ML18025C015: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
| Line 17: | Line 17: | ||
=Text= | =Text= | ||
{{#Wiki_filter: | {{#Wiki_filter: UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE RD. SUITE 210 LISLE, ILLINOIS 60532-4352 January 24, 2018 Mr. Scott D. Northard Site Vice President Prairie Island Nuclear Generating Plant Northern States Power Company, Minnesota 1717 Wakonade Drive East Welch, MN 55089-9642 SUBJECT: PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2REQUEST FOR INFORMATION FOR AN NRC TRIENNIAL BASELINE DESIGN BASES ASSURANCE INSPECTION (TEAM): INSPECTION REPORT 05000282/2018011; 05000306/2018011 Dear Mr. Northard: On May 7, 2018, the U. S. Nuclear Regulatory Commission (NRC) will begin a Triennial Baseline Design Bases Assurance Inspection (Team) at Prairie Island Nuclear Generating Plant, Units 1 and 2. This inspection will be performed in accordance with NRC Baseline Inspection Procedure 71111.21M. The Design Bases Assurance Inspection focuses on the design, maintenance, and operation of risk significant components with low margin, or associated with an accident scenario, or a specific system. The inspection also monitors the implementation of modifications to structures, systems, and components as modifications to one system may also affect the design bases and functioning of interfacing systems as well as introduce the potential for common cause failures. The components and modifications to be reviewed during this baseline inspection will be identified as part of the preparation for the inspection and finalized during the inoffice 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 2 weeks onsite. The inspection team will consist of 6 NRC inspectors who will focus on engineering/maintenance/operations of the selected components and modifications. The current inspection schedule is as follows: Preparation week: April 30 through May 4, 2018; and Onsite weeks: May 711, 2018, and May 2125, 2018. | ||
S. Northard -2- Experience with previous baseline design/modification 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 March 29, 2018. By April 9, 2018, the lead inspector will communicate the initial selected set of approximately seven components and seven modifications. 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 initially selected components and the modification packages associated with the initially selected modifications, should be provided to the lead inspector at the Regional Office no later than April 25, 2018. 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 7, 2018. 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 Andrew Dunlop. We understand that our licensing contact for this inspection is Frank Sienczak of your organization. If there are any questions about the inspection or the material requested in the enclosure, please contact the lead inspector at 630-829-9726 or via e-mail at Andrew.Dunlop@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. | |||
S. Northard -3- This letter and its enclosure will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR Sincerely, /RA/ Andrew Dunlop, Senior Reactor Engineer Engineering Branch 2 Division of Reactor Safety Docket Nos. 50282, 50306 License Nos. DPR42, DPR60 Enclosure: Design Bases Assurance Inspection Document Request cc: Distribution via LISTSERV | |||
S. Northard -4- Letter to Scott Northard from Andrew Dunlop dated January 24, 2018 SUBJECT: PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2REQUEST FOR INFORMATION FOR AN NRC TRIENNIAL BASELINE DESIGN BASES ASSURANCE INSPECTION (TEAM): INSPECTION REPORT 05000282/2018011; 05000306/2018011 DISTRIBUTION: Jeremy Bowen RidsNrrPMPrairieIsland Resource RidsNrrDorlLpl3 RidsNrrDirsIrib Resource Steven West Darrell Roberts Richard Skokowski Allan Barker Carole Ariano Linda Linn DRPIII DRSIII ROPreports.Resource@nrc.gov ADAMS Accession Number: ML18025C015 OFFICE RIII RIII RIII RIII NAME ADunlop:cl DATE 01/24/18 OFFICIAL RECORD COPY | |||
DESIGN BASES ASSURANCE INSPECTION DOCUMENT REQUEST Enclosure Inspection Report: 05000282/2018011; 05000306/2018011 Inspection Dates: May 711, 2018, and May 2125, 2018 Inspection Procedure: IP 71111.21M, Design Bases Assurance Inspection (Team) Lead Inspector: Andrew Dunlop, Senior Reactor Engineer, DRS 630-829-9726 Andrew.Dunlop@nrc.gov . Information Requested for Selection of Components/Modifications The following information is requested by March 29, 2018, or sooner, to facilitate inspection preparation. If you have any questions regarding this information, please call the lead inspector as soon as possible. (Please provide the information electronically in some portable electronic media (e.g., CD-ROM, DVD, etc.). The portable electronic media should contain descriptive names, and be indexed and hyperlinked to facilitate ease of use. Information in 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. See examples in Inspection Manual Chapter 0609, Appendix H, Table 4.1, Containment-Related SSCs Considered for Large Early Release Frequency Implications. 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. Provide copies of the emergency operating procedures. 7. 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). | |||
