Letter Sequence Other |
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MONTHYEARML0319802752003-08-21021 August 2003 License Amendment, Revise Drywell Leakage and Sump Monitoring Detection Section of the Current Plant Technical Specification Project stage: Other ML0323902442003-08-21021 August 2003 Technical Specification, Revise Drywell Leakage and Sump Monitoring Detection Section of the Current Plant Technical Specification Project stage: Other 2003-08-21
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Category:Letter
MONTHYEARML24025A9362024-01-31031 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0055 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000263/20230042024-01-31031 January 2024 Integrated Inspection Report 05000263/2023004 ML24024A0722024-01-24024 January 2024 Independent Spent Fuel Storage Installation, Onticello, Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000263/20244012024-01-22022 January 2024 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000263/2024401 L-MT-23-054, Subsequent License Renewal Application Supplement 82024-01-11011 January 2024 Subsequent License Renewal Application Supplement 8 L-MT-23-047, License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data2023-12-29029 December 2023 License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data L-MT-23-056, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 22023-12-18018 December 2023 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 2 ML23349A0572023-12-15015 December 2023 and Independent Spent Fuel Storage Installation, Revision to Correspondence Service List for Northern States Power - Minnesota IR 05000263/20234022023-12-13013 December 2023 Security Baseline Inspection Report 05000263/2023402 L-MT-23-042, 2023 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462023-12-11011 December 2023 2023 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46 L-MT-23-052, Subsequent License Renewal Application Supplement 72023-11-30030 November 2023 Subsequent License Renewal Application Supplement 7 L-MT-23-051, Update to the Technical Specification Bases2023-11-28028 November 2023 Update to the Technical Specification Bases L-MT-23-049, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 12023-11-21021 November 2023 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 ML23319A3182023-11-15015 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000263/20230032023-11-13013 November 2023 Integrated Inspection Report 05000263/2023003 and 07200058/2023001 L-MT-23-043, 10 CFR 50.55a(z)(1) Request Regarding OMN-17, Revision 1. VR-092023-11-13013 November 2023 10 CFR 50.55a(z)(1) Request Regarding OMN-17, Revision 1. VR-09 L-MT-23-038, License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.62023-11-10010 November 2023 License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6 L-MT-23-046, Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 12023-11-0909 November 2023 Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 1 ML23291A1102023-10-23023 October 2023 Environmental Audit Summary and RCIs and RAIs ML23285A3062023-10-12012 October 2023 Implementation of the Fleet Standard Emergency Plan for the Monticello Nuclear Generating Plant and the Prairie Island Nuclear Generating Plant L-MT-23-041, Subsequent License Renewal Application Response to Request for Confirmation of Information Set 22023-10-0303 October 2023 Subsequent License Renewal Application Response to Request for Confirmation of Information Set 2 L-MT-23-037, Subsequent License Renewal Application Response to Request for Additional Information Set 32023-09-22022 September 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 3 ML23262B0372023-09-19019 September 2023 Response to NRC Request for Additional Information Regarding the 2023 Monticello and Prairie Island Plant Decommissioning Funding Status Reports 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 ML23256A1682023-09-13013 September 2023 Independent Spent Fuel Storage Installation and Monticello Nuclear Generating Plant - Voluntary Security Clearance Program 2023 Insider Threat Program Self-Inspection IR 05000263/20230102023-09-0707 September 2023 Commercial Grade Dedication Inspection Report 05000263/2023010 L-MT-23-036, Subsequent License Renewal Application Response to Request for Additional Information Set 2 and Supplement 62023-09-0505 September 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 2 and Supplement 6 ML23214A2412023-08-31031 August 2023 Letter: Aging Management Audit - Monticello Unit 1 - Subsequent License Renewal Application IR 05000263/20230052023-08-30030 August 2023 Updated Inspection Plan for Monticello Nuclear Generating Plant (Report 05000263/2023005) L-MT-23-035, Subsequent License Renewal Application Supplement 52023-08-28028 August 2023 Subsequent License Renewal Application Supplement 5 ML23241A9732023-08-21021 August 2023 Request for Scoping Comments Concerning the Environmental Review of Monticello Nuclear Generating Plant, Unit 1, Subsequent License Renewal Application (Docket No. 50-263) L-MT-23-034, Subsequent License Renewal Application Response to Request for Additional Information Set 12023-08-15015 August 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 1 ML23222A0122023-08-10010 August 2023 Independent Spent Fuel Storage Installation and Monticello Nuclear Generating Plant - Changes in Foreign Ownership, Control or Influence ML23215A1312023-08-0909 August 2023 License Renewal Regulatory Audit Regarding the Environmental Review of the Subsequent License Renewal Application IR 05000263/20230022023-08-0707 August 2023 Plantintegrated Inspection Report 05000263/2023002 L-MT-23-028, 2023 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report2023-07-31031 July 2023 2023 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report L-MT-23-032, 10 CFR 50.55a(z)(2) Request Regarding MO-2397, VR-112023-07-31031 July 2023 10 CFR 50.55a(z)(2) Request Regarding MO-2397, VR-11 ML23198A0412023-07-28028 July 2023 LRA Availability Letter ML23206A2342023-07-25025 July 2023 Independent Spent Fuel Storage Installation, and Monticello Nuclear Generating Plant, Changes in Foreign Ownership, Control or Influence ML23201A0352023-07-24024 July 2023 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML23202A0032023-07-21021 July 2023 Independent Spent Fuel and Independent Spent Fuel Storage Installation, Monticello Nuclear Generating Plant, Submittal of Quality Assurance Topical Report (NSPM-1) L-MT-23-031, Subsequent License Renewal Application Supplement 4 and Responses to Request for Confirmation of Information - Set 12023-07-18018 July 2023 Subsequent License Renewal Application Supplement 4 and Responses to Request for Confirmation of Information - Set 1 ML23195A1732023-07-14014 July 2023 Revision of Standard Practice Procedures Plan IR 05000263/20235012023-07-13013 July 2023 Emergency Preparedness Inspection Report 05000263/2023501 2024-01-31
