Similar Documents at Byron |
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Category:Inspection Plan
MONTHYEARML24022A2722024-01-23023 January 2024 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000454/2024011 ML23297A2352023-10-26026 October 2023 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection IR 05000454/20230052023-08-30030 August 2023 Updated Inspection Plan for Byron Station (Report 05000454/2023005 and 05000455/2023005) ML23157A2832023-06-0606 June 2023 Notification of NRC Baseline Inspection and Request for Information IR 05000454/20220062023-03-0101 March 2023 Annual Assessment Letter for Byron Station, Units 1 and 2 (Report 05000455/2022006 and 05000454/2022006) ML23026A3272023-01-26026 January 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000454/2023001 ML22333A7712022-11-29029 November 2022 Request for Information for an NRC Post Approval Site Inspection for License Renewal Inspection Report 05000454/2023010 IR 05000454/20220052022-08-24024 August 2022 Updated Inspection Plan for Byron Station Units 1 and 2 (Report 05000454/2022005; 05000455/2022005) IR 05000454/20210062022-03-0202 March 2022 Annual Assessment Letter for Byron Station, Units 1 and 2 (Report 05000454/2021006 and 05000455/2021006) ML22040A1442022-02-0909 February 2022 Notification of NRC Baseline Inspection and Request for Information Inspection Report 05000455/2022003 ML21273A3312021-10-0404 October 2021 Information Request to Support Upcoming Biennial Problem Identification and Resolution (Pi&R) Inspection at Byron Station IR 05000454/20210052021-09-0101 September 2021 Updated Inspection Plan for Byron Station Units 1 and 2 (05000454/2021005 and 05000455/2021005) ML21159A1382021-06-0909 June 2021 Notification of NRC Baseline Inspection and Request for Information, Inspection Report 05000454/2021003 IR 05000454/20200062021-03-0404 March 2021 Annual Assessment Letter for Byron Station (Report 05000454/2020006 and 05000455/2020006) ML21007A1222021-01-0707 January 2021 Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Teams); Inspection Report 05000454/2021011; 05000455/2021011 ML20329A4852020-11-24024 November 2020 Notification of NRC Fire Protection Team Inspection Request for Information IR 05000454/20200052020-09-0101 September 2020 Updated Inspection Plan for Byron Station Units 1 and 2 (Report 05000454/2020005 and 05000455/2020005) ML20174A5672020-06-22022 June 2020 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000455/2020003 ML20162A0962020-06-10010 June 2020 Information Request for NRC Triennial Evaluations of Changes, Tests, and Experiments (50.59) Baseline Inspection; Inspection Report 05000454/2020011; 05000455/2020011 IR 05000454/20190062020-03-0303 March 2020 Annual Assessment Letter for Byron Station, Units 1 and 2 (Report 05000454/2019006 and 05000455/2019006) IR 05000454/20190052019-08-28028 August 2019 Updated Inspection Plan for Byron Station, Units 1 and 2 (Report 05000454/2019005; 05000455/2019005) ML19172A2772019-06-21021 June 2019 Information Request to Support Upcoming Problem Identification and Resolution Inspection at Byron Station, Units 1 and 2 ML19136A1852019-05-15015 May 2019 Byron Station, Clinton Power Station, Dresden Nuclear Power Station, LaSalle County Station, and Quad Cities Nuclear Power Station-Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency ML19123A0362019-05-0303 May 2019 Ltr. 05/03/19 Byron Station, Units 1 and 2 - Request for Information for an NRC Design Bases Assurance Inspection (Program): Implementation of the Environmental Qualification Program Inspection Report 05000454/2019012; 05000455/2019012 (DRS ML19065A2982019-03-0505 March 2019 Ltr. 03/05/19 Byron Station, Units 1 and 2 - Notification of an NRC Triennial Heat Sink Performance Inspection and Request for Information; Inspection Report 05000454/2019003 and 05000455/2019003 (DRS-L.Rodriguez) IR 