ML21033A611: Difference between revisions

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{{#Wiki_filter:February 1, 2021
{{#Wiki_filter:
Mr. Christopher P. Domingos
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 PLANTREQUEST FOR
              INFORMATION FOR AN NRC TRIENNIAL BASELINE DESIGN BASES
              ASSURANCE INSPECTION (TEAM); INSPECTION REPORT 05000282/2021010
              AND 05000306/2021010
Dear Mr. Domingos:
On May 3, 2021, the U.S. Nuclear Regulatory Commission (NRC) will begin a triennial baseline
Design Bases Assurance Inspection (Team) at Prairie Island Nuclear Generating Plant. 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 in-office
preparation week that occurs prior to the first onsite inspection week. In addition, operating
experience issues will 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 two weeks onsite, or remote "onsite" weeks. The inspection team
will consist of six NRC inspectors who will focus on engineering/maintenance/operations of the
selected components and modifications. The current inspection schedule is as follows:
      *  Preparation week:    May 3, 2021, through May 7, 2021
      *  Onsite weeks:        May 10, 2021, through May 14, 2021, and
                                May 24, 2021, through May 28, 2021
 
C. Domingos                                      -2-
Experience with previous baseline design/modification inspections of similar depth and length
has shown 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 8, 2021.
          By March 22, 2021, the lead inspector will communicate the initial selected set of
          components and 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 19, 2021. 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 by the first onsite
          date of May 10, 2021. 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 Michael A. Jones Jr. We understand that our licensing
contact for this inspection is Carol J. Seipp of your organization. If there are any questions
about the inspection or the material requested in the enclosure, contact the lead inspector at
630-829-9745 or via e-mail at Michael.Jones@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.
 
C. Domingos                                    -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 Title 10 of the Code of Federal Regulations, Part 2.390, Public Inspections,
Exemptions, Requests for Withholding.
                                            Sincerely,
                                            /RA/
                                            Michael A. Jones Jr., Reactor Inspector
                                            Engineering Branch 2
                                            Division of Reactor Safety
Docket Nos. 05000282 and 05000306
License Nos. DPR-42 and DPR-60
Enclosure:
Document Request for Design Bases
Assurance Inspection
cc: Distribution via LISTSERV
 
C. Domingos                                  -4-
Letter to Christopher P. Domingos from Michael A. Jones dated February 1, 2021.
SUBJECT: PRAIRIE ISLAND NUCLEAR GENERATING PLANTREQUEST FOR
              INFORMATION FOR AN NRC TRIENNIAL BASELINE DESIGN BASES
              ASSURANCE INSPECTION (TEAM); INSPECTION REPORT 05000282/2021010
              AND 05000306/2021010
DISTRIBUTION:
Jessie Quichocho
Mark Haire
Richard Skokowski
RidsNrrPMPrairieIsland Resource
RidsNrrDorlLpl3
RidsNrrDroIrib Resource
John Giessner
Kenneth OBrien
Jamnes Cameron
Allan Barker
DRPIII
DRSIII
ADAMS Accession Number: ML21033A611
    Publicly Available      Non-Publicly Available      Sensitive        Non-Sensitive
OFFICE      RIII
NAME        MJones:mb via
              e-mail
DATE        02/01/2021
                                OFFICIAL RECORD COPY
 
          DOCUMENT REQUEST FOR DESIGN BASES ASSURANCE INSPECTION
Inspection Report:              05000282/2021010 and 05000306/2021010
Inspection Dates:              May 10, 2021, through May 14, 2021, and
                                May 24, 2021, through May 28, 2021
Inspection Procedures:          Inspection Procedure 71111.21M, Design Bases Assurance
                                Inspection (Team)
Lead Inspector:                Michael A. Jones Jr., Reactor Inspector
                                630-829-9745
                                Michael.Jones@nrc.gov
I.      Information Requested for Selection of Components and Modifications
        The following information is requested by March 8, 2021, or sooner, to facilitate
        inspection preparation. Contact the lead inspector as soon as possible if you have any
        questions regarding this information request. Provide the information electronically in
        pdf files, Excel, or other searchable formats, preferably on some portable electronic
        media (e.g., CD-ROM, DVD). The files 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. Include values for
                  Birnbaum Importance, Risk-Reduction Worth, and Fussell-Veseley (as
                  applicable). Provide any basic event mapping used to develop the ranking of
                  components.
        2.      Risk-ranking of top 250 components from your site-specific PSA sorted by
                  Large Early Release Frequency. Provide any basic event mapping used to
                  develop the ranking of components.
        3.      List of the top 200 cut-sets from your PSA. Provide the descriptions of the
                  basic events in the list of cut-sets.
        4.      List of the top 200 cut-sets for each initiator modeled in the PSA that
                  contributes more than 5 percent to the baseline plant core damage frequency.
        5.      PSA system notebooks and latest PSA summary document.
        6.      Emergency and abnormal 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 and flood zone description.
        8.      Individual Plant Examination of External Events, if available.
                                                                                          Enclosure
 
