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Category:Letter
MONTHYEARML24268A3382024-10-16016 October 2024 Issuance of Amendment No. 253 Regarding the Modification of TS Surveillance Requirement 4.3.6.a Related to Adoption of TSTF-425, Revision 3 RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests NMP2L2890, Submittal of Revision 26 to the USAR and Reference Figures, 10 CFR 50.59 Evaluation Summary Report, TS Bases, TRM Requirements Manual Changes, and 10 CFR 54.37(b) Aging Management Review (Excludes Attachment 6)2024-10-0404 October 2024 Submittal of Revision 26 to the USAR and Reference Figures, 10 CFR 50.59 Evaluation Summary Report, TS Bases, TRM Requirements Manual Changes, and 10 CFR 54.37(b) Aging Management Review (Excludes Attachment 6) ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing IR 05000220/20243022024-10-0303 October 2024 Initial Operator Licensing Examination Report 05000220/2024302 ML24190A0012024-09-26026 September 2024 Issuance of Amendment Nos. 252 and 197 Regarding the Revision to Technical Specification Design Features Section to Remove Nine Mile Point Unit 3 Project Designation NMP1L3608, Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-09-20020 September 2024 Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation RS-24-090, Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-09-12012 September 2024 Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 IR 05000220/20240052024-08-29029 August 2024 Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2024005 and 05000410/2024005) IR 05000220/20240102024-08-22022 August 2024 Age-Related Degradation Inspection Report 05000220/2024010 and 05000410/2024010 NMP1L3603, Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan2024-08-20020 August 2024 Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000220/20240022024-08-0505 August 2024 Integrated Inspection Report 05000220/2024002 and 05000410/2024002 ML24215A3002024-08-0202 August 2024 Operator Licensing Examination Approval NMP1L3601, Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-07-31031 July 2024 Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation ML24213A1412024-07-31031 July 2024 Requalification Program Inspection NMP2L2883, Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations2024-07-24024 July 2024 Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations ML24198A0852024-07-16016 July 2024 Senior Reactor and Reactor Operator Initial License Examinations RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations NMP1L3584, License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2024-06-13013 June 2024 License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling IR 05000220/20244012024-05-30030 May 2024 Security Baseline Inspection Report 05000220/2024401 and 05000410/2024401(Cover Letter Only) ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 NMP1L3591, Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request2024-05-18018 May 2024 Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request NMP1L3589, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-05-16016 May 2024 Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable ML24158A2052024-05-15015 May 2024 Annual Radioactive Environmental Operating Report NMP1L3582, 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 22024-05-15015 May 2024 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 2 IR 05000220/20240012024-05-10010 May 2024 Integrated Inspection Report 05000220/2024001 and 05000410/2024001 RS-24-049, Updated Notice of Intent to Pursue Subsequent License Renewal Applications2024-05-0909 May 2024 Updated Notice of Intent to Pursue Subsequent License Renewal Applications RS-24-038, Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-05-0202 May 2024 Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds 05000410/LER-2024-001, Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum2024-05-0101 May 2024 Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests NMP1L3581, Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report2024-04-30030 April 2024 Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report NMP2L2877, 2023 Annual Environmental Operating Report2024-04-19019 April 2024 2023 Annual Environmental Operating Report NMP2L2878, Core Operating Limits Report2024-04-16016 April 2024 Core Operating Limits Report ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24092A3352024-04-0101 April 2024 NRC Office of Investigations Case No. 1-2023-002 ML24074A2812024-03-14014 March 2024 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000220/2024010 and 05000410/2024010 NMP1L3577, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-03-13013 March 2024 Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable IR 05000220/20230062024-02-28028 February 2024 Annual Assessment Letter for Nine Mile Point Nuclear Station, Units 1 and 2, (Reports 05000220/2023006 and 05000410/2023006) IR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 NMP1L3570, 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 05000410/LER-2023-001, Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater2024-01-30030 January 2024 Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024 CFR 50.46 Annual Report ML24004A2122024-01-0808 January 2024 Senior Reactor and Reactor Operator Initial License Examinations ML23354A0012024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0059 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) 05000220/LER-2023-002, Average Power Range Monitors Declared Inoperable Due to Trip of Reactor Recirculation Pump 122023-12-15015 December 2023 Average Power Range Monitors Declared Inoperable Due to Trip of Reactor Recirculation Pump 12 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 2024-09-04
[Table view] Category:Report
