ML20043A373

From kanterella
Jump to navigation Jump to search
Summary of 900420 Meeting w/C-E in Windsor,Ct to Discuss Application of Human Factors Engineering in Design of Sys 80+.Meeting Participants,Agenda & Slide Presentation Encl
ML20043A373
Person / Time
Site: 05000470
Issue date: 05/10/1990
From: Singh R
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
PROJECT-675A NUDOCS 9005210270
Download: ML20043A373 (87)


Text

.

n

.! 3 g '

44.

7 T

1 May 10,'1990 1

a Project No.:675 i

j f

' FACILITY:

.CE Syrism 80+'

APPLICANT:

' Combustion Engi_neering,.Inc..

SUBJECT:

-MEETING BETWEEN NRR;AND CE ON HUMAN FACTORS ENGINEERING.FOR; SYSTEM 80+;

1 the NRR staff met with representatives:of Combustion On April'20,;1990,(CE):at thetr; offices in Windsor, Connecticut tn discuss Engineering, Inc.

n the-application of human factors engineering
in:?the design:of System 80+.
' lists the meeting participants. Enclosure 2 provides the meeting-O agenda.- '

j

c; Fo110 wing'a brief overview of System 80+,- CE presented theLdesign bases and?

description of Nuplex 80+ Advanced Control Complex including: human' factors approach to the' design.'3The' presentations were followed by_a live. mock-up demonstration of.Nuplex 80+.-

' ~

In sunnary,- the staff obtained.a.better understanding of: Nuplex 80+ design 3

which would.be4 helpful in the. review of CESSAR-DC Chapter.18.0, Human Factors 1 Engineering.. Copies of: presentation, slides used by CE are' provided in ~

1

. Enclosure 5.

1 lsl

}

L

,Rabindra N. Singh,1 Project Manager.

L

-Standardization and Life Extension L

Project Directoratet jil L

Division of. Reactor Projects -;III, IV, 1

V'and.Special-Projects-Office of Nuclear Reactor Regulation

' Enclosures As stated t

?

cc w/ enclosures:

iL #

.See:next page i

)1STR::Bir 7 Nr..

.]

- p th r er NRC Participants

~

7 y' 0 -'

NRCIPDR ACRS(10)~

.O

  • F.'Miraglia RCorreia c

PDSLjR/F' REckenrode

.[i -

o c..

RSingh PShea W'

OGC' EJordan

(

C%

)'*

PDSL:l b H PDSL:PM/lfD D:PDSL

/

PSh VF RSingh:cw CMil 05/4}er

(

[

05/ /90 05y /90

/90 j

u

h NgmREO

~ Ib

' UNITED STATES NUCLEAR REGULATORY COMMISSION t 9

i

, WASHINGTON, D, C. 20066 x

May-10,M.990

_ {

Project No, 675 -

4:.

FACILITY:

CE System 80+ -

I

APPLICANT:'
Combustion Engineering,.Inc.

SUBJECT:

HEETING BETWEEN NRR AND CE ON: HUMAN FACTORS ENGINEERING:FOR!

SYSTEM 80+--

T0riApril 20, 1990,- the NRR staff met with: representatives of Combust 1on Engineering, Inc. -(CE) at their offices;in Windsor, Connecticut to discuss

- the application of. human factors engineering-in the design of. System 80+..

lists'the meeting participants.. Enclosure 2 provides the meeting q

cagenda.

.Following a_brief! overview of System 80+, CE presented the design; bases ande j

description of;Nuplex 80+^ Advanced-Control Complex including human factors 1

-approach to the design.. The' presentations were followed by,aflive mock-up_

h Jdemonstration of Nuplex'80+.=

,i I

In summary; the staff obtained 'a better~ understanding' of Nuplex 80+ design =

E 1which would'be helpful in1the review of CESSAR-DC-ChapterL18.0,iHuman Factors _

Engineering. Copies of presentation slides used by!CE-are provided in.

4 1,

e 1

Q Rabindr N. Singh, Project'. Manager-Standardization and Life Extension 1

'ProjectDirectoratel a

' Division of Reactor. Projects -EIII,_IV, Y and_Special Projectsc Office of Nuclear ReactorLRegulation

Enclosures:

1 As stateo 1

cc w/ enclosures:

l See next page t

I i

1

]

l m

1 o

f t

- u

,o

-f y

Combustion Engineering,;Inc.

Project No. 6751

~

cc:- Mr. C. B. Brinkman,' Manager:

' Washington Nuclear Operations Combustion Engineering, Inc.

12300 Twinbrook Parkway:

Suite 330' Rockv111e;' Maryland' ; 20852 =

4 Mr. St' n Ritterbbschl a

Nuclear Licensing Combustion Engineering 1000 Prospect Hill; Road ~

Post Office Box 500-Windsor.1 Connecticut - 06095-0500 l

i

]

l la s

L

~ - -

- )

l

{

i

I I

f(

)

Enclostire 1

+f 4

' MEETING BETWEEN NRR AND~CE ON SYSTEM 80+'.

-April'20;1990 n-t

' MEETING PARTICIPANTS NRR --

-CE.

l R.-Eckenrode.,

R. Turk i

.R. Correia S. Ritterbusch' R. Singh K..Scarola'.

D. Harmon, et'al.

,i r

t

,- r t

I l'

1 i

i

\\

. -i

.r

.i.

..i

,w k

~

.---.a-

./

s

$$END6_

MEETING BETWEEN NRR AND CE WINDSOR, CONNECTICUT a

APRIL 20, 1990-1 18:30 - 9:00-Introduction and Overview-S. Ritterbusch, 9:00 - 10:00 Nuplex 80+ Overview and'.

K. Scarola-Identification of Specific:

-NRC Interests.

10:00 - 11:45 Nuplex 80+ Mockup Demonstration' D.-Harmon-

.11:45 - 12:30 Lunch q

12:30 - 2:30 Continued. Presentation, D. Harmon

]

Demonstration and Discussion-i i

u

.]

q i

i i

1 l

i.

s

Lhw %

N'..

c.

L 4

. 12 a

3 ABB/C-E NUCLEAR DESIGN 3 ACTIVITIES o

EVOLUTIONARY ALWRs --SYSTEM 80+;

H

'o PASSIVE ALWRs:- SIR d'

-PIUS:

o ADVANCED NoN-WATER: REACTORS,- NHTGR 1

a b;-

1 t

e j

{

i.

e5 s

i l

SYSTEM $$#

~

=

4

$YSTEM 80+ DESIGN OBJECTIVES o

IMPR0vED SAFETY o

IMPRQVED PERroRMANCE o

PRovru TECHNOLOGY i

o AVAILABLE IN EARLY 1990's s.

1 4

syareu8@b"

^*

I SYSTEM 80+ IS A COMPLETE PLANT t

f o

NSSS I

O SAFEGUARDS SYSTEMS O

ELECTRICAL DISTRIBUTION SYSTEM i

o CONTAINMENT /IRWST j

' I 1

o NUPLEx 80+ ACC i

o BOP 1

1 r.

l

.i

.1

- 1

-l 1

k E

i d

l system $$#

l t

y

M e

O s

4 e

s

]g}

}i l

~

s f

l1l1

}gil0 8

l

~

4 9

i

__--______m___________._m___-----,~~.______--_.----.---,-..,-..e-

.+-44--..

w-->s.- - -

r e,.

e r w r-

+-

s 5

5 5

5 5

5 5

5 5

5 5

A o

t Ig 1 mam ii.

i MBERi!

l*

^

A I

11,

, ;f['

11' h

et sarj g

4 I,

assil~

33 i

s I

allil:

i E

B O'a 0 t

iI I

I I

e i

e i

e i

3 s

g a

e a

a a

.a a

=

(09 WBASAS SA +09 WBASAS)

WC10Vd N011000BW MSIM BAIAVTlR00

\\

a

'l

.i i

SYSTEN 80+ DESIGN STATUS 9

l-

)

i, u

o-NSSS ESSENTIALLY' COMPLETE i

o SELECTED B0P SYSTEMS NEARLY COMPLETE-1 CONTAINMENT-EFW NUPLEx 80+

4 i

o OTHER B0P SYSTEMS:

i SYSTEM DESCRIPTIONS ESSENTIALLY-COMPLETE -- STILL l'

WORKING ON DESIGN DETAIL AND SYSTEM LAYOUTS-

~.

t l

system $$#

V l

I 2.

x T

'h Q

11 i

I

[--

6 D

/7 aI j4 j

4 1

i j

g

I

~

4 c.im1

$aBil 1

,i,

_ i ci t

l.

52

~

=

r

-j

.l

.}

1 1

~

+

1 1.

MEET ALL CURRENT REGULATORY AND INDUSTRY REQUIREMENTS FOR INSTRUMENTAT10N AND' CONTROLS:

POST-TMI ACTION PLAN-j HUMAN FACTORS ENGINEERING j

FIRE PROTECTION AND SAB0TAGE I

VERIFICATION AND VALIDATION PRA 2..

T0 IMPROVE PLANT SAFETY:

DIGITAL PROTECTION SYSTEMS WITH CONTINUOUS AUTOMATIC TESTING l

FOUR TRAIN ESFAS IMPROVED MAN-MACHINE INTERFACE 3.

T0 IMPROVE PLANT AVAILABILITY:

I FAULT TOLERANT CONTROL SYSTEMS

' PRE-TRIP CONTROL ACTIONS POWER DEPENDENT PROTECTION LIMITS i

l IMPROVED MAN-MACHINE' INTERFACE 4.

'TO IMPROYE THE C0ST EFFECTIVENESS OF NUCLEAR POWER 1

GENERATION:

LOWER CONSTRUCTION COSTS 4

SHORTER DESIGN AND CONSTRUCTION SCHEDULES LOWER OPERATION AND MAINTENANCE COSTS 4

gypggygp

=

g.

