areva np inc., - inl advanced reactor technologies documents/areva/ngnp... · document no.:...

20004-015 (09/30/2008)

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AREVA NP Inc.,an AREVA and Siemens company

Engineering Information Record

Document No: 51 - 9105936 - 001

NGNP Nuclear Heat Source System Boundaries and Interfaces

BEA Contract No. 00075310

Disclaimer

This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, nor their contractors and subcontractors, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.

20004-015 (09/30/2008)

Document No.: 51-9105936-001 AREVA NP Inc., an AREVA and Siemens company


Record of Revision

Revision No. Date

Pages/Sections/ Paragraphs

Changed Brief Description / Change Authorization 000 3-19-09 ALL Initial Release

001 Section 1.0 Placed acronyms in alphabetical order Section 2.0 3rd paragraph, 4th sentence “… at their physical …” was “… at its

physical”. Added a 4th paragraph. Section 3.0 Added “(Reference 1) to the 1st sentence. Figure 8.1-2 Updated the Figure to include RS component callouts Figure 8.2-1 Updated the Figure to only list components of the vessel system. Table 8.2-1 Other interfaces column, added radiological interface # 2. Included

components column, “Cross vessel” was “Cross over vessel”. Boundaries column, added boundary # 14.

Section 8.3 Added reference to Figure 8.3-1 in the 2nd sentence Section 8.5 In the 1st sentence of the 3rd paragraph, “un-insulated portions of the

RPV” was “un-insulated RPV”. Inserted 3rd sentence into the 3rd paragraph.

Figure 8.5-1 Added “Dedicated cooling system” Figure 8.6-1 Changed title from “FUEL HANDLING MACHINE GRAPPLE” to

“FUEL HANDLING MACHINE GRAPPLING FEATURE” Section 8.8 “see Figure 8.6-2” was “see 8.6-3” Section 8.9 1st sentence “ … and maintains the correct coolant chemistry.” was

“and maintains the required atmosphere.” Section 8.10 Revised first sentence. Inserted the second sentence. Table 8.10-1 Added a general boundary in the Boundaries column Section 8.11 Reworded 1st paragraph and inserted new 4th paragraph Figure 8-19-1 “Water/Steam” was “Steam – Water” Table 8.19-1 In 2 places, “Power Conversion System at the pipe connections of the

first dump valves.” was “Power Conversion System at the pipe connection of the first dump valve.”

All Minor grammatical corrections as deemed necessary All Tables as

noted All Tables that have no Included components listed, changed “None” to “TBD”



Table of Contents Page

REVISION 001 SIGNATURE BLOCK.......................................................................................................2

RECORD OF REVISION ..........................................................................................................................3

LIST OF TABLES .....................................................................................................................................6

LIST OF FIGURES ...................................................................................................................................7

1.0 LIST OF ACRONYMS...................................................................................................................8

2.0 INTRODUCTION...........................................................................................................................9

3.0 SCOPE..........................................................................................................................................9

4.0 PURPOSE.....................................................................................................................................9

5.0 APPROACH................................................................................................................................10

6.0 ASSUMPTIONS..........................................................................................................................10

7.0 DESIGN INPUTS ........................................................................................................................10

8.0 NUCLEAR HEAT SOURCE DESCRIPTION ..............................................................................10 8.1 Reactor system ...............................................................................................................10 8.2 Vessel system .................................................................................................................16 8.3 Main Heat Transport System...........................................................................................20 8.4 Shutdown Cooling System ..............................................................................................24 8.5 Reactor Cavity Cooling System.......................................................................................26 8.6 Fuel Handling System .....................................................................................................28 8.7 Spent Fuel Storage and Cooling System ........................................................................31 8.8 New fuel handling and storage system ...........................................................................33 8.9 Helium service system ....................................................................................................34 8.10 NI HVAC system .............................................................................................................35 8.11 Plant Electrical System....................................................................................................36 8.12 NI Cooling Water System................................................................................................38 8.13 Component Handling System..........................................................................................40 8.14 Reactor Protection System..............................................................................................42 8.15 NHS Investment Protection System ................................................................................43 8.16 NHS Control and Monitoring System ..............................................................................45



Table of Contents

(continued)

Page

8.17 Control Room and Operator Interface System ................................................................46 8.18 Radioactive Waste and Decontamination System ..........................................................46 8.19 STEAM/WATER DUMP SYSTEM...................................................................................47

9.0 REFERENCES............................................................................................................................49

APPENDIX A : NHS SYSTEM BOUNDARY MATRIX ......................................................................................... A-1

APPENDIX B : NHS SYSTEM PHYSICAL INTERFACE MATRIX ...................................................................... B-1

APPENDIX C : NHS SYSTEM ELECTRICAL INTERFACE MATRIX..................................................................C-1

APPENDIX D : NHS SYSTEM RADIOLOGICAL CONCERNS MATRIX.............................................................D-1

APPENDIX E : NHS SYSTEM THERMAL HYDRAULIC INTERFACE MATRIX ................................................. E-1

APPENDIX F : NHS SYSTEM HEAT TRANSFER INTERFACE MATRIX .......................................................... F-1



List of Tables

Page

TABLE 8.1-1 REACTOR SYSTEM BOUNDARIES AND INTERFACES...............................................14 TABLE 8.2-1 VESSEL SYSTEM BOUNDARIES AND INTERFACES ...................................................18 TABLE 8.3-1 MAIN HEAT TRANSPORT SYSTEM BOUNDARIES AND INTERFACES......................22 TABLE 8.4-1 SHUTDOWN COOLING SYSTEM BOUNDARIES AND INTERFACES..........................25 TABLE 8.5-1 RCCS BOUNDARIES AND INTERFACES.......................................................................27 TABLE 8.6-1 FUEL HANDLING SYSTEM BOUNDARIES AND INTERFACES....................................30 TABLE 8.7-1 SPENT FUEL STORAGE AND COOLING SYSTEM BOUNDARIES AND INTERFACES32 TABLE 8.8-1 NEW FUEL HANDLING AND STORAGE SYSTEM BOUNDARIES AND INTERFACES33 TABLE 8.9-1 HELIUM SERVICE SYSTEM BOUNDARIES AND INTERFACES ..................................34 TABLE 8.10-1 NI HVAC SYSTEM BOUNDARIES AND INTERFACES................................................35 TABLE 8.11-1 PLANT ELECTRICAL SYSTEM BOUNDARIES AND INTERFACES............................37 TABLE 8.12-1 NI COOLING WATER SYSTEM BOUNDARIES AND INTERFACES ...........................39 TABLE 8.13-1 COMPONENT HANDLING SYSTEM BOUNDARIES AND INTERFACES ...................41 TABLE 8.14-1 REACTOR PROTECTION SYSTEM BOUNDARIES AND INTERFACES ....................42 TABLE 8.15-1 NHS INVESTMENT PROTECTION SYSTEM BOUNDARIES AND INTERFACES ......44 TABLE 8.16-1 NCMS BOUNDARIES AND INTERFACES....................................................................45 TABLE 8.17-1 CROIS BOUNDARIES AND INTERFACES...................................................................46 TABLE 8.18-1 RWDS BOUNDARIES AND INTERFACES ...................................................................47 TABLE 8.19-1 STEAM/WATER DUMP SYSTEM BOUNDARIES AND INTERFACES ........................48



List of Figures

Page

FIGURE 8.1-1 CORE PLAN VIEW .........................................................................................................11 FIGURE 8.1-2 REACTOR SECTION VIEW ...........................................................................................12 FIGURE 8.1-3 GRAPHITE BLOCK (ACTIVE ELEMENT) ......................................................................13 FIGURE 8.2-1 VESSEL SYSTEM COMPONENTS................................................................................17 FIGURE 8.3-1 MAIN HEAT TRANSPORT SYSTEM FLOW PATH........................................................21 FIGURE 8.4-1 SHUTDOWN COOLING SYSTEM..................................................................................24 FIGURE 8.5-1 REACTOR CAVITY COOLING SYSTEM SCHEMATIC .................................................26 FIGURE 8.6-1 FUEL HANDLING MACHINE GRAPPLING FEATURE ..................................................28 FIGURE 8.6-2 FUEL HANDLING SYSTEM PLAN VIEW.......................................................................29 FIGURE 8.19-1 STEAM/WATER DUMP SYSTEM ...............................................................................48



1.0 LIST OF ACRONYMS

Acronym Description CHS Component Handling System CROIS NHS Control Room Operator Interface System DCC Depressurized conduction cooldown EACS Essential AC electrical system EDCS Essential DC electrical system FHS Fuel Handling System HSS Helium Service System HTR High Temperature Reactor IPS Nuclear Heat Source Investment Protection System MHTS Main Heat Transport System NCA Neutron control assembly NCMS NHS Control & Monitoring System NFHS New Fuel Handling and Storage System NGNP Next Generation Nuclear Power NHS Nuclear Heat Source NI Nuclear island NICWS Nuclear Island Cooling Water System NIHVAC Nuclear Island Heating and Air Conditioning PACS Plant AC electrical system PCC Pressurized conduction cooldown PCS Power Conversion System PDCS Plant DC electrical system PES Plant Electrical System PUP Plant uninterruptible power supply RCCS Reactor Cavity Cooling System RPS Reactor Protection System RPV Reactor pressure vessel RS Reactor System RWDS Radioactive Waste and Decontamination System SCS Shutdown Cooling System SCW Site and Civil Works SCWS Shutdown Cooling Water Subsystem SFSS Spent Fuel Storage and Cooling System SG Steam generator VS Vessel System



2.0 INTRODUCTION NGNP Background: The Next Generation Nuclear Power plant (NGNP) is a modular gas cooled High Temperature Reactor (HTR) electrical power plant. The power plant can also be used to generate steam for industrial process heat, or a combination of both electricity and process heat. The key attributes of the modular HTR that distinguish it from other reactor types are its fuel, a refractory fuel consisting of coated particles which are embedded in graphite moderator, and its helium coolant. These attributes not only provide for a high temperature capability that is unique among established reactor concepts but also offers fuel cycle flexibility. Additionally, these characteristics associated with limitations on power level and power density makes possible the development of a modular concept with inherent safety characteristics simpler than those employed by current light water reactor technology.

