ML17138A541
| ML17138A541 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 12/20/1974 |
| From: | Becker PENNSYLVANIA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17138A531 | List: |
| References | |
| KWU-R-113-3267, NUDOCS 7903150354 | |
| Download: ML17138A541 (31) | |
Text
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I"<~~'l~~ iA~r~~~Imt<<r f)LKQ RESULTS OF THE NOi'-i' OIJ-llUCLQR HOT TESTS
']tITH SYSTEi"i IÃ THE BRUflSB0 THE RELIEF 3 TTEL f'fUCLEAR PO'tER PLAI]T
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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.
b)
Use of blocked out areas by cross hatch bands in the report text and figures/tables, e.g.
iii) iv)
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KRAFTWERK UN)ON Dffenbach Fl 20 Dec.
1974
'ate Technical Report EMU/R 113-3267 R 113 5epartment File number R 113 3267 Be mr Author Dr. Becker Countersignature
Title:
Results of the non-nuclear hot tests with the relief system in the Brunsbuttel nuclear power plant Key words (max.
- 12) to identify the report's content:
suppression chamber, relief system, thermohydraulic loads, test results with actual geometry Pages of text:
Figures:
Circuit diagrams:
Diagr./oscillogr.:
Tables:
Reference list:
Summary:
This report represents a summary of the thermohydzaulic loads measured during the non-nuclear hot tests with the relief system in the BrunsbGttel nucloar power plant.
The information relates in particular toz
- the measured maximum pressures in the suppression chamber during vent clearing and condensation)
- the pressure distribution in the vertical center section and in
'the circumferential direction;
- the loads on the relief system itself and on the internals in the suppression chamber;
- the temperature mixing in the pool.
There is an adequate margin between the specified limits and the test results, generally with large reserves (see Fig. 3.10 and 3.11).
/s/
/s/
Dr. Becker Dr. Koch
/s/
Class ifier II Class Foz zn ormatzon
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All rights to the award of patents or registration of utility patents reserved.
'2-1
Distribution list internal R - Ffm RZR 1
as RS 1
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~ RS 12/>~~
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3/h4>'S RS 14/REX RS 15 RS 2
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3 R 314 R 32 R 322 R 52 R 521 R 522 V 822 TA R 311 1'0 2 X 2 X X
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NONLIABILITYCLAUSE ical knowledge of This report is se ha d on the current technica TWERK UNION AG and all persons KRAFTWERK UNION AG.
- However, KRAFTWERK ticular, they are acting in its e
b half make no guarantee.
Xn par cu ac and completeness of the not liable or e
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rt is de'ivere" a
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ga ',
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tained there n re th i
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it will be handled confidentially.
l2-3
Table of contents Page 2 ~
3 ~
Introduction and summary Nature and scope of the tests Pressure oa on 1
d the suppression chamber 12-5 12-6 12" 7 3.1 Vent clearing 12-7 3.2 4,
5.
Cond casa tion in the suppression chamber Loads on internals Loads on the relief system 12-10 12-11 12"12 Figures List of references 12-4
- 1. Introduction in the Grosskraftw heim model test-stand (these test Station) and in the Grosswelshe mo e nte reted in /1, 2/), the hot results are fully documented and in erp tests in the Ker h
K nkraftwerk Brunsbuttel (KKB)
Brunsbuttel nuclear power plant]
w t e
i h th relief system represent ent confirmation tests d
der actual conditions.
Expecte on the actual geometry and under ac
/4/ for the tests specified in /3/.
values were given in tests with the perforated-ipe quencher After extensive development tests w t erk Nannheim (GKH) fMannheim Centra Power ummar of and supplement to the The present report gives a summary o S
6, 7/ concerning the evaluation described in detail in /
measured values lie within the thermohydrau lie loads.
The me i
an adequate margin between the speci-oxpected range.
There s an s
enerally with large reserves.
fied limits and the test results, gen imum bottom-pressure for relevan tests was In particular, the max um s to be compared to a specificQd Qj~3 bar.
This measured value is to 2
value of Q~3 kg/cm.
In summary, the results can be designs ted as very satisfactory.
12"5
I
- 2. Nature and sco e oof the tests t c earing
- goals, namely
'on chamber durin" d on the suppression
" lowering of the pressure load on assive measures, and vent clearing by pass n u to ig hi h water temperatures stem with per ved with the relief sys were fully achieved w
n
'densation, the in and during con Both during vent clear ng quencher.
