Licensing steps and documents to be reviewed in each

Report
Licensing and safety assessment of a new
NPP’s design - steps and documents to be
reviewed in each step
VN/RA/01 Task 1&2 Workshop
Hanoi, October 2012
Confidential
Ilari Aro
Ref. to Janne Nevalainen
STUK
SÄTEILYTURVAKESKUS • STRÅLSÄKERHETSCENTRALEN
RADIATION AND NUCLEAR SAFETY AUTHORITY
I.Aro,
October
2012
1
Outline
• Licensing steps and processes in Finland
–
–
–
–
–
•
•
•
•
environmental impact assessment
feasibility studies and preliminary safety assessment
Decision-in-principle
construction license
operating license
Documents to be reviewed in each step
Requirements for the documentation
Goals of the (document) review
Conclusions
SÄTEILYTURVAKESKUS • STRÅLSÄKERHETSCENTRALEN
RADIATION AND NUCLEAR SAFETY AUTHORITY
I.Aro, October 2012
2
Licensing steps
SÄTEILYTURVAKESKUS • STRÅLSÄKERHETSCENTRALEN
RADIATION AND NUCLEAR SAFETY AUTHORITY
I.Aro,
October
2012
3
NPP licensing steps in Finland (three step licensing)
•
•
•
•
environmental impact assessment (EIA)
decision in principle (DiP)
construction license (CL)
operating license (OLA)
Operating License
Construction
Construction License
Bidding & site preparation
technical stage
political stage
Decision in Principle
Feasibility studies
Environmental impact assessment
SÄTEILYTURVAKESKUS • STRÅLSÄKERHETSCENTRALEN
RADIATION AND NUCLEAR SAFETY AUTHORITY
I.Aro, October 2012
4
Regulatory review of the design is conducted in several phases – in
gradually increasing depths in each step
1.
2.
3.
4.
5.
6.
Enviromental Impact Assessment: NPP site safety issues which are in general level
presented in EIA programme and report.
Feasibility Studies: Design topics chosen mainly by the license applicant - identification of
possible “show stoppers” in licensing point of view (plant lay-out, air craft crash protection,
design basis accidents and application of redundancy, diversity and separation principles,
I&C design, SAM)
Decision in Principle: Basic design requirements and main safety features of each proposed
alternative design, selected NPP sites and licensees organisation are reviewed before STUK
presents its preliminary safety assessment
Construction License: Design criteria and conceptual design of the plant, safety relevant
systems and systems integration are reviewed before STUK presents safety assessment –
this includes both deterministic safety analysis and Probabilistic Risk Assessment (PRA)
During construction: Detailed design review of systems, structures and components is
conducted during construction – along progress of the design work.
Operation License: Final technical documentation including modifications made during
construction and commissioning, management system for operation
SÄTEILYTURVAKESKUS • STRÅLSÄKERHETSCENTRALEN
RADIATION AND NUCLEAR SAFETY AUTHORITY
I.Aro, October 2012
5
Licensing processes with main stakeholders
SÄTEILYTURVAKESKUS • STRÅLSÄKERHETSCENTRALEN
RADIATION AND NUCLEAR SAFETY AUTHORITY
I.Aro,
October
2012
6
Environmental Impact Assessment
Ministry of Employment and the Economy (MEE) is the liaison authority in the EIA process
Utility
Issues EIA
Programme
Updates
Programme
Issues an
EIA report
EIA
Completed
MEE
Asks
statements on
the
Programme
Issues
Statement on
Programme
Submits EIA
for Statement
Issues Final
Statement
on EIA
STUK
Statement on
Programme
Statement
on EIA
Municipalities
Statements on
Programme
Statements
on EIA
Authorities
Statements on
Programme
Statements
on EIA
Public
Statements on
Programme
Statements
on EIA
SÄTEILYTURVAKESKUS • STRÅLSÄKERHETSCENTRALEN
RADIATION AND NUCLEAR SAFETY AUTHORITY
I.Aro, October 2012
7
Decision in Principle
Utility
