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| | author name = Peterson H | | | author name = Peterson H |
| | author affiliation = NRC/RGN-III/DRS/OLB | | | author affiliation = NRC/RGN-III/DRS/OLB |
| | addressee name = Crane C M | | | addressee name = Crane C |
| | addressee affiliation = Exelon Generation Co, LLC, Exelon Nuclear | | | addressee affiliation = Exelon Generation Co, LLC, Exelon Nuclear |
| | docket = 05000456, 05000457 | | | docket = 05000456, 05000457 |
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| =Text= | | =Text= |
| {{#Wiki_filter: | | {{#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) |
| [[Issue date::June 6, 2006]]
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| Mr. Christopher M. CranePresident and Chief Nuclear Officer Exelon Nuclear Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
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| SUBJECT: BRAIDWOOD STATION, UNITS 1 AND 2NRC INITIAL LICENSE EXAMINATION REPORT 05000456/2006301(DRS);05000457/2006301(DRS)
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| ==Dear Mr. Crane:== | | ==Dear Mr. Crane:== |
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| C. Crane-2-We will gladly discuss any questions you have concerning this examination. | | C. Crane-2-We will gladly discuss any questions you have concerning this examination. |
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| Sincerely,/RA/Hironori Peterson, ChiefOperations Branch Division of Reactor SafetyDocket Nos. 50-456; 50-457License Nos. NPF-72; NPF-77 | | Sincerely, |
| | | /RA/Hironori Peterson, ChiefOperations Branch Division of Reactor SafetyDocket Nos. 50-456; 50-457License Nos. NPF-72; NPF-77 |
| ===Enclosures:===
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| 1.Operator Licensing Examination Report 05000456/2006301(DRS); 05000457/2006301(DRS)
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| ===w/Attachment:===
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| Supplemental Information2.Simulation Facility Report3.Written Examinations and Answer Keys (SRO)cc w/encl 1 & 2:Site Vice President - Braidwood StationPlant Manager - Braidwood Station Regulatory Assurance Manager - Braidwood Station Chief Operating Officer Senior Vice President - Nuclear Services Vice President - Operations Support Vice President - Licensing and Regulatory Affairs Director Licensing Manager Licensing - Braidwood and Byron Senior Counsel, Nuclear, Mid-West Regional Operating Group Document Control Desk - Licensing Assistant Attorney General Illinois Emergency Management Agency State Liaison Officer Chairman, Illinois Commerce Commissioncc w/encl 1, 2, & 3:C. Dunn, Training Manager, Braidwood Station C. Crane-2-We will gladly discuss any questions you have concerning this examination.
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| Sincerely,/RA/Hironori Peterson, ChiefOperations Branch Division of Reactor SafetyDocket Nos. 50-456; 50-457License 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) |
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| ===w/Attachment:===
| | REGION IIIDocket Nos:50-456; 50-457License Nos:NPF-72; NPF-77Report No:05000456/2006301(DRS)/05000457/02006301(DRS) |
| Supplemental Information2.Simulation Facility Report3.Written Examinations and Answer Keys (SRO)cc w/encl 1 & 2:Site Vice President - Braidwood StationPlant Manager - Braidwood Station Regulatory Assurance Manager - Braidwood Station Chief Operating Officer Senior Vice President - Nuclear Services Vice President - Operations Support Vice President - Licensing and Regulatory Affairs Director Licensing Manager Licensing - Braidwood and Byron Senior Counsel, Nuclear, Mid-West Regional Operating Group Document Control Desk - Licensing Assistant Attorney General Illinois Emergency Management Agency State Liaison Officer Chairman, Illinois Commerce Commissioncc w/encl 1, 2, & 3:C. Dunn, Training Manager, Braidwood StationDOCUMENT NAME: E:\Filenet\ML061590442.wpd G Publicly Available G Non-Publicly Available G Sensitive G Non-SensitiveTo receive a copy of this document, indicate in the concurrence box "C" = Copy without attach/encl "E" = Copy with attach/encl "N" = No copyOFFICERIIIRIIIRIII NAMEDMcNeil:coRSkokowskiHPetersonDATE06/01/0606/01/0606/06/06OFFICIAL RECORD COPY C. Crane-3-ADAMS Distribution
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| :DXC1 JBH1 RidsNrrDirsIrib
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| GEG KGO SPR CAA1 LSL (electronic IR's only)
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| C. Pederson, DRS (hard copy - IR's only)
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| DRPIII DRSIII PLB1 JRK1ROPreports@nrc.govMAB1SMS U. S. NUCLEAR REGULATORY COMMISSIONREGION IIIDocket Nos:50-456; 50-457License Nos:NPF-72; NPF-77Report No:05000456/2006301(DRS)/05000457/02006301(DRS)
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| 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 | | 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 |
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Category:Letter
MONTHYEARIR 05000456/20230042024-02-0202 February 2024 Integrated Inspection Report 05000456/2023004 and 05000457/2023004 ML24025C7242024-01-29029 January 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000456/2024002; 05000457/2024002 IR 05000457/20230112024-01-25025 January 2024 2B Auxiliary Feedwater Pump Diesel Fuel Oil Dilution Report 05000457/2023011 and Preliminary Greater than Green Finding and Apparent Violation ML24018A0362024-01-17017 January 2024 Paragon Energy Solutions, Defect with Detroit Diesel/Mtu Fuel Injectors P/N R5229660 Cat Id 0001390618 RS-24-004, Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators2024-01-11011 January 2024 Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators ML23348A2162023-12-15015 December 2023 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0030 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000456/20200232023-12-15015 December 2023 Baseline Security Inspection Document; 05000456/2023/402; 05000457/2023/402 ML23277A0032023-12-11011 December 2023 Issuance of Amendments Regarding Adoption of TSTF-370 ML23339A0452023-12-0505 December 2023 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000546/2024010 ML23313A1552023-12-0101 December 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report ML23331A8922023-11-22022 November 2023 Supplement - Braidwood Security Rule Exemption Request ISFSI Docket No. Reference 05000457/LER-2023-001, Submittal of LER 2023-001-00 for Braidwood Station, Unit 2, Train B Auxiliary Feedwater Pump Was Inoperable