[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
MONTHYEARML23248A2092023-09-18018 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 ML15154A4772015-06-0505 June 2015 Safety Evaluation Regarding License Amendment No. 188 Associated with Areva Atrium 10XM Fuel Transition (TAC No. MF2479) - (Redacted) ML14358A0392015-02-20020 February 2015 Northern States Power Company, Minnesota (NSPM) - Monticello Nuclear Generating Plant, Prairie Island Nuclear Generating Plant, Prairie Island ISFSI - Review of Changes to the NSPM Quality Assurance Topical Report 2023-09-18
[Table view] Category:Technical Specification
MONTHYEARL-MT-23-051, Update to the Technical Specification Bases2023-11-28028 November 2023 Update to the Technical Specification Bases L-MT-23-038, License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.62023-11-10010 November 2023 License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6 L-MT-22-048, Update to the Monticello Technical Specification Bases2022-11-28028 November 2022 Update to the Monticello Technical Specification Bases L-MT-22-010, License Amendment Request to Revise Technical Specification 3.6.1.8 Residual Heat Removal (RHR) Drywell Spray Header and Nozzle Surveillance Frequency2022-03-18018 March 2022 License Amendment Request to Revise Technical Specification 3.6.1.8 Residual Heat Removal (RHR) Drywell Spray Header and Nozzle Surveillance Frequency L-MT-21-067, Update to the Monticello Technical Specification Bases2021-11-29029 November 2021 Update to the Monticello Technical Specification Bases L-MT-20-043, Update to the Monticello Technical Specification Bases2020-11-24024 November 2020 Update to the Monticello Technical Specification Bases L-MT-20-023, License Amendment Request: Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR2020-11-0303 November 2020 License Amendment Request: Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR L-MT-19-049, Technical Specification Bases2019-11-0808 November 2019 Technical Specification Bases ML18324A6792018-11-16016 November 2018 Update to the Monticello Technical Specification Bases L-MT-17-083, License Amendment Request: Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program2017-12-19019 December 2017 License Amendment Request: Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program L-MT-16-064, Update to Technical Requirements Manual and Technical Specification Bases2016-11-21021 November 2016 Update to Technical Requirements Manual and Technical Specification Bases ML16047A2722016-02-10010 February 2016 License Amendment Request: Revise Technical Specification 5.5.11 to Provide a Permanent Extension of the Integrated Leakage Rate (Type a) Test Frequency from Ten to Fifteen Years ML15335A5082015-11-20020 November 2015 Technical Requirements Manual, Technical Specification Bases, Affected Pages, Revision 34 ML15335A5072015-11-20020 November 2015 Technical Requirements Manual, Technical Specification Bases, Affected Pages, Revision 33 ML15335A5062015-11-20020 November 2015 Technical Requirements Manual, Technical Specification Bases, Affected Pages, Revision 32 ML15335A5052015-11-20020 November 2015 Technical Requirements Manual, Technical Specification Bases, Affected Pages, Revision 31 ML15335A5042015-11-20020 November 2015 Technical Requirements Manual, Technical Specification Bases, Affected Pages, Revision 30 ML15335A4942015-11-20020 November 2015 Technical Requirements Manual, Technical Specification Bases, Revision 39 ML15335A5092015-11-20020 November 2015 Technical Requirements Manual, Technical Specification Bases, Affected Pages, Revision 35 ML15335A5102015-11-20020 November 2015 Technical Requirements Manual, Technical Specification Bases, Affected Pages, Revision 36 ML15335A5112015-11-20020 November 2015 Technical Requirements Manual, Technical Specification Bases, Affected Pages, Revision 37 ML15335A5122015-11-20020 November 2015 Technical Requirements Manual, Technical Specification Bases, Affected Pages, Revision 38 L-MT-15-088, Technical Requirements Manual, Technical Specification Bases, Affected Pages, Revision 392015-11-20020 November 2015 Technical Requirements Manual, Technical Specification Bases, Affected Pages, Revision 39 ML15275A0392015-10-0202 October 2015 Revision 38 to Technical Specification Bases ML15275A0382015-10-0202 October 2015 Revision 17 to Technical Requirements Manual Specifications and Bases ML15275A0402015-10-0202 October 2015 Revision 37 to Technical Specification Bases ML15135A2242015-05-12012 May 2015 Technical Specification Bases L-MT-13-041, License Amendment Request: Revision of Technical Specification 5.5.11 for Drywell Personnel Airlock Leakage Rate Testing2013-11-14014 November 2013 License Amendment Request: Revision of Technical Specification 5.5.11 for Drywell Personnel Airlock Leakage Rate Testing ML13261A1462013-09-12012 September 2013 MNGP Technical Specification Bases Updating Instructions ML13233A0962013-08-16016 August 2013 MNGP ISFSI Amendment 10 to Technical Specifications L-MT-12-077, License Amendment Request: Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-484, Revision 0, Use of TS 3.10.1 for Scram Time Testing Activities2012-12-0606 December 2012 License Amendment Request: Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-484, Revision 0, Use of TS 3.10.1 for Scram Time Testing Activities ML12083A2512012-03-22022 March 2012 Enclosure 1 - Monticello Nuclear Generating Plant Technical Specification Bases Revision 19 ML12033A1762011-09-0808 September 2011 License Amendment Request Revise the Technical Specifications to Include a Pressure Temperature Limits Report Pressure and Temperature Limits Report, Enclosure 4 ML11129A2392011-04-27027 April 2011 001 Monticello - Technical Specification Bases, Revision 16 ML1008405682010-02-18018 February 2010 Monticello - Technical Specification Bases Revision ML1002805582010-01-21021 January 2010 Monticello - License Amendment Request: Maximum Extended Load Line Limit Analysis Plus ML0914101202009-05-13013 May 2009 Monticello - Extended Power Uprate: Response to NRC Instrumentation & Controls Branch Request for Additional Information Dated March 11, 2009, and April 6, 2009, and Fire Protection Branch RAIs Dated March 12, 2009 ML0910506192009-04-15015 April 2009 License Amendment Request for Adoption of TSTF-511, Rev. 