ML20154A402
| ML20154A402 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 09/28/1987 |
| From: | Swope D SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER |
| To: | |
| Shared Package | |
| ML17201J425 | List: |
| References | |
| ANF-87-111, NUDOCS 8809120205 | |
| Download: ML20154A402 (49) | |
Text
- - - - -
Mackd 2 l
ANF-87-111 a53 x g>
\-}f ADVANCEDNUCLEARFUELSCORPORATION LOC A-ECCS AN ALYSIS FOR DRESDEN UNITS DURING SINGLE LOOP OPERATION WITH ANF FUEL SEPTEMBER 1987 pga'5888R8888liy P
{
. ... .,,e....., ,.. _
Q KWU l
l ADVANCED NUCLEARFUELS CORPORATION ANF-87-Ill ;
Issue Date: 9/28/87 l
)
LOCA-ECCS ANALYSIS FOR ORESDEN UNITS DURING SINGLE LOOP OPERATION WITH ANF FUE.L
)
)
Prepared By: lN b 3 "A _
) D. R. Swope BWR Safety' Analysis Licensing and Safety Engineering Fuel Engineering and Technical Services
)
...,, - ,. ...,~... -
- QMwu
/
CUSTOMER DISCLAIMER trORTANT NOTICE REGARDING CONTOfTS ANO JSE OF THIS ,
DOCURAENT PLEASE READ CAREPULLY Advanced Nucteer Fuele Corporation's warrances and representatens con.
comng the suogoct matter of tNe document are those set form in the Agreement between Advanced Nucteer Fuels Corporation and the Custorner pursuant to wNon mis document is teoued. Acconsr#y, except as omennee escreesty pro. L vided in such Agrooment. nenhor Advanced Nucieer Fuede Corporaten nor any person acong on as behelf makes any war.anty or representaten, expressed or irredied, with respect to .he accuracy, completenses, or usefulness of the otor-mason contamed in tNe document, or that the use of any informacon, apparatus, metod or procoes N in tNe document will not infringe prwetofy owned righte; or assumes any Estulities weh respect to the use of any informaton, ap-paratus, method of proosee disclosed in tNe document.
The intormenon contained herem le for the soie use of Cuesomer.
In order to avoid lmeermont of rights of Advanced Nuclear Fueis Corporaton in patents or Irwentions wNch may be included in the information contaened in tNe documert, the recesent, by its acceptance of tNo document, agrees not to put$en or make put#c use (in the patent use of tt's term) of such informabon until [
eo authortrod in writing by Advanced Nucteer Fuele Corporenon of until after sut 1 (s) monme sonovnng termoacon or expiranon of me aforoew Agreement and any extensen thereof, uniees othervnse expressly proveed n me Agreement. No rights or licer'see in or to any potente are impi6ed by the furrueneng of tNs docu-k r
s
(
{
s l
l XN.NF F04765 (1i87) i
X l . 's ANF-87-111 TABLE OF CONTENTS Section . Eag.t 1.0 INTR 000CTION........................................'.............. 'l 2.0 SUP#iARY........................................................... 2 3.0 JET PUMP BWR ECCS EVALUATION M00EL................................ 3 3.1 LOCA During Single Loop Operation................................. 3 3.2 EXEM/BWR Application To Dresden Units............................. :3
, 4.0 ANALYSIS RESULTS............'...................................... 7 I
5.0 REFERENCES
........................................................ 9 6
I l
i
/
}
r
- ii - ANF-87-Ill LIST OF TABLES I
Table Pagg
-3.1 Dresden Reactor System Data........................................ 10
)
3.2 Comparison Of MF MAPLHGP's On Equivalent Planar Power Basis...... 11 4.1 SLO LOCA Limiting Break Event Times............................... 12
, 4.2 MAPLHGR Results Under SLO Conditions - 9x9 Fue1................... 13 I
l l I
l LIST OF FIGURES f
l l i Fiaure Pagg l
l 3.1 Dresden 2/3 Power-Flow Map SLO Conditions......................... 14 i
3.2 System Bl owdown Nodal i zation For BWR/3. . . . . . . . . . . . . . . . . . . . . . . . . . . . 15
! 4.1 Blowdown System Pressure.......................................... 16 4.2 Blowdown Total Break F10w......................................... 17 4.3 Blowdown Average Core Inlet F1ow.................................. 28 4.4 Blowdown Average Core Outlet F10w................................. 19 f 4.5 Blowdown Hot Channel Inlet F10w................................... 20 4.6 Bl owdown Hot Channel Midpl ane F10w. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21 4.7 Blowdown Hot Channel Outlet F10w.................................. 22 l
4.8 Blowdown intact Loop Jet Pump Suction F1ow........................ 23 4.9 Blowdown Intact Loop Jet Pump Exit F1ow........................... 24 i
4.10 Blowdown Broken Loop Jet Pump Drive F10w.......................... 25
( 4.11 Blowdown Broken loop Jet Pump Suction Flow........................ 26 4.12 Blowdown Broken Loop Jet Pump Exit F1ow........................... 27 f
4.13 Glowdown Upper Downcomer Mixture Leve1............................ 28
o
- 111 - ANF-87-111 LIST OF FIGURES j I
(Continued)
