NUREG/IA-0192

International 

Agreement Report 

Assessment of 

RELAP5/MOD3.2.2 Gamma 

With the LOFT L9-3 Experiment 

Simulating an Anticipated 

Transient Without Scram 

Prepared by 

J.K. Suh, Y.S. Bang, H.J.Kim 

Korea Institute of Nuclear Safety 

19 Kusung-Dong, Yusong-Gu 

Taejeon, KOREA, 305-338 

Office of Nuclear Regulatory Research 

U.S. Nuclear Regulatory Commission 

Washington, DC 20555-0001 

January 2001 

Prepared as part of 

The Agreement on Research Participation and Technical Exchange under the International Code Application and Maintenance Program (CAMP) 

Published by 

U.S. Nuclear Regulatory Commission
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I
NUREG/IA-0192

International 

SAgreement Report 

Assessment of 

RELAP5/MOD3.2.2 Gamma 

With the LOFT L9-3 Experiment 

Simulating an Anticipated 

Transient Without Scram 

Prepared by 

J.K. Suh, Y.S. Bang, H.J.Kim 

Korea Institute of Nuclear Safety 

19 Kusung-Dong, Yusong-Gu 

Taejeon, KOREA, 305-338 

Office of Nuclear Regulatory Research 

U.S. Nuclear Regulatory Commission 

Washington, DC 20555-0001 

January 2001 

Prepared as part of 

The Agreement on Research Participation and Technical Exchange 

under the International Code Application and Maintenance Program (CAMP) 

Published by 

U.S. Nuclear Regulatory Commission
Assessment of RELAP5/MOD3.2.2gamma with the LOFT L9-3 Experiment 

Simulating an Anticipated Transient Without Scram 

Abstract 

The present work is to assess the capability of RELAP5/MOD3.2.2gamma to 

predict the system response following an Anticipated Transient Without Scram 

(ATWS) event. The experiment L9-3 which is a unique nuclear experiment 

simulating an ATWS event induced by loss of feedwater accident in Loss-of-Fluid

Test (LOFT) is calculated. The experimental condition and sequence are reviewed 

and a calculation modeling is developed with the important test specific features. The 

result of RELAP5 calculation is compared with the experimental data, and the 

predictability of the system response of the primary coolant system (PCS), the reactor 

power, and the steam generator (SG) secondary system is discussed. The base case 

showed a good agreement for the RCS pressure, temperature and reactor power with 

the experimental data. Therefore, it is shown that the RCS thermal-hydraulic response, 

the reactor power response, and the secondary system response following the LOFT 

L9-3 experiment can be reasonably predicted by the RELAP5 code under the current 

modeling scheme, and thus, that the code can be reasonably applied to the analysis of 

the system thermal-hydraulic response during the ATWS event in real plant. In 

addition, four parameters such as subcooled discharge coefficient of PORV, loss 

coefficient of spray valve, steam generator nodalization and moderator density 

coefficient (MDC) were selected and the effect of those parameters on the total 

discharged energy through the pressurizer safety relief valves is evaluated.

iii
Contents 

Abstract Abstract iii ........................................................... 111 

Contents .......................................................... v 

List of T ables ............................................................. Vi 

List of Figures ............................................................ Vii 

Executive Sum m ary ........................................................ ix 

1. Introduction ....-................................................ 1 

2. Facility and Test Description .............................................. 3 

2.1 Facility Description .................................................... 3 

2.2 Test D escription ....................................................... 3 

3. Code and M odeling ...................................................... 5 

3.1 Code Description ...................................................... 5 

3.2 Input Modeling ................................................... 5 

4. Review of Sensitivity Parameters ........................................... 7 

5. Result and Discussions .................................................... 9 

5.1 B ase Case ............................................................ 9 

5.2 Param etric Study ..................................................... 11 

5.3 Run statistics ........................................................ 13 

6. Summary and Conclusions ........................................... 14 

R eferences ............................................................... 15 

Tables ......................................-......................... 16 

F igures .................................................................. 19 

Appendix A: Input Deck for Steady State Calculation of Base Case .............. A-1 

Appendix B: Input Deck for Transient Calculation of Base Case ................ B-1

V
List of Tables

Table 1 Initial Condition for Experiment L9-3 ........................................... 16 

Table 2 Sequence of Events for Experiment L9-3 .......................................... 17 

Table 3 Summary of Parametric Study and Discharged Energy ...................... 18

vi
List of Figures

Fig. I LOFT System Configuration ............................................................... 19 

Fig. 2 RELAP5 Nodalization Diagram for Calculation of LOFT L9-3 Test ...... 20 

Fig. 3 Moderator Density Coefficient ............................................................. 21 

Fig. 4 Energy Flows through Relief Valves ................................................... 21 

Fig. 5 Comparison of RCS Pressure ................................................................ 22 

Fig. 6 Comparison of Coolant Temperatures at Hot and Cold Legs .............. 22 

Fig. 7 Comparison of Discharged Flow through PORV and SRV ................. 23 

Fig. 8 Comparison of Reactor Power ............................................................. 23 

Fig. 9 Comparison of SG Secondary Side Pressure ...................................... 24 

Fig. 10 Comparison of SG Liquid Level ........................................................... 24 

Fig. 11 Parametric Effect on RCS Pressure ...................................................... 25 

Fig. 12 Parametric Effect on Coolant Temperatures at Hot and Cold Legs ......... 25 

Fig. 13 Parametric Effect on Reactor Power .......................... 26 

Fig. 14 The Required CPU Time in the Base Case Calculation ....................... 27 

Fig. 15 The Time Step Size of Base Case Calculation .................................... 27 

Fig. 16 The Mass Error of Base Case Calculation ........................................... 28

vii
Executive Summary

Anticipated operating transients during which the reactor does not scram as 

designed, i.e., ATWS (Anticipated Transient Without Scram), can be occurred by 

multiple failures. The rapid excursion of the RCS pressure and temperature by loss of 

feedwater and no scram could result in damaging of the reactor core. To resolve this 

concern, the system thermal-hydraulic behavior following an ATWS event should be 

understood, and the capability of the plant safety features to mitigate the event should 

be assured. For this aspect, a thermal-hydraulic analysis code to be applied to the 

system response following an ATWS event should be verified for relevant experiment 

simulating the ATWS event. 

The Experiment L9-3 conducted in the Loss-of-Fluid-Test (LOFT) facility was a 

unique one simulating an ATWS event in pressurized water reactor (PWR). 

The present study aims to evaluate the capability of RELAP5/MOD3.2.2gamma 

code to predict the system response using the L9-3 experiment data. Also, this study 

is purposed to suggest major modeling scheme for future application to PWR plant 

analysis, as well as to understand the parametric effect on the thermal-hydraulic 

response following the ATWS. For those purposes, an effort to improve the predicted 

system response during the experiment was attempted starting from the previous 

result as a base line. 

The standard RELAP5/MOD3.2.2gama code was used in the present calculation. 

The LOFT system was modeled by 134 hydrodynamic volumes, 143 junctions, and 

148 heat structures, in which the reactor vessel, the primary coolant system (PCS), 

the steam generator (SG), the SG secondary system, and the pressurizer were 

included. 

The base case calculation was performed and its result was compared with the 

corresponded experimental data. The code predictability was discussed on the 

important parameters including the PCS pressure, the coolant temperatures at hot/cold 

legs, the discharged mass flow rate through safety relief valve, the reactor power, the 

water level and pressure of the SG secondary side. The calculation result showed a 

good agreement with the experimental data although a little difference in the heat

ix
transfer to the SG secondary side. 

Sensitivity calculations were performed varying several parameters such as 

subcooled discharge coefficient of the pilot operated relief valve (PORV), loss 

coefficient of spray valve, steam generator nodalization and moderator density 

coefficient (MDC), which were selected from the input model improvement to seek a 

better agreement with the experimental data. And the effect of those parameters on 

the system response was evaluated in terms of the total discharged energy through 

relief valves, which was believed to provide the insight on the effect in real plant 

ATWS mitigation. As a result, it was found that the subcooled discharge coefficient of 

PORV and the loss coefficient of spray valve had a significant effect on the behavior 

of the RCS pressure, and that the fine nodalization of SG U-tubes increased the 

primary to secondary heat transfer rate. And, the account of the additional negative 

reactivity inserted into the core as a result of pre-experiment power gave a good 

agreement for the coolant temperature between the experiment and the calculation. 

And the calculated total discharged energy through the relief valves larger than that of 

the experiment in the range of 25.7 - 72.8 %. Based on the parametric study, it is 

important to use an accurate MDC data in the analysis of an ATWS in the real plant, 

and the loss coefficient of spray valve should be carefully determined.

X
1. Introduction

Anticipated Transients Without Scram (ATWS) is defined as any of anticipated 

operating transients during which the reactor does not scram as designed [1]. The 

significance of ATWS for reactor safety is that some ATWS events could result in 

damaging of the reactor core and releasing of a large amount of radioactive fission 

products. The alternative system initiating auxiliary feedwater and turbine trip, 

diverse from the existing system was required by the current ATWS rule [I1]. 

The existing nuclear power plants constructed before YGN Units 3&4 in Korea 

were not known to have such an ATWS mitigating features, although there have been 

some attempts to study the ATWS mitigating features preliminarily. Based on the 

fact that the core damage frequency (CDF) from the ATWS events was 3.8x10-7

/RY 

for the YGN Units 3&4 [2] and a higher CDF can be expected for the plants older 

than the YGN Units 3&4 due to the aging effects, the ATWS can be a significant 

safety concern for the existing plants. 

In designing the ATWS mitigating features and evaluating the plant-specific 

ATWS coping capability, it is required to determine the thermal-hydraulic response 

of both primary and secondary systems following the ATWS event. The role of 

ATWS analysis is to confirm the ATWS system response is within the maximum 

pressure of the reactor coolant system (RCS) less than the ASME Service Class C 

(3200 psia), which has been considered as a bound during the deliberation leading to 

the final ATWS rule [3]. Also the reasonability of the success criterion such as the 

favorable moderator temperature coefficient (MTC) in the probabilistic safety 

assessment should be evaluated through the plant specific thermal-hydraulic analysis. 

Thermal-hydraulic response during the ATWS event was generally known to be 

related to the dryout phenomena in steam generator (SG) secondary side, the single

and two-phase coolant discharge phenomena through the relief valves on the 

pressurizer in RCS, and the reactivity feedback process to power through the MTC 

[4]. Therefore, thermal-hydraulic analysis computer code should have a capability to 

predict those phenomena and should be verified by the applicable experimental data

I
simulating those phenomena. The experiment L9-3 [5] which was a unique nuclear 

experiment simulating an ATWS event induced by loss of feedwater accident, 

conducted at the Loss-of-Fluid-Test (LOFT) facility has been a appropriate one to 

benchmark computer codes. The analysis of the LOFT L9-3 experiment was 

conducted by several researchers using the RELAP5 code [5]. It was reported that 

the code could reasonably predict the RCS thermal-hydraulic response, the reactor 

power response and the secondary system response following the experiment. In 

those analyses, the safety relief valve (SRV) opened more than two times by the 

over-prediction of the RCS pressure whereas it opened only one time in the 

experiment. And, the further sensitivity studies were needed on the effect of steam 

generator modeling, the SRV discharge modeling, and the MDC feedback on the 

system response. 

The present work evaluates the capability of the RELAP5/MOD3.2.2gamma code 

[6] to predict the system response following the ATWS event. For this purpose, the 

experiment L9-3 was assessed. The experimental condition and sequence were 

reviewed and a calculation modeling was developed with the important test-specific 

features. The RELAP5 calculation result was compared with the experimental data 

and the predictability of the system response of the RCS, the reactor power, and the 

SG secondary system was analyzed. 

Also, this study aims to suggest major modeling scheme for future application to 

PWR plant analysis, as well as to understand the parametric effect on the thermal

hydraulic response following the ATWS. For those purposes, an effort to improve the 

predicted system response during the experiment was attempted. And, sensitivity 

calculations were performed varying several parameters such as subcooled discharge 

coefficient of PORV, loss coefficient of spray valve, steam generator nodalization 

and MDC, which were selected from the input model improvement to seek a better 

agreement with experimental data. The effect of those parameters on the system 

response was evaluated in terms of the total discharged energy through relief valves, 

which was believed to provide the insight into the analysis on real plant ATWS 

mitigation.
2. Facility and Test Description

2.1 Facility Description 

The LOFT facility is a 50 MWt pressurized water reactor (PWR) with 1/60 power

to-volume scale with the Westinghouse four loop PWR. It has various 

instrumentation to measure and to provide data on the thermal-hydraulic and nuclear 

condition throughout the system. The LOFT facility consists of five major system : 

reactor system, primary coolant system, blowdown suppression system, emergency 

core cooling system and secondary coolant system. The length of the core and the 

reactor vessel is 1.68 and 7 m, respectively. The overall configuration is shown in 

Fig. 1. 

2.2 Test Description 

Experiment L9-3 is one of the anticipated transient with multiple failures test 

performed at the Loss-of-Fluid-Test (LOFT) facility and simulated a loss-of

feedwater anticipated transient without scram (ATWS). The objectives of 

Experiment L9-3 were to provide experimental data for benchmarking vendors' 

ATWS computer codes as required by the USNRC proposed ATWS rule (SECY-80

409) [7], to evaluate alternative methods of achieving long-term shutdown (without 

the insertion of control rods) following an ATWS event to address concerns defined 

in the proposed rule, and to determine the transient reactor power by using available 

neutron flux instrumentation and measured core thermal-hydraulic parameters to 

address the applicability of the point kinetics model used in predicting transient 

reactor power. The experimental data was also used to determine the steam generator 

secondary dryout behavior and its effect on the primary system response 

characteristics and to determine the two-phase and subcooled flow characteristics of 

pressurizer pilot operated relief valve (PORV) and safety relief valve (SRV) at high 

pressure (> 17 MPa). 

For those purposes, a two-position actuator relief valve was installed on the 

pressurizer to simulate a scaled PORV and a scaled SRV in addition to the plant
PORV and SRV. The relief capacity of valve scaled to the minimum PORV capacity 

of a generic Westinghouse PWR. [8] 

Prior to the experiment, the primary system pressure was 14.98 ± 0.06 MPa, the 

mass flow rate over the loop was 467.6 ± 2.7 kg/s, and the reactor power was 48.7 ± 

1.2 MWt. Table 1 summarizes an initial condition on the experiment. Measurement 

uncertainties of the important parameters were also presented in the table. 

The experiment was initiated by turning off the main feedwater pump. The steam 

generator steam control valve was closed manually at 67.3 s. The experimental 

PORV opened at 67.3 ± 0.2 s, and the experimental SRV opened at 96.8 ± 0.2 s at 

their set-point pressures. The maximum pressure occurred at 17.4 MPa, and the SRV 

could prevent the further pressure increase as designed. The plant recovery was 

initiated at about 600 s by starting one high pressure injection system (HPSI), 

starting the secondary coolant system auxiliary feedwater, and opening the PORV. 

The control rods remained withdrawn. Major sequence of events for experiment L9

3 are summarized in Table 2.

4
3. Code and Modeling

3.1 Code Description 

The standard RELAP5/MOD3.2.2gamma code, was used without any 

modification in the present analysis. The code has some improved capabilities when 

compared to the previous versions including computational time step control, flow 

anormalies, mass error reduction, etc. The detailed description of the improvements 

can be found in the reference [6]. 

3.2 Input Modeling 

The LOFT facility was modeled by 134 hydrodynamic volumes, 143 junctions, 

and 148 heat structures. Figure 2 shows a RELAP5 nodalization diagram for the 

calculation of test L9-3. The RELAP5 nodalization was based on the previous study 

on the assessment for the LOFT L9-1 experiment [9]. Changes from the previous one 

are the SG U-tube model with 12 volumes and the SG separator flow paths. The used 

models and options were based on the user guideline of the code [6]. A steady state 

input deck and a transient input deck are presented in Appendix A and B. 

The primary coolant system (PCS) composed of an intact loop and a broken loop, 

the former included a hot leg, a pump suction tee, two primary coolant punps (PCP) 

and a cold leg. The intact loop was modeled by 25 hydrodynamic volumes. All 

piping metal structures exposed to environmental atmosphere were simulated by the 

heat structure to consider the heat loss. 

The reactor vessel was modeled by a downcomer annulus, a lower plenum, an 

active core, a core-bypass flow path, an upper plenum, an upper head and a filler gap 

flow path. The filler gap flow path was especially modeled for simulating an upward 

flow during a natural circulation phase. The active core, the downcomer and the 

filler gap were modeled by 3, 6, 7 volumes stacked vertically, respectively. Totally 

26 volumes and 50 heat structures were used. The rod bundle interface friction 

model option was selected for the active core volumes. The fuel rods were modeled

5
by 3 heat structures representing the central fuel assembly and 3 heat structures 

representing the peripheral fuel assemblies of LOFT core. The reactor kinetics model 

was used for simulating the moderator density and doppler temperature feedback and 

a scram curve was provided. The ANS-79 model was used for a decay heat 

simulation. 

The pressurizer system was modeled by a surge line, a pressurizer vessel, a spray 

line from cold leg, a spray valve and a experiment PORV. Two volumes for the surge 

line, nine volumes for the vessel and one volume for the spray line were used, 

respectively. The spray valve and the PORV were simulated by two trip valves. The 

associated trip logics were prepared according to the experimental specification. To 

consider the environmental heat loss from the pressurizer vessel wall, the vessel wall 

was modeled by nine heat structures. 

The steam generator consisted of a SG inlet plenum, U-tubes, a outlet plenum, a 

feedwater inlet annulus, a SG secondary side downcomer, a boiler section, a 

separator inlet annulus, a separator, a main steam control valve (MSCV) and a 

MSCV downstream piping. All of the SG metal wall and U-tubes were described by 

the proper heat structures. The rod bundle interfacial friction option was used for the 

volumes contacted with the U-tubes heat structures. The separator section in SG was 

modeled by a branch component and a separator component. The separator inlet 

junction is connected to the bottom of the volume 520, as shown in Fig. 2. 

The initial condition for the transient calculation was obtained by RELAP5 steady 

state run. The calculated parameter was compared with the experimental data in 

Table 1. As shown in the table, all the important parameters were well-agreed to 

those of the test within a range of measurement uncertainty. For the transient 

calculation, all the major sequence were modeled including the SG feedwater pump 

trip, the pressurizer spray actuation, the pressurizer PORV open/close, the SRV 

open/close, the SG main steam control valve (MSCV) manual-closure, and the 

MSCV bypass valve open/close. The primary coolant pumps were modeled to run 

continuously throughout the transient.

6
4. Review of Sensitivity Parameters

As mentioned above, the previous calculation showed a reasonable prediction on 

L9-3 transient progression. However, an over-prediction of the system pressure and 

temperature was identified as a weakness in the RELAP5 assessment. The weakness 

dues mainly to the input model simulating the test not to the thermal-hydraulic 

models in the code. By this reason, an attempt to improve the input model was 

performed through the extensive sensitivity study on the several parameters. As a 

result, a base case was selected which gave a good agreement for the RCS pressure, 

temperature and reactor power with the experimental data within a range of 

measurement uncertainty. 

In the base case calculation, the contribution of Xenon buildup to core reactivity 

was considered. The amount of negative reactivity inserted into the core as a result 

of pre-experiment power operations was calculated as 22% of the total (Xenon plus 

moderator) negative reactivity. This is the maximum Xenon-reduced reactivity which 

was reported in reference [11]. Figure 3 shows the moderator density coefficient of 

base case and the case with no additional source of negative reactivity (Case D). In 

the base case, the subcooled discharge coefficient of PORV was set to 1.0, the loss 

coefficient of spray valve was set to 0.0, and the steam generator tubes were divided 

into 12 volumes. 

In sensitivity calculations, four cases were performed varying the parameters such 

that the subcooled discharge coefficient of PORV was set to 1.1 in Case A, the loss 

coefficient of spray valve was set to 15.432 in Case B, the steam generator tubes 

were divided into 34 instead of 12 in Case C, and the previous MDC curve in Fig. 3 

used in Case D. 

To assess the comparative effect of those parameters, the total discharged energy 

through relief valves was calculated. It is the important factor in mitigating the RCS 

pressure and was calculated by integrating the instantaneous energy flow curve 

presented in Fig. 4 with time as the Equation (1). It was calculated from the time of 

the PORV open to 200 seconds. Because the most important thermal-hydraulic

7
phenomenon, i.e., SG secondary side dryout, single- and two-phase coolant 

discharge and moderator temperature feedback to reactor power were observed 

before 200 seconds. The differences between calculation and experiment determined 

by the Equation (2) in each case were compared to identify the most dominant 

parameter to concern in the analysis of the ATWS at real plant. 

E = J rhhdt (1) 

6E = Ecl -EF-p (2) 

Figure 4 shows the energy flows through the PORV and SRV in cases of 

experiment and base calculation. The total discharged energy of other four cases are 

calculated as the same method.

8
5. Result and Discussions

With the initial and boundary conditions described in the Chapter 3, a transient 

RELAP5 run was executed up to 600 seconds. Because the most important thermal

hydraulic phenomena were observed before 200 seconds, the calculation result is 

discussed in short-term response (up to 200 seconds). During 200 to 600 seconds, the 

system was observed to stabilized after coolant discharge. 

5.1 Base Case 

RCS Response 

Figure 5 shows a comparison of RCS pressurizer pressure between the experiment 

and the RELAP5 calculation. At the beginning of the transient initiation, the main 

feedwater was lost and the auxiliary feedwater was unavailable throughout transient, 

which led to the RCS pressure increase up to the pressurizer spray setpoint at 30 

seconds and 55 seconds in the experiment. After that, the RCS pressure continued to 

increase due to the depletion of heat removal capability of SG secondary side. In the 

experiment, the pressurizer PORV was opened at 74 seconds and the SRV at 96.8 

seconds. The maximum RCS pressure was observed as the same as the SRV opening 

setpoint pressure, i.e., 17.24 MPa. After discharging the RCS coolant, the RCS was 

in the saturated condition at high temperature, which lowered the reactor power 

through the MTC feedback. The RCS pressure could be maintained within the range 

of the pressurizer PORV open/close setpoint (16-16.2 MPa) under this condition. 

The result of RELAP5 calculation shows a good agreement with the experimental 

data until the PORV open. Each actuation of the pressurizer spray valve and the 

PORV was well predicted even with the deviation in timing of the SRV open, and the 

maximum RCS pressure was reasonably calculated. However, after the PORV open, 

the calculation showed an over-prediction of the pressure. Also, the PORV 

open/close cycling response was delayed. The reason for such a SRV response is the 

excessive coolant expansion due to the coolant temperature over-prediction.

9
Figure 6 shows a comparison of coolant temperatures at hot and cold legs between 

the calculation and the experiment. The coolant temperature increased slowly, and 

then rapidly due to the complete loss of the SG secondary side heat removal 

capability. Both the temperatures moved eventually to the same level as the reactor 

power decreased to zero. The calculated temperatures are well agreed with the 

experimental data up to 100 seconds and then a little over-predicted. However, the 

difference between the calculation and the experiment is within the measurement 

uncertainty (±4.3K). It is indicated that the negative feedback effect of the MDC 

with respect to the coolant temperature was appropriately modeled. 

Figure 7 shows a comparison of the discharged coolant mass flow rate through the 

PORV and SRV between the calculation and the experiment. In the experiment, the 

discharged flow rate was 1 kg/sec for the PORV and 4.6 kg/sec for the combined 

SRV. During the PORV cycling mode, 2.6 kg/sec of coolant was discharged per cycle. 

The calculation showed a large mass discharge (4.9 kg/sec) for the combined SRV 

and a small discharge (1.9 kg/sec) for the PORV cycling. The total discharged energy 

through the relief valves was 312.73 MJ and this is larger by 25.7 % than that of the 

experiment. 

Reactor Power Response 

Figure 8 shows a comparison of the reactor power between the experiment and the 

RELAP5 calculation. In the experiment, the reactor power was slowly decreased due 

to the moderator density feedback caused by the coolant temperature increase. After 

50 seconds, the reactor power was significantly decreased to 2 MW level by the 

coolant temperature increase by 40 K. The power calculated by the RELAP5 was 

generally agreed with the experimental data. It is obvious that the MDC data used for 

the point kinetics model in the present RELAP5 calculation was appropriate one. 

Secondary System Response 

Figure 9 shows a comparison of SG secondary side pressure between the 

experiment and the RELAP5 calculation. The SG pressure increased due to the

10
continuous heat transfer from the RCS, as the main feedwater was lost in the test. 

The increasing rate of SG pressure was gradually reduced and eventually reversed as 

the reactor power decreased. The MSCV was closed at 67 seconds which led SG 

pressure to re-increase. After that, the SG pressure was maintained at about 6.4 MPa, 

by the steam bypass valve open/close. The calculated SG pressure was generally 

close to the experimental data although it was a little over-predicted. The reason for 

the over-prediction is believed to the high steaming rate in the SG which caused by 

the present SG modeling scheme e.g., the recirculation ratio. 

Figure 10 shows a comparison of the SG secondary side liquid level between the 

experiment and the RELAP5 calculation. It is shown that the RELAP5 calculation 

was well agreed with the experimental behavior. The complete dryout of the SG was 

shown at 100 seconds in calculation, while the complete dryout was not found in the 

experiment. This deviation may due to the SG modeling scheme and/or RELAP5 

code model. 

5.2 Parametric Study 

The parametric study and the discharged energy through relief valves are 

summarized in Table 3. The effects of each parameter on the thermal-hydraulic 

response in ATWS event are followings. 

Subcooled Discharge Coefficient of PORV (Case A) 

In Case A, the subcooled discharge coefficient of PORV was set to 1.1. There 

were no outstanding effects in the RCS temperatures and the reactor power 

compared with the base case. However, the behavior of the RCS pressure is 

significantly influenced by the subcooled discharge coefficient. As the coefficient 

increased, the discharged flow also increased, which resulted in the mitigation of the 

RCS pressure increasing. Figure 11 shows that the PORV opened three times before 

opening the SRV in the calculation whereas it opened only one time in the

I1
experiment. And, it can be identified that the PORV open/close frequency decreased 

because the pressure drops sharply after the PORV open and reaches the closing set 

point fast. The total discharged energy through the relief valves was 318.14 MJ 

which is larger by 27.9 % than that of the experiment. 

Loss Coefficient of Spray Valve (Case B) 

Sensitivity calculation for the loss coefficient of spray valve was conducted by 

setting it to 15.432, which was used in the previous calculation [12]. The coefficient 

has a remarkable effect on the RCS pressure as shown in Fig. 11. The pressure 

increased more rapidly and reached the setpoint of PORV open earlier than the 

experiment. This is because the RCS pressure was not appropriately controlled by 

the small amount of spray limited by the junction loss coefficient. Also, the pressure 

shows a large increment after the PORV open, which resulted in the increase of the 

energy discharge through the PORV. The total discharged energy through the relief 

valves was 318.39 MJ and this is larger by 28.0 % than that of the experiment. And, 

the increase of the loss coefficient has negligible effects on the RCS temperatures 

and the reactor power compared with the base case. 

Steam Generator Node Number (Case C) 

Using the modeling scheme that the steam generator tubes were divided into 34 

volumes, the coolant temperature increased slowly at the nearest to the experimental 

curve as shown in Fig. 12. This means that the heat transfer rate increased from the 

primary to the secondary. By this reason, the time delay of the second spray open 

was happened as the pressure did not increase to the setpoint of the spray open. The 

pressure decreased sharply after the PORV open and the time of the SRV open was 

delayed by 17 seconds as shown in Fig. 11. The reactor power showed abrupt drop at 

60 seconds when the coolant temperature rise rapidly. The total discharged energy 

through the relief valves was 316.12 MJ and this is larger by 27.1 % than that of the 

experiment.

12
Moderator Density Coefficient (Case D)

Figure 11 shows that the pressure increased unreasonably when the MDC curve 

was chosen as Case D in Fig. 3. This is because the negative feedback effect of the 

MDC with respect to the coolant temperature was not appropriately modeled. In Fig. 

13, the reactor power was over-predicted though the coolant temperature was higher 

than the experimental data as shown in Fig. 12. The total discharged energy through 

the relief valves was 429.98 MJ and this is larger by 72.8 % than that of the 

experiment. Therefore, the most care should be taken in choosing the accurate input 

MDC data in the analysis of the ATWS. 

5.3 Run Statistics 

The main frame computer used in the present calculation was a IBM Personal 

Computer (Pentium II 500 MHz) with DOS operating system. In the base case 

calculation, the grind time is can be calculated as follows. 

Computer time, CPU = 157.08 - 1.31 = 155.77 (sec) 

Number of time step, DT = 4421 

Number of volume, C = 128 

Grind time = CPUx I 000/(CxDT) = 0.27527 CPU m sec/vol/step 

Figure 14 shows the required CPU time with respect to the transient time for the base 

case run. And the time step size is also plotted in Fig. 15. The maximum time step 

was set to 0.05 second up to 200 seconds. Using the RELAP5/MOD3.2.2gamma 

time code, the step size was always same to the Courant time limit. In the Fig. 16, 

the mass error of the base case calculation is represented. The maximum mass error 

was less than 1.0 kg, while the total system mass was 5079 kg until 200 seconds.

13
6. Summary and Conclusions

The present study aims to evaluate the capability of the RELAP5/MOD3 code to 

predict the thermal-hydraulic system response following the ATWS events. The 

experiment L9-3 which was a unique nuclear experiment simulating an ATWS event 

induced by loss of feedwater accident in the LOFT facility was calculated. In 

addition, a sensitivity calculation was performed on such parameters as the 

subcooled discharge coefficient of PORV, the loss coefficient of spray valve, the 

steam generator nodalization and the MDC. Main observations and conclusions are 

as follows: 

1) The RELAP5 code reasonably predicted the RCS thermal-hydraulic response, the 

reactor power response, and the secondary system response following the LOFT 

L9-3 experiment under the current modeling scheme. Therefore, the code can be 

reasonably applied to the analysis of thermal-hydraulic response following the 

ATWS in real plant. 

2) The subcooled discharge coefficient of PORV and the loss coefficient of spray 

valve had a significant effect on the behavior of the RCS pressure, and the fine 

nodalization f the SG U-tubes increased the primary to secondary heat transfer 

rate. And, the account of the additional negative reactivity inserted into the core 

as a result of pre-experiment power gave a good agreement for the coolant 

temperature between the experiment and the calculation. 

3) The total discharged energy through the relief valves was calculated, and the value 

was larger than that of the experiment in the range of 25.7 - 72.8 %. 

4) It is important to use an accurate MDC data in the analysis of an ATWS in the real 

plant, and the loss coefficient of spray valve should be carefully determined. This 

sensitivity study will provide useful information for the analysis of an ATWS in 

the real plant.

