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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-24-095, 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 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 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 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) ML24227A0522024-08-29029 August 2024 Audit Plan for LAR to Remove ATWS Mtc Limit 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 ML24136A0132024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report ML24136A2452024-05-15015 May 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000457/2024004 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
MONTHYEARIR 05000456/20243012024-04-29029 April 2024 NRC Initial License Examination Report 05000456/2024301; 05000457/2024301 IR 05000456/20223012022-04-0606 April 2022 NRC Initial License Examination Report 05000456/2022301 and 05000457/2022301 IR 05000456/20203012020-08-27027 August 2020 NRC Initial License Examination Report 05000456/2020301 and 05000457/2020301 IR 05000456/20193012019-08-12012 August 2019 NRC Initial License Examination Report 05000456/2019301 and 05000457/2019301 IR 05000456/20183012018-07-19019 July 2018 NRC Initial License Examination Report 05000456/2018301; 05000457/2018301 (Rdb) IR 05000456/20163012016-10-17017 October 2016 NRC Initial License Examination Report 05000456/2016301; 05000457/2016301 (Rkw) IR 05000456/20143012015-01-16016 January 2015 Er 05000456/2014301; 05000457/2014301; on 11/12/2014 - 12/03/2014; Exelon Generation Company, LLC; Braidwood Station, Units 1 and 2; Initial License Examination Report RS-14-164, (EGC) Response to NRC Regulatory Issue Summary 2014-05, Preparation and Scheduling of Operator Licensing Examinations2014-05-29029 May 2014 (EGC) Response to NRC Regulatory Issue Summary 2014-05, Preparation and Scheduling of Operator Licensing Examinations IR 05000456/20113012011-08-10010 August 2011 Er 05000456-11-301(DRS), 05000457-11-301(DRS), on 06/20/2011-06/30/2011, Exelon Generation Company, LLC, Braidwood Station, Units 1 and 2, Initial License Examination Report ML1104604992011-02-14014 February 2011 Ltr. 02/14/2011 Braidwood Re Confirmation of Initial License Examination IR 05000456/20093012009-11-25025 November 2009 Er 05000456-09-301(DRS), 05000457-09-301(DRS); 10/05/09 - 10/29/09; Exelon Generation Company, LLC; Braidwood Station, Unit 1 and 2; Initial License Examination Report IR 05000045/20073012007-12-20020 December 2007 Er 05000456-07-301; 0500045-07-301; 12/03/07 - 12/10/07; Braidwood Station, Units 1 and 2; Initial License Examination Report IR 05000456/20023012002-07-25025 July 2002 Er 05000456-02-301, Er 05000457-02-301, on 07/8-18/2002, Exelon Generation Co., LLC, Braidwood Station, Units 1 & 2. Initial License Examination Report. Six RO & Five SRO Applicants Passed Written Exam & Operating Tests 2024-04-29
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Text
UNITED STATES ary 16, 2015
SUBJECT:
BRAIDWOOD STATION, UNITS 1 AND 2 NRC INITIAL LICENSE EXAMINATION REPORT 05000456/2014301; 05000457/2014301
Dear Mr. Pacilio:
On December 3, 2014, the U.S. Nuclear Regulatory Commission (NRC) completed the initial operator licensing examination process for license applicants employed your Braidwood Station, Units 1 and 2. The enclosed report documents the results of those examinations. Preliminary observations noted during the examination process were discussed on November 21, 2014, with Mr. D. Stiles, and other members of your staff. An exit meeting was conducted by telephone on December 12, 2014, between Mr. D. Styles, Braidwood Station Training Director, and Mr. R. Michael Morris, Senior Operations Engineer, to review the proposed final grading of the written examination for the licensed applicants. During the telephone conversation, NRC resolutions of the stations post-examination comments, initially received by the NRC on December 3, 2014, were discussed.
The NRC examiners administered an initial license examination operating test during the weeks of November 10 and November 17, 2014. The written examination was administered by Braidwood Station training department personnel on November 24, 2014. Six Senior Reactor Operator (SRO) and six Reactor Operator (RO) applicants were administered license examinations. The results of the examinations were finalized on December 17, 2014. One RO applicant failed the written examination and was issued a proposed license denial letter.
Eleven applicants passed all sections of their respective examinations and ten were issued applicable operator licenses. In accordance with NRC policy, the license for the one remaining applicant is being withheld pending the outcome of any written examination appeal that may be initiated.
The proposed written examination and the administered written examination will be withheld from public disclosure for 24 months per your request. However, the applicant that received a proposed license denial letter because of a written examination grade that was less than 80 percent, will be provided a copy of the administered written examination. For examination security purposes, your staff should consider the written examination uncontrolled and exposed to the public. In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding, of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRCs Public Document Room or from the Publicly Available Records (PARS)
component of the NRC's Agencywide Documents Access and Management System (ADAMS).
ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Hironori Peterson, Chief Operations Branch Division of Reactor Safety Docket Nos. 50-456; 50-457 License Nos. NPF-72; NPF-77
Enclosure:
Operator Licensing Examination Report (ER)
05000456/2014301; 05000457/2014301 w/Attachments:
1. Supplemental Information 2. Simulation Facility Report 3. Post-Examination Comments and Resolutions
REGION III==
Docket Nos: 50-456; 50-457 License Nos: NPF-72; NPF-77 Report No: 05000456/2014301; 05000457/2014301 Licensee: Exelon Generation Company, LLC Facility: Braidwood Station, Units 1 and 2 Location: Braceville, IL Dates: November 12, 2014 - December 3, 2014 Inspectors: R. M. Morris, Senior Operations Engineer D. Reeser, Operations Engineer N. Valos, Senior Reactor Analyst Approved by: H. Peterson, Chief Operations Branch Division of Reactor Safety Enclosure
SUMMARY OF FINDINGS
ER 05000456/2014301; 05000457/2014301; 11/12/2014 - 12/03/2014; Exelon Generation
Company, LLC; Braidwood Station, Units 1 and 2; Initial License Examination Report.