MONTHYEARNMP2L2883, Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations2024-07-24024 July 2024 Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations NMP1L3563, Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-12-0404 December 2023 Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) NMP1L3545, Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems .2023-08-0404 August 2023 Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems . NMP1L3515, Submittal of Emergency Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-03-27027 March 2023 Submittal of Emergency Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) NMP1L3469, Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits2022-06-30030 June 2022 Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits RS-21-001, Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping2021-01-0404 January 2021 Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping ML20303A1752020-10-23023 October 2020 Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting ML20190A1482020-07-0808 July 2020 FAQ 20-01 NMP Scram Final Approved ML20100F6822020-04-0909 April 2020 Submittal of Analytical Evaluation of Recirculation Discharge Nozzle-to-Safe End Weld Indication ML19228A0232019-08-15015 August 2019 Proposed Alternative to Utilize Code Case N-879 NMP2L2695, Supplement Information and Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of an Emergency License Amendment Request for One Time Extension to The.2018-12-0707 December 2018 Supplement Information and Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of an Emergency License Amendment Request for One Time Extension to The. NMP1L3229, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe ...2018-08-20020 August 2018 Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe ... ML18018B2922018-01-18018 January 2018 Appendix a, Justification for Continued Operation, Component Review Summary Sheet ML18018B2912018-01-18018 January 2018 Pipe Crack Task Force Report ML18018A9652018-01-18018 January 2018 Nine Mile Point, Unit 1 - Equipment Qualification Program and Tables I - Equipment Qualification Reports and Table Ii - TMI Action Plan ML18018B0122018-01-18018 January 2018 Semi-Annual Radioactive Effluent Release Report July-December 1999 ML17251A0452017-09-20020 September 2017 - Staff Assessment of Flooding Focused Evaluation (CACs No. MG0087 and MG0088) ML17109A3652017-04-13013 April 2017 Pressure and Temperature Limits Report ML17079A3842017-03-24024 March 2017 Summary of the U.S. Nuclear Regulatory Commission Staff'S Review of the Spring 2016 Steam Generator Tube Inservice Inspections ML17037A6862017-02-0606 February 2017 Table 7.2-1 ML17037A7032017-02-0606 February 2017 Table 7.2-1 (Cont'D) ML17027A0162017-01-27027 January 2017 10 CFR 50.46 Annual Report of the Emergency Core Cooling System Evaluation Model Changes and Errors RS-16-178, High Frequency Supplement to Seismic Hazard Screening Report2016-11-0202 November 2016 High Frequency Supplement to Seismic Hazard Screening Report ML16231A4522016-08-30030 August 2016 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Phase 2 of Order EA-13-109 (Severe Accident Capable Hardened Events) ML16223A8532016-08-25025 August 2016 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Phase 2 of Order EA-13-109 (Severe Accident Capable Hardened Vents) RS-16-091, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2016-06-14014 June 2016 Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) ML16160A0942016-06-0808 June 2016 ASP ANALYSIS- REJECT- Nine Mile Point Unit 1 Automatic Reactor Scram Due to Main Steam Isolation Valve Closure (LER 220-2015-004) ML15153A6602015-06-16016 June 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Re ML15028A1492015-02-11011 February 2015 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-13-109, Severe Accident Capable Hardened Vents RS-14-277, Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 12014-09-24024 September 2014 Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 ML15022A6612014-07-31031 July 2014 Stress Re-Evaluation of Nine Mile Point Unit 2 Steam Dryer at 115% CLTP, CDI Report No. 14-08NP, Revision 0, Non-proprietary Version ML14153A4102014-07-24024 July 2014 Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 ML14167A3492014-06-20020 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident (Tac. MF0249 & MF0250) ML15022A6622014-05-31031 May 2014 Acoustic and Low Frequency Hydrodynamic Loads at 115% CLTP Target Power Level on Nine Mile Point Unit 2 Steam Dryer to 250 Hz Using ACM Rev. 4.1R, C.D.I. Report No. 14-09NP, Revision 1, Non-proprietary Version ML15023A0312014-04-30030 April 2014 Computation of Cumulative Usage Factor for the 115% CLTP Power Level at Nine Mile Point Unit 2 with the Inboard RCIC Valve Closed, C.D.I. Technical Note No. 14-04NP, Revision 0, Non-proprietary Version ML14099A1962014-03-31031 March 2014 Constellation Energy Nuclear Group, LLC - Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task. ML14064A3242014-02-28028 February 2014 000N2495-R1-NP, Rev. 0, Nine Mile Point Nuclear Station Unit 2 Comparison of Mellla+ Reference Design to Cycle 15 Design Characteristics. ML14071A4782014-02-21021 February 2014 Response to Nrc'S Request for Cashflow Statements Regarding Application for Order Approving Transfer of Operating Authority and Conforming License Amendments ML14351A4272014-01-31031 January 2014 000N2528-SRLR, Revision 1, Supplemental Reload Licensing Report for Nine Mile Point 2 Reload 14 Cycle 15 Extended Power Uprate (3988 Mwt) / MELLLA (99-105% Flow). ML14064A3222014-01-31031 January 2014 00N0123-SRLR, Rev. 2, Supplemental Reload Licensing Report for Nine Mile Point 2 (NMP2) Reload 14 Cycle 15 Extended Power Uprate (Epu)/Maximum Extended Load Line Limit Plus (Mellla+). ML14024A4422014-01-0707 January 2014 Submittal of Report in Accordance with 10 CFR 26.719(c)(1) Regarding Unsatisfactory Blind Performance Sample Testing ML14064A3232013-12-31031 December 2013 000N0123-FBIR-NP, Rev. 0, Fuel Bundle Information Report for Nine Mile Point 2 Reload 14 Cycle 15. ML13225A5842013-12-19019 December 2013 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML13338A6632013-12-11011 December 2013 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Nine Mile Point, Unit 1, TAC No.: MF1129 ML13338A6642013-12-11011 December 2013 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Nine Mile Point, Unit 2, TAC No.: MF1130 ML13311A0542013-11-0404 November 2013 Pressure and Temperature Limits Report (PTLR) PTLR-2, Revision 0 (Draft B) ML13316B1102013-11-0101 November 2013 Attachment 9 - Global Nuclear Fuel Report GNF-0000-0156-7490-RO-NP, Gnf Additional Information Regarding the Requested Change to the Technical Specification SLMCPR, Dated August 26, 2013 (Non-proprietary) ML13311A0552013-09-30030 September 2013 Fluence Extrapolation in Support of NMP2 P-T Cure Update, MPM-913991, September 30, 2013, Attachment 3 ML13197A2222013-07-12012 July 2013 Supplemental Response to 10 CFR 50.54(f) Request for Information, Recommendation 2.3, Seismic 2024-07-24
