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{{Adams
#REDIRECT [[IR 05000361/2008010]]
| number = ML081130702
| issue date = 04/22/2008
| title = IR 05000361-08-010, IR 05000362-08-010, 06/09/2008, San Onofre Generating Station - Information Request for NRC Triennial Baseline Component Design Bases Inspection
| author name = Bywater R
| author affiliation = NRC/RGN-IV/DRS
| addressee name = Rosenblum R
| addressee affiliation = Southern California Edison Co
| docket = 05000361, 05000362
| license number = NPF-010, NPF-015
| contact person =
| document report number = IR-08-010
| document type = Inspection Report Correspondence, Letter, Inspection Report
| page count = 9
}}
See also: [[see also::IR 05000361/2008010]]
 
=Text=
{{#Wiki_filter:UNITED STATES
                                  NU CLE AR RE GU LATOR Y C O M M I S S I O N
                                                        R EGI ON I V
                                          611 R YAN PLAZA D R IV E, SU ITE 400
                                            AR LI N GTON , TEXAS 76011-4005
                                            April 22, 2008
Richard M. Rosenblum
Senior Vice President and
  Chief Nuclear Officer
Southern California Edison Company
San Onofre Nuclear Generating Station
P.O. Box 128
San Clemente, CA 92674-0128
SUBJECT:        SUBJECT: SAN ONOFRE NUCLEAR GENERATING STATION -
                INFORMATION REQUEST FOR NRC TRIENNIAL BASELINE COMPONENT
                DESIGN BASES INSPECTION (NRC INSPECTION REPORT
                05000361/2008010;050000362/2008010)
Dear Mr. Rosenblum:
On June 9, 2008, the U.S. Nuclear Regulatory Commission (NRC) will begin a triennial baseline
Component Design Bases Inspection at the San Onofre Nuclear Generating Station. A team of
six inspectors plus a team leader will perform this 3-week inspection. This inspection will be
performed in accordance with revised NRC Baseline Inspection Procedure 71111.21 and
replaces the biennial Safety System Design and Performance Capability inspection.
The component design bases inspection focuses on components that have high risk and low
design margins. The components to be reviewed during this baseline inspection will mainly be
identified during an information gathering visit and during the subsequent in-office preparation
week. In addition, a number of risk significant operator actions and operating experience
issues, associated with the component samples, will also be selected for review.
The inspection will be 4-weeks onsite, including the information gathering site visit and 3-weeks
of onsite inspection. The inspection will consist of six NRC inspectors, of which five will focus
on engineering and one on operations. The current inspection schedule is as follows:
                        Onsite information gathering visit: Week of June 9, 2008
                        Onsite weeks: June 23, July 7 and July 14, 2008
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 a member of your probabilistic risk analyst staff. Additional information
and documentation needed to support the inspection will be identified. A Region IV senior
reactor analyst was requested and may accompany the inspection team during the information
gathering visit to review probabilistic risk assessment data and assist in identifying risk
significant components, which will be reviewed during the inspection.
 
Experience with previous baseline design inspections of similar depth and length has shown
that these inspections 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 12, 2008. Insofar as possible, this information should be
provided electronically to the lead inspector. Since the inspection will be concentrated on high
risk/low margin component, calculations associated with your list of high risk components
should be available for the inspectors 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 are those items that the team will need access to
when onsite and after components are selected. 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. It is important that all of these documents are up to date and completed 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 Mr. Kelly Clayton. We understand that our licensing
engineer contact for this inspection is Mr. Mike McBrearty. If there are any questions about the
inspection or the requested materials, please contact the lead inspector at (817) 860-8216 or via
e-mail at kelly.clayton@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/
                                                Russ Bywater, Chief
                                                Engineering Branch One
                                                Division of Reactor Safety
Dockets: 50-361; 50-362
Licenses: NPF-10; NPF-15
Enclosure:
Component Design Basis Inspection
Document Request
 
cc w/enclosure:
Mr. Ross T. Ridenoure
Vice President and Site Manager
Southern California Edison Company
San Onofre Nuclear Generating Station
P.O. Box 128
San Clemente, CA 92674-0128
Chairman, Board of Supervisors
County of San Diego
1600 Pacific Highway, Room 335
San Diego, CA 92101
Gary L. Nolff
Assistant Director-Resources
City of Riverside
3900 Main Street
Riverside, CA 92522
Mark L. Parsons
Deputy City Attorney
City of Riverside
3900 Main Street
Riverside, CA 92522
Dr. David Spath, Chief
Division of Drinking Water and
Environmental Management
California Department of Health Services
850 Marina Parkway, Bldg P, 2nd Floor
Richmond, CA 94804
Michael J. DeMarco
San Onofre Liaison
San Diego Gas & Electric Company
8315 Century Park Ct. CP21G
San Diego, CA 92123-1548
Director, Radiological Health Branch
State Department of Health Services
P.O. Box 997414 (MS 7610)
Sacramento, CA 95899-7414
Mayor
City of San Clemente
100 Avenida Presidio
San Clemente, CA 92672
 