Objective: The objective of this document is to define the boundaries and interfaces of the major systems which make up the Nuclear Heat Source (NHS). Description of each system will be provided as needed to describe the boundaries and interfaces.

Document structure: For each major system of the NHS a brief verbal description of the system will be provided. Figures will be provided following the verbal description where deemed useful. After the description and Figures where used, a Table will be provided that lists the boundaries and interfaces. The boundaries will be described where possible at their physical location. The name of the system with which the boundary exists will be listed and the corresponding acronym listed in the interfaces. See Section 5.0 for additional information.

Document limitation: Changes were made to the system definitions of the NGNP Plant Design Requirements Document, 51-9106032-000 after the initial release of this document. In general, this does not significantly alter the NHS system boundaries and interfaces described herein. However, some nomenclature will have to be updated to make both documents fully consistent. Elimination of project funding precluded resolution of the detailed nomenclature at this time. Nonetheless, the boundaries provided in this document provide a reasonable starting point for initial conceptual design work.

3.0 SCOPE

The scope of information provided within this document pertains to the current AREVA-NP reference baseline design (Reference 1) for the NGNP project NHS systems. The NHS is considered to be limited to the primary (aka main) loop heat transport system and the secondary loop up to the first isolation valve from the steam generator and the first dump valve of the Steam/Water Dump System. The scope of this document does not include a detailed description of each of the NHS systems required for the NHS. A brief overview of each system will be provided sufficient to describe the system. The figures provided describe a NGNP general case and may not depict the exact details of a still immature AREVA-NP NGNP reference design. The accuracy of the component depictions does not affect the purpose of this document. A table will be provided for each system listing the boundaries and interfaces.

4.0 PURPOSE

The purpose of this document is to define the boundaries between the NHS systems required for the operation of the NHS and identify interfaces between those NHS systems. Where applicable, the boundary or interface will be described by the component or physical location on which the boundary or interface resides.



5.0 APPROACH

The systems which make up the NHS are listed in Section 8.0. A brief description is provided for each system that is meant to be generic as possible to provide flexibility as the plant design is refined. Specific components of the system are listed where needed to describe the system or interfaces of the system. The physical boundaries of each system are listed with the system name with which they bound. Specific interface points between systems that effect analysis or design are provided. Interface points may coincide with or help define boundaries but are not limited to physical boundaries. Five different interface categories are considered: physical, heat transfer, electrical & control, thermal hydraulic, and radiological. Thermal hydraulic is used to describe all heat balance and fluid flow considerations.

Two systems that are not part of the NHS are listed as boundaries. Those are Site & Civil Works (building structure) and Power Conversion System (secondary coolant loop).

6.0 ASSUMPTIONS

No assumptions were made in preparation of this document.

7.0 DESIGN INPUTS

None.

8.0 NUCLEAR HEAT SOURCE DESCRIPTION

The nuclear heat source is comprised of a graphite moderated nuclear reactor and heat transport system encased in pressure retaining vessels forming the main coolant loop. The reactor heats helium which is circulated through a steam generator where the heat is transferred to a secondary loop. The reactor core and the steam generator are located in separate pressure vessels connected together by a cross vessel. The heat generated from the reactor is transferred to the secondary loop to form steam. This steam can be used to drive an electrical generator via a steam turbine, used as process heat, or both. For the purpose of this document, the secondary loop is only considered up to the isolation valve. All auxiliary systems required for the function of the nuclear heat source systems such as controls, NIHVAC, refueling, etc. are included.

8.1 REACTOR SYSTEM

The purpose of the Reactor System is to generate heat for the power plant. The reactor is a prismatic block configuration; see Figures 8.1-1 and 8.1-2. The reference design is a graphite moderated helium cooled reactor. It is comprised of stacks of hexagonally shaped graphite blocks, see Figure 8.1-3. The blocks containing fissile material form a cylinder as shown in Figure 8.1-1 and are surrounded by reflector blocks, which contain no fissile material along the ID, OD, top and bottom. The stack is contained radially within a metallic core barrel. The reactor core rests atop a graphite core support assembly supported in turn by a metallic core support assembly. The reactor is controlled by neutron control equipment (neutron control and flux detection assemblies) which is considered part of the Reactor System. The Reactor System is considered to include all items contained within the reactor vessel, excluding the SCS circulator, SCS heat exchanger, and hot duct, up to the connection to the hot duct. The Reactor System also includes the reactor supports and reactor control elements. The reactor control elements include the neutron detectors that are external to the reactor vessel. See Table 8.1-1 for boundaries and interfaces.



Figure 8.1-1 CORE PLAN VIEW



Figure 8.1-2 REACTOR SECTION VIEW



Figure 8.1-3 GRAPHITE BLOCK (ACTIVE ELEMENT)

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8.2 VESSEL SYSTEM

The Vessel System is considered to be all major components that retain the primary coolant during operation and their structural supports. Their primary function is pressure retention of the primary coolant. The boundary of the Vessel System supports is the structural embed plate with which they are connected to. Piping for instrumentation, helium purification, etc. are not included in the vessel system. The boundary with these system connections is the vessel nozzle with which they connect.

The primary components that make up the Vessel System are the reactor pressure vessel (RPV), steam generator (SG) vessel, and the cross over vessel, see Figure 8.2-1. Other components of the system are the main and shutdown circulator housings, the neutron control assembly (NCA) housings, pressure relief valve and associated vent, and the supports for these vessels. The supports and pressure relief valve are not shown in the Figure below. See Table 8.2-1 for boundaries and interfaces.



Figure 8.2-1 VESSEL SYSTEM COMPONENTS

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hine

at t

he u

pper

he

ad N

CA

pen

etra

tions

(F

HS)

7)

Shu

tdow

n C

oolin

g Sy

stem

pip

ing

pene

tratio

n no

zzle

s on

SCS

hous

ing

(SC

S)

9) H

ot d

uct s

uppo

rts a

t cr

oss v

esse

l ID

(MH

TS)

10) S

G tu

be sh

eets

at

SG v

esse

l (PC

S)

Hea

t tra

nsfe

r 1)

Prim

ary

cool

ant

cool

ing

the

vess

el(s

) (M

HTS

) 2)

Rea

ctor

cor

e to

ves

sel

wal

ls (R

S)

4) H

eat r

adia

ted

from

ho

t duc

t and

con

duct

ed

alon

g su

ppor

ts to

cro

ss

vess

el (M

HTS

) 5)

Cor

e ba

rrel

and

cor

e su

ppor

ts to

reac

tor

vess

el (R

S)

6) F

rom

RPV

to c

avity

co

ncre

te (S

CW

) R

adio

logi

cal

1)

Neu

tron

atte

nuat

ion

thro

ugh

vess

el w

all

2)

Wat

er d

rain

at b

ase

of R

PV a

nd S

GV

(R

WD

S)

Elec

trica

l & c

ontro

l 1)

Con

nect

ions

to th

e re

lief v

alve

con

trols

(IPS

, PE

S)

2) C

onne

ctio

n to

pr

essu

re, t

empe

ratu

re,

acou

stic

em

issi

ons

sens

ors,

etc.

(NC

MS)

D

ocum

ent N

o.:

51-9

1059

36-0

01

AR

EVA

NP

Inc.

, an

AR

EVA

and

Sie

men

s co

mpa

nyN

GN

P N

ucle

ar H

eat S

ourc

e S

yste

m B

ound

arie

s an

d In

terfa

ces

P

age

19

VE

SSE

L S

YST

EM

BO

UN

DA

RIE

S A

ND

INT

ER

FAC

ES

Syst

em

Incl

uded

com

pone

nts

Bou

ndar

ies

Phys

ical

inte

rfac

es

Oth

er in

terf

aces

R

eact

or p

ress

ure

vess

el

Prot

ectio

n Sy

stem

at t

he

pres

sure

relie

f val

ve

actu

ator

con

trols

12

) NH

S C

ontro

l and

M

onito

ring

Syst

em a

t pr

essu

re, t

empe

ratu

re,

acou

stic

em

issi

ons s

enso

rs,

etc.

