Letter Sequence Supplement |
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EPID:L-2018-LLA-0491, Emergency License Amendment Request: One Time Extension to the High Pressure Core Spray Completion Time and Associated Surveillances (Approved, Closed) |
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Category:Letter type:NMP
MONTHYEARNMP1L3570, Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-02-0101 February 2024 Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024 CFR 50.46 Annual Report NMP1L3566, Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station2023-12-14014 December 2023 Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station NMP1L3564, Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements2023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements 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) NMP1L3557, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation NMP1L3554, Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases2023-10-0606 October 2023 Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases C NMP2L2851, Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations2023-08-25025 August 2023 Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations NMP1L3534, License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2023-08-18018 August 2023 License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation 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 . NMP1L3544, Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations2023-07-14014 July 2023 Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations NMP2L2846, Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications2023-07-0505 July 2023 Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications NMP1L3539, Day Commitment Response - 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)2023-06-0909 June 2023 Day Commitment Response - 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) NMP1L3523, Annual Radioactive Environmental Operating Report2023-05-12012 May 2023 Annual Radioactive Environmental Operating Report NMP1L3522, Independent Spent Fuel Storage Installation (ISFSI) - 2022 Radioactive Effluent Release Report2023-04-30030 April 2023 Independent Spent Fuel Storage Installation (ISFSI) - 2022 Radioactive Effluent Release Report NMP1L3525, Core Operating Limits Report2023-04-19019 April 2023 Core Operating Limits Report NMP1L3526, Submittal of Emergency Relief Request I5R-14 Concerning a Proposed Alternative Associated with N2E Safe End-to-Nozzle Dissimilar Metal Weld Repair with Laminar Indication2023-04-13013 April 2023 Submittal of Emergency Relief Request I5R-14 Concerning a Proposed Alternative Associated with N2E Safe End-to-Nozzle Dissimilar Metal Weld Repair with Laminar Indication NMP1L3520, Supplemental Information for License Amendment Request Application to Partially Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 22023-04-0404 April 2023 Supplemental Information for License Amendment Request Application to Partially Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2 NMP1L3519, 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)2023-03-30030 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) NMP1L3516, 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)2023-03-29029 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) NMP1L3517, Proposed Alternative Associated with a Weld Overlay Repair to the Torus2023-03-29029 March 2023 Proposed Alternative Associated with a Weld Overlay Repair to the Torus NMP1L3518, Proposed Alternative to Utilize Specific Provisions of Code Case N-716-3, Alternative Classification and Examination Requirements Section XI, Division 12023-03-29029 March 2023 Proposed Alternative to Utilize Specific Provisions of Code Case N-716-3, Alternative Classification and Examination Requirements Section XI, Division 1 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) NMP1L3513, 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)2023-03-24024 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) NMP1L3499, CFR 50.46 Annual Report2023-01-27027 January 2023 CFR 50.46 Annual Report NMP1L3482, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2022-12-15015 December 2022 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b NMP1L3486, Radiological Emergency Plan Document Revision2022-12-15015 December 2022 Radiological Emergency Plan Document Revision NMP1L3484, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Reatment of Structures, Systems and Components for Nuclear Power Reactors2022-12-15015 December 2022 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Reatment of Structures, Systems and Components for Nuclear Power Reactors NMP1L3485, Proposed Alternative Associated with a Weld Overlay Repair to the Torus2022-12-0808 December 2022 Proposed Alternative Associated with a Weld Overlay Repair to the Torus NMP2L2823, Supplemental Information for License Amendment Request Revise Surveillance Requirements to Reduce Excessive Fast Starting of Emergency Diesel Generators2022-10-28028 October 2022 Supplemental Information for License Amendment Request Revise Surveillance Requirements to Reduce Excessive Fast Starting of Emergency Diesel Generators NMP1L3481, Constellation Energy Generation, LLC, 10 CFR 50, Appendix E - Development of Evacuation Time Estimates2022-09-15015 September 2022 Constellation Energy Generation, LLC, 10 CFR 50, Appendix E - Development of Evacuation Time Estimates NMP1L3477, License Amendment Request - Application to Partially Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2, to Revise.2022-08-12012 August 2022 License Amendment Request - Application to Partially Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2, to Revise. NMP1L3478, Response to Request for Additional Information - Relief Request Associated with Pump Periodic Verification Tests of Core Spray System Pumps2022-08-0505 August 2022 Response to Request for Additional Information - Relief Request Associated with Pump Periodic Verification Tests of Core Spray System Pumps 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 NMP1L3467, License Amendment Request - Revision to Alternative Source Term Calculation for Main Steam Isolation Valve (MSIV) Leakage and Non-MSIV Leakage2022-06-29029 June 2022 License Amendment Request - Revision to Alternative Source Term Calculation for Main Steam Isolation Valve (MSIV) Leakage and Non-MSIV Leakage NMP1L3465, Independent Spent Fuel Storage Installation - General License 30-day Cask Registration Notifications2022-06-17017 June 2022 Independent Spent Fuel Storage Installation - General License 30-day Cask Registration Notifications NMP1L3462, Independent Spent Fuel Storage Installation, General License 30-day Cask Registration Notifications2022-06-0909 June 2022 Independent Spent Fuel Storage Installation, General License 30-day Cask Registration Notifications NMP2L2799, License Amendment Request - Revise Surveillance Requirements to Reduce Excessive Fast Starting of Emergency Diesel Generators2022-05-24024 May 2022 License Amendment Request - Revise Surveillance Requirements to Reduce Excessive Fast Starting of Emergency Diesel Generators NMP2L2811, Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2022 Owner'S Activity Report for RFO-18 Inservice Examinations2022-05-13013 May 2022 Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2022 Owner'S Activity Report for RFO-18 Inservice Examinations NMP1L3459, 2021 Annual Radiological Environmental Operating Report2022-05-0808 May 2022 2021 Annual Radiological Environmental Operating Report NMP1L3457, 2021 Radioactive Effluent Release Report for Nine Mile Point Units 1 and 22022-04-30030 April 2022 2021 Radioactive Effluent Release Report for Nine Mile Point Units 1 and 2 NMP2L2805, Annual Environmental Operating Report2022-04-23023 April 2022 Annual Environmental Operating Report NMP2L2807, Core Operating Limits Report2022-04-0707 April 2022 Core Operating Limits Report NMP1L3458, Constellation Energy Generation, LLC, Annual Property Insurance Status Report2022-04-0101 April 2022 Constellation Energy Generation, LLC, Annual Property Insurance Status Report NMP1L3454, Relief Request Associated with Pump Periodic Verification Tests of Core Spray System Pumps2022-03-0202 March 2022 Relief Request Associated with Pump Periodic Verification Tests of Core Spray System Pumps NMP1L3447, Constellation Energy Generation, LLC - Response to Request for Additional Information - Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs2022-02-0202 February 2022 Constellation Energy Generation, LLC - Response to Request for Additional Information - Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs NMP1L3444, CFR 50.46 Annual Report2022-01-27027 January 2022 CFR 50.46 Annual Report NMP2L2794, Supplemental Information to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-582, Revision 02022-01-11011 January 2022 Supplemental Information to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-582, Revision 0 NMP2L2793, Supplemental Information - Relief Request Associated with Excess Flow Check Valves2021-12-17017 December 2021 Supplemental Information - Relief Request Associated with Excess Flow Check Valves NMP2L2789, Response to Request for Additional Information by the Office of Reactor Regulation to Support Review of License Amendment Request to Adopt TSTF-582, Revision 02021-12-16016 December 2021 Response to Request for Additional Information by the Office of Reactor Regulation to Support Review of License Amendment Request to Adopt TSTF-582, Revision 0 2024-02-01
[Table view] Category:Report
MONTHYEARNMP1L3563, 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) 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 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 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 ML13066A1712013-02-28028 February 2013 R.E. Gina, Overall Integrated Plan for Mitigation Strategies for Beyond-Design-Basis External Events 2023-08-04
[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
[Table view] Category:Response to Request for Additional Information (RAI)
