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{{#Wiki_filter: UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA  30303-1257       October 3, 2013   
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION  
REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA  30303-1257
      October 3, 2013  
   
   
   
Mr. Mano Nazar Executive Vice President and Chief Nuclear Officer Florida Power and Light Company  
Mr. Mano Nazar Executive Vice President and Chief Nuclear Officer Florida Power and Light Company  
P.O. Box 14000  
P.O. Box 14000  
Juno Beach, FL  33408-0420  
Juno Beach, FL  33408-0420  
  SUBJECT: NOTIFICATION OF TURKEY POINT NUCLEAR GENERATING UNITS 3 AND 4 COMPONENT DESIGN BASES INSPECTION - NRC INSPECTION REPORT  
 
05000250/2014007 AND 05000251/2014007   
  SUBJECT: NOTIFICATION OF TURKEY POINT NUCLEAR GENERATING UNITS 3 AND 4
COMPONENT DESIGN BASES INSPECTION - NRC INSPECTION REPORT  
 
05000250/2014007 AND 05000251/2014007  
   
Dear Mr. Nazar:  
Dear Mr. Nazar:  
  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 Turkey Point  
  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 Turkey Point  
Nuclear Generating Units 3 and 4 during the weeks of January 27 - 31, February 10 - 14, and  
Nuclear Generating Units 3 and 4 during the weeks of January 27 - 31, February 10 - 14, and  
February 24 - 28, 2014.  Mr. Shakur Walker, a Senior Reactor Inspector from the NRC's Region  
February 24 - 28, 2014.  Mr. Shakur Walker, a Senior Reactor Inspector 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 August 14, 2012.  
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 August 14, 2012.  
   
   
The inspection will evaluate the capability of risk-significant / low margin components to function  
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 October 2, 2013, Mr. Walker confirmed with Ms. Stavy  
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 October 2, 2013, Mr. Walker confirmed with Ms. Stavy  
Mihalakea of your staff, arrangements for an information-gathering site visit and the three-week  
Mihalakea of your staff, arrangements for an information-gathering site visit and the three-week  
onsite inspection.  The schedule is as follows:  
onsite inspection.  The schedule is as follows:  
  * Information-gathering visit:  Week of January 6 - 10, 2014 * Onsite weeks:  January 27 - 31, February 10 - 14, and February 24 - 28, 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. John Hanna, a Region II Senior Reactor  
 
  * Information-gathering visit:  Week of January 6 - 10, 2014  
* Onsite weeks:  January 27 - 31, February 10 - 14, and February 24 - 28, 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. John Hanna, a Region II Senior Reactor  
Analyst, will support Mr. Walker during the information-gathering visit to review probabilistic risk  
Analyst, will support Mr. Walker 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.   
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 December 2, 2013.  
Please provide the referenced information to the Region II Office by December 2, 2013.  
M. Nazar 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  
M. Nazar 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 will need to be available to the team in the Region II Office prior to the inspection team's preparation week of January 20, 2014.  Mr. Walker will also discuss the following inspection support administrative details: (1)  
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 January 20, 2014.  Mr. Walker will also discuss the following inspection support administrative details: (1)  
availability of knowledgeable plant engineering and licensing personnel to serve as points of  
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,  
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)  
(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  
 
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  
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).   
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  
Thank you for your cooperation in this matter.  If you have any questions, regarding the  
information requested or the inspection, please contact Mr. Walker at 404-997-4639 or contact  
information requested or the inspection, please contact Mr. Walker at 404-997-4639 or contact  
me at 404-997-4530.        Sincerely,  
 
       RA  Rebecca L. Nease, Chief        Engineering Branch 1  
me at 404-997-4530.  
       Sincerely,  
 
       RA  
   Rebecca L. Nease, Chief        Engineering Branch 1  
       Division of Reactor Safety  
       Division of Reactor Safety  
   
   
Docket Nos.:  50-250, 50-251 License Nos.:  DPR-31, DPR-41
Docket Nos.:  50-250, 50-251 License Nos.:  DPR-31, DPR-41  
Enclosure: 
Information Request for Turkey Point 
  Nuclear Generating Units 3 and 4 
  Component Design Bases Inspection  cc:  Distribution via Listserv 
M. Nazar 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 will need to be available to the team in the Region II Office prior to the inspection team's preparation week of January 20, 2014.  Mr. Walker 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. Walker at 404-997-4639 or contact
me at 404-997-4530.        Sincerely,
      RA  Rebecca L. Nease, Chief        Engineering Branch 1
      Division of Reactor Safety
   
