| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
02/14/2014 - 02/18/2014 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 49665 | Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: MICHAEL MOORE
HQ OPS Officer: DONG HWA PARK | Notification Date: 12/19/2013
Notification Time: 19:18 [ET]
Event Date: 12/19/2013
Event Time: 15:11 [EST]
Last Update Date: 02/14/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
| 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 | Event Text LOSS OF REACTOR BUILDING VENTILATION
"At 1511 [EST] on December 19, 2013, bus 10A404 (D channel 4 kv 1E vital bus) deenergized while transferring infeed breakers after degraded voltage testing. Reactor building ventilation fans tripped resulting in a loss of secondary containment negative pressure. Filtration Recirculation and Ventilation System (FRVS) was manually started and secondary containment negative pressure was restored at 1525 [EST].
"Secondary containment pressure is stable with differential pressure negative.
"The technical specification requirement is to maintain secondary containment at a negative pressure for secondary containment integrity. Declaring secondary containment inoperable is reportable under 10CFR50.72(b)(3)(v)(C) as an event or condition that could have prevented the fulfillment of a safety function needed to control the release of radioactive material.
"The standby reactor building ventilation fans did not automatically start and [the reason for that] is being investigated."
The licensee notified the NRC Resident Inspector and will notify the Lower Alloways Creek township.
* * * UPDATE AT 1326 EST ON 2/14/14 FROM LINDSAY KOBERLEIN TO S. SANDIN * * *
The licensee is retracting this report based on the following:
"Hope Creek Generating Station Unit 1, is retracting the 8-hour non-emergency notification made on December 19, 2013, at 1918 EST (EN# 49665).
"The notification on December 19, 2013, reported that secondary containment was declared inoperable when reactor building ventilation system (RBVS) fans tripped resulting in the loss of secondary containment negative pressure.
"Subsequent engineering evaluation concluded that the safety function of secondary containment was not lost. The Hope Creek post-LOCA Exclusion Area Boundary, Low Population Zone, and Control Room dose calculation assumes that primary containment leakage is released directly to the environment with no credit for hold up or filtration for the first 375 seconds after the accident, i.e., the Hope Creek accident analysis does not assume that secondary containment is under vacuum at the start of an accident. In addition, the accident analysis relies upon the operation of the safety related Filtration Recirculation and Ventilation System (FRVS), which was fully operable. Upon receipt of an accident signal, FRVS would have automatically started and restored secondary containment negative pressure within the time limits of the design assumptions. The trip of the non-safety related RBVS and the failure of the stand-by RBVS fans to start did not result in an adverse impact on the dose consequence analysis. Although secondary containment was declared inoperable, the safety function was not lost and secondary containment was capable of performing its design function of minimizing any ground level release of radioactive material by providing a leak tight boundary so that FRVS may draw a vacuum In the Reactor Building and filter radioactive material at all times. The engineering evaluation is captured In the licensee's corrective action program. Based on the engineering evaluation, the condition reported in EN #49665 did not result in the loss of a safety function needed to control the release of radioactive material. This event report is being retracted.
"The NRC Resident Inspector has been briefed on the evaluation results and informed of this retraction."
Notified R1DO (Powell). |
| Agreement State | Event Number: 49798 | Rep Org: FLORIDA BUREAU OF RADIATION CONTROL
Licensee: ALL STATE ENGINEERING & TESTING CONSULTANTS
Region: 1
City: HIALEAH State: FL
County:
License #: FL1113-1
Agreement: Y
Docket:
NRC Notified By: TIM DUNN
HQ OPS Officer: STEVE SANDIN | Notification Date: 02/06/2014
Notification Time: 07:04 [ET]
Event Date: 02/06/2014
Event Time: [EST]
Last Update Date: 02/06/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
JON LILLIENDAHL (R1DO)
FSME EVENTS RESOURCE (EMAI)
ILTAB (EMAI)
|
| This material event contains a "Less than Cat 3 " level of radioactive material. | Event Text AGREEMENT STATE REPORT - TROXLER GAUGE STOLEN FROM TRUCK AT RESIDENCE
The State of Florida was notified at 0630 EST on 2/6/14, that the cab of a gauge user's truck was broken into and the case containing a Troxler Moisture-Density Gauge was stolen overnight at the gauge user's residence located in West Palm Beach, FL. The gauge, a model 3440, was properly stowed and locked in its case.
