a study on maintenance rule program and its application at … · 2005. 1. 17. · s. 2 delphi ^r ^...
TRANSCRIPT
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KR0101243
KAERI/TR-1680/2000
A Study on Maintenance Rule Program
and Its Application at Korean NPP
Rev.O
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PLEASE BE AWARE THATALL OF THE MISSING PAGES IN THIS DOCUMENT
WERE ORIGINALLY BLANK
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2000
: 2000. 11
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| * j # o ^ (Rev.o)
9«RS(Maintenance Rule : 10 CFR 50.65)[1]s|
(Technical
Specification)^!M 3.?^ §)-SSx|A|^(Allowed Outage Time ; AOT), 7|-i-#
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V. g^HiJ- m^[s\ #•§•
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SUMMARY
I. Project Title
A Study on Maintenance Rule Program and Its Application at Korean NPP
II. Objective and Requirement of the Project
The objective of the project is to understand the effectiveness and the
application method of the Maintenance Rule, which is one of the
performance-based regulations and to propose the effective maintenance and
regulation method.
We expect the safety of a plant can be improved because the performance of
an effective maintenance will reduce the failures of the safety-related systems
due to the improvement of reliability, availability and operability for
safety-related components. Also, the number of the transients will be
decreased. That is, appropriate maintenance is essential to keep the safety of
a plant. Therefore, we began on the research about the Maintenance rule.
Maintenance Rule requires monitoring of the overall continuing effectiveness of
licensee maintenance programs. It ensures that safety-related and certain
nonsafety-related SSCs(Structures, Systems and Components) are capable of
performing their intended functions. Also, for nonsafety-related equipment, it
ensures that their failures, which prevent the fulfillment of safety-related
functions will not occur. Failures resulting in scrams and unnecessary
actuation of safety-related systems are minimized.
Traditional Deterministic Regulation(TDR) is based on the Design Basis
Accident (DBA); on the other hand, the reliability informed regulation is based
on the probabilistic safety assessment. However, reliability informed regulation
would accompany with the risk. To prevent those risks, it needs the support
of the performance-based regulation one of which is Maintenance Rule.
Moreover, the result of the performance-based regulation can support the
plant life extension.
III. Scope and Contents of Project
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The Maintenance Rule has been implemented officially since 1996 in the USA.
Therefore, we survey the Maintenance Rule program and applications
performed in the USA, and also develop a Maintenance Rule program to
apply to Korean Nuclear Power Plants. In addition, we applied the
Maintenance Rule Program to the two pilot systems of Ulchin 3,4 Units
roughly with the Maintenance Rule Program developed in this project.
IV. Results of the Project
We developed the maintenance Rule application Program that is available to
apply to Korean NPPs. Also, we reviewed the feasibility of Maintenance Rule
application on Korean nuclear power plants through the application process for
the pilot systems.
However, we could not catch the effectiveness of Maintenance Rule
performance in direct with the result from the only two pilot systems'
application. But we came to the decision that the Maintenance Rule is
necessary to perform the Risk Based Regulation because the RIR can bring
the reduction of the safety on plant.
And, the side effects of the Maintenance Rule performance is the data
collected for the maintenance rule program application. These data can
support the plant life extension and can be used for reliability informed
regulation.
That is, Reg. Guide 1.174[13] requires the element monitoring as the
requirement of the RIR. The maintenance rule is just the element monitoring.
Also, it is expected that the maintenance rule can help to regulate effectively
through the unified regulation method.
V. Proposal for Applications
We prospect to support the regulatory body and the licensee with the
Maintenance Rule Program developed in this project.
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2
n. §j i
syiv.v. •s-^tm a^°i #§TIISI vi
SUMMARY V
I. Project Title V
II. Objective and Requirement of the Project V
III. Scope and Contents of Project V
IV. Results of the Project VI
V. Proposal for Applications VI
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1. * i^ m^ ssc
SSC
r a s ?i^s. ^^ohns °hg s b|°i-aSSColl CHS- ?||# 7|^# n^sfe
^ l#o| s|-s{- SJ x||*j ^|oi7H#(Chemical and Volume Control System;
CVCS)0|cK
S|-Sf S! «||s|fl|o|?ll*o||Ai I L ^ ^gj(high head injection)-^ 2hasF?j 7 |^o |H, * i -
^ SSKprimary loop cleanup)^ td|oj-g^g 7|^o|cK 5E& bi^iL-y^ziTi lS
(Emergency Core Cooling System ; ECCS)o||Ai H°j-°!-a^lgJ (High Pressure Safety
Injection ; HPSI)^ 2>S5Fa ^ l ^o iJ l , elS^'gj ^ ^ r ^ H #S(fiii safety injection
accumulator)^ u l ^ S ^ S 7|^o|cK a s m § ^ o ^ g ^ g s s c 7 | ^
ssc dS€-level)of|Ai
sscAm A| £Et
5r^ SSCA p A| ^ ^
H|^ ofa#a sscAf2 A| ££^
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ssc§•*! aHAi(Final Safety Analysis Report ; FSAR)oi|Ai §°|sl-3. Si
saa uieha ^ s sscl x [ A i (Emergency Operating Procedure ; EOP)
- ^ SSC
sscs-f-
ssc
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Reactor coolantsystemChemical volumeand control system
- Electric powersystem (AC,DC)
mum.31 fe
- Pressurlzer- PORVs- Steam generators
- Main feedwater system- Steam generators- Turbine- Main steam system
- Instrument air
- Containmentspray system
- Fan coolers~ Isolation
valves- Supporting
Equipment
- Injectlon/reclrculatlon/ - Main feedwatershutdown (I.e.. ECCS) - Auxiliary feedwaler
- Containment - Supporting equipment - Steam generatorbuilding (e.g., service water, - Steam dumps
component coolingwater, ESFAS,electric power, disseigenerators, instrumentair)
* Deviations from which result in accident initiation and safety challenges
- Circulating water system- Component cooling
water system- Service water system- Main condensor
SSC
15 -
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EOP SXKHIAH S H S J I J D U I g
au?
