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Letter  and Regulatory Guidance

ANSI N14.6 +, ANSI/ANS 3.1-1978 +, ANSI B30.2-1976 +, ANSI N45.2.12 +, ANSI/ANS 57.2 +, ANSI/ANS 3.2-1982 +, ANSI N13.1-1999 +, ANSI/ANS 56.5 +, ANSI/ANS 57.1 +, ANSI/ANS 57.1-1992 +, ANSI/ANS 59.51 +, ANSI/ANS 59.52 +, ANSI N13.6-1999 +, ANSI/ANS-3.1-1978 +, ANSI/ANS-6.4-1997 +  and ANSI/ANS 18.1-1999 11 +

ASME Section XI +, ASME Section III +  and ASME Section II +

Boron +, Iodine +, Uranium +, Carbon +, Hydrogen +, Lead +, Mercury +, Tin +  and Plutonium +

10 CFR 55 +, 10 CFR 50.67 +, 10 CFR 21 +, 10 CFR 26 +, 10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.36 +, 10 CFR 50.63 +, 10 CFR 50 Appendix J +, 10 CFR 50.59 +, 10 CFR 52 +, 10 CFR 71 +, 10 CFR 50.2 +, 10 CFR 50.55 +, 10 CFR 51 +, 10 CFR 61 +, 10 CFR 73 +, 10 CFR 19.12 +, 10 CFR 20.1201 +, 10 CFR 20.1301 +, 10 CFR 20.1302 +, 10 CFR 26.21 +, 10 CFR 50.33 +, 10 CFR 50.34 +, 10 CFR 50.44 +, 10 CFR 50.49 +, 10 CFR 50.61 +, 10 CFR 50.62 +...

Emergency Preparedness +  and Physical Protection +

SECY 88-260 +  and NRC 1971 +

05000438  +, 05000439  +, 00438  +  and 00439  +

Turbine Trip +  and Reactor Trip +

Tennessee Valley Authority +  and Stinson K +

GDC 50 +, GDC 10 +, GDC 55 +, GDC 61 +, GDC 14 +, GDC 60 +, GDC 13 +, GDC 64 +, GDC 62 +, GDC 32 +, GDC 2, Design bases for protection against natural phenomena +, GDC 19, Control room +, GDC 4, Environmental and dynamic effects design bases +, GDC 1, Quality standards and records +  and GDC 3, Fire protection +

NRC Generic Letter 91-18, Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability +, NRC Generic Letter 04-02 +, NRC Generic Letter 99-02 +, NRC Generic Letter 07-01 +, NRC Generic Letter 93-06, Research Results on Generic Safety Issue 106, "Piping and the Use of Highly Combustible Gases in Vital Areas" +, NRC Generic Letter 04-01 +, NRC Generic Letter 06-01 +, NRC Generic Letter 83-37, NUREG-0737 Technical Specifications +, NRC Generic Letter 98-01 +, NRC Generic Letter 97-06, Degradation of Steam Generator Internals +, NRC Generic Letter 86-10, Implementation of Fire Protection Requirements +, NRC Generic Letter 86-01, Safety Concerns Associated with Pipe Breaks in the BWR Scram System +, NRC Generic Letter 83-03 +, NRC Generic Letter 91-16, Licensed Operators' and Other Nuclear Facility Personnel Fitness for Duty +, NRC Generic Letter 90-08, Simulation Facility Exemptions +, NRC Generic Letter 82-10, Post-TMI Requirements +, NRC Generic Letter 77-08 +, NRC Generic Letter 78-06 +, NRC Generic Letter 78-07 +, NRC Generic Letter 78-25 +, NRC Generic Letter 78-33 +, NRC Generic Letter 78-37, Revised Meeting Schedule & Locations for Upgraded Guard Qualifications +, NRC Generic Letter 79-59 +, NRC Generic Letter 79-62 +, NRC Generic Letter 80-28, IEB 80-08 Examination of Containment Liner Penetration Welds +, NRC Generic Letter 81-31 +, NRC Generic Letter 81-33 +, NRC Generic Letter 82-03, High Burnup MAPLHGR Limits +, NRC Generic Letter 82-06 +, NRC Generic Letter 82-15 +...

