ML17138A549
| ML17138A549 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 08/31/1978 |
| From: | Becker, Schnabel PENNSYLVANIA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17138A531 | List: |
| References | |
| 2327, NUDOCS 7903150375 | |
| Download: ML17138A549 (54) | |
Text
.
gtIS!'"I'Ir~bO-'38~
QgtIcf0 780'>I5og >Z Rt~mam GREBES as translated I'r'to
..E.
t3.G. L.I. S.K.......
RESULTS OF THE ttGi~l-t'mCLEAR HOT TEST 1'fITH THE RELIEF SYSTEtl Ii'l THE PHILIPPSBUR6 t'UCLL<R POl'tER PLAHT astransla'ed from..G. E.R.
t;1 8,. 8.........
ERGEB'NISSE DES NICHTHUKLEAR"='.1 HEISSTESTS NIT DEIl ENTILASTUAGSSYSTEf1 It1 KERN'(RAFT'I=RA PHI LIPPSBURG I
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"-gQ MOTICE THE ATTACHED FILES ARE OFFICIAL RECORDS OF THE DIVISION OF DOCUMENT CONTROL.
THEY HAVE BEEN CHARGED TO YOU FOR A LIMITEDTIME PERIOD AND MUST BE RETURNED TO THE RECORDS FACILITY BRANCH 016.
PLEASE DO NOT SEND DOCUMENTS CHARGED OUT THROUGH THE MAIL. REMOVALOF ANY PAGE{8) FROM DOCUMENT FOR REPRODUCTION MUST Bf-REFERRED TO FILE PERSONNEl.
DEADLINE RETURN DATE n
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RECORDS FACILITYBRANCH
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PROPRIETARY INFORMATION This document has been made NON-PROPRIETARY by the deletion of that information which was classified as PROPRIETARY by KRAFTWERK UNION AG (KWU).
The PROPRIETARY information deletions are so noted throughout the report where indicated by a)
Use of the term KRAFTWERK UNION AG PROPRIETARY INFORMATION,.
')
Use of blocked out areas by cross hatch bands in the report text and figures/tables, e.g.
i)...." with a mass flow density ofQ~~1Kg/m2s...";
iii) iv)
M~ mm should be kept belowMetm."
8/l7/78
Horking Report Topic:
Results of the non-nuclear hot test with the relief system in the Philippsburg nuclear power plant Reference (e.g., project, RaD project):
Suppression chamber, relief system, test results R 142 - 38/77 Number (department/no./year)
Offenbach, 22 March )977
- Place, date Gobel R 142 3245 Author Department Tel.
II
/s/ Frenkel Class Signature/classifier File no.
Summary This report represents a summary of the loads measured with the relief system during the non-nuclear hot test in KKP.
The information relates to:
- the measured pressures and pressure distributions in the sup-pression chamber during vent clearing and condensation;
- the loads on the relief system itself, insofar as they are solely of a thermal<<hydraulic nature.
The measurement values are transposed to the most unfavorable boundary conditions in the plant and are compared with the speci-fication values.
The specification values aie not exceeded in any case.
There are adequate reserves relative to the specification values.
Accordingly, the expert condition of GB 2.6.3-7 of the expert opinion for the pressure relief system /9/ is satisfied.
/s/ (ille ible)
Countersignature
/s/
Gobe 1 Aut or s signature Distribution RF 13 3x R
1 R
14 R
142 3x list:
R 314 R 321 R 322 R 52
Table of Contents Pacae l.
Introduction 2.
Scope of the tests 3.
Pressure load on the suppression chamber 3.1 Vent clearing 3.2 Condensation 4.
Loads on the relief system 4.1 Vent clearing pressure 4.2 Steady-state pressure 4.3 Vertical force on the blowdown pipe 12 12 4.4 Forces on the struts of the protective tube 13 Re ferences 15
l.
Introduction Extensive development tests with the perforated-pipe quencher were performed in the Mannheim Central Power Plant and in the model test stand.
The test results are documented in /1,2/.
The relief system with perforated-pipe quencher was tested under actual conditions and in the actual geometry as part of a non-nuclear hot test in the Brunsbuttel nuclear power plant in October 1974.
The test results of those tests are documented in /3,4/.
The result of the KKB hot test displayed an adequate margin between the measurement results and the specified limits.
Furthermore, tests with the relief system were performed during the KKB nuclear start'up.
The measurement results are docu-mented in /5,6,7/.
Zn additxon, tests were performed with the relief system during the non-nuclear hot test in the Philippsburg nuclear power plant.
Those tests were based on the actual geometry of the relief system
-.. 4'hey were erfo p
rmed under plant-relevant or conservative operating conditions in S eptember 1976.
The measurement results confirm the measurements of the KKB non-nuclear hot test and the KKB nuclear commissioning.
cation values.
The
+~~3 bar, compared bar.
maximum measured pressure at the bottom was to a maximum specification value of Q~
The result" disisplay an adequate margin relative to the specifi-
2.
Sco e of the tests Vent clearing and condensation tests w'th th 1'
e re ief system were performed during the non-nuclear hot test, in September 1976 in the Philippsburg nuclear power plant.
The relief pilot valves were actuated in the relief and safety function.
In order to cover "single failures" th 1'
e re ie valves were also opened with simultaneous actuation of two pilot valves.
To measure the ress p
ure profile during clearing of several quenchers, clearin tests g
were performed with adjacent perforated-pipe quenchers (E, F, G)'.
A total of about 70 clear'ng and condensation tests were performed.
0 The operating range in which the relief system was tested is illustrated in Fi u in Figure 01.
The operating range tepted in KKB is illustrated in Figure 02.
The tests performed and their boundary conditions are shown in Tables 1-7.
The actuated relief valves and the associated perforated-pipe quenchers and all the instrumentation are shown in Fi'gures 1-13.
From the tests in KKP it was able to be demonstrated
- that the me asurement results of the non-nuclear hot test and the XKB nuclear start-up test are reproducible;
- any further test series with the relief system would provide no 18-4
new information concerning the loads on the containment and relief system; the load reductions determined for the containment load in KKB are equally valid for KKP; the clearing tests with three adjacent perforated-pipe quenchers resulted in no significant, increases of the bottom and wall pressures;
- the condensation proceeded calmly.
3.
Pressure load on the su ression chamber 3.1 Vent clearina In the vent clearing tests, the main interest lies on the pressure oscillations that are produced by the expulsion of air from the t
relief system into the pool of the suppression chamber.
The effect on the pressure oscillations caused by the variation of parameters such as reactor pressure, valve opening time, water pool temperature and condition in the blowdown pipe was examined thoroughly during the KKB non-nuclear hot test.
Accordingly, a repetition of these parameter variations was no longer necessary for the KKP non-nuclear hot test.