DESIGN BASES ASSURANCE INSPECTION DOCUMENT REQUEST 2 8. 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.). 9. Electronic copy of the site Individual Plant Examination of External Events, if available. 10. 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. 11. List of high risk Maintenance Rule systems/components based on engineering or expert panel judgment (i.e., those systems/components not identified high risk in the PSA). 12. Structures, systems, and components (SSCs) in the Maintenance Rule (a)(1) category for the last 3 years. 13. Site top 10 issues list (if applicable). 14. A list of operating experience evaluations for the last 3 years. 15. Information of any common cause failure of components experienced in the last 5 years at your facility. 16. List of Root Cause Evaluations associated with component failures or design issues initiated/completed in the last 5 years. 17. List of open operability evaluations. 18. List of SSCs considered operable but degraded/nonconforming. 19. in the last 3 years. (For the purpose of this inspection, permanent plant modifications include permanent: plant changes, design changes, set point changes, equivalency evaluations, suitability analyses, and commercial grade dedications.) The list should contain the number of each document, title, revision/date, and the affected system. 20. A list of calculation changes that have been issued for use in the last 3 years. 21. Copies of procedures addressing the following: modifications, design changes, set point changes, equivalency evaluations or suitability analyses, commercial grade dedications, and post-modification testing. 22. A list of corrective action documents (open and closed) in the last 3 years that address permanent plant modifications issues, concerns, or processes. These documents should also include the corrective action documents associated with the modification implementation. 23. Current management and engineering organizational chart. | |||
DESIGN BASES ASSURANCE INSPECTION DOCUMENT REQUEST 3 24. Electronic copies of Updated Final Safety Analysis Report, Technical Specifications, Technical Specifications Bases, and Technical Requirements Manual. 25. Major one line electrical drawings (ac and dc) and key diagrams (paper copies). 26. Electronic copy of Piping and Instrumentation Drawings (if available). II. Information Requested (for the approximate 7 selected components and 7 selected modifications) to be Available by April 25, 2018, (will be reviewed by the team in the Regional office during the week of April 30, 2018). This information should be separated for each selected component or modification, especially if provided electronically (e.g., folder with component or modification name that includes calculations, condition reports, maintenance history, etc.). Items 112 are associated with the selected components and item 13 for the selected modifications. 1. List of condition reports (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 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. Trend data on the selected electrical/mechanical comlast 3 -service testing, other vibration monitoring, oil sample results, etc., for valves: stroke time and leak rate results, diagnostic trend data, etc.). | |||
DESIGN BASES ASSURANCE INSPECTION DOCUMENT REQUEST 4 10. Provide copies of the normal and abnormal operating procedures associated with the selected components and selected scenarios. 11. List of time critical or risk significant operator actions associated with components. Identify those actions that do not have job performance measures. 12. Copy of latest completed tests and surveillances for each component, for example: a. Pumps: comprehensive test, quarterly test, flow balance, etc. b. Valves: stroke time testing, diagnostic testing, leak testing, interlocks, etc. c. Heat Exchangers/Room Coolers: thermal performance, clean/inspect, fan flows, etc. d. Components: Technical Specification surveillances. e. Acceptance criteria basis calculations should also be included. 13. For each of the selected modifications, copies of associated documents such as modification package, engineering changes, 50.59 screening or evaluation, calculations, post-modification test packages, corrective action documents, design drawings, preventive maintenance requirements and procedures, etc. 14. A copy of any internal/external self-assessments and associated corrective action documents generated in preparation for the inspection. 15. A copy of engineering/operations related audits completed in the last 2 years. III. Additional Information to be Provided on May 7, 2018, Onsite (for final selected components and modifications) 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 30, 2018. 2. Schedule of any testing/maintenance activities to be conducted on the selected components during the two onsite inspection weeks. IV. Information Requested to be Provided Throughout the Inspection 1. Copies of any corrective action documentquestions 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 by 2:00 p.m. during the inspection to each team member). 3. One complete set of Piping and Instrumentation Drawings (paper copies). | |||
DESIGN BASES ASSURANCE INSPECTION DOCUMENT REQUEST 5 4. Reference materials. (make available if needed during all onsite weeks): a. Individual Plant Examination/ report; b. Procurement documents for components and modifications selected (verify retrievable); c. Plant procedures (normal, abnormal, emergency, surveillance, etc.); and d. Vendor manuals. If you have questions regarding the information requested, please contact the lead inspector | |||
