ML23061A177
| ML23061A177 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 03/03/2023 |
| From: | James Baptist Division of Reactor Safety II |
| To: | Snider S Duke Energy Carolinas |
| References | |
| IR 2023011 | |
| Download: ML23061A177 (7) | |
See also: IR 05000269/2023011
Text
Steven M. Snider
Site Vice President
Duke Energy Carolinas, LLC
Oconee Nuclear Station
7800 Rochester Highway
Seneca, SC 29672-0752
SUBJECT: NOTIFICATION OF OCONEE NUCLEAR STATION COMPREHENSIVE
ENGINEERING TEAM INSPECTION - U.S. NUCLEAR REGULATORY
COMMISSION INSPECTION REPORT 05000269/2023011, 05000270/2023011
AND 05000287/2023011
Dear Steven Snider:
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
Oconee Nuclear Station during the weeks of June 26 and July 17, 2023. Geoffrey Ottenberg, 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 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 telephone conversation on February 23, 2023, with Laura Boyce, 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 May 15, 2023
Onsite weeks: Weeks of June 26 and July 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.
Andy Rosebrook, a Region II Senior Reactor Analyst, will support Geoffrey Ottenberg 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, May 5, 2023.
March 3, 2023
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, June 16, 2023, to support the inspection teams preparation week. During the
information-gathering trip, Mr. Ottenberg 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. Ottenberg at 404-997-4658 or
contact me at 404-997-4506.
Sincerely,
James Baptist, Chief
Engineering Branch 1
Division of Reactor Safety
Docket Nos. 05000269, 05000270, and 05000287
License Nos. DPR-38 and DPR-47 and DPR-55
Enclosure:
Information Request for Oconee Nuclear Station Comprehensive Engineering Team Inspection
cc w/ encl: Distribution via LISTSERV
Signed by Baptist, James
on 03/03/23
X
SUNSI Review
X
Non-Sensitive
Sensitive
X
Publicly Available
Non-Publicly Available
OFFICE
R2/DRS/EB1
R2/DRS/EB1
NAME
G. Ottenberg
J. Baptist
DATE
3/2/2023
3/3/2023
Enclosure
INFORMATION REQUEST FOR OCONEE NUCLEAR STATION 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:
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
Identifier
Unit
System1
Description
Type2
Status3
QA Condition4
50.595
2
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 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. 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
30. Index (procedure number, title, and current revision) of station Emergency Operating
Procedures, Abnormal Operating Procedures, and Annunciator Response Procedure
3
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)