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=Text=
=Text=
{{#Wiki_filter:Ms. Cheryl A. Gayheart Regulatory Affairs Director UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 26, 2019 Southern Nuclear Operating Company, Inc. 3535 Colonnade Parkway Birmingham, AL 35243  
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 26, 2019 Ms. Cheryl A. Gayheart Regulatory Affairs Director Southern Nuclear Operating Company, Inc.
3535 Colonnade Parkway Birmingham, AL 35243


==SUBJECT:==
==SUBJECT:==
JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 -AUDIT  
JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 - AUDIT  


==SUMMARY==
==SUMMARY==
IN SUPPORT OF THE LICENSE AMENDMENT REQUEST TO IMPLEMENT INFORMED TECHNICAL SPECIFICATIONS INITIATIVE 48 (EPID L-2018-LLA-0210)  
IN SUPPORT OF THE LICENSE AMENDMENT REQUEST TO IMPLEMENT RISK-INFORMED TECHNICAL SPECIFICATIONS INITIATIVE 48 (EPID L-2018-LLA-0210)


==Dear Ms. Gayheart:==
==Dear Ms. Gayheart:==


By letter dated July 27, 2018, Southern Nuclear Operating Company (SNC, the licensee) submitted a license amendment request to implement changes to their technical specifications program that establishes a risk-informed approach for voluntary extension of completion times for Limiting Conditions of Operations based on the Nuclear Energy Institute 06-09 methodology, "Risk-Informed Technical Specification Initiative 4b Risk-Managed Technical Specification (RMTS) Guidelines," Revision 0-A, for Joseph M. Farley Nuclear Plant, Units 1 and 2. The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the licensee's submittal and determined that a regulatory audit would assist in the timely completion of the licensing review process. The NRC staff issued the regulatory audit plan on January 4, 2019. The NRC staff conducted the regulatory audit on February 5-7, 2019, at the SNC corporate office in Birmingham, Alabama. The results of the regulatory audit will be used by the NRC staff to finalize requests for additional information.
By letter dated July 27, 2018, Southern Nuclear Operating Company (SNC, the licensee) submitted a license amendment request to implement changes to their technical specifications program that establishes a risk-informed approach for voluntary extension of completion times for Limiting Conditions of Operations based on the Nuclear Energy Institute 06-09 methodology, "Risk-Informed Technical Specification Initiative 4b Risk-Managed Technical Specification (RMTS) Guidelines," Revision 0-A, for Joseph M. Farley Nuclear Plant, Units 1 and 2.
The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the licensee's submittal and determined that a regulatory audit would assist in the timely completion of the licensing review process. The NRC staff issued the regulatory audit plan on January 4, 2019.
The NRC staff conducted the regulatory audit on February 5-7, 2019, at the SNC corporate office in Birmingham, Alabama. The results of the regulatory audit will be used by the NRC staff to finalize requests for additional information.
The audit summary report is provided as an enclosure to this letter.
The audit summary report is provided as an enclosure to this letter.
C. Gayheart If you have any questions, please contact me at 301-415-1009 or via e-mail at Shawn.Williams@nrc.gov.
 
Docket Nos. 50-348 and 50-364  
C. Gayheart                                     If you have any questions, please contact me at 301-415-1009 or via e-mail at Shawn.Williams@nrc.gov.
Sincerely, Shawn A. Williams, Senior Project Manager Plant Licensing Branch II 1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364


==Enclosure:==
==Enclosure:==
: 1. Audit Summary cc: Listserv Sincerely, Shawn A. Williams, Senior Project Manager Plant Licensing Branch II 1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FEBRUARY 5-7, 2019, AUDIT  
: 1. Audit Summary cc: Listserv
 
FEBRUARY 5-7, 2019, AUDIT  


==SUMMARY==
==SUMMARY==
LICENSE AMENDMENT REQUEST TO ADOPT NEI 06-09, REVISION 0-A RISK-INFORMED COMPLETION TIMES SOUTHERN NUCLEAR OPERA TING COMPANY JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-348 AND 50-364


==1.0 INTRODUCTION==
LICENSE AMENDMENT REQUEST TO ADOPT NEI 06-09, REVISION 0-A RISK-INFORMED COMPLETION TIMES SOUTHERN NUCLEAR OPERATING COMPANY JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-348 AND 50-364


