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Summary of 900520 & 21 Meetings w/C-E in Windsor,Ct to Discuss Instrumentation & Control for Sys 80+.List of Attendees & Meeting Agenda Encl
	ML20055E519
Person / Time
Site:	05000470
Issue date:	06/29/1990
From:	Singh R; Office of Nuclear Reactor Regulation
To:	; Office of Nuclear Reactor Regulation
References
	PROJECT-675A NUDOCS 9007120091
	Download: ML20055E519 (133)
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.. Project No '675 '

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l FACILITY:- CESSAR System 80+

APPLICANT: . Combustion Engineering, .Inc. ~ (CE)

SUBJECT:

SUMMARY

OF MEETING WITH CE ON SYSTEM 80+ 4 ,

On May.2O and 21, 1990 r the NRR staff and contractors met with; representatives

, Lof CE at their offices _in Windsor, Connecticut to discuss the instrumentation and ' control for System 80+'. Enclosure 1 lists the meeting participants.

Enclosure 2 provides the meeting. agenda..

Following a_brief overview of. System 80+, CE presented the design bases:and- ,'

t cdescription of NuplexL80+ Advanced Control Complex and related systems,i and hardware and software qualification. The presentations included a: mock-upt live. demonstration of Nuplex 80+. Copies of the presentation slides used by J >

CE are provided in Enclosure 3.

'Overall," tt was _a productive meeting. The staff obtained-a better understanding

,of; System 80+- 1 istrumentation and control which will be helpful in the- review . ,

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of CESSAR-DC. During the meeting, CE agreed.to make the 13 volumes of_Nuplex 80+-

.: reference design documentation available to support the staff's ongoing review..

. % The' reference documentation is now available at CE'sNRockv111e offices.

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f) Rab indra:N. S4ngh, . Project Manager l [.

? ' Standard 1zation Project' Directorate

? Division of Reactor Projects - III, ~

J IV, V and Special:Projectsi zfa.a ,

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. m 9007120091 900629 PDR ADOCK 05000470 '?

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p 1,; .1 June ~29,'1990-Project No. 675-FACILITY:- .CES'SAR System 80+

APPLICANT: . CombustionEngineering,Inc.(CE) j

SUBJECT:

SUMMARY

OF MEETING WITH CE ON SYSTEM 80+

i On~May 20 Land 21- 1990, the NRR staff and contractors met with representatives' M of CE'at their offices in Windsor, Connecticut to discuss the instrumentation- !

.and control for System 80+. Enclosure 1 lists the meeting participants. 1 Enclosure 2 provides the meeting agenda. l Following a brief overview of System 80+, CE presented the design bases and -

description of- Nuplex 80+ Advanced Control Complex and= related systems, and-hardware and software qualification. The presentations included a mock-up _

live demonstration of Nuplex 80+. Copies of the presentation slides used by CE are provided in Enclosure 3' .

0verall, it was a productive meeting. The-staff obtained a better understanding--

of System 80+ instrumentation ~and control which will be helpful in the review. ,

of CESSAR-DC. During the meeting, CE agreed to make the 13 volumes of Huplex 80+

reference design docurentation available to support-the staff's' ongoing review. l The refererce docu m . ation is now available at CE's Rockville offices. !

Isl

.Rabinclra N. Singh, Project Manager- o Standardization Project Directorate: ,:

Division of Reactor Projects III, j

', IV,~V and Special Projects -j i

Enclosures:

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cc w/ enclosures:

See next page ;

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.MAY'20 and 21, 1990' x 1. ,- . g

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K.:Scarola- ,

J.-Joyce. D. Harmon'

- .M.' Waterman; ' G. Altenhein

P.'Eshleman_(Contractor) ~ S. Wilkosz R.~ Ets'-(Contractor) - R. Manazir

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MAY 20 AND 21, 1990: N n

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1:00 p.m. - 1:15:p;m; ; System 80+ Overview S. Ritterbusch, !

~1:15 p.m. ;2:45 p.m. NUPLEX 60+ Overview K. Scarola' .