14
References

[1] USNRC, Code of Federal Register, 10 Part 50, Sec. 50.62, Requirements for 

reduction of risk from anticipated transients without scram (ATWS) events for 

light-water-cooled nuclear power plants, April 1989 

[2] KEPCO, Final Level I Probabilistic Safety Assessment for YGN Nuclear Units 3 

and 4, July 1993 

[3] USNRC, Final Safety Evaluation Report Related to the Certification of the 

System 80+ Design, NUREG- 1462, August 1994 

[4] Charles L. Nalezny, Summary of the Nuclear Regulatory Commission ' LOFT 

Program Research Findings, NUREG/CR-3005, April 1985 

[5] P. D. Bayless et. Al., Experiment Data Report for LOFT Anticipated Transient 

Without Scram Experiment L9-3, NUREG/CR-2717, May 1982 

[6] The Thermal Hydraulics Group, RELAP5/MOD3 Code Manual, Formerly 

NUREG/CR-5535, March 1998 

[7] USNRC, Proposed Rulemaking to Amend 10 CFR 50 Concerning Anticipated 

Transient Without Scram (ATWS) Event, SECY-80-409, Sept. 1980 

[8] W. Tauche, Loss-of-feedwater Induced Loss of Coolant Accident Analysis, 

WCAP-9744, May 1980 

[9] Young. S. Bang, et. al., Assessment of RELAP5/MOD3 With the LOFT L9-1/L3

3 Experiment Simulating an Anticipated Transient With Multiple Failures, 

NUREG/IA-0 114, Feb. 1994 

[10] D. Reeder, LOFTSystem and Test Description, NUREG/CR-0247, July 1978 

[11] J. P. Adams, Experiment Analysis and Summary Report for LOFT ATWS 

Experiment L9-3 and L9-4, NUREG/CR-3417 September 1983 

[12] A. Taylor, et al., Best Estimate Prediction for LOFT Nuclear Experiment L9

1/L3-3, EGG-LOFT-5413, April 1981

15
Table 1 Initial Condition for Experiment L9-3

16

Parameter Measured Calculated 

Base Case Case C 

Primary Coolant System 

Mass flow rate(kg/s) 467.6±2.7 467.6 467.6 

Hot leg pressure(MPa) 14.98±0.06 14.97 14.96 

Core AT(K) 19.4±2.2 19.35 19.36 

Intact loop average temperature (K) 566.7±1.5 567.4 567.0 

Cold leg temperature (K) 557.0-1.5 557.70 557.33 

Hot leg temperature (K) 576.4±1.6 577.05 576.69 

Reactor Vessel 

Power level (MWt) 48.7±1.2 48.7 48.7 

Maximum linear heat generation rate (kW/m) 51.6±3.9 51.6 51.6 

Pressurizer 

Liquid temperature(K) 615.2±0.3 611.24 611.0 

Pressure (MPa) 14.98±0.06 14.98 14.98 

Liquid level (m) 1.00o_0.03 0.9820 0.9865 

Steam Generator Secondary Side 

Liquid level (m) 3.15±0.09 3.148 3.155 

Liquid temperature(K) 544.4±0.7 544.0 544.08 

Pressure (MPa) 5.61±0.06 5.583 5.584 

Mass flow rate(kg/s) 25.7±1.1 25.85 25.85
Table 2 Sequence of Events for Experiment L9-3

Time (second) 

Event Calculated 

Experiment (Base Case) 

Main feedwater pump tripped off 0.0 0.0 

Pressurizer spray valve cycling initiated 29.5 ± 2.0 30.01 

Steam generator MSCV closed 67.3 ± 1.0 67.3 

Experiment PORV opened 73.8 ± 0.2 74.52 

Steam generator liquid level reached bottom of 94.5 ± 4.0 77.01 

indicating range (0.25 m above bottom) 

Experiment SRV opened 96.8 ± 0.2 105.02 

Experiment SRV closed 107 ± 1 119.0 

Experiment PORV closed 123 ±.1 149.5 

Experiment PORV cycling initiated 125.4 ± 0.2 153.03 

Experiment PORV cycling terminated 208 218.04 

End of ATWS phase / start of recovery 601.1 ± 0.2 -

End of calculation 600.0

17
Table 3 Summary of Parametric Study and Discharged Energy 

PORV Spray S/G MDC 

Discharge Loss Node # Curve Eca (MJ) 6E (MJ) 

Coef. Coef. 

Base Case 1.0 0.0 12 Base Case 312.73 63.97 

Case A 1.1 0.0 12 Base Case 318.14 69.38 

Case B 1.0 15.432 12 Base Case 318.39 69.63 

Case C 1.0 0.0 34 Base Case 316.12 67.36 

Case D 1.0 0.0 12 Case D 429.98 181.22

18
BL- I 

experimenlal

Quick opening 

valve (2) ,

Sleam

To blowdown 

Suppleaslon 

lank

PC,3

slatlon

Core

Lower plenum 

INEL.L9 1103 3.1500 

Fig. I LOFT System Configuration

19

fleaclor vessel
Steam Control Valve 

J550 J555

SRV

Intact Loop

Fig. 2 RELAP5 Nodalization Diagram for Calculation of LOFT L9-3 Test

20

J320 J330

Broken Loop
700 800 900 

Density(kgkn3) 

Fig. 3 Moderator Density Coefficient

50 100 150 

Time(sec) 

Fig. 4 Energy Flows through Relief Valves

21

6

4 

0 

(,D 

cr- -2 

-4

600 1000

9 

7 

5 

0 

.Li 

-1

0 200
18 ' I ,.. . 

17 

16 . 

V') 

15 

--- - Experiment " 

Base Case 

1411 1 

0 50 100 150 200 

Time(sec) 

Fig. 5 Comparison of RCS Pressure 

6 10 . .. .. . .. .. 

•- 590 

E Experiment(HL) 570 

Base Case(HL) 

--------. Experiment(CL) 

Base Case(CL) 

550 1 1 1 

0 50 100 150 200 

Time(sec) 

Fig. 6 Comparison of Coolant Temperatures at Hot and Cold Legs

22
50 100 150 

Time(s) 

Fig. 7 Comparison of Discharged Flow through PORV and SRV

50 100 150 

Time(sec) 

Fig. 8 Comparison of Reactor Power

23

6

bD 4 

(I) 

02 

LL

U', 

CU 

0

0

50 

40 

S30 

o 20 CL 

10 

0

200

0 200
50 100 150 

Time(s)

Fig. 9 Comparison of SG Secondary Side Pressure

50 100 

Time(s)

150

Fig. 10 Comparison of SG Liquid Level

24

7 

_6 

'5 

4

200

4 

3 

2 

1 (-J 

:3 

-_J

Experiment 

Base Case 

------------- --------- ---- --- 

-1

0 200

0

0
50 100 150 

Time(sec) 

Fig. 11 Parametric Effect on RCS Pressure

50 100 

Time(sec)

150

200

200

Fig. 12 Parametric Effect on Coolant Temperatures at Hot and Cold Legs

25

0

19 

18 

CL 

S17 

S16 

L

15 

14

610 

"•- 590 

E S570 

5

550

S------- Experiment(HL) 

Base Case (HL) 

S ....... • •,_• + Case C (HL) 

Sf . ...• - Case D (HL) 

•.--•--...... E xperiment(C L) 

_, *•.• • Base C ase (CL) 

,, • " - " " • Case C (CL) 

S7 Case D (CL) 

I 1 | R i I , I ,ý , I ,

0
50

40 Base Case 

-A--- Case C 

•:30•; 

•'3 .Case D 

6 20 

10 

0 50 100 150 200 

Time(sec) 

Fig. 13 Parametric Effect on Reactor Power

26
50 100 150 

Time (sec)

Fig. 14 The Required CPU Time in the Base Case Calculation

50 100 150 

Time (sec)

Fig. 15 The Time Step Size of Base Case Calculation

27

200

150 

M 100 

C/) 

0 

E 

50 

0

0 200

0.06 

"V 0.04 

0ý 

U) 

0 

E0.02 

0.00

0 200
1.0 . 

0.5 

0.0 

-0.5 

0 50 100 150 200 

Time (sec) 

Fig. 16 The Mass Error of Base Case Calculation

28
Appendix A. Input Deck for Steady State Calculation of Base Case
=loft L9-3 ATWS experiment assessment calculation deck 

*--------------1-----------1--1• 1• 1-. 

• initial conditions 

core power = 48.7 MW 

Spcs flow = 467.6 kgfs 

Pzr pressure = 14.98 MPa 

thot = 576.4 k 

tcold = 557.0 k 

SG U-tube 15 volumes with same discretizing in SG secondry 

* SG separator flow path changed 

•_ 11- -- 1 -11 -11- -11- - 11- -1

0000100 new stdy-st 

0000101 run 

0000102 si 

00001055. 10. 

0000110 nitrogen 

1--•1• -------- 1• ------1 - 1

time step control cards 

S end lime mindt maxdt optnmnrmjr rut 

0000201 400.0 1.e-4 0.1 2 5 1000 1000 - •••--1-------------------1----1I 

minor edit variables 

pressure 

0000308 cntrivar 51 *pe-pc-2 

0000309 cntrlvar 50 ' porv inlet 

0000314 cnitrlvar 53 * pt-p4-1Oa 

* temperatures 

0000322 tempt 100010000 *te-pc-2a,2b,2c 

0000323 tempt 185010000 * te-pc-1 

0000326 tempt 505010000 sg liq. temp. 

0000330 tempt 415030000 "pzr Ii~q. temp 

0000331 tempt 300010000 * broken loop hot leg 

0000332 tempt 335010000 * broken loop cold leg 

"mass flow rates 

0000360 mflowj 100010000 * ilhl nozzle 

0000363 mflowj 400010000 * pres. surge line flow 

0000364 mflowj 407000000 * pzr spray flow 

0000367 mflowj 550000000 " steam flow control valve 

0000369 mflowj 560000000 * main feed 

0000370 mflowj 546000000 * steam bypass 

water level 

0000371 cntrlvar 1 - s/g level 

0000372 cntrlvar 2 pzr level 

* power 

*0000376 cntrtvar 701 * moderator density "0000377 cntrlvar 702 doppler temp. 

0000378 cntrlvar 54 power 

0000379 rkreac 0 reactivity 

0000380 cntrlvar 220 steam discharge enthalpy 

0000381 cntrtvar 320 °eedwater input enthanpy 

0000382 cntrivar 330 pzr liquid volume 

0000383 cntrlvar 340 pzr vapor volume

* trips

* variable trips 

0000504time 0 It null 0 0.0 I 

0000508 time 0 ge null 0 0.0 I 

0000509tempfl00010000 ge null 0 597.0 1 

0000530 time 0 It null 0 0.0 I *exp. power curve turn on 

* logical trips 

0000609 504 or 504 I 

0000626 504 or 504 I * for porv open/close 

0000634 504 or 504 I * for srv open/dose 

* intact loop components 

* reactor vessel nozzle - intact loop hot leg 

1000000 rvnilhl branch 

1000001 2 0 

1000101 0.06414 1.4458 0.0 0.0 0.0 0.0 

1000102 4.0e-5 0.0 00000 

10002000 1.49719e+07 0.13440e+07 0.24606e+07 0.0 

1001101 250000000 1000000000.0634 0.00.0000100 

1002101 100010000 105000000 0.0 0.05 0.05 000100 

1001201 10.308 10.3080.0 

1002201 10.309 10.3090.0 

pressurizer connection tee reactor vessel side 

1050000 pzrtrvs branch 

1050001 1 0 

1050101 0.06414 1.0506 0.0 0.0 0.0 0.0 

1050102 4.Oe-5 0.0 00000 

10502000 1.49672e+07 0.13440e+07 0.24607e+07 0.0 

1051101 105010000 110000000 0.0 0.05 0.05 000000 

1051201 13.438 13.438 0.0 

• steam generator inlet piping 

1100000 sginlp branch 

1100001 1 0 

1100101 0.0 1.1061 0.064318 0.0 0.0 0.0 

1100102 4.0e-5 0.0 00000 

1100200 0 1.49304e+07 0.13440e+07 0.24615e+07.0 

1101101 110010000 115000000 0.0 0.1 0.1 000100 

1101201 13.439 13.439 0.0 

* steam generator plus piping 

1150000 sgppip pipe 

1150001 19 

1150101 0.0 3 

11501020.151 15 

11501030+0 18 

1150104 0.0634 19 

1150201 0.0 1 

115020200512 2 

11502030.0 15 

1150204 0.0512 16 

115020500 18

A-]
1150301 1.3889 1 

1150302 0.70769 2 

1150303 0.63 3 

1150304 0.3556667 6 

1150305 0.5335 8 

1150306 045 10 

1150307 0.5335 12 

1150308 0-3556667 15 

1150309 0.63 16 

1150310 0.543 17 

1150311 0.689 18 

1150312 0.55 19 

1150401 0-079697 1 

1150402 0-057961 2 

1150403 0-3227 3 

11504040.0 15 

1150405 0.335 16 

1150406 0.0437 17 

1150407 0.0462 18 

11504080.0 19 

1150501 0.0 19 

1150601 0.0 1 

1150602 90.0 9 

1150603 -90.0 19 

11507010.0 1 

1150702 0.246 2 

1150703 0.513 3 

1150704 0.3556667 6 

1150705 0.5335 8 

1150706 0.45 9 

1150707 -0.45 10 

1150708 -0.5335 12 

1150709 -0.3556667 15 

1150710 -0.513 16 

1150711 -0.498 17 

1150712 -0.689 18 

1150713 -0.356 19 

1150801 4.Oe-5 0.0 2 

1150802 4.0e-5 0.0102 3 

1150803 1. e-5 0.0102215 

1150804 4.0e-5 0.0102 16 

1150805 4.0e-5 0.0 19 

1150901 0-15 0.15 1 

1150902 0.05 0.05 2 

11509030.0 0.0 6 

1150904 0.05 0.05 8 

1150905 02 0.2 9 

1150906 0.1 0.1 10 

1150907 O0 0.0 15 

11509080.05 0.05 17 

1150909 0.1 0.1 18 

1151001 00000 19 

1151101 000100 3 

1151102 000000 13 

1151103 000100 18 

1151201 0 1.49472e+07 0.13440e+07 0.24611e+07 0.0 0.0 01 

11512020 1.49524e+07 0.13440e+07 0.24610e+07 0.0 0.0 02 

11512030 1.48727e+07 0.13440e+07 0.24627e+07 0.0 0.0 03 

11512040 1.48509e+07 0.13185e÷07 0.24631e+07 0.0 0.0 06 

11512050 1.48295e+07 0.12978e+07 0.24636e+07 0.0 0.0 08 

11512060 1.48142e+07 0.12801e+07 0.24639e+07 O0 0+0 09 

11512070 1.48072e+07 0.12650e+07 0.24641e+07 0+0 0.0 10 

11512080 1 48020e+07 0.12523e+07 0.24642e+07 0.0 0.0 12 

11512090 1.47964e+07 0.12410e+07 0.24643e+07 0.0 0.0 15 

11512100 1.47976e+07 012410e+07 024643e+07 0.0 0.0 16 

1151211 0 1 47251e+07 0.12410e+07 0 24658e+07 0.0 0.0 17 

1151212 0 1.47165e+07 0 12410e+07 0.24660e+07 0 0 0 0 18

11512130 1.47119e+07 0.12410e+07 0 24661e+07 0.0 0.0 19 

11513000 

1151301 10.447 10.4470.0 01 

1151302 8.1183 8.11830.0 02 

1151303 4.3289 4.3290 0.0 03 

1151304 4.2693 4.26930.0 06 

1151305 4.2239 4.22400.0 08 

1151306 4.1858 4.18580.0 09 

1151307 4.1546 4.15460.0 10 

1151308 4.1293 4.12930.0 12 

11513094.1070 4.10700.0 15 

1151310 7.7626 7.76260.0 16 

1151311 9.2494 9.24950.0 17 

1151312 9.7826 9.78260.0 18 

pump data 

"pump suction tee 

1200000 pmpsctt branch 

1200001 3 0 

1200101 0.0634 0.76 0.0 0.0 0.0 0.0 

1200102 4.0e-5 0.0 00000 

12002000 1,47085e+07 0.12410e+07 0.24662e+07 0.0 

1201101 115010000 120000000 0.0 0.1 0.1 000000 

1202101 120010000 125000000 0.0317 0.2 0.2 000100 

1203101 120010000 155000000 0.0317 0.2 0.2 000100 

1201201 9.7826 9.78270.0 

1202201 5.0746 5.0746 0.0 

1203201 5-0735 5.0735 0.0 

pump1 suction tee outlet 

1250000 pmplsctt branch 

1250001 2 0 

1250101 0.0 1.003 0.0613 0.0 90.0 0.521 

1250102 4.0e-5 0.0 00000 

12502000 1.46957e+07 0.12410e+07 0.24664e+07 0.0 

1251101 125010000 130000000 0.0 0.1 0.1 000100 

1252101 125000000 155000000 0.0 0.0 0.0 000100 

12512017.8657 7,8657 0.0 

1252201 -0.24790 -0.247900.0 

"pump 1 inlet 

1300000 pmpl nMet snglvol 

1300101 0.0 0.457 0.0189 0.0 90.0 0.457 

1300102 4.0e-5 0-0 00000 

13002000 1.46736e+07 0.12410e+07 0.24669e+07 0.0 

"primary coolant pump 1 

1350000 pcpumpl pump 

1350101 0-0366 0.0 0.099 0.0 90.0 0.319 

1350102 00000 

1350108 130010000 0.0 0.0 0.0 000100 

1350109 140000000 0.0 0.05 0.05 000100 

13502000 1.48967e+07 0.12412e+07 0.24622e+07 0.0 

13502010 8.8881 8.8882 00 

13502020 8.8868 8.8868 00 

13503010 0 0 -1 -1 519 0 

1350302 369.0 0.88469 3155000 96 000000 500.60000 1.431 

1350303613.6 0.0 207.0000 0.0040000 19.598000 0.0 

13503100.0 0.0 0+0 

single phase head curves 

* head curve no. 1 --. .. 1 -..... 1- ----1--- ---..1----..-.-1- .. - --..1-..-.

A- 2
13511001 1 

1351101 0.000000e+00 1.403600.+00 

1351102 1.906100e-01 1.363600e+00 

1351103 3.896300e-01 1.318600e+00 

1351104 5.939600e-01 1.232800e+00 

1351105 7.902000e-01 1.133600e+00 

1351106 1.000000e,00 1.000000e+00 

"-- -1--i-- -- 1--1- -1

* head curve no. 2 "*-----I- -1----1---- 11

13512001 2 

1351201 0.O00000e+00 -6.700000e-01 

1351202 2000000e-01 -5.0000006-01 

1351203 4.000000e-01 -2.500000e-01 

1351204 5.755400e-01 0.000000e+00 

1351205 7.443200e-01 2.583000e-01 

1351206 7.734800e-01 3.778000e-01 

1351207 8.631300e-01 6.326000e-01 

13512081.000000&+00 1.000000e+00 ",-- -1-- -1-- -1- -1-- -1-- -- 1-

* head curve no. 3 "*1-- - --------- 1

1351300 1 3 

1351301 -1.000000e+00 2.472200e+00 

1351302 -8.057400e-01 2.047400e+00 

1351303 -6.069000e-01 1.831000e+00 

1351304 -4.068300e-01 1.624000e+00 

1351305 -2.001710e-01 1.470500e+00 

1351306 0.000000e+00 1.403600e+00 

*-- ---- ----- -- 1-- -- ----- -- 1

head curve no. 4 "*---- -1 ---- -- 1- 1- ------ 1

1351400 1 4 

1351401 -1.000000e+00 2.472200e+00 

1351402 -8.229700e-01 1.996800e+00 

1351403 -6.333200e-01 1.589700e+00 

1351404 -4.553400e-01 1.327900e+00 

1351405 -2.710900e-01 1.194900e+00 

1351406 -1.771600e-01 1.060500e+00 

1351407 -9.073000e-02 1.015600e+00 

1351408 0.000000e+00 9.342790e-01 

*-- --- -- 1-- -- ----- ---- 1

* head curve no. 5 

*- -- -- 1-- -- 1----- ----- -- 1

13515001 5 

1351501 0.O00000e+00 2.500000e-01 

1351502 2.000000e-01 2.800000e-01 

1351503 4.000000e-01 3.400000e-01 

1351504 4.118000e-01 2.768000e-01 

1351505 5.976300e-01 4.584000e-01 

1351506 7.934670e-01 6.992000e-01 

1351507 1.000000e+00 1.000000e+00 

*-- --- -1-- -- 1-- -- 1-- ------ 1

head curve no. 6 

*-- --------- -- --1--1--1---1

13516001 6 

1351601 0.000000e+00 9.342790e-01 

1351602 9.109900e-02 9.229000e-01 

1351603 1.865090e-01 8.963000e-01 

1351604 2.717620e-01 8.750000e-01 

1351605 4.558720e-01 8.433000e-01 

1351606 5.744060e-01 8.355000e-01 

1351607 7.405760e-01 8.466000e-01 

1351608 7.666190e-01 8.469000e-01 

1351609 8.714710e-01 8.838000e-01 

1351610 1.000000e+00 1.000000e+00 

* - -- 1--i- -- 1-------1- -1- --- 1

"head curve no. 7 

1351700 1 7 

1351701 -1.000000e+00 -1.000000e+00 

1351702 -8-000000e-01 -6300000e-01

1351703 -6.000000e-01 -3.00OOOOe-01 

1351704 -4.000000e-01 -5.000000e-02 

1351705 -2.000000e-01 1.500000e-01 

1351706 0.000000e+00 2.500000e-01 

*----1- -1- -1l 1- 1-- lm--1-- --

head curve no. 8 

*-- ---- -- 1-- -11- -1

1351800 1 8 

1351801 -1.000000e+00 -1.0000Oe+00 

1351802 -8.000000e-01 -9.700000e-01 

1351803 -6.0000OOe-01 -9.500000e-01 

1351804 -4.000000e-01 -8.800000e-01 

1351805 -2.000000e-01 -8.000000e-01 

1351806 O.000006e+00 -6.700000e-01 

* single phase torque data 

torque curve no. 1 "*-- ---- ---- -- 1--- ---- -- 1-----1

13519002 1 

1351901 0.000000e+00 6.032000e-01 

1351902 1.930000e-01 6.325000e-01 

1351903 3.930000e-01 7.369000e-01 

1351904 5.955200e-01 8.331000e-01 

1351905 7.978200e-01 9.229000e-01 

1351906 1.000000e+00 1.000000e+00 "1--- 1-- -1-- -- 1- -1-- -1- - 1

"torque curve no. 2 ",-- -I1- -- 1--1 •1- -- 1 - -- 1-- -- 1 

13520002 2 

1352001 0.O00000e+D0 -6.700000e-01 

1352002 4.000000e-01 -2.500000e-01 

1352003 5.000000e-01 1.500000e-01 

1352004 7.372550e-01 5.265860e-01 

1352005 7.680490e-01 6.065940e-01 

1352006 8.672300e-01 7.436600e-01 

1352007 1.000000e+00 1.000000e+00 

*-- -- 1-- ----- ----- ---- -1

torque curve no. 3 "*---------------1---1------------1- 1 

1352100 2 3 

1352101 -1.000000e+00 1.984300e+00 

1352102 -8.009600e-01 1.394000e+00 

1352103 -6.063800e-01 1 097500e+00 

1352104 -4.068600e-01 8.220000e-01 

1352105 -1.992800e-01 6648000e-01 

1352106 0.000000e+00 6.032000e-01 "-- -1------ ----- -- ---- 1

* torque curve no. 4 

*-- ---- ---- ---- -- 1- -1- -1

1352200 2 4 

1352201 -1.00000e+00 1.984300e+00 

1352202 -8.223400e-01 1.830800e+00 

1352203 -6.337100e-01 1-682400e+00 

1352204 -4.585300e-01 1.557000e+00 

1352205 -2670230e-01 1.436200e+00 

1352206 -1.761070e-01 1.387900e+00 

1352207 -8.931000e-02 1.348100e+00 

1352208 0.000000e+00 1.233610e+00 

"torque curve no. 5 "-- -- I-- -- 1-- -1-- -1--- -1-- -1-

13523002 5 

1352301 O.00000e+00 -4 500000e-01 

1352302 4.000000e-01 -2.500000e-01 

1352303 5.000000e-01 0 000000e+00 

1352304 1.000OOOe+00 3.569000e-01 

"torque curve no. 6 

13524002 6 

1352401 0.000000e+00 1 233610e+00

A- 3
1352402 9.064300e-02 1.196500e+00 

1352403 1.885690e-01 1.109600e+00 

1352404 2-734700e-01 1.041600e+00 

1352405 4.586690e-01 8.958000e-01 

1352406 56744800e-01 7.807000e-01 

1352407 7.381600e-01 6.134000e-01 

1352408 7+685200e-01 5.849000e-01 

1352409 8-700570e-01 4.877000e-01 

1352410 1.000000e00 3.569000e-01 

*- -1--- -1- -1- -1- -1- -1-

* torque curve no. 7 

*- -1 .- -1-- -- 1------ ---

1352500 2 7 

1352501 -1.000000e400 -1.000000e+00 

1352502 -3.000000e-01 -9.000000e-01 

1352503 -1.000000e-01 -5.000000e-01 

1352504 0.000000e+00 -4.500000e-01 *- -1I- --- 1- -- 1- -1I- -- 1- ---

1

* torque curve no. 8 -- -1I- --- 1- -- 1-- -- 1-- -1-- -1-

1352600 2 8 

1352601 -1.000000e+00 -1.000000e+00 

1352602 -2,5000OOe-01 -9 O00000e-01 

1352603 -8.0000OOe-02 -8.0000OOe-01 

1352604 0.000000e+00 -6.700000e-01 

two 

- phase multiplier data from 19-1 test data 

head curve 

-1-- -1- -1--1----- -- ---- --

1

13530000 

1353001 0.000000e+00 0.000000e+00 

1353002 2.000000e-02 2.000000e-02 

1353003 6.0000OOe-02 5.000000e-02 

1353004 1.000000e-01 1.000000e-01 

1353005 2.000000e-0l 4.600000e-01 

1353006 2.400000e-01 8.000000e-01 

1353007 3.000000e-01 9.600000e-01 

1353008 4.000000e-01 9.800000e-01 

1353009 6.000000e-01 9.700000e-01 

1353010 8.0000OOe-01 9.000000e-01 

1353011 9.000000e-01 8.OOOOOe-01 

1353012 9.600000e-01 5.000000e-01 

1353013 1.000000e+00 0.000000e+00 

"- -I-- -1- -1---- ---- --

1

* torque curve 

*- -1--- -1-- -1-- -- 1-- -- 1- --

1

13531000 

1353101 0.000000e+00 0.000000e+00 

1353102 1.250000e-01 7.000000e-02 

1353103 1.650000e-01 1.250000e-01 

1353104 2.400000e-01 5.600000e-01 

1353105 8.0000O0e-01 5.600000e-01 

1353106 9 600000e-01 4.500000e-01 

1353107 1.000000e+00 0.000000e+00

pump 2-phase difference data 

* head curve no. 1 

13541001 1 

1354101 0.000000e+00 0.000000e+00 

13541021 O0000Oe-01 8 300000e-01 

1354103 2.0000O0e-01 1.090000e400 

1354104 5.000000e-01 1.020000e+00 

1354105 7.000000e-01 1010000e+00 

1354106 9.0000OOe-01 9.400000e-01 

1354107 1 O00000e+00 1.000000e+00 

" head curve no 2 -- ---- 1 ........ 1 - 1----.. 1 ----.... 1 --- --- 1 ---

13542001 

2

1354201 0.000000e+00 O.O00000e-+00 

1354202 1.0000OOe-01 -4.0000OOe-02 

1354203 2.000000e-01 0.000000e+00 

1354204 3.0000OOe-01 1.000000e-01 

1354205 4.000000e-01 2. 100000e-01 

1354206 8.000000e-01 6.700000e-01 

1354207 9.0000OOe-01 8.000000e-01 

1354208 1.000000e+00 1.000000e+00 *-- -1I- -- 1-- --- 1- -- 1-- -- 1-- -1-

head curve no. 3 - - - -1 1 1 

1 --- 1354300 1 3 

1354301 -1.000000e+00 -1.160000e+00 

1354302 -9 000000e-01 -1.240000e+00 

1354303 -8.000000e-01 -1.770000e+00 

1354304 -7.000000e-01 -2.360000e+00 

1354305 -6.O0000Oe-01 -2.790000e+00 

1354306 -5.000000e-01 -2.910000e+00 

1354307 -4.0000OOe-01 -2.670000e÷00 

1354308 -2.5000OOe-01 -1.690000e+00 

1354309 -1.0000OOe-01 -5.000000e-01 

1354310 0-000000e+00 0.000000e+00 

""- -"1- --- -1- -1- -- 1 

-

* head curve no. 4 

""- -1- -1- -1- -1- -1- -1

1354400 1 4 

1354401 -1-000000e+00 -1.160000e+00 

1354402 -9 000000e-01 -7.800000e-01 

1354403 -8.000000e-01 -5.000000e-01 

1354404 -7.0000O0e-01 -3.100000e-01 

1354405 -6.0000OOe-01 -1.700000e-01 

1354406 -5.00OOOOe-01 -8.000000e-02 

1354407 -3 500000e-01 0.O00000e+00 

1354408 -2.000000e-01 5.0000OOe-02 

1354409 -1.000000e-01 8.0000OOe-02 

1354410 0.000000e+00 1.100000e-01 "-- "-1-" -- I . 1- -1-1- 1

Shead curve no. 5 "---1- ----1-- --------- ----------1-

13545001 5 

1354501 0.000000e+00 0.000000e+00 

1354502 2.000000e-01 -3.400000e-01 

1354503 4.000000e-01 -6.5000OOe-01 

1354504 6.000000e-01 -9.300000e-01 

1354505 8.0000OOe-01 -1.190000e+00 

1354506 1.000000e+00 -1.470000e+00 

* head curve no. 6 

-- 1--1 -- ---- ---- 1-- -- ---

1

1354600 1 6 

1354601 0.000000e+00 1.100000e-01 

1354602 1.0000OOe-01 1-300000e-01 

1354603 2.5000OOe-01 1.500000e-01 

1354604 4.000000e-01 1.300000e-01 

1354605 5.000000e-01 7.0000OOe-02 

1354606 6.000000e-01 -4.000000e-02 

1354607 7.000000e-01 -2.300000e-01 

1354608 8.000000e-01 -5.100000e-01 

1354609 9.0000OOe-01 -9.1000OOe-01 

1354610 1.000000e+00 -1.470000e+00 

* head curve no 7 

13547001 7 

1354701 -1.000000e+00 O.O00000e+00 

1354702 0.000000e+00 0.000000e+00 "---..1--..---1---.----1-- -- 1-. -1-- 1....1----

