L-PI-16-100, Response to NRC Request for Information - License Amendment Request for Spent Fuel Pool Criticality Technical Specification Changes
RS-16-228, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition
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
ONS-2016-052, License Amendment Request to Revise Technical Specifications Associated with Dry Spent Fuel Storage Cask Loading and Unloading Requirements; License Amendment Request No. 2016-04
NG-16-0052, License Amendment Request (TSCR-159) to Revise Technical Specifications Fuel Storage Requirements
CNL-16-023, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 4, Responses to Requests for Additional Information
RS-15-226, Supplemental Information Regarding License Amendment Request Regarding Spent Fuel Storage Pool Criticality Methodology and Proposed Change to Technical Specification 4.3.1, Criticality
RS-15-119, Supplemental Information Regarding License Amendment Request Regarding Spent Fuel Storage Pool Criticality Methodology and Proposed Change to Technical Specification 4.3.1, Criticality
RS-14-310, License Amendment Request Regarding Spent Fuel Storage Pool Criticality Methodology and Proposed Change to Technical Specification 4.3.1, Criticality
RS-14-100, Additional Information Regarding License Amendment Request Associated with Use of Neutron Absorbing Inserts in Spent Fuel Pool Storage Racks
GNRO-2013/00073, Criticality Safety Analysis License Amendment Request - Supplemental Information
GNRO-2013/00066, Criticality Safety Analysis License Amendment Request - Supplemental Information
RS-13-202, Response to Request for Additional Information Regarding License Amendment Request to Remove License Conditions Associated with Unit 2 Spent Fuel Pool
RS-13-148, License Amendment Request - Use of Neutron Absorbing Inserts in Units 1 and 2 Spent Fuel Pool Storage Racks
GNRO-2012/00124, Response to NRC Request for Additional Information - GGNS Criticality Safety Analysis License Amendment Request
RS-12-061, License Amendment Request Regarding the Removal of License Conditions Addressing Interim Configurations of the LaSalle County Station Unit 2 SFP
GNRO-2012/00027, Responses to NRC Requests for Additional Information Pertaining to License Amendment Request for Criticality Safety Analysis
RS-11-157, License Amendment Request Regarding the Use of Neutron Absorbing Inserts in Unit 2 Spent Fuel Pool Storage Racks and the Timeline for Implementation
RS-11-153, Response to Request for Additional Information Regarding Unit 2 Spent Fuel Pool Storage Racks
GNRO-2011/00076, License Amendment Request Criticality Safety Analysis and Technical Specification 4.3.1, Criticality
L-PI-11-075, Letter from Xcel Energy License Amendment Request for Spent Fuel Pool Criticality Changes
RS-11-109, Completion of License Condition 2.C.(30) Associated with Unit 2 Spent Fuel Pool Storage Racks
L-11-103, Supplement to Spent Fuel Pool Rerack Amendment Request
RS-11-014, Additional Information Supporting License Amendment Request Regarding the Use of Neutron Absorbing Inserts in Unit 2 Spent Fuel Pool Storage Racks
RS-11-009, Additional Information Supporting License Amendment Request Regarding the Use of Neutron Absorbing Inserts in Unit 2 Spent Fuel Pool Storage Racks
CNL-18-018, Supplement to Application to Revise Watts Bar Unit 2 Technical Specification 4.2.1, Fuel Assemblies, and Watts Bar Units 1 and 2 Technical Specifications Related to Fuel Storage (WBN-TS-17-028)
ONS-2018-013, Technical Specification Bases Changes
RS-10-216, Additional Information Supporting License Amendment Request Regarding the Use of Neutron Absorbing Inserts in Unit 2 Spent Fuel Pool Storage Racks
RS-10-202, Additional Information Supporting License Amendment Request Re Use of Neutron Absorbing Inserts in Unit 2 Spent Fuel Pool Storage Racks
RS-09-069, Withdrawal of Request for License Amendment Regarding Spent Fuel Storage Pool Criticality
CP-200801686, Response to Request for Additional Information Regarding Spent Fuel Pool Criticality License Amendment Request
RS-08-087, License Amendment Request to Administratively Clarify the Operating Licenses and Technical Specifications
NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 9 - Auxiliary and Emergency Systems
NRC 2008-0044, Point Beach, Units 1 & 2, License Amendment Request No. 247, Transmittal of Changes to Technical Specifications Spent Fuel Pool Storage Criticality Control
RS-07-165, License Amendment Request Regarding Spent Fuel Storage Pool Criticality
BSEP 06-0128, Request for License Amendments Regarding Fuel Design and Storage Requirements for Areva Np Fuel
1CAN070603, License Amendment Request to Support the Use of Metamic@ Polson Insert Assembles in the Spent Fuel Pool
LIC-06-0065, Closure of NRC TAC Issues for Fort Calhoun Station Unit No. 1
NRC-2016-0100, Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: May 24, 2016
NRC-2011-0040, Sholly Report for Fr Publication on February 22, 2011
RBG-47949, Supplement to License Amendment Request Criticality Safety Analysis, Technical Specifications 4.3.1, Criticality, and Technical Specification 5.5, Programs and Manuals
B18790, Inservice Inspection Program - Owners Activity Reports
