| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
04/20/2017 - 04/21/2017 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 52674 | Facility: OYSTER CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-2
NRC Notified By: THOMAS J. BUSK
HQ OPS Officer: DONG HWA PARK | Notification Date: 04/12/2017
Notification Time: 21:06 [ET]
Event Date: 04/12/2017
Event Time: 15:30 [EDT]
Last Update Date: 04/20/2017 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
DON JACKSON (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 LOSS OF THE TECHNICAL SUPPORT CENTER VENTILATION SYSTEM
"Oyster Creek Generating Station has experienced a loss of the Technical Support Center (TSC) ventilation system due to charcoal filter test failure. A charcoal filter replacement is planned.
"If an emergency is declared requiring TSC activation during the time TSC ventilation is non-functional, the TSC will be staffed and activated using existing emergency planning procedure unless the TSC becomes uninhabitable due to ambient temperature, radiological, or other conditions. If relocation of the TSC becomes necessary, the Emergency Director will relocate the TSC staff to an alternate location in accordance with applicable site procedures.
"This notification is being made in accordance with 10 CFR 50.72(b)(3)(xiii) due to a loss of the TSC. An update will be provided once the TSC ventilation has been restored to normal operation.
"The NRC Resident Inspector will be notified."
* * * RETRACTION ON 4/20/17 AT 1447 EDT FROM JIM RITCHIE TO DONG PARK * * *
"This is a retraction of ENS notification 52674. After further testing and evaluation, the station concluded that the TSC Ventilation Charcoal filter met the acceptance criteria, and the TSC Ventilation was not inoperable at the moment the original ENS notification was performed."
The licensee will notify the NRC Resident Inspector. Notified R1DO (Arner). |
| Agreement State | Event Number: 52675 | Rep Org: NC DIV OF RADIATION PROTECTION
Licensee: NC DEPARTMENT OF TRANSPORTATION
Region: 1
City: RALEIGH State: NC
County:
License #: 092-0104-1
Agreement: Y
Docket:
NRC Notified By: DAVID CROWLEY
HQ OPS Officer: HOWIE CROUCH | Notification Date: 04/13/2017
Notification Time: 12:23 [ET]
Event Date: 04/11/2017
Event Time: [EDT]
Last Update Date: 04/13/2017 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
DON JACKSON (R1DO)
NMSS_EVENTS_NOTIFIC (EMAI)
ILTAB (EMAI)
|
| This material event contains a "Less than Cat 3 " level of radioactive material. | Event Text AGREEMENT STATE REPORT - LOST TROXLER MOISTURE DENSITY GAUGE
The following information was obtained from the state of North Carolina via email:
"1. Essential Details
"a. Narrative event description (e.g., Event circumstances and details including source radionuclide and activity).
RSO [Radiation Safety Officer] discovered gauge missing while doing inventory check on Tuesday, April 11, 2017. It was last checked in the log book on March 8, 2017 when it came back from calibration and leak testing from the manufacturer.
"b. Report identification number.
NC Local NMED 170014
"c. Event date and notification date.
Event discovered 4/11/2017 and notified on 4/12/2017.
"d. Licensee/reporting party information (i.e., name license number, and address).
NC License #: 092-0104-1
Licensee: NC Department of Transportation
Address: 1801 Blue Ridge Rd. Raleigh NC 27607
"e. Location (site) of event.
"f. Whether the event is NRC reportable and the applicable reporting requirement.
10 CFR 20.2201(a)(1)(i)
"g. Cause and corrective actions (States and licensees' actions).
Failure to properly log or check out gauge at time of use. RSO believes that it was checked out to a DOT field office and not properly recorded. They are currently contacting all trainers of gauge users, DOT engineers, and any District Engineers that may have access in order to locate gauge. They are in the process of developing a barcode scan in/out electronic use log to maintain better accountability and knowledge of gauge locations. Final causes/corrective actions are still to be determined.
"h. Notifications: local police, FBI, and other States; as needed.
Upper State DHSR/DHHS [North Carolina Department of Health Service Regulation/Department of Health and Human Services] management notified; working on press release with public information office.
"i. Indicate if there are any generic implications (i.e., generic issues or concerns).