AU3U 2IEAI2! AlS¥ISI Algolfe CH3I NEHOII
ZLH 4 (PSA SSC)
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2. ^ § £ 0 | | n|*|-^ S°j=o| & SSC
SSC» SHrSl-oi, O|# SSCO)|
SSC7|- ?IS£O)| n|*|£. g & - ^ gy«|£LS IPEClndividual Plant Examination),
PSAS^I- SEfe # 2 . ehS?|-^^1 -g-Ccritical safety function system)£| £-s- S £ ^ # #
§1-01 aSthciK
PSAi-|- IPE f- t i S SSCOII msH-M-b 7|7|S § ^ ! 2 S in-feJ^^ei5E(Core Damage
Frequency ; CDF), RRW(Risk Reduction Worth), RAW(Risk Achievement Worth)* @?moi o| §• em
NUMARC 93-01 [2,5]0l|Ai x||A|§|.^. g,^0|cK 0|
fi|o)t£ 27|cHlf-tp#u!£(Large Early Release-Frequency ; LERF) &§\O\\ ^ ®]-§-W
^ X i ^ 7 | 5 # SSK>I 0| 7|^S| 22M^Oll tt|-S|. -g~R-«D£. @CK
•& 7|# MIlAiollAi^ 7|# 7||a-s| ^ $ o S ERAW(Effective RAW) & Q # A^shoj Til
IPE &M CH^O| o)-t! SSColl c
ISHS, Delphi ihS # s l § £ * 1 §7F g ^ g f o|
hcK o| [C
Safety Analysis Report ; FSAR)s| -^
hfe 4=^ 7|7|(Passive equipment)^
oil D|*|fe SS0| s 5!^.^ 2.^©cK ^ , PSA
7|7|# d S ^ P I fl«HA
flaaoii D | * I^ gg=oi ^ ssc,SSC,7|7|,
fe SSC,^ 7|7|
B SSC
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Cp|£o| 7|7|
4JIWFSARa^Afltoii ¥1»J
Sfe t£K
ys7|7i
SSgo] 7|7|
2 a 2 £ °lst|
BOP 7I[£7| 7|
ej{i7|7|s)
713&4I S5a|s^7^^ a ^ i
fiS5(IS7|7|
11
?ltl £011 o|*lfeS§o|
T § ?|7| .
2i£Aia A|OII
FSARei ns
^o7|gg
£57i|S7|7|
Standby I Operating : Passive
°l*lrr AjEH
- 18 "
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7\. Delphi ^7F
Delphi 7 | g e Helmed Gordon^] s|«fl 7HSJ-S HJS
0| gj-^e PSA ££^ IPE
Delphi S 7 H ?|§HAi^ °jxi, ^^\±°.\ o^g 7 |-^# z i s^M A p A| &}^§
7|-^ §yo| nfl,
^t[7\ $\t$M 7|-#x|(weighting factor)cH| S§x|(scale value)*
0| §7|- «hSS| O |fe S 2S\ 7AZ-\. 0^|0||Ait Afi A|
m Delphi S7|-7|- SSt!- H-& § u | ^ S ^ § CH J- SSColt
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2. Delphi oj|
A^Ol| CHS- UJ-S1.Required to shutdown reactor and maintain in safe
shutdown condition2.Required to maintain fuel cladding and/ or the
reactor coolant pressure boundary3.Required to remove atmospheric heat and
radioactivity4.Required to remove heat from the reactorAccident Response TotalAccident Response Total x 3(additional emphasis)
1 .Required to provide primary side heat removal2.Required to power conversion3.Required for primary, secondary, or containment4.Required to provide cooling water, component or
room5.Required to provide electric power (AC, DC power)6.Required to provide other motive or control
powerOnstrument air)Normal Operations Total?rS*l i f = (MH em Ir x 3) + (3&SS fttNRV ratio(aS ?lij£.*l «ls )= Pr§*l § f x 10) / 1128(tJ|eil*l)
7h#*l
4.0*
6.7*
7.3*
9.0*2781
4.7*7.7*4.7*4.3*
6.7*3.7*
31.8112.8
1
Scale
(1-10)
8*
7*
6*
9*
8*8*6*7*
6*5*
"4. PSA 2 f #
SSC
Sl'bGI, NUMARC 93-01 o||Ai JH|A|S|-IJ ° i ^ | g £ g^± 7^|(Risk Reduction Worth ;
RRW), £ IU£ ^ - ^ 7r*l(Risk Achievement Worth ; RAW) na|3. in-fej^^j-u|JE(Core
Damage Frequency ; CDF)« o | # S ^ S^rSrfe ^Ho | cHasjo|cK HB-ju^ o|# § 2
ERAW(Effective Risk
s| 2&«rf§ RAW aAchievement Worth) gj-a#
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(D
£ SSO| S SSC
K o|
h. o| aH, PSA a i
, DG(Diesel Generator), ^ F g ^ l S ^
O|OH, 715
ssc
Oil a|*|fe SISO| a-
o||S MS, ohEH a 3O||Aife ipa| i
90%?r s|fe
o|2|- as B iS°s si^EiSSfM- assw ?IS£o)| D|*| . sso| & ssc
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s. 3.
No.12345678910
*
Mean8.820e-074.329e-073.780e-072.660e-072.520e-072.070e-071.989e-071.649e-071.590e-071.590e-07
*
FV0.10790.05300.04630.03250.03080.02530.02430.02020.01940.0194
*
Cumulative0.10790.16090.20710.23970.27050.29590.32020.34040.35980.3793
Cut SetsHSMVW67576 ISLNR-AC11HR ISBOHSMVWGHDR MXOPHDPLI ISGTRIRVRHSMVWGHDR MXOPHDPLI ISLMTC IATWSFSSKZSIAS ILLFSOPHBISIAS ILLHSOPHHLCLR ILLHSOPHHLCLR IML
•
(2) RRW
NUMARC 93-01 [5]oi| cch=ei, R R W «
fe ?ll?J-4;#2.£(Risk reduction importance)7\
^.(cumulative risk reduction importance)^
. §2.
§mfe RRW r
RRWS , 0|
Z| 7|7|0|| C«
$£r y g £ S PSA
RRW7|- 1.005 O|
fe RRW
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3. 4.
