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 Issue dateTitleTopic
RA-23-0154, Duke Energy - Response to Request for Additional Information Regarding Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)20 July 2023Duke Energy - Response to Request for Additional Information Regarding Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)Non-Destructive Examination
Weld Overlay
Finite Element Analysis
RA-23-0136, Duke Energy Response to Request for Additional Information Regarding Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)20 July 2023Duke Energy Response to Request for Additional Information Regarding Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)Non-Destructive Examination
RA-23-0142, Mcguire, Units 1 and 2, Oconee, Units 1, 2, and 3, H. B. Robinson, Unit 2, Response to Request for Additional Information Regarding the License Amendment Request to Revise Restrictive Technical Specification Surveillance Require7 July 2023Mcguire, Units 1 and 2, Oconee, Units 1, 2, and 3, H. B. Robinson, Unit 2, Response to Request for Additional Information Regarding the License Amendment Request to Revise Restrictive Technical Specification Surveillance RequireIncorporated by reference
Surveillance Frequency Control Program
Operational leakage
RA-23-0076, Supplement to Response to Request for Additional Information (RAI) Regarding McGuire Nuclear Station Unit 1 Spring, 2022 Outage Steam Generator Tube Inspection Report16 March 2023Supplement to Response to Request for Additional Information (RAI) Regarding McGuire Nuclear Station Unit 1 Spring, 2022 Outage Steam Generator Tube Inspection Report
RA-23-0024, Response to Request for Additional Information (RAI) for Relief Request for RPV Reactor Coolant System Welds28 February 2023Response to Request for Additional Information (RAI) for Relief Request for RPV Reactor Coolant System Welds
RA-23-0025, End of Cycle 28 (M1R28) Steam Generator Tube Inspection Report Response to Request for Additional Information (RAI)15 February 2023End of Cycle 28 (M1R28) Steam Generator Tube Inspection Report Response to Request for Additional Information (RAI)
RA-22-0147, Duke Energy Carolinas, LLC, and Duke Energy Progress, LLC, Response to Request for Additional Information (RAI) Regarding License Amendment Request for Relocating the Duke Energy Emergency Operations Facility13 May 2022Duke Energy Carolinas, LLC, and Duke Energy Progress, LLC, Response to Request for Additional Information (RAI) Regarding License Amendment Request for Relocating the Duke Energy Emergency Operations FacilityHealth Physics Network
High winds
RA-22-0102, Response to Request for Additional Information (RAI) Regarding Revision 1 of DPC-NE-1007-P, Conditional Exemption of the EOC Mtc Measurement Methodology7 April 2022Response to Request for Additional Information (RAI) Regarding Revision 1 of DPC-NE-1007-P, Conditional Exemption of the EOC Mtc Measurement MethodologyAffidavit
RA-22-0003, Response to Requests for Additional Information for Reactor Vessel Closure Stud Exam Extension Alternative31 January 2022Response to Requests for Additional Information for Reactor Vessel Closure Stud Exam Extension AlternativeBoric Acid
Hydrostatic
Finite Element Analysis
Aging Management
Stress corrosion cracking
License Renewal
Subsequent License Renewal
Liquid penetrant
Operational leakage
RA-21-0259, Response to Request for Additional Information for Request to Use Provisions of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI for Repair/ Replacement Activities in Accordance with 10 CFR 50.55a(g)(44 October 2021Response to Request for Additional Information for Request to Use Provisions of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI for Repair/ Replacement Activities in Accordance with 10 CFR 50.55a(g)(4
RA-21-0063, 1, 2; Catawba Nuclear Station 1, 2; H. B. Robinson Steam Electric Plant 2; Mcgguire Nuclear Station 1, 2; Oconee Nuclear Station 1, 2, 3; Shearon Harris Nuclear Power Plant 1 - Response to RAI Re Amend for Emergency Plan11 March 20211, 2; Catawba Nuclear Station 1, 2; H. B. Robinson Steam Electric Plant 2; Mcgguire Nuclear Station 1, 2; Oconee Nuclear Station 1, 2, 3; Shearon Harris Nuclear Power Plant 1 - Response to RAI Re Amend for Emergency PlanSafe Shutdown
Health Physics Network
Offsite Dose Calculation Manual
Tornado Missile
Met Tower
Emergency Lighting
Incorporated by reference
FLEX
Open House
Earthquake
Deep Dose Equivalent
Minimum staff
Fire Protection Program
Grace period
Siren
Overexposure
