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MONTHYEARML14064A3232013-12-31031 December 2013 000N0123-FBIR-NP, Rev. 0, Fuel Bundle Information Report for Nine Mile Point 2 Reload 14 Cycle 15. Project stage: Request ML14002A1702014-01-0202 January 2014 Unacceptable Application with Opportunity to Supplement - Nine Mile Point Nuclear Station, Unit 2 - MF3056, License Amendment Request - Maximum Extended Load Line Limit Analysis Plus Project stage: Other ML14002A2202014-01-0202 January 2014 Revised Unacceptable Application with Opportunity to Supplement - Nine Mile Point Nuclear Station, Unit 2 - License Amendment Request - Maximum Extended Load Line Limit Analysis Plus Project stage: Other ML14023A6542014-01-21021 January 2014 License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus - Commitment Date to Provide Supplemental Information Project stage: Supplement ML14028A3982014-01-28028 January 2014 MF3056 - Acceptance of Requested Licensing Action License Amendment Request- Maximum Extended Load Line Limit Analysis Plus (Mellla+) Project stage: Acceptance Review ML14064A3222014-01-31031 January 2014 00N0123-SRLR, Rev. 2, Supplemental Reload Licensing Report for Nine Mile Point 2 (NMP2) Reload 14 Cycle 15 Extended Power Uprate (Epu)/Maximum Extended Load Line Limit Plus (Mellla+). Project stage: Request ML14051A1382014-02-14014 February 2014 Response to Request for Supplemental Information to License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus Project stage: Supplement ML14043A0062014-02-20020 February 2014 First Round of Requests for Additional Information Regarding License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus (Mella+) Project stage: RAI ML14064A3212014-02-25025 February 2014 License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus - Core Reload and Safety Limit Supplemental Information Project stage: Supplement ML14064A3242014-02-28028 February 2014 000N2495-R1-NP, Rev. 0, Nine Mile Point Nuclear Station Unit 2 Comparison of Mellla+ Reference Design to Cycle 15 Design Characteristics. Project stage: Request ML14029A0392014-03-0505 March 2014 Request for Withholding Information from Public Disclosure License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus, Dated November 1, 2013 Project stage: Withholding Request Acceptance ML14051A0152014-03-0606 March 2014 Request for Withholding Information from Public Disclosure License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus, Dated February 14, 2014 Project stage: Withholding Request Acceptance ML14071A4662014-03-10010 March 2014 License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus - Response to Srxb RAI 1 and RAI 2 Project stage: Request ML14071A2422014-03-12012 March 2014 NMP Unit 2, MF3056, 2nd Round of Draft RAIs - LAR License Amendment Request- Maximum Extended Load Line Limit Analysis Plus (Mellla+) Project stage: Draft RAI ML14083A0232014-03-31031 March 2014 Second Round of Request for Additional Information Regarding License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus (Mellla+) Project stage: RAI ML14139A4162014-05-14014 May 2014 License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus - Response to RAI STSB-1 and RAI STSB-2 Project stage: Response to RAI ML14204A3692014-08-14014 August 2014 Third Round of Request for Additional Information & Enclosure 1, Regarding License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus (Mellla+) (Tac No. MF3056) Project stage: RAI ML14072A0152014-09-0303 September 2014 Request for Withholding Information from Public Disclosure License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus, Dated March 10, 2014 Project stage: Withholding Request Acceptance ML14246A3962014-09-0303 September 2014 NMP Unit 2, MF3056, 4th Round of Draft RAIs - LAR License Amendment Request- Maximum Extended Load Line Limit Analysis Plus (Mellla+) Project stage: Draft RAI ML14065A0902014-09-0303 September 2014 Request for Withholding Information from Public Disclosure License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus, Dated February 25, 2014 (Tac No. MF3056) Project stage: Withholding Request Acceptance NMP2L2556, Response to Request for Additional Information, License Amendment Request for Maximum Extended Load Line Limit Analysis Plus2014-09-15015 September 2014 Response to Request for Additional Information, License Amendment Request for Maximum Extended Load Line Limit Analysis Plus Project stage: Response to RAI ML14260A1202014-11-0606 November 2014 Request for Withholding Information from Public Disclosure License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus, Dated September 15, 2014 (Tac No. MF3056) Project stage: Withholding Request Acceptance ML14314A2142014-11-10010 November 2014 MF3056, E-mail Capture - LAR Mellla+, Simulator Audit Plan, November 20-21, 2014 at the Plant Site Project stage: Other ML14321A0642014-11-17017 November 2014 Point Unit 2, MF3056, LAR Mellla+, Supplement to the Simulator Audit Plan Project stage: Other ML14351A4282014-12-11011 December 2014 Updated TIP Comparisons for Current Operating Conditions, GE-PPO- 1GYEF-KG1-742, Enclosure 2 Project stage: Request ML15002A1622015-01-26026 January 2015 Request for Withholding Information from Public Disclosure Submission Dated December 11, 2014, for Supplement Information for