CNL-15-088, Application to Revise Technical Specifications for Component Cooling Water Snd Essential Raw Cooling Water to Support Dual Unit Operation (TS-WBN-15-13)
CNL-15-121, Shutdown Technical Specifications for Component Cooling System and Essential Raw Cooling Water System to Support Dual Unit Operation
L-15-045, Core Operating Limits Report, Cycle 19, Revision 1
L-14-107, Core Operating Limits Report, Cycle 19
NL-13-0322, Response to NRC Request for Additional Information, Revision of Technical, Specification 3.7.9 Ultimate Heat Sink
TMI-11-103, License Amendment Request to Revise Technical Specifications to Incorporate Administrative Changes
L-10-083, Core Operating Limits Report for Cycle 17
ULNRC-05655, Application for Amendment to Facility Operating License, Revision of Technical Specification 3.3.9
ULNRC-05633, Revision of Technical Specification 3.3.9
L-09-072, License Amendment Request to Incorporate the Use of Alternate Methodologies for Development of Reactor Pressure Vessel Pressure-Temperature Limit Curves and Request for Exemption from Certain Requirements Contained in 10 Cfr
L-06-172, Units 1 and 2, License Amendment Requests to Add LCO 3.0.8 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process
ULNRC-05233, Application for Amendment to Facility Operating License NPF-30
WO 18-0044, Clean Revised Technical Specification Pages for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term
NMP1L3248, Supplement to the Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Apply TSTF-542, Revision 2, Reactor Pre
WBL-19-023, Periodic Submission for Changes Made to the WBN Technical Specification Bases and Technical Requirements Manual
L-19-162, Submittal of Core Operating Limits Report, Cycle 21, Revision 1
L-19-245, Core Operating Limits Report, Cycle 21, Revision 2
RAIO-0319-64994, LLC Supplemental Response to NRC Request for Additional Information No. 512 (Erai No. 9634) on the NuScale Design Certification Application
ET 17-0016, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analyses
RAIO-0219-64635, LLC Response to NRC Request for Additional Information No. 512 (Erai No. 9634) on the NuScale Design Certification Application
ND-18-0053, Request for License Amendment: Technical Specification Applicability Changes to Support Pressurizer Safety Valve Operability (LAR-18-004)
L-20-063, Submittal of Core Operating Limits Report, Cycle 21, Revision 3
L-20-085, Core Operating Limits Report, Cycle 22, Revision 0
NSD-NRC-97-5501, Forwards W Responses to FSER Open Items on AP600.Summary of Responses Provided in Table 1,including FSER Open Item Number,Associated Oits Number & Status to Be Designated in W Status Column
NMP1L3402, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of License Amendment Request to Adopt TSTF-582, Revision 0
NSD-NRC-96-4833, Forwards Roadmap for Content of AP600 Tech Specs Vs NUREG-1431 & Description of General or Overall Changes Whose Explanations Apply to Multiple TS
L-22-047, Unit No.1 - Core Operating Limits Report, Cycle 23, Revision O and Revision 1
NL-23-0136, License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006)
NL-23-0385, License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006R1)
NL-23-0398, Withdrawal of Request of License Amendment Request Regarding More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006)
NL-24-0126, – Units 3 and 4, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Action a and SR 3.7.6.6
L-08-317, Core Operating Limits, and Pressure and Temperature Limits Report
ND-22-0831, Comments on AP1000 Standard Technical Specifications (STS) – Draft NUREG-2194, Revision 1
05000327/LER-1988-040, :on 881017,discovered That Unit Entered Mode 4 on 880927 w/safety-related Snubber Inoperable.Caused by Personnel Failure to Realize Snubber Disconnected.Event Reviewed W/Planning Personnel
RAIO-0119-64281, LLC Response to NRC Request for Additional Information No. 512 (Erai No. 9634) on the NuScale Design Certification Application
L-18-024, Core Operating Limits Report, Cycle 20, Revision 1
L-17-223, Application to Revise Technical Specifications to Adopt TSTF-547-A, Revision 1, Clarification of Rod Position Requirements
RAIO-0717-54951, LLC Response to NRC Request for Additional Information No. 41 (Drai No. 884) on the NuScale Design Certification Application
CNL-14-180, Technical Specification Sections 3.0 and 3.10.1
NMP1L3238, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Apply TSTF-542, .
05000362/LER-2006-004, Regarding Inoperable Breaker Causes Train a Charging Pump to Be Inoperable for Longer than Allowed by Technical Specifications
TSTF-04-04, TSTF-467, Revision 0, Add Restriction for Lowest Loop T(Ave) During Mode 2 Physics Testing
NMP1L3369, Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0 Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements
NL-24-0325, License Amendment Request: Move Surveillance Requirements from Technical Specifications (TS) 3.3.15 and 3.3.16 Engineered Safety Feature Actuation System (ESFAS) Actuation Logic
ULNRC-05883, Request to Correct Typographical Error Identified in Technical Specification 3.1.9 Required Action A.3
NL-25-0205, Units 3 and 4 License Amendment Request: Move Surveillance Requirements from Technical Specifications 3.3.15 and 3.3.16, Engineered Safety Feature Actuation System (ESFAS) Actuation Logic - Response to RAI
L-09-225, Supplemental Information Related to a License Amendment Request to Incorporate the Use of Alternate Methodologies for the Development of Reactor Pressure Vessel Pressure-Temperature Limit Curves, and Request for Exemption from