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Category:Letter
MONTHYEARML24222A6772024-08-0909 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) 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 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 NMP1L3582, Annual Radioactive Environmental Operating Report2024-05-15015 May 2024 Annual Radioactive Environmental Operating Report 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 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 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 IR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 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)) ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines IR 05000410/20243012023-12-14014 December 2023 Initial Operator Licensing Examination Report 05000410/2024301 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 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 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 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 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 - RITSTF Initiative 4b 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) IR 05000220/20234022023-11-28028 November 2023 Security Baseline Inspection Report 05000220/2023402 and 05000410/2023402 NMP1L3557, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums ML23305A0052023-11-0101 November 2023 Operator Licensing Examination Approval IR 05000220/20234202023-11-0101 November 2023 Security Baseline Inspection Report 05000220/2023420 and 05000410/2023420 IR 05000220/20230032023-10-25025 October 2023 Integrated Inspection Report 05000220/2023003 and 05000410/2023003 IR 05000220/20235012023-10-17017 October 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000220/2023501 and 05000410/2023501 IR 05000220/20230112023-10-16016 October 2023 Comprehensive Engineering Team Inspection Report 05000220/2023011 and 05000410/2023011 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans NMP1L3554, Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases2023-10-0606 October 2023 Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases C IR 05000220/20233032023-09-20020 September 2023 Retake Operator Licensing Examination Report 05000220/2023303 ML23250A0822023-09-19019 September 2023 Regulatory Audit Summary Regarding LARs to Adopt TSTF-505, Rev. 2, and 10 CFR 50.69 ML23257A1732023-09-14014 September 2023 Requalification Program Inspection IR 05000220/20230052023-08-31031 August 2023 Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2023005 and 05000410/2023005) RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs 2024-08-09
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARML24222A6772024-08-0909 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 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 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 . 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.... 2024-08-09
[Table view] |
Text
REGULATORY INFQRI'fATION DISTRIBUTION SYSTEM (RIDS)
DISTRIBUTION FOR INCOMING MATERIAL 50-410 REC: CASE E G ORG: RHODE G K DOCDATE: 04/28/78 NRC NIAGARA MOHAWK PWR DATE RCVD: 05/Oi/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED
SUBJECT:
LTR 1 ENCL 1 INFO REQUESTED BY S. VARGA IN LTR DTD 04/06/78 RE: UTILITY REQUEST FOR EXTENSION OF LATEST COMPLETION DATE FOR CPPR-112.
PLANT NAME: NINE MILE POINT UNIT 2 REVIEWER INITIAL: XBT DISTRIBUTOR DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS INITIAL: ~
REQUESTS FOR EXEMPTIONS (ALL TYPES)
<DISTRIBUTIOI4 CODE B006)
FOR BR CHIEF VARGA+~~W/ENCL PROS MGR KANE++W/ENCL ACTION'OR LIC ASST SERVICE++W/ENCL INFO: MOQRE++LTR ONLY(i) REGAN++LTR ONLY(i)
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INTERNAL: REG FILE++W/EN NRC PDR++W/ENCL J MILLER>+W/ENCL T ABELL+4W/ENCL E. QASF ~/E'~M-EXTERNAL: LPDR S OSWEGO) NY+>W/ENCL ACRS CAT B4~~W/16 ENCL
'ISTRIBUTION: LTR 30 ENCL 26 "CONTROL NBR: 781210181 SIZE: 2P THE END
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NIAGARA MOHAWK POWER CORPORATION NIAGARA '~ MOHAWK 300 ERIE BOULEVARO, WEST SYRACUSE. N. Y. I 3202 April 28, 1978 8
Mr. Edson G. Case, Acting Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission
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Washington, D. C. 20555 17
Dear Mr. Case:
Re: Nine Mile Point Unit 2 Docket No. 50-410 Enclosed is the additional information that Mr. Varga of your staff requested in a letter dated April 6, 1978 regarding the Niagara Mohawk Power Corporation request for an extension of the latest completion date for Construction Permit No. CPPR-112. This information quantifies the extent of the delay associated with each of the three causes cited.
It also identifies on a time scale, the point at which the delay was incurred and the extent it alone affected the overall schedule for completion of the plant. The delays show good cause for extending the latest date of Construction Permit No. CPPR-112 to December 31, 1984.