P Fiaure Eggt 4.14 Blowdown Middle Downcomer Mixture Leve1........................... 29 4.15 Blowdown Lower Downcomer Mixture Level............................ 30 4.16 Bl owdown Lower Downcomer Li quid Mas s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 31 4.17 Blowdown Upper Plenum Liquid Mass................................. 32 4.18 Blowdown Upper Downcomer Liquid Mass.............................. 33 1
4.19 Blowdown Lower Plenum Liquid Mass................................. 34 4.20 Re fi l l/ Re fl ood Sy s t em P re s s u re . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 35 4.21 Refill /Reflood Lower Plenum Mixture level . . . . . . . . . . . . . . . . . . . . . . . . . 36 1 4.22 Refill /Reflood Relative Core Midplane Entrainment. . . . . . . . . . . . . . . . . 37 4.23 Blowdown Hot Channel Center Volume Coolant Temperature............ 38 4.24 Blowdown Hot Channel Heat Transfer Coefficient.................... 39 4.25 Bl owdown Hot Channel Center Volume Quali ty. . . . . . . . . . . . . . . . . . . . . . . . 40 s
(
4.26 Typical Hot Assembly Heatup Results For 9x9 Fuel.................. 41 I
J
l l
l l
- iv - ANF-87-111 ACKNOWLEDGEMENT The assistance of Chuck Hendrix of Intermountain Technologies, Inc. (ITI) in preparing this analysis is acknowledged. i I
d f
f i
h i
i
1 ANF-87-111
1.0 INTRODUCTION
The results of a LOCA-ECCS analysis for the Dresden 2 and 3 nuclear power plants during single loop operation (SLO) are reported in this document.
These calculations were performed with the generically approved Exxon Nuclear Company EXEM/BWR Evaluation Model (Ref.1, 2) in accordance with Appendix K of 10 CFR 50 (Ref. 3), and the results comply with the U.S. NRC 10 CFR 50.46 criteria.
The Initial operating condition selected for this analysis was 81.3%
power /58.0% core flow. The analysis was performed using the Dresden Unit 3 conditions; however, the Dresden 2 and 3 Units are sufficiently similar so that the results of this analysis are applicable to both Units.
This analysis establishes the multiplier that is to be applied to the MAPLHGR's of the ANF fuel during single loop operation. The analysis was L performed with 9x9 fuel to determine this multiplier and justification is I
provided for its applicability to both ANF 8x8 and 9x9 fuel.
I l
f i
i
2 ANF-87-111 2.0
SUMMARY
The results of the ECCS analysis presented herein support the use of a 0.91 SLO multiplier on the two-loop MAPLHGR's for ANF fuels when the Dresden Units are operating in single loop operation.
All calculations were performed with the NRC approved EXEM/BWR ECCS Evaluation i Model, according to Appendix K of 10 CFR 50. Single loop operation of the Dresden Units with a multiplier of 0.91 on the two-loop ANF fuel MAPLHGR's assures that the emergency core cooling systems for the Dresden Units will meet the U.S. NRC acceptance criteria for loss-of-coolant accident breaks up to and including the double ended severance of a reactor coolant pipe. That is:
- 1. The calculated peak fuel element clad temperature does not exceed the 2200 F limit.
) 2. The calt:ulated total oxidation of the cladding nowhere exceeds 17f.
times the total cladding thickness before oxidation.
- 3. Yhe calculated maximum hydrogen generation does not exceed 17. of the zircaloy associated with the active fuel cladding in the reactor.
- 4. The LOCA cladding temperature transient is calculated to be terminated at a time when the core is still amenable to cooling.
- 5. The system long term cooling capabilities provided for the initial core and subsequent reloads remain applicable to ANF fuel, i
3 ANF-87-lll 3.0 JET PUMP BWR ECCS EVALUATION MODEL 3.1 LOCA Durina Sinale Looo Ooeration t Response to a loss of-coolant accident (LOCA) is described in the previous f analysis for two-loop operation (Ref. 4). This report addresses the instance of a LOCA during single loop operation (SLO).
During SLO the recirculation pump in the inactive loop is not operating and is l isolated from the remainder of the system by a valve. Thus, there is no flow
! through the idle, intact loop. A break might occur in either loop. However, a break in the inactive loop would behave essentially like a break during two-(
) loop operation except that substantial break flow would come from only one side of the break (because of the closed valve in the loop). System performance would then be like that resulting from a somewhat smaller break f
l during two-loop operation, This scenario is already covered by the previous l LOCA break spectrum analysis (5). Further consideration in this report will be
) given only to the case where a break occurs in the active loop. This case differs from the two loop case in one important respect: there is no
! coastdown flow in the intact loop.
