Top Banner
65 @ TRAINING COURSE SERIES VIENNA, 2017 Integral Pressurized Water Reactor Simulator Manual: Exercise Handbook
126

Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

Aug 16, 2020

Download

Documents

dariahiddleston
Welcome message from author
This document is posted to help you gain knowledge. Please leave a comment to let me know what you think about it! Share it to your friends and learn new things together.
Transcript
Page 1: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

65

Integral Pressurized Water R

eactor Simulator M

anual: Exercise Handbook

TR

AIN

ING

CO

UR

SE

SE

RIE

S

@65

T R A I N I N G C O U R S E S E R I E SV I E N N A , 2 0 1 7

Integral Pressurized Water Reactor Simulator Manual:

Exercise Handbook

ISSN 1018-5518

TCS-65_Exer_Handbook_cov.indd 1,3 2017-05-24 14:36:42

Page 2: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

INTEGRAL PRESSURIZED WATER REACTOR SIMULATOR MANUAL:

EXERCISE HANDBOOK

Page 3: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

AFGHANISTANALBANIAALGERIAANGOLAANTIGUA AND BARBUDAARGENTINAARMENIAAUSTRALIAAUSTRIAAZERBAIJANBAHAMASBAHRAINBANGLADESHBARBADOSBELARUSBELGIUMBELIZEBENINBOLIVIA, PLURINATIONAL

STATE OFBOSNIA AND HERZEGOVINABOTSWANABRAZILBRUNEI DARUSSALAMBULGARIABURKINA FASOBURUNDICAMBODIACAMEROONCANADACENTRAL AFRICAN

REPUBLICCHADCHILECHINACOLOMBIACONGOCOSTA RICACÔTE D’IVOIRECROATIACUBACYPRUSCZECH REPUBLICDEMOCRATIC REPUBLIC

OF THE CONGODENMARKDJIBOUTIDOMINICADOMINICAN REPUBLICECUADOREGYPTEL SALVADORERITREAESTONIAETHIOPIAFIJIFINLANDFRANCEGABON

GEORGIAGERMANYGHANAGREECEGUATEMALAGUYANAHAITIHOLY SEEHONDURASHUNGARYICELANDINDIAINDONESIAIRAN, ISLAMIC REPUBLIC OF IRAQIRELANDISRAELITALYJAMAICAJAPANJORDANKAZAKHSTANKENYAKOREA, REPUBLIC OFKUWAITKYRGYZSTANLAO PEOPLE’S DEMOCRATIC

REPUBLICLATVIALEBANONLESOTHOLIBERIALIBYALIECHTENSTEINLITHUANIALUXEMBOURGMADAGASCARMALAWIMALAYSIAMALIMALTAMARSHALL ISLANDSMAURITANIAMAURITIUSMEXICOMONACOMONGOLIAMONTENEGROMOROCCOMOZAMBIQUEMYANMARNAMIBIANEPALNETHERLANDSNEW ZEALANDNICARAGUANIGERNIGERIANORWAY

OMANPAKISTANPALAUPANAMAPAPUA NEW GUINEAPARAGUAYPERUPHILIPPINESPOLANDPORTUGALQATARREPUBLIC OF MOLDOVAROMANIARUSSIAN FEDERATIONRWANDASAN MARINOSAUDI ARABIASENEGALSERBIASEYCHELLESSIERRA LEONESINGAPORESLOVAKIASLOVENIASOUTH AFRICASPAINSRI LANKASUDANSWAZILANDSWEDENSWITZERLANDSYRIAN ARAB REPUBLICTAJIKISTANTHAILANDTHE FORMER YUGOSLAV

REPUBLIC OF MACEDONIATOGOTRINIDAD AND TOBAGOTUNISIATURKEYTURKMENISTANUGANDAUKRAINEUNITED ARAB EMIRATESUNITED KINGDOM OF

GREAT BRITAIN AND NORTHERN IRELAND

UNITED REPUBLICOF TANZANIA

UNITED STATES OF AMERICAURUGUAYUZBEKISTANVANUATUVENEZUELA, BOLIVARIAN

REPUBLIC OF VIET NAMYEMENZAMBIAZIMBABWE

The following States are Members of the International Atomic Energy Agency:

The Agency’s Statute was approved on 23 October 1956 by the Conference on the Statute of the IAEA held at United Nations Headquarters, New York; it entered into force on 29 July 1957. The Headquarters of the Agency are situated in Vienna. Its principal objective is “to accelerate and enlarge the contribution of atomic energy to peace, health and prosperity throughout the world’’.

Page 4: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

TRAINING COURSE SERIES No. 65

INTEGRAL PRESSURIZED WATER REACTOR SIMULATOR MANUAL:

EXERCISE HANDBOOK

INTERNATIONAL ATOMIC ENERGY AGENCYVIENNA, 2017

Page 5: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

COPYRIGHT NOTICE

All IAEA scientific and technical publications are protected by the terms of the Universal Copyright Convention as adopted in 1952 (Berne) and as revised in 1972 (Paris). The copyright has since been extended by the World Intellectual Property Organization (Geneva) to include electronic and virtual intellectual property. Permission to use whole or parts of texts contained in IAEA publications in printed or electronic form must be obtained and is usually subject to royalty agreements. Proposals for non-commercial reproductions and translations are welcomed and considered on a case-by-case basis. Enquiries should be addressed to the IAEA Publishing Section at:

Marketing and Sales Unit, Publishing SectionInternational Atomic Energy AgencyVienna International CentrePO Box 1001400 Vienna, Austriafax: +43 1 2600 29302tel.: +43 1 2600 22417email: [email protected] http://www.iaea.org/books

For further information on this publication, please contact:

Nuclear Power Technology Development SectionInternational Atomic Energy Agency

Vienna International CentrePO Box 100

1400 Vienna, AustriaEmail: [email protected]

INTEGRAL PRESSURIZED WATER REACTOR SIMULATOR MANUAL: EXERCISE HANDBOOKIAEA, VIENNA, 2017

IAEA-TCS-65/Exercise HandbookISSN 1018–5518

© IAEA, 2017Printed by the IAEA in Austria

June 2017

Page 6: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

FOREWORD

The IAEA has established a programme in nuclear reactor simulation computer programs to assist Member States in educating and training nuclear professionals in the operation and behaviour of nuclear power plants. The simulators enable hands-on training for nuclear professionals involved in teaching and training topics such as nuclear power plant design, safety, technology, simulation and operations. The simpler design of the simulators allows professionals to grasp the fundamentals without becoming lost in the details of a more complex full scope simulator. The objective is to provide, for various reactor types, insight and practice in reactor operational characteristics and their response to perturbations and accident situations.

Together with management and development, the IAEA regularly produces training material and provides training courses to assist professionals in Member States to understand the simulators and their associated technologies. This training is more cost effective and less time consuming than alternative methods and is highly suitable for Member States with limited resources.

This Exercise Handbook accompanies Training Course Series No. 65, Integral Pressurized Water Reactor Simulator Manual. It contains practical exercises as part of the educational and training material provided during IAEA training courses and workshops. The Manual provides an explanation of the theoretical concepts of integral pressurized water reactors and a description of the simulator’s features. The Exercise Handbook complements this by providing detailed, step by step operating instructions together with the required explanations to run various normal operations and transients in the simulator. The publications can be used both independently and together, and they serve as educational and training material for IAEA training courses and workshops. This publication provides comprehensive reference material to support human capacity building in all Member States improving their expertise in education and training related activities for small modular reactor technology.

The IAEA gratefully acknowledges the contribution of I. Parrado (Spain) to the preparation of this publication. The IAEA officer responsible for this publication was C. Batra of the Division of Nuclear Power.

Page 7: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

EDITORIAL NOTE

This publication has been prepared from the original material as submitted by the contributors and has not been edited by the editorial staff of the IAEA. The views expressed remain the responsibility of the contributors and do not necessarily reflect those of the IAEA or the governments of its Member States.

Neither the IAEA nor its Member States assume any responsibility for consequences which may arise from the use of this publication. This publication does not address questions of responsibility, legal or otherwise, for acts or omissions on the part of any person.

The use of particular designations of countries or territories does not imply any judgement by the publisher, the IAEA, as to the legal status of such countries or territories, of their authorities and institutions or of the delimitation of their boundaries.

The mention of names of specific companies or products (whether or not indicated as registered) does not imply any intention to infringe proprietary rights, nor should it be construed as an endorsement or recommendation on the part of the IAEA.

The IAEA has no responsibility for the persistence or accuracy of URLs for external or third party Internet web sites referred to in this publication and does not guarantee that any content on such web sites is, or will remain, accurate or appropriate.

Page 8: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

CONTENTS

1. INTRODUCTION ......................................................................................................... 1

1.1. BACKGROUND ............................................................................................. 1

1.2. OBJECTIVES.................................................................................................. 1

1.3. SCOPE ............................................................................................................ 2

1.4. STRUCTURE .................................................................................................. 2

2. SIMULATOR EXERCISES FOR STANDARD OPERATIONS ................................... 2

2.1. LOAD MANEUVERING (10%) IN TURBINE LEADING MODE ................ 3

2.2. LOAD MANEUVERING (10%) IN REACTOR LEADING MODE ............. 10

2.3. REACTOR POWER DECREASE FROM 100% TO 0% ............................... 16

2.4. REACTOR POWER RISE FROM 0% TO 100%........................................... 24

2.5. REACTOR TRIP AND RESTART................................................................ 33

3. SIMULATOR EXERCISES FOR MALFUNCTION TRANSIENT EVENTS ............ 44

3.1. SPURIOUS TURBINE TRIP AND RECOVERY .......................................... 45

3.2. LOSS OF FEEDWATER FLOW ................................................................... 53

3.3. TURBINE RUNBACK .................................................................................. 58

3.4. LARGE STEAM GENERATOR TUBE RUPTURE (SGTR) ........................ 61

3.5. LARGE STEAM LINE BREAK (MSLB) ...................................................... 68

3.6. STATION BLACKOUT (SBO) ..................................................................... 74

3.7. STEAM LINE ISOLATION .......................................................................... 79

3.8. PRESSURIZER SAFETY VALVE OPENING .............................................. 84

3.9. REACTOR COOLANT PUMP TRIP ............................................................ 89

3.10. FOUR REACTOR COOLANT PUMPS TRIP ............................................... 94

APPENDIX .......................................................................................................................... 99

ABBREVIATIONS ............................................................................................................ 109

CONTRIBUTORS TO DRAFTING AND REVIEW .......................................................... 111

Page 9: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA
Page 10: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

1

1. INTRODUCTION

1.1. BACKGROUND

The International Atomic Energy Agency (IAEA) has a suite of nuclear reactor simulation

computer programs to assist its Member States in education and training. The objective is to

provide, for a variety of advanced reactor types, insight and practice in-reactor operational

characteristics and their response to perturbations and accident situations. To achieve this, the

IAEA arranges for the supply and development of a suite of basic principles nuclear power

plant simulators which are available for free to Member States upon request and are intended

for educational purposes. The IAEA also provides associated training material, sponsors

training courses and workshops, and distributes the documentation and computer programs.

The use of basic principle simulators to aid in teaching complex system interactions can

considerably improve students’ comprehension and retention of engineering course materials.

In addition, the use of simulators on nuclear fundamentals type training courses can greatly

add to trainees’ understanding of reactor operation and the role of various systems.

The IAEA’s existing suite of basic principles simulators are currently based on a variety of

large scale, water cooled nuclear reactor technologies. The basic principle simulator helps in

demonstrating the essential physical processes as well as fundamental system engineering

concepts. This type of simulator also serves training objectives such as providing an overview

of plant behaviour or a basic understanding of the normal as well as abnormal operation

modes.

Such simulators may consist of complete primary and secondary circuits, sometimes with a

reduced number of loops or redundancies. The scope of simulation focusses on the main

systems where auxiliary or supporting systems may be neglected. The control room or panels

very often have a fundamentally different design in comparison with conventional control

room design.

The IAEA’s suite of simulators is used on personal computers to develop understanding of the

various reactor designs as well as their operational characteristics. They are intended for

nuclear professionals involved in teaching and training on topics related to nuclear power

plant design, safety, technology, simulation and operations; and could also be used, in some

cases, for a broad audience of both technical and non-technical personnel as introductory

educational tool. The simulators are not expected to produce accurate results but do

demonstrate realistic trends and transients in response to changes made by the user.

In recent years the IAEA has seen an increase in the participation of its Member States in its

programme for the technology development of small modular reactors. Various designs are

under development in several Member States. A large number of the designs that are in

development are light water cooled and moderated small integral pressurized water reactors

(iPWRs). Common features of iPWR designs include modularity, passive safety systems for

core and containment cooling, and integrated design — where most or all primary

components are located inside the reactor vessel.

1.2. OBJECTIVES

The objective of this exercise handbook is to provide a basic set of pratical exercises to

understand various normal operations as well as possible transients in this type of reactor. It

also serves as a step-by-step guidance document during the training courses. Full instructions

Page 11: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

2

on how to install the software and all of the background information is contained in the

accompanying Intergral Pressurized Water Reactor Simulator Manual (Training Course Series

No. 65).

1.3. SCOPE

This publication covers only a certain predefined list of standard operations and malfunction

transients. The simulator in itself is capable of simulating more transients and therefore users

can run various other transients depending upon his or her understanding level as well as the

capability of simulator. Sever accidents are out of scope of this simulator and therefore cannot

be simulated.

Most importantly, the responses manifested by the simulator, under accident situations,

should not be used for safety analysis purposes, despite the fact that they are realistic for

educational training.

1.4. STRUCTURE

The publication is divided into three sections. The first section provides the background

information along with the objectives, scope and structure of the document. The second and

third sections of this manual contain a set of exercises in normal and abnormal operation

respectively in order to help the user understand the working of an iPWR-SMR power plant.

Each exercise is made in the form of a table and contains five columns:

(a) Number of step in the exercise;

(b) Procedure step that indicates the user what has to be done;

(c) The display where the action has to be done;

(d) What is the expected response;

(e) A column where the user could indicate if the step has been done/succesful.

2. SIMULATOR EXERCISES FOR STANDARD OPERATIONS

This section contains the exercises required to allow the user to understand how to operate an

iPWR-SMR nuclear power plant under normal conditions.

In order to understand it, the following exercises are described:

1. Load maneuvering (10%) in turbine leading mode;

2. Load Maneuvering (10%) in reactor leading mode;

3. Reactor power decrease from 100% to 0% in turbine leading mode;

4. Reactor power rise from 0% to 100%;

5. Reactor trip and restart.

Page 12: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

3

Page 13: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

4

2.1

. L

OA

D M

AN

EU

VE

RIN

G (

10

%)

IN T

UR

BIN

E L

EA

DIN

G M

OD

E

The

load

maneu

ver

ing

in t

urb

ine

lead

ing m

ode

oper

atio

n e

xer

cis

e st

eps

are

list

ed i

n T

able

1.

TA

BL

E 1

. L

OA

D M

AN

EU

VE

RIN

G (

10%

) IN

TU

RB

INE

LE

AD

ING

MO

DE

(co

nt.

)

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

Set

up

Res

et t

he

sim

ula

tor

to I

C #

1 ‘

100%

BO

L n

atura

l cir

cula

tio

n’

or

IC #

4 ‘

100%

BO

L f

orc

ed c

ircu

lati

on’.

1

Ch

eck

the

follo

win

g v

aria

ble

s ar

e st

able

:

(1)

Neu

tro

n p

ow

er (

%);

(2)

Sta

rt-u

p r

ate

(SU

R)

(dpm

);

(3)

Ther

mal

po

wer

(M

W(t

h))

;

(4)

Gen

erat

or

load

(M

W(e

));

(5)

Co

ntr

ol ro

d p

osi

tio

n (

step

s);

(6)

Co

nd

ense

r pre

ssure

(m

mH

g);

(7)

Ste

am p

ress

ure

(M

Pa)

;

(8)

FW

flo

w (

kg/s

);

(9)

FW

tem

per

ature

(ºC

);

(10)

Tavg (

ºC);

(11)

Pre

ssu

rize

r pre

ssure

(M

Pa)

;

(12)

Pre

ssu

rize

r le

vel (%

).

Over

vie

w

Ro

d p

osi

tio

n

contr

ol

All

var

iable

s st

able

at:

(1)

100%

;

(2)

0 d

pm

;

(3)

150 M

W(t

h);

(4)

45 M

W(e

);

(5)

80 s

teps;

(6)

47.3

mm

Hg

;

(7)

2.7

MP

a;

(8)

78 k

g/s

;

(9)

173ºC

;

(10)

287.5

ºC;

(11)

15.5

MP

a;

(12)

43%

.

2

Ver

ify p

lant

mo

de

is i

n t

urb

ine

lead

ing m

ode.

R

od p

osi

tio

n

contr

ol

S

ele

cto

r in

turb

ine

lead

ing m

ode.

Page 14: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

5

TA

BL

E 1

. L

OA

D M

AN

EU

VE

RIN

G (

10%

) IN

TU

RB

INE

LE

AD

ING

MO

DE

(co

nt.

)

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

3

Sta

rt t

urb

ine

load

red

uct

ion t

o 9

0%

:

(1)

Intr

od

uce

tu

rbin

e lo

ad d

em

and (

40.5

MW

)

and

tu

rbin

e lo

ad r

ate

(2 M

W/m

in);

(2)

Sta

rt t

urb

ine

load

change

push

ing G

O;

(3)

Ch

eck

tu

rbin

e valv

es

beg

in t

o c

lose

;

(4)

Ch

eck

gen

erat

or

load

beg

ins

to lo

wer

.

Turb

ine

contr

ol

In

tro

duce

d v

alu

es

appea

r co

rrec

tly;

T

urb

ine

valv

es b

egin

to

clo

se;

G

ener

ato

r lo

ad (

GE

NP

T02_C

E)

beg

ins

to c

hange.

4

Bo

rate

R

CS

to

co

mpensa

te

for

the

po

wer

defe

ct,

Xe

conce

ntr

atio

n

and

rod

po

siti

on

reac

tiv

ity c

hang

es (

opti

onal)

:

(1)

Intr

od

uce

the

new

bo

ron c

once

ntr

atio

n

setp

oin

t (m

ax 2

0 p

pm

per

bad

ge)

;

(2)

Pla

ce s

ele

cto

r in

‘bo

rati

on’;

(3)

Ch

eck

bo

ron c

once

ntr

atio

n i

ncr

ease

s to

the

bo

ron c

once

ntr

atio

n s

etpo

int;

(4)

Rep

eat

1. an

d 3

. as

des

ired

;

(5)

Pla

ce s

ele

cto

r in

‘O

FF

’.

Co

re

In

tro

duce

d v

alu

es

appea

r co

rrec

tly;

B

oro

n c

once

ntr

atio

n (

RC

S_B

C)

beg

ins

to r

ise;

N

eutr

on p

ow

er (

RC

SN

P01_T

R)

low

ers.

5

Ch

eck

main

ste

am

flo

w b

egin

s to

lo

wer

due

to

turb

ine

load

red

uct

ion.

FW

co

ntr

ol

S

team

lin

e fl

ow

s (M

SS

FT

01_T

R

and M

SS

FT

02_T

R)

low

er;

R

efe

rence

tem

per

ature

beg

ins

to

low

er.

6

Ver

ify co

ntr

ol

rod

s m

ove ac

cord

ing to

T

avg -

Tre

f d

evia

tio

n.

Ro

d p

osi

tio

n

contr

ol

C

ontr

ol ro

d p

osi

tio

n c

hang

es;

N

eutr

on p

ow

er (

RC

SN

P01_T

R)

low

ers.

Page 15: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

6

TA

BL

E 1

. L

OA

D M

AN

EU

VE

RIN

G (

10%

) IN

TU

RB

INE

LE

AD

ING

MO

DE

(co

nt.

)

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

7

Ch

eck

the

follo

win

g:

(1) P

ZR

level

beg

ins

to lo

wer

due

to c

oo

lant

contr

acti

on

;

(2) P

ZR

level

contr

ol re

cover

s P

ZR

level.

PZ

R l

evel

contr

ol

P

ZR

level

(RC

SL

T02_T

R)

beg

ins

to

low

er.

8

Ther

mal

po

wer

(M

W(t

h))

lo

wer

s ac

cord

ing t

o

gen

erat

or

load

(M

W(e

)).

Over

vie

w

N

eutr

on p

ow

er (

RC

SN

P01_T

R)

and

gen

erat

or

load

change

at s

imil

ar

rate

s.

9

Once

tu

rbin

e lo

ad d

em

and (

40.5

MW

) has

bee

n

reac

hed

, v

erif

y t

her

e is

no

furt

her

change.

Over

vie

w

G

ener

ato

r lo

ad (

GE

NP

T02_C

E)

sett

les

at t

urb

ine

load

dem

and.

10

Ch

eck

th

at

neu

tro

n

po

wer

se

ttle

s at

co

rrec

t

valu

e (

90

%)

and

ver

ify u

sing

sur

(dp

m)

ther

e is

no

fu

rther

chang

e.

Co

re

N

eutr

on p

ow

er (

RC

SN

P01_T

R)

sett

les

at c

orr

ect

valu

e.

Page 16: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

7

TA

BL

E 1

. L

OA

D M

AN

EU

VE

RIN

G (

10%

) IN

TU

RB

INE

LE

AD

ING

MO

DE

(co

nt.

)

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

11

Ch

eck

the

follo

win

g v

aria

ble

s ar

e st

able

:

(1)

Neu

tro

n p

ow

er (

%);

(2)

Sta

rt-u

p r

ate

(SU

R)

(dpm

);

(3)

Ther

mal

po

wer

(M

W(t

h))

;

(4)

Tu

rbin

e lo

ad(M

W(e

));

(5)

Co

ntr

ol ro

d p

osi

tio

n (

step

s);

(6)

Co

nd

ense

r p

ress

ure

(m

mH

g);

(7)

Ste

am p

ress

ure

(M

Pa)

;

(8)

FW

flo

w (

kg

/s);

(9)

FW

tem

per

atu

re (

ºC);

(10

) T

avg (

ºC);

(11

) P

ress

uri

zer

pre

ssure

(M

Pa)

;

(12

) P

ress

uri

zer

level (%

).

Over

vie

w

All

var

iable

s st

able

at:

(1)

90%

;

(2)

0 d

pm

;

(3)

135 M

W(t

h);

(4)

40.5

MW

(e);

(5)

~74 s

teps;

(6)

47.3

mm

Hg

;

(7)

~2.7

MP

a;

(8)

71 k

g/s

;

(9)

172ºC

;

(10) 2

83.6

ºC;

(11) 1

5.5

MP

a;

(12) 4

1%

.

12

Ver

ify p

lant

mo

de

is i

n t

urb

ine

lead

ing m

ode.

R

od p

osi

tio

n

contr

ol

S

ele

cto

r in

turb

ine

lead

ing m

ode.

13

Rais

e tu

rbin

e lo

ad t

o 1

00%

:

(1)

Intr

od

uce

tu

rbin

e lo

ad d

em

and (

45 M

W)

and

tu

rbin

e lo

ad r

ate

(2 M

W/m

in);

(2)

Sta

rt t

urb

ine

load

change

push

ing G

O;

(3)

Ch

eck

tu

rbin

e co

ntr

ol valv

e beg

ins

to

op

en;

(4)

Ch

eck

gen

erat

or

load

beg

ins

to r

ise.

Turb

ine

contr

ol

In

tro

duce

d v

alu

es

appea

r co

rrec

tly;

T

urb

ine

contr

ol

valv

e beg

ins

to

open

;

G

ener

ato

r lo

ad (

GE

NP

T02_C

E)

beg

ins

to r

ise.

Page 17: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

8

TA

BL

E 1

. L

OA

D M

AN

EU

VE

RIN

G (

10%

) IN

TU

RB

INE

LE

AD

ING

MO

DE

(co

nt.

)

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

14

Dil

ute

RC

S t

o c

om

pensa

te f

or

the

po

wer

def

ect

,

Xe

conce

ntr

atio

n

and

rod

po

siti

on

reac

tivit

y

chang

es (

opti

onal)

:

(1)

Intr

od

uce

the

new

bo

ron c

once

ntr

atio

n

setp

oin

t (m

ax 2

0 p

pm

per

bad

ge)

;

(2)

Pla

ce s

ele

cto

r in

‘d

iluti

on’;

(3)

Ch

eck

bo

ron c

once

ntr

atio

n d

ecre

ases

to

the

bo

ron c

once

ntr

atio

n s

etpo

int;

(4)

Rep

eat

(1)

and

(3)

as d

esir

ed;

(5)

Pla

ce s

ele

cto

r in

‘O

FF

’.

Co

re

In

tro

duce

d v

alu

es

appea

r co

rrec

tly;

B

oro

n c

once

ntr

atio

n (

RC

S_B

C)

beg

ins

to lo

wer

.

15

Ch

eck

main

ste

am

flo

w b

egin

s to

ris

e due t

o a

n

incr

ease

in t

urb

ine

load

.

FW

co

ntr

ol

M

ain

ste

am

flo

w (

MS

SF

T01_T

R

and M

SS

FT

02_T

R)

rise

s;

R

efe

rence

tem

per

ature

beg

ins

to

rise

.

16

If

use

r is

no

t dil

uti

ng,

ver

ify

contr

ol

rods

wit

hd

raw

in o

rder

to m

atch

Tavg w

ith T

ref.

Ro

d p

osi

tio

n

contr

ol

C

ontr

ol ro

d p

osi

tio

n c

hang

es;

N

eutr

on p

ow

er (

RC

SN

P01_T

R)

incr

ease

s.

17

Ch

eck

the

follo

win

g:

(1)

PZ

R l

evel

beg

ins

to r

ise

due

to c

oo

lant

exp

an

sio

n;

(2)

PZ

R l

evel

contr

ol re

cover

s P

ZR

level.

PZ

R L

evel

contr

ol

P

ZR

level

(RC

SL

T02_T

R)

beg

ins

to

rise

.

Page 18: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

9

TA

BL

E 1

. L

OA

D M

AN

EU

VE

RIN

G (

10%

) IN

TU

RB

INE

LE

AD

ING

MO

DE

(co

nt.

)

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

18

Ther

mal

po

wer

(M

W(t

h))

ri

ses

acco

rdin

g

to

Gen

erat

or

load

(M

W((

e))

Over

vie

w

N

eutr

on p

ow

er (

RC

SN

P01_T

R)

and

gen

erat

or

load

(G

EN

PT

02_C

E)

chang

ing a

t si

mil

ar r

ates

.

19

Once

tu

rbin

e lo

ad s

etpo

int

(45 M

W)

has

bee

n

reac

hed

, v

erif

y t

her

e is

no

furt

her

change.

Over

vie

w

G

ener

ato

r lo

ad (

GE

NP

T02_C

E)

sett

les

at t

urb

ine

load

set

po

int.

20

Ch

eck

th

at

neu

tro

n

po

wer

se

ttle

s at

co

rrec

t

valu

e (1

00

%)

and

ver

ify

usi

ng

S

UR

(d

pm

)

ther

e is

no

fu

rther

change.

Co

re

N

eutr

on p

ow

er (

RC

SN

P01_T

R)

sett

les

at c

orr

ect

valu

e.

Page 19: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

10

2.2

. L

OA

D M

AN

EU

VE

RIN

G (

10

%)

IN R

EA

CT

OR

LE

AD

ING

MO

DE

The

load

maneu

ver

ing

in r

eact

or

lead

ing m

ode

oper

atio

n e

xer

cis

e st

eps

are

list

ed i

n T

able

2.

TA

BL

E 2

. L

OA

D M

AN

EU

VE

RIN

G (

10%

) IN

RE

AC

TO

R L

EA

DIN

G M

OD

E (

cont.

)

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

Set

up

Res

et t

he

sim

ula

tor

to I

C #

1 ‘

100%

BO

L n

atura

l cir

cula

tio

n’

or

IC #

4 ‘

100%

BO

L f

orc

ed c

ircu

lati

on’.

