ML17138A544
| ML17138A544 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 06/20/1975 |
| From: | Rupp PENNSYLVANIA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17138A531 | List: |
| References | |
| V-822-TA, NUDOCS 7903150366 | |
| Download: ML17138A544 (63) | |
Text
as translated into ENGLISH KKB SPECIFICATION FOR TESTS TO SUPPLEilEiHT THE RELIEF VALYE TESTS DURIi'lG THE i'<UCLEAR START-UP as translated from KKB SPEZIFIKATION DER 7 VENTILTESTS DER NUK NOT4CE THE ATTACHED FILES ARE OFFICIAL RECORDS OF THE DIVISION OF DOCUMENT. CONTROL.
THEY HAVE BEEN CHARGED TO YOU FOR A LIMITED TIME PERIOD AND MUST BE RETURNED TO THE RECORDS FACILITY BRANCH 016.
PLEASE DO NOT SEND DOCUMENTS CHARGED OUT THROUGH THE MAIL. REMOVALOF ANY PAGE(S) FROM-DOCUMENT FOR REPRODUCTION MUST BE REFERRED TO FILE PERSONNEL.
WUYHCIR/G/:
DEADLINERETURN DATE 9o-35"7 KM 20.
(P 9I'TII:iiJ 'Wf B)F')(VAii ra~
~.
AK IIVW gggggji RECORDS FACILITYBRANCH lR'rmea8CJ AUGUST 1977 VOOSZ50'5~
rOOCc PPaL PE N N S Y LVA8 I A P0 V/E R
& LlGHT COMPAI'uY.
ALLE)ITO'iYII.FE.'IiISY".~'II4 L>ig 71 BAANARQ AV".'JUE. 'iVATER i 0'iVN
PROPRIETARY INFORMATION This document has been made NON-PROPRIETARY by the deletion of that information which was classified as PROPRIETARY by KRAFTNERK UNION AG (KWU) ~
The PROPRIETARY information deletions are so noted throughout the report where indicated by V
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)
...." with a mass flow density of5~~1 Kg/m2s... ";
MMM'm should he kept helowPZWZP-atm."
VAPz 8/l7/78
l' l'
Topic:
BrunsbGttel nuclear power plant List of test parameters and most important measurement results of the non-nuclear hot tests with the pressure relief system
Reference:
KKB Summary:
Wumber Karlstein, 1 Au ust 1977
- ace, te Hoffmann R 521 337 Schmid R 521 328 u
ors Dept.
Tel.
2 5
C ass Signature Classifier R 521-Hff 1551-140 114 Fx e no.-
This report contains a summary of the most important measurement results of the non-nuclear hot tests with the pressure relief system in the Brunsbuttel nuclear power plant (KKB).
The results are presented in the form of Tables and gra'phs.
The content of those documents are briefly described.
In particular, the following subjects are discussed:
-.test parameters pressure load on the ntructures of the suppression chamber
- loads on the structuies of the pressure relief system.
A complete compilation of the instrumentation diagrams is not included.
Reference is made to,the Test Specification
/1/ for them.
The designations used for measurement points in this report corrospond to that Test Specification.
Countersigned Mitt Dr. Becker Author '
signature Hoffmann s/
Schmid Distribution list 3x R142 lxRF14 1 x R 52 4 x R 521 (rs Rl R14 R
5 R522 R523 a Summary for info only)):
s.K.
Xraftwerk Union 14-1
l
Brief descri tion of contents
- l. Abbreviations used Cerman English DES maxi rel.
SEV PSS PRS SC max.
re 1.
SRV PV pt D Pressure suppression system Pressure relief system Nsin valve Suppression chamber BrunsbGttel nuclear power plant maxim~
Reactor pressure vessel relative Safety/relief valve
(>> 4 MV)
Pilot valve pm/m 14 2
)
Topic
'runsbuttel nuclear power plant List of test parameters and most important measurement results of the non-nuclear hot tests with the pressure relief system
Reference:
KKB Summary:
Number Karlstein, 1 Au ust 1977
- ace, te Hoffmann R 521 337 Schmid R 521 328 u
ors Dept.
