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Category:Graphics incl Charts and Tables
MONTHYEARL-MT-21-068, 2021 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462021-12-15015 December 2021
2021 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46
ML21109A3322021-05-0404 May 2021
CoC 1004 Amendment No. 17 Appendix B Tables
ML21109A3332021-05-0404 May 2021
CoC 1004 Amendment No. 17 Appendix B Figures
ML21109A3342021-05-0404 May 2021
CoC 1004 Amendment No. 17 Appendix C
ML20308A4922020-12-21021 December 2020
Proposed CoC 1004 Amendment No. 17 Appendix B Figures
ML20308A4912020-12-21021 December 2020
Proposed CoC 1004 Amendment No. 17 Appendix B Tables
ML20308A4902020-12-21021 December 2020
Proposed CoC 1004 Amendment No. 17 Appendix B Text
L-MT-18-071, Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462018-12-12012 December 2018
Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46
ML18022A0782018-01-22022 January 2018
Enclosure 1: Revised Title for Figure 1-5 Corrected Technical Specifications for Certificate of Compliance No. 1004 Renewed Amendment No. 11, Revision 1 Enclosure 1
ML18022A0792018-01-22022 January 2018
Enclosure 2: Revised Title for Figure 1-5 Corrected Technical Specifications for Certificate of Compliance No. 1004 Renewed Amendment No. 13, Revision 1
ML16245A7202016-09-16016 September 2016
MSFHI Tables Final 8-31-2016
ML16056A1392016-03-11011 March 2016
Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports
ML14307B7072014-12-10010 December 2014
Supplemental Information Related to Development of Seismic Risk Evaluations for Information Request Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-T
L-MT-14-054, Thirty-Day Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462014-06-17017 June 2014
Thirty-Day Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46
ML14141A3992014-05-27027 May 2014
Correction Letter for License Amendment No. 180 Maximum Extended Load Line Limit Plus (Mellla+)
ML13105A1882013-04-10010 April 2013
Monticello Extended Power Uprate (Epu): Response to Request for Additional Information - Electrical Engineering Branch (TAC MD9990), Page 1 of 96 Through Page 57 of 96
L-MT-13-034, Extended Power Uprate (Epu): Response to Request for Additional Information - Electrical Engineering Branch (TAC MD9990), Page 58 of 96 Through End2013-04-10010 April 2013
Extended Power Uprate (Epu): Response to Request for Additional Information - Electrical Engineering Branch (TAC MD9990), Page 58 of 96 Through End
L-MT-08-058, Thirty (30) Day Notification Pursuant to 10CFR72.212, Conditions of General License Issued Under 6 72.210, for Storage of Spent Fuel2008-10-16016 October 2008
Thirty (30) Day Notification Pursuant to 10CFR72.212, Conditions of General License Issued Under 6 72.210, for Storage of Spent Fuel
ML0728203072007-10-11011 October 2007
Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists
ML0612402642006-06-0505 June 2006
Attachment 4 - Table L - Less Restrictive Changes for Monticello, Amendment 146 for the Conversion to the Improved Technical Specifications with Beyond-Scope Issues
ML0612402592006-06-0505 June 2006
Attachment 3 - Table M - More Restrictive Changes for Monticello, Amendment 146 for the Conversion to the Improved Technical Specifications with Beyond-Scope Issues
ML0612402552006-06-0505 June 2006
Attachment 2 - Table a - Administrative Changes for Monticello, Amendment 146 for the Conversion to the Improved Technical Specifications with Beyond-Scope Issues
ML0612402662006-06-0505 June 2006
Attachment 5 - Table La - Removed Details for Monticello, Amendment 146 for the Conversion to the Improved Technical Specifications with Beyond-Scope Issues
ML0612402692006-06-0505 June 2006
Attachment 6 - Table R - Relocated Specifications for Monticello, Amendment 146 for the Conversion to the Improved Technical Specifications with Beyond-Scope Issues
ML0613901442005-08-0404 August 2005
Web References for Monticello Dseis: Socioeconomics
ML0520105032005-08-0101 August 2005
Xcel Energy - Migratory Bird Reporting Form and Flow Chart, Revised 2003
ML0520104582005-04-11011 April 2005
NCDC Listing of Nonattainment Status for Each County by Year, as of April 11, 2005
ML0434501802003-12-11011 December 2003
NMC Program Health Status Fleet Program at a Glance
2021-05-04
[Table view]
Category:Letter type:L
MONTHYEARL-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-23-028, 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-23-032, 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-23-031, 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-23-020, Submittal of 2022 Annual Radioactive Effluent Release Report2023-05-10010 May 2023
Submittal of 2022 Annual Radioactive Effluent Release Report
