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Category:Letter
MONTHYEARIR 05000282/20230042024-02-0101 February 2024 Integrated Inspection Report 05000282/2023004 and 05000306/2023004 ML23356A1232024-01-29029 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) 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 ML24017A0182024-01-19019 January 2024 Confirmation of Initial License Examination ML23356A0032024-01-17017 January 2024 Issuance of Amendments Revise Technical Specification 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) L-PI-23-034, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System,2024-01-0202 January 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System, L-PI-23-035, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report2023-12-20020 December 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report IR 07200010/20234012023-12-20020 December 2023 Independent Spent Fuel Storage Installation Security Inspection Report 07200010/2023401 ML23349A0572023-12-15015 December 2023 and Independent Spent Fuel Storage Installation, Revision to Correspondence Service List for Northern States Power - Minnesota ML23215A1672023-12-15015 December 2023 Acceptance of Requested Licensing Action Amendment Request to Revise Surveillance Requirement 3.8.1.2 Note 3 IR 05000282/20234012023-12-13013 December 2023 Security Baseline Inspection Report 05000282/2023401 and 05000306/2023401 L-PI-23-033, Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-12-0505 December 2023 Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3 ML23304A1632023-11-15015 November 2023 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request to Revise SR 3.8.1.2 Note 3 ML23319A3182023-11-15015 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000282/20230032023-11-0808 November 2023 Integrated Inspection Report 05000282/2023003 and 05000306/2023003 ML23311A3572023-11-0707 November 2023 Core Operating Limits Report (COLR) for Prairie Island Nuclear Generating Plant (PINGP) Unit 2. Cycle 33. Revision 0 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 ML23270B9022023-09-29029 September 2023 Review of Reactor Vessel Material Surveillance Program Capsule N Technical Report L-PI-23-025, License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-09-28028 September 2023 License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3 ML23265A2532023-09-26026 September 2023 Review of Reactor Vessel Material Surveillance Program Capsule N Technical Report ML23262B0372023-09-19019 September 2023 Response to NRC Request for Additional Information Regarding the 2023 Monticello and Prairie Island Plant Decommissioning Funding Status Reports 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 L-PI-23-023, Baffle Former Bolts Alternate Aging Management Strategy2023-09-11011 September 2023 Baffle Former Bolts Alternate Aging Management Strategy IR 05000282/20230052023-08-30030 August 2023 Updated Inspected Plan for Prairie Island Nuclear Generating Plant Report 05000282/2023005 and 05000306/2023005 IR 05000282/20230102023-08-17017 August 2023 NRC Inspection Report 05000282/2023010 and 05000306/2023010 ML23222A0122023-08-10010 August 2023 Independent Spent Fuel Storage Installation and Monticello Nuclear Generating Plant - Changes in Foreign Ownership, Control or Influence IR 05000282/20230022023-08-0303 August 2023 Integrated Inspection Report 05000282/2023002 and 05000306/2023002 ML23214A2032023-08-0202 August 2023 Request for Information for an NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000282/2024010; 05000306/2024010 ML23206A2342023-07-25025 July 2023 Independent Spent Fuel Storage Installation, and Monticello Nuclear Generating Plant, Changes in Foreign Ownership, Control or Influence 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) ML23199A0922023-07-18018 July 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000306/2023004 ML23195A1732023-07-14014 July 2023 Revision of Standard Practice Procedures Plan L-PI-23-018, License Amendment Request to Revise ISFSI Technical Specification 4.4 to Allow Use of a Code Alternative to ASME Code, NB-5130, Examination of Weld Edge Preparation Surfaces, for the TN-40HT2023-07-14014 July 2023 License Amendment Request to Revise ISFSI Technical Specification 4.4 to Allow Use of a Code Alternative to ASME Code, NB-5130, Examination of Weld Edge Preparation Surfaces, for the TN-40HT ML23181A0192023-06-30030 June 2023 Independent Spent Fuel Storage Installation, Revision to Correspondence Service List for Northern States Power - Minnesota ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III L-PI-23-006, License Amendment Request to Revise Technical Specification 3.7.8 Required Actions2023-06-22022 June 2023 License Amendment Request to Revise Technical Specification 3.7.8 Required Actions L-PI-23-016, 2022 10 CFR 50.46 LOCA Annual Report2023-06-14014 June 2023 2022 10 CFR 50.46 LOCA Annual Report IR 05000282/20234202023-06-0101 June 2023 Security Baseline Inspection Report 05000282/2023420 and 05000306/2023420 ML23150A1722023-05-30030 May 2023 Preparation and Scheduling of Operator Licensing Examinations 2024-02-01