1

Ch

eck

the

follo

win

g v

aria

ble

s ar

e st

able

:

(1)

Neu

tro

n p

ow

er (

%);

(2)

Sta

rt-u

p r

ate

(SU

R)

(dpm

);

(3)

Ther

mal

po

wer

(M

W(t

h))

;

(4)

Gen

erat

or

load

(M

W(e

));

(5)

Co

ntr

ol ro

d p

osi

tio

n (

step

s);

(6)

Co

nd

ense

r p

ress

ure

(m

mH

g);

(7)

Ste

am p

ress

ure

(M

Pa)

;

(8)

FW

flo

w (

kg

/s);

(9)

FW

tem

per

atu

re (

ºC);

(10

) T

avg (

ºC);

(11

) P

ress

uri

zer

pre

ssure

(M

Pa)

;

(12

) P

ress

uri

zer

level (%

).

Over

vie

w

Ro

d p

osi

tio

n

contr

ol

All

var

iable

s st

able

at:

1.

100%

;

2.

0 d

pm

;

3.

150 M

W(t

h);

4.

45 M

W(e

);

5.

80 s

teps;

6.

47.3

mm

Hg

;

7.

2.7

MP

a;

8.

78 k

g/s

;

9.

173ºC

;

10.

287.5

ºC;

11.

15.5

MP

a;

12.

43%

.

2

Ensu

re p

lant

mo

de

is i

n r

eact

or

lead

ing m

ode.

R

od p

osi

tio

n

contr

ol

S

ele

cto

r in

rea

ctor

lead

ing m

ode.

Page 20: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

11

TA

BL

E 2

. L

OA

D M

AN

EU

VE

RIN

G (

10%

) IN

RE

AC

TO

R L

EA

DIN

G M

OD

E (

cont.

)

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

3

Sta

rt r

eact

or

po

wer

red

uct

ion t

o 9

0%

:

(1)

Intr

oduce

des

ired

rea

ctor

pow

er d

emand (

90%

)

and r

eact

or

pow

er r

ate

(2%

/min

);

(2)

Sta

rt r

eact

or

pow

er c

hange

push

ing G

O;

(3)

Chec

k c

ontr

ol

rods

beg

in t

o i

nse

rt.

Ro

d p

osi

tio

n

contr

ol

In

tro

duce

d v

alu

es

appea

r co

rrec

tly;

C

ontr

ol ro

d p

osi

tio

n c

hang

es.

4

Bo

rate

R

CS

to

co

mpensa

te

for

the

po

wer

defe

ct,

Xe

conce

ntr

atio

n

and

rod

po

siti

on

reac

tiv

ity c

hang

es (

opti

onal)

:

(1)

Intr

od

uce

the

new

bo

ron c

once

ntr

atio

n

setp

oin

t (m

ax 2

0 p

pm

per

bad

ge)

;

(2)

Pla

ce s

ele

cto

r in

‘bo

rati

on’;

(3)

Ch

eck

bo

ron c

once

ntr

atio

n i

ncr

ease

s to

the

bo

ron c

once

ntr

atio

n s

etpo

int;

(4)

Rep

eat

(1)

and (

3)

as d

esir

ed;

(5)

Pla

ce s

ele

cto

r in

‘O

FF

’.

Co

re

In

tro

duce

d v

alu

es

appea

r co

rrec

tly;

B

oro

n c

once

ntr

atio

n (

RC

S_B

C)

beg

ins

to r

ise;

N

eutr

on p

ow

er (

RC

SN

P01_T

R)

low

ers.

5

Ch

eck

main

ste

am

oper

atio

n:

(1)

Ch

eck

flo

w i

n b

oth

main

ste

am

lin

es

beg

ins

to lo

wer

;

(2)

Ch

eck

tu

rbin

e co

ntr

ol valv

e beg

ins

to

clo

se.

FW

co

ntr

ol

M

ain

ste

am

flo

w (

MS

SF

T01_T

R

and M

SS

FT

02_T

R)

low

ers;

T

urb

ine

contr

ol

valv

e clo

ses.

Page 21: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

12

TA

BL

E 2

. L

OA

D M

AN

EU

VE

RIN

G (

10%

) IN

RE

AC

TO

R L

EA

DIN

G M

OD

E (

cont.

)

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

6

Ch

eck

the

follo

win

g:

(1)

PZ

R l

evel

beg

ins

to lo

wer

due

to c

oo

lant

contr

acti

on

;

(2)

PZ

R l

evel

contr

ol re

cover

s P

ZR

level.

PZ

R l

evel

contr

ol

P

ZR

level

(RC

SL

T02_T

R)

beg

ins

to

low

er.

7

Ver

ify

gen

erat

or

load

(M

W(e

))

dec

reas

es

acco

rdin

g t

o t

her

mal po

wer

(M

W(t

h))

.

Over

vie

w

T

her

mal

po

wer

(R

CS

_T

P_M

W)

and

gen

erat

or

load

(G

EN

PT

02_C

E)

chang

ing a

t si

mil

ar r

ates

.

8

Once

re

acto

r p

ow

er

reac

hes

re

acto

r po

wer

dem

and

(9

0%

),

ver

ify

ther

e is

no

fu

rther

chang

e.

Co

re

N

eutr

on p

ow

er (

RC

SN

P01_T

R)

~90%

.

9

Ch

eck

that

turb

ine

load

set

tles

aro

und 4

0 M

W.

Over

vie

w

G

ener

ato

r lo

ad (

GE

NP

T02_C

E)

~

40 M

W.

Page 22: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

13

TA

BL

E 2

. L

OA

D M

AN

EU

VE

RIN

G (

10%

) IN

RE

AC

TO

R L

EA

DIN

G M

OD

E (

cont.

)

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

10

Ch

eck

the

follo

win

g v

aria

ble

s ar

e st

able

:

(1)

Neu

tro

n p

ow

er (

%);

(2)

Sta

rt-u

p r

ate

(SU

R)

(dpm

);

(3)

Ther

mal

po

wer

(M

W(t

h))

;

(4)

Tu

rbin

e lo

ad(M

W(e

));

(5)

Co

ntr

ol ro

d p

osi

tio

n (

step

s);

(6)

Co

nd

ense

r p

ress

ure

(m

mH

g);

(7)

Ste

am p

ress

ure

(M

Pa)

;

(8)

FW

flo

w (

kg

/s);

(9)

FW

tem

per

atu

re (

ºC);

(10

) T

avg (

ºC);

(11

) P

ress

uri

zer

pre

ssure

(M

Pa)

;

(12

) P

ress

uri

zer

level (%

).

Over

vie

w

All

var

iable

s st

able

at:

(1)

90%

;

(2)

0 d

pm

;

(3)

135 M

W(t

h);

(4)

40.5

MW

(e);

(5)

~74 s

teps;

(6)

47.3

mm

Hg

;

(7)

~2.7

MP

a;

(8)

71 k

g/s

;

(9)

172ºC

;

(10) 2

83.6

ºC;

(11) 1

5.5

MP

a;

(12) 4

1%

.

11

Ver

ify p

lant

mo

de

is i

n r

eact

or

lead

ing m

ode.

R

od p

osi

tio

n

contr

ol

S

ele

cto

r in

rea

ctor

lead

ing m

ode.

12

Sta

rt r

eact

or

po

wer

incr

ease

to 1

00%

:

(1)

Intr

od

uce

des

ired

rea

cto

r po

wer

dem

and

(10

0%

) an

d r

eact

or

po

wer

rat

e (2

%/m

in);

(2)

Sta

rt r

eact

or

po

wer

chan

ge

push

ing G

O;

(3)

Ver

ify c

ontr

ol ro

ds

beg

in t

o w

ithdra

w.

Ro

d p

osi

tio

n

contr

ol

In

tro

duce

d v

alu

es

appea

r co

rrec

tly;

C

ontr

ol ro

d p

osi

tio

n c

hang

es.

Page 23: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

14

TA

BL

E 2

. L

OA

D M

AN

EU

VE

RIN

G (

10%

) IN

RE

AC

TO

R L

EA

DIN

G M

OD

E (

cont.

)

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

13

Dil

ute

RC

S t

o c

om

pensa

te f

or

the

po

wer

def

ect

,

Xe

conce

ntr

atio

n

and

rod

po

siti

on

reac

tivit

y

chang

es:

(1)

Intr

od

uce

the

new

bo

ron c

once

ntr

atio

n

setp

oin

t (m

ax 2

0 p

pm

per

bad

ge)

;

(2)

Pla

ce s

ele

cto

r in

‘d

iluti

on’;

(3)

Ch

eck

bo

ron c

once

ntr

atio

n d

ecre

ases

to

the

bo

ron c

once

ntr

atio

n s

etpo

int;

(4)

Rep

eat

1. an

d 3

. as

des

ired

;

(5)

Pla

ce s

ele

cto

r in

‘O

FF

’.

Co

re

In

tro

duce

d v

alu

es

appea

r co

rrec

tly;

B

oro

n c

once

ntr

atio

n (

RC

S_B

C)

beg

ins

to lo

wer

.

14

Ch

eck

main

ste

am

oper

atio

n:

(1)

Ch

eck

flo

w i

n b

oth

main

ste

am

lin

es

beg

ins

to r

ise;

(2)

Ch

eck

tu

rbin

e co

ntr

ol valv

e beg

ins

to

op

en.

FW

co

ntr

ol

M

ain

ste

am

flo

w (

MS

SF

T01_T

R

and M

SS

FT

02_T

R)

low

ers;

T

urb

ine

contr

ol

valv

e o

pen

s.

15

Ch

eck

PZ

R l

ev

el

beg

ins

to r

ise d

ue t

o c

oo

lant

exp

an

sio

n a

nd

ho

w l

evel

contr

ol

reco

ver

s P

ZR

level.

PZ

R l

evel

contr

ol

P

ZR

level

(RC

SL

T02_T

R)

beg

ins

to

rise

.

16

Ver

ify

gener

ato

r lo

ad

(MW

(e))

is

in

crea

sing

acco

rdin

g t

o t

her

mal po

wer

(M

W(t

h))

.

Over

vie

w

T

her

mal

po

wer

(R

CS

_T

P_M

W)

and

gen

erat

or

load

(G

EN

PT

02_C

E)

chang

ing a

t si

mil

ar r

ates

.

Page 24: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

15

TA

BL

E 2

. L

OA

D M

AN

EU

VE

RIN

G (

10%

) IN

RE

AC

TO

R L

EA

DIN

G M

OD

E (

cont.

)

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

17

Once

re

acto

r p

ow

er

reac

hes

re

acto

r po

wer

dem

and

(1

00

%),

ver

ify

ther

e is

no

fu

rther

chang

e.

Co

re

N

eutr

on p

ow

er (

RC

SN

P01_T

R)

sett

les

at 1

00%

.

18

Ch

eck

that

tu

rbin

e lo

ad s

ettl

es a

t co

rrec

t valu

e

(45

MW

).

Over

vie

w

G

ener

ato

r lo

ad (

GE

NP

T02_C

E)

sett

les

at 4

5 M

W.

Page 25: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

16

2.3

. R

EA

CT

OR

PO

WE

R D

EC

RE

AS

E F

RO

M 1

00%

TO

0%

The

reac

tor

po

wer

dec

reas

e o

per

atio

n e

xer

cis

e st

eps

are

list

ed i

n T

able

3.

TA

BL

E 3

. R

EA

CT

OR

PO

WE

R D

EC

RE

AS

E F

RO

M 1

00%

TO

0%

(co

nt.

)

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

Set

up

Res

et t

he

sim

ula

tor

to I

C #

1 ‘

100%

BO

L n

atura

l cir

cula

tio

n’

or

IC #

4 ‘

100%

BO

L f

orc

ed c

ircu

lati

on’.

1

Ch

eck

the

follo

win

g v

aria

ble

s ar

e st

able

:

(1)

Neu

tro

n p

ow

er (

%);

(2)

Sta

rt-u

p r

ate

(SU

R)

(dpm

);

(3)

Ther

mal

po

wer

(M

W(t

h))

;

(4)

Gen

erat

or

load

(M

W(e

));

(5)

Co

ntr

ol ro

d p

osi

tio

n (

step

s);

(6)

Co

nd

ense

r p

ress

ure

(m

mH

g);

(7)

Ste

am p

ress

ure

(M

Pa)

;

(8)

FW

flo

w (

kg

/s);

(9)

FW

tem

per

atu

re (

ºC);

(10

) T

avg (

ºC);

(11

) P

ress

uri

zer

pre

ssure

(M

Pa)

;

(12

) P

ress

uri

zer

level (%

).

Over

vie

w

Ro

d p

osi

tio

n

contr

ol

All

var

iable

s st

able

at:

(1)

100%

;

(2)

0 d

pm

;

(3)

150 M

W(t

h);

(4)

45 M

W(e

);

(5)

80 s

teps;

(6)

47.3

mm

Hg

;

(7)

2.7

MP

a;

(8)

78 k

g/s

;

(9)

173ºC

;

(10) 2

87.5

ºC;

(11) 1

5.5

MP

a;

(12) 4

3%

.

Page 26: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

17

TA

BL

E 3

. R

EA

CT

OR

PO

WE

R D

EC

RE

AS

E F

RO

M 1

00%

TO

0%

(co

nt.

)

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

2

Ver

ify p

rop

er s

tatu

s o

f th

e m

ain

pla

nt

contr

ols

:

(1)

Ver

ify p

lant

mo

de

is i

n t

urb

ine

lead

ing

mo

de;

(2)

Co

ntr

ol ro

ds

in a

uto

;

(3)

MS

B i

n T

avg m

ode;

(4)

FW

syst

em

in a

uto

;

(5)

Co

nd

ense

r an

d c

ircu

lati

ng w

ater

syst

em

s

in s

erv

ice;

(6)

No

act

ive

ala

rms.

P

lant

mo

de

sele

ctor

in t

urb

ine

lead

ing m

ode;

M

SB

sele

cto

r in

Tavg m

ode;

F

W c

ontr

ol

valv

es

(FW

SV

13/F

WS

V14)

in a

uto

;

C

WS

in s

ervic

e (o

pen

or

clo

sed

loo

p).

3

Sta

rt t

urb

ine

load

red

uct

ion t

o 1

5%

:

(1)

Intr

od

uce

tu

rbin

e lo

ad d

em

and (

6.7

5 M

W)

and

tu

rbin

e lo

ad r

ate

(1 M

W/m

in m

ax);

(2)

Sta

rt t

urb

ine

load

change

push

ing G

O;

(3)

Ch

eck

tu

rbin

e co

ntr

ol valv

es b

egin

to

clo

se;

(4)

Ch

eck

gen

erat

or

load

beg

ins

to lo

wer

.

Turb

ine

contr

ol

In

tro

duce

d v

alu

es

appea

r co

rrec

tly;

T

urb

ine

contr

ol

valv

e beg

ins

to

clo

se;

G

ener

ato

r lo

ad (

GE

NP

T02_C

E)

beg

ins

to c

hange.

Page 27: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

18

TA

BL

E 3

. R

EA

CT

OR

PO

WE

R D

EC

RE

AS

E F

RO

M 1

00%

TO

0%

(co

nt.

)

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

4

Co

nti

nu

ou

s

acti

on

Bo

rate

R

CS

to

co

mpensa

te

for

the

po

wer

defe

ct,

Xe

conce

ntr

atio

n

and

rod

po

siti

on

reac

tiv

ity c

hang

es:

(1)

Intr

od

uce

the

new

bo

ron c

once

ntr

atio

n

setp

oin

t (m

ax 2

0 p

pm

per

bad

ge)

;

(2)

Pla

ce s

ele

cto

r in

‘bo

rati

on’;

(3)

Ch

eck

bo

ron c

once

ntr

atio

n i

ncr

ease

s to

the

bo

ron c

once

ntr

atio

n s

etpo

int;

(4)

Rep

eat

1. an

d 3

. as

des

ired

;

(5)

Pla

ce s

ele

cto

r in

‘O

FF

’.

Co

re

In

tro

duce

d v

alu

es

appea

r co

rrec

tly;

B

oro

n c

once

ntr

atio

n (

RC

S_B

C)

beg

ins

to r

ise.

NO

TE

I sh

ou

ld b

e co

ntr

olled

as

follo

ws:

(a)

If ∆

I is

at

the

left

sid

e o

f th

e ta

rget

ban

d,

rods

are

exce

ssiv

ely

inse

rted

. T

his

means

that

ro

ds

dep

ress

neu

tro

n f

lux i

n t

he

up

per

half

of

the

core

and f

orc

e a

hig

h f

lux t

o e

xis

t in

the

low

er h

alf

. T

o m

ake

∆I

retu

rn t

o t

he

targ

et b

and,

bo

rate

the

RC

S t

o m

ake

rods

wit

hdra

w f

rom

the

core

;

(b)

If ∆

I is

at

the

rig

ht

sid

e o

f th

e ta

rget

ban

d,

rods

are

exces

sively

wit

hdra

wn.

This

mea

ns

that

a h

igher

flu

x e

xis

ts i

n t

he

up

per

half

of

the

core

co

mpar

ed t

o t

he

low

er h

alf

. T

o m

ake

∆I

retu

rn t

o t

he

targ

et b

and,

dil

ute

the

RC

S t

o m

ake

rods

inse

rt into

the

core

.

5

Co

nti

nu

ou

s

acti

on

Ch

eck

that

∆I

is m

ain

tain

ed w

ithin

the

targ

et

band

if

reac

tor

po

wer

is

abo

ve

50%

.

Co

re

I st

ays

wit

hin

the

targ

et b

and.

Page 28: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

19

TA

BL

E 3

. R

EA

CT

OR

PO

WE

R D

EC

RE

AS

E F

RO

M 1

00%

TO

0%

(co

nt.

)

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

6

Ch

eck

main

ste

am

flo

w b

egin

s to

lo

wer

due

to

turb

ine

load

red

uct

ion.

Syst

em

s

M

ain

ste

am

flo

w (

MS

SF

T01_T

R

and M

SS

FT

02_T

R)

low

ers;

R

efe

rence

tem

per

ature

beg

ins

to

low

er.

7

Ver

ify c

ontr

ol

rod

s in

sert

in o

rder

to m

atch T

avg

wit

h t

he

new

lo

wer

Tre

f.

Ro

d p

osi

tio

n

contr

ol

C

ontr

ol ro

d p

osi

tio

n c

hang

es;

N

eutr

on p

ow

er (

RC

SN

P01_T

R)

low

ers.

8

Ch

eck

the

follo

win

g:

(1)

PZ

R l

evel

beg

ins

to lo

wer

due

to c

oo

lant

contr

acti

on

;

(2)

PZ

R l

evel

contr

ol re

cover

s P

ZR

level.

PZ

R l

evel

contr

ol

P

ZR

level

(RC

SL

T02_T

R)

beg

ins

to

low

er.

9

Ther

mal

po

wer

(M

W(t

h))

lo

wer

s ac

cord

ing t

o

gen

erat

or

load

(M

W(e

)).

Over

vie

w

N

eutr

on p

ow

er (

RC

SN

P01_T

R)

and

gen

erat

or

load

(G

EN

PT

02_C

E)

chang

e at

sim

ilar

rat

es.

10

Ch

eck

the

follo

win

g:

(1)

FW

pu

mp

sp

eed

lo

wer

ing

;

(2)

FW

flo

w l

ow

erin

g.

FW

Co

ntr

ol

F

low

in b

oth

FW

tra

ins

(FW

SF

T01_T

R a

nd F

WS

FT

02_T

R)

low

erin

g;

F

W p

um

p s

peed

(F

WS

P01)

low

erin

g;

F

W c

ontr

ol

valv

e (F

WS

V17)

clo

sing.

Page 29: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

20

TA

BL

E 3

. R

EA

CT

OR

PO

WE

R D

EC

RE

AS

E F

RO

M 1

00%

TO

0%

(co

nt.

)

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

NO

TE

E

ven i

f C

ontr

ol

rods

wit

hdra

w d

ue

to X

e co

nce

ntr

atio

n i

ncr

easi

ng b

efo

re r

each

ing a

lo

wer

equ

ilib

riu

m c

once

ntr

atio

n,

contr

ol

rod p

osi

tio

n a

nd

SU

R s

ho

uld

sti

ll b

e co

nsi

der

ed s

table

in s

tep 1

1.

11

Ver

ify s

tab

le p

lant

cond

itio

ns:

(1)

Once

tu

rbin

e lo

ad d

em

and (

6.7

5 M

W)

has

bee

n r

eached

, ver

ify t

her

e is

no

furt

her

chang

e;

(2)

Ch

eck

that

ste

p 1

var

iable

s re

main

sta

ble

.

Over

vie

w

G

ener

ato

r lo

ad (

GE

NP

T02_C

E)

sett

les

at t

urb

ine

load

dem

and.

12

Ch

eck

th

at

neu

tro

n

po

wer

se

ttle

s at

co

rrec

t

valu

e (a

rou

nd

22

%).

Ro

d p

osi

tio

n

contr

ol

N

eutr

on p

ow

er (

RC

SN

P01_T

R)

sett

les

at c

orr

ect

valu

e.

13

Sta

rt t

urb

ine

load

red

uct

ion t

o 6

%:

(1)

Intr

od

uce

tu

rbin

e lo

ad (

3 M

W)

and t

urb

ine

load

rat

e (0

.2 M

W/m

in m

ax)

in t

urb

ine

dis

pla

y;

(2)

Sta

rt t

urb

ine

load

change

push

ing G

O;

(3)

Ch

eck

tu

rbin

e co

ntr

ol valv

e beg

ins

to

clo

se;

(4)

Ch

eck

gen

erat

or

load

beg

ins

to lo

wer

.

Turb

ine

contr

ol

In

tro

duce

d v

alu

es

appea

r co

rrec

tly;

T

urb

ine

contr

ol

valv

e beg

ins

to

clo

se;

G

ener

ato

r lo

ad (

GE

NP

T02_C

E)

beg

ins

to c

hange.

14

Ch

eck

re

acto

r po

wer

ch

anges

acco

rdin

g

to

turb

ine

load

red

uct

ion.

Ro

d p

osi

tio

n

contr

ol

C

ontr

ol ro

d p

osi

tio

n c

hang

es.

Page 30: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

21

TA

BL

E 3

. R

EA

CT

OR

PO

WE

R D

EC

RE

AS

E F

RO

M 1

00%

TO

0%

(co

nt.

)

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

15

When t

urb

ine

load

rea

ches

3 M

W:

(1)

Manu

all

y t

rip

the

turb

ine;

(2)

Ver

ify t

urb

ine

trip

;

(3)

Ver

ify s

pee

d i

s lo

wer

ing u

p t

o t

urn

ing g

ear

spee

d (

5 r

pm

).

Syst

em

s

T

urb

ine

iso

lati

on v

alv

e (M

SS

V07)

clo

ses;

G

ener

ato

r bre

aker

open

s;

M

ain

ste

am

flo

w t

o t

urb

ine

(MS

SF

T04_T

R)

go

es t

o z

ero.

16

Ch

eck

MS

B i

s m

ain

tain

ing T

avg a

t no

-lo

ad T

ref.

Syst

em

s

N

on-z

ero f

low

thro

ugh t

urb

ine

bypass

(M

SS

FT

05_T

R).

M

ain

ste

am

pre

ssure

(MS

SP

T03_T

R)

stab

le.

17

When r

eact

or

po

wer

is

3%

, m

anuall

y t

rip t

he

reac

tor.

Ro

d p

osi

tio

n

contr

ol

A

ll c

ontr

ol and s

hutd

ow

n r

ods

at

bo

tto

m;

N

eutr

on p

ow

er (

RC

SN

P01_T

R)

reduce

s to

0%

;

P

lant

mo

de

swit

ches

to

rea

cto

r

lead

ing m

ode

aft

er r

eact

or

trip

.

Page 31: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

22

TA

BL

E 3

. R

EA

CT

OR

PO

WE

R D

EC

RE

AS

E F

RO

M 1

00%

TO

0%

(co

nt.

)

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

18

Ch

eck

th

e var

iable

s fr

om

st

ep

1

rem

ain

const

ant:

(1)

Ther

mal

po

wer

(su

bcr

itic

ali

ty);

(2)

Neu

tro

n p

ow

er (

subcr

itic

ali

ty);

(3)

SU

R (

subcr

itic

ali

ty);

(4)

Pri

mar

y t

em

per

ature

(co

re c

oo

ling);

(5)

Pri

mar

y p

ress

ure

(in

tegri

ty);

(6)

Pri

mar

y l

evel (i

nvento

ry);

(7)

FW

flo

w (

heat

sin

k).

Over

vie

w

Page 32: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

23

TA

BL

E 3

. R

EA

CT

OR

PO

WE

R D

EC

RE

AS

E F

RO

M 1

00%

TO

0%

(co

nt.

)

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

19

Ensu

re t

he

follo

win

g:

(1)

Rea

cto

r po

wer

at

0%

;

(2)

Tu

rbin

e lo

ad a

t 0 M

W;

(3)

Rea

cto

r th

erm

al po

wer

exhau

sted

to

cond

ense

r v

ia M

SB

valv

es;

(4)

Co

ntr

ol ro

ds

tota

lly i

nse

rted

and i

n

manu

al;

(5)

Pla

nt

Mo

de

in r

eact

or

lead

ing m

ode;

(6)

MS

B i

s co

ntr

oll

ing s

eco

ndar

y S

team

pre

ssu

re;

(7)

FW

syst

em

in a

uto

adju

stin

g F

W f

low

;

(8)

CW

syst

em

and c

onden

ser

syst

em

s in

serv

ice;

(9)

Tu

rbin

e sp

eed

(aft

er 3

0 m

inute

s

app

rox

imat

ely

) at

5 r

pm

wit

h t

he

turn

ing

gea

r en

gag

ed.

Over

vie

w

M

SB

co

ntr

ol

in s

wit

ches

to s

team

Pre

ssure

mo

de

afte

r re

acto

r tr

ip;

P

lace

ro

d c

ontr

ol se

lect

or

in m

anu

al.

20

Ch

eck

the

follo

win

g a

larm

co

nd

itio

ns

exis

t:

(1)

Rea

cto

r tr

ip;

(2)

Tu

rbin

e tr

ip;

(3)

Tu

rnin

g g

ear;

(4)

Gen

erat

or

bre

aker

open

;

(5)

Ro

ds

in m

anual.

Page 33: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

24

2.4

. R

EA

CT

OR

PO

WE

R R

ISE

FR

OM

0%

TO

100%

The

reac

tor

po

wer

ris

e fr

om

0%

to

100%

exer

cis

e st

eps

are

list

ed i

n T

able

4.

TA

BL

E 4

. R

EA

CT

OR

PO

WE

R R

ISE

FR

OM

0%

TO

100%

(co

nt.

)

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

Set

up

Res

et t

he

sim

ula

tor

to I

C #

7 ‘

0%

BO

L,

NC

, befo

re r

od w

ithdra

wal’

or

IC #

10 ‘

0%

BO

L,

FC

, befo

re r

od w

ithdra

wal’

.

1

Ch

eck

the

follo

win

g v

aria

ble

s ar

e st

able

:

(1)

Ther

mal

po

wer

(su

bcr

itic

ali

ty);

(2)

Neu

tro

n p

ow

er (

subcr

itic

ali

ty);

(3)

SU

R (

subcr

itic

ali

ty);

(4)

Pri

mar

y t

em

per

ature

(co

re c

oo

ling);

(5)

Pri

mar

y p

ress

ure

(in

tegri

ty);

(6)

Pri

mar

y l

evel (i

nvento

ry);

(7)

FW

flo

w (

heat

sin

k).

