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ASME Section XI +  and ASME Section III +

Carbon +, Oxygen +, Molybdenum +  and Lead +

10 CFR 50 Appendix J +, 10 CFR 50.12 +, 10 CFR 50.61 +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix H +, 10 CFR 54.3 +, 10 CFR 50.55a +, 10 CFR 50.61#b2 +, 10 CFR 54.21#c1 +, 10 CFR 54.21#c1i +, 10 CFR 54.21#c1ii +, 10 CFR 54.21#c1iii +, 10 CFR 50.55a#g6iiD +  and 10 CFR 50.55a#g6iiE +

ASME Code Case N-722 +, ASME Code Case N-729 +  and ASME Code Case N-770 +

L-2015-272, 1301103.401, Revision 0, Flaw Tolerance Evaluation of St. Lucie Surge Line Welds Using ASME Code Section XI, Appendix L, May 2015 +, L-2019-091, License Amendment Request to Modify the Reactor Coolant Pump (RCP) Flywheel Inspection Program Requirements +, L-2022-018, Amendment 27 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant +, L-2011-254, Inservice Inspection Program Fourth Interval-Second Period-Third Refueling Outage Owners Activity Report (OAR-1) +  and L-2002-222, Attachment 1, Supplemental Response to NRC Requests for Additional Information for Review of St. Lucie Units 1 & 2, License Renewal Application +

ML12235A463 +, ML12181A019 +, ML16235A138 +  and L-2011-524, Response to NRC Steam Generator Tube Integrity and Chemistry Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request +

EC-294618 +, EC-291838 +, EC-290921 +, EC-289971 +, EC-296122 +  and EC-296766 +

NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants +  and NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +

ML22111A114 +, ML22111A114 +, ML22111A114 +, ML22111A114 +, ML22111A114 +, ML22111A114 +, ML22111A114 +, ML22111A114 +, ML22111A114 +  and ML22111A114 +

L-2015-272, 1301103.401, Revision 0, Flaw Tolerance Evaluation of St. Lucie Surge Line Welds Using ASME Code Section XI, Appendix L, May 2015 +, L-2019-091, License Amendment Request to Modify the Reactor Coolant Pump (RCP) Flywheel Inspection Program Requirements +, L-2022-018, Amendment 27 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant +, L-2011-254, Inservice Inspection Program Fourth Interval-Second Period-Third Refueling Outage Owners Activity Report (OAR-1) +  and L-2002-222, Attachment 1, Supplemental Response to NRC Requests for Additional Information for Review of St. Lucie Units 1 & 2, License Renewal Application +

NUREG/CR-5704 +, NUREG/CR-6260 +, NUREG/CR-6583 +, NUREG/CR-5999, Forwards Updated Fatigue Design Curves for Austenitic Stainless Steels in LWR Environments.Design Curves Being Provided in Advance of Future Update of NUREG/CR-5999 to Facilitate Efforts on Resolution of GSI-190 +, NUREG-1779, Safety Evaluation Report Related to License Renewal of St. Lucie Nuclear Plant, Units 1 & 2 +  and NUREG-1801, Proprosed Revision of Chapters II & III of Generic Aging Lessons (Gall) Report on Aging Management of Concrete Elements +

Regulatory Guide 1.14 +  and Regulatory Guide 1.46 +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Auxiliary Feedwater +, Reactor Pressure Vessel +  and Main Steam +

Boric Acid +, Coatings +, Nondestructive Examination +, High Energy Line Break +, Aging Management +, Flow Accelerated Corrosion +, Stress corrosion cracking +, Moisture barrier +, License Renewal +, EVT-1 +, Fire Protection Program +, Power Uprate +, Overspeed +, Thermal fatigue +, Metamic +  and Leak-Before-Break +

WCAP-15973 +, WCAP-15973-P-A +  and WCAP-15793-P-A +

WCAP-15973 +, WCAP-15973-P-A +  and WCAP-15793-P-A +