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MONTHYEARML13011A2732013-01-11011 January 2013 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance Review License Amendment Request to Modify E-Plan - Revise EAL Setpoint for the Tbnws Rad Monitor Project stage: Acceptance Review ML13102A1942013-04-11011 April 2013 NRR E-mail Capture - Monticello Nuclear Generating Plant - Request for Additional Information License Amendment Request to Revise EAL RA1.2 Project stage: RAI ML13274A1732014-01-28028 January 2014 Issuance of License Amendment No. 177 to Renewed Facility Operating License Emergency Plan Change Project stage: Approval 2013-04-11
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Category:Letter
MONTHYEARIR 05000263/20240052024-08-30030 August 2024 Updated Inspection Plan and Follow-Up Letter for Monticello Nuclear Generating Plant, Unit 1 (Report 05000263/2024005) L-MT-24-028, Response to RCI for RR-017 ISI Impracticality2024-08-28028 August 2024 Response to RCI for RR-017 ISI Impracticality 05000263/LER-2024-002, Low Pressure Coolant Injection Inoperable Due to Motor Valve Failure2024-08-27027 August 2024 Low Pressure Coolant Injection Inoperable Due to Motor Valve Failure ML24222A1822024-08-27027 August 2024 – Proposed Alternative Request VR-09 to the Inservice Testing Requirements of the ASME OM Code for Main Steam Safety Relief Valves IR 05000263/20244202024-08-21021 August 2024 Security Baseline Inspection Report 05000263/2024420 - Cover Letter IR 05000263/20240022024-08-14014 August 2024 Integrated Inspection Report 05000263/2024002 ML24218A2282024-08-0505 August 2024 Request for Confirmation of Information for Relief Request RR-017, Inservice Inspection Impracticality During the Fifth Ten-Year Interval ML24208A1502024-07-26026 July 2024 Independent Spent Fuel Storage Installation - Submittal of Quality Assurance Topical Report (NSPM-1) ML24215A2992024-07-23023 July 2024 Minnesota State Historic Preservation Office Comments on Monticello SLR Draft EIS ML24198A2372024-07-18018 July 2024 Information Request to Support Upcoming Biennial Problem Identification and Resolution (Pi&R) Inspection at Monticello Nuclear Generating Plant L-MT-24-022, – Preparation and Scheduling of Operator Licensing Examinations2024-07-0909 July 2024 – Preparation and Scheduling of Operator Licensing Examinations ML24164A2402024-06-10010 June 2024 Minnesota State Historic Preservation Office- Comments on Draft Monticello SLR Draft EIS 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 ML24137A2792024-06-0303 June 2024 Audit Summary for License Amendment Request to Revise Technical Specification 3.8.6, Battery Parameters, Surveillance Requirement 3.8.6.6 IR 05000263/20244012024-05-30030 May 2024 Public - Monticello Nuclear Generating Plant - Cyber Security Inspection Report 05000263/2024401 ML24141A1292024-05-22022 May 2024 Northern States Power Company - Use of Encryption Software for Electronic Transmission of Safeguards Information ML24141A1782024-05-20020 May 2024 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection 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 ML24135A1902024-05-14014 May 2024 Submittal of 2023 Annual Radioactive Effluent Release Report IR 05000263/20240102024-05-13013 May 2024 Age-Related Degrading Inspection Report 05000263/2024010 ML24127A1472024-05-0909 May 2024 Letter to Mille Lacs Band- Section 106 Consultation Regarding the Monticello Nuclear Generating Plant Subsequent License Renew. Application ML24128A0042024-05-0909 May 2024 Letter to Minnesota State Historic Preservation Office- Section 106 Consultation Regarding the Monticello Nuclear Generating Plant Subsequent License Renewal Application 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) ML24089A2382024-04-29029 April 2024 Summary of Nuclear Property Insurance IR 05000263/20240012024-04-29029 April 2024 Plan - Integrated Inspection Report 05000263/2024001 L-MT-24-012, Reactor Scram, Containment Isolation, and Cooldown Rate Outside of Limits Following Technician Adjustment of Wrong Component2024-04-25025 April 2024 Reactor Scram, Containment Isolation, and Cooldown Rate Outside of Limits Following Technician