ML16054A444
From kanterella
Jump to navigation
Jump to search
ML16054A444 | |
Person / Time | |
---|---|
Site: | Monticello ![]() |
Issue date: | 01/26/2016 |
From: | Northern States Power Co, Xcel Energy |
To: | Office of Nuclear Reactor Regulation |
Shared Package | |
ML16054A376 | List:
|
References | |
L-MT-16-004 | |
Download: ML16054A444 (1) | |
Similar Documents at Monticello | |
---|---|
Category:Quality Assurance Program
MONTHYEARML18213A1542018-08-0101 August 2018
[Table view]Island Independent Spent Fuel Storage Installation, and Monticello, Submittal of Quality Assurance Topical Report (NSPM-1 Revision 13 ML17213A0362017-08-0101 August 2017 Submittal of Quality Assurance Topical Report (NSPM-1), Revision 11 ML16214A1122016-08-0101 August 2016 Submittal of Quality Assurance Topical Report (NSPM-1), Revision 9 ML16054A4442016-01-26026 January 2016 Revision 33 to the Updated Final Safety Analysis Report, Appendix C, Quality Assurance Program ML15211A0252015-07-30030 July 2015 ISFSI and Monticello - Submittal of Quality Assurance Topical Report (NSPM-1), Revision 8 ML15020A7112015-01-20020 January 2015 Independent Spent Fuel Storage Installation and Monticello, Supplement to Request for Review and Approval of Northern States Power Company Quality Assurance Topical Report ML14316A5942014-11-12012 November 2014 Quality Assurance Topical Report, NSPM-1, Revision 8a. ML13220A0072013-08-0606 August 2013 Submittal of Quality Assurance Topical Report (NSPM-1), Revision 6 ML12226A1782012-08-10010 August 2012 Independent Spent Fuel Storage Installation and Monticello - Submittal of Quality Assurance Topical Report (NSPM-1), Revision 5 ML1122014662011-08-0808 August 2011 Independent Spent Fuel and Monticello, Submittal of Quality Assurance Topical Report (NSPM-1), Revision 4 L-HU-05-017, Notification of Intent to Apply the Nuclear Management Company (NMC) Quality Assurance Topical Report, NMC-1, to Independent Spent Fuel Storage Installation (Isfsi), Spent Fuel Cask and Radioactive Waste Shipment Activities at NMC Operat2005-09-13013 September 2005 Notification of Intent to Apply the Nuclear Management Company (NMC) Quality Assurance Topical Report, NMC-1, to Independent Spent Fuel Storage Installation (Isfsi), Spent Fuel Cask and Radioactive Waste Shipment Activities at NMC Operated L-HU-04-039, Nuclear Management Company, Llc., Response to Request for Additional Information Request for Approval of Nuclear Management Company Quality Assurance Topical Report, Dated August 18, 20042004-09-22022 September 2004 Nuclear Management Company, Llc., Response to Request for Additional Information Request for Approval of Nuclear Management Company Quality Assurance Topical Report, Dated August 18, 2004 ML0330701612003-10-31031 October 2003 List of QATR Exceptions/Alternatives to NQA-1-1994 ML0330701602003-10-31031 October 2003 Existing Site QA Programs Vs QATR Comparison Matrices ML0330701572003-10-31031 October 2003 NMC Quality Assurance Topical Report NMC-1 Revision 0a L-MT-03-025, Submittal of Revision 25 of Operational Quality Assurance Plan (Oqap)2003-03-27027 March 2003 Submittal of Revision 25 of Operational Quality Assurance Plan (Oqap) 2018-08-01 Category:Updated Final Safety Analysis Report (UFSAR) MONTHYEARML23006A1322022-12-19019 December 2022
[Table view]0 to Updated Safety Analysis Report, Appendix H, Revision 29, Reactor Pressure Vessel Design Summary Report L-MT-22-021, 0 to Updated Safety Analysis Report, Appendix K, Revision 37, Renewed Operating License-USAR Supplement2022-12-19019 December 2022 0 to Updated Safety Analysis Report, Appendix K, Revision 37, Renewed Operating License-USAR Supplement ML23006A1532022-12-19019 December 2022 0 to Updated Safety Analysis Report, Appendix C, Revision 26, Quality Assurance Program ML23006A1492022-12-19019 December 2022 0 to Updated Safety Analysis Report, Section 10, Plant Auxiliary Systems ML23006A1282022-12-19019 December 2022 0 to Updated Safety Analysis Report, Appendix I, Revision 38, Evaluation of High Energy Line Breaks Outside Containment ML23006A1512022-12-19019 December 2022 0 to Updated Safety Analysis Report, Appendix F, Containment Vessel Design ML23006A1292022-12-19019 December 2022 0 to Updated Safety Analysis Report, Table of Contents ML23006A1472022-12-19019 December 2022 0 to Updated Safety Analysis Report, Section 15, Table of Contents - USAR Drawings ML23006A1482022-12-19019 December 2022 0 to Updated Safety Analysis Report, Section 14, Plant Safety Analysis ML23006A1502022-12-19019 December 2022 0 to Updated Safety Analysis Report, Section 8, Plant Electrical System ML23006A1452022-12-19019 December 2022 0 to Updated Safety Analysis Report, Section 