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Department of Natural Resources +  and Minnesota Department Of Health +

Carbon +, Oxygen +  and Plutonium +

10 CFR 54.4#a2 +, 10 CFR 51.53#c3iiE +, 10 CFR 51.53#c3iiK +, 10 CFR 2.309#f1i +  and 10 CFR 2.309#f1iii +

NRC 10 +  and NRC 138 +

05000282  +, 05000306  +, 00282  +  and 00306  +

ML052440054 +, Information Notice 2007-06, Potential Common Cause Vulnerabilities in Essential Service Water Systems +, Information Notice 1991-19, Steam Generator Feedwater Distribution Piping Damage +, Information Notice 1997-84, Rupture in Extraction Steam Piping as a Result of Flow-Accelerated Corrosion +, ML062650312 +, ML060930382 +, ML072890262 +, ML050400613 +, ML05291008 +, ML020630459 +, Press Release-III-07-024, - NRC Begins Special Inspection at Byron Nuclear Station to Review Corrosion and Leakage of Equipment Cooling Water Piping +, PNO-IV-06-001, Arizona Public Service Company - Followup for Tritium Contamination Found in Water Onsite +, PNO-III-07-012, Both Units at Byron Shut Down Due to a Lead in Pipe +, PNO-II-07-012A, Update - Onsite Ground Water Tritium Contamination at the Catawba Nuclear Station Site, Units 1 & 2 +  and PNO-III-05-016A, Braidwood Potential Off-Site Migration of Tritium Contamination +

Prairie Island Indian Community +  and Mahowald P +

ML082391038 +, ML082391038 +, ML082391038 +, ML082391038 +, ML082391038 +, ML082391038 +, ML082391038 +, ML082391038 +, ML082391038 +  and ML082391038 +

NRC 10 +  and NRC 138 +

NRC Bulletin 03-02 +  and NRC Bulletin 87-01 +

Information Notice 2007-06, Potential Common Cause Vulnerabilities in Essential Service Water Systems +, Information Notice 2006-13, E-mail from M. Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination +, Information Notice 2006-08, Secondary Piping Rupture at Mihama Power Station in Japan +, Information Notice 2004-05, Spent Fuel Pool Leakage to Onsite Groundwater +, Information Notice 1991-19, Steam Generator Feedwater Distribution Piping Damage +  and Information Notice 1997-84, Rupture in Extraction Steam Piping as a Result of Flow-Accelerated Corrosion +

NUREG/CR-6936 +, NUREG-1555, Supplement 1, Revision 2, Standard Review Plans for Environmental Reviews for Nuclear Power Plants Supplement 1: Operating License Renewal Final Report +, 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 +

202L-R2 +  and 470w-6 +

Connecticut +, Arizona +, Illinois +, Minnesota +, New Jersey +, South Carolina +, New York +, Florida +, Louisiana +, Missouri +, Mississippi +  and Alaska +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Reactor Pressure Vessel +, Emergency Core Cooling System +  and Extraction steam +

Safe Shutdown +, Ultimate heat sink +, Probabilistic Risk Assessment +, Coatings +, Aging Management +, Flow Accelerated Corrosion +, Stress corrosion cracking +, License Renewal +  and Environmental Justice +

Cooling Tower +, Mississippi River +  and Kankakee River +