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| issue date = 04/16/2015
| issue date = 04/16/2015
| title = Notification of North Anna Power Station - Component Design Bases Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000338/2015007 and 05000339/2015007
| title = Notification of North Anna Power Station - Component Design Bases Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000338/2015007 and 05000339/2015007
| author name = Bartley J H
| author name = Bartley J
| author affiliation = NRC/RGN-II/DRS/EB1
| author affiliation = NRC/RGN-II/DRS/EB1
| addressee name = Heacock D A
| addressee name = Heacock D
| addressee affiliation = Virginia Electric & Power Co (VEPCO)
| addressee affiliation = Virginia Electric & Power Co (VEPCO)
| docket = 05000338, 05000339
| docket = 05000338, 05000339
Line 14: Line 14:
| page count = 5
| page count = 5
}}
}}
See also: [[followed by::IR 05000338/2015007]]
See also: [[see also::IR 05000338/2015007]]


=Text=
=Text=
{{#Wiki_filter: UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257   April 16, 2015
{{#Wiki_filter:UNITED STATES
                                NUCLEAR REGULATORY COMMISSION
Mr. David A. Heacock President and Chief Nuclear Officer  
                                                REGION II
Virginia Electric and Power Company  
                            245 PEACHTREE CENTER AVENUE NE, SUITE 1200
Innsbrook Technical Center  
                                      ATLANTA, GEORGIA 30303-1257
5000 Dominion Boulevard  
                                            April 16, 2015
Glen Allen, VA 23060-6711 SUBJECT: NOTIFICATION OF NORTH ANNA POWER STATION - COMPONENT DESIGN BASES INSPECTION - U.S. NUCLEAR REGULATORY COMMISSION  
Mr. David A. Heacock
INSPECTION REPORT 05000338/2015007 AND 05000339/2015007
President and Chief Nuclear Officer
Dear Mr. Heacock: The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)  
Virginia Electric and Power Company
Region II staff will conduct a component design bases inspection (CDBI) at your North Anna  
Innsbrook Technical Center
Power Station during the weeks of July 20 - 24, August 3 - 7, and August 17 - 21, 2015.
5000 Dominion Boulevard
Geoffrey Ottenberg, a Senior Reactor Inspector from the NRC's Region II Office, will lead the inspection team. This inspection will be conducted in accordance with Inspection Procedure 71111.21, "Component Design Bases Inspection," issued November 29, 2013.  
Glen Allen, VA 23060-6711
SUBJECT: NOTIFICATION OF NORTH ANNA POWER STATION - COMPONENT DESIGN
The inspection will evaluate the capability of risk-significant /low-margin components to function  
              BASES INSPECTION - U.S. NUCLEAR REGULATORY COMMISSION
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 April 7, 2015, the staff confirmed with Mr. J. Leberstien of  
              INSPECTION REPORT 05000338/2015007 AND 05000339/2015007
your staff, arrangements for an information-gathering site visit and the three-week onsite  
Dear Mr. Heacock:
inspection. The schedule is as follows:  
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)
* Information-gathering visit: Week of June 29 - July 3, 2015 * Onsite weeks: July 20 - 24, August 3 - 7, and August 17 - 21, 2015 The purpose of the information-gathering visit is to meet with members of your staff to identify risk-significant components and operator actions. Information and documentation needed to support the inspection will also be identified. Mr. Geoffrey Ottenberg, a Senior Reactor  
Region II staff will conduct a component design bases inspection (CDBI) at your North Anna
Inspector, will be conducting all preparation activities associated with the inspection. In  
Power Station during the weeks of July 20 - 24, August 3 - 7, and August 17 - 21, 2015.
addition, Mr. George MacDonald, a Region II Senior Reactor Analyst, will support Mr. Ottenberg  
Geoffrey Ottenberg, a Senior Reactor Inspector from the NRCs Region II Office, will lead the
during the information-gathering visit to review probabilistic risk assessment data and identify risk-significant components, which will be examined during the inspection.
inspection team. This inspection will be conducted in accordance with Inspection Procedure
The Enclosure lists documents that will be needed prior to the information-gathering visit.
71111.21, Component Design Bases Inspection, issued November 29, 2013.
Please provide the referenced information to the Region II Office by June 15, 2015.  
The inspection will evaluate the capability of risk-significant /low-margin components to function
D. Heacock 2  Additional documents may be requested during the information-gathering visit.  The inspectors will try to minimize your administrative burden by specifically identifying only those documents
as designed and to support proper system operation. The inspection will also include a review
required for inspection preparation.  The additional information will need to be available to the team in the Region II office prior to the inspection team's preparation week of July 13, 2015.  During the information-gathering trip, Mr. Ottenberg will also discuss the following inspection
of selected operator actions, operating experience, and modifications.
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
During a telephone conversation on April 7, 2015, the staff confirmed with Mr. J. Leberstien of
requests during the inspection, (3) licensee computer access, (4) working space, 
your staff, arrangements for an information-gathering site visit and the three-week onsite
(5) arrangements for site access, and (6) other applicable information.  In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its
inspection. The schedule is as follows:
Enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's Agencywide
