| RA-23-0313, Baffle-Former Bolt (Bfb) Subsequent Inspection Interval Evaluation | 14 December 2023 | Baffle-Former Bolt (Bfb) Subsequent Inspection Interval Evaluation | Finite Element Analysis
Aging Management
Stress corrosion cracking
Affidavit |
| RA-23-0141, Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule | 12 July 2023 | Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule | License Renewal
Subsequent License Renewal |
| RA-23-0120, Supplemental Information Regarding Addition of Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.2 | 31 May 2023 | Supplemental Information Regarding Addition of Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.2 | |
| RA-23-0080, Refueling Outage 32 Steam Generator Tube Inspection Report Supplement Pursuant to Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube | 5 April 2023 | Refueling Outage 32 Steam Generator Tube Inspection Report Supplement Pursuant to Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube | Nondestructive Examination |
| RA-22-0302, Technical Specifications (TS) Section 5.6.6, Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range) | 1 November 2022 | Technical Specifications (TS) Section 5.6.6, Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range) | Post Accident Monitoring |
| RA-22-0239, Technical Specifications Section 5.6.6. Post Accident Monitoring Instrumentation Report for Inoperable Safety Valve Position (Primary) | 9 August 2022 | Technical Specifications Section 5.6.6. Post Accident Monitoring Instrumentation Report for Inoperable Safety Valve Position (Primary) | Post Accident Monitoring |
| RA-22-0165, Inservice Inspection Program Owner'S Activity Report for Refueling Outage 24 | 9 June 2022 | Inservice Inspection Program Owner'S Activity Report for Refueling Outage 24 | |
| RA-22-0134, Unit 1 Cycle 23 Mellla+ Eigenvalue Tracking Data | 25 May 2022 | Unit 1 Cycle 23 Mellla+ Eigenvalue Tracking Data | |
| RA-22-0017, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections | 6 January 2022 | Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections | Stress corrosion cracking
Eddy Current Testing |
| RA-21-0312, Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range) | 22 November 2021 | Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range) | Post Accident Monitoring |
| IR 05000261/2021005 | 25 August 2021 | Updated Inspection Plan for H. B. Robinson Steam Electric Plant, Unit 2 (Report 05000261/2021005) | Fitness for Duty
Cyber Security
Exemption Request
COVID-19 |
| RA-21-0198, Inservice Inspection Program Owner'S Activity Report for Refueling Outage 25 | 21 June 2021 | Inservice Inspection Program Owner'S Activity Report for Refueling Outage 25 | |
| RA-21-0176, Cycle 24 Mellla+ Eigenvalue Tracking Data | 7 June 2021 | Cycle 24 Mellla+ Eigenvalue Tracking Data | |
| RA-20-0353, Proposed Alternative to ASME Boiler & Pressure Vessel Code Section XI Requirements for Repair/Replacement of Service Water (SW) System Buried Piping in Accordance with 10 CFR 50.55a(z)(1) | 24 February 2021 | Proposed Alternative to ASME Boiler & Pressure Vessel Code Section XI Requirements for Repair/Replacement of Service Water (SW) System Buried Piping in Accordance with 10 CFR 50.55a(z)(1) | Fitness for Duty
Ultimate heat sink
Non-Destructive Examination
Safe Shutdown Earthquake
Coatings
Operating Basis Earthquake
Finite Element Analysis
Foreign Material Exclusion
Exemption Request
Affidavit |
| RA-20-0347, 10 CFR 71.95 Report on the 3-60B Cask | 16 November 2020 | 10 CFR 71.95 Report on the 3-60B Cask | |
| RA-19-0479, Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies | 31 December 2019 | Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies | Anticipated operational occurrence
Affidavit |
| RA-19-0411, Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies | 23 October 2019 | Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies | Shutdown Margin
Safety Limit Minimum Critical Power Ratio
Anticipated operational occurrence
Feedwater Controller Failure
MELLLA
Exclusive Use
Affidavit
Water rod |
| RA-19-0338, Pressure and Temperature Limits Report for Unit Nos. 1 and 2 | 15 August 2019 | Pressure and Temperature Limits Report for Unit Nos. 1 and 2 | Hydrostatic
Pressure and Temperature Limits Report
License Renewal
Power Uprate |
| RA-19-0243, Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies | 2 July 2019 | Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies | Stroke time
Post Accident Monitoring
Fuel cladding
Affidavit |
| RA-19-0223, Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.46 | 30 May 2019 | Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.46 | |
| RA-19-0240, Response to Request for Additional Information Regarding Advanced Framatome Methodologies License Amendment Request | 29 May 2019 | Response to Request for Additional Information Regarding Advanced Framatome Methodologies License Amendment Request | Feedwater Controller Failure