A previous SLO analysis (Ref. 6) assumed that the consequence of a lack of i coastdown flow (which continues to supply liquid from the downcomer to the lower plenum, although at a decreasing rate, during two-loop operation) would be an almost immediate flow stagnation in the core and a very early CHF (0.1
, sec); this resulted in poor heat transfer very early in the transient and I
required that a MAPLHGR reduction factor of 0.84 be imposed for SLO conditions on the MAPLHGR for GE 8x8 fuel.
3.2 EXEM/BWR Aeolication To Dresden Units The EXEM/BWR ECCS Evaluation Model codes (l) were used for this SLO LOCA ECCS calculation. The codes which comprise the Evaluation Model consist of 4
4 ANF-87-111 R00EX2(7), RELAX (8), FLEX (9), and HUXY/BULGEX(10,11). The latest versions of these codes were used for this analysis. The only significant geometric modeling difference necessary was to simulate SLO in the RELAX model of the intact loop. The isolation valve in the intact loop is closed.
The approved ANF generic break spectrum analysis (5) for the BWR/3 reactors of which the Dresden Units are typical, identified the limiting break as the double ended guillotine break of the recirculation pump suction pipe with a discharge coefficient of 1.0 (1.0 DEG/PS). This limiting break (including l worst single failure) was used in this analysis.
l If LOCA occurs during single loop operation, a rapid drop in core flow will occur during the early phase because the intact loop pump is not operating.
The core flow transient during the early phase (0 - 5 seconds) of a LOCA during single loop is the principal event which will distinguish such an I accident from a LOCA occurring during normal two-loop operation. As the break size increases, the magnitude of the initial drop in core flow also would increase, and the critical heat flux (CHF) will occur earlier in time due to the decreased core flow. This trend of a larger drop in core flow with increasing break size has been confirmed by ANF in so.uitivity analyses on similar plants. Thus, the worst case LOCA for single loop operation would be expected to be with a break at least as large in area as the limiting break for two-loop operation.
Since the limiting break for normal (two loop) operation is the break of the largest possible area, this break will also be the limiting one for single loop operation. The NSSS vendor also determined that this same break is limiting for two and single loop operation (6),
l The 81.3% power /58% core flow (81.3/58) operating point was selected as the initial operating condition for this analysis. This condition lies on the APRM single pump rod block line on the current operating power flow map for j the Dresden Units. This value was obtained by using the maximum core flow J
l 5 ANF 87-111 under SLO conditions of 58% and then selecting the appropriate power fr a the i power-flow map. This condition was determined in Reference 6 to be a conservative upper bound for single loop operation. Figure 3.1 shows the
- power-flow map and the selected single loop operating point. The plant conditions used for the analysis are presented in Table 3.1. This data applies to both Dresden Unit 2 and Unit 3 because of the similarity between the two plants.
The syst.m behavior during a LOCA is determined primarily by the LOCA break parameters: break location, break size, and break configuration, together with the system components and geometry. Variations in core parameters produce only secondary effects on the system behavior. Thus, by using bounding core neutronic parameters, the LOCA ECCS results established by this analysis will apply for future cycles unless significant changes are made in the plant operating conditions, plant hardware, or core design such that the analysis no longer bounds the plant conditions.
The blowdown calculations made for this analysis differ from those for the previous two loop analysis (4) in two important ways. An additional valve is included upstream of the pump in the intact loop and initial conditions are altered to correspond to the maximum power / flow conditions for SLO. The nodalization is shown in Figure 3.2. Consistent with plant procedures for
! SLO, this is closed during the entire calculation preventing any flow through the loop.
The average core blowdown calculations are followed by hot channel calculations. The hot channel geometry is identical with that used in the two-loop analysis (Ref. 4). A bounding radial peaking factor of 1.76 was used to set the assembly power for the hot channel analysis.
The nodalization and geometry used in the reflood calculation are also identical to those of the two loop analysis (4). In the FLEX code the intact loop is not modeled in detail because intact loop flows are insignificant by
i 5 ANF-87-Ill j the time of rated spray; thus no changes were required in the FLEX nodalization or geometry. Th'e initial conditions for the reflood calculation are entirely determined by the blowdown calculation.
The HUXY/BULGEX heatup calculation of the hot plane was done as in the previous two-loop analyses (4): fuel stored energy, thermal gap conductivity and dimensions from R00EX2 as a function of power and exposure; time of rated spray, decay power, heat transfer coefficients and coolant conditions from ;
RELAX; and time of hot node-reflood from FLEX. Aopendix K spray heat transfer coefficients are used for the spray cooling period. Peak clad temperature (PCT) and the cladding oxidation percentage are determined for ANF 9x9 fuel.
Table 3.2 shows the ANF 8x8 and 9x9 MAPLHGR's for the Dresden Units on the equivalent basis of bundle planar power (MAPLHGR times number of heated rods).
