Letter Sequence Response to RAI |
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Results
Other: ML043000333, ML043210580, ML051650086, ML053630052, ML060180205, ML060890579, ML060940577, ML060940622, ML060950413, ML061020154, ML061020166, ML061090064, ML062830307, ML062830317, ML082530250, ML091830049, ML091980454, ML110680289, ML110680291
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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 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 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 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 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 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 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 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 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 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 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 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 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 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 ML13256A3642013-09-17017 September 2013 Nine Mile Point Nuclear Station, Unit Nos. 1 and 2, and R.E. Ginna Nuclear Power Plant - Acceptance of Requested Licensing Action Regarding Direct License Transfer (TAC MF2584 - MF2588) Project stage: Acceptance Review ML13269A3122013-10-0202 October 2013 Request for Withholding Information from Public Disclosure for Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2, Nine Mile Point Nuclear Station, Unit Nos. 1 and 2, and R.E. Ginna Nuclear Power Plant (TAC Nos. MF2584, MF2585, MF2586, M Project stage: Withholding Request Acceptance ML13294A0392013-11-0707 November 2013 Notice of Consideration of Approval of Transfer of Renewed Facility Operating Licenses and Conforming Amendments,.. Project stage: Other ML13337A3902013-12-0505 December 2013 Request for Additional Information Regarding Order Approving Direct Transfer of Renewed Facility Operating License and Conforming Amendments Project stage: RAI ML13294A0702013-12-18018 December 2013 Consideration of Approval of Transfer of Renewed Facility Operating Licenses, Materials Licenses, and Conforming Amendments Containing SUNSI Project stage: Request ML14050A3712014-02-0505 February 2014 Supplemental Response to Nrc'S Requests for Additional Information Regarding Application for Order Approving Transfer of Operating Authority and Conforming License Amendments Project stage: Supplement ML14063A1842014-03-25025 March 2014 Order Approving Direct Transfer of Renewed Operating Licenses and Conforming License Amendments Project stage: Other ML14106A0532014-03-25025 March 2014 Order Approving Direct Transfer of Renewed Operating Licenses and Conforming License Amendments Project stage: Acceptance Review ML14078A5942014-03-25025 March 2014 Enclosure 2 - Conforming Amendments to Nine Mile Point License Project stage: Other ML14078A6072014-03-25025 March 2014 Draft License Pages Project stage: Draft Other ML14091A3232014-04-0101 April 2014 Issuance of Amendments to Conform the Renewed Facility Operating Licenses and Materials License to Reflect the Direct Transfer of Operating Authority Project stage: Approval ML14105A1362014-05-0808 May 2014 Request for Withholding Information from Public Disclosure for Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2, Nine Mile Point Nuclear Station, Unit Nos. 1 and 2, and R.E. Ginna Nuclear Power Plant Project stage: Withholding Request Acceptance ML14148A1142014-07-16016 July 2014 Correction Letter - Correction to the Title Page of the Renewed Facility Operating License No. NPF-69 and Change in the Title Page of the Current License No. NPF-69 Project stage: Other 2006-04-04
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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
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Constellation Energy-Nine Mile Point Nuclear Station P.O. Box 63 Lycoming, NY 13093 January 11, 2006 NMP1L 2015 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Nine Mile Point Units 1 and 2 Docket Nos. 50-220 and 50-410 Facility Operating License Nos. DPR-63 and NPF-69 Amended License Renewal Application (ALRA) -Responses to NRC Requests for Additional Information
-Sections 3.4 and 4.7 (TAC Nos. MC3272 and MC3273)Gentlemen:
By letter dated July 14, 2005, Nine Mile Point Nuclear Station, LLC (NMPNS) submitted an Amended License Renewal Application (ALRA) for the operating licenses of Nine Mile Point Units 1 and 2.In a letter dated December 23, 2005, the NRC requested additional information regarding ALRA Sections 3.4 and 4.7.The NMPNS responses to these requests for additional information are provided in Attachment
- 1. Attachment 2 provides a resultant new regulatory commitment.
If you have any questions about this submittal, please contact David Dellario, NMPNS License Renewal Project Manager, at (315) 349-7141.
/Nine Mile Point TJO/MSL/sac
'8' (O q r t Page 2 NMP1L 2015 STATE OF NEW YORK :: TO WIT: COUNTY OF OSWEGO : I, Timothy J. O'Connor, being duly sworn, state that I am Vice President Nine Mile Point, and that I am duly authorized to execute and file these responses on behalf of Nine Mile Point Nuclear Station, LLC. To the best of my knowledge and belief, the statements contained in this submittal are true and correct. To the extent that these statements are not based on my personal knowledge, they are based upon information provided by other Nine Mile Point employees and/or consultants.
