US-China PUNT (Peaceful Use of Nuclear Technology) Workshop on PSA - NRC Slides.ppt1
Terminology and Overview
• USA refers to
• Always associated with undesired event
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y
What is a PRA/PSA?
– What can go wrong? (accident scenario)
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– How likely is it to occur? (probability, frequency)
– What will be the outcome? (consequences)
• These three questions are commonly referred to as the risk triplet
3 Levels of PRA/PSA
PDS
Offsite Consequence Risk • Early Fatalities/year • Latent Cancers/year • Population Dose/year • Offsite Cost ($)/year
Plant Systems and Human Action Models (Fault Trees and Human Reliability Analyses)
Severe Accident Progression Analyses
Principle Steps in PRA/PSA
Why use Risk-Informed Approaches?
• Traditional analyses do not cover everything – Original nuclear plant analyses were
“deterministic” • Engineering judgment in determining accident categories
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• Reliance on worst case analyses, single failure criterion, defense-in-depth, and safety margins
• Analyses performed separately by various disciplines
– WASH-1400 (1975) assessed reactor risk • Revealed actual risk significant areas and interactions that
were very different from the design basis events
Specific Strengths of PRA/PSA
D l lit ti d i i i ht
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making • Provides a structure for sensitivity studies • Explicitly highlights and treats principal sources
of uncertainty
• “Use of Probabilistic Risk Assessment Methods in Nuclear Regulatory Activities,” August 16, 1995 – Increase use of PRA technology in all regulatory matters to the
extent supported by the state-of-the-art in PRA methods and data and in a way that complements the deterministic approach and supports the traditional defense-in-depth philosophy U PRA h ti l ithi th b d f th t t f th
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– Use PRA, where practical within the bounds of the state-of-the- art, to reduce unnecessary conservatism in current regulatory requirements, regulatory guides, license commitments, and staff positions and to support proposals for additional regulatory requirements in accordance with 10 CFR 50.109 (Backfit Rule)
– PRAs used in regulatory decisions should be as realistic as practicable and supporting data should be publicly available
– Safety goals and subsidiary numerical objectives are to used with appropriate consideration of uncertainties in making regulatory judgments on the need for new generic requirements
General Objective of Risk- Informed Decisionmaking
• Insights derived from probabilistic risk assessments are used in combination with traditional engineering analyses to focus licensee and regulatory attention on issues commensurate with their importance to safety.
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– Make more efficient use of Staff resources
– Reduce unnecessary regulatory burden on industry
Regulations that Incorporate Risk-Informed Approaches
• 10 CFR 50.44 Combustible gas control • 10 CFR 50.48(c) Fire protection • 10 CFR 50.62 Anticipated transient
without scram (ATWS)
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without scram (ATWS) • 10 CFR 50.63 Station blackout • 10 CFR 50.65 Maintenance rule • 10 CFR 50.69 Special treatment
requirements • 10 CFR 52 New reactor licensing
Risk-Informed Regulatory Guidance
• PRA Technical Adequacy – Regulatory Guide (RG) 1.200, Standard Review Plan (SRP) 19.1
• Risk-Informed Changes – General Guidance – RG 1.174, SRP 19.2
• Risk-Informed Inservice Inspection (ISI) (piping) – RG 1.178, SRP 3.9.8
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times, surveillance frequencies) – RG 1.177, SRP 16.1
• Risk-Informed Fire Protection – RG 1.205, SRP 9.5.1.2
• Risk-Informed Special Treatment Requirements – RG 1.201
• New Reactor Licensing – RG 1.206, SRP 19.0
Why not be Risk-Based?