3e-

\\

~

j l

I'o

=l l

i I

u t

i i

REMAINING CFESAR-DC SUBMI1 TAIT-W

[

USI/GSI REs0LUTIONs1(20)~

p APnIL 1990 ECCS AND CONTAINMENT ANALYSES ~

SAFE 1Y ANALYSTS h

Auousr 1990 PRA AND SEVERE ACCIDENT REsuLTs

{l

!l SEISMIC METHODS' BUILDING layouts Ll l

i DECEMsEn 1990. -

SEISMIC REsuLTs h

1 TECNNICAL SPECIFICATIONS INSPECTIONS, tests, ANALYSES MAINTENANCE AND-RELIAsILITY-L GUIDELINES REMAINING-USIs/GSIs 1

1

.l l

1-L L

i f

SYSTEMN#

i l

,_..._.......i..,-,,.,.~,._'.,........,...,,,.I,.,m._,.

-.s.

u m.

-r--

g

'h e

hli

~

CI

/

c

<M /

l I. x- --

l' s

1l

/

_t 8

5L "amin -

l B-G,IbG g

q l'

o o

i g

t-t t

l l w

M o

o li I

i h

1

. ~ _. _, _...

SLIDE 127 D006

^ '

NUPI FX B0+ MTAIiFB MtIGN NUPLEX 80+ !$ BEING APPLIED TO THE F0LLOWING PROGRAMS:

EACH IS CONTRIBUTING TO THE DETAILS DESIGN O

ADVANCEDCONTROLCOMPLEXFORSYSTEM80+(EV5LUT!0 NARY ALWR) --DOCUMENTATION HAS BER SUBNITTED TO TE U.S.;

NRC (CESSAR-DC) FOR DESIGN CERTIFICATION.

O ADVANCED CONTROL COMPLEX FOR THE SAFE INTEGRAL REACTOR O

ADVANCED CONTROL COMPLEX FOR NHTGR'- NEW PRODUCTION REACTOR ADVANCED CONTROL COMPLEX FOR EHWR - NEW PRODUCTION o

REACTOR o

APPLICATION OF NUPLEX 80+ TECHNOLOGY-TO SELECTED SYSTEMS FOR YGN 3&4

q

ii f

,a a

e APPLICATION OF GENERIC NUPLEX 80+ DESIGN-i

~

?

(!'

NUPLEX 80+

GENERIC DESIGN d!

r ii i

't.

7 v.

4

' DESIGN REQUIREMENTS 4

FOR.

REFERENCE REACTOR TYPE X SYSTEM 80+

SIR MHTGR.

!&C DESIGN.

MHTGR-K?R FOR EHWR REFERENCE REACTOR SAR' TYPE X

.t A

PROJECT SPECIFIC CUSTOMER REQUIREMENTS DOE UTILITY X FINAL ItC DESIGN-FOR PLANT X l

l x

FIGURE 2-2 l

r l

l f

..,--o s.mga

-~ums

--see,a-w rw w-

-v---.-r---m-sm-s----n.smeeau-

~-----~-wms-,.

e a a-vmaa.--w

.as

.<msr e-mm.--

ews---a+.

s+--

--,--.<-e-a

,l l

- e a

O

' i,

4 e

i' i

g 1

l.

1 a

n I

1

,s l

g g

l I

4 g

g

- ss -

l g

8 c

St g

N w

l

-l l

l ff o

o.

, a e

j-;

1 l

_.-___._.-__..._.,_.._,,...._.__..____....._.-..__._,_.1_,__..._..,__.._."

4-Ag d48+.M-4.d Ma#a,.ai-

-ewe.wtK---

4-4#-BA.---.

- + + -d.me w3h,8-*.b..WmaX

.a.A44 em--

.aw md.- - - -

444 s_.;--.,.4w-- - - - - -- - --

i wm s

--naa s-,---%

---,-y 1

i

{

l$'

r%.

i f

f

)

E

/

i h@

[%

E --

/

8-(\\.

,i: '& \\

8

\\

s s

. 4 L, 7. WA

.i

- -v j g7 e

s E

4r l l-l.

t V

L t.

e. e

q i

l L

q

.NUPLEX 80+ INFORMATION DESIGN BASIS-l i

l 1.

' CRITICAL FUNCTIONS l

j.

PLANT SAFETY AND POWER PRODUCTION CAN BE-

'l MAINTAINED BY CONTROLLING A MINIMUM SET OF i

CRITICAL FUNCTIONS l

2.

SUCCESS PATHS ll THE POTENTIAL T0 ADEQUATELY CONTROL A CRITICAL-FUNCTION IS MAXIMlZED BY KNOWING-THE PERFORMANCE l

QUALITY OF NORMALLY OPERATING PLANT SY4TEMS,.THE i

STATE.0F READINESS OF EMERGENCY SYSTEMS, AND THE 4

PERFORMANCE QUALITY OF EMERGENCY SYSTEMS Whil THEIR OPERATION IS REQUIRED i.

3.

INFORMATION QUALITY l-THE QUALITY OF OPERATOR DECISIONS AND 0PERATOR.

RESPONSE TIME ARE. ENHANCED BY KNOWING THE VALIDITY j

OF THE DATA PRESENTED.

4.

INFORMATION PRIORITIZATION INFORMATION OVERLOAD IS MINIMlZED BY PRIORIT! ZING INFORMATION, THEREBYLALLOWING AN OPERATOR.TO-BETTER FOCUS HIS ATTENTION s

l yggp

.. m

.r._,.,,, _

,. _... ~..

.m__

~... -. _ _ _ _ _. _...... ~... - _ _... _.. _ _. _.. _ _,... _... _.

...., ~....

4 '

9 0

0

{

-+

o L.

\\

h 3

l 2

M ttr

./

\\

/}v

,umma,t

/..,

.ga g 1;

f:

<8 9mm 8

n 1

an. a.

E',ya n

4

,t

.msmm'g. 6

)

+,

e-

<l j

@j

-l

  1. 4-

" d'

a i!h

% [m

!f 5

i 3

i

_1, 3 4

I.

48 <l 4

05

"""'u 1

A si 2

'"1 Y

UO

>sI s

4g 1jg imill as i

Ls s

'u'"'

M L

0 mus.a U ].3-l-

4

[

g lE L

i l.

+

l

.j

..1n i

____._.-.-.__.____.___,........___.._.,_..-_.,.__,_._.,...._...,...J_,...l-.d._,..

l l

l l

3 s

.T

~

4.,

p

~

.:y i

l a

s ' ['h l

l shM I

i

"*4 g,

-.,e.

3r,t, B

81 i

S I

E!

6s.sa p.,_,

a. ca..g:

g

. 4,g Ei d, Ar,. L '% " $

i:.

f d'* 'k-

',]

a

- w u..ve

^

,a v.u.

.K

'i' ' '4._ '

l\\ p jM.

t

.'j.l

~R

?'3.~

i l

{.

',? hW.~.

% r.

l A w % g $',

i

,..p,..

y LT I

C

(

.,f{,y f.' & V

(Q

?.* '

a Iaaa 4:,

1ill 3:

e-iAa.a.

Ce ggg -)

e

., -d l 'lilii!

e x

i, i

i o,

r 1

e


,---------v----.---,---,_u-n,,.-...n.-,,

,.,,,w-,---,----.-v--.,-,

an.,---.-,--,-,~~~-

e.

.-,.v.,,----e-e-

e w.r am'6u.a a

e.q.m.s-

.wa.a Aa, a.yes.

a s

m.

4._4 e

4

_.4 W_,4 2.

m4.a4..m

m. p

,sa_a:

4 4

ag.og.wA,,a,4

,p a44 p

, y 4g A.s 9

8

'A

'I mouname I

a-

'WC W

l y

ni llj*

1 wk g

W r -l l'

8

)

,.h,

~

i W

)

i r

I tl i

I 4

e 5

E E

C S

E l

" d g

ui x

i i

)

=

y

.i b

.i 5

1 i

l' 1

s we e

l a

e c

B

  • I wW d

l

=

g g

w l

?

- 't

- -. -. - - - -,... - -,.- -... -...:--..----:-..._.___..-..__.-__--...=---.__._---

y.

,,m


.-------..m.r m2 g

--um,,%ou.

a

--.am.4a*u_#aw__,m

..~,e

,.=.ma e

4m A

a,,

m6

  • eA4,4 4.

saak..

O-0 I,

p la s

,(

l

/

/

rll. x_#

~

y i-

-=

S d

i g

l I<

=

u g qdVb0

(

o g f,7 f

i g

n t

>l ili

=

m

-r, L

1

/

e 1

i O

O li 3

illi 4

6 d,

,+-,-re-n.

--,wv 3

.y

+-... -.-- -.,--, -.,,,,. ~,.,

s,#,,

.w-,...,,w

+... - -,c.

SLIDE 170, DOC NUPLEX 80+ TECHNOLOGY i

DATA PROCESSING SYSTEM

-REDUNDANT 32-BIT SUPER-MINICOMPUTERS (8 MIPS) l 15,000 Po!NT DATA BASE l

2 SECOND THROUGHPUT

[j OPTICAL DISK STORAGE 32-BIT MICRO-COMPUTER WORKSTATIONS TOUCH SENSITIVE COLOR CRT'S DISCRETE.. INDICATION AND ALARM SYST S l-L 16 AND 32-BIT MICRO-COMPUTERS - DISTRIBUTED 5,000 POINT DATA BASE 2 SECOND THROUGHPUT ELECTRO-LUMINESCENT DISPLAYS WITH TOUCH SENSITIVE l

SCREENS 4

)

COMPONENT CONTROL SYSTEM PLANT PROTECTION CALCULATORS d

POWER CONTRfA SYSTEM PROGRANt!NG LOGIC CONTROLLERS - DISTRIBUTED 16-B1T C0-PROCESSORS REMOTE MULTIPLEXED I/O 5

15,000 1/0 POINTS 50-250 MSEC THROUGHPUT CORE PROTECTION CALCULATORS 32-BIT SMALL MINICOMPUTERS l

Nunex80+

l

SLIDE 170 DOC e

g NUPLEX 80+ DIVERSITY o

NUPLEX 80+ MAXIMlZES STANDARDIZATION WHILE l

MAINTAINING DIVERSITY IN KEY AREAS TO ENSURE THAT.

