RS-16-256, Inservice Inspection Interval Relief Request 15R-07
NG-18-0013, Response to Second Request for Additional Information, Fifth Inservice Inspection Lnterval Program Plan, Relief Request RR-03
NLS2018012, Response to Nuclear Regulatory Commission Request for Additional Information for Relief Request RI5-03
NG-18-0036, Supplemental Information, Fifth Inservice Inspection Interval Program Plan, Relief Request RR-03
NL-08-054, Request for Extension of Completion Dates for Indian Point, Units 2 & 3, Corrective Actions Required by Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Wat
TSTF-04-03, TSTF-372, Revision 4, Addition of LCO 3.0.8, Inoperability of Snubbers
BVY 07-047, License Renewal Application, Amendment 27, Submitted on January 25, 2006
DCL-06-048, 2005 Annual Radioactive Effluent Release Report
CNL-18-123, Re-Submittal of American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program and Augmented Program, Second Ten Year Interval Request for Relief 1-ISI-27
CNL-19-052, Response to NRC Request for Additional Information Regarding Re-Submittal of American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program and Augmented Program, Second
DCL-03-049, 2002 Annual Radioactive Effluent Release Report
RA-20-0324, Response to Request for Additional Information for Proposed Alternative for RPV Nozzle-to-Vessel Weld and Inner Radii Examination Requirements
DCL-86-019, Applicant Exhibit A-3,consisting of Responding to NRC 860108 & 15 Ltrs Requesting Addl Info Re Plant Spent Fuel Pool Reracking Rept Submitted to NRC on 850919
RA-20-0247, Supplement to Proposed Alternative for RPV Nozzle-to-Vessel Weld and Inner Radii Examination Requirements in Accordance with 10 CFR 50.55a(z)(1)
ULNRC-06690, Enclosure 5: Callaway, Unit 1, LAR Supplement to Address Audit Discussion Points Summarized in NRC Letter Dated September 14, 2021 (ML21238A138)
BECO-90-106, Responds to 900103 Request for Confirmation That Evaluations of Compliance W/Station Blackout Rule Conducted,Per NUMARC-87-00.Util Selects Diesel Generator Target of 0.975 & Station Blackout Coping Duration of 4 H to Implement Rule
L-21-282, Proposed Inservice Inspection Alternative IR-063
RA-20-0373, Submittal of IWB-3640 Analytical Evaluation of RPV Nozzle N4D Safe End to Pipe Weld Indication
NUREG-2254, Summary of the Uncertainty Analyses for the State-of-the-Art Reactor Consequence Analyses Project
L-MT-09-078, Submittal of Cycle No. 24 Inservice Inspection Summary Report for Inservice Inspection and ASME Section Xl Repairs and Replacements
NUREG/CR-7288 Volume 2, Evaluation of In-Service Radon Barriers Over Uranium Mill Tailings Disposal Facilities - Appendices
RA-24-0102, Proposed Alternative for Reactor Pressure Vessel Nozzle-to-Vessel Weld and Inner Radii Examination Requirements in Accordance with 10 CFR 50.55a(z)(1)