ML22343A038: Difference between revisions

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| number = ML22343A038
| number = ML22343A038
| issue date = 12/13/2022
| issue date = 12/13/2022
| title = Notification of Joseph M. Farley Nuclear Plant Comprehensive Engineering Team Inspection (CETI) Baseline Inspection Report 05000348/2023010 and 05000364/2023010
| title = Notification of Joseph M. Farley Nuclear Plant Comprehensive Engineering Team Inspection (CETI) Baseline Inspection Report 05000348/2023010 and 05000364/2023010
| author name = Baptist J
| author name = Baptist J
| author affiliation = NRC/RGN-II/DRS
| author affiliation = NRC/RGN-II/DRS
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:December 13, 2022
{{#Wiki_filter:Mr. Delson Erb
Mr. Delson Erb
Site Vice President
Site Vice President
Southern Nuclear Operating Co., Inc.
Southern Nuclear Operating Co., Inc.
Line 24: Line 23:
7388 North State Highway 95
7388 North State Highway 95
Columbia, AL 36319-0470
Columbia, AL 36319-0470
SUBJECT: NOTIFICATION OF JOSEPH M. FARLEY NUCLEAR PLANT - COMPREHENSIVE
SUBJECT: NOTIFICATION OF JOSEPH M. FARLEY NUCLEAR PLANT - COMPREHENSIVE  
              ENGINEERING TEAM INSPECTION (CETI) BASELINE INSPECTION REPORT
ENGINEERING TEAM INSPECTION (CETI) BASELINE INSPECTION REPORT  
              05000348/2023010 AND 05000364/2023010
05000348/2023010 AND 05000364/2023010
Dear Mr. Erb:
Dear Mr. Erb:
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)  
Region II staff will conduct a Comprehensive Engineering Team Inspection (CETI) at your
Region II staff will conduct a Comprehensive Engineering Team Inspection (CETI) at your  
Joseph M. Farley Nuclear Plant during the weeks of April 3 and 17, 2023. Mr. Theo Fanelli, a
Joseph M. Farley Nuclear Plant during the weeks of April 3 and 17, 2023. Mr. Theo Fanelli, a  
senior reactor inspector from the NRCs Region II office, will lead the inspection team. The
senior reactor inspector from the NRCs Region II office, will lead the inspection team. The  
inspection will be conducted in accordance with Inspection Procedure 71111.21M,
inspection will be conducted in accordance with Inspection Procedure 71111.21M,  
Comprehensive Engineering Team Inspection (CETI), effective date January 1, 2023. This is a
Comprehensive Engineering Team Inspection (CETI), effective date January 1, 2023. This is a  
new procedure that was issued on October 7, 2022.
new procedure that was issued on October 7, 2022.
The inspection will evaluate the capability of components that have been modified and risk-
The inspection will evaluate the capability of components that have been modified and risk-
significant/low-margin components to function as designed and to support proper system
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, and operating
operation. The inspection will also include a review of selected operator actions, and operating  
experience, and modifications.
experience, and modifications.
During a Teams meeting Ms. Mandy Ludlam, licensing Engineer, we confirmed arrangements
During a Teams meeting Ms. Mandy Ludlam, licensing Engineer, we confirmed arrangements  
for an information-gathering site visit and the two-week onsite inspection. The schedule is as
for an information-gathering site visit and the two-week onsite inspection. The schedule is as  
follows:
follows:
      Information-gathering visit: Week of March 13, 2023
Information-gathering visit: Week of March 13, 2023  
      Onsite weeks: Weeks of April 3 and 17, 2023
Onsite weeks: Weeks of April 3 and 17, 2023
The purpose of the information-gathering visit is to meet with members of your staff to identify
The purpose of the information-gathering visit is to meet with members of your staff to identify  
components that have been modified, risk-significant components, and operator actions.
components that have been modified, risk-significant components, and operator actions.
Information and documentation needed to support the inspection will also be identified.
Information and documentation needed to support the inspection will also be identified.
Mr. Shane Sandal, a Region II Senior Risk Analyst, will support Mr. Fanelli during the
Mr. Shane Sandal, a Region II Senior Risk Analyst, will support Mr. Fanelli during the  
information-gathering visit to review probabilistic risk assessment data and identify components
information-gathering visit to review probabilistic risk assessment data and identify components  
to be examined during the inspection. Additionally, during the onsite weeks, time may be
to be examined during the inspection. Additionally, during the onsite weeks, time may be  
needed on the plant-referenced simulator to facilitate the development of operator action-based
needed on the plant-referenced simulator to facilitate the development of operator action-based  
scenarios.
scenarios.
The enclosure lists documents that will be needed prior to the information-gathering visit.
The enclosure lists documents that will be needed prior to the information-gathering visit.
Please provide the referenced information to the Region II Office by Friday, February 27, 2023.
Please provide the referenced information to the Region II Office by Friday, February 27, 2023.
Additional documents will be requested following the information-gathering visit. The inspectors
Additional documents will be requested following the information-gathering visit. The inspectors December 13, 2022
 