Over

vie

w

All

var

iable

s st

able

at:

(1)

1.5

9 M

W(t

h);

(2)

0%

;

(3)

0 d

pm

;

(4)

~ 2

48ºC

(te

ndin

g t

o 2

50ºC

= T

ref,

0-

load);

(5)

15.5

MP

a;

(6)

~ 2

3%

;

(7)

~ 0

.02 k

g/s

;

2

Ensu

re p

rop

er s

tatu

s o

f th

e m

ain

pla

nt

contr

ols

:

(1)

Pla

nt

mo

de

in r

eact

or

lead

ing m

ode;

(2)

Ro

d c

ontr

ol

in m

anu

al;

(3)

MS

B i

s co

ntr

oll

ing s

team

pre

ssure

;

(4)

FW

syst

em

in a

uto

;

(5)

CW

and

CN

R s

yst

em

s in

ser

vic

e;

(6)

FW

co

ntr

ol ad

just

ing F

W f

low

.

P

lant

mo

de

sele

ctor

in r

eact

or

lead

ing m

ode;

R

od c

ontr

ol se

lect

or

in m

anu

al

mo

de;

S

ele

cto

r in

ste

am

pre

ssure

mo

de;

F

W c

ontr

ol

valv

es

(FW

SV

13/F

WS

V14)

in a

uto

;

C

W s

yst

em

in s

ervic

e (o

pen

ed o

r

clo

sed l

oo

p).

Page 34: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

25

TA

BL

E 4

. R

EA

CT

OR

PO

WE

R R

ISE

FR

OM

0%

TO

100%

(co

nt.

)

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

3

Ch

eck

the

follo

win

g a

larm

co

nd

itio

ns

exis

t:

(1)

Rea

cto

r tr

ip;

(2)

Tu

rbin

e tr

ip;

(3)

Tu

rnin

g g

ear

(or

turb

ine

dec

ele

rati

ng);

(4)

Gen

erat

or

bre

aker

open

.

4

Res

et r

eact

or

trip

. T

rip

s

R

eact

or

trip

ala

rm d

eac

tivat

es.

5

Ch

eck

bo

ron c

once

ntr

atio

n s

table

. C

ore

6

Wit

hd

raw

sh

utd

ow

n

bank

whil

e m

onit

ori

ng

neu

tro

n f

lux:

(1)

Ensu

re b

ank

A i

s se

lect

ed;

(2)

Pu

sh O

UT

unti

l bank A

is

full

y w

ithdra

wn.

Ro

d p

osi

tio

n

contr

ol

S

hutd

ow

n r

od p

osi

tio

n c

hang

es.

7

Wit

hd

raw

co

ntr

ol

bank

B

whil

e m

onit

ori

ng

neu

tro

n f

lux:

(1)

Ensu

re b

ank

B i

s se

lect

ed;

(2)

Pu

sh O

UT

unti

l bank B

is

full

y w

ithdra

wn.

Ro

d p

osi

tio

n

contr

ol

C

ontr

ol ro

d p

osi

tio

n c

hang

es;

S

ourc

e ra

nge

po

wer

(RC

SN

P03_T

R)

beg

ins

to r

ise

but

stab

ilis

es o

r fa

lls

when r

od

mo

vem

ent

sto

ps.

Page 35: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

26

TA

BL

E 4

. R

EA

CT

OR

PO

WE

R R

ISE

FR

OM

0%

TO

100%

(co

nt.

)

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

8

Wit

hd

raw

co

ntr

ol

bank

C

to

the

esti

mat

ed

crit

ical

cond

itio

n w

hil

e m

onit

ori

ng n

eutr

on f

lux

for

crit

icality

:

(1)

Ensu

re b

ank

C i

s se

lect

ed;

(2)

Pu

sh O

UT

unti

l bank C

rea

ches

49 s

teps.

Ro

d p

osi

tio

n

contr

ol

C

ontr

ol ro

d p

osi

tio

n c

hang

es;

S

ourc

e ra

nge

po

wer

(RC

SN

P03_T

R)

beg

ins

to r

ise

but

stab

ilis

es o

r fa

lls

when r

od

mo

vem

ent

sto

ps.

9

Dil

ute

RC

S f

or

crit

icali

ty:

(1)

Intr

od

uce

the

new

bo

ron c

once

ntr

atio

n

setp

oin

t (m

ax 2

0 p

pm

per

bad

ge)

;

(2)

Pla

ce s

ele

cto

r in

‘d

iluti

on’;

(3)

Ch

eck

bo

ron c

once

ntr

atio

n d

ecre

ases

to

the

bo

ron c

once

ntr

atio

n s

etpo

int;

(4)

Rep

eat

1. an

d 3

. unti

l neu

tro

n f

lux s

low

ly

rise

s w

itho

ut

contr

ol ro

d m

ovem

ent

(cri

ticality

obse

rved

). P

lot

neu

tro

n p

ow

er

and

SU

R;

(5)

Pla

ce s

ele

cto

r in

‘O

FF

’.

Co

re

In

tro

duce

d v

alu

es

appea

r co

rrec

tly;

B

oro

n c

once

rtat

ion (

RC

S_B

C)

beg

ins

to lo

wer

;

W

hen c

riti

cal, n

eutr

on p

ow

er

(RC

SN

P01_T

R)

rise

s sl

ow

ly

wit

ho

ut

contr

ol ro

d m

ovem

ent;

P

oin

t o

f ad

din

g h

eat

occ

urs

when

inte

rmed

iate

ran

ge

~ 1

0E

-8.

NO

TE

A

bo

ve

the

po

int

of

add

ing h

eat,

SU

R s

ho

uld

no

t ex

ceed

a s

ust

ain

ed 0

.5 d

pm

.

10

Rais

e r

eact

or

po

wer

to

8%

wit

h r

od c

ontr

ol

in

manu

al.

Ro

d p

osi

tio

n

contr

ol

C

ontr

ol ro

d p

osi

tio

n c

hang

es;

N

eutr

on p

ow

er (

RC

SN

P01_T

R)

rise

s an

d s

tabil

ises

at

8%

.

Page 36: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

27

TA

BL

E 4

. R

EA

CT

OR

PO

WE

R R

ISE

FR

OM

0%

TO

100%

(co

nt.

)

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

11

Rais

e R

ract

or

po

wer

to

15%

wit

h r

od c

ontr

ol

in

auto

(1)

Ver

ify p

lant

mo

de

is i

n r

eact

or

lead

ing

mo

de;

(2)

Inse

rt 1

5%

in r

eact

or

po

wer

dem

and a

nd

5%

/min

in r

eact

or

po

wer

rat

e;

(3)

Pre

ss G

O;

(4)

Pla

ce c

ontr

ol ro

ds

in a

uto

.

Ro

d p

osi

tio

n

contr

ol

C

ontr

ol ro

d p

osi

tio

n c

hang

es;

N

eutr

on p

ow

er (

RC

SN

P01_T

R)

rise

s an

d s

tabil

ises

at

15%

.

12

Sta

rt-u

p t

he

turb

ine:

(1)

Res

et t

urb

ine

trip

;

(2)

Ensu

re t

urb

ine

contr

ol

valv

e (M

SS

V07)

is

in a

uto

;

(3)

Pu

sh r

un-u

p;

(4)

Tu

rbin

e co

ntr

ol

valv

e o

pen

s ar

ound 3

%;

(5)

When ‘

read

y t

o s

ync’

lig

ht

appea

rs,

push

‘syn

c’

bu

tto

n t

o c

lose

gen

erat

or

bre

aker

;

(6)

Ch

eck

tu

rbin

e ac

cepts

a m

inim

um

lo

ad;

(7)

Ch

eck

tu

rbin

e co

ntr

ol valv

e is

in m

anu

al.

Turb

ine

contr

ol

T

urb

ine

trip

ala

rm d

eact

ivat

es;

T

urb

ine

contr

ol

valv

e o

pen

s ar

ound

3%

;

T

urb

ine

speed

incr

ease

s

(TU

RC

N01_T

R)

fro

m 5

rp

m t

o

3600rp

m;

T

urn

ing g

ear

and g

ener

ator

bre

aker

ala

rms

cle

ar.

NO

TE

U

po

n c

losi

ng

the

gen

erat

or

bre

aker

, tu

rbin

e lo

ad s

ho

uld

be

rais

ed t

o 3

% t

o p

revent

mo

tori

ng o

f th

e gen

erat

or.

Page 37: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

28

TA

BL

E 4

. R

EA

CT

OR

PO

WE

R R

ISE

FR

OM

0%

TO

100%

(co

nt.

)

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

13

Rais

e tu

rbin

e lo

ad m

anuall

y t

o 3

%

(1)

Manu

all

y o

pen

turb

ine

contr

ol valv

e to

3%

;

(2)

Ch

eck

gen

erat

or

load

beg

ins

to r

ise.

Turb

ine

contr

ol

T

urb

ine

contr

ol

valv

e o

pen

s;

G

ener

ato

r lo

ad (

GE

NP

T02_C

S)

wo

uld

be

aro

und 3

.5 M

W(e

) w

hen

MS

SV

07 i

s 3%

open

;

S

team

thro

ugh M

SB

lo

wer

s.

14

Pla

ce t

urb

ine

contr

ol

in a

uto

:

(1)

Pla

ce t

urb

ine

contr

ol valv

e in

auto

;

(2)

Ch

eck

tu

rbin

e co

ntr

ol

is c

ontr

oll

ing S

team

pre

ssu

re (

pla

nt

mo

de

in r

eact

or

lead

ing).

Syst

em

dis

pla

y

NO

TE

S

wit

chin

g to

tu

rbin

e le

adin

g m

ode

wit

h a

big

te

mper

ature

er

ror

may le

ad to

po

wer

o

scil

lati

ons

and tu

rbin

e tr

ip (r

eact

or

po

wer

<4

%).

15

If t

em

per

atu

re e

rro

r is

gre

ater

than

2.5

0ºC

:

(1)

Pla

ce r

od

co

ntr

ol

in m

anu

al;

(2)

Rep

osi

tio

n b

ank C

to m

ake

tem

per

ature

erro

r le

ss t

han

2.8

0ºC

;

(3)

Ch

ang

e p

lant

mo

de

to t

urb

ine

lead

ing

mo

de;

(4)

Ch

eck

MS

B m

ode

to T

avg m

ode;

(5)

Go

to

Ste

p 1

8.

Ro

d p

osi

tio

n

contr

ol

Turb

ine

bypas

s

contr

ol

T

avg –

Tre

f devia

tio

n c

orr

ecti

on (

aft

er

mo

vin

g b

ank C

) w

ill

only

last

fo

r a

few

sec

ond

s.

16

Ch

ang

e p

lant

mo

de

to

turb

ine

lead

ing

mo

de

when e

rro

r is

less

than 2

.5ºC

.

Ro

d p

osi

tio

n

contr

ol

P

lace

sele

ctor

in t

urb

ine

lead

ing

mo

de.

Page 38: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

29

TA

BL

E 4

. R

EA

CT

OR

PO

WE

R R

ISE

FR

OM

0%

TO

100%

(co

nt.

)

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

17

Ch

eck

MS

B m

od

e to

Tavg m

ode.

T

urb

ine

bypas

s

contr

ol

M

SB

sele

cto

r in

Tavg m

ode.

18

Rais

e tu

rbin

e lo

ad t

o f

ull

po

wer

co

nd

itio

ns:

(1)

Intr

od

uce

tu

rbin

e lo

ad d

em

and (

20 M

W)

and

tu

rbin

e lo

ad r

ate

(1 M

W/m

in)

in

turb

ine

dis

pla

y;

(2)

Pre

ss G

O;

(3)

Ch

eck

tu

rbin

e co

ntr

ol valv

e beg

ins

to

op

en;

(4)

Ch

eck

gen

erat

or

load

beg

ins

to r

ise;

(5)

When t

urb

ine

load

rea

ches

20 M

W,

check

step

1 v

aria

ble

s ar

e st

able

;

(6)

Rais

e tu

rbin

e lo

ad t

o 4

5 M

W a

t a

turb

ine

load

rat

e o

f 1

MW

/min

rep

eat

ing s

ubst

eps

18

.1, 1

8.2

, 1

8.3

and 1

8.4

.

Turb

ine

contr

ol

In

tro

duce

d v

alu

es

appea

r co

rrec

tly;

T

urb

ine

valv

es b

egin

to

open

;

G

ener

ato

r lo

ad (

GE

NP

T02_C

S)

beg

ins

to r

ise.

Page 39: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

30

TA

BL

E 4

. R

EA

CT

OR

PO

WE

R R

ISE

FR

OM

0%

TO

100%

(co

nt.

)

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

19

Co

nti

nu

ou

s

acti

on

Dil

ute

RC

S t

o c

om

pensa

te f

or

the

po

wer

def

ect

,

Xe

conce

ntr

atio

n

and

rod

po

siti

on

reac

tivit

y

chang

es:

(1)

Intr

od

uce

the

new

bo

ron c

once

ntr

atio

n

setp

oin

t (m

ax 2

0 p

pm

per

bad

ge)

;

(2)

Pla

ce s

ele

cto

r in

‘d

iluti

on’;

(3)

Ch

eck

bo

ron c

once

ntr

atio

n d

ecre

ases

to

the

bo

ron c

once

ntr

atio

n s

etpo

int;

(4)

Rep

eat

(1)

and (

3)

as r

equir

ed;

(5)

Pla

ce s

ele

cto

r in

‘O

FF

’.

Co

re

In

tro

duce

d v

alu

es

appea

r co

rrec

tly;

B

oro

n c

once

ntr

atio

n (

RC

S_B

C)

beg

ins

to r

ise.

20

Co

nti

nu

ou

s

acti

on

When

bank

C

re

aches

80

step

s (f

ull

y

wit

hd

raw

n):

(1)

Ho

ld t

he

turb

ine

load

by p

ress

ing o

n

HO

LD

in t

he

turb

ine

contr

ol d

isp

lay;

(2)

Dil

ute

the

RC

S t

o r

epo

siti

on b

ank C

;

(3)

Co

nti

nu

e in

crea

sing t

urb

ine

load

by

cli

ckin

g o

n G

O i

n t

he

turb

ine

contr

ol

dis

pla

y.

Ro

d p

osi

tio

n

contr

ol

Co

re

Turb

ine

contr

ol

T

his

ste

p w

ould

no

t no

rmall

y b

e

per

form

ed.

21

Ch

eck

m

ain

ste

am

fl

ow

beg

ins

to r

ise

due

to

rise

in l

oad

in

crea

se.

Turb

ine

contr

ol

M

ain

ste

am

flo

w (

MS

SF

T01_T

R

and M

SS

FT

02_T

R)

rise

s;

R

efe

rence

tem

per

ature

beg

ins

to

rise

.

Page 40: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

31

TA

BL

E 4

. R

EA

CT

OR

PO

WE

R R

ISE

FR

OM

0%

TO

100%

(co

nt.

)

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

22

Ver

ify co

ntr

ol

rod

s w

ithdra

w in

o

rder

to

ris

e

aver

age

tem

per

atu

re.

Ro

d p

osi

tio

n

contr

ol

C

ontr

ol ro

d p

osi

tio

n c

hang

es;

N

eutr

on p

ow

er (

RC

SN

P01_T

R)

incr

ease

s.

23

Ch

eck

PZ

R l

ev

el

beg

ins

to r

ise d

ue t

o c

oo

lant

exp

an

sio

n a

nd

ho

w le

vel

contr

ol

reco

ver

s th

e

level.

PZ

R l

evel

contr

ol

P

ZR

level

(RC

SL

T02_T

R)

beg

ins

to

rise

;

C

hec

k c

har

ge/

dis

char

ge

flo

ws.

24

Ver

ify t

her

mal

po

wer

(M

W(t

h))

ris

es

acco

rdin

g

to g

ener

ato

r lo

ad (

MW

(e))

.

Over

vie

w

N

eutr

on p

ow

er (

RC

SN

P01_T

R)

and

gen

erat

or

load

(G

EN

PT

02_C

S)

chang

ing a

t si

mil

ar r

ates

.

25

Once

tu

rbin

e lo

ad r

eaches

turb

ine

load

dem

and

(45

MW

), v

erif

y t

her

e is

no

furt

her

change.

Over

vie

w

G

ener

ato

r lo

ad s

ettl

es

at t

urb

ine

load

dem

and.

NO

TE

I sh

ou

ld b

e co

ntr

olled

as

follo

ws:

(a)

If ∆

I is

at

the

left

sid

e o

f th

e ta

rget

ban

d,

rods

are

exce

ssiv

ely

inse

rted

. T

his

means

that

ro

ds

dep

ress

neu

tro

n f

lux i

n

the

up

per

half

of

the

core

and f

orc

e a

hig

h f

lux t

o e

xis

t in

the

low

er h

alf

. T

o m

ake

∆I

retu

rn t

o t

he

targ

et b

and,

bo

rate

the

RC

S t

o m

ake

rods

wit

hdra

w f

rom

the

core

;

(b)

If ∆

I is

at

the

rig

ht

sid

e o

f th

e ta

rget

ban

d,

rods

are

exces

sively

wit

hdra

wn.

This

mea

ns

that

a h

igher

flu

x e

xis

t in

the

up

per

half

of

the

core

co

mpar

ed t

o t

he

low

er h

alf

. T

o m

ake

∆I

retu

rn t

o t

he

targ

et b

and,

dil

ute

the

RC

S t

o m

ake

rods

inse

rt into

the

core

.

26

Ch

eck

∆I

is m

ain

tain

ed w

ithin

the

targ

et b

and.

Co

re

∆I

stay

s w

ithin

the

targ

et b

and.

Page 41: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

32

TA

BL

E 4

. R

EA

CT

OR

PO

WE

R R

ISE

FR

OM

0%

TO

100%

(co

nt.

)

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

27

Ch

eck

th

at

neu

tro

n

po

wer

se

ttle

s at

co

rrec

t

valu

e (1

00

%)

and

ver

ify

usi

ng

S

UR

(d

pm

)

ther

e is

no

fu

rther

change.

Co

re

N

eutr

on p

ow

er (

RC

SN

P01_T

R)

sett

les

at c

orr

ect

valu

e.

28

Ch

eck

the

follo

win

g c

ond

itio

ns:

(1)

Rea

cto

r po

wer

at

100%

;

(2)

Tu

rbin

e lo

ad a

t 45 M

W;

(3)

Tu

rbin

e le

adin

g m

ode

sele

cted

;

(4)

Co

ntr

ol ro

ds

in a

uto

;

(5)

MS

B i

n T

avg m

ode;

(6)

FW

syst

em

in a

uto

;

(7)

CW

syst

em

and c

onden

sate

syst

em

s in

serv

ice;

(8)

No

act

ive

ala

rms.

Page 42: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

33

Page 43: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

34

2.5

. R

EA

CT

OR

TR

IP A

ND

RE

ST

AR

T

The

reac

tor

trip

and

res

tart

op

erat

ion e

xer

cis

e st

eps

are

list

ed i

n T

able

5.

TA

BL

E 5

. R

EA

CT

OR

TR

IP A

ND

RE

ST

AR

T (

cont.

)

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

Set

up

Res

et t

he

sim

ula

tor

to I

C #

1 ‘

100%

BO

L n

atura

l cir

cula

tio

n’

or

IC #

4 ‘

100%

BO

L f

orc

ed c

ircu

lati

on’.

1

Ch

eck

the

follo

win

g v

aria

ble

s ar

e st

able

:

(1)

Neu

tro

n p

ow

er (

%);

(2)

Sta

rt-u

p r

ate

(SU

R)

(dpm

);

(3)

Ther

mal

po

wer

(M

W(t

h))

;

(4)

Gen

erat

or

load

(M

W(e

));

(5)

Co

ntr

ol ro

d p

osi

tio

n (

step

s);

(6)

Co

nd

ense

r p

ress

ure

(m

mH

g);

(7)

Ste

am p

ress

ure

(M

Pa)

;

(8)

FW

flo

w (

kg

/s);

(9)

FW

tem

per

atu

re (

ºC);

(10

) T

avg (

ºC);

(11

) P

ress

uri

zer

pre

ssure

(M

Pa)

;

(12

) P

ress

uri

zer

level (%

).

Over

vie

w

Ro

d p

osi

tio

n

contr

ol

All

var

iable

s st

able

at:

(1)

100%

;

(2)

0 d

pm

;

(3)

150 M

W(t

h);

(4)

45 M

W(e

);

(5)

80 s

teps;

(6)

47.3

mm

Hg

;

(7)

2.7

MP

a;

(8)

78 k

g/s

;

(9)

173ºC

;

(10)

287.5

ºC;

(11)

15.5

MP

a;

(12)

43%

.

2

Ver

ify p

lant

mo

de

is i

n t

urb

ine

lead

ing m

ode.

R

od p

osi

tio

n

contr

ol

S

ele

cto

r in

turb

ine

lead

ing m

ode.

3

Tri

p t

he

reac

tor.

B

oth

rea

ctor

and t

urb

ine

trip

.

Page 44: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

35

TA

BL

E 5

. R

EA

CT

OR

TR

IP A

ND

RE

ST

AR

T (

cont.

)

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

4

Ver

ify r

eact

or

trip

:

(1)

Ver

ify a

ll c

ontr

ol and s

hutd

ow

n r

ods

are

full

y i

nse

rted

;

(2)

Ch

eck

neu

tro

n f

lux i

s lo

wer

ing a

nd S

tart

-

up

rat

e is

neg

ativ

e.

Ro

d p

osi

tio

n

contr

ol

C

ontr

ol ro

d p

osi

tio

n a

t bott

om

;

N

eutr

on p

ow

er (

RC

SN

P01_T

R)

low

ers;

S

tart

-up r

ate

(RC

S_S

UR

_T

R)

is l

ess

than

zer

o.

5

Ver

ify t

urb

ine

trip

:

(1)

Ver

ify t

urb

ine

contr

ol valv

e M

SS

V07 h

as

clo

sed

;

(2)

Ver

ify M

SB

is

tak

ing m

ain

ste

am

flo

w t

o

CN

R.

Turb

ine

contr

ol

M

SS

to

TU

R f

low

(M

SS

FT

04_T

R)

go

es t

o z

ero

;

M

SS

to

CN

R f

low

(M

SS

FT

05_T

R)

rise

s;

T

urb

ine

trip

ala

rm a

ctiv

ates

.

6

Ver

ify

main

st

eam

fl

ow

lo

wer

s (a

fter

th

e

reac

tor

trip

).

Byp

ass

contr

ol

M

ain

ste

am

flo

w (

MS

SF

T01_T

R

and M

SS

FT

02_T

R)

low

ers.

7

Ch

eck

PZ

R l

evel

beg

ins

to lo

wer

due

to c

oo

lant

contr

acti

on (

aft

er t

he

reac

tor

trip

).

PZ

R l

evel

contr

ol

P

ZR

level

(RC

SL

T02_T

R)

beg

ins

to

low

er.

8

Ver

ify t

her

mal p

ow

er (

MW

(th))

has

lo

wer

ed.

Over

vie

w

9

Ch

eck

bo

ron c

once

ntr

atio

n s

table

. C

ore

10

Ch

eck

Xe

reac

tiv

ity b

eco

min

g m

ore

neg

ativ

e.

Co

re

X

eno

n r

eact

ivit

y (

RC

S_X

E_P

CM

)

bec

om

ing m

ore

neg

ativ

e.

Page 45: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

36

TA

BL

E 5

. R

EA

CT

OR

TR

IP A

ND

RE

ST

AR

T (

cont.

)

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

NO

TE

It

tak

es a

pp

rox

imat

ely

27 h

ours

aft

er t

he

reac

tor

trip

fro

m a

fu

ll p

ow

er c

ond

itio

n t

o r

eturn

to

the

Xe

equ

ilib

riu

m v

alu

e exis

ting a

t

10

0%

of

po

wer

. It

tak

es a

ppro

xim

ately

72 h

ours

aft

er t

he

reac

tor

trip

fro

m a

fu

ll p

ow

er c

ond

itio

n t

o r

eturn

to t

he

new

Xe

equ

ilib

riu

m v

alu

e.

Fo

r ti

me

com

pre

ssio

n,

the

reac

tor

wo

uld

be

pro

mptl

y r

est

arte

d.

Rea

ctiv

ity c

hanges

intr

oduce

d b

y X

e sh

ou

ld b

e id

enti

fied

and

com

pen

sate

d i

n a

deli

ber

ate,

car

efu

lly c

ontr

oll

ed m

anner

duri

ng t

he

crit

icali

ty a

nd p

ow

er a

scen

t.

11

Ch

eck

the

follo

win

g:

(1)

Pla

nt

mo

de

is r

eact

or

lead

ing m

ode

and

MS

B i

s in

ste

am

pre

ssure

mo

de;

(2)

Ste

p 1

var

iab

les

rem

ain

sta

ble

.

Ro

d p

osi

tio

n

contr

ol

Turb

ine

bypas

s

contr

ol

P

lant

mo

de

auto

mat

icall

y c

hanged

to r

eact

or

lead

ing m

ode

aft

er t

he

reac

tor

trip

;

M

SB

auto

mat

icall

y c

hanged

to

stea

m p

ress

ure

mo

de

when p

lant

mo

de

changed

to

rea

cto

r le

adin

g

mo

de.

12

Res

et r

eact

or

trip

. T

rip

s

R

eact

or

trip

ala

rm d

eac

tivat

es.

13

Pla

ce r

od

co

ntr

ol

in m

anu

al.

R

od p

osi

tio

n

contr

ol

R

ods

in m

anual

ala

rm a

ctiv

ates

14

Wit

hd

raw

sh

utd

ow

n

bank

whil

e m

onit

ori

ng

neu

tro

n f

lux:

(1)

Ensu

re b

ank

A i

s se

lect

ed;

(2)

Pu

sh O

UT

unti

l bank A

is

full

y w

ithdra

wn.

Ro

d p

osi

tio

n

contr

ol

S

hutd

ow

n r

od p

osi

tio

n c

hang

es.

Page 46: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

37

TA

BL

E 5

. R

EA

CT

OR

TR

IP A

ND

RE

ST

AR

T (

cont.

)

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

15

Wit

hd

raw

co

ntr

ol

bank

B

whil

e m

onit

ori

ng

neu

tro

n f

lux:

(1)

Ensu

re b

ank

B i

s se

lect

ed;

(2)

Pu

sh O

UT

unti

l bank B

is

full

y w

ithdra

wn.

Ro

d p

osi

tio

n

contr

ol

C

ontr

ol ro

d p

osi

tio

n c

hang

es;

S

ourc

e ra

nge

po

wer

(RC

SN

P03_T

R)

beg

ins

to r

ise

but

stab

ilis

es o

r fa

lls

when r

od

mo

vem

ent

sto

ps.

16

Wit

hd

raw

co

ntr

ol

bank

C

to

the

esti

mat

ed

crit

ical

cond

itio

n w

hil

e m

onit

ori

ng n

eutr

on f

lux

for

crit

icality

:

(1)

Ensu

re b

ank

C i

s se

lect

ed;

(2)

Pu

sh O

UT

unti

l bank C

rea

ches

49 s

teps.

Ro

d p

osi

tio

n

contr

ol

C

ontr

ol ro

d p

osi

tio

n c

hang

es;

S

ourc

e ra

nge

po

wer

(RC

SN

P03_T

R)

beg

ins

to r

ise

but

stab

ilis

es o

r fa

lls

when r

od

mo

vem

ent

sto

ps.

17

Dil

ute

RC

S f

or

crit

icali

ty:

(1)

Pla

ce s

ele

cto

r in

‘d

iluti

on’;

(2)

Lo

wer

the

RC

S b

oro

n c

once

ntr

atio

n b

y 2

0

pp

m;

(3)

Ch

eck

RC

S b

oro

n c

once

ntr

atio

n d

ecre

ases

to t

he

targ

et v

alu

e;

(4)

Rep

eat

subst

eps

2.

and 3

. unti

l neu

tro

n

flu

x s

low

ly r

ises

wit

ho

ut

contr

ol ro

d

mo

vem

ent

(cri

tica

lity

obse

rved

). P

lot

neu

tro

n p

ow

er a

nd S

UR

;

(5)

Pla

ce s

ele

cto

r in

‘O

FF

’.

