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{{Adams
#REDIRECT [[IR 05000280/2020010]]
| number = ML20171A348
| issue date = 06/19/2020
| title = Notification of Surry Power Station Design Bases Assurance Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000280/2020010 and 05000281/2020010
| author name = Baptist J
| author affiliation = NRC/RGN-II/DRS/EB1
| addressee name = Stoddard D
| addressee affiliation = Virginia Electric & Power Co (VEPCO)
| docket = 05000280, 05000281
| license number = DPR-032, DPR-037
| contact person =
| document report number = IR 2020010
| document type = Letter
| page count = 6
}}
See also: [[see also::IR 05000280/2020010]]
 
=Text=
{{#Wiki_filter:June 19, 2020
Mr. Daniel G. Stoddard
Senior Vice President and
  Chief Nuclear Officer
Innsbrook Technical Center
5000 Dominion Blvd.
Glen Allen, VA 23060-6711
SUBJECT: NOTIFICATION OF SURRY POWER STATION DESIGN BASES ASSURANCE
              INSPECTION - U.S. NUCLEAR REGULATORY COMMISSION INSPECTION
              REPORT 05000280/2020010 AND 05000281/2020010
Dear Mr. Stoddard:
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)
Region II staff will conduct a Design Bases Assurance Inspection (DBAI) at your Surry Power
Station during the weeks of September 14-18, 2020, and September 28-October 2, 2020.
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, Design Bases Assurance Inspection (Teams), dated December 8, 2016 (ADAMS
ML16238A320).
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, operating
experience, and modifications.
During a telephone conversation on June 15, 2020, with Mr. Steve Newman, 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 August 24, 2020
    *  Onsite weeks: Weeks of September 14 and September 28, 2020
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. Andy Rosebrook, 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 first onsite week, time will be
needed on the plant-referenced simulator in order to facilitate the development of operator
action-based scenarios.
 
D. Stoddard                                    2
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, August 14, 2020.
Additional documents will be requested following the information-gathering visit. The inspectors
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 Wednesday, September 2, 2020, 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.
In accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections,
Exemptions, Requests for Withholding, 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
Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible
from the NRC website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic
Reading Room).
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 Nos.: 50-280, 50-281
License Nos.: DPR-32, DPR-37
Enclosure:
Notification of Surry Power Station
  Design Bases Assurance Inspection (Teams)
cc: Distribution via Listserv
 
 
ML20171A348
OFFICE            RII:DRS        RII:DRS
SIGNATURE                EJS2      TNF1 FOR JBB1
NAME                  T. Fanelli      J. Baptist
DATE                  6/15/2020      6/15/2020
                                                 
                    INFORMATION REQUEST FOR SURRY POWER STATION
                        DESIGN BASES ASSURANCE INSPECTION (TEAMS)
Please provide the information electronically in .pdf files, Excel, or other searchable format on
CDROM (or Certrec, 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 February 1, 2017, until present.
1.    *List and brief description of permanent plant modifications including permanent plant
      changes, design changes, set point changes, procedure changes, equivalency evaluations,
      suitability analyses, calculations, and commercial grade dedications. Include an index of
      systems (system numbers/designators and corresponding names), the safety classification
      for each modification, and type of modification.
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
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 status.
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
                                                                                          Enclosure
 
                                                2
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 Original SER with all Supplements
22. Copy of procedures addressing the following: Corrective Action Program (CAP),
    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.
23. List of motor operated valves and air operated valves in valve programs, and their
    associated design margin and risk ranking (Please Note JOG program commitments for
    MOVs and AOVs).
24. Primary AC and DC calculations for safety-related buses
25. One-line diagram of electrical plant (Electronic only)
26. Index and legend for electrical plant one-line diagrams
27. Piping and instrumentation diagrams (P&IDs) for safety-related systems (Electronic)
28. Index and legend for P&IDs
29. Index (procedure number, title, and current revision) of station Emergency Operating
    Procedures, Abnormal Operating Procedures, and Annunciator Response Procedures
30. Copies of corrective action documents generated from previous CDBI / DBAI
31. Copy of any self-assessments performed, and corrective action documents generated, in
    preparation for current DBAI
 
                                                3
32. 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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