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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
3
y
What is a PRA/PSA?
– What can go wrong? (accident scenario)
4
– 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
7
• 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
8
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
9
– 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.
10
– 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)
11
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
12
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
13
• 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)
15
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
20
• 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
21
– 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
22
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
23
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
24
– 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
26
• 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
27
– 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
28
~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
29
– 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
30
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
31
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)
32
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
33
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
34
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
37
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
38
• 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
40
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
41
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
42
• 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
43
• 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
45
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
46
– 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
47
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
48
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
49
– 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
51
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
52
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
53
Overarching Philosophy
• The goal of a nuclear safety culture program is to be: –
Ongoing
– Holistic
54
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
55
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
56
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
57
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
58
– 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
59
• Design Certification Applicants – 10 CFR 52.47(a)(27) – FSAR must
contain a
description of the design-specific PRA and its lt
60
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
61
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
62
– 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
63
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
64
• 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
65
• 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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/ESP
<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>
/FRA
<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>
/ITA (Utilizzare queste impostazioni per creare documenti Adobe PDF
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
<FEFF005500740069006c0069007a006500200065007300730061007300200063006f006e00660069006700750072006100e700f50065007300200064006500200066006f0072006d00610020006100200063007200690061007200200064006f00630075006d0065006e0074006f0073002000410064006f00620065002000500044004600200061006400650071007500610064006f00730020007000610072006100200061002000760069007300750061006c0069007a006100e700e3006f002000650020006100200069006d0070007200650073007300e3006f00200063006f006e0066006900e1007600650069007300200064006500200064006f00630075006d0065006e0074006f007300200063006f006d0065007200630069006100690073002e0020004f007300200064006f00630075006d0065006e0074006f00730020005000440046002000630072006900610064006f007300200070006f00640065006d0020007300650072002000610062006500720074006f007300200063006f006d0020006f0020004100630072006f006200610074002000650020006f002000410064006f00620065002000520065006100640065007200200035002e0030002000650020007600650072007300f50065007300200070006f00730074006500720069006f007200650073002e>
/SUO
<FEFF004b00e40079007400e40020006e00e40069007400e4002000610073006500740075006b007300690061002c0020006b0075006e0020006c0075006f0074002000410064006f0062006500200050004400460020002d0064006f006b0075006d0065006e007400740065006a0061002c0020006a006f0074006b006100200073006f0070006900760061007400200079007200690074007900730061007300690061006b00690072006a006f006a0065006e0020006c0075006f00740065007400740061007600610061006e0020006e00e400790074007400e4006d0069007300650065006e0020006a0061002000740075006c006f007300740061006d0069007300650065006e002e0020004c0075006f0064007500740020005000440046002d0064006f006b0075006d0065006e00740069007400200076006f0069006400610061006e0020006100760061007400610020004100630072006f0062006100740069006c006c00610020006a0061002000410064006f00620065002000520065006100640065007200200035002e0030003a006c006c00610020006a006100200075007500640065006d006d0069006c006c0061002e>
/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