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	Site	Start date	Title	Topic
IR 05000382/2023010	Waterford	31 January 2024	Comprehensive Engineering Team Inspection Report 05000382/2023010	Stroke time Arc flash Significance Determination Process Foreign Material Exclusion Power Uprate
ML23283A028	Fermi	9 October 2023	Inservice Testing Program for Pumps and Valves - Part 6: IST Check Valve Condition Monitoring Plans Rev. 3	Safe Shutdown Packing leak Ultimate heat sink Stroke time Anchor Darling Temporary Modification
ENS 56821	Curtiss Wright Flow Control Co.	30 August 2023 07:00:00	Part 21 - Inconsistent Potentiometer Resistance Values
IR 05000315/2023012	Cook	22 June 2023	Biennial Problem Identification and Resolution Inspection Report 05000315/2023012 and 05000316/2023012	Commercial Grade Dedication Met Tower Condition Adverse to Quality Significance Determination Process Operability Determination
IR 05000382/2022013	Waterford	28 November 2022	Design Basis Assurance Inspection (Programs) Inspection Report 05000382/2022013	Past operability Anchor Darling Condition Adverse to Quality Significance Determination Process Large early release frequency Earthquake Power-Operated Valves Weak link
IR 05000346/2022010	Davis Besse	2 November 2022	Design Basis Assurance Inspection (Programs) Inspection Report 05000346/2022010	Stroke time Past operability Significance Determination Process Power-Operated Valves Weak link
ML22292A072	Nine Mile Point	5 October 2022	5 to Updated Final Safety Analysis Report, Chapter 3, Sections 3.9A Thru 3.11	Safe Shutdown Safe Shutdown Earthquake Weld Overlay Hydrostatic Operating Basis Earthquake Nondestructive Examination Incorporated by reference Finite Element Analysis Abnormal operational transient Design basis earthquake Earthquake Liquid penetrant Power Uprate Stretch Power Uprate
ML22096A187	Oconee	15 July 2022	Issuance of Amendment Nos. 424, 426, and 425 Revise TS 3.7.7, Low Pressure Service Water (LPSW) System to Extend the Completion Time for One Required Inoperable LPSW Pump	Boric Acid Ultimate heat sink Stroke time Probabilistic Risk Assessment Incorporated by reference Surveillance Frequency Control Program Time Critical Operator Action Manual Operator Action
RA-22-0089, Response to Request for Additional Information Regarding Application to Revise Technical Specification 3.7.7, Low Pressure Service Water System, to Extend the Completion Time for One Required Inoperable LPSW	Oconee	14 April 2022	Response to Request for Additional Information Regarding Application to Revise Technical Specification 3.7.7, Low Pressure Service Water System, to Extend the Completion Time for One Required Inoperable LPSW	Unanalyzed Condition Stroke time Surveillance Frequency Control Program Time Critical Operator Action
IR 05000315/2021011	Cook	15 November 2021	Design Basis Assurance Inspection (Programs) Inspection Report 05000315/2021011 and 05000316/2021011	Boric Acid Packing leak Probabilistic Risk Assessment Anchor Darling Significance Determination Process Power-Operated Valves Power Operated Valves Coronavirus COVID-19 Weak link
IR 05000397/2021012	Columbia	3 November 2021	Design Basis Assurance Inspection (Programs) Inspection Report 05000397/2021012	Past operability Anchor Darling Significance Determination Process Power-Operated Valves Coronavirus COVID-19 Weak link
IR 05000281/2020040	Surry	30 December 2020	95001 Supplemental Inspection Supplemental Report 05000281/2020040	Boric Acid Past operability Preliminary White Finding
