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#REDIRECT [[IR 05000369/2021010]]
{{Adams
| number = ML20280A672
| issue date = 10/06/2020
| title = Notfication of McGuire Nuclear Station Design Bases Assurance Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000369/2021010 and 05000370/2021010
| author name = Baptist J
| author affiliation = NRC/RGN-II/DRS/EB2
| addressee name = Ray T
| addressee affiliation = Duke Energy Carolinas, LLC
| docket = 05000369, 05000370
| license number = NPF-009, NPF-017
| contact person =
| document report number = IR 2021010
| document type = Inspection Plan, Letter
| page count = 5
}}
See also: [[see also::IR 05000369/2021010]]
 
=Text=
{{#Wiki_filter:UNITED STATES
                                NUCLEAR REGULATORY COMMISSION
                                                REGION II
                            245 PEACHTREE CENTER AVENUE NE, SUITE 1200
                                      ATLANTA, GEORGIA 30303-1257
                                          October 6, 2020
Mr. Tom Ray
Site Vice President
Duke Energy Carolinas, LLC
12700 Hagers Ferry Road
Huntersville, NC 28078-8985
SUBJECT: NOTIFICATION OF MCGUIRE NUCLEAR STATION DESIGN BASES
              ASSURANCE INSPECTION - U.S. NUCLEAR REGULATORY COMMISSION
              INSPECTION REPORT 05000369/2021010 AND 05000370/2021010
Dear Mr. Ray:
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 McGuire
Nuclear Station during the weeks of January 25 - 29, and February 8 - 12, 2021.
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 October 1, 2020, with Mr. Joseph Hussey and Jeff Thomas
we confirmed arrangements for an information-gathering site visit and the two-week onsite
inspection. The schedule is as follows:
    *  Information-gathering visit: January 5, 2021
    *  Onsite weeks: Weeks of January 25 - 29, and February 8 - 12, 2021
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 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 will be needed
on the plant-referenced simulator in order to facilitate the development of operator action-based
scenarios.
 
T. Ray                                        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 Monday, December 28,
2020. 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, January 15, 2021, 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.: 50-369, 50-370
License Nos.: NPF-9, NPF-17
Enclosure:
Notification of McGuire Nuclear Station,
  Design Bases Assurance Inspection (Teams)
cc: Distribution via Listserv
 
T. Ray
SUBJECT: NOTIFICATION OF MCGUIRE NUCLEAR STATION DESIGN BASES
            ASSURANCE INSPECTION - U.S. NUCLEAR REGULATORY COMMISSION
            INSPECTION REPORT 05000369/2021010 AND 05000370/2021010
DISTRIBUTION:
M. Kowal, RII
S. Price, RII
L. Gibson, RII
RidsNrrPMMcGuire Resource
PUBLIC
ADAMS: ACCESSION NO: ML20280A672
OFFICE          RII: DRS          RII: DRS
NAME            P. Carman          J. Baptist
DATE            10/5/2020          10/6/2020
 
                INFORMATION REQUEST FOR MCGUIRE NUCLEAR STATION
                      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, 2017, 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 Operability Determinations and Functionality Assessments
10. *List and reason for equipment that has been classified in maintenance rule (a)(1) status
                                                                                          Enclosure
 
                                                2
11. *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
12. List of current operator work arounds/burdens
13. Copy of Updated Final Safety Analysis Report
14. Copy of Technical Specification(s)
15. Copy of Technical Specifications Bases
16. Copy of Technical Requirements Manual(s)
17. Copy of the Quality Assurance Program Manual
18. Copy of Corrective Action Program Procedure(s)
19. Copy of Operability Determination Procedure(s)
20. List of motor operated valves and air operated valves in the valve program, and their
    associated design margin and risk ranking
21. Primary AC and DC calculations for safety-related buses
22. One-line diagram of electrical plant (Electronic only)
23. Index and legend for electrical plant one-line diagrams
24. Piping and instrumentation diagrams (P&IDs) for safety-related systems (Electronic)
25. Index and legend for P&IDs
26. Index (procedure number, title, and current revision) of station Emergency Operating
    Procedures, Abnormal Operating Procedures, and Annunciator Response Procedures
27. Copies of corrective action documents generated from previous CDBI
28. Copy of any self-assessments performed, and corrective action documents generated, in
    preparation for current DBAI
29. 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 17:24, 26 March 2021

