ML11236A134: Difference between revisions
From kanterella
Jump to navigation
Jump to search
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
Line 15: | Line 15: | ||
| page count = 150 | | page count = 150 | ||
}} | }} | ||
=Text= | |||
{{#Wiki_filter:}} |
Revision as of 10:45, 3 August 2018
Letter Sequence Request | |
---|---|
TAC:ME6984, (Approved, Closed) | |
MONTHYEARML11236A1342011-07-31031 July 2011
[Table View]Westinghouse WCAP-17400-NP, Rev. 0, Prairie Island, Units 1 and 2 Spent Fuel Pool Criticality Safety Analysis, Enclosure 4 Project stage: Request L-2011-409, Revision to Extended Power Uprate License Amendment Request Proposed Technical Specification Regarding Fuel Loading Curve and Areal Density Criteria for Metamic Inserts2011-10-14014 October 2011 Revision to Extended Power Uprate License Amendment Request Proposed Technical Specification Regarding Fuel Loading Curve and Areal Density Criteria for Metamic Inserts Project stage: Request ML1125602172011-10-25025 October 2011 Request for Withholding of Proprietary Information from Public Disclosure Project stage: Withholding Request Acceptance ML1206203892012-03-20020 March 2012 Request for Additional Information Related to License Amendment Request for Spent Fuel Pool Criticality Changes Project stage: RAI L-2012-132, Extended Power Uprate License Amendment Request - Supplement to Proposed Technical Specification Changes Related to Spent Fuel Storage Requirements and Core Operating Limits Report (COLR) References2012-03-31031 March 2012 Extended Power Uprate License Amendment Request - Supplement to Proposed Technical Specification Changes Related to Spent Fuel Storage Requirements and Core Operating Limits Report (COLR) References Project stage: Supplement L-PI-12-038, Westinghouse, Affidavit - CE-12-3 16, Revision 1, Westingliouse Suggested Responses to the Requests for Additional Information Presented in ML120620389.2012-05-0303 May 2012 Westinghouse, Affidavit - CE-12-3 16, Revision 1, Westingliouse Suggested Responses to the Requests for Additional Information Presented in ML120620389. Project stage: Other ML12139A1982012-05-16016 May 2012 Response to Requests for Additional Information (RAI) Associated with Spent Fuel Pool Criticality Changes (TAC Nos. ME6984 and ME69851) Project stage: Response to RAI ML12215A2522012-08-0707 August 2012 Request for Additional Information Related to License Amendment Request for Spent Fuel Pool Criticality Changes Project stage: RAI L-PI-12-066, Enclosure 2 to L-PI-12-066 - Westinghouse Affidavit, Application for Withholding Proprietary Information from Public Disclosure2012-08-27027 August 2012 Enclosure 2 to L-PI-12-066 - Westinghouse Affidavit, Application for Withholding Proprietary Information from Public Disclosure Project stage: Request ML12249A0692012-09-0404 September 2012 Response to Requests for Additional Information (RAI) Associated with Spent Fuel Pool Criticality Changes Project stage: Response to RAI ML13011A3162013-01-22022 January 2013 Request for Additional Information Related to License Amendment Request for Spent Fuel Pool Criticality Changes Project stage: RAI L-PI-13-002, Response to Request for Additional Information (RAI) Associated with Spent Fuel Pool Criticality Changes2013-02-0808 February 2013 Response to Request for Additional Information (RAI) Associated with Spent Fuel Pool Criticality Changes Project stage: Response to RAI ML13197A3972013-06-25025 June 2013 NRR E-mail Capture - Prairie Island Ngp - Sfpc LAR Draft RAI Project stage: Draft Other L-PI-13-067, Response to Request for Additional Information (RAI) Associated with Spent Fuel Pool Criticality Changes2013-07-17017 July 2013 Response to Request for Additional Information (RAI) Associated with Spent Fuel Pool Criticality Changes Project stage: Response to RAI ML13241A3832013-08-29029 August 2013 Issuance of Amendments Spent Fuel Pool Criticality Changes Project stage: Approval 2012-08-27 |
ML11236A134 | |
Person / Time | |
---|---|
Site: | Prairie Island |
Issue date: | 07/31/2011 |
From: | Bishop T C, Blanco A J Westinghouse |
To: | Office of Nuclear Reactor Regulation |
References | |
L-PI-11-075 WCAP-17400-NP, Rev. 0 | |
Download: ML11236A134 (150) | |
Similar Documents at Prairie Island | |
---|---|
Category:Topical Report
MONTHYEARL-PI-23-007, Supplement to Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)2023-03-28028 March 2023
