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Category:Letter type:L
MONTHYEARL-MT-24-022, – Preparation and Scheduling of Operator Licensing Examinations2024-07-0909 July 2024 – Preparation and Scheduling of Operator Licensing Examinations L-MT-24-019, Submittal of ASME Section XI, Section IWB-3720 Analytical Evaluation in Accordance with 10 CFR 50.55a(b)(2)(xliii)2024-06-10010 June 2024 Submittal of ASME Section XI, Section IWB-3720 Analytical Evaluation in Accordance with 10 CFR 50.55a(b)(2)(xliii) L-MT-24-017, Response to Request for Additional Information Regarding License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6 (EPID-L-2023-LLA-01602024-06-0404 June 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6 (EPID-L-2023-LLA-0160 L-MT-24-015, Response to Request for Additional Information - Alternative Request VR-09 for OMN-172024-05-16016 May 2024 Response to Request for Additional Information - Alternative Request VR-09 for OMN-17 L-MT-24-013, 2023 Annual Radiological Environmental Operating Report2024-05-14014 May 2024 2023 Annual Radiological Environmental Operating Report L-MT-24-016, 2023 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP)2024-05-0808 May 2024 2023 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP) L-MT-24-004, Submittal of 10 CFR 72.48 Report for Monticello Nuclear Generating Plant (MNGP)2024-04-17017 April 2024 Submittal of 10 CFR 72.48 Report for Monticello Nuclear Generating Plant (MNGP) L-MT-24-002, Submittal of Revision 41 to the Updated Safety Analysis Report2024-04-17017 April 2024 Submittal of Revision 41 to the Updated Safety Analysis Report L-MT-23-054, Subsequent License Renewal Application Supplement 82024-01-11011 January 2024 Subsequent License Renewal Application Supplement 8 L-MT-23-047, License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data2023-12-29029 December 2023 License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data L-MT-23-056, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 22023-12-18018 December 2023 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 2 L-MT-23-042, 2023 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462023-12-11011 December 2023 2023 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46 L-MT-23-052, Subsequent License Renewal Application Supplement 72023-11-30030 November 2023 Subsequent License Renewal Application Supplement 7 L-MT-23-051, Update to the Technical Specification Bases2023-11-28028 November 2023 Update to the Technical Specification Bases L-MT-23-049, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 12023-11-21021 November 2023 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 L-MT-23-043, 10 CFR 50.55a(z)(1) Request Regarding OMN-17, Revision 1. VR-092023-11-13013 November 2023 10 CFR 50.55a(z)(1) Request Regarding OMN-17, Revision 1. VR-09 L-MT-23-038, License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.62023-11-10010 November 2023 License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6 L-MT-23-046, Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 12023-11-0909 November 2023 Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 1 L-MT-23-041, Subsequent License Renewal Application Response to Request for Confirmation of Information Set 22023-10-0303 October 2023 Subsequent License Renewal Application Response to Request for Confirmation of Information Set 2 L-MT-23-037, Subsequent License Renewal Application Response to Request for Additional Information Set 32023-09-22022 September 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 3 L-MT-23-036, Subsequent License Renewal Application Response to Request for Additional Information Set 2 and Supplement 62023-09-0505 September 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 2 and Supplement 6 L-MT-23-035, Subsequent License Renewal Application Supplement 52023-08-28028 August 2023 Subsequent License Renewal Application Supplement 5 L-MT-23-034, Subsequent License Renewal Application Response to Request for Additional Information Set 12023-08-15015 August 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 1 L-MT-23-028, 2023 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report2023-07-31031 July 2023 2023 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report L-MT-23-032, 10 CFR 50.55a(z)(2) Request Regarding MO-2397, VR-112023-07-31031 July 2023 10 CFR 50.55a(z)(2) Request Regarding MO-2397, VR-11 L-MT-23-031, Subsequent License Renewal Application Supplement 4 and Responses to Request for Confirmation of Information - Set 12023-07-18018 July 2023 Subsequent License Renewal Application Supplement 4 and Responses to Request for Confirmation of Information - Set 1 L-MT-23-030, Subsequent License Renewal Application Supplement 32023-07-0404 July 2023 Subsequent License Renewal Application Supplement 3 L-MT-23-025, Subsequent License Renewal Application Supplement 