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 . NMP1L3519, 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)2023-03-30030 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) NMP1L3516, 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)2023-03-29029 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) NMP1L3478, Response to Request for Additional Information - Relief Request Associated with Pump Periodic Verification Tests of Core Spray System Pumps2022-08-0505 August 2022 Response to Request for Additional Information - Relief Request Associated with Pump Periodic Verification Tests of Core Spray System Pumps RS-22-027, Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated2022-02-23023 February 2022 Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated P NMP1L3447, Constellation Energy Generation, LLC - Response to Request for Additional Information - Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs2022-02-0202 February 2022 Constellation Energy Generation, LLC - Response to Request for Additional Information - Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs NMP2L2794, Supplemental Information to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-582, Revision 02022-01-11011 January 2022 Supplemental Information to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-582, Revision 0 NMP2L2789, Response to Request for Additional Information by the Office of Reactor Regulation to Support Review of License Amendment Request to Adopt TSTF-582, Revision 02021-12-16016 December 2021 Response to Request for Additional Information by the Office of Reactor Regulation to Support Review of License Amendment Request to Adopt TSTF-582, Revision 0 NMP2L2787, Response to Request for Additional Information - Relief Request Associated with Excess Flow Check Valves2021-11-15015 November 2021 Response to Request for Additional Information - Relief Request Associated with Excess Flow Check Valves JAFP-21-0087, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-09-16016 September 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments NMP2L2773, Company - Response to Request for Additional Information2021-06-30030 June 2021 Company - Response to Request for Additional Information JAFP-21-0044, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-06-11011 June 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments NMP1L3402, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of License Amendment Request to Adopt TSTF-582, Revision 02021-06-0404 June 2021 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of License Amendment Request to Adopt TSTF-582, Revision 0 JAFP-21-0032, Response to Request for Additional Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting2021-04-20020 April 2021 Response to Request for Additional Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting NMP1L3376, Supplemental Information to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Adopt TSTF-334, Revision 22021-01-27027 January 2021 Supplemental Information to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Adopt TSTF-334, Revision 2 NMP1L3373, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of License Amendment Request to Adopt TSTF-334, Revision 22021-01-22022 January 2021 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of License Amendment Request to Adopt TSTF-334, Revision 2 NMP2L2754, Responses to Request for Additional Information Questions 27 and 28 to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 22021-01-0707 January 2021 Responses to Request for Additional Information Questions 27 and 28 to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 NMP2L2749, Responses to Request for Additional Information Questions 17 and 26 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Rev. 22020-10-22022 October 2020 Responses to Request for Additional Information Questions 17 and 26 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Rev. 2 NMP2L2745, Request for Additional Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 22020-10-0202 October 2020 Request for Additional Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 RS-20-112, Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-5682020-09-0303 September 2020 Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-568 NMP2L2742, Response to Request for Additional Information by NRR to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request Re Risk Informed Categorization & Structures, Systems and Components2020-08-28028 August 2020 Response to Request for Additional Information by NRR to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request Re Risk Informed Categorization & Structures, Systems and Components ML20188A2642020-07-0606 July 2020 Clinton Power Station, R.E. Ginna Station, Limerick Station, Nine Mile Point Station & Peach Bottom Station - Proposed Alternative to Utilize Code Case OMN-26 - Response to Request for Additional Information NMP2L2713, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Increase Allowable MSIV Leakage Rates2019-11-21021 November 2019 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Increase Allowable MSIV Leakage Rates NMP2L2711, Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-8792019-10-16016 October 2019 Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-879 JAFP-19-0057, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-8802019-06-0404 June 2019 Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880 NMP1L3279, Response to Request for Additional Information - Proposed Alternatives to Utilize Code Cases N-878 and N-880 for Plants2019-05-0101 May 2019 Response to Request for Additional Information - Proposed Alternatives to Utilize Code Cases N-878 and N-880 for Plants NMP1L3264, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Revise Technical Specifications 3.3.1 for Primary Contain2019-02-25025 February 2019 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Revise Technical Specifications 3.3.1 for Primary Containm JAFP-19-0006, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-8802019-01-0808 January 2019 Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880 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. NMP1L3248, Supplement to the Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Apply TSTF-542, Revision 2, Reactor Pre2018-11-0202 November 2018 Supplement to the Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Apply TSTF-542, Revision 2, Reactor Pres NMP1L3238, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Apply TSTF-542, ...2018-10-0101 October 2018 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Apply TSTF-542, ... NMP1L3233, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, Removal of Boraflex Credit License Amendment Request (L-2018-LLA-0039)2018-08-17017 August 2018 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, Removal of Boraflex Credit License Amendment Request (L-2018-LLA-0039) NMP1L3221, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 & 2, R. E. Ginna - Response to Request for Additional Information License Amendment Request to Adopt Emergency Action Level Schemes.2018-05-10010 May 2018 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 & 2, R. E. Ginna - Response to Request for Additional Information License Amendment Request to Adopt Emergency Action Level Schemes. RS-18-061, Response to Request for Additional Information Regarding Decommissioning Funding Plans for Independent Spent Fuel Storage Installations (Isfsis)2018-05-0202 May 2018 Response to Request for Additional Information Regarding Decommissioning Funding Plans for Independent Spent Fuel Storage Installations (Isfsis) ML18025A7992018-01-25025 January 2018 Response to Request for Additional Information Regarding Generic Letter 2016-01 NMP2L2662, Supplemental Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22017-12-27027 December 2017 Supplemental Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 NMP2L2658, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-542, Revision 2, Reactor Pressure Vessel Water2017-11-0303 November 2017 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-542, Revision 2, Reactor Pressure Vessel Water NMP1L3180, Submittal of Relief Request NMP-RR-001 Concerning Nozzle-to-Vessel Weld and Inner Radii Examinations (Use of Code Case N-702)2017-09-18018 September 2017 Submittal of Relief Request NMP-RR-001 Concerning Nozzle-to-Vessel Weld and Inner Radii Examinations (Use of Code Case N-702) RS-17-053, Response to Request for Additional Information Regarding Generic Letter 2016-012017-04-27027 April 2017 Response to Request for Additional Information Regarding Generic Letter 2016-01 NMP1L3146, Response to Request for Additional Information to Relief to Perform Pressure Isolation Valve Leakage Testing at Frequencies Consistent with 10 CFR 50, Appendix J2017-04-0606 April 2017 Response to Request for Additional Information to Relief to Perform Pressure Isolation Valve Leakage Testing at Frequencies Consistent with 10 CFR 50, Appendix J RS-17-044, Response to Request for Additional Information Regarding Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography2017-03-13013 March 2017 Response to Request for Additional Information Regarding Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography RS-17-027, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal2017-03-10010 March 2017 Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal ML17037A2652017-02-0606 February 2017 Response to Request for Information Concerning Regional Meteorological Conditions Characterizing Atmospheric Transport Processes within 50 Miles of the Plant RA-16-049, Response to Request for Additional Information Regarding Requests to Withhold Emergency Preparedness Documents from Public Disclosure2016-05-26026 May 2016 Response to Request for Additional Information Regarding Requests to Withhold Emergency Preparedness Documents from Public Disclosure ML16131A6542016-05-0404 May 2016 Response to a Question Raised During the Audit ML16131A6552016-05-0404 May 2016 White Paper Prepared in Response to a Question Raised During the Audit NMP2L2616, Supplemental Response to Request for Additional Information by NRR to Support Review of Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual2016-03-21021 March 2016 Supplemental Response to Request for Additional Information by NRR to Support Review of Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual NMP1L3068, Supplemental Information to Request for Additional Information - Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to A....2016-01-25025 January 2016 Supplemental Information to Request for Additional Information - Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to A.... NMP2L2611, Response to Request for Additional Information by NRR to Support Review of Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual2016-01-0808 January 2016 Response to Request for Additional Information by NRR to Support Review of Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual NMP1L3064, Supplemental Response to Request for Additional Information - Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements....2015-12-22022 December 2015 Supplemental Response to Request for Additional Information - Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements.... 2023-08-04
