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{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION  
{{#Wiki_filter:UNITED STATES  
REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA  30303-1257
NUCLEAR REGULATORY COMMISSION  
    March 29, 2016  
REGION II  
 
245 PEACHTREE CENTER AVENUE NE, SUITE 1200  
Richard Michael Glover Site Vice President H.B. Robinson Steam Electric Plant  
ATLANTA, GEORGIA  30303-1257  
 
March 29, 2016  
Richard Michael Glover  
Site Vice President  
H.B. Robinson Steam Electric Plant  
Duke Energy  
Duke Energy  
3581 West Entrance Road, RNPA01  
3581 West Entrance Road, RNPA01  
Hartsville, SC  29550  
Hartsville, SC  29550  
 
SUBJECT:  NOTIFICATION OF H.B. ROBINSON STEAM ELECTRIC PLANT - COMPONENT DESIGN BASES INSPECTION - U.S. NUCLEAR REGULATORY COMMISSION  
SUBJECT:  NOTIFICATION OF H.B. ROBINSON STEAM ELECTRIC PLANT - COMPONENT  
DESIGN BASES INSPECTION - U.S. NUCLEAR REGULATORY COMMISSION  
INSPECTION REPORT 05000261/2016008  
INSPECTION REPORT 05000261/2016008  
  Dear Mr. Glover:  
   
 
Dear Mr. Glover:  
   
   
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)  
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)  
Region II staff will conduct a component design bases inspection (CDBI) at your H.B. Robinson Steam Electric Plant during the weeks of July 18 - 22, August 1 - 5, and August 15 - 19, 2016.  Geoffrey Ottenberg, a Senior Reactor Inspector from the NRC's Region II Office, will lead the inspection team.  This inspection will be conducted in accordance with Inspection Procedure  
Region II staff will conduct a component design bases inspection (CDBI) at your H.B. Robinson  
71111.21, "Component Design Bases Inspection," issued November 29, 2013.  
Steam Electric Plant during the weeks of July 18 - 22, August 1 - 5, and August 15 - 19, 2016.   
 
Geoffrey Ottenberg, a Senior Reactor Inspector from the NRCs Region II Office, will lead the  
inspection team.  This inspection will be conducted in accordance with Inspection Procedure  
71111.21, Component Design Bases Inspection, issued November 29, 2013.  
   
   
The inspection will evaluate the capability of risk-significant/low-margin components to function as designed and to support proper system operation.  The inspection will also include a review of selected operator actions, operating experience, and modifications.  
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 March 22, 2016, the staff confirmed with Mr. J. Wild of your  
During a telephone conversation on March 22, 2016, the staff confirmed with Mr. J. Wild of your  
staff, arrangements for an information-gathering site visit and the three-week onsite inspection.  The schedule is as follows:  
staff, arrangements for an information-gathering site visit and the three-week onsite inspection.   
  * Information-gathering visit:  Week of June 27 - July 1, 2016  
The schedule is as follows:  
* Onsite weeks:  July 18 - 22, August 1 - 5, and August 15 - 19, 2016  
   
  The purpose of the information-gathering visit is to meet with members of your staff to identify  
*  
Information-gathering visit:  Week of June 27 - July 1, 2016  
*  
Onsite weeks:  July 18 - 22, August 1 - 5, and August 15 - 19, 2016  
   
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  
risk-significant components and operator actions.  Information and documentation needed to  
support the inspection will also be identified.  Mr. Geoffrey Ottenberg, a Senior Reactor  
support the inspection will also be identified.  Mr. Geoffrey Ottenberg, a Senior Reactor  
Inspector, will be conducting all preparation activities associated with the inspection.  In addition, Mr. George MacDonald, a Region II Senior Reactor Analyst, will support Mr. Ottenberg during the information-gathering visit to review probabilistic risk assessment data and identify  
Inspector, will be conducting all preparation activities associated with the inspection.  In  
addition, Mr. George MacDonald, a Region II Senior Reactor Analyst, will support Mr. Ottenberg  
during the information-gathering visit to review probabilistic risk assessment data and identify  
risk-significant components, which will be examined during the inspection.  
risk-significant components, which will be examined during the inspection.  
The Enclosure lists documents that will be needed prior to the information-gathering visit. 
Please provide the referenced information to the Region II Office by June 13, 2016. 


