Letter Sequence RAI |
---|
|
Results
Other: ML043000333, ML043210580, ML051650086, ML053630052, ML060180205, ML060890579, ML060940577, ML060940622, ML060950413, ML061020154, ML061020166, ML061090064, ML062830307, ML062830317, ML082530250, ML091830049, ML091980454, ML110680289, ML110680291
|
MONTHYEARML0414902132004-05-26026 May 2004 Transmittal of Nine Mile Point Units 1 & 2 Application for Renewed Operating Licenses, Including Environmental Report Project stage: Request 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. Project stage: Other ML0432105802004-11-15015 November 2004 Audit and Review Plan for Plant Aging Management Reviews and Programs for the Nine Mile Point Nuclear Station, Units 1 and 2 (TAC Nos MC3272 and MC3273.) Project stage: Other ML0504601382005-02-14014 February 2005 Summary of a Conference Call Between the U.S. Nuclear Regulatory Commission and the Constellation Energy Group Inc. Concerning the Review of the Nine Mile Point Nuclear Station, Units 1 and 2 Project stage: Approval ML0516500862005-06-0909 June 2005 Presentation Slides, Nine Mile Point, Units 1 and 2, LRA Status Update Project stage: Other ML0516704462005-06-16016 June 2005 Summary of Meeting Held on June 9, 2005, Between the U.S. Nuclear Regulatory Commission (NRC) Staff and the Constellation Energy Group, Inc. Representatives to Discuss the Status of Their Recovery Effort, Nine Mile Point Nuclear Station, Un Project stage: Meeting ML0529702752005-10-20020 October 2005 E-mail from Ngoc Le of NRC to David Dellario Regarding the Audit and Review Plan for Plant Aging Management Programs and Reviews for Nine Mile Point Nuclear Station, Units 1 and 2 Project stage: Acceptance Review ML0536300522005-12-13013 December 2005 License Renewal Application (LRA) - Editorial Changes to Letter NMP1L 2005 and NMP1L 2007 Project stage: Other ML0601301972006-01-11011 January 2006 Amended License Renewal Application - Responses to NRC Requests for Additional Information - Sections 3.4 and 4.7 Project stage: Response to RAI ML0602200092006-01-18018 January 2006 Summary of Meeting with the Constellation Energy Group Inc. to Discuss Results of the Staff Audit of the Aging Management Programs and Reviews for Nine Mile Point, Units 1 and 2 Project stage: Meeting ML0601802052006-01-18018 January 2006 1/18/06 - Audit and Review Report for the Nine Mile Point Nuclear Station, Units 1 and 2, Amended License Renewal Application (TAC Nos. MC3272 and MC3273 Project stage: Other ML0605807562006-03-0303 March 2006 Transmittal Letter - Safety Evaluation Report for the Nine Mile Point Nuclear Station, Units 1 and 2, License Renewal Application Project stage: Approval ML0605807582006-03-0303 March 2006 Safety Evaluation Report for the Nine Mile Point Nuclear Station, Units 1 and 2, License Renewal Application Project stage: Approval ML0609504132006-03-23023 March 2006 SER Open Item 4.7B.1-1 and Closure of Amended License Renewal Application (Alra) Section A2.4, Commitment 39 - Biological Shield Wall Neutron Fluence Analysis Project stage: Other ML0609406222006-03-29029 March 2006 Email (3/29/06) from Peter Mazzaferro to Ngoc (Tommy) B. Le NMP2 Bioshield Fluence Calc Info Project stage: Other ML0608905792006-03-29029 March 2006 01/23/2006 Summary of a Telephone Conference Call Held Between the U.S. Nuclear Regulatory Commission and the Constellation Energy Group, Inc. Concerning the Review for the Nine Mile Point, Units 1 & 2, License Renewal Application Project stage: Other ML0610201662006-04-0303 April 2006 Safety Evaluation Report with Open Items Related to the License Renewal of Nine Mile Point, Dated March 2006 - NMPNS Comments (TAC Nos. MC3272 and MC3273) Project stage: Other ML0609405772006-04-0404 April 2006 Note to File - Docketing of Additional Information Pertaining to License Renewal Application of the Nine Mile Point Nuclear Station, Units 1 and 2 (TAC Nos. MC3272 and MC3273) Project stage: Other ML0610201542006-04-0404 April 2006 Safety Evaluation Report (Ser), with Open Items Related to the License Renewal Dated March 2006 - SER Open Item 3.0.3.2.17-1 Project stage: Other ML0610900642006-04-18018 April 2006 Note to File - Docketing of Additional Information Pertaining to License Renewal Application of the Nine Mile Point Nuclear Station, Units 1 and 2 (TAC No'S. MC3272 and MC3273) Project stage: Other ML0610901062006-04-19019 April 2006 Request for Additional Information, Review of Nine Mile Point Nuclear Station, Units 1 and 2, License Renewal Application (TAC Nos. MC3272 and MC3273) Project stage: RAI ML0612205952006-04-21021 April 2006 Amended License Renewal Application - NRC Request for Additional Information (RAI) 4.7.5. A-1 Project stage: Request ML0611802422006-06-0101 June 2006 Ltr to Timothy O' Connor - Final Safety Evaluation Report Related to the License Renewal of the Nine Mile Point Nuclear Station, Units 1 and 2 (TAC Nos. MC3272 and MC3273) Project stage: Approval ML0614603132006-06-0101 June 2006 Safety Evaluation Report Related to the License Renewal of the Nine Mile Point Nuclear Station, Units 1 and 2 (TAC Nos. MC3272 and MC3273) Project stage: Approval ML0619800502006-07-13013 July 2006 03/27/2006 Summary of Meeting Between U.S. Nuclear Regulatory Commission Staff & Constellation Energy Group Inc. Representatives to Discuss Status of Open Item 3.0.3.2.17-1 for Nine Mile Point Nuclear Station, Units 1 & 2, License Renewal A Project stage: Meeting ML0628303072006-10-31031 October 2006 LLC Docket No. 50-220 Nine Mile Point Nuclear Station, Unit 1 Renewed Facility Operating License Renewed License No. DPR-63 Project stage: Other ML0628303172006-10-31031 October 2006 LLC Docket No. 50-410 Nine Mile Point Nuclear Station, Unit 2 Renewed Facility Operating License Renewed License No. NPF-69 Project stage: Other ML0628304332006-10-31031 October 2006 Federal Register Notice for Nine Mile Point Nuclear, LLC Nine Mile Point Nuclear Station Units 1 and 2, Notice of Issuance of Renewed Facility Operating License Nos. DPR-63 and NPF-69 for an Additional 20-Year Period Project stage: Approval ML0628302732006-10-31031 October 2006 Issuance of Renewed Facility Operating License Nos. DPR-63 and NPF-69 for the Nine Mile Point Nuclear Station, Units 1 and 2 Project stage: Approval ML0825302502008-08-29029 August 2008 Request to Utilize an Alternative to the Requirements of 10 CFR 50.55a(g) for the Repair and Inservice Inspection of Control Rod Drive Stub Tubes for the License Renewal Period of Extended Operation Project stage: Other ML0907101082009-03-17017 March 2009 Request for Additional Information, Alternative for the Repair and Inservice Inspection of Control Rod Drive Stub Tubes for the License Renewal Period of Extended Operation Project stage: RAI ML0914104472009-05-14014 May 2009 Request to Utilize an Alternative to the Requirements of 10 CFR 50.55a(g) for the Repair and Inservice Inspection of Control Rod Drive Stub Tubes for the License Renewal Period of Extended Operation - Response to NRC Request for Additional Project stage: Request ML0918300492009-06-25025 June 2009 Request to Utilize an Alternative to the Requirements of 10 CFR 50.55a(g) for the Repair & Inservice Inspection of Control Rod Drive Stub Tubes for the License Renewal Period of Extended Operation - Response. Project stage: Other ML0919804542009-08-0303 August 2009 Request to Utilize Alternative of Applying ASME Code Case 730 for Repair and ISI of Control Rod Drive Bottom Head Penetrations for the License Renewal Period of Extended Operation Project stage: Other ML1106802892011-03-0404 March 2011 Areva Calculation No. 32-9138066-000, NMP-1 CRD Housing Idtb Weld Anomaly Analysis. (Non-Proprietary) Project stage: Other ML1106802912011-03-0404 March 2011 Request to Utilize an Alternative to the Requirements of 10CFR50.55a(g) for Repair of Control Rod Drive Housing Penetrations for the Remainder of License Renewal Period of Extended Operation Project stage: Other 2006-03-03
[Table View] |
|
---|
Category:Letter
MONTHYEARNMP1L3570, Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-02-0101 February 2024 Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation 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 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 IR 05000410/20243012023-12-14014 December 2023 Initial Operator Licensing Examination Report 05000410/2024301 ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 NMP1L3564, Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements2023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements ML23291A4642023-12-0707 December 2023 Issuance of Amendment No. 251 Regarding the Adoption of Title 10 the Code of Federal Regulations Section 50.69, Risk-Informed Categorization and Treatment of SSC for Nuclear Power Plants ML23289A0122023-12-0606 December 2023 Issuance of Amendment No. 250 Regarding the Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - 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 IR 05000220/20234202023-11-0101 