ML16092A200: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(StriderTol Bot change)
 
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:UNITED STATES
{{#Wiki_filter:UNITED STATES  
                                NUCLEAR REGULATORY COMMISSION
NUCLEAR REGULATORY COMMISSION  
                                                REGION II
REGION II  
                            245 PEACHTREE CENTER AVENUE NE, SUITE 1200
245 PEACHTREE CENTER AVENUE NE, SUITE 1200  
                                      ATLANTA, GEORGIA 30303-1257
ATLANTA, GEORGIA 30303-1257  
                                          March 29, 2016
Richard Michael Glover
Site Vice President
H.B. Robinson Steam Electric Plant
March 29, 2016  
Duke Energy
3581 West Entrance Road, RNPA01
Hartsville, SC 29550
Richard Michael Glover  
SUBJECT: NOTIFICATION OF H.B. ROBINSON STEAM ELECTRIC PLANT - COMPONENT
Site Vice President  
              DESIGN BASES INSPECTION - U.S. NUCLEAR REGULATORY COMMISSION
H.B. Robinson Steam Electric Plant  
              INSPECTION REPORT 05000261/2016008
Duke Energy  
Dear Mr. Glover:
3581 West Entrance Road, RNPA01  
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)
Hartsville, SC 29550  
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
SUBJECT: NOTIFICATION OF H.B. ROBINSON STEAM ELECTRIC PLANT - COMPONENT  
inspection team. This inspection will be conducted in accordance with Inspection Procedure
DESIGN BASES INSPECTION - U.S. NUCLEAR REGULATORY COMMISSION  
71111.21, Component Design Bases Inspection, issued November 29, 2013.
INSPECTION REPORT 05000261/2016008  
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
Dear Mr. Glover:  
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
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)  
staff, arrangements for an information-gathering site visit and the three-week onsite inspection.
Region II staff will conduct a component design bases inspection (CDBI) at your H.B. Robinson  
The schedule is as follows:
Steam Electric Plant during the weeks of July 18 - 22, August 1 - 5, and August 15 - 19, 2016.
    *   Information-gathering visit: Week of June 27 - July 1, 2016
Geoffrey Ottenberg, a Senior Reactor Inspector from the NRCs Region II Office, will lead the  
    *   Onsite weeks: July 18 - 22, August 1 - 5, and August 15 - 19, 2016
inspection team. This inspection will be conducted in accordance with Inspection Procedure  
The purpose of the information-gathering visit is to meet with members of your staff to identify
71111.21, Component Design Bases Inspection, issued November 29, 2013.  
risk-significant components and operator actions. Information and documentation needed to
support the inspection will also be identified. Mr. Geoffrey Ottenberg, a Senior Reactor
The inspection will evaluate the capability of risk-significant/low-margin components to function  
Inspector, will be conducting all preparation activities associated with the inspection. In
as designed and to support proper system operation. The inspection will also include a review  
addition, Mr. George MacDonald, a Region II Senior Reactor Analyst, will support Mr. Ottenberg
of selected operator actions, operating experience, and modifications.  
during the information-gathering visit to review probabilistic risk assessment data and identify
risk-significant components, which will be examined during the inspection.
During a telephone conversation on March 22, 2016, the staff confirmed with Mr. J. Wild of your  
The Enclosure lists documents that will be needed prior to the information-gathering visit.
staff, arrangements for an information-gathering site visit and the three-week onsite inspection.
Please provide the referenced information to the Region II Office by June 13, 2016.
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
R. Glover  
Additional documents may be requested during the information-gathering visit. The inspectors
2  
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
Additional documents may be requested during the information-gathering visit. The inspectors  
team in the Region II office prior to the inspection teams preparation week of July 11, 2016.
will try to minimize your administrative burden by specifically identifying only those documents  
During the information-gathering trip, Mr. Ottenberg will also discuss the following inspection
required for inspection preparation. The additional information will need to be available to the  
support administrative details: (1) availability of knowledgeable plant engineering and licensing
team in the Region II office prior to the inspection teams preparation week of July 11, 2016.
personnel to serve as points of contact during the inspection; (2) method of tracking inspector
During the information-gathering trip, Mr. Ottenberg will also discuss the following inspection  
requests during the inspection; (3) licensee computer access; (4) working space;
support administrative details: (1) availability of knowledgeable plant engineering and licensing  
(5) arrangements for site access; and (6) other applicable information.
personnel to serve as points of contact during the inspection; (2) method of tracking inspector  
In accordance with Title 10 of the Code of Federal Regulations 2.390 of the NRC's "Rules of
requests during the inspection; (3) licensee computer access; (4) working space;
Practice," a copy of this letter and its Enclosure will be available electronically for public
(5) arrangements for site access; and (6) other applicable information.  
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).
In accordance with Title 10 of the Code of Federal Regulations 2.390 of the NRC's "Rules of  
ADAMS is accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html (the
Practice," a copy of this letter and its Enclosure will be available electronically for public  
Public Electronic Reading Room).
inspection in the NRC Public Document Room or from the Publicly Available Records (PARS)  
Thank you for your cooperation in this matter. If you have any questions, regarding the
component of NRC's Agencywide Documents Access and Management System (ADAMS).
information requested or the inspection, please contact Mr. Ottenberg at 404-997-4658 or
ADAMS is accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html (the  
contact me at 404-997-4607.
Public Electronic Reading Room).  
                                                Sincerely,
                                                /RA/
Thank you for your cooperation in this matter. If you have any questions, regarding the  
                                                Jonathan H. Bartley, Chief
information requested or the inspection, please contact Mr. Ottenberg at 404-997-4658 or  
                                                Engineering Branch 1
contact me at 404-997-4607.  
                                                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
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
SUNSI REVIEW COMPLETE  
NAME                GOTTENBERG    JBARTLEY
FORM 665 ATTACHED  
DATE                    3/29/2016    3/26/2016
OFFICE  
E-MAIL COPY?          YES    NO  YES      NO  YES    NO                  YES    NO      YES    NO    YES    NO    YES
RII:DRS  
       