22023-06-26026 June 2023 Subsequent License Renewal Application Supplement 2 L-MT-23-019, Submittal of 2022 Annual Radiological Environmental Operating Report2023-05-10010 May 2023 Submittal of 2022 Annual Radiological Environmental Operating Report L-MT-23-020, Submittal of 2022 Annual Radioactive Effluent Release Report2023-05-10010 May 2023 Submittal of 2022 Annual Radioactive Effluent Release Report L-MT-23-021, Core Operating Limits Report (COLR) for the Monticello Nuclear Generating Plant for Cycle 322023-05-0202 May 2023 Core Operating Limits Report (COLR) for the Monticello Nuclear Generating Plant for Cycle 32 L-MT-23-017, 2022 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP)2023-04-18018 April 2023 2022 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP) L-MT-23-010, Subsequent License Renewal Application Supplement 12023-04-0303 April 2023 Subsequent License Renewal Application Supplement 1 L-MT-23-013, Core Operating Limits Report (COLR) for Cycle 31, Revision 32023-03-28028 March 2023 Core Operating Limits Report (COLR) for Cycle 31, Revision 3 L-MT-23-012, Core Operating Limits Report (COLR) for Monticello Nuclear Generating Plant Cycle 31, Revision 22023-03-17017 March 2023 Core Operating Limits Report (COLR) for Monticello Nuclear Generating Plant Cycle 31, Revision 2 L-MT-23-008, 10CFR50.55a Request to Use Later Edition of ASME Section XI for ISI Code of Record (RR-003)2023-02-0707 February 2023 10CFR50.55a Request to Use Later Edition of ASME Section XI for ISI Code of Record (RR-003) L-MT-23-004, CFR 50.55a Request RR-001, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI for the Monticello Third Interval Containment Inservice Inspection Program2023-01-23023 January 2023 CFR 50.55a Request RR-001, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI for the Monticello Third Interval Containment Inservice Inspection Program L-MT-23-005, Response to the NRC Request for Additional Information Regarding the 50.55a Request Pr 08, HPCI Pump Quarterly Testing (EPID Number L-2022-LLR-0088)2023-01-0606 January 2023 Response to the NRC Request for Additional Information Regarding the 50.55a Request Pr 08, HPCI Pump Quarterly Testing (EPID Number L-2022-LLR-0088) L-MT-22-049, Industry Groundwater Protection Initiative Special Report2022-12-15015 December 2022 Industry Groundwater Protection Initiative Special Report L-MT-22-052, L-MT-22-052 Monticello Nuclear Generating Plant 10 CFR 50.55a Request No. Pr 08, Request for HPCI Pump Quarterly Alternative2022-12-15015 December 2022 L-MT-22-052 Monticello Nuclear Generating Plant 10 CFR 50.55a Request No. Pr 08, Request for HPCI Pump Quarterly Alternative L-MT-22-046, 2022 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462022-12-13013 December 2022 2022 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46 L-MT-22-048, Update to the Monticello Technical Specification Bases2022-11-28028 November 2022 Update to the Monticello Technical Specification Bases L-MT-22-047, Withdrawal of Request for Relief from ASME OM Code for the Sixth Inservice Testing Interval2022-11-10010 November 2022 Withdrawal of Request for Relief from ASME OM Code for the Sixth Inservice Testing Interval L-MT-22-045, Letter Submitting Post-Exam Package2022-11-0404 November 2022 Letter Submitting Post-Exam Package L-MT-22-030, Sixth Interval Inservice Testing (1ST) Plan2022-09-0606 September 2022 Sixth Interval Inservice Testing (1ST) Plan L-MT-22-037, Supplement to 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval, Alternative VR-10, Excess Flow Check Valve Testing Frequency2022-08-29029 August 2022 Supplement to 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval, Alternative VR-10, Excess Flow Check Valve Testing Frequency L-MT-22-007, Response to Request for Additional Information for the Monticello Nuclear Generating Plant Alternative Request VR-08 (EPID: L-MT-22-007)2022-07-22022 July 2022 Response to Request for Additional Information for the Monticello Nuclear Generating Plant Alternative Request VR-08 (EPID: L-MT-22-007) L-MT-22-026, Changes to the Emergency Plan2022-07-19019 July 2022 Changes to the Emergency Plan L-MT-22-024, Response to a Request for Additional Information for the Monticello Nuclear Generating Plant Related to the Amendment to Adopt Advanced Framatome Methodologies2022-06-0606 June 2022 Response to a Request for Additional Information for the Monticello Nuclear Generating Plant Related to the Amendment to Adopt Advanced Framatome Methodologies L-MT-22-022, Response to a Request for Additional Information: Monticello Alternative VR-10, Excess Flow Check Valve Testing Frequency2022-05-25025 May 2022 Response to a Request for Additional Information: Monticello Alternative VR-10, Excess Flow Check Valve Testing Frequency 2024-07-09