[Table view] Category:Technical Specifications
MONTHYEARML23289A0122023-12-0606 December 2023 Issuance of Amendment No. 250 Regarding the Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs ML23131A4242023-06-23023 June 2023 Issuance of Amendment No. 249 Regarding the Revision to Technical Specification 3.3.1 to Adopt Technical Specifications Task Force Traveler TSTF-568 ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position RS-22-049, Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for2022-04-0404 April 2022 Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for V ML22033A3102022-03-0404 March 2022 Issuance of Amendment No. 190, Changes to Reactor Pressure Vessel Water Inventory Control Technical Specification Requirements ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements NMP2L2794, Supplemental Information to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-582, Revision 02022-01-11011 January 2022 Supplemental Information to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-582, Revision 0 ML21295A7342021-11-15015 November 2021 Issuance of Amendment No. 187 Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2021-09-27027 September 2021 Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML21033A5302021-04-0101 April 2021 Issuance of Amendments to Adopt Technical Specifications Task Force TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems ML21049A0062021-03-16016 March 2021 Issuance of Amendment No. 245 for Relaxation of Surveillance Frequency for Instrument-Line Flow Check Valve ML21077A0142021-03-16016 March 2021 License and Technical Specification Pages for Amendment No. 245, Relaxation of Surveillance Frequency for Instrument-Line Flow Check Valve ML21013A0052021-02-0404 February 2021 Issuance of Amendments to Adopt Technical Specifications Task Traveler TSTF-568, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2 ML20332A1152021-01-29029 January 2021 Issuance of Amendment No. 183 Regarding Risk-Informed Categorization and Treatment of Structures, Systems, and Components RS-20-016, County, Nine Mile Point, Peach Bottom Atomic and Quad Cities - Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems2020-04-13013 April 2020 County, Nine Mile Point, Peach Bottom Atomic and Quad Cities - Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems ML19176A0862019-07-30030 July 2019 Issuance of Amendment No. 237 Changes to Containment Oxygen Concentration Requirements ML18344A4522019-01-11011 January 2019 Issuance of Amendment No. 234 Change to Remove Boraflex Credit from Spent Fuel Racks 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. ML18330A0952018-11-30030 November 2018 Correction Duplicate Subparagraph (N) on Technical Specification Page 204 That Occurred in Amendment No. 186 Issued January 25, 2005 RS-18-020, Application to Revise Technical Specifications to Modify the APRM Channel Adjustment Surveillance Requirement2018-06-15015 June 2018 Application to Revise Technical Specifications to Modify the APRM Channel Adjustment Surveillance Requirement ML18032A1772018-03-0606 March 2018 Issuance of Amendment No. 166 to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-522 (CAC No. MF9804; EPID L-2017-LLA-0232) NMP2L2662, Supplemental Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22017-12-27027 December 2017 Supplemental Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 ML17324B1782017-12-21021 December 2017 Issuance of Amendment to Allow Greater Flexibility in Performing Surveillance Testing in Modes 1, 2, or 3 of Emergency Diesel Generators(Cac No. MF9579; EPID L-2017-LLA-0203) ML17152A3202017-06-30030 June 2017 Issuance of Amendments Emergency Plans Emergency Action Level HU1.5 ML17055A4512017-03-0909 March 2017 Issuance of Amendment Partial Length Fuel Rod Burnup ML16088A0532016-04-19019 April 2016 Issuance of Amendment License Amendment Request for Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual ML15352A1642016-03-17017 March 2016 Calvert Cliffs, Units 1 & 2 and Independent Spent Fuel Storage Installation; Nine Mile, Units 1 & 2 and R. E. Ginna - Issuance of Amendments Regarding the Emergency Plan Requalification Training Frequency for Emergency Response Organization Personnel NMP2L2611, Response to Request for Additional Information by NRR to Support Review of Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual2016-01-0808 January 2016 Response to Request for Additional Information by NRR to Support Review of Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual ML15341A3362016-01-0505 January 2016 Issuance of Amendment Technical Specifications for Safety Limit Minimum Critical Power Ratio NMP1L3064, Supplemental Response to Request for Additional Information - Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements....2015-12-22022 December 2015 Supplemental Response to Request for Additional Information - Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements.... ML15317A3072015-11-30030 November 2015 Issuance of Amendment Adoption of Technical Specification Task Force Traveler 425 ML15096A0762015-09-0202 September 2015 Issuance of Amendment Maximum Extended Load Line Limit Analysis Plus ML15223B2502015-08-14014 August 2015 and Nine Mile Point Nuclear Station, Unit No. 2- Copy of License Amendment Nos. 313, 291, 118, and 150 ML15161A3802015-07-30030 July 2015 R. E. Ginna and Nine Mile Point, Unit 2 - Issuance of Amendments Regarding Implementation of Technical Specification Task Force Traveler 523, Generic Letter 2008-01, Managing Gas Accumulation (TAC Nos. MF4405 - MF4409) ML15167A3152015-07-0808 July 2015 Issuance of Amendments Change to TS Requirements Regarding Education and Experience Eligibility Requirements for Licensed Operators ML15110A0082015-05-26026 May 2015 Issuance of Amendment Primary Containment Isolation Instrumentation Technical Specification Allowable Value Change ML15075A1592015-03-17017 March 2015 Correction Letter to Amendment No. 217 Diesel Generator Initiation - Degraded Voltage Time Delay Setting Change (Tac No. MF1022) ML15043A2702015-03-12012 March 2015 Issuance of Amendment Diesel Generator Initiation - Degraded Voltage Time Delay Setting Change ML14126A0032014-06-30030 June 2014 Issuance of Amendment Regarding Transition to a Risk-Informed, Performance-Based Fire Protection Program in Accordance with 10 CFR 50.48(c) ML14057A5542014-05-29029 May 2014 Issuance of Amendment Regarding Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report ML1233803362012-11-21021 November 2012 License Amendment Request Pursuant to 10 CFR 50.90: Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report ML1133000472011-12-22022 December 2011 NMP2 EPU - Operating License and Technical Specification Pages ML1133000412011-12-22022 December 2011 Cover Letter - Nine Mile Point Nuclear Station, Unit No. 2 - Issuance of Amendment Extended Power Uprate ML11208C3952011-07-20020 July 2011 License Amendment Requests Pursuant to 10 CFR 50.90: Revisions to the Technical Specifications Design Features Sections to Reflect Transfer of a Portion of Nine Mile Point Nuclear Station Site Real Property ML1018803332010-07-26026 July 2010 Issuance of Amendment No. 206 Modification of TS Section 3.2.7.1 and 4.2.7.1 ML1008904222010-03-22022 March 2010 License Amendment Request Pursuant to 10 CFR 50.90: Revision to Containment Spray System Nozzle Surveillance Frequency ML0926406812009-09-18018 September 2009 License Amendment Request Pursuant to 10 CFR 50.90: Revisions to Primary Coolant System Pressure Isolation Valve Requirements Consistent with Standard Technical Specifications - Tech. Spec. Sections 3.2.7.1 and 4.2.7.1 ML0919504152009-07-0202 July 2009 License Amendment Request to Remove Position Indication for Relief Valves and Safety Valves from Technical Specifications ML0905605222009-02-11011 February 2009 Units, 1 & 2, License Amendment Request for Adoption of TSTF-511-A Rev. 0 Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26. 2023-08-30
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Exelon Generation 200 Exelon Way Kennett Square. PA 19348 www exeloncorp com PROPRIETARY INFORMATION -WITHHOLD UNDER 10 CFR 2.390 10 CFR 50.90 NMP2L2695 December 7, 2018 U.S. Nuclear Regulatory Commission ATIN : Document Control Desk Washington, DC 20555-0001 Nine Mile Point Nuclear Station, Unit 2 Renewed Facility Operating License No. NPF-69 NRC Docket No. 50-410
Subject:
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 High Pressure Core Spray Completion Time and Associated Surveillances
Reference:
- 1. Letter from J. Barstow (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "Emergency License Amendment Request - One Time Extension to the High Pressure Core Spray Completion Time and Associated Surveillances," dated December 6, 2018
- 2. Electronic mail from M. Marshall (Senior Project Manager, U.S. Nuclear Regulatory Commission) to R. Reynolds (Exelon), Nine Mile Point, Unit 2-Request for Additional Information regarding Emergency Tech Spec Change RE HPCS Completion Time (L-2018-LLA-0491)," dated December 7, 2018 By letter dated December 6, 2018, (Reference 1) Exelon Generation Company, LLC (Exelon) requested a one-time change to the Nine Mile Point Unit 2 (NMP2) Technical Specifications (TS) under an emergency basis in accordance with 10 CFR 50.91(a)(5) . The proposed amendment request would apply a one time change to the Completion Time for TS 3.5.1, required Action B.2 from 14 days to 35 days.
By electronic mail dated December 7, 2018 (Reference 2), the NRC identified areas where additional information was necessary to complete the review.
Attachment 1 to this letter contains the NRC's request for additional information immediately followed by Exelon's response. Attachment 2 contains supplemental information for clarification to portions of Reference 1. Attachment 3 contains the proprietary version of GE Report 005N0847-P, Revision 1, with corresponding affidavit as supplemental information.
Attachment 3 transmitted herewith contains Proprietary Information.
When separated from Attachment 3, this document is decontrolled.
