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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
MONTHYEARIR 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 2022-04-06
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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