ML20211E084
| ML20211E084 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 02/20/1986 |
| From: | Robert Elliott, Gulde R GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER |
| To: | |
| Shared Package | |
| ML20211D893 | List: |
| References | |
| 907935, 907935-I-A, TAC-63576, NUDOCS 8702240228 | |
| Download: ML20211E084 (25) | |
Text
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GA Technologies Inc.
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ISSUE
SUMMARY
I' O R&D FSV: DELAYED FIREUATER C00LDOWii; EFFECT OF APPROVAL LEVEL 2 LINER COOLING ON ORIFICE VALVE TEMPERATURES hSfGN DISCIPLINE SYSTEM 00C. TYPE PROJECT
[00CUMENT NO. ISSUE NO TR.
N 11 CFL 1900 I 907935 A QUALITY ASSURANCE LEVEL SAFETY CLASSIFICATION SEISMIC CATEGORY ELECTRICAL CLAS$1FICAT10N 1 FSV-1 FSV-1 N/A p3 APPROVAL ISSUE PREPARED DATE gy DES RIPTION/
FUNDING APPLICA8LE ENGINEERING QA PROJECT CWBSNO.
PROJECT y /s ^ f T.
g N/C MAR 2 81985 R.Elliott A.Shenoy' .Peftycord R. QRosenb g g $5T 7:. b " -M"
( Initial Release:
k 2970 104 CA FES 1 0 IS86 R.Culde Release Basis Qg CN-005589 t
CONTINUE ON GA FORM 14851 NEXTINDENTURED DOCUMENTS Page Sur: mary: P.O.N6082 Preface / Body 21 Appendix A 1 Appendix B 1 Appendix C 2 Total Pages 25 0702240228 870217 7 PDR ADOCK 0500 F
REV A l l l SH C2 l l l REV l l l l l l l l SH 29 30 31 32 l 33 ' 34 l 35 l 36 37 38 39 40 41 42 43 44 45 46 ' 47 48 49 50 : 51 l 52 l $3 l $4 l 55 I 56 REV A lA Al l l l l A A A l l l l l SH I 2l3 4 5 6l7 8 9 10l11l12 13 14 15 16 17l18 19 20 21 22 23l24 25 l 26 l 27 l 28 MBCSTA RNTE-VAXC-80 PAGE 1 0F25
i e
l GA TECHNOL0GIES . M C.
TITLE: FSV: DELAYED FIREWATER C00LDOWN; EFFECT OF LINER COOLING ON ORIFICE VALVE TEMPERATURES DOCUMENT NO. 907935 ISSUE NO./LTR. N/C CONTENTS
- 1.
SUMMARY
........................................................... 4
- 2. INTRODUCTION ...................................................... 4 ,
3 DESCRIPTION OF THE PHYSICAL EVENT ................................. 4 4
M ETH O D O F A N A LY S I S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5
- 5. DISCUSSION OF RESULTS ............................................. 6
- 6. CONCLUSIONS ....................................................... 7
- 7. R E F E R EN C E S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 FIGURES
- 1. Delayed Firewater Cooldown, 175 psig water, with liner cooling (Case FSV2) ...................................................... 9
- 2. Delayed Firewater Cooldown, 175 psig water, liner cooling after 1.5 hr (Case FSV3) ............................................... 10 3 Delayed Firewater Cooldown,175 psig water, no liner cooling (Case FSV4) ...................................................... 11 4 Delayed Firewater Cooldown,175 psig water, Top Head Thermal j Barrier Cover Plate Temperature for Three Cases of Liner Cooling . 12 l
- 5. Delayed Firewater Cooldown,175 psig water, Top Head Liner Tem-p erature for three cas es of liner cooling . . . . . . . . . . . . . . . . . . . . . . . . . 13
- 6. Delayed Firewater Cooldown,175 psig water, Maximum Orifice Valve for Three Cas es of Liner Cooling . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14
- 7. Delayed Firewater Cooldown 175 psig water, Maximum and Average Core Temperatures for three cases of liner cooling . . . . . . . . . . . . . . . . . . . . . 15 Page 2
i
, uA TECHNOL0GIES 1 . C.
