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Safety Evaluation Report  and NUREG

ANSI/ANS 3.1-1978 +, ANSI 831.1 +, ANSI N45.2 +, ANSI 101.2 +, ANSI 18.1-1971 +, ANSI 13.1-1969 +, ANSI 830.2-1976 +, ANSI 5.12 +, ANSI/ANS 3.2 +, ANSI 51.2 +, ANSI 896.1-1971 +, ANSI/ANS-3.1-1978 +, ANSI 831.1.0-1967 +  and ANSI N18.7, Administrative Controls and Quality Assurance for Nuclear Power Plants during the Operational Phase +

ASME Section III +, ASME Section II +  and ASME Section VIII +

Atomic Energy Act of 1954 +  and Energy Reorganization Act of 1974 +

Federal Emergency Management Agency +, Occupational Safety and Health Administration +, Federal Aviation Administration +  and American Society of Civil Engineers +

Boron +, Iodine +, Cobalt +, Cesium +, Uranium +, Iron +, Krypton +, Nitrogen +, Carbon +, Oxygen +, Sodium +, Hydrogen +, Xenon +, Chlorine +, Chloride +, Lead +, Helium +, Lithium +, Aluminum +, Titanium +, Mercury +, Rhodium +, Silver +, Plutonium +  and Samarium +

10 CFR 50 Appendix R +, 10 CFR 55 +, 10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 70 +, 10 CFR 50 Appendix J +, 10 CFR 20 Appendix B +, 10 CFR 50 Appendix B +, 10 CFR 2 +, 10 CFR 19 +, 10 CFR 73 +, 10 CFR 140 +, 10 CFR 50.44 +, 10 CFR 50.47 +, 10 CFR 50 Appendix C +, 10 CFR 50 Appendix E +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix H +, 10 CFR 50 Appendix I +, 10 CFR 100.11 +, 10 CFR 100 Appendix A +, 10 CFR 50.34a +, 10 CFR 20.103 +, 10 CFR 50.7l#e +, 10 CFR 20.203 +, 10 CFR 50.55a +...

Emergency Preparedness +  and Initiating Events +

L-81-384, Forwards Responses to NRC Requests for Addl Info on Open Items in FSAR Section 7 Re Instrumentation & Control Sys. Responses Will Be Incorporated in Future FSAR Amend. Aperture Cards Are Available in PDR +, SECY-81-119 +, NRC 245 +, LD-78-069 +, LD-77-122 +  and L-81-362, Forwards Response to NRC Request for Addl Info Re Fsar.Info Will Be Incorporated in Future Amend +

05000389  +, 00389  +, 00244  +, 00368  +, 00400  +, 00335  +, 00362  +, 00382  +  and 00361  +

Technical Support Center +  and Emergency Operations Facility +

Turbine Trip +, Generator lockout relay trip +  and Reactor Trip +

Category:05000369/FSAR Chapter 15 +, Category:05000369/FSAR Chapter 14 +, Category:05000369/FSAR Chapter 11 +, 05000369/FSAR-7.3#1.1 +, Category:05000369/FSAR Chapter 7 +, 05000369/FSAR-3.9#3.3 +, 05000369/FSAR-4.4#1.1 +  and 05000369/FSAR-10.4#9 +

GDC 57 +, GDC 20 +, GDC 38 +, GDC 41 +, GDC 44 +, GDC 34 +, GDC 15 +, GDC 50 +, GDC 16 +, GDC 54 +, GDC 10 +, GDC 12 +, GDC 55 +, GDC 56 +, GDC 61 +, GDC 35 +, GDC 14 +, GDC 60 +, GDC 18 +, GDC 21 +, GDC 24 +, GDC 11 +, GDC 13 +, GDC 30 +, GDC 46 +, GDC 31 +, GDC 45 +, GDC 40 +, GDC 25 +, GDC 64 +...