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SAFETY ANALYSES-PRA'AND SEVERE ACCIDENT RESULTS L SEISMIC METHODS BUILDING LAYOUTS DECEMBER 1990 -

SEISMIC RESULTS' TECHNICAL SPECIFICATIONS:

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SLIDE 127. DOC 6 h0PtFX 80+'DETA11FD DESIGN

-.i NUPLEX 80+ IS-BEING APPLIED TO THE FOLLOWING PROGRAMS:-

EACH IS CONTRIBUTING TO THE DETAILED DESIGN: .

y o ADVANCED CONTROL COMPLEX FOR SYSTEN 80+ (EVOLUTIONARY ALWR)'- DOCUMENTATION HAS BEEN SUBMITTED TO THE U.S.

NRC (CESSAR-DC) FOR DESIGN CERTIFICATION.

o ADVANCED CONTROL COMPLEX FOR THE SAFE INTEGRAL- .

REACTOR o ADVANCED-CONTROL COMPLEX FOR MHTGR - NEW PRODUCTION REarinR o ADVANCED CONTROL COMPLEX FOR.EHWR:- NEW PRODUCTION REACTOR o- APPLICATION OF NUPLEX 80+ TECHNOLOGY TO SELECTED SYSTEMS FOR YGN 384 yypggggg+

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SLIDE 127. DOC 10' I:

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i NUP1FX 80+ DESIGN BASIS DEVELOPMENT l

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[ o THE NUPLEX 80+ DESIGN BASIS WAS ESTABLISHED THROUGH REQUIREMENTS ORIGINATING FROM:

CUSTOMERS - NUCLEAR POWER PLANT OWNERS AND OPERATORS ,

REGULATORS - U.S. NRC, DOE INDUSTRY - EPRI, INPO, IEEE l C-E EXPERIENCE - PAST PLANTS 0 THE NUPLEX 80+ DESIGN REPRESENTS A CAREFULLY EXECUTED' '

TECHNOLOGY EVOLUTION FROM NUPLEX 80 i

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SLIDE 156. DOC - 4 NUPLEX 80+ DESIGN RASES

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I 1. EET ALL CURRENT REGULATORY AND INDUSTRY REQUIREMENTS FOR INSTRUMENTATION AND CONTROLS: ,

p POST-TMI ACT10N PLAN l' -

HUMAN FACTORS ENGINEERING l

FIRE PROTECTION AND SAB0TAGE VERIFICATION AND VALIDATION .

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2. TO IMPROVE PLANT SAFETY:

DIGITAL PROTECTION SYSTEMS WITH CONTINU0US '

AUTOMATIC TESTING FOUR TRAIN ESFAS IMPROVED MAN-MACHINE INTERFACE

3. TO IMPROVE PLANT AVAILABILITY:

FAULT TOLERANT CONTROL SYSTEMS PRE-TRIP CONTROL ACTIONS POWER DEPENDENT PROTECTION LIMITS ,

IMPROVED MAN-MACHINE INTERFACE

4. 'T0 lMPROVE THE COST EFFECTIVENESS OF NUCLEAR PO S GENERATION:

LOWER CONSTRUCTION COSTS SHORTER DESIGN AND CONSTRUCTION SCHEDULES LOWER OPERAT10N AND MAINTENANCE C0STS gypggxff+

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NUPLEX 80+ SAFETY IWROVEENTs 1 1

0 PLANT PROTECTION SYSTEM PROVIDES CONTINUOUS SOFTWARE EXECUTION TO VERIFY TRIP LOGIC FUNCTIONALITY )

o DPS PROVIDES COMPUTER ASSISTED LOGGING AND VERIFICATION FOR PERIODIC COMPONENT SURVEILLANCE TESTS l

0 PLANT PRCTECTION SYSTEM PROVIDES EVENT BASED SEGMENTATION WITHIN EACH CHANNEL 1 I

o DIESEL LOADING SEQUENCER ADAPTS TO PLANT EVENTS TO.

MININIZE SEQUENCING TIE o PLANT PROTECTION SYSTEM INITIATES PRE-TRIP CONiROL :

ACTIONS SUCH AS RPC ,

o MEGAWATT DEMAND SETTER KEEPS PLANT WITHIN ,

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o ESTABLISH A IRR_TIDISCIPLINARY DESIGII AIS IIIDEPEWENT itEVIEW TEAN HF SPECIALIST REACTOR OPERATORS X IIUCLEAR SYSTEM ENGIKERS INSTRINEllT AIS CollTHOLS EIIGIIEERS o PERF0llM TOP DOWII IIEIEPElWENT SYSTEM AIIALYSIS

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l' NUPLEX 80+ INFORMATION DESIGN BASIS-p

