Rev 1 Protection Against Low-Trajectory Turbine Missiles
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RA-18-0090, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
LR-N25-0005, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
NUREG-0823, Supplement No. 1, Integrated Plant Safety Assessment, Systematic Evaluation Program
ONS-2013-037, Licensing Basis for Protected Service Water System - Responses to Request for Additional Information Item Nos. 172 Through 189, License Amendment Request (LAR) 2008-07 - Supplement 7
LIC-13-0061, Omaha Public Power District - Exigent License Amendment Request 13-02 Revise Current Licensing Basis to Adopt a Revised Design Basis / Methodology for Addressing Design-Basis Tornado / Tornado Missile Impact
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 3.1 Through 3.5
LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 1, Introduction and General Description of Plant
LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Appendix 3A, Pse&G Positions on Us NRC Regulatory Guides
LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 3.5, Missile Protection
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant
NRC-16-0034, Fermi, Unit 2, Revision 20 to Updated Final Safety Analysis Report. Appendix a
NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 3.0 - Design of Structures, Components, Equipment, and Systems, Pages 3-i - 3.5A-4
RS-14-006, Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 1 - Introduction and General Description of Plant
L-09-086, License Amendment Request No. 08-027, Spent Fuel Pool Rerack
CPSES-200700738, License Amendment Request (LAR) 07-001 Revision to Technical Requirements Surveillance 13.3.33.2 Frequency for the Turbine Stop and Control Valves
L-06-094, License Amendments Request Nos. 333 and 204
L-06-046, Responses to a Request for Additional Information in Support of License Amendment Request No. 202
RA-18-0026, Proposed Amendment to the Renewed Facility Operating Licenses Regarding Revisions to the Updated Final Safety Analysis Report Sections Associated with the Oconee Tornado Licensing Basis
TXX-3365, Forwards Draft Responses to NRC Questions 251.1-251.4. Responses Will Be Included in Amend 24 Scheduled for Submittal on 810715
NRC Generic Letter 79-05, Information Relating to Categorization of Recent Regulatory Guides by the Regulatory Requirements Review Committee
CPSES-200501587, 1OCFR50.59 Evaluation Summary Report 0012 and Commitment Material Change Evaluation Report 0006
NRC 2004-0029, Emergency Plan Implementing Procedures Manual Revisions
NRC 2004-0010, Emergency Plan Implementing Procedures Manual and Emergency Plan Manual Revisions
NRC 2003-0035, Emergency Plan Implementing Procedure Revisions Point Beach Nuclear Plant, Units 1 & 2
PLA-5565, Replacement of Main Turbine Rotors
NRC 2002-0107, Emergency Plan Implementing Procedure Revisions for Point Beach Nuclear Plant, Units 1 & 2
NRC-94-4194, Forwards Responses to NRC Requests for Addl Info Re AP600
W3F1-2020-0032, Report of Facility Changes, Tests and Experiments and Commitment Changes for Two Year Period Ending April 28, 2020
JAFP-21-0035, Summary of Plant and Independent Spent Fuel Storage Installation Changes, Tests, and Experiments as Required by 10 CFR 50.59 and 10 CFR 72.48, and Summary of Commitment Changes, for 2019 and 2020
JAFP-21-0069, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
IA-86-542, Requests Authorization to Issue Initial License for Dry Cask Storage of Spent Fuel Per 10CFR72 in Isfsi.License Should Be Granted
NSD-NRC-97-5425, Forwards Response to Questions Related to Missile Protection That Were Included in Ltr from NRC Dtd 971024.Listed Open Items Will Be Statused as Action N or Confirm W Pending Inclusion in SSAR Rev as Noted
AEP-NRC-2021-19, 0 to Updated Final Safety Analysis Report, Chapter 1, Introduction and Summary
ST-HL-AE-1802, Requests Deletion of Tech Spec Surveillance Requirements for Turbine Overspeed Protection,Per SER (NUREG-0781) Requirement to Implement Inservice Insp Program for Stated Valves.Encls Include Justification & Proposed Tech Specs