NRC-98-0150, Forwards Response to NRC 981026 RAI Re Fermi 2 Conversion to Improved Std Ts.Responses Reflect Results of Series of Meetings Between Util & NRC
2CAN028906, Forwards Supplemental Response to Request for Addl Info Re Atws.Info Covers QA Program for ATWS Per Generic Ltr 85-06 & Maint Bypass Breakers in Diverse Scram Sys one-line Diagram
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-22-064, 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
NL-22-0288, License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel
RS-22-083, Response to Request for Additional Information Related to the License Amendment Request to Change New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies, with Proposed Changes to Technical
RS-22-090, Response to Request for Additional Information Regarding Quad Cities New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies
AECM-84-0229, Forwards Program Completion Rept Re Conclusion of Tech Spec Review Program.Rept Documents That Thorough & in-depth Engineering,Operations & Licensing Review of Tech Specs Conducted Per Programmatic Commitments
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
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
RS-22-117, Response to Request for Additional Information License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies
RS-11-067, Response to Request for Additional Information Regarding Unit 2 Spent Fuel Pool Storage Racks
RS-06-116, License Amendment Request and Exemption Requests to Allow Use of Areva Np Inc., Advanced Mark-BW(A) Fuel Assemblies
RS-09-133, LaSalle, Units 1 & 2 - License Amendment Regarding the Use of Neutron Absorbing Inserts in Unit 2 Spent Fuel Pool Storage Racks
PMNS20211084, A Closed Meeting with Exelon Generation Company, LLC Regarding Proprietary Information in the Request for the Amendments to Renewed Facility Operating Licenses for LaSalle County Station, Units 1 and 2
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
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
RS-21-109, Request to Withhold Meeting Materials for the Non-Public Meeting Held on September 2, 2021
RS-22-109, Response to Request for Additional Information License Amendments Related to Fuel Storage
2CAN021890, Responds to NRC 881228 Request for Addl Info Re Design of Diverse Scram Sys & Diverse Turbine Trip,Per 10CFR50.62.Util Intends to Proceed W/Installation of Mods During Refueling 2R7,contingent on NRC Approval
05000528/LER-1986-062, :on 870211,discovered That Max Surveillance Interval for Monthly Functional Test of Plant Protection Sys (36ST-9SB02) Exceeded on 860222.Caused by Communication Error.Surveillance Program Enhanced
05000344/LER-1987-004, :on 870219,reactor Trip Bypass Breaker B Opened During Termination of Periodic Instrument & Control Test 10-1 Due to Sulfer Smell.Caused by Incorrect Termination of Test.Trip Signal Blocks Reinstated
L-PI-05-075, Supplement to License Amendment Request (LAR) to Revise the Spent Fuel Pool Criticality Analyses and Technical Specifications (TS) 3.7.17, Spent Fuel Pool Storage and 4.3, Fuel Storage
05000348/LER-1998-005, :on 980315,failure to Perform Nuclear Instrumentation Surveillance Requirements Prior to Mode 2 & 3 Entry,Was Discovered.Caused by Personnel Error.Revised Applicable Procedures
05000423/LER-1988-010, :on 880209,discovered That Nuclear Instrumentation Negative & Positive Rate Reactor Trips Set Nonconservatively.Caused by Personnel Failing to Properly Account for Leakage on Excore Instrumentation
1CAN100601, Supplement to License Amendment Request to Support Use of Metamic Poison Insert Assemblies in Spent Fuel Pool
05000483/LER-1992-009, :on 920807,discovered That Manual Reactor Trip Breaker Handswitch Contacts Inadequately Tested Per TS 4.3.1.1,Functional Unit 1.Caused by Incomplete Procedure. Procedure Request Form Revised in Jul 1988
05000416/LER-1983-003-01, /01T-0:on 830108,limiting Condition for Operation Entered Due to Intermediate Range Monitor Functional Test Not Being Performed within Required Time Period.Caused by Personnel Error.Personnel Made Aware of Error
1CAN040302, License Amendment Request to Modify the Fuel Assembly Enrichment, the Spent Fuel Pool (SFP) Boron Concentration TS 3. 7.14, the Loading Restrictions in the SFP in TS 3,7,15m and to Modify the Fuel Storage Design Features in TS 4.3
05000311/LER-1980-026-03, /03L-0:on 800811,during Review of Records, Determined That Reactor Was Taken Critical W/O Performing Functional Test on Source Range Instruments.Caused by Personnel Error
05000397/LER-1993-010, :on 940304,24 Reportable Problems Identified by Failure of Procedures to Fully Implement.Cause Was Less than Adequate Barrier & Controls for Program Changes.Corrective Actions Include Procedure & TS Changes
GO2-98-162, Requests Withdrawal of 980805 Proposed TS Amend,Modifying SR 3.8.4.7 to Allow Performance Discharge Test of SR 3.8.4.8 to Be Performed in Lieu of Battery Svc Test
L-PI-17-014, Summary of Public Meeting and Plan for NRC Request for Additional Information Regarding License Amendment Request for Spent Fuel Pool Criticality Technical Specification Changes (CAC Nos. MF7121.
