NUREG/IA-0125

* International

Agreement Report

Assessment of RELAP5/MOD2

Computer Code Against the

Natural Circulation Test

Data from Yong-Gwang Unit 2

Prepared by

N. Arne, S. Cho

Korea Electric Power Corporation

Research Center

117-15 Yongjeon-Dong, Dong-Gu

Daejon, Korea

H. J. Kim

Korea Institute of Nuclear Safety

P.O. Box 16, Daeduk-Danji

Daejon, Korea 305-353

Office of Nuclear Regulatory Research

U.S. Nuclear Regulatory Commission

Washington, DC 20555

June 1993

Prepared as part of

The Agreement on Research Participation and Technical Exchange

under the International Thermal-Hydraulic Code Assessment

and Application Program (ICAP)

Published by

U.S. Nuclear Regulatory Commission
NOTICE

This report was prepared under an international cooperative

agreement for the exchange of technical information. Neither

the United States Government nor any agency thereof, or any of

their employees, makes any warranty, expressed or implied, or

assumes any legal liability or responsibility for any third party's

use, or the results of such use, of any information, apparatus product or process disclosed in this report, or represents that its use

by such third party Would not infringe privately owned rights.

Available from

Superintendent of Documents

U.S. Government Printing Office

P.O. Box 37082

Washington, D.C. 20013-7082

and

National Technical Information Service

Springfield, VA 22161
NUREG/IA-0125

International

Agreement Report

Assessment of RELAP5/MOD2

Computer Code Against the

Natural Circulation Test

Data from Yong-Gwang Unit 2

Prepared by

N. Arne, S. Cho

Korea Electric Power Corporation

Research Center

117-15 Yongjeon-Dong, Dong-Gu

Daejon, Korea

H. J. Kim

Korea Institute of Nuclear Safety

P.O. Box 16, Daeduk-Danji

Daejon, Korea 305-353

Office of Nuclear Regulatory Research

U.S. Nuclear Regulatory Commission

Washington, DC 20555

June 1993

Prepared as part of

The Agreement on Research Participation and Technical Exchange

under the International Thermal-Hydraulic Code Assessment

and Application Program (ICAP)

Published by

U.S. Nuclear Regulatory Commission
NOTICE

This report is based on work performed under the sponsorship of The Korea

Advanced Energy Institute of Korea. The information in this report has been

provided to the USNRC under the terms of an information exchange agreement

between the United States and Korea (Agreement on Thermal-Hydraulic Research

between the United States Nuclear Regulatory Commission and The Korea Advanced

Energy Research Institute, May 1, 1986). Korea has consented to the publication

of this report as a USNRC document in order that it may receive the widest

possible circulation among the reactor safety community. Neither the United

States Government nor Korea or any agency thereof, or any of their employees,

makes any warranty, expressed or implied, or assumes any legal liability of

responsibility for any third party's use, or the results of such use, or any

information, apparatus, product or process disclosed in this report or

represents that its use by such third party would not infringe privately

owned rights.
TABLE OF CONTENIS

ABSTRACT 1

LIST OF TABLES - 2

LIST OF FIGURES - 3

CHAPTER 1. INTRODUCTION 4

CHAFPER 2. PLANT DESCRIPTION 6

CHAPTER 3. PLANT TRANSIENT DESCRIPTION 15

CHAPTER 4. NODALIZATION AND INITIALIZATION 20

CHAPTER 5. CALCULATION RESULTS AND ANALYSIS 28

CHAPTER 6. SENSITIVITY STUDY 41

CHAPTER 7. RUN STATISTICS 45

CHAPTER 8. CONCLUSIONS 49

REFERENCE --------------------------------------- 50

Appendix A ----------------------------------- A.1

iii

Abstract

The results of the RELAP5/MOD2 computer code, simulation for the

Natural Circulation Test in Yong-Gwang Unit 2 are analyzed here and

compared with the plant operation data. The result of comparison

reveals that the code calculation does present well the overall

macroscopic behaviors of thermalhydraulic parameters in primary and

secondary system compared with the plant operating data. The

sensitivity study is performed to find out the effect of steam dump

flow rate on the primary temperatures and it is found that the primary

temperatures are very sensitive to the steam dump flow rate during the

Natural Circulation. Because of the inherent uncertainties in the

plant data, the assessment work is forcussed on phenomena whereby the

comparison between plant data and calculated data is based more on

trends than on absolute values.

I
LIST OF TABLE

PAGE

Table 1. Steam dump control system setpoint - 14

Table 2. Acceptance Criteria 19

Table 3. Initialization Data 26

Table 4. Plant data for initial temperature - 27

Table 5. Summary of Run Statistics 48

2
LIST OF FIGURE

Figure

Figure

Figure

2.1

2.2

2.3

Figure 2.4

Figure

Figure

Figure

Figure

Figure

Figure

Figure

Figure

Figure

Figure

Figure

Figure

Figure

Figure

3.1

4.1

5.1

5.2

5.3

5.4

5.5

5.6

5.7

6.1

6.2

6.3

7.1

7.2

PAGE

P1R schematic diagram 10

PZR equipment Arrangement 11

Schematic Representation of the

Steam Dump Control System - 12

Functional Diagram of the

Steam Dump Control System 13

RCS Flow Fraction 18

Nodal ization 25

RCS Flow Rate 34

Hot Leg Temperature 35

Cold Leg Temperature 36

DEL T 37

Average Temperature 38

Steam Generator Pressure 39

Steam Dump Flow Rate 40

Sensitivity Study( dump flow rate ) 42

Sensitivity Study ( T hot ) 43

Sensitivity Study ( T cold ) 44

CPU 46

Time Step Size 47

3
1.0 Introduction

Natural Circulation, hereinafter named NCT, is one of the most

important heat transfer mechanisms to remove decay heat from a

pressurizer water reactor when the reactor coolant pumps are not

available. This situation could be occured during a small break

loss of coolant accident, during a station black-out transient,

during a steam generator tube rupture transient or when the RCP

are ceased due to other reasons.

NCT was conducted at Yong-Gwang Unit 2 on October 20, 1986.

This initial start up program test was structured to demonstrate the

capability of the Nuclear Steam Supply System ,hereinafter named NSSS,

for removing fission product decay heat by natural circulation.

The objective of this work is to perform the best estimate

transient analysis using the RELAP5/MOD2/36.04 computer code to

demonstrate that Reactor Coolant System Natural Cooldown Test

which was performed at Yong-Gwang unit 2 as a part of the initial

po•cer ascension program, can be simulated by this best estimate

computer code. The code assessment work presented in this report is

based on all the available data( from plant computer and plant

recordings) from this incident. Although the initial plant conditions

are well known, it must be emphasized that the the quantity and the

quality of the available data from real plant are inferior to the well

4
instrumented test facility data. Hence the objective of this study is

to assess a code performance based on the comparison of trends rather

than the comparison of absolute values.

The plant description and transient are described in chapter 2 and

chapter 3. In chapter 4. the plant nodalization and initialization

methodology are presented. The calculation results are analyzed in

chapter 5. The result of sensitivity study is introduced in chapter

6. Finally, the run statistics and conclusions are added in chapter

7 and chapter 8.

5
2.0 Plant description

The Yong-Gwang Nuclear Power Plant Unit 2, located on the

southwestern coast of the Republic of Korea, is comprised of PUR

NSSS and the Turbine Generator ,hereinafter named TG, designed by

Westinghouse.

2.1 Primary system

As shown in Figure 2.1, the reactor coolant system ,hereinafter

named RCS, is composed of the reactor vessel, reactor coolant

pump, hereinafter named RCP, pressurizer and steam generator. The

reactor vessel is cylindrical, with a welded, hemispherical bottom

head and a removable, flanged and gasketed, hemispherical upper head.

The vessel contains the core, core support structure,control rods,

neutron pads, and other parts directly associated with the core. The

control rods are operated by sealed drive mechanisms mounted on the

upper head. The vessel has inlet and outlet nozzles located in a

horizontal plane just below the upper head flange but above the top

of the core. Coolant enters the vessel through the inlet nozzles

and flow down the core barrel vessel wall annulus, turns at the

bottom and flows up through the core to the outlet nozzles. The

vessel is carbon steel with weld deposited austenitic stainless

steel or inconel cladding on all surfaces exposed to the reactor

coolant. The core generates 2785 Mwt and contains three independent

primary coxolant loops, each of vhich has one RCP and one steam

generator.

6
Three RCPs are identical single speed centrifugal units driven

by air-cooled, three phase induction motors. The shaft is vertical

with the motor mounted above the pump. A flywheel on the shaft

above the motor provides additional inertia to extend pump

coastdown.

The steam generators are vertical shell and LI-tube evaporators with

integral moisture separating equipment, a 48000 ft2 heat transfer area

and a 964 psia steam pressure at full poIer. The reactor coolant flows

through the inverted U-tubes, entering and leaving through the nozzles

located in the hemispherical bottom bead of the steam generator. The

head is divided into inlet and outlet chambers by a vertical

partition plate extending from the head to the tube sheet. Steam

is generated on the shell sides and flows upward through the

moisture separators to the outlet nozzle at the top of .the vessel.

The heat transfer tubes are inconel, the primary side of the tube

sheet is clad with inconel, and the interior surface of the reactor

coolant channel head and nozzles are clad with austenitic stainless

steel.

A pressurizer, with a 1400 ft3 volume and 1400 Mw heater capacity ,as

shown in Figure 2.2, provides a point in the RCS where liquid and

vapor can be maintained in equilibrium under saturated conditions for

pressure control purpose. The pressurizer is designed to accommodate

positive and negative surges caused by load transients. The surge

line, which is attached to the bottom of the pressurizer, connects the

pressurizer to the hot leg of a reactor coolant loop.

7
Auxiliary system components are provided to charge the RCS and add

makeup water, purify reactor coolant water, provide chemicals for

corrosion inhibition and reactivity control, cooling system

components, remove the decay heat when the reactor is shutdown, and

inject the cooling water to the reactor core under the emergency

condition.

2.2 Secondary system

The secondary system conveys steam from the steam generators to

the turbine generator system. The system consists of main steam

pipings, power operated relief valves, safety valves, main steam

isolation valves and the atmosphere and condenser dump valves.

The steam dump control system whose schematic representation is

shoun in Figure 2.3 , is comprised of 16 valves which can bypass

steam to the condenser and to the atmosphere. These valves have a

total capacity of approximately 70 % of the full load turbine steam

flow at full load steam pressure. These steam dump valves are

working by the signal from the deviation between the actual pressure

and the reference pressure in the steam generator. The functional

block diagram of the steam dump control system can be found in

Figure 2.4. The steam dump valves are actuated to maintain the

steam pressure within control range until a new equilibrium

condition is reached and strokes full open or modulated,

depending upon the magnitude of the pressure error signal resulting

from the transient.
2.3 Plant data acquisition

For the parameter values of plant operating data, a global recorder

uncertainty of 1.5 % should be added to the instrument uncertainty

[51.

The instrument uncertainty is estimated 1.5 % [5]. Hence some

engineering judgement is required to synchronize the recorder data

with the calculated data because they can be done on the basis of some

important events and on the basis of the timing in the plant computer

listing.

9
0

Fiyjuru 2.1 Reactor Coulaiut Systemi
SAFETY %v-.,'S

SPRAY

VALVES

TO CHIEMICAL AMt

VOLN'. CCKTPOL

CEKRATORSYSTEM

,)PRESSURE

LEVEL

IRIZER

TO REACTCR

VESSEL

REL IE F ~J S

1!

TO N .S SUR I ZER

iR EL I EF 'I -'

REACTOR

COOLAXT

puMP.

; - G

Figure 2.2.. Eressq:i~er Pressure and Level Associated Equipment Arrangement
A1MOSPHERIC

STEAM RELIEF

VALVES

SAFETY (3 VALVES)

VALVE I STOP

A VALVE

ATMOSPHERIC STEA;M

DUMP VALVES

(10 VALVES)

CONDENSER STEAM

DUMP VALVES

(6VALVES)

'.-4

Figure 2.3 Schematic Representation of the S~e-.m Dump Control System
T REFAUCTIONEERED

T AVGTRIP BANK A

CO.1.Et0S: :j

VALVES

TRIP BANK 3

CO;;DE t:SER

VALVES

TRIP CANK C

A T/,OSP :. 21IC

VALVES

TRIP BAtN< 0

ALVEOSP.RIC

VALVE S

TNO LOADO SELiECTC= S,.':ITCH

SET STEAM OUMP HEADER

PRESSURE T PRESSURE CONTROLLER

ST=M.•, H. T _. 1 I

H ,ADER - K II r. S

PPESSURE

TURBINE 7 S

IMPULSE

CHAIMBER 1 * S

PRESSURE

CON0ENSER AVAILABLE SIGNAL

TURBINE TRIP

TURBINE TRIP

/

S----T3

",ODULATI. % JAL U,.. VALVES

ALLOW

CO:;0E t R

S STEAM 0'*,;%'

OG VALVES -3 •E

:EITHER

TRIFPED :;ENJ

OR ItOO-lATED

"LLOW HALF )F

:3O'•E'SER STEAM

:UP VALVE! TO

" EITHER T.:PPED

"ni' OR

y0:)ULATE 0

'-4

Figure 21 Functional Block Diagram ol tihe Sceam Dump Control System
Table 1 Steam dump control system setpoints

set point

Header pressure controller

set pressure 76.8 kgf/cm2

proportional gain K 14% /(kgf/cm2)

Reset time constant 180 sec

14
3.0 Plant transient description

The natural circulation in a closed loop is an effective means for

the core cooling of a reactor after the main coolant pump has tripped.

In particular, for pressurized water reactors, single phase natural

circulation is essential for eliminating the decay heat generated in

core without the help of pump.

Single phase natural circulation is driven by an overall fluid

density gradient between the hot and cold sides of the loop. It occurs

when only fluids in the liquid phase is present in the primary system.

The circulation carries the heat from the core through the hot leg to

the steam generator. In steam generator, it is cooled by the secondary

system and returns to the core through the cold leg.

NCT is initiated by manually tripping all three RCPs simultaneously

witlout reactor trip, then maintain the RCS in hot standby for

approximately 30 minutes. In case of loss of main pumps flow

following the RCP trip, differential gravity heads between cold and

hot fluids, respectively in the steam generators and in the core

regions, create a driving force which is counter balanced by the

pressure losses all around the loop. This constitutes an inherently

safe mechanism suitable in removing nuclear decay heat for several

minutes even in the absense of emergency cooling.

Right after tripping all three RCPs, the RCS flow decreases

following the loss of enforced coolant flow. The RCS flow then

15
decreases exponentially as the RCPs coasted down prior to the RCS

developing natural circulation. As shown in Figure 3. 1, on tripping

all RCPs , the RCS flow rate does not drop to the equilibrium flow.

The RCS flow rate decreases to 50% RCS flow rate during 10 seconds and

approximately after 300 seconds it reaches to the equilibrium flow.

The hot leg temperatures increases as the RCS flow decreases and

results in pressurizer water level increase, maintaining a constant

RCS mass by matching charging and letdown flow. Pressurizer spray

from the loops will be lost and pressurizer pressure increases during

transition to natural circulation. The RCS temperature is determined

by the steam dump flow rate in the constant steam pressure mode. The

hot leg temperature increases sharply due to the sudden reduction of

RCS flow resulting from the RCP trip. The increase of the hot leg

temperature causes to increase the steam pressure. The increase of

steam pressure results in the increase of steam dump flow rate,

because the steam dump control system is operated by a steam pressure

mode. The increase of steam dump flow rate removes more heat from the

coolant and this causes the decrease of the cold leg temperature.

Recognition of the existance of natural circulation is crucial to the

safe performance of this test. During natural circulation, stable

core thermocouple readings, stable distinct T cold and T hot based on

the wide range temperature recorders, existence of steam dump to

condenser or atmosphere are indicative of natural circulation cooling.

16
This recognition of the existence of natural circulation should

continue at least for 30 minutes. After 30 minutes, the reactor power

increases and is synchronized to the grid again and returns to 100 %

power level. This test was performed at the plant with satisfying the

acceptance criteria specified in Table 2.

17
0.80

0. (60 C

U

C

L.

