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Attachment to NG-86-1181 C.D.I. TECH NOTE NO. 84-19 MARK I WETWELL TO DRYWELL DIFFERENTIAL PRESSURE LOAD AND VACUUM BREAKER RESPONSE FOR THE DUANE ARNOLD ENERGY CENTER UNIT 1 Revision 0 Prepared by CONTINUUM DYNAMICS, INC. P.O. BOX 3073 PRINCETON, NEW JERSEY 08540 Prepared under Purchase Order No. 205-YF495 for GENERAL ELECTRIC COMPANY 175 CURTNER AVENUE SAN JOSE, CALIFORNIA 95125 Approved by Alan. Bilanin January 1985 I) 8604150391 860408 PDR ADOCK 05000331 P -PDR

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Page 1: Attachment to NG-86-1181 - Nuclear Regulatory CommissionAttachment to NG-86-1181 C.D.I. TECH NOTE NO. 84-19 ... Figure 2-2. Schematic model of the vent system depicted by 12 dynamic

Attachment to NG-86-1181

C.D.I. TECH NOTE NO. 84-19

MARK I WETWELL TO DRYWELL DIFFERENTIAL

PRESSURE LOAD AND VACUUM BREAKER RESPONSE

FOR THE

DUANE ARNOLD ENERGY CENTER UNIT 1

Revision 0

Prepared by

CONTINUUM DYNAMICS, INC. P.O. BOX 3073

PRINCETON, NEW JERSEY 08540

Prepared under Purchase Order No. 205-YF495 for

GENERAL ELECTRIC COMPANY 175 CURTNER AVENUE

SAN JOSE, CALIFORNIA 95125

Approved by

Alan. Bilanin January 1985

I)

8604150391 860408 PDR ADOCK 05000331 P -PDR

Page 2: Attachment to NG-86-1181 - Nuclear Regulatory CommissionAttachment to NG-86-1181 C.D.I. TECH NOTE NO. 84-19 ... Figure 2-2. Schematic model of the vent system depicted by 12 dynamic

SUMMARY

Mark I wetwell to drywell vacuum breaker (VB) actuation velocities during

the chugging phase of a postulated loss of coolant accident (LOCA) are predicted. Data. collected during the full scale test facility (FSTF) test series is used to conservatively predict the differential pressure load across the VB. Adjustment is made for plant-unique drywell volumes with a vent dynamic model validated against FSTF test data. The predicted differential

pressure load is used to drive a valve dynamic model with the plant-specific VB valve characteristics. The valve dynamic model, validated against full scale test data, conservatively predicts actuation velocities. These

velocities are predicted on a plant-unique basis, and presented in this report.

Application of the above methodology to the Duane Arnold Energy Center Unit 1 results in a negative differential pressure peak of 1.11 psid, applied

across installed 18-inch GPE internal vacuum breakers, and a predicted maximum

closing impact velocity of 8.68 rad/sec.

i

Page 3: Attachment to NG-86-1181 - Nuclear Regulatory CommissionAttachment to NG-86-1181 C.D.I. TECH NOTE NO. 84-19 ... Figure 2-2. Schematic model of the vent system depicted by 12 dynamic

4?

TABLE OF CONTENTS

Section Page

Summary i

1 Introduction 1-1

2 Forcing Function Methodology 2-1

3 Vacuum Breaker Methodology 3-1

4 References 4-1

ii

Page 4: Attachment to NG-86-1181 - Nuclear Regulatory CommissionAttachment to NG-86-1181 C.D.I. TECH NOTE NO. 84-19 ... Figure 2-2. Schematic model of the vent system depicted by 12 dynamic

1. INTRODUCTION

The Mark I long term containment program included the construction of a

full scale test facility (FSTF) modeling a 1/16th sector of a Mark I torus and

ring header, with eight downcomers. A series of tests simulating a loss of

coolant accident (LOCA) demonstrated a chugging phenomenon occurring at the

ends of the downcomers. Continuum Dynamics, Inc. (C.D.I.) was requested to

examine the FSTF geometry and develop a vent acoustic model for predicting the

differential pressure across wetwell to drywell vacuum breakers during the

chugging phenomenon. Concurrently, C.D.I. developed a valve dynamic model

that includes the hydrodynamic effects of pressure alleviation across the

valve disc when the valve is partially open. These two efforts are summarized

in Sections 2 and 3, respectively, of this report.

These methodologies have recently been reviewed and accepted by the

Nuclear Regulatory Commission (Ref. 1). This report documents the application

of these methodologies to the Duane Arnold Energy Center Unit 1 (hereafter

referred to as Duane Arnold).

1-1

Page 5: Attachment to NG-86-1181 - Nuclear Regulatory CommissionAttachment to NG-86-1181 C.D.I. TECH NOTE NO. 84-19 ... Figure 2-2. Schematic model of the vent system depicted by 12 dynamic

2. FORCING FUNCTION METHODOLOGY

This section, of the report summarizes the methodology used to define

plant-unique wetwell to drywell Mark I vacuum breaker differential pressure

forcing functions from FSTF data. Additional details of the analysis may be

found in Refs. 2 and 3.

During the Mark I FSTF test series, wetwell to drywell vacuum breaker

actuation was observed during the chugging phase of a postulated LOCA. This

observation lead to the development of a methodology defining the plant-unique

pressure loading function acting across a vacuum breaker during the chugging

phenomenon. The methodology idealized the FSTF as an interconnection of

simple acoustic elements and modeled the chugging phenomenon as a condensation

process occurring at the exit of each downcomer across the steam water

interface. The FSTF drywell airspace pressure time history data was used with

a vent dynamic model to compute the consistent condensation source velocity

time history during chugging. The FSTF ring header pressure time history data

was then used to validate the methodology.

