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Letter, Safety Evaluation  and Code Relief or Alternative

10 CFR 50.55a +, 10 CFR 50.55a#a3i +, 10 CFR 50.55a#b +, 10 CFR 50.55a#f6i +, 10 CFR 50.55a#f5iii +, 10 CFR 50.55a#f4ii +, 10 CFR 50.55a#f4iv +, 10 CFR 50.55a#3i +  and 10 CFR 50.55a#b6 +

05000397  +  and 00397  +

Lyon C +  and NRC/NRR/ADRO/DORL/LPLIV +

ML070600111 +, ML070600111 +, ML070600111 +, ML070600111 +, ML070600111 +, ML070600111 +, ML070600111 +, ML070600111 +, ML070600111 +, ML070600111 +, ML070600111 +, ML070600111 +, ML070600111 +, ML070600111 +, ML070600111 +, ML070600111 +, ML070600111 +, ML070600111 +, ML070600111 +, ML070600111 +, ML070600111 +, ML070600111 +, ML070600111 +, ML070600111 +, ML070600111 +, ML070600111 +, ML070600111 +, ML070600111 +, ML070600111 +, ML070600111 +...

ISTC-3522 +  and ISTC-5152 +

GO2-07-053, Response to Request for Additional Information Regarding License Amendment Request to Technical Specifications Associated with AC and DC Electrical Power +, GO2-07-034, Response to Request for Additional Information Regarding Relief Request 3ISI-07 +  and GO2-05-166, Submittal of the Third Ten-Year Interval Pump and Valve Inservice Testing (IST) Program Plan +

NUREG-1492, Forwards Coversheets of Reg Guide 8.39, Release of Patients Administered Radioactive Matls & NUREG-1492, Regulatory Analysis on Criteria for Release of Patients.... Subj Reg Guide Is Not Major Rule as Defined in 5 U.S.C. 804(2) +  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 1.11 +  and Regulatory Guide 1.192 +

Washington +  and Oregon +

Secondary containment +, Reactor Core Isolation Cooling +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +  and Main Steam +

Energy Northwest +  and Parrish J +

Stroke time +, Incorporated by reference +  and Excess Flow Check Valve +