D. Erb 2
D. Erb                                         2
will try to minimize your administrative burden by specifically identifying only those documents  
will try to minimize your administrative burden by specifically identifying only those documents
required for inspection preparation. The additional information will be needed in the Region II  
required for inspection preparation. The additional information will be needed in the Region II
office by Friday, March 24, 2023, to support the inspection teams preparation week. During the  
office by Friday, March 24, 2023, to support the inspection teams preparation week. During the
information-gathering trip, Mr. Fanelli will also discuss the following inspection support  
information-gathering trip, Mr. Fanelli will also discuss the following inspection support
administrative details: (1) availability of knowledgeable plant engineering and licensing  
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  
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;  
requests during the inspection; (3) licensee computer access; (4) working space;
(5) arrangements for site access; and (6) other applicable information.
(5) arrangements for site access; and (6) other applicable information.
This letter, its enclosure, and your response (if any) will be made available for public inspection
This letter, its enclosure, and your response (if any) will be made available for public inspection  
and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document
and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document  
Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for
Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for  
Withholding.
Withholding.
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. Fanelli at 404-997-4433 or contact
information requested or the inspection, please contact Mr. Fanelli at 404-997-4433 or contact  
me at 404-997-4506.
me at 404-997-4506.
                                                Sincerely,
Sincerely,
                                                                      Signed by Baptist, James
James Baptist, Chief  
                                                                        on 12/13/22
Engineering Branch 1
                                                James Baptist, Chief
Division of Reactor Safety
                                                Engineering Branch 1
Docket No. 05000348 AND 05000364
                                                Division of Reactor Safety
License No. NPF-2 and NPF-8
Docket No. 05000348 AND 05000364
License No. NPF-2 and NPF-8
Enclosure:
Enclosure:
Information Request for Joseph M. Farley Nuclear Plant Comprehensive Engineering Team
Information Request for Joseph M. Farley Nuclear Plant Comprehensive Engineering Team  
            Inspection
Inspection
cc w/ encl: Distribution via LISTSERV
cc w/ encl: Distribution via LISTSERV
Signed by Baptist, James
on 12/13/22




  ML22343A038
  ML22343A038
                              X     Non-Sensitive           X    Publicly Available
                          X   Non-Sensitive                   X    Publicly Available
    X    SUNSI Review
  X    SUNSI Review
                                    Sensitive                   Non-Publicly Available
                              Sensitive                           Non-Publicly Available
  OFFICE RII/DRS           RII/DRS
 
  NAME     T. Fanelli      J. Baptist
OFFICE RII/DRS         RII/DRS
  DATE     12/09/22        12/13/22
 
                                     
NAME   T. Fanelli      J. Baptist
DATE   12/09/22        12/13/22
 
 
                               