• “Risk-based” would mean we decide using only the numerical results of a risk assessment
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• Risk is not measured, it is evaluated using analytical models
• We do not know everything, and therefore our models are incomplete
Specific Weaknesses of PRA/PSA
• Inadequacy of available data • Limited understanding of physical phenomena • High sensitivity of results to assumptions • Constraints on modeling effort (limited resources)
– Simplifying assumptions
– Simplifying assumptions – Truncation of results during quantification
• PRA is a snapshot in time – Plant changes (hardware, procedures and operating practices)
over time (“living” PRA) – Temporary system configuration changes (e.g., out of service
for maintenance
• Lack of completeness – Human errors of commission typically not considered
Balanced Approach to Risk-Informed Decisionmaking
• 5 Principles for Risk-Informed Decisionmaking for License Amendments – Meets current regulations (presumption of adequate
protection)
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p ) – Is consistent with the defense-in-depth philosophy – Maintains sufficient safety margins – Results in an increase in CDF or risk that is small
and consistent with the intent of the Commission’s Safety Goal Policy Statement
– Will be monitored using performance measurement strategies
Principle Elements of Risk- Informed Decisionmaking
Traditional Analysis PRA
PSA Roles and Responsibilities
Topics
– PSA Responsibilities
• Safety Goal Policy Statement
• Generic Letter 88-20 (IPE/IPEEE)
• Issued in 1975 (started in 1972) • Purpose/Objective:
– Realistic estimate of the public risks from potential accidents in commercial nuclear power plants
– Compare nuclear plant risks to other non-nuclear
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• Results showed risk to public are comparatively small
• Then came the 1979 event at Three Mile Island, Unit 2 – Identified in WASH-1400 as one of the more likely
accident scenarios
• Issued in 1986
Addressed risks to public from nuclear power plant
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– Addressed risks to public from nuclear power plant operations with the objective of establishing goals that broadly define an acceptable level of radiological risk that might be imposed on the public as a result of nuclear power plant operation
– Commission approved use of qualitative safety goals, including use of the quantitative health effects objectives, in the regulatory decisionmaking process
NRC Safety Goals Qualitative Objectives
• Established 2 qualitative objectives:
– Individual members of the public should be provided a level of protection from the consequences of nuclear power plant operation such that individuals bear no
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power plant operation such that individuals bear no significant additional risk to life and health
– Societal risks to life and health from nuclear power plant operation should be comparable to or less than the risks of generating electricity by viable competing technologies and should not be a significant addition to other societal risks
NRC Safety Goals Quantitative Objectives
• Established 2 quantitative objectives for determining achievement of the qualitative safety goals:
– Risk of prompt fatality to an average individual in vicinity of a nuclear power plant that might result from
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vicinity of a nuclear power plant that might result from reactor accidents should not exceed 1/10 of 1% of the sum of prompt fatality risks from other accidents the population is generally exposed
– Risk of cancer fatalities to population in area near a nuclear power plant that might result from operation should not exceed 1/10 of 1% of sum of cancer fatality risks from other causes
Subsidiary Quantitative Objectives
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– Large early release frequency (LERF) < 1 x 10-5/year
GL 88-20 Guidance Timeline
• 1988 GL 88-20 issued requesting IPEs • 1989 GL 88-20 Supplement 1
– Availability of NUREG-1335 – IPE Submittal Guidance
• 1990 GL 88-20 Supplement 2 – List of severe accident management strategies to consider in
IPE (NUREG/CR-5474)
IPE (NUREG/CR 5474)
• 1990 GL 88-20 Supplement 3 – Announced completion of NRC Containment Performance
Improvement (CPI) program
• 1991 GL 88-20 Supplement 4 – IPE for External Events (IPEEE)