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26 ML0902910452009-01-28028 January 2009 Monticello Nuclear Generating Plant Technical Specification Bases L-MT-08-034, License Amendment Request: Revision to Required Actions for Specification 3.5.1, Emergency Core Cooling System2008-06-26026 June 2008 License Amendment Request: Revision to Required Actions for Specification 3.5.1, Emergency Core Cooling System L-MT-08-025, Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process2008-04-0303 April 2008 Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process ML0805905412008-02-21021 February 2008 Issuance of Amendment Request to Revise Technical Specification Surveillance Requirements 3.5.1.3 to Correct the Alternate Nitrogen System Pressure (Tac MD4292) L-MT-07-036, License Amendment Request, Remove Table of Contents from Technical Specifications2007-07-0909 July 2007 License Amendment Request, Remove Table of Contents from Technical Specifications L-MT-07-009, License Amendment Request: Revision to the Allowable Values and Surveillance Intervals for the Low Pressure Coolant Injection Loop Select Logic Time Delay Relays2007-01-29029 January 2007 License Amendment Request: Revision to the Allowable Values and Surveillance Intervals for the Low Pressure Coolant Injection Loop Select Logic Time Delay Relays L-MT-06-054, Supplemental Submittal Regarding Full Scope Application of an Alternative Source Term (AST)2006-08-21021 August 2006 Supplemental Submittal Regarding Full Scope Application of an Alternative Source Term (AST) L-MT-04-047, Technical Specification Bases Change 138a2004-07-26026 July 2004 Technical Specification Bases Change 138a ML0411806122004-05-21021 May 2004 Issuance of Amendment Re. Elimination of Requirements for Hydrogen Recombiners and Hydrogen and Oxygen Monitors ML0404204242004-01-30030 January 2004 Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Recombiners and Hydrogen/Oxygen Monitors Using the Consolidated Line Item Improvement Process L-MT-03-085, Technical Specification Bases Pages Changes2003-11-11011 November 2003 Technical Specification Bases Pages Changes ML0319802752003-08-21021 August 2003 License Amendment, Revise Drywell Leakage and Sump Monitoring Detection Section of the Current Plant Technical Specification 2023-11-28
[Table view] Category:Amendment
MONTHYEARL-MT-23-038, License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.62023-11-10010 November 2023 License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6 L-MT-20-023, License Amendment Request: Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR2020-11-0303 November 2020 License Amendment Request: Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR L-MT-17-083, License Amendment Request: Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program2017-12-19019 December 2017 License Amendment Request: Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program L-MT-13-041, License Amendment Request: Revision of Technical Specification 5.5.11 for Drywell Personnel Airlock Leakage Rate Testing2013-11-14014 November 2013 License Amendment Request: Revision of Technical Specification 5.5.11 for Drywell Personnel Airlock Leakage Rate Testing ML13233A0962013-08-16016 August 2013 MNGP ISFSI Amendment 10 to Technical Specifications ML12033A1762011-09-0808 September 2011 License Amendment Request Revise the Technical Specifications to Include a Pressure Temperature Limits Report Pressure and Temperature Limits Report, Enclosure 4 ML1002805582010-01-21021 January 2010 Monticello - License Amendment Request: Maximum Extended Load Line Limit Analysis Plus ML0914101202009-05-13013 May 2009 Monticello - Extended Power Uprate: Response to NRC Instrumentation & Controls Branch Request for Additional Information Dated March 11, 2009, and April 6, 2009, and Fire Protection Branch RAIs Dated March 12, 2009 ML0910506192009-04-15015 April 2009 License Amendment Request for Adoption of TSTF-511, Rev. 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26 L-MT-08-025, Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process2008-04-0303 April 2008 Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process ML0805905412008-02-21021 February 2008 Issuance of Amendment Request to Revise Technical Specification Surveillance Requirements 3.5.1.3 to Correct the Alternate Nitrogen System Pressure (Tac MD4292) L-MT-07-036, License Amendment Request, Remove Table of Contents from Technical Specifications2007-07-0909 July 2007 License Amendment Request, Remove Table of Contents from Technical Specifications L-MT-07-009, License Amendment Request: Revision to the Allowable Values and Surveillance Intervals for the Low Pressure Coolant Injection Loop Select Logic Time Delay Relays2007-01-29029 January 2007 License Amendment Request: Revision to the Allowable Values and Surveillance Intervals for the Low Pressure Coolant Injection Loop Select Logic Time Delay Relays ML0411806122004-05-21021 May 2004 Issuance of Amendment Re. Elimination of Requirements for Hydrogen Recombiners and Hydrogen and Oxygen Monitors ML0404204242004-01-30030 January 2004 Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Recombiners and Hydrogen/Oxygen Monitors Using the Consolidated Line Item Improvement Process ML0319802752003-08-21021 August 2003 License Amendment, Revise Drywell Leakage and Sump Monitoring Detection Section of the Current Plant Technical Specification L-MT-03-017, License Amendment Request for TS Improvement to Eliminate Requirements for Post Accident Sampling Systems Using Consolidated Line Item Improvement Process2003-03-19019 March 2003 License Amendment Request for TS Improvement to Eliminate Requirements for Post Accident Sampling Systems Using Consolidated Line Item Improvement Process ML0212806022002-04-22022 April 2002 License Amendment Request for Risk-Informed Technical Specification Change Regarding Five Year Extension of Type a Test Interval ML17037B7791974-02-0707 February 1974 Letter Regarding Petition for Derating of Certain Boiling Water Reactors and Enclosed Before the Atomic Safety and Licensing Appeal Board in the Matter of Vermont Yankee Nuclear Power Corporation - Vermont Yankee Nuclear ... 2023-11-10
[Table view] |
Text
August 21, 2003 Mr. David L. Wilson Site Vice President Monticello Nuclear Generating Plant Nuclear Management Company, LLC 2807 West County Road 75 Monticello, MN 55362-9637
SUBJECT:
MONTICELLO NUCLEAR GENERATING PLANT ISSUANCE OF AMENDMENT RE: DRYWELL LEAKAGE AND SUMP MONITORING DETECTION SYSTEM (TAC NO. MB7945)
Dear Mr. Wilson:
The Commission has issued the enclosed Amendment No. 137 to Facility Operating License No. DPR-22 for the Monticello Nuclear Generating Plant. The amendment consists of changes to the Technical Specifications (TSs) in response to your application of January 29, 2003. This application superceded your previous application of October 8, 2002, as supplemented November 8, 2002.
