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IWB-2500 +, IWC-2500 +, IWB-4000 +  and IWB-7000 +

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

Boron +, Iodine +, Iron +, Nickel +, Copper +, Nitrogen +, Carbon +, Oxygen +, Hydrogen +, Chloride +  and Lead +

10 CFR 50.48 +, 10 CFR 50 +, 10 CFR 50.63 +, 10 CFR 50 Appendix J +, 10 CFR 54 +, 10 CFR 50.49 +, 10 CFR 50.61 +, 10 CFR 50.65 +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix H +, 10 CFR 54.3 +, 10 CFR 54.4 +, 10 CFR 54.21 +, 10 CFR 54.35, Requirements During Term of Renewed License +, 10 CFR 100.11 +, 10 CFR 2.790 +, 10 CFR 50.55a +, 10 CFR 54.4#a +, 10 CFR 54.4#a2 +, 10 CFR 54.4#a3 +, 10 CFR 54.4#a1 +, 10 CFR 54.4#b +, 10 CFR 54.3#a +, 10 CFR 50.49#f +, 10 CFR 54.21#d +, 10 CFR 54.21#c1 +, 10 CFR 54.21#c1ii +, 10 CFR 54.21#a1 +, 10 CFR 54.21#a1i +, 10 CFR 54.21#c +...

05000261  +  and 00261  +

FP-5 +, FP-61 +, FP-588 +, FP-585 +, FP-590 +, FP-56 +, FP-54 +, FP-58 +, FP-90 +, FP-71 +, FP-750 +, FP-449 +, FP-518 +, FP-575 +, FP-735 +, FP-565 +, FP-468 +, FP-806 +  and FP-793 +

Mitra S +  and Division of Regulatory Improvement Programs +

NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants +, 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 +

ML030640168 +, ML030640168 +, ML030640168 +, ML030640168 +, ML030640168 +, ML030640168 +, ML030640168 +, ML030640168 +, ML030640168 +, ML030640168 +, ML030640168 +, ML030640168 +, ML030640168 +  and ML030640168 +

9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +  and 4.62963e-4 d (0.0111 hours, 6.613757e-5 weeks, 1.522e-5 months)  +

LRA B.2.6 +  and LRA B.3.4 +

RNP-RA/02-0041, Submittal of Information Requested by NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity +  and ML14178B098 +

Westinghouse +, Limitorque +  and Target Rock +

NEI 95-10, Official Exhibit - ENT000098-00-BD01 - Industry Guideline for Implementing the Requirements of 10 CFR Part 54 - the License Renewal Rule +, 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 02-01 +, NRC Bulletin 01-01 +, NRC Bulletin 88-09 +, NRC Bulletin 88-08 +, NRC Bulletin 88-02 +  and NRC Bulletin 89-01 +

Information Notice 98-11 +, Information Notice 87-28 +, Information Notice 90-04 +, Information Notice 89-33 +, Information Notice 94-87 +, Information Notice 99-10 +, Information Notice 89-65 +  and Information Notice 2001-09, Main Feedwater System Degradation in Safety-Related ASME Code Class 2 Piping Inside the Containment of a Pressurized Water Reactor +

NUREG/CR-5704 +, NUREG/CR-6260 +, NUREG/CR-6583 +, NUREG/CR-5576 +, 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-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 +

Vince Klco +, Steve Jones +, John Lehning +, John Tsao +, James Medoff +, Stewart Bailey +, Bill Rogers +  and John Ma +

Regulatory Guide 1.163 +, Regulatory Guide 1.155 +, Regulatory Guide 1.190 +  and Regulatory Guide 1.99 +

North Carolina +, Washington +  and South Carolina +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Auxiliary Feedwater +, HVAC +, Reactor Pressure Vessel +, Residual Heat Removal +, Circulating Water System +, Emergency Core Cooling System +, Decay Heat Removal +, Control Rod +, Auxiliary Feed Water +, Main Steam +, Containment Spray +  and Extraction steam +

Safe Shutdown +, Boric Acid +, Ultimate heat sink +, Fire Barrier +, Anticipated operational occurrence +, Coatings +, Nondestructive Examination +, VT-2 +, Aging Management +, Flow Accelerated Corrosion +, Stress corrosion cracking +, Loss of Offsite Power +, Eddy Current Testing +, Moisture barrier +, License Renewal +, Maintenance Rule Program +, Biofouling +, Fire Protection Program +, Affidavit +, Overspeed +, Thermal fatigue +  and Spent fuel rack +

WCAP-13587 +, WCAP-14574 +, WCAP-15363 +, WCAP-10322 +  and WCAP-14209 +

WCAP-13587 +, WCAP-14574 +, WCAP-15363 +, WCAP-10322 +  and WCAP-14209 +