prairie island nuclear generating plant, units 1 and 2 ... · – install ovation dcs: • fw...
TRANSCRIPT
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Non-Safety Related Digital Feedwaterand AMSAC/DSS Control Systems
Replacement Project
Xcel EnergyPrairie Island Nuclear Generating Plant
8-30-2017
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Agenda
• Introductions
• Meeting Purpose
• Project Overview
• 10 CFR 50.59 Assessment
• Future Actions
• Summary
• Feedback and Questions
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Meeting Purpose
• Outline project scope, design, and licensing basis supporting the digital FW and AMSAC/DSS control system change
• Discuss the preliminary 10 CFR 50.59 assessments and conclusions
• Discuss possible future interaction with the NRC staff
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Project Overview
• Current System– Westinghouse WDPF System
• Digital Technology• Installed WDPF FWCS and AMSAC in 1989/1990• Modified AMSAC and installed DSS Feature in 1998/1999• Non-Safety Related Distributed Control System (DCS)
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Project Overview
• Project Drivers– Obsolescence
• WDPF Systems are 28 years old– Parts not manufactured since 2002 – Vendor technical support ends in 2017
• Recent Hardware Issues• Current system not suitable for plant life
– Unit 1 operation to 2033 – Unit 2 operation to 2034
– Long term operating and maintenance strategy• Common platform with demonstrated history of reliable operation
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Project Overview
• Timeline– 2015-2016: Preliminary Engineering Phase
• Multidiscipline team • Many team members from original WDPF team
– 2017: 10 CFR 50.59 Assessment Phase– 2018: Detailed Design Phase– 2019–2020: Installation Phase
• In service dates:– Unit 2 – 2019– Unit 1 - 2020
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Project Overview
• Project Scope– Replace existing DCS
• Digital to digital - Ovation• WDPF to Ovation
– Next generation of platform– Same OEM
– Upgrade FW Reg Valve Controls• Analog to digital - DVC
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Project Overview
• Project Design Principles– Mitigate obsolescence– Improve equipment reliability – Eliminate SPVs and transient initiators– Use well vetted, common platform with demonstrated
history– Design system hardware and software within the bounds
of current design and licensing basis – Use industry standard methods for design and testing– Use a multi-layer testing approach through fabrication,
installation, and commissioning – Design, test, and install system to minimize outage
impact
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Project Overview
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Project Overview
• Project Scope Detail– Install Ovation DCS:
• FW Control System (SGWLC)• AMSAC/DSS System• Control System Infrastructure
– Modify Main Control Board Operator Interface:• Retain operator manual controls• Move some indications to new graphic display
– Modify FW Control Valve field devices:• Replace FW Reg valve controls with dual redundant digital
positioners on Main Control Valves and single digital positioner on Bypass Control Valves
– Modify Simulator
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Project Overview
• Project Scope Detail (cont’d)– Improve Equipment Reliability
• Increase redundancy • Eliminate at least 16 SPVs (8 per unit)
– Functional Control Enhancements• Reduce operator burden• More fault tolerant• Improve FW Control strategies• Improve time response
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10 CFR 50.59 Assessment
• FW Design & Licensing Basis• AMSAC/DSS Design & Licensing Basis• Assessment Approach• Qualitative Assessment• 10 CFR 50.59 Criteria• Preliminary 10 CFR 50.59 Overall Conclusion
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10 CFR 50.59 Assessment
• FW Design & Licensing Basis– USAR described FWCS & Control Valve Design
Functions:• Provide FW flow to SGs for RCS heat removal during normal
operation • Provide SG Program Level Control during normal operation• Prevent control and protection interaction with Median Signal
Select (MSS) for NR SG level• Valves provide isolation of FW flow to SGs
– Licensing• Steam Flow/FW Flow mismatch trip elimination
– USAR described Failures and Accident Analysis
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• AMSAC/DSS Design & Licensing Basis– Design Function: Satisfy 10 CFR 50.62
• AMSAC Actuation: Turbine Trip and AFW actuation• DSS Actuation: Remove power to the control rods
– Licensing• Installed WDPF AMSAC to meet requirements of 10 CFR 50.62• Modified AMSAC logic and added DSS feature
– USAR described Failures and Accident Analysis
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10 CFR 50.59 Assessment
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10 CFR 50.59 Assessment
• Assessment Approach– Use current regulatory requirements & guidance
• NEI 96-07, Rev 1, endorsed by NRC RG 1.187• NEI 01-01 (including Appendix A) endorsed by NRC RIS 2002-22• NRC IN 2010-10
– Monitoring ongoing NEI/NRC efforts– 10 CFR 50.59 screening considerations (NEI 01-01
Section 4.3):• Software considerations• Functional segmentation• Time response• Human System Interface• Safety to Non-Safety Interface
– NEI 01-01 drives conservative conclusion to “screen in”
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10 CFR 50.59 Assessment
• Assessment Approach (cont’d)– 10 CFR 50.59 Evaluation Considerations (NEI 01-01
Section 4.4)• Same as screening considerations• Qualitative Assessment is key to addressing Criterion 1, 2, 5,
and 6 of 10 CFR 50.59
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10 CFR 50.59 Assessment
