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| {{#Wiki_filter:February 26, 2007Mr. Timothy J. O'ConnorVice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P. O. Box 63 Lycoming, NY 13093 | | {{#Wiki_filter:February 26, 2007 Mr. Timothy J. OConnor Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P. O. Box 63 Lycoming, NY 13093 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| REQUEST FOR ADDITIONAL INFORMATION REGARDING NINE MILE POINTNUCLEAR STATION, UNIT NO. 2, INSERVICE INSPECTION REQUEST FOR RELIEF NO. 2ISI-001 (TAC NO. MD3696) | | REQUEST FOR ADDITIONAL INFORMATION REGARDING NINE MILE POINT NUCLEAR STATION, UNIT NO. 2, INSERVICE INSPECTION REQUEST FOR RELIEF NO. 2ISI-001 (TAC NO. MD3696) |
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| ==Dear Mr. O'Connor:== | | ==Dear Mr. OConnor:== |
| By letter dated November 16, 2006, Nine Mile Point Nuclear Station, LLC requested NuclearRegulatory Commission (NRC) approval of proposed Request for Relief Number 2ISI-001 forNine Mile Point Unit 2 (NMP2). The request is for permanent relief from the inservice inspection requirements of Title 10 of the Code of Federal Regulations, Part 50, Section50.55a(g) for the volumetric examination of reactor pressure vessel shell circumferential welds for the remaining license period and the license renewal period of extended operation for NMP2.The NRC staff has reviewed the information provided in your request and has determined thatadditional information is needed to complete its review. Enclosed is the NRC staff's request for additional information (RAI). The RAI was discussed with your staff on February 1, 2007, and it was agreed that your response would be provided within 60 days from the date of this letter.Sincerely,/RA/Douglas V. Pickett, Senior Project ManagerPlant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-410 | | |
| | By letter dated November 16, 2006, Nine Mile Point Nuclear Station, LLC requested Nuclear Regulatory Commission (NRC) approval of proposed Request for Relief Number 2ISI-001 for Nine Mile Point Unit 2 (NMP2). The request is for permanent relief from the inservice inspection requirements of Title 10 of the Code of Federal Regulations, Part 50, Section 50.55a(g) for the volumetric examination of reactor pressure vessel shell circumferential welds for the remaining license period and the license renewal period of extended operation for NMP2. |
| | The NRC staff has reviewed the information provided in your request and has determined that additional information is needed to complete its review. Enclosed is the NRC staffs request for additional information (RAI). The RAI was discussed with your staff on February 1, 2007, and it was agreed that your response would be provided within 60 days from the date of this letter. |
| | Sincerely, |
| | /RA/ |
| | Douglas V. Pickett, Senior Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-410 |
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| ==Enclosure:== | | ==Enclosure:== |
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| RAIcc w/encl: See next page February 26, 2007Mr. Timothy J. O'ConnorVice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P. O. Box 63 Lycoming, NY 13093
| | RAI cc w/encl: See next page |
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| | February 26, 2007 Mr. Timothy J. OConnor Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P. O. Box 63 Lycoming, NY 13093 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| REQUEST FOR ADDITIONAL INFORMATION REGARDING NINE MILE POINTNUCLEAR STATION, UNIT NO. 2, INSERVICE INSPECTION REQUEST FOR RELIEF NO. 2ISI-001 (TAC NO. MD3696) | | REQUEST FOR ADDITIONAL INFORMATION REGARDING NINE MILE POINT NUCLEAR STATION, UNIT NO. 2, INSERVICE INSPECTION REQUEST FOR RELIEF NO. 2ISI-001 (TAC NO. MD3696) |
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| | ==Dear Mr. OConnor:== |
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| ==Dear Mr. O'Connor:==
| | By letter dated November 16, 2006, Nine Mile Point Nuclear Station, LLC requested Nuclear Regulatory Commission (NRC) approval of proposed Request for Relief Number 2ISI-001 for Nine Mile Point Unit 2 (NMP2). The request is for permanent relief from the inservice inspection requirements of Title 10, Part 50, of the Code of Federal Regulations, Section 50.55a(g) for the volumetric examination of reactor pressure vessel shell circumferential welds for the remaining license period and the license renewal period of extended operation for NMP2. |