U.S. Nuclear Regulatory Commission Response to Request for Additional Information to Emergency LAR for One Time Extension to HPCS DG Completion Time and Associated Surveillances Docket No. 50-41 O December 7, 2018 Page2 contains the Non-Proprietary version of GE Hitachi Nuclear Energy Report 005N0847-NP, Revision 1. Attachment 5 contains a revised complete set of marked up TS pages. Attachment 6 contains a revised complete set of clean TS pages.
Exelon has reviewed the information supporting a finding of no significant hazards consideration and the environmental consideration provided to the NRC in Reference 1. The supplemental information attached to this letter does not affect the bases for concluding that the proposed license amendment does not involve a significant hazards consideration. Furthermore. the supplemental information attached to this letter does not affect the bases for concluding that neither an environmental impact statement nor an environmental assessment needs to be prepared in connection with the proposed amendment.
There are no commitments contained in this response.
If you should have any questions regarding this submittal, please contact Ron Reynolds at 610-765-5247.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 7th day of December 2018.
James Barstow Director - Licensing & Regulatory Affairs Exelon Generation Company, LLC Attachment 1: Response to Request for Additional Information Attachment 2: Supplemental Information Attachment 3: GE Hitachi Nuclear Energy Report 005N0847-P, Revision 1 (Proprietary Information)
Attachment 4: GE Hitachi Nuclear Energy Report 005N0847-NP, Revision 1 (Non-Proprietary Information)
Attachment 5: Revised Markup of Proposed Technical Specification Pages Attachment 6: Revised Technical Specification Clean Pages cc: USNRC Region I Regional Administrator w/attachments (excluding Attachment 3)
II USN RC Senior Resident Inspector - NMP II USNRC Project Manager, NRR - NMP II A. L. Peterson, NYSERDA
U.S. Nuclear Regulatory Commission Response to Request for Additional Information to Emergency LAR for One Time Extension to HPCS DG Completion Time and Associated Surveillances Docket No. 50-410 December 7, 2018 Page3 bee: Senior Vice President - Mid-Atlantic Operations w/o attachments Site Vice President- NMP Vice President, Licensing and Regulatory Affairs Plant Manager - NMP Director, Operations - NMP Director, Site Engineering - NMP Director, Site Training - NMP Manager, Regulatory Assurance - NMP w/ attachments II Manager, Licensing, KSA II Manager, Fuels, KSA II R. Reynolds, KSA II Commitment Coordinator - KSA II Correspondence Control Desk - KSA
ATTACHMENT 1 Nine Mile Point Nuclear Station, Unit 2 Renewed Facility Operating License No. NFP-69 NRC Docket No. 50-410 Response to Request for Additional Information
Response to Request for Additional Information Attachment 1 Emergency Tech Spec Change RE HPCS Completion Time Page 1of5 Docket No. 50-410
RAI 1
In accordance with 10 CFR 50.90, licensees must fully describe proposed changes in license amendment request. In the third paragraph of page two of the letter dated December 6, 2018, Exelon indicates that the proposed change to the completion time for an inoperable high pressure core spray system would be a one-time extension. However, neither the amendment request nor the footnote on technical specification (TS) mark-up page 3.5.1-1 explicitly indicate that the revised completion time is a one-time change and could be mistakenly interrupted as a permanent - not a one-time change. Clarify whether the amendment request is for a one-time extension and describe any necessary changes to the footnote.
Exelon Response to RAI 1:
This amendment request is for a one-time extension of the affected Completion Time. The referenced footnote to LCO 3.5.1 is revised as follows:
"* A one-time change to this Completion Time from 14 days to 35 days due to the HPCS DG replacement has been approved via Emergency LAR. This Completion Time expires on 12/31/2018 at 0100."
RAl2:
In accordance with 10 CFR 50.90, licensees must fully describe proposed changes in license amendment request. On pages 11 and 12 of the license amendment request, Exelon list the surveillance requirements (SRs) that may be delayed until January 11 or 18, 2019 to support replacement of the HPCS DG. The frequencies for these SRs are controlled by the Surveillance Frequency Control Program (SFCP) at Nine Mile Point 2. Because the frequencies of these SRs are controlled by the SFCP, the current surveillance interval is not included in Nine Mile Point Technical Specifications, so the magnitude of the proposed delay for each SR is unclear.
For each of the SRs listed on page 11 and 12, provide:
- a. The current surveillance frequency.
- b. The date that the surveillance is scheduled to be completed during the replacement of the HPCS DG, including the 25 percent grace permitted by Nine Mile Point 2 TS.
Exelon Response to RAI 2:
The magnitude of the change to each Surveillance Requirement is summarized in the following table:
NOTE: The following surveillances will be completed as soon as practicable within the divisional week following return of the HPCS System to OPERABLE but no later than the dates committed to below.
Response to Request for Additional Information Attachment 1 Emergency Tech Spec Change RE HPCS Completion Time Page 2 of 5 Docket No. 50-41 O Surveillance Requirements Surveillance Current 125% Complete Maximum Procedure Frequency Scheduled Grace No Later Days Date Date than: Past LED (LED)
N2-0SP-EGS-M@001 (Division I)
- SR 3.8.1.2 - Diesel Voltage and Frequency (Standby Start)
- SR 3.8.1.13 - Diesel 31 Days 12/13/18 12/20/18 1/18/19 29 Days Voltage and Frequency (Hot Restart)
- SR 3.8.3.5 - Fuel Oil Storage Tank Water Accumulation N2-0SP-EGS-M@001 (Division 11)
- (Same SRs as Division 31 Days 12/4/18 12/11/18 1/18/19 38 Days I)
CY-NM-210-500 (Division I)
- SR 3.8.3.3 - Diesel Fuel 31 Days 12/13/18 12/20/18 1/18/19 29 Days Oil Prooerties N2-ESP-ENS-Q731
CHANNEL FUNCTIONAL TEST for TS 3.3.5.1-.1 Functions 92 Days 11/29/18 12/21/18 1/11/19 21 Days 2.e, 2.f, 2.g, and 2.h.
CHANNEL CALIBRATION TS
Response to Request for Additional Information Attachment 1 Emergency Tech Spec Change RE HPCS Completion Time Page 3 of 5 Docket No. 50-410 Surveillance Requirements Surveillance Current 125% Complete Maximum Procedure Frequency Scheduled Grace No Later Days Date Date than: Past LED (LED) 3.3.5.1-.1 Functions 2.e, 2.f, 2.g, and 2.h.
- SR 3.8.1.16 - Automatic Load Timer Relays for Division 2 Diesel N2-0SP-CSL-M001
- SR 3.5.1 .1 - LPCS Gas Accumulation 31 Days 12/20/18 12/27/18 1/11/19 15 Days Monitoring N2-0SP-ICS-M001
- SR 3.5.3.1 - RCIC Gas Accumulation 31 Days 12/7/18 12/14/18 1/11/19 28 Days Monitoring
RAI 3
The requirements in 10 CFR 50.36(c)(2)(i) "Limiting conditions for operation" states, in part, that limiting conditions for operation are the lowest functional capability or performance levels of equipment required for safe operation of the facility. When a limiting condition for operation is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the technical specifications until the condition can be met. Each remedial (or required) action has a completion time associated with it. Exelon is proposing to extend the completion time for an inoperable HPCS DG from 14 days to 35 days, which is a 21 day extension. Additional details concerning the HPSC DG is needed to determine whether the requested extension is appropriate. Provide timeline major activities (e.g., arrival of replacement, installation of replacement, testing or replacement) to be completed as part of the HPCS DG replacement and justify that the additional time is appropriate.
Exelon Response to RAI 3:
The replacement of the diesel engine for the HPCS system involves the following major activities, with estimated completion dates.
- Arrival of the new diesel engine on site by December 8, 2018.
- Removal of the damaged diesel engine by December 10, 2018.
Response to Request for Additional Information Attachment 1 Emergency Tech Spec Change RE HPCS Completion Time Page 4 of 5 Docket No. 50-41 O
- Placement of the new diesel engine into the HPCS Diesel room by December 12, 2018
- Assembly and reconnection of support systems to the new diesel engine by December 18, 2018.
- Preparations to support running the new diesel engine for the first time complete by December 24, 2018.
- Testing of the new diesel engine and performance of surveillances to restore the HPCS system to Operable by December 29, 2018.
- This requested completion date and time includes approximately two (2) days of margin from the end of the scheduled activities to allow for contingencies not otherwise accounted for in the current schedule.
