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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) 05000456/LER-2024-001, Submittal of LER 2024-001-00 for Braidwood Station, Unit 1, Trip on Low Steam Generator Level Due to Failure to Verify Isolation Valves Were Open2024-07-0303 July 2024 Submittal of LER 2024-001-00 for Braidwood Station, Unit 1, Trip on Low Steam Generator Level Due to Failure to Verify Isolation Valves Were Open 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 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
[Table view] |
Text
ber 25, 2009
SUBJECT:
BRAIDWOOD STATION NRC INITIAL LICENSE EXAMINATION REPORT 05000456/2009301(DRS);
05000457/2009301(DRS)
Dear Mr. Pardee:
On October 29, 2009, the U. S. Nuclear Regulatory Commission (NRC) completed the initial operator licensing examination process at your Braidwood Station. The enclosed report presents the results of the examination which were discussed with Mr. L. Coyle and other members of your staff on October 16, 2009, and Mr. P. DiGiovanna on November 10, 2009.
The NRC examiners administered initial license examination operating tests from October 5 through October 16, 2009. Members of the Braidwood Training Department administered the initial license written examination on October 19, 2009. One reactor operator and 12 senior reactor operator license examinations were administered. One of the applicants was a previously licensed reactor operator at Braidwood Station. The results of the examinations were finalized on November 10, 2009. All 13 applicants passed all sections of their examinations resulting in the issuance of 1 reactor operator and 12 senior reactor operator licenses.
In accordance with 10 CFR 2.390 of the NRCs 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 System (PARS) component of NRCs Agencywide Documents Access and Management System (ADAMS), 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 05000456/2009301(DRS); 05000457/2009301(DRS)
2. Simulation Facility Report 3. Written Examinations and Answer Keys (RO and SRO)
REGION III==
Docket Nos: 50-456; 50-457 License Nos: NPF-72; NPF-77 Report No: 05000456/2009301(DRS); 05000457/2009301(DRS)
Licensee: Exelon Generation Company, LLC Facility: Braidwood Station, Units 1 and 2 Location: Braceville, Illinois Dates: October 5 through October 29, 2009 Examiners: B. Palagi, Chief Examiner D. McNeil, Examiner C. Zoia, Examiner Approved by: Hironori Peterson, Chief Operations Branch Division of Reactor Safety Enclosure 1
SUMMARY OF FINDINGS
ER 05000456/2009301(DRS); 05000457/2009301(DRS); 10/05/09 - 10/29/09; Exelon
Generation Company, LLC; Braidwood Station, Unit 1 and 2; Initial License Examination Report.
The announced operator licensing initial examination was conducted by regional examiners in accordance with the guidance of NUREG-1021, Operator Licensing Examination Standards for Power Reactors, Revision 9, Supplement 1.
Examination Summary:
$ Thirteen examinations were administered (1 reactor operator and 12-senior reactor operator);
$ All 13 applicants passed all sections of their examinations resulting in the issuance of reactor operator and 12 senior reactor operator licenses.
REPORT DETAILS
OTHER ACTIVITIES (OA)
4OA5 Other
.1 Initial Licensing Examinations
a. Examination Scope
The NRC examiners conducted an announced operator licensing initial examination during the weeks of October 5 and October 12, 2009. The facility licensees training staff used the guidance prescribed in NUREG-1021, Operator Licensing Examination Standards for Power Reactors, Revision 9, Supplement 1, to prepare the outline and develop the written examination and operating test. The examiners administered the operating test, consisting of job performance measures and dynamic simulator scenarios, during the period of October 5 through October 16, 2009. The facility licensee administered the written examination on October 19, 2009. One reactor operator and 12 senior reactor operator applicants were examined. During the on-site validation week of September 14, 2009, the examiners audited four license applications for accuracy.
b. Findings
Written Examination The NRC examiners determined that the written examination, as originally submitted by the licensee, was within the range of acceptability expected for a proposed examination.
