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{{#Wiki_filter:January 18, 2022
{{#Wiki_filter:January 18, 2022
Mr. John A. Krakuszeski
Site Vice President
Mr. John A. Krakuszeski  
Brunswick Steam Electric Plant
Site Vice President  
Duke Energy Progress, LLC
Brunswick Steam Electric Plant  
8470 River Rd. SE (M/C BNP001)
Duke Energy Progress, LLC  
Southport, NC 28461
8470 River Rd. SE (M/C BNP001)  
SUBJECT: NOTIFICATION OF BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 & 2
Southport, NC 28461  
              DESIGN BASES ASSURANCE INSPECTION - U.S. NUCLEAR REGULATORY
              COMMISSION INSPECTION REPORT 05000324/2022010 AND
SUBJECT: NOTIFICATION OF BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 & 2  
              05000325/2022010
DESIGN BASES ASSURANCE INSPECTION - U.S. NUCLEAR REGULATORY  
Dear Mr. Krakuszeski:
COMMISSION INSPECTION REPORT 05000324/2022010 AND  
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)
05000325/2022010  
Region II staff will conduct a Design Bases Assurance Inspection (DBAI) at your Brunswick
Steam Electric Plant Units 1 & 2 during the weeks of April 25 and May 9, 2022.
Dear Mr. Krakuszeski:  
Mr. Paul Carman, 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
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)  
71111.21M, Design Bases Assurance Inspection (Teams), dated December 8, 2016 (ADAMS
Region II staff will conduct a Design Bases Assurance Inspection (DBAI) at your Brunswick  
ML16340B000).
Steam Electric Plant Units 1 & 2 during the weeks of April 25 and May 9, 2022.  
Mr. Paul Carman, 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  
ML16340B000).  
The inspection will evaluate the capability of components that have been modified and risk-
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
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
operation. The inspection will also include a review of selected operator actions, operating  
experience, and modifications.
experience, and modifications.  
During a telephone conversation on January 12, 2022, with Mr. Tom Sherrill we confirmed
arrangements for an information-gathering site visit and the two-week onsite inspection. The
During a telephone conversation on January 12, 2022, with Mr. Tom Sherrill we confirmed  
schedule is as follows:
arrangements for an information-gathering site visit and the two-week onsite inspection. The  
    *   Information-gathering visit: April 4, 2022
schedule is as follows:  
    *   Onsite weeks: Weeks of April 25 and May 9, 2022
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-gathering visit: April 4, 2022
Information and documentation needed to support the inspection will also be identified.
*  
Mr. Andy Rosebrook, a Region II Senior Risk Analyst, will support Mr. Carman during the
Onsite weeks: Weeks of April 25 and May 9, 2022  
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
The purpose of the information-gathering visit is to meet with members of your staff to identify  
needed on the plant-referenced simulator to facilitate the development of operator action-based
components that have been modified, risk-significant components, and operator actions.
scenarios.
Information and documentation needed to support the inspection will also be identified.  
The enclosure lists documents that will be needed prior to the information-gathering visit.
Mr. Andy Rosebrook, a Region II Senior Risk Analyst, will support Mr. Carman during the  
Please provide the referenced information to the Region II Office by Friday, March 25, 2022.
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, March 25, 2022.


J. Krakuszeski                                 2
J. Krakuszeski  
Additional documents will be requested following the information-gathering visit. The inspectors
2  
will try to minimize your administrative burden by specifically identifying only those documents
Additional documents will be requested following the information-gathering visit. The inspectors  
required for inspection preparation. The additional information will be needed in the Region II
will try to minimize your administrative burden by specifically identifying only those documents  
office by Friday, April 15, 2022, to support the inspection teams preparation week. During the
required for inspection preparation. The additional information will be needed in the Region II  
information-gathering trip, Mr. Carman will also discuss the following inspection support
office by Friday, April 15, 2022, to support the inspection teams preparation week. During the  
administrative details: (1) availability of knowledgeable plant engineering and licensing
information-gathering trip, Mr. Carman will also discuss the following inspection support  
personnel to serve as points of contact during the inspection; (2) method of tracking inspector
administrative details: (1) availability of knowledgeable plant engineering and licensing  
requests during the inspection; (3) licensee computer access; (4) working space;
personnel to serve as points of contact during the inspection; (2) method of tracking inspector  
(5) arrangements for site access; and (6) other applicable information.
requests during the inspection; (3) licensee computer access; (4) working space;
This letter, its enclosure, and your response (if any) will be made available for public inspection
(5) arrangements for site access; and (6) other applicable information.  
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
This letter, its enclosure, and your response (if any) will be made available for public inspection  
Withholding.
and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document  
Thank you for your cooperation in this matter. If you have any questions, regarding the
Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for  
information requested or the inspection, please contact Mr. Carman at 404-997-4471 or contact
Withholding.  
me at 404-997-4506.
                                                Sincerely,
Thank you for your cooperation in this matter. If you have any questions, regarding the  
                                                        /RA/
information requested or the inspection, please contact Mr. Carman at 404-997-4471 or contact  
                                                James Baptist, Chief
me at 404-997-4506.  
                                                Engineering Branch 1
                                                Division of Reactor Safety
Docket Nos. 05000324 and 05000325
License Nos. DPR-62 and DPR-71
Enclosure:
Information Request for Brunswick Steam Electric Plant, Units 1 & 2
   Design Bases Assurance Inspection (Teams)
cc w/ encl: Distribution via LISTSERV
Sincerely,  
/RA/  
James Baptist, Chief
Engineering Branch 1  
Division of Reactor Safety  
Docket Nos. 05000324 and 05000325  
License Nos. DPR-62 and DPR-71  
Enclosure:
Information Request for Brunswick Steam Electric Plant, Units 1 & 2  
   Design Bases Assurance Inspection (Teams)
cc w/ encl: Distribution via LISTSERV


