition is being reported in accordance with 10 CFR 50.72(b)(3)(ii)(B). Interim compensatory measures have been implemented."
The NRC Resident Inspector has been notified.
Power Reactor
Event Number: 49706
Facility: LIMERICK
Region: 1 State: PA
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: PAUL MARVEL
HQ OPS Officer: GEROND GEORGE
Region: 1 State: PA
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: PAUL MARVEL
HQ OPS Officer: GEROND GEORGE
Notification Date: 01/09/2014
Notification Time: 15:21 [ET]
Event Date: 01/09/2014
Event Time: 11:35 [EST]
Last Update Date: 01/09/2014
Notification Time: 15:21 [ET]
Event Date: 01/09/2014
Event Time: 11:35 [EST]
Last Update Date: 01/09/2014
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):
WAYNE SCHMIDT (R1DO)
WAYNE SCHMIDT (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 |
ENTRY INTO & EXIT FROM TECHNICAL SPECIFICATION 3.6.5.1.1 DUE TO OPEN AIR LOCK DOORS
"Station Personnel simultaneously opened the inner and outer air lock doors from Unit 2 (U2) Reactor Enclosure to the Refuel Floor. Reactor Enclosure Secondary Containment Integrity was declared Inoperable per U2 TS 3.6.5.1.1, due to failure to meet surveillance requirement U2 TS 4.6.5.1.1.b.2, due to the report of both containment airlock doors on 352' momentarily open at the same time. Reactor Enclosure D/P[differential pressure] remained steady at 0.35 inches vacuum water gauge.
"Reactor Enclosure Secondary Containment Integrity was declared Operable following verification that at least one air lock door to each access of secondary containment was closed per U2 TS 4.6.5.1.1.b.2. Total [Limiting Condition for Operation] time was approximately 5 seconds."
The NRC Resident Inspector has been informed.
"Station Personnel simultaneously opened the inner and outer air lock doors from Unit 2 (U2) Reactor Enclosure to the Refuel Floor. Reactor Enclosure Secondary Containment Integrity was declared Inoperable per U2 TS 3.6.5.1.1, due to failure to meet surveillance requirement U2 TS 4.6.5.1.1.b.2, due to the report of both containment airlock doors on 352' momentarily open at the same time. Reactor Enclosure D/P[differential pressure] remained steady at 0.35 inches vacuum water gauge.
"Reactor Enclosure Secondary Containment Integrity was declared Operable following verification that at least one air lock door to each access of secondary containment was closed per U2 TS 4.6.5.1.1.b.2. Total [Limiting Condition for Operation] time was approximately 5 seconds."
The NRC Resident Inspector has been informed.
Power Reactor
Event Number: 49707
Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [1] [] []
RX Type: [1] CE,[2] CE
NRC Notified By: DAVE FIELDS
HQ OPS Officer: NESTOR MAKRIS
Region: 2 State: FL
Unit: [1] [] []
RX Type: [1] CE,[2] CE
NRC Notified By: DAVE FIELDS
HQ OPS Officer: NESTOR MAKRIS
Notification Date: 01/09/2014
Notification Time: 18:56 [ET]
Event Date: 01/09/2014
Event Time: 18:03 [EST]
Last Update Date: 01/10/2014
Notification Time: 18:56 [ET]
Event Date: 01/09/2014
Event Time: 18:03 [EST]
Last Update Date: 01/10/2014
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
GEORGE HOPPER (R2DO)
JOHN LUBINSKI (NRR)
WILLIAM GOTT (IRD)
GEORGE HOPPER (R2DO)
JOHN LUBINSKI (NRR)
WILLIAM GOTT (IRD)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
UNUSUAL EVENT DECLARED DUE TO SEVERE RAIN STORM
"On January 9, 2014 St. Lucie Unit 1 declared an Unusual Event based on a severe rain storm, a natural occurrence affecting the Protected Area. Specifically, visual sightings by station personnel that water levels are approaching storm drain system capacity. Countermeasures are being deployed and are currently operating satisfactorily. Both units continue to operate at full power. All safety systems remain available.
The licensee has notified the NRC Resident Inspector, state, and other local authorities.
Notified R2DO (Hopper), NRR EO (Lubinski) and IRD.