By letter dated July 27, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 18208A619), Southern Nuclear Operating Company (SNC, the licensee) submitted a license amendment request (LAR) to implement changes to their technical specifications program that establishes a risk-informed approach for voluntary extension of completion times for Limiting Conditions of Operations based on the Nuclear Energy Institute (NEI) 06-09 methodology, "Risk-Informed Technical Specification Initiative 4b Risk-Managed Technical Specification (RMTS) Guidelines," Revision 0-A, for Joseph M. Farley Nuclear Plant, Units 1 and 2. The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the licensee's submittal and determined that a regulatory audit would assist in the timely completion of the licensing review process. The NRC staff issued the regulatory audit plan on January 4, 2019 (ADAMS Accession No. ML 18338A005) that included 26 questions to be discussed during the audit. The NRC staff conducted the regulatory audit on February 5-7, 2019, at the SNC corporate office in Birmingham, Alabama. The results of the regulatory audit will be used by the NRC staff to finalize requests for additional information (RAls). The regulatory audit was performed consistent with NRC Office of Nuclear Reactor Regulation (NRR) Office Instruction LIC-111, "Regulatory Audits" (ADAMS Accession No. ML082900195).
==1.0      INTRODUCTION==
2.0 AUDIT ACTIVITIES AND OBSERVATIONS The purpose of the audit was to understand the calculations, analyses, and bases for the LAR, and to develop requests for additional information, as needed. NRC staff discussions with SNC focused on internal events and fire probabilistic risk assessment (PRA) quality, PRA functionality, implementation of the risk informed completion time (RICT) program, TS limiting conditions for operation, and associated RICT program guidance documents.
 
SNC provided a demonstration of how it would implement the RICT. The NRC staff reviewed applicable program documents.
By letter dated July 27, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18208A619), Southern Nuclear Operating Company (SNC, the licensee) submitted a license amendment request (LAR) to implement changes to their technical specifications program that establishes a risk-informed approach for voluntary extension of completion times for Limiting Conditions of Operations based on the Nuclear Energy Institute (NEI) 06-09 methodology, "Risk-Informed Technical Specification Initiative 4b Risk-Managed Technical Specification (RMTS) Guidelines," Revision 0-A, for Joseph M. Farley Nuclear Plant, Units 1 and 2.
The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the licensee's submittal and determined that a regulatory audit would assist in the timely completion of the licensing review process. The NRC staff issued the regulatory audit plan on January 4, 2019 (ADAMS Accession No. ML18338A005) that included 26 questions to be discussed during the audit.
The NRC staff conducted the regulatory audit on February 5-7, 2019, at the SNC corporate office in Birmingham, Alabama. The results of the regulatory audit will be used by the NRC staff to finalize requests for additional information (RAls).
The regulatory audit was performed consistent with NRC Office of Nuclear Reactor Regulation (NRR) Office Instruction LIC-111, "Regulatory Audits" (ADAMS Accession No. ML082900195).
2.0     AUDIT ACTIVITIES AND OBSERVATIONS The purpose of the audit was to understand the calculations, analyses, and bases for the LAR, and to develop requests for additional information, as needed. NRC staff discussions with SNC focused on internal events and fire probabilistic risk assessment (PRA) quality, PRA functionality, implementation of the risk informed completion time (RICT) program, TS limiting conditions for operation, and associated RICT program guidance documents. SNC provided a demonstration of how it would implement the RICT. The NRC staff reviewed applicable program documents.
The following are the specific presentation and discussion topics discussed during the audit:
The following are the specific presentation and discussion topics discussed during the audit:
* SNC Presentation of Electrical Systems Modeled in the PRA (Question
* SNC Presentation of Electrical Systems Modeled in the PRA (Question 25)
: 25)
* Configuration Risk Management Program (CRMP) Tool Overview Enclosure
* Configuration Risk Management Program (CRMP) Tool Overview Enclosure
* SNC Presentation of Responses to Questions 12, 19, 20, 21 and 24 (LAR/TS)
* SNC Presentation of Responses to Questions 12, 19, 20, 21 and 24 (LAR/TS)
Line 53: Line 61:
* SNC Presentation of PRA Functional Definition, Development and Use
* SNC Presentation of PRA Functional Definition, Development and Use
* SNC responses to Questions 14, 17, 22, and 23 (PRA Functionality)
* SNC responses to Questions 14, 17, 22, and 23 (PRA Functionality)
* Presentation of Risk Management Actions (RMAs) Determinations  
* Presentation of Risk Management Actions (RMAs) Determinations /Examples (plus SNC response to 026)
/Examples (plus SNC response to 026)
* Detailed CRMP Presentation
* Detailed CRMP Presentation
* PRA Quality Discussion and SNC responses to Questions 1, 2, 3, 6, 8, 10
* PRA Quality Discussion and SNC responses to Questions 1, 2, 3, 6, 8, 10
* SNC responses to Questions 4 and 5 (PRA Modeling)
* SNC responses to Questions 4 and 5 (PRA Modeling)
* SNC responses to Questions 7 and 9 (Uncertainties)
* SNC responses to Questions 7 and 9 (Uncertainties)
Audit Exit: NRC staff went through each question/discussion topic in the Audit plan, and shared preliminary thoughts on any changes to the original set of questions/discussion topics. There were no regulatory decisions made regarding the final set of questions.
Audit Exit:
NRC staff stated that they planned to issue a formal RAI within 30 days of the Audit. 4.0 AUDIT PARTICIPANTS NRC Participants:
NRC staff went through each question/discussion topic in the Audit plan, and shared preliminary thoughts on any changes to the original set of questions/discussion topics. There were no regulatory decisions made regarding the final set of questions. NRC staff stated that they planned to issue a formal RAI within 30 days of the Audit.
4.0     AUDIT PARTICIPANTS NRC
 