0.40

0.20 -

0.00

0.0(

-1

2.00

' I 4.00 ' I

6.00

' I 8.00 I

10.00

tim e(sec)

Figure 3.1 RCS Flow Fraction
Table 2 Acceptance Criteria

1. RCS loop T avg and Del T must be less than 309.2 c and 34.99 c

2. RCS T hot must be less than or equal to 320.0 c

3. Recognition of the existence of natural circulation

- Stable thermocouple readings

- Stable distinct T cold and T hot

- Existence of steam dump to condenser or atmosphere

19
4.0 RELAP5/MOD2 plant nodalization and initialization

The used code version was RELAP5/MOD2/CY 36.04 and was processed on

a CDC machine cyber 170-875. The input deck was prepared by KEPCO. The

nodalization philosophy is based on the guideline of RELAP5 code

manual and the detailed data for specific volumes and junctions are

based on the design and drawing values for Yong-Gwang Unit 2.

The nodalization can be found in Figure 4.1, which was previously

developed for the LOCA analysis and was qualified through the analysis

of Net Load Trip Test in the Yong-Gwang Unit2. The whole system is

devided into 118 volumes, 122 junctions and 79 heat slabs. The reactor

core is described with 6 volumes and 6 core heat slabs. The reactor

power is computed by using the RELAP5/MOD2 point kinetics model,

which assumes that powr can be separated into the product of space

and time functions. The reactor vessel consists of 4 volumes, ie, the

downoomer, the lower plenum and core inlet, the upper plenum, the

upper head and control rod guide tube. Steam generator is divided into

the primary and the secondary system with the boundary of U-tube and

the primary system is described with 10 volumes and the secondary with

9 volumes. Two steam generators are lumped in order to match with the

RCP loop. Separator is depicted by using the RELAPS SEPARATOR model.

The RCP and the accumulator are also modeled in this simulation.

RELAPS ANS79 model is applied for computing the decay heat and the

20
negative reactivity of temperature and doppler coefficient is

considered. The plant consists of 3 loop coolant system but for the

convenience of the analysis, the reactor coolant system is modeled

with two loops, one is the loop which lumps the two loops in which the

pressurizer is not connected and the other is the single loop in which

pressurizer is added. Each loop is depicted with the RELAP5 pipe

component and consider the fluid-metal interaction by using the heat

structure. The safety and relief valve nodes of steam generator and

pressurizer are not included because it was confirmed by the simple

calculation that they did not open during this transient.

The outlet of both S/Gs are connected to a single volume, steam

header, which is connected to the turbine and the condenser volume.

The condenser volume in this nodalization contains the atmosphere

volume. According to the test result performed in the pouer plant,

the steam dump system was operated manually and the history of steam

dump control valve opening is not known. The test procedure

recommends that the steam dump control system be operated

automatically in the constant steam pressure mode. Therefore in the

RELAP5/MOD2 initialization, the steam dump valve opening is modeled to

be determined by the difference between the steam header pressure and

the set point pressure(76.8 kgf/cm2). In this case, the steam header

pressure is used in a proportional plus integral controller to supply

a modulated signal to the condenser dump valves. The condenser dump

21
valves are described using the time dependent junction and the dump

flow rate is modelled as a boundary condition which is determined by

the pressure difference between the steam header and the set point.

Turbine is modelled with the time dependent volume.

For the steady state initialization, the RELAP5/MOD2 code requires

the initial conditions which results in zero time deviation for each

of balance equation. The first part of activity consisted in achieving

the boundary and initial conditions in the loop (ie, secondary

feedwater flow, steam dump flow rate, RCS flow rate and the

temperature distribution of the hot leg at cold leg in the primary

system without pump running). The steady state initialization should

be obtained with the condition of closing the governor valves. Only

the steam dump flow makes a role of the secondary heat sink during the

natural circulation. The swumaries of the steady state initialization

values for the important thermal hydraulic parameters are shown in

Table 3.

The core power used in the RELAP5/MOD2 simulation was 3% full power'

which is equal to fission product decay heat power. The main purpose

of this test is to prove the capability of NSSS to remove the fission

product decay heat by natural circulation, thus the core power should

be maintained with 3 % full power without reactor trip.

22
As shown in Table 4, the plant operating data of the initial hot leg

and cold leg temperatures for each loop reveal somne differences.

Therefore, the initial hot leg and 'cold leg temperatures are

calculated by averaging the three operating values in order to

minimize the data collection error. The comparison between the plant

operating data and the simulation data for the initial hot leg and

cold leg temperature shows a little difference, but this difference

can be neglected if the instrument and recording uncertainty is

considered.

The initial RCS flow rate is determined with the RCS f low rate for

the 100% full power. The RCS flcw rate should be determined to be

coupled with the temperature of hot leg and cold leg in the reactor

coolant system in order to obtain the steady state condition at 3%

full power. The RCS f low rate used in this simulation is the f low

rate which is determined by steady state initialization at 100 % full

power. The plant operating data for the RCS f low at 100 % full powr

is not available.

Pressurizer pressure is used as a boundary condition because the

pressurizer pressure and water level control at the start up test is

in manual and pressurizer water level is at the hot no-load programed

value of 22 % level of span.

The pump model has the capability of coastdown effect of R.CP after it

is tripped, which is one of the most important thermal-hydraulic

characteristics for the heat transfer mechanism during the single

phase natural cinzulation.

23
The feedwater flow rate is determined as a boundary condition by

applying the time dependent junction at the feedwater valve and this

boundary conditions is determined with a value of the auxiliary

feedvater flow rate( 47 kg/sec).

Steam generator water levels are at the nominal hot no-load value of

50% level of span and being maintained by a auxiliary feedwater flow

rate.

All reactor trip function models are eliminated in the RELAP5/MOD2

simulation for preventing reactor trip.

The transients are initiated after 200 seconds steady state run in

the REILAP5/MOD2 simulation. Thus the figures for comparison between

the plant data and the calculation results indicate the transients

after the elapsed time of 200 seconds. As mentioned above, only the

steam dump flow is the secondary heat sink during the natural

circulation. Therefore, the steady state is reached with the help of

steam dump system. At the steady state condition, the steam dump

flow rate is 63.1 kg/sec.

24
C-q

...;Hec~t Structurc

If~ %Cross flow Junction

Fig 4.1 tNodalizat1ofl
Table 3 Initialization Data

Plant Data RELAP5/MOD2 Data

+

1.0 Core

T cold 291.8 ( c) 292.0 ( c)

T hot 293.1 ( c) 293.5 ( c)

Core Power 83.3 Mwt 83.3 1wt

+4+

:2.0 Pressurizer:

Lew 1 0. 22 0. 22

Pressure 157 (kgf/cm2) 157.4 (kgf/cm2)

13.0 S/G

Level 0.5 0.5

Pressure 66.4 (kgf/cm2) 67.2 (kgf/cm2)

+

26
Table 4 Plant Data for Initial Temperature

initial temperature ( c)

loop 1 loop 2 loop 3 average

T hot 293.5 293.7 292.1 293.1

T cold 292.5 293.0 290.0 291.8

27
5.0 Calculation results and Analysis

The single phase natural circulation in a RCS loop is the only

effective means for the core cooling of a reactor after the main

reactor coolant pump has tripped. During a single phase natural

circulation, heat generated in the core is transported to the heat

exchanger where it is dissipated. The driving mechanism for this

energy transport is an overall loop fluid density difference caused by

changes in the temperature of the fluid as it flows through the loop.

The coolant in the core, hot leg and upflow side of the heat exchanger

is less dense than coolant in the down flow side of the heat exchanger

and cold leg, thus causing an imbalance gravity head which drives the

single phase flow.

The plant operating data is compared with the calculated data by

RE1tAP5/MOD2 simulation for the important thermal-hydraulic parameters.

Uncertainties in boundary and initial conditions do not allow the

complete agreement between the plant operating data and the calculated

data. Therefore an emphasis is given to the ascertainment of the

capability of the code in predicting the measured transients instead

of the complete agreement by confirming the acceptance criteria

specified in the test procedure.

During the normal operation of RCP, the RCS flow rate is about 4800

kg/sec and the core power is 3 % full power. After all RCPs are

28
tripped, they experience the coast down prior to the RCS's developing

the Natural Circulation. Shown in Figure 5.1 is the RCS flow rate

trend which explains well the effect of the coast down. It reaches to

the steadv flow rate whose value is 250 kg/sec equal to 5.2 % full

RCS flow rate after 400 seconds.

The test procedure requires at least 5% of full RCS flow rate during

the natural circulation and the calculated RCS flow satisfies this

criteria. The effect of core power on single phase natural circulation

fl•w is strong. Increasing the core power causes the increase of

overall density gradient between the hot and cold sides of the system,

resulting in higher loop mass flow rate. It is found that there is

some influence of secondary flow rate to the primary flow. Higher

secondary feedwater flow rate causes lower temperature difference

between hot leg and cold leg because of higher cooling effect. This

makes lower primary flow, rate. In this RELAP5/MOD2 simulation, the

constant feed water flow rate is used, which is equal to the auxiliary

feedwater flow rate. The plant operating data for RCS flow rate is not

available, thus the comparison between the plant operating data and

the simulation data for the RCS flow rate is not made.

Right after tripping all three RCPs, the decrease in the RCS flow

rate limits the amount of energy which can be removed from the core.

The RCS flow rate decrease is not matched by an equivalent drop in the

29
core power. This unbalance of power drop results in increasing the hot

leg temperature. Figure 5.2 shows the comparison between the

calculated and the measured temperature of the hot leg in the RCS.

Both trends show the sharp increase in the hot leg temperature. The

calculated temperature increases up to 313 c during 400 seconds

following the RCP trip and then reaches to the equilibrium state. The

measured temperature reveals a little different trend. It goes up to

311 c with the same slope as the calculated one during 500 seconds and

then reach to the equilibrium state with some oscillation. This

instability due to the oscillation reflect to the thermal hydraulic

parameters as shown in the other figures. The period of measured

temperature oscillation ranges around 450 seconds, while the

calculated one does not show any oscillation. The difference between

the measured and calculated hot leg temperature appears to be induced

by the steam dump flow rate difference. The s~team dump control system

was in manual mode at the startup test and the maneuvering history

of the steam dump valve is not available. In the RELAP5/140D2

simulation, it is modelled in auto mode. According to the result of

comparison, it is assumed that the steam dump flow rate used in the

RELAP5/M1OD2 simulation is higher than that used in the power plant.

Even though the calculated temperature shows a little difference from

the plant operating data, its result satisfies the permitted error

band (2.5 %) and the peak temperature criterion (322 C) which is

specified in the test procedure.

30
The result of comparison between the plant operating data and the

calculated cold leg temperature during the transient is found in

Figure 5.3. With the onset of natural circulation, the cold leg

temperature decreases due to the increase of steam dump flow rate

under the constant steam pressure mode. More heat is transported from

the primary system to the secondary system due to the increase of

steam dump flow rate. Therefore, the cold leg temperature decreases.

Both trends indicate this effect. The calculated cold leg temperature

drops to 291.6 c for 50 seconds and then builds up to the initial

temperature( 292.6 c). After some oscillation, it reaches to the

steady temperature. The plant operating data shows a different

response. It drops to 291.0 c for 100 seconds and then increases more

slowly than the calculated one. It decreases slowly with some

oscillation. The test procedure requires that the RCS cold leg

temperature be kept under the saturation temperature for the steam

generator pressure and this criteria is satisfied.

The calculated Tavg and Del-T are compared with the plant operating

data, which are shown in Figure 5.4 and Figure 5.5. These

temperatures are obtained mathematically from the hot leg temperature

and the cold leg temperature. Figure 5.4 shows that the calculated

Del-T increases and reaches to the peak temperature (20.4 c). It has

the similar trend with the plant operating data and both results are

31
satisfying the permitted peak Del-T 34.94 c, specified in the test

procedure. As shown in Figure 5.5, the plant operating data for the

Tavg shows lower values than the calculated Tavg at the beginning

stage of the transient and reaches to the peak temperature (302 c)

with some oscillation. The trends for the calculated and measured

peak Tavg reveal far lower value than the permitted peak temperature

(309 c), specified in the test procedure.

Shown in Figure 5.6 is the steam generator pressure by the

RELAP5/MOD2 simulation which indicates the peak pressure with a value

of 77.5 kgf/cm2 about 100 second. The first increase of steam

pressure results from the decrease of steam dump flow in order to

match to the setpoint pressure. After then, it begins to decrease for

100 seconds. It reaches to the saturated pressure around 550 second

through some fluctuation. Since the plant operating data is not

available, the comparison with the operating data is not made. The

test procedure requirement for the steam generator pressure is that it

should be stable or decreasing during the transient. The result of

simulation shows that the steam generator pressure is stable.

The steam dump flow rate with the steam pressure mode is determined

by the pressure difference between the steam header pressure and the

set point pressure (76.8 kgf/cm2) with 120 second reset time. The

steam header pressure is used in a proportional plus integral

controller to supply a modulated signal to the condenser dump valves.

Figure 5.7 shows that the initial steam dump flow rate (63.1 kg/sec)

32
for the first 100 seconds in order to increase the steam pressure.

After 100 second, the steam dump flow begin to increase sharply up to

the 50 kg/sec and then reaches to the saturated flow rate with a value

of 51 kg/sec through some fluctuations. The dump f low rate after

saturated condition without RCPs shows a little lower value ( 11kg/sec

) than the flow rate with RCPs. This caused by the fact that three

RCPs supply about 10 Mwt energy to the RCS. Some small fluctuations

are found for around 400 seconds after 200 second. These

oscillations are mainly due to the steam generator pressure

oscillation.

In consideration of instrument and recording uncertainty of the

plant operating data, the errors shown from the comparisons between

the calculated values and the plant operating data of the primary

system can be neglected. The operating data permit around 3.0

instrument and recording uncertainty [5].

Judging from the results of the above comparisons, it can be

-concluded that the results of calculation show the similar trend to

the plant operating data and satisfy the criteria specified in the

test procedure.

33
5000.00

4000.00 -

-- RELAP

(oQ)

u),

--,, 3000.00

V

o 2000.00

(9

1000.00

0.00

0,(

L - 1 I I I I I I I 1 I 1 I I

DO 500.00 I I I I I I I I I I

1000.00

time(sec)

II I I I00I 1500.00 I I I 2I I I

2000.00

Fi g u re 5.1 RCS Flow Rate
V

~4~)

0

H320.00

315.00

310.00

305.00

300.00

295.CI0

*2'90.00

.28~5.00:

Ln

1000.00

time(sec )

Ficure 5-2 Hot Leq Temp.
500.00

..... PLANT

-- RELAP

K S * * * 4 . S P 9 * 4 4 4 4 4 4 4 4

4 4 S * * $ * * ~

C)

29 0.0 0

771

280.C::0 -

275.00

0.0 I I I I I I I I I I I I 500.00 I I I I I I I I I I I I I I I I I I I

1000.00 1500.00

tinm e(sec)

I I I 2I 0I I 2000.00

Figure 5.3 Cold Leg Temp.
30.00

..... PLANT

25.00 --- RELAP

a i * 6 * *

20.00

(-)

15.00

C310.00-

/N

01000

0,00 500.00 1000.00 1500.00 2000.00

time(sec)

Fji.ýýUre F5,4 T hot- T cold
3 I0.00

30D.00

29.0

1000.00

time(sec)

Fl g u re F-,_. 5 Average Temp.
.5O.00 .-

79.00 -

r - - __________________ ______________________

-- RELAP

E

C)

- 77.00 -

CL

(.4

VI)

76.00 -

---- ------ ýO'

75.00 I I

I I

0.00

SI I I i I5 I0 I I 500.00 I

1000.00 1500.00 2000.00

time(sec)

Figure 5.6 S/G PRES.
100.00

,30.00

F-S

Lu

D

0

60.00

40.00

20.00

FELAP

I j / ' • • -- --- ---- -- 0

U.Uhl) - 1

0.00 500.00 I I I I j i I I

1000.00

time(sec)

5.7 Dump

1500.00

I I I

2000.00

Figure Flow Rate
6.0 Sensitivity study

During the Natural Circulation, the heat removal in the steam

generator depends strongly on the steam dump flow rate. It is of

great interest to find out the effect of steam dump flow rate on the

primary RCS temperature. To illustrate this effect, the RCS hot leg

and cold leg temperatures are compared for the different steam dump

flow rates. Data 1, the base calculation data, is obtained from

RELAP5/MOD2 simulation by the automatic steam dump control with the

constant steam pressure mode . Data 2 curve, as shown in Figure 6.1,

shows 20 percent more steam than Datal and applies to the RELAP5/MOD2

simulation as a boundary condition. The difference in the hot leg

temperatures is observed in Figure 6.2. Data 2 reveals the same

increase rate as Data 1 for the first 300 seconds. After 300 seconds,

it reaches to the peak temperature, lower than Data 1 peak value, and

continues to decrease. Figure 6.3 illustrates the comparison fot the

cold leg temperature. Data 2 shows the similar trend to Data 1 for

the first 300 seconds and after that time, it continues to decrease.