Application
for
DIP
MEE
Asks
Statements
STUK
Ministry of Employment and the Economy (MEE)
is the liaison authority in the DiP preparation process
DIP
Public
Hearings
Prepares
Decision for
Government
No
DIP
DIP
Statement on Safety
Municipalities
Statement on
Siting
Authorities
Statements on
Application
Public
Statements on
Application
Government
Decision
Government
No
Yes
Parliament
SÄTEILYTURVAKESKUS • STRÅLSÄKERHETSCENTRALEN
RADIATION AND NUCLEAR SAFETY AUTHORITY
Ratification
No
I.Aro, October 2012
8
Yes
Construction and Operating Licenses
Utility
Application
for
CL or OL
MEE
Asks
Statements
STUK
Ministry of Employment and the Economy (MEE)
is the liaison authority in CL and OL process
Prepares
Decision for
Government
CL or OL
CL or OL
Rejected
CL or OL
Approved
Statement on
Safety
Municipalities
Statement on
Application
Authorities
Statements on
Application
Public
Statements on
Application
Yes
Government
Decision
Government
No
SÄTEILYTURVAKESKUS • STRÅLSÄKERHETSCENTRALEN
RADIATION AND NUCLEAR SAFETY AUTHORITY
I.Aro, October 2012
9
STUK’s Safety Assessment
Utility
STUK co-ordinates its own independent safety assessment work
Licensing
Documentation
Updated
Documentation
STUK’s
Statement
STUK’s
Statement
MEE
STUK
Review and
Assessment
TSOs
Independent
Analysis/Review
Requests for
Additional info
Safety
Assessment (*)
Statements on
STUK’s work
ACNS
MI
Statement
on Safety
Statements on
PP and EP plans
TSO = Technical Support Organisation
ACNS = STUK’s Advisory board on Nuclear Safety
MI = Ministry of the Interior
SÄTEILYTURVAKESKUS • STRÅLSÄKERHETSCENTRALEN
RADIATION AND NUCLEAR SAFETY AUTHORITY
(*) STUK’s safety assessment is based on
Government Decrees and YVL-guides
I.Aro, October 2012
10
Documents to be reviewed in each step
SÄTEILYTURVAKESKUS • STRÅLSÄKERHETSCENTRALEN
RADIATION AND NUCLEAR SAFETY AUTHORITY
I.Aro,
October
2012
11
Enviromental Impact Assessment (EIA) documents
EIA procedure
• Co-ordinating authority is Ministry of
Employment and the Economy (MEE)
• In accordance with environmental
legislation
• EIA Programme for STUK statement
• EIA Report for STUK statement
• -> EIA is an input for DiP-process
Construction and land use planning
• In accordance with land use and
building legislation
• Regional plans, master plans and local
plans of NPP sites for STUK statements.
• Impact of local conditions on safety as
well as physical protection and
emergency preparedness are to be
taken into account.
SÄTEILYTURVAKESKUS • STRÅLSÄKERHETSCENTRALEN
RADIATION AND NUCLEAR SAFETY AUTHORITY
I.Aro, October 2012
12
Decision in Principle Documentation
Documentation submitted to STUK (Nuclear Energy Degree, NED,
§ 24)
•
•
•
•
•
•
•
•
•
Outline of the technical principles of the planned nuclear facility
Description of the safety principles
Outline of the ownership and occupation of the site planned for the nuclear facility
Description of settlement and other activities and town planning arrangements
Description of the suitability of the planned location for its purpose, taking account
of the impact of local conditions on safety, security and emergency response
arrangements, and the impacts of the nuclear facility on its immediate
surroundings
EIA assessment report
Outline plan on nuclear fuel management
Outline of the applicant's plans and the available methods for nuclear waste
management
Any other information considered necessary by the authorities:
– Outline plans on management system ensuring safety and quality management and good
safety culture during the construction and operating stages
– Outline plans how to allocate adequate and competent personnel resources for the
different stages of the project.