EventHSMVW67576HSMVWGHDRNR-AC11HRHSMPW00102HCCQKCCPAFCVW104849HSMPK00102MFMPM07PFSSKZSISASAFTPS01BAAFTPWO1B2AAFCVW1007AB8ABAFCVW1003AB4ABAFCVW 1012 AB 4 ABHCCQWHPPHSSPPSUMP
:
mean2.94E-042.40E-043.90E-028.90E-052.40E-052.08E-068.52E-052.64E-021.17E-031.50E-021.20E-031.68E-061.68E-061.68E-066.00E-055.00E-05
i
rrw1.13561.08391.05541.03341.03281.03241.03191.02991.02781.02741.02551.02551.02551.02551.02231.0207
•
(3) R A W *
RAW
o| RRW«
^ s 5fe RAW
31
RAW g a
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3. 5. RAW f 2 £ o||
EVENT
AFCVW104849
AFCVW1007AB8AB
AFCVW10 0 3 AB 4 AB
AFCVW1012AB4AB
EDBYW125DC
AFPTK005678
HCCQKCCP
EDBSYDC01B
HSCVWG540123
HSCVWG212347
CVTKBRWTOO
CVCVW30506
HSMVW67576
HSSPPSUMP
HSCVW20506
HSMPW00102
HSMPK00102
HCCQWHPP
HCCQKHPP
HSCVW4 04 05
HSCVW42426
HSMVWGHDR
HSCVWG112343
AFCVW1012B4AB
AFCVW1007B8AB
MEAN
2.08E-06
1.68E-06
1.68E-06
1.68E-06
3.84E-06
2.64E-06
2.40E-05
4.80E-06
1.68E-06
1.68E-06
2.40E-06
2.08E-06
2.94E-04
5.00E-05
2.08E-06
8.90E-05
8.52E-05
6.00E-05
2.40E-05
2.08E-06
2.08E-06
2.40E-04
1.68E-06
1.87E-06
1.87E-06
RAW15069.8678
14804.33
14804.33
14804.33
4712.1089
1474.7272
1325.4577
1077.8596
1055.1975
1055.1975
954.7738
952.9386
406.7416
406.9675
406.0106
364.362364.3073
364.1145
363.6757
361.7929
341.1786
323.5703
320.5644
192.5216
192.5216
:
(4) Effective RAW»
RAW ssc»
SSCOil b|
1 ^ RAW
, RAW
7-lsl-oi
^Hrfe Effective RAW
|(w) (weld inspection importance measure)[10]£r
E. s|£(risk measure)
li(w) = PiX lite)
i°| u[0\E.
o||7r
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Effective RAW(ERAW)
ERAWi =
^ s - 7|7|
7| B7^ Di -E RAWgi* 5>*|e} 7|7| J i g S H S 5§Wl S|S US- S[#0| ^ S 7 |7 | A
S| ERAW SOI Dj ?H§ ^ SicK o||* #0 j , 7|7| A2h BS| Hg«|-#-i- 2|4 P(A)#
0.01, P(B)» 0.001O|B^ 7|-S§m, O| nj|S| RAW* 4 ^ 1, 2B^ t[°i ERAWfe
0.00271- £|CH RAW» U|H§H M OH, BS|
A2j ao| Ci 3 ^ . ZlB-iH^. ERAW«
SSC» d S S f e S0| § u | f l § ^ ! # « fl«H-Hfe
3,4S7|°| PSA H i ^l#o)| c(|5|-a| ERAW2|- RAWOll
-g S 6O||A-| 2i 7 |^A^o i | cut!- ERAWS|- RAW
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S. 6. RAW&F ERAW a 110.
EVENT
NR-HSMV-HL
NR-AC6HR
HSMVW67576
MSCKZTBV
NR-AC11HR
HSMVWGHDR
EGDGR01E
EGDGR01B
EGDGR01A
MFMPM07P
AFTPS01BA
MSSVZRESEAT
HSMPW00102
AFTPS02AB
HCCQKCCP
AFCVW104849
HSMPK00102
EGDGM01E
FSSKZSIASAFTPW01 B2AAFTPW1 007AB8AB
AFTPW1003AB4AB
AFTPW1012AB4AB
HCCQWHPP
HSSPPSUMP
IAACSCM02B
MEAN
1.90E-01
1.40E-01
2.94E-04
1.00E-01
3.90E-02
2.40E-04
5.76E-02
5.76E-02
5.76E-02
2.64E-02
1.50E-02
4.00E-02
8.90E-05
1.50E-02
2.40E-05
2.08E-06
8.52E-05
2.78E-02
1.17E-031.20E-031.68E-06
1.68E-06
1.68E-06
6.00E-05
5.00E-05
2.00E-02
RAW
1.0422
1.0878
406.9675
1.0163
2.2935
323.5703
1.0252
1.0206
1.0201
2.0708
2.7513
1.0001
364.362
2.1362
1325.4577
15069.8678
364.3073
1.022
24.120121.676914804.33
14804.33
14804.33
364.1145
406.7416
1.0009
ERAW
1.98E-01
1.52E-01
1.20E-01
1.02E-01
8.94E-02
7.77E-02
5.91 E-02
5.88E-02
5.88E-02
5.47E-02
4.13E-02
4.00E-02
3.24E-02
3.20E-02
3.18E-02
3.13E-02
3.10E-02
2.84E-02
2.82E-022.60E-022.49E-02
2.49E-02
2.49E-02
2.18E-02
2.03E-02
2.00E-02
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3 .
SSC
S o |g£ (availability)^
(reliability)O|cK flS£ol| a|s|fe ggo | & SSC2|- flS£ol| n|*|fe g®0| *|-& SSC
g CH7|^E||O|| SJ^ SSColl q fHAi ^ ?j|# ££^ 7|^o|| c\\m *)# 7tea- o |§M^£si- ssc ? te -yn« ^=^ 11^21 -y^7|$# -y§&cK 01 cm, n^° i A H ^ I ^ -
oil ^ ^ A i ^
S t ^ £ Si K ^ a , ?iato)| D|x|fe g§o| ^ ^ SSC-^1, a s & S^OIIEJ- SSC 7teo|
foil,
PSAOl|Ai
b | j a § ^ !S t [cK o| an,of Service Time ; OOS Time)* gj-§|-oi ^ A | 7|z]-o^ \J^o\
^§(.j) o| AJ^.7 |$0| *|S 7 teCDF §
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7|7|s| 0|§M^ol[ uJtm flSS. 7|tt|fe. i.0e-6S5. fllt^K ^ , i.0e-8O|S(-B
^ 3|o|EIs|
ZIB|L.|.
-ycH#(demand-based failure rate)^
(demand & time-based) -^EHftS ^ ^ - m AIZ} 7|g(time-based) -ysHfe- Poisson £ s ^ « O|#§Foi §|a y[^tl Un ^ » f
7 | s o^ i - ^ |PE dioiEj DC^ 7j.A|(surveillances)
Poisson
Poisson
x=0
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P(r)O| 1O%(5E& 5%)0|^0|olot Sf2, S ^ S SS#(false alarm rate)
95%) O|&# t ^ S f e r
alarm)o)| 2|
=H# (fail to start) 4!sH#o| qi-^-g- 0.01 SJEO|cK ZLS-JHS 7|-go||si ioo%oii 71-a-ji, ois-sus-s <^# O I # § M 3I&SFS i y i & y- s u s 5% MI
x| 15%, aa | j i 2ei i S - y- Sf-lS 0.1%
oi CK
(Reliability performance criteria)^! g ^ , NUMARCO||Ai § b | » #3|
7|-s- jlS"(maintenance preventable functional failures : MPFFs)£M-
oi mi, 7 |^
NUMARC 93-01 [5]o||Ai^ >g&± ^°\ ^ ^ 7 | § # 7000 1 #o||7|*| S:7j| #^(capability)# £
St
PLG[33]o||Ai *||ehS|ai a l t ^ 3 ^ ^ g s | AH^
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s. 7.