Notfication of McGuire Nuclear Station Design Bases Assurance Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000369/2021010 and 05000370/2021010
ML20280A672
Person / Time
Site: Mcguire, McGuire  Duke Energy icon.png
Issue date: 10/06/2020
From: James Baptist
NRC/RGN-II/DRS/EB2
To: Teresa Ray
Duke Energy Carolinas
References
IR 2021010
Download: ML20280A672 (5)


See also: IR 05000369/2021010

Text

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION II

245 PEACHTREE CENTER AVENUE NE, SUITE 1200

ATLANTA, GEORGIA 30303-1257

October 6, 2020

Mr. Tom Ray

Site Vice President

Duke Energy Carolinas, LLC

12700 Hagers Ferry Road

Huntersville, NC 28078-8985

SUBJECT: NOTIFICATION OF MCGUIRE NUCLEAR STATION DESIGN BASES

ASSURANCE INSPECTION - U.S. NUCLEAR REGULATORY COMMISSION

INSPECTION REPORT 05000369/2021010 AND 05000370/2021010

Dear Mr. Ray:

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 McGuire

Nuclear Station during the weeks of January 25 - 29, and February 8 - 12, 2021.

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 October 1, 2020, with Mr. Joseph Hussey and Jeff Thomas

we confirmed arrangements for an information-gathering site visit and the two-week onsite

inspection. The schedule is as follows:

  • Information-gathering visit: January 5, 2021
  • Onsite weeks: Weeks of January 25 - 29, and February 8 - 12, 2021

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 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 will be needed

on the plant-referenced simulator in order to facilitate the development of operator action-based

scenarios.

T. Ray 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 Monday, December 28,

2020. 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, January 15, 2021, 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.: 50-369, 50-370

License Nos.: NPF-9, NPF-17

Enclosure:

Notification of McGuire Nuclear Station,

Design Bases Assurance Inspection (Teams)

cc: Distribution via Listserv

T. Ray

SUBJECT: NOTIFICATION OF MCGUIRE NUCLEAR STATION DESIGN BASES

ASSURANCE INSPECTION - U.S. NUCLEAR REGULATORY COMMISSION

INSPECTION REPORT 05000369/2021010 AND 05000370/2021010

DISTRIBUTION:

M. Kowal, RII

S. Price, RII

L. Gibson, RII

RidsNrrPMMcGuire Resource

PUBLIC

ADAMS: ACCESSION NO: ML20280A672

OFFICE RII: DRS RII: DRS

NAME P. Carman J. Baptist

DATE 10/5/2020 10/6/2020

INFORMATION REQUEST FOR MCGUIRE NUCLEAR STATION

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, 2017, 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 Operability Determinations and Functionality Assessments

10. *List and reason for equipment that has been classified in maintenance rule (a)(1) status

Enclosure

2

11. *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

12. List of current operator work arounds/burdens

13. Copy of Updated Final Safety Analysis Report

14. Copy of Technical Specification(s)

15. Copy of Technical Specifications Bases

16. Copy of Technical Requirements Manual(s)

17. Copy of the Quality Assurance Program Manual

18. Copy of Corrective Action Program Procedure(s)

19. Copy of Operability Determination Procedure(s)

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

associated design margin and risk ranking

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

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

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

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

25. Index and legend for P&IDs

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

Procedures, Abnormal Operating Procedures, and Annunciator Response Procedures

27. Copies of corrective action documents generated from previous CDBI

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

preparation for current DBAI

29. 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)