Te 2
s/
C ass Signature Classifier R 521-Hif 1551-140 114 Fz e no.
This report contains a summary of the most important measurement results of the non-nuclear hot tests with the pressure relief system in the Brunsbuttel nuclear power plant (KKB).
The results are presented in the form of Tables and graphs.
The content of those documents are briefly-described.
In particular, the following subjects are discussed:
-.test parameters
- pressure load on the structures of the suppression chamber loads on the structuies of the pressure relief system.
A complete compilation of the instrumentation diagrams is not included., Reference is made to,the Test Specification
/1/ for them.
The designations used for measurement points in this report correspond to that Test Specification.
Countersigned Witt Dr. Backer s/
Author '
signature Hoffmann s/
Schmid Distribution list 3x R142 lxRF14 1 x R 52 4 x R 521 (Pz K
II Rl R14 R 5 R522 R523 Summary for info only)):
zoK.
Xraftwerk Union 14-1
I
~
~'r r P'It
- 2. Introduction In accordance with the goals set in the Test Specification /1/i primary emphasis in 'the KKB non-nuclear hot test was 'on pre-operational tes ting of
- the behavior of the components of'he pressure relief system and
- the magnitude and distribution of pressures in the suppression chamber.
The test results relevant to these subjects are discussed separately in the following Sections.
Comments are made only when necessary to understand the Tables and Figures.
~P
~
r We shall dispense here with a detailed description of the test arrangement and instrumentation, which are reported upon at length in /1/.
The overall arrangement of the pressure relief system inside the pressure suppression system is shown in Fig. 1.
The arrange-ment of the 7 SRV in the suppression chamber is shown in Fig.'..
The three blowdown quenchers A,
B and C, with which the blowdown tests were performed, are on the 135'A), 105'B) and 35'C) meridians.
The most important measurement transmitters for evaluating the pressure relief system and their exact positions can be seen in Figs. 3-5.
Fig.
3 is an enlarged section of the suppression chamber with the blowdown quenchers A,
B and C and the positions
\\
)
of'he pressure transducers.
Fig.
4 shows the arrangement of P
~
~
~P
~
the pressure transducers in the meridian cross-section.
Fig.
5 14-3
~
~
"l
shows the pressure relief system with blowdown quencher B on the 105'eridian, on which most of the blowdown tests are concentrated.
For further identification of the measurement transmitters and their positions, we refer here once again to the Test Specification /1/.
~
A complete list of the test parameters is given in Tables 1-7.
They include the relevant parameters for the blowdown tests:
- blowing SRV and quenchers (main valves),
- control medium (P
~ nitrogen
- ~ steam)
N2 I
I
<< time between actuation of the control module on the control panel (t E),
)
rel '
)
rel
'iquid lovel in RPV beforo awitching off the axial-flow pumps (8
)
- number of axial pumps actuated (A - P ),
x p
- initial liquid level in RPV (HA) r
- max. liquid lovel in RPV during valve opening (8
)
max
- final liquid lovel in RPV (HE),
liquid level in RPV after connecting the axial-flow pumps ACH) '
condition in blowdown pipe before the test
'I CC ~ clean conditions yes
~ aerated no
~ not aerated
- pool temperature before beginning of test (T )
~
K 14-4
~l r
I
~
~i
- 4. Load on the structures of the su ression chamber The pressure values indicated in Tables 8 - 27 represent maximum values of the measured dynamic pressures during the vent clearing phase.
The following subdivision was made:
- Pressures in 135'eridian in Tables 8 - 12,
- Pressures in 105'eridian in Tables 13 - 17,
- Pressures on periphery of conical bottom in Tables 18 - 22,
- Pressures on periphery of spherical shell in Tables 23 - 27.
To clarify the pressure distribution in the meridian cross-section at 135', Fig.
6 shows as a representative example the distribution measured in vent clearing test no.
8 with quencher A at a roactor pressure of ca.
70 bar.