• Assessment Approach (cont’d)– NEI 01-01, Section 5.3.1, “Factors that Affect
Dependability”• The ability to provide reasonable assurance that an upgrade will
exhibit sufficient dependability is a key element of 10 CFR 50.59 evaluations
– Qualitative Assessment characteristics:• System design features• System design development and quality processes • Operating history
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10 CFR 50.59 Assessment
• Qualitative Assessment – Design Features– Design Features to support low likelihood of failure
(examples):• Isolation Devices• Redundancy• Architectural assignments• Segmentation• Self Diagnostics• Failure states• Existing Manual Controls
– Susceptibility Analysis • Hardware Failures• Environmental• Design Defects • Operator or Maintenance Errors
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10 CFR 50.59 Assessment
• Qualitative Assessment – Design Development and Quality Processes
– Design specification provides requirements for design, fabrication, documentation, testing, and delivery
– Specification and Westinghouse design development processes based upon industry standards
– Specification requires multi-layer testing approach through fabrication, installation, and commissioning
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10 CFR 50.59 Assessment
• Qualitative Assessment – Operating History– Ovation Experience
• More than 100 Ovation nuclear systems deployed• Variety of nuclear applications worldwide• Greater than 500 Rx years of OE
– Fisher DVC Experience• Over 700,000 sold• Over 7 years
– OE Research
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10 CFR 50.59 Assessment
• Qualitative Assessment Preliminary Conclusions– Will demonstrate dependability and low likelihood of
failure:• Required design features maintained and no new failure results• Design development and quality processes being applied• Operating history is strong
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10 CFR 50.59 Assessment
• 10 CFR 50.59 Criteria– Expected 10 CFR 50.59 Criteria 1, 2, 5, and 6
conclusions based on preliminary Qualitative Assessment and preliminary design work:• No more than a minimal increase in frequency of an accident• No more than a minimal increase in likelihood of malfunction • No possibility of an accident of a different type• No possibility of a malfunction with a different result
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10 CFR 50.59 Assessment
• 10 CFR 50.59 Criteria (cont’d)– Other 10 CFR 50.59 Criteria:
• Criteria 3 & 4: – Systems do not initiate new failures or malfunctions– Radiological consequences are not evaluated for these events
• Criterion 7: – Systems do not impact any critical inputs credited in the Safety
Analysis for fission product barriers– Change will not exceed or alter a fission product barrier design
basis limit• Criterion 8:
– Change does not constitute, involve or modify a method of evaluation described in the USAR
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10 CFR 50.59 Assessment
• Preliminary 10 CFR 50.59 Overall Conclusion– Screens in for evaluation– Would not require prior NRC approval– Perform change under 10 CFR 50.59
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Future Actions
• Xcel Next Steps– Proceed with detailed design– 10 CFR 50.59 evaluation sufficiently complete in 3rd
Quarter 2018– Opportunity for additional learning with new guidance– Timing to accommodate project installation
• Unit 2 - 2019• Unit 1 - 2020
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Summary
• Described the project scope, design, and licensing basis supporting the digital FW and AMSAC/DSScontrol system change
• Discussed the preliminary 10 CFR 50.59 assessment and conclusions
• Outlined next steps and possible future interaction with the NRC staff
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Feedback and Questions
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?
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Acronyms
• AFW – Auxiliary Feedwater• AMSAC – ATWS Mitigating System Actuation Circuitry• AOO – Anticipated Operational Occurrences• ATWS – Anticipated Transient Without SCRAM• BFRV – Bypass Feedwater Regulating Valve• CCF – Common Cause Failure • CFR - Code of Federal Regulations• CR – Control Room• DCS – Distributed Control System• DSS – Diverse Scram System• DVC – Digital Valve Controller• FW – Feedwater
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Acronyms
• FWCS – Feedwater Control System• HSI - Human System Interface• IN – Information Notice• I/O – Input/Output• I/P – Current to Pressure Converter• LVDT – Linear Variable Differential Transformer• MFRV – Main FW Regulating Valve• M/A - Manual/Automatic Control Station• M/L – Manual Loading Station• M/P – Motor to Pressure Converter• MSS - Median Signal Select • NEI – Nuclear Energy Institute
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Acronyms
• NR – Narrow Range• NRC – Nuclear Regulatory Commission• NRR – Nuclear Reactor Regulation (Office of) • OE – Operating Experience• OEM – Original Equipment Manufacturer• P/I – Pressure to Current Converter• RCP – Reactor Coolant Pump• RCS – Reactor Coolant System• RG – Regulatory Guide• RIS – Regulatory Issue Summary• Rx - Reactor• SF/FF – Steam Flow/Feedwater Flow
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Acronyms
• SG – Steam Generator• SGWLC – Steam Generator Water Level Control• SLIM – Small Loop Interface Module• SME – Subject Matter Expert• SPV – Single Point Vulnerability• SWIL – Software In Loop• USAR – Updated Safety Analysis Report• WDPF – Westinghouse Distributed Processing Family• WR – Wide Range
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