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Category:Letter
MONTHYEARIR 05000282/20244032024-10-25025 October 2024 – Security Baseline Inspection Report 05000282/2024403 and 05000306/2024403 05000282/LER-2024-001-01, Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies2024-10-22022 October 2024 Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies L-PI-24-044, Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program2024-10-21021 October 2024 Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program ML24277A1012024-10-0303 October 2024 Closure of Interim Report of a Potential Deviation or Failure to Comply Associated with Bentley Systems Incorporated Autopipe Software ML24221A3622024-09-27027 September 2024 Issuance of Amendment Nos. 245 and 233 Revise Technical Specification 3.8.1, AC Sources-Operating, Surveillance Requirement 3.8.1.2, Note 3 ML24241A1682024-09-23023 September 2024 Transmittal Letter Amendment No. 13 to Materials License No. Special Nuclear Material-2506 for the Prairie Island Independent Spent Fuel Storage Installation 05000282/LER-2024-001, Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies2024-09-16016 September 2024 Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies IR 05000282/20243012024-09-13013 September 2024 NRC Initial License Examination Report 05000282/2024301 and 05000306/2024301 IR 05000282/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2024005 and 05000306/2024005) L-PI-24-040, Post-Submittal Package Letter2024-08-23023 August 2024 Post-Submittal Package Letter IR 05000282/20245012024-08-0505 August 2024 Emergency Preparedness Inspection Report 05000282/2024501 and 05000306/2024501 ML24213A1592024-07-31031 July 2024 Operator Licensing Examination Approval - Prairie Island Nuclear Generating Plant IR 05000282/20240022024-07-30030 July 2024 Integrated Inspection Report 05000282/2024002 and 05000306/2024002 ML24208A1502024-07-26026 July 2024 Independent Spent Fuel Storage Installation - Submittal of Quality Assurance Topical Report (NSPM-1) ML24197A2012024-07-15015 July 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2024004 IR 05000282/20240102024-06-28028 June 2024 Comprehensive Engineering Team Inspection Report 05000282/2024010 and 05000306/2024010 L-PI-24-036, – Preparation and Scheduling of Operator Licensing Examinations2024-06-28028 June 2024 – Preparation and Scheduling of Operator Licensing Examinations ML24158A5912024-06-0606 June 2024 CFR 50.46 LOCA Annual Report L-PI-24-031, Independent Spent Fuel Storage Installation, Supplement to License Amendment Request to Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2)2024-06-0505 June 2024 Independent Spent Fuel Storage Installation, Supplement to License Amendment Request to Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2) L-PI-24-014, License Amendment Request to Revise the Technical Specification Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumption2024-06-0303 June 2024 License Amendment Request to Revise the Technical Specification Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumption ML24155A1922024-05-31031 May 2024 Refueling Outage Unit 2 R33 Owners Activity Report for Class 1, 2, 3 and Mc Inservice Inspections 05000306/LER-2024-001-01, Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump2024-05-31031 May 2024 Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump ML24149A3712024-05-29029 May 2024 (Ping) - Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection ML24262A1992024-05-29029 May 2024 L-PI-24-018 PINGP 75 Day Letter L-PI-24-030, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.12024-05-22022 May 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.1 ML24141A1292024-05-22022 May 2024 Northern States Power Company - Use of Encryption Software for Electronic Transmission of Safeguards Information ML24141A0452024-05-20020 May 2024 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML24128A2572024-05-16016 May 2024 ISFSI A13 Acceptance Letter IR 05000282/20240012024-05-15015 May 2024 Integrated Inspection Report 05000282/2024001 and 05000306/2024001 ML24130A2362024-05-0909 May 2024 Independent Spent Fuel Storage Installation - 2023 Annual Radiological Environmental Monitoring Program Report ML24130A2392024-05-0909 May 2024 2023 Annual Radioactive Effluent Report ML24071A1162024-05-0101 May 2024 Issuance of Amendment Nos. 244 and 232 Revise TS 3.7.8, Cooling Water (Cl) System ML24128A0882024-04-30030 April 2024 Submittal of Updated Safety Analysis Report (Usar), Revision 38 ML24089A2382024-04-29029 April 2024 Summary of Nuclear Property Insurance 05000306/LER-2024-001, Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump2024-04-29029 