==Participants:==
* Shawn Williams, Project Manager, Office of Nuclear Reactor Regulation (NRR), Division of Reactor Licensing (DORL)
* Shawn Williams, Project Manager, Office of Nuclear Reactor Regulation (NRR), Division of Reactor Licensing (DORL)
* Mihaela Biro, NRR, Division of Risk Assessment (DRA), Probabilistic Risk Assessment Licensing Branch A (APLA)
* Mihaela Biro, NRR, Division of Risk Assessment (DRA), Probabilistic Risk Assessment Licensing Branch A (APLA)
Line 68: Line 78:
* Victor Cusumano, NRR, Division of Safety Systems (DSS), Branch Chief Technical Specifications Branch (STSB)
* Victor Cusumano, NRR, Division of Safety Systems (DSS), Branch Chief Technical Specifications Branch (STSB)
* Garill Coles, PNNL (Contractor)
* Garill Coles, PNNL (Contractor)
SNC Participants:
SNC
 
==Participants:==
* Pamela Burns-Frazier
* Pamela Burns-Frazier
* Jonathan Register
* Jonathan Register
Line 78: Line 90:
* Vish Patel
* Vish Patel
* Owen Scott
* Owen Scott
* Matthew Warden   5.0 DOCUMENTS REVIEWED The following documents were available on the Farley Portal, and reviewed by NRC and PNNL staff. 1. SNC Calculation PRA-BC-F-17-002, "Seismic Risk Evaluation based on IPEEE and EPRI 2014 Farley Seismic Hazard," Version 1 (Reference 6 of Enclosure 4 to NL-18-0039), and 2. "Joseph M. Farley Nuclear Plant Units 1 and 2, Evaluation of Other External Hazards," Southern Nuclear PRA Report, Revision 0, December 31, 2013 (Reference A.2-2 of Enclosure 3 to NL-18-0039).
* Matthew Warden
 