• 1995 GL 88-20 Supplement 5 – Modified recommended scope of seismic analysis to include
revised seismic hazard curves (NUREG/CR-1488, LLNL)
GL 88-20 Purpose
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• Develop understanding of what could possibly go wrong in a plant
• Identify and evaluate means for improving plant and containment performance with respect to severe accidents
• Decide which of these improvements to implement and when
GL 88-20 Did Not Require a PRA
• All utilities chose to perform a PRA – PRAs not performed to specified standard – No requirements specified for data or models
• Not all utilities used PRAs for external events
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– Earthquakes and fires could be analyzed via margins approach
• IPE submittal typically not a full PRA – Level of detail varies widely – only full-power operation considered
• IPEs not performed to support risk-informed, performance-based regulation
GL 88-20 Outcome
• Few licensee explicitly identified vulnerabilities – 4 BWRs and 15 PWRs
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~45% procedural/operational
~40% design/hardware
some both
NRC PRA Policy Statement
• Issued in 1995 • Statement
– Increase use of PRA technology in all regulatory matters to the extent supported by the state-of-the-art in PRA methods and data and in a way that complements the deterministic approach and supports the traditional defense-in-depth philosophy U PRA h ti l ithi th b d f th t t f th
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– Use PRA, where practical within the bounds of the state-of-the- art, to reduce unnecessary conservatism in current regulatory requirements, regulatory guides, license commitments, and staff positions and to support proposals for additional regulatory requirements in accordance with 10 CFR 50.109 (Backfit Rule)
– PRAs used in regulatory decisions should be as realistic as practicable and supporting data should be publicly available
– Safety goals and subsidiary numerical objectives are to used with appropriate consideration of uncertainties in making regulatory judgments on the need for new generic requirements
Risk Insights are used in All Work Areas
Regulations and Guidance
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Support for Decisions Research Activities Advisory Activities Adjudication
Licensing and Certification
Risk-Informed Regulatory Guidance
• PRA Technical Adequacy – Regulatory Guide (RG) 1.200, Standard Review Plan (SRP) 19.1
• Risk-Informed Changes – General Guidance – RG 1.174, SRP 19.2
• Risk-Informed Inservice Inspection (ISI) (piping) – RG 1.178, SRP 3.9.8
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times, surveillance frequencies) – RG 1.177, SRP 16.1
• Risk-Informed Fire Protection – RG 1.205, SRP 9.5.1.2
• Risk-Informed Special Treatment Requirements – RG 1.201
• New Reactor Licensing – RG 1.206, SRP 19.0
Regulations that Incorporate Risk-Informed Approaches
• 10 CFR 50.44 Combustible gas control • 10 CFR 50.48(c) Fire protection • 10 CFR 50.62 Anticipated transient
without scram (ATWS)
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without scram (ATWS) • 10 CFR 50.63 Station blackout • 10 CFR 50.65 Maintenance rule • 10 CFR 50.69 Special treatment
requirements • 10 CFR 52 New reactor licensing
Risk-Informed Licensing and Certification
• For New Reactors, there are specific regulatory requirements to develop and maintain PRAs
10 CFR 52.47(a)(27) Design Certifications
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Risk-Informed New Reactor Operations
• Combined License Holders – 10 CFR 50.71(h)(1) - No later than the scheduled date
of initial fuel loading, must develop Level 1 and Level 2 PSA covering those initiating events and modes for which NRC-endorsed consensus PSA standards exist
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which NRC endorsed consensus PSA standards exist 1 year prior to initial fuel loading
– 10 CFR 50.71(h)(2) – Must maintain and upgrade PSA to cover initiating events and modes for which NRC- endorsed consensus PSA standards exist 1 year prior to upgrade and must upgrade PSA every 4 years
– 10 CFR 50.71(h)(3) – When applying for renewed license, must upgrade PSA to cover all initiating events and modes
Risk-Informed Oversight
• Mitigating Systems Performance Index (MSPI)
– http://www.nrc.gov/NRR/ OVERSIGHT/ASSESS/mspi.html
inspection findings • Inspection Manual Chapter (MC) 0609
