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Category:Letter
MONTHYEARML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 ML24163A0012024-08-0505 August 2024 LTR-24-0119-1-1 Response to Nh Letter Regarding Review of NextEras Emergency Preparedness Amendment Review ML24193A2432024-07-12012 July 2024 – Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan ML24149A2862024-06-12012 June 2024 NextEra Fleet - Proposed Alternative Frr 23-01 to Use ASME Code Case N-752-1, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section X1, Division 1 (EPID L-2023-LLR-0009) - Letter ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities NG-24-0004, 2023 Annual Radiological Environmental Operating Report2024-05-0808 May 2024 2023 Annual Radiological Environmental Operating Report NG-24-0003, Submittal of 2023 Annual Radioactive Material Release Report2024-04-24024 April 2024 Submittal of 2023 Annual Radioactive Material Release Report ML24072A0292024-03-29029 March 2024 Nextera Energy Duane Arnold, Llc. Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) NG-24-0001, 2024 Annual Decommissioning and Spent Fuel Management Funding Status Report and Independent Spent Fuel Storage Installation (ISFSI) Decommissioning Financial Assurance Update2024-03-0606 March 2024 2024 Annual Decommissioning and Spent Fuel Management Funding Status Report and Independent Spent Fuel Storage Installation (ISFSI) Decommissioning Financial Assurance Update NG-24-0002, 2023 Annual Exposure Report - Form 5s2024-03-0606 March 2024 2023 Annual Exposure Report - Form 5s L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) NG-23-0010, Supplement to Duane Arnold Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-12-0606 December 2023 Supplement to Duane Arnold Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule NG-23-0009, Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment NG-23-0006, Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-05-23023 May 2023 Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update ML23137A1672023-05-11011 May 2023 Submittal of 2022 Annual Radiological Environmental Operating Report NG-23-0004, 2022 Annual Radioactive Material Release Report2023-04-25025 April 2023 2022 Annual Radioactive Material Release Report NG-23-0003, 2022 Annual Exposure Report - Form 5s2023-04-21021 April 2023 2022 Annual Exposure Report - Form 5s NG-23-0002, 10 CFR 50.59 Report, Commitment Changes, 10 CFR 72.48 Report, Quality Assurance Program Changes, Technical Specification Basis Changes, and Revision of the DAEC Defueled Safety Analysis Report2023-03-27027 March 2023 10 CFR 50.59 Report, Commitment Changes, 10 CFR 72.48 Report, Quality Assurance Program Changes, Technical Specification Basis Changes, and Revision of the DAEC Defueled Safety Analysis Report NG-23-0001, 2023 Annual Decommissioning and Spent Fuel Management Funding Status Report2023-03-27027 March 2023 2023 Annual Decommissioning and Spent Fuel Management Funding Status Report L-2023-029, and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3)2023-03-10010 March 2023 and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3) ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities ML22339A0012022-12-22022 December 2022 Acceptance of Requested Licensing Action Amendment Request for Common Emergency Plan IR 05000331/20220032022-12-13013 December 2022 NRC Inspection Report No. 05000331/2022003 (Drss) ML22285A0072022-10-13013 October 2022 NRC Analysis of NextEra Energy Duane Arnold'S Decommissioning Funding Status Report, Docket No. 50-331 IR 05000331/20220022022-07-13013 July 2022 NRC Inspection Report Nos. 05000331/2022002(DNMS) and 07200032/2022002(DNMS) ML22090A1922022-05-26026 May 2022 Letter to B. Coffey, FPL from M. Doell - Duane Arnold Post Shutdown Activities Report Review Letter ML22132A2872022-05-24024 May 2022 ISFSI DQAP Approval Letter ML22111A0332022-05-20020 May 2022 Operating License Page Correction Letter to B. Coffey, Florida Power and Light, from M. Doell NG-22-0055, Revision to Duane Arnold Energy Center (DAEC) ISFSI-Only Emergency Plan2022-05-20020 May 2022 Revision to Duane Arnold Energy Center (DAEC) ISFSI-Only Emergency Plan ML22089A0492022-05-12012 May 2022 Sfmp Review Letter NG-22-0053, 2021 Annual Radiological Environmental Operating