BSEP 17-0032, Cycle 23 Core Operating Limits Report (COLR)
CNL-16-165, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 34, Revised Proposed License Conditions and Technical Specification Change
BSEP 16-0078, Request for License Amendment - Revision to Technical Specification 2.1.1.2 Minimum Critical Power Ratio Safety Limit
RA-15-0058, Response to Second NRC Request for Additional Information (RAI) Regarding Application to Revise Technical Specifications for Methodology Report DPC-NE-2005-P, Revision 5
L-2015-189, License Amendment Request 240, Conditional Exemption from End-of-Life Moderator Temperature Coefficient Measurement
CNL-15-056, Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Safety Limits (TS-506)
RA-15-0037, Transmittal of Response to NRC Request for Additional Information (RAI) Regarding Application to Revise Technical Specifications for Methodology Report DPC-NE-2005-P, Revision 5
BSEP 15-0036, Submittal of Core Operating Limits Report (Colr), Revision 1 for Cycle 20
L-15-087, Response to a Request for Additional Information Concerning Report of Errors in Evaluation Model
BSEP 15-0022, Cycle 22 Core Operating Limits Report (COLR)
GNRO-2015/00020, Revision to Letter GNRO-2014/00091 Dated January 6,2015 to Add Revision Number Eight (8) to Reference NEDC-33075P-A, GE Hitachi Boiling Water Reactor Detect and Suppress Solution - Confirmation Density
BSEP 15-0007, Request for License Amendments - Adoption of Topical Report ANP-10298P-A, Revision 1
NL-15-0188, Response to Request for Additional Information Regarding the License Amendment Request to Revise Technical Specification Surveillance Requirement 3.1.3.2 and Specification 5.6.5
GNRO-2014/00091, Revision to Technical Specification 5.6.5.b to Add Reference NEDC-33075P-A, GE Hitachi Boiling Water Reactor Detect and Suppress Solution - Confirmation Density
CNL-14-089, (Bfn), Units 1, 2, and 3 - Application to Modify Technical Specification 2.1.1, Reactor Core Safety Limits (BFN-TS-492)
PLA-7236, Response to Request for Additional Information on the Low-Pressure Safety Limit Amendment Request
CNL-14-081, Units, 1, 2 & 3, Revised Pages to Technical Specification Change TS-478-Addition of Analytical Methodologies to Technical Specification 5.6.5 and Revision of Tech Spec 2.1.1.2 in Support of ATRIUM-10 Xm Fuel Use at Browns Ferry
BSEP 14-0033, Cycle 20 Core Operating Limits Report (COLR)
L-PI-13-030, License Amendment Request (LAR) to Add a Methodology to Technical Specification (TS) 5.6.5, Core Operating Limits Report (Colr)
BSEP 13-0039, Submittal of Cycle 21 Core Operating Limits Report (COLR)
PLA-6915, Proposed Amendment No. 312 to Unit 1, and Proposed Amendment No. 284 to Unit 2 Low Pressure Safety Limit and Reference Changes
BSEP 12-0111, Response to Request for Additional Information Regarding the Core Operating Limits Report for Unit 1 Cycle 19
AEP-NRC-2012-56, Response to Request for Additional Information Regarding the License Amendment Request for Use of Optimized ZIRLO Fuel Rod Cladding
DCL-12-035, Report for 10 CFR 50.59, Changes, Test, and Experiments, for the Period January 1, 2010, Through December 31, 2011
RNP-RA/12-0014, Transmittal of Core Operating Limits Report
BSEP 12-0018, Submittal of Confirmatory Evaluation for Cycle 19
BSEP 11-0038, Renewed Facility Operating License and Cycle 20 Core Operating Limits Report
BSEP 18-0042, Cycle 22 Core Operating Limits Report (COLR)
RNP-RA/10-0096, Request for Technical Specifications Change Regarding Use of M5 Alloy Fuel
BSEP 10-0083, Additional Information Supporting Requests for License Amendments - Addition of Analytical Methodology Topical Report to Technical Specification 5.6.5, Core Operating Limits Report
RNP-RA/10-0043, Submittal of Revision 26 to FMP-001, Core Operating Limits Report (COLR)
BSEP 10-0057, Request for License Amendments - Addition of Analytical Methodology Topical Report to Technical Specification 5.6.5, Core Operating Limits Report