THE DEFENSE IN-DEPTH CONCEPT IS NOT COMPROMISED l

0 NUPLEX 80+ DIVERSITY:

FUNCTION DESIGN TYPE 1 DESIGN TYPE 2 REACTOR TRIP PLANT' ALTERNATE j

PROTECTION REACTOR TRIP l

SYSTEM WITHIN PROCESS-CCS-4 FLUID SYSTEM EMERGENCY NORMAL CONTROLS SUCCESS PATHS SUCCESS PATHS L

(E.G.,

(E.G., MAIN-EMERGENCY FEEDWATER)-VIA l

FEEDWATER) VIA PROCESS-CCS l

ESF-CCS i

y REACTIVITY EMERGENCY NORMAL CEA-CONTROLS BORAT10N VIA CONTROL VIA ESF-CCS POWER CONTROL SYSTEM ALARM AND ALARM TILES CRT DISPLAYS -

INDICATION AND DISCRETE VIA DPS INDICATORS -

VIA DIAS 4

ax80+

k i

a- -.., - - - - -- - - - - _ _ - -. - - -

--.-,..---------.-----..-----------,--u.--,--su.-

w-,me a,..-vm.+-

s.

m

\\

I

~

T j

CONTROL Sir 5 TEM i

s

'f n

j

_e m

m r

4 gg M OPTCCS 1

~

l

\\ )

' f OMA 8'880CESsuces J f

g %

sysw.no

)

N i

Pt.A N Y P F

.,TeON l

m i

1 sw an 1

W

'l l

A n

=

m

-]


9 was.mancos essater i

l d

--p t.Dec

> '#0CES M yCRT

)

e

'I

+

a I

e 4

c g

1 i

i s

t

)

l 3

i o asra.

N M sCS TRIP j

j eitss ic i_oose

)

,unu caocess o

1942 3

-l se.noas f

J

+

__ [

/ !, _

i

=

1

=== son l

N 4.OWIC i

=

'moessenes ff i

~

t USE OF VAllDATED SENSOR DATA secsert mocaman,.e TOR INFORMATION DISPLAYS AND CONTROL j

c

-- - -m:

I j

L..

4 6

l NUPLEX 80+ DATA C0muNICATION DESIGN BASIS-L J

0 MULTIPLEXING IS USED WHERE COST EFFECTIVE IN y

SAFETY AND NON-SAFETY APPLICATIONS.

R o

N0 MULTIPl.EXING INSIDE CONTAINENT.

,j i -

o MULTI-DROP NETWORK TYPE COMUNICATIONS IS UTILIZED q

WITHIN SYSTEM BOUNDARIES ONLY.

i o

SYSTEM TO SYSTEM COMMUNICATIONS'ARE HARDWIRED OR DATA LINKED POINT TO PolNT.

o FIBER OPTIC INTERFACES ARE USED WHERE ISOLATION IS l

REQUIRED (A, B, C, D, X, Y, MCP, RSP).

'J o

CONTROL, PROTECTION AND PAM SYSTEMS RECEIVE FIELD:

DATA DIRECTLY.

DIAS AND DPS RECEIVE FIELD DATA FROM OTHER SYSTEMS.

4 l

)

i l-

~

l

- 5 mrth$

L i'--.' -.-,,

~ - - - - - -.

~

f2&ibiw* l I

,l

,g- -

8 g

i Ah il n:

....1 n~a u

l1--

g33___.

'e w.

{

4

'E I-

%l v

ljj

)

l >j,j!.ll

!!!Ii!

yl i

d, i

t o Illid-l!,ill

! *I

(

4iey glii:

, e--

i b

8 ii y

r l

1 yp~

, ipp4bi c L

..L 3

f ilh

~

e.

jgp!

H9 l

l

,4>

jl e

,'5h A.

, dl, l

. isAabl s II l

L

,. e o

gie i p,,:

llll h][

-j n

Y e.

[jl !

j'!-

i;llfi!!$l!bi l

.!!,idY illi'!it r,,hg

@l wi n

,,iy i

us:

.,e i sa I'

%l

'hkll' 'i!!!>l !!!I

.kk ~, !

3053 g._

g e

sv dh S'

=

l u.ne.nt i e

Decemb.r 30, 1988 TYPICAL UNIT MAIN POWER SYSTEM ONE LINE R

1 NUPLEX 80+ SAFETY IMPR0VEENTS i

0 l

L o

PLANT PROTECTION SYSTEM PROVIDES CONTINUOUS SOFTWARE EXECUTION TO VERIFY TRIP. LOGIC FUNCTIONALITY r

o DPS PROVIDES C0WUTER ASSISTED LOGGING AND l

VERIFICATION FOR PERIODIC COMP 0NENT SURVEILLANCE-l TESTS l

o PLANT PROTECTION SYSTEM PROVIDES EVENT BASED SEGMENTATION WITHIN EACH CHANNEL o

DIESEL LOADING SEQUENCER ADAPTS TO PLANT EVENTS TO MINIMIZE SEQUENCING TIE-o PLANT PROTECTION SYSTEM INITIATES PRE-TRIP CONTROL ACTIONS SUCH-AS RPC O

MEGAWATT DEMAND SETTER KEEPS PLANT WITHIN OPERATING' LIMITS l

l.

i e

Ex80+

O 9

p.

._______________________s__.-._,-_..__.m.__,e--_

.m--

,v..,

_~5,..-.....,,,,..,%.-

.y_m,y,%,..._-...h,

i.

I NUPLEX A0+ SOFTWARE QLIALIFICATION 1

4 o

, VERIFICATION AND VALIDATION 0F. USER DEVELOPED APPLICATIONS SOFTWARE IN ACCORDANCE WITH:

i I

ANS!/IEEE - ANS - 7.4.3.2 REGULATORY 6UIDE 1.152 o

HIGH LEVEL LANGUAGES ARE USED T0 THE MAXIMUM EXTENT l

PRACTICAL:

oco LADDER LOGIC 1

o COMPILERS AND MACHINE OPERATING SYSTEMS ARE QUALIFIED BASED ON PRIOR FIELD OPERATING EXPERIENCE AND VSV AT I

j THE APPLICATIONS LEVEL o

EXTENSIVE CONFIGURATION CONTROL NUPLEX80+~

l, l

l'

e i

NUPtFX 80+ COMPLIANCE WITH EPRI REQUIREMENTS MULTIPLEXED DATA C0mVNICATION SUPPORT EPRI G0ALS FOR REDUCED PLANT CONSTRUCTION COSTS AND SCHEDULES.

l i --

FACTORY TESTED AND INTEGRATED SYSTEMS SUPPORT EPRI i

G0ALS FOR REDUCED PLANT COMISSIONING T!fE.

IMPROVED PERFORMANCE AND RELIABILITY OF DIGITAL i

i CONTROL AND PROTECTION SYSTEMS SUPPORT EPRI G0AL OF LESS THAN ONE REACTOR TRIP PER YEAR.

j ADVANCED INFORMATION DISPLAY TECHNOLOGY SUPPORTS EPRI GOAL OF ENHANCED OPERATOR PERFORMANCE FOR SAFETY AND AVAILABILITY.

i ADVANCED HUMAN FACTORS AND AUTOMATION FEATURES SUPPORT EPRI G0ALS FOR REDUCED OPERATOR STAFFING.

i STANDARDIZED HARDWARE FOR NSSS AND B0P SYSTEMS SUPPORT EPRI GOALS FOR REDUCED SPARE PARTS AND MAINTENANCE PERSONNEL.

SOFTWARE BASED SYSTEMS AND MULTIPLEXED INTERFACES l

SUPPORT.EPRI GOALS FOR EASY MODIFICATION AND EXPANSION.

L.

l l

NUPLEXM+

= '

SLIDE 143. DOC j

'^

c NUPLEX 80+ - EPRI ALWR COMPLIANCE

^

a NUPLEX 80+ MEETS THE CURRENT EPRI ALWR REQUIREMENTS, WITH J'

SOME EXCEPTIONS'-

8 U

EPRI-ALWR MPLEX B0+

g o MANUALLY INITIATED CONTINU0US ON-LINE AUTOMATIC i

AUTOMATIC TESTING TESTING o ALL ISC RECONFIGURABLE RECONFIGURATION.FOR FAILURES

  • j ON FAILURES NOT ACCOMODATED ELSEWHERE o THREE FULL CAPABILITY CONTROL PANELS WITH SPATIALLY.

3 COMPACT WORKSTATIONS-DEDICATED INFORMATION AND-i CONTROLS o BACK-UP QUALIFIED NO BACK-UP REQUIRED CONTROL-PANEL o BIG BOARD DISPLAY WITH BIG BOARD DISPLAY WITH PRE-1 COMPONENT LEVEL PROCESSED OVERVIEW INFORMATION' INFORMATION i

n l

  1. 7 ~n e L 4 r e w g e c e s.c e up

[A2Z-ui? D l

CHAPreit

/o i.c ww u n.c a r s w e NWc n 96e 0 e.ri a n ou a tra y

___.)

l

.., ~....

........,.. ~ --- _...,_,,,-......-, - 2,m.,.._.....,

,-.m_..

e s

SYSTEM 80+

1 l

Function &

ThskAnalysis se L

FinalReport 4

o j

i l

Prepared by:

j Human Factors Services January 19'89 l

1 OPERATIONS SERVlCES SOMBUSTION ENGINEEltING

. a

[

['

4 a

l '.

5 I ;llllli-

+

3 NUPLEX 80+

L u,

B8 X O Tat lL;

'. 7,,

-3Il

-l i

Verification Analysis Report Revision 2 l

u 1

NPX80-TE790-01 December 1989 i

^

Human Factors & Cognitive Engineering Group SOMBUSTION ENGENBERING

e

%,_ m

J SLIDE 127. DOC 19 -

L, 3

- NUPLEX.80+?.

N DESIGN BASIS FOR THE CONTROL ROOM-

.l Lx CONTROL ROOM DESIGNED FOR; OPERATIONAL FLEXIBILITY TO MEET THE VARIETY 0F STAFFING ASSIGNMENTS EXPECTED AT.

VARIOUS: UTILITIES.

.THERE:ARE TWO: DESIGN BASES-CONDITIONS:

3 A.

OPERATION BY SINGLE OPERATOR WITHIN THE I

- CONTROLLING WORKSPACE BETWEEN.H0TiSTANDBY.AND FULLLPOWER..