As shown in this table, the 9x9 MAPLHGR's at lower exposures are significantly higher (on an equivalent bundle planar power basis) than 8x8 MAPLHGR's; at 5 ,
j GWd/MTV the equivalent 9x9 MAPLHGR is about 13% higher than the equivalent 8x8 MAPLHGR limit.
In preliminary SLO analyses it was determined that the high planar power of the 9x9 MAPLHGR at 5 GWd/MTU was sufficient to cause an early CHF; thus a reduction in the 9x9 MAPLHGR was indicated for SLO conditions to delay CHF.
Preliminary analyses show that a reduction in the peak 9x9 MAPLHGR value by I kW/ft (9%) to 10.75 kW/ft was sufficient to significantly delay CHF. Thus, SLO analyses were performed with 10.7i kW/ft as the peak MAPLHGR.
I
(
j
I
) 7 ANF-87-111 f
4.0 ANALYSIS RESULTS Analyses were performed for the assembly exposure (0-20 GWd/MTM) for which the two-loop MAPLHGR's had the highest PCT's (see Table 3.2). In all cases the MAPLHGR's justified in the single loop analysis were within 9% of the two-loop MAPLHGR's and the PCT's for the most limiting exposures (0-10 GWd/MTU) were not only less than acceptance criteria of 2200*F, but less than the PCT's from the two-loop analyses. Thus, a .91 multiplier on the two-loop 9x9 MAPLHGR curve assures that the 10 CFR 50.46 criteria are met under SLO conditions.
Calculated event time results are given in Table 4.1. System blowdown results are presented in figures 4.1 through 4.19. System refill and reflood results are given in Figures 4.20 through 4.22. These system conditions are used as boundary conditions for a series of exposure dependent maximum power assembly heatup calculations. Results from a RELAX /H0T CHANNEL calculation are given in Figures 4.23 through 4.25 for 9x9 fuel at MAPLHGR values of 10.75 kW/ft.
Resulting clad temperctures as calculated by HUXY/BULGEX are shown in Figure 4.26.
An examination of these plots reveals the following information:
- 1. The sudden loss of drive fluid in the jet pumps allowed a sudden drop in lower plenum pressure of sufficient magnitude '^ allow flow through the inactive jet pumps to "reverse" from 1:*- initial
- negative flow to a positive flow in the earlier part of the blowdown.
- 2. The lack of a pump coasting down in the intact loop allowed flow I through the suction and exit junctions of the operating (broken loop) jet pumps to remain in the positive direction (the drive, of course, reversed to supply fluid to the break) during the earlier part of the blowdown.
4
8 ANF-87-111
- 3. There is an immediate plunge in core flow accompanied by a reduction in the heat transfer coefficient.
- 4. The plunge in core flow is not sufficient to cause CHF to )
immediately occur at the high powered plane for the MAPLHGR's analyzed. The flow in the high power planes continue in the upward I direction as shown in Figure 4.6. CHF is delayed until about 9 seconds. This is because, while the hot channel inlet flow actually -
reverses, the lower part of the channel continues to supply a two phase liquid-vapor mixture to the high powered hot regions of the i
channel.
The peak MAPLHGR analyzed for the 9x9 fuel under SLO cenditions (10.75 kW/ft) f is about 5% higher than the two-loop ANF 8x8 MAPLHGR on an equivalent planar power basis; thus these analyses demonstrate that early CHF would not be )
expected to occur in the ANF 8x8 fuel; thus application of the same SLO multiplier (.91) to the two loop ANF fuel MAPLHGR will conservatively protect the ANF 8x8 fuel from exceeding the 10 CFR 50.46 criteria during SLO conditions. Use of this multiplier (9% reduction) and the lower equivalent power of the 8x8 MAPLHGR (5%) result in an equivalent ANF 8x8 MAPLHGR for SLO '
conditions 14% lower than the peak bundle planar power analyzed in this I
reoort.
- This application of a .91 multiplier during SLO conditions to all ANF fuel <
MAPLHGR's in the Technical Specifications will protect ANF fuel in the Dresden Units from exceeding 10 CFR 50.46 criteria.
l t
9 ANF-87-111
5.0 REFERENCES
- 1. "Exxon Nuclear Methodology for Boiling Water Reactors, Volume 2, EXEM: ECCS Evaluation Model Summary Descripticn," XN-NF-80-19fEl, Volume 2, Revision 1, Exxon Nuclear Company, June 1981.
- 2. "Exxon Nuclear Company ECCS Cladding Swelling and Rupture Model," XN-NF-82-07(A), Revision 1, Exxon Nuclear Company, November 1982.
- 3. "Acceptance Criteria for Emergency Core Cooling Systems for Light Water Cooled Nuclear Power Reactors " 10 CFR 50.46 and 10 CFR 50 Appendix K, Federal Register, Volume 39, Number 3, January 4, 1974.
