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| number = ML15107A022
| number = ML15107A022
| 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:
{{#Wiki_filter:UNITED STATES
[[Issue date::April 16, 2015]]
                                NUCLEAR REGULATORY COMMISSION
 
                                                REGION II
Mr. David President and Chief Nuclear Officer Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
                            245 PEACHTREE CENTER AVENUE NE, SUITE 1200
 
                                      ATLANTA, GEORGIA 30303-1257
SUBJECT: NOTIFICATION OF NORTH ANNA POWER STATION - COMPONENT DESIGN BASES INSPECTION - U.S. NUCLEAR REGULATORY COMMISSION INSPECTION REPORT 05000338/2015007 AND 05000339/2015007
                                            April 16, 2015
 
Mr. David A. Heacock
==Dear Mr. 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)
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.
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 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.
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
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:  
71111.21, Component Design Bases Inspection, issued November 29, 2013.
* 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 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.
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.


Please provide the referenced information to the Region II Office by June 15, 2015. 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).
D. Heacock                                    2
 
Additional documents may be requested during the information-gathering visit. The inspectors
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.
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
Sincerely,/RA/
team in the Region II office prior to the inspection teams preparation week of July 13, 2015.
Jonathan Bartley, Chief Engineering Branch 1 Division of Reactor Safety  
During the information-gathering trip, Mr. Ottenberg will also discuss the following inspection
 
support administrative details: (1) availability of knowledgeable plant engineering and licensing
Docket Nos: 50-338, 50-339 License Nos: NPF-4, NPF-7  
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,
===Enclosure:===
(5) arrangements for site access, and (6) other applicable information.
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).
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
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.
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
Sincerely,/RA/ Jonathan Bartley, Chief Engineering Branch 1 Division of Reactor Safety
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
Docket Nos: 50-338, 50-339 License Nos: NPF-4, NPF-7
information requested or the inspection, please contact Mr. Ottenberg at 404-997-4658 or
 
contact me at 404-997-4607.
===Enclosure:===
                                                Sincerely,
Information Request for North Anna Power Station, Component Design Bases Inspection cc: Distribution via Listserv  
                                                /RA/
 
                                                Jonathan Bartley, Chief
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.
                                                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


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.
ML15107A022        x SUNSI REVIEW COMPLETE    FORM 665 ATTACHED
 
OFFICE              RII:DRS    RII:DRS
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.
SIGNATURE            GKO          JHB1
 
NAME              G. Ottenberg  J. Bartley
9. List and brief description of common-cause component failures that have occurred since July 1, 2012.
DATE              4/16/2015    4/16/2015
 
E-MAIL COPY?      YES      NO YES      NO
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).
                                           
 
              INFORMATION REQUEST FOR NORTH ANNA POWER STATION
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.
                            COMPONENT DESIGN BASES INSPECTION
 
Please provide the information electronically in .pdf files, Excel, or other searchable format on
12. List and reason for equipment classified in maintenance rule (a)(1) status from July 1, 2012, to present.
CDROM (or FTP site, Sharepoint, etc.). The CDROM (or website) should be indexed and
 
hyperlinked to facilitate ease of use.
13. Copy of Updated Final Safety Analysis Report. 14. Copy of Technical Specification(s).
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.
15. Copy of Technical Specifications Bases.
 
16. Copy of Technical Requirements Manual(s).
16. Copy of Technical Requirements Manual(s). 17. List and brief description of Root Cause Evaluations performed since July 1, 2012.
17. List and brief description of Root Cause Evaluations performed since July 1, 2012.
 
18. Corrective Action Program Procedure(s).
18. Corrective Action Program Procedure(s).
 
19. Copy of Operability Determination 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)  
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.
21. Index and legend for electrical plant one-line diagrams.
 
22. Piping and instrumentation diagrams (P&IDs) for safety-related systems. (Electronic
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)  
    and 1/2 size - hard copy week of June 29 - July 3, 2015)
 
23. Index and Legend for P&IDs.
23. Index and Legend for P&IDs.
 
24. Copies of corrective action documents (i.e. CRs) associated with findings from previous
24. Copies of corrective action documents (i.e. CRs) associated with findings from previous CDBI. (If applicable)
    CDBI. (If applicable)
25. Index (procedure number, title, and current revision) of station Emergency Operating Procedures, Abnormal Operating Procedures, and Annunciator Response Procedures.
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.
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).
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
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)
    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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