|
---|
Category:Letter
MONTHYEARIR 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 ML24149A3712024-05-29029 May 2024 (Ping) - Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 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 ML24130A2392024-05-0909 May 2024 2023 Annual Radioactive Effluent Report ML24130A2362024-05-0909 May 2024 Independent Spent Fuel Storage Installation - 2023 Annual Radiological Environmental Monitoring Program 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 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 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) ML24093A2832024-04-0202 April 2024 Nuclear Material Transaction Report 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 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 L-PI-24-009, Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Unit 2, Alternative RR-09 Safety Injection System and Volume Control System Category C Check Valve Quarterly Testing2024-02-13013 February 2024 Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Unit 2, Alternative RR-09 Safety Injection System and Volume Control System Category C Check Valve Quarterly Testing ML24040A1712024-02-0909 February 2024 Interim Report of a Potential Deviation or Failure to Comply Associated with Bentley Systems Incorporated Autopipe Software IR 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, IR 07200010/20234012023-12-20020 December 2023 Independent Spent Fuel Storage Installation Security Inspection Report 07200010/2023401 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 ML23215A1672023-12-15015 December 2023 Acceptance of Requested Licensing Action Amendment Request to Revise Surveillance Requirement 3.8.1.2 Note 3 ML23349A0572023-12-15015 December 2023 and Independent Spent Fuel Storage Installation, Revision to Correspondence Service List for Northern States Power - Minnesota 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 ML23319A3182023-11-15015 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation 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 2024-08-05
[Table view] Category:License-Operator Examination Report
MONTHYEARML18333A3062018-11-29029 November 2018 NRC Initial License Examination Report 05000288/2018301 and 05000306/2018301 (Rdb) IR 05000288/20183012018-11-29029 November 2018 NRC Initial License Examination Report 05000288/2018301 and 05000306/2018301 (Rdb) IR 05000282/20163012016-07-26026 July 2016 NRC Initial License Examination Report 05000282/2016301; 05000306/2016301 L-PI-15-067, Operator Examination Updated Data2015-08-0404 August 2015 Operator Examination Updated Data IR 05000282/20123012012-06-15015 June 2012 Er 05000282-12-301(DRS), 05000306-12-301(DRS), on 5/14/2012 - 5/30/2012, Northern States Power Company, Minnesota, Prairie Island Nuclear Generating Plant, Initial License Examination Report IR 05000282/20103012010-04-30030 April 2010 Initial License Examination Report Er 05000282-10-301(DRS), 05000306-10-301(DRS), on 03/15/2010 - 03/25/2010, Northern States Power Company, Minnesota, Prairie Island Nuclear Generating Plant IR 05000282/20073012007-09-20020 September 2007 Er 05000282-07-301 (Drs); 05000306-07-301 (Drs); 07/30/07 - 08/06/07; Prairie Island Nuclear Generating Plant, Units 1 and 2; Initial License Examination Report IR 05000282/20043012004-05-11011 May 2004 Er 050000282/2004301(DRS); 05000306/2004301(DRS); 04/23/2004; Prairie Island Nuclear Generating Plan, Units 1 & 2; Initial License Examination Report IR 05000282/20033012003-10-29029 October 2003 Er 05000282-03-301(DRS) & 05000306-03-301(DRS), on 09/08/2003 Through 09/18/2003, for Prairie Island Nuclear Generating Plant, Units 1 and 2, Welch, Mn 2018-11-29
[Table view] |
Text
SUBJECT:
PRAIRIE ISLAND NUCLEAR POWER PLANT NRC INITIAL LICENSE EXAMINATION REPORT 005000282/2004301(DRS);
05000306/2004301(DRS)
Dear Mr. Solymossy:
On April 23, 2004, NRC examiners completed initial operator licensing examinations at your Prairie Island Nuclear Power Plant. The enclosed report presents the results of the examination.