This gauge contained 5.7 mCi of Cs-137, and 39.1 mCi of Am-241:Be.
Local Law Enforcement is on-scene conducting an investigation.
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: 49805 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: TEXAS QA SERVICES INC.
Region: 4
City: GRAND PRAIRIE State: TX
County:
License #: 04601
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: PETE SNYDER | Notification Date: 02/07/2014
Notification Time: 08:44 [ET]
Event Date: 02/06/2014
Event Time: [CST]
Last Update Date: 02/07/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
GREG WERNER (R4DO)
FSME EVENT RESOURCE (FSME)
| Event Text AGREEMENT STATE REPORT - SOURCE DISCONNECT AND RETRIEVAL
The following information was obtained from the State of Texas via email:
"On February 7, 2014, the Agency [Texas Department of State Health Services] was notified by the licensee's Radiation Safety Officer (RSO) a source disconnect had occurred on February 6, 2014. The disconnect occurred while radiographers were working at a field location using a QSA model 880D exposure device with a 39 curie iridium-192 source.
"The radiographers were working in a shooting bay and had been working for about five hours when the problem occurred. The RSO stated the radiographer had extended the source to the collimator and was attempting to retract the source when the source moved a few inches and then could not be moved in any direction. The radiographer contacted the RSO who directed them to secure the area and wait for his arrival.
"The RSO and an assistant arrived at the facility and attempted to retract the source, but could not. The RSO stated the guide tube had a sharp bend near the area of the collimator and believed that could have damaged the guide tube causing the hang-up. The RSO disconnected the guide tube from the exposure device and using a remote handling tool, slid the guide tube down the drive cable. When the end of the drive cable was exposed, the RSO noted the source was not attached. He then shook the source from the guide tube and onto the ground. The source was covered with bags of lead shot.
"The RSO connected the source to the drive cable and was able to retract the source into the exposure device. The exposure device and drive cable connectors were tested using a go-no-go device and both passed. The highest exposure received from the source retrieval was 38 millirem. No overexposures occurred and no member of the general public was exposed due to this event. The RSO stated the guide tube would be returned to the manufacturer for inspection. Additional information will be provided as it is received in accordance with SA-300."
TX Incident: I-9155 |
| Non-Agreement State | Event Number: 49811 | Rep Org: US ARMY 20TH CBRNE COMMAND
Licensee: US ARMY 20TH CBRNE COMMAND
Region: 1
City: ABERDEEN State: MD
County:
License #: 19-31127-01
Agreement: Y
Docket:
NRC Notified By: SCOTT DAVIDSON
HQ OPS Officer: JEFF ROTTON | Notification Date: 02/10/2014
Notification Time: 14:26 [ET]
Event Date: 02/10/2014
Event Time: [EST]
Last Update Date: 02/10/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
| Person (Organization):
ROBERT DALEY (R3DO)
RAY POWELL (R1DO)
FSME EVENTS RESOURCE (EMAI)
NICK TAYLOR (R4DO)
|
| This material event contains a "Less than Cat 3 " level of radioactive material. | Event Text SOURCE LOST DURING SHIPMENT
"A shipment of licensed material was shipped from our CBRNE Analytical and Remediation Activity, CARA, located in Pine Bluff, AR on 3 February 2014 was not received by the consignee, Frontier Technology Corporation, 1641 Burnett Drive, Xenia, OH 45385, [Ohio license # - 03214290000]
"The source, a 1.3 mCi Frontier Model 100 Cf-252 source Serial Number 4151, was shipped in a DOT Spec 7A Type A container. The transportation index on the package was 2.
