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ANSI N45.4-1972 +, ANSI N101.2 +, ANSI/ANS 5.1 1979 +  and ANSI B16.104 +

ASME Section XI +  and ASME Section III +

Boron +, Iodine +, Copper +, Nitrogen +, Carbon +, Oxygen +, Sodium +, Hydrogen +, Zirconium +, Lead +, Aluminum +  and Zinc +

10 CFR 50.67 +, 10 CFR 50 Appendix A +, 10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 50 +, 10 CFR 50 Appendix J +  and 10 CFR 50.44 +

L-91-066 +  and SECY-00-0198, Letter to R. Beedle Status Report on Study of Risk-Informed Changes to the Technical Requirements of 10 CFR Part 50 (Option 3) and Recommendations on risk-informed Changes to 10 CFR 50.44 (Combustible Gas Control) +

DRN-04-705 +, DRN-05-1135 +, DRN-05-785 +, DRN-01-230 +, DRN-03-2060 +, DRN-06-1061 +, DRN-06-1026 +, DRN-00-314 +, DRN-05-1332 +, DRN-04-631 +, DRN-05-1769 +, DRN-02-525 +, DRN-03-1355 +, DRN-05-12 +, DRN-00-204 +, DRN-02-9 +, DRN-03-1543 +, DRN-05-75 +  and DRN-02-385 +

05000382  +, 00400  +, 00471  +, 00361  +, 00362  +  and 00335  +

EC-706 +, EC-19087 +, EC-8458 +, EC-40281 +, EC-5000082406 +, EC-999 +, EC-1002 +, EC-6494 +, EC-9533 +, EC-29816 +, EC-8437 +, EC-25199 +  and EC-40195 +

GDC 57 +, GDC 38 +, GDC 41 +  and GDC 54 +

ML16256A273 +, ML16256A273 +, ML16256A273 +, ML16256A273 +, ML16256A273 +, ML16256A273 +, ML16256A273 +, ML16256A273 +, ML16256A273 +  and ML16256A273 +

2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +  and 0 d (0 hours, 0 weeks, 0 months)  +

IEEE 323-1974 +, IEEE 279-1971 +, IEEE 344-1975 +, IEEE 323-1971 +, IEEE 344-1971 +  and IEEE 317-1972 +

NEI 04-07, Response to Request No. 2 in NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. +  and NEI 94-01, License Amendment Request Supplement Pursuant to 10 CFR 50.90: Adoption of NEI 94-01, Revision 2-A, and Extension of Primary Containment Integrated Leakage Rate Test Interval to Fifteen (15) Years +

NUREG-0589 +, 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-1061, Summary of 890217 Meeting W/Util in Rockville,Md Re Resolution of Open Civil/Seismic Issues for Plant.List of Attendees & Slide Presentation Encl +

Regulatory Guide 1.183 +, Regulatory Guide 1.97 +, Regulatory Guide 1.1 +, Regulatory Guide 1.52 +, Regulatory Guide 1.7 +, Regulatory Guide 1.82 +, Regulatory Guide 1.26 +, Regulatory Guide 1.29 +, Regulatory Guide 1.11 +  and Regulatory Guide 1.73 +

3A-SA +, 3B-SB +, 3D-SB +, 3C-SA +, 07-04-705 +, 07-04-631 +, 07-01-230 +, 2HV-Bl66 +  and W3F1-2016-0053, Redacted - Waterford Steam Electric Station, Unit 3, Revision 309 to Final Safety Analysis Report, Chapter 3, Design of Structures, Components Equipment and Systems, Section 3.8, Figures 3.8-1 Through 3.8-47 +

Idaho +  and New York +

Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Main Steam Isolation Valve +, Primary containment +, Shutdown Cooling +, HVAC +, Shield Building +, Emergency Core Cooling System +, Main Steam Line +, Safety Relief Valve +, Main Steam +, Containment Spray +  and Emergency Feedwater System +

Safe Shutdown +, Boric Acid +, Grab sample +, Safe Shutdown Earthquake +, Hydrostatic +, Coatings +, Nondestructive Examination +, Loss of Offsite Power +, Excess Flow Check Valve +, Integrated leak rate test +, Earthquake +, Fuel cladding +, GOTHIC +, Power Uprate +  and Leak-Before-Break +