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Issue date | Title | |
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ML23006A146 | 19 December 2022 | 0 to Updated Safety Analysis Report, Section 12, Plant Structures and Shielding |
ML21070A106 | 11 February 2021 | 8 to Updated Safety Analysis Report, Section 12, Plant Structure and Sheilding |
IR 05000263/2018012 | 24 October 2018 | NRC Design Bases Assurance Inspection (Teams); Inspection Report 05000263/2018012 (DRS-J.Benjamin) |
ML18130A921 | 14 May 2018 | Correction 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 Reactors | 28 March 2018 | Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors |
ML17319A591 | 10 December 2017 | Safety 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 Events | 28 September 2017 | Supplemental 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 Conditions | 14 June 2017 | 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 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 Interval | 31 January 2017 | 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 Interval |
ML15275A023 | 29 September 2015 | Monticello 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 Events | 20 December 2010 | Correction to Appendix C of the Monticello Individual Plant Examination of External Events |
ML070860170 | 27 March 2007 | IR 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 Report | 20 November 2003 | Submittal of Revision 20 to the Updated Safety Analysis Report |
ML20216H647 | 5 September 1997 | Forwards Response to 970414 RAI Re License Amend Request for MNGP Power Rerate Program |
ML20080L113 | 23 February 1995 | Forwards Summary Description of Monticello Vehicle Barrier Sys.Encl Withheld |