"This was one of two items shipped from CARA, Pine Bluff, AR [scheduled to arrive on February 10, 2014]. The second source, serial number 4152, was received by Frontier Technology Corporation today along with an unrelated package containing what appeared to be environmental samples in a combination package."
Common Carrier has not claimed that they have lost physical control.
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: 49812 | Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: QUALSPEC, LLC., DBA TC INSPECTION LLC
Region: 4
City: RODEO State: CA
County:
License #: 5299-07
Agreement: Y
Docket:
NRC Notified By: KENT PENDERGAST
HQ OPS Officer: JOHN SHOEMAKER | Notification Date: 02/10/2014
Notification Time: 16:53 [ET]
Event Date: 02/09/2014
Event Time: 00:30 [PST]
Last Update Date: 02/10/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
NICK TAYLOR (R4DO)
FSME EVENT RESOURCES (EMAI)
|
| This material event contains a "Category 2 " level of radioactive material. | Event Text AGREEMENT STATE REPORT - RADIOGRAPHY CAMERA LEFT UNATTENDED
The following Agreement State report was received via email:
"[The California Department of Health, Radiologic Health Branch] RHB Richmond received an incident report from the Qualspect Manager, via an email that a radiography camera had been left unattended. On February 9, 2014, between 0030 and 0245 [PST], Qualspect employees were conducting a radiography operation using [a camera containing an] Ir-192 104 Curie [source], camera s/n 4850, at the Valero Benicia Refinery. During the operation a few Qualspect rope [access] employees were in the area, their presence distracted the two radiographers thinking that another radiographer was in the area, so they left to process film. While the film was being processed, the camera was [left] dangling at 2 feet from the floor and unattended. A Valero Benicia Refinery employee discovered the suspended camera and brought it to the Qualspect employees' attention. Shortly thereafter, the Qualspect employees took possession of the camera."
The California RHB considers this a major event and is conducting an investigation. There were no personnel overexposures.
California Report #021014
Category 2 sources, if not safely managed or securely protected, could cause permanent injury to a person who handled them, or were otherwise in contact with them, for a short time (minutes to hours). It could possibly be fatal to be close to this amount of unshielded radioactive material for a period of hours to days. These sources are typically used in practices such as industrial gamma radiography, high dose rate brachytherapy and medium dose rate brachytherapy. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf |
| Power Reactor | Event Number: 49826 | Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: LINDSAY KOBERLEIN
HQ OPS Officer: DANIEL MILLS | Notification Date: 02/14/2014
Notification Time: 08:12 [ET]
Event Date: 02/14/2014
Event Time: 01:13 [EST]
Last Update Date: 02/14/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
RAY POWELL (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 METEOROLOGICAL TOWER OUT-OF-SERVICE DUE TO WEATHER
"On February 14, 2014 at 0113 EST, all Meteorological Tower data for wind direction was lost for Hope Creek and Salem Units 1 and 2. The loss of wind direction data occurred from environmental conditions during a period of heavy snowfall and ice accumulation. Valid wind direction from Meteorological Tower data input to the Hope Creek Safety Parameter Display System was observed to return at 0246 EST, and was confirmed by visual observation of wind direction onsite.
"The loss of Meteorological Tower data had no effect on plant operations and all units [Hope Creek and Salem Units 1 and 2] remain at 100% power.
"No personnel injuries resulted from the event.
"The NRC Resident Inspector has been notified." |
| Power Reactor | Event Number: 49827 | Facility: SALEM
Region: 1 State: NJ
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: LINDSAY KOBERLEIN
HQ OPS Officer: DANIEL MILLS | Notification Date: 02/14/2014
Notification Time: 08:12 [ET]
Event Date: 02/14/2014
Event Time: 01:13 [EST]
Last Update Date: 02/14/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
RAY POWELL (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 | N | 0 | | 0 | | Event Text METEOROLOGICAL TOWER OUT-OF-SERVICE DUE TO WEATHER
"On February 14, 2014 at 0113 EST, all Meteorological Tower data for wind direction was lost for Hope Creek and Salem Units 1 and 2. The loss of wind direction data occurred from environmental conditions during a period of heavy snowfall and ice accumulation. Valid wind direction from Meteorological Tower data input to the Hope Creek Safety Parameter Display System was observed to return at 0246 EST, and was confirmed by visual observation of wind direction onsite.