RAl4:
The requirements in 10 CFR 50.36(c)(3), "Surveillance requirements," state in part that calibration are necessary to ensure quality of components and that facility operation will be within safety limits and limiting conditions of operation met. It is unclear if Functions 2.e, 2.f, 2.g, and 2.h, which are part of SR 3.3.5.1.5 - Channel Calibration, will drift out of calibration during the proposed extension.
- a. Please provide the time period used for determining total drift in the uncertainty calculation associated with the allowable value for each function.
- b. Please provide the total accumulated time from the last calibration until the end of the proposed calibration interval for each function.
- c. Please provide a brief description of the available margin in the uncertainty calculation, and the amount used to address the additional time in the proposed surveillance interval extension.
Exelon Response to RAI 4:
- a. The time period for determining total drift is 24 months based on data collected.
- b. The total time accumulated from the last calibration to the end of the proposed calibration interval is 134 days.
- c. Over the proposed timeframe, the relays are not expected to drift; therefore, there is no challenge to the available margin to the TS limits.
Extension of the SR 3.3.5.1.5, performed per N2-ESP-ENS-Q731 on a quarterly basis, for Division 2 ECCS systems will result in minimal drift of the associated timing relays. Based on data collected from past performances and calculations associated with relay drift conclude that for the A GASTAT Model 7000 and AGASTAT Model 7012 relays used in this application there is no measurable drift up to approximately 746 days (e.g. drift is time independent). Predicted drift values were further estimated out to a range of 900 days, with no significant drift expected (values again indicating no time dependency).
Currently N2-ESP-ENS-Q731 is performed on a quarterly basis, more frequently than specifically necessary per supporting analysis. Results from the past 24 months of performances were reviewed by NMP2 for additional confidence that empirical data supports calculation results. Results from the past 24 months of performance are consistent with calculation conclusions. The below table summarizes the findings:
Response to Request for Additional Information Attachment 1 Emergency Tech Spec Change RE HPCS Completion Time Page 5 of 5 Docket No. 50-410 All Times in Seconds Date of LOOP RHR LOOP RHR LOOP+LOCA LOOP+LOCA Performance B c RHR B RHRC 12/8/2016 4.339 8.883 0.897 5.418 3/10/2017 4.35 8.98 0.9 5.5 6/8/2017 4.308 8.9 0.916 5.413 8/31/2017 4.35 9.09 0.91 5.45 12/7/2017 4.3 8.82 0.9 5.41 3/8/2018 4.34 9.07 0.9 5.5 6/7/2018 4.29 8.9 0.91 5.39 8/30/2018 4.33 9.04 0.92 5.39 Nominal Band [4.1-5.0l [8.2-10] [0.85-0.971 [5.18-5.72]
Tech.Spec Limit (TS<=?) (TS<=12) (TS<=2) (TS<=6.75)
Least As-Found Margin to TS Limit 2.65 2.91 1.08 1.25 Note: Shaded cells indicate the as-found values with the least margin to TS Limits.
NMP2 requests relief from the performance of the aforementioned SR until January 11, 2019; this will be 21 days past the SR 125 percent late end date. As the last performance was completed on August 30, 2018, the total time between performances will be 134 days. Based upon review of calculated and measured past drift, NMP2 has high confidence that any additional relay drift during the requested extension period will be minimal and non-consequential to equipment performance. Further, based on empirical data collected, there is sufficient evidence to conclude that margin to the required Technical Specification limits will be maintained during the extended SR window.
ATTACHMENT 2 Nine Mile Point Nuclear Station, Unit 2 Renewed Facility Operating License No. NFP-69 NRG Docket No. 50-410 Supplemental Information
Supplemental Information Attachment 2 Emergency Tech Spec Change RE HPCS Completion Time Page 1of1 Docket No. 50-41 O In addition to the above mentioned RAls Exelon is supplementing this amendment as follows:
- 1. Due to the non-intrusive nature of their testing methodologies, the following Surveillance Requirements extension requests will be retracted:
- 2. The note explaining the extension of affected Technical Specification (TS) SR pages is revised for clarity as follows:
- Following return to OPERABILITY of the HPCS System, the past due Surveillances will be completed by January 11(18),2019.
- 3. The note on TS markup page 3.8.1-16 was revised to reflect a date of January 11, 2019, to coincide with the completion stated on page 11 of 15 in the submittal dated December 6, 2018.
- 4. A Compensatory Measure for the HPCS Out of Service window included verification of the OPERABILITY of the RCIC System. RCIC OPERABILITY will continue to be verified during the extended LCO window with the exception of SR 3.5.3.1 which is being suspended by this request.
ATTACHMENT 4 Nine Mile Point Nuclear Station, Unit 2 Renewed Facility Operating License No. NFP-69 NRC Docket No. 50-410 GE Hitachi Nuclear Energy Report 005N0847-NP (Non-Proprietary Information)
GE Hitachi Nuclear Energy 005N0847-NP Revision 1 December 2018 Non-Proprietary Information Supplemental NMP2 LOCA Evaluation for HPCSDGOOS Copyright 2018, GE-Hitachi Nuclear Energy Americas LLC All Rights Reserved
OOSN0847-NP Revision l Non-Proprietary Information INFORMATION NOTICE This is a non-proprietary version of the document OOSN0847-P Revision I, 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 (( )).
IMPORTANT NOTICE REGARDING CONTENTS OF THIS REPORT Please Read Carefully The design, engineering, and other information contained in this document are furnished in accordance with the contract between Exelon and GEH, and nothing contained in this document shall be construed as changing the contract. The use of this information by anyone other than Exelon, or for any purpose other than that for which it is furnished by GEH is not authorized; and with respect to any unauthorized use, GEH makes no representation or warranty, express or implied, 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.
II
005N0847-NP Revision 1 Non-Proprietary Information REVISION
SUMMARY
Revision Revision Summary 0 Initial release 1 Revised for submittal to the NRC Ill
005N0847-NP Revision l Non-Proprietary Information TABLE OF CONTENTS 1.0 Background and Purpose ....................................................................................................... l 2.0 Analysis Procedure ................................................................................................................ l 3.0 Inputs to the Analysis ............................................................................................................ l 4.0 Analysis Results and Conclusion .......................................................................................... 2 5.0 Reference ............................................................................................................................... 3 LIST OF TABLES Table l PCT Summary (°F) ...................................................................................................... 4 IV
005N0847-NP Revision l Non-Proprietary Information ACRONYMS Acronym Explanation ADS Automatic Depressurization System AOR Analysis of Record BWROG Boiling Water Reactor Owners' Group CFR Code of Federal Regulations CLTP Current Licensed Thermal Power DEG Double-Ended Guillotine DG Diesel Generator ECCS Emergency Core Cooling System GEH GE-Hitachi Nuclear Energy Americas LLC HPCS High Pressure Core Spray LHGR Linear Heat Generation Rate LOCA Loss-of-Coolant Accident LPCI Low Pressure Coolany Injection LPCS Low Pressure Core Spray MELLLA+ Maximum Extended Load Line Limit Analysis MLO Maximum Local Oxidation NIA Not Applicable NMP2 Nine Mile Point Unit 2 oos Out-of-Service PCT Peak Cladding Temperature v
005N0847-NP Revision l Non-Proprietary Information 1.0 Background and Purpose The Exelon Nine Mile Point Unit 2 (NMP2) plant experienced a Division III Diesel Generator (DG) (High Pressure Core Spray Diesel Generator (HPCS DG)) failure. An evaluation of the plant Loss-of-Coolant Accident (LOCA) response assuming the HPCS DG Out-of-Service (OOS) condition was performed and the results are presented in this report.
2.0 Analysis Procedure The analysis procedure used in this report is the same as that described in the NMP2 GNF2 Emergency Core Cooling System (ECCS)-LOCA evaluation in Section 3.0 of Reference 1. The LOCA evaluation methodology is the SAFER/PRIME methodology described in the same report.
Two 10 Code of Federal Regulations (CFR) 50.46 Notification Letters, 2017-01 and 2017-02, apply to the Reference 1 analysis. Because both notifications have a zero degree effect on the Peak Cladding Temperature (PCT), they are not explicitly modeled in this analysis. Therefore, these two notifications are applied consistently to the analysis in this report and in the Reference 1 GNF2 analysis.
3.0 Inputs to the Analysis The inputs to the analysis in this report are described in the NMP2 GNF2 ECCS-LOCA evaluation in Section 4.0 of Reference 1.
