NMP2L2639, Supplement to License Amendment Request - Proposed Revision to Technical Specification in Response to GE Energy- Nuclear 10 CFR Part 21 Safety Communication SC05-03
NMP2L2584, License Amendment Request - Proposed Revision to Technical Specification in Response to GE Energy - Nuclear 1 O CFR Part 21 Safety Communication SC05-03
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
GO2-16-087, License Amendment Request for Changes to Technical Specification 2.1.1, Reactor Core SLs
1CAN021601, Cycle 26 Core Operating Limits Report, Revision 1
L-18-024, Core Operating Limits Report, Cycle 20, Revision 1
ULNRC-06264, Revision of TS 2.1.1.1 and 5.6.5 to Remove Uncertainties from the DNBR Safety Limit and Adopt Approved WCAP-14565-P-A Methodology
1CAN081504, Cycle 26 Core Operating Limits Report (COLR)
ULNRC-06215, Revision of TS 2.1.1.1 and 5.6.5 to Remove Uncertainties from the DNBR Safey Limit and Adopt Approved WCAP-14565-P-A Methodology
L-15-045, Core Operating Limits Report, Cycle 19, Revision 1
1CAN021501, Unit 1 - Submits Revision 0 of Cycle 26 Core Operating Limits Report
L-MT-14-088, Areva Atrium 10XM Fuel Transition License Amendment Request Supplement
JAFP-14-0123, Response to Request for Additional Information (RAI) for Low Pressure Safety Limit License Amendment
1CAN101408, Cycle 25 Core Operating Limits Report
L-14-107, Core Operating Limits Report, Cycle 19
NL-13-2035, License Amendment Request to Reduce the Reactor Steam Dome Pressure Specified in the Reactor Core Safety Limits
L-MT-14-003, Enclosures 2 & 3 to L-MT-14-003, ANP-3286NP, Rev. 0, Responses to RAI from Srxb on MNGP Transition to Areva Fuel & Areva Atrium 10XM Fuel Transition - Response to Requests for Additional Information
1CAN121301, Clarification of Proposed Change to Technical Specification 2.1.1.1 Reactor Core Safety Limits
JAFP-13-0115, Application to Revise Technical Specifications for Technical Specification Low Pressure Safety Limit
1CAN081301, Unit 1, ANO-1 Cycle 25 COLR, Revision 1
1CAN061303, Cycle 25 Core Operating Limits Report
1CAN061301, License Amendment Request, Revision to Technical Specification 2.1.1.1 Reactor Core Safety Limits
PLA-6915, Proposed Amendment No. 312 to Unit 1, and Proposed Amendment No. 284 to Unit 2 Low Pressure Safety Limit and Reference Changes
1CAN101202, Unit 1: Cycle 24 Core Operating Limits Report (Colr), Revision 5
1CAN081203, Cycle 24 Core Operating Limits Report (Colr), Revision 4
1CAN041201, Unit 1, ANO-1 Cycle 24 COLR, Revision 3
1CAN111103, Unit 1, ANO-1 Cycle 24 Core Operating Limits Report (Colr), Revision 1
1CAN101101, Submittal of Cycle 24 Core Operating Limits Report (COLR)
L-10-083, Core Operating Limits Report for Cycle 17
W3F1-2010-0051, Technical Specification Bases Update to the NRC for Period July 2, 2009 Through May 24, 2010
1CAN041005, Submittal of Rev. 1 to Cycle 23 Core Operating Limits Report
1CAN041001, Cycle 23 Core Operating Limits Report
RS-10-001, LaSalle, Units 1 and 2, Attachment 8 - NEDO-33485, Rev. 0, Safety Analysis Report for LaSalle County Station Units 1 and 2, Thermal Power Optimization.