[Table view] Category:Miscellaneous
MONTHYEARNMP2L2883, Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations2024-07-24024 July 2024 Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations NMP1L3563, Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-12-0404 December 2023 Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) 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) 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 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 ML17251A0452017-09-20020 September 2017 - Staff Assessment of Flooding Focused Evaluation (CACs No. MG0087 and MG0088) 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 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 ML14153A4102014-07-24024 July 2014 Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation 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) 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. ML14024A4422014-01-0707 January 2014 Submittal of Report in Accordance with 10 CFR 26.719(c)(1) Regarding Unsatisfactory Blind Performance Sample Testing ML13066A1712013-02-28028 February 2013 R.E. Gina, Overall Integrated Plan for Mitigation Strategies for Beyond-Design-Basis External Events ML13037A0822013-01-31031 January 2013 Submittal of Supplemental Seismic Walkdown Report ML12312A0142012-09-17017 September 2012 Transmittal of Pressure and Temperature Limits Report Revision 02.00 ML1127000692011-09-26026 September 2011 Enclosure 2, Mfn 10-245 R4, Description of the Evaluation and Surveillance Recommendations for BWR/2-5 Plants ML11154A0982011-05-25025 May 2011 License Amendment Request Pursuant to 10 CFR 50.90: Revision to License Condition 2.B.(2) to Delete Outdated Reference ML1108712502011-03-24024 March 2011 BWR Vessel and Internals Inspection Summaries for Spring 2010 Outages ML1019504972010-07-0909 July 2010 Attachment 1, CDI Report No. 10-11NP, Stress Assessment of Nine Mile Point Unit 2 Steam Dryer Using the Acoustic Circuit Model Rev. 4.1, Rev. 0, Cover Through Chapter 5 ML1007000882010-03-0303 March 2010 Pressure and Temperature Limits Report Revision ML0911802792009-04-21021 April 2009 Core Operating Limits Report, COLR1-19, Revision 0 ML12220A1012008-11-24024 November 2008 Constellation Energy Group, Inc. Definitive Proxy Statement Schedule 14A ML0629702462006-10-16016 October 2006 Special Report: Channel #12 of the Containment Hydrogen Monitoring System Inoperable for Planned Preventive Maintenance ML0627700442006-09-29029 September 2006 State Pollutant Discharge Elimination System, Permit No. Ny 000 1015, Request for Information Re Environmental Benefit Permit Strategy ML0619503912006-07-0505 July 2006 Post Accident Monitoring Instrumentation Report: Division 2 of the Containment Monitoring System Inoperable ML0611804852006-04-28028 April 2006 NRC 2006 a, Gen&Sis - Census 2000 Low Income Ej Nine Mile Point License Renewal ML0610906202006-04-19019 April 2006 NYSDEC 2003k, Website Reference Used in Chapter 2 NMP FSEIS, Round Whitefish Fact Sheet. ML0608804422006-03-24024 March 2006 GE Evaluation of OPRM Performance During Instability Events at Nine Mile Point, Unit 2 and Perry Nuclear Power Plant ML0606703632006-02-27027 February 2006 Special Report: Channel #11 of the Containment Hydrogen Monitoring System Inoperable for Planned Preventive Maintenance ML0609404802005-06-15015 June 2005 Doe/Eia 2005, Website Reference Used in Chapter 8 NMP FSEIS ML0727008492005-01-31031 January 2005 Caldon Experience in Nuclear Feedwater Flow Measurement ML0430003332004-10-26026 October 2004 to Audit and Review Plan for Plant Aging Management Reviews and Programs for the Nine Mile Point Nuclear Station, Units 1 and 2. ML0609401922004-10-0505 October 2004 Ohio Department of Natural Resources, Website Reference Used in Chapter 2 NMP FSEIS ML0609401352004-08-24024 August 2004 NYSDEC 2003a, Website Reference Used in Chapter 2 NMP FSEIS ML0609400532004-07-28028 July 2004 Campus Program.Com 2004, Website Reference Used in Chapter 2 NMP FSEIS ML0421203072004-07-20020 July 2004 2004 Owner'S Activity Report for Inservice Examinations for Nine Mile Point Unit 2 ML0419501842004-07-0606 July 2004 Special Report, Channel #11 of the Containment Hydrogen Monitoring System Removed from Service for Planned Maintenance ML0330702722003-10-23023 October 2003 10CFR50.59 Evaluation Summary Report for 2003 ML0323304182003-08-13013 August 2003 Guarantee of Retrospective Premium ML0318909502003-07-10010 July 2003 Relaxation of the Order, Exercising Enforcement Discretion, and Extension of the Time to Submit an Answer or Request a Hearing Regarding Order EA-03-038, Fitness-for-duty Enhancements for Nuclear Security Force Personnel for Calvert Cliffs, ML0619303922002-10-31031 October 2002 Identification of Changes, Reasons and Bases for Nine Mile Point Nuclear Station, L.L.C., Quality Assurance Program Topical Report, Nine Mile Point Nuclear Station - Unit 2 (USAR Appendix B) 2024-07-24
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Constellation Energy, RO. Box 63 Nine Mile Point Nuclear Station Lycoming, New York 13093 July 20, 2004 NMP2L 2118 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
Nine Mile Point Unit 2 Docket No. 50-410 License No. NPF-69 2004 Owner's Activity Report for Inservice Examinations Gentlemen:
Pursuant to 10 CFR 50.55a, Nine Mile Point Nuclear Station, LLC (NMPNS) is submitting the 2004 Owner's Activity Report for Inservice Examinations for Nine Mile Point, Unit 2. The report summarizes the results of examinations performed during the Second Period of the Second Ten-Year Interval, April 5, 2001 through April 25, 2004, including those conducted during Refueling Outage Nine (RFO9). This report closes out the Second Inservice Inspection Period.