As documented in the LOCA Analysis of Record (AOR), Reference 1, and as summarized in Table 1, the limiting LOCA scenario for NMP2 is the recirculation suction line small break with a Division III DG (HPCS DG) single failure for both nominal and Appendix K conditions. Even though the limiting scenario is the small break of the recirculation suction line, the HPCS DG OOS condition is expected to affect both small and large break results. Therefore, this supplemental analysis addresses both small and large break limiting scenarios. The following two limiting scenarios are evaluated in this report:
(1) Large Break (Case: Double-Ended Guillotine (DEG), Current Licensed Thermal Power (CLTP) I Maximum Extended Load Line Limit Analysis Plus (MELLLA +) Flow, Mid-Peak from Table 3 in Reference l ). Both nominal and Appendix K conditions were analyzed.
(2) Small Break (Case: 0.07ft 2, CLTP I Rated Flow, Top-Peak, 6 Automatic Depressurization System (ADS) in Table 4 of Reference 1). Both nominal and Appendix K conditions were analyzed. In addition, ((
))
The NMP2 design has three DGs: Division I (Low Pressure Core Spray (LPCS) DG), Division II (Low Pressure Coolant Injection (LPCI) DG), and Division III (HPCS DG). [n this supplemental LOCA evaluation, failure of the LPCS DG or the LPCI DG is also considered in addition to the unavailability of the HPCS DG. Based on the plant ECCS network, the following failures are assumed in this evaluation:
(1) Failure I: Concurrent failure of both the HPCS DG and LPCI DG, which leaves only the LPCS DG available. For this failure, one (I) LPCI system and one (1) LPCS system are
005N0847-NP Revision l Non-Proprietary Information available for the ECCS LOCA analysis. Six ADS valves are used in the analysis, which is the same as those used in the Reference l analysis.
(2) Failure 2: Concurrent failure of both the HPCS DG and LPCS DG, which leaves only the LPCI DG available. For this failure, two (2) LPCI systems are available for the ECCS LOCA analysis. Six ADS valves are used in the analysis, which is the same as those used in the Reference l analysis.
4.0 Analysis Results and Conclusion The PCT results for the cases defined in Section 3.0 above are summarized in Table 1. The sensitivity results shown in Table l demonstrate that:
( l) The small break remains the limiting break.
(2) The limiting failure is the concurrent failure of both the HPCS DG and the LPCS DG.
(3) Based on the nominal results presented in Table l, the NMP2 design has significant built-in margin (more than (( ))) to the l 0 CFR 50.46 acceptance criteria even after considering multiple concurrent failures in the ECCS network.
(4) The Appendix K results presented in Table l confirm that there is still significant margin (more than (( ))) available to the 10 CFR 50.46 acceptance criteria, even after considering the licensing basis Appendix K requirements. The Appendix K PCT is less than (( )) for the most limiting small break. ((
)) and the licensing basis PCT
( l ,690°F). Considering the significant Appendix K PCT margin to 2,200°F, the corresponding licensing basis PCT for the current limiting break will still be less than the 10 CFR 50.46 PCT limit of2,200°F.
- a. Table 1 results show that the small recirculation suction line break is still the most limiting scenario. Therefore, a limited scope break spectrum was performed for small recirculation lines to identify the most limiting small break size.
(5) The Maximum Local Oxidation (MLO) is less than the 10 CFR 50.46 limit of 17%.
- a. MLO is less than l % for nominal results.
- b. MLO is less than 4% for Appendix K results.
(6) The core wide oxidation is less than 0.1 % for both nominal and Appendix K results, which is less than the 10 CFR 50.46 limit of 1%.
(7) The results confirm that there is no change to the compliance of the coolable geometry requirement documented in Reference 1.
(8) The NMP2 compliance with the core long-term cooling requirement remains satisfied.
This is satisfied for the worst case scenario (with no spray available), which has enough injection capacity (with two LPCI pumps) to flood the core bypass region. For this scenario, the calculated spill over from the bypass region is more than the Boiling Water Reactor Owners' Group (BWROG) requirement of minimum 1.5 gpm of liquid flow to 2
005N0847-NP Revision l Non-Proprietary Information every bundle (Reference 2). Furthermore, analysis performed in the supplemental LOCA evaluation showed that the subsequent core heatup for the long-term evaluation has a PCT significantly less than the 10 CFR 50.46 limit of 2,200°F, satisfying the long-term core cooling requirement.
(9) Results presented in this supplemental analysis are for GNF2 fuel only. However, these results also bound the LOCA response for the co-resident fuel type, GEl4, because
- a. The GNF2 Linear Heat Generation Rate (LHGR) is 1 KW /ft higher than that of GE 14.
- b. The GE 14 ECCS LOCA analysis results in Reference 3 are lower than those of GNF2 fuel.
5.0 References I. GE Hitachi Nuclear Energy, "Nine Mile Point Unit 2 GNF2 ECCS-LOCA Evaluation,"
002N4205-RO, December 2015.
- 2. OG00-0382-01, "GE Position Summary Regarding Long-Term Post-LOCA Adequate Core Cooling Requirements," November 16, 2000.
- 3. GE Hitachi Nuclear Energy, "Safety Analysis Report for Nine Mile Point Unit 2 Maximum Extended Load Line Limit Analysis Plus," NEDC-33576P, Revision 0, October 2013.
3
005N0847-NP Revision I Non-Proprietary Information Table I PCT Summary (°F)
((
))
Notes:
I. (( ))
- 2. (( ))
4
ATTACHMENT 5 Nine Mile Point Nuclear Station, Unit 2 Renewed Facility Operating License No. NFP-69 NRC Docket No. 50-410 Revised Markup of Proposed Technical Specifications Pages (These markups replace the TS markups is Reference 1 in their entirety)
TS LCO Pages 3.5.1-1 TS SR Pages:
3.3.5.1-8 3.5.1-4 3.5.3-2 3.8.1-6 3.8.1-7 3.8.1-14 3.8.1-16 3.8.3-3
ECCS - Operating 3.5.1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS), RPVWATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.1 ECCS - Operating LCO 3.5.1 Each ECCS injection/spray subsystem and the Automatic Depressurization System (ADS) function of six safety/relief valves shall be OPERABLE.
APPLICABILITY: MODE 1, MODES 2 and 3, except ADS valves are not required to be OPERABLE with reactor steam dome pressure ::::; 150 psig.
ACTIONS
~---------------------------------NOTE-------------------------------------------------------
LCO 3.0.4.b is not applicable to HPCS.
CONDITION REQUIRED ACTION COMPLETION TIME A. One low pressure ECCS A.1 Restore low pressure 7 days injection/spray ECCS injection/spray subsystem inoperable. subsystem to OPERABLE status.
B. High Pressure Core B.1 Verify by Immediately Spray (HPCS) System administrative means inoperable. RCIC System is OPERABLE when RCIC is required to be OPERABLE.
AND B.2 Restore HPCS System to OPERABLE status.
14days~
(continued)
" A one-time change to this Completion Time from 14 days to 35 days due to the HPCS DG replacement has been approved via Emergency LAR. This Completion Time expires on 12/31/2018 at 0100.
NMP2 3.5.1-1 Amendment 91, 109, 168
ECCS Instrumentation 3.3.5.1 SURVEILLANCE REQUIREMENTS
NOTES ------------------------------------------------
- 1. Refer to Table 3.3.5.1-1 to determine which SRs apply for each ECCS Function.
- 2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated Function or the redundant Function maintains ECCS initiation capability.
SURVEILLANCE FREQUENCY SR 3.3.5.1.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.5.1.2 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control
) Program~
SR 3.3.5.1.3 Calibrate the trip unit. In accordance with the Surveillance Frequency Control Program SR 3.3.5.1.4 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.5.1.5 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program~
SR 3.3.5.1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Proqram .Yl_
) ,.,,,.:-----1* Following return to OPERABILITY of the HPCS
' System, the past due Surveillances will be completed by January 11, 2019.
NMP2 3.3.5.1-8 Amendment 91, 152, 168
ECCS - Operating 3.5.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify, for each ECCS injection/spray In accordance with subsystem, locations susceptible to the Surveillance gas accumulation are sufficiently filled Frequency Control with water. Program~
SR 3.5.1.2 ----~-~---~--------NOTE----------------------------
Not required to be met for system vent paths opened under administrative control.
Verify each ECCS injection/spray subsystem In accordance with manual, power operated, and automatic valve the Surveillance in the flow path, that is not locked, Frequency Control sealed, or otherwise secured in position, Program is in the correct position.