05000454/20180062019-03-0404 March 2019 Annual Assessment Letter for Byron Station, Units 1 and 2 (Report 05000454/2018006 and 05000455/2018006) ML18354A7012018-12-19019 December 2018 Ltr. 12/19/18 Byron Generating Station, Units 1 and 2 - Notification of NRC Triennial Fire Protection Baseline Inspection and Request for Information 05000454/2019011; 05000455/2019011 (DRS-A.Shaikh) IR 05000454/20180052018-08-28028 August 2018 Updated Inspection Plan for Byron Station, Units 1 and 2 (Report 05000454/2018005 and 05000455/2018005) ML18170A1742018-06-19019 June 2018 Notification of NRC Inspection and Request for Information (DRS-J.Bozga) IR 05000454/20170062018-03-0202 March 2018 Annual Assessment Letter for Byron Station, Units 1 and 2 (Report 05000454/2017006 and 05000455/2017006) IR 05000454/20170052017-08-28028 August 2017 Updated Inspection Plan for Byron Station, Units 1 and 2 (Report 05000454/2017005 and 05000455/2017005) ML17158B1462017-06-0606 June 2017 Information Request to Support Upcoming Problem Identification at and Resolution Inspection at Byron, Units 1 and 2 ML17146A7262017-05-11011 May 2017 Inspection Plan for Byron Station, Units 1 and 2, for Evaluation of Changes, Tests, and Experiments (Triennial Review) Inspection Report 2017009 (Dxs) IR 05000454/20160062017-03-0101 March 2017 Annual Assessment Letter for Byron Station Units 1 and 2 (Report 05000454/2016006 and 05000455/2016006) IR 05000454/20160052016-08-31031 August 2016 Mid-Cycle Assessment Letter for Byron Station, Units 1 and 2 (Report 05000454/2016005; 05000455/2016005) ML16225A4222016-07-29029 July 2016 Inspection Plan - Byron Station, Units 1 and 2, Triennial Fire Protection Baseline Inspection 2016 007 (Dxs) ML16091A4402016-03-31031 March 2016 Request for Information for Inservice Inspection 2016 002 (Msh) IR 05000454/20150062016-03-0202 March 2016 Annual Assessment Letter for Byron Station, Units 1 and 2 (Inspection Report 05000454/2015006 and 05000455/2015006) IR 05000454/20150052015-09-0101 September 2015 Mid-Cycle Assessment Letter for Byron Station, Units 1 and 2 (Report 05000454/2015005; 05000455/2015005) IR 05000454/20140012015-03-0404 March 2015 Annual Assessment Letter for Byron Station, Units 1 and 2 (Report 05000454/2014001; 05000455/2014001) ML15029A1672015-01-28028 January 2015 CDBI Request for Information ML14245A0922014-09-0202 September 2014 Mid-Cycle Assessment Letter for Byron Station, Unit 1 and 2 IR 05000454/20130012014-03-0404 March 2014 Annual Assessment Letter for Byron Station, Units 1 and 2 (Report 05000454/2013001; 05000455/2013001) ML13246A1982013-09-0303 September 2013 2013 Byron MOC Letter Combined IR 05000454/20120012013-03-0404 March 2013 Annual Assessment Letter - Byron Station, Units 1 and 2, 05000454/2012001 and 05000455/2012001 ML12248A3312012-09-0404 September 2012 Mid-Cycle Assessment Letter for Byron Station Units 1 and 2 ML12179A1962012-06-26026 June 2012 ISI Request for Information- Baseline Inspection IR 05000454/20110072012-03-0505 March 2012 Annual Assessment Letter for Byron Station, Units 1 and 2 (Report 05000454/2011007 and 05000455/2011007) IR 05000454/20110062011-09-0101 September 2011 Mid-Cycle Letter for Byron Station, Units 1 & 2, 05000454/2011-006; 05000455/2011-006 ML11221A1962011-08-0808 August 2011 Notification of NRC Inspection and Request for Information 2024-01-23
[Table view] Category:Letter