  INFORMATION REQUEST FOR BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 & 2
                      DESIGN BASES ASSURANCE INSPECTION (TEAMS)
Enclosure
Please provide the information electronically in .pdf files, Excel, or other searchable format on
INFORMATION REQUEST FOR BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 & 2
CDROM (or FTP site, SharePoint, etc.). The CDROM (or website) should be indexed and
DESIGN BASES ASSURANCE INSPECTION (TEAMS)  
hyperlinked to facilitate ease of use. The requested items below, identified with an asterisk (*),
should have a date range from January 1, 2019, until present.
Please provide the information electronically in .pdf files, Excel, or other searchable format on  
1.   *List and brief description of permanent and field work completed plant modifications
CDROM (or FTP site, SharePoint, etc.). The CDROM (or website) should be indexed and  
    including permanent plant changes, design changes, set point changes, procedure
hyperlinked to facilitate ease of use. The requested items below, identified with an asterisk (*),  
    changes, equivalency evaluations, suitability analyses, calculations, and commercial grade
should have a date range from January 1, 2019, until present.  
    dedications. Include an index of systems (system numbers/designators and corresponding
    names), the safety classification for each modification, and type of modification.
1.  
2.   From your most recent probabilistic safety analysis (PSA) excluding external events and
*List and brief description of permanent and field work completed plant modifications  
    fires:
including permanent plant changes, design changes, set point changes, procedure  
          a. Two risk rankings of components from your site-specific PSA: one sorted by Risk
changes, equivalency evaluations, suitability analyses, calculations, and commercial grade  
                Achievement Worth (RAW), and the other sorted by Birnbaum Importance
dedications. Include an index of systems (system numbers/designators and corresponding  
          b. A list of the top 500 cut-sets
names), the safety classification for each modification, and type of modification.  
          c. A list of the top 500 LERF contributors
3.   From your most recent PSA including external events and fires:
2.  
          a. Two risk rankings of components from your site-specific PSA: one sorted by RAW,
From your most recent probabilistic safety analysis (PSA) excluding external events and  
                and the other sorted by Birnbaum Importance
fires:  
          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
a. Two risk rankings of components from your site-specific PSA: one sorted by Risk  
    reliability worksheets for these items
Achievement Worth (RAW), and the other sorted by Birnbaum Importance  
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
b. A list of the top 500 cut-sets  
    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
c. A list of the top 500 LERF contributors  
    associated evaluations or calculations
7.   *List and brief description of Root Cause Evaluations performed
3.  
8.   *List and brief description of common-cause component failures that have occurred
From your most recent PSA including external events and fires:  
9.   List and brief description of equipment currently in degraded or nonconforming status as
    described in NRC Inspection Manual Chapter 0326, issued September 30, 2019
a. Two risk rankings of components from your site-specific PSA: one sorted by RAW,  
10. *List and brief description of Operability Determinations and Functionality Assessments
and the other sorted by Birnbaum Importance  
                                                                                          Enclosure
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 as  
described in NRC Inspection Manual Chapter 0326, issued September 30, 2019  
10. *List and brief description of Operability Determinations and Functionality Assessments  


