ML20059A520
| ML20059A520 | |
| Person / Time | |
|---|---|
| Site: | 05200004 |
| Issue date: | 10/20/1993 |
| From: | Marriott P GENERAL ELECTRIC CO. |
| To: | Joshua Wilson Office of Nuclear Reactor Regulation |
| References | |
| MFN-170-93, NUDOCS 9310260361 | |
| Download: ML20059A520 (56) | |
Text
GENucic:rEn:rgy Ger:eralDecmc Carrpany 175 Curtner Avenue. San.icse. CA 95125 October 20,1993 MFN No.170-93 Docket STN 52-004 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Jerry N. Wilson, Acting Director Standardization Project Directorate
Subject:
SHWR Test Program ,
Reference:
Purdue Testing Meeting, GIRAFFE Testing Program RAls, October 1,1993 ,
This letter transmits responses to questions posed prior to and during the referenced meeting.
Sincerely, P. W. Maryktt SBWR Project Manager M/C 781, (408)925-6948
Enclosure:
Two (2) copies of each of the following:
A. Requests for Information by Purdue University prior to meeting on October 1.
B. GE Answers to Purdue University Questions on SBWR Systems (Given to Purdue staff during meeting on October 1,1993)
C. Additional responses to Questions and Requests from Attachment A not covered in Attachment B D. Responses to Questions made to GE by Purdue staff during meeting on October 1, 1993 cc: M. Malloy, Project Manager (NRC) 1.1RhK 93 $$
1 040 9310260361 931020 D PDR ADOCK 05200004 A PDR [Md
i i
i ATTACHMENTS ;
A. Requests for Information by Purdue University prior to meeting on October 1, ;
1993.
l B. GE Answers to Purdue University Questions on SBWR Systems (Given to Purdue staff during meeting on October 1,1993)
C. Additional responses to questions and Requests from Attachment A not covered ;
in Attachment B. :
D. Responses to Questions made to GE by Purdue staff during meeting on October i 1,1993. i
.I
-l J
I I
l
1 i ATTACHMENT A ,
Requests for Information by Purdue University prior to meeting on October 1,1993. ;
t i
e t
9 h
l 7
r .s <
~
d y see-as *s wen 3 2 :2s ev= putt uvet. sap _cus caveoooste PURDUE UNIVERSITY Y=e :
p :
i September 15,1993 scwoot or nuettAn suomtrame ;
A Draft of Required Informations From GE About Prototype SBWR System i
- 1. Fced Water Line
- a. During a feedwater line break the Bow wiu be chokedheetncted by the area of the _.!
sparler.Therefore we need detailed design of the sparger.
- b. Isometric drawing of the Feedwater supply line is needed to know the cicvation difference etc,in came of break.
- c. What netion is taken with feedwater supply line during a LOCA7 Which valves are ,
closed ( There is one manual valve. thres check valves and onc roosor operated valve on each line. Which of theas are closed during LOCA)? Ses anached Tabic 3.1 in SBWR Response to Loss of Feed Water. At uvel 2, what actions are taken? ,
- 2. Provide detaDed information on the losa coeffeclents for all the lines. In panicular give the minor loss coeffecients of all the valves in the following lines:
t
- b. IC Supplyline (from vesselto1C)
- " c. IC condensate drain and vent!!ne
- d. PCC supply, drain and ventline
- e. GDCS drain line
- f. Equalizationline :
3 CRDline (into vessel bouom)
- h. RWC/SDC system llac
- 1. Drywell & wetwell sprsy lines (flow rates also needed)
-i J. FoodWaterline
- 3. Provide the following information for the ICCS and PCCS :
"a. What is the dealga of the headers and the separators? (drawings are aceded). In
)
particular please provide the loss coeffecients for these.
- b. IC pool water level depletion as a function of time (up to 3 days). Can we reduce !
the volume? 1 l
- rm -- - . w.m., . ei e j l
l
- 3V ey:60 E66T-9T-So-i I
.- - . . . . + -.
g-s yeomogyo
'I seP-19-os W2D s2225 PUocue educt. gen aves 4
c.
Provide the elevation of the PCCS condensatp retum line.
d.
Do we have IC tube rupture detection sysum? What is the automade dete ,
system? Line break (retum) need not be consider. [
- c. Detailed design of the ICS and PCCS modules.
- 4. RPV: i s.
What is the insulation material? (its physical thermal propenics and thickness t needed) ,
b.
What is the loss coefficient across the steam separators? - '
c, Explain the pressure drop data across the lower plemtm and the corl cf the core inlet now restrictors (ori5ce K values)is needed. 5 ,
5.
How are the upper drywell and the lower drywell connected? Detail of drywl including neutron shield outside the vessel are needed. (drawings, Acw assal '
coefnects). e
- 6. Need isometric drawings for pipings of the following auxiliary systems :
l a.
Reactor water cleanup systemrShut Down System
- b. Control Rod Drive System
- c. Fuel and Auxiliary PoolCooling Systems l
- d. Fsed Water Lines .;
- 7. Can OE provide us with their code calculations of blowdown phase? We a' the ther7nal hydraulic parameters at about 150 see. After MSL break, informadoni vcsact liquid level (time dpandent level due to swelling). quality, void fraction, >
decay beat powcr levels will be useful.
- 8. During the inidal transients following LOCA or blowdown, say at and after are the status of the followinglines?
.f
- a. Is RWCISD Systern operadas? What valves are open?
1 l
- b. In CRD systems what valves are open? Are pumps active?
j
- c. Is FAPCS active? What valves are open? Are pumps active 7
- d. Is FWL pwnp is tripped? How does it work during and ther this stage of tra What valves are open?
- c. How the vacuum breakers opersac during transions? What is the AP to ope l
- 9. What is the setpoint to open vacuum breakers? What logic are used to open I
- 10. Operating procedores and actuation logic for low pressure coolant inje CRD and RWCUISDC. I on,.= m wmses seasemmas. . .oruwam. .
- 3~1 - *O TP:60 ES6T-97
.a@'d i
i 3374949970 m l I C3P-t9-95 WED 12 24 PU2Duc 'NUct.E AR ENG !
t
'e i
i II.
Fault tres analysis for SBWR needed to develop ~e tast malda. Detecdon of ICS tube svptu 37 Any automatic function to handle ICS tubc rupture. 'i Question and Bepests on GIST Facillry l 1.
How were heaters 5tted to the vessel? How hemist surface temper'stures were !
measured? ,
- 2. Provide the loss coeffectents in all the lines of GIST facility. .
- 3. Need detailed test resutu and conditions for Sve OlST tests used fo calculations in order to run similar emperiments as mguired by NRC. Need design of the break simulation using pipe sad valve on various lines of GIST facility.
- 4. How the pressure sense line weis connected to ths vessel and pressure tranadec 5.
What Sow meters were used to measure a) water, b) steam and c) two phase now in .l >
pipe? And what How meters were used for downcomerliquid Row rees? - :
Other Questions '
- 1. Can GE supply us heaters with built-in surface thermocouples?
- 2. Who made GIST heaters? I t
l l
i i
i i
l
.etweem.mme . ewp.m. ;
==s= - mame .
1 i
TF:60 E66T-91-50 ,
I 1
i
~ * *
~ TatitT").T*'$vemary of ItwR sysism a ede sentes wipelas b Compeeen -
Eles. (m m) er Erstem Attles Level - - ,
, ... ree.. ..e, m,e 1,i, 18790 Restler Power Mlgt Level Scram 8
Male Tutties YrlP Feedwater Pompe Rusteck (4tes cJ-h.s ,
88340 78eenal Operates IGfL
.t 2p%iJ [
87353 Reatier Poes Lew Lses Serum
- )
' L1 e I a bsl.s nJwL f
~
M5IVS Cloes 3 1409$
e(,, fe (p f
- )*g .rA' Isolatles fal:Istes Ceassaser '
1 CRD Ideedse Islaletos with IMsMg ,
n ut lstes' i -Y y' , .
t 10093 4 3Rvs r --
8
== (Q . .gg LSIS ) ADS se *
, 4 3RVs 9 e?.* A NI m Ab'*E**'-* 3(3FV6 S h sf**d 3 DPys 9 641.a ** ~ ,
3 DPYa W #9,*p. .
IW
.g inttf atet. c '
83*3 # #) ,
~
6493 (EI* TAP .
