Letter Sequence Approval |
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EPID:L-2018-LLA-0307, License Amendment Request: Revise Limiting Condition for Operation (LCO) of Specification 3.5.1, Emergency Core Cooling System - Operating, to Remove the LCO Note (Approved, Closed) |
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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 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 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) ML24164A2402024-06-10010 June 2024 Minnesota State Historic Preservation Office- Comments on Draft Monticello SLR Draft EIS 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 ML24135A1902024-05-14014 May 2024 Submittal of 2023 Annual Radioactive Effluent Release Report L-MT-24-013, 2023 Annual Radiological Environmental Operating Report2024-05-14014 May 2024 2023 Annual Radiological Environmental Operating 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) IR 05000263/20240012024-04-29029 April 2024 Plan - Integrated Inspection Report 05000263/2024001 ML24089A2382024-04-29029 April 2024 Summary of Nuclear Property Insurance ML24115A3022024-04-25025 April 2024 Sec106 Tribal, Stiffarm, Jeffrey-Fort Belknap Indian Community ML24115A3032024-04-25025 April 2024 Sec106 Tribal, Taylor, Louis-Lac Courte Oreilles Band of Lake Superior Chippewa Indians ML24115A2902024-04-25025 April 2024 Sec106 Tribal, Jackson-Street, Lonna-Spirit Lake Nation ML24115A3072024-04-25025 April 2024 Sec106 Tribal, Williams, Jr., James-Lac Vieux Desert Band of Lake Superior Chippewa Indians ML24115A2892024-04-25025 April 2024 Sec106 Tribal, Fowler, Thomas-St. Croix Chippewa of Wisconsin ML24115A2952024-04-25025 April 2024 Sec106 Tribal, Kakkak, Gena-Menominee Indian Tribe of Wisconsin 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 ML24115A3012024-04-25025 April 2024 Sec106 Tribal, Seki, Darrell-Red Lake Nation ML24115A2922024-04-25025 April 2024 Sec106 Tribal, Jensvold, Kevin-Upper Sioux Community ML24115A2942024-04-25025 April 2024 Sec106 Tribal, Johnson, John-Lac Du Flambeau Band of Lake Superior Chippewa Indians ML24115A2962024-04-25025 April 2024 Sec106 Tribal, Larsen, Robert-Lower Sioux Indian Community ML24115A3062024-04-25025 April 2024 Sec106 Tribal, Wassana, Reggie-Cheyenne and Arapaho Tribes ML24115A2972024-04-25025 April 2024 Sec106 Tribal, Miller, Cole-Shakopee Mdewakanton Sioux Community ML24115A3052024-04-25025 April 2024 Sec106 Tribal, Vanzile, Jr., Robert-Sokaogon Chippewa Community ML24115A3002024-04-25025 April 2024 Sec106 Tribal, Rhodd, Timothy-Iowa Tribe of Kansas and Nebraska ML24115A2872024-04-25025 April 2024 Sec106 Tribal, Dupuis, Kevin-Fond Du Lac Band of Lake Superior Chippewa ML24115A2982024-04-25025 April 2024 Sec106 Tribal, Reider, Anthony-Flandreau Santee Sioux Tribe ML24115A2932024-04-25025 April 2024 Sec106 Tribal, Johnson, Grant-Prairie Island Indian Community ML24115A2992024-04-25025 April 2024 Sec106 Tribal, Renville, J. Garret-Sisseton Wahpeton Oyate of the Lake Travers Reservation ML24106A1112024-04-24024 April 2024 Notice of Availability of the Draft Site Specific Environmental Impact Statement for Monticello ML24106A1102024-04-24024 April 2024 Mille Lacs Band of Ojibwe -Monticello Sec106 Tribal ML24115A2842024-04-24024 April 2024 Sec106 Tribal, Chavers, Catherine-Boise Forte Band of Chippewa ML24115A2782024-04-24024 April 2024 Sec106 Tribal, Azure, Jamie-Turtle Mountain Band of Chippewa Indians 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
MONTHYEARML24138A1212024-07-0202 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 ML15072A1412015-06-0505 June 2015 Issuance of Amendment No. 188 Regarding Transition to Areva Atrium 10XM Fuel and Areva Safety Analysis Methods 2024-07-02
[Table view] Category:Technical Specifications
