ML13354B972: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
 
Line 18: Line 18:
=Text=
=Text=
{{#Wiki_filter:UNITED STATES
{{#Wiki_filter:UNITED STATES
NUCLEAR REGULATORY COMMISSION
                                NUCLEAR REGULATORY COMMISSION
REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200
                                                REGION II
ATLANTA, GEORGIA 30303
                            245 PEACHTREE CENTER AVENUE NE, SUITE 1200
-1257       December 20, 2013
                                      ATLANTA, GEORGIA 30303-1257
  Mr. T. A. Lynch
                                        December 20, 2013
Vice President
Mr. T. A. Lynch
Southern Nuclear Operating Company, Inc.
Vice President
Joseph M. Farley Nuclear Plant
Southern Nuclear Operating Company, Inc.
P.O. Drawer 470, BIN B500
Joseph M. Farley Nuclear Plant
Ashford, AL 36312
P.O. Drawer 470, BIN B500
  SUBJECT: NOTIFICATION OF
Ashford, AL 36312
JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1, AND 2   COMPONENT DESIGN BASES INSPECTION
SUBJECT:         NOTIFICATION OF JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1, AND 2
- NRC INSPECTION REPORT
                COMPONENT DESIGN BASES INSPECTION - NRC INSPECTION REPORT
  05000348/2014007, 05000364/2014007
                05000348/2014007, 05000364/2014007
  Dear M r. 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
Dear Mr. Lynch:
(CDBI) at your Farley Nuclear Plant, Units 1, and 2 during the weeks of May 5 - 9, Ma y 19 - 23, and June 2 - 6, 2014. Tonya Lighty, a Project Engineer
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)
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, "Component Design Bases Inspection," issued November 29, 2013
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
The inspection will evaluate the capability of risk
Lighty, a Project Engineer from the NRCs Region II Office, will lead the inspection team. This
-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.  
inspection will be conducted in accordance with the baseline inspection procedure, Procedure
  During a telephone conversation on December 13, 201 3 , M s. Lighty confirmed with William Arens of your staff, arrangements for an information
71111.21, Component Design Bases Inspection, issued November 29, 2013.
-gathering site visit and the three
The inspection will evaluate the capability of risk-significant / low margin components to function
-week onsite inspection
as designed and to support proper system operation. The inspection will also include a review
. The schedule is as follows:
of selected operator actions, operating experience, and modifications.
  Information
During a telephone conversation on December 13, 2013, Ms. Lighty confirmed with William
-gathering visit: Week of April 7 - 11 , 201 4  Onsite weeks: May 5 - 9, May 19  
Arens of your staff, arrangements for an information-gathering site visit and the three-week
- 23, and June 2  
onsite inspection. The schedule is as follows:
- 6, 2014 The purpose of the information
    *  Information-gathering visit: Week of April 7 - 11, 2014
-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, w ill support M s. Lighty during the information
    *  Onsite weeks: May 5 - 9, May 19 - 23, and June 2 - 6, 2014
-gathering visit to review probabilistic risk assessment data and identify risk
The purpose of the information-gathering visit is to meet with members of your staff to identify
-significant components, which
risk-significant components and operator actions. Information and documentation needed to
will be examined during the inspection.
support the inspection will also be identified. Mr. George MacDonald, a Region II Senior
  The enclosure lists documents needed prior to the information
Reactor Analyst, will support Ms. Lighty during the information-gathering visit to review
-gathering visit. Please provide the referenced information to the Region II Office by March 1 4, 201 4. 
probabilistic risk assessment data and identify risk-significant components, which will be
T.A. Lynch
examined during the inspection.
2  Additional documents will be requested during the information
The enclosure lists documents needed prior to the information-gathering visit. Please provide
-gathering visit. The inspectors will try to minimize your administrative burden by specifically identifying only those documents required for inspection preparation.
the referenced information to the Region II Office by March 14, 2014.
  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.   M s. 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
w e bsite 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
M s. Lighty at 404-997-4 565 or contact me at 404-997-4 530.        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
w e bsite 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: DR P RII: DRS RII: DR P    SIGNATURE RA RA RA     NAME Lighty NEASE MacDonald     DATE 12/ 20/2013 1 2/20/2013 12/20/2013
Additional documents will be requested during the information-gathering visit. The inspectors
    E-MAIL COPY?
will try to minimize your administrative burden by specifically identifying only those documents
    YES NO       YES NO       YES NO       YES NO       YES NO       YES NO       YES NO    
required for inspection preparation. The additional information should be available to the team
  Enclosur e INFORMATION REQUEST FARLEY NUCLEAR PLANT, UNITS 1, AND 2 COMPONENT DESIGN BASES INSPECTION
in the Region II Office prior to the inspection teams preparation week of April 28, 2014.