RA-21-0032, Duke Energy - Response to Requests for Additional Info for Request to Use a Provision of Later Edition & Addenda of the ASME Boiler & Pressure Vessel Code, Section XI for Repair/Replacement Activities in Accordance with 10 CFR 50.55a(g)(411 February 2021Duke Energy - Response to Requests for Additional Info for Request to Use a Provision of Later Edition & Addenda of the ASME Boiler & Pressure Vessel Code, Section XI for Repair/Replacement Activities in Accordance with 10 CFR 50.55a(g)(4)(
RA-21-0017, Response to Request for Additional Information Re License Amendment Request to Revise Tech Spec 3.8.1 to Reduce Emergency Diesel Generator Maximum Steady State Voltage29 January 2021Response to Request for Additional Information Re License Amendment Request to Revise Tech Spec 3.8.1 to Reduce Emergency Diesel Generator Maximum Steady State Voltage
RA-20-0087, Response to Request for Additional Information Regarding Request for Alternative in Accordance with 10CFR 50.55a(z)(1) to Delay the Update of the ASME Code of Record for the First Inspection Period2 April 2020Response to Request for Additional Information Regarding Request for Alternative in Accordance with 10CFR 50.55a(z)(1) to Delay the Update of the ASME Code of Record for the First Inspection Period
RA-19-0189, Supplement to Response for Request for Additional Information Regarding License Amendment Request Proposing Changes to the Technical Specifications 3.8.18 April 2019Supplement to Response for Request for Additional Information Regarding License Amendment Request Proposing Changes to the Technical Specifications 3.8.1
RA-19-0004, Response to NRC for Additional Information (RAI) Regarding License Amendment Request Proposing Changes to the Technical Specifications 3.8.1 for Catawba Nuclear Station, Units 1 and 27 March 2019Response to NRC for Additional Information (RAI) Regarding License Amendment Request Proposing Changes to the Technical Specifications 3.8.1 for Catawba Nuclear Station, Units 1 and 2Safe Shutdown
Time of Discovery
High winds
Mission time
Anticipated operational occurrence
Internal Flooding
Probabilistic Risk Assessment
Qualified Offsite Circuit
Functionality Assessment
FLEX
Large early release frequency
Operability Determination
Earthquake
Offsite Circuit
RA-19-0026, Response to Request for Additional Information (RAI) Regarding Proposed Alternative to the Depth Sizing Qualification Requirement of Appendix Viii, Supplements 2 and 10 (18-GO-001)11 February 2019Response to Request for Additional Information (RAI) Regarding Proposed Alternative to the Depth Sizing Qualification Requirement of Appendix Viii, Supplements 2 and 10 (18-GO-001)
RA-19-0005, Response to NRC Request for Additional Information Regarding Review Request of the Aging Management Program and Inspection Plan for the Reactor Vessel Internals to Implement MRP-227-A30 January 2019Response to NRC Request for Additional Information Regarding Review Request of the Aging Management Program and Inspection Plan for the Reactor Vessel Internals to Implement MRP-227-AAging Management
Design basis earthquake
Stress corrosion cracking
Affidavit
RA-18-0229, Response to NRC Request for Additional Information Regarding License Amendment Request Proposing Changes to the Technical Specification 3.8.13 December 2018Response to NRC Request for Additional Information Regarding License Amendment Request Proposing Changes to the Technical Specification 3.8.1Safe Shutdown
Time of Discovery
High winds
Mission time
Anticipated operational occurrence
Safe Shutdown Earthquake
Internal Flooding
Probabilistic Risk Assessment
Qualified Offsite Circuit
Functionality Assessment
FLEX
Seismically rugged
Surveillance Frequency Control Program
Large early release frequency
Operability Determination
Commercial Grade
Offsite Circuit
RA-18-0213, Response to the Second Request for Additional Information Regarding the License Amendment Request to Revise the Licensing Bases for Protection from Tornado-Generated Missiles1 November 2018Response to the Second Request for Additional Information Regarding the License Amendment Request to Revise the Licensing Bases for Protection from Tornado-Generated MissilesSafe Shutdown
Ultimate heat sink
Tornado Missile
Tornado-Generated Missile
Tornado Missile Protection
TORMIS
Earthquake
ML18191A56410 July 2018Attachment 3 - Response to NRC Request for Additional InformationSafe Shutdown
High winds
Safe Shutdown Earthquake
Internal Flooding
Probabilistic Risk Assessment
Earthquake
MNS-18-036, Redacted Response to the Request for Additional Information Regarding the License Amendment Request to Revise the Licensing Bases for Protection from Tornado Generated Missiles3 July 2018Redacted Response to the Request for Additional Information Regarding the License Amendment Request to Revise the Licensing Bases for Protection from Tornado Generated MissilesTornado Generated Missile