3739 (3 g' I BAP I
%+ con vu1+WC Ttr:60 E66T-9T-SO M
14 j i
- l' - ;
I
-ATTACHMENT B ,
I
.i a
I r
l i
GE ANSWERS TO PURDUE UNIVERSITY QUESTIONS ON SBWR SYSTEMS ,
i l
i i
i
.1 i
4 1
i t
t 5
h 1
I i
NOTE: All answers are based on currently ;
available data. In many cases this data is -i preliminary and all necessary verification has not been completed. l l
- 6 l
- 1 1
'h
I Answers to Purdue University Questions j
- 1. FEEDWATER LINE t
- a. During a feedwater line break, the flow will be choked / restricted at the sparger inlet as shown in the figure.
Detail sparger dimensions given in figure.
- b. Isometric drawing of Feedwater Supply line (inside containment) is attached. ,
- c. Actions taken with FW supply line during a LOCA: j
- During a LOCA, no action is taken with the feedwater supply line, unless the f reactor water level rises to Level 8. At level 8, equipment protective action will trip the main turbine and reduce feedwater demand to zero. The feedwater pumps will ,
be tripped if the water level reaches level 9.
- If the water level drops to Level 2, the high pressure make-up function of the CRD system will be initiated. Isolation condenser system automatically initiates, and the MSIVs close.
If RPV water level drops to Level 1, the Automatic Depressurization system initiates. j
- 2. MINOR LOSS COEFFICIENTS FOR VALVES , f
- Per Crane Technical Paper l
" Flow of Fluids through Valves, Fittings and Pipe"
- Valve types and sizes per P& ids. (included in the SBWR SSAR)
- MSIVs are Y-pattern globe valves, all other globe valves are not y-pattern.
- Main Steam SRVs are throttled Angle Valves
- Conventional Swing Check Valves: K=50fT
- GDCS and Equalization Line Check Valves:
Cv, flow coefficient per attached figure t
- GDCS and Equalization Line Squib Valves:
Cv > 876 gpm/psio.5
- Turbine stop/controlvalve: 0.03 x Pressure = Pressure loss DRYWELL AND WETWELL SPRAY MAX FLOW RATE 94 Kg/sec
,N <
/
- FE%ED , ATERgE v"'u,; *"7 x o .
v
%* t@ ED- 59aest) .J R pnse Y ikoa '
t m
Cd !
e i i i .
% Q ,! . Sh
[~r S mg
, e's f$ -
Y!
' ^
/
f/
~
oN -
~.
3/ .g 3 i
/
x ;- a g
_, 1102.
r
. i r% 4 i
~!a.3b;p)i o
.l ,
f(TYP.) [ !
[/
,. , i,
i -
n i g /, l-y' f~
/,' *
$ f .
/ l
! i g- .-
x a.noo ) N
~
N
~
u j
. 16 a;) \
%/
^
///) LLL o.oc W 26tN :
h g. ,e
. RlP_V 3
_z .
s / mus - . . .
.. ,, ..... . . r:
i g5 QW &
Response
i Feedwater Line (1 of 2)
~i 14" Schedule 80 1.D. = 12.500* r
. Flow area = 0.8522 ft2 l f
i
.l Feedwater sparger reducing tee -
6" Schedule 80 intet 5" Schedule 80 outlet Feedwater branch to nozzle l 6" 1.D. = 5.761* 10" Schedule 80 'i 6' flow area = 0.1810 ft2 1.D. = 9.562* i 5' l.D. = 4.813" Flow area = 0.4989 ft2 !
2 5" flow area = 0.1263 ft
//////. >
i
'I f
- l Sparger nozzles 20 per sparger .
Nozzle I.D. = 1.75* max. ,
/ Flow area per nozzle = 0.0167 ft2 .l 1
I r
/ }
r
- i
'i f
///// i i
Feedwater Line Break Area Calculation I
+
I file: 3.2.4
i 4
/^ W !
' Queshon la i Respanse ;
Feedwater Line Break Area Calculation Summatiori ,
i 14" feedwater line 1 line 0.852 ft2 10" feedwater branch to nozzle 2 lines 100 ft2 .
6" Tee inlet 2 lines 0.362 ft2 5" Tee outlet 4 lines 0.504 ft2 Sparger nozzles 40 total 0.668 ft2 ,
Conclusion - Limiting break area = 0.362 ft2 s I
I i
l l
l file: 3.2.4
_g.
Cv (gpm/peLxx.51 N N O,
! D
-i
\N 3^
o 960 -
ACCEPTABLE 3a s
72 -
g$
w p
32 *
\';-
480 -
, ~
/////
ACCEPTABLE O%
m' 2'10 - , _
' ' ' ' O O
g ; , ,
," d'- a m r Q ~' .
600 1000 1400 1600
-200 200 Plov at. 60 F (gpm) 6 ,,
b GDCS j
Figure 4.3.3-2. Check Valve Minimum Required Flow Coctricient (English Units)
Answers to Purdue University Qucstions l f
- 3. ICCS AND PCCS INFORMATION .
- a. Design of headers and separators is shown in the drawings.
I oss coefficients: calculated using Crane Technical Paper
- b. IC pool water depletion as a function of time is shown in attached figure. .
Can volume be reduced? Yes, as shown in the figure.
- c. Elevation of PCCS condensate return line
- Karen Vierow will cover this @ the meeting.
- d. IC tube rupture detection system The leak detection and isolation system (LD and IS) will isolate each IC loop individually on high pool radiation or on high flow (as measured by high differential pressure) in the steam supply line or the condensate return line.
- e. Detailed design of the ICS and PCCS modules is shown in the drawings.
- 4. RPV - ,
- a. Insulation material and thermal properties given on attached sheet.
- b. Steam separator loss coefficients: Given in attached response to NRC Questions ;
- c. Pressure drop data across the lower plenum and the core plate, K values of the core inlet flow restrictors:
Given in attached response to NRC questions. .
1
- 5. UPPER AND LOWER DRYWELL CONNECTION DETAILS Detail drawing is attached.
- Flow Area : 14 vents, inside diameter = 0.82m ;
- Loss coefficients: assumed = 0 (Due to low flow rate through the vents) !
- 6. ISOMETRIC DRAWINGS OF AUXILIARY SYSTEMS f
- a. RWCU/SDC system drawings attached.
- b. CRD system: no isometric drawings available. l l
(P&ID drawing is included in the SBWR SSAR) l
-Q- i i
momGntctry isolation Condenser Performance with AVenting (once @ 4 hrs) .
CReycase in Queshon 3b) d Number of Condensers: 2 Tube Fouling: Yes Non-Condensable Storage Volume: 26 cu ft
-- 0 1400 - ,
.400
,,# y 1200 - . ' ' -
-800 E
''~- Top of IC g -1200 1000 -
- -- -1600 Zo 3
.g e.
800 -~ Rx Pres. -2000 $
g 3 i-
= -
-2400 m f-
. Pool Level 808 ~~ E-Ffect d g s g buidup in bot mg m.
~
2800$
I 400 "
-3200 3 E o n.
3600 g
-4000
- O l l l l l l l l l l l I i l l l l l 't l l t- - t ; 't 4400 0.013 5 10 ~ 15 20
- 25 30 35 40 45 50 55 '60 65 .70 Time - (hours)
[
7/21/92..
- P211-26V - ,
- r. ,....~,_....,......,_...-......,_........_.u.. '
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ , _ . _ _ _ _ _ _ _ _ . . _ , . . _ . _ . . . . . , . . . . . . .-. . . . . . _ . . . 4 ..
I Resjonse +o Qu es hon 4a SRWR RPV insulation:
f The RPV insulation is reflective metal type, constructed entirely of series 300 stainless j steel. Heat loss from the vessel to the outside surroundings is based on the insulation having an arcrage heat transfer coeflicient of 0.907 W/m2 #C (0.16 Btu /hr-R2.ep) between the vessel surface and the surrounding atmosphere. At operating conditions, the average maximum heat transfer rates of the outside insulation surface in the refueling 2
bellows region and on the top head are 176 kcal/m2 -hr (65 Bru/R2 .hr) and 163 kcal/m .hr (60 Btu /R2.hr) respectively. The average insulation thickness requirement at all locations is 93 mm or 3.66 inches. Minimum air temperatures outside the vessel and insulation are tabuleted as follows.