BSEP 10-0052, Request for License Amendments - Addition of Analytical Methodology Topical Report to Technical Specification 5.6.5, Core Operating Limits Report
BSEP 10-0050, Cycle 18 Core Operating Limits Report
RS-09-178, License Amendment Request Regarding Large Break Loss-of-Coolant Accident Analysis Methodology
PLA-6438, Proposed Amendment No. 274 to Unit 2: MCPR Safety Limits, Including Enclosure 2 to PLA-6438, PPL Evaluation of the Proposed Changes Unit 2 Minimum Critical Power Ratio Safety Limits, Non-Proprietary Version
RNP-RA/08-0112, Transmittal of Core Operating Limits Report for Cycle 26
RNP-RA/08-0103, Transmittal of Rev. 2 to Core Operating Limits Report for Cycle 25
BSEP 08-0097, Cycle 17 Core Operating Limits Report, Revision 1
BSEP 08-0093, Cycle 18 Core Operating Limits Report, Revision 1
RNP-RA/08-0079, Transmittal of Core Operating Limits Report
ULNRC-06328, Revision of TS 5.6.5, Core Operating Limits Report (Colr), to Allow the Use of the Paragon and Nexus Core Design Methods (LDCN 16-0011)
PLA-7837, Request for Due Date Extension to Respond to a Request for Additional Information (PLA-7837)
PLA-6230, Proposed License Amendment for Units 1 and 2, Extended Power Uprate Application & Supplement to Request for Additional Information Responses
BSEP 07-0034, Core Operating Limits Report, Revision 1 for Unit 1 Cycle 16
PLA-6199, Resubmittal of Proprietary Information
CPSES-200700605, License Amendment Request (LAR) 07-003, Revision to Technical Specifications 3.1, Reactivity Control Systems, 3.2, Power Distribution Limits, 3.3, Instrumentation, & 5.6.5b, Core Operating Limits Report
PLA-6132, Proposed Amendments No. 259 to Unit 2 License NPF-22: MCPR Safety Limits and Reference Changes
BSEP 06-0129, Request for License Amendments Regarding Linear Heat Generation Rate and Core Operating Limits Report References for Areva Np Fuel
L-PI-06-092, Supplement to License Amendment Request (LAR) to Incorporate Large Break Loss of Coolant Accident (LOCA) Analyses Using the Automated Statistical Treatment of Uncertainty Method
L-PI-06-070, Supplement to License Amendment Request to Incorporate Large Break Loss of Coolant Accident Analyses Using Automated Statistical Treatment of Uncertainty Method
ULNRC-05322, Application for Amendment to License No. NPF-30, Relocation of Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report Adoption of Industry Travelers TSTS-339 and TSTS-363
BSEP-06-0061, Core Operating Limits Report (Colr), Revision 2 for Plant Cycle 17
NL-06-1087, Response to Followup Questions from Staff from Teleconference Held on May 11, 2006 Regarding the Use of W(Z) Factors in the Unit 1 Core Operating Limits Report
RS-05-078, Submittal Letter and Attachments 1 Through 5, Request for License Amendment Regarding Transition to Westinghouse Fuel; Dresden Units 2 and 3, Quad Cities Units 1 and 2
RNP-RA/18-0060, Transmittal of Core Operating Limits Report
RA-18-0170, Unit 1 Cycle 22 and Unit 2 Cycle 23 Core Operating Limits Reports
RA-18-0241, Update to Request for License Amendment Regarding Application of Advanced Framatome Methodologies
RA-18-0202, Transmittal for NRC Confirmatory Calculations
RS-18-134, Request to Revise Technical Specifications 2.1.1 for Minimum Critical Power Ratio Safety Limits
NRC-2016-0273, Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations; Publication Date: January 3, 2017
NRC-2015-0240, Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing SUNSI and Order Imposing Procedures for Access to SUNSI - Publication Date: Novemb
NRC-2015-0104, Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication in April 28, 2015, Federal Register
NRC-2011-0216, September 20, 2011 Applications and Amendments to Facility Operating License Involving No Significant Hazards Considerations
NRC-2011-0040, Sholly Report for Fr Publication on February 22, 2011
RS-19-038, Supplement to the Application to Adopt TSTF-564, Safety Limit MCPR
RA-19-0240, Response to Request for Additional Information Regarding Advanced Framatome Methodologies License Amendment Request
