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| =Text= | | =Text= |
| {{#Wiki_filter:June 6, 2006Mr. Christopher M. CranePresident and Chief Nuclear Officer Exelon Nuclear Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555SUBJECT:BRAIDWOOD STATION, UNITS 1 AND 2NRC INITIAL LICENSE EXAMINATION REPORT 05000456/2006301(DRS);05000457/2006301(DRS) | | {{#Wiki_filter:une 6, 2006 |
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| | ==SUBJECT:== |
| | BRAIDWOOD STATION, UNITS 1 AND 2 NRC INITIAL LICENSE EXAMINATION REPORT 05000456/2006301(DRS); |
| | 05000457/2006301(DRS) |
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| ==Dear Mr. Crane:== | | ==Dear Mr. Crane:== |
| On May 19, 2006, Nuclear Regulatory Commission (NRC) examiners completed initial operatorlicensing examinations at your Braidwood Station. The enclosed report documents the resultsof the examination which were discussed on May 19, 2006, with K. Polson and other membersof your staff. A subsequent telephone conversation was conducted on May 22, 2006, between Mr. D. Stiles of your staff and Mr. D. McNeil, Senior Operations Engineer, to ensure there were no post examination comments on the written examination and to ensure there was noproprietary or sensitive information contained in the examination materials.The NRC examiners administered an initial license examination operating test during the weekof May 15, 2006. A written examination was administered by Braidwood Station training department personnel on May 19, 2006. Three Senior Reactor Operator applicants wereadministered license examinations. One of the Senior Reactor Operator applicants was apreviously licensed Reactor Operator at Braidwood Station. The results of the examinationswere finalized on May 25, 2006. All applicants passed all sections of their respective examinations and were issued applicable operator licenses.In accordance with 10 CFR Part 2.790 of the NRC's "Rules of Practice," a copy of this letter andits enclosures will be available electronically for public inspection in the NRC Public DocumentRoom or from the Publicly Available Records component of NRC's 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). | | On May 19, 2006, Nuclear Regulatory Commission (NRC) examiners completed initial operator licensing examinations at your Braidwood Station. The enclosed report documents the results of the examination which were discussed on May 19, 2006, with K. Polson and other members of your staff. A subsequent telephone conversation was conducted on May 22, 2006, between Mr. D. Stiles of your staff and Mr. D. McNeil, Senior Operations Engineer, to ensure there were no post examination comments on the written examination and to ensure there was no proprietary or sensitive information contained in the examination materials. |
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| | The NRC examiners administered an initial license examination operating test during the week of May 15, 2006. A written examination was administered by Braidwood Station training department personnel on May 19, 2006. Three Senior Reactor Operator applicants were administered license examinations. One of the Senior Reactor Operator applicants was a previously licensed Reactor Operator at Braidwood Station. The results of the examinations were finalized on May 25, 2006. All applicants passed all sections of their respective examinations and were issued applicable operator licenses. |
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| | In accordance with 10 CFR Part 2.790 of the NRC's "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 component of NRC's document system (ADAMS). |
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| C. Crane-2-We will gladly discuss any questions you have concerning this examination.