NRC Simulator Audit LAR for Mellla+ Project stage: Withholding Request Acceptance ML15033A0022015-01-30030 January 2015 MF3056, LAR - Mellla+, Revised RAI - Neutron Fluence Calculation Related Project stage: RAI ML15051A4642015-02-18018 February 2015 Response to Fifth Request for Additional Information Concerning License Amendment Request for Maximum Extended Load Line Limit Analysis Plus Project stage: Request ML15056A3792015-03-16016 March 2015 Request for Withholding Information from Public Disclosure Submission Dated February 18, 2015, for License Amendment Request Pursuant to 10 CFR 50.90 Maximum Extended Load Line Limit Analysis Plus Project stage: Withholding Request Acceptance ML15105A4432015-05-0404 May 2015 Draft Safety Evaluation for License Amendment Request - Mellla+ Project stage: Draft Approval ML15114A1602015-05-0707 May 2015 Issuance of Simulator Audit Report License Amendment Request Regarding MELLLA Plus Project stage: Approval ML15096A0762015-09-0202 September 2015 Issuance of Amendment Maximum Extended Load Line Limit Analysis Plus Project stage: Approval ML15210A3262015-09-0404 September 2015 LTR-15-0388-1 - John W. Stetkar Letter Nine Mile Point Nuclear Station Unit 2 Maximum Extended Load Line Limit Analysis Plus (Mellla+) License Amendment Request Project stage: Other 2014-03-12
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Category:Report
MONTHYEARNMP2L2883, Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations2024-07-24024 July 2024 Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations NMP1L3563, Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-12-0404 December 2023 Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) NMP1L3545, Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems .2023-08-0404 August 2023 Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems . NMP1L3515, Submittal of Emergency Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-03-27027 March 2023 Submittal of Emergency Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) NMP1L3469, Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits2022-06-30030 June 2022 Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits RS-21-001, Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping2021-01-0404 January 2021 Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping ML20303A1752020-10-23023 October 2020 Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting ML20190A1482020-07-0808 July 2020 FAQ 20-01 NMP Scram Final Approved ML20100F6822020-04-0909 April 2020 Submittal of Analytical Evaluation of Recirculation Discharge Nozzle-to-Safe End Weld Indication ML19228A0232019-08-15015 August 2019 Proposed Alternative to Utilize Code Case N-879 NMP2L2695, Supplement Information and Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of an Emergency License Amendment Request for One Time Extension to The.2018-12-0707 December 2018 Supplement Information and Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of an Emergency License Amendment Request for One Time Extension to The. NMP1L3229, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe ...2018-08-20020 August 2018 Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe ... ML18018B2922018-01-18018 January 2018 Appendix a, Justification for Continued Operation, Component Review Summary Sheet ML18018B2912018-01-18018 January 2018 Pipe Crack Task Force Report ML18018A9652018-01-18018 January 2018 Nine Mile Point, Unit 1 - Equipment Qualification Program and Tables I - Equipment Qualification Reports and Table Ii - TMI Action Plan ML18018B0122018-01-18018 January 2018 Semi-Annual Radioactive Effluent Release Report July-December 1999 ML17251A0452017-09-20020 September 2017 - Staff Assessment of Flooding Focused Evaluation (CACs No. MG0087 and MG0088) ML17109A3652017-04-13013 April 2017 Pressure and Temperature Limits Report ML17079A3842017-03-24024 March 2017 Summary of the U.S. Nuclear Regulatory Commission Staff'S Review of the Spring 2016 Steam Generator Tube Inservice Inspections ML17037A6862017-02-0606 February 2017 Table 7.2-1 ML17037A7032017-02-0606 February 2017 Table 7.2-1 (Cont'D) ML17027A0162017-01-27027 January 2017 10 CFR 50.46 Annual Report of the Emergency Core Cooling System Evaluation Model Changes and Errors RS-16-178, High Frequency Supplement to Seismic Hazard Screening Report2016-11-0202 November 2016 High Frequency Supplement to Seismic Hazard Screening Report ML16231A4522016-08-30030 August 2016 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Phase 2 of Order EA-13-109 (Severe Accident Capable Hardened Events) ML16223A8532016-08-25025 August 2016 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Phase 2 of Order EA-13-109 (Severe Accident Capable Hardened Vents) RS-16-091, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2016-06-14014 June 2016 Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) ML16160A0942016-06-0808 June 2016 ASP ANALYSIS- REJECT- Nine Mile Point Unit 1 Automatic Reactor Scram Due to Main Steam Isolation Valve Closure (LER 220-2015-004) ML15153A6602015-06-16016 June 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Re ML15028A1492015-02-11011 February 2015 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-13-109, Severe Accident Capable Hardened Vents 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 