RA-19-0241, Response to Request for Additional Information Regarding Advanced Framatome Methodologies License Amendment Request
NL-19-0709, Core Operating Limits Report, Cycle 21, Version 1, SNC Response to NRC Request for Additional Information
RA-19-0243, Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies
PLA-5990, Proposed Amendment No. 283 to Unit 1 MCPR Safety Limits and Reference Changes PLA-5990
BSEP-05-0139, Core Operating Limits Report (Colr), Revision 1 for Unit 2, Cycle 17
BSEP 05-0137, Core Operating Limits Report, Revision 2, Cycle 15
PLA-5967, Proposed Amendment No. 282 to Facility Operating License NPF-14: Proposed Change to Technical Specification 2.1.1.2 MCPR Safety Limit
NL-05-0068, Technical Specification Amendment Request to Incorporate Best Estimate LOCA Analysis Using ASTRUM
CPSES-200501532, (Cpses), Request for Additional Information Regarding License Amendment Request (LAR) Revision to Technical Specification (TS) 5.6.5, Core Operating Limits Report (COLR) - Response Letter Dated 07/20/2005
BSEP 05-0087, Core Operating Limits Report (COLR) for Unit 1 Cycle 15, Revision 1
RS-05-010, Application for Amendments to Renew Licenses DPR-19, DPR-25, DPR-29 & DPR-30, Supporting Transition to Westinghouse SVEA-96 Optima2 Fuel
RA-18-0100, Request for License Amendment Regarding Application of Advanced Framatome Methodologies
RA-19-0479, Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies
ET 11-0010, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.6.5, Core Operating Limits Report for Large Break Loss-of-Coolant Accident Analysis Methodology
1CAN090402, License Amendment Request to Support Use of M5 Fuel Cladding and Bhtp Departure from Nucleate Boiling Correlation, and 10 CFR 50.46 and 10 CFR Appendix K Exemption Request
PLA-5793, Proposed Amendment No. 233 to Unit 2 License NPF-22: MCPR Safety Limits and Reference Changes
BSEP 04-0091, Request for License Amendment - Addition of Tracg Methodology for Determining Core Operating Limits
BSEP 04-0015, Supplement to Request for License Amendments Regarding Core Flow Operating Range Expansion
BSEP 04-0012, Cycle 16 Core Operating Limits Report
L-PI-14-002, Supplement to License Amendment Request (LAR) to Add a Methodology to Technical Specification (TS) 5.6.5, Core Operating Limits Report(Colr)
PLA-5686, Proposed Amendment No. 259 to License NPF-14, and Proposed Amendment No. 224 to License NPF-22, Revised Response to Gl 94-02: Long-term Stability Solution
BSEP 03-0168, Cycle 14 Core Operating Limits Report
PLA-5694, Proposed Amendment Regarding Revised Main Turbine Bypass System Requirements
NRC 2003-0108, Revision of Pressure Temperature Limits Expiration Dates
BSEP 03-0148, Request for License Amendment Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ration Safety Limits and Revision to References in Technical Specification 5.6.5, Core Operating Limits Report
NRC 2003-0091, Request for Withdrawal, and Resubmittal, of Request for Exemptions to 10 CFR 50.61, Appendices G and H to 10 CFR 50, Approval of PTS Application for Pbnp Unit 2 and Withdrawal of Associated License Amendment Request (LAR) 235 and Submi
RA-19-0431, Application to Revise Technical Specifications to Adopt TSTF 564, Safety Limit MCPR
PLA-7847, Submittal of Revised Topical Report to Support License Amendment Requesting Application of Advanced Framatome Methodologies
PLA-5672, Proposed Amendment No. 221 to Unit 2 License NPF-22: Revised MCPR Safety Limits
PLA-5638, Proposed Amendment No. 256 to Unit 1, License NPF-14: MCPR Safety Limits & Reference Changes
L-PI-03-042, Supplement to License Amendment Request (LAR) Dated 03/25/2003, Safety Analyses Transition
GO2-03-063, Request for Amendment to Technical Specification 4.2.1 & 5.6.5.b, Corrections to Original Submittal
RS-20-010, Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR)
RS-03-049, Withdrawal of Request for a License Amendment to Modify the Method of Controlling Unfavorable Exposure Time Related to an Anticipated Transient Without Scram Event