| | 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. |
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| Sincerely, | | Sincerely, |
| /RA/Hironori Peterson, ChiefOperations Branch Division of Reactor SafetyDocket Nos. 50-456; 50-457License Nos. NPF-72; NPF-77 | | /RA/ |
| | Hironori Peterson, Chief Operations Branch Division of Reactor Safety Docket Nos. 50-456; 50-457 License Nos. NPF-72; NPF-77 |
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| ===Enclosures:=== | | ===Enclosures:=== |
| 1.Operator Licensing Examination Report 05000456/2006301(DRS); 05000457/2006301(DRS) | | 1. Operator Licensing Examination Report 05000456/2006301(DRS); 05000457/2006301(DRS) |
| w/Attachment: Supplemental Information2.Simulation Facility Report3.Written Examinations and Answer Keys (SRO) | | w/Attachment: Supplemental Information 2. Simulation Facility Report 3. Written Examinations and Answer Keys (SRO) |
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| REGION IIIDocket Nos:50-456; 50-457License Nos:NPF-72; NPF-77Report No:05000456/2006301(DRS)/05000457/02006301(DRS) | | REGION III== |
| Licensee:Exelon Generation Company, LLC Facility:Braidwood Station, Units 1 and 2Location:Braceville, IL Dates:May 15 through May 19, 2006 Examiners:D. McNeil, Senior Operations EngineerR. Walton, Operations Engineer C. Zoia, Operations EngineerApproved by:Hironori Peterson, ChiefOperations Branch Division of Reactor Safety Enclosure 1 1 | | Docket Nos: 50-456; 50-457 License Nos: NPF-72; NPF-77 Report No: 05000456/2006301(DRS)/05000457/02006301(DRS) |
| | Licensee: Exelon Generation Company, LLC Facility: Braidwood Station, Units 1 and 2 Location: Braceville, IL Dates: May 15 through May 19, 2006 Examiners: D. McNeil, Senior Operations Engineer R. Walton, Operations Engineer C. Zoia, Operations Engineer Approved by: Hironori Peterson, Chief Operations Branch Division of Reactor Safety |
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| =SUMMARY OF FINDINGS= | | =SUMMARY OF FINDINGS= |
| ER 05000456/2006301(DRS), 05000457/2006301(DRS); 05/12/2006 - 05/19/2006;Exelon Generation Company, LLC, Braidwood Station. Initial License Examination Report.The announced operator licensing initial examination was conducted by regional NuclearRegulatory Commission examiners in accordance with the guidance of NUREG-1021,"Operator Licensing Examination Standards for Power Reactors," Revision 9.Examination Summary | | ER 05000456/2006301(DRS), 05000457/2006301(DRS); 05/12/2006 - 05/19/2006; |
| :*All applicants passed all sections of their respective examinations and were issuedapplicable operator licenses. (Section 4OA5.1).
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| | Exelon Generation Company, LLC, Braidwood Station. Initial License Examination Report. |
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| 2
| | The announced operator licensing initial examination was conducted by regional Nuclear Regulatory Commission examiners in accordance with the guidance of NUREG-1021, |
| | Operator Licensing Examination Standards for Power Reactors, Revision 9. |
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| | Examination Summary: |
| | * All applicants passed all sections of their respective examinations and were issued applicable operator licenses. (Section 4OA5.1). |
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| =REPORT DETAILS= | | =REPORT DETAILS= |
| 4.OTHER ACTIVITIES (OA)4OA5Other.1Initial Licensing Examinations
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| | ==OTHER ACTIVITIES (OA)== |
| | {{a|4OA5}} |
| | ==4OA5 Other== |
| | |
| | ===.1 Initial Licensing Examinations=== |
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| ====a. Examination Scope==== | | ====a. Examination Scope==== |
| Braidwood Station's training staff prepared the examination outline and developed thewritten examination and operating test. The Nuclear Regulatory Commission (NRC)examiners validated the proposed examination during the week of April 3, 2006, andconducted the operator licensing initial examination during the week of May 12, 2006. Braidwood Station training department staff members administered the written examination on May 19, 2006. In all cases, the training staff and the NRC examinersused the guidance established in NUREG-1021, "Operator Licensing ExaminationStandards for Power Reactors," Revision 9, to prepare, validate, revise, administer, and grade the examination. | | Braidwood Station's training staff prepared the examination outline and developed the written examination and operating test. The Nuclear Regulatory Commission (NRC)examiners validated the proposed examination during the week of April 3, 2006, and conducted the operator licensing initial examination during the week of May 12, 2006. |
| | |
| | Braidwood Station training department staff members administered the written examination on May 19, 2006. In all cases, the training staff and the NRC examiners used the guidance established in NUREG-1021, Operator Licensing Examination Standards for Power Reactors, Revision 9, to prepare, validate, revise, administer, and grade the examination. |
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| ====b. Findings==== | | ====b. Findings==== |
