ELSEVIER www.elsevier.com/locate/pnucene
Progress in Nuclear Energy, Vol. 44, No. 3, pp. 191-213, 2004
Available online at www.sciencedirect.com © 2004 Elsevier Ltd. All r ights reserved Printed in Great Britain
sc ,~ . cE D , .ECV" 0149-1970/$ - see front matter
doi: 10.1016/j.pnucene.2003.12.001
FUZZY FMEA APPLIED TO PWR CHEMICAL AND VOLUME CONTROL SYSTEM
Antonio C6sar Ferreira Guimar~es* and Celso Marcelo Franklin Lapa a
Instituto de Engenharia Nuclear (IEN-CNEN) - Divis~o de Reatores / Programa de P6s-Gradua@o, Ilha do Fund~o s/n, Rio de Janeiro, Brazil, Zip Code: 21945-970, Po. Box: 68550
E-mail: *[email protected] or l [email protected]
ABSTRACT
In this paper, a fuzzy inference system (FIS) modeling technique is introduced to treat a nuclear reliability engineering problem. This method uses the concept of a pure fuzzy logic system where the fuzzy rule base consists of a collection of fuzzy IF-THEN rules. The fuzzy inference engine uses these fuzzy IF-THEN rules to determine a mapping of the input universe of discourse over the output universe of discourse based on fuzzy logic principles. The risk priority number (RPN) (typical of a traditional Failure Mode & Effects Analysis - FMEA) is calculated and compared to fuzzy risk priority number (FRPN), obtained by the use of the scores from expert opinion. These scores are opinions about probabilities of Occurrence, Severity and not Detection of a failure of the studied system. The Chemical and Volume Control System was adopt as practical example in the study of case. The results demonstrated the potential of the inference system to this problem clas s . © 2004 Elsevier Ltd. All rights reserved.
Keywords: Expert Opinion, FMEA, Fuzzy Logic, CVCS
191
192 A. C. F. Guimar~es and C. M. F. Lapa
1. INTRODUCTION
In recent study, the effect of aging on the Chemical and Volume Control System (CVCS) of a pressurized water reactor (PWR) has been evaluated (Grove and Travis, 1995). Since the CVCS provides many normal and emergency operating functions, it is important to understand the effect of aging in order to detect and correct these instances prior to component failures. A detailed review of the Nuclear Plant Reliability Data System (NPRDS) and Licensing Events Report (LER) databases for the 1988-1991 time period, together with a review of industry and NRC experience and research, indicate that age-related degradations and failures have occurred. These failures had significant effects on plant operation, including reactivity excursions, and pressurizer level transients. The majority of these component failures resulted in leakage of reactor coolant outside the containment.
Grove and Travis (1995) visited a representative plant of PWR design Westinghouse to obtain specific information on system inspection, surveillance, monitoring, and inspection practices. The results of these visits indicate that adequate system maintenance and inspection is being performed. In some instances, the frequencies of inspection were increased in response to repeated failure events. Also, a parametric study was performed to assess the effect of system aging on Core Damage Frequency (CDF). This study showed that as MOV operating failures increased, the contribution of the High Pressure Injection to CDF also increased. Failure mode and effects analysis (FMEA) is an important technique (Stamatis, 1995) that is used to identify and eliminate known or potential failures to enhance reliability and safety of complex systems and is intended to provide information for making risk management decisions. A modified failure mode and effects analysi s (FMEA) and knowledge base system (KBS) are proposed here to estimate the risk using scores from experts. Fuzzy logic systems (Zadeh, 1987) is a name for the systems which have relationship with fuzzy concepts (like fuzzy sets, linguistic variables, and so on) and fuzzy logic. The most popular fuzzy logic systems in the literature may be classified into three types: pure fuzzy logic systems, Takagi and Sugeno's fuzzy system, and fuzzy logic systems with fuzzifier and defuzzifier (Wang, 1993). The methodology used in this paper was the fuzzy logic systems with fuzzifier and defuzzifier, as used in the most investigations e.g. Pillay and Wang (2003), Xu et al. (2002) and Guimarfies (2003).
The knowledge-based fuzzy systems allows for descriptive or qualitative representation of expressions such as "remote" or "high", incorporate symbolic statements that are more natural and intuitive than mathematical equation. A direct method with one expert (Klir and Yuan, 1995) was used to aggregate opinion of individual expert.
This work investigates the potential application of knowledge-based fuzzy systems in a case study. The Chemical Volumetric Control System (CVCS) was chosen for this study.
2. DESCRIPTION OF CHEMICAL VOLUME CONTROL SYSTEM (CVCS)
A simplified CVCS system schematic is shown in Figure 1. The primary sub-systems included in this study are:
• letdown cooling system, • demineralizers, • boron thermal regeneration,
Fuzzy FMEA 193
• volume control storage tank, • boric acid supply, • charging pumps, and • Reactor Coolant Pump (RCP) seal water injection
Most of the components are located outside of containment, so aging degradations may result in external leakage of the reactor coolant. To fully understand the effect of system aging, specific information on the system's operating characteristics, material and design function is presented in the next description.
COMPONENT COOLING
~ , ~ WATER SYSTEM REGENEF~TIVE ''~.."~,~ " I
HEAT EXCHANGER ~".X'N _ :1 ~ ' " ~ : ~ ; ........
. . . . . . .
. . . . . . . . !.'~I COM~HEg
PRESSURtZER~
0 REACTOR (~ COOLAta ~ , ' Pu.P ~ ~
, i ."
L---
, / ?
s'm i !J ~NER =, "i :'('!
COOLING WATER SYSTEM
SEAL WATER RETURN COOLER
PUMP SEAL WATER
SUPPLY _
. . . . I . . . . . . . 1
~ DEMINERALIZER I BORON THERMAL I REGENERATION J
SYSTEM [
pu,G'ff" " ~ --#'~TE GAS " GASES
SUPPLIES /ME
MAKE-UP WATER , , . , i
BORIC ACIO
CHARGING PUMPS
Figure 1 - Chemical and volume control system.
The Chemical and Volume Control System (CVCS) for Pressurized Water Reactor (PWR) Westinghouse plant provides both normal and emergency operation functions. During normal operation, the three primary functions are to purify the reactor coolant, control reactor coolant system (RCS) inventory (pressurizer level control), and provide the reactor coolant pump (RCP) seal water injection. During an emergency, the primary functions for the majority of PWR plants are to provide high-pressure safety injection, RCP seal injection, and emergency boration. In addition, the containment isolation system, which includes CVCS valves, isolates the letdown and charging lines.
The typical system design used in the majority of plants is shown schematically in Figure 2. More detail about description of CVCS system can be found in Grove and Travis (1995).
194 A. C. E Guimar6es and C. M. F. Lapa
L a ~ From A
Co~LtO
r~S
F~S
P~S
LC~ LCV
Comment L~
H~I
AY p~ Sis9
L~
I ~ ~ , 111, 8157
,'g
k t
F~t
k a
Figure 2 - Westinghouse CVCS with boron thermal regeneration system.
3. DESCRIPTION OF FUZZY INFERENCE SYSTEM APPROACH
The "pure fuzzy logic system" is the system where the fuzzy rule base consists of a collection of fuzzy IF-THEN rules, and the fuzzy inference engine uses these fuzzy IF-THEN rules to determine a mapping from fuzzy sets in the input universe of discourse U C R " to fuzzy sets in, the output universe of discourse V C R based on fuzz3; logic principles. ~rhe fuzzy IF-THEN rules are of the following form:
R ~0 • IF xl is Fll and ... x , is F%
T H E N y is G l (1)
Fuzzy FMEA 195
where Fli and G t are fuzzy sets, x = (xl,. ..... , Xn) T ~ U and y ~ V are input and output linguistic variables, respectively, and l = 1,2, .. . , M. Practice has shown that these fuzzy IF-THEN rules provide a convenient framework to incorporate human experts' knowledge. Each fuzzy IF-THEN rule (Eq. 1) defines fuzzy set F~ x ... xF ln ~ G 1 in the product space U x V. In order to use the "pure fuzzy logic system" in engineering systems where inputs and outputs are real-valued variables. The most straightforward way is to add a fuzzifier to the input and a defuzzifier to the output of the pure fuzzy logic system. The fuzzifier maps crisp points in U to fuzzy sets in U, and the defuzzifier maps fuzzy sets in V to crisp points in V. The fuzzy rule base and fuzzy inference engine are the same as those in the pure fuzzy logic system. In the literature, this fuzzy logic system is often called the fuzzy logic controller since it has been mainly used as a controller. It was first proposed by Mamdani and Assilian (1974), and has been successfully applied to a variety of industrial process and consumer products. A detailed description of this fuzzy logic system can be found in Wang (1993).
4. APPLICATION OF THE PROPOSED APPROACH TO CVCS
Initially, an "expert" with knowledge domain on the analyzed system was adopted. The selected specialist belongs to the reliability engineering and can participate in other domains. A traditional FMEA using the risk priority number (RPN) ranking system is carried out in the first moment. Mathematically, RPN is represented as:
R P N = O x S x D (2)
where, "O" represents the probability of occurrence, "S" represents the severity of the failure and "D" represents the probability of not detecting of the failure. The values for O, S, and D are obtained by using the values scaled presented in Table 1 (Xu et al., 2002 and Pillay and Wang, 2003). The expert in the FMEA analysis was the same as in the proposed.
Table 1 - Traditional FMEA scales for RPN.
Occurrence (O)
Severity (S)
Not Detection (D)
Rating Possible failure rate (operating days) Probability Range (%)
Remote 1 < 1:20,000 0-5/6-15
Low 2 / 3 1:20,000/1:10,000 16-25/26-35
Moderate 4 / 5 / 6 1:2000/1:1000/1:200 36-45/46-55/56-65
High 7 / 8 1:100/1:20 66-75/76-85
Very High 9 / 10 1:10/1:2 86-100
196 A. C. F. Guirnaraes and C. M. F. Lapa
As presented in Figure 2, the primary functions of the CVCS are letdown, purification, boration and chemical addition, boron regeneration, charging, RCP seal injection and safety injection. The system consists of the mechanical components (pumps, valves, heat exchangers, volume control tanks, and de!onizers), instrumentation, and controls, necessary to perform these functions.
A Failure Modes and Effects Analysis (FMEA) was performed to determine the effects of failure of the major system components. Each FMEA included the following items: (a) Failure Mode: the basic manner(s) which a component may fail or cease to perform as design. The failure modes for these components were consistent with those used in industry reliability; (b) Failure Cause: the particular type of degradation mechanisms, which may cause the component to failure (stresses); (c) Failure Effects: the effects on the CVCS system due to the component failure; (d) Detection Methods: functional indicators or system and plant operating characteristics, which would alert the operator of component degradation and/or failure.
An important system function in many PWR plants is to provide High Pressure Injection under certain accident conditions. Since this function was previously evaluated (Meyer, 1989), it was not included in these FMEAs. However, it is important to recognize that many of the CVCS components that provide reactor charging are used for High Pressure Injection. Aging degradation and failures of these components, which result from normal plant operation, will also affect their ability to provide high-pressure injection. It is essential that system aging be understood, and detected, before it results in the inability of the system to perform its safety-related function.
The FMEA analysis for Chemical Volumetric Control System (CVCS) is summarized in Appendix 01. Grove and Travis (1995) developed the FMEA and the "expert" the numbers for O, S and D.
4.1 - Fuzzy membership function
Making use of the toolbox simulator of Matlab (2000), the expert was invited to define each membership function and the values in the universe of discourse using the interpretations of the linguistic terms described in Table 2 (Pillay and Wang, 2003). The expert chose the triangular membership function (a, b, c). After that, the following question may be answered by the expert: "Which elements x (a,b,c) have the degree of membership ~ a = zero, ab = one and ~tc= zero". Direct methods with one expert (Klir and Yuan, 1995) were used. The five linguistic terms describing the input are Remote (R), Low (L), Moderate (M), High (H) and Very High (VH), and for output are lowly (LL), Low (L), Fairly Low (FL), Moderate (M), Fairly high (FH) and High (H). The membership functions of the five linguistic terms to input are shown in the Figure 3. The six membership functions for output in Figure 4. The graphical representation of membership function to occurrence, severity and not detection are identical and only one, occurrence was shown.
4~
I t~
P~
0 .
t~
t~ F
t',J
r..O
~,"
r_rl
"4
Beg
ree
ef m
embe
rshi
p
r-
r--~
.. .
..
..
..
..
..
.
, t-
i. %
........
........
. ~ ~
.~_
_:.~
r--
........
.......
.....
i,,. ...
........
.....
~ ~
~ ~
" ....
.......
~ -1
-
O
"
,-~=
O =¥ (:
3"
~.-,.
~.-,.
O
(3"
O
O
O p~
c~
L~
1"...3
(...J
Q
¢-
Deg
ree
ef m
embe
rshi
p
I ~
____
~..
_
t '~2
2::~
"T
..... .
......
,..-.
"
..........
......... I
I
I "i"
........
........
........
.. I~
198 AI C. E Guimar6es and C. M. F. Lapa
4.2 - Fuzzy rule base application
Since there are three factors, occurrence, severity and not detection, and five linguistic terms describing each factor, the total number of rules is 125. The total number of rules in the fuzzy rules base is reduced to 14 rules for this system analyzed with extensive FMEA after some simplifications to reduce the numbers of rules of the fuzzy rule base. These rules can estimate the results and are presented
1. If (Occurrence is M) and (Severity is VH) and (Not detection is VH) then (Risk is H) (1)
2. If (Occurrence is M) and (Severity is H) and (Not detection is M) then (Risk is H) (1)
32 If (Occurrence is M) and (Severity is M) and (Not detection is M) then (Risk is FL) (1)
4. If (Occurrence is L) and (Severity is VH) and (Not detection is M) then (Risk is FL) (1)
5. If (Occurrence is L) and (Severity is H) and (Not detection is H) then (Risk is FL) (1)
6. If (Occurrence is M) and (Severity is M) and (Not detection is L) then (Risk is L) (1)
7. If (Occurrence is M) and (Severity is H) and (Not detection is L) then (Risk is L) (1)
8. If (Occurrence is L) and (Severity is M) and (Not detection is M) then (Risk is L) (1)
9. If (Occurrence is L) and (Severity is M) and ~Not detection is M) then (Risk is FL) (1)
10. If (Occurrence as L) and (Severity is R) and (Not detection is L) then (Risk is LL) (1)
11. If (Occurrence as L) and (Severity is L) and (Not detection is L) then (Risk is LL) (1)
12. If (Occurrence as L) and (Severity is M) and (Not detection is L) then (Risk is L) (1)
13. If (Occurrence as R) and (Severity is M) and (Not detection is M) then (Risk is LL) (1)
14. If (Occurrence is R) and (Severity is VH) and (Not detection is M) then (Risk is FL) (1)
Fuzzy FMEA
Table 2 - Interpretations of the linguistic terms for developing the fuzzy rule system.
iiiiiii!iiiiiiii!iiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiii•iiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiii•iii
to be observed
Likely to occur once, but
unlikely to occur more
I I frequently
i : i
Moderate
' if!i; !i iil; ii!i ~!iill i~iiiiiiiiiiii!~ i~ % 1 i!!~i;ii~iiii! ! ? I)!!! i~i~5i~i~i!i~!~!!~i~ii~i~ii~ii~i~iii~!~!ii~!~!~i~ii~!~!i~i!~i!~!~
'~ iiii!iiiiiiiii;i!ii~il iiiiiii~ii!? ~̧ ,~ ~,~ ~i i,ii ~ iiii~iii!iii!!. I~i ~iiiil ~ ~i i~ii:ii~ii?iiiill I ii~ii;i!iiiiii~i!i ii ii~ iiiiiiii~iiiii!i i!ii~i ~!iiii!iiiiiiii~il
Likely to occur more
than once
A failure that has no
effect on the system
performance, the
operator probably
will not notice
A failure that would
cause slight
annoyance to the
operator, but that
cause no deterioration
to the system
A failure that would
cause a high degree
of operator
dissatisfaction or that
causes noticeable but
slight deterioration in
system performance
Defect remains
undetected until the
system performance
degrades to the extent
that the task will not be
completed.
Defect remains
undetected until system
performance is severely
reduced.
Defect remains
undetected until system
performance is affected
1 9 9
200 A. C. F. Guimaraes and C. M. E Lapa
iHigh:: : : I Near certain to occur at I A failure that causes
............ least once s;on~f;cant I ' ~ r : ! : i i i r
, deterioration in
, system performance
. . . . . . . . . . . . . . and/or leads to minor
................................................................................................ inj ies I I u r
i
V e ~ High ~ Near certain to occur
several times
• !ii!ii !i!i! i !iiii i~iiiiii !i:iiiiii i % !ii~!i iiiiii!ii i!iill i iliii !i ii!ii: iiiiiiil i 1 , iiii!! ii,!ii!ili!~!i!i! ii ~iii;i~iiiiiiii!iiii!iiiiiiiiiii~ii:i!i!i!iii!! !iiii!!i! iiiiii!ili!i:iiiii:i!!i!:i~ ~
ii!i!i!!~iii!!!!! i!i~!iiii~ii!iiiii~iiiii~iii,!~iiiil ii!ii!ii!iiiiii!!i!i~i!ii!i!! !!iiiiii!i iiiiiiiliiiill
,!!i~ii~ili I ,! i:i~!~ili!i~i~i!!!i:i!i~i~!i~ili!i!!!i!i ilili~iiiii~ii~ii~ii!i!~i!i!i:ii!~i~i~i iii~i!~!?!ii! ~',
~i~i~:iii~iii!~i!iiiiiii~i!iii~i!!!ii~iiiiiii~i~!~ii!~!!i~i!!~i~iii~!~i~!!iiiiiiiii~
Defect remains
undetected until
inspection or test is
carried out
A failure that would.
seriously affect the
ability to complete
the task or cause
damage, serious
injury or death
Failure remains
undetected; such a
defect would almost
certainly be detected
during inspection or test.
5. RESULTS
In the Table 3 are presented the results for RPN and fuzzy approach. "ID" is component event, RPN and Fuzzy are the risk numbers and Rankingrpn and Ranking_fuzzy are the ranking of RPN and fuzzy methodology, respectively. For example, the components 33, 52, 53, 54, 66, 68, and 69 produce a result of 144 for RPN method and the same Rank_rpn of value 12. Fuzzy approach produces for component 66 the highest risk priority number followed of events 33, 52 and 53 and the lowest risk priority number for events 33, 52 and 53. For events 9, 10, 11 and 12, the defuzzified ranking is 2 and the four events should be given the same fuzzy risk priority number 5. The RPN method, produces a result of 45, 75, 60 and 100 for events 9, 10, 11 and 12, respectively. This means that event 12 has the highest priority followed by event 12, 10 and 9, respectively. High level of uncertainty in the safety analysis data could be representing a problem.
L~
0 0 ~t
.~
.~
4~
~ ~
'l
"-~
~ -1
~ O
~ I~
I~
I~
~
~1~
-,,4 (XI *-,,I 0
0 (Jr~ ~
~ O~
) I'00-P~
4~ O
0 0
0 0
00~
*"I "~'
~(~0 (~
O~ O~
0"~
"10
0 (.~ (J'l O0
O0 0
0 f'n 0"I 0
0 O
0 O
0 Z
0 -
Oo
=11
{0
=I"I I~
,w~
,=i
I'-)
0 b~
~0
~~
~0
~~
~0
~~
~0
~~
--~ "~I O0 O0 I~'-~ ~
O0 "-~ O~ O0 O0 I~O .I~ .I~ I~ .I~ I~3
--~ --~ O~
-I~ -I~ -I~
O0 O00~
i~ 00~
--~ -I~
0 IX3 0
0 0
0 .i~ .i~ O.i~
0 0
I~O ~0
-I~ -I~ -I~
0 0
0 IX3 ~Jn 0
0 0
0
o
o
o
o
o
"rl
Fuzzy FMEA 203
6. CONCLUSION
In this paper a new approach was proposed using the "Fuzzy Inference System" (FIS) applied to estimate "Fuzzy Risk Priority Number" (FRPN) using the expert opinion for quantify linguistic variables. This article introduces in the nuclear area a capable methodology to subsidize new reactor projects through of the fuzzy identification of critical systems and components and possible failure modes.
Another important contribution of this approach to nuclear area is propitiate the building of a linguistic knowledge bases for studies of extension of residual life in aging components. Is important to mention that, the population of commercial nuclear power plants has matured and its principal safety and operational components are under aging process. By the year 2014, forty-eight of the wide world plants will have been operating for forty years (design life expectance).
In this paper, to exemplify the methodology, the extensive Failure Mode & Effects Analysis (FMEA) of Chemical and Volume Control System (CVCS) was used as nuclear power plant application. This was a simple and complete example, where a reduced number of rules in the knowledge base ware necessary to mapping all analysis situations.
According to Table 3, different ranking are obtained using the fuzzy approach proposed in a case of the same value of RPN but with different values assigned for occurrence, severity and not detection. The risk implication may be very different (Bem-Daya and Raouf, 1993 and Gilchrist, 1993). The advantages of the proposed fuzzy rule base for application to FMEA of CVCS can be summarized as follows:
• This fuzzy approach combines (i) expert knowledge and experience for use in an FMEA study,
and (ii) can be used for systems where safety data is unavailable or unreliable.
Converting the scale of RPN traditional in (i) variable linguistic with values defined as input by expert is the great situation and (ii) not force precision and use the system by people without knowledge about interpretations of these linguistic terms. Permitting to use the fuzzy system in a simple way.
ff some change is made in part of system component or sub-component of system analyzed as result of FMEA study, new ranking results after improvements can be obtained so quickly using the "Fuzzy Inference System" (FIS).
In accordance with Grove and Travis (1995) the results of this NPAR (Nuclear Plant Aging Research program) study show that aging degradation and failures has occurred in the CVCS. These failures have not prevented the system from responding as designed in an emergency, but have resulted in normal plant operation perturbations. These occurrences have resulted in unnecessary actuation and operation of other system components in response, cause unnecessary stresses. The results of the plant visits indicate that significant attention is being concentrated on the CVCS, and that maintenance practices are being employed in response to specific component failure histories. However, the larger number of failure events reported to the databases (NPRDS and LER),
204 A. C. E Guimaraes and C. M. F. Lapa
indicating that: system failures are still occurring, highlights the need for continued attention to the Operation and aging of the system.
Future work for risk is the "control system" that can be developed with "Simulink" using FIS and the factor values; occurrence, severity and not detection, where recommendations are used for control factors values.
REFERENCES
Ben-Daya M. and Raouf A. (1993), A Revised Failure Mode and Effects Analysis Model. Int. Journal Quality Reliability Mgmt. v.3 (1), pp. 43 - 47.
Gilchrist W. (1993), Modeling Failure Modes and Effects Analysis. Int. Journal Quality Reliability Mgmt, v.10(5), pp. 11 - 23.
Grove E. J. and Travis, R. J. (1995), Effect of Aging on the PWR Chemical and Volume Control System, NUREG/CR - 5954, BNL - NUREG - 52410, June.
Guimar~es A C. F. (2003), A New Methodology for the Study of FAC Phenomenon Based on a Fuzzy Rule System, Annals of Nuclear Energy, v. 30/7, pp. 853 - 864.
Klir G.J. and Yuan B. (1995), Fuzzy Sets and Fuzzy logic: Theory and Application. New Jersey: Prentice Hall.
Mamdani E.H. and Assilian S. (1975), An Experiment in Linguistic Synthesis with a Fuzzy Logic Controller. International Journal of Man-Machine Studies, v.7, No. 1, pp. 1 - 13.
MatLab 6 (2000), Users Guide of the Fuzzy Logic Toolbox.
Meyer L.C. (1989), Nuclear Plant Aging Research on High Pressure Injection Systems, NUREG/CR-4967. August.
l
Pillay A. and Wang J. (2003), Modified Failure Mode and Effects Analysis Using Approximate Reasoning. Reliability Engineering and System Safety. v.79, pp. 69 - 85.
Fuzzy FMEA 205
Stamatis D. H. (1995), Failure Mode and Effects Analysis - FMEA from Theory to Execution. New York; ASQC Quality Press.
Xu K., Tang L. C., Xie M., Ho S. L. and Zhu M. L. (2002), Fuzzy Assessment of FMEA for Engine Systems. Reliability Engineering and System Safety. v.75, pp.17- 29.
Wang Li-Xin (1993). Adaptive Fuzzy Systems And Control - Design And Stability Analysis, University of California at Berkeley. PTR Prentice Hall.
Zadeh L. A. (1987), Fuzzy Sets and Applications: Selected Papers. New York: Wiley.
App
endi
x 01
- C
VC
S Fa
ilure
Mod
e an
d E
ffec
t Ana
lysi
s (F
ME
A)
ID
1,2
Com
pone
nt
Fai
lure
mod
e F
ailu
re C
ause
s F
ailu
re E
ffec
t
1. F
ails
Ope
n M
echa
nica
l Bin
ding
L
etdo
wfi
Flo
w C
ontr
ol
Val
ves
3,4,
5,6
Reg
ener
ativ
e H
eat
Exc
hang
er
7,8
Ori
fice
Iso
latio
n V
alve
s
9,10
11,1
2
13,
14,
15,
2. F
ails
Clo
se
3. P
lugg
ed T
ubes
4. I
nsuf
fici
ent
heat
tr
ansf
er
5. E
xter
nal
leak
age
6. T
ube
Lea
kage
7. F
ails
Ope
n
8. F
ails
Clo
sed
Los
s o
f ai
r or
ele
ctri
cal
pow
er. S
puri
ous
sign
al.
Cor
rosi
on p
rodu
ct
build
up. B
orn
Bui
ldup
. F
orei
gn m
ater
ial
in R
CS.
S
cale
bui
ldup
on
tube
s.
Cas
ing
crac
k. V
ent v
alve
se
at le
akag
e.
Cor
rosi
on.
Man
ufac
turi
ng.
Mec
hani
cal B
indi
ng
Los
s of
redu
ndan
cy.
Una
ble
to te
rmin
ate
letd
own
flow
.
Los
s of
redu
ndan
cy.
Los
s o
f no
rmal
let
dow
n fl
ow
path
thro
ugh
rege
nera
tive
heat
exc
hang
er.
Red
uced
let
dow
n fl
ow.
Tem
pera
ture
of l
etdo
wn
flow
may
exc
eed
desi
gn
limits
, re
sulti
ng i
n po
ssib
le
dam
age
to d
owns
trea
m
com
pone
nts.
R
educ
ed le
tdow
n fl
oe.
Prim
ary
cool
ant r
elea
se.
No
effe
ct
Los
s of
redu
ndan
cy.
Los
s o
f no
rmal
let
dow
n fl
ow
path
. L
oss
of a
ir o
r el
ectr
ical
B
lock
age
of fl
ow to
VC
T.
pow
er.
Spur
ious
sig
nal
Con
tain
men
t Is
olat
ion
9. F
ails
Ope
n M
echa
nica
l Bin
ding
V
alve
10. F
ails
Clo
sed
Los
s o
f ai
r or
ele
ctri
cal
pow
er. S
puri
ous
sign
al
Los
s of
redu
ndan
cy.
Deg
rade
d co
ntai
nmen
t is
olat
ion.
L
oss
of re
dund
ancy
. L
oss
of n
orm
al l
etdo
wn
flow
pa
th.
Let
dow
n li
ne r
elie
f 11
. Fai
ls O
pen
Set
poin
t dri
ft.
• Pr
imar
y co
olan
t di
scha
rged
va
lve
Mec
hani
cal
failu
re,
to p
ress
uriz
er r
elie
f tan
k.
12. F
ails
Clo
sed
Set
poin
t dri
ft.
Los
s o
f ov
erpr
essu
re
Mec
hani
cal
failu
re,
prot
ectio
n.
13. P
lugg
ed T
ubes
R
educ
ed l
etdo
wn
flow
N
on-r
egen
erat
ive
heat
ex
chan
ger
Cor
rosi
on p
rodu
ct
build
up.
Bor
on b
uild
up.
For
eign
mat
eria
l in
RC
S.
Fai
lure
Det
ecti
on
Met
hods
R
emot
e va
lve
posi
tion
in
dica
tion.
Dow
nstr
eam
fl
ow a
nd t
empe
ratu
re
indi
cato
rs.
Rem
ote
valv
e po
siti
on
indi
catio
n. L
etdo
wn
flow
an
d pr
essu
re in
dica
tors
.
Flo
w in
dica
tor
Reg
ener
ativ
e he
at
exch
ange
r out
let
tem
pera
ture
ind
icat
ors.
Exc
essi
ve m
akeu
p fl
ow
rate
. C
onta
inm
ent
radi
atio
n m
onit
ors
Rem
ote
valv
e po
siti
on
indi
cato
r. L
etdo
wn
flow
an
d pr
essu
re in
dica
tors
. R
emot
e va
lve
posi
tion
in
dica
tor.
Let
dow
n fl
ow
and
pres
sure
indi
cato
rs.
Rem
ote
valv
e po
siti
on
indi
cato
r. A
ppen
dix
J L
eak
test
ing.
R
emot
e va
lve
posi
tion
in
dica
tor.
Let
dow
n fl
ow
and
pres
sure
indi
cato
rs.
Exc
essi
ve u
se o
f m
akeu
p w
ater
. D
owns
trea
m lo
w
flow
and
pre
ssur
e A
SM
E S
ecti
on X
I te
stin
g.
Dow
nstr
eam
flow
and
pr
essu
re in
dica
tors
.
Not
es
Val
ves
are
desi
gned
to
fail
clos
ed u
pon
loss
of
pow
er (o
r ai
r su
pply
)
Sam
e.
Val
ves
desi
gned
to fa
il cl
osed
upo
n lo
ss o
f po
wer
(or
air
supp
ly)
O 3 5
D 5 8
4 5
3
3 4
5
3 4
5
3 8
7
10
10
3 5
3
5 5
3
3 5
4
5 5
4
4 9
3
t~
O E.
ID
16
17,
18,
19
20,2
1
227
23,
24
I Com
pone
nt
Fai
lure
mod
e F
ailu
re C
ause
s F
ailu
re E
ffec
t F
ailu
re D
etec
tion
N
otes
M
etho
ds
Scal
e bu
ildup
on
tube
.
Pres
sure
Con
trol
Val
ve
3 W
ay T
empe
ratu
re
cont
rol
Val
ve
Dem
iner
aliz
ers
14. I
nsuf
fici
ent
Hea
t T
rans
fer.
15. T
ube
Lea
k.
16. E
xter
nal
leak
age
17. F
ails
Ope
n
18. F
ails
Clo
sed
19. F
ails
to O
pen
prop
erly
20.
Fai
ls o
pen
for
flow
on
ly to
VC
T.
21.
Fails
ope
n fo
r fl
ow
only
to d
emin
eral
izer
s.
22. I
neff
ecti
ve io
n or
bo
ron
rem
oval
23. P
lugg
ed
24.
Ext
erna
l L
eaka
ge
Cor
rosi
on.
Man
ufac
turi
ng
defe
ct.
Cas
ing
crac
k. V
ent v
alve
se
at le
akag
e.
Val
ve o
pera
tor
mal
func
tion.
Mec
hani
cal
bind
ing.
L
oss
of
air
or e
lect
rica
l po
wer
. Spu
riou
s si
gnal
.
Val
ve o
pera
tor
mal
func
tion.
Mec
hani
cal
bind
ing.
Val
ve o
pera
tor
mal
func
tion.
Mec
hani
cal
failu
re.
Val
ve o
pera
tor
mal
func
tion.
Mec
hani
cal
failu
re.
Deg
rade
resi
n. I
ncor
rect
re
sin.
Part
icul
ate
cont
amin
atio
n
Cra
cked
ves
sel.
C
orro
sion
. M
anuf
actu
ring
def
ect.
Hig
h ex
it te
mpe
ratu
re m
ay
exce
ed d
esig
n lim
its,
resu
lting
in
dow
nstr
eam
co
mpo
nent
dam
age.
C
onta
min
atio
n o
f C
CW
co
olin
g w
ater
.
Red
uced
letd
own
flow
. [ P
rim
ary
cool
ant
rele
ase.
L
oss
of
redu
ndan
cy.
Los
s of
pre
ssur
e. C
ontr
ol .t
o ] p
reve
nt s
team
flas
hing
. L
oss
of
redu
ndan
cy.
Los
s of
letd
own
flow
. Pos
sibl
e I R
CS
over
pres
suri
zatio
n.
Pres
sure
inc
reas
e in
non
- re
gene
rativ
e he
at
exch
ange
r. R
educ
ed
letd
own
flow
. O
peni
ng o
f do
wns
trea
m re
lief
val
ve.
Pos
sibl
e R
CS
ov
erpr
essu
riza
tion.
L
etdo
wn
prev
ents
from
fl
owin
g to
dem
iner
aliz
ers.
[ F
issi
on p
rodu
ct b
uild
up.
Con
tinuo
us l
etdo
wn
flow
to
dem
iner
aliz
ers.
Pos
sibl
e da
mag
e to
dem
iner
aliz
ers
] due
to
high
RC
S
tem
pera
ture
Pr
imar
y co
olan
t fi
ssio
n pr
oduc
t and
bor
on b
uild
up.
Dec
reas
ed le
tdow
n fl
ow
Prim
ary
cool
ant r
elea
se
outs
ide
of
cont
ainm
ent
Hea
t ex
chan
ger o
utle
t fl
ow te
mpe
ratu
re
indi
cato
r.
CC
W r
adia
tion
mon
itor.
E
xces
s us
e o
f m
akeu
p w
ater
. CC
W s
urge
tan
k le
vel
incr
ease
. L
ow f
low
in
dica
tion
Exc
essi
ve m
akeu
p fl
ow
rate
P
ress
ure
indi
catio
n al
arm
0
ow
pre
ssur
e, h
igh
tem
pera
ture
) R
emot
e pr
essu
re a
nd
flow
indi
cato
rs.
Rem
ote
valv
e po
siti
on in
dica
tor.
P
ress
ure
indi
catio
n al
arm
.
Rem
ote
valv
e po
sitio
n in
dica
tor.
Rem
ote
valv
e po
sitio
n in
dica
tor.
Pro
cess
radi
atio
n m
onito
r. P
roce
ss
sam
plin
g.
Dem
iner
aliz
er
diff
eren
tial
pres
sure
in
crea
se
Loc
al le
ak a
nd ra
diat
ion
mon
itor
s.
10
--..O
ID
Com
pone
nt
25,
VC
T le
vel D
iver
t 26
V
alve
27
Vol
ume
Con
trol
Tan
k
28,
VC
T R
elie
f Val
ve
29
30,
Che
mic
al A
ddit
ion
31
Con
trol
Val
ve
32,
VC
T D
egas
sifi
er V
alve
33
34,
VC
T v
olum
e C
ontr
ol
35
Val
ve
36
Bor
ic A
cid
Tan
ks
Fai
lure
mod
e F
ailu
re C
ause
s F
ailu
re E
ffec
t F
ailu
re D
etec
tion
N
otes
M
etho
ds
25.
Fails
Ope
n to
byp
ass
Val
ve o
pera
tor
Dec
reas
e in
VC
T le
vel.
VC
T le
vel
indi
cato
r.
posi
tion
m
alfu
nctio
n. S
puri
ous
Unp
lann
ed re
leas
e o
f R
emot
e va
lve
posi
tion
si
gnal
, pr
imar
y co
olan
t to
hold
up
indi
catio
n.
tank
s.
26. F
ails
ope
n to
VC
T
Val
ve o
pera
tor
Una
ble
to b
ypas
s.V
CT
for
VC
T le
vel i
ndic
ator
. m
alfu
nctio
n. M
echa
nica
l ad
ditio
nal
cool
ant
Rem
ote
valv
e po
siti
on
failu
re,
trea
tmen
t, in
dic
atio
n.
27.
Ext
erna
l L
eaka
ge
Rel
ease
of p
rim
ary
cool
ant
I VC
T le
vel
indi
catio
n.
outs
ide
of
cont
ainm
ent.
28. F
ails
to O
pen
29. F
ails
Clo
sed
30. F
ails
to O
pen
31. F
ails
Clo
sed
32. F
ails
Ope
n
33. F
ails
Clo
sed
Cor
rosi
on.
Man
ufac
turi
ng d
efec
t. S
etpo
int D
rift
. M
echa
nica
l fa
ilure
.
Setp
oint
Dri
ft.
Mec
hani
cal
failu
re.
Mec
hani
cal
bind
ing.
V
alve
ope
rato
r m
alfu
nctio
n.
Los
s o
f ai
r su
pplie
s.
Spur
ious
sig
nal.
Mec
hani
cal
bind
ing.
V
alve
ope
rato
r m
alfu
nctio
n.
Los
s o
f ai
r su
pplie
s.
Spur
ious
sig
nal.
VC
T li
quid
ven
ted
to
nucl
ear
drai
n sy
stem
. L
oss
of
VC
T c
onte
nts.
D
egra
ded
syst
em
oper
atio
n.
Ove
rpre
ssur
izat
ion
of
VC
T.
Ove
rpre
ssur
izat
ion
of
VC
T
wit
h H
ydro
gen
or
Nitr
ogen
. L
oss
of
Hyd
roge
n an
d N
itro
gen
flow
to V
CT
re
sult
ing
in R
CS
fiss
ion
prod
uct i
ncre
ase.
L
oss
of
over
pres
suri
zatio
n o
f V
CT
Los
s o
f ven
ting
VC
T g
as
mix
ture
to b
oron
recy
cles
de
gass
ifie
r.
VC
T le
vel
decr
ease
. ] H
oldu
p ta
nk le
vel
incr
ease
.
I VC
T p
ress
ure
indi
cato
r
VC
T p
ress
ure
indi
cato
r
VC
T p
ress
ure
indi
cato
r an
d lo
w p
ress
ure
alar
m.
VC
T p
ress
ure
indi
cato
r
VC
T p
ress
ure
indi
cato
r an
d re
mot
e hi
gh-p
ress
ure
alar
m.
34. F
ails
Ope
n M
echa
nica
l bi
ndin
g.
Hig
h pr
imar
y m
akeu
p fl
ow
Low
bor
on
Val
ve o
pera
tor
tO V
CT
. P
ossi
ble
RC
S co
ncen
trat
ion.
Hig
h fl
ow
mal
func
tion,
de
bora
tion
an
d V
CT
leve
l in
dica
tors
. ! 3
5. F
ails
Clo
sed
Sha
ft b
indi
ng.
Val
ve
Low
pri
mar
y m
akeu
p fl
ow
Hig
h bo
ron
oper
ator
mal
func
tion,
to
VC
T.
Pos
sibl
e R
CS
conc
entr
atio
n. L
ow f
low
de
bora
tion,
in
dica
tion
s to
VC
T.
36. E
xter
nal
Lea
kage
C
orro
sion
. L
oss
of
all,
or p
artia
l, T
ank
leve
l m
onit
ors
Man
ufac
turi
ng d
efec
t, vo
lum
e o
f ta
nks.
Los
s of
bo
ric
acid
sup
ply
to V
CT
an
d R
CS
0 3
10
8 10
D 5
to
ID
37,
38,
39
Com
pone
nt
Fai
lure
mod
e F
ailu
re C
ause
s F
ailu
re E
ffec
t F
ailu
re D
etec
tion
N
otes
M
etho
ds
Bor
ic A
cid
Tra
nsfe
r 37
. Fai
ls to
Ope
rate
Sh
aft
shea
r. S
haft
L
oss
of
boro
n ad
ditio
n L
ow f
low
and
pre
ssur
e Pu
mp
seiz
ure.
Mot
or fa
ilure
, ca
pabi
lity.
Los
s o
f al
arm
s fr
om p
ump.
Bor
ic
Ele
ctri
cal
failu
re.
Los
s o
f re
dund
ancy
. B
oric
Aci
d A
cid
Tan
k le
vel
Hea
d.
crys
talli
zatio
n. F
ailu
re o
f in
dica
tors
. B
oric
Aci
d T
ank
heat
ers.
38
. Sp
urio
us S
tart
P
ossi
ble
exce
ssiv
e bo
ron
Pum
p di
scha
rge
pres
sure
ad
ditio
n,
and
flow
indi
cato
rs.
40
Che
mic
al M
ixin
g T
ank
41,
Bor
ic A
cid
Ble
nder
42
F
low
Con
trol
Val
ve
43,
Bor
ic A
cid
Ble
nder
44
O
utle
t F
low
Con
trol
V
alve
45,
46
39. F
alls
to p
rodu
ce
desi
gn o
utpu
t
40. E
xter
nal
Lea
k
41. F
ails
Ope
n
42. F
ails
Clo
sed
43.
Fai
ls O
pen
Spur
ious
ele
ctri
cal
sign
al.
Bor
on c
ryst
alliz
atio
n.
Failu
re o
f pi
ping
hea
t tr
ace.
C
orro
sion
. M
anuf
actu
ring
def
ect.
Mec
hani
cal
bind
ing.
V
alve
ope
rato
r fa
ilure
Los
s of
air
sup
plie
s.
Spur
ious
sig
nal.
Mec
hani
cal
bind
ing.
V
alve
ope
rato
r fai
lure
Los
s of
bor
on a
dditi
on
capa
bilit
y.
Che
mic
al s
olut
ion
spill
. R
educ
ed c
hem
ical
add
ition
ca
pabi
lity
Una
ble
to p
rovi
de re
quir
ed
wat
er m
akeu
p vo
lum
e re
quir
ed f
or n
orm
al p
lant
op
erat
ion.
U
nabl
e to
pro
vide
wat
er
mak
eup
requ
ired
for
no
rmal
pla
nt o
pera
tion.
U
nabl
e to
pro
vide
requ
ired
co
ncen
trat
ion
of b
oric
aci
d to
RC
S w
hen
atta
inin
g a
hot s
hutd
own.
Pum
p fl
ow a
nd d
isch
arge
pr
essu
re in
dica
tors
. R
CS
bo
ron
leve
l sa
mpl
ing.
R
CS
che
mic
al s
ampl
ing.
T
ank
leve
l ind
icat
ors.
Val
ve p
osit
ion
indi
catio
n. M
akeu
p w
ater
fl
ow in
dica
tor.
Val
ve p
osit
ion
indi
catio
n. M
akeu
p w
ater
fl
ow in
dica
tor.
V
alve
pos
itio
n in
dica
tor.
B
oric
aci
d fl
ow re
cord
er.
44. F
aiis
Clo
sed
Los
s of
air
sup
plie
s.
Una
ble
to p
rovi
de
Val
ve p
osit
ion
indi
cato
r.
Spur
ious
sig
nal,
conc
entr
atio
n bo
ric
acid
B
oric
aci
d fl
ow re
cord
er.
solu
tion
dur
ing
hot
shut
dow
n.
VC
T O
utle
t C
ontr
ol
45.
Fai
ls O
pen
Mec
hani
cal
bind
ing.
G
as b
indi
ng o
f ch
argi
ng
Val
ve p
osit
ion
indi
cato
r V
alve
V
alve
ope
rato
r fa
ilure
pu
mps
. H
ydro
gen
inje
ctio
n in
to R
CS.
46
. Fai
ls C
lose
d L
oss
of p
ower
, Spu
riou
s V
alve
pos
itio
n in
dica
tor.
si
gnal
. V
CT
leve
l in
dica
tor.
M
echa
nica
l bi
ndin
g.
47. F
ails
Ope
n 47
, E
mer
genc
y B
orat
ion
48
Val
ves
Los
s o
f fl
uid
flow
fro
m
VC
T t
o ch
argi
ng p
umps
. U
nabl
e to
iso
late
flo
w
from
bor
ic a
cid
tran
sfer
pu
mps
. Ove
r-bo
ratio
n of
R
CS.
Val
ve p
osit
ion
indi
cato
r.
Bor
ic a
cid
tank
lev
el
indi
cato
r.
48. F
ails
Clo
sed
Shaf
t bi
ndin
g. V
alve
U
nabl
e to
pro
vide
V
alve
pos
itio
n in
dica
tor.
op
erat
or m
alfu
nctio
n,
emer
genc
y bo
ratio
n.
Bor
ic a
cid
tank
lev
el
indi
cato
r.
Not
sto
rage
tan
k.
Che
mic
al s
olut
ion
mad
e an
d ad
ded
to R
CS
as
need
ed.
O
3 5 3
D 8
t,q
to
iD
49,
Cha
rgin
g P
umps
50
, I (
Cen
trif
ugal
and
51
po
siti
ve d
ispl
acem
ent
pum
ps)
Com
pone
nt
Fai
lure
mod
e F
ailu
re C
ause
s
52,
Cha
rgin
g P
umps
53
, i O
utle
t Che
ck V
alve
s 54
49. F
ailu
re to
ope
rate
co
ntin
uous
ly.
Sha
ft s
hear
. Sha
ft
seiz
ure.
Mot
or fa
ilure
.
55,
Cha
rgin
g Pu
mp
Flow
56
C
ontr
ol V
alve
57,5
8 C
harg
ing
Flow
.
Isol
atio
n V
alve
50. D
egra
ded
Ope
rati
on
51. S
puri
ous
Star
t.
52. F
ails
to o
pen
53. F
ails
to o
pen
full
y.
54. F
ails
to c
lose
.
55. F
ails
Ope
n.
56. F
ails
Clo
sed.
57. F
ails
Ope
n.
Los
s of
pow
er.
Los
s of
su
ctio
n he
ad.
Bor
on c
ryst
alli
zati
on.
Spur
ious
Sta
rt.
Bro
ken
inte
rnal
s.
Fati
gue.
Vib
rati
on.
Bro
ken
inte
rnal
s. R
CS
debr
is.
Bro
ken
inte
rnal
s.
Fati
gue.
Vib
rati
on. R
CS
debr
is.
Mec
hani
cal B
indi
ng.
Los
s of
air
or
elec
tric
al
pow
er.
Spur
ious
sig
nal.
Mec
hani
cal b
indi
ng.
Fai
lure
Eff
ect
Fai
lure
Det
ecti
on
Not
es
Met
hods
L
oss
of re
dund
ancy
. U
nabl
e to
pro
vide
cha
rgin
g fl
ow u
nder
nor
mal
op
erat
ing
cond
itio
ns (3
pu
mps
fai
l)
Los
s of
redu
ndan
cy.
Una
ble
to p
rovi
de p
rope
r ch
argi
ng fl
ow in
res
pons
e to
ope
rati
ons.
Los
s of
RC
P se
al w
ater
of
cool
ing.
Po
ssib
le e
xces
sive
RC
S ch
argi
ng fl
ow.
Los
s of
red
unda
ncy.
Fa
ilur
e to
pro
vide
des
ired
ou
tput
cha
rgin
g fl
ow a
nd
RC
P s
eal c
ooli
ng fl
ow.
Los
s of
red
unda
ncy.
F
ailu
re to
pro
vide
ful
l flo
w
for
char
ging
and
RC
S co
olin
g B
ackf
low
to p
ump.
Una
ble
to p
rovi
de d
esig
n fl
ow.
Una
ble
to a
utom
atic
ally
ad
just
cha
rgin
g fl
ow
thro
ugh
cont
rol o
f pr
essu
rize
r wat
er le
vel,
char
ging
flow
, an
d R
CP
seal
flo
w.
Una
ble
to a
utom
atic
ally
ad
just
cha
rgin
g fl
ow
thro
ugh
cont
rol o
f pr
essu
rize
r wat
er le
vel,
char
ging
flow
, an
d R
CP
seal
flo
w.
Nor
mal
bor
atio
n fl
ow p
ath
unav
aila
ble.
L
oss
of r
edun
danc
y in
pr
ovid
ing
isol
atio
n of
ch
argi
ng li
ne d
urin
g ac
cide
nt c
ondi
tion
s.
Pum
p ou
tlet
flow
and
pr
essu
re in
stru
men
tati
on.
Cir
cuit
bre
aker
- m
onit
orin
g li
ght.
Pum
p ou
tlet
flow
and
pr
essu
re in
stru
men
tati
on.
Pum
p ou
tlet
flo
w a
nd
pres
sure
ins
trum
enta
tion
. C
ircu
it b
reak
er
mon
itor
ing
ligh
ts.
Cha
rgin
g pu
mps
out
put
flow
and
pre
ssur
e in
dica
tion
.
Cha
rgin
g pu
mps
out
put
flow
and
pre
ssur
e in
dica
tor.
Pum
p op
erat
ing
in
reve
rse.
Cha
rgin
g w
ater
flo
w
indi
cato
r.
Low
cha
rgin
g fl
ow
indi
catio
n.
Rem
ote
valv
e po
siti
on
indi
cati
on,
Onl
y no
rmal
ope
rati
on o
f ch
argi
ng p
umps
is
cons
ider
ed. H
igh-
pr
essu
re in
ject
ion
not
incl
uded
in th
is s
tudy
. S
ame
Sam
e
Val
ve n
orm
ally
full
op
en.
Mot
or o
pera
tor
ener
gize
d up
on
gene
rati
on o
f sa
fety
]i
njec
tion
O 5
D 6
tO
O
ID
59,6
0
61,6
2
63,6
4
65,6
6
67,6
8
Com
pon
ent
Fai
lure
mod
e F
ailu
re C
ause
s F
ailu
re E
ffec
t F
ailu
re D
etec
tion
N
otes
M
eth
ods
58.
Fai
ls C
lose
d.
Sam
e.
RC
P s
eal
wat
er f
low
co
ntro
l va
lve
59. F
ails
Ope
n
Los
s of
ele
ctri
cal
pow
er.
Spu
riou
s si
gnal
.
Mec
hani
cal
bind
ing.
L
oss
of a
ir o
r el
ectr
ical
po
wer
.
Los
s of
nor
mal
cha
rgin
g fl
ow p
ath
flow
bor
atio
n,
dilu
tion
and
coo
lant
m
akeu
p. L
oss
of c
ooli
ng
flow
to
rege
nera
tive
hea
t ex
chan
ger.
Una
ble
to p
rovi
de m
anua
l ad
just
men
t of
RC
P s
eal
wat
er f
low
.
Rem
ote
valv
e po
siti
on
indi
cato
r. L
etdo
wn
tem
pera
ture
flo
w
indi
cato
r. C
harg
ing
wat
er
flow
and
tem
pera
ture
in
dica
tion
VC
T l
evel
in
dica
tion
. R
CP
sea
l w
ater
flo
w
pres
sure
indi
cati
on.
Val
ve d
esig
ned
to f
ail
open
on
loss
of
air
or
elec
tric
al p
ower
to
ensu
re f
low
to
num
ber
1 R
CP
sea
ls.
60.
Fai
ls C
lose
d -
Spu
riou
s si
gnal
. U
nabl
e to
pro
vide
man
ual
RC
P s
eal
wat
er f
low
S
ame.
ad
just
men
t of
RC
P s
eal
pres
sure
ind
icat
ion.
w
ater
flo
w.
RC
P s
eal
wat
er m
otor
61
. F
ails
Ope
n M
echa
nica
l bi
ndin
g.
No
effe
ct o
ther
tha
n to
R
CP
sea
l w
ater
flo
w
oper
ated
val
ve
Los
s of
air
or
elec
tric
al
isol
ate
seal
wat
er f
low
. pr
essu
re i
ndic
atio
n.
9ow
er.
62.
Fai
ls C
lose
d S
puri
ous
sign
al.
I Los
s of
sea
l w
ater
to
RC
P
63.
Fai
ls O
pen
RC
P S
eals
Sta
nd P
ipe
Glo
be V
alve
Sea
l W
ater
R
etur
n H
eade
r R
elie
f V
alve
Mec
hani
cal
bind
ing.
Los
s of
pow
er.
Spu
riou
s si
gnal
. S
etpo
int
drif
t.
Mec
hani
cal
fail
ure
Set
poin
t dr
ift.
M
echa
nica
l fa
ilur
e
Mec
hani
cal
bind
ing.
L
oss
of e
lect
rica
l po
wer
. S
eal
Wat
er
Ret
urn
Hea
der
Glo
be
valv
e
64.
Fai
ls C
lose
d
seal
s. R
CP
d °
age.
P
rim
ary
cool
ant
leak
age.
N
one.
RC
P s
eal
wat
er r
etur
n fl
ow
and
exce
ss le
tdow
n fl
ow
bypa
ssed
to p
ress
uriz
ed
reli
ef t
ank.
Fai
lure
inh
ibit
s us
e of
exc
ess
letd
own
flui
d sy
stem
as
an a
lter
nate
m
eans
of
letd
own
flow
co
ntro
ls.
Los
s of
sea
l w
ater
ret
urn
head
er o
ver
pres
sure
pr
otec
tion
.
Los
s of
red
unda
ncy
of
prov
idin
g is
olat
ion
of s
eal
wat
er a
nd e
xces
s le
tdow
n fl
ow.
65. F
ails
Ope
n
66.
Fai
ls C
lose
d
RC
P s
eal
wat
er f
low
and
pr
essu
re in
dica
tion
. R
CP
ex
tern
al l
eaka
ge.
Val
ve p
osit
ion
indi
cati
on.
Sta
ndpi
pe
leve
l in
dica
tor
Pre
ssur
izer
rel
ief
tank
le
vel
and
pres
sure
in
dica
tion
. V
CT
lev
el
indi
cati
on.
VC
T l
evel
ind
icat
ion
pres
suri
zer
reli
ef ta
nk
leve
l an
d pr
essu
re
indi
cati
on.