IR 05000313/2020011	Arkansas Nuclear	15 July 2020	Design Basis Assurance Inspection (Programs) Inspection Report 05000313/2020011 and 05000368/2020011	Stroke time Power-Operated Valves Coronavirus COVID-19
ENS 54001	Curtiss Wright Enertech	15 April 2019 07:00:00	Part-21 Notification - Snubber Hydraulic Fluid Batch Contains Particulates
ML19102A304		21 March 2019	Transcript of Advisory Committee on Reactor Safeguards NuScale Subcommittee Meeting - March 21, 2019	Safe Shutdown High Radiation Area Ultimate heat sink Offsite Dose Calculation Manual Anticipated operational occurrence Locked High Radiation Area Process Control Program Exemption Request Earthquake Turbine Missile
IR 05000338/2018010	North Anna	19 December 2018	NRC Design Bases Assurance Inspection (Team) Report 05000338/2018010 and 05000339/2018010	Reserve Station Service Transformer Anchor Darling Significance Determination Process Large early release frequency Operability Determination Battery sizing Weak link
ENS 53673	Itt Enidine	23 August 2018 04:00:00	Part 21 Report - Environmental Qualification Test Discrepancy
ENS 52828	Itt Enidine Inc.	26 June 2017 04:00:00	Part 21 - Potential Transducer Component Defect
ENS 52458	Itt Enidine Inc.	2 November 2016 05:00:00	Part 21 - Potential Transducer Component Defect
ENS 52300	Itt Enidine Inc.	19 August 2016 04:00:00	Part 21 Report - Defective Current to Pressure Transducers
ML16127A595	Mcguire Catawba Summer Seabrook McGuire	4 May 2016	Rotork Controls Inc. Part 21 Notification Concerning V12 (Pt No. N69-921) and K5 (N69-838 & N69-926) Safety Related Micro Switches	Coatings
IR 05000458/2015002	River Bend	11 August 2015	IR 05000458/2015002; on 04/01/2015 - 06/30/2015; River Bend Station; Integrated Resident and Regional Report; Problem Identification and Resolution; Other Activities - Inspection of Commercial-Grade Dedication Programs	High winds Packing leak Ultimate heat sink Stroke time Hydrostatic Temporary Modification Functionality Assessment Significance Determination Process Operability Determination Fire Protection Program Unidentified leakage
RNP-RA/14-0061, Submittal of Snubber Examination and Testing Program	Robinson	29 May 2014	Submittal of Snubber Examination and Testing Program	Safe Shutdown Maintenance Rule Program
CP-201401379, Transmittal of Inservice Testing Plan for Pumps and Valves Third Interval, Revision 1	Comanche Peak	24 February 2014	Transmittal of Inservice Testing Plan for Pumps and Valves Third Interval, Revision 1	Safe Shutdown Boric Acid Loop seal Mission time Stroke time Probabilistic Risk Assessment Incorporated by reference Large early release frequency Earthquake Power Operated Valves
RNP-RA/14-0014, Submittal of Ninety Day Inservice Inspection Summary Report	Robinson	30 January 2014	Submittal of Ninety Day Inservice Inspection Summary Report	Non-Destructive Examination Hydrostatic Coatings Anchor Darling VT-2 Moisture barrier Liquid penetrant Dissimilar Metal Weld Eddy-Current Testing
ENS 49302	Baldor Electric Co.	23 August 2013 04:00:00	Part-21 Notification - Motors May Have a Point for Foreign Material Entry
ML15331A221	Indian Point	3 May 2013	Official Exhibit - NYS000536-00-BD01 - Indian Point Nuclear Generating Units 2 and 3 - NRC Integrated Inspection Report 05000247/2013002 and 05000286/2013002 (May 3, 2013)	Boric Acid High Radiation Area Non-Destructive Examination Offsite Dose Calculation Manual Fire Barrier Anticipated operational occurrence Water Inventory Control Enforcement Discretion Probabilistic Risk Assessment Nondestructive Examination Functionality Assessment Significance Determination Process Annual Radioactive Effluent Release Report Foreign Material Exclusion Annual Radiological Environmental Operating Report Operability Determination Annual Radiological Effluent Release Report Liquid penetrant Fire Protection Program Dissimilar Metal Weld DM weld Substantial potential for overexposure Power change
