ML16099A305: Difference between revisions
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| number = ML16099A305 | | number = ML16099A305 | ||
| issue date = 04/08/2016 | | issue date = 04/08/2016 | ||
| title = | | title = Request for Information for an NRC Triennial Baseline Component Design Bases Inspection; Inspection Report 05000341/2016007 | ||
| author name = Feliz-Adorno N J | | author name = Feliz-Adorno N J | ||
| author affiliation = NRC/RGN-III/DRS/EB2 | | author affiliation = NRC/RGN-III/DRS/EB2 | ||
Revision as of 12:03, 28 January 2019
| ML16099A305 | |
| Person / Time | |
|---|---|
| Site: | Fermi |
| Issue date: | 04/08/2016 |
| From: | Feliz-Adorno N J NRC/RGN-III/DRS/EB2 |
| To: | Fessler P DTE Energy |
| References | |
| IR 2016007 | |
| Download: ML16099A305 (8) | |
See also: IR 05000341/2016007
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE RD. SUITE 210 LISLE, IL 60532-4352 April 8, 2016 Mr. Paul Fessler Chief Nuclear Officer DTE Energy Company Fermi 2 - 210 NOC 6400 North Dixie Highway Newport, MI 48166 SUBJECT: FERMI POWER PLANT, UNIT 2 - REQUEST FOR INFORMATION FOR AN NRC TRIENNIAL BASELINE COMPONENT DESIGN BASES INSPECTION; INSPECTION REPORT 05000341/2016007 Dear Mr. Fessler: On August 1, 2016, the U. S. Nuclear Regulatory Commission (NRC) will begin a triennial baseline Component Design Bases Inspection at Fermi Power Plant, Unit 2. This inspection will be performed in accordance with NRC Baseline Inspection Procedure 71111.21. The Component Design Bases Inspection 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 in-office preparation week that occurs prior to the first onsite 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 onsite 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 3 weeks onsite. The inspection team will consist of 6 NRC inspectors, of which 5 will focus on engineering/maintenance and 1 on operations. The current inspection schedule is as follows: Onsite weeks: August 1 5, 2016; August 15 19, 2016; and August 29 September 2, 2016. The team will be preparing for the inspection, mainly during the week of July 25 29, 2016, as discussed in the enclosure.
P. Fessler -2- 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 onsite 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 June 13, 2016. By June 24, 2016, 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 July 18, 2016. 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 August 1, 2016. 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 Mr. Néstor J. Féliz Adorno. We understand that our licensing contact for this inspection is Mr. Jason Haas 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 of this letter, its enclosure, and your response (if any) will be available electronically for public
P. Fessler -3- inspection in the NRcomponent 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/ Néstor J. Féliz-Adorno, Senior Reactor Inspector Engineering Branch 2 Division of Reactor Safety Docket No. 50-341 License No. NPF-43 Enclosure: Information Request for Component Design Bases Inspection cc: Distribution via LISTSERV
REQUEST FOR INFORAMTION COMPONENT DESIGN BASES INSPECTION Enclosure Inspection Report: 05000341/2016007 Inspection Dates: August 1 5, 2016; August 15 19, 2016; and August 29 September 2, 2016. Inspection Procedure: IP 71111.21, Lead Inspector: Néstor J. Féliz-Adorno, Senior Reactor Inspector, DRS 630-829-9739 Nestor.Feliz-Adorno@nrc.gov I. Information Requested Prior to the Onsite Information Gathering/Inspection Week The following information is requested by June 13, 2016, 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 eferably on some portable electronic media (e.g., CD-ROM, DVD). The portable electronic media should contain descriptive 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. Include values for Birnbaum Importance, Risk-Reduction Worth, and Fussell-Veseley (as applicable). 2. Risk-ranking of top 100 containment-related components (i.e., Large Early Release Frequency) from your site specific PSA sorted by Risk-Achievement Worth. 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 5 percent to the baseline plant core damage frequency. 5. 6. List of time critical operator actions. Identify those actions that do not have job performance measures. 7. Provide copies of the emergency operating procedures. 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).
