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Iodine +, Cobalt +, Cesium +, Nickel +, Potassium +, Zinc +  and Niobium +

10 CFR 20 +, 10 CFR 50 +, 10 CFR 20 Appendix B +, 10 CFR 50.59 +, 10 CFR 20.1003 +, 10 CFR 20.1302 +, 10 CFR 20.2203 +, 10 CFR 50.4 +, 10 CFR 50.90 +, 10 CFR 50 Appendix I +, 10 CFR 50.36a +, 10 CFR 50.36a#a2 +, 10 CFR 20.106 +, 10 CFR 50.36a#3 +, 10 CFR 20.106#10 +, 10 CFR 10.50 +, 10 CFR 20.1302#40 +, 10 CFR 20.1302#3 +, 10 CFR 20 Appendix B#20 +  and 10 CFR 50#3 +

05000334  +  and 05000412  +

FM-1 +  and FM-1GW-101 +

ML13126A043 +, ML13126A043 +, ML13126A043 +, ML13126A043 +, ML13126A043 +, ML13126A043 +, ML13126A043 +, ML13126A043 +, ML13126A043 +, ML13126A043 +, ML13126A043 +, ML13126A043 +, ML13126A043 +  and ML13126A043 +

9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +  and 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +

H-3 +  and Tritium +

ML20235K002 +  and IR 05000334/1989001 +

NUREG-1431 +, NUREG-1301, Amends 188 & 70 to Licenses DPR-66 & NPF-73,respectively, Revising App a TSs by Relocating Requirements of RETS & Solid Radwaste TSs from App a TSs to ODCM or to PCP in Accordance W/Gl 89-01 & NRC Rept NUREG-1301 +, NUREG-130 +, NUREG/CR-2919 +, NUREG-0172 +, NUREG/CR-2907, Responds to 851105 Request for Info Re Radwaste & Containment Spray Sys.Nrc Methodology for Estimating Radwaste Generation Delineated in Encl NUREG-0017.USA Experience Summarized in Encl NUREG/CR-2907.W/o Encls +, NUREG-0133, Safety Evaluation Accepting Licensee Rev 3 to ODCM for Plant Through Temporary Change 4.Rev Meets Criteria of NUREG-0133 & Other Guidance. Guidance +, NUREG-0473, Forwards Draft,Rev 3 to NUREG-0472, Std Radiological Effluent Controls for Pwrs, Containing Draft Guidance for Radiological Effluent Tech Specs/Odcm Commitments,Per Generic Ltr 89-01 +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +  and NUREG-0324, Forwards Crac Code Input for 790328-0402 at Site.Wind Speeds Corrected to 10 Meter Level Using Procedures Outlined in NUREG-0324 +

TAC:93996 +  and TAC:63996 +

Regulatory Guide 1.97 +, Regulatory Guide 1.1 +, Regulatory Guide 1.21 +, Regulatory Guide 1.109 +, Regulatory Guide 1.23 +  and Regulatory Guide 1.113 +

SR-4.11.2.4.1 +, SR-4.11.2.2.1 +, SR-4.11.1.1.3 +, SR-4.11.4.1.1 +, SR-4.11.1.4.1 +, SR-4.11.2.3.1 +, SR-4.12.3.1 +  and SR-8.1.8.3 +

1MSP-1 +, 2SWS-RQ100A +, 2SGC-RQ100 +, 2RMF-RQ301A +, 2MSP-43 +, 2HVS-RQ101 +, 2RMQ-RQ301 +, 2HVL-RQ112 +, 2OST-43 +, 2RMQ-RQ303 +, 20M-1 +, 2HVS-RQ109B +, 2RMQ-RQ303B +, 2HVS-RQ109A +, 2OM-54 +, 1OST-43 +, 20M-54 +, 1OM-54 +, 2RMR-RQ203 +, 2CHS-RQ101A +, 2A-193 +, 2SWS-RQ101 +, 2SWS-RQ102 +, 1MSP-43 +, 1A-188 +, 1A-246 +, 1A-250 +, 1A-175 +, 1A-287 +, 1A-291 +...

Ohio +  and Idaho +

Steam Generator +, Reactor Coolant System +, Auxiliary Feedwater +  and Safety Relief Valve +

TS-3.3.3.1 +, TS-3.11.2.5 +, TS-6.14 +, TS-6.9.1 +, TS-6.9 +, TS-3.11.1.4 +  and TS-6.8.6 +

Grab sample +, Offsite Dose Calculation Manual +, Anticipated operational occurrence +, Annual Radioactive Effluent Release Report +, Sewage Treatment Plant +, Stress corrosion cracking +  and Power Uprate +

F-LW-1 +, F-LW-104-2 +, F-LW-104-1 +  and F-LW-103 +