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

AR 00546157 +  and AR 00552024 +

IWC-1220 +  and IWC-1230 +

Nitrogen +, Sodium +  and Hydrogen +

10 CFR 50 Appendix J +, 10 CFR 50.55a#a +, 10 CFR 50.55a#a3 +, 10 CFR 50.55a#b2 +  and 10 CFR 50.55a#f4ii +

05000275  +, 05000323  +, 00275  +  and 00323  +

FP-2 +, FP-1 +, FP-3 +, FP-180 +, FP-867 +, FP-I +, FP-l +, FP-307 +  and FP-306 +

Pacific Gas & Electric +  and Becker J +

DCL-02-116, Letter Regards Inservice Testing Program Plan, Revision 19 +, DCL-02-116, Letter Regards Inservice Testing Program Plan, Revision 19 +, DCL-02-116, Letter Regards Inservice Testing Program Plan, Revision 19 +, DCL-02-116, Letter Regards Inservice Testing Program Plan, Revision 19 +, DCL-02-116, Letter Regards Inservice Testing Program Plan, Revision 19 +, DCL-02-116, Letter Regards Inservice Testing Program Plan, Revision 19 +, DCL-02-116, Letter Regards Inservice Testing Program Plan, Revision 19 +, DCL-02-116, Letter Regards Inservice Testing Program Plan, Revision 19 +, DCL-02-116, Letter Regards Inservice Testing Program Plan, Revision 19 +, DCL-02-116, Letter Regards Inservice Testing Program Plan, Revision 19 +, DCL-02-116, Letter Regards Inservice Testing Program Plan, Revision 19 +  and DCL-02-116, Letter Regards Inservice Testing Program Plan, Revision 19 +

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 +  and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +

RT +, TST +  and Emergency Plan +

Regulatory Guide 1.26 +  and Regulatory Guide 1.261 +

SR-3.5.1.1 +, SR-3.7.5.2 +, SR-3.6.6.3 +, SR-3.5.2.1 +, SR-3.6.3.4 +, SR-3.5.1.5 +, SR-3.6.3.7 +, SR-3.6.3.3 +, SR-3.4.14.1 +  and SR-3.4.12.1 +

33A-E +, 45A-D +, 1WB-1220 +, 07-90-025 +, 33A-D +, 47A-B +, 3l-A +, 48A-D +, 2nd-off +, 43D-C +, 44B-B +, 43D-D +, 57B-B +, 57B-A +, 33A-A +, 33A-C +, 33A-B +, 40B-B +, 43B-D +, 47B-C +, 45B-C +, 45B-B +, 45B-A +, 40D-B +, 43B-B +, 32B-D +, 52B-B +, 44B-D +, 52B-A +, 37A-E +...

Texas +, Washington +  and California +

Steam Generator +, Reactor Coolant System +, Feedwater +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Residual Heat Removal +, Decay Heat Removal +, Main Steam Line +, Auxiliary Feed Water +  and Containment Spray +

TS-3.3.4 +  and TS-3.7.8 +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Safe Shutdown +, Unanalyzed Condition +, Boric Acid +, Ultimate heat sink +, Stroke time +, Incorporated by reference +, Cold shutdown justification +, Earthquake +, Power Operated Valves +  and Water hammer +