[Table view] Category:License-Operator
MONTHYEARML24017A0182024-01-19019 January 2024 Confirmation of Initial License Examination ML22270A2372022-09-26026 September 2022 Form 5.1-1 Post Exam Checklist IR 05000282/20223012022-08-31031 August 2022 NRC Initial License Examination Report 05000282/2022301; 05000306/2022301 ML22249A0062022-08-26026 August 2022 2.1-1 Examination Preparation Checklist for Prairie Island 08092022 ML22270A2252022-08-26026 August 2022 Ile Security Agreement - Final ML22249A0072022-08-19019 August 2022 Ile 2022 Post Exam Comments Letter ML22213A1852022-08-0808 August 2022 Plan, Operator Licensing Examination Approval ML22237A3022022-08-0808 August 2022 Ile 2.3-2 ML22237A3032022-08-0808 August 2022 Ile 2.3-4 ML22166A3892022-07-28028 July 2022 Issuance of Amendments 239 and 227 24-Month Operating Cycle ML22174A3902022-06-27027 June 2022 Licensed Operator Positive Fitness-For-Duty Test ML22237A3012022-05-27027 May 2022 Ile Licensee Letter Transmitting Proposed Exam and Test ML22242A3032022-03-24024 March 2022 2.3-1 Exam Outline Quality Checklist ML22242A3072022-03-24024 March 2022 3.4-1 Scenario Events & Evolutions Checklist RO & SRO ML22027A8012022-01-27027 January 2022 Confirmation of Initial License Examination ML21121A0002021-04-27027 April 2021 Preparation and Scheduling of Operator Licensing Examinations ML21110A5922021-04-19019 April 2021 GFE Results, March 2021 ML21082A4892021-03-23023 March 2021 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information IR 05000282/20203012020-09-22022 September 2020 NRC Initial License Examination Report 05000282/2020301 and 05000306/2020301 ML20265A1722020-09-21021 September 2020 ES-201-1 L-PI-20-048, Post Exam Comments2020-09-21021 September 2020 Post Exam Comments ML20265A1802020-09-21021 September 2020 ES-403-1 L-PI-20-053, ES-201-32020-09-18018 September 2020 ES-201-3 ML20245E5482020-08-27027 August 2020 ES-D-1, Scenario Outline ML20252A2542020-08-27027 August 2020 Proposed facility-developed RO-SRO Written Examination ML20245E5792020-08-27027 August 2020 ES-301-6 ML20246G7462020-08-27027 August 2020 Ile As-Administered RO Admin JPMs ML20246G7432020-08-27027 August 2020 Ile As-Administered In-Plant JPMs ML20246G7322020-08-27027 August 2020 Ile As-Administered Simulator JPMs ML20245E5632020-08-27027 August 2020 ES-301-7 ML20245E5582020-08-27027 August 2020 ES-401-2, 3, 4, PWR Examination Outline ML20245E5822020-08-27027 August 2020 ES-201-2, Examination Outline Quality Checklist ML20245E5802020-08-27027 August 2020 75 Day Letter ML20245E5812020-08-27027 August 2020 ES-301-5, Transient and Event Checklist ML20252A2512020-08-27027 August 2020 Proposed Operating Test - Dynamic Simulator Scenarios ML20245E5692020-08-27027 August 2020 ES-401-9 ML20252A2482020-08-27027 August 2020 Proposed Operating Test - Walkthrough Portion JPMs ML20246G7542020-08-27027 August 2020 Ile As-Administered Scenarios ML20245E5702020-08-27027 August 2020 NRC Comments and Resolution on Licensee Outlines ML20245E5662020-08-27027 August 2020 ES-401-6 ML20245E5762020-08-27027 August 2020 ES-301-4 ML20246G7342020-08-27027 August 2020 Ile As-Administered SRO Admin JPMs ML20246G7402020-08-27027 August 2020 Ile As-Administered Written Exam ML20245E5742020-08-27027 August 2020 ES-301-3 ML20245E5642020-08-27027 August 2020 ES-401-4 ML20258A0162020-08-27027 August 2020 ES-401-6 ML20245E5452020-08-27027 August 2020 ES-301-1 and ES-301-2, Administrative Topics Outline ML20219A8402020-08-0707 August 2020 Operator Licensing Examination Approval ML20076F0592020-03-16016 March 2020 Preparation and Scheduling of Operator Licensing Examinations ML20023A2342020-01-23023 January 2020 Confirmation of Initial License Examination 2024-01-19
[Table view] Category:Fitness for Duty (FFD)
MONTHYEARML22174A3902022-06-27027 June 2022 Licensed Operator Positive Fitness-For-Duty Test 2022-06-27
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June 27, 2022 Mr. Christopher P. Domingos Site Vice President Prairie Island Nuclear Generating Plant Northern States Power Company, Minnesota 1717 Wakonade Drive East Welch, MN 55089-9642
SUBJECT:
PRAIRIE ISLAND NUCLEAR GENERATING PLANT; LICENSED OPERATOR POSITIVE FITNESS-FOR-DUTY TEST
Dear Mr. Domingos:
On June 14, 2022, your facility reported to the U.S. Nuclear Regulatory Commission (NRC) via Title 10 of the Code of Federal Regulations (10 CFR) 26.719 that an NRC-licensed operator tested positive following a fitness-for-duty test administered under 10 CFR 26.31(c) on June 14, 2022, (Event Report 55942). Although we have obtained preliminary information, this letter is a formal request for information pertaining to this occurrence. Within 30 days of the date of this letter, please provide responses to the questions listed in the enclosure. In addition, please provide other records and information on this operators fitness-for-duty that are relevant to this occurrence. If you are unable to meet this deadline, please notify us no later than 15 days from the date of this letter, with the reasons for the delay and a proposed date of submittal.
