ML18065A020

March 12, 2018, Public Meeting Presentation

ML18065A020
Person / Time
Site:	Farley
Issue date:	03/12/2018
From:	Shawn Williams Plant Licensing Branch II
To:
Williams S, NRR/DORL/LPLII-1
Shared Package
ML18065A015	List: ML18065A020 ML18065A022 ML18065A025
References
Download: ML18065A020 (8)

Text

Joseph M. Farley Nuclear Plant Risk-Informed Technical Specifications Risk-Informed Initiative 4bPre-submittal MeetingMarch 12, 2018 OverviewFarley 4b License Amendment Request (LAR)

• Plant specific application based on the approved Vogtle Safety Evaluation(SE)

• Implementation plans

• Probabilistic Risk Assessment (PRA) models

• LAR Enclosures

• SNC RequestsKey Dates*Vogtle Application approved June 2017

• Farley LAR submittal planned for early 2Q

-2018 3 FNP Identical to Vogtle Application

• Identical to approved Vogtle Risk

-Informed Technical Specifications (RITF)

-"Methods" license condition identical to Vogtle

-Tech Spec Section 3.3, Instrumentation, not in scope

-Use of either Common Cause Failure (CCF) Risk Managed Actions (RMAs) or modify CCF factors as required when applying an emergent Risk

-Informed Completion Time (RICT)

-Use of 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> backstop and design

-basis parameter success criteria for Loss of Function (LOF) RICT

-Providing examples of RMAs planned during RICTs related to TS inoperability of electrical equipment, like Diesel Generators (DGs), Inverters and offsite sources.

-Vogtle Requests for Additional Information (RAI) incorporated and explicitly described in Attachment 1.

4 Implementation Plans

• Implementing procedures are based on

-NEI 06-09 guidance

-NRC Vogtle 4b audit inputs

-Vogtle RAI responses

-Vogtle 4b LAR NRC SE.

• FNP site is planning for a 4b implementation by the middle to end of 2019 by focusing on:

-Change management

-Procedures changes to make fleet procedures applicable to Farley

-Training to be delivered to Operations , Work Management and Supervision; as it was for Plant Vogtle.

5 Farley PRA Models

• Appendix X not utilized

• F&O resolutions reviewed in previous submittals

-NFPA 805 *Original SE

-March 10,2015

-ML14308A048

• Final SE -November 1, 2017

-ML17269A166

-ILRT (SE -ML17261A087)

-5b, Surveillance frequency control program(SE ML11167A226)

• Fire model data updates

-Incipient Detection

• FAQ-08-046 to NUREG 2180

-Reactor Coolant Pump Shutdown Seal model credit

• (Verification of approval version: ML17200C865)

-Fire Ignition Frequencies (NUREG 2169)

-Heat Release Rates (NUREG 2178) 6 LAR EnclosuresEnclosure 1: List of Revised Required Actions to Corresponding PRA Functions.

-Similar to VEGP LAR in content

-RICT calculations based on PEER Reviewed frozen models (previous version of the model)

• Example calculations of RICTs

• Actual RICTs may vary based on plant configuration

• Review of Vogtle RAI for DC subsystemsEnclosure 2: Information Supporting Consistency with Reg. Guide 1.200, Revision 2.

-Documents resolution of F&Os for Internal, Internal Flooding and Internal Fire PRAsEnclosure 3: Information Supporting Justification of Bounding Analysis or Excluding Sources of Risk Not Addressed by the PRA Models

-Documents use of Seismic bounding value based on convolution of FNP IPEEE and EPRI 2014 hazard Enclosure 4: Baseline CDF and LERF

-Total CDF/LERF meet 1E

-04/1E-05 RG 1.1.74 risk thresholds based on latest version FNP modelsEnclosure 5: PRA Model Update ProcessEnclosure 6: Attributes of the CRMP ModelEnclosure 7: Key Assumptions and Sources of UncertaintyEnclosure 8: Program ImplementationEnclosure 9: Cumulative Risk and Performance Monitoring ProgramEnclosure 10: Risk Management Action Example 7

SNC Requests 8*Alignment on plant specific applications

-Identical to Vogtle

-Any issues with NRC approval of Vogtle 4b

• Use of previously approved models and recent changes

• NRC Staff feedback on SNC approach to Enclosure 1