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MONTHYEARRBG-48143, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-02-27027 February 2023 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Project stage: Request ML23103A4672023-04-0404 April 2023 NRR E-mail Capture - River Bend Station, Unit 1 - Acceptance Review for LAR to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Project stage: Acceptance Review ML23278A2402023-10-0606 October 2023 Regulatory Audit Plan in Support of License Amendment Requests to Revise TSs to Adopt Risk-Informed Completion Times and Implement the Provisions of 10 CFR 50.69 Project stage: Other 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 Project stage: Request 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 Project stage: Acceptance Review ML24036A0042024-02-14014 February 2024 – Audit Plan in Support of Review of License Amendment Request to Revise Technical Specification 3.8.6, Battery Parameters, Surveillance Requirement 3.8.6.6 Project stage: Other 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 Project stage: Other ML24102A2842024-05-0707 May 2024 Summary of Regulatory Audit in Support of LARs to Revise Technical Specifications to Adopt Risk-Informed Completion Times and Implement the Provisions of 10 CFR 50.69 Project stage: Approval ML24131A0802024-05-10010 May 2024 Final RAI for LAR to Revise TS 3.8.6, Battery Parameters, SR 3.8.6.6 Project stage: RAI ML24093A0892024-05-16016 May 2024 Issuance of Amendment No. 214 Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors Project stage: Approval 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 Project stage: Other 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 Project stage: Response to RAI ML24199A1752024-10-0101 October 2024 Issuance of Amendment No. 212 Revise Technical Specification 3.8.6, Battery Parameters, Surveillance Requirement 3.8.6.6 Project stage: Approval 2024-02-14
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Category:Audit Plan
MONTHYEARML24137A2792024-06-0303 June 2024 Audit Summary for License Amendment Request to Revise Technical Specification 3.8.6, Battery Parameters, Surveillance Requirement 3.8.6.6 ML24036A0042024-02-14014 February 2024 – Audit Plan in Support of Review of License Amendment Request to Revise Technical Specification 3.8.6, Battery Parameters, Surveillance Requirement 3.8.6.6 ML23332A1652023-11-30030 November 2023 Second Limited Aging Management Audit Plan Regarding the Subsequent License Renewal Application Review ML23215A1312023-08-0909 August 2023 License Renewal Regulatory Audit Regarding the Environmental Review of the Subsequent License Renewal Application ML23214A2422023-05-25025 May 2023 Breakout Questions - Aging Management Audit - Monticello Unit 1 - Subsequent License Renewal Application ML23048A0232023-02-24024 February 2023 Subsequent License Renewal Application - Audit Plan ML22067A2032022-03-0808 March 2022 Audit Plan to Support Review of an Amendment to Transition to Atrium 11 Fuel (Redacted) ML17220A3282017-08-10010 August 2017 Nuclear Regulatory Commission Audits of Licensee Responses to Phase 2 of Order EA-13-109 to Modify Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions ML17177A4462017-07-0606 July 2017 Audit Plan for Licensee Responses Concerning Seismic Hazard Reevaluations Related to Request for Information -(50.54(F) Letter) Regarding Recommendation 2.1 of the Near-Term Task Force ML16259A1892016-12-0505 December 2016 Nuclear Regulatory Commission Plan for the Audit of Mitigation Strategies Assessment Submittals Related to Order EA-12-049, Order to Modify Licenses With Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events ML16152A1252016-06-0707 June 2016 Nuclear Regulatory Commission Plan for the Audit of Northern States Power Company Minnesota'S Flood Hazard Reevaluation Report Submittal Relating to the Near-Term Task Force Recommendation 2.1-Flooding for Monticello Nuclear Generating Plan ML14356A0032015-02-10010 February 2015 Audit of Licensee Responses to the Expedited Seismic Evaluation Process to Support Implementation of Near-Term Task Force Recommendation 2.1, Seismic ML14290A3672014-10-22022 October 2014 Plan for the Onsite Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Order EA-12-049 and EA-12-051 ML14083A6202014-03-26026 March 2014 Nuclear Regulatory Commission Audits of Licensee Responses to Reliable Spent Fuel Pool Instrumentation Order EA-12-051 ML13127A1632013-05-23023 May 2013 Plan for the Regulatory Audit Regarding Flooding Walkdowns to Support Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident - Monticello Nuclear Generating Plant, Unit 1 2024-06-03
