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| | number = ML17234A359 | | | number = ML17234A359 |
| | issue date = 08/30/2017 | | | issue date = 08/30/2017 |
| | title = Nine Mile Point Nuclear Station, Units 1 and 2 - Request for Additional Information Regarding Relief Request NMP-RR-001 to Utilize Code Case N-702 (CAC Nos. MF9381 and MF9382) | | | title = Request for Additional Information Regarding Relief Request NMP-RR-001 to Utilize Code Case N-702 |
| | author name = Marshall M L | | | author name = Marshall M |
| | author affiliation = NRC/NRR/DORL/LPLI | | | author affiliation = NRC/NRR/DORL/LPLI |
| | addressee name = Hanson B C | | | addressee name = Hanson B |
| | addressee affiliation = Exelon Generation Co, LLC, Exelon Nuclear | | | addressee affiliation = Exelon Generation Co, LLC, Exelon Nuclear |
| | docket = 05000220, 05000410 | | | docket = 05000220, 05000410 |
| | license number = DPR-063, NPF-069 | | | license number = DPR-063, NPF-069 |
| | contact person = Marshall M L, NRR/DORL/LPL1, 415-2871 | | | contact person = Marshall M, NRR/DORL/LPL1, 415-2871 |
| | case reference number = CAC MF9381, CAC MF9382 | | | case reference number = CAC MF9381, CAC MF9382 |
| | document type = Letter, Request for Additional Information (RAI) | | | document type = Letter, Request for Additional Information (RAI) |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Bryan C. Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 August 30, 2017 | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 30, 2017 Mr. Bryan C. Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| NINE MILE POINT NUCLEAR STATION, UNITS 1 AND 2 -REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST NMP-RR-001 TO UTILIZE CODE CASE N-702 (CAC NOS. MF9381 AND MF9382) | | NINE MILE POINT NUCLEAR STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST NMP-RR-001 TO UTILIZE CODE CASE N-702 (CAC NOS. MF9381 AND MF9382) |
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| ==Dear Mr. Hanson:== | | ==Dear Mr. Hanson:== |
| By letter dated March 7, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 17067A056), as supplemented by letter dated July 24, 2017 (ADAMS Accession No. ML 17206A 101 ), Exelon Generation Company, LLC submitted Relief Request NMP-RR-001 for the Nine Mile Point Nuclear Station, Units 1 and 2. The proposed relief request would authorize an alternative to performing 100 percent examination of the reactor pressure vessel nozzles listed in the request. The proposed alternative is to examine a minimum of 25 percent of the nozzle-to-vessel welds and inner radii sections, including at least one nozzle from each system and nominal pipe size, in accordance with the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-702, "Alternative Requirements for Boiling Water Reactor (BWR) Nozzle Inner Radius and Nozzle-to-Shell Welds, Section XI, Division 1." The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information provided in that letter and has determined that additional 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 August 25, 2017, and it was agreed that your response would be provided within 30 days from the date of this letter. Docket Nos. 50-220 and 50-410 | | |
| | By letter dated March 7, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17067A056), as supplemented by letter dated July 24, 2017 (ADAMS Accession No. ML17206A101 ), Exelon Generation Company, LLC submitted Relief Request NMP-RR-001 for the Nine Mile Point Nuclear Station, Units 1 and 2. The proposed relief request would authorize an alternative to performing 100 percent examination of the reactor pressure vessel nozzles listed in the request. The proposed alternative is to examine a minimum of 25 percent of the nozzle-to-vessel welds and inner radii sections, including at least one nozzle from each system and nominal pipe size, in accordance with the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-702, "Alternative Requirements for Boiling Water Reactor (BWR) Nozzle Inner Radius and Nozzle-to-Shell Welds, Section XI, Division 1." |
| | The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information provided in that letter and has determined that additional 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 August 25, 2017, and it was agreed that your response would be provided within 30 days from the date of this letter. |