MONTHYEARIR 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 RS-23-117, 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 ML23313A0852023-11-0909 November 2023 Submittal of 2023-301 Byron Initial License Examination Post-Examination Comments 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 ML23297A2352023-10-26026 October 2023 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection RS-23-100, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-13013 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation 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 ML23278A0272023-10-0505 October 2023 Operator Licensing Examination Approval - Byron Station, October 2023 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. ML23251A1622023-09-29029 September 2023 Steam Generator Tube Inspection Reports to Reflect TSTF-577 Reporting Requirements RS-23-094, Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 752023-09-29029 September 2023 Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 75 RS-23-091, Relief Request I4R-25, Alternative Requirements for Reactor Pressure Vessel Inservice Inspection Intervals2023-09-26026 September 2023 Relief Request I4R-25, Alternative Requirements for Reactor Pressure Vessel Inservice Inspection Intervals 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) ML23242A3282023-09-0101 September 2023 Amendment No. 233 Correction IR 05000454/20235012023-08-31031 August 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000454/2023501 and 05000455/2023501 IR 05000454/20230052023-08-30030 August 2023 Updated Inspection Plan for Byron Station (Report 05000454/2023005 and 05000455/2023005) IR 05000454/20230022023-08-0303 August 2023 Integrated Inspection Report 05000454/2023002 and 05000455/2023002 ML23209A7242023-07-31031 July 2023 Request for Information on the NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000454/2024010 and 05000455/2024010 ML23192A0362023-07-25025 July 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report ML23122A3022023-07-20020 July 2023 Issuance of Amendments Technical Specifications 2.1.1 and 4.2.1 to Allow a Previously Irradiated Accident Tolerant Fuel Lead Test Assembly to Be Further Irradiated in Unit No. 2 IR 05000454/20234022023-07-18018 July 2023 Baseline Security Inspection Document; 05000454/2023402; 05000455/2023402 ML23198A0372023-07-17017 July 2023 Information Request to Support Upcoming Problem Identification and Resolution (PIR) Inspection at Byron Nuclear Plant 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 ML23172A1172023-06-22022 June 2023 Notification of NRC Fire Protection Team Inspection Request for Information 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 ML23159A1302023-06-0808 June 2023 Day Inservice Inspection Report for Interval 4, Period 3, (B1R25) ML23159A1542023-06-0808 June 2023 2022 Regulatory Commitment Change Summary Report 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 ML23157A2832023-06-0606 June 2023 Notification of NRC Baseline Inspection and Request for Information BYRON 2023-0029, Response to Request for Additional Information Regarding Steam Generator Tube Inspection Reports to Reflect TSTF-577 Reporting Requirements2023-06-0101 June 2023 Response to Request for Additional Information Regarding Steam Generator Tube Inspection Reports to Reflect TSTF-577 Reporting Requirements 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 ML23003A7882023-05-11011 May 2023 Report for December 12-16, 2022, Regulatory Audit Regarding Reinsertion of a High Burnup Accident Tolerant Fuel Lead Test Assembly 2024-02-02
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Inspection Report - Byron - 2011006 |
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Text
UNITED STATES ber 1, 2011
SUBJECT:
MID-CYCLE LETTER FOR BYRON STATION, UNITS 1 AND 2; 05000454/2011-006; 05000455/2011-006
Dear Mr. Pacilio:
On August 9, 2011, the 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, 2010, through June 30, 2011. This letter informs you of the NRCs assessment of your facility during this period and its plans for future inspections at your facility. This performance review and enclosed inspection plan do not include security information. A separate letter will include the NRCs assessment of your performance in the Security Cornerstone and its security-related inspection plan.