ML15022A6612014-07-31031 July 2014 Stress Re-Evaluation of Nine Mile Point Unit 2 Steam Dryer at 115% CLTP, CDI Report No. 14-08NP, Revision 0, Non-proprietary Version ML14153A4102014-07-24024 July 2014 Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 ML14167A3492014-06-20020 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident (Tac. MF0249 & MF0250) ML15022A6622014-05-31031 May 2014 Acoustic and Low Frequency Hydrodynamic Loads at 115% CLTP Target Power Level on Nine Mile Point Unit 2 Steam Dryer to 250 Hz Using ACM Rev. 4.1R, C.D.I. Report No. 14-09NP, Revision 1, Non-proprietary Version ML15023A0312014-04-30030 April 2014 Computation of Cumulative Usage Factor for the 115% CLTP Power Level at Nine Mile Point Unit 2 with the Inboard RCIC Valve Closed, C.D.I. Technical Note No. 14-04NP, Revision 0, Non-proprietary Version ML14099A1962014-03-31031 March 2014 Constellation Energy Nuclear Group, LLC - Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task. ML14064A3242014-02-28028 February 2014 000N2495-R1-NP, Rev. 0, Nine Mile Point Nuclear Station Unit 2 Comparison of Mellla+ Reference Design to Cycle 15 Design Characteristics. ML14071A4782014-02-21021 February 2014 Response to Nrc'S Request for Cashflow Statements Regarding Application for Order Approving Transfer of Operating Authority and Conforming License Amendments ML14351A4272014-01-31031 January 2014 000N2528-SRLR, Revision 1, Supplemental Reload Licensing Report for Nine Mile Point 2 Reload 14 Cycle 15 Extended Power Uprate (3988 Mwt) / MELLLA (99-105% Flow). ML14064A3222014-01-31031 January 2014 00N0123-SRLR, Rev. 2, Supplemental Reload Licensing Report for Nine Mile Point 2 (NMP2) Reload 14 Cycle 15 Extended Power Uprate (Epu)/Maximum Extended Load Line Limit Plus (Mellla+). ML14024A4422014-01-0707 January 2014 Submittal of Report in Accordance with 10 CFR 26.719(c)(1) Regarding Unsatisfactory Blind Performance Sample Testing ML14064A3232013-12-31031 December 2013 000N0123-FBIR-NP, Rev. 0, Fuel Bundle Information Report for Nine Mile Point 2 Reload 14 Cycle 15. ML13225A5842013-12-19019 December 2013 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML13338A6632013-12-11011 December 2013 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Nine Mile Point, Unit 1, TAC No.: MF1129 ML13338A6642013-12-11011 December 2013 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Nine Mile Point, Unit 2, TAC No.: MF1130 ML13311A0542013-11-0404 November 2013 Pressure and Temperature Limits Report (PTLR) PTLR-2, Revision 0 (Draft B) ML13316B1102013-11-0101 November 2013 Attachment 9 - Global Nuclear Fuel Report GNF-0000-0156-7490-RO-NP, Gnf Additional Information Regarding the Requested Change to the Technical Specification SLMCPR, Dated August 26, 2013 (Non-proprietary) ML13311A0552013-09-30030 September 2013 Fluence Extrapolation in Support of NMP2 P-T Cure Update, MPM-913991, September 30, 2013, Attachment 3 ML13197A2222013-07-12012 July 2013 Supplemental Response to 10 CFR 50.54(f) Request for Information, Recommendation 2.3, Seismic 2024-07-24
[Table view] Category:Technical
MONTHYEARNMP1L3545, Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems .2023-08-0404 August 2023 Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems . NMP1L3469, Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits2022-06-30030 June 2022 Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits RS-21-001, Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping2021-01-0404 January 2021 Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping ML20100F6822020-04-0909 April 2020 Submittal of Analytical Evaluation of Recirculation Discharge Nozzle-to-Safe End Weld Indication ML19228A0232019-08-15015 August 2019 Proposed Alternative to Utilize Code Case N-879 NMP2L2695, Supplement Information and Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of an Emergency License Amendment Request for One Time Extension to The.2018-12-0707 December 2018 Supplement Information and Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of an Emergency License Amendment Request for One Time Extension to The. NMP1L3229, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe ...2018-08-20020 August 2018 Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe ... ML18018B0122018-01-18018 January 2018 Semi-Annual Radioactive Effluent Release Report July-December 1999 ML18018A9652018-01-18018 January 2018 Nine Mile Point, Unit 1 - Equipment Qualification Program and Tables I - Equipment Qualification Reports and Table Ii - TMI Action Plan ML17109A3652017-04-13013 April 2017 Pressure and Temperature Limits Report ML17037A7032017-02-0606 February 2017 Table 7.2-1 (Cont'D) ML17037A6862017-02-0606 February 2017 Table 7.2-1 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 ML15022A6612014-07-31031 July 2014 Stress Re-Evaluation of Nine Mile Point Unit 2 Steam Dryer at 115% CLTP, CDI Report No. 14-08NP, Revision 0, Non-proprietary Version ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 ML15022A6622014-05-31031 May 2014 Acoustic and Low Frequency Hydrodynamic Loads at 115% CLTP Target Power Level on Nine Mile Point Unit 2 Steam Dryer to 250 Hz Using ACM Rev. 4.1R, C.D.I. Report No. 14-09NP, Revision 1, Non-proprietary Version ML15023A0312014-04-30030 April 2014 Computation of Cumulative Usage Factor