13

) Pla

nt E

lect

rical

Sys

tem

at

the

pow

er c

onne

ctio

n of

th

e va

lve

actu

ator

con

trol

14) R

adio

activ

e W

aste

and

D

econ

tam

inat

ion

Syst

em a

t ve

ssel

noz

zle

of th

e R

PV

and

SGV

wat

er d

rain

Ther

mal

hyd

raul

ic

1)

Coo

lant

flow

pat

h fo

rmed

by

the

vess

els

and

othe

r com

pone

nts

with

in th

e N

HS

(MH

TS,

SCS)

2)

N

IHV

AC

coo

ling

air

flow

s acr

oss N

CA

ho

usin

gs (N

IHV

AC

) 3)

H

eat l

oad

from

re

acto

r ves

sel t

o (R

CC

S)

SCS

encl

osur

e

N

CA

hou

sing

V

esse

l sup

port

Seis

mic

rest

rain

t (ve

ssel

ID)

St

eam

gen

erat

or v

esse

l

Mai

n ci

rcul

ator

hou

sing

Ves

sel s

uppo

rts

V

esse

l OD

insu

latio

n

Pres

sure

relie

f val

ve

Cro

ss v

esse

l



8.3 MAIN HEAT TRANSPORT SYSTEM

The main function of the Main Heat Transport System (MHTS) is to transfer heat from the reactor core to the secondary loop heat transfer system. The heat transfer fluid, helium, flows downward through the reactor core and out through the hot duct, see Figure 8.3-1. It flows from the hot duct into the SG upper plenum and is channeled over the SG tubes via the inner and outer shroud. After flowing across the SG tubes, the cooled helium flows along the annulus formed by the SG vessel and the outer shroud up to the main circulator. The main circulator forces the cooled helium through the annulus formed by the hot duct and the cross vessel. It then flows upward along the core barrel where it turns direction in the upper reactor plenum and flows back down into the reactor core. The flow path remains the same for each loop. There is a check valve just upstream of the circulator to prevent unwanted helium circulation. The major components of the Main Heat Transport System are the hot duct, steam generator, main helium circulator with check valve, all items such as the plenums that direct helium flow through the steam generator vessel, and supports for the items listed. The physical boundary of the system is the interface between supports and the permanently affixed features of the pressure containing vessel. See Table 8.3-1 for boundaries and interfaces.



Figure 8.3-1 MAIN HEAT TRANSPORT SYSTEM FLOW PATH

D

ocum

ent N

o.:

51-9

1059

36-0

01

AR

EVA

NP

Inc.

, an

AR

EVA

and

Sie

men

s co

mpa

nyN

GN

P N

ucle

ar H

eat S

ourc

e S

yste

m B

ound

arie

s an

d In

terfa

ces

P

age

22

TAB

LE 8

.3-1

MA

IN H

EAT

TRA

NSP

OR

T SY

STEM

BO

UN

DA

RIE

S A

ND

INTE

RFA

CES

MA

IN H

EA

T T

RA

NSP

OR

T S

YST

EM

BO

UN

DA

RIE

S A

ND

INT

ER

FAC

ES

Syst

em

Incl

uded

com

pone

nts

Bou

ndar

ies

Phys

ical

inte

rfac

es

Oth

er in

terf

aces

M

ain

Hea

t Tr

ansp

ort S

yste

m

1) P

ower

Con

vers

ion

Syst

em a

t tub

e bu

ndle

2)

Ves

sel S

yste

m a

t the

m

ain

circ

ulat

or a

nd v

esse

l ci

rcul

ator

flan

ge

3) V

esse

l Sys

tem

at S

G

supp

orts

on

ID o

f SG

ves

sel

4) R

eact

or S

yste

m a

t the

hot

du

ct c

onne

ctio

n to

cor

e ba

rrel

5)

NH

S C

ontro

l and

M

onito

ring

Syst

em a

t Mai

n ci

rcul

ator

con

nect

ions

6)

NH

S C

ontro

l and

M

onito

ring

Syst

em a

t ci

rcul

ator

mot

or c

ontro

l and

fa

ult m

onito

ring

(ove

r-am

p,

vibr

atio

n, e

tc.)

7) R

eact

or P

rote

ctio

n Sy

stem

at m

ain

circ

ulat

or

mot

or c

ontro

ls

8) N

I Coo

ling

Wat

er

Syst

em: c

hills

the

circ

ulat

or

mot

or (o

ptio

nal)

9) H

eliu

m S

ervi

ce S

yste

m:

Hel

ium

pur

ge a

nd/o

r che

ck

valv

e op

erat

ion

(opt

iona

l) 10

) Hel

ium

Ser

vice

Sys

tem

at

mai

n ci

rcul

ator

(opt

iona

l) 11

) Fue

l Han

dlin

g Sy

stem

at

seal

s to

prev

ent c

oola

nt

1) S

team

gen

erat

or

supp

orts

at S

G v

esse

l (V

S)

2) H

ot d

uct s

uppo

rts a

t cr

oss v

esse

l ID

(VS)

3)

Mai

n ci

rcul

ator

at

conn

ectio

n to

SG

ves

sel

(VS)

4)

The

coo

ling

of

circ

ulat

or c

ompo

nent

s ca

n be

don

e w

ith c

hille

d w

ater

(NIC

WS,

op

tiona

l) 5)

Hel

ium

mak

e-up

and

m

anip

ulat

or o

pera

tion

can

be d

one

with

hel

ium

(H

SS, o

ptio

nal)

6) H

ot d

uct c

onne

ctio

n at

cor

e ba

rrel

(RS)

7)

All

equi

pmen

t tha

t m

ay n

eed

repl

aced

or

rem

oved

mus

t hav

e ad

equa

te li

fting

/ m

anip

ulat

ing

equi

pmen

t an

d ac

cess

(CH

S)

Hea

t tra

nsfe

r 1)

A

cros

s the

SG

tube

w

all (

PCS)

2)

H

eat l

oss t

hrou

gh th

e ho

t duc

t ins

ulat

ion

and

cond

uctio

n al

ong

hot

duct

supp

orts

(VS)

Th

erm

al h

ydra

ulic

1)

Coo

lant

flow

thro

ugh

the

circ

ulat

or, c

oola

nt

duct

s & p

lenu

ms,

vess

els,

and

reac

tor (

RS,

V

S)

2) H

eat b

alan

ce b

etw

een

prim

ary

& se

cond

ary

loop

s (PC

S)

Elec

trica

l & c

ontro

l 1)

C

onne

ctio

ns to

the

circ

ulat

or a

nd se

nsor

s (N

CM

S fo

r con

trol a

nd

mon

itorin

g, R

PS fo

r m

onito

ring

and

shut

dow

n, IP

S sh

ut

dow

n an

d cl

ose

valv

e,

PES

for p

ower

supp

ly)

Rad

iolo

gica

l 1)

Tr

itium

tran

sfer

ac

ross

tube

bun

dle

D

ocum

ent N

o.:

51-9

1059

36-0

01

AR

EVA

NP

Inc.

, an

AR

EVA

and

Sie

men

s co

mpa

nyN

GN

P N

ucle

ar H

eat S

ourc

e S

yste

m B

ound

arie

s an

d In

terfa

ces

P

age

23

MA

IN H

EA

T T

RA

NSP

OR

T S

YST

EM

BO

UN

DA

RIE

S A

ND

INT

ER

FAC

ES

Syst

em

Incl

uded

com

pone

nts

Bou

ndar

ies

Phys

ical

inte

rfac

es

Oth

er in

terf

aces

lo

ss

12) N

HS

Inve

stm

ent

Prot

ectio

n Sy

stem

at

circ

ulat

or c

ontro

ls to

shut

do

wn

circ

ulat

or a

nd c

lose

va

lve

13) P

lant

Ele

ctric

al S

yste

m

at c

onne

ctio

n to

circ

ulat

or

cont

rols

to su

pply

pow

er

St

eam

gen

erat

or

Tube

shee

ts

Tube

bun

dle

Upp

er p

lenu

m w

/ cro

ss d

uct e

lbow

In

ner &

out

er sh

roud

Low

er p

lenu

m

Mai

n he

lium

circ

ulat

or

El

ectri

c m

otor

Impe

ller

M

ain

loop

shut

off v

alve

Hot

duc

t

Inne

r sle

eve

In

sula

tion

Out

er sl

eeve

Duc

t sup

ports



8.4 SHUTDOWN COOLING SYSTEM

The purpose of the Shutdown Cooling System (SCS) is to remove heat from the reactor core during shutdown and when the MHTS is not working. This system consists of the shutdown cooling circulator, the shutdown cooling secondary heat removal loop, and the Shutdown Cooling System controls. The primary coolant (helium) is pulled through a heat exchanger by the SCS circulator where heat is rejected to the shutdown cooling water system (SCWS) and expelled to the atmosphere via a second heat exchanger. The SCWS consists of a dedicated self-contained loop for each reactor module. The SCS circulator contains a normally closed shut off valve similar to the check valve used in the main helium circulator. See Figure 8.4-1 below. See Table 8.4-1 for boundaries and interfaces.