| By letter dated November 16, 2006, Nine Mile Point Nuclear Station, LLC requested NuclearRegulatory Commission (NRC) approval of proposed Request for Relief Number 2ISI-001 forNine Mile Point Unit 2 (NMP2). The request is for permanent relief from the inservice inspection requirements of Title 10, Part 50, of the Code of Federal Regulations , Section50.55a(g) for the volumetric examination of reactor pressure vessel shell circumferential welds for the remaining license period and the license renewal period of extended operation for NMP2.The NRC staff has reviewed the information provided in your request and has determined thatadditional information is needed to complete its review. Enclosed is the NRC staff's request for additional information (RAI). The RAI was discussed with your staff on February 1, 2007, and it was agreed that your response would be provided within 60 days from the date of this letter.Sincerely,/RA/Douglas V. Pickett, Senior Project ManagerPlant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-410 | | The NRC staff has reviewed the information provided in your request and has determined that additional information is needed to complete its review. Enclosed is the NRC staffs request for additional information (RAI). The RAI was discussed with your staff on February 1, 2007, and it was agreed that your response would be provided within 60 days from the date of this letter. |
| | Sincerely, |
| | /RA/ |
| | Douglas V. Pickett, Senior Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-410 |
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| ==Enclosure:== | | ==Enclosure:== |
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| RAIcc w/encl: See next pageDISTRIBUTION
| | RAI cc w/encl: See next page DISTRIBUTION: |
| :PUBLICRidsNrrPMDPickettRidsNrrLASLittleLPLI-1PDI-1 Reading FileMDavidRidsOgcRpRidsNrrAdesDciCvibRidsNrrAcrsAcnwMailCenterAccession Number: ML070380152NRR-088OFFICELPL1-1/PELPL1-1/PMLPL1-1/LACVIB/BCLPL1-1/BC(A)NAMEMDavidDPickettSLittleMMitchellJBoskaDATE2/22/072/23/072/22/072/23/072/26/07OFFICIAL RECORD COPY Nine Mile Point Nuclear Station cc:
| | PUBLIC RidsNrrPMDPickett RidsNrrLASLittle LPLI-1 PDI-1 Reading File MDavid RidsOgcRp RidsNrrAdesDciCvib RidsNrrAcrsAcnwMailCenter Accession Number: ML070380152 NRR-088 OFFICE LPL1-1/PE LPL1-1/PM LPL1-1/LA CVIB/BC LPL1-1/BC(A) |
| Mr. Michael J. WallacePresident Nine Mile Point Nuclear Station, LLC c/o Constellation Energy Group 750 East Pratt Street Baltimore, MD 21202Mr. Mike HeffleySenior Vice President and Chief Nuclear Officer Constellation Generation Group 1997 Annapolis Exchange Parkway Suite 500 Annapolis, MD 21401Regional Administrator, Region IU.S. Nuclear Regulatory Commission | | NAME MDavid DPickett SLittle MMitchell JBoska DATE 2/22/07 2/23/07 2/22/07 2/23/07 2/26/07 OFFICIAL RECORD COPY |
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| | Nine Mile Point Nuclear Station cc: |
| | Mr. Michael J. Wallace Mark J. Wetterhahn, Esquire President Winston & Strawn Nine Mile Point Nuclear Station, LLC 1700 K Street, NW c/o Constellation Energy Group Washington, DC 20006 750 East Pratt Street Baltimore, MD 21202 Supervisor Town of Scriba Mr. Mike Heffley Route 8, Box 382 Senior Vice President and Chief Oswego, NY 13126 Nuclear Officer Constellation Generation Group Carey W. Fleming, Esquire 1997 Annapolis Exchange Parkway Senior Counsel Suite 500 Constellation Generation Group, LLC Annapolis, MD 21401 750 East Pratt Street, 17th Floor Baltimore, MD 21202 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 126 Lycoming, NY 13093 Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271 Mr. Paul D. Eddy Electric Division NYS Department of Public Service Agency Building 3 Empire State Plaza Albany, NY 12223 Mr. Peter R. Smith, President New York State Energy, Research, and Development Authority 17 Columbia Circle Albany, NY 12203-6399 |