Minimum AirTemperature Vessel Region Outside Insulation Below and outside bottom i head insulation and inside 38 C(100 F) vessel suppon skin Outside vessel support skirt 38 C (100 F)
~
Top head 57 C(135 F) 1 e
e 1
i
Response to NRC question August 24,1992:
4 b
- O C-
$ Pwduc fuesf]Cr15
- Response to NRC question 2c i
inside Chan- Bypass (outside channels)
%oaction nels Rod Position:
t Inserted Withdrawn 2 5.6 5.0 Flow area (m ) l7.4
' Response to NRC question 2e
- Flow Path Pressure Drop Loss Coefficient (K,dimensionless)
(Pascal) t Across Lower Plenum 5240 K=.9 per CRD guide tube row,83% area obstructed I K=.4 per CRD housing row,65% area ob-structed 2
6400 A/,iK=.036 m l Core Plate 48200* Multiple 2 phase losses iCore K=1, associated area =1.7 m 2
! Top Guide 600 ,
iChimney 31700* K=0.
26300* AP=0.083 046 Q,2+8.3 where:
! Ste Response du Q1=2 phase volumetric flow, per separator (ft 3/hr divided by 1000) j b< Ate- QueshDn &
AP= pressure drop, ft of 2 phase mixtur.e i
2 iSteam Dryer l2500. K=165. associated area =28.8 m
- Pressure drop includes hydrostatic pressure of 2 phase fluid
%m
& Response to NRC RAI 950.13 an PutJue question 4c.
Area (m2) Irreversible loss coefficient Descnption ofloss
(+mensinniess, from TRAC)
FA FRICP 9.6FAI (mlet onfice,3.84 for penpheral channels) 2.992000FA3 1.011000E-02 8.450000E+00 (lower ne plate)
J 1.011000FA2 1.244000E@ (per spacers for 5 spacers) 9.188000E-03 6.290000FAI (upper tie plate) 5.350000FA4 1.500000E+00 (approumation of rhmv 1 to bypass flow-path as flow squared loss coefficient) l l
l l
sown s
'"'"'"*^
. Rd Gucste eb" sichnt s1ry Actysis R:pm
~SBWR' l
2,PV bead _.
t s F ' Refuehng bellows Steam cryer "~5 .{
X l support skirt
. _ . al Head vent WC owet 5 f Steam,iow restnctor i j
j J l- i _
J q'
Steam separators LIJ i , Stabilizer
,oII- .
k ti l, l l, l i
.,,!l, ,
d s __,e _ _ re.owat., spars.r g g,
- fi ,
S'p,$$j
+9.hti l Feoowater inkt Shutdown coohng j :. - - - - - - -
-l(.
outlet : in I , - - , SLC Wet
%_ d .
I Chimney restra:nt
^
l _
- Cheney i
IC retum . T l .
' Chimney partitions ,
l j / ; 3DCS inlet -h f Top gue l s- GDCS equalizing
- u woi
__m __ Support skirt i1 i= j
' 'f l Shrous Fuel & control rode #"~ ,.
i
' ~ ,
n" - - inteprai ,u. .uppo,i .
- =="a sua '** x klIl >
II J N ' kJ7 ""' "'" l 1 I l[lj'/ a j CRO housmg r trWore housng :! i , '
- ;- j CnD roeiren o.am l
s ! , Onun = 1s i <: JU J i; . Figure 5.3-3 Reactor Pressure Vessel System Key Features Reactor Vessel s.a.22 -go - 1
1 l m,/*
- SAsm Ru A
~ SBWR " A ] 5 $C5f61SC lD OufibCn 5 standard savory Analysis Report \ I I ISOLATION PASSIVE UPPER CONDENSER SHIELD CONTAINMENT DRYWELL (TOTALTHREE) WALL COOLERS (TOTAL THREE) / i GDCS POOLS m ae
\.
3,,, s, (TOTAL THREE) C - . jh - - [--[ UL _! b4_t " h l ll '/ /
$, DIAPHRAGM r / FLOOR am i r . , . .
~
] ---:
j
/
/ [-
s
- GAS SPACE som t, -i i i
- j. -
- / _
,n _
=
,. - = i ,
V a ssa 1 , l W yr! ' r i *' = " ~ C d i T i !t 132co 17so' nsoso i . l AAnMMOIFVFI im !_ . . . - . . _ . ,_ , ,, -.._.. . __
'~'
ELEV.10000 i / g
" a , t =a . _ ,, . ,\,,p % SUPPRESSION m :_ nao _ _ _, /
'w n' ~
i Oi,~
,_ \NN -
POOL mo _
-- - - N HORIZONTAL VENT SYSTEM o i m - _ _
n '
, . no ,
N CONTAINMENT ' O C - ] BOUNDARY LOWER
- n. ism DRYWELL i
14 \/ents Figure 6.21 SBWR Containment Bounderi
- 2- "'
contanmentsynans-rescuara sees -\\- F
Answers to Purdue University Questions
- 6. Continued
- c. FAPCS: see attached isometric drawings (isometric drawings are only available for !
Portions of this system). i
- d. FW line: See response to question Ib.
- 7. THERMAL HYDRAULIC PARAMETERS @ 150 SECONDS AFTER MSL BREAE INSIDE i
CONTAINMENT: Assume FW pump trip and reactor scram at time zero.
- Water level: Chimney 16.1 m (two phase) Downcomer 9.2 m
- Void Fraction: ,
Lower Plenum 0.24 Channel 0.63 Bypass 0.62 Chimney 0.66 Steam Dome 1.0 Downcomer 0.70 ,
- Vessel Pressure @ Dome: 349.4 psia
- Quality @ Dome: 1.0
- Power @ 150 sec.: 5.78 x 107 watts (Water level and pressure as a function of time is shown on attached figures.)
- 8. DURING INITIAL TRANSIENTS FOLLOWING A LOCA OR BLOWDOWN, AT AND AFTER 150 PSI: ,
RWCU/SDC System ,
- Above RPV water level 3:
SDC mode can be manually initiated ,
- Below RPV water level 3 and above level 2:
RWCU/SDC pump "runsback" to RWCU flow rate (172 gpm) and the regenerative heat i exchangers are placed in senice. (SDC mode is terminated)
- Below RPV water level 2 or high steam tunnel temperature ,
RWCU isolation valves automatically close
- II -
. ay
\
s \0085bdn ] kCS W S113 w Sud:rd Safety A:alysis R:p:rt i 1.50E+01 ! I i i
.l 1 MCPR _
q _ O L h 1.00E+01 L - g - tu - t 3 O _
- c. _
p - 9 5.00E+00 - i b - x - O _ 0.00E+00 1.00E+01 2.00E+01 3.00E+01 4.00E+01 5.00E+01 O.00E 00 TIME (sec) Figure 6.3-17 MCPR,inside Steam Line Creek,1 DPV Failure i 2.50E+01 , , , WATER LEVEL , 2.00E+01 - 2-
' I 1.50E+01 -
eto 3 ' 2 - id 1.00E+01 - - 3 a - ; 5.00E40 - I ' ' ' ' I ' ' ' ' I ' ' ' ' ' ' ' ' ' 0.00E+00 7.50E+02 1.00E+03 - 1.25E+03
. 0.00E+00 2.50E+02 5.00E42 TIME (sec)
Figure 6.3-18 Chimney Water Level,inside Steam Une Brook,1 DPV Failure 6.3-45 Emerpency Core Cooling Syenome , ,
- y ,
, 0 25A5113 Rev. A stuent s:tery Analysis a:p:rs SBWR F 2.50E+01 , i _ i ,' WATER LEVEL - l 2.00E+01 A y-IL \ - . Z L - 9 1.50E+01 - t- - v) _ 2 - d 1.00E+01 h
$ [ s _
5.00E+00 - L ~
~
' ' ' ' ' I ' ' ' ' ' ' ' ' ! ' ' ' '
0.00E+00
'.50E 2 42 5.00E+02 7.50E+02 1.00E+03 1.25E43 O.00E+00 TIME (sec)
Figure 6.3-19 Downcomer Weter Level,inside Steem Line Brook,1 DPV Failure
, . i i . .. .
8.00E+06 , , , , ,
. , i i ; 3 ,
1
~
1 VESSEL PRESSURE _
~
6.00E+06 ' -
% )
0,. 1 m 4 e . 3 - g 4.00E+06 - w _ 1 - a . 2.00E+06 - 1
- 1
' ' ' ' I ' ' ' ' ' ' ' ' ' ' ' ' ' '
0.00E+00 1.00E43 1.25E43 2.50E+02 5.00E+02 7.50E+02
. 0.00E 40 TIME (soc)
Figure 6.3 20 Vessel Pressure,inside Steem Line Broek,1 DPV Fellure Emergency Core Cooting systems gm
h Answers to Purdue University Questions ;
- 8. Continued CRD Svstem a RPV water level 2: High pressure makeup initiates
- RPV water level 8, or low GDCS water level: High pressure makeup shuts off l FAPC System
- Spent fuel pool cooling & cleanup continue if AC power is available. - If AC power is not available, the spent fuel pool temperature increases and is allowed to boil. Make up Water is provided from safety-related piping (having no active components) from outside sources.
