ML20024G843
| ML20024G843 | |
| Person / Time | |
|---|---|
| Issue date: | 05/01/1991 |
| From: | Ananyev G, Vitkov V NRC - U.S./U.S.S.R. JOINT COORDINATING COMMITTEE FOR CIVILI |
| To: | |
| References | |
| JCCCNRS-WG-8, NUDOCS 9105010164 | |
| Download: ML20024G843 (67) | |
Text
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i NUCLEAR POWER PLANT OPERATIONAL SAFETY INDICATORS V. M. Vitkov and G.
I. Anan'yev Nuclear power plant (NPP) operational safety ludicators must
/1*
encompass spheres of technology and human activity that influence or could influence operation of systems and their components alter-ing the level of condition of nuclear and/or radiation safety of the'NPP.
The indicators must adequately, and if possible, comprehensively reflect levels characterizing NPP safety during their operation.
The indicators must be calculated fairly simply, exclude confusion during their analysis and unequivocally characterize the change in trend in the sector controlled by the indicator.
The task is not being set of defining the comprehensive indi-cator that as a whole guarantees the level of safety, as for example in making a probability analysis of NPP safety, a calculation is made of the probability of core meltdown or release of radionuclides-into the braironment whose magnitude is a certain generalized char-acterization of power unit safety with assigned initial events.
The
_ selection of indicators must be such that their combination makes it possible :o define fairly precisoly the trend for change in.
levels of'different sectors characterizing safety, and to reveal the sectors in which active measures should be taken to improve opera-ting safety.
. Combined with probability analysis which has fairly large indefinitenesses, it becomes possible to define more precisely measures to improve.the quality of operation and safety of nuclear power plantc.
- Numbers in margin indicate pagination in original foreign text.
9105010164 Ob5bt PDR REVQP NROUSUSR 1
'O PDR
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On this basis work was done to select indicators and calculations were made for their quantitative evaluation.
Selection of the indi-cators used the experience of-employing indicators in international practice (indicator system-used in INPO, NRC, UNIPED, WANO).
The indicators were calculated on a computer employing a data base about incidents at-NPP and technical and economic indicators.
At the first stage of creating the system of indicators it was decided to limit ourselves to the following indicators:
1 number of unscheduled shutdowns of the power units reduced to 7000 hour0.081 days <br />1.944 hours <br />0.0116 weeks <br />0.00266 months <br />s-of reactor operation on line; number of actuntions of the reactor protection system reduced-to 7000 hours0.081 days <br />1.944 hours <br />0.0116 weeks <br />0.00266 months <br /> of reactor operation on line;-
number of: unscheduled actuations of-the safety system during oper-1 ator reaction on line; indicator ~of unreadiness of the safety system; indicator-of unreadiness of the operating personnel; use coefficient of the rated power.
Subsequently for development and perfection of the system of
/2 indicators it is proposed that:
methods of calculation be refined of already' employed indicators; thensystem of data collection for calculations be unified; the set-offindicators be expanded by indicators which make it possible to quantitatively assess the-level of environmental protection, the level of maintenance and repair of the NPP equipment,
. safety.of-the fuel components, level of reliability and operability of the system of automated monitoring and control of the reactor.
However because of-difficulties at the initial stage of calcu-
lation and the use of indicators which emerge during collection and analysis of the necessary information, some of the indicators were calculated the first time by simplified formulas.
2
1 1.1.
Number of Unscheduled Shutdowns of Power Units Reduced to 7000 Hours of Operation of the Reactor on Line (Nus) 1.1.1.
The indicator assesses the intensity of unscheduled transitional processes influencing generation of lifetime of the primary NPP equipment, its reliability and safety during operation.
1.1.2, Method of computation.
Calculation of the indicator for the power unit:
N
- 7000 Nus a-To
.where N is the number of unscheduled shutdowns in the reporting period; T
is the operating time of the power unit on line.
o The indicator for the NPP as a whole is calculated as the mean value of indicators for operating power units.
1.1.3.
Data collection.
Data to calculate the indicator may be obtained as a result of analysis and processing of acts of inves-tigating violations at NPP.
All unscheduled shutdowns of the power units and unscheduled reductions in power of the power units >
25% in the space of 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> were considered.
1.2.
Number of actuations of Reactor Protection System Reduced to 7000 Hours of Reactor Operation on Line (Narp) 1.2.1.
The indicator characterizes the intensity of the most serious transitional conditions emerging during power unit opera-tion which have a significant impact on the service life of the
/3 entire reactor.
l
l l
1.2.2.
Method of computation.
Calculation of the indicator for the power unit:
M
- 7000 Narp To M is the number of actuations of the reactor protection system dur-ing the reporting period; T
is the operating time of the power unit on line (critical time).
o 1.2.3.
Data collection.
Data to calculate the indicator may be obtained as a result of analysis and processing of acts of investigating violations at NPP.
For VVER-1000, 440 only actuations of the reactor protection system are taken into consideration that are accompanied by inser-tion into the core of all reactor protection rods simultaneously or sequentially (mode reactor protection system 1 or reactor pro-tection system 2).
For RBMK-1000 only actuations of the reactor protection system are considered with simultaneous insertion of all groups of protec-tion rods.
In contrast to the indicator used in the international orga-nization WANO and in the INPO (United States) the number of emer-gency shutdowns, this indicator considers all ictuations of the reactor protection system, including emergency shutdown of the power unit by the operator from the reactor protection system key, 1.3.
Number of Unscheduled Actuations of Safety Systems During Operation of Reactor on Line 1.3.1.
The indicator assesses the level of operational safety of the power unit since start-up of the main technological safety
. =.
i systems is a sign of rapid thermohydraulic changes in the first or second loops, while start-up of the emergency sources of electricity supply of internal consumption is a sign 'of significant deterior-ation in the condition-of the most'important systems.