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| 475 Allendale Road King of Prussia, PA 19406Resident InspectorU.S. Nuclear Regulatory Commission P.O. Box 126 Lycoming, NY 13093Charles Donaldson, EsquireAssistant Attorney General New York Department of Law 120 Broadway New York, NY 10271Mr. Paul D. EddyElectric Division NYS Department of Public Service Agency Building 3 Empire State Plaza Albany, NY 12223Mr. Peter R. Smith, PresidentNew York State Energy, Research, and Development Authority 17 Columbia Circle Albany, NY 12203-6399Mark J. Wetterhahn, EsquireWinston & Strawn 1700 K Street, NW Washington, DC 20006SupervisorTown of Scriba Route 8, Box 382 Oswego, NY 13126Carey W. Fleming, EsquireSenior Counsel Constellation Generation Group, LLC 750 East Pratt Street, 17th Floor Baltimore, MD 21202 EnclosureREQUEST FOR ADDITIONAL INFORMATIONNINE MILE POINT NUCLEAR STATION, UNIT NO. 2REQUEST FOR RELIEF NO. 2ISI-001By letter dated November 16, 2006, Nine Mile Point Nuclear Station, LLC (the licensee)submitted Request for Relief (RR) No. 2ISI-001 for Nine Mile Point Unit 2 (NMP2) requesting analternative to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), Section XI, Table IWB-2500-1, Category B-A, Item Number B1.11, reactor pressure vessel (RPV) circumferential shell welds inspection requirements. RR No. 2ISI-001 is for the second 10-year inservice inspection (ISI) interval, in which NMP2 adopted the 1989 Edition of Section XI of the ASME Code, with no addenda, as the ASME Code of record.
| | REQUEST FOR ADDITIONAL INFORMATION NINE MILE POINT NUCLEAR STATION, UNIT NO. 2 REQUEST FOR RELIEF NO. 2ISI-001 By letter dated November 16, 2006, Nine Mile Point Nuclear Station, LLC (the licensee) submitted Request for Relief (RR) No. 2ISI-001 for Nine Mile Point Unit 2 (NMP2) requesting an alternative to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), Section XI, Table IWB-2500-1, Category B-A, Item Number B1.11, reactor pressure vessel (RPV) circumferential shell welds inspection requirements. RR No. 2ISI-001 is for the second 10-year inservice inspection (ISI) interval, in which NMP2 adopted the 1989 Edition of Section XI of the ASME Code, with no addenda, as the ASME Code of record. |
| Subarticle IWB-2500 of the ASME Code requires components specified in Table IWB-2500-1 to be examined. Table IWB-2500-1 requires volumetric examination of all RPV shell circumferential welds each inspection interval. The licensee is requesting permanent relief from the above ASME Code requirements for theremaining license period and the license renewal period of extended operation for NMP2. The following information is required to complete the Nuclear Regulatory Commission staff's review of RR No. 2ISI-001.In order for the licensee to request relief for the extended operation period, it must also addressBWRVIP-74, "BWR Reactor Pressure Vessel Inspection and Flaw Evaluation Guidelines," | | Subarticle IWB-2500 of the ASME Code requires components specified in Table IWB-2500-1 to be examined. Table IWB-2500-1 requires volumetric examination of all RPV shell circumferential welds each inspection interval. |
| dated September 21, 1999. The staff's evaluation of BWRVIP-74 was provided by safety evaluation (SE), dated October 18, 2001 (ML012920549). That SE concluded that Appendix E of the staff's July 28, 1998 SE of BWRVIP-05 ("BWR RPV Shell Weld Inspection Recommendations," dated September 1995) conservatively evaluated BWR RPVs to 64 Effective Full Power Years (EFPY), which is 10 EFPY greater than what is realistically expected for the end of an additional 20-year license renewal period. Therefore, the staff's analysis provides a technical basis for relief from the current ISI requirements of ASME Code, Section XI for volumetric examination of circumferential welds as they may apply for the license renewal period. The October 18, 2001, SE further stated that, to obtain relief, each licensee will have to demonstrate:That, at the end of the renewal period, the circumferential welds will satisfy the limitingconditional failure probabilities for circumferential welds in Appendix E of the staff's July 28, 1998 SE, and that they have implemented operator training and established procedures that limit the frequency of cold overpressure events to the frequency specified in the staff's July 28, 1998 SE.}} | | The licensee is requesting permanent relief from the above ASME Code requirements for the remaining license period and the license renewal period of extended operation for NMP2. The following information is required to complete the Nuclear Regulatory Commission staffs review of RR No. 2ISI-001. |
| | In order for the licensee to request relief for the extended operation period, it must also address BWRVIP-74, "BWR Reactor Pressure Vessel Inspection and Flaw Evaluation Guidelines," |