MONTHYEARML22357A1002023-03-31031 March 2023 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Issuance of Amendments Standard Emergency Plan and Consolidated Emergency Operations Facility ML22318A2152022-12-27027 December 2022 Issuance of Amendment No. 209 Ten-Year Inspection of the Diesel Generator Fuel Oil Storage Tank 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 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 ML18291B2142018-11-26026 November 2018 Issuance of Amendment Adoption of TSTF-551 Revise Secondary Containment Surveillance Requirements L-MT-18-060, License Amendment Request: Revise the Safety Limit Minimum Critical Power Ratio in Reactor Core Safety Limit 2.1.12018-11-12012 November 2018 License Amendment Request: Revise the Safety Limit Minimum Critical Power Ratio in Reactor Core Safety Limit 2.1.1 L-MT-18-006, Application to Revise Technical Specifications to Adopt TSTF-551, Revision 3, Revise Secondary Containment Surveillance Requirements2018-07-0303 July 2018 Application to Revise Technical Specifications to Adopt TSTF-551, Revision 3, Revise Secondary Containment Surveillance Requirements ML17346A0852017-12-12012 December 2017 Final Pre-App TS Markups ML17250A8702017-09-0707 September 2017 MNGP TSTF-542 Draft Variations ML17250A8712017-09-0707 September 2017 MNGP TSTF-542 TS Draft Markups 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 ML15335A4932015-11-20020 November 2015 Technical Requirements Manual, Revision 17 L-MT-15-032, License Amendment Request to Revise Technical Specification Surveillance Requirement 3.5.1.3.b to Correct the Alternate Nitrogen System Pressure2015-09-0202 September 2015 License Amendment Request to Revise Technical Specification Surveillance Requirement 3.5.1.3.b to Correct the Alternate Nitrogen System Pressure ML15072A1412015-06-0505 June 2015 Issuance of Amendment No. 188 Regarding Transition to Areva Atrium 10XM Fuel and Areva Safety Analysis Methods L-MT-15-043, Withdrawal of License Amendment Request to Revise Technical Specification Surveillance Requirement 3.5.1.3.b to Correct the Alternate Nitrogen System Pressure2015-05-29029 May 2015 Withdrawal of License Amendment Request to Revise Technical Specification Surveillance Requirement 3.5.1.3.b to Correct the Alternate Nitrogen System Pressure ML15110A2802015-04-15015 April 2015 Operating License and Technical Specifications ML14323A0332015-01-0808 January 2015 Issuance of Amendment No. 187 Regarding Revision to TS 5.5.11 for Drywell Personnel Airlock Leakage Rate Testing ML14281A3182014-11-25025 November 2014 Issuance of Amendment Regarding Reduction in Steam Dome Pressure Safety Limit L-MT-14-088, Areva Atrium 10XM Fuel Transition License Amendment Request Supplement2014-11-11011 November 2014 Areva Atrium 10XM Fuel Transition License Amendment Request Supplement ML14246A4492014-11-0303 November 2014 Issuance of Amendment to Revise TS 3.5.1, ECCS - Operating L-MT-14-043, License Amendment Request for Fuel Storage Changes Supplement to Proposed Spent Fuel Pool Boral Monitoring Program Technical Specification2014-05-30030 May 2014 License Amendment Request for Fuel Storage Changes Supplement to Proposed Spent Fuel Pool Boral Monitoring Program Technical Specification ML14035A2482014-03-28028 March 2014 Issuance of Amendment No. 180 to Implement Maximum Extended Load Line Limit Analysis Plus (Mellla+) Operating Domain ML14072A3902014-03-13013 March 2014 License Amendment Request for Fuel Storage Changes, Supplement to Propose a Spent Fuel Pool Boral Monitoring Program Technical Specification 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 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 L-MT-13-055, License Amendment Request for Transition to Areva Atrium 10XM Fuel and Areva Safety Analysis Methodology2013-07-15015 July 2013 License Amendment Request for Transition to Areva Atrium 10XM Fuel and Areva Safety Analysis Methodology ML13189A1942013-06-27027 June 2013 Operating License and Technical Specifications Updating Instructions L-MT-13-030, License Amendment Request: Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-535, Revision 0, Revise Shutdown Margin Definition to Address Advanced Fuel Designs2013-04-19019 April 2013 License Amendment Request: Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-535, Revision 0, Revise Shutdown Margin Definition to Address Advanced Fuel Designs L-MT-12-076, License Amendment Request for Fuel Storage Changes2012-10-30030 October 2012 License Amendment Request for Fuel Storage Changes L-MT-12-071, License Amendment Request: Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control.2012-09-18018 September 2012 License Amendment Request: Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control. L-MT-12-055, License Amendment Request: Revise Renewed Facility Operating License & Technical Specifications to Clarify Fuel Storage Capacity, Remove Obsolete Information and Make Minor Corrections and Miscellaneous Editorial Changes2012-08-21021 August 2012 License Amendment Request: Revise Renewed Facility Operating License & Technical Specifications to Clarify Fuel Storage Capacity, Remove Obsolete Information and Make Minor Corrections and Miscellaneous Editorial Changes L-MT-12-051, License Amendment Request: Remove Degraded Voltage Transfer to the 1AR Transformer2012-05-25025 May 2012 License Amendment Request: Remove Degraded Voltage Transfer to the 1AR Transformer L-MT-12-028, License Amendment Request: Revise Allowable Value for the Automatic Depressurization System Bypass Timer2012-04-0505 April 2012 License Amendment Request: Revise Allowable Value for the Automatic Depressurization System Bypass Timer ML12083A2522012-03-22022 March 2012 Enclosure 2 - Monticello Nuclear Generating Plant Technical Requirements Manual Revision 10 L-MT-11-022, 002 Monticello - Technical Requirements Manual, Revision 72011-04-27027 April 2011 002 Monticello - Technical Requirements Manual, Revision 7 L-MT-09-047, Supplement to Extended Power Uprate License Amendment Request: Revision to Proposed Technical Specification Changes in Response to Staff Comments2009-08-31031 August 2009 Supplement to Extended Power Uprate License Amendment Request: Revision to Proposed Technical Specification Changes in Response to Staff Comments L-MT-09-020, License Amendment Request: Revise the Modes of Applicability for Reactor Water Cleanup System Isolation on a Standby Liquid Control System Initiation2009-05-29029 May 2009 License Amendment Request: Revise the Modes of Applicability for Reactor Water Cleanup System Isolation on a Standby Liquid Control System Initiation L-MT-09-041, Supplement to License Amendment Request: Revision to the Allowable Value and Channel Calibration Surveillance Interval for the Recirculation Riser Differential Pressure - High Function2009-04-0202 April 2009 Supplement to License Amendment Request: Revision to the Allowable Value and Channel Calibration Surveillance Interval for the Recirculation Riser Differential Pressure - High Function ML0834406812009-01-30030 January 2009 (Mngp), License Amendment No. 159 Regarding the Power Range Neutron Monitoring System L-MT-08-012, License Amendment Request: Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency and a Clarification of a Frequency Example Using the Consolidated Line Item Improvement Process2008-04-22022 April 2008 License Amendment Request: Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency and a Clarification of a Frequency Example Using the Consolidated Line Item Improvement Process L-MT-08-013, License Amendment Request: Application for Technical Specification Change TSTF-427, Add Limiting Condition for Operation 3.0.9 Regarding the Unavailability of Barriers Using the Consolidated Line Item Improvement Process2008-04-0404 April 2008 License Amendment Request: Application for Technical Specification Change TSTF-427, Add Limiting Condition for Operation 3.0.9 Regarding the Unavailability of Barriers Using the Consolidated Line Item Improvement Process ML0810101932008-03-31031 March 2008 Monticello, License Amendment Request: Extended Power Uprate ML0802806012008-01-30030 January 2008 Technical Specifications ML0802400852008-01-23023 January 2008 Tech Specs - Issuance of Amendment Two Inoperable Control Room Ventilation Subsystems Per TSTF-447 2023-03-31
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 30, 2019 Mr. Christopher Church Senior Vice President and Chief Nuclear Officer Northern States Power Company - Minnesota 2807 West County Road 75 Monticello, MN 55362-9637
SUBJECT:
MONTICELLO NUCLEAR GENERATING PLANT- ISSUANCE OF AMENDMENT NO. 202 RE: DELETION OF THE NOTE ASSOCIATED WITH TECHNICAL SPECIFICATION 3.5.1, "ECCS -OPERATING" (EPID L-2018-LLA-0307)
Dear Mr. Church:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 202 to Renewed Facility Operating License No. DPR-22, for the Monticello Nuclear Generating Plant. The amendment consists of changes to the Technical Specifications in response to your application dated November 12, 2018, as supplemented by letter dated April 18, 2019.