6, Plant Engineered Safeguards ML23006A1432022-12-19019 December 2022 0 to Updated Safety Analysis Report, Section 13, Plant Operations ML23006A1412022-12-19019 December 2022 0 to Updated Safety Analysis Report, Section 9, Plant Radioactive Waste Control Systems ML23006A1422022-12-19019 December 2022 0 to Updated Safety Analysis Report, Appendix G, Probable Maximum Flood at Mississippi at Monticello Minnesota May 26, 1969 ML23006A1402022-12-19019 December 2022 0 to Updated Safety Analysis Report, Section 11, Plant Power Conversion System ML23006A1302022-12-19019 December 2022 0 to Updated Safety Analysis Report, Section 1, Introduction and Summary ML23006A1462022-12-19019 December 2022 0 to Updated Safety Analysis Report, Section 12, Plant Structures and Shielding ML23006A1442022-12-19019 December 2022 0 to Updated Safety Analysis Report, Section 5, Containment System ML23006A1392022-12-19019 December 2022 0 to Updated Safety Analysis Report, Section 2, Site and Environs ML23006A1382022-12-19019 December 2022 0 to Updated Safety Analysis Report, Appendix J, Revision 40, Fire Protection Program ML23006A1372022-12-19019 December 2022 0 to Updated Safety Analysis Report, Section 15-2 Drawing Set ML23006A1362022-12-19019 December 2022 0 to Updated Safety Analysis Report, Appendix D, Revision 35, Pre-Operational and Startup Tests ML23006A1272022-12-19019 December 2022 0 to Updated Safety Analysis Report, Section 7, Plant Instrumentation and Control System ML23006A1522022-12-19019 December 2022 0 to Updated Safety Analysis Report, Section 4, Reactor Coolant System ML23006A1552022-12-19019 December 2022 0 to Updated Safety Analysis Report, Section 3, Reactor ML23006A1352022-12-19019 December 2022 0 to Updated Safety Analysis Report, Appendix a, Revision 29, Seismic Design Criteria ML23006A1342022-12-19019 December 2022 0 to Updated Safety Analysis Report, List of Effective Pages ML23006A1562022-12-19019 December 2022 0 to Updated Safety Analysis Report, Appendix E, Revision 35, Plant Comparative Evaluation with the Proposed AEC 70 Design Criteria ML23006A1332022-12-19019 December 2022 Submittal of Revision 40 to Updated Safety Analysis Report ML21070A1112021-02-11011 February 2021 8 to Updated Safety Analysis Report, Section 3, Reactor ML21070A1202021-02-11011 February 2021 8 to Updated Safety Analysis Report, Appendix D, Pre-Operational and Startup Tests ML21070A1062021-02-11011 February 2021 8 to Updated Safety Analysis Report, Section 12, Plant Structure and Sheilding ML21070A1092021-02-11011 February 2021 8 to Updated Safety Analysis Report, Section 8, Plant Electrical Systems ML21070A1332021-02-11011 February 2021 8 to Updated Safety Analysis Report, Section 9, Plant Radioactive Waste Control Systems ML21070A1252021-02-11011 February 2021 8 to Updated Safety Analysis Report, Appendix J, Fire Protection Program ML21070A1342021-02-11011 February 2021 8 to Updated Safety Analysis Report, Section 10, Plant Auxiliary Systems ML21070A1182021-02-11011 February 2021 8 to Updated Safety Analysis Report, Section 2, Site and Environs ML21070A1222021-02-11011 February 2021 8 to Updated Safety Analysis Report, Appendix H, Reactor Pressure Vessel Design Summary Report ML21070A1322021-02-11011 February 2021 8 to Updated Safety Analysis Report, Section 13, Plant Operations ML21070A1102021-02-11011 February 2021 8 to Updated Safety Analysis Report, Drawings ML21070A1242021-02-11011 February 2021 8 to Updated Safety Analysis Report, Section 15, Drawings ML21070A1142021-02-11011 February 2021 8 to Updated Safety Analysis Report, Appendix F, Containment Vessel Design Summary Design ML21070A1162021-02-11011 February 2021 8 to Updated Safety Analysis Report, Appendix I, Evaluation of High Energy Line Breaks Outside Containment ML21070A1262021-02-11011 February 2021 8 to Updated Safety Analysis Report, Section 7, Plant Instrumentation and Control Systems ML21070A1072021-02-11011 February 2021 8 to Updated Safety Analysis Report, Appendix C, Quality Assurance Program ML21070A1042021-02-11011 February 2021 8 to the Updated Safety Analysis Report ML21070A1292021-02-11011 February 2021 8 to Updated Safety Analysis Report, Drawings ML21070A1312021-02-11011 February 2021 8 to Updated Safety Analysis Report, Section 1, Introduction and Summary L-MT-21-004, 8 to Updated Safety Analysis Report, Section 11, Plant Conversion Systems2021-02-11011 February 2021 8 to Updated Safety Analysis Report, Section 11, Plant Conversion Systems ML21070A1212021-02-11011 February 2021 8 to Updated Safety Analysis Report, Section 6, Plant Engineered Safeguards 2022-12-19 |
Text
Retrieved from "https://kanterella.com/w/index.php?title=ML16054A444&oldid=1386020"