    *   Information-gathering visit: Week of June 29 - July 3, 2015
Documents Access and Management System (ADAMS).  ADAMS is accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). 
    *   Onsite weeks: July 20 - 24, August 3 - 7, and August 17 - 21, 2015
Thank you for your cooperation in this matter.  If you have any questions, regarding the
The purpose of the information-gathering visit is to meet with members of your staff to identify
information requested or the inspection, please contact Mr. Ottenberg at 404-997-4658 or
risk-significant components and operator actions. Information and documentation needed to
contact me at 404-997-4607.        Sincerely,
support the inspection will also be identified. Mr. Geoffrey Ottenberg, a Senior Reactor
Inspector, will be conducting all preparation activities associated with the inspection. In
      /RA/ 
addition, Mr. George MacDonald, a Region II Senior Reactor Analyst, will support Mr. Ottenberg
Jonathan Bartley, Chief        Engineering Branch 1
during the information-gathering visit to review probabilistic risk assessment data and identify
      Division of Reactor Safety
risk-significant components, which will be examined during the inspection.
The Enclosure lists documents that will be needed prior to the information-gathering visit.
Docket Nos: 50-338, 50-339 License Nos: NPF-4, NPF-7 
Please provide the referenced information to the Region II Office by June 15, 2015.
Enclosure: 
Information Request for North Anna Power 
  Station, Component Design Bases Inspection 
cc:  Distribution via Listserv 
2  Additional documents may be requested during 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 need to be available to the team in the Region II office prior to the inspection team's preparation week of July 13, 2015.  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.  In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its
Enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's Agencywide
Documents Access and Management System (ADAMS).  ADAMS is accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). 
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 404-997-4607.        Sincerely,
              /RA/  Jonathan Bartley, Chief        Engineering Branch 1
      Division of Reactor Safety
Docket Nos: 50-338, 50-339 License Nos: NPF-4, NPF-7 
Enclosure: 
Information Request for North Anna Power 
  Station, Component Design Bases Inspection
cc:  Distribution via Listserv 
x PUBLICLY AVAILABLE NON-PUBLICLY AVAILABLESENSITIVE x NON-SENSITIVE ADAMS: x Yes ACCESSION NUMBER:  ML15107A022                x SUNSI REVIEW COMPLETE        FORM 665 ATTACHED OFFICE RII:DRS RII:DRS      SIGNATURE GKO JHB1      NAME G. Ottenberg J. Bartley      DATE 4/16/2015 4/16/2015      E-MAIL COPY? YES NO YES NO      OFFICIAL RECORD COPY   
    Enclosure INFORMATION REQUEST FOR NORTH ANNA POWER STATION  COMPONENT DESIGN BASES 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. 
1. 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 cutsets  2. 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 cutsets    3. Risk ranking of operator actions from your site-specific PSA sorted by RAW.  Provide human reliability worksheets for these items.  4. List of time-critical operator actions with a brief description of each action.
5. List of Emergency and Abnormal Operating Procedures revised (significant) since  July 1, 2012, with a brief description of each revision. 
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.).  7.  List of station-operating experience evaluations/reviews performed, and documented in the station's corrective action program, for industry events and safety-related equipment
failures/vulnerabilities (as communicated by NRC Generic Communications, Industry
Communications, 10 CFR Part 21 Notifications, etc.) since July 1, 2012.  8. List and brief description of safety-related structures, systems, or components (SSCs) design modifications implemented since July 1, 2012. 
9. List and brief description of common-cause component failures that have occurred 
since July 1, 2012.
10. List of equipment on the site's 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). 
2  11. List and brief description of equipment currently in degraded or nonconforming status as described in NRC Inspection Manual Chapter 0326, Operability Determinations and
Functionality Assessments for Conditions Adverse to Quality or Safety, issued  January 31, 2014. 
12.  List and reason for equipment classified in maintenance rule (a)(1) status from 
July 1, 2012, to present.
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.  List and brief description of Root Cause Evaluations performed since July 1, 2012.
18.  Corrective Action Program Procedure(s).
19.  Copy of Operability Determination procedure(s).  20.  One-line diagram of electrical plant.  (Electronic and full size - hard copy week 
of June 29 - July 3, 2015)
21.  Index and legend for electrical plant one-line diagrams.
22.  Piping and instrumentation diagrams (P&IDs) for safety-related systems.  (Electronic  and 1/2 size - hard copy week of June 29 - July 3, 2015)
23.  Index and Legend for P&IDs.
24.  Copies of corrective action documents (i.e. CRs) associated with findings from previous CDBI.  (If applicable) 
25.  Index (procedure number, title, and current revision) of station Emergency Operating Procedures, Abnormal Operating Procedures, and Annunciator Response Procedures. 
26. Copy of any self-assessments performed in preparation for this inspection.  27.  List of any condition reports generated in preparation for this inspection.
28.  Copies of condition reports generated from previous CDBI (2012).
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) 


