ML17138A546
| ML17138A546 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 09/30/1976 |
| From: | Gobel PENNSYLVANIA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17138A531 | List: |
| References | |
| R142-136-76, NUDOCS 7903150372 | |
| Download: ML17138A546 (31) | |
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I PROPRIETARY INFORMATION This document has been made NON-PROPRIETARY by the deletion of that ipformation which was classified as PROPRIETARY by KRAFTNERK UNION AG (KWU);
The PROPRIETARY information deletions are so noted
) throughout the report where indicated by INFORMATION a) Use of the term KRAFTWERK UNION AG PROPRIETARY b) Use of blocked out areas by cross hatch bands in the report text and figures/tables, e.g.'i)
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Working Report R 142 - 136/76 Topic: N er epartment no. year KKB - Nuclear start-up Offenbach, 30 Se tember 1976 Results of the tests with ace, ate the pressure relief system Gobel R 142 3245 Reference (e.g., Project, ut or Department Te .
RtD project) s ass signature c assxfier x e number The res its of the tests with the pressure relief system during the KKB nuclear start up confirm the reSults of the )(KB non-nuclear hot test of October 1974. The measured maximum vertical force qn the blowdown pipe is aboutg~Q'kN. Computational extra-polations show that, even under extrem~ assumptions (reactor II pressure++bar, valve opening time g~lms), the specified'value of g~~ kN is not exceeded.
The pressure amplitude at the bottom during vent clearing is at most~~bar (measurement value) and is thus withiq the scatter range of the hot-test results.
I The maximum strut load on the struts of the protective tube's
+~kN and is thus also within the scatter range of the hot-test data and far below the spyCified load of Q' kN.
ll s s Countersignature Author s signature Distributionlist ("s.K." ~ summary for information only):
Kraftwerk Union 16-1
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- 1. 'Introduction hs part of the nuclear start-up of the BrunsQuttel nuclear power plant; a performance test, of the relief valves was performed at load point 2 (approximately 25% of reactor thermal power) at a reactor pressure of about 68 bar and c15 bar.
Measurements were also made on the relief system (see Figures 1-3 for measurement points) in order to confirm the results of the h
non-nuclear hot test of the relief system with respect, to bottom pressures, forces on the struts of the protective tube, vertical forces on the blowdown pipe during vent clearing.
- 2. Bottom ressures durin vent clearin V
(
To measure the bottom pressures, two pressure transducers were
(
mounted perpendicularly with respect to the quencher center point at two circumferential positions. Pressure transducer DA 4 was mounted at quencher A (1354'ee Figure 2) and pressure trans-ducer DA 14 at quencher B (105'~ see Figure 2).
The measured maximum amplitude (see. Figure 5) of Q+ bar at a suppression chamber water temperature yf about 32'C fits very well into'he scatter range measured in the non-nuclear hot teSt (see Figure 4) .
- 3. Loads on the struts of the rotective tube To measure +e strut forces, twc,struts eaCh)on three protective 16 2
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tubes were instrumented as shown in Figure 3 ~
Zn the quiescent condition there is contact between the blowdown pipe and protective tube of quenchers A and B. For quencher E there is )ust no contact in the quiescent condition, but(that does not rule out the possibility that contact is made at times during the blowdown.
The measured maxtuam strut forces are:
Quencher E ~ /+++I Quencher B ~ i%%%%%%%%%%
I >2 Quencer A ~ L++
I They are consistent with the strut forces measured in the non-nuclear hot test, so that those measurements have been confirmed
,I by the more recent measurements.
Accordingly, the design value of g~3 kN per strut is verified to be conservative.
- 4. Yertical force durin vent clearin 4.1 Determination of the vertical force by measurement W
When the water column is expelled from theI blowdown pipe,'.it is deflected by 904 in the Q arms of the perforated-pipe quencher.
This impulsive deflection causes an external force4 apting down-ward along'he axis of +e blowdown pipe. This force acts at the center. of the quencher, is conducted through the blowdown pipe 16"3
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and is absorbed in the restraining structure. This force can be measured by strain measurements on the blowdown pipe. In'he non-nuclear hot test, that was'ccomplished by two foil strain gauges glued onto the blowdown pipe in the lorigitudinal direction.
Difficulties arose in determining the strain component from the temperature gradient in the radial direction.
For that reason, for the measurements during the nuclear start-up two strain gauges were mounted in the circumferential direction
~ in addition to the two in the longitudinal direction. As di's-cussed in the following, the vertical force can then be calculated immediately from two measurement values.
A triaxial stress state prevails in the pipe wall. However,'ince measurements are made at the outer fiber where the radial stress is sero, the triaxial stress state is reduced here to a biaxial stress state. The strain relations then have the following form:
~rD in circumferential g.rection 8y + p ( C)0 i.n longitudinal direction Conversely, the stress-strain relations have the following 'form:
coefficient of transverse contracti~n t
modulus of elasticity (N/mm C ).