Under the direction of NRC examiners, Prairie Island training department personnel administered an initial license re-take written examination on April 23, 2004. One Reactor Operator (RO) and six Senior Reactor Operator (SRO) applicants were administered the written examinations. The results of the written examinations were finalized on April 30, 2004. All applicants passed all sections of their respective examinations and were issued applicable operator licenses. The operating tests were waived for each of these applicants based on their operating performance during a previous initial examination and upon their successful completion of an accelerated remedial training program to address identified performance weaknesses.
In accordance with 10 CFR Part 2.390 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/
Roger D. Lanksbury, 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 005000282/2004301(DRS);
05000306/2004301(DRS)
2. Written Examinations and Answer Keys (RO & SRO)
REGION III==
Docket Nos: 50-282; 50-306 License Nos: DPR-42; DPR-60 Report No: 05000282/2004301(DRS); 05000306/2004301(DRS)
Licensee: Nuclear Management Company, LLC Facility: Prairie Island Nuclear Generating Plant, Units 1 and 2 Location: 1717 Wakonade Drive East Welch, MN 55089 Date: April 23, 2004 Examiners D. McNeil, Chief Examiner N. Valos, Examiner Approved by: Roger D. Lanksbury, Chief Operations Branch Enclosure 1
SUMMARY OF FINDINGS
ER 05000282/2004301(DRS), 05000306/2004301(DRS); 04/23/2004; Prairie Island Nuclear
Generating Plant, Units 1 & 2; Initial License Examination Report.
The announced operator licensing re-take initial written examination was conducted by Prairie Island Nuclear Generating Plant training personnel under the direction of regional NRC examiners in accordance with the guidance of NUREG-1021, Operator Licensing Examination Standards for Power Reactors, Revision 9, Draft.
Examination Summary:
- Seven applicants (one Reactor Operator (RO) and six Senior Reactor Operators (SROs)), passed all sections of their respective examinations and were issued applicable operator licenses. (Section 4OA5.1)
REPORT DETAILS
OTHER ACTIVITIES (OA)
4OA5 Other
.1 Initial Licensing Examinations
a. Examination Scope
The NRC reviewed a Prairie Island Nuclear Generating Plant developed re-take initial license written examination for Reactor Operators and Senior Reactor Operators. The facility's training staff used the guidance established in NUREG-1021, Operator Licensing Examination Standards for Power Reactors, Revision 9, Draft, to prepare the examination outline and to develop the written examination. Prairie Island Nuclear Generating Plant training staff members were directed to administer the written examination between April 23, 2004, and April 30, 2004. One Reactor Operator and six Senior Reactor Operator applicants were examined.
b. Findings
Written Examination The licensee developed the written examination. During their initial review, the NRC examiners determined that the examination, as submitted by the licensee, was within the range of acceptability expected for a proposed examination. During the week of March 15, 2004, examination changes agreed upon between the NRC and the licensee were incorporated according to the guidance contained in NUREG-1021.
Examination Results All applicants passed the written examination. The licensee had no post examination comments on the written examination.
.2 Examination Security
a. Examination Scope
The examiners reviewed the licensee's implementation of examination security requirements during the examination preparation and administration.
b. Findings
No findings were noted in this area. The licensee staff appeared to be enforcing correct examination security procedures.
4OA6 Meetings
.1 Exit Meeting
The chief examiner presented the examination teams preliminary observations and findings on April 29, 2004, to Mr. W. Markham of the Prairie Island Nuclear Generating Plant. Mr. Markham acknowledged the observations and findings presented.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
Enclosure 1
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee
- J. Lash, Station Training Manager
- T. Bacon, Initial License Training
- W. Markham, Initial License Training
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
WRITTEN EXAMINATIONS AND ANSWER KEYS (RO/SRO)
RO Retake Examination and Answer Key ADAMS Accession No. ML041280252
SRO Retake Examination and Answer Key ADAMS Accession No. ML041280275
2