"The loss of Meteorological Tower data had no effect on plant operations and all units [Hope Creek and Salem Units 1 and 2] remain at 100% power.
"No personnel injuries resulted from the event.
"The NRC Resident Inspectors has been notified." |
| Power Reactor | Event Number: 49828 | Facility: DAVIS BESSE
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] B&W-R-LP
NRC Notified By: NICK BUEHLER
HQ OPS Officer: DANIEL MILLS | Notification Date: 02/14/2014
Notification Time: 11:14 [ET]
Event Date: 02/14/2014
Event Time: 03:25 [EST]
Last Update Date: 02/14/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
ROBERT DALEY (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Defueled | 0 | Defueled | Event Text SHIELD BUILDING CONSTRUCTION OPENING
"On 02/14/2014, an unfilled area was discovered in the concrete along the top of the shield building construction opening on the annulus side. The condition was discovered during the current steam generator replacement outage, and is likely due to not completely repouring the shield building wall opening in 2011. Analysis shows this condition is bounded by previous calculations that demonstrate the containment function is maintained such that the protection of the health and safety of the public was not in question. Further analysis is planned to reconfirm previous calculations.
"The NRC Resident Inspector has been notified." |
| Power Reactor | Event Number: 49829 | Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: (1) CE
NRC Notified By: CHARLES TACK
HQ OPS Officer: STEVE SANDIN | Notification Date: 02/14/2014
Notification Time: 14:00 [ET]
Event Date: 02/14/2014
Event Time: 08:38 [CST]
Last Update Date: 02/14/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
| Person (Organization):
NICK TAYLOR (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 FITNESS-FOR-DUTY REPORT INVOLVING A NON-LICENSED EMPLOYEE SUPERVISOR
A non-licensed employee supervisor had a confirmed positive for marijuana during a random fitness-for-duty test. The employee's access to the plant has been terminated.
The licensee informed the NRC Resident Inspector. |
| Part 21 | Event Number: 49830 | Rep Org: ENGINE SYSTEMS, INC.
Licensee: ENGINE SYSTEMS, INC.
Region: 1
City: ROCKY MOUNT State: NC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: TOM HORNER
HQ OPS Officer: STEVE SANDIN | Notification Date: 02/14/2014
Notification Time: 16:39 [ET]
Event Date: 02/10/2014
Event Time: [EST]
Last Update Date: 02/14/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
| Person (Organization):
EUGENE GUTHRIE (R2DO)
PART 21 GROUP (EMAI)
| Event Text PART 21 REPORT - FAILED PRESSURE REGULATOR DURING POST-INSTALLATION EDG PRESSURE TESTING
"Component: Starting air pressure regulator (Nordberg P/N 1776 506).
"Summary: Engine Systems Inc. (ESI) began a 10CFR21 evaluation on 12/13/13 upon completion of a failure analysis performed on a pressure regulator part number 1776 506 (S/N 20776487) that was returned by Brunswick Nuclear Plant (BNP) following a failure that occurred during post-installation pressure testing on their emergency diesel generator [EDG] set. The downstream pressure would not maintain its set point and began to equalize to the inlet pressure.
