| 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 |
| ML022110343 | 31 January 2002 | Caldon, Inc Engineering Report: ER-267N, Bounding Uncertainty Analysis for Thermal Power Determination at CP&L Robinson Nuclear Power Station Using the LEFM Check Plus System | Power Uprate
Affidavit |
| ML023040268 | 19 September 2002 | Part 4 of 4 - Westinghouse Technology Manual, Course Outline for R-104P and Course Manual | Safe Shutdown
Boric Acid
Shutdown Margin
Ultimate heat sink
Power-Operated Valves |
| ML030520269 | 15 February 2003 | Follow-up Report, Reference Event #39516 | |
| ML031120705 | 18 April 2003 | Review of 90-day Steam Generator Tube Inservice Inspection Report for a Refueling Outage in 2001 | |
| ML031700027 | 6 June 2003 | Submittal of 10-O Report | Boric Acid
Power Uprate |
| ML031890936 | 10 July 2003 | Relaxation of the Order, Exercising Enforcement Discretion, and Extension of the Time to Submit an Answer or Request a Hearing Regarding Order EA-03-038, Fitness-for-Duty Enhancements for Nuclear Security Force Personnel for Brunswick, Crys | Enforcement Discretion |
| ML032471632 | 22 August 2003 | Submittal of 10-Q Report | Boric Acid |
| ML041460246 | 19 May 2004 | Q Report for Period Ending 03/31/2004 | |
| ML050700408 | 20 February 2004 | EMF-3030(NP), Revision 0, Robinson Nuclear Plant, Realistic Large Break LOCA Analysis, February 2004, Non-Proprietary Version | Loop seal
Exclusive Use
Affidavit |
| ML082190013 | 7 August 2008 | Monthly Operating Reports Second Quarter 2008 | Reserve Station Service Transformer
Power change |
| ML101930417 | 6 May 2010 | Tritium Database Report | Offsite Dose Calculation Manual
Hydrostatic |
| ML112411358 | 23 September 2011 | Final Precursor Analysis: Concurrent Unavailabilities - EDG B Inoperable Due to Failed Output Breaker and EDG a Unavailable Due to Testing and Maintenance | Significance Determination Process |
| ML112411359 | 23 September 2011 | Final Precursor Analysis: Electrical Fault Causes Fire and Subsequent Reactor Trip with a Loss of Reactor Coolant Pump Seal Injection and Cooling | Fitness for Duty
Arc flash
Significance Determination Process
Preliminary White Finding |
| ML112800528 | 29 December 2010 | NRC 2011 Hb Robinson | |
| ML12068A133 | 23 February 2012 | Calculation RNP-M/MECH-1815, Revision 1, Evaluation of Emergency Diesel Generator Starting Capability at 150 PSIG | Overspeed trip |
| ML121070716 | 17 May 2012 | Letter Report on the Evaluation of Cables from the HEAF Fire Event at the H.B. Robinson Steam Electric Plant | Arc flash |
| ML12278A399 | 31 August 2012 | WCAP-17077-NP, Rev 1, PWR Vessel Internals Program Plan for Aging Management of Reactor Internals at Robinson Nuclear Plant | Operating Basis Earthquake
Nondestructive Examination
Functionality Assessment
Aging Management
Stress corrosion cracking
Eddy Current Testing
License Renewal
EVT-1 |
| ML12331A175 | 26 November 2012 | Draft Bypass Fiber Quantity Test Plan | |
| ML13267A212 | 30 September 2013 | Enclosure 1, Transition Report - NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition | Hot Short
Safe Shutdown
Boric Acid
High winds
Shutdown Margin
Mission time
Fire Barrier
Time to boil
Safe Shutdown Earthquake
Enforcement Discretion
Probabilistic Risk Assessment
Coatings
Fire impairment
Operator Manual Action
Multiple Spurious Operation
Emergency Lighting
B.5.b
Significance Determination Process
Thermoset
Large early release frequency
Exemption Request
Earthquake
Fire Protection Program
Fire Watch
Very Early Warning Fire Detection
Manual Operator Action |
| ML13270A176 | 24 September 2013 | Redacted - Office of Nuclear Reactor Regulation (NRR) Reactor Systems Branch (Srxb) Support of Region II Inspection of H. B. Robinson Treatment of Voids in Systems That Are Important to Safety | Stroke time
Past operability
Functionality Assessment
Operability Determination
GOTHIC
Operability Assessment
Affidavit |
| ML13365A291 | 19 February 2014 | Interim Staff Evaluation Regarding Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) | Safe Shutdown
Boric Acid
High winds
Shutdown Margin
Ultimate heat sink
Tornado Missile
Safe Shutdown Earthquake
Internal Flooding
Operating Basis Earthquake
Emergency Lighting
