| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
05/13/2016 - 05/16/2016 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 51909 | Rep Org: PA BUREAU OF RADIATION PROTECTION
Licensee: N/A
Region: 1
City: State: PA
County: BLAIR
License #:
Agreement: Y
Docket:
NRC Notified By: JOSEPH MELNIC
HQ OPS Officer: DONG HWA PARK | Notification Date: 05/05/2016
Notification Time: 15:02 [ET]
Event Date: 05/05/2016
Event Time: [EDT]
Last Update Date: 05/05/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
FRED BOWER (R1DO)
NMSS_EVENTS_NOTIFICA (EMAI)
| Event Text AGREEMENT STATE REPORT - DISCOVERY OF VACUUM GAUGE
The following was received from the Commonwealth of Pennsylvania via email:
"On May 5, 2016, the Blair County Emergency Management Agency notified the Department [of Environmental Protection] of the discovery of a NRC Equipment Corporation Model 530 Alphatron vacuum gauge. This gauge was located in a wooded area in Blair County, Pennsylvania. The gauge was manufactured with approximately 100 microcuries of radium-226. The manufacturer is no longer in business. The Department has retrieved the gauge and will safely store it until its annual collection of radium sources in September, 2016. No exposures have occurred with this discovery. It is reportable under 10 CFR 20.2201(a)(1)(i)."
Event Report ID No: PA160013 |
| Agreement State | Event Number: 51911 | Rep Org: ALABAMA RADIATION CONTROL
Licensee: MILLENNIUM RESOURCES, LLC
Region: 1
City: GRAYSVILLE State: AL
County:
License #: G/L
Agreement: Y
Docket:
NRC Notified By: MYRON K. RILEY
HQ OPS Officer: HOWIE CROUCH | Notification Date: 05/06/2016
Notification Time: 10:24 [ET]
Event Date: 05/06/2016
Event Time: 09:15 [CDT]
Last Update Date: 05/06/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
FRED BOWER (R1DO)
NMSS_EVENTS_NOTIFIC (EMAI)
|
| This material event contains a "Less than Cat 3 " level of radioactive material. | Event Text ALABAMA AGREEMENT STATE REPORT - LOST GENERALLY LICENSED PROCESS GAUGE
The following information was obtained from the State of Alabama via facsimile:
"On May 5, 2016, it was determined that Millennium Resources, LLC, Graysville, Alabama had lost control and possession of a generally licensed device (Ronan SA1-C5 #2255GO containing 5 mCi of Cs-137).
"During a requested visit by the new owner Cane Creek, LLC on April 7, 2016, it was determined that they possessed a new generally licensed device. The new owners only knew that the site once contained a similar plant which contained a device with radioactive material. The old plant was constructed in 1997, and our [Alabama Department of Public Health - Office of Radiation Control] records show that device being received by Millennium Resources, LLC on November 14, 1997. The plant was torn down and sold for scrap during the year of 2006. The new owners had no information in regards to whom the scrap was sold or the whereabouts of the device.
"On April 7, 2016, the Agency [Alabama Department of Public Health - Office of Radiation Control] contacted Ronan and their records indicated no transfer for disposal. During the next few weeks, several calls were made to the Alabama Department of Environmental Management and the Alabama Surface Mining Commission to determine if any new information could be obtained. None of the representatives could provide any additional information.
"As of today [5/6/16], 0915 CDT, the device containing radioactive material has not been recovered. This incident remains open until further investigation can be completed."
Alabama Incident 16-15
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: 51925 | Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: CARL YOUNG
HQ OPS Officer: HOWIE CROUCH | Notification Date: 05/13/2016
Notification Time: 05:00 [ET]
Event Date: 05/13/2016
Event Time: 01:10 [EDT]
Last Update Date: 05/13/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
50.72(b)(2)(iv)(A) - ECCS INJECTION
| Person (Organization):
ART BURRITT (R1DO)
SCOTT MORRIS (NRR)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | M/R | Y | 100 | Power Operation | 0 | Hot Shutdown | Event Text MANUAL REACTOR SCRAM DUE AFTER LOSS OF AN ESSENTIAL MOTOR CONTROL CENTER
"At approximately 0110 hours [EDT] on May 13, 2016, Susquehanna Steam Electric Station Unit Two reactor was manually scrammed by plant operators due to a sustained loss of AC power to essential plant loads. Power to MCC 2B246 was lost at 2355 on May 12, 2016, resulting in a loss of Drywell cooling. Drywell pressure increased to 1.3 psig when operators placed the mode switch to the shutdown position to manually SCRAM the reactor. All rods inserted as expected. Reactor water level lowered to -27 inches and was immediately restored by normal feedwater level control. Level 3 (+13 inch) PCIS isolations occurred, along with an initiation of the RCIC system (-30 inches). Once adequate level was verified, RCIC was overridden. Pressure was controlled with turbine bypass valves, and subsequently main steam line drains. All safety systems functioned as expected.
"The power loss also tripped Reactor Building HVAC, causing a loss of secondary containment differential pressure resulting in a loss of safety function.
"Due to the loss of drywell cooling, high drywell pressure actuations and a second reactor SCRAM signal, this signal was automatic, occurred at 0314 hours. HPCI [which automatically initiated on high drywell pressure] was subsequently overridden and declared inoperable, resulting in a loss of safety function. [HPCI did not inject into the vessel].
"The reactor is currently stable in Mode 3. Initial reports from the field indicate a phase to phase fault on the MCC 2B246 bus bars."
The licensee has notified the NRC Resident Inspector and will be issuing a press release. |
| Power Reactor | Event Number: 51928 | Facility: RIVER BEND
Region: 4 State: LA
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: ROB MELTON
HQ OPS Officer: VINCE KLCO | Notification Date: 05/13/2016
Notification Time: 20:02 [ET]
Event Date: 05/13/2016
Event Time: 12:00 [CDT]
Last Update Date: 05/13/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
| Person (Organization):
VIVIAN CAMPBELL (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 EXISTING DESIGN INADEQUACY COULD PREVENT STANDBY GAS TREATMENT SYSTEM OPERABLITY
"At 1200 [CDT] May 13, 2016, while the plant was operating at 100% power, it was brought to the attention of the River Bend Station Main Control Room staff that an existing design inadequacy could prevent both trains of the Standby Gas Treatment System (GTS) from performing its design function. Under certain specific conditions, the installed Masterpact breakers may not close to allow energization of the filter train exhaust fans. A start signal (reactor level 2, drywell pressure 1.68 psid, annulus high radiation, annulus low flow) combined with a trip signal within a certain time differential, could result in a failure of the breakers to close. As a result of this condition, both Standby Gas Trains were declared inoperable, which required entry into LCO 3.6.4.3 Condition C (requires entering Mode 3 in 12 hours). Declaring both trains of Standby Gas Treatment System inoperable resulted in loss of the safety function since a system that has been declared inoperable is one in which the capability has degraded to the point where it cannot perform with reasonable expectation or reliability.
"The Standby Gas Treatment System (GTS) limits release to the environment of radioisotopes, which may leak from the primary containment, ECCS systems, and other potential radioactive sources to the secondary containment under accident conditions.
"At 1240 [CDT] May 13, 2016, one division of GTS, GTS 'A', was manually started from the Main Control Room. This action prevents the breaker failure mode, restored the operability of one train and restored the safety function of the GTS system. LCO 3.6.4.3 Condition A (restore Operability in 7 days) is currently entered for Standby Gas Train 'B'. During the 40 minutes of inoperability, both trains of Standby Gas remained available. At no time was the health or safety of the public impacted.
"This condition is being reported in accordance with 10CFR50.72(b)(3)(v)(C) as an event that could have caused a loss of safety function to control the release of radioactive material. The Senior NRC Resident was notified." |
| Power Reactor | Event Number: 51929 | Facility: MILLSTONE
Region: 1 State: CT
Unit: [ ] [ ] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: MICHAEL CICCONE
HQ OPS Officer: DONALD NORWOOD | Notification Date: 05/15/2016
Notification Time: 07:08 [ET]
Event Date: 05/15/2016
Event Time: 06:38 [EDT]
Last Update Date: 05/15/2016 | Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
ART BURRITT (R1DO)
DAVID LEW (R1DR)
BRIAN MCDERMOTT (NRR)
JEFFERY GRANT (IRD)
SCOTT MORRIS (NRR)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | M/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text UNUSUAL EVENT DUE TO MAIN GENERATOR HYDROGEN LEAK IN TURBINE BUILDING
At 0638 EDT on 5/15/2016, an Unusual Event (EAL GU.2) was declared on Millstone Unit 3 due to a Main Generator hydrogen gas leak into the Turbine Building. At 0645 EDT, operators manually tripped the reactor. All rods inserted. All systems functioned as expected following the reactor trip. Operators are currently venting the remaining hydrogen from the generator through the normal vent path. There is no safety related equipment out-of-service. The plant is in a normal post-trip electrical line-up. All Emergency Diesel Generators are available.