November 2023 Security Baseline Inspection Report 05000220/2023420 and 05000410/2023420 ML23305A0052023-11-0101 November 2023 Operator Licensing Examination Approval 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 NMP2L2851, Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations2023-08-25025 August 2023 Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations ML23151A3472023-08-21021 August 2023 Issuance of Amendments to Adopt TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration NMP1L3534, License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2023-08-18018 August 2023 License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation ML23220A0262023-08-0808 August 2023 Licensed Operator Positive Fitness-for-Duty Test IR 05000220/20234012023-08-0808 August 2023 Cyber Security Inspection Report 05000220/2023401 and 05000410/2023401 (Cover Letter Only) 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 . RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023 Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor IR 05000220/20230022023-08-0101 August 2023 Integrated Inspection Report 05000220/2023002 and 05000410/2023002 ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 NMP1L3544, Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations2023-07-14014 July 2023 Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations ML23186A1642023-07-0606 July 2023 Operator Licensing Retake Examination Approval NMP2L2846, Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications2023-07-0505 July 2023 Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications ML23192A0622023-06-30030 June 2023 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance, Report No. 10CFR21-0136, Rev. 0 IR 05000220/20230102023-06-29029 June 2023 Biennial Problem Identification and Resolution Inspection Report 05000220/2023010 and 05000410/2023010 ML23131A4242023-06-23023 June 2023 Issuance of Amendment No. 249 Regarding the Revision to Technical Specification 3.3.1 to Adopt Technical Specifications Task Force Traveler TSTF-568 RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations NMP1L3539, Day Commitment Response - Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-06-0909 June 2023 Day Commitment Response - Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling IR 05000410/20233022023-05-15015 May 2023 Initial Operator Licensing Examination Report 05000410/2023302 2024-02-01
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23264A7992023-09-21021 September 2023 NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC Fleet Request License Amendment Request to Adopt TSTF-580, Revision 1 ML23205A2432023-07-19019 July 2023 NRC Staff Follow-up Question on Audit Question 18 TSTF-505 and 50.69 Regulatory Audit (E-mail Dated 7/19/2023) (EPIDs L-2022-LLA-0185 and L-2022-LLA-0186) ML23087A2912023-03-28028 March 2023 Request for Additional Information (3/28/2023 E-mail) - Proposed Emergent I5R-11 Alternative Associated with a Weld Overlay on RPV Recirculation Nozzle N2E DM Weld ML23061A0522023-03-0202 March 2023 Request for Additional Information (3/2/2023 E-mail) - Proposed Alternative Associated with a Weld Overlay Repair to the Torus ML23012A2002023-01-13013 January 2023 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000220/2023401 and 05000410/2023401 ML22207A2162022-07-26026 July 2022 Information Request to Support Triennial Baseline Design-Basis Capability of Power-Operated Valves Inspection; Inspection Report 05000220/2022010 and 05000410/2022010 ML22194A9412022-07-13013 July 2022 Request for Additional Information Relief Request CS-PR-02 (7/13/2022 e-mail) ML22041B5362022-02-10010 February 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Request for Additional Information Regarding Fleet License Amendment Request to Adopt TSTF-541 ML22020A0642022-01-13013 January 2022 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative for Repair of Water Level Instrumentation Partial Penetration Nozzles ML21320A3472021-11-16016 November 2021 Request for Additional Information LAR to Revise TSs to Adopt TSTF-582, Revision 0 ML21306A3312021-11-0202 November 2021 Request for Additional Information Alternative Request GV-RR-10 (11/2/2021 e-mail) ML21256A1902021-09-10010 September 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21144A2132021-05-24024 May 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21117A0342021-05-0505 May 2021 Request for Additional Information Regarding Proposed Alternative