for the 115% CLTP Power Level at Nine Mile Point Unit 2 with the Inboard RCIC Valve Closed, C.D.I. Technical Note No. 14-04NP, Revision 0, Non-proprietary Version ML14064A3242014-02-28028 February 2014 000N2495-R1-NP, Rev. 0, Nine Mile Point Nuclear Station Unit 2 Comparison of Mellla+ Reference Design to Cycle 15 Design Characteristics. ML14071A4782014-02-21021 February 2014 Response to Nrc'S Request for Cashflow Statements Regarding Application for Order Approving Transfer of Operating Authority and Conforming License Amendments ML14064A3222014-01-31031 January 2014 00N0123-SRLR, Rev. 2, Supplemental Reload Licensing Report for Nine Mile Point 2 (NMP2) Reload 14 Cycle 15 Extended Power Uprate (Epu)/Maximum Extended Load Line Limit Plus (Mellla+). ML14351A4272014-01-31031 January 2014 000N2528-SRLR, Revision 1, Supplemental Reload Licensing Report for Nine Mile Point 2 Reload 14 Cycle 15 Extended Power Uprate (3988 Mwt) / MELLLA (99-105% Flow). ML14064A3232013-12-31031 December 2013 000N0123-FBIR-NP, Rev. 0, Fuel Bundle Information Report for Nine Mile Point 2 Reload 14 Cycle 15. ML13225A5842013-12-19019 December 2013 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML13338A6632013-12-11011 December 2013 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Nine Mile Point, Unit 1, TAC No.: MF1129 ML13338A6642013-12-11011 December 2013 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Nine Mile Point, Unit 2, TAC No.: MF1130 ML13311A0542013-11-0404 November 2013 Pressure and Temperature Limits Report (PTLR) PTLR-2, Revision 0 (Draft B) ML13316B1102013-11-0101 November 2013 Attachment 9 - Global Nuclear Fuel Report GNF-0000-0156-7490-RO-NP, Gnf Additional Information Regarding the Requested Change to the Technical Specification SLMCPR, Dated August 26, 2013 (Non-proprietary) ML13311A0552013-09-30030 September 2013 Fluence Extrapolation in Support of NMP2 P-T Cure Update, MPM-913991, September 30, 2013, Attachment 3 ML13197A2222013-07-12012 July 2013 Supplemental Response to 10 CFR 50.54(f) Request for Information, Recommendation 2.3, Seismic ML13078A3232013-02-28028 February 2013 XGEN-2012-25-NP, Revision 1, Westinghouse Engineering Report, Technical Basis for the Inspection Frequency of the Modified Alloy 718 Jet Pump Beam, Attachment 2 ML13066A1692013-02-28028 February 2013 Units I and 2, Overall Integrated Plan for Reliable Hardened Vents ML12313A2032012-10-26026 October 2012 Attachment 1, NMP2 Extended Power Uprate, Power Ascension Test Report ML12313A2042012-10-26026 October 2012 Attachment 2, Final Steam Dryer Stress Report, Continuum Dynamics, Incorporated Report No. 12-18NP, Attachment 3, Affidavit from CDI ML12277A0902012-10-12012 October 2012 Technical Letter Report on Aging Management Program Audits at Ginna and Nine Mile Point 1 ML12284A1842012-09-30030 September 2012 Attachment 3, Final EPU Steam Dryer Load Definition CDI Report No. 12-20NP, Acoustic and Low Frequency Hydrodynamic Loads at 115% CLTP Target Power Level on Nine Mile Point, Unit 2 Steam Dryer to 250 Hz Using ACM Rev. 4.1 ML12284A1852012-06-30030 June 2012 Attachment 4, Steam Dryer Limit Curves CDI Technical Note No. 12-13NP, Limit Curves with ACM Rev. 4.1 for the 100% Power Level Basis at Nine Mile Point, Unit 2, Revision 1 ML12170A8692012-06-30030 June 2012 Transition to 10 CFR 50.48(c) - NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition ML11221A0132011-08-0505 August 2011 Attachment 3, Continuum Dynamics, Inc Technical Note No. 11-17NP, Limit Curve Analysis with ACM Rev. 4.1 for Power Ascension at Nine Mile Point Unit 2, Revision 1. (Non-Proprietary) ML11208B7732011-07-0808 July 2011 Report No. 1100539.401, Rev. 1, Nine Mile Point Unit 1, Steam Dryer Support Bracket Flaw Evaluation. ML11188A1952011-06-28028 June 2011 Calculation S0VESSELM035 (SIA File No. 1100566.301), Reactor Pressure Vessel Head Weld Flaw Evaluation, Rev. 00.00 ML11171A0602011-05-31031 May 2011 Attachment 3, CDI Report No. 11-04NP, Stress Evaluation of Nine Mile Point Unit 2 Steam Dryer Using ACM Rev. 4.1 Acoustic Loads, Revision 0. (Non-Proprietary), Attachment 4, Affidavit from Continuum Dynamics, Inc ML1108803022011-03-31031 March 2011 NEDO-33636, Fuel Storage Criticality Safety Analysis of New Fuel Storage Racks - GE14, Attachment 3, (Non-Proprietary) ML1104601602011-01-31031 January 2011 Attachment 1, CDI Report No. 10-09NP, ACM Rev. 4.1: Methodology to Predict Full Scale Steam Dryer Loads from In-Plant Measurements, Revision 3 ML12135A6232011-01-14014 January 2011 Off-Site Dose Calculation Manual (Odcm), Revision 32 ML1035003652010-12-13013 December 2010 Holtec Report No. HI-2012621 (Non-Proprietary), Criticality Safety Evaluation for the Nine Mile Point 2 Rack Installation Project ML1021702952010-07-30030 July 2010 Attachment 5, Continuum Dynamics, Inc., CDI Report No. 10-12NP, Design and Stress Evaluation of Nine Mile Point Unit 2 Steam Dryer Modifications for EPU Operation ML1021701862010-07-28028 July 2010 Attachment 4, Structural Integrity Associates, Inc., Flaw Evaluation of Indications in the Nine Mile Point Unit 2 Steam Dryer Vertical Support Plates Considering Extended Power Uprate Flow Induced Vibration Loading ML1019004492010-06-30030 June 2010 C.D.I. Report No. 10-10NP, Acoustic and Low Frequency Hydrodynamic Loads at CLTP Power Level on Nine Mile Point Unit 2 Steam Dryer to 250 Hz Using ACM Rev. 4.1, Rev. 1 ML1021701852010-06-30030 June 2010 Attachment 3, Global Nuclear Fuel - Americas, LLC, MCNP01A, Low Enriched UO2 Pin Lattice in Water Critical Benchmark Evaluations Using ENDF/B-V Nuclear Cross-Section Data, Revision 1 ML1019004482010-06-30030 June 2010 C.D.I. Report No. 10-09NP, ACM Rev. 4.1: Methodology to Predict Full Scale Steam Dryer Loads from In-Plant Measurements, Rev. 1 (Non-Proprietary) 2023-08-04