RBG-34-834, Application for Amend to License NPF-47,changing Tech Spec Surveillance Requirement 4.3.8.2.a Re Turbine Overspeed Protection to Allow Monthly Testing of High Pressure Turbine Control Valves in Lieu of Weekly Testing
NRC-94-4184, Forwards Responses to NRC RAIs on AP600 from NRC 940316, 0419,29,0502,11,12,23 & 26 Ltrs.Revs of Responses Previously Submitted Also Provided,Completing Responses for NRC
B13813, Forwards Response to NRC 910404 Request for Addl Info Concerning Util Response to Original SER Re Station Blackout Rule
NMP1L3484, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Reatment of Structures, Systems and Components for Nuclear Power Reactors
RS-23-060, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors
W3P87-2313, Application for Amend to License NPF-38,consisting of Tech Spec Change Request NPF-38-69.Amend Revises Low Pressure Turbine Disc Insp Interval to Accommodate Installation of New Disc.Fee Paid
LD-92-063, Forwards Info to Supplement 920325 Responses to NRC Request for Addl Info Re Analysis of Ruptured Reactor Coolant Pump Seal Cooler Tube & Single Failure Assumptions for Analysis of moderate-energy-line Break
LD-94-023, Forwards Responses to Questions Raised by ACRS ABB-CE Std Plant Designs Subcommittee at 940308-09 Meeting on Sys 80+
PLA-8081, 1 to Updated Final Safety Analysis Report, Questions and Responses 121.1 Through 121.21
RS-24-056, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors
LD-91-012, Forwards Response to NRC 890119 Request for Addl Info to Enable NRC to Continue Review of CESSAR - Design Certification (CESSAR-DC)
LD-90-008, Forwards Response to 881216 Request for Addl Info Re CESSAR-DC,Chapters 3,4,5 & 6 Re Turbine Missiles,Control Element Drive Structural Matls,Cleaning & Contamination Protection Procedures & Reactor Internals Matls
B10288, Forwards Safety Assessment for SEP Topic III-4.B,re Turbine Missiles.Periodic Insps,Maint of High Purity Feedwater & Overspeed Protection Sys Testing Assure Low Probability of Generating Missiles Affecting safety-related Equipment
1CAN112401, Safety Analysis Report (SAR) Amendment 32, Technical Requirements Manual (Trm), Technical Specifications (TS) Bases, 10 CFR 50.59 Report, and Commitment Change Summary Report
NUREG-0124, Forwards Addl NRC Testimony by KM Campe,A Hafiz,Sa Varga & Others to Be Presented at Hearings.Nrc Exhibit,Gessar SER, Suppl 1 (NUREG-0124) & Draft Hearing Schedule Encl
RAIO-1018-62357, LLC Response to NRC Request for Additional Information No. 504 (Erai No. 9605) on the NuScale Design Certification Application
RAIO-0418-59509, LLC Response to NRC Request for Additional Information No. 369 (Erai No. 9329) on Design Certification Application
RAIO-1018-62389, LLC Response to NRC Request for Additional Information No. 503 (Erai No. 9596) on the NuScale Design Certification Application
L-89-144, Forwards Assessment of Amended Station Blackout Rule 10CFR50.63,description of Procedures in Place That Will Be Modified & Proposed Mods & Implementation Schedule
L-89-145, Responds to Station Blackout Rule Re Capability of Plant to Maintain Core Cooling & Containment Integrity.Proposed 10CFR50.63 Mods Will Permit Powering Either Unit from Other Unit Emergency Diesel Generators in 10 Minutes
RAIO-1217-57779, LLC Response to NRC Request for Additional Information No. 225 (Erai No. 9058) on the NuScale Design Certification Application
CNL-16-048, Responses to Requests for Additional Information, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU)
NUREG-1916 Volume 2, Safety Evaluation Report - Related to the License Renewal of Shearon Harris Nuclear Power Plant, Unit 1
W3F1-2021-0003, Application for Technical Specification Change to Adopt Risk-Informed Extended Completion Times - RITSTF Initiative 4B
NL-21-0845, License Amendment Request: Revise Technical Specification 3.7.2 Limiting Condition for Operation to Remove One Main Steam Isolation Valve System
RBG-27108, Forwards Suppl Rept of Safety Evaluations for Documents Only Changes Included in USAR for Mar 1986 - Feb 1987