The licensee notified the State of Connecticut and the NRC Resident Inspector.
Notified DHS SWO, FEMA Ops Center, and DHS NICC Watch Officer. Notified via E-mail FEMA National Watch Center and NuclearSSA.
* * * UPDATE FROM MIKE CICCONE TO HOWIE CROUCH AT 1044 EDT ON 5/15/16 * * *
At 0949 EDT, the licensee terminated the Unusual Event.
"At 0645 EDT on 5/15/16, a manual reactor trip was initiated at Millstone Unit 3 due to a hydrogen leak from the main generator. As expected, Auxiliary Feedwater System (AFW) initiated on the reactor trip. The trip was uncomplicated and the plant is currently in Mode 3 with a normal electric lineup and decay heat is being removed via steam dumps to the condenser. The cause of the hydrogen leakage is under investigation. This is reportable under 10 CFR 50.72(b)(2)(iv)(B) - RPS actuation while critical, and 10 CFR 50.72 (b)(3)(iv)(A) - valid specified system actuation."
The licensee has notified Waterford Township, the State of Connecticut and the NRC Resident Inspector.
Notified R1DO (Burritt), NRR ET (McDermott), NRR EO (Morris), IRD (Grant), DHS SWO, FEMA Ops Center, DHS NICC, FEMA National Watch Center (email) and NuclearSSA (email). |
| Power Reactor | Event Number: 51931 | Facility: BYRON
Region: 3 State: IL
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RICARDO ROSAS
HQ OPS Officer: VINCE KLCO | Notification Date: 05/15/2016
Notification Time: 12:34 [ET]
Event Date: 05/15/2016
Event Time: 11:18 [CDT]
Last Update Date: 05/15/2016 | Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
ERIC DUNCAN (R3DO)
CYNTHIA PEDERSON (RA3)
BILL DEAN (NRR)
JEFF GRANT (IRD)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | Hot Standby | 0 | Hot Standby | Event Text UNUSUAL EVENT DECLARED DUE TO EXCESSIVE UNIDENTIFIED LEAKAGE DURING PLANT STARTUP
"Unit 2 experienced RCS Leakage, potentially pressure boundary leakage, or Unidentified Leakage greater than 10 gpm for [greater than] 15 minutes. Reactor Vessel Flange Temperature High Leakoff alarm was received. This met threshold for declaration of an Unusual Event at 1118 CDT per MU6. Unit 2 is currently in MODE 3. Investigation is in progress to identify specific leakage location."
The plant is stable, leakage indicates about 32 gpm and the startup has been stopped. There is no impact on Unit 1.
The licensee notified the NRC Resident Inspector and State authorities.
Notified DHS SWO, FEMA Ops Center, DHS NICC,. Notified FEMA National Watch and Nuclear SSA via email.
* * * UPDATE FROM RICARDO ROSAS TO VINCE KLCO ON 5/15/16 AT 1626 EDT * * *
"At 1459 CDT, the conditions under MU6 are no longer met. The site has terminated the Unusual Event. In addition, a press release will be made of this event."
Unit 2 is stable and in Mode 3 pending further evaluation. The leak stopped when a loop drain isolation valve was closed.
The licensee notified the NRC Resident Inspector and State and local authorities.
Notified the R3DO (Duncan), NRR EO (Morris), IRD MOC (Grant), DHS SWO, FEMA Ops Center, and DHS NICC. Notified the FEMA National Watch and Nuclear SSA via email. |
| Power Reactor | Event Number: 51932 | Facility: SEABROOK
Region: 1 State: NH
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: MATTHEW LARRABEE
HQ OPS Officer: DAN LIVERMORE | Notification Date: 05/16/2016
Notification Time: 02:02 [ET]
Event Date: 05/16/2016
Event Time: 03:00 [EDT]
Last Update Date: 05/16/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
ART BURRITT (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 | Event Text SEISMIC MONITORING SYSTEM OUT OF SERVICE FOR PLANNED UPGRADE
"At 0300 EDT on May 16, 2016, Seabrook Station's seismic monitoring instrumentation will be removed from service for a planned upgrade to the Seismic Monitoring Control Panel and its accelerometers. Modifications are expected to be complete on May 27, 2016. Proceduralized compensatory measures are in place and have been communicated to applicable emergency response decision makers. This preplanned action is being reported in accordance with 10 CFR 50.72(b)(xiii)."
The NRC Resident Inspector has been notified. | |