PLA-5586, Supplemental Information for Proposed Amendment No. 211 to Unit 2 License NPF-22:MCPR Safety Limits & Reference Changes
RS-02-214, Response to Request for Additional Information Addressing Request for Amendment to Technical Specification 5.6.5, Core Operating Limits Report (Colr), for Addition of New Analytical Methodology
GO2-02-192, Request for Amendment to TS 4.2.1 and 5.6.5.b, Corrections to Original Submittal
RS-02-160, Request for Amendment to TS 5.6.5, Core Operating Limits Report for Addition of New Analytical Methodology
GO2-02-138, (WNP-2) Application for Amendment to License NPF-21, for Three Changes to Technical Specifications 4.2.1 & 5.6.5.b
PLA-5509, Supplement to Proposed Amendments 243 & 207 Adoption of NRC Approved Generic Changes to Improved Technical Specifications
BSEP 02-0108, Cycle 14 Core Operating Limits Report, Supplemental Reload Licensing Report & Loss-Of-Coolant Accident Analysis Report for Operation with Extended Power Uprate
RNP-RA/02-0066, Request for Amendment Re Increase Authorized Reactor Core Power Level from 2399 Mwt to 2339 Mwt (Approximately 1.7 Percent)
1CAN010202, License Amendment Request Re Technical Specification Change Request Concerning an Addition to the Core Operating Limits Report References
RA-20-0091, Unit 1 Cycle 23 Core Operating Limits Report (COLR
RS-02-030, Stations, License Amendment Request to Modify the Method of Controlling Unfavorable Exposure Time Related to an Anticipated Transient Without Scram Event
BSEP 02-0059, Unit 1 Cycle 14 Core Operating Limit Report, Supplemental Reload Licensing Report, Loss-of-Coolant Accident Analysis Report & Plant-Specific Emergency Core Cooling System (ECCS) Evaluation
PLA-7853, Ninety-Day Response to Request for Additional Information Regarding Proposed License Amendment Requesting Application of Advanced Framatome Methodologies PLA-7853
RA-20-0118, Cycle 23 Operating Limits Report (COLR) Revision 1
RA-20-0168, Cycle 23 Core Operating Limits Report (COLR) Revision 2
PLA-7910, Submittal of Unit 2 Cycle 21 Fuel Rod Design Report to Support License Amendment Requesting Application of Advanced Framatome Methodologies PLA-7910
RA-21-0094, Day Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Acceptable Loss of Coolant Evaluation Model
RA-20-0296, Letter from Sabrina Salazar (Duke Energy) to NRC Document Control Desk, Cycle 23 Core Operating Limits Report (Colr), Revision 2, Dated June 19, 2020
BSEP-99-0126, Application for Amend to License DPR-71,revising TS 2.1.1.2 to Remove Note That Limits Use of MCPR Safety Limit Values to Cycle 12 Operation
RS-21-113, Response to Supplemental Request for Information Related to Request for Licensing Amendment Regarding Transition to GNF3 Fuel
RS-22-006, Request to Expand Applicability of Prime Methods to Evaluate Fuel Centerline Melt and Cladding Strain Compliance for Framatome Fuel
RS-22-041, Withdrawal of License Amendment Request to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR) to Add References to NRC Approved Topical Report with Administrative Changes
RS-22-028, Supplement to Request to Expand Applicability of Prime Methods to Evaluate Fuel Centerline Melt and Cladding Strain Compliance for Framatome Fuel at Quad Cities
RA-22-0095, Unit 1 Cycle 24 Core Operating Limits Report (COLR)
RS-22-040, Response to Request for Additional Information Related to the License Amendment Request to Transition to GNF3 Fuel
HL-5698, Application for Amends to Licenses DPR-57 & NPF-5,revising TS 2.1.1.2 by Deleting Footnote Which Specifies That SLMCPRs Are for Cycle 18 Only & Deleting TS 5.6.5.b.2
CNL-22-066, Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for in Support of Atrium 11 Fuel Use Supplement 3, Response to Request for Additional Information
RS-22-095, Response to Request for Additional Information Regarding Request to Expand Applicability of GNF Thermal Mechanical Analysis Methods to Framatome Fuel
RA-22-0153, License Amendment Request to Add Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.2 and Update the List of Analytical Methods Used in the Determination of Core.