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ATTACHMENT (3)
NINE MILE POINT NUCLEAR STATION UNIT 2, COMPARISON OF MELLLA+ REFERENCE DESIGN TO CYCLE 15 DESIGN CHARACTERISTICS (000N2495-R1-NP)
(NON-PROPRIETARY)
Nine Mile Point Nuclear Station, LLC February 25, 2014
GNF Global Nuclear Fuel Global Nuclear Fuel 3901 Castle Hayne Rd Wilmington, NC 28401 A Joint Venture of GE.Tohiba,. & Hitachi 00ON2495-R1-NP Revision 0 February 2014 GNF ProprietaryInformation - Class I (Public)
Nine Mile Point Nuclear Station Unit 2 Comparison of MELLLA+ Reference Design to Cycle 15 Design Characteristics Responsible Engineer:
L. Trosman Approving Manager:
R.Fawcett Authorizing Document: WA GNFO2 KG 1004 Rev 1 Verification Status: Verified
000N2495-Rl-NP Revision 0 GNF ProprietaryInformation - Class I (Public)
IMPORTANT NOTICE REGARDING THE CONTENTS OF THIS REPORT Please Read Carefully Disclaimer The only undertakings of Global Nuclear Fuel (GNF) respecting information in this document are contained in the contract between the company receiving this document and GNF.
Nothing contained in this document shall be construed as changing the applicable contract.
The use of this information by anyone other than a customer authorized by GNF to have this document, or for any purpose other than that for which it is intended, is not authorized. With respect to any unauthorized use, GNF makes no representation or warranty, and assumes no liability as to the completeness, accuracy or usefulness of the information contained in this document, or that its use may not infringe privately owned rights.
Information Notice This is a non-proprietary version of the document 000N2495-R1-P, Revision 0, which has the proprietary information removed. Portions of the document that have been removed are indicated by an open and closed bracket as shown here R I].
Page ii
000N2495-Rl-NP Revision 0 GNF Proprietary Information - Class I (Public)
REVISION
SUMMARY
Rev 0 Initial Issue Summary of Changes I
Page iii
000N2495-R1-NP Revision 0 GNF ProprietaryInformation - Class I (Public)
TABLE OF CONTENTS Section Paqe REV ISIO N SU MMARY .................................................................................................................................................... iii AC RO NYMS AND ABBREV IATIO NS .......................................................................................................................... v
- 1. SC OPE AND SU MMARY ............................................................................................................................... 1
- 2. COMPA RISO NS ............................................................................................................................................... 1 2.2 Energy Req uirem ents .................................................................................................................................. 1 2.3 Fuel Utilizatio n ................................................................................................................................................ 1 2.4 Sig nifica nt Ana lytica l Inputs ..................................................................................................................... 2 2.5 Reactivity Ma rg ins ........................................................................................................................................ 2 2.6 Therm a l Lim it Marg ins ................................................................................................................................ 3 Page iv
000N2495-R1-NP Revision 0 GNF ProprietaryInformation - Class I (Public)
ACRONYMS AND ABBREVIATIONS Item Short Form Description 1 BOC Beginning Of Cycle 2 ECCS Emergency Core Coolant System 3 MAPLHGR Maximum Average Planar Linear Heat Generation Rate 4 MELLLA+ Maximum Extended Load Line Limit Analysis Plus 5 MOC Middle Of Cycle 6 MWd Energy units MegaWatts-days 7 MWd/ST Exposure units MWd thermal energy per core weight Short Tons 8 N/A Not Applicable 9 NRC Nuclear Regulatory Commission 10 OLMCPR Operating Limit for Minimum Critical Power Ratio 11 OLTP Original Licensed Thermal Power 12 SAR Safety Analysis Report 13 SLCS Standby Liquid Control System 14 SRO Strongest Rod Out Page v
000N2495-R1-NP Revision 0 GNF ProprietaryInformation - Class I (Public)
- 1. SCOPE AND
SUMMARY
The Nine Mile Point Nuclear Station Unit 2 (NMP2) MELLLA+ project consists of the evaluations necessary to support the extensions of the NMP2 operating domain to permit operation up to 120% (3988 MWt) of OLTP at core flows as low as 85% of rated (RCF). A MELLLA+ SAR was performed with a reference core design designated hereafter as Reference Design. The scope of this report is to compare the Reference Design to the Cycle 15 design which is anticipated to apply the MELLLA+ domain once approval is obtained.
