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CORRESPONDENCE-LETTERS, NRC TO U.S. CONGRESS  and OUTGOING CORRESPONDENCE

Iodine +, Cesium +, Carbon +, Oxygen +, Hydrogen +, Cadmium +, Indium +, Lead +, Silver +  and Tellurium +

Emergency Preparedness +  and Initiating Events +

05000443  +  and 05000444  +

Stello V +  and NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) +

ML20214T383 +, ML20214T383 +, ML20214T383 +, ML20214T383 +, ML20214T383 +, ML20214T383 +, ML20214T383 +, ML20214T383 +, ML20214T383 +, ML20214T383 +, ML20214T383 +, ML20214T383 +, ML20214T383 +, ML20214T383 +, ML20214T383 +, ML20214T383 +, ML20214T383 +, ML20214T383 +, ML20214T383 +, ML20214T383 +, ML20214T383 +, ML20214T383 +, ML20214T383 +  and ML20214T383 +

6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +  and 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +

ML20197B365 +, ML20203E594 +, ML20207B600 +  and ML20211J303 +

NUREG/CR-2239, Forwards Slides/Handout Used at 821110 Presentation of NUREG/CR-2239 Re Sandia Siting or Consequences Study. Transcript of Meeting in PDR Did Not Include Slides +, NUREG-0356 +, NUREG-1150, Weekly Info Rept for Wk Ending 890922 +, NUREG-1037, Requests Support in Development & Implementation of New Accident Source Term Info to Improve Regulations & Related Regulatory & Staff Practices,Per 860326 Presentation of SECY-86-76 +, NUREG-1079, Forwards Documents to Be Placed on Document Control Sys. Advance Copy Already Sent to PDR +, NUREG-0900, Informs Commission of Status of Staff Reassessment of Source Terms & Related Severe Accident Research Activities,For Use in Implementing Commission Severe Accident Policy Statement. NEA Mar 1986 Rept, Nuclear Reactor...Source Terms, Encl +, NUREG-0772, Contract: Evaluate NUREG-0772, Technical Bases for Estimating Fission Product Behavior During LWR Accidents, Awarded to Jl Kelly +, NUREG-1050, Forwards Regulatory Analysis of Generic Safety Issue 61, Safety/Relief Valve Discharge Line Break within Mark I or II Wetwell Airspace. Based on Results Discussed in NUREG/CR-4594,risk Lower than Previously Estimated +  and NUREG-0090, SECY-25-0016: Enclosure 1 - NUREG-0090, Volume 47, Report to Congress on Abnormal Occurrences: Fiscal Year 2024 +

Maryland +, Washington +  and California +

Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Auxiliary Feedwater +, Residual Heat Removal +, Decay Heat Removal +, Control Rod +  and Containment Spray +

Markey E +, HOUSE OF REP. +  and ENERGY & COMMERCE +

Hydrostatic +, Probabilistic Risk Assessment +, Exemption Request +, Chernobyl +  and Fuel cladding +