DOCUMENT REQUEST FOR DESIGN BASES ASSURANCE INSPECTION
9.  If available, 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).
10. List of available design margins in both the open and closed direction for valves
    in the motor-operated valve and air-operated valve programs. Identify the
    safety-related direction and the basis for how the margin was determined.
11. Provide the In-Service Testing Program (IST) document identifying the
    in-scope valves and pumps, and the associated IST Program requirements for
    each component (e.g., IST valve table identifying category, active/passive
    function).
12. List of high-risk Maintenance Rule systems/components based on engineering
    or expert panel judgment (i.e., those systems/components not identified as
    having high risk in the PSA).
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 available.
15. Information of any common cause failure of SSCs experienced in the last
    5 years at your facility.
16. List of Root Cause Evaluations associated with SSCs 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. List of permanent plant modifications to SSCs that are field work complete 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. List of all time critical and/or risk significant operator actions.
22. Procedures addressing the following: modifications, design changes, set
    point changes, equivalency evaluations or suitability analyses, commercial
    grade dedications, and post-modification testing.
23. A list of corrective action documents (open and closed) in the last 3 years that
    address permanent plant modifications issues, concerns, or processes.
                                        2
 
    DOCUMENT REQUEST FOR DESIGN BASES ASSURANCE INSPECTION
    24.    Current management and engineering organizational chart.
    25.    Updated Final Safety Analysis Report, Technical Specifications, Technical
            Specifications Bases, and Technical Requirements Manual. If any of these
            documents is not available electronically, contact the lead inspector.
    26.    Major one-line electrical drawings (ac and dc) and key diagrams. If these
            documents are not available electronically, contact the lead inspector.
    27.    Piping and Instrumentation Drawings, if available electronically. If these
            documents are not available electronically, contact the lead inspector.
    28.    Simplified drawings (e.g., training schematics), if available electronically. If
            these documents are not available electronically, contact the lead inspector.
II. Information Requested to Be Available by April 19, 2021
    This information should be separated for each selected component and modification,
    especially if provided electronically (e.g., a folder for each component and modification
    named after the component or modification that includes the information requested
    below). Items 1-12 are associated with the selected components and item 13 for the
    selected modifications.
    1.      List of corrective action documents associated with each selected component
            for the last 6 years.
    2.      Maintenance history (e.g., corrective, preventive, and elective) associated with
            each selected component for the last 10 years. Identify frequency of
            preventive maintenance activities.
    3.      Aging Management Program documents applicable to each selected
            component.
    4.      Calculations associated with each selected component, excluding data files.
            Pipe stress calculations are excluded from this request.
    5.      System Health Reports (last two performed), System Descriptions, Design
            Basis Documents, and/or Training Lesson Plans associated with each selected
            component.
    6.      A list of modifications, including equivalency evaluations and setpoint changes,
            associated with each selected component. This list should include a
            description of the purpose of the modification. Ensure this list only includes
            completed modifications.
    7.      Operability evaluations (open and closed) for last 3 years associated with each
            selected component and associated corrective action documents.
    8.      Operator work-around evaluations associated with each selected component
            and plans for resolution, if applicable.
                                              3
 
    DOCUMENT REQUEST FOR DESIGN BASES ASSURANCE INSPECTION
    9.    Any open temporary modifications associated with each selected component, if
            applicable.
    10.    Trend data on the selected components performance for the last 3 years (e.g.,
            pumps performance including IST, other vibration monitoring, oil sample
            results).
    11.    Normal operating and alarm response procedures associated with each
            selected component.
    12.    Completed tests and surveillances for each selected component performed
            during the last 3 years. For those tests and surveillances performed at a
            periodicity of greater than 3 years, provide the latest two performed. Include
            the associated acceptance criteria basis calculations.
    13.    For each selected modification, 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, and preventive maintenance requirements and procedures.
    14.    Procedures addressing time critical and/or risk significant operator actions.
            Identify those actions that do not have job performance measures.
    15.    Corrective Action Program procedures, including the operability/functionality
            determination procedure.
    16.    Quality Assurance Program document/procedure.
    17.    Any internal/external self-assessments and associated corrective action
            documents generated in preparation for the inspection.
    18.    Engineering/operations related audits (last two performed).
III. Additional Information to Be Provided Onsite on May 10, 2021
    1.    During the in-office preparation activities, the team will be making final sample
            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 26, 2021.
    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.    Any corrective action documents generated as a result of the teams questions
            during this inspection as the documents are generated.
                                            4
 
        DOCUMENT REQUEST FOR DESIGN BASES ASSURANCE INSPECTION
        2.    List of questions and/or document requests submitted by the team and their
                status (e.g., open, closed) sorted by inspector. Provide daily by 2:30 p.m.
                during the inspection to each inspector. It is recommended to provide the team
                leader with a master list sorted by inspector and each inspector with a list
                containing only the items originated by that inspector.
        3.    If available in hardcopy form, one complete set of Piping and Instrumentation
                Drawings and simplified drawings (e.g., training schematics). If any of these
                documents is not available in hardcopy form, contact the lead inspector.
        4.    Reference materials (make available if needed during all onsite weeks):
                a.      Individual Plant Examination/Probabilistic Risk Assessment report;
                b.      Procurement documents for components and modifications
                        selected (verify retrievable);
                c.      Plant procedures (normal, abnormal, emergency, surveillance, etc.);
                d.      Historical revisions of the Final Safety Analysis Report; and
                e.      Vendor manuals.
Contact the lead inspector if you have questions regarding the information requested.
                                                  5
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Revision as of 07:47, 18 January 2022

Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team); Inspection Report 05000282/2021010 and 05000306/2021010
ML21033A611
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 02/01/2021
From: Michael Jones
Division of Reactor Safety III
To: Domingos C
Northern States Power Company, Minnesota
References
IR 2021010
Download: ML21033A611 (9)


See also: IR 05000282/2021010

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