ML13078A254

03/21/2013 Licensee Meeting Slides Re Joseph M. Farley Nuclear Plant NFPA 805 Fire Modeling LAR Submittal - Session 9

ML13078A254
Person / Time
Site:	Farley
Issue date:	03/19/2013
From:	Jo Y Southern Co, Southern Nuclear Operating Co
To:	Ellen Brown Plant Licensing Branch II
Brown E
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ML13078A286	List: ML13078A254
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Download: ML13078A254 (15)

Text

FNP LAR AUDIT PRESENTATION March 19, 2013 Session 9 - Fire PRA Young Jo

Agenda

• Unique Team Efforts in FNP Fire PRA

• P Peer R Review i off FNP FPRA

• Results of FNP Fire PRA

• FNP Fire PRA Model Development

• Use of Electrical Cabinet Factors

• FRE Process

FNP Fire PRA

• Farley Fire PRA was developed based on th state-of-the-art the t t f th t methodologies th d l i available in 2010 ~ 2012 time frame which i l d ffour non-NUREG/CR-6850 include NUREG/CR 6850 methods approved by the EPRI Methods R i Review P Panel:l

- Frequencies for cable fires initiated by welding and cutting

- Alignment factor for pump oil fires

- Clarification for transient fires

- Electrical cabinet fire treatment (Electrical cabinet factor)

Unique Team Efforts in FNP Fire PRA

• More than 9 focused reviews (each was about a week long) of all technical aspects of Farley fire PRA to make the Farley fire PRA model as realistic as possible

• Participants to the focused reviews were from all related technical areas:

- PRA logic modeling (Internal events and Fire)

- Fire modeling

- Fire Protection/SSA/NSCA

- Circuit analysis

- O Operations ti andd Design D i

Peer Review of FNP FPRA

• A RG 1.200, Rev. 2, Peer Review against the ASME PRA Supporting Requirements.

Requirements

• The review was conducted by the WOG in October 2011 and issued under LTR-RAM-II 007.

• The conclusion of the review was that the FNP methodologies being used were appropriate and sufficient to satisfy the ASME/ANS PRA Standard RA-Sa-2009

• All 31 finding level F&Os have been addressed in the LAR, Attachment V

Results of FNP Fire PRA CDF LERF Unit 1 5.24E-05/yr 1.26E-06/yr Unit 2 5.85E-05/yr 2.39E-06/yr from FNP NFPA 805 LAR Attachment W

FNP Fire PRA Development

• Task 1) Plant Partitioning

- PAUs - Fire Protection Program Fire Areas

- Administrative Partitions used for data management -

fire zones

• Task 2) Equipment Selection

- All PRA model basic events reviewed

- MSO components t

- All NSCA component failure modes are modeled or dispositioned p

- Cue Instruments for credited human actions FNP Fire PRA Development

• Task 3 and 9) Cable Selection/Analysis

- Used equipment functional states approach

- Consistent with guidance in NEI 00-01

- Identify Off Scheme Circuits

- Breaker Coordination addressed

- Analysis is entered into ARC FDM Database Software

- Consistent with industry practice FNP Fire PRA Development

• Task 5) Fire-Induced Risk Model

-BBased d on FNP IInternal t l PRA model, d l R Rev. 9 ((peer reviewed March 2010)

- Added logic structure for Fire PRA

• Accounts all applicable MSO Scenarios and SSD equipments

• Additional HVAC systems

• HEP cues - instruments

• Task 6) Fire Ignition Frequency

- Used supplement 1 (FAQ-08-0048) IGFs (with sensitivity)

- Plant Pl specific ifi iignition i i ffrequency via i BBayesian i update d

FNP Fire PRA Development

• Task 8 and 11) Scoping and Detailed Fi Modeling Fire M d li

- Generic Treatment Fire Modeling analysis results used to define zone of influence

- HGL evaluation used to address impact on generic zone of influence,, defines NSP for a ZOI scenario to lead to full zone damage

- Multi-Compartment Analysis

- Control Room Abandonment evaluation

FNP Fire PRA Development

• Task 10) Circuit Failure Mode &

Lik lih d A Likelihood Analysis l i

- In accordance with NUREG/CR-6850

• Table T bl 10 10-1 1 and d 10 10-2 2

- CPT credited

• Task 12) Fire HRA

- Based on FNP Internal PRA HRA with EPRI HRA calculator

- Credited additional EOP/AOP/SOP actions for Fire PRA

FNP Fire PRA Development

• Task 13) Seismic-Fire Interactions

- Credit previous analyses associated with IPEEE and an assessment of Fire Related Vulnerabilities

• Task 14) Fire Risk Quantification

- Documents results incorporating input from above tasks

• Task 15) Uncertainty and Sensitivity

- Provided qualitative evaluation of uncertainties associated with each NUREG/CR-6850 task

- Performed various sensitivityy analyses y and parametric uncertainty analysis using UNCERT code FNP FRE Process FNP Fire Delta Risk Delta CDF Delta LERF Unit 1 8.80E-06/yr 4.14E-07/yr Unit 2 8.99E-06/yr 5.98E-07/yr f

from FNP NFPA 805 LAR Att Attachment h tW

Results - FNP Plant Risk (/yr)

Unit 1 Unit 2 Hazard CDF LERF CDF LERF Internal Events 1.06E-05 1.24E-07 7.98E-06 1.20E-07 S i i Seismic 1 08E 05 1.08E-05 1 26E 07 1.26E-07 1 08E 05 1.08E-05 1 62E 07 1.62E-07 Other External Insignificant Insignificant Insignificant Insignificant Risk (IPEEE)

Fire 5.24E-05 1.26E-06 5.85E-05 2.39E-06 TOTAL 7.38E-05 1.51E-06 7.73E-05 2.67E-06 f

from FNP NFPA 805 LAR Att Attachment h tW