The amendment deletes a note associated with the limiting condition of operation (LCO) 3.5.1 of Technical Specifications Section 3.5.1, "ECCS [emergency core cooling system] - Operating."
The deleted note permitted the low pressure coolant injection system to be considered operable under certain conditions in Mode 3.
A copy of our related safety evaluation is also enclosed. A Notice of Issuance will be included in the Commission's bi.weekly Federal Register notice.
<bert'F. Ku tz, S~ior Project Manager Plant Licensin Br 'nch Ill Division of Oper ng Reactor Licensing Office of Nuclear eactor Regulation Docket No. 50-263
Enclosure:
- 1. Amendment No. 202 to DPR-22
- 2. Safety Evaluation cc: Listserv
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. 202 Renewed 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 - Minnesota dated November 12, 2018, as supplemented by letter dated April 18, 2019, 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 1O 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
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-22 is hereby amended to read as follows:
The Technical Specifications contained in Appendix A and Appendix B, as revised through Amendment No. 202, are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of its date of issuance and shall be implemented within 90 days of the date of issuance.
Lisa M. Regner, Acting Chief Plant Licensing Branch 111 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: July 30, 2019
ATTACHMENT TO LICENSE AMENDMENT NO. 202 MONTICELLO NUCLEAR GENERATING PLANT AMENDMENT TO RENEWED FACILITY OPERATING LICENSE DOCKET NO. 50-263 Renewed Facility Operating License No. DPR-22 Replace the following page of the Renewed Facility Operating License No. DPR-22 with the attached revised page. The revised page is identified by amendment number and contain marginal lines indicating area of change INSERT REMOVE Page 3 Page 3 Technical Specifications Replace the following pages of Appendix A, Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
INSERT REMOVE 3.5.1-1 3.5.1-1
- 2. Pursuant to the Act and 1O CFR Part 70, NSPM to receive, possess, and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operations, as described in the Final Safety Analysis Report, as supplemented and amended, and the licensee's filings dated August 16, 1974 (those portions dealing with handling of reactor fuel);
- 3. Pursuant to the Act and 1O CFR Parts 30, 40 and 70, NSPM to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required;
- 4. Pursuant to the Act and 10 CFR Parts 30, 40 and 70, NSPM to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and
- 5. Pursuant to the Act and 10 CFR Parts 30 and 70, NSPM to possess, but not separate, such byproduct and special nuclear material as may be produced by operation of the facility.
C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission, now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
- 1. Maximum Power Level NSPM is authorized to operate the facility at steady state reactor core power levels not in excess of 2004 megawatts {thermal).
- 2. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 202, are hereby incorporated in the license. NSPM shall operate the fa~ility in accordance with the Technical Specifications.
- 3. Physical Protection NSPM shall implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Renewed License No. DPR-22 Amendment No. 202
ECCS - Operating 3.5.1 3.5 EMERGENCY CORE COOLING SYSTEM (ECCS), RPV WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.1 ECCS - Operating LCO 3.5.1 Each ECCS injection/spray subsystem and the Automatic Depressurization System (ADS) function of three safety/relief valves shall be OPERABLE.
APPLICABILITY: MODE 1, MODES 2 and 3, except high pressure coolant injection (HPCI) and ADS valves are not required to be OPERABLE with reactor steam dome pressures 150 psig.
ACTIONS
NOTE-----------------------------------------------------------
LCO 3.0.4.b is not applicable to HPCI.
CONDITION REQUIRED ACTION COMPLETION TIME A. One LPCI pump A.1 Restore LPCI pump to 30 days inoperable. OPERABLE status.
B. One LPCI subsystem B.1 Restore low pressure 7 days inoperable for reasons ECCS injection/spray other than Condition A. subsystem to OPERABLE status.
OR One Core Spray subsystem inoperable.
Monticello 3.5.1-1 Amendment No. 202 I
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 202 TO RENEWEDFACILITY OPERATING LICENSE NO. DPR-22 NORTHERN STATES POWER COMPANY- MINNESOTA MONTICELLO NUCLEAR GENERATING PLANT DOCKET NO. 50-263
1.0 INTRODUCTION
By application dated November 12, 2018 (Agencywide Documents Access and Management System (ADAMS Accession No. ML18317A172), as supplemented by letter dated April 18, 2019 (ADAMS Accession No. ML19108A223), Northern States Power Company- Minnesota, doing business as Xcel Energy (NSPM, the licensee) requested changes to the technical specifications {TSs) for Monticello Nuclear Generating Plant (MNGP). The supplemental letter dated November 12, 2018, 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 or Commission) staff's original proposed no significant hazards consideration determination as published in the Federal Register on January 2, 2019 (84 FR 24).