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-23-021, 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-22-052, 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-22-049, Industry Groundwater Protection Initiative Special Report2022-12-15015 December 2022
Industry Groundwater Protection Initiative Special Report
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
L-MT-22-007, Response to Request for Additional Information for the Monticello Nuclear Generating Plant Alternative Request VR-08 (EPID: L-MT-22-007)2022-07-22022 July 2022
Response to Request for Additional Information for the Monticello Nuclear Generating Plant Alternative Request VR-08 (EPID: L-MT-22-007)
L-MT-22-026, Changes to the Emergency Plan2022-07-19019 July 2022
Changes to the Emergency Plan
L-MT-22-024, Response to a Request for Additional Information for the Monticello Nuclear Generating Plant Related to the Amendment to Adopt Advanced Framatome Methodologies2022-06-0606 June 2022
Response to a Request for Additional Information for the Monticello Nuclear Generating Plant Related to the Amendment to Adopt Advanced Framatome Methodologies
L-MT-22-022, Response to a Request for Additional Information: Monticello Alternative VR-10, Excess Flow Check Valve Testing Frequency2022-05-25025 May 2022
Response to a Request for Additional Information: Monticello Alternative VR-10, Excess Flow Check Valve Testing Frequency
L-MT-22-018, 2021 Annual Radioactive Effluent Release Report2022-05-11011 May 2022
2021 Annual Radioactive Effluent Release Report
L-MT-22-017, 2021 Annual Radiological Environmental Operating Report2022-05-11011 May 2022
2021 Annual Radiological Environmental Operating Report
L-MT-22-016, 2021 Annual Report of Individual Monitoring2022-04-28028 April 2022
2021 Annual Report of Individual Monitoring
L-MT-22-019, Withdrawal of Requests for Relief from ASME OM Code for the Sixth Inservice Testing Interval2022-04-18018 April 2022
Withdrawal of Requests for Relief from ASME OM Code for the Sixth Inservice Testing Interval
L-MT-22-010, License Amendment Request to Revise Technical Specification 3.6.1.8 Residual Heat Removal (RHR) Drywell Spray Header and Nozzle Surveillance Frequency2022-03-18018 March 2022
License Amendment Request to Revise Technical Specification 3.6.1.8 Residual Heat Removal (RHR) Drywell Spray Header and Nozzle Surveillance Frequency
L-MT-22-012, Special Report for the Bypass of the Offgas Treatment Storage System2022-03-15015 March 2022
Special Report for the Bypass of the Offgas Treatment Storage System
L-MT-22-008, 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval Alternative Related to Excess Flow Check Valve Testing Frequency (L-MT-22-008)2022-03-0707 March 2022
10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval Alternative Related to Excess Flow Check Valve Testing Frequency (L-MT-22-008)
L-MT-22-006, 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval OMN-26 (L-MT-22-006)2022-02-18018 February 2022
10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval OMN-26 (L-MT-22-006)
2024-01-11
[Table view] |
Text
October 16,2008 L-MT-08-058 10 CFR 72.212(b)(l)(ii)
ATTN: Document Control Desk Director, Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Monticello Nuclear Generating Plant Docket 50-263 License No. DPR-22 ISFSl License No.72-058 Thirty (30) Dav Notification Pursuant to 10CFR72.212, "Conditions of General License Issued Under 6 72.210," for Storage of Spent Fuel Pursuant to 10 CFR 72.212(b)(l)(ii), Northern States Power Company, a Minnesota corporation (NSPM) hereby provides notification of the use of a spent fuel cask on September 17, 2008 at the Monticello Nuclear Generating Plant (MNGP).
Licensee Name: Northern States Power - Minnesota Licensee Address: Monticello Nuclear Generating Station 2807 W. County Road 75 Monticello, MN 55362 Reactor License No.: DPR-22 Reactor Docket No.: 50-263 Cask Certificate No.: 1004 Cask Model No.: NUHOMS 8 - 61BT Cask Identification No.: MNP-61BTH-1-A-3-004 As required by Amendment 9 of the Certificate of Compliance 1004, NSPM is providing the results of the initial thermal performance in Enclosure 1.
This letter makes no new commitments or changes to any existing commitments.
2807 West County Road 75 Monticello, Minnesota 55362-9637 Telephone: 763.295.5151
USNRC Page 2 of 2 ns, please contact Tim Blake, Regulatory Affairs Manager, at nticello Nuclear Generating Plant Company, a Minnesota corporation (NSPM) cc: Administrator, Region Ill, USNRC Project Manager, Monticello, USNRC Resident Inspector, Monticello, USNRC Minnesota Department of Commerce
L-MT-08-058 Enclosure 1 Page 1 of 3 Enclosure 1 - Summary Report of Cask System Heat Removal Characteristics This report summarizes the results of initial thermal performance testing required by Certificate of Compliance 1004, Amendment 9, issued to Transnuclear, Inc. for the Standardized NUHOMSB Horizontal Modular Storage System for Irradiated Nuclear Fuel.
