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Category:Letter type:L
MONTHYEARL-MT-24-028, Response to RCI for RR-017 ISI Impracticality2024-08-28028 August 2024 Response to RCI for RR-017 ISI Impracticality L-MT-24-022, – Preparation and Scheduling of Operator Licensing Examinations2024-07-0909 July 2024 – Preparation and Scheduling of Operator Licensing Examinations L-MT-24-019, Submittal of ASME Section XI, Section IWB-3720 Analytical Evaluation in Accordance with 10 CFR 50.55a(b)(2)(xliii)2024-06-10010 June 2024 Submittal of ASME Section XI, Section IWB-3720 Analytical Evaluation in Accordance with 10 CFR 50.55a(b)(2)(xliii) L-MT-24-017, Response to Request for Additional Information Regarding License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6 (EPID-L-2023-LLA-01602024-06-0404 June 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6 (EPID-L-2023-LLA-0160 L-MT-24-015, Response to Request for Additional Information - Alternative Request VR-09 for OMN-172024-05-16016 May 2024 Response to Request for Additional Information - Alternative Request VR-09 for OMN-17 L-MT-24-013, 2023 Annual Radiological Environmental Operating Report2024-05-14014 May 2024 2023 Annual Radiological Environmental Operating Report L-MT-24-016, 2023 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP)2024-05-0808 May 2024 2023 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP) L-MT-24-002, Submittal of Revision 41 to the Updated Safety Analysis Report2024-04-17017 April 2024 Submittal of Revision 41 to the Updated Safety Analysis Report L-MT-24-004, Submittal of 10 CFR 72.48 Report for Monticello Nuclear Generating Plant (MNGP)2024-04-17017 April 2024 Submittal of 10 CFR 72.48 Report for Monticello Nuclear Generating Plant (MNGP) L-MT-24-006, Subsequent License Renewal Application Annual Update 1 and Supplement 92024-02-29029 February 2024 Subsequent License Renewal Application Annual Update 1 and Supplement 9 L-MT-24-007, Response to NRC Request for Additional Information on Proposed Inservice Inspection Alternative RR-002 for the Sixth Ten-Year ISI Interval2024-02-15015 February 2024 Response to NRC Request for Additional Information on Proposed Inservice Inspection Alternative RR-002 for the Sixth Ten-Year ISI Interval L-MT-24-001, 10 CFR 50.55a Request RR-017 - Inservice Inspection (ISI) Impracticality in Accordance with 10 CFR 50.55a(g)(5)(iii) During the Fifth Ten-Year Interval2024-01-30030 January 2024 10 CFR 50.55a Request RR-017 - Inservice Inspection (ISI) Impracticality in Accordance with 10 CFR 50.55a(g)(5)(iii) During the Fifth Ten-Year Interval L-MT-23-054, Subsequent License Renewal Application Supplement 82024-01-11011 January 2024 Subsequent License Renewal Application Supplement 8 L-MT-23-047, License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data2023-12-29029 December 2023 License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data L-MT-23-056, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 22023-12-18018 December 2023 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 2 L-MT-23-042, 2023 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462023-12-11011 December 2023 2023 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46 L-MT-23-052, Subsequent License Renewal Application Supplement 72023-11-30030 November 2023 Subsequent License Renewal Application Supplement 7 L-MT-23-051, Update to the Technical Specification Bases2023-11-28028 November 2023 Update to the Technical Specification Bases L-MT-23-049, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 12023-11-21021 November 2023 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 L-MT-23-043, 10 CFR 50.55a(z)(1) Request Regarding OMN-17, Revision 1. VR-092023-11-13013 November 2023 10 CFR 50.55a(z)(1) Request Regarding OMN-17, Revision 1. VR-09 L-MT-23-038, License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.62023-11-10010 November 