The result of this sensitivity study illustrates that the steam dump

flow rate can have a significant impact on the primary RCS flow rate.

41
100.00

;0.00

Li

0

1-

0L60.00

40.00

20.00

(N

0.00

time(sec)

Figure 6.1 Sensitivity Study (Dump Flow Rate)
320 .01

DATAI

DATA2

315.()C310.00

0 300.00 1+

295.00 4

290.00

2 8 5J.0 0 - - i-T -r- i i i i1 i i f 1 ¢ 1 1 1i1 1 1 1 1 i 1 i 1 ii1 1 J ll i1 1 1 i i 1 11 

0.00 500.00 1000.00 1500.00 2000.00

time (s c)

Figure 6.2 Sensitivity study (T hot)
310.00

300.00

, 290.00

o 280.00

270.00

260.00

time( sec,'

Figure 6.3 Sensitivity study (T cold)
7.0 Run Statistics

The CDC CYBER 170-875 which has one unified extended memery unit is

used for this analysis and the operating system is the NOS 2.6.1 level

700. Aplot of CPU vs RTand aplot of DTvs:RT are shown inFigure

7.1 and Figure 7.2 respectively. Since the transient is initiated

after 100 seconds steady state run, the consumed CPU time and time

step size are computed after 100 seconds. The total CPU time consumed

for this simulation of the whole transient 1800 seconds is 650.47

seconds.

Figure 7.1 indicates that the slope of CPU time in the first

100 seconds is sharper than that in the last 1800 seconds. The time

step size trend, shown in Figure 7.2, reveals the same phenomena as

the CPU trend. The advancement of calculation could not be successful

with the given maximum time step size 1.0 second during the first 230

seconds, so the advancement was made with reduced time step size. For

the first 50 seconds , the used time step size was 0.125 second.

After 230 seconds, the time step was 1.0 second, which was given in

the input. From the both figures, it can be known that at the

begining of the transient, the transient is very severe enough not

to be calculated with the given maximum time step size. The

calculated grind time is 2.68. The summaries for the run

statistics is given in Table 5.

45
1 O,)C,.oC - ________________ ___

RELAP

800.0 •

600.0C0

v) a

40 .00 (C200.(00- j/

,/

0 -00 -- W I i i i I

0.00 500.00 1000.00 1500.00 2000.00

time (sec)

Figure 7.1 CPU
2.00 -

1.50 -

-- RELAP

U)

N

(I)

'1)

U)

.Fz

.3 I nP.~

I .5L0

0.50 -~ 71

0.00 - I -- ~

-" IllI IIIIII l Ij i Ii I I 11 1 1 11I1 I IIII I 1 IIIIIIJIIIIIIiII

0.00 500.00 1000.00 1500.00 2000.00

time(sec)

Figure 7.2 Time Step Size
Table 5 Summary of the Run Statistics

Run Statistics

Computer

Operating System

CPU

# of Time Steps

# of Volumes

Transient Real Tin

(sec)

Grind Time

ie

CDC CYBER 170-875

NOS Vers.2.6.1

650.47

1927

126

1800

2.68

48
8.0 Conclusion and recommendations

The results of RELAP5/13D2 simulation using the natural circulation

test data of Yong-Gwang Unit 2 were compared with the plant operating

data. As far as the code application on the nuclear power plant

operation is concerned, the simulation results show a good behavior

of the code even in the prediction of the period and amplitude of the

important thermal-hydraulic parameters. Uncertainties in boundary and

initial conditions did not allow a complete identification of the

reasons of discrepancies between measured and calculated trends.

The sensitivity study shows that the steam dump flow rate has a

great impact on the determination of primary temperatures during

Natural Circulation.

Finally, it can be concluded the thermal-hydraulic characteristics

of the natural circulation flow after RCP pump tripping can be

estimated very well by this RELAP5/MOD2 simulation and any

possibility to clearly identify code limitation was not found.

49
Reference

1. Precation,Limitation and Setpoints for NSSS, January, 1986

prepared by Westinghouse

2. Setpoint Study for KNU 7 $ 8.October 1984,by Westinghouse

3. Young Gwang Unit 2 F.S.A.R by KEPCO in 1983

4. RELAP5/MOD2 Code Manual Volume 2 by EG $ G

5. Yong Gwang Unit 2 System Manual by KEPCO in 1980

6. Developement of Thermal-Hydraulic Safety Analysis Code

for Nuclear Power Plant by KAERI in 1989

7. Test Procedure for Natural circulation in Yong-Gwang Unit

2 prepared by Westinghouse

50
- RUN OF RELAP CODE FOR UNIT YK-Z

100 NEW TRANSNT

101 RUN

102 BRITISH SI

105 90. 100.

110 NITROGEN

**C**************************************** T* H ** 

* TIME STEP CARDS *

************* ************ ***

201 1900. 1.E-7 0.5 3 10 2000 00800 *

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

* MINOR EDIT VARIABLE *

* ------------------------------------------------

301

302

303

304

305

306

307

308

309

310

311

CNTRLVAR

CNTRLVAR

CNTRL VAR

CNTRLVAR

MFLOWJ

MFLOWJ

MFLOWJ

NFLOWJ

CNTRLVAR

CPUTIME

CNTRLVAR

250

251

254

255

430010000

521000000

566000000

579000000

49

0

43 *

506

507

508

509

TIME

TIME

TIME

TIME

0

0

0

0

GE

6E

GE

GE

NULL

NULL

NULL

NULL

0

0

0

0

2000.0

0.0

1000.0

100.0

L

L

L

L

* REACTOR VESSEL *

- ------ ---------------------------------- * * ,

***** ** *******   ** **   ** ** *******   ** *** *

* COMPNENT 100 : VESSEL INLET ANNULUS ABOVE *

* COLD LEG CENTERLINE *

**************************

- A. 1 -
1000000

1000001

1000101

1000301

1000302

1000401

1000402

1000601

1000801

1000802

1001001

1001101

1001201

1001202

1001300

1001301

INL-ANN

2

0.0

1.8064

3.311

51.284

54.119

90.0

0.00015

0.00015

00

10000

003

003

1

438.20

ANNULUS

2

1

2

1

2

2

1.4792

1.0662

2

1

2332.7

2331.9

1

2

557.00

557.00

00001

0002

1 0.0 0.0

* COMPONENT 102 : VESSEL INLET ANNIULIS BELOW *

* COLD LEG CENTERLINE *

* (UPPER VOLMJE) * ************************ *****   **  ***   ** **

1020000

1020001

1020101

1020102

1020200

1021101

1022101

1023101

1024101

1025101

1021201

1022201

1023201

1024201

1025201

INL-ANN BRANCH

5 1

0.0 3.6128

-3.6128 0.00015

003 2333.6

102000000 100000000

102000000 120000000

252010000 102000000

452010000 102000000

102010000 104000000

438.20 0.0

342.80 0.0

20208. 0.0

10104.00 0.0

29531.000 0.0

79.9315

1.3685

557.00

28.3899

0.08932

13.531

6.766

28.390

0.0

0.0

0.0

0.0

0.0

0.0

00

0.0

1.0170

0.1122

0.1122

0.0

-90.0

0.0

1.0170

0.1122

0.1122

0.0

00000

0000316:50:32

00001

00001

00000

* COMPONENT 104 : VESSEL INLET ANNIULUS BELOW *

* COLD LEG CENTERLINE *

* (LOWER VOLUME) *

1040000 INL-A1N ANNULUS

1040001 1

1040101 0.0 1

1040301 2.2481 1

1040401 67.1589 1

- A. 2 -
1040601 -90.0 1

1040801 0.00015 1.5515 1

1041001 00 1

1041201 003 2332.2 557.00 0 0 0 1

* COMPONENT 105 JUNCTION BETWEEN INLET *

* ANNULUS AND DOWNCOMER * **** * * ***** ** ******* *** *********** ****** *** ** *

1050000 INL-DNCO SNGLJUN

1050101 104010000 106000000 371.358 0.0 0.0 00000

1050201 1 29531.000 0.0 0.0

* COMPONENT 106 : DOWNCOHER *

1060000 DOWNCOMR ANNULUS

1060001 7

1060101 0.0 7

1060301 2.1060 6

1060302 4.1084 7

1060401 56.7903 1

1060402 52.5935 6

1060403 124.619 7

1060601 -90.0 7

1060801 0.00015 1.3855 1

1060802 0.00015 1.2776 6

1060803 0.00015 1.5702 7

1061001 00 7

1061101 20000 6

1061201 003 2332.30 557.00 0 0 0 1

1061202 003 2333.000 557.00 0 0 0 2

1061203 003 2333.6 557.00 0 0 0 3

1061204 003 2334.2 557.00 0 0 0 4

1061205 003 2334.8 557.00 0 0 0 5

1061206 003 2335.4 557.00 0 0 0 6

1061207 003 2326.6 557.00 0 0 0 7

1061300 1

1061301 29531.000 0.0 0.0 6

* COMPONENT 108 : LOWER PLENUM (UPPER VOLUHE) * *********** ** ***   ** *** ********* *******   ** * *

1080000 LOW-PLEM BRANCH

1080001 3 1

1080101 0.0 2.0486 243.693 0.0 -90.0 -2.0486 0.00015 5.40124 00

1080200 003 2337.00 557.00

- A. 3 -
1081101

1082101

1083101

1081201

1082201

1083201

106010000

110010000

108000000

29531.000

0.0

29531.000

108000000

108010000

112000000

0.0

0.0

0.0

30.6454

85.8360

31.7180

0.0

0.0

0.0

1.3180

0.0

3.2184

1.3180

0.0

3.2184

00000

00000

00000

* COMPONENT 110 : LOWER PLENUM (LOWER VOLUME) *

1100000 LOW-PLEM SNGLVOL

1100101 0.0 3.777 228.2687 0.0 90.0 3.777

1100200 003 2337.00 557.00

* CMPONET 112 : CORE INLET *

1120000 CORE-INL BRANCH

1120001 2 1

1120101 0.0 4.1084 293.7050 0.0 90.0 4.1084

1120200 003 2328.90 557.00

1121101 112010000 114000000 44.0363 0.1979

1122101 112010000 116000000 4.7853 59.4200

1121201 28513.000 0.0 0.0

1122201 1018.700 0.0 0.0 C

* COMPONEN 114 :CORE FLOW CHANNEL, *

0.00015 2.6400

0.00015 0.1281

0.1979 00000

59.4200 00000

00

00

1140000

1140001

1140101

1140301

1140301

1140601

1140701

1140801

1140901

1141001

1141101

1141201

1141202

1141203

1141204

1141205

1141206

1141300

CORE

6

0.0

2.1060

92.7394

90.0

2.1060

0.00015

2.8000

00

00000

003

003

003

003

003

003

1

PIPE

6

6

6

6

6

0.040092

2.8000

6

5

2326.3

2321.4

2316.4

2311.3

2306.1

2300.8

6

5

567.630

579.320

591.010

603.620

617.210

624.750

0001

00002

0003

0004

0005 0006

- A. 4 -
1141301 28513.000 0.0 0.0 5

* CONPONENT 116 : CORE BYPASS CHANNEL *

1160000 BYPASS PIPE

1160001 6

1160101 0.0 6

1160301 2.1060 6

1160401 38.9608 6

1160601 90.0 6

1160701 2.1060 6

1160801 0.00015 0.0 6

1160901 59.4200 59.4200 5

1161001 00 6

1161101 00000 5

1161201 003 2322.0 557.000 00 0 1

1161202 003 2320.9 557.000 0 0 0 2

1161203 003 2319.8 557.000 0 0 0 3

1161204 003 2318.7 557.000 0 0 0 4

1161205 003 2317.6 557.000 0 0 0 5

1161206 003 2316.5 557.000 0 0 0 6

1161300 1

1161301 1018.700 0.0 0.0 5

*********   **  ******** ***** ** ***   ** *** ** *******

* COMPONENT 118 : UPPER PLENUM BELOW HOT LEG *

* CENTERLINE (LOWER VOLUME) *

1180001

1180101

1180200

1181101

*1181101

1182101

1183101 1184101

1181201

*1181201

1182201

1183201

1184201

UP-PLEI

4

BRANCH

1

0.0 2.2481 158.2969

003

116010000

116010000

114010000

130010000

118010000

1018.700

0.000000

28513.000

438.20 (

29970.000

2298.4 118000000

118000000

118000000

118000000

120000000

0.0

0.0

0.0

0.00.0

0.0 90.0

621.270

2.9090

0.0001

44.0363

12.7033

75.8606

0.0

0.0

0.0

0.0

0.0

2.2481 0.00015 0.2936 00

59.4200

59.4200

1.4483

0.0

0.0

59.4200

59.4200

1.4483

0.0

0.0

00000

00000

00000

00000

00000

* COMPONENT 120 : UPPER PLENUM BELOW HOT LEG *

* CENTERLINE (UPPER VOLUME) * ** **** * *** ***** ** *** *** ******* ******* ***** ** ****** *

- A. 5 -
1200000

1200001

1200101

1200200

1201101

1202101

1203101

1201201

1202201

1203201

UP-PLEM BRANCH

3 1

0.0 3.6128 303.8130

003 2297.8

120010000 400000000

120010000 200000000

122010000 120010000

10104.00 0.0

20208.000 0.0

0.0 0.0

0.0 90.0

621.270

4.5775

9.1549

76.7457

0.0

0.0

0.0

3.6128 0.00015 1.7577 00

0.04

0.04

0.0

1.00

1.00

0.0

00002

00002

00000

* COMIONENT 122 : UPPER PLENUM ABOVE HOT LEG *

* CENTERLINE *

1220000 JP-PLEM SNGLVOL

1220101 0.0 1.8064 154.6250 0.0 -90.0 -1.8064

1220200 003 2297.2 621.27

0.00015 1.7577 00

* COMPONENT 124 : UPPER HEAD (LOWER VOLUME) *

*

1240000 UP-HEAD

1240101 0.0 2.311

1240200 003

SNGL VOL

154.854

Z299.10

0.0 90.0 2.311 0.00015 1.7327

557.00

00

* COMPONENT 126 : UPPER HEAD (MIDDLE VOLUME) *

**************************

1260000

1260001

1260101

1260200

1261101

1262101

1263101

1264101

1261201

1262201

1263201

1264201

UP-HEAD BRANCH

4 1

0.0 3.0117 277.7566

003 2298.20

100010000 126000000

124010000 126000000

128010000 126010000

126010000 130000000

438.20 0.0

0.0 0.0

0.0 0.0

438.20 0.0

0.0 90.0 3.0117

557.00

0.1442 1.52000

67.0074 0.0

72.7028 0.0

0.5973 1.52

0.0

0.0

0.0

0.0

0.00015 2.3769 00

1.52000

0.0

0.0

1.52

00000

00000

00000

00100

*

*************** ************************************

* COMPONENT 128 : UPPER HEAD (UPPER VOLUME) *

*

- A. 6 -
1280000

1280001

1280101

1280301

1280401

1280402

1280601

1280801

1280802

1280901

1281001

1281101

1281201

1281300

1281301

UP-HEAD

2

0.0

1.4833

40.4626

109.4264

-90.0

0.00015

0.00015

0.0

00

00000

003

1

0.0

PIPE

2

2

1

2

2

2.4415

4.0476

0.0

2

1

2297.00

0.0

1

2

1

557.00 O0 0 2

0.0 1

* COMNENT 130 : GUIDE TUBES *

1300000

1300101

1300200

GUIDE SNOLVOL

0.0 13.9900. 217.8076

003 2296.90

0.0 -90.0 -13.9900 0.00015 0.7455 00

557.00

*

* ,

--------------------------------------------------------- *

• INTACT LOOP PIPINGS *

*---------------------------------------------------- *k.