The amendment revises the drywell leakage and sump monitoring detection section of the current TSs. Specifically, the changes clarify the associated definitions and divide TS 3.6.D/4.6.D, Coolant Leakage, into two subsections and retitle it Reactor Coolant System (RCS). One of the subsections contains the Limiting Condition for Operations (LCOs) for RCS operational leakage, and the other subsection contains the LCOs for the RCS leakage detection 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.
Sincerely,
/RA/
L. Mark Padovan, Project Manager, Section 1 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-263
Enclosures:
- 1. Amendment No. 137 to DPR-22
- 2. Safety Evaluation cc w/encls: See next page
ML031980275
- SE input provided by memo ** see previous concurrence OFFICE PDIII-1/PM PDIII-1/LA SPLB/SC* IORB/SC** OGC PDIII-1/SC NAME LPadovan RBouling SWeerakkody SMagruder SCole LRaghavan DATE 08/01/03 08/01/03 5/30/03 7/31/03 08/14/03 08/20/02 Monticello Nuclear Generating Plant cc:
Jonathan Rogoff, Esquire Commissioner General Counsel Minnesota Department of Commerce Nuclear Management Company, LLC 121 Seventh Place East 700 First Street Suite 200 Hudson, WI 54016 St. Paul, MN 55101-2145 U.S. Nuclear Regulatory Commission Adonis A. Neblett Resident Inspectors Office Assistant Attorney General 2807 W. County Road 75 Office of the Attorney General Monticello, MN 55362 445 Minnesota Street Suite 900 Manager, Regulatory Affairs St. Paul, MN 55101-2127 Monticello Nuclear Generating Plant Nuclear Management Company, LLC John Paul Cowan 2807 West County Road 75 Executive Vice President & Chief Nuclear Monticello, MN 55362-9637 Officer Nuclear Management Company, LLC Robert Nelson, President 700 First Street Minnesota Environmental Control Hudson, WI 54016 Citizens Association (MECCA) 1051 South McKnight Road Nuclear Asset Manager St. Paul, MN 55119 Xcel Energy, Inc.
414 Nicollet Mall, R.S. 8 Commissioner Minneapolis, MN 55401 Minnesota Pollution Control Agency 520 Lafayette Road St. Paul, MN 55155-4194 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, IL 60532-4351 Commissioner Minnesota Department of Health 717 Delaware Street, S. E.
Minneapolis, MN 55440 Douglas M. Gruber, Auditor/Treasurer Wright County Government Center 10 NW Second Street Buffalo, MN 55313 March 2003
NUCLEAR MANAGEMENT COMPANY, LLC DOCKET NO. 50-263 MONTICELLO NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 137 License No. DPR-22
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Nuclear Management Company, LLC (the licensee), dated January 29, 2003, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions 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 Commissions 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 Commissions regulations and all applicable requirements have been satisfied.
- 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 Facility Operating License No. DPR-22 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 137 , are hereby incorporated in the 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 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
L. Raghavan, Chief, Section 1 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: August 21, 2003
ATTACHMENT TO LICENSE AMENDMENT NO. 137 FACILITY OPERATING LICENSE NO. DPR-22 DOCKET NO. 50-263 Replace the following pages of the 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.
REMOVE INSERT ii ii 5 5 126 126 126a 126a 127 127
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 137 TO FACILITY OPERATING LICENSE NO. DPR-22 NUCLEAR MANAGEMENT COMPANY, LLC MONTICELLO NUCLEAR GENERATING PLANT DOCKET NO. 50-263
1.0 INTRODUCTION
By application dated January 29, 2003, the Nuclear Management Company, LLC (NMC),
requested changes to the Technical Specifications (TSs) for the Monticello Nuclear Generating Plant. This application superceded NMCs previous application of October 8, 2002, as supplemented November 8, 2002. The proposed amendment would revise the drywell leakage and sump monitoring detection section of the current TSs. Specifically, the changes would clarify the associated definitions and divide TS 3.6.D/4.6.D, Coolant Leakage, into two subsections and retitle it Reactor Coolant System (RCS). One of the subsections would contain the Limiting Condition for Operations (LCOs) for RCS operational leakage, and the other subsection would contain the LCOs for the RCS leakage detection instrumentation.