CNS-16-005, Final Notification of Full Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events and with Order EA-12-051, Order to Modify
RS-16-042, Supplemental Information Supporting License Amendment Request Regarding Spent Fuel Storage Pool Criticality Methodology and Proposed Change to Technical Specification 4.3.1, Criticality
05000206/LER-1991-009, :on 910429,local Leak Rate Tests of Emergency Escape & Personnel Airlocks Exceeded 6-month Surveillance Interval.Caused by Miscommunication & Lack of Formality in Scheduling Process.Formal Process Established
05000206/LER-1988-008-01, :on 880524,inadvertent Omission of Safety Injection Vent Valves from Local Leak Rate Testing Program. Caused by Valves Associated W/Penetration E15 Omitted from Local Leak Rate Testing Program
GNRO-2012/00120, Responses to NRC Requests for Additional Information – GGNS Criticality Safety Analysis License Amendment Request
PNP 2012-071, Response to Request for Additional Information — License Amendment Request — Replacement of Spent Fuel Pool Region I Storage Racks
05000277/LER-2011-002, For Peach Bottom, Units 2 and 3 - Condition Prohibited by Technical Specifications Due to Degraded Spent Fuel Pool Racks Boraflex Panels
05000255/LER-2008-004, Noncompliance with Technical Specification 4.3.1.1.b
LIC-06-0063, Exigent LAR, Deletion of Design Features Technical Specifications Redundant to 10 CFR 50.68, Criticality Accident Requirements
L-PI-04-075, Supplement to License Amendment Request (LAR) to Revise the Spent Fuel Pool Criticality Analyses and Technical Specifications (TS) 3.7.17, Spent Fuel Pool Storage and 4.3, Fuel Storage
LIC-05-0075, Response to Request for Additional Information on the License Amendment Request, Revisions of Technical Specifications Table 1-1 and Section 4.0
LIC-04-0117, License Amendment Request, Revisions of Technical Specifications Table 1-1 and Section 4.0
L-PI-04-129, License Amendment Request (LAR) to Revise the Spent Fuel Pool Criticality Analyses and Technical Specifications (TS) 3.7.17, Spent Fuel Pool Storage and 4.3, Fuel Storage
B18684, Response to a Request for Additional Information Technical Specifications Change Request (Tscr) 2-10-01 Fuel Pool Requirements
NL-04-0973, Request to Revise Technical Specifications to Reflect Updated Spent Fuel Rack Criticality Analyses for Units 1 and 2
RS-24-098, Units 1 and 2 - Supplement to License Amendment Request to Revise Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel Assembly Storage, 4.3.1, Fuel Storage, Criticality
GNRO-2011/00033, Supplemental Information Extended Power Uprate
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
CNL-21-050, License Amendment Request Regarding Criticality Safety Analysis of Spent Fuel Pool Storage of Atrium 11 Fuel (TS-534)
PMNS20250456, Notice of pre-submittal Meeting Between Southern Nuclear Operating Company (SNC) and NRC Regarding a Proposed License Amendment Request (LAR) to Change Technical Specification (TS) 4.3.1, Criticality, Related to Fuel Storage
L-21-007, License Amendment Request 21-02 - Proposed Revisions to Humboldt Bay Independent Spent Fuel Storage Installation - Special Nuclear Materials License Number 2514 and Technical Specifications
05000206/LER-1988-015-01, :on 881114,performance of Local Leakage Rate Tests (LLRT) on 880720 at Below Required Pressure Discovered.Caused by Cognitive Personnel Error.Assessment of LLRT Procedure Will Be Performed
05000461/LER-1987-049, :on 870819,two Channel Tests Not Performed within 24 H Time Interval.Caused by Util Licensed Operator Error Due to Confusion During Shift Transition.Control Room Operator Surveillance Log Data Sheet Revised
GNRO-2011/00025, NET-287-01, Revision 1, BADGER Test Campaign at Grand Gulf Nuclear Station