design basis for plim programme · manageme nt and evaluation part 4: new psr ... material codes...

Design Basis for PLiM Programme

Nov.1 2013

Nuclear Power Division

Ki Sig KANG

Plant safety &

reliability

Smooth operation of failure-free and capable

SSCs

Minimization of

unplanned unit outages

Maintenance optimization

Optimization of

Production cost efficiency

LTO

PLiM Programme Objectives

Life extension vs Life Management

3

Plant Life Management Output

• Critical SSCs (safety and power production)

• Provides a decision analysis tool and methodology that prioritizes and allocates the plant resources

• Provides financially optimized long-term aging and obsolescence management plans f

• Identifies and mitigates risks associated with components

• Identifies aging effects that can lead to reduced reliability and unexpected degradation to availability.

SSC : System Structure Components

Plant Life Management - Planning

Plant Life Management

0202-0080..00202-0080..0

Ass

et C

ost

$$

(m

illio

ns)

PLIM

Planning

Operation and Maintenance

Obsolescence and losttime failures

PLIM-Strategic planning and risk management reduces cost

ExamplePLIM Model

No

Plan

Time (years)

Refurbishment

End of asset

life or sale

Oconee, Davis Besse, Seabrook, Angra, Point Beach Oconee, Davis Besse, Seabrook, Angra, Point Beach

Status of Operating Npps

7

Reference : Economics

8

9

World Status of Operating Reactors

10

U.S. NPPs – Years of Operation

40 years or greater

9 units - end of 2011 (9%)

15 units - end of 2012 (14%)

26 units - end of 2013 (25%)

11

U.S. Nuclear Capacity - Impact of License Renewal

0

20,000

40,000

60,000

80,000

100,000

120,000 Capacity with 100% license renewal

Capacity without license renewal

Source: Nuclear Energy Institute

15 units would have been shutdown by end of 2012 without license renewal! 100 nuclear units

produce ~20% of U.S. capacity

At June 2013, the NRC had extended the licences of 73 reactors (72

still operating). The NRC is considering licence renewal

applications for 18 further units, with 7 more applications expected.

Service life in France Npps

• Design life : 40 years • Improvement of safety

continuously through O&M • 10 years basis

• Management of ageing: • Improvement operating

performance

• Dynamic and proactive way

• 18 units will reach the age of 40 ys between 2015 and 2020 • 900 MWe series (34 Units) -

• 1300 MWe series (20 Units)

• 1500 MWe series (4 Units)

• PLiM for LTO considered within the framework of PSR

Considering 50 ~

60 years operation.

GRAVELINES 6 units

NOGENT-sur-SEINE 2 units

DAMPIERRE 4 units

CHOOZ 2 units

CATTENOM 4 units

FESSENHEIM 2 units

BELLEVILLE 2 units

LE BUGEY 4 units

SAINT-ALBAN 2 units

CRUAS 4 units

TRICASTIN 4 units

1300 MW 900 MW 1450 MW

PENLY 2 units

FLAMANVILLE 2 units

PALUEL 4 units

GOLFECH 2 units

LE BLAYAIS 4 units

CIVAUX 2 units

CHINON 4 units

SAINT-LAURENT 2 units

19 sites

Paris

Lyon

Marseille

EPR

FA3

PE3

12

13

Scenario Of Npps’ Power Generation In Russia

00

100020003000

4000

5000

6000

9000

1044011440

12440

13880

15480

17480

1849219504

19968

21825

21408

22242

1000

0

2000

3000

40005000

6000

9000

10440

11440

12440

13880

15480

17480

18492

19504

19968

2140821825

0

2000

4000

6000

8000

10000

12000

14000

16000

18000

20000

22000

24000

2000 2002 2004 2006 2008 2010 2012 2014 2016 2018 2020 2022 2024 2026 2028 2030 2032 2034 2036 2038 2040 2042 2044 2046

Lifetime

prolongation

on 15 years

Operation during

30 years

МW • WWER 440- 230: Design life : 25 Y 15 Y (40Y)