SÄTEILYTURVAKESKUS • STRÅLSÄKERHETSCENTRALEN
RADIATION AND NUCLEAR SAFETY AUTHORITY
I.Aro, October 2012
13
Construction License (CL) Documents
• Documentation submitted to STUK (NED § 35)
–
–
–
–
–
–
–
–
–
Preliminary Safety Analysis Report
Probabilistic Risk Analysis
Safety Classification
Quality Management
Preliminary plan for physical protection
Preliminary plan for emergencies
Plan for safeguards control
STUK’s oversight possibilities
Other documents
• License applicant’s safety assessment
• Assessment on the compliance with regulations
• An applicant for a licence shall also provide the Radiation and Nuclear Safety
Authority with any other reports that the STUK considers necessary.
SÄTEILYTURVAKESKUS • STRÅLSÄKERHETSCENTRALEN
RADIATION AND NUCLEAR SAFETY AUTHORITY
I.Aro, October 2012
14
Operation License (OL) Documents
• Documentation submitted to STUK (NED § 36)
–
–
–
–
–
–
–
–
–
–
–
–
–
Final Preliminary Safety Analysis Report
Probabilistic Risk Analysis
Safety Classification - classification document
Quality Management programme for the facility operation
Technical Specifications - provide operating restrictions result from
component failures and requirements for testing
Summary programme for periodic inspections
Plans for physical protection and emergencies
Plan for safeguards control
Administrative rules for the nuclear facility
Programme for radiation monitoring in the environment
Description of how safety requirements are met
Programme for ageing management
In addition, the applicant must provide STUK with any other information considered necessary by the
Radiation and Nuclear Safety Authority.
SÄTEILYTURVAKESKUS • STRÅLSÄKERHETSCENTRALEN
RADIATION AND NUCLEAR SAFETY AUTHORITY
I.Aro, October 2012
15
Requirements for the documentation
SÄTEILYTURVAKESKUS • STRÅLSÄKERHETSCENTRALEN
RADIATION AND NUCLEAR SAFETY AUTHORITY
I.Aro,
October
2012
16
General requirements for the licensing documentation in
regulatory guides
• Regulatory YVL guidelines gives requirements for licensing
documentation - what, when and how it shall be submitted
– design of the plant, systems, structures and components,
– safety demonstration of the design,
– manufacturing, construction, QA, QC, etc.
• Therefore
– Most of the YVL guides have to be known by the licensee/vendor to be
able to timely submit a documentation capable of “once through”
regulatory approval
– Discussions on the content and scope of the documentation with the
regulator are needed, and probably pilot/master document prior “bulk
production” of system documentation, construction plans for structures
and components
SÄTEILYTURVAKESKUS • STRÅLSÄKERHETSCENTRALEN
RADIATION AND NUCLEAR SAFETY AUTHORITY
I.Aro, October 2012
17
General requirements for the design documentation
• Prerequisites for “Once through” design documentation - for
example
– uses specific, unambiguous wording for the design and design
requirements (no phrases like “in principle”, “and/or”, “mainly” etc.) - in
other words explicit, verifiable design criteria and requirements
– includes clear references to supporting analyses (and also submittal of
references)
– gives clear references to applied design standards (no use of phrases like
“will be followed in principle” etc.)
– design documentation creates an entity (system, component, structure)
• If the text is not specific enough,
– regulator is not able to approve it or at least give specific approvals,
– results in prolonged regulatory review and approval
SÄTEILYTURVAKESKUS • STRÅLSÄKERHETSCENTRALEN
RADIATION AND NUCLEAR SAFETY AUTHORITY
I.Aro, October 2012
18
Final Safety Analysis Report - content
• No specific YVL guide concerning the content or format –
from the decree one gets general idea about the content
• Earlier reference has been made to US NRC standard
format - accordingly US NRC Standard Review Plans have
been utilized as reference materials
• Currently reference is made to the IAEA Safety Guide No.
GS-G-4.1 on content and format
• WENRA has presented guidance for SAR with reference to
the IAEA
SÄTEILYTURVAKESKUS • STRÅLSÄKERHETSCENTRALEN
RADIATION AND NUCLEAR SAFETY AUTHORITY
I.Aro, October 2012
19
Safety Analysis Report:
WENRA Reference levels
1. Objective
– The Licensee shall provide a SAR and use it as a basis for continuous support
of safe operation.
• SAR: a consistent safety document or integrated set of documents
constituting the licensing basis of the plant and updated under control of
the regulatory body
– The Licensee shall use the SAR as a basis for assessing the safety
implications of changes to the plant or to operating practices.