Adjustment of Wrong Component ML24115A2922024-04-25025 April 2024 Sec106 Tribal, Jensvold, Kevin-Upper Sioux Community ML24115A2912024-04-25025 April 2024 Sec106 Tribal, Jacskon, Sr., Faron-Leech Lake Band of Ojibwe ML24115A2882024-04-25025 April 2024 Sec106 Tribal, Fairbanks, Michael-White Earth Nation.Docx ML24115A3032024-04-25025 April 2024 Sec106 Tribal, Taylor, Louis-Lac Courte Oreilles Band of Lake Superior Chippewa Indians ML24115A3052024-04-25025 April 2024 Sec106 Tribal, Vanzile, Jr., Robert-Sokaogon Chippewa Community ML24115A3012024-04-25025 April 2024 Sec106 Tribal, Seki, Darrell-Red Lake Nation ML24115A2872024-04-25025 April 2024 Sec106 Tribal, Dupuis, Kevin-Fond Du Lac Band of Lake Superior Chippewa ML24115A3002024-04-25025 April 2024 Sec106 Tribal, Rhodd, Timothy-Iowa Tribe of Kansas and Nebraska ML24115A2962024-04-25025 April 2024 Sec106 Tribal, Larsen, Robert-Lower Sioux Indian Community ML24115A2932024-04-25025 April 2024 Sec106 Tribal, Johnson, Grant-Prairie Island Indian Community ML24115A2892024-04-25025 April 2024 Sec106 Tribal, Fowler, Thomas-St. Croix Chippewa of Wisconsin ML24115A3022024-04-25025 April 2024 Sec106 Tribal, Stiffarm, Jeffrey-Fort Belknap Indian Community ML24115A3072024-04-25025 April 2024 Sec106 Tribal, Williams, Jr., James-Lac Vieux Desert Band of Lake Superior Chippewa Indians ML24115A2942024-04-25025 April 2024 Sec106 Tribal, Johnson, John-Lac Du Flambeau Band of Lake Superior Chippewa Indians ML24115A3062024-04-25025 April 2024 Sec106 Tribal, Wassana, Reggie-Cheyenne and Arapaho Tribes ML24115A2992024-04-25025 April 2024 Sec106 Tribal, Renville, J. Garret-Sisseton Wahpeton Oyate of the Lake Travers Reservation ML24115A2902024-04-25025 April 2024 Sec106 Tribal, Jackson-Street, Lonna-Spirit Lake Nation ML24115A2952024-04-25025 April 2024 Sec106 Tribal, Kakkak, Gena-Menominee Indian Tribe of Wisconsin ML24115A2972024-04-25025 April 2024 Sec106 Tribal, Miller, Cole-Shakopee Mdewakanton Sioux Community ML24115A2982024-04-25025 April 2024 Sec106 Tribal, Reider, Anthony-Flandreau Santee Sioux Tribe ML24106A1102024-04-24024 April 2024 Mille Lacs Band of Ojibwe -Monticello Sec106 Tribal ML24115A2792024-04-24024 April 2024 Sec106 Tribal, Blaker, Doreen-Keweenaw Bay Indian Community 2024-08-05
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML23262B2272023-09-21021 September 2023 September 21, 2023, Pre-Submittal Meeting on License Amendment Request to Revise PTLR to Incorporate New Surveillance Capsule Data (EPID L-2023-LRM-0070) (Slides) ML22357A1002023-03-31031 March 2023 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Issuance of Amendments Standard Emergency Plan and Consolidated Emergency Operations Facility ML23012A1562023-01-13013 January 2023 Issuance of Amendment No. 210 Re Revised Methodologies for Determining the Core Operating Limits (EPID L-2021-LLA-0144) - Non-proprietary ML22318A2152022-12-27027 December 2022 Issuance of Amendment No. 209 Ten-Year Inspection of the Diesel Generator Fuel Oil Storage Tank ML22308A1962022-11-10010 November 2022 Regulatory Audit Report Regarding License Amendment Request to Transition to Atrium 11 Fuel ML22264A1062022-10-31031 October 2022 Issuance of Amendment No. 208 Residual Heat Removal Drywell Spray Header and Nozzle Surveillance Frequency ML22208A2192022-08-0303 August 2022 Summary of July 25, 2022, Meeting with Northern States Power Company, Doing Business as Xcel Energy, Related to the Amendment to Adopt Advanced Framatome Inc. Methodology for Determining Core Operating Limits for Monticello Plant ML21223A2802021-10-15015 October 2021 Issuance of Amendment No. 207 Adoption of TSTF-564 Safety Limit MCPR ML21148A2742021-07-12012 July 2021 Issuance of Amendment No. 206 TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML20352A3492021-01-0808 January 2021 Issuance of Amendment No. 205, Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-582, RPV WIC Enhancements, and TSTF-583-T, TSTF-582 Diesel Generator Variation ML20210M0142020-09-0808 September 2020 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Issuance of Amendment Nos. 204, 231, and 219 TSTF-529 Clarify Use and Application Rules ML20153A8042020-07-31031 July 