5.0     DOCUMENTS REVIEWED The following documents were available on the Farley Portal, and reviewed by NRC and PNNL staff.
: 1. SNC Calculation PRA-BC-F-17-002, "Seismic Risk Evaluation based on IPEEE and EPRI 2014 Farley Seismic Hazard," Version 1 (Reference 6 of Enclosure 4 to NL-18-0039), and
: 2. "Joseph M. Farley Nuclear Plant Units 1 and 2, Evaluation of Other External Hazards,"
Southern Nuclear PRA Report, Revision 0, December 31, 2013 (Reference A.2-2 of Enclosure 3 to NL-18-0039).
: 3. Draft Responses to the Audit Questions.
: 3. Draft Responses to the Audit Questions.
: 4. F-RIE-FIREPRA-U00-014, Fire PRA Quantification and Summary Report, Revision 1 5. F-RIE-IEIF-U00-01, Internal Events and Internal Flooding and LERF Model Update" Revision 10, Version 2.0. 6. F-RIE-IEIF-U00-013, Characterizing the Sources of Model Uncertainty for Farley Nuclear Plant 7. 05058-RPT-011, Farley Fire PRA Uncertainty Analysis, Revision 2 8. NMP-GM-031-003, Risk Management Actions for RICT Program, Version 4.0 9. NMP-GM-031-002, Calculation of RMAT and RICT for the RICT Program, Version 3.1 10. NMP-GM-031-004, PRA Functionality Determination
: 4. F-RIE-FIREPRA-U00-014, Fire PRA Quantification and Summary Report, Revision 1
: 5. F-RIE-IEIF-U00-01, Internal Events and Internal Flooding and LERF Model Update" Revision 10, Version 2.0.
: 6. F-RIE-IEIF-U00-013, Characterizing the Sources of Model Uncertainty for Farley Nuclear Plant
: 7. 05058-RPT-011, Farley Fire PRA Uncertainty Analysis, Revision 2
: 8. NMP-GM-031-003, Risk Management Actions for RICT Program, Version 4.0
: 9. NMP-GM-031-002, Calculation of RMAT and RICT for the RICT Program, Version 3.1
: 10. NMP-GM-031-004, PRA Functionality Determination
: 11. FNP-O-SOP-0.13, Recording Limiting Conditions for Operation
: 11. FNP-O-SOP-0.13, Recording Limiting Conditions for Operation
: 12. SNCF-00358-REPT-001, Farley Internal Events F&O Closure Review (ENERCON)
: 12. SNCF-00358-REPT-001, Farley Internal Events F&O Closure Review (ENERCON)
: 13. F-FIE-FIREPAR U00-014, Internal Events PRA Uncertainty Analysis 14. FNP-O-AOP-21.0, Severe Weather Abnormal Operating Procedure
: 13. F-FIE-FIREPAR U00-014, Internal Events PRA Uncertainty Analysis
: 14. FNP-O-AOP-21.0, Severe Weather Abnormal Operating Procedure
: 15. SNCF-00355-REPT-001, Farley Fire PRA Focused-Scope Peer Review, July 2018 (ENERCON)
: 15. SNCF-00355-REPT-001, Farley Fire PRA Focused-Scope Peer Review, July 2018 (ENERCON)
: 16. R-401292913-255, Farley Fire PRA Focused-Scope Peer Review, January 2018 (ABS Consulting)
: 16. R-401292913-255, Farley Fire PRA Focused-Scope Peer Review, January 2018 (ABS Consulting)
C.Gayheart 
==SUBJECT:==
JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 -AUDIT


==SUMMARY==
ML19042A108                                    *via E-mail OFFICE   NRR/DORL/LPL2-1/PM NRR/DORL/LPL2-1 /LA NRR/DE/APLA/BC* NRR/DORL/LPL2-1/BC NAME     SWilliams           KGoldstein         MWentzel       MMarkley DATE     02/22/19           02/14/19           02/22/19        02/26/19 OFFICE   NRR/DORL/LPL2-1 /PM NAME     SWilliams DATE     02/26/19}}
IN SUPPORT OF THE LICENSE AMENDMENT REQUEST TO IMPLEMENT INFORMED TECHNICAL SPECIFICATIONS INITIATIVE 4B (EPID L-2018-LLA-0210)
DATED FEBRUARY 26, 2019 DISTRIBUTION:
PUBLIC RidsACRS MailCTR Resource RidsNrrLAKGoldstein Resource RidsNrrPMFarley Resource RidsRgn2MailCenter Resource MBiro, NRR VCusumano, NRRs BTjader, NRR GMatharu, NRR CDeMessieres, NRR JEvans, NRR DWu, NRR SVasavada, NRR ADAMS Accession No. ML 19042A108 OFFICE NRR/DORL/LPL2-1/PM NRR/DORL/LPL2-1  
/LA NRR/DE/APLA/BC*
NAME SWilliams KGoldstein MWentzel DATE 02/22/19 02/14/19 02/22/19 OFFICE NRR/DORL/LPL2-1  
/PM NAME SWilliams DATE 02/26/19 OFFICIAL RECORD COPY *via E-mail NRR/DORL/LPL2-1/BC MMarkley 02/26/19}}

Latest revision as of 04:37, 30 November 2019

Audit Summary in Support of the License Amendment Request to Implement Risk-Informed Technical Specifications Initiative 4B
ML19042A108
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 02/26/2019
From: Shawn Williams
Plant Licensing Branch II
To: Gayheart C
Southern Nuclear Operating Co
Williams S NRR/DORL/LPL2-2 415-1009
References
EPID L-2018-LLA-0210
Download: ML19042A108 (6)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 26, 2019 Ms. Cheryl A. Gayheart Regulatory Affairs Director Southern Nuclear Operating Company, Inc.