Due to Degraded Oil in the Crank Case2023-11-17017 November 2023 Submittal of LER 2023-001-00 for Braidwood Station, Unit 2, Train B Auxiliary Feedwater Pump Was Inoperable Due to Degraded Oil in the Crank Case ML23321A0442023-11-17017 November 2023 Notification of Deviation from Electric Power Research Institute (EPRI) Topical Report MRP-227, Revision 1-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guideline RS-23-118, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums RS-23-114, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2023-11-0101 November 2023 Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds IR 05000456/20234012023-10-18018 October 2023 Security Baseline Inspection Report 05000456/2023401 and 05000457/2023401 IR 05000456/20230102023-10-18018 October 2023 Functional Engineering Inspection Commercial Grade Dedication Report 05000456/2023010 and 05000457/2023010 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023 Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023 Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections RS-23-093, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel.2023-09-29029 September 2023 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel. ML23226A0062023-09-19019 September 2023 Review of License Renewal Commitment Number 10 Submittal ML23180A1692023-09-11011 September 2023 Calvert Cliff Units 1 & 2, and R.E. Ginna Plant - Withdrawal of Proposed Alternatives to American Society of Mechanical Engineers (ASME) Requirements (Epids L-2022-LRR-0074, 0076, 0079, 0091, 0092, 0093 and 0094) IR 05000456/20230052023-08-30030 August 2023 Updated Inspection Plan for Braidwood Station Report 05000456/2023005 and 05000457/2023005 ML23234A2462023-08-25025 August 2023 Confirmation of Initial License Examination IR 05000456/20230022023-08-0303 August 2023 Integrated Inspection Report 05000456/2023002 and 05000457/2023002 ML23188A1292023-07-26026 July 2023 Issuance of Amendment Nos. 233 and 233 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 ML23087A0762023-07-13013 July 2023 Issuance of Amendment Nos. 232 and 232 Revision of Technical Specifications for the Ultimate Heat Sink ML23191A8442023-07-10010 July 2023 05000456; 05000457 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information 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 RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023 Withdrawal - Proposed Alternatives Related to the Steam Generators RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23110A1152023-06-12012 June 2023 Environmental Assessment and Finding of No Significant Impact Related to a Requested Increase in Ultimate Heat Sink Temperature (EPID L-2023-LLA-0042) (Letter) RS-23-074, Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-06-0909 June 2023 Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-23-075, Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process2023-06-0707 June 2023 Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process RS-23-050, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube.2023-05-22022 May 2023 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube. ML23138A1342023-05-18018 May 2023 Information Meeting with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Braidwood Station and Byron Station ML23132A0472023-05-12012 May 2023 Submittal of 2022 Annual Radiological Environmental Operating Report ML23130A0072023-05-10010 May 2023 Submittal of Core Operating Limits Report Cycle 24, Rev. 16 IR 05000456/20230012023-05-0808 May 2023 Integrated Inspection Report 05000456/2023001 and 05000457/2023001 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML23118A0202023-04-28028 April 2023 Submittal of 2022 Annual Radioactive Effluent Release Report ML23110A3202023-04-21021 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection RS-23-056, Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 102023-04-20020 April 2023 Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 10 RS-23-055, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2023-04-10010 April 2023 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML23095A1292023-04-0505 April 2023 Steam Generator Tube Inspection Report for Refueling Outage 23 ML23094A1352023-04-0404 April 2023 Request for Information for Nrc Commercial Grade Dedication Inspection Inspection Report 05000456/2023010 05000457/2023010 RS-23-052, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-03-24024 March 2023 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations 2024-02-02
[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
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)
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).
C. Crane-2-We will gladly discuss any questions you have concerning this examination.
Sincerely,
/RA/Hironori Peterson, ChiefOperations Branch Division of Reactor SafetyDocket Nos. 50-456; 50-457License Nos. NPF-72; NPF-77
Enclosures:
1.Operator Licensing Examination Report 05000456/2006301(DRS); 05000457/2006301(DRS)
w/Attachment: Supplemental Information2.Simulation Facility Report3.Written Examinations and Answer Keys (SRO)
REGION IIIDocket Nos:50-456; 50-457License Nos:NPF-72; NPF-77Report No:05000456/2006301(DRS)/05000457/02006301(DRS)
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
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
- All applicants passed all sections of their respective examinations and were issuedapplicable operator licenses. (Section 4OA5.1).
2
REPORT DETAILS
4.OTHER ACTIVITIES (OA)4OA5Other.1Initial Licensing Examinations
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.
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.
3.2Examination Security
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.
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:
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
None
USEDADAMSAgency-Wide Document Access and Management SystemDRSDivision of Reactor Safety
NRCNuclear Regulatory Commission
SIMULATION FACILITY REPORTFacility Licensee:Braidwood StationFacility Docket No:50-456; 50-457Operating Tests Administered:May 12 - 18, 2006
The following documents observations made by the NRC examination team during the initialoperator license examination. These observations do not constitute audit or inspection
findings and are not, without further verification and review, indicative of non-compliance with
- CFR 55.45(b). These observations do not affect
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
- WRITTE N EXAMINATIONS
- AND [[]]
- ANSWER [[]]
- KEYS (
- RO /SRO)SRO Initial Examination
- ADAMS Accession #
- ML 061510494Enclosure 3