2020 Co. - Issuance of Amendments Revising Emergency Action RA3 ML19176A4212019-08-29029 August 2019 Issuance of Amendment No. 203 Adoption of 10 CFR 50.69 ML19162A0932019-07-30030 July 2019 Issuance of Amendment No, 202 Regarding Deletion of the Note Associated with Technical Specification 3.5.1., Erccs - Operating ML19074A2692019-04-22022 April 2019 Non-Proprietary - Issuance of Amendment Revision to Technical Specifications 2.1.2 Safety Limit Minimum Critical Power Ratio ML19065A2002019-03-11011 March 2019 Correction to License Amendment No. 200 Related to Adoption of TSTF-425, Relocated Surveillance Frequencies to Licensee Control - RITSTF Initiative 5B ML19007A0902019-01-28028 January 2019 Issuance of Amendment Adoption of TSTF-425, Relocate Surveillance Frequencies to Licensee Control-RITSTF Initiative 5B ML18291B2142018-11-26026 November 2018 Issuance of Amendment Adoption of TSTF-551 Revise Secondary Containment Surveillance Requirements ML18250A0752018-10-29029 October 2018 Issuance of Amendment Adoption of TSTF-542, Reactor Pressure Vessel Water Inventory Control ML17345A0462018-03-0606 March 2018 Issuance of Amendment No. 197 to Adopt Changes to the Emergency Plan (CAC No. MF9560; EPID L-2017-LLA-0184) ML17310B2392017-11-28028 November 2017 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Issuance of Amendment Unit Staff Qualifications (CAC Nos. MF9545, MF9546, and MF9547; EPID L-2017-LLA-0195) ML17172A4312017-06-23023 June 2017 Correction of Amendment No. 194, Issuance of Amendment to Adopt F Tstf 545, Revision 3, Ts Inservice Testing Program Removal & Clarify Sr Usage Rule Application to Section 5.5 Testing ML17123A3212017-06-16016 June 2017 Issuance of Amendment Adoption of TSTF-545, Revision 3, TS Inservice Testing Program Removal and Clarify SR Usage Rule Application to Section 5.5 Testing ML17103A2352017-04-25025 April 2017 Issuance of Amendment Technical Specification 5.5.11 Primary Containment Leakage Rate Testing Program ML17013A4352017-02-27027 February 2017 Issuance of Amendment Revision to Technical Specification Surveillance Requirement 3.8.4.2 ML17054C3942017-02-23023 February 2017 Non-Proprietary Issuance of Amendment Extended Flow Window ML16196A3032016-08-0101 August 2016 Issuance of Amendment Technical Specifications Surveillance Requirement 3.5.1.3 B to Correct Alternative Nitrogen System Pressure (Cac. No. MF6704) ML16125A1652016-06-21021 June 2016 Issuance of Amendment Technical Specifications Task Force (TSTF) Standard Technical Specifications (STS) Change Traveler TSTF-523, Revision 2 Generic Letter 2008-01, Managing Gas Accumulation ML16063A0332016-02-29029 February 2016 License Amendment Request for Areva Extended Flow Window Supplement to Disposition Changes to Non-Limiting Transient Analyses ML15072A1412015-06-0505 June 2015 Issuance of Amendment No. 188 Regarding Transition to Areva Atrium 10XM Fuel and Areva Safety Analysis Methods ML14323A0332015-01-0808 January 2015 Issuance of Amendment No. 187 Regarding Revision to TS 5.5.11 for Drywell Personnel Airlock Leakage Rate Testing ML14239A2572014-11-28028 November 2014 and Prairie Island Nuclear Generation Plant, Units 1 and 2 - Issuance of License Amendments Regarding Cyber Security Plan Implementation Schedule Milestones ML14281A3182014-11-25025 November 2014 Issuance of Amendment Regarding Reduction in Steam Dome Pressure Safety Limit ML14246A4492014-11-0303 November 2014 Issuance of Amendment to Revise TS 3.5.1, ECCS - Operating ML14196A3282014-10-31031 October 2014 Issuance of Amendment to Change the Site Emergency Plan to Remove the Radwaste Operator as One of the 60-Minute Responders Specified in the Site Emergency Plan ML15160A2072014-10-24024 October 2014 Redacted, Issuance of Amendment No. 182 to Revise the Technical Specifications to Support Fuel Storage System Changes ML14058A8252014-05-0202 May 2014 Issuance of Amendment No. 181 to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month ML14035A2482014-03-28028 March 2014 Issuance of Amendment No. 180 to Implement Maximum Extended Load Line Limit Analysis Plus (Mellla+) Operating Domain ML14027A2322014-02-28028 February 2014 Issuance of Amendment No. 179 to Adopt