D. Heacock                                    2
Additional documents may be requested during 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 need to be available to the
team in the Region II office prior to the inspection teams preparation week of July 13, 2015.
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.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its
Enclosure will be available electronically for public inspection in the NRC Public Document
Room or from the Publicly Available Records (PARS) component of NRC's Agencywide
Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC
website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
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 404-997-4607.
                                                Sincerely,
                                                /RA/
                                                Jonathan Bartley, Chief
                                                Engineering Branch 1
                                                Division of Reactor Safety
Docket Nos: 50-338, 50-339
License Nos: NPF-4, NPF-7
Enclosure:
Information Request for North Anna Power
  Station, Component Design Bases Inspection
cc: Distribution via Listserv
ML15107A022        x SUNSI REVIEW COMPLETE    FORM 665 ATTACHED
OFFICE              RII:DRS    RII:DRS
SIGNATURE            GKO          JHB1
NAME              G. Ottenberg  J. Bartley
DATE              4/16/2015    4/16/2015
E-MAIL COPY?      YES      NO YES      NO
                                           
              INFORMATION REQUEST FOR NORTH ANNA POWER STATION
                            COMPONENT DESIGN BASES 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.
1.  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 cutsets
2.  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 cutsets
3.  Risk ranking of operator actions from your site-specific PSA sorted by RAW. Provide
    human reliability worksheets for these items.
4.  List of time-critical operator actions with a brief description of each action.
5.  List of Emergency and Abnormal Operating Procedures revised (significant) since
    July 1, 2012, with a brief description of each revision.
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.).
7.  List of station-operating experience evaluations/reviews performed, and documented in the
    stations corrective action program, for industry events and safety-related equipment
    failures/vulnerabilities (as communicated by NRC Generic Communications, Industry
    Communications, 10 CFR Part 21 Notifications, etc.) since July 1, 2012.
8.  List and brief description of safety-related structures, systems, or components (SSCs)
    design modifications implemented since July 1, 2012.
9.  List and brief description of common-cause component failures that have occurred
    since July 1, 2012.
10. 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).
                                                                                          Enclosure
                                                2
11. List and brief description of equipment currently in degraded or nonconforming status as
    described in NRC Inspection Manual Chapter 0326, Operability Determinations and
    Functionality Assessments for Conditions Adverse to Quality or Safety, issued
    January 31, 2014.
12. List and reason for equipment classified in maintenance rule (a)(1) status from
    July 1, 2012, to present.
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. List and brief description of Root Cause Evaluations performed since July 1, 2012.
18. Corrective Action Program Procedure(s).
19. Copy of Operability Determination procedure(s).
20. One-line diagram of electrical plant. (Electronic and full size - hard copy week
    of June 29 - July 3, 2015)
21. Index and legend for electrical plant one-line diagrams.
22. Piping and instrumentation diagrams (P&IDs) for safety-related systems. (Electronic
    and 1/2 size - hard copy week of June 29 - July 3, 2015)
23. Index and Legend for P&IDs.
24. Copies of corrective action documents (i.e. CRs) associated with findings from previous
    CDBI. (If applicable)
25. Index (procedure number, title, and current revision) of station Emergency Operating
    Procedures, Abnormal Operating Procedures, and Annunciator Response Procedures.
26. Copy of any self-assessments performed in preparation for this inspection.
27. List of any condition reports generated in preparation for this inspection.
28. Copies of condition reports generated from previous CDBI (2012).
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 13:55, 31 October 2019

Notification of North Anna Power Station - Component Design Bases Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000338/2015007 and 05000339/2015007
ML15107A022
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 04/16/2015
From: Bartley J
NRC/RGN-II/DRS/EB1
To: Heacock D
Virginia Electric & Power Co (VEPCO)
References
IR 2015007
Download: ML15107A022 (5)
v • d • e


See also: IR 05000338/2015007

Text

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION II

245 PEACHTREE CENTER AVENUE NE, SUITE 1200

ATLANTA, GEORGIA 30303-1257

April 16, 2015

Mr. David A. Heacock

President and Chief Nuclear Officer

Virginia Electric and Power Company

Innsbrook Technical Center

5000 Dominion Boulevard

Glen Allen, VA 23060-6711

SUBJECT: NOTIFICATION OF NORTH ANNA POWER STATION - COMPONENT DESIGN

BASES INSPECTION - U.S. NUCLEAR REGULATORY COMMISSION

INSPECTION REPORT 05000338/2015007 AND 05000339/2015007

Dear Mr. Heacock:

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

Region II staff will conduct a component design bases inspection (CDBI) at your North Anna

Power Station during the weeks of July 20 - 24, August 3 - 7, and August 17 - 21, 2015.

