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| issue date = 12/20/2013 | | issue date = 12/20/2013 | ||
| title = Notification of Joseph M. Farley Nuclear Plant, Units 1 and 2 Component Design Bases Inspection - NRC Inspection Report 05000348-14-007, 05000364-14-007 | | title = Notification of Joseph M. Farley Nuclear Plant, Units 1 and 2 Component Design Bases Inspection - NRC Inspection Report 05000348-14-007, 05000364-14-007 | ||
| author name = Nease R | | author name = Nease R | ||
| author affiliation = NRC/RGN-II/DRS/EB1 | | author affiliation = NRC/RGN-II/DRS/EB1 | ||
| addressee name = Lynch T | | addressee name = Lynch T | ||
| addressee affiliation = Southern Nuclear Operating Co, Inc | | addressee affiliation = Southern Nuclear Operating Co, Inc | ||
| docket = 05000348, 05000364 | | docket = 05000348, 05000364 | ||
Line 14: | Line 14: | ||
| page count = 6 | | page count = 6 | ||
}} | }} | ||
See also: [[ | See also: [[see also::IR 05000348/2014007]] | ||
=Text= | =Text= | ||
{{#Wiki_filter: | {{#Wiki_filter:UNITED STATES | ||
NUCLEAR REGULATORY COMMISSION | |||
REGION II | |||
245 PEACHTREE CENTER AVENUE NE, SUITE 1200 | |||
ATLANTA, GEORGIA 30303-1257 | |||
December 20, 2013 | |||
Mr. T. A. Lynch | |||
Vice President | |||
Southern Nuclear Operating Company, Inc. | |||
Joseph M. Farley Nuclear Plant | |||
P.O. Drawer 470, BIN B500 | |||
Ashford, AL 36312 | |||
SUBJECT: NOTIFICATION OF JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1, AND 2 | |||
COMPONENT DESIGN BASES INSPECTION - NRC INSPECTION REPORT | |||
05000348/2014007, 05000364/2014007 | |||
Dear Mr. Lynch: | |||
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 Farley Nuclear | |||
Plant, Units 1, and 2 during the weeks of May 5 - 9, May 19 - 23, and June 2 - 6, 2014. Tonya | |||
Lighty, a Project Engineer from the NRCs Region II Office, will lead the inspection team. This | |||
inspection will be conducted in accordance with the baseline inspection procedure, Procedure | |||
71111.21, Component Design Bases Inspection, issued 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 December 13, 2013, Ms. Lighty confirmed with William | |||
Arens 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 April 7 - 11, 2014 | |||
* Onsite weeks: May 5 - 9, May 19 - 23, and June 2 - 6, 2014 | |||
The purpose of the information-gathering visit is to meet with members of your staff to identify | |||
risk-significant components and operator actions. Information and documentation needed to | |||
support the inspection will also be identified. Mr. George MacDonald, a Region II Senior | |||
Reactor Analyst, will support Ms. Lighty 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 needed prior to the information-gathering visit. Please provide | |||
the referenced information to the Region II Office by March 14, 2014. | |||
T.A. Lynch 2 | |||
Additional documents will be requested during the information-gathering visit. The inspectors | |||
will try to minimize your administrative burden by specifically identifying only those documents | |||
required for inspection preparation. The additional information should be available to the team | |||
in the Region II Office prior to the inspection teams preparation week of April 28, 2014. | |||
Ms. Lighty will also discuss the following inspection support administrative details: | |||
(1) availability of knowledgeable plant engineering and licensing personnel to serve as points of | |||
contact during the inspection, (2) method of tracking inspector requests during the inspection, | |||
(3) licensee computer access, (4) working space, (5) arrangements for site access, and (6) | |||
other applicable information. | |||
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its | |||
enclosure will be available electronically for public inspection in the NRC Public Document | |||
Room or from the Publicly Available Records (PARS) component of NRC's Agencywide | |||
Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC | |||
website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). | |||
Thank you for your cooperation in this matter. If you have any questions, regarding the | |||
information requested or the inspection, please contact Ms. Lighty at 404-997-4565 or contact | |||
me at 404-997-4530. | |||
Sincerely, | |||
RA | |||
Rebecca L. Nease, Chief | |||
Engineering Branch 1 | |||
Division of Reactor Safety | |||
Docket Nos.: 50-348, 50-364 | |||
License Nos.: NPF-2, NPF-8 | |||
Enclosure: | |||
Information Request for Farley Nuclear Plant, Units 1, and 2, Component | |||
Design Bases Inspection | |||
cc: Distribution via Listserv | |||
Additional documents will be requested during the information-gathering visit. The inspectors | |||
will try to minimize your administrative burden by specifically identifying only those documents | |||
required for inspection preparation. The additional information should be available to the team | |||
in the Region II Office prior to the inspection teams preparation week of April 28, 2014. | |||
Ms. Lighty will also discuss the following inspection support administrative details: | |||