Report2022-05-0606 May 2022 2021 Annual Radiological Environmental Operating Report NG-22-0052, Regulatory Issue Summary 2000-11. NRC Emergency Telecommunications System, Statement of Intent to Implement the Proposed Voluntary Initiative2022-05-0404 May 2022 Regulatory Issue Summary 2000-11. NRC Emergency Telecommunications System, Statement of Intent to Implement the Proposed Voluntary Initiative IR 05000331/20224012022-04-27027 April 2022 Decommissioning Security Inspection Report 05000331/2022401 NG-22-0050, Revised Response to Request for Additional Information Relating to Decommissioning Quality Assurance Program, Revision 02022-04-26026 April 2022 Revised Response to Request for Additional Information Relating to Decommissioning Quality Assurance Program, Revision 0 NG-22-0049, 2021 Annual Radioactive Material Release Report2022-04-26026 April 2022 2021 Annual Radioactive Material Release Report ML22066A7632022-04-25025 April 2022 ISFSI-Only Emergency Plan License Amendment Approval L-2022-068, NextEra Energy Duane Arnold Quality Assurance Topical Report (FPL-3) Revision 22022-04-25025 April 2022 NextEra Energy Duane Arnold Quality Assurance Topical Report (FPL-3) Revision 2 NG-22-0035, Response to Request for Additional Information Relating to Decommissioning Quality Assurance Program. Revision 02022-04-13013 April 2022 Response to Request for Additional Information Relating to Decommissioning Quality Assurance Program. Revision 0 NG-22-0047, Registration of Independent Spent Fuel Installation Storage Cask and Notification of Permanent Removal of All Spent Fuel Assemblies from the Spent Fuel Pool2022-04-11011 April 2022 Registration of Independent Spent Fuel Installation Storage Cask and Notification of Permanent Removal of All Spent Fuel Assemblies from the Spent Fuel Pool NG-22-0042, Registration of Independent Spent Fuel Installation Storage Casks2022-04-0808 April 2022 Registration of Independent Spent Fuel Installation Storage Casks NG-22-0041, and Independent Spent Fuel Storage Installation, 2022 Annual Decommissioning and Spent Fuel Management Funding Status Report2022-03-31031 March 2022 and Independent Spent Fuel Storage Installation, 2022 Annual Decommissioning and Spent Fuel Management Funding Status Report NG-22-0031, 2021 Annual Exposure Report - Form 5s2022-03-23023 March 2022 2021 Annual Exposure Report - Form 5s NG-22-0030, Registration of Independent Spent Fuel Installation Storage Casks2022-03-23023 March 2022 Registration of Independent Spent Fuel Installation Storage Casks ML22080A1822022-03-22022 March 2022 Letter to B. Coffey from M. Doell - Duane Arnold ISFSI QAPD RAI Letter L-2022-012, Florida Power & Light Company Nuclear Property Insurance - 10 CFR 50.54(w)(3)2022-03-16016 March 2022 Florida Power & Light Company Nuclear Property Insurance - 10 CFR 50.54(w)(3) ML22059A7462022-03-10010 March 2022 ISFSI-Only Physical Security Plan License Amendment Approval NG-22-0025, Registration of Independent Spent Fuel Installation Storage Casks2022-03-0808 March 2022 Registration of Independent Spent Fuel Installation Storage Casks IR 05000331/20220012022-03-0404 March 2022 Subject: NRC Inspection Report Nos. 05000331/2022001(DNMS) and 07200032/2022001(DNMS) 2024-09-04
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24193A2432024-07-12012 July 2024 – Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan ML22005A0862022-01-0404 January 2022 1-4-2022 Email Communication to Duane Arnold Regarding Its ISFSI Related Exemption Request on Supplemental Information Needed ML21335A0712021-12-0101 December 2021 Request for Additional Information - Duane Arnold Energy Center ISFSI Only Emergency Plan ML21335A0702021-12-0101 December 2021 Cover Letter to B. Coffey from K. Conway - Duane Arnold Energy Center RAI Re License Amendment Request for ISFSI Only Emergency Plan ML21250A3002021-09-0808 September 2021 Defueled Physical Security Plan RAI Cover Letter ML21006A4052021-01-0606 January 2021 NRR E-mail Capture - Final RAI - Duane Arnold - Post-Shutdown Decommissioning Activities Report ML20316A0212020-11-10010 November 2020 NRR E-mail Capture - Final RAI - Duane Arnold - Duane Arnold Amendment for Proposed Defueled EP and EAL Scheme ML20153A3772020-05-28028 May 2020 NRR E-mail Capture - Request for Additional