| | Sincerely, Michael L. Marshall, Jr., Senior Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-220 and 50-410 |
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| ==Enclosure:== | | ==Enclosure:== |
| Request for Additional Information cc w/encl: Distribution via Listserv Sincerely, Michael L. Marshall, Jr., Senior Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation REQUEST FOR ADDITIONAL INFORMATION NINE MILE POINT NUCLEAR STATION, LLC EXELON GENERATION COMPANY, LLC NINE MILE POINT NUCLEAR STATION, UNITS 1 AND 2 DOCKET NOS. 50-220 AND 50-410 By letter dated March 7, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 17067 A056), as supplemented by letter dated July 24, 2017 (ADAMS Accession No. ML 17206A 101 ), Exelon Generation Company, LLC submitted Relief Request NMP-RR-001 for the Nine Mile Point Nuclear Station (Nine Mile Point), Units 1 and 2. The proposed relief request would authorize an alternative to performing 100 percent examination of the reactor pressure vessel nozzles listed in the request. The proposed alternative is to examine a minimum of 25 percent of the nozzle-to-vessel welds and inner radii sections, including at least one nozzle from each system and nominal pipe size, in accordance with the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-702, "Alternative Requirements for Boiling Water Reactor (BWR) Nozzle Inner Radius and Nozzle-to-Shell Welds, Section XI, Division 1." BWRVIP-108 and BWRVIP-241 are referenced by the licensee as the technical basis for its use of Code Case N-702. Both BWRVIP-108 and BWRVIP-241 are applicable for 40 years of operation. Appendix A of BWRVIP-241 extends the application of BWRVIP-108 and BWRVIP-241 through the period of extended operation (i.e., 40 years to 60 years). The licensee provided a demonstration in its submittal (NMP-RR-001) that the Nine Mile Point Unit 1, recirculation outlet nozzle (N 1 ), met criteria #4 and #5 established in the staff's safety evaluation for BWRVIP-241 (ADAMS Accession No. ML 13071A240). Furthermore, the licensee provided a demonstration that the Nine Mile Point, Unit 2, recirculation inlet nozzle (N2) met criteria #2 and #3 established in the staff's SE for BWRVIP-241. The licensee requested approval of its proposed alternative for the through the remainder of the 10-year intervals defined in Section 3 of the relief request and the remainder of the Nine Mile Point, Units 1 and 2 renewed facility operating licenses (RFOLs), which currently expire on August 22, 2029 and October 31, 2046, respectively. However, the licensee's probabilistic fracture mechanics (PFM) analyses for 60 years are only applicable to the recirculation inlet nozzle for Unit 1 and the recirculation outlet nozzle for Unit 2. For other inlet and outlet nozzles, application of ASME Code Case N-702 through the period of extended operation of the Nine Mile Point, Units 1 and 2 RFOLs still needs to be established. Specifically, Sections A.3 and A.4 of Appendix A to BWRVIP-241 indicate the following areas should be addressed: | | |
| * Demonstrate that the structural analysis of the representative nozzle geometry and the evaluation of the safety consequences of the nozzle failure in BWRVIP-108 and BWRVIP-241 applies to their plant's current licensing basis. Enclosure | | Request for Additional Information cc w/encl: Distribution via Listserv |
| * The stress and cycling range during the extended operating period require evaluation to demonstrate that commitments for the current license term can be maintained. Furthermore, BWRVIP-108 and BWRVIP-241 assumed that neutron fluence effects were negligible at all nozzle locations for the initial license period. The U.S. Nuclear Regulatory Commission (NRC) staff noted that this assumption may not be appropriate when considering plant operation through the period of extended operation of an RFOL. For the Nine Mile Point, Unit 1, recirculation outlet nozzle (i.e., N1 nozzle), and the Nine Mile Point, Unit 2, recirculation inlet nozzle (i.e., N2 nozzle), the NRC staff has determined that the following additional information is required to complete its review: | | |
