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{{Adams
#REDIRECT [[IR 05000348/2023010]]
| number = ML22343A038
| issue date = 12/13/2022
| title = Notification of Joseph M. Farley Nuclear Plant – Comprehensive Engineering Team Inspection (CETI) Baseline Inspection Report 05000348/2023010 and 05000364/2023010
| author name = Baptist J
| author affiliation = NRC/RGN-II/DRS
| addressee name = Erb D
| addressee affiliation = Southern Nuclear Operating Co, Inc
| docket = 05000348, 05000364
| license number = NPF-002, NPF-008
| contact person =
| document report number = IR 2023010
| document type = Inspection Report, Letter
| page count = 6
}}
See also: [[see also::IR 05000348/2023010]]
 
=Text=
{{#Wiki_filter:Mr. Delson Erb
Site Vice President
Southern Nuclear Operating Co., Inc.
Joseph M. Farley Nuclear Plant
7388 North State Highway 95
Columbia, AL 36319-0470
SUBJECT:  NOTIFICATION OF JOSEPH M. FARLEY NUCLEAR PLANT - COMPREHENSIVE
ENGINEERING TEAM INSPECTION (CETI) BASELINE INSPECTION REPORT
05000348/2023010 AND 05000364/2023010
Dear Mr. Erb:
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)
Region II staff will conduct a Comprehensive Engineering Team Inspection (CETI) at your
Joseph M. Farley Nuclear Plant during the weeks of April 3 and 17, 2023.  Mr. Theo Fanelli, a
senior reactor inspector from the NRCs Region II office, will lead the inspection team.  The
inspection will be conducted in accordance with Inspection Procedure 71111.21M,
Comprehensive Engineering Team Inspection (CETI), effective date January 1, 2023. This is a
new procedure that was issued on October 7, 2022.
The inspection will evaluate the capability of components that have been modified and risk-
significant/low-margin components to function as designed and to support proper system
operation.  The inspection will also include a review of selected operator actions, and operating
experience, and modifications.
During a Teams meeting Ms. Mandy Ludlam, licensing Engineer, we confirmed arrangements
for an information-gathering site visit and the two-week onsite inspection.  The schedule is as
follows:
Information-gathering visit:  Week of March 13, 2023
Onsite weeks:  Weeks of April 3 and 17, 2023
The purpose of the information-gathering visit is to meet with members of your staff to identify
components that have been modified, risk-significant components, and operator actions. 
Information and documentation needed to support the inspection will also be identified. 
Mr. Shane Sandal, a Region II Senior Risk Analyst, will support Mr. Fanelli during the
information-gathering visit to review probabilistic risk assessment data and identify components
to be examined during the inspection.  Additionally, during the onsite weeks, time may be
needed on the plant-referenced simulator to facilitate the development of operator action-based
scenarios. 
The enclosure lists documents that will be needed prior to the information-gathering visit. 
Please provide the referenced information to the Region II Office by Friday, February 27, 2023. 
Additional documents will be requested following the information-gathering visit.  The inspectors December 13, 2022
D. Erb 2
will try to minimize your administrative burden by specifically identifying only those documents
required for inspection preparation.  The additional information will be needed in the Region II
office by Friday, March 24, 2023, to support the inspection teams preparation week.  During the
information-gathering trip, Mr. Fanelli will also discuss the following inspection support
administrative details: (1) availability of knowledgeable plant engineering and licensing
personnel to serve as points of contact during the inspection; (2) method of tracking inspector
requests during the inspection; (3) licensee computer access; (4) working space;
(5) arrangements for site access; and (6) other applicable information.
This letter, its enclosure, and your response (if any) will be made available for public inspection
and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document
Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for
Withholding.
Thank you for your cooperation in this matter.  If you have any questions, regarding the
information requested or the inspection, please contact Mr. Fanelli at 404-997-4433 or contact
me at 404-997-4506.
Sincerely,
James Baptist, Chief
Engineering Branch 1
Division of Reactor Safety
Docket No.  05000348 AND 05000364
License No.  NPF-2 and NPF-8
Enclosure:
Information Request for Joseph M. Farley Nuclear Plant Comprehensive Engineering Team
Inspection
cc w/ encl:  Distribution via LISTSERV
Signed by Baptist, James
on 12/13/22
 
 
ML22343A038
                          X    Non-Sensitive                  X    Publicly Available
  X    SUNSI Review
                              Sensitive                          Non-Publicly Available
 
OFFICE  RII/DRS          RII/DRS
 
NAME    T. Fanelli      J. Baptist
DATE    12/09/22        12/13/22
 
 
                               
INFORMATION REQUEST FOR JOSEPH M. FARLEY NUCLEAR PLANT COMPREHENSIVE
                            ENGINEERING TEAM INSPECTION
 
Please provide the information electronically in .pdf files, Excel, or other searchable format on
CDROM (or FTP site, SharePoint, etc.).  The CDROM (or website) should be indexed and
hyperlinked to facilitate ease of use.  The requested items below, identified with an asterisk (*),
should have a date range from January 1, 2020, until present.
 
