ML24045A122
| ML24045A122 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 02/15/2024 |
| From: | Theodore Fanelli Division of Reactor Safety II |
| To: | Coffey B Florida Power & Light Co |
| References | |
| IR 2024011 | |
| Download: ML24045A122 (6) | |
See also: IR 05000250/2024011
Text
Bob Coffey
Executive Vice President, Nuclear Division
and Chief Nuclear Officer
Florida Power & Light Company
700 Universe Blvd
Mail Stop: EX/JB
Juno Beach, FL 33408
SUBJECT: NOTIFICATION OF TURKEY POINT NUCLEAR GENERATING STATION -
COMPREHENSIVE ENGINEERING TEAM INSPECTION (CETI) BASELINE
INSPECTION REPORT 05000250/2024011 AND 05000251/2024011
Dear Mr. Coffey:
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
Turkey Point Nuclear Generating Station during the weeks of June 10 and 24, 2024. 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, operating
experience, and modifications.
During a Teams meeting Mr. Boris Bazan, 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 May 12, 2024
Onsite weeks: Weeks of June 10 and 24, 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. 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 onsite weeks, time may be
needed on the plant-referenced simulator to facilitate the development of operator action-based
scenarios.
February 15, 2024
B. Coffey
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, May 3, 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, May 31, 2024, 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 Nos. 05000250 AND 05000251
License Nos. DPR-31 and DPR-41
Enclosure:
Information Request for Turkey Point Nuclear
Generating Station Comprehensive
Engineering Team Inspection
cc w/ encl: Distribution via LISTSERV
Signed by Baptist, James
on 02/15/24
X
SUNSI Review
X
Non-Sensitive
Sensitive
X
Publicly Available
Non-Publicly Available
OFFICE
RII/DRS
RII/DRS
NAME
T. Fanelli
J. Baptist
DATE
2/14/2024
2/15/2024
Enclosure
INFORMATION REQUEST FOR TURKEY POINT NUCLEAR GENERATING 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, 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,
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 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,
3
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),
35. Schedule for the station control room simulator activities during the onsite inspection weeks
(Weeks of June 10 and 24, 2024).