- 4. "Dresden Unit 3 LOCA-ECCS Analysis MAPLHGR Results for 9x9 Fuel," XN NF-85-63fP), Exxon Nuclear Company, September 1981.
- 5. "Generic Jet Pump BWR 3 LOCA-ECCS Analysis Using the ENC EXEM Evaluation Model," M NF-81-71(P)(A) and Supplement 1(P)(A), Exxon Nuclear Company,
, September 1982. -
- 6. "Dresden Nuclear Power Stations Units 2 and 3 and Quad Cities Nuclear Power Station Units 1 and 2, Single Loop Operation," NEDO-24807, General i Electric, November 1980.
- 7. "R00EX2: Fuel Rod Thermal-Mechanical Response Evaluation Model," XN NF-1 81-58fA), Revision 2, Exxon Nuclear Company, February 1983.
- 8. "RELAX: A RELAP4-Based Computer Code for Calculating Blowdown Phenomena," XN NF 80-19fP), Volume 2A, Revision 1, Exxon Nuclear Company, June 1981.
- 9. "FLEX: A Computer Code for the Refill and Reflood Period of a LOCA," XN-NF 80 19fP), Volume 28, Revision 1, Exxon Nuclear Company, June 1981.
- 10. "HUXY: A Generalized Multirod Heatup Code with 10 CFR 50 Appendix X Heatup Option - User's Manual," XN CC 33f A), Revision 1, Exxon Nuclear Company, November 1, 1975.
j 11. "BULGEX: A Computer Code to Determine the Deformation and the Onset of !
Bulging of Zircaloy Fuel Rod Cladding," XN 74-21, Revision 2, and XN NF-22, Revision 2, Exxon Nuclear Company, December 31, 1974.
i i
t 10 ANF-87-111 TABLE 3.1 DRESDEN REACTOR SYSTEM DATA
- Primary Heat Output, MW 2095.54 Total Reactor System Volume, ft**3 20160.0 l Total Reactor Flow Rate, Ib/hr 56.84 x 10**6 Active Core Flow Rate, Ib/hr 51.36 x 10**6 l Nominal Reactor System Pressure 995.46 l (upper plenum) psia l Core Inlet Enthalpy Btu /lb 506.87 l
, Recirculation Loop Flow Rate, Ib/hr 15.83 x 10**6 l Steam Flow Rate, lb/hr 7.92 x 10**6 )
Feedwater Flow Rate,'lb/hr 7.91 x 10**6 Rated Recirculation Pump Head, ft 570.00 Rated Recirculation Pump Speed, rpm 1,670.00 Homent of Inertia, lbm ft**2/ rad 10,950.00 Recirculation Suction Pipe I.D., in. 25.59 Recirculation Discharge Pipe I.D., in. 25.59 9x9fuelAssemblyIodDiameter,in 0.424 )
9x9 Fuel Assembly Rod Pitch, in 0.572 9x9 Active Core Height, in 145.24 t
1
- 81.3% of rated power /58% of rated core flow.
l
{
~
n.
r e
11 ANF-87-111 6
t..
V TABLE 3.2 CONPARISON OF ANF MAPLHGR'S ON EQU1 VALENT PLANAR POWER BASIS l-i
/ l
! 8undle Averago PCT MAPLHGR Equivalent Planar !
) Exposure ('F) (kW/ft) Power (kW/ft) l
_ fGWd/MTU) M M M M M M ;
O 1879 2006 13.0 11.4 819 900 5 1942 2,045 13.0 11.75 819 928 l 10 2123 1893 13.0 11.4 819 900 15 2159 1805 12.85 10.55 810 833 20 2074 1710 12.6 9.7 794 766 25 2011 1623 11.95 8.85 753 649 j 30 1895 1529 11.2 8.00 706 632 35 1908 1421 10.45 1.15 658 565 !
f 40 -- 1309 -- 6.30 -- 498 ,
i !
. t l I i i i I j :
} !
r
[
[
i t
, l t
9 4
l i !
3 j
J i
i,
)
I
12 ANF-87-111 TABLE 4.1 SLO LOCA LIMITING BREAK EVENT TIMES
[ygni Time (sec)
Start 0.00 Initiate Break 0.05 Feedwater Flow Stops 0.55 Steam Flow Stops 5.05 Low-Low Hixture Level 5.16 Jet Pumps Uncover 8.38 Recirculation Pipe Uncovers 12.05 Lower Plenum Flashes 14.16 HPCI Flow Starts 15.16 LPCS Starts 57.06 Rated Spray Calculated 60.70 Depressurization Ends 114.05 Start of Reflood 152.22 Time of Hot Node Reflood 163.05 Peak Clad Temperature Reached 163.05 l
l l
t__ _
l 13 ANF-87-111 TABLE 4.2 MAPLHGR RESULTS UNDER SLO CONDITIONS ,
9X9 FUEL Sinale Loon Conditions
}
Assembly Average Local Burnup MAPLHGR MWR PCT (GWd/MTU) (kW/ft) _IfiL L'El 0 10.75 1.1 1898 5 10.75 1.0 1887 f 10 10.75 0.9 1874 15 10.55 0.8 1851 20 9.70 0.6 1750 I
t
14 ANF-87-111 120 11 0 -
100 - Single Pump APPN Line 90- SLO Analysis Point (81,3% Power /58% Flow) j 80-70- 100% Rod Line E l l le m- l so - l
,! Minimum Pump Speed
~
Natural e Circulation l l
Jo- l l
Y e0-l l
l 10 - ,
o'
\
0- , , , , , r- , , ,
10 20 00 40 s0 60 70 00 90 100 11 0 CORE FLOW (7.) J Figure 3.1 Dresden 2/3 Power-Flow Map SLO Conditions
15 ANF-87-111 ACS Act 37 m o 34 o 37 lt 1r it sier om t
l' u
~~~> = n, n, ue.