"This evaluation was concluded on 02/10/14 and it was determined that this issue is a reportable defect as defined by 10CFR Part 21. The failure to regulate downstream pressure is attributed to an o-ring within the piston guide assembly of the pressure regulating valve that was improperly installed at the factory. Failure of the o-ring's pressure boundary allows inlet pressure to leak to the outlet pressure side eventually causing equalization to occur. This equalization is undesirable since it could lead to pressures that exceed the capabilities of the engine's downstream air start solenoid valve; thereby potentially preventing the diesel engine from starting during an emergency event and performing its safety related function." |
| Power Reactor | Event Number: 49831 | Facility: SUMMER
Region: 2 State: SC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP,[2] W-AP1000,[3] W-AP1000
NRC Notified By: JAMIE BOLAND
HQ OPS Officer: PETE SNYDER | Notification Date: 02/14/2014
Notification Time: 23:08 [ET]
Event Date: 02/14/2014
Event Time: 22:45 [EST]
Last Update Date: 02/15/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
| Person (Organization):
EUGENE GUTHRIE (R2DO)
JOHN MONNINGER (NRR)
JEFFERY GRANT (IRD)
VICTOR MCCREE (R2)
JENNIFER UHLE (NRR)
|
| 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 NOTICE OF UNUSUAL EVENT DUE TO EARTHQUAKE FELT ONSITE
"An earthquake was felt in the control room at Virgil C. Summer Nuclear Station Unit 1 (VCSNS) at approximately 2223. The earthquake was confirmed with USGS at 2240. An unusual event in accordance with the emergency plan was declared at 2245 and NRC was notified at [2308 EST] via ENS per 10 CFR 50.72(a)(1)(i)."
The plant is stable and continues to operate at 100% power. The licensee has completed preliminary building walkdown inspections with no damage noted. There were no injuries.
The licensee notified the NRC Resident Inspector.
* * * UPDATE FROM BETH DALICK TO JOHN SHOEMAKER AT 1108 EST ON 2/15/14 * * *
"[V.C. Summer Nuclear Station] VCSNS has terminated the [Unusual] Event after walkdowns of the plant were satisfactorily completed and no aftershocks were felt. An update to ENS has also been made. The event was terminated at 1045 [EST] on 2/15/2014.
The plant continues to operate at 100% power and the licensee has notified the NRC Resident Inspector.
Notified R2RA (McCree), R2DO (Guthrie), NRR EO (Monninger), NRR (Uhle), IRD (Grant), DHS SWO, FEMA Ops, DHS NICC, and NuclearSSA via email. |
| Power Reactor | Event Number: 49832 | Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [ ] [2] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: CARL JONES
HQ OPS Officer: STEVE SANDIN | Notification Date: 02/16/2014
Notification Time: 18:21 [ET]
Event Date: 02/16/2014
Event Time: 12:16 [EST]
Last Update Date: 02/17/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
RAY POWELL (R1DO)
JOHN MONNINGER (NRR)
JIM WHITNEY (ILTA)
|
| 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 UNIT 2 EXPERIENCED A PARTIAL LOSS OF OFFSITE POWER WITH AUTOSTART OF DIVISION I AND III EDGS
"An automatic initiation of Emergency Diesel Generators was received due to a loss of one of two off-site power sources.
"On February 16, 2014 at 1216 [EST], Nine Mile Point Unit 2 experienced an automatic initiation of the Division 1 and 3 Emergency Diesel Generators [EDGs] due to a loss of Line 5. Line 5 is one of the two 115KV offsite power sources.
"Line 5 was lost due to an offsite event that is currently being evaluated by the grid operator.
"During the electrical transient, Nine Mile Point Unit 2 also experienced a feedwater level control lockup, requiring manual control. No Emergency Core Cooling Systems actuated, and feedwater level control was returned to automatic. Nine Mile Point Unit 2 remained at 100% power during the loss of Line 5, one of the offsite power sources.
"The NRC resident has been notified."
The licensee also notified the State of New York.
Unit 2 is currently in a 24-hour Technical Specification Limiting Condition of Operation [TS LCO] Action Statement 3.8.1.A3. Once Division III is realigned to the "B" side Line 6 offsite power, Unit 2 will be in a 72-hour LCO. Both EDGs are currently running. There was no effect on Unit 1.