* COMPONENT 200: INTACT LOOP HOT LEG *

2000000 I-HOTLEG PIPE

2000001 2

2000101 0.0 2

2000301 6.4413 2

2000401 59.0536 2

2000601 0.0 2

2000801 0.00015 2.4167 2

2001001 00 2

2001101 00000 1

2001201 003 2284.4 621.270 0 0 0 2

2001300 1

2001301 20208.000 0.0 0.0 1

********k*****************

* COMPONENT 205 : INTACT LOOP BRANCH *

* BETWEEN HOT LEG SEGMENTS *

- A. 7 -
AND PZR SURGELINE

* AND PZR SURGELINE * * *** ** * *********   **  *** ** ***   **  ***** *** * *** *

*

2050000 I-HOTLEG BRANCH

2050001 3 1

2050101 0.0 3.5499 32.5662

2050200 003 2283.7 621.270

2051101 200010000 205000000

2052101 205010000 210000000

2053101 630010000 205000000

2051201 20208.000 0.0

2052201 20208.000 0.0

2053201 0.0 0.0

*2050000 I-HOTJUN SNGJJUN

0.0 0.0 0.0 0.00015 2.4167 00

0.0

0.0

0.0

0.0

0.0

0.0

0.0 0.0 00000

0.0 0.0 00000

0.0 0.0 00101

*2050101 200010000

*2050201 1

210000000

21734.840

0.0 0.0

0.0 0.0

0.0 00000

*

*

* COMP1ONENT 210 : INTACT LOOP HOT LEG *

2100000 I-HOTLEG

2100001 2

2100101 0.0

2100301 3.5499

2100302 3.7973

2100401 32.5662

2100402 39.8066

2100601 0.0

2100602 50.0

2100701 0.0

2100702 2.9087

2100801 0.00015

2100802 0.00015

*2100901 0.0

2100901 0.07007

2101001 00

2101101 00000

*2101102 00000

2101201 003

2101202 003

2101300 1

2101301 20208.000

PIPE

2

1

2

1

2

1

2

1

2

2.4167

2.5833

0.0

0. 071929

2

1

2

2283.5

2285.0

0.0

1

2

1

1

621.270 0 0 0 1

621.270 0 0 0 2

0.0 1

* COMPONENT 215 : JUNCTION BETWEEN HOT LEG AND *

* STEAM GENERATOR INLET PLENUM *

******* ******************

- A. 8 -
2150000 I-HOT-SG

2150101 210010000

2150201 1

SNGLJUN

300000000 10.4828

20208.000 0.0

0.7324

0.0

0.459 00000

*

4444 ++4+444+44444+4+4++444+4+4+4+*444+44.+4+

* COMPONENT 502 : JUNCTION BETWEEN Sf6 OUTLET . PLENUM AND PUMP SUCTION *

*

3020000

3020101

3020201

I-SG-SUC

300010000

1

SNGIJUN

220000000 10.4828 0.459

20208.000 0.0 0.0

0.7324 00000

* COMPONENT 220 : INTACT LOOP PUMP SUCTION *

* PIPING *

2200000

2200001

2200101

2200301

2200302

2200303

2200304

2200305

2200401

2200402

2200403

2200404

2200405

2200601

22006O2

2200603

2200604

2200605

2200801

2200901

2200902

2200903

2200904

2201001

2201101

2201102

2201201

2201300

2201301

I-PMPSUC

5

0.0

4.8392

4.5283

7.0686

2.5573

7.0686

50.7290

47.4700

74.0992

26.8078

74.0992

-60.0475

-90.0

-39.5402

0.0

39.5402

0.00015

0.05645

0.0

0.143

0.143

00

00000

00000

003

1

20208.000

PIPE

5

1

2

3

4

5

1

2

3

4

5

1

3

4

5

2.5833

0.05645

0.0

0.143

0.143

5

2

4

2243.8

5

1

2

3

4

556.6 0 00 5

0.0 0.0 4

* COMPONENT 225 : INTACT LOOP RC PUMP *

- A. 9 -
2250000

2250101

2250108

2250109

2250200

2250201

2250202

2250301

2250302

2250303

*250310

*256001

*256002

*256003

*2560O4

*256005

I-PUMP PUMP

0.0 9.8458

220010000 10.4828

230000000 8.2494

003 2289.6

1 20208.000

1 20208.000

-2 -1 -2

1188.0 1.0 205600.0

1162.16 0.0 1736.06

100.0 1188.0 0.0

0.0 0.95 716.56

1079.6 2.08 1162.

1200.0 0.0 1239.6

1681.5 -1.32 2159

3000.0 -0.94

0.0 0.0 36.182 5.8125 00

0 0.0 00000

0 0.0-.. 00000

7.0

0 0.0

0 0.0

1 -1 509 0

294.0 56000.0 190000.0 46.43 0.0

-399.66

1.15 955.4 1.6

7 2.53 1188.0

-2.62 1442.6

.2 -1.0 2398.1

1.0

-1.87

-0.95

* COMPONENT 230 INTACT LOOP COLD LEG FROM *

* PUMP DISCHARGE TO *

* ACCUMULATOR LINE / BREAK *

2300000 I-COLDLG PIPE

2300001 2

2300101 8.2494 2

2300301 4.4073 2

2300401 0.0 2

2300601 0.0 2

2300801 0.00015 2.2917 2

2301001 00 2

2301101 00000 1

2301201 003 2321.60 557.00 0 0 0 2

2301300 1

2301301 20208.000 0.0 0.0 1

* *** ***** * *** ***** *** ***** ***   ** **** *** *** ** *** *

* COMPONENT 240 : INTACT LOOP COLD LEG FROM *

* ACCUMULATOR LINE / BREAK *

* TO SI LINE *

2400000

2400001

2400101

2400200

2401101

I-COLDLG

2

8.2494

003

230010000

BRANCH

1

3.6833 0.0

2321.60

240000000

0.0 0.0 0.0 0.00015 2.2917 00

557.00

8.2494 0.0 0.0 00000

- A.10 -
2402101 240010000 252000000

2401201 20208.000 0.0

2402201 20208.000 0.0

8.2494

0.0

0.0

0.0 0.0 00000

* COMPONENT 252 : INTACT LOOP COLD LEG FROM *

* SI LINE TO VESSEL *

20

2520000

2520001

2520101

2520301

2520401 2520402

2520601

2520801

2520802

2521001

2521101

2521201

2521300

2521301

I-COLDLG

2

0.0

6.5969

54.4204

64.4660

0.0

0.00015

0.00015

00

00000

003

1

20208.000

PIPE

2

2

1

2

2

2.2917

2.4942

2

1

2320.7

1

2

557.00 0 0 0 2

0.0 0.0 1

* COMPONENT 300; INTACT STEAM GENERATOR TUBES *

3000000

3000001

3000101

3000102

3000103

3000301

3000302

3000303

3000401

3000402

3000403

3000601

3000602

3000603

3000604

3000801

3000802

3000803

3001001

3001101

3001102

3001103

3001201

BSGTBS PIPE

10

0.0 01

21.550 09

0.0 10

4.0095 1

7.20 9

4.0095 10

284.52 1

0.000 9

284.52 10

90. 4

61.733 5

-61.733 6

-90. 10

0.00015 6.72127 1

0.00000 0.0505 9

0.00015 6.72127 10

00 10

00100 1

00000 8

00100 9

3 2286.3 620.64 0.0 0 0 1

- A.11 -
3001202 3 2279.7

3001203 3 2273.8

3001204 3 2267.8

3001205 3 2262.0

3001206 3 2258.3

3001207 3 2256.8

3001208 3 2255.4

3001209 3 2254.1

3001210 3 2255.0

3001300 1

3001301 20208.000

607.44

593.99

584.00

575.96

569.56

564.30

559.78

556.71

556.71

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0

0

0

0

0

0

0

0

0

0

0

0

0

0

0

0

0

0

2

3

4

5

6

7

8

9

10

0.0 0.0 9

* COMPONENT 340; INTACT STEAM GENERATOR RISER *

3400000

3400001

3400101

3400201

3400202

3400301

3400302

3400303

3400304

3400401

3400402

3400403

3400404

3400601

3400801

3400802

3400901

3401001

3401101

3401201

3401202

3401203

3401204

3401205

3401301

3401302

3401303

3401304

"ISG-RSR" PIPE

5

0.0 5

43.94 3

0.0 4

5.43 1

7.20 3

6.34 4

12.22 5

615.12 1

787.56 3

740.96 4

1548.8 5

90. 5

1.5E-4 0.0908

1.5E-4 10.25

0.5 0.5 4

00 5

10100 4

2 975.7 2.7•

2 974.4 8.2.

2 973.1 0.i•

2 972.1 0.2•

2 971.4 0.2•

2.5693 4.291

4.3156 6.97T

5.9254 9.40•

8.5445 10.5,

4

5

36E-2

4E-2

'707

O46

8785

?3 0.0

85 0.0

U1 0.0

59 0.0

0.0

0.0

0.0

0.0

0.0

1

2

3

4

0

0

0

0

0

0

0

0

0

0

1

2

3

4

5

wwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwxwwwwwwwwwwwwwwwwwwwxw

* COMPONENT 350; INTACT STEAM GENERATOR SEPERATOR *

3500000

3500001

3500101

3500200

3501101

"ISGS SPR"

3

0.0 6.69

2 970.43

350010000

SEPARATR

2050.0 0.0

3.60460E-2

360000000

90. 6.69 1.5E-4 1.625

58.56 15.0 15.0 11000 0.15

00

- A.12 -
3502101 350000000 330000000 8.42 0.1 0.1 21000 0.15

3503101 340010000 350000000 66.36 0.1 0.1 11000

3501201 7.1844 18.267 0.0

3502201 15.994 -24.970 0.0

3503201 14.866 18.851 0.0

* COMPONENT 360; INTACT STEAM GENERATOR STEAM DOME/DRYER *

3600000 "ISG DOME" PIPE

3600001 3

3600101 0.0 2

3600102 9.86 3

3600201 2.8 2

3600301 9.79 1

3600302 5.29 2

3600303 137.0 3

3600401 3078.0 1

3600402 800.0 2

3600403 0.0 3

3600601 90.0 2

3600602 0.0 3

3600801 1.5E-4 14.0 2

3600802 1.5E-4 2.505 3

3600901 0.0 0.0 2

3601001 00 3

3601101 10000 2

3601201 2 968.56 0.99974 0.0 0 0 1

3601202 2 968.44 0.99954 0.0 0 0 2

3601203 2 964.81 0.99890 0.0 0 0 3

3601301 333.87 382.69 0.0 1

3601302 271.78 382.76 0.0 2

* COMPONENT 330; INTACT STEAM GENERATOR DOWNCOMER *

3300000 "ISOS DWN" PIPE

3300001 5

3300101 0.0 5

3300201 15.54 1

3300202 13.46 2

3300203 13.98 3

3300204 12.72 4

3300301 12.22 1

3300302 6.34 2

3300303 7.20 4

3300304 5.43 5

3300401 991.2 1

3300402 99.04 2

3300403 112.44 4

3300404 84.88 5

3300601 -90. 5

- A.13 -
3300801 1.5E-4 2.1104 1

3300802 1.5E-4 0.469 5

3301001 00 5

3301101 20000 1

3301102 20100 4

3301201 3 972.9 515.20 0. 0 0 1

3301202 3 975.3 515.21 0. 0 0 2

3301203 3 977.4 515.22 0. 0 0 3

3301204 3 979.6 515.23 0. 0 0 4

3301205 3 981.4 515.24 0. 0 0 5

3301301 11.463 11.463 0.0 1

3301302 11.406 11.406 0.0 2

3301303 11.406 11.406 0.0 4

* COMPONENT 331; INTACT STEAM GEN DOWNCOIER TO RISER JUNCTION *

3310000 ISGSDRSR SNGLJUN

3310101 330010000 340000000 14.48 8.71 8.71 00100

3310201 0 11.515 14.399 0.0

* COMPONENT 321; INTACT STEAM GENERATOR MAIN FEEDWATER JUNCTION*

3210000 "1 MNFEED" TMDPJIN

3210101 320000000 330000000 0.60

3210200 1 507

3210201 0.0 67.60 0.0 0.0

3210202 100.0 67.60 0.0 0.0

3210203 5000.00 67.60 0.0 0.0

******************** ********** *** ******* ******* *** ****** *

* COMPONENT 320; INTACT STEAM GEN MIIN FEEDWATER SOURCE VOLUME *

3200000 "I MNFEED" TMDPVOL

3200101 2000. 1.0 0.0 0.0 0.0 0.0 0.0 50.0 00

3200200 3

3200201 0.0 1025.7 440.000

* COMPONENT 370; INTACT LOOP STEAM LINE ( M S I V)

3700000 "IMAINSTN' VALVE

3700101 360010000 565000000 9.86 0.0 0.0 00100

3700201 1 0.0 10.0 0.0

3700300 MTRVLV

3700301 507 506 0.20 1.0

* ------------------------------------------------- *

* ~BROKEN LOOP PIPINGS*

* COMPONENT 400 : BROKEN LOOP HOT LEG *

- A.14 -
4000000

4000O01

4000101

4000301

4000401

4000601

4000801

4001001

4001101

4001201

4001300

4001301

B-HOTLEG

2

0.0

6.4413

29.5286

0.0

0.00015

00

00000

003

1

10104.00

PIPE

2

2

2

2

2.4167

2

1

2284.4

2

621.270 0 0 0 2

0.0 0.0 1

* COMPONENT 405 : BROKEN LOOP JUNCTION *

* BETWEEN HOT LEG SEGMENTS *

4050000 B-HOTJUN SNGLJUN

4050101 400010000 41000000 0.0 0.0 0.0 (•

4050201 1 10104.00 0.0 0.0

* COIMPONENT 410 : BROKEN LOOP HOT LEG *

**************************

w00O

4100000

4100001

4100101

4100301

4100302

4100401

4100402

4100601

4100602

4100701

4100702

4100801

4100802

4100901

4100902

4101001

4101101

4101102

4101201

4101202

4101300

4101301

B-HOTEG

3

0.0

3.5499

3.7973

16.2831

19.9033

0.0

50.0

0.0

2.9087

0.00015

0.00015

0.0

0.07007

00

00000

00000

003

003

1

10104.00

PIPE

3

2

3

2

3

2

3

2

3

2.4167

2.5833 0.0

0.071929

3

1

2

2283.7

2283.5

2

3

1

2

621.270 0 0 0 2

621.270 0 0 0 3

0.0 0.0 2

- A.15 -
* COMPONENT 415 : JUNCTION BETWEEN HOT LEG AND *

* STEAM GENERATOR INLET PLENUM *

**************************

4150000 B-HOT-SG

4150101 410010000

4150201 1

SNGLJUN

500000000

10104.00

5.2414 0.7324 0.459

0.0 0.0

00000

* COMPONENT 502 JUNCTION BETWEEN SfG OUTLET *

* PLENUM AND PUMP SUCTION *

**************************

5020000

5020101

5020201

B-SG-SUC

500010000

1

SNGLJUN

420000000

10104.00

5.2414 0.459

0.0 0.0

0.7324 00000

* COMPONENT 420 : BROKEN LOOP PUMP SUCTION *

* PIPING * ********** * *********** *** ***** ********* *** ** *

4*00QPO

4200001

4200101

4200301

4200302

4200303

4200304

4200305

4200401

4200402

4200403

4200404

4200405

4200601

4200602

4200603

4200604

4200605

4200801

4200901

4200902

4200903

4200904

4201001

4201101

4201102

B-PMPSIIC

5

0.0

4.8392

4.5283

7.0686

2.5573

7.0686

25.3645

23.7350

37.0496

13.4039

37.0496

-60.0475

-90.0

-39.5402

0.0

39.5402

0.00015

0.05645

0.0

0.143

0.143

00

00000

00000

PIPE

5

1

2

3

4

5

1

2

3

4

5

1

2

3

4

5

2.5833

0.05645

0.0

0.143

0.143

5

2

4

5

1

2

3

4

- A.16 -
4201201 003 22•

4201300 1

4201301 10104.00 0.0

13.8 556.6 0 0 0 5

0.0 4

* COMPONENT 425 : BROKEN LOOP RC PUMP *

4250000

4250101

4250108

4250109

4250200

4250201

4250202

4250301

4250302

4250303

B-PUMP

0.0

420010000

430000000

003 1

-2

1188.0 ]