I 8 35 ,,
MPCI X -
, s, i s.
16, b _gg m L. v. - f ,,,
"~ ~
I I .
n, J O @
13 3 4 35i'~
g swee ,
- "* 4 O n 3
,n -
= t#' -
f' f
~
l
} 22
.u ci
~~ waa > - : t:t
- @ 3d 23 b
'* 6 $ a g )# I e ]
J JD.~T
..,,,o ,, "j TaL "
ved;T "8-O i,gg, e .
O v.w ,2 g
G 15 O
14
_L e -
.. .,, vu / C ~~ c.
i figure 3.2 System 810wdown Nodalization For BWR/3
16 ANF-87-111 l l
p r
s i i : i $
, i 4
?
y e
a h a
E l m
a E u
U #
,I cml .
n
. s 4 ,
E
" 5 .
! C !
t 4 f
g ;
i l
1 r i i i i eest eest oce see set see 1 i PdY (VISd) '3HnSS3Wd MON 31d W3ddo j i
I T
l
- ~
i, _
l -
17 ANF-0/-111 r.
g b
o 5
a 2 g 3
\ m .E 3 -
a f
?.
g W
p -
=
~ ~
S t w
c v s.
- - - 8, a .-
w 4 $ - -
e a 4 i i
, .... , 4 MP (33S/97) 'M0ld MV3WS 1V101 i
l r
i
-,, n_. . -- - -.n-.---,, - - - - . , - , . , .- - - --, - - - , , - , , , _ - - - - - - - - - - - - - , . - , . ,
e 18 ANF-87-lli i i i i i 3 g
=
o 1
O b
S - ' -
s y d S z o M L g S U U" W
w b
g <
Y M %
O
& D 3
CD 0 M *
- g &
o.
N LD W M O
O T'
- ~
M f n a 3
c 8
m G
. N- .
C3 i I i t -_
ocoor ooos ocoat oaos ooce o ocor*
IMP (03S/81) 'M013 131NI 3800
h 1' 19 ANF-87-111 i i . . . 3 g
8 C
Ia - < -
g je a
l g $
' U h
- e
! - - ,- 4 W
' C f
e.
g
~
S G C
W - -
g i _ e i i N MI MI M M $
PMr (335/97) 'M073 137100 3WO3
e 20 ANF-87-111
. . . i i 3 g
3 C
3 a 3
1
, - Te a
a 5 '
W U w 6 z '
x / 8 d S
- - a
- U w w
H O h p
5 O
a $
s O V O
~
Y "
$ = ,
N 3 e 5 '
O -
0 m
~ 2 sa oa si os e o @
IMP (03S/HGl) M0ld 131NI DH e
s>
21 ANF-87-111
. . . . . 3 l
l R !
8 :
C o
" ~
3 b e i 2 g "e d - 5
= e 6 5
) s -
em e a i 6 z - ,5 CD 3 m - " O 2 -
=
E.
O @
- o. - -
- 2 ,
Z m u b c y -
) -
a i t i i os si as e t o t?
PMP (33S/MG7) 831N33 3600 M0ld DH
e 22 ANF-87-lli l
1 i
i . . i i S R
5 C \
u 3 3 a
e E
' i S 6 z <
a"
- g~
u ) >
w g . -
a E a ; -
g 4 t
9 . -
a
- e
=
i O :
l E W E .
. i i I :'
08 95 33 8 ' '
eMr (33S/M91 MO id 131100 3WO3 3H :
1 l
e 1
l I
. . u. . _ _ _ _ . _ _ - - _ - , _ _ _ . _ _ _ . -
4
[
l
. . . . . 3 8
1 n C 8
a .-
O O
a - t -
t 5 a s CD E Z 3 (4 0-
)
a t W o C
O d
. . . u 9 U LL)
Z 9
>=4 d
b h
2 !
s 0 10 C
Q b
J 2 ,
E 5 m .
b w - -
e a e 6 Q
coos coes coot coor o coor- ooer*
92Mr (33S/07) 'M0ld NOIlonS dr 7I 1
i e
24 ANF-87-111 l
l
}
. i . . i 3 i
m ka =
- < ~
g
.I.
g L
- ~
3 4 U "
I
_u -
a t ,
i W T l > p -
i
~
h
~
i 3
l 3 -
= !