~

B.

OPERATINGoSTAFF 0F SIX PEOPLE'FOR"BOTH NORMAL AND EMERGENCY OPERATION IN CONTROLLING' WORKSPACE, INCLUDING A: CONTROL'R00M SUPERVISOR.

4 OTHER. STAFFING LEVELS SELECTED BY THEtUTILITY ARE l

ENVELOPED BY THESE. DESIGN BASES.

1 l

i d

g

+ - - - -

c-,--+n.s,.n

,......m,*

e-e

+-w e

4

l--

.1 d

l=

Z o

j.

l to I

'l b-l.

g2

~'

"~

l I

g 4

S

.I i

h j' E

h 1

i I

r-

-l-

[

l l-l-

1 I

i t_________________-

________I COMWUN!=

fo[h"

{!

SECOND LEVEL ~

ooCUMENT SC 8 VIEWING sTomaeg GALLERY' SECURITT ' i (010)

(i i

DESK

/

r cas!

!b uo

/

.j CRS CONSOLE

,=

as 1

tan

-(

orax orax sec0Nonny COOLING CYCLE N

WATER (A2)

FtRE PROTEC-HVRC

.l TION TURBINE

-RCS (All (RS)

(W5)

(M1) b E

FO wTR CONDENSAT CVCS (W4)

PLANT-(W2)

(M3)

WONITORING AND CONTROL l

IPSO l

CALMA FILE:

i

[I, t

a s

i l

=

.YGN 3&4 CONTROL.

ROOM; comparison with::

d

-N U PLEX-80;+

CONTROL 1 ROOM-4 g#

-n i

s

-m n

I I

g om 5

I

..o....

.s

.i I

l e

atm s

3

  • M[

Contact k tarn listavi st

+

i, CONEGLE

)

At

,,,g,

'/ -

/

3' sn$s I

[ enY a

s l

=== 4,3'

-===

g ifgtempi C00Llos

)

M8 14.3 enttR tatt 6

N

l'

. p-82' 1

N 18C=

J ft.se,tt,es AC. S.

N 9

ik r o.tn.

4g Osetastarg Cvtt -

tas*8 Plasef maps st9M 4'

y(

g Pee CopeineL j

11890

]

i

~

h.

gy

~

m..

.i

-1

l J_

N t

~

E C

L d

O

- a l

]

J A gS

)

I

_ 7-E U

~

vS L

^.

oR P

eO 0

s

-G a'

N 7

oc' Eo 8

DW i

vA Ro X

I P

EE n

N 1

Gi L

Nv 1

I

- p r.

~

HPO R

v T

c

-. s t

P 4

"'C*o o

j m, 2 k

L g

N E.

t-9

&E.

A Y

GA E-8eA RSL S

V R

On ASP EO S

so S

LEt T

e AsD E

R EO T

a A

E RD R C Ct L

So L

fN O

OI R

T NO v'-

C L,

B

[

S s

eS s

EE SIV C

A e

L C

'A P

M ELN O

VI

~

+

ET l9 1

s s LC E

E 4EY T0 T

s

- 0 E

GA ET ET MA L RA RA 8

PS RSP I

I O

ASS CC C

. X TS LEI SD

- P S

AtsD DN DO I

N RR lF i

AC l

DN&

lq i

k' E

E

&EY TO T

T GA ET ET S

MAL RA RA RSP Cc CC ASS t

I LEf SD SD t

I AMO DN DN lg l

l A

ERA e

. n

, e H

C T

i T

I R

W l

C S

i L

O s s R

T s

N OC i

l lI i

&EY ER TO GA ET ET MA L RA RA RSP C

CC

. ASS CID ID LE!

S SI AMO DN N

I ll l

l l9 l

& E'Y E

E GA T0 T

ET ET MAL RA RA

. RSP CC CC ASS SI I

Dna SD e

LE8 ID BON 3

AM f -

, e <

ll i

l

go 1

x a

7 pll

~

n d

e 3

C C

x

{-

2

.g.

2 tg g

-)

g, 5-R R-

~

s t

A.

(

e

.pl m

v[.

vw

.I Er e<

l"g!

gl f

r r

v I {

u J Q.

s a

w

s y' s

U

{,3 g;

y; d

a g

<s a n Ji )

l s

w w

I

!,5 rv v2 z

"G H H l

-g

{

(

-s

.h.

N

.\\

\\L

\\'

\\

5-1 3*5 v

d'$

r r

/

/e I

f.

E W w

3

~

sas E3

<w jg1 d[5

\\

  1. G H H h-l

!s wt r2

%g ss se,,,,,

a, q

3 s

1

-- ~ ~ =

~ :l ll

(*

- 3 i

1 g

NUPIFX 80+~ REMOTE SHUTDOWN-PANFl Lo

'RSP PROVIDES INSTRUMENTATION?AND: CONTROLS NECESSARY.:'l

'TO ACCOMMODATE GETTING.LT0;AND MAINTAINING:-

HOT SHUTDOWN ~-:WITH;SAME Peti AS. CONTROL-ROON!

3 COLD SHUTDOWN --WITH~CRT!INFORMATION AND: SOFT CONTROLS.

5

.s

(

+

~

n o

RSP COMPLETELY ISOLATED FRON CONTROL ROOM

]

a i

)

o RSP PROVIDES TWO-CONTROL TRAINS-4 i

'I CONTROL TRANSFERRED BY. SEPARATE CHANNEL SWITCHES o

LOCATED IN EQUIPMENT R00M.

ALL TRANSFERS ARE BUMPLESS.

U 9-h k

g a

^

n u.

c l'

b illi y t

$(

"I f

,q a

.)

4 N

a a

A S.,

U a,

,r,

.;j I

H.

C (E

-l j

U -.

- j; y

a g

storw g

. i, t

/i2 go

)"

4 1

4 l

3 y

3 q

g, Igg-4

\\

-1

(-

Amendment E

'\\'

December 30,1988

i m-Figure Jg REMOTE SHUTDOWN PANEL LAYOUT 18.8 1

t.

t-

~

+

c.

- NUPLEX 80+LDESIGN' BASIS.

'FOR i

INFORMATION PROCESSING AND DISPLAY 1.

REDUCE THE 00ANTITV'0F DATA:THAT'MUST BE MENTALLY:.

. PROCESSED BY AN OPERATOR, TO MINIMIZE "INFORMATION' I

OVERLOAD":

i o

CROSS-CHANNEL SIGNAL VALIDATION PRIOR T0; DISPLAY-

-o REDUCE DATA THROUGH.RELATED PARAMETER; CORRELATION PRIOR.TO DISPLAY:

j

'l J

+

2.

DISPLAY INFORMATION USING HIERARCHICAL PRESENTATION, TO BETTER-RELATE DATA TO PLANT-STATUS:

i o

PLANT LEVEL'0VERVIEW INFORMATION'ONLIPS01 0

KEY SYSTEM PARAMETERS ON DISCRETE' INDICATORS-0 FOUR-LEVEL CRT DISPLAY PAGE HIERARCHY-t 3.

USE DISPLAY TECHNIQUES THAT ALLOW RAPID.

COMPREHENSION:

o ANALOG BAR GRAPHS 0-TREND INDICATORS o

COLOR GRAPHIC DISPLAYS o

UNIFORM SYMBOLOGY AND DYNAMICS i

NUPLEX80+

O s

1 y

m j

SLIDE 127. DOC 72 4.

ALLOW EASY ACCESS OF INFORMATION AT ALL LEVELS:-

0-INDICATORS PROVIDE TOUCH ACCESS TO SUPPORTING-1 DATA

{

- 0 CRT; DISPLAYS PROVIDE TOUCH ACCESS AND-MENU SELECTIONS 5.

ALLOW AN OPERATOR TO USE THE SAME DISPLAYS DURING ACCIDENTS THAT HE USES DURING NORMAL OPERATION, TO ENSURE FAMILIARITY:

T iSMICALLY: QUALIFIED; INDICATORS CORRELATE l

o NORMALLY USED' SENSORS TO PAMI SENSORS-

\\

SPDS IS INTEGRATED IN NORMAL CRT DISPLAY SYSTEMS o

1 i

i 6..

PROVIDE REDUNDANCY AND DIVERSITY-IN-INFORMATION-PROCESSING AND DISPLAY SUCH THAT 0PERATORS HAVE CONFIDENCE IN INTELLIGENT DISPLAY l TECHNIQUES AND SUCH l

THAT PLANT SAFETY AND' AVAILABILI1Y ARE.NOT IMPACTEDl BY EQUIPMENT FAILURES:

h t

.INFORMATION REQUIRED FOR OPERATION FOR 24 HOURS o

i WITHOUT DPS-IS ALSO PROCESSED AND DISPLAYED BY DIAS' TWO SYSTEM REDUNDANCY IS' INVISIBLE TO OPERATORS.

o THROUGH CONTINUOUS CROSS-CHECKING AND INTEGRATED OPERATOR INTERFACES NUPMX80+

d M%

w

n I

i

. SLIDE 125; DOC i

NUPLEX 80+: DESIGN BASIS "

FOR.

l ALARM PROCESSINGLAND DISPLAY.

j s

q

'\\

1.

REDUCE THE NUMBER OF ALARMS-GENERATED TO MINIMIZEL OPERATOR"INFORMATION.'0VERLOAD*:.

y y

l 1

0.

CROSS-CHANNEL SIGNAL VALIDATION PRIOR..TO ALARM d

GENERATION l

H o

ALARM = LOGIC AND-'SETPOINTS; CONTINGENT ONL APPLICABLE PLANT MODE-J 1

-)

2.

DISPLAY ALARM WITH DISTINCT VISUAL CUEING.IN ACCORDANCE WITH PRIORITY 0F REQUIRED'0PERATOR RESPONSE,-TO BETTER' FOCUS OPERATOR ATTENTION:-

U i

1 1

0

' PRIORITY 1 IMEDIATE ACTION j

0

~ PRIORITY-2 PROMPT ACTION O

PRIORITY 3

. CAUTION 0

OPERATOR AID STATUS INFORMATION I

+

.,..~........_....4

..__.,,,__......,...-,..d.