| Written ExaminationDuring the initial in-office review of the examination, the examiners determined that theexamination, as submitted by the licensee, was within the range of acceptabilityexpected for a proposed examination. During examination validation the week,examination changes agreed upon between the NRC and the licensee wereincorporated.The NRC examiners graded the written examination on May 22, 2006, and conducted areview of each missed question to determine the accuracy and validity of the examination questions. The licensee declined to submit post-examination comments for the written examination.Operating TestThe NRC examiners determined that the operating test, as originally submitted by thelicensee, was within the range of acceptability expected for a proposed operating test. Operating test changes made during the validation of the operating test were agreedupon between the NRC and the licensee.Examination ResultsAll applicants passed all sections of their respective examinations and were issuedapplicable operator licenses. | | Written Examination During the initial in-office review of the examination, the examiners determined that the examination, as submitted by the licensee, was within the range of acceptability expected for a proposed examination. During examination validation the week, examination changes agreed upon between the NRC and the licensee were incorporated. |
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| | The NRC examiners graded the written examination on May 22, 2006, and conducted a review of each missed question to determine the accuracy and validity of the examination questions. The licensee declined to submit post-examination comments for the written examination. |
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| | 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 operating test. |
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| 3.2Examination Security
| | Operating test changes made during the validation of the operating test were agreed upon between the NRC and the licensee. |
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| | Examination Results All applicants passed all sections of their respective examinations and were issued applicable operator licenses. |
| | |
| | ===.2 Examination Security=== |
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| ====a. Scope==== | | ====a. Scope==== |
| The NRC examiners reviewed and observed the licensee's implementation ofexamination security requirements during the examination preparation and administration. The examiners used the guidelines provided in NUREG 1021, "OperatorLicensing Examination Standards for Power Reactors" to determine acceptability of thelicensee's examination security activities. | | The NRC examiners reviewed and observed the licensee's implementation of examination security requirements during the examination preparation and administration. The examiners used the guidelines provided in NUREG 1021, "Operator Licensing Examination Standards for Power Reactors to determine acceptability of the licensees examination security activities. |
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| ====b. Findings==== | | ====b. Findings==== |
| During development of the examination one examination question was replaced. Clarifying material for the question was left on a liquid chalk surface in an uncontrolled classroom. Upon discovery, the NRC was immediately notified and the questionreplaced. During validation of the examination, a control room operator (UnitSupervisor) was shown some examination material. The Unit Supervisor was immediately placed on the station's examination security agreement and advised of the security requirements for the examination. Because the examination material was replaced and no applicants gained an unfair advantage as a result of the questions being uncontrolled, no violation of 10 CFR 55.49 occurred.4OA6MeetingsExit MeetingThe chief examiner presented the examination team's preliminary observations andfindings on May 19, 2006, to Mr. K. Polson and other members of the Braidwood StationOperations and Training Department staff. No proprietary or sensitive information was identified during the examination.ATTACHMENT: | | During development of the examination one examination question was replaced. |
| | |
| | Clarifying material for the question was left on a liquid chalk surface in an uncontrolled classroom. Upon discovery, the NRC was immediately notified and the question replaced. During validation of the examination, a control room operator (Unit Supervisor) was shown some examination material. The Unit Supervisor was immediately placed on the stations examination security agreement and advised of the security requirements for the examination. Because the examination material was replaced and no applicants gained an unfair advantage as a result of the questions being uncontrolled, no violation of 10 CFR 55.49 occurred. |
| | |
| | {{a|4OA6}} |
| | ==4OA6 Meetings== |
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| | Exit Meeting The chief examiner presented the examination team's preliminary observations and findings on May 19, 2006, to Mr. K. Polson and other members of the Braidwood Station Operations and Training Department staff. No proprietary or sensitive information was identified during the examination. |
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| | ATTACHMENT: |