• WWER 440- 213 : Design life 25 Y 25 Y (50Y)

• WWER 1000 : Design life 30 Y 30 Y (60Y)

• RBMK : Design life 30 Y 15Y (45Y)

10 NPPs, 30 units – 22 242 МW including

12 units of the 1st Generation - 5 752 MW

14

Czech Republic

• 4 units of WWER-440/V-213C type in

DUKOVANY

• Operation start-up : 1985, 1986, 1986, 1987

• Design lifetime: NPP – 30 years, RPV – 40 years

• 2 units of WWER-1000/V-320 C type in TEMELIN

• Operation start-up: 2002, 2003

• Design lifetime: NPP – 40 years, RPV – 40 years

Considering 60 years operation through

LTO project supported by PSR.

UK Reactor

• PLiM for LTO considered within

the framework of PSR

• In Dec. 2010 EDF Energy

announced 5-year lifetime

extensions to 2 AGR NPPs;

• Magnox (4) : Design life time : 25 Y

• AGR (14) : Design life time : 25 Y

• PWR (1) : Design life time : 40 Y

• Enable 5-year lifetime extensions

for remaining AGRs

• 20-year lifetime extension for

Sizewell B PWR

15

16

5. Industry Guidance 5. Industry Guidance

EPRI 1002950 EPRI 1002950 - - structural structural

EPRI 1003056 EPRI 1003056 - - mechanical mechanical

EPRI 1003057 EPRI 1003057 - - electrical electrical

Owners Groups Owners Groups

3. NEI Guidance 3. NEI Guidance

NEI 95 NEI 95 - - 10 10

NEI 98 NEI 98 - - 06 (draft) 06 (draft)

1. NRC Rules 1. NRC Rules

10CFR54 10CFR54

10CFR51 10CFR51

4. NRC Reports 4. NRC Reports

NUREG NUREG - - 1800 1800

SRP SRP


GALL GALL


Environmental Environmental

2. NRC Guidance 2. NRC Guidance

RG 1.188 RG 1.188

RG 4.2 RG 4.2

5. Industry Guidance 5. Industry Guidance

EPRI 1002950 EPRI 1002950 - - structural structural

EPRI 1003056 EPRI 1003056 - - mechanical mechanical

EPRI 1003057 EPRI 1003057 - - electrical electrical

Owners Groups Owners Groups

3. NEI Guidance 3. NEI Guidance

NEI 95 NEI 95 - - 10 10

NEI 98 NEI 98 - - 06 (draft) 06 (draft)

1. NRC Rules 1. NRC Rules

10CFR54 10CFR54

10CFR51 10CFR51

4. NRC Reports 4. NRC Reports


SRP SRP


GALL GALL


Environmental Environmental

2. NRC Guidance 2. NRC Guidance

RG 1.188 RG 1.188

RG 4.2 RG 4.2

Part 1: Ageing

Manageme

nt and

Evaluation

Part 4: PSR

Part 2:

Radiologic

al Impact

Evaluation

Part 3: New

Regulation

Analysis

Current Requirements to Renew

Operating License (within design

life)

Long Term Operating Requirements

(beyond design life)

Application

for Long Term

Operation

../../../../Data/2007/2004/LM/HWR/CS Jan-10-13/Documents and Settings/KangK/Local Settings/Ref matterial/IAEA PSR/PSR.pdf

17

PSR Report and updated FSAR

Design Basis Document

18

Configuration

Management

Terminology Relationships

Design Control

Design Bases

Reg. Reqs

Other Design Reqs

Tech. Specs

Drawings

Lists

Calculations

Analyses

Evaluations

O & M Procedures

Instructions

Others

Design

Process

Design

Output Design

Input

Physical Plant Other Controlled

Documents

Design

Documents

#39 Owner

Requirements

Regulatory Agency

Requirements

Design Criteria

Design Process

Design Output

Design Input Interdisciplinary

Design Review

Procurement Construction/Start-up

Design

Characteristics

Reference Plant

Material

Codes &

Standards

Industry

Information

Review/

Response

Construction

Interfaces

Procurement

Spec.

