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Sodium +, Hydrogen +, Lead +, Calcium +  and Zinc +

10 CFR 50 Appendix B +, 10 CFR 50.54#f +  and 10 CFR 50.71#e +

05000315  +, 05000316  +  and 00315  +

ML042360586 +  and ML050750069 +

05000364/FSAR-6.1 +  and 05000364/FSAR-6.2#2 +

Jensen J +  and Indiana Michigan Power Co +

NRC Generic Letter 04-02 +, NRC Generic Letter 84-04, Safety Evaluation of Westinghouse Topical Reports Dealing with Elimination of Postulated Pipe Breaks in PWR Primary Main Loops (Generic Letter 84-04) +  and NRC Generic Letter 98-04, Potential for Degradation of the Emergency Core Cooling System and the Containment Spray System After a Loss-of-Coolant Accident Because of Construction and Protective Coating Deficiencies and Foreign Material in Containment +

ML052510512 +, ML052510512 +, ML052510512 +, ML052510512 +, ML052510512 +, ML052510512 +, ML052510512 +, ML052510512 +, ML052510512 +, ML052510512 +, ML052510512 +, ML052510512 +, ML052510512 +, ML052510512 +, ML052510512 +, ML052510512 +, ML052510512 +, ML052510512 +, ML052510512 +, ML052510512 +, ML052510512 +, ML052510512 +, ML052510512 +, ML052510512 +, ML052510512 +, ML052510512 +  and ML052510512 +

2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +  and 1.157407e-4 d (0.00278 hours, 1.653439e-5 weeks, 3.805e-6 months)  +

NEI 02-01 +  and NEI 04-07, Response to Request No. 2 in NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. +

Maryland +, Washington +, Michigan +  and Indiana +

Steam Generator +, Reactor Coolant System +, Residual Heat Removal +, Emergency Core Cooling System +, Decay Heat Removal +  and Containment Spray +

Document Control Desk +  and Office of Nuclear Reactor Regulation +

Mission time +, Coatings +, High Energy Line Break +, Exemption Request +  and Leak-Before-Break +