All changes made to the submitted examination were made in accordance with NUREG-1021, "Operator Licensing Examination Standards for Power Reactors, Revision 1, Supplement 1. The licensee graded the written examination on October 19, 2009, and conducted a review of each question to determine the accuracy and validity of the examination questions. On October 29, 2009, the NRC received the licensees letter concerning the post examination material. The licensee did not submit any post examination comments for consideration by the NRC examiners when grading the written examination or enhancements based on a post examination review with the applicants.
Operating Test The NRC examiners determined that the operating test, as originally submitted by the licensee, was within the range of acceptability expected for a proposed examination.
All changes made to the submitted examination were made in accordance with NUREG-1021, "Operator Licensing Examination Standards for Power Reactors,"
Revision 1, Supplement 1. The NRC examiners completed operating test grading on October 30, 2009.
Examination Results All 13 applicants passed all sections of their examinations resulting in the issuance of 1 reactor operator and 12 senior reactor operator licenses.
.2 Examination Security
a. Inspection Scope
The NRC examiners briefed the facility contact on the NRCs requirements and guidelines related to examination physical security (e.g., access restrictions and simulator considerations) and integrity in accordance with 10 CFR 55.49, Integrity of Examinations and Tests, and NUREG-1021, Operator Licensing Examination Standard for Power Reactors, Revision 9, Supplement 1. The examiners reviewed and observed the licensees implementation and controls of examination security and integrity measures (e.g., security agreements) throughout the examination process.
b. Findings
No Findings
4OA6 Meetings
Debrief The chief examiner presented the examination team's preliminary observations and findings on October 16, 2009, to Mr. L. Coyle, Plant Manager, and other members of the Braidwood Operations and Training Department staff.
Exit Meeting The chief examiner conducted an exit meeting by telephone on November 10, 2009, with Mr. P. DiGiovanna, Operations Training Manager. The NRC=s preliminary examination results were provided to Mr. DiGiovanna 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.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
Enclosure 1
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee
Larry Coyle, Plant Manager
Tom McCool, Operations Director
Tricia Matteson, Regulatory Engineer
Paul DiGiovanna, Operations Training Manager
Darren Stiles, Initial License Training Group Lead
Brian Kempen, Lead Regulatory Exam Author
Ken Norris, Senior Operations Training Instructor
Dan Burton, Simulator Supervisor
NRC
B Palagi, Chief Examiner
- D. McNeil, Examiner
- C. Zoia, Examiner
ITEMS OPENED, CLOSED, AND DISCUSSED
Opened, Closed, and Discussed
None
LIST OF ACRONYMS
ADAMS Agency-Wide Document Access and Management System
CFR Code of Federal Regulations
DRS Division of Reactor Safety
NRC U. S. Nuclear Regulatory Commission
PARS Publicly Available Records System
Attachment
SIMULATION FACILITY REPORT
Facility Licensee: Braidwood Station, Unit 1 and 2
Facility Licensee Docket No. 50-456; 50-457
Operating Tests Administered: October 5 through October 16, 2009
The following documents observations made by the NRC examination team during the initial
operator license examination. These observations do not constitute audit or inspection findings
and are not, without further verification and review, indicative of non-compliance with
CFR 55.45(b). These observations do not affect NRC certification or approval of the
simulation facility other than to provide information which may be used in future evaluations.
No licensee action is required in response to these observations.
During the conduct of the simulator portion of the operating tests, the following items were
observed:
ITEM DESCRIPTION
None
Enclosure 2
WRITTEN EXAMINATIONS AND ANSWER KEYS (RO/SRO)
RO/SRO Initial Examination ADAMS Accession #ML093230542
Enclosure 3
C. Pardee -2-
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 05000456/2009301(DRS); 05000457/2009301(DRS)
2. Simulation Facility Report
3. Written Examinations and Answer Keys (RO and SRO)
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