2023 License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6 L-MT-23-046, Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 12023-11-0909 November 2023 Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 1 L-MT-23-041, Subsequent License Renewal Application Response to Request for Confirmation of Information Set 22023-10-0303 October 2023 Subsequent License Renewal Application Response to Request for Confirmation of Information Set 2 L-MT-23-037, Subsequent License Renewal Application Response to Request for Additional Information Set 32023-09-22022 September 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 3 L-MT-23-036, Subsequent License Renewal Application Response to Request for Additional Information Set 2 and Supplement 62023-09-0505 September 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 2 and Supplement 6 L-MT-23-035, Subsequent License Renewal Application Supplement 52023-08-28028 August 2023 Subsequent License Renewal Application Supplement 5 L-MT-23-034, Subsequent License Renewal Application Response to Request for Additional Information Set 12023-08-15015 August 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 1 L-MT-23-032, 10 CFR 50.55a(z)(2) Request Regarding MO-2397, VR-112023-07-31031 July 2023 10 CFR 50.55a(z)(2) Request Regarding MO-2397, VR-11 L-MT-23-028, 2023 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report2023-07-31031 July 2023 2023 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report L-MT-23-031, Subsequent License Renewal Application Supplement 4 and Responses to Request for Confirmation of Information - Set 12023-07-18018 July 2023 Subsequent License Renewal Application Supplement 4 and Responses to Request for Confirmation of Information - Set 1 L-MT-23-030, Subsequent License Renewal Application Supplement 32023-07-0404 July 2023 Subsequent License Renewal Application Supplement 3 L-MT-23-025, Subsequent License Renewal Application Supplement 22023-06-26026 June 2023 Subsequent License Renewal Application Supplement 2 L-MT-23-019, Submittal of 2022 Annual Radiological Environmental Operating Report2023-05-10010 May 2023 Submittal of 2022 Annual Radiological Environmental Operating Report L-MT-23-020, Submittal of 2022 Annual Radioactive Effluent Release Report2023-05-10010 May 2023 Submittal of 2022 Annual Radioactive Effluent Release Report L-MT-23-021, Core Operating Limits Report (COLR) for the Monticello Nuclear Generating Plant for Cycle 322023-05-0202 May 2023 Core Operating Limits Report (COLR) for the Monticello Nuclear Generating Plant for Cycle 32 L-MT-23-017, 2022 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP)2023-04-18018 April 2023 2022 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP) L-MT-23-010, Subsequent License Renewal Application Supplement 12023-04-0303 April 2023 Subsequent License Renewal Application Supplement 1 L-MT-23-013, Core Operating Limits Report (COLR) for Cycle 31, Revision 32023-03-28028 March 2023 Core Operating Limits Report (COLR) for Cycle 31, Revision 3 L-MT-23-012, Core Operating Limits Report (COLR) for Monticello Nuclear Generating Plant Cycle 31, Revision 22023-03-17017 March 2023 Core Operating Limits Report (COLR) for Monticello Nuclear Generating Plant Cycle 31, Revision 2 L-MT-23-008, 10CFR50.55a Request to Use Later Edition of ASME Section XI for ISI Code of Record (RR-003)2023-02-0707 February 2023 10CFR50.55a Request to Use Later Edition of ASME Section XI for ISI Code of Record (RR-003) L-MT-23-004, CFR 50.55a Request RR-001, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI for the Monticello Third Interval Containment Inservice Inspection Program2023-01-23023 January 2023 CFR 50.55a Request RR-001, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI for the Monticello Third Interval Containment Inservice Inspection Program L-MT-23-005, Response to the NRC Request for Additional Information