Very truly yours, NIAGARA MOHAWK POWER CORPORATION Ger ld . Rhode, Vice President System Projec Management NLR/s zd Enclosure 781210)ag Soo< s(a+
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7/73 I/74 7/74 I/75 7/75 i/76 7/76 7/77 I/77 I/78 7/78 I/79 7/79 CP ISSUE 7 74 CP EXPIRATI N 7/78 (2)
- 13) i (3) iii
- 3) iv (3 (3)v (3 vi 3)vii (3)viii (3)i (3)x DELAYCAUSE DATE OF DELAY DURATION OF DELAY DELAY CAUSE DATE OF DELAY DURATION OF DELAY (I) NEED FOR POWER POSTPONED DEC. I s 1973 72 MO. vii DELAY IN GRANTING ORIGINAL CONSTRUCTION JUI I, 1973 12 MO.
PERMIT (2) LACK OF FUNDS AT REASONABLE RATES NOV. I s 1974 12 MO. viii IMPLEMENTATIONOF NRC REQUIREMENT FOR ECCS OCT. I, 1973 IO MO.
PUMP FLOOD PROTECTION (3) i MARK 3E LAR DESIGN CHANGES SEP. I, 1976 12 MO.
ix IMPLEMENTATIONOF PIPE WHIP PROTECTION MAY I, 1973 12 MO.
il STUDY OF GEOLOGICAL FEATURES DEC. 13s 1976 12 Ma REQUNIEMENTS OF RG. 1.46 iii CHANGE FROM ONCE-THROUGH TO CLOSED JUL. 19s 1976 4 MO. x RG.1.89 CLASS IE EQUIPMENT REQUIREMENTS. NOV. I, 1974 6 MO.
LOOP COOLING iv ELECTRICAL RACEWAY AND REACTOR BUILDING JAN I s 1975 9 MO.
STRUCTURAL REDESIGN v LABOR PROBLEMS NCLUDDIG WORK STOPPAGES JUN. I s ISN OCT I sl977 3 MO.
I MO.
CONSTRUCTION DELAYS vi WELDER DELAYS SHORTAGE AND MATERIALPROCUREMENT DEC. I s 1977 12 MO.
NINE MILE POINT, UNIT 2
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NUC R REGULATORY COMMISSION 0 REGION I 631 PARK AVENUE C>
KING OF PRUSSIA, PENNSYLVANIA I 9406 n qo 4+*+ 4 Docket No. 50-410 g 6 APR l978 DRAVO Corporation Pipe Fabrication Division ATTN: Mr. Gustav Schwab Vice President and General Manager 1115 Gilman Avenue Marietta, Ohio 45750 Gentlemen:
Subject:
Niagara Mohawk Power Corporation Report of January 30, 1978 Regarding the Dravo Pipe Fabrication Division guality Assurance Program Me received your letter of April 7, 1978, concerning the subject report. Your letter will 'be made a part of the public record as you requested.
Sincerely, I
Bo ce H. Gr ier Director
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~p,s Abc' UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 "vA APR 25 j978
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Docket Nos: 50-358 50-387 50-352/353 50-367 50-373/374 50-388 50-410 50-322
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APPLICANT; MEMBERS OF MARK II OWNER'S GROUP
SUBJECT:
TRIP TO LIVERMORE, STANFORD RESEARCH INSTITUTE AND GENERAL ELECTRIC TO DISCUSS MARK II POOL DYNAMIC LOADS
~kkdd The purpose of this trip was to discuss several analytical and experimental programs related'o Mark II pool dynamic loads. A copy of the attendees, agenda and slides distributed at the meeting are attached.
In the morning of the first day (Wednesday) we met with Livermore personnel to discuss the Livermore/DOR program to study fluid structure interactions (FSI) in the Mark-I Monticello Safety Relief Valve (SRV) tests.
a Wednesday afternoon we met with personnel at Stanford Research Institute to discuss their 1/13 scale Mark II pool swell tests.
Thursday we met with representatives of the Mark II owner's group and General Electric to discuss the status of several tasks in their Mark II pool dynamic load program. A summary of -the topics discussed in the meetings is provided below.
~Sumar Livermore Meetin Ed McCauley of Livermore summarized the results of the FY 77 Livermore FSI program. Their study of SRV-FSI effects showed a trend of decreasing loads with increasing wall flexibility. The major limitations of their study included the plane section modeling of the containment and the modeling of the source. These assumptions result in an over-estimate of the dependence of SRV loads on wall flexibility. Future studies by Livermore are aimed at evaluating the importance of these parameters.
h APR 35 ]g7g Standford Research Institute Meetin The purpose of this meeting was to discuss the preliminary results of the'Mark II 1/13 scale single vent tests. These SRI tests consisted of air charging tests. .Shakedown tests were conducted to determine the affect of water vapor in scale air tests on pool swell phenomenon.