The proposed change would revise TS 3.5.1, "ECCS [emergency core cooling system] -
Operating," by erasing the note in limiting condition of operation (LCO) 3.5.1.
2.0 REGULATORY EVALUATION
2.1 Plant and System Description MNGP is a single cycle, forced circulation, low power density boiling-water reactor (BWR)/3 with a Mark I pressure suppression type primary containment. As described in Section 5.1 of the Updated Safety Analysis Report (USAR), the primary containment encloses the reactor pressure vessel (RPV), the reactor coolant recirculation loops, and other branch connections of the reactor coolant system (RCS). The major elements of the primary containment are the drywall, the pressure suppression chamber (or wetwell) that stores a large volume of water (suppression pool), the connecting vent pipe system between the drywell and the wetwell, isolation valves, the vacuum relief system, the containment cooling systems and service equipment.
Enclosure 2
MNGP USAR Section 6.2.3, "Residual Heat Removal System (RHR)," and Section 10.2.4, "Reactor Shutdown Cooling System," describes the RHR system, its functions, and operating modes. The RHR system consists of two subsystems. Each subsystem consists of a heat exchanger, two pumps in parallel, and associated piping, and is located in a different corner room of the lowest elevation of the reactor building. The discharge of the two RHR subsystems is cross-connected by a single header making it possible for either RHR subsystem to supply water to the other subsystem.
Among the RHR system operating modes, the two modes that are related to the proposed license amendment request are the LPCI mode and the shutdown cooling (SDC) mode. Each RHR subsystem aligned in the LPCI mode consists of a suppression pool suction line, parallel flow paths through the two pumps, and a common injection line to the RPV. The SDC subsystem consists of a suction line from one of the reactor recirculation loops, parallel flow paths through the pump(s), and heat exchanger to discharge heat to the RHR service water system, and then return to the RPV through either one of the recirculation loops.
The RHR system in the LPCI mode is a part of the ECCS. Besides this mode, the ECCS network consists of the HPCI system, the core spray (CS) system, and the automatic depressurization system. The LPCI subsystem restores and maintains RPV inventory for adequate core cooling during a LOCA at low RPV pressure.
The RHR system in its SDC mode is used to remove decay and residual heat from the reactor during a normal reactor shutdown and cooldown and lower the RCS inventory temperature below 212 degrees Fahrenheit (°F) prior to servicing and refueling operations. The SDC subsystem is placed in service in Mode 3 (hot shutdown) when the reactor steam dome pressure is less than the SDC supply isolation valve interlock pressure. This interlock is provided to prevent the over-pressurization of the RHR SDC suction line by inadvertent operation of the suction isolation valve from the recirculation loop. Operation in SDC is not permitted when the reactor steam dome pressure is greater than the pressure interlock setting of the SDC suction isolation valve.
2.2 Proposed Change The change proposed in the license amendment request would revise LCO 3.5.1 of TS 3.5.1, to delete the following note:
Low pressure coolant injection (LPCI) subsystems may be considered OPERABLE during alignment and operation for decay heat removal with reactor steam dome pressure less than the Residual Heat Removal (RHR) shutdown cooling supply isolation interlock in MODE 3, if capable of being manually realigned and not otherwise inoperable.
2.3 Regulatory Requirements The following regulatory requirements are applicable to the proposed amendment:
- Title 10 of the Code of Federal Regulations Section 50.36, "Technical Specifications,"
details the content and information that must be included in a plant TS. It requires to include (1) safety limits, limiting safety system settings, and limiting control settings; (2)
LCOs; (3) surveillance requirements (SRs); (4) design features; and (5) administrative controls. As described in 10 CFR 50.36(c)(2), the LCOs are the lowest functional
capability or performance levels of equipment required for safe operation of the facility.
When an LCO is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the technical specifications until the condition can be met.
- Section 50.46(a)(1 )(i) of 10 CFR requires that each boiling- or pressurized light-water nuclear power reactor be provided with an ECCS designed with a calculated cooling performance in accordance with an acceptable evaluation model following a postulated loss-of-coolant accident (LOCA).