NRC Generic Letter 81-27, Privacy and Proprietary Material in Emergency Plans +, NRC Generic Letter 81-23, INPO Plant Specific Evaluation Reports +, NRC Generic Letter 81-21, Natural Circulation Cooldown +, NRC Generic Letter 81-16, NUREG-0737 Item I.C.1 SER on Abnormal Transient Operating Guidelines (ATOG) +, NRC Generic Letter 81-06, Periodic Updating of Final Safety Analysis Reports (FSARS) +, NRC Generic Letter 81-04, Emergency Procedures And Training for Station Blackout Events +, NRC Generic Letter 81-01, Qualification of Inspection, Examination, Testing and Audit Personnel +  and NRC Generic Letter 87-29 +

ML19115A331 +, ML19115A331 +, ML19115A331 +, ML19115A331 +, ML19115A331 +, ML19115A331 +, ML19115A331 +, ML19115A331 +  and ML19115A331 +

1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 1.041667e-4 d (0.0025 hours, 1.488095e-5 weeks, 3.4245e-6 months)  +, 8.101852e-5 d (0.00194 hours, 1.157407e-5 weeks, 2.6635e-6 months)  +  and 5.787037e-4 d (0.0139 hours, 8.267196e-5 weeks, 1.9025e-5 months)  +

IEEE 384 +, IEEE 344 +, IEEE 323 +, IEEE 323-1974 +, IEEE 279 +, IEEE 279-1971 +, IEEE 308-1971 +, IEEE 308 +, IEEE 344-1975 +, IEEE 387 +  and IEEE 317 +

Tritium +, Kr-85 +, I-131 +, Nitrogen-16 +, Iodine-131 +, C-14 +  and Carbon-14 +

L-81-384, Forwards Responses to NRC Requests for Addl Info on Open Items in FSAR Section 7 Re Instrumentation & Control Sys. Responses Will Be Incorporated in Future FSAR Amend. Aperture Cards Are Available in PDR +  and L-81-362, Forwards Response to NRC Request for Addl Info Re Fsar.Info Will Be Incorporated in Future Amend +

LD-78-069 +  and LD-77-122 +

Westinghouse +, General Electric +  and Electro-Motive +

NFPA 20 +, NFPA 14 +  and NFPA 15 +

NRC Bulletin 79-27 +  and NRC Bulletin 80-06 +

CLI-81-12 +  and CLI-80-21, Response in Opposition to Tx Association of Community Organizations for Reform Now 800804 Motion Seeking Briefs on CLI-80-21 & Admission of Contention 11.Rulemaking on Environ Qualification Addresses Issue.W/Certificate of Svc +

NUREG-0623 +, NUREG/CR-1577 +, NUREG/CR-0497 +, NUREG/CR-2252 +, NUREG-0705 +, NUREG-0418 +, 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/CR-2062 +, NUREG-0635, Forwards SER Re TMI Item II.K.3.30 for C-E Plants,Per Conditional Acceptance of CEN-203(P),Rev 1, Response to NRC Action Plan Item II.K.3.30 Justification of Small Break LOCA Methods +, NUREG-0694, Advises That Augmented Natural Circulation Training Should Be Performed.Descriptions of Natural Circulation Tests Should Be Included in Fsar.Detailed Test Procedures Must Be Submitted 60 Days Prior to Scheduled Test Performance +, NUREG-0606, Discusses 336th Meeting of ACRS on 880407-09 Re Proposed Resolution of USI A-47, Safety Implications of Control Sys. Disagrees That NRC Recommendations Constitute Resolution of USI A-47 as Originally Defined +, NUREG-0649, Summary of ACRS Subcommittee on Auxiliary Sys 880810 Meeting in Washington,Dc to Discuss Proposed Resolution of USI A-17, Sys Interactions in Nuclear Power Plants. Related Info, Including List of Submitted Documents Encl +, 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-0801, Forwards Comments on Program Plan for Detailed Control Room Design Review (Dcrdr).Program Plan Addresses All Required Elements of DCRDR.In-progress Audit Not Planned +, NUREG-0484, Forwards SER Suppl Info on Applicant 830203 Submittal Re Applicability of Square Root of Sum of Squares Combination of Dynamic Responses.Method Applicable & Complies w/NUREG-0484 +, 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-0696, Forwards SER Accepting Proposed Alternate Emergency Operations Facility Location +, NUREG-0611, Forwards Safety Evaluation Finding Auxiliary Feedwater Sys Adequately Designed,Maintained & Operated.Finding Predicated on Implementation of Listed Recommendations Agreed to During 860929-1002 Visit +, NUREG-0843, Informs of Potential Deficiency Re 860702 Application for Amend to License NPF-16.Applicability of GDC 5 Discussed in SER (NUREG-0843) Section 9.1.2 May Need Evaluation & Analysis.Served on 861212 +, NUREG-0654, Correction to Amendment Nos. 221 and 206 to Authorize Revision of the Emergency Plan Based on NUREG-0654/FEMA-REP-1, Revision 2 +, 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-0585, Forwards NUREG-0578, TMI-2 Lessons Learned Task Force Status Report & Short-Term Requirements, & NUREG-0585, TMI-2 Lessons Learned Task Force Final Rept, in Response to .W/O Encl +, NUREG-0712, Forwards Suppl 6 to SER,NUREG-0712.W/o Encl +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-0410, Speech Entitled Shutdown Decay Heat Removal, for Presentation at 890418-20 NRC Regulatory Info Conference in Washington,Dc +, NUREG-0138, Exemption from GDC 17 Requirements Re LPCI Swing Bus Design +, NUREG-0212, Safety Evaluation Supporting Amend 99 to License DPR-20 +, NUREG/CR-0130, Responds to Encl to President Carter Re Nuclear Power Plants.Presidential 791207 Statement on Kemeny Commission Rept on TMI-2 & Excerpts from NUREG-0662 & NUREG/CR-0130 Encl +, NUREG/CR-0660, Forwards Sample Ltr to Applicants,Cp Holders & Licensees of LWRs Transmitting NUREG/CR-0660 Enhancement of Onsite Emergency Diesel Generator Reliability +...

