Similar Documents at Byron |
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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] Category:Request for Additional Information (RAI)
MONTHYEARML23297A2352023-10-26026 October 2023 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection ML23209A7242023-07-31031 July 2023 Request for Information on the NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000454/2024010 and 05000455/2024010 ML23198A0372023-07-17017 July 2023 Information Request to Support Upcoming Problem Identification and Resolution (PIR) Inspection at Byron Nuclear Plant ML23172A1172023-06-22022 June 2023 Notification of NRC Fire Protection Team Inspection Request for Information ML23110A3202023-04-21021 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML23069A0342023-03-0606 March 2023 Unit 1 Lr Commitment 10 RAI Set 1 - (Non-Proprietary) ML23069A0332023-03-0606 March 2023 Email to K. Lueshen Byron and Braidwood Commitment 10 - Request for Additional Information Set 1 ML23115A2412023-01-20020 January 2023 NRR E-mail Capture - Preliminary RAIs Related to L-2022-LLA-0131 - Byron, Unit 2, Reinsertion of an Accident Tolerant Fuel Lead Test Assembly ML22237A0272022-08-25025 August 2022 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML22271A0772022-05-0606 May 2022 NRR E-mail Capture - Final RAIs 9.1.2021 Constellation Relief Request ML22129A0132022-05-0606 May 2022 NRR E-mail Capture - Draft RAIs for Requests for Alternatives I4R-17, I4R-23, ISI-05-018, I6R-10 ML22116A1272022-04-26026 April 2022 Unit 2 RFI for an NRC Triennial Heat Exchanger/Sink Performance Inspection and RFI IR 05000454/2022002 05000455/2022002 ML22091A0852022-04-0101 April 2022 NRR E-mail Capture - Braidwood and Byron - Final RAI Regarding Proposed Alternative for Various Pressurizer Welds (EPID L-2021-LLR-0035 and 0036) ML22041B5362022-02-10010 February 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Request for Additional Information Regarding Fleet License Amendment Request to Adopt TSTF-541 ML21273A3312021-10-0404 October 2021 Information Request to Support Upcoming Biennial Problem Identification and Resolution (Pi&R) Inspection at Byron Station ML21256A1902021-09-10010 September 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21203A3112021-07-21021 July 2021 NRR E-mail Capture - Final Byron Permanently Defueled Technical Specifications (PDTS) - Second Round RAI ML21189A1602021-07-0808 July 2021 NRR E-mail Capture - Request for Additional Information - Braidwood, Byron, and Ginna - Amendment to Address the Issues in Westinghouse NSALs ML21189A1612021-07-0808 July 2021 NRR E-mail Capture - Second Round Request for Additional Information - Byron Permanently Defueled Technical Specification Amendment ML21144A2132021-05-24024 May 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21117A0342021-05-0505 May 2021 Request for Additional Information Regarding Proposed Alternative to Use ASME Code Case N-893 ML21062A0652021-03-0101 March 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative to Documentation Requirements for Pressure Retaining Bolting ML21049A2572021-02-18018 February 2021 Request for Additional Information Byron/Dresden Proposed Changes to Site Emergency Plans to Support Post-Shutdown and Permanently Defueled Conditions (EPID-2020-LLA-0240 & EPID-2020-LLA-0237) ML21036A1102021-02-0404 February 2021 NRR E-mail Capture - Draft RAIs for Byron Station, Unit Nos. 1 and 2, Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition ML21029A3302021-01-29029 January 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Fleet Alternative Request to Use ASME Code Case N-885 ML21004A1452020-12-30030 December 2020 NRR E-mail Capture - Request for Additional Information Regarding Relief Requests Braidwood I4R-11 and Byron I4R-18 ML20329A4852020-11-24024 November 2020 Notification of NRC Fire Protection Team Inspection Request for Information ML20294A5492020-10-21021 October 2020 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML20289A1142020-10-0909 October 2020 NRR E-mail Capture - Preliminary RAIs for LAR Regarding Non-conservative TS EDG Frequency Tolerance ML20077M2212020-03-20020 March 2020 Ti 2515/194 Inspection Documentation Request ML20008D3992020-01-0808 January 2020 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000454/2020001 ML19275H1362019-10-0202 October 2019 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Request to Use ASME Code Case N-879 ML19252C1542019-08-22022 August 2019 NRR E-mail Capture - Issuance of the Remainder of Preliminary RAIs for Braidwood/Byron TSTF-505 Application ML19232A2242019-08-0707 August 2019 NRR E-mail Capture - Partial Issuance of Final RAIs for Braidwood/Byron TSTF-505 Application ML19207A0672019-07-26026 July 2019 NRR E-mail Capture - Partial Issuance of Preliminary RAIs for