3535 Colonnade Parkway Birmingham, AL 35243

SUBJECT:

JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 - AUDIT

SUMMARY

IN SUPPORT OF THE LICENSE AMENDMENT REQUEST TO IMPLEMENT RISK-INFORMED TECHNICAL SPECIFICATIONS INITIATIVE 48 (EPID L-2018-LLA-0210)

Dear Ms. Gayheart:

By letter dated July 27, 2018, Southern Nuclear Operating Company (SNC, the licensee) submitted a license amendment request to implement changes to their technical specifications program that establishes a risk-informed approach for voluntary extension of completion times for Limiting Conditions of Operations based on the Nuclear Energy Institute 06-09 methodology, "Risk-Informed Technical Specification Initiative 4b Risk-Managed Technical Specification (RMTS) Guidelines," Revision 0-A, for Joseph M. Farley Nuclear Plant, Units 1 and 2.

The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the licensee's submittal and determined that a regulatory audit would assist in the timely completion of the licensing review process. The NRC staff issued the regulatory audit plan on January 4, 2019.

The NRC staff conducted the regulatory audit on February 5-7, 2019, at the SNC corporate office in Birmingham, Alabama. The results of the regulatory audit will be used by the NRC staff to finalize requests for additional information.

The audit summary report is provided as an enclosure to this letter.

C. Gayheart If you have any questions, please contact me at 301-415-1009 or via e-mail at Shawn.Williams@nrc.gov.

Sincerely, Shawn A. Williams, Senior Project Manager Plant Licensing Branch II 1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364

Enclosure:

1. Audit Summary cc: Listserv

FEBRUARY 5-7, 2019, AUDIT

SUMMARY

LICENSE AMENDMENT REQUEST TO ADOPT NEI 06-09, REVISION 0-A RISK-INFORMED COMPLETION TIMES SOUTHERN NUCLEAR OPERATING COMPANY JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-348 AND 50-364

1.0 INTRODUCTION

By letter dated July 27, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18208A619), Southern Nuclear Operating Company (SNC, the licensee) submitted a license amendment request (LAR) to implement changes to their technical specifications program that establishes a risk-informed approach for voluntary extension of completion times for Limiting Conditions of Operations based on the Nuclear Energy Institute (NEI) 06-09 methodology, "Risk-Informed Technical Specification Initiative 4b Risk-Managed Technical Specification (RMTS) Guidelines," Revision 0-A, for Joseph M. Farley Nuclear Plant, Units 1 and 2.

The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the licensee's submittal and determined that a regulatory audit would assist in the timely completion of the licensing review process. The NRC staff issued the regulatory audit plan on January 4, 2019 (ADAMS Accession No. ML18338A005) that included 26 questions to be discussed during the audit.

The NRC staff conducted the regulatory audit on February 5-7, 2019, at the SNC corporate office in Birmingham, Alabama. The results of the regulatory audit will be used by the NRC staff to finalize requests for additional information (RAls).

The regulatory audit was performed consistent with NRC Office of Nuclear Reactor Regulation (NRR) Office Instruction LIC-111, "Regulatory Audits" (ADAMS Accession No. ML082900195).

2.0 AUDIT ACTIVITIES AND OBSERVATIONS The purpose of the audit was to understand the calculations, analyses, and bases for the LAR, and to develop requests for additional information, as needed. NRC staff discussions with SNC focused on internal events and fire probabilistic risk assessment (PRA) quality, PRA functionality, implementation of the risk informed completion time (RICT) program, TS limiting conditions for operation, and associated RICT program guidance documents. SNC provided a demonstration of how it would implement the RICT. The NRC staff reviewed applicable program documents.