1.3.2.
Method of computation.
Computation of the indicator for the power unit:
( P + 3 )
- 7000 Nuas.
To where P is the number-of unscheduled start-ups of the technological safety /4 systems; 3 is the number of unscheduled engagements of emergency sources of.
electricity supply for internal consumption mechanisms of the NPP; To is the operating time of the power unit on line (critical time).
-1.3.3.
. Data collection.
The data for calculating the indi-cator can be obtained as a result of analysis of processing of acts of investigating violations at NPP.
Collection of data for power units with VVER type reactors takes-into consideration all cases of actuation of components of the following safety systems:
systems of emergency addition of high-pressure' boron;
-systems of emergency cooling of the core; systems of1 emergency feedwater; systems of. safety valves of the first loop.. pressure compensator:s
- systems of safety-valves of the steam generator; systems of-forced pressure reduction in the second loop (into high-speed pressure regulator for steam release into the atmcisphere);
system of emergency electricity supply to-consumers of t he second group of reliability of power unit internal consumption..
5 l
c.
.n 1
.In~ collectingsdata-for the number of unscheduled actuations of the safety system for power units with RBMK type reactors all cases of=actuations of components of the following systems are considered:
systems of emergency feed of feedwater; systems of emergency reactor cooling; systems of reliable electricity supply of consumers of the second group of reliability of power unit internal consumption; systems of-protecting the coolant circulation loop from exceeding pressure.
Consideration of the number of actuations of safety systems is similar to that employed in INPO and Uniped.
In order to calculate this indicator data are collected about the -number of unscheduled actuations of the safety systems that
-occurred during operation of the reactor on line.
.l.4.
Indicator of Unreadiness of the Safety Systems 1.4.l.
The indicator numerically assesses the readiness of the' safety--systemo to perform-the required function and the effec-tiveness of the power plant' activity aimed at maintaining a high-leve1Lof operability of the primary safety systems.
Data collection to calculate the indicator is currently only
.being setLup, then calculation of the indicator of unreadiness of the safety systems is made by the following formula:
/5 H
- 7000 Iuss
=
'To
-where H is the number of malfunctions of the safety system channels; To is the operating time of the reactor on line during the reporting period.
6
l
- 1. 4. 3. - Data collection. ~ Data on the number of-mal functions
- l 1
can be'obtained as a result of analysis of processing of acts of i
investigating violations at NPP.
Calculation of this indicator takes into consideration mal-
-functions in-the following safety systems:
l for pWR:
--system of emergency core cooling (active section);
i
--system of emergency core cooling (passive section, hydrocapaci-tance);
--system of emergency injection of high pressure boron;
--system of emergency introduction of high pressure boron;
--sprinkler system;
--system of emergency feedwater;
--system of service-water of important consumers;
--system of emergency electricity supply of consumers of the first and second group of reliability for1NPP internal consumption.
For RBMK:
--system of emergency reactor cooling - (active section);
--system of emergency reactor cooling (cylinder system);
--system of; emergency supply of feedwater;
--sprinkler-cooling system;
--system of electricity supply of. consumers of the first and second group l of reliability of NPP internal consumption;
--system 7of service water-of important consumers.
--1.5.
Indicator of.. Unreadiness of NPP Operating Personnel- (C uop) 1.5.1.
Indicator assesses the technical level of' training of the operating personnel to operate the power unit in its normal
. operating mode in emergency situations.
1.5.2.
Computation method.
The formula for calculating
/6-indicator for a power unit:
7
1 i
(Y+X)
- 7000 Cuop To Y is the number of erroneous actions of the operating personnel which led to disruption in power unit operation; X is the number of ertoncous actions of the operating personnel which led to development of a disruption in the power unit operation; To is the operating time of the reactor on line during the reporting period.
1.5.3.
Data collection.
Data for calculating the indicator can be obtained as a result of analysis of processing acts of inves-tigating violations at NPP.
Active erroneous actions of the personnel are taken into con-sideration that caused a disruption, incorrect actions and inaction of the operating personnel (if they can be precisely defined based on analysis of investigation acts) that were allowed into transitional modes during disruption of NPP operation.
1.6.
Coefficient of Use of the Rated Power (Curo )
1.6.1.
The coefficient of use of rated power characterizes the effectiveness of measures at the NPP to reduce the accident rate at the power unit, and also the impact of dispatcher limitations on NPP operation.
1.6.2.
Method of computation.
The formula for calculating indicators for the power unit E
Curp =
--
- 100%
Py
- To E is the actual electricity generated at the power unit during the reporting period; Py is the power of the power unit according to 8
I the. plan of-maximum permissible power on which the power unit is permitted to operato during a lengthy period; To is the. duration of the reporting period.
The.mean value of the coefficient of use of the rated power of the NPP during the reporting period is calculated as the ratio of NPP power generation during the repotting period to the rated power
{
generation of the NPP.
l
-.1.6.3.
Data collection.
Data to calculata the indicator is
/7 i
taken from the monthly information coming from the NPP in the established order.
Generalized indicators for the NPP are calculated as the mean value of the corresponding indicators of the power units.
As an example these indicators are presented for NPP with PWR' and RBMK type reactors, as well as the Zaporozh NPP (VVER-1000 for five power units), Novovoronezh NPP ( VVER-1000, fifth power unit),
Kursk NPP,(RBMK-1000 four power units), Kola NPP (VVER-440, four power units)..