2.0 REGULATORY EVALUATION
The applicable regulatory requirements and guidelines are as follows:
- Title 10 of the Code of Federal Regulations (10 CFR), Sections 50.36, 50.90, 50.91, and 51.22
- NUREG-1433, Standard Technical Specifications General Electric Plants, BWR/4,"
Revision 2, dated April 2001
3.0 TECHNICAL EVALUATION
NMC is maintaining a plant-specific TS format (not reformatting the Monticello TSs to be in accordance with NUREG-1433). This safety evaluation (SE) assesses NMCs proposed TS changes to determine if the proposed changes are acceptable.
3.1 Current TS Definitions 1.0.AC, Identified Leakage, 1.0.AD, Unidentified Leakage, and Proposed TS Definition 1.0.AE, Total Leakage (Change 1) 3.1.1 Proposed TS Changes NMC proposed revising current TS Definitions 1.0.AC and 1.0.AD, and adding new TS Definition 1.0.AE. These changes would match the proposed changes to TS 3.6.D/4.6.D (see Section 3.2 of this SE), and be generally consistent with NUREG-1433. The current TS 1.0.AC definition for identified leakage is as follows:
- 1. Reactor coolant leakage into the drywell collection systems, such as pump seal or valve packing leaks, that is captured and conducted to a sump or collection tank, or
- 2. Reactor coolant leakage into the drywell atmosphere from sources which are specifically located and known not to be Pressure Boundary Leakage, or which do not significantly impair the methods used to detect reactor coolant leakage.
The proposed changes would revise TS Definition 1.0.AC to define identified leakage as follows:
- 1. Leakage into the drywell, such as that from pump seals or valve packing leaks, that is captured and conducted to a sump or collection tank, or
- 2. Leakage into the drywell atmosphere from sources that are both specifically located and known either not to interfere with the operation of the leakage detection systems or not to be Pressure Boundary Leakage.
The current TS Definition 1.0.AD defines unidentified leakage as Unidentified leakage shall be all reactor coolant leakage which is not Identified Leakage. The proposed changes would redefine unidentified leakage as All leakage into the drywell that is not Identified Leakage. A new TS Definition 1.0.AE would define total leakage to be the Sum of the Identified and Unidentified Leakage.
3.1.2 NRC Staff Evaluation The changes to the identified and unidentified definitions clarify that the leakage is not limited to reactor coolant. Leakage will include all leakage into the drywell, not just leakage to the collection systems. NMC proposed using the term leakage detection systems, and adding a definition for total leakage that is consistent with proposed changes to TS 3/4.6.D. The proposed changes are generally more conservative than the current definitions because they include all leakage inside the drywell. They are also necessary to support the proposed TS changes. Therefore, the NRC staff finds the proposed changes acceptable.
3.2 Current TS 3.6.D/4.6.D, Coolant Leakage (Change 2) 3.2.1 Proposed TS Changes NMC proposed revising current TS 3.6.D/4.6.D to change the name from Coolant Leakage to Reactor Coolant System (RCS). NMC also proposed dividing the TS section into two subsections titled Operational Leakage, and RCS Leakage Detection Instrumentation. The TS Table of Contents (TOC) would also be revised, and the TS LCO and Surveillance Requirement (SR) subparagraphs renumbered accordingly.
3.2.2 NRC Staff Evaluation NMC states that the proposed changes to the TS are needed to clarify the TS and make them more usable and understandable. Dividing current TS Section 3.6.D/4.6.D into two subsections would make it clear which portion pertains to RCS operational leakage and which pertains to
the instrumentation that detects RCS leakage. Additionally, revising the TS TOC supports the proposed changes.
The proposed revisions are editorial in nature. Separating operational leakage LCOs and SRs from leakage-detection instrumentation LCOs and SRs adds clarity and consistency.
Therefore, the NRC staff finds the proposed changes acceptable.
The remainder of this SE evaluates NMCs proposed changes using the proposed, renumbered TS LCO and SR subparagraphs, as follows:
Current TS Proposed TS 3.6.D.1 3.6.D.1.a 3.6.D.1.a 3.6.D.1.a.1) 3.6.D.1.b 3.6.D.1.a.2) 3.6.D.1.c 3.6.D.1.a.3) 3.6.D.1.d 3.6.D.1.a.4) 3.6.D.2 3.6.D.1.b 3.6.D.3 3.6.D.1.c 3.6.D.4 3.6.D.1.d 3.6.D.5 3.6.D.2.a 3.6.D.5.a 3.6.D.2.a.1) 3.6.D.5.b 3.6.D.2.a.2) 3.6.D.6.b 3.6.D.2.b.2) 3.3 Proposed TS LCO 3.6.D.1.a (Change 3) 3.3.1 Proposed TS Changes NMC proposed deleting the words based on sump monitoring in current TS LCO 3.6.D.1 with regard to RCS operational leakage limits.
3.3.2 NRC Staff Evaluation NMC indicates the proposed changes are necessary to support transferring from the current method of complying with the current Coolant Leakage TS (by measuring/monitoring leakage) to the proposed method of complying with the new Reactor Coolant System TS (by verifying leakage to be within TS limits). The proposed changes would require observing operational leakage limits regardless of how the leakage is monitored. Thus, the proposed changes would provide for continued verification of being within TS limits.
RCPB leakage is the safety concern associated with leakage into the drywell, as it could indicate RCPB degradation. Since the unidentified leakage rate limits would not change, the proposed change would give added operational flexibility without a corresponding reduction in safety. The proposed TS changes would provide at least the same level of safety as the current TS because the limits would not change. Therefore, the NRC staff finds the proposed changes acceptable.