The following are the specific presentation and discussion topics discussed during the audit:

  • SNC Presentation of Electrical Systems Modeled in the PRA (Question 25)
  • Configuration Risk Management Program (CRMP) Tool Overview Enclosure
  • SNC Presentation of Responses to Questions 12, 19, 20, 21 and 24 (LAR/TS)
  • Loss of Function Discussion and SNC response to Questions 13, 15, 16, and 18
  • External Hazards Discussion and SNC response to Question 11
  • SNC Presentation of PRA Functional Definition, Development and Use
  • SNC responses to Questions 14, 17, 22, and 23 (PRA Functionality)
  • Presentation of Risk Management Actions (RMAs) Determinations /Examples (plus SNC response to 026)
  • Detailed CRMP Presentation
  • PRA Quality Discussion and SNC responses to Questions 1, 2, 3, 6, 8, 10
  • SNC responses to Questions 4 and 5 (PRA Modeling)
  • SNC responses to Questions 7 and 9 (Uncertainties)

Audit Exit:

NRC staff went through each question/discussion topic in the Audit plan, and shared preliminary thoughts on any changes to the original set of questions/discussion topics. There were no regulatory decisions made regarding the final set of questions. NRC staff stated that they planned to issue a formal RAI within 30 days of the Audit.

4.0 AUDIT PARTICIPANTS NRC

Participants:

  • Shawn Williams, Project Manager, Office of Nuclear Reactor Regulation (NRR), Division of Reactor Licensing (DORL)
  • Candace De Messieres, NRR, APLA
  • Gurcharan Matharu, NRR, Division of Engineering (DE), Electrical Engineering Operating Reactors Branch (EEOB)
  • Victor Cusumano, NRR, Division of Safety Systems (DSS), Branch Chief Technical Specifications Branch (STSB)
  • Garill Coles, PNNL (Contractor)

SNC

Participants:

  • Pamela Burns-Frazier
  • Jonathan Register
  • Adam Coker
  • Alex Gilbreath
  • Dan Williams
  • Matthew Barefield
  • Phillip Ward
  • Vish Patel
  • Owen Scott
  • Matthew Warden

5.0 DOCUMENTS REVIEWED The following documents were available on the Farley Portal, and reviewed by NRC and PNNL staff.

1. SNC Calculation PRA-BC-F-17-002, "Seismic Risk Evaluation based on IPEEE and EPRI 2014 Farley Seismic Hazard," Version 1 (Reference 6 of Enclosure 4 to NL-18-0039), and
2. "Joseph M. Farley Nuclear Plant Units 1 and 2, Evaluation of Other External Hazards,"

Southern Nuclear PRA Report, Revision 0, December 31, 2013 (Reference A.2-2 of Enclosure 3 to NL-18-0039).

3. Draft Responses to the Audit Questions.
4. F-RIE-FIREPRA-U00-014, Fire PRA Quantification and Summary Report, Revision 1
5. F-RIE-IEIF-U00-01, Internal Events and Internal Flooding and LERF Model Update" Revision 10, Version 2.0.
6. F-RIE-IEIF-U00-013, Characterizing the Sources of Model Uncertainty for Farley Nuclear Plant
7. 05058-RPT-011, Farley Fire PRA Uncertainty Analysis, Revision 2
8. NMP-GM-031-003, Risk Management Actions for RICT Program, Version 4.0
9. NMP-GM-031-002, Calculation of RMAT and RICT for the RICT Program, Version 3.1
10. NMP-GM-031-004, PRA Functionality Determination
11. FNP-O-SOP-0.13, Recording Limiting Conditions for Operation
12. SNCF-00358-REPT-001, Farley Internal Events F&O Closure Review (ENERCON)
13. F-FIE-FIREPAR U00-014, Internal Events PRA Uncertainty Analysis
14. FNP-O-AOP-21.0, Severe Weather Abnormal Operating Procedure
15. SNCF-00355-REPT-001, Farley Fire PRA Focused-Scope Peer Review, July 2018 (ENERCON)
16. R-401292913-255, Farley Fire PRA Focused-Scope Peer Review, January 2018 (ABS Consulting)

ML19042A108 *via E-mail OFFICE NRR/DORL/LPL2-1/PM NRR/DORL/LPL2-1 /LA NRR/DE/APLA/BC* NRR/DORL/LPL2-1/BC NAME SWilliams KGoldstein MWentzel MMarkley DATE 02/22/19 02/14/19 02/22/19 02/26/19 OFFICE NRR/DORL/LPL2-1 /PM NAME SWilliams DATE 02/26/19