Notified DHS SWO, DOE Ops Center, FEMA Ops Center, HHS Ops Center, NICC Watch Officer, and Nuclear SSA via email.
* * * UPDATE FROM RACHEL SMITH TO GEROND GEORGE ON 01/10/2014 AT 0043 EST * * *
"On January 10, 2014 at 0001 EST, St. Lucie Unit 1 terminated an Unusual Event. Site storm drain system functioning as required. Severe weather has passed, site water levels have returned to normal."
Notified R2DO (Hopper), NRR EO (Lubinski) and IRD.
Notified DHS SWO, DOE Ops Center, FEMA Ops Center, HHS Ops Center, NICC Watch Officer, and Nuclear SSA via email.
"On January 9, 2014 St. Lucie Unit 1 declared an Unusual Event based on a severe rain storm, a natural occurrence affecting the Protected Area. Specifically, visual sightings by station personnel that water levels are approaching storm drain system capacity. Countermeasures are being deployed and are currently operating satisfactorily. Both units continue to operate at full power. All safety systems remain available.
The licensee has notified the NRC Resident Inspector, state, and other local authorities.
Notified R2DO (Hopper), NRR EO (Lubinski) and IRD.
Notified DHS SWO, DOE Ops Center, FEMA Ops Center, HHS Ops Center, NICC Watch Officer, and Nuclear SSA via email.
* * * UPDATE FROM RACHEL SMITH TO GEROND GEORGE ON 01/10/2014 AT 0043 EST * * *
"On January 10, 2014 at 0001 EST, St. Lucie Unit 1 terminated an Unusual Event. Site storm drain system functioning as required. Severe weather has passed, site water levels have returned to normal."
Notified R2DO (Hopper), NRR EO (Lubinski) and IRD.
Notified DHS SWO, DOE Ops Center, FEMA Ops Center, HHS Ops Center, NICC Watch Officer, and Nuclear SSA via email.
Power Reactor
Event Number: 49708
Facility: ROBINSON
Region: 2 State: SC
Unit: [2] [] []
RX Type: [2] W-3-LP
NRC Notified By: JOHN MCDONALD
HQ OPS Officer: NESTOR MAKRIS
Region: 2 State: SC
Unit: [2] [] []
RX Type: [2] W-3-LP
NRC Notified By: JOHN MCDONALD
HQ OPS Officer: NESTOR MAKRIS
Notification Date: 01/10/2014
Notification Time: 00:27 [ET]
Event Date: 01/09/2014
Event Time: 22:34 [EST]
Last Update Date: 01/10/2014
Notification Time: 00:27 [ET]
Event Date: 01/09/2014
Event Time: 22:34 [EST]
Last Update Date: 01/10/2014
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):
GEORGE HOPPER (R2DO)
GEORGE HOPPER (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
AUTOMATIC REACTOR TRIP DUE TO TURBINE TRIP
"At 2234 hours EST on 01/09/2014, with the unit in Mode 1 at 100% power, an automatic reactor trip occurred. At the time of the event, Steam Generator Water level Protection Channel Testing was in progress. While testing was in progress with the 'C' Steam Generator Channel 1 Water Level Protection channel in trip for testing, a Turbine Trip occurred. The cause of the Turbine Trip is under investigation.
"The [Turbine Driven and Motor Driven] Auxiliary Feedwater System automatically actuated, as expected due to low steam generator water level, and provided feedwater to the steam generators. The pressurizer Power Operated Relief Valves (PORVs) and the Main Steam Safety Valves did not open during the event. All control rods indicated fully inserted following the reactor trip.
"Currently, the unit is stable in Hot Standby (Mode 3).
"This event is being reported as a 4 hour Non-Emergency per 10 CFR 50.72(b)(2)(iv)(B) due to the valid Reactor Protection System Actuation.
"This event is being reported as an 8 hour Non-Emergency per 10 CFR 50.72(b)(3)(iv)(A) due to the valid actuation of Auxiliary Feedwater System.
"At no time during this occurrence was the public or plant staff at risk as a result of this event.
"The NRC Resident Inspector has been notified. State and local authorities will be notified. Estimated restart date is 1/12/2014"
"At 2234 hours EST on 01/09/2014, with the unit in Mode 1 at 100% power, an automatic reactor trip occurred. At the time of the event, Steam Generator Water level Protection Channel Testing was in progress. While testing was in progress with the 'C' Steam Generator Channel 1 Water Level Protection channel in trip for testing, a Turbine Trip occurred. The cause of the Turbine Trip is under investigation.
