Letter Sequence Approval |
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EPID:L-2024-LLR-0014, 10 CFR 50.55a Request RR-017 - Inservice Inspection (ISI) Impracticality in Accordance with 10 CFR 50.55a(g)(5)(iii) During the Fifth Ten-Year Interval (Approved, Closed) |
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Category:E-Mail
MONTHYEARML24304B0562024-10-30030 October 2024 Acceptance of LAR to Revise TS to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements ML24284A2822024-10-0707 October 2024 Cover Email Re Monticello SLRA-3rd Round Request for Additional Information ML24254A3932024-08-26026 August 2024 SLRA - 2nd Round Request for Additional Information ML24239A3722024-08-26026 August 2024 SLRA - 2nd Round Request for Additional Information ML24218A2282024-08-0505 August 2024 Request for Confirmation of Information for Relief Request RR-017, Inservice Inspection Impracticality During the Fifth Ten-Year Interval ML24131A0802024-05-10010 May 2024 Final RAI for LAR to Revise TS 3.8.6, Battery Parameters, SR 3.8.6.6 ML24036A2462024-04-24024 April 2024 NRC to Fws, NRC Issuance of Draft Environmental Impact Statement for Monticello Subsequent License Renewal, Opportunity for Public Comment, and Endangered Species Act Determinations ML24092A2152024-03-27027 March 2024 Email: Requests for Information to Support Deis ML24068A0612024-03-0707 March 2024 Extension of Audit for License Amendment Request to Revise TS 3.8.6, Battery Parameters, SR 3.8.6.6 ML24064A1802024-03-0404 March 2024 Acceptance of Relief Request RR-017, Inservice Inspection (ISI) Impracticality During the Fifth Ten-Year Interval ML24036A0932024-02-0202 February 2024 Acceptance of License Amendment Request to Revise TS 5.6.5 and Update PTLR Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data ML24022A0212024-01-20020 January 2024 NRR E-mail Capture - Monticello - Request for Additional Information ISI RR-002 Alternative to Use IWB-2500(f) ML23353A0742023-12-19019 December 2023 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Proposed Alternative VR-09, Modifications to OMN-17 ML23348A3462023-12-14014 December 2023 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of License Amendment Request to Revise TS 3.8.6, Battery Parameters, SR 3.8.6.6 ML23268A0292023-09-20020 September 2023 SLRA - Requests for Confirmation of Information - Set 2 - Email from Marieliz Johnson to Shawn Hafen ML23249A2092023-09-0606 September 2023 NRR E-mail Capture - Action: Opportunity to Review and Comment on a New NRC Information Collection, 10 CFR Part 50.55a, Codes and Standards (3150-XXXX) ML23248A3462023-09-0505 September 2023 NRR E-mail Capture - Request for Additional Information for Monticello Nuclear Generating Plant and Prairie Island Nuclear Generating Plant - Decommissioning Funding Status Reports ML23237A4822023-08-25025 August 2023 SLRA - Request for Additional Information - Set 3 - Email from Marieliz Johnson to Shawn Hafen ML23228A1212023-08-16016 August 2023 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Alternative Request VR-11 for MO-2397 ML23227A2182023-08-15015 August 2023 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Alternative Request RR-002 to Use IWB-2500(f) ML23219A1072023-08-0707 August 2023 SLRA - Requests for Additional Information - Set 2 - Email from Marieliz Johnson to Shawn Hafen ML23200A3502023-07-19019 July 2023 SLRA - Requests for Additional Information - Set 1 - Email from Marieliz Johnson to Christopher Domingos ML23172A1122023-06-21021 June 2023 SLRA - Requests for Confirmation of Information - Set 1 - Email from Marieliz Johnson to Christopher Domingos ML23054A3322023-02-23023 February 2023 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Relief Request to Use Later Edition of ASME BPV Code, Section XI, for ISI Program Code of Record ML23053A1362023-02-13013 February 2023 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Relief Request to Use Later Edition of ASME BPV Code, Section XI, for Cisi Program ML23017A2222023-01-13013 