Transcript of 1 Preparing a decommissioning project H. Sterner E. Thurow Energiewerke Nord GmbH H. Sterner; E....
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- 1 Preparing a decommissioning project H. Sterner E. Thurow
Energiewerke Nord GmbH H. Sterner; E. Thurow, EWN, chapter 1
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- 2 Company EWN View of the Greifswald NPP Site
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- 3 Company EWN Basic data on the reactor units
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- 4 Company EWN Dismantling project Project Facts Objective:green
field site reuse Duration:1995 2012 Dismantling Masses:1.800 Mio Mg
Spent Fuel:5037 elements
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- 5 Company EWN State of dismantling/disposal unrestricted
material suspected/contaminated material (turbine hall) (reactor
building) (other places) (09/2002) Mg
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- 6 Company EWN Site reuse - vision
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- 7 Preparing a decommissioning project Introductory Remarks
1.1Fundamentals 1.2Project analysis 1.3Technical concept
1.4Decommissioning plan 1.5Licensing aspects 1.6Financial aspects
1.7Social aspects Contents of presentation
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- 8 Introduction Decommissioning reasons achieving of planned
designed life time less actual life time than planned high
maintenance and operational costs future costs can not be
calculated safety uncertainties material aging incident political
decision
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- 9 Introduction Decommissioning final phase in life-cycle of
nuclear facility objective:exemption / removal from regulatory
control activities:decontamination, dismantling, demolition,
fuel/waste/material disposal..... consideration: health and safety
of personnel and public, preservation of environment
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- 10 Basic considerations Decommissioning strategy Financing
Technical Waste Management Fuel Management Social
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- 11 Boundary conditions acceptance by authority and public
legal/licensing constrictions specific local conditions political :
technical : plant and site conditions plant design availability of
fuel storages waste management possibilities and disposal
options
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- 12 Boundary conditions financial : availability of budget cash
flow personnel age and competence personnel strategy integration in
project privatisation strategy social :
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- 13 Project objectives implementation of project minimum risk as
cheap as possible (i.e. generally also as fast as possible)
socially acceptable
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- 14 Project objectives Example of derived criteria fulfilment of
safety criteria minimum costs maximum use of own personnel and
local companies site reuse know-how transfer privatisation
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- 15 Project objectives Safety criteria guarantee nuclear safety
- undercriticality - cooling guarantee appropriate radiation
protection - limit dose commitment (ALARA) conventional workers
safety release of radioactivity below licensed levels
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- 16 Project analysis evaluation of the project under all
boundary conditions, considering feasible alternatives
determination of main project tasks and necessary investments
determination of main conditions and basic time schedule
determination of requirements on personnel (qualification and
number) Objectives of project analysis
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- 17 Project analysis spent fuel management (and fresh fuel if
present) waste management dismantling strategy mass flow logistic
post operation personnel strategy site reuse options Main issues of
the project analysis
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- 18 Project analysis main dependencies between project
activities mile stones and overall project life time key decision
plan (with arguments) Result of the project analysis
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- 19 Project analysis direct dismantling instead of safe
enclosure necessity of a new dry spent fuel storage necessity of an
interim storage with treatment capabilities for radioactive
material from dismantling due to lack of final disposal capacities
license for decommissioning and dismantling instead of operation
license prolongation preferable project realisation by own staff
instead of contractors site reuse for industrial activities instead
of green field Example:Key decisions by EWN
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- 20 Project analysis
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- 21 Decommissioning variants operation post operational phase
decommissioning variant establish safe enclosure safe enclosure
complete dismantling complete immediate dismantling 1 2
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- 22 Decommissioning variants planning 4 a ~ 30 a12 - 14 a
operational licencedecommissioning licence safe enclosure operation
3-5 a2-3 a variant 1: safe enclosure post operation realisation
safe enclosure operation 3-5 a12 - 14 a variant 2: immediate
dismantling post operation immediate dismantling shutdown
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- 23 Decommissioning variants activity reduction by radioactive
decay timely postponement of investments progress in
decontamination technique Safe enclosure - advantage:
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- 24 Decommissioning variants qualified plant personnel is not
available possible negative effects on public extensive backfitting
necessary safe enclosure dismantling technical infrastructure is
not usable radiological problems due to decay of Co-60 Safe
enclosure - disadvantage:
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- 25 Project analysis
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- 26 Dismantling controlled area unit 1 Transport steam generator
No. 5 from the steam generator room via reactor hall to the interim
storage
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- 27 Dismantling in the steam generator room unit 1
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- 28 Project analysis
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- 29 ISN cross section storage for spent fuel and interim/decay
storage for radioactive material storage area 20.000m dimension l.