"The [Turbine Driven and Motor Driven] Auxiliary Feedwater System automatically actuated, as expected due to low steam generator water level, and provided feedwater to the steam generators. The pressurizer Power Operated Relief Valves (PORVs) and the Main Steam Safety Valves did not open during the event. All control rods indicated fully inserted following the reactor trip.
"Currently, the unit is stable in Hot Standby (Mode 3).
"This event is being reported as a 4 hour Non-Emergency per 10 CFR 50.72(b)(2)(iv)(B) due to the valid Reactor Protection System Actuation.
"This event is being reported as an 8 hour Non-Emergency per 10 CFR 50.72(b)(3)(iv)(A) due to the valid actuation of Auxiliary Feedwater System.
"At no time during this occurrence was the public or plant staff at risk as a result of this event.
"The NRC Resident Inspector has been notified. State and local authorities will be notified. Estimated restart date is 1/12/2014"
Power Reactor
Event Number: 49709
Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [] []
RX Type: [2] GE-5
NRC Notified By: JASON LOVEGREN
HQ OPS Officer: DAN LIVERMORE
Region: 4 State: WA
Unit: [2] [] []
RX Type: [2] GE-5
NRC Notified By: JASON LOVEGREN
HQ OPS Officer: DAN LIVERMORE
Notification Date: 01/10/2014
Notification Time: 02:14 [ET]
Event Date: 01/09/2014
Event Time: 17:43 [PST]
Last Update Date: 01/10/2014
Notification Time: 02:14 [ET]
Event Date: 01/09/2014
Event Time: 17:43 [PST]
Last Update Date: 01/10/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
BOB HAGAR (R4DO)
BOB HAGAR (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 |
LOSS OF SECONDARY CONTAINMENT DIFFERENTIAL PRESSURE
"Reactor Building (Secondary Containment) pressure increased to above the Technical Specification Surveillance requirement of 0.25 inches vacuum water gauge briefly (two minutes or less) on two occasions. This is reportable as an event that could have prevented fulfillment of a safety function needed to control the release of radiation and mitigate the consequences of an accident. Reactor Building pressure has been restored to normal (greater than 0.25 inches vacuum water gauge) returning Secondary Containment to operable status. The cause of the event is under investigation.
"There were no radiological releases associated with the event.
"No safety system actuations or isolations occurred."
The licensee notified the NRC Resident Inspector.
"Reactor Building (Secondary Containment) pressure increased to above the Technical Specification Surveillance requirement of 0.25 inches vacuum water gauge briefly (two minutes or less) on two occasions. This is reportable as an event that could have prevented fulfillment of a safety function needed to control the release of radiation and mitigate the consequences of an accident. Reactor Building pressure has been restored to normal (greater than 0.25 inches vacuum water gauge) returning Secondary Containment to operable status. The cause of the event is under investigation.
"There were no radiological releases associated with the event.
"No safety system actuations or isolations occurred."
The licensee notified the NRC Resident Inspector.
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 49710
Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [] []
RX Type: (1) CE
NRC Notified By: SCOTT MOECK
HQ OPS Officer: DAN LIVERMORE
Region: 4 State: NE
Unit: [1] [] []
RX Type: (1) CE
NRC Notified By: SCOTT MOECK
HQ OPS Officer: DAN LIVERMORE
Notification Date: 01/10/2014
Notification Time: 06:39 [ET]
Event Date: 01/09/2014
Event Time: 23:17 [CST]
Last Update Date: 01/16/2014
Notification Time: 06:39 [ET]
Event Date: 01/09/2014
Event Time: 23:17 [CST]
Last Update Date: 01/16/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
WAYNE WALKER (R4DO)
WAYNE WALKER (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Hot Standby | 0 | Hot Shutdown |
DEGRADED FITTINGS CONNECTED TO CONTAINMENT PENETRATION
"During an engineering walk down inside containment a minor leak from a pipe fitting was discovered on the primary sampling piping connected to penetration M-45. There was previously identified minor leakage from a fitting on this same penetration outside of containment in the auxiliary building. The containment isolation valves are currently tagged closed."