April 2024 Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump IR 05000282/20244012024-04-25025 April 2024 – Security Baseline Inspection Report 05000282/2024401 and 05000306/2024401 ML24100A8042024-04-24024 April 2024 – Alternative Request RR-09 for Safety Injection and Volume Control System Category C Check Valve Inservice Testing ML24114A0882024-04-23023 April 2024 Annual Report of Individual Monitoring for the Prairie Island Nuclear Generating Plant (PINGP) ML24113A1182024-04-12012 April 2024 NRC Letter Re NRC Office of Investigations Report No. 3-2023-004 ML24100A1212024-04-0909 April 2024 Submittal of Revised Pressure and Temperature Limits Report ML24093A2832024-04-0202 April 2024 Nuclear Material Transaction Report L-PI-24-012, Independent Spent Fuel Storage Installation - License Amendment Request: Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2)2024-04-0202 April 2024 Independent Spent Fuel Storage Installation - License Amendment Request: Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2) ML24089A2402024-03-29029 March 2024 Guarantee of Payment of Deferred Premiums ML24060A1232024-03-27027 March 2024 to Request 1-RR-5-10 and 2-RR-5-10 Regarding Reactor Pressure Vessel Welds and Nozzle Welds ML24081A1532024-03-21021 March 2024 Reactor Trip, Auxiliary Feedwater and Emergency Service Water System Actuation Due to Electrical Transient in DC Control Power Cables ML24262A1512024-03-15015 March 2024 L-PI-24-011 150 Day Letter 2024 PINGP ILT NRC Exam ML24010A0582024-03-0505 March 2024 Amendment No. 12 to Materials License No. Special Nuclear Material-2506 for the Prairie Island Independent Spent Fuel Storage Installation L-PI-24-004, Independent Spent Fuel Storage Installation - Annual Effluent Report, January Through December 20232024-02-29029 February 2024 Independent Spent Fuel Storage Installation - Annual Effluent Report, January Through December 2023 IR 05000282/20230062024-02-28028 February 2024 Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2023006 and 05000306/2023006) ML24088A1102024-02-25025 February 2024 Fairbanks Morse (Fm) Part 21 Notification Report Number 23-01 Re Asco Stainless Steel Solenoid Valves 2024-09-27
[Table view] Category:License-Operator Examination Report (Non-Power Reactors Only)
MONTHYEARML11229A7782011-08-16016 August 2011 Confirmation of Initial License Examination IR 05000282/20023012002-09-12012 September 2002 NRC Initial License Examination Report 50-282/02-301(DRS) & 50-306/02-301(DRS) 2011-08-16
[Table view] |
Text
ber 12, 2002
SUBJECT:
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NRC INITIAL LICENSE EXAMINATION REPORT 50-282/02-301(DRS);
50-306/02-301(DRS)
Dear Mr. Nazar:
On August 16, 2002, the NRC completed initial operator licensing examinations at your Prairie Island Nuclear Generating Plant. The enclosed report presents the results of the examination.
The NRC administered the written examination on August 16, 2002, and the operating test from August 12 -15, 2002. Four reactor operator and four senior reactor operator applicants were administered license examinations. The results of the examinations were finalized on August 30, 2002. All eight applicants passed all sections of their respective examinations resulting in the issuance of four reactor operator licenses and four senior reactor operator licenses.
In accordance with 10 CFR Part 2.790 of the NRCs "Rules of Practice," a copy of this letter and its enclosures 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 Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). We will gladly discuss any questions you have concerning this examination.
Sincerely,
/RA/
David Pelton, Acting Chief Operations Branch Division of Reactor Safety Docket Nos. 50-282; 50-306 License Nos. DPR-42, DPR-60
Enclosures:
1. Operator Licensing Examination Report 50-282/02-301(DRS); 50-306/02-301(DRS)
2. Simulation Facility Report 3. Written Examinations and Answer Keys (RO & SRO)
REGION III==
Docket Nos: 50-282; 50-306 License Nos: DPR-42, DPR-60 Report No: 50-282/02-301(DRS); 50-306/02-301(DRS)
Licensee: Nuclear Management Company, LLC Facility: Prairie Island Nuclear Generating Plant Location: 1717 Wakonade Drive East Welch, MN 55089 Dates: August 12 through August 16, 2002 Examiners: Hironori Peterson, Chief Examiner Bruce Palagi, Examiner Phillip Young, Examiner Charles Phillips, Examiner in Certification Nicholas Valos, Examiner in Certification Approved by: David Pelton, Acting Chief Operations Branch Division of Reactor Safety
SUMMARY OF FINDINGS ER 05000282-02-301(DRS), 05000306-02-301(DRS), on 08/12-16/2002, Nuclear Management Company, LLC, Prairie Island Nuclear Generating Plant, Units 1 and 2.