The preliminary results for the SRI tests showed differences from similar tests conducted at MIT. The purpose of the meeting was to identify reasons for the differences. Additional SRI testing was
.discussed to resolve differences in results. Hhi'le at the SRI facility we toured the pool dynamic test stands. Me noted that SRI is conducting EPRI funded tests to investigate steam chugging phenomena. Tests are being conducted at three different scales including single and multivent tests. This test program is a study of the fundamental phenomena of chugging. This program is not a par t of the Mark II owner group supporting program.
Mark II Owner's Grou Meetin The topics discussed in this meeting are listed in the attached meeting agenda. A summary of discussion follows:
- 1. Monticello SRV - Mark II Fluid Structure Interaction Studies Or. H. Tang of General Electric discussed the results of studies at GE to determine the effect of containment wall flexibility on the measured SRV loads in the Monticello tests. GE performed calculations similar to those performed by Livermore. Their plane strain calculations utilized similar assumptions of containment rigidity and load source to those performed by Livermore. Under these conditions they observed the same trend of reducing load with increasing wall flexibility as observed in the Livermore studies.
However, the GE studies were extended to include axisymmetric calculations, 3D modeling of a torus segment and a multiple pulse source. Results of these studies show that wall flexibility amplifies the loads. This conclusion contradicts the Livermore 2D study. In addition they conducted analytical-experimental comparisons using their model and the Monticello data. The use of the more realistic assumptions in the analytical model substantiated the Mark II owner's claim that the Monticello benchmark is valid.
The Monticello FSI study is now considered complete by the Mark II owner's group. Documentation will be provided to the NRC by the end of May 1978,
In our March meeting with the Mark II owner's group we discussed the desirability of formulating a conservative chugging impulse load to resolve 4 T FSI questions. Dr. Healzer of General Electric discussed their plan for this task. They should complete this study by early June 1978. A status report will be provided at the next Mark II owner's meeting.
This meeting is tentatively scheduled for mid May 1978, In addition we requested that Dr. Healzer provide us, within the next few'eeks, an outline of the objective of this task.
- 3. SRV Pool Tem erature Limits T. Su of NRC provided an NRC status report on the issue of SRV pool temperature limits. He stated that based on our current review of the small scale tests there is inadequate supporting data to justify the current pool temperature limits for rams-head relief valve devices. As a result of our review we are preparing an NRC position requiring the use of quencher type devices in Mark II plants since these devices have higher pool temperature limits.
- 4. DFFR Lead Plant SRV Loads T. Su of NRC provided a status report on the NRC review of the Mark II ramshead model. He highlighted several deficiencies in the current model. We also discussed the use of the ramshead model for those lead plants which have committed to a switch from a ramshead to a quencher device. H. Brinkman representing the Mark II owner's group stated that their plans are to use the current ramshead model to predict SRV loads for plants with quencher devices.
Test programs are being developed to show that the use of these ramshead loads for quencher devices is a conservative approach.
Current plans call for completion of the confirmatory tests prior to operation of the first Mark II plant.
5, PSTF Im act Loads G. Maise of BNL outlined the results of the NRC evaluation of Mark II Pool Dynamic - impact loads. This study concluded that the current DFFR impact load specification is inadequate in that
4 APR 2g ]97B the impulse load specification does not include a conservative pulse duration. In addition no consideration has been given to the affect of target geometry on the impact load. The Mark II owner's stated that they had not had sufficient time to review the basis for our conclusions nor the impact of this potential load modification on equipment in specific Mark II plants. Their preliminary review of the BNL study has not uncovered any deficiences in the BNL study. However, conservatisms in the current impact load specification could be balanced against these recently identified non conservatisms. At the next Mark II owner's meeting in mid-May the Mark II owners will provide us their evaluation of the BNL study and a review of the impact of this load modification on specific Mark II plants.
g.(<,6 I. Peltier, Project Manager Light Hater Reactors Branch No. 1 Division of Project Management
Enclosures:
- l. Agenda
- 2. Attendance List
- 3. Viewgraph Material cc: See Following Pages
Long Island Lighting Company <PR 25 ><78 ATTN: Mr. Andrew W. Wofford Vice President 175 East Old Country Road Hicksville, New York 11801 Edward M. Barrett, Esq.
General Counsel Long Island Lighting Company 250 Old Country Road Mineola, New York 11501 Edward J. Walsh. Esq.
General Attorney Long Island Lighting Company 250 Old Country Road Mineola, New York 11501 Mr. Thomas Burke Project Manager, Shoreham Nuclear Power Station P. 0. Box 618 Wading River, New York 11792 Director, Technical Development Programs State of New York Energy Office Agency Building 2 Empire State Plazq Albany, New York 12223 Haward L. Blau Blau and Cohn, P. C.
