IR 05000029/1988010 | 13 September 1988 | Yankee Rowe | Insp Rept 50-029/88-10 on 880601-0801.No Violations Noted. Major Areas Inspected:Licensee Action on Previous Inspector Findings,Operational Safety Verification,Radiological Controls & Events Requiring Telephone Notification to NRC | Steam Generator Emergency Diesel Generator Main Steam Line Control Rod |
IR 05000184/2013001 | 1 November 2012 | National Bureau of Standards Reactor | Examination Report, No. 50-184/13-01, National Institute of Standards and Technology | Control Rod |
IR 05000188/2013201 | 24 July 2013 | Kansas State University | IR 05000188-13-201; 06/24-27/2013 at Kansas State University Reactor - NRC Routine Inspection Report No. 50-188/2013-201 | |
IR 05000213/1997003 | 9 October 1997 | Haddam Neck | Insp Rept 50-213/97-03 on 970408-0707 & 0805.Violations Noted.Major Areas Inspected:Operations,Engineering,Maint & Plant Support | Steam Generator Reactor Coolant System Feedwater Service water Emergency Diesel Generator Steam Jet Air Ejector Main Steam Line |
IR 05000213/1998001 | 13 May 1998 | Haddam Neck | Insp Rept 50-213/98-01 on 980113-0413.Violations Noted.Major Areas Inspected:Decommissioning Support Activities,Spent Fuel Safety,Plant Support & Radiological Controls & Facility Mgt & Control | Steam Generator Reactor Coolant System Service water Emergency Diesel Generator Auxiliary Feedwater |
IR 05000220/2012005 | 11 February 2013 | Nine Mile Point | IR 05000220-12-005, 05000410-12-005, on 10/01/2012 - 12/31/2012; Nine Mile Point Nuclear Station, Units 1 and 2, Equipment Alignment; Post Maintenance Testing | Feedwater Service water Reactor Protection System Emergency Diesel Generator Main Steam Isolation Valve Reactor Core Isolation Cooling Primary containment Main Transformer Shutdown Cooling High Pressure Core Spray Core Spray Residual Heat Removal Control Room Emergency Ventilation Standby Liquid Control Remote shutdown Decay Heat Removal Main Steam Line Control Rod Main Steam Containment Spray |
IR 05000220/2016002 | 8 August 2016 | Nine Mile Point | Integrated Inspection Report 05000220/2016002 and 05000410/2016002 and Exercise of Enforcement Discretion | Reactor Coolant System Feedwater Secondary containment Service water Emergency Diesel Generator Main Steam Isolation Valve Reactor Core Isolation Cooling Primary containment Shutdown Cooling Reactor Recirculation Pump Reactor Pressure Vessel High Pressure Core Spray Core Spray Residual Heat Removal Reactor Water Cleanup Standby Gas Treatment System Standby Liquid Control Remote shutdown Reactor Building Closed Loop Cooling Emergency Core Cooling System Control Room Envelope Main Condenser Control Rod |
IR 05000244/2006004 | 31 October 2006 | Ginna | IR 05000244-06-004 on 07/01/2006 Through 09/30/2006; R.E. Ginna Nuclear Power Plant | Steam Generator Feedwater Service water Emergency Diesel Generator Auxiliary Feedwater Residual Heat Removal Main Steam Line Main Steam Containment Spray |
IR 05000244/2006006 | 15 October 2006 | Ginna | IR 05000244-06-006, on 08/14-31/2006, R.E. Ginna Nuclear Power Plant, LLC | Steam Generator Reactor Coolant System Service water Reactor Protection System Main Steam Isolation Valve Auxiliary Feedwater Main Steam Line |
IR 05000244/2013003 | 22 July 2013 | Ginna | IR 05000244-13-003; 04/01/2013 - 06/30/2013; R.E. Ginna Nuclear Power Plant, LLC (Ginna); Operability Determinations and Functionality Assessments | Steam Generator Reactor Coolant System Service water Reactor Protection System Emergency Diesel Generator Auxiliary Feedwater Containment Spray |
IR 05000245/1986019 | 12 November 1986 | Millstone | Insp Repts 50-245/86-19 & 50-336/86-21 on 860930-1103.No Unacceptable Conditions Identified.Engineered Safeguards Actuations Will Be Reviewed During Next Salp.Major Areas Inspected:Unit 1 Safety Insp & Unit 2 Refueling Outage Insp | Steam Generator Reactor Coolant System Feedwater Service water Reactor Protection System Emergency Diesel Generator Shutdown Cooling Reactor Pressure Vessel Main Steam Safety Valve |