2. Content of the SAR (next slides)
3. Review and update of the SAR
– The licensee shall update the SAR to reflect modifications, new regulatory
requirements, and relevant standards, as soon as practicable after the new
information is available and applicable.
SÄTEILYTURVAKESKUS • STRÅLSÄKERHETSCENTRALEN
RADIATION AND NUCLEAR SAFETY AUTHORITY
I.Aro, October 2012
20
WENRA Reference level (2)
Content: SAR shall describe
– plant site, plant layout and normal operation; and demonstrate how
safety is achieved
– safety functions; all safety systems and safety-related structures,
systems and components; their design basis and functioning in all
operational states, including shut down and accident conditions
– applicable regulations codes and standards
– plant organization and the management of safety
– evaluation of the safety aspects related to the site
– general design concept and the approach adopted to meet the
fundamental safety objectives
– safety analyses performed to assess the safety of the plant in
response to postulated initiating events against safety criteria and
radiological release limits
SÄTEILYTURVAKESKUS • STRÅLSÄKERHETSCENTRALEN
RADIATION AND NUCLEAR SAFETY AUTHORITY
I.Aro, October 2012
21
WENRA Reference level (2)
Content: SAR shall describe
– emergency operation procedures and accident management
guidelines, the inspection and testing provisions, the qualification,
and training of personnel, the operational experience feedback
programme, and the management of ageing
– technical bases for the operational limits and conditions.
– policy, strategy, methods, and provisions for radiation protection
– emergency preparedness arrangements
– on-site radioactive waste management provisions
– decommissioning and end-of-life aspects are taken into account
during operation
SÄTEILYTURVAKESKUS • STRÅLSÄKERHETSCENTRALEN
RADIATION AND NUCLEAR SAFETY AUTHORITY
I.Aro, October 2012
22
IAEA Safety Guide: contents of SAR
•
•
•
•
•
•
•
•
•
•
•
•
•
•
•
Chapter I: Introduction
Chapter II: General plant description
Chapter III: Management of safety
Chapter IV: Site evaluation
Chapter V: General design aspects
Chapter VI: Description and conformance to the design of plant systems
Chapter VII: Safety analyses
Chapter VIII: Commissioning
Chapter IX: Operational aspects
Chapter X: Operational limits and conditions
Chapter XI: Radiation protection
Chapter XII: Emergency preparedness
Chapter XIII: Environmental aspects
Chapter XIV: Radioactive waste management
Chapter XV: Decommissioning and end of life aspects
SÄTEILYTURVAKESKUS • STRÅLSÄKERHETSCENTRALEN
RADIATION AND NUCLEAR SAFETY AUTHORITY
I.Aro, October 2012
23
Flexibility in FSAR practices: three NPP’s, three
different FSAR practices
• TVO BWR’s follow Swedish practice in FSAR: general part,
system description part and topical reports
• Fortum VVER’s follow US NRC standard format; system
descriptions included
• STUK has four FSAR pieces in paper form (official); Loviisa
FSAR is also in electric form (unofficial); TVO BWR’s have
updating going on towards electric form;
• a new plant - a new practice: SAR follows US NRC standard
format + STUK and IAEA supplements; STUK has two paper
copies and electric copy (unofficial pdf version)
SÄTEILYTURVAKESKUS • STRÅLSÄKERHETSCENTRALEN
RADIATION AND NUCLEAR SAFETY AUTHORITY
I.Aro, October 2012
24
Contents of SAR of OL3
• The Preliminary Safety Analysis Report (PSAR) follows the intent of US
NRC Regulatory Guide 1.70 rev. 3, also including descriptions of non
safety plant items.
• The role of the PSAR is to provide STUK with comprehensive
documentation for the first stage of licensing.
• The activities that will be performed in the scope of the construction
permit such as the further design of systems, structures and
components are dealt with in the PSAR and the associated Topical
Reports.
• The licensing procedure is an ongoing process during which the
contents of the Safety Analysis Report are developed into the final
version (FSAR).
• The FSAR will then describe the final state of the systems, structures
and components and demonstrate final results of all the analyses
performed.
