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
Fl Ci as translatediri to .F.
F. N.G L.I. S.H Co
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RESULTS OF THE NOi'-i' OIJ-llUCLQR HOT TESTS ']tITH THE SYSTEi"i IÃ THE BRUflSB0 RELIEF 3 TTEL f'fUCLEAR PO'tER PLAI]T l
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%0 ERGEBNI SSF DER NICHTN IH 'NTLASTUNGSSYSTEN NOTICE C Q
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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.
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I Dffenbach 20 Dec. 1974 KRAFTWERK UN)ON Fl 'ate Technical Report EMU/R 113-3267 File number R 113 3267 Be mr R 113 Author Dr. Becker 5 epartment Countersignature
Title:
Pages of text:
Results of the non-nuclear hot Figures:
tests with the relief system in Circuit diagrams:
the Brunsbuttel nuclear power plant Diagr./oscillogr.:
Key words (max. 12) to identify Tables:
the report's content: Reference list:
suppression chamber, relief system, thermohydraulic loads, test results with actual geometry 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/ /s/ II Dr. Becker Dr. Koch Class ifier Class Foz zn ormatzon Distr'tzon est:
{cover sheet only): lx KWV/GA 19 Erl lx PSM 22 Ffm ransmzssxon or up cat on o zs ocument, exp oztatzon or com- .
munication of its content not permitted unless expressly. authorized.
Infringers liable to pay damages. All rights to the award of patents or registration of utility patents reserved.
'2-1
Distribution list internal R - Ffm RZR 1 2 X as RS 1 Rs 11 RS 1/KRB RS 115/GET
~ RS 12/>~~
RS 12/U"'S 1 3/h4>'S RS 14/REX RS 15 RS 2 RS 21 RS 213 R 11 Ffm R 11 - Erl R 111 2 X R 113 X R 113-SD X R 114 R 213 2 X R 3 R 314 3 x R 32 R 322 R 52 R 521 5 x R 522 V 822 TA 2 X R 311 1'0
NONLIABILITYCLAUSE This report is ha se d on the current technica ical knowledge of KRAFTWERK UNION AG. However, TWERK UNION AG KRAFTWERK and all persons acting in its b e half make no guarantee. Xn par ticular, cu they are not liable for th e correctness, accuracy ac completeness and corn of the data contained n thiss observance of third-report nor for thee observ party rights.
i or the expertss licensing aut h oriities a This reservation does not aapp 1 y insofar as the report in fulfillment of contractual oobligaations, nor." with respect appo rt is de'ivere" es ect to inted by the."...
KRAFTWERK UNION AG reserves s aD a rights to the techn'cal informa-tion contained in this report> rt, parrticularly cu the right to apply for patents.
Further dissemination on of thiss report and of thee knowledge kn con-there in re tained th requires the written en aapp roval of KRAFTWERK UNXON AG.
Moreover, this reportt iss communicated under thee aassumption that it will be handled confidentially.
l2-3
Table of contents Page Introduction and summary 12-5 2 ~ Nature and scope of the tests 12-6 3 ~ Pressure 1 oa d on the suppression chamber 12" 7 3.1 Vent clearing 12-7 3.2 Cond casa tion 12-10 4, Loads on internals in the suppression chamber 12-11
- 5. Loads on the relief system 12"12 Figures List of references 12-4
- 1. Introduction After extensive development tests wwith t the perforated- ipe quencher in the Grosskraftw erk Nannheim (GKH) fMannheim Centra Power Station) and in the Grosswelsheheim mo e test-stand model (these test results are fully documented and innteerp reted in /1, 2/), the hot tests in the Ker nkraftwerk Brunsbuttel (KKB) Brunsbuttel nuclear h K power plant] wit h th e relief system represent ent confirmation tests on the actual geometry and under der acactual conditions. Expecte d values were given in /4/ for the tests specified in /3/.