* head curve no. 8 

1354800 1 8 

1354801 -1.000000e+00 0.000000e+00 

1354802 0.000000e+00 0.000000e*00

A4
* 1- -1- -1----1- ----- 1

* torque curve no. 1 

"" -1- -1- -1 -- 1--1--1---1

13549002 1 

1354901 0.O00000e+00 6.032000e-01 

1354902 1.930000e-01 6.325000e-01 

1354903 3.930000e-01 7.369000e-01 

1354904 5.955200e-01 8.331000e-01 

1354905 7.978200e-01 9.229000e-01 

1354906 1.000000e+00 1.000000e+00 

*---- - - -1-- 1------1

* torque curve no. 2 

*a-- 1-- -1- -1--1- --- 1 

13550002 2 

1355001 0.000000e+00 -6.700000e-01 

1355002 4.000000e-01 -2.500000e-01 

1355003 5.000000e-01 1.500000e-01 

1355004 7.372550e-01 5.265860e-01 

1355005 7.680490e-01 6.065940e-01 

1355006 8.672300e-01 7.436600e-01 

1355007 1.000000e+00 1.000000e+00 

*-- ----- -- 1-- -- 1--1-------1-- -1-

* torque curve no. 3 "*-- -------- -- 1-- --------- 1

1355100 2 3 

1355101 -1.OOO0Oe+00 1.984300e+00 

1355102 -8.009600e-01 1.394000e+00 

1355103 -6.063800e-01 1.097500e+00 

1355104 -4.068600e-01 8.220000e-01 

1355105 -1.992800e-01 6.648000e-01 

1355106 0.000000e+00 6.032000e-01 

*-- ---- 1-- -- -------- -1---1-

* torque curve no. 4 

*-- ---- ------ -- ---- 1-- -1

1355200 2 4 

1355201 -1.000000e+00 1.984300e+00 

1355202 -8.223400e-01 1.830800e.00 

1355203 -6.337100e-01 1.682400e+00 

1355204 -4.585300e-01 1.557000e+00 

1355205 -2.670230e-01 1.436200e+00 

1355206 -1.761070e-01 1.387900e+00 

1355207 -8.931000e-02 1.348100e+00 

1355208 0.O00000e+00 1.233610e+00 

*-- --------- ---------- -- 1- -1

* torque curve no. 5 

*- -•-- -- -- -1- -1- -1

13553002 5 

1355301 0.O00000e+00 -4.500000e-01 

1355302 4.000000e-01 -2.500OOe-01 

1355303 5.000000e-01 0.000000e+00 

1355304 1.000000e+00 3.509000e-01 "1----- ---- 1- -- -------- -1

'torque curve no. 6 

* --- -- 1--- ----- -- 1-- -- 1---1 

13554002 6 

1355401 OO-00000e+00 1.233610e+00 

1355402 9.064300e-02 1.196500eL00 

1355403 1.885690e-01 1.109600e+00 

1355404 2.734700e-01 1.041600e+00 

1355405 4.586690e-01 8.958000e-01 

1355406 5.744800e-01 7.807000e-01 

1355407 7.381600e-01 6.134000e-01 

1355408 7.685200e-01 5.849000e-01 

1355409 8.700570e-01 4.877000e-01 

1355410 1-000000e+00 3.569000e-01 

•-1----1-- -1--- -.. 1-- -- 1--1 ---..1- -- 1--

torque curve no. 7 

• - 1--i- -- 1- -- 1-- 11-- --- 1-- --

1355500 2 7 

1355501 -1.000000e+00 -1.000000e+00 

1355502 -3.000000e-01 -9.000000e-01 

1355503 -1.000000e-01 -5.000000e-01

1355504 O.OOOOOe+00 -4.500000e-01 "* -- 1-- -- 1-- 1-- -1- -1-•-1-

"torque curve no. 8 "*--1-- -- 1- -1--1 -1- -1

1355600 2 8 

1355601 -1.000000e+00 -1.000000e+O0 

1355602 -2.500000e-01 -9.000000e-01 

1355603 -8.0000OOe-02 -8.000000e-01 

1355604 0.O00000e+00 -6.700000e-01 

' pump 1 outlet pump side 

1400000 pmploutp snglvol 

1400101 0.0366 0.502 0.0 0.0 0.0 0.0 

1400102 4.0e-5 0.0 00000 

14002000 1.51268e+07 0.12412e+07 0.24568e+07 0.0 

"pump1 outlet pipe tee side 

1450000 pmploutt branch 

1450001 2 0 

1450101 0.0 1.4084 0.0633 0.0 0.0 0.0 

1450102 4.0e-5 0.0 00000 

14502000 1.51312e+07 0.12412e+07 0.24567e+07 0.0 

1451101 140010000 145000000 0.0 0.1 0.1 000100 

1452101 145010000 150000000 0.0 0.0 0.0 000100 

1451201 8.8843 8.88430.0 

1452201 10.426 10.426 0.0 

* pump outlet tee 

1500000 pmpoutt branch 

1500001 3 0 

1500101 0.0634 0.4966 0.0 0.0 0.0 0.0 

1500102 4.0e-5 0.0 00000 

15002000 1.51126e+07 0.12412e+07 0.24572e+07 0.0 

1501101 170010000 150000000 0.0183 0.2 0.2 000100 

1502101 150010000 175000000 0.0 0.1 0.1 000100 

1503101 1500100004060000000.0 0.0 0.0 000100 

1501201 4.1361 4.1361 0.0 

1502201 9.7788 9.7788 0.0 

15032012.66479e-07 2.66479e-07 0.0 

* pump 2 suction tee outlet 

1550000 pmp2sctt branch 

1550001 1 0 

1550101 0.0 1.003 0.0613 0.0 90-0 0.521 

1550102 4.0e-5 0.0 00000 

15502000 1.46976e+07 0.12410e+07 0.24664e+07 0.0 

1551101 155010000 1600000000.0 0.1 0.1 000100 

1551201 7.1313 7.1313 0.0 

* pump 2 inlet pipe 

1600000 pmp2inet snglvol 

1600101 00 0.457 0.0189 0.0 900 0.457 

16001024.0e-5 0.0 00000 

16002000 1.46788e+07 0.12410e+07 0.24668e+07 0.0 

Sprimary coolant pump 2

1650000 pcpump2 pump 

1650101 0.0366 00 0099 0.0 90.0 0.319 

1650102 00000 

1650108 160010000 0.0 0.0 0.0 000100 

1650109 170000000 00 0.1 01 000100 

16502000 1.49127e+07 0.12412e+07 0-24618e+07 0.0 

1650201 0 8.0583 8.0583 0.0 

1650202 0 8.0569 8.0569 0.0 

1650301 135 135 135 -1 -1 519 0 

1650302 369 00000 0.8599 31550000 96.000000 50060000 1.431

A- 5
1650303 613.6 0.0 207.433 0 004 19.59800.0 

16503100.0 00 0.0 

. pump 2 outlet 

1700000 pmp2outt branch 

1700001 1 0 

1700101 0.0366 0.514 0.0 0.0 0.0 0.0 

1700102 4.0e-5 0.0 00000 

1700200 0 1.51515e+07 0.12412e+07 0.24562e+07 0.0 

1701101 145010000 170010000 0.0183 0.2 0.2 000100 

1701201 -3.9184 -3.9184 0.0 *- -- 1--- -1-- -1-- -1 -- --- 1-- -1

cold leg pipe to ecc connection tee 

1750000 ilclpipe pipe 

1750001 2 

1750101 0.0634 2 

1750201 0.0 1 

1750301 0.559 1 

1750302 0.613 2 

1750401 0.0 2 

1750501 0.0 2 

1750601 0.0 2 

1750701 0.0 2 

1750801 4.0e-5 0.0 2 

1750901 0.15 015 1 

1751001 00000 2 

1751101 000100 1 

1751201 0 1.51081e+07 0.12412e+07 024573e+07 0.0 0.0 01 

17512020 1 51017e+07 0.12412e+07 0.24574e+07 0.0 0.0 02 

17513000 

1751301 9.7789 9.7789 0.0 01 

ecc connection tee pump side 

1800000 ecct branch 

1800001 1 0 

1800101 0.06343 1 152 0.0 0.0 0.0 0.0 

18001024.0e-5 0.0 00000 

18002000 1+50985e+07 0.12412e+07 0-24575e+07 0.0 

1801101 175010000 180000000 0.0 0.05 0.05000100 

1801201 9.7789 9.77890.0

"cold leg pipe from ecc connection to reactor vessel 

1850000 rvnilcl branch 

1850001 3 0 

1850101 0.06379 1,01 0.0 0.0 0.0 0.0 

1850102 4.0e-5 0.0 00000 

18502000 1.50967e+07 0.12412e+07 0.24576e+07 0.0 

1851101 1850100002050000000.0634 1.0 1.0 000100 

1852101 180010000 185000000 00 0.0 0.0 000100 

1853101 185010000 223000000 0 0 45.045-0 000100 

1851201 9.0375 9.0375 00 

1852201 9.7790 9 7790 O0 

1853201 1.6149 1 6149 0.0 

•reactor vessel 

"-. 1.... ...... .. 1 1.. ... ..... 1-...... .............. 1 

* inlet annulus top volume 

2000000 inantop branch 

2000001 2 0 

20001010.0 033 0.0855 00 900 033 

20001024.Oe-5 0.178 00000 

2000200 0 1.50826e+07 0.12412e+07 0.24579e+07 0.0 

2001101 200000000 205000000 0.0 0.0 0.0 000100 

2002101 200000000 245010000 0.001 1800 1800 000100 

2001201 -2 99198e-02 -2 99198e-02 0

2002201 6.79995e-02 6.79995e-02 0.0 "1-----1--- --------- ---- -- 1- -- 1- " inlet annulus bottom volume "*- --- 1-- -1-- -1-- -1--- -1-- -1-

2050000 inanbot branch 

20500011 0 

2050101 0.0 0.424 0.11 0.0 -90.0 -0.424 

2050102 4.0e-5 0.172 00000 

20502000 1-50837e+07 0.12412e+07 0.24579e+07 0.0 

2051101 205010000 210000000 0.0 0.0 0.0 000100 

2051201 3.9237 3.9237 0.0 ""- -"1- -1- -1- -1- -- 1- -- 1-

downcomer 

""- -1-- -1- -1- -1- -1- -1

2100000 downcomr annulus 

2100001 4 

2100101 0.142 4 

21002010.0 3 

2100301 0.958 4 

21004010.0 4 

21005010.0 4 

2100601 -90.0 4 

2100801 4.0e-5 0.102 4 

21009010.0 0.0 3 

2101001 00000 4 

2101101 000000 3 

2101201 0 1.50830e+07 0.12412e+07 0.24579e4+07 0.0 0.0 01 

21012020 1.50892e+07 0.12412e+07 0.24577e+07 0.0 0.0 02 

21012030 1.50954e+07 0.12412e+07 0.24576e+07 0.0 0.0 03 

21012040 1.51016e+07 0.12412e+07 0.24574e+07 0.0 0.0 04 

2101300 0 

2101301 3.9237 3.92370.0 01 

2101302 3.9237 3.92370.0 02 

2101303 3 9237 3.9237 0.0 03 *- -1- -- 1- -- 1--i--1- -- 1

lower plenum top volume 

"-- -1- -- 1---- - 1-- - 11-- -1

2150000 lwrptop branch 

2150001 3 0 

2150101 0.74 0.360 0.0 00 -90.0 -0.36 

2150102 4.0e-5 0.0 00000 

21502000 1.51098e+07 0.12410e+07 0-24572e+07 0.0 

2151101 2100100002150000000.0 0.0 0.0 000100 

215210112150100002200000000.0 0.0 0.0 000100 

2153101 2150000002250000000.150.0 0.0 000100 

2151201 3.9236 3.9237 0.0 

2152201 -6.34506e-02 -6.34506e-02 0.0 

2153201 2.4164 2.4164 0.0 

"-1-- -1-- --1-- ----- ------ -- 1

lower plenum bottom volume 

*-- -1-- -- 1---- - 1---- -- -- 1

2200000 lwrplot snglvol 

2200101 0.79 0.37 0.0 0.0 -90.0 -0.37 

2200102 4.0e-5 0.0 00000 

22002000 1.51125e+07 0.12387e+07 0.24572e+07 0.0 

"--1---- -- 1-- --- 1-I---i--- -1

core filler bypass 

*- ----I ---- 1- -- -- 1-- -1- --- 1-- --- 1-

2230000 fillegap annulus 

2230001 7 

2230101 2.9110-2 7 

2230201 0.0 6 

2230301 0+424 1 

2230302 0 958 5 

2230303 0.36 6 

2230304 0.37 7 

2230401 0.0 7 

2230501 0.0 7 

2230601 -90.0 7 

2230801 4.0e-5 0,0 7 

2230901 0.0 O0 6 

2231001 00000 7

A- G
2231101 000000 6 

2231201 0 1.50887e+07 0.12410e+07 0.24578e+07 0.0 0.0 01 

22312020 1.50937e+07 0.12405e+07 0.24576e+07 0.0 0.0 02 

22312030 1.51007e+07 0.12401e+07 0.24575e+07 0.0 0.0 03 

22312040 1.51078e+07 0.12396e+07 0.24573e+07 0.0 0.0 04 

22312050 1.51148e+07 0.12392e+07 0.24571e+07 0.0 0.0 05 

22312060 1.51196e+07 0.12390e+07 0.24570e+07 0.0 0.0 06 

22312070 1.51223e+07 0.12388e+07 0.24569e+07 0.0 0.0 07 

22313000 

2231301 1.6148 1.6148 0.0 01 

2231302 1.6144 1.61440.0 02 

2231303 1.6141 1.6141 0.0 03 

2231304 1.6137 1.61370.0 04 

2231305 1.6133 1.61330.0 05 

2231306 1.6132 1.61320.0 06 

* junction from filler gap to lower plenum "2-- -- 1- -- 11- -- 1-- -1-- -1-- -1-

2240000 fUrgapp sngljun 

2240101 2230100002200100000.0 10. 10. 000100 

2240201 0 1.6131 1.6131 0.0 

S- -1- -1- 1--1-----1- -- -1-

* lower core support structure 

* -- -11- 1 1--1--1------1---1

2250000 Icoreup branch 

2250001 2 0 

22501010.25 0.52 0.0 0.0 90.0 0.52 

2250102 4.0e-5 0.095 00000 

2250200 0 1.50986e+07 0.12410e+07 0.24575e+07 .0 

2251101 225010000 230000000 0.0975 0.3 0.3 000000 

2252101 225010000 235000000 0.0 0.0 0.0 000000 

2251201 3.3511 3.3511 0.0 

2252201 2.1831 2.1831 0.0 

""- -1- -1- 1--1-- -- --- ---- 1

* active core 

*-- -1- -- 1-- ---- ----- -- 1-- -- 1

2300000 core pipe 

2300001 3 

2300101 0.1705 3 

2300201 0.1440 2 

2300301 0.559 2 

2300302 0.657 3 

2300401 0.0 3 

2300501 0.0 3 

2300601 90.0 3 

2300801 4.0e-5 0.012 3 

2300901 0.66 0.66 2 

2301001 00100 3 

2301101 000100 2 

2301201 0 1.50762e+07 0.12871e+07 0.24581e+07 0.0 0.0 01 

23012020 1.50637e+07 0.13370e+07 0.24584e+07 0.0 0.0 02 

23012030 1.50502e+07 0.13529e+07 0.24587e+07 0.0 0.0 03 

23013000 

2301301 3.4276 3.4276 0.0 01 

2301302 3.5187 3.5187 0.0 02 

*-- -1- --- 1-- -1--- -1- -1- -1

"core bypass volume 

""- -1- -11- -1--1----- -- 1- -- 1

2350000 corebyps pipe 

2350001 3 

2350101 0.015 3 

2350201 0.0 2 

2350301 0.559 2 

2350302 0.657 3 

2350401 0.0 3 

2350501 0.0 3 

2350601 90.0 3 

2350801 4.0e-5 0.003 3 

2350901 0.0 0.0 2 

2351001 00000 3 

2351101 000000 2 

2351201 0 1.50877e+07 0.12410e+07 0.24578e+07 0.0 0.0 01

23512020 1.50693e+07 0.12410e+07 0.24582e+07 0.0 0.0 02 

2351203 0 1. 50492e+07 0.12411e+07 0.24587e+07 0.0 0.0 03 

23513000 

2351301 2.1831 2.1831 0.0 01 

2351302 2.1832 2.1832 0.0 02 

-1- -1- -1- -1-- --- -1 -- 

upper core support structure 

........... -- 1 -

2400000 ucosSt branch 

2400001 2 0 

2400101 0.297 1.118 0.0 0.0 90.0 1.118 

2400102 4.0e-5 0.145 00000 

24002000 1.50346e+07 0.13468e+07 0.24591e+07 0.0 

24011012300100002400000000.12 0.3 0.3 000000 

2402101 235010000 240000000 0.0 0.0 0.0 000000 

2401201 3.5504 3.5504 0.0 

2402201 2.1833 2.1833 0.0 

-I- -I- -1- - -1 -

* upper flow skirt region 

1- 1- - 1- 11 ---

2450000 ufosre branch 

24500011 0 

2450101 0.114 0.843 0.0 0.0 90.0 0.843 

2450102 4.0e-5 0.131 00000 

2450200 0 1.50141e+07 0.13455e+07 0.24596e+07 0.0 

2451101 240010000 245000000 0.0 0.0 0.0 000100 

2451201 5.5952 5.5952 0.0 

*-- -1- -1- -1- -1---1- -- 1

• dead end of fuel modules 

""--"1- -1-1- 1- -1- -1

2460000 fumodu branch 

24600011 0 

2460101 0.183 0.7 0.0 0.0 90.0 0.7 

2460102 4.Oe-5 0.214 00000 

24602000 1.50299e+07 0.13438e+07 0.24592e+07 0.0 

2461101 240010000 246000000 0.0 0.0 0.0 000100 

2461201 -8.22277e-07 -8.22277e-07 0.0 

1 1 1 -- 1- -1- -1

upper plenum lower volume 

-1- -1- -1- -1- -1- -1 --- 

2500000 upllvol branch 

2500001 1 0 

2500101 0.268 1.566 0.0 0.0 90.0 1.566 

2500102 4.0e-5 0.0 00000 

25002000 1.50159e+07 0.13440e+07 0.24595e+07 0.0 

2501101 245010000 250000000 0.0 0.0 O0 000100 

2501201 5.6629 5.6629 0.0 

broken loop 

"reactor vessel nozzle - broken loop hot leg -- -- 1 -- --- 1 -- -- 1-- -- 1-- -- 1 - 1-

3000000 rvblhl branch 

3000001 2 0 

3000101 0.0634 0.876 0.0 0.0 0.0 0.0 

3000102 4.0e-5 0.0 00000 

3000200 0 1-50214e+07 0.12349e+07 0.24594e+07 0.0 

3001101 2500000003000000000.0634 0.0 00 000100 

3002101 300010000 305000000 0.0 0.1 0.1 000000 

3001201 -0.12677 -0.12677 0.0 

3002201 -0.12680 -0.12680 0.0 

*----1-1...1----- -1. .. 1..1

* hot leg pipe to reflood assist bypass tee *-- --1---... . .1-- .. .. 1.. 

3050000 hlpras branch 

30500011 0 

3050101 00634 0.698 0.0 0.0 0.0 0-0 

3050102 4.0e-5 0.0 00000 

30502000 1 50214e+07 0.12354e+07 0.24594e+07 0.0 

3051101 305010000 310000000 0.0 0-1 0.1 000100

A- 7
3051201 -0.17141 -0.17141 0.0 

* broken loop hot leg contraction --..1 .. -- 1- -- -- 1 --- .. -- 1---1-- 

3100000 sgsii branch 

3100001 2 0 

3100101 0.0 1.5001 0.06785 0.0 0.0 0.0 

3100102 4.0e-5 0.0 00000 

31002000 1.50214e+07 0.12358e+07 0.24594e+07 0.0 

3101101 370010000 310000000 0.0 0.0 0.0 000100 

3102101 310010000 315000000 0.0 0,0 00 000100 

3101201 0.20738 0.20738 0.0 

3102201 3.10704e-04 3.10704e-04 0.0 "*-- -1-- -1- -1--- -1- -- 1- -1-

* steam generator and pump simulatior 

1- -1-- 1-- ---1- -1-- -1--- -1-

3150000 sgpsi pipe 

3150001 12 

3150101 0.00836 2 

3150102 0.108 8 

31501030.0 10 

3150104 0,00836 •1 

3150105 0.0525 12 

3150201 0.0 2 

3150202 0.0326 4 

3150203 0.108 5 

3150204 0.0326 7 

315020500 8 

31502060.0 9 

3150207 0.0081 10 

315020800 11 

3150301 0.4054 1 

3150302 0.5265 2 

3150303 0 362 3 

3150304 1+692 4 

3150305 0.8495 6 

3150306 1692 7 

3150307 0.362 8 

31503081.346 9 

3150309 1.325 10 

31503101.842 11 

3150311 0667 12 

3150401 0.0 8 

3150402 0.0162 9 

3150403 0.0648 10 

31504040.0 12 

3150601 90.0 5 

3150602 -900 10 

3150603 90.0 11 

3150604 0.0 12 

3150701 0.127 1 

3150702 0488 2 

3150703 0.362 3 

3150704 1.692 4 

3150705 0.457 5 

3150706-0.457 6 

3150707 -1.692 7 

3150708 -0362 8 

3150709 -1 143 9 

3150710 -0.686 10 

3150711 1.214 11 

31507120.0 12 

3150801 4 0e-5 00 3 

31508024.0e-5 0 124 4 

3150803 4.0e-5 00 6 

315080440e-5 0124 7 

31508054.0e-5 00 12 

3150901 0.2 02 1 

315090200 00 2 

3150903 939 939 4 

315090404 04 5 

3150905939 939 7

31509060.0 0.0 8 

31509070.2 0.2 9 

3150908 4.1 4.1 10 

31509090.4 0.4 11 

3151001 00000 12 

3151101 000000 1 

3151102 000100 4 

3151103 000000 5 

3151104 000100 11 

3151201 0 1.50209e+07 0.11839e+07 0.24594e+07 0.0 0.0 01 

31512020 1.50186e+07 0.11694e+07 0.24595e+07 0.0 0.0 02 

31512030 1.50153e+07 0.12058e+07 0.24595e+07 0.0 0.0 03 

31512040 1.50077e+07 0.12176e+07 0.24597e+07 0.0 0.0 04 

31512050 1.49996e+07 0 12206e+07 0.24599e+07 0.0 0.0 05 

31512060 1 49996e+07 0.12220e+07 0.24599e+07 0.0 0.0 06 

31512070 1.50076e+07 0.12245e+07 0.24597e+07 0.0 0.0 07 

31512080 1 50153e+07 0.12198e+07 0.24596e+07 0.0 0.0 08 

31512090 1.50209e+07 0.12237e+07 0.24594e+07 0.0 0.0 09 

31512100 1 .50277e+07 0.12236e+07 0.24592e+07 0.0 0-0 10 

3151211 0 1.50258e+07 0.12244e+07 0-24593e+07 0.0 0.0 11 

31512120 1.50212e+07 0.12233e+07 0.24594e+07 0.0 0.0 12 

31513000 

3151301 .0 .0 0.0 01 

3151302.0 .0 0.0 02 

3151303.0 .0 0.0 03 

3151304 .0 .0 0.0 04 

3151305 .0 .0 0.0 05 

3151306.0 .0 0.0 06 

3151307.0 .0 0.0 07 

3151308.0 .0 0.0 08 

3151309.0 .0 0.0 09 

3151310.0 .0 0.0 10 

3151311 .0 .0 0.0 11 "--1----- -1- -- 1- -1-- -1-- -1

* isolation valve hot leg 

*--- -- 1- -1-- -- 1- -1-- -1- -1-

3200000 isvhl valve 

3200101 315010000 325000000 0 0 0.0 0.0000100 

3200201 1 0-0 0.0 0.0 

3200300 trpvlv 

3200301 504 "---1--- -- 1---- - 1---- --- 1

* pipe section between isolat 

*-- -- 1-- -- 1-- -- 1--1 -- 1----1-

3250000 vwolhl sngtvol 

3250101 0.0525 0.823 0.0 0 0 0.0 0.0 

3250102 4.0e-5 0.0 00000 

3250200 0 1.47400e+07 0.12385e+07 0.24655e+07 0.0 

"quick opening blowdown valve hot leg "---1--- -- 1-- -- ----- ----- ---

3300000 qobvhl valve 

3300101 325010000 800000000 0.0466 0.0 0.0 000100 

3300201 1 0.0 0.0 0.0 

3300300 trpvlv 

3300301 504 "*- ..... 1 .... - 1 -- .. -- 1 --- - -- 1 --1-- -- 1 

reactor vessel nozzJe - broken loop cold leg 

3350000 rvnbl branch 

3350001 2 0 

3350101 0.0634 0.7495 0.0 0.0 0.0 0.0 

3350102 4.0e-5 0.0 00000 

33502000 1.50838e+07 0.12408e+07 0.24579e+07 0.0 

3351101 205000000 335000000 0.0634 1.0 1.0 000100 

3352101 335010000 340000000 0.0 0.1 0.1 000000 

3351201 0.12722 0.127220.0 

3352201 0 12719 0.127190.0 

* cold leg pipe to reflood assist bypass tee 

30-..1-...1 - 1 h1-1-----1--- -- 3400000 ctbarv branch

A-S
3400001 1 0 

3400101 0.0634 0.698 0.0 0.0 0.0 0.0 

3400102 4.0e-5 0.0 00000 

34002000 1.50838e+07 0.12404e+07 0.24579e+07 0.0 

3401101 340010000 345000000 0.0 0.1 0.1 000000 

3401201 0.12717 0.12717 0.0 

""- -1- -1- -1- -1- -I--1- "broken loop cold leg contraction to break plane *ý-- -I1- -- 1- -- 11- -- 1- -1I- -- 1-

3450000 baoet branch 

3450001 2 0 

3450101 0.0634 0.974 0.0 0.0 0.0 0.0 

3450102 4.0e-5 0.0 00000 

34502000 1.50838e+07 0.12398e+07 0.24579e+07 0.0 

3451101 345000000 385000000 0.0 0.0 0.0 000100 

3452101 345010000 350000000 0.0 0.0 0.0 000100 

3451201 0.20769 0.20769 0.0 

3452201 2.02355e-04 2.02355e-04 0.0 

*- -11- -11- -1- -1- -1--1

ecc tee isolation valve cold leg 

*- -11- -1- -1- -1- -1- -1

3500000 etivcl pipe 

3500001 2 

3500101 0.0 2 

3500201 0.0 1 * break plane 

3500301 0.488 1 

3500302 1.6085 2 

3500401 0.00541 1 

3500402 0.07770 2 

3500601 0.0 2 

3500801 4.0e-5 0.0 1 

3500802 4.0e-5 0.0 2 

3500901 0.0 0.0 1 

3501001 00000 2 

3501101000100 1 

3501201 0 1.50838e+07 0.10201e.+07 0.24579e+07 0-0 0.0 01 

35012020 1.50838e+07 0.11596e-07 0.24579e+07 0.0 0.0 02 

35013000 

3501301.0 .0 0.0 01 "*- -1-- -1-- -1-- -1- --- 1-- -- 1-1 

isolation valve cold leg 

*- -1-- --- ---- ---- ---- -- 1

3550000 isvcl valve 

3550101350010000 360000000 0.0 0.0 0.0 000100 

35502011 0.0 0.0 0.0 

3550300 trpvOv 

3550301 504 

*- -- -1- -- ---- ---- -- 1 "pipe section between isolation valve and qobv cold leg -- --- -1--i- -- 1-i- -- 1- -- 1-

3800000 vvolcl snglvol 

3600101 0.0525 0.8130.0 0.0 0.0 0.0 

3600102 4.0e-5 0.0 00000 

3600200 0 1.47400e+070.12385e+07 0.24655e+07 0.0 

--.- 1-- ---- ------- 1--1--1--1--1

* quick opening blowdown cold leg 

I-- -- 1-- ---- ---- -----------1---1

3650000 qobvd valve 

3650101 360010000 805000000 0.0466 0.0 0.0 000100 

3650201 1 0.00.0 00 

3650300 tpvlv 

3650301 504 *-- -1--1 --.. 1...- - -- 1-- -1---1--- -1--

" reflood assist bypass piping - cold leg side --- -1-- -1- -- 1-- -1--- -1---

3700000 rabsphl branch 

3700001 1 0 

3700101 0.0388 2.203 0.0 0.0 90.0 0.653 

370010240e-5 0.0 00000 

3700200 0 1.50238e+07 0.12366e+07 0.24593e+07 0.0 

3701101 375010000 370000000 0.0 0.0 0.0 000100 

3701201 0 20747 0-20747 0.0

*-- --- 1--i- -- 1--- -1- -1- -1-

* reflood assist bypass parrel pipes hot leg side *-- -1-- -- 1- -- 1 - -- 1-- -- 1- -11-

