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| issue date = 05/25/2012
| issue date = 05/25/2012
| title = IR 05000346-12-008 (Drs), on 05/24/12 Davis-Besse Nuclear Power Station Request for Information for an NRC Triennial Baseline Component Design Bases Inspection (CDBI) Inspection
| title = IR 05000346-12-008 (Drs), on 05/24/12 Davis-Besse Nuclear Power Station Request for Information for an NRC Triennial Baseline Component Design Bases Inspection (CDBI) Inspection
| author name = Stone A M
| author name = Stone A
| author affiliation = NRC/RGN-III/DRS/EB2
| author affiliation = NRC/RGN-III/DRS/EB2
| addressee name = Allen B
| addressee name = Allen B
Line 14: Line 14:
| page count = 8
| page count = 8
}}
}}
See also: [[followed by::IR 05000346/2012008]]
See also: [[see also::IR 05000346/2012008]]


=Text=
=Text=
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE ROAD, SUITE 210 LISLE, IL 60532-4352 May 25, 2012 Mr. Barry Allen Site Vice President FirstEnergy Nuclear Operating Company Davis-Besse Nuclear Power Station 5501 North State Route 2, Mail Stop A-DB-3080 Oak Harbor, OH 43449-9760 SUBJECT: DAVIS-BESSE NUCLEAR POWER STATION REQUEST FOR INFORMATION FOR AN NRC TRIENNIAL BASELINE COMPONENT DESIGN BASES INSPECTION (CDBI) INSPECTION REPORT 05000346/2012008 (DRS) Dear Mr. Allen: On August 13, 2012, the U.S. Nuclear Regulatory Commission (NRC) will begin a triennial baseline Component Design Bases Inspection (CDBI) at Davis-Besse Nuclear Power Station. 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 the first on-site inspection week. In addition, operating experience issues, associated with the component samples, will also be selected for review.   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: August 13 - 17, 2012;   August 27 - 31, 2012; and   September 10 - 14, 2012. The team will be preparing for the inspection, mainly during the week of August 6, 2012, as discussed in the attached enclosure. A Region III Senior Reactor Analyst may accompany the inspection team during the week of August 13, 2012, to review probabilistic risk assessment data, and assist in identifying risk significant components and/or specific component functions, which will be reviewed during the inspection. 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:
{{#Wiki_filter:UNITED STATES
  B. Allen -2-  The first group lists information necessary for our initial inspection scoping activities.  This information should be provided to the lead inspector no later than July 2, 2012.  By July 13, 2012, 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 August 1, 2012.  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 13, 2012.  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.  If you have questions regarding the information requested, please contact Mr. Dunlop 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
                            NUCLEAR REGULATORY COMMISSION
currently valid Office of Management and Budget control number. In accordance with 10 CFR 2.390 of the NRC's "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 (PARS) component of NRC's document system (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). Sincerely,  /RA/ 
                                              REGION III
                                2443 WARRENVILLE ROAD, SUITE 210
Ann Marie Stone, Chief Engineering Branch 2 Division of Reactor Safety  Docket No. 50-346 License No. NPF-3 Enclosure: INFORMATION REQUEST FOR COMPONENT DESIGN BASES INSPECTION cc w/encl: Distribution via ListServŽ
                                        LISLE, IL 60532-4352
INFORMATION REQUEST FOR COMPONENT DESIGN BASES INSPECTION 1 Enclosure Inspection Report:  05000346/2012008(DRS) Inspection Dates:  August 13 - 17, 2012; August 27 - 31, 2012; and      September 10 - 14, 2012 Inspection Procedure:  Inspection Procedure (IP) 71111.21 "Component Design Bases Inspection" Lead Inspector:  Andrew Dunlop, Lead Inspector  (630) 829-9726      andrew.dunlop@nrc.gov I. Information Requested Prior to the On-site Information Gathering/Inspection Week The following information is requested by July 2, 2012, 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
                                            May 25, 2012
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 5 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
Mr. Barry Allen
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).
Site Vice President
INFORMATION REQUEST FOR COMPONENT DESIGN BASES INSPECTION 2 Enclosure 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 3 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 5 years at your facility. 17. List of Root Cause Evaluations associated with component failures or design issues
FirstEnergy Nuclear Operating Company
initiated/completed in the last 5 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).
Davis-Besse Nuclear Power Station
INFORMATION REQUEST FOR COMPONENT DESIGN BASES INSPECTION 3 Enclosure II. Information Requested (For The Approx. 20 Selected Components) to be Available By August 1, 2012, (Will Be Reviewed by the Team in the Regional Office During the Week of August 6, 2012) 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 four 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). 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 (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. 11. Provide copies of the normal and abnormal operating procedures associated with the selected components and selected scenarios. 
5501 North State Route 2, Mail Stop A-DB-3080
INFORMATION REQUEST FOR COMPONENT DESIGN BASES INSPECTION 4 Enclosure 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 August 13, 2012, On-Site (for final selected Components)  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 August 6, 2012.  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. The lead inspector for this inspection is Andrew Dunlop.  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.
Oak Harbor, OH 43449-9760
  B. Allen -2-  The first group lists information necessary for our initial inspection scoping activities.  This information should be provided to the lead inspector no later than July 2, 2012.  By July 13, 2012, 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 August 1, 2012.  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 13, 2012.  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.  If you have questions regarding the information requested, please contact Mr. Dunlop 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
SUBJECT:         DAVIS-BESSE NUCLEAR POWER STATION REQUEST FOR INFORMATION
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 10 CFR 2.390 of the NRC's "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 (PARS) component of NRC's document system (ADAMS), accessible from the NRC Web site at
                FOR AN NRC TRIENNIAL BASELINE COMPONENT DESIGN BASES
http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). Sincerely, 
                INSPECTION (CDBI) INSPECTION REPORT 05000346/2012008 (DRS)
Dear Mr. Allen:
/RA/ 
On August 13, 2012, the U.S. Nuclear Regulatory Commission (NRC) will begin a triennial
Ann Marie Stone, Chief Engineering Branch 2 Division of Reactor Safety  Docket No. 50-346 License No. NPF-3 cc w/encl: Distribution via ListServŽ DISTRIBUTION: See next page DOCUMENT NAME:  G:\DRSIII\DRS\Work in Progress\Ltr 052412 DavisBesse CDBI RFI AXD.docx  -Publicly Available  -Sensitive To receive a copy of this document, indicate in the concurrence box "C" = Copy without attach/encl "E" = Copy with attach/encl "N" = No copy OFFICE RIII  RIII        NAME ADunlop:ls AMStone    DATE 05/24/12 05/24/12    OFFICIAL RECORD COPY
baseline Component Design Bases Inspection (CDBI) at Davis-Besse Nuclear Power Station. A
  Letter to Mr. Barry Allen from Ms. Ann Marie Stone dated May 24, 2012. SUBJECT: DAVIS-BESSE NUCLEAR POWER STATION  REQUEST FOR INFORMATION FOR AN NRC TRIENNIAL BASELINE COMPONENT DESIGN BASES INSPECTION (CDBI) INSPECTION REPORT 05000346/2012008 (DRS) DISTRIBUTION: RidsNrrDorlLpl3-2 Resource Shawn Williams  RidsNrrPMDavisBesse Resource RidsNrrDirsIrib Resource Chuck Casto Cynthia Pederson Steven Orth Jared Heck Allan Barker Carole Ariano Linda Linn DRPIII DRSIII Patricia Buckley Tammy Tomczak 
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 the
first on-site inspection week. In addition, operating experience issues, associated with the
component samples, will also be selected for review.
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: August 13 - 17, 2012;
                      August 27 - 31, 2012; and
                      September 10 - 14, 2012.
The team will be preparing for the inspection, mainly during the week of August 6, 2012, as
discussed in the attached enclosure. A Region III Senior Reactor Analyst may accompany the
inspection team during the week of August 13, 2012, to review probabilistic risk assessment
data, and assist in identifying risk significant components and/or specific component functions,
which will be reviewed during the inspection.
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:


B. Allen                                          -2-
*    The first group lists information necessary for our initial inspection scoping activities.
    This information should be provided to the lead inspector no later than July 2, 2012. By
    July 13, 2012, 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 August 1, 2012. 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 13, 2012. 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. If you have questions regarding the
information requested, please contact Mr. Dunlop 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.
In accordance with 10 CFR 2.390 of the NRCs 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 (PARS) component of NRCs document system (ADAMS),
accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public
Electronic Reading Room).
                                              Sincerely,
                                              /RA/
                                              Ann Marie Stone, Chief
                                              Engineering Branch 2
                                              Division of Reactor Safety
Docket No. 50-346
License No. NPF-3
Enclosure:        INFORMATION REQUEST FOR COMPONENT DESIGN BASES INSPECTION
cc w/encl:        Distribution via ListServ'
          INFORMATION REQUEST FOR COMPONENT DESIGN BASES INSPECTION
Inspection Report:              05000346/2012008(DRS)
Inspection Dates:              August 13 - 17, 2012; August 27 - 31, 2012; and
                                September 10 - 14, 2012
Inspection Procedure:          Inspection Procedure (IP) 71111.21 Component Design Bases
                                Inspection
Lead Inspector:                Andrew Dunlop, Lead Inspector
                                (630) 829-9726
                                andrew.dunlop@nrc.gov
I.    Information Requested Prior to the On-site Information Gathering/Inspection Week
      The following information is requested by July 2, 2012, 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 5 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).
                                                    1                                        Enclosure
  INFORMATION REQUEST FOR COMPONENT DESIGN BASES INSPECTION
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 3 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 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/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                                    Enclosure
      INFORMATION REQUEST FOR COMPONENT DESIGN BASES INSPECTION
II. Information Requested (For The Approx. 20 Selected Components) to be Available
    By August 1, 2012, (Will Be Reviewed by the Team in the Regional Office During the
    Week of August 6, 2012)
    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 four 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).
    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 (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.
    11.    Provide copies of the normal and abnormal operating procedures associated with
            the selected components and selected scenarios.
                                                  3                                        Enclosure
          INFORMATION REQUEST FOR COMPONENT DESIGN BASES INSPECTION
      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 August 13, 2012, On-Site (for final selected
      Components)
      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 August 6, 2012.
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):
                *  IPE/PRA report;
                *  Procurement documents for components selected (verify retrievable);
                *  Plant procedures (normal, abnormal, emergency, surveillance, etc.); and
                *  Vendor manuals.
The lead inspector for this inspection is Andrew Dunlop. 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.
                                                    4                                      Enclosure
B. Allen                                                                      -2-
*    The first group lists information necessary for our initial inspection scoping activities. This information should
      be provided to the lead inspector no later than July 2, 2012. By July 13, 2012, 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 August 1, 2012. 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 13, 2012. 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. If you have questions regarding the information
requested, please contact Mr. Dunlop 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.
In accordance with 10 CFR 2.390 of the NRCs 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 (PARS) component of NRCs document system (ADAMS), accessible from the NRC Web site at
http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
                                                                          Sincerely,
                                                                          /RA/
                                                                          Ann Marie Stone, Chief
                                                                          Engineering Branch 2
                                                                          Division of Reactor Safety
Docket No. 50-346
License No. NPF-3
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To receive a copy of this document, indicate in the concurrence box "C" = Copy without attach/encl "E" = Copy with attach/encl "N" = No copy
OFFICE                  RIII                      RIII
NAME                    ADunlop:ls                AMStone
DATE                    05/24/12                  05/24/12
                                                            OFFICIAL RECORD COPY
Letter to Mr. Barry Allen from Ms. Ann Marie Stone dated May 24, 2012.
SUBJECT:      DAVIS-BESSE NUCLEAR POWER STATION REQUEST FOR INFORMATION
              FOR AN NRC TRIENNIAL BASELINE COMPONENT DESIGN BASES
              INSPECTION (CDBI) INSPECTION REPORT 05000346/2012008 (DRS)
DISTRIBUTION:
RidsNrrDorlLpl3-2 Resource
Shawn Williams
RidsNrrPMDavisBesse Resource
RidsNrrDirsIrib Resource
Chuck Casto
Cynthia Pederson
Steven Orth
Jared Heck
Allan Barker
Carole Ariano
Linda Linn
DRPIII
DRSIII
Patricia Buckley
Tammy Tomczak
}}
}}