}} | }} | ||
Revision as of 23:21, 20 March 2018
| ML18025C015 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 01/24/2018 |
| From: | Dunlop A Division of Reactor Safety III |
| To: | Northard S D Nuclear Management Co |
| References | |
| IR 2018001 | |
| Download: ML18025C015 (9) | |
See also: IR 05000282/2018011
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE RD. SUITE 210 LISLE, ILLINOIS 60532-4352 January 24, 2018 Mr. Scott D. Northard Site Vice President Prairie Island Nuclear Generating Plant Northern States Power Company, Minnesota 1717 Wakonade Drive East Welch, MN 55089-9642 SUBJECT: PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2REQUEST FOR INFORMATION FOR AN NRC TRIENNIAL BASELINE DESIGN BASES ASSURANCE INSPECTION (TEAM): INSPECTION REPORT 05000282/2018011; 05000306/2018011 Dear Mr. Northard: On May 7, 2018, the U. S. Nuclear Regulatory Commission (NRC) will begin a Triennial Baseline Design Bases Assurance Inspection (Team) at Prairie Island Nuclear Generating Plant, Units 1 and 2. This inspection will be performed in accordance with NRC Baseline Inspection Procedure 71111.21M. The Design Bases Assurance Inspection focuses on the design, maintenance, and operation of risk significant components with low margin, or associated with an accident scenario, or a specific system. The inspection also monitors the implementation of modifications to structures, systems, and components as modifications to one system may also affect the design bases and functioning of interfacing systems as well as introduce the potential for common cause failures. The components and modifications to be reviewed during this baseline inspection will be identified as part of the preparation for the inspection and finalized during the inoffice 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 2 weeks onsite. The inspection team will consist of 6 NRC inspectors who will focus on engineering/maintenance/operations of the selected components and modifications. The current inspection schedule is as follows: Preparation week: April 30 through May 4, 2018; and Onsite weeks: May 711, 2018, and May 2125, 2018.
S. Northard -2- Experience with previous baseline design/modification 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 March 29, 2018. By April 9, 2018, the lead inspector will communicate the initial selected set of approximately seven components and seven modifications. 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 initially selected components and the modification packages associated with the initially selected modifications, should be provided to the lead inspector at the Regional Office no later than April 25, 2018. 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 7, 2018. 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 Andrew Dunlop. We understand that our licensing contact for this inspection is Frank Sienczak of your organization. If there are any questions about the inspection or the material requested in the enclosure, please contact the lead inspector at 630-829-9726 or via e-mail at Andrew.Dunlop@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.
S. Northard -3- This letter and its enclosure will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR Sincerely, /RA/ Andrew Dunlop, Senior Reactor Engineer Engineering Branch 2 Division of Reactor Safety Docket Nos. 50282, 50306 License Nos. DPR42, DPR60 Enclosure: Design Bases Assurance Inspection Document Request cc: Distribution via LISTSERV
S. Northard -4- Letter to Scott Northard from Andrew Dunlop dated January 24, 2018 SUBJECT: PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2REQUEST FOR INFORMATION FOR AN NRC TRIENNIAL BASELINE DESIGN BASES ASSURANCE INSPECTION (TEAM): INSPECTION REPORT 05000282/2018011; 05000306/2018011 DISTRIBUTION: Jeremy Bowen RidsNrrPMPrairieIsland Resource RidsNrrDorlLpl3 RidsNrrDirsIrib Resource Steven West Darrell Roberts Richard Skokowski Allan Barker Carole Ariano Linda Linn DRPIII DRSIII ROPreports.Resource@nrc.gov ADAMS Accession Number: ML18025C015 OFFICE RIII RIII RIII RIII NAME ADunlop:cl DATE 01/24/18 OFFICIAL RECORD COPY
DESIGN BASES ASSURANCE INSPECTION DOCUMENT REQUEST Enclosure Inspection Report: 05000282/2018011; 05000306/2018011 Inspection Dates: May 711, 2018, and May 2125, 2018 Inspection Procedure: IP 71111.21M, Design Bases Assurance Inspection (Team) Lead Inspector: Andrew Dunlop, Senior Reactor Engineer, DRS 630-829-9726 Andrew.Dunlop@nrc.gov . Information Requested for Selection of Components/Modifications The following information is requested by March 29, 2018, or sooner, to facilitate inspection preparation. If you have any questions regarding this information, please call the lead inspector as soon as possible. (Please provide the information electronically in some portable electronic media (e.g., CD-ROM, DVD, etc.). The portable electronic media should contain descriptive names, and be indexed and hyperlinked to facilitate ease of use. Information in 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. See examples in Inspection Manual Chapter 0609, Appendix H, Table 4.1, Containment-Related SSCs Considered for Large Early Release Frequency Implications. 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. Provide copies of the emergency operating procedures. 7. 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).