1. CRITICAL' FUNCTIONS PLANT SAFETY AND POWER PRODUCTION CAN M M MAINTAINED BY CONTROLLING A MINIMUM SET OF i CRITICAL FUNCTIONS e

2. SUCCESS PATHS THE POTENTIAL TO ADEQUATELY CONTROL A CRITICAL

[' , FUNCTION IS MAXlM12ED BY KNOWING THE PERFORMANCE l

'0VALITY OF NORMALLY OPERATING PLANT SYSTEMS, THE STATE OF READINESS OF EMERGENCY SYSTEMS, AND THE-

,- PERFORMANCE QUALITY 0F EMERGENCY SYSTEMS WHEN i- THEIR OPERATION 15 REQUIRED L

L

3. INFORMATION QUALITY tl THE 00ALITY OF OPERATOR DECISIONS AND'0PERATOR- ,)

RESPONSE TIME ARE ENHANCED BY KNOWING THE VALIDITY l 0F THE DATA PRESENTED.- l l 4. INFORMATION PRIORITIZATION-INFORMATION OVERLOAD IS MINIM 12ED BY PRIORITIZING INFORMATION, THEREBY ALLOWING AN OPERATOR TO BETTER FOCUS HIS ATTENTION ;

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i IPS0 VALIDATION 1984-1986 I i

HALDEN REACTOR PROJECT PWR SIMULATOR j d

,,q REPORTS: HWR-158 l HWR-184 1 i

"THE FINDINGS OF THE TWO EXPERIENTS REINFORCE THE :

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. . . HELPS OPERATORS IN THE DETECTION AND 1 DIAGNOSIS OF PLANT DISTURBANCES. . .

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, . . \

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SPMS VALIDATION !

1987-1988- l l

HALDEN REACTOR PROJECT PWR SIMULATOR

~

9 REPORTS:' HWR-213 )

I HWR-222 HWR-223

,., HWR-224 1 e -

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" SPEED AND ACCURACY OF OPERATOR PERFORMANCE IN i TAKING APPROPRIATE CORRECTIVE ACTION WAS CLEARLY d SUPERIOR WITH THE SPMS. :

. . . RESULTS CLEARLY ILLUSTRATE QUITE DISTINCT ADVANTAGES . ." -

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( h NUPLEX 80+ - EPRI ALWR COMPLIANCE l W -

NUPLEX 80+ MEETS THE CURRENT EPRI ALWR REQUIRDENTS, WITH SOME EXCEPTIONS: !

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o ALL I4C RECONFIGURABLE RECONFIGURATION FOR FAILURES * ..

GN FAILURES NOT ACCo m 0 DATED ELSEWHERE I

o THREE FULL CAPABILITY CONTROL PANELS WITH SPATIALLY COMPACT WORKSTATIONS DEDICATED INFORMATION AND CONTROLS o BACK-UP GUALIFIED NO BACK-UP REQUIRED CONTROL PANEL l 1

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SLIDE 077 NUPLEX 80+

l EPRI KEY ISSUES - DIVERSITY ,

L o PRESENT PLANTS EXHIBIT SIGNIFICANT INHERENT :

DIVERSITY DUE TO MULTIPLE SUPPLIERS OF 18C SYSTEMS l 0 ALTHOUGH UNPLANNED, THIS DEFENSE IN DEPTH HAS BEEN l IMPORTANT TO THE SAFETY RECORD =OF THE NUCLEAR INDUSTRY AND THE AVAILABILITY OF C-E PLANTS i

O DIVERSITY BECOMES EVEN MORE IMPORTANT AS THE COMPLEXITY OF SYSTEM INCREASES AND EXPERIENCE WITH THE TECHNOLOGY IS LOW t

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o DIVERSITY WAS A KEY FACTOR IN THE LICENSABILITY OF C-E'S DIGITAL PROTECTION SYSTEM o QA IN DESIGN AND OPERATION IS' CONSIDERED FUNDAMENTAL IN ACHIEVING SYSTEM RELIABILITY, BUT IS NOT AN ADEQUATE SUBSTITUTE FOR DEFENSE IN DEPTH .

