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CONTRACTED REPORT - RTA, QUICK LOOK, ETC. (PERIODIC  and TEXT-PROCUREMENT & CONTRACTS

IWB-2500 +, IWB-3000 +, IWC-2500 +, IWC-5222 +, IWB-1220 +, IWC-1220 +, IWC-2430 +, IWB-3515 +, IWB-2430 +, IWC-5210 +, IWB-3517 +, IWC-1230 +, IWA-6220 +, IWA-6230 +, IWA-6000 +, IWA-5000 +, IWA-4400 +, IWA-5250 +, IWA-3100 +, IWA-5211 +, IWA-4000 +, IWA-5213 +, IWA-2413 +, IWA-2600 +  and IWA-6340 +

Nitrogen +  and Lead +

10 CFR 50.55a Appendix J +, 10 CFR 50.55a +, 10 CFR 50.55a#g5 +, 10 CFR 50.55a#a3i +, 10 CFR 50.55a#a3 +, 10 CFR 50.55a#g4 +, 10 CFR 50.55a#b +, 10 CFR 50.55a#g6i +, 10 CFR 50.55a#a3ii +, 10 CFR 50.55a#c3 +, 10 CFR 50.55a#g6 +  and 10 CFR 50.55a#d2 +

ASME Code Case N-509 +, ASME Code Case N-498-1 +, ASME Code Case N-416-1 +, ASME Code Case N-524 +, ASME Code Case N-532 +, ASME Code Case N-498 +  and ASME Code Case N-522 +

05000321  +, 05000366  +, 00321  +  and 00366  +

IDAHO NATIONAL ENGINEERING & ENVIRONMENTAL LABORATORY +, Hall K +, Feige E +  and Mary Anderson +

NRC Generic Letter 81-11, BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking (NUREG-0619) +, NRC Generic Letter 88-01, NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping +  and NRC Generic Letter 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors +

L-96-018, Rev 1 to INEL-96/0188, TER on Third 10-Yr Interval Inservice Insp Program Plan:Gpc,Ei Hatch Nuclear Plant Units 1 & 2 +, L-96-018, Rev 1 to INEL-96/0188, TER on Third 10-Yr Interval Inservice Insp Program Plan:Gpc,Ei Hatch Nuclear Plant Units 1 & 2 +, L-96-018, Rev 1 to INEL-96/0188, TER on Third 10-Yr Interval Inservice Insp Program Plan:Gpc,Ei Hatch Nuclear Plant Units 1 & 2 +, L-96-018, Rev 1 to INEL-96/0188, TER on Third 10-Yr Interval Inservice Insp Program Plan:Gpc,Ei Hatch Nuclear Plant Units 1 & 2 +, L-96-018, Rev 1 to INEL-96/0188, TER on Third 10-Yr Interval Inservice Insp Program Plan:Gpc,Ei Hatch Nuclear Plant Units 1 & 2 +, L-96-018, Rev 1 to INEL-96/0188, TER on Third 10-Yr Interval Inservice Insp Program Plan:Gpc,Ei Hatch Nuclear Plant Units 1 & 2 +, L-96-018, Rev 1 to INEL-96/0188, TER on Third 10-Yr Interval Inservice Insp Program Plan:Gpc,Ei Hatch Nuclear Plant Units 1 & 2 +, L-96-018, Rev 1 to INEL-96/0188, TER on Third 10-Yr Interval Inservice Insp Program Plan:Gpc,Ei Hatch Nuclear Plant Units 1 & 2 +, L-96-018, Rev 1 to INEL-96/0188, TER on Third 10-Yr Interval Inservice Insp Program Plan:Gpc,Ei Hatch Nuclear Plant Units 1 & 2 +, L-96-018, Rev 1 to INEL-96/0188, TER on Third 10-Yr Interval Inservice Insp Program Plan:Gpc,Ei Hatch Nuclear Plant Units 1 & 2 +, L-96-018, Rev 1 to INEL-96/0188, TER on Third 10-Yr Interval Inservice Insp Program Plan:Gpc,Ei Hatch Nuclear Plant Units 1 & 2 +, L-96-018, Rev 1 to INEL-96/0188, TER on Third 10-Yr Interval Inservice Insp Program Plan:Gpc,Ei Hatch Nuclear Plant Units 1 & 2 +, L-96-018, Rev 1 to INEL-96/0188, TER on Third 10-Yr Interval Inservice Insp Program Plan:Gpc,Ei Hatch Nuclear Plant Units 1 & 2 +, L-96-018, Rev 1 to INEL-96/0188, TER on Third 10-Yr Interval Inservice Insp Program Plan:Gpc,Ei Hatch Nuclear Plant Units 1 & 2 +, L-96-018, Rev 1 to INEL-96/0188, TER on Third 10-Yr Interval Inservice Insp Program Plan:Gpc,Ei Hatch Nuclear Plant Units 1 & 2 +, L-96-018, Rev 1 to INEL-96/0188, TER on Third 10-Yr Interval Inservice Insp Program Plan:Gpc,Ei Hatch Nuclear Plant Units 1 & 2 +, L-96-018, Rev 1 to INEL-96/0188, TER on Third 10-Yr Interval Inservice Insp Program Plan:Gpc,Ei Hatch Nuclear Plant Units 1 & 2 +, L-96-018, Rev 1 to INEL-96/0188, TER on Third 10-Yr Interval Inservice Insp Program Plan:Gpc,Ei Hatch Nuclear Plant Units 1 & 2 +, L-96-018, Rev 1 to INEL-96/0188, TER on Third 10-Yr Interval Inservice Insp Program Plan:Gpc,Ei Hatch Nuclear Plant Units 1 & 2 +, L-96-018, Rev 1 to INEL-96/0188, TER on Third 10-Yr Interval Inservice Insp Program Plan:Gpc,Ei Hatch Nuclear Plant Units 1 & 2 +, L-96-018, Rev 1 to INEL-96/0188, TER on Third 10-Yr Interval Inservice Insp Program Plan:Gpc,Ei Hatch Nuclear Plant Units 1 & 2 +  and L-96-018, Rev 1 to INEL-96/0188, TER on Third 10-Yr Interval Inservice Insp Program Plan:Gpc,Ei Hatch Nuclear Plant Units 1 & 2 +

4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +  and 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +

ML20129D914 +, HL-5166, Requests Exemption from 10CFR70.24(a), Criticality Accident Requirements, Requirements for Units 1 & 2.Criticality Accident Monitoring Sys Unnecessary +  and HL-5118, Requests That NRC Grant Encl Third 10-yr Interval ISI Program Requests for Relief RR-13 & RR-14,based on Encl ASME Code Cases N-522 & N-532,respectively,in Response to NRC RAI & Clarification Re Util 960126 Submittal +

NUREG-0803, Forwards Request for Addl Info to Be Transmitted to Applicant Re Internally Generated Missiles & NUREG-0803 +, NUREG-0619, Informs That Staff Finds PP&L 980330 Request for Relief from Requirements of Section 4.3 of NUREG-0619,exams of Feedwater Nozzle Bore & Inner Radius for Another Operating Cycle to Be Acceptable +, NUREG-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +  and NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +

Nozzle:N12 +  and Nozzle:N16 +

Regulatory Guide 1.147 +  and Regulatory Guide 1.150 +

0AR-1 +, 1y-induced +, 2HX-A-1 +  and 2HX-B-1 +

Georgia +, Washington +  and Idaho +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, High Pressure Coolant Injection +, Reactor Core Isolation Cooling +, Primary containment +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Control Rod +  and Main Steam +

TS-3.4.1 +  and TS-3.4.2.1 +

Safe Shutdown +, Boric Acid +, High Radiation Area +, Hydrostatic +, Nondestructive Examination +, VT-2 +, Incorporated by reference +, Intergranular Stress Corrosion Cracking +, Integrated leak rate test +, Liquid penetrant +, Pressure boundary leak +, Through-Wall Leakage +  and Scaffolding +