and appendices
(NOED) • MC 9900 Technical Guidance
Risk-Informed Operating Experience
8.3
– Accident Sequence Precursor (ASP) program
PSA Responsibilities of Current Licensees
• For current operating plants, there are no regulatory requirements to develop and maintain PSAs
• Many applications are possible or enhanced by
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Many applications are possible or enhanced by using PSAs; thus nearly all plants have an Internal Events PSA and many are developing Fire PSAs to support other applications
• All licensee Internal Events PSAs have been peer reviewed
• Licensees develop and maintain their PSAs
PSA Responsibilities of Regulator
• Ensure that licensee submittals are identified and processed in accordance with risk-informed guidance
• Identify current requirements that could be significantly enhanced with a risk-informed and/or performance- based approach
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• Ensure objectives of risk-informed regulation are met – Enhanced safety decisions – Efficient use of NRC resources – Reduced unnecessary regulatory burden on industry
• Ensure adequate staff training on use of risk-informed guidance and underlying PSA technical disciplines
• Maintain current levels of safety
PSA Standards and Guidelines
PRA Standards Versus PRA Guidance
• PRA Standard addresses the technical adequacy of the elements of a PRA
• PRA Guidance describe how to develop or perform the elements of a PRA – Data Handbook
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Data Handbook – HRA Good Practices – Fire PRA Methods – Uncertainty Guidance
• Regulatory Guide (RG) 1.200 endorses, with exceptions and clarifications, the ASME/ANS PRA Standards and associated industry peer review guidance
PRA Infrastructure
RG 1.174RG 1.174RG 1.174 RG 1.201 RG 1.205 RG 1.206
10 CFR 50.90 License Amendment
10 CFR 50.69 Special Treatment
10 CFR 50.48(c) NFPA 805
10 CFR Part 52 New Reactors
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RG 1.200
Objective of PRA Standard
• Establishes the technical requirements for a base PRA for a specific application
• Establishes a process for determining the needed scope, level of detail, plant specificity, and realism of base PRA for a specific application
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• Establishes the requirements for a PRA configuration control process to ensure that the base PRA represents the as-built and as-operated plant
• Establishes the requirements for a peer review addressing the review process, team qualifications, and documentation
Why Use a PRA Standard?
• Acceptability
• Consistency
To ensure the PRA insights and results are sufficiently adequate to be used in decisionmaking
To provide consistent understanding regarding the development of a PRA model
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• Transparency
• Cost-Effectiveness
model
To enable independent understanding of the PRA model and its results
To encourage risk-informed decisionmaking to enhance regulatory and licensee processes and practices
Goal of PSA Standards, Peer Review, and RG 1.200
Peer reviews
technical guidance Endorsed
guidance
Benefits of Meeting the PRA Standard
• Confidence in the PRA can increase its use in design and operational decisions
• Obviates the need for an in-depth review
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of the base PRA by the NRC reviewers – NRC focuses on the licensee’s resolution of
peer review findings as they impact the specific application and on the risk impacts of the specific application
Current Scope of PRA Standard
• Reactor Type – Estimates the risk for Light Water Reactors (LWRs)
• Plant Stage – Estimates the risk for Operating Plants
• Plant Risk E l t th i k f th t
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– Evaluates the risk from the reactor core – Estimates CDF and LERF
• Plant Challenges – Evaluates the risk from internal and external hazards
• Plant Operating Modes – Evaluates the risk from at-power conditions
PRA Standard Contents
The requirements are specific to the hazard under consideration
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hazard
Risk-Informed Application Process
Determine the PRA scope, level of detail, plant specificity and realism needed to support the application
Determine whether the scope of the existing PRA model is adequate to support the decision
