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| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE RD. SUIT E 210 LISLE, IL 60532-4352 August 31, 2016 Mr. Bryan Senior VP, Exelon Generation Company, LLC President and CNO, Exelon Nuclear 4300 Winfield Road | | {{#Wiki_filter:UNITED STATES ust 31, 2016 |
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| Warrenville, IL 60555 SUBJECT: MID-CYCLE ASSESSMENT LETTER FOR BYRON STATION, UNITS 1 AND 2 (REPORT 05000454/2016005; 05000455/2016005)
| | ==SUBJECT:== |
| | MID-CYCLE ASSESSMENT LETTER FOR BYRON STATION, UNITS 1 AND 2 (REPORT 05000454/2016005; 05000455/2016005) |
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| ==Dear Mr. Hanson:== | | ==Dear Mr. Hanson:== |
| On August 10, 2016, the U.S. Nuclear Regulatory Commission (NRC) completed its mid-cycle performance review of Byron Station Units 1 and 2. | | On August 10, 2016, the U.S. Nuclear Regulatory Commission (NRC) completed its mid-cycle performance review of Byron Station Units 1 and 2. The NRC reviewed the most recent quarterly performance indicators (PIs) in addition to inspection results and enforcement actions from July 1, 2015 through June 30, 2016. This letter informs you of the NRCs assessment of your facility during this period and its plans for future inspections at your facility. |
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| The NRC reviewed the most recent quarterly performance indicators (PIs) in addition to inspection results and enforcement actions from July 1, 2 0 15 through June 30, 20 16. This letter informs you of the NRC's assessment of your facility during this period and its plans for future inspections at your facility. | | The NRC determined that overall, Byron Station Units 1 and 2 operated in a manner that preserved public health and safety and met all cornerstone objectives. The NRC determined the performance at Byron Station Units 1 and 2 during the most recent quarter was within the Licensee Response Column of the NRCs Reactor Oversight Process (ROP) Action Matrix because all inspection findings had very low (i.e., green) safety significance, and all PIs indicated that your performance was within the nominal, expected range (i.e., green). |
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| The NRC determined that overall, Byron Station Units 1 and 2 operated in a manner that preserved public health and safety and met all cornerstone objectives.
| | Therefore, the NRC plans to conduct ROP baseline inspections at your facility. |
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| The NRC determined the performance at Byron Station Units 1 and 2 during the most recent quarter was within the Licensee Response Column of the NRC
| | The enclosed inspection plan lists the inspections scheduled through June 30, 2018. Routine inspections performed by resident inspectors are not included in the inspection plan. The inspections listed during the second half of the inspection plan are tentative and may be revised at the end-of-cycle performance review. The NRC provides the inspection plan to allow for the resolution of any scheduling conflicts and personnel availability issues. The NRC will contact you as soon as possible to discuss changes to the inspection plan should circumstances warrant any changes. This inspection plan does not include security related inspections, which will be sent via separate, non-publicly available correspondence. |
| 's Reactor Oversight Process (ROP) Action Matrix because all inspection findings had very low (i.e., green) safety significance, and all PIs indicated that your performance was within the nominal, expected range (i.e., green). Therefore, the NRC plans to conduct ROP baseline inspections at your facility
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| . The enclosed inspection plan lists the inspections scheduled through June 30 , 201 8. Routine inspections performed by resident inspectors are not included in the inspection plan.
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| The inspections listed during the second half of the inspection plan are tentative and may be revised at the end-of-cycle performance review. The NRC provides the inspection plan to allow for the resolution of any scheduling conflicts and personnel availability issues. The NRC will contact you as soon as possible to discuss changes to the inspection plan should circumstances warrant any changes.
| | In response to the accident at Fukushima, the Commission issued Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events, and Order EA-12-051, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation. The NRC conducted audits of licensee efforts towards compliance with these Orders, and the information gathered will aid staff in development of the ultimate Safety Evaluation for the site. After the NRC staff receives the Final Compliance letter for the site, the Safety Evaluation will be issued. Then, the NRC staff will confirm through inspections the full implementation of the orders mentioned above by performing Temporary Instruction 191, Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans. Pending receipt of the final compliance letter, this inspection is currently scheduled in August 2017. |
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| This inspection plan does not include security related inspections, which will be sent via separate, non-publicly available correspondence.