January 2023 Verbal Authorization of Proposed Alternative PR-08 Regarding Inservice Testing Requirements of Certain High Pressure Coolant Injection System Components (EPID L-2022-LLR-0088) (Email) ML23004A1982023-01-0404 January 2023 NRR E-mail Capture - Draft Request for Additional Information Monticello Nuclear Generating Plant Request Pr 08, HPCI Pump Quarterly Testing ML23012A2102022-07-26026 July 2022 Letter Submitting Monticello Outline Package ML22175A1602022-06-24024 June 2022 NRR E-mail Capture - RAI Monticello Fuel Oil Storage Tank Inspection ML22181A1962022-06-24024 June 2022 NRR E-mail Capture - Draft RAI Monticello Alternative VR-08 ML22131A2652022-05-11011 May 2022 NRR E-mail Capture - Request for Additional Information Xcel Energy Amendment Request to Create a Common Eplan and EOF for Monticello and Prairie Island ML22123A2822022-05-0303 May 2022 NRR E-mail Capture - Request for Additional Information Monticello Alternative VR-10, EFCV Testing Frequency ML22101A0712022-04-11011 April 2022 NRR E-mail Capture - Monticello - Acceptance of Requested Licensing Action License Amendment Request to Revise TS 3.6.1.8 Residual Heat Removal (RHR) Drywell Spray Header and Nozzle Surveillance Frequency ML22089A1302022-03-30030 March 2022 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Alternative Related Excess Flow Check Valve Testing Frequency ML22082A1812022-03-23023 March 2022 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of VR-08 Alternative to Adopt ASME OM Code Case OMN-28 ML22075A2612022-03-16016 March 2022 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of VR-07 Alternative Related to MOV Testing Per ASME OM Code Case OMN-26 ML22067A2032022-03-0808 March 2022 Audit Plan to Support Review of an Amendment to Transition to Atrium 11 Fuel (Redacted) ML22011A0642022-01-11011 January 2022 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Licensing Action License Amendment Request to Support Diesel Generator Fuel Oil Storage Tank Inspection ML22005A3612022-01-0505 January 2022 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related to Pump Vibration Testing Per ASME OM Code Case OMN-22 ML21347A0082021-12-10010 December 2021 NRR E-mail Capture - Monticello and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested License Amendment Standard Emergency Plan and Consolidated Emergency Operations Facility ML21330A0382021-11-18018 November 2021 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related RHR and RHRSW Pump Testing ML21286A7882021-10-0606 October 2021 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related to Residual Heat Removal Heat Exchanger Flow Control Valve Stroke Timing ML21256A1892021-09-13013 September 2021 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related to Testing the Control Rod Drive Scram Discharge Header Check Valves ML21256A1862021-09-13013 September 2021 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related to HPCI and RCIC Pump Testing ML21256A1882021-09-13013 September 2021 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related to Vibration Testing Range for the Sblc Pumps ML21253A2002021-09-10010 September 2021 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related to Pressure Isolation Valve Testing ML21252A0132021-08-31031 August 2021 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Licensing Action License Amendment Request to Adopt Advanced Framatome Methodologies ML21130A3022021-05-0707 May 2021 Initial and Final Written 10 CFR 21 Notification for GE Hitachi Numac Prnm System ML21110A7042021-04-20020 April 2021 Response: Monticello Nuclear Plant Outage - Covid Risk to On-Site Employees ML21084A2522021-03-24024 March 2021 NRR E-mail Capture - Revised Review Schedule for Monticello TSTF-505 (EPID L-20200LLA-0062) 2024-08-05
[Table view] Category:Letter
