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Category:Letter
MONTHYEARIR 05000266/20240032024-11-0505 November 2024 Integrated Inspection Report 05000266/2024003 and 05000301/2024003 ML24295A1142024-10-31031 October 2024 Suppl Env Audit Summary Letter W/Enclosure 1 L-2024-176, Annual 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2024-10-30030 October 2024 Annual 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums L-2024-160, Core Operating Limits Report (COLR) Unit 2 Reload Cycle 41 (U2C41)2024-10-21021 October 2024 Core Operating Limits Report (COLR) Unit 2 Reload Cycle 41 (U2C41) ML24295A0862024-10-21021 October 2024 Notification of NRC Baseline Inspection and Request for Information Inspection Report 0500026/2025002 L-2024-169, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site- Specific Annexes2024-10-15015 October 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site- Specific Annexes L-2024-118, Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1)2024-10-0808 October 2024 Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1) L-2024-120, LAR 301 - Revise Renewed Facility Operating Licenses to Adopt an Alternative Approach for Addressing Seismic Risk in 10 CFR 50.69 Risk-Informed Categorization2024-10-0808 October 2024 LAR 301 - Revise Renewed Facility Operating Licenses to Adopt an Alternative Approach for Addressing Seismic Risk in 10 CFR 50.69 Risk-Informed Categorization L-2024-158, Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-25025 September 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes IR 05000266/20240112024-09-18018 September 2024 Biennial Problem Identification and Resolution Inspection Report 05000266/2024011 and 05000301/2024011 L-2024-136, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-16016 September 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-145, Notification of Deviation from EPRI MRP-227, Revision 1-A Baffle Bolt Inspection Frequency2024-09-0909 September 2024 Notification of Deviation from EPRI MRP-227, Revision 1-A Baffle Bolt Inspection Frequency ML24207A0202024-08-28028 August 2024 Response to Request for Re-Engagement Regarding the Subsequent License Renewal Environmental Review for Point Beach Nuclear Plant, Units 1 and 2 (Docket Numbers: 50-0266 and 50-0301) IR 05000266/20240052024-08-21021 August 2024 Updated Inspection Plan for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2024005 and 05000301/2024005) IR 05000266/20240022024-08-13013 August 2024 Integrated Inspection Report 05000266/2024002 and 05000301/2024002 L-2024-131, Response to Request for Additional Information Regarding License Amendment Request 300, Modify Containment Average Air Temperature Requirements2024-08-0909 August 2024 Response to Request for Additional Information Regarding License Amendment Request 300, Modify Containment Average Air Temperature Requirements ML24163A0012024-08-0505 August 2024 LTR-24-0119-1-1 Response to Nh Letter Regarding Review of NextEras Emergency Preparedness Amendment Review ML24214A3092024-08-0202 August 2024 Confirmation of Initial License Examination ML24194A1802024-07-24024 July 2024 – Revision to the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024 Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-113, License Amendment Request 294, Application to Revise Technical Specifications to Adopt TSTF- 577, Revised Frequencies for Steam Generator Tube Inspections2024-07-24024 July 2024 License Amendment Request 294, Application to Revise Technical Specifications to Adopt TSTF- 577, Revised Frequencies for Steam Generator Tube Inspections IR 05000266/20244012024-07-23023 July 2024 Public - Point Beach Nuclear Plant Cyber Security Inspection Report 05000266/2024401 and 05000301/2024401 ML24193A2432024-07-12012 July 2024 – Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan L-2024-116, Preparation and Scheduling of Operator Licensing Examinations2024-07-11011 July 2024 Preparation and Scheduling of Operator Licensing Examinations IR 05000266/20240102024-07-10010 July 2024 Age-Related Degradation Inspection Report 05000266/2024010 and 05000301/2024010 L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024 Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal L-2024-105, License Amendment Request 300, Modify Containment Average Air Temperature Requirements2024-06-26026 June 2024 License Amendment Request 300, Modify Containment Average Air Temperature Requirements L-2024-107, Schedule for Subsequent License Renewal Environmental Review2024-06-25025 June 2024 Schedule for Subsequent License Renewal Environmental Review ML24176A2242024-06-24024 June 2024 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update ML24149A2862024-06-12012 June 2024 NextEra Fleet - Proposed Alternative Frr 23-01 to Use ASME Code Case N-752-1, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section X1, Division 1 (EPID L-2023-LLR-0009) - Letter L-2024-093, Steam Generator Divider Plate Assemblies Bounding Analysis Evaluation for Aging Management Commitment 14 Revision2024-06-10010 June 2024 Steam Generator