TSTF-535, Revise Shutdown Margin Definition to Address Advanced Fuel Designs ML13218A0612014-01-28028 January 2014 Issuance of Amendment No. 178 to Adopt TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML13274A1732014-01-28028 January 2014 Issuance of License Amendment No. 177 to Renewed Facility Operating License Emergency Plan Change ML13316B2982013-12-0909 December 2013 Issuance of Amendment No. 176 to Renewed Facility Operating License Regarding Extended Power Uprate ML13168A3732013-08-28028 August 2013 Issuance of Amendment No. 175 to Make Minor Corrections and Editorial Changes, Clarify Fuel Storage Capacity, and Remove Obsolete Information ML13168A2192013-08-0909 August 2013 Issuance of Amendment No. 174 to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-484, Revision 0, Use of TS 3.10.1 for Scram Time Testing Activities ML13168A0252013-07-15015 July 2013 Issuance of Amendment No. 173 to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-476, Revision 1, Improved BPWS Control Rod Insertion Process (NEDO-33091) ML13025A1552013-02-27027 February 2013 Issuance of License Amendment No. 172 to Revise and Relocate Pressure Temperature Curves to a Pressure-Temperature Limits Report ML12339A0352013-01-25025 January 2013 Issuance of License Amendment No. 171 Regarding Restoration Period Before Declaring Average Power Range Monitors Inoperable When Surveillance Requirement 3.3.1.1.2 Is Not Met ML12220A2802012-09-0707 September 2012 Issuance of Amendment No. 170 Regarding Automatic Depressurization System Bypass Timer ML12216A2692012-08-27027 August 2012 Issuance of Amendment No. 169 Regarding the Licensing Basis of the 1AR Transformer ML12185A2162012-07-27027 July 2012 Issuance of Amendment No. 168 Regarding Safety/Relieve Valves Testing 2023-09-21
[Table view] Category:Safety Evaluation
MONTHYEARML24222A1822024-08-27027 August 2024 – Proposed Alternative Request VR-09 to the Inservice Testing Requirements of the ASME OM Code for Main Steam Safety Relief Valves ML24138A1212024-07-0202 July 2024 Alternative Request RR-002 ML24077A0012024-03-18018 March 2024 Safety Evaluation to the SLRA of Monticello Nuclear Generating Plant, Unit 1 ML23248A2092023-09-18018 September 2023 Proposed Alternative VR-11 to the Requirements of the ASME OM Code Associated with Periodic Verification Testing of MO-2397, Reactor Water Cleanup Inboard Isolation Valve ML23107A2852023-04-25025 April 2023 Authorization and Safety Evaluation for Alternative Request PR-08 ML23079A0742023-04-11011 April 2023 Request RR-003 to Use Later Edition of ASME Section XI Code for ISI Code of Record ML22357A1002023-03-31031 March 2023 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Issuance of Amendments Standard Emergency Plan and Consolidated Emergency Operations Facility ML23012A1562023-01-13013 January 2023 Issuance of Amendment No. 210 Re Revised Methodologies for Determining the Core Operating Limits (EPID L-2021-LLA-0144) - Non-proprietary ML22318A2152022-12-27027 December 2022 Issuance of Amendment No. 209 Ten-Year Inspection of the Diesel Generator Fuel Oil Storage Tank ML22264A1062022-10-31031 October 2022 Issuance of Amendment No. 208 Residual Heat Removal Drywell Spray Header and Nozzle Surveillance Frequency ML22270A2312022-09-30030 September 2022 Authorization and Safety Evaluation for Alternative Request No. VR-10 ML22154A5502022-06-0707 June 2022 Authorization and Safety Evaluation for Alternative Request No. PR-02 ML22126A1342022-05-12012 May 2022 Authorization and Safety Evaluation for Alternative Request No. PR-05 ML22098A1272022-05-0202 May 2022 Authorization and Safety Evaluation for Alternative Request No. VR-02 ML22018A1772022-01-21021 January 2022 Authorization and Safety Evaluation for Alternative Request No. VR-05 ML21223A2802021-10-15015 October 2021 Issuance of Amendment No. 207 Adoption of TSTF-564 Safety Limit MCPR ML21148A2742021-07-12012 July 2021 Issuance of Amendment No. 206 TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML20352A3492021-01-0808 January 2021 Issuance of Amendment No. 205, Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-582, RPV WIC Enhancements, and TSTF-583-T, TSTF-582 Diesel Generator