Braidwood/Byron TSTF-505 Application ML19179A0612019-07-19019 July 2019 Three Mile Point 1 - Supplemental Information Needed to Proposed Alternative to Use ASME Code Case N-879 ML19032A1062019-02-0101 February 2019 NRR E-mail Capture - Preliminary RAIs for Byron On--time Extension of Completion Time 3.8.1, A.2 ML19011A3452019-01-11011 January 2019 NRR E-mail Capture - Preliminary RAIs Regarding Byron Request to Use ATF LTAs ML18149A2842018-05-24024 May 2018 NRR E-mail Capture - B/B 50.69 RAI - Potential Typo ML18129A1082018-05-0909 May 2018 NRR E-mail Capture - Preliminary RAIs for Braidwood and Byron Stations 50.69 Amendment ML18067A1482018-03-0808 March 2018 Enclosurequest for Additional Information (Letter to P. R. Simpson Request for Additional Information Regarding Exelon Generating Company, Llc'S Decommissioning Funding Plan Update for Independent Spent Fuel Storage Installation) ML18022A0422018-01-19019 January 2018 18 Byron Station, Units 1 and 2 - Information Request to Support Upcoming Temporary Instruction 2515/194 Inspection (DRS-I.Hafeez) ML17179A2852017-06-28028 June 2017 NRR E-mail Capture - Request for Additional Information Regarding Braidwood and Byron Amendments to Remove Obsolete License and Technical Specification Items ML17159A6292017-06-0707 June 2017 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection (Mxg) ML17137A0562017-05-17017 May 2017 Information Request to Support Upcoming Temporary Instruction 191 Inspection at Byron Station, Units 1 and 2 ML17062A4912017-03-0303 March 2017 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Fleet Alternative to RPV Threads in Flange Examination (CAC Nos. MF8712-MF8729) ML17019A2022017-01-19019 January 2017 NRR E-mail Capture - Preliminary RAIs for Byron Station TORMIS License Application Request ML16355A0322016-12-19019 December 2016 Notification of NRC Inspection and Request for Information (Msh) ML16343A2522016-12-0808 December 2016 NRR E-mail Capture - Preliminary Request for Additional Information (RAI) Regarding Relief Request I4R-10 ML16196A1102016-07-14014 July 2016 Notification of NRC Triennial Heat Sink Performance Inspection and Request for Information; Inspection Report 05000454/2016004; 05000455/2016004 2023-07-31
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UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE RD. SUITE 210 LISLE, IL 60532-4352 June 5, 2015 Mr. Bryan C. Hanson Senior VP, Exelon Generation Company, LLC President and CNO, Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
INFORMATION REQUEST TO SUPPORT UPCOMING PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION AT BYRON STATION, UNITS 1 AND 2
Dear Mr. Hanson:
This letter is to request information to support our biennial Problem Identification and Resolution (PI&R) inspection beginning July 20, 2015, at the Byron Station, Units 1 and 2. This inspection will be performed in accordance with the U.S. Nuclear Regulatory Commission (NRC) Baseline 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. This information request may be provided in either CD-ROM/DVD/Thumb Drive or hard copy format and should be ready for NRC review by June 29, 2015. Mr. Jamie Benjamin, 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 or e-mail Mr. Jamie Benjamin at 630-842-7109 or Jamie.Benjamin@nrc.gov This letter does not contain new or amended information collection requirements subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection requirements were approved by the Office of Management and Budget, Control Number 3150-0011.
B. Hanson The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid Office of Management and Budget Control Number.
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding, of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRCs Public Document Room or from the Publicly Available Records (PARS) component of the NRC's Agencywide Documents Access and Management System (ADAMS).
ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
John Ellegood, Acting Chief Branch 3 Division of Reactor Projects Docket Nos. 50-454; 50-455 License Nos. NPF-37; NPF-66
Enclosure:
RFI to Support PI&R Inspection cc w/encl: Distribution via LISTSERV
Requested Information to Support Problem Identification and Resolution (PI&R) Inspection Please provide the information on five compact discs or thumb drives (one for the team lead, one for the Resident Inspector Office, one for the IEMA Resident Inspector Office and one for the two other scheduled inspectors), if possible. Unless otherwise specified, the time frame for requested information is for the period of July 2013, through the time the information request is answered. Please label any electronic files with content information.
In addition, inspectors will require computer access to the corrective action program (CAP) database while on site.