This report meets the requirements of American Society of Mechanical Engineers (ASME) Code Case N-532-1, approved for use by the Regulatory Guide 1.147, "Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1," Revision 13.
Very truly yours, William C. Holston Manager Engineering Services WCH/RF/jm Attachment cc: Mr. H. J. Miller, NRC Regional Administrator, Region I Mr. G. K. Hunegs, NRC Senior Resident Inspector Mr. P. S. Tam, Senior Project Manager, NRR (2 copies)
Constellation Energy Group Nine Mile Point Nuclear Station Nine Mile Point Nuclear Station, LLC P.O. Box 63 Lake Road Lycoming, New York 13093 SECOND INSERVICE INSPECTION INTERVAL SECOND INSERVICE INSPECTION PERIOD 2004 OWNER'S ACTIVITY REPORT FOR RFO-09 INSERVICE EXAMINATIONS Prepared For Nine Mile Point Nuclear Station P.O. Box 63 Lycoming, New York 13093 Commercial Service Date: April 5, 1988 NRC Docket Number: 50-410 Document Number: NMP2-OAR-006-02 Revision Number: 00 Date: May 19, 2004 Prepared by: r Y, 9'Edward L. Anderson - NMPNS IS1 Program Manager Reviewed by ,. . /:) *1 Arttuir P. Giverson - Principal Engineer ASME Programs Approved by: -n I4 44) 5222) 0 Glenn R. Perkins - General Supervisor En ineering Programs
Nine Mile Point Nuclear Station Unit 2 [ NMP2-OAR-006-02 Constellation SECOND INSERVICE INSPECTION INTERVAL Rev. 00 0 Energy Group 2004 OWNERS' ACTIVITY REPORT Nine MileStation Point Nuclear FOR Date: May 19, 2004 INSERVICE EXAMINATIONS
.. Page i-2 of i - 13 TABLE OF CONTENTS Table of Contents ......................................................................... i-2 Record of Revision ........................................................................ i-3 Abstract . ................................................................................ i-4 Form OAR-1 Owner's Activity Report for Inservice (ISI) Inspection Plan NMP2-ISI-006 ... .............. i-7 Form OAR-1 Owner's Activity Report for Risk-Informed (RI-ISI) Inspection Plan NMP2-RI-ISI-006 ... ..... i-8 Form OAR-1 Owner's Activity Report for Containment (CISI) Inspection Plan NMP2-CISI-006 ... ........ i-9 Table 1 Abstract of Examination and Tests ................................................... i-10 Table 2 Items, with Flaws or Relevant Conditions that Require Evaluation for Continued Service ... ...... i-11 Table 3 Abstract of Repairs, Replacements, or Corrective Measures Required for Continued Service ..... i-12
Nine Mile Point Nuclear Station Unit 2 NMP2-OAR-006-02 Conella*i on SECOND INSERVICE INSPECTION INTERVAL Rev. 00 0p Energy Group 2004 OWNERS' ACTIVITY REPORT Nine Mile Point F Date: May19 2004 Nudear Station FOR Date:_May_19__2004 INSERVICE EXAMINATIONS Page i -3 of i -13
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x -P--AGEI S -eKyaRASN 00 May 19, 2004 Entire Initial issue of Owner's Activity Report for ASME Document Section XI Inservice, Risk-informed and Containment Examinations in accordance with the requirements of ASME Code Case N-532-1.
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Nine Mile Point Nuclear Station Unit 2 NMP2-OAR-006-02 03 0 Constellation Energy NinergyePn Group G
NineMile Point SECOND INSERVICE INSPECTION INTERVAL 2004 OWNERS' ACTIVITY REPORT FOR Rev.
Date:
00 May 19, 2004 Nudear Station l INSERVICE EXAMINATIONS Pacie i-4 of i - 13 ABSTRACT This Owner's Activity Report summarizes the results of the Nine Mile Point Nuclear Station (NMPNS), Unit 2, American Society of Mechanical Engineers (ASME) Section Xl Inservice, Risk-Informed and Containment Examinations performed during the Second Refueling Outage (RFO-09), from March 15, 2004 through April 25, 2004, and the last outage of the Second Inservice Inspection Period that started on 5 April 2001 and is scheduled to end on 4 April 2005. This Owner's Activity Report closes out the Second Inservice Inspection Period.
As an alternate to the requirements of the ASME, Boiler and Pressure Vessel Code (B&PVC), Section Xl, Article IWA-6000, NMPNS submitted Request for Relief ISI-19 on December 15, 2000, to implement ASME Code Case N-532, "Alternative Requirements to Repair and Replacement Documentation Requirements and Inservice Summary Report Preparation and Submission as Required by IWA-4000 and IWA-6000,Section XI, Division 1".