INFORMATION REQUEST FOR JOSEPH M. FARLEY NUCLEAR PLANT COMPREHENSIVE
INFORMATION REQUEST FOR JOSEPH M. FARLEY NUCLEAR PLANT COMPREHENSIVE
                                ENGINEERING TEAM INSPECTION
                            ENGINEERING TEAM INSPECTION
 
Please provide the information electronically in .pdf files, Excel, or other searchable format on
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
CDROM (or FTP site, SharePoint, etc.). The CDROM (or website) should be indexed and
hyperlinked to facilitate ease of use. The requested items below, identified with an asterisk (*),
hyperlinked to facilitate ease of use. The requested items below, identified with an asterisk (*),
should have a date range from January 1, 2020, until present.
should have a date range from January 1, 2020, until present.
1.  *List of modifications to systems, structures or components (SSCs) that are permanent
    and field work completed. (For the purpose of this inspection, modifications include
    permanent: plant changes, design changes, calculation changes, procedure changes, and
    set point changes.)
    The list should contain the number of the modification, a short description, affected system
    and unit. If multiple categories/stages of modifications exist, provide a description of the
    types relative to the coding scheme in your transmittal. Additionally, the list should be
    categorized by quality level (i.e., safety or non-safety) as well as whether accompanied by
    a screening or 10 CFR 50.59 evaluation. A query report return-field-set might look like:
  Identifier Unit    System1    Description    Type2      Status3 QA Condition4      50.595
        1  e.g. If systems are provided with some type of number or acronym designation,
            define the systems designation on a separate list or document
        2  e.g. Engineering Design/Document Change, Design Change Notice, Test,
            Experiment, etc.
        3  e.g. Closed, Returned to Operation, Void, Partially Completed, Released for
            Installation, Phase 1 Completed, etc.
        4  e.g. Safety Related or Non-Safety Related
        5  e.g. Screened Out or Full 10 CFR 50.59 Evaluation
2.  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 cut-sets
          c. A list of the top 500 LERF contributors
3.  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 cut-sets
4.  Risk ranking of operator actions from your site-specific PSA sorted by RAW and human
    reliability worksheets for these items
5.  List of time-critical operator actions with a brief description of each action
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 and brief description of Root Cause Evaluations performed
                                                                                          Enclosure


8. *List and brief description of common-cause component failures that have occurred
1.    *List of modifications to systems, structures or components (SSCs) that are permanent
9. List and brief description of equipment currently in degraded or nonconforming condition
    and field work completed.  (For the purpose of this inspection, modifications include
10. *List and brief description of Operability Determinations and Functionality Assessments
    permanent: plant changes, design changes, calculation changes, procedure changes, and
11. *List and reason for equipment that has been classified in maintenance rule (a)(1) status
    set point changes.)
12. *List of equipment on the sites Station Equipment Reliability Issues List, including a
    The list should contain the number of the modification, a short description, affected system
    and unit.  If multiple categories/stages of modifications exist, provide a description of the
    types relative to the coding scheme in your transmittal.  Additionally, the list should be
    categorized by quality level (i.e., safety or non-safety) as well as whether accompanied by
    a screening or 10 CFR 50.59 evaluation.  A query report return-field-set might look like:
 
  Identifier Unit  System1    Description    Type2    Status3  QA Condition4    50.595
            1    e.g. If systems are provided with some type of number or acronym designation,
          define the systems designation on a separate list or document
      2    e.g. Engineering Design/Document Change, Design Change Notice, Test,
          Experiment, etc.
      3    e.g. Closed, Returned to Operation, Void, Partially Completed, Released for
          Installation, Phase 1 Completed, etc.
      4    e.g. Safety Related or Non-Safety Related
      5    e.g. Screened Out or Full 10 CFR 50.59 Evaluation
 