581.08 (

PUMP

9.8458

5.2414

4.1247

2289.6

10104.00

10104.00

80.0

0.0

0.0

557.0

0.0

0.0

0.0 36.182

0.0 00000

0.0 00000

5.8125 00

0.0

0.0

-1 -2

1.0 102800.0

).O 868.03

-1 -1 509

294.0 28000.0

-199.83

0

190000.0 46.43 0.0

wwwwwwXKXwwKwwww Xw

*

*

*

COMPONENT 430 : BROKEN LOOP COLD LEG FROM

PUMP DISCHARGE TO

ACCUMULATOR LINE / BREAK

*

*

*

*

4300000 B-COLDLG

4300001 2

4300101 4.1247

4300301 4.4073

4300401 0.0

4300601 0.0

4300801 0.00015

4301001 00

4301101 00000

4301201 003

4301300 1

4301301 10104.00

PIPE

2

2

2

2

2.2917

2

1

2321.60

2

557.00 0002

0.0 0.0 1

* COMPONENT 440 : BROKEN LOOP COLD LEG FROM *

* ACCUMULATOR LINE / BREAK *

* TO SI INE *

4400000 B-COLDLG

4400001 2

4400101

4400200

4401101

4402101

4401201

4.1347 3

003

430010000

440010000

10104.00

BRANCH

1

.6833 0.0

2321.10

440000000

452000000

0.0

0.0 0.0

557.00

4.1247

4.1247

0.0

0.0 0.00015 2.2917 00

0.0 0.0 00000

0.0 0.0 00000

- A.17 -
4402201 10104.00 0.00. 0.0

* COMPONENT 452 BROKEN LOOP COLD LEG FROM *

* ~SI LINE TO VESSEL*

4520000 B-COLDLG PIPE

4520001 2

4520101 0.0 2

4520301 6.5969 2

4520401 27.2102 1

4520402 32.2330 2

4520601 0.0 2

4520801 0.00015 2.2917 1

4520802 0.00015 2.4942 2

4521001 00 2

4521101 00000 1

4521201 003 2320.7 557.00 0 0 0 2

4521300 1

4521301 10104.00 0.0 0.01

*COMPONENT 500; BROKEN STEAM GENERATOR TUBES*

5000000 BSGTBS PIPE

5000001 10

5000101 0.0 01

5000102 10.776 09

5000103 0.0 10

5000301 4.0095 1

5000302 7.20 9

5000303 4.0095 10

5000401 142.26 1

5000402 0.000 9

5000403 142.26 10

5000601 90. 4

5000602 61.733 5

5000603 -61.733 6

5000604 -90. 10

5000801 0.00015 6.72127 1

5000802 0.00000 0.0505 9

5000803 0.00015 6.72127 10

5001001 00 10

5001101 00100 1

5001102 00000 .8

5001103 00100 9

5001201 3 2286.30 620.64 0.0 0 0 1

5001202 3 2279.7 607.44 0.0 0 0 2

5001203 3 2273.8 593.99 0.0 0 0 3

- A. 18 -
5001204

5001205

5001206

5001207

5001208

5001209

5001210

5001300

5001301

3 3 226' Z26'

3 2256

3 225E

3 2259

3 225

3 225•

3 225~

1

10104.00

7.]

5.4

4.1

5.0

584.01 0.(

575.96 0.(

569.56 0.(

564.30 0.(

1 559.78 0.(

556.71 0.(

556.71 0.(

0.0 0.0 9

)

)

)

)

)

)

0

0

0

0

0

0

0

0

0

0

0

0

0

0

4

5

6

7

8

9

10

* COMPONENT 540; BROKEN STEAM GENERATOR RISER *

5400000

5400001

5400101

5400201

5400202

5400301

5400302

5400303

5400304

5400401

5400402

5400403

5400404

5400601

5400801

5400802

5400901

5401001

5401101

5401201

5401202

5401203

5401204

5401205

5401301

5401302

5401303

5401304

"BSG-RSR" PIPE

5

0.0 5

21.97 3

0.0 4

5.43 1

7.20 3

6.34 4

12.22 5

307.56 1

393.78 3

370.48 4

774.4 5

90. 5

1.5E-4 0.0908

1.5E-4 10.25

0.5 0.5 4

00 5

10100 4

2 975.7 2.7W

2 974.4 8.25

2 973.1 0.1"

2 972.1 0.2•

2 971.4 0.2•

2.5693 4.28'

4.3156 6.97Z

5.9254 9.40•

8.5445 10.5,

4

5

36E-2

)4E-2

M707

O46

,785

73 0.0

85 0.0

31 0.0

59 0.0

0.0

0.0

0.0

0.0

0.0

1

2

3

4

0

0

0

0

0

0

0

0

0

0

1

2

3

4

5

* COMPONENT 550; BROKEN STEAM GENERATOR SEPERATOR *

5500000

5500001

5500101

5500200

5501101

5502101

5503101

"BSGS SPR"

3

0.0 6.69

2 970.43

550010000

550000000

540010000

SEPARATR

1025.0 0.0

3.60460E-2

560000000

530000000

550000000

90. 6.69 1.5E-4 1.625 00

29.28

4.21

33.18

15.0

0.1

0.1

15.0 11000 0.15

0.1 21000 0.15

0.1 11000

- A.19 -
5501201 7.1844 18.267 0.0

5502201 15.994 -24.970 0.0

5503201 14.866 18.851 0.0

* COMPONENT 560; BROKEN STEAM GENERATOR STEAM DONE/DRYER *

5600000 "BSG DOME" PIPE

5600001 3

5600101 0.0 2

5600102 4.93 3

5600201 1.4 2

5600301 9.79 1

5600302 5.29 2

5600303 137.0 3

5600401 1539.0 1

5600402 400.0 2

5600403 0.0 3

5600601 90.0 2

5600602 0.0 3

5600801 1.5E-4 14.0 2

5600802 1.5E-4 2.505 3

5600901 0.0 0.0 2

5601001 00 3

5601101 10000 2

5601201 2 968.56 0.99974 0.0 0 0 1

5601202 2 968.44 0.99954 0.0 0 0 2

5601203 2 964.81 0.99890 0.0 0 0 3

5601301 333.87 382.69 0.0 1

5601302 271.78 382.76 0.0 2

* COMPONENT 530; BROKEN STEAM GENERATOR DOWNCOMER *

5300000 "BSGS DWN" PIPE

5300001 5

5300101 0.0 5

5300201 7.77 1

5300202 6.73 2

5300203 6.99 3

5300204 6.36 4

5300301 12.22 1

5300302 6.34 2

5300303 7.20 4

5300304 5.43 5

5300401 495.6 1

5300402 49.52 2

5300403 56.22 4

5300404 42.44 5

5300601 -90. 5

5300801 1.5E-4 2.1104 1

5300802 1.5E-4 0.469 5

- A.20 -
5301001 00 5

5301101 20000 1

5301102 20100 4

5301201 3 972.9 515.20 0. 0 0 1

5301202 3 975.3 515.21 0. 0 0 2

5301203 3 977.4 515.22 0. 0 0 3

5301204 3 979.6 515.23 0. 0 0 4

5301205 3 981.4 515.24 0. 0 0 5

5301301 11.463 11.463 0.0 1

5301302 11.406 11.406 0.0 2

5301303 11.406 11.406 0.0 4

, COMPONENT 531; BROKEN STEAM GEN DOWNCOMER TO RISER JUNCTION *

5310000 BSGSDRSR SNGLJUN

5310101 530010000 54000 7.24 8.71 8.71 00100

5310201 0 11.515 14.399 0.0

* COMPONENT 521; BROKEN STEA GENERATOR MAIN FEEDWATER JUNCTION*

5210000 "'B MNFEED" TMDPJUN

5210101 520000000 530000000 0.30

5210200 1 507

5210201 0.0 33.8 0.0 0.0

5210202 100.0 33.8 0.0 0.0

5210203 5000.0 33.8 0.0 0.0

* COMPONENT 520; BROKEN STEAM GEN MAIN FEEDWATER SOURCE VOLUME *

5200000 "B MNFEED" ThDPVOL

5200101 1000. 1.0 0.0 0.0 0.0 0.0 0.0 50.0 00

5200200 3

5200201 0.0 1025.7 440.000

SCOPONENT 570; BROKEN LOOP STEAM LINE ( M S I V) *

5700000 "BMAINSTM" VALVE

5700101 560010000 565000000 4.93 0.0 0.0 00100

5700201 1 0.0 5.0 0.0

5700300 MTRVLV

5700301 507 506 0.20 1.0

--------------------------------------------------------- *

• PRESSURIZER *

*----------------------------------------------------------*

• COMPONENT *620 : PRESSURIZER VESSEL *

- A.21 -
*200000

*200001

*200101

*200301

*200302

*200303

*200304

*200305

*200401

*200402

*200403

*200601

*Z00801

*200802

*200803

*200901

*201001

*201101

*201201

*201202

*201203

*201300

*201301

6200000

6200101

6200200

6200201

6200202

6200203

6200204

6200205

6200206

6200207

6200208

6200209

6200210

6200211

6200212

6200213

6200214

6200215

6200216

6200217

6200218

6200219

6200220

6200221

6200222

6200223

PZR

8

0.0

5.3036

3.8977

5.1969

3.8977

5.3036

150.00

200.00

150.00

90.000

0.00015

0.00015

0.00015

0.0

00

00000

002

002

002

1

0.0

PZR-STDY

0.0 1.0

003 0

PIPE

8

1

2

6

7

8

2

6

8

8

6.0009

7.0000

6.0009

0.0

8

7

2250.0

2250.0

2250.0

0.0

TMDPVOL

100.0 0.0

1

7

8

7

1.0 0

0.3 0

0.0 0

0

0

0

0

0

0

3

4

8

0.0 7

0.0 0.0 0.0 0.0 00

0.0 2262.45

60.0 2263.1(

120.0 2263.1

180.0 2261.(

240.0 2260.M

300.0 2258.J

360.0 2255.,

420.0 2253V

480.0 2251.M

540.0 2244.(

600.0 2237.M

660.0 2211..(

720.0 2208.,

780.0 2222.(

840.0 2224.C

900.0 2231M

960.0 2211.'

1020.0 2212.(

1080.0 2211.V

1140.0 2214.'

1200.0 2219.1

1260.0 2223.,

1320.0 2224.'

621.271

i 621.271

16 621.271

)2 621.27

U1 621.27

09 621.27

13 621.27

)l 621.27

W7 621.27

P7 621.27

i5 621.27

)5 621.27

09 621.27

i2 621.27

5 621.27

%6 621.27

A4 621.27

i6 621.27

)5 621.27

(9 621.27

(9 621.27

13 621.27

75 621.27

- A.22 -
6200224

6200225

6200226

6200227

6200228

6200229

6200230

1380.0

1440.0

1500.0

1560.0

1620.0

1680.0

1740.0

2226.17

2227.60

2223.33

2220.48

2217.64

2227.60

2230.44

621.27

621.27

621.27

621.27

621.27

621.27

621.27

* COMPONENT 625 : JUNCTION BETWEEN PRESSURIZER *

* AND SURGELINE * ****   ** *** ** ***** *****   ** ***** ** ******* ***

6250000

6250101

6250201

PRZ-JUN

620000000

1

SNGLJUN

630000000

0.0

0.0 0.0

0.0 0.0

0.0 00100

* COMPONENT 630 : PRESSURIZER SURGE-LINE *

6300000 PZR-SUR PIPE

6300001 3

6300101 1.0690 3

6300301 13.00 1

6300302 22.0129 3

6300601 -90.0 1

6300602 0.0 3

6300801 0.00015 1.167 3

6301001 00 3

6301101 00000 1

6301102 00000 2

6301201 003 2281.9 621.270 0 0 0 3

6301300 1

6301301 0.0 0.0 0.0 2

*********************** ***** ** ********** ***

* COMPONENT 635 JUNCTION BETWEEN SURGELINE *

* TO INTACT LOOP HOT LEG *

**************************

*6350000 SUR-HOT

*6350101 630010000

*6350201 1

SNGLJUN

200000000

0.0

0.0 0.0

0.0 0.0

0.0 00100

* HEAT STRUCTURE INPUT *

*------------------------------------------- ---------- *

- A.23 -
* HEAT STRUCTURE 100 : REACTOR VESSEL WALL IN *

* DOWNCOMDER ANNULAR REGION *

----------------------------------------------------------------- *

11000000

11000100

11000101

11000102

11000201

11000202

11000301

11000400

11000401

11000501

11000502

11000503

11000504

11000601

11000602

11000603

11000604

11000701

11000801

-1000802

11000803

11000804

4 8

0 1

2 6.4925

5 7.2772

5 2

6 7

0.0 7

0

557.00 8

100010000 0

100020000 0

102010000 0

104010000 0

0 0

0 0

0 0

0 0

0 0.0

0 0.0

0 0.0

0 0.0

0 0.0

2 1 6.4792

1

1

1

1

0

0

0

0

1

1

1

1

1

1

1

1

0.0000

2.7895

1.6058

2.7895

2.6410

1.8014

3.3114

3.6128

2.2486

1.8014

3.3114

3.6128

2.2486

0.0

0.0

0.0

0.0

0.0

1

2

3

4

1

2

3

4

4

1

2

3

4

----------------------------------------------------------------- *

* HEAT STRUCTURE 102 : CORE BARREL WALL *

* -------------------------------------------------------- *

11020000

11020100

11020101

11020201

11020301

11020430

11020401

11020501

11020502

11020503

11020504

11020505

11020506

11020507

11020508

11020509

11020510

11020511

11020601

11

0

2

5

0.0

0

3 2

1

5.7396

2

2

1 5.5729

557.00 3

112010000

116010000

116020000

116030000

116040000

116050000

116060000

118010000

120010000

122010000

0

106070000

0

0

0

0

0

0

0

0

0

0

0

0

1

1

1

1

1

1

1

1

1

1

0

1

1

1

1

1

1

1

1

1

1

1

1

1

4.1084

2.1060

2.1060

2.1060

2.1060

2.1060

2.1060

2.2481

3.6128

1.8064

3.3114

4.1084

1

2

3

4

5

6

7

8

9

10

11

1

- A.24 -
11020602 106060000

11020603 106050000

11020604 106040000

11020605 106030000

11020606 106020000

11020607 106010000

11020608 104010000

11020609 102010000

11020610 100010000

11020611 100020000

11020701 0 0.0

11020801 0 0.0

11020802 0 0.0

11020803 0 0.0

11020804 0 0.0

11020901 0 0.0

11020902 0 0.0

11020903 0 0.0

11020904 0 0.0

11020905 0 0.0

11020906 0 0.0

11020907 0 0.0

0 1

0 1

0 1

0 1

0 1

0 1

0 1

0 1

0 1

0 1

0.0000

10.6784

2.1134

8.6659

0.0000

3.3545

2.7700

2.9910

3.3120

2.4540

3.1489

1.8127

1

1

1

1

1

1

1

1

1

1

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

2.1060 2

2.1060 3

2.1060 4

2.1060 5

2.1060 6

2.1060 7

2.2481 8

3.6128 9

1.8064 10

3.3114 11

11

1

7

10

11

1

6

7

8

9

10

11 *

*--------------------------------------*

* HEAT STRUCTURE 106 : REACTOR VESSEL WALL IN

* THE INLET ANNILUS *

*

*-------------------------------------------------------

11060000 7 8 2 1

11060100 0 1

11060101 2 6.5550

11060102 5 7.2117

11060201 5 2

11060202 6 7

11060301 0.0 7

11060400 0

11060401 557.00 8

11060501 106010000 0

11060502 106020000 0

11060503 106030000 0

11060504 106040000 0

11060505 106050000 0

11060506 106060000 0

11060507 106070000 0

11060601 0 0

11060602 0 0

11060603 0 0

11060604 0 0

11060605 0 0

11060606 0 0

6.5417

1

1

1

1

1

1

1

0

0

0

0

0

0

1

1

1

1

1

1

1

1

1

1

1

1

1

2.1060

2.1060

2.1060

2.1060

2.1060

2.1060

4.1084

2.1060

2.1060

2.1060

2.1060

2.1060

2.1060

1

2

3

4

5

6

7

1

2,

3

4

5

6

- A.25 -
11060607

11060701

11060801

11060802

11060803

0

0

0

0

0

0

0.0

0.0

0.0

0.0

0 1

0.0000

2.6243

2.4304

2.9519

4.1084

0.0

0.0

0.0

0.0

7

7

1

6

7

-*

HEAT STRUCTURE 107 NEUTRON PANEL ASSEMBLY

IN DOWNCOMER

*

*

----------------------------------------------------------------- *

11070000

11070100

11070101

11070201

11070301

11070400

11070401

11070501

11070502

11070503

11070504

11070505

11070506

11070601

11070602

11070603

11070604

11070605

11070606

11070701

11070801

11070802

11070901

11070902

6 4

0 1

3 0.382

5 3

0.0 3

0

557.00

106010000

106020000

106030000

106040000

106050000

106060000

106010000

106020000

106030000

106040000

106050000

106060000

0 0

0 (

0 (

0 (

0 (

1

•5

1 0.000

4

0

0

0

0

0

0

0

0

0

0

0

0

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

0.0000

3.4535

3.1983

3.4535

3.1983

43.8333

65.7766

65.7766

65.7766

65.7766

65.7766

43.8333

65.7766

65.7766

65.7766

65.7766

65.7766

0.0 6

0.0 1

0.0 6

0.0 1

0.0 6

1

2

3

4

5

6

1

2

3

4

5

6

.0

).0).0

3.0

•.0

----------------------------------------------------------------- *

* HEAT STRUCTURE 108 : VESSEL WALL IN *

* LLOW PLENUM REGION *

----------------------------------------------------------------- *

11080000

11080100

11080101

11080102

11080201

11080202

11080301

11080400

11080401

2

0

2

3

5

6

0.0

0

6 3 1 6.5908

1

6.6092

7.0208

2

5

5

557.00 6

- A..26 -
11080501

11080502

11080601

11080602

11080701

11080801

108010000

110010000

0

0

0 0.0

0 0.0

0

0

0

0

0.0

0.0

1

1

0

0

1

1

1

1

0.0

0.0

0.1554

0.2866

0.1554

0.2866

2

2

1

2

1

2

*

* .*

* HEAT STRUCTURE 110 : LOWER PLENUM4/CORE INLET *

* VOLUME INTERNALS *

----------------------------------------------------------------------- *

11100000

11100100

11100101

11100201

11100301

11100400

11100401

11100501

11100502

11100503

11100601

11100602

11100603

11100701

11100801

11100802

11100803

11100901

11100902

11100903

3 3 1

0 1

2 0.1218

5 2

0.0 2

0

557.00 3

110010000 0

108010000 0

112010000 0

110010000 0

108010000 0

112010000 0

0 0.0

0 0.0

0 0.0

0 0.0

0 0.0

0 0.0

0 0.0

1 0.0000

1 1 1 1

1 1

1 1

1 1

1 1

0.0000

5.0274

9.9978

4.6385

5.0274

9.9978

4.6385

114.7142

62.2150

124.7717

114.7142

62.2150

124.7717

0.0000

0.0000

0.0000

0.0000

0.0000

0.0000

0.0000

1

2

3

1

2

3

3

1

2

3

1

2

3

----------------------------------------------------------------------- *

* HEAT STRUCTURE 11-1 : LOWER CORE SUPPORT PLATE* *---------------------------------- ------------------------------------ -- 

11110000

11110100

11110101

11110101

11110201

11110301

11110400

11110401

11110501

11110601

11110701

11110801

11110901

1

0

5

5

0.0

6 1 1 0.0000

1

0.4162

5

5

0

557.00

108010000

112010000

6

0

0

1

1 1

1

0

0

0

0.0

*0.0

0.0

0.000

0.7118

0.7118

196.8048

196.8048

0.0000

0.0000

0.0000

1

1

1

1

1

- A.27 -
* - - - - - - - - - - - ----- - - - - - - - - - - - -*

*HEAT STRUCTURE 113 :LOWER CORE PLATE AND FUEL * ASSEMBLY BOTTOM NOZZLES *

*

----------------------------------------------------------------------- *

11130000

11130100

11130101

11130201

11130301

11130400

11130401

11130501

11130601

11130701

11130801

11130901

1 3

0 1

2 0.054:

5 2

0.0 2

0

557.00

112010000

112010000

0 0.0

0 0.0

0 0.0

1 1 0.0000

3

3

0

0

0.0000

0.0513

0.0513

267.0491

267.0491

0.0000

0.0000

0.0000

1

1

1

1

1

*-----------------------------------------------------------------------

* HEAT STRUCTURE 116 :CORE BAFFLE ASSEMBLY* ----------------------------------------------------------------------- *

11600

111601000

11160100

11160101

11160201

11160301

11160400

11160401

11160501

11160502

11160503

11160505

11160505

11160506

11160601

11160603

11160603

11160604

11160605

11160606

11160701

M60901

6 3

0 1

2 7.1195

5 2

0.0 2

0

557.00

114010000

1-14020000

114030000

114040000

114050000

114060000

1-16010000

116020000

1-16030000

116040000

116050000

116060000

0 0.0

0 0.0

0 0.0

1 1 7.0209

3

0

0

0

0

0

0

0

0

0

0

0

0

1

1

1

1

1

1

1

1

1

1

1

1

0.0000

4. 1593

1.5093

1

1

1

1

1

1

1

1

1

1

1

1

2.1060

2.1060

2.1060

2.1060

2.1060

2.1060

2.1060

2.1060

2.1060

2.1060

2.1060

2.1060

0.0000

0.0000

0.0000

3

4

5

6

1

2

3

4

5

6

6

6

6

----------------------------------------------------------------------- *

* HEAT STRUCTURE 118 *UPPER CORE PLATE AND FUEL* * ~ASSEMBLY TOP NOZZLES* ----------------------------------------------------------------------- *

- A. 28 -
11180000

11180100

11180101

11180201

11180301

11180400

11180401

11180501

11180601

11180701

11180801

11180901

1 3

0 1

2 0.087(

5 2

0.0 2

0

618.90

118010000

118010000

0 0.0

0 0.0

0 0.0

1 1 0.0

3

0

0

1 1 1 1

0.0000

0.0913

0.0913

227.8132

227.8132

0.0000

0.0000

0.0000

1

1

1

1

1

----------------------------------------------------------------- *

* HEAT STRUCTURE 121 : UPPER CORE SUPPORT COLUMNS *

----------------------------------------------------------------- *

11210000 3 4 2 1 0.0

11210100 0 1

11210101 3 0.1630

11210201 5 3

11210301 0.0 3

11210400 0

11210401 618.00 4

11210501 0 0 0 1 72.2567 1

11210502 0 0 0 1 144.5133 2

11210503 0 0 0 1 62.2300 3

11210601 122010000 0 1 1 72.2567 1

11210602 120010000 0 1 1 144.5133 2

11210603 118010000 0 1 1 62.2300 3

11210701 0 0.0 0.0000 0.0000 3

11210901 0 0.0 7.4958 0.0000 3

----------------------------------------------------- *

*HEAT STRUCTURE 122 : GUIDE TUBE LOWER ASSEMBLY WALL* *---------------------------------------------------------------

11220000

11220100

11220101

11220201

11220301

11220400

11220401

11220501

11220502

11220503

11220601

1120602

11220603

3 3 2

0 1

2 0.3652

5 2

0.0 2

0

587.00

130010000

130010000

130010000

122010000

120010000

118010000

1 0.3216

3

0

0

0

0

0

0

1

1

1

1

1

1

1

1

1

1

1

1

93.9337

187.8673

80.8990

93.9337

187.8673

80.8990

1

2

3

1

2

3

- A.29 -
11220701

11220801

11220901

0

0

0

0.0

0.0

0.0

0.0000

0.0000

1.4094

0.0000

0.0000

0.0000

3

3

3

----------------------------------------------------------------------- *

* HEAT STRUCTURE 123 :SUPPORT PLATE PORTION OF UPPER *

* ~CORE SUPPORT ASSEMBLY ----------------------------------------------------------------------- *

11230000

11230100

11230101

11Z30201

11Z30301

11Z30400

11Z30401

11Z30501

11230601

11230701

11230801

11230901

1 5 1

0 1

4 0.4794

5 4

0.0 4

0

587.00 5

122010000 0

124010000 0

0 0.0000

0 11.0900

0 10.6733

1 0.0

1 0

1 0

0.0

0.0

0.0

138.86-35

138.8635

0.0000

0.0000

0.0000

1

1

1

1

1

----------------------------------------------------------------------- *

*HEAT STRUCTURE 124 :GUIDE TUBE UPPER ASSEMBLY WALL* ----------------------------------------------------------------------- *

11240000 2 3 2 1 0.3166

11240100 0 1

11240101 2 0.3708

11240201 5 2

11240301 0.0 2

11240400 0

11240401 557.00 3

11240501 130010000 0 1 1 120.1720 1

11240502 130010000 0 1 1 156.6067 2

11240601 124010000 0 1 1 120.1720 1

11240602 126010000 0 1 1 156.6067 2

11240701 0 0.0 0.0000 0.0000 2

11240801 0 0.0 0.0000 0.0000 2

1124090 0 0.0 2.2122 0.0000 1

11240902 0 0.0 3.0448 0.0000 2

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

*HEAT STRUCTURE 125 :CYLINDRICAL PORTION OF UPPER *

* ~CORE SUPPORT ASSEMBLY*

11500

112501000

11250100

1

0

2

3 2 1 5.3367

1

5.6957

- A. 30 -
11250201 5 2

11250301 0.0 2

11250400 0

11250401 557.00

11250501 124010000

11250601 0

11250701 0 0.0

11250801 0 0.0

3

0

0

1 1

0 1

0.0000

7.9934

2.3110

2.3110

0.0000

0.0000

1

1

1

1

----------------------------------------------------------------- *

* HEAT STRUCTURE 128 : VESSEL CLOSURE HEAD *

----------------------------------------------------------------- *

11280000 3 8 3

11280100 0 1

11280101 2 6.6042

11280102 5 7.1200

11280201 5 2

11280202 6 7

11280301 0.0 7

11280400 0

11280401 557.00 8

11280501 128010000 0

11280502 128020000 0

11280503 126010000 0

11280601 0 0

11280602 0 0

11280603 0 0

11280701 0 0.0

11280801 0 0.0

1 6.5858

1 1 1 1

1 1

0 1

0 1

0 1

0.0000

0.0000

0.1126

0.1126

0.2286

0.1126

0.1126

0.2286

0.0000

0.0000

1

2

3

1

2

3

3

3

----------------------------------------------------------------------- +

* HEAT STRUCTURE 400 : INTACT AND BROKEN HOT LEG

* PIPING *

*

14000000 10 6

14000100 0 1

14000101 5 1.417

14000201 5 5

14000301 0.0 5

14000400 0

14000401 617.00

14000501 400010000

14000502 400020000

14000503 410010000

14000504 410020000

14000505 410030000

14000506 200010000

14000507 200020000

2 1 1.208

6

0

0

0

0

0

0

0

1

1

1

1

1

1

1

1

1

1

1

1

1

1

6.4413

6.4413

3.5499

3.5499

3.7973

12.8826

12.8826

1

2

3

4

5

6

7

- A.31 -
14000508 205010000 0 1 1

14000509 210010000 0 1 1

14000510 210020000 0 1 1

14000601 0 0 0 1

14000602 0 0 0 1

14000603 0 0 0 1

14000604 0 0 0 1

14000605 0 0 0 1

14000606 0 0 0 1

14000607 0 0 0 1

14000608 0 0 0 1

14000609 0 0 0 1

14000610 0 0 0 1

14000701 0 0.0 0.0000

7.0998

7.0998

7.5946

6.4413

6.4413

3.5499

3.5499

3.7973

12.8826

12.8826

7.0998

7.0998

7.5946

0.0000

8

9

10

1

2

3

4

5

6

7

8

9

10

10

14000801 0 0.0 0.0000 0.0000 10

*----------------------------------------------------------------------- 4

*HEAT STRUCTURE 420 :INTACT AND BROKEN LOOP PUMIP

* SUCTION PIPING

*

*

14200000 10 6

14200100 0 1

14200101 5 1.500(

14200201 5 5

14200301 0.0 5

14200400 0

14200401 557.00

14200501 420010000

14200502 420020000

14200503 420030000

14200504 420040000

14200505 420050000

14200506 220010000

14200507 220020000

14200508 220030000

14200509 220040000

14200510 22005000

14200601 0

14200602 0

14200603 0

14200604 0

14200605 0

14200606 0

14200607 0

14200608 0

14200609 0

14200610 0

14200701 0 0.0

2 1 1.2917

011

011

011

011

011

011

011

01i

0 1

0 1

0100

4.8392

4.5283

7.0686

2.5573

7.068

9.6785

9.0567

14.1372

5.1146

14.1372

4.8392

4.5283

7.0686

2.5573

7.0686

9.6785

9. 0567

14.1372

5.1146

14.1372

0.0000

3

4

5

6

7

8

9

10

3

4

5

6

7

8

9

10

10

- A. 32 -
14200801 0 0.0 0.0000 0.0000 10

14200801 0- --- -- -0.0 --- ---- --- ---- --- ----- 10

*HEAT STRUCTURE 425 :INTACT AND BROKEN LOOP * ~PUMIP CASING *

*

14250000 2 9 2

14250100 0 1

14250101 8 3.0072

14250201 5 8

14250301 0.0 8

14250400 .0

14250401 557.00 9

14250501 425010000 0

14250502 225010000 0

14250601 0 0

14250602 0 0

14250701 0 0.0

14250801 0 0.0

1 2.346

1 1 9.8460 1

1 1 19.6920 2

0 1 9.8460 1

0 1 19.6920 2

0.0000 0.0000 2

0.0000 0.0000 2

*------------------------------------------------------------------------*

*HEAT STRUCTURE 430 :INTACT AND BROKEN LOOP * COLD LEG PIPING *

*

14300000 10 5

14300100 0 1

14300101 4 1.333(

14300201 5 4

14300301 0.0 4

14300400 0

14300401 557.00

14300501 430010000

14300502 430020000

14300503 440010000

14300504 452010000

14300505 452020000

14300506 230010000

14300507 230020000

14300508 240010000

14300509 252010000

14300510 252020000

14300601 0

14300602 0

14300603 0

14300604 0

14300605 0

14300606 0

14300607 0

2 1 1.1460

1

1

1

1

1

1

0

4.4073

4.4073

3.6835

6.5969

6.5969

8. 8147

8.8147

7.3665

13.1938

13.1938

4.4073

4.4073

3.6835

6.5969

6.5969

8.8147

8.8147

1

2

3

4

5

6

7

8

9

10

1

2

3

4

5

6

7

- A. 33 -
14300608

14300609

14300610

14300701

14300801

0

0

0

0

0

0

0

0

0 1

0 1

0 1

0.0000

0.0000

7.3665

13.1938

13.1938

0.0000

0.0000

8

9

10

10

10

0.0

0.0

----------------------------------------------------------------- *

* HEAT STRUCTURE 6201 : PRESSURIZER VESSEL WALL *

* (UPPER PARTIAL WALL) *

----------------------------------------------------------------- *

*6201000 1 8 3 1 3.5833

*6201100 0 1

*6201101 2 3.5992

*6201102 5 3.7575

*6201201 5 2

*6201202 6 7

*6201301 0.0 7

*6201400 0

*6201401 652.00 8

*6201501 620010000 0 1 1 0.3928 1

*6201601 0 0 0 1 0.3928 1

*6201701 0 0.0 0.0 0.0000 1

*6201801 0 0.0 0.0 0.0000 1

- --

* HEAT STRUCTURE 6202 : PRESSURIZER VESSEL WALL *

* (MIDDLE CYLINDRICAL VOLUMIE) *

*6202000

*6202100

*6202101

*6202102

*6202201

*6202202

*6202301

*6202400

*6202401

*6202501

*6202502

*6202503

*6202504

*6202505

*6202506

*6202507

*6202508

*6202601

*6202602

*6202603

8 8

0 1

2 3.5:

5 3.6•

5 2

6 7

0.0 7

0

652.00

620010000

620020000

620030000

620040000

620050000

620060000

620070000

620080000

0

0

0

158

742

1 3.5000

8

0

0

0

0

0

0

0

0

0

0

0

1

1

1

1

1

1

1

1

0

0

0

1

1

1

1

1

1

1

1

1

1

1

2.4886

3.8977

5.1969

5.1969

5.1969

5.1969

3.8977

2.4866

2.4886

3.8977

5.1969

1

2

3

4

5

6

7

8

1

2

3

- A.34 -
*6202604 0 0 0 1 5.1969 4

*6202605 0 0 0 1 5.1969 5

*6202606 0 0 0 1 5.1969 6

*6202607 0 0 0 1 3.8977 7

*6202608 0 0 0 1 2.4866 8

*6202701 0 0.0 0.0 0.0000 8

*6202801 0 0.0 0.0 0.0000 8

----------------------------------------------------------------- *

* HEAT STRUCTURE 6203 : PRESSURIZER VESSEL WALL *

* (LOWER PARTIAL VOLUME) *

----------------------------------------------------------------- *

*6203000 1 2 3 0 3.5833

*6203100 0 1

*6203101 1 3.7575

*6203201 5 1

*6203301 1.0 1

*6203400 0

*6203401 652.00 2

*6203501 620080000 0 2901 1 0.3928 1

*6203601 0 0 0 1 0.3928 1

*6203701 751 1.0 0.0 0.3928 1

*6203801 0 0.0 0.0 0.0000 1

** ** ******   ** ******* *** ********** *** ******** *** ***** **

* CORE FUEL PIN *

11140000 6 17 2 1 0.0 2 1 8

11140100 0 1

11140101 6 0.0129

11140102 2 0.01316

11140103 8 0.015035

11140201 1 6

11140202 2 8

11140203 3 16

11140301 1.0 6

11140302 0.0 16

11140401 1100. 3

11140402 900. 5

11140403 620. 7

11140404 600. 9

11140405 570. 17

11140501 0 0 0 0 0.0 1

11140502 0 0 0 0 0.0 2

11140503 0 0 0 0 0.0 3

11140504 0 0 0 0 0.0 4

11140505 0 0 0 0 0.0 5

11140506 0 0 0 0 0.0 6

- A.35 -
11140601 114010000 00000 1

11140602 114020000 10000 1

11140603 114060000 00000 1

11140701 1000 0.135870 0.0

11140702 1000 0.158960 0.0

11140703 1000 0.163920 0.0

11140704 1000 0.182110 0.0

11140705 1000 0.210220 0.0

11140706 1000 0.122920 0.0

11140801 0 0.0 0.0

11140901 0 0.04250 0.0

11140902 0 0.04250 0.0

11140903 0 0.04250 0.0

1 87178.96 1

1 87282.58 5

1 61999.30 6

0.003630 1

0.004240 2

0.004380 3

0.004860 4

0.005610 5

0.003280 6

0.0 6

2.0103 1

2.1058 5

1.4958 6

* HEAT STRUCTURE INPUT*

*HEAT STRUCTURE 500; BROKEN STEAM GENERATOR U-TUBES*

15001000

15001100

15001101

15001201

15001301

15001401

*5001501

*5001502

*5001503

*5001601

*5001602

*5001603

*5001604

15001501

15001502

15001503

15001601

15001602

15001603

15001604

15001701

15001801

15001802

15001803

15001901

15001902

15001903

8 3 2 1 0.02525

0 1

2 0.028667

4 2

0.0 2

550. 3

500020000 0 1 1

500030000 10000 1 1

500090000 0 1 1

540010000 0 1 1

540020000 10000 1 1

540040000 -10000 1 1

540010000 0 1 1

500020000 0 1 1

500030000 10000 1 1

500090000 0 1 1

540010000 0 1 1

540020000 10000 1 1

540040000 -10000 1 1

540010000 0 1 1

0 0.0 0.0 0.0- 8

0 0.0505. 0.0 5.43 1

0 0.0505 0.0 7.20 7

0 0.0505 0.0 5.43 8

0 0.0908 0.0 5.43 1

0 0.0908 0.0 7.20 7

0 0.0908 0.0 5.43 8

35566.07

47159.44

35566.07

35566.07

47159.44

47159.44

35566.07

12803.79

16977.40

12803.79

12803.79

16977.40

16977.40

12803.79

1

7

8

1

7

8

1

4

7

8

*HEAT STRUCTURE 5002; CHANNEL HEAD*

- A. 36 -
15002000 A 6 3 1 5.234

15002100 0 1

15002101 5 5.8601

15002201 6 5

15002301 0.0 5

15002401 600.0 6

15002501 500010000 90000 1 1 0.25 2

15002502 300010000 90000 1 1 0.50 4

15002601 0 0 0 1 0.25 2

15002602 0 0 0 1 0.50 4

15002701 0 0.0 0.0 0.0 4

15002801 0 0.0 0.0 4.0095 4

15002901 0 0.0 0.0 4.0095 4

* HEAT STRUCTURE 5301; S/G TRAN4SITION CONE SHELL *

15301000 2 6 2 1 6.205

15301100 0 1

15301101 5 6.5033

15301201 6 5

15301301 0.0 5

15301401 520.0 6

15301501 530010000 0 1 1 7.43 1

15301502 330010000 0 .1 1 14.86 2

15301601 0 0 0 1 7.43 1

15301602 0 0 0 1 14.86 2

15301701 0.0 0.0 0.0 0.0 2

15301801 0 0.0 0.0 7.43 2

15301901 0 0.0 0.0 7.43 2

* HEAT STRUCTURE 5302; S/G LOWER SHELL *

15302000

15302100

15302101

15302201

15302301

15302401

15302501

15302502

15302503

15302504

15302505

15302506

15302507

15302508

15302601

15302602

15302603

10 5 2 1 5.391

0 1

4 5.578

6 4

0.0 4

500. 5

530050000 0 1

530040000 -10000 1

530020000 0 1

530010000 0 1

330050000 0 1

330040000 -10000 1

33002000 0 1

330010000 0 1

0 0 0

0 0 0

0 0 0

1 5.43 1

1 7.20 3

1 6.34 4

1 4.79 5

1 10.86 6

1 14.40 8

1 12.68 9

1 9.58 10

1 5.43 1

1 7.20 3

1 6.34 4

- A. 37 -
15302604 0

15302605 0

15302606 0

15302607 0

15302608 0

15302701 0

1530Z801 0

15302802 0

15302803 0

15302804 0

15302805 0

15302806 0

15302807 0

15302808 0

15302901 0

15302902 0

15302903 0

15302904 0

15302905 0

15302906 0

15302907 0

15302908 0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0

0

0

0

0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0

0

0

0

0

0.0

5.43

7.20

6.34

4.79

5.43

7.20

6.34

4.79

5.43

7.20

6.34

4.79

5.43

7.20

6.34

4.79

1 4.79 5

1 10.86 6

1 14.40 8

1 12.68 9

1 9.58 10

10

1

3

4

5

6

8

9

10

1

3

4

5

6

8

9

10

* HEAT STRUCTURE 5401; BROKEN SIG WRAPPER *

15401000 5 3 2 1 5.125

15401100 0 1

15401101 2 5.15625

15401201 6 2

15401301 0.0 2

15401401 535.0 3

15401501 540010000 0

15401502 540020000 10000

15401503 540040000 0

15401504 540050000 0

15401601 530050000 0

15401602 530040000 -10000

15401603 530020000 0

15401604 530010000 0

15401701 0 0.0 0.0 0.

15401801 0 0.0 0.0 5.

15401802 0 0.0 0.0 7.

15401803 0 0.0 0.0 6.

15401804 0 0.0 0.0 2.

15401901 0 0.0 0.0 5.

1540190Z 0 0.0 0.0 7.

154010903 0 0.0 0.0 6.

15401904 0 0.0 0.0 2.