2.4 Applicable General Design Criteria In 1967, the Atomic Energy Commission (AEC) published for comments an amendment to 10 CFR 50, Appendix A, a revised set of proposed General Design Criteria (GDC) in the Federal Register (32 FR 10213), dated July 11, 1967. The purpose of the amendment was to provide guidance to applicants to develop the Principal Design Criteria (PDC) to be Included in applications for construction permits. The PDCs used for the MNGP design basis are listed in USAR Section 1.2, "Principal Design Criteria". An evaluation which compares the MNGP design basis PDC to the AEC proposed GDC of 1967 is presented in MNGP USAR, Appendix E "Plant Comparative Evaluation with the Proposed AEC 70 Design Criteria." While MNGP is not explicitly licensed to the 1967 AEC proposed GDCs or the current GDCs, the following AEC proposed GDCs and the current GDCs equivalent to the MNGP PDC are applicable to the proposed amendment:
AEC Proposed GDC 6, "Reactor Core Design (Category A}," states that:
The reactor core shall be designed to function throughout its design lifetime, without exceeding acceptable fuel damage limits which have been stipulated and justified. The core design, together with reliable process and decay heat removal systems, shall provide for this capability under all expected conditions of normal operation with appropriate margins for uncertainties and for transient situations which can be anticipated, including the effects of the loss of power to recirculation pumps, tripping out of a turbine generator set, isolation of the reactor from its primary heat sink, and loss of off-site power.
The corresponding 10 CFR 50, Appendix A, GDC Criterion 34, "Residual heat removal," states, in part, that:
A system to remove residual heat shall be provided. The system safety function shall be to transfer fission product decay heat and other residual heat from the reactor core at a rate such that specified acceptable fuel design limits and the design conditions of the reactor coolant pressure boundary are not exceeded.
AEC proposed GDC 44, "Emergency core cooling capability (Category A)," states that:
At least two emergency core cooling systems, preferably of different design principles, each with a capability for accomplishing abundant emergency core cooling, shall be provided. Each emergency core cooling system and the core shall be designed to prevent fuel and clad damage that would interfere with the emergency core cooling function and to limit the clad metal-water reaction to negligible amounts of all sizes of breaks in the reactor coolant pressure boundary, including the double-ended rupture of the largest pipe. The
performance of each emergency core cooling system shall be evaluated conservatively in each area of uncertainty. The systems shall not share active components and shall not share other features or components unless it can be demonstrated that (a) the capability of the shared feature or components to perform its required function can be readily ascertained during reactor operation, (b) failure of the shared feature or component does not initiate a loss-of-coolant accident, and (c) capability of the shared feature or component to perform its required function is not impaired by the effects of a loss-of-coolant accident and is not lost during the entire period this function is required following the accident.
The corresponding 10 CFR 50, Appendix A, GOC 35, "Emergency core cooling," states that:
A system to provide abundant emergency core cooling shall be provided. The system safety function shall be to transfer heat from the reactor core following any loss of reactor coolant at a rate such that ( 1) fuel and clad damage that could interfere with continued effective core cooling is prevented and (2) clad metal-water reaction is limited to negligible amounts ....
3.0 TECHNICAL EVALUATION
The note proposed for deletion in TS LCO 3.5.1 states that the RHR system in its LPCI mode may be considered operable during alignment and operation for decay heat removal with reactor steam dome pressure less than the RHR SOC isolation interlock in Mode 3, if capable of being manually realigned and not otherwise inoperable. The license amendment request states the following issue in the RHR system operation as the reasons for deletion of this note:
... industry operating experience has indicated that application of this LCO note could result in some cases in water flashing to steam in the RHR System piping, water hammer, pressure locking, and/or thermal binding of valves. This is similar to the concerns reflected in NRC Information Notice 2010-11, "Potential for Steam Voiding Causing Residual Heat Removal System lnoperability", dated June 16, 2010. This phenomenon is applicable to some boiling water reactor plants due to the physical arrangement (that is the common interface) of the SOC and LPCI suction lines for the RHR pumps. Realignment from SOC to the LPCI mode transfers the suction source for the RHR pump. The resultant flashing or boiling of the high pressure / high temperature SOC water when introduced to the low pressure LPCI piping could result in voiding in the suction piping, RHR pump cavitation, water hammer and potentially RHR System damage. This possibility is greatest during the early stages of hot shutdown operation when the SOC water temperature is the highest.
