Pages that link to "RA-22-0165, Inservice Inspection Program Owner'S Activity Report for Refueling Outage 24"
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The following pages link to RA-22-0165, Inservice Inspection Program Owner'S Activity Report for Refueling Outage 24:
Displayed 50 items.
- RA-18-0170, Unit 1 Cycle 22 and Unit 2 Cycle 23 Core Operating Limits Reports (← links)
- RA-18-0144, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Report (← links)
- RA-18-0079, Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO (← links)
- RA-18-0110, Request for One-Time Allowance to Submit License Amendment Request Referencing Topical Report Draft Safety Evaluation (← links)
- RA-18-0101, Unit 1 Cycle 22 and Unit 2 Cycle 23 Reload Safety Analysis Reports (← links)
- RA-18-0067, Inservice Inspection Program Owner'S Activity Report for Unit 1 Refueling Outage 22 (← links)
- RA-15-0036, Annual Report of Changes Pursuant to 10 CFR 50.46 (← links)
- RA-12-015, Carolina Power & Light Company'S Answer to March 12, 2012, Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents (Order Number EA-12-050) (← links)
- RA-09-016, Request for Exemptions from Physical Security Requirements (← links)
- RA-09-020, NRC Correspondence Distribution List Update (← links)
- RA-19-2019, Brunswick 2019-301 Post-Exam Comments (← links)
- RA-19-0083, Reactor Operator and Senior Reactor Operator License Post-Examination Documentation (← links)
- RA-19-0029, Revision to Radiological Emergency Response Plan Implementing Procedure (← links)
- RA-18-0246, Revised Response to Request for Additional Information: Request for License Amendment to Revise the Technical Specifications to Relocate the Pressure- Temperature Limit Curves to a Pressure & Temperature .. (← links)
- RA-18-0241, Update to Request for License Amendment Regarding Application of Advanced Framatome Methodologies (← links)
- ML18249A159 (← links)
- RA-19-0139, Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies (← links)
- RA-19-0015, Request for License Amendment: Surveillance Requirements for Safety Relief Valves (← links)
- RA-18-0148, License Amendment Request to Revise Units 1 and 2 Technical Specification 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies (← links)
- RA-19-0010, Response to NRC RAI Re Application to Adapt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (← links)
- RA-19-0089, Response to Request for Additional Information - Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure... (← links)
- RA-18-0258, (Bsep), Unit Nos. 1 and 2 - Ninth Six-Month Status Report in Response to June 6, 2013, Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident... (← links)
- RA-18-0234, (Bsep), Unit Nos. 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-269, Allow Administrative Means of Position Verification for Locked or Sealed Valves. (← links)
- RA-18-0131, Technical Requirements Manual, Revision 66 (← links)
- RA-18-0132, Report of 10 CFR 50.59 Evaluations, 10 CFR 72.48 Evaluations, and Commitment Changes (← links)
- RA-18-0041, (Bsep), Unit Nos. 1 and 2 - Eighth Six-Month Status Report in Response to June 6, 2013, Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident... (← links)
- RA-18-0052, (Bsep), Unit Nos. 1 and 2, Registration for Use of General License Spent Fuel Casks (← links)
- RA-18-0017, (Bsep), Unit No. 1, Completion of Required Action for NRC Order EA-13-109, Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (← links)
- RA-19-0157, Supplement to Request for License Amendment Technical Specification 3.8.3, Diesel Fuel Oil, One-Time Extension of Main Fuel Oil Storage Tank Completion Time (← links)
- RA-19-0162, Cycle 24 Core Operating Limits Report (COLR) (← links)
- RA-19-0150, Response to Request for Additional Information - Request for License Amendment - Technical Specification 3.3.8.1, Loss of Power (LOP) Instrumentation (← links)
- BSEP 18-0044, Application of Dissimilar Metal Weld Full Structural Overlay - Reactor Pressure Vessel Nozzles N4A and N4D (← links)
- BSEP 16-0056, ANP-3108(NP), Revision 1, Applicability of Areva BWR Methods to Brunswick Extended Power Flow Operating Domain. (← links)
- BSEP 14-0131, Expedited Seismic Evaluation Process Report in Response to 10 CFR 50.54(f) Request for Information Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-lchi Accident (← links)
- BSEP 14-0101, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors (← links)
- BSEP 14-0093, Report of 10 CFR 50.59 Evaluations and Commitment Changes (← links)
- BSEP 14-0028, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi A (← links)
- BSEP 13-0030, Overall Integrated Plan in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (← links)
- BSEP 13-0002, Technical Data Record, 12-9197120-000, Brunswick SAFLIM3D LAR Support - Calculation Error Impact (← links)
- BSEP 12-0127, Recommendation 2.3 Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident (← links)
- BSEP 12-0133, Document No. 51-9195058-000, Areva Input to Process Energy: Follow-Up to SAFLIM3D LAR Request for Additional Information 3, Enclosure 3 to BSEP 12-0133 (← links)
- BSEP 12-0128, Special Report - Technical Requirements Manual Section 3.4, Accident Monitoring Instrumentation (← links)
- BSEP 12-0040, ANP-3061(NP), Revision 0, Brunswick, Unit 1, Cycle 19 Reload Safety Analysis. (← links)
- BSEP 12-0031, Areva Document ANP-3086(NP), Brunswick Units 1 and 2 SLMCPR Operability Assessment Critical Power Correlation for Atrium 10XM Fuel - Improved K-factor Model, Enclosure 20 to BSEP 12-0031 (← links)
- BSEP 11-0038, Renewed Facility Operating License and Cycle 20 Core Operating Limits Report (← links)
- BSEP 11-0031, Areva Report ANP-2992NP, Revision 0, Areva Response to Additional RAI on the Brunswick RODEX4 LAR (← links)
- BSEP 10-0141, ANP-2978NP, Rev. 0, Areva Responses to RAIs on the Atrium 10XM Compliance Audit and Brunswick Lars. (← links)
- BSEP 10-0118, ANP-2950NP, Revision 0, Atrium 10XM Fuel Rod Thermal and Mechanical Evaluation for Brunswick Unit 2 Cycle 20 Reload BRK2-20. (← links)
- BSEP 10-0097, Report of 10 CFR 50.59 Evaluations and Commitment Changes (← links)
- RA-19-0152, Response to NRC Request for Additional Information (RAI) Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures,Systems, and Components (Sscs) for Nuclear Power Reactors. (← links)