240m x w. 140m x h. 18m halls 1-7radioactive material: -
20-containers - cast iron containers - concrete containers - steel
containers - casks (cast iron) - large components hall 8spent fuel
in CASTOR casks masseshalls 1-7approx. 110.000Mg hall 8585Mg (heavy
metal)
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- 30 Interim Storage North
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- 31 Project analysis
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- 32 Site reuse
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- 33 Technical concept General main issues main decommissioning
and dismantling steps dismantling principles operational waste
management categorisation of systems/buildings/areas by
radiological classes inventory mass flow logistic (from
dismantling) main items of partial plant adaptation main items of
investments (new equipment) special dismantling and disposal
concept for highly activated components safe post operation,
evaluation of the residual life time of old equipment possibilities
to reduce operational costs
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- 34 Technical concept EWN table of content 1.Introduction 2.Site
and buildings description 3.Present status 4.Decommissioning and
dismantling activities 5.Decontamination methods 6.Emissions
7.Material flow and waste management 8.Radiological protection
9.Declassification 10.Necessary new installations and systems
11.Fire protection 12.Workers protection 13.Plant security
14.Infrastructure 15.Safety case 16.Environmental impact
assessment
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- 35 Technical concept EWN - dismantling principles as large
components / parts as possible for treatment in our warm workshop
or interim storage dismantling planning on system basic, execution
on room basis start in unit 5; low contamination / radiation dose
from low to high contamination / radiation dose use market
equipment in situ decontamination only for dose reduction
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- 36 Technical concept EWN - main direction of dismantling
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- 37 Technical concept Plant inventory Systems and other
components on a room-by-room basis Masses and material types (on a
room- and system-basis) Contamination in rooms and systems
(including estimation of contamination penetration in concrete
structures) Dose rates, including ambient rates in rooms, hot
spots, and at large components Hazardous materials (Asbestos, PCB
etc.)
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- 38 Technical concept Categorisation by radiological classes
Category I- unrestricted material Category II- suspected material
(an eventual contamination cannot be excluded) Category III-
contaminated material
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- 39 Technical concept Categorisation by radiological classes EWN
- example Estimated masses for different contamination categories
in the turbine hall units 1 4 Category Iunrestricted material ca.
45 % Category IIsuspected materialca. 53 % Category IIIcontaminated
materialca. 2 %
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- 40 Technical concept Classification of systems ISystems
necessary for nuclear safety and radiation protection IISystems
necessary for industrial safety and operation IIINot necessary
systems
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- 41 Technical concept WWER 440 - classification of systems
SystemUnit System Category Remarks Post Operation Preparation Safe
Enclosure Safe Enclosure ventilation for reactor- and auxiliary
building 1, 2, 3, 4III Capacity reduction, Adaptation and/or
Installation of new Ventilation systems water cleaning system 2
(SVO-2) 1/2 3/4 III water cleaning system 3 (SVO-3) including
sewage water system 1/2 3/4 II III water cleaning system 4 (SVO-4)
1/2 3/4 II III steam generator facility1, 2, 3, 4III steam
generator blowdown system1, 2, 3, 4III water cleaning system 5
(SVO-5)1, 2, 3, 4III water cleaning system 6 (SVO-6)1 - 4III solid
radioactive waste store1 - 4IIIIIremoval solid waste liquid
radioactive waste store1 - 4IIIII off-gas cleaning system1/2 3/4
III
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- 42 Technical concept Waste and material management Fuel
Operational waste Dismantled material
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- 43 Technical concept EWN - fuel management 19901999
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- 44 Technical concept EWN - waste management
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- 45 Technical concept EWN - material management Building
structures Ca. 1.185.000 Mg Building structures Ca. 1.185.000 Mg
Remaining building structures Ca. 471.000 Mg Remaining building
structures Ca. 471.000 Mg Plant Greifswald site 1.800.000 Mg Plant
Greifswald site 1.800.000 Mg Plant parts TH 1 6, IH 6 Ca. 50.000 Mg
Plant parts TH 1 6, IH 6 Ca. 50.000 Mg Category II and III
Potentially contaminated Ca. 565.000 Mg Category II and III
Potentially contaminated Ca. 565.000 Mg Category I Not contaminated
Ca. 1.235.000 Mg Category I Not contaminated Ca. 1.235.000 Mg
Concrete and plant parts Ca. 94.000 Mg Concrete and plant parts Ca.