The licensee notified the NRC Resident Inspector.
* * * UPDATE FROM SCOTT MOECK TO JOHN SHOEMAKER AT 1320 EST ON 1/16/14 * * *
"Additional testing was performed on penetration M-45 which determined that the penetration met the required leakage limits. Therefore this issue does not represent a degraded condition for the containment and is not reportable. The previous notification is being retracted."
The licensee has notified the NRC Resident Inspector.
Notified the R4DO (Kellar).
"During an engineering walk down inside containment a minor leak from a pipe fitting was discovered on the primary sampling piping connected to penetration M-45. There was previously identified minor leakage from a fitting on this same penetration outside of containment in the auxiliary building. The containment isolation valves are currently tagged closed."
The licensee notified the NRC Resident Inspector.
* * * UPDATE FROM SCOTT MOECK TO JOHN SHOEMAKER AT 1320 EST ON 1/16/14 * * *
"Additional testing was performed on penetration M-45 which determined that the penetration met the required leakage limits. Therefore this issue does not represent a degraded condition for the containment and is not reportable. The previous notification is being retracted."
The licensee has notified the NRC Resident Inspector.
Notified the R4DO (Kellar).
Agreement State
Event Number: 49711
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: ASCEND PERFORMANCE MATERIALS OPERATIONS LLC
Region: 4
City: ALVIN State: TX
County:
License #: 06721
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: JIM DRAKE
Licensee: ASCEND PERFORMANCE MATERIALS OPERATIONS LLC
Region: 4
City: ALVIN State: TX
County:
License #: 06721
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: JIM DRAKE
Notification Date: 01/10/2014
Notification Time: 09:45 [ET]
Event Date: 01/09/2014
Event Time: 00:00 [CST]
Last Update Date: 01/10/2014
Notification Time: 09:45 [ET]
Event Date: 01/09/2014
Event Time: 00:00 [CST]
Last Update Date: 01/10/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
WAYNE WALKER (R4DO)
ANGELA MCINTOSH (FSME)
FSME EVENT RESOURCE (EMAI)
WAYNE WALKER (R4DO)
ANGELA MCINTOSH (FSME)
FSME EVENT RESOURCE (EMAI)
AGREEMENT STATE REPORT INVOLVING STUCK SHUTTER ON LEVEL GAUGE
"On January 10, 2014, the Agency received a report from the licensee's Radiation Safety Officer (RSO) stating the shutter on a Ohmart Vega model SGLG gauge containing a 500 millicurie cesium - 137 source was found stuck in the open position. Open is the normal operation position of the gauge shutter. The RSO stated a contractor was performing a calibration of a level detector on January 9, 2014, when they could not get the gauge shutter to close. The contractor sprayed the shutter with a light oil and attempted to rotate the handle and operating arm. While trying to free the shutter, the operating arm separated from the gauge. The contractor was able to insert the operating rod into the gauge, but the shutter would not move. The manufacturer has been contacted to assist in the repair or replacement of the gauge. No exposure resulted from this event and the current position of the gauge shutter does not create any additional exposure risk to any personnel. A contact dose rate survey of the gauge was conducted and the highest reading observed was 1.2 millirem per hour. Additional information will be provided as it is received in accordance with SA-300."
Texas Incident Number: I-9145
"On January 10, 2014, the Agency received a report from the licensee's Radiation Safety Officer (RSO) stating the shutter on a Ohmart Vega model SGLG gauge containing a 500 millicurie cesium - 137 source was found stuck in the open position. Open is the normal operation position of the gauge shutter. The RSO stated a contractor was performing a calibration of a level detector on January 9, 2014, when they could not get the gauge shutter to close. The contractor sprayed the shutter with a light oil and attempted to rotate the handle and operating arm. While trying to free the shutter, the operating arm separated from the gauge. The contractor was able to insert the operating rod into the gauge, but the shutter would not move. The manufacturer has been contacted to assist in the repair or replacement of the gauge. No exposure resulted from this event and the current position of the gauge shutter does not create any additional exposure risk to any personnel. A contact dose rate survey of the gauge was conducted and the highest reading observed was 1.2 millirem per hour. Additional information will be provided as it is received in accordance with SA-300."
Texas Incident Number: I-9145