ML20052D9363 July 2018Response to Nrg Request for Additional Information (RAI) Regarding NAC Magnastor Cask Loaded to Incorrect Helium Backfill Density
MNS-17-048, Response to Request for Additional Information License Amendment Request Permanent Extension of Type a and Type C Leak Rate Test Frequencies12 December 2017Response to Request for Additional Information License Amendment Request Permanent Extension of Type a and Type C Leak Rate Test FrequenciesHigh winds
Internal Flooding
Probabilistic Risk Assessment
B.5.b
ML17349A15712 December 2017Response to Request for Additional Information Regarding License Amendment Request for Temporary Changes to Technical Specifications to Address the 'A' Train Nuclear Service Water System Non-Conforming ConditionSafe Shutdown Earthquake
Operating Basis Earthquake
Earthquake
RA-17-0039, Response to Request for Additional Information (RAI) Regarding 10 CFR 50.55a(z)(1)Proposed Alternative to ASME Section XI Threads in Flange Examination (17-GO-001)9 August 2017Response to Request for Additional Information (RAI) Regarding 10 CFR 50.55a(z)(1)Proposed Alternative to ASME Section XI Threads in Flange Examination (17-GO-001)Finite Element Analysis
Stress corrosion cracking
Weak link
RA-17-0035, Supplement to License Amendment Request Proposing Changes to Technical Specification 3.5.1, AC Sources - Operating.20 July 2017Supplement to License Amendment Request Proposing Changes to Technical Specification 3.5.1, AC Sources - Operating.Safe Shutdown
High winds
Ultimate heat sink
Anticipated operational occurrence
Internal Flooding
Probabilistic Risk Assessment
Large early release frequency
Offsite Circuit
MNS-17-030, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal28 June 2017Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary SubmittalHigh winds
Hydrostatic
FLEX
Fukushima Dai-Ichi
Spent Fuel Pool Instrumentation
Flood Hazard Mitigation Strategies Assessment
Flooding Focused Evaluation
RA-17-0030, Response to Request for Additional Information Regarding Application to Reverse Technical Specifications to Adopt Multiple Technical Specification Task Force Travelers8 June 2017Response to Request for Additional Information Regarding Application to Reverse Technical Specifications to Adopt Multiple Technical Specification Task Force Travelers
MNS-17-023, Response to Request for Additional Information to License Amendment Request Permanent Extension of Type a and Type C Leak Rate Test Frequencies25 May 2017Response to Request for Additional Information to License Amendment Request Permanent Extension of Type a and Type C Leak Rate Test Frequencies
CNS-16-066, Stations - Supplemental Information Regarding Reevaluated Seismic Hazard Screening and Prioritization Results - Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task..20 October 2016Stations - Supplemental Information Regarding Reevaluated Seismic Hazard Screening and Prioritization Results - Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task..Safe Shutdown
Ultimate heat sink
Safe Shutdown Earthquake
Probabilistic Risk Assessment
FLEX
B.5.b
Fukushima Dai-Ichi
Significance Determination Process
Seismically rugged
Large early release frequency
Spent Fuel Pool Instrumentation
Earthquake
Hardened vent
Backfit
ML16294A25413 October 2016Response to Request for Additional Information Regarding Relief Request 16-MN-002, Alternative to Defect Removal Prior to Performing Repair Activities on Nuclear Service Water System PipingVT-2
Through-Wall Leak
Through-Wall Leakage
RA-16-0035, Response to Request for Additional Information (RAI) Regarding Application for Emergency Operations Facility (EOF) Consolidation3 October 2016Response to Request for Additional Information (RAI) Regarding Application for Emergency Operations Facility (EOF) Consolidation
ML16244A06018 August 2016Response to Request for Addition Information to RR 16-MN-003
MNS-16-070, Response to Request for Additional Information to Relief Request 16-MN-00318 August 2016Response to Request for Additional Information to Relief Request 16-MN-003Non-Destructive Examination
License Renewal
Liquid penetrant
MNS-16-060, Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident18 August 2016Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi AccidentSafe Shutdown Earthquake
Probabilistic Risk Assessment
Fukushima Dai-Ichi
ML16230A00611 August 2016Response to Request for Additional Information Regarding License Amendment Request to Technical Specification 3.6.13, Ice Condenser DoorsSurveillance Frequency Control Program
