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| | number = ML092260614 | | | number = ML092260614 |
| | issue date = 09/28/2009 | | | issue date = 09/28/2009 |
| | title = Monticello, License Amendment 164 Regarding Reactor Water Cleanup System Isolation (TAC No. ME1514) | | | title = Monticello, License Amendment 164 Regarding Reactor Water Cleanup System Isolation |
| | author name = Feintuch K D | | | author name = Feintuch K D |
| | author affiliation = NRC/NRR/DORL/LPLIII-1 | | | author affiliation = NRC/NRR/DORL/LPLIII-1 |
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| | page count = 9 | | | page count = 9 |
| | project = TAC:ME1514 | | | project = TAC:ME1514 |
| | stage = Approval | | | stage = Other |
| }} | | }} |
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| By letter dated May 29, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML091690575), Northern States Power Company of Minnesota (NSPM, the licensee) requested changes to the Technical Specifications (TSs) for Monticello Nuclear Generating Plant. The licensee proposed to revise the applicability for isolation of the Reactor Water Cleanup (RWCU) system on a Standby Liquid Control (SLC) system initiation (Function 5.d, in Table 3.3.6.1-1, "Primary Containment Isolation Instrumentation") | | By letter dated May 29, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML091690575), Northern States Power Company of Minnesota (NSPM, the licensee) requested changes to the Technical Specifications (TSs) for Monticello Nuclear Generating Plant. The licensee proposed to revise the applicability for isolation of the Reactor Water Cleanup (RWCU) system on a Standby Liquid Control (SLC) system initiation (Function 5.d, in Table 3.3.6.1-1, "Primary Containment Isolation Instrumentation") |
| to align with the modes stated in Specification 3.1.7. 2.0 BACKGROUND On September 15, 2005, the licensee submitted an application for a full-scope alternative source term (AST) amendment (Accession No. ML052640366), which was approved by the Nuclear Regulatory Commission (NRC) staff on December 7,2006, by Amendment No. 148 (Accession No. ML062790015). | | to align with the modes stated in Specification 3.1.7. |
| | |
| | ==2.0 BACKGROUND== |
| | |
| | On September 15, 2005, the licensee submitted an application for a full-scope alternative source term (AST) amendment (Accession No. ML052640366), which was approved by the Nuclear Regulatory Commission (NRC) staff on December 7,2006, by Amendment No. 148 (Accession No. ML062790015). |
| With adoption of the full-scope AST, the SLC system became credited for control of suppression pool pH to mitigate the radiological consequences of the design-basis accident loss-of-coolant accident in which fuel is damaged. The licensee submitted a supplement to the AST full-scope License Amendment Request, dated August 21,2006 (Accession No. ML062350046), translating the proposed AST changes from the custom Technical Specifications (CTS) format to the corresponding improved Technical Specifications (ITS) format. The applicability of the SLC system in Specification 3.1.7 was revised in this supplement to reflect the addition of Mode 3 to the previously existing modes of applicability for the SLC System, i.e., Modes 1 and 2, which had been carried over from the CTS to the ITS. However, the applicability for isolation of the (RWCU) system on a SLC system initiation (Function 5.d in Table 3.3.6.1-1) was not changed to include Mode 3. 3.0 TECHNICAL EVALUATION The SLC System is designed to provide the capability of bringing the reactor, at any time in a fuel cycle, from full power and minimum control rod inventory (which is at the peak of the xenon transient) to a subcritical condition with the reactor in the most reactive xenon free state without taking credit for control rod movement. | | With adoption of the full-scope AST, the SLC system became credited for control of suppression pool pH to mitigate the radiological consequences of the design-basis accident loss-of-coolant accident in which fuel is damaged. The licensee submitted a supplement to the AST full-scope License Amendment Request, dated August 21,2006 (Accession No. ML062350046), translating the proposed AST changes from the custom Technical Specifications (CTS) format to the corresponding improved Technical Specifications (ITS) format. The applicability of the SLC system in Specification 3.1.7 was revised in this supplement to reflect the addition of Mode 3 to the previously existing modes of applicability for the SLC System, i.e., Modes 1 and 2, which had been carried over from the CTS to the ITS. However, the applicability for isolation of the (RWCU) system on a SLC system initiation (Function 5.d in Table 3.3.6.1-1) was not changed to include Mode 3. 3.0 TECHNICAL EVALUATION The SLC System is designed to provide the capability of bringing the reactor, at any time in a fuel cycle, from full power and minimum control rod inventory (which is at the peak of the xenon transient) to a subcritical condition with the reactor in the most reactive xenon free state without taking credit for control rod movement. |
| The SLC System satisfies the requirements of 10 CFR 50.62 on anticipated transient without scram. | | The SLC System satisfies the requirements of 10 CFR 50.62 on anticipated transient without scram. |
|
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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] |
Text
UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555*0001 September 28, 2009 Mr. Timothy J. O'Connor Site Vice President Monticello Nuclear Generating Plant Northern States Power Company -Minnesota 2807 West County Road 75 Monticello, MN 55362-9637 SUB..MONTICELLO NUCLEAR GENERATING PLANT (MNGP) -ISSUANCE OF AMENDMENT REGARDING REACTOR WATER CLEANUP SYSTEM ISOLATION (TAC NO. ME1514)
Dear Mr. O'Connor:
The Commission has issued the enclosed Amendment No. 164 to Renewed Facility Operating License No. DPR-22 for the Monticello Nuclear Generating Plant. The amendment consists of changes to the Technical Specifications in response to your application dated May 29, 2009. The amendment changes the MNGP Technical Specifications, revising the applicability for isolation of the Reactor Water Cleanup System on a Standby Liquid Control system initiation to align with the modes stated in Specification 3.1.7. 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, Karl D. Feintuch, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-263
Enclosures:
- 1. Amendment No. 164 to DPR-22 2. Safety Evaluation cc Distribution via ListServ UNITED NUCLEAR REGULATORY WASHINGTON';
a.e.