IR 05000245/1997202 | 29 August 1997 | Millstone | Insp Repts 50-245/97-202,50-336/97-202 & 50-423/97-202 on 970529-0721.Violations Noted.Major Areas Inspected: Operations,Maint,Engineering & Plant Support,Including Emergency Preparedness Issues & Fire Protection Activities | Steam Generator Reactor Coolant System Feedwater Service water Emergency Diesel Generator Main Steam Isolation Valve Auxiliary Feedwater Residual Heat Removal Reactor Water Cleanup Standby Liquid Control Main Steam Safety Valve Main Steam Line Safety Relief Valve Control Room Envelope Main Steam |
IR 05000247/2017003 | 27 October 2017 | Indian Point | Integrated Inspection Report 05000247/2017003 and 05000286/2017003 | Steam Generator Reactor Coolant System Feedwater Service water Reactor Protection System Emergency Diesel Generator Auxiliary Feedwater Shutdown Cooling Reactor Pressure Vessel Residual Heat Removal Intermediate Range Monitor Decay Heat Removal Control Rod |
IR 05000250/1986027 | 1 December 1986 | Turkey Point 05000000 | SALP Repts 50-250/86-27 & 50-251/86-27 for Nov 1984 - Apr 1986 | Steam Generator Reactor Coolant System Feedwater Reactor Protection System Emergency Diesel Generator Main Steam Isolation Valve Auxiliary Feedwater Main Transformer Main Turbine Safety Parameter Display System Residual Heat Removal Decay Heat Removal Main Steam Line Control Rod Auxiliary Feed Water Main Steam Containment Spray |
IR 05000250/1986045 | 13 January 1987 | Turkey Point | Insp Repts 50-250/86-45 & 50-251/86-45 on 861103-1215. Violations Noted:Failure to Meet Requirements of Tech Spec 6.8.1 Re Written Procedures & Administrative Policies & 10CFR50,App B,Criterion Xvi Re Corrective Actions | Steam Generator Feedwater Service water Reactor Protection System Emergency Diesel Generator Auxiliary Feedwater Residual Heat Removal Safety Relief Valve |
IR 05000255/2008002 | 15 May 2008 | Palisades | IR 05000255-08-002 on 01/01/2008 - 03/31/2008 for Palisades, Fire Protection, Maintenance Effectiveness, Outage Activities, Access Control to Radiologically Significant Areas, Radiological Environmental Monitoring Program and Radioactive Ma | Steam Generator Reactor Coolant System Feedwater Service water Reactor Protection System Emergency Diesel Generator Auxiliary Feedwater Main Transformer Emergency Core Cooling System Decay Heat Removal Auxiliary Feed Water |
IR 05000261/2012002 | 30 April 2012 | Robinson | IR 05000261-12-002, Carolina Power and Light Company, on 01/01/2012-03/31/2012, H.B. Robinson Steam Electric Plant, Unit 2, Operability Evaluations, Refueling and Outage Activities | Steam Generator Reactor Coolant System Feedwater Service water Emergency Diesel Generator Auxiliary Feedwater Reactor Pressure Vessel Residual Heat Removal Decay Heat Removal Control Rod |
IR 05000261/2014003 | 21 July 2014 | Robinson | IR 05000261-14-003, 4/01/2014 - 6/30/2014; H.B. Robinson Steam Electric Plant, Unit 2; Follow-up of Events and Notices of Enforcement Discretion | Steam Generator Reactor Coolant System Feedwater Service water Emergency Diesel Generator Auxiliary Feedwater Control Room Emergency Ventilation Main Steam Safety Valve Safety Relief Valve |
IR 05000261/2014004 | 28 October 2014 | Robinson | IR 05000261/2014004, on July 1, 2014 Through September 30, 2014; H. B. Robinson Steam Electric Plant, Unit 2; Integrated Inspection Report | Steam Generator Reactor Coolant System Service water Emergency Diesel Generator Main Steam Isolation Valve Auxiliary Feedwater Control Room Emergency Ventilation |