| | dated September 21, 1999. The staffs evaluation of BWRVIP-74 was provided by safety evaluation (SE), dated October 18, 2001 (ML012920549). That SE concluded that Appendix E of the staffs July 28, 1998 SE of BWRVIP-05 (BWR RPV Shell Weld Inspection Recommendations, dated September 1995) conservatively evaluated BWR RPVs to 64 Effective Full Power Years (EFPY), which is 10 EFPY greater than what is realistically expected for the end of an additional 20-year license renewal period. Therefore, the staffs analysis provides a technical basis for relief from the current ISI requirements of ASME Code, Section XI for volumetric examination of circumferential welds as they may apply for the license renewal period. The October 18, 2001, SE further stated that, to obtain relief, each licensee will have to demonstrate: |
| | That, at the end of the renewal period, the circumferential welds will satisfy the limiting conditional failure probabilities for circumferential welds in Appendix E of the staff's July 28, 1998 SE, and that they have implemented operator training and established procedures that limit the frequency of cold overpressure events to the frequency specified in the staffs July 28, 1998 SE. |
| | Enclosure}} |
Letter Sequence RAI |
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MONTHYEARML0703801522007-02-26026 February 2007
RAI Regarding Inservice Inspection Request for Relief No. 2ISI-001
Project stage: RAI
ML0712102452007-04-20020 April 2007
Response to NRC Request for Additional Information Regarding Request for Permanent Relief from Inservice Inspection Requirements of 10 CFR 50.55a(g) for the Volumetric Examination of Circumferential Reactor Pressure Vessel Welds
Project stage: Response to RAI
ML0728300472007-11-0505 November 2007
Authorization Under 10 CFR 50.55(a)(3)(i) for Proposed Alternative Reactor Pressure Vessel Circumferential Shell Weld Volumetric Examinations (Tac No. MD3696)
Project stage: Other
2007-02-26
[Table View] |
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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
[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
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2023-09-21
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Text
February 26, 2007 Mr. Timothy J. OConnor 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. 2, INSERVICE INSPECTION REQUEST FOR RELIEF NO. 2ISI-001 (TAC NO. MD3696)
Dear Mr. OConnor:
By letter dated November 16, 2006, Nine Mile Point Nuclear Station, LLC requested Nuclear Regulatory Commission (NRC) approval of proposed Request for Relief Number 2ISI-001 for Nine Mile Point Unit 2 (NMP2). The request is for permanent relief from the inservice inspection requirements of Title 10 of the Code of Federal Regulations, Part 50, Section 50.55a(g) for the volumetric examination of reactor pressure vessel shell circumferential welds for the remaining license period and the license renewal period of extended operation for NMP2.
The NRC staff has reviewed the information provided in your request and has determined that additional information is needed to complete its review. Enclosed is the NRC staffs request for additional information (RAI). The RAI was discussed with your staff on February 1, 2007, and it was agreed that your response would be provided within 60 days from the date of this letter.
Sincerely,
/RA/
Douglas V. Pickett, Senior Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-410
Enclosure:
RAI cc w/encl: See next page
February 26, 2007 Mr. Timothy J. OConnor 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. 2, INSERVICE INSPECTION REQUEST FOR RELIEF NO. 2ISI-001 (TAC NO. MD3696)
Dear Mr. OConnor:
By letter dated November 16, 2006, Nine Mile Point Nuclear Station, LLC requested Nuclear Regulatory Commission (NRC) approval of proposed Request for Relief Number 2ISI-001 for Nine Mile Point Unit 2 (NMP2). The request is for permanent relief from the inservice inspection requirements of Title 10, Part 50, of the Code of Federal Regulations, Section 50.55a(g) for the volumetric examination of reactor pressure vessel shell circumferential welds for the remaining license period and the license renewal period of extended operation for NMP2.
The NRC staff has reviewed the information provided in your request and has determined that additional information is needed to complete its review. Enclosed is the NRC staffs request for additional information (RAI). The RAI was discussed with your staff on February 1, 2007, and it was agreed that your response would be provided within 60 days from the date of this letter.
