ML18248A107

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Presentation Slides - Watts Bar Nuclear Plant Units 1 and 2 Adoption of 10 CFR 50.69 - September 6, 2018
ML18248A107
Person / Time
Site: Watts Bar Tennessee Valley Authority icon.png
Issue date: 09/05/2018
From: Shea J W, Skaggs M D
Tennessee Valley Authority
To:
Division of Operating Reactor Licensing
Jordan N J
References
Download: ML18248A107 (16)


Text

Watts Bar Nuclear Plant Units 1 and 2Adoption of 10 CFR 50.69September 6, 2018 Agenda*10 CFR 50.69 Background

  • License Amendment Background
  • Operating Experience

-Submittal Meeting With NRC l 2 10 CFR 50.69 Overview Watts Bar 10 CFR 50.69 LAR Pre

-Submittal Meeting With NRC l 3It has the potential to provide the industry substantial cost savings and drive the goals of the Delivering the Nuclear Promise InitiativeFrom NEI Risk Informed Engineering ProgramsReduce BurdenLow Safety Significant AreasHigh Safety Significant AreasIncrease Focus Overview -CategorizationWatts Bar 10 CFR 50.69 LAR Pre

-Submittal Meeting With NRC l 450.69Safety RelatedNon Safety RelatedLow RiskHigh RiskFrom NEI Risk Informed Engineering Programs Overview -Exempted Special Treatment RequirementsWatts Bar 10 CFR 50.69 LAR Pre

-Submittal Meeting With NRC l 5From NEI Risk Informed Engineering Programs License Amendment Background

  • Delivering the Nuclear Promise Efficiency Bulletins (EB)EB 17-09 LAR SubmittalLAR TemplateEB 17-16 Process Implementation
  • LAR Coordinating CommitteePeer review prior to submittalComments resolved prior to submittalWatts Bar 10 CFR 50.69 LAR Pre

-Submittal Meeting With NRC l 6 License Amendment Background

-cont.*Joint Owners' Group CommitteeCollaborationSharing InfrastructureTrainingInformation SharingWatts Bar 10 CFR 50.69 LAR Pre

-Submittal Meeting With NRC l 7 HSS Component Determination OverviewDetermination of High Safety Significant (HSS) Components for Indicated Events/Hazards

-Internal Events, Risk Imp. Measures & Sensitivity Studies

-Internal Flooding, Risk Imp. Measures & Sensitivity Studies

-Seismic Events, Risk Imp. Measures & Sensitivity Studies

-Internal Fire, Fire Protection Program Safe Shutdown Equipment List (SSEL)

-Other External Hazards, any System, Structure or Component (SSC) Credited by the IPEEE to Screen the Hazard

-Shutdown Risks, Safety Function Defense

-In DepthWatts Bar 10 CFR 50.69 LAR Pre

-Submittal Meeting With NRC l 8 PRA Technical Adequacy EvaluationInternal Events & Internal Flooding PRA Model

-Peer reviewed in accordance with RG 1.200 Rev. 2 and ASME/ANS PRA Standard (2008) Addendum a

-Underwent Fact and Observation (F&O) Closure Process

-Seven Open F&Os (Finding Level) which were assessed

against the 50.69 applicationWatts Bar 10 CFR 50.69 LAR Pre

-Submittal Meeting With NRC l 9 PRA Technical Adequacy Evaluation cont.Seismic PRA Model-Full Scope Peer Review against the 2008 ASME/ANS PRA Standard Addendum b Part 5 (seismic)

-Underwent F&O Closure Process

-One Open F&O (Finding Level) which was assessed

against the 50.69 ApplicationWatts Bar 10 CFR 50.69 LAR Pre

-Submittal Meeting With NRC l 10 Model Update and Maintenance TVA procedures ensure or provide:

-Model configuration, fidelity and realism

-Periodic update requirements

-Living model requirements

-PRA model updates

>PRA Maintenance

>PRA Upgrade

-Peer Review requirementsWatts Bar 10 CFR 50.69 LAR Pre

-Submittal Meeting With NRC l 11 Non-Modeled HazardsInternal Fire Hazards -Deviationfrom the NEI 00

-04 approach.

-The Watts Bar 50.69 process will use the Fire Protection Program Safe-Shutdown Equipment List (SSEL)Watts Bar 10 CFR 50.69 LAR Pre

-Submittal Meeting With NRC l 12 Non-Modeled Hazards cont.

  • Other External Hazards

-the WBN process will use the screening results from the IPEEE for evaluation of safety significance related to:

-High Winds

-External Flooding

-Transportation and Nearby Facility Accidents

-Other External Initiating Events

  • All SSCs credited in IPEEE Other External Hazards evaluation to allow the hazard to screen will be considered High Safety Significant (HSS)
  • Other External Hazard screening was reviewed against the

current as-built, as-operated plantWatts Bar 10 CFR 50.69 LAR Pre

-Submittal Meeting With NRC l 13 Low-Power / Shutdown

  • The WBN Categorization process will use the shutdown safety management plan described in NUMARC 91

-06, for evaluation of safety significance related to low power and shutdown conditions.

  • TVA process assesses the potential impact on shutdown

risk oFocus on planning, conservative decision

-making and maintaining defense

-in-depth oAssessment of plant shutdown configurations for impact

on Key Safety FunctionsWatts Bar 10 CFR 50.69 LAR Pre

-Submittal Meeting With NRC l 14 LAR Schedule

  • Week of 9/10/18

-Draft 50.69 LAR to be reviewed by Industry Coordinating Committee*Coordination with TSTF

-425 Submittal

-It is expected that there will be review efficiencies gained because of the common PRA usage

-Both the 10 CFR 50.69 LAR and TSTF

-425 LAR submittals are planned for 9/28/18

  • A one-yearNRC review is requested
  • Upon approval, the 50.69 License Amendment will be implemented within 60 daysWatts Bar 10 CFR 50.69 LAR Pre

-Submittal Meeting With NRC l 15