R. Glover
2
   
   
The Enclosure lists documents that will be needed prior to the information-gathering visit. 
Additional documents may be requested during the information-gathering visit.  The inspectors  
Please provide the referenced information to the Region II Office by June 13, 2016. 
will try to minimize your administrative burden by specifically identifying only those documents  
R. Glover 2
required for inspection preparation.  The additional information will need to be available to the  
Additional documents may be requested during the information-gathering visit.  The inspectors will try to minimize your administrative burden by specifically identifying only those documents  
team in the Region II office prior to the inspection teams preparation week of July 11, 2016.   
required for inspection preparation.  The additional information will need to be available to the team in the Region II office prior to the inspection team's preparation week of July 11, 2016.  During the information-gathering trip, Mr. Ottenberg will also discuss the following inspection  
During the information-gathering trip, Mr. Ottenberg will also discuss the following inspection  
support administrative details: (1) availability of knowledgeable plant engineering and licensing personnel to serve as points of contact during the inspection; (2) method of tracking inspector  
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;   
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.  
  In accordance with Title 10 of the Code of Federal Regulations 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 Sy
In accordance with Title 10 of the Code of Federal Regulations 2.390 of the NRC's "Rules of  
stem (ADAMS).  ADAMS is accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).  
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  
Thank you for your cooperation in this matter.  If you have any questions, regarding the  
Line 67: Line 97:
contact me at 404-997-4607.  
contact me at 404-997-4607.  
   
   
      Sincerely,
   
   
      /RA/  Jonathan H. Bartley, Chief       Engineering Branch 1  
      Division of Reactor Safety  
 
Docket No: 50-261 License No: DPR-23  
 
Sincerely,
/RA/  
   
Jonathan H. Bartley, Chief
Engineering Branch 1  
Division of Reactor Safety  
Docket No:  
50-261  
License No:  
DPR-23  
   
   
Enclosure:   
Enclosure:   
Information Request for H.B. Robinson Steam Electric  
Information Request for H.B. Robinson Steam Electric  
   Plant, Component Design Bases Inspection  
   Plant, Component Design Bases Inspection  
  cc:  Distribution via Listserv
   
cc:  Distribution via Listserv  


_________________________  SUNSI REVIEW COMPLETE  FORM 665 ATTACHED OFFICE RII:DRS RII:DRS 
    SIGNATURE JHB1 FOR GKO JHB1      NAME GOTTENBERG JBARTLEY      DATE 3/29/2016 3/26/2016      E-MAIL COPY?    YES NO      YES NO      YES NO        YES NO      YES NO      YES NO      YES
    Enclosure INFORMATION REQUEST FOR H.B. ROBINSON STEAM ELECTRIC PLANT  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. 


_________________________
SUNSI REVIEW COMPLETE
FORM 665 ATTACHED
OFFICE
RII:DRS
RII:DRS
SIGNATURE
JHB1 FOR GKO JHB1
NAME
GOTTENBERG
JBARTLEY
   
   
1. From your most recent probabilistic safety analysis (PSA)
excluding external events and
DATE
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
3/29/2016
3/26/2016
   
E-MAIL COPY?
    YES
NO   
  YES
NO      YES
NO   
   
  YES
NO      YES
NO   
  YES
NO   
  YES


b. A list of the top 500 cutsets
2. From your most recent PSA
including external events and fires:
a. Two risk rankings of components from your site-specific PSA:  one sorted by RAW, and the other sorted by Birnbaum Importance
b.  A list of the top 500 cutsets 
3. Risk ranking of operator actions from your site-specific PSA sorted by RAW.  Provide human reliability worksheets for these items.
4. List of time-critical operator actions with a brief description of each action.
5. List of Emergency and Abnormal Operating Procedures revised (significant) since  July 1, 2013, 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  
Enclosure
INFORMATION REQUEST FOR H.B. ROBINSON STEAM ELECTRIC PLANT 
COMPONENT DESIGN BASES INSPECTION
Please provide the information electronically in .pdf files, Excel, or other searchable format on
CDROM (or FTP site, Sharepoint, etc.).  The CDROM (or website) should be indexed and
hyperlinked to facilitate ease of use. 
1.
From your most recent probabilistic safety analysis (PSA) excluding external events and
fires:
a. Two risk rankings of components from your site-specific PSA:  one sorted by Risk
Achievement Worth (RAW), and the other sorted by Birnbaum Importance
b. A list of the top 500 cutsets
2.
From your most recent PSA including external events and fires:
a. Two risk rankings of components from your site-specific PSA:  one sorted by RAW,
and the other sorted by Birnbaum Importance
b.  A list of the top 500 cutsets 
3.
Risk ranking of operator actions from your site-specific PSA sorted by RAW.  Provide
human reliability worksheets for these items.
4.
List of time-critical operator actions with a brief description of each action.
5.
List of Emergency and Abnormal Operating Procedures revised (significant) since 
July 1, 2013, 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.).  
rated design heat removal, and motor-operated valve risk-margin rankings, etc.).  
  7.  List of station-operating experience evaluations/reviews performed, and documented in the station's corrective action program, for industry events and safety-related equipment  
   
