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ASME Section XI +, ASME Section III +  and ASME Section VIII +

10 CFR 50.63 +, 10 CFR 54 +, 10 CFR 50.49 +, 10 CFR 50.61 +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix H +, 10 CFR 140.92#1 +, 10 CFR 50.55a +, 10 CFR 54.4#a3 +, 10 CFR 100#1 +  and 10 CFR 51#1 +

Mitra S +  and Office of Nuclear Reactor Regulation +

NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants +, NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +, NRC Generic Letter 89-08, Erosion/Corrosion-Induced Pipe Wall Thinning +, NRC Generic Letter 92-01, Reactor Vessel Structural Integrity +, NRC Generic Letter 96-04, Boraflex Degradation in Spent Fuel Pool Storage Racks +, NRC Generic Letter 97-05, Steam Generator Tube Inspection Techniques +  and NRC Generic Letter 97-01, Degradation of Control Rod Drive Mechanism Nozzle and Other Vessel Closure Head Penetrations +

ML040200991 +, ML040200991 +, ML040200991 +, ML040200991 +, ML040200991 +, ML040200991 +, ML040200991 +, ML040200991 +, ML040200991 +, ML040200991 +  and ML040200991 +

NEI 95-10, Official Exhibit - ENT000098-00-BD01 - Industry Guideline for Implementing the Requirements of 10 CFR Part 54 - the License Renewal Rule +  and NEI 97-06, Steam Generator Conditioning Monitoring Report +

NRC Bulletin 02-01 +, NRC Bulletin 01-01 +, NRC Bulletin 88-09 +, NRC Bulletin 82-02 +, NRC Bulletin 87-01 +, NRC Bulletin 88-11 +, NRC Bulletin 88-08 +, NRC Bulletin 88-02 +  and NRC Bulletin 89-01 +

Information Notice 90-04 +, Information Notice 89-33 +, Information Notice 94-87 +, Information Notice 1999-10, Degradation of Prestressing Tendon Systems in Prestresssed Concrete Containments +, Information Notice 1997-46, Unisolable Crack in High-Pressure Injection Piping +, Information Notice 91-19 +, Information Notice 89-65 +, Information Notice 1980-38, Cracking in Charging Pump Casing Cladding +, Information Notice 1987-28, Air Systems Problems at U.S. Light Water Reactors +, Information Notice 1987-43, Gaps in Neutron-Absorbing Material in High-Density Spent Fuel Storage Racks +, Information Notice 1993-70, Degradation of Boraflex Neutron Absorber Coupons +, Information Notice 1995-38, Degradation of Boraflex Neutron Absorber in Spent Fuel Storage Racks +  and Information Notice 2000-17, Crack in Weld Area of Reactor Coolant System Hot Leg Piping at V.C. Summer +

NUREG/CR-5704 +, NUREG/CR-6260 +, NUREG/CR-6583 +, NUREG/CR-1004 +, NUREG/CR-1557 +, NUREG/CR-1801 +, NUREG/CR-1800 +, NUREG/CR-5576 +, NUREG/CR-0313 +, NUREG/CR-1437 +, NUREG/CR-0612 +, NUREG/CR-1522 +, NUREG/CR-1739, Forwards NUREG/CR-1739,Vols 1 & 2 Re Floor Plan of NRC Operations Ctr & Diagram Indicating Info Flow,Respectively. W/O Encl +, 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-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 +

Regulatory Guide 1.155 +, Regulatory Guide 1.65 +, Regulatory Guide 1.99 +, Regulatory Guide 1.188 +  and Regulatory Guide 1.89 +

Steam Generator +, Reactor Coolant System +, Feedwater +, Auxiliary Feedwater +, Reactor Pressure Vessel +  and Control Rod +

Moyer J +  and Carolina Power & Light Company +

Boric Acid +, Aging Management +, Flow Accelerated Corrosion +, Stress corrosion cracking +  and License Renewal +

WCAP-15805 +, WCAP-15828 +, WCAP-14574-A +, WCAP-13045 +, WCAP-15338 +, WCAP-13587 +, WCAP-15628 +, WCAP-15363 +, WCAP-12962 +, WCAP-15628-NP +, WCAP-10322 +, WCAP-14209 +  and WCAP-14575A +

WCAP-15805 +, WCAP-15828 +, WCAP-14574-A +, WCAP-13045 +, WCAP-15338 +, WCAP-13587 +, WCAP-15628 +, WCAP-15363 +, WCAP-12962 +, WCAP-15628-NP +, WCAP-10322 +, WCAP-14209 +  and WCAP-14575A +