380 North Broadway jericho, New York 11753 Irving Like, Esq.
Reilly, Like and Schnieder 200 West Main Street Babylon, New York 11702 MUB Technical Associates 366 California Avenue Suite 6 Palo Alto, California 94306
APR 25 1978 Philadelphi Electric Company Eugene J. Bradley ATTN: Mr. Edward G. Bauer, Jr. Philadelphia Electric Company Vice President and General Associate General Counsel Counsel 2301 Market Street 2301 Market Street Philadelphia, Pennsylvania 19101 Philadelphia, Pensylvania 19101 Troy B, Conner, Jr. Ewq.
Conner, Moore & Corber 1747 Pennsylvania Avenue, N. W.
Washington, D. C. 20006 W. William Anderson, Esq.
Deputy Attorney General Room 512, Main Capitol Building Harrisburg, Pennsylvania 17120 Frank R. Clokey, Esq.
Special Assistant Attorney General Room 218, Towne House Apartments P. 0. Box 2063 Harrisburg, Pensylvania 17105 Honorable Lawrence Coughlin House of Representatives Congress of the United States Washington, D. C. 20515 Roger BE Reynolds, Jr., Esq.
324 Swede Street Norristown, Pennsylvania 19401 Willard C. Hetzel, Esq.
312 main Street East Greenville, Pennsylvania 18041 Lawrence Sager, Esq.
Sager & Sager Associates 45 High Street Pottstown, Pennsylvania 19464 Joseph A. Smyth Assistant County Solicitor County of Montgomery Courthouse Norristown, Pennsylvania 19404
APR 25 1978 The Cincinnati Gas 8 Electric Company David B. Fankhauser, PhD ATTN: Mr, Earl A, Borgmann 3569 Nine Mile Road Vice President - Engineering Cincinnati, Ohio 45230 P. 0. Box 960 Cincinnati, Ohio 45201 Thomas A. Luebbers, Esq.
Cincinnati City Solicitor Mr. William J. Moran Room 214 - City Hall General Counsel Cincinnati, Ohio 45202 The Cincinnati Gas 8 Electric Co.
P. 0. Box 960 Troy 8 Conner, Esq.
~
Cincinnati, Ohio 45201 Conner, Moore & Cober 1747 Pennsylvania Ave. N. WE Mr. William G. Porter, Jr. Washington, D. C, 20006 Porter, Stanley, Arthur, & Platt 37 West Broad Street Columbus, Ohio 43215 Mr. Robert Killen, Chairman of the Board 8 Chief Executive Officer The Dayton Power & Light Company P. 0. Box 1034 Dayton, Ohio 45401 Mr. J. Robert Newlin, Counsel The Dayton Power & Light Company P. 0. Box 1034 Dayton, Ohio 45401 Mr. Stephen Schumacher Miani Valley Power Project P. 0. Box 252 Dayton, Ohio 45401 Ms. Augusta Price 601 Stanley Avenue Cincinnati, Ohio 45226 Mr. James D. Flynn Manager, Licensing 8 Environmental Affairs The Cincinnati Gas & Electric Company P, 0. Box 960 Cincinnati, Ohio 45201 Mr. J. P. Fenstermaker Senior Vice President -, Operations Columbus 8 Southern Ohio Electric Co.
215 North Front Street Columbus, Ohio 43215
APR g5 F8 Northern Indiana Public Service Company ATTN: Mr. H. P. Lyle, Vice President Electric Production 5 Engineering 5265 Holman Ave.
Hammond, Indiana 46325 Meredith Hemphill, Jr. Esq.
Assistant General Counsel Bethlehem Steel Corporation Martin Tower Bethlehem, Pennsylvania 18016 William H. Eichhorn, Esq.
Eichhorn, Morrow 8 Eichhorn 5243 Hohman Avenue Hammond, Indiana 46320 Edward W. Osann, Jr., Esq.
Wolfe, Hubbard, Leydid, Voit & Osann, Ltd.
Suite 4600 One IBM Plaza Chicago, Illinois 60611 Marvin N. Berm, Esq ~
Special Assistant Attorney General 134 North LaSalle Street Suite 2222 Chicago, Illinois 60602 Robert J. Vollen, Esq.
109 North Oearborn Street Chicago, Illinois 60602
Commonwealth Edison Company APR 2g )g78 A&i N; Mr. Byron Lee, Jr, Vice President P, 0. Box 767 Chicago, Illinois 60690 Richard E. Powell, Esq.
