Semantic search

Jump to navigation Jump to search
Condition
Printout selection
Options
Parameters [
limit:

The maximum number of results to return
offset:

The offset of the first result
link:

Show values as links
headers:

Display the headers/property names
mainlabel:

The label to give to the main page name
intro:

The text to display before the query results, if there are any
outro:

The text to display after the query results, if there are any
searchlabel:

Text for continuing the search
default:

The text to display if there are no query results
class:

An additional CSS class to set for the table
transpose:

Display table headers vertically and results horizontally
sep:

The separator between results
prefix:

Control display of namespace in printouts
Sort options
Delete
Add sorting condition
 Issue dateTitleTopic
05000280/LER-2016-00111 July 20161 OF 4
LER 16-001-00 for Surry Power Station, Unit 1 and 2, Regarding Emergency Service Water Pump Inoperable Due to Corrosion of Valve Support
05000280/LER-2017-0016 October 20171 OF 3
LER 17-001-00 for Surry, Unit 1, Regarding Shutdown due to an Unisolable Leak in Reactor Coolant Pressure Boundary
High Radiation Area
Pressure Boundary Leakage
Pressure boundary leak
05000280/LER-2019-0024 February 2020LER 2019-002-00 for Surry Power Station Unit 1, Items Non-Conforming to Design for Tornado Missile ProtectionSafe Shutdown
Unanalyzed Condition
Tornado Missile
Enforcement Discretion
Tornado Generated Missile
Tornado Missile Protection
05000281/LER-2016-0012 December 2016Unit 2 Reactor Trip due to Generator Differential Lockout
LER 16-001-00 for Surry Power Station, Unit 2, Regarding Reactor Trip Due to Generator Differential Lockout
Reserve Station Service Transformer
05000281/LER-2020-001, Cancellation of LER 2020-001-00 for Surry Power Station Unit 2 Re Loss of Containment Cooling Affecting Containment Partial Pressure Indication6 November 2020Cancellation of LER 2020-001-00 for Surry Power Station Unit 2 Re Loss of Containment Cooling Affecting Containment Partial Pressure Indication
05000336/LER-2015-0037 January 2016Valid Actuation of the Reactor Protection System
LER 15-003-00 for Millstone, Unit 2, Regarding Valid Actuation of the Reactor Protection System
Downpower
05000336/LER-2016-00127 June 2016Turbine Driven Auxiliary Feedwater Putnp Room HELB Door Left Open
LER 16-001-00 for Millstone Power Station Unit 2 RE: Turbine Driven Auxiliary Feedwater Pump Room HELB Door Left Open
05000336/LER-2016-00220 September 2016Manual Reactor Trip Due to Loss of Two Circulating Water Pumps
LER 16-002-00 for Millstone Power Station Unit 2 Regarding Manual Reactor Trip Due Loss Of Two Circulating Water Pumps
05000338/LER-2016-00116 March 20161 OF 3
LER 16-001-00 for North Anna, Units 1 and 2, Regarding Emergency Diesel Generators Automatic Start Due to Loss of Power to "C" Reserve Station Service Transformer
Reserve Station Service Transformer
05000338/LER-2016-0025 May 2016, Chemical Addition System Outside of Technical Specification Due to Excessive Unseating Thrust on MOVs
LER 16-002-00 for North Anna, Unit 1, Regarding Chemical Addition System Outside of Technical Specification Due to Excessive Unseating Thrust on MOVs
05000338/LER-2016-00316 June 20161 OF 3
LER 16-003-00 for North Anna, Unit 1, Regarding Engineered Safety Feature Actuation Due to Loss of Power to "A" Reserve Station Service Transformer
Reserve Station Service Transformer
05000339/LER-2016-00121 September 2016Technical Specification Required Shutdown Due to Reactor Coolant System Leak
LER 16-001-00 for North Anna Power Station, Unit 2 Regarding Technical Specification Required Shutdown Due to Reactor Coolant System Leak