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARL-MT-23-054, Subsequent License Renewal Application Supplement 82024-01-11011 January 2024 Subsequent License Renewal Application Supplement 8 L-MT-23-047, License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data2023-12-29029 December 2023 License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data L-MT-23-038, 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-23-035, Subsequent License Renewal Application Supplement 52023-08-28028 August 2023 Subsequent License Renewal Application Supplement 5 L-MT-23-031, Subsequent License Renewal Application Supplement 4 and Responses to Request for Confirmation of Information - Set 12023-07-18018 July 2023 Subsequent License Renewal Application Supplement 4 and Responses to Request for Confirmation of Information - Set 1 L-MT-23-025, Subsequent License Renewal Application Supplement 22023-06-26026 June 2023 Subsequent License Renewal Application Supplement 2 L-MT-23-010, Subsequent License Renewal Application Supplement 12023-04-0303 April 2023 Subsequent License Renewal Application Supplement 1 ML23009A3542023-01-0909 January 2023 Subsequent License Renewal Application Sections 1 - 4 and Appendices a - D 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-21-072, License Amendment Request: Revise MNGP Technical Specifications to Support a Ten-Year Inspection of the Diesel Generator Fuel Oil Storage Tank2021-12-13013 December 2021 License Amendment Request: Revise MNGP Technical Specifications to Support a Ten-Year Inspection of the Diesel Generator Fuel Oil Storage Tank L-MT-21-067, Update to the Monticello Technical Specification Bases2021-11-29029 November 2021 Update to the Monticello Technical Specification Bases ML21320A2262021-11-15015 November 2021 License Amendment Request: Standard Emergency Plan and Consolidated Emergency Operations Facility for the Monticello Nuclear Generating Plant and the Prairie Island Nuclear Generating Plant L-MT-21-043, Supplement to License Amendment Request: Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2021-06-30030 June 2021 Supplement to License Amendment Request: Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b 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-20-018, License Amendment Request: Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2020-09-22022 September 2020 License Amendment Request: Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements L-MT-20-003, License Amendment Request: Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times-RITSTF Initiative 4b2020-03-30030 March 2020 License Amendment Request: Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times-RITSTF Initiative 4b ML20058F9432020-02-27027 February 2020 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - License Amendment Request: Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules Revision 4 L-MT-18-073, Supplement to License Amendment Request: Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee...2018-11-20020 November 2018 Supplement to License Amendment Request: Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee... L-MT-18-009, License Amendment Request: Revise Limiting Condition for Operation (LCO) of Specification 3.5.1, Emergency Core Cooling System - Operating, to Remove the LCO Note2018-11-12012 November 2018 License Amendment Request: Revise Limiting Condition for Operation (LCO) of Specification 3.5.1, Emergency Core Cooling System - Operating, to Remove the LCO Note 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-18-051, Supplement to License Amendment Request to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control,2018-09-11011 September 2018 Supplement to License Amendment Request to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, 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 L-MT-18-020, Supplement to License Amendment Request: Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Control2018-04-24024 April 2018 Supplement to License Amendment Request: Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Control L-MT-18-010, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2018-03-28028 March 2018 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors 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-17-058, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control2017-10-20020 October 2017 Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control ML17095A1142017-03-31031 March 2017 License Amendment Request to Revise Emergency Action Level Scheme: Attachment 4, Supporting Calculations for EAL Thresholds, Part 2 of 5 ML17095A1202017-03-31031 March 2017 License Amendment Request to Revise Emergency Action Level Scheme: Attachment 4, Supporting Calculations for EAL Thresholds, Part 5 of 5 ML17090A2012017-03-31031 March 2017 License Amendment Request to Revise Technical Specification for Plant/Unit Staff Qualifications Education and Experience Eligibility Requirements for Licensed Operators ML17095A1152017-03-31031 March 2017 License Amendment Request to Revise Emergency Action Level Scheme: Attachment 4, Supporting Calculations for EAL Thresholds, Part 3 of 5 ML17095A1132017-03-31031 March 2017 License Amendment Request to Revise Emergency Action Level Scheme: Attachment 4, Supporting Calculations for EAL Thresholds, Part 1 of 5 ML17095A1182017-03-31031 March 2017 License Amendment Request to Revise Emergency Action Level Scheme: Attachment 4, Supporting Calculations for EAL Thresholds, Part 4 of 5 ML17095A1122017-03-31031 March 2017 License Amendment Request to Revise Emergency Action Level Scheme: Attach. 