| | REQUEST FOR ADDITIONAL INFORMATION NINE MILE POINT NUCLEAR STATION, LLC EXELON GENERATION COMPANY, LLC NINE MILE POINT NUCLEAR STATION, UNITS 1 AND 2 DOCKET NOS. 50-220 AND 50-410 By letter dated March 7, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17067A056), as supplemented by letter dated July 24, 2017 (ADAMS Accession No. ML17206A101 ), Exelon Generation Company, LLC submitted Relief Request NMP-RR-001 for the Nine Mile Point Nuclear Station (Nine Mile Point), Units 1 and 2. |
| | The proposed relief request would authorize an alternative to performing 100 percent examination of the reactor pressure vessel nozzles listed in the request. The proposed alternative is to examine a minimum of 25 percent of the nozzle-to-vessel welds and inner radii sections, including at least one nozzle from each system and nominal pipe size, in accordance with the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-702, "Alternative Requirements for Boiling Water Reactor (BWR) Nozzle Inner Radius and Nozzle-to-Shell Welds, Section XI, Division 1." |
| | BWRVIP-108 and BWRVIP-241 are referenced by the licensee as the technical basis for its use of Code Case N-702. Both BWRVIP-108 and BWRVIP-241 are applicable for 40 years of operation. Appendix A of BWRVIP-241 extends the application of BWRVIP-108 and BWRVIP-241 through the period of extended operation (i.e., 40 years to 60 years). |
| | The licensee provided a demonstration in its submittal (NMP-RR-001) that the Nine Mile Point Unit 1, recirculation outlet nozzle (N 1), met criteria #4 and #5 established in the staff's safety evaluation for BWRVIP-241 (ADAMS Accession No. ML13071A240). Furthermore, the licensee provided a demonstration that the Nine Mile Point, Unit 2, recirculation inlet nozzle (N2) met criteria #2 and #3 established in the staff's SE for BWRVIP-241. |
| | The licensee requested approval of its proposed alternative for the through the remainder of the 10-year intervals defined in Section 3 of the relief request and the remainder of the Nine Mile Point, Units 1 and 2 renewed facility operating licenses (RFOLs), which currently expire on August 22, 2029 and October 31, 2046, respectively. However, the licensee's probabilistic fracture mechanics (PFM) analyses for 60 years are only applicable to the recirculation inlet nozzle for Unit 1 and the recirculation outlet nozzle for Unit 2. For other inlet and outlet nozzles, application of ASME Code Case N-702 through the period of extended operation of the Nine Mile Point, Units 1 and 2 RFOLs still needs to be established. |
| | Specifically, Sections A.3 and A.4 of Appendix A to BWRVIP-241 indicate the following areas should be addressed: |
| | * Demonstrate that the structural analysis of the representative nozzle geometry and the evaluation of the safety consequences of the nozzle failure in BWRVIP-108 and BWRVIP-241 applies to their plant's current licensing basis. |
| | Enclosure |
| | * The stress and cycling range during the extended operating period require evaluation to demonstrate that commitments for the current license term can be maintained. |
| | Furthermore, BWRVIP-108 and BWRVIP-241 assumed that neutron fluence effects were negligible at all nozzle locations for the initial license period. The U.S. Nuclear Regulatory Commission (NRC) staff noted that this assumption may not be appropriate when considering plant operation through the period of extended operation of an RFOL. |
| | For the Nine Mile Point, Unit 1, recirculation outlet nozzle (i.e., N1 nozzle), and the Nine Mile Point, Unit 2, recirculation inlet nozzle (i.e., N2 nozzle), the NRC staff has determined that the following additional information is required to complete its review: |
| * Provide a justification that the PFM analyses provided in relief request NMP-RR-001 demonstrates application of ASME Code Case N-702 for Nine Mile Point Unit 1, recirculation outlet nozzle, and the Nine Mile Point Unit 2, recirculation inlet nozzle, for the duration of the Nine Mile Point, Units 1 and 2 RFOLs. | | * Provide a justification that the PFM analyses provided in relief request NMP-RR-001 demonstrates application of ASME Code Case N-702 for Nine Mile Point Unit 1, recirculation outlet nozzle, and the Nine Mile Point Unit 2, recirculation inlet nozzle, for the duration of the Nine Mile Point, Units 1 and 2 RFOLs. |
| * Alternatively, address the following areas: | | * Alternatively, address the following areas: |