The measured maximum values of the pressure amplitudes decrease approximately in proportion to the distance from the quencher.
This results in a distinctly reduced load on the spherical shell in comparison to the Specification values.
In addition, the absolute maximum values noasured by individual pressure transducers in all blowdown tests are entered in pig. 6.
In Tables 18 - 22 for the measured pressures on the periphe'ry of the conical bottom, pressure transducers DA 3 and DA 13 were recorded additionally and considered together with DA 4 and DA 14 as "unit", i.e.,
as the pressure under'he quencher.
Tables 28 - 32 contain the corresponding noznalised values of 14-5
4
'I the positive dynamic pressure amplitudes at the individual measurement points.
The normalisation was made to the maximum value of DA 4(3) and DA, 14(13).
The max. positive pressure amplitudes themselves are indicated in the column " pmax The normalized values are listed separately in Table 33 for the 16 tests having the highest positive pressure amplitudes at the conical bottom, namely~~~~~~~~3 For comparison, the specified values are listed too.
Table 34 shows as the result a comparison of the specified values with the scatte" band determined from the 16 tests mentioned above.
Figure 7
represents the normalised pressure distribution in the circum-ferential direction. It also confirms the validity of the 1/R law.
- 5. Load on the structures of the relief stem The strains and defloctions indicated in Tables,35 - 40 repre-sent the maximum values measured during the vent clearing phases.
This compilation is oriented toward the measurement points DS 26/27 on the cladding tube struts.
It'ncludes all tests I
in which those measurement points were applied.
In particular, Tables 35 - 40 contain the measured dynamic strains and deflections of cladding tube, blowdown pipe, perforated-pipe
- quencher, bottom mount and cladding-tube struts.
The strains measured at the measurement fin welded to the inner cylinder are also indicated.
For correlation purposes, the strain of the inner cylinder above the sandwich reinforcement 14-6
and also'he deflection of the conical bottom below the quencher are indicated too.
The strains and deflections indicated in Tables 41 - 46 likewise represent maximum measured values fioa the vent clearing phases.
In contrast to Tables 35 - 40, thii list is oriented toward the measurement points DS 42/43 on one of the quencher arms.
It encompasses all tests in which those measurement points were applied.
s
~
In particular, Tables 41 - 46 contain the measured dynamic strains and deflections of the blowdown pipe and perforated-pipe quencher.
For correlation purposes, the vent clearing pressure and max. bottom pressure are also shown.
These results are analysed and interpreted thoroughly in /2/.
\\
- 6. References
/1/ KKS Specification for the blowdown tests in the non-nuclear hot test Revision 1 of 4 October 1974.
/2/ Analysis of the loads measured on the relief system in the KK8 non-nuclear hot test Technical Report KWU/R ll/R 31 - 3346 14<<7
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Liquid level vas read off
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KRAFTWERK UNION AG PROPRIETARY INFORMATION Table..
8 through 46 14-15 through 54
i l
~
l' I
4
@ET 1
Safetylrelief valve
- 2. Fittiag vith orifice plate
- 3. Neatraiaiag atructure
- 4. Ceeectiooe foi anifter valve (total of 2)
+ 27,.200 5.
Protective tube Slovdova pipe 7.
perforated-pipe jueacher 8.
Bottom aouat nttostui s-I Sich"rhe t v
t't a.
'FOrmStuak mit R hrbleJde ferns gnakonstruktion
.I!:;
~
AnschluA fur Schniif'~lven'il (insgcscrnt 2 Stuck)
Schut2robr g Abblaserohr
~C~ a.~.c" 2000
- +20,000
. r~
'.f 8,890 Ln Ol c
Qj,',t,'ocbrohrd Use
+14,915 9 Bodenhclt" n"
4J
~JJ A ~
%KB treasure, relief system
',,tigure 1 t,
14-55
I f
I
F l10 4'g
~rtm/re
~
gI ~'lI~ S
//
I i
/
'I KEY!