None.
"2. Source/Radioactive Material
Isotope and activity; manufacturer, model and serial number, and leak test results, if applicable.
Nuclear Gauge
Make: Troxler
Model: 4640-B (thin-lift asphalt)
Serial Number: 1628
Type of Source: Cs-137 (8.0 mCi)
Source Serial Number: 75-7134
Leak Test Results: Pass (Performed by manufacturer at last calibration)."
* * * UPDATE FROM DAVID CROWLEY TO HOWIE CROUCH (VIA EMAIL) ON 4/13/17 AT 1535 EDT * * *
"Gauge was discovered back at the manufacturer's facility. It apparently was checked back into the licensee, but something didn't work appropriately (not regarding RAM sources) and went immediately back to the manufacturer. Gauge was not logged appropriately for being shipped right back out and it was forgotten by the licensee sometime in the last month."
Notified R1DO (Jackson) and NMSS 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 |
| Non-Agreement State | Event Number: 52676 | Rep Org: QAL-TEK ASSOCIATES, LLC
Licensee: QAL-TEK ASSOCIATES, LLC
Region: 4
City: IDAHO FALLS State: ID
County:
License #: 11-27610-01
Agreement: N
Docket:
NRC Notified By: MICHAEL ALBANESE
HQ OPS Officer: DONG HWA PARK | Notification Date: 04/13/2017
Notification Time: 13:51 [ET]
Event Date: 04/13/2017
Event Time: 09:40 [MDT]
Last Update Date: 04/13/2017 | Emergency Class: NON EMERGENCY
10 CFR Section:
20.1906(d)(2) - EXTERNAL RAD LEVELS > LIMITS
| Person (Organization):
JOHN KRAMER (R4DO)
DANIEL COLLINS (NMSS)
NMSS_EVENTS_NOTIFIC (EMAI)
| Event Text SHIPMENT EXCEEDING PACKAGE DOSE RATE LIMITS
The following was received via email from the Licensee:
"At 0940 [MDT] on April 13th, 2017 [the common carrier] dropped off a 20 gallon drum (37.8 Kg) at Qal-Tek Associates (QTA) Idaho [ID] facility with an on-contact reading of 1.45 R/hr and a TI [Transport Index] of 15, both in excess of 10CFR20.1906(d)(2). No contamination existed on the inside or outside of the package. Upon further investigation, all three sources (Cs-137, 19.4 mCi; Cs-137, 23 mCi; and Co-60, 2.5 mCi) shipped in a gray lead pig were outside their gray lead pig and in the Type 7A drum. The gray lead pig was found packaged upright in the drum with a slight tilt. The pig lid was intact and properly seated on the pig base. Apparently, the lid was displaced enough during shipment that all three sources came out of the pig by the time they arrive[d] at QTA ID. The root cause appears to be from improper sealing of the gray pig. The pig wasn't taped or strapped shut to prevent displacement of the pig and lid resulting in the release of the sources.
"The shipper confirmed the sources where originally placed in the gray pig around 1100 [MDT].
"The [common] carrier was contact[ed] at 1140 [MDT]. Assuming the maximally exposed member of the public was [the common carrier] transport employee, and they were on-contact with the drum at the highest reading, they could have potentially received 100 mrem in a little over 4 minutes. Likewise, they could have received 2 mrem in 5 seconds. Considering the TI of 15 mrem/hour, the MEI [maximally exposed individual] could potentially receive 100 mrem in 6.67 hours and 2 mrem in 0.13 hours." |
| Power Reactor | Event Number: 52696 | Facility: HATCH
Region: 2 State: GA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: PAUL UNDERWOOD
HQ OPS Officer: STEVE SANDIN | Notification Date: 04/20/2017
Notification Time: 05:57 [ET]
Event Date: 04/20/2017
Event Time: 03:02 [EDT]
Last Update Date: 04/20/2017 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
PHILIP McKENNA (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | A/R | Y | 1 | Startup | 0 | Hot Shutdown | Event Text AUTOMATIC REACTOR SCRAM DURING STARTUP
"On 04/20/2017 at 0302 EST during a reactor startup, a reactor scram resulted from upscale spike on two Intermediate Range Monitors (IRMs), 1C51K601A and 1C51K601B. IRM A, 1C51K601A is in Reactor Protection System Channel A and IRM B, 1C51K601B is in Reactor Protection System Channel B. All control rods fully inserted. No PCIS [Primary Containment Isolation System] actuations occurred and none were expected to occur based upon plant condition following the reactor scram.