Rem
ote
valv
e po
siti
on
indi
cati
on
! 67.
Fai
ls O
pen
Sta
ndpi
pe a
larm
set
to
allo
w a
ddit
iona
l R
CP
op
erat
ion
befo
re
com
plet
e lo
ss o
f se
al
wat
er f
low
.
Val
ve i
s no
rmal
ly o
pen.
M
OV
ene
rgiz
ed t
o cl
ose
the
valv
e up
on r
ecei
pt o
f E
SF
sig
nal
O 6
S 7
D 5
t,,i
t,~
t,~
ID
69,7
0
71,
72,
73,
74
75,7
6
Com
pon
ent
Seal
Wat
er H
eat
Exc
hang
er R
elie
f V
alve
Seal
Wat
er H
eat
Exc
hang
er
Exc
ess
Let
dow
n F
low
C
ontr
ol V
alve
FaiL
ure
mod
e
68. F
ails
Clo
sed
69. F
ails
Ope
n
70. F
ails
Clo
sed
71. P
lugg
ed tu
bes
72. I
nsuf
fici
ent H
eat
Tra
nsfe
r.
73.
Tub
e L
eak.
74. E
xter
nal
leak
age.
75.
Fail
s O
pen
76.
Fail
s C
lose
d.
FaiL
ure
Cau
ses
Spu
riou
s si
gnal
.
Set
poin
t dri
ft.
Mec
hani
cal
fail
ure.
Set
poin
t dri
ft.
Mec
hani
cal
fail
ure.
Cor
rosi
on p
rodu
ct
buil
dup.
B
oron
pre
cipi
tati
on.
For
eign
mat
eria
l in
RC
S.
Sca
le b
uild
up o
n tu
bes.
Cor
rosi
on.
Man
ufac
turi
ng d
efec
t.
No
effe
ct.
Mec
hani
cal
bind
ing
Los
s of
pow
er.
Spur
ious
si
gnal
.
Fai
lure
Eff
ect
Seal
wat
er r
etur
n an
d ex
cess
let
dow
n fl
ow
bloc
ked.
D
egra
ded
deal
-coo
ling
ca
pabi
lity
. P
orti
on o
f se
al w
ater
ret
urn
flow
and
cha
rgin
g pu
mp
min
-flo
w b
ypas
sed
to
VC
T.
Los
s of
sea
l wat
er h
eat
exch
ange
r ov
erpr
essu
re
prot
ecti
on.
Red
uced
sea
l wat
er r
etur
n fl
ow.
Hig
h ex
it te
mpe
ratu
re m
ay
exce
ed V
CT
des
ign
tem
pera
ture
.
Con
tam
inat
ion
of C
CW
sy
stem
. RC
S d
ilut
ion.
No
effe
ct.
Una
ble
to i
sola
te f
low
to
eith
er e
xces
ses
letd
own
heat
exc
hang
er o
r dr
ain
tank
s.
i Una
ble
to u
se t
he e
xces
s le
tdow
n fl
uid
syst
em a
s an
al
tern
ate
mea
ns o
f co
ntro
llin
g le
tdow
n fl
ow,
and
pres
suri
zer
leve
l co
ntro
l
Fai
lure
Det
ecti
on
Met
hods
R
emot
e va
lve
posi
tion
in
dica
tion
. Sea
l wat
er
retu
rn f
low
indi
cato
r.
Hig
h V
CT
tem
pera
ture
. H
igh
seal
wat
er h
eat
exch
ange
r tem
p.
Seal
wat
er h
eat
exch
ange
r pre
ssur
e an
d fl
ow in
dica
tor
Seal
wat
er h
eat
exch
ange
r fl
ow,
tem
pera
ture
, and
pr
essu
re i
ndic
ator
. Se
al w
ater
hea
t ex
chan
ger f
low
, te
mpe
ratu
re, a
nd
pres
sure
indi
cato
r.
Seal
wat
er h
eat
exch
ange
r fl
ow a
nd d
elta
pr
essu
re in
dica
tors
. C
CW
sur
ge t
ank
leve
l in
dica
tor.
P
ress
ure
diff
eren
tial
ac
ross
hea
t exc
hang
er.
Tem
pera
ture
ind
icat
ors.
R
emot
e va
lve
posi
tion
in
dica
tor.
Exc
ess
letd
own
pres
sure
and
te
mpe
ratu
re in
dica
tion
. V
alve
pos
itio
n in
dica
tor.
E
xces
s le
tdow
n pr
essu
re
and
tem
pera
ture
in
dica
tion
.
No
~s
O 6
D 4
ID
77,7
8
79,
80,
81,
82
Com
pone
nt
Fai
lure
mod
e F
ailu
re C
ause
s F
ailu
re E
ffec
t F
ailu
re D
etec
tion
N
otes
M
etho
ds
77. F
ails
Ope
n C
harg
ing
Syst
em
Isol
atio
n V
alve
s
Exc
ess
Let
dow
n H
eat
Exc
hang
er
78. F
ails
Clo
sed.
79. P
lugg
ed t
ubes
80. I
nsuf
fici
ent H
eat
Tra
nsfe
r
81. T
ube
Lea
k
82. E
xter
nal L
eaka
ge
Los
s of
ele
ctri
cal p
ower
. M
echa
nica
l bin
ding
Spur
ious
sig
nal.
Cor
rosi
on p
rodu
ct
buil
dup.
B
oron
pre
cipi
tati
on.
For
eign
mat
eria
l in
RC
S.
Scal
e bu
ildu
p.
Cor
rosi
on.
Man
ufac
turi
ng d
efec
t.
Cor
rosi
on.
Man
ufac
turi
ng d
efec
t.
For
nor
mal
ly o
pen
valv
es,
no e
ffec
t dur
ing
regu
lar
oper
atio
n. H
owev
er, u
nder
ac
cide
nt c
ondi
tion
s, fa
ilur
e re
sult
s in
sig
nal t
o is
olat
e ch
argi
ng li
ne. F
or n
orm
ally
cl
osed
val
ves
fail
ure
resu
lts
in in
adve
rten
t op
erat
ion
of a
uxil
iary
sp
ray
resu
ltin
g in
red
uced
pr
essu
rize
r pre
ssur
e.
For
nor
mal
ly o
pen
valv
es,
loss
of n
orm
al c
harg
ing
flow
pat
h. F
or n
orm
ally
cl
osed
val
ves,
loss
of
abil
ity
to p
rovi
de a
uxil
iary
sp
ray
if re
quir
ed r
esul
ting
I i
n pr
essu
rize
r ove
r-
pres
suri
zati
on.
Red
uced
let
dow
n fl
ow.
Hig
h ou
tlet
tem
pera
ture
.
J Con
tam
inat
ion
of C
CW
sy
stem
. RC
S di
luti
on.
No
effe
ct.
Val
ve p
osit
ion
indi
cati
on. C
harg
ing
flow
indi
cato
r.
Pre
ssur
izer
pre
ssur
e in
dica
tion
.
Val
ve p
osit
ion
indi
cati
on. C
harg
ing
flow
indi
cato
r.
Pre
ssur
izer
pre
ssur
e in
dica
tor a
nd le
vel.
Let
dow
n fl
ow, h
eats
ex
chan
ger
flow
, te
mpe
ratu
re, a
nd
pres
sure
ind
icat
ors.
L
etdo
wn
flow
, he
ats
exch
ange
r fl
ow,
tem
pera
ture
, and
pr
essu
re in
dica
tors
. L
etdo
wn
flow
, hea
ts
exch
ange
r fl
ow,
tem
pera
ture
, and
pr
essu
re in
dica
tors
. Pr
essu
re d
iffe
rent
ial
acro
ss h
eat e
xcha
nger
, te
mpe
ratu
re in
dica
tion
.
D 5
¢q
ba
t.aa