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| {{#Wiki_filter:CENG.a joint venture of Constellation M neM,4gyqD NINE MILE POINT NUCLEAR STATION August 7, 2013 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 ATTENTION: | | {{#Wiki_filter:CENG. |
| | a joint venture of Constellation M neM,4gyqD NINE MILE POINT NUCLEAR STATION August 7, 2013 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 ATTENTION: Document Control Desk Director, Division of Spent Fuel Storage and Transportation Office of Nuclear Material Safety and Safeguards |
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| ==SUBJECT:== | | ==SUBJECT:== |
| 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. 5 0-220 and 50-410 Nine Mile Point Nuclear Station Independent Spent Fuel Storage Installation General License Docket No. 72-1036 General License 30-day Cask Registration Notification and First System 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 DPR-63 and NPF-69 Reactor License Numbers: Docket Numbers: Person Responsible for Providing additional information:
| | 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 General License 30-day Cask Registration Notification and First System 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) |
| Cask Certificate Number: Certificate Amendment Number: Cask Model Number: Cask Identification Numbers: 50-220, 50-4 10 and 72-1036 Ms. Theresa H. Darling 315-349-2221 1004 10 NUHOMSO-61BT NMP6 1 B-007-A, loaded July 11, 2013 NMP61B-008-A, loaded July 23, 2013 Nine Mile Point Nuclear Station, LLC P.O. Box 63, Lycoming, NY 13093 Document Control Desk August 7, 2013 Page 2 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.
| | Independent Spent Fuel Storage Installation (ISFSI). |
| 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). | | 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, 50-4 10 and 72-1036 Person Responsible for Ms. Theresa H. Darling Providing additional information: 315-349-2221 Cask Certificate Number: 1004 Certificate Amendment Number: 10 Cask Model Number: NUHOMSO-61BT Cask Identification Numbers: NMP6 1B-007-A, loaded July 11, 2013 NMP61B-008-A, loaded July 23, 2013 Nine Mile Point Nuclear Station, LLC P.O. Box 63, Lycoming, NY 13093 |
| The 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 seventh and eighth DSCs in place at the NMPNS ISFSI is submitted for your information. | | |
| Horizontal Storage Module (HSM) Model: NUHOMS Model 102 HSM Identification Number: 7DFS-HSM004G Cask: NMP61B-007-A Calculated Heat Load: 9 kW Calculated AT: 49 degrees F Actual AT (Note 1): 47.5 degrees F HSM Identification Number: 7DFS-HSM004H Cask: NMP61B-008-A Calculated Heat Load: 8.98 kW Calculated AT: 48.1 degrees F Actual AT (Note 1): 32.7 degrees F Note 1: The actual AT represents the measured AT obtained during equilibrium conditions. | | Document Control Desk August 7, 2013 Page 2 The Technical Specifications (TS) for Certificate of Compliance (CoC) No. 1004, Amendment No. 10, |
| 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. | | §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 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 me at (315) 349-2221.Sincerely, Theresa H. Darling Acting Director Licensing cc: NRC Regional Administrator, Region I NRC Resident Inspector NRR Project Manager}} | | A summary of the thermal performance of the seventh and eighth DSCs in place at the NMPNS ISFSI is submitted for your information. |
| | Horizontal Storage Module (HSM) Model: NUHOMS Model 102 HSM Identification Number: 7DFS-HSM004G Cask: NMP61B-007-A Calculated Heat Load: 9 kW Calculated AT: 49 degrees F Actual AT (Note 1): 47.5 degrees F HSM Identification Number: 7DFS-HSM004H Cask: NMP61B-008-A Calculated Heat Load: 8.98 kW Calculated AT: 48.1 degrees F Actual AT (Note 1): 32.7 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 me at (315) 349-2221. |
| | Sincerely, Theresa H. Darling Acting Director Licensing cc: NRC Regional Administrator, Region I NRC Resident Inspector NRR Project Manager}} |
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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 IR 05000410/20243012023-12-14014 December 2023 Initial Operator Licensing Examination Report 05000410/2024301 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 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 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 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 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 ML23293A2992023-11-0808 November 2023 Amendment No. 18 to Certificate of Compliance No. 1004 for the Standardized NUHOMS System (Docket No. 72-1004, CAC No. 001028, (Enterprise Project Identifier: L-2022-LLA-0079) 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 ML23284A0642023-10-11011 October 2023 Supplement to Submittal of Biennial Reports of 72.48 Evaluations Performed for the Standardized NUHOMS System, Certificate of Compliance (CoC) 1004, for the Periods 07/26/2016 to 07/25/2018 and 7/28/2020 to 7/27/2022, Docket 72-1004 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 ML23206A0172023-09-29029 September 2023 Congressional Letters: List of Approved Spent Fuel Storage Casks: Tn Americas LLC Standardized NUHOMS Horizontal Modular Storage System, Certificate of Compliance No. 1004, Renewed Amendment No.18 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) 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 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 . 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 2024-02-01
[Table view] Category:License-Registry of Sealed Source or Device (New/Amend/Renewal)
MONTHYEARML13227A0152013-08-0707 August 2013 Independent Spent Fuel Storage Installation - General License 30-day Cask Registration Notification and First System Thermal Performance Assessment 2013-08-07
[Table view] |
Text
CENG.
a joint venture of Constellation M neM,4gyqD NINE MILE POINT NUCLEAR STATION August 7, 2013 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 ATTENTION: Document Control Desk Director, Division of Spent Fuel Storage and Transportation Office of Nuclear Material Safety and Safeguards
SUBJECT:
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 General License 30-day Cask Registration Notification and First System 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, 50-4 10 and 72-1036 Person Responsible for Ms. Theresa H. Darling Providing additional information: 315-349-2221 Cask Certificate Number: 1004 Certificate Amendment Number: 10 Cask Model Number: NUHOMSO-61BT Cask Identification Numbers: NMP6 1B-007-A, loaded July 11, 2013 NMP61B-008-A, loaded July 23, 2013 Nine Mile Point Nuclear Station, LLC P.O. Box 63, Lycoming, NY 13093
Document Control Desk August 7, 2013 Page 2 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 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 seventh and eighth DSCs in place at the NMPNS ISFSI is submitted for your information.
Horizontal Storage Module (HSM) Model: NUHOMS Model 102 HSM Identification Number: 7DFS-HSM004G Cask: NMP61B-007-A Calculated Heat Load: 9 kW Calculated AT: 49 degrees F Actual AT (Note 1): 47.5 degrees F HSM Identification Number: 7DFS-HSM004H Cask: NMP61B-008-A Calculated Heat Load: 8.98 kW Calculated AT: 48.1 degrees F Actual AT (Note 1): 32.7 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 me at (315) 349-2221.
Sincerely, Theresa H. Darling Acting Director Licensing cc: NRC Regional Administrator, Region I NRC Resident Inspector NRR Project Manager