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| issue date = 12/20/2013
| issue date = 12/20/2013
| title = Notification of Joseph M. Farley Nuclear Plant, Units 1 and 2 Component Design Bases Inspection - NRC Inspection Report 05000348-14-007, 05000364-14-007
| title = Notification of Joseph M. Farley Nuclear Plant, Units 1 and 2 Component Design Bases Inspection - NRC Inspection Report 05000348-14-007, 05000364-14-007
| author name = Nease R L
| author name = Nease R
| author affiliation = NRC/RGN-II/DRS/EB1
| author affiliation = NRC/RGN-II/DRS/EB1
| addressee name = Lynch T A
| addressee name = Lynch T
| addressee affiliation = Southern Nuclear Operating Co, Inc
| addressee affiliation = Southern Nuclear Operating Co, Inc
| docket = 05000348, 05000364
| docket = 05000348, 05000364
Line 14: Line 14:
| page count = 6
| page count = 6
}}
}}
See also: [[followed by::IR 05000348/2014007]]
See also: [[see also::IR 05000348/2014007]]


=Text=
=Text=
{{#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
                                      ATLANTA, GEORGIA 30303-1257
-1257       December 20, 2013
                                        December 20, 2013
  Mr. T. A. Lynch
Mr. T. A. Lynch
Vice President
Vice President
Southern Nuclear Operating Company, Inc.
Southern Nuclear Operating Company, Inc.
Joseph M. Farley Nuclear Plant
Joseph M. Farley Nuclear Plant
P.O. Drawer 470, BIN B500
P.O. Drawer 470, BIN B500
Ashford, AL 36312
Ashford, AL 36312
  SUBJECT: NOTIFICATION OF
SUBJECT:         NOTIFICATION OF JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1, AND 2
JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1, AND 2   COMPONENT DESIGN BASES INSPECTION
                COMPONENT DESIGN BASES INSPECTION - NRC INSPECTION REPORT
- NRC INSPECTION REPORT
                05000348/2014007, 05000364/2014007
  05000348/2014007, 05000364/2014007
Dear Mr. Lynch:
  Dear Mr. Lynch: 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
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)
(CDBI) at your Farley Nuclear Plant, Units 1,  
Region II staff will conduct a component design bases inspection (CDBI) at your Farley Nuclear
and 2 during the weeks of May 5 - 9, May 19 - 23, and June 2 - 6, 2014. Tonya Lighty, a Project Engineer
Plant, Units 1, and 2 during the weeks of May 5 - 9, May 19 - 23, and June 2 - 6, 2014. Tonya
from the NRC's Region II Office, will lead the inspection team. This inspection will be conducted in accordance with the baseline inspection procedure, Procedure 71111.21,  
Lighty, a Project Engineer from the NRCs Region II Office, will lead the inspection team. This
"Component Design Bases Inspection,
inspection will be conducted in accordance with the baseline inspection procedure, Procedure
" issued November 29, 2013
71111.21, Component Design Bases Inspection, issued November 29, 2013.
.
The inspection will evaluate the capability of risk-significant / low margin components to function
The inspection will evaluate the capability of risk
as designed and to support proper system operation. The inspection will also include a review
-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.  
of selected operator actions, operating experience, and modifications.
  During a telephone conversation on December 13, 2013, Ms. Lighty confirmed with William Arens of your staff, arrangements for an information
During a telephone conversation on December 13, 2013, Ms. Lighty confirmed with William
-gathering site visit and the three
Arens of your staff, arrangements for an information-gathering site visit and the three-week
-week onsite inspection
onsite inspection. The schedule is as follows:
. The schedule is as follows:
    *  Information-gathering visit: Week of April 7 - 11, 2014
  Information
    *  Onsite weeks: May 5 - 9, May 19 - 23, and June 2 - 6, 2014
-gathering visit: Week of April 7 - 11, 2014 Onsite weeks: May 5 - 9, May 19  
The purpose of the information-gathering visit is to meet with members of your staff to identify
- 23, and June 2  
risk-significant components and operator actions. Information and documentation needed to
- 6, 2014 The purpose of the information
support the inspection will also be identified. Mr. George MacDonald, a Region II Senior
-gathering
Reactor Analyst, will support Ms. Lighty during the information-gathering visit to review
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. George MacDonald, a Region II Senior Reactor Analyst,  
probabilistic risk assessment data and identify risk-significant components, which will be
will support Ms. Lighty during the information
examined during the inspection.
-gathering
The enclosure lists documents needed prior to the information-gathering visit. Please provide
visit to review probabilistic risk assessment data and identify risk
the referenced information to the Region II Office by March 14, 2014.
-significant components, which
will be examined during the inspection.
  The enclosure lists documents needed prior to the information
-gathering
visit. Please provide the referenced information to the Region II Office by March 14, 2014.  
T.A. Lynch
2  Additional documents will 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 should
be available to the team in the Region II
Office prior to the inspection team's preparation week of April 28, 2014.  Ms. Lighty 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
Ms. Lighty at 404-997-4565 or contact me at 404-997-4530.        Sincerely,
        RA  Rebecca L. Nease, Chief        Engineering Branch 1
      Division of Reactor Safety
  Docket Nos.
:  50-348, 50-364 License Nos.
:  NPF-2, NPF-8  Enclosure:
  Information Request for Farley Nuclear Plant, Units 1, and 2, Component
  Design Bases
Inspection
  cc:  Distribution via Listserv
Additional documents will 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 should be available to the team in the Region II
Office prior to the inspection team's preparation week of April 28, 2014
.  Ms. Lighty
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).
 