ML12290A087 +, ML12290A087 +, ML12290A087 +, ML12290A087 +, ML12290A087 +, ML12290A087 +, ML12290A087 +, ML12290A087 +, ML12290A087 +, ML12290A087 +, ML12290A087 +, ML12290A087 +, ML12290A087 +, ML12290A087 +, ML12290A087 +, ML12290A087 +  and ML12290A087 +

IEEE 323-1974 +, IEEE 279 +, IEEE 603-1991 +, IEEE 279-1971 +, IEEE 603 +, IEEE 603-1998 +, IEEE 338-1987 +  and IEEE 323-1971 +

ML101880337 +  and ML11132A118 +

Cutler-Hammer +, Westinghouse +, Limitorque +, Valcor +, General Electric +  and Target Rock +

NEI 03-12 +, NEI 97-06, Steam Generator Conditioning Monitoring Report +, 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 . +  and NEI 99-01, SNC Slides - SNC Fleet - Pre-Submittal Meeting - LAR for EAL Scheme Change to NEI 99-01 Rev 7 +

NRC Bulletin 91-01 +, NRC Bulletin 03-01 +, NRC Bulletin 80-04 +, NRC Bulletin 05-01 +, NRC Bulletin 80-24 +, NRC Bulletin 80-14 +, NRC Bulletin 04-01 +, NRC Bulletin 79-27 +, NRC Bulletin 02-01 +, NRC Bulletin 01-01 +, NRC Bulletin 02-02 +, NRC Bulletin 80-11 +, NRC Bulletin 79-14 +, NRC Bulletin 86-02 +, NRC Bulletin 93-03 +, NRC Bulletin 11-01, Mitigating Strategies +, NRC Bulletin 88-09 +, NRC Bulletin 79-15 +, NRC Bulletin 05-02 +, NRC Bulletin 79-19 +, NRC Bulletin 83-03 +, NRC Bulletin 03-02 +, NRC Bulletin 82-02 +, NRC Bulletin 84-02 +, NRC Bulletin 96-03 +, NRC Bulletin 93-02 +, NRC Bulletin 80-06 +, NRC Bulletin 95-02 +, NRC Bulletin 87-01 +, NRC Bulletin 78-01 +...

NUREG-1736 +, NUREG-1430 +, NUREG-1823 +, NUREG/CR-4933 +, NUREG-0321 +, NUREG-0181, Forwards NUREG/CR-0181 to All Power Reactor Licensees Re Basic Barrier & Penetration Data for Physical Security Sys Assessment.W/O Encl.Addressed to All Power Reactor Licensees & Applicants +, NUREG/CR-0727 +, NUREG-0916, Notice of Issuance & Availability of Amend 51 to License DPR-18 +, NUREG-10588 +, NUREG/CR-3587 +, NUREG-1791 +, NUREG/CR-5291 +, Nureg-0313 +, 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-0219, Notice of Regional Meetings to Discuss Upgraded Guard Qualification & Training Requirements Per NUREG-0219. Agenda,Meeting Locations & Meeting Dates for Each Region & Registration Form Encl +, NUREG-0408, Discusses Review of Generic Mark I Containment Short Term Program Conducted by Owners Group.Info Avaiable in NUREG-0408 +, 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-0965, Forwards marked-up Copy of Section 3.2 of NUREG-0965, NRC Inventory of Dams, & Corrected Pages for App C & App E +, NUREG-0396, Forwards Chronology of Meetings & Discussions W/Util & Other Groups,Internal Meetings & Lists of Public & Internal Documents,Per 860828 Request for Info Re Reducing Emergency Planning Zones for Seabrook & Calvert Cliffs +, 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-1262, Discusses Review of Plant Simulation Facility Development Plan,Submitted on 880526.Overall Approach of Plan Acceptable Due to Reliance on Util Simulation Facility Group Baseline Document.Issues Requiring Resolution Stated +, NUREG-0619, Informs That Staff Finds PP&L 980330 Request for Relief from Requirements of Section 4.3 of NUREG-0619,exams of Feedwater Nozzle Bore & Inner Radius for Another Operating Cycle to Be Acceptable +, NUREG-0133, Safety Evaluation Accepting Licensee Rev 3 to ODCM for Plant Through Temporary Change 4.Rev Meets Criteria of NUREG-0133 & Other Guidance. Guidance +, 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-0473, Forwards Draft,Rev 3 to NUREG-0472, Std Radiological Effluent Controls for Pwrs, Containing Draft Guidance for Radiological Effluent Tech Specs/Odcm Commitments,Per Generic Ltr 89-01 +, NUREG-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +, NUREG-1465, Provides Commission W/Results & Findings of Evaluation of Impact of Implementing Revised Source Term Described in NUREG-1465, Accident Source Terms for Light-Water Npps, for Operating Reactors +, NUREG-0696, Forwards SER Accepting Proposed Alternate Emergency Operations Facility Location +, 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 +...

