ML24016A251
| ML24016A251 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 01/17/2024 |
| From: | James Baptist Division of Reactor Safety II |
| To: | Carr E Dominion Energy South Carolina |
| References | |
| IR 2024011 | |
| Download: ML24016A251 (6) | |
See also: IR 05000395/2024011
Text
Eric S. Carr
President, Nuclear Operations and
Chief Nuclear Officer
Dominion Energy
Innsbrook Technical Center
5000 Dominion Blvd., Floor: IN-3SE
Glen Allen, VA 23060
SUBJECT:
NOTIFICATION OF VIRGIL C. SUMMER NUCLEAR STATION
COMPREHENSIVE ENGINEERING TEAM INSPECTION - U.S. NUCLEAR
REGULATORY COMMISSION INSPECTION REPORT 05000395/2024011
Dear Eric S. Carr:
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 Virgil
C. Summer Nuclear Station during the weeks of March 25 and April 8, 2024. Mr. Christopher
Even, 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), issued January 1, 2023.
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 January 10, 2024, with Mr. William Kirkland, 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 February 12, 2024
Onsite weeks: Weeks of March 25 and April 8, 2024
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 Reactor Analyst, will support Mr. Even 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.
January 17, 2024
E. Carr
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 Wednesday, February 7, 2024.
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 Friday, March 15, 2024, to support the inspection teams preparation week. During the
information-gathering trip, Mr. Even 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. Even at 404-997-4661 or contact me
at 404-997-4506.
Sincerely,
James B. Baptist, Chief
Engineering Branch 1
Division of Reactor Safety
Docket No.:
05000395
License No.:
Enclosure:
Information Request for Virgil C. Summer
Nuclear Station Comprehensive Engineering
Team Inspection
cc w/encl: Distribution via LISTSERV
Signed by Baptist, James
on 01/17/24
X
SUNSI Review
X
Non-Sensitive
Sensitive
X
Publicly Available
Non-Publicly Available
OFFICE
R2/DRS
R2/DRS
NAME
C. Even
J. Baptist
DATE
01/16/2024
01/17/2024
Enclosure
INFORMATION REQUEST FOR VIRGIL C. SUMMER NUCLEAR STATION
COMPREHENSIVE ENGINEERING TEAM INSPECTION
Please provide the information electronically in .pdf files, Excel, or other searchable format on
CD-ROM (or FTP site, SharePoint, etc.). The CD-ROM (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, 2021, 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:
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 with applicable
administrative procedures used to maintain them
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
Identifier
Unit
System1
Description
Type2
Status3
QA Condition4
50.595
2
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 as
described in NRC Generic Letter 91-18, Revision 1
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 Selected Licensee Commitments (SLC)
18. Copy of the Quality Assurance Program Document
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. List of heat exchangers or equipment cooled by service water directly or indirectly. Include
the risk ranking for each listed heat exchanger.
24. List of motor operated valves and air operated valves in valve programs, and their
associated design margin and risk ranking
25. Primary AC and DC calculations for safety-related buses
26. One-line diagram of electrical plant (Electronic only)
27. Index and legend for electrical plant one-line diagrams
28. Piping and instrumentation diagrams (P&IDs) for safety-related systems (Electronic)
29. Index and legend for P&IDs
3
30. Index (procedure number, title, and current revision) of station Emergency Operating
Procedures, Abnormal Operating Procedures, and Annunciator Response Procedures
31. Copies of corrective action documents generated from previous design bases assurance
inspections
32. Copy of any self-assessments performed, and corrective action documents generated, in
preparation for current comprehensive engineering team inspection
33. 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)
34. List of system acronyms