PROGRAM DOCUMENTS
- 1. Copies of current administrative procedures associated with the corrective action program (CAP). This should include procedures related to: 1) corrective action process; 2) cause evaluations; 3) operating experience program; 4) self-assessment program; 5) maintenance rule program; 6) operability determination process;
- 7) degraded/non-conforming condition process (e.g., RIS 2005-20); 8) system health process or equivalent equipment reliability improvement programs; and 9) operational decision making (ODMI) process.
- 2. A current copy of the Employee Concerns Program/Ombudsman administrative procedure.
- 3. Description of any substantive changes made to the CAP since the last PI&R Inspection (September 2013). Please include the effective date with each listed change.
ASSESSMENTS
- 4. A copy of Quality Assurance (QA) audits of the CAP and audits of the QA program.
- 5. A list of all completed assessments and QA audits for those programs related to the CAP (e.g., Operating Experience, Maintenance Rule, etc.)
- 6. Copies of completed assessments of the CAP, the QA program and the self-assessment program. Include the plan/schedule for future CAP self-assessments.
- 7. A chronological list of completed department and site self-assessments (include date completed).
- 8. A list of condition reports (CRs) initiated for findings or concerns identified in self-assessments and audits. Include a short description/title of the finding, its status, and include a cross-reference to the audit or self-assessment number.
Enclosure
CORRECTIVE ACTION DOCUMENTS
- 9. Copies of completed root cause evaluations.
- 10. A list of completed apparent cause evaluations with a brief description of the issue.
Provide status of any actions developed as part of the evaluations and their present status. Include a reference, if not part of the apparent cause package, to the documents and/or CRs directing and tracking the actions.
- 11. A list of all open CRs sorted by significance level. Include CR number, date initiated, a brief description/title, affected system(s), significance level, and anticipated completion date, if available. This list should be grouped by responsible department and arranged in order of initiation date (oldest listed first).
- 12. A list of closed CRs sorted by significance level. Include CR number, date initiated, a brief description/title, affected systems(s), significance level, date closed. This list should be grouped by responsible department.
- 13. A list of open corrective actions, sorted by priority level, with a brief description/title, initiating date and due date. The list should be grouped by the responsible department.
- 14. A list of CRs captured in databases operated and/or maintained by the sites corporate office related to Byron Station sorted by significance level. Include the date initiated, a brief description/title, site(s) affected, system(s) affected, significance/priority level, assigned organization, and status (if closed include date closed; if open, include scheduled date to be closed).
- 15. A list of completed effectiveness reviews. Include a cross-reference to the CRs for which the effectiveness review was conducted and, if applicable, CR numbers documenting any additional follow-up actions.
- 16. A list of CRs initiated for inadequate or ineffective corrective actions. Include the date initiated, a brief description/title, significance level, system affected, assigned organization, and status (if closed include date closed; if open, include scheduled date to be closed). Include a cross-reference to the CR or evaluation that generated the original corrective action.
- 17. A copy of any performance reports/indicators used to track CAP effectiveness for the past 18 months. End-of-quarter data will suffice; monthly reports are not required.
TRENDS
- 18. A list of CRs initiated for trends of conditions adverse to quality. Include the date initiated, a brief description/title, significance level, and status (if closed include date closed; if open, include scheduled date to be closed).
- 19. Copies of any completed trend reports that are associated with overall CAP performance and/or effectiveness.
- 20. Copies of all apparent, common and/or root cause evaluations regarding adverse equipment reliability and adverse human performance trends.
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OPERATING EXPERIENCE
- 21. A copy of the most recent operating experience program effectiveness review and or assessment.
- 22. A list of CRs initiated to evaluate industry and NRC operating experience, and NRC generic communications (e.g., bulletins, information notices, generic letters, etc.).
Include date the CR was initiated, a brief description/title, and the status (if closed include date closed; if open, include scheduled date to be closed).
SYSTEMS AND COMPONENTS
- 23. A list of the top ten risk significant systems, risk significant components and risk significant operator actions.
- 24. A list of test failures (in-service tests and technical specification surveillance tests) with a brief description of component/system that failed.
- 25. A list of all structures, systems and components (SSCs) that are classified as (a)(1) in accordance with the Maintenance Rule. Include: 1) date SSC entered (a)(1); 2) brief description/reason for being in (a)(1); and 3) status of action plan.
- 26. Copy of current system health report for SSCs classified as (a)(1).
- 27. A list of maintenance preventable functional failures (MPFFs). Include the CR number; a brief description of the system/component that failed; and date the MPFF occurred.
- 28. A list of plant trips, unplanned downpowers (greater than 20 percent), unscheduled limiting condition for operation entries and licensee event reports, including dates of these events.