The announced operator licensing initial examination was conducted by regional examiners in accordance with the guidance of NUREG-1021, Operator Licensing Examination Standards for Power Reactors, Revision 8, Supplement 1.
Examination Summary
- Four reactor operator and four senior reactor operator applicants were administered written examinations and operating tests for initial operator licensing. All eight applicants passed all sections of their respective examinations resulting in the issuance of four reactor operator licenses and four senior reactor operator licenses (Section 4OA5.1).
Report Details 4. OTHER ACTIVITIES (OA)
4OA5 Other
.1 Initial Licensing Examinations a. Inspection Scope The NRC examiners conducted announced operator licensing initial examinations during the week of August 12, 2002. The NRC staff used the guidance established in NUREG-1021, Operator Licensing Examination Standards for Power Reactors, Revision 8, Supplement 1, to prepare the examination outline and to develop the written examination and operating test. The NRC administered the written examination on August 16, 2002. The NRC examiners administered the operating test from August 12 through 15, 2002. Four reactor operator and four senior reactor operator applicants were examined.
b. Findings Written Examination The NRC developed the written examination. The licensee reviewed the written examination for technical accuracy from July 9 through 10, 2002, prior to the operating test validation week. Examination changes, agreed upon between the NRC and the licensee, were incorporated into the written examination in accordance with the guidelines provided in NUREG-1021.
The NRC examiners administered the written examination in accordance with NUREG-1021. The NRC examiners and licensee independently graded the written examination and concluded that all eight applicants passed. The licensee submitted no post written examination comments.
Operating Test The NRC developed the operating test. The licensee reviewed the operating test for technical accuracy from July 15 through 18, 2002, during the operating test validation week. Examination changes, agreed upon between the NRC and the licensee, were incorporated into the operating test according to NUREG-1021. The licensee submitted no post examination comments on the operating test.
Examination Results Four reactor operator and four senior reactor operator applicants were administered written examinations and operating tests for initial operator licensing. All eight applicants passed all sections of their respective examinations resulting in the issuance of four reactor operator licenses and four senior reactor operator licenses.
.2 Examination Security a. Inspection Scope The examiners reviewed and observed the licensees implementation of examination security requirements during the examination preparation and administration.
b. Findings The NRC examiners determined that the licensees examination security practices associated with the development and administration of the operator license examinations were satisfactory.
4OA6 Meetings Exit Meeting The chief examiner presented the examination teams preliminary observations and findings to you and other members of the licensee management on August 16, 2002.
The licensee acknowledged the observations and findings presented and did not identify any proprietary information.
PARTIAL LIST OF PERSONS CONTACTED Licensee R. Alexander, Licensing Engineer T. Allen, Operations Support Manager M. Gardzinski, Simulator Support D. Herling, Superintendent of Plant Operations J. Kempkes, Initial License Training Supervisor J. Lash, Operations Training Superintendent R. Lingle, Operations Manager M. Werner, Plant Manager NRC J. Adams, Prairie Island Senior Resident Inspector D. Karjala, Prairie Island Resident Inspector ITEMS OPENED, CLOSED AND DISCUSSED Opened None Closed None Discussed None LIST OF ACRONYMS ADAMS Agency-Wide Document Access and Management System DRS Division of Reactor Safety NRC Nuclear Regulatory Commission PARS Publicly Available Records RO Reactor Operator SRO Senior Reactor Operator
Enclosure 2 Simulation Facility Report Facility Licensee: Prairie Island Nuclear Generating Plant, Units 1 and 2 Facility Docket No.: 50-282; 50-306 Operating Tests Administered: August 12 - 15, 2002 The following documents observations made by the NRC examination team during the initial operator license examination. These observations do not constitute audit or inspection findings and are not, without further verification and review, indicative of non-compliance with 10 CFR Part 55.45(b). These observations do not affect NRC certification or approval of the simulation facility other than to provide information which may be used in future evaluations. No licensee action is required in response to these observations.
During the conduct of the simulator portion of the operating tests, the following items were observed:
ITEM DESCRIPTION None
Enclosure 3 Written Examinations and Answer Keys (RO/SRO)
ADAMS Accession # for RO/SRO Exam: ML022550657 7