BYRON 2014-0003, Pressure and Temperature Limits Report (PTLR) for Measurement Uncertainty Recapture (Mur) Power Uprate
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| ML14044A019 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 02/13/2014 |
| From: | Kearney F A Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 1.10.0101, 2.01.0300, BYRON 2014-0003 | |
| Download: ML14044A019 (45) | |
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Category:Letter type:BYRON
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ML17360A1742016-10-0707 October 2016 Attachment 6: Areva Document 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations (Non-Proprietary) ML16356A0202016-10-0707 October 2016 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations. ML17095A2692016-10-0707 October 2016 Attachment 6, Areva Document 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations. ML17170A1472016-10-0707 October 2016 Areva, 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations. 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ML17360A1742016-10-0707 October 2016 Attachment 6: Areva Document 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations (Non-Proprietary) RS-16-057, Supplement to Response to Requests for Additional Information for Relief for Alternate Requirements for Repair of Reactor Vessel Head Penetrations with Nozzles Having Pressure-Retaining Partial-Penetration J-Groove Welds2016-03-15015 March 2016 Supplement to Response to Requests for Additional Information for Relief for Alternate Requirements for Repair of Reactor Vessel Head Penetrations with Nozzles Having Pressure-Retaining Partial-Penetration J-Groove Welds RS-15-267, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2015-11-30030 November 2015 Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) RS-14-277, Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 12014-09-24024 September 2014 Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 ML14178B2222014-06-24024 June 2014 Technical Review of TIA 2013-02, Single Spurious Assumptions for Braidwood and Byron Stations Safe-Shutdown Methodology BYRON 2014-0040, Pressure and Temperature Limits Report (PTLR) Revised for Negative Pressure Application During Reactor Coolant System Vacuum Fill2014-03-27027 March 2014 Pressure and Temperature Limits Report (PTLR) Revised for Negative Pressure Application During Reactor Coolant System Vacuum Fill ML14079A4232014-03-12012 March 2014 Enclosure 1, Byron Nuclear Generating Station, Flood Hazard Reevaluation Report, Revision 0 RS-14-082, ECCS Evaluation Model Error - 10 CFR 50.46 30-Day Report2014-02-27027 February 2014 ECCS Evaluation Model Error - 10 CFR 50.46 30-Day Report BYRON 2014-0003, Pressure and Temperature Limits Report (PTLR) for Measurement Uncertainty Recapture (Mur) Power Uprate2014-02-13013 February 2014 Pressure and Temperature Limits Report (PTLR) for Measurement Uncertainty Recapture (Mur) Power Uprate ML13338A6422013-12-0909 December 2013 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Byron Station, Units 1 and 2, TAC Nos.: MF0893 and MF0894 ML17255A8322013-07-0101 July 2013 Full Action Request Report AR 1531420, No Actions Tracking Update to Calculation 3C8-0282-001, Redacted RS-17-119, Byron, Units 1 and 2 - Full Action Request Report AR 1531420, No Actions Tracking Update to Calculation 3C8-0282-001, Redacted2013-07-0101 July 2013 Byron, Units 1 and 2 - Full Action Request Report AR 1531420, No Actions Tracking Update to Calculation 3C8-0282-001, Redacted ML17255A8312011-10-31031 October 2011 Full Action Request Report AR 1284054, Legacy Issues with Main Steam Tunnel Pressurization Calculation, Redacted RS-17-119, Byron, Units 1 and 2 - Full Action Request Report AR 1284054, Legacy Issues with Main Steam Tunnel Pressurization Calculation, Redacted2011-10-31031 October 2011 Byron, Units 1 and 2 - Full Action Request Report AR 1284054, Legacy Issues with Main Steam Tunnel Pressurization Calculation, Redacted ML12083A1232011-06-30030 June 2011 WCAP-17330-NP, Rev. 1, H*: Resolution