NSPM does not have an analysis to demonstrate that realignment of an RHR subsystem from SOC to the LPCI mode does not result in thermal-hydraulic transients which could potentially challenge the system under certain scenarios during realignment to the LPCI for injection. Therefore, continued retention of this note is inappropriate and this note should be removed from the MNGP TS.
In the TS Bases for LCO 3.5.1, it is stated that all ECCS subsystems are required to be operable during Mode 3, when there is considerable energy in the reactor core and core cooling would be required to prevent fuel damage in the event of a LOCA. In Mode 3, when reactor steam dome pressure is 150 pounds per square inch gauge (psig), automatic depressurization
system and HPCI are not required to be operable because the low pressure ECCS subsystems, which include the RHR LPCI subsystem and the CS system, can provide sufficient flow below this pressure.
USAR Section 10.2.4.3 states that:
The reactor shutdown cooling system is placed into operation during a normal plant cooldown when reactor dome pressure is below 81.8 psig. Operation of this portion of the RHR system for shutdown cooling does not compromise the ability of the RHR system to operate in the low-pressure coolant injection system (LPCI) mode. During shutdown, the probability of requiring LPCI operation is very low. However, if LPCI operation is required, the operator can manually terminate shutdown cooling and start LPCI operation from the main control room.
The above USAR statement allows the RHR system be transferred to the LPCI mode of RHR system from the main control room while in SOC operation, if required. The transfer to LPCI mode may be completed in the event of a LOCA in Mode 3 when the reactor water has cooled enough to avoid the possibility of water/steam hammer in the RHR pump suction piping. The April 18, 2019 supplement stated that the alignment to the LPCI mode is still permitted, if required, in the region between the RHR shutdown cooling supply isolation interlock interlock and cold shutdown/ refueling conditions. To achieve LPCI alignment, if required, would require both control room and outside control room operations in accordance with established plant procedures.
The SOC mode can be initiated in Mode 3 at RPV pressure below 81.8 psig using both RHR subsystems. In this scenario both RHR subsystems would be declared inoperable in the LPCI mode because of the identified potential for voiding in the pump suction piping, RHR pump cavitation, water hammer, and potential RHR system damage. Since LCO 3.5.1 is applicable in Mode 3 upon initiation of SOC using both RHR subsystems, the plant could be in a situation where LCO 3.5.1 was not met for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> according to TS 3.5.1 Condition D. As stated in USAR Section 10.2.4.2, the RHR SOC mode can complete cooldown to 125 °F in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and maintain the nuclear system at 125 °F or less. Therefore, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from the initiation of SOC, the LCO would no longer be applicable, the reactor would be in Mode 4, and LPCI subsystems may be re-aligned from the SOC mode if required, without the potential for voiding in the pump suction piping, RHR pump cavitation, water hammer, and RHR system damage.
The NRC staff review confirmed that the potential for flashing/boiling in the RHR suction piping and the suppression pool suction valve thermal binding are the result of the RHR system design that supports several different operating modes using common equipment. This design feature, and the associated temperature phenomenon, prevents timely realignment of the RHR subsystem from SOC mode to LPCI mode.
Based on the above, the NRC staff finds that the current note in LCO 3.5.1 could potentially allow operating conditions to exist that could adversely impa_ct the function of the RHR system because high pressure, high temperature water when introduced to the low-pressure piping could result in voiding in the suction piping, RHR pump cavitation, water hammer, and associated RHR system damage. Therefore, the NRC staff finds that removal of the note in TS LCO 3.5.1 is acceptable and conservative, and the applicable regulatory requirements will continue to be met.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Michigan State official was notified of the proposed issuance of the amendment on date June 10, 2019. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes the requirements with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment 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 (84 FR 24). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(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 amendment.
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 amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: Ahsan Sallman, NRR Dateofissuance: July 30, 2019
ML19162A093 *memo date **via e-mail OFFICE NRR/DORL/LPL3/PM N RR/DORL/LPL3/LA NRR/DSS/SRXB/BC N RR/DSS/STSB/BC(A)
NAME RKuntz SRohrer JWhitman* PSnyder **
DATE 6/13/19 6/13/19 5/20/19 7/2/19 OFFICE OGC NLO NRR/DORL/LPL3/BC(A) NRR/DORL/LPL3/PM NAME DRoth** LRegner (MOrenak for) RKuntz DATE 7/22/19 7/30/19 7/30/19