.,m.-_,.......-,...m

...m..-

- SLIDE 125. DOC x\\.

gc 3.

DISPLAY ALARMS USING TECHNIQUES THAT HELP THE a

OPERATOR QUICKLY'CORRELATELTHE' IMPACT OF THE ALARM-ON

' PLANT SAFETY OR PERFORMANCE:

I o

GROUPED DISPLAYS WHICH' HIGHLIGHT THE NATURE 0F THE-PROBLEM RATHER' THAN THE: SYMPTOM-DEN 0TED BY.

2 THE SPECIFIC ALARM CONDITION.

j o

FIXED SPATIALLDEDICATION OF ALARM DISPLAYS ALLOWING. PATTERN RECOGNITION P PLANT LEVEL PICTORIAL OVERVIEW DISPLAY.SHOWS~

SUCCESS PATHS AND CRITICAL FUNCTIONS: IMPACTED BY l

PRIORITY 1l ALARMS 1

+

4. -

ENSURE THAT ALLLALARMS AREiRECOGNIZED BYJTHE OPERATORS, WITHOUTc" TASK'0VERLOAD":

0 ALL ALARMS ARE INDIVIDUALLY ACKNOWLEDGEDr OR g

ACKNOWLEDGED-IN SMALL FUNCTIONALLY RELATED GROUPS o

ALL-ALARMS CANLBE ACKNOWLEDGED AT ANY CONTROL-j PANEL j

o MOMENTARY AUDIBLE ALERTS FOR ALARM STATE CHANGES

' REQUIRING NO OPERATOR ACTION TO SILENCE--

1 o

0

. PERIODIC MOMENTARY AUDIBLE REMINDERS FOR' UNACKNOWLEDGED CONDITIONS 0

GLOBAL STOP FLASH WITH RESUME TO ALLOW DEFERRED ACKNOWLEDGEMENT a

ypygg -

l t1

-l

rO SLIDE 125. DOC l

+

o s-k 5.

PRhlDEQUICK,DIRECTfACCESS_-TOSUPPORTINGL INFORMATION TO ENHANCE'0PERATORiRESPONSE:TO ALARM.

t CONDITIONS:

3 o

SINGLE OPERATOR ACTION:PROVIDES L

ALARMTACKNOWLEDGEENT LJ

-DISPLAY OF ALARM PARAETERS l

H SELECTION OPTIONS FOR.CRT DISPLAY PAGES' d

APPROPRIATE FOR ALARM CONDITION-l y

6.

PROVIDE' REDUNDANCY:AND DIVERSITY:IN ALARM' PROCESSING-H AND DISPLAY:SUCH;THAT OPERATORS HAVE CONFIDENCE IN j

INTELLIGENT ALARM' PROCESSING lTrCHNIQUES AND SUCHLTHAT

PLANT SAFETY AND AVAILABILITY ARE NOT-IMPACTED BY:

EQUIPMENT FAILURES:

4 O

PRIORITY l'AND 2' ALARMS'ARE PROCESSED kND-DISPLAYED BY TWO ' INDEPENDENT SYSTEMS

\\

o TWO SYSTEM REDUNDANCY IS INVISIBLE 4TO OPERATORS ~-

j THROUGH CONTINUOUS CROSS-CHECKING AND INTEGRATED H

OPERATOR-INTERFACES y

)

y e-

- - ~..

.-,,-e,-.3,

.e-

.m.,,,.

-3

a l

1

_ INTEGRATED BIFORRAATIOOG PRESEB8TKFIOss NUPLEX 80+:

i a

w

~

i p

INTEGRATED

!L PROCESS l

STATUS OVERVIEW

~

ALARM l

+-

. CRT DISPLM i

PAGES 1 1

TILES l

l r

t PHiMARY

')

Fi+%

Fe%

FEA_-_

.r

/

x

=c i

f DISCRETE

=.

lm'

..l]&

g eNIECT INDICATORS. -l

. -l i

"??

CVCS ggs s'

s e's i

e s

k u

fl\\/IN

. j SYSTEM-]

l l

l l

l l

l l

ECH.

- OIL SEALS GING UP RCP RCP RCP CHAR-MAKE 1

CONTROLS l l

l l

l l

l l

l IN t

1

\\

.r r

~

I f

}

{

l

. _.. _ _ _ _ _ _ _ _ - _ _ = _, _ _ _. _

%g

.O' B4TEGRATED BEFORREATIOIS PRESEIETATIOIG.. NUPLEX 80+

INTEGRATED L

l PROCESS u

' STATUS H

l s,

a #

OVERVIEW

~

a j

ALARM Af

~

? CRT DISPL AYl-j.

TILES y

. PAGES g

l-PaumAny y

M M-FL-L VL W

.t t i

O.

C.

O.h.

i DISCRETE gw

~y asNECT INDICATORS,,ig

,,i

,.}g RCP

' e _a '

e _e CVCS e-e SYSTEM

[.l'

/{

L CONTROLS RCP RCP RCP CHAA-asAKE

~

M OIL.

SEALS GING UP m -

i

^

h 1

[

y 1 --

1 4

4 l-m

'I

-,--,,,,.-i_

-v -

e-N -

e-l s-e0 - ' nd.f, L ~.,-,.

,r,,

e:

n

f f!GUAEl-18.6.5-t NUPLEX 40* CONTA0L R00W i

l g

1 l-Rw 1-o

.I -

'l

[

g r

l

.}

w-S i a-e l-

~

1 w

n r.

w

[

f' 5-

~

9,. f, L r- %

-g

,Y, l-I L_____________

. h,,

_ _ _ _.) e F---

q Couuw. <

occuusNT SECONO LEVEL -

C,$[:I0' stoAAes IIC 8 VII'IN8-3 M LERJ

-I Sigt

OSSN q

oNII :

J

\\

M.E.se CRS CONSOLE settem-vg ESF

( ASI -.

DESN casu

\\

sacemenev cvssa sees COOLING WATER (A2) h

' FIRE Pm0ftC*

IION

'*83 TURS!NE HVAC1 L

(WS)

MCS (All (W))

i; i

F0 sTR CONOENSAT CVCS tyg)

Pl. AN T.

tW2)

- (W3)

WONt70 RING ANO CONTROL

[

\\

l

' L IP50 ].

l (j

e,g g g gj,,,,

^

_ _,., _,. - - ' ^ " "

asuaaw.em m

i o

>I o

n o

l{

/b p.

L o-REDUCES A-LARGE QUANTITY'0'F DAT TOA-SMALNQUANTITYOF l

f

. EASILY RECOGNIZED AND UNDERSTOOD:INFORMATION.

f

~

o PROVIDES A SINGLE LOCATION TO ALLOW QUICK' ASSESSMENT OF.

l KEY 'INFORMATION-. INDICATIVE: 0F CRITICAL PLANT POWER.

q PRODUCTION AND SAFETY: FUNCTIONS (

O IPS0:INFORMATIONfINCLUDES::

I

. TRENDS, DEVIATIONS,. NUMERIC VALUES OFLMOST..

i REPRESENTATIVE CRITICAL FUNCTION P RAMETERS:

1 EXISTENCE AND SYSTEM LOCATION OF PRIORITY 1 ALARMS,

q INCLUDING AVAILABILITY AND-PERFORMANCE STATUS FOR.-

-SYSTEMSSUPPORTINGCRITICAL/FUNCTIDNS'(SUCCESS

' (

PATHS)

L o

EXISTENCE.AND PLANT-AREA'LOCATIONIOF:0THER; UNACKNOWLEDGED' ALARMS-k

+

0 IPSO. BRIDGES THE GAP-BETWEEN AN OPERATOR'S1 TENDENCY.-

i TOWARD SYSTEM THINKING AND THE MORE; DESIRABLE ASSESSMENT 1

0F CRITICAL FUNCTIONS.

i<

COMPENSATES FOR A REDUCTION IN DEDICATED DISP' LAYS T0-HE 0-OPERATORS MAINTAIN A " FEEL" 0F PLANT CONDITIONS.

o COMPENSATES FOR REDUCEDLSTAFFING BY HELPING OPERATORS.

MAINTAIN AN OVERVIEW 0F PLANT PERFORMANCE'WHILE BEING-

/

L INVOLVED IN DETAILED DIAGNOSTIC TASKS,

[

o

-l;

~

o PROVIDES A COMMON MENTAL VISUALIZATION OF!THE PLANT m

PROCESS TO FACILITATE BETTER COMMUNICATION AMONG ALL L

+

i

- - x -

.,4j

^

'~.

~

j

~

i' g

SFSC:Rx Trip

'CS t

g: Q PC SF

~

C1

- CH.

RH: ' CI-EG P

.T I

CEg.RE

.VA HR i-j

^ [S

+

3 newe 1234.

u

.a d n-L I

y g,

MM]

23 l,

f L I" n

b g

AA

[

Y 12 i

w n

cp- _rx..

i-4-

N D

g h

T4 AT 27 TR u

~.

DG

-r w

4 y

C J.

1 RC EF.

~

u

-I

- Mode:Rx Trip -

~

+

~

ff f.

CVCS $ g IR CCW SW g

gf t

'Rx P 95.11 SDC CWL

~

- 3 y f] _

~

rm --

...m w

. - ; ~

, __,,.l

,.____j____.__.

...._,a_.,

_ -, _ =.

.a...

,,.-._..,r.

.:_~;;_ L

~

e m,

y s!:

l/

4,j; l

- IPS01 VALIDATION-3

-1984-1986 1

.i HALDEN. REACTOR! PROJECT PWR SIMULATOR-

- REPORTS:

HWR-158 Y

HWR-184

. s.

"THE-FINDINGS OF THE~ TWO EXPERIENTS REINFORCE THE

. SUPPORT FOR A LARGEt SCREEN' PLANT OVERVIEW IN THE

. CONTROL ROOM.' -

r:

... HELPS OPERATORS': TIN THELDETECTION AND DIAGNOSIS OF PLANT DISTURBANCES....

s FACILITATED:A RAPID: IMPRESSION OF PLANT STATE, AND PROMOTED. LIVELY DISCUSSION BETWEEN CREW' MEMBERS'."-

}

4

,--w.

e.

e,,

.-.v..-..%-r-

,w.-.

v.4,.