Co

re

In

tro

duce

d v

alu

es

appea

r co

rrec

tly;

B

oro

n c

once

ntr

atio

n (

RC

S_B

C)

beg

ins

to lo

wer

;

W

hen c

riti

cal, n

eutr

on p

ow

er

(RC

SN

P01_T

R)

rise

s sl

ow

ly

wit

ho

ut

contr

ol ro

d m

ovem

ent;

P

oin

t o

f ad

din

g h

eat

occ

urs

when

inte

rmed

iate

ran

ge

~ 1

0E

-8.

Page 47: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

38

TA

BL

E 5

. R

EA

CT

OR

TR

IP A

ND

RE

ST

AR

T (

cont.

)

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

NO

TE

A

bo

ve

the

po

int

of

add

ing h

eat,

SU

R s

ho

uld

no

t ex

ceed

a s

ust

ain

ed 0

.5 d

pm

.

18

Rais

e r

eact

or

po

wer

to

8%

wit

h r

od c

ontr

ol

in

manu

al.

Ro

d p

osi

tio

n

contr

ol

C

ontr

ol ro

d p

osi

tio

n c

hang

es;

N

eutr

on p

ow

er (

RC

SN

P01_T

R)

rise

s an

d s

tabil

ises

at

8%

.

19

Rais

e re

act

or

po

wer

to

15%

wit

h r

od c

ontr

ol

in

auto

:

(1)

Ver

ify p

lant

mo

de

is i

n r

eact

or

lead

ing

mo

de;

(2)

Inse

rt 1

5%

in r

eact

or

po

wer

dem

and a

nd

5%

/min

in r

eact

or

po

wer

rat

e;

(3)

Pre

ss G

O;

(4)

Pla

ce c

ontr

ol ro

ds

in a

uto

.

Ro

d p

osi

tio

n

contr

ol

C

ontr

ol ro

d p

osi

tio

n c

hang

es;

N

eutr

on p

ow

er (

RC

SN

P01_T

R)

rise

s an

d s

tabil

ises

at

15%

.

Page 48: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

39

TA

BL

E 5

. R

EA

CT

OR

TR

IP A

ND

RE

ST

AR

T (

cont.

)

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

20

Sta

rt-u

p t

he

turb

ine:

(1)

Res

et t

urb

ine

trip

;

(2)

Ensu

re t

urb

ine

contr

ol

valv

e (M

SS

V07)

is

in a

uto

;

(3)

Pu

sh r

un-u

p;

(4)

Tu

rbin

e co

ntr

ol

valv

e o

pen

s ar

ound 3

%;

(5)

When ‘

read

y t

o s

ync’

lig

ht

appea

rs,

push

‘syn

c’

bu

tto

n t

o c

lose

gen

erat

or

bre

aker

;

(6)

Ch

eck

tu

rbin

e ac

cepts

a m

inim

um

lo

ad;

(7)

Ch

eck

tu

rbin

e co

ntr

ol valv

e is

in m

anu

al.

Turb

ine

contr

ol

T

urb

ine

trip

ala

rm d

eact

ivat

es;

T

urb

ine

contr

ol

valv

e o

pen

s ar

ound

3%

;

T

urb

ine

speed

incr

ease

s

(TU

RC

N01_T

R)

fro

m 5

rp

m t

o

3600rp

m;

T

urn

ing g

ear

and g

ener

ator

bre

aker

ala

rms

cle

ar.

NO

TE

U

po

n c

losi

ng

the

gen

erat

or

bre

aker

, tu

rbin

e lo

ad s

ho

uld

be

rais

ed t

o 3

% t

o p

revent

mo

tori

ng o

f th

e gen

erat

or.

21

Rais

e tu

rbin

e lo

ad m

anuall

y t

o 3

%

(1)

Manu

all

y o

pen

turb

ine

tontr

ol

valv

e to

3%

;

(2)

Ch

eck

gen

erat

or

load

beg

ins

to r

ise.

Turb

ine

contr

ol

T

urb

ine

contr

ol

valv

e o

pen

s;

G

ener

ato

r lo

ad (

GE

NP

T02_C

S)

wo

uld

be

aro

und 3

.5 M

W(e

) w

hen

MS

SV

07 i

s 3%

open

;

S

team

thro

ugh M

SB

lo

wer

s.

22

Pla

ce t

urb

ine

contr

ol

in a

uto

:

(1)

Pla

ce t

urb

ine

contr

ol valv

e in

auto

;

(2)

Ch

eck

tu

rbin

e co

ntr

ol

is c

ontr

oll

ing S

team

pre

ssu

re (

pla

nt

mo

de

in r

eact

or

lead

ing).

Syst

em

dis

pla

y

Page 49: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

40

TA

BL

E 5

. R

EA

CT

OR

TR

IP A

ND

RE

ST

AR

T (

cont.

)

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

NO

TE

S

wit

chin

g t

o t

urb

ine

lead

ing m

ode

wit

h a

big

tem

per

ature

err

or

may l

ead

to

po

wer

osc

illa

tio

ns

and t

urb

ine

trip

.

23

If t

em

per

atu

re e

rro

r is

gre

ater

than

2.5

0ºC

:

(1)

Pla

ce r

od

co

ntr

ol

in m

anu

al;

(2)

Rep

osi

tio

n b

ank C

to m

ake

tem

per

ature

erro

r le

ss t

han

2.5

0ºC

;

(3)

Ch

ang

e p

lant

mo

de

to t

urb

ine

lead

ing

mo

de;

(4)

Ch

ang

e M

SB

mo

de

to T

avg m

ode;

(5)

Go

to

ste

p 2

6.

Ro

d p

osi

tio

n

contr

ol

Turb

ine

bypas

s

contr

ol

T

avg –

Tre

f devia

tio

n c

orr

ecti

on (

aft

er

mo

vin

g B

ank C

) w

ill o

nly

last

fo

r a

few

sec

ond

s.

24

Ch

ang

e p

lant

mo

de

to t

urb

ine

lead

ing m

ode.

R

od p

osi

tio

n

contr

ol

P

lace

sele

ctor

in t

urb

ine

lead

ing

mo

de.

25

Ch

ang

e M

SB

mo

de

to T

avg m

ode.

T

urb

ine

bypas

s

contr

ol

M

SB

sele

cto

r in

Tavg m

ode.

Page 50: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

41

TA

BL

E 5

. R

EA

CT

OR

TR

IP A

ND

RE

ST

AR

T (

cont.

)

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

26

Rais

e tu

rbin

e lo

ad t

o f

ull

po

wer

co

nd

itio

ns:

(1)

Intr

od

uce

tu

rbin

e lo

ad d

em

and (

20 M

W)

and

tu

rbin

e lo

ad r

ate

(1 M

W/m

in)

in

turb

ine

dis

pla

y;

(2)

Pre

ss G

O;

(3)

Ch

eck

tu

rbin

e co

ntr

ol valv

e beg

ins

to

op

en;

(4)

Ch

eck

gen

erat

or

load

beg

ins

to r

ise;

(5)

When t

urb

ine

load

rea

ches

20 M

W,

check

step

1 v

aria

ble

s ar

e st

able

;

(6)

Rais

e tu

rbin

e lo

ad t

o 4

5 M

W a

t a

turb

ine

load

rat

e o

f 1

MW

/min

rep

eat

ing s

ubst

eps

26

.1, 2

6.2

, 2

6.3

and 2

6.4

;

Turb

ine

contr

ol

In

tro

duce

d v

alu

es

appea

r co

rrec

tly;

T

urb

ine

valv

es b

egin

to

open

;

G

ener

ato

r lo

ad (

GE

NP

T02_C

S)

beg

ins

to r

ise.

27

Co

nti

nu

ou

s

acti

on

Dil

ute

RC

S t

o c

om

pensa

te f

or

the

po

wer

def

ect

,

Xe

conce

ntr

atio

n

and

rod

po

siti

on

reac

tivit

y

chang

es:

(1)

Intr

od

uce

the

new

bo

ron c

once

ntr

atio

n

setp

oin

t (m

ax 2

0 p

pm

per

bad

ge)

;

(2)

Pla

ce s

ele

cto

r in

‘D

iluti

on’;

(3)

Ch

eck

bo

ron c

once

ntr

atio

n d

ecre

ases

to

the

bo

ron c

once

ntr

atio

n s

etpo

int;

(4)

Rep

eat

1. an

d 3

. as

des

ired

;

(5)

Pla

ce s

ele

cto

r in

‘O

FF

’.

Co

re

In

tro

duce

d v

alu

es

appea

r co

rrec

tly;

B

oro

n c

once

ntr

atio

n (

RC

S_B

C)

beg

ins

to r

ise.

Page 51: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

42

TA

BL

E 5

. R

EA

CT

OR

TR

IP A

ND

RE

ST

AR

T (

cont.

)

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

28

Co

nti

nu

ou

s

acti

on

When

bank

C

re

aches

80

step

s (f

ull

y

wit

hd

raw

n):

(1)

Ho

ld t

he

turb

ine

load

by p

ress

ing o

n

HO

LD

in t

he

turb

ine

contr

ol d

isp

lay;

(2)

Dil

ute

the

RC

S t

o r

epo

siti

on b

ank C

;

(3)

Co

nti

nu

e in

crea

sing t

urb

ine

load

by

cli

ckin

g o

n G

O i

n t

he

turb

ine

contr

ol

dis

pla

y.

Ro

d p

osi

tio

n

contr

ol

Co

re

Turb

ine

contr

ol

T

his

ste

p w

ould

no

t no

rmall

y b

e

per

form

ed.

29

Ch

eck

m

ain

ste

am

fl

ow

beg

ins

to r

ise

due

to

rise

in l

oad

in

crea

se.

Turb

ine

contr

ol

M

ain

ste

am

flo

w (

MS

SF

T01_T

R

and M

SS

FT

02_T

R)

rise

s;

R

efe

rence

tem

per

ature

beg

ins

to

rise

.

30

Ver

ify co

ntr

ol

rod

s w

ithdra

w in

o

rder

to

ris

e

aver

age

tem

per

atu

re.

Ro

d p

osi

tio

n

contr

ol

C

ontr

ol ro

d p

osi

tio

n c

hang

es;

N

eutr

on p

ow

er (

RC

SN

P01_T

R)

incr

ease

s.

31

Ch

eck

PZ

R l

ev

el

beg

ins

to r

ise d

ue t

o c

oo

lant

exp

an

sio

n a

nd

ho

w le

vel

contr

ol

reco

ver

s th

e

level.

PZ

R l

evel

contr

ol

P

ZR

level

(RC

SL

T02_T

R)

beg

ins

to

rise

;

C

hec

k c

har

ge/

dis

char

ge

flo

ws

32

Ver

ify t

her

mal

po

wer

(M

W(t

h))

ris

es

acco

rdin

g

to g

ener

ato

r lo

ad (

MW

(e))

.

Over

vie

w

N

eutr

on p

ow

er (

RC

SN

P01_T

R)

and

gen

erat

or

load

(G

EN

PT

02_C

S)

chang

ing a

t si

mil

ar r

ates

.

Page 52: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

43

TA

BL

E 5

. R

EA

CT

OR

TR

IP A

ND

RE

ST

AR

T (

cont.

)

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

33

Once

tu

rbin

e lo

ad r

eaches

turb

ine

load

dem

and

(45

MW

), v

erif

y t

her

e is

no

furt

her

change.

Over

vie

w

G

ener

ato

r lo

ad s

ettl

es

at t

urb

ine

load

dem

and.

34

Ch

eck

th

at

neu

tro

n

po

wer

se

ttle

s at

co

rrec

t

valu

e (1

00

%)

and

ver

ify

usi

ng

S

UR

(d

pm

)

ther

e is

no

fu

rther

change.

Co

re

N

eutr

on p

ow

er (

RC

SN

P01_T

R)

sett

les

at c

orr

ect

valu

e.

35

Ch

eck

the

follo

win

g c

ond

itio

ns:

(1)

Rea

cto

r po

wer

at

100%

;

(2)

Tu

rbin

e lo

ad a

t 45 M

W;

(3)

Tu

rbin

e le

adin

g m

ode

sele

cted

;

(4)

Co

ntr

ol ro

ds

in a

uto

;

(5)

MS

B i

n T

avg M

ode;

(6)

FW

syst

em

in a

uto

;

(7)

CW

and

co

nd

ensa

te s

yst

em

s in

ser

vic

e;

(8)

No

act

ive

ala

rms.

Page 53: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

44

3. SIMULATOR EXERCISES FOR MALFUNCTION TRANSIENT EVENTS

This section contains the exercises required to allow the user to understand how to operate

iPWR-SMR nuclear power plants under transient/accident conditions.

The following exercises are described:

(a) Turbine trip and recover;

(b) Loss of feedwater flow;

(c) Turbine runback;

(d) Large steam generator tube rupture (SGTR);

(e) Large main steam line break (MSLB);

(f) Station blackout (SBO);

(g) Steam line isolation;

(h) Reactor pressure vessel safety valve opening;

(i) Reactor coolant pump trip;

(j) All reactor coolant pumps trip.

Page 54: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

45

Page 55: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

46

3.1

. S

PU

RIO

US

TU

RB

INE

TR

IP A

ND

RE

CO

VE

RY

The

spuri

ou

s tu

rbin

e tr

ip a

nd

rec

over

y o

per

atio

n s

teps

are

list

ed i

n T

able

6.

TA

BL

E 6

. S

PU

RIO

US

TU

RB

INE

TR

IP A

ND

RE

CO

VE

RY

(co

nt.

)

MA

LF

UN

CT

ION

: S

M-T

UR

-1

DE

SC

RIP

TIO

N:

Spuri

ous

turb

ine

trip

ST

EP

ID

.

PR

OC

ED

UR

E S

TE

PS

G

UI

SH

EE

T

EX

PE

CT

ED

RE

SP

ON

SE

S

TA

TE

Set

up

Res

et t

he

sim

ula

tor

to I

C #

1 ‘

100%

BO

L n

atura

l cir

cula

tio

n’

or

IC #

4 ‘

100%

BO

L f

orc

ed c

ircu

lati

on’.

Init

ial C

ond

itio

ns

Ch

eck

the

follo

win

g v

aria

ble

s ar

e st

able

:

(1)

Neu

tro

n p

ow

er (

%);

(2)

Sta

rt-u

p r

ate

(SU

R)

(dpm

);

(3)

Ther

mal

po

wer

(M

W(t

h))

;

(4)

Gen

erat

or

load

(M

W(e

));

(5)

Co

ntr

ol ro

d p

osi

tio

n (

step

s);

(6)

Co

nd

ense

r pre

ssure

(m

mH

g);

(7)

Ste

am p

ress

ure

(M

Pa)

;

(8)

FW

flo

w (

kg/s

);

(9)

FW

tem

per

ature

(ºC

);

(10

) T

avg

(ºC

);

(11

) P

ress

uri

zer

pre

ssure

(M

Pa)

;

(12

) P

ress

uri

zer

level (%

).

Over

vie

w

Ro

d p

osi

tio

n

contr

ol

All

var

iable

s st

able

at:

(1)

100%

;

(2)

0 d

pm

;

(3)

150 M

W(t

h);

(4)

45 M

W(e

);

(5)

80 s

teps;

(6)

47.3

mm

Hg

;

(7)

2.7

MP

a;

(8)

78 k

g/s

;

(9)

173ºC

;

(10) 2

87.5

ºC;

(11) 1

5.5

MP

a;

(12) 4

3%

.

Page 56: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

47

TA

BL

E 6

. S

PU

RIO

US

TU

RB

INE

TR

IP A

ND

RE

CO

VE

RY

(co

nt.

)

MA

LF

UN

CT

ION

: S

M-T

UR

-1

DE

SC

RIP

TIO

N:

Spuri

ous

turb

ine

trip

ST

EP

ID

.

PR

OC

ED

UR

E S

TE

PS

G

UI

SH

EE

T

EX

PE

CT

ED

RE

SP

ON

SE

S

TA

TE

1

Ch

eck

the

follo

win

g c

ond

itio

ns:

(1)

Rea

cto

r po

wer

at

100%

;

(2)

Tu

rbin

e lo

ad a

t 45 M

W(e

);

(3)

Co

ntr

ol ro

ds

in a

uto

;

(4)

FW

syst

em

in a

uto

;

(5)

CW

and

co

ndensa

te s

yst

em

s in

ser

vic

e;

(6)

No

act

ive

ala

rms.

Over

vie

w

2

Pu

sh t

urb

ine

trip

butt

on o

r

load

'tu

rbin

e tr

ip' m

alf

unct

ion (

SM

-TU

R-1

).

T

urb

ine

trip

, gen

erat

or

bre

aker

and

step

bac

k a

larm

s.

3

Ver

ify t

urb

ine

trip

:

(1)

MS

SV

07

clo

ses;

(2)

MS

B t

akes

main

ste

am

flo

w t

o C

NR

.

Syst

em

M

SS

to

TU

R f

low

(M

SS

FT

04_T

R)

go

es t

o z

ero

;

M

SS

to

CN

R f

low

(M

SS

FT

05_T

R)

rise

s.

4

Ver

ify r

eact

or

step

bac

k:

(1)

Co

ntr

ol ro

ds

inse

rt i

nto

the

core

to t

he

new

po

wer

tar

get

;

(2)

Rea

cto

r po

wer

lo

wer

s to

60%

.

Ro

d p

osi

tio

n

C

ontr

ol ro

d p

osi

tio

n c

hang

es;

N

eutr

on p

ow

er (

RC

SN

P01_T

R)

low

ers

to 6

0%

;

R

eact

or

step

bac

k a

larm

bec

om

es

acti

ve.

NO

TE

A

reac

tor

step

bac

k i

s expec

ted t

o o

ccur

follo

win

g a

turb

ine

load

reje

ctio

n t

hat

exce

eds

the

cap

acit

y o

f th

e s

team

du

mp a

nd

rod

Co

ntr

ol

(e.g

. tu

rbin

e t

rip).

In o

ther

wo

rds,

a r

eact

or

step

bac

k a

ssu

mes

the l

oad

reje

ctio

n t

hat

is

beyo

nd

the

stea

m d

um

p

and

ro

d c

ontr

ol

desi

gn.

Wit

h a

100%

cap

acit

y s

team

du

mp,

a r

eact

or

step

bac

k w

ou

ld n

ot

be

nec

ess

ary.

Even s

o a

rea

ctor

step

bac

k t

o 6

0%

has

bee

n i

mp

lem

ente

d f

or

trai

nin

g p

urp

ose

s.

Page 57: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

48

TA

BL

E 6

. S

PU

RIO

US

TU

RB

INE

TR

IP A

ND

RE

CO

VE

RY

(co

nt.

)

MA

LF

UN

CT

ION

: S

M-T

UR

-1

DE

SC

RIP

TIO

N:

Spuri

ous

turb

ine

trip

ST

EP

ID

.

PR

OC

ED

UR

E S

TE

PS

G

UI

SH

EE

T

EX

PE

CT

ED

RE

SP

ON

SE

S

TA

TE

5

Ver

ify m

ain

ste

am

flo

w l

ow

ers.

Turb

ine

contr

ol

M

ain

ste

am

flo

w (

MS

SF

T01_T

R a

nd

MS

SF

T02_T

R)

low

ers.

6

Ensu

re p

lant

mo

de

is i

n r

eact

or

lead

ing m

ode

and

MS

B i

n s

team

pre

ssure

mo

de.

Ro

d p

osi

tio

n

contr

ol

Ste

am d

um

p

contr

ol

P

lant

mo

de

sele

ctor

sho

uld

be

pla

ced i

n

reac

tor

lead

ing m

ode;

M

SB

sw

itches

auto

mat

icall

y t

o s

team

pre

ssure

mo

de

wit

h p

lam

in r

eact

or

lead

ing.

7

Chec

k

PZ

R

level

beg

ins

to

low

er

due

to

reac

tor

coo

lant

contr

acti

on.

PZ

R l

evel

contr

ol

P

ZR

level

(RC

SL

T02_T

R)

beg

ins

to

low

er;

8

Chec

k v

aria

ble

s fr

om

the

init

ial

cond

itio

n a

re

stab

le.

A

ll v

aria

ble

s fr

om

the

init

ial

cond

itio

n

are

expec

ted t

o b

e st

able

.

9

Rem

ov

e 'tu

rbin

e tr

ip'

malf

unct

ion (

SM

-TU

R-

1)

If u

ser

did

no

t use

the

turb

ine

trip

butt

on.

NO

TE

W

ait

unti

l th

e tu

rnin

g g

ear

has

engag

ed b

efo

re s

tart

ing u

p t

he

turb

ine.

Page 58: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

49

TA

BL

E 6

. S

PU

RIO

US

TU

RB

INE

TR

IP A

ND

RE

CO

VE

RY

(co

nt.

)

MA

LF

UN

CT

ION

: S

M-T

UR

-1

DE

SC

RIP

TIO

N:

Spuri

ous

turb

ine

trip

ST

EP

ID

.

PR

OC

ED

UR

E S

TE

PS

G

UI

SH

EE

T

EX

PE

CT

ED

RE

SP

ON

SE

S

TA

TE

10

Sta

rt-u

p t

he

turb

ine:

(1)

Res

et t

urb

ine

trip

;

(2)

Ensu

re M

SS

V07 i

n a

uto

;

(3)

Ro

ll t

urb

ine

to s

ynchro

no

us

spee

d (

3600

rpm

) b

y c

lick

ing o

n ‘

run-u

p’;

(4)

Once

‘re

ady t

o s

ync’

lig

ht

has

appea

red,

cli

ck o

n ‘

sync’

to c

lose

bre

aker

;

(5)

Ch

eck

tu

rbin

e ac

cepts

a m

inim

um

Lo

ad;

(6)

Ch

eck

MS

SV

07 i

s in

manual.

Turb

ine

contr

ol

T

urb

ine

trip

ala

rm c

lear

s;

T

urb

ine

contr

ol

valv

e M

SS

V07 o

pen

s

aro

und 3

%;

T

urb

ine

speed

incr

ease

s

(TU

RC

N01_T

R)

fro

m 5

rp

m t

o 3

600

rpm

;

G

ener

ato

r bre

aker

clo

ses

and g

ener

ato

r

bre

aker

ala

rm c

lear

s;

T

urn

ing g

ear

ala

rm c

lear

s.

11

If r

isin

g t

urb

ine

load

in a

uto

:

(1)

Ensu

re M

SS

V07 c

ontr

ol

is i

n a

uto

;

(2)

Go

to

ste

p 1

4.

Turb

ine

contr

ol

M

SS

to

TU

R f

low

(M

SS

FT

04_T

R)

rise

s;

MS

S t

o C

NR

flo

w (

MS

SF

T05_T

R)

go

es t

o z

ero.

12

If r

isin

g t

urb

ine

load

in m

anual:

(1)

Manu

all

y o

pen

MS

SV

07 u

nti

l st

eam

hea

der

pre

ssure

equals

the

turb

ine

contr

ol

refe

rence

pre

ssure

;

(2)

Ch

eck

gen

erat

or

load

beg

ins

to r

ise;

(3)

Ch

eck

MS

SV

09 s

tart

s cl

osi

ng.

Turb

ine

contr

ol

T

he

turb

ine

contr

ol re

fere

nce

pre

ssure

wo

uld

be

~ 2

.98 M

Pa

(MS

SV

07 ~

21%

);

MS

SV

09 w

ould

be

full

y c

lose

d b

efo

re

the

stea

m h

eader

pre

ssure

equals

the

turb

ine

contr

ol re

fere

nce

pre

ssure

.

13

Pla

ce M

SS

V0

7 i

n a

uto

. S

yst

em

s

Page 59: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

50

TA

BL

E 6

. S

PU

RIO

US

TU

RB

INE

TR

IP A

ND

RE

CO

VE

RY

(co

nt.

)

MA

LF

UN

CT

ION

: S

M-T

UR

-1

DE

SC

RIP

TIO

N:

Spuri

ous

turb

ine

trip

ST

EP

ID

.

PR

OC

ED

UR

E S

TE

PS

G

UI

SH

EE

T

EX

PE

CT

ED

RE

SP

ON

SE

S

TA

TE

14

Res

et s

tep

bac

k.

Tri

ps

S

tepbac

k a

larm

cle

ars.

15

If

reac

tor

lead

ing

mo

de

is

stil

l desi

red

to

incr

ease

rea

cto

r po

wer

to 1

00%

:

(1)

Set

rea

cto

r po

wer

dem

and t

o 1

00%

and

reac

tor

po

wer

rat

e to

1%

/min

;

(2)

Pre

ss G

O;

(3)

Ver

ify c

ontr

ol ro

d w

ithdra

wal

to m

atch

reac

tor

po

wer

wit

h r

eact

or

po

wer

dem

and

.

Ro

d p

osi

tio

n

contr

ol

C

ontr

ol ro

d p

osi

tio

n c

hang

es;

N

eutr

on p

ow

er (

RC

SN

P01_T

R)

incr

ease

s

16

If t

urb

ine l

ead

ing m

ode

is d

esi

red

to

incr

ease

turb

ine

load

to

45 M

W (

100%

):

(1)

Ch

ang

e p

lant

mo

de

fro

m r

eact

or

lead

ing

mo

de

to t

urb

ine

lead

ing m

ode;

(2)

Ch

eck

ste

am

du

mp f

rom

ste

am

pre

ssure

mo

de

to T

avg m

ode;

(3)

Set

tu

rbin

e lo

ad d

em

and t

o 4

5 M

W a

nd

turb

ine

load

rat

e to

2%

/min

;

(4)

Ver

ify M

SS

V07 s

tart

s o

pen

ing

;

(5)

Ver

ify c

ontr

ol ro

d w

ithdra

wal.

Ro

d p

osi

tio

n

contr

ol

Ste

am d

um

p

contr

ol

P

lant

mo

de

sele

ctor

sho

uld

be

manuall

y p

lace

d i

n t

urb

ine

lead

ing

mo

de;

G

ener

ato

r lo

ad (

GE

NP

T02_T

R)

beg

ins

to r

ise.

NO

TE

X

eno

n c

once

ntr

atio

n (

neu

tro

n p

ois

on)

wil

l in

crea

se i

n t

he

next

few

ho

urs

due

to t

he

reduct

ion i

n c

ore

po

wer

. A

n

RC

S d

ilu

tio

n w

ill

be

nec

essa

ry t

o c

om

pensa

te f

or

Xe

eff

ect

s an

d r

eco

ver

the

100%

co

nd

itio

n.

Page 60: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

51

TA

BL

E 6

. S

PU

RIO

US

TU

RB

INE

TR

IP A

ND

RE

CO

VE

RY

(co

nt.

)

MA

LF

UN

CT

ION

: S

M-T

UR

-1

DE

SC

RIP

TIO

N:

Spuri

ous

turb

ine

trip

ST

EP

ID

.

PR

OC

ED

UR

E S

TE

PS

G

UI

SH

EE

T

EX

PE

CT

ED

RE

SP

ON

SE

S

TA

TE

17

Dil

ute

RC

S:

(1)

Intr

od

uce

the

new

bo

ron c

once

ntr

atio

n

setp

oin

t (m

ax 2

0 p

pm

per

bad

ge)

;

(2)

Pla

ce s

ele

ctor

in ‘

dil

uti

on’;

(3)

Ch

eck

bo

ron c

once

ntr

atio

n d

ecre

ases

to

the

bo

ron c

once

ntr

atio

n s

etpo

int;

(4)

Rep

eat

(1)

and (

3)

as d

esir

ed;

(5)

Pla

ce s

ele

ctor

in ‘

OF

F’.

Co

re

B

oro

n c

once

ntr

atio

n (

RC

S_B

C)

low

ers.

18

Ch

eck

main

ste

am

flo

w b

egin

s to

ris

e d

ue

to

an i

ncr

ease

in t

urb

ine

load

.

