ML18248A107
| ML18248A107 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 09/05/2018 |
| From: | James Shea, Skaggs M Tennessee Valley Authority |
| To: | Division of Operating Reactor Licensing |
| Jordan N | |
| References | |
| Download: ML18248A107 (16) | |
Text
Watts Bar Nuclear Plant Units 1 and 2 Adoption of 10 CFR 50.69 September 6, 2018
Agenda
- 10 CFR 50.69 Background
- License Amendment Background
- Operating Experience
- Watts Bar 50.69 Evaluation Watts Bar 10 CFR 50.69 LAR Pre-Submittal Meeting With NRC l 2
10 CFR 50.69 Overview Watts Bar 10 CFR 50.69 LAR Pre-Submittal Meeting With NRC l 3 It has the potential to provide the industry substantial cost savings and drive the goals of the Delivering the Nuclear Promise Initiative From NEI Risk Informed Engineering Programs Reduce Burden Low Safety Significant Areas High Safety Significant Areas Increase Focus
Overview - Categorization Watts Bar 10 CFR 50.69 LAR Pre-Submittal Meeting With NRC l 4 50.69 Safety Related Non Safety Related Low Risk High Risk From NEI Risk Informed Engineering Programs
Overview - Exempted Special Treatment Requirements Watts Bar 10 CFR 50.69 LAR Pre-Submittal Meeting With NRC l 5 From NEI Risk Informed Engineering Programs
License Amendment Background
- Delivering the Nuclear Promise Efficiency Bulletins (EB)
EB 17-09 LAR Submittal LAR Template
EB 17-16 Process Implementation
- LAR Coordinating Committee
Peer review prior to submittal
Comments resolved prior to submittal Watts Bar 10 CFR 50.69 LAR Pre-Submittal Meeting With NRC l 6
License Amendment Background - cont.
- Joint Owners Group Committee
Collaboration
Sharing Infrastructure
Training
Information Sharing Watts Bar 10 CFR 50.69 LAR Pre-Submittal Meeting With NRC l 7
HSS Component Determination Overview Determination 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 Depth Watts Bar 10 CFR 50.69 LAR Pre-Submittal Meeting With NRC l 8
PRA Technical Adequacy Evaluation Internal 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 application Watts 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 Application Watts 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 requirements Watts Bar 10 CFR 50.69 LAR Pre-Submittal Meeting With NRC l 11
Non-Modeled Hazards Internal Fire Hazards Deviation from 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 plant Watts 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 o Focus on planning, conservative decision-making and maintaining defense-in-depth o Assessment of plant shutdown configurations for impact on Key Safety Functions Watts 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-year NRC review is requested Upon approval, the 50.69 License Amendment will be implemented within 60 days Watts Bar 10 CFR 50.69 LAR Pre-Submittal Meeting With NRC l 15