2.    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 cut-sets
        c.  A list of the top 500 LERF contributors
3.    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 cut-sets
4.    Risk ranking of operator actions from your site-specific PSA sorted by RAW and human
    reliability worksheets for these items
5.    List of time-critical operator actions with a brief description of each action
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 and brief description of Root Cause Evaluations performed
 
 
 
 
                                                                                    Enclosure
8.   *List and brief description of common-cause component failures that have occurred
9.   List and brief description of equipment currently in degraded or nonconforming condition
10. *List and brief description of Operability Determinations and Functionality Assessments
11. *List and reason for equipment that has been classified in maintenance rule (a)(1) status
12. *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
     description of the reason(s) why each component is on that list, and summaries (if
     available) of your plans to address the issue(s) along with dates added or removed from
     available) of your plans to address the issue(s) along with dates added or removed from
     the issues list
     the issues list
13. List of current operator work arounds/burdens
13. List of current operator work arounds/burdens
14. Copy of Updated Final Safety Analysis Report
14. Copy of Updated Final Safety Analysis Report
15. Copy of Technical Specification(s)
15. Copy of Technical Specification(s)
16. Copy of Technical Specifications Bases
16. Copy of Technical Specifications Bases
17. Copy of Technical Requirements Manual(s)
17. Copy of Technical Requirements Manual(s)
18. Copy of the Quality Assurance Program Manual
18. Copy of the Quality Assurance Program Manual
19. Copy of Corrective Action Program Procedure(s)
19. Copy of Corrective Action Program Procedure(s)
20. Copy of Operability Determination Procedure(s)
20. Copy of Operability Determination Procedure(s)
21. Copy of procedures addressing the following: Modifications, design changes, set point
21. Copy of procedures addressing the following: Modifications, design changes, set point
     changes, equivalency evaluations or suitability analyses, commercial grade dedications,
     changes, equivalency evaluations or suitability analyses, commercial grade dedications,
     post-modifications testing, 10 CFR 50.59 screenings and evaluations, and UFSAR updates
     post-modifications testing, 10 CFR 50.59 screenings and evaluations, and UFSAR updates
22. Copy of procedures addressing the following: loss of service water system or ultimate heat
22. Copy of procedures addressing the following: loss of service water system or ultimate heat
     sink (UHS); controls to prevent clogging due to macrofouling; and performance, testing,
     sink (UHS); controls to prevent clogging due to macrofouling; and performance, testing,
     and inspection requirements for service water system and UHS
     and inspection requirements for service water system and UHS
23. Response to Generic Letter 89-13 including any regulatory commitments made
23. Response to Generic Letter 89-13 including any regulatory commitments made
24. List of heat exchangers or equipment cooled by service water directly or indirectly. Include
24. List of heat exchangers or equipment cooled by service water directly or indirectly. Include
     the risk ranking for each listed heat exchanger.
     the risk ranking for each listed heat exchanger.
25. List of motor operated valves and air operated valves in the valve program, and their
25. List of motor operated valves and air operated valves in the valve program, and their
     associated design margin and risk ranking
     associated design margin and risk ranking
26. Primary AC and DC calculations for safety-related buses
26. Primary AC and DC calculations for safety-related buses
27. One-line diagram of electrical plant (Electronic only)
27. One-line diagram of electrical plant (Electronic only)
28. Index and legend for electrical plant one-line diagrams
28. Index and legend for electrical plant one-line diagrams
29. Piping and instrumentation diagrams (P&IDs) for safety-related systems (Electronic)
29. Piping and instrumentation diagrams (P&IDs) for safety-related systems (Electronic)
30. Index and legend for P&IDs
30. Index and legend for P&IDs
31. Index (procedure number, title, and current revision) of station Emergency Operating
31. Index (procedure number, title, and current revision) of station Emergency Operating
     Procedures, Abnormal Operating Procedures, and Annunciator Response Procedures
     Procedures, Abnormal Operating Procedures, and Annunciator Response Procedures
                                              2