Sincerely,
/RA/
Douglas V. Pickett, Senior Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-410
Enclosure:
RAI cc w/encl: See next page DISTRIBUTION:
PUBLIC RidsNrrPMDPickett RidsNrrLASLittle LPLI-1 PDI-1 Reading File MDavid RidsOgcRp RidsNrrAdesDciCvib RidsNrrAcrsAcnwMailCenter Accession Number: ML070380152 NRR-088 OFFICE LPL1-1/PE LPL1-1/PM LPL1-1/LA CVIB/BC LPL1-1/BC(A)
NAME MDavid DPickett SLittle MMitchell JBoska DATE 2/22/07 2/23/07 2/22/07 2/23/07 2/26/07 OFFICIAL RECORD COPY
Nine Mile Point Nuclear Station cc:
Mr. Michael J. Wallace Mark J. Wetterhahn, Esquire President Winston & Strawn Nine Mile Point Nuclear Station, LLC 1700 K Street, NW c/o Constellation Energy Group Washington, DC 20006 750 East Pratt Street Baltimore, MD 21202 Supervisor Town of Scriba Mr. Mike Heffley Route 8, Box 382 Senior Vice President and Chief Oswego, NY 13126 Nuclear Officer Constellation Generation Group Carey W. Fleming, Esquire 1997 Annapolis Exchange Parkway Senior Counsel Suite 500 Constellation Generation Group, LLC Annapolis, MD 21401 750 East Pratt Street, 17th Floor Baltimore, MD 21202 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 126 Lycoming, NY 13093 Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271 Mr. Paul D. Eddy Electric Division NYS Department of Public Service Agency Building 3 Empire State Plaza Albany, NY 12223 Mr. Peter R. Smith, President New York State Energy, Research, and Development Authority 17 Columbia Circle Albany, NY 12203-6399
REQUEST FOR ADDITIONAL INFORMATION NINE MILE POINT NUCLEAR STATION, UNIT NO. 2 REQUEST FOR RELIEF NO. 2ISI-001 By letter dated November 16, 2006, Nine Mile Point Nuclear Station, LLC (the licensee) submitted Request for Relief (RR) No. 2ISI-001 for Nine Mile Point Unit 2 (NMP2) requesting an alternative to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, Table IWB-2500-1, Category B-A, Item Number B1.11, reactor pressure vessel (RPV) circumferential shell welds inspection requirements. RR No. 2ISI-001 is for the second 10-year inservice inspection (ISI) interval, in which NMP2 adopted the 1989 Edition of Section XI of the ASME Code, with no addenda, as the ASME Code of record.
Subarticle IWB-2500 of the ASME Code requires components specified in Table IWB-2500-1 to be examined. Table IWB-2500-1 requires volumetric examination of all RPV shell circumferential welds each inspection interval.
The licensee is requesting permanent relief from the above ASME Code requirements for the remaining license period and the license renewal period of extended operation for NMP2. The following information is required to complete the Nuclear Regulatory Commission staffs review of RR No. 2ISI-001.
In order for the licensee to request relief for the extended operation period, it must also address BWRVIP-74, "BWR Reactor Pressure Vessel Inspection and Flaw Evaluation Guidelines,"
dated September 21, 1999. The staffs evaluation of BWRVIP-74 was provided by safety evaluation (SE), dated October 18, 2001 (ML012920549). That SE concluded that Appendix E of the staffs July 28, 1998 SE of BWRVIP-05 (BWR RPV Shell Weld Inspection Recommendations, dated September 1995) conservatively evaluated BWR RPVs to 64 Effective Full Power Years (EFPY), which is 10 EFPY greater than what is realistically expected for the end of an additional 20-year license renewal period. Therefore, the staffs analysis provides a technical basis for relief from the current ISI requirements of ASME Code,Section XI for volumetric examination of circumferential welds as they may apply for the license renewal period. The October 18, 2001, SE further stated that, to obtain relief, each licensee will have to demonstrate:
That, at the end of the renewal period, the circumferential welds will satisfy the limiting conditional failure probabilities for circumferential welds in Appendix E of the staff's July 28, 1998 SE, and that they have implemented operator training and established procedures that limit the frequency of cold overpressure events to the frequency specified in the staffs July 28, 1998 SE.
Enclosure