Drawing/

Construction Spec.

Equipment/Material

Licensing

Requirements

Regulation/

Codes &

Standards

Site

Characteristics

Quality

Requirements

Reference Plant

Design Data

Conceptual

Design

Basic

Design

Detail

Design

Owner Requirements

• Design Improvement

• Operability/Maintainability

• Optimization : Reliability/Safety

• Constructability : Economics/Efficiency

• A/E Design Standards

• New Technology

Conceptual

Design

Basic

Design

Detail

Design

Site Evaluation

/Environmental

Study

Site

Characteristics

Site Plot Plan

Regulatory

Requirements

Codes &

Standards

QA

Requirements

Owner

Requirements

Design Concept of plant Design Standards

System Design Criteria

General

Arrangements

Structural Analysis

Seismic Analysis

System Calculation

P&ID,SLD,CLD

Structural

Design

Structure

Detail DWGS.

Cable Tray & Conduit

Raceway DWGS.

Cable Block

Piping/HVAC/

Instrument Layout

Support Design

Constructor

Detail Drawings

Purchase Spec.

Supplier Documents

Review

Delivery to Site

Installation

Field Change Request

As Built

Construction

Packages

Potential Design Bases Doc. Applications

• Engineering

• Conceptual design development and alternative considerations

• Design specification for in-house or contractor designers and for inter discipline

coordination

• Calculations and analyses

• Bases for technical reviews, safety reviews, and Independent design verification

• Procurement specifications

• Identification of information and documents affected by change

• Installation specifications

• Installation and functional testing requirements and acceptance criteria

• Field change request evaluations

• Evaluations of operational events and non-conforming conditions

• Justifications for continued operation

• Selection and review of equipment performance surveillance data

• Bases for operations, maintenance, and surveillance procedures review

• Evaluation of material substitution, spare parts equivalency, and material

upgrades

23

• Operations • Abnormal event assessments

• Bases for unusual system alignment (e.g., for

maintenance or testing) assessments

• Temporary modifications reviews

• Selection and review of component and system

performance data

• Addressing non-proceduralized events

• Operator aids and training material development

• Operations procedures preparation and review

24

Potentiel Design Bases Doc. Applications

Maintenance • Post-maintenance test requirements and acceptance

criteria

• Procedure and work instruction preparation and

review

• Assessment of material condition requirements

Licensing • Licensing analyses (e.g., UFSAR)

• Technical specifications review and changes

• License amendments

25


Training • Bases for lesson plans and training materials

• Simulator fidelity

Other • Performing technical audits

• Determining recommendations for reducing

personnel doses

• License Renewal

• Safety System Functional Inspections

• Probabilistic Risk Assessments

• Margin Management

• Setpoint Selection

26


Doel and Tihnage Npps

1. Tihange 1 (962 MW, 1975)

2. Tihange 2 (1008 MW, 1983)

3. Tihange 3 (1054 MW, 1985)

Doel 2 and Tihange 2 RPV structure and

components

• RPV (including the vessel head) is approximately 13 metres in

height with an outer diameter of 4.4 metres for a total weight of

330 tonnes.

• The pressure vessel is made of thick low-alloy steel (up to 20 cm

thick for the cylindrical portion of the vessel).

Upper Vessel Ring : Around 930 indications

Lower Vessel Ring : Around 7800 indications

Nozzle Ring : Around ten indications

Number of Flaw Indications

Origin and Evolution

Origin and nature of the indications: Indications

present at manufacturing stage?

• Licensee Evaluation: based on

• Documentation review (manufacturing file)

• Root cause analysis

• Comparison with an affected piece

• Possible evolution of the indications:

• Licensee Evaluation : based on

• Depending on previous answer

• Literature study

• Fatigue crack growth analysis

33

Support for Operation, Expansion & New comers

Operating NPP Programme

Expansion NPP Programme

New Comers Programme

34

Share OPEX and LLs with Nuclear Industry to reflect new

NPPs design