REQUEST FOR INFORAMTION COMPONENT DESIGN BASES INSPECTION 2 9. Electronic copy of the site Individual Plant Examination of External Events, if available. 10. Any pre-existing evaluation or list of components and associated calculations with low design margins, (e.g., 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). 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 and Air-Operated Valve 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 PSA). 13. Structures, systems, and components in the Maintenance Rule (a)(1) category for the last 3 years. 14. Site top ten issues list (if applicable). 15. A list of operating experience evaluations for the last 3 years. 16. Information of any common cause failure of components experienced in the last 5 years at your facility. 17. List of Root Cause Evaluations associated with component failures or design issues initiated/completed in the last 5 years. 18. List of open operability evaluations. 19. List of components/systems considered operable but degraded/non-conforming. 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 (electronic copies are preferred). 23. (electronic copies are preferred).
REQUEST FOR INFORAMTION COMPONENT DESIGN BASES INSPECTION 3 II. Information Requested (for the approximate 20 selected components) to be Available by July 18, 2016, (will be reviewed by the team in the Regional office during the week of July 25 29, 2016). This information should be separated for each selected component, especially if provided electronically (e.g., folder with component name that includes calculations, condition reports, and maintenance history). 1. List of condition reports (i.e., corrective action documents) associated with each of the selected components for the last 6 years. 2. The maintenance history (corrective, preventive, and elective) associated with each of the selected components for the last 10 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). [Pipe stress calculations are excluded from this request] 4. System Health Reports, System Descriptions, Design Basis Documents, and/or Training Lesson Plans 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 3 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. -service testing, other vibration monitoring, oil sample results, etc., for valves: stroke time and leak rate results, etc.). 10. Provide copies of the normal and abnormal operating procedures associated with the selected components and selected scenarios. 11. A copy of any internal/external self-assessments and associated corrective action documents generated in preparation for the inspection. 12. Copy of latest completed tests and surveillances for each component, for example:
REQUEST FOR INFORAMTION COMPONENT DESIGN BASES INSPECTION 4 Pumps: comprehensive test, quarterly test, flow balance, etc. Valves: stroke time testing, diagnostic testing, leak testing, interlocks, etc. Heat Exchangers/room coolers: thermal performance, clean/inspect, fan flows, etc. Acceptance criteria basis calculations should also be included. 13. A copy of engineering/operations related audits completed in the last 2 years. III. Additional Information to be Provided on August 1, 2016, Onsite (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 July 25 29, 2016. 2. Schedule of any testing/maintenance activities to be conducted on the selected components during the three on-site inspection weeks. 3. One complete set of Piping and Instrumentation Drawings (paper copies). 4. Major one line electrical drawings (AC and DC) and key diagrams (paper copies). IV. Information Requested to be Provided Throughout the Inspection 1. 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. Reference materials. (make available if needed during all onsite weeks): Individual Plant Examination/Probabilistic Risk Assessment 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.
P. Fessler -3- 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/ Néstor J. Féliz-Adorno, Senior Reactor Inspector Engineering Branch 2 Division of Reactor Safety Docket No. 50-341 License No. NPF-43 Enclosure: Information Request for Component Design Bases Inspection cc: Distribution via LISTSERV DISTRIBUTION: Kimyata MorganButler RidsNrrDorlLpl3-1 Resource RidsNrrPMFermi2 Resource RidsNrrDirsIrib Resource Cynthia Pederson Darrell Roberts Richard Skokowski Allan Barker Carole Ariano Linda Linn DRPIII DRSIII Jim Clay Carmen Olteanu ADAMS Accession Number ML16099A305 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 NFeliz-Adorno:cl DATE 04/08/16 OFFICIAL RECORD COPY