Figure 8.4-1 SHUTDOWN COOLING SYSTEM

D

ocum

ent N

o.:

51-9

1059

36-0

01

AR

EVA

NP

Inc.

, an

AR

EVA

and

Sie

men

s co

mpa

nyN

GN

P N

ucle

ar H

eat S

ourc

e S

yste

m B

ound

arie

s an

d In

terfa

ces

P

age

25

TAB

LE 8

.4-1

SH

UTD

OW

N C

OO

LIN

G S

YSTE

M B

OU

ND

AR

IES

AN

D IN

TER

FAC

ES

SHU

TD

OW

N C

OO

LIN

G S

YST

EM

BO

UN

DA

RIE

S A

ND

INT

ER

FAC

ES

Syst

em

Incl

uded

com

pone

nts

Bou

ndar

ies

Phys

ical

inte

rfac

es

Oth

er in

terf

aces

Sh

utdo

wn

Coo

ling

Syst

em

(SC

S)

1)

V

esse

l Sys

tem

at

circ

ulat

or c

onne

ctio

n to

R

PV

2)

Rea

ctor

Sys

tem

at

low

er c

ore

supp

ort

3)

NH

S C

ontro

l and

M

onito

ring

Syst

em a

t co

nnec

tions

to c

ircul

ator

an

d se

nsor

s 4)

N

HS

Inve

stm

ent

Prot

ectio

n Sy

stem

at

conn

ectio

ns to

circ

ulat

or

cont

rols

5)

N

I Coo

ling

Wat

er

Syst

em: p

rovi

des

mot

or

cool

ing

(opt

iona

l)

6)

Hel

ium

Ser

vice

Sys

tem

at

circ

ulat

or (o

ptio

nal)

7)

Si

te &

Civ

il W

orks

at

the

build

ing

/ equ

ipm

ent

inte

rfac

e 8)

Pl

ant E

lect

rical

Sys

tem

at

circ

ulat

or c

ontro

ls fo

r po

wer

supp

ly

1) S

CS

pene

tratio

n in

lo

wer

RPV

hea

d at

at

tach

men

t poi

nt o

f the

SC

S ci

rcul

ator

(VS)

2)

SC

S du

ct c

onne

ctio

n to

the

reac

tor s

uppo

rt st

ruct

ure

(RS)

3)

Con

cret

e em

beds

for

equi

pmen

t pla

cem

ent

(SC

W)

4) L

iftin

g eq

uipm

ent

and

acce

ss m

ust b

e ad

equa

te fo

r rep

air &

re

plac

emen

t (C

HS)

5)

The

coo

ling

of

circ

ulat

or c

ompo

nent

s ca

n be

don

e w

ith c

hille

d w

ater

(NIC

WS,

op

tiona

l) 7)

Hel

ium

mak

e-up

and

m

anip

ulat

or o

pera

tion

can

be d

one

with

hel

ium

(H

SS, o

ptio

nal)

Elec

trica

l & c

ontro

l 1)

C

onne

ctio

n to

the

circ

ulat

or m

otor

, sen

sors

&

bear

ings

(NC

MS

for c

ontro

ls

& m

onito

ring,

IPS

for s

tartu

p w

hen

need

ed, P

ES fo

r el

ectri

cal p

ower

) Th

erm

al h

ydra

ulic

s 1)

C

oola

nt fl

ow p

ath

form

ed

by th

ese

syst

ems (

VS,

RS)

2)

H

eat b

alan

ce b

etw

een

prim

ary

and

seco

ndar

y lo

ops

of th

e (M

HTS

) H

eat t

rans

fer

1) A

cros

s hea

t exc

hang

er h

eat

trans

fer s

urfa

ces f

rom

prim

ary

cool

ant (

MH

TS)

Rad

iolo

gica

l 1)

Mon

itor S

CW

S he

at tr

ansf

er

fluid

Sh

utdo

wn

cool

ing

circ

ulat

or

Mot

or

Sh

utdo

wn

cool

ing

loop

shut

-off

val

ve

Shut

dow

n co

olin

g he

at e

xcha

nger

Shut

dow

n co

olin

g w

ater

syst

em



8.5 REACTOR CAVITY COOLING SYSTEM

The Reactor Cavity Cooling System (RCCS) performs two functions. It keeps the concrete of the reactor cavity within allowable limits and removes decay heat from the reactor core when neither the MHTS nor the SCS are working.

The cavity walls and floor are lined with water panels that form an air to water heat exchanger. The heated water in the chambers flow to a water storage tank and is constantly replaced by cooler water. There are two separate complete systems planned for each reactor cavity. The water in each storage tank is cooled by a dedicated cooling system. In the event that the dedicated tank cooling system is not functioning, the cavity cooling system rejects heat by vaporizing the water in the holding tanks.

When neither the MHTS nor the SCS are working, decay heat form the core is removed by conduction through the outer graphite reflectors and by radiation and natural convection from the un-insulated portions of the RPV to the water chambers lining the cavity walls and floor. The heat is then removed as described above. For the purpose of this discussion, the un-insulated portion of the RPV is the cylindrical segment between the upper and lower head. See Table 8.5-1 for boundaries and interfaces.

Figure 8.5-1 REACTOR CAVITY COOLING SYSTEM SCHEMATIC

Water Storage and Heat Exchangers

Natural Convection Flow

Forced flow

Panel wall Cavity Cooler

Inlet Headers

Outlet Headers

Reactor Vessel

Dedicated cooling system

D

ocum

ent N

o.:

51-9

1059

36-0

01

AR

EVA

NP

Inc.

, an

AR

EVA

and

Sie

men

s co

mpa

nyN

GN

P N

ucle

ar H

eat S

ourc

e S

yste

m B

ound

arie

s an

d In

terfa

ces

P

age

27

TAB

LE 8

.5-1

RC

CS

BO

UN

DA

RIE

S A

ND

INTE

RFA

CES

RC

CS

BO

UN

DA

RIE

S A

ND

INT

ER

FAC

ES

Syst

em

Incl

uded

com

pone

nts

Bou

ndar

ies

Phys

ical

inte

rfac

es

Oth

er in

terf

aces

R

eact

or C

avity

C

oolin

g Sy

stem

(R

CC

S)

1)

N

HS

Con

trol a

nd

Mon

itorin

g Sy

stem

at

sens

ors

2)

Site

& C

ivil

Wor

ks a

t th

e bu

ildin

g / e

quip

men

t in

terf

ace

3)

R

adio

activ

e W

aste

and

D

econ

tam

inat

ion

Syst

em

(liqu

id) a

t RPV

cav

ity d

rain

to

sum

p

4)

Plan

t Ele

ctric

al S

yste

m

at ta

nk c

hille

r sys

tem

pow

er

conn

ectio

ns

5)

NH

S C

ontro

l and

M

onito

ring

Syst

em a

t se

nsor

s in

tank

chi

ller

syst

em

1) C

oncr

ete

embe

ds fo

r al

l equ

ipm

ent s

uppo

rts

& b

uild

ing

stee

l as

need

ed (S

CW

)

Hea

t tra

nsfe

r 1)

Th

is sy

stem

is to

pr

even

t ove

rhea

ting

RPV

ca

vity

con

cret

e fr

om h

eat

gene

rate

d by

RPV

(VS,

SC

W)

Ther

moh

ydra

ulic

1)

H

eat l

oad

from

RPV

to

the

RC

CS

(VS)

R

adio

logi

cal

1) M

onito

ring

RC

CS

cool

ant a

nd ta

nk c

hille

r co

olan

t. El

ectri

cal &

con

trol

1) P

ower

con

nect

ion

to

equi

pmen

t and

con

trols

(P

ES)

2) M

onito

ring

stat

us se

nsor

co

nnec

tions

(NC

MS)

RC

CS

cavi

ty b

ase

cool

ing

pane

ls &

pip

ing

RC

CS

verti

cal c

oolin

g pa

nels

& p

ipin

g

C

oolin

g w

ater

tank

s

Ta

nk c

hille

r sys

tem

R

CC

S co

olin

g w

ater

che

mis

try



8.6 FUEL HANDLING SYSTEM

The purpose of the Fuel Handling System is to replace used fuel and reflector elements within the reactor core. First, new fuel and reflector elements are moved to the fuel storage wells, see Figure 8.6-2. Then, the used elements are un-stacked from the core and placed into the storage well one sector at a time. Each element is grappled by the fuel handling machine using a handling feature like that shown in Figure 8.6-1. The element is then transferred vertically from the core through the vessel NCA openings. The fuel is then transferred to fuel transfer equipment which transports the elements to the fuel storage wells. The spent fuel and reflector elements are sent for processing in the Spent Fuel Storage and Cooling System. The process is then reversed to restack the partially spent elements using new elements where needed. See Table 8.6-1 for boundaries and interfaces.