| * Provide a justification that demonstrates that the structural analysis of the representative nozzle geometry and the evaluation of the safety consequences of the nozzle failure in BWRVIP-108 and BWRVIP-241 apply to the plant's current licensing basis. | | * Provide a justification that demonstrates that the structural analysis of the representative nozzle geometry and the evaluation of the safety consequences of the nozzle failure in BWRVIP-108 and BWRVIP-241 apply to the plant's current licensing basis. |
| * Provide a justification that demonstrates that the current licensing basis can be maintained when considering the stress and cycling range during the extended operating period. | | * Provide a justification that demonstrates that the current licensing basis can be maintained when considering the stress and cycling range during the extended operating period. |
| * Provide a justification that demonstrates that neutron fluence effects are negligible at the nozzle locations when considering the period of extended operation. | | * Provide a justification that demonstrates that neutron fluence effects are negligible at the nozzle locations when considering the period of extended operation. |
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| ==SUBJECT:== | | ==SUBJECT:== |
| NINE MILE POINT NUCLEAR STATION, UNITS 1 AND 2 -REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST NMP-RR-001 TO UTILIZE CODE CASE N-702 (CAC NOS. MF9381 AND MF9382) DATED AUGUST 30, 2017 DISTRIBUTION: Public RidsNrrDorlLpl 1 RidsRgn 1 MailCenter RidsACRS_MailCTR RidsNrrLALRonewicz RidsNrrPMNineMilePoint RidsNrrDeEvib Resource OYee, NRR ADAMS A ccess1on N b ML 17234A359 um er: *b *1 1y e-ma1 OFFICE DORL/LPL 1 /PM DORL/LPL 1/LA DE/EVIB/BC* DORL/LPL 1/BC DORL/LPL 1/PM NAME MMarshall LRonewicz DRudland JDanna MMarshall DATE 08/24/17 08/23/2017 08/10/2017 08/29/17 08/30/17 OFFICIAL RECORD COPY}} | | NINE MILE POINT NUCLEAR STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST NMP-RR-001 TO UTILIZE CODE CASE N-702 (CAC NOS. MF9381 AND MF9382) DATED AUGUST 30, 2017 DISTRIBUTION: |
| | Public RidsNrrDorlLpl 1 RidsRgn 1MailCenter RidsACRS_MailCTR RidsNrrLALRonewicz RidsNrrPMNineMilePoint RidsNrrDeEvib Resource OYee, NRR ADAMS A ccess1on N um ber: ML17234A359 *b1y e-ma1*1 OFFICE DORL/LPL 1/PM DORL/LPL 1/LA DE/EVIB/BC* DORL/LPL 1/BC DORL/LPL 1/PM NAME MMarshall LRonewicz DRudland JDanna MMarshall DATE 08/24/17 08/23/2017 08/10/2017 08/29/17 08/30/17 OFFICIAL RECORD COPY}} |
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Category:Letter
MONTHYEARML24268A3382024-10-16016 October 2024
Issuance of Amendment No. 253 Regarding the Modification of TS Surveillance Requirement 4.3.6.a Related to Adoption of TSTF-425, Revision 3
RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024
Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests
NMP2L2890, Submittal of Revision 26 to the USAR and Reference Figures, 10 CFR 50.59 Evaluation Summary Report, TS Bases, TRM Requirements Manual Changes, and 10 CFR 54.37(b) Aging Management Review (Excludes Attachment 6)2024-10-0404 October 2024
Submittal of Revision 26 to the USAR and Reference Figures, 10 CFR 50.59 Evaluation Summary Report, TS Bases, TRM Requirements Manual Changes, and 10 CFR 54.37(b) Aging Management Review (Excludes Attachment 6)
ML24275A2442024-10-0303 October 2024
Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing
IR 05000220/20243022024-10-0303 October 2024
Initial Operator Licensing Examination Report 05000220/2024302
ML24190A0012024-09-26026 September 2024
Issuance of Amendment Nos. 252 and 197 Regarding the Revision to Technical Specification Design Features Section to Remove Nine Mile Point Unit 3 Project Designation
NMP1L3608, Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-09-20020 September 2024
Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation
RS-24-090, Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-09-12012 September 2024
Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds
ML24249A1362024-09-0404 September 2024
EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21
IR 05000220/20240052024-08-29029 August 2024
Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2024005 and 05000410/2024005)
IR 05000220/20240102024-08-22022 August 2024
Age-Related Degradation Inspection Report 05000220/2024010 and 05000410/2024010