_ __x SUNSI REVIEW COMPLETE FORM 665 ATTACHED
T.A. Lynch                                    2
  OFFICE RII: DRP RII: DRS RII: DRP     SIGNATURE
Additional documents will be requested during the information-gathering visit. The inspectors
  RA RA RA     NAME Lighty NEASE MacDonald
will try to minimize your administrative burden by specifically identifying only those documents
    DATE 12/ 20/2013 12/20/2013 12/20/2013
required for inspection preparation. The additional information should be available to the team
    E-MAIL COPY?
in the Region II Office prior to the inspection teams preparation week of April 28, 2014.
    YES NO       YES NO       YES NO       YES NO       YES NO       YES NO       YES NO    
Ms. Lighty will also discuss the following inspection support administrative details:
  Enclosure INFORMATION REQUEST FARLEY NUCLEAR PLANT, UNITS 1, AND 2 COMPONENT DESIGN BASES INSPECTION
(1) availability of knowledgeable plant engineering and licensing personnel to serve as points of
  Please provide the information electronically in ".pdf" files, Excel, or other searchable format on CDROM (or FTP site, Sharepoint, etc
contact during the inspection, (2) method of tracking inspector requests during the inspection,
.). The CDROM
(3) licensee computer access, (4) working space, (5) arrangements for site access, and (6)
(or website)
other applicable information.
should be indexed and hyperlinked to facilitate ease of use.  
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its
  1. From your most recent probabilistic safety analysis (PSA) excluding
enclosure will be available electronically for public inspection in the NRC Public Document
external events and fires: a. Two risk rankings of components from your site
Room or from the Publicly Available Records (PARS) component of NRC's Agencywide
-specific PSA: one sorted by Risk Achievement Worth (RAW), and the other sorted by Birnbaum Importance
Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC
  b. A list of the top 500 cutsets
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
2. From your most recent PSA including
information requested or the inspection, please contact Ms. Lighty at 404-997-4565 or contact
external events and fires:
me at 404-997-4530.
  a. Two risk rankings of components from your site
                                                Sincerely,
-specific PSA: one sorted by RAW, and the other sorted by Birnbaum Importance
                                                RA
  b. A list of the top 500 cutsets
                                                Rebecca L. Nease, Chief
    3. Risk ranking of operator actions from your site
                                                Engineering Branch 1
-specific PSA sorted
                                                Division of Reactor Safety
by RAW. Provide human reliability worksheets for these items
Docket Nos.: 50-348, 50-364
4. List of time
License Nos.: NPF-2, NPF-8
-critical operator actions with a brief description of each action
Enclosure:
5. List of Emergency and Abnormal Operating Procedures revised (significant) since September
Information Request for Farley Nuclear Plant, Units 1, and 2, Component
1, 2011, with a brief description of each revision
  Design Bases Inspection
6. List of components with low design margins (i.e., pumps closest to the design limit for flow  
cc: Distribution via Listserv
or pressure, diesel generator close to design-required output, heat exchangers close to rated design heat removal,  
Additional documents will be requested during the information-gathering visit. The inspectors
and motor-operated valve risk-margin rankings, etc.)
will try to minimize your administrative burden by specifically identifying only those documents
, and associated evaluations or calculations
required for inspection preparation. The additional information should be available to the team
7.  List of station operating experience evaluations/reviews performed
in the Region II Office prior to the inspection teams preparation week of April 28, 2014.
, and documented in the station's corrective action program
Ms. Lighty will also discuss the following inspection support administrative details:
, for industry events and safety
(1) availability of knowledgeable plant engineering and licensing personnel to serve as points of
-related equipment failures/vulnerabilities  
contact during the inspection, (2) method of tracking inspector requests during the inspection,
(as communicated by NRC  
(3) licensee computer access, (4) working space, (5) arrangements for site access, and (6)
Generic Communications, Industry  
other applicable information.
Communications, 10 CFR  
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its
Part 21 Notifications, etc.
enclosure will be available electronically for public inspection in the NRC Public Document
) since September
Room or from the Publicly Available Records (PARS) component of NRC's Agencywide
1, 2011.
Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC
8. List and brief description of safety
website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
-related structures, systems, or components (
 