All that remained was the parameter variations caused by the trial operation:
reactor pressure, valve opening time, condition in the blowdown H
pipe
~
The variation of the valve opening time was caused by the.different 18 5
opening characteristics of the relief valves and al o by the actua-I tion of one or two pilot valves.
The condition in the blowdown pipe was varied in such a way that the initial conditions in the blowdown pipe with respect to the water level in the pipe were left as they were set instantane-ously (real conditions) or a pressure equalization was brought about by opening the snifting valves so that the water levels in the pipe and in the suppression chamber were the same (clean con-ditions).
Xn the tests with real conditions, the water level in the blowdown pipe was determined by a pressure-difference measurement.
As in KKB, no.dependence of the pressure oscillations on the above>>mentioned parameters was found in KKP.
A dependence of the pressure oscillations on the clearing pressure was found, as in KKB.
Figure 14 shows the measured maximum pressure amplitudes in com-parison to the limits of the scatter band that was measured in the KEB non-nuclear hot test.
We note that the pressure amplitudes measured in KKP fit well into the KKB scatter band.
The measure-m'ent values from test 19Z are somewhat above the KKB scatter band boundary.
Considering the boundary conditions prevailing for that test (e.g., clearing pressure i~ bar, which was not nearly reached 1
in KKB), the difference is within the statistical error of the test Figure 15 shows the slight rise of the pressure oscillations with clearing pressure for "clean conditions",
as measured previously 18-6
in KKB.
For comparison, the test results with "real conditions" t
are also entered in this Figure.
No dependence of these bottom pressures on, the clearing pressure is recognizable.
I When the relief valves were opened sequentially at intervals of 5 or 10 seconds, the following pressures were measured at the bot-
, tom in time order:
bar.
Thus, the interval test shows a behavior similar to that observed for such boundary conditions in the multiple interval tests in KEB.
A slight load increase must be anticipated in the second and subsequent clearing processes
/3/.
This is probably attributable to the larger amount of air expelled, due to the quencher being only just filled with water.
Figure 16 shows the variation of the bottom pressure (DA 10) for "real conditions".
Figure 17 shows the same pressure variation for "clean conditions". It is clearly evident from the two Figures that after five oscillations the bottom pressure has fal-len below i~~~~~~~~~~~~~~~~~~~~~Q.
According to the expert condition GB2.6.3-9 from /9/, the bottom pressure ofQ~gbar is to be used as a basis for the fatigue analysis as a mean expected load.
From the KKp hot test it can be confirmed that this is a very conservative hypothesis.
The decay of the clearing oscillations can also be seen at the protective tube.
This is demonstrated by DMS 5/6 in Figure 17.
The KKP containment is designed to be durable for a pressure load 18-7
of 4~~~~~~~
bar for loads from the pressure relief system (see /12/).
Figure 18 shows a comparison of the ratio of positive to negative pressure amplitudes based on KKB measurements and theory.
The theory is based on the formula hp
~ p neg hp
+ p o
KK ETT pos 0
pKK = pressure in the air space of the suppression chamber BRETT = hydrostatic pressure corresponding to the submergence (ETT) of the blowdown pipe.
This formula was presented at the 1974 Reactor Convention in the lecture entitled "Depressurization of a boiling water reactor with perforated-pipe quencher; Part 1:
Air oscillations during vent clearing".
The formula is also the basis of the pressure ampli-tude assignment in the expert opinion for the KK8 pressure relief system /8/.
A theory describes the primary trend of a process which proceeds under the conditions specified in the theory.
Zn practice, those conditions are falsified by perturbing factors.
Therefore, this formula is confirmed in practice only for those events which are large enough to enable possible perturbing factors to be neglected.
Zn the non-nuclear hot test, the pressure ampli-tudes
'were Q~Q bar.
Zn that range, the measurement values were scattered about the theoretical curve in KKB also.
Only for pressure amplitudes greater than Kg did the theoretical curve 18-8
indicate the trend unambiguously.
In principle, therefore, the theoretical relation hp neg hp
+
pos po is valid for KKP also.
The negative pressure am 1
,p itude measured under extreme conditions (opening with two ilot va p'lves under clean conditions with a valve opening time of 250 ms) was 4~@ bar a d th ar an t us was sufficiently far from the design value of g~Q bar.
As shown in Fi ures 14 g
and 15, the KKP measurement values fit in well with the KKB measurement values.
As shown in Fi ure 15 t
'g, the pressure amplitude remains g~g bar*
even at the specified clearing pressure of@'g bar.
Therefore, the pressure amplitudes in Table 8 from /9/, which were specified on the basis of KKB mea surements, can be considered as verified.
Figure 19 shows th the czrcumferential distribution of the bottom pressures.
The measuredd circumferential distribution for test 19K is illustrated in the u
er art upper part of the Figure.
Test 19'as used on the basis of the evaluation of the KEB tests, where 'bottom pres-sures i~~~ bar werere selected for the circumferential distribution, since it turned out to be. the only KKP test having a comparably high bottom-pressure of '~~~~
g~~ bar.
In turn, the selection of the pressure ma nitude g
is based on the fact that perturbing influences 18-9
can be minimized only for relatively powerful events.
Thus, what was already said concerning the'ratio of positive to negative pressure amplitudes applies here also.
The 1/R law in the circumferential direction was able to be con-firmed with the KKB tests.
For the KKP tests, Figure 19 shows'hat the 1/R law was also able to be confirmed in test 192.
In this circumferential distribution it is assumed that the pressure 4
f remains constant within the circumscribed circle having the radius of the quencher.
In the bottom part of the Figure it is shown that the 1/R circm-ferential distribution, based on bar (see Table 8), represents an the specification value of 4~~
upper envelope for normal response of the relief system for all KKP tests.
As already shown in Figure 14, the load reduction found at the spherical shell in comparison to the values at the L-joint in the vicinity of=.the quencher is also verified in the EEB hot test.
As part of the vent clearing test program,.a few tests were run in which three adjacent relief valves were opened simultaneously.
The measurement results show that this causes no increase of the pressures.
Furthermore, there were also no differences in the pressure distributions in the meridional and circumferential directions compared to the single-valve tests.
The pressure values measured in the multi<<pipe tests are entered as crosses in Figure 14.
18-10
On the whole, it can be stated that the vent clearing tests in Philippsburg have fully confirmed the KKB measurements in regard to the pressure amplitudes and pressure distribution.
- Thus, the suppression charrher loads according to Table 8 were able to be verified for the clearing of the pressure relief system.
3.2 Condensation The condensation tests were so performed that condensation occur-red through one or two quenchers at reactor pressures of 70-11.5 bar and with the quenchers provided only in the automatic depres-surization mode IX at reactor pressures below ll,'5 bar.
A maximum harmonic pressure oscillation of +~~%bar was measured (see Figure 20).
This is below the specified condensation pres-sure of/~~+bar.
The frequency was approximately LM4W At re-actor pressures below 11.5 bar, pulsating condensation occurred.