FML Pump
- RPV water level 9, (or due to exceedance of pump protection parameters): Pumps tripped .
- Motor Operated Valves: Remain open unless power is lost.
- FW Control System: regulates flow to maintain RPV water level. .
Vacuum Breakers ,
- Self actuating
- Full open at AP = 0.5 psi
- 9. VACUUM BREAKER SET POINT = 0.5 PSI (DIFFERENTIAL PRESSURE BETWEEN DRYWELL AND SUPPRESSION CHAMBER)
No logic required. Full open at AP = 0.5 psi.
- 10. OPERATING PROCEDU'RES AND ACTUATION LOGIC
- Low Pressure Coolant iniection of FAPCS
- Manuallyinitiated 72 hours after a LOCA to provide RPV coolant makeup.
- RPV Pressure s; 100 psig to initiate flow. Full flow of at least 1000 gpm when reactor ;
j pressure is below 55 psig.
- Used in conjunction with SRV discharge lines for Decay Heat Removal if RWCU/SDC not available, and the DPV's are not open.
- \6 -
Answers to Purdue University Questions
- 10. Continued
- CRD
- RPV Water Level 2: CRD pump suction filter bypass valves (F014) open, standby CRD pump is actuated, flow control valves (F020) in high pressure makeup lines open, isolation valves in the purge water header (F012) and charging water header (F030) close so all makeup flow is delivered to Reactor through high pressure ~
makeup lines.
- RPV Water Level 8: Flow control valves (F014) close to stop flow, to prevent flooding of Main Stea,m lines. ,
~ '
- RWCU /SDC
- Manually initiated for LOCA recovery to perform Decay heat removal.
4
- Above RPV Water Level 3: RWCU/SDC used to remove decay heat.
- At RPV Water Level 3: RWCU/SDC flow rate is reduced to normal cleanup flow rate of 172 gpm, to avoid uncovering the RWCU/SDC RPV nozzle locatedjust below Level 3. .1
- At RPV water Level 2 or high MS Tunnel temperature, the RWCU/SDC system is isolated.
f I 1. FAULT TREE ANALYSIS FOR SB%R GE has already sent Fault Tree's to the NRC. (For detection ofICS tube rupture and automatic functions to handle tube rupture, see response to Question 3d.)
- Ib -
I- n- -
. a e
! :a A I I3!l 9 O
!I
;E 3 .
(
*d .! *
$8 E! !l *;. !/Dil/ C 5 ii I d ! ! 7 :-
b Id I! .'o f
" i
!!]! -
4
'l e
- m
=a =!. Y. **o.4 4*4- y !:t .13a,.ta!e/ Bm 2
!. a e W !
;e4D
-s s s s 5 :
c.,a s s N s s s ( 34,5 v,0 a'G Veud! s s
. 5 s N = fe N 5
N 'pav3w4 34sva r 0 [G
)
'4Jv0f0vw cri cas ai .
s ... ,8 s s
- (iD :
2. Q, __ --
- % g s
lt s s s s s s N s s s
, s s s s
s . s 9 s ' s f s s g*- *23r' 6 s O : - s , s s s x ' k
) W ,i,
- 2 :
- 1[. :]E- :
1 3 :
- = x ,.
e _J : q:s s 6
- s s
s s y s s s a,,s s e s, ,
.. s s,
s s s' s
~1 8 ? ?! = ?
, 1 ,
?
* : O :
- t . i :
- O :
as-
- o kt b
- = :s .]'t s i e s t s
s s s o. s, w , , , s
> : < =
- : , s a s , ,
s s s s s. <
'_m, , .
m, S s > s Q Q s s s m _ s o o s, s s m m
- : * \ \
s 5 s s .. 6
. ,. e r
6 s s
)s 2 a uo
- :s s s am s
, : s
- ee I
s' s a t O 4 M : t o : 24 0 !, e 5 s e 2, L '. , w s t i i 4 I .. :s s < s
> s s
s . g s s ss s x>s xx ss _s )g , {
? =
- i s
!s & j ,
o . y I'/% s
- 2 t i :
' l
- o :
s s o a 1 N2 : : m s o
- a. 17 17 :
. s a
a s
, 2 a
k ,
-% t.:s:
[.
* :s e ts s
s g w {:
- ts m s ms m s i s s / s 1 x x x sgg
_n- G 8
. .]
ArrAcHMENT 1
- 1. _
$\ }
/
~
b 'V A w /
,.,A 4
O e a c [ - y fx x 9, 4 o ;
.o
.m.
f s : yr.; ' _ sy / e
. ~
o 4 ,,O ,
\7Q "$ c \
l l 4 r #- @' , l '
\
s '
~
,/ N h
e
, /
.5 e ,
j
^
1 j of+ o .
$ $ h*
\
/
=g i f
~ ms!/ aswp
/%2 \i '
~
N
\ NT hp
*\ \/\ /
.' '4
/\
\o O
Q
\
'C
[h\ "+ Vj' T - e, ; as 7 p !
%)
Q & . e% g.w...
~ l8 .
ATT. 2..
,y
\_f ,
\
j\$ /x 3
$ / x'"lzt /
h \ Y a O,. /
/
\
\
\ j
\
\ j /
\ [ ~
k, @
\
,/ \ +
s ,- o Ay x/
/\ / '\
/\ '
'l
/
\ytj[Mh,N/ x/ / \
7 uwn
,s <,
'x ' !
7 x s, x sf / g j/ \ f ,
, s -
y/a s\. s / Y\ h Q \ o/ %k x
,$ -[, h %m \
m \ IV i
% / 'n- QaQ
- w. ,r 4- Y\
4 _l t\/ 8 o o '
'\ f) p j 4
; v4
* ~ s, N/ji f .,
/\
/
Y
/ x . / >% \
m 5
%% l,e - =,
I 43 j/\ z
/ xs
\ pz d \^8 s 'h~' s
[d,/'\, Q/
~
i N
'\ 0/N. ,/,\
'\. .
1 4 . i
e
' ATT3 !
g/ f, s w/ / ,( , o :l a 'x a4 g g/m se ' i
+
%*f'
/ [b .ig .y o,
e. Q p. x+ a s y 4 is/ 4 r N . w *, ,
.i ,
Vb.aA '
/, /\ , \. . '
x / \ /s@/N \. ' 9 1 sq
\ % s % g4'
\
\ f _ r. _,
'\,,/ f fl % ~
v, '\ z/ , w . y f/sx/x N/ : o\ /'. o ,. s - 96
$[
\ e p
s / x \ ,' x 4 ' Y h es- f' 'y
.,t o ru, su , en'-.s .
y [ .y 3,/Ny ,/\ '" +# y;
/.
5 xa e, / . g : f \ * ', W,'& %% $s% s o$' .,
'lpp e'
\
l %)% >
\)'
,g'<
n.
*j t j/\ 3 ~\\ ,
n .a _- i i \ Oo j/ 0 k . dP / e-
,3 S s/
' Q' y 5 - 8 u %& o% w} 4, ;}
,s x w ,
-\ 's g =c k n y
*f \
\ ;
T /
% .; C V $ /\ '
t / 3 / o-
+ s ,,s -
~v a.e ..
x < c* o+
'a 9fy-L-- \ x'8 g ,\
n 1 o y j e h _. g - zo - g/ g %s ,
~
Am + 1 w\, y y r#
,j --
6 Y 4 a o 4 'Q% 9 % 9f o %o ^/ g Q y
.e A a .
s
\
4 4
/
p. 9
# x- a N'x/k_
~
y ; '\ N
. $" 'f 'N
. m
_ o i _*+ ~
.g
'q e,
4
~
C
%+ /\ j/ 7pt o ) \
~g / /
r
,y D %$%
g '.
- / /
' * \ / s ,
g %% p*
'\l =e b/
uw n /% i sos
\
\ /\ ,
xl pg, j%g Vy 1 3 / Ih g
)
u. c k.
,. \
j.
-r-A c a
G h ! A S%p.. ju /N
\(
i
, l l
j NTT. 6 l k . l 4 Y Y
,_o
, k
/ b,e s i \ / l
.. /
N N f
\.
,/
/
Og J s O +, = \ ! O h. o n,.\ y; . .., . . ; , g , s x .x. A c x . s s/ N-
<v -
, $g se s
\ s!" ' ,j/ $.gy '3 vs k3 %; '\ g 's
+ -
C n .
