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{{Adams
#REDIRECT [[IR 05000275/2013007]]
| number = ML13032A314
| issue date = 02/01/2013
| title = IR 05000275-13-007, 05000323-13-007, on 05/20/2013, Diablo Canyon - Notification of NRC Component Design Bases Inspection and Initial RAI
| author name = Farnholtz T
| author affiliation = NRC/RGN-IV/DRS/EB-1
| addressee name = Halpin E
| addressee affiliation = Pacific Gas & Electric Co
| docket = 05000275, 05000323
| license number = DPR-080, DPR-082
| contact person =
| document report number = IR-13-007
| document type = Inspection Plan, Letter
| page count = 7
}}
See also: [[see also::IR 05000275/2013007]]
 
=Text=
{{#Wiki_filter:UNITE D S TATE S
                                  NUC LEAR RE GULATOR Y C OMMI S SI ON
                                                    R E G IO N I V
                                                1600 EAST LAMAR BLVD
                                          AR L I NGTON , TEXAS 7 601 1- 4511
                                                February 1, 2013
Mr. Edward D. Halpin
Senior Vice President and
  Chief Nuclear Officer
Pacific Gas and Electric Company
Diablo Canyon Power Plant
P.O. Box 56, Mail Code 104/6
Avila Beach, CA 93424
SUBJECT:        DIABLO CANYON POWER PLANT - NOTIFICATION OF NRC COMPONENT
                DESIGN BASES INSPECTION (05000275/2013007 and 05000323/2013007)
                AND INITIAL REQUEST FOR INFORMATION
Dear Mr. Halpin:
On May 20, 2013, the NRC will begin a triennial baseline Component Design Bases Inspection
at the Diablo Canyon Power Plant. A seven-person team will perform this inspection using NRC
Inspection Procedure 71111.21, Component Design Bases Inspection.
The inspection focuses on components and operator actions that have high risk and low design
margins. The samples reviewed during this inspection will be identified during an information
gathering visit and during the subsequent in-office preparation week. In addition, a number of
operating experience issues will also be selected for review.
The inspection will include an information gathering site visit by the team leader and a senior
reactor analyst, and 3-weeks of onsite inspection by the team. The inspection will consist of five
NRC inspectors and two contractors, of which six will focus on engineering and one on
operations. The current inspection schedule is as follows:
        Onsite Information Gathering Visit: May 20-23, 2013
        Preparation Week(s): June 3-7, 2013 and June 17-21, 2013
        Onsite Week(s): June 10-15, 2013, June 24-28, 2013, and July 8-12, 2013
The purpose of the information gathering visit is to meet with members of your staff to identify
potential risk-significant components and operator actions. The lead inspector will also request
a tour of the plant with members of your operations staff and probabilistic safety assessment
staff. During the onsite weeks, several days of time will be needed on the plant-referenced
simulator in order to facilitate the development of operator action-based scenarios. Additional
information and documentation needed to support the inspection will be identified during the
inspection, including interviews with engineering managers, engineers, and probabilistic safety
assessment staff.
 
E. Halpin                                      -2-
Our experience with these inspections has shown that they are 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, we have enclosed a request for information
needed for the inspection. The request has been divided into three groups. The first group lists
information necessary for the information gathering visit and for general preparation. This
information should be available to the regional office no later than May 13, 2013. Insofar as
possible, this information should be provided electronically to the lead inspector. Since the
inspection will be concentrated on high risk/low margin components, calculations associated
with your list of high risk components should be available to review during the information
gathering visit to assist in our selection of components based on available design margin.
The second group of documents requested is those items that the team will need access to
during the preparation week in order to finalize the samples to be inspected. The third group
lists information necessary to aid the inspection team in tracking issues identified as a result of
the inspection. It is requested that this information be provided to the lead inspector as the
information is generated during the inspection. Additional requests by inspectors will be made
throughout all three onsite weeks for specific documents needed to complete the review of that
component/selection. 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. In order to facilitate the inspection, we request that a
contact individual be assigned to each inspector to ensure information requests, questions, and
concerns are addressed in a timely manner.
The lead inspector for this inspection is Wayne C. Sifre. We understand that our licensing
engineer contact for this inspection is Mr. Mike McCoy. If there are any questions about the
inspection or the requested materials, please contact the lead inspector by telephone at
817-200-1193 or by e-mail at Wayne.Sifre@nrc.gov.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter will be
made available electronically for public inspection in the NRC Public Document Room or from
the Publicly Available Records (PARS) component of NRCs document system (ADAMS).
ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the
Public Electronic Reading Room).
                                                Sincerely,
                                                /RA/
                                                Thomas R. Farnholtz, Chief
                                                Engineering Branch 1
                                                Division of Reactor Safety
Docket Nos.: 05000275, 05000323
License Nos.: DPR-80, DPR-82
Enclosure:
Component Design Bases Inspection Request for Information
 