TITLE: FSV DELAYED FIREWATER C00LDOWN; EFFECT OF LINER COOLING ON ORIFICE VALVE TEMPERATURES DOCUMENT NO. 907935 ISSUE NO./LTR. A ,
1 TABLES
- 1. CASE FSV2, CONTINUOUS LINER COOLING 175 PSIG FIREWATER, DELAYED 1.5 HOUR CORE ORIFIC ED FO R 250C P . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16
- 2. CASE FSV3, LINER COOLING AFTER 1.5 HOUR 175 PSIG FIREWATER, DELAYED
- 1. 5 HOUR CO R E O RIFIC ED FO R 25 0C P . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17 3 CASE FSV4, NO LINER COOLING 175 PSIG FIREWATER, DELAYED 1.5 HOUR CO R E O R I FIC ED FO R 25 0 C P . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18 4 CASE FSV2, CONTINUOUS LINER COOLING 175 PSIG FIREWATER, DELAYED
- 1. 5 HOUR COR E O RIFIC ED FO R 25 0 C P . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19
- 5. CASE FSV3, LINER COOLING AFTER 1.5 HOUR 175 PSIG FIREWATER, D ELAYED 1. 5 HOUR CORE ORIFIC ED FO R 250 CP . . . . . . . . . . . . . . . . . . . . . . . . . 20
- 6. CASE FSV4, NO LINER COOLING 175 PSIG FIREWATER, DELAYED 1.5 HOUR CORE ORIFIC ED FO R 25 0 C P . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21 APPENDIX A. INPUT D ATA ELEMENTS AND COMPUTER PROGR AM DETAILS . . . . . . . . . . A-1 APPENDIX 3. STOR AGE OF PROGRAM AND DATA IN ISD ARCHIVES . . . . . . . . . . . . . . . 3-1 APPENDIX C. C ALCU LAT ION R EVI EW R EPORTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-1 Page 3
- . _ . . - _ , - - . , , ,-~_...w.-
_ _ _ _ _y _ _ _ _ . _ _ _ _ _ .
, GA TECHNOL0GIES N C.
TITLE: FSV: DELAYED FIREWATER C00LDOWN; EFFECT OF LINER COOLING ON ORIFICE VALVE TEMPERATURES DOCUMENT No. 907935 ISSUE NO./LTR. N/C ,
- 1.
SUMMARY
This document presents the results of a study to determine the effect of having or not having liner cooling available during a delayed cooldown of the Fort St. Vrain plant using boosted firewater to drive a circulator and to remove the residual heat from the reactor.
It is shown that the lack of liner cooling, even for an indefinitely long time, has no significant effect on either orifice valve temperatures or on maximum fuel temperature.
- 2. INTRODUCTION The updated FSAR for the Fort St. Vrain plant (Ref. 1) discusses in Section 14.4.2.2 the matter of cooling with one water-turbine driven circula-tor powered by boosted-pressure firewater following a 1 5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> delay. The analysis reported there led to the conclusion that the maximum fuel tempera-ture and the maximum orifice valve temperature would not exceed safe limits during such a cooldown. That analysis was done with the assumption that the liner cooling water system continued to operate on at least one loop during the cooldown period.
The question has been raised as to the effects on critical reactor temperatures if the liner cooling water system were to be inoperative during the 1.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> delay period or for even longer periods. A study made in 1977 (Ref. 2) indicated that the lack of top head liner cooling might make a large difference in the orifice valve temperature. This present study was, there-fore, initiated using the same version of the computer program, RECA2/EE, which was used in 1977.-1978 and using the same initial conditions.
3 DESCRIPTICN OF THE PHYSICAL EVENT A reactor cooldown using the firewater system would not be initiated unless all other means of removing residual heat from the core had failed.
The water would be pumped in fece a storage pool, its pressure being boosted to 175 psig so as to drive the circulater at a speed adequate for pumping enough helium to cool the core. The firewater would also be put through the steam generator tubes and the condenser.
I Page 4 l
, dA TECHNOLOGIES . A C.
- l. TITLE: FSV: DELAYED FIREWATER C00LDOWN; EFFECT OF LINER COOLING ON ORIFICE VALVE . TEMPERATURES j i
DOCUMMT NO. 907935 ISSUE NO./LTR. N/C .
The conservative scenario adopted for this analysis takes no credit for
- main loop rundown and it also assumes a 1.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> delay in starting the fire-water flow due to operator action required to inspect the pipes and to make the necessary modifications following a Design Basis Earthquake. The PCRV is assumed to remain pressurized.
4 METHOD OF ANALYSIS '
The RECA2/EE computer program was used for this study. This version of RECA is the one used for previous analyses in support of the FSAR, and is stored in the OA Technologies Information Systems Division archives as program TMSD-2071. The thermal model of the upper plenus, including the orifice assemblies, the thermal barrier, and the top head liner is described in Section 9 of the RECA3 program description, Ref. 3 Although it was deemed to be essential for consistency to use the RECA2/EE program without any changes in computational methods, it was found that some changes to the input subroutines were necessary. First, it was
- found that an unformatted data file was required not only to give the nodal network structure, but to give the initial nodal heat rates, the orifice settings, and the initial nedal temperatures. The file used in 1978 by Sender (Ref. 4) was for an equilibrium core, starting at 1055 power, and crificed for
- a 250*F outlet temperature dispersion. (File SSICECSB3105*0RF250CP.) This file could not be located, ao file SSIC-PSC'C (archive THSD-1954) was used to
, give the nodal network connections and the basic geometric factors. These were identical to those used by Bender. Then the heat rates, orifice settings, and initial temperatures were taken from the print-out of Bender's run and put into data elements. The heat rates and orifice loss coefficients were put in as " cards" of type 27 through 31 in the data elements called DATELT, DATELT3, and DATELT4 (These elements differ only in line 1, where the starting time for liner cooling is given.)