NL-22-0609, Response to NRC Requests for Information License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel
RA-22-0347, Transmittal of Core Operating Limits Report
RA-23-0021, Unit 2 Cycle 26 Core Operating Limits Report (COLR)
TXX-2304, (Cpnpp), Response to Request for Information for Application to Revise Technical Specifications to Apply the Westinghouse Full Spectrum Loss of Coolant Accident Evaluation Model LAR 22-002
PY-CEI-NRR-2325, Application for Amend to License NPF-58,applying Addl Conservatism by Modifying MCPR Safety Limit Values,As Calculated by Ge.Proprietary Addl Info Re 1.09 Cycle Specific Slmcpr,Encl.Proprietary Info Withheld
PMNS20231313, Notice of Meeting with Constellation Energy Generation, LLC (Constellation) Regarding a Future Amendment Request to Delete Byron and Braidwood Station Technical Specification 5.6.5.b.5
PMNS20231393, Notice of Meeting with Constellation Energy Generation, LLC (Constellation) Regarding a Future Amendment Request to Delete Byron and Braidwood Station Technical Specification 5.6.5.b.2
CNL-16-056, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 9, Responses to Requests for Additional Information
PLA-7841, Thirty-Day Response to Request for Additional Information Regarding Proposed License Amendment Requesting Application of Advanced Framatome Methodologies
L-PI-04-002, Supplement to License Amendment Request (LAR) Dated March 25, 2003, Safety Analyses Transition
RA-19-0380, Response to Request for Additional Information Regarding Advanced Framatome Methodologies License Amendment Request
CNL-15-002, Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Saftey Limits (TS-499)
RA-24-0058, Cycle 25 Core Operating Limits Report (COLR)
RS-09-036, Request for License Amendment to Technical Specification (TS) 3.4.5, RCS Leakage Detection Instrumentation, TS 5.6.5, Core Operating Limits Report (Color), and Renewed Facility Operating License
RA-18-0206, Supplement for License Amendment Request to Self-Perform Core Reload Design and Safety Analyses
RS-24-026, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 5.6.5, Core Operating Limits Report (COLR)
CPSES-200401948, License Amendment Request (LAR) 04-009 Revision to Technical Specification (TS) 5.6.5 Core Operating Limits Report (COLR)
CPSES-200200907, License Amendment Request, Revision to Technical Specifications (TS) TS 4.2 & 5.6.5
CPSES-200600123, License Amendment Request 05-06 Revision to Technical Specification 5.6.5 Revise Listing of LOCA and Non-LOCA Analysis Methodologies
NL-23-0152, License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-14483
RS-06-116, License Amendment Request and Exemption Requests to Allow Use of Areva Np Inc., Advanced Mark-BW(A) Fuel Assemblies
PLA-5467, Proposed Amendment No. 211 to Unit 2 License NPF-22: MCPR Safety Limits and Reference Changes
PLA-7881, Submittal of Unit 2 Cycle 21 Safety Limit Minimum Critical Power Ratio Report to Support License Amendment Requesting Application of Advanced Framatome Methodologies (PLA-7881)
RS-22-065, License Amendment Request Regarding Transition to GNF3 Fuel
BSEP 08-0047, Cycle 17 Core Operating Limits Report
PLA-5563, Response to Request for Additional Information for Proposed Amendment No. 211 to Unit 2, MCPR Safety Limits and Reference Changes
CNL-22-044, To Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535)
NL-16-165, Browns Ferry Nuclear Plant, Units 1, 2, & 3 - Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 34, Revised Proposed License Conditions and Technical Specificat