..er,

.~-,, w

,-*--,,,-ew.,+,er,-w--y-w,wy+,

.,ww..,.,wy,5

l

' ~ ~.,.

x i

1

~

ALARM AND DISPLAY HIERARCHY x

J a

--9

- IPSO.

q l

e.

\\ DATA i

TRANSMISSION -

m L

DIAS..

F.-

- DPS -

t 5

i aurauw ii l

~

+

m w

l-

~

I r.L ;.. i.

cn;;.. _.l. <..

a a, ;,_... __,_;.,..

1..-

-. ~

,.z,-_ _ _... _. -

y

,s 4

j-a-

,O INFORMATI0H FROM' DISCRETE INDICATION AND' ALARM SYSTEM 4

k N4IM M'$V$M mi l g M

azy a...

1

ee.nsi as,

'Eir ag.:-

~.

tt:::::n.

m l

'f, c x;a

  • p a

+

Bs

  • W a..""

)

mee an..

8 '

G<

6 M

25 5 -

. 6-i

---+. --e

=

4

  • -1::..

"1 "4".

- S' k"" t.. '$-

".(

  • = -

[. '[=.

e 00 J

l

.1-

~!-

.s,,_

wm CW. n:t h"a r'aserts7 r e

f,'

I i

~$

.,. g m

= = -

.,f 1-p.Y

!i

\\

g a

n-g 4 h

$ h' y

\\

l f

t

=

'~

c. _

I.* ** l' -

i e:

I-I.,

[

f n

\\;

39 l

l

'.--C-

,) : ~.

7.

,y.-

}

, -., -..., _, _ _ - - _ = - _ _ - -

e=--':----=r---^- - - - ^ - ^ ^ ^

  • w

-;,,_..--.,l~c

~4A

  • O ~
  • O-

"~

'~

'^

n

er

_ INTEGRATED BEFORRRATION PlWESENTM80ss

NUPLEX 80+

J INTEGRATED PROCESS-STATUS-OVERVIEW

~

f CRTD8 SPLAY '

o wrS

/ /

N

=

j PasmAny

/

\\

c

.ScR m c

' ' ~ ~

j

1

[=

mancaToas g

ace coes u.

e ~e e ~e e ~e $

s

/ I\\/IN MECH.ll SYSTEM I l

l l

l l

l l

l l

RCP RCP RCP CHAR-MAKE I CONTROLS l l

l l

l l

l l

l l

000 SEALS GING UP.l e

.e

.s.~

- _ _ ~-

--.v n

nn

-,, A

..,s-.

- s

'. '-r,..'

- sa-m, l-

-~d*

w-so--.--

n

+--~r..a

.-----n._-

s.-a-

-s~

~~.--,------u-,

,'y.

SLIDE 127. DOC 36

+

NUPIFX 80+ ALARM SYSTEM-c L

i.

o.

~ SPATIALLY; DEDICATED TILES ARRANGED BY SYSTfM, 1

I

~

FUNCTION, PRIORITY l

c 0-GROUPED ALARMS WITH-DYNAMIC MESSAGE DISPLAYS FOR l}

[

SPECIFIC.CONDITIONSt i

'o M0MENTARY AUDIBLE-TONES,.WITH: PERIODIC AUDIBLET r

+

h REMINDER FOR UNACKNOWLEDGED CONDITION l

L i

l

'o' NO' GLOBAL'ACKNOWLEDGEMENTL ALL ALARMS MUST-BE' l

L

' RECOGNIZED BY OPERATOR-l

.i o

MODE DEPENDENT: LOGIC AND SETPOINTS, WITH' SIGNAL.

i l

. VALIDATION TO' MINIMIZE-ALARMS L

j L

o.

'STOP FLASH AND RESUME FOR INSTANCES OF HIGH ALARM

[

DENSITY i

LL O

ALARMS ALSO DISPLAYED ON CRT INFORMATION DISPLAYS AND i

VARIOUS ALARM LISTINGS y

-i o

ACKNOWLEDGEMENT ON TILE OR CRT WITH CONSISTENT TILE REPRESENTATION-o EASY ACCESS TO APPROPRIATE CRT INFORMATION o

A THREE-LEVEL PRIORITY ALARM' SYSTEM N

O PRIORITY 1 ALARMS HIGHLIGHTED-0N IPS0 NUPLEX80+

j A

~~

_l y

r RCP IA,s i RCP' IB,i n RCP 2A ii RCP ~28:,i r--------

r------- ar--------

1 i

j

' __SE AL______Jt__ SEAL _ _ _ _ _ _ --' '

J u _ _S E A L J t _ _LS E A L. J

1 t

r RCP IA,.ii r RCP IBl,i r RCP. 2A,i i RCP 28,i L

r--------

E i

LCooLtygj LCooLlegj LCqoLLygj LCooLtygj

~

r R C P. I A,i n i-RCP

, r RCP 2 A, i" RCP 2B E,i i---------

IB iil i

PP/MTR'L' RCP/MTR lPP/MTR J LLPP/MTR '

e i

L J

_I L J

. i R C P I A....i LRCP IB!

i R C P ' 2 A i i L R C P J ' 2 B. i y

o i

i

! SEAL /olLi SEAL / OIL iSEAL/oILi:! SEAL / OIL!

. l

~

ALARM CLEAR RCP~ 115 SEAL 1 *2 INLET PRESSi HI ~

_ - RC-P-162 4

F LIST I

~'

e 4

j

-s

.RCP ALARM TlLES: (DEECO)-

- 1, g

s t

i l

'=.

E

~

' CALMA YILE3 '

i

~

^

~

c

. ~.-

~

e--

em l

TILE STATUS ALARM DESCRIPTION

~~

~

POINT 10 o

o RCP IB-RCP.18 SEAL el' INLET. PRESS LO.

RC-P-161

~

i.

o RCP e-Seat.*z inter press si RC-e-isz SEAL /01L RCP 2 SEAL.*3. INLET PRESS - HI-

- RC-P-163

~ RCP - lB PP BRG OIL ~ RSVR : LVL LO RC-L-il7 '

~

-RCP' IS MTR LWR LOIL RSVR LVLTHl:

RC-L-IIB-l RCP IB MTR LWR.' OIL) RSVR LVL LO -

RC-L-II8~

RCP :.18 MTR UPR ' OIL. RSVR'~ LVL T HI L RC-L-II9 RCP. IB MTR' UPR OILT RSVR LVL LOT

' RC-L-II9 O RCP 18 : OIL LIFT TANK - LVL+ P' RC-L-14t :

RCP 18 OIL-LIFT TANK LVL LO.

' RC-L-144.

l RCP IB Oll' LIFT: PUMP: FLOW LO RC--Y-FRCPB l

RCP ' IB : OIL. LIFT PUMP OUTJ PRESS LO RC-Y-PRCPIB i

Y Vnd A'A LIST

. CLEAR i.

l

.R C P IB S E A L / O IL.

ALARMi: STATUS PAGE

c CALMA FILE
-

'.;,..,.--_,,x,,

x

~

,2___

( '

~

asTEGRATED BEFORRAATIODG PRESEBmmoes NUPLEX 80+

i 186TEGRATED

~

\\

PROCESS-t

" STATUS OVERVIEW

.. g CRT OISPLK ALARM TILES

$p

+-

PAGES

[g emasany 9

F?~ %

FL-L FL W n

f

~

~

~

]

\\

a.

m a.

~

L DISCRETE gw f

p

-l BNUECT

{

INDICATORS,,ig *

,,ig

,,ig

- RCP

~

CWCS 1

O __ra O'

s e

s L

1

/ :1 N. / IN SYSTEM l

l l

l l

l l

l l8EC88-llll OIL RCP

'ACP SICP CHAR-RSAKE

-CONTROLS,

l l

l l

l l

l l

[

SEALS GING UP.

l x

e' s

e

-. m.

.a m....

.~ - -. -... -.

y

.j g:

s 1

o_-.<

f'^

- NUPIsm 20+ DIRCRETE INDICATORS

./

1 1-L

' PROVIDE [CONTINU0US!DISPLAYLOFALLFREQUENTLYM

[

DATA.

v 1

L

-1 PROVIDE THE OPERATOR WITH THE H0ST ACCURATE VALIDATED-INFORMATION.:

1 p

o:

y 1

[

PROVIDE REDUCTION:0F. INDICATIONS THROUGN.AUT0; RANGING AND '

-i LSIGNAL VALIDATION TECHNIQUES.

p 7

i PROVIDE: REDUCTION 0FINDICATORSLCOMPAREDT0iCONVENTIONAL, W

CONTROL'R00NS THROUGN' OPERATOR SELECTABLE DISPLAYS.

y

}

PROV!DE. DIRECT ACCESS TO' RELATED CRT!PAGES.

7 PROVIDE ACCESS 70' PLANT DATA REQUIRED:FORf 0PERATION WIT THE PLANT COMPUTERr FUNCTIONALLYi!NDEPENDENT FROM PLANT j L

' COMPUTER. -

i H

muhh l

I'

_,._..,..._..,.m.r__....,...~....,....

,,,....mw,

,,._,.,4.,,

n

... ~

~...

a 4

s 1.,, -

l l..

i.:x si j

[

4 i

I j

t g

==

N 2~

w 5

13 o

a o

l J=

e

-1 1

i s=e s

Q

.j g

.g s

i 4

1 I

y

.se g

O o

O E

i

~

f

.h 1.

3 I

t..,>

=Q y.

. t i. ;

//

j M'

, k pipf unioin"pincot g$$yllp Il 4

a

[

i 4

L 5

=!

i f.

[

o 1,

l-m g

t

.e.

e ny 1

ll l

z y

-+J

'3

[

. O

.c o

N

.~

l I.

e o

1

-O

. =________ ____ __

7

. _ = #--_-

O u

[,.

lIllIlIlllllIIIII IIlllllllllll 3j a$

/*

t I '.

P t

i.

