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{{#Wiki_filter:UNITED STATES
{{#Wiki_filter:UNITED STATES  
                                NUCLEAR REGULATORY COMMISSION
NUCLEAR REGULATORY COMMISSION  
                                                REGION II
REGION II  
                            245 PEACHTREE CENTER AVENUE NE, SUITE 1200
245 PEACHTREE CENTER AVENUE NE, SUITE 1200  
                                      ATLANTA, GEORGIA 30303-1257
ATLANTA, GEORGIA 30303-1257  
                                              July 9, 2018
Mr. Daniel G. Stoddard
July 9, 2018  
Senior Vice President and
  Chief Nuclear Officer
Innsbrook Technical Center
Mr. Daniel G. Stoddard  
5000 Dominion Boulevard
Senior Vice President and  
Glen Allen, VA 23060-6711
    Chief Nuclear Officer  
SUBJECT: NOTIFICATION OF NORTH ANNA POWER STATION, UNITS 1 & 2 DESIGN
Innsbrook Technical Center
              BASES ASSURANCE INSPECTION (TEAM) - U.S. NUCLEAR REGULATORY
5000 Dominion Boulevard  
              COMMISSION INSPECTION REPORT 05000338/2018010 AND
Glen Allen, VA 23060-6711  
              05000339/2018010
Dear Mr. Stoddard:
SUBJECT: NOTIFICATION OF NORTH ANNA POWER STATION, UNITS 1 & 2 DESIGN  
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)
BASES ASSURANCE INSPECTION (TEAM) - U.S. NUCLEAR REGULATORY  
Region II staff will conduct a Design Bases Assurance Inspection (DBAI) at your North Anna
COMMISSION INSPECTION REPORT 05000338/2018010 AND  
Power Station, Units 1 & 2 during the weeks of October 29 and November 26, 2018.
05000339/2018010  
Mr. 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
Dear Mr. Stoddard:  
71111.21M, Design Bases Assurance Inspection (Team), dated December 8, 2016 (ADAMS
ML16340B000).
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 North Anna  
Power Station, Units 1 & 2 during the weeks of October 29 and November 26, 2018.  
Mr. 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, Design Bases Assurance Inspection (Team), 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 June 28, 2018, with Mr. Donald Taylor, we confirmed
arrangements for an information-gathering site visit and the two-week onsite inspection. The
During a telephone conversation on June 28, 2018, with Mr. Donald Taylor, we confirmed  
schedule is as follows:
arrangements for an information-gathering site visit and the two-week onsite inspection. The  
    *   Information-gathering visit: Week of September 4- 7, 2018
schedule is as follows:  
    *   Onsite weeks: Weeks of October 29- November 2, 2018 and November 26- 30, 2018
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: Week of September 4- 7, 2018  
Information and documentation needed to support the inspection will also be identified.
*  
Mr. George Macdonald, a Region II Senior Risk Analyst, will support Mr. Ottenberg during the
Onsite weeks: Weeks of October 29- November 2, 2018 and November 26- 30, 2018  
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
The purpose of the information-gathering visit is to meet with members of your staff to identify  
on the plant-referenced simulator in order 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.  
Mr. George Macdonald, a Region II Senior Risk Analyst, will support Mr. 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 will be needed  
on the plant-referenced simulator in order to facilitate the development of operator action-based  
scenarios.


D. Stoddard                                   2
D. Stoddard  
The enclosure lists documents that will be needed prior to the information-gathering visit.
2  
Please provide the referenced information to the Region II Office by August 24, 2018.
The enclosure lists documents that will be needed prior to the information-gathering visit.
Additional documents will be requested following the information-gathering visit. The inspectors
Please provide the referenced information to the Region II Office by August 24, 2018.
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 October 19, 2018, 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. Ottenberg will also discuss the following inspection support
office by October 19, 2018, to support the inspection teams preparation week. During the  
administrative details: (1) availability of knowledgeable plant engineering and licensing
information-gathering trip, Mr. Ottenberg 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; (5)
personnel to serve as points of contact during the inspection; (2) method of tracking inspector  
arrangements for site access; and (6) other applicable information.
requests during the inspection; (3) licensee computer access; (4) working space; (5)  
This letter, its enclosure, and your response (if any) will be made available for public inspection
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. Ottenberg at 404-997-4658 or
Withholding.  
contact me at 404-997-4639.
                                                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. Ottenberg at 404-997-4658 or  
                                                Marvin D. Sykes, Chief
contact me at 404-997-4639.  
                                                Engineering Branch 1
                                                Division of Reactor Safety
Docket Nos.: 50-338, 50-339
License Nos.: NPF-4, NPF-7
Enclosure:
Notification of North Anna Power Station, units 1 & 2,
   Design Bases Assurance Inspection (Team)
cc: Distribution via Listserv
Sincerely,  
/RA/  
Marvin D. Sykes, Chief
Engineering Branch 1  
Division of Reactor Safety  
Docket Nos.: 50-338, 50-339  
License Nos.: NPF-4, NPF-7  
Enclosure:
Notification of North Anna Power Station, units 1 & 2,
   Design Bases Assurance Inspection (Team)
cc: Distribution via Listserv  