MELLLA
Fuel cladding
Power Uprate
Affidavit |
| RA-19-0139, Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies | 18 March 2019 | Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies | Shutdown Margin
Affidavit
Water rod |
| RA-18-0100, Request for License Amendment Regarding Application of Advanced Framatome Methodologies | 11 October 2018 | Request for License Amendment Regarding Application of Advanced Framatome Methodologies | Anticipated operational occurrence
Power Uprate
Affidavit |
| ML18249A159 | 13 August 2018 | Technical Requirements Manual, Revision 73 | Time of Discovery
Reactor Vessel Water Level
Ultimate heat sink
Offsite Dose Calculation Manual
Safe Shutdown Earthquake
Post Accident Monitoring
Hydrostatic
Operating Basis Earthquake
Functionality Assessment
Scram Discharge Volume
Process Control Program
Stress corrosion cracking
Excess Flow Check Valve
Operability Determination
Earthquake
Pressure Boundary Leakage
Offsite Circuit
Operational leakage |
| RA-18-0131, Technical Requirements Manual, Revision 66 | 13 August 2018 | Technical Requirements Manual, Revision 66 | Time of Discovery
Reactor Vessel Water Level
Ultimate heat sink
Non-Destructive Examination
Offsite Dose Calculation Manual
Safe Shutdown Earthquake
Post Accident Monitoring
Hydrostatic
Operating Basis Earthquake
Functionality Assessment
Scram Discharge Volume
Process Control Program
Stress corrosion cracking
Excess Flow Check Valve
Operability Determination
Earthquake
Pressure Boundary Leakage
Offsite Circuit
Operational leakage |
| RA-18-0024, Supplemental Information to Request for License Amendment to Revise the Technical Specifications to Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report | 29 May 2018 | Supplemental Information to Request for License Amendment to Revise the Technical Specifications to Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report | Pressure and Temperature Limits Report |
| BSEP 18-0044, Application of Dissimilar Metal Weld Full Structural Overlay - Reactor Pressure Vessel Nozzles N4A and N4D | 11 April 2018 | Application of Dissimilar Metal Weld Full Structural Overlay - Reactor Pressure Vessel Nozzles N4A and N4D | Weld Overlay
Dissimilar Metal Weld |
| RNP-RA/18-0024, Report of Changes Pursuant to 10 CFR 50.59(d)(2) | 2 April 2018 | Report of Changes Pursuant to 10 CFR 50.59(d)(2) | Unanalyzed Condition
Open Phase Condition
Fire Watch
Overspeed trip |
| RA-17-0040, Providing Methodology Reports DPC-NE-1008-P, Revision 0, DPC-NF-2010, Revision 3, and DPC-NE-2011-P, Revision 2. (Non-Proprietary Versions) | 15 August 2017 | Providing Methodology Reports DPC-NE-1008-P, Revision 0, DPC-NF-2010, Revision 3, and DPC-NE-2011-P, Revision 2. (Non-Proprietary Versions) | Boric Acid
Shutdown Margin
Anticipated operational occurrence
Post Accident Monitoring
Nondestructive Examination
Fuel cladding
Affidavit
Water rod |
| ML17024A036 | 31 December 2016 | Operating Data Report for 2016 | Temporary Modification
Biofouling
Power change
Coast down |
| ML16281A510 | 15 December 2016 | Staff Assessment of the Reactor Vessel Internals Aging Management Program Plans | Aging Management
Stress corrosion cracking
License Renewal |
| RNP-RA/16-0087, Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable High Range Containment Area Radiation Monitors | 31 October 2016 | Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable High Range Containment Area Radiation Monitors | Post Accident Monitoring |
| RNP-RA/16-0078, Technical Specifications Section 5.6.6, Post Accident Monitoring Instrumentation Report for Inoperable High Range Containment Area Radiation Monitors | 5 October 2016 | Technical Specifications Section 5.6.6, Post Accident Monitoring Instrumentation Report for Inoperable High Range Containment Area Radiation Monitors | Post Accident Monitoring |
| ML16280A200 | 5 October 2016 | Response to Request for Additional Information Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals | Aging Management
Power change
Power Uprate
Affidavit |
| RA-16-0024, Supplemental Information for License Amendment Request Regarding Methodology Report DPC-NE-3008-P | 3 October 2016 | Supplemental Information for License Amendment Request Regarding Methodology Report DPC-NE-3008-P | Safe Shutdown
Boric Acid
Shutdown Margin
Loop seal
Anticipated operational occurrence
Post Accident Monitoring
Nondestructive Examination
Annual Radiological Environmental Operating Report
Process Control Program
Fuel cladding
Coast down
Affidavit
Manual Operator Action |
| ML16287A422 | 26 September 2016 | FS1-0028339 Revision 1.0, Brunswick, Unit 1, Cycle 21 and Unit 2 Cycle 23 MELLLA SLMCPR Analyses with SAFLIM30 Methodology. | Anticipated operational occurrence
Minimum Critical Power Ratio
MELLLA |
