+ All Categories
Home > Documents > National Status on Life Management of NPPs in … Status on Life Management of NPPs in Finland 2017...

National Status on Life Management of NPPs in … Status on Life Management of NPPs in Finland 2017...

Date post: 06-Apr-2018
Category:
Upload: dinhngoc
View: 217 times
Download: 2 times
Share this document with a friend
31
National Status on Life Management of NPPs in Finland 2017 Meeting of the IAEA TWG-LMNPP February 22-24 th 2017 Vienna, Jyrki Kohopää
Transcript

National Status on Life Management of NPPs in Finland 2017Meeting of the IAEA TWG-LMNPPFebruary 22-24th 2017 Vienna, Jyrki Kohopää

NUCLEAR POWER IN FINLAND

2

• Teollisuuden Voima Oyj, Olkiluoto:

• OL1/2: 2 x BWR 880 MW

• OL3/EPR 1600 MW

• OL4 decision in principle in 2010 (max 1800 MW), extension denied by the Government in 2014.

• Fortum Power and Heat Oy,

• Loviisa:

• Lo1/2: 2 x VVER 502 MW

• Fennovoima Oy, Pyhäjoki:

• FV1 decision in principle in 2010 (max 1800 MW). Change of the reactor type approved in Government 2014, ratification in the Parliament in December 2014.

• Fennovoima submitted a construction license application to the Government at the end of June 2015.

Helsinki

TVO,Olkiluoto

Fortum, Loviisa

Fennovoima,Pyhäjoki

FINLAND

CONFIDENTIAL© Teollisuuden Voima Oyj

TVO – OLKILUOTO

• 37 years electricity production

with a high utilization and low

emmissions

• 17% of the electricity needs in

Finland produced in Olkiluoto

OL1/OL2 licence renewal main issues

• New YVL guides

• Life Time Extension for 20 years (2018-2038)

• Deterministic analysis updating

• Structural analyses

originally many load cases were not calculated

take care of earthquake

fatigue analysis for LTO

4 14.10.2015

OL1/OL2; Top ten modification for new licence

5

Fukushima, PSR and ageing management related works:

• diverse reactor level measurement

• new main circulation pumps and

frequent converter

• LATE (forward pumping of high

pressure bleed)

• New EDGs

• ELMA-project (el & automation

component renewal in containment)

• ACIS (high pressure steam driven

pump)

• fire water feed to reactor

• 327 (auxiliary feed water)-bypass line

• fuel pool level measurement

• fire water feed to fuel pools

• diverse RHR

• emergency control room

6

OL1/OL2; Modernization project 2016-2018

Reneval of generator

transformer (OL2)

Started, 2015

Renewal of PS electrical

and I&C components

Execution acc. to planned

program

Renewal of

Emergency Diesel

Generators

Started, 2018-2022

Diversification of reactor pressure

vessel level measurement (upper

and lower limit)

Started, delayed to 2017-2019

Renewal of LV-

switchgears

Execution, 2010-2016

Diversification of RHR

Started, 2016-2019

Renewal of HP

preheaters and forward

pumping of HP-bleed

Started, 2017-2018

Renewal of Neutron flux

Monitoring Calibration

system Started, 2016-2017

Renewal of Battery

backed 380/220V AC

System UPS-devices

Started, 2016-2019

Remote control room

Started, 2014-2016

Condenser re-tubing

and ejector replacement

Started, 2017-2018

Replacement of FW spargers

Started, 2017-2018

Renewal of Reactor internal

pumps and their frequency

converters Started, 2016-

2018

HP and LP auxiliary FW

Started, 2017-2018

Repair of RPV safe-end

welds

Started, 2017-2018

CONFIDENTIAL© Teollisuuden Voima Oyj

OLkiluoto 3

7

CONFIDENTIAL© Teollisuuden Voima Oyj 8

Olkiluoto 3 EPR project has achieved two

major milestones: start of Nuclear Circuit

Cleaning and completion of Full Scope

Simulator testing.

Cold Functional Tests planned for early

summer 2017.

OL3 Operating License Application

submitted 14.4.2016

OL3 STATUS IN 2017

© Teollisuuden Voima Oyj

Complete nuclear waste management on one

island, Olkiluoto

FINAL DISPOSAL FACILITY FOR

SPENT NUCLEAR FUEL

Nuclear facility construction in progress since

December 2016. Posiva’s preparedness

approved by Finnish regulatory body STUK

and Ministry of Economic Affairs and

Employment.

