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Inservice/Preservice Inspection and Test Report  and Letter type:NG

Nitrogen +  and Sodium +

10 CFR 100 +, 10 CFR 50 Appendix J +, 10 CFR 50.55a +, 10 CFR 50.55a#f +, 10 CFR 50.55a#a3i +, 10 CFR 50.55a#b +, 10 CFR 50.55a#a3ii +  and 10 CFR 50.55a#f5iii +

05000331  +  and 00331  +

Vanmiddlesworth G +  and Nuclear Management Co +

NRC Generic Letter 89-16, Installation of a Hardened Wetwell Vent +  and NRC Generic Letter 89-04, Guidance on Developing Acceptable Inservice Testing Programs +

NG-05-0427, Inservice Testing Program, Fourth Ten-Year Interval Update +, NG-05-0427, Inservice Testing Program, Fourth Ten-Year Interval Update +, NG-05-0427, Inservice Testing Program, Fourth Ten-Year Interval Update +, NG-05-0427, Inservice Testing Program, Fourth Ten-Year Interval Update +, NG-05-0427, Inservice Testing Program, Fourth Ten-Year Interval Update +, NG-05-0427, Inservice Testing Program, Fourth Ten-Year Interval Update +, NG-05-0427, Inservice Testing Program, Fourth Ten-Year Interval Update +, NG-05-0427, Inservice Testing Program, Fourth Ten-Year Interval Update +, NG-05-0427, Inservice Testing Program, Fourth Ten-Year Interval Update +, NG-05-0427, Inservice Testing Program, Fourth Ten-Year Interval Update +, NG-05-0427, Inservice Testing Program, Fourth Ten-Year Interval Update +  and NG-05-0427, Inservice Testing Program, Fourth Ten-Year Interval Update +

ISTC-5221 +, ISTC-3522 +  and ISTC-3521 +

IP 228 +, IP 216 +, IP 226 +, IP 14613 +, IP 219 +  and IP 2211 +

Union Pump +  and General Electric +

NUREG-1472 +  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 +

ST +, MP +, SAP +  and SP +

Regulatory Guide 1.97 +  and Regulatory Guide 1.11 +

SR-3.1.5.1 +, SR-3.6.1.3.7 +, SR-3.1.3.2 +, SR-3.1.3.3 +  and SR-3.1 +

1P-211A +, 1P-211B +, 1G-31 +, 1o-a +, V1I3-0121 +, 1Y-SRV +, 1S260H-BAL +, 1S26OC-BAI +, 1S260C-SIIE +, 1E-18B +, 1E-18A +, 80DO-2 +, 2Y-3 +  and 1P-Il +

Washington +  and Iowa +

Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Shutdown Cooling +, Reactor Recirculation Pump +, HVAC +, Core Spray +, Residual Heat Removal +, Standby Liquid Control +, Steam Jet Air Ejector +, Main Steam Line +, Safety Relief Valve +, Main Condenser +, Control Rod +, Main Steam +  and Low Pressure Coolant Injection +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Reactor Vessel Water Level +, Stroke time +, Squib +, Feedwater Heater +, Scram Discharge Volume +, Excess Flow Check Valve +, Power-Operated Valves +  and Unidentified leakage +