RA-16-0027, Response to NRC Regulatory Issue Summary 2016-09 Preparation and Scheduling of Operator Licensing Examinations14 July 2016Response to NRC Regulatory Issue Summary 2016-09 Preparation and Scheduling of Operator Licensing ExaminationsGeneric Fundamentals Examination
MNS-16-056, License Amendment Request, One-Time Extension of Appendix J Type a Integrated Leakage Rate Test Interval, Response to Request for Additional Information30 June 2016License Amendment Request, One-Time Extension of Appendix J Type a Integrated Leakage Rate Test Interval, Response to Request for Additional InformationBoric Acid
Coatings
Aging Management
Moisture barrier
License Renewal
MNS-16-023, Response to Request for Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding License Amendment Request for Control Room Chilled Water System Technical Specifications16 March 2016Response to Request for Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding License Amendment Request for Control Room Chilled Water System Technical Specifications
ML16056A24218 February 2016Response to Request for Additional Information Regarding the License Amendment Request (LAR) to Change the Emergency Plan to Upgrade Emergency Action Levels Based on NEI 99-01, Revision 6Safe Shutdown
Ultimate heat sink
Offsite Dose Calculation Manual
Time to boil
Operating Basis Earthquake
Earthquake
MNS-16-005, Response to Request for Additional Information (RAI) During January 12, 2016, NRC Teleconference Pertaining to License Amendment Request for Nuclear Service Water System Allowed Outage Time Extension10 February 2016Response to Request for Additional Information (RAI) During January 12, 2016, NRC Teleconference Pertaining to License Amendment Request for Nuclear Service Water System Allowed Outage Time ExtensionSafe Shutdown
FLEX
Foreign Material Exclusion
Earthquake
MNS-16-008, Expedited Seismic Evaluation Process (ESEP) Closeout, Response to NRC Request for Information, Per 10 CFR 50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima..4 February 2016Expedited Seismic Evaluation Process (ESEP) Closeout, Response to NRC Request for Information, Per 10 CFR 50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima..Safe Shutdown Earthquake
Probabilistic Risk Assessment
FLEX
B.5.b
Fukushima Dai-Ichi
Earthquake
Power-Operated Valves
MNS-16-009, Response to NRC Letter Dated December 9, 2015, Request for Additional Information Regarding Request for Exemption from Title 10 of the Code of Federal Regulations (10 CFR) Part 74.19(c)4 February 2016Response to NRC Letter Dated December 9, 2015, Request for Additional Information Regarding Request for Exemption from Title 10 of the Code of Federal Regulations (10 CFR) Part 74.19(c)Exemption Request
RA-16-0006, Response to NRC Request for Additional Information (RAI) Regarding Application to Use Alternate Fission Gas Gap Release Fractions1 February 2016Response to NRC Request for Additional Information (RAI) Regarding Application to Use Alternate Fission Gas Gap Release FractionsTornado Missile
MNS-16-003, Response to Request for Additional Information (RAI) Regarding License Amendment Request to Revise Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation7 January 2016Response to Request for Additional Information (RAI) Regarding License Amendment Request to Revise Technical Specification 3.3.1, Reactor Trip System (RTS) InstrumentationSafe Shutdown
Safe Shutdown Earthquake
Grace period
ML15343A0127 December 2015Response to NRC Letter Dated 10/26/2015, Request for Additional Information Regarding License Amendment Request, Nuclear Service Water System Allowed Outage Time Extension.Internal Flooding
FLEX
Foreign Material Exclusion
Earthquake
MNS-15-093, Response to Request for Additional Information Regarding License Amendment Request Regarding Residual Heat Removal System13 November 2015Response to Request for Additional Information Regarding License Amendment Request Regarding Residual Heat Removal System
MNS-15-078, Response to NRC Letter Dated September 14, 2015, Request for Additional Information Regarding License Amendment Request, Nuclear Service Water System Allowed Outage Time Extension8 October 2015Response to NRC Letter Dated September 14, 2015, Request for Additional Information Regarding License Amendment Request, Nuclear Service Water System Allowed Outage Time ExtensionFLEX
Foreign Material Exclusion
Earthquake
MNS-15-077, Expedited Seismic Evaluation Process (ESEP) Report (CEUS Sites), Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima..8 October 2015Expedited Seismic Evaluation Process (ESEP) Report (CEUS Sites), Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima..Fukushima Dai-Ichi