3750000 rabphl snglvol 

3750101 0.0776 0.0 0-0858 0.0 0.0 0.0 

3750102 4.0e-5 0.0 00000 

37502000 1.50262e+07 0.12375e+07 0.24593e+07 0.0 "- -1--i- -1--i- -1---.- -1

reflood assist bypass valves 

*-- -1- -1- -1- -1- -1- -1

3770000 rabsvlv sngljun 

3770101 380010000 375000000 0.0 1.4e+4 1.4e+4 000000 

3770201 0 0.10375 0.10375 0.0 

-- 1- -1- -1- -1- -1- -1 -- "reflood assist bypass parrel pipes cold leg side 

-- 1- -1- -1- -1- -1- -1 -l 

3800000 rabppcl snglvol 

3800101 0.0776 0.0 0.0855 0.0 0.0 0.0 

38001024.0e-5 0.0 00000 

38002000 1.50886&+07 0.12380e+07 0.24578e+070.0 

*-- -1-- -1-- -1- -- -1- -- 1

* reflood assist bypass single pipe cold leg side 

-1 -1- -1- -1- -1- -

3850000 rabspcl branch 

3850001 1 0 

3850101 0.0388 0.0 0.118020.0 -90.0 -0.653 

3850102 4.0e-5 0.0 00000 

3850200 0 1.50862e+07 0.12384e+07 0.24578e+07 0.0 

3851101 385010000 380000000 0.0 0.0 0.0 000100 

3851201 0.20755 0.20755 0.0 

pressurizer

surge line pcs side ""- -1- -1- -1- -1-- -1- -1

4000000 slpcs branch 

4000001 2 0 

4000101 0.00145 3.45 0.0 0.0 90.0 0.54 

4000102 4.0e-5 0.0 00000 

40002000 1.49932e+07 0.13445e+07 0.24601e+07 0.0 

4001101 110000000 400000000 0.0 0.93 0.93 000100 

4002101 400010000 405000000 0.0 0.93 0.93 000000 

4001201 -1.76611e-03 -1.76611e-03 0.0 

4002201 -1.76637e-03 -1.76637e-03 0.0 ""--1- -1-- -- -1- -1--1

surge line pressurizer vessel *-- -1-- -- 1-- -1...1- --- 1 - 1- ---1 

4050000 slprv snglvol 

4050101 0.00145 3.45 0.0 0.0 90.0 0.60 

4050102 4.0e-5 0.0 00000 

4050200 0 1.49892e+07 0.13500e+07 0.24602e+07 0.0 

* spray line 

*- -1- -- 1- -1- -1-- -1-- -1

4060000 spray snglvol 

4060101 0.000336 6.322 0.0 0.0 90.0 

4060102 3.161 4.0e-5 0.0 00000 

4060200 0 1.51369e+07012441e+07 0.24566e+070.0 

spray valve "*- -- 1-- -1-- -1--1-- -- 1...1- --- 1

4070000 sprvlv valve 

4070101 406010000 420010000 3.3451e-4 0.0 0.0 000100 

0.93 

4070201 0 .000000.000000 0.0 

4070300 trpvlv 

4070301 690

A- 9
pressurizer surge line valve 

*- -- 1-- -1--- -1- -- 1-- -1-- 1--

4100000 slvalv sngljun 

4100101405010000 415000000 0.0 0.93 0.93 000100 

4100201 0 -1.78329e-03-1.78229e-03 0.0 

-__ -- 1--- -- 1--- -1--- -1I- -- 1-- -1-

* pressurizer vessel 

*--- -- 1-- -- 1-- -- 1...1--- -- 1-- 1- ---1 

4150000 pzrve pipe 

4150001 8 

4150101 0.362 1 

41501020,565 5 

41501030466 7 

41501040.13 8 

4150201 0.0 7 

4150301 0.224 1 

4150302 0.403 3 

4150303 0.207 5 

4150304 0.1705 7 

4150305 0.118 8 

4150401 0.0 8 

41505010.0 8 

4150601 90.0 8 

4150801 4.0e-5 0.0 8 

4151001 00000 8 

4151101 000000 7 

4151201 0 1.49863e+07 0.14689e+07 0.24602e+07.0 0.001 

41512020 1-49844e+07 0.15556e+07 0-24603e+07.0 0.0 02 

41512030 1.49820e+07 0.15592e+07 0.24612e+07 0.10700 0.0 03 

41512040 1 .49808e+07 0.15853e+07 0.24604e+07 0.99997 0.0 04 

41512050 1 .49806e+07 0.15852e+07 0+24604e+07 0.99994 0.0 05 

41512060 1.49805e+07 0.15853e+07 0.24604e+07 0.99995 0.0 06 

41512070 1.49803e+07 0.15853e+07 0.24604e+07 0.99996 0.0 07 

41512080 1.49802e+07 0.15851e+07 0.24604e+07 099995 0.0 08 

41513000 

4151301 -9.80221e-06 1.72291e-04 0.0 01 

4151302 -1.00009e-05 0.29111 0.0 02 

4151303 -0.26445 -1.27089e-05 0.0 03 

4151304 -9.80199e-02 -2.35256e-05 0.0 04 

4151305 -0.11938 -4.16312e-05 0.0 05 

4151306 -9.40738e-02 -5.24284e-05 0.0 06 

4151307 -0.16661 -2.26655e-04 0.0 07 *.... 1- ... 1 ..1-- -- 1- - ..1-- -- 1- -1 

pressurizer top hat and relief connection 

4200000 toppre branch 

4200001 1 0 

4200101 013 0.118 0.0 00 90.0 0.118 

42001024.0e-5 0.0 00000 

42002000 1.49801e+07 015854e+07 0.24604e+07 099995 

4201101 415010000 420000000 0.0 0.0 0.0 000000 

4201201 -9.69743e-02 -2.46255e-04 0.0 

" 1--- 1 -- -- ---.. 1 -...--- 1- -1-- -1-

porv 

1-- -- 1 ..... 1 .. ... 1 -....... 1.--...1 --. -- 1-

4250000 porv valve 

4250101 420010000 810000000 2.4784e-5 0.0 0.0 000100 

4250201 0 .000000 00000 0.0 

4250300 trpvlv 

4250301 626 

"- -- 1----- 1---1---...I.... ... -- 1--- -1----I.. 

experimental SRV 

4300000 porv valve 

4300101 420010000 820000000 6.24e-5 0.0 0.0 000100 

4300201 0 000000 00000 0 0 

4300300 trpvlv 

4300301 634

"-- ---- --- 1--- ------ 1-- ---- -- 1-

containment power operated relief valve 

*- -- I- -1-- -1- -1- -1- -1-

8100000 cporv tmdpvol 

81001010.0 1.0 0.1 0.0 0.0 0.0 

81001020.0 0.0 00000 

8100200 2 

81002010.0 0.107e+6 10 

"-- -1-- -- 1-- -- I-----1-------------

"containment power operated relief valve 

"*-- -- 1---- - 1-- - 11-- - 1-- -1

8200000 cporv trndpvol 

8200101 0.0 1.0 0.1 0-0 0.0 0.0 

8200102 0.0 0.0 00000 

8200200 2 

8200201 0.0 0.107e+6 1.0 

"steam generator secondary side 

pnmary separator "*- -1 -- -- 1 - -- I-- -- I-- -- 1 - -- 1 

5000000 sepaout branch 

5000001 2 0 

50001011.273 0.718 0.0 0.0 +90.0 +0.718 

5000102 4.e-5 0.7874 01000 

5000200 0 5-61017e+06 0.11842e+07 0.25930e+07 0.98167 

5001101 500010000 525000000 0.0 5.0 5.0 000000 

5002101 500000000 505000000 0.0 0.0 0.0 000000 

5001201 -2.7011 0.700730.0 

5002201 0.58921 -8.34267e-05 0.0 

-1- -1-I 1- -1- -1- - 1- 

separator outlet region "- -- 1-- -- 1-- --------- ---- -- 1

5050000 lwrsep branch 

5050001 1 

5050101 1.273 0.718 0.0 0.0 -900 -0.718 

5050102 4.e-5 0.7874 01000 

5050200 0 5 61221e+06 0.11842e+07 0.25930e+07 0.30082 

5051101 505010000 510000000 0.0 0.0 0.0 000000 

5051201 0.17414 -9.48643e-02 0.0 "-- -1 -- -- 1-----1-------1----1 "feed inlet volume 

"-- 1-I- -- 1---. I-1- -1---- -- I--1--i 

5100000 feedinl branch 

51000011 0 

5100101 0.7525 0.518 0.0 0.0 -90.0 -0.518 

5100102 4.e-5 0.10796 01000 

5100200 0 5.61615e+06 0.11030e+07 0.25930e+07 0.0000 

5101101 510010000 515000000 0.0 0.0 0.0 000100 

5101201 0.51954 0.51954 0.0 

"steam generator downcomer 

5150000 dwncmr annulus 

5150001 14 

5150101 0.23226 6 

5150102 0.258 14 

5150201 0.0 5 

515020200 6 

51502030.0 13 

5150301 07102 1 

5150302 03551 3 

5150303 0.2367333 6 

5150304 0.61691667 9 

5150305 0.925375 11 

5150306 1.85075 13 

5150307 0718 14

A-1 0
5150401 0.0 14 

5150601 -90.0 6 

5150602 21.0 12 

5150603 16.0 13 

5150604 90.0 14 

5150701 -0.7102 1 

5150702 -0.3551 3 

5150703 -0.2367333 6 

5150704 0.2367333 9 

5150705 0.3551 11 

5150706 0.7102 12 

5150707 0.518 13 

5150708 0.718 14 

5150801 4.e-5 0.10793 6 

5150802 4.e-5 0.0305 13 

5150803 4.e-5 0.0 14 

5150901 0.0 0.0 5 

5150902 17.5 17.5 6 

5150903 0.0 0.0 8 

5150904 2.1 2.1 9 

51509054.2 4.2 12 

51509064.4 4.4 13 

5151001 0001000 6 

5151002 0001100 12 

5151003 0001000 14 

5151101 000000 5 

5151102 000000 6 

5151103 000000 13 

5151201 0 5.62080e+06 0.11038e+07 0.25929e+07 0.0000 0.0 

01 

5151202 0 5.62631e+06 0.11046e+07 0.25929e+07 0.0000 0.0 

03 

5151203 0 5&63182e+06 0.11053e+07 0.25929e+07 0.0000 0.0 

06 

5151204 0 5.63067e+06 0.11745e+07 0.25928e+07 0.32326 0.0 09 

5151205 0 5.62614e+06 0.11839e+07 0.25929e+07 0.49171 0.0 11 

51512060 5.62047e+06 0.11846e+07 0.25929e+07 0.604090.0 12 

51512070 5.61560e+06 0.11844e+07 0.25930e+07 0.59935 0.0 13 

5151208 0 5.61269e.06 0.11844e+07 0.25930e+07 0.51173 0.0 14 

51513000 

5151301 0.51971 0,51971 0.0 01 

5151302 0.51987 0.519870.0 03 

5151303 0.52002 0.83703 0.0 06 

5151304 0.61397 2.5665 0.0 09 

5151305 0.73514 4.0513 0.0 11 

5151306 0.83034 5.2889 0.0 12 

5151307 0.82057 5.3343 0.0 13 

"-- -"1- ----- 1---- -- 1------

* top of the riser 

, -- -1-- -- 1-- -1---- -1--i

5200000 separin separatr 

5200001 3 0 

5200101 0.27871 0.718 0.0 0.0 90.0 0.718 

5200102 4.e-5 0.0 01000 

5200200 0 5.61107e+06 0.11843e+07 0.25930e+07 0.81644 

5201101 520010000 5250000000.0 3.7 3.7000000 

5202101 520000000 505000000 0.0 0.0 0.0 000000 

5203101 515010000 520000000 0.0 4.4 4.4 000000 

5201201 0.67331 6.2512 0.0 

5202201 0.67331 6.2512 0.0 

5203201 0.67331 6.2512 0.0 

below mist extractor, above top of shroud in steam dome - -- 1--- 1 -- 1....1-- --... -i---i-- -1---

5250000 botstm branch 

52500011 0 

5250101 1.5886 0.762 0.0 0.0 90.0 0.762 

5250102 4.e-5 00 00000 

52502000 5.60992e+06 0.11841e+07 0.25930e+07 1.0000

5251101 525010000 530000000 0.0 0.8 0.8 000100 

5251201 0.66195 0.71981 0.0 

"mist extractor and steam generator outlet pipe to scv 

-- 1- -1- -1- -1-- -1- -1 --- 5300000 stmpipe pipe 

5300001 2 

5300101 1.2728 1 

5300102 0.04635 2 

5300201 0.01365 1 

5300301 0.762 1 

5300302 25.074 2 

5300401 0.0 2 

5300601 90.0 1 

53006020.0 2 

5300801 4.e-5 0.0 2 

5300901 0.8 0.8 1 

5301001 00000 2 

5301101 000100 1 

53012013 5.61e+06 554.0 0.0 0.0 0.0 01 

53012023 5.49e+06 554.0 0.0 0.0 0.0 02 

53013000 

5301301 10.500 19.767 0.0 01 • - -- 1-- -- 1-- -- 1-- -- 1-- -- 1-- -1-I

"pipe downstream of steam control valve 

5350000 condint snglvol 

5350101 0.06557 54.44 0.0 0.0 0.0 0.0 

5350102 4.e-5 0.0 00000 

53502000 2.12350e+06 0.92017e+06 0.25983e+07 0.99600 

*-- -- 1--- ---- -1- -1

* air cooled condenser 

-1-- -- -1-1 - -- 1 -1- 

5400000 condnsr tmdpvol 

5400101 0.21677 17.67 0.0 0.0 0.0 0.0 

5400102 4.e-5 0.02 00000 

54002002 

5400207 0.0 2.069e+6 1.0 

*- -1- -- 1-----1---1-- -1

* feed storage tank 

"-- -1 - -1-- -1- -1-- -11- -1

5450000 feedtnk tmdpvol 

5450101 29.81 3.048 0.0 0.0 0-0 0.0 

5450102 4.e-5 0.0 00000 

5450200 1 

5450201-1.0 480.62 0.0 

54502020.0 480-62 0.0 

*-- -- 1- -1- -1-- -- -1- -1 "steam control valve bypass 

-1- -1- -- 1- -1- -1- -1 --- 

5460000 scvbyp valve 

5460101 530010000 547000000 4.48e-4 0.0 0.0 000000 

5460201 0 .000000.000000 0.0 

5460300 trpvlv 

5480301 504 

*- -I--- --- 1- -I--1--1--1

* air cooled condenser 

""- -1- -1-- -1- -1-- -1-- -- 1

5470000 conders tmdpvol 

5470101 0.21677 17.67 0.0 0.0 0.0 0.0 

5470102 4.e-5 0.0 00000 

54702002 

5470207 0.0 2.069e+6 1.0 "I---1- --- 1 - 1-- -..1---1-- --- ... 1---

• steam flow control valve 

*- --- 1.....I-- 1 -- 1--- --1 . . ....... I---

5500000 cv-p4-1 sngljun 

5500101 530010000 535000000 0.003370+0 0.0 000100 0.93 

5500201 0 18.585 20.163 0.0 

"-- --p 1-- ----1--- co1-- -1-- ---- -- •flOW path to the air cooled condenser 

"---...1---... - 1 -.....1 -. ... 1- -. .. 1 ..... 1-....

A- 1 I
5550000 coacco sngljun 

5550101 535010000 540000000 0.0 0.0 0.0 000100 

5550201 0 8.1357 35ý082 0.0 

- -- 1- -- 1--i--i- -- 1- --- 1

main feed water valve 

5600000 mnfeed tmdpjun 

5600101 545000000 510000000 0.05 

5600200 1 

5600201 0.0 25.7 0.0 00

containment 

*- -1-- -1-- - 1-- -- 1-- -1-

* containment broken loop hot leg 

*- -- 1----------1- --- - 1-------1-

8000000 cblhl tmdpvol 

8000101 0-0 1.0 0.1 0.0 0.0 0.0 

80001020.0 0.0 00000 

8000200 2 

8000201 0.0 0.107e6 1.0 

8000202 10000.0 0.107e6 1.0 

*. 1---I----I----1--------1

containment broken loop cold leg 

"--- -"1-- ---- ----- -- -1-- --- 1-

8050000 c805 tmdpvol 

8050101 0.0 1.0 0.1 0.0 0.0 0.0 

8050102 0.0 0.0 00000 

8050200 2 

8050201 0.0 1.Oe+5 1.0 

8050202 10000.0 1.0e+5 1 0 

---- 1- -..- 1-- --.. 1--- --- -...-1-- --..1--

heat structure input data 

steam generator heat structures 

* steam generator tubing

12 8 2 1 

0 1 

7 0.006348984 

6 7 

0.0 7 

540.0 8 

115040000 10000 

115070000 10000 

115090000 10000 

115110000 10000 

115130000 10000 

515070000 10000 

515100000 10000 

515120000 0 1 

515110000 -10000 

515090000 -10000

0.0051054

1 562.493667 3 

1 843.7405 5 

1 1687.481 7 

1 8437405 9 

1 562.493667 12 

1 562.493667 3 

1 843.7405 5 

1687.481 7 

1 8437405 9 

1 562493667 12

10060701 0 0 0 0 12 

10060801 0.0 11.0 11.00.0 0.0 0.0 0.0 1.012*mod3 

10060901 00 11.0 11M000 O0 00 00 1012*mod3

11151101 1 6.35e-3 

11151102 2 7.072376e-3 

11151201 6 1 

11151202 5 3 

11151301 0.0 3 

11151401 5770 4 

11151501 115030000 130000 1 1 0.25 2 

11151601 -939 0 3949 1 0.25 2 

11151701 0 0.0 0.0 0.0 2 

11151801 0.0 11.0 11.00.0 0.0 0.0 0.0 1-02 mod3 

"tube sheet periphery

11152000 

11152100 

11152101 

11152201 

11152301 

11152401 

11152501 

11152502 

11152601 

11152701 

11152801 

11152901

2 20 1 1 00 

0 1 

19 0.623795 

5 19 

0.0 19 

577.0 20 

1150300000 1 1 0.1579621 1 

1151600000 1 1 01579621 2 

5150600000 1 1 0.1579621 2 

0 0.0 0.0 0.0 2 

00 11.0 11.00.0 0.0 0.0 0.0 1.02 *mod3 

0.0 11.0 11.00.0 0.0 0.0 0.0 1.02 *mod3

* intact loop piping 

11001000 12 11 2 1 0142 

11001100 0 1 

11001101 10 0.178 

11001201 4 10 

11001301 0.0 10 

11001401 540.0 11 

11001501 100010000 0 1 1 1.5373 1 

11001502 1050100000 1 1 1.634 2 

11001503 1100100000 1 1 0.623 3 

11001504 1150100000 1 1 1.4385 4 

11001505 115180000 0 1 1 0.689 5 

11001506 1151900000 1 1 0.559 6 

11001507 120010000 0 1 1 0.76 7 

11001508 1500100000 1 1 0.4966 8 

11001509 1750100000 1 1 0.559 9 

11001510 175020000 0 1 1 0-613 10 

11001511 1800100000 1 1 0.701 11 

11001512 1850100000 1 1 1.461 12 

11001601 -939 0 3949 1 1.5373 1 

11001602 -939 0 3949 1 1.634 2 

11001603 -939 0 3949 1 0.623 3 

11001604 -939 0 3949 1 1.4385 4 

11001605 -939 0 3949 1 0.689 5 

11001606 -939 0 3949 1 0.559 6 

11001607 -939 0 3949 1 0.76 7 

11001608 -939 0 3949 1 04966 8 

11001609 -939 0 3949 1 0.559 9 

11001610 -939 0 3949 1 0.613 10 

11001611 -939 0 3949 1 0701 11 

11001612 -939 0 3949 1 1.461 12 

11001701 0 0 0 0 12 

11001801 0.0 11.0 11 0 0.0 0.0 0.0 0.0 1.0 1 mod 3 

11001802 0.0 11.0 11 00.0 0.0 0.0 0.0 1.02*rmod3 

11001803 0.0 11.0 11.00.0 0.0 0.0 0.0 1.03*rood3 

11001804 0.0 110 11.00.0 O0 0.0 0.0 1.04m*rod3 

11001805 0.0 11.0 11.00.0 0.0 0.0 0.0 1.05*rmod3 

11001806 0.0 11.0 11.000 0.0 0.0 0.0 1.06 mod3 

11001807 0.0 11.0 11.000 00 0.0 0.0 1.07 *rmod3 

11001808 0.0 11.0 11.00.0 0.0 0.0 0.0 1.08*mod3 

11001809 0.0 110 1100.0 00 0.0 0.0 1.09*rood3 

11001810 00 110 11.00.0 00 00 0.0 1.010 *mod3 

11001811 00 11.0 11.00.0 0.0 0.0 0.0 1.011 *mod3 

11001812 0.0 11.0 1100.0 0.0 0.0 0.0 1.012 *rmod3 - 1..... .... - .1 -.. ... 1 -.. ... 1 -.. ... 1 -... .1----

A- 1 2

10060000 

10060100 

10060101 

10060201 

10060301 

10060401 

10060501 

10060502 

10060503 

10060504 

10060505 

10060601 

10060602 

10060603 

10060604 

10060605

* tubesheet central section 

11151000 2 4 2 1 51054e-3 

11151100 0 1
* steam generator connections 

* -1- -1- ---------- 1---1

11002000 2 11 2 1 0.1625 

11002100 0 1 

11002101 10 0.203 

11002201 4 10 

11002301 0.0 10 

11002401 540.0 11 

11002501 115020000 0 1 1 0.708 1 

11002502 115170000 0 1 1 0.547 2 

11002601 -939 0 3949 1 0.708 1 

11002602 -939 0 3949 1 0.547 2 

11002701 0 0 0 0 2 

11002801 0.0 11.0 11.00.0 0.0 0.0 0.0 1.01 mrod3 

11002802 0.0 11.0 11.00.0 0.0 0.0 0.0 1.02 -mod3 

*--1---- 1--1- -1- -1

*.216 meter diameter piping *ý- -- 1-- -1- --- 1-- -1-- -1-- -1

11003000 7 11 2 1 0.108 

11003100 0 1 

11003101 10 0.1365 

11003201 4 10 

11003301 0.0 10 

11003401 540.0 11 

11003501 1250100000 1 1 1.00 1 

11003502 1300100000 1 1 0.457 2 

11003503 1400100000 1 1 0.502 3 

11003504 1450100000 1 1 1.4084 4 

11003505 1550100000 1 1 1.003 5 

11003506 1600100000 1 1 0.457 6 

11003507 170010000 0 1 1 0.514 7 

11003601 -939 0 3949 1 1.00 1 

11003602 -939 0 3949 1 0.457 2 

11003603 -939 0 3949 1 0.502 3 

11003604 -939 0 3949 1 1.4084 4 

11003605 -939 0 3949 1 1.003 5 

11003606 -939 0 3949 1 0.457 6 

11003607 -939 0 3949 1 0.514 7 

11003701 0 0 0 0 7 

11003801 0.0 11.0 11.00.0 0.0 0.0 0.0 1.01 -rmod3 

11003802 0.0 11.0 11.00.0 0.0 0.0 0.0 1.02 -rmod3 

11003803 0.0 11.0 11.00.0 0.0 0.0 0.0 1.03 -rmod3 

11003804 0.0 11.0 11.00.0 0.0 0.0 0.0 1.04 *mood3 

11003805 0.0 11.0 11.00.0 0.0 0.0 0.0 1.05 *rmod3 

11003806 0.0 11.0 11.00.0 0.0 0.0 0.0 1.06 *mood3 

11003807 0.0 11.0 11.00.0 0.0 0.0 0.0 1.07 *rmod3 

- -- -1- 1---- -- ---- -- 1 "steam generator plena -- 1--i-1------•--1-------------1-

11004000 2 11 3 1 0.6858 

11004100 0 1 

11004101 10 0.7747 

11004201 5 10 

11004301 0.0 10 

11004401 540.0 11 

11004501 1150300000 1 1 0.25 1 

11004502 1151600000 1 1 0.25 2 

11004601 -939 0 3949 1 0.25 1 

11004602 -939 0 3949 1 0.25 2 

11004701 0 0 0 0 2 

11004801 0.0 11.0 11.00.0 0.0 0.0 0.0 1.01 *mo~d3 

11004802 0.0 11.0 11.00.0 0.0 0.0 0.0 1.02 *mod 3 

11004901 0.0 11.0 11.00.0 00 0.0 0.0 1.02 *rmod3 

* reactor vessel heat structures 

the reactor vessel wall is not modelled above the nozzles. 

t the vessel to filler gap is assumed to insulate the vessel 

from the fillers, the vessel to filler gap is not modelled "at this elevation. 

* filler blocks inlet annulus top volume "station 264 to 277

12000000 

12000100 

12000101 

12000201 

12000301 

12000401 

12000501 

12000601 

12000701 

12000801

1 21 2 1 0.508 

0 1 

20 0.7264 

4 20 

0.0 20 

558.0 21 

2000100000 1 1 0.33 1 

0 0 0 1 0.33 1 

0 0.0 0.0 0.0 1 

0.0 11.0 11.00.0 0.0 0.0 0.0 1.01 *mod3

core support barrel 

* station 96.44 to 277

12001000 6 11 2 1 0.381 

12001100 0 1 

12001101 10 0.419 

12001201 4 10 

12001301 0.0 10 

12001401 558.0 11 

12001501 0 0 0 1 0.33 1 

12001502 0 0 0 1 0.424 2 

12001503 0 0 0 1 0.958 3 

12001504 0 0 0 1 0.958 4 

12001505 0 0 0 1 0.958 5 

12001506 0 0 0 1 0.958 6 

12001601 2000100000 1 1 0.33 1 

12001602 2050100000 1 1 0.424 2 

12001603 2100100000 1 1 0.958 3 

12001604 2100200000 1 1 0.958 4 

12001605 2100300000 1 1 0.958 5 

12001606 2100400000 1 1 0.958 6 

12001701 0 0.0 0.0 0.0 6 

12001901 0.0 11.0 11.00.0 0.0 0.0 0.0 1.01 -mod3 

12001902 0.0 11.0 11.00.0 0.0 0.0 0.0 1.02 -rmod3 

12001903 0.0 11.0 11.00.0 0.0 0.0 0.0 1.06 -mod3

"* filler blocks inlet annulus lower volume 

" station 247.3 to 264.0 

12050000 1 21 2 1 0.501 

12050100 0 1 

12050101 20 0.7264 

12050201 4 20 

12050301 0.0 20 

12050401 558.0 21 

12050501 2050100000 1 1 0.424 1 

12050601 223010000 0 1 1 0.424 1 

12050701 0 0.0 0.0 0.0 1 

12050801 0.0 11.0 11.0 0.0 0.0 0.0 0.0 1.01 * rod 3 

12050901 0.0 11.0 11.0 0.0 0.0 0.0 0.0 1.01 - mod 3 

"* downcomer and lower plenum "* station 67.7 to 247.3

12100000 6 21 2 1 

12100100 0 1 

12100101 20 0.7264 

12100201 4 20 

12100301 0.0 20 

12100401 558.0 21 

12100501 210010000 10000 

12100505 215010000 0 1 

12100506 2200100000 1 

12100601 2230200000 1 

12100602 2230300000 1 

12100603 2230400000 1 

12100604 2230500000 1 

12100605 2230600000 1 

12100606 223070000 0 1 

12100701 0 0.0 0.0 0

0.47

1 0.958 4 

0.36 5 

0.37 6 

0.958 1 

0-958 2 

0.958 3 

0.958 4 

0.36 5 

0.37 6

'0 6

A-1 3
12100801 0.0 11.0 1100.0 0.0 O0 0.0 1.04 *mod3 

12100802 0.0 11.0 11 00.0 0.0 0.0 0.0 1.05 'mod3 

12100803 0.0 11.0 11.00.0 0.0 0.0 0.0 1.06 mod3 

12100901 0.0 11.0 11.00.0 0.0 0.0 0.0 1.04 mod3 

12100902 0.0 11.0 1100.0 0.0 0.0 0.0 1.05 *mod3 

12100903 0.0 11.0 1100.0 0.0 0.0 0.0 1.06 mod3 

reactor vessel wall above station 178 - 5.50 inches thick 

* station 178 to 258 rv not modelled above bottom of nozzles 

12110000 3 11 2 1 07328 

12110100 0 1 

12110101 10 0.8725 

12110201 5 10 

12110301 0.0 10 

12110401 558.0 11 

12110501 2230100000 1 1 0.424 1 

12110502 2230200000 1 1 0.958 2 

12110503 2230300000 1 1 0.6500 3 

12110601 -939 0 3949 1 0424 1 

12110602 -939 0 3949 1 0.958 2 

12110603 -939 0 3949 1 0.6500 3 

12110701 0 0.0 0.0 0.0 3 

12110801 0.0 11ý0 1100.0 0.0 0.0 0.0 1.01 rmod3 

12110802 0.0 11.0 11.00.0 0.0 0.0 0.0 1.02 *rmod3 

12110803 0.0 11.0 11.00.0 0.0 0.0 0.0 1.0 3 * mod 3 

" reactor vessel wall bellow station 178 - 3.62 inches thick 

* station 67.7 to 178 

12120000 5 7 2 1 0.7328 

12120100 0 1 

12120101 6 0.8247 

12120201 5 6 

12120301 0.0 6 

12120401 558.0 7 

12120501 2230300000 1 1 0.308 1 

12120502 223040000 10000 1 1 0,958 3 

12120503 223060000 0 1 1 0.3600 4 

12120504 2230700000 1 1 0.37 5 

12120601 -939 0 3949 1 0.308 1 

12120602 -939 0 3949 1 0.958 3 

12120603 -939 0 3949 1 0.36 4 

12120604 -939 0 3949 1 0.37 5 

12120701 0 0.0 0.0 0.0 5 

12120801 0.0 11.0 1100.0 0.0 0.0 00 1.01 *mod3 

12120802 0.0 11.0 11.00.0 0.0 0.0 0.0 1.0 3 mod 3 

12120803 0.0 11.0 11.00.0 0.0 0.0 0.0 1.04 mod 3 

12120804 00 11.0 11.000 0.0 0.0 0.0 1.05 *mod3 

* reactor vessel bottom station 67.7 

12200000 1 11 1 1 00 

12200100 0 1 

12200101 10 0.092 

12200201 5 10 

12200301 0.0 10 

12200401 558.0 11 

12200501 2200100000 1 0 1.68 1 

12200601 -939 0 3949 0 1,68 1 

12200701 0 00 0 0 0.0 1 

12200801 0.0 11.0 11.000 00 0.0 0.0 1.01 'mod3 

12200901 0.0 11.0 11 00.0 0.0 0.0 0.0 1 01 'rmod3 

"flow skirt - core filler assembly station 96.44 to 261.13 

12250000 7 11 2 1 0.3 

12250100 0 1 

12250101 10 038 

12250201 4 10 

12250301 00 10 

12250401 558 0 11

12250501 

12250502 

12250503 

12250504 

12250505 

12250506 

12250507 

12250601 

12250602 

12250603 

12250604 

12250605 

12250606 

12250607 

12250701 

12250801 

12250802 

12250803 

12250804 

12250805 

12250806

2250100000 1 1 0.52 1 

2300100000 1 1 0.559 2 

2300200000 1 1 0.559 3 

2300300000 1 1 0.657 4 

2400100000 1 1 1.118 5 

2450100000 1 1 0.42 6 

2460100000 1 1 0.35 7 

0 0 0 1 0.52 1 

0 0 0 1 0.559 2 

0 0 0 1 0.559 3 

0 0 0 1 0.657 4 

0 0 0 1 1.118 5 

0 0 0 1 0.42 6 

0 0 0 1 0.35 7 

0 0.0 0.0 0.0 7 

0.0 11.0 11.00.0 0.0 0.0 oo 1.01 *rmod3 

0.0 11.0 11.00.0 0.0 0.0 0.0 1.03 *rmod3 

0.0 110 11.00.0 0.0 0.0 0.0 1.04 *rmod3 

0.0 110 11.00.0 0.0 0.0 0.0 1.05 'mod3 

0.0 11.0 11.00.0 0.0 0.0 0.0 1.06 *mod3 

0.0 11.0 11.00.0 0.0 0.0 0.0 1.07 *rmod3

lower core support structure station 96.44 to 116.91 

includes core support barrel lip, lower core support 

structure, and fuel module lower end boxes 

12260000 1 7 2 1 0.282 

12260100 0 1 

12260101 6 0.3 

12260201 4 6 

12260301 0.0 6 

12260401 558.0 7 

12260501 2250100000 1 1 0.52 1 

12260601 0 0 0 1 0.52 1 

12260701 0 0.0 0.0 0.0 1 

12260801 0.0 11.0 1i.oo.o 0.0 0.0 0.0 1.01 *mod3 

active core station 116.91 to 182.94 

12300000 3 10 2 1 0.0 

12300100 0 1 

12300101 5 4.647e-3 

12300102 1 4.742e-3 

12300103 3 5.359e-3 

12300201 1 5 

12300202 2 6 

12300203 3 9 

12300301 1.0 5 

12300302 0.0 9 

12300401 5580 10 

12300501 0 0 0 1 725.1 3 

12300601 2300100000 1 1 725.1 1 

12300602 2300200000 1 1 725.1 2 

12300603 2300300000 1 1 725.1 3 

12300701 1000 0.41209 0.0 0.0 1 

12300702 1000 0.44565 0.0 0.0 2 

12300703 1000 0.14226 0.0 0.0 3 

12300901 0.012411.0 11.00.0 0.0 0.0 0.0 1.03rmod3 

upper core support structure station 190.5 to 234.5 .. . ... ...... .............. 

12400000 1 7 2 1 0.282 

12400100 0 1 

12400101 6 0.31 

12400201 4 6 

12400301 0 0 6 

12400401 558.0 7 

12400501 2400100000 1 1 1.118 1 

12400601 0 0 0 1 1.118 1 

12400701 0 O0 0.0 0.0 1 

12400801 0.0 11.0 11.0 0 0.0 00 00 1 0 1 "mod 3 I...... .......... ..........

A- I 4
* fuel modules station 187.6 to 258.4 

12460000 1 5 1 1 0.0 

12460100 0 1 

12460101 4 0.01 

12460201 4 4 

12460301 0.0 4 

12460401 558.0 5 

12460501 2450100000 1 1 1.8 1 

12460601 2460100000 1 1 1.8 1 

12460701 0 0.0 0.0 1.8 1 

12460801 0.0 11.0 11.0 0.0 0.0 0.0 0.0 1.01 - mod 3 

12460901 0.0 11.0 11.00.0 0.0 0.0 0.0 1.01 *rmod3 

* core support barrel - upper plenum lower volume "* station 264 to 297.6 "* reactor vessel not modelled above bottom of nozzles 

* the vessel to filler gap is assumed to insulate the vessel 

" from the fillers, the vessel to filler gap is not modelled 

* at this elevation. 

12500000 1 11 2 1 0.381 

12500100 0 1 

12500101 10 0.419 

12500201 5 10 

12500301 0.0 10 

12500401 558.0 11 

12500501 2500100000 1 1 0.854 1 

12500601 0 0 0 1 0.854 1 

12500701 0 0.0 0.0 0.0 1 

12500801 0.0 11.0 11.00.0 0.0 0.0 0.0 1.01 *mod3 

"internals upper plenum 

12510000 2 5 1 1 0.0 

12510100 0 1 

12510101 4 0.005 

12510201 4 4 

12510301 0.0 4 

12510401 558.0 5 

12510501 2500100000 1 1 1.0 1 

12510502 2500100000 1 1 1.0 2 

12510601 0 0 0 1 1.0 2 

12510701 0 0.0 0.0 0.0 2 

12510801 0.0 11.0 11.00.0 0.0 0.0 0.0 1.02 *mod3 

' core support barrel - upper plenum top volume 

"station 297.6 to 325 "* reactor vessel not modelled above bottom of nozzles 

* the vessel to filler gap is assumed to insulate the vessel 

* from the fillers. the vessel to filler gap is not modelled 

"at this elevation. 

12501000 1 21 2 1 0.381 

12501100 0 1 

12501101 20 0.728 

12501201 5 20 

12501301 0.0 20 

12501401 558.0 21 

12501501 2500100000 1 1 0.712 1 

12501601 0 0 0 1 0.712 1 

12501701 0 0.0 0.0 0.0 1 

12501801 0.0 11.0 11.00.0 0.0 0.0 0.0 1.01 *mod3 

"upper head top plate station 325 

12550000 1 21 1 1 0.0 

12550100 0 1 

12550101 20 0.474 

12550201 5 20 

12550301 0.0 20 

12550401 558.0 21

12550501 250010000 0 1 1 0.712 1 

12550601 -939 0 3949 1 0.712 1 

12550701 0 0.0 0.0 0.0 1 

12550801 0.0 11.0 11.00.0 0.0 0.0 0.0 1.01 *rmod3 

"* broken loop hot leg piping heat structures 

13150000 2 11 2 1 0.0515 

13150100 0 1 

13150101 10 0.0705 

13150201 4 10 

13150301 0.0 10 

13150401 540.0 11 

13150501 315010000 0 1 1 0.4054 1 

13150502 3150200000 1 1 0.5265 2 

13150601 -939 0 3979 1 0.4054 1 

13150602 -939 0 3979 1 0.5265 2 

13150701 0 0 0 0 2 

13150801 0.0 11.0 11.0 0.0 0.0 0.0 0.0 1.0 1 * mod 3 

13150802 0.0 11.0 11.00.0 0.0 0.0 0.0 1.02 "mod3 

13151000 1 11 2 1 0.0550 

13151100 0 1 

13151101 10 0.0705 

13151201 4 10 

13151301 0.0 10 

13151401 540.0 11 

13151501 3150900000 1 1 0.0120357 1 

13151601 -939 0 3979 1 0.0120357 1 

13151701 0 0 0 0 1 

13151801 0.0 11.0 11.0 0.0 0.0 0.0 0.0 1.0 1 *mod 3 

13152000 1 11 2 1 0.0660 

13152100 0 1 

13152101 10 0.0840 

13152201 4 10 

13152301 0.0 10 

13152401 540.0 11 

13152501 315110000 0 1 1 0.00836 1 

13152601 -939 0 3979 1 0.00836 1 

13152701 0 0 0 0 1 

13152801 0.0 11.0 11.00.0 0.0 0.0 0.0 1.01 mod3 

13153000 6 11 2 1 0.1835 

13153100 0 1 

13153101 10 0.2285 

13153201 4 10 

13153301 0.0 10 

13153401 540.0 11 

13153501 315030000 10000 1 1 0.108 6 

13153601 -939 0 3979 1 0.108 6 

13153701 0 0 0 0 6 

13153801 0.0 11.0 11.00.0 0.0 0.0 0.0 1.06 *mod3 

13154000 1 11 2 1 0.1285 

13154100 0 1 

13154101 10 0.1620 

13154201 4 10 

13154301 0.0 10 

13154401 540.0 11 

13154501 3151200000 1 1 0.0525 1 

13154601 -939 0 3979 1 0.0525 1 

13154701 0 0 0 0 1 

13154801 0.0 11.0 11-00.0 0.0 0-0 0.0 1.01 "mod3 

13155000 1 11 2 1 0.1420 

13155100 0 1 

13155101 10 0.1780 

13155201 4 10 

13155301 0.0 10 

13155401 540.0 11 

13155501 3151000000 1 1 0.04890571

A- 1 5
13155601 -939 0 3979 1 0.04890571 

13155701 0 0 0 0 1 

13155801 0.0 11.0 11.00.0 0.0 0.0 0.0 1.01 rod3 

. nozzle piping 

13000000 3 11 2 1 0.1420 

13000100 0 1 

13000101 10 01780 

13000201 4 10 

13000301 0.0 10 

13000401 540.0 11 

13000501 3000100000 1 1 0.876 1 

13000502 3050100000 1 1 0.698 2 

13000503 3100100000 1 1 1.424 3 

13000601 -939 0 3979 1 0.876 1 

13000602 -939 0 3979 1 0698 2 

13000603 -939 0 3979 1 1.424 3 

13000701 0 0 0 0 3 

13000801 0.0 11.0 11.0 0.0 0.0 0.0 0.0 10 1 mod 3 

13000802 0.0 11.0 11.00.0 0.0 0.0 0.0 1.02 mod3 

13000803 0.0 11.0 11.0 0.0 0.0 0.0 0.0 10 3 mod 3 

* broken loop cold leg

nozzle piping

13350000 

13350100 

13350101 

13350201 

13350301 

13350401 

13350501 

13350502 

13350503 

13350601 

13350602 

13350603 

13350701 

13350801 

13350802 

13350803

3 11 2 1 0.1420 

0 1 

10 0.1780 

4 10 

0.0 10 

540.0 11 

3350100000 1 1 -0.7495 1 

3400100000 1 1 0.698 2 

3450100000 1 1 0.974 3 

-939 0 3949 1 0.7495 1 

-939 0 3949 1 0.698 2 

-939 0 3949 1 0.974 3 

0 0 0 0 3 

00 11.0 11.00.0 0.0 0.0 0.0 1.0 1 mod 3 

0.0 11.0 11.00.0 0.0 00 00 1.02 'mod3 

0.0 11.0 11.00.0 0.0 0.0 00 103 "mod3

13501000 1 11 2 1 0.0550 

13501100 0 1 

13501101 10 0.1780 

13501201 4 10 

13501301 0.0 10 

13501401 540.0 11 

13501501 3500100000 1 1 0.488 1 

13501601 -939 0 3949 1 0488 1 

13501701 0 0 0 0 1 

13501801 0.0 110 11.00.0 0.0 00 0.0 1.01 "rod3 

13502000 1 11 2 1 00865 

13502100 0 1 

13502101 10 0.1095 

13502201 4 10 

13502301 0.0 10 

13502401 540.0 11 

13502501 3500200000 1 1 1 6085 1 

13502601 -939 0 3949 1 1.6085 1 

13502701 0 0 0 0 1 

13502801 0.0 11.0 11.00.0 00 00 0.0 1.01 *rmod3 ...oooo.o.o~ o....I............... oo °°, .... ° ..... °, .....*.**. o...... 

* reflood assist piping and valves [rabvs] 

13700000 4 11 2 1 0 111 

13700100 0 1 

13700101 10 01365 

13700201 4 10

13700301 0.0 10 

13700401 540.0 11 

13700501 3700100000 1 1 2.00 1 

13700502 3750100000 1 1 1.105672 

13700503 3800100000 1 1 1.101804 3 

13700504 3850100000 1 1 3.042014 

13700601 -939 0 3979 1 2.00 1 

13700602 -939 0 3979 1 1.105672 

13700603 -939 0 3949 1 1.101804 3 

13700604 -939 0 3949 1 3.04201 4 

13700701 0 0 0 0 4 

13700801 0.0 11.0 11.0 0.0 0.0 0.0 0.0 1.01 mod 3 

13700802 0.0 11.0 11.00.0 00 0.0 0.0 1-02 mod3 

13700803 0.0 11.0 11.00.0 00 0-0 0.0 1.03 mod3 

13700804 0.0 11.0 11.00.0 0.0 0.0 0.0 1.04 mod3 

pressunzer heat structures

"vessel bottom 

- - - 1 - - 1 1 1 --- 

14151000 1 11 1 1 0.0 

14151100 0 1 

14151101 10 0.0762 

14151201 5 10 

14151301 0-0 10 

14151401 617.0 11 

14151501 4150100000 1 1 0.362 1 

14151601 -939 0 3969 1 0.362 1 

14151701 0 0 0 0 1 

14151801 0.0 11.0 11.00.0 0.0 0.0 0.0 1.01 *mod 3 "- --- 1- -- 1 -- -- -- 1-- -1- -1

* vessel sides - large diameter section * --- -- 1- ... 1-- -- 1--1 -1- 1- ---1 

14152000 7 11 2 1 0.42291 

14152100 0 1 

14152101 10 0.49911 

14152201 5 10 

14152301 0.0 10 

14152401 617.0 11 

14152501 4150100000 1 1 0.224 1 

14152502 415020000 10000 1 1 0.403 3 

14152503 415040000 10000 1 1 0.207 5 

14152504 415060000 10000 1 1 0.1705 7 

14152601 -939 0 3969 1 0.224 1 

14152602 -939 0 3969 1 0.403 3 

14152603 -939 0 3969 1 0.207 5 

14152604 -939 0 3969 1 0.1705 7 

14152701 0 0 0 0 7 

14152801 0.0 11.0 1100.0 0.0 0.0 0.0 1.07 rmod3 

vessel sides - small diameter section 

14162000 1 11 2 1 0.2032 

14162100 0 1 

14162101 10 0.3683 

14162201 5 10 

14162301 0.0 10 

14162401 617.0 11 

14162501 4150800000 1 1 0.118 1 

14162601 -939 0 3969 1 0118 1 

14162701 0 0 0 0 1 

14162801 0.0 11.0 11.00.0 00 0.0 0.0 1.01 *mod3 ........ oooo°°...o...o °.o.........°°N*•o........... ...

* pressurizer heaters 

14172000 12 9 2 1 00 

14172100 0 1 

14172101 3 40132e-3 

14172102 2 4.3942e-3 

14172103 1 5.6642e-3 

14172104 2 8.3820e-3 

14172201 7 3

A- 1 6
14172202 8 5 

14172203 7 6 

14172204 4 8 

14172301 0.0 3 

14172302 1.0 5 

14172303 0.0 8 

14172401 617.6 9 

14172501 0 0 0 1 0.6096 12 

14172601 4150200000 1 1 0.6096 12 

14172701 417 1.0 0.0 0.0 9 -cydi 

14172702 418 1.0 0.0 0.0 12 *backu 

14172901 1.6764e-2 11.0 11.0 0.0 0.0 0.0 0.0 1.0 12 * mod 

3 

"pressurizer cycling heaters *- -1-- 1• - 1- -1- -1- -- 1

* pressurizer backup heaters *- -1• - 1- -1- -1-1 -1• - 11 

14201000 1 11 2 1 0.2032 

14201100 0 1 

14201101 10 0.3683 

14201201 5 10 

14201301 0.0 10 

14201401 617. 11 

14201501 4200100000 1 1 0.118 1 

14201601 -939 0 3969 1 0.118 1 

14201701 0 0 0 0 1 

14201801 0.0 11.0 11.0 0.0 0.00.0 0.0 1.0 1 mod3 

14202000 1 11 1 1 0.0 

14202100 0 1 

14202101 10 0.18415 

14202201 5 10 

14202301 0.0 10 

14202401 617. 11 

14202501 4200100000 1 1 0.13 1 

14202601 -939 0 3969 1 0.13 1 

14202701 0 0 0 0 1 

14202801 0.0 11.0 11.00.0 0.0 0.0 0.0 1.01 mod3 

"steam generator heat structures 

* shroud secondary side steam generator -upper section 

"" -1--1- -- ---- -1- -11

15000000 3 4 2 1 0.3048 

15000100 0 1 

15000101 3 0.3143 

15000201 5 3 

15000301 0.0 3 

15000401 540.0 4 

15000501 5000100000 1 1 0.7725 1 

15000502 5050100000 1 1 0.7725 2 

15000503 5100100000 1 1 0.152 3 

15000601 5200100000 1 1 0-7725 1 

15000602 5151400000 1 1 0.7725 2 

15000603 5151300000 1 1 0.152 3 

15000701 0 0.0 0.0 0.0 3 

15000801 0.0 11.0 1100.0 0.0 0.0 0.0 1.03 *mod3 

15000901 0.0 11.0 11.00.0 0.0 0.0 0.0 1.03 *mod3 ".- -- I-I --- 1--- -- 1-- -1-- -1-- -- 1-

* shroud - lower section 

* -- -- 1-- ---... 1-- -- 1-- -1---1--- -- 1-

15150000 7 4 2 1 0.6445 

15150100 0 1 

15150101 3 0.6572 

15150201 5 3 

15150301 0.0 3 

15150401 540.0 4 

15150501 510010000 0 1 1 0.152 1 

15150502 5150100000 1 1 0.7113 2 

15150503 515020000 10000 1 1 0.355654 

15150504 515040000 10000 1 1 0.2371 7

15150601 5151300000 1 1 0.152 1 

15150602 5151200000 1 1 0.7113 2 

15150603 515110000-10000 1 1 0.355654 

15150604 515090000-10000 1 1 0.2371 7 

15150701 0 0 0 0 7 

15150801 0.0 11.0 11.00.0 0.0 0.0 0.0 1.07 *rmod3 

15150901 0.0 11.0 11.00.0 0.0 0.0 0.0 1.07 *rmod3 

""-- -"-- -- 1 -1- -1--1 "1- "vessel wall 

""- -1-- -- 1- -1- - - 11--1

15300000 11 10 2 1 0.7112 

15300100 0 1 

15300101 9 0.765165 

15300201 5 9 

15300301 0.0 9 

15300401 530.0 10

15300501 5300100000 1 

15300502 5250100000 1 

15300503 5000100000 1 

15300504 5050100000 1 

15300505 5100100000 1 

15300506 5150100000 1 

15300507 515020000 10000 

15300508 51504000010000

15300601 -939 0 3959 

15300602 -939 0 3959 

15300603 -939 0 3959 

15300604 -939 0 3959 

15300605 -939 0 3959 

15300606 -939 0 3959 

15300607 -939 0 3959

0.762 1 

0.762 2 

0.718 3 

0.718 4 

0.518 5 

0.7102 6 

1 0.3551 8 

1 0.23673 11

0.762 1 

0.762 2 

0.718 4 

0.518 5 

0.7102 6 

0.3551 8 

0.2367311

15300701 0 0.0 0.0 0.0 11 

15300801 0.0 11.0 11.00.0 0.0 0.0 0.0 1.011 "mod3 

heat structure thermal property data 

20100100 tbllfctn 1 1 * uo2 

20100200 tbl/fctn 1 1 * gap 

20100300 tblfctn 1 1 * zr 

20100400 tbl/fctn 1 1 *s-steel 

20100500 c-steel 

20100600 tb•/tcn 1 1 "inconel 600 

20100700 tbl/fctn 1 1 * mgo 

20100800 tb/fctn 1 1 * nicr "*-- -1-- -- 1------ -- --- -- 1

* uo2 - thermal conductivity 

*-- -1-- -1------- -- 1----•---1

20100101 2.7315e2 8.44 

20100102 4.1667e2 6.46 

20100103 5.3315e2 5.782385 

20100104 6.99817e2 4.633177 

20100105 8.66483e2 3.880307 

20100106 1.03315e3 3.357625 

20100107 1.08871e3 3.155129 

20100108 1.19982e3 2.983787 

20100109 128315e3 2.836674 

20100110 1.36648e3 2.713792 

20100111 1.53315e3 2.521680 

20100112 1.61648e3 2.448990 

20100113 1.69982e3 2.391875 

20100114 1.97759e3 2.289762 

20100115 2.25537e3 2.307069 

20100116 2.53315e3 2.433413 

20100117 2.81093e3 2.661870 

20100118 3.08871e3 2.994171 "- . ... ... 1.-.. 1 . -.. - -.. .. .. .1 -

A-1 7

1 1 

1 

1 

1 

1 

1 

1

1 1 

1 

1 

1 

1 

1
"gap - thermal conductivity --- -1-- --- 1-- -- 1--i-1- -1--- ---..1---

20100201 273.15 014 

20100202 590.0 0.24 

20100203 810.0 0.29 

20100204 1090.0 0.36 

20100205 1370.0 0.42 

20100206 3260.0 0.75 

*- -- 1--- --- - 1--- -- 1- -- 1

* zircaloy-4 - thermal conductivity from matpro 

*--1--- -1--- -1- -1-- -1- -- 1

20100301 380.4 13.6 

20100302 469.3 14.6 

20100303 577.6 15.8 

20100304 685.9 17.3 

20100305 774.8 18.4 

20100306 872.0 19.8 

20100307 973.2 21.8 

20100308 1073.2 23.2 

20100309 1123.2 254 

20100310 1152.3 24.2 

20100311 1232.2 25.5 

20100312 1331.2 26.6 

20100313 1404.2 28.2 

20100314 1576.2 33.0 

20100315 1625.2 36.7 

20100316 1755.2 41.2 

20100317 2273.2 55.0 

""- ------- 1 -- 1---1

s-steel - thermal conductivity "-- ---- 1-- -- 1-- I-- ...----- 1-- -- 1

20100401 273-15 12.98 

20100402 1199.82 25.1 

*- -- 1 --- -1-- -1 --- -1 -- 1 . -1- .

inconel-600 - thermal conductivity "-- -1--i-1- -- 1-- ---1-.. -- 1----

20100601 366-5 13.85 

20100602 477.6 15.92 

20100603 5887 18.17 

20100604 700.0 20.42 

20100605 810-9 22.50 

20100606 922.0 24.92 

20100607 1033.2 2683 

20100608 11443 29.42 

20100609 1477.6 36.06 "--1---i-- -- 1-- 1--- ---- --- 1...1- -- 1--

* uo2 - volumetric heat capacity "---1----- 1-----------------1- -.. ---

20100151 2.73150e2 2.310427e6 

20100152 3.23150e2 2.571985e6 

20100153 3.73150e2 2.746357e6 

20100154 6.7315e2 3.138694e6 

20100155 1.37315e3 3.443844e6 

20100156 1.77315e3 3.531030e6 

20100157 1.97315e3 3.792588e6 

20100158 2.17315e3 4228518e6 

20100159 2.37315e3 4.882412e6 

20100160 2.67315e3 6.015829e6 

20100161 2.77315e3 6.320980e6 

20100162 2.87315e3 6.582538e6 

20100163 2.97315e3 6.713317e6 

20100164 3.11315e3 6.800503e6 

20100165 4.69982e3 6.800503e6 "- .. 1.. .. .. 1.... .1-----1 -.. . .1-.. ... 1---

* gap - volumetric heat capacity "- . . .. 1 .. . .. 1 -... . 1 -.... 1 .. -...1 -.. ... 1--... 

20100251 273.15 54 

20100252 3260.0 5.4 ----- --- 1 ....... 1 . -..... 1 ........ 1 ----.... 1 ---- 1--

zircaloy-4 - volumetric heat capacity from matpro " - 1 --...... 1 ----1- -1 -- --.... 1 ........ 1 ---

20100351 255.4 1.904e6

20100352 1077.6 2.312e6 

20100353 1185.9 5.712e6 

20100354 1248.4 2.311e6 

20100355 2199.8 2.312e6 

*----1-- 1---- --- 1---- --- -1

* s-steel - volumetric heat caoacitv "- -1--i- -1--- ----- i- -1--

20100451 273.15 3.83e6 

20100452 366.5 3.83e6 

20100453 1366.5 5.376e6 

*--1- -- 1- -1-- ----1--- -1--1

i nconel-600 - volumetnc heat capacity 

*--1-- -1- -1- --- 1- -1- -1

20100651 366.5 3.908+6 

20100652 477.6 4.084+6 

20100653 588.7 4.260+6 

20100654 700.0 4.436+6 

20100656 810.9 4.665+6 

20100657 922.0 4.929+6 

20100658 1033.2 5.105+6 

20100659 1477.6 5,727+6 

*-- -- -1-- -1- -- -1-- -

magnesium oxide - thermal conductivity 

*- -1--i- -i- --- 1--i- -1---

20100701 373.15 0.2451 

20100702 422.04 0.2405 

20100703 477.59 0.2352 

20100704 533.15 02300 

20100705 588.71 0.2249 

20100706 644ý26 0.2196 

20100707 699,82 0.2143 

20100708 755.37 0.2091 

20100709 81093 0.2039 

20100710 866.48 0.1987 

20100711 922.04 0.1934 

20100712 977.59 0.1882 

20100713 1033.15 0.1830 

20100714 1088.71 0.1777 

20100715 1144.260.1725 

20100716 1199.82 0.1673 

20100717 1255.37 0.1621 

20100718 1310.93 0.1568 

20100719 1366.480.1516 

20100720 1422.040.1464 

20100721 1477.59 0.1412 

20100722 1533.15 0.1359 

20100723 1588.71 0.1307 

20100724 1644.260.1255 

20100725 1699.82 0.1203 

20100726 1755.37 0.1150 

20100727 1810.93 0.1098 

20100728 1866.48 0.1046 

20100729 1922.040.0993 

20100730 5000.00 0.0993 "-- -1-- -1----- ----- -1...- ---- 1-- .. - 1--

magnesium oxide - volumetric heat capacity * - 1-1- 1- -- I--1---1- ... ---.. 1---..-1--

20100751 373.15 2033.52 

20100752 422.04 2004.59 

20100753 477.59 1917.74 

20100754 533.15 1938.87 

20100755 588.71 1906.01 

20100756 644.26 1873.15 

20100757 699.82 1840.29 

20100758 755.37 1807.43 

20100759 810.93 177456 

20100760 866.48 1741.70 

20100761 922.04 1708.84 

20100762 977.59 1675.96 

20100763 1033.15 1643.11 

20100764 1088.71 161025 

20100765 1144.26 1577.39

A- I S
20100766 1199.82 1544.53 

20100767 1255.37 1511.67 

20100768 1310.93 1478.80 

20100769 1366.48 1445.94 

20100770 1422.04 1413.08 

20100771 1477.59 1380.22 

20100772 1533.15 1347.35 

20100773 1588.71 1314.49 

20100774 1644.26 1281.63 

20100775 1699.82 1248.77 

20100776 1755.37 1215.90 

20100777 1810.93 1183.04 

20100778 1866.48 1150.18 

20100779 1922.04 1117.32 

20100780 5000.00 1117.32 

-1- --- -- ---- 1--1---1- "nichrome - thermal conductivity 

*- -1---- -- ---------- 1--1

20100801 373.15 1.1163 

20100802 1922.04 1.1163 

20100803 5000.00 1.1163 *-- -- 1- -1-- -- 1-- -1-- -- 1 --

1

•nichrome 

- volumetric heat capacity 

*-- -1-- ---1--- -- -- --

1

20100851 373.15 2180.80 

20100852 1922.04 2180.80 

20100853 500.00 2180.80 

general table 

° -- 1--i-----------•-----1------1-

"pressurizer cycling heaters 

- -1-.-i-- 111- -1- 

- 1I -1

20241700 power 

20241701 0.0 0.0 

20241702 60. 0.0 • 1---1--i-1-i- --- 1 1--im--

pressurizer backup haters 

* -1-- -1 1-1-- -1-- -1-- -1-

20241800 power 

20241801 0.0 0.0 

20241802 60 0.0 

•- -1--1i-- -1--1--1--1

"scram reactivity data 

*-- -1--i---- -- -- 1--11

20260900 reac-t 609 

20260901 0.0 0.0 

20260902 0.5 -0.5 

20260903 0.59 -3.13 

20260904 0.65 -3.95 

20260905 0.75 -6.27 

20260906 0.83 -8.72 

20260907 0.90 -12.00 

20260908 0.97 -17.12 

20260909 1.125 -20.67 

20260910 1.213 -22-10 

20260911 1.3 -22.78 

20260912 1.4 -23.17 

20260913 1.6 -23.32 

20260914 600 -23.32 

reactor power table 

20290000 power 

20290001 0.0 48.7e6 

n- -1e-1 --- --ht1- -- -- 1--- -1- --- 1- *environmental heat loss boundary temperature

20293900 temp 

20293901 0.0 311.0 

* reactor vessel environmental loss heat xfer coefficient 

""--1- -1- -- 1- -1- -- 1 

-

20294900 htc-t 

20294901 0.0 13.450 "----1-- -- 1-- --------- ----- --

1

"steam generator environmental loss heat xfer coefficient "*--1 -l -- 1-- -1I- -11- -- 1- -- 1 