Geoffrey Ottenberg, a Senior Reactor Inspector from the NRCs Region II Office, will lead the

inspection team. This inspection will be conducted in accordance with Inspection Procedure 71111.21, Component Design Bases Inspection, issued November 29, 2013.

The inspection will evaluate the capability of 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 April 7, 2015, the staff confirmed with Mr. J. Leberstien of

your staff, arrangements for an information-gathering site visit and the three-week onsite

inspection. The schedule is as follows:

  • Information-gathering visit: Week of June 29 - July 3, 2015
  • Onsite weeks: July 20 - 24, August 3 - 7, and August 17 - 21, 2015

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

risk-significant components and operator actions. Information and documentation needed to

support the inspection will also be identified. Mr. Geoffrey Ottenberg, a Senior Reactor

Inspector, will be conducting all preparation activities associated with the inspection. In

addition, Mr. George MacDonald, a Region II Senior Reactor Analyst, will support Mr. Ottenberg

during the information-gathering visit to review probabilistic risk assessment data and identify

risk-significant components, which will be examined during the inspection.

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 June 15, 2015.

D. Heacock 2

Additional documents may be requested during 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 need to be available to the

team in the Region II office prior to the inspection teams preparation week of July 13, 2015.

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.

In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its

Enclosure will be available electronically for public inspection in the NRC Public Document

Room or from the Publicly Available Records (PARS) component of NRC's Agencywide

Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC

website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

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 404-997-4607.

Sincerely,

/RA/

Jonathan Bartley, Chief

Engineering Branch 1

Division of Reactor Safety

Docket Nos: 50-338, 50-339

License Nos: NPF-4, NPF-7

Enclosure:

Information Request for North Anna Power

Station, Component Design Bases Inspection

cc: Distribution via Listserv

ML15107A022 x SUNSI REVIEW COMPLETE FORM 665 ATTACHED

OFFICE RII:DRS RII:DRS

SIGNATURE GKO JHB1

NAME G. Ottenberg J. Bartley

DATE 4/16/2015 4/16/2015

E-MAIL COPY? YES NO YES NO

INFORMATION REQUEST FOR NORTH ANNA POWER STATION

COMPONENT DESIGN BASES 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.

1. 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 cutsets

2. 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 cutsets

3. Risk ranking of operator actions from your site-specific PSA sorted by RAW. Provide

human reliability worksheets for these items.

4. List of time-critical operator actions with a brief description of each action.

5. List of Emergency and Abnormal Operating Procedures revised (significant) since

July 1, 2012, with a brief description of each revision.

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.).

7. List of station-operating experience evaluations/reviews performed, and documented in the

stations corrective action program, for industry events and safety-related equipment

failures/vulnerabilities (as communicated by NRC Generic Communications, Industry

Communications, 10 CFR Part 21 Notifications, etc.) since July 1, 2012.

8. List and brief description of safety-related structures, systems, or components (SSCs)

design modifications implemented since July 1, 2012.

9. List and brief description of common-cause component failures that have occurred

since July 1, 2012.

10. 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).

Enclosure

2

11. List and brief description of equipment currently in degraded or nonconforming status as

described in NRC Inspection Manual Chapter 0326, Operability Determinations and

Functionality Assessments for Conditions Adverse to Quality or Safety, issued

January 31, 2014.

12. List and reason for equipment classified in maintenance rule (a)(1) status from

July 1, 2012, to present.

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. List and brief description of Root Cause Evaluations performed since July 1, 2012.

18. Corrective Action Program Procedure(s).

19. Copy of Operability Determination procedure(s).

20. One-line diagram of electrical plant. (Electronic and full size - hard copy week

of June 29 - July 3, 2015)

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

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

and 1/2 size - hard copy week of June 29 - July 3, 2015)

23. Index and Legend for P&IDs.

24. Copies of corrective action documents (i.e. CRs) associated with findings from previous

CDBI. (If applicable)

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

Procedures, Abnormal Operating Procedures, and Annunciator Response Procedures.

26. Copy of any self-assessments performed in preparation for this inspection.

27. List of any condition reports generated in preparation for this inspection.

28. Copies of condition reports generated from previous CDBI (2012).

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)

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