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NilPIFX 80+ DIVERSITJ.

o NUPLEX 80+ MAXIMIZES STANDARDIZATION WHILE MAINTAINING DIVERSITY IN KEY AREAS TO ENSURE THAT THE DEFENSE IN-DEPTH CONCEPT IS NOT COMPROMISED o NUPLEX 80+ DIVERSITY:

FUNCTION DESIGN TYPE 1 DESIGN TYPE 2 l- i REACTOR TRIP PLANT ALTERNATE l PROTECTION REACTOR TRIP l

SYSTEM WITHIN PROCESS-CCS .

FLUID SYSTEM EMERGENCY NORMAL CONTROLS SUCCESS PATHS SUCCESS PATHS (E.G., (E.G., MAIN EMERGENCY FEEDWATER) VIA FEEDWATER) VIA PROCESS-CCS ,

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REDUNDANT IE HVAC ELECTRICAL AND HVAC REDUNDANT IE HVAC e TECHNICAL SUPPORT C1411k ;

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CHANNEL A EQUIPMENT ROOM NON-1E EQUIPM NT ROOM !

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a, NUPLEX 80+ DATA C0mVNICATION DESIGN BASIS 0 MULTIPLEXING IS USED WHERE COST EFFECTIVE IN SAFETY AND NON-SAFETY APPLICATIONS.

O NO MULTIPLEXING INSIDE CONTAINENT.

O MULTI-DROP RETWORK TYPE COMUNICATIONS IS UTILIZED WITHIN SYSTEM BOUNDARIES ONLY.

O SYSTEM TO SYSTEM COMMUNICATIONS ARE HARDWIRED OR DATA LINKED POINT TO POINT.

O FIBER OPTIC INTERFACES-ARE USED WHERE ISOLATION IS REQUIRED (A, B, C, D, X, Y, MCP, RSP).

O CONTROL, PROTECTION AND PAM SYSTEMS RECEIVE FIELD DATA.DIRECTLY. DIAS AND DPS RECEIVE FIELD DATA FROM OTHER SYSTEMS.