20295900 htc-t 

20295901 0.0 3.385 

*-- -1- -1--1-- -1

pressurizer generator environmental loss heat xfer coefficient 

..-- 1 -1---1 -- 1 -- 1- 

- -- 1 -- 1 

20296900 htc-t 

20296901 0.0 3.019 

*- --- -- 1-- -1- 

- 1- 

- 1- -1

"blhl environmental loss heat xfer coefficient 

*---- ----------- ----- -1

20297900 htc-t 

20297901 -1.0 0.0 

20297902 0.0 13.450 ",-- -1-- -1-- -1-- -1-- -1- --

1

• core collapsed liquid level 

*v-- --- 1-- -- 1-- -1- -1

20255000 normarea 0 1.0 1.0 

20255001 0.0 9.25e-4 

20255002 9.25e-4 9.25e-4 

20255003 1.0 1.0 *-- -- 1--- --------------------------- 1-

"power curve (?) *--1--- -- 1----1------------------1-

20290000 power 609 

20290001 0-0 48.9ea-6 

20290002 0.15 43.032e6 

20290003 0.3 37.164e6 

20290004 0.6 28.362e6 

20290005 085 8.6064e6 

20290006 1.0 5.99538e6 

20290007 1.3 4.89e6 

20290008 2.0 4.274e6 

20290009 4.0 3.7060332e6 

20290010 7.0 3.1296e6 

20290011 10.0 2.93458e6 

20290012 25.0 2.28548e6 

20290013 65.0 1.7115e6 

20290014 100.0 1-5425994e6 

20290015 2500 1.232769e6 

20290016 650.0 0-91932e6 

20290017 1000.0 0.80196e6 

20290018 1500.0 0.6846e6 

20290019 3000.0 0.5379e6 

20290020 5000.0 0.44988e6 

• reactor kinetics data 

30000000 point 

30000001 gamma-ac 48.7e+6 0.0 348.43 1.0 0.556 

30000002 ans79-1 

shoud not be changed for transient 

* delayed neutron constants .~l . ......... t .. t.. *t- • t t-j ~ -*t ti-l

30000101 0.0349 

30000102 0.2035 

30000103 0.1848 

30000104 0.4046 

30000105 0.1401

0.01275 

003177 

0.1181 

0.3160 

1.402

A-1 

9
30000106 00321 3.914 

power history 

30000401 4.87e+7 70. hr 

* reactivity curve numbers 

30000011 609 

"moderator density reactivity table 

30000501 0.62626e+3 -4.4769 

30000502 0.66396e+3 -3.2923 

30000503 0.71617e+3 -1.5692 

30000504 0.76112e+3 -0.1692 

30000505 0.76837e+3 0.04615 

30000506 0.79157e+3 0.6923 

30000507 0.81188e+3 1.2398 

30000508 0.86263e+3 2.2415 

30000509 0.93804e+3 3.9231 

30000510 0.99749e+3 5.1077 

"doppler reactivity table 

30000601 293.16 1.375 

30000602 338.72 1.125 

30000603 422.05 0-682 

30000604 477.60 0-419 

30000605 505.38 0.274 

30000606 570+72 0.000 

30000607 588.72 -0.075 

30000608 695.83 -0.526 

30000609 922-05 -1.386 

30000610 1310.94 -2.543 

30000611 1810.94 -3.865 

30000612 2088.72 -4.502 

30000613 2499.83 -5.392 

30000614 3027.60 -6.417 . volume weighting factors 

moderator temperature feedback 

"30000701230010000 0 0314930.0 "30000702 230020000 0 031493 0.0 

"30000703 230030000 0 0.37014 0.0 

doppler feedback 

'30000801 2300001 0 0 43153 0.0 

•30000802 2300002 0 051686 0.0 

°30000803 2300003 0 0,05161 0.0 

mtc curve -..... monitor 

20593300 mtcmon function 1.0 0 0 

20593301 rho 230020000 933 

20293300 reac-t 

20293301 0 62626e+3 -9 2 

20293302 0.66396e+3 -3.8 

20293303 684,0 -1.5 

20293304 692 0 -0 7 

20293305 707T0 -0.2 

20293306 071819e+3 0.0 

20293307 737 0 0 5 

20293308 744 0 0 6 

20293309 0 76112e+3 07

20293310 0.76837e+3 0.8 

20293311 0.79157e+3 1.05 

" -1 "_ .--- --- 1---- -- 1--- ----- --

1

power from experimental data 

*- -- 1-- -1-- -1-- -1--- -1--- -1

20270000 power 530 

20270001 1.08400000e+00 4.878200307e+07 

20270002 3.48400000e+00 4.886505087e+07 

20270003 4.68400000e+00 4.890413219e+07 

20270004 7.08400000e+00 4.895786901e&07 

20270005 9.48400000e+00 4.909465363e+07 

20270006 1.18840000e+01 4.874292175e+07 

20270007 1.42840000e+01 4.845469701e+07 

20270008 1.66840000e+01 4.843515635e+07 

20270009 1.90840000e+01 4.822020909e+07 

20270010 2.14840000e+01 4.790755853e+07 

20270011 2.38840000e+01 4.788313271e+07 

20270012 2.62840000e+01 4.768772610e+07 

20270013 2.86840000e+01 4.751186016e+07 

20270014 3.10840000e+01 4.708685081e+07 

20270015 3.34840000e+01 4.712104696e+07 

20270016 3.58840000e+01 4.690609970e+07 

20270017 3.82840000e+01 4.695006619e+07 

20270018 4.06840000e+01 4.672534860e+07 

20270019 4.30840000e+01 4.704288432e+07 

20270020 4.54840000e+01 4.659344914e+07 

20270021 4.78840000e+01 4.664230079e+07 

20270022 5.02840000e+01 4.659344914e+07 

20270023 5.26840000e+01 4.620263594e+07 

20270024 5.50840000e+01 4.571900460e+07 

20270025 5.74840000e+01 4.442932104e+07 

20270026 5.98840000e+01 4.379913475e-07 

20270027 6.22840000e+01 4.278790559e+07 

20270028 6.46840000e+01 4.149822202e+07 

20270029 6.70840000e+01 4.057004067e+07 

20270030 6.94840000e+01 3.890908456e+07 

20270031 7.18840000e+01 3.757054935e-,07 

20270032 7.42840000e+01 3.564090916e+07 

20270033 7.66840000e-01 3.282216895e+07 

20270034 7-90840000e+01 3.039424193e+07 

20270035 8.14840000e+01 2.798097041e+07 

20270036 8.38840000e+01 2.556281373e+07 

20270037 8.62840000e+01 2.344265211e+07 

20270038 8.86840000e+01 2+193313611e+07 

20270039 9.10840000e+01 2.060437123e+07 

20270040 9.34840000e+01 1.918278821e+07 

20270041 9.58840000e+01 1.834742499e+07 

20270042 9.82840000e+01 1.717498538e+07 

20270043 1.00684000e+02 1.594880896e+07 

20270044 1.03084000e+02 1.494735014e+07 

20270045 1,05484000e+02 1.385795834e+07 

20270046 1.07884000e+02 1.279299236e+07 

20270047 1.10284000e+02 1.198694013e+07 

20270048 1.12684000e+02 1.132255769e+07 

20270049 1.15084000e+02 1,072168239e+07 

20270050 1.17484000e+02 1.011103676e+07 

20270051 1.19884000e+02 9.471080147e+06 

20270052 1.22284000e+02 8.943482324e+06 

20270053 1 .24684000e+02 8 489161978e+06 

20270054 1.27084000e+02 8.059267456e÷06 

20270055 1.29484000e+02 7.595176779e+06 

20270056 1.31884000e+02 7.277641052e+06 

20270057 1 34284000e+02 6.906368511e+06 

20270058 1.36684000e+02 6.554636629e+06 

20270059 1.39084000e+02 6.305493213e+06 

20270060 1 .41484000e+02 6.046579467e+06 

20270061 1.43884000e+02 5.699732751e+06 

20270062 1.46284000e+02 5.470129995e+06 

20270063 1 48684000e+02 5.318689879e+06 

20270064 1 51084000e+02 5.030465143e+06 

20270065 1.53494000e+02 4.810632717e+06

A-2 0
20270066 1.55884000e+02 4.629881611e+06 

20270067 1.58284000e+02 4.405164020e+06 

20270068 1.60684000e+02 4.214642584e+06 

20270069 1.63084000e+02 4.014350818e+06 

20270070 1.65484000e+02 3.901992023e+06 

20270071 1.67884000e+02 3.716355752e+06 

20270072 1.70284000e+02 3.589341462e+06 

20270073 1.73884000e+02 3.349968376e+06 

20270074 1.75084000e+02 3.276690900e+06 

20270075 1.77484000e+02 3.095939795e+06 

20270076 1.79884000e+02 3.086169465e+06 

20270077 1.81084000e+02 3.017777154e+06 

20270078 1.83484000e+02 2.807715058e+06 

20270079 1.85884000e+02 2.695356263e+06 

20270080 1.87084000e+02 2.656274943e+06 

20270081 1.89484000e+02 2.568341972e+06 

20270082 1.91884000&+02 2.495064497e+06 

20270083 1.94284000e+02 2.382705702e+06 

20270084 1.95484000e+02 2.328968886e+06 

20270085 1.96684000e+02 2.299657896e+06 

20270086 1.97884000e+02 2.260576576e+06 

20270087 1.99084000e+02 2.211724926e+06 

20270088 2.00284000e+02 2.182413936e+06 

* control variables 

* steam generator downcomer collapsed liquid level 

1--1- -1--- -1--- -1--i-- -1

20500100 sglvl sum 1.0 0.0 1 

20500101 0.0 0.718 voidf 500010000 

20500102 0.718 voidf 505010000 

20500103 0.518 voidf 510010000 

20500104 07102 voidf 515010000 

20500105 0.3551 voidf 515020000 

20500106 0.3551 voidf 515030000 

20500107 0.2367333 voidf 515040000 

20500106 0.2367333 voidf 515050000 

20500109 0.2367333 voidf 515060000 

*--1------------------------------1

pressurizer collapsed liquid level 

-- 1------------------------------1

20500200 pzrlvl sum 1.0 0.0 13 0.0 1.83 

20500201 0.0 0.224 voidf 415010000 

20500202 0.403 voidf 415020000 

20500203 0.403 voidf 415030000 

20500204 0.207 void! 415040000 

20500205 0.207 voidW 415050000 

20500206 0.1705 voidf 415060000 

20500207 0.1705 voidf 415070000 

20500208 0.118 voidf 415080000 

20500209 0.118 voidf 420010000 *--- --- 1- -- 1-- -- 1- -- 1-- -1-- -1-

core collapsed liquid level 

-- -1---- -- -------- -- 1

20500300 rvlvl sum 1.0 0.0 1 

20500301 0.0 0.712 voidf 250010000 

20500302 0.854 voidf 250010000 

20500303 0.843 voidf 245010000 

20500304 1.118 voidf 240010000 

20500305 0.657 voidf 230030000 

20500306 0.559 voidf 230020000 

20500307 0.559 voidf 230010000 

20500308 0.520 voidf 225010000 

20500309 0.360 voidf 215010000 

20500310 0370 voidf 220010000 

"hot leg intact loop 

20504100 pcsvoll sum 1.0 00 1 

20504101 0.0 .09746482 rho 100010000

20504102 0.1035956 rh0 105010000 

20504103 3.0300e-2 rho 110010000 

20504104 9.00OOe-2 rho 115010000 

20504105 5.7000e-2 rho 115020000 

*- . . 1-11 . . . . . 1 . . 1 ..-1

steam generator 

*1---- -1- -1- -1- -1

20504200 pcsvol2 sum 1.0 0.0 1 

20504201 0.0 0.3350000 rho 115030000 

20504202 0.1611170 rho 115040000 

20504203 0.1611170 rho 115050000 

20504204 6.7950e-2 rho 115060000 

20504205 6.7950e-2 rho 115070000 

20504206 1.61117-1 rho 115080000 

20504207 1.61117-1 rho 115090000 

20504208 3.3500e-1 rho 115100000 

* sg-pump piping "*-- --- - 1- --- -•1 -1 1- --- 1

20504300 pcsvol3 sum 1.0 0.0 1 

20504301 0.0 4.37000-2 rho 115170000 

20504302 4.62000-2 rho 115180000 

20504303 3.54406-2 rho 115190000 

20504304 4.81840-2 rho 120010000 

20504305 6.13000-2 rho 125010000 

20504306 1.89000-2 rho 130010000 

20504307 6.13000-2 rho 155010000 

20504308 1.89000-2 rho 160010000 

I---1--------1-----------1- -1

cold leg intact loop 

"--1--1---1----1---1-•--1

20500400 pCsvol4 sum 1.0 0.0 1 

20500401 0.0 9.90000-2 rho 135010000 

20500402 1.83732-2 rho 140010000 

20500403 6.33000-2 rho 145010000 

20500404 3.14844-2 rho 150010000 

20500405 9.90000-2 rho 165010000 

20500406 1.88124-2 rho 170010000 

20500407 3.54406-2 rho 175010000 

20500408 3.88642-2 rho 175020000 

20500409 4.44434-2 rho 180010000 

20500410 9.26274-2 rho 185010000 "*-- -- -- 1--- -11----- -- 1

* reactor 

*-- ---- ----- -- 1-- -- ----- -- 1

20500500 pcsvol5 sum 1.0 0.0 1 

20500501 0.0 2.66400-1 rho 215010000 

20500502 2.92300-1 rho 220010000 

20500503 1.30000-1 rho 225010000 

20500504 9.53095-2 rho 230010000 

20500505 9.53095-2 rho 230020000 

20500506 0.1120185 rho 230030000 

20500507 8.38500-3 rho 235010000 

20500508 8.38500-3 rho 235020000 

20500509 9.35500-3 rho 235030000 

20500510 3.32046-1 rho 240010000 

20500511 9.61020-2 rho 245010000 

20500512 1.28100-1 rho 246010000 

20500513 2.45952-1 rho 250010000 

20500514 1-73728-1 rho 250010000 

- - - - - - -- - - 1 --- Shot leg broken loop *-- -- 1-- 1 --- - 1--.. -- ... 1 1- -I1--

20500600 pcsvol6 sum 1.0 0.0 1 

20500601 0.0 5.55384-2 rho 300010000 

20500602 4.42532-2 rho 305010000 

20500603 6.68000-2 rho 310010000 

20500604 3.38914-3 rho 315010000 

20500605 4.40154-3 rho 315020000 

20500606 3.90960-2 rho 315030000 

20500607 1.82736-1 rho 315040000 

20500608 9.17460-2 rho 315050000

A-2 1
20500609 9.17460-2 rho 315060000 

20500610 1.82736-1 rho 315070000 

20500611 3.90960-2 rho 315080000 

20500612 1 62000-2 rho 315090000 

20500613 6.48000-2 rho 315100000 

20500614 .01539912 rho 315110000 

20500615 3-50175-2 rho 315120000 

20500616 8.54764-2 rho 370010000 

20500617 8.58000-2 rho 375010000 

-1- --1--- -1-- -- 1---- --- 1- -- 1

* cold leg broken loop "- -1-- -- 1- -1-- --- 1- -1-- -1

20500700 pcsvol7 sum 1.0 0 0 1 

20500701 0,0 4.75183-2 rho 335010000 

20500702 4.42532-2 rho 340010000 

20500703 6.17516-2 rho 345010000 

20500704 5.41000-3 rho 350010000 

20500705 8.55000-2 rho 380010000 

20500706 1.18030-1 rho 385010000 "- -1- -1-- -- 1- -- 1- -- 1-- -1- "pressurizer "- -1- -1- -1---- ---- -- 1

20500800 pcsvol8 sum 1.0 0,0 1 

20500801 0.0 5.00250-3 rho 400010000 

20500802 5.00250-3 rho 405010000 

20500803 8.10880-2 rho 415010000 

20500804 2-27695-1 rho 415020000 

20500805 2.27695-1 rho 415030000 

20500806 1 16955-1 rho 415040000 

20500807 1.16955-1 rho 415050000 

20500808 7.94530-2 rho 415060000 

20500809 7 94530-2 rho 415070000 

20500810 1.53400-2 rho 415080000 "-- 1-----I-1--1---1--1.. I.. I -..--1-

reactor vessel downcomer mass "-- -1--- -1--- ---..1--- -1-- -1- --- -.. 1-

20500900 dwncrms sum 1.0 0.0 1 

20500901 0.0 8.55000-2 rho 200010000 

20500902 1.10000-1 rho 205010000 

20500903 1 36036-1 rho 210010000 

20500904 1.36036-1 rho 210020000 

20500905 1.36036-1 rho 210030000 

20500906 1 36036-1 rho 210040000 

20500907 1 23426-2 rho 223010000 

20500908 2.78874-2 rho 223020000 

20500909 2.78874-2 rho 223030000 

20500910 2.78874-2 rho 223040000 

20500911 2.78874-2 rho 223050000 

20500912 1.04796-2 rho 223060000 

20500913 1.04796-2 rho 223070000 -- -1I---- -- 1 -1---- ---- 1--- -1%-- -- 1--

"pcs mass "--- --- 1--1 ---..1--...1-.....1- ---. 1-- --- 1-

20501000 pcsmass sum 1.0 0.0 1 

20501001 0.0 1.0 cntrlvar 41 

20501002 1.0 cntrlvar 42 

20501003 1.0 cntrlvar 43 

20501004 1.0 cntrlvar 4 

20501005 1.0 cntrtvar 5 

20501006 1,0 cntrtvar 6 

20501007 1.0 cntrlvar 7 

20501008 1.0 cntrlvar 8 

20501009 1,0 cntrlvar 9 

break energy computer 

20542500 pvfstm div 1 0 0,0 1 

20542501 rhof 420010000 p 420010000 

20542600 hfstm sum 1 0 0.0 1 

20542601 0 0 1 0 uf 420010000 

20542602 1.0 cntrIvar 425

20542700 pvgstmn div 1.0 0.0 1 

20542701 rhog 420010000 p 420010000 

20542800 hgstm sum 1.0 0.0 1 

20542801 0 0 1 0 ug 420010000 

20542802 1.0 cntrtvar 427 

20542900 xhgstm mult 1.0 0.0 1 

20542901 quals 420010000 cntrfvar 428 

20543000 xhfstm muft 1.0 0.0 1 

20543001 quals 420010000 cntrtvar 426 

20543100 yhfstm sum 1.0 0.0 1 

20543101 0.0 1.0 cntrlvar 426 

20543102 -1.0 cntrlvar 430 

20543200 hsteam sum 1.0 0.0 1 

20543201 0.0 1.0 cntrlvar 429 

20543202 1-0 cntrtvar 431 

20543300 brkpwr mutt 1.0 0.0 1 

20543301 inflow] 425000000 cntrivar 432 

20543400 brkflow integral 1.0 0-0 1 

20543401 mflow] 425000000 

"- SRV 

20552500 pvfstm div 1.0 0.0 1 

20552501 rhof 420010000 p 420010000 

20552600 hfstm sum 1.0 0.0 1 

20552601 0.0 1.0 uf 420010000 

20552602 1.0 cntrlvar 525 

20552700 pvgstm div 1.0 0.0 1 

20552701 rhog 420010000 p 420010000 

20552800 hgstm sum 1.0 0.0 1 

20552801 0.0 1.0 ug 420010000 

20552802 1.0 cntrtvar 527 

20552900 xhgstm mult 1.0 0.0 1 

20552901 quais 420010000 cntivar 528 

20553000 xhfstm muir 1.0 0.0 1 

20553001 quals 420010000 cntrtvar 526 

20553100 yhfstrn sum 1.0 0.0 1 

20553101 0 0 1.0 cntrlvar 526 

20553102 -1.0 cntrlvar 530 

20553200 hsteam sum 1 0 0.0 1 

20553201 O00 1.0 cntrlvar 529 

20553202 1.0 cntrlvar 531 

20553300 brkpwr mult 1.0 0.0 1 

20553301 mflowj 430000000 cntrtvar 532 

20553400 brkflow integral 1.0 0.0 1 

20553401 mflowj 430000000 

011 - 031 heat transfer rate calculator 

* heat added to pcs from core ---.. .. 1 -.. ... 1- ----..1- - -.. .-1 .. - .. 1--......1---

20511100 corhttrsum 10 0.0 1 

20511101 00 24.374 htrnr 230000101 

20511102 24.374 htrnr 230000201

A-2 2
20511103 24.374 htmr 230000301 

- -1- -1- -- -- 1------ --- 1

"heat removed from pcs at to s/g tubes 

*- 1 - -1--1-----------1 

20511200 sghttr sum 1.0 0.0 1 

20511201 0.0 14.2746667 htmr 006000100 

20511202 14.2746667 htmr 006000200 

20511203 14.2746667 htmr 006000300 

20511204 22.412 htmr 006000400 

20511205 22.412 htmr 006000500 

20511206 44.824 htnr 006000600 

20511207 44.824 htmr 006000700 

20511208 22.412 htmr 006000800 

20511209 22.412 htmr 006000900 

20511210 14.2746667 htmr 006001000 

20511211 14.2746667 htmr 006001100 

20511212 14.2746667 htmr 006001200 

* heat loss from reactor vessel 

*- 1-1 1--1 - -1 -- 1 

20511300 rvheat sum 1.0 0.0 1 

20511301 0.0 2.3244 htmr 211000101 

20511302 5.25183 htmr 211000201 

20511303 3.56335 htrnr 211000301 

20511304 1.59598 htrnr 212000101 

20511305 4.96411 htmr 212000201 

20511306 4.96411 htrnr 212000301 

20511307 1.86543 htmr 212000401 

20511308 1.91724 htrnr 212000501 

20511309 1.68000 htmr 220000101 

20511310 0.71200 htmr 255000101 " 1--1--1--1----1--1--1--1-

"heat loss from pzr 

20511400 pzrheatsum 1.0 0.0 1 

20511401 0.0 0.362 htmr 415100101 

20511402 0.702464 htmr 415200101 

20511403 1.26381 htmr 415200201 

20511404 1.26381 htmr 415200301 

20511405 0.649152 htmr 415200401 

20511406 0.649152 htmr 415200501 

20511407 0.534688 hlmr 415200601 

20511408 0.534688 htmr 415200701 

20511409 0273063 hlmr 416200101 

20511410 0.130000 hmrnr 420100101 

20511411 0.273063 htmr 420200101 

*ý-- -- - -1--1----1-----1

heat loss from s/g 

*-- 1- -1- -1---1-------1 

20511500 sgheat sum 1.0 0.0 1 

20511501 0.0 3.5343 htmr 530000101 

20511502 3.5343 htmr 530000201 

20511503 3.33022 htr" 530000301 

20511504 3.33022 htrnr . 530000401 

20511505 2.40258 hltnr 530000501 

20511506 3.29404 htmr 530000601 

20511507 3.29404 htnrrr 530000701 

20511508 3.29404 htmr 630000801 - -1---..-1-- -.. 1--•1- m-- -- 1-

toal heat loss from major oomponents 

*- -- 1-- ------ ---- - -1- -- 1-

20511600 totheat sum 1.0 0.0 1 

20511601 0.0 1.0 cntrlvar 113 

20511602 1.0 cntrlvar 114 

20511603 1.0 cntrtvar 115 - ---- 1 -..... 1- --..1-- -1-- i-1 ---. 1-

heat loss from broken loop hot leg "---..1-... - ... -- 1---- 1-- -- 1-- -- - 1--i

20511700 blhlheat sum 1-0 0.0 1 

20511701 00 0.97972 htmr 300000101 

20511702 0.78065 htmr 300000201 

20511703 1.59260 htmr 300000301

*- -- 1-- -- ---- -------- -- 1

heat loss from broken loop cold leg 

-1- -1---1--1- - --1- 

20511800 blclheat sum 1.0 0.0 1 

20511801 0.0 0.83825 htrnr 335000101 

20511802 0.78065 htmr 335000201 

20511803 1.0893 htmr 335000301 

*- --- 1-- -1--1- - -1- -1

* heat loss from rabs piping 

-1- -- -- -1- -1- - --- 

20511900 rabheat sum 1.0 0.0 1 

20511901 0.0 1.7153 htmr 370000101 

20511902 0.94828 htmr 370000201 

20511903 0.94497 htmr 370000301 

20511904 2.6090 htmr 370000401 

1-- -- 1- -1--- 1 ---

heat loss from intact loop hot leg "- -1-- --- -- 1-- ----- 1-- -1

20512000 ilhlheat sum 1.0 0.0 1 

20512001 0.0 1.7193 htmr 100100101 

20512002 1.8275 htrnr 100100201 

20512003 0.69677 htmr 100100301 

20512004 1.6088 htmr 100100401 

20512005 0.90304 htmr 100200101 

20512006 1.8855 htmr 100400101 

""--1-- -1- -1--1- -1--1l 

* heat loss from intact loop cold leg 

* -- 1- --- 1-- ----- -- 1-- ---- 1

20512100 ilclheat sum 1.0 0.0 1 

20512101 0.0 0.77058htnlr 100100501 

20512102 0.62519 htmr 100100601 

20512103 0.84999 htmr 100100701 

20512104 0.55540 htmr 100100801 

20512105 0.62519 htrnr 100100901 

20512106 0.68558 htmr 100101001 

20512107 0.78400 htmr 100101101 

20512108 1.6340 htmr 100101201 

20512109 0.69769 htmr 100200201 

20512110 0.85765 htmr 100300101 

20512111 0.39195 htmr 100300201 

20512112 0.43054 htmr 100300301 

20512113 1.2079 htmr 100300401 

20512114 0.86023 htnir 100300501 

20512115 0.39195 htnr 100300601 

20512116 0.44083 htmr 100300701 

20512117 1.8855 htmr 100400201 

-- -1

toal heat loss to environment 

-1- -1- -1-1- l-1- -1 -

20512200 sumhtls sum 1.0 0.0 1 

20512201 0.0 1.0 cntrlvar 116 

20512202 1.0 cntrlvar 117 

20512203 1.0 cntrlvar 118 

20512204 1-0 cntrlvar 119 

20512205 1.0 cntrtvar 120 

20512206 1.0 cntrlvar 121 

*- -1--1-- 1--1--1- - -1 "metal heating in pzr "*- -- 1-. . -- ---1 l 1-- 1 1- -- 1-

20512300 pzrmtht sum 1.0 0.0 1 

20512301 0.0 0.3620 htrnr 415100100 

20512302 0.59522 htmr 415200100 

20512303 1.07086 htmr 415200200 

20512304 1.07086 htmr 415200300 

20512305 0.550045 htmr 415200400 

20512306 0.550045 htmr 415200500 

20512307 0.453056 htmr 415200600 

20512308 0453056 htmr 415200700 

20512309 0.150656 htmr 416200100 

20512310 0.13000 htmr 420100100 

20512311 0.150656 htnr 420200100 "-----1-.....1..... -- 1--- -1--i -- --...1--..-

A-2 3
metal heating in reactor vessel (1st part) -- -- 1-- --..1--- -1I- ----1--- -- 1--- -1-I--

20525100 rvl sum 1.0 0.0 1 

20525101 0.0 1.05331 htmr 200000100 

20525102 0.79000 htmr 200100101 

20525103 1.01501 htmr 200100201 

20525104 2.29335 htmr 200100301 

20525105 229335 htmr 200100401 

20525106 2.29335 htmr 200100501 

20525107 2.29335 htmr 200100601 

20525108 1.33475 htmr 205000100 

20525109 1.93518 htmr 205000101 

20525110 2.82907 htmr 210000100 

20525111 2.82907 htmr 210000200 

20525112 2.82907 htmr 210000300 

20525113 2.82907 htmr 210000400 

20525114 1.06311 htnr 210000500 

20525115 1.09265 htmr 210000600 

20525116 4.37241 htmr 210000101 

20525117 4.37241 htmr 210000201 

20525118 4.37241 htmr 210000301 

20525119 4.37241 htmr 210000401 

20525120 1.64308 htmr 210000501 

20525200 rv2 sum 1.0 0.0 1 

20525201 0.0 1.68872 htmr 210000601 

20525202 1.95223 htmr 211000100 

20525203 4.41094 htmr 211000200 

20525204 2.99281 htmr 211000300 

20525205 1.41813 htmr 212000100 

20525206 4.41094 htmr 212000200 

20525207 4.41094 htmr 212000300 

20525208 1.65755 htmr 212000400 

20525209 1 70360 htmr 212000500 

20525210 1.6800 htmr 220000100 

20525300 rv3 sum 1.0 0.0 1 

20525301 0.0 0.695734 htmr 225000700 

20525302 0.921366 htmr 226000100 

20525303 1.98094 htmr 240000100 

20525304 1.80000 htmr 246000100 

20525305 1.80000 htmr 246000101 

20525306 2.04439 htmr 250000100 

20525307 1.00000 htmr 251000100 

20525308 1.00000 htmr 251000200 

20525309 1 70445 htmr 250100100 

20525310 0.71200 htmr 255000100 

20525311 1.68000 htmr 220000101 

20525312 0.980177 htrnr 225000100 

20525313 1 05369 htmr 225000200 

20525314 1 05369 htmr 225000300 

20525315 1.23842 htmr 225000400 

20525316 2.10738 htmr 225000500 

20525317 0 791681 htmr 225000600 

20525318 1 0 cntrlvar 251 

20525319 1.0 cntrlvar 252 ..... 1 "-.....1-- ...-- 1--1--- --- -- 1-1....1-.... 

metal heating in broken loop (1st part) .1 -.. ... 1--.....1--....-1 --... . ... . .- 1 

20512600 bklpmht sum 1.0 0.0 1 

20512601 00 0.157878 htrnr 300000100 

20512602 0622764 htmr 300000200 

20512603 1.27051 htmr 300000300 

20512616 0.668713 htmr 335000100 

20512617 0622764 htmr 335000200 

20512618 0869015 htmr 335000300 .. ... 1---- --.. 1 -.. . .1 -. ... 1 - -.. .1 .- ... 1---

metal heating in broken loop 

20512700 bklpmt sum 1.0 O0 1 

20512701 00 1 39487 htrnr 370000100 

20512702 0771131 htrnr 370000200

20512703 0.768435 htmr 370000300 

20512704 2.12160 htmr 370000400 

20512705 1.0 cntdvar 126 "*--1I- -- 1-- -1-- -1-- -1I- -- 1-

* metal heating in intact loop hot leg 

20512800 ilhlmht sum 1.0 0.0 1 

20512801 0.0 1.3716 htmr 100100100 

20512802 1.45787 htmr 100100200 

20512803 0.55548 htmnr 100100300 

20512804 1.28345 htmr 100100400 

20512805 0.72288 htmr 100200100 

20512806 1.4772 htmr 100400100 

""- -1- -1- -1- -1- -1- -

* metal heating in intact loop cold leg "--- -- 1-- -- 1-- -- 1-- -1-- -- 1- -- 1-