F e l
,. - w l M I h j h
- 5 -
. c :
1 B #
C , .
f eees sees eeet eees e seos- eeed l-t.EMr (33S/97) ' Mold lIX3 dP 1I I l
[
i f
t I
i
25 ANF-87-111 1
f
, i i i i 3 5
n c N
a - -
[
) m I
- J
, 4 5 '
5 m
- - E 4 .g 9
C
@ a 3 -
= s m J
- o m I
. . . en g
c
, i i -
ooes ooo, ooos e oose- oooe- oco#
FEMP (33S/97) 'M07d 3AIWO dr 19
26 ANF-87-111 i
\ t i i i i i 8 8
R C 8
Ia . ~
g 3 m
I
'. se L
s .g U
I E -
s
=!- 4 a
l -
?
a l 1
g E a -
m ~.
E
- W 2
I"' c t g a _ t t
$$$$$ $$$$I $$$II M N h stMr (33s/97) 'M01.4 NOI130S dr 19
)
.i 27 ANF-87-111
' ' ' . .. 3 ,
R .5 i
"- I N I a
e a .
J s ,
~
') s.
k 3 M
{
3 '
u .
I
~ g
- ~
ba -5 u '
>.4 co H
i
= -
n e., b
- h. N g
M v E
. P .
- u. :
s m
e i i
, I HM 0480I 00005 0008 0 "$ l SEMr (ogs/g1) 'M07.4 lIX3 de le i
f
.. . .. . . .- _ . . . .-_ . -- - . = _ _ _ - - _ _ - .. = . . _ _ ... - _ --- - _ .
4 1 ,
i 4
4 1
l DRESDEN3 1.0DEG/PS8 SNGL LOOP 1
- in a 1
i i
l -
7 i
3 i*
k.
i 5 .
a.
w-w s ~
m 4 .x.
4 x, 1
- o O
1 e
! w i n. -
4 a.
3 1
?
3 i
l
' ~l 4
t i n i e i i n
- . = = . . . .
] TIME (SEC) R m
a i u 4 Figure 4.13 810wdown Upper Downconer Mixture Level 4 W
i a
'f 1
s
'-&w--- ,e-wtwr~--y-=e--%m,*ww--..,ymm-v.m-wew,.,-=a-e9,v, .-y-- - - --v -.m- - - ,, *-9 --v- *t~w, e- - ---, y. --e-w_ - -
. +__ww - _ _ .__.
l
(
/ 29 ANF-87-111 i
i i i i , 3 R }
ll ts - .
3 e
3-
, 1 1
G
_a f.
~
I I
[ - .
1 a
- O N ~ =
g m
E r =
g !
I i i I 3 as el e s , a 1 41M (id) '13A31 XIM 00 OIN
W ^
t l
r 30 ANF-87-111 i i i e i 3 i
3 .
o ,
Ik h -
3 . ~
E % .
E 8
i <
- i S
Y a i w .
I
>= i R
E - ,
& =
, q ;
w .
m g ,
E
~
~
S i
I i I e g
's os es as s , g l 97N (13) *13A37 XIM 00 W3M07 ,
i, t
l
f k
31 ANF-87-lli l
i . i i i 3 1 - -
g g E
g 3 3 sa 1 a
g u U
g 3 Y
C l E
= }-
a 8 .
9 a ,
2 l - - e W
t i i i t MI MI HM HM HM MM 1 SMM (97) 'SSYN 0100I7 W3MODNM00 W3M07 4
f 32 ANF-87-111 i
~
a h
J -
K- . }
b Y
j G
p
@ a To a
$ E r -
= ;
E 1 C
g
- t t I i MM M M MI MI M 1 PMM (91) 'SSVM OIn0Il MON 31d W3ddn
33 .iNF-87-111 1
~ ~
E N 2
% 3 5 - -
s 5 a a l
a y G 8 d
- b
- . a Iw &
m - 3o E a i
g m w
Q h
a ;
E ?
, w n O
0 -
1 l- a w
\
...... ....., ..... ..... ...., ..... 2 GHM (87) 'SSYH OIODIl 63H00NM00 83ddn
34 ANF-87-111 L
n i
r
> i i i . 3 l i
s s1 i 8
a g 3
l l
r 3 _
._, A ;
U a
8 ,
t E
H L
L
~ ~ ~
$ go N
(D L
, - i e :
E l N - -
f i g
1 1
?
l 1 1 I I i ,
NI NI MI M M M MM (91) 'SSYM 0I00I7 MAN 31d W3M01
[
\ ,
I i
l l I
t P
+- 3 --- - . . . - , - . - , . - - , _ - _ _ , . - . - - - - - - _ _ - - - - - , -
- v,, e , ,- _-
Ays.-__- m~._ea 44J. ma24.-4-a--u %e m%4h--A- eu A .e***h4&% h 4
1 1
k l
l j REF JUNCT PRESSURE, PBAR 362 ,
. e, ** * *
- aan ** tamo name j i i i i t
I l
l l
E, ,
! W 2 m .