SR 3.5.1.3 Verify: In accordance with the Surveillance
- a. For each ADS nitrogen receiver discharge Frequency Control header, the pressure is !:: 160 psig; and Program
- b. For each ADS nitrogen receiver tank, the pressure is ~ 334 psig.
(continued)
- Following return to OPERABILITY of the HPCS System, the past due Surveillances will be completed by January 11, 2019.
NMP2 3.5.1-4 Amendment 91, 150,152, 170
RCIC System 3.5.3
) SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.1 Verify the RCIC System locations susceptible to In accordance with gas accumulations are sufficiently filled with water. the Surveillance Frequency Control Program~
SR 3.5.3.2 -----------------------NOTE ----------------------------
Not required to be met for system vent flow paths opened under administrative control.
Verify each RCIC System manual, power In accordance with operated, and automatic valve in the flow the Surveillance path, that is not locked, sealed, or Frequency Control otherwise secured in position, is in the Program correct position.
SR 3.5.3.3 --------------------------- NOTE ----------------------------
Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
) after reactor steam pressure and flow are adequate to perform the test.
Verify, with reactor pressure :s 1035 psig In accordance with and ;:.; 935 psig, the RCIC pump can develop a the Surveillance flow rate =:: 600 gpm against a system head Frequency Control corresponding to reactor pressure. Program SR 3.5.3.4 -------------------------- NOTE ---------------------------
Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.
Verify, with reactor pressures 165 psig, In accordance with lhe RCIC pump can develop a flow rate the Surveillance
~ 600 gpm against a system head Frequency Control corresponding to reactor pressure. Program (continued)
) *Following return to OPERABILITY of the HPCS System, the past due Surveillances will be completed by January 11, 2019.
NMP2 3.5.3-2 Amendment Q1, 150, 152
AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3.8.1.2 ---------------------*-------- NOTE----------------------------
All DG starts may be preceded by an engine prelube period and followed by a warmup period prior to loading.
Verify each required DG starts from standby conditions and achieves:
- a. In ~ 1 O seconds, voltage ~ 3950 V for In accordance with Division 1 and 2 DGs and 2'. 3820 V for the Surveillance Division 3 DG, and frequency 2'. 58.8 Hz Frequency Control for Division 1 and 2 DGs and~ 58.0 Hz Program~
for Division 3 DG; and
- b. Steady state voltage ~ 3950 V and
~ 4370 V and frequency ~ 58.8 Hz and
~61.2Hz.
)
(continued)
~
\_System, the past due Surveillances will be completed by January 18, 2019.
)
NMP2 3.B.1-6 Amendment fµ, 152
AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.8.1.3 ----------------------------- NOTES----------------------------
- 1. DG loadings may include gradual loading as recommended by the manufacturer.
- 2. Momentary transients outside the load range do not invalidate this test.
- 3. This Surveillance shall be conducted on only one OG at a time.
- 4. This SA shall be preceded by, and immediately follow, without shutdown, a successful performance of SR 3.8.1.2.
Verity each required DG is synchronized and In accordance with loaded and operates for 2: 60 minutes at a the Surveillance
) load 2: 3960 kW and :::; 4400 kW for Division 1 and 2 DGs, and ~ 2340 kW and ::::; 2600 kW for Frequency Control Program~
Division 3 DG.
SR 3.8.1.4 Verify each required day tank contains In accordance with
~ 403 gal of fuel oil tor Division 1 and 2 the Surveillance DGs and~ 282 gal for Division 3 DG. Frequency Control Program~
SR 3.8.1.5 Check for and remove accumulated water from In accordance with each required day tank. the Surveillance Frequency Control Program~
SR 3.8.1.6 Verify each required fuel oil transfer In accordance with subsystem operates to automatically the Surveillance transfer fuel oil from the storage tank to Frequency Control the day tank. Program~
~ *Following return to OPERABILITY of the HPCS (continued)
) \__System, the past due Surveillances will be completed by January 18, 2019.
NMP2 3.8.1-7 Amendment 9+, 152
AC Sources - Operating 3.8.1
) SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SA 3.8.1.13 --------------------------- NOTES---------------------------
- 1. This Surveillance shall be performed within 5 minutes of shutting down the DG after the DG has operated ~ 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> loaded ~ 3960 kW for Division 1 and 2 DGs, and ~ 2340 kW for Division 3 DG.
Momentary transients below the load limit do not invalidate this test.
- 2. All OG starts may be preceded by an engine prelube period.
Verify each required DG starts and In accordance with achieves: the Surveillance Frequency Control
- a. In ~ 1O seconds, voltage ;;::: 3950 V for Program "--EJ Division 1 and 2 OGs and ;;::: 3820 V for
) Division 3 OG, and frequency ~ 58.8 Hz for Division 1 and 2 DGs and ~ 58.0 Hz tor Division 3 DG; and
- b. Steady state voltage ~ 3950 V and
~ 4370 V and frequency ~ 58.8 Hz and ~ 61.2 Hz.
(continued)
~ *Following return to OPERABILITY of the HPCS
\_System, the past due Surveillances will be completed by January 18, 2019.
)
NMP2 3.8.1-14 Amendment B+, 152
AC Sources -Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.8.1.16 ---------------------------- NOTE ------------------------
Th is Surveillance shall not normally be performed in MODE 1, 2, or 3. However, this Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced.
Credit may be taken for unplanned events that satisfy this SR.
Verify interval between each sequenced load In accordance with block, for the Division 1 and 2 DGs only, the Surveillance is 2!: 90% of the design interval for each Frequency Control automatic load sequence time delay relay. Program "--EJ
~
. \_System, the past due Surveillances will be completed (continued) by January 11, 2019.
)
NMP2 3.8.1-16 Amendment 91, 152, 165
Diesel Fuel Oil, Lube Oil, and Starting Air 3.8.3
') SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SA 3.8.3.1 Verify each fuel oil storage tank contains: In accordance with the Surveillance
- a. ~ 50,000 gal of fuel for Division 1 DG Frequency Control and Division 2 DG; and Program~
- b. ~ 35,342 gal of fuel for Division 3DG.
SA 3.8.3.2 Verify lube oil inventory is: In accordance with the Surveillance
- a. ;::, 99 gal for Division 1 DG and Frequency Control Division 2 DG; and Program
- b. ;::, 168 gal for Division 3 DG.
SR 3.8.3.3 Verify fuel oil properties of new and In accordance stored fuel oil are tested in accordance with the Diesel r{J
) with, and maintained within the limits of, Fuel Oil ~
the Diesel Fuel Oil Testing Program. Testing Program SR 3.8.3.4 Verify each DG air start receiver pressure In accordance with IS: the Surveillance Frequency Control
- a. 2:: 225 psig for Division 1 DG and Program Division 2 DG; and
- b. ~ 190 psig for Division 3 DG.
SR 3.8.3.5 Check for and remove accumulated water from In accordance with each fuel oil storage tank. the Surveillance Frequency Control Program ~
- Following return to OPERABILITY of the HPCS System, the past due Surveillances will be completed by January 18, 2019.
)
NMP2 3.8.3-3 Amendment 9+, 152
ATTACHMENT 6 Nine Mile Point Nuclear Station, Unit 2 Renewed Facility Operating License No. NFP-69 NRC Docket No. 50-410 Revised Technical Specification Clean Pages TS LCO Pages 3.5.1-1 TS SR Pages:
3.3.5.1-8 3.5.1-4 3.5.3-2 3.8.1-6 3.8.1-7 3.8.1-14 3.8.1-16 3.8.3-3
ECCS - Operating 3.5.1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS), RPV WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.1 ECCS - Operating LCO 3.5.1 Each ECCS injection/spray subsystem and the Automatic Depressurization System (ADS) function of six safety/relief valves shall be OPERABLE.
APPLICABILITY: MODE 1, MODES 2 and 3, except ADS valves are not required to be OPERABLE with reactor steam dome pressure ::;; 150 psig.
ACTIONS
--~~-------~~-~-~-~------~~-~----~-------~~----~NOTE-~-----~--~---~~-~------~--~-------~---~--~---~----~-
LCO 3.0.4.b is not applicable to HPCS.
CONDITION REQUIRED ACTION COMPLETION TIME A. One low pressure ECCS A.1 Restore low pressure 7 days injection/spray ECCS injection/spray subsystem inoperable. subsystem to OPERABLE status.
B. High Pressure Core B.1 Verify by administrative Immediately Spray (HPCS) System means RCIC System is inoperable. OPERABLE when RCIC is required to be OPERABLE.
AND B.2 Restore HPCS System 14 days*
to OPERABLE status.