DESIGN BASES ASSURANCE INSPECTION DOCUMENT REQUEST 2 8. 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.). 9. Electronic copy of the site Individual Plant Examination of External Events, if available. 10. 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. 11. List of high risk Maintenance Rule systems/components based on engineering or expert panel judgment (i.e., those systems/components not identified high risk in the PSA). 12. Structures, systems, and components (SSCs) in the Maintenance Rule (a)(1) category for the last 3 years. 13. Site top 10 issues list (if applicable). 14. A list of operating experience evaluations for the last 3 years. 15. Information of any common cause failure of components experienced in the last 5 years at your facility. 16. List of Root Cause Evaluations associated with component failures or design issues initiated/completed in the last 5 years. 17. List of open operability evaluations. 18. List of SSCs considered operable but degraded/nonconforming. 19. in the last 3 years. (For the purpose of this inspection, permanent plant modifications include permanent: plant changes, design changes, set point changes, equivalency evaluations, suitability analyses, and commercial grade dedications.) The list should contain the number of each document, title, revision/date, and the affected system. 20. A list of calculation changes that have been issued for use in the last 3 years. 21. Copies of procedures addressing the following: modifications, design changes, set point changes, equivalency evaluations or suitability analyses, commercial grade dedications, and post-modification testing. 22. A list of corrective action documents (open and closed) in the last 3 years that address permanent plant modifications issues, concerns, or processes. These documents should also include the corrective action documents associated with the modification implementation. 23. Current management and engineering organizational chart.
DESIGN BASES ASSURANCE INSPECTION DOCUMENT REQUEST 3 24. Electronic copies of Updated Final Safety Analysis Report, Technical Specifications, Technical Specifications Bases, and Technical Requirements Manual. 25. Major one line electrical drawings (ac and dc) and key diagrams (paper copies). 26. Electronic copy of Piping and Instrumentation Drawings (if available). II. Information Requested (for the approximate 7 selected components and 7 selected modifications) to be Available by April 25, 2018, (will be reviewed by the team in the Regional office during the week of April 30, 2018). This information should be separated for each selected component or modification, especially if provided electronically (e.g., folder with component or modification name that includes calculations, condition reports, maintenance history, etc.). Items 112 are associated with the selected components and item 13 for the selected modifications. 1. List of condition reports (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 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. Trend data on the selected electrical/mechanical comlast 3 -service testing, other vibration monitoring, oil sample results, etc., for valves: stroke time and leak rate results, diagnostic trend data, etc.).
DESIGN BASES ASSURANCE INSPECTION DOCUMENT REQUEST 4 10. Provide copies of the normal and abnormal operating procedures associated with the selected components and selected scenarios. 11. List of time critical or risk significant operator actions associated with components. Identify those actions that do not have job performance measures. 12. Copy of latest completed tests and surveillances for each component, for example: a. Pumps: comprehensive test, quarterly test, flow balance, etc. b. Valves: stroke time testing, diagnostic testing, leak testing, interlocks, etc. c. Heat Exchangers/Room Coolers: thermal performance, clean/inspect, fan flows, etc. d. Components: Technical Specification surveillances. e. Acceptance criteria basis calculations should also be included. 13. For each of the selected modifications, copies of associated documents such as modification package, engineering changes, 50.59 screening or evaluation, calculations, post-modification test packages, corrective action documents, design drawings, preventive maintenance requirements and procedures, etc. 14. A copy of any internal/external self-assessments and associated corrective action documents generated in preparation for the inspection. 15. A copy of engineering/operations related audits completed in the last 2 years. III. Additional Information to be Provided on May 7, 2018, Onsite (for final selected components and modifications) 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 30, 2018. 2. Schedule of any testing/maintenance activities to be conducted on the selected components during the two onsite inspection weeks. IV. Information Requested to be Provided Throughout the Inspection 1. Copies of any corrective action documentquestions 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 by 2:00 p.m. during the inspection to each team member). 3. One complete set of Piping and Instrumentation Drawings (paper copies).
DESIGN BASES ASSURANCE INSPECTION DOCUMENT REQUEST 5 4. Reference materials. (make available if needed during all onsite weeks): a. Individual Plant Examination/ report; b. Procurement documents for components and modifications selected (verify retrievable); c. Plant procedures (normal, abnormal, emergency, surveillance, etc.); and d. Vendor manuals. If you have questions regarding the information requested, please contact the lead inspector