NMP1L3603, Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan2024-08-20020 August 2024
Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan
ML24222A6772024-08-0909 August 2024
Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition
IR 05000220/20240022024-08-0505 August 2024
Integrated Inspection Report 05000220/2024002 and 05000410/2024002
ML24215A3002024-08-0202 August 2024
Operator Licensing Examination Approval
NMP1L3601, Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-07-31031 July 2024
Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation
ML24213A1412024-07-31031 July 2024
Requalification Program Inspection
NMP2L2883, Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations2024-07-24024 July 2024
Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations
ML24198A0852024-07-16016 July 2024
Senior Reactor and Reactor Operator Initial License Examinations
RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024
Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions
RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024
Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations
NMP1L3584, License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2024-06-13013 June 2024
License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling
IR 05000220/20244012024-05-30030 May 2024
Security Baseline Inspection Report 05000220/2024401 and 05000410/2024401(Cover Letter Only)
ML24079A0762024-05-23023 May 2024
Issuance of Amendments to Adopt TSTF 264
NMP1L3591, Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request2024-05-18018 May 2024
Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request
NMP1L3589, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-05-16016 May 2024
Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable
ML24158A2052024-05-15015 May 2024
Annual Radioactive Environmental Operating Report
NMP1L3582, 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 22024-05-15015 May 2024
2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 2
IR 05000220/20240012024-05-10010 May 2024
Integrated Inspection Report 05000220/2024001 and 05000410/2024001
RS-24-049, Updated Notice of Intent to Pursue Subsequent License Renewal Applications2024-05-0909 May 2024
Updated Notice of Intent to Pursue Subsequent License Renewal Applications
RS-24-038, Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-05-0202 May 2024
Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds
05000410/LER-2024-001, Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum2024-05-0101 May 2024
Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum
RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024
Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests
NMP1L3581, Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report2024-04-30030 April 2024
Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report
NMP2L2877, 2023 Annual Environmental Operating Report2024-04-19019 April 2024
2023 Annual Environmental Operating Report
NMP2L2878, Core Operating Limits Report2024-04-16016 April 2024
Core Operating Limits Report
ML24103A2042024-04-12012 April 2024
Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition
RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024
Constellation Energy Generation, LLC - Annual Property Insurance Status Report
ML24092A3352024-04-0101 April 2024
NRC Office of Investigations Case No. 1-2023-002
ML24074A2812024-03-14014 March 2024
Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000220/2024010 and 05000410/2024010
NMP1L3577, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-03-13013 March 2024
Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable
IR 05000220/20230062024-02-28028 February 2024
Annual Assessment Letter for Nine Mile Point Nuclear Station, Units 1 and 2, (Reports 05000220/2023006 and 05000410/2023006)
IR 05000220/20230042024-02-0101 February 2024
Integrated Inspection Report 05000220/2023004 and 05000410/2023004
NMP1L3570, Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-02-0101 February 2024
Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation
05000410/LER-2023-001, Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater2024-01-30030 January 2024
Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater
NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024
CFR 50.46 Annual Report
