| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
01/31/2014 - 02/03/2014 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 49760 | Rep Org: PA BUREAU OF RADIATION PROTECTION
Licensee: UNIVERSITY OF PENNSYLVANIA MEDICAL CENTER - HORIZON
Region: 1
City: GREENVILLE State: PA
County:
License #: PA-0057
Agreement: Y
Docket:
NRC Notified By: JOSEPH MELNIC
HQ OPS Officer: HOWIE CROUCH | Notification Date: 01/23/2014
Notification Time: 13:24 [ET]
Event Date: 11/22/2013
Event Time: [EST]
Last Update Date: 01/23/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
ANTHONY DIMITRIADIS (R1DO)
FSME EVENTS RESOURCE (EMAI)
| Event Text PENNSYLVANIA AGREEMENT STATE REPORT - LOST THEN FOUND BRACHYTHERAPY SEEDS
The following information was obtained from the Commonwealth of Pennsylvania via facsimile:
"Notifications: On November 22, 2013, the DEP [Pennsylvania Department of Environmental Protection] Southwest Regional Office was notified that some palladium-103 (Pd-103) brachytherapy seeds were inadvertently disposed but then recovered by the licensee. On January 22, 2014, the Department was provided the actual activity amount and made the determination that this event qualifies as a reportable event under 10 CFR 20.2201(a)(1)(i).
"Event Description: On November 20, 2013, a box containing Pd-103 brachytherapy seeds was delivered to the Nuclear Medicine Department. On November 22, 2013, the Medical Physicist, prior to the implant procedure, noticed that all the seeds were not present. It was later acknowledged that all 90 seeds equaling 170 mCi of Pd-103 were inadvertently disposed.
"Cause of the Event: Human error. The seeds were not removed from the shipping box prior to the box being disposed of.
"Actions: On November 22, 2013, the Medical Physicist retrieved the missing box containing all the seeds. No exposure to anyone is expected while the seeds were missing. The regional office will further determine, with the licensee, the root cause of this event and the corrective actions to prevent this from reoccurring.
"Media attention: None at this time."
Event Report ID No: PA140001 |
| Agreement State | Event Number: 49761 | Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: POLAR CORPORATION
Region: 1
City: WORCESTER State: MA
County:
License #: G0118
Agreement: Y
Docket:
NRC Notified By: JOSH DAEHLER
HQ OPS Officer: HOWIE CROUCH | Notification Date: 01/23/2014
Notification Time: 16:21 [ET]
Event Date: 01/23/2014
Event Time: [EST]
Last Update Date: 01/23/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
HAROLD GRAY (R1DO)
FSME EVENTS RESOURCE (EMAI)
|
| This material event contains a "Less than Cat 3 " level of radioactive material. | Event Text MASSACHUSETTS AGREEMENT STATE REPORT - MISSING DEVICE CONTAINING AMERICIUM - 241
The following information was obtained from the Commonwealth of Massachusetts via email:
"Immediate report in accordance with 105 CMR 120.281(A)(1) of missing device containing a 100 millicurie americium-241sealed source.
"After [a] billing inquiry by Massachusetts Radiation Control Program [the Program] [to] the licensee about generally licensed devices registered with [the] Program, the licensee reported on January 23, 2014 that one Industrial Dynamics Co., LTD Model FT-12 device [a fill level gauge], S/N 102282, containing a 100 millicurie americium-241 sealed source, cannot be located or is missing.
"The licensee informed the Program that the device is obsolete and has been out of service for about 15 years and may have been returned to manufacturer or might be in storage at licensee's facilities. The licensee informed [the] Program that it is making the effort of contacting a person that may have known about the device and is conducting a search of it's storage facilities.
"The Program notified the licensee of it's responsibility for providing [a] written report in accordance with the requirements of 105 CMR 120.281(B).
"Root cause and corrective actions are not known at this time and the Program intends to make site visit.
"This event remains open."
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: 49762 | Rep Org: PA BUREAU OF RADIATION PROTECTION
Licensee: THOMAS JEFFERSON UNIVERSITY HOSPITALS
Region: 1
City: PHILADELPHIA State: PA
County:
License #: PA-0130
Agreement: Y
Docket:
NRC Notified By: JOSEPH MELNIC
HQ OPS Officer: NESTOR MAKRIS | Notification Date: 01/24/2014
Notification Time: 10:56 [ET]
Event Date: 01/22/2014
Event Time: [EST]
Last Update Date: 01/24/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
HAROLD GRAY (R1DO)
FSME EVENTS RESOURCE (EMAI)
| Event Text PENNSYLVANIA AGREEMENT STATE REPORT - MEDICAL UNDERDOSE
The following was received via fax from the Commonwealth of Pennsylvania:
"Notifications: Licensee reported this event to the Department's [Pennsylvania Department of Environmental Protection] Southeast Regional Office on January 23, 2014. This is an immediate reporting event under 35.3045(a)(1)(i).