to Use ASME Code Case N-893 ML21125A1282021-05-0404 May 2021 OPC Document Request - Feb 2021 ML21110A5112021-04-20020 April 2021 Request for Additional Information Review of License Amendment Request to Revise Technical Specifications to Adopt TSTF-582 ML21088A2682021-03-30030 March 2021 Notification of Conduct of a Fire Protection Team Inspection ML21062A0652021-03-0101 March 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative to Documentation Requirements for Pressure Retaining Bolting ML21049A2572021-02-18018 February 2021 Request for Additional Information Byron/Dresden Proposed Changes to Site Emergency Plans to Support Post-Shutdown and Permanently Defueled Conditions (EPID-2020-LLA-0240 & EPID-2020-LLA-0237) ML20365A0092020-12-30030 December 2020 Request for Additional Information Concerning Review of License Amendment Request and Relief Request to Change Excess Flow Check Valve Testing Frequency (EPIDs L-2020-LLA-0188 and L-2020-LLR-0114) ML20358A2602020-12-28028 December 2020 Changes to Draft Request for Additional Information Regarding License Amendment Request and Relief Request to Change Excess Flow Check Valve Testing Frequency ML20272A2802020-09-28028 September 2020 Withdrawal and Replacement of Request for Additional Information to Support Review of License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times ML20248H5192020-09-28028 September 2020 Changes to Draft Request for Additional Information Regarding Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times ML20246G6362020-09-0202 September 2020 Request for Additonal Information to Support Review of License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times NMP2L2739, 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 22020-08-28028 August 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 ML20239A7982020-08-25025 August 2020 NRR E-mail Capture - Exelon Generation Company, LLC - Fleet License Amendment Request to Adopt TSTF-568, Revision 2 ML20212L8702020-07-30030 July 2020 Request for Additonal Information Review of License Amendment Requests Regarding Riskinformed Categorization and Treatment of Structures, Systems and Components (L-2019-LLA-0290) ML20213A9352020-07-30030 July 2020 Request for Additional Information Review of License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times ML20153A7042020-06-0101 June 2020 NRR E-mail Capture - Preliminary RAI for Fleet Request to Use Alternative OMN-26 ML20135H1972020-05-14014 May 2020 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Request to Extend Safety Relief Valve Test Interval ML20045E3582020-02-14014 February 2020 Draft Request for Additional Information Regarding License Amendment Request to Increase Allowable MSIV Leakage Rates ML19296A1862019-10-23023 October 2019 Request for Additional Information Regarding License Amendment Request to Increase Allowable MSIV Leakage Rates (L-2019-LLA-0115) ML19275H1362019-10-0202 October 2019 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Request to Use ASME Code Case N-879 ML19179A0612019-07-19019 July 2019 Three Mile Point 1 - Supplemental Information Needed to Proposed Alternative to Use ASME Code Case N-879 ML19151A8132019-05-31031 May 2019 Licensed Operator Positive Fitness-For-Duty Test ML19025A1572019-01-25025 January 2019 Request for Additional Information Regarding Primary Containment Oxygen Concentration License Amendment Request ML19025A1202019-01-24024 January 2019 NRR E-mail Capture - Calvert Cliffs, Fitzpatrick, and Nine Mile Point - Request for Additional Information Regarding License Amendment Request to Revise Emergency Response Organization Staffing ML18341A2212018-12-0707 December 2018 Request for Additional Information Regarding Emergency Tech Spec Change Re HPCS Completion Time (EPID -L-2018-LLA-0491) ML18228A6932018-08-15015 August 2018 Request for Additional Information Regarding Reactor Pressure Vessel Water Inventory Control License Amendment Request (L-2017-LLA-0426) ML18205A3922018-07-24024 July 2018 Request for Additional Information Regarding Reactor Pressure Vessel Water Inventory Control License Amendment Request (L-2017-LLA-0426) ML18184A2882018-07-0303 July 2018 Request for Additional Information Regarding Removal of Boraflex Credit from Spent Fuel Pool License Amendment Request(L-2018-LLA-0039) ML18102A2372018-04-12012 April 2018 NRR E-mail Capture - Calvert Cliffs, Ginna, and Nine Mile Point - Request for Additional Information Regarding License Amendment Request to Revise Emergency