The initial temperatures were put into a data element called INTEMP. A special subroutine called INPUTZ was written to read and store these tempera-tures. Small modifications were made to subroutines INPUT and INPUTT to enable the heat rates and orifice coefficients to be read. All items were carefully checked for agreement with Bender's run. Details of the program changes are described further in Appendix A. The revised program and all of the input data sets have been archived as described in Appendix B.
Page 5
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., GA TECRNOL0GIES I N C.
TITLE: FSV DELAYED FIREWATER C00LDOWN; EFFECT OF LINER COOLING ON ORIFICE VALVE TEMPERATURES DOCUMENT NO. 907935 ISSUE NO./LTR. A ,
4 Three computer runs were made with the firewater pressure set at 175 l psig. In each case, the flow of firewater was started at 1.5 he af ter reactor trip. In one case (FSV2) the liner cooling water was left on continuously from time zero. In another (FSV3) the liner cooling water was turned off at time zero and was turned on again at time = 1.5 hr. In the third case (FSV4) the water was left off for the whole run of 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> (simulated time). All other conditions were kept the same for the three runs. Tables I through 6 .
present numerical values selected from the computer print-outs.
The liner cooling water, when on, was simulated by a node held at a '
temperature of 120*F and connected to the liner node by a heat path having a thermal conductance that had been found by previous analysis to be character-istic of a liner cooled by one of the two liner cooling loops. When the liner cooling system was off, the conductance of this heat path was set to zero.
- 5. DISCUSSION OF RESULTS The results of the computer simulations show that the following phenomena would occur during a delayed firewater cooldown:
During the 1.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> period before the circulater is started, the helium in the core would rise in some regions and fall in others because of differ-ences in the gas temperatures and therefore in the densities. During this period, the mean temperature of the gas in the upper plenum would reach approximately 1200'F and the temperature of the gas leaving the upflcwing regions woule. reach approximately 1650*F. (See Figures 1 through 3.)
After the firewater system is started, the circulater speed would rise to about 1100 rpm. The circulator would produce enough pressure rise to drive the helium downward through the core and through the steam generators. The downflow would be aided by the weight of the gas in the core, and most of the cere regions would soon be cooled. A few of the higher-powered regions would heat up f aster than the gas would cool them. The lower density of the gas in these regions would tend to block the coolant downflow, causing the gas to become still hotter. At about 3 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> af ter the start of this event, the i
flow in these hot regions would actually reverse, and the temperature of the gas leaving the top of these regions would reach a maximum of 1650'F. There-after this temperature would slowly decrease due to heat transfer within the core.
l l The total flow rate in all of the upward-flowing regions would never exceed 1.5 percent of the downflow rate af ter the circulators have started.
i l
l l
Page 6
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GA TECHEOL00IEs i N c.
TITLE: FSV: DELAYED FIREWATER C00LDOWN; EFFECT OF LINER COOLING ON ORIFICE VALVE TEMPERATURES DOCITrur.mi NO. 907935 ISSUE NO./LTR. N/C The mixed mean temperature of the gas in the upper plenum would f all to about 135'F at about an hour after the start of the circulator.
The temperatures of the top reflectors and the orifice assemblies for the upflowing regions would be determined by the heat balances between the cold gas entering the plenum and the hot gas leaving the upflowing regions. The tenperatures of these components would also be influenced by the radiant heat ,
exchanges between the orifice assemblies and the walls of the top plenum. The thermal barrier cover plates would reach a temperature of about 1050'F during the period before the circulator starts, but would quickly cool to about 200*F after the coolant flow starts. (See Figures 1 through 4).
The temperatures of the cover plates would be determined mainly by the convective heat exchange with the gas in the upper plenum and by the radiant heat exchanges with the top reflectors and orifice assemblies. The tempera-ture of the liner would have only a small effect on the cover plate tempera-ture, as was shown by thg results of this analysis. (See Figures 4 and 5.)
The effect on maximum orifice valve temperature would be even less, or virtually zero. (See Figure 6.)