"Event Description: On January 22, 2014, the licensee experienced a medical event in which 76% of a yttrium-90 (Y -90) TheraSphere liver cancer therapy dose was delivered to the patient. Both the patient and referring physician were notified of the under dose.
"Cause of the Event: Occlusion. The remaining activity appeared to have precipitated out and remained in the catheter.
"Actions: Awaiting the required 15 day written report from the licensee. The Department will provide updated information as received.
"Media attention: None at this time."
Event number: PA140005
A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient. |
| Agreement State | Event Number: 49764 | Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: BOSTON UNIVERSITY MEDICAL CENTER
Region: 1
City: BOSTON State: MA
County:
License #: 44-0062
Agreement: Y
Docket:
NRC Notified By: BRUCE PACKARD
HQ OPS Officer: HOWIE CROUCH | Notification Date: 01/24/2014
Notification Time: 17:24 [ET]
Event Date: 01/24/2014
Event Time: 15:00 [EST]
Last Update Date: 01/24/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
HAROLD GRAY (R1DO)
FSME EVENTS RESOURCE (EMAI)
| Event Text MASSACHUSETTS AGREEMENT STATE REPORT - MISADMINISTRATION OF I-131
The following information was obtained from the Commonwealth of Massachusetts via facsimile:
"30 mCi of I-131 (NaI) was administered to the wrong patient. Blocking agent has been prescribed by doctor. Patient is described as in their 70s. Doctor and patient have been informed. 15 day report will follow."
A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient. |
| Power Reactor | Event Number: 49776 | Facility: LASALLE
Region: 3 State: IL
Unit: [1] [2] [ ]
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: JASON DEPRIEST
HQ OPS Officer: DANIEL MILLS | Notification Date: 01/29/2014
Notification Time: 18:33 [ET]
Event Date: 01/29/2014
Event Time: 09:53 [CST]
Last Update Date: 01/31/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
STUART SHELDON (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 97 | Power Operation | 97 | Power Operation | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text LOSS OF TECHNICAL SUPPORT CENTER VENTILATION FAN
"This telephone notification is provided in accordance with Exelon Reportability manual SAF 1.10, 'Major Loss of Emergency Preparedness Capabilities', and 10 CFR 50.72(b)(3)(xiii).
"On January 29th at 09:53 CST, it was determined that the onsite Technical Support Center (TSC) Ventilation System Supply Fan had failed (due to failed fan belts as a result of degraded alignment), resulting in loss of ventilation for the TSC. Repairs have been initiated, however repairs will not have been completed within the time required to staff the TSC. There is currently no emergency event in progress requiring TSC staffing. The Main Control Room remains available as an Emergency Response Facility (ERF), should an event occur requiring Emergency Response Facilities to be staffed.
"The licensee has notified the Senior Resident Inspector of the issue."
* * * UPDATE FROM MARK SMITH TO VINCE KLCO AT 0217 EST ON 1/31/2014 * * *
"After repairs were completed, the TSC Ventilation was restored to service at [2350 CST on 01/30/2014].
"The licensee has notified the NRC Resident Inspector."
Notified the R3DO (Sheldon). |
| Power Reactor | Event Number: 49778 | Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [1] [2] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: GENE DAMMAN
HQ OPS Officer: HOWIE CROUCH | Notification Date: 01/30/2014
Notification Time: 19:03 [ET]
Event Date: 01/30/2014
Event Time: 13:20 [CST]
Last Update Date: 01/31/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
STUART SHELDON (R3DO)
|
| 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 OFFSITE NOTIFICATION DUE TO INADVERTENT ACTIVATION OF ONE EMERGENCY SIREN
"One siren false actuation. At approximately 1415 CST on January 30, 2014, the licensee was notified of a false activation of emergency siren (G-14). The site contacted the siren vendor. It was determined that the siren had falsely actuated 5 to 6 times and has since been deactivated. The Goodhue County Sheriff's department received calls from some area residents. The siren remains out of service and is the only siren out of service within the 10 mile Emergency Planning Zone (EPZ). NRC Resident Inspector has been informed.''