Information - Duane Arnold Energy Center Quality Assurance Topical Report (FPL-3) - EPID L-2020-LLQ-0002) ML20141L8132020-05-19019 May 2020 NRR E-mail Capture - Request for Additional Information - Duane Arnold Energy Center (DAEC) - Exemption Request for Security Training Requirements Due to COVID-19 Pandemic - EPID L-2020-LLE-0042 to 45, L-2020-LLE-0051 ML20133K0482020-05-14014 May 2020 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML20127H8662020-05-0505 May 2020 NRR E-mail Capture - Duane Arnold Energy Center (DAEC) - Request for Additional Information (RAI) - Request for Exemptions from 10 CFR 50.82(a)(8)(i)(A) and 1O CFR 50.75(h)(1)(iv) - EPID L-2020-LLE-0011 ML19280A0352019-10-0404 October 2019 NRR E-mail Capture - Final - RAI Related to License Amendment Request (TSCR-182) for Proposed Changes to the Emergency Plan for Permanently Defueled Conditions at Duane Arnold Energy Center (DAEC) - L-2019-LLA-0075 ML18283B0522018-10-0909 October 2018 NRR E-mail Capture - Final Second Round - Request for Additional Information (RAI) - Duane Arnold Energy Center (DAEC) - LAR TSCR-166, Adoption of EAL Scheme Pursuant to NEI 99-01 - EPID L-2017-LLA-0420 ML18255A2922018-09-11011 September 2018 NRR E-mail Capture - Draft Second Round - Request for Additional Information (RAI) - Duane Arnold Energy Center (DAEC) - LAR TSCR-166, Adoption of EAL Scheme Pursuant to NEI 99-01 - EPID L-2017-LLA-0420 ML18247A2002018-08-21021 August 2018 E-Mailed Request for Information for Duane Arnold, Dated 08/21/18 (DRS-M.Holmberg) ML18166A2982018-06-15015 June 2018 NRR E-mail Capture - Draft Request for Additional Information (RAI) - Duane Arnold Energy Center (DAEC) - LAR TSCR-166, Adoption of EAL Scheme Pursuant to NEI 99-01 - EPID L-2017-LLA-0420 ML18088A0102018-03-28028 March 2018 NRR E-mail Capture - Final RAI for Duane Arnold (DAEC) 5th-10 Year ISI (RR-05) ML18058A0522018-02-27027 February 2018 Enclosurequest for Additional Information (Letter: RAI Regarding Florida Power and Light/Nextera Decommissioning Funding Plan Updates for St. Lucie, Units 1 & 2; Seabrook Station; Duane Arnold Energy Center; and Point Beach, Units 1 and 2) ML18037B0032018-02-0606 February 2018 NRR E-mail Capture - Draft Request for Additional Information - Duane Arnold Energy Center (DAEC) - License Amendment Request (TSCR-170), Revision to Technical Specification 3.5.1, ECCS-Operating - EPID L-2017-LLA-0288 ML17347A8752017-12-12012 December 2017 NRR E-mail Capture - Second Round of Request for Additional Information - Duane Arnold Energy Center (DAEC) - LAR to Adopt TST-542, Revision 2, Reactor Pressure Vessel Water Inventory Control - CAC No. MF9829 ML17277A3652017-10-0404 October 2017 NRR E-mail Capture - Final Request for Additional Information - Duane Arnold - Application to Revise Technical Specifications to Adopt TSTF-542, Revision 2, Reactor Pressure Vessel Water Inventory Control - CAC No. MF9829 ML17240A0082017-08-25025 August 2017 NRR E-mail Capture - Request for Additional Information - Duane Arnold Energy Center (DAEC) - Fifth Ten Year Service Inspection Interval - Relief Request No. RR-04, Rev. 0 - Proposed Alternative for Seal Weld Procedure Qualification - MF937 ML17220A3332017-08-0808 August 2017 NRR E-mail Capture - Request for Additional Information - Duane Arnold Energy Center - Relief Request No. RR-03 - Alternative Requirements for Nozzle Inner Radius and Nozzle-To-Shell Welds - CAC No. MF9374 ML17159A7962017-06-0707 June 2017 17 Duane Arnold Energy Center - Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection (Mxg) ML17068A0632017-03-0808 March 2017 NRR E-mail Capture - Final - Request for Additional Information (RAI) - Duane Arnold Energy Center (DAEC) - Revision to Staff Augmentation Times in the Duane Arnold Energy Center (DAEC) Emergency Plan (Eplan) - MF8390 ML16333A4622016-11-28028 November 2016 NRR E-mail Capture - Final Request for Additional Information - Duane Arnold Energy Center - LAR - SFP Criticality - MF7486 ML16326A0092016-11-18018 November 2016 NRR E-mail Capture - Request for Additional Information Re. Nextera/Fpl LAR to Adopt TSTF-545 - CACs MF8203, MF8204, MF8208, and MF8209 ML16313A0742016-11-0808 November 2016 NextEra Audit Plan Nov 2016 (DAEC SFP Criticality LAR) ML16075A0032016-03-14014 March 2016 NRR E-mail