The maximum core fuel temperature would reach about 1780*F at about nine hours. Again, the absence of liner cooling would have no significant effect on this value. (See Figure 7. ) There would be a small effect on average ccre temperature, however. At 20 hcurs, the average temperature would be about 40*F greater if there were no liner coaling.
In order to explain the difference between the results of this present study and the results reported in 1977 (Ref. 2), the computer print-outs for
, the 1977 runs were recalled frem storage and examined. It was found that the cases without liner cooling had been made with the conservative assumption that there was no heat transfer from the orifice assemblies. This had the effect of raising the calculated orifice temperatures by several hundred de grees . Such an assumption is now deemed to be unrealistic.
! 6. CONCLUSIONS l
The presence or abserce c' liner cooling has no significant effect on maximum orifice assembly temper.vare nor on maximum fuel temperature during a delayed firewater cooldown.
1 Page 7
GA TECHNOLOGIES A N C.
^
TITLE:
FSV: DELAYED FIREWATER COOLDOWN; EFFECT OF LINER _
_ COOLING ON ORIFICE VALVE TEMPERATURES DOCUMENT NO. 907935 t - ISSUE No./LTR. N/C
- 7. REFERENCES 1.
Analysis Report, Revision 2. Fort St. Vrain Nuclear Power Gen nal Safety
- 2. Petersen, J. F., "Effect Temperatures February 15, 1977. During Firewater Cooldown," GA :
Memorand
- 77,
- 3. Petersen, J. F., "RECA3:
HTGR August Emergency 1977. Cooling Transients," Report - GA-A14520
-22),
4 D. M.,
File DEC-21127, Computer Run Stored in Box DME-6013, MadeFSV-78-573 20 Sender on September 1978, l
l t
l l
Page 8
FIREUATER COOLDOWN, !?S PSIS UATER, LIteER COOLING AFTER 1.5 m .
- 2000 T , _
~
~
E -
M p 1500 - '
E R -
- ""*L8""
A - -
i T -
U g R 1000 - ..
E -
- /
_ 1 /
- l l D
- E --
i G 500 --- !
I F
'l k ,___._.----
i f ,.
gs. **
a== - ** 2 - -4. *
-==.a
- s .
-- m I
s # 'I I I I I I I I I I I I I I i
- a
! O 5 10 15 20 'S y
?
m TIME (HR) $
m e
z l E Fig. 2: Delayed Firewater Cooldown, 175 psig water, Liner Cooling After 1.5 hr (case Fsv3) %
l .
i FIREUATER COOLDOUN, 175 PSIG UATER, NO LINER COOLING 2000-T ana meescs ==
E -
M p 1500 -
- = - -
l E '"" **' 8 R -
A _ w une Lawn T -
/~
U R 1000-- ,/f E - lJ .
- \
D i E
O
]
j 500 -
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F [g l fg. .._..m.._.__..
g _ ..___..._._.___c.
~_ -= a.___ _____ _..__ _ _ ..
l g _m .
- x. . . . . . . . ...x...g....
........x...
l 0- , , = , - , , , , , , , , i i i i i l
0 5 10 15 20 u>
o m TIME (HR) O m
l DB US S Fig. 3: Delayed firewater Cooldown, 175 psig water, No Liner Cooling (Case FSV4) z l e n l H
l I
TOP HEAD THERMAL BARRIER COVER PLATE TEMPERATURE 1200 uma eseuses.
' CONTINUOUS (Fsv2) 4 T 1000- ...........
E .s a satay (Fsv3)
. M _ o .
P I E NO COOLING (FsV4)
- 800 --
1 i
R A
\
J i T
! U R 600 -
! E i o l -
j D 400 -
E G _.
- y ___;-- - - z - _ - - . _m . _ _ _ _ _ _ _ _ _ _ _ _ _ _
i
_ 280-- %g-
~
l e- i i i i i i i . . i i i i i i i
! e s to is 20 j ,
TIME (HR) m
, a; O
)
- Fig. 4: Delayed firewater Cooldown, 175 psig water, Top Head Thermal Barrier Cover Plate $
m e
I " Temperature for Three Cases of Liner Cooling 2 n
.l -
i
Tor HEAS LINER TEMPERAfumE WITH ANS WIThouf LINEA COOLING 258 _ uMEa comunes t
t -
- CONTINUOUS (FsV2)
T 225- ,
\
, E --
6 \
i M -
1 t s Ha ottav (Fsv3) p -
,d. .
E j:;
NO COOLING (Fsv4) i R
200- \
,g s, A -
T -
i: x' .m U -
f !
R 175 .
E -
/ ;:
- 9 4 D 150 - f 4
E - 4 -
G - ' ".
! y -i ..