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  
failures/vulnerabilities (as communicated by NRC Generic Communications, Industry  
Communications, 10 CFR Part 21 Notifications, etc.) since July 1, 2013.  
Communications, 10 CFR Part 21 Notifications, etc.) since July 1, 2013.  
  8. List and brief description of safety-related structures, systems, or components (SSCs)  
   
8.  
List and brief description of safety-related structures, systems, or components (SSCs)  
design modifications implemented since July 1, 2013.  
design modifications implemented since July 1, 2013.  
   
   
9. List and brief description of common-cause component failures that have occurred   
9.  
  since July 1, 2013.  
List and brief description of common-cause component failures that have occurred   
   
since July 1, 2013.  
10. List of equipment on the sites Station Equipment Reliability Issues List, including a
description of the reason(s) why each component is on that list, and summaries (if
available) of your plans to address the issue(s).


  10. List of equipment on the site's Station Equipment Reliability Issues List, including a description of the reason(s) why each component is on that list, and summaries (if
   
available) of your plans to address the issue(s).
2
 
11. List and brief description of equipment currently in degraded or nonconforming status as described in NRC Inspection Manual Chapter 0326, Operability Determinations and  
11. List and brief description of equipment currently in degraded or nonconforming status as  
described in NRC Inspection Manual Chapter 0326, Operability Determinations and  
Functionality Assessments for Conditions Adverse to Quality or Safety, issued   
Functionality Assessments for Conditions Adverse to Quality or Safety, issued   
January 31, 2014.  
January 31, 2014.  
   
   
12.  List and reason for equipment classified in maintenance rule (a) (1) status from   
12.  List and reason for equipment classified in maintenance rule (a) (1) status from   
  July 1, 2013, to present.  
   
 
July 1, 2013, to present.  
   
   
13. Copy of Updated Final Safety Analysis Report.  
13. Copy of Updated Final Safety Analysis Report.  
  14.  Copy of Technical Specification(s).  
   
 
14.  Copy of Technical Specification(s).  
   
   
15.  Copy of Technical Specifications Bases.  
15.  Copy of Technical Specifications Bases.  
   
   
16.  Copy of Technical Requirements Manual(s).  
16.  Copy of Technical Requirements Manual(s).  
  17.  List and brief description of Root Cause Evaluations performed since July 1, 2013.  
   
 
17.  List and brief description of Root Cause Evaluations performed since July 1, 2013.  
   
   
18.  Corrective Action Program Procedure(s).  
18.  Corrective Action Program Procedure(s).  
   
   
19.  Copy of Operability Determination procedure(s).  
19.  Copy of Operability Determination procedure(s).  
  20.  one-line diagram of electrical plant.  (Electronic and full size - hard copy week   
   
  of June 27 - July 1, 2016)  
20.  one-line diagram of electrical plant.  (Electronic and full size - hard copy week   
 
   
of June 27 - July 1, 2016)  
   
   
21.  Index and legend for electrical plant one-line diagrams.  
21.  Index and legend for electrical plant one-line diagrams.  
 
22.  Piping and instrumentation diagrams (P&IDs) for safety-related systems.  (Electronic   and 11 x 17 size - hard copy week of June 27 - July 1, 2016)  
22.  Piping and instrumentation diagrams (P&IDs) for safety-related systems.  (Electronic
 
and 11 x 17 size - hard copy week of June 27 - July 1, 2016)  
   
   
23.  Index and Legend for P&IDs.  
23.  Index and Legend for P&IDs.  
   
   
24.  Copies of corrective action documents (i.e. CRs) associated with findings from previous CDBI.  (If applicable)  
24.  Copies of corrective action documents (i.e. CRs) associated with findings from previous  
CDBI.  (If applicable)  
   
   
25.  Index (procedure number, title, and current revision) of station Emergency Operating Procedures, Abnormal Operating Procedures, and Annunciator Response Procedures.  
25.  Index (procedure number, title, and current revision) of station Emergency Operating  
Procedures, Abnormal Operating Procedures, and Annunciator Response Procedures.  
   