Turb

ine

contr

ol

M

ain

ste

am

flo

w (

MS

SF

T01_T

R a

nd

MS

SF

T02_T

R)

rise

s.

19

Ch

eck

PZ

R l

evel

beg

ins

to r

ise

due

to c

oo

lant

exp

an

sio

n.

PZ

R l

evel

contr

ol

P

ZR

level

(RC

SL

T02_T

R)

beg

ins

to

rise

.

20

Ver

ify

ther

mal

po

wer

(M

W(t

h))

ri

ses

acco

rdin

g t

o g

ener

ato

r lo

ad (

MW

(e))

.

Over

vie

w

N

eutr

on p

ow

er (

RC

SN

P01_T

R)

and

gen

erat

or

load

(G

EN

PT

02_C

E)

chang

ing a

t si

mil

ar r

ates

.

21

Once

tu

rbin

e lo

ad

dem

and

(45

MW

(e))

has

bee

n

reac

hed

, ver

ify

ther

e is

no

fu

rther

chang

e.

Over

vie

w

G

ener

ato

r lo

ad (

GE

NP

T02_C

E)

stab

iliz

es a

t 45 M

W.

22

Ch

eck

re

acto

r po

wer

is

st

able

at

100%

an

d

ver

ify u

sin

g S

UR

(d

pm

) th

ere

is

no

fu

rther

chang

e.

Co

re

N

eutr

on p

ow

er (

RC

SN

P01_T

R)

sett

les

at c

orr

ect

valu

e.

Page 61: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

52

TA

BL

E 6

. S

PU

RIO

US

TU

RB

INE

TR

IP A

ND

RE

CO

VE

RY

(co

nt.

)

MA

LF

UN

CT

ION

: S

M-T

UR

-1

DE

SC

RIP

TIO

N:

Spuri

ous

turb

ine

trip

ST

EP

ID

.

PR

OC

ED

UR

E S

TE

PS

G

UI

SH

EE

T

EX

PE

CT

ED

RE

SP

ON

SE

S

TA

TE

23

Ch

eck

the

follo

win

g f

inal

pla

nt

cond

itio

ns:

(1)

Rea

cto

r po

wer

at

100%

;

(2)

Tu

rbin

e lo

ad a

t 45 M

W;

(3)

Ro

d c

ontr

ol

in a

uto

;

(4)

Ste

am d

um

p i

n a

uto

;

(5)

FW

syst

em

in a

uto

;

(6)

CW

and

co

ndensa

te s

yst

em

s in

ser

vic

e;

(7)

No

act

ive

ala

rms.

NO

TE

I sh

ou

ld b

e co

ntr

olled

as

follo

ws:

(a)

If ∆

I is

at

the

left

sid

e o

f th

e ta

rget

ban

d,

rods

are

exce

ssiv

ely

inse

rted

. T

his

means

that

ro

ds

dep

ress

neu

tro

n

flu

x i

n t

he

upper

half

of

the

core

and f

orc

e a

hig

h f

lux t

o e

xis

t in

the

low

er h

alf

. T

o m

ake

∆I

retu

rn t

o t

he

targ

et

band,

bo

rate

the

RC

S t

o m

ake

rods

wit

hdra

w f

rom

the

core

.

(b)

If ∆

I is

at

the

rig

ht

sid

e o

f th

e ta

rget

ban

d,

rods

are

exces

sively

wit

hdra

wn.

This

mea

ns

that

a h

igher

flu

x e

xis

t

in t

he

upper

half

of

the

core

co

mpar

ed t

o t

he

low

er h

alf

. T

o m

ake

∆I

retu

rn t

o t

he

targ

et b

and,

dil

ute

the

RC

S

to m

ake

rods

inse

rt i

nto

the

core

.

Page 62: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

53

Page 63: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

54

3.2

. L

OS

S O

F F

EE

DW

AT

ER

FL

OW

The

loss

of

feed

wat

er f

low

exer

cis

e st

eps

are

list

ed i

n T

able

7.

TA

BL

E 7

. L

OS

S O

F F

EE

DW

AT

ER

FL

OW

(co

nt.

)

MA

LF

UN

CT

ION

: S

M-F

WS

-3

DE

SC

RIP

TIO

N:

Lo

ss o

f no

rmal

feed

wat

er f

low

(F

W p

um

ps

trip

)

ST

EP

ID

.

PR

OC

ED

UR

E S

TE

PS

G

UI

SH

EE

T

EX

PE

CT

ED

RE

SP

ON

SE

S

TA

TE

Set

up

Res

et t

he

sim

ula

tor

to I

C #

1 ‘

100%

BO

L n

atura

l cir

cula

tio

n’

or

IC #

4 ‘

100%

BO

L f

orc

ed c

ircu

lati

on’.

Init

ial C

ond

itio

ns

Ch

eck

the

follo

win

g v

aria

ble

s ar

e st

able

:

(1)

Neu

tro

n p

ow

er (

%);

(2)

Sta

rt-u

p r

ate

(SU

R)

(dpm

);

(3)

Ther

mal

po

wer

(M

W(t

h))

;

(4)

Gen

erat

or

load

(M

W(e

));

(5)

Co

ntr

ol ro

d p

osi

tio

n (

step

s);

(6)

Co

nd

ense

r pre

ssure

(m

mH

g).

(7)

Ste

am p

ress

ure

(M

Pa)

;

(8)

FW

flo

w (

kg/s

);

(9)

FW

tem

per

ature

(ºC

);

(10

) T

avg

(ºC

);

(11

) P

ress

uri

zer

pre

ssure

(M

Pa)

;

(12

) P

ress

uri

zer

level (%

).

Over

vie

w

Ro

d p

osi

tio

n

contr

ol

All

var

iable

s st

able

at:

(1)

100%

;

(2)

0 d

pm

;

(3)

150 M

W(t

h);

(4)

45 M

W(e

);

(5)

80 s

teps;

(6)

47.3

mm

Hg

;

(7)

2.7

MP

a;

(8)

78 k

g/s

;

(9)

173ºC

;

(10) 2

87.5

ºC;

(11) 1

5.5

MP

a;

(12) 4

3%

.

Page 64: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

55

TA

BL

E 7

. L

OS

S O

F F

EE

DW

AT

ER

FL

OW

(co

nt.

)

MA

LF

UN

CT

ION

: S

M-F

WS

-3

DE

SC

RIP

TIO

N:

Lo

ss o

f no

rmal

feed

wat

er f

low

(F

W p

um

ps

trip

)

ST

EP

ID

.

PR

OC

ED

UR

E S

TE

PS

G

UI

SH

EE

T

EX

PE

CT

ED

RE

SP

ON

SE

S

TA

TE

1

Ch

eck

the

follo

win

g c

ond

itio

ns:

(1)

Rea

cto

r po

wer

at

100%

;

(2)

Tu

rbin

e lo

ad a

t 45 M

W;

(3)

Co

ntr

ol ro

ds

in a

uto

;

(4)

FW

syst

em

in a

uto

;

(5)

CW

and

co

ndensa

te s

yst

em

s in

ser

vic

e;

(6)

No

act

ive

ala

rms;

2

Lo

ad

'loss

o

f F

W

flo

w'

malf

unct

ion

(SM

-

FW

S-3

).

Syst

em

s

F

W p

um

ps

trip

.

3

Ver

ify m

alf

unct

ion:

(1)

Ch

eck

FW

hea

der

pre

ssure

lo

wer

s

init

iall

y;

(2)

Ch

eck

sec

ond F

W p

um

p f

ail

s to

sta

rt;

(3)

Ch

eck

FW

co

ntr

ol

valv

e o

pen

s

com

ple

tely

;

(4)

Ch

eck

FW

flo

w d

rops.

Syst

em

s

F

W p

um

p d

ischar

ge

pre

ssure

(FW

SP

T01_T

R)

go

es t

o 0

;

2

nd F

W p

um

p (

FW

SP

02)

fail

s to

sta

rt;

F

WS

V17 o

pen

s;

F

WS

FT

01/2

dro

ps;

Page 65: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

56

TA

BL

E 7

. L

OS

S O

F F

EE

DW

AT

ER

FL

OW

(co

nt.

)

MA

LF

UN

CT

ION

: S

M-F

WS

-3

DE

SC

RIP

TIO

N:

Lo

ss o

f no

rmal

feed

wat

er f

low

(F

W p

um

ps

trip

)

ST

EP

ID

.

PR

OC

ED

UR

E S

TE

PS

G

UI

SH

EE

T

EX

PE

CT

ED

RE

SP

ON

SE

S

TA

TE

4

Ver

ify R

eact

or

trip

:

(1)

Ver

ify a

ll c

ontr

ol and s

hutd

ow

n r

ods

are

have

full

y i

nse

rted

;

(2)

Ch

eck

neu

tro

n f

lux i

s lo

wer

ing a

nd S

tart

-

up

rat

e is

neg

ativ

e.

Ro

d p

osi

tio

n

contr

ol

R

eact

or

trip

due

to F

W p

um

ps

trip

;

C

ontr

ol ro

d p

osi

tio

n a

t bott

om

;

N

eutr

on p

ow

er (

RC

SN

P01_T

R)

low

ers;

S

tart

-up r

ate

(RC

S_S

UR

_T

R)

is l

ess

than

zer

o;

R

eact

or

trip

ala

rm.

5

Ver

ify t

urb

ine

trip

:

(1)

Ver

ify t

urb

ine

contr

ol valv

e M

SS

V07 h

as

clo

sed

.

Syst

em

s

M

SS

to

TU

R f

low

(M

SS

FT

04_T

R)

go

es t

o z

ero

;

M

SS

to

CN

R f

low

(M

SS

FT

05_T

R)

is

gre

ater

than

zer

o;

T

urb

ine

trip

and b

reak

er o

pen

ala

rms.

6

Ch

eck

DH

R a

ctu

atio

n:

(1)

Ver

ify D

HR

inle

t an

d o

utl

et i

sola

tio

n

valv

es

hav

e o

pen

ed a

nd t

her

e is

flo

w

thro

ug

h b

oth

leg

s;

(2)

Ch

eck

FW

S i

sola

tio

n.

Syst

em

s

D

HR

inle

t an

d o

utl

et i

sola

tio

n v

alv

es

(DH

RV

02/0

4/0

1/0

3)

hav

e o

pen

ed a

nd

ther

e is

flo

w t

hro

ugh b

oth

leg

s

(DH

RF

T01/2

_T

R);

B

oth

main

FW

iso

lati

on v

alv

es

(FW

SV

15/1

6)

have

clo

sed

;

P

DH

R a

ctuat

ion a

larm

.

Page 66: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

57

TA

BL

E 7

. L

OS

S O

F F

EE

DW

AT

ER

FL

OW

(co

nt.

)

MA

LF

UN

CT

ION

: S

M-F

WS

-3

DE

SC

RIP

TIO

N:

Lo

ss o

f no

rmal

feed

wat

er f

low

(F

W p

um

ps

trip

)

ST

EP

ID

.

PR

OC

ED

UR

E S

TE

PS

G

UI

SH

EE

T

EX

PE

CT

ED

RE

SP

ON

SE

S

TA

TE

7

Ch

eck

DH

R o

per

atio

n:

(1)

RC

S t

emp

erat

ure

is

stab

le o

r lo

wer

ing

;

(2)

RC

S p

ress

ure

is

low

erin

g;

(3)

CB

DH

R p

oo

ls t

emper

ature

is

risi

ng.

Syst

em

s

R

CS

tem

per

ature

(R

CS

TE

01_T

R)

is

stab

le o

r lo

wer

ing

;

C

B D

HR

poo

l te

mper

ature

s

(CB

ST

E01/2

_T

R)

are

risi

ng.

NO

TE

D

HR

co

oli

ng

d

epre

ssuri

zes

RC

S.

Use

rs

sho

uld

blo

ck

AD

S

befo

re

RC

S

pre

ssure

dro

ps

belo

w

9.0

M

Pa

to

avo

id

an

un

nec

essa

ry A

DS

act

uat

ion.

8

Blo

ck A

DS

act

uat

ion:

(1)

Pre

ss B

LO

CK

on t

rips

dis

pla

y;

(2)

Ver

ify A

DS

blo

ck s

tatu

s li

ght

is o

n.

Tri

ps

A

DS

blo

ck a

ctuat

ed t

o a

vo

id A

DS

actu

atio

n.

9

Ch

eck

rea

cto

r is

sta

ble

:

(1)

Neu

tro

n f

lux i

s no

t ri

sing a

nd S

UR

is

no

t

po

siti

ve;

(2)

RC

S f

low

is

po

siti

ve;

(3)

RC

S t

emp

erat

ure

is

stab

le o

r lo

wer

ing.

Syst

em

s

N

eutr

on p

ow

er (

RC

SN

P01_T

R)

is n

ot

risi

ng

;

R

CS

coo

lant

flo

w (

RC

SF

T01_T

R)

is

no

n-z

ero

;

S

tart

-up r

ate

(RC

S_S

UR

_T

R)

is l

ess

than

zer

o;

R

CS

tem

per

ature

(R

CS

TE

01_T

R)

is

stab

le o

r lo

wer

ing.

Page 67: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

58

3.3

. T

UR

BIN

E R

UN

BA

CK

The

turb

ine

runbac

k e

xer

cis

e st

eps

are

list

ed i

n T

able

8.

TA

BL

E 8

. T

UR

BIN

E R

UN

BA

CK

(co

nt.

)

MA

LF

UN

CT

ION

: S

M-T

UR

-2

DE

SC

RIP

TIO

N:

Spuri

ous

turb

ine

runbac

k

ST

EP

ID

.

PR

OC

ED

UR

E S

TE

PS

G

UI

SH

EE

T

EX

PE

CT

ED

RE

SP

ON

SE

S

TA

TE

Set

up

Res

et t

he

sim

ula

tor

to I

C #

1 ‘

100%

BO

L n

atura

l cir

cula

tio

n’

or

IC #

4 ‘

100%

BO

L f

orc

ed c

ircu

lati

on’.

Init

ial C

ond

itio

ns

Ch

eck

the

follo

win

g v

aria

ble

s ar

e st

able

:

(1)

Neu

tro

n p

ow

er (

%);

(2)

Sta

rt-u

p r

ate

(SU

R)

(dpm

);

(3)

Ther

mal

po

wer

(M

W(t

h))

;

(4)

Gen

erat

or

load

(M

W(e

));

(5)

Co

ntr

ol ro

d p

osi

tio

n (

step

s);

(6)

Co

nd

ense

r pre

ssure

(m

mH

g);

(7)

Ste

am p

ress

ure

(M

Pa)

;

(8)

FW

flo

w (

kg/s

);

(9)

FW

tem

per

ature

(ºC

);

(10

) T

avg (

ºC);

(11

) P

ress

uri

zer

pre

ssure

(M

Pa)

;

(12

) P

ress

uri

zer

level (%

).

Over

vie

w

Ro

d p

osi

tio

n

contr

ol

All

var

iable

s st

able

at:

(1)

100%

;

(2)

0 d

pm

;

(3)

150 M

W(t

h);

(4)

45 M

W(e

);

(5)

80 s

teps;

(6)

47.3

mm

Hg

;

(7)

2.7

MP

a;

(8)

78 k

g/s

;

(9)

173ºC

;

(10) 2

87.5

ºC;

(11) 1

5.5

MP

a;

(12) 4

3%

.

Page 68: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

59

TA

BL

E 8

. T

UR

BIN

E R

UN

BA

CK

(co

nt.

)

MA

LF

UN

CT

ION

: S

M-T

UR

-2

DE

SC

RIP

TIO

N:

Spuri

ous

turb

ine

runbac

k

ST

EP

ID

.

PR

OC

ED

UR

E S

TE

PS

G

UI

SH

EE

T

EX

PE

CT

ED

RE

SP

ON

SE

S

TA

TE

1

Ch

eck

the

follo

win

g c

ond

itio

ns:

(1)

Rea

cto

r at

100%

;

(2)

Tu

rbin

e lo

ad a

t 45 M

W;

(3)

Co

ntr

ol ro

ds

in a

uto

;

(4)

FW

syst

em

in a

uto

;

(5)

CW

syst

em

and c

onden

sate

syst

em

s in

serv

ice;

(6)

No

act

ive

ala

rms;

2

Pu

sh r

unb

ack

butt

on o

r lo

ad 'm

ajo

r tu

rbin

e

runbac

k' m

alf

unct

ion (

SM

-TU

R-2

).

Tri

ps

R

unbac

k a

larm

.

3

Ver

ify s

team

du

mp o

per

atio

n i

n r

espo

nse

to

the

turb

ine

runback

.

Ste

am d

um

p

contr

ol

M

SS

to

CN

R f

low

(M

SS

FT

05_T

R)

rise

s.

4

Ver

ify r

od

co

ntr

ol o

per

atio

n:

(1)

Ver

ify c

ontr

ol ro

ds

hav

e in

sert

ed t

o

mat

ch T

avg w

ith t

he

new

lo

wer

Tre

f;

(2)

Ch

eck

neu

tro

n p

ow

er lo

wer

s.

Ro

d p

osi

tio

n

contr

ol

C

ontr

ol ro

d p

osi

tio

n c

hang

es;

N

eutr

on p

ow

er (

RC

SN

P01_T

R)

low

ers.

5

Ch

eck

PZ

R l

evel

has

low

ered

due

to c

oo

lant

contr

acti

on.

PZ

R l

evel

contr

ol

P

ZR

level

(RC

SL

T02_T

R)

low

ers.

6

Ch

eck

m

ain

st

eam

fl

ow

has

lo

wer

ed due

to

turb

ine

load

red

uct

ion.

Syst

em

s

M

ain

ste

am

flo

w (

MS

SF

T01_T

R a

nd

MS

SF

T02_T

R)

low

ers.

Page 69: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

60

TA

BL

E 8

. T

UR

BIN

E R

UN

BA

CK

(co

nt.

)

MA

LF

UN

CT

ION

: S

M-T

UR

-2

DE

SC

RIP

TIO

N:

Spuri

ous

turb

ine

runbac

k

ST

EP

ID

.

PR

OC

ED

UR

E S

TE

PS

G

UI

SH

EE

T

EX

PE

CT

ED

RE

SP

ON

SE

S

TA

TE

7

Ch

eck

m

ain

F

W

flo

w

has

lo

wer

ed

due

to

turb

ine

load

red

uct

ion.

Syst

em

s

M

ain

FW

flo

w (

FW

SF

T01_T

R a

nd

FW

SF

T02_T

R)

low

ers;

V

alv

e F

WS

V17 c

lose

s and F

W p

um

p

spee

d l

ow

ers

(duri

ng t

he

runbac

k).

8

Ch

eck

var

iab

les

fro

m

the

init

ial

cond

itio

ns

have

stab

iliz

ed.

NO

TE

I sh

ou

ld b

e co

ntr

olled

as

follo

ws:

(a)

If ∆

I is

at

the

left

sid

e o

f th

e ta

rget

band,

rods

are

exces

sively

inse

rted

. T

his

mea

ns

that

ro

ds

dep

ress

neu

tro

n f

lux

in t

he

upper

half

of

the

core

and f

orc

e a

hig

h f

lux t

o e

xis

t in

the

low

er h

alf

. T

o m

ake

∆I

retu

rn t

o t

he

targ

et b

and,

bo

rate

the

RC

S t

o m

ake

rods

wit

hdra

w f

rom

the

core

;

(b)

If ∆

I is

at

the

rig

ht

side o

f th

e ta

rget

ban

d,

rods

are

exce

ssiv

ely

wit

hdra

wn.

This

mea

ns

that

a h

igher

flu

x e

xis

t in

the

upper

half

of

the

core

co

mp

ared

to

the

low

er h

alf

. T

o m

ake

∆I

retu

rn t

o t

he

targ

et b

and,

dil

ute

the

RC

S t

o

mak

e ro

ds

inse

rt i

nto

the

core

.

Page 70: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

61

Page 71: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

62

3.4

. L

AR

GE

ST

EA

M G

EN

ER

AT

OR

TU

BE

RU

PT

UR

E (

SG

TR

)

The

larg

e st

eam

gener

ato

r tu

be

ruptu

re e

xer

cis

e st

eps

are

list

ed i

n T

able

9.

TA

BL

E 9

. L

AR

GE

ST

EA

M G

EN

ER

AT

OR

TU

BE

RU

PT

UR

E (

cont.

)

MA

LF

UN

CT

ION

: S

M-M

SS

-2

DE

SC

RIP

TIO

N:

Ste

am g

ener

ator

1 t

ube

ruptu

re

ST

EP

ID

.

PR

OC

ED

UR

E S

TE

PS

G

UI

SH

EE

T

EX

PE

CT

ED

RE

SP

ON

SE

S

TA

TE

Set

up

Res

et t

he

sim

ula

tor

to I

C #

1 ‘

100%

BO

L n

atura

l cir

cula

tio

n’

or

IC #

4 ‘

100%

BO

L f

orc

ed c

ircu

lati

on’.

Init

ial C

ond

itio

ns

Ch

eck

the

follo

win

g v

aria

ble

s ar

e st

able

:

(1)

Neu

tro

n p

ow

er (

%);

(2)

Sta

rt-u

p r

ate

(SU

R)

(dpm

);

(3)

Ther

mal

po

wer

(M

W(t

h))

;

(4)

Gen

erat

or

load

(M

W(e

));

(5)

Co

ntr

ol ro

d p

osi

tio

n (

step

s);

(6)

Co

nd

ense

r pre

ssure

(m

mH

g);

(7)

Ste

am p

ress

ure

(M

Pa)

;

(8)

FW

flo

w (

kg/s

);

(9)

FW

tem

per

ature

(ºC

);

(10

) T

avg (

ºC);

(11

) P

ress

uri

zer

pre

ssure

(M

Pa)

;

(12

) P

ress

uri

zer

level (%

).

Over

vie

w

Ro

d p

osi

tio

n

contr

ol

All

var

iable

s st

able

at:

(1)

100%

;

(2)

0 d

pm

;

(3)

150 M

W(t

h);

(4)

45 M

W(e

);

(5)

80 s

teps;

(6)

47.3

mm

Hg

;

(7)

2.7

MP

a;

(8)

78 k

g/s

;

(9)

173ºC

;

(10) 2

87.5

ºC;

(11) 1

5.5

MP

a;

(12) 4

3%

.

Page 72: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

63

TA

BL

E 9

. L

AR

GE

ST

EA

M G

EN

ER

AT

OR

TU

BE

RU

PT

UR

E (

cont.

)

MA

LF

UN

CT

ION

: S

M-M

SS

-2

DE

SC

RIP

TIO

N:

Ste

am g

ener

ator

1 t

ube

ruptu

re

ST

EP

ID

.

PR

OC

ED

UR

E S

TE

PS

G

UI

SH

EE

T

EX

PE

CT

ED

RE

SP

ON

SE

S

TA

TE

1

Ch

eck

the

follo

win

g c

ond

itio

ns:

(1)

Bo

th r

eact

or

and t

urb

ine

at 1

00%

of

po

wer

;

(2)

Co

ntr

ol ro

ds

in a

uto

;

(3)

FW

syst

em

in a

uto

;

(4)

CW

syst

em

and c

onden

sate

syst

em

s in

serv

ice;

(5)

No

act

ive

ala

rms.

2

Lo

ad

'Ste

am

gener

ator

tube

ruptu

re1'

malf

unct

ion (

SM

-MS

S-2

, S

ever

ity =

100.0

%).

Syst

em

s

3

Ver

ify m

alf

unct

ion:

(1)

Ch

eck

fo

r hig

h r

adia

tio

n l

evel

in M

ain

Ste

am l

ine

1 (

N-1

6);

(2)

Ch

eck

RC

S p

ress

ure

beg

ins

to d

rop;

(3)

Ch

eck

PZ

R l

evel

beg

ins

to d

rop;

(4)

FW

flo

w l

ow

ers;

(5)

Subco

oli

ng m

arg

in l

ow

ers.

Syst

em

s

H

igh r

adia

tio

n a

larm

in m

ain

ste

am

line

1;

R

CS

pre

ssure

(R

CS

PT

01_T

R)

dro

ps;

P

ZR

level

(RC

SL

T02_T

R)

dro

ps;

C

har

gin

g f

low

(R

CS

FT

02_T

R)

rise

s;

Page 73: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

64

TA

BL

E 9

. L

AR

GE

ST

EA

M G

EN

ER

AT

OR

TU

BE

RU

PT

UR

E (

cont.

)

MA

LF

UN

CT

ION

: S

M-M

SS

-2

DE

SC

RIP

TIO

N:

Ste

am g

ener

ator

1 t

ube

ruptu

re

ST

EP

ID

.

PR

OC

ED

UR

E S

TE

PS

G

UI

SH

EE

T

EX

PE

CT

ED

RE

SP

ON

SE

S

TA

TE

4

Ver

ify r

eact

or

trip

:

(1)

Ver

ify a

ll c

ontr

ol and s

hutd

ow

n r

ods

are

full

y i

nse

rted

;

(2)

Ch

eck

neu

tro

n f

lux i

s lo

wer

ing a

nd S

tart

-

up

rat

e is

neg

ativ

e.

Ro

d p

osi

tio

n

contr

ol

R

eact

or

trip

on l

ow

PZ

R l

evel;

C

ontr

ol ro

d p

osi

tio

n c

hang

es;

N

eutr

on p

ow

er (

RC

SN

P02_T

R)

low

ers;

S

tart

-up r

ate

(RC

S_S

UR

_T

R)

is l

ess

than

zer

o;

R

eact

or

trip

ala

rm.

5

Ver

ify t

urb

ine

trip

:

(1)

Ver

ify t

urb

ine

contr

ol valv

e M

SS

V07 h

as

clo

sed

;

(2)

Ver

ify M

SB

is

tak

ing m

ain

ste

am

flo

w t

o

CN

R.

Syst

em

s

M

SS

to

TU

R f

low

(M

SS

FT

04_T

R)

go

es t

o z

ero

;

M

SS

to

CN

R f

low

(M

SS

FT

05_T

R)

rise

s;

T

urb

ine

trip

and b

reak

er o

pen

ala

rms.

6

When

Up

per

ple

nu

m p

ress

ure

< 9

MP

a (L

ow

-Lo

w)

OR

Ves

sel

level

< 9

0%

(L

ow

-Lo

w),

ver

ify A

DS

act

uat

ion:

(1)

AD

S v

alv

es o

pen

seq

uenti

all

y w

ith f

low

thro

ug

h e

ach v

alv

e;

(2)

RC

Ps

trip

(if

pre

vio

usl

y r

unnin

g).

Tri

ps

R

CS

pre

ssure

(R

CS

PT

02_T

R)

belo

w 9

MP

a is

expec

ted t

o o

ccur

firs

t;

A

DS

valv

es o

pen

seq

uenti

all

y w

ith 5

min

tim

e dela

ys;

F

low

ris

ing t

hro

ugh a

ll t

hre

e A

DS

valv

es

(AD

S_

W1/2

/3);

A

DS

act

uat

ion a

larm

.

Page 74: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

65

TA

BL

E 9

. L

AR

GE

ST

EA

M G

EN

ER

AT

OR

TU

BE

RU

PT

UR

E (

cont.

)

MA

LF

UN

CT

ION

: S

M-M

SS

-2

DE

SC

RIP

TIO

N:

Ste

am g

ener

ator

1 t

ube

ruptu

re

ST

EP

ID

.

PR

OC

ED

UR

E S

TE

PS

G

UI

SH

EE

T

EX

PE

CT

ED

RE

SP

ON

SE

S

TA

TE

7

If

AD

S

actu

atio

n

occ

urs

, ch

eck

A

DS

op

erat

ion:

(1)

RC

S p

ress

ure

lo

wer

s;

(2)

CB

sup

pre

ssio

n p

oo

l te

mper

ature

ris

es.

PZ

R h

eat

ers

are

dis

connect

ed a

uto

mat

icall

y.