This report supports the commitment made by Nine Mile Point Nuclear Station Unit 2 to the NRC in a MELLLA+ pre-submittal meeting to supplement the MELLLA+ SAR. It should be noted Limitation and Condition 12.4, "Reload analysis submittal", from the final SE for NEDC-33006P, "Maximum Extended Load Line Limit Analysis Plus," requires that "... the SRLR for the initial MELLLA+ submittal implementation cycle shall be submitted for NRC staff confirmation." There is no SE requirement to provide a comparison report.
The items included in this comparison are as follows:
- Significant analytical inputs (i.e., design basis),
" Reactivity Margins, and
" Thermal limits.
- 2. COMPARISONS 2.1 Energy Requirements Item Parameter Units Reference Design Cycle 15 1 Total Energy MWd 2,801,012 2,580,225 2 Coastdown Length Days 40 56 2.2 Fuel Utilization Item Parameter Units Reference Design Cycle 15 3 Batch Size Bundles Bundle Average Wt. % U235 Enrichment 5 Fuel Design N/A GE14 GE14 Page 1
000N2495-R1-NP Revision 0 GNF ProprietaryInformation - Class I (Public) 2.3 Significant Analytical Inputs Item Parameter Units Reference Design Cycle 15 6 Power MWt 3988 3988
% of 7 Flow Window Rated85 Rated to 105 87 to 104 Exp Exp (MWd/ST) Values (MWd/ST) Values 8 Hot Target N/A Eigenvalues Exp Exp Cold Target (MWd/ST) Values (MWd/ST) Values 9 Eigenvalues N/A (Distributed)
Thermal Mechanical 10 Model N/A PRIME PRIME 2.4 Reactivity Margins Item Parameter Units Reference Design Cycle 15 Cold SRO Minimum 11 Shutdown Margin - % Ak Minimum occurs at BOC SLCS Minimum 12 Shutdown Margin- % Ak Minimum occurs at BOC Page 2
000N2495-R1-NP Revision 0 GNF ProprietaryInformation - Class I (Public) 2.5 Thermal Limits Item Parameter Units Reference Design Cycle 15 13 OLMCPR N/A (( ((
Exp LHGR Exp LHGR (GWd/MT) (kW/ft) (GWd/MT) (kW/ft) 14 U02 Thermal N/A Mechanical Limit Exp MAPLHGR Exp MAPLHGR (GWd/MT) (kW/ft) (GWd/MT) (kW/ft) 0.0 12.82 16.00 12.82 21.09 12.82 15 MAPLHGR Limit* N/A 63.50 8.00 70.00 5.00
Page 3
ATTACHMENT (4)
AFFIDAVIT FROM GLOBAL NUCLEAR FUEL - AMERICAS, LLC (GNF-A) JUSTIFYING WITHHOLDING PROPRIETARY INFORMATION CONTAINED IN ATTACHMENT (6)
Nine Mile Point Nuclear Station, LLC February 25, 2014
Global Nuclear Fuel - Americas AFFIDAVIT I, Lukas Trosman, state as follows:
(1) I am Engineering Manager, Reload Design and Analysis, Global Nuclear Fuel -
Americas, LLC (GNF-A), and have been delegated the function of reviewing the information described in paragraph (2) which is sought to be withheld, and have been authorized to apply for its withholding.
(2) The information sought to be withheld is contained in GNF-A proprietary report 000N0123-FBIR-P, Fuel Bundle Information Report for Nine Mile Point 2 Reload 14 Cycle 15, Revision 0, December 2013. GNF-A proprietary information in 000N0123-FBIR-P, Fuel Bundle Information Report for Nine Mile Point 2 Reload 14 Cycle 15, Revision 0, December 2013 is identified by a dotted underline inside double square brackets. ((Thi.ssentence is an.example.1 31 )) Figures and large equation objects are identified with double square brackets before and after the object. In each case, the superscript notation (31 refers to Paragraph (3) of this affidavit, which provides the basis for the proprietary determination.
(3) In making this application for withholding of proprietary information of which it is the owner or licensee, GNF-A relies upon the exemption from disclosure set forth in the Freedom of Information Act ("FOIA"), 5 USC Sec. 552(b)(4), and the Trade Secrets Act, 18 USC Sec. 1905, and NRC regulations 10 CFR 9.17(a)(4), and 2.390(a)(4) for "trade secrets" (Exemption 4). The material for which exemption from disclosure is here sought also qualify under the narrower definition of "trade secret", within the meanings assigned to those terms for purposes of FOIA Exemption 4 in, respectively, Critical Mass Energy Project v. Nuclear Regulatory Commission, 975 F2d 871 (DC Cir. 1992), and Public Citizen Health Research Group v. FDA, 704 F2d 1280 (DC Cir. 1983).
