ML20043A373
| 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
- 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!
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
- 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
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
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
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
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
. ASS CID ID LE!
S SI AMO DN N
I ll l
l l9 l
& E'Y E
E GA T0 T
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
\\
- 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
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
^ [S
+
3 newe 1234.
u
.a d n-L I
y g,
MM]
23 l,
f L I" n
b g
[
Y 12 i
w n
cp- _rx..
i-4-
N D
g h
T4 AT 27 TR u
~.
-r w
- 4 y
C J.
1 RC EF.
~
u
-I
- Mode:Rx Trip -
~
+
~
ff f.
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.
- 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 :
' 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
m OFF-SIS SDC SIS SI CCW dyR i
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
=
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 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
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
,