SSCs) design modifications implemented since September
 
1, 2011. 9. List and brief description of common
_ __x SUNSI REVIEW COMPLETE FORM 665 ATTACHED
-cause component failures that have occurred  
  OFFICE             RII: DRP     RII: DRS     RII: DRP
  since September
  SIGNATURE          RA           RA           RA
1, 2011.
NAME               Lighty       NEASE       MacDonald
10. List and brief description of operability evaluations completed
DATE                 12/ 20/2013   12/20/2013   12/20/2013
since September
E-MAIL COPY?         YES     NO   YES     NO   YES     NO     YES NO     YES   NO     YES   NO YES NO
1, 2011.  
       
2 11. 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
          INFORMATION REQUEST FARLEY NUCLEAR PLANT, UNITS 1, AND 2
, and summaries (if available) of your plans to address the issue(s)
                            COMPONENT DESIGN BASES INSPECTION
.
Please provide the information electronically in .pdf files, Excel, or other searchable format on
12. List and brief description of equipment currently in degraded or nonconforming status as  
CDROM (or FTP site, Sharepoint, etc.). The CDROM (or website) should be indexed and
described in Regulatory  
hyperlinked to facilitate ease of use.
Issue Summary 05-020.
1. From your most recent probabilistic safety analysis (PSA) excluding external events and
13. List and reason for equipment classified in maintenance rule (a)(1) status from   September
    fires:
1, 2011, to present
          a. Two risk rankings of components from your site-specific PSA: one sorted by Risk
14. Copies of  
              Achievement Worth (RAW), and the other sorted by Birnbaum Importance
system descriptions (or the design basis documents) for safety-related systems. 15. Copy of Updated Final Safety Analysis Report.
          b. A list of the top 500 cutsets
16. Copy of Technical Specification
2. From your most recent PSA including external events and fires:
(s).
          a. Two risk rankings of components from your site-specific PSA: one sorted by RAW,
17. Copy of Technical Specifications Bases
              and the other sorted by Birnbaum Importance
18. Copy of Technical Requirements Manual(s)
          b.   A list of the top 500 cutsets
19. List and brief description of Root Cause Evaluations performed since September
3. Risk ranking of operator actions from your site-specific PSA sorted by RAW. Provide
1, 2011. 20. In-service Testing Program Procedure(s)
    human reliability worksheets for these items.
.
4.  List of time-critical operator actions with a brief description of each action.
21.   Corrective Action Program Procedure
5.  List of Emergency and Abnormal Operating Procedures revised (significant) since
(s).
    September 1, 2011, with a brief description of each revision.
22. One-line diagram of electrical plant
6.  List of components with low design margins (i.e., pumps closest to the design limit for flow
. (Electronic
    or pressure, diesel generator close to design-required output, heat exchangers close to
and full size
    rated design heat removal, and motor-operated valve risk-margin rankings, etc.), and
- hard copy week of  
    associated evaluations or calculations.
  April 7 - 11, 2014)
7.  List of station operating experience evaluations/reviews performed, and documented in the
23. Index and legend for electrical plant one
    stations corrective action program, for industry events and safety-related equipment
-line diagrams
    failures/vulnerabilities (as communicated by NRC Generic Communications, Industry
.
    Communications, 10 CFR Part 21 Notifications, etc.) since September 1, 2011.
24. Primary AC calculation(s) for safety
8. List and brief description of safety-related structures, systems, or components (SSCs)
-related buses
    design modifications implemented since September 1, 2011.
25. Primary DC calculation(s) for safety
9. List and brief description of common-cause component failures that have occurred
-related buses
    since September 1, 2011.
26. Piping and instrumentation diagrams (P&IDs)
10. List and brief description of operability evaluations completed since September 1, 2011.
for safety-related systems. (Electronic
                                                                                          Enclosure
and 1/2 size - hard copy week of April 7 - 11, 2014)
 