Syst

em

s

PZ

R p

ress

ure

contr

ol

R

CS

pre

ssure

(R

CS

PT

02_T

R)

low

ers;

C

B s

uppre

ssio

n p

oo

l te

mper

ature

(CB

ST

E03_T

R)

rise

s.

8

Act

uat

e P

DH

R t

o i

sola

te F

W l

ines.

T

rip

s

9

Ch

eck

DH

R a

ctu

atio

n:

(1)

Ver

ify D

HR

inle

t an

d o

utl

et i

sola

tio

n

valv

es

hav

e o

pen

ed a

nd t

her

e is

flo

w

thro

ug

h b

oth

leg

s;

(2)

Ch

eck

FW

S i

sola

tio

n;

(3)

Ch

eck

MS

S i

sola

tio

n w

hen M

SS

pre

ssure

lin

e <

2.5

Mpa

wit

h D

HR

sig

nal.

Syst

em

s

D

HR

inle

t an

d o

utl

et i

sola

tio

n v

alv

es

(DH

RV

02/0

4/0

1/0

3)

hav

e o

pen

ed a

nd

ther

e is

flo

w t

hro

ugh b

oth

leg

s

(DH

RF

T01/2

_T

R);

B

oth

main

FW

iso

lati

on v

alv

es

(FW

SV

15/1

6)

have

clo

sed

;

P

DH

R a

ctuat

ion a

larm

.

10

Ch

eck

DH

R o

per

atio

n:

(1)

RC

S t

emp

erat

ure

sta

ble

or

low

erin

g;

(2)

CB

DH

R p

oo

ls t

emper

ature

s ri

sing.

Syst

em

s

R

CS

tem

per

ature

(R

CS

TE

01_T

R)

is

stab

le o

r lo

wer

ing

;

C

B D

HR

poo

l te

mper

ature

s

(CB

ST

E01/2

_T

R)

are

risi

ng.

Page 75: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

66

TA

BL

E 9

. L

AR

GE

ST

EA

M G

EN

ER

AT

OR

TU

BE

RU

PT

UR

E (

cont.

)

MA

LF

UN

CT

ION

: S

M-M

SS

-2

DE

SC

RIP

TIO

N:

Ste

am g

ener

ator

1 t

ube

ruptu

re

ST

EP

ID

.

PR

OC

ED

UR

E S

TE

PS

G

UI

SH

EE

T

EX

PE

CT

ED

RE

SP

ON

SE

S

TA

TE

11

Ch

eck

co

re s

tatu

s:

(1)

Neu

tro

n f

lux i

s no

t ri

sing a

nd S

UR

is

no

t

po

siti

ve;

(2)

Nat

ura

l cir

cula

tio

n i

s m

ain

tain

ing c

oo

lant

flo

w.

Syst

em

s

N

eutr

on p

ow

er (

RC

SN

P01_T

R)

is n

ot

risi

ng

;

S

tart

-up r

ate

(RC

S_S

UR

_T

R)

is l

ess

than

zer

o;

C

oo

lant

flo

w (

RC

SF

T01_T

R)

is n

ot

zero

.

12

When

R

CS

p

ress

ure

is

le

ss

than

5.0

M

Pa,

ver

ify P

IS a

ctu

atio

n:

(1)

PIS

flo

w r

isin

g i

n b

oth

tra

ins;

(2)

PIS

tan

ks

level

low

erin

g.

Syst

em

s

P

IS f

low

into

RC

S (

PIS

FT

01/2

_T

R)

rise

s;

P

IS t

anks

(PIS

TL

01/2

_T

R)

level

low

ers.

13

When

R

CS

p

ress

ure

is

le

ss

than

0.5

M

Pa,

ver

ify G

IS a

ctu

atio

n:

(1)

GIS

flo

w r

isin

g i

n b

oth

tra

ins;

(2)

GIS

tan

ks

level

low

erin

g.

Syst

em

s

G

IS f

low

into

RC

S (

GIS

FT

01/2

_T

R)

risi

ng

;

G

IS t

anks

(GIS

TL

01/2

_T

R)

level

low

erin

g.

Page 76: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

67

TA

BL

E 9

. L

AR

GE

ST

EA

M G

EN

ER

AT

OR

TU

BE

RU

PT

UR

E (

cont.

)

MA

LF

UN

CT

ION

: S

M-M

SS

-2

DE

SC

RIP

TIO

N:

Ste

am g

ener

ator

1 t

ube

ruptu

re

ST

EP

ID

.

PR

OC

ED

UR

E S

TE

PS

G

UI

SH

EE

T

EX

PE

CT

ED

RE

SP

ON

SE

S

TA

TE

14

Ch

eck

rea

cto

r st

able

:

(1)

Neu

tro

n f

lux i

s no

t ri

sing a

nd S

UR

is

no

t

po

siti

ve;

(2)

Bo

ron c

once

ntr

atio

n i

s ri

sing

;

(3)

Nat

ura

l cir

cula

tio

n i

s m

ain

tain

ing

Rea

cto

r co

ola

nt

flo

w;

(4)

RC

S s

ub

coo

ling i

s po

siti

ve;

(5)

RC

S t

emp

erat

ure

is

stab

le o

r lo

wer

ing.

Syst

em

s

N

eutr

on p

ow

er (

RC

SN

P01_T

R)

is

low

erin

g;

R

CS

bo

ron c

once

ntr

atio

n (

RC

S_B

C)

is

risi

ng

;

R

CS

flo

w r

ate

(RC

SF

T01_T

R)

is n

on-

zero

;

S

tart

-up r

ate

(RC

S_S

UR

_T

R)

is l

ess

than

zer

o;

R

CS

tem

per

ature

(R

CS

TE

01_T

R)

is

stab

le o

r lo

wer

ing.

Page 77: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

68

3.5

. L

AR

GE

ST

EA

M L

INE

BR

EA

K (

MS

LB

)

The

last

ge

stea

m l

ine

bre

ak (

MS

LB

) exer

cis

e st

eps

are

list

ed i

n T

able

10.

TA

BL

E 1

0.

LA

RG

E S

TE

AM

LIN

E B

RE

AK

(co

nt.

)

MA

LF

UN

CT

ION

: S

M-M

SS

-4

DE

SC

RIP

TIO

N:

Majo

r st

eam

syst

em

pip

ing f

ail

ure

wit

hin

co

nta

inm

ent

ST

EP

ID

.

PR

OC

ED

UR

E S

TE

PS

G

UI

SH

EE

T

EX

PE

CT

ED

RE

SP

ON

SE

S

TA

TE

Set

up

Res

et t

he

sim

ula

tor

to I

C #

1 ‘

100%

BO

L n

atura

l cir

cula

tio

n’

or

IC #

4 ‘

100%

BO

L f

orc

ed c

ircu

lati

on’.

Init

ial C

ond

itio

ns

Ch

eck

the

follo

win

g v

aria

ble

s ar

e st

able

:

(1)

Neu

tro

n p

ow

er (

%);

(2)

Sta

rt-u

p r

ate

(SU

R)

(dpm

);

(3)

Ther

mal

po

wer

(M

W(t

h))

;

(4)

Gen

erat

or

load

(M

W(e

));

(5)

Co

ntr

ol ro

d p

osi

tio

n (

step

s);

(6)

Co

nd

ense

r pre

ssure

(m

mH

g);

(7)

Ste

am p

ress

ure

(M

Pa)

;

(8)

FW

flo

w (

kg/s

);

(9)

FW

tem

per

ature

(ºC

);

(10

) T

avg (

ºC);

(11

) P

ress

uri

zer

pre

ssure

(M

Pa)

;

(12

) P

ress

uri

zer

level (%

).

Over

vie

w

Ro

d p

osi

tio

n

contr

ol

All

var

iable

s st

able

at:

(1)

100%

;

(2)

0 d

pm

;

(3)

150 M

W(t

h);

(4)

45 M

W(e

);

(5)

80 s

teps;

(6)

47.3

mm

Hg

;

(7)

2.7

MP

a;

(8)

78 k

g/s

;

(9)

173ºC

;

(10) 2

87.5

ºC;

(11) 1

5.5

MP

a;

(12) 4

3%

.

Page 78: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

69

TA

BL

E 1

0.

LA

RG

E S

TE

AM

LIN

E B

RE

AK

(co

nt.

)

MA

LF

UN

CT

ION

: S

M-M

SS

-4

DE

SC

RIP

TIO

N:

Majo

r st

eam

syst

em

pip

ing f

ail

ure

wit

hin

co

nta

inm

ent

ST

EP

ID

.

PR

OC

ED

UR

E S

TE

PS

G

UI

SH

EE

T

EX

PE

CT

ED

RE

SP

ON

SE

S

TA

TE

1

Ch

eck

the

follo

win

g c

ond

itio

ns:

(1)

Bo

th r

eact

or

and t

urb

ine

at 1

00%

of

po

wer

;

(2)

Co

ntr

ol ro

ds

in a

uto

;

(3)

FW

syst

em

in a

uto

;

(4)

CW

syst

em

and c

onden

sate

syst

em

s in

serv

ice;

(5)

No

act

ive

ala

rms.

2

Lo

ad 'M

ain

ste

am

lin

e bre

ak i

nsi

de

conta

inm

ent' m

alf

unct

ion (

SM

-MS

S-4

, S

ever

ity=

100%

).

3

Ver

ify m

alf

unct

ion:

(1)

Ch

eck

main

ste

am

hea

der

and s

team

lin

es

pre

ssu

res

dro

p;

(2)

Ch

eck

co

nta

inm

ent

pre

ssure

beg

ins

to

rise

;

(3)

Ch

eck

PZ

R p

ress

ure

dro

ps;

(4)

Ch

eck

co

nta

inm

ent

sum

p l

evel ri

ses.

Syst

em

s

M

ain

ste

am

head

er p

ress

ure

(MS

SP

T03_T

R)

dro

ps;

M

ain

ste

am

lin

e pre

ssure

s

(MS

SP

T01_T

R/M

SS

PT

02_T

R)

dro

p

(ste

am l

ine

2 p

ress

ure

rec

over

s af

ter

MS

S i

sola

tio

n);

C

onta

inm

ent

pre

ssure

(CB

SP

T01_T

R)

rise

s;

P

ZR

pre

ssure

RC

SP

T02_T

R d

rops;

C

onta

inm

ent

sum

p l

evel

CB

SL

T04_T

R r

ises.

Page 79: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

70

TA

BL

E 1

0.

LA

RG

E S

TE

AM

LIN

E B

RE

AK

(co

nt.

)

MA

LF

UN

CT

ION

: S

M-M

SS

-4

DE

SC

RIP

TIO

N:

Majo

r st

eam

syst

em

pip

ing f

ail

ure

wit

hin

co

nta

inm

ent

ST

EP

ID

.

PR

OC

ED

UR

E S

TE

PS

G

UI

SH

EE

T

EX

PE

CT

ED

RE

SP

ON

SE

S

TA

TE

4

Ch

eck

the

follo

win

g a

larm

co

nd

itio

ns

exis

t:

(1)

Hig

h C

BS

pre

ssure

;

(2)

Lo

w s

team

pre

ssure

.

H

igh C

BS

pre

ssure

ala

rm w

hen C

BS

pre

ssure

> 0

.012 M

Pa.

5

Ver

ify r

eact

or

trip

:

(1)

Ver

ify a

ll c

ontr

ol and s

hutd

ow

n r

ods

are

have

full

y i

nse

rted

;

(2)

Ch

eck

neu

tro

n f

lux i

s lo

wer

ing a

nd S

tart

-

up

rat

e is

neg

ativ

e.

Ro

d p

osi

tio

n

dis

pla

y

C

ontr

ol ro

d p

osi

tio

n a

t bott

om

;

N

eutr

on p

ow

er (

RC

SN

P01_T

R)

low

ers;

S

tart

-up r

ate

(RC

S_S

UR

_T

R)

is l

ess

than

zer

o;

R

eact

or

trip

ala

rm.

6

Ver

ify t

urb

ine

trip

:

(1)

Ver

ify t

urb

ine

contr

ol valv

e M

SS

V07

has

clo

sed.

Syst

em

s

M

SS

to

TU

R f

low

(M

SS

FT

04_T

R)

go

es t

o z

ero

;

M

SS

dum

pin

g s

team

to a

tmo

spher

e

thro

ugh M

SS

V01/2

rel

ief

valv

es;

T

urb

ine

trip

and g

ener

ato

r bre

aker

open

ala

rms.

Page 80: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

71

TA

BL

E 1

0.

LA

RG

E S

TE

AM

LIN

E B

RE

AK

(co

nt.

)

MA

LF

UN

CT

ION

: S

M-M

SS

-4

DE

SC

RIP

TIO

N:

Majo

r st

eam

syst

em

pip

ing f

ail

ure

wit

hin

co

nta

inm

ent

ST

EP

ID

.

PR

OC

ED

UR

E S

TE

PS

G

UI

SH

EE

T

EX

PE

CT

ED

RE

SP

ON

SE

S

TA

TE

7

When

Up

per

ple

nu

m p

ress

ure

< 9

MP

a (L

ow

-Lo

w)

OR

CB

S p

ress

ure

> 0

.019 M

Pa

(Hig

h-H

igh),

ver

ify A

DS

act

uat

ion:

(1)

AD

S v

alv

es o

pen

seq

uenti

all

y w

ith f

low

thro

ug

h e

ach v

alv

e;

(2)

RC

Ps

trip

(if

pre

vio

usl

y r

unnin

g).

Tri

ps

L

ow

pre

ssure

upper

ple

nu

m

(RC

SP

T02_T

R)

low

er t

han

9.0

MP

a

is e

xpec

ted t

o o

ccur

firs

t;

A

DS

valv

es o

pen

seq

uenti

all

y w

ith 5

min

tim

e dela

ys;

F

low

ris

ing t

hro

ugh a

ll t

hre

e A

DS

valv

es

(AD

S_

W1/2

/3);

A

DS

act

uat

ion a

larm

.

8

If

AD

S

actu

atio

n

occ

urs

, ch

eck

A

DS

op

erat

ion:

(1)

RC

S p

ress

ure

lo

wer

s;

(2)

CB

sup

pre

ssio

n p

oo

l te

mper

ature

ris

es.

and

dis

con

nect

PZ

R h

eate

rs.

Syst

em

s

PZ

R p

ress

ure

contr

ol

R

CS

pre

ssure

(R

CS

PT

02_T

R)

low

ers;

C

B s

uppre

ssio

n p

oo

l te

mper

ature

(CB

ST

E03_T

R)

rise

s.

9

When

co

nta

inm

ent

pre

ssure

is

gre

ater

th

an

0.0

19

MP

a, c

hec

k:

(1)

Co

nta

inm

ent

spra

y p

um

ps

star

t;

(2)

Co

nta

inm

ent

spra

y s

yst

em

in

ject

s.

Syst

em

s

C

CS

P01/0

2 s

tart

;

F

low

ris

ing t

hro

ugh b

oth

spra

y

conta

inm

ent

legs

(CC

SF

T01/0

2_T

R);

C

onta

inm

ent

pre

ssure

(CB

SP

T01_T

R)

dro

ps

when

conta

inm

ent

spra

y s

yst

em

is

in

serv

ice.

Page 81: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

72

TA

BL

E 1

0.

LA

RG

E S

TE

AM

LIN

E B

RE

AK

(co

nt.

)

MA

LF

UN

CT

ION

: S

M-M

SS

-4

DE

SC

RIP

TIO

N:

Majo

r st

eam

syst

em

pip

ing f

ail

ure

wit

hin

co

nta

inm

ent

ST

EP

ID

.

PR

OC

ED

UR

E S

TE

PS

G

UI

SH

EE

T

EX

PE

CT

ED

RE

SP

ON

SE

S

TA

TE

10

Ver

ify m

ain

ste

am

iso

lati

on:

(1)

MS

SV

05

and M

SS

V06 c

lose

d.

Syst

em

s

11

Ver

ify f

eed

wat

er i

sola

tio

n:

(1)

FW

iso

lati

on v

alv

es

clo

sed.

Syst

em

s

F

WS

V15/1

6 c

lose

d.

12

Ver

ify D

HR

act

uat

ion:

(1)

DH

R i

nle

t an

d o

utl

et i

sola

tio

n v

alv

es

(DH

RV

02

/04/0

1/0

3)

open

;

(2)

Po

siti

ve

flo

w t

hro

ugh b

oth

DH

R leg

s.

Syst

em

s

D

HR

flo

ws

(DH

RF

T01/2

_T

R)

gre

ater

than

0.

13

Ch

eck

DH

R o

per

atio

n:

(1)

RC

S t

emp

erat

ure

is

stab

le o

r lo

wer

ing

;

(2)

CB

DH

R p

oo

ls t

emper

ature

s ri

se.

Syst

em

s

R

CS

tem

per

ature

(R

CS

TE

01_T

R)

is

stab

le o

r lo

wer

ing

;

C

B D

HR

poo

ls t

emper

ature

s

(CB

ST

E01/2

_T

R)

are

risi

ng.

14

Ch

eck

co

re s

tatu

s:

(1)

Neu

tro

n f

lux i

s no

t ri

sing a

nd S

UR

is

no

t

po

siti

ve;

(2)

Nat

ura

l cir

cula

tio

n i

s m

ain

tain

ing c

oo

lant

flo

w.

Syst

em

s

N

eutr

on p

ow

er (

RC

SN

P01_T

R)

is

no

t ri

sing

;

S

tart

-up r

ate

(RC

S_S

UR

_T

R)

is l

ess

than

zer

o;

C

oo

lant

flo

w r

ate

(RC

SF

T01_T

R)

is

no

t ze

ro.

Page 82: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

73

TA

BL

E 1

0.

LA

RG

E S

TE

AM

LIN

E B

RE

AK

(co

nt.

)

MA

LF

UN

CT

ION

: S

M-M

SS

-4

DE

SC

RIP

TIO

N:

Majo

r st

eam

syst

em

pip

ing f

ail

ure

wit

hin

co

nta

inm

ent

ST

EP

ID

.

PR

OC

ED

UR

E S

TE

PS

G

UI

SH

EE

T

EX

PE

CT

ED

RE

SP

ON

SE

S

TA

TE

15

When

R

CS

p

ress

ure

is

le

ss

than

5.0

M

Pa,

ver

ify P

IS a

ctu

atio

n:

(1)

PIS

flo

w r

isin

g i

n b

oth

tra

ins;

(2)

PIS

tan

ks

level

low

erin

g.

Syst

em

s

P

IS f

low

into

RC

S (

PIS

FT

01/2

_T

R)

rise

s;

P

IS t

anks

(PIS

TL

01/2

_T

R)

level

low

ers.

16

When

R

CS

p

ress

ure

is

le

ss

than

0.5

M

Pa,

ver

ify G

IS a

ctu

atio

n:

(1)

GIS

flo

w i

s ri

sing i

n b

oth

tra

ins;

(2)

GIS

tan

ks

level

low

erin

g.

Syst

em

s

R

CS

pre

ssure

(R

CS

PT

01_T

R)

is l

ess

than

0.5

MP

a;

G

IS f

low

into

RC

S (

GIS

FT

01/2

_T

R)

risi

ng

;

G

IS t

anks

(GIS

TL

01/2

_T

R)

level

low

erin

g.

17

Ch

eck

rea

cto

r is

sta

ble

:

(1)

Neu

tro

n f

lux i

s no

t ri

sing a

nd S

UR

is

no

t

po

siti

ve;

(2)

Bo

ron c

once

ntr

atio

n i

s ri

sing

;

(3)

RC

S s

ub

coo

ling p

osi

tive;

(4)

RC

S t

emp

erat

ure

is

stab

le o

r lo

wer

ing.

Syst

em

s

N

eutr

on p

ow

er (

RC

SN

P01_T

R)

is

no

t ri

sing

;

R

CS

bo

ron c

once

ntr

atio

n (

RC

S_B

C)

is r

isin

g;

S

tart

-up r

ate

(RC

S_S

UR

_T

R)

is l

ess

than

zer

o;

R

CS

tem

per

ature

(R

CS

TE

01_T

R)

is

stab

le o

r lo

wer

ing.

Page 83: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

74

3.6

. S

TA

TIO

N B

LA

CK

OU

T (

SB

O)

The

stat

ion b

lack

ou

t (S

BO

) ex

ercis

e st

eps

are

list

ed i

n T

able

11.

TA

BL

E 1

1. S

TA

TIO

N B

LA

CK

OU

T (

cont.

)

MA

LF

UN

CT

ION

: S

M-G

EN

-1

DE

SC

RIP

TIO

N:

Sta

tio

n b

lack

out

(tota

l lo

ss o

f A

C p

ow

er)

ST

EP

ID

.

PR

OC

ED

UR

E S

TE

PS

G

UI

SH

EE

T

EX

PE

CT

ED

RE

SP

ON

SE

S

TA

TE

Set

up

Res

et t

he

sim

ula

tor

to I

C #

1 ‘

100%

BO

L n

atura

l cir

cula

tio

n’

or

IC #

4 ‘

100%

BO

L f

orc

ed c

ircu

lati

on’.

Init

ial C

ond

itio

ns

Ch

eck

the

follo

win

g v

aria

ble

s ar

e st

able

:

(1)

Neu

tro

n p

ow

er (

%);

(2)

Sta

rt-u

p r

ate

(SU

R)

(dpm

);

(3)

Ther

mal

po

wer

(M

W(t

h))

;

(4)

Gen

erat

or

load

(M

W(e

));

(5)

Co

ntr

ol ro

d p

osi

tio

n (

step

s);

(6)

Co

nd

ense

r pre

ssure

(m

mH

g);

(7)

Ste

am p

ress

ure

(M

Pa)

;

(8)

FW

flo

w (

kg/s

);

(9)

FW

tem

per

ature

(ºC

);

(10

) T

avg (

ºC);

(11

) P

ress

uri

zer

pre

ssure

(M

Pa)

;

(12

) P

ress

uri

zer

level (%

).

Over

vie

w

Ro

d p

osi

tio

n c

ontr

ol

All

var

iable

s st

able

at:

(1)

100%

;

(2)

0 d

pm

;

(3)

150 M

W(t

h);

(4)

45 M

W(e

);

(5)

80 s

teps;

(6)

47.3

mm

Hg

;

(7)

2.7

MP

a;

(8)

78 k

g/s

;

(9)

173ºC

;

(10) 2

87.5

ºC;

(11) 1

5.5

MP

a;

(12) 4

3%

.

Page 84: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

75

TA

BL

E 1

1. S

TA

TIO

N B

LA

CK

OU

T (

cont.

)

MA

LF

UN

CT

ION

: S

M-G

EN

-1

DE

SC

RIP

TIO

N:

Sta

tio

n b

lack

out

(tota

l lo

ss o

f A

C p

ow

er)

ST

EP

ID

.

PR

OC

ED

UR

E S

TE

PS

G

UI

SH

EE

T

EX

PE

CT

ED

RE

SP

ON

SE

S

TA

TE

1

Ch

eck

the

follo

win

g c

ond

itio

ns:

(1)

Rea

cto

r po

wer

at

100%

;

(2)

Tu

rbin

e lo

ad a

t 45 M

W;

(3)

Co

ntr

ol ro

ds

in a

uto

;

(4)

FW

syst

em

in a

uto

;

(5)

CW

and

co

ndensa

te s

yst

em

s in

ser

vic

e;

(6)

No

act

ive

ala

rms.

2

Lo

ad 'S

tati

on b

lack

out’

malf

unct

ion (

SM

-GE

N-1

).

3

Ver

ify m

alf

unct

ion:

(1)

All

fo

ur

RC

Ps

trip

(if

pre

vio

usl

y

run

nin

g);

(2)

FW

pu

mp

s tr

ip;

(3)

CW

pu

mp

s tr

ip.

Syst

em

s

A

ll f

our

RC

Ps

(RC

SP

01/2

/3/4

) tr

ip

(if

pre

vio

usl

y r

unnin

g);

F

W p

um

ps

(FW

SP

01/0

2)

trip

;

C

W p

um

ps

trip

(C

WS

P01/2

);

F

WS

iso

lati

on.

4

Ver

ify r

eact

or

trip

:

(1)

Ver

ify a

ll c

ontr

ol and s

hutd

ow

n r

ods

are

have

full

y i

nse

rted

;

(2)

Ch

eck

neu

tro

n f

lux i

s lo

wer

ing a

nd

Sta

rt-u

p r

ate

is n

egat

ive.

Ro

d p

osi

tio

n c

ontr

ol

S

hutd

ow

n a

nd c

ontr

ol bank

s at

bo

tto

m;

N

eutr

on p

ow

er (

RC

SN

P01_T

R)

low

ers;

S

tart

-up r

ate

(RC

S_S

UR

_T

R)

is l

ess

than

zer

o;

R

eact

or

trip

on F

WS

pu

mps

trip

.

Page 85: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

76

TA

BL

E 1

1. S

TA

TIO

N B

LA

CK

OU

T (

cont.

)

MA

LF

UN

CT

ION

: S

M-G

EN

-1

DE

SC

RIP

TIO

N:

Sta

tio

n b

lack

out

(tota

l lo

ss o

f A

C p

ow

er)

ST

EP

ID

.

PR

OC

ED

UR

E S

TE

PS

G

UI

SH

EE

T

EX

PE

CT

ED

RE

SP

ON

SE

S

TA

TE

5

Ver

ify t

urb

ine

trip

:

(1)

Ver

ify t

her

e is

no

ste

am f

low

go

ing t

o

the

turb

ine.

Syst

em

s

M

SS

to

TU

R f

low

(M

SS

FT

04_T

R)

go

es t

o z

ero (

MS

SV

08 i

s a

‘fail

clo

se’

valv

e);

M

SS

to

CN

R f

low

(M

SS

FT

05_T

R)

is z

ero

(M

SS

V09 is

a ‘f

ail

clo

se’

valv

e);

T

urb

ine

trip

and g

ener

ato

r bre

aker

open

ala

rms.

6

Ver

ify p

ow

er s

upp

ly:

(1)

Off

site

po

wer

lig

ht

is o

ff;

(2)

Em

erg

ency d

iese

l li

ght

is o

ff;

(3)

Bat

tery

lig

ht

is o

n.

7

Ver

ify m

ain

ste

am

safe

ty v

alv

es a

re d

um

pin

g

stea

m t

o a

tmo

spher

e.

Syst

em

s

M

SS

V03/4

open

;

S

afe

ty v

alv

e re

lief

setp

oin

t is

5.7

0

MP

a.

NO

TE

A

DS

valv

es

are

fail

clo

se v

alv

es.

On a

sta

tio

n b

lack

out

even

t, A

DS

valv

es

clo

se t

o a

vo

id a

n u

nnec

essa

ry b

reac

h o

n t

he

reac

tor

coo

lant

pre

ssure

bo

undar

y.

Thes

e valv

es

sho

uld

be

po

wer

ed fr

om

it

s ass

ocia

ted bat

teri

es

befo

re th

ey ar

e fu

lly

dis

char

ged

.

Page 86: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

77

TA

BL

E 1

1. S

TA

TIO

N B

LA

CK

OU

T (

cont.

)

MA

LF

UN

CT

ION

: S

M-G

EN

-1

DE

SC

RIP

TIO

N:

Sta

tio

n b

lack

out

(tota

l lo

ss o

f A

C p

ow

er)

ST

EP

ID

.

PR

OC

ED

UR

E S

TE

PS

G

UI

SH

EE

T

EX

PE

CT

ED

RE

SP

ON

SE

S

TA

TE

8

Ch

eck

DH

R a

ctu

atio

n:

(1)

Ver

ify t

her

e is

flo

w t

hro

ugh b

oth

DH

R

leg

s;

(2)

Ch

eck

ther

e is

no

flo

w t

hro

ugh b

oth

MS

lin

es;

(3)

Ch

eck

in c

ase

ther

e is

sm

all

fee

dw

ater

flo

w i

s bein

g d

um

ped

thro

ugh s

afet

y

valv

es.