- l. Concrete-free sons.un'der cone
- 2. Concrete-free
- 3. Measurement fin
- 4. Steel support
- 5. Concrete column KKB-HeiOtest Abbla seversuchc
't I
- Anordnung derAbblasedUsen in der
'ondensationskamrner-XKB hot teat>
blovdown testa, 1xrengement of bloitdcwn, quenchers pl((j in the suppression chamber tEquie'~
14 56
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KKB relief valve tests
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KRAFTWERK UNION AG PROPRIETARY INFORMATION 6
Fxgureo
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14-60
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KRAFTWERK UNION AG PROPRIETARY INFOÃ4ATION Figureb
~ ~ ~ ~ ~ ~
7 14-61
I
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 ofLW~~ Kg/m2s.
~
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ii)
W mm iii)...." should be kept below P/KZZ~ atm iv)
WP 8/17/78
KKB Specification for tests to supplement the relief valve tests during the nuclear start-up June 1977 Kraftwerk Union 15-1
TO: Internal PROM:
V 822/TA distribution NAME: Rupp PHONE:
2490 YOUR FILE NO.
AND LETTER OF:
OUR FILE NUMBER: Rp/Ri NOTES ON RECEIPT:
DATE: 20 June 1975 KKB Specification for tests to supplement the re'ie valve tests durin the nuclear start-u I am sending you enclosed the signed Specification (Rev.
- 1).
Concerning the changes made in Rev.
1, all that need be aentione' Temperature limit where long-term test is to be ended prematurely (Section 2)
- The Pressure lowering with relief valves" test series could also be executed in a hot test (KKP or KKI) if necessary (Section 3)
- Equipping of all 7 relief valves with fast measurement of control pressure (last Section)
- Slight change in the mounting of the strain gauges m the struts (Figure 2)
Please replace the old copy of 29 April by Revision l.
V 822/TA
/s/ Rupp Internal distribution:
External distribut ".-:
1t 111 111 113 113 11 113 31 R 314 R 314 R~ ii~
314 R 322 R 322 Dr. Koch, R
Pron)col, R
GS.osselor, R
Dr.5obot t!co, R
Dr Bockcr, R
Dr Prouschc, R
Br)LuhKuscr, R
Stu.pr,,
R
- Vebcr, Feist, BlaCS~
- 5chmitt, Kuscho 1,
- Anderson, vxa RS
)
TUV North Germany 3 x Institute for Reactor Safety I x KKB client Sx Dr Simon, R 5" 1 Dr.Melchior, R 522 Ecl'crt, RS 12 Frol.lich, RS 12 Sur th, RS 12
- Romohn, VF 13
- Koch, V '2 liart o 1, V 822-KKD Dietricb/KarSer, V 622/TA Nitschlco, V 622/TA-iD'"
- Rupp, V 622/TA 2xc
- adolf, V 822/TA 15-2
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KWU V 822/TA Offenbach, 20 June 1975 Rp/Ri KKB Specification for tests to supplement the relief valve tests during the nuclear start-up Revision 1 of 20 June 1975 This supplemental specification is a supplement to the Power Testing Tnstruction No. 23, "Relief Valves".
Prepared:
Checked:
/s/
/s/
/s/
/s/
(Rupp, V 822/TA)
(Dr. Koch, R ll)
(Kuschel, R 322)
(Weber, R 314)
I
Test ro ram for relief valve tests Test no, Reactor Valve no.
Blowdown Remarks pressure duration (bar) 1-7 8-12 13-14 15 16 17 18 19 20 21 22 70 Beginning with 30 s each valves A"G* in alphabetical, order, indivi-dually C-G 30 s each Znitiation by pilot relief valve 70 70 AgB 1) 70 B
2) 70 Pressure lowering via 70-50 50-35 35-23 B
ca.
125 s
ca.
3 min ca. 2;3 min B
A+B simul-taneously A+B A+B 25 min 25 min 23-14 ca.
4.3 min ca. 6.5 min 25 min 30 min 14-8 8-4. 5 A+B ZnxtxaMon by palo sa fety valve 20 s each Associated valve
~'nxtl.ation by pilot safety valve 3
m max.