4 4i

-r g

r

-.-9--

e w

+

8ll_l

_f 7l l J

~

i R

I r

l I

g g -[

r

, 5 I

l 3

_A 1______!L__ I

.m 7,_,_,

o l1 A

8 p

[I TT li 5

e 1

8 r

l

  • A a

!jf ll lllll H

9 ii T T T _gll[rn A

]

gAA "I

T I -ll_e l

=

f

_e_

_ _4_ _J E

A ITT 1

i r

r

  • r

_h*IIki,

~

b O

"I 4

i1 1

9

' 11 9ll9 e

l PL e

J

f 1_. ~

.1 ui !

pa,

4 E

s l

L$

i 12 il m

t.>

x I

l,8 ll[t 8

[

Q i,',u

11) :' [i M

.{ @

n i

  • E g

dl, F

F III

~

l,(1:[.

l ll l

I 0

y y

a 3a 4 lE" N

{Q 6BEHE g

l C

=

a l l :

2 i

. d, s

1

.j

. i

-8 i

m

=

ec L

J a

1 1

YYYY

@EME i

'[

J 3

i I

j

_h_.

E l

d i

n 4

g

()

i a

e, gEMD E

u h

ll gEMa l<

.i p

a i

,j i Bam i

iI I

l i

l 1

'^

i us11EG5UMED BdFORWUMODE PIMESSETMBON NUPLEX 80+

i I

i 4

i 800TEGRATED i

L PROCESS STATUS

~

i i

,wass5 #

C'#ERVIEW g

ALARM l

t

~

+

CRT DISPLAW l

Tit.ES PAGES l

fg i

/

PRIMAMV i

i EM, I'-~%

FR.

l i

~

j c.

e.

c.

i DISCHETE J

J J

p SMECT u..

u ",.,

^

h M

~

j e ~s O ~e e

~~e {

s

/ I\\/lN 1

l SYSTEM I l

[

l l

l l

l l

l l RCP RCP l CHAR.

GAAKEI laMiCOLl[l RCP CONTROLS l l

l l

l l

l l

l l

l es.

SEALS Gnes up [

i l

l r

F f

ne

~s I

l

~

-. -. =.

...

---....w-

. ~..

m

[.

NUPIrX 90+'CRT DISPLAYS-CRT DISPLAYS' PROVIDE ACCESS TO ESSENTIALLY ALL PLANT l

INFORMATION FROM ANY LOCATION WITNIN CONTROL ROOM OR REMOTE LOCATIONS:

1 DYNAMIC COLOR GRAPHIC PLANT MINIC DISPLAYS, h

INCLUD!!!G IPS0 j

ALARMS AND OPERATOR. AID INFORMATION-1 PLANT COMPUTER CALCULATED INFORMATION:

r i

TRENDS AND REPORTS t

IMPLEMENTATION THROUGN NON-SAFETY PLANT COMPUTER DUPLICATES AND VERIFIES ALL DISCRETE ALARM AND DISPLAY SYSTEM PROCESSING AND IDENTIFIES SIGNIFICANT 1

DIFFERENCES.

l o

i t

gyggggg+ ---

I ll o

,,,,,,,,!..,,,-m

i s.ip, i

tily i,

s

)

gl a

ll h,.

x q

a 153-I g

l 3

1.E-I q

g

. sl.

1 j

l

\\

_c NN t (,

3 Ei l 4 4

a i

l I <

a 1

i e

s.

lj 1

-l

_,_..i

e e

t 3

s b

b 2

g y

.I I

l j

e g N_

7, l

8 i d

g i

y g.

1

g i v

/

E i

s' L

e-1 l

l k

lg,

"- 1 l

l L _ _J o

l l

L _ _.T bi

--]

\\

g w,

l__j L__j 2

g Ni C

g!

E5 ga 8

d-e

\\:

f m

e_

Si E

04

~

L e

1 l8 g

(.

~

1

(

jK q

(

<5 h fi E

3 E

G

)

x/

n x

i r f.

I W

sv M

'T'. -++

W 5

Ef

< g V8

[..

1 vb l

i V '.

( s.

4

- = = = -

4

+g.

4M i,

+.

5 Ag 48 w vW (5D is-r

+L L

J P

H i

<l r

i r

~

A

.. i r aa m a z.

,5 f

mm nu A

Q W.

$5 N

l f

l.j r

TYPICAL DISPLAY PAGE DIRECTORY

_,. -'i CRIT FUNCT MONITORMG

-l RC CH RH IC PC CI CE RE VA-SF EG -

HR-il

~

l ROD MAIN PZR CredT MAIN TURB Cl-l CNTL FEED q

N ST M CNTR COND {-

t f

j J

J l

i J

CVCS EMEG

' FEED CVCS Cl-2 STE w

CE RAD EMEATE MOS WATER 4

m OFF-SIS SDC SIS SI CCW dyR i

CET CVCS CNMT VITAL TJe 1

FM E

TURS g

RCS Cre4T VITAL mTL sib SPRAY PC

'TG i

I CLR E

B

- h3y

^

(TtQ oIR IPSO PRI SEC PWR ELEC A4JX CFM OTHR FIGURE 7

CRITICAL FUNCTION SECTION OF. THE" DISPLAY PAGE HIERARCHY

~.

CRITICAL FU N CTION MONITORING REACTIVITY CNTR INVENTORY CNTR PRESSURE CNTR STEAM / FEED CONV i

I J.

CORE HEAT REM RCS HEAT REM CNMT ISOLATION --

ELECTRIC GEN l SD-232 OPENl c

g, i-CNMT ENVIRON RAD EMISSIONS VITAL : AUX HEAT REJECTION l HI VENT STACK RAD l l

i l

i i

i OPER l

CLR ESTO MS' DIR Yg" ^$"7 IPSO PRI SEC PWR ELE AUX CFM OTHR

)

r q

FIGURE 8

1 st ' Level Critical Functin Displav Page

4

-es

~J e CRITICAL FU N CTIO N M O NITO RI N G 1

SAFETY FUNCTION f

REACTIVITY CNTR INVENTORY CNTR PRESSURE CNTR STATUS CKECK g

~

  • !??

LdCA CORE HEAT REM RCS HEAT REM CNMT ISOLATION SGTR ESDE lSD-232 OPEN]

i LOAF LOOP l

h l'

CNMT ENVIRON RAD EMISSIONS VITAL AUX sTATSON f

BLACKOUT i

l lHI VENT STACK RAD l r

FUNCTIONAL RECOVERY GUIDELINE 4

OPER CLR 4

csTe j

R P$cy DIR ^,[g" ^usT IPSO PRI SEC lPWR ELE AUX CFM OTHR FIGURE 9

Critical Function 1 st Level Display Page After A Reactor Trip e

-s e-w

+m.--

.x

.=m.2.. m..

w

~ -

JMY g

i

.g

'O m

O-L_

E IN

~~

au

[

g a

1 5

u

~

N I,,

c 4

O

.9 +

i

-e g.

.. J -

o n o

sin,;

(5 zE 5

6j o

O W C; o

in -

it E I Z

~

co e

3 4-I Og$0 g@r g

Oc OC

%d F

du (k(f a

p.

g-8

-1 i

zb o

o.

=

_i w

g w z-O k ) L)

N-h hy p-t L

z i.

1 s,

{

l Q.h m m Z

hf$

E

_O g-7 o

C < <

< d

.o wE b<

~l

.y a.

O 10 Q

b l

3 j

ar

$2.

Q Em

b. c.

d3 m

gW 3

r" !

't ad i

i n= x o. {>

a t

1 h.

a c..

U N

.J CL..

___L___1___.__________________.___________u____

L s

1 s

SPMS VALIDATION 4

1987-1988 HALDEN REACTOR PROJECT PWR SIMULATOR REPORTS: 'HWR-213 HWR-222 HWR-223 HWR-224 4

i

" SPEED AND ACCURACY OF OPERATOR PERFORMANCE IN "l

TAKING APPROPRIATE CORRECTIVE ACTION WAS. CLEARLY.

SUPERIOR WITH'THE SPMS.'

h

... RESULTS CLEARLY ILLuf#DATE QUITE DISTINCT o

ADVANTAGES..."

.l 4

a 1

i NUPLEX80+

t I.,

.. -... ~ _ _ _.. _,,. _ _ _.... _...

L O

i

.+

o W

E L.

I z

3 I~

- )

\\,\\((j

.g 1

r g-g pl g/

s w

/

d

[

3 m

p

>g l

% c.,

=2.,t :

Llg ig s

i I __7p s

.s d'

r l

-9 1

l 1

5-

~

f lg L

E l

0 s

l ll I

,1 ll Ej -Q

.-y u

i g

A e

N 5

.o l

l

' ' ~

'~

.-..-..-.y.-.....

L I: -

,p A.e.s,u s u~p s,--as

<4+-s+

-- a s s wnn#

s-

--n---sn=svs-m-a---w*-eva----


s

"-- - - - ---~

w - - - - -

- - ~ - - - ~ - - - - - - - - - -

p4

_N

.I u

L

+

l I (I*

I gl 5*

L s8 g g g.

D E

Y EEd

'\\

b$$

e g

/:

Yg N

b lil

~

g k-l',*?

>e i

a

~

f l

I 11 3g 7

~

J, s

Sumus y

2

(

11

/

p l

6 8

a I-s l\\'$ w lg l

s g

(

8 E-e I

I L

lt i Il a

s

<r i

0 3

b mn

)

l Or VV W yj _$f y

a M

is

)

f f(

g

[

g i

n

.4

.a f

Y j T, -

I \\

..._._>...,,i

7_.

7 ip.

L-i PRESSURI2ER PRESSURE s m w vmLvcs sarEn vaLws TEM" IDE I

a ik l 92* l-I l

o+-ass i

M i

a_

4 l --

SA W_

__gh imL e-sec-seeE E

a_

S_

I se Atasene

. sysises ac-seer suc-aea g,-

seiroswva i

stC-2e3 g

i it

---390.F N

Ms l

i u

acs i

e -.rn e

vzu raen tU-

- 296 F e

im-m e-+e**

.to.tu.