9
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Number of actuations of reactor protection system (by 7000 h of reactor operation on lino)
VVER-230 (distribution by quarters) 4 qtr 1939 3qtr 1939 0.9j i qtr 1990 2qtr 1990 0.00 0,00 0.00 pyg;py Number of unscheduled changes in power VVER-230 (Distribution'by quarters)
. - 2qtr 1990 3.23 4qtr 1999 3qtr 1989 1.85 iqtr 1990 f
1 0.79 L3sMsM 0.82 f
fen?M '
I'3Nhb:
f@@@@d.
+ 99_ss e 10
Number of malfunctiona of safety system (by 7000 h of reactor operation on line)
WER-2 3 0 (distribution by quarters)
(A ludbl5' d
if 3q tr1939 4 qtr 198) 0.79 0.97 iq tr 1990 2 q tr1990 0,00 0.00 Fesmq Rwss;d Number of unscheduled actuations of safety system '
(by 7000 h of reactor operation on line)
WER-230 (distribution by quarters) f M $
A
/;
2 qtr1990 3.28 i
3 qtr1999 4 qtr 1939 i qtr1990 g
0.00 0,00
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11
Indicator of unreadiness of operating personnel VVER-230 (distribution by quarters) 4 qtr1933 2 qtr1930 J.dd J. (,0
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'M i qtr1990 3 qtr1999 0.90 9.00 C
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t VVER-230 (distribution by quartern) ii 19 tr 1990 N <[
93.97
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Number of actuations of reactor protection system (by 7000 h of reactor operation on line)
WER-213 (distribution by quarters) l 1 qtr 1990 2 qtr1990 3 qtr100, 4 qtr1989 g,71
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.tsea s sq Mumber of unsheduled changes in power WER-213 (distribution by quarters i g tr1990 8.88 b
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spygg I'20 9.80 I
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Number of unscheduled actuations of safety system (by 7000 h of reactor operation on lino)
VVER-213 (distribution by quarters)
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Number of safety system malfunctions (bv 7000 h of reactor operation on line) l VVER-213 (distribution by quarters) i q tr i?90 f.59 nteet:
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O
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2 qtr1990 4qtr 1999 95,og 97.67 1qtr 1990 3 q tr1989 MES$k 77.82 I
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l Number of actuations of reactor protection system (by 7000 h of reactor operation on line)
WER-1000 (distribution by quarters)
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I VVER-1000 (distribution by quarters)
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VVER-1000 (distribution by quarters) o N
t h
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J LA l(f s
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tb 4 q t r1989 i q tr1990 66.36 66.00 2 q tr1990
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RDMK (distribution by quarters) g,4 4 qtr1999 i q tr1990 2qtr1990 3 qtr1989 1.22 1.29 1,28 0.53 u;' w r m:,,
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.. i Number of unscheduled changes in power RDMK (distribution by quarterc)
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l RBMK (distribution by quarters)
[
Yp
'p, t 4"
4 qtr 1939 sqtr1933 1.19 19 tr 1990 29 tr1990 0.00 f?P:W O'"
g,gg Number of safety system malfunctions (by 7000 h of reactor operation on line)
RBMK (distribution by quarters) pY
' ')W b Q
h[
2 q tr1990 4 q tr 1999 q tr 19E.s i q tr 1990 1.35 g, g
.gj{gg 0.21 Es, /l z,
20
Indicator of unroadiness of operating personnel RBMK (distribution by quarters)
Ll f
i pl'\\\\
I iqtr 1990 2qtr1930 3qtr1939 4 qtr1969 1.69 1,68 1.31 h'hb N!hh$
CURP (distribution by quartersq A
RBMK A ),
I 4 qtr1989 iqtr 1990
"' 03 75,18 3qtr1999 2 qtr1990 66,66 WRa%
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Number of actuations of reactor protection system (by 7000 h of operation of reactor on line)
KOL-1 (distribution by quarters) k 1
f I
Sq tr1989 4 atr1989 i qtr1990 2 qt21990 0.00 0.00 0,00 0.00 Number of-unscheduled changos in power KOL-1 (distribution by quarters) t 49tr1989 3.52 y:
..m iqtr 1990 2qtr 1990 3atr1989 0,00 0.00 0.00 22
11 umber of unscheduled actuations of safety system (by 7000 h of reactor operation on line)
KOL-1 (distribution by quarters) 3 q tr1989 4 4t r19!9 14 tr 1990 2 atr1990 0.00 0.00 0.00 0.00 Number of safety system malfunctions (by 7000 h of reactor operation on line)
KOL-1 (distribution by quarters) 3 qtr1989 4 a tr1909 i a tr 1990 20 tr 1990 0.00 0.00 0.00 0.00 23
CURP KOL-1 (distribution by quarters) 14tr1990 100'57 4 q tr1989 68.61 3'"
y 2qtr1993 0
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, Indicator of unroadiness of operating personnel KOL-1 (distribution by quarters) t 8
3atr 1999 44tr 1999
' ! q tr 1990 2qtr1990 0.00 0.00 0.00 0.00 24
Number of actuations of reactor protection system (by 7000 h of ro' actor operation on lino)
KOL-2 (distribution by quarters) 34tr1989 4 a tr1989 la tr 1990 20tr1990 0,09 0.00 0,00 0.00 Number of unscheduled changes in power t
KOL-2 (distribution by quarters) 2 gtr1999 13.13 3 0tr1909 4 qtr1989 I qtr 1990 0.00 0.00 0.00
- y 25
...., -.... -..... -. _ - -. -... -. ~,.
