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Iron +, Lead +  and Plutonium +

10 CFR 50 Appendix A +, 10 CFR 50.63 +, 10 CFR 2 +, 10 CFR 51 +, 10 CFR 54 +, 10 CFR 50.49 +, 10 CFR 54.4 +, 10 CFR 54.21 +, 10 CFR 54.29 +, 10 CFR 54.37 +, 10 CFR 54.4#a3 +  and 10 CFR 51.53#C +

SECY-99-148 +, NRC 39 +, NRC 111 +, NRC 13 +, NRC 142 +, NRC 317 +, NRC 124 +, NRC 281 +, NRC 451 +, NRC 207 +, NRC 1041 +, NRC 18 +, NRC 287 +, NRC 460 +, NRC 461 +, NRC 631 +, NRC 383 +, NRC 328 +, NRC 90 +, NRC 1423 +, NRC 237 +, NRC 257 +, NRC 113 +, NRC 509 +, NRC 131 +, NRC 43 +, NRC 149 +, NRC 139 +, NRC 433 +, NRC 325 +...

ML073400187 +, ML073410093 +, ML073400205 +, ML060530203 +, ML071430583 +, ML003751930 +, ML051860406 +, ML060930382 +, ML072890262 +, ML071640133 +, ML061640065 +, ML101620331 +, ML101620333 +, ML101620334 +, ML101620329 +, ML101620330 +, ML102420042 +, ML062560259 +, NRC Generic Letter 2007-01 +, ML003727052 +, ML1026660219 +, ML071290579 +, ML02090464 +, SBK-L-10095, Drawing PID-1-MAH-LR20497, Rev. 9, Through Drawing PID-1-SF-LR20482 +, PNO-IV-06-001, Arizona Public Service Company - Followup for Tritium Contamination Found in Water Onsite +, ML072850013 +  and PNO-III-07-012, Both Units at Byron Shut Down Due to a Lead in Pipe +

NextEra Energy Seabrook +  and Hamrick S +

ML103190494 +, ML103190494 +, ML103190494 +, ML103190494 +, ML103190494 +, ML103190494 +, ML103190494 +, ML103190494 +, ML103190494 +, ML103190494 +, ML103190494 +, ML103190494 +, ML103190494 +, ML103190494 +, ML103190494 +, ML103190494 +  and ML103190494 +

Union of Concerned Scientists +, Pilgrim Watch +, Beyond Nuclear +  and Sierra Club +

LBP-08-13 +, LBP-05-31 +, LBP-06-20 +, LBP-06-23 +, LBP-10-19 +, LBP-92-37 +, LBP-90-16 +, LBP-01-39 +, LBP-08-26 +, LBP-83-76 +, LBP-07-13 +, LBP-09-03 +, LBP-08-23 +  and LBP-07-12 +

ML020910482 +  and ML101180134 +

NEI 95-10, Official Exhibit - ENT000098-00-BD01 - Industry Guideline for Implementing the Requirements of 10 CFR Part 54 - the License Renewal Rule +  and NEI 05-01 +

NRC 39 +, NRC 111 +, NRC 13 +, NRC 142 +, NRC 317 +, NRC 124 +, NRC 281 +, NRC 451 +, NRC 207 +, NRC 1041 +, NRC 18 +, NRC 287 +, NRC 460 +, NRC 461 +, NRC 631 +, NRC 383 +, NRC 328 +, NRC 90 +, NRC 1423 +, NRC 237 +, NRC 257 +, NRC 113 +, NRC 509 +, NRC 131 +, NRC 43 +, NRC 149 +, NRC 139 +, NRC 433 +, NRC 325 +, NRC 195 +...

CLI-06-09 +, CLI-01-17 +, CLI-06-10 +, CLI-00-05 +, CLI-95-12 +, CLI-10-01 +, CLI-99-11 +, CLI-91-12 +, CLI-00-06 +, CLI-96-07 +, CLI-89-03 +, CLI-09-12 +, CLI-03-17 +, CLI-02-17 +, CLI-03-14 +, CLI-83-19 +, CLI-00-20 +, CLI-03-13 +, CLI-10-14 +, CLI-04-36 +, CLI-10-17 +, CLI-10-22 +, CLI-09-08 +, CLI-02-25 +, CLI-05-20 +, CLI-06-16 +, CLI-01-22 +, CLI-08-23 +, CLI-95-10 +, CLI-02-26 +...

NUREG/BR-0058 +, NUREG/BR-0184 +, NUREG/CR-5643 +, NUREG/CR-7000 +, NUREG-1950, Official Exhibit - ENT000528-00-BD01 - NUREG-1950, Disposition of Public Comments and Technical Bases for Changes in the License Renewal Guidance Documents NUREG-1801 and NUREG-1800 (Apr. 2011) (Excerpted) +, NUREG-7000 +, NUREG/CR-5643.24 +, NUREG-1465.50 +, NUREG-1907, Letter to Board from Staff Transmitting NUREG-1907-Safety Evaluation Report Related to License Renewal of Vermont Yankee Nuclear Power Station, Volumes 1 and 2 +, NUREG-1150, Weekly Info Rept for Wk Ending 890922 +, NUREG-1465, Provides Commission W/Results & Findings of Evaluation of Impact of Implementing Revised Source Term Described in NUREG-1465, Accident Source Terms for Light-Water Npps, for Operating Reactors +, NUREG/CR-6613, Exhibit K - NUREG/CR-6613, Vol. 1, SAND97-0594 - Code Manual for MACCS2 - Users Guide +, NUREG-1800, Proposed Staff Guidance on Aging Management of Fire Protection Systems for License Renewal +, NUREG-1801, Proprosed Revision of Chapters II & III of Generic Aging Lessons (Gall) Report on Aging Management of Concrete Elements +  and NUREG-1437, Supp. 17, Second Renewal, Generic Environmental Impact Statement for License Renewal of Nuclear Plants Supplement 17, Second Renewal Regarding Subsequent License Renewal for Dresden Nuclear Power Station, Units 2 and 3 Final Rep +

PNO-III-08-011, D. C. Cook - Unit 1 Manual Trip Due to Main Turbine Generator Fire and Significant Fire Suppression System Degradation +, PNO-II-07-012, Catawba Nuclear Station Units 1 & 2, Onsite Ground Water Tritium Contamination +  and PNO-III-07-012, Both Units at Byron Shut Down Due to a Lead in Pipe +

Mary Spencer +, Megan Wright +  and Edwin Lyman +

Texas +, Pennsylvania +, Connecticut +, Utah +, Arizona +, Georgia +, Washington +, California +, Massachusetts +, South Carolina +, New York +, Florida +, Louisiana +, Oklahoma +, Indiana +, New Hampshire +, Vermont +  and Maine +

Reactor Coolant System +, Feedwater +, Service water +  and Auxiliary Feedwater +

Anticipated operational occurrence +, Hydrostatic +, Probabilistic Risk Assessment +, Coatings +, High Energy Line Break +, Aging Management +, License Renewal +, Chernobyl +, Affidavit +  and Thermography +