(4) Some examples of categories of information which fit into the definition of proprietary information are:
- a. Information that discloses a process, method, or apparatus, including supporting data and analyses, where prevention of its use by GNF-A's competitors without license from GNF-A constitutes a competitive economic advantage over other companies;
- b. Information which, if used by a competitor, would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product;
- c. Information which reveals aspects of past, present, or future GNF-A customer-funded development plans and programs, resulting in potential products to GNF-A;
- d. Information which discloses patentable subject matter for which it may be desirable to obtain patent protection.
00ON0123-FBIR-P Affidavit Page 1 of 3
The information sought to be withheld is considered to be proprietary for the reasons set forth in paragraphs (4)a. and (4)b. above.
(5) To address 10 CFR 2.390 (b) (4), the information sought to be withheld is being submitted to NRC in confidence. The information is of a sort customarily held in confidence by GNF-A, and is in fact so held. The information sought to be withheld has, to the best of my knowledge and belief, consistently been held in confidence by GNF-A, no public disclosure has been made, and it is not available in public sources. All disclosures to third parties including any required transmittals to NRC, have been made, or must be made, pursuant to regulatory provisions or proprietary agreements which provide for maintenance of the information in confidence. Its initial designation as proprietary information, and the subsequent steps taken to prevent its unauthorized disclosure, are as set forth in paragraphs (6) and (7) following.
(6) Initial approval of proprietary treatment of a document is made by the manager of the originating component, the person most likely to be acquainted with the value and sensitivity of the information in relation to industry knowledge, or subject to the terms under which it was licensed to GNF-A. Access to such documents within GNF-A is limited on a "need to know" basis.
(7) The procedure for approval of external release of such a document typically requires review by the staff manager, project manager, principal scientist or other equivalent authority, by the manager of the cognizant marketing function (or his delegate), and by the Legal Operation, for technical content, competitive effect, and determination of the accuracy of the proprietary designation. Disclosures outside GNF-A are limited to regulatory bodies, customers, and potential customers, and their agents, suppliers, and licensees, and others with a legitimate need for the information, and then only in accordance with appropriate regulatory provisions or proprietary agreements.
(8) The information identified in paragraph (2) is classified as proprietary because it contains details of GNF-A's fuel design and licensing methodology. The development of this methodology, along with the testing, development and approval was achieved at a significant cost to GNF-A.
The development of the fuel design and licensing methodology along with the interpretation and application of the analytical results is derived from an extensive experience database that constitutes a major GNF-A asset.
(9) Public disclosure of the information sought to be withheld is likely to cause substantial harm to GNF-A's competitive position and foreclose or reduce the availability of profit-making opportunities. The information is part of GNF-A's comprehensive BWR safety and technology base, and its commercial value extends beyond the original development cost. The value of the technology base goes beyond the extensive physical database and analytical methodology and includes development of the expertise to determine and apply the appropriate evaluation 00ON0123-FBIR-P Affidavit Page 2 of 3
process. In addition, the technology base includes the value derived from providing analyses done with NRC-approved methods.
The research, development, engineering, analytical, and NRC review costs comprise a substantial investment of time and money by GNF-A.
The precise value of the expertise to devise an evaluation process and apply the correct analytical methodology is difficult to quantify, but it clearly is substantial.
GNF-A's competitive advantage will be lost if its competitors are able to use the results of the GNF-A experience to normalize or verify their own process or if they are able to claim an equivalent understanding by demonstrating that they can arrive at the same or similar conclusions.
The value of this information to GNF-A would be lost if the information were disclosed to the public. Making such information available to competitors without their having been required to undertake a similar expenditure of resources would unfairly provide competitors with a windfall, and deprive GNF-A of the opportunity to exercise its competitive advantage to seek an adequate return on its large investment in developing and obtaining these very valuable analytical tools.
I declare under penalty of perjury that the foregoing affidavit and the matters stated therein are true and correct to the best of my knowledge, information, and belief.
Executed on this 11th day of December 2013.
Lukas Trosman Engineering Manager, Reload Design and Analysis Global Nuclear Fuel - Americas, LLC 00ON0123-FBIR-P Affidavit Page 3 of 3
ATTACHMENT (5)
AFFIDAVIT FROM GLOBAL NUCLEAR FUEL - AMERICAS, LLC (GNF-A) JUSTIFYING WITHHOLDING PROPRIETARY INFORMATION CONTAINED IN ATTACHMENT (7)
Nine Mile Point Nuclear Station, LLC February 25, 2014
Global Nuclear Fuel - Americas AFFIDAVIT I, Lukas Trosman, state as follows:
(1) I am Engineering Manager, Reload Design and Analysis, Global Nuclear Fuel -
Americas, LLC (GNF-A), and have been delegated the function of reviewing the information described in paragraph (2) which is sought to be withheld, and have been authorized to apply for its withholding.
(2) The information sought to be withheld is contained in GNF-A proprietary report 000N2495-R1 -P, Nine Mile Point Nuclear Station Unit 2 Comparisonof MELLLA +
Reference Design to Cycle 15 Design Characteristics,Revision 0, February 2014.