1

13

1o

20

'34

.88

1

1

1

1

1

1

1

1

5.43 1

7.20 3

6.34 4

2.88 5

5.43 1

7.20 3

6.34 4

2.88 5

5

1

3

4

5

4

5

* HEAT STRUCTURE 5402; BROKEN S/G WRAPPER *

- A. 38 -
* TRANSITION CONE *

15402000 1 3 2 1 6.422

15402100 0 1

15402101 2 6.453

15402201 6 2

15402301 0.0 2

15402401 530.0 3

15402501 540050000 0 1 1 4.75 1

15402601 530010000 0 1 1 4.75 1

15402701 0 0.0 0.0 0.0 1

15402801 0 0.0 0.0 4.75 1

15402901 0 0.0 0.0 4.75 1

* HEAT STRUCTURE 5403; BROKEN S/G RISER BARREL *

15403000

15403100

15403101

15403201

15403301

15403401

15403501

15403502

15403601

15403602

15403701

15403801

15403802

15403901

15403902

2 3 2 1 0.8125

0 1

2 0.8333

6 2

0.0 2

538.0 3

540050000 0

550010000 0

530010000 0

550010000 0

0 0.0 0.0

0 0.0 0.0

0 0.0 0.0

0 0.0 0.0

0 0.0 0.0

1 1 1 1

1 1

1 1

0.0

4.59

6.667

4.59

6.667

73.44 1

106.67 2

73.44 1

106.67 2

2

1

2

1

2

* HEAT STRUCTURE 3404; S/G TUBE SUPPORT/SPACER PLATE *

15404000

15404100

15404101

15404201

15404301

15404401

15404501

15404502

15404601

15404602

15404701

15404801

15404802

15404803

15404804

15404805

8 3 1 1 0.0

0 1

2 0.09375

6 2

0.0 2

545.0 3

540010000 10000 1

340010000 10000 1

540010000 10000 1

340010000 10000 1

0 0.0 0.0 0.0

0 0.0 0.0 5.43

0 0.0 0.0 7.20

0 0.0 0.0 6.34

0 0.0 0.0 5.43

0 0.0 0.0 7.20

1 121.6 4

1 243.2 8

1 121.6 4

1 243.2 8 8

1

3

4

5

7

- A.39 -
15404806 0 0.0 0.0 6.34

15404901 0 0.0 0.0 5.43

15404902 0 0.0 0.0 7.20

15404903 0 0.0 0.0 6.34

15404904 0 0.0 0.0 5.43

15404905 0 0.0 0.0 7.20

15404906 0 0.0 0.0 6.34

8

1

3

4

5

7

8

*HEAT STRUCTURE 5601; SIG STEAM DRIER ASSEMBLY

15601000 2 5 1 1 0.0

15601100 0 1

15601101 4 0.1667

15601201 6 4

15601301 0.0 4

15601401 545.0 5

15601501 560010000 0 1 1 277.1 1

15601502 360010000 0 1 1 554.2 2

15601601 560010000 0 1 1 277.1. 1

15601602 360010000 0 1 1 554.2 2

15601701 0 0.0 0.0 0.0 2

15601801 0 0.0 0.0 9.8333 2

15601901 0 0.0 0.0 9.8333 2

* HEAT STRUCTURE 5602; SIG UPPER SHELL CYLINDER *

15602000

15602100

15602101

15602201

15602301

15602401

15602501

15602502

15602503

15602504

15602601

15602602

15602603

15602604

15602701

15602801

15602802

15602803

15602804

15602901

1502902

15602903

15602904

4 5 21

0 1

4 7.3500

6 4

0.0 4

545.0 5

550010000 0

560010000 0

350010000 0

360010000 0

0 0

0 0

0 0

0 0

0 0.0 0.0

0 0.0 0.0

0 0.0 0.0

0 0.0 0.0

0 0.0 0.0

0 0.0 0.0

0 0.0 0.0

0 0.0 0.0

0 0.0 0.0

7. 0208

1 1 6.69 1

1 1 12.21 2

1 1 13.38 3

1 1 24.42 4

0 1 6.69 1

0 1 12.21 2

0 1 13.38 3

0 1 24.42 4

0.0 4

6.69 1

12.21 2

13.38 3

24.42 4

6.69 1

12.21 2

13.38 3

24.42 4

- A. 40 -
• HEAT STRUCTURE 5603; S/G STEAM DRUM HEAD *

15603000 2 5 3 1 7.0208

15603100 0 1

15603101 4 7.3541

15603201 6 4

15603301 0.0 4

15603401 540.0 5

15603501 560020000 0 1 1 0.431 1

15603502 360020000 0 1 1 0.862 2

15603601 0 0 0 1 0.431 1

15603602 0 0 0 1 0.862 2

15603701 0 0.0 0.0 0.0 2

15603801 0 0.0 0.0 5.29 2

15603901 0 0.0 0.0 5.29 2

• HEAT STRUCTURE 3001; INTACT S/G U-TUBES *

13001000 8 3 2 1 0.02525

13001100 0 1

13001101 2 0.028667

13001201 4 2

13001301 0.0 2

13001401 550. 3

*3001501 300020000 0 1 1 71132.14 1

*3001502 300030000 10000 1 1 94318.87 7

*3001503 300090000 0 1 1 71132.14 8

*3001601 340010000 0 1 1 71132.14 1

*3001602 340020000 10000 1 1 94318.87 4

*3001603 340040000 -10000 1 1 94318.87 7

*3001604 340010000 0 1 1 71132.14 8

13001501 300020000 0 1 1 25607.57 1

13001502 300030000 10000 1 1 33954.79 7

13001503 300090000 0 1 1 25607.57 8

13001601 340010000 0 1 1 25607.57 1

13001602 340020000 10000 1 1 33954.79 4

13001603 340040000 -10000 1 1 33954.79 7

13001604 340010000 0 1 1 25607.57 8

13001701 0 0.0 0.0 0.0 8

13001801 0 0.0505 0.0 5.43 1

13001802 0 0.0505 0.0 7.20 7

13001803 0 0.0505 0.0 5.43 8

13001901 0 0.0908 0.0 5.43 1

13001902 0 0.0908 0.0 7.20 7

13001903 0 0.0908 0.0 5.43 8

* HEAT STRUCTURE 3401; BROKEN S/G WRAPPER *

13401000 5 3 2 1 5.125

13401100 0 1

- A.41 -
13401101 2 5.15625

13401201 6 2

13401301 0.0 2

13401401 535.0 3

13401501 340010000

13401502 340020000

13401503 340040000

13401504 340050000

13401601 330050000

13401602 330040000

13401603 330020000

13401604 330010000

13401701 0 0.0

13401801 0 0.0

13401802 0 0.0

13401803 0 0.0

13401804 0 0.0

13401901 0 0.0

13401902 0 0.0

13401903 0 0.0

13401904 0 0.0

0

10000

0

0

0

-10000

0

0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

1

1

1

1

1

1

1

1

0.0

5.43

7.20

6.34

2.88

5.43

7.20

6.34

2.88

1 10.86 1

1 14.40 3

1 12.68 4

1 3.76 5

1 10.86 1

1 14.40 3

1 12.68 4

1 3.76 5

5

1

3

4

5

1

3

4

5

* HEAT STRUCTURE 3402; INTACT S/G WRAPPER *

13402000 1 3 2 1 6.422

13402100 0 1

13402101 2 6.453

13402201 6 2

13402301 0.0 2

13402401 530.0 3

13402501 340050000 0 1 1 9.50 1

13402601 330010000 0 1 1 9.50 1

13402701 0 0.0 0.0 0.0 1

13402801 0 0.0 0.0 4.75 1

13402901 0 0.0 0.0 4.75 1

* HEAT STRUCTURE 3403; BROKEN S/G RISER BARREL "*

13403000 2 3 2 1 0.8125

13403100 0 1

13403101 2 0.8333

13403201 6 2

13403301 0.0 2

13403401 538.0 3

13403501 340050000 0 1 1 146.88 1

13403502 350010000 0 1 1 213.34 2

13403601 330010000 0 1 1 146.88 1

13403602 350010000 0 1 1 213.34 2

13403701 0 0.0 0.0 0.0 2

13403801 0 0.0 0.0 4.59 1

- A.42 -
13403802

13403901

13403902

0

0

0

0.0 0.0 6.667

0.0 0.0 4.59

0.0 0.0 6.667

2

1

2

*********** ** *********   ** *** ****************** ******* *** ** *

* CONTROL VARIABLES *

***** ********** ** ******** *** ****** ***** ***** ** ******** ** ******

* CONTROL VARIABLE 15; BROKEN S/G WATER LEVEL *

20501500 BSGLEVEL SUM 6.286E-4 0.50 1

20501501 30.78269 62.4 VOIDF 540050000 187.6 VOIDF 530010000

20501502 1025.0 VOIDF 550010000 335.0 VOIDF 560010000

20515000 ASGLEV SUM 1.0 0.0 1

20515001 0.0 1.0 P 530010000 -1.0 P 560010000

20515100 AH DIV 0.10204 0.0 1

20515101 RHO 530010000 CNTRLVAR 150

20515200 LENGTH SUM 1.0 0.0 1

20515201 -2.3282 1.0 CNTRLVAR 151

20515300 ASLEVEL MULT 0.3076 0.0 1

20515301 CNTRLVAR 152

* CONTROL VARIABLE 16; BROKEN SIG SECONDARY MASS INVENTORY *

20501600 BSGSMASS SUM 0.0624306 0.0 1

20501601 0.0 307.56 RHO 540010000 393.78 RHO 540020000

20501602 393.78 RHO 540030000 370.48 RHO 540040000

20501603 774.40 RHO 540050000 1025.0 RHO 550010000

20501604 1539.0 RHO 560010000 400.00 RHO 560020000

20501605 495.60 RHO 530010000 49.520 RHO 530020000

20501606 56.220 RHO 530030000 56.220 RHO 530040000

20501607 42.440 RHO 530050000

* CONTROL VARIABLE 17; BROKEN S/G FEEDWATER VALVE GAIN *

*0501700 BSFGAIN SUM 1.0 1.0 1

*0501701 2.65 -3.3 CNTRLVAR 015

* CONTROL VARIABLE 18; INTACT S/G WATER LEVEL *

20501800 ISGLEVEL SUM 3.143E-4 0.50 1

20501801 61.56538 124.8 VOIDF 340050000 375.2 VOIDF 330010000

20501802 2050.0 VOIDF 350010000 670.0 VOIDF 360010000

* CONTROL VARIABLE 19; INTACT S/G SECONDARY MASS INVENTORY *

20501900 ISGSMASS SUM 0.0624306 0.0 1

20501901 0.0 615.12 RHO 340010000 787.56 RHO 340020000

- A.43 -
20501902 787.56 RHO 340030000 740.96 RHO 340040000

20501903 1548.80 RHO 340050000 2050.0 RHO 350010000

20501904 3078.0 RlO 360010000 800.00 RHO 360020000

20501905 991.20 RHO 330010000 99.040 RHO 330020000

20501906 112.44 RHO 330030000 112.44 RHO 330040000

20501907 84.880 RHO 330050000

* CONTROL VARIABLE 20; INTACT S/G FEEDWATER VALVE GAIN *

*0502000 ISFGAIN SUM 1.0 1.0 1

*0502001 2.65 -3.3 CNTRLVAR 018

* HEAT STRUCTURE THERMAL PROPERTY DATA *

* COMPOSITION TYPE AND DATA FORMAT *

20100100 TBL/FCTN 1 1 * CORE FUEL

20100200 TBL/FCTN 1 1 * CORE FUEL GAP

20100300 TBL/FCTN 1 1 * CORE FUEL CLADDING

20100400 TBL/FCTN 1 1 * INCONEL

20100500 TBL/FCTN 1 1 * STAINLESS STEEL

20100600 TBL/FCTN 1 1 * CARBON STEEL

* THERMAL CONDUCTIVITY DATA (BTU/SEC-FT/DEG F) AND VOLUMETRIC HEAT *

* CAPACITY DATA (BTIJ/FT**3-DEG F) VERSUS TEMPERATURE FOR ABOVE *

* COMPOSITION *

* CORE FUEL

* TEMPERATURE THERMAL CONDUCTIVITY

20100101 188.6 2.284E-3

20100102 332.6 2.1235E-3

20100103 440.6 8.951E-4

20100104 500.0 8.2806E-04

20100105 650.0 6.4194E-04

20100106 800.0 5.4361E-04

20100107 950.0 5.7750E-04

20100108 1100.0 4.2278E-04

20100109 1250.0 7.7722E-04

- A.44 -
20100110

20100111

20100112

20100113

20100114

20100115

20100116

20100117

20100118

20100119

20100120

20100121

20100122

20100123

1400.0

1500.0

1700.0

1850.0

2000.0

2150.0

2300.0

2450.0

2600.0

3100.0

3600.0

4100.0

4600.0

5100.0

7.3889E-04

8.0739E-04

8.7789E-04

4.5628E-04

3.3556E-04

5.1661E-04

4.0472E-04

3.5306E-04

6.6689E-04

5.4350E-04

3.7228E-04

4.6156E-04

5.4722E-04

2.3056E-04

HEAT CAPACITY

20100151

20100152

20100153

20100154

20100155

20100156

20100157

20100158

20100159

20100160

20100161

20100162

20100163

20100164

20100165

20100166

TEMPERATURE

32.0

122.0

212.0

392.0

752.0

2012.0

2732.0

3092.0

3452.0

3812.0

4352.0

4532.0

4712.0

4892.0

5144.0

8000.0

30.45

34.35

47.75

44.55

45.70

41.35

32.65

66.55

83.05

52.80

69.70

44.25

38.15

120.10

96.40

131.40

* CORE FUEL GAP

20100201

20100202

20100251

20100252

TEMPERATURE THERMAL CONDUCTIVITY

2.4487788E-04

2.4487788E-04

32.0

5400.0

TEMPERATURE HEAT CAPACITY

32.0

5400.0

0.000065

0.000065

* CORE FUEL CLADDING *k

- A.45 -
* TEMPERATURE

20100301 392.0

20100302 752.0

20100303 1112.0

20100304 1472.0

20100305 1832.0

20100306 2192.0

20100307 2552.0

20100308 2912.0

20100309 3272.0

20100310 3632.0

20100311 3992.0

* TEMPERATURE

20100351 0.0

20100352 1480.3

20100353 1675.0

20100354 1787.5

20100355 3500.0

* INCONEL ,

* TEMPERATURE

20100401 32.0

20100402 1050.0

* TEMPERATURE

20100451 100.0

20100452 400.0

20100453 600.0

20100454 800.0

* STAINLESS STEEL *

* TEMPERATURE

20100501 32.0

20100502 1700.0

20100503 5000.0

* TEMPERATURE

20100551 200.0

20100552 300.0

20100553 400.0

THERIMAL CONDUCTIVITY

2.9267E-03

1.2478E-03

4.7297E-03

5.0508E-03

6.5325E-03

4.0142E-03

5.8169E-03

8.7803E-03

1.0647E-03

1.8311E-03

9.0918E-02

HEAT CAPACITY

26.392

35.476

75.176

44.370

24.476

THERMAL CONDUCTIVITY

2.1167E-03

4.0394E-03

HEAT CAPACITY

57.180

61.140

63.770

66.410

THERMAL CONDUCTIVITY

2.0833E -03

4.0294E-03

4.0294E-03

HEAT CAPACITY

57.114

59.118

61.122

- A.46 -
20100554

20100555

20100556

20100557

20100558

20100559

20100560

* CARBON

20100601

20100602

20100603

20100604

20100605

20100606

20100607

20100608

20100609

20100651

20100652

20100653

20100654

20100655

500.0

600.0

700.0

800.0

1000.0

2000.0

5000.0

STEEL

TEMPERATURE

80.0

440.33

800.33

1160.33

1520.33

1880.33

2240.33

2600.33

2960.33

TEMPERATURE

80.0

200.03

1600.07

2600.33

2960.33

63.126

64.629

66.130

67.134

69.138

80.160

80.160

THERMAL CONDUCTIVITY

0.01126

0.01009

0.00908

0.00824

0.00756

0.00705

0.00670

0.00652

0.00649

HEAT CAPACITY

57.29

57.29

82.04

104.71

112.49

*

*

*

* REACTOR KINETICS

*

30000000

30000001

30000002

*0000011

*0000012

*0000501

30000501

30000502

30000601

30000602

30000603

POINT

GAMMA-AC 80.48E06 0.0 297.0 1.0 0.48

ANS73

10118

998

44.0 0.0

44.0 0.07696 44.78 0.06964 45.52 0.04398

46.2 0.01010 46.4 0.0

557.0 0.0 653.3 -0.1789 749.6 -0.3401

845.9 -0.5043 942.2 -0.6597 1038.5 -0.8137

1134.8 -0.9529 1231.1 -1.0908 1327.4 -1.2168

- A.47 -
30000604

*0000601

30000701

30000702

30000703

30000704

30000705

30000706

30000801

30000802

30000803

30000804

30000805

30000806

1423.7 -1.3371

1600.0 0.0

114010000 0

114020000 0

114030000 0

114040000 0

114050000 0

114060000 0

1140001 0

1140002 0

1140003 0

114OOO4 0

1140005 0

1140006 0

1520.0 -1.4514

0.1367

0.2229

0.1991

0.1862

0.1922

0.0629

0.1367

0.2229

0.1991

0.1862

0.1922

0.0629

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0 *

* COMPONENT 565 STEAM HEADER

5650000

5650101

5650200

ISTfHDR

0.0 42.38

2 970.0

SNGL VOL

450.97 0.0 0.0. 0.0 0.0 0.0 10

1.0

* COMPONENT 566 GOVERNOR VALVE

*r

5660000

5660101

5660200

5660201

5660202

5660203

5660204

*660202

*660202

*660203

*660204

*660205

*660206

*660207

*660208

*660209

TBNVAL ThDPJUN

565010000 569000000 1000.0

1 507

0.0 0.0 50.07 0.0

100.0 0.0 50.07 0.0

101.0 0.0 50.07 0.0

1.0•E04 0.0 50.07 0.0

50.0 0.0 3381.0 0.0

1.0 0.0 2028.6 0.0

2.0 0.0 1196.7 0.0

3.0 0.0 983.87 0.0

4.0 0.0 770.87 0.0

5.0 0.0 561.24 0.0

10.0 0.0 135.24 0.0

1.E04 0.0 135.24 0.0

1000.0 0.0 3381.0 0.0

* COMPONENT 569 TBN

5690000

5690101

5690200

5690201

TBNCON T'DP VOL

1000.0 1.0 0.0 0.0 0.0

2

0.0 964.0 1.0

0.0 0.0 0.0 00

- A.48 -
* STEAM DUMP SYSTEM

20504300 RXPWR MULT

20504301 RKTPOW 0

20504400 SGPRES MULT

20504401 P 360030000

* UNIT CONVERSION

20504500 CONV1 SUM 1.

3.59E-04 0.03 0

1.01972E-05 77.0 0

.0 621.3 0

20504501 -459.67 1.8 TEMPF 200010000

20504600 CONVZ SUM

20504601 -459.67 1.8

20504700 CONV3 SUM

20504701 -459.67 1.8

20504800 CONV4 SUM

20504801 -459.67 1.8

* STEAM HEADER PRESSURE

20504900 STMIIR MULT

20504901 P 565010000

20505000 PIDIF SUM

20505001 -76.8 1.0

1.0 556.99 0

TEMPF 252020000

1.0 621.3 0

TEMPF 400010000

1.0 556.99 0

TEMPF 452020000

1. 01972E-5 76.8 0

1.0 0.0

CNTRLVAR

0

49

20505100 PINTEG INTEGRAL 0.0056 0.0 0

20505101 CNTRLVAR 50

* TIME DEPENDENT JUNCTION

5790000 DUMP TNDPJUN

5790101 565010000 580000000 1000.0

5790200 1 507 CNTRLVAR 51

5790201 0.0 0.0 0.0 0.0

5790202 1.0 0.0 268.0 0.0

5790203 4.0 0.0 1072.00 0.0

* TEMPERATURE CONVERSION FROM FHAR. TO CENTI.

20525000

20525001

20525100

20525101

20525200

20525201

ITEMPH

-32.0

ITEMPC

-32.0

BTEMPH

-32.0

SUM

1.0

SUM

1.0

SUM

1.0

0.5556

CNTRLVAR

0.5556

CNTRLVAR

0.5556

CNTRLVAR

293.5

45

289.8

46

293.0

47

0

0

0

- A.49 -
*

20525300 BTEMPC SUM 0.5556 293.0 0

20525301 -32.0 1.0 CNTRLVAR 48

20525400 AVGT SUM 0.5 292.5 0

20525401 0.0 1.0 CNTRLVAR 250 1.0 CNTRIVAR 251

20525500 DELT SUM 1.0 1.0 0

20525501 0.0 1.0 CNTRLVAR 250 -1.0 CNTRLVAR 251

* COMPONENT 580 CONDENSER ( STH SINK )

5800000 CONDEN1 TlDPVOL

5800101 1000.0 1.0 0.0 0.0 0.0 0.0 0.0 0.0 00

5800200 2

5800201 0.0 14.7 1.0

- A.50 -
N..C FORM 335 U.S. NUCLEAR REGULATORY COMMISSION 1. REPORT NUMBER

124191 (A-s"jh d by NRC. Add V.I.. Supo. Raw,

NRCM 1102. and Addendu.m Numen•. If any.I

3201.3202 BIBLIOGRAPHIC DATA SHEET

fe inst,-C.iOJn7S On *e AeveRIhl NUREG/IA-0125

2. TITLE AND SUBTITLE

Assessment of RELAP5/MOD2 Computer Code Against the 3. DATE REPORT PUBLISHED

Natural Circulation Test Data from Yong-Gwang Unit 2 MONTH 1 3AR

June 1993

4. FIN OR GRANT NUMBER

L2245

6. AUTHOR (S) 6. TYPE OF REPORT

N. Arne, S. Cho H. J. Kim

Korea Electric Power Corporation Korea Institute of Nuclear Safety Technical

7. PERIOD COVERED gtnawwD Ost

S II*UlIVIH'1. p. Y .BJ•,AI. P IJ* •eeI - M q Pl*P4d uu f'I . . PfWW-_ ADVI..--- U"~z . ... I W-- in---a.dVIJ * t-- -, - ... w .... .. E• •---II lI - a ....ao~g5 .WICJ...........

wd meffig ahVsst&v

Korea Electric Power Corporation Korea Institute of Nuclear Safety

Research Center P.O. Box 16, Daeduk-Danji

117-15 Yongjeon-Dong, Dong-Gu Daejon, Korea 305-353

Daejon, Korea

9. SPONSORING ORGANIZATION - NAME AND ADDRESS III DJC. type " ,, bve "N onf acW, .pro. idEPJRC 0 i . Ofti e Re . U. .Ii ,,iew #agutaeo •, Co ,, i .

Office of Nuclear Regulatory Research

U.S. Nuclear Regulatory Commission

Washington, D.C. 20555

10. SUPPLEMENTARY NOTES

11. ABSTRACT (20o'w.ootoo,,

The results of the RELAP/MOD2 computer code simulation for the Natural Circulation Test in Yong-Gwang

Unit 2 are analyzed here and compared with the plant operation data. The result of comparison reveals that the code

calculation does present well the overall macroscopic behaviors of thermalhydraulic parameters in primary and

secondary system compared with the plant operating data. The sensitivity study is performed to find out the effect

of steam dump flow rate on the primary temperatures and it is found that the primary temperatures are very

sensitive to the steam dump flow rate during the Natural Circulation. Because of the inherent uncertainties in the

plant data, the assessment work is focussed on phenomena whereby the comparison between plant data and

calculated data is based more on trends than on absolute values.

12. KEY WORDSIDESCR:PTORS tazi wwz wph-ws 01or w•,ars,•, •, e.a, incad.g Me s•,•w. I&. AVAILABILITY STATEMENT

ICAP Program Unlimited

RELAPS/MOD2 14. SECURITY CLAS"IFICATION

Yong-Gwang Unit 2 Ir,,Pwol

Unclassified

Unclassified

15. NUMBER OF PAGES

16. PRICE

NRC FORM 33S 1249)


Federal Recycling Program

UNITED STATES

NUCLEAR REGULATORY COMMISSION

WASHINGTON, D.C. 20555-0001

OFFICIAL BUSINESS

PENALTY FOR PRIVATE USE, $300

SPECIAL FOURTH-CLASS RATE

POSTAGE AND FEES PAID

USNRC

PERMIT NO. G-e7

Dr. Gene Rhee

RES

NLN-353

(4)