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Determine if the PRA Standard is adequate to support the decision
Determine if the existing PRA model satisfies the application portions of the Standard
Update PRA and supplement Standard, as needed
PRA Standard Technical Requirements
• Hazard Groups – Specifies the different plant challenges for which risk is
estimated • Technical Elements
– Determines the minimum technical analyses that need to be performed in evaluating each hazard
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– Describes the goals of each technical element • High Level Requirements
– Sets forth the minimum requirements to achieve the objective of each technical element
• Supporting Requirements – Specifies the minimum technical requirements that are
needed to meet the associated high level requirement
PRA Standards Technical Supporting Requirements
Capability Category I minimum addressed by
the technical requirement
Supporting Requirement
Level of detail of plant model
Plant design and operational
minimum to achieve “current good practice” for the technical requirement
Capability Category III minimum to achieve the state-of-the-art for the technical requirement
with regard to level of detail, plant design and operational specificity, and realism of plant
response
Review Process Requirements
Review Frequency Requirements
A written process that defines the objective and purpose and provides the review approach
Only a single complete peer review is necessary prior to using a PRA unless the PRA is upgraded
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Sufficient documentation to demonstrate that the review process appropriately implemented the review requirements, and documentation of the peer review results
The reviewer to determine the specific scope and depth of the review of each PRA element
Personnel with the expertise to assess all PRA Elements and have the collective knowledge of the plant design and operation
Status of PRA Standards
• Level 1 CDF/LERF (ASME/ANS RA-Sa-2009) for at-power – Internal and external hazards, operating LWRs – Published and endorsed
• Level 1 CDF/LERF (ASME/ANS RA-Sa-2009) for low power/shutdown – In consensus process – Does not address internal fire
• Level 1 CDF/LERF (ASME/ANS RA-Sa-2009) for new reactors
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Level 1 CDF/LERF (ASME/ANS RA Sa 2009) for new reactors – Preliminary draft
• Level 2 (ANS/ASME 58.xx) for operating and new reactors – Does not address low power/shutdown – Preliminary draft complete, ready to start consensus process
• Level 3 (ANS/ASME 58.xx) for operating and new reactors – All hazards and all plant conditions – Preliminary draft, ready to start consensus process
PSA and Nuclear Safety Culture
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Overarching Philosophy
• The goal of a nuclear safety culture program is to be: – Ongoing
– Holistic
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Holistic
– Objective
– Transparent
– Safety-focused
– Using all information available to: • Provide early indication of potential problems
• Develop effective corrective actions
Aspects of Nuclear Safety Culture
• Nuclear Safety Culture Programs need to include: – Decisionmaking – Resources – Work control and work practices – Accountability
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corrective actions – Employee concerns programs
• Environment for Raising Concerns • Preventing, Detecting, and Mitigating Perception of Retaliation
Safety Culture Is Important to All Staff
• It is important for all staff to keep the right focus on the agency’s mission, for which all play an important and unique role in supporting
• Diverse views are encouraged throughout the agency
• Each employee has specific expertise and unique experiences that
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Each employee has specific expertise and unique experiences that allows for a range of valuable perspectives that: – are necessary to support effective and fully informed decisionmaking – should be provided early in the decisionmaking process, when possible,
so that they can be fully considered throughout the process – should be considered and responded to respectfully, by all levels
(managers, supervisors, peers, etc.)
• Raising and responding to diverse views can be challenging in some situations. Doing so requires time, effort, and continuous ongoing focus, but the value brought to the end result is worth the effort.