.. _. _ _ _ _. _. _. _ _.. _.. _ _. _ _.. ~. _ _ _. _ _ _ _. _ _ _. _ _ _ -
Number of unscheduled actuations of anfety system (by.7000 h of reactor operation on lino)
KOL-2 (distribution by quarters) i i
3 qtr1989 4 qtr1989 iqtr 1990 2qtr1990 0.00 0.00
'O.00 0.00 Number of safety system malfunctions (by 7000 h o y reactor operation on line)
K0b-2 (distribution by quarters) 29tr1990 13,13 3
3 qtr1989 4qtr1999 19tr1990 0.00' O.00 9.00 t
26 i
... -. - - -...... _..,.,. + _,..
1 t
CURP KOL-2 (distribution by quarters) 4q tr 1989 1 q tr1990 3qtr1929 99.62 100.42 93.30 sW:wm WMs ag:A '
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_3 Indicator of unreadiness of operating personnel KOL-2 (distribution by quarters) 9 2 q tr1990 13.13 cw r- ;
?
3 ctr1989 4 q tr 1989 i c tr1990 0.00 0.00 0.00 me w 27
Number of actuations of reactor protection system (by 7000 h of reactor operation on line)
KOL-3 l distribution by quartevr!
2 a t r1990 3.23 3qtr 1989 4 qtr1999 i qt r 1990 f'
d 0.00 0.00 0.00
$l $II.
Number of unscheduled changes in power
,KOL-3 (distribution by quarters) 2 atr1990 3.23 3qtr 1989 4q tr 1989 iatr 1990 e.co e.ee o.co Em 28
Number of unscheduled actuations of safoty, system (by_7000 h of reactor operation on lino)
I KOL-3 (distribution by quartern) l 3q tr 1989 ~
4atr 1989
!.atr 1990 2atr1990 0.,00
,0.00 0.00 0.00 i
I Number of safety system malfunctions (by 7000 h
).
. of ' reactor operation on line)
KOL $ -(distribution -by quarters) l 3'4tr1989 4qtr 1989 4.29 7.._.
3.33 7-- --- m; iq tr 1990 2 qtr1990 0.00 O.00
...A 29
. =..
j CURP l
KOL-3 (distribution by quarters) 2qtr1990 1 qtr1990 4 qtr1989 93.49 mmau EWaxe.
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$4WN;vN A ;wavev ay49 9#d%
bin:?S$
dM[M NihWMC
$$tMSE',
i NS Db%
- 9 CN 6-v i
Mp#3ph;
- b 3en 3m arn s N99&m:
m' isss 5Em Geb%
4 m 4 % $pQ
' 'Lkth?
W%@
- 9;
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- M@:
- Mt'Rb'dh MPke::
tS W!
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' @6%s At>
R4-N k&S
$4e%Sx s x yh"Q &j E$
,3
>it M^%i yuk M'{ke:e:
.:v, 48 8 q@ctse 3 e@se mseh M:,.
4 M
a g ve,N.
- }ij e spey?c}3@
R$
yi M:
MNNM!$)
'DGWW L ' @MSNg w)aase' teuase s,y
- s 9 >'4'3 *
'\\x ' e ";)..
, M y + ".'c.,
... e :A "
s Indicator of unreadinosa of operating personnel KOL-3 (distribution by quarters) 4 9 tr1989 2 qtrigpo 3.33 3.23 y_MsNN
, - - - _,j ye s
3qtr 1989 A' 'j iqtr 1990 2,
fh3x 9,f y/qyjf 9.00 O.00 30
_=
Number of actuations of reactor protection system (by 7000 h of reactor operation on line)
KOL-4-(distribution by quarters) l 1
3qtr19ap i
4.80 '
19tr 1990 3.35 g
j 4 qtr1989 2qtr1990 1,
0.00 I
j 0.00
.m r
Number of unscheduled changes in power KOL-4 (distribution by quarters) 1qtr 1990 2qtr1990 6.71 6.63 3qt.r 1999 ll
[
4.00 ll I
4{
g 4 q tr1989 yyj 0.00 1_,yyl 1
]
31
Number of unscheduled actuations of safety system (by 7000 h of reactor operation on line)
KOL-4 (distribution by quarters) 3qtr 1989 -
4 qtr1989
-i qtr 1990 2qtr 1990 0.00 0.00 0.00 0.00 Number of safety system malfunctions (by 7000 h k
of reactor operation on line)
/
KOL-4 (distribution by quarters) 19tr1990 6.71 3qtr1989 L
'j 4.00 l
"d i
.s 4 9tr1999 2 9tr1990
- 5.... )
0.00~
i_ _ _ _ _ d.
0.00 32
i i
i CURP 1
KOL-4 (distribution by quarters) iqtr 1990 2 qtr1990 4 qtr1959 95.00 95.68 91.22
.., 7.q 3 qtr1999
)
6'.95
[
5 s
L'
'i l1 s
l i
i s) d
' n.
.s a1 L.
Indicator of unreadiness of operating personnel KOL-4 (distribution by quarters)
F 3 qtr1989 4 q tr1989 i qtr1990 2qtr1990 0.00
.O.00 0.00 0.00 33
Number of actuations of reactor protection system (by 7000 h of reactor operation on lino)
NVO-5 (distribution by quarters) 2 qtr1990 10.22 I 9D#i990 N[s 4 qtr1999 7'ii N N 6.4 p'%
j bY j
3 tri?B9 j
g l
9 j
00
.h.R..d L.....o.j b.. d..
Number of unscheduled changes in power NVO-5 (distribution by quarters) 2 qtr1990 13,63 19 tr 1990 49 #I#
3 qtr1989 10,67 9.62 n%@
MNh ikkk\\
i l
h' MM. l
....... MS t.
34
.. ~.
Number of unscheduled safety system actuations (by 7000 h of reactor operation on line) i NVO-5 (distribution by quarters)
Iqtr1HD 4 qtr1989 7,gg 6.41 mes e 3 qtr1999 gy
]
((M gh i
g l
4.39 e
i 4
')
'8:-
?'