Capture - Request for Additional Information - Duane Arnold Energy Center - LAR to Reduce the Reactor Steam Dome Pressure Specified in the Technical Specifications 2.1.1, Reactor Core Safety Limits - MF6618 ML16074A3142016-03-14014 March 2016 NRR E-mail Capture - Second Round RAIs - Duane Arnold Energy Center - LAR (TSCR-143) to Extend Containment Leakage Test Frequency - MF6619 ML16021A0122016-01-21021 January 2016 Request for Additional Information by the Containment & Ventilation Branch and PRA Licensing Branch License Amendment Request - Extension of the 10 CFR 50 Appendix J Containment Type a & Type C Test Intervals ML16022A0092016-01-21021 January 2016 NRR E-mail Capture - Request for Additional Information - LAR to Revise and Relocate Pressure and Temperature Limit Curves to a Pressure and Temperature Limits Report - MF6617 ML16014A6962016-01-0707 January 2016 E-Mail: Duane Arnold, MOD/50.59 Inspection Request for Information (Jsp) ML16005A6082015-12-24024 December 2015 E-Mail: Duane Arnold Request for Information; December 24, 2015 (AAS) ML15175A0652015-06-23023 June 2015 Ltr. 06/23/15 Duane Arnold Energy Center - Notification of an NRC Triennial Heat Sink Performance Inspection and Request for Information Inspection Report 05000331/2015003 (Axd) ML14057A7562014-02-25025 February 2014 14 Duane Arnold CDBI Request for Information ML14031A1462014-01-29029 January 2014 Update to NextEra Energy Duane Arnold, Llc'S Response to NRC Request for Additional Information Associated with Near-Term Task Force Recommendations ML13323B4432013-11-26026 November 2013 Interim Staff Evaluation and Request for Additional Information Regarding the Overall Integrated Plan for Implementation of Order EA-12-051, Reliable Spent Fuel Pool Instrumentation ML13255A1982013-09-16016 September 2013 Request for Additional Information Regarding Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) ML13175A3932013-06-27027 June 2013 Request for Additional Information for Review Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 ML13154A5112013-06-0404 June 2013 Rai'S Following Ifib Analysis of NextEra Energy'S 2013 Decommissioning Funding Status Reports for Duane Arnold Energy Center and Point Beach Units 1 and 2 ML12107A0592012-04-11011 April 2012 NRR E-mail Capture - ME7246 - DAEC - Request for Additional Information (RAI) Relief Requests NDR-R003, R010, R011, R014, R015 ML12056A0502012-03-12012 March 2012 Enclosure 4 - Recommendation 2.3: Flooding ML12056A0482012-03-12012 March 2012 Enclosure 2 - Recommendation 2.1: Flooding ML12056A0512012-03-12012 March 2012 Enclosure 5 - Recommendation 9.3: Emergency Preparedness ML12056A0492012-03-12012 March 2012 Enclosure 3 - Recommendation 2.3: Seismic ML12056A0472012-03-12012 March 2012 Enclosure 1 - Recommendation 2.1: Seismic ML1201203182012-01-17017 January 2012 Request for Additional Information Amendment to Change Emergency Action Levels ML12011A0602012-01-0404 January 2012 NRR E-mail Capture - ME6508 - DAEC - Emergency Action Level (EAL) Changes ML1132105812011-11-28028 November 2011 Request for Additional Information Regarding 60-Day Response to Bulletin 2011-01, Mitigating Strategies. 2024-07-12
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE RD. SUIT E 210 LISLE, IL 60532
-4352 February 25, 2014 Mr. Richard L. Anderson Vice President NextEra Energy Duane Arnold, LLC 3277 DAEC Road Palo, IA 52324-9785
SUBJECT:
DUANE ARNOLD ENERGY CENTER REQUEST FOR INFORMATION FOR AN NRC TRIENNIAL BASELINE COMPONENT DESIGN BASES INSPECTION (CDBI) INSPECTION REPORT 05000 331/201400 8
Dear Mr. Anderson:
On Ma y 19, 201 4 , the U. S. Nuclear Regulatory Commission (NRC) will begin a triennial baseline Component Design Bases Inspection (CDBI) at Duane Arnold Energy Center
. A team of six inspectors will perform this 3-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. The components to be reviewed during this baseline inspection will be identified during the in-office preparation week that occurs prior to th e 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 you r 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:
Ma y 19, 201 4; June 02, 201 4; and June 16, 201 4 The team will be preparing for the inspection, mainly during the week of May 1 2, 201 4, as discussed in the attached enclosure.