Variation ML20346A0972020-12-21021 December 2020 Request for Alternative for Examination of Reactor Pressure Vessel Threads in Flange ML20336A1602020-12-0909 December 2020 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20307A0172020-11-0202 November 2020 Request for Alternative for Core Support Structure Weld Examination ML20210M0142020-09-0808 September 2020 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Issuance of Amendment Nos. 204, 231, and 219 TSTF-529 Clarify Use and Application Rules ML20153A8042020-07-31031 July 2020 Co. - Issuance of Amendments Revising Emergency Action RA3 ML20174A5452020-07-15015 July 2020 Request for Alternative for Pressure Isolation Valve Testing ML20153A4012020-06-0101 June 2020 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Relief from the Requirements of the ASME Code ML20135G9922020-05-29029 May 2020 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Relief from the Requirements of the ASME Code ML20134H9582020-05-29029 May 2020 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Relief from the Requirements of the ASME Code ML19255F5822019-10-0101 October 2019 Safety Evaluation Regarding Implementation of Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Related to Order EA-13-109 (CAC No. MF4376; EPID No. L-2014-JLD-0052) ML19162A0932019-07-30030 July 2019 Issuance of Amendment No, 202 Regarding Deletion of the Note Associated with Technical Specification 3.5.1., Erccs - Operating ML19074A2692019-04-22022 April 2019 Non-Proprietary - Issuance of Amendment Revision to Technical Specifications 2.1.2 Safety Limit Minimum Critical Power Ratio ML19052A1422019-03-11011 March 2019 Correction to License Amendment No. 198 Related to Adoption of TSTF-542, Reactor Pressure Vessel Water Inventory Control ML19065A2002019-03-11011 March 2019 Correction to License Amendment No. 200 Related to Adoption of TSTF-425, Relocated Surveillance Frequencies to Licensee Control - RITSTF Initiative 5B ML19007A0902019-01-28028 January 2019 Issuance of Amendment Adoption of TSTF-425, Relocate Surveillance Frequencies to Licensee Control-RITSTF Initiative 5B ML18291B2142018-11-26026 November 2018 Issuance of Amendment Adoption of TSTF-551 Revise Secondary Containment Surveillance Requirements ML18250A0752018-10-29029 October 2018 Issuance of Amendment Adoption of TSTF-542, Reactor Pressure Vessel Water Inventory Control ML18270A0152018-10-19019 October 2018 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Relief from the Requirements of the ASME OM Code ML17345A0462018-03-0606 March 2018 Issuance of Amendment No. 197 to Adopt Changes to the Emergency Plan (CAC No. MF9560; EPID L-2017-LLA-0184) ML17319A5912017-12-10010 December 2017 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML17310B2392017-11-28028 November 2017 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Issuance of Amendment Unit Staff Qualifications (CAC Nos. MF9545, MF9546, and MF9547; EPID L-2017-LLA-0195) ML17123A3212017-06-16016 June 2017 Issuance of Amendment Adoption of TSTF-545, Revision 3, TS Inservice Testing Program Removal and Clarify SR Usage Rule Application to Section 5.5 Testing ML17122A1572017-05-15015 May 2017 Request for Alternative to Use Code Case OMN-20 for the Fifth 10-Year Inservice Testing Interval ML17103A2352017-04-25025 April 2017 Issuance of Amendment Technical Specification 5.5.11 Primary Containment Leakage Rate Testing Program ML17013A4352017-02-27027 February 2017 Issuance of Amendment Revision to Technical Specification Surveillance Requirement 3.8.4.2 ML17054C3942017-02-23023 February 2017 Non-Proprietary Issuance of Amendment Extended Flow Window ML16320A0212016-11-28028 November 2016 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Review of Changes to the Northern States Power Company Quality Assurance Topical Report ML16244A1202016-09-0606 September 2016 Generation Plant - Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Phase 2 of Order EA-13-109 (Severe Accident Capable Hardened Vents) ML16208A4622016-08-0303 August 2016 Safety Evaluation for Request for Alternative Associated with Reactor Pressure Vessel Internals and Components Inspection for the Fifth 10-Year Interval ML16196A3032016-08-0101 August 2016 Issuance of Amendment Technical Specifications Surveillance Requirement 3.5.1.3 B to Correct Alternative Nitrogen System Pressure (Cac. No. MF6704) ML16125A1652016-06-21021 June 2016 Issuance of Amendment Technical Specifications Task Force (TSTF) Standard Technical Specifications (STS) Change Traveler TSTF-523, Revision 2 Generic Letter 2008-01, Managing Gas Accumulation ML15175A0162015-06-30030 June 2015 Staff Evaluation of 10 CFR 50.54(p)(2) Changes to Security Plans 2024-08-27
