GNF3
GNF3# QUERYab7d00160db58dfc0f729e9a7c80b29f
GNF3# QUERY98bfd5d8255dec5a5ef09d7af39de29d
GNF3# QUERY16a6906dc4366db397de6653acadccb7
GNF3 Calvert Cliffs
GNF3# QUERY2a1da90050908eaac9973fa6b60b2fc5
GNF3# QUERY21b776c2af3e3fbff418ae06d491afe5
GNF3# QUERYeff30cb9e4bc408b065ac05134b3c651
GNF3# QUERYa9f427f8cc4fc21e7d7c4e0ad5a7b4af
GNF3 Nine Mile Point
GNF3# QUERY796902a6fe6a2e6cf320da19da3beb08
GNF3# QUERYd9deb043899f8c1d9e7096773dfb25af
GNF3# QUERY5e518ed004cb7d6ad46c7a6593d2bbc7
NRC Region 1 false
GNF3# QUERY7a67bed0767cfcf0d82172f65aac0556
GNF3# QUERY71cfd8bbb0895f21f1384ef2ac5862cc
GNF3# QUERY71fa09bd6d3ac8a7197e9dba457bcdd4
GNF3# QUERY1b27d69f902fe729f12f9cead398dca6
GNF3 Three Mile Island
GNF3 Vermont Yankee
GNF3# QUERYa0e65fc3d5f57e7ec54bbd52f0579ab3
GNF3# QUERY4ae0ecc7ea9bd483f18681f2dae89d99
GNF3# QUERY6bdea1e2b95b1cca1d9b2f438d535f25
NRC Region 1 true
GNF3# QUERY2fd4bced5a3364fc1a8471abf80dc9b2
GNF3# QUERY17d75fe4ab8d6352dec5105d7eb12d44
GNF3# QUERY50ce512dbc51c6a83cd68f100f7944cb
GNF3# QUERY525970b40b8db1ac31de2e4d21ea3df7
GNF3# QUERY2bb985adab56be80b19ae95bb152c7bd
GNF3# QUERY36b202adf501b7878c39dea8c8b10af1
GNF3# QUERYe8e3c4fb731ca28f264d09c1e58bbfad
GNF3# QUERY8fd70db2c6624e3f59c699da4f8e363d
GNF3# QUERY02e6100f171eb27ab6fad57df745b1f7
GNF3# QUERY22cf75535ead5168edc51c1c0ccce1c4
GNF3# QUERY5332cdd533fef2a056199db4ddcfa577
GNF3# QUERYd9371bb38851d9d03bbde8031e6ca1d8
GNF3# QUERY69de4c5bfb2e55bd0430a52a20c8622b
GNF3# QUERY3b077e4eb7eb17407fd41fbf637d8fe1
GNF3# QUERY0df5725448c92bc367ecbca11adae0ac
NRC Region 2 false
GNF3# QUERYef2ed89eccc51cc609623ec1f2ae0e81
GNF3# QUERYde3c5bb89d875a82a58cd2f4edddcb0b
GNF3# QUERY68b1093b9c7dfba775aa4e032ee132b6
GNF3# QUERY1dfd4e9b04d198f33c15cad2d7d8dd48
NRC Region 2 true
GNF3# QUERY03a4ee5432c9daa6cecac06e7884f24d
GNF3# QUERY5ca25c6819c8efaf91addd3e567e9715
GNF3# QUERYba42a3eb71aa27030d6475daf7ea3369
GNF3# QUERYe7b0488fd97d2e7ae190ae149ea76e0c
GNF3# QUERYa4701725a493bb0ea1ddc01792eab4ef
GNF3# QUERY1d9edafe5866d3e5d8ff4383f21628d5
GNF3# QUERY99bde631e7167c3c22be6be7d88f68b2
GNF3# QUERY3d330ccebe28824674cfa5ebe7423aaa
GNF3 Prairie Island
GNF3# QUERY32999abd0a2ade2fe20844b48c3038ed
NRC Region 3 false
GNF3 Big Rock Point
GNF3# QUERYa92dec9f581be9221a3ddcf54e717005
GNF3# QUERYe5bbc094d7c3b7fa3990fd159d87b753
NRC Region 3 true
GNF3# QUERY4b875cd2f5745a1db5699c9bf7b8b28c
GNF3 Arkansas Nuclear
GNF3# QUERYe9fef4c0edf5dd478ad4f49dfe847543
GNF3# QUERY65bf99feefa1ec483fc5710c7b3fd265
GNF3# QUERY5f12bbeae7c382ba720489962f5b3e5a
GNF3# QUERY9fa06bd66f7e66606bf3fc15ff8d6173
GNF3# QUERYf77fdff5a25ddfc57692d134d4375cd7
GNF3# QUERY857ca4b6d7dd7f0fbc57dca346210858
GNF3# QUERYa8a6d998b09daaabb1a537c59ba2e8a9
GNF3# QUERYea36d9b0c266781efa7637fcf60ee77a
GNF3# QUERY00d5a7c6ac27e139fb3408bff2f2f20f
NRC Region 4 false
GNF3# QUERYdd4802b8dded669ace517af6046ec47b
GNF3 Fort Saint Vrain
GNF3# QUERY2d4719e265bc2a082ae6f4fc9d7e1ea4
GNF3# QUERY93bb008df4b55a9570a1ab10ab1bfdc7
GNF3# QUERYdd74518880c512e13ebe2cd0cfa94b97
GNF3# QUERY66a58fe52630beb8bdcbb9a34e5e10a6
NRC Region 4 true
GNF3# QUERY0aaf8a2fde5773959f3cd83c94f3cea7
GNF3# QUERY7fde4e21b781df40fa20a8185d8e8c1d
GNF3# QUERY78cc3c78a07d6be5b44708fd989adbcd
GNF3# QUERYdd03bb6df474dcc3b7caceddcb0abe33
NRC-20-0046, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Utilize Neutron Absorbing Inserts in Criticality Safety Analysis for Fermi 2 Spent Fuel Storage Racks
JAFP-24-0034, 10 CFR 50.46 Annual Report
RS-22-108, Response to Request for Additional Information LaSalle County Station, Units 1 and 2 and Quad Cities Nuclear Power Station, Units 1 and 2 License Amendments Related to Fuel Storage
RS-23-071, Application to Adopt TSTF-564, Safety Limit MCPR
RA22-041, Unit 2 Cycle 19 Core Operating Limits Report Revision
GNRO-2020/00020, Core Operating Limits Report (COLR) Cycle 23, and Pressure and Temperature Limits Report (PTLR) Update for Grand Gulf Nuclear Station, Unit 1 (GGNS)
NRC-20-0009, DTE Energy Company Transmittal of Revision to the Pressure and Temperature Limits Report (PTLR)
SVP-23-013, Core Operating Limits Report Cycle 27
JAFP-23-0040, License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis
RS-21-065, License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies with Proposed Change to Technical Specifications Section 4.3.1
RS-23-007, Application to Adopt TSTF-564, Safety Limit MCPR
RS-22-064, License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies with Proposed Change to Technical Specifications Section 4.3.1
RA21-019, Unit 2 Cycle 19 Core Operating Limits Reports
RS-22-040, Response to Request for Additional Information Related to the License Amendment Request to Transition to GNF3 Fuel
LG-24-040, Unit - Issuance of the Core Operating Limits Report (COLR) for Unit 1 Reload 20, Cycle 21
JAFP-22-0046, Core Operating Limits Report Cycle 26
RS-22-006, Request to Expand Applicability of Prime Methods to Evaluate Fuel Centerline Melt and Cladding Strain Compliance for Framatome Fuel
RS-22-090, Response to Request for Additional Information Regarding Quad Cities New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies
JAFP-23-0043, 10 CFR 50.46 Annual Report
RA22-010, Cycle 20 Core Operating Limits Reports
NRC-20-0010, Submittal of Plant Specific Emergency Core Cooling System (ECCS) Evaluation Model Reanalysis. Non-Proprietary GE Hitachi Nuclear Energy Report NEDO-33919 Enclosed
NL-19-0719, GNF3 New Fuel Introduction Startup Test Report
NRC-24-0032, Transmittal of the Core Operating Limits Report for Cycle 23
RS-21-115, Supplemental Information for License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies, with Proposed Changes to Technical Specifications 4.3.1 and 5.6.5
RS-22-109, Response to Request for Additional Information License Amendments Related to Fuel Storage
NRC-20-0011, Transmittal of the Core Operating Limits Report for Cycle 21
NL-24-0026, Application to Revise Technical Specifications Surveillance Requirements to Increase Safety/Relief Valves Setpoint
LG-22-040, Issuance of the Core Operating Limits Report (COLR) for Unit 1 Reload 19, Cycle 20
RA19-021, Cycle 18 Core Operating Limits Report (COLR)
NRC-22-0006, Transmittal of the Core Operating Limits Report for Cycle 22
LG-23-040, Issuance of the Core Operating Limits Report (COLR) for Unit 2 Reload 17, Cycle 18
RA23-019, Cycle 20 Core Operating Limits Reports
RA24-006, Cycle 21 Core Operating Limits Reports
NL-24-0061, Cycle 32 Core Operating Limits Report Version 1
RBG-47567, Submittal of Nineteenth Fuel Cycle Core Operating Limits Report (COLR)
LR-N20-0023, License Amendment Request: Revise Hope Creek Generating Station Low Pressure Safety Limit to Address General Electric Nuclear Energy Part-21 Safety Communication SC05-03
LR-N21-0018, Response to Requests for Additional Information SNSB-RAI 2 and SNSB-RAI 3 License Amendment Request to Revise Low Pressure Safety Limit to Address General Electric Part 21 Safety Communication
RBG-48110, Core Operating Limits Report (COLR) - Cycle 22, Revision 1
RS-22-107, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station
NRC-23-0025, Submittal of 2022 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report
NL-22-0510, Plants Units 1 and 2, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2021
NRC-22-0003, Submittal of 2021 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report
RBG-48226, Core Operating Limits Report (COLR) - Cycle 23, Revision 0
RS-23-004, Response to Request for Additional Information Regarding Transition to GNF3 Fuel License Amendment Request
RA15-020, Cycle 16 Core Operating Limits Report (COLR)