Regarding the 50.55a Request Pr 08, HPCI Pump Quarterly Testing (EPID Number L-2022-LLR-0088)2023-01-0606 January 2023 Response to the NRC Request for Additional Information Regarding the 50.55a Request Pr 08, HPCI Pump Quarterly Testing (EPID Number L-2022-LLR-0088) L-MT-22-049, Industry Groundwater Protection Initiative Special Report2022-12-15015 December 2022 Industry Groundwater Protection Initiative Special Report L-MT-22-052, L-MT-22-052 Monticello Nuclear Generating Plant 10 CFR 50.55a Request No. Pr 08, Request for HPCI Pump Quarterly Alternative2022-12-15015 December 2022 L-MT-22-052 Monticello Nuclear Generating Plant 10 CFR 50.55a Request No. Pr 08, Request for HPCI Pump Quarterly Alternative L-MT-22-046, 2022 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462022-12-13013 December 2022 2022 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46 L-MT-22-048, Update to the Monticello Technical Specification Bases2022-11-28028 November 2022 Update to the Monticello Technical Specification Bases L-MT-22-047, Withdrawal of Request for Relief from ASME OM Code for the Sixth Inservice Testing Interval2022-11-10010 November 2022 Withdrawal of Request for Relief from ASME OM Code for the Sixth Inservice Testing Interval L-MT-22-045, Letter Submitting Post-Exam Package2022-11-0404 November 2022 Letter Submitting Post-Exam Package L-MT-22-030, Sixth Interval Inservice Testing (1ST) Plan2022-09-0606 September 2022 Sixth Interval Inservice Testing (1ST) Plan L-MT-22-037, Supplement to 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval, Alternative VR-10, Excess Flow Check Valve Testing Frequency2022-08-29029 August 2022 Supplement to 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval, Alternative VR-10, Excess Flow Check Valve Testing Frequency 2024-08-28
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2807 West County Road 75 Monticello, MN 55362 (l Xcel Energy RESPONSIBLE BY NATURE 800.895.4999 xcelenergy. com September 28, 2018 L-MT-18-055 10 CFR 72.212(b)(2)
U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Director, Division of Spent Fuel Management Office of Nuclear Material Safety and Safeguards Washington, DC 20555-0001 Monticello Nuclear Generating Plant Docket 50-263 Renewed Facility Operating License No. DPR-22 Independent Spent Fuel Storage Installation Docket No. 72-58 Thirty (30) Day Notification Pursuant to 10 CFR 72.212, Conditions of General License Issued Under 10 CFR 72.210, for the Storage of Spent Fuel In accordance with 10 CFR 72.212(b)(2), Northern States Power Company- Minnesota (NSPM),
doing business as Xcel Energy, Inc., is registering the use of two U. S. Nuclear Regulatory Commission (NRG) approved spent fuel storage casks at the Monticello Nuclear Generating Plant (MNGP) Independent Spent Fuel Storage Installation (ISFSI). Registration of a cask is required no later than 30 days after using that spent fuel storage cask to store spent fuel in accordance with 10 CFR 72.212(b)(2). Cask-specific registration information is provided for each NUHOMS-61 BTH dry shielded canister (DSC) in Enclosure 1. of this letter provides a summary of the results of the thermal performance assessment for the highest heat load DSC as required by the General Requirements and Conditions of the Technical Specifications for Amendment No. 10, Revision 1 to Certificate of Compliance No. 1004, Section 1.1.7, "Special Requirements for First System in Place." Enclosure 2 provides the results of the thermal performance assessment for DSC MN P 61BTH-1-B-2-019 and MN P 61 BTH-1-B 020 which have successively higher heat loads to date.
If you have any questions or require additional information, please contact Mr. Stephen Sollom, Regulatory Affairs Sr. Engineer, at (612) 342-8982.
Document Control Desk L-MT-18-055 Page 2 of 2 Summary of Commitments This letter makes no new commitments and no revisions to existing commitments.