~q ALs.-
' O c
O' Q" + l & ,' .
) \0 J
~
g ' V # ',. Of'. ,
~'j
,0-
%m x
\
_s
',\
' $e5
\ p' i s \ \
O \
'l $39Y, ! '
g
" 0 fg '
9 i ,
,i \. ,
l z g .s',' s ' xs cs y& / x
- s- xm xy '
v coo # /
,s, y
Qs. ,
, /\ \ '
$ / 'z, .
N O,. k- @4 , M ks
~
s N =
\ /\\/ A. 9 g o.
P4 A y\ o o o *V N O R
% % 9 N O
h - N _ _ _ _ _
L- . ~ y- n ,-
~
/
x, e e p/%g,y-n e
'. 0
/ .-
, igy w
D e p
$i / *
, Dg U ,
/
t\ \ 4:. ,m%
'y - d' e
8,- s q
%5 s
O x o x o A T x ,
/ ,
/\ ' x ';o
'N s s =
~
,c
'g' e\\,s'N % \= so '
Q
'4 1
s o *9/ <
.yN x o,
[pN s j % g/, ,
, , \ $
/O # f
$ l,-
s f _1 ' Ok' ll.,*5 _ '
~
,/
/
s
/
7 O M I . ~ y.' N ~ 3l l% '
)g .
\ / ,? "N 'qcs/'
w h
. m ' f' /
NS p^ j \/ j %m/\ i ,s i
/ o.
'y e S &
'y ,
's t-
- t. s s
eg , e x f yi o' % x
%m o \
\ 8 g %w / % ,%o N /-
_._/ 1 h
/
.l A N,
$ ' ' . N e A
/-
9 , j\ / \. m- 94 i
'. '\
- 4. Q ,. '
s, .
/ e N '
f s og ye:f Su-- 1 e ;g o / \ p0g s
, 3 k!
\9 .'[ g/ N9 Oi us o &, '.
m co y, 4, ,\ to. \ N < v./ s v. x + a /\ t
/
n x l' 1I o g m 1(o e 2 s k , xs g ' ,\ h d r u-
~7 c 4,5
% y' '\< \ ff' 3 N @k'i Nti [\'\(. k.
rs
~~
e .s..
\%;
, +4Z=y~q$
.g-
ATTACHMEN T . 7-
'z 9
s -
% c4 .c 5oe2 .<
,', 'aPo Gis T-o O 4+ 7 o
%* a 6 -
@%+ .
?Q' ._g { _w . _ ._ _
0 x e s o
/ \ os *
%o 7 *o + 3&
o=% z
- OLW$
gi $3o e It
*l c 'e b <3 Q2
\'ea5)/
k ' '
$.O 4
1 1 s A/KXlk ( ll i\ X / 9- g p 4 4. ', < O E
~
Y.~~YY # 2 m s '# O ' D _ G - /f o - m c M ., ' g.
#s
/ y,. / \
~Z. q" j WM
# /bh, g f-x
% - y g S >
m - W _c
'G Q 8
*Q . ~
9 i
*4
= esmer ae
_, --ew
*66
,p h #
f
]
euMP
- g w
1 a Q ,4
~"
Q ! I 7 s ,g i 2 b
\s. ,x s s it
, c 2
$g
~~
~ ~ ~
'Y /\ ' /3_ 5- -
o z '@
*oe a e
- R o AS p ~' 2 '
2 - t4 c c 0 O 7,. g 4e +h '
- bx V
s $2
~ w ,
d N g s
& s ,, -
w .o . 4Q-
'n ;/
/ '
g ' j '\ '\ /
,1 4, p
4 s
/ o '
x f s , d _, .,
/ . ,
\
M Q N \, 2 . O ',
# .3 4 4 O 'c- 9,.
@ \
8.-se gf\ 5 - T 1/ ,c 0 gg ,s eY ,
. q O y- ;
e N m O , T
@ y ,
s
\ s J\ *f, -
_ y_ e. i I20 o* 1 8 h , Sy g y o' >o- j' 'hMl / ,q t 9' s' 090 9 N 55 f33 g< p; g ; % e>% :P ' - g Y [ ! Mhk i RWCf 1!SDC. SucTicu. (D W, MES. Ditmu Co uu. O !
*6 15 kot D.(40T S cw u.)
gbO p ?
' n ua.ta tw A.
$ p <~
wp. r-ce rewcu/s n c_ :
/ ,
M- 'a' nue 'a' s[),g,w- ;
FAPCS REACTOR BUILDING h, 1,-
/
g -L/
/f\,
l s ./
./ \,
l "x / ', [ ' s_ ,
/ g-11 1 1I -
/
LO 1 Lf al g lT - l-F1 u 3:'3-'t 7:3r1 3r l goo
- s I C 3 : 'I' 1: I: T ,
y .-
- t. s u : . ,
ln _S 1
,, =c '
p,/ s .c m
. iym l y
.c ,. ..x
'y'~
' E
_N@ _
<51T_81 __
/' "
,'a #
= %. _'. . - -
2-
> _ . s %
s 5 _
,.. ......_. f-7 g- , - -..- - - . . - . . _
=
=
_ _ _ _ 7= T " T
.]
. l FAPCS WT l pm g __
-...v' -
_ ; ;; ~
, .amo . . . .
$f1 '
__ _ n f nam woo
.- - :1 :.t m n w.- . .y . p...,.
~.. \.
L.
.{
S.: * . . . J. .
.f . ; . , _ - -
_a me I '- ' I' 1 N 9 . , .
%/ _.Y_ _ $,.. _
.., ' kat f ..,'\" .,,, V . "._ _,A_f NUCON Nudear Technology B.V.
FAPCS. LOCATION OF POOLS AND EQUIPMENT (SKETCH)
+-
f% T~
~
'l 8
I \
<- Nx s 8
ll g ' I (#*
- I g lI l
II s Yt . . f 9 s u t ., 14 WON Nuclear Technology B.v.
FAPCS. ELEVATION OF POOLS AND EQUIPMENT (SKETCH) e M.Bae m -- y r X Amayf , '
#24 4 u4 awwwo(sf . ,
We 4maase u e -
~
4 % o . ._ ane.ame , J u hav al eq, _
' " ' * * * ' " + -au, ,
saamme summers t- SW 1h N #/2.ase A
\
i r j /agp 4 #* M d- - , w.. .
.g;:_f o -- _ ,
ede %ro y,
/1/50- -
V 41(soo , I A
- 5.4*o h.e
! M ICON P&aclear Techno400V B V.
-- - ..__ .._.. _ __ _ _ ___ ,. ._ _ - - ~ ~~.-- -- --._._ , ___ , _
d 1
! l 4.s ' !
t'l '! l 4 ; ~. II I ... ' .
~'
I I! 6 i 1 _
. i j '
1
; ; ' i ' 'i -' $ . I! t t
! ! . i.
i m ','., Al ! i q, i j ! 2' _
- ~
i s.> , ~
^..
'f
. ~, i
, -mG ll t fa 4 ,&.
A 4 $ .g 3e 8
- Z~ j ,
1 i. > I I
.', M ll t
+
4 f s H' og N {l l{ I I@ 'a J I. '
-a,
,',* ------~~~ 4, =gl
}Q-#
i i 8 h
^
^D 4 '
h
- j M
3
- o
" ' O' k*'
O l i It_ .,.!! .... +
,II ' ) ;l i ,
, a g I o '
III. , g lII *
-- -]- i W .
'i J ::::::. t i
I ,
-- i E
,' ll
_....,..,..o. ll
, O F.
..oo. . . . . . . .
,-~..-, ,".
===
[;) ,My -* - . g g gf ' e o
.nH-
, t
.' t *'
' t ? j
& ~ -
w 1 h,. '. : ; ; v]&'h'
. 4 og.
.. i c....,J.
--- i t .,
t W'
- M* *. i ; t.-
5,' l i !. . . .- o' . i i; ;
.:.;'1 i
-< : : : : : : -[; .,. i .! .: e. -
*(.
. l '
i
- r: :: >
( f../'~..t. , j s, N, . ___._.__.t,. I;, ,
- v. i g.o
*j*"
"10 0 *! ' f '. !
h _____.b
' b !l,l.. { 7' >
m
- h. . j!th.n..;,.n.g'-
i
+ -
-~~~~ , 2 j j : .
