CNL-17-026, Application to Modify Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Fluid Oil Pressure (390-WBN-TS-17-04)
CNL-17-128, Application to Modify the Watts Bar Nuclear Plant Unit 2 Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Fluid Oil Pressure (391-WBN-TS-17-23)
L-2016-233, License Amendment Request 250, Modify Technical Specifications for Auxiliary Feedwater Actuation on Bus Stripping and on Trip of All Main Feedwater Pump Breakers
NOC-AE-16003351, License Amendment Request to Revise Technical Specification 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies
2CAN121705, Exigent License Amendment Request Allowance to Exclude Exercise of Control Element Assembly 4 with Respect to Surveillance Requirement 4.1.3.1.2 for the Remainder of Cycle 26
NOC-AE-15003315, Emergency License Amendment Request to Revise Technical Specification 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies for Cycle 20
LR-N15-0020, License Amendment Request to Revise Technical Specification 3/4.3.1, Reactor Trip System Instrumentation
NL-15-021, Proposed License Amendment Regarding a Change to Technical Specification 3.1.4 Reactivity Control Systems Indian Point Unit Number 2
2CAN021501, License Amendment Request Allowance to Eliminate Movement of Control Element Assembly 18 from Surveillance Requirement 4.1.3.1.2 for the Remainder of Cycle 24
DCL-12-050, Attachment 2 to DCL-12-050, Final Safety Analysis Report Changes for Process Protection System Replacement
GNRO-2011/00039, Responses to NRC Requests for Additional Information Pertaining to License Amendment Request for Power Range Neutron Monitoring System
WO 11-0008, Revision to Technical Specifications 3.3, Instrumentation, 3.7, Plant Systems, and 3.8, Electrical Power Systems
LR-N17-0088, Redacted - Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 3, Design of Structures, Components, Equipment and Systems, Sections 3.6 Through 3.11
DCL-17-038, Diablo Canyon Power Plant, Units 1 & 2, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 7
LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 7, Instrumentation and Controls
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Section 15.2
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Figures 3.7.B.2-27 Through 3D-17
L-2016-198, Turkey Point, Units 3 & 4, Updated Final Safety Analysis Report, Chapter 7, Instrument and Control
WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 7.0 - Instrumentation and Controls
NRC-16-0034, Fermi 2 Revision 20 to Updated Final Safety Analysis Report, Chapter 11
DCL-16-011, Pacific Gas & Electric Co. Diablo Canyon Power Plant Units 1 & 2 Functional Requirements Specification Process Protection System (PPS) Replacement Nuclear Safety-Related,08-0015-SP-001, Rev. 9
LR-N15-0178, Hope Creek - License Amendment Request, Digital Power Range Neutron Monitoring (Prnm) System Upgrade
NL-17-008, Sequoyah and Watts Bar - License Amendment Request to Modify Technical Specification (TS) Surveillance Requirement 3.2.4, Qptr, and TS 3.3.1, Reactor Trip System (RTS) Instrumentation, Condition D (SQN-TS-17-02 and WBN-TS-17-014)
NL-16-109, Indian Point, Unit 2, Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26 - Chapter 7, Instrumentation and Control
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 7 - Instrumentation and Control
RS-14-006, Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 7 - Instrument and Control Systems
NL-13-130, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Rev. 24, Chapter 7 - Instrumentation and Control
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
DCL-12-069, Diablo Canyon, Units 1 and 2 - 08-0015-SP-001, Functional Requirements Specification, Revision 5, Attachment 2
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
NRC 2009-0120, License Amendment Request 261, Supplement 3 Extended Power Uprate
RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Chapter 11.0 - Radioactive Waste Management
RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Chapter 7.0 - Instrumentation and Control Systems
NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 7 - Instrumentation and Control
W3P81-1169, Forwards Itemized Reviews of Compliance W/Various Sections of 10CFR.Util Meets or Exceeds Requirements
CNL-17-008, License Amendment Request to Modify Technical Specification (TS) Surveillance Requirement 3.2.4, QPTR, and TS 3.3.1, Reactor Trip System (RTS) Instrumentation, Condition D (SQN-TS-17-02 and WBN-TS-17-014)
NLS2004122, License Amendment Request to Revise the Required Channels Per Trip System for Primary and Secondary Containment Isolation and Control Room Emergency Filter System Instrumentation
DCL-03-011, License Amendment Request 03-01, Revision to TS 3.3.1, Reactor Trip System Instrumentation
CNL-19-095, Application to Modify the Sequoyah Nuclear Plant Units 1 and 2 Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Fluid Oil Pressure (SQN-TS-19-04)
W3F1-2021-0032, Revised License Amendment Request - Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System
RBG-44551, Responds to NRC Re Fire Protection Functional Insp Rept 50-458/97-201 on 970616-20 & 0630-0703.Requested Addl Info in Re Review of Certain Issues Found During Insp,Also Included
L-PI-21-006, License Amendment Request to Revise Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation, to Incorporate Installed Bypass Test Capability for the Power Range RTS Functions
ST-HL-AE-1422, Forwards Response to Draft Ser/Fsar Items Re Section 3.11 Concerning Environ Design of Mechanical & Electrical Equipment.Encl marked-up FSAR Pages Will Be Incorporated in Future FSAR Amend
ST-HL-AE-1435, Forwards Responses to Draft SER & Draft FSAR Items Re Section 3.11N on Environ Design of Mechanical & Electrical Equipment.Info Will Be Incorporated in Future FSAR Amend
SNRC-1105, Forwards Exemption Requests for Containment Isolation, MSIV-App J Testing,Seismic Qualifications & Remote Shutdown, Per NRC Request Resulting from Commission Order CLI-84-8
RS-23-048, Exigent Amendment Request to Revise Design Basis Related to Seismic Requirements
1CAN032301, License Amendment Request to Modify the Arkansas Nuclear One, Unit 1, Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Control Oil Pressure
TXX-6745, Forwards Revised Environ Qualification Program,Addressing Mild Environs for Plant
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
BYRON 2024-0060, CFR 50.59 Summary Report, Changes, Tests and Experiments
RAIO-0118-58190, LLC Supplemental Response to NRC Request for Additional Information No. 58 (Erai No. 8835) on the NuScale Design Certification Application
05000397/LER-1989-039, :on 890914,discovered Three Discrepancies W/ Current Configuration of Reactor Bldg Exhaust Air Radiation Monitoring Sys That Do Not Satisfy Design Basis Requirements
GO2-83-417, Forwards marked-up FSAR Pages Describing Equipment for Sampling & Monitoring Process & Effluent Streams During Postulated Accidents.Submittal Closes Out Commitment in Section 11.5.2 (Page 11-14) of SER,NUREG-0892
L-81-429, Forwards Itemized Review of Compliance W/Significant Rules & Regulations,Per 10CFR,in Response to NRC 810929 Request
RC-05-0143, License Amendment Request - LAR 05-2926 Implementation of WCAP-14333-P-A, Rev. 1, Probabilistic Risk Analysis of the RPS and ESFAS Test Times and Completion Times
TXX-0513, License Amendment Request - Revision to Technical Specification Surveillance Requirements 3.3.1.2 & 3.3.1.3, Reactor Trip System Instrumentation
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
NLS2024070, Response to Integrated Inspection Report No. 05000298/2024003
ET 21-0010, License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation