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KR9700120
KAER I/TR-846/97
System Analysis Procedures for ConductingPSA of Nuclear Power Plants
1997. 3
VOL 2 8 te 2
KAERI/TR-846/97
System Analysis Procedures for ConductingPSA of Nuclear Power Plants
1997. 3
PSA
(System Analysis Procedures for Conducting PSA of Nuclear Power
Plants)
1997ld
: o|
S * W £ «Wa|tfgrfcs| *tm£*\ £^^^S^^ (Probabilistic Safety
Assessment : o|*|- PSA) °\\M
a. ^ ^ ( F a u ) t
Tree Analysis) ?|g# Afgs^cK H & ^ ^ o i a ?f|#o| i | a » ?|^
^ , 0| «• #^*h Efl7h S|fe- S-B 3 ^ * AND, OR § NOT S|
711* ^ ^ ^ ^ ^ # ?l«H i Si^i ^t ^ l# s l Sa^rZ! (Top Event)
|B[ 7||*0| fflfiS ^ | ^ § AHg
f§0||Ai aS^CK 7||*S
, o|o|| U\B\ ^ 711*011
@2|o|| txj-s|- $ 7||a| e^sj- (Segment) ° ^ f S S f 2 , o |#
7|7| £ [ f lS « - ^ t Top-Down
, o|
(Basic Event) o\B\
711* n^^r^ ^4io| &Ajs|g KIRAP SHSI CUT a i t
Til&*K oi
71l*a| o|#
3J
** 1 S M& 1
*l| 2 S- *IS£41 3
*il 1 3 7|£?l-§ 51 §0iS2| 3
*l| 2 S H§^a £*j ^ a 4
1. «H3 4
2. 2L§^^ gq 5
n 3 3 ^IS^^J 7IS- u| 9
1. H2K^£*1 ^IS ^ 9
2. H£K^ 7|^A^ %yi\O\m %<£* 9
3. c«#*|5s| AIS §! # 10
4. ^ I S # * l # ^ & ^ S ^ S § i ^£ 10
5. nm^mi =?•£ 12
6. *IS£}33I£ 5! #^-y 13
7. 7|£ UBiA^ Si 7 ^ A ^ 19
7.1 nx^a^AjA| 2 ^ 4 f 19
7.2 £*J2| Al-Ai|S£ 20
7.3 HS^^g-M 7|^7|-aA^ 21
^ 4 S E ^ TflSS 3 2 ^ ^ ^ £ * j 21
1. ^ I # ^ ^ ^ I ^ ^ I S O|sH 23
2. 7j|#^7i| Si £33£O|SH 23
9! ta| 50
5 4
5 5
5 6
5,6^1
5,6
5,6
8
12
15
18
24
(HPSI) IIS •a^l S f i 28
MB
TMI 3! *ll itSJ S U H ^ S ^ (§ig) A p t g* |7 |g A p t ^7 W t gcHApsA-l, o|
A p o | * n | ^ ^ b|5g|. *ui|7j| SS M ^ S S « r * & 3 S+S£ S?r (PSA :
Probabilistic Safety Assessment) g jg# M § § N gc||Apo||
3J
o,£joj| c^^aj ^ y ^ ^ ^ ^ H d 31 ApfiJal H ^ z i ^ S ^S-S- PSA*
faf f Am Ama|2gfc n|-2t*m n2^a^# S^^Jl, 0|fi|- -g
^ m ^ m PSA ^ Sh pSA
PI flff S^S^ ^Ifisi £#o||
£ S PSA £ £
(SystemAnalysis) o!e|- ffc|-. psA0||Aio|
K o| ^ § S
(Failure Mode and Effect Analysis),
(Logic Diagram), ^ § T ^ (Success Tree), 2 ^ t ^ (Fault Tree) §o |
sfQS 711* &M (System Analysis) o|ef
PSA $IS ^
o| 2 f§§^fe Ti^^M, ?||*2| ^711, § 2 , A|g 3| M^ § 7i|
711 * # ^cHS^ 7|^o^_^ nxj.ac. °j g^t^.^ (Faj|ure M o d e a n d E f fec t Analysis)
(Logic Diagram), ^ ^ ^ ^ (Success Tree), U S T ^ - (Fault Tree) §o|
1 2 ?|£7rS S!
5,6S7| 5 j # ^ Level 1 PSAOll
0 |2|s|
• PSA «r#&«1 ehS S 7 r (Probabilistic Safety Assessment)
• KIRAP
(KAERI Integated Reliability Assessment code Package)
o| 7|"g€ 1962"doi| Q R 2 | Bell S S ^ ^ i k (BTL, Bell Telephone Laboratories) a| H. A.
Watson oil sisHAi 7H#£ |OHCL 0 | ^ Minuteman Missile s| ^ A
me- s i± MHA-ioj WASH-UOOOI M ^ OI
ya|
o| ^ S
2.
Event) °
* m 1 & £ E S SSM-^I ^ & 2 S f l E , S?»k 3J flS^ * * l (Failure Modes, Effects &CriticaIJty Analysis) S # s ^ n z j * ^ A J S ^ 7p|° | j i ^HHf i f ?||#o|| Q|*|^- S2,kS
J 7|7|O||
gjo|| 2|&Seo|
Fussel ۥ
ojo|0| £|^
2*3 g 5J
*i*oi|Ai fe a e 7|7|2)
7|7|fi|
aa si ^ i * §3
EHZ§-^o|
s n &
o —r
US
oiSM711
S.
9 y\ s.
O (Basic Event)
o (Conditional Event) fl|oj= § . (Priority,Inhibit »|o| EO||
o (Undeveloped Event)
(External Event)
(Intermediate Event)
0 OR gate
Q AND gate
O Inhibit gate 0| 7f|0|M2|
Exclusive OR gate OR
Priority AND gate
c f l(Transfer Symbol)
n||0|x|) 7\\o\E.s\9\
i TransferIn J*r Transfer Out o|
Si
1.
32
7|7| £J£|£ Xf£, t S ± S3 EH §0| PSA £30|| £|*H ^^EJDi, 0|0)|
2. H ? h ^ ^ ? I & A ^ 3! 7i\o\ e g a | a (Naming Convention)
Si
7|7|S|
3. cfl#7flss| 4dS 9J
5,6 S?|° | g ^ A p g f l t n r ^ *P I fl«H ^ S A ^ ^ S / D H S 2 l # ^ s ( S m a N E v e n t
Tree/Large Fault Tree) g j g # A ^ S S ^ D K O| ghas
(Front-Line System)
§J
(Support System) o|sh
Ol SiCK 0|
nm Soilo| #
(Source
Term) s| 37 |# ^ S ^ ^ 2J^ 7j|#£ H & ^ = ^^o l | a»ScK o|37|| Mo
, PSAS *|sH tiSS ^ l # ^ ^ S3)oil a.\z\ A ^ 4 » ^ S | fifll (Heading)
* (Front-Line System) S^r Sfl|o|| u^E^^lfe %x\°} Sfl?||#2
M i ^ l s (Support System) ° ^ S#t.^K ollSAH, S ^ 5,627|
^ 31 # S § S 2011
10
•§• £! (System Operation)
(System Design)
31IP I (System Function)
# 3 I £ *' # ^ - ^ (Interfaces and Dependencies)
-MS *! S^r (Test and Maintenance)
5!
^ D H T T 9 (Station Manual)
t}-yH(Electrical Single Line Diagram)
• *\\o\ *' i |§5 |SH(Cont ro l and Actuation Circuit Diagram)
- # W (General Operating Procedure)
•§•-§•£] * W (System Operating Procedure)
* W (Emergency Operating Procedure)
1 * W (Abnormal Operating Procedure)
• ?Is-S-S*l£l>M(Technical Specification)
XrSS|O||£. SI
£ £ ,
11
B.2
T I P (High Pressure Safety Injection System)
i* 001 g 3 (Safety Injection Tank)
(LQW Pressure Safety Injection System)
a 91 *i #(Front Line
Systems)
(Shutdown Cooling System)
(Containment Spray System)
(Safety Depressurization System)
°i (Chemical and Volume Control System)
(RCS Pressure Control System)
(Auxiliary Feedwater System)
(Main Feedwater System)
(Mam Steam System)
7)1 g (Engineered Safety Features Actuation
System)
(Reactor Protection System)
(Steam Generator Blowdown System)
(Electical Power System)
(Support
Systems)
(Component Cooling Water System)
(Essential Service Water System)
(Essential Chilled Water System)
(Heating, Ventilation and Air Conditioning System)
(Instrument Air System)
5. (System Boundary) s\
t 0|O)|
(Interface)
12
7|ja|
6. n^7J <£n& % ^ ^ (System Interfaces & Dependency)
7|7|
CO), 5
#) o|
7|7|2|
oie §° a^^l#§a|
(Transfer) ?1|O|E
o|a711 |#z}s| fl# Sfll# S«r*l H^ ^ l § ^Ai |* | iAf«Hof fj-ch 04|« ^ o i 4.16W AC a^^ l«o f | CH& HQ^S^^ n. 4.16kV
AC j sa a
13
fe 5101
K o|
*l
3 * 1 * 1 * ^ g^SHfr * l * (CE)
3*1*1*011 2|*H s^#s|fe- * l * (AB)
jfe * i * (ggh)
14
Reference*
Interfacing
HPSIS
LPSIS
SCS
CSS
SDS
AFWS
MFWS
MSS
CVCS
EPS(Vital)
DG
CCWS
ESWS
ECWS
HVAC
IAS
ESFAS
RPS
S.
HPSIS
**
CE
CE
CE
CE
D
D
D
D
D
D
AB
3 9^5,6
LPSIS
CE
**
CE
CE
CE
D
D
D
D
D
D
AB
SCS
CE
CE
**
CE
D
D
D
D
D
D
*IS 3! # ^
CSS
CE
CE
CE
**
CE
D
D
D
D
D
D
AB
^ (1/3)
SDS
**
D
D
AFWS
**
CE
D
D
D
D
D
D
D
D
AB
AB
CEDSAAB
Common ElementDependentSupportsActuatesActuated By
15
Reference*
Interfacing
HPSIS
LPSIS
SCS
CSS
SDS
AFWS
MFWS
MSS
CVCS
EPS(Vital)
DG
CCWS
ESWS
ECWS
HVAC
IAS
ESFAS
RPS
a.
MFWS
CE
D
D
D
D
D
D
D
3 23^5,6
MSS
S
D
D
D
D
D
D
D
§.7\ 2tm 9i
CVCS
CE
CE
CE
D
D
D
D
D
D
D
EPS(Vital)
S
S
S
S
S
S
S
S
S
**
S/D
S/D
S/D
S/D
S/D
& (2/3)
DG
S
S
S
S
S
S
S
S
S
S/D
**
S/D
S/D
S/D
S/D
CCWS
S
S
S
S
S
S
S
S
S
S/D
S/D
*•*
D
S/D
D
CEDSAAB
Common ElementDependentSupportsActuatesActuated By
16
Reference*
Interfacing
HPSIS
LPSIS
SCS
CSS
SDS
AFWS
MFWS
MSS
eves
EPS(Vital)
DG
CCWS
ESWS
ECWS
HVAC
IAS
ESFAS
RPS
3.
ESWS
S
S
S
S
S
S
S
s
s
D
D
D
**
D
D
3 ocf5,6
ECWS
S
S
S
S
S
S
S
S
S
D
D
D
D
**
S/D
2.7\ 3I#?3
HVAC
S
S
S
S
S
S
S
S
S
S/D
S/D
S/D
S/D
S/D
IAS
S
S
s
s
**
2 (3/3)
ESFAS
A
A
A
A
**
RPS
A
**
CEDSAAB
Common ElementDependentSupportsActuatesActuated By
17
S. 4 5,6
HPSIS
SIT
LPSIS
SCS
CSS
SDS
CVCS
RCSPCS
AFWS
MFWS
MSS
SGBS
EPS
DG
CCWS
ESWS
ECWS
HVAC
IAS
ESFAS
RPS
*l * o| s
HgJ-eiS^'gJ^II-S- (High Pressure Safety Injection System)
o}£ *IOJ |y 3 (safety Injection Tank)
* i ^ S F S * S * l # (Low Pressure Safety Injection System)
S *l ^ 4*1 * (Shutdown Cooling System)
3 te ras ^ - ^ r ^ l ^ (Containment Spray System)
2^3 ^ M I S - (Safety Depressurization System)
*r*|- §=' * l ^ fl|oi?l|-9 (Chemical and Volume Control System)
S^rSy)4^H^I* £^*H°i3l# (RCS pressure Control System)
M-E^^ l -S- (Auxiliary Feedwater System)
^•^"r^l^ (Main Feedwater System)
^ § ^ M I # (Main Steam System)
f P I ^ A p l ^ISTJl-g- (Steam Generator Blowdown System)
2 ^ g ^ 3 l # (Electric Power System)
q a gj-g 71 (Diesel Generator)
? 1 ? 1 y Z-TT8 *l S (Component Cooling Water System)
B ^ S T M I ^ (Essential Service Water System)
H T ^ ^ I ^ (Essential Chilled Water System)
57|ss|-7i|S- (Heating, Ventiation and Air Conditioning)
o^^g7| ?j|# (instrument Air System)
g«f-sj o>S-y b|^|-g. (Engineered Safety Features Actuation System)
S ^ S £S^ i ! # (Reactor Protection System)
18
7.
7.1
31341* ^X|&CK ^ ^ £4| c«& 7j|#o| a f l , t a p i s , 7|£A^H S E Sj
i-a §o| o|7|o||
o|so||fe-
_ 7|7|2|
(Dependent Failure) o||
ejsH a
(Functional Dependence) o|| a i £ 7|7|7F g
A| g si s ^ (Common Test and Maintenance Activities) oil
(Multiple Failure Events) o|| m a S«|-a
h s.§| 7|7|a|
19
(Common Cause Failure) *\ qz\ * I 5 S §A|O« 0 | g#7 H=r
(Common Mode Failure) o| g ^ i h ^ Xi^HS ^i§sf7|| Q S & C K O)|#
o|A/s| cfg 7j|^ (Multiple Trains)^
c|)71 goj A^EHS HSISSWI S^K H B M d|§M saspoilAi
(Identical Number) ar ?|7|fi|
7.2 S* l 2| ^A|| § £ (Level of Detail)
j x^a| ^
20
*KS7rB=2r*l|OfS|£ (Control Circuit) §2 I
C||0|Erd||0|>:0|| °|
SS§F0i nxi-^aollAi fl|2|^cK o||* g S tins, Qgl&EHs g-21 S (Locked
Open Valve) sr ^ ^ ^r^7|7| (Passive Component) <-\ y ^ ^ ^ « r » * * l t ! 2 ? , ^
2| fi-
7.3
CrgS S & 5,6
7|| * 2 | 5 | ^ A | 7 | (Mission Time) S ^ ^ ^ ^SrO| oft! & 24*1 Z>° 3.
7\°\ ^X\ Sf
7|7|
(Short) §e}
fi = , ffls. H & ^ s i ^IAJA| ^ g S|S*rE^| (Circuit Breaker) fe-
o|#
ai *ia§
21
(Top Event) ^ o|o|| CH°[ £ g 7 | ^ § o|5[|SR
SMOI«H
(System-Level)
(Node-Level) £ 1 T 1 ^
(Segment-Level) a f
(Component-Level) £
5!
M Sf- (Documentation)
22
3!
Til*, * | # 374 (System Boundary), * |*z}- g a i £ , 2 § K ^ 7J|o|M gi
7|7|o|| c«&
7|7|S|
iiihSEH go||
2.
0|*H7|- SSLSr^K 0|
oj|d| % £ | ^ e ^ a ^ ^ ^ a H A i (PSAR, FSAR) 2|
(Design Requirement)
(Design Specification)
(Interface Requirement)
(System Description)
(Operation Guideline)
3.
7||*0|
23
2.O\, 0|Oil
£- (Safety Function) 3jI M.>
££,
5<=HI
LOCA
S. 5 Hlgm
GHSIETOP
GHSIGTOP
GHSRDTOP
GHSRGTOP
GHSHBTOP
s-T-fcL|7ii-§- o i S ' T ^ agA| -a §• STS a
Failure to inject water from RWT toRCS through 2 of 3 cold legs using 1of 2 HPSI pumps
Failure to inject water from RWT toRCS through 1 of 4 cold legs using 1of 2 HPSI pumps
Failure to inject water from Sump toRCS through 1 of 3 cold legs using 1of 2 HPSI pumps
Failure to inject water from Sump toRCS through 1 of 4 cold legs using 1of 2 HPSI pumps
Failure to inject water from Sump toRCS through 1 of 3 cold legs and 1 of2 hot legs using HPSI pumps : LOCA
a
S.LOCA
± § LOCA,
Pi § LOCA,
H-B
«LOCA
24
£- PSA
3 (P&ID) §
f psA0]|A-i ^ S £ | r r ^I
o|
3J ^ A i t
15- (Front-line Fluid System)
-S| -S. (Minimum Recirculation Lines)
• a s ^* ) | 3 I# (Support Fluid System)
(Electric Power System)
tJ £ (Single-Line Diagram)
3i ^|CH3I§ (Instrumentation and Control System)
7ii 71 SJ X-IIOJ 1 #°i ch^Tii^s^ a asm awe) s a s
§71SSMI5 (HVAC System)
(Damper, Fan)
a 7 p | (Compressor, Damper)
25
• o\x.\^; ^tg£.MI•§• (PowerConversion System)
t! § 7 | g J £ « « (ADV, MSSV)
# (Primary Pressure Relief System)
S (SDS), 7rgp| y S l H (PSV) SI
(instrument Air)
P&ID, S7|^|# £*££. SI Y * W ^ (Load List), B+S fi5 £ 3 i!
P&IDS ti 7|fe ^^ol l 5+SS t*H f i j 7|7|#
rsSrCK O|
7|7| SS ^ ^ # #£§ | HSiSK^ B £ & HHfil- S 7|7|# ^p^
§0| 7|7| SS
ojgcK 7|7|2| 7 |^
0|«H0||§='
10
7|7|
(ESFAS) CHI SI
26
^PI (Active Component) fe
K o| S X I * c i ^ Sft ist f l *PI ? l^o i "Inside Containment" ^ "Outside
Containement" B^
5. E|- TflSBfSl ^7l|Aj JZ|.Q|
O|o|
a 3011 ,
H S.
t. o| S ^
2| 7p|2| s ^ i & ^ ^ o | | s o | ?flo|M (Transfer Gate)
27
(HPSI) sa
SI-617, 627, 637,
647
SI-616, 626, 636,
646
SI-603*
SI-604*
SI-321*
SI-331*
SHOrifice
SI-699**
SI-698**
7|7| £5*|#
4.16KV 5-SW01A
125VDC12-DC01A
4.16KV5-SW01A
125VDC12-DC01B
480V MCC 8-MC08A
480V MCC 8-MC08B
480V MCC 8-MC05A
480V MCC 8-MC05B
125VDC12-DC01C
125VDC12-DC01D
480V MCC 8-MC05A
480V MCC 8-MC05B
S 0 | 7 | | 0 | E 0 | S
GEK01A
GED01A
GHCHPSIP1
GFSSIASA
GEK01A
GED01B
GHCHPSIP2
GFSSIASB
GEM08A
GFSSIASA
GEM08B
GFSSIASB
GEM05A
GEM05B
GED01C
GED01D
GEM05A
GEM05B
H| H
*| |Oj*1^
SIASS ^ #
Motive power
Open on SIAS
Motive power
Open on SIAS
6.
* S (Flow)
PSA
28
e** l£S % ?1\2\ z\* * IS ^ f e ^ S ^ H (Flow Node) o)| s|«H
^l Ei-^i (Segments) ° ^ • ? £ » 4s 2J^K oi^|A-| ±E.B[ %^ ^
fi|°l*W, ^ a | ° c= 7||o|
Top-Down
7|7|
7|7|S| ^
6.1
O|
H§ ,^^^<M 3E°J KIRAP^ = o||Ai^ £|CH 8 2 ^ ;
^l^m ^ Sic- S?I^F fl|&=|0| SP|
KIRAP
7|7|o||
7|7|
2 :
| ^ h | | | | & a OR
AND ^ S ORM7|- 7|7| £hfl * ^ Ef 71IS o ig t ^ l ^ W O|
3: a- 7|7|sj
o|
29
oe
tekk \sU & Ma g (sjuawBas) tea Is Ik 16
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l o i
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^ k IIO|Y : z.
kilo*Ikte fs kk ^tete^ Bte §^#§lo te*ik 1°fb : 9
lotelta
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o|£|- ^ §
| Top-Down
221 l# A *
31
m•Ho
<IUJO
n
32
6.3.1
332-o|o||
c- 'House Event' 'Conditional Event '*
° H ^ oil-
IE-2HIBIA2I
GSYS-A-IE1 : No Flow to One of Three Loops (Loop 1, 2 or 3) from System A
GSYS-A-IE2 : No Flow to One of Two Loops (Loops 2 or 3) from System A
GSYS-A-IE2^ Loop 12| n r£ ^ ° ^ Loop 1 °
Loop 2 ^ 3 S S|4i& O\± Z\\-\g. ^
4011
6.3.2 i n = (Node)
33
No Flow toLoop 1 fromSegment A
GYS-A-IE1
No Flow toLoop 2 fromSegment G
No Flow toLoop 3 fromSegment H
3. GSYS-A-IE14I cHfi
GYS-A-IE2
No Flow toLoop 2 fromSegment G
No Flow toLoop 3 fromSegment H
GSYS-A-IE20II
3«r (diversion)
^ ^ l # A
t £
S O|
O R
A2| Loop
34
6.3.3 ^(Segment) ^ 5 fil
CC|-£|. SjSsJ 37|S|
5^1 n ^ ^ a o l l ^ Et^LHsj ^ * | | * S # SEis fe 7|7|
"OR" ?1|O|E^ g § g c h f
6.3.4 7|7| (Component) ^r
f e^LHS| ^AH 7|7|0||
7|7|
7|7|
(Independent Component Failure)
7|7|2| SS-Sei^lS- (Common Cause Failure)
• * IS S! ^ ^ S . ° J ^ 0| §M-^- (Outages due to Test and Maintenance)
• a^=§! ^-S ^ S ^ s | °J7} £ # (Human Error related Test and Maintenance Activity)
• 7|7|2| ^ § M ^ # i £ H s ^ M i? j |#s | 7|-^ &AJ ( L o s s o f F u n c t j 0 n o f Support
System)
- *l|ci % AJS n& (Control & Actuation Signal System) s| 7|^-
- 2 717|| § (Electric System) s| 71 ^AJ
35
MJfO
<m|o
10mn
36
GYS-A-IE1
No Flow to Loop 1from Segment A
No Flow to Loop 2from Segment B
No Flow to Loop 3from Segment C
Loss of Flow dueto Segment A
Failure
No Flow fromNode a
No Flow fromSegment B
No Flow fromSegment C
JZLoss of Flow due
to Segment BFailure
No Flow fromNoded
_LLoss of Flow due
to Segment DFailure
No Flow fromNodeh
6. LOOP1
37
No Flow fromSegment D
TJ
Valve W41Failure
PumpPP101Failure
Check ValveCV 22 Failure
Valve W 42Failure
Motor OperatedValve MV 02
Failure
7. D oil
Pump PP 101Failure
Q
PP 101 Fails tcStart onDemand
PP 101 Fails toRun
Failure ofSupportingSystems
PP101Unavailabledue to T & M
CCF of PP101 & 102
Loss of ElectricPower
Loss of CCWto PP 101
Loss of Signalto PP 101
Failure of PP 10due to Loss ofRoom Cooling
8. S ^
38
(Component Cooling Water System) 2|
(HVAC System) s M f e S6I
(Instrument Air System) s| 7|fe
? € (Actuation) 3!
*«oj (Control) * l * * r 2
— (Motor-Driven Pump, Turbine-Driven Pump, Diesel-Driven Pump)
-&x||7|^^u(| (Fail to Start or Fail to Restart)
U S (Fail to Run)
S— (Check Valve, Manual Valve, Safety/Relief Valve, Motor-Operated Valve,
Pneumatic/ Hydraulic-Operated Valve)
- fi S / £ S 61 =H (Fail to Open/Close)
- IB S &E|| ^-^1 -y "H (Fail to Remain Open/Transfer Closed : Manual Valve or Check
(Heat Exchanger)
(Tank)
(Compressor) 31 SI (Fan)
8011
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PSA
50
[1 ] "PRA Procedure Guide", NUREG/CR-2300", ANS and IEEE, 1982.