The pressure spikes measured then had a maximum value of lkM3bar with a base width ofi~+ms.
Because of this small duration of action, the pressure spikes have no effect on the stresses in the structural members of the suppression chamber (see Figures 21, 22)
~
The temperature distribution in circumference and elevation ex-
\\
hibited a mean deviation of h~~Q in the condensation tests.
On the whole, the condensation proceeded calmly and exhibited the results already measured previously in KKB.
4 ~
Loads on the relief s stem
4.1 Vent clearing pressure Pronounced clearing pressures were measured only in three tests.
The reactor pressure was approximately 70.5 bar.
The measured maximum clearing pressure was approximately k% bar with a valve opening time of approximately 250 ms.
Figure 23 shows the extrapolation, to 88 bar reactor pressure and 100 ms valve opening time based on the measurement values.
The computation results for the reactor pressure of 70.5 bar and the corresponding valve opening times envelop the measurement results.
- Thus, the basis of the extrapolation is conservative with respect to the clearing pressures.
The maximum clearing pressure calculated on that basis isQQ bar.
Th's value is clearly smaller than the specified clearing pressure of iW bar.
4.2 Steady-state pressure The steady-state pressure in the quencher's vicinity is plotted the maximum steady-state pressure for a reactor pressure of 88 value is below the value of bar is approximately h~ bar.
This g~ bar specified for the quencher.
versus the mass flow density in Figure 24.
Zt can be seen that 4.3 Vertical force on the blowdown pipe To measure the vertical force on the blowdown pipe, two strain gauges each in the circumferential and vertical directions were 18-12
mounted in the water region (see Figure 2).
The evaluation technique used to infer the vertical force from the measured stresses and to perform the extrapolation to 100 ms valve opening time and 88 bar reactor pressure based on the available measurement results is described in /7/.
I The evaluated measurement results for the three informative tests are shown in the following,Table:
Test Reactor Valve pressure opening time bar m's Pipe pressure bar Vertical force kN
.19Z
- 70. 8 70 71 816 [?)*
616 255 KRAFTWERK UNION AG PROPRIETARY INFORMATION The extrapolation to 100 ms valve opening time and 88 bar reactor pressure results in a vertical force of approximately '.ILMMX The specification value of the vertical force is5kWM~.
There is an adequate margin between the specification value of KW%%
and the extrapolated value of K~gkN for the vertical force.
4.4 Forces on the struts of the protective tube The maximum strut force was measured in test 19Z at a'clearing pressure of ~3 bar and a valve opening time of abouts ms.
Zt was L~
- Tr. note:
First digit not clear in German document.
18-13
This force is composed of three factors:
1.
Pressure difference across the vent pipe 2.
Pressure difference across the protective tube 3.
Displacement of the pivot point of the struts on the inner cylinder.
All three factors together yield the total force.
The measured I
total force must be viewed in terms of the load case on which the design is determined.'hat case is not the clearing of the relief system, but rather air-poor condensation at the vent pipes.
A temporal coincidence of the two load cases was excluded by the premature automatic depres urization.
The external force on a strut of the inner cylinder for the load case of air-poor condensation is /~3 kt< /10/.
This force is larger by a factor of Q~~ than the measured force of 4Q kN on the struts of the protective tube.
The difference'etween the two values seems to be large enough, so that it can be stated that the load case of air-free condensation conservatively envelops the load case of vent clearing.
-3 For the probability of occurrence of 10
/LOCA, a maximum inner strut force of approximatelg hW kN was demonstrated in /11/.
This force is greater by a factor of g~Q than the force of L% kN measured in KKP and.can surely still be supported by the struts.
18-14
References
/1/
- Becker, M.s Construction and design of the relief system with perforated-pipe quencher U
Technical Report KWU/R 113 - 2703, July 1973
/2/
Becker, M.:
KKB - Blow-free with the perforated-pipe quencher Technical Report KWU/R 113 - 2796, October 1973
~
/3/
Becker, M.:
Results of the non-nuclear hot. test with the relief system in the Brunsbuttel nuclear power plant Technical Report KWU/R 113 - 3267, December 1974
/4/
Becker, Feist, Gobel:
Analysis of the loads measured on the relief system in the KKB non-nuclear hot test Technical report KWU/R ll/R21 - 3346, April 1975
/5/
KKB - Relief valve tests KKB - EB 50, August 1976
/6/
KKB - Relief valve tests KKB - EB 46, August 1976
/7/
Gobel, D.:
KKB - Nuclea:. start-up, results of the tests with the pressure relief system Working Report KWU/R 142-136/76, September 1976 18-15.
/8/
Expert opinion on the safety of the 770 MWe boiling water reactor for the Srunsbuttel site, Part 9, April 1976 1
/9/
KKP pressure suppression system Expert opinion on the relief system May 1976
/10/ Gobel, D.:
Design specification for load on the bracing of the pipes immersed in the pool of the suppression chamber Spec.
No. KKP/XK/SD 010, Rev. 1, Oct.
1975
/ll/ Gobel, D.:
Determination of strut load combinations and their probabil-
'ty, based on the GKM II tests with the 600 mm pipe and a
submergence of 2 m
Working Report KWU/R 142 - 168/76, Nov. 1976
/12/ Nowotny:
Design specification KKP ], KKP 2 Pressure and temperature load on the containment and suppres-sion chamber No. KKP/XA/SD/002, Rev. 1, April 1974 18-16
e 4 v ne>eenvenae eevvee a KV/U V 822/R 52 t si KKP I HOT TEST, test phase II (blowdown tests)
Operating Log KKP I HEISSTEST, Testphase II (Abblaseversut he)
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(SEE NEXT PAGE FOR KEY)
KEY FOR TABLE 1 1.
Test 3 ~
4 ~
5.
6.
7 ~
8 ~
9
~
10.
12.
13.
14.
15.
16.
17.
18.
.-. - 19.
20.
21.
22.
23.
PA no.
[abbreviation unknown]
Running no.
Date Time Relief valve no.
5)
Actuation lEVV ~ relief pilot valve, SVV ~ safety pilot valve)
Liquid level in blowdown pipe 4) mRS "-m water column BYK before beginning K
Test duration Reactor pressure 1)
PR el PR el Beginning End Liquid level in suppression chamber Liquid level in reactor pressure vessel before beginning Flow rate, valve no.
fStrang
~ leg) 2)
Remarks
- 1) Entered reactor pressures were read from the digital reading in the control room before and after the test.
- 2) Flow-rate determination according to a-value measurements
- 3) Interval test
- 4) rc ~ real conditions, cc ~ clean conditions
- 5) Valves E and G with swing check valve in,control line of independent safety and accident protection system from 26 September 1976 on.
1 min previously, F opened 2 s due to cc Measurement technique only partially covered Repeat test of test 6.1 5 s after test 9.1 10 s after test 9.2 Test was repeated (valve had not opened)
Repeat test of test 13.1 18-18
KKP I HOT TEST, test phase II (blowdown tests)
Operating log Status 26 Jan.
1977 I(WU V 822/R 521 V>'(such i<op tit Oalvm
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Ii<.r<s
')e'1
~
(iv,sp I( s)n I,~(
~t s
~ Sos s i ss 7<),4 7it ~ 7
)<to,l t,tl ~ I tn,l 67,6
<< ~ ~ I Ih, 1 I,~its I(.n-.
I \\
ep Co<top tin ~
k its+
><oil nit(t Ii <s\\\\
~ r ~tt I els'slh I
~ ~ I rhn> ~ ~ ~
s
~ ~ ~
~ Is ~ I ~ ets s
ve n V ~ rviir<e,"tr. I 22 11 Clngrtc<tgrttn Ih">kl p<dt<vkO <Nv<d(n vn<<ssttnttpcpt v(t und na(h VCfvvCh vC<n dC'r O<g<lcplanzr<gn in drt Waftts atsgtottoSCon.
))
Yne ~ I ~
~
I
~s.r.,ss
~
t t.
~ei 1 I ntk ~<<sin ev to<
~ I (ro
.I Out(hna>cbr firn<nun) na(h it -WC<I-h>C
~.Vngtn
)I tnt(fVattt(nt Cl r( = r<al (On<>i>iona. (( = (I<'an (OlttiilianS
<<VSC.S<
n.1.<n (SEE NEXT PAGE FOR KEY)
KEY FOR TABLE 2 ~
3 ~
4 ~
Test PA no.
[abbreviation unknown)
Running no.
Date 5.
Time 6.
7 ~
8.
9.
'10.
12.
13.
14.
15.
16.
17
~
18.
19.
20.
21.
22
'elief valve no.
5)
Actuation fest%
~ relief pilot valve, SVV = safety pilot valve)
Liquid level in blowdown pipe 4) mWS ~ m water column 8KK befor>> beginning Test duration Reactor pressure 1)
PRrel PR 1
rel Beginning End Liquid level in suppression chamber Liquid level in reactor pressure vessel before beginning Flow rate, valve no.
[Strang
= leg) 2)
Remarks
- 1) Entered reactor pressures were read from the digital reading in 'the control room before and after the test.
- 2) Flow-rate determination according to a-value measurements
- 3) Interval test
- 4) rc = real conditions, cc ~ clean conditions
- 5) Valves E and G with swing check valve in control line of independent safety and accident protection system from 26 September 1976 on.
No computer log available No recording of liftfor valve E
No recording of lift for valve G
7 s after test 22.1 **
No recording of lift, therefore repetition Repeat of test 24.1 18-20
KKP I HOT TEST, test phase II (blowdown tests)
Operating Log Status 26 Jan.
1977 KWU V 822/A 52 I KKP I HEISSTEST, Testphase II (Abblaseversuche)
- Detriebsprolokoll Stand 5hr-teil VJ 76
<<a
-fo "I 'I 11 I I
- Versvch, 3
00IU<n
<A ttl
) tt<
Cnt tontvni)~
-.I ventit-
- ttr, OF CVV ryVV 7
Ai>>teueru<>c)
~ e WS lnWS CIFvll-l<>n<t P3 Abbr e> ctroh<
<0 vul nucl
>g Oer)i<<> >I<I<<el C >C Fillet I). c)><en be> t I >A<>>I Er>cte b1<
l"I, Pi I<
i<
)tent>IOI uric I ut;>I in KK If> ~ )0 eeQI~~
nub v<><
nprtoeon I" 0 n.c Sltonq I
A ~ II 5 linn>)
7 Irh I<h
< ~ 'o )
D ~ K SI<one) c F
Cl St<<>no]
)
I<h l<h
)urrhsolz Vcnlil-)tr.<'nmer I<unpen
'7
-e, "I.'<. I ' ill X.
i C
))
~
'7<>, fo l>7 ~ C Ifo ~ 1 I'
<>7
(,ein "0
V>>
r.n.7
<r,.)4 i,r.i
'v>. I;:I.'i. 1<<11 hn
'o hi ei 11 )
r>>
rc P
P 71 Pi 71of'Co, ))
Ir'e el n<7 10
)n
)7 71 o7 frn ~ t 1(o ~ 'l I I'eI f.in h.v n,v V.
I X
X r.
v X
X rp nrc v
<>,0
- ,n
<e I
~ <>, <e frl,ie Sn ~ i 4'J. S I(i,) ~
ire>S)
~ <,
I ),n<e frhre V tint'4 1<e'a 1<<<<<fr ~
n <inch IC< ~ 1 e ~ f rei ~ 1 l7
)io
'I'o I. iei.
i'C
~i<i
<r< eP>7 ICi
<<r'e I<< ~ 11 I. Iei.
I l.
r>>
)n
<e<>,
PS
)ie P
ICi, <<v(o
~ lr~
1<e 7 I, Il>.
I<
)
o ln
'10 1)e)
(
1(o ~ <<7 I I ~rill
-np 17
=)7 I, I< ~.
Ie
<i.4
<<o) h
<<Cr ~ I If,.n 11,07
<<pu ln 17
)'<
le<
I
~ ~ ">
I, I ~ ~,
I t.<ete 0
<o ~ <,
<on
<i<<
)0 h<<o,(o
-= n
.....n 1(..Sn
'1>7 IC>,<<n Il <7
~
ro 117
<e I
'el. I
.. I"~
<'n ~.r
<, I ru
'... Iii. i>li,;7 r>>
~'C fen 0<>
Ife,n I> ~
I 'e e I 1(i,<e r.I
< t ~
Iro,<e o
I".7r
'l)S I<
o P<y ve'chat I at I>>lee>>i A>~ > ~ initio I<
<e I
<el,
~ o.'I
.<e ~,
eo'i.'. ~ ~
rc rc 1<e, I
'I '1, 1
\\
~ <r I) ~ 1
<I,n I Ce, <o,
I' r t Ihl vt chio.i ~
I I le>pn
..I hint ~ ie
~I phi"li I ieeipi XI > Ini eo ve char< 1i 11 l ~i<<i.'0 I Ini i ~
II il Ee<>ctnt<u<tniil'tput to< ~t<>v4n wu<<trt> u<><nittnit>0< vr<
Un<) nclti Vrrpvch von dc'r Ihlt>tot<in<co>rte in ilr< 1Vnrte ot>9cte.en.
1< '
~ e< II Y. ie,< a'"i, ~>,7(r
~
~ I Ii<<iLhi < I oee' pe ~<< I I>i
)I gvrrt>not(tin li<niroiiiv) noch
> -vl<<l - Mr>>nut>et< n
)I Intc <votltn>>t ct rc = <col conllilion.
ec
= el<on ennclilicons 0<
(SEE NEXT PAI. E FOR KEY)
KEY FOR TABLE 3 1.
Test 2.
