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Safety Evaluation Report  and NUREG

ANSI N18.2 +, ANSI N45.2-1971 +, ANSI/ANS-5.1-1979 +, ANSI/ANS-3.1-1981 +  and ANSI/ANS-18.1 +

ASME Section III +  and ASME Section II +

Environmental Protection Agency +  and Federal Emergency Management Agency +

Boron +, Iodine +, Uranium +, Vanadium +, Carbon +, Hydrogen +, Xenon +, Zirconium +, Lead +, Silicon +, Zinc +, Tin +  and Platinum +

10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.63 +, 10 CFR 2.390 +, 10 CFR 20.1301 +, 10 CFR 20.1501 +, 10 CFR 50.49 +, 10 CFR 50.61 +, 10 CFR 50.62 +, 10 CFR 50.68 +, 10 CFR 73.1 +, 10 CFR 73.54 +, 10 CFR 73.55 +, 10 CFR 20.1101 +, 10 CFR 50.54 +, 10 CFR 50.34a +, 10 CFR 50.34a#c +, 10 CFR 50.34a#a +, 10 CFR 50.49#l +, 10 CFR 73.54#a1 +, 10 CFR 73.54#a +, 10 CFR 73.54#e +, 10 CFR 73.54#a1iii +, 10 CFR 73.54#a1ii +, 10 CFR 50.54#f +, 10 CFR 50.54#q +, 10 CFR 50.54#w +...

Emergency Preparedness +, Initiating Events +  and Physical Protection +

SECY-07-0096, Safety Evaluation Regarding Generic Letter 2006-03, Potentially Nonconforming Hemyc and Mt Fire Barrier Configurations +, SECY-83-293 +  and NRC 15-59 +

05000391  +, 00391  +  and 00390  +

ML110600206 +, ML110070348 +, ML072060688 +, ML11206A499 +, IR 05000391/2011605 +, IR 05000391/2011604 +, ML101720050 +, ML073551056 +, ML110980637 +, ML103480708 +, ML101200155 +, ML072570676 +, SECY-07-0096, Safety Evaluation Regarding Generic Letter 2006-03, Potentially Nonconforming Hemyc and Mt Fire Barrier Configurations +, ML073541207 +, ML112232205 +, ML092151155 +, ML103200146 +, ML090340159 +, RIS 2005-29, Anticipated Transients Developing Into More Serious Events +, ML071220492 +, ML092710381 +, ML111960228 +, ML093631061 +, ML100130227 +, ML100190443 +, ML100539515 +, ML100200375 +, ML100260594 +, ML100270076 +, ML100120052 +...

Technical Support Center +  and Emergency Operations Facility +

EC-135 +  and EC-121 +

Turbine Trip +  and Reactor Trip +

GDC 20 +, GDC 38 +, GDC 15 +, GDC 50 +, GDC 16 +, GDC 10 +, GDC 61 +, GDC 35 +, GDC 14 +, GDC 60 +, GDC 18 +, GDC 24 +, GDC 11 +, GDC 13 +, GDC 31 +, GDC 25 +, GDC 64 +, GDC 28 +, GDC 27 +, GDC 63 +, GDC 17, Electric power systems +, GDC 19, Control room +, GDC 4, Environmental and dynamic effects design bases +, GDC 1, Quality standards and records +, GDC 26, Reactivity control system redundancy and capability +  and GDC 5, Sharing of structures, systems, and components +