INTERIM STORAGE FOR

SPENT NUCLEAR FUEL

In operation since 1987

FINAL DISPOSAL REPOSITORY FOR

DECOMMISSIONING WASTE

To be built for decommissioning of plant units

OPERATING WASTE

REPOSITORY

In operation since 1992

Final disposal facility around 2120’s

10

• Construction of Nuclear facility in progress since December 2016

• Operation license application end of 2020. Start of operation end of 2023.

• Repository capacity is 6500 tU (about 3300 capsules)

• Depth of the tunnel system -400-450 m and the extent is about 2 km²

• Construction and operating time approximately 100 years

• The volume of the cave about 1,5 million.m³

• Tunnel length about 60-70 km

Loviisa NPP approach to long term operation

Introduction

• Fortum Power and Heat Oy

• PWR type VVER-440/213

• Commissioning

– Loviisa 1 in February 1977

‒ Loviisa 2 in March 1980

• Licensed until

‒ Loviisa 1 the year 2027

‒ Loviisa 2 the year 2030

• Gross (net) efficiency

– 2 x 526 (502) MW

• Electricity generation 8.33 TWh (2016)

• Load factor 91.1 % (2016)

• Reference unit power (net) of the Loviisa units has increased during plant history from 445 MW to 502 MW (2016).

12

Loviisa approach to Long Term Operation

13

To reach the goal of 50 (+) operating years it is required

• Safe and reliable production and balanced economy

• Syncronising of outages and large projects

• Integration of life time management with safety improvement goals and actions

• Success in personnel generation exchange, competence management and human performancedevelopment

Loviisa ER Development and Implementation

Background

• Identified challenges

– Overlapping operations are performed separately in several organizations

– Focus is too much on “shutdown fires”

– The prioritization of problems / investment principles are not clearly defined

– Availability risk identification is inadequate

15

Awareness of the overall condition and state

of the power plant is limited

Corrective actions

• Develop and implement Loviisa Equipment Reliability Process to:

– Improve organization efficiency

– Allocate resources on the right things

– Provide a better overview of the status and performance of the power plant

– Identify problem areas better and more proactive way

– Prioritize issues with common criteria's

– Provide facts to support decision making

– Develop tools and reports to support daily ER activities

And also fulfill the WANO Peer Review AFI

“Procedures and practices for evaluation and analysis of equipment performance are not

comprehensive and complete”

16

1st AP-913 was compared with the existing processes

17

• Need to identify SPV

components

• Own classification already

in use

• No need for reclassification.

• Almost all actions in this area

have been made but the work

has been missing a systematic

approach.

• Continuing Improvement

function area was little bit lost

under other work.

• We collect lots of data

• No systematic analyzing,

trending or forecasting.

• No proactive obsolescence

management

• Spare part management

need to improve

• Remaint ® concept in use.

• No necessary need to do

big changes in

maintenance strategy.

• Some small detail

enhancement. Example

quality of maintenance

Feedback.

• Lack of prioritization

• Fault cause evaluation could

be more systematic.

• Obsolescence management.

• Poor station level prioritization

and scheduling.

• LRP/TYP is not in balance

• Identified needs vs. available

resources doesn’t meet

AP-913

Top Level Diagram

Journey into the LOER-process

• From the very beginning it was clear that there is no sense to start directly

implementation of the AP-913.

• The target was

– Identify Loviisa’s strengths vs. AP-913

– Identify AP-913 strengths vs. Loviisa’s processes

– Combines the best practices from both and customize a streamlined process to Loviisa

– Define responsibilities in different stages of process

– Define inputs and outputs of processes

18

SPV and Component Criticality Classification

• Component criticality classification is taken in use 2006

– High critical (1)

– Critical (2)

– Low critical (3)

– Run To Failure (4)

• SPV identification was done in 2016

– SPV1 = Reactor trip (24 pcs.)

– SPV2 = Turbine trip (209 pcs.)

– SPV criteria was integrated into the Criticality classification criteria

• SPV1 = High critical

• SPV2 = Critical

– SPV mitigation is in progress

• 82 analyzed 38 actions / 22 completed / 44 no actions needed

• 152 not started yet

19

New Loviisa ER organization

20

Engineering & Maintenance

Quality

Control

Maintenance

• Mechanical

• Electrical

• I&C

• Civil Structures

Planning

• Mechanical

• Process

• Electrical

• I&C

• Civil Structures

• Work Planning

• Outage Planning

Lifetime Management

• Long Term Planning

• PHC function

• Performance Monitoring

• Prioritization

• Technical support

Ageing management

• AM-programs

(Mech. Elec. I&C

Civil Structures)

• Loads and

transient

Monitoring

• AM-Reporting

Reliability management

• Maintenance

optimization

• Criticality

classification

• Spare parts strategy

• Obsolescence

Management

• Condition

monitoring

development

21

Research focus on concrete close to Loviisa reactor

Areas

of

interest

in this

project

• Consists of serpentinite shield and

structural concrete.

