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Boron +, Strontium +, Iodine +, Cesium +, Krypton +, Carbon +, Hydrogen +, Lead +, Ruthenium +, Tellurium +, Barium +, Lanthanum +  and Cerium +

05000286  +  and 05000247  +

ML11355A237 +, ML11355A237 +, ML11355A237 +, ML11355A237 +, ML11355A237 +, ML11355A237 +, ML11355A237 +, ML11355A237 +, ML11355A237 +  and ML11355A237 +

2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +  and 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +

Strontium-90 +, Cesium-137 +, Americium-241 +, Iodine-131 +, Yttrium-90 +, Krypton-85 +  and Cobalt-60 +

NUREG/CR-6525 +, NUREG/BR-0184 +, NUREG/CR-4551 +, NUREG/CR-4691 +, NUREG-1743, Review of Revisions to Regulatory Commitments Documented in NUREG-1743, Safety Evaluation Report Related to License Renewal of Arkansas Nuclear One, Unit 1 +, NUREG-0498, Supp 2 DFC, (2.2) Pt 5 - End, Draft Final Environmental Statement, Related to the Operation of Watts Bar Nuclear Plant, Unit 2 +, NUREG/CR-5567 +, NUREG/CR-5630 +, NUREG/CR-5575 +, NUREG-1462, Notification of 921209 Meeting w/ABB-C-E in Rockville,Md to Discuss Status of Closure of Open Items in Draft SER for Sys 80+ (NUREG-1462).Meeting Agenda Encl +, NUREG-1560, Forwards Draft NUREG-1560 Public Workshop Summary Rept from Workshop Held on 970407-09 in Austin,Texas.Rept Summarizes Discussions Held During Workshop & Documents All of Presentation Matl Distributed to Workshop by Attendees +, NUREG-1150, Weekly Info Rept for Wk Ending 890922 +  and NUREG/CR-6613, Exhibit K - NUREG/CR-6613, Vol. 1, SAND97-0594 - Code Manual for MACCS2 - Users Guide +

4kV +  and 4.16kV +

2A-3 +, 2A-4 +, 2B-5 +, 2T-41A +, 2T-41B +, 2T-57A +, 2CV-5255-1 +, 2CV-5649-1 +, 2B-64 +, 2B-6 +, 2CV-5650-2 +, 2CV-1531-2 +, 2CV-1530-1 +, 2C-16 +, 2B-51 +, 2B-54 +, 2B-61 +, 2CV-2401-1 +, 2T-57B +, 2CV-5254-2 +, 2SV-8231-2 +, 2C21-1 +, 2C21-2 +, 07-94-171 +, 2HPA-2 +, 2CV-2400-2 +, 2CVH-8 +, 2BS-46 +  and 2LT-5636-5 +

New York +  and Arkansas +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Reactor Core Isolation Cooling +, Primary containment +, Shutdown Cooling +, HVAC +, Residual Heat Removal +, Main Steam Safety Valve +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Control Rod +, Main Steam +  and Containment Spray +

Mission time +, Probabilistic Risk Assessment +, License Renewal +, Earthquake +, Eddy-Current Testing +  and Leak Before Break +