Isham, Lincoln & Beale One First National Plaza 2400" Chicago, Il 1 inoi s 60670
APR 85 1978 Pennsylvania Power and Light Company ATTN: Mr. Norman W. Curtis Vice President - Engineering and Construction 2 North Ninth Street Allentown, Pennsylvania 18101 Mr. Earle M. Mead Project Manager Pennsylvania Power 4I Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Gerald Charnoff, Esq.
Shaw, Pittman, Potts, Trowbridge 5 Madden 1800 M Street, N. W.
Washington, D. C. 20036 Mr. William E. Barberich Licensing Engineer Pennsylvania Power II Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mr. Robert J. Shovlin, Project Manager Susquehanna Pennsylvania Power 5 Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Hubert, Barnes, Esq.
Pennsylvania Power 8 Light Company 901 Hamilton Street Allentown, Pennsylvania 18101 Edward M. Nagel, Esquire General Counsel and Secretary Pennsylvania Power 8 Light Company 2 North Ninth Street Allentown, Pennsylvania, 18101
Washington Public Power Supply System ATTN: Nr. Kneil 0. Strand APR Bg )~78 Hanaging Oirector 3000 George Washington Way Richland Washington 99352 Joseph B. Knotts, Jr., Esq.
Oebevoise 5 Liberman 700 Shoreham Building 806 Fifteenth Street, N. W.
Washington, O. C. 20005 Richard Q. Quigley, Esq.
Washington Public Power Supply System P. 0. Box 968 Richland, Washington 99352
Niagra Mohawk Power Corporation ATTN: Mr. Jerald K. Rhode ~~R ~~ 197s Vice President Engineering 300 Erie Boulavard West Syracuse New York 13202 .
Eugene BE Thomas, Jr.
LeBoeuf, Lamb, Leiby 8 MacRae 1757 N Street, N, W.
Washington, D, C. 20036 Anthony Z. Roisman, Esq.
Roisman, Kessler & Cashdan 1025 15th Street, N. W.
Washington, D. C. 20036 Mr. Richard Goldsmith Syracuse University College of Law E. I. White Hall Campus Syracuse, New York 13210 T. K. DeBoer, Director Technological Development Programs New York State Energy Office Swan Street Building Core 1 - 2nd Floor Empire State Plaza Albany, New York 12223
0 Mark II - NRC Meeting'roposed APR 2g )978 Agenda Livermore - A ril 5 1978 I. Livermore Fluid Structure Interaction Program A. SRV Study B. Chugging Study II. Submerged Structure Drag Loads A. NRC Questions B. DFFR Loads for Lead Plants San Jose - A ril 6, 197S I. Monticello SRY - Mark II Fluid Structure Interaction Studies
'I. Pool Temperature Limits NRC Review Status III. DFFR Lead Plant SRY Loads A. Philosophy B. Ramshead Model IV. 4T FSI - Mark II Program to Devise Chugging Impulse Load V. PSTF. Impact Load A. BNL Study B. Plant Target Characteristics
Lawrence Livermore Lab 4-5-78 Meeting Attendance NRC Nutech-MKI Owners K. S. Herring Abdel Hafiz N. W. Edwards T. M. Su Chris Grimes LLL C. Andes son G. S. Holman SSL S. C. Lu R. W. Martin C. N. Krishnawamy W. E. Mason Frank J. Tokarz Bechtel R. E. Koppe Moe Michail MIT Pa. Powers Li ht Com an Ain A. Sonin Peter Huber Howard W. Holland BNL SRI Chee Tung George Abrahamsen C. Economus R. Scanlan EPRI C. Bienkowski George Maise John Carey EG5G H. T. Tang C. Y. Liaw V. M. Healter R. J. Muzzy L. H. Srauenholz J. E. Rogers R. F. McClelland L. J. Sobon
APR g8 )g)8 Attendance List NRC/Mark II Owners Group April 6, 1978 Holiday Inn - San Jose, CA General Electric CGE A. R. Smith H. C. Brinkmann H. T. Tang J. R. Martin L. H. Frauenholz Pa. Power E Li ht Com an R. J. Muzzy L. J. Sobon Howard W. Holland R. E~ McClelland NSC NRC R. E. Koppe C. Anderson I. A. Peltier T. M. Su Bechtel C. I. Grimes A. Hafiz Jack Weyandt H. M. Schoenhoff D. M. O'onnor MIT P. W. Huber A. A. Sonin C. N. Krishna Swamy BNL LLL C. Tung C. Economos E. W. McCauley George Maise G. S. Holman R. H. Scanian R. Bienkowski
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