(1) availability of knowledgeable plant engineering and licensing personnel to serve as points of | |||
contact during the inspection, (2) method of tracking inspector requests during the inspection, | |||
(3) licensee computer access, (4) working space, (5) arrangements for site access, and (6) | |||
other applicable information. | |||
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its | |||
enclosure will be available electronically for public inspection in the NRC Public Document | |||
Room or from the Publicly Available Records (PARS) component of NRC's Agencywide | |||
Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC | |||
website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). | |||
_ __x SUNSI REVIEW COMPLETE FORM 665 ATTACHED | |||
OFFICE RII: DRP RII: DRS RII: DRP | |||
SIGNATURE RA RA RA | |||
NAME Lighty NEASE MacDonald | |||
DATE 12/ 20/2013 12/20/2013 12/20/2013 | |||
E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO | |||
INFORMATION REQUEST FARLEY NUCLEAR PLANT, UNITS 1, AND 2 | |||
COMPONENT DESIGN BASES INSPECTION | |||
Please provide the information electronically in .pdf files, Excel, or other searchable format on | |||
CDROM (or FTP site, Sharepoint, etc.). The CDROM (or website) should be indexed and | |||
hyperlinked to facilitate ease of use. | |||
1. From your most recent probabilistic safety analysis (PSA) excluding external events and | |||
fires: | |||
a. Two risk rankings of components from your site-specific PSA: one sorted by Risk | |||
Achievement Worth (RAW), and the other sorted by Birnbaum Importance | |||
b. A list of the top 500 cutsets | |||
2. From your most recent PSA including external events and fires: | |||
a. Two risk rankings of components from your site-specific PSA: one sorted by RAW, | |||
and the other sorted by Birnbaum Importance | |||
b. A list of the top 500 cutsets | |||
3. Risk ranking of operator actions from your site-specific PSA sorted by RAW. Provide | |||
human reliability worksheets for these items. | |||
4. List of time-critical operator actions with a brief description of each action. | |||
5. List of Emergency and Abnormal Operating Procedures revised (significant) since | |||
September 1, 2011, with a brief description of each revision. | |||
6. List of components with low design margins (i.e., pumps closest to the design limit for flow | |||
or pressure, diesel generator close to design-required output, heat exchangers close to | |||
rated design heat removal, and motor-operated valve risk-margin rankings, etc.), and | |||
associated evaluations or calculations. | |||
7. List of station operating experience evaluations/reviews performed, and documented in the | |||
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 September 1, 2011. | |||
8. List and brief description of safety-related structures, systems, or components (SSCs) | |||
design modifications implemented since September 1, 2011. | |||
9. List and brief description of common-cause component failures that have occurred | |||
since September 1, 2011. | |||
10. List and brief description of operability evaluations completed since September 1, 2011. | 10. List and brief description of operability evaluations completed since September 1, 2011. | ||
Enclosure | |||
2 11. List of equipment on the | 2 | ||
11. List of equipment on the sites Station Equipment Reliability Issues List, including a | |||
12. List and brief description of equipment currently in degraded or nonconforming status as described in Regulatory Issue Summary 05-020. | description of the reason(s) why each component is on that list, and summaries (if | ||
available) of your plans to address the issue(s). | |||
13. List and reason for equipment classified in maintenance rule (a)(1) status from September 1, 2011, to present. 14. Copies of system descriptions (or the design basis documents) for safety-related systems. 15. Copy of Updated Final Safety Analysis Report. | 12. List and brief description of equipment currently in degraded or nonconforming status as | ||
described in Regulatory Issue Summary 05-020. | |||
13. List and reason for equipment classified in maintenance rule (a)(1) status from | |||
September 1, 2011, to present. | |||
14. Copies of system descriptions (or the design basis documents) for safety-related systems. | |||
15. Copy of Updated Final Safety Analysis Report. | |||
16. Copy of Technical Specification(s). | 16. Copy of Technical Specification(s). | ||
17. Copy of Technical Specifications Bases. | |||
17. Copy of Technical Specifications Bases. 18. Copy of Technical Requirements Manual(s). 19. List and brief description of Root Cause Evaluations performed since September 1, 2011. 20. In-service Testing Program Procedure(s). | 18. Copy of Technical Requirements Manual(s). | ||
19. List and brief description of Root Cause Evaluations performed since September 1, 2011. | |||
20. In-service Testing Program Procedure(s). | |||
21. Corrective Action Program Procedure(s). | 21. Corrective Action Program Procedure(s). | ||
22. One-line diagram of electrical plant. (Electronic and full size - hard copy week of | |||