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mrs. Karen D. Fili Site Vice President January 28, 2014 Monticello Nuclear Generating Plant Northern Power Company -Minnesota 2807 West County Road 75 Monticello, MN 55362-9637
SUBJECT:
MONTICELLO NUCLEAR GENERATING PLANT -ISSUANCE OF AMENDMENT NO. 177 TO RENEWE'D FACILITY OPERATING LICENSE RE: EMERGENCY PLAN CHANGE (TAC NO. MF0461)
Dear Mrs. Fili:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 177 to Renewed Facility Operating License No. DPR-22 for the Monticello Nuclear Generating Plant (MNGP). The amendment consists of changes to the facility operating license in response to your application dated December 21, 2012, as supplemented by letter dated May 16, 2013. The amendment revises the MNGP Emergency Plan by revising the Emergency Action Level (EAL) setpoint for the Turbine Building Normal Waste Sump Monitor. Specifically, a chang'e was requested to EAL RA 1.2, such that the change restores indication of an Alert condition to within the range of the applicable instrumentation. A copy of our related safety evaluation is also enclosed. The Notice of Issuance will be inCluded in the Commission's biweekly Federal Register notice. Docket No. 50-263
Enclosures:
1. Amendment No. 177 to DPR-22 2. Safety Evaluation cc: ListServ Terry A. Beltz, Senior Project Manager :Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 NORTHERN STATES POWER COMPANY-MINNESOTA DOCKET NO. 50-263 MONTICELLO NUCLEAR GENERATING PLANT AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 177 License No. DPR-22 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that: A. The application for amendment by Northern States Power Company, a Minnesota Corporation (NSPM, the licensee), dated December 21, 2012, as supplemented by letter dated May 16, 2013, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied. Enclosure 1
_ _ __8cco_1gingly, py __________ _ hereby .amended to authorize revision to the Monticello Nuclear Generating Plant Emergency Plan as set forth in NSPM's application dated December 21, 2012, as supplemented by letter dated May 16, 2013, and evaluated in the NRC staff's safety evaluation dated 2014Jhe license amendment is effective as of its date of issuance and shall be implemented within 120 days. FOR THE NUCLEAR REGULATORY COMMISSION ric J. Leeds, Director Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Facility Operating License UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 177 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-22 NORTHERN STATES POWER COMPANY-MINNESOTA MONTICELLO NUCLEAR GENERATING PLANT DOCKET NOS. 50-263
1.0 INTRODUCTION
By application dated December 21, 2012 (Reference 1 ), and as supplemented by letter dated May 16, 2013 (Reference 2), Northern States Power Company, a Minnesota corporation (NSPM, the licensee), doing business as Xcel Energy, proposed a change to the Monticello Nuclear Generating Plant (MNGP) Emergency Plan by revising the Emergency Action Level (EAL) setpoint for the Turbine Building Normal Waste Sump (TBNWS) [Radiation] Monitor. The proposed change to EAL RA1.2, "VALID reading on any of the following radiation monitors that exceeds or is expected to exceed the reading shown for 15 minutes or longer," is necessary to restore indication of an Alert condition to within the range of the applicable instrumentation. The supplemental letter dated May 16, 2013, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the U.S. Nuclear Regulatory Commission (NRC) staff's original proposed no significant hazards consideration determination as published in the Federal Register on March 4, 2013 (78 FR 14133).
