RS-17-017, License Amendment Request to Clarify RHR Subsystem Operability Requirements During Decay Heat Removal Operations
NMP2L2652, License Amendment Request - Revise Surveillance Requirement 3.5.1.2 to Remove Note
GO2-16-119, License Amendment Request for One-Time 7 Day Extension of Completion Time for TS Condition 3.5.1.A, 3.6.1.5.A, and 3.6.2.3.A
RA-16-0021, License Amendment Request Proposing an Updated Final Safety Analysis Report Revision to Reflect Electrical Power Systems Alignments for Shared Systems
NRC-15-0091, License Amendment Request to Revise Technical Specification Section 3.5.1, ECCS - Operating
L-PI-15-030, Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process
DCL-15-023, License Amendment Request 15-01 - Incorporation Into Licensing Basis of Pressurizer Filling Analysis for Major Rupture of a Main Feedwater Pipe Accident
RS-15-002, License Amendment Request to Revise Technical Specifications Sections 3.5.1, ECCS - Operating
NRC-2014-0035, License Amendment Request (LAR) 275, Application to Revise Technical Specifications Task Force (TSTF) Traveler TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process
L-MT-12-004, License Amendment Request: Revise Technical Specification Requirements for Testing the Main Steam Safety/Relief Valves
L-MT-11-015, License Amendment Request: Revise Core Spray Pump Flow Rate in Specification 3.5.1, ECCS - Operating
DCL-17-038, Diablo Canyon Power Plant, Units 1 & 2, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 7
DCL-17-038, Diablo Canyon Power Plant, Units 1 & 2, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 6, Engineered Safety Features (Redacted)
LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 7, Instrumentation and Controls
L-2016-198, Redacted Turkey Point, Units 3 & 4, Updated Final Safety Analysis Report, Chapter 6, Engineered Safety Features
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Section 15.2
WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Response to NRC Questions
WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 7.0 - Instrumentation and Controls
DCL-15-069, Diablo Canyon, Units 1 and 2 - License Amendment Request 15-03 Application of Alternative Source Term - Updated Final Safety Analysis Report Markup. Part 3 of 8
NL-16-109, Indian Point, Unit 2, Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26 - Chapter 6, Engineered Safety Features
NL-16-109, Indian Point, Unit 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26 - Chapter 1, Introduction and Summary
RC-16-0083, Virgil C. Summer, Unit 1 - Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Controls
NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 7.0 - Instrumentation and Controls
NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Chapter 6 - Engineered Safety Features
NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Chapter 1, Introduction and Summary
NL-13-130, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Rev. 24, Chapter 6 - Engineered Safety Features
NL-13-130, Indian Point, Unit 2 - Updated Final Safety Analysis Report (Ufsar), Rev. 24, Chapter 1 - Introduction and Summary
RS-13-009, Clinton, Unit 1, Updated Safety Analysis Report, Revision 15, Chapter 7 - Instrumentation and Control Systems
RS-12-221, Braidwood, Units 1 and 2 and Byron, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Chapter 7.0 - Instrumentation and Controls
NL-11-1812, Edwin I. Hatch, Unit 2 - 2011 Updated Final Safety Analysis Report, Revision 29, Chapter 6, Engineered Safety Features Through Chapter 7, Instrumentation and Control
TMI-10-054, Technical Specifications Change Request (Tscr) No. 348 Relocation of Equipment Load List from TS 4.5.1.1 B, Sequence and Power Transfer Test, to the Updated Final Safety Analysis Report
NRC 2010-0129, License Amendment Request 261, Supplement 7, Extended Power Uprate
NRC 2010-0097, Response to Request for Additional Information on License Amendment Request 261, Supplement 5, Extended Power Uprate
NRC 2009-0066, License Amendment Request 261 Supplement 1 Extended Power Uprate
NL-08-136, Nine Month Response to NRC Generic Letter 2008-001, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems.
