ML15070A252
ML15070A252 | |
Person / Time | |
---|---|
Site: | Palo Verde ![]() |
Issue date: | 02/18/2015 |
From: | Edington R K Arizona Public Service Co |
To: | Watford M M Plant Licensing Branch IV |
Singal B K | |
References | |
Download: ML15070A252 (34) | |
Text
Palo Verde/NRC Pre-submittal MeetingRisk Informed Completion TimesFebruary 18, 2015 IntroductionsBryan ThieleDepartment LeaderRisk Informed Project Manager Agenda*Introduction Bryan Thiele
- Palo Verde OverviewThomas Romay
- License Amendment Thomas Weber
- PRA Summary Everett DePue
- Implementation Plan Bryan Thiele
- Path Forward and Closing CommentsBryan 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 OverviewTom Romay Shift ManagerSenior 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 RequestThomas WeberDepartment LeaderNuclear Regulatory Affairs RICT Timeline 2012 2013 2014 2015 2016+10License Amendment Drafted and Sent Out for Cross Organization Review -
1 st CutBenchmarking with Vogtleand Diablo CanyonLAR SubmittalAll PRA Peer Reviews Complete (Internal Events, Fire, Flood, Seismic)Approval and ImplementationLAR Final PVNGS Internal ReviewFire and Seismic PRA Development PVNGS LAR Content
- 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:*RICT added to two LCOs not in TSTF 505
- 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-HV105RCA-HV106 TS 3.7.3, Main FeedwaterIsolation 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 *LAR to remove "Second Completion Time" (TSTF 439) in progress
- Monitoring TSTF 505 Operating Experience
- Participating in Industry Committees
- Monitoring TSTF 505 RAIs 16 PRA ModelsEverett DePueSenior EngineerPRA 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
- 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
- PVNGS is not NFPA-805 plant, -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
- RICT CRMP model will be either:
-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
- FLEX strategies not yet reflected in the PRA models -conservatism 24 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 PlanBryan Thiele Department LeaderRisk 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
capability
-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 CommentsBryan ThieleDepartment LeaderRisk 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 34We SAFELY and efficientlygenerate electricity for the long term