SÄTEILYTURVAKESKUS • STRÅLSÄKERHETSCENTRALEN
RADIATION AND NUCLEAR SAFETY AUTHORITY
I.Aro, October 2012
25
US NRC Regulatory Guide 1.70 rev. 3+:
Contents of SAR
1.
2.
3.
INTRODUCTION AND GENERAL DESCRIPTION OF PLANT
SITE CHARACTERISTICS
GENERAL DESIGN BASES OF STRUCTURES, COMPONENTS, EQUIPMENT AND
SYSTEMS
4.
REACTOR
5.
REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS
6.
CONTAINMENT AND ENGINEERED SAFETY FEATURES
7.
INSTRUMENTATION AND CONTROL
8.
ELECTRIC POWER
9.
AUXILIARY SYSTEMS
10. STEAM AND POWER CONVERSION SYSTEM
11. RADIOACTIVE WASTE MANAGEMENT
12. RADIATION PROTECTION
13. CONDUCT OF OPERATIONS
14. PLANT COMMISSIONING
15. ACCIDENT ANALYSES
16. TECHNICAL SPECIFICATIONS
17. QUALITY ASSURANCE
18. HUMAN FACTORS ENGINEERING (+)
19. PROBABILISTIC RISK ASSESSMENT AND SEVERE ACCIDENT EVALUATION FOR
NEW REACTORS (+)
SÄTEILYTURVAKESKUS • STRÅLSÄKERHETSCENTRALEN
I.Aro, October 2012
RADIATION AND NUCLEAR SAFETY AUTHORITY
26
Contents of safety system descriptions (ref. to YVL
2.0)
• Content of PSAR of Safety Class 1, 2 and 3 systems and, where necessary, of
Safety Class 4 systems:
•
•
•
•
•
•
•
•
•
system design bases and principles
system functions, operating principles and essential design parameters
a description of a system’s importance in the accomplishment of a safety
function proper if the system supports a system performing a safety function
the separation principles of a system and its components (compartments,
shielding) and their preliminary location at the plant
requirements and dependencies arising from other systems, including auxiliary
and support systems
the reliability target of the safety function to the implementation of which the
system contributes
a description of analyses and tests that have been or are to be made to
demonstrate system operation
designer’s preliminary safety assessment
licensee’s own safety assessment
SÄTEILYTURVAKESKUS • STRÅLSÄKERHETSCENTRALEN
RADIATION AND NUCLEAR SAFETY AUTHORITY
I.Aro, October 2012
27
OL3 PSAR content and structure
• In addition to the 17 Chapters required by US NRC
Regulatory Guide 1.70 Rev.3
– Chapter 18, “Human Factors Engineering” ;
– Chapter 19, “Probabilistic Safety Assessment and
– Chapter 20, “Decommissioning”
have been added to meet the state-of–the-art
requirements for licensing documentation.
• The Contents meet the intent of the IAEA Safety Standard
Series Safety Guide GS-G-4.1 “Format and Content of SAR
for Nuclear Power Plants.