MONTHYEARML24283A1192024-10-28028 October 2024 Letter to Shawn Hafen, Re Monticello Subsequent License Renewal Schedule Change L-MT-24-038, Subsequent License Renewal Application Response to Request for Additional Information - 3rd Round RAI2024-10-15015 October 2024 Subsequent License Renewal Application Response to Request for Additional Information - 3rd Round RAI ML24277A0202024-10-0303 October 2024 Operator Licensing Examination Approval Monticello Nuclear Generating Plant, October 2024 ML24199A1752024-10-0101 October 2024 Issuance of Amendment No. 212 Revise Technical Specification 3.8.6, Battery Parameters, Surveillance Requirement 3.8.6.6 IR 05000263/20240112024-10-0101 October 2024 Biennial Problem Identification and Resolution Inspection Report 05000263/2024011 L-MT-24-025, Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements2024-09-26026 September 2024 Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements L-MT-24-029, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information-Supplement to Set 1 Part 2 and Response to 2ci Round RAI2024-09-13013 September 2024 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information-Supplement to Set 1 Part 2 and Response to 2ci Round RAI IR 05000263/20240052024-08-30030 August 2024 Updated Inspection Plan and Follow-Up Letter for Monticello Nuclear Generating Plant, Unit 1 (Report 05000263/2024005) L-MT-24-028, Response to RCI for RR-017 ISI Impracticality2024-08-28028 August 2024 Response to RCI for RR-017 ISI Impracticality ML24222A1822024-08-27027 August 2024 – Proposed Alternative Request VR-09 to the Inservice Testing Requirements of the ASME OM Code for Main Steam Safety Relief Valves 05000263/LER-2024-002, Low Pressure Coolant Injection Inoperable Due to Motor Valve Failure2024-08-27027 August 2024 Low Pressure Coolant Injection Inoperable Due to Motor Valve Failure IR 05000263/20244202024-08-21021 August 2024 Security Baseline Inspection Report 05000263/2024420 - Cover Letter IR 05000263/20240022024-08-14014 August 2024 Integrated Inspection Report 05000263/2024002 ML24218A2282024-08-0505 August 2024 Request for Confirmation of Information for Relief Request RR-017, Inservice Inspection Impracticality During the Fifth Ten-Year Interval ML24208A1502024-07-26026 July 2024 Independent Spent Fuel Storage Installation - Submittal of Quality Assurance Topical Report (NSPM-1) ML24215A2992024-07-23023 July 2024 Minnesota State Historic Preservation Office Comments on Monticello SLR Draft EIS ML24198A2372024-07-18018 July 2024 Information Request to Support Upcoming Biennial Problem Identification and Resolution (Pi&R) Inspection at Monticello Nuclear Generating Plant L-MT-24-022, – Preparation and Scheduling of Operator Licensing Examinations2024-07-0909 July 2024 – Preparation and Scheduling of Operator Licensing Examinations ML24164A2402024-06-10010 June 2024 Minnesota State Historic Preservation Office- Comments on Draft Monticello SLR Draft EIS L-MT-24-019, Submittal of ASME Section XI, Section IWB-3720 Analytical Evaluation in Accordance with 10 CFR 50.55a(b)(2)(xliii)2024-06-10010 June 2024 Submittal of ASME Section XI, Section IWB-3720 Analytical Evaluation in Accordance with 10 CFR 50.55a(b)(2)(xliii) L-MT-24-017, Response to Request for Additional Information Regarding License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6 (EPID-L-2023-LLA-01602024-06-0404 June 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6 (EPID-L-2023-LLA-0160 ML24137A2792024-06-0303 June 2024 Audit Summary for License Amendment Request to Revise Technical Specification 3.8.6, Battery Parameters, Surveillance Requirement 3.8.6.6 ML24141A1292024-05-22022 May 2024 Northern States Power Company - Use of Encryption Software for Electronic Transmission of Safeguards Information ML24141A1782024-05-20020 May 2024 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection L-MT-24-015, Response to Request for Additional Information - Alternative Request VR-09 for OMN-172024-05-16016 May 2024 Response to Request for Additional Information - Alternative Request VR-09 for OMN-17 L-MT-24-013, 2023 Annual Radiological Environmental Operating Report2024-05-14014 May 2024 2023 Annual Radiological