  Please provide the information electronically in ".pdf" files, Excel, or other searchable format on CDROM (or FTP site, Sharepoint, etc
Ms. Lighty will also discuss the following inspection support administrative details:
.). The CDROM (or website)
(1) availability of knowledgeable plant engineering and licensing personnel to serve as points of
should be indexed and hyperlinked to facilitate ease of use.  
contact during the inspection, (2) method of tracking inspector requests during the inspection,
  1. From your most recent probabilistic safety analysis (PSA) excluding external events and fires: a. Two risk rankings of components from your site
(3) licensee computer access, (4) working space, (5) arrangements for site access, and (6)
-specific PSA: one sorted by Risk Achievement Worth (RAW), and the other sorted by Birnbaum Importance
other applicable information.
  b. A list of the top 500 cutsets
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
2. From your most recent PSA including external events and fires:
Room or from the Publicly Available Records (PARS) component of NRC's Agencywide
  a. Two risk rankings of components from your site
Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC
-specific PSA: one sorted by RAW, and the other sorted by Birnbaum Importance
website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
  b. A list of the top 500 cutsets
Thank you for your cooperation in this matter. If you have any questions, regarding the
    3. Risk ranking of operator actions from your site
information requested or the inspection, please contact Ms. Lighty at 404-997-4565 or contact
-specific PSA sorted
me at 404-997-4530.
by RAW. Provide human reliability worksheets for these items
                                                Sincerely,
.  4. List of time
                                                RA
-critical operator actions with a brief description of each action
                                                Rebecca L. Nease, Chief
.  5. List of Emergency and Abnormal Operating Procedures revised (significant) since September 1, 20 11 , with a brief description of each revision
                                                Engineering Branch 1
.  6. List of components with low design margins (i.e., pumps closest to the design limit for flow  
                                                Division of Reactor Safety
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
Docket Nos.: 50-348, 50-364
.  7.  List of station operating experience evaluations/reviews performed , and documented in the station's corrective action program , for industry events and safety
License Nos.: NPF-2, NPF-8
-related equipment failures/vulnerabilities  
Enclosure:
(as communicated by NRC  
Information Request for Farley Nuclear Plant, Units 1, and 2, Component
Generic Communications, Industry Communications, 10 CFR  
  Design Bases Inspection
Part 21 Notifications, etc.
cc: Distribution via Listserv
) since September 1, 2011.
Additional documents will be requested during the information-gathering visit. The inspectors
8. List and brief description of safety
will try to minimize your administrative burden by specifically identifying only those documents
-related structures, systems, or components (SSC s) design modifications implemented since September 1, 2011. 9. List and brief description of common
required for inspection preparation. The additional information should be available to the team
-cause component failures that have occurred  
in the Region II Office prior to the inspection teams preparation week of April 28, 2014.
  since September 1, 2011.
Ms. Lighty will also discuss the following inspection support administrative details:
10. List and brief description of operability evaluations completed
(1) availability of knowledgeable plant engineering and licensing personnel to serve as points of
since September 1, 2011.  
contact during the inspection, (2) method of tracking inspector requests during the inspection,
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 , and summaries (if available) of your plans to address the issue(s)
(3) licensee computer access, (4) working space, (5) arrangements for site access, and (6)
.
other applicable information.
12. List and brief description of equipment currently in degraded or nonconforming status as  
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its
described in Regulatory  
enclosure will be available electronically for public inspection in the NRC Public Document
Issue Summary 05-020.
Room or from the Publicly Available Records (PARS) component of NRC's Agencywide
13. List and reason for equipment classified in maintenance rule (a)(1) status from   September 1, 2011, to present
Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC
.  14. Copies of  
website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
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).
_ __x SUNSI REVIEW COMPLETE FORM 665 ATTACHED
17. Copy of Technical Specifications Bases
  OFFICE             RII: DRP      RII: DRS     RII: DRP
.  18. Copy of Technical Requirements Manual(s)
SIGNATURE         RA           RA           RA
.  19. List and brief description of Root Cause Evaluations performed since September 1, 2011. 20. In-service Testing Program Procedure(s)
NAME               Lighty       NEASE       MacDonald
.
DATE                 12/ 20/2013   12/20/2013   12/20/2013
21.   Corrective Action Program Procedure
E-MAIL COPY?         YES     NO   YES     NO   YES     NO     YES NO     YES   NO     YES   NO YES NO
(s).
       