- 29. A list of control room deficiencies, operator workarounds and burdens, sorted by priority, with a brief description/title and corresponding CR and/or work order number.
- 30. A list of operability determinations/evaluations. Include a brief description/title, date initiated, date closed or date scheduled to be closed. Also include any open operability evaluations that were initiated prior to July 1, 2012.
- 31. A list of temporary modifications that were installed since July 1, 2012, with a brief description/title, installation date, and current status. Include any in-place temporary modifications that were installed prior to July 1, 2012.
SAFETY CULTURE
- 32. Copies of assessments or evaluations (internal or external) regarding station and/or department safety culture/safety conscious work environment.
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REGULATORY ISSUES
- 33. A list of CRs for issues (findings, violations, etc.) documented in NRC inspection reports.
Include the CR number, brief description/title, date initiated and the status (if closed include date closed; if open, include scheduled date to be closed).
- 34. A list of CRs for licensee identified violations that have been documented in NRC inspection reports. Include the CR number, brief description/title, date initiated and the status (if closed include date closed; if open, include scheduled date to be closed).
- 35. A list of CRs associated with NRC identified issues. Include the CR number, brief description/title, date initiated and the status (if closed include date closed; if open, include scheduled date to be closed).
- 36. A list of degraded/non-conforming conditions. Include the CR number, brief description/title, date initiated and date closed or projected closeout date. Include open issues that were identified prior to July 1, 2012.
5-YEAR REVIEW
- 37. A list of CRs regarding the Radiation Process and Area Radiation Monitors that have been generated since July 1, 2009. Include the CR number, brief description/title, level of evaluation (i.e., root cause, apparent cause, common cause, etc.), date initiated, and the status (if closed include date closed; if open, include scheduled date to be closed).
- 38. A list of CRs regarding the 1B and 2B (Diesel Driven) Auxiliary Feedwater Systems that have been generated since July 1, 2009. Include the CR number, brief description/title, level of evaluation (i.e., root cause, apparent cause, common cause, etc.), date initiated, and the status (if closed include date closed; if open, include scheduled date to be closed).
- 39. Copies 50.59 screenings or evaluations, operability evaluations and ODMIs, maintenance rule evaluations, and root and apparent cause evaluations completed since July 1, 2009, associated with the 1B and 2B (Diesel Driven) Auxiliary Feedwater Systems.
- 40. Copies of root and apparent cause evaluations completed since July 1, 2009, for age management degradation issues related to the 1B and 2B (Diesel Driven) Auxiliary Feedwater Systems.
ADMIN
- 41. A copy of the latest plant organizational chart and phone listing.
- 42. Scheduled dates, times, and location for all meetings associated with implementing the CAP (e.g., CR screening meetings, corrective action review board meetings). Include work order screening/assessment meetings.
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Documents requested to be available on-site during the inspection
- a. Updated Final Safety Analysis Report.
- b. 4 Copies on Compact Disc.
- c. Technical Specifications.
- d. Copies of any self-assessments and associated CRs initiated while preparing for this PI&R inspection.
- e. Quality Assurance Manual.
- f. A list of issues brought to the ECP/ombudsman and the actions taken for resolution.
- g. A list of the codes used in the CAP.
Other On the first day of the inspection, or early on the second day, please provide the inspection team a briefing/overview of your CAP, including any actions taken associated with recent industry efforts to improve the efficiency of the CAP. Include your expectations for personnel using the program and how the work order system fits into the overall scheme for addressing identified issues. Also include a demonstration on how to access the CAP data on the computer.
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B. Hanson The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid Office of Management and Budget Control Number.
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding, of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRCs Public Document Room or from the Publicly Available Records (PARS) component of the NRC's Agencywide Documents Access and Management System (ADAMS).
ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA John Ellegood, Acting Chief Branch 3 Division of Reactor Projects Docket Nos. 50-454; 50-455 License Nos. NPF-37; NPF-66
Enclosure:
RFI to Support PI&R Inspection cc w/encl: Distribution via LISTSERV DISTRIBUTION w/encl: Allan Barker Kimyata MorganButler Carole Ariano rDorlLpl3-2 Resource Linda Linn RidsNrrPMByron Resource DRPIII RidsNrrDirsIrib Resource DRSIII Cynthia Pederson Jim Clay Darrell Roberts Carmen Olteanu Richard Skokowski ROPassessment.Resource@nrc.gov ADAMS Accession Number: ML15156A816 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 JEllegood:mt DATE 06/05/15 OFFICIAL RECORD COPY