C of C 1004 Technical Specification Requirement 1. I .7, "Special Requirements for First System in Place", requires that the thermal performance of the cask system be assessed and reported to the NRC for the first Dry Shielded Canister (DSC) placed in service for a particular cask system. The thermal performance of the cask system is assessed by measuring the Horizontal Storage Module (HSM) air inlet and outlet temperatures for normal airflow, as described in C of C 1004 Technical Specification 1.2.8, "HSM Maximum Air Exit Temperature with a Loaded 24P, 52B, 61BT, 32PT, 24PHB or 24PTH-S-LC Only". This report also needs to be generated for any subsequent DSCs placed in service which contain higher heat loads.
A letter report summarizing the results of the measurements is to be submitted to the NRC for evaluation and assessment of the heat removal characteristics of the cask in place within 30 days of placing the DSC in service.
MNGP's use of the NUHOMSB-61BT DSC stored in the NUHOMSB HSM Model 202 for the 2008 loading campaign constitutes the first use of this cask system.
DSC model NUHOMSB-61BT, serial number MNP-61BTH-1-A-3-004, was placed in a NUHOMSB HSM Model 202, serial number HSM-IB, on September 17,2008. The decay heat load is approximately 10.4 kW.
This is the first DSC to be loaded at MNGP. Projected decay heat loads for the remaining casks in the MNGP 2008 loading campaign are lower than the heat load for this initial DSC, so it is anticipated that no further reporting under Technical Specification 1. I .7 will be required for this campaign.
Test Methodology Reference 1 was used to establish maximum acceptable HSM air temperature rise (AT) as a function of heat load and ambient temperature, as required by C of C Technical Specification 1.2.8. The calculation used the same methodology documented in the NUHOMSB UFSAR (Reference 2), as required by Technical Specification 1.2.8. As discussed in the Bases for Technical Specification 1.2.8, "The specified temperature rise is selected to ensure the fuel clad and concrete temperatures are maintained at or below acceptable long-term storage limits."
L-MT-08-058 Enclosure 1 Page 2 of 3 Thermal performance testing was conducted as described in and required by Technical Specification 1.2.8. Daily inlet air temperature (ambient) and HSM outlet air temperature measurements were performed until thermal equilibrium was reached.
Test Results Initial thermal performance testing results are shown in Table 1 and Figure 1.
The test data were within the maximum acceptable HSM temperature rise (AT) established by Reference 1, as shown in Table 1, except for two readings taken prior to reaching thermal equilibrium which exceeded the calculated limit.
Those two readings (taken 9/25/08 and 9/28/08) were recorded when ambient temperature was at its lowest point of the day, following large ambient temperature drops. The calculated maximum temperature rise limits are based on a 24-hour average ambient temperature, and thus taking temperature readings at the daily ambient temperature low point results in maximized temperature rises which do not represent actual system performance, as the HSMIDSC system with its large thermal inertia cools down much more slowly than the atmosphere.
MNGP has determined that the NUHOMSB storage system is performing as designed, as demonstrated by the measured equilibrium temperature rise (AT).
References
- 1. Transnuclear Calculation NUH004-0433, Revision 1, Air Flow Calculation for NUHOMSB HSM Model 202 with 61BT DSC.
- 2. Transnuclear NUH003, Revision 10, Updated Final Safety Analysis Report For The Standardized NUHOMSB Horizontal Modular Storage System For Irradiated Nuclear Fuel.
L-MT-08-058 Enclosure 1 Page 3 of 3 Table 1 DSCIHSM-1B Data Ambient Avg Exhaust Measured Delta Calculated Delta Date I Time Temperature ("F) Temperature (OF) (AT OF) (AT OF) 9/17/0823:38 58.0 84.5 26.5 34.0 9/19/080:43 66.0 84.5 18.5 35.0 9/20/080:53 58.0 86.5 28.5 34.0 9/21/081 :25 55.0 85.5 30.5 34.0 9/22/080:33 68.0 89.0 21 .O 35.0 9/23/080:53 68.0 89.0 21 .O 35.0 9/24/080:17 60.0 93.0 33.0 35.0 9/25/080:07 51.0 87.5 36.5 34.0 9/26/080:44 66.0 85.0 19.0 35.0 9/27/080:41 67.0 89.0 22.0 35.0 9/28/084:17 49.0 85.0 36.0 34.0 9/28/0823:33 57.0 82.5 25.5 34.0 9/29/0816:15 60.0 87.0 27.0 35.0 Figure 1 DSCIHSM-1B Temperature Data
+Ambient Temperature ("F)
&A4 Exhaust Temperature ("F) 100 90 80 70 G
L 60 "E
g!
n so cE 40 30 20 10 0
9117/2008 911 9/2008 9/21/2008 9/23/2008 9/25/2008 9/27/2008 9/29/2008 1011ROO8 Date