£!£E(Non-risk
;ensitive reactor trip
frequency)
PSA results indicate a
>90% confidence of
meeting and risk levels
kept within 5% of baseline
value
Tr-ft!- ej£(Risk-sensitive
nitiator frequency)
Zero events/3-year
PSA results indicate a
>90% confidence of
meeting could have large
isk impact and likely NRC
concerns
Zero events/3-year
PSA results indicate a
>90% confidence of
meeting could have large
risk impact and likely NRC
concernsRunning average unplanned
capacity loss factorNo more than a 10%
increase in cumulative
annual core damage prob.
or 1yr running average
CDF
Uncertainties in PSA results
preclude more accurate
estimates; NRC reluctance
to accept greater increase
ltd LERF
No more than a 50%
increase in the cumulative
annual large early reliance
frequency or 1 yr running
average LERF
Uncertainties in PSA results
preclude more accurate
estimates; NRC reluctance
to accept greater increase
Zero events/3-year
Should not occur with
three train design and
increased sensitivity to
NRC concerns
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4. £fe7|§ Ho\s\ SS ^(Balancing)
§ <M 0|
o|7|
o||s zj-^Sl- n£HH» #«H - SSH MS, f^m^ S-oi i f i t ^ SJCK Ps ^ , pp# ?j|a|g Sd|oi| o|§H 7 | ^ ^ s s
^ t % t , P,S MA|o)| 7 | ^ 4=S« S l f «|-#o|5|- s ^ , P = PP + Pf s HSSc:F. P,
Pp, Prb IPE ^O||Ai ° j ^ E | ^ 7 | £ A^Oll CH#H|fe ^#SJtO|CK ££ US §U| 0 |§M-^
S ^ , P= U
, P= PP + Pr(Pp)O|cK 0i7|Ai, pp0||
dPf / dPp = 0 | )
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1.464e-07
1.402e-07
1.342e-07
1.236e-07
1.236e-07
1.236e-07
1.080e-07
1.004e-07
9.854e-08
9.450e-08
9.345e-08
9.040e-08
8.946e-08
7.803e-08
7.803e-08
7.200e-08
6.300e-08
4.998e-08
4.998e-08
4.959e-08
4.845e-08
4.800e-08
4.641 e-08
4.454e-08
4.454e-08
4.380e-08
3.780e-08
3.416e-08
3.416e-08
0.1079
0.0530
0.0463
0.0325
0.0308
0.0253
0.0243
0.0202
0.0194
0.0194
0.0187
0.0184
0.0179
0.0172
0.0164
0.0151
0.0151
0.0151
0.0132
0.0123
0.0121
0.0116
0.0114
0.0111
0.0109
0.0095
0.0095
0.0088
0.0077
0.0061
0.0061
0.0061
0.0059
0.0059
0.0057
0.0055
0.0055
0.0054
0.0046
0.0042
0.0042
0.1079 HSMVW67576 ISL
0.1609 NR-AC11HR ISBO
0.2071 HSMVWGHDR MXOPHDPLI ISGTR
0.2397 IRVR
0.2705 HSMVWGHDR MXOPHDPLI ISL
0.2959 MTC IATWS
0.3202 FSSKZSIAS ILL
0.3404 FSOPHBISIAS ILL
0.3598 HSOPHHLCLR ILL
0.3793 HSOPHHLCLR IML
0.3980 AFCVW104849 SDOPHEARLY ILOFW0.4164 HSSPPSUMP ISL0.4343 EDBYW125DC NR-AC1HR ILOOP
0.4514 HSMPW00102 MXOPHDPLI ISGTR0.4678 HSMPK00102 MXOPHDPLI ISGTR
0.4830 AFCVW1007AB8AB SDOPHEARLY ILOFW0.4981 AFCVW1012AB4AB SDOPHEARLY ILOFW0.5132 AFCVW1003AB4AB SDOPHEARLY ILOFW0.5264 HCCQKCCP ISGTR0.5387 MXOPHEBOR IATWS
0.5508 AFOPHALTWT SCOPHSDCOP ILOFW SDOPHLATE-HD1
0.5623 HCCQWHPP MXOPHDPLI ISGTR
0.5738 HSMPW00102 MXOPHDPLI ISL0.5848 AFOPHALTWT ILOFW SDOPHLATE-HD1 MSOPHSR-T0.5958 HSMPK00102 MXOPHDPLI ISL0.6053 CSMPWCSSP ILL0.6149 CSMPWCSSP IML0.6237 HCCQKCCP ISL0.6314 HCCQWHPP MXOPHDPLI ISL0.6375 HSMVW67576 ILL0.6436 HSMVW67576 IML0.6497 AFTPW01B2A EGDGK01ABET ILOOP NR-AC6HR0.6556 LSMVWD61245T ILL
0.6615 HSMVO0675A HSMVO0676B ISL0.6672 HSMVWHHDR IML0.6726 HSMVWDHDR ILL0.6781 HSMVWDHDR IML0.6834 AFCVO1049B SDOPHEARLY ILSSB0.6881 HCCQKHPP MXOPHDPLI ISGTR0.6922 AFOPHALTWT SCMVW65152 ILOFW SDOPHLATE-HD10.6964 AFOPHALTWT SCMVW65354 ILOFW SDOPHLATE-HD1
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11. 3,4 : 3,4 : (2/3)
Prob. FV Cutsets
3,,277e-083.075e-08
222
222
22
22
111
1
1
111
1
1
1
1
111
111
11
1
1
1
1
1
.791e-08
.647e-08
.647e-08
,647e-08.520e-08,428e-08
,405e-08.326e-08.312e-08
,015e-08
,969e-08.943e-08.943e-08.943e-08
.943e-08,873e-08.873e-08
.868e-08
.754e-08
.699e-08
.548e-08
,513e-08
,513e-08,508e-08.508e-08
.508e-08
.452e-08
.448e-08
.448e-08,421e-08
.364e-08
.343e-08
.340e-08
.274e-08
.202e-08
0.00400.
0.0.0.
0.0.
0038
003400320032
00320031
0.0030
0.0.0.
0.
0.0.0.
0,
00
0.0000
002900280028
0025
,0024,0024.0024,0024.0024
.0023
.0023
.0023
.0021
.0021
.0019
0.0019
000
000
00
00
00
.0019
.0018
.0018
.0018
.0018
.0018
.0018
.0017
.0017
.0016
.0016
.00160.0015
0.0.
70047042
0.70760.7109
0.
0.
7141
71730.72040.
0.0.0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0,
0,
0
0.