GNF-A proprietary information in 000N2495-RI-P, Nine Mile Point Nuclear Station Unit 2 Comparison of MELLLA+ Reference Design to Cycle 15 Design Characteristics,Revision 0, February 2014 is identified by a dotted underline inside double square brackets. ((This sentence is an exa.mpe..13.,)) In each case, the superscript notation 313 refers to Paragraph (3) of this affidavit, which provides the basis for the proprietary determination.
(3) In making this application for withholding of proprietary information of which it is the owner or licensee, GNF-A relies upon the exemption from disclosure set forth in the Freedom of Information Act ("FOIA"), 5 USC Sec. 552(b)(4), and the Trade Secrets Act, 18 USC Sec. 1905, and NRC regulations 10 CFR 9.17(a)(4), and 2.390(a)(4) for "trade secrets" (Exemption 4). The material for which exemption from disclosure is here sought also qualify under the narrower definition of "trade secret", within the meanings assigned to those terms for purposes of FOIA Exemption 4 in, respectively, Critical Mass Energy Project v. Nuclear Regulatory Commission, 975 F2d 871 (DC Cir. 1992), and Public Citizen Health Research Group v. FDA, 704 F2d 1280 (DC Cir. 1983).
(4) Some examples of categories of information which fit into the definition of proprietary information are:
- a. Information that discloses a process, method, or apparatus, including supporting data and analyses, where prevention of its use by GNF-A's competitors without license from GNF-A constitutes a competitive economic advantage over other companies;
- b. Information which, if used by a competitor, would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product;
- c. Information which reveals aspects of past, present, or future GNF-A customer-funded development plans and programs, resulting in potential products to GNF-A;
- d. Information which discloses patentable subject matter for which it may be desirable to obtain patent protection.
00ON2495-RI-P Affidavit Page 1 of 3
The information sought to be withheld is considered to be proprietary for the reasons set forth in paragraphs (4)a. and (4)b. above.
(5) To address 10 CFR 2.390 (b) (4), the information sought to be withheld is being submitted to NRC in confidence. The information is of a sort customarily held in confidence by GNF-A, and is in fact so held. The information sought to be withheld has, to the best of my knowledge and belief, consistently been held in confidence by GNF-A, no public disclosure has been made, and it is not available in public sources. All disclosures to third parties including any required transmittals to NRC, have been made, or must be made, pursuant to regulatory provisions or proprietary agreements which provide for maintenance of the information in confidence. Its initial designation as proprietary information, and the subsequent steps taken to prevent its unauthorized disclosure, are as set forth in paragraphs (6) and (7) following.
(6) Initial approval of proprietary treatment of a document is made by the manager of the originating component, the person most likely to be acquainted with the value and sensitivity of the information in relation to industry knowledge, or subject to the terms under which it was licensed to GNF-A.
(7) The procedure for approval of external release of such a document typically requires review by the staff manager, project manager, principal scientist or other equivalent authority, by the manager of the cognizant marketing function (or his delegate), and by the Legal Operation, for technical content, competitive effect, and determination of the accuracy of the proprietary designation. Disclosures outside GNF-A are limited to regulatory bodies, customers, and potential customers, and their agents, suppliers, and licensees, and others with a legitimate need for the information, and then only in accordance with appropriate regulatory provisions or proprietary agreements.
(8) The information identified in paragraph (2) is classified as proprietary because it contains details of GNF-A's fuel design and licensing methodology. The development of this methodology, along with the testing, development and approval was achieved at a significant cost to GNF-A.
The development of the fuel design and licensing methodology along with the interpretation and application of the analytical results is derived from an extensive experience database that constitutes a major GNF-A asset.
(9) Public disclosure of the information sought to be withheld is likely to cause substantial harm to GNF-A's competitive position and foreclose or reduce the availability of profit-making opportunities. The information is part of GNF-A's comprehensive BWR safety and technology base, and its commercial value extends beyond the original development cost. The value of the technology base goes beyond the extensive physical database and analytical methodology and includes development of the expertise to determine and apply the appropriate evaluation 00ON2495-RI-P Affidavit Page 2 of 3
process. In addition, the technology base includes the value derived from providing analyses done with NRC-approved methods.
The research, development, engineering, analytical, and NRC review costs comprise a substantial investment of time and money by GNF-A.
The precise value of the expertise to devise an evaluation process and apply the correct analytical methodology is difficult to quantify, but it clearly is substantial.
GNF-A's competitive advantage will be lost if its competitors are able to use the results of the GNF-A experience to normalize or verify their own process or if they are able to claim an equivalent understanding by demonstrating that they can arrive at the same or similar conclusions.
The value of this information to GNF-A would be lost if the information were disclosed to the public. Making such information available to competitors without their having been required to undertake a similar expenditure of resources would unfairly provide competitors with a windfall, and deprive GNF-A of the opportunity to exercise its competitive advantage to seek an adequate return on its large investment in developing and obtaining these very valuable analytical tools.
I declare under penalty of perjury that the foregoing affidavit and the matters stated therein are true and correct to the best of my knowledge, information, and belief.
Executed on this 7th day of February 2014.
uaTrosman Engineering Manager, Reload Design and Analysis Global Nuclear Fuel - Americas, LLC 00ON2495-Rl-P Affidavit Page 3 of 3