[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 IR 05000263/20240112024-10-0101 October 2024 Biennial Problem Identification and Resolution Inspection Report 05000263/2024011 ML24199A1752024-10-0101 October 2024 Issuance of Amendment No. 212 Revise Technical Specification 3.8.6, Battery Parameters, Surveillance Requirement 3.8.6.6 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 IR 05000263/20244012024-05-30030 May 2024 Public - Monticello Nuclear Generating Plant - Cyber Security Inspection Report 05000263/2024401 ML24141A1292024-05-22022 May 2024 Northern States Power Company - Use of Encryption Software for Electronic Transmission of Safeguards Information ML24141A1782024-05-20020 May 2024 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection L-MT-24-015, Response to Request for Additional Information - Alternative Request VR-09 for OMN-172024-05-16016 May 2024 Response to Request for Additional Information - Alternative Request VR-09 for OMN-17 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 ML24127A1472024-05-0909 May 2024 Letter to Mille Lacs Band- Section 106 Consultation Regarding the Monticello Nuclear Generating Plant Subsequent License Renew. Application ML24128A0042024-05-0909 May 2024 Letter to Minnesota State Historic Preservation Office- Section 106 Consultation Regarding the Monticello Nuclear Generating Plant Subsequent License Renewal Application L-MT-24-016, 2023 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP)2024-05-0808 May 2024 2023 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP) ML24089A2382024-04-29029 April 2024 Summary of Nuclear Property Insurance IR 05000263/20240012024-04-29029 April 2024 Plan - Integrated Inspection Report 05000263/2024001 ML24115A3032024-04-25025 April 2024 Sec106 Tribal, Taylor, Louis-Lac Courte Oreilles Band of Lake Superior Chippewa Indians ML24115A2892024-04-25025 April 2024 Sec106 Tribal, Fowler, Thomas-St. Croix Chippewa of Wisconsin ML24115A2902024-04-25025 April 2024 Sec106 Tribal, Jackson-Street, Lonna-Spirit Lake Nation ML24115A3062024-04-25025 April 2024 Sec106 Tribal, Wassana, Reggie-Cheyenne and Arapaho Tribes ML24115A2952024-04-25025 April 2024 Sec106 Tribal, Kakkak, Gena-Menominee Indian Tribe of Wisconsin ML24115A2992024-04-25025 April 2024 Sec106 Tribal, Renville, J. Garret-Sisseton Wahpeton Oyate of the Lake Travers Reservation ML24115A2932024-04-25025 April 2024 Sec106 Tribal, Johnson, Grant-Prairie Island Indian Community ML24115A2872024-04-25025 April 2024 Sec106 Tribal, Dupuis, Kevin-Fond Du Lac Band of Lake Superior Chippewa ML24115A3002024-04-25025 April 2024 Sec106 Tribal, Rhodd, Timothy-Iowa Tribe of Kansas and Nebraska ML24115A3072024-04-25025 April 2024 Sec106 Tribal, Williams, Jr., James-Lac Vieux Desert Band of Lake Superior Chippewa Indians ML24115A3022024-04-25025 April 2024 Sec106 Tribal, Stiffarm, Jeffrey-Fort Belknap Indian Community ML24115A2912024-04-25025 April 2024 Sec106 Tribal, Jacskon, Sr., Faron-Leech Lake Band of Ojibwe 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 ML24115A3052024-04-25025 April 2024 Sec106 Tribal, Vanzile, Jr., Robert-Sokaogon Chippewa Community ML24115A2962024-04-25025 April 2024 Sec106 Tribal, Larsen, Robert-Lower Sioux Indian Community ML24115A2942024-04-25025 April 2024 Sec106 Tribal, Johnson, John-Lac Du Flambeau Band of Lake Superior Chippewa Indians 2024-09-26
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Text
June 3, 2024
Shawn Hafen Site Vice President Northern States Power Company
- Minnesota Monticello Nuclear Generating Plant 2807 West County Road 75 Monticello, MN 55362
SUBJECT:
MONTICELLO NUCLEAR GENERATING PLANT - AUDIT
SUMMARY
FOR LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATION 3.8.6, BATTERY PARAMETERS, SURVEILLANCE REQUIREMENT 3.8.6.6 (EPID L-2023-LLA-0160)
Dear Shawn Hafen:
By letter dated November 10, 2023 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML23317A122), Northern States Power Company, a Minnesota Corporation (NSPM, the licensee), doing business as Xcel Energy, submitted a license amendment request (LAR) for the Monticello Nuclear Generating Plant to the U.S. Nuclear Regulatory Commission (NRC). Specifically, the proposed amendment revises Technical Specification 3.8.6, Battery Parameters, Surveillance Requirement 3.8.6.6, acceptance criteria for 125-volt direct current (VDC) batteries.