| | As noted in the attached inspection plan, some planned non-routine inspections the NRC plans to perform include Inspection Procedure 60855.1, Operation of an ISFSI at Operating Reactors, in October of this year. |
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| In response to the accident at Fukushima, the Commission issued Order EA-12-049, "Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events | | In Staff Requirements Memorandum - SECY 16-0009, Recommendations Resulting from the Integrated Prioritization and Re-Baselining of Agency Activities, the Commission approved the NRC staff recommendation to discontinue the formal mid-cycle assessment process beginning in calendar year 2017. This will be the final mid-cycle assessment letter. The staff will continue to conduct quarterly assessment meetings and communicate changes in the assessment of licensee performance in accordance with the guidance in Inspection Manual Chapter 0305, Operating Reactor Assessment Program. |
| ," and Order EA-12-051, "Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation." The NRC conducted audits of licensee efforts towards compliance with these Orders, and the information gathered will aid staff in development of the ultimate Safety Evaluation for the site. | |
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| After the NRC staff receives the Final Compliance letter for the site, the Safety Evaluation will be issued.
| | In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390 of the NRCs Rules of Practice, a copy of this letter will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) 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). |
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| Then, the NRC staff will confirm through inspections the full implementation of the orders mentioned above by performing Temporary Instruction 191, "Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans." Pending receipt of the final compliance letter, this inspection is currently schedule d in August 2017.
| | Please contact me at 630-829-9620 with any questions you have regarding this letter. |
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| As noted in the attached inspection plan, some planned non-routine inspections the NRC plans to perform include Inspection Procedure 60855.1, "Operation of an ISFSI at Operating Reactors," in October of this year.
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| In Staff Requirements Memorandum
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| - SECY 16-0009, "Recommendations Resulting from the Integrated Prioritization and Re-Baselining of Agency Activities," the Commission approved the NRC staff recommendation to discontinue the formal mid-cycle assessment process beginni ng in calendar year 2017. This will be the final mid-cycle assessment letter. The staff will continue to conduct quarterly assessment meetings and communicate changes in the assessment of licensee performance in accordance with the guidance in Inspection Manual Chapter 0305, "Operating Reactor Assessment Program."
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| In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390 of the NRC
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| 's "Rules of Practice," a copy of this letter will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) 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).
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| Please contact me a t 630-829-9620 with any questions you have regarding this letter. | |
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| Sincerely, | | Sincerely, |
| /RA/ | | /RA/ |
| Eric Duncan, Chief Branch 3 Division of Reactor Projects | | Eric Duncan, Chief Branch 3 Division of Reactor Projects Docket Nos. 50-454; 50-455 License Nos. NPF-37; NPF-66 Enclosure: |
| | | Inspection Plan cc: Distribution via LISTSERV |
| Docket Nos. | |
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| 50-454; 50-455 License Nos. | |
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| NPF-37; NPF-66 Enclosure: | |
| Inspection Plan | |
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| cc: Distribution via LISTSERV | |
| }} | | }} |
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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 BYRON 2024-0031, Completion of License Renewal Activities Prior to Entering the Period of Extended Operation2024-05-16016 May 2024 Completion of License Renewal Activities Prior to Entering the Period of Extended Operation IR 05000454/20240012024-05-10010 May 2024 Integrated Inspection Report 05000454/2024001; 05000455/2024001 and 07200068/2024001 BYRON 2024-0028, Annual Radiological Environmental Operating Report (AREOR)2024-05-0909 May 2024 Annual Radiological Environmental Operating Report (AREOR) BYRON 2024-0022, 2023 Regulatory Commitment Change Summary Report2024-05-0202 May 2024 2023 Regulatory Commitment Change Summary 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 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) ML24116A1192024-04-25025 April 2024 2023 Annual Radioactive Effluent Release Report (ARERR) 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) ML24113A2892024-04-22022 April 2024 Notification of NRC Baseline Inspection and Request for Information BYRON 2024-0020, Annual Dose Report for 20232024-04-18018 April 2024 Annual Dose Report for 2023 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 BYRON 2024-0021, Registration of Use of Cask to Store Spent Fuel2024-04-11011 April 2024 Registration of Use of Cask to Store Spent Fuel 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 IR 05000454/20244012024-04-0303 April 2024 Cyber Security Inspection Report 05000454/2024401 and 05000455/2024401 (Public) 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 BYRON 2024-0019, Registration of Use of Cask to Store Spent Fuel2024-03-28028 March 2024 Registration of Use of Cask