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,,,,,, Data Link Optical (Fiber Optic Cond)
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E , ;, ; SLIDE 127. DOC 49'
-i '
l NUPtfX 80+ SOFTWARE QUALIFICATION y
i <
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, 'o- VERIFICATION AND VALIDATION OF USER DEVELOPED ,
1 APPLICATIONS SOFTWARE IN ACCORDANCE WITH:
-ANSI /IEEE - ANS!- 7.4.3.2 R REGULATORY GUIDE 1.152 l 1
l 1
L o HIGH-LEVEL LANGUAGES ARE USED TO THE MAXIMUM EXTENT PRACTICAL:
j 1 .
,C' l LADDER LOGIC i l '.
0- COMPILERS AND MACHINE OPERATING. SYSTEMS ARE 0UAL'IFIED-BASED ON PRIOR FIELD 0PERATING EXPERIENCE AND V8V AT THE APPLICATIONS LEVEL-
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o SOFTWARE REQUIREMENTS DOCUMENTATION IS WRITTEN,: THEN !
VERIFIED THROUGH INDEPENDENT REVIEW. t
+
.O STANDARD-SOFTWARE' MODULES ARE WRITTEN AND DEBUGGED USING.
DEVELOPMENT SYSTEM' EQUIPMENT. YFRIFICATION:IS THROUGH INDEPENDENT REVIEW 0F CODE FOR E6 d MODULE. '
i o STANDARD SOFTWARE MODULES ARE INTEGRATED AND DEBUGGED USING
. DEVELOPMENT SYSTEM.
o UPON COMPLETION, STANDARD SOFTWARE CAN BE SHIPPED TO THE' ,
SITE TO-PERMIT EARLY FUNCTIONAL VERIFICATION OF INSTALLED -
HARDWARE.
! 1 o FINAL SOFTWARE MODULES ARE WRITTEN,. INTEGRATED AND DEBUGGED u WITH INDEPENDENT VaV AS BEFORE. INTEGRATED-TESTING-IS =
m PERFORMED USING DEVELOPMENT SYSTEM OR DELIVERABLE HARDWARE.
IF--AVAILABLE.
l' 1 0: AT SITE,-QUALIFIED SOFTWARE-IS-LOADED IN INSTALLED EQUIPMENT :
AND FINAL-ACCEPTANCE TESTING IS PERFORMED.
I o ' REVISION LEVELS OF APPLICATION SOFTWARE, OPERATING SYSTEM SOFTWARE AND HARDWARE ARE CONTROLLED THROUGHOUT-THE' LIFE OF.
THE EQUIPMENT THROUGH STRICT CONFIGURATION: CONTROLS. 1 l
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( QUALIFICATION STANDARDS 1
Li HARDWARE
\
IEEE-323-1983 --
IEEE STANDARD FOR QUALIFYING CLASS'1Ei EQUIPMENT ~FOR NUCLEAR POWER GENERATING -
STATIONS a
1
- IEEE-344-1987 -
RECO N NDED PRACTICES FOR SEISMIC .
QUALIFICATION OF CLASS 1E EQUIPMENT- .l l
FOR NUCLEAR POWER GENERATING j STATIONS' IEEE-472-1974 -
GUIDE FOR SURGE WITHSTAND-CAPABILITY FOR TESTS IEC-801- -
ELECTRICAL MAGNETIC COMPATIBILITY FOR INDUSTRIAL' PROCESS MEASUREMENT' ;
4
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ELECTROMAGNETIC EMISSION AND A SUSCEPTIBILITY REQUIREMENTS-FOR.THE 4
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i o A REPRESENTATIVE DESIGN IS BUILT USING ALL HARDWARE MODULES.
L.
l 0- PERFORMANCE TEST-SOFlyARE IS LOADED- AND HARDWARE SEISMIC l TEST IS PERFORMED.
I m
o- ALL IN-SERVICE HARDWARE CONFIGURATIONS ARE ANALYZED USING. 3 L < SEISMIC TEST RESULTS. !
-it'-
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o ' EQUIPMENT MANUFACTURER'S SPECIFICATIONS AND: TEST DATA ARE-
' ANALYZED FOR QUALIFICATION:IN:0THER AREAS'(I.E.,.
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TESTING IS PERFORMED, IF REQUIRED
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Definitions '
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MIBE I a
In' general terms, the Assembly or System failure rate is the summation of the l individual failure rates of'all the independent elements of the Assembly or- 'l System. The MTBF is the reciprocal of the.fallure rate, j M
in general terms, The Mean Time To Repair is the total Assembly or System -
W. repair time divided by the total number of failures.
Availabilitv I q
Availability = MTBF / (MTBF + MTTR) X 100 in E ,
i Unavailability = 1 A'vailability. !
' System Calculations . a.
Generally, all systems are reduced to simple: series or parallel elements and -
computations then performed. If circumstances warrant, special consideration ..