IR 05000261/2015003 | 29 October 2015 | Robinson | IR 05000261/2015003, on July 1, 2015, Through September 30, 2015; H.B. Robinson Steam Electric Plant, Unit 2, Integrated Inspection Report | Steam Generator Reactor Coolant System Feedwater Service water Auxiliary Feedwater Emergency Core Cooling System Containment Spray |
IR 05000261/2015004 | 27 January 2016 | Robinson | NRC Integrated Inspection Report 05000261/2015004, October 1, 2015 Through December 31, 2015 | Steam Generator Reactor Coolant System Feedwater Service water Auxiliary Feedwater Shutdown Cooling HVAC Residual Heat Removal Emergency Core Cooling System Decay Heat Removal Control Rod |
IR 05000261/2016008 | 3 October 2016 | Robinson | NRC Component Design Bases Inspection Report 05000261/2016008 | Steam Generator Feedwater Emergency Diesel Generator Auxiliary Feedwater |
IR 05000266/2014004 | 30 October 2014 | Point Beach | IR 05000266/2014004, 05000301/2014004, 07200005/2014001; 07/01/2014 - 09/30/2014; Point Beach Nuclear Plant, Units 1 & 2; Fire Protection, and Operability Determinations and Functional Assessments | Steam Generator Reactor Coolant System Service water Emergency Diesel Generator Auxiliary Feedwater HVAC Residual Heat Removal Standby Gas Treatment System Decay Heat Removal Containment Spray |
IR 05000275/1999012 | 13 September 1999 | Diablo Canyon | Insp Repts 50-275/99-12 & 50-323/99-12 on 990711-0821. Noncited Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support | Reactor Coolant System Feedwater Auxiliary Feedwater Main Turbine Residual Heat Removal Emergency Core Cooling System Safety Relief Valve |
IR 05000275/2002003 | 1 August 2002 | Diablo Canyon | IR 05000275-02-003, IR 05000323-02-003, on 04/07/2002 to 07/06/2002, Pacific Gas and Electric. Co., Diablo Canyon Units 1 & 2, Postmaintenance Test, Access to Rad Sig Areas | Steam Generator Reactor Coolant System Feedwater Auxiliary Feedwater Main Turbine Reactor Pressure Vessel Residual Heat Removal Circulating Water System Emergency Core Cooling System Decay Heat Removal Main Steam Line Main Condenser Control Rod Containment Spray |
IR 05000275/2017001 | 10 May 2017 | Diablo Canyon | NRC Integrated Inspection Report 05000275/2017001 and 05000323/2017001 | Reactor Coolant System Emergency Diesel Generator Auxiliary Feedwater Residual Heat Removal Control Room Envelope Control Rod Containment Spray |
IR 05000282/2006005 | 5 February 2007 | Prairie Island | IR 05000282-06-005, 05000306-06-005; Nuclear Management Company, LLC; 10/01/06 - 12/31/06; Prairie Island Nuclear Generating Plant, Units 1 and 2; Inservice Inspection Activities | Steam Generator Reactor Coolant System Feedwater Auxiliary Feedwater Shutdown Cooling Residual Heat Removal Shield Building Decay Heat Removal Containment Spray |
IR 05000282/2017004 | 26 January 2018 | Prairie Island | NRC Integrated Inspection Report 05000282/2017004; 05000306/2017004; 05000282/2017501 and 05000306/2017501 | Steam Generator Reactor Coolant System Feedwater Secondary containment Emergency Diesel Generator Auxiliary Feedwater Shutdown Cooling Reactor Pressure Vessel Emergency Core Cooling System Decay Heat Removal Main Steam Line Auxiliary Feed Water Containment Spray |
IR 05000282/2019003 | 14 November 2019 | Prairie Island | Integrated Inspection Report 05000282/2019003 and 05000306/2019003 | Reactor Coolant System Emergency Diesel Generator Auxiliary Feedwater Primary containment Residual Heat Removal Shield Building Control Rod Auxiliary Feed Water Containment Spray |
IR 05000286/2010003 | 10 August 2010 | Indian Point | IR 05000286-10-003, on 04/01/2010 - 06/30/2010; Indian Point Nuclear Generating (Indian Point) Unit 3; Event Follow-Up | Steam Generator Reactor Coolant System Feedwater Service water Reactor Protection System Emergency Diesel Generator Auxiliary Feedwater Main Turbine Residual Heat Removal Remote shutdown Control Rod |
