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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 | ||
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 | Region II staff will conduct a component design bases inspection (CDBI) at your H.B. Robinson | ||
71111.21, | 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 | |||
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. | |||
required for inspection preparation. The additional information will need to be available to the team in the Region II office prior to the 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 | 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 | 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 | |||
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 | |||
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 | |||
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). | |||
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 | 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) | |||
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) | |||
}} | }} | ||
Latest revision as of 01:49, 10 January 2025
| ML16092A200 | |
| Person / Time | |
|---|---|
| Site: | Robinson |
| 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:
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)