22. One-line diagram of electrical plant. (Electronic
          INFORMATION REQUEST FARLEY NUCLEAR PLANT, UNITS 1, AND 2
and full size
                            COMPONENT DESIGN BASES INSPECTION
- hard copy week of  
Please provide the information electronically in .pdf files, Excel, or other searchable format on
  April 7 - 11, 201 4)
CDROM (or FTP site, Sharepoint, etc.). The CDROM (or website) should be indexed and
23. Index and legend for electrical plant one
hyperlinked to facilitate ease of use.
-line diagrams
1. From your most recent probabilistic safety analysis (PSA) excluding external events and
.
    fires:
24. Primary AC calculation(s) for safety
          a. Two risk rankings of components from your site-specific PSA: one sorted by Risk
-related buses
              Achievement Worth (RAW), and the other sorted by Birnbaum Importance
.  25. Primary DC calculation(s) for safety
          b. A list of the top 500 cutsets
-related buses
2. From your most recent PSA including external events and fires:
.  26. Piping and instrumentation diagrams (P&IDs)
          a. Two risk rankings of components from your site-specific PSA: one sorted by RAW,
for safety-related systems. (Electronic
              and the other sorted by Birnbaum Importance
and 1/2 size - hard copy week of April 7 - 11, 201 4)
          b.   A list of the top 500 cutsets
27. Index and Legend for P&
3. Risk ranking of operator actions from your site-specific PSA sorted by RAW. Provide
I Ds.
    human reliability worksheets for these items.
28. Copy of Operability  
4.  List of time-critical operator actions with a brief description of each action.
Determination procedure(s). 30. Copies of corrective action documents (i.e. CR s) associated with findings from previous CDBI. (If applicable)
5.  List of Emergency and Abnormal Operating Procedures revised (significant) since
  31. Index (procedure number, title, and current revision) of station Emergency Operating Procedures, Abnormal Operating Procedures, and Annunciator Response Procedures.
    September 1, 2011, with a brief description of each revision.
  32. Copy of any self
6.  List of components with low design margins (i.e., pumps closest to the design limit for flow
-assessments performed in preparation for this inspection
    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
3 33. List of any condition reports generated in preparation for this inspection
    associated evaluations or calculations.
. 34. Copies of condition reports generated from previous CDBI (2011).
7.  List of station operating experience evaluations/reviews performed, and documented in the
3 5. Contact information for a person to discuss PSA information prior to the information
    stations corrective action program, for industry events and safety-related equipment
-gathering trip. (Name, title, phone number, and e
    failures/vulnerabilities (as communicated by NRC Generic Communications, Industry
-mail address)
    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.
 
                                                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)
v • d • e


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.

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)

Retrieved from "https://kanterella.com/w/index.php?title=ML13354B972&oldid=2055151"