Browse wiki

10 CFR 50 Appendix J +, 10 CFR 2.309 +, 10 CFR 51.22 +, 10 CFR 50.55a +, 10 CFR 2.302#g +, 10 CFR 50.91#a +, 10 CFR 50.55a#f +, 10 CFR 2.309#d +, 10 CFR 2.309#f +, 10 CFR 2.309#c1i +, 10 CFR 2.309#h1 +, 10 CFR 2.309#h2 +, 10 CFR 2.315#c +, 10 CFR 2.315#a +, 10 CFR 51.22#b +  and 10 CFR 50.92#c +

05000255  +, 05000298  +, 05000302  +, 05000313  +, 05000324  +, 05000325  +, 05000327  +, 05000328  +, 05000336  +, 05000341  +, 05000348  +, 05000352  +, 05000353  +, 05000354  +, 05000364  +, 05000397  +, 05000423  +, 05000458  +, 05000483  +, 05000498  +, 05000499  +, 05200025  +, 05200026  +, 00336  +, 00423  +, 00341  +, 00397  +, 00313  +, 00352  +, 00353  +...

NRC-19-0001, License Amendment Request to Revise Technical Specification 3.3.5.3, Reactor Pressure Vessel (RPV) Water Inventory Control Instrumentation +, GO2-19-027, License Amendment Request for Licensing Basis Change to Control Room Air Conditioning System +, ULNRC-06485, License Amendment Request to Revise Technical Specifications for Testing of Main Turbine Control Slave Relay (LDCN 18-0025) +, ULNRC-06478, Specifications to Adopt TSTF-545 Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing, (LDCN 18-0021) +, ML19109A100 +, LR-N19-0004, Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements +, ML19099A367 +, NL-19-0221, Risk-Informed Technical Specifications Initiative 4b, Risk-Managed Technical Specifications, SNC Response to NRC Request for Additional Information (RAI) +, ML19114A535 +, ML19107A053 +, ML19092A449 +, ML19080A186 +, ML19058A029 +, ML19018A206 +, NL-19-0623, Significant Hazards Evaluation and Environmental Considerations for Farley Risk Informed Technical Specifications Response to Request for Additional Information +, ML19070A062 +, ND-19-0274, Request for License Amendment and Exemption: Update to Tier 1 Figure for Steam Generator System and Main Steam System (LAR-19-004) +, 1CAN031901, License Amendment Request Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an Lco +, NLS2019011, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation +, NL-18-0039, License Amendment Request to Revise Technical Specifications to Implement NEI 06-09, Revision 0-A, Risk-Informed Technical Specifications Initiative 4b, Risk Managed Technical Specifications (RMTS) . +  and TSTF-05-10, TSTF-439, Revision 2, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an Lco +

Turbine Trip +  and Reactor Trip +

72 FR 49139 +, 77 FR 46562 +, 75 FR 79048 +, 83 FR 26107 +, 83 FR 31183 +, 83 FR 40347 +, 84 FR 3507 +, 83 FR 48466 +  and 83 FR 36975 +

Division of Operating Reactor Licensing +  and Gregory Suber +

ML19140A456 +, ML19140A456 +, ML19140A456 +, ML19140A456 +, ML19140A456 +, ML19140A456 +, ML19140A456 +, ML19140A456 +, ML19140A456 +, ML19140A456 +, ML19140A456 +, ML19140A456 +, ML19140A456 +, ML19140A456 +, ML19140A456 +, ML19140A456 +, ML19140A456 +, ML19140A456 +, ML19140A456 +, ML19140A456 +, ML19140A456 +, ML19140A456 +, ML19140A456 +, ML19140A456 +, ML19140A456 +, ML19140A456 +, ML19140A456 +, ML19140A456 +, ML19140A456 +, ML19140A456 +...

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 +, NEI 06-09, Risk-Managed Technical Specifications (RMTS) Guidelines +  and NEI 99-01, SNC Slides - SNC Fleet - Pre-Submittal Meeting - LAR for EAL Scheme Change to NEI 99-01 Rev 7 +

ML19140A456 +, ML19140A456 +  and ML19140A456 +

EPID:L-2019-LLA-0004 +  and EPID:L-2018-LLA-0296 +

SR-3.3.2.6 +, SR-4.6.5.1.b +, SR-3.3.2 +, SR-3.3.5 +, SR-4.6.2.1.e +  and SR-4.6.5.1.a +

Millstone +, Palisades +, Fermi +, Hope Creek +, Cooper +, Sequoyah +, Arkansas Nuclear +, Columbia +, Brunswick +, Limerick +, River Bend +, Crystal River +, Callaway +, Vogtle +, Farley +  and South Texas +

Sequoyah +, Brunswick +  and Vogtle +

Texas +, Tennessee +, Pennsylvania +, Connecticut +, Georgia +, Maryland +, North Carolina +, Washington +, Alabama +, New Jersey +, Michigan +, Florida +, Louisiana +, Missouri +, Nebraska +  and Arkansas +

Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, Main Steam Isolation Valve +, Primary containment +, Main Turbine +, Emergency Core Cooling System +  and Main Steam +

TS-3.3.5.1 +, TS-3.8.3 +, TS-1.1 +, TS-3.3.5 +, TS-3.7.8 +, TS-5.5.8 +, TS-3.6.5.1 +, TS-3.3.5.3 +  and TS-6.8.4.g +

TSTF-522 +, TSTF-545 +, TSTF-439 +  and TSTF-514 +

Coatings +, Surveillance Frequency Control Program +, Exemption Request +  and Control Room Habitability +