Latest revision as of 03:09, 12 November 2019

IR 05000346-12-008 (Drs), on 05/24/12 Davis-Besse Nuclear Power Station Request for Information for an NRC Triennial Baseline Component Design Bases Inspection (CDBI) Inspection
ML12146A423
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 05/25/2012
From: Ann Marie Stone
NRC/RGN-III/DRS/EB2
To: Allen B
FirstEnergy Nuclear Operating Co
References
IR-12-008
Download: ML12146A423 (8)


See also: IR 05000346/2012008

Text

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION III

2443 WARRENVILLE ROAD, SUITE 210

LISLE, IL 60532-4352

May 25, 2012

Mr. Barry Allen

Site Vice President

FirstEnergy Nuclear Operating Company

Davis-Besse Nuclear Power Station

5501 North State Route 2, Mail Stop A-DB-3080

Oak Harbor, OH 43449-9760

SUBJECT: DAVIS-BESSE NUCLEAR POWER STATION REQUEST FOR INFORMATION

FOR AN NRC TRIENNIAL BASELINE COMPONENT DESIGN BASES

INSPECTION (CDBI) INSPECTION REPORT 05000346/2012008 (DRS)

Dear Mr. Allen:

On August 13, 2012, the U.S. Nuclear Regulatory Commission (NRC) will begin a triennial

baseline Component Design Bases Inspection (CDBI) at Davis-Besse Nuclear Power Station. 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 the

first on-site inspection week. In addition, operating experience issues, associated with the

component samples, will also be selected for review.

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: August 13 - 17, 2012;

August 27 - 31, 2012; and

September 10 - 14, 2012.