To support its review, by letter dated February 14, 2024 (ML24036A004), the NRC staff notified the licensee that they would conduct a regulatory audit from February 26, 2024, to March 8, 2024, through an online portal (also known as electronic portal, Certrec Portal, electronic reading room) established by NSPM. Due to the volume and complexity of calculations, and the need for clarifying information, the virtual audit was extended and concluded on April 3, 2024. The results of the re gulatory audit were used by the NRC staff to finalize requests for additional information, which were issued by email dated May 10, 2024 (ML24131A080). The regulatory audit summary is enclosed with this letter.
S. Hafen
If you have any questions, please contact me at 301-415-0860 or via e-mail at Brent.Ballard@nrc.gov.
Sincerely,
/RA/
Brent T. Ballard, Project Manager Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Docket No. 50-263
Enclosure:
Regulatory Audit Summary
cc: Listserv REGULATORY AUDIT
SUMMARY
REGARDING LICENSE AMENDMENT REQUEST TO
REVISE TECHNICAL SPECIFICATION 3.8.6, "BATTERY PARAMETERS"
SURVEILLANCE REQUIREMENT 3.8.6.6
NORTHERN STATES POWER COMPANY
MONTICELLO NUCLEAR GENERATING PLANT
DOCKET NO. 50-263
1.0 BACKGROUND
By letter dated November 10, 2023 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML23317A122), Norther n States Power Company, a Minnesota Corporation (NSPM, the licensee), doing business as Xcel Energy, submitted a license amendment request (LAR) for the Monticello Nuclear Generating Plant (Monticello).
The proposed amendment revises Technical Specification 3.8.6, Battery Parameters, Surveillance Requirement 3.8.6.6, acceptance criteria for 125-volt direct current (VDC) batteries.
The U. S. Nuclear Regulatory Commission (NRC) staff performed a preliminary review of the LAR and determined that a regulatory audit would assist in the timely completion of the review.
An audit plan was provided to the licensee on February 14, 2024 (ML24036A004), which provided the list of requested documents and other details pertaining to the audit. The purpose of the audit was to gain an understanding of the information needed to support the NRC staffs licensing decision regarding the LAR and to develop requests for additional information (RAIs),
if necessary. The information submitted in suppo rt of the LAR is under final review, and any additional information needed to support the LAR review will be formally requested by the NRC staff using the RAI process.
2.0 REGULATORY AUDIT BASES
A regulatory audit is a planned license or regulation-related activity that includes the examination and evaluation of primarily non-docketed information. The audit is conducted with the intent to gain understanding, to verify information, and to identify information that will require docketing to support the basis of a licensing or regulatory decision. Performing a regulatory audit is expected to assist the NRC staff in effi ciently conducting its review and gaining insights to the licensees processes and procedures. Inform ation that the NRC staff relies upon to make the safety determination must be submitted on the docket.
This regulatory audit is based on the following regulatory requirements and guidance:
Title 10 of the Code of Federal Regulations, section 50.63, Loss of All Alternating Current Power.
Enclosure
The Monticello Updated Safety Analysis Report, Principal Design Criteria (PDC),
specifically:
o PDC 1.2.1.a, General Criteria, o PDC 1.2.6, Plant Electrical Power, o PDC 1.2.10, Separation of Safety Systems, o PDC 1.2.11, Class I Equipment and Structures.
IEEE [Institute of Electrical and Electronics Engineers] Standard 450-1995, IEEE Recommended Practice for Maintenance, Testing, and Replacement of Vented Lead-Acid Batteries for Stationary Applications.
3.0 AUDIT ACTIVITIES AND SCOPE
By letter dated February 14, 2024 (ML24036A004), the NRC staff issued an audit plan. The original audit duration was from February 26, 20 24, to March 8, 2024. The NRC audit team held an entrance meeting with NSPM on February 26, 2024. Due to the volume and complexity of calculations, and the need for clarifying information, the virtual audit was extended and concluded on April 3, 2024. The audit was performed via online portal and there were no person-to-person interactions between the audit team and the licensee. Therefore, there was no need for a formal exit briefing. The NRC staff conducted this audit under the guidance provided in the Nuclear Reactor Regulation Office Instruction LIC-111, Regulatory Audits, Revision 1 (ML19226A274).