| RNP-RA/16-0073, Response to Request for Additional Information Regarding License Amendment Request to Revise Reactor Coolant System Pressure and Temperature Limits | 14 September 2016 | Response to Request for Additional Information Regarding License Amendment Request to Revise Reactor Coolant System Pressure and Temperature Limits | Power Uprate |
| ML16223A725 | 17 August 2016 | Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Phase 2 of Order EA-13-109 (Severe Accident Capable Hardened Events) CAC Nos. MF4467 and MF4468) | FLEX
Fukushima Dai-Ichi
Earthquake
Hardened vent |
| ML18250A002 | 11 August 2016 | Technical Requirements Manual, Revision 70 | Time of Discovery
Reactor Vessel Water Level
High Radiation Area
Ultimate heat sink
Offsite Dose Calculation Manual
Safe Shutdown Earthquake
Post Accident Monitoring
Hydrostatic
Operating Basis Earthquake
Scram Discharge Volume
Process Control Program
Stress corrosion cracking
Excess Flow Check Valve
Operability Determination
Earthquake
Offsite Circuit
Operational leakage |
| ML18250A003 | 11 August 2016 | Technical Requirements Manual, Revision 63 | Time of Discovery
Reactor Vessel Water Level
High Radiation Area
Ultimate heat sink
Offsite Dose Calculation Manual
Safe Shutdown Earthquake
Post Accident Monitoring
Hydrostatic
Operating Basis Earthquake
Scram Discharge Volume
Process Control Program
Stress corrosion cracking
Excess Flow Check Valve
Operability Determination
Earthquake
Offsite Circuit
Operational leakage |
| ML16257A411 | 31 July 2016 | DUKE-0B21-1104-000(NP), Safety Analysis Report for Brunswick Steam Electric Plant, Units 1 and 2, Maximum Extended Load Line Limit Analysis Plus. | Unanalyzed Condition
Safety Limit Minimum Critical Power Ratio
Ultimate heat sink
Anticipated operational occurrence
Probabilistic Risk Assessment
Design basis earthquake
Flow Accelerated Corrosion
Feedwater Controller Failure
Large early release frequency
MELLLA
Stress corrosion cracking
Power Uprate
Affidavit |
| RNP-RA/16-0038, Transition Report, Revision 1, Transition to National Fire Protection Association Standard 805, with Attachments a, I, J, L, M, and V. Pages 22-174 | 25 May 2016 | Transition Report, Revision 1, Transition to National Fire Protection Association Standard 805, with Attachments a, I, J, L, M, and V. Pages 22-174 | Hot Short
Safe Shutdown
High winds
Mission time
Fire Barrier
Time to boil
Enforcement Discretion
Probabilistic Risk Assessment
Fire impairment
Operator Manual Action
Multiple Spurious Operation
Significance Determination Process
Thermoset
Large early release frequency
Exemption Request
Fire Protection Program
Fire Watch
Very Early Warning Fire Detection |
| RA-16-0023, Supplemental Information for License Amendment Request Regarding Methodology Report DPC-NE-1008-P | 4 May 2016 | Supplemental Information for License Amendment Request Regarding Methodology Report DPC-NE-1008-P | Shutdown Margin
Reactor Vessel Water Level
Anticipated operational occurrence
Post Accident Monitoring
Nondestructive Examination
Annual Radiological Environmental Operating Report
Process Control Program
Fuel cladding
Affidavit |
| ML15253A410 | 11 March 2016 | Enclosure 2 Screening Analysis Report | Ultimate heat sink
Tornado Missile
Fukushima Dai-Ichi
Earthquake
Generic Issues Program |
| ML16041A435 | 1 March 2016 | Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50 Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force | Safe Shutdown Earthquake
Probabilistic Risk Assessment
Operating Basis Earthquake
Fukushima Dai-Ichi
Earthquake |
| ML16257A406 | 31 December 2015 | ANP-3106(NP), Revision 2, Brunswick Units 1 and 2 LOCA-ECCS Analysis MAPLHGR Limit for Atrium 10XM Fuel for Mellla+ Operation. | Stroke time
MELLLA
Fuel cladding
Exclusive Use
Affidavit |
| RA-15-0042, Application to Revise Technical Specifications to Adopt Methodology Report DPC-NE-3008-P, Revision 0, Thermal-Hydraulic Models for Transient Analysis. | 19 November 2015 | Application to Revise Technical Specifications to Adopt Methodology Report DPC-NE-3008-P, Revision 0, Thermal-Hydraulic Models for Transient Analysis. | Safe Shutdown
Shutdown Margin
Loop seal
Anticipated operational occurrence
Post Accident Monitoring
Nondestructive Examination
Annual Radiological Environmental Operating Report
Process Control Program
Fuel cladding
Affidavit |
| RA-15-0047, Annual Report of Changes Pursuant to 10 CFR 50.46 | 17 November 2015 | Annual Report of Changes Pursuant to 10 CFR 50.46 | |
| ML15280A199 | 19 October 2015 | Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50 Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review | Safe Shutdown Earthquake
Fukushima Dai-Ichi
Earthquake |
| ML15275A290 | 30 September 2015 | Areva, Inc., - ANP-3397NP, Revision 0, Brunswick, Unit 2, Atrium 11 Lead Test Assemblies Design & Licensing Summary Report. | Shutdown Margin
Anticipated operational occurrence |