Similar Documents at Byron |
---|
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
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE RD. SUITE 210 LISLE, IL 60532-4352 January 28, 2015 Mr. Bryan C. Hanson Senior VP, Exelon Generation Company, LLC President and CNO, Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
BYRON STATION, UNITS 1 AND 2; REQUEST FOR INFORMATION FOR AN NRC TRIENNIAL BASELINE COMPONENT DESIGN BASES INSPECTION (CDBI)
INSPECTION REPORT 05000454/2015008; 05000455/2015008
Dear Mr. Hanson:
On April 20, 2015, the U.S. Nuclear Regulatory Commission (NRC) will begin a triennial baseline Component Design Bases Inspection (CDBI) at Byron Station, Units 1 and 2. A team of six inspectors will perform this three-week inspection. This inspection will be performed in accordance with NRC Baseline Inspection Procedure (IP) 71111.21.
The CDBI focuses on the design, maintenance, and operation of risk-significant components associated with one or more accident scenario or systems. The components to be reviewed during this baseline inspection will be identified during the inoffice preparation week that occurs prior to the first on-site inspection week. In addition, operating experience issues, associated with the component samples, will also be selected for review. The inspection team may request scenarios to be performed on the simulator. This request would require support from your simulator staff to validate scenarios, simulator time, and a crew to perform the actions which would most likely occur during the second on-site week. The team will work closely with your staff early on during the inspection process to ensure this activity can be accomplished with minimal impact.
The inspection will include three weeks on-site. The inspection team will consist of six NRC inspectors, of which five will focus on engineering/maintenance and one on operations. The current inspection schedule is as follows:
- On-site weeks: April 20 - 24, 2015; May 4 - 8, 2015; May 18 - 22, 2015.
The team will be preparing for the inspection, mainly during the week of April 13 - 17, 2015, as discussed in the enclosure.
B. Hanson Experience with previous baseline design inspections of similar depth and length has shown that this type of inspection is extremely resource intensive, both for the NRC inspectors and the licensee staff. In order to minimize the inspection impact on the site and to ensure a productive inspection for both parties, we have enclosed a request for information needed for the inspection.
It is important that all of these documents are up-to-date and complete in order to minimize the number of additional documents requested during the preparation and/or the on-site portions of the inspection. Insofar as possible, this information should be provided electronically to the lead inspector. The information request has been divided into three groups:
- The first group lists information necessary for our initial inspection scoping activities.
This information should be provided to the lead inspector no later than March 3, 2015. By March 20, 2015, the lead inspector will communicate the initial selected set of approximately 15 components.
- The second group of documents requested is those items needed to support our in-office preparation activities. This set of documents, including the calculations associated with the initial selected components, should be provided to the lead inspector at the Regional Office no later than April 8, 2015. During the in-office preparation activities, the team may identify additional information needed to support the inspection.
- The last group includes the additional information above as well as plant-specific reference material. This information should be available to the team onsite on April 20, 2015. It is also requested that corrective action documents and/or questions developed during the inspection be provided to the lead inspector as the documents are generated.
The lead inspector for this inspection is Néstor J. Féliz-Adorno. We understand that our licensing contact for this inspection is Lisa Zurawski of your organization. If there are any questions about the inspection or the material requested in the enclosure, please contact the lead inspector at (630) 829-9739 or via e-mail at nestor.feliz-adorno@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. 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)
B. Hanson 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/
Christine A. Lipa, Chief Engineering Branch 2 Division of Reactor Safety Docket Nos. 50-454; 50-455 License Nos. NPF-37; NPF-66
Enclosure:
Information Request for Component Design Bases Inspection (CDBI) cc w/encl: Distribution via LISTSERV
INFORMATION REQUEST FOR COMPONENT DESIGN BASIS INSPECTION (CDBI)
Inspection Report: 05000454/2015008; 05000455/2015008 Inspection Dates: April 20 - 24, 2015; May 4 - 8, 2015; May 18 - 22, 2015.
Inspection Procedure: IP 71111.21 Component Design Bases Inspection Lead Inspector: Néstor J. Féliz-Adorno, Senior Reactor Engineer, DRS (630) 829-9739 nestor.feliz-adorno@nrc.gov I. Information Requested Prior to the On-site Information Gathering/Inspection Week The following information is requested by March 3, 2015, or sooner, to facilitate inspection preparation. If you have any questions regarding this information, please call the team leader as soon as possible. Please provide the information electronically in pdf files, Excel, or other searchable formats, preferably on some portable electronic media (e.g., CDROM, DVD, flash drive, etc.). The portable electronic media should contain descriptive names, and be indexed and hyperlinked to facilitate ease of use.
Information in lists should contain enough information to be easily understood by someone who has knowledge of light water reactor technology.
- 1. Risk-ranking of top 250 components from your site-specific Probabilistic Safety Analysis (PSA) sorted by Risk-Achievement Worth (RAW). Include values for Birnbaum Importance, Risk-Reduction Worth (RRW), and Fussell-Veseley (FV)
(as applicable).
- 2. Risk-ranking of top 100 containment-related components from your site specific PSA sorted by Large Early Release Frequency (LERF).
- 3. Provide a list of the top 200 cut-sets from your PSA.
- 4. Provide a list of the top 100 cut-sets for each initiator modeled in the PSA that contributes more than five percent to the baseline plant Core Damage Frequency (CDF).
- 5. Copies of PSA system notebooks and latest PSA summary document.
- 6. List of time critical operator actions. Identify those actions that do not have job performance measures (JPMs).
- 7. Provide copies of the Emergency Operating Procedures (EOPs).
- 8. If you have an External Events or Fire PSA Model, provide the information requested in Items 1 and 2 for external events and fire. Provide narrative description of each coded event (including fire, flood zone description).
