ML21322A261

Request for Information for a Triennial Baseline Design Bases Assurance Inspection (Teams); Inspection Report 05000443/2022011

ML21322A261
Person / Time
Site:	Seabrook
Issue date:	11/18/2021
From:	Mel Gray NRC/RGN-I/DORS
To:	Coffey R NextEra Energy Seabrook
Gray M
References
IR 2022011
Download: ML21322A261 (6)

See also: IR 05000443/2022011

Text

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION I

2100 RENAISSANCE BLVD., SUITE 100

KING OF PRUSSIA, PENNSLYVANIA 19406-2713

November 18, 2021

Mr. Robert 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: SEABROOK STATION, UNIT NO. 1 - REQUEST FOR INFORMATION FOR A

TRIENNIAL BASELINE DESIGN BASES ASSURANCE INSPECTION (TEAM);

INSPECTION REPORT 05000443/2022011

Dear Mr. Coffey:

The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)

Region I staff will conduct a Design Bases Assurance Inspection (DBAI) at your Seabrook

Station. Kevin Mangan, a Senior Reactor Inspector from the NRCs Region I office, will lead the

inspection team. The inspection will be conducted in accordance with Inspection Procedure 71111.21M, Design Bases Assurance Inspection (Team), dated December 8, 2016 (ADAMS

Accession No. ML16340B000).

The inspection will evaluate the capability of risk-significant/low-margin components to function

as designed to support proper system operation. The inspection will also include a review of

selected modifications, operating experience, and as applicable, operator actions.

During communications on November 17, 2021, with Joshua Greene, Senior Nuclear Engineer -

Licensing, we confirmed arrangements for an information-gathering meeting and the two-week

onsite inspection. The schedule is as follows:

• Information-gathering meeting: Week of December 13, 2021

• Onsite weeks: Weeks of January 24 and February 7, 2022

The purpose of the information-gathering visit is to meet with members of your staff to identify

risk-significant components, modifications, operator actions, and operating experience items.

Information and documentation needed to support the inspection will also be identified.

Frank Arner, a Region I Senior Risk Analyst, will support Kevin Mangan during the information-

gathering visit to review probabilistic risk assessment data and identify components to be

examined during the inspection.

Experience with previous baseline design/modification inspections of similar depth and length

has shown this type of inspection is resource intensive, both for the NRC inspectors and the

licensee staff. In order to minimize the inspection impact on the site and to ensure a productive

R. Coffey 2

inspection for both parties, we have enclosed a request for information needed for the

inspection.

It is important that all of these documents are up-to-date and complete in order to minimize the

number of additional documents requested during the preparation and/or the onsite portions of

the inspection. Insofar as possible, this information should be provided electronically to the lead

inspector. The information request has been divided into two groups:

• The first group lists information necessary for our initial inspection scoping activities.

This information should be provided to the lead inspector by December 13, 2021.

By December 17, 2021, the lead inspector will communicate the initial selected set of

components and modifications.

• The second group of documents requested is those items needed to support our in-

office preparation activities. This set of documents, specific to the selected components

and modifications, should be provided to the lead inspector at the Regional Office no

later than January 14, 2022. During the in-office preparation activities, the team may

identify additional information needed to support the inspection, and those items will be

communicated directly to Joshua Green, Senior Nuclear Engineer - Licensing.

If there are any questions about the inspection or the material requested in the enclosure,

please contact the lead inspector at 610-337-5234 or via e-mail at kevin.mangan@nrc.gov.

This letter does not contain new or amended information collection requirements subject to the

Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection

requirements were approved by the Office of Management and Budget, Control Number 3150-

0011. The NRC may not conduct or sponsor, and a person is not required to respond to, a

request for information or an information collection requirement unless the requesting document

displays a currently valid Office of Management and Budget Control Number.

This letter and its enclosure 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 Title 10 of the Code of Federal Regulations, Part 2.390, Public Inspections,

Exemptions, Requests for Withholding.

Sincerely,

Digitally signed by Melvin K.

Gray

Melvin K. Gray Date: 2021.11.18 15:57:19

-05'00'

Mel Gray, Chief

Engineering Branch 1

Division of Operating Reactor Safety

Docket No. 50-443

License No. NPF-86

Enclosure:

Document Request for Design Bases

Assurance Inspection

cc: Distribution via ListServ

ML21322A261

x Non-Sensitive x Publicly Available

x SUNSI Review

Sensitive Non-Publicly Available

OFFICE RI/DORS RI/DORS RI/DORS

NAME KMangan FArner MGray

DATE 11/17/21 11/18/21 11/17/21

DOCUMENT REQUEST FOR DESIGN BASES ASSURANCE INSPECTION

Inspection Report: 05000443/2022011

Onsite Inspection Dates: January 24 through January 28 and

February 7, through February 11, 2022

Inspection Procedure: Inspection Procedure 71111.21M, Design Bases Assurance

Inspection (Team)

Lead Inspector: Kevin Mangan, Senior Reactor Inspector

610-337-5234

Kevin.mangan@nrc.gov

I. Information Requested for Selection of Components and Modifications

The following information is requested by December 14, 2021, to facilitate inspection

preparation. Feel free to contact the lead inspector as soon as possible if you have any

questions regarding this information request. Please provide the information electronically

in pdf files, Excel, or other searchable formats, preferably on some portable electronic

media (e.g., CD-ROM, DVD). The files should contain descriptive names, and be indexed

and hyperlinked to facilitate ease of use. Information in lists should contain enough

information to be easily understood by someone who has knowledge of light water reactor

technology.