2 qtr1990 xi IC_3) 0.00 m
Number of safoty system malfunctions (by 7000 h of reactor operation on line)
NVO-5 (distribution by quarters) 9 3 qtr1989 4 qtr1989 iqtr1990 2qtr 1990 0.00 0.00 0.00 0,00 35
1 I
CURP NVO-5 (distribution by quarters) 4 q tr 1909 97.50 1qtr1990
- qtr1990 g
(,.,
?4.10
.h.
- NM s t.sai
? q tr1999
$%f
$Q
- g;4 (1,02 MbD
- ;
,f:?ief#
WF8b e s:s.e.., f m, u.n.,N,,
wwe
~<.s-un:;w wm,., ?
M;:w.
m m o o s.s
,.su 4% M a?'
- 1NSs '
SM&b s
'Vc$$'.^0M,
W W
M e48Mt3 cec &, &N vs.KulK.'g a,w,b. ce4 y\\uy3 W
-.4wvaW',a ss n s.. e t%e.
m
.mm Nwsaw s..
N\\$I \\'
hhNk'
')
[$$@D(';
\\ 'hNf\\V
'N%W NEEs' h,\\\\ 0
'EMMNNE.
. NMihNhD
.1 Ni>&NMNO
- neas,
. hams,'
'n d %'
OtM@it M
max
- was rais %
@69%2N s9:3W ub",
myty N RSS'#m*N
- WegNJ, R
T $N3<.
etx4 ram ipMva/O
,NN66-thMMMS bha A U
$$hS'MR.
M$$NAl ORM\\\\i%
thM'hh@l FO' Wh-.
' sir _yt xse-
&&sfibME
%'M4MS,S.
d mo
_m _mv.,,1.__-
v Indicator of unroadiness of operating personnel NVO-5 (distribution by quarters) 4 qtr1999 i qtr1990 3.56
- 3. 3.i y m ;w NN- - -.. _., Ni'
.hY8NhfNO 3 q tr1999 Nt'E
':'2'MN 2 q t r1990
- mac wsws+3
.$m &;ef
$' erie \\'sts' 0,00 M0P 0.00 wv 36
]
)
)
Number of actuations of reactor protection system (by 7000 h of operation of reactor on lino) 1 ZAP-1 (distribution by quarters)
)
b
}
f 3 gtr 1909 4 gtr 1909 i qtr 1990 2 qtr1990 0.00 0.00 0,00 0,00-Number of-unscheduled changes in power-ZAP-1. - (distribution by quarters).
1 qtr1990
+
21.99 a
i aqtr 1990 3.62 S qtr1989 4qtr1999
?
i k
U!k@.
0.00 0.00 l
1$
+s. - _ w 37 i
.--..a4-
.,__,_.-~...._-,._...,,.,._.-._.-,_,___,,,_,,,-__...._,_,.,_m.,,,,.,
11 umber of unscheduled safety system actuations ZAP-1 (distribution by quarters) 3 qtr1989 4 q tr190 iqtr 1990 2 qtr1990 0.00 0 00 0'00
$)
1 umber of safety system malfunctions (by 7000 h 1of reactor operation on lino)
ZAP-1 (distribution by quarters) i qtr1990 5.49 3 qtr1989 4 q t r 1989 2qt r1990 0a
- 0.
- 0.a 38
CURP ZAP-1 (distribution by quarters) 2qtr1990 76.S3 i gtr1990 hh 54.41 l
M
- j W %i
~:
[y ij 3
);
'?
t y
w d
t S qtr1989 4 gtr1999 ji J
4)S)
.i YR 0,00 0.00 2
f
. Indicator of-unreadiness of operating personnel ZAP-1 (distribution by quarters) 19tr1990 10.99
- 1tRt
(
i
. 2 qtr1990 3,62 3 qtr 1999 4 qtr1989 L
i I
sg)#
W
.0,00 0.00 t.
a:
, s 9s m s 39 1
- -.. -. s
.-.,--_-s
-...,.. ~. -..,...... -,. -.
1 Numlier of actuations of reactor protection system (by_7000 h of reactor operation on line)
ZAP-3 (distribution by quarters)
I i
29tr1990 7.60 gs' 4
l 4 qtr1999
^
3.17
!l
.,-5 34tr1909 j
iqtr 1990 p'
]
L 9.90
__j 0.00 sy Number of unscheduled changes in power ZAP-3-(distribution by quarters) 2qtr1990 19tr1990 11.52-
-10.04
- 3qtr1989 m
7.16
,(\\k,D$
4qtr1989 kk 40
l t
11 umber of unscheduled actuations of safety system)
(by 7000 h of reactor operation on line)
ZAP-3 (distribution by quarters) iqtr 1990 13.65 s:s'$da:
Ygeg:
s es ey
@hN $4 35v10 qv
.sarxces
%9
- s@[:fh;$f.e]
2qtr1990 3 qtr1969 4qtriH9 g)wM3 0.00 0.00 0.00 x
m, s w l
11 umber of safety system malfunctions (by 7000 h of) reactor operation on line)
ZAP-3 (distribution by quarters) 3 qtr1989 7.16 4 9 t r1989 ao9xa%:
6.34
'kkh
- 5:sqhs; tqtr1990 a
M&wy E
.W:.A 3'04
,;e jc
.N@%kVL 4MN9%'
$ 61W
- 4ppgg mRMM M9
- e92.