! . h-'* J l
- W f****'
Y.Y. I w
' )
r
~%. ll 1.._r ;
a L.4' .t..:.?:::d.::.:.::.:__::::::::::::::::::fi:_....:...n... ,i
. i 1. 1 f H l
[ 3 e.. .... .h .
-...............-...i..
e _____ . I H
. O 8
o -- < e:::~:: t.
.: 2 u.
- 30 ~
Y / .,f& Mw thvted. -
\
i I i t l
--- ... _ _._, ._ - - . . - - - - ~ - -~~
~~p, / l $
\'t -o
(
<e r. %- . . . e ..
d' l ff' N. )Qq
'%f'C>
/'(
e .. x
?,,e </ s % "YA ' s4gd- ;
/ /,/
. . , ,~ !
- $'.j
- s. , - 4,
~
' 5.
/
/l Q9a
/
~
.e
~
,e f
o ,-
! /
N[ , Y f*y-
, . .s
.- _ , 4., .
g~ .,.A A e.. .
- .sp N .: s m .. . , '
d w.o ceu. b .~l"* rau4 N - s ; e5cm QLtfa. .: 1 g *
, g Peces.o mecs 4 LWs: :
ec,ures.. - a i
?
1
I O O *
--- / i:
e
%_ i
; og -
g) - GN
. . . _ . / 4 -
. W o
_.._3_.._ 0 gg w / y
/
/ E) /
./ ~ 07 8
O W) Y - c m CV 0 m
. . i -
l . .
. . . . . . . . 2 .
*e m .
.u.a.
. . .B - g ausam. .
"U.
s ._e. .N E.I.. T .- i . . t . . h
- 1. . . . -
- 2. . _.
w M o ... __ _.. q_.. .
.o g g (M .
o>. . 4 .._ . c h) g E q I
-. . __ . . 4 4
i__ _ _ _ g W L.L
. -..- _ - . .h . . . . .
yu.
. 4 g
# q t -
3 -; - _ - O .i / 1 e h' , tt) .. l (I - _ ._ -. q.- . 1 I,0 . a DI . . . ..
. in - . .
W , y-1
/ ..._ / / _
M
/ / i
- ./ e, f .
-3z-n ;
\
. ? V r i
. . - . . _ ~ .. . . . _
l c r B i f ' / ' g { } bl d 2 c
' I. - x , -
x
. . f A ". .
g s g. q
\
iG \ E g$g
\ ' s
~
~~ '
' ,f/ ' .,
, g -
o
\ J , , .
- 4 p tJ y
/ j. , -
b x
, ~
I '
\. . Ng j m ,
. . o -
.[
'. s L(r),
'. 9- / \ -
I
<C k
.A s ' -
y.
, h1 '. ... . .- '..7\ ..
*/ \ / ,
/ =3 ,
'g ,
w.. , -
- g. A
' \
.j. , . _ .'. .,
.\x
,s x--
s
\{
g .
. .. r.
fs "$ \ s + -
.1 - f '
.\
X =ar /. gg. . ,
\ .. .
s h . /x . . ./ /
' \ . .
,/ ;
',/
x N _
- s. . .
\ I o b'
'\
- ./ .- %-- i ,
j
/ ,
\f-. . , / \ .
\
s i ./ ,i - ' i u, - L,* .
.' , / .. f ,..
- i.
i k M f g '/ , Y /
/
\ -- -
1, , l
\ \ \ :.,.' w .
, i E '
d'
\- d af xp e
, o
% cy
~. .. \. .
\.,: '
\s .
', ~g a
- q
. s
%S Q'c- 4 e :s ..
o6 , 2 e 1 2
/
/ \/ 'N-b _.
e s
\ e=
e u k d _ _ .. _ - _ _ , _- 4
-J ,a -
1 e
~
c l G C 1 m e m o c.- S (M
\ '
I Sg '{ - m l O f s, og$ y%
=- h '
, x-
),
. . . . -- .-- ~
- ~~
'g i
*I -
, .i-
.K ~
s ( 0 i O 4 ..... 6 q to 7 g . Y W
^
S \ - s sg. ; j
~
g ) v A.g
\ \ \ v g ( '
.g 0
?
- k 3 1
l i 0
+
?
-i i = t t
I
.i 5
l. 4 S 2\ C t.O' H2060 . th7 o~h o , OC NM M ar% V 57- l
' {
# CPir.t.im% \S 8Eco . . _ _
+ b S 7_ o _ _ _ ~
- - - ~ _ . . - . , . ... __._ _ _ .
l 1 n
! Qo >
63\800 U.W.L) I c 'l
~
. o 1
~
I m i . . 4.31h . 6 <
- I,. i A.
f .
.[
I
/
; Q - l. . .
1 i g i / , i 1
.Q ;
t 4 . O
.\
, , i' s l ,
.l. ,
i N l !
, g y ..
h, - .. l
. . . .._, p P i, . g
. o. . '
. N . , . .
g.._ - ..
.___ _ N_ _ n_
, ' I
- l. .,. .
! l l
! l f
i i i
. - 1 i .
i. i . 1 1 $ . I .l _ -,. .,
. . . . s ._, .
t . ;
- i .. * *
- i . .
4 -. , 4 . . 8 . . i 3 ; -
- I j -
FAPCS ,
; , smr .nes. mu jom: ~ un i
ma een - f f P t o n.. i { l l i
- t .
A I 1 l 1
$ )
; j I
' SM'
I
.. a ATTACHMENT C ,
Additional responses to questions and requests from ;
~
Attachment A not covered in Attachment B 5
'r h
i
?
l 1 t A e P 4 i
.I
- 3. ICS AND PCCS INFORMATION
- c. Elevation of the PCCS condensate return line.
Isometric drawing of the PCCS supply, drain and vent lines is attached.
- e. Detailed design of the ICS and PCCS modules. ;
Enclosed are the drawings of the prototype IC and PCC to be tested in ; the PANTHERS Test Program. The PCC drawings contain the two modules of the condenser unit. The IC drawings show one module of the two module unit. i L 1
- 92 0 6 EEi c_
4 0 P C C. SuP9LN,bRmo AuD g%, s/Eh3T L.)uE.t 1 tin su 9.u . ( T Y P. tor 'h PC C.) o a h.g 1 W apt =.12 L EcJ E L g@g y n s C=DC.S YooL 2_?_ SOO {OQ3 ll h ,, { SUP9 PDCL i 010.9 , C f IP y ! r ~ ix J L N,q o , () . f;( ~ p C'S Ng pr ; a a, 'p, 99F'N r i >%
. %, %sgk h
m+[ [s,e.ij, 6 A I?$ j= : f 0,
- 9 V ,pV 1*
lf O! e p . ' . 10 ' 6Wf :' W y-1
/- 4 h/
f / , sed i
i Question and Requests on GIST Facility ,
- 1. How were heaters fitted to the vessel?- How heater surface :
temperatures were measured? ;
.1 Response !
The GIST core heaters are cartridge heaters rated at 3500 Watts at - i 440V AC single phase. The heat flux is constant from the bottom j to the midpoint, decareasing linearly from the midpoint to the top. : The cartridges are_ manufactured by Wellman Thermo Systems i and were purchased from Montgomerty Bros. inc.,1831 Bay ; Shore Highway, Burlingame, CA 94010. Refer to GE Purchase Order #190-RP614 on August 10,1987.' t The bottom end of each heater cartridge is fitted with a plug which is inserted into and retained by a test vessel flange. The heater : cartridge spacing is maintained by spacer collars (washers) and .j the confines of the vessel intemais. Surface temperatures were measured by Gordon Type T - grounded junction stainless steel sheathed thermocouples. The . sheath nominal diameter is 0.062" except for a tip with a nominal diameter of 0.04" x 1.5" long, The thermocouples were fixed to a heater rod surface by spot welded stainless steel foil strips during .; vessel assembly. l
- 2. Provide the loss coefficients in all the lines of GIST facility. l Resoonse .
Local losses for the important flow path restrictions in the GIST j facility are as follows: ;i Bottom Ipp. I Guide Tubes 1.5 1.3 Bypass 1.3 1.2 Channels 1.68 1.273 Downcomer (annulus) 0.8 1.0 l Standpipe 0.3 1.36 ! 9 w w m v v-m .- , -w -- y
e Resoonse to Question 2 Continued ! The local loss for the channel to bypass leakage path is 2.5 The local loss for the SRV orifice is 2.71 The losses for tne GDCS lines should be chosen so that the l GDCS system flow matches the design flow. ,
- 3. Need detailed test results and conditions for five GIST tests 3 used for TRACG calculations in order to run similar experiments as required by NRC. Need design of the break- ,
simulation using pipe and valve on various lines of GIST facility. !