USNRC Safety Evaluation dated April 10,2001, under TAC No. MB0585 authorized use during 10-year inspection interval or until such time as the Code Case is referenced in a future revision of 10 CFR 50.55a, at which time NMPNS must follow all provisions in the Code Case with limitation (if any) specified in 10 CFR 50.55a.
Regulatory Guide 1.147, Revision 13, approved ASME Code Case N-532-1 for use. In keeping with the condition imposed under the USNRC authorization of RR-ISI-19, NMPNS is continuing to use the Owner's Activity Report.
f This Report complies with the requirements of Code Case N-532-1 and the conditions identified in RG 1.147.
OWNER'S ACTIVITY REPORTS - FORM OAR-1 Owner's Activity Reports Form OAR-1 were prepared and certified upon completion of the 2004 refueling outage (RFO-09) Examination activity for the following inspection plans:
- NMP2-lSI-006, Inservice Inspection Plan and Schedule
- NMP2-RI-ISI-006, Risk-Informed Inspection Plan and Schedule
- NMP2-CISI-006, Containment Inspection Plan and Schedule.
In addition to the Owner's Activity Reports, Form OAR-1, the following Tables are also included:
- a. Abstract of Examinations and Tests, Table 1, provides such information as ASME Code Examination Category, Total Examinations Required for the Inspection Interval, Total Examinations Required for this Period, Total Examinations Credited (%) for this Period, Total Examinations Credited (%) to Date for the Interval, and any remarks that may be applicable to each Examination Category.
- b. Items with Flaws or Relevant Conditions that Require Evaluation for Continued Service, Table 2, provides a listing of item(s) with flaws or relevant conditions that required evaluation to determine acceptability for continued service, whether or not the flaw or relevant condition was discovered during a scheduled examination or test, and provides such information as Examination Category, Examination Item Number, Item Description, Flaw Characterization (as required by IWA-3300), and whether the flaw or relevant condition was found during a scheduled Section Xl examination or test.
Nine Mile Point Nuclear Station Unit 2 NMP2-OAR-006-02 Constellatifon SECOND INSERVICE INSPECTION INTERVAL Rev. 00
~ Energy Group 2004 OWNERS' ACTIVITY REPORT Nine Mile Point ate May 19 2004 Nuclear Station
_ _ _INSERVICE EXAMINATIONS Paqe i-5 of i -13
- c. Abstract of Repairs, Replacements or Corrective Measures Required for Continued Service, Table 3, identifies those items containing flaws or relevant conditions that exceeded the ASME Section Xi acceptance criteria (IWX-3000) or in the case of supports IWF-3000 acceptance criteria; even though the discovery of the flaw or relevant condition that necessitated the repair, replacement or corrective measure, may not have resulted from an examination or test required by Section XI, and provides such information as Code Class, whether the item is a repair, replacement or corrective action, item description, description of work, ifthe flaw or relevant condition was found during a scheduled Section Xi Examination or test, date completed and the repair replacement plan number.
In accordance with ASME Section Xl, IWB-2412 (a), with the exception of the examinations that may be deferred until the end of the inspection interval as specified in Table IWB-2500-1, and for those examinations which NMPNS has requested and received approval in the form of relief request, the required examinations in each examination category have been completed for the Second Inservice Inspection Period in accordance with Table IWB-2412-1.
. Nine Mile Point Nuclear Station Unit 2 NMP2-OAR-006-02
% Cnstellaton SECOND INSERVICE INSPECTION INTERVAL Rev. 00 W Energy Group 2004 OWNERS' ACTIVITY REPORT Nine Mile Point FOR Date: May 19, 2004 Nu.ear Station FOR I INSERVICE EXAMINATIONS Page -6 of i - 13 FORM OAR-1 OWNER'S ACTIVITY REPORT As required by the provisions of the ASME Code Case N-532-1 Report Number NMP9-r)AP-nnr%-n Owner Nine Mile Point Nuclear Station. LLC. P.O. Box 63 Lake Road. Lvcomina. New York 13093 (Name and Address of Owner)
Plnnt1.
I -a Nine Mile Point Nuclear Station. P. 0. Box 63. Lvcomina. New York 13093 (Name and Address of Plant)
Plant Unit 2 Commercial Service Date April 5. 1988 Refueling Outage Number RFO-09 Current Inspection Interv al Second Inservice Innection Interval - Anril 5 1998 to Anril 4 2008 (1st, 2nd, 3rd, 4th, Other)
Current Inspection Period Second Inservice Inspection Period - April 5. 2001 to April 4. 2005 (1st, 2nd, 3rd)
Edition and Addenda of Section XI applicable to the Inspection Plan 1989 Edition. No Addenda Date and Revision of Inspection Plan NMP2-ISI-006. Revision 04. Dated December 30. 2003 Edition and Addenda of ASME Section Xl applicable to Repairs and Replacements, if different than the Inspection Plan N/A CERTIFICATE OF CONFORMANCE I certify that the statements made in this Owner's Activity Report are correct, and that the examinations, tests, repairs, replacements, evaluations and corrective measures represented by this report conform to the requirements of Section Xl.
Certificate of Authorfation No.
