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 Issue dateTitle
ML23006A14619 December 20220 to Updated Safety Analysis Report, Section 12, Plant Structures and Shielding
ML21070A10611 February 20218 to Updated Safety Analysis Report, Section 12, Plant Structure and Sheilding
IR 05000263/201801224 October 2018NRC Design Bases Assurance Inspection (Teams); Inspection Report 05000263/2018012 (DRS-J.Benjamin)
ML18130A92114 May 2018Correction to the Report for the Audit of Lic. Responses to Interim Staff Eval. Open Items Related to U.S. Nuclear Regulatory Commission Order EA-13-109 to Modify Lic. with Regard to Reliable.....Supersedes ML18094A804
L-MT-18-010, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors28 March 2018Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
ML17319A59110 December 2017Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051
L-MT-17-066, Supplemental Information for the Notification of Full Compliance of Required Action for NRC Order EA-12-049 Mitigation Strategies for Beyond-Design-Basis External Events28 September 2017Supplemental Information for the Notification of Full Compliance of Required Action for NRC Order EA-12-049 Mitigation Strategies for Beyond-Design-Basis External Events
L-MT-17-042, Sixth Six-Month Status Report in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions14 June 2017Sixth Six-Month Status Report in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions
L-MT-17-002, Part 2 Response to Probabilistic Risk Assessment (PRA) Related Requests for Additional Information: License Amendment Request for a Permanent Extension of the 10 CFR 50Appendix J Containment Type a Test Interval31 January 2017Part 2 Response to Probabilistic Risk Assessment (PRA) Related Requests for Additional Information: License Amendment Request for a Permanent Extension of the 10 CFR 50Appendix J Containment Type a Test Interval
ML15275A02329 September 2015Monticello ISFSI - Exemption Request for Nonconformincg Dry Shielded Canister Dye Penetrant Examinations
L-MT-10-080, Correction to Appendix C of the Monticello Individual Plant Examination of External Events20 December 2010Correction to Appendix C of the Monticello Individual Plant Examination of External Events
ML07086017027 March 2007IR 05000263-07-006( Drs); 02/12/2007 Through 03/01/2007; Monticello Nuclear Generating Plant. Evaluations of Changes, Tests, Experiments and Permanent Plant Modifications
L-MT-03-083, Submittal of Revision 20 to the Updated Safety Analysis Report20 November 2003Submittal of Revision 20 to the Updated Safety Analysis Report
ML20216H6475 September 1997Forwards Response to 970414 RAI Re License Amend Request for MNGP Power Rerate Program
ML20080L11323 February 1995Forwards Summary Description of Monticello Vehicle Barrier Sys.Encl Withheld