ML15160A400	Indian Point	3 May 2013	NYS000536 - Indian Point Nuclear Generating Units 2 and 3 - NRC Integrated Inspection Report 05000247/2013002 and 05000286/2013002 (May 3, 2013)	Boric Acid High Radiation Area Non-Destructive Examination Offsite Dose Calculation Manual Fire Barrier Anticipated operational occurrence Water Inventory Control Enforcement Discretion Probabilistic Risk Assessment Nondestructive Examination Functionality Assessment Significance Determination Process Annual Radioactive Effluent Release Report Foreign Material Exclusion Annual Radiological Environmental Operating Report Operability Determination Annual Radiological Effluent Release Report Liquid penetrant Fire Protection Program Dissimilar Metal Weld DM weld Substantial potential for overexposure Power change
L-13-027, Sixteenth Refueling Outage Inservice Inspection Summary Report	Beaver Valley	1 February 2013	Sixteenth Refueling Outage Inservice Inspection Summary Report	Boric Acid Weld Overlay Hydrostatic VT-2 Control of Heavy Loads Liquid penetrant Dissimilar Metal Weld
L-2012-361, Report of 10 CFR 50.59 Plant Changes	Saint Lucie	1 October 2012	Report of 10 CFR 50.59 Plant Changes	Safe Shutdown Boric Acid Loop seal Operating Basis Earthquake Cyber Security Design basis earthquake Earthquake Power-Operated Valves Turbine Missile Flow Induced Vibration Power Uprate Stretch Power Uprate Measurement Uncertainty Recapture
IR 05000317/2012007	Calvert Cliffs	24 August 2012	IR 05000317-12-007 & 05000318-12-007, 5/21/2012 - 6/21/2012, Calvert Cliffs Nuclear Power Plant, Units 1 and 2, Component Design Bases Inspection	Safe Shutdown Loop seal Ultimate heat sink Stroke time Tornado Missile Probabilistic Risk Assessment Tornado Generated Missile Significance Determination Process Tornado Missile Protection Large early release frequency Operability Determination
ML12216A114	Oconee	8 August 2012	Summary of Meeting with Duke Energy Carolinas, LLC to Discuss Ongoing Major Projects as Oconee Nuclear Station, Units 1, 2, and 3	Fire Barrier
RNP-RA/12-0063, Submittal of 90 Day Inservice Inspection Summary Report	Robinson	15 June 2012	Submittal of 90 Day Inservice Inspection Summary Report	Non-Destructive Examination Hydrostatic Past operability Coatings Anchor Darling VT-2 Liquid penetrant Eddy-Current Testing
ML12017A092	Oconee	17 January 2012	Slides for Meeting with Duke Energy Carolinas to Discuss Oconee Nuclear Station, Units 1, 2, and 3 Regarding Major Project Plans	Fire Barrier Probabilistic Risk Assessment
ENS 47539	Dresser Consolidated	20 December 2011 06:00:00	Part 21 - Capacity Failure of Pressure Relief Valve
IR 05000348/2011002	Farley	29 April 2011	IR 05000348-11-002 and 05000364-11-002, on 01/01/11 - 03/31/11, Joseph M. Farley, Units 1 & 2	Boric Acid Fire Barrier Internal Flooding Enforcement Discretion Functionality Assessment Significance Determination Process Operability Determination Power change Flow Induced Vibration
IR 05000348/2010004	Farley	29 October 2010	IR 05000348-10-004 & 05000364-10-004, 07/01/2010 - 09/30/2010, Joseph M. Farley Nuclear Plant, Units 1 and 2, Identification and Resolution of Problems, Event Followup	Fire Barrier Enforcement Discretion Temporary Modification Functionality Assessment Job Performance Measure Fuel cladding