NORTHERN STATES POWER COMPANY DOCKET NO. 50-263 MONTICELLO NUCLEAR GENERATING PLANT AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 164 License No. DPR-22 The U. S. Nuclear Regulatory Commission (the Commission) has found that: The application for amendment by Northern States Power Company -Minnesota (the licensee), dated May 29, 2009, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; 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 The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.2 of Renewed Facility Operating License No. DPR-22 is hereby amended to read as follows: Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 164, are hereby incorporated in the license. NSPM shall operate the facility in accordance with the Technical Specifications.
-2This license amendment is effective as of its date of issuance and shall be implemented within 90 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Peter S. Tam, Acting Chief Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Attachment Changes to Renewed Facility Operating License and Technical Specifications Date of Issuance:
September 28, 2009 ATTACHMENT TO LICENSE AMENDMENT NO. RENEWED FACILITY OPERATING LICENSE NO. DOCKET NO. Replace the following page of Renewed Facility Operating License DPR-22 with the revised page attached.
The revised page is identified by amendment number and contains a marginal line indicating the area of change. REMOVE INSERT 3 3 Replace the following page of Appendix A, Technical Specifications, with the revised page attached.
The revised page is identified by amendment number and contains a marginal line indicating the area of change. REMOVE INSERT 3.3.6.1-7 3.3.6.1-7
-3Pursuant to the Act and 10 CFR Part 70, NSPM to receive, possess, and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operations, as described in the Final Safety Analysis Report, as supplemented and amended, and the licensee's filings dated August 16, 1974 (those portions dealing with handling of reactor fuel) and August 17, 1977 (those portions dealing with fuel assembly storage capacity); Pursuant to the Act and 10 CFR Parts 30, 40 and 70, NSPM to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentati and radiation monitoring equipment calibration, and as fission detectors in amounts as required; Pursuant to the Act and 10 CFR Parts 30, 40 and 70, NSPM to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and Pursuant to the Act and 10 CFR Parts 30 and 70, NSPM to possess, but not separate, such byproduct and special nuclear material as may be produced by operation of the facility. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission, now or hereafter in effect; and is subject to the additional conditions specified or incorporated below: Maximum Power Level NSPM is authorized to operate the facility at steady state reactor core power levels not in excess of 1775 megawatts (thermal). Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 164, are hereby incorporated in the license. NSPM shall operate the facility in accordance with the Technical Specifications. Physical Protection NSPM shall implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Renewed License No. DPR-22 Amendment No. 164 Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 3 of 3) Primary Containment Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM CONDITIONS REFERENCED FROM REQUIRED ACTION C.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 5. RWCU System Isolation
- d. SLC System Initiation 1,2,3 H SR 3.3.6.1.6 NA e. Reactor Vessel Water Level -Low Low 1,2,3 2 F SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 -48 inches 6. Shutdown Cooling System Isolation
- a. Reactor Steam Dome Pressure High 1,2,3 2 F SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 5; 81.8 psig b. Reactor Vessel Water Level -Low 3,4,5 2(a) SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 7 inches 7. Traversing Incore Probe System Isolation
- a. Reactor Vessel Water Level -Low 1,2,3 2 G SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 7 inches b. Drywell Pressure High 1,2,3 2 G SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 5; 2.0 psig (a) Only one channel per trip system, with an isolation signal available to one shutdown cooling supply isolation valve, is required in MODES 4 and 5, provided RHR Shutdown Cooling System integrity is maintained.