(continued)
- A one-time change to this Completion Time from 14 days to 35 days due to the HPCS DG replacement has been approved via Emergency LAR. This Completion Time expires on 12/31/2018 at 0100.
NMP2 3.5.1-1 Amendment Q1, 1OQ, 198,
ECCS Instrumentation 3.3.5.1 SURVEILLANCE REQUIREMENTS
N0 TES-----------------------------------------------------------
- 1. Refer to Table 3.3.5.1-1 to determine which SRs apply for each ECCS Function.
- 2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated Function or the redundant Function maintains ECCS initiation capability.
SURVEILLANCE FREQUENCY SR 3.3.5.1.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.5.1.2 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program*
SR 3.3.5.1.3 Calibrate the trip unit. In accordance with the Surveillance Frequency Control Program SR 3.3.5.1.4 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.5.1.5 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program*
SR 3.3.5.1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Proo ram*
'Following return to OPERABILITY of the HPCS System, the past due Surveillances will be completed by January 11, 2019.
NMP2 3.3.5.1-8 AmendmentQ1, 152, 168,
ECCS - Operating 3.5.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify, for each ECCS injection/spray In accordance with subsystem, locations susceptible to the Surveillance gas accumulation are sufficiently filled Frequency Control with water. Program*
SR 3.5.1.2 --------------NOTE--------------
Not required to be met for system vent paths opened under administrative control.
Verify each ECCS injection/spray subsystem In accordance with manual, power operated, and automatic valve the Surveillance in the flow path, that is not locked, Frequency Control sealed, or otherwise secured in position, Program is in the correct position.
SR 3.5.1.3 Verify: In accordance with the Surveillance
- a. For each ADS nitrogen receiver discharge Frequency Control header, the pressure is~ 160 psig; and Program
- b. For each ADS nitrogen receiver tank, the pressure is ~ 334 psig.
(continued)
- Following return to OPERABILITY of the HPCS System, the past due Surveillances will be completed by January 11, 2019.
NMP2 3.5.1-4 Amendment Q1, 150, 152, 170
RCIC System 3.5.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.1 Verify the RCIC System locations susceptible to In accordance with gas accumulations are sufficiently filled with water. the Surveillance Frequency Control Program*
SR 3.5.3.2 -------------------------NO TE ------------------------------
Not required to be met for system vent flow paths opened under administrative control.
Verify each RCIC System manual, power In accordance with operated, and automatic valve in the flow the Surveillance path, that is not locked, sealed, or Frequency Control otherwise secured in position, is in the Program correct position.
SR 3.5.3.3 -------------------------N 0 TE ----------------------------
Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.
Verify, with reactor pressure s 1035 psig In accordance with and ;:: 935 psig, the RCIC pump can develop a the Surveillance flow rate ;:: 600 gpm against a system head Frequency Control corresponding to reactor pressure. Program SR 3.5.3.4 -------------------------NO TE ----------------------------
Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.
Verify, with reactor pressure s 165 psig, In accordance with the RCIC pump can develop a flow rate the Surveillance
- 600 gpm against a system head Frequency Control corresponding to reactor pressure. Program (continued)
- Following return to OPERABILTY of the HPCS System, the past due Surveillances will be completed by January 11, 2019.
NMP2 3.5.3-2 Amendment Q1, 150, 152,
AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3.8.1.2 --------------------------NOTE --------------------------
All DG starts may be preceded by an engine prelube period and followed by a warmup period prior to loading.
Verify each required DG starts from standby conditions and achieves:
- a. In $ 1O seconds, voltage ~ 3950 V for In accordance with Division 1 and 2 DGs and ~ 3820 V for the Surveillance Division 3 DG, and frequency~ 58.8 Hz Frequency Control for Division 1 and 2 DGs and ~ 58.0 Hz Program*
for Division 3 DG; and
- b. Steady state voltage ~ 3950 V and
$ 4370 V and frequency ~ 58.8 Hz and
$61.2Hz.
continued
- Following return to OPERABILITY of the HPCS System, the past due Surveillances will be completed by January 18, 2019.
NMP2 3.8.1-6 Amendment 91, 152,
AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.8.1.3 ------------------------N 0 TES ------------------------
- 1. DG loadings may include gradual loading as recommended by the manufacturer.
- 2. Momentary transients outside the load range do not invalidate this test.
- 3. This Surveillance shall be conducted on only one DG at a time.
- 4. This SR shall be preceded by, and immediately follow, without shutdown, a successful performance of SR 3.8.1 .2.
Verify each required DG is synchronized and In accordance with loaded and operates for :::: 60 minutes at a the Surveillance load :::: 3960 kW and ~ 4400 kW for Division 1 Frequency Control and 2 DGs, and :::: 2340 kW and ~ 2600 kW for Program*
Division 3 DG.
SR 3.8.1.4 Verify each required day tank contains In accordance with
- 403 gal of fuel oil for Division 1 and 2 the Surveillance DGs and :::: 282 gal for Division 3 DG. Frequency Control Program*
SR 3.8.1.5 Check for and remove accumulated water from In accordance with each required day tank. the Surveillance Frequency Control Program*
SR 3.8.1.6 Verify each required fuel oil transfer In accordance with subsystem operates to automatically the Surveillance transfer fuel oil from the storage tank to Frequency Control the day tank. Program*
(continued)
- Following return to OPERABILITY of the HPCS System, the past due Surveillances will be completed by January 18, 2019.
NMP2 3.8.1-7 Amendment 91, 152,
AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3.8.1.13 -------------------------------NOTES ---------------------------
- 1. This Surveillance shall be performed within 5 minutes of shutting down the DG after the DG has operated ~ 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> loaded ~ 3960 kW for Division 1 and 2 DGs, and ~ 2340 kW for Division 3 DG.
Momentary transients below the load limit do not invalidate this test.
- 2. All DG starts may be preceded by an engine prelube period .
Verify each required DG starts and In accordance with achieves: the Surveillance Frequency Control
- a. In :::; 1O seconds, voltage ~ 3950 V for Program*
Division 1 and 2 DGs and ~ 3820 V for Division 3 DG, and frequency ~ 58.8 Hz for Division 1 and 2 DGs and~ 58.0 Hz for Division 3 DG; and
- b. Steady state voltage ~ 3950 V and
- 4370 V and frequency ~ 58.8 Hz and
- ::; 61.2 Hz.
continued
- Following return to OPERABILITY of the HPCS System, the past due Surveillances will be completed by January 18, 2019.
NMP2 3.8.1-14 Amendment Q1, 152,
AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3.8.1.16 ------------------------ N0 TE --------------------------
Th is Surveillance shall not normally be performed in MODE 1, 2, or 3. However, this Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced.
Credit may be taken for unplanned events that satisfy this SR.
Verify interval between each sequenced load In accordance with block, for the Division 1 and 2 DGs only, the Surveillance is ~ 90% of the design interval for each Frequency Control automatic load sequence time delay relay. Program*
continued
- Following return to OPERABILITY of the HPCS System, the past due Surveillances will be completed by January 11, 2019.
NMP2 3.8.1-16 Amendment Q1, 152, 165,
Diesel Fuel Oil, Lube Oil, and Starting Air 3.8.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.3.1 Verify each fuel oil storage tank contains: In accordance with the Surveillance
- a. ;::: 50,000 gal of fuel for Division 1 DG Frequency Control and Division 2 DG; and Program*
- b. ;::: 35,342 gal of fuel for Division 3 DG.
SR 3.8.3.2 Verify lube oil inventory is: In accordance with the Surveillance
- a. ;::: 99 gal for Division 1 DG and Frequency Control Division 2 DG; and Program
- b. ;::: 168 gal for Division 3 DG.
SR 3.8.3.3 Verify fuel oil properties of new and In accordance stored fuel oil are tested in accordance with the Diesel with, and maintained within the limits of, Fuel Oil the Diesel Fuel Oil Testing Program. Testing Program
- SR 3.8.3.4 Verify each DG air start receiver pressure In accordance with is: the Surveillance Frequency Control
- a. ;::: 225 psig for Division 1 DG and Program Division 2 DG; and
- b. ;::: 190 psig for Division 3 DG.
SR 3.8.3.5 Check for and remove accumulated water from In accordance with each fuel oil storage tank. the Surveillance Frequency Control Program ..
- Following return to OPERABILITY of HPCS System, the past due Surveillances will be completed by January 18, 2019.
NMP2 3.8.3-3 Amendment ~2.