Divider Plate Assemblies Bounding Analysis Evaluation for Aging Management Commitment 14 Revision IR 05000266/20244202024-06-0505 June 2024 Security Baseline Inspection Report 05000266/2024420 and 05000301/2024420 ML24149A1922024-05-28028 May 2024 Notification of NRC Baseline Inspection and Request for Information ML24141A1382024-05-20020 May 2024 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection.Docx ML24127A0632024-05-0606 May 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes IR 05000266/20243012024-04-29029 April 2024 NRC Initial License Examination Report 05000266/2024301; 05000301/2024301 L-2024-067, Annual Monitoring Report2024-04-26026 April 2024 Annual Monitoring Report ML24116A0402024-04-23023 April 2024 Periodic Update of the Updated Final Safety Analysis Report ML24071A0912024-04-22022 April 2024 Issuance of Relief Request I6-RR-03 - Extension of the Unit 2 Steam Generator Primary Nozzle Dissimilar Metal Welds Sixth 10-Year Inservice Inspection Program Interval IR 05000266/20240012024-04-11011 April 2024 Integrated Inspection Report 05000266/2024001 and 05000301/2024001 L-2024-030, Supplement to Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements2024-03-27027 March 2024 Supplement to Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements L-2024-043, Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules2024-03-25025 March 2024 Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules L-2024-011, And Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2024-03-13013 March 2024 And Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications IR 05000266/20230062024-02-28028 February 2024 Annual Assessment Letter for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2023006 and 05000301/2023006) L-2024-020, Refueling Outage Owners Activity Report (OAR-1) Unit 1 for Inservice Inspections2024-02-22022 February 2024 Refueling Outage Owners Activity Report (OAR-1) Unit 1 for Inservice Inspections ML24053A3732024-02-22022 February 2024 Operator Licensing Examination Approval Point Beach, March 2024 ML24036A2652024-02-0505 February 2024 Notice of Inspection and Request for Information for the NRC Age-Related Degradation Inspection: Inspection Report 05000266/2024010 and 05000301/2024010 IR 05000266/20230042024-02-0101 February 2024 Integrated Inspection Report 05000266/2023004 and 05000301/2023004 ML24030A0352024-01-30030 January 2024 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 2024-09-09
[Table view] Category:License-Operator Examination Report
MONTHYEARIR 05000266/20243012024-04-29029 April 2024 NRC Initial License Examination Report 05000266/2024301; 05000301/2024301 IR 05000266/20213012021-09-14014 September 2021 NRC Initial License Examination Report 05000266/2021301; 05000301/2021301, and 07200005/2021301 IR 05000266/20193012019-09-17017 September 2019 NRC Initial License; Examination Report 05000266/2019301; 05000301/2019301 (DRS-R.Baker) IR 05000266/20153012015-04-0909 April 2015 Er 05000266/2015301; 05000301/2015301; 02/23/2015 - 03/06/2015; NextEra Energy Point Beach, LLC; Point Beach Nuclear Plant, Units 1 and 2; Initial License Examination Report IR 05000266/20113012011-06-13013 June 2011 Er 05000266-11-301(DRS), 05000301-11-301(DRS), on 04/25/2011 - 05/12/2011, Nextera Energy, Point Beach, LLC, Point Beach Nuclear Plant, Units 1 and 2, Initial License Examination Report ML0917406702009-06-21021 June 2009 Er 05000266-09-301 (Drs); 05000301-09-301 (DRS) on 05/11/09 - 05/26/09 for Point Beach, Units 1 and 2 IR 05000266/20023012002-03-0606 March 2002 Exam Reports 05000266/2002-301 & 050000301/2002-301, Nuclear Management Company, LLC, Point Beach Nuclear Plant, Units 1 & 2, Initial Operator Licensing Exams on 01/28-02/01/2002. Other Activities 2024-04-29
[Table view] |
Text
rch 6, 2002
SUBJECT:
POINT BEACH NUCLEAR PLANT NRC EXAMINATION REPORT 50-266/02-301(DRS); 50-301/02-301(DRS)
Dear Mr. Warner:
On February 1, 2002, the NRC completed initial operator licensing examinations at your Point Beach Nuclear Power Station. The enclosed report presents the results of the examination which were discussed on February 1, 2002, with Mr. M. Reddemann and other members of your staff.
Your training department personnel administered the written examination on February 2, 2002.
NRC examiners administered the operating examination during the period of January 28 through February 1, 2002. Two applicants were administered senior reactor operator license examinations, six applicants were administered reactor operator license examinations and three of your previously licensed operators were administered senior reactor operator upgrade examinations. The license applicants performance evaluations were finalized on February 19, 2002. All applicants passed all sections of their corresponding examinations and were issued their respective licenses. In accordance with 10 CFR 2.790 of the NRC's "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 System (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/NRC/ADAMS/index.html (the Public Electronic Reading Room).