1. The site probabilistic risk analysis (PRA) System Notebook and latest PRA Summary

Document.

2. Risk ranking of top 250 basic events sorted by Risk Achievement Worth (>/= 1.3).

Include values for Risk Reduction Worth, Birnbaum Importance, and Fussell-Vesely (as

applicable). Please provide in an excel spreadsheet or other sortable format, and

include an understandable definition of the coded basic events.

3. Risk-ranking of top 100 components from site specific PRA sorted by Large Early

Release Frequency. Provide any basic event mapping used to develop the ranking of

components.

4. List of the top 200 cut-sets from your PRA. Provide the descriptions of the basic events

in the list of cut-sets.

5. List of the top 200 cut-sets for each initiator modeled in the PRA that contributes more

than 5 percent to the baseline plant core damage frequency.

6. List of time-critical and/or risk significant operator actions.

7. List of emergency and abnormal operating procedures.

DOCUMENT REQUEST FOR DESIGN BASES ASSURANCE INSPECTION

8. If available, any pre-existing evaluation or list of components and associated

calculations with low design margins (e.g., 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).

9. If applicable, copy of any self-assessments and/or Quality Assurance assessments of

low margin structures, systems and components (SSC), completed in the last 3 years.

10. List of available design margins in both the open and closed direction for valves in the

motor-operated valve and air-operated valve programs. Identify the safety-related

direction and the basis for how the margin was determined.

11. The age and capacity of the safety-related DC batteries.

12. SSCs in the Maintenance Rule (a)(1) category in the last 3 years.

13. List of Root Cause Evaluations associated with SSCs failures or design issues

initiated/completed in the last 4 years.

14. List of formal operability evaluations in the last 3 years.

15. List of permanent plant modifications to SSCs that are field work complete in the last 3

years. For the purpose of this inspection, permanent plant modifications include

permanent: plant changes, design changes, set point changes, equivalency

evaluations, suitability analyses, and commercial grade dedications. The list should

contain the number of each document, title (sufficient to understand the purpose of

the modification), revision/date, and the affected system.

16. List of calculation changes that have been issued for use in the last 3 years.

17. Procedures addressing the following: modifications, design changes, set point changes,

equivalency evaluations or suitability analyses, commercial grade dedications, and

post-modification testing.

18. List of corrective action documents (open and closed) in the last 3 years that address

permanent plant modifications issues, concerns, or processes.

19. Any internal/external self-assessments and associated corrective action documents

generated in preparation for this inspection.

20. Corrective Action Program documents (e.g., condition reports) associated with

inspection findings from the previous NRC Inspection Procedure 71111.21 (or 71111.21

Attachment M inspection).

21. Updated Final Safety Analysis Report, Technical Specifications, Technical

Specifications Bases, and Technical Requirements Manual.

22. Major one line safety-related electrical drawings (AC and DC), and Piping and

Instrumentation Drawings of emergency core cooling systems, ultimate heat sink, and

[for PWRs - emergency feedwater system].

DOCUMENT REQUEST FOR DESIGN BASES ASSURANCE INSPECTION

II. Information Requested to Be Available by January 21, 2022

This information should be separated for each selected component and modification,

especially if provided electronically (e.g., a folder for each component and modification

named after the component or modification that includes the information requested below).

Items 1 through 11 are associated with the selected components and Item 12 is for the

selected modifications.

1. List of corrective action documents associated with each selected component for the

last 4 years.

2. Maintenance history (e.g., corrective, preventive, and elective) associated with each

selected component for the last 6 years. Identify frequency of preventive maintenance

activities.

3. Aging Management Program documents and/or License Renewal committed inspection

results applicable to each selected component.

4. List of calculations associated with each selected component, excluding data files. Pipe

stress calculations are excluded from this request.

5. System Health Report (last completed) and Design Basis Document associated with

each selected component.

6. Access to or copy of vendor manual(s) for each selected component.

7. List of open temporary modifications associated with each selected component, if

applicable.

8. Trend data/graphs on the selected components performance for the last 3 years (e.g.,

pump performance including IST, other vibration monitoring, oil sample results).

9. List of normal operating and alarm response procedures associated with each selected

component.

10. Last completed tests and surveillances for each selected component performed during

the last 3 years. For those tests and surveillances performed at a periodicity of greater

than three years, provide the latest test performed.

11. Schedule of surveillance testing of selected components that occur during the onsite

inspection weeks.

12. For each selected modification, copies of associated documents such as modification

package, engineering changes, 50.59 screening or evaluation, relevant calculations,

post-modification test packages, associated corrective action documents, design

drawings, and new/revised preventive maintenance requirements.