,~,N/A (if applicable)
Expiration Date N/A Ainnipl A kd (General Supervisor - Engineering Programs)
Date =rlkMJz CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of N/A and employed by ABSG Consulting Inc. of Houston, Texas 77060 have inspected the items described in this Owners Activity Report, during the period 03/15/04 to 04/25/04 , and state that to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section Xl.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations, tests, repairs, replacements, evaluations and corrective measures described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspction.
_ _ a_ __ _ _ _ Commissions 10195 N. I C/ lnspector:saignatur' National Board, State, Province, and Endorsements Date
Nine Mile Point Nuclear Station Unit 2 NMP2-OAR-006-02 Constellation SECOND INSERVICE INSPECTION INTERVAL Rev. 00 0 Energy Group 2004 OWNERS' ACTIVITY REPORT Nine Mile Point Nucdear Station FORDate:
INSERVICE EXAMINATIONS j Page ,
May 19,2004 i -7 1,
of i -13 FORM OAR-1 OWNER'S ACTIVITY REPORT As required by the provisions of the ASME Code Case N-532-1 Report Number NMP2-OAR-006-02 Owner Nine Mile Point Nuclear Station, LLC. P.O. Box 63 Lake Road. Lycoming. New York 13093 (Name and Address of Owner)
Plant Nine Mile Point Nuclear Station. P. 0. Box 63. Lycoming. New York 13093 (Name and Address of Plant)
Plant Unit 2 Commercial Service Date April 5. 1988 Refueling Outage Number RFO-09 Current Inspection Intervall Second Inservice Insoection Interval - Anril 5. 1998 to Aoril 4. 2008 (1st, 2nd, 3rd, 4th, Other)
Current Inspection Period _ Second Inservice Inspection Period - April 5. 2001 to April 4. 2005 (1st, 2nd, 3rd)
Edition and Addenda of Section Xl applicable to the Inspection Plan 1989 Edition, No Addenda Date and Revision of Inspection Plan NMP2-RI-ISI-006. Revision 00. Dated December 30. 2003 Edition and Addenda of ASME Section XI applicable to Repairs and Replacements, if different than the Inspection Plan N/A CERTIFICATE OF CONFORMANCE I certify that the statements made in this Owner's Activity Report are correct, and that the examinations, tests, repairs, replacements, evaluations and corrective measures represented by this report conform to the requirements of Section XI.
Certificate of Authrization No. N/A Expiration Date N/A
// D (Ifapplicable)
Sioned
-a go . ' /-4't
. Date 5/z9kBY (General Supervisor- Engineering Programs)
CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of NIA and employed by ABSG Consulting Inc. of Houston, Texas 77060 have inspected the items described in this Owner's Activity Report, during the period 03/15/04 to 04/25/04 , and state that to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section Xl.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations, tests, repairs, replacements, evaluations and corrective measures described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
_ _ _ __ __Commissions 10195 N. I Ad Inspector'"ignature- National Board, State, Province, and Endorsements Date
Nine Mile Point Nuclear Station Unit 2 NMP2-OAR-006-02
" Constellation SECOND INSERVICE INSPECTION INTERVAL Rev. 00
%J Energy Group 2004 OWNERS' ACTIVITY REPORT NineaMrSton FOR Date: May 19, 2004
. INSERVICE EXAMINATIONS Page i -8 of i -13 FORM OAR-1 OWNER'S ACTIVITY REPORT As required by the provisions of the ASME Code Case N-532-1 Report Number NMP2-OAR-006-02 Owner Nine Mile Point Nuclear Station. LLC. P.O. Box 63 Lake Road. Lycoming. New York 13093 (Name and Address of Owner)
Pinnt I Hal lX Nine Mile Point Nuclear Station. P. O. Box 63. Lvcomina. New York 13093 (Name and Address of Plant)
Plant Unit 2 Commercial Service Date April 5. 1988 Refueling Outage Number RFO-09 Current Inspection Interval. First Inservice Insnection Interval - Anril 5. 1998 to Anril 4- 2008 (1st, 2nd, 3rd, 4th, Other)
Current Inspection Period Second Inservice Inspection Period - April 5. 2001 to April 4. 2005 (1st, 2nd, 3rd)
Edition and Addenda of Section XI applicable to the Inspection Plan 1998 Edition, No Addenda Date and Revision of Inspection Plan NMP2-CISI-006. Revision 00. Dated February 24. 2000 Edition and Addenda of ASME Section XI applicable to Repairs and Replacements, if different than the Inspection Plan NIA CERTIFICATE OF CONFORMANCE I certify that the statements made in this Owner's Activity Report are correct, and that the examinations, tests, repairs, replacements, evaluations and corrective measures represented by this report conform to the requirements of Section Xl.
Certificate of Authorization No. N/A Expiration Date N/A
/7 7) 6 ~ (ifaapplicable)
Signed 1$z4 Date &ZYJG ST (General Supervisor - Enaineerino Proorams)
CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of N'A and employed by ABSG Consulting Inc. of Houston. Texas 77060 have inspected the items described in this Owners Activity Report, during the period 03115/04 to 04/25104 , and state that to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations, tests, repairs, replacements, evaluations and corrective measures described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this ipection.