1, EAL Comparison Matrix Document (Deviations & Differences) and Attachments 2 & 3, Red-Line & Clean Versions of EAL Technical Bases Document L-MT-16-031, Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing, and to Request an Alternative to the ASME Code2016-07-28028 July 2016 Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing, and to Request an Alternative to the ASME Code L-MT-16-014, License Amendment Request: Revise Battery Charger Surveillance Requirement 3.8.4.22016-04-0404 April 2016 License Amendment Request: Revise Battery Charger Surveillance Requirement 3.8.4.2 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 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 L-MT-15-048, License Amendment Request: Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process2015-07-15015 July 2015 License Amendment Request: Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process 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 ML14126A7272014-05-0505 May 2014 Supplement to License Amendment Request (LAR) for Cyber Security Plan Implementation Date Extension L-MT-14-009, License Amendment Request: Revision to Required Actions for Technical Specification 3.5.1, Emergency Core Cooling System (ECCS)2014-04-0404 April 2014 License Amendment Request: Revision to Required Actions for Technical Specification 3.5.1, Emergency Core Cooling System (ECCS) ML14072A3902014-03-13013 March 2014 License Amendment Request for Fuel Storage Changes, Supplement to Propose a Spent Fuel Pool Boral Monitoring Program Technical Specification ML13333B6742013-11-27027 November 2013 License Amendment Request (LAR) for Northern States Power Company, Minnesota (NSPM) Cyber Security Plan Implementation Date Extension L-MT-13-081, Maximum Extended Load Line Limit Analysis Plus License Amendment Request - Request for Additional Information Responses2013-08-14014 August 2013 Maximum Extended Load Line Limit Analysis Plus License Amendment Request - Request for Additional Information Responses 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 L-MT-13-046, License Amendment Request for Fuel Storage Changes, Supplement to Respond to NRC Staff Requests for Additional Information2013-05-16016 May 2013 License Amendment Request for Fuel Storage Changes, Supplement to Respond to NRC Staff Requests for Additional Information 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-13-010, License Amendment Request: Reduce the Reactor Steam Dome Pressure Specified in the Reactor Core Safety Limits2013-03-11011 March 2013 License Amendment Request: Reduce the Reactor Steam Dome Pressure Specified in the Reactor Core Safety Limits L-MT-12-102, License Amendment Request: Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month.2013-01-0404 January 2013 License Amendment Request: Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month. L-MT-12-078, License Amendment Request: Modification to the MNGP Emergency Plan Concerning a Revision to the Emergency Action Level Setpoint for the Turbine Building Normal Waste Sump Monitor2012-12-21021 December 2012 License Amendment Request: Modification to the MNGP Emergency Plan Concerning a Revision to the Emergency Action Level Setpoint for the Turbine Building Normal Waste Sump Monitor 2024-01-11
[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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N Monticello Nuclear Generatinq Plant Cornmiffed to Nuclear Excellence Operated by Nuclear Management Company, LLC January 30,2007 L-MT-07-0 14 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Monticello Nuclear Generating Plant Docket 50-263 License No. DPR-22 License Amendment Request to Revise Technical Specification Surveillance Requirement 3.5.1.3 to Correct the Alternate Nitrogen Svstem Pressure Pursuant to 10 CFR 50.90, the Nuclear Management Company, LLC (NMC) hereby requests an amendment to the Technical Specifications (TS) for the Monticello Nuclear Generating Plant (MNGP) Renewed Operating License DPR-22. The proposed change would revise MNGP TS Surveillance Requirement 3.5.1.3.b to state that the MNGP Alternate Nitrogen System required pressure for operability is 2 41 0 psig not the 2 220 psig currently stated in the TS Surveillance Requirement.