Bot ur arl below the values e
am litudes vere clearly o
measured pressure amp u
P ecified previously.
total of about 100 ven From 20 to c
30 October
- 1974, a tota o
ed Srunsbuttel nuclear ests were performed Srun ed in the Srun an d condensation tes s
rin t e ot tests wit t o
hree)safety/relic rin the non-nuclear ho power plant during t e h
the development it was demonstrat h
ed that valves.
In these tests ts r of ts and the large number cted during the tests The values select e
'hamber are shown ressure measuring points in e
the suppression c
f the relief system p
d 2. 2.
The nsi trumentation o
e in Figures 2.1 and e
2 ~ 3i itself is illustrated in Figur and condensation we" ~
loads during vent clearing an c
In the tests, the loads dur g
imits.
The ranges the operating limi s.
thoroughly inves g
sti ated along
'n ra ge are shoe-..
d lso the operating ra tested during the ttests and a s Figure 2.4.
12-6
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3.
Pressure load on the su ression chamber 3.1. Vent clearing Of primary interest during the vent c clearin tests are the press re oscillations whic resu h
lt from the expulsion of air from the relief system into the water pool and which depend on the reactor time conditions in the blowdown pipe and
- pressure, valve opening t e,
1 The valve opening times were varied temperature of the water poo
.el fast valve by insert ng one o
i or two control valves.
Extrem y
opening was achieved wi ni
'th
'trogen as control medium unde" a
r
- ressure, in order to simulate pressure higher than the reactor pre even the most unfavorable conceivable beha vior of an initially seising valve.
At first, the initial conditions in the relief system were care-ature, air content and water fully adjusted in regard to temperatur level.
Tests were also performed with air overpressure in the pipe.
The later ser es es s
i t t started from initial conditions as they are set during operation.
I Figure 3.1 shows the maximum measured pressur p
e am litudes in the d
") and heated quencher's vicinity at the L-joint for col hamber.
Figure 3.2 depicts the (W~~ C) water in the suppression chamber.
ts at the spherical shell.
No clea=
corresponding measurement points a
lief s stem is eviden influence of the initial conditions in the relic y.
am litudes rise slightly (as On the other
- hand, the pressure amp i erature (Figures 3.l and 3.2)
~
expected) with increasing water temperatu 12-7
a sli ht'ise of the pressure ampli-Also as expected, there is a s
g r
tudes wi ve
'h vent clearing pressure (Figure 3.3).
Mhen a re i 'd re eatedly at intervals of a few when a relief valve is actuated repea e
bottom-pressures arise beginn' innin with
- seconds, somewhat higher This phenomenon vanishes for xs intervals in the second clearing.
The maximum pressure ampli'tudes that occurred the minute, range
~
el
/~%bar, were measured in this way at in the tests, approximate y
with the water pool heated up above the rated reactor-pressure and wi Fi ure 3.
s o
4 h ws the maximum press re operating temperature.
g "interval tests" at the L-join and amplitudes measured in these n
at the sp erica th herical shell for lower (Q9C) an high (gW") water temperatures.
5 and 3.6, the envelopes of the p e
ressure amplitudes'n Figures 3.5 t the spherical shell are compared measur ed at the L-joint and a
-called ed to enchers and the so-ca with the KKp Specification adapte qu base load of the KKB Specification still valiid for plain ended es at the L-joint are at pipes.
T e rc e h
l vant measurement values a
e s cification limits.
most bar an
%@VS",b d thus lie far below the spec'alues at the spherical shell are even The relevant measurement values at e
smaller compare to d
the specification values.
alised pressure distribution in the Figure 3.8 shows the norma ise according to n.
The pressures decrease a
vertical center section.
s over and above this base load are specified d
i (F'
7) in the vicinity of the blow own
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1 r ion> vhere R is the 1/R law in the lower p
~
s the encher No the circle which circumscribes qu Above the taken for is.
n th
. in the specifications-arl to sero at the vater pressure decreases linear y the radius 0-credit vas quencher>
level.
ressure distzibutinn in the Figure 3.9 depicts the normalized pressur The validity of the 1/R law is circumferential direction.
e confirmed here also.
11 the absolute distribution curves of In Figures 3,10 and 3.
m ared vi'th the maximum pressure the KKP specification are comp vant tests for the vertical am litude of az a~~t measured in relevan e
p er This representation erential direction.
center section and circumfer e large reserves demonstra y
ted b the tests.
makes clearly evident the arge ad acont valves and also circum-Zn a series of teats, closely adjacon va re o ed o r
imultaneously.
