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Letter  and Inservice/Preservice Inspection and Test Report

Nitrogen +, Oxygen +, Sodium +, Hydrogen +  and Lead +

10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50 Appendix B +, 10 CFR 50.55 +, 10 CFR 50.55a +, 10 CFR 50.55a#a3i +, 10 CFR 50.55a#b +, 10 CFR 50.55a#a3ii +, 10 CFR 50.55a#b3 +, 10 CFR 50.55a#f4ii +, 10 CFR 50.55a#b3vi +, 10 CFR 50.55a#b3ivA +  and 10 CFR 50.55#a +

05000277  +, 05000278  +, 00277  +  and 00278  +

CC-AA-102 +, CC-AA-103 +, MA-AA-716-003 +, ER-AA-380 +, ER-AA-321 +, SM-AA-102 +, MA-MA-716-009 +, MA-MA-716-010-1008 +, MA-MA-716-010-1010 +, MA-MA-716-010-1005 +, CC-AA-311 +, PC-AA-1005 +, CC-MA-103-1001 +, MA-MA-716-010-1000 +, MA-MA-716-010-1002 +, MA-MA-716-010-1003 +, MA-MA-716-010-1004 +, MA-MA-716-010-1007 +  and MA-MA-716-010-1009 +

Exelon +  and David Helker +

MPR-1807 +  and MPR-2524-A +

NRC Generic Letter 87-06, Periodic Verification of Leak Tight Integrity of Pressure Isolation Valves +, NRC Generic Letter 89-04, Guidance on Developing Acceptable Inservice Testing Programs +, NRC Generic Letter 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves +  and NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +

ML083230056 +, ML083230056 +, ML083230056 +, ML083230056 +, ML083230056 +, ML083230056 +, ML083230056 +, ML083230056 +, ML083230056 +, ML083230056 +, ML083230056 +, ML083230056 +, ML083230056 +, ML083230056 +  and ML083230056 +

5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +, 0.00111 d (0.0267 hours, 1.587302e-4 weeks, 3.6528e-5 months)  +  and 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +

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

NUREG/CR-6396 +, NUREG-0626, Forwards NUREG-0645,Vols 1-2, Rept of Bulletins & Orders Task Force & NUREG-0626, Generic Evaluation of Feedwater Transients & Small Break LOCAs in GE-Designed Operating Plants & Near Term OL Applications. W/O Encl +  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 +

Tom Loomis +  and None none +

ST +, RT +, TP +, CP +, TP-7 +, TP-3 +, TP-8 +, TP-10 +, TP-6 +, TP-5 +, TP-9 +, TP-12 +, TP-2 +, TP-13 +, TP-4 +, TP-1 +, TP-01 +, TP-04 +, TP-02 +, ST-C +, TP-11 +, TP-14 +, TP-15 +, TP-16 +, TP-X +, TP-17 +, TP-18 +  and TP-19 +

TAC:MB0290 +  and TAC:MD6701 +

Regulatory Guide 1.197 +  and Regulatory Guide 1.192 +

01A-VRR-2 +, 01A-VCS-2 +, 07B-VCS-1 +, 01A-VRR-1 +, 01ANVRR-1 +, 01A-VCS-1 +, 1O-VCS-2 +, 1O-VCS-3 +, 40B-VCS-1 +, 44A-VCS-1 +, 01A-074 +, 02G-ROJ-1 +, 07C-ROJ-1 +, 07C-ROJ-2 +, 07D-ROJ-1 +, 13C-ROJ-1 +, 16B-ROJ-1 +, 16B-ROJ-2 +, 36B-ROJ-1 +, 36B-ROJ-2 +, 07C-ROJ-01 +, 07C-ROJ-02 +, 16B-ROJ-02 +, 6B-ROJ-1 +  and 6B-ROJ-2 +

Washington +  and Pennsylvania +

Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Reactor Core Isolation Cooling +, Primary containment +, Shutdown Cooling +, Reactor Recirculation Pump +, Reactor Pressure Vessel +, Core Spray +, Reactor Building Ventilation +, Residual Heat Removal +, Reactor Water Cleanup +, Fuel Pool Cooling and Cleanup +, Automatic Depressurization System +, Standby Liquid Control +, Emergency Core Cooling System +, Main Steam Line +, Safety Relief Valve +, Control Rod +  and Main Steam +

TS-3.6.4.1 +, TS-3.6.2.1 +, TS-3.4.3 +, TS-3.1.7 +, TS-3.4.1 +, TS-3.3.6.2 +  and TS-3.6.3.2 +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Safe Shutdown +, Reactor Vessel Water Level +, High Radiation Area +, Stroke time +, Squib +, Incorporated by reference +, Notice of Violation +, Excess Flow Check Valve +, Operability Determination +, Cold shutdown justification +  and Power Operated Valves +