. _ 125- -
-b ; ; ; ; ; ;
1 1 _
l 100 I . . i i i i i i i i i i i e i i i
4 0 5 10 15 20 'a s
, TIME (HR) =
g sn
, e Fig. 5: Delayed Firewater Cooldown, 175 psig Water, Top Head Liner Temperature i4n l for Three Cases of Liner Cooling i
l MAXIMUM ORIFICE VALUE TEMPERATURE i
i 2000 LisetA Coettma
- CONTINU00g (FSV2)
T , _
y- .....n.....
[
M 1s00= ) .
s.s m utav (FSV3)
P -
/
E R - f NO COOLING (FSV4)
A --
, T ~
! U R 1000 - -
E -
D E --
0 500 -
t j F j
0- i . =i i i i i i i i i i i i i i 0 5 10 15 20 to m
TIME (HR) '$
m i
u} Fig. 6: Delayed Firewater Cooldown, 175 psig Water, tiaximum Orifice Valve Teniperature
]
7 for Three Cases of Liner Cooling n'
i l
MAXIMUM AND AVERAGE CORE TEMPERATURES 3000
. uma centua.
~
=
- _
MAXIMA -
- p. / N CONTINUOUS (FSV2) 2500 - -
, i 1.8 Ha mLAY (FSV31 I
NO COOLING (FSV4)
- 2000 CONTINUOUS (FSV2)
.....n.....
s.s ha utav (rSv3)
I -
m 1500--
I S I e a
. E -
1 E 1000 -
1 4
~
^"'"^"'*-
% . _ . _ A =.: = _ - - . ,/. _ .
5 e-1 -
! 500 - i i i i i i i i i , ,i i . . i 1
- O 5 10 15 20 m
! o
.o TIME (HR) il w
u l T Fig. 7: Delayed Firewater Cooldown, 175 psig Water, Maximian and Average Core C. Temperatures for Three Cases of Liner Cooling n' i
GA TECHNOLOGIES a A C.
TITLE: TSV: DELAYED FIREWATER C00LDOWN; EFFECT OF LINER COOLING ON ORIFICE VALVE TEMPERATURES DOCUMENT NO. 907935 ISSUE NO./LTR. N/C .
TABLE 1 CASE FSV2. CONTINUOUS LINI3t COOLING -
175 PSIG FIRENATER. DELAYED 1.5 HOUR CORE ORIFICIZ) FOR 250CP TEMPERATURES (DEG F1 TIME COVI3t LINER UPPER ORIFICE MAXIMUM AVERAGE HR PLATE PLENUM VALVE N CORE
.00 770. 129. 773. 773. 2012. 1215.
.02 765. 130. 776. 807. 2023. 1222.
05 757. 132. 782. 821. 2033. 1234.
.30 760. 135. 824. 944, 2160. 1287.
.47 785. 135. 870. 1045. 2267. 1313.
.95 901. 137. 1034. 1352. 2499. 1371.
1.36 1010. 139. 1170. 1580. 2621. 1407.
1.49 1044. 139. 1213. 1647. 2652. 1418.
1.53 901. 140. 640. c. 2658. 1419.
1.70 482. 140. 260. O. 2636. 1378.
1.87 317. 139. 176. Q. 2590. 1323.
2.05 258, 136. 156. O. 2586. 1257.
2.45 215. 131. 139. O. 2580. 1119.
3.19 181. 125. 123. O. 2601. 967.
3.71 176. 124. 123. 141. 2642. 920.
3.99 173. 123. 122. 155. 2664. 906.
4.39 171. 122. 123. 243. 2676. 893.
4.79 171. 122. 124. 418. 2657. 885.
5.99 181. 122. 131. 1010. 2711. 869.
7.19 198. 122. 135. 1372. 2754. 854.
8.79 213. 122. 136. 1573. 2768. 830.
11.59 218. 122. 135. 1646. 2741. 789.
13.99 213. 122. 133. 1624. 2663. 756.
19.99 198. 122. 131. 1520. 2475. 684.
1 Page 16
GA TECHNOLOGIES
- N C.
TITLE: FSV: DELAYED FIREWATER C00LDOWN; EFFECT OF LINER COOLING ON ORIFICE VALVE TEMPERATURES DOCN NO. 907935 ISSUE NO./LTR. N/C i
TABLE 2 CASE FSV3. LINER COOLING AFTER 1.5 HOUR 175 PSIG FIRDUCER. DELAYED 1.5 HOUR )
CORE ORITICII) FOR 250CP TEMPERATURES (DEG F)
TIME COVER LING UPPER ORIFICE MAXIMUM AVERACE
. HR PLATE PLENUM VALVE FUEL CORE
.00 770. 129. 773. 807. 2012. 1215.
