ML17037B959
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| ML17037B959 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 04/06/1976 |
| From: | Babcock H LeBoeuf, Lamb, Leiby & MacRae |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| Download: ML17037B959 (4) | |
Similar Documents at Nine Mile Point | |
|---|---|
Category:Letter
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Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station IR 05000410/20243012023-12-14014 December 2023 Initial Operator Licensing Examination Report 05000410/2024301 ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 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 ML23291A4642023-12-0707 December 2023 Issuance of Amendment No. 251 Regarding the Adoption of Title 10 the Code of Federal Regulations Section 50.69, Risk-Informed Categorization and Treatment of SSC for Nuclear Power Plants ML23289A0122023-12-0606 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 - 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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 . RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023 Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor IR 05000220/20230022023-08-0101 August 2023 Integrated Inspection Report 05000220/2023002 and 05000410/2023002 ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 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 ML23186A1642023-07-0606 July 2023 Operator Licensing Retake Examination Approval 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 ML23192A0622023-06-30030 June 2023 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance, Report No. 10CFR21-0136, Rev. 0 IR 05000220/20230102023-06-29029 June 2023 Biennial Problem Identification and Resolution Inspection Report 05000220/2023010 and 05000410/2023010 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 RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations 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) ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling IR 05000410/20233022023-05-15015 May 2023 Initial Operator Licensing Examination Report 05000410/2023302 2024-02-01 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
[Table view]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. 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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. 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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 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
[Table view]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 |
Text
NRC FOAM 195);.. U.S. NUCLEAR REGULATORV COMMISSION DOCKET NUMBER FILE NUMBEA NRC DISTRIBUTION FoR rART 50 DOCKET MATERIAL TO: FROM: DATE OF DOCUMENT Mr Stolz LEBOEUF, LAMB,LE XBY&MACRAE 4-6-76 Washington, DC DATE RECEIVED H M Babcock 4 6 76 QLETTER Cl NO TO R I Z E D PROP INPUT FORM NUMBER OF COPIES RECEIVED ORIGINAL g3 UN C LASS I F I E 0 one signed OCOr V DESCRIPTION ENCLOSURE Ltr on behalf of Niagara. Mohawk Pwr Corp... "Design & Analysis Methods 'for. Revetment-Ditch re their 3-5-76 submittal:.; .. transmitting System...." dtd Feb 1976..'........;..........,
addi reques ted cys o f document 1 is ted on encl side of MC...... (25 addi cys rec'd)
ACKNOWLEDGEO, XIO NOT RL<'MOVEI Nine Mile Pt N2 SAFETY FOR ACTION/INFORMATION ENVIRO - - b e r ASSIGNED AD: ASSIGNED AD:
BRANCH CHIEF: BRANCH CHIEF ~
PROJECT OfANAGER: PROJECT IfANAGER:
LXC ~ ST.: LIC ~ ASST' INTERNAL DISTRIBUTION FILE f-4I-NRC PDR ERNST I&E BENAROYA ALLARD N SPANGLER GOSSICK & STAFF ~HN 1NEEE N IPPOLITO SITE TECH KNIGHT OPERATING REACTORS GA1 0"I ILL SIHI&XL STELLO STEPP PAWLICKX HULMAN OPERATXNG TECH PROJECT MANAGEMENT REACTOR SAFETY EISENHUT SITE ANALYSIS BOYD ROSS SHAO VOLLIfER P. COLLXNS NOVAK BAER BUNCH HOUSTON ROSZTOCZY SCHWENCER J, COLLINS PETERSON CHECK GRltfES KREGER MELTZ HELTEMES AT & I SITE SAFETY & FNV SKOVHOLT SALTZIfAN ANALYSIS RUTBERG DFNTON & MULLER EXTERNAL DISTRIBUTION CONTROL NUMBE LPD OS' A/ NATL LA BROOKHAVEN NATL LAB TIC REG, V"IE UI RI KSON (ORNL)
NS LA PDR ASLB COiIS ULTANTS SF NAC FOAM 195 (2 26)
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~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 4 ~ ~ ~ ~ ~ ~ ~ ~ ~ ll RE~ JLATORY OXI(ET RLE goPy LAW OFFICES OF LEBOEUF, LAMB, LEIBY 8c MAC RAE 1757 N STREET> N.W.
WASHINGTON) D. C. 20036 TELEPHONE 202 457 7500 CACLE ADDRESS LEON A AI LENa JR CAMCRON F. MAcRAC 4 LCSWIH, WASHINGTON D. C, RANDALL J. LCSDEUFs JR l929 l97d JOSCPH C. BACHCLDKR.IK CAMERON F. MAC RAC.TI2 4 CRN EST S. BALLARD.JR GCRARD A.MAHER TELEX: 440274 ADRIAN C.LKISY l952 l970
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O. 8 ~ PETER BERG CN 4 SHEILA H. MARSHALL DAVID P. DICKS JAMES O. McELROY TAYLOR A. BRIOGS JAMES P. McGRANERY, JR.'4 OF COUNSEL KEITH BROWN L. MANNINO MUNTEING 4 CHARLES N.BURGER HENRY V. NICKEL 4 ARVIN C. VPTON WILLIAM O, DOUB04 JAMCS O MALI CYo JR.4 JACOB FRIEDLANDER Ji MICHACL PARISH DONALD J OREENC
~ PAUL O. RUSSELL JAMES A ORCCRo32 4 HAROI.D M. SCIDCL I 40 BROADWAY JOHN L. GROSC 4 CHARLES P. SIFTON DOUGLAS W. HAWES CARL D. HOBELMAN MICHACI IOVENKO HALCYON G. SKINNER JOSCPH S.STRAUSS SAMUCL M.SUGDEN April 6, 1976 HEW YORK) N.Y. IDOOS TELEPHONE 212 289 HDO JAMES F. JOHNSON, 4TH CVOCNE B THOMAS'R 4 CABLE ADDRESS RONALD D.JONES LCONARD M. TROSTEN LEBWIHsNEW YORK LEX K. LARSON 4 HARAY H. VOIOT 4 ORANT S. LEWIS H. RICHARD WACHTCL TELEX: 4234IS GERAAD P. WATSON
~ RESIDENT PARTNERS WASHINGTON OFFICC 4 ADMITTED TO THE DISTRICT OF COLUMBIA BAR Director of Reactor Regulation Attention: Mr. J. F. Stolz Chief, Branch 2-1 6 ~
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22GUIATOIK OISl mNAISSOH yol84 8l U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Re: Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station Unit No. 2 Docket No. 50-410
Dear Sir:
On March 5, 1976, Niagara Mohawk Power Corporation transmitted to the Commission three copies of a report en-titled "Design and Analysis Methods For Revetment-Ditch System, Nine Mile Point Nuclear Station Unit 2, Niagara Mohawk Power Corporation" dated February 1976. This letter transmits an additional 25 copies of that report, in response to a verbal request from a member of the Regulatory Staff.
Very truly yours,'
ope M. abcock PHI
0 'P A ~
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