The announced initial operator licensing examination was conducted by regional U.S. Nuclear Regulatory Commission examiners in accordance with the guidance of NUREG-1021,
Operator Licensing Examination Standards for Power Reactors, Revision 9-Supplement 1.
Examination Summary Eleven of twelve applicants passed all sections of their respective examinations. Six applicants were issued Senior Operator licenses and four applicants were issued Operator licenses.
One applicant failed the written examination and was issued a proposed license denial. The license for the remaining applicant is being held and may be issued pending the outcome of any written examination appeal. (Section 4OA5.1).
REPORT DETAILS
4OA5 Other Activities
.1 Initial Licensing Examinations
a. Examination Scope
The U.S. Nuclear Regulatory Commission (NRC) examiners and members of the facility licensees staff used the guidance prescribed in NUREG-1021, Operator Licensing Examination Standards for Power Reactors, Revision 9-Supplement 1, to develop, validate, administer, and grade the written examination and operating test. Members of the facility licensees staff prepared the outline and developed the written examination and operating test. The NRC examiners validated the proposed examination during the week of October 20, 2014, with the assistance of members of the facility licensees staff.
During the on-site validation week, the examiners audited four license applications for accuracy. The NRC examiners, with the assistance of members of the facility licensees staff, administered the operating test, consisting of job performance measures and dynamic simulator scenarios, during the period of November 12 through November 21, 2014. The facility licensee administered the written examination on November 24, 2014.
b. Findings
- (1) Written Examination The NRC examiners determined that the written examination, as proposed by the licensee, was within the range of acceptability expected for a proposed examination.
Less than 20 percent of the proposed examination questions were determined to be unsatisfactory and required modification or replacement.
All changes made to the proposed written examination, were made in accordance with NUREG-1021, "Operator Licensing Examination Standards for Power Reactors, and documented on Form ES-401-9, Written Examination Review Worksheet, which will be available electronically in the NRC Public Document Room or from the Publicly Available Records component of NRC's Agencywide Documents Access and Management System (ADAMS).
On December 3, 2014, the licensee submitted documentation noting that there were four post-examination comments for consideration by the NRC examiners when grading the written examination. The post-examination comments and the NRC resolution for the post-examination comments are included as Attachment 2 to this report. The proposed written examination, as well as the final as-administered examination and answer key (ADAMS Accession Number ML14363A062), will be available in 24 months electronically in the NRCs Public Document Room or from the Publicly Available Records component of NRC's ADAMS.
The NRC examiners graded the written examination on December 15, 2014, and conducted a review of each missed question to determine the accuracy and validity of the examination questions.
- (2) Operating Test The NRC examiners determined that the operating test, as originally proposed by the licensee, was within the range of acceptability expected for a proposed examination.
Changes made to the operating test, documented in a document titled, Operating Test Comments, as well as the final as-administered dynamic simulator scenarios and Job Performance Measures, are available electronically in the NRC Public Document Room or from the Publicly Available Records component of NRC's ADAMS.
The NRC examiners completed operating test grading on December 15, 2014.
- (3) Examination Results Six applicants at the SRO level and six applicants at the RO level were administered written examinations and operating tests. Ten applicants passed all portions of their examinations and were issued their respective operating licenses on December 18, 2014.
One applicant failed the administered written examination and was issued a proposed license denial. One applicant passed all portions of the license examination, but received a written test grade below 82 percent. In accordance with NRC policy, the applicants license will be withheld until any written examination appeal possibilities by other applicants have been resolved. If the applicants grade is still equal to or greater than 80 percent after any appeal resolution, the applicant will be issued an operating license. If the applicants grade has declined below 80 percent, the applicant will be issued a proposed license denial letter and offered the opportunity to appeal any questions the applicant feels were graded incorrectly.
.2 Examination Security
a. Scope
The NRC examiners reviewed and observed the licensee's implementation of examination security requirements during the examination validation and administration to assure compliance with 10 CFR 55.49, Integrity of Examinations and Tests. 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
No findings were identified
4OA6 Management Meetings
.1 Debrief
The chief examiner presented the examination team's preliminary observations and findings on November 21, 2014, to Mr. D. Stiles, Training Director, and other members of the Braidwood Station Operations and Training Department staff.
.2 Exit Meeting
The chief examiner conducted an exit meeting on December 15, 2014, with Mr. D. Stiles, Braidwood Station Training Director, by telephone. The NRCs final disposition of the stations post-examination comments were disclosed and discussed with Mr. Stiles during the telephone discussion. The examiners asked the licensee whether any of the material used to develop or administer the examination should be considered proprietary. No proprietary or sensitive information was identified during the examination or debrief/exit meetings.
ATTACHMENTS:
1. Supplement Information
2. Simulation Facility Report
3. Post-Examination Comments and Resolutions
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee
- D. Stiles, Training Director
- K. Dovas, Operations Training Manager
- J. Eilertson, Exam Author
- A. Ferko, Ops Director
- M. Henson, ILT Group Lead
- R. Schleissman, Regional Assurance
- G. Stopka, Shift Operations Supervisor
U.S. Nuclear Regulatory Commission
- R. M. Morris, Senior Operations Engineer
- B. Boston, Reactor Engineer
ITEMS OPENED, CLOSED, AND DISCUSSED
Opened, Closed, and Discussed
None
LIST OF DOCUMENTS REVIEWED