&pgw
$$$ W AR$MS
, ' _43.g, aNMpp@m aw:sJ
' w;
,s wa3&&h qqqqq$,;
iqt r i990 7
gg:
g.,v.,g q.p3gq:3, gge w+ ry:.
gg-
,,swe. cavag
,93, 41
l CURP ZAP-3 (distribution by suarters) j 4 qtr1989 iq tr 1990 99.26 94,94 2qtr1990 hh*9) flggg 80.19 W;
LM
~
- SRhw x
n j
k j
3 qtr1999
- ['
j i
i 32.43 1
s
}
s h?NEN Li
. nn:
0 Indicator of unreadiness of operating personnel ZAP-3 (distribution by quarters) 4 29tr1990 1qtr 1990 11.52 10.24 2sM%
\\
- hhh j
3gtr!989 4 q tr1989
- El
- f O.00 0.00
)
e ss m a:
2 9.
..J 42 a.-.--.
I l
l l
l Number of actuations of reactor protection system (by 7000 h of reactor operation on line)
ZAP-4 (distribution by q.tarters)
Iqtr 1930 3 qtr1989 3 41 3.20
!$${j[$'i?N NM@
jijj;i 2 qtr1990 hjjgy{
4 q tr1999 jg jg 0.00 0.00
$'!pMy Number of unscheduled changes in power ZAP-4 (distribution by quarters) k iqtr 1990 3 qtr19'89 17.06 16.00 jesddi
- xe.m w
, (N 4 qtr1999 i
~j s u, w'
7.31 s!
2 qtr1990 s
N
- 3. 34 1 ~ y*M i
.sgy ' J
?
M 2
in Ajgp@
ihmM6 gg{g sv
- MWh 5.;,, #
bd NEh 15!#!!!P 43
1 Number of unscheduled actuations of safety system (by 7000 h of reactor operation on lino)
ZAP-4 (distribution by quarters) l 1 qtr1990 10.24 say Q xaMD
?
3 qtr1989 3.20
'Issj MMMxs 4 qtr1999 2 qtr1990 9.00 0.00
((
sl Number of safety system malfunctions (by 7000 h of reactor operation on line)
ZAP-4 (distribution by quarters) i qtr1990 17.06 3qtr1989
[
j
?
2 6.40 j
' ' ~
M 4 c t r 1989 J
2 qtr1990 0.k'0 0.00 g
44
l I
CURP ZAP-4 (distribution by quarters)
Iqtr 1990 2qtr 19N 95.92 95.69 3 gtr1999
- MEWi,
, xyM 4N? 35'h;kM
.}4&fS;Mt 7).70 SV('J6)ME'
,Oc$$$R.fst',
way
- 0mmn;s,
,ynyme MS@@f MR}!QA455
' ',"$;M4(+y
',1'VNN&t1 MlKRR.',
5
'g,%vg&b:
49%w 4 qtr.939 uews ww v
wga93A
.mgp$p$5 M3sw 42.80 yagt; g3x p%et W3se; ap\\se
- itM x4
+4mne:
gngs s 49c
\\\\\\Mj)'A@
\\dQ"DeMY 3p'$;kFjj($'
'i;}Ms% 4
.i;s+@tyk:
ge,+tMN wwwyn:
stt sese99 4
@M32:g0
%%3 Sne%@
@psawiga T 1% il N491 nex s
e e%iMW numaw vaem (5:psw 43AA; 4'
,g,
St Sy
+ @N.
siiSM MiSM
. s:x%*n? I fsx gii.
s w
.ema:aa
- d yn 0,Agiquy:
we
$ dyb9s
. Awop-_hm RG p
3 Indicator of unreadiness of operating personnel ZAP-4.(distribution by quarters) 4 q tr 1999 i q tr1990 7.31 6.83 aWs$.%l5
!$\\%kRV
'ssass i $:
sj AWfe g$gp'
, t+$QW c.
3qtr 1985 jf$ge@s 4
+v g
.sppl83R 2$0S55'
$*NiE; 3 e
- axw'6Rt$'MtET e
2"l!w#W):h e
- Gex 2S
, $95#Mse.$1R
,aJ d$$'$y M D
NN$ksI b 3 {.$'h3.{
$86$$$$$2
<* b'$}'x$w sY N
g9(pg99g W ;
.wstRse saw+N d:sWh e;
eqswg
,waaw:-:
MW\\
@'N' O 00 45
~..
Number of actuations of reactor protection system (by 7000..h of operation of reactor on lino)--
KUR-1 (distribution by quarters)
~
3gtr1989 4qtr 1939 1 qtrl990 2 qtr1990 0.00
,0,00 0.00 0.00 Number of unscheduled changes in power
'KUR-1 (distribution by quarters) 3 qtr1989 4 qtr1989 i qtr1990 2 qtr1990 0.00 0.00 0.00 0.00 46
E--
Number of unscheduled actuations of safety system p-(by 7000 h of operation of reactor on line)
KUR-1 (distribution by quarters)
=
b_-
I l
l i
1 3 qtr1999 4 qtr1999 i qtr1990 2q tr 1990 0.00 0.00 0.00 0.00 m
Number of safety system malfunctions (by 7000 h of reactor operation on line)
KUR-1 (distribution by quarters) 3 qtr1999 4 gtr1939 i q tr1990 2 q tr1990 0.00 0.00 0.00 0.00 47
1 CURP KUR-1 (distribution by quarters) 2qtr1990 90.27 iqtr 1990 81.11
"" ~ " ' ' '
[
4 qtri989
'.G# ' &
i j
66.67
' n' q a i.
l L
I 3 9tr1989 I
i 30.86 p
f.
Indicator of unreadiness of operating personnel KUR-1 (distribution by quarters) i q tr1990 3 ?1 p.s j
u aqtr iss?