20512900 ilclmht sum 1.0 0.0 1 

20512901 0.0 0.614734 htmr 100100500 

20512902 0.498747 htmr 100100600 

20512903 0.678081 htrnr 100100700 

20512904 0.443073 htmr 100100800 

20512905 0.498747 htmr 100100900 

20512906 0.546926 htmr 100101000 

20512907 0.625441 htmr 100101100 

20512908 1.30352 htmr 100101200 

20512909 0.558497 htmr 100200200 

20512910 0.678584 htmr 100300100 

20512911 0.310113 htmr 100300200 

20512912 0.340649 htmr 100300300 

20512913 0.955718 htmr 100300400 

20512914 0.680620 htmr 100300500 

20512915 0.310113 htmr 100300600 

20512916 0.348792 htmr 100300700 

20512917 1.4772 htmr 100400200 "--1- -- 1- 1- -1-- -1-- -- 1

metal heating in broken loop simulators 

--- -- 1-- --------- ----------- -- 1

20513000 blhlsim sum 1.0 0.0 1 

20513001 0.0 0.1312 htmr 315000100 

20513002 0.1703 htmr 315000200 

20513003 0.0042 htmr 315100100 

20513004 0.00347 htnr 315200100 

20513005 0.12452 htmr 315300100 

20513006 0.12452 htmr 315300200 

20513007 0.12452 htmr 315300300 

20513008 0.12452 htmr 315300400 

20513009 0-12452 htmr 315300500 

20513010 0.12452 htmr 315300600 

20513011 0.04239 htmr 315400100 

20513012 004363 htmr 315500100 

metal heating in steam generator 

20555100 sgmthl sum 1.0 0.0 1 

20555101 0.0 1.47943 htmr 500000100 

20555102 1.47943 htmr 500000200 

20555103 0.291097 htmr 500000300 

20555104 1.52566 htmr 500000101 

20555105 1.52566 htmr 500000201 

20555106 0.300194 htrnr 500000301 

20555107 0.615526 htmr 515000100 

20555108 2.88042 htmr 515000200 

20555109 1.44021 htmr 515000300 

20555110 1.44021 htmr 515000400 

20555111 0.96014 htmr 515000500 

20555112 0.96014 htmr 515000600 

20555113 0.96014 htmr 515000700 

20555114 0.627655 htmr 515000101 

20555115 2.93718 htmr 515000201 

20555116 1,46859 htmr 515000301 

20555117 1.46859 htmr 515000401 

20555118 0.994572667 htmr 515000501

A- 2 -4
20555119 0.994572667 htmr 515000601 

20555120 0.994572667 htmr 515000701 

20555200 sgmth2 sum 1.0 0.0 1 

20555201 0.0 3.40507 htmr 530000100 

20555202 3.40507 htmr 530000200 

20555203 3.20846 htmr 530000300 

20555204 3.30846 htmr 530000400 

20555205 2.31474 htmr 530000500 

20555206 3.17360 htmr 530000600 

20555207 3.17360 htmr 530000700 

20555208 3.17360 htrnr 530000800 

S-1- -1--1----- ---- 1---1

* pcs-tubesheet heat transfer 

*- -1--i--i- -- 1- -1-- -- 1

20513200 pcstub sum 1.0 0.0 1 

20513201 0.0 56.4226 htmr 115100100 

20513202 56.4226 htmr 115100200 

20513203 0.157962 htmr 115200100 

20513204 0.157962 htnr 115200200 "-- -1--i-1----1----1----------1-

* tubesheet-scs heat transfer 

*--1-------11--1--1---1

20513300 tushscs sum 1.0 0.0 1 

20513301 0.0 0.157962 hbmr 115200101 

20513302 0.157962 htmr 115200201 

metal hx in rabs 

-- -1 ---- ----1---- -1

20517000 rabs sum 1.0 0.0 1 

20517001 0.0 1.39487 htmr 370000100 

20517002 0.77113 htmr 370000200 

20517003 0.77278 htmr 370000300 

20517004 2.12160 htmr 370000400 

"bl total metal hx 

20517100 qbltotal sum 1.0 0.0 1 

20517101 0.0 1.0 cnblvar 127 

"20517102 1.0 cntlvar 170 

20517103 1.0 cntrlvar 130 *only for simula 

* pcs stored energy excluding pressurizer 

20557000 pcsqre sum 1.0 0.0 1 

20557001 0.0 1.0 cntrlvar 253 * rv metal heat 

20557002 1.0 cntrlvar 113 * rv ambloss 

20557003 1.0 cntrlvar 171 * only for simula 

20557004 1.0 cntrlva 117 *bthl ambloss 

20557005 1.0 cntrvar 118 * bid amnbloss 

20557006 1.0 cntlvar 119 * rabv ambloss 

20557007 1 0 cntrlvar 128 *ilhl heat 

20557008 1.0 cntrvar 120 * ilhl ambloss 

20557009 1.0 critvar 129 *ilid heat 

20557010 1.0 cntrlvar 121 ild ambloss 

20557011 1.0 cntrlvar 132 * pcs-tubesheet 

20557012 1.0 cntrlvar 133 *tubesheet-scs 

"scs stored energy 

20557300 scsqse sum 1.0 0.0 1 

20557301 0.0 1.0 cntblvar 552 * sg heat 

20557302 1.0 cntrlvar 115 * sg ambloss 

' heat flow calculations 

ecc energy flow 

-20515300 pvecc div 1.0 0.0 1 

"20515301 rhol 630000000 p 600010000 

"20515400 hecc sum 1.0 0.0 1

"20515401 

"20515402 

*20515500 

*20515501 

*20515502

0.0 1.0 uqj 630000000 

1.0 cntrlvar 153

mdothecc mult 1.0 0.0 

m"no 630000000 

cntrlvar 154

1

20515600 qecctv muft 0.1266460.0 

2051 5601 cntrlvar 155

"20515700 mdotev mult 0.1266460.0 1 

20515701 mflo"j 630000000

* sg hx per unit pcs volume 

20516000 qsg/v mult 0.126646 0.0 1 

20516001 cntrvar 112 

* core hx per unit pcs volume 

20516100 qcore/v mult 0.126646 0.0 1 

20516101 cntrvar 111 

* pump power 

20516200 pledotv mult 0.04136 0.0 1 

20516201 voidgi 135020000 

20516202 velgi 135020000 

20516203 pmphead 135 

20516300 pledotl mult 0.04136 0.0 1 

20516301 voidfi 135020000 

20516302 velfj 135020000 

20516303 pmphead 135 

20516400 p2edotv mult 0.04136 0.0 1 

20516401 voidgj 165020000 

20516402 velgj 165020000 

20516403 pmphead 165 

20516500 p2edotl mult 0.04136 0.0 1 

20516501 voidfij 165020000 

20516502 velfj 165020000 

20516503 pmphead 165 

20516600 qpmp sum 1.0 0.0 1 

20516601 0.0 1.0 cntrivar 162 

20516602 1.0 cntbvar 163 

20516603 1.0 cntrlvar 164 

20516604 1.0 cntrlvar 165 

20516700 qpmp/v mult 0.1266460.0 1 

20516701 cntrlvar 166 

* energy to fluid in vessel from structures 

20562000 rvhx sum 6.2832 0.0 1 

20562001 0.0 0.3080 htmr 205000101 

20562002 0.6959 htmr 210000101 

20562003 0.6959 htmr 210000201 

20562004 0.6959 htmr 210000301 

20562005 0.6959 htmr 210000401 

20562006 0.2615 htmr 210000501 

20562007 0.2688 htmr 210000601 

20562008 0.3107 htmr 211000100 

20562009 0.7020 htmr 211000200 

20562010 0.7020 htmr 212000100 

20562011 0.7020 htmr 212000200 

20562012 0.7030 htmr 212000300 

20562013 0.6 htmr 212000400 

20562014 0.2 htmr 212000500 

20562015 1.0 cntrtvar 253 

.- 1-- -1-- --- 1- -1--- --- 1--- -1

total vessel hx/v "-----1-1 --..1--..-- -- 1 -1-- ----1--...-1

20562100 rvhx/v mult 1.0 00 1 

20562101 cntrlvar 620

A-2 5
* total massless energy flows from pcs excluding qcore and qsg 

20562200 qstruc sum 1.0 0 0 1 

20562201 0.0 1.0 cntrlvar 123 *przr 

20562202 1.0 cntrlvar 620 rv 

20562203 1.0 cntrivar 171 bi 

20562204 1 0 cntrlvar 128 * ilhl 

20562205 1 0 cntdvar 129 ild 

20562300 qstruc/v mult 0 126646 0.0 1 

20562301 cntrlvar 622 

' sum of all massless energy flows from pcs 

20562400 de/dt sum 1 0 0.0 1 

20562401 0.0 1.0 cntrlvar 111 * core 

20562402 1.0 cntrlvar 112 "sg 

20562403 1.0 cntrlvar 622 * structure 

20562404 1.0 cntrlvar 166 * pumps 

20562500 de/dt/vv mutt 0.126646 0.0 1 

20562501 cntrlvar 624 

" sum of mass flow energy flows and massless energy flows 

20562600 dtqflo sum 1.0 0.0 1 

20562601 0.0 1.0 cntrivar 624 * de/dt 

20562602 -1.0 cntilvar 433 * porv 

20562603 -1.0 cntrlvar 533 "srv 

20562700 dtqf/v mutt 0.126646 0.0 1 

20562701 cntrtvar 626 

pressurizer pressure in MPa 

20505000 pzrpres sum 1.0e-06 0.0 1 

20505001 0.0 1.0 p 420010000 

"hot leg pressure in MPa 

20505100 hlpres sum 1.0e-06 00 1 

20505101 00 1.0 p 100010000 

cold leg pressure in MPa 

20505200 clpres sum 1.0e-06 0.0 1 

20505201 0.0 1.0 p 185010000 

sg steam pressure in MPa 

20505300 sgpres sum 1.0e-06 0.0 1 

20505301 0 0 1.0 p 530010000 

reactor power in MWt 

20505400 reacpor sum 1.Oe-06 0.0 1 

20505401 0.0 .0Orktpow 0 

PORV upstream density in Mg/m3 

20505500 updensi sum 1.0e-03 0 0 1 

20505501 0.0 1 0 rho 420010000 

total dischrged flow 

20505700 tdis sum 1 0 0.0 1 

20505701 0.0 1 0 mflowj 425000000 

20505702 1.0 mflowj 430000000 

"- --- 1 .. - ... 1-.....1.......1-.....1 ---...1--

"inlet outlet energy computer 

... 1-.. ... 1-.....1-.. "-.. ... 1-----.. 1 -... .. 1--

20521100 pvfstm div 1 0 00 1 

20521101 rhof 530020000 p 530020000

20521200 hfstrn sum 1.0 0.0 1 

20521201 0.0 1.0 uf 530020000 

20521202 1.0 cntrlvar 211 

20521300 pvgstm div 1.0 0.0 1 

20521301 rMNog 530020000 p 530020000 

20521400 hgstm sum 1.0 0.0 1 

20521401 0.0 1.0 ug 530020000 

20521402 1.0 catrvar 213 

20521500 xhgstm mutt 1.0 0.0 1 

20521501 quals 530020000 cntrlvar 214 

20521600 xhfstm mutt 1.0 0-0 1 

20521601 quals 530020000 cntrlvar 212 

20521700 yhfstrn sum 1.0 0.0 1 

20521701 0.0 1.0 cntrlvar 212 

20521702 -1.0 cntrlvar 216 

20521800 hsteam sum 1.0 0.0 1 

20521801 0.0 1.0 cntrlvar 215 

20521802 1.0 cntrlvar 217 

20521900 stmms sum 1.0 0.0 1 

20521901 0.0 1.0 mflowj 550000000 

20521902 1.0 mflow4 546000000 

20522000 brkpwr mult 1.0 0.0 1 

20522001 cntrlvar 219 cntrlvar 218 

20531100 pvfstm div 1.0 0.0 1 

20531101 rhof 545010000 p 545010000 

20531200 hfstm sum 1.0 0.0 1 

20531201 0.0 1.0 uf 545010000 

20531202 1.0 cntrlvar 311 

20531300 pvgstm div 1-0 0.0 1 

20531301 rhog 545010000 p 545010000 

20531400 hgstm sum 1.0 0.0 1 

20531401 0.0 1.0 ug 545010000 

20531402 1.0 cntrlvar 313 

20531500 xhgstm mutt 1.0 0.0 1 

20531501 quals 545010000cntrlvar 314 

20531600 xhfstm mutt 1.0 0.0 1 

20531601 quals 545010000 cntrtvar 312 

20531700 yhfstm sum 1,0 0.0 1 

20531701 0.0 1.0 cntrlvar 312 

20531702 -1.0 cntrtvar 316 

20531800 hsteam sum 1.0 0.0 1 

20531801 0.0 1.0 cntrlvar 315 

20531802 1.0 cntrlvar 317 

20532000 brkpwr mutt 1 0 0.0 1 

20532001 mflowj 560000000 cntrlvar 318 

Pressurizer Liquid Volume 

20533000 pzrliqv sum 1.0 0.0 1 

20533001 0.0 8.10880-2 voidf 415010000 

20533002 2.27695-1 voidf 415020000 

20533003 2.27695-1 voidf 415030000

A- 2C
20533004 

20533005 

20533006 

20533007 

20533008 

20533009

116955-1 voidf 415040000 

1.16955-1 voidf 415050000 

7.94530-2 voidf 415060000 

7 94530-2 voidf 415070000 

1.53400-2 voidf 415080000 

0.01534 voWdf 420010000

Pressurizer Vapor Volume 

20534000 pzrliqv sum 1.0 0.0 1 

20534001 0.0 8.10880-2 voidg 415010000 

20534002 2.27695-1 voidg 415020000 

20534003 2.27695-1 voidg 415030000 

20534004 1.16955-1 voidg 415040000 

20534005 1.16955-1 voidg 415050000 

20534006 7.94530-2 voidg 415060000 

20534007 7.94530-2 voidg 415070000 

20534008 1.53400-2 voidg 415080000 

20534009 0.01534 voidg 420010000 

"Steady State Controllers 

*- -1-- -- 1-- -- 1------1-----1------1-

primary coolant pump speed controllers 

"-- -1-- ----- ----- ----- -- 1

"calculate mass flow error "-- -1--1----- --- 1----1---1

20590100 msserr sum 1.0 0.0 1 

20590101 467.6 -1.0 mflowj 100010000 "*- -1-- --- ---- ---- ---- -- 1

* pump 1 speed • --- -- 1--- -- 1-- -1I- -- 1-- -1-- -1-

20590200 pcplspd integral 0.34482 333.7236 1 

20590201 cntblvar 901 

*-- ---- ---- ----- ----------- -- 1

"* pcpl pump velocity table 

-- -- I- -I---- ---- ---- -- 1

1356100508 cntrtvar 902 

1356101 0.0 0.0 

1356102 369.0 369.0 

"modify pcpl pump data 

13503010 0 0 -1 0 504 0 

*-- ---- -----------------------------1 

"pump 2 speed "*----1------------------1-- -- 1- --- 1-.-

20590300 pcp2spd integral 0.34482 331.9524 1 

20590301 critrvar 901 

*-- -1--i- -1--i- --- -1- "pcp2 pump velocity table "--- 1- -- -1--i--i-- -1- -- 1

1656100508 Catrtvar 903 

1656101 0.0 0.0 

1656102 369.0 369.0 

"modify pcp2 pump data 

--- 1- ---1--1----------1------1

1650301 135 135 135 -1 0 504 0 

*---1...1--- -- 1-- -1--i-- -- -- 1-

"pressurizer spray valve controller 

spray valve "--...1--... -- 1---1--- -- -- 1 .. --- -- 1--i 

4070000 sprvlv valve 

40701014060100004200100003.3451e-4 0.0 0.0 0001000.93 

4070201 0 .00000000.00000000 0.0

4070300 srvvlv 

4070301 904 999 "1-- -1I- -- 1-- -1-- -1- -- 1-- -1-

"spray valve position calculator 

*-- ---- ---- ----- ----- ----- -- 1

20590400 spray sum -0.0001 0.0 1 contin + 3 0.0 1.0 

20590401 14.98e+6 -1.0 p 420010000 

-- ---- -- 1-- ----- 1----------1--1

• position vs area table "*- -I1- -1I- -- 1-- -1-- -1-- -1-

20299900 normarea 

20299901 0.0 0.0 

20299902 0.1 0.0 

20299903 1.0 1.0 

1------------ --------- I-1- -- 1-

"pressurizer level control using charging and letdown components 

-1- -1- ----- 1-- -1 -- 1

* charging reservior 

"- -1-- --- ---- ---- ----- -- 1

9800000 chrg tmdpvol 

9800101 1.0 1.0 0.0 0.0 0.0 0.0 

9800102 4.0-5 0.0 00000 

98002003 

9800201 0.0 2.07+07 558.9 

"charging valve 

* ----- 1-- 1 - -1- -1-- -1

9850000 chrg valve 

9850101 980000000 185000000 3.8e-05 00 0.0 000100 

9850201 0 .00000000.00000000 0.0 

9850300 srvvtv 

9850301 905 999 

,-- -1--i--i- -- 1--1--i "charging valve position calculator 

"-- -1-- --- ---- ----- ----- -- 1

20590500 charge sum 7.7 0.0 1 *contin + 3 0.0 1.0 

20590501 1.0 -1.0 cntrtvar 2 "- 1--1---- ---- ----- 1------1

* letdown sink 

*w-- ---- -- 1-- ----- ----------- -- 1

9900000 ltdwn tmdpvol 

9900101 1.0 1.0 0.0 0.0 0.0 0.0 

9900102 4.0-5 0.0 00000 

9900200 3 

9900201 0.0 1.4+7 558.9 "*-- -------- ----- -- 1- -i- -1

* letdown valve 

*--1--1--1- --- 1-- -1

9950000 ltdwn valve 

9950101 185000000 990000000 2.5-5 0.0 0.0 000100 

9950201 0 .00000000.00000000 0.0 

9950300 srvvlv 

9950301 906 999 "*--- - 1-- - 1--1- -- 1-- -- 1

"letdown valve position calculator 

"--1--I- -- 1- -1-- -- 1-- -1-

20590600 letdown sum -7.7 0.0 1 *contin + 3 0.0 1.0 

20590601 1.03 -1.0 cntrlvar 2 

steam valve controller • -- - -- .. . .. . .. .. .1- --.. 

* changes to steam valve 

'5500201 0 18.585 20.163 0.0 

"5500300 srvvlv 

*5500301 910 540 -- 1- ----1---.. --.. .1- - -..... - ----..1-.....1---

A-2 7
"srv 550 valve area table "-- -- 1--- -- 1 ---.1----.---1- --..1- ---..1---

20254000 normarea 

20254001 0.0 0.0 

20254002 0.0001 0 0 

20254003 0.9 0.6 *modi at 8/26 in base 

20254004 1.0 0.6 1- I--1 -1--- -- 1-- -1--i- -1-

"GT 908 

- -1-- -- 1 --- -1- -1-- --- 1 - -- 1

20290800 reac-t 

20290801 -100. -100. 

20290802 -0.25 -0.25 

20290803 -0.25 0.0 

20290804 0.25 0.0 

20290805 0.25 0.25 

20290806 100 100. *.. -- -1--1-- -1I- -1-I- -- -- 1.. -

compute delta t error "*-- -- I-- -1I- -- I-- --- I--- -- 1-- --- I--

20590700 delta sum 1.0 0.0 1 

20590701 557.0 -1 tempf 185010000 

*-- -1-- -- 1---- -1--- -1-- -1--- -- 1- "filter delta t thru deadband 

- -1- -1-- -1-----1--1- -- 1

20590800 deadband function 1.0 0-0 1 

20590801 cntrdvar 907 908 "----1I- -1-1 .. I--- -1I- -- 1-- -----

"integrate delta t error "-- 1- -- i 1-- 1...1...-- --- --- 1-- ---1--

20590900 int integral 1.0 0.0 1 

20590901 cntrlvar 908 "-...1-- --- 1-- -..1-- ---.-.- ---...1- -....- 1--

"steam valve position calculator 

20591000 tcontrol sum 1.0 0.645229 0 + 3 0.6 0.90 

20591001 0.645229 -0.07126 cntrlvar 908 

20591002 -0.01492 cntrlvar 909 

*-- -1- -- --1- -1- -- 1- -- 1-- -1--

simplified feed system controller 

*--1-- --- 1 -- --1- -- 1 -- -- 1-- -1

20591100 sgivlerr sum 1.0 00 1 

20591101 3.15 -1.0 cntrlvar 001 

*--1-- --1---- -- 1-- -1- --- 1- -- 1-

20591200 feedflow sum 1 0 00 1 

20591201 0.0 1.0 mflowj 550000000 

20591202 48.4 crntrlvar 911 ---- 1-- -1-- -1-- --... 1-- .. I-1- --- 1--

* junction quantities 

-- 1-- -- 11-- 1--..1 -- -- 1- -1-

20800001 flenth 425000000 20800002 ftenth 430000000 

replace feed junction table 

5600200 1 0 cntrlvar 912 

5600201 -100.0 25.553 0 0 0.0 

5600202-1.0 0.0 0.0 00 

560020300 00 0.0 0.0 

5600204 50.0 50 0 0.0 0.0 

* boundary volume intact loop hot leg 

5920000 bvolum trndpvol 

5920101 0.0 1 0 0.1 0 0 0.0 00 

59201020.0 00 00000 

59202002 

5920201 0.0 5 47091e6 1 0 

1-.... 1 1 ---- ---- 1 ........ - 1 ---- ----1 --- S---- 

* boundary valve for steam generator 

. .. 1 . . .. .1 . . . . -1.. --.. .. 1 . . . .. 1 . . .. 1 . .

"conti

5930000 bvalv sngljun 

5930101 530020002 592000000 0.001 0.0 0.0 000100 

5930201 0 0.0 00 0.0 

""- -1- -1- -1- -- 1- -- --

boundary valve intact loop hot leg 

- ---- -1-- -1- -1- -1- -1

9000000 bvalv sngljun 

9000101 420010000 905000000 0.00001 0.0 0.0 000100 

9000201 0 0.0 0.0 0.0 "1- -- 1-- -- 1-- -- 1-- ----- -- 1-- -1-

boundary volume intact loop hot leg 

*- -1- ---- -1-- -- -1- -

9050000 bvolum tmdpvol 

9050101 0.0 1.0 1.0 0.0 0.0 0.0 

90501020.0 0.0 00000 

9050200 2 

9050201 0.0 14.98e6 1.0

A-2 8
Appendix B. Input Deck for Transient Calculation of Base Case
=loft L9-3 ATWS experiment assessment calculation deck 

initial conditions 

core power = 48.7 MW 

pcs flow = 467.6 kg/s 

• Pzr pressure = 14.98 MPa 

* thot = 576.4 k 

tcold =557.0 k 

-- 1-----1---1

"use reactor kinetics feedback 

change mscv area to 0.0052235 from 0.00337 

• 1---1- -1--i - --- -1--- -- 1-

0000100 restart transnt 

0000101 run 

0000102 si 

00001055. 10. 

0000103 2241 rst 

* 1- 1-- -- ---- ---- -- 1

* time step control cards 

* end time min dt max dt optn mnr mjr rst 

0000201 600.0 1.e-4 0.1 2 5 1000 1000 -- 1--1-------1----1------1-

minor edit variables 

pressure 

0000308 cntlvar 51 * pe-pc-2 

0000309 cntilvar 50 * porv inlet 

0000314 cntrivar 53 * pt-p4-1 Oa 

"* temperatures 

0000322 tempf 100010000 * te-pc-2a,2b,2c 

0000323 temptf 185010000 * te-pc-1 

0000326 tempt 505010000 - sg flq. temp. 

0000330 tempt 415030000 - pzr Iiq. tep 

0000331 tempf 300010000 * broken loop hot leg 

0000332 tempt 335010000 * broken loop cold leg 

* mass flow rates 

0000360 mnflowj 100010000 * ilhl nozzle 

0000363 mflo"j 400010000 * pres. surge line flow 

0000364 mflowj 407000000 * pzr spray flow 

0000367 mflovj 550000000 * steam flow control valve 

0000369 mflowj 560000000 * main feed 

0000360 mflowj 546000000 ' sg bypass flow 

* water level 

0000370 cntrivar 1 * slg level 

0000375 cntrtvar 2 * pzr level 

power

*0000376 cntrivar 701 

"0000377 cntrlvar 702 

0000378 cntrlvar 54 

0000379 rkreac 0

" moderator density 

" doppler temp. 

"power 

•reactivity

* delete steady state component "----1--- -- 1 ----.1-.....1-.....1 ...- 1-....

20590100 

20590200 

20590300 

20590400 

9800000 

9850000 

20590500 

9900000 

9950000 

20590600 

20590700 

20590800 

20590900 

20591000 

20591100 

20591200 

5930000 

5920D0O 

900D00 

9050000

msserr delete 

pcplspd delete 

pcp2spd delete 

spray delete 

chrg delete 

chrg delete 

charge delete 

ftdwn delete 

ltdwn delete 

letdown delete 

delta delete 

deadband delete 

int delete 

int delete 

sgvlerr delete 

feedflow delete 

bvalv delete 

bvolum delete 

bvalv delete 

bvolum delete

Strips 

vaiable trips 

000OSO4time 0 It null 0 0,0 I 

O000508time 0 ge null 0 0.0 I 

0000509tempflO0010000 ge null 0 597.0 

l logical trips 

0000609 504 or 504 I 

"---1--i-1----1----1-----------1-

Loss of Feedwater : 501 "-- -- 1-- -- 1-- --- 1-- -- 1-- -- 1-- -1 -

O000501ltime 0 ge null 0 0.0 I 

"*----1-----1------------ --------- 1-*-

experimental power curve turn on 

-- -1-- -1-- ---- ---- ---- -- 1

0000530 time 0 ge null 0 0.0 I 

*----1----1--- ----- -------------- 1 

"Reactor Trip: 529, 609 

*-- -- 1- -1- -11- -1- -1- -1

0000529 time 0 ge null 0 10000.0 I 

0000609 529 or 529 I 

* primary coolant pump running on : 519 "-ý-- I1 .. 1-- --- 1-- ---1 1- -- 1----1-

0000519 time 0 It null 0 0-0 I 

Pressurizer Spray Cycling : 690 "*-- -- 1 .. 1-- 1 --- I ... -- 1- -1- --1 

0000551 time 0 ge timeof 626 0.0 I 

0000574 p 420010000 gt null 0 1.532e7 n 

0000575 p 420010000 It null 0 1.498e7 n 

"-- changed close setpoint from 15.16 MPa 

0000688 690 or 574 n 

0000689 -575 and -575 n 

0000690688 and 689 n

B-I
•Pressunzer experimental PORV Cycling & Latch Open: 625 

*--1---1 -..1-- ----1---- -1-- ---..1--- -1-

"latch open at 612 6 and close at 14.98 MPa 

0000581 time 0 ge null 0 6126 I 

0000552 p 420010000 It null 0 1498e71 

cycling 

0000570 p 420010000 gt null 0 1.62e7 n 

0000571 p 420010000 It null 0 1.59e7 n 

- changed lower setpoint from 16.0 MPa 

0000621 623 or 570 n 

0000622 -571 and -571 n 

0000623621 and 622 n 

0000624 581 and -552 n 

0000625 623 or 624 n 

exclude simultaneous open with SRV 

0000626 625 and -634 n 

---- 1- --- 1--- --- 1- -- 1- -1-- --1.-

*Pressunzer experimental SRV: 633 

"---1--i--1-- .. - 0 -- 1 --.. 1 -- 1-.-e1-n 

0000577 p 420010000 gt null 0 1.724e7 n 0000]578 p 420010000 It null 0 1 626e7 n 

-- lower setpoint changed from 16.46 MPa 

0000631 633 or 577 n 

0000632 -578 and -578 n 

0000633 631 and 632 n 

exclude simultaneous open with PORV 

0000634 633 and 633 n 

Steam Control Valve Manual Close: 612 

0000520 time 0 ge null 0 67 3 I 

0000616 520 or 520 n 

0000612504 or 504 n 

- - -...1- ----1-...1- ---.. 1-- -...1- ----1--

• MSCV Bypass Valve Open/Close 

--0005421 -... 1 .... 0000 1 0 6.5 n 

0000542 p 530010000 gt null 0 6.5e6 n 0000543 p 530010000 It null 0 6 3e6 n 

0000642 644 or 542 n 

0000643 -543 and -543 n 

0000644 642 and 643 n 

"--...1 ...---.1- - --..1-- -....1- --.... 1 - -.. .1--

mscv bypass 2 from 30 sec ... 1 -.. ... 1 -.. ... ... 1- -....1 -.. .. 1- - -.. .1 .... 

0000548 time 0 ge null 0 30.0 I .. .1 .-. .. .1 "-.. ... ... 1 . -.. .1 . -. .. .1 .-. .. .1 . . 

transient components 

.............................. ........ 1 -1-....... --... 

" primary coolant pump 1 S.... .,..... .... ° ................... t.°.•.°. **°... .... •.•..•.. °...