"Investigation is in progress. Condition was not due to a true flux event.
"This event is reportable per 10 CFR 50.72(b)(2)(iv)(B) as an event or condition that resulted in actuation of the reactor protection system (RPS) when the reactor is critical except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation.
"CR 10356172
"The NRC Resident has been notified."
The reactor was at 0.5% (percent) power at the time of the event and will remain in Hot Shutdown pending the results of the root cause investigation. |
| Power Reactor | Event Number: 52698 | Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: RONALD HANNA
HQ OPS Officer: DONG HWA PARK | Notification Date: 04/20/2017
Notification Time: 19:13 [ET]
Event Date: 04/20/2017
Event Time: 13:06 [EDT]
Last Update Date: 04/20/2017 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
FRANK ARNER (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 MONITOR PANEL NON-FUNCTIONAL
"At 1306 [EDT] on April 20, 2017, Control Room Overhead Alarm C6-C4, Seismic Monitor Panel, was received. This alarm normally indicates an actuation of the Hope Creek OBE [Operational Basis Earthquake] Seismic Switch at 0.1g, however, this alarm was accompanied by no other indications of seismic activity. The indicator for a 0.01g earthquake was not actuated, no earthquake was felt on site, and the National Earthquake Information Center recorded no seismic activity in the area.
"The Seismic Monitor Panel was considered non-functional. With the Seismic Monitor Panel non-functional, the ability to classify EAL HA1.1, Operating Basis Earthquake Detected Onsite, was lost. Testing of the Seismic Monitor Panel is in progress to determine system functionality."
The licensee will notify the NRC Resident Inspector. |
| Power Reactor | Event Number: 52699 | Facility: SALEM
Region: 1 State: NJ
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JASON HANCOCK
HQ OPS Officer: DONALD NORWOOD | Notification Date: 04/20/2017
Notification Time: 21:36 [ET]
Event Date: 04/20/2017
Event Time: 21:10 [EDT]
Last Update Date: 04/20/2017 | Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
| Person (Organization):
FRANK ARNER (R1DO)
DAN DORMAN (R1)
BRIAN McDERMOTT (NRR)
MICHAEL F. KING (NRR)
JEFF GRANT (IRD)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | Refueling | 0 | Refueling | Event Text UNUSUAL EVENT DECLARED DUE TO HYDRAZINE IN CONTAINMENT
"At 2110 EDT, Salem control room received data that supported unacceptable levels of hydrazine concentration in the U2 Containment atmosphere based on Site Protection atmospheric sampling. The high hydrazine levels were caused due to Steam Generator venting into the Containment atmosphere in support of maintenance for the current Salem Unit 2 Refueling Outage (2R22). The NIOSH habitability limit for hydrazine is 0.03 ppm (2 hour limit). Area samples indicated concentrations as high as 0.25 ppm. Salem Unit 2 Containment has been evacuated while a mitigation plan is being developed. There were no personnel injuries as a result of this occurrence. Salem Unit 2 defueling activities were in progress during this event. All fuel assemblies have been placed in a safe condition. All Salem Unit 2 Containment activities are currently on hold. There has been no impact to the equipment in the Unit 2 Containment, no adverse impact to any equipment located in the vicinity of the high hydrazine concentration, and no operational impact to the plant including Shutdown Cooling which is currently on RHR."
The Unusual Event was declared under EAL HU3.1, Toxic/Flammable Gas Release Affecting Plant Operations.
The licensee plans to issue a press release.
The licensee notified the NRC Resident Inspector, Lower Alloways Creek Township, State of New Jersey and State of Delaware.
Notified DHS SWO, FEMA Operations Center, DHS NICC, FEMA NWC (email), DHS Nuclear SSA (email), and FEMA NRCC SASC (email). | |