______________               SUNSI REVIEW COMPLETE   FORM 665 ATTACHED
______________  
OFFICE           RII:DRS       RII:DRS
  SIGNATURE        GKO          MDS EMAIL
SUNSI REVIEW COMPLETE  
  NAME              OTTENBERG    SYKES
FORM 665 ATTACHED  
  DATE                  7/9/2018    6/29/2018
OFFICE  
  E-MAIL COPY?        YES    NO  YES      NO
RII:DRS  
       
RII:DRS  
        INFORMATION REQUEST FOR NORTH ANNA POWER STATION, UNITS 1 & 2
   
                        DESIGN BASES ASSURANCE INSPECTION (TEAM)
   
Please provide the information electronically in .pdf files, Excel, or other searchable format on
   
file sharing website, if utilized (ex. FTP site, SharePoint, etc.) or CDROM. The website (or
   
CDROM) should be indexed and hyperlinked to facilitate ease of use. The requested items
below, identified with an asterisk (*), should have a date range from April 1, 2015, until
SIGNATURE
present.
GKO 
1.    *List and brief description of permanent and field work completed plant modifications
MDS EMAIL
      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:
NAME
            a. Two risk rankings of components from your site-specific PSA: one sorted by Risk
OTTENBERG
                Achievement Worth (RAW), and the other sorted by Birnbaum Importance
SYKES
            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
DATE
4.    Risk ranking of operator actions from your site-specific PSA sorted by RAW and human
7/9/2018
      reliability worksheets for these items
6/29/2018
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
E-MAIL COPY?
8.    *List and brief description of common-cause component failures that have occurred
    YES
9.    List and brief description of equipment currently in degraded or nonconforming status as
NO   
      described in NRC Inspection Manual Chapter 0326, issued November 20, 2017
  YES
                                                                                          Enclosure
NO     


                                                2
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
Enclosure
12. *List of equipment on the sites Station Equipment Reliability Issues List, including a
INFORMATION REQUEST FOR NORTH ANNA POWER STATION, UNITS 1 & 2
    description of the reason(s) why each component is on that list, and summaries (if
DESIGN BASES ASSURANCE INSPECTION (TEAM)  
    available) of your plans to address the issue(s) along with dates added or removed from
    the issues list
Please provide the information electronically in .pdf files, Excel, or other searchable format on  
13. List of current operator work arounds/burdens
file sharing website, if utilized (ex. FTP site, SharePoint, etc.) or CDROM.  The website (or
14. Copy of Updated Final Safety Analysis Report
CDROM) should be indexed and hyperlinked to facilitate ease of use. The requested items
15. Copy of Technical Specification(s)
below, identified with an asterisk (*), should have a date range from April 1, 2015, until
16. Copy of Technical Specifications Bases
present.  
17. Copy of Technical Requirements Manual(s)
18. Copy of the Quality Assurance Program Manual
1.  
19. Copy of Corrective Action Program Procedure(s)
*List and brief description of permanent and field work completed plant modifications
20. Copy of Operability Determination Procedure(s)
including permanent plant changes, design changes, set point changes, procedure
21. Copy of procedures addressing the following: Modifications, design changes, set point
changes, equivalency evaluations, suitability analyses, calculations, and commercial grade  
    changes, equivalency evaluations or suitability analyses, commercial grade dedications,
dedications.  Include an index of systems (system numbers/designators and corresponding
    post-modifications testing, 10 CFR 50.59 screenings and evaluations, and UFSAR updates.
names), the safety classification for each modification, and type of modification.
22. List of motor operated valves and air operated valves in the valve program, and their
    associated design margin and risk ranking
2.  
23. Primary AC and DC calculations for safety-related buses
From your most recent probabilistic safety analysis (PSA) excluding external events and  
24. One-line diagram of electrical plant (Electronic only)
fires:
25. Index and legend for electrical plant one-line diagrams
26. Piping and instrumentation diagrams (P&IDs) for safety-related systems (Electronic)
a. Two risk rankings of components from your site-specific PSA:  one sorted by Risk
27. Index and legend for P&IDs
Achievement Worth (RAW), and the other sorted by Birnbaum Importance
28. Index (procedure number, title, and current revision) of station Emergency Operating
    Procedures, Abnormal Operating Procedures, and Annunciator Response Procedures
b. A list of the top 500 cut-sets
29. Copies of corrective action documents generated from previous CDBI
30. Copy of any self-assessments performed, and corrective action documents generated, in
c. A list of the top 500 LERF contributors
    preparation for current DBAI
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 November 20, 2017