Pressure Boundary Leakage
Through Wall Leak
05000423/LER-2016-00116 March 2016Automatic Reactor Trip on Reactor Coolant System Low Flow Due to Loss of 'B' Reactor Coolant Pump
LER 16-001-00 for Millstone Power Station Unit 3, Regarding Automatic Reactor Trip on Reactor Coolant System Low Flow Due to Loss of 'B' Reactor Coolant Pump
Coast down
05000423/LER-2016-00223 March 2016Feedwater Isolation Signal Defeated Due to Wiring Error
LER 16-002-00 for Millstone Power Station Unit 3 Regarding Feedwater Isolation Signal Defeated Due to Wiring Error
05000423/LER-2016-0038 June 2016Loss of Safety Function- Supplementary Leak Collection and Release System
LER 16-003-00 for Millstone Power Station, Unit 3, Regarding Loss of Safety Function-Supplementary Leak Collection and Release System
05000423/LER-2016-00413 July 2016Manual Reactor Trip Due to Low Hydrogen Gas Pressure In Main Generator
LER 16-004-00 for Millstone Power Station Unit 3 RE: Manual Reactor Trip Due to Low Hydrogen Gas Pressure In Main Generator
05000423/LER-2016-0059 August 2016Technical Specification Required Shutdown and Manual Reactor Trip Due to Steam Generator Level Oscillation
LER 16-005-00 for Millstone Power Station Unit 3 RE: Technical Specification Required Shutdown and Manual Reactor Trip Due to Steam Generator Level Oscillation
Pressure Boundary Leakage
Power change
05000423/LER-2017-00120 March 2017Loss of Safety Function - Secondary Containment
LER 17-001-00 for Millstone, Unit 3 Regarding Loss of Safety Function - Secondary Containment
05000423/LER-2019-00113 February 2020LER 2019-001-00 for Millstone Power Station Unit 3 Regarding Plant Shutdown Required by Technical Specifications, Emergency Diesel Generator Exceeded Allowed Outage Time
CY-04-011, Withdrawal as Pilot Plant for Implementation of 10 CFR 50.6912 June 2006Withdrawal as Pilot Plant for Implementation of 10 CFR 50.69Probabilistic Risk Assessment
CY-92-223, G20110523/LTR-11-0411/EDATS: SECY-2011-0411 - Ltr. from Rep. E.J. Markey to Chairman Jaczko NRC Safety Requirements for Reactors Granted Construction Permits Prior to 197114 July 2011G20110523/LTR-11-0411/EDATS: SECY-2011-0411 - Ltr. from Rep. E.J. Markey to Chairman Jaczko NRC Safety Requirements for Reactors Granted Construction Permits Prior to 1971Fukushima Dai-Ichi
Significance Determination Process
Earthquake
Backfit
IR 05000028/201941331 October 2019Security Insp Report 5000280/ 2019413 and 500028/2019413
IR 05000039/20180018 May 2018NRC Integrated Inspection Report 05000338/3018001 and 0500039/2018001Boric Acid
High winds
Fire Barrier
Enforcement Discretion
Reserve Station Service Transformer
Nondestructive Examination
Functionality Assessment
Significance Determination Process
Operability Determination
Earthquake
Liquid penetrant
Fire Protection Program
Power change
IR 05000245/20020134 March 2003IR 05000245-02-013, on 07/06/02 - 01/28/03 for Dominion Nuclear Connecticut, Inc., Millstone Power Station Unit 1, Waterford, ConnecticutHigh Radiation Area
Fire Watch
IR 05000245/200300711 September 2003IR 05000245-03-007, on 01/29/2003 - 07/27/2003, Millstone Power Station Unit 1. This Integrated Inspection Included Aspects of Licensee Operations and Plant Support During Decommissioning ActivitiesAnnual Radioactive Effluent Release Report
Fire Protection Program
IR 05000245/200301123 January 2004IR 05000245-03-011, Dominion Nuclear Connecticut, Inc., Millstone Power Station Unit 1, Waterford, ConnecticutHigh Radiation Area
Locked High Radiation Area
Foreign Material Exclusion
IR 05000245/20040119 July 2004IR 05000245-04-011, Dominion Nuclear Connecticut, Inc., Millstone Power Station Unit 1, Waterford, ConnecticutHigh Radiation Area