Environmental Operating Report ML24135A1902024-05-14014 May 2024 Submittal of 2023 Annual Radioactive Effluent Release Report IR 05000263/20240102024-05-13013 May 2024 Age-Related Degrading Inspection Report 05000263/2024010 ML24128A0042024-05-0909 May 2024 Letter to Minnesota State Historic Preservation Office- Section 106 Consultation Regarding the Monticello Nuclear Generating Plant Subsequent License Renewal Application ML24127A1472024-05-0909 May 2024 Letter to Mille Lacs Band- Section 106 Consultation Regarding the Monticello Nuclear Generating Plant Subsequent License Renew. Application L-MT-24-016, 2023 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP)2024-05-0808 May 2024 2023 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP) ML24089A2382024-04-29029 April 2024 Summary of Nuclear Property Insurance IR 05000263/20240012024-04-29029 April 2024 Plan - Integrated Inspection Report 05000263/2024001 ML24115A2902024-04-25025 April 2024 Sec106 Tribal, Jackson-Street, Lonna-Spirit Lake Nation ML24115A2872024-04-25025 April 2024 Sec106 Tribal, Dupuis, Kevin-Fond Du Lac Band of Lake Superior Chippewa ML24115A2932024-04-25025 April 2024 Sec106 Tribal, Johnson, Grant-Prairie Island Indian Community ML24115A3062024-04-25025 April 2024 Sec106 Tribal, Wassana, Reggie-Cheyenne and Arapaho Tribes 05000263/LER-2024-001, Reactor Scram, Containment Isolation, and Cooldown Rate Outside of Limits Following Technician Adjustment of Wrong Component2024-04-25025 April 2024 Reactor Scram, Containment Isolation, and Cooldown Rate Outside of Limits Following Technician Adjustment of Wrong Component ML24115A3032024-04-25025 April 2024 Sec106 Tribal, Taylor, Louis-Lac Courte Oreilles Band of Lake Superior Chippewa Indians ML24115A3002024-04-25025 April 2024 Sec106 Tribal, Rhodd, Timothy-Iowa Tribe of Kansas and Nebraska ML24115A2972024-04-25025 April 2024 Sec106 Tribal, Miller, Cole-Shakopee Mdewakanton Sioux Community ML24115A2962024-04-25025 April 2024 Sec106 Tribal, Larsen, Robert-Lower Sioux Indian Community ML24115A2952024-04-25025 April 2024 Sec106 Tribal, Kakkak, Gena-Menominee Indian Tribe of Wisconsin ML24115A2982024-04-25025 April 2024 Sec106 Tribal, Reider, Anthony-Flandreau Santee Sioux Tribe ML24115A2912024-04-25025 April 2024 Sec106 Tribal, Jacskon, Sr., Faron-Leech Lake Band of Ojibwe ML24115A3052024-04-25025 April 2024 Sec106 Tribal, Vanzile, Jr., Robert-Sokaogon Chippewa Community ML24115A2992024-04-25025 April 2024 Sec106 Tribal, Renville, J. Garret-Sisseton Wahpeton Oyate of the Lake Travers Reservation ML24115A3022024-04-25025 April 2024 Sec106 Tribal, Stiffarm, Jeffrey-Fort Belknap Indian Community ML24115A3072024-04-25025 April 2024 Sec106 Tribal, Williams, Jr., James-Lac Vieux Desert Band of Lake Superior Chippewa Indians ML24115A2892024-04-25025 April 2024 Sec106 Tribal, Fowler, Thomas-St. Croix Chippewa of Wisconsin 2024-09-26
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24290A0452024-10-0707 October 2024 Attachment - Monticello SLRA - 3rd Round Request for Additional Information 3rd Round RAI ML24254A4542024-08-26026 August 2024 RAI-holding Ponds ML24218A2282024-08-0505 August 2024 Request for Confirmation of Information for Relief Request RR-017, Inservice Inspection Impracticality During the Fifth Ten-Year Interval ML24198A2372024-07-18018 July 2024 Information Request to Support Upcoming Biennial Problem Identification and Resolution (Pi&R) Inspection at Monticello Nuclear Generating Plant ML24141A1782024-05-20020 May 2024 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML24131A0802024-05-10010 May 2024 Final RAI for LAR to Revise TS 3.8.6, Battery Parameters, SR 3.8.6.6 ML24107A1462024-04-15015 April 2024 Final Request for Additional Information Re VR-09 ML24040A0482024-02-12012 February 2024 – Request for Information for the NRC Age-Related Degradation Inspection: Inspection Report 05000263/2024010 ML24022A0212024-01-20020 January 2024 NRR E-mail Capture - Monticello - Request for Additional Information ISI RR-002 