With supp.
chamber cool.'..-..
3 m max.
Without supp.
chamber cooling and recircula ic;.
relief valves 3g Holding pauses due to R
'5 ain
~)
The valve designations are as follows (see Figure 1):
A ~ Ra 21/S 211 D ~
Ra 41/S 221 G a Ra 31/S 211 B ~ Ra 21/S 221 E ~ Ra 41/S 211 C ~
Ra 11/S 211 F ~ Ra 31/S 221
~" Tr. note:
Word cut off here at right side of German page.
First few letters of German word (gesch) make it likely that the missing German word is geschlossen
~ closed.
15-4
After all preparations are made for performing the tests and recording the data, the associated isolating valve Ra 21 S 101 is closed.
After 20 s (for steady-state),
relief valve A is opened for 20 s.
20 s after A is closed again, isolating valve Ra 21 S
101 is reopened.
Test no.
14 for valve B is performed in the same way.
- 2) Long-term tests for temperature distribution Using valve B, bio@down should be performed for a maximum of "3 minutes in each instance at a reactor pressure of 70 bar.
Initial temperature of the pool should he 34~C.
A reactor scram due to too high temperature of the suppression chamber eater
(>45') must be avoided.
Thereforeg the test should be terminated prematurely if two out of three temperatures in one leg are >424C or if one temperature is >45'C.
The three temperature legs are composed as follovs:
Leg 1:
2 TH 03 TO21, 1 TH 03 TO22, 3 TH 03 TO23 Leg 2:
1 TH 03 TO24, 3
TH 03 TO25, 2
TH 03 TO26
'Leg 3:
3 TH 03 T027, 2 TH 03 TO28, 1
TH 03 TO29 tor spatial configuration of the temperatures, see LP23, Figure 5.
Reactor scram is triggered if 2 out of 3 in one leg reach ) 45'.
The temperatures are monitored by temperature recorders.
15-5
- 3) Pressure lowering by relief valves:
The purpose of these tests is to get an exact flow-rate measurement in the range of low reactor pressures.
These tests
~re to be executed with the reactor shut down. It is therefore appropriate to combine them with the shutting down of the plan..
The permissible cooldown rate of the RPU is to,be respected:
50'C/h between 285'nd 180'0'C/h below 1804.
To accomplish that, the specified holding pauses are to be respected.
It should be made certain that the water level in the RPU does not drop impermissibly.
The axial-flow pumps are to be shut off and interlocked during the blewdown.
The suppression chamber cooling system should be in operation.
The pressure lowering by relief valves might be eliminated if m
these tests are able to be executed on a more favorable time schedule during the hot test of a subsequent plant.
Instrumentation:
Figures 1 -
3 show the operating measurement points and the special measurement points.
The following special measurement points are to bq'nytalled:
For all valves (Pigures 1+3),, fast pressure transmitters to measure the transient pressure variation of the control pressure.
15-6
- At the flow limiter pf valves A+B, support 2, an additional fast pressure-transmitter (measurement range 3.5 bar) in order to be able to record the flow-rate variation during the opening period.
- 2 vent-clearing pressures PDg &nd PD10.
- 2 bottom pressures DA 4 and DA 14.
4 strain gauges each on the two struts to the cladding tube, quencher B.
2 strain gauges each on the two struts to the cladding tube, quencher A.
2 strain gauges each on the two struts to the cladding tube>
quencher E.
For quenchers A and B, the cladding tube presses against the hlowdown pipe, but not for quencher E.
The temperatures after the valves (total of 21) and in the pool (12) are to be recorded also during the entire test period.
The temperatures in the pool must be recorded fast enough for monitor-ing of the pool heating.
The time between 2 consecutive tempera-ture interrogations should be 2 s.
V $22/TA Rupp C
Encl.
h
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KKB BLC%DCAlà TESTS Nuclear start-up Statuss i/29/75 Rev. lx 6/20/75 figure 1 KKB Abbloscvc'rsuchc'
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409/75 tigure 3
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