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| | issue date = 07/09/2015 | | | issue date = 07/09/2015 |
| | title = Independent Spent Fuel Storage Installation (ISFSI) - General License 30-Day Cask Registration Notification and Thermal Performance Assessment | | | title = Independent Spent Fuel Storage Installation (ISFSI) - General License 30-Day Cask Registration Notification and Thermal Performance Assessment |
| | author name = Moore D M | | | author name = Moore D |
| | author affiliation = Exelon Generation Co, LLC | | | author affiliation = Exelon Generation Co, LLC |
| | addressee name = | | | addressee name = |
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| =Text= | | =Text= |
| {{#Wiki_filter:.6, I nmExelon Generation. | | {{#Wiki_filter:.6, I nmExelon Generation. |
| NMP1L 3036 July 9, 2015 10 CFR 72.212(b)(2) | | NMP1L 3036 10 CFR 72.212(b)(2) |
| U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 ATTN: Document Control Desk Director, Division of Spent Fuel Storage and Transportation Office of Nuclear Material Safety and Safeguards Nine Mile Point Nuclear Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-63 and NPF-69 Docket Nos. 50-220 and 50-410 Nine Mile Point Nuclear Station Independent Spent Fuel Storage Installation General License Docket No. 72-1036 | | July 9, 2015 U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 ATTN: Document Control Desk Director, Division of Spent Fuel Storage and Transportation Office of Nuclear Material Safety and Safeguards Nine Mile Point Nuclear Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-63 and NPF-69 Docket Nos. 50-220 and 50-410 Nine Mile Point Nuclear Station Independent Spent Fuel Storage Installation General License Docket No. 72-1036 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| General License 30-day Cask Registration Notification and Thermal Performance Assessment Pursuant to the requirements of 10 CFR 72.212(b)(2), this letter provides the information to register the use of two approved spent fuel storage casks at the Nine Mile Point Nuclear Station (NMPNS) Independent Spent Fuel Storage Installation (ISFSI).Licensee's Name: Address: Reactor License Numbers: Docket Numbers: Person Responsible for Providing additional information: | | General License 30-day Cask Registration Notification and Thermal Performance Assessment Pursuant to the requirements of 10 CFR 72.212(b)(2), this letter provides the information to register the use of two approved spent fuel storage casks at the Nine Mile Point Nuclear Station (NMPNS) Independent Spent Fuel Storage Installation (ISFSI). |
| Cask Certificate Number: Certificate Amendment Number: Cask Model Number: Cask Identification Numbers: Nine Mile Point Nuclear Station, LLC PO Box 63 Lycoming, NY 13093 DPR-63 and NPF-69 50-220, 50-410 and 72-1036 Mr. Kenneth J. Kristensen 315-349-2069 1004 10 NUHOMSO-61 BTH NMP-61 BTH-1 -A-2-021, loaded June 11, 2015 NMP-61 BTH-1 -A-2-022, loaded June 25, 2015 The Technical Specifications (TS) for Certificate of Compliance (CoC) No. 1004, Amendment No. 10, §1.1.7 "Special Requirements for First System in Place", requires the results of the temperature measurements of the first Dry Shielded Canister (DSC) placed in service be submitted to the NRC for evaluation and assessment.