• The serpentinite shield close to the

reactor is supposed to withstand the

heat and the neutron fluence.

• The load of the reactor pressure

vessel is supported deeper in the

structural concrete

22

Research steps

1. Concrete samples were drilled in the reactor shaft

– accessible location

– based on the documentation the concrete originates in the same concrete mix => representative content.

2. Irradiation of concrete samples in IFE-institute (Kjeller and Halden) in Norway

– Moderate temperature

– Online measurements

– Post-irradiation experiments

3. Interpretation of results

– Degradation mechanisms?

– Threshold fluence?

– Lifetime of the structure?

Specimens irradiated at JEEP-II, Kjeller

• Planned neutron fluences (E > 0.1 MeV) 3.5 x 1018 … 8.1 x 1019 n/cm2,

corresponding to 30 …700 years of equivalent operation time at the Loviisa NPP

– Longer irradiation times to see the damage mechanism

• Temperature was below 100 ºC, some fluctuation of temperature

• Preliminary results:

– Expansion of specimens observed

– Reduction in mechanical properties

– Stronger reduction in the e-modulus than in the stregth

– No “complete degradation”

– Thin sections indicate changes in both the aggregate and the paste

– Further investigations needed, ongoing

23

24

Fennovoima’s Hanhikivi-1 Project

Fennovoima builds a new nuclear power plant at Hanhikivi site, to produce electricity to its shareholders at cost price.

25

Fennovoima’s Hanhikivi-1 Project

• AES-2006 plant supplied by Rosatom

• AES-2006 is a 1200MW PWR and the latest development step of VVER plant series

• Finnish Radiation and Nuclear Safety Authority (STUK) stated in its preliminary safety assessmentthat the AES-2006 can bedesigned and constructed in accordance with the Finnish safetyrequirements

• Similar units to AES-2006 areordered worldwide and are alsobeing currently constructed

© Rosatom

Target schedule of the Hanhikivi 1

Preparation Development Construction Operation

2008

EIA

2010

Decision-in-Principle

2011

Site selection

2012

First bids for nuclear

power plant

2013

Rosatom chosen as

the plant supplier

2014

Supplementary

Decision-in-Principle

Preparatory works at

the site starts

2015

Construction License

Application

2017

Construction License

2018

Construction of the plant

begins

Operating License

Fuel loading

2024

Electricity production

begins

60 years of operation

Waste disposal

Decommissioning

2007-2012 2013-2017 2018-2023 2024-

27

The Finnish Nuclear Power Plant Safety Research Programme

2015-2018

Plant safety and systems

engineering

• Wide interdisciplinary research area

covering the interfaces between

operations and technologies

• Operation of the plant as a whole

• Design principles, defence-in-depth

• Operating processes, information

model and documentation of safety

justification

• Human and organisational

performance, I&C, PRA applications

Reactor safety

• Goal to ensure the

experimental facilities,

computational methods, and

skilled experts

• The methods should enable

independent assessment of the

supplier’s and licensee’s

proposals

• Thermal hydraulics, reactor

dynamics, severe accidents ,

PRA, electric systems etc.

Structural safety and materials

• Safe long term use of the plants

• Research on the management of

the ageing of materials and

structures

• New materials, manufacturing,

and structural engineering

• Life cycle management and

extension

• Probabilistic and deterministic

design (RI-ISI)

29

INFRASTRUCTURE FOR NUCLEAR ENERGY R&DVTT - RENEWAL OF HOT CELLS AND LABORATORIES

- The VTT Centre for Nuclear Safety is under commissioning

- To be completed in 2017- Includes new material hot

cells, laboratories for waste management, radio chemistry, filter testing

- The office wing hosts 150 researchers (experimental staff + computer modellers)

30

VTT took over the laboratory wing of the new Center for Nuclear Safety, CNS, in

May 2016.

Moving of laboratory equipment into the new facilities is well underway.

Official inauguration event was on September 20th; focus was Finnish clientele.

Installation of hot cells starts in January 2017.

The Centre for Nuclear Safety today

31


Recommended