22. One-line diagram of electrical plant. (Electronic and full size - hard copy week of April 7 - 11, 2014) | April 7 - 11, 2014) | ||
23. Index and legend for electrical plant one-line diagrams. | 23. Index and legend for electrical plant one-line diagrams. | ||
24. Primary AC calculation(s) for safety-related buses. | |||
24. Primary AC calculation(s) for safety-related buses. 25. Primary DC calculation(s) for safety-related buses. 26. Piping and instrumentation diagrams (P&IDs) for safety-related systems. (Electronic and 1/2 size - hard copy week of April 7 - 11, 2014) | 25. Primary DC calculation(s) for safety-related buses. | ||
26. Piping and instrumentation diagrams (P&IDs) for safety-related systems. (Electronic and | |||
1/2 size - hard copy week of April 7 - 11, 2014) | |||
27. Index and Legend for P&IDs. | 27. Index and Legend for P&IDs. | ||
28. Copy of Operability Determination procedure(s). | |||
30. Copies of corrective action documents (i.e. CRs) associated with findings from previous | |||
CDBI. (If applicable) | |||
31. Index (procedure number, title, and current revision) of station Emergency Operating | |||
Procedures, Abnormal Operating Procedures, and Annunciator Response Procedures. | |||
32. Copy of any self-assessments performed in preparation for this inspection. | |||
3 | |||
33. List of any condition reports generated in preparation for this inspection. | |||
34. Copies of condition reports generated from previous CDBI (2011). | |||
35. Contact information for a person to discuss PSA information prior to the information- | |||
35. Contact information for a person to discuss PSA information prior to the information-gathering trip. (Name, title, phone number, and e-mail address) | gathering trip. (Name, title, phone number, and e-mail address) | ||
}} | }} |
Latest revision as of 10:58, 4 November 2019
ML13354B972 | |
Person / Time | |
---|---|
Site: | Farley ![]() |
Issue date: | 12/20/2013 |
From: | Nease R NRC/RGN-II/DRS/EB1 |
To: | Lynch T Southern Nuclear Operating Co |
References | |
IR-14-007 | |
Download: ML13354B972 (6) | |
See also: IR 05000348/2014007
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION II
245 PEACHTREE CENTER AVENUE NE, SUITE 1200
ATLANTA, GEORGIA 30303-1257
December 20, 2013
Mr. T. A. Lynch
Vice President
Southern Nuclear Operating Company, Inc.
Joseph M. Farley Nuclear Plant
P.O. Drawer 470, BIN B500
Ashford, AL 36312
SUBJECT: NOTIFICATION OF JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1, AND 2
COMPONENT DESIGN BASES INSPECTION - NRC INSPECTION REPORT
05000348/2014007, 05000364/2014007
Dear Mr. Lynch:
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 Farley Nuclear
Plant, Units 1, and 2 during the weeks of May 5 - 9, May 19 - 23, and June 2 - 6, 2014. Tonya
Lighty, a Project Engineer from the NRCs Region II Office, will lead the inspection team. This
inspection will be conducted in accordance with the baseline inspection procedure, Procedure
71111.21, Component Design Bases Inspection, issued 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 December 13, 2013, Ms. Lighty confirmed with William
Arens 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 April 7 - 11, 2014
- Onsite weeks: May 5 - 9, May 19 - 23, and June 2 - 6, 2014
The purpose of the information-gathering visit is to meet with members of your staff to identify
risk-significant components and operator actions. Information and documentation needed to
support the inspection will also be identified. Mr. George MacDonald, a Region II Senior
Reactor Analyst, will support Ms. Lighty 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 needed prior to the information-gathering visit. Please provide
the referenced information to the Region II Office by March 14, 2014.
T.A. Lynch 2
Additional documents will be requested during the information-gathering visit. The inspectors
will try to minimize your administrative burden by specifically identifying only those documents
required for inspection preparation. The additional information should be available to the team
in the Region II Office prior to the inspection teams preparation week of April 28, 2014.
Ms. Lighty will also discuss the following inspection support administrative details:
(1) availability of knowledgeable plant engineering and licensing personnel to serve as points of
contact during the inspection, (2) method of tracking inspector requests during the inspection,
(3) licensee computer access, (4) working space, (5) arrangements for site access, and (6)
other applicable information.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its
enclosure will be available electronically for public inspection in the NRC Public Document
Room or from the Publicly Available Records (PARS) component of NRC's Agencywide
Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC
website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Thank you for your cooperation in this matter. If you have any questions, regarding the
information requested or the inspection, please contact Ms. Lighty at 404-997-4565 or contact
me at 404-997-4530.