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The stresses are composed of several components:
g g~r Internal pressure component Temperature component
<7' ap r Internal pressure Temperature Vertical force component component component hp ~ internal pressure (bar 10 )
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r mean radius of blowdown pipe (mm) s ~ thickness of blowdown pipe wall (mm)
The stress resulting from .the vertical force can now be determined in two ways.
~
f easily eliminate the temperature From g~ ~y ~ we can stress component, since the pipe pressure is measured as a function of time.
This calculated temperature stress component is inserted into the I
following equation:
The stress component from the vertical force is then knowr..
Alternatively we can also use the relation 16-5
4.2 Measurement values Figures 7 and 8 show two representative examples of measurement traces. The following values can be read off from them:
Test Pipe pressure Water level Temperature Vertical (differential in blowdown in suppr'es- force pressure) pipe sion chamber 2/1. ~%bar %D'c 14/4 g~g bar ~c 4.3 Extrapolation of measurement values The basis for an extrapolation of the measured vertical forces to the most unfavorable conditions in the reactor plant is a computational check of the tests. The HOGEM computer program
,was used for that.
V Figure 9 presents a comparison of the measured and computed values.
The numbers above the points indicate the measurement values with which the computer results are associated. The following input data were used for checking the test results.
The steam flow rates were entered into the program directly according to the measured valve lift variation and conversion by means of the o value (see Figure 10):
The conversion was made by using the following formula:
h PR 16-6
I If we insert A in mm 2 Q~~
pR in bar (reactor pressure) x ~ 1.92 then we get the flow rate in kg/h.
Condensation at the walls of the blowdown pipe was assumed to occur 250 ms after valve opening (lowering of water level in
.blowdown pipe approximately 1 m) . The total amount that can be condensed is obtained from:
3( Pp P)- g 3
~is Ct 2 r and 6t =
kcal with a x4 h . degrees 2
6 m 4,1 ~ 1o mter level drop z a 22oo kJ/kg 16-7
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This results in a total amount of condensing steam of Q~L kg per m of water level drop.
The valve lifts approximated by a series of straight lines are illustrated in Figure 11 for the two tests.
The temperature after the relief valve was always 110'C before the beginning of the test. It can therefore be assumed that there is already a steam-air mixture above the water surface before the relief valve is opened. Inclusion of this effect in the HCGD'.
computer program had no significant effect on the final result.
In the extrapolations it was assumed that there is a pure air atmosphere in the blowdown pipe above the, water surface before opening the valve.
The input data for the computational check of the test results are illustrated below:
1500 A i~i.r ( "r .I>LA3ATw . " ( V ) ' -~ e P i ~ I ') i A L5, 1 L .<,
1510 P IMP 2tP 3iPc4oPol ~
1520 T3I,TB?,T83, 1530 TA TA I, iA 2, TA3, TAN, TA5 TA6 A 7 ~ TA 8, TA I I .
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l Do/2i/75 KRAFTWERK UNION AG PROPRIETARY INPO~TION Figure 12 represents a comparison of the calculation of the pres-sure build-up in the pipe and of the vertical force with the measurements made in test 2.1.
comparison demonstrates (as previously in Figure I'he
- 9) that the calculations with the HOGEN program reproduce the measurement data relatively well.
The following assumptions were made to determine upper values for the vertical force.
Blowdown from the pressure transient at a reactor pressure of L~ bar. Normal water level in the blowdown pipe and an air tem-perature of 35'C in the air space of the blowdown pipe. The flow rate through the relief valve was inserted as a function of reactor pressure according to Figure 13.
Condensation at the walls of the blowdown pipe was neglected.
Two valve lift curves (Figure 14) were used for the opening behavior, of the relief valve.
16" 9
,The computer results are illustrated in Figure 9.
According to them, the following vertical forces are obtained
,for vent clearing from the pressure transient:
for shortest realistic valve opening time gLMlkN for an unrealistic valve opening time of 100 ms@~WkN For the case of a valve opening time of 100 ms, a vent clearing pressure of bpf ~~'bar is calculated. This value differs from the vent clearing pressure in the Specification /1/ by
%bar. The reasons are as follows:
a) @+bar vent clearing pressure was calculated with a resistance coefficient t ~ Q~
Qggbar vent clearing pressure was calculated with < ~ ~~
h) Zn the HOGEM program, the steam is treated" like an ideal gas.
A computation of the internal energy according to the relation 4! + p ~ v showed that in the calculations for the Specification the internal energy was set too low by about 200 kJ/kg.
References Design load for the restraining structure of the relief system Spec." No.: KKB /XH/SD 010, Revision 1, December 1973 16-10
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Figure 2 KKB -nukleare tnbetriebnahme Bild 2 Ent Iostvngsventi!:ests C P ~
KKB nuclear start-.up Relief valve tests
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Entlastungsventit tests KKB nuclear start-up Relief valve tests 16-13
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KRAFTWERK UNION AG PROPRIETARY INFOKIATION Figure....... 4 14 16-l4 1 6-24
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