94.000 Mg
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- 46 Technical concept Project structuring Different structures
depending on point of view Work breakdown Responsibility Objects
Type of work Phases
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- 47 Technical concept EWN - Work breakdown
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- 48 Decommissioning plan Content and structure Comprehensive
Project Management Licensing Process Characterisation of the
facility (dose mapping and inventory classification) Safety
assessment Criticality assessment Radiation Protection and
Monitoring Environmental impact assessment Waste Management
Decontamination Dismantling and demolition Remote dismantling
Engineering support Quality Assurance and Quality control Physical
Protection Site adaptation and development Public relation
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- 49 Decommissioning plan EWN Explanatory reports ERFirst issue
in 1994Issue Index one year later ER1Licensing concept for
decommissioning/dismantling of units 1 - 62 ER2Radiation protection
concept2 ER3Site operation4 ER4Incident analyses2 ER5Fire
protection concept2 ER6Intervention in contaminated building
structures under controlled area conditions 3 ER7Reconstruction/new
construction of the complex of central active workshop/melting
facility 3 ER8General dismantling plan1 ER9Material flow/release
measurement concept1 ER10Decontamination concept2 ER11Disposal of
damaged fuel elements1 ER12Physical protection3 ER13Remote
dismantling of reactor pressure vessels 1 to 52 ER14Clearing of
tube storages for activated components1 ER15Disposal of absorber
sections and shielding assemblies2
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- 50 Decommissioning plan Initial for operation license Updating
during operation Final for decommissioning license Ultimate after
project termination
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- 51 Licensing aspects Decrease in potential risk
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- 52 Licensing aspects EWN Strategy - overview strategy
determination of main licensing steps common understanding of
decommissioning and dismantling in parallel to post operation and
permanent system adaptation categorisation of systems based on
safety importance for the different decommissioning phases step by
step procedure of documents
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- 53 Licensing aspects EWN Strategy - overview system dismantling
supervised area personnel occupation one basic license - possession
- post operation -large dismantling part work security part
licences -controlled areas -remote dismantling smooth workload
planning and authorized control no public hearing necessary
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- 54 Licensing aspects EWN - licensing mile stones (basic
schedule )
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- 55 Licensing aspects EWN - step by step procedure of
documents
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- 56 Finacial aspects EWN experience - cost Decommissioning start
as early as possible after shutdown 1 additional year of post
operation costs ca. 100 Mio DM Comparison of dismantling costs per
unit: Greifswald:400 Mio DM German utilities:600 Mio DM
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- 57 Social aspects Problems after shut down Substantial problems
at the NPP: Restructuring of the company for decommissioning is
necessary Planning, preparation and realisation of decommissioning
Motivation of personnel, ensuring the permanent personnel level
Planning of the personnel reduction
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- 58 Social aspects EWN - Measures and principles No major
contractors Retirement scheme Privatisation/outsourcing Education -
decommissioning - better position on labour market Dismissal with
economical support Re-industrialisation of the site
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- 59 Social aspects EWN personnel reduction
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- 60 Social aspects EWN personnel reduction
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- 61 Social aspects Approaches for the NPP Further qualification
of the personnel Support for the creation of new working places
(Outsourcing) Inclusion of local companies in decommissioning
activities Timely release of NPP territory for the settlement of
industries Use of national and international support
programmes
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- 62 Social aspects Approaches for the region Further
qualification of unemployed people (increase of chances at the
labour market) Creation of new working places (privatisation)
Development of regional development programmes Use of national and
international support programmes Co-ordination of regional
activities/measures
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- 63 Social aspects Approaches for the country Creation of
boundary conditions (legal framework, financing, infrastructure)
Initiation of national and international support programmes
Creation of a centralised organisational structure for controlling
and co-ordination of all measures