2.0 REGULATORY EVALUATION
This safety evaluation addresses the impact of the proposed changes on the MNGP EALs. The regulatory requirements and guidance on which the NRC staff based its acceptance are as follows: 2.1 Regulations Title 10 of the Code of Federal Regulations (1 0 CFR), Section 50.47, "Emergency plans," sets forth emergency plan requirements for nuclear power plant facilities. The regulations in 10 CFR 50.47(a)(1 )(i) state, in part, that: Enclosure 2
... no initial operating license for a nuclear power reactor will be issued unless a finding is made by the NRC that there is reasonable assurance that adequate protective measures can and will be taken in the event of a radiological emergency: . Section 50.47(b) establishes the standards that the onsite and offsite emergency response plans must meet for NRC staff to make a positive finding that there is reasonable assurance that the licensee can and will take adequate protective measures in the event of a radiological emergency. Planning Standard (4) of this section requires that a licensee's emergency response plan contain: "A standard emergency classification and action level scheme, the bases . of which include facility system and effluent parameters, is in use by the nuclear facility licensee, and State and local response plans call for reliance on information provided by facility licensees for determinations of minimum initial offsite response measures." Section 50.54(q)(4) states, in part, that: [C]hanges to a licensee's emergency plan that reduce the effectiveness of the plan ... may not be implemented without prior approval by the NRC, ... [A licensee's request forapproval] must be accompanied by a forwarding letter . identifying the change, the reason for the change, and the basis for concluding that the licensee's emergency plan, as revised, will continue to meet the requirements in appendix E to [1 0 C.F.R. part 50 and] the planning standards of§ 50.47(b). The Staff's review standards likewise are similar. .Specifically, The NRC may approve a proposed emergency plan change that the licensee determined to be a reduction in effectiveness if the NRC can find that the emergency plan, as modified, continues to meet the requirements of Appendix E, and for nuclear power reactor licensees, the planning standards of§ 50.47(b), and continues to provide reasonable assurance that adequate protective measures can and will be taken in the event of a radiological emergency. Final Rule, Enhancements to Emergency Preparedness Regulations, 76 Fed. Reg. 72,560, 72,577 (Nov. 23, 2011 ). 2.2 Guidance Revision 4 to Regulatory Guide (RG) 1.101, issued in July 2003 (Reference 3), endorses the guidance contained in the Nuclear Energy Institute (NEI) document NEI 99-01 "Methodology for Development of Emergency Action Levels" Revision 4, January 2003 (Reference 4), as acceptable to the NRC staff as an alternative method to that described in the following guidance for developing EALs required in Section IV of Appendix E to 10 CFR Part 50 and
- Appendix 1 to NUREG-0654/FEMA-REP-1, "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in. Support of Nuclear Power Plants" (Reference 5).
Regulatory Issue Summary (RIS) 2003-18, with Supplements 1 and 2, "Use.of NEI 99-01, Methodology for Development of Emergency Action Levels," (Reference 6), provides guidance for developing or changing a standard emergency classification and action level scheme. In addition, this RIS provides recommendations to assist licensees, consistent with Section IV.B to Appendix E of Part 50, in determining whether to seek prior NRC approval of deviations from the . guidance.
3.0 TECHNICAL EVALUATION
3.1 Background The current NRC-approved emergency classificati9n scheme for MNGP is based on NEI 99-01, Revision 4 and was approved by letter dated January 5, 2006 (Reference 7). The initially approved setpoint for the Alert EAL for the TBNWS Monitor in RA 1.2 was 3, 775,200 Counts per Minute (CPM). Subsequent to implementing the revised EALs, MNGP has determined that the indicating range of the installed monitor was insufficient to support the NEI 99-01 intended value of 200 times the Offsite Dose Calculation Manual (ODCM) alarm setpoint value. The proposed change revises the setpoint for an Alert condition, such that the indications are within the range of the associated instrumentation relied upon to make the declaration. 3.2 Evaluation The fundamental basis of RA 1.2 is not a radiation dose or dose rate, but rather the potential or actual decrease in the level of safety of the plant implied by a radiological release that exceeds regulatory commitments .for an extended period of time. The previous emergency classification set point was greater than the indicating range of the radiation monitor used for this purpose. The EAL change was requested in order to restore the Alert setpoint to within the indicating range of the TBNWS Monitor. The proposed setpoint 900,000 CPM is 90 percent of the range of the monitor and corresponds to 48 times the ODCM alarm setpoint. Therefore, the proposed setpoint change would 1) provide a setpoint value within the installed instrument's indicating range, and 2) correspond-to an ODCM alarm setpoint that continues to remain well below the NEI 99-01 intended value for an Alert declaration. The NRC staff requested additional information to determine 1) how a decision maker would know that the setpoint had been reached, 2) if an extent of condition analysis had discovered any similar situation with other radiation monitors, and 3) whether the EAL would apply if the. release path were isolated. In a letter dated May 16, 2013, the licensee stated that 1) alarm response procedures, radiation monitor alarms, and simulator training would ensure that the decision maker has the information necessary and ability to make a timely classification; 2) an of condition review indicated that each of the other EAL thresholds were measurable within the corresponding instrument's range; and 3) the EAL level would be declared regardless of the isolation state of the release. The NRC staff finds the licensee responses to be acceptable. The NRC staff also evaluated the differences between the Emergency Classification Level setpoints, the possible redundancy between RA 1.1 and RA 1.2, the readability of the associated radiation monitor's indication, and the mechanism available to communicate that the setpoint had been reached. The staff finds these to be acceptable.