The audit team reviewed documentation and calculations that provide the technical support for the LAR. The NRC staffs audit focused on the following subjects:
The 125 VDC battery sizing calculations that have been revised.
The NRC staff provided four audit questions with items for NSPM to clarify. NSPM posted answers to these questions to the online portal. The audit questions are included in section 4.0 of this audit summary.
4.0 DOCUMENTS AND FILES REVIEWED
No. Audit Item 1 NSPM Calculation No.02-179, Revision 4, MNGP 125 Volt Div. I Battery Calculation 2 NSPM Calculation No.02-192, Revision 4, MNGP 125 Volt Div. II Battery Calculation
No. Audit Item 3 Licensee response to audit question 1 (question copied below):
According to Section 7.1 (pdf page 26 of 1165) of the 125 VDC Division 1 Battery Calculation, Attachment S (pdf page 1051) provides an overview of each specific scenario and the composite scenario.
The Attachment S provides scenarios with following time-steps:
(1) 23 time-steps (pdf pages 1052-1053)
(2) 29 time-steps (pdf pages 1054-1055)
(3) 31 times-steps (pdf pages 1056-1058)
(4) 61 time-steps (pdf pages 1059-1062)
The titles of the above four scenarios are missing. Please confirm that the titles are similar to ones provided in the Division 2 Battery Calculation Attachment S: (1) SBO Scenario, (2) SBLOCA Scenario, (3) LBLOCA Scenario, and (4) Composite Scenario.
4 Licensee response to audit question 2 (question copied below):
Attachment L (pdf pages 951-955) shows 17 load periods considered for the Cell Sizing Worksheet. Attachment M (pdf pages 955-956) provides Load Profile for Battery D1. Please explain how the load periods in Attachment L and load profile in Attachment M were developed considering various scenarios shown in question 1.
5 Licensee response to audit question 3 (question copied below):
Monticello TS SR 3.8.4.3, Note 1 states: The modified performance discharge test SR 3.8.6.6 may be performed in lieu of SR 3.8.4.3 (battery service test).
According to the LAR, the proposed revised TS SR 3.8.6.6 states:
Verify battery capacity is:
90% of the manufacturers rating for 250 VDC batteries 80% of the manufacturers rating for 125 VDC batteries when subjected to a performance discharge test or a modified performance discharge test.
Please provide the 125 VDC battery load profile(s) for (1) battery service test which would be considered for SR 3.8.4.3, and (2) performance discharge test, or a (3) modified performance test for SR 3.8.6.6. Also, explain how these test profiles were developed considering the 17 load periods considered in Attachment L, and the load profile provided in Attachment M of the battery sizing calculations.
No. Audit Item 6 Licensee response to audit question 4 (question copied below):
In response to audit Question 3 (3.3), for the #11, 125 VDC Battery, the Minimum Test Voltage is considered as 105 V for all load test steps. However, for the #12, 125 VDC Battery, the Minimum Test Voltage is considered as varying between 109.1 V and 106.8 V for the various load steps - with a footnote to 106.8 V stating: Terminal voltage required to satisfy the Service Test is 105.455.
Please explain why the minimum test voltage is considered as varying for Battery #12, and constant 105 V for Battery #11 for various load steps. Also, explain how the varying minimum test voltage is determined.
The licensee responses to the staff audit questions provided clarifications to the battery sizing calculations and the LAR. The NRC staff did not remove non-docketed information from the online portal.
5.0 AUDIT TEAM
The NRC audit team included the following:
Brent Ballard, Project Manager - Brent.Ballard@nrc.gov Kayleh Hartage, Electrical Engineer - Kayleh.Hartage@nrc.gov Vijay Goel, Senior Electrical Engineer - Vijay.Goel@nrc.gov Robert Elliot, Senior Safety and Plant Systems Engineer - Robert.Elliott@nrc.gov
6.0 RESULTS OF THE AUDIT
As a result of the audit, the NRC staff gained a better understanding of the licensees calculations supporting the LAR. RAIs were issued to the licensee on May 10, 2024 (ML24131A080). The licensee is scheduled to provide a response to the RAIs by June 10, 2024.
ML24137A279 OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DEX/EEEB/BC NAME BBallard SRohrer WMorton DATE 5/13/2024 5/16/2024 5/16/2024 OFFICE NRR/DORL/LPL3/BC NRR/DORL/LPL3/PM NAME JWhited BBallard DATE 5/31/2024 6/3/2024