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ASME Section III +  and ASME Section XI +

Boron +, Iodine +, Copper +, Nitrogen +, Carbon +, Oxygen +, Hydrogen +, Chlorine +, Lead +, Aluminum +, Sulfur +, Argon +  and Plutonium +

10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 50.4 +, 10 CFR 50.65 +, 10 CFR 59.59 +  and 10 CFR 50.59#d2 +

05000413  +, 05000414  +, 00413  +  and 00414  +

Turbine Trip +  and Reactor Trip +

Duke Energy +  and Gordon Peterson +

NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +, NRC Generic Letter 89-04, Guidance on Developing Acceptable Inservice Testing Programs +  and NRC Generic Letter 96-01, Testing of Safety-Related Logic Circuits +

ML020930579 +, ML020930579 +, ML020930579 +, ML020930579 +, ML020930579 +, ML020930579 +, ML020930579 +, ML020930579 +, ML020930579 +, ML020930579 +  and ML020930579 +

Limitorque +  and Westinghouse +

NUREG-1431 +, NUREG-1216, Safety Evaluation Supporting Amend 16 to License NPF-35 +, NUREG-0588, Responds to 870709 Request for NRR Assistance in Determining Adequacy of Two Test Repts Re Acceptance Criteria of NUREG-0588,Category I.Qualification of Kulka Terminal Blocks Demonstrated & Not Used in Instrumentation Circuits +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +  and NUREG-1482, Revision 4, Guidelines for Inservice Testing at Nuclear Power Plants: Inservice Testing of Pumps and Valves and Inservice Examination and Testing of Dynamic Restraints (Snubbers) at Nuclear Power Plants Final Report +

Regulatory Guide 1.97 +, Regulatory Guide 1.52 +  and Regulatory Guide 1.23 +

SR-3.4.13.1 +, SR-3.4.15.2 +, SR-3.4.14.1 +, SR-3.3.1.6 +, SR-3.1.7.1 +, SR-3.6.7.1 +, SR-3.6.12.3 +, SR-3.6.12.1 +, SR-3.6.12.2 +, SR-3.4.13 +  and SR-3.6.7 +

2CRA-C-1 +, 1CRA-C-1 +, 1NV-849 +, 1NM-26B +, 2RN-250A +, 2NV-849 +, 1o-lo +, 07-80-131 +, 2CA-6 +, 2NV-477 +, 2NV-476 +, 2SM-44 +, 2SM-044 +, 2SM-54 +, 2SM-55 +, 2SM-56 +, 2SM-57 +, 2SM-41 +, 2SM-43 +, 2SM-42 +, 2RN-159 +, 2KF-097 +, 1VF-RC-2 +, 2RL-845 +, 1AD29-1 +, 1RL-A7 +, 2CRA-C-I +, 1NM-941 +, 1NM-942 +, 2NV-481 +...

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Primary containment +, Main Turbine +, HVAC +, Residual Heat Removal +, Circulating Water System +, Main Steam Safety Valve +, Stator Water +, Emergency Core Cooling System +, Decay Heat Removal +, Safety Relief Valve +, Moisture Separator Reheater +, Control Rod +, Main Steam +  and Containment Spray +

TS-3.4.14 +, TS-3.7.2 +, TS-3.4.13 +, TS-3.5.2 +, TS-3.5.3 +, TS-3.7 +, TS-3.6.3 +, TS-3.7.10 +, TS-3.4.3 +, TS-3.7.6 +, TS-3.3.2 +, TS-3.1.7 +, TS-3.9.3 +, TS-3.1.3.3 +, TS-3.7.8 +, TS-3.1.4 +, TS-3.4.15 +, TS-3.6.13 +, TS-3.2.1 +  and TS-3.6.12 +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Safe Shutdown +, Boric Acid +, Shutdown Margin +, Packing leak +, Ultimate heat sink +, Grab sample +, Stroke time +, Met Tower +, Anchor Darling +, Temporary Modification +, Condition Adverse to Quality +, Stress corrosion cracking +, Loss of Offsite Power +, Integrated leak rate test +, Commercial Grade +, Pressure boundary leak +, Fire Protection Program +, Scaffolding +, Overspeed trip +, Manual Operator Action +, Operational leakage +  and Water hammer +

WO 98376683 +  and WO 98417226 +