1350000 pcpumpl pump 

1350101 0.0366 0.0 0.099 0.0 90.0 0.319 

1350102 00000 

1350108 130010000 0.0 0.0 0.0 000100 

1350109 140000000 0.0 0 05 0.05 000100 

13502000 1.48950e+07 0.12394e+07 0.24622e+07 0.0 

1350201 0 8.6588 8.6589 0.0 

13502020 8.6575 8.65750.0 

1350301 0 0 0 -1 -1 519 0 

1350302 369.00000 0 87485 31550000 960 500.60000 1.431 

1350303 613.6 00 207.0000 0.0040000 19.598000 0.0 

13503100.0 0.0 0.0

single phase head curves 

head curve no. 1 

*- -1- -1-- -11- -1- -1- -1

13511001 1 

1351101 0.000000e+00 1.403600e+00 

1351102 1906100e-01 1 363600e+00 

1351103 3.896300e-01 1.318600e+00 

1351104 5939600e-01 1.232800e+00 

1351105 7.902000e-01 1.133600e+00 

1351106 1-000000e+0 1.OOOOOOe+00 

-- 1-- 1----1-- -- 1----1-- -- 1

* head curve no. 2 

-- -1- -11- -1- -1- - 1- 

13512001 2 

1351201 O.O00000eO-00 -6.700000e-01 

1351202 2.0000OOe-01 -5.000000e-01 

1351203 4.0000OOe-01 -2.500000e-01 

1351204 5.755400e-01 0.O00000e+O0 

1351205 7.443200e-01 2.583000e-01 

1351206 7.734800e-01 3.778000e-01 

1351207 8.631300e-01 6.326000e-01 

1351208 1.000000e+00 1.00000Oe+0 

*- -1- -1-- -1- -- 1-- -1-- ---

head curve no. 3 --- I-1 -- -- --...1--- --- 1--- -1-- --.. 1

1351300 1 3 

1351301 -1000000e+00 2.472200e+00 

1351302 -8.057400e-01 2.047400e+00 

1351303 -6.069000e-01 1.831000e+00 

1351304 -4.068300e-01 1.624000e+00 

1351305 -2.001710e-01 1.470500e+00 

1351306 0.000000e+00 1.403600e+00 

"head curve no. 4 "*- -1-- -1--i- --- 1- -1- -1-

1351400 1 4 

1351401 -1.000000e+00 2.472200e+00 

1351402 -8 229700e-01 1.996800e+00 

1351403 -6 333200e-01 1.589700e+00 

1351404 -4.553400e-01 1 327900e+00 

1351405 -2 710900e-01 1 194900e+00 

1351406 -1.771600e-01 1.060500e+00 

1351407 -9.073000e-02 1.015600e+00 

1351408 0000000e+00 9.342790e-01 "-1---1-- -- 1--- ---..1-- ---..1- --- 1--- ---..1--

• head curve no. 5 

13515001 5 

1351501 0.000000e+00 2.500000e-01 

1351502 2 0000Oe-01 2 800000e-01 

1351503 4.0000OOe-01 3.400000e-01 

1351504 4,1180OOe-01 2.768000e-01 

1351505 5976300e-01 4 584000e-01 

1351506 7934670e-01 6 992000e-01 

1351507 1.000000e+00 1000000e+00 

-1-----------1.. .1. 1-- --1-....... * head curve no 6 

S. . . . .. 1 -.. ... 1 -.. ... 1 ... - -..1 -.. ...1----.

B- 2
13516001 6 

1351601 0.O00000e+00 9.342790e-01 

1351602 9.109900e-02 9.229000e-01 

1351603 1.865090e-01 8.96300Xe-01 

1351604 2.717620e-01 8.750000e-01 

1351605 4.558720e-01 8.433000e-01 

1351606 5.744060e-01 8.355000e-01 

1351607 7.405760e-01 8.466000X"1 

1351608 7.666190e-01 8.469000e-01 

1351609 8.714710e-01 8.838000e-01 

1351610 1.000000e+00 1.000000e+00 "- -1--- -- 1-- -- 1-- -1-- -1--.--1-

"head curve no. 7 

"---- -1-- -1 - -1- -1- -1

13517001 7 

1351701 -1.000000e+00 -1.00OOOOe+00 

1351702 -8.000OO0e-01 -. 300000e-01 

1351703 -6.000OOOe-01 -3.000000e-01 

1351704 -4.000000e-01 -5.000OO0e-02 

1351705 -2.000000e-01 1.500000e-01 

1351706 0.000000e+00 2.500000e-01 • 1--1--1----1------1-- -1--

"head curve no. 8 •- 1-I- -I1- -I1- -I1- -- 1-- -1-

13518001 8 

1351801 -1.000000e+00 -1.000000e+00 

1351802 -8.0000O0e-01 -9.700000e-01 

1351803 -6.0000OOe-01 -9.500000e-01 

1351804 -4.000000e-01 -8.800000e-01 

1351805 -2.0000O0e-01 -8.000000e-01 

1351806 0.000000e+00 -6.700000e-01 

" single phase torque data 

"* torque curve no. 1 

- -1- -- 1- -- ---- ----- -- 1

13519002 1 

1351901 0.000000e+00 6.032000e-01 

1351902 1.930000e-01 6.325000e-01 

1351903 3.930000D-01 7.369000e-01 

1351904 5.955200e-01 8.331000e-01 

1351905 7.978200e-01 9.229000e-01 

1351906 1.000000e+00 1.000000e+00 

"*- -1- -1-- -- 1--1----------1---1- "torque curve no. 2 "*- -1-- -1-- ---- ----- ----- -- 1

13520002 2 

1352001 O.000000e+00 -6.700000e-01 

1352002 4.0000000-01 -2.500000e-01 

1352003 5.000000e-01 1.500000e-01 

1352004 7.372550e-01 5.265860e-01 

1352005 7.680490e-01 6.065940e-01 

1352006 8.672300e-01 7.436600e-01 

1352007 1.000000e+00 1.000000e+00 "*- -1--1-- -1--1--1- -1

torque curve no. 3 

""- -I- -1-- 1---- -- -- 1- -- 1-

13521002 3 

1352101 -1.000000e+00 1.984300e+00 

1352102 -8.009600e-01 1.394000e+00 

1352103 -6.063800e-01 1.097500e+00 

1352104 -4.068600e-01 8.220000e-01 

1352105 -1.992800e-01 6.648000e-01 

1352106 0.000000e+00 6.0320000-01 "-- 1-- - -1--1- -- 1--1- -- 1-- "torque curve no. 4 

"* 1- -1-- -- 1-- -- 1- -i-- -- 1

13522002 4 

1352201 -1 000000e+00 1.984300e+00 

1352202 -8.223400e-01 1.830800"+00 

1352203 -6+337100e-01 1.682400e+00 

1352204 -4.585300e-01 1.557000e+00

1352205 -2.670230e-01 1.436200e+00 

1352206 -1.761070e-01 1.387900e+00 

1352207 -8.931000e-02 1.348100e+00 

1352208 0.000000e+00 1.233610e+00 

*-- ---- --------- ----- ----- -- 1

"torque curve no. 5 

*-- ---- --------- -------- 1--1--1

13523002 5 

1352301 O.000000e+00 -4.500000e-01 

1352302 4.000000e-01 -2.500000e-01 

1352303 5.000000e-01 0.000000e+00 

1352304 1.000000e+00 3.569000e-01 "-- -1-- --- ---- ---- ----- -- 1

"torque curve no. 6 

*-- -1-- -1-- --------- -----1 -- 1

13524002 6 

1352401 0.000000e+00 1.233610e+00 

1352402 9.064300e-02 1.196500e+00 

1352403 1.885690e-01 1.109600e+00 

1352404 2.734700e-01 1.041600e+00 

1352405 4.586690e-01 8.958000e-01 

1352406 5.744800e-01 7.807000e-01 

1352407 7.381600e-01 6.134000e-01 

1352408 7.685200e-01 5.849000e-01 

1352409 8.700570e-01 4.877000e-01 

1352410 1.000000e+00 3.589000e-01 *----- 1----1------------------------1-

"torque curve no. 7 

*--- -1- --- 1-- ---- ----- ----- -- 1

13525002 7 

1352501 -1.000000e+00 -1.000000e+00 

1352502 -3.000000e-01 -9.000000e-01 

1352503 -1.000000e-01 -5.000000e-01 

1352504 O.000000e+00 -4.500000e-01 "*-- ---- -- ----- 1-- -- 1-- ----- -- 1

* torque curve no. 8 

°-- --------- -- 1-- -- 1-- ----- -- 1

13526002 8 

1352601 -1.000000e+00 -1.000000e+00 

1352602 -2.500000e-01 -9.000000e-01 

1352603 -8.000000e-02 -8.000000e-01 

1352604 0.000000e+00 -6.700000e-01 

• two - phase multiplier data from 19-1 test data

• head curve 

*.---1---------- -- 1--1--1

13530000 

1353001 0.000000e+00 0.000000e+00 

1353002 2.000000e-02 2.000000e-02 

1353003 6.0000OOe-02 5.000000e-02 

1353004 1.000000e-01 1.000000e-01 

1353005 2.000000e-01 4.600000e-01 

1353006 2.400000e-01 8.000000e-01 

1353007 3.000000e-01 9.600000e-01 

1353008 4.000000e-01 9.800000e-01 

1353009 6000000e-01 9.700000e-01 

1353010 8.000000e-01 9.000000e-01 

1353011 9.000000e-01 8.000000e-01 

1353012 9.600000e-01 5.000000e-01 

1353013 1.000000e+00 O.000000e+00 

"*-- -- 1-- --- --------- 1-----1-- -- 1-

torque curve *-- --- 1...I...1-- --- 1 -- --- -- 1-- -- 1- --

13531000 

1353101 0.000000e+00 0.000000e+00 

1353102 1.250000e-01 7.000000e-02 

1353103 1.650000e-01 1.250000e-01 

1353104 2.400000e-01 5.600000e-01 

1353105 8.000000e-01 5.600000e-01 

1353106 9.600000e-01 4.500000e-01 

1353107 1 000000e+00 0.000000e+00

B- 3
pump 2-phase difference data 

* head curve no. 1 

*---1-- -1-- -- 1-- --- 1-- -1--- -- 1-

13541001 1 

1354101 0.000000e+O0 0.O00000e+00 

1354102 1.0000OOe-01 8.300000e-01 

1354103 2.0000OOe-01 1.090000e+00 

1354104 5.000000e-O1 1.020000e+00 

1354105 7.000Oe-01 1.010000e+00 

1354106 9000000e-01 9.400000e-01 

1354107 1.000000e+00 1.00OOO0e+00 ----- 1 -. .1 - - 1 . . - - -- -1 

• head curve no. 2 

*- --- 1------1-----1- -1-- -- 1

13542001 2 

1354201 0.000000e+00 0.000000e+00 

1354202 1.000000e-01 -4.0000OOe-02 

1354203 2.000000e-01 0.000000e+00 

1354204 3.0000OOe-01 1.0000OOe-01 

1354205 4.0000OOe-01 2.1000OOe-01 

1354206 8.000000e-01 6.700000e-01 

1354207 9.OOOOOe-01 8.0000OOe-01 

1354208 1.000000e+00 1.000000e+00 

* ----- 1--1- -- 1-- --1---- -- 1-- --- 1

head curve no. 3 "---1----i----i- - --- - 1-- I...1--- --.. 

13543001 3 

1354301 -1.000000e+00 -1.160000e+00 

1354302 -9.0000OOe-01 -1.240000e+00 

1354303 -8.0000O0e-01 -1 .770000e÷00 

1354304 -7.0000OOe-01 -2.360000e+00 

1354305 -6 0000O0e-01 -2.790000e+00 

1354306 -5.0000OOe-01 -2,910000e+00 

1354307 -4.000000e-01 -2.670000e+00 

1354308 -2.500000e-01 -1.690000e+00 

1354309 -1.0000OOe-01 -5.0000OOe-01 

1354310 0.000000e+00 0.000000e+00 

*-- -. 1-- -- 1-- -1-- -1-- -1-- -1- "head curve no. 4 "----1-- --..1-...-- -- 1--....-1-- ..-. 1--

13544001 4 

1354401 -1.000000e+00 -1.160000e+00 

1354402 -9.0000OOe-01 -7+800000e-01 

1354403 -8.0000OOe-01 -50000OOe-01 

1354404 -7.0000O0e-01 -3.1000OOe-01 

1354405 -6.0000OOe-01 -1.700000e-01 

1354406 -5.000000e-01 -8. 0000Oe-02 

1354407 -3.5000OOe-01 0.000000e+00 

1354408 -2.0000O0e-01 5.0000O0e-02 

1354409 -1.0000OOe-01 8.0000OOe-02 

1354410 0.000000e+00 1.100000e-01 -... - . 1 .... ..- 1 ... ..- 1- .... 1- .... ...-1- ... .. 1---

head curve no. 5 "--...1 ---..1---.---1- --..1--.. -- 1....1---1

1354500 1 5 

1354501 0O.00000e+00 0000000e+00 

1354502 2 00000e-01 -3.400000e-01 

1354503 4 0000Oe-01 -6.5000O0e-01 

1354504 6 0000e-01 -9.300000e-01 

1354505 8 00000e-01 -1.190000e+00 

1354506 1 O00000e+00 -1.470000e+00 

head curve no 6 

13546001 6 

1354601 0 000000e+00 1 1000OOe-01 

1354602 1 0000e-01 1 300000e-01 

1354603 2 500000e-01 1.500000e-01 

1354604 4 000000e-01 1 300000e-01 

1354605 5.000000e-01 7 000000e-02

1354606 6.000000e-01 -4.000OOOe-02 

1354607 7,000000e-O1 -2.300000e-01 

1354608 8.000000e-01 -5.1000OOe-01 

1354609 9.000000e-01 -9.1000O0e-01 

1354610 1 O0OOOOe+00 -1 470000e+00 

*- -1--i- -- 1-- -1- -- 1-- -1

* head curve no 7 "--I--- -- 1---- --- ------- ---

13547001 7 

1354701 -1.000000e+00 0.000000e+00 

1354702 0.000000e+00 0.000000e+00 

"---1----1--------1------1

* head curve no 8 

*- ----- ---- ---- --------- 1-- --

13548001 8 

1354801 -1.000000e+00 0.O0OOOOe+00 

1354802 0.000000e+00 0.000000e+00 "--- -1- -- 1--- -- 1-- -1- -- 1

* torque curve no. I 

---- I1- --- 1--i- -- 1- -1-- -1-

13549002 1 

1354901 0.O00000e+00 6.032000e-01 

1354902 1.930000e-01 6.325000e-01 

1354903 3.930000e-01 7.369000e-01 

1354904 5.955200e-01 8.331000e-01 

1354905 7.978200e-01 9.229000e-01 

1354906 1.000000e+00 1.OOOO0e+00 

1- -1-- -1--i- --- 1- -1- -i

torque curve no 2 "- -1--i -- i - -- 1--i-- -1

13550002 2 

1355001 O.O00000e+00 -6.700000e-01 

1355002 4.00OOOOe-01 -2.,50000e-01 

1355003 5.000000e-01 1.500000e-01 

1355004 7.372550e-01 5.265860e-01 

1355005 7680490e-01 6.065940e-01 

1355006 8.672300e-01 7.436600e-01 

1355007 1-000000e+00 1.000000e+00 

*- -1--i- --- 1--i- ---1---- -1--

torque curve no. 3 

13551002 3 

1355101 -1.000000e+00 1.984300e+00 

1355102 -8.009600e-01 1.394000e+00 

1355103 -6.063800e-01 1.097500e+00 

1355104 -4.068600e-01 8.220000e-01 

1355105 -1.992800e-01 6.648000e-01 

1355106 0.000000e+00 6.032000e-01 "*- --- I- --- 1- -1...1-- -- 1-- -1---1-

"torque curve no. 4 "*- -- 1 .... -- -- -- 1 -1--1--- -- 1--- -- 1 

1355200 2 4 

1355201 -1.000000e+00 1.984300e+00 

1355202 -8.223400e-01 1.830800e+00 

1355203 -6.337100e-01 1.682400e+00 

1355204 -4.585300e-01 1.557000e-00 

1355205 -2.670230e-01 1.436200e+00 

1355206 -1.761070e-01 1.387900e+00 

1355207 -8.931000e-02 1.348100e+00 

1355208 0.000000e÷00 1.233610e+00 

"- ---- 1--- --. 1- ---- 1-- -- 1 1. - ---- 1 I--- 1-

"torque curve no. 5 

13553002 5 

1355301 0 O00000e+00 -4.500000e-01 

1355302 4 0000e-01 -2 500000e-01 

1355303 5 O000Oe-01 0.000000e+00 

1355304 1 000000e+00 3.569000e-01 

* torque curve no 6 

13554002 6

B- j
1355401 O.OOOOOe+00 1.233610e+00 

1355402 9.064300e-02 1.196500e+00 

1355403 1.885690e-01 1.109600e+00 

1355404 2.734700e-01 1.041600e+00 

1355405 4.586690e-01 8.958000e-01 

1355406 5.744800e-01 7.807000e-01 

1355407 7.381600e-01 6.134000e-01 

1355408 7.685200e-01 5.849000e-01 

1355409 8.700570e-01 4.877000e-01 

1355410 1.000OOOe+00 3.569000e-01 * -- 1-- -- 1-- -- 1-- -- 11- -- 1-- -- 1-

* torque curve no. 7 ,-- -- 1-- -- 1-- -- 1-- -- 1-- -- 1-- -- 1-

13555002 7 

1355501 -1.000000e+00 -1.000000e+00 

1355502 -3.0000OOe-01 -9.OOO0Oe-01 

1355503 -1.000000e-01 -5.OOOO0e-01 

1355504 0.0000O0e+00 -4.50000e-01 

torque curve no. 8 

*-- ---- ----- ----- ----- -- 1 -- 11

13556002 8 

1355601 -1.000000e+00 -1.0000000e+0 

1355602 -2.500000e-01 -9.OOO00e-01 

1355603 -8.0000OOe-02 -8.000000e-01 

1355604 0.000000e+00 -6.700000e-01 

* primary coolant pump 2 

1650000 pcpump2 pump 

16501010.0366 0.0 0.099 0.0 90.0 0.319 

1650102 00000 

16501081600100000.0 0.0 0.0 000100 

1650109 170000000 0.0 0.1 0.1 000100 

1650200 0 1.49088e+07 0.12394e+07 0.24619e+07 0.0 

1650201 0 8.2731 8.2732 0.0 

1650202 0 8.2717 8.27170.0 

1650301 135 135 135 -1 -1 519 0 

1650302 369.00000 0.87005.31550000 96.000000 500.60000 1.431 

1650303 613.6 0.0 207.433 0.004 19.5980 0.0 

1650310 0.0 0.0 0.0 

-- -- 1-- -- 1-- -- 1-- -- 1-- -- 1-- -- 1-

"spray valve 

4070000 spryly valve 

*4070101 406010000 420010000 3.3451e-4 15.432 15.432 000100 

4070101 406010000 420010000 3.3451e-4 0.0 0.0 000100 

4070201 0 .000000.000000 0.0 

4070300 tpvliv 

4070301 690 

*- -1--- --1--i-- ...--- 1--i--- -- 1--

•porv 

-...1-- -- 1----------------1----1--i

4250000 porv valve 

4250101 420010000810000000 2.4784e-5 0.0 0.0 000100 

4250201 0 .000000.00000 0.0 

4250300 trpvlv 

4250301 626 

"*--...1--1--1--.---1--- -1--1-- -- ...1 1-

experimental SRV "*-- -1---i- -- i--i-- --- 1

4300000 porv valve 

4300101 420010000820000000 624e-5 0.0 0.0 000100 

4300201 0 .000000 .00000 0.0 

4300300 trpvlv 

4300301 634

"steam control valve bypass *-- ---- ----- ----- ---------- -- 1

5460000 scvbyp valve 

5460101 530010000547000000 4.8e-4 0.0 0.0000100 

5460201 0 0.0 0.0 0.0 

5460300 tMvlv 

540301 644 

*-- ---- ---- ----- ---- ---- -- 1

* steam flow control valve 

*-- ---- ----- ----- -- 1- -1- -1

5500000 cv-p4-1 valve 

5500101 530010000 535000000 0.0052235 0.0 0.0 000100 

5500201 0 18.039 19.452 0.0 

5500300 mtrvlv 

5500301 612 616 0.05 0.6 550 

"*----1----------------------1----1--i 

* main feed water valve 

1-- ---- ----- ----- ----- 1--1

5600000 mnfeed tmdpjun 

5600101 545000000 510000000 0.05 

56002000 501 

5600201 0.0 0.67842 0.67642 0.0 

56002025.0 0.0 0.0 0.0

" reactor kinetics data 

30000000 point 

30000001 gamma-ac 48.7e+6 0.0 348.43 1.0 0.556 

30000002 ans79-1 

-- shoud not be changed for transient 

* delayed neutron constants 

30000101 0.0349 0.01275 

30000102 0.2035 0.03177 

30000103 0.1848 0.1181 

30000104 0.4046 0.3160 

30000105 0.1401 1.402 

30000106 0.0321 3.914

* power history 

30000401 4.87e+7 70. hr 

reacivity curve numbers 

30000011 609 

"moderator density reactivity table (slope change)

"30000501 0.62626e+3 

"30000502 0.66396e+3 

"30000503 0.71617e+3 "30000504 0.76112e+3 

"30000505 0.76837e+3 "30000506 0-79157e+3 

*30000507 0.81188e+3 

"30000508 0.86263e+3 

"30000509 0.93804e+3 

"30000510 0.99749e+3 

30000501 0.62626e+3 

30000502 0.66396e+3 

30000503 0-71617e+3 

30000504 0.76112e+3 

30000505 0.76837e+3 

30000506 0.79157e+3

-4.4769 

-3.2923 

-1.5692 

-0.1692 

0.04615 

0.6923 

1.2398 

2.2415 

3.9231 

5.1077 

-5.7396 

-4.2208 

-2.0118 

-0.1692 

0.04615 

0.6923

B- 5
30000507 0.81188e+3 1.2398 

30000508 0.86263e+3 22415 

30000509 0+93804e-+3 3+9231 

300005100.99749e+3 5.1077 

doppler reactivity table

30000601 293+16 1 375 

30000602 338.72 1.125 

30000603 422.05 0.682 

30000604 477.60 0.419 

30000605 505.38 0.274 

30000606 570.72 0.000 

30000607 588.72 -0.075 

30000608 695.83 -0.526 

30000609 922.05 -1.386 

30000610 1310.94 -2543 

30000611 1810.94 -3.865 

30000612 2088.72 -4.502 

30000613 2499.83 -5.392 

30000614 3027.60 -6.417 

volume weighting factors 

moderator temperature feedback 

30000701 230010000 0 0.314930 0. 

30000702 230020000 0 0.31493 0.0 

30000703 230030000 0 037014 0.0

* doppler feedback 

30000801 2300001 0 0.43153 0.0 

30000802 2300002 0 0.51686 0.0 

30000803 2300003 0 0.05161 0.0 

" "_ 1---- ---- -- -- 1 ----- ---- ---

scram reactivity data 

.-- 1-- .. -- 1--- -- 1- -1- -- 1-- -1

20260900 reac-t 609 

20260901 0.0 0.0 

20260902 0.5 -0.5 

20260903 0.59 -3.13 

20260904 0.65 -3.95 

20260905 0.75 -6.27 

20260906 0.83 -8.72 

20260907 0.90 -1200 

20260908 0.97 -17 12 

20260909 1.125 -20,67 

20260910 1.213 -22.10 

20260911 1.3 -22.78 

20260912 1.4 -23.17 

20260913 1,6 -23.32 

20260914 60.0 -23,32 

"mtc curve monitor .. . .- ......- . 

20593100 mtcmonl function 1 0 0 0 

20593101 rho 230010000933 

20593200 mtcmon2 function 1 0 0 0 

20593201 rho 230020000 933 

20593300 mtcmon3 function 1 0 0 0 

20593301 rho 230030000 933 

20593400 mtcmon sum 1.0 0 0 

20593401 0.0 0.31493 cntrlvar 931 

20593402 0 31493 cntrlvar 932 

20593403 0 37014 cntrtvar 933

20293300 reac-t 

20293301 0.62626e+3 -5.7396 

20293302 0.66396e+3 -42208 

20293303 0.71617e+3 -20118 

20293304 0.76112e+3 -0.1692 

20293305 0.76837e+3 0-04615 

20293306 0.79157e+3 0-6923 

20293307 0.81188e+3 1.2398 

20293308 0.86263e-4-3 2.2415 

20293309 0.93804e-+3 3-9231 

20293310 0.99749e+3 5.1077 

-- dtc curve monitor 

20597100 dtcmonl function 1.00. 0 

20597101 htvat 2300001 973 

20597200 dtcmon2 function 1.00. 0 

20597201 htvat 2300002 973 

20597300 dtcmon3 function 1.00. 0 

20597301 htvat 2300003 973 

20597400 dtcmon sum 1.00. 0 

20597401 0.0 0.43153 cntrivar 971 

20597402 0,51686 cntrlvar 972 

20597403 0.05161 cntrlvar 973 

20297300 reac-t 

20297301 293.16 1.375 

20297302 338.72 1.125 

20297303 422.05 0.682 

20297304 477.60 0.419 

20297305 505.38 0.274 

20297306 570.72 0.000 

20297307 588-72 -0.075 

20297308 695.83 -0.526 

20297309 922.05 -1.386 

20297310 1310.94 -2.543 

20297311 1810.94 -3.865 

20297312 2088.72 -4.502 

20297313 2499.83 -5.392 

20297314 3027.60 -6.417 

*- -1- -1- -1-- -1- -1- -1

power from experimental data 

I--- -- 1-- -1-- --- 1--- -1-- -1-- -1

20270000 power 530 

20270001 1.08400000e+00 4.878200307e+07 

20270002 3.48400000e+00 4.886505087e-+07 

20270003 4.68400000e-00 4.890413219e+07 

20270004 7.08400000e+00 4.895786901e+07 

20270005 9.48400000e+00 4.909465363e+07 

20270006 1.18840000e+01 4.874292175e+07 

20270007 1.42840000e+01 4.845469701e+07 

20270008 1.66840000e+01 4.843515635e+07 

20270009 1.90840000e÷01 4.822020909e+07 

20270010 2,14840000e+01 4.790755853e+07 

20270011 2.38840000e+01 4.788313271e+07 

20270012 2 62840000e+01 4.76877261 Oe+07 

20270013 2.86840000e+01 4.751186016e+07 

20270014 3. 10840000e+01 4.708685081e+07 

202700153 3.34840000e+01 4.712104696e+07 

20270016 3.58840000e+01 4.690609970e÷07 

20270017 3.82840000e+01 4.695006619e+07 

20270018 4.06840000e+01 4.672534860e+07 

20270019 4 30840000e+01 4.704288-432e+07 

20270020 4.54840000e+01 4 659344914e+07 

20270021 4 78840000e+01 4.664230079e+07 

20270022 5.02840000e+01 4.659344914e÷07 

20270023 5.26840000e+01 4 620263594e+07 

20270024 5.50840000e+01 4.571900460e+07

B- 6
20270025 5.74840000e+O1 4.442932104e+07 

20270026 5.98840000e+01 4.379913475e+67 

20270027 6.22840000e+01 4.278790559e+07 

20270028 6.46840000e+O01 4.149822202e+07 

20270029 6.70840000e+01 4.057004067e+07 

20270030 6.94840000e+01 3.890908456e+07 

20270031 7.18840000e+01 3.757054935e+07 

20270032 7.42840000e+01 3.564090916e+07 

20270033 7.66840000e+O01 3.282216895e+07 

20270034 7.90840000e+01 3.039424193e+07 

20270035 8.14840000e+01 2.798097041e+07 

20270036 8.38840000e+01 2.556281373e+07 

20270037 8.62840000e+01 2.344265211e+07 

20270038 8.86840000e+01 2.193313611e+07 

20270039 9.10840000e401 2.060437123e+07 

20270040 9.34840000e+01 1.918278821e+07 

20270041 9.58840000e+01 1.834742499e+07 

20270042 9.82840000e001 1.717498538e+07 

20270043 1.00684000e+02 1.594880896e+07 

20270044 1.03084000e+02 1.494735014e-07 

20270045 1.05484000e+02 1.385795834"+07 

20270046 1.07884000e-02 1.279299236e+07 

20270047 1.10284000e+02 1.198694013e+07 

20270048 1.12684000e+02 1.132255769e+07 

20270049 1.15084000e+02 1.072168239e+07 

20270050 1.17484000e+02 1.011103676e+07 

20270051 1.19884000e+02 9.471080147e+06 

20270052 1.22284000e+02 8.943482324e+06 

20270053 1.24684000e+02 8.489161978e+06 

20270054 1.27084000e+02 8.059267456e+06 

20270055 1.29484000e+02 7.595176779e,06 

20270056 1.31884000e+02 7.277641052e+06 

20270057 1.34284000e+02 6.906368511e+06 

20270058 1.36684000e.02 6.554636629e+06 

20270059 1.39084000e+02 6.306493213e+06 

20270060 1.41484000e+02 6.046579467e+06 

20270061 1.438840000+02 5.699732751e+06 

20270062 1.46284000e+02 5.470129995e+06 

20270063 1.48684000e+02 5.318689879e+06 

20270064 1.51084000e+02 5.030465143e+06 

20270065 1.53484000e+02 4.810632717e+06 

20270066 1.55884000e+02 4.629881611e+06 

20270067 1.58284000e+02 4.405164020e006 

20270068 1.60684000e+02 4.214642584e+06 

20270069 1.63084000e+02 4.014350818e+06 

20270070 1.65484000e+02 3.901992023e+06 

20270071 1.67884000&+02 3.716355752e+06 

20270072 1.70284000&+02 3.589341462e+06 

20270073 1.73884000e+02 3.349968376e.06 

20270074 1.75084000e+02 3.276690900e+06 

20270075 1.77484000e+02 3.095939795e-06 

20270076 1.79884000e+02 3.086169465e.06 

20270077 1.81084000e+02 3.017777154e+06 

20270078 1.83484000e+02 2.807715058e+06 

20270079 1.85884000e+02 2.695356263e+06 

20270080 1.87084000e+02 2.656274943e+06 

20270081 1.89484000e+02 2.568341972e+06 

20270082 1.91884000e+02 2.495064497e+06 

20270083 1.94284000e+02 2.382705702e+06 

20270084 1.95484000e+02 2.328968866e+06 

20270085 1.96684000e+02 2.299657896e+06 

20270086 1.97884000e+02 2 260576576e.06 

20270087 1.99084000e+02 2.211724926e+06 

20270088 2.00284000e+02 2.182413936e+06 

: reactor power in MWt 

20505400 reacpor sum 1.0e-06 00 1 

20505401 0.0 1.0 rktpow 0 

* end of input

B- 7
NRC FORM 335 U.S. NUCLEAR REGULATORY COMMISSION 1. REPORT NUMBER 

(2-89) NRCM (Assigned by NRC, Add Vol, Supp. Rev. 1102. 201. 3202 BIBLIOGRAPHIC DATA SHEET *WAdnlmNnmi .,Nu....m, l.ny.) n. 

•s=, •/NUREG/IA-01 one 92 

2. TITLE AND SUBTITLE 

Assessment of RELAP5/MOD3.2.2 Gamma With the LOFT L9-3 

Experiment Simulating Anticipated Transient Without Scram 3. DATE REPORT PUBLISHED 

MONTH YEAR 

January 2001 

4. FIN OR GRANT NUMBER 

5. AUTHOR(S) 6. TYPE OF REPORT 

J.K. Suh, Y.S. Bang, H.J. Kim Technical 

7. PERIOD COVERED (Incusive Dates) 

8. PERFORMING ORGANIZATION - NAME AND ADDRESS (f NRC. pwe DWnn, Offi or Regio. U.S. Nuer Reguiatoy Cormission, and nmeing addres" i contractor, 

providee and nuifirg ad*-s) 

Korea Institute of Nuclear Safety 

19 Kusung-Dong, Yusong-Gu 

Taejeon, KOREA, 305-338

9. SPONSORING ORGANIZATION - NAME AN D ADDRESS [I9 NRC, "yp "Sern as above', I contractor, provide NRC Division, OfiJce or Region, U.$. Nulear Regulatory Comrnission, 

and mAiVg addess.) 

Division of Systems Analysis and Regulatory Effectiveness 

Office of Nuclear Regulatory Research 

U.S. Nuclear Regulatory Commission 

Washington, DC 20555-0001 

10. SUPPLEMENTARY NOTES 

11. ABSTRACT (2rOwords or lss) 

The present work is to assess the capability of RELAPS/MOD3.2.2 gamma to predict the system response following an 

Anticipated Transient Without Scram (ATWS) event. The experiment L9-3 which is a unique nuclear experiment simulating an 

ATWS event induced by loss of feedwater accident in Loss-of-Fluid-Test (LOFT) is calculated. The experimental condition and 

sequence are reviewed and a calculation modeling is developed with the important test specific features. The result of RELAP5 

calculation is compared with the experimental data, and the predictability of the system response of the primary coolant system (PCS), the reactor power, and the steam generator (SG) secondary system is discussed. The base case showed a good 

agreement for the RCS pressure, temperature and reactor power with the experimental data. Therefore, it is shown that the 

RCS thermal-hydraulic response, the reactor power response, and the secondary system response following the LOFT L9-3 

experiment can be reasonably predicted by the RELAPS code under the current modeling scheme, and thus, that the code can 

be reasonably applied to the analysis of the system thermal-hydraulic response during the ATWS event in real plant. In 

addition, four parameters such as subcooled discharge coefficient of PORV, loss coefficient of spray valve, steam generator nodalization and moderator density coefficient (MDC) were selected and the effect of those parameters on the total discharged 

energy through the pressurizer safety relief valves is evaluated.

12. KEY WORDS/DESCRIPTORS (List words orphroaes tWat wiN aist researcesau si -cfing Me report.) 13. AVAILAILITY STATEMENT 

RELAP5/MOD3.2.2 Gamma unlimited 

ATWS 14. SECURITY CLASSIFICATION 

LOFT ("95 Page) 

unclassified 

(rhis Report) 

unclassified 

15. NUMBER OF PAGES 

16. PRICE

NRC FORM 335 (249)
Federal Recycling Program
ý'v tilixj/ LA-tfl.7ý •3bii~viI UF ' KELAPI/MUO3.2.2 GAMMA WITh THE LOFT L9-3 EXPERIMENT 

SIMULATING AN ANTICIPATED TRANSIENT WITHOUT SCRAM

UNITED STATES 

NUCLEAR REGULATORY COMMISSION 

WASHINGTON, DC 20555-0001 

OFFICIAL BUSINESS 

PENALTY FOR PRIVATE USE, $300

JANUARY 2001