NRC 2017-0017, License Amendment Request 278, Risk-Informed Approach to Resolve Construction Truss Design Code Nonconformances
NRC-15-0013, Response to NRC Request for Additional Information for the Review of the Fermi 2 License Renewal Application - Severe Accident Mitigation Alternatives
NG-13-0056, Response to RAI, License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants
L-2016-198, Turkey Point, Units 3 & 4, Updated Final Safety Analysis Report, List of Effective Pages
L-2016-198, Turkey Point, Units 3 & 4, Updated Final Safety Analysis Report, Chapter 5, Structures
NG-17-0235, Duane Arnold Energy Center, Calc No. NEE-323-CALC-005, Revised Gaseous Radiological EALs Per NEI 99-01 Rev. 06
L-MT-10-080, Correction to Appendix C of the Monticello Individual Plant Examination of External Events
L-2010-212, Turkey Point, Units 3 & 4, Updated Final Safety Analysis Report - Unit 4 Cycle 24 Update, Chapter 5, Structures
NLS2009048, Response to Request for Additional Information for License Renewal Application Severe Accident Mitigation Alternatives
NEI 99-01, Wolf Creek Generating Station Proposed Revised EAL Technical Basis Document
TSTF-04-03, TSTF-372, Revision 4, Addition of LCO 3.0.8, Inoperability of Snubbers
TSTF-03-11, Traveler - November 17, 2003, Transmits TSTF-372, R.3 Addition of LCO 3.0.8, Inoperability of Snubbers
U-603798, Attachment 3, U-603798, SA-1578, Revision 3, Significance Determination Process (SDP) Evaluation for CPS HPCS RCIC Storage Tank Suction Vortexing
GO2-19-136, Seismic Probabilistic Risk Assessment Response to NRC Request for Information Pursuant to 10 CFR 50.54(F)Regarding Recommendation 2.1 of the Near-Term Task Force (NTTF) Review of Insights from the Fukushima Dai-Ichi
L-2002-022, Response to Request for Additional Information Regarding Risk-Informed Inservice Inspection (RI-ISI) Relief Request for Turkey Point Unit 4
3F0522-01, Safety Analysis Report, Quality Assurance Program and 10 CFR 50.59 - 10 CFR 72.48 Report - May 2022
CEO-88-170, Provides Status Update on post-accident Sampling Sys Methods (Primary & Backup),Sample Measurement Accuracy Ranges for Reactor Coolant Total Gas & Reactor Coolant Total Gas Sampling Procedure
05000331/LER-1984-023, :on 840619,w/plant at 75% Power,Surveillance Test Revealed Three of Four Reactor High Pressure Switches Out of Tolerance in Nonconservative Direction.Switches Recalibr,Returned to Svc & Retested
RS-24-019, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Completion Times TSTF
RS-18-098, Seismic Probabilistic Risk Assessment Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from .
L-85-364, Forwards Addl Response to Generic Ltr 83-28,Item 1.2 Re post-trip Review,Data & Info Capability,Per 850815 Telcon & NRC 850719 Draft Technical Evaluation Rept.Reliability of Digital Data Processing Sys Also Discussed
GO2-90-144, Washington Nuclear Plant 2 Semiannual Effluent Release Rept,Jan-June 1990
NUREG/CR-6410, USEC - Staff Pre-filed Exhibit 25, NUREG/CR-6410, Nuclear Fuel Cycle Facility Accident Analysis Handbook
RA-02-008, Transmittal of Special Report, Transuranic and Other Hard to Detect Radionuclides in Maine Yankee Sample Media
3F0524-02, Safety Analysis Report, Quality Assurance Program and 10CFR 50.59 - 10 CFR 72.48 Report - May 2024