27. Index and Legend for P&
                                                2
IDs.
11. List of equipment on the sites Station Equipment Reliability Issues List, including a
28. Copy of Operability  
    description of the reason(s) why each component is on that list, and summaries (if
Determination procedure(s). 30. Copies of corrective action documents (i.e. CRs) associated with findings from previous CDBI. (If applicable)
    available) of your plans to address the issue(s).
  31. Index (procedure number, title, and current revision) of station Emergency Operating Procedures, Abnormal Operating Procedures, and Annunciator Response Procedures.
12. List and brief description of equipment currently in degraded or nonconforming status as
  32. Copy of any self
    described in Regulatory Issue Summary 05-020.
-assessments performed in preparation for this inspection
13. List and reason for equipment classified in maintenance rule (a)(1) status from
    September 1, 2011, to present.
3 33. List of any condition reports generated in preparation for this inspection
14. Copies of system descriptions (or the design basis documents) for safety-related systems.
. 34. Copies of condition reports generated from previous CDBI (
15. Copy of Updated Final Safety Analysis Report.
2011).
16. Copy of Technical Specification(s).
35. Contact information for a person to discuss PSA information prior to the information
17. Copy of Technical Specifications Bases.
-gathering
18. Copy of Technical Requirements Manual(s).
trip. (Name, title, phone number, and e
19. List and brief description of Root Cause Evaluations performed since September 1, 2011.
-mail address)
20. In-service Testing Program Procedure(s).
21. Corrective Action Program Procedure(s).
22. One-line diagram of electrical plant. (Electronic and full size - hard copy week of
    April 7 - 11, 2014)
23. Index and legend for electrical plant one-line diagrams.
24. Primary AC calculation(s) for safety-related buses.
25. Primary DC calculation(s) for safety-related buses.
26. Piping and instrumentation diagrams (P&IDs) for safety-related systems. (Electronic and
    1/2 size - hard copy week of April 7 - 11, 2014)
27. Index and Legend for P&IDs.
28. Copy of Operability Determination procedure(s).
30. Copies of corrective action documents (i.e. CRs) associated with findings from previous
    CDBI. (If applicable)
31. Index (procedure number, title, and current revision) of station Emergency Operating
    Procedures, Abnormal Operating Procedures, and Annunciator Response Procedures.
32. Copy of any self-assessments performed in preparation for this inspection.
 