IR 05000315/2007006 | 24 January 2008 | Cook | IR 05000315-07-006, 05000316-07-006, on 10/01/2007 - 12/31/2007, D. C. Cook, Units 1 and 2, Evaluations of Changes, Tests, or Experiments, Event Response | Steam Generator Reactor Coolant System Feedwater Service water Reactor Protection System Emergency Diesel Generator Auxiliary Feedwater Main Turbine Shutdown Cooling Steam Jet Air Ejector Emergency Core Cooling System Decay Heat Removal Main Steam Line Control Rod Main Steam Containment Spray |
IR 05000315/2008003 | 13 August 2008 | Cook | IR 05000315-08-003, 05000316-08-003; on 04/01/2008 - 06/30/2008; D. C. Cook Nuclear Power Plant, Units 1 and 2; Operability Evaluations, Permanent Plant Modifications, Refueling & Other Outage Activities, Surveillance Testing, ALARA Plannin | Steam Generator Reactor Coolant System Feedwater Secondary containment Service water Reactor Protection System Emergency Diesel Generator Auxiliary Feedwater Main Turbine Safety Parameter Display System Reactor Pressure Vessel Residual Heat Removal Emergency Core Cooling System Decay Heat Removal Main Condenser Main Steam Containment Spray |
IR 05000317/1987001 | 30 March 1987 | Calvert Cliffs | Insp Repts 50-317/87-01 & 50-318/87-01 on 870112-0228.No Violations Noted.Major Areas Inspected:Routine Facility Activities,Operational Events,Maint,Surveillance,License Initiatives Re SALP & Physical Security | Steam Generator Reactor Coolant System Service water Reactor Protection System Emergency Diesel Generator Emergency Core Cooling System Safety Relief Valve Control Rod Auxiliary Feed Water Main Steam Containment Spray |
IR 05000327/2020003 | 10 November 2020 | Sequoyah | Integrated Inspection Report 05000327/2020003, 05000328/2020003 and 07200034/2020002 | Steam Generator Reactor Coolant System Feedwater Emergency Diesel Generator Main Turbine Reactor Pressure Vessel Auxiliary Building Gas Treatment System Residual Heat Removal Control Room Emergency Ventilation Control Rod |
IR 05000334/1986007 | 29 May 1986 | Beaver Valley | Insp Rept 50-334/86-07 on 860419-0521.No Violations Noted. Major Areas Inspected:Plant Operations,Housekeeping,Fire Protection,Radiological Controls,Physical Security,Esf Verification & Reactor Cavity Seal | Steam Generator Reactor Coolant System Feedwater Reactor Protection System Emergency Diesel Generator Main Steam Safety Valve Main Steam |
IR 05000334/2021001 | 13 May 2021 | Beaver Valley | Integrated Inspection Report 05000334/2021001 and 05000412/2021001 | Steam Generator Service water Emergency Diesel Generator Auxiliary Feedwater Control Rod Auxiliary Feed Water Main Steam |
IR 05000335/2016010 | 9 June 2016 | Saint Lucie | NRC Design Bases Inspection (Programs) Report, 05000335/2016010 and 05000389/2016010, April 25, 2016 April 29, 2016 | Containment Spray |
IR 05000338/1990013 | 27 June 1990 | North Anna | Insp Repts 50-338/90-13 & 50-339/90-13 on 900514-18 & 29. Noncited Violations Noted.Major Areas Inspected:Radiation Monitoring Sys,Water Chemistry & QC | Steam Generator Reactor Coolant System Feedwater |
IR 05000338/1996010 | 2 December 1996 | North Anna | Insp Repts 50-338/96-10 & 50-339/96-10 on 960922-1102. Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support | Steam Generator Reactor Coolant System Feedwater Service water Reactor Protection System Auxiliary Feedwater Main Turbine Safety Parameter Display System Emergency Core Cooling System Main Steam |
IR 05000338/2010005 | 28 January 2011 | North Anna | IR 05000338-10-005, 05000339-10-005, 07200056-10-002, on 10/01/2010 - 12/31/2010, North Anna Power Station, Units 1 & 2, and Independent Spent Fuel Storage Installation | Steam Generator Reactor Coolant System Feedwater Emergency Diesel Generator Main Steam Isolation Valve Auxiliary Feedwater Primary containment Residual Heat Removal Emergency Core Cooling System Control Rod |