NMC has determined that the current MNGP TS value for the alternate nitrogen system is non-conservative and that the guidance of Nuclear Regulatory Commission (NRC) Administrative Letter 98-1 0, "Dispositioning of Technical Specifications that are Insufficient to Assure Plant Safety," applies. Therefore, NMC has currently implemented administrative controls to maintain the Alternate Nitrogen System pressure at 2 41 0 psig, and is submitting this License Amendment Request to address this nonconformance. Enclosure 1 provides the Proposed Change, Background, Technical Analysis, Regulatory Safety Analysis and Environmental Consideration.
Enclosure 2 provides the Marked-up MNGP Technical Specification page. Enclosure 3 provides the Re-typed MNGP Technical Specification Page. Enclosure 4 provides the Marked-up MNGP TS Bases page, provided for information only. The Plant Operations Review Committee has reviewed this application.
A copy of this submittal, including the Determination of No Significant Hazards Consideration, is being forwarded to our appointed state official pursuant to 10 CFR 50.91 (b)(l). 2807 West County Road 75 Monticello, Minnesota 55362-9637 Telephone:
763.295.5151 USNRC Page 2 NMC requests approval of the proposed amendment by the end of January 2008. Once approved, the amendment will be implemented within 60 days. This letter contains no new commitments and makes no revisions to any existing commitments. I declare under penalty of perjury that the foregoing is true and correct. Executed on January 3 Q ,2007 Pohn T. Conway Site Vice President, Monticello Nuclear Generating Plant Nuclear Management Company, LLC
Enclosures:
(4) cc: Administrator, Region Ill, USNRC Project Manager, Monticello, USNRC Resident Inspector, Monticello, USNRC Minnesota Department of Commerce ENCLOSURE 1 Licensee's Evaluation of Proposed Change Section Title Page No.
1.0 DESCRIPTION
2
2.0 PROPOSED CHANGE
2 2.1 Change to TS SR 3.5.1.3.b 2
3.0 BACKGROUND
2 3.1 Change to TS SR 3.5.1.3.b 2
4.0 TECHNICAL ANALYSIS
4 4.1 Revision to TS SR 3.5.1.3.b 4 5.0 REGULATORY SAFETY ANALYSIS 4 5.1 No Significant Hazards Consideration 4 5.2 Applicable Regulatory Requirements/Criteria 6
6.0 ENVIRONMENTAL CONSIDERATION
7 Page 1 of 7 ENCLOSURE 1 1.0 Description Nuclear Management Company, LLC (NMC) hereby requests an amendment to the Technical Specifications (T S) for the Monticello Nucl ear Generating Plant (MNGP)
Renewed Operating License DPR-22.
NMC has determined that the current MNGP TS value for the alternate nitrogen system is non-conservative and that the guidance of Nuclear Regulatory Commission (NRC)
Administrative Letter 98-10, "Dispositioni ng of Technical Specif ications that are Insufficient to Assure Plant Safety," applies. Therefore, NMC has currently implemented administrative controls to maintain t he Alternate Nitrogen System pressure at 410 psig, and is submitting this License Amendment Request to address this nonconformance. This proposed change would revise MNGP TS Surveillance Requirement (SR) 3.5.1.3.b to correctly state that the r equired pressure at which the Alternate Nitrogen System is determined to be operable is 410 psig, not the currently stated pressure of 220 psig.
2.0 Proposed Change 2.1 Change to TS Surveill ance Requirement 3.5.1 This change to TS Surveillance Requirement 3.5.1, "ECCS - Operating," is being proposed to correct the require ments for the Alternate Nit rogen System pressure. TS Surveillance Requirement 3.5.1.3 require s verification of limits for Automatic Depressurization System (ADS) pneumatic pr essure for both of the required ADS pneumatic supplies.
This proposed change would revise the MNGP TS SR 3.5.1.3.b pressure limit for determining operability of the Alternate Nitrogen System, from 220 psig to the correct value of 410 psig.
3.0 Background 3.1 TS Surveillance Requirement 3.5.1.3 In response to NUREG 0737 Item II.K.3.28, t hat required a long term (100 day) post accident depressurization capability to assure long term shutdown cooling operability, NMC installed separate seismic Class 1 pneum atic sources from high pressure nitrogen bottles to supply two Sa fety Relief Valves (SRVs). The drywell penetration valves consist of a check valve and a solenoid valve for each SRV. The
solenoid valves were capable of holding pressu re in either direction of flow and are oriented so that flow from containment will seat the valve plug. Each SRV is supplied Page 2 of 7 ENCLOSURE 1 by a bottle bank which is sized to handle system leakage and one actuation of each of the two SRVs for a period of seven days.