* * * UPDATE FROM MARK LOOSBROCK TO HOWIE CROUCH AT 1743 EST ON 1/31/14 * * *
"Based upon further review, the event time of the false siren actuation was approximately 1320 CST. The previously reported event time of 1415 CST was the confirmation time of the siren vendor responding to the siren actuation. This does not represent a significant loss in emergency notification. The siren system has significant overlap between sirens. For any failed siren, backup methods are implemented per our emergency plan to ensure timely public notification."
The licensee notified the NRC Resident Inspector of this update. Notified R3DO (Sheldon). |
| Power Reactor | Event Number: 49779 | Facility: MILLSTONE
Region: 1 State: CT
Unit: [ ] [2] [ ]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: FRED PERKINS
HQ OPS Officer: VINCE KLCO | Notification Date: 01/31/2014
Notification Time: 04:09 [ET]
Event Date: 01/31/2014
Event Time: 03:30 [EST]
Last Update Date: 01/31/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
| Person (Organization):
ART BURRITT (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 100 | Power Operation | 31 | Power Operation | Event Text TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO DEGRADATION OF THE PRESSURIZER PROPORTIONAL HEATERS GROUP 1
Operators commenced a Technical Specification required shutdown due a 480 volt supply breaker trip resulting in degradation of the Pressurizer Proportional Heaters Group 1. The licensee plans on making a containment entry to investigate the cause of the breaker trip.
The B-Emergency Diesel-Generator is currently inoperable for planned maintenance. Unit 2 is currently ramping down and proceeding to a shutdown. The plant is in a normal electrical configuration. There is no indication of any primary to secondary leakage. Unit 3 is unaffected.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 49780 | Facility: SALEM
Region: 1 State: NJ
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ERIC POWELL
HQ OPS Officer: VINCE KLCO | Notification Date: 01/31/2014
Notification Time: 11:44 [ET]
Event Date: 01/31/2014
Event Time: 10:01 [EST]
Last Update Date: 01/31/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
ART BURRITT (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | M/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text MANUAL REACTOR TRIP
"This 4-hour notification is being made to report that Salem Unit 2 has performed an unplanned manual reactor trip. The trip was initiated due to reactor coolant temperature approaching the minimum temperature for criticality, 543 degree F, due to boration to achieve shutdown margin requirements following identification of a misaligned control rod.
"All control rods inserted on the reactor trip. All ECCS [Emergency Core Cooling System] and ESF [Engineered Safety Features] systems functioned as expected with no equipment actuated. The 21 safety injection pump was out of service for scheduled maintenance during the event as was the 2R41 plant vent radiation monitor.
"Salem Unit 2 is currently in Mode 3. Reactor coolant system pressure is at 2235 psig and temperature is 547 degrees F with decay heat removal via the main steam dump and auxiliary feedwater systems. Unit 2 has no active shutdown technical specification action statements in effect.
"There was no major secondary equipment tagged for maintenance prior to the event."
Prior to the event, the licensee was conducting their monthly control rod surveillance. No primary or secondary relief valves lifted during the transient. The electrical grid is stable and the plant is in its normal shutdown electrical lineup. There was no effect on Unit 1.
The licensee notified the NRC Resident Inspector, the State of New Jersey, the State of Delaware and the Lower Alloways Creek Township. |
| Part 21 | Event Number: 49781 | Rep Org: WESTINGHOUSE ELECTRIC COMPANY
Licensee: WESTINGHOUSE ELECTRIC COMPANY
Region: 1
City: CRANBERRY TOWNSHIP State: PA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: JAMES GRESHAM
HQ OPS Officer: DANIEL MILLS | Notification Date: 01/31/2014
Notification Time: 13:39 [ET]
Event Date: 01/31/2014
Event Time: [EST]
Last Update Date: 01/31/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(a)(2) - INTERIM EVAL OF DEVIATION
50.55(e) - CONSTRUCT DEFICIENCY
| Person (Organization):
GERALD MCCOY (R2DO)
PART 21 GROUP (EMAI)
ART BURRITT (R1DO)
| Event Text PART 21/50.55 - AP1000 UPDATED REACTOR COOLANT PUMP LOCKED ROTOR ANALYSIS
The following was received via facsimile:
"The purpose of this letter is to provide the Commission with the prescribed interim report as required per 10 CFR 21.21(a)(2) of a deviation identified by Westinghouse Electric Company LLC. This also will serve as an interim report under 10 CFR 50.55 (3)(ii) to the extent applicable.