4 qtr1989 qg gl:
2 9tr1990 0.00 0.00 0.00 r
t_
48
m.
f Number of actuations of reac':or protection system (by 7000 h of' reactor operation on line) i KUR-2 (distribution by quarters) 1 i
3qtr1989 iqtr1990 3.75 3.65 2qtr1990 49tr1999
+
w
-0.00 l
0.00 i
s u - -..a Number of unscheduled changes in power KUR-2 (distribution by quarters)
- H i gtr1990 7.50 h
f 39tr1989 3.65 k
l 3
2qtrig90 4 gtr1939 0.00
. j 0.00 49
Number of unscheduled actuations of safety systemg (by 7000 h of reactor operation on line)
KUR-2 (distribution by quarters) 3 qtr1989 4qtr 1989 iqtr1990 2 qtr1990 0.00 0.00 0.00 0.00 Number-of safety system malfunctions (by 7000 h o-reactor operation on line)
KUR-2 (distribution by quarters) 1 3qtr 1989 4 qtr 1999 i qtr1990 2 qtr1990 0.00 0.00 0.00 0.00 50
CURP KUR-2 (distribution by quarters) 4 qtr1939 102.40 Sqtr 19f9 g3,gg 67.16 i qtr1990
';- - - ~
..m.
');
i 2qtr1990 e
s 3g,4g i
Indicator-of unreadiness of operating personnel KUR-2 (digtribution by quarters) 3 qtr1999 4 qtr1989 i qtr 1990 2qtr 1990 0,00 0.00 0.00 0,00 51
l l
Number--of actuations of reactor-protection system
)
(by 7000 h of coactor operation _on line)
KUR-3 (distribution by quarters)'
2 qtr1990 3.30 3qtr1909 4qtr 1999 19 tr 1990 9
0,00 0,00 0,00 Number of unscheduled changes in power KUR-3 (dis.tr.ibution by quarters) 34 tr1989 6.34 2qtr1990 t
i
~3.30 4
44tr1989 i qtr1990 l
i 0.00 0,00 52
ll Number of unscheduled actuations of safety system)
(by=7000 h of reactor operation on line)
'KUR-3 (distribution by quarters) j l
1
- 3q tr1989 4 q tr1989
- 1 qtr1990 24tr1990 0.00-0.00 0.00 0.00 Number,of safety system malfunctions (by 7000 h of reactor-operation on line)
KUR-3 (distribution by quarters)
~
i 4
S qtr1939 4 qtr1939 iqtr 1990 2 qtr1990 0.,00
,0.00 0.00 0.00 53
CURP KUR-3 (distribution by quarters) i q tr 1990 99.61 2 qtr1990 s qtr1989 89.32
&%W%i 81.01 y"
p Y'Gmh N
4 qtr19B9
's u. 2, x
Mn\\%%iY
.9:
1:
Indicator of unreadiness of operating personnel KUR-3 (distribution by quarters) 3 q tr1989 3.17 s.;.,*,
4 qtr1999 iqtr 1990 2 qtr1990 k m4 0.00 0.00 0.00 54
l l
l Number of actuations of reactor protection system (by 7000 h of reactor operation on line)
KUR-4 (distribution by quarters) 1 I
3at:1999 4 atr1909 i a tr 1990 2a tr 1990 0,00 0,00 0,00 0.00 Number of unscheduled changes in power KUR-4 (distribution by quarters) 3 atr1989 15.54 dd($5 2qtr1990 huii$s 8,40
), M?}
w
's, 1 a tr1990 Auxmgi
_1_
l"e!"""
Ih
_e w Na
- mm
> we p: eew su ss
1 l
Indicator of unreadiness of operating personnel KUR-4 (distribution by quarters) 39tr1989 4 qtr 1989 10tr 1990 20 tr 1993 0.00 0.00 0.00 0.00 CURP KUR-4 (distribution by quarters) iq tr 1990 4 qtr1999 98.35 96.00 l
gggg 2 qtr1990 M&MMW
- s
'5 "gw'E'\\'#'
3 9tr' 989 gygs y
56.12 M WV G M W aMMMR SMMM iss9&Wl
- &WWW MMME MMNM I
d'lM' N,C apgst
- 8Mh2
.v a
s fMMB MMM M$Re'i s
@MmE' hhMM WMh h's
\\
AddMM MME W3M M%WM 4kMMam tRMam&
43RM MRWE
- Wem8#
A%MWM M M x
wav SMMMp AWMM d)h@ynN MWEEC "MMWJi
@$tMW mMM WMMM 4
,MMMW e-:M2M,1
$$sR@M
&w 9
- m39e yv. xx u j
Iwwawt.
mw y_1 56
i l
.I-Number of-sdfoty system malfunctions (by 7000 h of)-
~
' reactor operation on line)
KUR-4 (distribution by quarters) 1
)
2 qtr1990 4.20 39tr1989 4 qtr1989 iqtr 1990
)
l 0.00 0.00 0,00
(
.s
- w. m i
Number of unscheduled actuations of safety system (by 7000 h of reactor operation on line)
KUR-4.(distribution by ' quarters) 34tr1969 4 gtr 1999 iqtr 1990 2 qtr1990 0.00 0.00 0,00 0.00 57
Number of actuations of reactor protection system (by 7000 h of reactor operation on line)
ChER-1 (distribution by quarters) sqtr 1989 4 gtr1989 iqtr 1990
- qtr199g 0.00 0.00 0.00 0.00 Number of unscheduled changes in power ChER-1 (distribution by quarters) 3 qtrt989 7.91 ll
4 atr1989 l atr1990 3.36 3,33 00 58
l Number of unscheduled actuations of safety systent (by 7000 h of reactor operation on line)
ChER-1 (distribution by quarters) 3 4tr1989 4 q tr1999 i qtr1990 2 0 tr1990 0.,00 0.00 0.00 0.00 Number of safety system malfunctions (by 7000 h of reactor operation on line)
ChER-1. (distribution by quarters) r 20tr1990 5.60 34tr1989 44tr 1989 1 atr1990 -
0.00 0.00 0.00 59
i CURP ChER-1 (distribution by quarters) 4qtr 1989 iqtr 1990 93.59 92.78 3 qtr1989 g
g.