W3F1-2009-0021, License Amendment Request to Revise the Departure from Nucleate Boiling Ratio (DNBR) Safety Limit
2CAN050901, License Amendment Request to Revise the Departure from Nucleate Boiling Ratio (DNBR) Safety Limit
2CAN110801, Technical Specification Change to Modify RCS Flow Verification
1CAN110801, Cycle 22 Core Operating Limits Report (COLR)
PLA-7837, Request for Due Date Extension to Respond to a Request for Additional Information (PLA-7837)
PLA-6250, Proposed License Amendment Nos. 285 and 253, for Extended Power Uprate Application Reactor Systems Technical Review Request for Additional Information Responses
1CAN050701, Arkansas - Unit 1 - Cycle 21 Core Operating Limits Report
NRC-2009-0433, FRN: General Notice. Biweekly Notice Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations
L-19-162, Submittal of Core Operating Limits Report, Cycle 21, Revision 1
1CAN120503, Unit 1, Cycle 20 Core Operating Limits Report (COLR) Per Technical Specification 5.6.5
PLA-7847, Submittal of Revised Topical Report to Support License Amendment Requesting Application of Advanced Framatome Methodologies
W3F1-2002-0072, Supplement to Amendment Request NPF-38-239 Revision of Letdown Line Break Dose Consequences
1CAN070203, Submittal of Revision to Arkansas Nuclear One, Unit 1 Core Operating Limits Report
PLA-7853, Ninety-Day Response to Request for Additional Information Regarding Proposed License Amendment Requesting Application of Advanced Framatome Methodologies PLA-7853
PLA-7910, Submittal of Unit 2 Cycle 21 Fuel Rod Design Report to Support License Amendment Requesting Application of Advanced Framatome Methodologies PLA-7910
NOC-AE-000471, Application for Amends to Licenses NPF-76 & NPF-80, Relocating cycle-specific RCS-related TS Parameter Limits to COLR
L-22-047, Unit No.1 - Core Operating Limits Report, Cycle 23, Revision O and Revision 1
2CAN018505, Application to Amend License NPF-6,revising DNBR Limit. Nonproprietary & Proprietary CEN-289(A), Revised Rod Bow Penalties..., Supporting Changes Encl.Proprietary Rept Withheld (Ref 10CFR2.790).Fee Paid
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.
PLA-7841, Thirty-Day Response to Request for Additional Information Regarding Proposed License Amendment Requesting Application of Advanced Framatome Methodologies
L-08-317, Core Operating Limits, and Pressure and Temperature Limits Report
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)
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
DCL-04-178, License Amendment Request 04-09, Relocation of Technical Specification Cycle Specific Parameters to the Core Operating Limits Report
L-16-179, License Amendment Request to Reduce the Reactor Steam Dome Pressure Specified in Technical Specification 2.1.1. Reactor Core Safety Limits
RS-16-076, Response to Request for Additional Information Regarding License Amendment Request to Reduce the Reactor Steam Dome Pressure Specified in the Technical Specification 2.1.1, Reactor Core Sls
RS-16-077, Response to Request for Additional Information Regarding Request for License Amendment to Reduce the Reactor Steam Dome Pressure Specified in the Technical Specification 2.1.1, Reactor Core Sls
RS-15-279, Request for License Amendment to Reduce the Reactor Steam Dome Pressure Specified in the Technical Specification 2.1.1, Reactor Core Sls
RS-15-108, Request for License Amendment to Reduce the Reactor Steam Dome Pressure Specified in the Technical Specification 2.1.1, Reactor Core Sls
RS-15-052, (EGC) Response to NRC Regulatory Issue Summary 2014-13, Planned Licensing Action Submittals for All Power Reactor Licensees
L-91-004, Additional Information Supporting the Request for License Amendment Related to 24-Month Fuel Cycle
HL-6328, Request for License Amendment Measurement Uncertainty Recapture Power Uprate, Enclosures 1 - 6
RS-11-099, Request for License Amendment Regarding Measurement Uncertainty Recapture (MUR) Power Uprate
SBK-L-04044, Changes to License Amendment Request 04-03, Application for Stretch Power Uprate
W3F1-2009-0042, Response to Request for Additional Information for License Amendment Revise Departure from Nucleate Boiling Ratio (DNBR) Safety Limit
PLA-7929, Submittal of Unit 2 Cycle 21 Reload Safety Analysis Report
CNL-21-039, Response to Request for Additional Information Re Application to Modify Technical Specification to Allow for Transition to Westinghouse RFA-2 Fuel (SQN-TS-20-09)
1CAN111104, Unit 1, ANO-1 Cycle 24 Core Operating Limits Report (Colr), Revision 2