1.    *List of modifications to systems, structures or components (SSCs) that are permanent
    and field work completed.  (For the purpose of this inspection, modifications include
    permanent: plant changes, design changes, calculation changes, procedure changes, and
    set point changes.)
    The list should contain the number of the modification, a short description, affected system
    and unit.  If multiple categories/stages of modifications exist, provide a description of the
    types relative to the coding scheme in your transmittal.  Additionally, the list should be
    categorized by quality level (i.e., safety or non-safety) as well as whether accompanied by
    a screening or 10 CFR 50.59 evaluation.  A query report return-field-set might look like:
 
  Identifier Unit  System1    Description    Type2    Status3  QA Condition4    50.595
            1    e.g. If systems are provided with some type of number or acronym designation,
          define the systems designation on a separate list or document
      2    e.g. Engineering Design/Document Change, Design Change Notice, Test,
          Experiment, etc.
      3    e.g. Closed, Returned to Operation, Void, Partially Completed, Released for
          Installation, Phase 1 Completed, etc.
      4    e.g. Safety Related or Non-Safety Related
      5    e.g. Screened Out or Full 10 CFR 50.59 Evaluation
 
2.    From your most recent probabilistic safety analysis (PSA) excluding external events and
    fires:
        a.  Two risk rankings of components from your site-specific PSA:  one sorted by Risk
            Achievement Worth (RAW), and the other sorted by Birnbaum Importance
        b.  A list of the top 500 cut-sets
        c.  A list of the top 500 LERF contributors
3.    From your most recent PSA including external events and fires:
        a.  Two risk rankings of components from your site-specific PSA:  one sorted by RAW,
            and the other sorted by Birnbaum Importance
        b.  A list of the top 500 cut-sets
4.    Risk ranking of operator actions from your site-specific PSA sorted by RAW and human
    reliability worksheets for these items
5.    List of time-critical operator actions with a brief description of each action
6.    *List of components 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, and motor-operated valve risk-margin rankings, etc.) and
    associated evaluations or calculations
7.    *List and brief description of Root Cause Evaluations performed
 
 
 
 
                                                                                    Enclosure
8.    *List and brief description of common-cause component failures that have occurred
9.    List and brief description of equipment currently in degraded or nonconforming condition
10.  *List and brief description of Operability Determinations and Functionality Assessments
11.  *List and reason for equipment that has been classified in maintenance rule (a)(1) status
12.  *List of equipment on the sites Station Equipment Reliability Issues List, including a
    description of the reason(s) why each component is on that list, and summaries (if
    available) of your plans to address the issue(s) along with dates added or removed from
    the issues list
13.  List of current operator work arounds/burdens
14.  Copy of Updated Final Safety Analysis Report
15.  Copy of Technical Specification(s)
16.  Copy of Technical Specifications Bases
17.  Copy of Technical Requirements Manual(s)
18.  Copy of the Quality Assurance Program Manual
19.  Copy of Corrective Action Program Procedure(s)
20.  Copy of Operability Determination Procedure(s)
21.  Copy of procedures addressing the following:  Modifications, design changes, set point
    changes, equivalency evaluations or suitability analyses, commercial grade dedications,
    post-modifications testing, 10 CFR 50.59 screenings and evaluations, and UFSAR updates
22.  Copy of procedures addressing the following:  loss of service water system or ultimate heat
    sink (UHS); controls to prevent clogging due to macrofouling; and performance, testing,
    and inspection requirements for service water system and UHS
23.  Response to Generic Letter 89-13 including any regulatory commitments made
24.  List of heat exchangers or equipment cooled by service water directly or indirectly.  Include
    the risk ranking for each listed heat exchanger.
25.  List of motor operated valves and air operated valves in the valve program, and their
    associated design margin and risk ranking
26.  Primary AC and DC calculations for safety-related buses
27.  One-line diagram of electrical plant (Electronic only)
28.  Index and legend for electrical plant one-line diagrams
29.  Piping and instrumentation diagrams (P&IDs) for safety-related systems (Electronic)
30.  Index and legend for P&IDs
31.  Index (procedure number, title, and current revision) of station Emergency Operating
    Procedures, Abnormal Operating Procedures, and Annunciator Response Procedures
 
 
 
 
                                          2
32.  Copies of corrective action documents generated from previous design bases assurance
    inspections
33.  Copy of any self-assessments performed, and corrective action documents generated, in
    preparation for current comprehensive engineering team inspection
34.  Contact information for a person to discuss PSA information prior to and during the
    information-gathering trip (Name, title, phone number, and e-mail address)
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
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}}

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