Similar Documents at Byron |
---|
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
[Table view] |
Inspection Report - Byron - 2011005 |
---|
|
|
|
|
Text
ary 14, 2012
SUBJECT:
ERRATA FOR BYRON STATION, UNITS 1 AND 2, INTEGRATED INSPECTION REPORT 05000454/2011-005; 05000455/2011-005
Dear Mr. Pacilio:
On February 7, 2012, the U. S. Nuclear Regulatory Commission (NRC) issued an Integrated Inspection Report 05000454/2011-005, 05000455/2011-005 for your Byron Station. An inspection sample for the Mitigating Systems Performance Index Residual Heat Removal System was inadvertently omitted in the original report.
The enclosed errata contain the omitted inspection sample. No findings were identified. We regret any inconvenience this may cause.
In accordance with 10 CFR 2.390 of the NRCs "Rules 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 NRCs document system (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Should you have any questions concerning this errata, we will be pleased to discuss them with you.
Sincerely,
/RA/
Eric R. Duncan, Chief Branch 3 Division of Reactor Projects Docket Nos. 50-454; 50-455 License Nos. NPF-37; NPF-66
Enclosure:
Errata for Inspection Report 05000454/2011-005; 05000455/2011-005
REGION III==
Docket Nos: 05000454; 05000455 License Nos: NPF-37; NPF-66 Report No: 05000454/2011005; 05000455/2011005 Licensee: Exelon Generation Company, LLC Facility: Byron Station, Units 1 and 2 Location: Byron, IL Dates: October 1, 2011, through December 31, 2011 Inspectors: B. Bartlett, Senior Resident Inspector J. Robbins, Resident Inspector R. Ng, Project Engineer J. Dalzell-Bishop, DRS Emergency Response Specialist J. Cassidy, Senior Health Physicist R. Jickling, Senior Emergency Preparedness Inspector B. Palagi, Senior Operations Engineer J. Nance, Reactor Engineer J. Benjamin, Braidwood Senior Resident Inspector C. Thompson, Resident Inspector, Illinois Emergency Management Agency Approved by: E. Duncan, Chief Branch 3 Division of Reactor Projects
4. OTHER ACTIVITIES (OA)
4OA1 Performance Indicator Verification (71151)
.1 Mitigating Systems Performance Index - Residual Heat Removal System a. Inspection Scope The inspectors sampled licensee submittals for the MSPI - Residual Heat Removal System PI for Unit 1 and Unit 2, for the period from October 1, 2010, through September 30, 2011. To determine the accuracy of the PI data reported during those periods, PI definitions and guidance contained in NEI 99-02, Regulatory Assessment Performance Indicator Guideline, Revision 6, dated October 2009, was used. The inspectors reviewed the licensees operator narrative logs, issue reports, event reports, MSPI derivation reports, and NRC Integrated Inspection Reports for the period of October 1, 2010, through September 30, 2011, to validate the accuracy of the submittals. The inspectors reviewed the MSPI component risk coefficient to determine if it had changed by more than 25 percent in value since the previous inspection, and if so, whether the change was in accordance with applicable NEI guidance. The inspectors also reviewed the licensees issue report database to determine if any problems had been identified with the PI data collected or transmitted for this indicator. Documents reviewed are listed in the Attachment to this report.
This inspection constituted two MSPI residual heat removal system samples as defined in IP 71151-05.
b. Findings No findings of significance were identified.
4OA6 Meetings
.1 Exit Meeting Summary On January 12, 2012, the inspectors presented the inspection results to Mr. B. Youman, and other members of the licensee staff. The licensee personnel acknowledged the inspection results presented. The inspectors confirmed that all proprietary material reviewed during the inspection was returned to the licensee staff.
.2 Interim Exit Meetings Interim exits were conducted for:
- The results of an Operator Licensing inspection with the Lead Operations Training staff instructor, Mr. M. McCue, via telephone on December 8, 2011.
- The results of an annual review of Emergency Action Level and Emergency Plan changes with the Emergency Preparedness Coordinator, Mr. R. Kartheiser, via telephone on December 7, 2011.
- The results of Occupational and Public Radiation Safety programs inspections with the Site Vice President, Mr. T. Tulon, on November 10, 2011, and with the Acting Plant Manager, E. Hernandez, on December 28, 2011.
The licensee acknowledged the issues presented. The inspectors confirmed that none of the potential report input discussed was considered proprietary. Proprietary material received during the inspection was returned to the licensee.
SUPPLEMENTAL INFORMATION KEY POINTS OF CONTACT Licensee T. Tulon, Site Vice President B. Youman, Plant Manager D. Coltman, Operations Manager J. Feimster, Design Engineering Manager D. Damptz, Acting Maintenance Director S. Swanson, Nuclear Oversight Manager B. Barton, Radiation Protection Manager K. Anderson, Acting Radiation Protection Manager A. Creamean, Chemistry Manager D. Gudger, Regulatory Assurance Manager T. Hulbert, Regulatory Assurance Specialist R. Cameron, Licensed Operator Requalification Lead Nuclear Regulatory Commission E. Duncan, Chief, Branch 3, Division of Reactor Projects LIST OF ITEMS OPENED, CLOSED AND DISCUSSED Open None Closed None
UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION III
2443 WARRENVILLE ROAD, SUITE 210 LISLE, IL 60532-4352 February 14, 2012 Mr. Michael