Action Level Schemes (EPID-L-2017-LLA-0237) ML17331B1342017-12-12012 December 2017 2, and R.E. Ginna Nuclear Power Plant - Request for Additional Information - Regarding ML17285B1962017-10-27027 October 2017 Request for Additional Information Regarding Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools. ML17272A0112017-10-10010 October 2017 Request for Additional Information Regarding License Amendment Concerning Reactor Pressure Vessel Water Inventory Control ML17234A3592017-08-30030 August 2017 Request for Additional Information Regarding Relief Request NMP-RR-001 to Utilize Code Case N-702 ML17241A2752017-08-29029 August 2017 Request for Additional Information Response MSA (MF7946,7) and FE (MG0087,8) E-mail Attachment ML17240A3102017-08-15015 August 2017 NRR E-mail Capture - Nine Mile Point MSA and FE RAI ML17172A0842017-06-27027 June 2017 Request for Additional Information Regarding Relief Request to Utilize ASME Code Case N-702 ML17065A1622017-03-14014 March 2017 Request for Additional Information Regarding Proposed Alternative to Perform Pressure Isolation Valve Leakage Testing at Frequencies Consistent with 10 CFR Part 50, Appendix J 2023-09-21
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 17,2009 Mr. Keith J. Polson Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P.O. Box 63 Lycoming, NY 13093
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING NINE MILE POINT NUCLEAR STATION, UNIT NO.1, ALTERNATIVE FOR THE REPAIR AND INSERVICE INSPECTION OF CONTROL ROD DRIVE STUB TUBES FOR THE LICENSE RENEWAL PERIOD OF EXTENDED OPERATION (TAC NO. MD9604)
Dear Mr. Polson:
By letter dated August 29, 2008, Nine Mile Point Nuclear Station, LLC, submitted for Nuclear Regulatory Commission (NRC) staff review and approval, Relief Request 11SI-02 for Nine Mile Point Unit No.1 (NMP1). The relief request would allow the use of American Society of Mechanical Engineers, Boiler and Pressure Vessel Code (ASME Code),Section XI, Code Case N-730, "Roll-Expansion of Class 1 Control Rod Drive [CRD] Bottom Head Penetrations in BWRs," as an alternative permanent repair for CRD housing penetrations that may exhibit leakage during the license renewal period of extended operation (Le., from August 23, 2009 to August 22, 2029) or for the re-roll expansion of any previously roll expanded CRD housing that exhibits a repeat occurrence of leakage.
The NRC staff is reviewing the submittal and has determined that additional information is needed to support its review. Enclosed is the NRC staff's request for additional information (RAI). The RAI was discussed with your staff on February 3 and 19, 2009, and it was agreed that your response would be provided within 60 days from the date of this letter.
Sincerely, Richard V. Guzman, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-220
Enclosure:
RAI cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION NINE MILE POINT NUCLEAR STATION, UNIT NO.1 REQUEST TO UTILIZE AN ALTERNATIVE FOR THE REPAIR AND INSERVICE INSPECTION OF CONTROL ROD DRIVE STUB TUBES FOR THE LICENSE RENEWAL PERIOD OF EXTENDED OPERATION DOCKET NO. 50-220 The Nuclear Regulatory Commission (NRC) staff is reviewing the Nine Mile Point Nuclear Station (NMPNS or the licensee) submittal for Nine Mile Point Unit NO.1 (NMP1) dated August 29, 2008. The NRC staff has determined that additional information requested below will be needed to support its review.
In its proposed alternative for repair of control rod drive stub tubes, the licensee requested in Alternative 1A to apply the American Society of Mechanical Engineers, Boiler and Pressure Vessel Code (ASME Code),Section XI, Code Case N-730, "Roll-Expansion of Class 1 Control Rod Drive [CRD] Bottom Head Penetrations in BWRs." In Alternative 2A, the licensee requested to apply ASME Code,Section XI, Code Case N-730, but with the exception to perform the post-roll expansion VT-2 examination at approximately 900 pounds-per-square inch (psig) prior to returning NMP1 to full power operation. ASME Code Case N-730 requires a post repair leakage test at the operating pressure. As the basis for the proposed alternatives (1A and 2A), the submittal references both Title 10 to Code of Federal Regulations (10 CFR),
Section 50.55a(a)(3)(i) related to demonstrating an acceptable level of quality and safety as well as Section 50.55a(a)(3)(ii) related to demonstrating hardship. Please clarify which regulatory basis is being applied for each alternative when responding to the questions below.