Syst

em

s

D

HR

inle

t an

d o

utl

et i

sola

tio

n v

alv

es

(DH

RV

02/0

4/0

1/0

3)

are

‘fail

open’

valv

es;

M

S i

sola

tio

n v

alv

es (

MS

SV

05/0

6)

are

‘fail

clo

se’

valv

es;

F

W i

sola

tio

n v

alv

es

(FW

SV

15/1

6)

are

‘fail

clo

se’

valv

es;

P

DH

R a

ctuat

ion a

larm

.

9

Ch

eck

DH

R o

per

atio

n:

(1)

RC

S t

emp

erat

ure

is

stab

le o

r lo

wer

ing

;

(2)

CB

DH

R p

oo

ls t

emper

ature

s ar

e ri

sing.

Syst

em

s

R

CS

tem

per

ature

(R

CS

TE

01_T

R)

is

stab

le o

r lo

wer

ing

;

C

B D

HR

poo

l te

mper

ature

s

(CB

ST

E01/2

_T

R)

are

risi

ng.

10

When

R

CS

p

ress

ure

is

le

ss th

an 5.0

M

Pa,

ver

ify P

IS a

ctu

atio

n:

(1)

PIS

flo

w r

isin

g i

n b

oth

tra

ins;

(2)

PIS

tan

ks

level

low

erin

g.

Syst

em

s

P

IS f

low

into

RC

S (

PIS

FT

01/2

_T

R)

rise

s;

P

IS t

anks

(PIS

TL

01/2

_T

R)

level

low

ers.

Page 87: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

78

TA

BL

E 1

1. S

TA

TIO

N B

LA

CK

OU

T (

cont.

)

MA

LF

UN

CT

ION

: S

M-G

EN

-1

DE

SC

RIP

TIO

N:

Sta

tio

n b

lack

out

(tota

l lo

ss o

f A

C p

ow

er)

ST

EP

ID

.

PR

OC

ED

UR

E S

TE

PS

G

UI

SH

EE

T

EX

PE

CT

ED

RE

SP

ON

SE

S

TA

TE

11

Ch

eck

co

re s

tatu

s:

(1)

Neu

tro

n f

lux i

s no

t ri

sing a

nd S

UR

is

no

t po

siti

ve;

(2)

Nat

ura

l cir

cula

tio

n i

s m

ain

tain

ing

coo

lant

flo

w.

Syst

em

s

N

eutr

on p

ow

er (

RC

SN

P01_T

R)

is

no

t ri

sing

;

S

tart

-up r

ate

(RC

S_S

UR

_T

R)

is l

ess

than

zer

o;

C

oo

lant

flo

w (

RC

SF

T01_T

R)

is n

ot

zero

.

12

Ch

eck

rea

cto

r is

sta

ble

:

(1)

Bo

ron c

once

ntr

atio

n i

s ri

sing

;

(2)

RC

S s

ub

coo

ling i

s po

siti

ve;

(3)

RC

S t

emp

erat

ure

is

stab

le o

r lo

wer

ing.

Syst

em

s

R

CS

bo

ron c

once

ntr

atio

n (

RC

S_B

C)

is r

isin

g;

S

tart

-up r

ate

(RC

S_S

UR

_T

R)

is l

ess

than

zer

o;

R

CS

tem

per

ature

(R

CS

TE

01_T

R)

is

stab

le o

r lo

wer

ing.

Page 88: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

79

Page 89: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

80

3.7

. S

TE

AM

LIN

E I

SO

LA

TIO

N

The

stea

m l

ine

iso

lati

on e

xer

cis

e st

eps

are

list

ed i

n T

able

12.

TA

BL

E 1

2. S

TE

AM

LIN

E I

SO

LA

TIO

N (

cont.

)

MA

LF

UN

CT

ION

: C

M-V

LV

-MO

T-8

D

ES

CR

IPT

ION

: In

adver

tent

main

ste

am

lin

e is

ola

tio

n

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

Set

up

Res

et t

he

sim

ula

tor

to I

C #

1 ‘

100%

BO

L n

atura

l cir

cula

tio

n’

or

IC #

4 ‘

100%

BO

L f

orc

ed c

ircu

lati

on’.

Init

ial C

ond

itio

ns

Ch

eck

the

follo

win

g v

aria

ble

s ar

e st

able

:

(1)

Neu

tro

n p

ow

er (

%);

(2)

Sta

rt-u

p r

ate

(SU

R)

(dpm

);

(3)

Ther

mal

po

wer

(M

W(t

h))

;

(4)

Gen

erat

or

load

(M

W(e

));

(5)

Co

ntr

ol ro

d p

osi

tio

n (

step

s);

(6)

Co

nd

ense

r pre

ssure

(m

mH

g);

(7)

Ste

am p

ress

ure

(M

Pa)

;

(8)

FW

flo

w (

kg/s

);

(9)

FW

tem

per

ature

(ºC

);

(10

) T

avg (

ºC);

(11

) P

ress

uri

zer

pre

ssure

(M

Pa)

;

(12

) P

ress

uri

zer

level (%

).

Over

vie

w

Ro

d p

osi

tio

n c

ontr

ol

All

var

iable

s st

able

at:

(1)

100%

;

(2)

0 d

pm

;

(3)

150 M

W(t

h);

(4)

45 M

W(e

);

(5)

80 s

teps;

(6)

47.3

mm

Hg

;

(7)

2.7

MP

a;

(8)

78 k

g/s

;

(9)

173ºC

;

(10) 2

87.5

ºC;

(11) 1

5.5

MP

a;

(12) 4

3%

.

Page 90: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

81

TA

BL

E 1

2. S

TE

AM

LIN

E I

SO

LA

TIO

N (

cont.

)

MA

LF

UN

CT

ION

: C

M-V

LV

-MO

T-8

D

ES

CR

IPT

ION

: In

adver

tent

main

ste

am

lin

e is

ola

tio

n

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

1

Ch

eck

the

follo

win

g c

ond

itio

ns:

(1)

Rea

cto

r is

at

100%

;

(2)

Tu

rbin

e lo

ad i

s at

45 M

W;

(3)

Co

ntr

ol ro

ds

in a

uto

;

(4)

FW

syst

em

in a

uto

;

(5)

CW

syst

em

and c

onden

sate

syst

em

s in

serv

ice;

(6)

No

act

ive

ala

rms.

2

Lo

ad:

Co

nfi

g �

Gen

eric

malf

unct

ion �

VL

V �

MS

S �

MS

SV

05/M

SS

V06 �

Clo

se (

bo

th o

f th

em)

3

Ver

ify m

alf

unct

ion:

(1)

Ver

ify b

oth

MS

S iso

lati

on v

alv

es c

lose

;

(2)

Ch

eck

bo

th M

SS

lin

e pre

ssure

s ar

e

risi

ng

;

(3)

Ch

eck

MS

S h

eader

pre

ssure

dro

ps.

Syst

em

s

B

oth

MS

S i

sola

tio

n v

alv

es

(MS

SV

05/6

) cl

ose

;

M

SS

lin

e pre

ssure

s

(MS

SP

T01/2

_T

R)

rise

;

M

SS

hea

der

pre

ssure

(MS

SP

T03_T

R)

dro

ps

belo

w 1

.0

MP

a, c

ausi

ng F

WS

pu

mps

trip

.

Page 91: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

82

TA

BL

E 1

2. S

TE

AM

LIN

E I

SO

LA

TIO

N (

cont.

)

MA

LF

UN

CT

ION

: C

M-V

LV

-MO

T-8

D

ES

CR

IPT

ION

: In

adver

tent

main

ste

am

lin

e is

ola

tio

n

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

4

Ver

ify r

eact

or

trip

:

(1)

Ver

ify a

ll c

ontr

ol and s

hutd

ow

n r

ods

are

full

y i

nse

rted

;

(2)

Ch

eck

neu

tro

n f

lux i

s lo

wer

ing a

nd

Sta

rt-u

p r

ate

is n

egat

ive.

Ro

d p

osi

tio

n

contr

ol

R

eact

or

trip

s o

n F

WS

pu

mps

trip

;

C

ontr

ol ro

d p

osi

tio

n a

t bott

om

;

N

eutr

on p

ow

er (

RC

SN

P01_T

R)

low

ers;

S

tart

-up r

ate

(RC

S_S

UR

_T

R)

is l

ess

than

zer

o;

R

eact

or

trip

ala

rm.

5

Ver

ify t

urb

ine

trip

:

(1)

Ver

ify t

urb

ine

contr

ol valv

e M

SS

V07

has

clo

sed

.

Syst

em

s

M

SS

to

TU

R f

low

(M

SS

FT

04_T

R)

go

es t

o z

ero

;

B

oth

main

ste

am

iso

lati

on v

alv

es

(MS

SV

05/6

) hav

e clo

sed

;

M

SS

flo

w t

hro

ugh m

ain

reli

ef

valv

es

(MS

SV

01/2

);

T

urb

ine

trip

and g

ener

ato

r bre

aker

open

ala

rms.

6

Ch

eck

DH

R a

ctuat

ion:

(1)

Ver

ify D

HR

inle

t an

d o

utl

et i

sola

tio

n

valv

es

hav

e o

pen

ed a

nd t

her

e is

flo

w

thro

ug

h b

oth

leg

s;

(2)

Ch

eck

FW

S i

sola

tio

n.

Syst

em

s

D

HR

inle

t an

d o

utl

et i

sola

tio

n v

alv

es

(DH

RV

02/0

4/0

1/0

3)

hav

e o

pen

ed

and t

her

e is

flo

w t

hro

ugh b

oth

(DH

RF

T01/2

_T

R);

B

oth

main

FW

iso

lati

on v

alv

es

(FW

SV

15/1

6)

have

clo

sed

;

P

DH

R a

ctuat

ion a

larm

.

Page 92: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

83

TA

BL

E 1

2. S

TE

AM

LIN

E I

SO

LA

TIO

N (

cont.

)

MA

LF

UN

CT

ION

: C

M-V

LV

-MO

T-8

D

ES

CR

IPT

ION

: In

adver

tent

main

ste

am

lin

e is

ola

tio

n

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

7

Ch

eck

DH

R o

per

atio

n:

(1)

RC

S t

emp

erat

ure

is

stab

le o

r lo

wer

ing

;

(2)

CB

DH

R p

oo

ls t

emper

ature

s ar

e ri

sing.

Syst

em

s

R

CS

tem

per

ature

(R

CS

TE

01_T

R)

is

stab

le o

r lo

wer

ing

;

C

B D

HR

poo

l te

mper

ature

s

(CB

ST

E01/2

_T

R)

are

risi

ng.

8

Blo

ck A

DS

act

uat

ion:

(1)

Pre

ss B

LO

CK

on t

rips

dis

pla

y;

(2)

Ver

ify A

DS

blo

ck s

tatu

s li

ght

is o

n.

Tri

ps

A

DS

blo

ck a

ctuat

ed t

o a

vo

id A

DS

actu

atio

n.

9

Ch

eck

rea

cto

r is

sta

ble

:

(1)

Neu

tro

n f

lux i

s no

t ri

sing a

nd S

UR

is

no

t po

siti

ve;

(2)

RC

S f

low

> 0

;

(3)

RC

S t

emp

erat

ure

is

stab

le o

r lo

wer

ing.

Syst

em

s

N

eutr

on p

ow

er (

RC

SN

P01_T

R)

is

no

t ri

sing

;

R

CS

coo

lant

flo

w r

ate

(RC

SF

T01_T

R)

is n

on-z

ero

;

S

tart

-up r

ate

(RC

S_S

UR

_T

R)

is l

ess

than

zer

o;

R

CS

tem

per

ature

(R

CS

TE

01_T

R)

is

stab

le o

r lo

wer

ing.

Page 93: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

84

3.8

. P

RE

SS

UR

IZE

R S

AF

ET

Y V

AL

VE

OP

EN

ING

The

reac

tor

coo

lant

trip

exer

cis

e st

eps

are

list

es i

n T

able

13.

TA

BL

E 1

3.

RE

AC

TO

R C

OO

LA

NT

TR

IP (

cont.

)

MA

LF

UN

CT

ION

: C

M-V

LV

-SE

G-2

D

ES

CR

IPT

ION

: In

adver

tent

open

ing o

f pre

ssuri

zer

safe

ty v

alv

e (L

OC

A)

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

Set

up

Res

et t

he

sim

ula

tor

to I

C #

1 ‘

100%

BO

L n

atura

l cir

cula

tio

n’

or

IC #

4 ‘

100%

BO

L f

orc

ed c

ircu

lati

on’.

Init

ial C

ond

itio

ns

Ch

eck

the

follo

win

g v

aria

ble

s ar

e st

able

:

(1)

Neu

tro

n p

ow

er (

%);

(2)

Sta

rt-u

p r

ate

(SU

R)

(dpm

);

(3)

Ther

mal

po

wer

(M

W(t

h))

;

(4)

Gen

erat

or

load

(M

W(e

));

(5)

Co

ntr

ol ro

d p

osi

tio

n (

step

s);

(6)

Co

nd

ense

r pre

ssure

(m

mH

g);

(7)

Ste

am p

ress

ure

(M

Pa)

;

(8)

FW

flo

w (

kg/s

);

(9)

FW

tem

per

ature

(ºC

);

(10

) T

avg (

ºC);

(11

) P

ress

uri

zer

pre

ssure

(M

Pa)

;

(12

) P

ress

uri

zer

level (%

).

Over

vie

w

Ro

d p

osi

tio

n c

ontr

ol

All

var

iable

s st

able

at:

(1)

100%

;

(2)

0 d

pm

;

(3)

150 M

W(t

h);

(4)

45 M

W(e

);

(5)

80 s

teps;

(6)

47.3

mm

Hg

;

(7)

2.7

MP

a;

(8)

78 k

g/s

;

(9)

173ºC

;

(10) 2

87.5

ºC;

(11) 1

5.5

MP

a;

(12) 4

3%

.

Page 94: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

85

TA

BL

E 1

3.

RE

AC

TO

R C

OO

LA

NT

TR

IP (

cont.

)

MA

LF

UN

CT

ION

: C

M-V

LV

-SE

G-2

D

ES

CR

IPT

ION

: In

adver

tent

open

ing o

f pre

ssuri

zer

safe

ty v

alv

e (L

OC

A)

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

1

Ch

eck

the

follo

win

g c

ond

itio

ns:

(1)

Rea

cto

r po

wer

at

100%

;

(2)

Tu

rbin

e lo

ad a

t 45 M

W;

(3)

Co

ntr

ol ro

ds

in a

uto

;

(4)

FW

syst

em

in a

uto

;

(5)

CW

and

co

ndensa

te s

yst

em

s in

ser

vic

e;

(6)

No

act

ive

ala

rms.

2

Lo

ad:

Co

nfi

g �

Gen

eric

malf

unct

ion �

VL

V �

RC

S �

RC

SV

01 �

Lea

kag

e

3

Ver

ify m

alf

unct

ion:

(1)

Ch

eck

RC

SV

01 o

pen

s;

(2)

Ch

eck

RC

S p

ress

ure

beg

ins

to d

rop;

(3)

CB

sup

pre

ssio

n p

oo

l te

mper

ature

beg

ins

to r

ise;

(4)

Subco

oli

ng l

oss

.

Syst

em

s

R

CS

pre

ssure

(R

CS

PT

01_T

R)

dro

ps;

C

B s

uppre

ssio

n p

oo

l te

mper

ature

(CB

ST

E03_T

R)

rise

s.

4

Ver

ify r

eact

or

trip

:

(1)

Ver

ify a

ll c

ontr

ol and s

hutd

ow

n r

ods

are

full

y i

nse

rted

;

(2)

Ch

eck

neu

tro

n f

lux i

s lo

wer

ing a

nd

Sta

rt-u

p r

ate

is n

egat

ive.

Ro

d p

osi

tio

n

contr

ol

C

ontr

ol ro

d p

osi

tio

n c

hang

es;

N

eutr

on p

ow

er (

RC

SN

P01_T

R)

low

ers;

S

tart

-up r

ate

(RC

S_S

UR

_T

R)

is l

ess

than

zer

o;

R

eact

or

trip

ala

rm.

Page 95: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

86

TA

BL

E 1

3.

RE

AC

TO

R C

OO

LA

NT

TR

IP (

cont.

)

MA

LF

UN

CT

ION

: C

M-V

LV

-SE

G-2

D

ES

CR

IPT

ION

: In

adver

tent

open

ing o

f pre

ssuri

zer

safe

ty v

alv

e (L

OC

A)

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

5

Ver

ify t

urb

ine

trip

:

(1)

Ver

ify t

urb

ine

contr

ol valv

e M

SS

V07

has

clo

sed

;

(2)

Ver

ify M

SB

is

tak

ing m

ain

ste

am

flo

w

to C

NR

.

Syst

em

s

M

SS

to

TU

R f

low

(M

SS

FT

04_T

R)

go

es t

o z

ero

;

M

SS

to

CN

R f

low

(M

SS

FT

05_T

R)

rise

s;

T

urb

ine

trip

and g

ener

ato

r bre

aker

open

ala

rms.

6

When

up

per

ple

nu

m p

ress

ure

< 9

MP

a (

Lo

w-

Lo

w),

ver

ify A

DS

act

uat

ion:

(1)

AD

S v

alv

es o

pen

seq

uenti

all

y w

ith f

low

thro

ug

h e

ach v

alv

e;

(2)

RC

Ps

trip

(if

pre

vio

usl

y r

unnin

g).

Tri

ps

L

ow

pre

ssure

upper

ple

nu

m

(RC

SP

T02_T

R)

< 9

.0 M

Pa

is

expect

ed t

o o

ccur

firs

t;

A

DS

valv

es o

pen

seq

uenti

all

y w

ith 5

min

tim

e dela

ys;

F

low

ris

ing t

hro

ugh a

ll t

hre

e A

DS

valv

es

(AD

S_

W1/2

/3);

A

DS

act

uat

ion a

larm

.

7

If A

DS

act

uat

ion h

as o

ccurr

ed,

chec

k A

DS

op

erat

ion:

(1)

RC

S p

ress

ure

lo

wer

s;

(2)

CB

sup

pre

ssio

n p

oo

l te

mper

ature

ris

es,

and

dis

con

nect

PZ

R h

eate

rs.

Syst

em

s

PZ

R p

ress

ure

contr

ol

R

CS

pre

ssure

(R

CS

PT

02_T

R)

low

ers;

C

B s

uppre

ssio

n p

oo

l te

mper

ature

(CB

ST

E03_T

R)

rise

s.

Page 96: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

87

TA

BL

E 1

3.

RE

AC

TO

R C

OO

LA

NT

TR

IP (

cont.

)

MA

LF

UN

CT

ION

: C

M-V

LV

-SE

G-2

D

ES

CR

IPT

ION

: In

adver

tent

open

ing o

f pre

ssuri

zer

safe

ty v

alv

e (L

OC

A)

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

8

RC

S t

emp

erat

ure

is

stab

le o

r lo

wer

ing.

Syst

em

s

R

CS

tem

per

ature

(R

CS

TE

01_T

R)

is

stab

le o

r lo

wer

ing.

9

Ch

eck

co

re s

tatu

s:

(1)

Neu

tro

n f

lux i

s no

t ri

sing a

nd S

UR

is

no

t po

siti

ve;

(2)

Nat

ura

l cir

cula

tio

n i

s m

ain

tain

ing

coo

lant

flo

w.

Syst

em

s

N

eutr

on p

ow

er (

RC

SN

P01_T

R)

is

no

t po

siti

ve;

S

tart

-up r

ate

(RC

S_S

UR

_T

R)

is l

ess

than

zer

o;

C

oo

lant

flo

w (

RC

SF

T01_T

R)

is

po

siti

ve.

10

When

R

CS

p

ress

ure

is

le

ss th

an 5.0

M

Pa,

ver

ify P

IS a

ctu

atio

n:

(1)

PIS

flo

w r

isin

g i

n b

oth

tra

ins;

(2)

PIS

tan

ks

level

low

erin

g.

Syst

em

s

P

IS f

low

into

RC

S (

PIS

FT

01/2

_T

R)

rise

s;

P

IS t

anks

(PIS

TL

01/2

_T

R)

level

low

ers.

11

When

main

st

eam

hea

der

pre

ssure

re

aches

1.0

MP

a, v

erif

y:

(1)

FW

pu

mp

s tr

ip;

(2)

PD

HR

act

uat

es.

Syst

em

s

R

CS

tem

per

ature

(R

CS

TE

01_T

R)

is

stab

le o

r lo

wer

ing

;

C

B D

HR

poo

l te

mper

ature

s

(CB

ST

E01/2

_T

R)

are

risi

ng;

M

SS

/FW

S i

sola

tio

n a

nd D

HR

actu

atio

n a

larm

.

Page 97: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

88

TA

BL

E 1

3.

RE

AC

TO

R C

OO

LA

NT

TR

IP (

cont.

)

MA

LF

UN

CT

ION

: C

M-V

LV

-SE

G-2

D

ES

CR

IPT

ION

: In

adver

tent

open

ing o

f pre

ssuri

zer

safe

ty v

alv

e (L

OC

A)

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

12

When

R

CS

p

ress

ure

is

le

ss th

an 0.5

M

Pa,

ver

ify G

IS a

ctu

atio

n:

(1)

GIS

flo

w i

s ri

sing i

n b

oth

tra

ins;

(2)

GIS

tan

ks

level

low

erin

g.

Syst

em

s

G

IS f

low

into

RC

S (

GIS

FT

01/2

_T

R)

risi

ng

;

G

IS t

anks

(GIS

TL

01/2

_T

R)

level

low

erin

g.

13

Ch

eck

rea

cto

r is

sta

ble

:

(1)

Neu

tro

n f

lux i

s no

t ri

sing a

nd S

UR

is

no

t po

siti

ve;

(2)

Bo

ron c

once

ntr

atio

n i

s ri

sing

;

(3)

Nat

ura

l cir

cula

tio

n i

s m

ain

tain

ing

reac

tor

coo

lant

flo

w;

(4)

RC

S s

ub

coo

ling >

0;

(5)

RC

S t

emp

erat

ure

is

stab

le o

r lo

wer

ing.

Syst

em

s

N

eutr

on p

ow

er (

RC

SN

P01_T

R)

is

no

t po

siti

ve;

R

CS

bo

ron c

once

ntr

atio

n (

RC

S_B

C)

is r

isin

g;

R

CS

flo

w r

ate

(RC

SF

T01_T

R)

is

no

n-z

ero

;

S

tart

-up r

ate

(RC

S_S

UR

_T

R)

is l

ess

than

zer

o;

R

CS

tem

per

ature

(R

CS

TE

01_T

R)

is

stab

le o

r lo

wer

ing.

Page 98: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

89

Page 99: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

90

3.9

. R

EA

CT

OR

CO

OL

AN

T P

UM

P T

RIP

The

reac

tor

coo

lant

trip

exer

cis

e st

eps

are

list

ed i

n T

able

14.

TA

BL

E 1

4.

RE

AC

TO

R C

OO

LA

NT

TR

IP (

cont.

)

MA

LF

UN

CT

ION

: C

M-B

OM

-BO

M-6

D

ES

CR

IPT

ION

: R

eact

or

coo

lant

pum

p t

rip

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

Set

up

Res

et t

he

sim

ula

tor

to I

C #

4 ‘

100%

BO

L f

orc

ed c

ircu

lati

on’.

Init

ial C

ond

itio

ns

Ch

eck

the

follo

win

g v

aria

ble

s ar

e st

able

:

(1)

Neu

tro

n p

ow

er (

%);

(2)

Sta

rt-u

p r

ate

(SU

R)

(dpm

);

(3)

Ther

mal

po

wer

(M

W(t

h))

;

(4)

Gen

erat

or

load

(M

W(e

));

(5)

Co

ntr

ol ro

d p

osi

tio

n (

step

s);

(6)

Co

nd

ense

r pre

ssure

(m

mH

g);

(7)

Ste

am p

ress

ure

(M

Pa)

;

(8)

FW

flo

w (

kg/s

);

(9)

FW

tem

per

ature

(ºC

);

(10

) T

avg (

ºC);

(11

) P

ress

uri

zer

pre

ssure

(M

Pa)

;

(12

) P

ress

uri

zer

level (%

).

Over

vie

w

Ro

d p

osi

tio

n c

ontr

ol

All

var

iable

s st

able

at:

(1)

100%

;

(2)

0 d

pm

;

(3)

150 M

W(t

h);

(4)

45 M

W(e

);

(5)

80 s

teps;

(6)

47.3

mm

Hg

;

(7)

2.7

MP

a;

(8)

78 k

g/s

;

(9)

173ºC

;

(10) 2

87.5

ºC;

(11) 1

5.5

MP

a;

(12) 4

3%

.

Page 100: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

91

TA

BL

E 1

4.

RE

AC

TO

R C

OO

LA

NT

TR

IP (

cont.

)

MA

LF

UN

CT

ION

: C

M-B

OM

-BO

M-6

D

ES

CR

IPT

ION

: R

eact

or

coo

lant

pum

p t

rip

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

1

Ch

eck

the

follo

win

g c

ond

itio

ns:

(1)

Rea

cto

r po

wer

at

100%

;

(2)

Tu

rbin

e lo

ad a

t 45 M

W;

(3)

Co

ntr

ol ro

ds

in a

uto

;

(4)

FW

syst

em

in a

uto

;

(5)

CW

and

co

ndensa

te s

yst

em

s in

ser

vic

e;

(6)

No

act

ive

ala

rms.

2

Lo

ad:

Co

nfi

g �

Gen

eric

malf

unct

ion �

BO

M �

RC

S �

RC

SP

01 �

Ele

ctri

cal

fail

ure

3

Ver

ify m

alf

unct

ion:

(1)

1 R

CP

tri

ps;

(2)

RC

S f

low

lo

wer

s.

Syst

em

s

1 R

CP

tri

ps

(co

loure

d i

n r

ed);

R

CS

flo

w (

RC

SF

T01_T

R)

low

ers.

4

Ver

ify r

eact

or

step

bac

k:

(1)

Ver

ify c

ontr

ol ro

ds

inse

rt i

nto

the

core

;

(2)

Ver

ify r

eact

or

low

ers

to 5

0%

;

(3)

Ver

ify p

lant

mo

de

in r

eact

or

lead

ing

;

(4)

Ver

ify M

SB

in s

team

pre

ssure

mo

de.

Ro

d p

osi

tio

n

contr

ol

C

ontr

ol ro

d p

osi

tio

n c

hang

es;

N

eutr

on p

ow

er (

RC

SN

P01_T

R)

low

ers

to 5

0%

;

R

eact

or

step

bac

k a

larm

.

Page 101: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

92

TA

BL

E 1

4.

RE

AC

TO

R C

OO

LA

NT

TR

IP (

cont.

)

MA

LF

UN

CT

ION

: C

M-B

OM

-BO

M-6

D

ES

CR

IPT

ION

: R

eact

or

coo

lant

pum

p t

rip

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

5

Ver

ify t

urb

ine

resp

onse

to

rea

cto

r st

epbac

k:

(1)

Ver

ify t

urb

ine

contr

ol valv

e beg

ins

to

clo

se;

(2)

Ch

eck

tu

rbin

e lo

ad b

egin

s to

red

uce

to

50

% a

pp

rox.

Syst

em

s

M

SS

to

TU

R f

low

(M

SS

FT

04_T

R)

low

ers.

6

If p

lant

mo

de

was

in

itia

lly i

n t

urb

ine

lead

ing

mo

de:

(1)

Ver

ify p

lant

mo

de

has

changed

to

reac

tor

lead

ing m

ode;

(2)

Ver

ify M

SB

has

changed

fro

m T

av

g t

o

stea

m p

ress

ure

mo

de.

Ro

d p

osi

tio

n c

ontr

ol

S

ele

cto

r in

rea

ctor

lead

ing m

ode

(Ste

pbac

k);

S

ele

cto

r in

ste

am

pre

ssure

(pla

nt

mo

de

in r

eact

or

lead

ing).