72347263
72927320
7345
7369
739374167440,746474877510
7533.7554.7575.7594
.7612
0.7631
00
.7649
.7668
0.768600
00
00
00
.7704
.7722
.7739
.7757
.7773
.7790
.7806
.78220.7837
AFCVW104849 MFOPHSUFWP ITRSN SDOPHEARLY-HD2MSOPHEVADV-2 NR-AC7HR ISBO
AFTPS01BA AFMPR02BB SDOPHEARLY ILODCAFCVW1007AB8AB MFOPHSUFWP ITRSN SDOPHEARLY-HD2AFCVW1012AB4AB MFOPHSUFWP ITRSN DOPHEARLY-HD2
AFCVW1003AB4AB MFOPHSUFWP ITRSN SDOPHEARLY-HD2HCCQKHPP MXOPHDPLI ISLAFMPW01A2B AFTPW01B2A SDOPHEARLY ILOFW
AFCVW104849 MFMPM07P SDOPHEARLY ITRSNAFTPS01BA AFMPS02BB SDOPHEARLY ILODCLSMPWLPSIP ILLHCOPVCQHPPA HCSKWHPP MXOPHDPLI ISGTRHCOPVCQHPPB-HD
AFTPS01BA HCCQMAFMP2B SDOPHEARLY ILODCAFPTK005678 SDOPHEARLY ILOFW NR-AFIKAFCVW1003AB4AB MFMPM07P SDOPHEARLY ITRSNAFCVW1007AB8AB MFMPM07P SDOPHEARLY ITRSNAFCVW1012AB4AB MFMPM07P SDOPHEARLY ITRSNCSMPKCSSP ILLCSMPKCSSP IMLAFCVW104849 SDOPHEARLY ILOOPAFOPHALTWT HCCQKCCP ILOFWEDBSYDC01B ILODC
AFOPHALTWT MFMPM07P SCOPHSDCOP ITRSNDOPHLATE-HD1HSMPW00102 IMLHSMPW00102 ILLAFCVW1012AB4AB SDOPHEARLY ILOOPAFCVW1003AB4AB SDOPHEARLY ILOOP
AFCVW1007AB8AB SDOPHEARLY ILOOPAFTPW01B2A HCCQKCCP ILOFWHSMPK00102 IMLHSMPK00102 ILLAFOPHALTWT MFMPM07P ITRSN SDOPHLATE-HD1MSOPHSR-T
AFTPS01BA AFMPM02BB SDOPHEARLY ILODCHCOPVCQHPPA HCSKWHPP MXOPHDPLI ISLHCOPVCQHPPB-HD
AFTPR01BA AFMPR02BB SDOPHEARLY ILODCAFTPS01BA HCCQRCCPB ILODCAFOPHALTWT SCOPHSDCOP ILOOP SDOPHLATE-HD1
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3. 11. IS 3,4 : 3,4 (3/3)
Prob. FV Cutsets
1.183e-081.116G-081.103e-081.102e-081.080e-081.039e-08
1.020e-081.020e-081.020e-081.020e-081.020e-089.855e-099.846e-099.496e-099.496e-099.496e-099.496e-099.496e-099.496e-099.496e-099.496e-099.496e-09
0.00140.00140.00130.00130.00130.0013
0.00120.00120.00120.00120.00120.00120.00120.00120.00120.00120.00120.00120.00120.00120.00120.0012
0.78510.78650.78780.78920.79050.7918
0.79300.79430.79550.79680.79800.79920.80040.80160.80270.80390.80510.80620.80740.80850.80970.8109
AFTPS02AB AFMPR02BB SDOPHEARLY ILSSB.AFTPR01BA AFMPS02BB SDOPHEARLY ILODC
AFOPHALTWT ILOOP SDOPHLATE-HD1 MSOPHSR-TAFTPS02AB EDBSYDC01B ILOCCWCVTKBRWT00 ISGTR
MSCKZTBV MSSVWMSSVALLM ITRSNSDOPHEARLY-HD1T MSOPHSR-THCCQWHPP ILLHCCQWHPP IMLHCCQWCSP ILLHCCQWLPP ILL
HCCQWCSP IML
AFTPS02AB AFMPS02BB SDOPHEARLY ILSSBFSOPVSIAS FSSKZSIAS ISGTR
CSMVW3536 ILL NR-CSMVCCMVWCSHX IML NR-CSMVHSMVW32131 IML NR-HSMV-HL
CSMVW3536 IML NR-CSMVHSMVW60304 ILL NR-HSMV-HLHSMVW69899 IML NR-HSMV-HLHSMVW60304 IML NR-HSMV-HLHSMVW32131 ILL NR-HSMV-HLCCMVWCSHX ILL NR-CSMV
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or
LH
ol
W
M
co"
ORu
co"
o|ni
CM
1*1
II
C\IC\IO'*COlOlOh-lOiocoC\JCOCVICV|{\ICO'—CDCDCD'sJ'lO^—
I I I I I I I I I I I I I I + I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I
cviojT^ T^T--r^co CDco aico c\ico c\i w odc\iai a> to CD m ^ co T- T - i^- co T - T- r co N* - co
UJ II — CU — — — J L _ H — UJ - — : l_zr_Z:_i_r=:
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S 13. 3,4 3,4 (RAW)
Event
123456789
1011121314151617181920212223242526272829303132333435363738394041424344454647484950
ISLMXOPHDPLISDOPHEARLYISGTRILOFWILLHSMVW67576HSMVWGHDRIMLAFOPHALTWTISBOSDOPHLATE-HD1NR-AC11HRILOOPITRSNHSOPHHLCLRILODCIATWSHSMPW00102IRVRHCCQKCCPHSMPK00102AFCVW104849MFMPM07PFSSKZSIASAFTPS01BAMTCMFOPHSUFWPAFTPW01B2ASDOPHEARLY-HD2AFCVW1003AB4ABAFCVW1007AB8ABAFCVW1012AB4ABFSOPHBISIASHCCQWHPPNR-AC1HRHSSPPSUMPCSMPWCSSPEDBYW125DCILSSBAFTPS02ABMSOPHSR-TSCOPHSDCOPILOCCWNR-AC6HREGDGK01ABETAFMPR02BBAFTPR01BAMXOPHEBORAFMPS02BB
Mean
3.000e-033.500e-011.460e-014.500e-035.040e-011.700e-042.940e-042.400e-041.7006-041.450e-031.110e-051.590e-013.900e-026.150e-023.000e+009.350e-043.540e-032.070e-058.900e-052.660e-072.400e-058.520e-052.080e-062.640e-021.170e-031.500e-021.000e-021.300e-021.200e-034.040e-011.6806-061.680e-061.680e-069.700e-046.000e-056.200e-015.000e-054.590e-043.840e-061.500e-031.500e-027.780e-048.480e-041.530e-011.400e-014.800e-033.600e-037.200e-034.850e-033.000e-03
FV
0.22740.19100.15760.13900.12990.12810.12050.07810.07740.06340.05870.05760.05300.04850.04390.03890.03880.03860.03260.03250.03160.03120.03040.02950.02730.02670.02530.02470.02450.02420.02410.02410.02410.02270.02200.02140.02050.01920.01830.01790.01720.01720.01670.01530.01440.01430.01400.01250.01230.0116
RAW
76.57661.35481.922131.75621.1279754.3930410.6014326.4229456.403044.68765292.55081.30482.30521.74060.970742.564211.92691864.2644367.6136122363.03911319.6593367.558414599.15822.089524.33002.75183.50762.877421.42211.035714332.009814332.009814332.009824.3336367.34461.0131410.380642.86354754.866712.90472.131123.118520.67701.08481.08863.95474.87192.72113.52064.8493
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3.
8S|
O| ran^ 4 c ( |o|
zj
7.
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8.
7|7|o|| cHffl-
*£ 7|7|0||
oil
31
7|7|
fe s=o||4!sis. -^^
O| ^ PSA
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- fit^l, 0| S i °S^E i §U| f l§ &A|7|£ho| 2 ^ # ^ 2 | Z| 7i|S0|| cuei-
s t o|#MfeA|?h# Til^acK chg-s as^4=^ l l« 7|^o|| CHS- PSA o\g^ ^^7\
APC) fllt.^O|cK
(0.64*24+0.64*24)*2 = 61.4hrs/2year/train
# 7|s0l| CH& 0 | # # ^ £ ^ 7 | 5 £ £€• g f S ° l 3l£isW PSA 0 | # ^
92.2hrs/2year/trainH^ SSl^K ^ , PSA APC^
^ , PSA SlO)|Ai 7 f f g° ! 7|7|0||
SJ 7|7|0||
l-Sa^K 0|
H§H 2|Z| 1.36E-3[0.498/365]2F 1.14E-2[(2.08*2)
o| §u | f lS MUAgm SiaS. &^| ^ S A| A ^ S - ^ K
P S A A P C ^ ^|Aj§fe gHgJH go| Su | f lS o|SM^A l2i-# ? i l ^sM, MS
cHtHAi^ 35.9hrs/2yr/train, 7|7|^z|^^|#oi | c||3HA-l£- 199.7hrs/2yr/train
PSA
3,4S7|2| ic^j^^eiE. ^ § #7^|fe 34.67%
10 [-a51og 826*10"-11=34.67%
, CDFtee=8.26 x 10~6
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s. 14.
MR
Func
AF1AF1AF1AF1CC1CC1
Component
AFMPM01AAAFMPM02BBAFTPMO1 BAAFTPMO1ABCCMPM002PACCMPM002PB
PSA
MUA
1.76E-31.76E-31.76E-31.76E-32.63E-32.63E-3
PSA
APC
days/
yr0.640.640.640.640.960.96
MR
APC
days/
yr0.4980.4980.4980.4982.082.08
Train-*.
111122
MR APC
MUA
1.36E-31.36E-31.36E-31.36E-31.14E-21.14E-2
MR APC
Hrs/2yr/tr
35.856
199.7
PSA APC
Hrs/2yr/tr
61.4
92.2
PSA
2| 7|7|S|
SSCOll
PSA
7p|o||
XI581
A|n|-c|- 10-g-o.
1=21
18S
PSA
oii
PSA
siK o|
1.1709,
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7-1*1 Poisson
3 1 , fe 96.87%^.
20.54%0|H fe 96.87%?J
e 2.43%^
152|-
15.
ssasfos cuePSA 7IS Ma
AFMPR01AA
AFMPR02BB
AFMPS01AA
AFMPS02BB
AFTPR01BA
AFTPR02AB
AFTPS01BA
AFTPS02AB
CCMPR001PA
CCMPR001PB
CCMPR002PA
CCMPR002PB
CCMPS002PA
CCMPS002PB
PSA
S
3.60e-3
3.60e-3
3.0e-3
3.0e-3
7.2e-3
7.2e-3
1.5e-2
1.5e-2
1.2e-4
1.2e-4
t.2e-4
1.2e-4
i.3e-3
1.3e-3
Sfc A[Lf
Hourly
Hourly
Demand
Demand
Hourly
Hourly
Demand
Demand
Hourly
Hourly
Hourly
Hourly
Demand
Demand
s s ai.50e-4
i.50e-4
3.0e-3
3.0e-3
3.0e-4
3.0e-4
i.5e-2
1.5e-2
5.0e-6
5.0e-6
5.0e-6
5,0e-6
i.3e-3
i.3e-3
afgAiLf
5
5
32
32
20
20
32
32
8760
8760
8760
8760
18
18
1
1
1
1
1
1
1
1
1
1
1
1
2
2
^ S * l
1.1709
0.2688
P(n)%
8.3
20.54
P(n+I)
%
2.43
2.76
P(n)
%
96.87
97.24
n
3
1
n+l
4
2
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4. £ ^
t 34.67%)
5 .