   
26. Copies of any self-assessments performed in preparation for this inspection (2016 CDBI) and the self-assessment performed in preparation for the previous CDBI (2013).  
26. Copies of any self-assessments performed in preparation for this inspection (2016 CDBI)  
and the self-assessment performed in preparation for the previous CDBI (2013).  
   
   
27.  List of any condition reports generated in preparation for this inspection.  
27.  List of any condition reports generated in preparation for this inspection.  
   
   
28.  Copies of condition reports generated from previous CDBI (2013).  
28.  Copies of condition reports generated from previous CDBI (2013).  
 
29. Contact information for a person to discuss PSA information prior to and during the information-gathering trip.  (Name, title, phone number, and e-mail address)
29. Contact information for a person to discuss PSA information prior to and during the  
information-gathering trip.  (Name, title, phone number, and e-mail address)
}}
}}

Latest revision as of 01:49, 10 January 2025

Notification of H.B. Robinson Steam Electric Plant - Component Design Bases Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000261/2016008
ML16092A200
Person / Time
Site: Robinson Duke Energy icon.png
Issue date: 03/29/2016
From: Bartley J
NRC/RGN-II/DRS/EB1
To: Glover R
Duke Energy Corp
References
IR 2016008
Download: ML16092A200 (5)


See also: IR 05000261/2016008

Text

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION II

245 PEACHTREE CENTER AVENUE NE, SUITE 1200

ATLANTA, GEORGIA 30303-1257

March 29, 2016

Richard Michael Glover

Site Vice President

H.B. Robinson Steam Electric Plant

Duke Energy

3581 West Entrance Road, RNPA01

Hartsville, SC 29550

SUBJECT: NOTIFICATION OF H.B. ROBINSON STEAM ELECTRIC PLANT - COMPONENT

DESIGN BASES INSPECTION - U.S. NUCLEAR REGULATORY COMMISSION

INSPECTION REPORT 05000261/2016008

Dear Mr. Glover:

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 H.B. Robinson

Steam Electric Plant during the weeks of July 18 - 22, August 1 - 5, and August 15 - 19, 2016.

Geoffrey Ottenberg, a Senior Reactor Inspector from the NRCs Region II Office, will lead the

inspection team. This inspection will be conducted in accordance with Inspection Procedure

71111.21, Component Design Bases Inspection, issued November 29, 2013.

The inspection will evaluate the capability of risk-significant/low-margin components to function

as designed and to support proper system operation. The inspection will also include a review

of selected operator actions, operating experience, and modifications.

During a telephone conversation on March 22, 2016, the staff confirmed with Mr. J. Wild of your

staff, arrangements for an information-gathering site visit and the three-week onsite inspection.

The schedule is as follows:

Information-gathering visit: Week of June 27 - July 1, 2016

Onsite weeks: July 18 - 22, August 1 - 5, and August 15 - 19, 2016

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

risk-significant components and operator actions. Information and documentation needed to

support the inspection will also be identified. Mr. Geoffrey Ottenberg, a Senior Reactor

Inspector, will be conducting all preparation activities associated with the inspection. In

addition, Mr. George MacDonald, a Region II Senior Reactor Analyst, will support Mr. Ottenberg

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

risk-significant components, which will be examined during the inspection.

The Enclosure lists documents that will be needed prior to the information-gathering visit.

Please provide the referenced information to the Region II Office by June 13, 2016.

R. Glover

2

Additional documents may be requested during the information-gathering visit. The inspectors

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

required for inspection preparation. The additional information will need to be available to the

team in the Region II office prior to the inspection teams preparation week of July 11, 2016.

During the information-gathering trip, Mr. Ottenberg will also discuss the following inspection

support administrative details: (1) availability of knowledgeable plant engineering and licensing

personnel to serve as points of contact during the inspection; (2) method of tracking inspector

requests during the inspection; (3) licensee computer access; (4) working space;

(5) arrangements for site access; and (6) other applicable information.