RS-16-054, Transmittal of 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors
RBG-48198, Report of Changes and Errors to 10CFR50.46
TSTF-18-05, TSTF Response to NRC Questions on TSTF-564, Safety Limit (Minimum Critical Power Ratio) MCPR
RS-23-090, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station
RA15-008, Cycle 16 Core Operating Limits Report (COLR)
RA15-079, Cycle 16 Core Operating Limits Report (COLR)
NRC-24-0019, Submittal of 2023 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report
NL-17-0516, Enclosure 2: Edwin I. Hatch Nuclear Plant, Unit 2 - Cycle 25 Core Operating Limits Report Version 1
RA-17-029, Cycle 17 Core Operating Limits Report (COLR)
NL-19-0304, Cycle 26 Core Operating Limits Report, Version 1.0
RS-23-057, Supplement to License Amendment Request Regarding Transition to GNF3 Fuel
NL-19-0250, Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR
NRC-23-0011, License Renewal Commitment 7c: Transmittal of Core Plate Hold-Down Bolt Analysis
NRC-20-0022, Submittal of 2019 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report
NL-22-0129, Cycle 31 Core Operating Limits Report Version 1
RBG-48078, Core Operating Limits Report (COLR) - Cycle 22, Revision 0
RS-20-024, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors
RBG-47610, Report of Changes and Errors to 10CFR50.46
RS-21-113, Response to Supplemental Request for Information Related to Request for Licensing Amendment Regarding Transition to GNF3 Fuel
RBG-48112, Report of Changes and Errors to 10CFR50.46
NL-20-0242, Unit 2 Cycle 26 Core Operating Limits Report Version 2.0
NL-21-0091, Cycle 27 Core Operating Limits Report Version 1
NL-18-0539, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2017
RS-22-066, License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times
RS-22-095, Response to Request for Additional Information Regarding Request to Expand Applicability of GNF Thermal Mechanical Analysis Methods to Framatome Fuel
RS-22-065, License Amendment Request Regarding Transition to GNF3 Fuel
RS-19-020, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station
RS-15-074, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors
RBG-48254, Report of Changes and Errors to 10CFR50.46
NRC-21-0014, Submittal of 2020 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report
NL-23-0101, Cycle 28 Core Operating Limits Report Version 1
RBG-47971, Report of Changes and Errors to 10 CFR 50.46
RS-22-005, Response to Request for Additional Information for the GNF3 Fuel Transition License Amendment Request
GNRO-2020/00027, Core Operating Limits Report (COLR) Cycle 23 Revision 1 for Grand Gulf Nuclear Station, Unit 1 (GGNS)
RS-15-004, County Station Introduction of Lead Use Assemblies
RS-22-117, Response to Request for Additional Information License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies
RBG-48264, Core Operating Limits Report (COLR) - Cycle 23, Revision 1
RS-17-100, Request to Revise Technical Specifications 2.1.1 for Minimum Critical Power Ratio Safety Limits
RS-21-108, Application to Revise Technical Specification 3.1.4, Control Rod Scam Times
RBG-45789, Report of Changes and Errors to 10CFR50.46
RS-17-034, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors
JAFP-22-0040, 10 CFR 50.46 Annual Report
RS-22-018, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station
NL-20-0630, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2019
RS-21-020, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station
RBG-47902, Report of Changes and Errors to 10CFR50.46
NL-19-0650, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2018
RS-24-014, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors
LR-N21-0040, Response to Request for Additional Information SNSB-RAI 1 License Amendment Request to Revise Low Pressure Safety Limit to Address General Electric Part 21 Safety Communication
NRC-20-0062, Submittal of the Startup Report for Cycle 21
RBG-48039, Report of Changes and Errors to 10CFR50.46
NL-21-0606, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2020
RS-23-070, Supplement to License Amendment Request Regarding Transition to GNF3 Fuel
NRC-19-0002, Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR
TSTF-18-12, TSTF Comments on Draft Safety Evaluation for Traveler TSTF-564, Revision 1, Safety Limit MCPR
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
RA15-016, Cycle 16 Core Operating Limits Report (COLR)
RS-23-037, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station
CNRO-2019-00009, Stations - Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR, Revision 2
NL-20-0241, Cycle 30 Core Operating Limits Report Version 1.0
RBG-48306, Report of Changes and Errors to 10CFR50.46
JAFP-24-0044, Core Operating Limits Report Cycle 27
NRC-23-0079, Transmittal of Revision 1 of the Core Operating Limits Report for Cycle 22
U-604662, Submittal of the Core Operating Limits Report for Clinton Power Station, Unit 1, Cycle 21, Revision 17
JAFP-23-0048, Supplemental Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis
NL-19-1124, Submittal of Revision 37 to Updated Final Safety Analysis Report, Fire Hazard Analysis Changes, Technical Specification Bases Changes, Technical Requirements Manual Changes, 10CFR50.59 Summary Report and Revised Nrc
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-15-279, Request for License Amendment to Reduce the Reactor Steam Dome Pressure Specified in the Technical Specification 2.1.1, Reactor Core Sls
TSTF-17-12, Technical Specifications Task Force - Transmittal of TSTF-564, Safety Limit Mcpr
RS-25-020, Additional Information Regarding License Amendment Request for One-Time Extension of Standby Gas Treatment System Technical Specifications Completion Time
RS-25-028, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station
SVP-25-001, CFR 50.59/10 CFR 72.48 Summary Report
NRC-21-0001, License Amendment Request to Revise Technical Specifications to Remove Obsolete Information, Make Minor Corrections, and Make Miscellaneous Editorial Changes
RA25-003, Cycle 21 Core Operating Limits Reports
LG-25-001, Core Operating Limits Report for Limerick Generating Station, Unit 1, Reload 20, Cycle 21
SVPLTR 24-0037, Core Operating Limits Report for Dresden Unit 3 Cycle 29, Revision 19
SVP-25-019, Core Operating Limits Reports for Quad Cities Unit 1 Cycle 29
RBG-48350, State Core Operating Limits Report (COLR) - Cycle 24, Revision 0
NL-25-0068, Cycle 29 Core Operating Limits Report Version 1
RS-24-087, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station
RS-24-103, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors
05000352/LER-2024-003, Core Operating Limits Report Thermal Limit Exceeded for Unit 1 Fuel Bundle GGK123
05000373/LER-2024-001, Core Operating Limits Report Thermal Limits Exceeded
NRC-25-0020, Submittal of 2024 Safety Relief Valve Challenge Report Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report
LG-25-083, Issuance of the Core Operating Limits Report (COLR) for Unit 2 Reload 18, Cycle 19
RA25-036, Cycle 21 Core Operating Limits Report
NRC-25-0030, Transmittal of the Core Operating Limits Report for Cycle 23, Revision 1
PMNS20241038, Closed Meeting to Discuss GNF3 Spacer Relocation
RS-25-135, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors
JAFP-25-0046, License Amendment Request - Proposed Change to the Technical Specifications to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment Isolation
U-604846, Submittal of the Core Operating Limits Report Cycle 23, Revision 19
RBG-48375, Report of Changes and Errors to 10 CFR 50.46