"A postulated reactor coolant pump (RCP) locked rotor (LR) transient has been explicitly analyzed for the AP1000 steam generator (SG) structural design, as documented in the latest AP1000 Design Control Document (DCD), Revision 19. This includes the calculation of LR hydrodynamic forces (HF) on the SG using the BANG UP code. This activity was performed based upon the unique features of the AP1000 design. However, the other AP1000 reactor coolant system (RCS) structural component analyses have not considered the locked rotor transient for hydrodynamic forces, even though a determination has been made that the effects of these loads could be more bounding than the limiting design-basis loss of coolant accident (LOCA) hydrodynamic forces (based on the BANG UP calculation of pressure pulsations through the RCS).
"Westinghouse has not yet completed its evaluation as to whether there is a reportable condition as defined in 10 CFR 21 (or 10 CFR 50.55 to the extent applicable) if the deviation is left uncorrected.
"Westinghouse expects to complete this evaluation by September 30, 2014. We will inform the staff if there are any changes to this schedule, prior to that date." |
| Power Reactor | Event Number: 49783 | Facility: MILLSTONE
Region: 1 State: CT
Unit: [ ] [ ] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: EDWIN MICHAEL SOCHA
HQ OPS Officer: DANIEL MILLS | Notification Date: 02/01/2014
Notification Time: 14:12 [ET]
Event Date: 02/01/2014
Event Time: 10:00 [EST]
Last Update Date: 02/01/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
ART BURRITT (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text CONTROL ROOM DOOR BLOCKED OPEN FOR PLANNED MAINTENANCE
"Door in Control Room boundary blocked open for scheduled maintenance. No impact as door is opened under administrative control OP3314F, Section 4.24. Door has been closed following maintenance.
"Door opened under administrative control could have prevented the fulfillment of Safety Function to Mitigate the Consequences of an Accident.
"A door credited for Control Room Boundary was blocked open under administrative controls as part of a Pre-Planned maintenance activity. Technical Specification 3.7.7, Control Room Emergency Ventilation System, is applicable and allows 'The Control Room Envelope (RE) boundary may be opened under administrative control'
"NUREG 1022, Revision 3, states inoperability of a single train system is reportable even though the plant's Technical Specifications may allow the condition to exist for a limited time. Although the plant was operated within the licensing basis, since the Control Room Envelope was rendered inoperable, Dominion is reporting that this condition could have prevented the fulfillment of the safety function to mitigate the consequences of an accident."
The licensee has notified the NRC Resident Inspector, State government, and Local government. |
| Power Reactor | Event Number: 49784 | Facility: NORTH ANNA
Region: 2 State: VA
Unit: [ ] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP,[3] M-4-LP
NRC Notified By: PAGE KEMP
HQ OPS Officer: VINCE KLCO | Notification Date: 02/02/2014
Notification Time: 11:01 [ET]
Event Date: 02/02/2014
Event Time: 08:59 [EST]
Last Update Date: 02/02/2014 | 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
| Person (Organization):
GERALD MCCOY (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | M/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text MANUAL REACTOR TRIP FOLLOWING LOSS OF THE "A" MAIN FEEDWATER PUMP
"On 2-2-2014 at 0859 [EST], with Unit 2 operating at 100% power, a manual reactor trip was initiated by the control room staff following a trip of the 'A' main feedwater pump and automatic start of the 'C' feedwater pump due to crew concerns that both motors of the 'C' feedwater pump had not actuated. When the 'C' feedwater pump auto started, the running indicator light for one of the 'C' feedwater pump motors failed to illuminate. Both motors of the 'C' feedwater pump had started as designed. Following the reactor trip, all control rods fully inserted into the core and Unit 2 was stabilized in Mode 3 at normal reactor coolant system temperature and pressure. Decay heat is being removed using the normal condenser steam dump system. Unit 2 is in a normal shutdown electrical alignment with power being supplied from the Reserve Station Service Transformers. This event is reportable per 10CFR50.72(b)(2)(iv)(B) for actuation of the reactor protection system.
"Following the reactor trip, the auxiliary feedwater pumps automatically started as designed and provided makeup flow to the steam generators. The steam generator levels were returned to normal operating level and the auxiliary feedwater pumps were returned to the normal standby automatic alignment. This event is reportable per 10CFR50.72(b)(3)(iv)(A) for actuation of an ESF system.
"Unit 1 is operating at 100% power and was not affected by the event."
The licensee informed the NRC Resident Inspector and will inform the Louisa County Administrator. |
| Fuel Cycle Facility | Event Number: 49785 | Facility: HONEYWELL INTERNATIONAL, INC.