WO 08-0019, Application to Revise Technical Specification 3.5.2, ECCS-Operating, in Accordance with TSTF-325-A
RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Chapter 7.0 - Instrumentation and Control Systems
RC-18-0080, Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 7.0, Instrumentation and Controls
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 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 6 - Engineered Safety Features
NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 1 - Introduction and Summary
NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), List of Effective Pages
L-07-017, License Amendment Requests Nos. 334 and 205
L-PI-06-097, License Amendment Request (LAR) to Revise Technical Specification (TS) 3.5.3 Operability Requirements for Safety Injection (SI) Subsystem
W3P81-1169, Forwards Itemized Reviews of Compliance W/Various Sections of 10CFR.Util Meets or Exceeds Requirements
RAIO-0218-58728, LLC Supplemental Response to NRC Request for Additional Information No. 149 (Erai No. 8955) on the NuScale Design Certification Application
L-2019-053, License Amendment Request 269, Modify Reactor Trip System (RTS) Turbine Trip Instrumentation Requirements and Resolve Two Non-Conservative Requirements
ND-19-0321, Request for License Amendment: Crediting Previously Completed ADS Blowdown First Three Plant Tests (LAR-19-006)
ND-18-0111, Supplement to Request for License Amendment Regarding: Passive Residual Heat Removal Heat Transfer and In-containment Refueling Water Storage Tank Heat Up Test Acceptance Criteria Change (LAR-17-033S1)
DCL-04-096, Emergency License Amendment Request 04-03, Revision to Technical Specification 3.6.6, Containment Spray and Cooling Systems
RC-03-0006, License Amendment Request - LAR 02-2820, Emergency Core Cooling Systems - Exclusion of Safety Injection Pumps from Requirement to Vent ECCS Pumps
LIC-02-0044, Revision to License Amendment Request, Allowance to Perform Recirculation Actuation Logic Channel Functional Test
LIC-02-0040, License Amendment Request, Allowance to Perform Recirculation Actuation Logic Channel Functional Test
M200041, GE-Hitachi ABWR Design Control Document Tier 1 & 2, Rev. 7 - Chapter 05 - Reactor Coolant System and Connected Systems
ND-20-0507, Request for License Amendment: Core Makeup Tank Boron Concentration Requirements (LAR-20-004)
L-2021-071, License Amendment Request 273, Update Listing of Approved LOCA Methodologies to Adopt Full Spectrum Tm LOCA Methodology
ST-HL-AE-1674, Forwards Comments & marked-up SER (NUREG-0781) Re Operation of South Texas Projects 1 & 2
B11184, Forwards Status Summary & Responses to Reactor Sys Branch Draft SER Open Items.Summary Reflects Discussions Held W/Nrc at 840509 meeting.Marked-up FSAR Pages Also Encl
ST-HL-AE-3916, Requests Exemption from Requirements of 10CFR50.62, Eliminating Requirements for Specific ATWS Mitigating Sys Actuation Circuitry.Proprietary Pages to Rev 0 to WCAP-12385 Encl.Encl Withheld
B11091, Forwards Addl Info Re Status & Formal Responses to 19 Draft SER Open Items,Per 840313 Review Meeting W/Instrumentation & Control Sys Branch.Responses Will Be Incorporated Into Future FSAR Amend
NRC-22-0026, License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Emergency Diesel Generator Voltage and Frequency Surveillance Requirements
PY-CEI-NRR-2216, Forwards Supplemental Response to NRC Bulletin 96-003, Potential Plugging of ECCS Strainers by Debris in Bwrs. Updated Info to NRC on Several Design Approaches Which Have Been Revised During Final Design Process,Provided
CNL-23-018, – Request for Amendment Regarding Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves (BFN TS-540)
CNL-24-021, Application to Revise Technical Specification Limiting Condition of Operation 3.5.2, ECCS – Operating, Note 1 to Include Residual Heat Removal Pump Flow Paths (SQN-TS-23-04 and WBN-TS-23-020)
A01825, Comments on NRC Evaluation of SEP Topic VI-7.A.3 Re ECCS Actuation Sys.Disagrees W/Nrc Conclusion Re Core Spray & LPCI Sys.Section D.4 of Reg Guide 1.22 Only Applies to Actuated Equipment Not Tested During Reactor Operation
AECM-81-202, Forwards Assurance That Facility Will Be in Compliance W/All Applicable NRC Regulations,In Response to NRC Request.Public Health & Safety Will Be Protected
RAIO-1019-67696, LLC Response to NRC Request for Additional Information No. 526 (Erai No. 9719) on the NuScale Design Certification Application
GO2-17-028, License Amendment Request for Change to Technical Specification 3.5.1, ECCS-Operating
L-81-429, Forwards Itemized Review of Compliance W/Significant Rules & Regulations,Per 10CFR,in Response to NRC 810929 Request
RAIO-0717-55158, LLC Response to NRC Request for Additional Information No. 47 (Erai No. 8820) on the NuScale Design Certification Application
NRC 2003-0029, To License Amendment Request 229 Technical Specification LCO 3.5.2, ECCS - Operating, and LCO 3.5.3, ECCS - Shutdown
LIC-02-0124, License Amendment Request, Removal of Allowance to Perform Recirculation Actuation Logic Channel Functional Test
NUREG-0754, Requests Commission Approval of Issuance of Draft Fr Notice Requiring Documentation of Deviations from SRP & Draft NUREG-0754, Plan for Systematic Safety Evaluation of Nuclear Power Reactors. Related Documentation Encl
CNL-25-041, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-423-A, Revision 1, Technical Specifications End States, NEDC-32988-A, Using the Consolidated Line.
NL-25-0317, Emergency License Amendment Request: One-Time Change to Technical Specification 3.5.2, Core Makeup Tanks (Cmts) - Operating