Browse wiki

Environmental Protection Agency +, U.S. Fish and Wildlife Service +, Department of Natural Resources +, New York State Department of Environmental Conservation +  and New York Independent System Operator +

Piping Plover +, Alewife +, Sculpin +  and Yellow perch +

Iodine +, Uranium +, Copper +, Nitrogen +, Carbon +, Sodium +, Hydrogen +, Chlorine +, Lead +, Phosphorus +  and Zinc +

BWRVIP-75-A +, BWRVIP-75 +, BWRVIP-139 +, BWRVIP-74 +, BWRVIP-14A +, BWRVIP-62 +, BWRVIP-135 +, BWRVIP-181 +, BWRVIP-05 +, BWRVIP-1 +, BWRVIP-194 +  and BWRVIP-182 +

10 CFR 20 +, 10 CFR 50 Appendix K +, 10 CFR 50.59 +, 10 CFR 51 +, 10 CFR 50.75 +, 10 CFR 50.90 +, 10 CFR 50 Appendix I +, 10 CFR 51.41, Requirement to Submit Environmental Information +, 10 CFR 54.21 +, 10 CFR 51.51 +, 10 CFR 51.52 +, 10 CFR 9.17#a4 +, 10 CFR 2.390#a4 +  and 10 CFR 2.390#b4 +

NRC 1985 +, NRC 1996 +, NRC 2006 +  and NRC 1988 +

05000410  +, 00220  +  and 00410  +

Regulatory Guide 1.3 +, ML081230581 +, ML003714475 +, ML032760696 +, ML080230230 +, ML053360526 +  and ML070250414 +

EC-552 +  and EC-1905 +

Turbine Trip +  and Reactor Trip +

53 FR 6040 +  and 72 FR 36737 +

SC06-01 +  and SC04-14 +

MFN 06-481 +, MFN 08-693 +, MFN 04-026 +, MFN 08-089 +, MFN 05-038 +, MFN 07-517 +  and MFN 05-141 +

NRC Generic Letter 88-01, NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping +, 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 +, NRC Generic Letter 97-04, Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps +, NRC Generic Letter 98-05, Boiling Water Reactor Licensees Use of the BWRVIP-05 Report to Request Relief from Augmented Examination Requirements on Reactor Pressure Vessel Circumferential Shell Welds +, 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 88-20, Individual Plant Examination for Severe Accident Vulnerabilities +, NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +  and NRC Generic Letter 95-07, Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves +

ML091610105 +, ML091610105 +, ML091610105 +, ML091610105 +, ML091610105 +, ML091610105 +, ML091610105 +, ML091610105 +  and ML091610105 +

Tritium +, N-16 +  and Nitrogen-16 +

NEI 00-02 +  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 1985 +, NRC 1996 +, NRC 2006 +  and NRC 1988 +

NUREG/CR-6928 +, NUREG-0586, Forwards NUREG-0586, Final Generic Environ Impact Statement on Decommissioning of Nuclear Facilities, W/Re to 971113 Request for Info Pertaining to Expected Occupational Doses Associated w/long-term Storage.W/O Encl +, NUREG-1048, Forwards Safety Evaluation Supporting Proposed Turbine Sys Maint Program Submitted w/870513 Ltr +, NUREG-1555, Supplement 1, Revision 2, Standard Review Plans for Environmental Reviews for Nuclear Power Plants Supplement 1: Operating License Renewal Final Report +, 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 +, NUREG-0808, Forwards Safety Evaluation Accepting Revised Safety Relief Valve & Condensation Oscillation Loads Per NUREG-0802 & NUREG-0808 & Temp Cutoff Value Used for Elimination of Data Base for Load Computations +, NUREG-0487, Summary of 851220 Meeting W/Util & S&W Re Adequacy of Design of Downcomers at Facility.List of Attendees & Handouts Encl +, NUREG-1801, Proprosed Revision of Chapters II & III of Generic Aging Lessons (Gall) Report on Aging Management of Concrete Elements +, NUREG-0802, Notification of CRGR 820811 Meeting 16 to Discuss Resolution of Unresolved Safety Issue A-39,reg Guide Re Form of Nuclear Energy Liability Policy & Final Rule Re Reporting QA Program Changes +  and NUREG-1437, Supp. 17, Second Renewal, Generic Environmental Impact Statement for License Renewal of Nuclear Plants Supplement 17, Second Renewal Regarding Subsequent License Renewal for Dresden Nuclear Power Station, Units 2 and 3 Final Rep +

115kV +  and 345kV +

SP +, ISP +, TOP +, Emergency Operating Procedure +  and OSP-LOG-DOOl +

TAC:MC3788 +, TAC:MD0277 +  and TAC:MA6185 +

Regulatory Guide 1.183 +, Regulatory Guide 1.200 +, Regulatory Guide 1.174 +, Regulatory Guide 1.155 +, Regulatory Guide 1.3 +, Regulatory Guide 1.52 +, Regulatory Guide 1.49 +, Regulatory Guide 1.99 +, Regulatory Guide 1.54 +, Regulatory Guide 1.61 +, Regulatory Guide 1.20 +  and Regulatory Guide 1.115 +

NEDO-32465 +, NEDO-32047 +, NEDO-32686 +, NEDC-31336P +, NEDC-33351P +, NEDC-32424P +, NEDC-32399 +, NEDO-20533 +, NEDO-21231 +, NEDC-33006P +, NEDC-33173P +, NEDE-32906P +, NEDC-32906P +, NEDC-32523P +, NEDC-33004P +, NEDC-32983P +, NEDO-24548 +, NEDO-21061 +, NEDC-24154P +, NEDO-23842 +, NEDC-31994P +, NEDO-32164 +, NEDO-32424 +, NEDO-33004 +, NEDO-33159 +, NEDO-33351 +, NEDE-31604P +  and NEDO-3335t +

2CNM-AOV101 +, 07-08-08P +, 07-08-13P +  and 07-08-24P +

Maryland +, Washington +, New Jersey +, New York +  and Indiana +

Reactor Coolant System +, Feedwater +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Main Transformer +, Main Turbine +, Reactor Recirculation Pump +, HVAC +, Reactor Pressure Vessel +, High Pressure Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Circulating Water System +, Intermediate Range Monitor +, Remote shutdown +, Emergency Core Cooling System +, Main Steam Line +, Safety Relief Valve +, Electrohydraulic Control +, Main Condenser +, Control Rod +, Main Steam +, Containment Spray +  and Extraction steam +

TS-5.1 +  and TS-4.0 +

Safe Shutdown +, Shutdown Margin +, Reactor Vessel Water Level +, Non-Destructive Examination +, Stroke time +, Anticipated operational occurrence +, Probabilistic Risk Assessment +, Coatings +, Zebra Mussel +, Finite Element Analysis +, Residual transfer +, Feedwater Heater +, Intergranular Stress Corrosion Cracking +, MELLLA +, Loss of Offsite Power +, Frazil ice +, License Renewal +, Power-Operated Valves +, Turbine Missile +, Biofouling +, Offsite Circuit +, Power change +, Flow Induced Vibration +, Power Uprate +, Affidavit +, Overspeed trip +  and Spill +

Cooling Tower +  and Lake Ontario +

Continuum Dynamics +  and GE Hitachi Nuclear Energy +