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| =SUPPLEMENTAL INFORMATION= | | =SUPPLEMENTAL INFORMATION= |
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| ==KEY POINTS OF CONTACT== | | ==KEY POINTS OF CONTACT== |
| | |
| Licensee | | Licensee |
| : [[contact::K. Polson]], Site Vice President | | : [[contact::K. Polson]], Site Vice President |
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| NRC | | NRC |
| : [[contact::D. Smith]], P.E., DRS Branch 3 | | : [[contact::D. Smith]], P.E., DRS Branch 3 |
| | |
| ==ITEMS OPENED, CLOSED, AND DISCUSSED== | | ==ITEMS OPENED, CLOSED, AND DISCUSSED== |
| Opened, Closed, and | | |
| ===Discussed===
| | ===Opened, Closed, and Discussed=== |
| | |
| None | | None |
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| ==LIST OF DOCUMENTS REVIEWED== | | ==LIST OF DOCUMENTS REVIEWED== |
| None
| | |
| ==LIST OF ACRONYMS==
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| USEDADAMSAgency-Wide Document Access and Management SystemDRSDivision of Reactor Safety
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| NRCNuclear Regulatory Commission
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| SIMULATION FACILITY REPORTFacility Licensee:Braidwood StationFacility Docket No:50-456; 50-457Operating Tests Administered:May 12 - 18, 2006
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| The following documents observations made by the NRC examination team during the initialoperator license examination. These observations do not constitute audit or inspection
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| findings and are not, without further verification and review, indicative of non-compliance with
| |
| : [[CFR]] [[55.45(b). These observations do not affect]]
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| NRC certification or approval of thesimulation 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 wereobserved:ITEMDESCRIPTIONNoneEnclosure 2
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| : [[WRITTE]] [[N EXAMINATIONS]]
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| : [[AND]] [[]]
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| : [[ANSWER]] [[]]
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| : [[KEYS]] [[(]]
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| : [[RO]] [[/SRO)SRO Initial Examination]]
| |
| : [[ADAMS]] [[Accession #]]
| |
| : [[ML]] [[061510494Enclosure 3]]
| |
| }} | | }} |
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Category:Letter
MONTHYEARRS-24-098, Units 1 and 2 - Supplement to License Amendment Request to Revise Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel Assembly Storage, 4.3.1, Fuel Storage, Criticality2024-10-23023 October 2024 Units 1 and 2 - Supplement to License Amendment Request to Revise Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel Assembly Storage, 4.3.1, Fuel Storage, Criticality ML24291A0012024-10-17017 October 2024 Submittal of Core Operating Limits Report, Cycle 25 RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests RS-24-095, Relief Request I4R-19 and I4R-26, Associated with the Fourth and Fifth Inservice Inspection Intervals2024-10-10010 October 2024 Relief Request I4R-19 and I4R-26, Associated with the Fourth and Fifth Inservice Inspection Intervals ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing ML24263A1272024-09-23023 September 2024 – Request for Additional Information (EPID 2023-LLA-0136) - Non-Proprietary IR 05000456/20240112024-09-12012 September 2024 Biennial Problem Identification and Resolution Inspection Report 05000456/2024011 and 05000457/2024011 ML24164A0032024-09-10010 September 2024 Issuance of Amendment Nos. 235 and 235 Revision of Technical Specifications for the Ultimate Heat Sink ML24227A0522024-08-29029 August 2024 Audit Plan for LAR to Remove ATWS Mtc Limit IR 05000456/20240052024-08-29029 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2024005 and 05000457/2024005) ML24225A1112024-08-13013 August 2024 Notification of NRC Fire Protection Team Inspection Request for Information ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000456/20240022024-08-0808 August 2024 Integrated Inspection Report 05000456/2024002 and 05000457/2024002 ML24172A1252024-07-26026 July 2024 Environmental Assessment and Finding of No Significant Impact Related to a Requested Increase in Ultimate Heat Sink Temperature (EPID L-2024-LLA-0075) - Transmittal Letter ML24179A3262024-07-23023 July 2024 LTR - Constellation - SG Welds and Nozzles (L-2023-LLR-0053, L-2023-LLR-0054, L-2023-LLR-0055, L-2023-LLR-0056) ML24163A3922024-06-25025 June 2024 Individual Notice of Consideration of Issuance of Amendments to Renewed Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, & Opportunity for a Hearing (EPID L-2024-LLA-0075)- Letter RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24164A2132024-06-13013 June 2024 Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Braidwood Nuclear Plant RS-24-057, License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink2024-06-0404 June 2024 License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink IR 05000456/20240102024-05-31031 May 2024 License Renewal Phase 1 Report 05000456/2024010 RS-24-044, License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed2024-05-28028 May 2024 License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed RS-24-043, Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications2024-05-24024 May 2024 Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 ML24142A3352024-05-21021 May 2024 Quad Cities—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report ML24136A2452024-05-15015 May 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000457/2024004 ML24136A0132024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report ML24128A1212024-05-0707 May 2024 Response to Braidwood and Dresden FOF Dates Change Request (2025) ML24122A6522024-05-0101 May 2024 Submittal of 2023 Annual Radioactive Effluent Release Report RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests IR 05000456/20243012024-04-29029 April 2024 NRC Initial License Examination Report 05000456/2024301; 05000457/2024301 RS-24-026, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 5.6.5, Core Operating Limits Report (COLR)2024-04-25025 April 2024 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 5.6.5, Core Operating Limits Report (COLR) ML24116A0052024-04-25025 April 2024 Transmittal of Braidwood Station, Unit 1, Core Operating Limits Report, Braidwood Unit 1 Cycle 25 IR 05000456/20240012024-04-24024 April 2024 Integrated Inspection Report 05000456/2024001 and 05000457/2024001 ML24113A1272024-04-22022 April 2024 Audit Plan in Support of Review of LAR Revision of TS 3.7.15, 3.7.16, and 4.3.1 (EPID: L-2023-LLA-0136) (Non-Proprietary) IR 05000457/20240902024-04-19019 April 2024 Final Significance Determination for 2b Auxiliary Feedwater Pump Diesel Engine Fuel Oil Dilution Issue - NRC Inspection Report 05000457/2024090 ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition RS-24-034, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2024-04-10010 April 2024 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML24094A2692024-04-0303 April 2024 Notification of Deviation from Pressurized Water Reactor Owners Group (PWROG) Report, WCAP-17451-P, Revision 2, Reactor Internals Guide Tube Wear Westinghouse Domestic Fleet Operational Projections RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24057A0372024-03-26026 March 2024 Proposed Alternative from Certain Requirements Contained in the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI RS-24-024, Response to Request for Additional Information Regarding Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2024-03-22022 March 2024 Response to Request for Additional Information Regarding Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds ML24067A3252024-03-0707 March 2024 U.S. Department of Energy, Office of Legacy Management, 2023 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites ML24066A0122024-03-0606 March 2024 Operator Licensing Examination Approval Braidwood Station, Units 1 and 2, March 2024 IR 05000456/20244012024-03-0505 March 2024 Cyber Security Inspection Report 05000456/2024401 and 05000457/2024401 (Public) IR 05000456/20230062024-02-28028 February 2024 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2023006 and 05000457/2023006) ML24057A3022024-02-26026 February 2024 Regulatory Conference Supplemental Information ML24047A2382024-02-20020 February 2024 Regulatory Conference to Discuss Risk Associated with 2b Auxiliary Feedwater Pump Diesel Engine Fuel Oil Leak RS-24-013, Response to Request for Additional Information Regarding Proposed Alternative to Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators2024-02-13013 February 2024 Response to Request for Additional Information Regarding Proposed Alternative to Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators IR 05000456/20230042024-02-0202 February 2024 Integrated Inspection Report 05000456/2023004 and 05000457/2023004 2024-09-23
[Table view] Category:License-Operator Examination Report (Non-Power Reactors Only)
MONTHYEARIR 05000456/20063012006-06-0606 June 2006 Er 05000456-06-301 (Drs), 05000457-06-301 (Drs); 05/12/2006 - 05/19/2006; Exelon Generation Company, LLC, Braidwood Station, Initial License Examination Report 2006-06-06
[Table view] |
Text
une 6, 2006
SUBJECT:
BRAIDWOOD STATION, UNITS 1 AND 2 NRC INITIAL LICENSE EXAMINATION REPORT 05000456/2006301(DRS);
05000457/2006301(DRS)
Dear Mr. Crane:
On May 19, 2006, Nuclear Regulatory Commission (NRC) examiners completed initial operator licensing examinations at your Braidwood Station. The enclosed report documents the results of the examination which were discussed on May 19, 2006, with K. Polson and other members of your staff. A subsequent telephone conversation was conducted on May 22, 2006, between Mr. D. Stiles of your staff and Mr. D. McNeil, Senior Operations Engineer, to ensure there were no post examination comments on the written examination and to ensure there was no proprietary or sensitive information contained in the examination materials.
The NRC examiners administered an initial license examination operating test during the week of May 15, 2006. A written examination was administered by Braidwood Station training department personnel on May 19, 2006. Three Senior Reactor Operator applicants were administered license examinations. One of the Senior Reactor Operator applicants was a previously licensed Reactor Operator at Braidwood Station. The results of the examinations were finalized on May 25, 2006. All applicants passed all sections of their respective examinations and were issued applicable operator licenses.