0|0||
SSC 7 | ^ 0 | ^fe-
. o| HH,
SSC 7 | ^ s |
^(Trigger)
o|« fl«H, Su|
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S o| [«|s|
3,427121
3
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4 g-
fe PUMAS-N
SSI-el- S H I1 -
o|g flJi|# #sn
S S 0|
0|S|- g ^ d
of Plant)?ll
SSC
-, o|a|-
BOP(Balnce
XICK
§J
SI
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h 01 &^
§ a ^gjtysoiiAH. £oix|±r ^ a ^ a s s
, |SI, 1ST, AOT, GQA§2| flfll^SHI flsH-Mfe- Reg. Guide 1.174[22]o||
o|S flfll A|ga| 5 2 o £ a i ^A|(eiement monitoring)* 2.^§F
So| sscc^l cHfi ^ f e ^ A | 0 | H ^ uhs o|o)| « H 9 S D K z i B i n s g
STI/AOT #S| S | £ § f i 0|S flfl|S| A | ^ ^ 7feS|-7|| S ^ Si
SE&, S « l f f S # 4=a«SS* | Data Rule* Su|ffSo||Ai
3! 2a | 3,4s:7|s|
(RPS/ESFAS)£
PSA S | a ^ l ^^|7r SSSI-HS., SXH "34:^1 &E|) gJ S S # aj-gth PSAPSA H I S shgi a-y tMioiiAi ss « | 7 ^ ° S 4*9a-
31 *|a|,
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fe 7|7| £ ^
=- o|Bit!- 4#
a- e¥^^oi PSAfe PSA
*\\ 3
A|0||
A|O]|
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5 g- s ^ a1?- s-»
Sga(2J 2^3 ^ ^ ^ I S b in-y^^BJHtCore Damage Frequency; CDF),
^A|-^ip#H15.(Large Early Release Frequency; LERF),
O|£|-
A|O|| i s
PSA
-s7|5 A|-0|2|
PSA H I M ^HSsHo^ # 5!o|cK
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6 9
1. U.S. Nuclear Regulatory Commission, 10 CFR 50.65, "Requirement for
Monitoring the Effectiveness of Maintenance at Nuclear Power Plants", 1991. 7
2. Nuclear Management and Resource Council, NUMARC 93-01, "Industry Guideline
for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants, Rev.1",
1993. 5
3. U.S. Nuclear Regulatory Commission, Regulatory Guide 1.160, "Monitoring the
Effectiveness of Maintenance at Nuclear Power Plants, Rev. 1" , 1995
4. NUREG-1526, "Lessons Learned from Early Implementation of Maintenance Rule
at Nine Nuclear Power Plants," 1995. 6
5. Nuclear Management and Resource Council, NUMARC 93-01, Rev.2, "Industry
Guideline for Monitoring the Effectiveness of Maintenance at Nuclear Power
Plants, Rev.2", 1996. 4
6. U.S. Nuclear Regulatory Commission, 10CFR 50.63, "Loss of All Alternating
Current Power,"(Station Blackout Rule)
7. D. Mauldin, S. Boardman, 10 CFR 50.65 Maintenance Rule Implementation, The
Nuclear Power Industries Joint Emergency Diesel Generator Owners Group
Conference, 1997. 6
8. NEI 96-03 "Industry Guideline for Monitoring the Condition of Structures at
Nuclear Power Plants"
9. NUREG/CR-5695, "A Process for Risk Focused Maintenance",
10. Truong V. Vo, Bryan F. Gore, Elizabeth J. Eschbach, Frederic A. Simonen,
"Probabilistic Risk Assessment Based Guidance for Piping In-Service
Inspection", Nuclear Technology Vol 88, 1989. 10, Page 13 -20
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11. Richard G. Allen Jr., 6th International Conference on Nuclear Engineering,
"Implementation of the maintenance rule at the San Onofre Nuclear Generating
Station(SONGS) Program Overview, Benefits, NRC inspection, and
enhancements", 1998. 5
12. Nuclear Management and Resources Council, NUMARC 87-00, Rev. 1,
"Guidelines and Technical Bases for NUMARC Initiatives Addressing Station
Blackout at Light Water Reactors", 1991. 8
13. NRC Reg. Guide 1.174,"An Approach for Using Probabilistic Assessment In
Risk-Informed Decisions on Plants-Specific Changes to the Licensing Basis",
1998.7
14. Inspection Procedure 62706, "Maintenance Rule," 1997. 12
15. Inspection Procedure 62707, "Maintenance Observation"
16. U.S. Nuclear Regulatory Commission, Reg. Guide 1.160, "Monitoring the
Effectiveness of Maintenance at Nuclear Power Plants", 1993
17. » £ ! 3,4 « H & s j e h S ^ S ^ &.3.M, 1997
18. § 3 3 , 4 Sj#2hSg§7|- 2.3.*\, 1997
19. -8£! 3,4
20. EPRI Technical Bulletin 96-11-01 ."Monitoring Reliability for the Maintenance
Rule", 1996. 11
21. EPRI Technical Bulletin 97-03-01 ."Monitoring Reliability for the Maintenance
Rule - Failure to Run", 1997. 3
22. S°IS 2U "I, 2000. 5
23.
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, 1998, 10
24.|, 1999, 10
25. S S I s\,1997, 10
26. a?PI SI, "S7|gg^7| oi^Oll p^# RPS/ESFAS|, 1999, 10
27. ?J^& ai,1998, 10
28. Aio|s S|, "984^ 1 Sf#^HS|, 1998, 10
29. UCHU SJ, "#Sl, 1998, 10
30. ,
X|-^oj-S|, 9 8 ^ ^ | £ [ # ^ S 2 | , 1998, 10
31. INPO AP-913, "Equipment Reliability Process Description", 2000. 3
32. IAEA, "Periodic Safety Review of Operational Nuclear Power Plants", SafetySeries No. 50-SG-012, A Safety Guide, Vienna, 1994
33. IAEA, "Training Course on Risk-Based Optimization of Tasks and Procedures in
NPP Operationdncluding Plant Design/Modification)", 1995. 7
34. J.T. Hawley, M.A. Melnicoff, "Calculation No.: BRW-97-0938-N : PSA Basisfor Braidwoods Maintenance Rule Performance Criteria", ComEd., 1997. 10. 16
35. G.P. Rozga, "Calculation/Addendum Title : PSA Assessment of MR APC and
RPC", Southern Co. 1998. 12.
36. EPRI TR-105396, "PSA Applications Guide", 1995. 8
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1 . fl*ll *l£|>M(Reg. Guide) 1.160
NRCfe- 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities"
s| 50.65 Hol|A-|, "Requirements for Monitoring the Effectiveness of Maintenance at
Nuclear Power Plants"^. 1991^ 7S 10S!
r:n 2 ass-(Reliability), o|g£(Availability)
, 0| S^l- M^IS^I(Transient) Mil
^ A p t 2£H
s| 2 S § #o|fe 5 j§ NRC2| ^#gHH(Defense in Depth) *So||Ai2|
S»H. ei-a^a sscej- saa- ui-ei-aas SSCOII
nn, ui-eta^a sscsi ^is-as JSH ei-aaa ? i ^
NUMARC 93-01 [2],"Industry Guideline
for Monitoring the Effectiveness of Maintenance at NPPs"-!- ^ l -^SitK o| X | * J A ^
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NUMARC01H s ^ s i o i NRC I S § £ S NUMARCO||Ai g # gj
NRCfe- Reg. Guide 1.160# *l|A|iJ-o.SM| NUMARC 93-0101
1995^011 10 CFR 50.652I (a)(3)Sf B>S& Reg. Guide 1.160 Rev.1[3]«
(1) ^ 2 ^ , 7I IS, 7 j | ^ % 7|7|
fe 7|7| ,
EH (plant), ?l|#(system) Sfe- ^|^(train) ^5o||AHo| ^x\y[ o|-f-CH<EJcK
safety-significant)
(low safety-significant standby) SSCOil c^fHAife fi.# ?j|# SE
safety-significant) 7|-i- ^»J SSCOil
(performance criteria)-^ i-§-^ho
(2)
n|.# ^A|(surveillances), A|§H|-
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(4)
NUMARC 93-
risk-significance^r non risk-significance^.