ML24004A2122024-01-0808 January 2024
Senior Reactor and Reactor Operator Initial License Examinations
ML23354A0012024-01-0404 January 2024
Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0059 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting))
05000220/LER-2023-002, Average Power Range Monitors Declared Inoperable Due to Trip of Reactor Recirculation Pump 122023-12-15015 December 2023
Average Power Range Monitors Declared Inoperable Due to Trip of Reactor Recirculation Pump 12
NMP1L3566, Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station2023-12-14014 December 2023
Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station
2024-09-04
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML24312A1662024-11-0707 November 2024
Request for Additional Information (11/7/2024 E-mail) - LAR to Revise TSs to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3
ML24197A0162024-07-12012 July 2024
NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC - Fleet Request - License Amendment Request to Adopt TSTF-591
ML24074A2812024-03-14014 March 2024
Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000220/2024010 and 05000410/2024010
ML23264A7992023-09-21021 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
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Request for Additional Information Regarding Relief Request NMP-RR-001 to Utilize Code Case N-702
2024-07-12
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 30, 2017 Mr. Bryan C. Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
NINE MILE POINT NUCLEAR STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST NMP-RR-001 TO UTILIZE CODE CASE N-702 (CAC NOS. MF9381 AND MF9382)
Dear Mr. Hanson:
By letter dated March 7, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17067A056), as supplemented by letter dated July 24, 2017 (ADAMS Accession No. ML17206A101 ), Exelon Generation Company, LLC submitted Relief Request NMP-RR-001 for the Nine Mile Point Nuclear Station, Units 1 and 2. The proposed relief request would authorize an alternative to performing 100 percent examination of the reactor pressure vessel nozzles listed in the request. The proposed alternative is to examine a minimum of 25 percent of the nozzle-to-vessel welds and inner radii sections, including at least one nozzle from each system and nominal pipe size, in accordance with the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-702, "Alternative Requirements for Boiling Water Reactor (BWR) Nozzle Inner Radius and Nozzle-to-Shell Welds,Section XI, Division 1."
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information provided in that letter and has determined that additional 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 August 25, 2017, and it was agreed that your response would be provided within 30 days from the date of this letter.
Sincerely, Michael L. Marshall, Jr., Senior Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-220 and 50-410
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION NINE MILE POINT NUCLEAR STATION, LLC EXELON GENERATION COMPANY, LLC NINE MILE POINT NUCLEAR STATION, UNITS 1 AND 2 DOCKET NOS. 50-220 AND 50-410 By letter dated March 7, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17067A056), as supplemented by letter dated July 24, 2017 (ADAMS Accession No. ML17206A101 ), Exelon Generation Company, LLC submitted Relief Request NMP-RR-001 for the Nine Mile Point Nuclear Station (Nine Mile Point), Units 1 and 2.
The proposed relief request would authorize an alternative to performing 100 percent examination of the reactor pressure vessel nozzles listed in the request. The proposed alternative is to examine a minimum of 25 percent of the nozzle-to-vessel welds and inner radii sections, including at least one nozzle from each system and nominal pipe size, in accordance with the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-702, "Alternative Requirements for Boiling Water Reactor (BWR) Nozzle Inner Radius and Nozzle-to-Shell Welds,Section XI, Division 1."
BWRVIP-108 and BWRVIP-241 are referenced by the licensee as the technical basis for its use of Code Case N-702. Both BWRVIP-108 and BWRVIP-241 are applicable for 40 years of operation. Appendix A of BWRVIP-241 extends the application of BWRVIP-108 and BWRVIP-241 through the period of extended operation (i.e., 40 years to 60 years).