3.4 Proposed TS SR 4.6.D.1 (Change 4) 3.4.1 Proposed TS Changes NMC proposed revising current TS SR 4.6.D.1 to delete the requirement to record unidentified and identified leakage rates once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> using primary containment floor and equipment drain sump monitoring equipment. Instead, the proposed SR would require verifying, every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, that unidentified leakage, increase in unidentified leakage, and total leakage are within the TS limits.
3.4.2 NRC Staff Evaluation NMC proposed revising the TS SR to provide for the new method for determining compliance with proposed TS 3.6.D.1.a. The new method would require verifying that the drywell unidentified leakage, increase in unidentified leakage, and total leakage are all within the acceptable limits of TS 3.6.D.1.a. The old method requires recording unidentified leakage and identified leakage every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> using sump monitoring equipment. These changes are necessary to provide continuity and consistency with the overall proposed changes.
The proposed changes are acceptable because RCS leakage can be monitored by a variety of instruments that alarm when leakage is indicated and quantify the various types of leakage.
Sump level and flow rate are typically monitored to determine actual leak rates. However, other methods may be used to quantify leakage. Plant operators can look for step changes in conditions, or perform calculations to determine leakage and verify that it remains within TS limits. Operators can use preexisting information, in conjunction with alternate measurements (e.g., drywell pressure and temperature), to do this. The proposed TS changes would provide at least the same level of safety as the current TS since the leakage rate limits would not change. The proposed changes would also provide more operational flexibility than the current TS. The 12-hour SR to verify leakage would not change from the current TS.
Therefore, the NRC staff finds the proposed changes acceptable.
3.5 Proposed TS LCO 3.6.D.1.a.1), 3.6.D.1.a.2) and 3.6.D.1.a.3) (Change 5) 3.5.1 Proposed TS Changes NMCs proposed changes are as follows:
- Add # to proposed TS LCOs 3.6.D.1.a.1), 3.6.D.1.a.2) and 3.6.D.1.a.3).
- Revise proposed TS LCO 3.6.D.1.a.2) to delete Any, replace it with the previous, and add while in the Run Mode.
- Revise proposed TS LCO 3.6.D.1.a.3) to delete reference to 20 gpm [gallons per minute]
Identified Leakage and replace it with # 25 gpm Total Leakage averaged over the previous 24-hour period.
3.5.2 NRC Staff Evaluation
NMC proposed adding # in front of the leakage limits to clarify that the leakage must be less than or equal to the specified values. The proposed change to include a total-leakage limit, which combines unidentified and identified leakage is consistent with the overall TS changes.
NMC proposed revising the increase in unidentified leakage limit during the previous 24-hour period while in the Run Mode, and total leakage limit averaged over the previous 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period, were also made to be consistent with industry standards.
The proposed revision to add # in front of the leakage limits is acceptable because it would remove the ambiguity associated with the current TS wording, and is essentially cosmetic in nature because it would not change the actual limits. Similarly, the proposed change to a total leakage limit of 25 gpm versus a limit of 20 gpm for identified leakage is also acceptable because it would not change the actual limits (since total leakage combines identified and unidentified leakage). Revising the total-leakage limit to be averaged over the previous 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period is acceptable because it would prevent momentary spikes from requiring an unnecessary entry into an action statement. The revised wording for the unidentified leakage increase, which includes the previous 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period while in the Run Mode, is also acceptable because temporary changes in leakage rate may occur as a result of transient conditions (e.g., startup). Measurements should be performed during steady-state conditions.
Therefore, the NRC staff finds the proposed changes acceptable.
3.6 Proposed TS LCOs 3.6.D.1.b, 3.6.D.1.c, 3.6.D.1.d, 3.6.D.2.a.2), and 3.6.D.2.b.2)
(Change 6) 3.6.1 Proposed TS Changes NMC requested changes to current TS LCOs 3.6.D.2, 3.6.D.3, 3.6.D.4, 3.6.D.5.b and 3.6.D.6.b.
The proposed changes included revising the unit shutdown statements for the LCOs to say that the unit should be in hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in cold shutdown within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> if the TS LCO limits are exceeded.
3.6.2 NRC Staff Evaluation The current TS shutdown action statements require operators to initiate an orderly shutdown of the reactor and reduce reactor water temperature to less than 212EF [degrees Fahrenheit]
within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The proposed changes would make the shutdown requirements of TS LCO 3.6.D.1 and other similar shutdown requirements found elsewhere in the Monticello TSs consistent. The proposed time frames of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to be in hot shutdown and an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to be in cold shutdown are reasonable (based on operating experience) to reach the required plant conditions from full power conditions in an orderly manner and without challenging the plant safety systems.
Adding an additional 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to reach cold shutdown conditions in the revised TS LCOs is acceptable because this allows for a more orderly plant shutdown. Also, the probability that an imperfection or crack associated with the TS leakage limits would grow significantly within the additional 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is acceptably small. Thus, the additional 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> might even provide a small increase in safety because it permits a more orderly plant shutdown. Therefore, the NRC staff finds the proposed changes acceptable.
3.7 Proposed TS LCOs 3.6.D.1.b and 3.6.D.1.c (Change 7) 3.7.1 Proposed TS Changes NMC proposed changing current TS LCOs 3.6.D.2 and 3.6.D.3 to revise the wording of the initial action statements for leakage in excess of the limits. The proposed changes would also add a clarifying statement to proposed TS LCO 3.6.D.1.c to state reduce leakage to within limits within four hours or identify that the source of increased leakage is not service sensitive type 304 or type 316 austenitic stainless steel.
3.7.2 NRC Staff Evaluation The current initial action statement for TS LCO 3.6.D.2 requires reducing RCS leakage to within acceptable limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. The current initial action statement for TS LCO 3.6.D.3 for the increase in unidentified leakage limit says to identify the source of increased leakage within four hours. Thus, the proposed changes are necessary because the current TS LCOs are unclear as to what the expectations are once a leakage source is identified. The proposed changes would also enhance TS readability and usability.