BSEP 17-0108, Request for Emergency License Amendment - Technical Specification 3.8.1, AC Sources - Operating, One-Time Extension of Emergency Diesel Generator Completion Times and Suspension of Surveillance Requirements
AEP-NRC-2009-23, License Amendment Request Regarding Large Break Loss-of-Coolant Accident Analysis Methodology
NMP2L2556, Response to Request for Additional Information, License Amendment Request for Maximum Extended Load Line Limit Analysis Plus
CNL-24-013, Cycle 22 Reload Analysis Report
CNL-22-100, To Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3,in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535)
CP-202200355, Application to Revise Technical Specifications to Apply the Westinghouse Full Spectrum Loss of Coolant Accident Evaluation Model LAR 22-002
CNL-18-011, Tennessee Valley Authority Response to NRC Request for Additional Information Related to BFN Application to Revise Technical Specification 5.5.12 Primary Containment Leakage Rate Testing Program (BFN-TS-497)
GO2-98-049, Provides Mod to 971204 Request for Amend to Licnese NPF-21, Establishing Interim SLMCPR for Siemens Power Corp ATRIUM-9X Fuel Applicable to Cycle 14 Only,As Identified by T Huang (NRR) During 980211 Site Visit
RS-16-034, License Amendment Request and 10 CFR 50.12 Exemption Request for the Use of Optimized ZIRLO Fuel Rod Cladding
NL-16-0034, License Amendment Request and 10 CFR 50.12 Exemption Request, Optimized ZIRLO Fuel Rod Cladding
BSEP 16-0001, Status of Confirmatory Evaluation for Unit 1, Cycle 21
RA-15-0020, License Amendment Request and 10 CFR 50.12 Exemption Request for Use of Optimized ZIRLO Fuel Rod Cladding
RS-13-288, Request for License Amendment to Technical Specifications Section 5.6.5. Core Operating Limits Report
BSEP 12-0104, Response to Request for Additional Information Regarding License Amendment Request for Addition of Analytical Methodology Topical Report to Technical Specification 5.6.5, Core Operating Limits Report (Colr), and Rev. to
RS-12-036, License Amendment Request to Technical Specifications Section 5.6.5, Core Operating Limits Report (Colr)
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
BSEP 11-0040, Unit I & 2, Additional Information Supporting License Amendment Request to Add Analytical Methodology ANP-10298PA to Technical Specification 5.6.5,Core Operating Limits Report (COLR) (NRC TAC ME3856 & Me.
BSEP 11-0031, Areva Report ANP-2992NP, Revision 0, Areva Response to Additional RAI on the Brunswick RODEX4 LAR
NL-20-0170, Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC
BSEP 09-0054, Core Operating Limits Report, Revision 2 for Unit 1 Cycle 17
RS-09-134, Supplemental Information Concerning Request for License Amendment to Revise TS 3.4.5, RCS Leakage Detection Instrumentation, TS 5.6.5, Core Operating Limits Report, & Renewed Facility Operating
PLA-6209, Susquenhanna - Proposed License Amendment No. 285 for Unit 1 Operating License NPF-14 and Proposed License Amendment No. 253 for Unit 2 Operating License NPF-22 Extended Power Uprate Application Reactor Systems Technical Review Request for
BSEP 07-0026, Enclosure 1 - Design Calc. 21321-1267, Revision 0, Brunswick, Unit 2, Cycle 18 Core Operating Limits Report March 2007
RBG-46583, License Amendment Request, Changes to the Analytical Methods Referenced in Technical Specification 5.6.5, Core Operating Limits Report (Colr)
L-PI-06-045, License Amendment Request (LAR) to Incorporate Large Break Loss of Coolant Accident (LOCA) Analyses Using ASTRUM)
DCL-05-146, License Amendment Request 05-07 Revision to Technical Specification 5.6.5, Core Operating Limits Report (Colr)
CPSES-200500919, (CPSES) License Amendment Request (LAR) 05-002, Revision to Technical Specification (TS) 5.6.5, Core Operating Limits Report (Colr)