Alternative to Use IWB-2500(f) ML23268A0252023-09-25025 September 2023 SLRA - Requests for Confirmation of Information - Set 2 ML23248A3462023-09-0505 September 2023 NRR E-mail Capture - Request for Additional Information for Monticello Nuclear Generating Plant and Prairie Island Nuclear Generating Plant - Decommissioning Funding Status Reports ML23237A4832023-08-25025 August 2023 SLRA - Request for Additional Information - Set 3 ML23219A1072023-08-0707 August 2023 SLRA - Requests for Additional Information - Set 2 - Email from Marieliz Johnson to Shawn Hafen ML23219A1082023-08-0707 August 2023 SLRA - Requests for Additional Information - Set 2 ML23201A0352023-07-24024 July 2023 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML23200A3502023-07-19019 July 2023 SLRA - Requests for Additional Information - Set 1 - Email from Marieliz Johnson to Christopher Domingos ML23200A3512023-07-19019 July 2023 SLRA - Request for Additional Information - Set 1 ML23059A3522023-03-0101 March 2023 Request for Information for NRC Commercial Grade Dedication Inspection: Inspection Report 05000263/2023010 ML23058A1522023-02-27027 February 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000263/2023002 ML23004A1982023-01-0404 January 2023 NRR E-mail Capture - Draft Request for Additional Information Monticello Nuclear Generating Plant Request Pr 08, HPCI Pump Quarterly Testing ML22206A1662022-07-25025 July 2022 Information Request to Support Upcoming Problem Identification and Resolution Inspection at Monticello Nuclear Generating Plant ML22181A1962022-06-24024 June 2022 NRR E-mail Capture - Draft RAI Monticello Alternative VR-08 ML22175A1602022-06-24024 June 2022 NRR E-mail Capture - RAI Monticello Fuel Oil Storage Tank Inspection ML22131A2652022-05-11011 May 2022 NRR E-mail Capture - Request for Additional Information Xcel Energy Amendment Request to Create a Common Eplan and EOF for Monticello and Prairie Island ML22123A2822022-05-0303 May 2022 NRR E-mail Capture - Request for Additional Information Monticello Alternative VR-10, EFCV Testing Frequency ML21322A2362021-11-18018 November 2021 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000263/2022401 ML21085A8582021-03-26026 March 2021 Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team): Inspection Report 05000263/2021010 ML21068A2772021-03-0909 March 2021 NRR E-mail Capture - Monticello TSTF-505, Request for Additional Information ML20343A1292020-12-0808 December 2020 NRR E-mail Capture - Request for Additional Information ML20302A1972020-10-26026 October 2020 NRR E-mail Capture - Monticello Request for Additional Information TSTF-505 License Amendment Request ML20191A0252020-07-0101 July 2020 NRR E-mail Capture - Draft Request for Additional Information Monticello Alternative Request RR-016 Related to H8, H9, and H 10 Weld Examinations ML20133K0532020-05-14014 May 2020 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML20134H9282020-05-12012 May 2020 Notification of NRC Design Bases Assurance Inspection (Programs) and Initial Request for Information: Inspection Report 05000263/2020013 ML20120A0272020-04-28028 April 2020 NRR E-mail Capture - Request for Additional Information Monticello Long Term Steam Dryer Inspection Plan ML20099F3622020-04-0606 April 2020 Lr Phase 4 Request for Information ML20055F3672020-02-24024 February 2020 Information Request to Support Upcoming Temporary Instruction 2515/193 Inspection at Monticello Nuclear Generating Plant ML20035F1552020-02-0404 February 2020 NRR E-mail Capture - Request for Additional Information Monticello and Prairie Island Alternative Requests to Adopt Code Cases N-786-3 and N-789-3 (Epids: L-2019-LLR-0078 and L-2019-LLR-0079) ML19270E8652019-09-27027 September 2019 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information (Rbaker) ML19080A2182019-03-21021 March 2019 NRR E-mail Capture - Request for Additional Information Monticello License Amendment Request to Remove Note TS LCO 3.5.1 ML19070A1302019-03-0808 March 2019 Ltr. 03/08/19 Monticello