32. Copies of corrective action documents generated from previous design bases assurance
 
 
 
                                          2
32. Copies of corrective action documents generated from previous design bases assurance
     inspections
     inspections
33. Copy of any self-assessments performed, and corrective action documents generated, in
33. Copy of any self-assessments performed, and corrective action documents generated, in
     preparation for current comprehensive engineering team inspection
     preparation for current comprehensive engineering team inspection
34. Contact information for a person to discuss PSA information prior to and during the
34. Contact information for a person to discuss PSA information prior to and during the
     information-gathering trip (Name, title, phone number, and e-mail address)
     information-gathering trip (Name, title, phone number, and e-mail address)
                                                3
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
                                              3
}}
}}

Revision as of 15:33, 15 November 2024

Notification of Joseph M. Farley Nuclear Plant – Comprehensive Engineering Team Inspection (CETI) Baseline Inspection Report 05000348/2023010 and 05000364/2023010
ML22343A038
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 12/13/2022
From: James Baptist
Division of Reactor Safety II
To: Erb D
Southern Nuclear Operating Co
References
IR 2023010
Download: ML22343A038 (6)


See also: IR 05000348/2023010

Text

Mr. Delson Erb

Site Vice President

Southern Nuclear Operating Co., Inc.

Joseph M. Farley Nuclear Plant

7388 North State Highway 95

Columbia, AL 36319-0470

SUBJECT: NOTIFICATION OF JOSEPH M. FARLEY NUCLEAR PLANT - COMPREHENSIVE

ENGINEERING TEAM INSPECTION (CETI) BASELINE INSPECTION REPORT

05000348/2023010 AND 05000364/2023010

Dear Mr. Erb:

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

Region II staff will conduct a Comprehensive Engineering Team Inspection (CETI) at your

Joseph M. Farley Nuclear Plant during the weeks of April 3 and 17, 2023. Mr. Theo Fanelli, a

senior reactor inspector from the NRCs Region II office, will lead the inspection team. The

inspection will be conducted in accordance with Inspection Procedure 71111.21M,

Comprehensive Engineering Team Inspection (CETI), effective date January 1, 2023. This is a

new procedure that was issued on October 7, 2022.

The inspection will evaluate the capability of components that have been modified and 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, and operating

experience, and modifications.

During a Teams meeting Ms. Mandy Ludlam, licensing Engineer, we confirmed arrangements

for an information-gathering site visit and the two-week onsite inspection. The schedule is as

follows:

Information-gathering visit: Week of March 13, 2023

Onsite weeks: Weeks of April 3 and 17, 2023

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

components that have been modified, risk-significant components, and operator actions.

Information and documentation needed to support the inspection will also be identified.

Mr. Shane Sandal, a Region II Senior Risk Analyst, will support Mr. Fanelli during the

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

to be examined during the inspection. Additionally, during the onsite weeks, time may be

needed on the plant-referenced simulator to facilitate the development of operator action-based

scenarios.

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 Friday, February 27, 2023.

Additional documents will be requested following the information-gathering visit. The inspectors December 13, 2022

D. Erb 2

will try to minimize your administrative burden by specifically identifying only those documents

required for inspection preparation. The additional information will be needed in the Region II

office by Friday, March 24, 2023, to support the inspection teams preparation week. During the

information-gathering trip, Mr. Fanelli 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.

This letter, its enclosure, and your response (if any) will be made available for public inspection

and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document

Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for

Withholding.

Thank you for your cooperation in this matter. If you have any questions, regarding the

information requested or the inspection, please contact Mr. Fanelli at 404-997-4433 or contact

me at 404-997-4506.