[Table view]Supplement to Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) ML22067A1492021-11-30030 November 2021 WCAP-18660-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 1 Reactor Vessel Radiation Surveillance Program, Cover Through Section 5 ML22067A1502021-11-30030 November 2021 WCAP-18660-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 1 Reactor Vessel Radiation Surveillance Program, Section 6 Through Appendix B ML22067A1512021-11-30030 November 2021 WCAP-18660-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 1 Reactor Vessel Radiation Surveillance Program, Appendix C, Part 1 ML22067A1522021-11-30030 November 2021 WCAP-18660-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 1 Reactor Vessel Radiation Surveillance Program, Appendix C, Part 2 ML22067A1532021-11-30030 November 2021 WCAP-18660-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 1 Reactor Vessel Radiation Surveillance Program, Appendix C, Part 3 ML22067A1542021-11-30030 November 2021 WCAP-18660-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 1 Reactor Vessel Radiation Surveillance Program, Appendix C, Part 4 L-PI-22-005, WCAP-18660-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 1 Reactor Vessel Radiation Surveillance Program, Appendix C, Part 5 Through Appendix D2021-11-30030 November 2021 WCAP-18660-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 1 Reactor Vessel Radiation Surveillance Program, Appendix C, Part 5 Through Appendix D L-PI-21-006, License Amendment Request to Revise Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation, to Incorporate Installed Bypass Test Capability for the Power Range RTS Functions2021-10-0202 October 2021 License Amendment Request to Revise Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation, to Incorporate Installed Bypass Test Capability for the Power Range RTS Functions ML19213A1602019-08-0101 August 2019 Submittal of Quality Assurance Topical Report (NSPM-1), Revision 14 ML18213A1542018-08-0101 August 2018 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 ML16272A1782016-09-28028 September 2016 Xcel Energy, Northern States Power Company - Minnesota - Quality Assurance Topical Report NSPM-1, Revision 10 ML15327A2292015-10-31031 October 2015 Westinghouse, WCAP-17400-NP, Supplement 1, Rev. 1, Prairie Island, Units 1 and 2 Spent Fuel Pool Criticality Analysis, Supplemental Analysis for the Storage of Ifba Bearing Fuel. 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 ML14218A6732013-12-20020 December 2013 Enclosure 2 - Xcel Energy Northern States Power Company - Minnesota - Quality Assurance Topical Report NSPM-1, Revision 7 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 ML11236A1342011-07-31031 July 2011 Westinghouse WCAP-17400-NP, Rev. 0, Prairie Island, Units 1 and 2 Spent Fuel Pool Criticality Safety Analysis, Enclosure 4 L-PI-05-110, Supplement to License Amendment Request (LAR) to Revise the Spent Fuel Pool Criticality Analyses and Technical Specifications (TS) 3.7.17, Spent Fuel Pool Storage and 4.3, Fuel Storage2005-12-0202 December 2005 Supplement to License Amendment Request (LAR) to Revise the Spent Fuel Pool Criticality Analyses and Technical Specifications (TS) 3.7.17, Spent Fuel Pool Storage and 4.3, Fuel Storage 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 L-PI-04-017, Development and Qualification of a Gothic Containment Evaluation Model for the Prairie Island Nuclear Generating Plants.2004-04-30030 April 2004 Development and Qualification of a Gothic Containment Evaluation Model for the Prairie Island Nuclear Generating Plants. ML0406803962004-01-31031 January 2004 Safety Anaysis Transition Program Licensing Report. ML0332302252003-11-12012 November 2003 Submittal of WCAP-16084-NP, Development of Risk-Informed Safety Analysis Approach and Pilot Application. ML0330701622003-10-31031 October 2003 Table Comparing ANSI N18.7-1976 to ASME Nqa -1-1994 & NMC QATR ML0330701642003-10-31031 October 2003 NQA-1 Vs Non-Programmatic ANSI Standards Comparison Tables L-PI-03-040, Praire Island, Unit 1 - Transmittal of Westinghouse Lower Row Tube Dent Root Cause Analysis2003-04-25025 April 2003 Praire Island, Unit 1 - Transmittal of Westinghouse Lower Row Tube Dent Root Cause Analysis 2023-03-28 |
Text
Retrieved from "https://kanterella.com/w/index.php?title=ML11236A134&oldid=942114"