(5)
^ NUMARC 93-01 s| ?H§&
S S gJ-a(Safety significance ranking methodology)
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2. StilflS * i§ T U ^*\M : NUMARC 93-01
NUMARC 93-01, "Industry Guideline for Monitoring for the Effectiveness of
Maintenance NPPs[2]",€- 10 CFR 50.65[1]£r Reg. Guide 1.160[3]o||A-j -ygSI-JL &
NUMARC 93-01 [2]S|
ssc» m^ss ^fi-sfeEii, eraas sscoii^*W(EOP), ^ a 7 p | s s ( M a s t e r Equipment List) #S|
K o| g § b | f l S s |§ cH-feKfliAH fl|a|Sfe s s c ^ S^H a s
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Facilities) ||0|Dh
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fe SSC # ?llj£o|| a|*|fe. g®o| ^ SSC
level)2|
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CDF(Core Damage Frequency), RAW(Risk Achievement Worth )# o|g§|-o^
(1)
s| RRW» n&ste., o|
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£]£}• RRWfe
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3.
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reporting
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, OOS(Out of Service) o|^o| f£5|-c[ . ^Ms|S. sF^#
TR(Trouble Reporter TrMi± PIF(Problem Identification Forms)£ £j x|-S
(2)
(3) ^ ^ 7|
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(4) £ ^
L-K Pilgrim
(1) S H R S ^ § m^ §l Sliisoil S&o| SSC
NUMARC 93-
SSC2r ^ IS£^I o|*lfe SSO| s SSC
(2) ^ ^
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function)^ ^^I IA I1 ^r Sl^h. ^ l » S S , IPEO||Ai "diesel driven fire pump fail to
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s| ftp I an sol q .
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(3) ^^(Trigger)
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PVNGS (1/2)
Maintenance Rule Annunciator Report for January, 1997
High Risk Significant Systems
AF/CT
ARCDCH
DG/DF/HEMPEECEWFTFWGT/NE
HjNANCNKNNPBPGPHPKPNRCSASBSF
SG
SI/XO
SP
we
Auxiliary Feedwater
Condenser Air RemovalCondensateChemical & Volume Control
Class IE Standby GenerationEssential Chilled WaterEssential Cooling WaterMain Feedwater Pump TurbineFeedwaterGas Turbine Generator 1 & 2
HVAC - Control BuildingNon-Class IE 13.8kv AC PowerNuclear Cooling WaterNon-Class IE 125 VDC Power SystemNon-Class IE Instrument AC PowerClass IE 4.16 kv PowerClass IE 480 VAC Power SystemClass IE 480 VAC Power MCC SystemClass IE 125 VDC Power SystemClass IE 120 VAC Power SystemReactor CoolantEngineered Safety Feature ActuationSystemReactor ProtectionSteam Bypass Control
CEDMCSFeedwater Control SystemReactor Power Cutback
Main SteamHigh Pressure Safety InjectionLow Pressure Safety InjectionContainment SprayShutdown CoolingSafety Injection TanksIndirect Radioactive ReleaseEssential Spray PondSwitchyard/GridNormal Chilled Water
Train ATrains B/N
APSSCharging PumpsBoration Flow Path
Low Risk Significant Standby Systems
CLESHAHF
Containment IntegritySafety Equipment Status SystemHVAC-Auxiliary BuildingHVAC-Fuel Building
UnitlU Ra a• D
DPDPD@
D D
UnitlU R
Unit2U R• Da a
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D D
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Unit3U RD DD D
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D •
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3. A.1 PVNGS (2/2)
Maintenance Rule Annunciator Report for January, 1997HP
RKQD/QBSS
Hydrogen MonitoringHydrogen RecombinersHydrogen PurgePlant AnnunciatorEmergency Lighting (Site-wide)Nuclear Sampling System
Low Risk Significant Systems With Performance Criteria
PCQFRDSESQ
Fuel Pool Cooling & CleanupIn-Plant CommunicationRadioactive Waste DrainEncore Nuclear InstrumentationRadiation Monitoring
Plant Level PerformanceUnplanned Capacity Loss FactorCO Control OilUnplanned Reactor Trip (1 trip per 7,000 hours in 36 months)Shutdown Performance (No unplanned change to reactivity, inventory, or heatremoval)
0 Established Target Met• 75% of Target or 1st Trigger Reached. Target Still MetO Exceeded Established Target Values for the MonthU = UnavailabilityR = ReliabilityP = Plant
UnitlU R
Unitl
Unit2U R
Unit2
Unit3U R
Unit3
Red Border Denotes System in (a)(l)
t Improving i Declining -»Steady
Performance Reported on a 12 Months RollingWindow
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BIBLIOGRAPHIC INFORMATION SHEET
Performing Org.Report No.
Sponsoring Org.Report No.
Standard Report No. INIS Subject Code
KAERI/TR-1680/2000
Title / Subtitle
A Study on Maintenance Rule Program and Its Application at Korean NPPs (Rev.0)
Project Managerand Department(or Main Author)
Meejeong Hwang, Integrated Safety Assessment Team,
Researcher andDepartment
Kilyoo Kim, Dae-Il Kang, Joon-Eon Yang, Jaejoo Ha,
Integrated Safety Assessment Team,
PublicationPlace
Publisher KAERIPublication
Date2000. 11
Page 110 p. 111. & Tab. Yes( 0 ), No ( ) Size A4
Note
Classified Open( 0 ), Restricted(Class Document
Report Type Technical Report
Sponsoring Org. I Contract No.
Abstract (15-20Lines)
The objective of the Maintenance Rule is to requiremonitoring of the overall continuing effectiveness of
maintenance programs to ensure that safety related and certain1 i censee
nonsafety-related SSCs are capable of performing their intended functions and,
for nonsafety-related equipment failures will not occur that prevent the!
fulfillment of safety-related functions, and failures resulting in scrams andj
unnecessary actuations of safety-related systems are minimized. That is, properj
maintenance is essential to plant safety.
U.S. Maintenance Rule, which was effective July 1996 in USA., was not officially
adopted in Korea by Korean regulatory body. However, since many PSA and IPE have
been performed for NPPs, the philosophy and usefulness of the Maintenance Rule as
well as performance-based regulation are being acceptable.
We survey the Maintenance Rule program and applications in the USA, and also
developed the Maintenance Rule program to apply to Korean NPPs. In addition, we
applied the Maintenance Rule Program apply to Ulchin 3,4 Units roughly with the
Maintenance Rule Program developed in this project.
Subject Keywords(About 10 words)
Maintenance Rule, Prescriptive Regulation, Performance-basedRegulation, SSC, Risk Significant SSC, MPFF, Performance
Criteria, Reliability, Availability, Operability