   
Docket Nos.:  50-250, 50-251 License Nos.:  DPR-31, DPR-41 
Enclosure:   
Enclosure:   
Information Request for Turkey Point   
Information Request for Turkey Point   
   Nuclear Generating Units 3 and 4   
   Nuclear Generating Units 3 and 4   
   Component Design Bases Inspection   cc:  via Listserv  
   Component Design Bases Inspection
cc:  Distribution via Listserv
 
__ML13280A151  x SUNSI REVIEW COMPLETE  x FORM 665 ATTACHED OFFICE RII:DRS RII:DRS      SIGNATURE RA RA      NAME WALKER NEASE      DATE 10/  2 /2013 10/3 /2013 10/    /2013 10/    /2013 10/    /2013 10/    /2013 10/    /2013 E-MAIL COPY?    YES NO      YES NO      YES NO      YES NO      YES NO      YES NO      YES NO     
Letter to Mr. Mano Nazar from Rebecca L. Nease dated October 3, 2013.
   
   
SUBJECT: NOTIFICATION OF TURKEY POINT NUCLEAR GENERATING UNITS 3 AND 4
x PUBLICLY AVAILABLE  NON-PUBLICLY AVAILABLE  SENSITIVE x NON-SENSITIVE ADAMS:x  Yes ACCESSION NUMBER:__ML13280A151  x SUNSI REVIEW COMPLETE  x FORM 665 ATTACHED OFFICE RII:DRS RII:DRS      SIGNATURE RA RA      NAME WALKER NEASE      DATE 10/  2 /2013 10/3 /2013 10/    /2013 10/    /2013 10/    /2013 10/    /2013 10/    /2013 E-MAIL COPY?    YES NO      YES NO      YES NO      YES NO      YES NO      YES NO      YES NO    OFFICIAL RECORD COPY          DOCUMENT NAME:  S:\DRS\ENG BRANCH 1\BRANCH INSPECTION FILES\2014-2015-2016 CYCLE INSPECTION FOLDER FOR ALL SITES\TURKEY POINT\CDBI\TP CDBI 2014007 NOTIFICATION LETTER.DOCX 
COMPONENT DESIGN BASES INSPECTION - NRC INSPECTION REPORT  
Letter to Mr. Mano Nazar from Rebecca L. Nease dated October 3, 2013. 
05000250/2014007 AND 05000251/2014007
SUBJECT: NOTIFICATION OF TURKEY POINT NUCLEAR GENERATING UNITS 3 AND 4 COMPONENT DESIGN BASES INSPECTION - NRC INSPECTION REPORT 05000250/2014007 AND 05000251/2014007 Distribution RIDSNRRDIRS  
Distribution
RIDSNRRDIRS  
 
PUBLIC  
PUBLIC  
RidsNrrPMTurkeyPoint Resource   
RidsNrrPMTurkeyPoint Resource   
   Enclosure INFORMATION REQUEST FOR TURKEY POINT NUCLEAR GENERATING UNITS 3 AND 4 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  
   Enclosure INFORMATION REQUEST FOR TURKEY POINT NUCLEAR GENERATING UNITS 3 AND 4 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.   
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.
   
   
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  
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.   
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 station's corrective action program, for industry events and safety related equipment  
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  
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.   
Communications, 10 CFR Part 21 Notifications, etc-) 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.  
  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.  
 
    
    
2  Enclosure 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  
2  Enclosure 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).  12. List and brief description of equipment currently in degraded or nonconforming status as described in Regulatory Issue Summary 05-020.   
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   
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.  
  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.  
15. Copy of Updated Final Safety Analysis Report.  
   
   
16.  Copy of Technical Specification(s).  17.  Copy of Technical Specifications Bases.  
16.  Copy of Technical Specification(s).  
  17.  Copy of Technical Specifications Bases.  
 
   
   
18.  Copy of Technical Requirements Manual(s).  
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).  
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).  
21.  Corrective Action Program Procedure(s).  
22.  One line diagram of electrical plant.  (Electronic and full size - hard copy week of  January 6, 2014)
   
   
22.  One line diagram of electrical plant.  (Electronic and full size - hard copy week of  January 6, 2014) 
23.  Index and legend for electrical plant one-line diagrams.  
23.  Index and legend for electrical plant one-line diagrams.  
   
   
24.  Primary AC calculation(s) for safety-related buses.  
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 January 6, 2014) 
  25.  Primary DC calculation(s) for safety-related buses.  
27.  Index and Legend for P&IDs.  28.  Copy of Operability Determination procedure(s).  
   