                                                3
2
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)
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. 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
 
3  
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 17:51, 5 January 2025

Notification of North Anna Power Station, Units 1 & 2 Design Bases Assurance Inspection (Team) - U.S. Nuclear Regulatory Commission Inspection Report 05000338/2018010 and 05000339/2018010
ML18190A478
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 07/09/2018
From: Marvin Sykes
NRC/RGN-II/DRS/EB1
To: Stoddard D
Virginia Electric & Power Co (VEPCO)
References
IR 2018010
Download: ML18190A478 (6)
v • d • e


See also: IR 05000338/2018010

Text

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION II

245 PEACHTREE CENTER AVENUE NE, SUITE 1200

ATLANTA, GEORGIA 30303-1257

July 9, 2018

Mr. Daniel G. Stoddard

Senior Vice President and

Chief Nuclear Officer

Innsbrook Technical Center

5000 Dominion Boulevard

Glen Allen, VA 23060-6711

SUBJECT: NOTIFICATION OF NORTH ANNA POWER STATION, UNITS 1 & 2 DESIGN

BASES ASSURANCE INSPECTION (TEAM) - U.S. NUCLEAR REGULATORY

COMMISSION INSPECTION REPORT 05000338/2018010 AND

05000339/2018010

Dear Mr. Stoddard:

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 North Anna

Power Station, Units 1 & 2 during the weeks of October 29 and November 26, 2018.

Mr. 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, Design Bases Assurance Inspection (Team), 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 June 28, 2018, with Mr. Donald Taylor, 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 September 4- 7, 2018

Onsite weeks: Weeks of October 29- November 2, 2018 and November 26- 30, 2018

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. George Macdonald, a Region II Senior Risk Analyst, will support Mr. 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 will be needed

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

scenarios.

D. Stoddard

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 August 24, 2018.

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 October 19, 2018, 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 404-997-4639.

Sincerely,

/RA/

Marvin D. Sykes, Chief

Engineering Branch 1

Division of Reactor Safety

Docket Nos.: 50-338, 50-339

License Nos.: NPF-4, NPF-7

Enclosure:

Notification of North Anna Power Station, units 1 & 2,

Design Bases Assurance Inspection (Team)

cc: Distribution via Listserv

______________

SUNSI REVIEW COMPLETE

FORM 665 ATTACHED

OFFICE

RII:DRS

RII:DRS

SIGNATURE

GKO

MDS EMAIL

NAME

OTTENBERG

SYKES

DATE

7/9/2018

6/29/2018

E-MAIL COPY?

YES

NO

YES

NO

Enclosure

INFORMATION REQUEST FOR NORTH ANNA POWER STATION, UNITS 1 & 2

DESIGN BASES ASSURANCE INSPECTION (TEAM)

Please provide the information electronically in .pdf files, Excel, or other searchable format on

file sharing website, if utilized (ex. FTP site, SharePoint, etc.) or CDROM. The website (or

CDROM) should be indexed and hyperlinked to facilitate ease of use. The requested items

below, identified with an asterisk (*), should have a date range from April 1, 2015, 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 November 20, 2017

2

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. 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

3

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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