to Store Spent Fuel 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 IR 05000454/20230112024-03-20020 March 2024 Fire Protection Team Inspection Report 05000454/2023011 and 05000455/2023011 IR 05000454/20240102024-03-15015 March 2024 Comprehensive Engineering Team Inspection Report 05000454/2024010 and 05000455/2024010 IR 05000454/20230062024-02-28028 February 2024 Annual Assessment Letter for Byron Station, Units 1 and 2 (Report 05000455/2023006 and 05000454/2023006) IR 05000454/20230042024-02-0202 February 2024 Integrated Inspection Report 05000454/2023004 and 05000455/2023004 ML24022A2722024-01-23023 January 2024 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000454/2024011 ML24018A0362024-01-17017 January 2024 Paragon Energy Solutions, Defect with Detroit Diesel/Mtu Fuel Injectors P/N R5229660 Cat Id 0001390618 ML23320A1762023-12-13013 December 2023 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0027 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23277A0032023-12-11011 December 2023 Issuance of Amendments Regarding Adoption of TSTF-370 ML23318A5102023-12-0101 December 2023 Relief from the Requirements of the ASME Code IR 05000454/20233012023-11-27027 November 2023 NRC Initial License Examination Report 05000454/2023301 and 05000455/2023301 BYRON 2023-0065, Unit 2 - 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 Guideline2023-11-17017 November 2023 Unit 2 - 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 BYRON 2023-0063, Day Inservice Inspection Report for Interval 4, Period 3, (B2R24)2023-11-16016 November 2023 Day Inservice Inspection Report for Interval 4, Period 3, (B2R24) IR 05000454/20230032023-11-13013 November 2023 Integrated Inspection Report 05000454/2023003 and 05000455/2023003 and Exercise of Enforcement Discretion 2024-09-06
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Inspection Report - Byron - 2016005 |
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UNITED STATES ust 31, 2016
SUBJECT:
MID-CYCLE ASSESSMENT LETTER FOR BYRON STATION, UNITS 1 AND 2 (REPORT 05000454/2016005; 05000455/2016005)
Dear Mr. Hanson:
On August 10, 2016, the U.S. Nuclear Regulatory Commission (NRC) completed its mid-cycle performance review of Byron Station Units 1 and 2. The NRC reviewed the most recent quarterly performance indicators (PIs) in addition to inspection results and enforcement actions from July 1, 2015 through June 30, 2016. This letter informs you of the NRCs assessment of your facility during this period and its plans for future inspections at your facility.
The NRC determined that overall, Byron Station Units 1 and 2 operated in a manner that preserved public health and safety and met all cornerstone objectives. The NRC determined the performance at Byron Station Units 1 and 2 during the most recent quarter was within the Licensee Response Column of the NRCs Reactor Oversight Process (ROP) Action Matrix because all inspection findings had very low (i.e., green) safety significance, and all PIs indicated that your performance was within the nominal, expected range (i.e., green).
Therefore, the NRC plans to conduct ROP baseline inspections at your facility.
The enclosed inspection plan lists the inspections scheduled through June 30, 2018. Routine inspections performed by resident inspectors are not included in the inspection plan. The inspections listed during the second half of the inspection plan are tentative and may be revised at the end-of-cycle performance review. The NRC provides the inspection plan to allow for the resolution of any scheduling conflicts and personnel availability issues. The NRC will contact you as soon as possible to discuss changes to the inspection plan should circumstances warrant any changes. This inspection plan does not include security related inspections, which will be sent via separate, non-publicly available correspondence.
In response to the accident at Fukushima, the Commission issued Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events, and Order EA-12-051, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation. The NRC conducted audits of licensee efforts towards compliance with these Orders, and the information gathered will aid staff in development of the ultimate Safety Evaluation for the site. After the NRC staff receives the Final Compliance letter for the site, the Safety Evaluation will be issued. Then, the NRC staff will confirm through inspections the full implementation of the orders mentioned above by performing Temporary Instruction 191, Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans. Pending receipt of the final compliance letter, this inspection is currently scheduled in August 2017.
As noted in the attached inspection plan, some planned non-routine inspections the NRC plans to perform include Inspection Procedure 60855.1, Operation of an ISFSI at Operating Reactors, in October of this year.
In Staff Requirements Memorandum - SECY 16-0009, Recommendations Resulting from the Integrated Prioritization and Re-Baselining of Agency Activities, the Commission approved the NRC staff recommendation to discontinue the formal mid-cycle assessment process beginning in calendar year 2017. This will be the final mid-cycle assessment letter. The staff will continue to conduct quarterly assessment meetings and communicate changes in the assessment of licensee performance in accordance with the guidance in Inspection Manual Chapter 0305, Operating Reactor Assessment Program.
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390 of the NRCs Rules of Practice, a copy of this letter will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) 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).
Please contact me at 630-829-9620 with any questions you have regarding this letter.
Sincerely,
/RA/
Eric Duncan, Chief Branch 3 Division of Reactor Projects Docket Nos. 50-454; 50-455 License Nos. NPF-37; NPF-66 Enclosure:
Inspection Plan cc: Distribution via LISTSERV