-i Resoonse The initial conditions for each GIST test are given in the GIST final :
test report GEFR-00850. The key results of the five GIST tests _ 1 used for TRACG calculations are included on the enclosed .! diskette. The tests simulated were a 2 inch diameter drainline break in the bottom of the RPV, a GDCS injection line break with a 2 inch diameter flow limiter in the vessel nozzle at 29 ft above vessel "0" and a steam line break with a 13.93 inch diameter flow limiter in the vessel nozzle at 62 ft above vessel "0". The piping for l the breaks which directs the flow from the vessel to the ! containment must be large enough in diameter to insure that the : back pressure in the piping has a minimal effect. . l
- 4. How the pressure sense line were connected to the vessel .!
and pressure transducers? . Resoonse l The pressure sensing lines were connected to 1/2" pipe nipples welded to the vessel and pipes of the test facility. The through ; holes were flush with the inside diameter and deburred. l l
\
l l i
L
- 5. What flow meters were used to measure a) water, b) steam and c) two-phase flow in pipe? And what flow meters were used for downcomer liquid flow rate?
Resoonse Orifice plates and nozzles were used to measure single and mixed i phase flows. Turbine flow meters were used in the GDCS . injection lines. The important parameter for this test was water level which was measured throughout the facility. Downcomer liquid flow rate was not important and therefore not measured. Other Questions
- 1. Can GE supply us heaters with built-in surface thermocouples?
Resoonse No. See response to question 1 above.
- 2. Who made GIST heaters?
Resoonse See response to question 1 above. 1 s I
j ATTACHMENT D i Responses to Questions made to GE by Purdue staff l during meeting on October 1,1993 : t n l I t i i I i i i i
_ _ . _ . _ - . . - ~_ _ __ t
- 1. Send paper on heat transfer coefficient correlation for condensation in the presence of noncondensable gases.
Efellly Attached is the paper from the Tsukuba, Japan conference, (Purdue has the less-detailed paper from the ICONE-1 Tokyo, Japan conference.)
- 2. Is there any bypass flow in the GIRAFFE RPV? If so, how does the GIRAFFE bypass flow-compare with that of the SBWR?
Reply The GIRAFFE testing was not intended to simulate all of the phenomena expected in the - ; SBWR RPV. Since the purpose was to investigate containment performance, the amount of bypass flow is not considered to be a major parameter for the GIRAFFE program. j r
- 3. How were thermocouples attached to the PCC tube walls?
Reply ! The thermocouples were sheathed, therefore thermocouple junctions were not directly i attached to the PCC tube wall. .; i
- 4. For all three LOCA simulations, how many PCC, IC, and DPV units were operating in GIRAFFE?
Reply Main Steam Line Break Bottom Drain Line Break GDCS L ine Break .; SBWR PCC units 3 SBWR PCC units 3 SBWR PCC units 3 , IC units 0 IC units 0 IC units 0 One GIRAFFE PCC unit simulated three SBWR PCC units. Y l l l l 1TRilK 9158 ) i I
Proceedings of The international Conference on Multiphase Flows
'91-TSUKUBA bW '
i ICMF'91 TSUKUBA VOLUME 1 Extended Abstracts l Edited by G. Matsui, September 24-27 A. Serizawa and Y. Tsuji 3gg3 in cooperation with the members of the Conference Committee and the Scientific Committee
Proceeding of Tha Interrationzl Conference on
. Multiphtse Flows '91-Tsukuba # September 24 - 27. 1991. .
- Tsukuba. Jepsn .
i i CONDENSATION.IN A NATURAL CIRCULATION LOOP WITH NONCONDENSABLE GASES PART I - HEAT TRANSFER Karen M. Vierow G. E. Nuclear Energy I San Jose. CA DM25, USA 5' C Mr 4 C 76' O and # Virgil E. Schrock Department of Nuclear Engineering University of California, Berkeley , Berkeley. CA 94720, USA ABSTRACT equilibrium dictates that the interface temperature (saturation temperature at the vapor partial pressure) The reduction of condensation heat transfer due is then lower than in the bulk. For condensation of ' to the presence of a noncondensable gas in the vapor is pure vapor, the thermal resistance of the draining ' a critical consideration in the design of heat exchangers condensate film controls the condensation rate for where such gases are present. Heat transfer coefficients condensation of pure vapor. With noncondensable may be so greatly diminished that the exchanger fails gas present, there is a significant, additional thermal to perform its required function. The present paper resistance on the vapor-gas side associated with the deals with the effect that a noncondensable gas has composition boundary layer. upon the condensation within a natural circulation This same physical picture is expe< ted to apply to loop. A vertical natural circulation loop was used with the present problem of condensation inside vertical the condenser section at the upper part of the heat exchanger tubes. However Sparrow's problem downflow side. Steam injected into a lower plenum resulted in self-similar boundary layers and a uniform flowed up the adiabatic side of the loop and the interface temperature. The present problem is clearly condensate formed on the downflow side drained back nonsimilar. The tube wall temperature varies axially, , to the plenum. Local heat transfer coefficients were the vapor-gas composition varies axially as well as measured for ranges of gas content and steam flowrate. radially, and the interfacial shear imposed by the r The experimental results have been correlated as a vapor gas flow has a significant effect upon the liquid > correction factor to a heat transfer coefficient calculated film thickness, particularly near the entrance of the from Nusselt theory. When applied to the theoretical condenser tube. value, the correlation provides a local heat transfer The need for the present study results from a coefficient which includes effects of the lack of full understanding of the heat transfer noncondensable gas and interfacial shear on mechanisms involved when noncondensable effects ; condensation, and gas-film shear are significant. Earlier experimental studies of forced flow condensation under such c nditions have been conducted, however, only INTRODUCTION length-averaged data are available. Local data and ; analysis are needed for a full understanding of the Earlier work by Sparrow and others [1.2] clarified P henomena involved. the basic role played by the noncondensable gas The present work [3] was carried out in support through the study of faminar film condensation on a _ of the Simplified Boiling Water Reactor (SB.WR) , vertical wall, adjacent to a large body of vapor-gas at a ' uniform ambient state. The gas is carried toward the which is an advanced light water reactor being condensing surface by the flowing vapor. It developed by an international team led by the General ; accumulates there until the diffusion of gas back into Electric Co., with support from the US Department of : the vaper-gas mixture balances the convecilve flow Energy, the Electric Power Research Institute, and other toward the interface. At steady state, the vapor partial participants. In this design, an isolation condenser pressure at the condensing surface is therefore lower may be called upon to remove heat from the i than in the bulk mixture. Thermodynamic containment by condensing vapor from a steam- !
- 183 -
l
, nitrogen mixture. The gas micure would flow by with the condensate and nencondensable with a natural circulation from the drywell to the isolation partial pressure which maintains tube total pressure at condenser. Successful design ef the condenser requires nearly the loop pressure. f knowledge of the local heat transfer coefficient. Another distinguishing feature of internal cendensation is the presence of interfa :31 shear. The THEORY gas phase has a higher velocity thar the condensate film, producmg mterfacial shear which, m the case of The physical situation inside a vertical tube is downflow, tends to decrease the hquid ft!m thickness shown schematically in Figure 1. Axial vanaticns of and reduce the film Reynolds number for transition the cross-section average temperature and species from laminar to turbulent film flow. The thermal concentration for the internal flow case introduce resistance of the liquid him is reduced by this thinning additional phenomena not considered in previous effect and also by turbulence when it is present. These studies. In contrast to the natural convection case, the concepts havc been employed in the present work to bulk vapor saturation temperature decreases with develop a suitable correlation form. Theorectical ; distance along the condenser tube and the bulk analysis along these lines is being pursued in a follow-noncondensable concentration increases. This en program at the University of California, Berkeley. produces axial variations in the conditions driving heat and mass transfer. A plausible detailed physical EXPERIMENTAL DESCRIPTION l descriptien is as follows. Steam begins to cendense frem the pas mixture A natural circulation loop, with a vertical i at the inlet. As steam is drawn to the coelmg surface, condenser tube 22 mm I.D. and 2.1 m in length, the gas rmture expenences a fcrce similar to suction provided the experimental data for calculation of l through a permeable wall. Noncondensable gas localized heat transfer coefficients. The closed loop j concentration at the film interface becomes higher consisted of a lower plenum, an adiabatic vertical riser, than in the central core and a gas-vapor boundary layer the condenser leg, and an adiabatic downcomer develops adjacent to the liquid boundary layer. returning to the plenum. The entire system was ; Between the annular gas boundary layer and tube insulated, with connections to the plenum for the i l centerline, the steam concentration is constant. steam supply line and condensate drain line. As part , l However the cross-section average of noncondensable of the startup procedures, the closed loop was brought I gas concentration increases with distance along the down to a vacuum and then given an initial charge of , l tube axis as the boundary layer thickens. At some axial noncendensable gas (air). The quantity of air remained l location, the boundary layer bridges the tube so that fixed throughout a test run, enabling determmation of there is no longer a central core of inlet composition. noncondensable concentrations in the loop. Steam Resistance to heat transfer increases with the was then injected into the lower plenum where it composition boundary layer thickness. mixed well with the air. Upon condensing in the test j With steam continuing to condense, but at section, the condensate (and the air) returned to the , diminishing rates, a fully-developed composition lower plenum via the downcomer. Cendensate was i distribution may not be achieved in the gas phase. removed at a rate to maintain a constant liquid level Downstream from the point of complete condensation, in the plenum as measured using a sight glass. , the gaseous mixture contains steam in equilibrium Recirculatmg air mixed with the incoming steam in j the lower plenum. Fitted with an annular cooling jacket, the I condenser tube was cooled by single-phase heat i i transfer to cooling water. The coolant flow rate was i U maintained so as to provide essentially complete steam Irterface l g condensation on the primary side, yet obtain an Ti (z) -- - U(r,z) accurate determination of the secondary-side , temperature rise along the test section (approximately Maj(z) M4r-) ( l) 110C). I Centerline The system was instrumented with pressure transducers and thermocouples m the lower plenum Wall TC (z) l and at the top of the loop. Coolant and test section Tw (z) - M3c(z) outer wall temperature profiles were measured for
, , Uc (z) local determination of heat transfer parameters.