'*-~
ris pher R. Church Site Vice President, Monticello Nuclear Generating Plant Northern States Power Company - Minnesota Enclosures(2) cc: Administrator, Region Ill, USNRC Project Manager, Monticello, USNRC Resident Inspector, Monticello, USNRC Minnesota Department of Commerce
ENCLOSURE 1 MONTICELLO NUCLEAR GENERATING PLANT
SUMMARY
OF REGISTRATION INFORMATION FOR THE DRY SHIELDED CANISTERS LOADED DURING THE 2018 LOADING CAMPAIGN 1 Page Follows
L-MT-18-055 Page 1 of 1
SUMMARY
OF REGISTRATION INFORMATION FOR THE DRY SHIELDED CANISTERS LOADED DURING THE 2018 LOADING CAMPAIGN HSM Model HSM Date Placed Number Serial into Service Number Cask Certificate of No. 1004 Compliance:
Cask Amendment Amendment 10, Number: Revision 1 DSC Model NUHOMS-61 BTH Number:
DSC Serial MNP-61 BTH-1-B NUHOMS HSM- HSM-9B 8/30/2018 Number: 019 H MNP-61 BTH-1-B NUHOMS HSM- HSM- 9/13/2018 020 H 10B
ENCLOSURE 2 MONTICELLO NUCLEAR GENERATING PLANT
SUMMARY
OF THE THERMAL PERFORMANCE OF THE MNP-61BTH-1-B-2-019 AND MNP-61BTH-1-B-2-020 DRY SHIELDED CANISTERS 6 Pages Follow
L-MT-18-055 Page 1 of 6
SUMMARY
OF THE THERMAL PERFORMANCE OF THE MNP-61 BTH-1-8-2-019 DRY SHIELDED CANISTER On August 30, 2018 the Monticello Nuclear Generating Plant (MNGP) placed NUHOMS-61 BTH Dry Shielded Canister (DSC) Serial No. MNP-61 BTH-1-B-2-019 into storage. Technical Specification 1.1.7 of Certificate of Compliance 1004, Amendment 10 requires that the heat transfer characteristics of the system be recorded by temperature measurements of the first DSC placed in service and any subsequent DSCs contain ing higher decay heat loads. DSC MNP-61 BTH-1-B 011 was the first DSC placed in service under CoC 1004 Amendment 10 on 09/09/2013. DSC MNP-61 BTH-1-B-2-019 has the highest heat load to date. The thermal performance of the system will be assessed by measuring the air inlet and outlet temperature for normal airflow through the HSM in accordance with Technical Specification 1.2.8b.
Technical Specification 1.1.7 requires that a letter report be submitted to the NRC for the evaluation and assessment of the heat removal characteristics of the loaded DSC in the HSM within 30 days of placing the DSC in service, in accordance with 10 CFR 72.4. This report is being submitted to meet this requirement.
System Information DSC Serial Number: MNP-61 BTH-1-B-2-019 DSC Model: NUHOMS-61 BTH Total Decay Heat Load for 11.716 kW DSC:
HSM Serial Number: HSM-9B HSM Model: HSM-H Certificate of Compliance: No. 1004, Amendment 10, Revision 1
L-MT-18-055 Page 2 of 6 As required by Technical Specification 1.2.8b, inlet and outlet vent temperatures for HSM-9B were taken daily. These readings are shown in Figure 1.
Figure 1- HSM-98 Inlet and Outlet Vent Temperatures 110 100 - ~
90
~ ~
80 - - - - - - - - - - - - - - - ... ... ...
70 ..... ~ --- - - - - - - - - .
U::- 60 QI
- so
+,I
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~ 40 E
{E. 30 20 10 0
8/31/2018 9/1/2018 9/2/2018 9/3/2018 9/4/2018 9/5/2018 9/6/2018 Date
- - HSM-H Inlet - HSM-H Outlet Technical Specification 1.2.8b requires that, if a 61 BTH DSC is placed in the HSM-H with a heat load less than 31.2 kW, the limiting difference between outlet and ambient temperatures shall be determined by a calculation performed by the user using the same methodology and inputs documents in Appendix T of the Standardized NU HOMS FSAR. Transnuclear calculation NUH61 BTH-0425, NUHOMS HSM-H Air Temperature Rise vs. Decay Heat Calculation establishes acceptance criteria for the temperature rise across the HSM-H vents for varying ambient temperatures and decay heat loads.
Data on the Temperature Rise across the inlet and outlet vents of HSM-9B are shown in Figure 2, along with the associated allowable temperature difference from Transnuclear calculation NUH61 BTH-0425.
L-MT-18-055 Page 3 of 6 Figure 2 - HSM-9B Vent Temperature Difference 40 35 30 25 U:-
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20 QJ
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QJ 0.