Locked High Radiation Area
Exclusive Use
IR 05000245/200501319 August 2005IR 05000245-05-013, on 06/27-29/2005, Dominion Nuclear Connecticut, Inc., Millstone Power Station Unit 1, Waterford, ConnecticutHigh Radiation Area
Locked High Radiation Area
IR 05000245/20060096 April 2006IR 05000245-06-009, on March 13-15, 2006, Dominion Nuclear Connecticut, Millstone Power Station Unit 1, Waterford, Connecticut
IR 05000245/200700616 April 2007IR 05000245-07-006, on 03/19/21-2007, Dominion Nuclear Connecticut, Millstone Power Station Unit 1, Waterford, Connecticut
IR 05000245/200800929 May 2008IR 05000245-08-009, on 03/03/2008 - 04/30/2008, Millstone, Unit 1, PLC Alarm ResponseFire Watch
IR 05000245/20090077 April 2009IR 05000245-09-007, on 03/11/09, Dominion Nuclear Connecticut, Inc., Millstone Power Station Unit 1, Waterford, CT
IR 05000245/201100523 January 2012IR 05000336/2011005 and 05000423/2011005, Millstone Power Station NRC Integrated Inspection Report
IR 05000245/201100913 May 2011IR 05000245/2011009, 05000336/2011009, and 05000423/2011009; 04/01/2011 - 04/29/2011; Millstone Power Station, Units 1, 2 and 3; Temporary Instruction 2515/183 - Followup to the Fukushima Daiichi Nuclear Station Fuel Damage EventB.5.b
Seismically rugged
Design basis earthquake
Severe Accident Management Guideline
IR 05000245/201140617 February 2012Millstone Power Station-NRC Material Control and Accounting Program Inspection Report No. 05000336-11-406 and 05000423-11-406Affidavit
IR 05000245/201200223 April 2012IR 05000336-12-002, 05000423-12-002, on 1/1/12-3/31/12, Millstone Units 2 and 3, Routine Quarterly Integrated ReportBoric Acid
Loop seal
Fire Barrier
Probabilistic Risk Assessment
Temporary Modification
Functionality Assessment
Significance Determination Process
Operability Determination
Scaffolding
IR 05000245/201200323 July 2012IR 05000336-12-003, 05000423-12-003, on 04/01/2012-06/30/2012, Millstone Power Station Units 1 and 2, Operability Determinations and Functionality AssessmentsHigh winds
Fire Barrier
Stroke time
Internal Flooding
Enforcement Discretion
Operator Manual Action
Temporary Modification
Functionality Assessment
Significance Determination Process
Operability Determination
Time Critical Operator Action
Liquid penetrant
Fire Protection Program
IR 05000245/20120042 November 2012IR 05000336-12-004, 05000423-12-004; 7/1/2012 - 9/30/2012; Millstone Power Station Units 2 and 3; Post Maintenance Testing; Follow-Up of Events and Notices of Enforcement DiscretionUltimate heat sink
Offsite Dose Calculation Manual
Fire Barrier
Internal Flooding
Enforcement Discretion
Probabilistic Risk Assessment
Nondestructive Examination
Temporary Modification
Functionality Assessment
Condition Adverse to Quality
Fukushima Dai-Ichi
Significance Determination Process
Process Control Program
Operability Determination
Preliminary White Finding
GOTHIC
Operability Assessment
Power Uprate
Stretch Power Uprate
Overspeed trip
IR 05000245/201200516 January 2013IR 05000336-12-005 and 05000423-12-005; Millstone Power Station - NRC Integrated Inspection Report (10-01-12 - 12-31-12)Boric Acid
High winds
Shutdown Margin
High Radiation Area
Ultimate heat sink
Offsite Dose Calculation Manual
Fire Barrier
Water Inventory Control
Internal Flooding
Enforcement Discretion
Probabilistic Risk Assessment
Coatings
Reserve Station Service Transformer
Nondestructive Examination
Functionality Assessment
Locked High Radiation Area
Finite Element Analysis
Significance Determination Process
Job Performance Measure
Operability Determination
Maintenance Rule Program
Control of Heavy Loads
Fuel cladding
Liquid penetrant
Through-Wall Leak