IR 05000338/2017004 | 1 February 2018 | North Anna | NRC Integrated Inspection Report 05000338/2017004 and 05000339/2017004 | Steam Generator Reactor Coolant System Feedwater Auxiliary Feedwater Residual Heat Removal Decay Heat Removal Main Condenser Control Rod |
IR 05000341/1988012 | 19 July 1988 | Fermi | Insp Rept 50-341/88-12 on 880401-0527.Violations Noted.Major Areas Inspected:Action on Previous Insp Findings,Operational Safety,Maint,Surveillance,Ler Followup,Mgt Meetings,Tmi Action Item Followup & Operation Safety Team Insp Followup | Reactor Coolant System Feedwater Reactor Protection System Emergency Diesel Generator Primary containment Shutdown Cooling Core Spray Residual Heat Removal Reactor Water Cleanup Standby Gas Treatment System Automatic Depressurization System Standby Liquid Control Emergency Equipment Cooling Water Emergency Core Cooling System Main Steam Line Control Rod Main Steam |
IR 05000344/1987021 | 20 May 1987 | Trojan | Enforcement Conference Rept 50-344/87-21 on 870514.Major Areas Discussed:Implementation of Licensee Radiation Protection Program Following 870409 Dispersal of Irradiated Fuel Fragments in Containment Bldg | Steam Generator |
IR 05000344/1987026 | 27 July 1987 | Trojan | Insp Rept 50-344/87-26 on 870706-10.No Violations or Deviations Noted.Major Areas Inspected:Licensee Action on Previous Insp Findings,External & Internal Exposure Control, Control of Radioactive Matls & Contamination & ALARA | Steam Generator Reactor Coolant System Main Condenser |
IR 05000344/1987033 | 28 September 1987 | Trojan | Insp Rept 50-344/87-33 on 870831-0903 & 0914-17.No Violation or Deviation Noted.Major Areas Inspected:Licensee Action on Previous Insp Findings,Organization & Mgt,Transportation of Radioactive Matls,Facilities & Equipment | Steam Generator |
IR 05000344/1987040 | 30 November 1987 | Trojan | Insp Rept 50-344/87-40 on 871018-1121.Violations Noted. Major Areas Inspected:Operational Safety Verification,Maint, Surveillance & Event Followup | Steam Generator Reactor Coolant System Feedwater Reactor Protection System Auxiliary Feedwater Main Steam Line Main Condenser Control Rod |
IR 05000348/1987001 | 13 February 1987 | Farley | Insp Repts 50-348/87-01 & 50-364/87-01 on 870112-16.No Violations or Deviations Noted.Major Areas Inspected:Liquid & Gaseous Radwaste Mgt,Effluent Monitoring,Environ Monitoring,Tmi Items & IE Info Notices | Steam Generator Reactor Coolant System Control Room Emergency Ventilation |
IR 05000348/2009007 | 31 December 2009 | Farley | IR 05000348-09-007 and 05000364-09-007 on 11/02/08 - 11/06/08 and 11/16/09 - 11/20/09 for Joseph M. Farley - NRC Problem Identification and Resolution Inspection Report | Service water Auxiliary Feedwater |
IR 05000348/2010005 | 27 January 2011 | Farley | IR 05000348-10-005 and 05000364-10-005; 10/01/2010 - 12/31/2010; Joseph M. Farley Nuclear Plant, Units 1 and 2; Fire Protection, Identification, and Resolution of Problems | Steam Generator Reactor Coolant System Feedwater Service water Auxiliary Feedwater Shutdown Cooling Residual Heat Removal Decay Heat Removal Containment Spray |
IR 05000352/2015001 | 14 May 2015 | Limerick | NRC Integrated Inspection Report 05000352/2015001 and 05000353/2015001 (January 1 - March 31, 2015) | Feedwater Secondary containment Service water High Pressure Coolant Injection Emergency Diesel Generator Main Steam Isolation Valve Reactor Core Isolation Cooling Primary containment Main Transformer Main Turbine HVAC Residual Heat Removal Standby Gas Treatment System Automatic Depressurization System Reactor Enclosure Recirculation System Remote shutdown Residual Heat Removal Service Water Spray Pond Emergency Core Cooling System Decay Heat Removal Control Rod |