of NRC Technical Issue Regarding Tubesheet Bore Eccentricity (Model F/Model D5). RS-12-023, WCAP-17330-NP, Rev. 1, H*: Resolution of NRC Technical Issue Regarding Tubesheet Bore Eccentricity (Model F/Model D5).2011-06-30030 June 2011 WCAP-17330-NP, Rev. 1, H*: Resolution of NRC Technical Issue Regarding Tubesheet Bore Eccentricity (Model F/Model D5). ML1117900382011-06-23023 June 2011 Steam Generator Tube Rupture Analysis Report, Attachment 5a to Braidwood Station, Units 1 & 2, Byron Station, Unit 1 & 2, Request for License Amendment Regarding Measurement Uncertainty Recapture (Mur) Power Uprate ML1117900422011-06-21021 June 2011 Mur Technical Evaluation, (Non-Proprietary Version), Attachment 7 to Braidwood Station, Units 1 & 2, Byron Station, Unit 1 & 2, Request for License Amendment Regarding Measurement Uncertainty Recapture (Mur) Power Uprate ML1000503662009-09-18018 September 2009 Exelon Nuclear, Form NIS-2 Owner'S Report for Repair/Replacement Activity as Required by the Provisions of the ASME Code Section Xi BYRON 2010-0001, Form NIS-2 Owner'S Report for Repair/Replacement Actitivity as Required by the Provisions of the ASME Code Section XI2009-09-16016 September 2009 Form NIS-2 Owner'S Report for Repair/Replacement Actitivity as Required by the Provisions of the ASME Code Section XI ML0925202652009-09-0404 September 2009 Attachment 3, Corrected Pages to WCAP-17072-NP (Non-Proprietary) ML17255A8302009-07-0101 July 2009 Engineering Change EC 366685, Revision 67, OP Eval. 07-006, Aux Feed Tunnel Covers Installation, Redacted RS-17-119, Byron, Units 1 and 2 - Engineering Change EC 366685, Revision 67, OP Eval. 07-006, Aux Feed Tunnel Covers Installation, Redacted2009-07-0101 July 2009 Byron, Units 1 and 2 - Engineering Change EC 366685, Revision 67, OP Eval. 07-006, Aux Feed Tunnel Covers Installation, Redacted ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 ML17255A8402008-06-30030 June 2008 Full Action Request Report AR 792213, MSLB Calc. Energy Release Error, Redacted ML17255A8372008-06-12012 June 2008 Full Action Request Report AR 789344, Error in Ms Tunnel Pressurization Calculation, Redacted RS-17-119, Byron, Units 1 and 2 - Full Action Request Report AR 789344, Error in Ms Tunnel Pressurization Calculation, Redacted2008-06-12012 June 2008 Byron, Units 1 and 2 - Full Action Request Report AR 789344, Error in Ms Tunnel Pressurization Calculation, Redacted RS-08-075, LTR-CDME-08-11, Rev. 3 Np, Interim Alternate Repair Criterion (ARC) for Cracks in the Lower Region of the Tubesheet Expansion Zone.2008-06-0303 June 2008 LTR-CDME-08-11, Rev. 3 Np, Interim Alternate Repair Criterion (ARC) for Cracks in the Lower Region of the Tubesheet Expansion Zone. ML0802304852008-01-14014 January 2008 Evaluation of 2002 USGS National Seismic Hazard Assessment, Final Report RS-07-100, Emergency Core Cooling System Evaluation Model Error - 10 CFR 50.46 Report2007-06-22022 June 2007 Emergency Core Cooling System Evaluation Model Error - 10 CFR 50.46 Report RS-07-079, Plant Specific ECCS Evaluation Change - 10 CFR 50.46 Report2007-05-10010 May 2007 Plant Specific ECCS Evaluation Change - 10 CFR 50.46 Report RS-07-059, Transmittal of WCAP-16401-NP, Revision 0, Technical Basis for Repair Options for Reactor Vessel Head Penetration Nozzles and Attachment Welds: Byron and Braidwood Units 1 & 2.2007-05-0303 May 2007 Transmittal of WCAP-16401-NP, Revision 0, Technical Basis for Repair Options for Reactor Vessel Head Penetration Nozzles and Attachment Welds: Byron and Braidwood Units 1 & 2. BYRON 2007-0051, Reactor Coolant System (RCS) Pressure and Temperature Limits Reports (PTLR)2007-04-17017 April 2007 Reactor Coolant System (RCS) Pressure and Temperature Limits Reports (PTLR) ML0702402612007-01-23023 January 2007 Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) ML0634601312006-12-0707 December 2006 Attachment 11, Exelon/Amergen Response to the Request for Additional Information, EP-EAL-0611, Criteria for Choosing Containment Radiation Monitor Reading Indicative Loss of the RCS Barrier 2023-09-29 |