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Letter  and License-Application for Facility Operating License (Amend/Renewal) DKT 50

ANSI/ANS 56.8-1994 +, ANSI/ANS 56.8 +, ANSI/ANS 56.8-2002 +  and ANSI/ANS-56.8-2002 +

ASME Section XI +  and ASME Section V +

Nitrogen +, Carbon +, Chloride +, Lead +, Zinc +  and Tin +

10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 50 +, 10 CFR 50.36 +, 10 CFR 50 Appendix J +, 10 CFR 52 +, 10 CFR 54 +, 10 CFR 50.65 +, 10 CFR 50.90 +, 10 CFR 50.92 +, 10 CFR 50.55a +, 10 CFR 50.54#f +, 10 CFR 50.54#o +, 10 CFR 50.36#c5 +, 10 CFR 50.65#a4 +, 10 CFR 50.55a#g4 +, 10 CFR 50.55a#b2ixG +, 10 CFR 50.55a#b2ixE +, 10 CFR 51.22#b +, 10 CFR 51.22#c9 +  and 10 CFR 50.92#c +

Emergency Preparedness +, Initiating Events +  and Physical Protection +

05000244  +, 00244  +, 00317  +  and 00278  +

ML12053A340 +, ML14099A196 +, ML100270582 +, ML15364A544 +, IR 05000244/2016011 +, ML16124A038 +, NUREG-1786, Safety Evaluation Report, Related to License Renewal of R.E. Ginna Nuclear Power Plant +, ML17103A235 +, ML15271A101 +, ML13093A064 +, ML112070867 +, ML14083A586 +, ML16060A223 +, ML15153A026 +, RS-15-288, High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information, Per 10CFR50.54(f)Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident +, L-14-121, License Amendment Request to Extend Containment Leakage Test Frequency +, ML17262A711 +  and ML13311A353 +

ER-AA-600 +, ER-AA-600-1015 +, ER-AA-600-1012 +, ER-AA-600-1061 +  and ER-AA-600-1068 +

Category:05000304/FSAR Chapter 15 +, 05000304/FSAR-3.8#1.7 +  and 05000304/FSAR-18.2#1.3 +

Exelon +  and James Barstow +

GDC 50 +, GDC 52 +, GDC 53 +  and GDC 51 +

NRC Generic Letter 87-02, Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors (USI A-46) +, NRC Generic Letter 98-04, Potential for Degradation of the Emergency Core Cooling System and the Containment Spray System After a Loss-of-Coolant Accident Because of Construction and Protective Coating Deficiencies and Foreign Material in Containment +  and NRC Generic Letter 88-20, Individual Plant Examination for Severe Accident Vulnerabilities +

ML19045A282 +, ML19045A282 +, ML19045A282 +, ML19045A282 +, ML19045A282 +, ML19045A282 +, ML19045A282 +, ML19045A282 +, ML19045A282 +, ML19045A282 +, ML19045A282 +, ML19045A282 +, ML19045A282 +, ML19045A282 +, ML19045A282 +, ML19045A282 +, ML19045A282 +, ML19045A282 +, ML19045A282 +, ML19045A282 +, ML19045A282 +, ML19045A282 +, ML19045A282 +, ML19045A282 +, ML19045A282 +, ML19045A282 +, ML19045A282 +, ML19045A282 +, ML19045A282 +, ML19045A282 +...

NEI 07-12 +, NEI 05-04 +, NEI 12-13 +  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 +

Information Notice 92-20 +, Information Notice 2004-09, Corrosion of Steel Containment and Containment Liner +, Information Notice 1992-20, Inadequate Local Leak Rate Testing +, Information Notice 2010-12, Containment Liner Corrosion +  and Information Notice 2014-07, Degradation of Leak-Chase Channel Systems for Floor Welds of Metal Containment Shell and Concrete Containment Metallic Liner +

NUREG-1493 +, NUREG/CR-4550 +, NUREG-1742 +, NUREG/CR-4551 +, NUREG/CR-3539 +, NUREG/CR-4220 +, NUREG-1273 +, NUREG/CR-4330 +, NUREG/CR-2728 +, NUREG-2122 +, NUREG-1150, Weekly Info Rept for Wk Ending 890922 +  and NUREG-1801, Proprosed Revision of Chapters II & III of Generic Aging Lessons (Gall) Report on Aging Management of Concrete Elements +

CAC:MF7359 +, CAC:MF1393 +, TAC:MB0178 +, TAC:MC9663 +, TAC:ME2164 +, CAC:MF1147 +, TAC:ME4090 +, TAC:ME5997 +, TAC:MF3972 +, TAC:ME1650 +  and TAC:MC6375 +

Regulatory Guide 1.177 +, Regulatory Guide 1.200 +, Regulatory Guide 1.174 +, Regulatory Guide 1.163 +, Regulatory Guide 1.147 +  and Regulatory Guide 1.54 +

05000304/SR-3.6.1.2 +  and 05000304/SR-3.0.2 +

Peach Bottom +  and Ginna +

Illinois +, Washington +, New York +, Florida +  and Arkansas +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Auxiliary Feedwater +, Primary containment +, Residual Heat Removal +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam +  and Containment Spray +

05000304/TS-5.5 +, 05000304/TS-5.5.15 +, 05000304/TS-3.6.1 +, 05000304/TS-5.5.6 +  and 05000304/TS-5.5.11 +

TSTF-505 +  and TSTF-425 +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Safe Shutdown +, Boric Acid +, High winds +, High Radiation Area +, Non-Destructive Examination +, Tornado Missile +, Safe Shutdown Earthquake +, Internal Flooding +, Probabilistic Risk Assessment +, Coatings +, Operating Basis Earthquake +, Incorporated by reference +, FLEX +, Aging Management +, Tornado Generated Missile +, Fukushima Dai-Ichi +, Local Leak Rate Testing +, Large early release frequency +, Loss of Offsite Power +, Integrated leak rate test +, Spent Fuel Pool Instrumentation +, Moisture barrier +, License Renewal +, Earthquake +, Fuel cladding +, Fire Protection Program +  and Scaffolding +