RII:DRS  
        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:
SIGNATURE  
          a. Two risk rankings of components from your site-specific PSA: one sorted by Risk
JHB1 FOR GKO JHB1  
              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
NAME
    human reliability worksheets for these items.
GOTTENBERG
4. List of time-critical operator actions with a brief description of each action.
JBARTLEY
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
DATE
    failures/vulnerabilities (as communicated by NRC Generic Communications, Industry
3/29/2016
     Communications, 10 CFR Part 21 Notifications, etc.) since July 1, 2013.
3/26/2016
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
E-MAIL COPY?
    available) of your plans to address the issue(s).
     YES
                                                                                          Enclosure
NO      
  YES
NO      YES
NO      
   
  YES
NO      YES
NO      
  YES
NO      
  YES


                                            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.
Enclosure
12. List and reason for equipment classified in maintenance rule (a) (1) status from
INFORMATION REQUEST FOR H.B. ROBINSON STEAM ELECTRIC PLANT 
    July 1, 2013, to present.
COMPONENT DESIGN BASES INSPECTION
13. Copy of Updated Final Safety Analysis Report.
14. Copy of Technical Specification(s).
Please provide the information electronically in .pdf files, Excel, or other searchable format on
15. Copy of Technical Specifications Bases.
CDROM (or FTP site, Sharepoint, etc.).  The CDROM (or website) should be indexed and
16. Copy of Technical Requirements Manual(s).
hyperlinked to facilitate ease of use. 
17. List and brief description of Root Cause Evaluations performed since July 1, 2013.
18. Corrective Action Program Procedure(s).
1.
19. Copy of Operability Determination procedure(s).
From your most recent probabilistic safety analysis (PSA) excluding external events and
20. one-line diagram of electrical plant. (Electronic and full size - hard copy week
fires:
    of June 27 - July 1, 2016)
21. Index and legend for electrical plant one-line diagrams.
a. Two risk rankings of components from your site-specific PSA:  one sorted by Risk
22. Piping and instrumentation diagrams (P&IDs) for safety-related systems. (Electronic
Achievement Worth (RAW), and the other sorted by Birnbaum Importance
    and 11 x 17 size - hard copy week of June 27 - July 1, 2016)
23. Index and Legend for P&IDs.
b. A list of the top 500 cutsets
24. Copies of corrective action documents (i.e. CRs) associated with findings from previous
    CDBI. (If applicable)
2.
25. Index (procedure number, title, and current revision) of station Emergency Operating
From your most recent PSA including external events and fires:
    Procedures, Abnormal Operating Procedures, and Annunciator Response Procedures.
26. Copies of any self-assessments performed in preparation for this inspection (2016 CDBI)
a. Two risk rankings of components from your site-specific PSA:  one sorted by RAW,
    and the self-assessment performed in preparation for the previous CDBI (2013).
and the other sorted by Birnbaum Importance
27. List of any condition reports generated in preparation for this inspection.
28. Copies of condition reports generated from previous CDBI (2013).
b.  A list of the top 500 cutsets 
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)
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)
}}
}}

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)