Nuclear Generating Plant - Notification of an NRC Triennial Heat Sink Performance Inspection and Request for Information; Inspection Report 05000263/2019003 (DRS-V.Petrella) ML19031A9132019-01-31031 January 2019 NRR E-mail Capture - Request for Additional Information Monticello License Amendment Request to Adopt 10 CFR 50.69 ML18269A3572018-09-26026 September 2018 NRR E-mail Capture - Request for Additional Information Monticello License Amendment Request to Adopt TSTF-425 ML18173A0512018-06-22022 June 2018 NRR E-mail Capture - Request for Additional Information Monticello Request for Exemption from Appendix R Requirements (L-2018-LLE-0001) ML18130A7472018-05-0909 May 2018 NRR E-mail Capture - Request for Information Monticello TSTF-542 License Amendment Request ML18121A2542018-05-0101 May 2018 Enclosurequest for Additional Information (05/01/2018, E-Mail from C. Jacobs/Dsfm to S. Jurek Monticello Exemption: NRC Clarification Questions on RAI#1 Responses) ML18065A5482018-03-0606 March 2018 EnclosuRAI-1 (non-proprietary) (Letter to T. J. O'Connor First Request for Additional Information for Review of Exemption Request for Five Nonconforming Dry Shielded Canisters 11 Through 15) ML17293A0912017-10-18018 October 2017 NRR E-mail Capture - Request for Additional Information Monticello Request for Exemption from Appendix R Requirements (CAC No. MF9586; EPID L-2017-LLE-00012) ML17235B0012017-08-23023 August 2017 NRR E-mail Capture - Request for Additional Information Monticello EAL Scheme Change Amendment Request ML17221A3882017-08-0909 August 2017 NRR E-mail Capture - Request for Additional Information for Monticello Nuclear Generating Plant License Amendment Request Dated March 24, 2017 Emergency Response Organization ML17219A0752017-08-0707 August 2017 NRR E-mail Capture - Request for Additional Information for Monticello Nuclear Generating Plant License Amendment Request Dated March 24, 2017 Emergency Response Organization 2024-08-05
[Table view] |
Text
Brent Ballard
From: Brent Ballard Sent: Monday, August 5, 2024 2:03 PM To: Miller, Michael A; Jacobson, Ronald G.
Cc: Jeff Whited
Subject:
Monticello - Final RCI for RR-017 ISI Impracticality (EPID L-2024-LLR-0014)
Attachments: Monticello - Final RCI for RR-017.docx
Good morning, Mike and Ron,
By leer dated January 30, 2024 (Agencywide Documents Access Management System (ADAMS) Accession No. ML24033A295), Northern States Power Company, a Minnesota corporaon, doing business as Xcel Energy, submi ed inservice inspecon (ISI) relief request RR-017 for the "h ten-year ISI interval for the Moncello Nuclear Generang Plant. The RR-017 submi al requests relief for a number of designated reactor pressure vessel (RPV) nozzle-to-vessel welds on the basis that achievement of the required examinaon coverage of "essenally 100 percent," as required in Paragraph IWA-2200(c) of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Secon XI, Division 1, is impraccal due to physical obstrucons and the limitaons in the geometry of the RPV design.
The NRC sta has determined that addional informaon is needed to complete its review. A ached is NRC stas request for con"rmaon of informaon (RCI). The NRC sta is requesng a response to the RCI within 30 days of the date of this email, which is September 4, 2024. Please let me know if you have any quesons.
Thank you, Brent
Brent Ballard Project Manager Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 301-415-0680
1 REQUEST FOR CONFIRMATION OF INFORMATION ON
10 CFR 50.55a RELIEF REQUEST NO. RR-017
FOR FIFTH 10-YEAR INSERVICE INSPECTION INTERVAL
MONTICELLO NUCLEAR GENERATING PLANT
NORTHERN STATES POWER COMPANY
DOCKET NO. 50-263
By letter L-MT-2024-001 dated January 30, 2024 (Agencywide Documents Access Management System (ADAMS) Accession No. ML24033A295), Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy, (NSPM, the licensee) submitted inservice inspection (ISI) relief request RR-017 for the fifth ten-year ISI interval for the Monticello Nuclear Generating Plant (Monticello).
