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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 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