RAP +, ES +, ST +, TP +, CP +  and CP.holders +

Regulatory Guide 1.97 +, Regulatory Guide 1.4 +, Regulatory Guide 1.25 +, Regulatory Guide 1.1 +, Regulatory Guide 1.75 +, Regulatory Guide 1.63 +, Regulatory Guide 1.74 +, Regulatory Guide 1.9 +, Regulatory Guide 1.45 +, Regulatory Guide 1.47 +, Regulatory Guide 1.52 +, Regulatory Guide 1.76 +, Regulatory Guide 1.108 +, Regulatory Guide 1.33 +, Regulatory Guide 1.70 +, Regulatory Guide 1.143 +, Regulatory Guide 1.84 +, Regulatory Guide 1.7 +, Regulatory Guide 1.82 +, Regulatory Guide 1.106 +, Regulatory Guide 1.117 +, Regulatory Guide 1.81 +, Regulatory Guide 1.6 +, Regulatory Guide 1.26 +, Regulatory Guide 1.21 +, Regulatory Guide 4.15 +, Regulatory Guide 1.8 +, Regulatory Guide 8.25 +, Regulatory Guide 8.8 +, Regulatory Guide 8.10 +...

Manual Scram +  and Automatic Scram +

Tennessee +, Connecticut +, Georgia +, Washington +, California +, Massachusetts +, Virginia +, New Jersey +, South Carolina +, Idaho +, New York +, Florida +, Louisiana +, Nebraska +, Arkansas +  and Maine +

Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Primary containment +, Main Turbine +, Shutdown Cooling +, Safety Parameter Display System +, HVAC +, Reactor Pressure Vessel +, Residual Heat Removal +, Reactor Water Cleanup +, Shield Building +, Fuel Pool Cooling and Cleanup +, Circulating Water System +, Main Steam Safety Valve +, Intermediate Range Monitor +, Remote shutdown +, Steam Jet Air Ejector +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Electrohydraulic Control +, Control Room Envelope +...

Safe Shutdown +, Boric Acid +, High winds +, Shutdown Margin +, Ultimate heat sink +, Grab sample +, Fire Barrier +, Anticipated operational occurrence +, Tornado Missile +, Safe Shutdown Earthquake +, Internal Flooding +, Hydrostatic +, Coatings +, Operating Basis Earthquake +, Nondestructive Examination +, Emergency Lighting +, High Energy Line Break +, Tornado Generated Missile +, Tornado Missile Protection +, Feedwater Heater +, Shift Technical Advisor +, Stress corrosion cracking +, Loss of Offsite Power +, Safeguards Contingency Plan +, Earthquake +, Control of Heavy Loads +, Turbine Missile +, Fuel cladding +, Pressure Boundary Leakage +, Generic Issues Program +...