3 ~
4 ~
PA no.
[abbreviation unknown)
Running no.
Date 5.
Time 6.
7 ~
8.
9.
10.
12.
13.
14.
15.
16.
17.
18.
19.
Relief valve no.
5) 1 Actuation
[EVV = relief pilot valve, SVV ~ safety pilot valve]
Liquid level in blowdown pipe 4) mWS ~
m water column 8~ before beginning Test duration Reactor pressure 1)
PR 1
PR 1
rel Beginning End Liquid level in suppression chamber Liquid level in reactor pressure vessel before beginning Flow rate, valve no.
[Strang
= leg) 2)
Remarks
- 1) Entered reactor pressures were read from the digital reading in the control room before and after the test.
- 2) Flow-rate determination according to a-value measurements
- 3) Interval test
- 4) rc = real conditions, cc
= clean conditions
- 5) Valves E and G with swing check valve in control line of independent safety and accident protection system from 26 September 1976 on.
E opened after 14 s
E opened after 10 s
Two-way blowdown 18-22
KWU V 822/R 521 KKP I HOT TEST, test phase IX (blowdown tests)
Operating Log KKP I HElSSTEST, Testphase 8 (Abblaseversuche)
Det riebsprotokoll Status 26 Jan 1977 Stand I ~ I '177 VC'(5uCh
't On)urn IC teil En)ln iong-
' vvnti)-0 EVV SVV 7
Atlv> Cue(ting C)FIIIIStiS im P
At>t>IO>CC vor Oeg cys rr Vn sue hs.
dotter lt I
))ra)s)oi ut)I
)'nrci )arri ftegnn t:ni)e I?
r'ss hl It1 KK FvlI In I on VOI Ilrginn t) ~ C F. ~ II vvlrssng 51>nng I
F ~ G 5llnnq Cl ~ I 5'llqng c
@')ttr(hgn)Z Vcnli)-)<r.
>s+
Occncrtsungcn 1976
~ mW5
- mW5
-'C
-s iver t>>>SI rn m
tits lrh lrh I Ih I ~ tis.
IC..".
re too
).h
~ ).5 Ir..s
,hi
>>)
~e ~ rh<<e.l rl I lnr>>
At lit.o I n 17 I >>
I >>
I ~ I ~I, Ion I) ~ 5 I
~ 7 I(i~ '"
~hi
<<rrh>>e I<<rltlnv<<
Aiehln<<n es
~ I I ~ II) re re Ion Ion Go Go Ih>>7 I I >>>I I I ~ ')
I i,h 1(,5..
I"eh I 111
~
I '14
>>' 'cli
~'
~i I I ~ 9vr Al eh I n <<v>e
<<c Ch>>vl ~ e i I lee ~ ~
Alii>I 'l<>Aec 6 '>>C rc G
h,h Ce>>
I) Ie I 'I ~
~
7 ~ 9 I(e ~ 5) i",Ie,'I Iiyslrnoill<<eh>>> Of Crnhnlle
~ ~
eel t Tll Fy << le>>
Ig Io.
17 ~"I ti ~ F. ~ A >C I:,A,C re re h,o
)7 ri <s in,h 7,h IC'.
7 I'-'l)n
')5 95 ur(vi tent tv<<y. Icn (9
>>, Ill, II "0 r..(...l.C ISA>>C
~'C h) 11 ~ Ce 7 ~ 9 1(,I>>>
I>>
~ 'l(i Inn Inn Inn Inn nf(rnhnl te <<y<<te io
>,(e II~
n I. )n F.. A,r.,r.
I. ~ A>C
~ C n
h
~
I >>
11,5 7 7 I( Ii7 l,vl nn 90 gls Iis'A IIC <vest ~iel ti'>>y<<t ~
>ei>>IS ~
)Il~
A,C:,C: Csin rhnl tvt I 7
>,7 I, lis.
V ~ A>>C ~ I C ~ A>>C re Cs Vi
,Ce h,o 1(.511 I"~ 7 I~ C I ~ nl>nl I ~ <<v. I vio esisrll ln<<A.C:.0 I>>inn<<rhvltvt hrl
>eh
. ~ II~
ill,s>II C >K ~ A>>C
- s. ~ A>>C
~'C r.
Ie ri
>its I
~ ~
~
Ie, lt I(i,v><el 71 71 71
~
71 0ff ~ so hn I I i'.<<I << t ~ eo 09 (9
v)n hn I Ii~I In, 1 ln ~
I 'I ~ 5(i lo ~ I'e
~Is
)Ie ri ~ F. ~ A,C I I ~ Aec Il,n,(
F. ~ AeC
~'C rc I'C 0
h ~ h Cire
>>(
160
)nn 7>0 (i ~ )
1(i ~ >5 l)enli
)0 1(h..
I",9 (n
0 9 u,h 1u Go orfrnhnl tv y>>t ~ n nb>or I, ln, I>>
~ <<Vn IVVI' lleil nsl
'i
~ i I. les<<I
~
s <<rn Iv sr Ivrhnl ~ > ~>es<<
Vvr<<sirh
>e>>1 \\ I Ofre'nllnl tl'sy>>tvn Qi (Di I) Elngcltorcnc F'eok)ordcuttsc vtucdcn urvnsllclbor vof und no(h Vcr. u(h von d('f t)tgitalanzctge in t)cr hY<trlc obgcicocn.
- 5) I'cnti I F. n,r.
nt> '.,n,)(.
- 7) r)uc(hsal ticslimirning no(h Ii -hvcr)- )4cssungcn
)) Inicrvaliicvl
() rc = real (andi)inrts, cc
= ciean condil)ons jG (SEE NEXT PAGE FOR KEX)
KEY FOR TABLE 4 1.
Test 2 ~
3 ~
PA no.
[abbreviation unknown)
Running no.
Date 5.
Time 6.
7 ~
8.
9.
10.
12.
13.
14.
15.
16.
17.
18.
19.
20.
21.
'22.
Relief valve no.
5)
Actuation
[EVV ~ relief pilot valve, SVV = safety pilot valve]
Liquid level in blowdown pipe 4) mNS ~ m water column 8KK be fore beginning Test, duration Reactor pressure 1)
PRrel rel p
Beginning End Liquid level in suppression chamber Liquid level in reactor pressure vessel before beginning Flow rate, valve no.
[Strang
~ leg) 2)
Remarks
- 1) Entered reactor'pressures were read from the digital reading in the control room before and after the test.
- 2) Flow-rate determination according to a-value measurements
- 3) Interval test
- 4) rc ~ real conditions, cc
~ clean conditions
- 5) Valves E and G with swing check valve in control line of independent safety and accident protection system from 26 September 1976 on.
Two-way blowdown Hydraulic holding open with TH system Hold-open system Hold-open system connected to A, C, G after 30 s Hold-open system without injection (test interrupted)
Hold-open system without injection (repeat of test 49.1) 18-24
KV/U V 822/R 521 I Vc fsuch 3
ttotvrn I'c d Nr 5
zc il I
Cnt tostungs.