In accordance with 10 CFR Part 2.790 of the NRC's "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 component of NRC's 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/
Hironori Peterson, Chief Operations Branch Division of Reactor Safety Docket Nos. 50-456; 50-457 License Nos. NPF-72; NPF-77
Enclosures:
1. Operator Licensing Examination Report 05000456/2006301(DRS); 05000457/2006301(DRS)
w/Attachment: Supplemental Information 2. Simulation Facility Report 3. Written Examinations and Answer Keys (SRO)
REGION III==
Docket Nos: 50-456; 50-457 License Nos: NPF-72; NPF-77 Report No: 05000456/2006301(DRS)/05000457/02006301(DRS)
Licensee: Exelon Generation Company, LLC Facility: Braidwood Station, Units 1 and 2 Location: Braceville, IL Dates: May 15 through May 19, 2006 Examiners: D. McNeil, Senior Operations Engineer R. Walton, Operations Engineer C. Zoia, Operations Engineer Approved by: Hironori Peterson, Chief Operations Branch Division of Reactor Safety
SUMMARY OF FINDINGS
ER 05000456/2006301(DRS), 05000457/2006301(DRS); 05/12/2006 - 05/19/2006;
Exelon Generation Company, LLC, Braidwood Station. Initial License Examination Report.
The announced operator licensing initial examination was conducted by regional Nuclear Regulatory Commission examiners in accordance with the guidance of NUREG-1021,
Operator Licensing Examination Standards for Power Reactors, Revision 9.
Examination Summary:
- All applicants 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
Braidwood Station's training staff prepared the examination outline and developed the written examination and operating test. The Nuclear Regulatory Commission (NRC)examiners validated the proposed examination during the week of April 3, 2006, and conducted the operator licensing initial examination during the week of May 12, 2006.
Braidwood Station training department staff members administered the written examination on May 19, 2006. In all cases, the training staff and the NRC examiners used the guidance established in NUREG-1021, Operator Licensing Examination Standards for Power Reactors, Revision 9, to prepare, validate, revise, administer, and grade the examination.
b. Findings
Written Examination During the initial in-office review of the examination, the examiners determined that the examination, as submitted by the licensee, was within the range of acceptability expected for a proposed examination. During examination validation the week, examination changes agreed upon between the NRC and the licensee were incorporated.
The NRC examiners graded the written examination on May 22, 2006, and conducted a review of each missed question to determine the accuracy and validity of the examination questions. The licensee declined to submit post-examination comments for the written examination.
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 operating test.
Operating test changes made during the validation of the operating test were agreed upon between the NRC and the licensee.
Examination Results All applicants passed all sections of their respective examinations and were issued applicable operator licenses.
.2 Examination Security
a. Scope
The NRC examiners reviewed and observed the licensee's implementation of examination security requirements during the examination preparation and administration. The examiners used the guidelines provided in NUREG 1021, "Operator Licensing Examination Standards for Power Reactors to determine acceptability of the licensees examination security activities.
b. Findings
During development of the examination one examination question was replaced.
Clarifying material for the question was left on a liquid chalk surface in an uncontrolled classroom. Upon discovery, the NRC was immediately notified and the question replaced. During validation of the examination, a control room operator (Unit Supervisor) was shown some examination material. The Unit Supervisor was immediately placed on the stations examination security agreement and advised of the security requirements for the examination. Because the examination material was replaced and no applicants gained an unfair advantage as a result of the questions being uncontrolled, no violation of 10 CFR 55.49 occurred.
4OA6 Meetings
Exit Meeting The chief examiner presented the examination team's preliminary observations and findings on May 19, 2006, to Mr. K. Polson and other members of the Braidwood Station Operations and Training Department staff. No proprietary or sensitive information was identified during the examination.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee
- K. Polson, Site Vice President
- C. Boerschig, Plant Manger
- S. Butler, Operations Training Manager
- C. Dunn, Training Director
- R. Cameron, ILT Lead Instructor
- D. Stiles, Examination Author
- S. Deprest, OTPS
- T. McCool, Exelon Corporate Training Director
- M. Cichon, Regulatory Assurance
- P. Summers, Nuclear Oversight
NRC
- D. Smith, P.E., DRS Branch 3
ITEMS OPENED, CLOSED, AND DISCUSSED
Opened, Closed, and Discussed
None
LIST OF DOCUMENTS REVIEWED