BSEP-05-0024, Design Calculation No. 2821-1064, Rev 0, Brunswick Unit 2, Cycle 17 Core Operating Limits Report, February 2005
RS-05-012, Request for Amendment to Technical Specification Section 5.6.5, Core Operating Limits Report (Cola)
CPSES-200600097, Revision to Technical Specifications 3.3.1, Reactor Trip System Instrumentation, 3.3.2, ESFAS Instrumentation, 3.4.5, RCS Loops-Mode 3, 3.4.6, RCS Loops-Mode 4, and 3.4.7, RCS Loops-Mode 5, Loops Filled
05000293/LER-2003-001, Re Manual Scram & Completion of a Required Shutdown Due to Recirculation Motor-Generator Trip & Runback
RS-06-044, Request for License Amendment to Technical Specification 5.6.5, Core Operating Limits Report (Colr)
RA-24-0286, Transmittal of Core Operating Limits Report
BSEP 10-0133, Response to Additional Information Request Supporting License Amendment Requests for Addition of Analytical Methodology Topical Reports to Technical Specification 5.6.5 (NRC TAC Nos. ME3856, ME3857, ME3858, and ME3859)
DCL-15-047, License Amendment Request 15-02 Revision of Updated Final Safety Analysis Report for Beacon Power Distribution Monitoring System Methodology and Technical Specification 5.6.5. Core Operating Limits Report (Colr), For.
PY-CEI-NRR-2218, Documents Agreement to NRC Proposed Clarifications That Would Add Note to TS 2.1.1.2 & Add Footnote to TS 5.6.5.b. Revised TS Pages W/Clarifications,Encl
SVP-25-001, CFR 50.59/10 CFR 72.48 Summary Report
CNL-21-050, License Amendment Request Regarding Criticality Safety Analysis of Spent Fuel Pool Storage of Atrium 11 Fuel (TS-534)
RA-21-0098, Unit 2 Cycle 25 Core Operating Limits Report (COLR) and Reload Safety Analysis Report (RSAR)
RA-20-0382, 30-Day Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Acceptable Loss of Coolant Evaluation Model
RA-19-0162, Cycle 24 Core Operating Limits Report (COLR)
DCL-25-029, License Amendment Request 25-01: Application to Utilize Optimize ZIRLO for Improved Fuel Rod Cladding Performance
RA-25-0071, Cycle 27 Core Operating Limits Report (COLR)
NL-21-0962, Core Operating Limits Report, Cycle 24, Version 1
PLA-7929, Submittal of Unit 2 Cycle 21 Reload Safety Analysis Report
CNL-21-061, Information Transmittal for NRC Confirmatory Calculations Regarding Transition to Atrium 11 Fuel
CNL-24-062, Cycle 16 Reload Analysis Report
CNL-22-096, To Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3, in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535)
CNL-22-076, To Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 in Support of Atrium 11 Fuel
CPSES-200701323, License Amendment Request 07-006, Revision to Technical Specification 3.1.4, Rod Group Alignment Limits, Table 3.3.1-1, Reactor Trip System Instrumentation, Table 3.3.2-1, Engineered Safety Feature Actuation System
RA-25-0023, Cycle 25 Core Operating Limits Report (Colr), Revision 1
RS-25-089, Additional Response to Request for Additional Information Related to License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46
RS-25-088, Response to Request for Additional Information Related to License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2 to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46
L-PI-06-005, License Amendment Request for Miscellaneous Technical Specification Administrative Changes
RA-25-0014, License Amendment Request to Adopt the Full Spectrum Loss of Coolant Accident Methodology and Axiom Fuel Cladding Topical Reports and Associated 10 CFR 50.46 Exemption Request for Use of Axiom Fuel Cladding
RA-25-0197, Cycle 25 Core Operating Limits Report (Colr), Revision 2