- 5) vcntit-Nr.
Qg KKP I HOT TEST, test phase II (blowdown tests)
Operating Log
~I tl Aenktar fudf 7
Ans s erung CIFifltstong Icn US tie vor sue hv>
Begim doucr rt'ur(tisntz Ventit-Nr, 'I FofI.
II 3
)tnt vfer npfienn Fu st.
In IC IC B ~ c St conn I
OvE Sttonei C
A ~ II F ~ 6 Slcnceft tttong 5
AACPI Enfte PArct B'qinn Syy Abhtnsrrohr KKP I HEISSTEST, Tesiphase 8 (Abblaseversuche)
- Betriebsprolotcolt Status 26 Jan.
1977 Stand I )sir S'ccncckvngen 21
)976
~ I iI I I. Ci I tmvf5 2eJ
- mvf5 o 'c oS hot 17,}
hot
)6.4 12, en Ifh tch Ifh I 5Q Ifh rn 27.n.
I ri ~ 7 IG,o IG, Io 12 ~ Ori
- 2) 'l 12.))
se5 15, ti I fe ~ 7 Iri ~ fe 157 17 I fr
)eo 5n 76,n r"Ie'I I re ~ 5I 12,Gsi I-2
<f)
~ PC 57 7J ~ 7 Go,s IG, 11 12 ~ fi r 72 co I
)fl,ie, 17 I) fe ~
rc 77 7 Il ~ 5 7II,n 67,2 67,.r Ice ~ )fr
)oe51
~ I rl Gffr.
21 2
2)Z
~ r zl,o, 21 O ~
15.II7 Ife,o
~
I'C rc rc 57 5n 5n 75.5 7
~ I 7.n 7n.f.
16,5k ci J ~ 5 I re ~ 5'I rin te I re ) fe I",G 12,G 12,te )
G)..
6"I 17
~ /
"I,'I I r> ~ Ore
<i. ~ is rC rc 77 sv rin, o nfl r.f..n Ir,5fe 12, fit.
~ i
~ ~
'I'nrv roice 4 cee V ~ rr en I~ I, rVeir Vin111
- r. ii"~ ~ Cf ~I~ I II I CI
.7n Il Eing tragene ACOktOfdfutke Wufften uCMCIittetbar VOr und narh VerSurh VOn dCr OigitalanZCiqe in der WnCte abgeteSCn.
5I " 'ntf
) r v.n Pn
( 'I 76 7I OVCChSO)rbeS)inlfnung nnrh el -Worl - hth=,ounqnn 5I InleCVatlleSt ZI rC = rCnl COnditiOnS.
CC = CICan COndltianS (SEE NEXT PAGE FOR KEY)
KEY FOR TABLE 5 1.
Test 2.
PA no.
tabbreviation unknown) 3 ~
4 ~
Running no.
Date 5.
Time 6.
Relief valve no.
5) 7.
Actuation
[EVV = relief pilot valve, SVV = safety pilot valve) 8.
Liquid level in blowdown pipe 4)
AS ~
m water column 9.
8K> before beginning
- 10. Test duration
- 11. Reactor pressure 1)
PR 1
PR Beginning End
- 12. Laquid level in suppression chamber
- 13. Liquid level in reactor pressure vessel before beginning
- 14. Flow rate, valve no.
[Strang
= leg) 2)
15.
Remarks 16.
- 1) Entered reactor pressures were read from the digital reading in the control room before and after the test.
- 2) Plow-rate determination according to a-value measurements
- 3) Interval test
- 4) rc = real conditions, cc ~ clean conditions 5), Valves E and G with swing check valve in control line of independent safety and accident protection system from 26 September 1976 on.
- 17. Preliminary test for test 17, only valve E opened 18-26
n/ oOseoootsvv,rva~
~voesnia V 822/R 521
/ Vcrsvch Q g s. -)It Pcg
>rt l)alum 19)G En) >ashtngs.
sr 7
hts r>tctung 8vv
."ivv IFulsslon~
sm
~$
'>eb>O>rtchr
~mws
- mws Vc vor cvclss Oct)ins ksucr c'c sI ev Orcskln
~ turk
)'I I
).nc>c
)'O tv >
nngenn
>vst
>asst r
>I Its KK Feil >
i /I hn>
vett I>l eJenn te/ Ou>CKSOIC Vrn>il-Hr. "
0 ~ C h ~ Il S>tons Sltnn9 I
7 I I Is F ~ a 0 ~ F.
Slross9 Slitleo9 3
C
'I>Is It>e KKP I HOT TEST, test phase II (blowdown tests)
Operating Log KKP I HEISSTEST, Testphctse II (Abblaseversuche)
- Betriebsprotokott Status 26 Jan.
1977 Stand
"(e, I ~ 1777 Ocmcr kungc 0
/. Is ~ I 1st'.10
/. Is>eo
/.>0)
"I,'I, 1st et ~
cG. i. s>.)r.
0 os, I's toil 0 o I'I ~
? ~ I
)
~
)2
)
~
1st
)et ~It le 7
47 F 7 teoeu I
~
~
~
- a!e.n tofe,"
~ e ~
I 'I ts')
>f ~ I I 12 ~ 7>e Ira ~ 1 a
>hen>
> fe ~ )
I'f.
~ )r s2.7 tictn ts I/o 2> I Ie>9
/.I>ore
'I '>, "0 10 Is rc tsr,l to l,'>
ICi ~ 1>'2,'>7
)02
/I~ s ~
/,I ~ it>
":I s, cis,'ts t> 'I, /ss, Jn 0
i'c 33 tefe,h t te,n t
e 4),0 IG."lt' fo ~ )
I,n)
)9..
.74 n>er) 2>l e>
(I to 5 rc ter tete, )
>c,.)n sa,rn
)>)7
/,110 cn,n,
. I ~ ure rc
)te to7.'I CG,C
>G,)es
>2.)oh tents 2n.o. >. n rc 3r rn,)
'"),0 Il',)i 12 ~ )G t,2t, Ci 12
'en er
..>.tsn te ~ )
)fo i,n,n hro,)
Sr
~ )
12,24 Cnr te 4 ~
)fo, te te ts ) ~ )
I Co ~ 4 12,>
~
377
/I ste rn t.
)Ce ~'her 4)oa
>Co ~ )" I"~ 11 Vi~
~irrneosssesee vnn Vrrrsich /I>l
/er Cn.9.
Sn.etn te
)ts 71 ~ So if.,h. Ia,r I C.ifo
/.> ICe sr..nn 2
u.aus /ii'c
~ 4 Co9 ere IG ~ vr I ) ~ I>>
Cot
- .117
>t.. sr rc 7).2 fe'I, 7 I (>> ~ is 1)e01 G)s
/IIn s.
i).ns 0
)7 7) ro 7n.