The licensee provided a demonstration in its submittal (NMP-RR-001) that the Nine Mile Point Unit 1, recirculation outlet nozzle (N 1), met criteria #4 and #5 established in the staff's safety evaluation for BWRVIP-241 (ADAMS Accession No. ML13071A240). Furthermore, the licensee provided a demonstration that the Nine Mile Point, Unit 2, recirculation inlet nozzle (N2) met criteria #2 and #3 established in the staff's SE for BWRVIP-241.
The licensee requested approval of its proposed alternative for the through the remainder of the 10-year intervals defined in Section 3 of the relief request and the remainder of the Nine Mile Point, Units 1 and 2 renewed facility operating licenses (RFOLs), which currently expire on August 22, 2029 and October 31, 2046, respectively. However, the licensee's probabilistic fracture mechanics (PFM) analyses for 60 years are only applicable to the recirculation inlet nozzle for Unit 1 and the recirculation outlet nozzle for Unit 2. For other inlet and outlet nozzles, application of ASME Code Case N-702 through the period of extended operation of the Nine Mile Point, Units 1 and 2 RFOLs still needs to be established.
Specifically, Sections A.3 and A.4 of Appendix A to BWRVIP-241 indicate the following areas should be addressed:
- Demonstrate that the structural analysis of the representative nozzle geometry and the evaluation of the safety consequences of the nozzle failure in BWRVIP-108 and BWRVIP-241 applies to their plant's current licensing basis.
Enclosure
- The stress and cycling range during the extended operating period require evaluation to demonstrate that commitments for the current license term can be maintained.
Furthermore, BWRVIP-108 and BWRVIP-241 assumed that neutron fluence effects were negligible at all nozzle locations for the initial license period. The U.S. Nuclear Regulatory Commission (NRC) staff noted that this assumption may not be appropriate when considering plant operation through the period of extended operation of an RFOL.
For the Nine Mile Point, Unit 1, recirculation outlet nozzle (i.e., N1 nozzle), and the Nine Mile Point, Unit 2, recirculation inlet nozzle (i.e., N2 nozzle), the NRC staff has determined that the following additional information is required to complete its review:
- Provide a justification that the PFM analyses provided in relief request NMP-RR-001 demonstrates application of ASME Code Case N-702 for Nine Mile Point Unit 1, recirculation outlet nozzle, and the Nine Mile Point Unit 2, recirculation inlet nozzle, for the duration of the Nine Mile Point, Units 1 and 2 RFOLs.
- Alternatively, address the following areas:
- Provide a justification that demonstrates that the structural analysis of the representative nozzle geometry and the evaluation of the safety consequences of the nozzle failure in BWRVIP-108 and BWRVIP-241 apply to the plant's current licensing basis.
- Provide a justification that demonstrates that the current licensing basis can be maintained when considering the stress and cycling range during the extended operating period.
- Provide a justification that demonstrates that neutron fluence effects are negligible at the nozzle locations when considering the period of extended operation.
SUBJECT:
NINE MILE POINT NUCLEAR STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST NMP-RR-001 TO UTILIZE CODE CASE N-702 (CAC NOS. MF9381 AND MF9382) DATED AUGUST 30, 2017 DISTRIBUTION:
Public RidsNrrDorlLpl 1 RidsRgn 1MailCenter RidsACRS_MailCTR RidsNrrLALRonewicz RidsNrrPMNineMilePoint RidsNrrDeEvib Resource OYee, NRR ADAMS A ccess1on N um ber: ML17234A359 *b1y e-ma1*1 OFFICE DORL/LPL 1/PM DORL/LPL 1/LA DE/EVIB/BC* DORL/LPL 1/BC DORL/LPL 1/PM NAME MMarshall LRonewicz DRudland JDanna MMarshall DATE 08/24/17 08/23/2017 08/10/2017 08/29/17 08/30/17 OFFICIAL RECORD COPY