Monticello 3.3.6.1-7 Amendment No. 164
REGl/{ "I r 0-s> UNITED STATES NUCLEAR REGULATORY COMMISSION
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... IJI '</.'f.-" i:; ..,.0 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 164 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-22 NORTHERN STATES POWER COMPANY -MINNESOTA MONTICELLO NUCLEAR GENERATING PLANT DOCKET NO. 50-263
1.0 INTRODUCTION
By letter dated May 29, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML091690575), Northern States Power Company of Minnesota (NSPM, the licensee) requested changes to the Technical Specifications (TSs) for Monticello Nuclear Generating Plant. The licensee proposed to revise the applicability for isolation of the Reactor Water Cleanup (RWCU) system on a Standby Liquid Control (SLC) system initiation (Function 5.d, in Table 3.3.6.1-1, "Primary Containment Isolation Instrumentation")
to align with the modes stated in Specification 3.1.7.
2.0 BACKGROUND
On September 15, 2005, the licensee submitted an application for a full-scope alternative source term (AST) amendment (Accession No. ML052640366), which was approved by the Nuclear Regulatory Commission (NRC) staff on December 7,2006, by Amendment No. 148 (Accession No. ML062790015).
With adoption of the full-scope AST, the SLC system became credited for control of suppression pool pH to mitigate the radiological consequences of the design-basis accident loss-of-coolant accident in which fuel is damaged. The licensee submitted a supplement to the AST full-scope License Amendment Request, dated August 21,2006 (Accession No. ML062350046), translating the proposed AST changes from the custom Technical Specifications (CTS) format to the corresponding improved Technical Specifications (ITS) format. The applicability of the SLC system in Specification 3.1.7 was revised in this supplement to reflect the addition of Mode 3 to the previously existing modes of applicability for the SLC System, i.e., Modes 1 and 2, which had been carried over from the CTS to the ITS. However, the applicability for isolation of the (RWCU) system on a SLC system initiation (Function 5.d in Table 3.3.6.1-1) was not changed to include Mode 3. 3.0 TECHNICAL EVALUATION The SLC System is designed to provide the capability of bringing the reactor, at any time in a fuel cycle, from full power and minimum control rod inventory (which is at the peak of the xenon transient) to a subcritical condition with the reactor in the most reactive xenon free state without taking credit for control rod movement.
The SLC System satisfies the requirements of 10 CFR 50.62 on anticipated transient without scram.
The Bases for Specification 3.1.7 and Table 3.3.6.1-1 for Function 5.d state that isolation of the RWCU system on SLC system initiation is necessary to prevent dilution and removal of the boron solution by the RWCU system. In addition, Section 5.4.8 "Reactor Water Cleanup System (BWR)," of the Standard Review Plan states that design should include: "Provisions to automatically terminate flow to the RWCS following liquid poison injection into the reactor water." This provision was included in the SLC system design. Later this provision was captured in the applicable TS requirements.
Therefore, the proposed change merely serves to restate the system design requirements in the applicable portions of the TS. The NRC staff agrees that the proposed change will continue to assure that the SLC system and RWCU system design requirements and assumptions of the AST analysis are met. Based on this, the NRC staff finds that the proposed change is 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 use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure.
The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration and there has been no public comment on such finding (74 FR 37248). 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 NRC staff has concluded, on the basis of 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 Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public. Principal Contributors:
Tony Nakanishi Date: September 28, 2009 Mr. Timothy J. O'Connor September 28, 2009 Site Vice President Monticello Nuclear Generating Plant -Minnesota Northern States Power Company -Minnesota 2807 West County Road 75 Monticello, MN 55362-9637 MONTICELLO NUCLEAR GENERATING PLANT (MNGP) -ISSUANCE OF AMENDMENT REGARDING REACTOR WATER CLEANUP SYSTEM ISOLATION (TAC NO. ME1514)
Dear Mr. O'Connor:
The Commission has issued the enclosed Amendment No. 164 to Renewed Facility Operating License No. DPR-22 for the Monticello Nuclear Generating Plant. The amendment consists of changes to the Technical Specifications in response to your application dated May 29,2009. The amendment changes the MI\lGP Technical Specifications, revising the applicability for isolation of the Reactor Water Cleanup System on a Standby Liquid Control system initiation to align with the modes stated in Specification 3.1.7. 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, IRAJ Karl D. Feintuch, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-263
Enclosures:
- 1. Amendment No. 164 to DPR-22 2. Safety Evaluation cc Distribution via ListServ DISTRIBUTION:
PUBLIC LPL3-1 rtf RidsNrrDorlLpl3-1 Resource RidsNrrPMMonticelio Resource RidsNrrLATHarris Resource RidsOGCRp Resource RidsAcrsAcnw_MailCTR Resource RidsNrrDirsSbpb RidsRgn3MailCenter Resource A. Nakanishi, NRR RidsNrrDorlDpr Accession No'.. ML092260614 OFFICE LPL3-1/PM LPL3-1/LA SRXB/BC OGC/NLO LPL3-1/BC(A)
NAME KFeintuch THarris for BTuily GCranston*
AJones PTam DATE 09/23/09 08/28/09 07/17/09 09/09/09 09/28/09 *Safety evaluation input transmitted by memo on date shown. OFFICIAL RECORD COpy