_ _ _ _ _ _ Commissions 10195 N. I
/ Inspectorsagnature" National Board, State, Province, and Endorsements Date
Nine Mile Point Nuclear Station Unit 2 NMP2-OAR-006-02 e Constellation SECOND INSERVICE INSPECTION INTERVAL Rev. 00 Energy Group 2004 OWNERS' ACTIVITY REPORT l Nine Mile Point Dat May 19 2004 Nucear Station F, 2I INSERVICE EXAMINATIONS Page i -9 of i -13 TABLE 1 ABSTRACT OF EXAMINATION AND TESTS As reouired by the provisions of the ASME Code Case N-532-1 TOTAL TOTAL 'TOTAL TOTAL EXAMINATIONS CODE EXAMINATIONS EXAMINATIONS EXAMINATIONS CREDITED (%) TO EXAMINATION REQUIRED FOR REQUIRED FOR CREDITED (%) DATE FOR THE CATEGORY INTERVAL THIS PERIOD FOR THE PERIOD INTERVAL REMARKS B-A 35 11 11 - 100% 22 - 62.8% Deferral Permissible B-D 66 28 28 -100% 44 - 66.6% Deferral Permissible B-G-1 307 100 75 - 75.0% 178 - 57.9% Deferral Permissible B-G-2 95 40 35 - 87.5% 56 - 58.9% Note 1 B-K 8 2 2-100% 5 - 62.5% CC N-509 B-L-2 1 0 0 - 0.0% 0 - 0.0% Deferral Permissible, When Disassembled B-M-2 35 13 9 - 69.2% 15 - 39.4% Deferral Permissible, When Disassembled B-N-1 82 81 81 -100% 142 - 67.0% Note 2 B-N-2 15 3 1 - 33.3% 12 - 67.0% Deferral Permissible B-O 8 4 4 - 100% 8 - 57.1% Deferral Permissible C-A 2 1 1 - 100% 1 - 50.0% Note 3 C-B 4 2 2-100% 2 - 50.0% Note 3 C-C 24 7 5 - 71.4% 13 -. 54.1% CC N-509 C-D 1 1 1-100% 1-100%
C-G 58 27 11 - 40.7% 25-.43.1% RR-IWC-1, When Disassembled D-A 24 8 8-100% 16 - 67.0% CC-N-509 E-A 2784 874 874 - 100% 1860 - 66.8% Note 2 F-A 245 94 94-100% 194 - 63.1% CC N-491-1 L-A 123 0 0 - 0.0% 61 - 50.0% Note 4 R-A 125 75 74 - 98.6% 74 - 59.2% RI-ISI, Note 5 R-C 25 12 12-100% 19 - 67.0% RI-BER's, Note 5 Notes:
- 1. Does not include 185 CRD's examined when disassembled
- 2. 100% of accessible surfaces examined each period
- 3. All examinations are performed during 2'1 or 3' period
- 4. Category requires 100% examination every 5 years
- 5. Reference RR-RI-ISI-2, all examinations to be completed in the 2" and 3T periods
Nine Mile Point Nuclear Station Unit 2 NMP2-OAR-006-02 O Constellation Energy Group SECOND INSERVICE INSPECTION INTERVAL 2004 OWNERS' ACTIVITY REPORT Rev. 00 Nine Mile Point FOR Date: May 19, 2004 Nudear Station FOR
. INSERVICE EXAMINATIONS Page i-10 of i -13 TABLE 2 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRE EVALUATION FOR CONTINUED SERVICE As required by the provisions of the ASME Code Case N-532-1 FLAW OR RELEVANT FLAW CONDITION EXAMINATION ITEM ITEM CHARACTERIZATION FOUND DURING CATEGORY NUMBER DESCRIPTION (IWA-3300) SCHEDULED SECTION Xi EXAMINATION OR TEST I _(YES OR NO)
F-A F1.20 2RHS-PSST319A2 Loose Jam Nuts on Strut YES B-G-2 B7.70 2MSS-AOV6CVB548 Identified 6 studs with thread YES
_ _ _ _ _ _ __ _ _ __ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _d am aq e_ _ _ _ _ _ _ _ _ _ _
B-M-2 B12.50 2WCS-MOV103.VBY175 denied (2) Linear YES in 'Cations across seatI B-K Bi0.20 2FWS-47-15-FW3141315 Identifiedcd2? rounded YES indi tionsl R-A R1.16 2RPV-KB1O Previous' recorded welding YES
_a___continuines R-A R1.16 2RPV-KB20-OL Previousreoreded flaws YES
__ _ _ __ __ __ __ __ ___ __ _ __ _ _ _p rio r tdWe ¶ o ve rla y _ _ _ _ _ _ _ _ _ _ _ _
Nine Mile Point Nuclear Station Unit 2 NMP2-OAR-006-02 O Constellaion Energy Group SECOND INSERVICE INSPECTION INTERVAL 2004 OWNERS' ACTIVITY REPORT Rev. 00 Nine Mile Point Date: May 19, 2004 Nuclear Station FOR Date M 19 2004 I-INSERVICE EXAMINATIONS Pacie i -11 of i -13 I TABLE 3 ABSTRACT OF REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES REQUIRED FOR CONTINUED SERVICE As required by the provisions of the ASME Code Case N-532-1 FLAW OR RELEVANT REPAIR CONDITION FOUND REPLACEMENT DURING SCHEDULED REPAIR OR DESCRIPTION SECTION Xi REPLACEMENT CODE CORRECTIVE ITEM OF EXAMINATION OR TEST DATE PLAN CLASS MEASURE DESCRIPTION WORK (YES OR NO) COMPLETE NUMBER 1 Replacement 2MSS-PSV123, Replaced 12 Studs NO 04/21/04 03-08206-00 PB116 and Nuts 1 Replacement 2MSS*PSV124, Replaced 12 Studs NO 04/21/04 03-07962-00 PB119 and Nuts 1 Replacement 2MSS'PSV130, Replaced 12 Studs NO 04/21/04 03-01301-00 PB137 and Nuts_