3 j{
M,
'i 71.7B s
y h
2 qtr1990 1cvsgj j-i 46.95 e
I'"
3 4
I%%W....
...i F weM Indicator.of unreadiness of operating personnel ChER-1 (distribution by quarters) 1 qtr1990 6.66
- s"
!m f
sh\\W;
)
3 q tr1939 4q tr 1989 2 4 tr1990 0.00 0.00
- e. _._ as:.y/
0.00 60
s..
e.
Number of actuations of reactor protection system (by.7000 h of operation of reactor on line)
ChER-1 (distribution by quarters) 4qtr 1999 4.31 3c tr 1989 '
N h
i q tr1990 2 9tr1990 g'g 0.00.
0.00 0.00 Number of unscheduled enanges in power ChER-2 (distribution by quarters) 4 qtrt989 21.54 2 n,tr1990 17.47 iq tr 1990 8.26 3qtr 1989 i
I I
3.17 h
61
s, Number of unscheduled actuations of safety system (by 7000 h of reactor operation on line)
ChER-2 (Distribution by quarters)
S qtr1989 4 qtr 1989 1 gtr1990 2gtr1990 0.,00 0.00 0.00 0.00 Number of safety system malfunctions '(by 7000 h of reactor operation on line)
ChER'-2 (distribution by quarters) 3qtr1989 4 q tr1989 ig tr 1990 2 q tr1990 0.00 0.00 0.00 0.00 62
- i..
Indicator of unreadiness of operating personnel ChER-2 (distribution by quarters) 1 l
iqtr1990 0.26 l-.,,
4qtr 1939 2 qtr1990 3qtr1989 4,31 3'49 (Wm?
3.17 p
i p
i CURP ChER-2 (distribution by quarters) t 3 qtr 1989 95.47 2 gtr 1990 82.03 m
\\\\\\
i 4 qtr 1989 52.20 s
4 I<J iqtr 1990 22.75
\\
E, ex o
6.
63 j
s.
Number of actuations of reactor protection system (by 7000 h of operation of reactor on line)
. ChER-3 (distribution by quarters) 4qtr 1989 3.73 3 qtr 1989 i gtr 1990 2 qtr1990 j
O 00 0.00 0.00 Number of unscheduled changes in power ChER-3 (distribution by quarters) 4 qtr 1989 11.19 E5' 3 qtr 1909 2 qtr 1990 5.74 4.19 00 64
Number of unscheduled actuations of safety system (by 7000.h of reactor operation on line) 1 ChdR-3 (distribution by quarters) 3 qtr 1989 4gtr 1989 i qtr 1990 2 gtz 1990 0.00 0.00 0.00 0.00 Number of safety system malfunctions (by 7000 h o reactor operation on line)
ChER-3 (distribution by quarters) 2:itr1990
-8.38 u
i:
4 qtr 1989 3.73
,m%vm 3 qtr 1989 1 qtr 1990 l
0.00 0.00 1:
65 09
CURP ChER-3 (distribution by quarters) i gtr 1990 -
102.70 4 qtr 1989 2 qtr 1990 93,70 3
74.00 i
39tr 1989 50,33 sS3whh 3
Indicator of unreadiness of operating personnel ChER-3 (distribution by quarters) 4 3qtr 1989 5.74 5f%k'qkY 4gtr 1989 iqtr 1990 2 gtr 1990 o.ca a.ca mm MM 66
W91)
USNRC GPA/IP-EDO DISTRIBUTION SHEET Joint Coordinating Committee on Civilian Nucioar Reactor Safety (JCCCNRS)
Betwoon the U.S. and the USSR O For Comment By:
O For Information Description of Anachment&
h)V DOCS Ch*ck bon for each recapont
[
U.S. Committee Members:
Rl JCLinville JTaylor, EDO TSpels, RES (WG4)
O R.IV LJCallan
~
EJordan AEOD
~
FMiraglia. NRR O
SRI PPNarbut
~
SRosen, NE 14, USDOE
~
MSchulman, ER 70, USDOE (WG 7)
USDOE DGlossing, NE 14 (WG 11)
~
HJaffe, IE 12
~
EDO JSnlezek GdelaTorre, IE 12
~
JWechselberger State SSmith, EUR/SOV O
GPA HDenton JBosken OES/tRS CEberhard OES/NTS
-~
IP JShea RSenseney, OES/NEC AKenrieke CCampbell, OES/SCT EShomaker
~~
GFovder O
American Embassy Moscow AMHaycraft LWhitney
_/
tral FJ 9 h O
SEC ALSilvious PDR (Rev GP NRG USUSSR-General)
C'POR (Rev GP NnG USUSSR Working Group [}
RES LShao (WG 3)
Not for POR BSheron F141 JCCCNRS Genera!
[
RBosnak (WG 12) g F141 JCCCNRS Working Group
""~
AEOD Dross (WG 5)
C Other(s):
TNovak (WG 8)
KRaglin (WG 9)
NRR MCullingford EButcher (WG 1)
JRichardson (WG 10)
CMcCracken (WG 4)
PMadden AThadant (WG 2)
Rernark s.
9
.J~
'1rd f _
/
1OAh
)
- Note: No Proprietary, Forsonnel Sensative, copyfighted, of Untranslated foreign documents go to NUDOG5 of the PDR. These data go directly to Central Files lot off' lal retention.
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