FPP +, RAP +  and CP +

TAC:79277 +  and TAC:79283 +

Regulatory Guide 1.183 +, Regulatory Guide 1.97 +, Regulatory Guide 1.4 +, Regulatory Guide 1.25 +, Regulatory Guide 1.27 +, Regulatory Guide 1.1 +, Regulatory Guide 2.6 +, Regulatory Guide 1.163 +, Regulatory Guide 1.75 +, Regulatory Guide 1.147 +, Regulatory Guide 1.45 +, Regulatory Guide 1.52 +, Regulatory Guide 1.76 +, Regulatory Guide 1.93 +, Regulatory Guide 1.33 +, Regulatory Guide 1.121 +, Regulatory Guide 1.70 +, Regulatory Guide 1.143 +, Regulatory Guide 1.84 +, Regulatory Guide 1.7 +, Regulatory Guide 1.82 +, Regulatory Guide 1.100 +, Regulatory Guide 1.106 +, Regulatory Guide 1.117 +, Regulatory Guide 1.81 +, Regulatory Guide 1.26 +, Regulatory Guide 1.8 +, Regulatory Guide 1.23 +, Regulatory Guide 1.65 +, Regulatory Guide 1.99 +...

RIS 2005-20, Rev. 1: Revision to NRC Inspection Manual Part 9900 Technical Guidance, Operability Determinations & Functionality Assessments for Resolution of Degraded or Nonconforming Conditions Adverse to Quality or Safety +  and RIS 2005-29, Anticipated Transients Developing Into More Serious Events +

07-79-05C +  and N323A-1 +

Manual Scram +  and Automatic Scram +

Tennessee +, Georgia +, Washington +  and Alabama +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Primary containment +, Emergency Response Data System +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Standby Liquid Control +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Main Condenser +, Control Rod +, Main Steam +  and Containment Spray +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Safe Shutdown +, Boric Acid +, Fitness for Duty +, Reactor Vessel Water Level +, Ultimate heat sink +, Offsite Dose Calculation Manual +, Fire Barrier +, Probabilistic Risk Assessment +, Coatings +, Anchor Darling +, Cyber Security +, Design basis earthquake +, Flow Accelerated Corrosion +, Scram Discharge Volume +, Process Control Program +, Stress corrosion cracking +, Loss of Offsite Power +, Safeguards Contingency Plan +, Hemyc +, Earthquake +, Control of Heavy Loads +, Turbine Missile +, Fuel cladding +, Pressure Boundary Leakage +, Fire Protection Program +, Brachytherapy +, Uranium Hexafluoride +, Subsequent actuation +, Manual Operator Action +, Water hammer +...