James D. Boyd, Commissioner
California Energy Commission
1516 Ninth Street (MS 34)
Sacramento, CA 95814
Douglas K. Porter, Esq.
Southern California Edison Company
2244 Walnut Grove Avenue
Rosemead, CA 91770
A. Edward Scherer
Southern California Edison Company
San Onofre Nuclear Generating Station
P.O. Box 128
San Clemente, CA 92674-0128
Mr. Steve Hsu
Department of Health Services
Radiologic Health Branch
MS 7610, P.O. Box 997414
Sacramento, CA 95899-7414
Mr. James T. Reilly
Southern California Edison Company
San Onofre Nuclear Generating Station
P.O. Box 128
San Clemente, CA 92674-0128
Chief, Radiological Emergency Preparedness Section
National Preparedness Directorate
Technological Hazards Division
Department of Homeland Security
1111 Broadway, Suite 1200
Oakland, CA 94607-4052
 
Electronic distribution by RIV:
Regional Administrator (Elmo.Collins@nrc.gov)
DRP Director (Dwight.Chamberlain@nrc.gov)
DRS Director (Roy.Caniano@nrc.gov)
DRS Deputy Director (Troy.Pruett@nrc.gov)
Senior Resident Inspector (Clyde.Osterholtz@nrc.gov)
Branch Chief, DRP/D (Michael.Hay@nrc.gov)
Senior Project Engineer, DRP/D (Greg.Werner@nrc.gov)
Senior Project Engineer, DRP/D (Geoff.Miller@nrc.gov)
Team Leader, DRP/TSS (Chuck.Paulk@nrc.gov)
RITS Coordinator (Marisa.Herrera@nrc.gov)
NRR CDBI Coordinator, (Donald.Norkin@nrc.gov)
Only inspection reports to the following:
DRS STA (Dale.Powers@nrc.gov)
J. Adams, OEDO RIV Coordinator (John.Adams@nrc.gov)
ROPreports
SO Site Secretary (Heather.Hutchinson@nrc.gov))
SUNSI Review Completed: _Yes_ ADAMS: Yes No              Initials: _KDC _____
Publicly Available  Non-Publicly Available      Sensitive      Non-Sensitive
S:DRS\REPORTS\SO CDBI FRI ltr-KDC                              ML
RIV:RI:DRS/EB1          BC/EB1
KDClayton              RBywater
/RA/                    /RA/
04/22/08                04/22/08
OFFICIAL RECORD COPY                                T=Telephone        E=E-mail  F=Fax
 
INFORMATION REQUEST FOR SAN ONOFRE NUCLEAR GENERATING STATION
COMPONENT DESIGN BASES INSPECTION (CDBI)
Inspection Report:                        05000361/2008010; 05000362/2008010
Information Gathering Dates:              June 9 - 11, 2008
On-site Inspection Dates:                June 23 - 27 2008, July 7 through July 18, 2008
Inspection Procedure:                    IP 71111.21, Component Design Bases
                                          Inspection
Lead Inspector/Team Leader:              Kelly Clayton
                                          817-860-8216
                                          kelly.clayton@nrc.gov
I.      Information Requested Prior to the information Gathering Visit
The following information is requested by May 12, 2008, or sooner, to facilitate
inspection preparation. If you have any questions regarding this information, pleased
call the lead inspector as soon as possible. (Please provide the information
electronically in pdf files, Excel, or other searchable formats. 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).
        1.      An excel spreadsheet of equipment basic events (with definitions)
                including importance measures risk achievement worth, Fusselly-Veseley
                (RAW, FV) from your internal events probabilistic risk assessment (PRA),
                including risk ranking of top 50 components from your site-specific PRA
                sorted by (RAW). Include values for Birnbaum Importance, risk reduction
                worth (RRW), and Fussell-Veseley FV (as applicable).
        2.      Provide a list of the top 500 cut-sets from your PRA.
        3.      Copies of PRA system notebooks.
        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 1-3 for external events and fire.
        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.  Any pre-existing evaluation or list of components and calculations with
    low design margins (i.e., pumps closest to the design limit for flow or
    pressure, diesel generators close to design required output, heat
    exchangers close to rated design heat removal, etc.).
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. San Onofre Nuclear Generating Station 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.
 
II. Information Requested to be Available on First Day of Inspection (June 23,
    2008)
    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 he 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.  Provide list of PRA assumptions regarding operator actions and the
          associated procedures.
    15.  List of licensee contacts for the inspection team with pager or phone
          numbers.
 
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:
Kelly Clayton
Senior Reactor Inspector
(817) 860-8216
kelly.clayton@nrc.gov
Mailing Address:
US NRC, Region IV
Attn: Kelly Clayton
611 Ryan Plaza Dr, Ste 400
Arlington, TX 76011
}}

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