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Letter, Report  and Miscellaneous

ASME Section II +  and ASME Section XI +

Boron +, Iodine +, Cobalt +, Cesium +, Iron +, Nickel +, Potassium +, Copper +, Carbon +, Oxygen +, Hydrogen +, Xenon +, Chlorine +, Chloride +, Lead +, Lithium +, Sulfur +  and Chromium +

10 CFR 21 +  and 10 CFR 50 Appendix A +

05000346  +  and 00346  +

FirstEnergy +  and Myers L +

NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants +  and NRC Generic Letter 97-01, Degradation of Control Rod Drive Mechanism Nozzle and Other Vessel Closure Head Penetrations +

ML022750125 +, ML022750125 +, ML022750125 +, ML022750125 +, ML022750125 +, ML022750125 +, ML022750125 +, ML022750125 +, ML022750125 +, ML022750125 +, ML022750125 +, ML022750125 +  and ML022750125 +

8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 2.430556e-4 d (0.00583 hours, 3.472222e-5 weeks, 7.9905e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 1.157407e-4 d (0.00278 hours, 1.653439e-5 weeks, 3.805e-6 months)  +  and 2.199074e-4 d (0.00528 hours, 3.141534e-5 weeks, 7.2295e-6 months)  +

Westinghouse +  and Limitorque +

NRC Bulletin 01-01 +  and NRC Bulletin 82-02 +

Information Notice 80-27 +, Information Notice 94-63 +, Information Notice 90-10 +, Information Notice 96-11 +, Information Notice 82-06 +, Information Notice 2002-11, Recent Experience with Degradation of Reactor Pressure Vessel Head +, Information Notice 2001-05, Through-Wall Circumferential Cracking of Reactor Pressure Vessel Head Control Rod Drive Mechanism Penetration Nozzles at Oconee Nuclear Station Unit 3 +  and Information Notice 2000-17, Crack in Weld Area of Reactor Coolant System Hot Leg Piping at V.C. Summer +

SP +  and TOP +

SER 41-85 +, SER 10-89 +, SER 32-84 +, SER 57-83 +, SER 72-83 +, SER 13-87 +, SER 46-80 +, SER 35-81 +, SER 11-82 +, SER 20-93 +, SER 31-87 +, SER 35-87 +  and SER 90-2 +

SOER 84-5 +  and SOER 81-12 +

5x10-12 +, 14a-e +, 21GB-01002-45L +, 21GF-01004-30L +, 21GC-01001-55L +, 21GA-01004-45L +, 22CD-01001-65L +, 54-1S1-100-08 +, 0EPRI-4 +, 07R1-2 +, 07R0-7 +, 01o-0019 +  and 3t5-18I +

Ohio +, Arkansas +  and Maine +

Steam Generator +, Reactor Coolant System +, Service water +, Shutdown Cooling +, Reactor Pressure Vessel +, Control Rod +  and Containment Spray +

TS-4.4.6.2 +  and TS-3.3.3.1 +

NRC Region 3 +  and Dyer J +

Boric Acid +, Time of Discovery +, Packing leak +, Non-Destructive Examination +, Hydrostatic +, Coatings +, Nondestructive Examination +, VT-2 +, Finite Element Analysis +, Condition Adverse to Quality +, Flow Accelerated Corrosion +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, Operability Determination +, Fuel cladding +, Pressure Boundary Leakage +, Through Wall Leak +, Through-Wall Leakage +, Downpower +, Unidentified leakage +, Unidentified leak +, Operational leakage +, Thermal fatigue +, Leak-Before-Break +  and Leak Before Break +