can be.given to any system configuration. The following approaches, however, {
are the general case.
Series Elements Series Availability (As) = (A1) (A2) (A3)......(An).
MTBF = 1/(1/MTBF1 + 1/MTBF2.+ + + 1/MTBFn).
MTTR = MTBF (1 As)/As, b, * .
Parallel Elements !
Unavailability = 1 Availability.
l Parallet Unavailability (Up) = (U1)-(U2) (U3) ....... (Un). .
, Parallel Availability (Ap)~= 1 Up.
p-J MTTR = 1/(1/MTTR1 + 1/MTTR2 + + + .1/MTTRn).
~'
MTBF = MTTR(Ap)/(1 Ap). !
' Table 2.1 provides sample MTBF and MTTR-data' for several. basic (i.e.,
- . nucleus) computer systems. Both' single -(CPU) ~and dual (CPU /IPU) i
. configurations are included for the CONCEPT 32/67,32/87 and 32/97 product lines. '
i l
Combustion Engineering, Inc. 22 Gould CSD l
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TrueLreliability is revealed by field performance. Reliability estimates, however, .
arei a valuable tool in design, maintenance / spares planning, system-configuration and evaluation. Field performance of Gould CSD products ,
consistently demonstrate reliabil;ty which exceeds that estimated by a factor of 2:1 or greater. The use of MIL-HDBK 217D as a common denominator, coupled -
with conservative assumptions in the areas of duty cycle, quality levels ~ and; j worst case configurations, provide the user with estimates that are both uniform-t and traceable. ,
J\ , Assumptions .
D The following assumptions are utilized in system calculations. l Assembly predications are generated considering all elements in a series configuration.
. System calculations are performed by developing reliability block diagrams which reflect the actual configuration of the system' (series, parallel, series / parallel, with/without repair, etc.).
IC failure rates are predicted by means of Section 5.1.2 of MIL-HDBK 217D. Bit and gate counts are obtained from MIL HOBK-
. 217D as well as from vendors and RADC Handbook MDR 18. ,
Failure data on all other components'is derived from MIL-STD- t 217D.
The Ground Benign environment ( '=1) is used throughout. f
(
H.
Calculations are based upon +35 degrees C ambient temperature. .i The duty cycle of all hardware, except.for memories, is assumed to be 100%. Memory devices have duty cycles which are defined by :
L: the configuration of the memory assemblies.
In order to inject worst case conditions, peripheral devices are assumed to experience 100% duty cycles.' Failure rates are l
generally supplied by the vendor.
A quality level of B 2 is used throughout.
+
The effect of using Error Correcting Codes (ECC) are considered in calculations of memory devices.
Combustion Engineering, Inc. 21 Gould CSD
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THE ONE-0VT-6F-TWO CEA POSITION / CALCULATOR ~ DESIGN, ,
y FOR. INSERTION DEVIATIONS (REAL OR : SPURIOUS) DELAY'CPC TRIP AND. INITIATE REACTOR POWER CUTBACK. IF: CUTBACK FAILSLOR DOES NOT PROVIDE SUFFICIENT MARGIN, THEN CPC TRIP W'ILL- N r
j OCCUR,
- FOR W!THDRAWAL DEVIATIONS (REALLOR SPURIOUS),sINITIATE.CEAL M0T10N' BLOCK USING REDUNDANT 1/2 LOGIC. CHANGE'CPC.TRIPTTO:
H 2/2 LOGIC'.
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ESF-COMPONENT CONTROL SYSTEM - SCOPE OF CONTROL L
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C C uN 1/0 0 0 C C UN 1/0 0 0 q ($fANDBY)
E O NT C C E O NT C C 8 M DR E E 8 M DR E E ,
B A 0 8 8 $ A 0 $ $
0 NL $ $ 0 NL 8 8 R C 0 0 R C 0 0 Y R R Y R R ,
I II i q MULTIDROP l l NETWORK ,,
F SUSGROUP I/O (i.e, PPS, APC, ...etc.)
ese see eee t
N N N E RFM E RFM E RFM T T ooo T C (FIELD C (FIELD C (FIELD 1/0) 0 1/0) 0 0 1/0)
M M M hh h h h h COMPONENT & COMPONENT & COMPOWENT &
DATA ACQUISITION DATA ACQUISITION DATA ACQUl$1T10N INTERFACES INTERFACES INTERFACES