Figure 8.6-1 FUEL HANDLING MACHINE GRAPPLING FEATURE



Figure 8.6-2 FUEL HANDLING SYSTEM PLAN VIEW

The Figure above depicts a multiple (4) module configuration. The number of modules may vary.

D

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Inc.

, an

AR

EVA

and

Sie

men

s co

mpa

nyN

GN

P N

ucle

ar H

eat S

ourc

e S

yste

m B

ound

arie

s an

d In

terfa

ces

P

age

30

TAB

LE 8

.6-1

FU

EL H

AN

DLI

NG

SYS

TEM

BO

UN

DA

RIE

S A

ND

INTE

RFA

CES

FUE

L H

AN

DL

ING

SY

STE

M B

OU

ND

AR

IES

AN

D IN

TE

RFA

CE

S Sy

stem

In

clud

ed c

ompo

nent

s B

ound

arie

s Ph

ysic

al in

terf

aces

O

ther

inte

rfac

es

Fuel

Han

dlin

g Sy

stem

1)

Site

& C

ivil

Wor

ks a

t th

e bu

ildin

g / e

quip

men

t in

terf

ace

2)

R

eact

or S

yste

m a

t re

flect

or a

nd fu

el e

lem

ents

3)

V

esse

l Sys

tem

at a

cces

s (N

CA

) ope

ning

s 4)

Pl

ant E

lect

rical

Sys

tem

at

equ

ipm

ent m

otor

s &

cont

rol c

onne

ctio

n 5)

Sp

ent F

uel S

tora

ge a

nd

Coo

ling

Syst

em a

t fue

l ha

nd-o

ff in

the

fuel

stor

age

wel

ls

6)

Com

pone

nt H

andl

ing

Syst

em: u

sed

to m

ove

and

inst

all e

quip

men

t 7)

M

ain

Hea

t Tra

nspo

rt Sy

stem

at s

eals

to p

reve

nt

cool

ant l

oss

1)

At N

CA

ves

sel

pene

tratio

ns (V

S)

2)

Rea

ctor

upp

er

plen

um sh

roud

acc

ess

for f

uel h

andl

ing

equi

pmen

t (R

S)

3)

Fuel

and

refle

ctor

el

emen

ts w

ith fu

el

hand

ling

equi

pmen

t (R

S)

4)

Fuel

stor

age

wel

l w

ith fu

el h

andl

ing

equi

pmen

t (SF

SS)

5)

Con

cret

e st

ruct

ural

em

beds

& b

uild

ing

stee

l (S

CW

) 6)

Eq

uipm

ent m

ust b

e ha

ndle

d w

ith th

e C

ompo

nent

Han

dlin

g Eq

uipm

ent (

CH

S)

Elec

trica

l & c

ontro

l 1)

Pow

er c

onne

ctio

n to

eq

uipm

ent a

nd c

ontro

ls

(PES

) R

adio

logi

cal

1)

Rad

iatio

n sh

ield

ing

for w

orke

rs d

urin

g al

l as

pect

s of f

uel m

ovem

ent

and

any

pote

ntia

l eq

uipm

ent r

epai

r sc

enar

io

2)

Con

trol o

f co

ntam

inat

ion

on

equi

pmen

t 3)

C

ritic

ality

con

trol o

f fu

el e

lem

ents

Fu

el h

andl

ing

cont

rol s

tatio

n

Fu

el h

andl

ing

mac

hine

Fu

el e

leva

tor

Fuel

serv

er



8.7 SPENT FUEL STORAGE AND COOLING SYSTEM

This system receives the irradiated fuel and reflector elements from the reactor core, packages them into containers, and provides intermediate storage until they are shipped off. The elements are removed from the core and placed into the fuel storage wells as described in Section 8.6. The spent elements are transferred to the fuel canning facility where they are sealed into containers. The containers will then be relocated to a spent fuel cooling facility where it will be stored until their decay heat has decreased to the point that they can be safely loaded into large capacity shipping and storage cask. The spent fuel elements are stored in tubes surrounded by water to remove the decay heat. The cooling water used for decay heat removal is part of the NI Cooling Water System. As an option, a long term dry cask storage facility could be added to store the shipping and storage casks on site. This option could be added at a later date. See Table 8.7-1 for boundaries and interfaces.

D

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Inc.

, an

AR

EVA

and

Sie

men

s co

mpa

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GN

P N

ucle

ar H

eat S

ourc

e S

yste

m B

ound

arie

s an

d In

terfa

ces

P

age

32

TAB

LE 8

.7-1

SPE

NT

FUEL

STO

RA

GE

AN

D C

OO

LIN

G S

YSTE

M B

OU

ND

AR

IES

AN

D IN

TER

FAC

ES

SPE

NT

FU

EL

ST

OR

AG

E A

ND

CO

OL

ING

SY

STE

M B

OU

ND

AR

IES

AN

D IN

TE

RFA

CE

S Sy

stem

In

clud

ed c

ompo

nent

s B

ound

arie

s Ph

ysic

al in

terf

aces

O

ther

inte

rfac

es

Spen

t Fue

l Sto

rage

an

d C

oolin

g Sy

stem

1)

Plan

t Ele

ctric

al S

yste

m

at e

quip

men

t & c

ontro

ls

2)

Site

& C

ivil

Wor

ks a

t th

e bu

ildin

g / e

quip

men

t in

terf

ace

3)

Rad

ioac

tive

Was

te a

nd

Dec

onta

min

atio

n Sy

stem

(li

quid

) at s

tora

ge w

ell d

rain

to

sum

p

4)

Fuel

Han

dlin

g Sy

stem

at

exc

hang

e po

int b

etw

een

syst

ems (

fuel

stor

age

wel

l) 5)

N

ew F

uel H

andl

ing

and

Stor

age

Syst

em a

t han

d-of

f po

int w

ith S

pent

Fue

l St

orag

e an

d C

oolin

g Sy

stem

6)

N

HS

Con

trol a

nd

Mon

itorin

g Sy

stem

at

devi

ce c

onne

ctio

n

1) C

oncr

ete

stru

ctur

al e

mbe

ds

& b

uild

ing

stee

l (SC

W)

2) I

nter

face

bet

wee

n eq

uipm

ent

and

the

Com

pone

nt H

andl

ing

Syst

em e

quip

men

t suc

h as

the

over

head

cra

ne. (

CH

S)

3) T

he fu

el st

orag

e w

ell m

ust

acco

mm

odat

e th

e fu

el h

andl

ing

equi

pmen

t for

pic

k-up

and

off

-lo

adin

g of

fuel

and

refle

ctor

el

emen

ts (F

HS,

NFH

S)

4) I

nter

face

with

Com

pone

nt

Han

dlin

g Eq

uipm

ent t

o en

sure

fe

asib

le re

pair

& re

plac

emen

t (C

HS)

5)

Rea

ctor

cor

e fu

el a

nd

refle

ctor

ele

men

ts (R

S)

6) I

nter

face

with

radi

olog

ical

w

aste

at s

yste

m d

rain

pip

e co

nnec

tion

(RW

DS)

Rad

iolo

gica

l 1)

C

ontro

l of c

onta

min

atio

n

2)

Rad

iatio

n sh

ield

ing

for

wor

kers

at a

ll po

ints

of s

yste

m

3)

Crit

ical

ity c

ontro

l of s

pent

fuel

4)

R

adia

tion

and

cont

amin

atio

n m

onito

ring

at se

lect

poi

nts

thro

ugho

ut th

e sy

stem

El

ectri

cal &

con

trol

1)

Pow

er c

onne

ctio

n to

syst

em

equi

pmen

t and

con

trols

(NC

MS

for m

onito

ring,

PES

for p

ower

su

pply

) Th

erm

al h

ydra

ulic

s 1)

Dec

ay h

eat f

rom

spen

t fue

l pr

ovid

es a

hea

t loa

d to

the

(NIC

WS)

2)

Dec

ay h

eat f

rom

spen

t fue

l pr

ovid

es a

hea

t loa

d to

the

(NIH

VA

C)

Fu

el st

orag

e w

ell

Spen

t fue

l can

ning

faci

lity

Spen

t fue

l coo

ling

syst

em

Spen

t fue

l cas

k lo

adin

g fa

cilit

y



8.8 NEW FUEL HANDLING AND STORAGE SYSTEM

The purpose of the New Fuel Handling and Storage System is to receive and inspect new fuel and reflector elements. Then the elements are delivered to the fuel storage well (see Figure 8.6-2). The new elements are then installed into the reactor core using the Fuel Handling System. The new fuel elements would be transported to the fuel storage well via the same transport equipment used to move the spent elements from the fuel storage well to the fuel canning facility. See Table 8.8-1 for boundaries and interfaces.