FLEX
Fukushima Dai-Ichi
Job Performance Measure
Frazil ice
Earthquake
GOTHIC |
| ML14027A063 | 24 January 2014 | Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for H. B. Robinson Steam Electric Plant, Unit 2, TAC No.: MF0720 | Safe Shutdown
Boric Acid
High winds
Shutdown Margin
Ultimate heat sink
Tornado Missile
Safe Shutdown Earthquake
Internal Flooding
Operating Basis Earthquake
Emergency Lighting
FLEX
Fukushima Dai-Ichi
Job Performance Measure
Frazil ice
Earthquake
GOTHIC |
| ML15253A410 | 11 March 2016 | Enclosure 2 Screening Analysis Report | Ultimate heat sink
Tornado Missile
Fukushima Dai-Ichi
Earthquake
Generic Issues Program |
| 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 |
| 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 |
| ML16281A510 | 15 December 2016 | Staff Assessment of the Reactor Vessel Internals Aging Management Program Plans | Aging Management
Stress corrosion cracking
License Renewal |
| ML18288A369 | 31 October 1990 | ANF-88-054(NP)(A), PDC-3: Advanced Nuclear Fuels Corp Power Distribution Control for PWRs & Application of PDC-3 to Hb Robinson Unit 2. | |
| NRC Generic Letter 1979-45 | 25 September 1979 | NRC Generic Letter 1979-045: Transmittal of Reports Regarding Foreign Reactor Operation Experiences | Boric Acid |
| RA-05-0104, Transmittal of Core Operating Limits Report | 10 October 2005 | Transmittal of Core Operating Limits Report | Shutdown Margin |
| RA-15-0031, Application to Revise Technical Specifications for Methodology Report DPC-NE-1008-P, Revision 0, Nuclear Design Methodology Using CASMO-5/Simulate-3 for Westinghouse Reactors. | 19 August 2015 | Application to Revise Technical Specifications for Methodology Report DPC-NE-1008-P, Revision 0, Nuclear Design Methodology Using CASMO-5/Simulate-3 for Westinghouse Reactors. | Shutdown Margin
Anticipated operational occurrence
Post Accident Monitoring
Nondestructive Examination
Annual Radiological Environmental Operating Report
Process Control Program
Fuel cladding
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 | |
| 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 |
| 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 |
| 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 |
| 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-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 |
| 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-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-22-0302, 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-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-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-23-0141, 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-23-0313, 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 |
| RNP-RA/02-0028, Request for Technical Specifications Change Re One-Time Extension of Containment Type a Test Interval | 26 March 2002 | Request for Technical Specifications Change Re One-Time Extension of Containment Type a Test Interval | |
| RNP-RA/02-0164, Part 17 of 17, CD-ROM Providing the Review Tool Supporting the Application for Renewal of Operating License | 6 November 2002 | Part 17 of 17, CD-ROM Providing the Review Tool Supporting the Application for Renewal of Operating License | |
| RNP-RA/02-0172, Steam Generator Tube Plugging During Refueling Outage 21 | 11 November 2002 | Steam Generator Tube Plugging During Refueling Outage 21 | |
| RNP-RA/03-0012, Request for Relief Pertaining to Examination Coverage Less than Essentially 100 Percent | 11 February 2003 | Request for Relief Pertaining to Examination Coverage Less than Essentially 100 Percent | |
| RNP-RA/03-0031, Response to Request for Additional Information Re Application for Renewal of Operating License, Attachment III, Pages 356 - 504 | 28 April 2003 | Response to Request for Additional Information Re Application for Renewal of Operating License, Attachment III, Pages 356 - 504 | Boric Acid
Non-Destructive Examination
Coatings
Nondestructive Examination
Incorporated by reference
Aging Management
Flow Accelerated Corrosion
Eddy Current Testing
Moisture barrier
License Renewal
Maintenance Rule Program
Pressure Boundary Leakage
Through-Wall Leakage
Thermal fatigue |