SÄTEILYTURVAKESKUS • STRÅLSÄKERHETSCENTRALEN
RADIATION AND NUCLEAR SAFETY AUTHORITY
I.Aro, October 2012
28
Review procedures
• There is no detailed regulatory guidance how to perform
the review – such as US NRC Standard Review Plans
• STUK Project Plan has been developed and contains
guidance for the review work
• Criteria is provided by YVL Guide system – if domestic
regulatory criteria is lacking foreign standards are used
• IAEA Safety Guide provides content and format – for
compliance inspection
SÄTEILYTURVAKESKUS • STRÅLSÄKERHETSCENTRALEN
RADIATION AND NUCLEAR SAFETY AUTHORITY
I.Aro, October 2012
29
•documentation required by NE Act section 35
•PSAR, PSA, Safety Classification, QA, Safeguards,
Emergency and Security plans, others
•about 5000 pages
SÄTEILYTURVAKESKUS • STRÅLSÄKERHETSCENTRALEN
RADIATION AND NUCLEAR SAFETY AUTHORITY
I.Aro, October 2012
30
Process to review : STUK Project Plan
Key document is a Project Plan including
• Project organization and
• Appendix 4: Handling of application documents related to Construction
License application including
– Nomination of coordinators for reviewing documents
– Coordinators nominate reviewers for documents and schedule
– PSAR is divided on the basis of main chapters to the managers of corresponding
subprojects; they coordinate inside their subproject and between subprojects and
they nominate the reviewers for each subchapters
– Reviewers provide review results in the form of memorandum and at the end,
Subproject Manager writes Inspection Report including criteria
– PSAR coordinator collects all subproject managers’ contributions and compiles PSAR
Inspection Report
– On the basis of Inspection Reports coordinators write draft regulatory decisions and
memorandums of their regulatory bases
SÄTEILYTURVAKESKUS • STRÅLSÄKERHETSCENTRALEN
RADIATION AND NUCLEAR SAFETY AUTHORITY
I.Aro, October 2012
31
Reactor, safety functions,
systems and analyses
Radiation safety and emergency
preparedness
Layout, Auxiliary systems
Turbine systems
RETU
LATE
SÄVY
Nuclear materials
and Waste
Probabilistic safety
analyses
PISA
YDIN
VALO
Operational safety
management
RAKE
KATU
Mechanical
equipment
KOLA
MEKA
AUTO
Automation systems
SÄTEILYTURVAKESKUS • STRÅLSÄKERHETSCENTRALEN
RADIATION AND NUCLEAR SAFETY AUTHORITY
32
I.Aro,
October
2012
SATU
Electrical systems
Civil construction, Structures,
Fire protection
Quality Management
and Commissioning
During the review
•
•
•
•
•
During the review, the key instrument between the regulatory body, operating
organization and plant vendor is List of Findings where all numbered findings and
comments were listed chapter by chapter according to list of contents.
These lists were sent to power company and further to vendor and returned with
answers of vendor. When necessary, common meetings were organized to handle
questions, findings and comments as well as answers of vendor to provide full
understanding of the issue.
Finally, Lists of Findings were closed and remaining issues were handled during the next
phase, when further developed system descriptions were provided after granting of
Construction License.
Open issues were taken into account when PSAR Review Report was drafted. Since the
plant was first of its kind (prototype), practically all system descriptions needed further
development and this was specifically pointed out in regulatory decision with
corresponding requirement of delivery.
STUK’s review work is based on system descriptions. Practical guidance for inspection
memorandum including the key review issues was provided. Also Standard Review Plans
were utilized as a reference material since the structure of PSAR followed the US practice.
SÄTEILYTURVAKESKUS • STRÅLSÄKERHETSCENTRALEN
RADIATION AND NUCLEAR SAFETY AUTHORITY
I.Aro, October 2012
33
STUK activities during CL stage
•
•
•
•
•
Review of submitted CL documentation (PSAR, PSA, etc.)
– identification of documentation deficiencies (against YVL guides, RG 1.70)
– review and assessment of the fulfilment of safety requirements
– Outcomes: PSAR and PSA inspection reports, decisions (other documents),
memos
Independent calculations to validate accident analysis
– in co-operation with expert organisations, also contracted work
Meetings with license applicant and vendor
– several meetings weekly on technical issues and quality management
Audits on plant vendor and applicant: design process, project management
STUK inspections on design and manufacturing of reactor vessel and steam
generators
SÄTEILYTURVAKESKUS • STRÅLSÄKERHETSCENTRALEN
RADIATION AND NUCLEAR SAFETY AUTHORITY
I.Aro, October 2012
34
STUK’s resources spent for Olkiluoto 3 review
and inspections
Year 2004 of Construction License review :