TABLE 8.8-1 NEW FUEL HANDLING AND STORAGE SYSTEM BOUNDARIES AND INTERFACES

NEW FUEL HANDLING AND STORAGE SYSTEM BOUNDARIES AND INTERFACES System Included

components Boundaries Physical interfaces Other interfaces

New Fuel Handling and Storage System

TBD 1) Spent Fuel Handling System at hand-off point of new elements to the fuel transport equipment of the spent Fuel Handling System 2) Plant Electrical System at power connection to equipment & controls 3) Site & Civil Works at the building /equipment interface

1) Interface with structural embeds & building steel (SCW) 2) Interface with spent fuel handling equipment at hand-off point of new elements (SFSS) 3) Interface with Component Handling Equipment to ensure feasible repair & replacement of equipment (CHS) 4) Reactor fuel and reflector elements at handling features of the elements (RS)

Radiological 1) Radiation shielding for workers 2) Criticality control Electrical & control 1) Power connection to system equipment and controls (PES)



8.9 HELIUM SERVICE SYSTEM

The Helium Service System purifies the primary coolant and maintains the correct coolant chemistry. The recycled coolant is compressed and transferred to helium storage tanks. The system helps control primary coolant pressure and replaces small quantities of helium lost to leakage. The helium is returned back into the system as a purge gas at specific points of the Main Heat Transport System. The purification system components can be modular to allow real time repair and replacement. See Table 8.9-1 for boundaries and interfaces.

TABLE 8.9-1 HELIUM SERVICE SYSTEM BOUNDARIES AND INTERFACES

HELIUM SERVICE SYSTEM BOUNDARIES AND INTERFACES System Included


Helium Service System

TBD 1) NI Cooling Water System at equipment connection 2) Main Heat Transport System at main circulator (optional) 3) Shutdown Cooling System at the SCS circulator (optional) 4) Vessel System at penetration nozzles 5) NHS Control and Monitoring System at device connection 6) Plant Electrical System at equipment power connection 7) Site & Civil Works at the building /equipment interface 8) NHS Control and Monitoring System at sensor connections for HSS monitoring

1) Main He circulator for possible valve actuation (MHTS) 2) Shutdown He circulator for possible valve actuation (SCS) 3) RPV penetration nozzles for make-up (VS) 4) Structural concrete embeds & building steel (SCW) 5) Chilled water to equipment for cooling (NICWS)

Radiological 1) Control of contamination and possibly shielding for workers from irradiated particulates removed from the helium Electrical & control 1) Electrical power and sensor connections (NCMS for monitoring, PES for power input) Thermal hydraulics 3) Cooled helium added to Main Heat Transport System coolant (MHTS) 4) NI Cooling Water System water is used to cool HSS equipment (NICWS) Heat transfer 1) Cooled helium in injected into the primary coolant stream cools the vessel nozzle (VS)



8.10 NI HVAC SYSTEM

The Nuclear Island Heating, Ventilation, and Air Conditioning System (NIHVAC) is responsible for the overall HVAC of the NI. It is composed of several discrete systems for different areas including clean and potentially contaminated areas. The system is made up of conventional industrial equipment. The system will also help remove contamination from the air. The systems shall be designed to maintain appropriate temperatures for personnel and equipment. See Table 8.10-1 for boundaries and interfaces.

TABLE 8.10-1 NI HVAC SYSTEM BOUNDARIES AND INTERFACES

NI HVAC SYSTEM BOUNDARIES AND INTERFACES System Included


NI HVAC System

TBD General Boundaries correspond to the specific areas being ventilated. Specific boundaries conform to the actual HVAC equipment boundaries up to the air intake and exhaust point. Detailed boundaries will be defined as the design progresses. 1) Plant Electrical System at equipment connection 2) NHS Control and Monitoring System at device connection 3) Site & Civil Works at the building / equipment interface 4) NI Cooling Water System at air chillers (optional)

1) Concrete structural embeds & building steel (SCW) 2) Chilled water to air handlers (NICWS)

Thermal hydraulics 1) The NIHVAC system is used to cool the NCA housings (VS) 2) Decay heat from spent fuel provides a heat load to the NIHVAC system (SFSS) Electrical & control 1) Power connection for system equipment (PES for power input, NCMS for monitoring system) Radiological 1) Control of contamination and dose from potentially contaminated system filters 2) Filtering air to trap some radioactive particulates



8.11 PLANT ELECTRICAL SYSTEM

The Plant Electrical System (PES) consists of four subsystems, the plant AC electrical system (PACS), the Plant Essential AC Electrical System (EACS), Plant DC Electrical System (PDCS), and Plant Essential DC Electrical System (EDCS). The PES boundaries are the low voltage bushings of the unit transformers and the high voltage bushings of the unit startup auxiliary transformers. See Table 8.11-1 for boundaries and interfaces.

Major distribution equipment of the PACS include the unit and startup auxiliary transformers, isolated phase bus duct, switchgear, unit substations, motor control centers, and distribution panel boards. The components are located as close to the point of utilization as possible.

When the plant is on-line, the normal source of power is the unit generator. When the plant is shut down or the normal power source is unavailable, power is delivered from offsite via the switchyard and is capable of starting and running all normal and essential loads.

The Plant AC Electrical System (PACS) delivers power generated by the plant offsite to the transmission network through the unit transformer(s) and receives power from the network through the unit startup auxiliary transformer(s).

The Essential AC Electrical System (EACS) includes a plant uninterruptible power (PUP) supply with capacity to supply all control, instrumentation, and plant protection AC loads which must not lose power via redundant channels. There is one PUP per unit and is powered by a dedicated essential DC electrical system. The PACS supplies emergency AC/DC lighting for all areas needed for safe shutdown and fire fighting and access/egress routes thereto. The EACS supplies emergency AC lighting for the control room.

The Plant DC Electrical System (PDCS) supplies DC voltage to the plant control and instrumentation loads. The system includes storage batteries, battery chargers, and distribution switchgear.

The Essential DC Electrical System (EDCS) supplies DC voltage to the “Safety Related” DC plant loads. The system includes storage batteries, battery chargers, and distribution switchgear. The EDCS power supply is fully independent of other modules.

D

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Inc.

, an

AR

EVA

and

Sie

men

s co

mpa

nyN

GN

P N

ucle

ar H

eat S

ourc

e S

yste

m B

ound

arie

s an

d In

terfa

ces

P

age

37

TAB

LE 8

.11-

1 P

LAN

T EL

ECTR

ICA

L SY

STEM

BO

UN

DA

RIE

S A

ND

INTE

RFA

CES

PLA

NT

EL

EC

TR

ICA

L S

YST

EM

BO

UN

DA

RIE

S A

ND

INT

ER

FAC

ES

Syst

em

Incl

uded

com

pone

nts

Bou

ndar

ies

Phys

ical

in

terf

aces

O

ther

inte

rfac

es

Plan

t El

ectri

cal

Syst

em

1)

All

syst

ems u

sing

ele

ctric

al p

ower

: At t

he

conn

ectio

n w

ith e

ach

elec

trica

l dev

ice.

See

inte

rfac

es

for s

yste

m li

st.

2)

Site

& C

ivil

Wor

ks a

t bui

ldin

g / s

uppo

rt in

terf

ace.

3)

Si

te &

Civ

il W

orks

at s

witc

hyar

d: L

ow v

olta

ge

bush

ings

of t

he u

nit t

rans

form

ers (

outb

ound

vol

tage

) 4)

Si

te &

Civ

il W

orks

at s

witc

hyar

d: H

igh

volta

ge

bush

ings

of t

he u

nit s

tartu

p au

xilia

ry tr

ansf

orm

ers

(inbo

und

volta

ge)

1) S

truct

ural

co

ncre

te e

mbe

ds

& b

uild

ing

stee

l (S

CW

)

Elec

trica

l & c

ontro

l 1)

At e

ach

elec

trica

l de

vice

or d

evic

e co

ntro

ller t

o su

pply

po

wer

(RC

CS,

FH

S,

SFSS

, NFH

S, H

SS,

NIH

VA

C, C

HS,

RPS

, IP

S, P

MC

S, S

WD

S)

Pl

ant A

C e

lect

rical

syst

em (P

AC

S) li

nk to

grid

St

artu

p au

xilia

ry tr

ansf

orm

er

U

nit t

rans

form

er

Is

olat

ed p

hase

bus

duc

t

Switc

hgea

r

Uni

t sub

stat

ions

Mot

or c

ontro

l cen

ters

Dis

tribu

tion

pane

l boa

rds

Bac

kup

pow

er g

ener

ator

(s)

Es

sent

ial A

C e

lect

rical

syst

em

Plan

t uni

nter

rupt

ible

pow

er su

pply

Es

sent

ial D

C e

lect

rical

syst

em

St

orag

e ba

tterie

s

B

atte

ry c

harg

ers

Dis

tribu

tion

switc

hgea

r

Plan

t DC

ele

ctric

al sy

stem

St

orag

e ba

tterie

s

B

atte

ry c

harg

ers

Dis

tribu

tion

switc

hgea

r



8.12 NI COOLING WATER SYSTEM

The NI Cooling Water System removes heat from plant components such as:

� Helium purification train components

� Main helium circulator

� Nuclear Island HVAC

� Other equipment as necessary

The nuclear island NI Cooling Water System is completely separate from the balance of plant cooling water system to prevent the spread of radiological contamination. Each reactor module cooling water loop consists of pumps, chillers, a surge tank, filter / de-mineralizer train, piping, instruments, and controls as needed. See Table 8.12-1 for boundaries and interfaces.