   
30.  Copies of condition reports associated with findings from previous CDBI (Inspection Report 2011-008).  31.  Index (procedure number, title, and current revision) of station Emergency Operating Procedures, Abnormal Operating Procedures, and Annunciator Response Procedures.  
26.  Piping and instrumentation diagrams (P&IDs) for safety-related systems.  (Electronic and 1/2 size - hard copy week of January 6, 2014)
32. Copy of any self-assessments performed in preparation for this inspection.  
   
3 Enclosure 33.  List of any condition reports generated in preparation for this inspection. 
27. Index and Legend for P&IDs.  
34.  Copies of all condition reports generated from previous CDBI (Inspection Report 2011-008). 35. Contact information for a person to discuss PSA information prior to the information-gathering trip.  (Name, title, phone number, and e-mail address) 
  28.  Copy of Operability Determination procedure(s).  


30.  Copies of condition reports associated with findings from previous CDBI (Inspection Report
2011-008).
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  Enclosure 33.  List of any condition reports generated in preparation for this inspection.
34.  Copies of all condition reports generated from previous CDBI (Inspection Report 2011-008).
35. Contact information for a person to discu
ss PSA information prior to the information-gathering trip.  (Name, title, phone number, and e-mail address)
}}
}}

Revision as of 00:54, 4 July 2018

Turkey Point, Units 3 and 4, Component Design Bases Inspection 05000250/2014007 and 05000251/2014007, Notification Letter Final
ML13280A151
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 10/03/2013
From: Nease R L
NRC/RGN-II/DRS/EB1
To: Nazar M K
Florida Power & Light Co
References
IR-14-007
Download: ML13280A151 (5)
v • d • e


See also: IR 05000250/2014007

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION

REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257

October 3, 2013

Mr. Mano Nazar Executive Vice President and Chief Nuclear Officer Florida Power and Light Company

P.O. Box 14000

Juno Beach, FL 33408-0420

SUBJECT: NOTIFICATION OF TURKEY POINT NUCLEAR GENERATING UNITS 3 AND 4

COMPONENT DESIGN BASES INSPECTION - NRC INSPECTION REPORT

05000250/2014007 AND 05000251/2014007

Dear Mr. Nazar:

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 Turkey Point

Nuclear Generating Units 3 and 4 during the weeks of January 27 - 31, February 10 - 14, and

February 24 - 28, 2014. Mr. Shakur Walker, a Senior Reactor Inspector 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 August 14, 2012.

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 October 2, 2013, Mr. Walker confirmed with Ms. Stavy

Mihalakea 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 January 6 - 10, 2014
  • Onsite weeks: January 27 - 31, February 10 - 14, and February 24 - 28, 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. John Hanna, a Region II Senior Reactor

Analyst, will support Mr. Walker 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 December 2, 2013.

M. Nazar 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 will need to be available to the team in the Region II Office prior to the inspection team's preparation week of January 20, 2014. Mr. Walker 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. Walker at 404-997-4639 or contact

me at 404-997-4530.

Sincerely,

RA

Rebecca L. Nease, Chief Engineering Branch 1

Division of Reactor Safety

Docket Nos.: 50-250, 50-251 License Nos.: DPR-31, DPR-41

Enclosure:

Information Request for Turkey Point

Nuclear Generating Units 3 and 4

Component Design Bases Inspection

cc: Distribution via Listserv

__ML13280A151 x SUNSI REVIEW COMPLETE x FORM 665 ATTACHED OFFICE RII:DRS RII:DRS SIGNATURE RA RA NAME WALKER NEASE DATE 10/ 2 /2013 10/3 /2013 10/ /2013 10/ /2013 10/ /2013 10/ /2013 10/ /2013 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO

Letter to Mr. Mano Nazar from Rebecca L. Nease dated October 3, 2013.

SUBJECT: NOTIFICATION OF TURKEY POINT NUCLEAR GENERATING UNITS 3 AND 4

COMPONENT DESIGN BASES INSPECTION - NRC INSPECTION REPORT

05000250/2014007 AND 05000251/2014007

Distribution

RIDSNRRDIRS

PUBLIC

RidsNrrPMTurkeyPoint Resource

Enclosure INFORMATION REQUEST FOR TURKEY POINT NUCLEAR GENERATING UNITS 3 AND 4 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 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 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.

2 Enclosure 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).

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 January 6, 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 January 6, 2014)

27. Index and Legend for P&IDs.

28. Copy of Operability Determination procedure(s).

30. Copies of condition reports associated with findings from previous CDBI (Inspection Report

2011-008).

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

34. Copies of all condition reports generated from previous CDBI (Inspection Report 2011-008).

35. Contact information for a person to discu

ss PSA information prior to the information-gathering trip. (Name, title, phone number, and e-mail address)

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