Browse wiki

TEXT-SAFETY REPORT  and SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES

Copper +  and Nickel +

10 CFR 50 +, 10 CFR 50.61 +, 10 CFR 50 Appendix G +, 10 CFR 51.22#b +  and 10 CFR 51.22#c9 +

05000321  +, 05000366  +, 00321  +  and 00366  +

NRC Generic Letter 88-11, NRC Position on Radiation Embrittlement of Reactor Vessel Materials and Its Impact on Plant Operations +  and NRC Generic Letter 92-01, Reactor Vessel Structural Integrity +

ML20137N181 +, ML20137N181 +, ML20137N181 +, ML20137N181 +, ML20137N181 +, ML20137N181 +, ML20137N181 +, ML20137N181 +, ML20137N181 +, ML20137N181 +, ML20137N181 +, ML20137N181 +, ML20137N181 +, ML20137N181 +, ML20137N181 +, ML20137N181 +, ML20137N181 +, ML20137N181 +, ML20137N181 +, ML20137N181 +, ML20137N181 +, ML20137N181 +, ML20137N181 +, ML20137N181 +  and ML20137N181 +

ML20129D914 +, HL-5360, Informs That All Pending License Amend Applications, Exemption Requests & Other Submittals Have Been Revised to Reflect Snoc as Current Authorized Operator of Plants Hatch & Vogtle +, HL-5348, Forwards Request for Addl Info Re Hatch Units 1 & 2 TS Amend on Pressure/Temp Curves +, HL-5310, Elaborates Response to NRC RAI Re P/T Submittal of 960918 +, HL-5301, Forwards Response to RAI Re 960919 TS Rev Request Re Reactor Pressure Vessel Pressure & Temp Limits +, HL-5213, Application for Amends to Licenses DPR-57 & NPF-5,clarifying Applicability of Certain Surveillances Addressing Rvp & Temp Limits & Replacing Vessel Pressure & Temp Limit Curves W/New Curves +  and 05000321/LER-1996-015, :on 961119,automatic Primary Containment Isolation Sys Actuation Occurred.Caused by Failed Control Relay.Replaced Fuse 1A71B-F21 & Coil of Relay 1A71B-K56 & Evaluated Other Relays for Replacement +

Georgia +, Illinois +  and Washington +

Reactor Coolant System +  and Reactor Pressure Vessel +