D

ocum

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o.:

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EVA

NP

Inc.

, an

AR

EVA

and

Sie

men

s co

mpa

nyN

GN

P N

ucle

ar H

eat S

ourc

e S

yste

m B

ound

arie

s an

d In

terfa

ces

P

age

39

TAB

LE 8

.12-

1 N

I CO

OLI

NG

WA

TER

SYS

TEM

BO

UN

DA

RIE

S A

ND

INTE

RFA

CES

NI C

OO

LIN

G W

AT

ER

SY

STE

M B

OU

ND

AR

IES

AN

D IN

TE

RFA

CE

S Sy

stem

In

clud

ed c

ompo

nent

s B

ound

arie

s Ph

ysic

al in

terf

aces

O

ther

inte

rfac

es

NI C

oolin

g W

ater

Sy

stem

The

boun

dary

for a

ll eq

uipm

ent i

nter

face

s are

at

the

conn

ectio

n po

int o

n th

e eq

uipm

ent

1)

NIH

VA

C sy

stem

s at a

ir ha

ndle

rs

2)

Hel

ium

Ser

vice

Sys

tem

at

hel

ium

syst

em c

ompo

nent

3)

M

ain

Hea

t Tra

nsfe

r Sy

stem

at t

he e

quip

men

t co

nnec

tion

4)

Ves

sel S

yste

m a

t the

ve

ssel

pen

etra

tion

5)

Site

& C

ivil

Wor

ks a

t the

bu

ildin

g /e

quip

men

t int

erfa

ce

1)

Hel

ium

serv

ices

pu

rific

atio

n tra

in (H

SS)

2)

Mai

n &

SC

S he

lium

ci

rcul

ator

s (M

HTS

, SC

S)

3)

NIH

VA

C a

ir ha

ndle

rs

(NIH

VA

C)

4)

Con

cret

e st

ruct

ural

em

beds

& b

uild

ing

stee

l (S

CW

)

Ther

mal

hyd

raul

ic

1) T

he N

I Coo

ling

Wat

er

Syst

em p

rovi

des c

oolin

g ca

paci

ty to

equ

ipm

ent i

n th

e fo

llow

ing

syst

ems (

HSS

, M

HTS

, SC

S, N

IHV

AC

) 2)

Dec

ay h

eat f

rom

spen

t fue

l pr

ovid

es a

hea

t loa

d to

the

NI

Coo

ling

Wat

er S

yste

m

(SFS

S)

Rad

iolo

gica

l 1)

Con

tam

inat

ion

cont

rol (

NI

syst

em o

nly)

El

ectri

cal &

con

trol

1) P

ower

con

nect

ion

for

syst

em e

quip

men

t (PE

S)

Pu

mp(

s)

C

hille

r(s)

Surg

e ta

nk

Fi

lter /

de-

min

eral

izer

trai

n

Pipi

ng

In

stru

men

tatio

n

Con

trols



8.13 COMPONENT HANDLING SYSTEM

Maintenance and repair of the NHS requires lifting and handling equipment for all components that are expected to be replaced or moved. This handling equipment includes cranes, special temporary handling/manipulating equipment, temporary equipment storage areas, building access for replacement components, and interface with external transportation facilities. A “flight path” and temporary resting area will be developed for each item expected to be replaced. Floor loading shall be considered where needed along the flight path. See Table 8.13-1 for boundaries and interfaces.

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TAB

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.13-

1 C

OM

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ENT

HA

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LIN

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AN

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FAC

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RIE

S A

ND

INT

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uded

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ies

Phys

ical

inte

rfac

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er in

terf

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C

ompo

nent

H

andl

ing

Syst

em

1)

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eact

or S

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m a

t el

emen

ts a

nd c

ompo

nent

s re

quire

d to

be

rem

oved

2)

Si

te &

Civ

il W

orks

at

the

build

ing

/ sup

port

inte

rfac

e 3)

Pl

ant E

lect

rical

Sys

tem

at

the

equi

pmen

t con

nect

ion

4)

Fuel

Han

dlin

g Sy

stem

: m

ust b

e ab

le to

man

ipul

ate

& in

stal

l thi

s equ

ipm

ent

5)

The

Com

pone

nt

Han

dlin

g Eq

uipm

ent

boun

dary

is li

mite

d to

the

poin

t at w

hich

mob

ile

equi

pmen

t can

acc

ess t

he

inte

nded

load

. 6)

Fu

el H

andl

ing

Syst

em

is in

stal

led

and

man

euve

red

by C

ompo

nent

Han

dlin

g Sy

stem

equ

ipm

ent

1)

Mus

t lift

and

m

anip

ulat

e th

e Fu

el

Han

dlin

g Sy

stem

eq

uipm

ent (

FHS)

2)

M

ust l

ift a

nd/o

r m

anip

ulat

e sp

ecifi

c N

HS

equi

pmen

t req

uirin

g sp

ecia

l han

dlin

g or

lif

ting

capa

bilit

ies.

Equi

pmen

t lis

t to

be

deve

lope

d. (V

S, R

S,

MH

TS, S

CS,

RW

DS)

3)

Si

te &

Civ

il W

orks

at

all

tem

pora

ry re

stin

g lo

catio

ns fo

r com

pone

nts

and

thei

r lift

rigg

ing

(SC

W)

Elec

trica

l & c

ontro

l 1)

Pow

er c

onne

ctio

n fo

r sy

stem

equ

ipm

ent (

PES)

C

ore

serv

ice

tool

s

A

uxili

ary

serv

ice

cask

Se

rvic

e to

ols f

or R

eact

or S

yste

m

Res

erve

shut

dow

n va

cuum

tool

N

eutro

n de

tect

or se

rvic

e eq

uipm

ent



8.14 REACTOR PROTECTION SYSTEM

The Reactor Protection System (RPS) is the system that ensures that off-site radiological dose rates do not exceed allowable limits. Each reactor module has an independent RPS. The RPS is designed to operate automatically but can be initiated by an operator. See Table 8.14-1 for boundaries and interfaces. This system performs the following functions:

� Reactor trip utilizing the control rods, which initiate rapid reduction in reactor power following reactivity excursions or loss of core cooling.

� Reactor trip utilizing the reserve shutdown control equipment, which acts as a diverse reactor trip system and as additional protection against reactivity excursions caused by water ingress.

� In the event of a steam generator leak into the primary coolant, the main coolant loop is shutdown and the main steam line is isolated. This acts to isolate the steam generator and trip the main helium circulator to limit water ingress into the core and other vulnerable components on the Vessel, Reactor, and Main Heat Transport Systems.

TABLE 8.14-1 REACTOR PROTECTION SYSTEM BOUNDARIES AND INTERFACES

REACTOR PROTECTION SYSTEM BOUNDARIES AND INTERFACES System Included


Reactor Protection System (RPS)

TBD 1) Reactor System at NCA and pellet hopper connections 2) Power Conversion System at isolation valve connections 3) Plant Electrical System at power input connection for this system 4) Site & Civil Works at the building / component support interface 5) NHS Control Room Operator Interface System at the distribution panels for the control room 6) Main Heat Transport System at main circulator motor controls 7) Vessel System at relief valve

1) Connection with structural concrete embeds and building steel (SCW) The interfaces are at the physical electrical connection at the device.

Electrical & control 1) Power connection for system equipment (PES) 2) Connection to control room (CROIS) 3) Boronated graphite pellet hoppers (RS) 4) Neutron control assemblies (RS) 5) Secondary loop steam isolation valves (PCS) 6) Connections to the circulator and sensors for monitoring and shutdown during a loss of primary coolant (MHTS)



8.15 NHS INVESTMENT PROTECTION SYSTEM

The NHS Investment Protection System (IPS) is designed to limit damage to plant equipment during upsets and events. There is likely one IPS for each reactor module. Like the RPS, the IPS is designed to operate automatically but can be initiated by an operator. See Table 8.15-1 for boundaries and interfaces. The types of functions this system will perform are:

� Steam generator isolation and steam/water dump which limits the quantity of water that can leak into the core and the resulting chemical attack on reactor components.

� Primary coolant pump down, which limits the release of primary coolant and the thermal cycling of reactor components.

� Shutdown Cooling System initiation, which starts the Shutdown Cooling System upon loss of primary coolant , thus reducing thermal cycling of large components.

� Startup control rod insertion at reactor shutdown event.

The IPS may also provide the following investment related plant monitoring functions:

� The Vessel System pressure relief valve closure interlock

� Safety related equipment status and RPS channel readout information displays

� Investment protection equipment status and channel readout information displays

� Post accident monitoring information and displays

� Monitoring to facilitate post transient plant restart

� Helium leak monitoring

� A continuous, dedicated display of a minimum set of plant parameters or derived variables that may be used by the operator during all plant conditions to access plant safety status.