The word acceptable in the phrase within acceptable limits is redundant. Thus, deleting this word is editorial in nature. The new wording within limits conveys the proper meaning.
The proposed change to identify that the source of increased leakage is not service-sensitive Type 304 or Type 316 austenitic stainless steel is acceptable because it focuses the leakage investigation on piping that is susceptible to intergranular stress-corrosion cracking (IGSCC),
which forms the technical basis for the limit related to increases in unidentified leakage. IGSCC produces tight cracks and the small flow increase limit (2 gpm) is capable of providing an early warning of such deterioration. Verifying that the source of the increased leakage is not Type 304 or Type 316 austenitic stainless steel essentially eliminates IGSCC as a possible cause of the increased leakage. This significantly reduces concerns about crack instability, crack growth, and a failure of the RCPB. Therefore, the NRC staff finds the proposed changes acceptable.
3.8 Proposed TS LCO 3.6.D.1.d (Change 8) 3.8.1 Proposed TS Changes NMC proposed changing current TS LCO 3.6.D.4 to replace the words is detected when the corrective actions outlined in 3.6.D.2 and 3.6.D.3 above are taken with the word exists.
3.8.2 NRC Staff Evaluation Currently, the TS LCO 3.6.D.4 action statement reads, If any Pressure Boundary Leakage is detected when the corrective actions outlined in 3.6.D.2 and 3.6.D.3 above are taken . . . . The proposed change reads If any Pressure Boundary Leakage exists . . . . The proposed change enhances the readability, usability, and understanding of the TS. Deleting the references to LCOs 3.6.D.2 and 3.6.D.3 is appropriate because the revisions discussed in Sections 3.6 and 3.7 of this SE (which provided each of the referenced TS subsections with their own evaluation criteria and action statements) make the references redundant. Adding the word exists is administrative and is necessary to make the wording grammatically correct.
The proposed changes are acceptable because they are administrative in nature and do not change the technical content and resulting actions of the existing TS. The proposed changes are also necessary to make the associated action statement consistent with the overall changes made in the proposed TS. Therefore, the NRC staff finds the proposed changes acceptable.
3.9 Proposed TS LCO 3.6.D.2.a (Change 9) 3.9.1 Proposed TS Changes NMC proposed changing current TS LCO 3.6.D.5 to delete the statements at least one of the leakage measurement instruments associated with each sump, and no leak rate measurement instruments associated with a sump are. NMC proposed replacing these statements with the Drywell Floor Drain Sump Monitoring System, and the Drywell Floor Drain Sump Monitoring System is not, respectively.
3.9.2 NRC Staff Evaluation NMCs proposed change to current TS LCO 3.6.D.5 would delete the requirement to have operable leakage and leak rate monitoring instruments associated with each sump (equipment and floor drain sumps). The proposed change would require an operable drywell floor drain sump monitoring system instead. An operable drywell floor drain sump monitoring system is necessary to quantify unidentified leakage into the drywell. The equipment drain sump monitoring system is not required to monitor unidentified leakage. Therefore, because the equipment drain sump instrumentation is not normally used to detect (and indicate in the control room) a significant degradation (via unidentified leakage measurements) of the RCPB, 10 CFR 50.36 does not require it to be in the TSs. NMC also proposed adding an asterisk to the word operable. The asterisk is associated with the change discussed in Section 3.12 of this SE.
The NRC staff considers these changes to be acceptable because of the following:
- They provide additional operational flexibility without a significant reduction in safety.
- They may reduce the number of unnecessary shutdowns due to inoperable drain sump equipment.
For the drywell floor drain sump monitoring system to be considered operable, either the flow or level monitoring portion of the system must be operable. The system consists of a sump discharge flow integrator, one sump level recorder, and one sump fill rate computer point (rate of change). The drywell floor drain sump monitoring system is operable whenever one these three channels is operable.
An alternate to the drywell floor drain pump monitoring system is the drywell equipment drain sump monitoring system, provided the floor drain sump is overflowing to the equipment drain sump. The system becomes inoperable during periods when the floor drain sump level and flow indications are not capable of being monitored. Once the drywell floor drain sump is overflowing to the equipment drain sump, NMC can use the drywell equipment drain sump monitoring system to quantify leakage (i.e., unidentified leakage) into the floor drain sump. This alternate method gives added flexibility, and safety is not reduced because unidentified leakage is still being monitored and indicated in the control room. Therefore, the NRC staff finds the proposed changes acceptable.
3.10 Proposed TS LCO 3.6.D.2.a.1 (Change 10) 3.10.1 Proposed TS Changes NMC proposed changing current TS LCO 3.6.D.5.a. Currently, it reads Perform manual leak rate measurements once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and restore a measurement instrument to operable status within 30 days. It would be changed to read Restore the Drywell Floor Drain Sump Monitoring System to operable status within 30 days.
3.10.2 NRC Staff Evaluation The proposed change would delete the existing requirement to perform manual leak rate measurements because NMC proposed to redefine the equipment for the drywell monitoring system to incorporate the equipment that would be used to perform a manual leak rate measurement (as discussed in Section 3.9 of this SE). With the revised description of the drywell floor drain sump monitoring system, the monitoring system will remain operable whenever any of the three channels are operable (as discussed in Section 3.9.2).
The proposed change to delete the manual leak rate measurement is necessary because the equipment required to perform such calculations would likely not be available because of the new definition of the drywell floor drain sump monitoring system. However, NMC proposed to add a new requirement for the drywell air particulate monitor to be operable if the drywell floor drain sump monitoring system is inoperable (as discussed in Section 3.11 of this SE).