In RR-017, the licensee requests relief for a number of designated reactor pressure vessel (RPV) nozzle-to-vessel (NV) welds listed in Tables A, B, and C of Enclosure Attachment 1 to the L-MT-2024-001 letter. The licensee justified the requested relief on the basis that achievement of the required examination coverage of "essentially 100 percent," as required in Paragraph IWA-2200(c) of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, Division 1 (ASME Section XI), is impractical due to physical obstructions and the limitations in the geometry of the RPV design. Therefore, pursuant to 10 CFR 50.55a(g)(5)(iii), NSPM requested authorization of an alternative to the requirements of ASME Section XI Table IWB-2500-1, Category B-D, Item B3.90 and associated ASME Code Case N-613-1 and proposes to use the actual coverages of completed fifth interval examinations on the specified welds as an acceptable alternative that provides reasonable assurance of continued structural integrity of the RPV and of the NV welds in the RPV.
Regulatory Basis: The regulation in 10 CFR 50.55a, Paragraph (g)(4) requires, in part, that license holders of commercial operating licenses (including renewed and subsequent renewed licenses) to implement the ISI requirements of ASME Section XI for structures, systems and components (SSCs) identified as ASME Code Class 1, 2, and 3 SSCs. Acceptable editions of ASME Section XI for implementation are defined in 10 CFR 50.55a, Paragraph (a)(1)(ii). The regulation in 10 CFR 50.55a, Paragraph (g)(5)(iii) requires that, if the licensee has determined that conformance with a Code requirement is impractical for its facility, the licensee must notify the NRC and submit, as specified in § 50.4, information to support the determinations. The regulation in 10 CFR 50.55a(g)(5)(iii) requires the determinations of impracticality to be based on the demonstrated limitations experienced when attempting to comply with the ASME requirements during the ISI interval for which the request is being submitted and states that the ISI impracticality requests must be submitted to the NRC no later than 18 months after the expiration of the initial or subsequent 120-month inspection interval for which relief is sought.
The regulation in 10 CFR 50.55a, Paragraph (g)(6) states that the Commission: (1) will evaluate determinations submitted under 10 CFR 50.55a, Paragraph (g)(5) that the code requirements
1 are impractical, and (2) may grant such relief and may impose such alternative requirements as it determines that the alternatives are authorized by law, will not endanger life or property or the common defense and security, and are otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility.
Request for Confirmation of Information (RCI)
RCI #RR-017-1
Incoming Request and Background Information. The RR-017 impracticality request contains what appears to be contradictory information in the submittal. In section 6.2.1, on page 5 of the Enclosure in NSPM Letter No. L-MT-24-001, the licensee states that:
For the examinations conducted, satisfactory results were achieved, and no flaw indications were detected.
However, in the Indications Reported column entry of the line item for the NV weld of RPV main steam line nozzle N-3C in Table A of Enclosure, Attachment 1 in letter L-MT-24-001, the licensee reports that one acceptable flaw indication was detected in the weld (i.e., for the UT examination that was performed on the weld during the Year 2019 refueling outage). The footnote for Table A (the staff notes the footnote does not have a corresponding superscript in Table A; assumed to be for the N -3C NV weld as it is the only indication reported) states, "Previously recorded sub-surface indication was re-confirmed and re-evaluated as acceptable per Code paragraph IWB-3512-1. No observed change since previous exam in 2009."
Additionally, Table A of Enclosure 2 to NSPM's fourth interval alternative request (ML101300050) has a similar footnote for the N-3C NV weld and says no observed change since the 1998 exam.
In NSPMs response (ML24046A132) to RAI #RR-002-1, asked during the NRC staff's review of NSPM's RR-002 alternative request, a table provided in Attachment 1 shows a B3.90 relevant indication (RI) was found on the N-3C NV weld in 2019. NSPM also stated in the RAI response that, "One B3.90 relevant indication (RI) was evaluated for the N-3C NV weld that was accepted per IWB-3512-1 of the 2007 Edition with 2008 Addenda ASME Section XI for the 5th ISI Interval.
Request:
The staff requests that the licensee confirm the footnote for Table A of the Enclosure, in letter L-MT-24-001 is applicable to the N-3C NV weld. Further, the staff requests NSPM confirm one RI was detected during the 2019 exam for the N-3C NV weld, evaluated, and determined to be acceptable per IWB-3512-1, and that the statement in Section 6.2.1 on page 5 of the submittal enclosure, " For the examinations conducted, satisfactory results were achieved, and no flaw indications were detected," is in error. If necessary, please provide additional information to reconcile the apparent contradictory information between Table A and the quoted text in Section 6.2.1 on page 5 of the submittal enclosure.
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