LOCATED.!N CCS EQUlPMENT ROOM CABINETS = WIRE INTERFACE
= REMOTELY LOCATED IN CONTR0i PANELS - - - - - = F I B E R OP T I C INTERFACE
a REMOTELY LOCATED IN DISTRIBUTED ENCLOSURES FIGURE 5 CCS SUBGROUP SEGMENT
l ! .
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1I1 ggg ggg i I I I l 1 I I
. DOE - SIC - K - R - K -
! .I I Db IRIRLINK Db' INDEDE 4 RRE's 4 CPM's (OmrIYDL 4 Rf9t's 4 RRE's 4 RFM's 1 CRt (RE!MME 52 OGEUENIS 52 CGEUE!NFS 52 OGEU ESFIS 52 GEEGE!NFS DIVISIN B 1 I I I I I I I I DPft WWE I I I I I DOE - K - SIC - SBC - SBC -
l l i DES Dk I 4 CRE's (GNIRL MXDI) INDEDE IRIALDEl: 4 RPM's 4 RRE's- 4 RRt's 4 RFM's '
1 CRt (RDUIE SIMID0tet 52 GEEU4!NIS 52 ESEUE!NFS 52 OGWU45ftS 52 OWEUE!NIS PANEL)
DIVISION C 1 1 I i !
DovS*:- De l l mm l I I Note: DOE = DIVISIGE GNINE 95t!!FIER I DES Db IEWE = DIVISIGE AUXII2ARY 95tSHR i 4 RRt's IRIRLDEC IRIRIDEC SC = SUBGRX3P IWG11!R GEftRN22R :
25 OGEUENIS CRt = 0[BFINE PAfE!L MLTIPIEXER !
2 CRt's (CGFINL RETE = REBUIE FIEID PULTIPIEXER i 1 CHI (Mentim '
DIVISIN D '
I I I !
I DpM l met i Da v&-
1 I -
DES Db 4 RRt's DPLTALDEC IRIRLDEC 25 COMEGENIS !
CRt !'
PANEL)
FIGNIE 8 ;
SYS80+ ESF-CES SIZDG 1 CCNFIGJRATION '
i i
_ _ _ _ _ _ _ _ _ _ . . _ _ . _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ ___________.____..-r___m _________________m_ _ _ _ _ _ _ _ _ . _ _ _ . - ~ . _ _ , , _ _ _ _ _ _ _ _ _ _ _ _ _ = _ _ _ _ _ _ _ _ _ _ _ _ . ______m ___-,
1 1.
DIVISION N1
. I I I I I I I I '
1 fl I I I I l-not -
DPM DPH -
s:c - suc - suc ] l suc l see ops or,S I I I I I 8 CRt's (00NIR L IRIALDEC IEEPLDEC 7 RRE's 9 RRt's 9 Rf9t's 9 RI9t's 9 RRt's .:
RXM 59 GBEGE!NIS 59 OGWUIENIS 59 OWEUENFS 59 QBEUENIS 59 GBEUENIS i 1 CRt (REN7IE ) i SIIIIDCBM i PANEL)
DIVISION N2 '
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1 Cm (REN7tE SIRTIDOIE f PANEL) .;
l I'
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IEWE = DIVISIGE JEKILIARY 95MMIR i EBc = sUBGEXP IWtEm5t gem 0tJJ!R !
CHE = QBmEL PfGE!L DELTIPfJDER 1 RE9E = RIBUIE FIEID NX21PENI5t i
! I l
P FIGNIE 9 SYS80+ PIO3 SEMIS SIZDG !
00NFIGURPGION l
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1 Document No. NPX80-IC-SD640 i Rev. 00 Page 135 of 137 ,
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FUNCTIONAL GROUP CONTROL y
Reliability Andysis Shows the CCS Functional Group Control to be More Reliable than Traditional Single Loop Control
Improvements in CCS P2H"y nessnesy Anmysis senese Funcnons over Single Loop Control increases Loop Group j
with Flow Path Complexity Typionicomoeor MTBF 6 years 5 years Typics cenerener MTTn a neurs s nours
Since all Possible CCS Failures Flow Pam Compteuky 5 components 5 components
]
, Would be Restricted to a Functional nummerwcowomers s i l Group Rather than Individual l Components, the Effects are er. ore Fiour Pelh Awmanhammy 1B9.9230% 99.9817 %
Predictable and therefore more ~ .
Manageable. Fiow Pam UnevensMuty 33.3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months 8.0. hours M year)
T I
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! COMEBUSTION ENGWdEERW8G COMPODNENT CONTROL SYSTEM i
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FIGURE 'A - HPSI TRAIN's CONTRf.JL GY FUNCT3ONAL GROUP A3 1 CONTROL '
~W4ESPONSE 73 POWER A3 .
T-- T--- F----- T'' T--- T- F : T - -- r -- - - t l I I l l l 1 1 I I I l- I I I I 4 I ple 8 I l .
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, FIGURE B - HPS3 TRAIN I CONTROL BY TRADITIONAL ILS
! CONTROL POWER -- --- ---- ------ -- ---- -- ---- -- -- -----
INDIVIDUAL ~
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(P-1) (P-2) .
(SG-1113) (SG-1123) (PULIN) (n---.s>tW) o OWEDIG o OIRRGDEG IHESSURIZER IEESSIAE o FHDSt1ER o FEEIDetHR S1 DIM BYRtSS RDF 1 RPF 2 CONIM L RDF 1 RDF 2 CONIRDI, W (OIP-1) (OE'2) o , , (FWP-1) (MfP-2) ,.
< IRESSURIZER IEVEI, CONINDI, o FMD8mR o FUDemR :
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e:
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? DATA DIVISIOff
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---_me-- - - --_ u---- --m-s- -i..-_--c- . . . . - - _ - - - - - - - _ -
SLIDE 065 NUPLEX 80+ ALTERNATE PROTECTION SYSTEM ALTERNATE REACTOR TRIP SYSTEM (ARTS)
TRIPS CEDM POWER SOURCE ON HIGH PRESSURIZER PRESSURE. i i
ALTERNATE FEEDWATER ACTUATION SYSTEM:(AFAS)
ACTUATES EMERGENCY FEEDWATER SYSTEM ON LOW STEAM GENERATOR LEVEL.
1 DIVERSE FROM PPS l
1 l
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ML20055E519

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