Nuclear Accident Reporting System
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Nuclear Accident Reporting System Ginna
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Nuclear Accident Reporting System Indian Point
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Nuclear Accident Reporting System Limerick
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Nuclear Accident Reporting System Nine Mile Point
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Nuclear Accident Reporting System Peach Bottom
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Nuclear Accident Reporting System Pilgrim
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Nuclear Accident Reporting System Three Mile Island
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Nuclear Accident Reporting System Vermont Yankee
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Nuclear Accident Reporting System Zion
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Nuclear Accident Reporting System Browns Ferry
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Nuclear Accident Reporting System Clinton
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Nuclear Accident Reporting System Dresden
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Nuclear Accident Reporting System Callaway
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Nuclear Accident Reporting System Waterford
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Nuclear Accident Reporting System Fort Calhoun
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Nuclear Accident Reporting System Fort Saint Vrain
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Nuclear Accident Reporting System Hallam
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Nuclear Accident Reporting System Humboldt Bay
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Nuclear Accident Reporting System Parr
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Nuclear Accident Reporting System Big Rock Point
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Nuclear Accident Reporting System Elk River
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Nuclear Accident Reporting System South Texas
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Nuclear Accident Reporting System Sundesert
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Nuclear Accident Reporting System Victoria
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Nuclear Accident Reporting System Clinch River
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Nuclear Accident Reporting System Kemmerer
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RS-17-001, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
RS-17-021, Eighth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design-Basis External Events
RS-17-096, Ninth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order No. EA-12-049)
RS-16-147, Seventh Six-Month Status Report in Response to 03/12/ 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design-Basis External Events (Order Number EA-12-049)
RS-16-149, Seventh Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design-Basis External Events (Order Number EA-12-049)
RS-16-024, Sixth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
RS-16-026, Sixth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
RS-17-162, Radiological Emergency Plan Addendum Revision
RS-15-214, Fifth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
RS-15-212, Fifth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events
NRC 2015-0015, License Amendment Request 277, Revision to Staff Augmentation Times in the Emergency Plan
RS-14-222, License Amendment Request to Revise Emergency Plan Requalification Training Frequency for Emergency Response Organization Personnel
RS-13-280, Request for Exemption from the Biennial Emergency Preparedness Exercise Requirements in 10 CFR 50, Appendix E, IV.F.2.c
RS-17-126, Quad Cities Nuclear Power Station, Units 1 & 2, Revision 14 to Updated Final Safety Analysis Report, Chapter 9, Auxiliary Systems
RA-15-019, Attachment 6 - EP-AA-1005, Revised Radiological Emergency Plan Annex Information for LaSalle County Station
RA-15-019, Attachment 5 - EP-AA-1004, Revised Radiological Emergency Plan Annex Information for Dresden Station
RA-15-019, Attachment 4 - EP-AA-1003, Revised Radiological Emergency Plan Annex Information for Clinton Power Station
RA-15-019, Attachment 3 - EP-AA-1002, Revised Radiological Emergency Plan Annex Information for Byron Station
RA-15-019, Attachment 1 - Response to the Request for Additional Information - License Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors
RA-14-032, Dresden, Units 2 & 3, Attachment 5, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1004, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosure 5B and 5C, Dr 3-77 - Dr 3-160
RA-14-032, Clinton, Unit 1, Attachment 4, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1003, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosure 4B and 4C, Cl 3-74 - Cl 3-151
RA-14-032, Byron, Units 1 and 2, Attachment 3, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1002, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosures 3B, 3C, by 3-75 - by 3-157
RS-14-128, LaSalle, Units 1 & 2, Updated Final Safety Analysis Report, Revision 20, Chapter 9.0, Auxiliary Systems
RS-10-082, Changes to Emergency Plan, Rev. 12 and Emergency Plan Implementing Procedure EPIP-07, Rev. 7
RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Chapter 9.0 - Auxiliary Systems
NEI 99-01, Dresden, Units 2 & 3, Attachment 5, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1004, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosure 5B and 5C, Dr 3-77 - Dr 3-160
NEI 99-01, Clinton, Unit 1, Attachment 4, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1003, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosure 4B and 4C, Cl 3-74 - Cl 3-151
NEI 99-01, Byron, Units 1 and 2, Attachment 3, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1002, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosures 3B, 3C, by 3-75 - by 3-157
NRC 2009-0022, 2009 Point Beach Initial License Examination Proposed Administrative JPMs