I fo ~
~ I I 2 ~ Ce7 I'a)4
- e. I I'I
~ ~.et.
I/.. )II rc
)7 o
, 0 ~ /e f.h.
>G.;:
in.n >
t,n7 II cstsac>tc>grnc r>ce>>Istic>tvckn wurdcn utvnillrllsnr vnt und nach vctsvch von d>r otg>lu)nnrcsgc in dcr svnrlc o)>gclrscn.
- 5) v>>III >,
~i.n>>e ol.e/.)r.
tei I It Ictavrt ~ 1netvri ~ I I I isa
)I Ourchnn)z)>c tiinn>>ino) nnrh i> -hvcrl - Mns unt)cn
- 3) )nlcrvalllc t C) rC = rt nl cnndi)in>le.
CC = CICan Condilions iicvs str...e i. i >i e<<
(SEE NEXT PAGE FOR KEY)
KEY FOR TABLE 6 1.
Test 2.
PA no.
(abbreviation unknown) 3.
Running no.
4 Date 5.
Time 6.
Relief valve no.
5)
"7.
Actuation
[EVV = relief pilot valve, SVV ~ safety pilot valve]
8.
Liquid level in blowdown pipe 4) mt<S ~ m water column 9.
8~~ before beginning
- 10. Test duration ll. Reactor pressure 1)
'PRrel PR e Beginning End
- 12. Liquid level in suppression chamber
- 13. Liquid level in reactor pressure vessel before beginning
- 14. Flow rate, valve no.
[Strang
= leg) 2)
15.
Remarks 16.
- 1) Entered reactor pressures were read from the digital reading in the control room before and after the test.
- 2) Flow-rate determination according to u-value measurements
- 3) Interval test
- 4) rc real conditions,. cc = clean conditions
- 5) Valves E and G with swing check valve in control.line of independent safety and accident protection system from 26 September 1976 on.
17.
Repeat of test Z113
- 18. Independent safety and accident protection system 18-28
- KV/U' 822/A 521 KKP I NOT TEST, test phase ZI (blowdown tests)
Operating Log KKP I HEISSTEST, Testphase II (Abblaseversuche)
- Oetriebsproloicotl Status 26 Jan.
1977 Stand
- li I I'177 I Versuch PA-tlr lr 0 Iturn I'f76 Ent tOStlrngS.
al vc'nlll Nr.
Ans ever ung EVV SVV nllv5 rnWS Ct Fv I l a Inn lnl 5'bblnreroril Gegiltl Vc suchr
<lover 11 Ir Jtcoktor<
ctr
~rer ttcrtiiln fndc bill ha 1 tu ln KK FvlI./)
III'Ol 0eltinn
<< l)urctlsotz Vcntit-Nr"
+
t)cmert unqnn 0 ~ C A ~ II F ~ G 0 ~ C Strong Slrniv) Slrnng 511 any c
Irh Irh Irh Irh AI<<rl lll~ a CI, I C u
1'e re
)7 7
~ )
(ir,<<
7",0 I'l~II 1(i. a \\
1(i ~ )li (i ~)
con hi lese t ii lrnrilirnchrlrhe "I~
~ ~
I (itl~ I
(,n.(.
1(i ~ 1 i (i'
r(17 Alv'I rI'<<)
<<1<<6 I ~ lu, 11 ~ 17 I. In.
- 11. )7 I ~ In, I 5 ~ill o
re'
'n
)'
(<<i)
(i7i')
(i'7 ~ 'I I:fi~ 1<
(ir,s Ifi~ "1 I( ~ ~
'f.,s I ) ~ ri'1 I)i77 Sill)
-n
~ /
hrln llrrhnirlrnirihnl I vnrhnii~I II hi in llrrlnirrlrornliiilI vnrhnnilrn
'I t: "gct'or)me tt~nl torrtrlrc'kc~urdcn vrvrgttettrnr vor vnd noch vcr(Orch von dc( ttigitotunzclgc in clc( v(orle ntrltctesen.
)I t"i~Iil I: v.r. nb "(.n.)r,
~ilI nhvh ~ll~lrilvililI I
)t nvrchsnt(hestimmvng nnrh il -'tYcrt - Mcssirngnn
)l Intcrvolltesl cl rc = rc ol conditions, cc - clenn conditioils u<<ll ~ al
~ I ili ia (SEE NEXT PAGE FOR KEY)
KEY, FOR TABLE 7 1.
Test 2 ~
3 ~
4.
PA no.
[abbreviation unknown)
Running no.
Date 5.
Time 6.
7 ~
8.
9 ~
10.
12.
13.
14.
15
'6.
17 ~
Relief valve no.
5)
Actuation,tEVV ~ relief pilot valve, SVV ~ safety pilot valve)
Liquid level in blowdown pipe 4) mWS ~ m water column 8KE before beginning Test duration Reactor pressure 1)
PR el PR Beginning End Liquid level in suppression chamber Liquid level in reactor pressure vessel before beginning Flow rate, valve no.
[Strang
= leg]
2)
Remarks
- 1) Entered reactor pressures were read from the digital reading in the control room before and after the test.
- 2) Flow-rate determination according to a-value measurements
- 3) Interval test
- 4) rc ~ real conditions, cc = clean conditions
- 5) Valves E and G with swing check valve in control line of independent safety and accident protection system from 26 September 1976 on.
No Visicorder traces 18.
No computer log available
- 19. Independent safety and accident protection system 18-30
,KRAFTNERK UNION AG PROPRIETARY INFORMATION 18-31
KRAFTNERK UNION AG PROPRIETARY INFORMATION Key for table 8
Table.......
18-32
I
KRAFTWERK UNION AG PROPRIETARY INFOKIATION 18-33
KRAFTWERK UNION AG PROPRIETARY INFOM4ATION Figure.......
02 18-34
I Arrangement of blowdown quenchers'in the suppression chamber with associated relief.
valve numbers I >>S c8e
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0 0
Q tb C40 00 ttf Figure l:
KRP I hot test,
Figure 2:
KEP I - Bio~down tests during the hot, test.
Instrumentation of the p
mb 1976 pressure relief system.
Revision.~
3 of 1 Se te er
[SEE NEXT PAGE FOR KEY]
I I
Pd-5 QJ'0 :KKPI-Abb(oseversvche telm Heir)(es(
esstrs'rsseprheesJrq oes prs2ss ersI!cslvc s+!c&s Revision:
3 vom 19 76 1
Ny f
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ScRnit t I/I Wd -2 We) 1 P'
Ps(
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P
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P P
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P DMS(Y)1 DMS (V) 2
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P
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P P
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P
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P
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P
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r P
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P P
~ P Q
0 OMS(V) 3 Abb(user ohr Pd-5
~ P I
a-- <<s an J-.~r..