                                                2
2  
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
11. *List and reason for equipment that has been classified in maintenance rule (a)(1) status  
    available) of your plans to address the issue(s) along with dates added or removed from
    the issues list
12. *List of equipment on the sites Station Equipment Reliability Issues List, including a  
13. List of current operator work arounds/burdens
description of the reason(s) why each component is on that list, and summaries (if  
14. Copy of Updated Final Safety Analysis Report
available) of your plans to address the issue(s) along with dates added or removed from  
15. Copy of Technical Specification(s)
the issues list  
16. Copy of Technical Specifications Bases
17. Copy of Technical Requirements Manual(s)
13. List of current operator work arounds/burdens  
18. Copy of the Quality Assurance Program Manual
19. Copy of Corrective Action Program Procedure(s)
14. Copy of Updated Final Safety Analysis Report  
20. Copy of Operability Determination Procedure(s)
21. Copy of procedures addressing the following: Modifications, design changes, set point
15. Copy of Technical Specification(s)  
    changes, equivalency evaluations or suitability analyses, commercial grade dedications,
    post-modifications testing, 10 CFR 50.59 screenings and evaluations, and UFSAR updates
16. Copy of Technical Specifications Bases  
22. List of motor operated valves and air operated valves in the valve program, and their
    associated design margin and risk ranking
17. Copy of Technical Requirements Manual(s)  
23. Primary AC and DC calculations for safety-related buses
24. One-line diagram of electrical plant (Electronic only)
18. Copy of the Quality Assurance Program Manual  
25. Index and legend for electrical plant one-line diagrams
26. Piping and instrumentation diagrams (P&IDs) for safety-related systems (Electronic)
19. Copy of Corrective Action Program Procedure(s)  
27. Index and legend for P&IDs
28. Index (procedure number, title, and current revision) of station Emergency Operating
20. Copy of Operability Determination Procedure(s)  
    Procedures, Abnormal Operating Procedures, and Annunciator Response Procedures
29. Copies of corrective action documents generated from previous CDBI
21. Copy of procedures addressing the following: Modifications, design changes, set point  
30. Copy of any self-assessments performed, and corrective action documents generated, in
changes, equivalency evaluations or suitability analyses, commercial grade dedications,  
    preparation for current DBAI
post-modifications testing, 10 CFR 50.59 screenings and evaluations, and UFSAR updates
31. 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)
22. List of motor operated valves and air operated valves in the valve program, and their  
associated design margin and risk ranking  
23. Primary AC and DC calculations for safety-related buses  
24. One-line diagram of electrical plant (Electronic only)  
25. Index and legend for electrical plant one-line diagrams  
26. Piping and instrumentation diagrams (P&IDs) for safety-related systems (Electronic)  
27. Index and legend for P&IDs  
28. Index (procedure number, title, and current revision) of station Emergency Operating  
Procedures, Abnormal Operating Procedures, and Annunciator Response Procedures  
29. Copies of corrective action documents generated from previous CDBI  
30. Copy of any self-assessments performed, and corrective action documents generated, in  
preparation for current DBAI  
31. 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)
}}
}}

Latest revision as of 19:04, 27 November 2024

Notification of Brunswick Steam Electric Plant, Units 1 & 2 - Design Bases Assurance Inspection - U.S. Nuclear Regulatory Inspection Report 05000324/2022010 and 05000325/2022010
ML22018A184
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 01/18/2022
From: James Baptist
Division of Reactor Safety II
To: Krakuszeski J
Duke Energy Progress
References
IR 2022010
Download: ML22018A184 (4)
v • d • e


See also: IR 05000324/2022010

Text

January 18, 2022

Mr. John A. Krakuszeski

Site Vice President

Brunswick Steam Electric Plant

Duke Energy Progress, LLC

8470 River Rd. SE (M/C BNP001)

Southport, NC 28461

SUBJECT: NOTIFICATION OF BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 & 2

DESIGN BASES ASSURANCE INSPECTION - U.S. NUCLEAR REGULATORY

COMMISSION INSPECTION REPORT 05000324/2022010 AND

05000325/2022010

Dear Mr. Krakuszeski:

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 Brunswick

Steam Electric Plant Units 1 & 2 during the weeks of April 25 and May 9, 2022.

Mr. Paul Carman, 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

ML16340B000).

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 12, 2022, with Mr. Tom Sherrill we confirmed

arrangements for an information-gathering site visit and the two-week onsite inspection. The

schedule is as follows:

Information-gathering visit: April 4, 2022

Onsite weeks: Weeks of April 25 and May 9, 2022

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. Carman 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, March 25, 2022.

J. Krakuszeski

2

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, April 15, 2022, to support the inspection teams preparation week. During the

information-gathering trip, Mr. Carman 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. Carman at 404-997-4471 or contact

me at 404-997-4506.

Sincerely,

/RA/

James Baptist, Chief

Engineering Branch 1

Division of Reactor Safety

Docket Nos. 05000324 and 05000325

License Nos. DPR-62 and DPR-71

Enclosure:

Information Request for Brunswick Steam Electric Plant, Units 1 & 2

Design Bases Assurance Inspection (Teams)

cc w/ encl: Distribution via LISTSERV

Enclosure

INFORMATION REQUEST FOR BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 & 2

DESIGN BASES ASSURANCE INSPECTION (TEAMS)

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, 2019, until present.

1.

  • List and brief description of permanent and field work completed 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 as

described in NRC Inspection Manual Chapter 0326, issued September 30, 2019

10. *List and brief description of Operability Determinations and Functionality Assessments

2

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. List of motor operated valves and air operated valves in the valve program, and their

associated design margin and risk ranking

23. Primary AC and DC calculations for safety-related buses

24. One-line diagram of electrical plant (Electronic only)

25. Index and legend for electrical plant one-line diagrams

26. Piping and instrumentation diagrams (P&IDs) for safety-related systems (Electronic)

27. Index and legend for P&IDs

28. Index (procedure number, title, and current revision) of station Emergency Operating

Procedures, Abnormal Operating Procedures, and Annunciator Response Procedures

29. Copies of corrective action documents generated from previous CDBI

30. Copy of any self-assessments performed, and corrective action documents generated, in

preparation for current DBAI

31. 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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