RS-06-185, Additional Information Supporting Request for NRC Approval of Changes to Clinton Power Station Emergency Plan Annex
RS-06-080, Request for NRC Approval of Changes to the Plant Emergency Plan Annex
RS-18-143, Supplemental Information Supporting License Amendment Requests for Approval of Changes to Emergency Plan Staffing Requirements
ZS-2010-0324, Changes to Emergency Plan, Revision 13
RS-03-207, Revisions to the Exelon Nuclear Standardized Radiological Emergency Plan Implementing Procedures
RS-03-197, Revisions to the Exelon Nuclear Standardized Radiological Emergency Plan Implementing Procedures
NRC 2003-0092, Emergency Plan Implementing Procedure Revisions
RS-03-159, Revisions to the Exelon Nuclear Standardized Radiological Emergency Plan Implementing Procedure
NRC 2003-0017, Emergency Plan Implementing Procedure Revisions Point Beach Nuclear Plant, Units 1 & 2
NRC 2003-0011, Emergency Plan Implementing Procedure Revisions
RS-20-131, Part II: Planning Standards and Criteria
U-602951, Provides Update to Summary Provided in Util Ltr U-602940. Condition Rept 1-98-02-448 Initiated to Track Investigation & Corrective Actions for Failure to Update State of Il as Required by EC-07
U-600288, Emergency Response Facilities Design Rept
U-603126, Informs That CPS Graded Exercise Was Conducted on 981118. Several Areas for Improvement Were Identified During Critique Process.More Significant Critique Findings Are Listed
U-601279, 10CFR50.59 Rept for Plant Mods,Temporary Mods,Procedures & Documents,Jan-Mar 1988
U-601790, Summarizes Util Performance Improvement Since 891031 Re End of SALP 9 Period & Presents Brief Description of 1991 Initiatives for Further Improvement of Performance
SECY-24-0007, Weekly Information Report Week Ending January 19, 2024
05000456/LER-1989-005-06, :on 890422,instrument Inverter 111 Tripped & Repair Not Completed within 24 H Per Tech Spec.Caused by Shorted Capacitor Due to Normal Wear.Instrument Bus Energized & Inverter Repaired
05000254/LER-1989-004-07, :on 890417,reactor Manually Scrammed Due to Electromagnetic Relief Valve 1-203-3D Being Stuck Open. Caused by Steam Leakage Past Pilot Valve & Obstruction of Drain Orifice.Relief & Pilot Valves Replaced
05000457/LER-1989-001-09, :on 890223,loss of RHR 2B Loop Occurred as Result of Procedural Deficiency.Caused by Failure to Identify That Placing Ssps in Test Would Not Block auto- Closure of Pump Valves.Procedure Revised
05000456/LER-1989-002-09, :on 890416,main Steam Line Low Pressure Reactor Trip,Safety Injection & Main Steam Isolation Occurred.Caused by RCS Pressure Above 1,1930 Psig & Main Steam Pressure Less than 640 Psig.Heatup Procedure Will Be Revised
05000265/LER-1989-002-11, :on 890524,unusual Event Declared Due to Reactor Coolant Leakage Into Primary Containment in Excess of Tech Spec Limit of 5 Gpm.Caused by Leakage from RCIC Steam Supply Isolation Valve 2-1301-16
05000456/LER-1988-022-02, :on 881016,reactor Tripped on Reactor Coolant Pump Low Flow Followed by Turbine/Generator Trip.Caused by Potential Transformer Failure on Offsite 138 Kv Line.Subj Potential Transformer Replaced & Line Restored
05000265/LER-1987-004-10, :on 870218,suppression Chamber to Drywell Vacuum Breaker 2-1601-33A Would Not Return to Normal Closed Position After Being Tested.Caused by Either Slightly Dimpled Valve Bushing or Corroded Solenoid
05000456/LER-1988-024-04, :on 881031,operator Noted That Hydraulic Pump on 1A MSIV Pumping Continuously.Caused by Failure of M1 Four Way Valve.Nuclear Work Request A26531 Written to Replace Defective Four Way Hydraulic Valve M1
05000456/LER-1988-008, :on 880325 & 27,operators Noted Decreasing Vol Control Tank Level Causing Increased make-up.Caused by Improperly Locked Closed Valve Inadvertently Bumped Off Closed Seat.Valve Repaired & Reinstalled
05000237/LER-1985-034-03, :on 850816,unit Tripped from Low Reactor Water Level Scram.Caused by Loss of Offsite Power.Procedure Written to Modify Main Transformer During Extended Loss of Offsite Power Event
05000254/LER-1996-007-02, :on 960510,secondary Containment Damaged.Caused by Tornado.Initiated Shutdown,Ac Power Restored to Prompt Notification Sys & Station Blackout Bldg Cables Spliced Per Er 9603099
05000457/LER-1996-001-03, :on 960118,inadequate Control of Staged Roofing Matls Lead to Loss of Offsite Power Due to Loss of Both Unit 2 Station Auxiliary Transformers.Addressed Control of Staged Const Matls Onsite
05000254/LER-1992-010-03, :on 920407,loss of 125 Volt Dc Turbine Bldg Bus 1A & 1A-2 Occurred.Caused by Personnel Error.Plexiglass Covers Placed Over Disconnects Until Work Completed
05000254/LER-1991-027-01, :on 911216,leak from Drain Valve,Water Drained Through a Floor Pipe Onto an Emergency Bus.Caused by Leak from Reactor Bldg Sys Through Manual Drain Valve Which Was Open.Drain Valve Closed
05000254/LER-1993-005-05, :on 930609,numerous Alarms Received in CR, Including HPCI Turbine Rupture Disc High Pressure Alarm. Caused by Ruptured Disk,Releasing Steam/Water Mixture. Test Will Be Conducted on Rupture Disks
05000254/LER-1990-006-01, :on 900313,tornado Warning for Rock Island County Received on Weather Radio.Station Entered Procedure Qoa 010-10.One Person Substained Minor Injuries & Some Site Damage Sustained.Notification to Be Evaluated
05000456/LER-1989-016-05, :on 891201,RHR Pump Suction Relief Valve Premature Actuation Occurred & Failed to Reseat.Caused by Deficient Work Practices & Pesonnel Error.Maint Procedures Reviewed.Training Conducted
05000456/LER-1989-002-01, :on 890416,main Steamline Low Pressure Reactor Trip,Safety Injection & Main Steamline Isolation Occurred. Caused by Mgt & Procedural Deficiencies.Formal Policy on Use of Extra Operator During Startup Developed
RS-22-069, Constellation Nuclear Radiological Emergency Plan Addendum Revision. Includes EP-AA-1006, Addendum 3, Revision 10, Emergency Action Levels for Quad Cities Station
RA-15-048, Response to Request for Additional Information on License Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors
05000457/LER-2009-002, Regarding Loss of Offsite Power Coincident with a Reactor Trip Due to Loss of 2C Reactor Coolant Pump
RS-22-057, Constellation Radiological Emergency Plan Addendum Revision
RS-22-056, Constellation Radiological Emergency Plan Addendum Revision