Previously, both the particulate monitor and the sump monitors could be inoperable if manual measurements were performed. When considered in conjunction with the rest of the changes NMC proposed in its January 29, 2003, application, this change essentially provides an equivalent level of safety while adding a significant amount of operational flexibility. This might reduce the number of unnecessary shutdowns. Therefore, the NRC staff finds the proposed changes acceptable.
3.11 Proposed TS LCO 3.6.D.2.c (Change 11) 3.11.1 Proposed TS Changes NMC proposed adding a new TS LCO 3.6.D.2.c that states, Any time irradiated fuel is in the reactor vessel and reactor water temperature is above 212EF at least one channel of the required leakage detection instrumentation shall be operable. If all channels of both systems (Drywell Floor Drain Sump Monitoring System and drywell particulate radioactivity monitoring system) are inoperable, restore at least one channel of the required leakage detection instrumentation to operable status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, or be in Hot Shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in Cold Shutdown within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.11.2 NRC Staff Evaluation This proposed change would provide TS actions if all the required RCS leakage detection instrumentation is inoperable. If all channels of both systems are inoperable, there is no means to detect leakage using TS instrumentation. NMCs proposed change is acceptable because it is more conservative that the existing TS. The change adds a new LCO which requires at least one channel of the RCS leakage detection instrumentation to be available for monitoring potential leakage. Therefore, the NRC staff finds the proposed changes acceptable.
3.12 Proposed TS LCOs 3.6.D.2.a and 3.6.D.2.b (Change 12) 3.12.1 Proposed TS Changes NMC proposed adding a footnote (asterisk) to current TS LCO 3.6.D.6 that states, A mode change is allowed when this system is inoperable. It would apply when either the drywell floor drain sump monitoring system or the drywell particulate radioactivity monitoring system is inoperable. It would not apply when both of these systems are simultaneously inoperable.
3.12.2 NRC Staff Evaluation The proposed change would clarify that a mode change is allowed if either of the above monitoring systems is inoperable. This change is acceptable because other instrumentation (e.g., the drywell particulate radioactivity monitoring system) is available to monitor RCS leakage if the drywell floor drain sump monitoring system is inoperable. Although the drywell particulate radioactivity monitoring system cannot quantify leakage, it will indicate changes in RCS leakage. Additionally, if the drywell particulate radioactivity monitoring system is inoperable, other instrumentation (e.g., the drywell floor drain sump monitoring system) is available to monitor and quantify RCS leakage. Furthermore, drywell pressure and temperature monitors can provide other indications of a change in RCS leakage. Thus, other instrumentation is available to monitor RCS leakage and a mode change should be allowed.
Allowing a mode change under these conditions is consistent with industry practice. Therefore, the NRC staff finds the proposed changes acceptable.
3.13 Proposed TS SR 4.6.D.2 (Change 13) 3.13.1 Proposed TS Changes NMC proposed changes to the wording of the current TS SR 4.6.D.2 which specifies the SRs for the RCS leakage detection systems. Currently, the TS SR states that The reactor coolant system leakage detection systems shall be demonstrated OPERABLE by: . . . . NMC proposes to revise this to read RCS leakage detection instrumentation shall be demonstrated OPERABLE by: . . . . Also, NMC proposes to change TS SR 4.6.D.2.b from Primary containment sump leakage measurement system - performance of a sensor check once per . . . to Required leakage detection instrumentation - perform a sensor check once per . . . . NMC proposed other minor grammatical changes for consistency.
3.13.2 NRC Staff Evaluation The proposed changes are necessary to be consistent with the rest of the TS changes. The proposed changes are acceptable because they are basically editorial in nature. Therefore, the NRC staff finds the proposed changes acceptable.
3.14 Proposed TS SR 4.6.D.2.b (Change 14) 3.14.1 Proposed TS Changes NMC proposes adding a new SR to current TS 4.6.D.2.b requiring a channel function test**
(flow instruments only) at least monthly. NMC also proposes adding a footnote (the double asterisk) which states A functional test of this instrument means injection of a simulated signal
into the instrument (not primary sensor) to verify the proper instrument channel response alarm and/or initiating action.
3.14.2 NRC Staff Evaluation This proposed change would require monthly functional testing of the required leakage detection flow instrumentation. This functional test, along with the sensor check and channel calibration, would help ensure that the required leakage detection sump instrumentation will operate with a high degree of reliability. This test would only be performed on the flow instruments because they are the only instruments that can be functionally tested monthly.
Level instrumentation, with the exception of the recorders, is inaccessible during power operation. The SRs that help ensure the reliability of the primary containment atmosphere particulate radioactivity monitoring systems are addressed in current (and proposed)
TS 4.6.D.2.a. This TS SR remains essentially unchanged, except for a minor grammatical revision. The addition of the footnote is necessary to prevent a potential conflict with TS definition 1.0.E, Instrument Functional Test. It would also clarify that a functional test at the flow sensor cannot be performed while at power because of the location of the sensor.
The addition of a monthly functional test for the required leakage detection flow instruments is acceptable because it would provide an additional means of ensuring that the required sump flow monitoring instrumentation is performing properly. It is, therefore, an enhancement with respect to safety. In addition to the existing sensor check once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and the calibration check at least once per cycle, this test would give added assurance that at least part of the circuitry is performing as designed. It is also consistent with similar notes elsewhere in the Monticello TSs (e.g., TS Table 4.2.1, Note 5). Therefore, the NRC staff finds the proposed changes acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Minnesota State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes SRs.
The 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 (68 FR 18279). 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) such activities will be conducted in compliance with the Commissions 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: B. LeFave Date: August 21, 2003