The present report gives ummar o a summary of and supplement to the
/
evaluation described in detail in S 6, 7/ concerning the thermohydrau lie loads. The me measured values lie within the i
oxpected range. There s an adequate margin between the speci-fied limits and the test results,s gen enerally with large reserves.
In particular, the max imumum bottom-pressure for relevan tests was Qj~3 bar. This measured value iss to be compared to a specificQd value of Q~3 kg/cm 2 .
In summary, the results can be designs ted as very satisfactory.
12" 5
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- 2. Nature and sco e oof the tests From 20 to 30 October c 1974, a total of tota o about 100 ven t c earing an d condensation tes estss were performed ed in the SrunSrunsbuttel nuclear power rin tthee non-nuclear hooot tests wit plant during '
three)safety/relic valves. In these tests it was demonstrat ed that h the development goals, namely
" lowering o f the pressure loadd on the suppression 'on chamber durin" vent clearing by pass assive measures, and n u to hiig h water temperatures were fully achieved ved wwith the relief sysstem with per quencher. Both during Bot ur vent clear innng and during 'densation, con the measured pressuree am litudes amp u vere arl below clearly o the values ecified previously. P The values cted during the tests select ts and the large numberr of p ressure measuring po ints in thee suppression 'hamber c are shown in Figures 2.1 andd 2. 2. The ins trumentation o f thee relief system itself is illustrated in Figur e 2 3i ~
In the tests, the loads duringdur g vent clearing an and ccondensation we" ~
thoroughly invessti g ated along the operating limi imits. s. The ranges tested during the tests andd a lso s the operating 'n ra ge are shoe-..
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 clearin c tests are the press re oscillations whic h resu lt from the expulsion of air from the relief system into the water pool and which depend on the reactor pressure, valve opening ttimee, conditions in the blowdown pipe and temperature of the water poo 1 The valve opening times were varied by insert ing one oro two control valves. Extrem.el y fast valve opening was achieved wi'th ni'trogen as control medium unde" a pressure higher than the reactorr pre ressure, in order to simulate even the most unfavorable conceivable beha vior of an initially seising valve.
At first, the initial conditions in the relief system were care-fully adjusted in ature,,
regard to temperatur air content and water level. Tests were also performed with air overpressure in the pipe. The later ser ies t es t s started from initial conditions as they are set during operation.
I Figure 3.1 shows the maximum measured pressur e am p litudes in the quencher's vicinity at the L-joint for col d ") and heated (W~~ C) water in the suppression chamber.
hamber. Figure 3.2 depicts the corresponding measurement ts aat the spherical shell. No clea=
points influence of the initial conditions in the relic lief s y stem
. is eviden On the other hand, the pressure amp i am litudes rise slightly (as expected) with increasing water temperatu erature (Figures 3.l and 3.2) ~
12-7
there is a ssli g ht'ise
'd Also as expected, r of the pressure ampli-tudes wi 'h vent clearing pressure (Figure 3.3) .
ve when Mhen a re i valve is relief actuated repea re eatedlye at intervals of a few seconds, somewhat higher bottom-pressures innin with arise beginn' the second clearing. This xs phenomenon vanishes for intervals in the minute, range ~ The maximum pressure ampli'tudes that occurred in the tests, approximateel y /~%bar, were measured in this way at rated reactor-pressure and wi with the water pool heated up above the operating temperature. Fi g ure 3. 4 s h o ws the maximum press re amplitudes measured in these "interval n tests" at the L-join and at th the sp herical erica shell for lower (Q9C) an high (gW") water temperatures.
Figures 3.55 and 3.6, the envelopes of thee p ressure amplitudes'n measur ed at the L-joint and a t the spherical shell are compared with the KKp Specification adapteed to qu enchers and the so-ca -called base load of the KKB Specification still valiid for plain ended pipes. .* T h e rc l e vant measurement values es aat the L-joint are at most %@VS",b
. bar an d thus lie far below thee s cification limits.
spec'alues The relevant measurement values at thee spherical shell are even smaller compare d to the specification values.