The NRC determined the performance at Byron Station Unit 1 during the most recent quarter, as well as the first three quarters of the assessment period, 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 NRC determined the performance at Byron Station Unit 2 during the most recent quarter was within the Regulatory Response Column of the NRCs ROP Action Matrix, based on one inspection finding being classified as having low-to-moderate safety significance (i.e., White)
and all PIs indicated that your performance was within the nominal, expected range (i.e.,
Green). The White finding involved the failure to ensure that a flange connection on the upper lube oil cooler of the 2A diesel generator was correctly torqued following maintenance. This led to the 2A diesel generator being required to be shut down when a significant oil leak developed during routine surveillance testing on November 17, 2010. This finding caused Byron Unit 2 to transition from the Licensee Response Column to the Regulatory Response Column of the ROP Action Matrix in the first quarter of 2011. Therefore, based upon completion of a supplemental inspection as discussed below, the NRC plans to conduct ROP baseline inspections at your facility. On July 14, 2011, your staff notified the NRC of your readiness for the NRC to conduct a supplemental inspection to review the actions taken to address the White finding. Therefore, we conducted a supplemental inspection for Byron Unit 2 using Inspection Procedure (IP) 95001, Inspection For One or Two White Inputs in a Strategic Performance Area, in addition to routine ROP baseline inspections. The onsite portion of the inspection was completed on August 26, 2011, and the results of the inspection will be documented in NRC Inspection Report 05000455/2011016 after these results are finalized.
From July 1, 2010, to June 30, 2011, the NRC issued six Severity Level IV traditional enforcement violations to Byron Station. Four of these violations were associated with the construction and operation of the Independent Spent Fuel Storage Installation (ISFSI).
These four violations did not involve willfulness, impede the regulatory process, or have an actual safety consequence. Therefore, the NRC will not perform IP 92723, Follow Up Inspection for Three or More Severity Level IV Traditional Enforcement Violations in the Same Area in a 12-Month Period, at your facility to review the Severity Level IV violations related to the ISFSI. However, one of the Severity Level IV violations was associated with a compliance backfit issue. Consistent with the NRCs practice in reviewing compliance backfit issues, the NRC will perform IP 92723 at your facility to review your efforts to implement corrective actions and identify any extent of condition concerns associated with the compliance backfit issue.
The enclosed inspection plan lists the inspections scheduled through December 31, 2012.
Routine inspections performed by resident inspectors are not included in the inspection plan.
The inspections listed during the last nine months 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. The NRC also plans to conduct several special and infrequently performed inspections, which include inspections related to the operation of the ISFSI.
In the days following the Fukushima Daiichi nuclear accident in Japan, the Commission directed the staff to establish a senior-level agency task force to conduct a methodical and systematic review of the NRCs processes and regulations to determine whether the agency should make additional improvements to its regulatory system. The NRC has since completed Temporary Instruction (TI) 183, Follow-up to Fukushima Daiichi Nuclear Station Fuel Damage Event, and TI-184, Availability and Readiness Inspection of Severe Accident Management Guidelines (SAMGs) at your facility. Results of these inspections can be found here: http://www.nrc.gov/japan/japan-activities.html. Additionally, on May 11, 2011, the agency issued NRC Bulletin 2011-01, Mitigating Strategies, to confirm compliance with Order EA-02-026, subsequently imposed license conditions, and 10 CFR 50.54(hh)(2), and to determine the status of licensee mitigating strategies programs. On July 12, 2011, the NRCs Task Force made its recommendations to the Commission in its report, Recommendations for Enhancing Reactor Safety in the 21st Century: The Near-Term Task Force Review of Insights from the Fukushima Daiichi Accident. The NRC is currently reviewing the Task Forces recommendations to determine what additional actions may be warranted. In accordance with 10 CFR 2.390 of the NRC=s ARules of Practice,@ a copy of this letter and its enclosure will be made 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 Eric Duncan at 630-829-9620 with any questions you may have regarding this letter or the inspection plan.
Sincerely,
/RA/
Steven West, Director Division of Reactor Projects Docket Nos. 50-454, 50-455 License Nos. NPF-37, NPF-66 Enclosure: Byron Station Inspection/Activity Plan cc w/encl: Distribution via ListServ