• 23 manyears divided among 60 persons
• 2,0 Meuros contracted work (equals about another 23 manyears of work
by contracted experts)
Previous years 1999-2003:
• 8 manyears & 0,6 Meuros contracts, altogether
Support to STUK from Finnish expert organisations
• VTT: advice and independent analysis of several topics including PSA,
water chemistry, postulated accidents, severe accidents and I&C
validation; tests including simulation of aircraft crash and of cable fires
• Lappeenranta Technical University: tests and assessment of approach to
severe accident management
SÄTEILYTURVAKESKUS • STRÅLSÄKERHETSCENTRALEN
RADIATION AND NUCLEAR SAFETY AUTHORITY
I.Aro, October 2012
35
Support to STUK from expert organisations
Foreign organisations
– DGSRN and IRSN France: exchange of information on
assessment of several design topics, in specific I&C systems
– GRS Germany: assessment of Break Preclusion concept for
primary and secondary systems; independent analysis and
assessment of aircraft crash protection approach
– ISaR Germany: independent analysis of specific accidents,
assessment of the ECCS
SÄTEILYTURVAKESKUS • STRÅLSÄKERHETSCENTRALEN
RADIATION AND NUCLEAR SAFETY AUTHORITY
I.Aro, October 2012
36
Goals of the review
SÄTEILYTURVAKESKUS • STRÅLSÄKERHETSCENTRALEN
RADIATION AND NUCLEAR SAFETY AUTHORITY
I.Aro,
October
2012
37
Summary on the stages and goals
Plant and site selection by utility
Construction permit application
Decision in principle
Preparatory
phase
Construction
permit reviews
Oversight during
construction
Operating
license reviews
Regulations
Guidelines
Technical
solutions
Verification
and validation
Operational
readiness
Plant
design
Buildings
Reviews
Tech Specs
Systems
Analyses
Commissioning
Safety
analyses
Structures
Testing
Components
Inspections
Physical
protection and
emergency
preparedness
Principal
design
Implementation
requirements
Design bases
OK
SÄTEILYTURVAKESKUS • STRÅLSÄKERHETSCENTRALEN
RADIATION AND NUCLEAR SAFETY AUTHORITY
Project and quality management
Organization
Training
Preparations for operation
Implementation
OK
I.Aro, October 2012
38
Instructions
Plant OK
Conclusions
1
• Licensing steps in each country has certain differences,
but nuclear safety related documentation structure is
similar as well as the gradually increasing level of detail
in each step
• Requirements for licensing documentation in each step
should be presented in Regulation, in Finland
requirements are presented in legislation level, in the
Nuclear Energy Decree and in several regulatory guides
(YVL guides) - important elements are:
– YVL guides are followed
– explicit text and requirements
– transparent and traceable documentation
SÄTEILYTURVAKESKUS • STRÅLSÄKERHETSCENTRALEN
RADIATION AND NUCLEAR SAFETY AUTHORITY
I.Aro, October 2012
39
Conclusions
2
• What is the level of design that has to be completed and
documented in each step?
• E.g. in the construction license phase
– Clearly defined design basis → Demonstrated by supporting
safety analyses → explicit design requirements
– In general, the design documentation and design process shall
provide evidence that
• status of the design is in a phase were design of different technical
disciplines (civil, process, electrical, I&C, HVAC etc.) has proceeded to
a level in which there are verifiable design requirements originating
from the design basis of the plant
• requirements have been comprehensively managed from safety point
of view, systematically taken into account in the plant layout, systems
and component’s design
SÄTEILYTURVAKESKUS • STRÅLSÄKERHETSCENTRALEN
RADIATION AND NUCLEAR SAFETY AUTHORITY
I.Aro, October 2012
40
Conclusions
3
• To proceed into the detailed design
– Vendor’s design management and Licensee’s activities
in the design review and approval need to be able to
create confidence on well managed and competent
performance
– the licensing of detailed design is well planned and
progresses logically with the project implementation
• Configuration and change management as well as requirement
management systems are in place from the beginning of the
project and well documented to ensure that design meets
safety requirements
SÄTEILYTURVAKESKUS • STRÅLSÄKERHETSCENTRALEN
RADIATION AND NUCLEAR SAFETY AUTHORITY
I.Aro, October 2012
41
Conclusions
4
• Regulatory access to Licensee’s licensing document data
base would increase the productivity of regulatory review.
Paper format documentation still needed.
• Licensing plan which indicates the document submissions
to the each party in each step of review process.
SÄTEILYTURVAKESKUS • STRÅLSÄKERHETSCENTRALEN
RADIATION AND NUCLEAR SAFETY AUTHORITY
I.Aro, October 2012
42

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