In accordance with Title 10 of the Code of Federal Regulations 2.390 of the NRC's "Rules of

Practice," a copy of this letter and its Enclosure will be available electronically for public

inspection in the NRC Public Document Room or from the Publicly Available Records (PARS)

component of NRC's Agencywide Documents Access and Management System (ADAMS).

ADAMS is accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html (the

Public Electronic Reading Room).

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

information requested or the inspection, please contact Mr. Ottenberg at 404-997-4658 or

contact me at 404-997-4607.

Sincerely,

/RA/

Jonathan H. Bartley, Chief

Engineering Branch 1

Division of Reactor Safety

Docket No:

50-261

License No:

DPR-23

Enclosure:

Information Request for H.B. Robinson Steam Electric

Plant, Component Design Bases Inspection

cc: Distribution via Listserv

_________________________

SUNSI REVIEW COMPLETE

FORM 665 ATTACHED

OFFICE

RII:DRS

RII:DRS

SIGNATURE

JHB1 FOR GKO JHB1

NAME

GOTTENBERG

JBARTLEY

DATE

3/29/2016

3/26/2016

E-MAIL COPY?

YES

NO

YES

NO YES

NO

YES

NO YES

NO

YES

NO

YES

Enclosure

INFORMATION REQUEST FOR H.B. ROBINSON STEAM ELECTRIC PLANT

COMPONENT DESIGN BASES INSPECTION

Please provide the information electronically in .pdf files, Excel, or other searchable format on

CDROM (or FTP site, Sharepoint, etc.). The CDROM (or website) should be indexed and

hyperlinked to facilitate ease of use.

1.

From your most recent probabilistic safety analysis (PSA) excluding external events and

fires:

a. Two risk rankings of components from your site-specific PSA: one sorted by Risk

Achievement Worth (RAW), and the other sorted by Birnbaum Importance

b. A list of the top 500 cutsets

2.

From your most recent PSA including external events and fires:

a. Two risk rankings of components from your site-specific PSA: one sorted by RAW,

and the other sorted by Birnbaum Importance

b. A list of the top 500 cutsets

3.

Risk ranking of operator actions from your site-specific PSA sorted by RAW. Provide

human reliability worksheets for these items.

4.

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

5.

List of Emergency and Abnormal Operating Procedures revised (significant) since

July 1, 2013, with a brief description of each revision.

6.

List of components with low-design margins (i.e., pumps closest to the design limit for flow

or pressure, diesel generator close to design-required output, heat exchangers close to

rated design heat removal, and motor-operated valve risk-margin rankings, etc.).

7. List of station-operating experience evaluations/reviews performed, and documented in the

stations corrective action program, for industry events and safety-related equipment

failures/vulnerabilities (as communicated by NRC Generic Communications, Industry

Communications, 10 CFR Part 21 Notifications, etc.) since July 1, 2013.

8.

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

design modifications implemented since July 1, 2013.

9.

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

since July 1, 2013.

10. List of equipment on the sites Station Equipment Reliability Issues List, including a

description of the reason(s) why each component is on that list, and summaries (if

available) of your plans to address the issue(s).

2

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

described in NRC Inspection Manual Chapter 0326, Operability Determinations and

Functionality Assessments for Conditions Adverse to Quality or Safety, issued

January 31, 2014.

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

July 1, 2013, to present.

13. Copy of Updated Final Safety Analysis Report.

14. Copy of Technical Specification(s).

15. Copy of Technical Specifications Bases.

16. Copy of Technical Requirements Manual(s).

17. List and brief description of Root Cause Evaluations performed since July 1, 2013.

18. Corrective Action Program Procedure(s).

19. Copy of Operability Determination procedure(s).

20. one-line diagram of electrical plant. (Electronic and full size - hard copy week

of June 27 - July 1, 2016)

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

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

and 11 x 17 size - hard copy week of June 27 - July 1, 2016)

23. Index and Legend for P&IDs.

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

CDBI. (If applicable)

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

Procedures, Abnormal Operating Procedures, and Annunciator Response Procedures.

26. Copies of any self-assessments performed in preparation for this inspection (2016 CDBI)

and the self-assessment performed in preparation for the previous CDBI (2013).

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

28. Copies of condition reports generated from previous CDBI (2013).

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

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