E. Halpin                                      -3-
cc: Electronic Distribution for Diablo Canyon Power Plant
Electronic distribution by RIV:
Regional Administrator (Elmo.Collins@nrc.gov)
Deputy Regional Administrator (Steven.Reynolds@nrc.gov)
DRP Director (Kriss.Kennedy@nrc.gov)
Acting DRP Deputy Director (Barry.Westreich@nrc.gov)
Acting DRS Director (Tom.Blount@nrc.gov)
Acting DRS Deputy Director (Jeff.Clark@nrc.gov)
Senior Resident Inspector (Thomas.Hipschman@nrc.gov)
Resident Inspector (Laura.Micewski@nrc.gov)
Branch Chief, DRP/B (Neil.OKeefe@nrc.gov)
Senior Project Engineer, DRP/B (Leonard.Willoughby@nrc.gov)
Project Engineer, DRP/B (David.You@nrc.gov)
DC Administrative Assistant (Madeleine.Arel-Davis@nrc.gov)
Public Affairs Officer (Victor.Dricks@nrc.gov)
Public Affairs Officer (Lara.Uselding@nrc.gov)
Project Manager (Joseph.Sebrosky@nrc.gov)
Branch Chief, DRS/TSB (Ray.Kellar@nrc.gov)
RITS Coordinator (Marisa.Herrera@nrc.gov)
Regional Counsel (Karla.Fuller@nrc.gov)
Technical Support Assistant (Loretta.Williams@nrc.gov)
Congressional Affairs Officer (Jenny.Weil@nrc.gov)
OEMail Resource
RIV/ETA: OEDO (John.Cassidy@nrc.gov)
DRS/TSB STA (Dale.Powers@nrc.gov)
    S:\DRS\REPORTS\Reports Drafts\DC 2013007 RFI WCS.docx        ML13032A314
  SUNSI Review                      Non-Sensitive          Publicly Available
Initials:WCS                          Sensitive              Non-Publicly Available
SRI:EB1                          C:EB1
WSifre                            TFarnholtz
/RA/                              /RA/
1/30/13                          2/1/13
                                    OFFICIAL RECORD COPY
 
                                  Initial Request for Information
                              Component Design Bases Inspection
                                    Diablo Canyon Power Plant
Inspection Report:                      05000275/2013007, 05000323/2013007
Information Gathering Dates:            May 20, 2013
Inspection Dates:                        June 10-13, 2013, June 24-28, 2013, July 8-12, 2013
Inspection Procedure:                    IP 71111.21, Component Design Bases Inspection
Lead Inspector:                          Wayne C. Sifre, Senior Reactor Inspector
I.    Information Requested Prior to Information Gathering Visit (May 20, 2013)
      The following information (Section I of this enclosure) should be sent to the Region IV
      office in hard copy or electronic format (Certrec IMS preferred), to the attention of Wayne
      Sifre by May 13, 2013, to facilitate the reduction in the items to be selected for a final list
      during the preparation week June 3, 2013. The inspection team will finalize the selected
      list during the prep week using the additional documents requested in Section II of this
      enclosure. The specific items selected from the lists shall be available and ready for
      review on the day indicated in this request. *Please provide requested documentation
      electronically in pdf files, Excel, or other searchable formats, if possible. The
      information 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 pressurized water reactor
      technology. If requested documents are large and only hard copy formats are available,
      please inform the inspector(s), and provide subject documentation during the first day of
      the onsite inspection.
            1. An Excel spreadsheet of equipment basic events (with definitions) including
                importance measures sorted by risk achievement worth (RAW) and Fussell-
                Vesely (FV) from your internal events probabilistic risk assessment (PRA).
                Include basic events with RAW value of 1.3 or greater.
            2. Provide a list of the top 500 cut-sets from your PRA.
            3. Copies of PRA system notebooks and the latest PRA summary document.
            4. An Excel spreadsheet of PRA human action basic events or risk ranking of
                operator actions from your site specific PSA sorted by RAW and FV. Provide
                copies of your human reliability worksheets for these items.
            5. If you have an external events or fire PSA model, provide the information
                requested in items 1-4 for external events and fire.
                                              -1-                                        Enclosure
 