>go y r._._._._._.__

3031 esGee A 2250 A 2250 MN g

304-etGee 8 225e S.2250 SP So.GE seS *eGee C 2258 SET PT M g

'g CPEMATOR ESTasas ammeEO ses eesse O 2250 DeIL M

M 2258 SE N 1

Y-2250 i

{

e s

5 OPCH i

25 2

E ESTU aEE7 2'55 am

{

1 H8485

-m i

' 950 em 8

t CMcCEL ENTER 1-r see ramp j

geggs 1

?

LO FEEDWATER TEMP OUTLET HTH 12A 12:33:12 Fw-232 290/ '985 F OPE" ESTB CLR i

LASI iJii<. ALitM ALRM

. t>lel i-a

~-

. EC-PwR ELE AUX CFM PAiX 3

fW-1 TR E 1lst Gas es<

3 g.

.., s se e

.J J

g r

I W

Alant Guerlay 4 IM) %3y {gMggg.

,-__. _,.~

.m

-,,..v

.... - - - ~ -.... - -

, -,. ~... - ~. _.., -. _.,

...,., ~,....,, -......

a DPS VALVE CODING C0WB610NS Normal /

Abnormal Data Attributes Position Operability Status

.CcA11ty Alarm of

~~

Coding Fill Color Descriptor Asterisk-Solid-Closed Green-Operable Descriptor Present-

& Open Grey Nermal Suspect Data-Code-Physical Hollow-Open Red-Operable Descriptor Absent-

{

Meaning Map

& Closed Highlighted Good Data Yellow for Alarm-Abnormal Half Filled-Grey-Inoperable Throttled /

Intermediate i

.,.m

ms=

I 1

D4TEGRATED INFORIEATmB6 58RESEBETsnoes NUPLEX 80+

l i.

l 1

INTEGRATED p

PROCESS L

STATUS g

I ALARM CRT DeSPLAY !

T8LES PAGES r

N FReasA8sv i

Fi+--L.

PL IP--: L

~

c.

a.

l a.

DeSCRETE -

p SERECT

~

j..

d,.,

l M

(NCE e

e.

O ~e e ~e g s

fl\\/IN v

SYSTEM J l

l l

l l

l l

l l

lBECBL]l[l RCP ]

IRCP 8tCP CHAR.

SSAIE l

l CONTHOLS l l

l l

l l

l l

l l

l OE l SEALS GIBGE UP l

l I

,q I.

. SLIOE159.00C

.a-

.:.-.i a

t NUPLEX 80+

i M N-MCHINE INTERFACE FOR PROCESS-COMPONENT CONTDOL SYSTEM I

i i

g..

j r

i piiEran~samuss ammans amn 6

4*.~.~

w j-W

~~ a:.? -

[

se e

{

f T

i g;;lg;;3 -=

j m

A

+m a

Il

_ _ -.I ClO

._g l 6 p.

r_,

r_,

l

~*

. ::.=2.

-~*-

(

)

I 3

oo nn h

r 1

i

'..,,,__-n_.. _ _ _ _.

W3 j

U,_ _,. _ _._.,

=

L E-U B-E DM H-M -If

~g g

.g g. -g

?

i e

I i

!L E

E'

.R H -5

/

n n

n m

= = = a- -arwas-L s.

r 1 1

l l

\\ l /,//

l

/

~

- OIE,

M SS M IFR SMITCNES

.~

I i

3 e

l~,._ s,

-;.....;-,-,--...--.-..a..

-..-6..-

- ~

-'b u

i i.

o i

i i

I NUPtFX 80+'- PROCFES CONTRCLlFRS 1

I 1

CONTROLS ARE SEPARATED FROM DISPLAYS TO ENSURE o

I DELIBERATE OPERATOR ACTIONS j

.,l i

o e

o CONTROLS ARE GROUPED BY FUNCTIONAL TASKS

)

j CONTROLS PROVIDE CONTINUOUS DISPLAY OF ALL PA o

j BEING CONTROLLED l

PROCESS CONTROLLERS ALLOW EASY ACCESS T0. SE o

CONTROLS FOR EACH PARAMETER' 4i ~

' l

. s AfUSLffff+

4 l

Sh

=

1 PROCESS COIITROLIER DISPIAY PAGE SWOtf180G MASTER SETPOINT SELECTICII-1 1

PRESSURZER LEVEL CONTROL l

~

I LEVEL l

l CHARGING l[

LETDOWN l

i 1

Semi-54.0%

55.0%

AUTO ime.,

AUTO aAANUAL l

.r a

+5

+20

+20 i

soo i.

l 55.0% l O2 GPa8 80 GPas j

i I va's I r-aiz -

F-zaz A,

1

~

=

i o,.

50.0%

l 40.0% l.

^

G louTeuil j

-S

~

~

O i

I CLEAR E

.i

(

l 6 -+tWR T-0 -k9 -*!6

+,

4

,h r

. ~

,.w-

~~.rn-.

~.. -.. -,... -.. _.

9 O

t 1

g g

Ti F 77 gIL B E l,

1..' di E

Bi i$

g 1

n_

8 a

' l

_1 y e

3 ll

}

$5 L_

hk "3

l e,..,....,,

i 4

j se tre

5 b

i g.

+

c 1

E I

Ii i !! !DE li!

t j

j g g

6' i$

L.ljl 11 o o

1 3

g llg.

m W

g v

d i

I I I I I

I I 1.

=l gg O.

s

,7 yi....I

-k

)

w

W;-

i i

t

~

,8 l

e1.:.nd 5

g i

"J 3 r l

P D

ll

~

L i

l!

I l

.1 MM o

g Q h

Y

$ b g

)

4 4

.e

h l

4 q=

0 a

i 4

bu j

m i

l.

3 hl i

~

g k

l-

&.1 1' 5

i I

l.

~

%l r*

.lV :

i i

L-------_-----____

_________J COWuu

=

SECONO LEVEL CAf tt -

(Otta

=-

00cuutut T5C 9 VIEWING STORASE GALLERY SECum a

(0108

~

DESN I[

M QT

=

~

c ggg (A4)

/

CAS CONSOLE mn (A38 DER oggg "l @

C00 LINS 1

inu WATER (A23 PNYC=

n a

=

,S

=

N.

a u

FD WTR CONotNSAT CVCS

=

6 (W4).

PLA T (W2) 3 WONITORIN8 AND CONTROL l

IPSO l

CALMA FILtr t.TAlWAN#101 WR

v.

SAFETY MONITOTING PANEL-

~

j

. r q

i N

nLARM nLaRM CRT ntnnM nLaves enn i

1WWOOW MnTHIX MRTRIX i

1 adR1 HEX edRTRIX WDE105 I

i l

l y. _a I

I DIAS-P OIAS-P CCS

-CCS 1

2 ESF X

Y~

STATUS MONI.T. O.-f t.,

I it..

CCS IWUIATION

'CCS 1:t:S i

s's I

MONITOR B

C 11 i

CPC.

CPC CPC

- ClC A

B C-p l

PPS PPS j

PPS 11xi A

B C

>O.

y Rx TRIP.

y IlxTRIP' MODULE MOOLA _E-FIGURE 18.7A-5 SAFETY MONITORING PANEL LAYOUT L

Cntaan FILE

  • SYSa[FIGIG795 b

e y9..

r

'F'

~"""h

W

'F

  • W" Y

' ' " " * ' ~ " ' " * '

  • 9"
  • "U"'W

'~ ' ' ' '~*

V'*

          • 'N*
  • r

--*"I"'"*'

I l

s k

l l

DIS PLAY HIERARCHY s

[.

t Y

STATUS 4'

.//

f.

s'./

i

/,/

\\

//

r

/,/

/

/

./

/

j e

2 17

-l RPS-1 BIAS /

MSIS/

EFAS-y wwf l

l VOP-HH CT F CIAS

. CSAS EFAS-2 N

I-RPS-2 4

O 0

4 e

s T

_... _.... ~, -.......,

4

.a

.~

~

l s

8 l

r PPS STATOS.

CHANNEL A

\\

l j-

}

TRIP PARAMETER INmATION/ ACTUATION '

PARAME1ER lPlT CO 08 PARAMETER P

T CE OB i

I VOP SYSTEM w

ll' l LO sc1 PRESl i

lHi LOG PWRll l LO SC2 PRES l RPSl1

~i L

l LO DNBR ll l

l Hi CT PRES 1 SIAS

-l I

~

l HlLPD ll.l LO RC1 FLOW CIAS i

lHi PZR PRES ll l LO RC2 FLOW l CSASi l

lLO PZR PRES l h-M CT PRE 5l i

i m

lto.soi LVtl km to M1 Ld Msist l

y lLOSG2LVLll.-l kNLoM2LQ j

EFAS-1 I Hi SG1 LVL ll l

N -2 l Hl_l SG2 ~ LVL lll.

l

{

b

~

I i.

~ ~.

=

i q

t I

l:

l 8

q l

(

t PPS LO PZR PRESS CHANNEL A-l-

BISTABLE STATUS

- SETPOINT RESET l

I

~

[

ALARM SETPOONT INPUT MARGsN i

r i-PRr-Tmp igg psga O PSm RESET

(

1800 PSm

]

MP.

i700 psgA.

3og psm j

i

- TRIP CHANNEL BYPASS OPERATING BYPASS STATUS INSERTION a

t (BYPASSED)_

. s,mS8,g LCL 8NPUT-i 1-

^

r

=

==

==

==

a

'I on I 1

A

- 9 C

D A

a C

N SYPA

~

i

=

i lOFFl 3

%.L i

i.

?-

7

=

_ _ _ _ - _ _ _ _. _ _ _ _ _ _ _ _+..,.,Me,w

---a

+-w.,----e,[

cw ~ E -

e-~,

2

...,.+e.,

...n-w

-w.-c=..s#-..-e,,~

r,w_.-.,c

+

.I..E....,.......rde,-

...s~~~-..

--u.

a.,

-e m.

1.

1 o

S SIAS INITIKilON ACTUATION TRIP INPUT c ace /o us.

A B

C D

LCL AA AB AC AD PARAMETER T

B T

B T

B T

B LO PZR PRES A Tame Hi-HI CT PRES CIAS INITIATION ACTUATION N'c E c s/n un A^ ^B AC AO' A Tame s.

e L

N

..g

,