TABLE 8.15-1 NHS INVESTMENT PROTECTION SYSTEM BOUNDARIES AND INTERFACES

NHS INVESTMENT PROTECTION SYSTEM BOUNDARIES AND INTERFACES System Included


NHS Investment Protection System (IPS)

TBD General note: Boundary of this system is at electrical connection of each device. 1) Reactor System at NCA controls for rod drop at shutdown 2) Vessel System at the pressure relief valve block connections 3) Main Heat Transport System at connections to circulator controls 4) Shutdown Cooling System at connections to circulator controls 5) NHS Control Room Operator Interface System at the distribution panels for the control room 6) Power Conversion System at steam isolation valve 7) Plant Electrical System at power connection for system 8) Site & Civil Works at the building / component support interface. 9) Plant Electrical System at power input connection for this system 10) Steam/Water Dump System at connection to dump valve actuator controls

All electrical interfaces are at the device connection point 1) Connection with structural concrete embeds and building steel (SCW)

Electrical & control 1) Power connection for system equipment (PES) 2) Steam isolation valves for steam dump and isolation (PCS) 3) Vessel System relief valve for coolant pump down (VS) 4) Primary coolant circulator to shut down and close valve (MHTS) 5) Start SCS circulator to cool the reactor core during shutdown (SCS) 6) NCA rod insertion at reactor shutdown (RS) 7) Connection to control room (CROIS) 8) Connection to dump valve actuator control(SWDS)



8.16 NHS CONTROL AND MONITORING SYSTEM

The NHS Control and Monitoring System (NCMS) provides direct interface to all plant actuators and sensors to perform plant control functions within the Nuclear Island (NI) and the Power Conversion System (PCS). Plant level load allocation is performed by the NCMS. Each reactor module can be controlled independently. See Table 8.16-1 for boundaries and interfaces.

TABLE 8.16-1 NCMS BOUNDARIES AND INTERFACES

NCMS BOUNDARIES AND INTERFACES System Included


NHS Control and monitoring System (NCMS)

TBD 1) The boundary of this system is at electrical connection of each device 2) Spent Fuel Storage and Cooling System at device connection 3) NIHVAC system at device connection 4) Helium Service System at device connection 5) Reactor Cavity Cooling System at device connection 6) Shutdown Cooling System at device connection 7) Site & Civil Works at the building / component support interface 8) Reactor System at connection to NCAs that enable removal and installation of the NCA 9) Vessel System at pressure relief valve 10) NHS Control and Monitoring System at circulator motor control and fault monitoring (over-amp, vibration, etc.) 11) Plant Electrical System at power input connection for this system 12) Steam/Water Dump System at sensor for leak detection

1) Connection with structural concrete embeds and building steel (SCW)

Electrical & control 1) The NHS Control and Monitoring System interfaces to all plant actuators and sensors. The interface point is considered the connection point nearest the device. (RS, VS, MHTS, SCS, RCCS, SFSS, HSS, NIHVAC, PES, CROIS, SWDS)



8.17 CONTROL ROOM AND OPERATOR INTERFACE SYSTEM

The purpose of the Control Room and Operator Interface System (CROIS) is to provide a means for the operator to monitor and control the plant. This system provides the operator with information from the NCMS, IPS, and RPS systems. Similarly, the CROIS allows the operator to transmit instructions to NCMS, IPS, and RPS controllers or directly to individual actuators.

TABLE 8.17-1 CROIS BOUNDARIES AND INTERFACES

CROIS BOUNDARIES AND INTERFACES System Included


Control room and operator interface system (CROIS)

TBD 1) The boundary of this system is at the distribution panels for the control room. All physical connections with other systems are made here. 2) Site & Civil Works at the building / component support interface

1) Connection with structural concrete embeds and building steel (SCW)

Electrical & control 1) Power connection for system equipment The control room and operator interface system interfaces with the NCMS, IPS, and RPS systems to provide the operator full control and monitoring of NHS equipment. The interface point for connection to these systems is the distribution panel.

8.18 RADIOACTIVE WASTE AND DECONTAMINATION SYSTEM

The Radioactive Waste and Decontamination System provides a means of managing and where possible, decontamination of all radioactive waste generated within the plant. See Table 8.18-1 for boundaries and interfaces.

All potentially radioactive gas generated in the reactor plant is collected. Gases with low levels of radioactivity may be stored allowing for activity decay to allowable levels prior to release; otherwise, the gasses are processed by the system.

All potentially radioactive liquids are captured and treated based upon the liquid type and the expected level of contamination. Liquids may be treated and prepared for disposal, treated and recycled for use in the plant, or treated and released to the environment.

All potentially radioactive solid waste generated within the reactor plant are captured and treated in this facility except used fuel elements. Compactable items are compacted and made ready for shipment. Liquefied waste are treated and solidified where necessary.

The decontamination services provides the facility and tools required for general decontamination of equipment and components used within the reactor plant.



TABLE 8.18-1 RWDS BOUNDARIES AND INTERFACES

RWDS BOUNDARIES AND INTERFACES System Included


Radioactive Waste and Decontamination System (RWDS)

TBD 1) The boundaries of this system are at the collection point of the source and the physical boundaries of the processing facility. 2) Site & Civil Works at the building / component support interface 3) Spent Fuel Storage and Cooling System (liquid) at the storage well drain to sump 4) Reactor Cavity Cooling System (liquid) at cavity drain to sump

1) Connection with structural concrete embeds and building steel (SCW) 2) Component Handling System equipment to assure capacity to lift and manipulate RWDS equipment (CHS) 3) Spent Fuel Storage and Cooling System (liquid) at the storage well drain to sump (SFSS) 4) Reactor Cavity Cooling System (liquid) at cavity drain to sump (RS)

Radiological Monitoring of system as deemed necessary by health physics Electrical & control 1) Power connection for system equipment (PES)

8.19 STEAM/WATER DUMP SYSTEM

The STEAM/WATER Dump System is capable of emptying the steam generator’s steam/water inventory in the event of a leak which results in moisture ingress to the primary coolant. It can also be used to drain the steam generator to perform maintenance. The system consists of a redundant valve train connected to the main feedwater line between the SG and the feedwater line isolation valve, see Figure 8.19-1. The boundary of this system is the pipe connection of the first dump valve off of the feedwater line. See Table 8.19-1 for boundaries and interfaces.



Figure 8.19-1 STEAM/WATER DUMP SYSTEM

Feedwater

Main Steam

Cold Reheat

Hot Reheat

Isolation Valves

SG vessel

Dump Valves

Dump Tank

to Gaseous Radwaste

to Liquid Radwaste

Water-Steam Dump System

Quench water

Feedwater

Main Steam

Cold Reheat

Hot Reheat

Isolation Valves

SG vessel

Dump Valves

Dump Tank

to Gaseous Radwaste

to Liquid Radwaste

Water-Steam Dump System

Quench water

TABLE 8.19-1 STEAM/WATER DUMP SYSTEM BOUNDARIES AND INTERFACES

STEAM/WATER DUMP SYSTEM BOUNDARIES AND INTERFACES System Included


Steam/Water Dump System (SWDS)

Dump valve

1) Power Conversion System at the pipe connections of the first dump valves. 2) Site & Civil Works at the building / component support interface 3) Radioactive Waste and Decontamination System at the pipe connection to the dump tank 4) NI Investment Protection System at valve controls 5) Plant Electrical System at valve actuator 6) NHS Plant Control and Monitoring at sensor for dump valve leak detection

1) Power Conversion System at the pipe connections of the first dump valves. (PCS) 2) Site & Civil Works at the building / component support interface (SCW) 3) Radioactive Waste and Decontamination System at the exhaust/vent pipe connection to the dump tank (RWDS)

Radiological Monitoring of system at the dump tank, dump tank relief, and as deemed necessary by health physics Electrical & control 1) Power connection for dump valves (PES) 2) IPS for valve actuation 3) Sensor for dump valve leak detection (NCMS)

Steam/Water Dump System



9.0 REFERENCES

1. AREVA document 51-9103803-000, NGNP Conceptual Design Baseline Document for Conventional Steam Cycle for Process Heat and Cogeneration

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11

12

13

14

15

16

17

18

19

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E-1

APP

END

IX E

: N

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MA

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TRIX

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12

13

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16

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36-0

01

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NP

Inc.

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P

age

F-1

APP

END

IX F

: N

HS

SYST

EM H

EAT

TRA

NSF

ER IN

TER

FAC

E M

ATR

IX

Sect

. #

1 2

3 4

5 6

7 8

9 10

11

12

13

14

15

16

17

18

19

RS

VS

MH

TS

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uel H

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ium

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tem

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em

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tive

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min

atio

n Sy

stem

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ity C

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ning

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stm

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rote

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n Sy

stem

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W

Site

& C

ivil

Wor

ks

PCS

Pow

er C

onve

rsio

n Sy

stem

SW

DS

Stea

m/W

ater

Dum

p Sy

stem

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