RX Type: URANIUM HEXAFLUORIDE PRODUCTION
Comments: UF6 CONVERSION (DRY PROCESS)
Region: 2
City: METROPOLIS State: IL
County: MASSAC
License #: SUB-526
Agreement: Y
Docket: 04003392
NRC Notified By: MICHAEL ABEL
HQ OPS Officer: STEVE SANDIN | Notification Date: 02/02/2014
Notification Time: 11:21 [ET]
Event Date: 02/01/2014
Event Time: 21:30 [CST]
Last Update Date: 02/02/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
40.60(b)(3) - MED TREAT INVOLVING CONTAM
| Person (Organization):
GERALD MCCOY (R2DO)
BRIAN SMITH (NMSS)
| Event Text CONTAMINATED PLANT EMPLOYEE RECEIVED MEDICAL TREATMENT INSIDE THE RESTRICTED AREA
"An employee with a laceration to his ear reported to the on-site dispensary yesterday evening. The plant nurse administered first aid. A whole body survey of the employee in his plant clothing was performed; the maximum amount of contamination was present on the employee's boots, 2,136 dpm/100cm2. The plant nurse allowed the employee to return to work. The employee remained inside the Restricted Area over the course of the event."
The source of the contamination is Uranium Ore Concentrates inside the process building. The licensee will request a bioassay when the employee returns to the site.
The licensee informed R2 (Hartland) via email. |
| Power Reactor | Event Number: 49786 | Facility: DIABLO CANYON
Region: 4 State: CA
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BOB KLINE
HQ OPS Officer: DANIEL MILLS | Notification Date: 02/02/2014
Notification Time: 18:16 [ET]
Event Date: 02/02/2014
Event Time: 11:29 [PST]
Last Update Date: 02/02/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
NEIL OKEEFE (R4DO)
|
| 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 | Event Text UNIT 2 AUTOMATIC REACTOR TRIP
"On February 2, 2014, at 11:29 PST, Diablo Canyon Power Plant Unit 2 500kV line differential relay actuated. This action tripped the turbine and opened the generator output breakers to isolate the generator. With the turbine tripped and Unit 2 operating above the P-9 50% power permissive, a reactor trip was initiated from the reactor protection system. All systems operated as designed with no problems observed. All three Unit 2 Auxiliary Feedwater pumps started, the Containment Fan Cooling units started and ran in slow speed, and the standby Auxiliary Saltwater train started, all as expected.
"Unit 2 is stable at normal operating temperature and pressure. All power transferred to the plant startup source without incident. Condenser vacuum was maintained.
"The preliminary cause of the differential relay actuation was a flashover of Phase B 500 kV to ground across the Phase B lightning arrestor during a rainstorm.
"Decay heat is being removed by steam dumps to the condenser. No relief valves lifted during the transient. The steam generators are being supplied by the auxiliary feedwater pumps. There were no injuries to personnel. Unit 1 was not affected.
"NRC Senior Resident Inspector and Region Branch Chief have been informed of this event.
"A press release is planned for local media." |
| Power Reactor | Event Number: 49787 | Facility: DRESDEN
Region: 3 State: IL
Unit: [ ] [2] [3]
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: STEVEN MELL
HQ OPS Officer: JEFF ROTTON | Notification Date: 02/03/2014
Notification Time: 02:41 [ET]
Event Date: 02/03/2014
Event Time: 00:43 [CST]
Last Update Date: 02/03/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
STUART SHELDON (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text TECHNICAL SUPPORT CENTER EMERGENCY VENTILATION SYSTEM OUT OF SERVICE FOR PLANNED MAINTENANCE
"At 0043 [CST] on Monday, February 3, 2014, the Dresden Nuclear Power Station (DNPS) Technical Support Center (TSC) emergency ventilation system was removed from service for planned preventative maintenance activities on the TSC ventilation system condensing unit. The TSC air handing and filtration units will be non-functional, rendering the TSC HVAC accident mode non-functional. This maintenance is scheduled to minimize out of service time. The planned TSC ventilation outage is scheduled to be completed within 88 hours. If an emergency is declared requiring TSC activation during this period, the TSC will be staffed and activated using existing Emergency Preparedness (EP) procedures and checklists. If radiological conditions require TSC facility evacuation during ventilation system maintenance; the Station Emergency Director will evacuate and relocate the TSC staff in accordance with established procedures.
"The licensee notified the NRC Resident Inspector." | |