~<~~~IVd 2 I
1 (~
Schnitt II / ll DMS(V) 10 OMS(V) 8 DMS(V) 5 DMS (V) 6
~ ~
E E
O~,.he Bild
) 2 Os SchnPr III / III DMS(V) 1C 8 Gl lS(Y)16 OMS(V) 11
~
DMS,"J) 18 J/
e D. sM 12 DMS(u)17 8 OMS(Y) 13 AhhlrsFcrohr Dwsivlrs I
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"i Hullrohr ~~ OMS(V) 9
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~ ee ea Anmer k un9e V= Ver(ikal U sum tang' Foils es ch.'saaesesversheskI.
9 sr& s.'re st!"ea>> ms Ersilmags-s)%(eel/)cv(
26p o 18-36
KEY FOR FIGURE 2 1.
Section 2.
Blowdown pipe 3.
Quencher E
4.
Quencher G
5.
PF 1 and PF 2 (quencher G) 6.
Normal water level 7.
See Figure 12 8.
Note:
V "- vertical, U ~ circumference
- 9. If not otherwise noted, the measurement transmitters in relief system F at 260 DMS = stain gauge 18-37
Figure 3:
KKP I - BIowdown tests in the hot. test Instrumentation of quencher F
(BA 3l S22)
Revision 3 of 1 September 3.976 BLO 7: KKPI-Abbtaseversuche beirn Heiittest lnstrurnentierung der Duse F ]RA 3t 5 221)
View toward fitting All strain gauges displaced rotatably to the left by.%am from the middle of the weld on the top of the two quencher arms Weld SchweiOembt DMS-23 DMS ~ strain gauge DM5-198 ////
DMS - 25/ 26
/I DMS-2c, I
~
DMS-20'y HS-2)122 eben ~MenonDusena. ~en in dei senkiecnten F bene Top and bottom on quencher arms in the vertical plane 18-38
~ 16.54 WA-16 ADA-14 Duse A Quencher A
+12,78 m
~ DA ~ pressur transducer WA ~ displa ement transducer DMS strain gauge
'oo DA-16 DA-15 DWS-86 DMS -87
+ 1G45 m
WA-18 WA-17 OMS-88 DM"-89 Figure 4:
KEP 1
Instrumentation of the suppression chamber Meridian:
108 Revision:
3 of 1 September 1976 Bild 4:
KKP 1
inst rum en t i er ung der Kondensa t i ons-Kamrn er Meridian:
108.'
e v i s i On: 3 vo~ 1.9. 76
DA<<17
+>0~5 m
DMS-94 4 A-19 DMS -95 Figure 5:
KKP 1 Instrumentation of the suppression chamber Meridian:
145o Revision 3 of 1 September 1976 Bild 5
KKP 1
Instrumen ti er ung der Kondensations-Karnrner Meridian: 145'o Re V i S l on: 3 vom 1 9.76 18" 40
Duse G
Quencher G
+ 12,780 WA-20 DA-2 DMS-90 DA-1 WA-21 MS-91 SA-22 DMS-92 DMS-93 Figure 6:
KYP l Instrumentation of the suppression chamber Meridian:
228'o Revision:
3 of l September l976 B)ld o KKP 1
Instrumen tier ung der Kondensations-Kammer Meridian: 228o Revision:
3 vom 1.9.76
+ 1450 DA-6 DA-3 DA-5 Figure 7:
KKP 1 Instrumentation of the suppression chamber Heridian:
244o Revision:
3 of 1 September 1976 Bild 7.'KP t Instrumentierung aer Kon de ns a t i ons-Ka rnm er Meridian: 244 Revision:
3 vom 1.9.76
~ 16.54 DM
+14 50 DMS-68/70 69/71 /i)
DA-12 DA7
+ 15,04 DMS-67 DMS@6 WA-23 H.
11 WA-15
+ 11,92 DMS-65 DMS-64 f"
12 780 DA-1 l DMS-63,
/~DM5'62 DUse F
Quencher F
oo WA-14 DMS-60 DMS-61 DA-10 DA-8 DMS-92
++49 D MS-53~i DM5-50 DMS-51 DMS-57 DMS.56 DMS 58 DMS 55
- 1) St,rain gauges glued tvicc~ 'w1.red'P connected only once DA-9
- 1) DMS doppelt Kleben, verdrohten,nor 1-fach onschlie Aen Bi ld 8 'KP 1
Instrume.n ti er ung der Figure 8:
KKP 1 Kondensotions-Karnmer Instrumentation of the g er i diQn 26O o suppression chamber Meridian:
260o Revision:
3 vorn1.9.76 Revision:
3 of 1 September 1976
Ouse E
'uencher E
+8 DA-t I
4x strain gauges, earth displaced by 90 DtlS 85 CxDt45 jeweits um 90~verse tz t Stutze auf 285~
Dh'is 82 Support. at 285 x"
Rtr, 360 D>S BS i MS8r.
270 180 OJvIS 83 Bitd 9 'KP 1
Inst ru men tier ung der Konden so t i ons-Ko rnm er Meridian: 284o Re v i s i on; 1.9.76 Figure 9:
KKP 1 Instrumentation of the suppression chamber Meridian:
284o Revision:
1 September 1976
- 1) Lt.
KRAFTWERK UNION AG PROPRIETARY INFOM4ATION 18-45
KRAFTWERK UNION AG PROPRIETARY INFOK4ATION Fxgures
~
~
~
~
~
~
18-46
DMS-78 D
S 79 DMS 76 DMS 7g, DM S - 77 DM S -75 DMS-80 DMS-81 yf.
j 4>1
~ ~ 1 c r1i:.
DViS
)'it.
)lik 73 longitudinally~
glued Middle conical ri$/
Ii I)
~l
+ 9890 m I
at
<<W A - 11/12 auf 260 W A - 17 ouf 108'A
- 21 uf 228 a
a I
Ansicht von unten gegen Rippe a
bottom view toward rib WA-12 hg Meridian 260O DMS - 72 long s gekl e bl longitudinally glued Bi(d i" Inst ru men t i er ung des Bereiches Bodenha t ter ung in der Kond-Kammer
'evision3 y 1 9 76 I
Figure 12:
Instrumentation of the region of the bottom mount in the suppression chamber Revision 3 of 1 September 1976 I
1.8-47
+10)4 5 (M)
'(U)
Figure 13:
KKP 1 Xnstrumentation of the suppression chamber lining Revision:
3 of 1 September 1976 at DMS -96 auf 108'(M)
DMS-97 auf 228~(M)
DMS-98 auf 260~(M)
DMS - 99 auf 108 (V)
DMS - 100 auf,. 228' U)
DMS - 101 auf 260 (U)
Bitd G: KKP 1
Instrumentierung der Kondensations-Kamrner
-Lfn ing-Re Yl SIOn:
3 VOfll 5.9.76.
18-48
KRAFTWERK UNION AG PROPRIETARY INFOMIATION Figure, 14 through, 24 18-49 through 59