Enclosure
INFORMATION REQUEST FOR COMPONENT DESIGN BASIS INSPECTION (CDBI)
- 9. Electronic copy of the site Individual Plant Examination Of External Events (IPEEE), if available.
- 10. Any pre-existing evaluation or list of components and associated calculations with low design margins, (i.e., pumps closest to the design limit for flow or pressure, diesel generator close to design required output, heat exchangers close to rated design heat removal etc.).
- 11. List of available design (setup) margins in both the open and closed direction (identify safety-related direction) for valves in the Motor-Operated Valve (MOV) and Air-Operated Valve (AOV) Programs. Identify the basis for how the margin was determined.
- 12. List of high risk Maintenance Rule systems/components based on engineering or expert panel judgment (i.e., those systems/components not identified in the PRA).
- 13. Structures, systems, and components (SSCs) in the Maintenance Rule (a)(1) category for the last three years.
- 14. Site top ten issues list (if applicable).
- 15. A list of operating experience evaluations for the last three years.
- 16. Information of any common cause failure of components experienced in the last five years at your facility.
- 17. List of Root Cause Evaluations associated with component failures or design issues initiated/completed in the last five years.
- 18. List of open operability evaluations.
- 19. List of components/systems considered operable but degraded/nonconforming.
- 20. Current management and engineering organizational chart.
- 21. Electronic copies of Updated Final Safety Analysis Report, Technical Specifications, Technical Specifications Bases, and Technical Requirements Manual.
- 22. Major one line electrical drawings (ac and dc) and key diagrams (paper copies).
- 23. Electronic copy of P&IDs (if available).
2
INFORMATION REQUEST FOR COMPONENT DESIGN BASIS INSPECTION (CDBI)
II. Information Requested (for the approximate 15 selected components) to be Available by April 8, 2015, (will be reviewed by the team in the Regional office during the week of April 13 - 17, 2015).
This information should be separated for each selected component, especially if provided electronically (e.g., folder with component name that includes calculations, condition reports, maintenance history, etc.).
- 1. List of condition reports (corrective action documents) associated with each of the selected components for the last six years.
- 2. The maintenance history (corrective, preventive, and elective) associated with each of the selected components for the last ten years. Identify frequency of preventive maintenance activities.
- 3. Copies of calculations associated with each of the selected components (if not previously provided), excluding data files. Please review the calculations and also provide copies of important referenced material (such as drawings, engineering requests, and vendor letters).
- 4. System Health Reports, System Descriptions, Design Basis Documents, and/or Training Lesson Plans that are associated with each of the selected components.
- 5. A list of modifications, including equivalency evaluations and setpoint changes, associated with each of the selected components. This list should include a descriptive paragraph on the purpose of the modification. Please ensure this list only includes design completed (not canceled) modifications.
- 6. Copies of operability evaluations (open/closed for last three years) associated with each of the selected components and plans for restoring operability, if applicable.
- 7. Copies of selected operator work-around evaluations associated with each of the selected components and plans for resolution, if applicable.
- 8. Copies of any open temporary modifications associated with each of the selected components, if applicable.
- 9. Trend data on the selected electrical/mechanical components performance for last three years (e.g., pumps performance including in-service testing, other vibration monitoring, oil sample results, etc., for valves: stroke time and leak rate results, etc.).
- 10. Copy of latest completed surveillance tests for each component (e.g., for pumps this would include: comprehensive test, quarterly test, flow balance, etc. for valves: stroke time testing, diagnostic testing, leak testing, etc.). Acceptance criteria basis calculations should also be included.
- 11. Provide copies of the normal and abnormal operating procedures associated with the selected components and selected scenarios.
3
INFORMATION REQUEST FOR COMPONENT DESIGN BASIS INSPECTION (CDBI)
- 12. A copy of any internal/external self-assessments and associated corrective action documents generated in preparation for the inspection.
- 13. A copy of engineering/operations related audits completed in the last two years.
III. Additional Information to be Provided on April 20, 2015, On-Site (for final selected components)
- 1. During the in-office preparation activities, the team will be making final selections and may identify additional information needed to support the inspection. The lead inspector will provide a list of the additional information needed during the week of April 13 - 17, 2015.
- 2. Schedule of any testing/maintenance activities to be conducted on the selected components during the three onsite inspection weeks.
IV. Information Requested to be Provided Throughout the Inspection
- 1. Copies of any corrective action documents generated as a result of the teams questions or queries during this inspection.
- 2. Copies of the list of questions submitted by the team members and the status/resolution of the information requested (provide daily during the inspection to each team member).
- 3. One complete set of P&IDs (paper copies).
- 4. Reference materials. (make available if needed during all on-site weeks):
- Procurement documents for components selected (verify retrievable);
- Plant procedures (normal, abnormal, emergency, surveillance, etc.); and
If you have questions regarding the information requested, please contact the lead inspector.
4
B. Hanson 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/
Christine A. Lipa, Chief Engineering Branch 2 Division of Reactor Safety Docket Nos. 50-454; 50-455 License Nos. NPF-37; NPF-66
Enclosure:
Information Request for Component Design Bases Inspection (CDBI) cc w/encl: Distribution via LISTSERV DISTRIBUTION:
Kimyata MorganButler RidsNrrDorlLpl3-2 Resource RidsNrrPMByron Resource RidsNrrDirsIrib Resource Cynthia Pederson Darrell Roberts Eric Duncan Allan Barker Carole Ariano Linda Linn DRPIII DRSIII Jim Clay Carmen Olteanu ADAMS Accession Number ML15029A167 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 RIII RIII NAME BJose for NFeliz-Adorno: cl CLipa DATE 01/27/15 01/28/15 OFFICIAL RECORD COPY