.02 765. 131. 776. 807. 2023. 1222.
.05 757. 136. 783. 821. 2033. 1234.
.10 752. 141. 789. 840. 2063. 1248.
.16 750. 146. 797. 866. 2093. 1260.
.22 752. 151. 806. 897. 2120. 1272.
.30 760. 157. 824. 944. 2160. 1288.
.39 771. 162. 846. 994. 2213. 1301.
.47 785. 167. 870. 1045. 2267. 1314.
.95 902. 192. 1035. 1352. 2499. 1372.
1.36 1012. 713. 1171. 1580. 2622. 1410.
1.49 1000. 218. 1214. 1647. 2653. 1421.
1.53 903. 194. 640. O. 2658. 1422.
1.70 485. 161. 261. O. 2636. 1380.
1.87 320. 150. 176. O. 2590. 1326.
2.05 261. 143. 156. O. 2586. 1260.
2.45 217. 134. 139. O. 2580. 1123.
2.79 196. 130. 131. O. 2588. 1039.
3.71 175. 126. 123. 141. 2641. 924.
3.99 174. 124. 122. 154. 2663. 910, 4.39 172. 123. 123. 241. 2675. 897.
1 4.79 172. 123. 124. 415. 2656. 890.
5.99 181. 122. 131. 1007. 2709. 873.
7.19 198. 122. 135. 1370. 2753. 857.
8.79 213, 122. 136. 1572. 2768. 834.
9.59 216. 122. 136. 1614. 2775. 822.
11.59 218. 122. 135, 1645. 2741. 792.
13.99 213. 122. 133. 1624. 2663. 759.
19.99 198. 122. 131. 1520. 2476. 687.
i Page 17 i
. GA TECHNOLOGIES A K C.
TITLE: FSV: DELAYED FIREWATER C00LDOWN; EFFECT OF LINER COOLING ON ORIFICE VALVE TEMPERATURES DOCIDEENT NO. 907935 ISSUE NO./LTR. N/C ,
TABLE 3 CASE FSV4. NO LINI3t COOLING 175 PSIG FIRENATI3t. DELAYED 1.5 HOUR CORE ORITICED FOR 250CP TEMPERATURES (DEG F)
TIME COVI3t LINI3t UPPI3t ORIFICE MAXIMUM AVERAGE HR PLATE PLENUM VALVE fvEL CCRE
.00 770. 129. 773. 807. 2012. 1215.
.02 765. 131. 776. 807. 2023. 1222.
.05 757, 136. 783. 821. 2033. 1234.
.10 752. 141. 789. 840. 2063. 1248.
.16 750. 146. 797. 866. 2093. 1260.
.22 752, 151. 806. 897. 2120. 1272.
.30 760. 157 824. 944. 2160. 1288.
.39 771. 162. 846. 998. 2213. 1301.
.47 785. 167. 870. 1045. 2267. 1314.
.95 902. 192. 1035. 1352. 2499. 1372.
1.36 1012, 213. 1171. 1580. 2622. 1410.
1.49 1047. 218. 1214. 1647. 2653. 1421.
1.53 903. 223. 640. O. 2658. 1422.
1.70 485. 232. 261. O. 2636. 1381.
1.87 321. 237 176. O. 2590, 1326.
2.05 262. 239. 156. O. 2586. 1261.
2.45 220, 236. 140. O. 2580. 1125.
3.19 187. 221. 123. O. 2599. 975.
3.71 182. 215. 123. 141. 2640. 930.
3.99 180. 208. 123. 154. 2662. 916.
4.79 178. 198. 124. 410. 2656. 897.
5.99 187. 189. 131. 1001, 2708. 885.
7.19 203.. 183. 136, 1365. 2753. 872.
8.79 218. 180. 136. 1568. 2768. 852.
11.59 223. 179. 135. 1641. 2743. 817.
13.99 219. 179. 134. 1621. 2667 788.
19.99 204. 177. 131. 1516, 2483. 725.
Page 18
. GA TECHNOLOGIES INC.