3.3 Conclusion The NRC staff performed a technical and regulatory review of the proposed changes to EAL RA 1.2. The staff finds the justification for changing the setpoint for the TBNWS Monitor technically acceptable. The corresponding radiation monitor alarm and the alarm response procedure provide adequate information for the decision maker to determine that an EAL setpoint has been exceeded. Therefore, the NRC staff has determined, based on the considerations discussed in the Evaluation section above, that the proposed change: 1) continues to meet the requirements in Appendix E to 10 CFR Part 50 and the planning standards in 10 CFR 50.47(b), and 2) continues to provide reasonable assurance that adequate protective measures can and will be taken in the event of a radiological emergency.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Minnesota State official was notified of the proposed issuance of the amendments. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes the requirements with respect to use of a facility component located within the restricted area, as defined in 10 CFR Part 20. The NRC staff has determined that the involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration and
- there has been no public comment on such finding (78 FR 14133). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments;
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public. 7.0 REFERENCES 1. Letter from NSPM to the U.S. Nuclear Regulatory Commission dated December 21, 2012, "License Amendment Request: Modification to the MNGP Emergency Plan Concerning a Revision to the Emergency Action Level Setpoint for the Turbine Building Normal Waste Sump Monitor" (ADAMS Accession No. ML 12356A473).
2. Letter from NSPM to the U.S. Nuclear Regulatory Commission dated May 16, 2013; "Response to a Request for Additional Information for License Amendment Request: Modification to the MNGP Emergency Plan Concerning a Revision to the Emergency Action Level Setpoint for the Turbine Building Normal Waste Sump Monitor (TAC No. MF0461)" (ADAMS Accession No. ML 13136A289). 3. Regulatory Guide 1.101, Revision 4, "Emergency Planning and Preparedness for Nuclear Power Reactors" (ADAMS Accession No. ML032020276). 4. NEI 99-01, "Methodology for Development of Emergency Action Levels," Revision 4, dated January 2003 (ADAMS Accession No. ML041470143). 5. NUREG-0654, "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" (ADAMS Accession No. ML040420012). 6. Regulatory Issue Summary 2003-18, with Supplements 1 and 2, "Use of NEI99-01, Methodology for Development of Emergency Action Levels" (ADAMS Accession Nos. ML032580518, ML041550395, and ML051450482). 7. Letter from PeterS. Tam, U.S. Nuclear Regulatory Commission, to John T. Conway, Nuclear Management Company, LLC, regarding "Monticello Nuclear Generating Plant, Unit No. 1 -Revision to Emergency Plan Emergency Action Levels" (ADAMS Accession No. ML060040437). Principal Contributors: D. Johnson, NSIR/DPR M. Wasem, NSIR/DPR January 28, 2014 Mrs. Karen D. Fili January 28, 2014 Site Vice President Monticello Nuclear Generating Plant Northern States Power Company -Minnesota 2807 West County Road 75 Monticello, MN 55362-9637
SUBJECT:
MONTICELLO NUCLEAR GENERATING PLANT-ISSUANCE OF AMENDMENT NO. 177 TO RENEWED FACILITY OPERATING LICENSE RE: EMERGENCY PLAN CHANGE (TAC NO. MF0461)
Dear Mrs. Fili:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 177 to Renewed Facility Operating License No. DPR-22 for the Monticello Nuclear Generating Plant (MNGP). The amendment consists of changes to the facility operating license in response to your application dated December 21, 2012, as supplemented by letter dated May 16, 2013. The amendment revises the MNGP Emergency Plan by revising the Emergency Action Level (EAL) setpoint for the Turbine Building Normal Waste Sump Monitor. Specifically, a change was requested to EAL RA 1.2, such that the change restores indication of an Alert condition to within the range of the applicable instrumentation. A copy of our related safety evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice. Docket No. 50-263
Enclosures:
Sincerely, /RAJ Terry A. Beltz, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation 1. Amendment No. 177 to DPR-22 2. Safety Evaluation cc: ListServ DISTRIBUTION: PUBLIC LPL3-1 r/f RidsNrrPMMonticello Resource RidsNrrLAMHenderson Resource RidsNrrDorllpl3-1 Resource RidsAcrsAcnw_MaiiCTR Resource RidsOgcMaiiCenter Resource RidsNrrDoriDpr Resource ADAMS Accession No* ML13274A173 .. OFFICE NRR/LPL3-1/PM NRR/LPL3-1/LA NSIR/BC* NAME TBeltz MHenderson JAnderson DATE 11/07/13 11/06/13 08/19/13 OFFICE NRR/DORUDD NRR/DORUD NRR/D NAME JMonninger ME vans Eleeds (JUhle for) DATE 01/07/14 01/09/14 01/25/14 OFFICIAL RECORD COPY RidsRgn3MaiiCenter Resource DJohnson, NSIR MWasem, NSIR *via memorandum OGC NRR/LPL3-1/BC SUttal (NLO) RCa rison 12/23/13 01/02/14 NRR/LPL3-1/PM TBeltz 01/28/14