Sincerely,

James Baptist, Chief

Engineering Branch 1

Division of Reactor Safety

Docket No. 05000348 AND 05000364

License No. NPF-2 and NPF-8

Enclosure:

Information Request for Joseph M. Farley Nuclear Plant Comprehensive Engineering Team

Inspection

cc w/ encl: Distribution via LISTSERV

Signed by Baptist, James

on 12/13/22

ML22343A038

X Non-Sensitive X Publicly Available

X SUNSI Review

Sensitive Non-Publicly Available

OFFICE RII/DRS RII/DRS

NAME T. Fanelli J. Baptist

DATE 12/09/22 12/13/22

INFORMATION REQUEST FOR JOSEPH M. FARLEY NUCLEAR PLANT COMPREHENSIVE

ENGINEERING TEAM 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. The requested items below, identified with an asterisk (*),

should have a date range from January 1, 2020, until present.

1. *List of modifications to systems, structures or components (SSCs) that are permanent

and field work completed. (For the purpose of this inspection, modifications include

permanent: plant changes, design changes, calculation changes, procedure changes, and

set point changes.)

The list should contain the number of the modification, a short description, affected system

and unit. If multiple categories/stages of modifications exist, provide a description of the

types relative to the coding scheme in your transmittal. Additionally, the list should be

categorized by quality level (i.e., safety or non-safety) as well as whether accompanied by

a screening or 10 CFR 50.59 evaluation. A query report return-field-set might look like:

Identifier Unit System1 Description Type2 Status3 QA Condition4 50.595

1 e.g. If systems are provided with some type of number or acronym designation,

define the systems designation on a separate list or document

2 e.g. Engineering Design/Document Change, Design Change Notice, Test,

Experiment, etc.

3 e.g. Closed, Returned to Operation, Void, Partially Completed, Released for

Installation, Phase 1 Completed, etc.

4 e.g. Safety Related or Non-Safety Related

5 e.g. Screened Out or Full 10 CFR 50.59 Evaluation

2. 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 cut-sets

c. A list of the top 500 LERF contributors

3. 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 cut-sets

4. Risk ranking of operator actions from your site-specific PSA sorted by RAW and human

reliability worksheets for these items

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

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 and brief description of Root Cause Evaluations performed

Enclosure

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

9. List and brief description of equipment currently in degraded or nonconforming condition

10. *List and brief description of Operability Determinations and Functionality Assessments

11. *List and reason for equipment that has been classified in maintenance rule (a)(1) status

12. *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) along with dates added or removed from

the issues list

13. List of current operator work arounds/burdens

14. Copy of Updated Final Safety Analysis Report

15. Copy of Technical Specification(s)

16. Copy of Technical Specifications Bases

17. Copy of Technical Requirements Manual(s)

18. Copy of the Quality Assurance Program Manual

19. Copy of Corrective Action Program Procedure(s)

20. Copy of Operability Determination Procedure(s)

21. Copy of procedures addressing the following: Modifications, design changes, set point

changes, equivalency evaluations or suitability analyses, commercial grade dedications,

post-modifications testing, 10 CFR 50.59 screenings and evaluations, and UFSAR updates

22. Copy of procedures addressing the following: loss of service water system or ultimate heat

sink (UHS); controls to prevent clogging due to macrofouling; and performance, testing,

and inspection requirements for service water system and UHS

23. Response to Generic Letter 89-13 including any regulatory commitments made

24. List of heat exchangers or equipment cooled by service water directly or indirectly. Include

the risk ranking for each listed heat exchanger.

25. List of motor operated valves and air operated valves in the valve program, and their

associated design margin and risk ranking

26. Primary AC and DC calculations for safety-related buses

27. One-line diagram of electrical plant (Electronic only)

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

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

30. Index and legend for P&IDs

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

Procedures, Abnormal Operating Procedures, and Annunciator Response Procedures

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32. Copies of corrective action documents generated from previous design bases assurance

inspections

33. Copy of any self-assessments performed, and corrective action documents generated, in

preparation for current comprehensive engineering team inspection

34. Contact information for a person to discuss PSA information prior to and during the

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

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