Sincerely,
/RA/
David E. Hills, Chief Operations Branch Division of Reactor Safety Docket Nos. 50-266; 50-301 License Nos. DPR-24; DPR-27
Enclosures:
1. Operator Licensing Examination Report 50-266/02-301(DRS); 50-301/02-301(DRS)
2. Simulation Facility Report 3. Written Examination and Answer Key (RO)
4. Written Examination and Answer Key (SRO)
REGION III==
Docket Nos: 50-266; 50-301 License Nos: DPR-24; DPR-27 Report No: 50-266/02-301(DRS); 50-301/02-301(DRS)
Licensee: Nuclear Management Company, LLC Facility: Point Beach Nuclear Plant, Units 1 & 2 Location: 6610 Nuclear Road Two Rivers, WI 54241 Dates: January 28 through February 1, 2002 Inspectors: D. R. McNeil, Chief Examiner H. Peterson, Examiner R. M. Morris, Examiner Approved by: David E. Hills Chief Operations Branch Division of Reactor Safety
SUMMARY OF FINDINGS ER 05000266-02-301, ER 05000301-02-301, on 01/28-02/01/02, Nuclear Management Company, LLC, Point Beach Nuclear Plant, Units 1 and 2. Other Activities.
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:
Five applicants were administered senior reactor operator license examinations and six applicants were administered reactor operator license examinations. All eleven applicants passed all portions of their respective examinations and were awarded senior reactor operator and reactor operator licenses as appropriate (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 period of January 28 through February 1, 2002. The facility licensees training staff used the guidance prescribed in NUREG-1021, Operator Licensing Examination Standards for Power Reactors, Revision 8, Supplement 1, to prepare the outline and develop the written examination and operating test. The examiners administered the operating test, consisting of job performance measures and dynamic simulator scenarios, during the period of January 28 through February 1, 2002. The facility licensee administered the written examination on February 2, 2002. Five senior reactor operator applicants and six reactor operator applicants received written examinations and operating tests.
b. Findings Written Examination The NRC examiners determined that the written examination, as originally submitted by the licensee, was within the range of acceptability expected for a proposed examination.
All changes made to the submitted examination were made in accordance with NUREG-1021, "Operator Licensing Examination Standards for Power Reactors."
The NRC examiners independently graded the written examination and concluded that all eleven applicants achieved or surpassed the passing criteria of 80.0 percent. The licensee declined to submit post-examination comments.
Operating Test The NRC examiners determined that the operating test, as originally submitted by the licensee, was within the range of acceptability expected for a proposed examination.
All applicants demonstrated satisfactory performance in all three areas of the operating examination (administrative, control room and systems walkthrough, and integrated plant response).
.2 Examination Security a. Inspection Scope The examiners reviewed and observed the licensees implementation and controls of examination security during the examination preparation and administration.
b. Findings The NRC examiners determined that the licensees overall examination security practices associated with the development and administration of the operator license examinations were satisfactory.
4OA6 Management Meetings Exit Meeting Summary The chief examiner presented the examination teams preliminary observations and findings to Mr. Reddemann and other members of the licensee management on February 1, 2002. The licensee acknowledged the observations and findings presented, and did not identify any information as proprietary.
PARTIAL LIST OF PERSONS CONTACTED Licensee M. Reddemann, Site Vice President A. Cayia, Site Director T. Taylor, Plant Manager T. Webb, Site Licensing Director F. Flentje, Senior Regulatory Compliance Specialist C. Sizemore, Training Supervisor P. Smith, Operations Training Supervisor, LOR P. Smith, Senior Technical Instructor D. Schoon, Operations Manager P. Walker, Training Manager J. Fouse, Operations training Supervisor, ILT LIST OF ACRONYMS CFR Code of Federal Regulations DRS Division of Reactor Safety NCV Non-Cited Violation NRC Nuclear Regulatory Commission RHR Residual Heat Removal SDP Significance Determination Process SI Safety Injection
Enclosure 2 SIMULATION FACILITY REPORT Facility Licensee: Point Beach Nuclear Power Station Facility Licensee Docket Nos. 50-266; 50-301 Operating Tests Administered: January 28 - February 1, 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 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 1. Boron addition did During the administration of the 4th group using the second not affect reactivity scenario the boron model froze. The addition of boron had no effect on reactivity. The simulator was frozen and the candidates sequestered in another part of the room while the simulator was rebooted. The boron model worked correctly after the reboot and the scenario was continued without further problems.
Enclosure 3 WRITTEN EXAMINATION AND ANSWER KEY (RO)
ADAMS Accession # ML020730392
Enclosure 4 WRITTEN EXAMINATION AND ANSWER KEY (SRO)
ADAMS Accession # ML020730408