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0 I I 8/31/2018 9/1/2018 9/2/2018 9/3/2018 9/4/2018 9/5/2018 9/6/2018 Date Temperature Difference - Allowable The system reached thermal equilibrium on or before September 4, 2018 with additional data collected through September 6, 2018 for trending. On September 6, the temperature difference across the inlet and outlet vents was 14.9°F. This is below the acceptance criteria of 38.6°F.
MNGP has determined the system is functioning as designed.
L-MT-18-055 Page 4 of 6
SUMMARY
OF THE THERMAL PERFORMANCE OF THE MNP-61 BTH-1-B-2-020 DRY SHIELDED CANISTER On September 13, 2018 the Monticello Nuclear Generating Plant (MNGP) placed NUHOMS-61BTH Dry Shielded Canister (DSC) Serial No. MNP-61 BTH-1-B-2-020 into storage. Technical Specification 1.1. 7 of Certificate of Compliance 1004, Amendment 10 requires that the heat transfer characteristics of the system be recorded by temperature measurements of the first DSC placed in service and any subsequent DSCs containing higher decay heat loads. DSC MNP-61 BTH-1-B 020 has the highest heat load to date at the time of loading into the Horizontal Storage Module (HSM). The thermal performance of the system will be assessed by measuring the air inlet and outlet temperature for normal airflow through the HSM in accordance with Technical Specification 1.2.8b.
Technical Specification 1.1 .7 requires that a letter report be submitted to the NRC for the evaluation and assessment of the heat removal characteristics of the loaded DSC in the HSM within 30 days of placing the DSC in service, in accordance with 10 CFR 72.4. This report is being submitted to meet this requirement.
System Information DSC Serial Number: MNP-61 BTH-1-B-2-020 DSC Model: NUHOMS-61 BTH Total Decay Heat Load for 11.719kW DSC:
HSM Serial Number: HSM-10B HSM Model: HSM-H Certificate of Compliance: No. 1004, Amendment 10, Revision 1
L-MT-18-055 Page 5 of 6 As required by Technical Specification 1.2.8b, inlet and outlet vent temperatures for HSM-1 OB were taken daily. These readings are shown in Figure 3.
Figure 3 - HSM-10B Inlet and Outlet Vent Temperatures 110 100
--- ... .. - - - - - - ~
90
' ~
80 70 U:-60 ' '-
QJ
- i 50
+-'
....co QJ 40 a.
E
~ 30 20 10 0
9/14/2018 9/15/2018 9/16/2018 9/17/2018 9/18/2018 9/19/2018 Date
- - HSM-H Inlet - HSM-H Outlet Technical Specification 1.2.8b requires that, if a 61 BTH DSC is placed in the HSM-H with a heat load less than 31 .2 kW, the limiting difference between outlet and ambient temperatures shall be determined by a calculation performed by the user using the same methodology and inputs documents in Appendix T of the Standardized NU HOMS FSAR. Transnuclear calculation NUH61 BTH-0425, NUHOMS HSM-H Air Temperature Rise vs. Decay Heat Calculation establishes acceptance criteria for the temperature rise across the HSM-H vents for varying ambient temperatures and decay heat loads.
Data on the Temperature Rise across the inlet and outlet vents of HSM-1 OB are shown in Figure 4, along with the associated allowable temperature difference from Transnuclear calculation NUH61 BTH-0425.
L-MT-18-055 Page 6 of 6 Figure 4 - HSM-10B Vent Temperature Difference 40 35 30 25 i::L
...:::s
';' 20
+-'
~ 15 Q) a.
E
~ 10 5
0 9/14/2018 9/15/2018 9/16/2018 9/17/2018 9/18/2018 9/ 19/ 2018 Date
- - Temperature Difference - Allowable The system reached thermal equilibrium on or before September 19, 2018. At that time the temperature difference across the inlet and outlet vents was 19.9°F. This is below the acceptance criteria of 37.4 °F. MNGP has determined the system is functioning as designed.