                                                3
33. List of any condition reports generated in preparation for this inspection.
34. Copies of condition reports generated from previous CDBI (2011).
35. Contact information for a person to discuss PSA information prior to the information-
    gathering trip. (Name, title, phone number, and e-mail address)
}}
}}

Latest revision as of 10:58, 4 November 2019

Notification of Joseph M. Farley Nuclear Plant, Units 1 and 2 Component Design Bases Inspection - NRC Inspection Report 05000348-14-007, 05000364-14-007
ML13354B972
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 12/20/2013
From: Nease R
NRC/RGN-II/DRS/EB1
To: Lynch T
Southern Nuclear Operating Co
References
IR-14-007
Download: ML13354B972 (6)


See also: IR 05000348/2014007

Text

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION II

245 PEACHTREE CENTER AVENUE NE, SUITE 1200

ATLANTA, GEORGIA 30303-1257

December 20, 2013

Mr. T. A. Lynch

Vice President

Southern Nuclear Operating Company, Inc.

Joseph M. Farley Nuclear Plant

P.O. Drawer 470, BIN B500

Ashford, AL 36312

SUBJECT: NOTIFICATION OF JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1, AND 2

COMPONENT DESIGN BASES INSPECTION - NRC INSPECTION REPORT

05000348/2014007, 05000364/2014007

Dear Mr. Lynch:

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 Farley Nuclear

Plant, Units 1, and 2 during the weeks of May 5 - 9, May 19 - 23, and June 2 - 6, 2014. Tonya

Lighty, a Project Engineer from the NRCs Region II Office, will lead the inspection team. This

inspection will be conducted in accordance with the baseline inspection procedure, 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 December 13, 2013, Ms. Lighty confirmed with William

Arens 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 April 7 - 11, 2014
  • Onsite weeks: May 5 - 9, May 19 - 23, and June 2 - 6, 2014

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. George MacDonald, a Region II Senior

Reactor Analyst, will support Ms. Lighty 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 needed prior to the information-gathering visit. Please provide

the referenced information to the Region II Office by March 14, 2014.

T.A. Lynch 2

Additional documents will 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 should be available to the team

in the Region II Office prior to the inspection teams preparation week of April 28, 2014.

Ms. Lighty 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 Ms. Lighty at 404-997-4565 or contact

me at 404-997-4530.

Sincerely,

RA

Rebecca L. Nease, Chief

Engineering Branch 1

Division of Reactor Safety

Docket Nos.: 50-348, 50-364

License Nos.: NPF-2, NPF-8

Enclosure:

Information Request for Farley Nuclear Plant, Units 1, and 2, Component

Design Bases Inspection

cc: Distribution via Listserv

Additional documents will 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 should be available to the team

in the Region II Office prior to the inspection teams preparation week of April 28, 2014.

Ms. Lighty 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).

_ __x SUNSI REVIEW COMPLETE FORM 665 ATTACHED

OFFICE RII: DRP RII: DRS RII: DRP

SIGNATURE RA RA RA

NAME Lighty NEASE MacDonald

DATE 12/ 20/2013 12/20/2013 12/20/2013

E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO

INFORMATION REQUEST FARLEY NUCLEAR PLANT, UNITS 1, AND 2

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

September 1, 2011, 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.), and

associated evaluations or calculations.

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 September 1, 2011.

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

design modifications implemented since September 1, 2011.

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

since September 1, 2011.

10. List and brief description of operability evaluations completed since September 1, 2011.

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).

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

described in Regulatory Issue Summary 05-020.

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

September 1, 2011, to present.

14. Copies of system descriptions (or the design basis documents) for safety-related systems.

15. Copy of Updated Final Safety Analysis Report.

16. Copy of Technical Specification(s).

17. Copy of Technical Specifications Bases.

18. Copy of Technical Requirements Manual(s).

19. List and brief description of Root Cause Evaluations performed since September 1, 2011.

20. In-service Testing Program Procedure(s).

21. Corrective Action Program Procedure(s).

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

April 7 - 11, 2014)

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

24. Primary AC calculation(s) for safety-related buses.

25. Primary DC calculation(s) for safety-related buses.

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

1/2 size - hard copy week of April 7 - 11, 2014)

27. Index and Legend for P&IDs.

28. Copy of Operability Determination procedure(s).

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

CDBI. (If applicable)

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

Procedures, Abnormal Operating Procedures, and Annunciator Response Procedures.

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

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

34. Copies of condition reports generated from previous CDBI (2011).

35. Contact information for a person to discuss PSA information prior to the information-

gathering trip. (Name, title, phone number, and e-mail address)