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ANSI/ANS 3.5-2009 +, ANSI/ANS 3.1-1978 +, ANSI/ANS 3.1 +, ANSI 18.7-1976 +, ANSI/ANS 3.1-1993 +, ANSI 3.1-1993 +, ANSI/ANS-3.1-1978 +  and ANSI N18.7, Administrative Controls and Quality Assurance for Nuclear Power Plants during the Operational Phase +

Iodine +  and Carbon +

10 CFR 55 +, 10 CFR 20 +, 10 CFR 73 +, 10 CFR 2.390 +, 10 CFR 50.40 +, 10 CFR 50.49 +, 10 CFR 50.65 +, 10 CFR 50.90 +, 10 CFR 50.120 +, 10 CFR 50 Appendix E +, 10 CFR 50 Appendix H +, 10 CFR 55.59 +, 10 CFR 73.2 +, 10 CFR 73.21 +, 10 CFR 73.51 +, 10 CFR 73 Appendix B +, 10 CFR 73 Appendix C +, 10 CFR 50.54 +, 10 CFR 37.41 +, 10 CFR 50.54#m2i +, 10 CFR 50.54#p +, 10 CFR 50.54#i +, 10 CFR 50.47#b +, 10 CFR 50.55a#g +  and 10 CFR 50.40#b +

DCL-12-108 +, DCL-91-143 +, DCL-94-262 +, DCL 99-031 +, DCL-88-192 +, DCL-91-027 +, DCL-91-091 +, DCL-91-178 +, DCL-96-213 +, DCL-17-038, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 8, Electric Power +  and DCL-11-040, Response to Request for Additional Information E-mail Dated March 4, 2011, from the U.S. NRC Concerning Cyber Security Plan License Amendment Request 09-05 +

DCL-12-108 +, DCL-91-143 +, DCL-94-262 +, DCL 99-031 +, DCL-88-192 +, DCL-91-027 +, DCL-91-091 +, DCL-91-178 +, DCL-96-213 +, DCL-17-038, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 8, Electric Power +  and DCL-11-040, Response to Request for Additional Information E-mail Dated March 4, 2011, from the U.S. NRC Concerning Cyber Security Plan License Amendment Request 09-05 +

05000275  +  and 05000323  +

NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants +, NRC Generic Letter 87-07, Information Transmittal of Final Rulemaking for Revisions to Operator Licensing - 10 CFR 55 and Confirming Amendments +, NRC Generic Letter 88-17, Loss of Decay Heat Removal +, NRC Generic Letter 88-06, Removal of Organization Charts from Technical Specification Administrative Control Requirements +, NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +, NRC Generic Letter 89-08, Erosion/Corrosion-Induced Pipe Wall Thinning +, 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 +

ML17206A053 +, ML17206A053 +, ML17206A053 +, ML17206A053 +, ML17206A053 +, ML17206A053 +, ML17206A053 +, ML17206A053 +, ML17206A053 +  and ML17206A053 +

Westinghouse +  and General Electric +

NEI 09-14, New York State (NYS) Pre-Filed Evidentiary Hearing Exhibit NYS000168, Guideline for the Management of Underground Piping and Tank Integrity, NEI 09-14 (Rev.1) (December 2010) (NEI 09-14 Rev. 1) +  and NEI 03-08, Notification of Deviation from Electric Power Research Institute (EPRI) Materials Reliability Program (MRP) 2019-008, Materials Reliability Program: Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants . +

NUREG-0731, Summary of 860314 Meeting W/Util in Bethesda,Md Re Qualifications of Radiation Protection Manager as Compared to Qualifications Outlined in 1975 Rev 1 to Reg Guide 1.8, Personnel Selection & Training. Viewgraphs Encl +, NUREG-0612, Safety Evaluation Supporting Util Request to Delete Three Commitments in Response to NUREG-0612 Re Heavy Load Control on 5-ton Electric Monorail Hoist W/Integral Trolley & 4-ton Monorail Chain Hoist W/Geared Trolley +, NUREG-0675, Forwards Decision DD-86-12 in Response to Petition & Suppls Re Licensing Actions Based on Allegations.Nrc Evaluation of Allegation & Basis for Conclusions in Decision DD-86-12 Contained in Sser 33 to NUREG-0675,transmitted on 860527 +, NUREG-1021, Revised Effectiveness Review Plan for NUREG-1021 Revision 12 (Public) +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +  and NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +

OP-1 +, OP-3 +, OP-2 +  and OP-8 +

PSP +  and ES-202 +

Regulatory Guide 1.97 +, Regulatory Guide 1.33 +, Regulatory Guide 1.160 +  and Regulatory Guide 1.8 +

Pennsylvania +, Connecticut +, Illinois +, Maryland +  and Massachusetts +

Reactor Coolant System +, Feedwater +, Service water +, Reactor Pressure Vessel +  and Decay Heat Removal +

TS-5.3.1 +, TS-5.2.2.b +, TS-5.2.2.e +, TS-5.2.2.f +, TS-5.2.1.a +, TS-5.2.2.a +, TS-5.2.2.c +, TS-5.3.1.a +  and TS-5.3.1.c +

Boric Acid +, Fitness for Duty +, Safe Shutdown Earthquake +, Cyber Security +, Aging Management +, Fukushima Dai-Ichi +, Shift Technical Advisor +, Process Control Program +, Safeguards Contingency Plan +, Maintenance Rule Program +, Control of Heavy Loads +, Liquid penetrant +  and Fire Protection Program +