[2] "Probabilistic Safety Analysis Procedures Guide", NUREG/CR-2815,1984.
[3] "Procedures for Conducting Probabilitic Safety Assessment of NPPs (Level 1)",
IAEA, 1992.
[4] "Hal 3,4 2? | SJ S i r 1,2 2?I PSA 4 * 9 1 W , £ R 9 ^ § > 4 , 1992.
[5] "Fault Tree Anlaysis Guidelines", Commonwealth Edison IPE/Accident
Management Program, Rev.0,1990.
[6] "SI* 5,6 2 7 | S r l ^ s j ei-S^ S7|-o||ti| m?t ^^LM", tl^tt^gM, 1996.
[7] "-£]£|£ 71 ^ - ,
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1.2.4 Y § ^j ' i x|- (Component Identifier)
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ST
HS
LS
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S! x r s a 4xn ?i| § (Reactor Coolant System)
°}*\ ^o j ^ B. (Safety Injection Tank)
H^ej-S^-i i (High Pressure Safety Injection System)
x\oi2}x\^°}%\& (Low Pressure Safety Injection System)
S ^ l ^ 4 ^ l # (Shutdown Cooling System)
(SC S\ LS?r g ^ S r ^ ^-#oll V\mMTt "LS" « Ar8£rCr. )
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CF
PS
PG
PZ
MS
CD
MF
AF
BD
CC
CW
SW
PW
s.\s\ §J *)|sj xi|cH^IS (Chemical and Volume ControlSystem)
^ y - ^ i l - M ^ r ^ l * (Containment Spray System)
3 ^ 2 5 # # ^ z p | ^ l # (Containment Fan Cooler System)
^I-M^I MT^ I -S - (Pressurizer Spray System - Main, Aux)
?F^7| 7F^ ^ # ^ | # (Pressurizer Gas Vent System)
7 r gp I £h£! S S (Pressrizer Safety Valve)
T=-#7|?| |§ (Main Steam System)
^ 7 ! ? l l # (Condensate System)
^ « ^ r ^ l S (Main FeedwaterSystem)
S i ^ ^ l ! - (Auxiliary Feedwater System)
§71 7 1 ^|S^=^IS (Steam Gnerator Blowdown System)
7 | 7 | L § 4 ^ > | | # (Component Cooling Water System)
S ^ ^ I S (Essential Chilled Water System)
H T S ^ I S - (Essential Service Water System)
^ 2 ^ ^ T ^ I S (Plant Chilled Water System)
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S T ^ I I (Raw Water System)
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MV
AV
CV
W
LV
RV
SV
EV
XV
MP
DP
DG
AC
AB
AU
AD
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CQ
CU
FL
FE
NZ
¥ # oi m
Motor Operated Valve
Air Operated Valve
Check Valve
Manual Valve
Solenoid Valve
Relief Valve
Safety Valve
Electro Hydrulic Operated Valve
Other Valves
Motor Driven Pump
Diesel Driven Pump
Diesel Generator
Air Compressor
Blower / Ventilation Fan
Air Handling Unit / Air Cleaning Unit
Air Dryer
Air Separator
Cubicle Cooler
Chiller Unit
Filter / Strainer
Flow Element / Orifice
Nozzles
58
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DM
TK
PI
HX
CD
TB
HT
HR
BY
BC
HB
LB
RB
FS
XH
XM
XL
SP
GD
SY
BS
LC
¥ i o| §
Dampers
Tanks
Piping
Heat Exchanger (Including Steam Generator)
Condenser
Turbine
Heater
Heat Tracing
Battery
Battery Charger
Circuit Breaker (around 4 KV)
Circuit Breaker (around 600V)
Reactor Trip Breaker
Fuse
Transformer (High Voltage)
Transformer (4 KV to 600 / 408V)
Transformer (Low Voltage)
Sump
Grid
Switchyard
Bus
Load Center
59
1 2 fOi (3/4)
T#^oi
MC
PN
CR
IR
VR
FT
PT
TT
LT
PW
VW
MW
QW
LW
TW
SW
CA
CO
AL
AN
ID
Bl
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Motor Control Center
Distrbution Panel
Converter
Inverter
Voltage Regulator
Flow Transmitter
Pressure Transmitter
Temperature Transmitter
Level Transmitter
Pressure Switch
Level Switch
Manual Switch
Torque Switch
Limit Switch
Temeprature Switch
Other Switch
Cable
Coil
Alarm
Annunciator
Indicator
Bistable
60
'^. £2 (4/4)
RY
SQ
CP
Dl
RS
IK
CK
SK
FW
OP
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Relay
Sequencer
Capacitor
Diode
