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ASME Section III +  and ASME Section XI +

Iron +, Carbon +, Oxygen +, Chloride +, Lead +  and Aluminum +

10 CFR 50 Appendix J +, 10 CFR 50.59 +  and 10 CFR 54 +

SECY-96-146 +, L-90-230, Reactor Containment Bldg Integrated Leakage Rate Test Final Rept +, L-89-230, Reactor Containment Bldg Integrated Leak Rate Test +, L-93-206, Forwards St Lucie Nuclear Plant,Unit 1 Reactor Containment Bldg ILRT Rept,Documenting Results of Type a Leakage Rate Testing & Including Suppl Controlled Leakage Rate Test Method Utilized for Verification.Test Completed on 930520 +, L-92-251, Reactor Containment Bldg Integrated Leakage Rate Test. W/ +, L-87-237, Forwards Reactor Containment Bldg Integrated Leakage Rate Test, Final Rept,Per App J to 10CFR50 +, L-75-510 +, L-2002-061, Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity +, L-2002-116 +, L-2002-61 +, L-2002-185, Response to NRC Bulletin 2002-02 - Reactor Pressure Vessel Head Penetration Nozzle Inspection Programs +, L-79-214, Forwards Reactor Containment Bldg Integrated Leak Rate Test +, L-83-116, Forwards Reactor Containment Bldg Integrated Leakage Rate Test, Final Rept,Per App J Requirements +, L-83-434, Forwards Rev 7 to Security Plan.Rev Withheld (Ref 10CFR73.21) +, L-86-343, Forwards Final Rept, Reactor Containment Bldg Integrated Leakage Rate Test, Per App J to 10CFR50 +, L-2002-166, Response to NRC Request for Additional Information for Review of the License Renewal Application +  and L-2002-159, Response to NRC Request for Additional Information for Review of the License Renewal Application +

05000335  +, 05000389  +, 00335  +  and 00389  +

Jernigan D +  and NextEra Energy +

NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +  and NRC Generic Letter 88-14, Instrument Air Supply System Problems Affecting Safety-Related Equipment +

L-2002-166, Response to NRC Request for Additional Information for Review of the License Renewal Application +, L-2002-166, Response to NRC Request for Additional Information for Review of the License Renewal Application +, L-2002-166, Response to NRC Request for Additional Information for Review of the License Renewal Application +, L-2002-166, Response to NRC Request for Additional Information for Review of the License Renewal Application +, L-2002-166, Response to NRC Request for Additional Information for Review of the License Renewal Application +, L-2002-166, Response to NRC Request for Additional Information for Review of the License Renewal Application +, L-2002-166, Response to NRC Request for Additional Information for Review of the License Renewal Application +, L-2002-166, Response to NRC Request for Additional Information for Review of the License Renewal Application +, L-2002-166, Response to NRC Request for Additional Information for Review of the License Renewal Application +, L-2002-166, Response to NRC Request for Additional Information for Review of the License Renewal Application +, L-2002-166, Response to NRC Request for Additional Information for Review of the License Renewal Application +, L-2002-166, Response to NRC Request for Additional Information for Review of the License Renewal Application +, L-2002-166, Response to NRC Request for Additional Information for Review of the License Renewal Application +  and L-2002-166, Response to NRC Request for Additional Information for Review of the License Renewal Application +

L-90-230, Reactor Containment Bldg Integrated Leakage Rate Test Final Rept +, L-89-230, Reactor Containment Bldg Integrated Leak Rate Test +, L-93-206, Forwards St Lucie Nuclear Plant,Unit 1 Reactor Containment Bldg ILRT Rept,Documenting Results of Type a Leakage Rate Testing & Including Suppl Controlled Leakage Rate Test Method Utilized for Verification.Test Completed on 930520 +, L-92-251, Reactor Containment Bldg Integrated Leakage Rate Test. W/ +, L-87-237, Forwards Reactor Containment Bldg Integrated Leakage Rate Test, Final Rept,Per App J to 10CFR50 +, L-75-510 +, L-2002-061, Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity +, L-2002-116 +, L-2002-61 +, L-2002-185, Response to NRC Bulletin 2002-02 - Reactor Pressure Vessel Head Penetration Nozzle Inspection Programs +, L-79-214, Forwards Reactor Containment Bldg Integrated Leak Rate Test +, L-83-116, Forwards Reactor Containment Bldg Integrated Leakage Rate Test, Final Rept,Per App J Requirements +, L-83-434, Forwards Rev 7 to Security Plan.Rev Withheld (Ref 10CFR73.21) +, L-86-343, Forwards Final Rept, Reactor Containment Bldg Integrated Leakage Rate Test, Per App J to 10CFR50 +, L-2002-166, Response to NRC Request for Additional Information for Review of the License Renewal Application +  and L-2002-159, Response to NRC Request for Additional Information for Review of the License Renewal Application +

NRC Bulletin 02-01 +  and NRC Bulletin 02-02 +

Information Notice 92-20 +  and Information Notice 85-24 +

Washington +, Virginia +  and Florida +

Steam Generator +, Service water +, Emergency Diesel Generator +, Auxiliary Feedwater +  and Shield Building +

Document Control Desk +  and Office of Nuclear Reactor Regulation +

Non-Destructive Examination +, Fire Barrier +, Coatings +, Aging Management +, Local Leak Rate Testing +, Microbiologically influenced corrosion +, Stress corrosion cracking +, Integrated leak rate test +, License Renewal +, Biofouling +, Through-Wall Leakage +  and Fire Protection Program +