6. 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.).
7. List of high risk maintenance rule systems/components and functions; based on
    engineering or expert panel judgment.
8. A list of operating experience evaluations for the last 2 years.
9. A list of all time-critical operator actions in procedures.
10. A list of permanent and temporary modifications sorted by component identified
    in Item 1.
11. List of current operator work arounds/burdens.
12. A list of the design calculations, which provide the design margin information for
    components included in Item 1. (Calculations should be available during the
    information gathering visit).
13. List of root cause evaluations associated with component failures or design
    issues initiated/completed in the last 5 years.
14. Current management and engineering organizational charts.
15. Diablo Canyon Power Plant IPEEE, if available electronically.
16. Mechanical piping drawings for:
    *    Engineered safety features
    *    Emergency core cooling systems
    *    Emergency diesel generators
17. Electrical one-line drawings for:
    *    Offsite power/switchyard supplies
    *    Normal AC power systems
    *    Emergency AC/DC power systems including
    *    120VAC power, and
    *    125VDC/24VDC safety class systems
18. List of any common-cause failures of components in the last 3 years.
19. An electronic copy of the Design Bases Documents.
20. An electronic copy of the System Health notebooks.
                                  -2-                                      Enclosure
 
II. Information Requested to be Available on First Day of Preparation Week (June 3,
    2013)
    1. List of condition reports (corrective action documents) associated with each of the
        selected components for the last 5 years.
    2. The corrective maintenance history associated with each of the selected components
        for the last 2 years.
    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 reference material (such as drawings, engineering requests, and
        vendor letters).
    4. Copies of operability evaluations associated with each of the selected components
        and plans for restoring operability, if applicable.
    5. Copies of selected operator work-around evaluations associated with each of the
        selected components and plans for resolution, if applicable.
    6. Copies of any open temporary modifications associated with each of the selected
        components, if applicable.
    7. Trend data on the selected electrical/mechanical components performance for last 3
        years (for example, pumps performance including in-service testing, other vibration
        monitoring, oil sample results, etc., as applicable).
    8. A copy of any internal/external self-assessments and associated corrective action
        documents generated in preparation for the inspection.
    9. A copy of engineering/operations related audits completed in the last 2 years.
    10. List of motor operated valves (MOVs) in the program, design margin and risk
        ranking.
    11. List of air operated valves (AOVs) in the valve program, design and risk ranking.
    12. Structure, system and components in the Maintenance Rule (a)(1) category.
    13. Site top 10 issues list.
    14. Procedures used to accomplish operator actions associated with the basic events in
        your PRA.
    15. List of licensee contacts for the inspection team with pager or phone numbers.
                                        -3-                                      Enclosure
 
III.    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. Reference materials (available electronically and as needed during all onsite weeks):
            *  General set of plant drawings
            *  IPE/PRA report
            *  Procurement documents for components selected
            *  Plant procedures (normal, abnormal, emergency, surveillance, etc.)
            *  Technical Specifications
            *  Updated Final Safety Analysis Report
            *  Vendor manuals
Inspector Contact Information:
Wayne C. Sifre                Robert Latta                  Clyde Osterholtz
Senior Reactor Inspector      Senior Reactor Inspector      Senior Operations Engineer
817-200-1193                  817-200-1532                  817-200-1269
Wayne.Sifre@nrc.gov            Robert.Latta@nrc.gov          Clyde.Osterholtz@nrc.gov
Jeffrey Josey                  John Watkins
Senior Resident Inspector      Reactor Inspector
Jeffrey.Josey@nrc.gov          John.Watkins@nrc.gov
Mailing Address:
U.S. NRC, Region IV
Attn: Wayne C. Sifre
1600 East Lamar Blvd.
Arlington, TX 76011-4511
                                            -4-                                        Enclosure
}}

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