1 4 - -
m 4
- x
.h (A
'e- g f M
? - -
- = 33 m i
! @ w r-
.; 2
- g .>
j c - <
l [ RS - - ,
e 1
0 A
E.
I
, (
! 3 e i E E 1 ~
i l .
4 i
i i i i i 2
l .
III-18-JNY $E
)
.h I ,
.i a > \
h e - -
== '
en to w
4 4
i M m
5 Um - _
x4 e,
f f y I 2 g W
.4 8# see Time from Start Of Rer) Secs.)
figure 4 21 Refill /Reflood t w pi g g
=
W
. i i i i i i
~
w r
~
1 1 z
I -
1 I
H E _
y* ~ ~
w- g w
7 Z
4
- ~ ~
' l O.
" w I ~
w m - -
d J
w K
f I f f f E E g
che se see ise 12e 13e see see see Time From Start Of Reflood (Secs.)
}
Figure 4.22 Refill /Reflood Relative Core Midplane Entrainment 7
^
C
k i
l i ,
l 1
i I i
i i
o 9
i HC CENTER VOLUME FLUID TEMPERATURE (F) AT5 2
, ye m m m m m m
- i i i i i 2
. 3 m
L s . .
i l
e a s . - r
$ [
4 e
9 u - -
l C E l *.
i
, n -
h
, ~
9 c c r-
. < s - , .
- E =.g I _
w :
f
-A U - =
j g . . . ,
l l
III-l8-JNV 8C
)
. t
- --_...__________.mi_-__-.-_____
\
t 2
(BTU /HR FT 0F)
CR4
, pCCENTERHEATTRASFERC0EgFICIENT
. y . . .....
I
- l. _ - 3 s
c N ,
- W
, I . .
e v . _
g e
~
n E 9 Aa . .
n F
% s . .
3 A
q s . .
S g * - .
n g a a a a a mia a a a namin a a a m a n n ii a a a a n a ni, a a..
1II-48-JNV 6C 1
<_-1-_------ .
}
40 ANF-87-111
. i i i i 3 b
R &
3 3
b
- - O E v J -
2 kC M w m M
- ~
U y x a o,
H n S k- 1 8 =
o * " ~
,.g M 9 4 uJ g I C
m 1 4.
,. . .. o w
a w i i i a es es n'a eo r's s's o '6 GXY A11'lV00 3HS10A B31N33 OH 1
l l
0 gm$JC .
R E 0 T 8 62S ,2 21I NNM IIA PPC l
5 e
, 4 u 2 F 9
x O 9 r
0 o 1 F 2 s t
l
=
u s
e o 5 7
R
, p e 1 )
C t u
E a a
S
( H e
y e 0 E 4 1 l
b
, r 1 i m T e s
s A
t 5 o
, 0 H 1 l a
7 4 0 5 s2 4 5 c s1 2 33 3 4 4 4 i p
5 3 9 4 8 1 3 4 y 8 1 2 2 3 3 4 4 4
-- 1 2 T
5 2 8 3 7 0
- 7 1 2 23 3 4 4 4 , 0 4 1 7 2 6 7 8 s " 7 6 1 2 2 3 3 33 3 6 1 2 3 4 5 2 3
5 1 0 6 2 23 3 3 3 3 2
4 1 1
9 1
8 5 67 8 s0 2 2 2 2 23 3 0 1 2 3 4 3 1 1 1 2 2 2 2 2
[g _
, 5 4
e r
g u
0 3 23 4 5 6 7 3 i 2 1 1 1 1 1 1 1 1 F 1 2 3 4 5 67 8 s 0 0 0 0 d 0 0 0 0 0 5 0 5 0 5 2 2 1 1 CE UO&
1 9
l l
l l
i t
I 1
i f,
I i
i f
i l
1
?
t l
l i
l i
I i
Y ANF 87-111 l
Issue Date: 9/28/87 LOCA ECCS ANALYS15 FOR DRE5 DEN UNITS DURING $1NGLE LOOP OPERATION WITH ANF FUEL Distribution l
D. A. Adkisson 1 D. J. Braun ,
R. E. Collingham T. H. Keheley r T. L. Krysinski J. L. Maryott t J. N. Morgan !
D. F. Richey l G. L. Ritter ,
D. R. Swope l C. J. Volmer !
J. A. White :
H. E. Williamson !
Ceco /J. M. Ross (60)
DocumentControl(5) ,
t i
t f
i t
f i
e f
r r
-k l
f b
1 t
i l
l I
o I
1 I
i V
h I
I I
(
t I
+
l l