U(r,z) When at a steady state, the condensate drainage rate g was measured. The coolant flow rate, as measured i 1 Ma(r,z) through an orifice flow meter, and the steam inlet flow gg , I rate were continuously monitored to prevent E (Z) T deviations from the approach to s t ea dy-s ta te ccaditions. The rate of steam supply was determined ! by the electric power supphed to the boiler and the heat Figure 1 Developing Boundary Layers of vaporization at the system pressure. Using flow i
- 184 -
t x_
,' i
?' .,
a J measurements, in conjunction with heat. loss data, before undergoing rapid change to nearly 1.0 and 0.0 ? heat balances were performed to ensure that all energy respectively, at the end of the condensation zone. '! in the system could be accounted for. The data have been correlated as a. correction 'l ' A steady state was deemed to exist when signals factor to the local heat transfer coefficient based on from all instrumentation had been constant for a Nusselt theory, i.e., liquid thermal conductivity i
, period of at least ten minutes. The operating pressure divided by the local liquid film thickness. The ,
i and temperatures were determined by the ability of the "Nusselt" film thickness was calculated from system to circulate the gas mixture and remove heat in the test section. A process sensitive to changes in ' 3uir # , steam and cooling water flow rates and plenum water 6= (1) e
; level, the approach to a steady state was observed to be MN 's 8 ;
4 very gradual. As described in Part II of this paper, 4 oscillations occurred with higher air concentrations where r is the film flowrate per unit circumference, l This equation is for laminar film flow in the absence of : and prevented attainment of a steady state. The ' operatMg parameters were as below; interfacial shear. It was confirmed that the film was always laminar in the present experiments. The l Parameter Operating Range correction factor is defined as the ratio of the local Heater power input 6 - 18.9 kW experimental condensation heat transfer coefficient to ;
',apor flow rate 5.9 25 kg/hr the local theoretical Nusselt value. Correlated in System pressare 30 - 4521&a terms of the bulk local air mass fraction and steam-air- ;
Reynolds number, Re m, this factor is based on the data 4 System temperature 72 - 146 C Inlet air mass fraction 0.0-0.14 from runs without temperature inversions. The result . t Coolant inlet temperature 9 -12 C is Coolant outlet temperature 17 - 23 C Coolant flow rate 364 - 1432 kg/hr f = (1 + 2.88x10-5 Rem 118 )(1 - C Mab) (2) ; i For this range of conditions, the condensing length where M, is the bulk air mass fraction and . varied from 0.4 to 1.25 m. RESULTS AND DISCUSSIONS C 0 38, b = . 3 for 063 a < 0.60 C = 1.0, b = 0.2.2 for Ma > 0.60. For test runs in which a steady state was ! achieved, two types of tube wall temperature profiles The experimental results are shown in the form of the l were observed. The majority showed a momatonically correlation in Figure 2. The data scatter may be due in ; i decreasing temperature along the condensing length. part to the relatively large uncertainty in the air mass Cases with a low air content revealed an anomolous fraction. , temperature profile which increased from the tube The correction factor accounts for two entrance before decreasing, herein referred to as a Some conjecture is competing effects. First, the Rem factor introduces the
" temperature inver%n". effect of gas flow causing interfacial shear which l
!. provided in reference 3 for this behavior but it remains enhances condensation rates. This is the first bracketed to be adequately explained. A thermosyphon mode of l term in Equation 2. It tends to unity as Rem tends to-l operation was considered, but this would appear to zero. The interfacial shear is predominant near the ;
violate flooding limits for countercurrent flow in the ' downcomer. A similar, although less pronounced, tube entrance where Rem is maximum and ' I noncondensable mass fractions are. minimum. The
! effect was observed in low head forced convection tests Second bracketed term, which accounts for the presence <
at Toshiba (4] in Japan. of noncondensable gas, ranges from unity for Ma = 0 to From the majority of the runs, data were used to , zero for Ma =1. . I obtain local condensation heat transfer coefficients. To A preliminary version of the correlation has obtain the air mass fraction at the condenser entrance, been used in the TRAC-G code at G. E. Nuclear Energy l the air holdup in the condenser and downtomer was to analyze the Toshiba tube-average data. This resulted , found from approximate calculations. This amount of air was subtracted from the known loop air inventory in underpredicting the data by as much as 30%. l and the remainder was assumed to be uniformly j distributed within the remaining system volume. CONCLUSIONS The axial profiles of the primary-side and secondary-Condensation of steam in a natural circulation I side fluid temperatures, bulk air mass fraction, I P was' experimentally studied to investigate the - condensate flow rate, and bulk gas-vapor mixture Rem, effects of a noncondensable gas on condenser among other parameters were obtained From a high performance. Steady-state ' operating conditions
! value at the inlet, the heat flux decreased as an depended strongly on air content and inlet steam flow-
-l exponential or as a power function of distance from rate. Local heat transfer coefficients decreased as bulk i the entrarice. The air mass fraction gradually air mass fraction ine eased and increased with mixture increased, and the mixture Rem gradually decreased, i
- 185 - i I
\ . .
o"J i ldg
. . . . . . . ; = ..: ". j, i.g ... . " ..; 7...
.. . 3
...,...,.g..
, . .j.7 ,-7,.
. i -
T'
"" I
- ..... . . m .. ! .!. .
. ., f . um ;
i i
. . i :
- - i i s ei ei i Local Air Mass Fraction Figure 2 Correlation of Heat Transfer Degradation Factor Note: fi = 1 + 2.88x104Rem its Reynolds number A localized correlation has been developed which accounts for the effects of heat transfer degradation due to noncondensable gas mass fraction and condensation rate enhancement due to '
interfacial shear (gas-vapor Reynolds number effect). a For low air contents, a temperature inversion phenomenon occurred which indicated low heat fluxes and heat transfer coefficients at the test section l i inlet. However the locally reduced heat transfer rates did not prevent complete steam condensation. Further work is needed to clarify the temperature inversion phenomon. REFERENCES
- 1. Sparrow, E. M., S. H. Lin, " Condensation Heat Transfer in the Presence of a Noncondensable Gas", i Journal of Heat Transfer, Aug.1964, pp. 430-436.
- 2. Minkowycz, W. J.,, E. M. Sparrow, i
" Condensation Heat Transfer in the Presence of Noncondensables, Interfacial Resistance, Superheating, Variable Properties, and Diffusion", Int. J. Heat Mass Transfer,1966, Vol. 9, pp.1125-1144.
- 3. Vierow, K. M./ Behavior of Steam-Air Systems Condensing in Cocurrent Vertical Downflow", M.S.
thesis, U. of CA at Berkeley, Aug.1990.
- 4. Nagasaka, H., Private Communication, October 1990.
- l l
l 1 1
- 186 -
j _ J}}