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ACI-201 +  and ACI-349 +

ANSI B31.1 +, ANSI/ANS 56.8 +  and ANSI 831.1.0 +

Boron +, Iron +, Nickel +, Copper +, Carbon +, Oxygen +, Sodium +, Molybdenum +, Chloride +, Lead +, Aluminum +  and Titanium +

10 CFR 50 Appendix A +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50 Appendix B +, 10 CFR 54 +, 10 CFR 50.49 +, 10 CFR 50.65 +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix H +, 10 CFR 54.21 +, 10 CFR 50.55a +, 10 CFR 50.49#a +, 10 CFR 50.61#b2 +, 10 CFR 50.61#b1 +, 10 CFR 54.21#d +, 10 CFR 54.21#c1 +, 10 CFR 54.21#c1i +, 10 CFR 54.21#c1ii +, 10 CFR 54.21#c1iii +, 10 CFR 54.21#c +  and 10 CFR 50.55#a +

ASME Code Case N-729-1 +, ASME Code Case N-578-1 +  and ASME Code Case N-481 +

05000272  +  and 05000311  +

NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants +, NRC Generic Letter 88-08, Mail Sent or Delivered to the Office of Nuclear Reactor Regulation +  and NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +

LR-N18-0053, 0 to Updated Final Safety Analysis Report, Appendix B, License Renewal Final Safety Analysis Report Supplement +, LR-N18-0053, 0 to Updated Final Safety Analysis Report, Appendix B, License Renewal Final Safety Analysis Report Supplement +, LR-N18-0053, 0 to Updated Final Safety Analysis Report, Appendix B, License Renewal Final Safety Analysis Report Supplement +, LR-N18-0053, 0 to Updated Final Safety Analysis Report, Appendix B, License Renewal Final Safety Analysis Report Supplement +, LR-N18-0053, 0 to Updated Final Safety Analysis Report, Appendix B, License Renewal Final Safety Analysis Report Supplement +, LR-N18-0053, 0 to Updated Final Safety Analysis Report, Appendix B, License Renewal Final Safety Analysis Report Supplement +, LR-N18-0053, 0 to Updated Final Safety Analysis Report, Appendix B, License Renewal Final Safety Analysis Report Supplement +, LR-N18-0053, 0 to Updated Final Safety Analysis Report, Appendix B, License Renewal Final Safety Analysis Report Supplement +, LR-N18-0053, 0 to Updated Final Safety Analysis Report, Appendix B, License Renewal Final Safety Analysis Report Supplement +, LR-N18-0053, 0 to Updated Final Safety Analysis Report, Appendix B, License Renewal Final Safety Analysis Report Supplement +, LR-N18-0053, 0 to Updated Final Safety Analysis Report, Appendix B, License Renewal Final Safety Analysis Report Supplement +, LR-N18-0053, 0 to Updated Final Safety Analysis Report, Appendix B, License Renewal Final Safety Analysis Report Supplement +  and LR-N18-0053, 0 to Updated Final Safety Analysis Report, Appendix B, License Renewal Final Safety Analysis Report Supplement +

0.00926 d (0.222 hours, 0.00132 weeks, 3.044e-4 months)  +  and 0 d (0 hours, 0 weeks, 0 months)  +

LRA B.2.1.7 +, LRA B.2.1.9 +, LRA B.2.1.11 +, LRA B.2.1.21 +, LRA B.2.1.29 +, LRA B.2.1.30 +, LRA B.2.1.32 +, LRA B.2.1.39 +, LRA B.2.2.3 +  and LRA B.2.2.6 +

NEI 97-06, Steam Generator Conditioning Monitoring Report +  and NEI 94-01, License Amendment Request Supplement Pursuant to 10 CFR 50.90: Adoption of NEI 94-01, Revision 2-A, and Extension of Primary Containment Integrated Leakage Rate Test Interval to Fifteen (15) Years +

NRC Bulletin 80-11 +, NRC Bulletin 88-09 +, NRC Bulletin 88-11 +  and NRC Bulletin 88-08 +

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-0612, Safety Evaluation Supporting Util Request to Delete Three Commitments in Response to NUREG-0612 Re Heavy Load Control on 5-ton Electric Monorail Hoist W/Integral Trolley & 4-ton Monorail Chain Hoist W/Geared Trolley +, NUREG-0588, Responds to 870709 Request for NRR Assistance in Determining Adequacy of Two Test Repts Re Acceptance Criteria of NUREG-0588,Category I.Qualification of Kulka Terminal Blocks Demonstrated & Not Used in Instrumentation Circuits +, NUREG-1339, Summarizes Resolution of GI 29 Bolting Degradation or Failure in Nuclear Power Plants +, NUREG-0554, Responds to to Chairman Jackson Re Resolution of Berkeley Township Environ Commission. Forwards Reply to L Worrall Which Contains Directors Decision,Per 10CFR2.206 +, NUREG-1800, Proposed Staff Guidance on Aging Management of Fire Protection Systems for License Renewal +, NUREG-1801, Proprosed Revision of Chapters II & III of Generic Aging Lessons (Gall) Report on Aging Management of Concrete Elements +  and NUREG-2192, Rev. 1, Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants Final Report +

RT +  and TOP +

Regulatory Guide 1.163 +, Regulatory Guide 1.160 +, Regulatory Guide 1.127 +, Regulatory Guide 1.65 +, Regulatory Guide 1.99 +, Regulatory Guide 1.43 +  and Regulatory Guide 1.89 +

S1DF-1DFE21 +, S1DF-1DFE2 +, S2DF-2DFE1 +  and S2DF-2DFE2 +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Auxiliary Feedwater +, Primary containment +, HVAC +, Reactor Pressure Vessel +  and Circulating Water System +

Safe Shutdown +, Boric Acid +, Non-Destructive Examination +, Fire Barrier +, Hydrostatic +, Coatings +, Operating Basis Earthquake +, Nondestructive Examination +, VT-2 +, High Energy Line Break +, Aging Management +, Design basis earthquake +, Flow Accelerated Corrosion +, Feedwater Heater +, Intergranular Stress Corrosion Cracking +, Microbiologically influenced corrosion +, Stress corrosion cracking +, Eddy Current Testing +, Moisture barrier +, License Renewal +, Earthquake +, Biofouling +, Fire Protection Program +, Power Uprate +, Overspeed +, Thermography +, Thermal fatigue +  and Leak-Before-Break +