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ANSI B31.1 +  and ANSI B31.1-1973 +

ASME Section XI +, ASME Section III +  and ASME Section IX +

Boron +, Iodine +, Copper +, Carbon +  and Lead +

05000244  +  and 00244  +

NRC Generic Letter 84-24, Certification of Compliance to 10 CFR 50.49, Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power Plants +, NRC Generic Letter 87-11, Relaxation in Arbitrary Intermediate Pipe Rupture Requirements +, NRC Generic Letter 87-02, Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors (USI A-46) +, NRC Generic Letter 89-04, Guidance on Developing Acceptable Inservice Testing Programs +, NRC Generic Letter 88-20, Individual Plant Examination for Severe Accident Vulnerabilities +  and NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +

ML20339A057 +, ML20339A057 +, ML20339A057 +, ML20339A057 +, ML20339A057 +, ML20339A057 +, ML20339A057 +, ML20339A057 +, ML20339A057 +  and ML20339A057 +

1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 months)  +, 3.009259e-4 d (0.00722 hours, 4.298942e-5 weeks, 9.893e-6 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 2.314815e-4 d (0.00556 hours, 3.306878e-5 weeks, 7.61e-6 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 1.157407e-4 d (0.00278 hours, 1.653439e-5 weeks, 3.805e-6 months)  +  and 4.62963e-4 d (0.0111 hours, 6.613757e-5 weeks, 1.522e-5 months)  +

IEEE 344-1987 +, IEEE 344 +, IEEE 344-1975 +  and IEEE 344-1971 +

Westinghouse +  and Foxboro +

NRC Bulletin 79-14 +, NRC Bulletin 88-11 +, NRC Bulletin 88-08 +, NRC Bulletin 79-07 +, NRC Bulletin 79-04 +, NRC Bulletin 96-01 +, NRC Bulletin 80-21 +  and NRC Bulletin 79-02, Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts +

NUREG/CR-1161 +, 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/CR-1821, Forwards List of Open Issues from Draft NUREG/CR-1821, Seismic Review of Robert E. Ginna Power Plant as Part of Sep. Addl Info Re Seismic Design Consideration & Component Integrity Should Be Submitted within 30 Days +

SAP +  and SP-5375 +

Regulatory Guide 1.26 +, Regulatory Guide 1.60 +, Regulatory Guide 1.61 +, Regulatory Guide 1.89 +, Regulatory Guide 1.124 +  and Regulatory Guide 1.151 +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, HVAC +, Reactor Pressure Vessel +, Residual Heat Removal +, Circulating Water System +, Main Steam Safety Valve +, Emergency Core Cooling System +, Main Steam Line +, Safety Relief Valve +, Control Rod +, Main Steam +  and Containment Spray +

Safe Shutdown +, Boric Acid +, Loop seal +, Safe Shutdown Earthquake +, Operating Basis Earthquake +, Nondestructive Examination +, Loss of Offsite Power +, Operability Determination +, Earthquake +, Flow Induced Vibration +, Power Uprate +, Water hammer +  and Leak-Before-Break +

WCAP-15029 +, WCAP-15029-P-A +, WCAP-8708-P-A +  and WCAP-9735 +

WCAP-15029 +, WCAP-15029-P-A +, WCAP-8708-P-A +  and WCAP-9735 +