The modifications provided two separate and independent safety related nitrogen supply trains to the primar y containment purge and vent valves and to the reactor building to torus vacuum breaker valves (t o maintain containment integrity). This improved the reliabilit y of the primary containment system.
Additional modifications re vised the Alternate Nitrogen S ystem to provide a safety related backup pneumatic supply for six of th e eight SRVs, all of the inboard MSIVs and the T-ring seals.
The bottled nitrogen supply racks used fo r the Alternate Nit rogen System are manually checked for adequate supply and pre ssure during plant operation at a frequency to assure minimum design capac ity requirements of the system will be met, when required, assuming worst case leakage rates.
The safety related Alternat e Nitrogen System provides an alternate pressure source to equipment required during or following an accident. An instrument nitrogen supply is provided to instruments, controls, and equi pment located in the drywell in lieu of instrument air. This is to eliminate a source of oxy gen build-up in containment through in-leakage. The Alter nate Nitrogen System consists of two separate safety related trains providing a safety related back-up pneumatic source from nitrogen bottle racks located in the turbine building. The location of the bottle racks permits replacement of nitrogen bottles to maintain the nitrogen pressure during normal operation and following an accident. Train A provides a backup pneumatic supply to the T-ring seals of the inboard Primary Containment Atmospheric Control System
purge and vent valves, the T-ring seals and actuators of the reactor building to
suppression chamber vacuum breakers, and sa fety relief valves. Train B provides a backup pneumatic supply to the T-ring s eals of the outboard Pr imary Containment Atmospheric Control System purge and vent valves, the inboard main steam isolation valves and safety relief valves.
Train B also provides the sole pneumatic supply to the Primary Containment Hard Pipe Vent System. Manifold and system pressures of each train are monitored by pr essure switches which give control room annunciation on low pressure. The accumulator bank associated with each ADS (safety relief) valve provides pneumatic pressure for valve actuation. The design pneumatic supply pressure requirements for the accumulator banks are such that, following a failure of the pneumatic supply to the accumulator banks, at least five valve actuations can occur over a ten hour period. The Emergency Core Cooling System (ECCS) safety analysis assume s only one actuation to achieve the depressurization required for operati on of the low pressure ECCS.
Page 3 of 7 ENCLOSURE 1 4.0 Technical Analysis 4.1 Revision to TS Surveillanc e Requirement 3.5.1.3.b This proposed change would revise MNGP TS Surveillance Requirement (SR) 3.5.1.3.b to correctly state that the required pressure at which the Alternate Nitrogen System is determined to be operable should be 410 psig, not the currently stated pressure of 220 psig.
A safety related Alternate Nitrogen System pr ovides an alternate pressure source to equipment required during or following an accident. An instrument nitrogen supply is provided to instruments, c ontrols, and equipment located in the drywell in lieu of instrument air, in order to eliminate a source of oxygen build-up in containment through in-leakage. The Alter nate Nitrogen System consists of two separate safety related trains providing a safety related back-up pneumatic source from nitrogen bottle racks located in the turbine building. The location of the bottle racks permits replacement of nitrogen bottles to maintain the nitrogen pressure during normal operation and following an accident. The accumulator bank associated with each ADS (safety relief) valve provides pneumat ic pressure for valve actuation. The design pneumatic supply pressure requirem ents for the accumulator banks are such that, following a failure of the pneumatic supply to the accumulator banks, at least five valve actuations can occur over a ten hour period. The ECCS safety analysis assumes only one actuation to achieve the depressurization required for operation of the low pressure ECCS.
A full nitrogen bottle is pressurized to 2640 psig and the Alter nate Nitrogen System instruments have a range from 200 to 3500 psig, therefore this change does not alter a design basis or a safety limit for a parameter established in the MNGP Updated Safety Analysis Report (USAR) or the MNGP renewed facility operating license. 5.0 Regulatory Safety Analysis 5.1 No Significant Hazards Consideration Determination This proposed change would revise MNGP TS Surveillance Requirement (SR) 3.5.1.3.b to correctly state that the required pressure at which the Alternate Nitrogen System is determined to be operable is 410 psig, not the currently stated pressure of 220 psig.