TITLE: FSV DELAYED FIREWATER C00LDOWN EFFECT OF LINER COOLING ON ORIFICE VALVE TEMPERATURES DOCUMENT NO. 907935 ISSUE NO./LTR. A ,
TABLE 4 l CASE FSV2, CONTINUOUS LINER C00 LINO 175 PSIO FIREWATER, DELAYED 1.5 HOUR CORE ORIFICED FOR 250 CP LOWER CORE PLENUM TEMPERATURES ,
TIME HOUR MAXIMUM HELIUM. 'F AVERA0E HELIUM. *F 0 1427 1180
.02 1393 1169
.05 1427 1161 30 1403 1156 47 1411 1167
.95 1417 1196 1 36 1445 1209 1.49 1456 1212 1.53 1603 1506 1.70 1727 1553 1.87 1842 1565 2.05 1944 1536 2.45 2088 1335 3 19 2164 823 3 71 2154 539 3 99 2136 518 l 4 39 1905 453 l' 4.79 1713 418 5.99 940 366
, 7.19 485 345 8.79 434 335 11.59 410 320 13 99 392 308 19.99 361 288 l
l.
i Page 19 l
- . _ - . _ _ _ , _ . . _ _ _ _ _ _ , _ _ . _ _ _ _ . . , - . . . . . _ _ . _ _ _ _ _ . . _ _ _ _ , , _ _ . _ _ _ _ . _ _ _ _ _ _ _ - _ _ _ , _ . . . , _ . ~ . . . . _ . _ _ _ _
I O I j
o GA TECHNOLOGIES INC.
TITLE: FSV DELAYED FIREWATER C00LDOWN; EFFECT OF LINER COOLING ON ORIFICE VALVE TEMPERATURES DOClimmi No. 907935 ISSUE NO./LTR. A .
TABLE 5 CASE FSV3, LINER COOLING AFTER 1.5 HOUR 175 PSIG FIREWATER, DELAYED 1.5 HOUR CORE ORIFICED FOR 250 CP LOWER CORE PLENUM TEMPERATURES TIME HOUR MAXIMUM HELIUM. 'F AVERAGE HELIUM. *F 0 1427 '
1180
.02 1393 1169
.05 1427 1161 30 1403 1156 47 1411 1167
.95 1417 1196 1 36 1446 1210 1.49 1456 1213 1 53 1603 1506 1.70 1728 1553 1.87 1842 1566 2.05 1944 1537 2.45 2088 1336 3 19 2165 824 3 71 2154 589 3.99 2137 518 4 39 1961 454 4.79 1714 419 5.99 944 366 7.19 458 345 8.79 434 336 11.59 410 320 13 99 392 308 19.99 361 288 Page 20
0 GA TECHNOLOGIES INC.
TITLE: FSV DELAYED FIREWATER C00LDOWN EFFECT OF LINER COOLING ON ORIFICE VALVE TEMPERATURES DOCirama NO. 907935 ISSUE NO./LTR. A
- TABLE 6 CASE FSV4, NO LINER C00 LINO 175 PSIG FIREWATER, DELAYED 1.5 HOUR CORE ORIFICED FOR 250 CP LOWER CORE PLENUM TEMPERATURES TIME HOUR MAXIMUM HELIUM. 'F AVERA0E HELIUM. 'F 0 1427 1180
.02 1393 1171
.05 1427 1161 30 1403 1156
. 47 1411 1167
.95 1417 1196 1 36 1446 1210 1.49 1455 1213 1.53 1603 1506 1.70 1728 1553 1.87 1842 1566 2.05 1944 1537 2.45 2088 1336 3 19 2164 825 3 71 2155 590 3 99 2138 519 4 39 2010 455 4.79 1712 419 5.99 951 367 7.19 457 346 8.79 434 337 11.59 411 321 13 99 395 31 0 19.99 364 290 Page 21
, GA TECHNOLOGIES A N C.
TITLE: FSV: DELAYED FIREWATER C00LDOWN EFFECT OF LINER COG.ING ON ORIFICE VALVE TEMPERATURES DOCimrmi No. 907935 ISSUE NO./LTR. N/C ,
APPENDIX A. Input Data Elements and Computer Program Details It was intended to use the computer program RECA2/EE exactly as it was used by Bender in 1978, but it was found necessary to revise the input subrou-tines slightly because the proper mass-storage file of input data could not be located. RECA2/EE requires inputs of three types: a massestorage file giving the nodal network details and including heat generation rates and initial temperatures a formatted data file giving data for the case to be run; and a blockedata subroutine called TABLES giving additional data. The pressure of the firewater is one of the items given in T ABLES.
Subroutine INPUT was changed so that it would read the initial heat rates and the orifice loss coefficients from the formatted data file. Also, the helium inlet temperature, HETIN, and the ef fective thermal conductance between the fuel and the coolant, EXC, were read in from the file.
Subroutine INPUTT was changed so that the initial power ratio. PFACT1, would be read from the file. In addition, INPUTT was made to call another subroutine, INPUTZ, which read and distributed the initial nodal temperatures.
These initial temperatures were keypunched into a data element called INTEMP, using values from Bender's run.
It was found that RECA2 program would no longer fit into the core of the Sperry-UNIVAC without using extended memory. To avoid this, the program was segmented into an input part and an execute part. It then took 59503 comery words and fit nicely.