Such information has been reviewed in awcordance w company practice and I believe it to be reliable.Timothy O'Conn Vice r sident Nine Mile Point Subscribed and sworn before me, aNotary Public in and for the State of New York and County of Oswego, this I day of , 2006.WITNESS my Hand and Notarial Seal: No ubit of New Y6 Notary Public Commission Expires ataco My Commission Expires: soj2sl0o j lo')-5 lo9 Date Attachments:
- 1. Responses to NRC Requests for Additional Information
-ALRA Section 4.7.1 and Table 3.4.1.A 2. New regulatory commitment cc: Mr. S. J. Collins, NRC Regional Administrator, Region I Mr. L. M. Cline, NRC Senior Residenf Inspector Mr. T. G. Colburn, Senior Project Manager, NRR Mr. N. B. Le, License Renewal Project Manager, NRR Mr. J. P. Spath, NYSERDA ATTACHMENT 1 Responses to NRC Requests for Additional Information (RAIs) Regarding Amended License Renewal Application (ALRA) Section 4.7.1 and Table 3.4.1.A This attachment provides the Nine Mile Point Nuclear Station, LLC (NMPNS) responses to the RAIs contained in the NRC letter dated December 23, 2005. Each RAI is repeated, followed by the NMPNS response for Nine Mile Point Unit 1 (NMP1) and/or Nine Mile Point Unit 2 (NMP2), as applicable.
REACTOR PRESSURE VESSEL (RPV) BIOLOGICAL SHIELD -NMP UNIT 2 ONLY aRAI 4.7.1B-1 With respect to time-limited aging analyses (TLAA) 4.7.1 on the RPVBiological Shield, for NMP2, please provide a calculation using an NRC-approvedfluence methodology that will not invalidate your original fracture mechanics analysis (i.e., fluence will be less that IEI 7 n/cm 2). The methodology that is referred to in the amended LRA has not been reviewed and approved by the staff Otherwise, the applicant could submit a commitment indicating that the calculation/methodology will be submitted to the stafffor review and approval 2 years prior to the period of extended operation.
Response NMPNS will perform a fluence analysis for the period of extended operation (PEO) using plant specific methodology that is consistent with Reg. Guide 1.190. This methodology has been approved by the NRC as part of the NMP1 and NMP2 Pressure-Temperature Curve analysis review. The fluence analysis will establish whether or not the maximum fluence at the Biological Shield Wall or the fluence at the shield wall flaws, on which the ALRA Section 4.7.1 TLAA is based, is below the threshold value above which neutron embrittlement is considered to be an issue (1017 n/cm 2). NMPNS will submit the summary of this analysis to the NRC for review and approval no later than two years prior to entry into the PEO. Based on the results of this analysis, the submittal will also include revised ALRA Sections 4.7.1 and A2.2.5.1, and any other supporting analysis, as applicable.
ALRA Section A2.4 (ALRA p. A2-39) is revised to add new Item 39 as follows: ITEM COMMITMENT SOURCE SCHEDULE No later than two years prior to entry into the PEO, NMP will submit, for NRC review and approval, the summary of the Reg. Guide 1.190 based analysis that determines the LRA Section 4.7.1 maximum neutron fluence at the NMP2 Biological Shield and Appendix October 31,2024 Wall or at the shield wall flaw locations that are the basis A2.2.5. 1 for the ALRA Section 4.7.1 TLAA. The submittal will include revised ALRA Sections 4.7.1 and A2.2.5.1, and any other supporting analysis, as applicable.
1 of 2 i i TABLE 3.4.1.A AGING MANAGEMENT PROGRAM FOR STEAM AND POWER CONVERSION SYSTEMS aRAI 3.4.1.A-1 In the NMPALRA Table 3.4.JLA Items 3.4.J.A-09 and 3.4.J.A-10, the applicant states that these items are not applicable because "All other heat exchangers are of a different material (copper alloys or stainless steel) and do not have this aging effect/mechanism.
" However, both copper alloy and stainless steel are subjected to the aging effects of pitting and crevice corrosion.
Please explain the discrepancy provided under the discussion columns of the table.Response NMPNS has reviewed the in-scope heat exchangers in the NMP1 and NMP2 Steam and Power Conversion Systems and concluded that none are cooled by open or closed-cycle cooling water systems. Additionally, since neither Item 3.4.1.A-09, Item 3.4.1.A-10, Item 3.4.1.B-09, nor Item 3.4.1.B-10 is included as a "Table 1 Item" column entry in any of the ALRA Type 2 ("Summary of Aging Management Evaluation")
Tables, the"Discussion" column entries for these four (4) Table 3.4.1.A/B Items should be revised.The "Discussion" column entries for Items 3.4.1.A-09 and 3.4.1.A-10 (ALRA pp. 3.4-24 and -25) are, therefore, revised to read as follows: "Not applicable for the following reasons:* The NMP1 condenser hotwell is evaluated in Item 3.4.1.A-02.
- These components are not subject to an AMR in the NMP1 Steam and Power Conversion Systems." The "Discussion" column entries for Items 3.4.1.B-09 and 3.4.1.B-10 (ALRA pp. 3.4-27 and -28) are revised to read as follows: "Not applicable for the following reasons:* The NMP2 condenser hotwell is evaluated in Item 3.4.1.B-02.
- These components are not subject to an AMR in the NMP2 Steam and Power Conversion Systems." 2 of 2 4A I ATTACHMENT 2 The following table identifies an action committed to by Nine Mile Point Nuclear Station, LLC in this document.
Any other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments.
ALRA ALRA Commitment Text New or Due Date Section Commitment
- Revised No later than two years prior to entry into the PEO, NMP will submit, for NRC review and approval, the summary of the Reg. Guide 1.190 based analysis that determines the maximum A2.4 39 neutron fluence at the NMP2 Biological Shield New October.Wall or at the wall flaw locations that are the 31,2024 basis for the ALRA Section 4.7.1 TLAA. The submittal will include revised ALRA Sections 4.7.1 and A2.2.5.1, and any other supporting analysis, as applicable.
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