RAI-1. For proposed Alternative 1A, provide additional basis for using ASME Code Case N-730 instead of the ASME Code,Section XI, requirements by addressing the 4 considerations of the evaluation stated in Section 5 of the ASME Code Case N-730. If a generic evaluation is available, demonstrate that the generic evaluation is applicable to NMP1.
RAI-2. For proposed Alternative 2A, provide the basis for using ASME Code Case N-730 with the exception of performing a leakage test at 900 psig, instead of the ASME Code,Section XI, requirements. If 10 CFR 50.55a(a)(3)(ii) is the applicable regulatory basis, as discussed during the teleconference between NRC and licensee staff on February 19, 2009, provide a more detailed justification to support your use of 10 CFR 50.55a(a)(3)(ii) and, in particular, the following referenced items in your original submittal:
- Basis for Relief (ii) states, "[i]nspections of CRD stub tubes for leakage durlnq a system leakage test at the nominal operating pressure (-1030 psiq) associated with 100% rated reactor power cannot be performed during a normal plant startup, Enclosure
- 2 due to the excessive temperature and radiological exposure conditions to which the NDE [nondestructive examination] examiners performing the visual VT-2 examinations would be exposed in the primary containment." Provide justification to support this statement as a hardship.
- Basis for Relief (iii) states, "[tlhls special test usually takes one full day of plant outage time, and the additional valve lineups and system reconfigurations necessary to support this special test impose an additional challenge to the affected systems." Provide justification to support this statement as a hardship.
March 17, 2009 Mr. Keith J. Polson Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P.O. Box 63 Lycoming, NY 13093
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING NINE MILE POINT NUCLEAR STATION, UNIT NO.1, ALTERNATIVE FOR THE REPAIR AND INSERVICE INSPECTION OF CONTROL ROD DRIVE STUB TUBES FOR THE LICENSE RENEWAL PERIOD OF EXTENDED OPERATION (TAC NO. MD9604)
Dear Mr. Polson:
By letter dated August 29, 2008, Nine Mile Point Nuclear Station, LLC, submitted for Nuclear Regulatory Commission (NRC) staff review and approval, Relief Request 11SI-02 for Nine Mile Point Unit NO.1 (NMP1). The relief request would allow the use of American Society of Mechanical Engineers, Boiler and Pressure Vessel Code (ASME Code),Section XI, Code Case N-730, "Roll-Expansion of Class 1 Control Rod Drive [CRD] Bottom Head Penetrations in BWRs," as an alternative permanent repair for CRD housing penetrations that may exhibit leakage during the license renewal period of extended operation (Le., from August 23, 2009 to August 22, 2029) or for the re-roll expansion of any previously roll expanded CRD housing that exhibits a repeat occurrence of leakage.
The NRC staff is reviewing the submittal and has determined that additional information is needed to support its review. Enclosed is the NRC staff's request for additional information (RAI). The RAI was discussed with your staff on February 3 and 19, 2009, and it was agreed that your response would be provided within 60 days from the date of this letter.
Sincerely, IRA!
Richard V. Guzman, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-220
Enclosure:
RAI cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC RidsNrrPMRGuzman RidsNrrLASLittle RidsNrrDorlLpl1-1 Resource LPLI-1 R/F RidsRgn1 MailCenter RidsOGCRp RidsNrrAcrsAcnw&mMailCenter SSheng RidsNrrDciCvib Resource Accession No.: ML090710108 *RAI Wit. h concurrence provt'dedbiv e-man. . I chanqes rnade. NRR058 "I No su bst antia OFFICE LPLI-1/PM LPLI-1/LA CVIB/BC LPLI-1/BC NAME RGuzman MO'Brien for SLittle* MMitchell* MKowal DATE 3/12/09 3/12/09 3/12/09 3/17/09 OFFICIAL RECORD COpy