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] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE ROAD, SUITE 210 LISLE, IL 60532
-4352 June 8, 2011 Mr. Michael J. Pacilio Senior Vice President, Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO), Exelon Nuclear 4300 Winfield Road Warrenville IL 60555
SUBJECT:
INFORMATION REQUEST TO SUPPORT UPCOMING PROBLEM IDENTIFICATION AND RESOLUTION (PI&R) INSPECTION AT BYRON STATION
Dear Mr. Pacilio:
This letter is to request information to support our PI&R inspection beginning August 1 5, 20 11 , at Byron Station. This inspection will be performed in accordance with NRC Inspection Procedure 71152.
Experience has shown that these inspections are extremely resource intensive both for the NRC inspectors and the utility staff. In order to minimize the impact that the inspection has on the site and to ensure a productive inspection, we have enclosed a list of documents required for the inspection.
The documents requested are copies of condition reports and lists of information, necessary to ensure the inspection team is adequately prepared for the inspection. The information may be provided in either CD
-ROM or hard copy format and should be ready for NRC review by July 25 , 2011. Mr. Raymond Ng, the Lead Inspector, will contact your staff to determine the best method of providing the requested information.
If there are any questions about the material requested, or the inspection in general, please do not hesitate to call Mr.
Ng at 630-829-9 574 or email at raymond.ng@nrc.gov
.
M. Pacilio In accordance with 10 CFR 2.790 of the NRC's "Rules of Practice," a copy of this letter and its enclosure 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), accessible from the NRC Web site at http://www.nrc.gov/reading
-rm/adams.html (the Public Electronic Reading Room).
Sincerely, /RA/ Eric R. Duncan, Chief Branch 3 Division of Reactor Projects Docket No. 50
-454; 50-455 License No. NPF
-37; NPF-66
Enclosure:
Requested Information to Support PI&R Inspection cc w/encl:
Distribution via ListServ
1 Enclosure Requested Information to Support Problem Identification and Resolution (PI&R) Inspection
- 1. A copy of administrative procedure(s) for the corrective action program (CAP), trending program, quality assurance audit program, self
-assessment program, corrective action effectiveness review program, and industry experience review program
. 2. A copy of the employee concerns program/Ombudsman administrative procedure
. 3. A copy of quality assurance (QA) audits of the corrective action program completed since July 1, 2009
. 4. The plan for self
-assessments of the corrective action program and a copy of completed self-assessments of the corrective action program since July 1, 2009
. 5. A list of self
-assessments completed since July 1, 2009, with a brief description of areas where findings were identified.
- 6. A list of QA audits completed since July 1, 2009, with a brief description of areas where findings were identified.
- 7. A list of root cause evaluations completed since July 1, 2009, with a brief description of the issue. 8. A list of apparent cause evaluations completed since July 1, 2009, with a brief description of the issu
- e. 9. A list of all open condition reports sorted by significance level and then initiation date. Include the date initiated, a description of the issue, system affected, significance level, and priority level.
- 10. A list of condition reports closed since July 1, 2009 , sorted by significance level and then initiation date. Include a description, the significance level, the priority level, the date initiated and closed, system affected and whether there was an associated operability evaluation
.
- 11. A list of effectiveness reviews completed since July 1, 2009, with a brief description of areas where findings were identified.
- 12. A list of condition reports initiated since July 1, 2009
, that involve inadequate or ineffective corrective actions. Include the date initiated, a brief description, status, significance level of the issue, system affected and priority level to correct.
- 13. A list of condition reports initiated since July 1, 2009
, that identify trends of conditions adverse to quality. Include the date initiated, a brief description, status, significance level, and priority level for each item
.
2 Enclosure 14. A copy of any performance reports for the past 2 years used to track the corrective action program effectiveness
. 15. A list of operating experience documents received since July 1, 2009
, and any associated condition reports
. 16. A list of test failures (IST or Technical Specifications surveillances) since July 1, 2009 , with a brief description of component/system
, which failed
. 17. A list of condition reports issued during the past two refueling outages sorted by system and component, including a brief description, status, significan ce level, and priority level for each item
. 18. A list of Maintenance Rule (a)(1) systems and components, and the associated health reports since July 1, 2009
. 19. A list of rework items and repeat failures since July 1, 2009
. 20. A current list of operator workarounds and burdens, with a listing of condition reports and work order/work order request generated to address those items and the last two evaluations of the impact of operator workarounds and burdens
- 21. Copies of corrective actions taken for issues identified in NRC findings since July 1, 2009. 22. A copy of the most recent operating experience program effectiveness review
. 23. A list of the top ten risk significant systems and top ten risk significant components
.
- 24. A list of the dates, times, and location for all scheduled meetings associated with the implementation of the CAP. 25. A list of current operability determinations
. 26. A copy of the latest Byron Station organizational chart and phone listing
. 27. Results of any safety culture/safety conscious work environment survey or self-assessment completed since January 200
- 9. 28. Description of changes made to the corrective action program since the last PI&R inspection.
Documents requested to be available on
-site during the inspection
- a. Updated Final Safety Analysis Report
. b. Technical Specifications
.
- c. Procedures and procedure index
.
3 Enclosure d. Copies of any self
-assessments and associated condition reports generated in preparation for the inspection
. e. A copy of the QA manual
. f. A list of issues brought to the ECP/ombudsman and the actions taken for resolution
.
- g. A list of the organization codes used in the CAP
.
M. Pacilio In accordance with 10 CFR 2.790 of the NRC's "Rules of Practice," a copy of this letter and its enclosure 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), accessible from the NRC Web site at http://www.nrc.gov/reading
-rm/adams.html (the Public Electronic Reading Room).
Sincerely, /RA/ Eric R. Duncan, Chief Branch 3 Division of Reactor Projects Docket No. 50
-454; 50-455 License No. NPF
-37; NPF-66
Enclosure:
Requested Information to Support PI&R Inspection cc w/encl:
Distribution via ListServ
DOCUMENT NAME:
G:\DRPIII\BYRO\Byron PIR 2011008 Info Request.doc Publicly Available Non-Publicly Available Sensitive Non-Sensitive To receive a copy of this document, indicate in the concurrence box "C" = Copy without attach/encl "E" = Copy with attach/encl "N" = No copy OFFICE RIII RIII NAME RNg:dtp EDuncan DATE 06/08/11 06/08/11 OFFICIAL RECORD COPY
Letter to M. Pacilio from E Duncan dated June 8, 2011.
SUBJECT:
INFORMATION REQUEST TO SUPPORT UPCOMING PROBLEM IDENTIFICATION AND RESOLUTION (PI&R) INSPECTION AT BYRON STATION DISTRIBUTION:
Daniel Merzke
RidsNrrDorlLpl3
-2 Resource RidsNrrPMByron Resource
RidsNrrDirsIrib Resource Cynthia Pederson
Steven Orth Jared Heck Allan Barker Carole Ariano Linda Linn DRPIII DRSIII Patricia Buckley Tammy Tomczak ROPreports Resource