We request that any personal privacy, proprietary, or safeguards information in your response be contained in a separate enclosure and appropriately marked. The affidavit required by 10 CFR 2.390(b) must accompany your response, where applicable.
You should determine whether the operator meets the requirements of 10 CFR 55.33(a)(1).
You should ensure that: (1) the operator meets the general health requirements of ANSI/ANS-3.4-1983; (2) the operator does not have a disqualifying condition under Section 5.3 of that standard; and (3) documentation describing the designated physician's conclusion that the operator meets the requirements of ANSI/ANS-3.4-1983 is available for review by the NRC.
If a conditional license is requested per 10 CFR 55.25, that condition should be documented on NRC Form 396, Certification of Medical Examination by Facility Licensee, and sent to the U.S. Nuclear Regulatory Commission, ATTN: Regional Administrator, Region III Office, 2443 Warrenville Road, Suite 210, Lisle, IL 60532-4352.
If you determine that the operator no longer meets the medical qualifications described in 10 CFR 55.33(a)(1), then, in accordance with 10 CFR 55.25, you must notify the NRC, in writing, of the operators permanent incapacitation. For example, you must notify the NRC if you determine, based on your employee assistance program in consultation with your designated physician, that the operator can no longer meet the medical criteria of ANSI/ANS-3.4-1983.
The NRC will evaluate the information in your reply to this letter to determine if further action is warranted pursuant to 10 CFR Part 50 or Part 55. The information supplied will be maintained in NRC Privacy Systems of Records-16 and will be subject to the Privacy Act.
C. Domingos 2 Please provide a copy of this letter, as well as your response to this letter, to the operator.
If you are unwilling to provide this information to the operator for any reason, the NRC will provide the information to the operator when it is available as part of the operators docket file.
If you have any questions concerning this matter, please contact Patricia J. Pelke, Chief, Operations Branch, 630-829-9868. The requested information should be sent to the attention of Patricia J. Pelke at the NRC Region III Office, 2443 Warrenville Road, Suite 210, Lisle, IL 60532-4352. Your cooperation is appreciated.
In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRCs document system (ADAMS). ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely, Curtis, David signing on behalf of Atack, Sabrina on 06/27/22 Sabrina Atack, Acting Director Division of Reactor Safety Docket Nos. 50-282, 50-306 License Nos. DPR-42, DPR-60
Enclosure:
Fitness-for-Duty Request for Additional Information cc: Distribution via LISTSERV Chad Boegeman, Training Manager
C. Domingos 3 Letter to Christopher Domingos from Sabrina Attack dated June 27, 2022.
SUBJECT:
PRAIRIE ISLAND NUCLEAR GENERATING PLANT; LICENSED OPERATOR POSITIVE FITNESS-FOR-DUTY TEST Distribution:
John Giessner Mohammed Shuaibi David Curtis Jamie Heisserer Kenneth Lambert Hironori Peterson Lauren Nist ADAMS Accession Number: ML22174A390 OFFICE RIII/DRS/OB RIII/DRS/OB RIII/EICS RIII/DRS/OB/BC NAME CZoia:jw BBartlett DBetancourt PPelke DATE 06/23/22 06/23/22 06/24/22 06/27/22 OFFICE RIII/DRS/DD NAME DCurtis for SAtack DATE 06/27/22 OFFICIAL RECORD COPY
Fitness-for-Duty Request for Additional Information Prairie Island Nuclear Generating Plant is requested to provide the following information concerning the fitness-for-duty occurrence (10 CFR 26.719) reported on June 14, 2022, regarding the involved licensed operator:
- 1. Name, Docket Number, and responsibilities of the operator.
- 2. A summary of the operators entire fitness-for-duty testing history.
Please include the dates and times the operator was tested, the reasons for the tests (i.e., random, for-cause, or follow-up), the results of the tests, including quantification, and the dates that any tests were confirmed positive.
- 3. Whether the operator used, sold, or possessed illegal drugs. If so, please provide the details of the circumstances surrounding such use, sale, or possession.
OR Whether the operator consumed alcoholic beverages within the protected area.
If so, please provide the details of the circumstances surrounding such consumption.
- 4. Whether the operator was at the controls or supervising licensed activities while under the influence of illegal drugs or alcohol. If so, please provide the details of the operators performance of licensed duties while under the influence.
- 5. Whether the operator fulfilled a position that was required to meet minimum licensed operating staffing requirements (fire brigade, emergency plan operations, etc.) while under the influence.
- 6. Whether the operator was involved in procedural errors related to this occurrence. If so, please provide the details of the procedural errors and the consequences of the errors.
- 7. The extent to which you reviewed the operators past work history, both on the day of the occurrence and prior to June 14, 2022.
- 8. Your intentions with regard to the operators resumption of duties under the 10 CFR 50 and 10 CFR 55 licenses, including your plans for follow-up testing.
Enclosure