R. Anderson Experience with previous baseline design inspections of similar depth and length has shown that th is 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 31, 201 4. By April 18, 2014, the lead inspector will communicate the initial selected set of approximately 20 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 May 7, 2014. 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 May 19, 2014. 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 Benny Jose. We understand that our licensing contact for this inspection is Robert Murrell 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) 829-97 5 6 or via e-mail at benny.jose@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.
R. Anderson In accordance with Title 10, Code of Federal Regulations (CFR) "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 System (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading
-rm/adams.html (the Public Electronic Reading Room).
Sincerely, /RA/
Stuart Sheldon , Acting Chie f Engineering Branch 2 Division of Reactor Safety Docket No s. 50-331;72-032 License No. DPR-49
Enclosure:
Information Request for Component Design Bases Inspection cc w/encl:
Distribution via ListServŽ
INFORMATION REQUEST FOR COMPONENT DESIGN BASES INSPECTION Enclosure 1 Inspection Report:
05000 331/201400 8 Inspection Dates:
Ma y 19 - 23, 2014; June 2 - 6, 2014; and June 16 - 20, 2014 Inspection Procedure:
Inspection Procedure 71111.21 "Component Design Bases Inspection" Lead Inspector:
Benny Jose , Senior Reactor Engineer, DRS (630) 829-97 5 6 benny.jose@nrc.gov I. Information Requested Prior to the On
-site Information Gathering/Inspection Week The following information is requested by March 31, 2014 , 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 2 50 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 10 0 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 P SA 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).
INFORMATION REQUEST FOR COMPONENT DESIGN BASES INSPECTION 2 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)
. 9. Electronic copy of the site 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).
INFORMATION REQUEST FOR COMPONENT DESIGN BASES INSPECTION 3 II. Information Requested (for the approx.
20 selected components) to be Available by May 07, 2014. This information will be reviewed by the team in the regional office during the week of May 12, 2014. The 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 three years. 2. The maintenance history (corrective, preventive, and elective) associated with each of the selected components for the last 5 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 those 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 (For example, 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 (for example, 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.
INFORMATION REQUEST FOR COMPONENT DESIGN BASES INSPECTION 4 11. Provide copies of the normal and abnormal operating procedures associated with the selected components and selected scenarios
. 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 Ma y 19, 2014 , O n-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 Ma y 19, 2014. 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 team's 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):
IPE/PRA report
- Procurement documents for components selected (verify retrievable);
Plant procedures (normal, abnormal, emergency, surveillance, etc.); and Vendor manuals.
If you have questions regarding the information requested, please contact the lead inspector.
R. Anderson In accordance with Title 10, Code of Federal Regulations (CFR) "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 System (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading
-rm/adams.html (the Public Electronic Reading Room).
Sincerely, /RA/ Stuart Sheldon, Acting Chie f Engineering Branch 2 Division of Reactor Safety Docket No.
50-331;72-032 License No. DPR-49
Enclosure:
Information Request for Component Design Bases Inspection (CDBI) cc w/encl:
Distribution via ListServŽ DISTRIBUTION
- Ernesto Quinones RidsNrrDorlLpl3
-1 Resource RidsNrrPMDuaneArnold Resource RidsNrrDirsIrib Resource Cynthia Pederson Darrell Roberts Steven Orth Allan Barker Carole Ariano Linda Linn DRPIII DRSIII Patricia Buckley DOCUMENT NAME: G:\DRSIII\DRS\Work in Progress
\Ltr 022514 DAEC CDBI RFI BJ.docx
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