NRC Generic Letter 04-02 +, NRC Generic Letter 07-01 +, NRC Generic Letter 04-01 +, NRC Generic Letter 06-01 +, NRC Generic Letter 97-06, Degradation of Steam Generator Internals +, NRC Generic Letter 2006-03 +, NRC Generic Letter 80-77, Refueling Water Level +, NRC Generic Letter 80-14, LWR Primary Coolant System Pressure Isolation Valves +, NRC Generic Letter 81-21, Natural Circulation Cooldown +, NRC Generic Letter 82-28, Inadequate Core Cooling Instrumentation System +, NRC Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events +, NRC Generic Letter 86-09, Technical Resolution of Generic Issue B-59, (N-1) Loop Operation in BWRs and PWRs +, NRC Generic Letter 88-11, NRC Position on Radiation Embrittlement of Reactor Vessel Materials and Its Impact on Plant Operations +, NRC Generic Letter 89-21, Request for Information Concerning Status of Implementation of Unresolved Safety Issue (USI) Requirements +, NRC Generic Letter 89-04, Guidance on Developing Acceptable Inservice Testing Programs +, NRC Generic Letter 90-06, Resolution of Generic Issues 70, "PORV and Block Valve Reliability," and 94, "Additional Ltop Protection for PWRs" +, NRC Generic Letter 92-08, Thermo-Lag 330-1 Fire Barriers +, NRC Generic Letter 92-01, Reactor Vessel Structural Integrity +, NRC Generic Letter 95-05, Voltage-Based Repair Criteria for Westinghouse Steam Generator Tubes Affected by Outside Diameter Stress Corrosion Cracking +, NRC Generic Letter 95-03, Circumferential Cracking of Steam Generator Tubes +, NRC Generic Letter 96-06, Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions +, NRC Generic Letter 97-05, Steam Generator Tube Inspection Techniques +, NRC Generic Letter 97-04, Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps +, NRC Generic Letter 97-01, Degradation of Control Rod Drive Mechanism Nozzle and Other Vessel Closure Head Penetrations +, 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 +, NRC Generic Letter 98-02, Loss of Reactor Coolant Inventory and Associated Potential for Loss of Emergency Mitigation Functions While in a Shutdown Condition +, NRC Generic Letter 06-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power +, NRC Generic Letter 88-20, Individual Plant Examination for Severe Accident Vulnerabilities +, NRC Generic Letter 2003-01, Control Room Habitability +, NRC Generic Letter 08-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems +...

ML11277A148 +, ML11277A148 +, ML11277A148 +, ML11277A148 +, ML11277A148 +, ML11277A148 +, ML11277A148 +, ML11277A148 +, ML11277A148 +, ML11277A148 +, ML11277A148 +, ML11277A148 +, ML11277A148 +, ML11277A148 +, ML11277A148 +, ML11277A148 +, ML11277A148 +, ML11277A148 +, ML11277A148 +, ML11277A148 +, ML11277A148 +, ML11277A148 +, ML11277A148 +, ML11277A148 +, ML11277A148 +  and ML11277A148 +

2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 8.680556e-4 d (0.0208 hours, 1.240079e-4 weeks, 2.85375e-5 months)  +, 0.00104 d (0.025 hours, 1.488095e-4 weeks, 3.4245e-5 months)  +, 0.00111 d (0.0267 hours, 1.587302e-4 weeks, 3.6528e-5 months)  +, 3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 months)  +  and 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +

IEEE 384 +, IEEE 344 +, IEEE 323 +, IEEE 279 +, IEEE 603 +, IEEE 1012-1998 +  and IEEE 1028-1997 +

IR 05000391/2011605 +  and IR 05000391/2011604 +

Tritium +, Co-60 +, Cs-137 +, Sr-90 +, Co-57 +, Kr-85 +, I-131 +, C-14 +, H-3 +  and Mn-54 +

NEI 04-04 +, NEI 08-09, Re-Submittal of the Exelon Cyber Security Plan +  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 . +

NRC Bulletin 79-27 +, NRC Bulletin 80-06 +, NRC Bulletin 77-04 +  and NRC Bulletin 75-08 +

NUREG-0847, Suppl. 22, Safety Evaluation Report, Related to the Operation of Watts Bar Nuclear Plant, Unit 2 +, NUREG-847 +, NUREG/CR-2919 +, NUREG/CR-4653 +, NUREG/CR-0460 +, NUREG/CR-2907, Responds to 851105 Request for Info Re Radwaste & Containment Spray Sys.Nrc Methodology for Estimating Radwaste Generation Delineated in Encl NUREG-0017.USA Experience Summarized in Encl NUREG/CR-2907.W/o Encls +, 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-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-0713, Vol.43, Occupation Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities 2021: Fifty-Fourth Annual Report +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +  and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +

SP +, PSP +, CP +, Emergency Operating Procedure +  and Emergency Plan +

ML11277A148 +, ML11277A148 +  and ML11277A148 +

TAC:MA4176 +  and TAC:ME4620 +

Regulatory Guide 1.97 +, Regulatory Guide 1.180 +, Regulatory Guide 1.75 +, Regulatory Guide 1.70 +, Regulatory Guide 1.100 +, Regulatory Guide 1.21 +, Regulatory Guide 4.15 +, Regulatory Guide 1.8 +, Regulatory Guide 8.8 +, Regulatory Guide 1.99 +, Regulatory Guide 1.133 +, Regulatory Guide 1.152 +, Regulatory Guide 1.168 +, Regulatory Guide 1.153 +, Regulatory Guide 1.209 +, Regulatory Guide 5.71 +  and Regulatory Guide 8.19 +

SECY-07-0096, Safety Evaluation Regarding Generic Letter 2006-03, Potentially Nonconforming Hemyc and Mt Fire Barrier Configurations +  and SECY-83-293 +

SR-3.1.8 +, SR-3.3.1.3 +  and SR-3.2 +

2B1-B +, 1x10-9 +, 1x10-1 +  and 10W222-1 +

Manual Scram +  and Automatic Scram +

Tennessee +, Washington +, Idaho +  and New York +

Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Emergency Response Data System +, Safety Parameter Display System +, HVAC +, Reactor Pressure Vessel +, Auxiliary Building Gas Treatment System +, Residual Heat Removal +, Fuel Pool Cooling and Cleanup +, Emergency Gas Treatment System +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Main Condenser +, Control Rod +, Main Steam +, Containment Spray +, Extraction steam +  and Turbine Gland Sealing System +

TS-3.4.14 +, TS-3.0.1 +, TS-3.3.3 +, TS-3.4.4 +, TS-3.4.8 +, TS-3.4.12 +, TS-3.1 +, TS-3.3.1 +, TS-3.2.2 +, TS-3.9.5 +, TS-3.4.11 +, TS-3.2 +, TS-3.2.4 +, TS-3.2.1 +  and TS-3.1.8 +

Safe Shutdown +, Boric Acid +, Shutdown Margin +, High Radiation Area +, Ultimate heat sink +, Grab sample +, Fire Barrier +, Anticipated operational occurrence +, Safe Shutdown Earthquake +, Post Accident Monitoring +, Hydrostatic +, Operating Basis Earthquake +, Nondestructive Examination +, Temporary Modification +, Cyber Security +, Finite Element Analysis +, Condition Adverse to Quality +, Aging Management +, Feedwater Heater +, Stress corrosion cracking +, Loss of Offsite Power +, Eddy Current Testing +, Operability Determination +, Safeguards Contingency Plan +, Hemyc +, Earthquake +, Control of Heavy Loads +, Fuel cladding +, Core Exit Thermocouple +, Measurement Uncertainty Recapture +...

WCAP-8330 +, WCAP-12472-P-A +, WCAP-7769 +, WCAP-7907-P-A +, WCAP-7907-A +, WCAP-7979-P-A +, WCAP-9226-P-A +, WCAP-11397-P-A +, WCAP-11394-P-A +, WCAP-8567 +, WCAP-16009-P-A +, WCAP-8745-P-A +, WCAP-12945-P-A +, WCAP-9226 +, WCAP-7908-A +, WCAP-14565-P-A +, WCAP-12472-P +, WCAP-9230 +, WCAP-11395-A +, WCAP-14986 +, WCAP-11398-A +, WCAP-13869 +, WCAP-16009 +  and WCAP-8753 +

WCAP-8330 +, WCAP-12472-P-A +, WCAP-7769 +, WCAP-7907-P-A +, WCAP-7907-A +, WCAP-7979-P-A +, WCAP-9226-P-A +, WCAP-11397-P-A +, WCAP-11394-P-A +, WCAP-8567 +, WCAP-16009-P-A +, WCAP-8745-P-A +, WCAP-12945-P-A +, WCAP-9226 +, WCAP-7908-A +, WCAP-14565-P-A +, WCAP-12472-P +, WCAP-9230 +, WCAP-11395-A +, WCAP-14986 +, WCAP-11398-A +, WCAP-13869 +, WCAP-16009 +  and WCAP-8753 +