| | Licensee's Name: Nine Mile Point Nuclear Station, LLC Address: PO Box 63 Lycoming, NY 13093 Reactor License Numbers: DPR-63 and NPF-69 Docket Numbers: 50-220, 50-410 and 72-1036 Person Responsible for Mr. Kenneth J. Kristensen Providing additional information: 315-349-2069 Cask Certificate Number: 1004 Certificate Amendment Number: 10 Cask Model Number: NUHOMSO-61 BTH Cask Identification Numbers: NMP-61 BTH-1 -A-2-021, loaded June 11, 2015 NMP-61 BTH-1 -A-2-022, loaded June 25, 2015 The Technical Specifications (TS) for Certificate of Compliance (CoC) No. 1004, Amendment No. 10, §1.1.7 "Special Requirements for First System in Place", requires the results of the temperature measurements of the first Dry Shielded Canister (DSC) placed in service be submitted to the NRC for evaluation and assessment. Additionally, this section of TS requires subsequent users of the system to report heat loads higher than the first user. The first user of the NUHOMS CoC No. 1004, Duke Energy, submitted the heat transfer characteristics for an 18.95 kilowatt (kW) Dry Shielded Canister (DSC) in a letter to the NRC, from Duke Energy, "Cask Certificate of Compliance, Docket No.: 72-1004, 30-day Report for Higher Canister Heat Loading per General Requirement Section 1.1.7," dated August 8, 2007 (ML072340622). The k |
| Additionally, this section of TS requires subsequent users of the system to report heat loads higher than the first user. The first user of the NUHOMS CoC No. 1004, Duke Energy, submitted the heat transfer characteristics for an 18.95 kilowatt (kW) Dry Shielded Canister (DSC) in a letter to the NRC, from Duke Energy,"Cask Certificate of Compliance, Docket No.: 72-1004, 30-day Report for Higher Canister Heat Loading per General Requirement Section 1.1.7," dated August 8, 2007 (ML072340622). | | ý,IjA f>2v'(o |
| Theý,IjA k f>2v'(o ii-I 30 Day Cask July 9, 2015 Page 2 Registration first DSC loaded at NMPNS had a heat load of 7.30 kW, as reported in our letter dated October 17,2012.A summary of the thermal performance of the 21st and 22nd DSCs in place at the NMPNS ISFSI is submitted for your information.
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| Horizontal Storage Module (HSM) Model: HSM Identification Number: 7DF Cask: NM Calculated Heat Load: 11., Calculated AT: 56 Actual AT (Note 1): 42.HSM Identification Number: 7DF Cask: NM Calculated Heat Load: 11., Calculated AT: 54 Actual AT (Note 1): 44.: NUHOMS Model 102:S-HSM002A P-61 BTH-1 -A-2-021 4585 kW degrees F 15 degrees F:S-HSM002B P-61 BTH-1 -A-2-022 4258 kW degrees F 35 degrees F Note 1: The actual AT represents the measured AT obtained during equilibrium conditions. | | ii |
| Equilibrium conditions were achieved when the daily temperature change observed was less than 6 degrees F over three consecutive days.This letter contains no NRC commitments. | | -I 30 Day Cask Registration July 9, 2015 Page 2 first DSC loaded at NMPNS had a heat load of 7.30 kW, as reported in our letter dated October 17,2012. |
| Should you have any questions regarding the information in this submittal, please contact Ken Kristensen at (315) 349-2069.Sincerely, Dennis M. Moore Regulatory Assurance Manager, Nine Mile Point Nuclear Station Exelon Generation Company, LLC DMM/KJK cc: NRC Regional Administrator, Region I NRC Resident Inspector NRR Project Manager}} | | A summary of the thermal performance of the 21st and 22nd DSCs in place at the NMPNS ISFSI is submitted for your information. |
| | Horizontal Storage Module (HSM) Model: NUHOMS Model 102 HSM Identification Number: 7DF:S-HSM002A Cask: NM P-61 BTH-1 -A-2-021 Calculated Heat Load: 11., 4585 kW Calculated AT: 56 degrees F Actual AT (Note 1): 42. 15 degrees F HSM Identification Number: 7DF:S-HSM002B Cask: NM P-61 BTH-1 -A-2-022 Calculated Heat Load: 11., 4258 kW Calculated AT: 54 degrees F Actual AT (Note 1): 44.:35 degrees F Note 1: The actual AT represents the measured AT obtained during equilibrium conditions. |
| | Equilibrium conditions were achieved when the daily temperature change observed was less than 6 degrees F over three consecutive days. |
| | This letter contains no NRC commitments. Should you have any questions regarding the information in this submittal, please contact Ken Kristensen at (315) 349-2069. |
| | Sincerely, Dennis M. Moore Regulatory Assurance Manager, Nine Mile Point Nuclear Station Exelon Generation Company, LLC DMM/KJK cc: NRC Regional Administrator, Region I NRC Resident Inspector NRR Project Manager}} |
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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 ML24130A1742024-05-10010 May 2024 Tn Americas Llc. - the U.S. Nuclear Regulatory Commission Inspection Report No. 72-1004/2024-201 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 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 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 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 2024-09-04
[Table view] |
Text
.6, I nmExelon Generation.
