Browse wiki

Carbon +  and Lead +

10 CFR 50 +, 10 CFR 54 +, 10 CFR 54.120 +, 10 CFR 54.124 +  and 10 CFR 54.254 +

NL-14-013, Additional Information Regarding the License Renewal Application - Action Item 7 from MRP-227-A +, NL-12-037, License Renewal Application - Revised Reactor Vessel Internals Program and Inspection Plan Compliant with MRP-227-A +, NL-10-063, Amendment 9 to License Renewal Application, Reactor Vessel Internals Program +, NRC 451 +, NRC 1041 +, NRC 460 +, NRC 461 +, NRC 1076 +, NRC 301 +, NRC 314 +, NRC 449 +, NRC 43 +, NRC 246 +, NRC 235 +, NRC 255 +, NRC 571 +, NRC 365 +, NRC 419 +, NRC 163 +, NRC 93 +  and NL-11-107, New York State (NYS) Pre-Filed Evidentiary Hearing Exhibit NYS000314, License Renewal Application- Completion of Commitment 30 Regarding the Reactor Vessel Internals Inspection Plan +

05000247  +  and 05000286  +

ML103050402 +, ML15044A493 +, ML15044A491 +, ML15090A771 +, ML14310A803 +, ML15069A677 +, ML080300149 +, ML080230543 +, ML12335A461 +, ML103010104 +  and ML102850764 +

MRP-227 +, MRP-175 +, MRP-228 +, MRP-191 +, MRP-210 +, MRP-232 +, MRP-230 +  and MRP-134 +

ML15261A830 +, ML15261A830 +, ML15261A830 +, ML15261A830 +, ML15261A830 +, ML15261A830 +, ML15261A830 +, ML15261A830 +  and ML15261A830 +

LBP-13-13 +  and LBP-08-13 +

NL-14-013, Additional Information Regarding the License Renewal Application - Action Item 7 from MRP-227-A +, NL-12-037, License Renewal Application - Revised Reactor Vessel Internals Program and Inspection Plan Compliant with MRP-227-A +, NL-10-063, Amendment 9 to License Renewal Application, Reactor Vessel Internals Program +  and NL-11-107, New York State (NYS) Pre-Filed Evidentiary Hearing Exhibit NYS000314, License Renewal Application- Completion of Commitment 30 Regarding the Reactor Vessel Internals Inspection Plan +

NRC 451 +, NRC 1041 +, NRC 460 +, NRC 461 +, NRC 1076 +, NRC 301 +, NRC 314 +, NRC 449 +, NRC 43 +, NRC 246 +, NRC 235 +, NRC 255 +, NRC 571 +, NRC 365 +, NRC 419 +, NRC 163 +  and NRC 93 +

CLI-09-07, Staff Assessment of the Oyster Creek 3-D Finite Element Analysis of the Drywell Shell +, CLI-01-17 +, CLI-15-06 +, CLI-06-10 +, CLI-83-19 +, CLI-05-15 +, CLI-10-14 +, CLI-10-17 +, CLI-01-22 +, CLI-08-23 +  and CLI-12-05, 6/12/2012 - Seabrook Lr Certified Index +

NUREG-1950, Official Exhibit - ENT000528-00-BD01 - NUREG-1950, Disposition of Public Comments and Technical Bases for Changes in the License Renewal Guidance Documents NUREG-1801 and NUREG-1800 (Apr. 2011) (Excerpted) +, NUREG-1930, Lr Hearing - NUREG-1930 in ADAMS +, NUREG-1800, Proposed Staff Guidance on Aging Management of Fire Protection Systems for License Renewal +  and NUREG-1801, Proprosed Revision of Chapters II & III of Generic Aging Lessons (Gall) Report on Aging Management of Concrete Elements +

50ft-lb +  and M16A-1 +

Pennsylvania +, Connecticut +, Maryland +, Washington +, Massachusetts +, New York +, Michigan +, Wisconsin +, Oklahoma +, Missouri +  and Arkansas +

Steam Generator +, Reactor Pressure Vessel +  and Control Rod +

Boric Acid +, Non-Destructive Examination +, Incorporated by reference +, Aging Management +, Stress corrosion cracking +, License Renewal +, Flow Induced Vibration +  and Thermal fatigue +