Through Wall Leak
Dissimilar Metal Weld
Scaffolding
Operability Assessment
IR 05000245/201200720 June 2012IR 05000336-12-007, 05000423-12-007, on 4/16/12 - 5/11/12, Millstone Power Station, Units 2 and 3, Component Design Bases InspectionSafe Shutdown
Boric Acid
Stroke time
Internal Flooding
Probabilistic Risk Assessment
Temporary Modification
Significance Determination Process
Battery sizing
Weak link
GOTHIC
Operability Assessment
IR 05000245/20120086 July 2012IR 05000245-12-008, on 06/25-27/12, Millstone Power Station Unit 1
IR 05000245/20120099 May 2012Assessment Follow-Up Letter for Millstone Power Station Unit 2 (ML 05000336/2012009)
IR 05000245/201201031 August 2012IR 05000336-12-010 and 05000423-12-010, 07/16/2012 - 08/02/2012, Millstone Power Station; Biennial Baseline Inspection of Problem Identification and ResolutionSafe Shutdown
High winds
Locked High Radiation Area
Condition Adverse to Quality
Significance Determination Process
Operability Determination
Time Critical Operator Action
Maintenance Rule Program
Fuel cladding
IR 05000245/20120112 November 2012IR 05000336-12-011, 9/10/2012 - 9/13/2012, Millstone Power Station, Unit 2, Supplemental Inspection, and Assessment Follow-Up LetterSignificance Determination Process
Preliminary White Finding
IR 05000245/201240324 February 2012IR 05000336-12-403, 05000423-12-403; on 2/6/2012 - 2/9/2012; Millstone Power Station, Units 2 and 3; Baseline Security Inspection Report. (letter only)Affidavit
IR 05000245/201250316 November 2012IR 05000336-12-503, 05000423-12-503; 8/20/2012 - 10/4/2012; Millstone Power Station, Units 2 & 3; Emergency Preparedness Exercise EvaluationSignificance Determination Process
IR 05000245/201300211 April 2013IR 05000336-13-002, 05000423-13-002; 01/01/2013 - 03/31/2013: Millstone Power Station Units 2 and 3; Problem Identification and ResolutionSafe Shutdown
Boric Acid
High winds
Fire Barrier
Stroke time
Internal Flooding
Probabilistic Risk Assessment
Reserve Station Service Transformer
Temporary Modification
Functionality Assessment
Significance Determination Process
Operability Determination
Earthquake
Maintenance Rule Program
Downpower
IR 05000245/20130036 August 2013IR 05000336-13-003, 05000423-13-003, on 04/01/2013-06/30/2013, Millstone, Units 2 and 3, Refueling and other Outage Activities, Follow-Up of Events and Notices of Enforcement Discretion, Maintenance Risk Assessments and Emergent Work ControlEnforcement Discretion
IR 05000245/20130048 November 2013Millstone Power Station-NRC Integrated Inspection Report 05000336/2013004 And 05000423/2013004 and Notice of Violation and Independent Spent Fuel Storage Installation Report No. 07200047/2013001High winds
Ultimate heat sink
Offsite Dose Calculation Manual
Fire Barrier
Stroke time
Enforcement Discretion
Reserve Station Service Transformer
Anchor Darling
Functionality Assessment
Condition Adverse to Quality
Significance Determination Process
Annual Radioactive Effluent Release Report
Operability Determination
Annual Radiological Effluent Release Report
Fuel cladding
Grace period
Fatality
IR 05000245/201300510 February 2014IR 05000336-13-005, 05000423-13-005; 10/01/2013 - 12/31/2013; Millstone Power Station Units 2 and 3; Operability Determinations and Functional Assessments and Other ActivitiesSafe Shutdown
Boric Acid
High Radiation Area
Fire Barrier
Hydrostatic
Enforcement Discretion
Reserve Station Service Transformer
Temporary Modification
Functionality Assessment
Main transformer failure
Significance Determination Process
Job Performance Measure
Operability Determination
Time Critical Operator Action
Fire Protection Program
Scaffolding
Downpower
Operability Assessment
Siren