ML092320364	Oconee	14 August 2009	EOC 24 Refueling Outage Inservice Inspection Report Fourth Ten-Year Inservice Inspection Interval	Boric Acid Hydrostatic VT-2 Eddy Current Testing Liquid penetrant Through-Wall Leakage Dissimilar Metal Weld
ML090760635	Oconee	6 March 2009	EOC 23 Refueling Outage Inservice Inspection Report Fourth Ten-Year Inservice Inspection Interval	Weld Overlay Hydrostatic VT-2 Eddy Current Testing Liquid penetrant Dissimilar Metal Weld
ML082490152	Oconee	28 August 2008	Inservice Inspection Report for End of Cycle 24 Refueling Outage, Fourth Ten-Year Inservice Inspection Interval	Boric Acid Weld Overlay Hydrostatic VT-2 Liquid penetrant Through-Wall Leakage Dissimilar Metal Weld
ENS 43748	Enertech	25 October 2007 07:00:00	Potential 10Cfr Part 21 Reportable Condition for Enertech Cartridge Solenoid Valve
RNP-RA/07-0077, Submittal of 90 Day Inservice Inspection Summary Report	Robinson	2 August 2007	Submittal of 90 Day Inservice Inspection Summary Report	Hydrostatic Anchor Darling VT-2 Liquid penetrant
IR 05000482/2007002	Wolf Creek	11 May 2007	IR 05000482-07-002; 01/01/07 - 04/07/07; Wolf Creek Generating Station; Fire Protection, Followup of Events and Notices of Enforcement Discretion, Access Control to Radiologically Significant Areas	Safe Shutdown Packing leak High Radiation Area Internal Flooding Enforcement Discretion Fire impairment Temporary Modification Locked High Radiation Area Significance Determination Process Fuel cladding Biofouling Fire Protection Program Hourly Fire Watch Substantial potential for an overexposure Power change Overexposure
ML060890203	Brunswick	27 April 2006	Request for Relief Request No. VRR-15 for Regarding Check Valves Related to the Third 10-Year Inservice Testing Program
BSEP 06-0015, Response to Request for Additional Information Regarding Relief Request VRR- 15, Emergency Diesel Generator Service Water Check Valves	Brunswick	25 January 2006	Response to Request for Additional Information Regarding Relief Request VRR- 15, Emergency Diesel Generator Service Water Check Valves
BSEP 05-0104, Response to Request for Additional Information Regarding Relief Request VRR-15, Emergency Diesel Generator Service Water Check Valves	Brunswick	2 September 2005	Response to Request for Additional Information Regarding Relief Request VRR-15, Emergency Diesel Generator Service Water Check Valves
BYRON 2004-0077, Day Inservice Inspection Report for Interval 2, Period 2, Outage 2 (B2R11)	Byron	2 July 2004	Day Inservice Inspection Report for Interval 2, Period 2, Outage 2 (B2R11)	Boric Acid Hydrostatic Nondestructive Examination VT-2 Moisture barrier Pressure Boundary Leakage
BYRON 2004-0004, Day Inservice Inspection Report for Interval 2, Period 3, Outage 1 (81 R12)	Byron	12 January 2004	Day Inservice Inspection Report for Interval 2, Period 3, Outage 1 (81 R12)	Boric Acid Hydrostatic Nondestructive Examination VT-2 Moisture barrier Pressure Boundary Leakage
IR 05000361/2002010	San Onofre	18 December 2002	IR 05000361-02-010 & IR 05000362-02-10, on 10/28 - 11/22/02, San Onofre Nuclear Generating Station, Units 2 and 3, Safety System Design and Performance Capabilities and Permanent Plant Modifications. No Violations Noted	Boric Acid Probabilistic Risk Assessment
IR 05000315/1996012	Cook	31 July 1998	Forwards Resolution of Specific Issues Identified in Insp Repts 50-315/96-12 & 50-316/96-12.Resolution Will Enable NRC to Close Out Review of GL 89-10 Program	Operability Determination Weak link

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