Figure 3.8 shows the normaalised ise pressure distribution in the vertical center section.n. The pressures decrease aaccording to s over and above this base load are specified in the vicinity of the blowd own i (F' 7)
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the 1/R law in the lower p 1 r ion> vhere R is the radius 0-the circle which circumscribess the qu encher
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. No credit vas taken for th is. inn the specifications-
. Above the quencher>
pressure decreases lineararl y to sero at the vater level.
Figure 3.9 depicts the normalized pressur ressure distzibutinn in the circumferential direction. Thee validity of the 1/R law is confirmed here also.
In Figures 3,10 and 3. 11 the absolute distribu tion curves of the KKP specification are comp m ared vi 'th the maximum pressure am p litude of a~~t az measured in relevan
. vant tests e for the vertical center section and circumfer erential direction. This representation er makes clearly evident thee large arge reserves demonstra ted b y the tests.
Zn a series of teats, closely ad acont va adjacon valves and also circum-ferentially remote valves marrre o ed o imultaneously. The measure-ment values allow no inference of increased p ressure values compared to the individual tests. likewise, se no special effects occurred vhen condensaation on anand clearing vere s u p er po sed at adjacent quenchezs. I The ununder p ressures measur ed during vent clearing ex exceed the specs.
fied@~+bar slightly in onnl y one test in vhich Q~~ bar occurr<
ony1 in the immediate vicinity oit of the quencher. This, also causes no difficulties at a ll for o the load absorption.
12-9
3.2 Condensation The condensation mee the specification.
tests also meet The pressure amplitudes were small throug ou the entire investigated range, u hout which envelops the operating range ran e,Figure gu 2.4). A maximum of g~tL bar at a frequency of aboutg~ t 'Hzz was measured in the quencher's vicini't y (reactor pressure then below be bar) . These amplitudes also remain clearly beloww the s p ecification values.
The temperature i in the distr ibu tion suppression chamber proved C
to be ve y good even in longer condensation tests. Thermocouple elements distri'b u t e d over the circumference and height of the suppression c hamb err 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 igures 4.1 and 4.2 in the form of differen-chamber are shown in Figures 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 i , butu equivalent static loads were indicated loads were speci'f'ed 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 ing p ressures as a function of the reactor pressure. The higheest p ressure of Q3bars resulted during the simulation of an initially seizing valve, with nitrogen as control medium under a p ressure higher than the reactor pressure.
The . ver t ical for ce i at the blowdown p pee and at the valve suppo during vent clearing is plotted inn Fi g ure 5.2 as a function of the vent clearing pressure.. The measur measured values are clearly lowe" than specified.
The bending stresses measured at the quen encher arms are composed of one component due to an external loa oad and a second componentnt
. due to mass inertia forces. The division is presently being analyzed on the bas is o f the measured ~venent of the quencher.
The present status of the investigaations o pe rmits the conclusion that the measured external loads aree covere covered by the specification.
The magnitude sured in the bracing of the of the stresses measured protective tube during the clear arinng oof the associated quencher could not be explained at first. During an ins p ection of the structural condition, it was discovered that the b)owdown pipe was resting against the protect ective ve tube.
u The current status of the analysis initiated on thiss su ec permits subject p the conclusion that the measured forces can be explainex lained byy thee structural condition 12-12
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Z,ist of references
/1/ -Backer, Frenkel, Melchior, Slegers Construction i and des gn o f the relief system with perforated-pipe quencher KWU/E 3 - 2703, July 1973
/2/ Backer, Bo ffma nn, Knapp I Kraemer, Melchior, Meyer, Schnabel 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 th e blowdown tests with the relief system in the.non-nuclear hot test in .the Brun sbuttel nuclear power plant KWU/R ll - 3141, September 1974
/5/ Backer Pressure loa ding o f the suppression chamber dur ing relief processes Pirst results of the non-nuclear hot tes eatss 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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