ML15070A252
| ML15070A252 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde |
| Issue date: | 02/18/2015 |
| From: | Edington R Arizona Public Service Co |
| To: | Watford M Plant Licensing Branch IV |
| Singal B | |
| References | |
| Download: ML15070A252 (34) | |
Text
Palo Verde/NRC Pre-submittal Meeting Risk Informed Completion Times February 18, 2015
Introductions
Bryan Thiele Department Leader Risk Informed Project Manager
Agenda
- Introduction Bryan Thiele
- Palo Verde Overview Thomas Romay
- License Amendment Thomas Weber
- PRA Summary Everett DePue
- Implementation Plan Bryan Thiele
- Path Forward and Closing Comments Bryan Thiele 3
Desired Meeting Outcomes
- Summarize PVNGS design with focus on unique features
- Discuss license amendment content and variances from TSTF 505
- Provide overview of PRA models
- Discuss implementation plan
- Describe path forward 4
Palo Verde Design Overview Tom Romay Shift Manager Senior Reactor Operator
6
Transmission Network 7
Palo Verde Design Features
- Three identical, separate Units, minimal shared SSCs
- No pressurizer PORVs
- Low leakage RCP seals following loss of seal cooling
- Four channels of class instrumentation (two trains w/2 channels each) with separate power
- Demonstrated capability to feed SG with no AC/DC power 8
License Amendment Request Thomas Weber Department Leader Nuclear Regulatory Affairs
RICT Timeline 2012 2013 2014 2015 2016+
10 License Amendment Drafted and Sent Out for Cross Organization Review -
1st Cut Benchmarking with Vogtle and Diablo Canyon LAR Submittal All PRA Peer Reviews Complete (Internal Events, Fire, Flood, Seismic)
Approval and Implementation LAR Final PVNGS Internal Review Fire and Seismic PRA Development
- Based on TSTF 505-A & NEI 06-09-A
- Scope includes components modeled in PRA
- 25 LCOs
- Mode 1 and 2 only
- New TS Section 5.5 Program
- Variances from TSTF 505 addressed in LAR and include:
- Miscellaneous variances described in LAR 11
TS 3.4.12, Pressurizer Vents
- Not in TSTF 505 or NUREG 1432
- In PV Safety Analysis
- Modeled in PRA
- RICT added to Two Required Actions
- Note added to preclude use of RICT when all pressurizer vent paths are intentionally made inoperable 12
Pressurizer Vent Paths 13 Reactor Drain Tank S
S S
S S
Pressurizer To Containment Atmosphere RCB-HV108 RCA-HV103 RCB-HV109 RCB-HV105 RCA-HV106
TS 3.7.3, Main Feedwater Isolation Valves (MFIVs)
- Not in TSTF 505 but is in NUREG 1432
- LAR adds restoration action
- MFIVs modeled in PRA
- RICT added to Two Required Actions 14
Miscellaneous Variances
- TS 3.7.2, Main Steam Isolation Valves (MSIVs)
- TS 3.7.4, Atmospheric Dump Valves (ADVs)
- Note added to preclude use of RICT when all ADV lines are intentionally made inoperable
- TS 3.7.9, Ultimate Heat Sink (UHS)
- Added new 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> restoration condition for UHS
- Note added to preclude use of RICT when the UHS is intentionally made inoperable
- TS 3.8.7, Inverters
- Revised note since PVNGS design has two inverters per train supporting 4 channels of vital instruments
- Note precludes use of RICT for two or more inverters intentionally made inoperable resulting in a loss of safety function 15
Summary
- Monitoring TSTF 505 Operating Experience
- Participating in Industry Committees
PRA Models Everett DePue Senior Engineer PRA Lead for TSTF-505
Summary of PRA Models
- PRA models developed and peer reviewed
- Internal events
- Internal flood
- Internal fire
- Seismic
- RG 1.200 Rev. 2 hazards screened and peer reviewed
- Total CDF/LERF meet RG 1.174 Rev. 2 limits
- Internal events and internal flood risk very low
- CDF/LERF dominated by internal fire and seismic hazards 18
Internal Events PRA
- Peer review by CEOG conducted in 1999
- Self-assessment performed against entire RA-Sa-2009 in 2015
- RA-Sa-2009 Supporting Requirements met to Capability Category II except:
- Some sub-elements of SY-C1, SY-C2 System Notebook Documentation need completion
- To be completed prior to RICT Program implementation 19
Internal Flood PRA
- Industry Peer Review conducted in 2010
- All ASME/ANS PRA requirements met to Capability Category II after peer review findings addressed 20
Internal Fire PRA
- Fire PRA complies with methods in NUREG/CR-6850
- Industry Peer Review conducted in 2012
- Follow-up Industry Peer Review conducted in 2014 - addressed 2012 findings
- All ASME/ANS requirements met to Capability Category II after peer review findings addressed 21
Seismic PRA
- Industry peer review conducted in 2013
- All ASME/ANS requirements met to Capability Category II after peer review findings addressed except
- SPR B7 Complementary Success Logic
- Meets Capability Category II for ASME/ANS RA-Sb-2013 22
Plant-Specific Modeling
- Real time risk model as currently used for existing Technical Specification CRMP OR
- Pre-solved solutions (STP approach)
- Common Cause treatment will be in accordance with NEI 06-09-A or Regulatory Guide 1.177 Rev. 1 23
Plant Modifications
- PRA models rely on installation of modifications or taking compensatory measures
- RICT Program will not be implemented until modifications complete or compensatory measures in place
Summary
- All hazards have been evaluated in accordance with RG 1.200 Rev. 2
- All PRA models peer reviewed
- Capability Category II met for all PRA models with three exceptions
- Total CDF/LERF meet RG 1.174 Rev. 2 25
Implementation Plan Bryan Thiele Department Leader Risk Informed Project Manager
Implementation Plan
- Engineering coordinate RICT implementation
- Cross organization team supporting implementation
- RICT implemented in Modes 1 and 2 only
- CRMP tool PRA Models will include Internal Events, Internal Flooding, Fire, and Seismic
- Extensive use of industry participation &
benchmarking to develop program, procedures, training 27
Procedures
- Revise 40DP-9RS01, Operations Department Online Nuclear Risk Management Mode 1 and 2, to include
- RICT
- Risk management action times
- Risk management action determinations
- PRA functionality
- New RICT Program Procedure 28
Training
- Licensed Operators
- Hands-on training on RICT calculations
- Classroom training to address how RICT impacts Station Operations
- Station Management
- Affected managers trained on process, expectations, limitations
- Multi-discipline management representatives attend annual MIT nuclear operational risk management (NORM) course
- Engineering
- Work Management 29
Communications
- Industry peers via TSTF-505 task force
- Site-wide communication
- Newsletter
- VP weekly video
- While submittal under review
- Once submittal is approved
- Leader Alignment Meetings
- Department All Hands Meetings 30
Modifications
- DC ammeter circuits
- Non-class 1E DC motor circuits
- Replace RCP control cables with fire rated cables
- Install new Steam Generator (SG) makeup pump that utilizes FLEX connections
- Breaker coordination on risk significant non-class 1E motor control centers/panels 31
Path Forward and Closing Comments Bryan Thiele Department Leader Risk Informed Project Manager
Path Forward
- Resolve Fire PRA peer review findings and complete documentation
- Submit LAR in June
- Finalize scope and install modifications
- Develop procedures, software and training in parallel with NRC review
- Implement in late 2016 33
34 We SAFELY and efficiently generate electricity for the long term