Sincerely,
Rebecca L. Nease, Chief
Engineering Branch 1
Division of Reactor Safety
Docket Nos.: 50-348, 50-364
Enclosure:
Information Request for Farley Nuclear Plant, Units 1, and 2, Component
Design Bases Inspection
cc: Distribution via Listserv
Additional documents will be requested during the information-gathering visit. The inspectors
will try to minimize your administrative burden by specifically identifying only those documents
required for inspection preparation. The additional information should be available to the team
in the Region II Office prior to the inspection teams preparation week of April 28, 2014.
Ms. Lighty will also discuss the following inspection support administrative details:
(1) availability of knowledgeable plant engineering and licensing personnel to serve as points of
contact during the inspection, (2) method of tracking inspector requests during the inspection,
(3) licensee computer access, (4) working space, (5) arrangements for site access, and (6)
other applicable information.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its
enclosure will be available electronically for public inspection in the NRC Public Document
Room or from the Publicly Available Records (PARS) component of NRC's Agencywide
Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC
website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
_ __x SUNSI REVIEW COMPLETE FORM 665 ATTACHED
OFFICE RII: DRP RII: DRS RII: DRP
NAME Lighty NEASE MacDonald
DATE 12/ 20/2013 12/20/2013 12/20/2013
E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO
INFORMATION REQUEST FARLEY NUCLEAR PLANT, UNITS 1, AND 2
COMPONENT DESIGN BASES INSPECTION
Please provide the information electronically in .pdf files, Excel, or other searchable format on
CDROM (or FTP site, Sharepoint, etc.). The CDROM (or website) should be indexed and
hyperlinked to facilitate ease of use.
1. From your most recent probabilistic safety analysis (PSA) excluding external events and
fires:
a. Two risk rankings of components from your site-specific PSA: one sorted by Risk
Achievement Worth (RAW), and the other sorted by Birnbaum Importance
b. A list of the top 500 cutsets
2. From your most recent PSA including external events and fires:
a. Two risk rankings of components from your site-specific PSA: one sorted by RAW,
and the other sorted by Birnbaum Importance
b. A list of the top 500 cutsets
3. Risk ranking of operator actions from your site-specific PSA sorted by RAW. Provide
human reliability worksheets for these items.
4. List of time-critical operator actions with a brief description of each action.
5. List of Emergency and Abnormal Operating Procedures revised (significant) since
September 1, 2011, with a brief description of each revision.
6. List of components with low design margins (i.e., pumps closest to the design limit for flow
or pressure, diesel generator close to design-required output, heat exchangers close to
rated design heat removal, and motor-operated valve risk-margin rankings, etc.), and
associated evaluations or calculations.
7. List of station operating experience evaluations/reviews performed, and documented in the
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 September 1, 2011.
8. List and brief description of safety-related structures, systems, or components (SSCs)
design modifications implemented since September 1, 2011.
9. List and brief description of common-cause component failures that have occurred
since September 1, 2011.
10. List and brief description of operability evaluations completed since September 1, 2011.
Enclosure
2
11. 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).
12. List and brief description of equipment currently in degraded or nonconforming status as
described in Regulatory Issue Summary 05-020.
13. List and reason for equipment classified in maintenance rule (a)(1) status from
September 1, 2011, to present.
14. Copies of system descriptions (or the design basis documents) for safety-related systems.
15. Copy of Updated Final Safety Analysis Report.
16. Copy of Technical Specification(s).
17. Copy of Technical Specifications Bases.
18. Copy of Technical Requirements Manual(s).
19. List and brief description of Root Cause Evaluations performed since September 1, 2011.
20. In-service Testing Program Procedure(s).
21. Corrective Action Program Procedure(s).
22. One-line diagram of electrical plant. (Electronic and full size - hard copy week of
April 7 - 11, 2014)
23. Index and legend for electrical plant one-line diagrams.
24. Primary AC calculation(s) for safety-related buses.
25. Primary DC calculation(s) for safety-related buses.
26. Piping and instrumentation diagrams (P&IDs) for safety-related systems. (Electronic and
1/2 size - hard copy week of April 7 - 11, 2014)
27. Index and Legend for P&IDs.
28. Copy of Operability Determination procedure(s).
30. Copies of corrective action documents (i.e. CRs) associated with findings from previous
CDBI. (If applicable)
31. Index (procedure number, title, and current revision) of station Emergency Operating
Procedures, Abnormal Operating Procedures, and Annunciator Response Procedures.
32. Copy of any self-assessments performed in preparation for this inspection.
3
33. List of any condition reports generated in preparation for this inspection.
34. Copies of condition reports generated from previous CDBI (2011).
35. Contact information for a person to discuss PSA information prior to the information-
gathering trip. (Name, title, phone number, and e-mail address)