1 Replacement 2MSS*PSV1 34. Replaced 12 Studs NO 04/21/04 03-07964-00 PB149 and Nuts 1 Replacement 2MSS*PSV136, Replaced 12 Studs NO 04/21/04 03-07965-00 PB155 and Nuts _
1 Replacement 2MSSPSV137, Replaced 12 Studs NO 04121/04 03-07966-00 PB158 and Nuts 1 Replacement 2FWS-AOV23A Replaced 12 Nuts NO 03121/04 01-02885-03
,VB506 1 Replacement 2RPV-CRD158 Replaced 8 Cap NO 03126104 03-05448-00 Screws and Washers 1 Replacement 2RPV-CRD143 Replaced 8 Cap NO 03/26/04 03-13382-00 Screws and Washers 1 Replacement 2RPV-CRD129 Replaced 8 Cap NO 03/26/04 03-13085-00 Screws and Washers 1 Replacement 2RPV-CRD099 Replaced 8 Cap NO 03/26/04 03-05447-00 Screws and Washers 1 Replacement 2RPV-CRD039 Replaced 8 Cap NO 03/'26/04 03-05446-00 Screws and Washers 1 Replacement 2RPV-CRD002 Replaced 8 Cap NO 03'26/04 03-13091-00 Screws and Washers l 1 Replacement 2RPV-CRD032 Replaced 8 Cap NO 03/26/04 03-13087-00 Screws and Washers 1 Replacement 2RPV-CRD008 Replaced 8 Cap NO 03126,/04 03-13082-00 Screws and Washers 1 Replacement 2RPV-CRD030 Replaced 8 Cap NO 03/26/04 03-13083-00 Screws and Washers 1 Replacement 2RPV-CRD087 Replaced 8 Cap NO 03/26/04 03-13089-00 Screws and Washers 1 Replacement 2RPV-CRD167 Replaced 8 Cap NO 03/'26104 03-13086-00 Screws and Washers 1 Replacement 2RPV-CRD185 Replaced 8 Cap NO 03/26104 03-13090-00
_Screws and Washers I
Nine Mile Point Nuclear Station Unit 2 NMP2-OAR-006-02 Constellation SECOND INSERVICE INSPECTION INTERVAL Rev. 00 Energy Group 2004 OWNERS' ACTIVITY REPORT Nine Mile Point FOR Date: May 19, 2004 Nuclear Station FOR 1 INSERVICE EXAMINATIONS Page i - 12 of i - 13 FLAW OR RELEVANT REPAIR CONDITION FOUND REPLACEMENT DURING SCHEDULED REPAIR OR DESCRIPTION SECTION Xi REPLACEMENT CODE CORRECTIVE ITEM OF EXAMINATION OR TEST DATE PLAN CLASS MEASURE DESCRIPTION WORK (YES OR NO) COMPLETE NUMBER 1 Replacement 2RPV-CRD163 Replaced 8 Cap NO 03/26/04 03-12249-00 Screws and Washers 1 Replacement 2RPV-CRD137 Replaced 8 Cap NO 03/26/04 03-05450-00 Screws and Washers 1 Replacement 2RPV-CRD148 Replaced 8 Cap NO 03/26/04 03-13088-00 Screws and Washers 1 Replacement 2RPV-CRD123 Replaced 8 Cap NO 03/26/04 03-13084-00 Screws and Washers l 1 Replacement 2RPV-CR0146 Replaced 8 Cap NO 03/26/04 03-00202-00 Screws and Washers 1 Replacement 2RPV-CRD116 Replaced 8 Cap NO 03/26/04 03-00200-00 Screws and Washers 1 Replacement 2RPV-CRD102 Replaced 8 Cap NO 03/26/04 03-00201-00 Screws and Washers 1 Replacement 2FWS- Replaced Mechanical NO 03/19/04 02-13034-13 PSSP194A1 Snubber l 2 Replacement 2RHS- Replaced Mechanical NO 03/19/04 02-13034-08 PSSP719A2 Snubber l 2 Replacement 2RHS- Replaced Mechanical NO 03/29/04 02-13034-01 PSSP718A2 Snubber l 1 Replacement 2WCS- Replaced Mechanical NO 03/29/04 04-05842-00 PSSP622A1 Snubber l 1 Replacement 2WCS- Replaced Mechanical NO 03/29104 04-05842-00 PSSP569A1 (B) Snubber 1 Replacement 2WCS- Replaced Mechanical NO 03/29/04 04-05842-00 PSSP569A1 (A) Snubber 1 Replacement 2WCS*MOV102 Replaced Valve NO 04/08/04 03-04797-07
Nine Mile Point Nuclear Station Unit 2 NMP2-OAR-006-02 3 Cnellation SECOND INSERVICE INSPECTION INTERVAL Rev. 00 W~jF Energy Group 2004 OWNERS' ACTIVITY REPORT Nuiear StaMion FOR Date: May 19, 2004
.:INSERVICE EXAMINATIONS Page i -13 of i -13 End of Inservice Inspection Owner's Activity Report For Refueling Outage Nine (RFO-09)