Each case simulating 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> of real time took slightly less than 20 minutes of computer time.
The program and the data elements have been saved as described in Appendix B.
e 40 Page A-1
e
!, GA TECE50LOGIES A d C.
TITLE: FSV: DELAYED FIREWATER C00LDOWN EFFECT OF LINER COOLING ON ORIFICE VALVE TEMPERATURES l
DOC u ram 30 907935 ISSUE NO./LTR. N/C '
l
. i APPENDIX B. Storage of Program and Data in ISD Archives -
The program and the input data files used in this study have been stored in the GA Technologies Information Systens Division i Archives under the number SYSD-3914 ;
That file contains the following components: ,
- 1. RECA2*EE (The program as amended for this study)
- 2. SSIC-PSC'C (The mass-storage file used fcr the nodal network description) 3 FSVFWC'RUNSTREAMS (The run stressa which orchestrate each of the i computer runs) -
l 4 FSVFWC'SUPERPLOT (Hand picked data 'hrom each of the runs, used 4
with the SUPER
- PLOT program to make the graphs)
- 5. RECAP 0KE*A (This program would be used if it were necessary i
to change the orifice settings. It was not used in this study but is archived here 30 that it will be handy if the need arises. It is the same as Archive THSD-2073) l The RECA2/EE program used in this study was retrieved from Archive THSD-2071. The file, SSIC-PSC'C, was retrieved from Archive THSD-1954 The computer outputs for runa JFP-1090 -1901. -1094, and -1097 were found in storage box FSV-1666.
! Outputs for runs DMS-6012 and 6013, as well as JFP-1411 were found in box
! FSV-78-573 (DEC-21127). Also, JFP-1504 was found in box FSV-79-574 l
Page B-1
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s.
uissamav. iness CALCULATION REVIEW REPORT TITLE:
Delayed Fireweter Cooldown; Effect of Liner Cooling on APPROVAL LEVEL Orifica Valve Temperatures QAL LEVEL 0ISCIPLINE SYSTEM 00C. TYPE PROJECT 00CUMENT NO. ISSUE NO AT R.
N 11 CFL 1900 907935 N/C INDEPENDENT REVIEWER:
NAME Th = = W- chan
- ORGANIZATION HTGR System Design & Plant Dynamics @ 7)
~
REVIEWER SELECTION APPROVAL: BR MGR OATE 37T REVIEW METHOD: YES NO ERROR DETECTED ARITHMETIC CHECK LOGIC CHECK MN ALTERNATE METHOD USED SPOT CHECX PERFORMED COMPUTER PROGRAM USED
- 7) ele rn,nat chsek / Alema,.
REMARXS: (ATTACH LIST OF 00CUMENTS USEO IN REVIEW)
/, FS V G.lc. F;te. Ds2C :Li l17 , R ec.A F ire. n.+4 - Gib cmJu R.ws Due:wo es , Sr.se L Box rsV- 72 -5 73 , q i, CALCULATIONS FOUNO TO 8E VAll0 AND CONCLUSIONS TO BE CORRECT:
INDEPENDENT R EVIEWER
~~ *
$10N ATU R E OATE ON Page C-1
F 4
3d.1543(MV 1125 ,
CALCULATION REVIEW REPORT TITLE: pu: d s /m y e / F< > < w e / u d'e # /* w ' 34/<s/ ,# A /,.u ('n/,'g APPROVAL LEVEL .L___
- ** O r / s /s
- Vd /v* Tr W *
- A "<3 /
QAL LEVEL OISCIPLINE SYSTEM 00C. TYPE PROJECT ' 0OCUMENT NO. ISSUE N0;LTR.
/V // 4 Art,, /$$O $e 7 $I.S'" oA INDEPENDENT REVIEWER:
NAME $A Y61 $4D W A LL A 09/2 ORGANIZATION 4 W - Sle 4 9 Es//d4/A*4 REVIEWER SELECTION APPROVAL: 8R MGR -
OATE REVIEW METHOD: YES NO ERROR DETECTED ARITHMETIC CHECK LOGIC CHECK X ALTERNATE METH00 USED X SPOT CHECK PERFORMED E
- COMPUTER PROGRAM USED X
%& dd ChuV X 6e REMARKS: (ATTACH LIST 0F OOCUMENTS USED IN REVIEW)
'fibles f gud (o VeriA4' sk it. Ons'a/W /8 compete esput s%dm 304 G 4-o~s 749.
CALCULATIONS FOUNO TO BE VAL 10 AND CONCLUSIONS TO 8E CORRECT:
INDEPENDENT REVIEWER - " ###C DATE 13 44 N
// SIGNATURE C-2