Resistor
Interlock
Control Circuit
Actuation Signal Generating Circuitry
Flow Switch
Operator Action
61
1.13
S
R
O
C
T
G
P
L
B
Y
A
1
M
H
V
U
X
N
E
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F
W
K
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Fails to Start
Fail to Run / Continue Operating
Fail to Open
Fail to Close
Transfer Closed
Fail to Reclose / Reseat
Plugged
Leakage (Reverse / Internal)
Leakage (External) / Rupture / Break
Fails While Operating / Fails to Maintain Output
Fails to Provide Output / Fail to Actuate / Generate Actuation
Signal
Spurious Operation
Unavailable Due to Test / Maintenance
Operator Error to Perform a Task / Operator Inadvertant Action
Operator RecoveryAction Failure
Operator Fails to Restore After T&M
Eletrical Short
Open Circuit
Fails to Energize
Fails to Deenergize
Failure (General)
Common Cause Failure (Demand)
Common Cause Failure (Operating)
Modularized Event
62
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INIS
KAERI/TR-
S!(AR, TR2J
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CH a 1996.12.
miom 68 p H 0) ¥( ) 3 J\ 26 cm
SUMS
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BIBLIOGRAPHIC INFORMATION SHEET
Performing Org. ReportNo.
Sponsoring Org.Report No.
Standard ReportNo.
INIS SubjectCode
KAERI/TR-
Title/Subtitle FTA Procedures Guide for conduting PSA of NPPs
ProjectOept.
Manager and Yoon Hwean Lee, Integrated Safety Assessment Team
Researcher and Dep't : Won Dea Jung, Tae Woon Kim, Kil Yoo Kim, Seung CheolJang, Sang Hoon Han, Joon Eon Yang, Tae Yong Sung, DaeII Kang. Mi Jung Hwang, Jin Hee Park, Young Ho Jin
Pub.Place
Taejon Pub. Org. KAERI Pub.Date
1996.12.
Page 68 p Fig.Tab.
& Yes( 0 ) No( ) Size 26 cm
Note
Classified Open ( 0 ). Outside( ),
( )Class
Report Type Tech. Report
Sponsoring Org. Contract No.
Abstract
This document, the Probabilistic Safety Assessment (PSA) procedures guide forsystem analysis, is intended to provide the guidelines to analyze the target ofsystem consistently and technically in the performance of PSA for Nuclear PowerPlants (NPPs). The guide has been prepared in accordance with the procedures andtechniques for fault Tree Analysis (FTA) used in system analysis.
Normally the main objective of system analysis is to assess the reliability of systemmodeled by Event Tree Analysis (ETA). A variety of analytical techniques can beused for the system analysis, however, FTA method is used in this proceduresguide.
FTA is the method used for representing the failure logic of plant systemsdeductively using AND, OR or NOT gates. The fault tree should reflect all possiblefailure modes that may contribute to the system unavailability. This should includecontributions due to the mechanical failures of the components, Common CauseFailures (CCFs), human errors and outages for testing and maintenance.
After the construction of fault tree is completed, system unavailability is calculatedwith the CUT module of KIRAP, and the qualitative and quantitative analysis isperformed through the process as above stated.
As above mentioned, the procedures for system analysis is based on PSAprocedures and methods which has been applied to the safety assessments ofconstructing NPPs in the country.
Accordingly, the method of FTA stated in this procedures guide will be applicable toPSA for the NPPs to be constructed in the future.
Subject Keywords : PSA, Fault Tree Analysis. System Analysis Procedure