NMP1L 3036 10 CFR 72.212(b)(2)
July 9, 2015 U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 ATTN: Document Control Desk Director, Division of Spent Fuel Storage and Transportation Office of Nuclear Material Safety and Safeguards Nine Mile Point Nuclear Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-63 and NPF-69 Docket Nos. 50-220 and 50-410 Nine Mile Point Nuclear Station Independent Spent Fuel Storage Installation General License Docket No. 72-1036
SUBJECT:
General License 30-day Cask Registration Notification and Thermal Performance Assessment Pursuant to the requirements of 10 CFR 72.212(b)(2), this letter provides the information to register the use of two approved spent fuel storage casks at the Nine Mile Point Nuclear Station (NMPNS) Independent Spent Fuel Storage Installation (ISFSI).
Licensee's Name: Nine Mile Point Nuclear Station, LLC Address: PO Box 63 Lycoming, NY 13093 Reactor License Numbers: DPR-63 and NPF-69 Docket Numbers: 50-220, 50-410 and 72-1036 Person Responsible for Mr. Kenneth J. Kristensen Providing additional information: 315-349-2069 Cask Certificate Number: 1004 Certificate Amendment Number: 10 Cask Model Number: NUHOMSO-61 BTH Cask Identification Numbers: NMP-61 BTH-1 -A-2-021, loaded June 11, 2015 NMP-61 BTH-1 -A-2-022, loaded June 25, 2015 The Technical Specifications (TS) for Certificate of Compliance (CoC) No. 1004, Amendment No. 10, §1.1.7 "Special Requirements for First System in Place", requires the results of the temperature measurements of the first Dry Shielded Canister (DSC) placed in service be submitted to the NRC for evaluation and assessment. Additionally, this section of TS requires subsequent users of the system to report heat loads higher than the first user. The first user of the NUHOMS CoC No. 1004, Duke Energy, submitted the heat transfer characteristics for an 18.95 kilowatt (kW) Dry Shielded Canister (DSC) in a letter to the NRC, from Duke Energy, "Cask Certificate of Compliance, Docket No.: 72-1004, 30-day Report for Higher Canister Heat Loading per General Requirement Section 1.1.7," dated August 8, 2007 (ML072340622). The k
ý,IjA f>2v'(o
ii
-I 30 Day Cask Registration July 9, 2015 Page 2 first DSC loaded at NMPNS had a heat load of 7.30 kW, as reported in our letter dated October 17,2012.
A summary of the thermal performance of the 21st and 22nd DSCs in place at the NMPNS ISFSI is submitted for your information.
Horizontal Storage Module (HSM) Model: NUHOMS Model 102 HSM Identification Number: 7DF:S-HSM002A Cask: NM P-61 BTH-1 -A-2-021 Calculated Heat Load: 11., 4585 kW Calculated AT: 56 degrees F Actual AT (Note 1): 42. 15 degrees F HSM Identification Number: 7DF:S-HSM002B Cask: NM P-61 BTH-1 -A-2-022 Calculated Heat Load: 11., 4258 kW Calculated AT: 54 degrees F Actual AT (Note 1): 44.:35 degrees F Note 1: The actual AT represents the measured AT obtained during equilibrium conditions.
Equilibrium conditions were achieved when the daily temperature change observed was less than 6 degrees F over three consecutive days.
This letter contains no NRC commitments. Should you have any questions regarding the information in this submittal, please contact Ken Kristensen at (315) 349-2069.
Sincerely, Dennis M. Moore Regulatory Assurance Manager, Nine Mile Point Nuclear Station Exelon Generation Company, LLC DMM/KJK cc: NRC Regional Administrator, Region I NRC Resident Inspector NRR Project Manager