The measure-ferentially remote valves mar inference of increased pressure values ment values allow no se no special effects individual tests.
likewise, no compared to the ation and clearing vere s p po u er sed at occurred vhen condensa on an I
adjacent quenchezs.
ed during vent clearing ex exceed the specs.
The un p
under ressures measur Q~~ bar occurr<
nl one test in vhich fied@~+bar slightly in on yit of the quencher.
This, also causes ony n
1 i the immediate vicinity o ll for the load absorption.
no difficulties at a
o 12-9
3.2 Condensation meet the specification.
The pressure The condensation tests also mee u hout the entire investigated
- range, amplitudes were small throug ou ran e,Figure 2.4).
A maximum of which envelops the operating range gu t
'Hz was measured in the g~tL bar at a frequency of aboutg~
z below bar).
These quencher's vicini y't (reactor pressure then be w the s ecification values.
amplitudes also remain clearly below p
C ib tion in the suppression chamber proved The temperature distr u i Thermocouple to be ve y good even ni longer condensation tests.
and height of the elements distri u e
'b t d over the circumference suppression c
er hamb r show differences lying below the maximum expected Qg Y.
12-10
- 4. Loads on internals in the su ression c3MLmber The loads measured during the tests on internals in the suppression chamber are shown in igures Figures 4.1 and 4.2 in the form of differen-tial. pressures on the lateral and vertical projected areas, respectively.
These involve equivalent static loads.
Whereas the differential pressures in the vertical direction are practically independent of the distance above the quencher, the lateral loads 1
above the submergence of the quencher decrease linearly to zero at the water level.
The measurement results remain clearly below the specified values.
It must still be taken into consideration that dynamically acting loads were speci i u
'f'ed but equivalent static loads were indicated from the measured stresses.
All dynamic effects are thus contained in them.
The measured lateral loads decrease toward the water level faster than was specified.
12-11
- 5. Loads on the relief s stem Figure 5.1 shows the measured vent clear g p in ressures as a
function of the reactor pressure.
The highe p
est ressure of Q3bars tially seizing valve, with resulted during the simulation of an ini '
a ressure higher than the nitrogen as control medium under a p reactor pressure.
i e and at the valve suppo The
. vert ical for ce at the blowdown p pe in Fi ure 5.2 as a function of during vent clearing is plotted n
g measured values are clearly lowe" the vent clearing pressure..
The measur than specified.
the encher arms are composed The bending stresses measured at the quen oad and a second component of one component due to an external loa nt
. due to mass inertia forces.
The division is presently being analyzed on the bas s o i
f the measured ~venent of the quencher.
ations rmits the conclusion The present status of the investiga o
pe e covered by the specification.
that the measured external loads are covere sured in the bracing of the The magnitude of the stresses measured arin of the associated quencher protective tube during the clear ng o could not be explained at first.
During p
an ins ection of the that the b)owdown pipe structural condition, it was discovered ective tube.
The current status of was resting against the protect ve u
s subject permits the conclusion that the analysis initiated on this su ec p
x lained by the structural condition the measured forces can be explaine y
e 12-12
KKB relief valve tests ES~<<r<<<<
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KRAFTMERK UNION AG PROPRIETARY
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Z,ist of references
/1/ -Backer, Frenkel, Melchior, Slegers Construction and des gn o i
f the relief system with perforated-pipe quencher KWU/E 3 - 2703, July 1973
/2/
- Backer, Bo nn, ffma Knapp Kraemer, Melchior, Meyer, Schnabel I
KKB Vent clearing with the perforated-pipe quencher KWU/E 3 - 2796, October 1973
/3/
Rupp KKB Specification for the blowdown tests in the non-nuclear hot test,.
KWU/V 822, Revision I, October 1974
/4/
Backer, 65bel, Rupp Expected values of e
th blowdown tests with the relief system in the.non-nuclear hot test in.the Brunsbuttel nuclear power plant KWU/R ll - 3141, September 1974
/5/
Backer in relief Pressure loa ng o di f the suppression chamber dur g
processes Pirst results of the non-nuclear hot tes s
eats in the Brunsbuttel nuclear power plant of October 1974 KWU/R, 11, 4 November 1974
/$/
Gobel RKB hot test results
'Loads on internals in the pool of the suppression chamber during relief processes.
KWU/R ll, AN 203, 13 November 1974
/7/
Gobel KKB hot test results Maximum vertical load on the restraining structure and the bio@down pipe during vent clearing.
KNJ/R ll, AN 220, December 1974 12-33
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