Risk Insights are used in All Work Areas
Regulations and Guidance
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Support for Decisions Research Activities Advisory Activities Adjudication
Licensing and Certification
• PRA is a valuable tool for gaining insights
• The goal of using PRAs/PSAs is to make good safety decisions – It is not the bottom line risk number produced by the
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– It is not the bottom line risk number produced by the PRA that is often the most useful result
– It is the structured assessment process that provides insights into the relative strengths and weaknesses of the design or operational practices
• PRA is a tool that can support a nuclear safety culture program
Role of PSA for New Nuclear Power Plants
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• Design Certification Applicants – 10 CFR 52.47(a)(27) – FSAR must contain a
description of the design-specific PRA and its lt
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results
• Combined License Applicants – 10 CFR 52.79(a)(46) – FSAR must contain a
description of the plant-specific PRA and its results
PRA Requirements for New Power Reactors
• Combined License Holders – 10 CFR 50.71(h)(1) – No later than the scheduled date
of initial fuel loading, must develop Level 1 and Level 2 PRA covering those initiating events and modes for which NRC-endorsed consensus PRA Standards exist
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which NRC endorsed consensus PRA Standards exist 1 year prior to initial fuel loading
– 10 CFR 50.71(h)(2) – Must maintain and upgrade PRA to cover initiating events and modes for which NRC- endorsed consensus PRA standards exist 1 year prior to upgrade and must upgrade PRA every 4 years
– 10 CFR 50.71(h)(3) – When applying for renewed license, must upgrade PRA to cover all initiating events and modes
PRA Submittal Guidance for New Power Reactors
• Regulatory Guide (RG) 1.206, Section C.I.19 – Guidance for applicant regarding information to
provide in Final Safety Analysis Report (FSAR), Chapter 19
– Addresses design-specific PRA for design certification or plant specific PRA for combined
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– Addresses deterministic evaluation of severe accident mitigation design alternatives (SAMDAs)
– Information is to enable NRC to determine acceptability of risks of proposed new plant
– Appendix A (C.I.19-A) provides Standard Format and Content of FSAR Chapter 19
PRA Review Guidance for New Power Reactors
• Standard Review Plan (SRP) Section 19.0 – Guidance on the review of the PRA
information to support design certification and bi d li li ti i
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combined license application reviews
– Appendix A provides Final Safety Evaluation Report (FSER) Input Format and Content
Risk Metrics for New Reactors
• Core Damage Frequency < 1 x10-4/year
• Large Release Frequency < 1 x 10-6/year
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• Containment Performance Goals – Containment integrity maintained for 24 hours
following onset of core damage for more likely severe accident challenges
– Conditional Containment Failure Probability < 0.1
Key PRA-Related Aspects of FSAR Chapter 19
• Description of PRA and results • Uses and applications of the PRA in each phase • Quality of PRA
– Scope, Level of Detail, Technical Adequacy, PRA Maintenance and Upgrade Program
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• Special design/operational features intended to improve plant safety
• Safety insights from internal and external events PRA for at-power operations
• Safety insights from PRA for other modes of operation (e.g., low power and shutdown)
• PRA-related inputs to other programs and processes – Maintenance Rule, Reactor Oversight, Reliability Assurance, etc.
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adatti per visualizzare e stampare documenti aziendali in modo affidabile. I documenti PDF creati possono essere aperti con Acrobat e Adobe Reader 5.0 e versioni successive.) /JPN <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> /KOR <FEFFc7740020c124c815c7440020c0acc6a9d558c5ec0020be44c988b2c8c2a40020bb38c11cb97c0020c548c815c801c73cb85c0020bcf4ace00020c778c1c4d558b2940020b3700020ac00c7a50020c801d569d55c002000410064006f0062006500200050004400460020bb38c11cb97c0020c791c131d569b2c8b2e4002e0020c774b807ac8c0020c791c131b41c00200050004400460020bb38c11cb2940020004100630072006f0062006100740020bc0f002000410064006f00620065002000520065006100640065007200200035002e00300020c774c0c1c5d0c11c0020c5f40020c2180020c788c2b5b2c8b2e4002e> /NLD (Gebruik deze instellingen om Adobe PDF-documenten te maken waarmee zakelijke documenten betrouwbaar kunnen worden weergegeven en afgedrukt. De gemaakte PDF-documenten kunnen worden geopend met Acrobat en Adobe Reader 5.0 en hoger.) /NOR <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> /PTB <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> /SUO <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> /SVE <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> /ENU (Use these settings to create Adobe PDF documents suitable for reliable viewing and printing of business documents. Created PDF documents can be opened with Acrobat and Adobe Reader 5.0 and later.) >> >> setdistillerparams << /HWResolution [300 300] /PageSize [612.000 792.000] >> setpagedevice