* * * UPDATE PROVIDED BY MARK GREER TO JEFF ROTTON AT 1727 EST ON 2/17/2014 * * *
"In addition to the initiation of Division 1 and 3 Emergency Diesel Generators, Service Water Radiation Monitor 2SWP*RE146A and Radwaste/Reactor Building Vent Gaseous Effluent Monitoring Systems were also lost. Compensatory actions were established as required by station procedures and the Offsite Dose Calculation Manual. The loss of these instruments is reportable as a major loss of Emergency Assessment Capability per 10CFR50.72(b)(3)(xiii). The Service Water Radiation Monitor 2SWP*RE146A was restored to service on February 16, 2014 at 1450 EST. The Radwaste/Reactor Building Vent Gaseous Effluent Monitoring Systems were restored to service on February 17, 2014 at 0240. It is recognized that this notification is not within eight hours of the event.
"Line 5 is restored to OPERABLE February 17, 2014 at 1628.
"The NRC Resident Inspector has been informed of this additional reportable condition [and the update on the lost off-site power source]. The condition has been entered into the corrective action program."
The licensee also notified the State of New York Public Service Commission. The licensee exited the 72-hour LCO for the lost off-site power at 1628 on February 17, 2014.
Notified R1DO(Krohn), NRREO (Monninger) and ILTAB (Whitney). |
| Power Reactor | Event Number: 49833 | Facility: DAVIS BESSE
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] B&W-R-LP
NRC Notified By: ERIC HORVATH
HQ OPS Officer: PETE SNYDER | Notification Date: 02/16/2014
Notification Time: 21:37 [ET]
Event Date: 02/16/2014
Event Time: 17:25 [EST]
Last Update Date: 02/16/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xii) - OFFSITE MEDICAL
| Person (Organization):
ROBERT DALEY (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Defueled | 0 | Defueled | Event Text CONTRACT WORKER TRANSPORTED TO HOSPITAL AFTER FALL
"At time 1725 [EST] on 02/16/2014 a contract worker fell ten to fifteen (10-15) feet off of a ladder while descending the ladder above the 565 foot level in the Containment Building. The individual received lacerations to the forehead and potential other injuries.
"For his work activities the individual was dressed in anti-contamination clothing.
"The individual was transported via off-site ambulance in his anti-contamination clothing to H.B. Magruder hospital in Port Clinton, Ohio. A First Energy (FENOC) Radiation Protection (RP) Technician accompanied the injured person in the ambulance during the transfer to the hospital. A FENOC RP Supervisor along with the RP Technician assisted at the hospital while the injured individual received medical treatment. The protective anti-contamination clothing was removed from the individual. A full body frisk was performed and showed no contamination on the individual.
"Smear readings on the anti-contamination booties and gloves showed [approximately] 1500 dpm / 100 square cm. The clothing was bagged and subsequent readings and surveys on the outside of the bag showed no readings above background. The bagged anti-contamination clothing will be transported back to Davis-Besse NPS by FENOC RP Supervision. The H.B. Magruder Hospital Treatment Room and the off-site ambulance also were frisked and showed no residual contamination."
The licensee notified the State of Ohio and Lucas and Ottawa Counties. The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 49834 | Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: QUOC VO
HQ OPS Officer: CHARLES TEAL | Notification Date: 02/17/2014
Notification Time: 10:42 [ET]
Event Date: 02/17/2014
Event Time: 00:44 [PST]
Last Update Date: 02/17/2014 | 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
| Person (Organization):
NICK TAYLOR (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 LOSS OF SECONDARY CONTAINMENT DIFFERENTIAL PRESSURE
"Reactor Building (Secondary Containment) pressure rose above the Technical Specification Surveillance requirement of 0.25 inches vacuum water gauge multiple times from 0044 [PST] to 0305 [PST] on 2/17/14. The alarm was received in the control room at 0305 [PST]. 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 of vacuum water gauge), returning Secondary Containment to operable status. Highest actual value indicated was +0.21 inches pressure water gauge. The cause of the event is under investigation.
"There were no radiological releases associated with the event.
"The NRC Resident Inspector has been notified." | |