7

Chec

k m

ain

ste

am

flo

w b

egin

s to

lo

wer

. S

yst

em

s

M

ain

ste

am

flo

w (

MS

SF

T01_T

R

and M

SS

FT

02_T

R)

low

ers.

8

Ch

eck

P

ZR

le

vel

beg

ins

to

low

er

due

to

coo

lant

contr

acti

on.

PZ

R l

evel

contr

ol

P

ZR

level

(RC

SL

T02_T

R)

beg

ins

to

low

er.

9

Ch

eck

var

iab

les

fro

m th

e in

itia

l co

nd

itio

ns

are

stab

le.

Syst

em

s

A

ll v

aria

ble

s st

able

at

50%

of

reac

tor

po

wer

.

Page 102: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

93

TA

BL

E 1

4.

RE

AC

TO

R C

OO

LA

NT

TR

IP (

cont.

)

MA

LF

UN

CT

ION

: C

M-B

OM

-BO

M-6

D

ES

CR

IPT

ION

: R

eact

or

coo

lant

pum

p t

rip

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

10

Fin

al

stat

e:

(1)

Bo

th r

eact

or

and t

urb

ine

at 5

0%

of

po

wer

;

(2)

Co

ntr

ol ro

ds

in a

uto

;

(3)

FW

syst

em

in a

uto

;

(4)

CW

and

co

ndense

r sy

stem

s in

ser

vic

e;

(5)

1 R

CP

tri

pped

.

Syst

em

s

S

tepbac

k a

larm

act

ivat

ed.

NO

TE

I sh

ou

ld b

e co

ntr

olled

as

follo

ws:

(a)

If ∆

I is

at

the

left

sid

e o

f th

e ta

rget

band,

rods

are

exces

sively

inse

rted

. T

his

mea

ns

that

ro

ds

dep

ress

neu

tro

n f

lux

in t

he

upper

half

of

the

core

and f

orc

e a

hig

h f

lux t

o e

xis

t in

the

low

er h

alf

. T

o m

ake

∆I

retu

rn t

o t

he

targ

et b

and

,

bo

rate

the

RC

S t

o m

ake

rods

wit

hdra

w f

rom

the

core

;

(b)

If ∆

I is

at

the

rig

ht

side

of

the

targ

et b

and,

rods

are

exce

ssiv

ely

wit

hdra

wn.

This

mea

ns

that

a h

i gher

flu

x e

xis

t in

the

upper

half

of

the

core

co

mpar

ed t

o t

he

low

er h

alf

. T

o m

ake ∆

I re

turn

to

the

targ

et b

and,

dil

ute

the

RC

S t

o

mak

e ro

ds

inse

rt i

nto

the

core

.

Page 103: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

94

3.1

0.

FO

UR

RE

AC

TO

R C

OO

LA

NT

PU

MP

S T

RIP

The

reac

tor

coo

lant

pu

ms

trip

(all

fo

ur)

exer

cis

e st

eps

are

list

ed i

n T

able

15.

TA

BL

E 1

5.

FO

UR

RE

AC

TO

R C

OO

LA

NT

PU

MP

S T

RIP

(co

nt.

)

MA

LF

UN

CT

ION

: C

M-B

OM

-BO

M-6

D

ES

CR

IPT

ION

: F

our

reac

tor

coo

lant

pu

mps

trip

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

Set

up

Res

et s

imu

lato

r to

IC

#4 ‘

100%

BO

L f

orc

ed c

ircu

lati

on’.

Init

ial C

ond

itio

ns

Ch

eck

the

follo

win

g v

aria

ble

s ar

e st

able

:

(1)

Neu

tro

n p

ow

er (

%);

(2)

Sta

rt-u

p r

ate

(SU

R)

(dpm

);

(3)

Ther

mal

po

wer

(M

W(t

h))

;

(4)

Gen

erat

or

load

(M

W(e

));

(5)

Co

ntr

ol ro

d p

osi

tio

n (

step

s);

(6)

Co

nd

ense

r pre

ssure

(m

mH

g);

(7)

Ste

am p

ress

ure

(M

Pa)

;

(8)

FW

flo

w (

kg/s

);

(9)

FW

tem

per

ature

(ºC

);

(10

) T

avg (

ºC);

(11

) P

ress

uri

zer

pre

ssure

(M

Pa)

;

(12

) P

ress

uri

zer

level (%

).

Over

vie

w

Ro

d p

osi

tio

n c

ontr

ol

All

var

iable

s st

able

at:

(1)

100%

;

(2)

0 d

pm

;

(3)

150 M

W(t

h);

(4)

45 M

W(e

);

(5)

80 s

teps;

(6)

47.3

mm

Hg

;

(7)

2.7

MP

a;

(8)

78 k

g/s

;

(9)

173ºC

;

(10) 2

87.5

ºC;

(11) 1

5.5

MP

a;

(12) 4

3%

.

Page 104: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

95

TA

BL

E 1

5.

FO

UR

RE

AC

TO

R C

OO

LA

NT

PU

MP

S T

RIP

(co

nt.

)

MA

LF

UN

CT

ION

: C

M-B

OM

-BO

M-6

D

ES

CR

IPT

ION

: F

our

reac

tor

coo

lant

pu

mps

trip

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

1

Ch

eck

the

follo

win

g c

ond

itio

ns:

(1)

Rea

cto

r po

wer

at

100%

;

(2)

Tu

rbin

e lo

ad a

t 45 M

W;

(3)

Co

ntr

ol ro

ds

in a

uto

;

(4)

FW

syst

em

in a

uto

;

(5)

CW

and

co

ndensa

te s

yst

em

s in

ser

vic

e;

(6)

No

act

ive

ala

rms.

2

Lo

ad '4

RC

P t

rip

' malf

unct

ion (

ele

ctri

cal

fail

ure

) or

SM

-RC

S-7

3

Ver

ify m

alf

unct

ion:

(1)

All

RC

Ps

trip

;

(2)

RC

S f

low

lo

wer

s;

Syst

em

Dis

pla

y

A

ll R

CP

s tr

ip (

red);

R

CS

flo

w (

RC

SF

T01_T

R)

low

ers.

4

Ver

ify r

eact

or

step

bac

k:

(1)

Ver

ify c

ontr

ol ro

ds

inse

rt i

nto

the

core

;

(2)

Ver

ify r

eact

or

low

ers

to 3

0%

;

Co

ntr

ol ro

ds

dis

pla

y

C

ontr

ol ro

d p

osi

tio

n c

hang

es;

N

eutr

on p

ow

er (

RC

SN

P01_T

R)

low

ers

to 3

0%

;

R

eact

or

step

bac

k a

larm

.

Page 105: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

96

TA

BL

E 1

5.

FO

UR

RE

AC

TO

R C

OO

LA

NT

PU

MP

S T

RIP

(co

nt.

)

MA

LF

UN

CT

ION

: C

M-B

OM

-BO

M-6

D

ES

CR

IPT

ION

: F

our

reac

tor

coo

lant

pu

mps

trip

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

5

Ver

ify t

urb

ine

resp

onse

to

rea

cto

r st

epbac

k:

(1)

Ver

ify t

urb

ine

contr

ol valv

e beg

ins

to

clo

se.

Syst

em

dis

pla

y

M

SS

to

TU

R f

low

(M

SS

FT

04_T

R)

low

ers.

6

If p

lant

mo

de

is i

n t

urb

ine

lead

ing m

ode:

(1)

Ver

ify p

lant

mo

de

has

changed

to

reac

tor

lead

ing m

ode;

(2)

Ver

ify M

SB

has

change

fro

m T

av

g t

o

stea

m p

ress

ure

mo

de.

Co

ntr

ol ro

ds

dis

pla

y

S

ele

cto

r in

rea

ctor

lead

ing m

ode

(ste

pbac

k);

S

ele

cto

r in

ste

am

pre

ssure

(pla

nt

mo

de

in r

eact

or

lead

ing).

7

Chec

k m

ain

ste

am

flo

w b

egin

s to

lo

wer

. S

yst

em

dis

pla

y

M

ain

ste

am

flo

w (

MS

SF

T01_T

R

and M

SS

FT

02_T

R)

low

ers.

8

Ch

eck

P

ZR

le

vel

beg

ins

to

low

er

due

to

coo

lant

contr

acti

on.

PZ

R l

evel

contr

ol

P

ZR

level

(RC

SL

T02_T

R)

beg

ins

to

low

er.

9

Chec

k var

iab

les

fro

m t

he

init

ial

cond

itio

ns

are

stab

le.

Syst

em

dis

pla

y

A

ll v

aria

ble

s st

able

at

30%

of

po

wer

.

Page 106: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

97

TA

BL

E 1

5.

FO

UR

RE

AC

TO

R C

OO

LA

NT

PU

MP

S T

RIP

(co

nt.

)

MA

LF

UN

CT

ION

: C

M-B

OM

-BO

M-6

D

ES

CR

IPT

ION

: F

our

reac

tor

coo

lant

pu

mps

trip

ST

EP

ID

. P

RO

CE

DU

RE

ST

EP

S

GU

I S

HE

ET

E

XP

EC

TE

D R

ES

PO

NS

E

ST

AT

E

10

Ch

eck

rea

cto

r is

sta

ble

:

(1)

Neu

tro

n f

lux i

s no

t ri

sing a

nd S

UR

is

no

t po

siti

ve;

(2)

Nat

ura

l cir

cula

tio

n i

s m

ain

tain

ing

Rea

cto

r co

ola

nt

flo

w;

(3)

RC

S s

ub

coo

ling

;

(4)

RC

S t

emp

erat

ure

is

reducin

g o

r st

able

.

Syst

em

dis

pla

y

R

od p

osi

tio

n w

ill

no

t be

stab

le a

s ro

d

contr

ol w

ill

be

com

pensa

ting t

he

neg

ativ

e re

acti

vit

y i

ntr

oduce

d b

y X

e.

NO

TE

I sh

ou

ld b

e co

ntr

olled

as

follo

ws:

(a)

If ∆

I is

at

the

left

sid

e o

f th

e ta

rget

ban

d,

rods

are

exce

ssiv

ely

inse

rted

. T

his

means

that

ro

ds

dep

ress

neu

tro

n f

lux

in t

he

upper

half

of

the

core

and f

orc

e a

hig

h f

lux t

o e

xis

t in

the

low

er h

alf

. T

o m

ake

∆I

retu

rn t

o t

he

targ

et b

and,

bo

rate

the

RC

S t

o m

ake

rods

wit

hdra

w f

rom

the

core

;

(b)

If ∆

I is

at

the

rig

ht

sid

e o

f th

e ta

rget

ban

d,

rods

are

exces

sively

wit

hdra

wn.

This

mea

ns

that

a h

igher

flu

x e

xis

t in

the

upper

half

of

the

core

co

mpar

ed t

o t

he

low

er h

alf

. T

o m

ake

∆I

retu

rn t

o t

he

targ

et b

and,

dil

ute

the R

CS

to

mak

e ro

ds

inse

rt i

nto

the

core

.

Page 107: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

98

Page 108: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

99

APPENDIX

A.1. SUMMARY OF THERMAL HYDRAULIC VARIABLES

The thermal hydraulic variables are listed in Table 16.

TABLE 16. THERMAL HYDRAULIC VARIABLES

Thermal hydraulic variable Value Units

Reactor neutron power 100.0 %

Thermal power 150.0 MW

Generator power 45.0 MW(e)

Primary pressure 15.5 MPa

Pressurizer level 43.0 %

Core level 100.0 %

Core flow 422.0 Kg/s

Inlet core temperature 255.51 ºC

Outlet core temperature 320.36 ºC

Average core temperature 288.0 ºC

Steam header pressure 2.72 MPa

Steam reheating 29.0 ºC

Steam flow 77.0 Kg/s

Feedwater flow 77.0 Kg/s

Feedwater temperature 173.0 ºC

Turbine speed 3600.0 rpm

Condenser vacuum 47.81 mmHg

Lake temperature 20.0 ºC

Containment pressure 0.011 MPa

Containment temperature 33.4 ºC

Page 109: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

100

A.2. THERMAL HYDRAULIC VARIABLES AT DIFFERENT POWERS

In order to understand the reactor conditions at different power levels, the thermal hydraulic

variables at differen powers are listed in Table 17-Table 22.

TABLE 17. 100% REACTOR POWER

Thermal hydraulic variable Value Units

Reactor neutron power 100.0 %

Thermal power 150.0 MW

Generator power 45.0 MW(e)

Primary pressure 15.5 MPa

Pressurizer level 43.0 %

Steam header pressure 2.72 MPa

Steam flow 77.0 Kg/s

TABLE 18. 75% REACTOR POWER

Thermal hydraulic variable Value Units

Reactor neutron power 75.0 %

Thermal power 113.0 MW

Generator power 33.75 MW(e)

Primary pressure 15.5 MPa

Pressurizer level 39.0 %

Steam header pressure 2.9 MPa

Steam flow 59.0 Kg/s

TABLE 19. 54% REACTOR POWER

Thermal hydraulic variable Value Units

Reactor neutron power 54.0 %

Thermal power 82.0 MW

Generator power 22.5 MW(e)

Primary pressure 15.5 MPa

Pressurizer level 34.0 %

Steam header pressure 3.15 MPa

Steam flow 42.0 Kg/s

TABLE 20. 30% REACTOR POWER

Thermal hydraulic variable Value Units

Reactor neutron power 30.0 %

Thermal power 47.0 MW

Generator power 11.25 MW(e)

Primary pressure 15.5 MPa

Pressurizer level 28.0 %

Steam header pressure 3.55 MPa

Steam flow 23.0 Kg/s

Page 110: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

101

TABLE 21. 20% REACTOR POWER

Thermal hydraulic variable Value Units

Reactor neutron power 20.0 %

Thermal power 31.0 MW

Generator power 6.75 MW(e)

Primary pressure 15.5 MPa

Pressurizer level 26.0 %

Steam header pressure 3.65 MPa

Steam flow 16.0 Kg/s

TABLE 22. 12% REACTOR POWER

Thermal hydraulic variable Value Units

Reactor neutron power 12.0 %

Thermal power 18.0 MW

Generator power 3.6 MW(e)

Primary pressure 15.5 MPa

Pressurizer level 25.0 %

Steam header pressure 3.7 MPa

Steam flow 10.0 Kg/s

Page 111: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

102

A.3. LIST OF MALFUNCTIONS

The specific malfunctions already present in the simulator are listed in Table 23.

TABLE 23. LIST OF MALFUNCTIONS

Number System Specific Malfunction

1 ADS Inadvertent initiation of ADS

2 CBS Loss of containment vacuum

3 CNR Loss of condenser vacuum

4 CWS Condenser coolant pumps trip

5 DHR Inadvertent initiation of decay heat removal system

6 FWS Reduction in feedwater temperature (loss of FW heating)

7 Abnormal increase in FW flow

8 Loss of normal feedwater flow (FW pumps trip)

9 Feedwater system pipe break

10 GEN Station blackout (loss of AC power)

11 MSS Steam header break

12 Steam generator tube failure 1

13 Steam generator tube failure 2

14 Major steam system piping failure within containment

15 RCS Reactor setback fail

16 One bank of shutdown control rods drop into the core

17 Charging (feed) valve fails open

18 Inadvertent operation of pressurizer heaters

19 Uncontrolled control rod assembly withdrawal at power

20 Fail of PZR control system

21 Failure of main coolant pumps

22 Reactor stepback fail

23 Seismic event

24 TUR Turbine spurious trip

25 Turbine spurious run-back

26 Turbine trip with bypass valves failed closed

Page 112: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

103

A.4. VARIABLES TO PLOT

The variables than can be plotted by the simulator are listed in Table 24.

TABLE 24. VARIABLES TO PLOT (cont.)

System Variable

ADS ADS total flow

ADS1 valve flow

ADS2 valve flow

ADS3 valve flow

CBS DHR1 pool level

DHR2 pool level

Suppression pool level

Sump level

Containment pressure

DHR1 pool temperature

DHR2 pool temperature

Suppression pool temperature

Containment temperature

CCS Containment coolant spray flow rate of train 1

Containment coolant spray flow rate of train 2

CNR Condenser level

Condenser pressure vacuum

CWS Coolant pump 1 power

Coolant pump 2 power

Condenser coolant flow

Coolant temperature at condenser inlet

Coolant temperature at condenser outlet

DHR Flow train 1

Flow train 2

FWS Feedwater total flow

Pump-1 speed

Pump-2 speed

Flow to steam generator 1

Flow to steam generator 2

Flow through heater 3

Flow through heater 2

Flow through heater 1

Water storage tank level

Header feedwater pressure

Feedwater line-1 pressure

Feedwater line-2 pressure

Pressure inlet heat exchanger-1

Inlet temperature to SG1

Inlet temperature to SG2

Heater -3 outlet temperature

Heater -2 outlet temperature

Page 113: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

104

TABLE 24. VARIABLES TO PLOT (cont.)

System Variable

Heater -1 outlet temperature

GEN Generator load

GIS Water injection flow from gravity driven injection system-1

Water injection flow from gravity driven injection system-2

Gravity driven injection tank1 level

Gravity driven injection tank2 level

MSS % turbine valve opening

% bypass valve opening

Steam flow rate line-1

Steam flow rate line-2

Total flow through pressure header

Steam flow to turbine

Steam flow to condenser

Steam pressure line 1

Steam pressure line 2

Pressure header

Steam temperature header

Saturation temperature

PIS Water injection flow from pressure injection system-1

Water injection flow from pressure injection system-2

Pressure injection system tank1 level

Pressure injection system tank2 level

RCS Boron concentration

Boron reactivity %dk/k

Boron reactivity pcm

Rod reactivity %dk/k

Rod reactivity pcm

Core reactivity %dk/k

Core reactivity pcm

Fuel reactivity (Doppler) %dk/k

Fuel reactivity (Doppler) pcm

Moderator temperature reactivity %dk/k

Moderator temperature reactivity pcm

Xe reactivity %dk/k

Xe reactivity pcm

Start-up rate (SUR)

Clad surface temperature average

Clad surface temperature max

Average fuel temperature

Peak fuel temperature

Reactor thermal power (%)

Reactor thermal power (MW)

Relief valve flow

Coolant flow rate

Flow charge

Page 114: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

105

TABLE 24. VARIABLES TO PLOT (cont.)

System Variable

Flow discharge

Spray flow

RPV water level

PZR level

Setpoint PZR level

Nuclear power

Power intermediate range

Power source range

RPV pressure

PZR Pressure

Coolant average temperature

Coolant temperature at core inlet

Coolant temperature at core outlet

Delta temperature

Subcooling margin

TUR Turbine speed

Pressure first stage

Page 115: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

106

A.5. LIST OF SETPOINTS

The setpoints for all the systems are listed in Table 25.

TABLE 25. LIST OF SETPOINTS

System Setpoint Value

RCS Heaters P <15.5 MPA

Spray P >15.5 MPA

Relief RCS valve P>16.7 MPA

Safety RCS valve P>17.05MPA

Alarm low RCS pressure P<12.5MPA

PCS-Trips Low pressure upper plenum P <11. MPA

Low level PZR L<5%

Low flow downcomer W<347Kg/s

High core outlet temperature T>340ºC

High reactor neutron core flux Flux>120%

High log rate SUR>2dpm

High pressure upper plenum P>16.4

PCS-Setbacks High PZR level L>67%

High steam header pressure P>4.9 MPA

PCS-Stepbacks High zone flux Flux>115%

ADS Low-low pressure upper plenum P <9 MPA

Low low level vessel L<90%

High-high pressure upper plenum P>17.2MPA

High-high pressure CBS P>0.019MPA

CBS Alarm high CBS pressure P>0.012MPA

CCS CCS starts at CBS pressure P>0.019MPA

PIS Pressure setpoint P<5MPA

GIS Pressure setpoint P<0.5MPA

CNR Alarm low CNR vacuum P>100mmHg

Loss of CNR vacuum P>254mmHg

MSS Relief RCS valve P>5.3 MPA

Safety RCS valve P>5.7 MPA

Page 116: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

107

A.6. VALVE FAILURE

The state of the failure of various valves is listed in Table 26.

TABLE 26. VALVE FAILURE

System Valve Failure

ADS ADSV01 Close

ADSV02 Close

ADSV03 Close

PIS PISV02 Open

PISV04 Open

GIS GISV02 Open

GISV04 Open

MSS MSSV01 Close

MSSV02 Close

MSSV05 Close

MSSV06 Close

MSSV08 Close

MSSV09 Close

DHR DHRV01 Open

DHRV02 Open

DHRV03 Open

DHRV04 Open

RCS RCSV07 Close

RCSV08 Close

RCSV09 Close

FWS FWSV15 Close

FWSV16 Close

Page 117: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

108

Page 118: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

109

ABBREVIATIONS

ADS AUTOMATIC DEPRESSURIZATION SYSTEM.

AI ANALOGICAL INPUT

BOL BEGINNING OF LIFE

BOP BALANCE OF PLANT

BWR BOILING WATER REACTOR

CBS CONTAINMENT BUILDING SYSTEM.

CCS CONTAINMENT COOLING SYSTEM.

CNR CONDENSER SYSTEM.

CWS CIRCULATING WATER SYSTEM.

DNBR DEPARTURE FROM NUCLEAR BOILING RATIO

EOL END OF LIFE

FWS FEEDWATER SYSTEM

FC FORCE CIRCULATION

GEN GENERATOR SYSTEM

GIS GRAVITY INJECTION SYSTEM

GUI GRAPHIC USER INTERFACE

HFE HUMAN FACTORS ENGINEERING

HX HEAT EXCHANGER

IAEA INTERNATIONAL ATOMIC ENERGY AGENCY

IC INITIAL CONDITION

iPWR INTEGRAL PRESSURISED WATER COOLED REACTOR

LWR LIGTH WATER REACTOR

LOCA LOSS OF COOLANT ACCIDENT

MOL MEDIUM OF LIFE

Page 119: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

110

MSS MAIN STEAM SYSTEM

NC NATURAL CIRCULATION

NPP NUCLEAR POWER PLANT

PCS PROTECTION AND CONTROL SYSTEM.

PDHR PASSIVE DECAY HEAT REMOVAL SYSTEM.

PID PROCESS AND INSTRUMENTATION DIAGRAM

PIS PRESSURE INJECTION SYSTEM

POAH POINT OF ADDING HEAT

PWR PRESSURISED WATER REACTOR

PZR PRESSURIZER

RCP REACTOR COOLANT PUMP

RCS REACTOR COOLANT SYSTEM.

RPV REACTOR PRESSURE VESSEL

SBO STATION BLACKOUT

SCS SHUTDOWN COOLING SYSTEM

SG STEAM GENERATOR

SMR SMALL MODULAR REACTOR

SUR START UP RATE

TUR TURBINE SYSTEM

Page 120: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

111

CONTRIBUTORS TO DRAFTING AND REVIEW

Abarca, D. TECNATOM, Spain

Batra, C. International Atomic Energy Agency

De la Torre, R. TECNATOM, Spain

Fernandez, D. TECNATOM, Spain

Fuentes, A. TECNATOM, Spain

Lenhardt, G. TECNATOM, Spain

López, J. TECNATOM, Spain

Maroto, E. TECNATOM, Spain

Painter, C. International Atomic Energy Agency

Parrado, I. TECNATOM, Spain

Ruiz, J.A. TECNATOM, Spain

Sancho, A. TECNATOM, Spain

Subki, M.H . International Atomic Energy Agency

Villalba, S. TECNATOM, Spain

Page 121: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA
Page 122: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

ORDERING LOCALLYIn the following countries, IAEA priced publications may be purchased from the sources listed below or from major local booksellers.

Orders for unpriced publications should be made directly to the IAEA. The contact details are given at the end of this list.

CANADARenouf Publishing Co. Ltd22-1010 Polytek Street, Ottawa, ON K1J 9J1, CANADATelephone: +1 613 745 2665 Fax: +1 643 745 7660Email: [email protected] Web site: www.renoufbooks.com

Bernan / Rowman & Littlefield15200 NBN Way, Blue Ridge Summit, PA 17214, USATel: +1 800 462 6420 • Fax: +1 800 338 4550Email: [email protected] Web site: www.rowman.com/bernan

CZECH REPUBLICSuweco CZ, s.r.o.Sestupná 153/11, 162 00 Prague 6, CZECH REPUBLICTelephone: +420 242 459 205 Fax: +420 284 821 646Email: [email protected] Web site: www.suweco.cz

FRANCEForm-Edit5 rue Janssen, PO Box 25, 75921 Paris CEDEX, FRANCETelephone: +33 1 42 01 49 49 Fax: +33 1 42 01 90 90Email: [email protected] Web site: www.form-edit.com

GERMANYGoethe Buchhandlung Teubig GmbHSchweitzer FachinformationenWillstätterstrasse 15, 40549 Düsseldorf, GERMANYTelephone: +49 (0) 211 49 874 015 Fax: +49 (0) 211 49 874 28Email: [email protected] Web site: www.goethebuch.de

INDIAAllied Publishers1st Floor, Dubash House, 15, J.N. Heredi Marg, Ballard Estate, Mumbai 400001, INDIATelephone: +91 22 4212 6930/31/69 Fax: +91 22 2261 7928Email: [email protected] Web site: www.alliedpublishers.com

Bookwell3/79 Nirankari, Delhi 110009, INDIATelephone: +91 11 2760 1283/4536Email: [email protected] Web site: www.bookwellindia.com

@ No. 25

Page 123: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

ITALYLibreria Scientifica “AEIOU”Via Vincenzo Maria Coronelli 6, 20146 Milan, ITALYTelephone: +39 02 48 95 45 52 Fax: +39 02 48 95 45 48Email: [email protected] Web site: www.libreriaaeiou.eu

JAPANMaruzen-Yushodo Co., Ltd10-10 Yotsuyasakamachi, Shinjuku-ku, Tokyo 160-0002, JAPANTelephone: +81 3 4335 9312 Fax: +81 3 4335 9364Email: [email protected] Web site: www.maruzen.co.jp

RUSSIAN FEDERATIONScientific and Engineering Centre for Nuclear and Radiation Safety107140, Moscow, Malaya Krasnoselskaya st. 2/8, bld. 5, RUSSIAN FEDERATIONTelephone: +7 499 264 00 03 Fax: +7 499 264 28 59Email: [email protected] Web site: www.secnrs.ru

UNITED STATES OF AMERICABernan / Rowman & Littlefield15200 NBN Way, Blue Ridge Summit, PA 17214, USATel: +1 800 462 6420 • Fax: +1 800 338 4550Email: [email protected] Web site: www.rowman.com/bernan

Renouf Publishing Co. Ltd812 Proctor Avenue, Ogdensburg, NY 13669-2205, USATelephone: +1 888 551 7470 Fax: +1 888 551 7471Email: [email protected] Web site: www.renoufbooks.com

Orders for both priced and unpriced publications may be addressed directly to:Marketing and Sales UnitInternational Atomic Energy AgencyVienna International Centre, PO Box 100, 1400 Vienna, AustriaTelephone: +43 1 2600 22529 or 22530 • Fax: +43 1 2600 29302 or +43 1 26007 22529Email: [email protected] • Web site: www.iaea.org/books

Page 124: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA
Page 125: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

17-18101

Page 126: Integral Pressurized Water Reactor Simulator Manual ... · Marketing and Sales Unit, Publishing Section International Atomic Energy Agency Vienna International Centre ... The IAEA

65

Integral Pressurized Water R

eactor Simulator M

anual: Exercise Handbook

TR

AIN

ING

CO

UR

SE

SE

RIE

S

@65

T R A I N I N G C O U R S E S E R I E SV I E N N A , 2 0 1 7

Integral Pressurized Water Reactor Simulator Manual:

Exercise Handbook

ISSN 1018-5518

TCS-65_Exer_Handbook_cov.indd 1,3 2017-05-24 14:36:42