NLS2018012, Response to Nuclear Regulatory Commission Request for Additional Information for Relief Request RI5-03
NL-13-156, 51-9195289-000, Flood Hazard Reevaluation Report Required by 10 CFR 50.54 (F) Near-Term Task Force Recommendation 2.1. Cover Through Page 3-57, Enclosure to NL-13-156
TSTF-04-03, TSTF-372, Revision 4, Addition of LCO 3.0.8, Inoperability of Snubbers
NL-04-2265, Unit 1 Updated Analysis of Core Shroud Vertical Welds and Supplemental Information
BSEP 04-0157, Response to Request for Additional Information Relief Request RR-34, Control Rod Drive System Hydraulic Lines
NL-03-2158, Updated Analysis of Core Shroud Vertical Welds
HBL-03-003, Annual Radioactive Effluent Release Report for 2002
B12382, Forwards Addl Info Supporting 861217 Proposed Amend to License DPR-61,revising Tech Specs to Permit Repositioning & Blocking of Flow Control Valve to Ensure Adequate Cooling in Event of Postulated Pipe Break in Core Deluge Piping
NMP1L3518, Proposed Alternative to Utilize Specific Provisions of Code Case N-716-3, Alternative Classification and Examination Requirements Section XI, Division 1
BVY 04-097, Technical Specification Proposed Change No. 263 - Supplement No. 13 Extended Power Uprate - Response to Steam Dryer Action Items
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)
L-MT-08-040, Extended Power Uprate: Acceptance Review Supplemental Information Package 3
NUREG-1343, Forwards NUREG-1353, Regulatory Analysis for Resolution of Generic Issue 82, Beyond Design Basis Accidents in Spent Fuel Pools. No Actions Should Be Required of Licensees