Nuclear Management Company, LLC (NMC) has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below:
Page 4 of 7 ENCLOSURE 1
- 1. Does the proposed amendment involve a significant in crease in the probability or consequences of an accident previously evaluated?
Response: No The system operability criter ia for the Alternate Nitr ogen System pressure is being revised from 220 psig to 410 psig to correct an incorrect value that was added to the TS during the conversion from MNGP custom TS to the improved TS. NMC has determined that the current MNGP TS value for the alternate nitrogen system is non-conservative and that the guidance of Nuclear Regulatory Commission (NRC) Administra tive Letter 98-10, "Dispositioning of Technical Specifications that are Insufficient to Assure Plant Safety," applies.
Therefore, NMC has current ly implemented administrative controls to maintain the Alternate Nitrogen S ystem pressure at 410 psig, and is submitting this License Amendment Request to address th is nonconformance. This proposed TS change does not introduce new equipm ent or new equipment operating modes, nor does the proposed change alter existing system relationships. The proposed change does not affect plant operation, design function or any analysis that verifies the capability of a system, structure or component (SSC) to perform a design function. Further, the proposed change does not increase the likelihood of the malfunction of any SSC or impact any analyzed accident. Consequently, the probability of an accident previ ously evaluated is not affected.
As stated above this nonconforming condition is currently being controlled by administrative controls to ensure that the verified Alternate Nitrogen System accumulator bank pressure is being maintained 410 psig. NMC has determined that the current MNGP TS value for the alternate nitrogen system is non-conservative and that the guidance of Nuclear Regulatory Commission (NRC) Administrative Letter 98-10 applies. The proposed change does not
increase the likelihood of the malfunction of any SSC or impact any analyzed accident. Consequently, there is no significant increase in the consequences of any accident previously evaluated.
Therefore, the proposed amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No.
The verified Alternate Nitrogen System accumulator bank pressure is being maintained 410 psig. This revision to the s ystem operability criteria for the Page 5 of 7 ENCLOSURE 1 Alternate Nitrogen Syst em pressure from 220 psig to 410 psig is a correction to a value that was inadvertently added to the TS during the conversion from MNGP custom TS to the improved TS. This revision does not change the design function or operation of any SSC. There is no new system component being installed, no construction of a new facility, no performance of a new test or maintenance function. The proposed TS change does not create
the possibility of a new credible failur e mechanism, or malfunction. The change does not modify the design function or operation of any SSC. Further, the proposed change does not introduce new ac cident initiators. Consequently, the changes cannot create the possibi lity of a new or different kind of accident from any accident previously evaluated.
Therefore, the proposed amendment will not create the possibility of a new or different kind of accident from any accident previously analyzed.
- 3. Does the proposed amendment involve a significant reduction in the margin of safety? Response: No The revision to the system operability crit eria for the Alternate Nitrogen System pressure from 220 psig to 410 psig is a correction to a value that was inadvertently added to the TS during the conversion from MNGP current TS to the improved TS. This change does not ex ceed or alter a design basis or a safety limit for a parameter establis hed in the MNGP Updated Safety Analysis Report (USAR) or the MNGP renewed faci lity operating license. Consequently, the change does not result in a r eduction in the margin of safety.
Therefore, the propos ed amendment does not involve a significant reduction in a margin of safety.
Based on the above, NMC concludes t hat the proposed amendment presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and accordingly, a finding of "no significant hazards consideration" is justified.
5.2 Applicable Regulatory Requirements/Criteria 10 CFR 50.36(c)(3), Surveillance Requirem ents are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operat ion will be within safety limits, and that the limiting conditions for operation will be met.
The proposed change would revise the system operability criteria for the Alternate Nitrogen System, from 220 psig to 410 psig; this is a correction to a value that Page 6 of 7 ENCLOSURE 1 was inadvertently added to the MNGP TS du ring the conversion from MNGP TS to the improved TS.
In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed m anner, (2) such activiti es will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the commo n defense and security or to the health and safety of the public.
6.0 Environmental Consideration NMC's review has determined that t he proposed amendment would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, or would change an inspection or surveillance requirement. However, the proposed amendm ent does not involve (i) a significant hazards consideration, (ii) a significant chang e in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occ upational radiation exposure.
Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9). Th erefore, pursuant to 10 CFR 51.22(b), no environmental impact statem ent or environmental a ssessment need be prepared in connection with the proposed amendment.
Page 7 of 7 ENCLOSURE 2 MARKED-UP TECHNICAL SPECIFICATION PAGE ECCS - Operating 3.5.1 ACTIONS (continued)
CONDITION M. Two or more low pressure ECCS injectionlspray subsystems inoperable for reasons other than Condition C, D, or F. HPCl System and one or more ADS valves inoperable.
REQUIRED ACTION M.l Enter LC0 3.0.3. COMPLETION TIME Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.5.1 .I Verify, for each low pressure ECCS injectionlspray subsystem, the piping is filled with water from the pump discharge valve to the injection valve. SR 3.5.1.2 Verify each ECCS injectionlspray subsystem manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.
SR 3.5.1.3 Verify ADS pneumatic pressure is as follows for each required ADS pneumatic supply: a. SIRV Accumulator Bank header pressure r 88.3 psig; and b. Alternate Nitrogen System pressure is r mpsig. FREQUENCY 31 days 31 days 31 days Monticello Amendment NO.^
ENCLOSURE 3 RETYPED TECHNICAL SPECIFICATION PAGE ECCS - Operating 3.5.1 M. Two or more low pressure ECCS injectionlspray subsystems inoperable for reasons other than Condition C, D, or F. ACTIONS (continued)
HPCl System and one or more ADS valves inoperable.
CONDITION M.l Enter LC0 3.0.3. Immediately REQUIRED ACTION COMPLETION TIME SR 3.5.1.1 Verify, for each low pressure ECCS injectionlspray subsystem, the piping is filled with water from the pump discharge valve to the injection valve. SURVEILLANCE REQUIREMENTS 31 days SURVEILLANCE SR 3.5.1.2 Verify each ECCS injectionlspray subsystem manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.
FREQUENCY 31 days SR 3.5.1.3 Verify ADS pneumatic pressure is as follows for each required ADS pneumatic supply: a. SIRV Accumulator Bank header pressure r 88.3 psig; and b. Alternate Nitrogen System pressure is r 41 0 psig. 31 days Monticello Amendment No. 446 ENCLOSURE 4 MARKED-UP TECHNICAL SPClFlCATlON BASES PAGE (Provided for Information Only)
ECCS - Operating 3.5.1 BASES SURVEILLANCE REQUIREMENTS (continued) also prevent a water hammer following an ECCS initiation signal. One acceptable method of ensuring that the lines are full is to vent at the high points. While the potential for developing voids in the HPCl System exists, the effects of a void have been analyzed and shown to be acceptable. The 31 day Frequency is based on the gradual nature of void buildup in the ECCS piping, the procedural controls governing system operation, and operating experience. Verifying the correct alignment for manual, power operated, and automatic valves in the ECCS flow paths provides assurance that the proper flow paths will exist for ECCS operation.
This SR does not apply to valves that are locked, sealed, or otherwise secured in position since these were verified to be in the correct position prior to locking, sealing, or securing. A valve that receives an initiation signal is allowed to be in a nonaccident position provided the valve will automatically reposition in the proper stroke time. This SR does not require any testing or valve manipulation; rather, it involves verification that those valves capable of potentially being mispositioned are in the correct position. This SR does not apply to valves that cannot be inadvertently misaligned, such as check valves. For the HPCl System, this SR also includes the steam flow path for the turbine and the flow controller position.
The 31 day Frequency of this SR was derived from the Inservice Testing Program requirements for performing valve testing at least once every 92 days. The Frequency of 31 days is further justified because the valves are operated under procedural control and because improper valve position would only affect a single subsystem.
This Frequency has been shown to be acceptable through operating experience.
Verification every 31 days that each ADS pneumatic pressure is within the analysis limits (SIRV Accumulator Bank header pressure 2 88.3 psig and Alternate Nitrogen System accumulator bank pressure 2m psig) ensures adequate air pressure for reliable ADS operation. The 410 accumulator bank associated with each ADS valve provides pneumatic pressure for valve actuation. The design pneumatic supply pressure requirements for the accumulator banks are such that, following a failure of the pneumatic supply to the accumulator banks, at least five valve actuations can occur over a ten hour period (Ref. 10). The ECCS safety analysis assumes only one actuation to achieve the depressurization - - Monticello B 3.5.1-1 1 Revision No. 2