The team will be preparing for the inspection, mainly during the week of August 6, 2012, as

discussed in the attached enclosure. A Region III Senior Reactor Analyst may accompany the

inspection team during the week of August 13, 2012, to review probabilistic risk assessment

data, and assist in identifying risk significant components and/or specific component functions,

which will be reviewed during the inspection.

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:

B. Allen -2-

  • The first group lists information necessary for our initial inspection scoping activities.

This information should be provided to the lead inspector no later than July 2, 2012. By

July 13, 2012, 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 August 1, 2012. 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 13, 2012. 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. If you have questions regarding the

information requested, please contact Mr. Dunlop 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.

In accordance with 10 CFR 2.390 of the NRCs 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 (PARS) component of NRCs document system (ADAMS),

accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public

Electronic Reading Room).

Sincerely,

/RA/

Ann Marie Stone, Chief

Engineering Branch 2

Division of Reactor Safety

Docket No. 50-346

License No. NPF-3

Enclosure: INFORMATION REQUEST FOR COMPONENT DESIGN BASES INSPECTION

cc w/encl: Distribution via ListServ'

INFORMATION REQUEST FOR COMPONENT DESIGN BASES INSPECTION

Inspection Report: 05000346/2012008(DRS)

Inspection Dates: August 13 - 17, 2012; August 27 - 31, 2012; and

September 10 - 14, 2012

Inspection Procedure: Inspection Procedure (IP) 71111.21 Component Design Bases

Inspection

Lead Inspector: Andrew Dunlop, Lead Inspector

(630) 829-9726

andrew.dunlop@nrc.gov

I. Information Requested Prior to the On-site Information Gathering/Inspection Week

The following information is requested by July 2, 2012, 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 5 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).

1 Enclosure

INFORMATION REQUEST FOR COMPONENT DESIGN BASES INSPECTION

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 3 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 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/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 Enclosure

INFORMATION REQUEST FOR COMPONENT DESIGN BASES INSPECTION

II. Information Requested (For The Approx. 20 Selected Components) to be Available

By August 1, 2012, (Will Be Reviewed by the Team in the Regional Office During the

Week of August 6, 2012)

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 four 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).

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 (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.

11. Provide copies of the normal and abnormal operating procedures associated with

the selected components and selected scenarios.

3 Enclosure

INFORMATION REQUEST FOR COMPONENT DESIGN BASES INSPECTION

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 August 13, 2012, On-Site (for final selected

Components)

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 August 6, 2012.

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):

  • IPE/PRA report;
  • Procurement documents for components selected (verify retrievable);
  • Plant procedures (normal, abnormal, emergency, surveillance, etc.); and
  • Vendor manuals.

The lead inspector for this inspection is Andrew Dunlop. 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.

4 Enclosure

B. Allen -2-

  • The first group lists information necessary for our initial inspection scoping activities. This information should

be provided to the lead inspector no later than July 2, 2012. By July 13, 2012, 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 August 1, 2012. 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 13, 2012. 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. If you have questions regarding the information

requested, please contact Mr. Dunlop 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.

In accordance with 10 CFR 2.390 of the NRCs 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 (PARS) component of NRCs document system (ADAMS), accessible from the NRC Web site at

http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,

/RA/

Ann Marie Stone, Chief

Engineering Branch 2

Division of Reactor Safety

Docket No. 50-346

License No. NPF-3

cc w/encl: Distribution via ListServ'

DISTRIBUTION:

See next page

DOCUMENT NAME: G:\DRSIII\DRS\Work in Progress\Ltr 052412 DavisBesse CDBI RFI AXD.docx

Publicly Available Non-Publicly Available Sensitive Non-Sensitive

To receive a copy of this document, indicate in the concurrence box "C" = Copy without attach/encl "E" = Copy with attach/encl "N" = No copy

OFFICE RIII RIII

NAME ADunlop:ls AMStone

DATE 05/24/12 05/24/12

OFFICIAL RECORD COPY

Letter to Mr. Barry Allen from Ms. Ann Marie Stone dated May 24, 2012.

SUBJECT: DAVIS-BESSE NUCLEAR POWER STATION REQUEST FOR INFORMATION

FOR AN NRC TRIENNIAL BASELINE COMPONENT DESIGN BASES

INSPECTION (CDBI) INSPECTION REPORT 05000346/2012008 (DRS)

DISTRIBUTION:

RidsNrrDorlLpl3-2 Resource

Shawn Williams

RidsNrrPMDavisBesse Resource

RidsNrrDirsIrib Resource

Chuck Casto

Cynthia Pederson

Steven Orth

Jared Heck

Allan Barker

Carole Ariano

Linda Linn

DRPIII

DRSIII

Patricia Buckley

Tammy Tomczak