For plant-unique applications the most important parameter controlling the

magnitude of the vent pressure oscillations (and hence the VB forcing

function) was determined to be the ratio of the drywell volume to main vent

area. These forcing functions are specified as time histories of the

differential pressure across the valve disc, using the time segment of actual

FSTF data that generated the most conservative condensation source strength.

The steps taken in the development of the plant-unique forcing function

model are shown in Figure 2-1. Step 1 involves the development of analytical

models for: the unsteady motion in the steam vent system (characterized as

shown in Figure 2-2); the dynamics of condensation across the steam water

interface (schematically shown in Figure 2-3); and the dynamics of the

suppression pool and the wetwell airspace (idealized as shown in Figure 2

4). In the analysis the condensation source is a velocity time history

representing the transport of steam into water at the steam water interface.

2-1

Page 6: Attachment to NG-86-1181 - Nuclear Regulatory CommissionAttachment to NG-86-1181 C.D.I. TECH NOTE NO. 84-19 ... Figure 2-2. Schematic model of the vent system depicted by 12 dynamic

0

STEP

1 DEVELOP A DYNAMIC MODEL OF THE VENT SYSTEM, STEAM WATER INTERFACE AND POOL SLOSH WITH THE CONDENSATION RATE AT THE INTERFACE UNKNOWN*

2 USE MEASURED DRYWELL PRESSURE TO DETERMINE THE CONDENSATION RATE.

3 WITH THE CONDENSATION RATE DETERMINED, PREDICT UNSTEADY PRESSURES AT OTHER VENT LOCATIONS TO VALIDATE THE MODEL.

4I USE THE CONDENSATION SOURCE AT THE VENT EXIT TO DRIVE DYNAMIC MODELS OF MARK I PLANTS TO DETERMINE PLANT-UNIQUE VACUUM BREAKER FORCING FUNCTIONS.

Figure 2-1. Steps in determining plant-unique vacuum breaker forcing functions.

2-2

Page 7: Attachment to NG-86-1181 - Nuclear Regulatory CommissionAttachment to NG-86-1181 C.D.I. TECH NOTE NO. 84-19 ... Figure 2-2. Schematic model of the vent system depicted by 12 dynamic

External Breaker

Downcomers

Figure 2-2. Schematic model of the vent system depicted by 12 dynamic components.

2-3

- A-

Page 8: Attachment to NG-86-1181 - Nuclear Regulatory CommissionAttachment to NG-86-1181 C.D.I. TECH NOTE NO. 84-19 ... Figure 2-2. Schematic model of the vent system depicted by 12 dynamic

S

Steam Side

'S

w

dh Water Side

dt

Figure 2-3. Details of the steam water interface.

2-4

Page 9: Attachment to NG-86-1181 - Nuclear Regulatory CommissionAttachment to NG-86-1181 C.D.I. TECH NOTE NO. 84-19 ... Figure 2-2. Schematic model of the vent system depicted by 12 dynamic

ell Airspace

Pool

Figure 2-4. Details of the pool dynamic model around each downcomer.

2-5

0

H

Page 10: Attachment to NG-86-1181 - Nuclear Regulatory CommissionAttachment to NG-86-1181 C.D.I. TECH NOTE NO. 84-19 ... Figure 2-2. Schematic model of the vent system depicted by 12 dynamic

For the purposes of step 1, this velocity time history is assumed to be unknown. The steam dynamics in the .vent system are governed by onedimensional acoustic theory (in the configuration used here, element 3 in Figure 2-2 is nulled). Jump conditions across the steam water interface are the Rankine-Hugoniot relationships. A one-dimensional model of the

suppression pool (assigning an equal share of the wetwell airspace volume and

pool area to each downcomer) was developed to account for the compression of

the airspace with the lowering of the steam water interface in the downcomers.

For plants with external lines connecting the vacuum breakers to the main

vent and the wetwell airspace (elements 11 and 12 in Figure 2-2), additional

analysis and bounding linearized loss coefficients obtained from subscale

acoustic tests (Ref. 4) are included in the vent model to conservatively

predict the differential pressure across the VB disc. Internal vacuum

breakers are attached at the main vent intersection with the ring header, element 7 of Figure 2-2. The same condensation source velocity time history

is assumed to act at the end of each downcomer.

Step 2 involves determining the condensation source velocity time history

by using the FSTF measured drywell pressure time history data during the period of most severe chugging.

Step 3 involves validation of the model in the FSTF by using the

condensation source velocity time history determined in step 2 to predict the pressure elsewhere in the FSTF. A prediction of the ring header pressure time

history was made and compared with experimental data. To bound the negative

pressure peaks, a load factor of 1.06 was used to multiply the predicted

results to match the largest pressure data spike. To identify the origin of

the nonconservatism in the vent dynamic model, the input parameters to the

model were varied by wide margins without altering the results (Ref. 5). The

origin of the nonconservatism appears to result from the assumption of

applying an averaged condensation source of each downcomer exit. This

assumption was required because sufficient independent data sets do not exist

to determine the condensation source at the exit of each downcomer

independently.

2-6

Page 11: Attachment to NG-86-1181 - Nuclear Regulatory CommissionAttachment to NG-86-1181 C.D.I. TECH NOTE NO. 84-19 ... Figure 2-2. Schematic model of the vent system depicted by 12 dynamic

Step 4 applies the modified condensation source velocity time history to

the plant-unique vent dynamic model. The key assumption is made that the

condensation source at the end of a downcomer is plant independent. The

amount of steam condensed per chug per downcomer is assumed to be the same

between the FSTF and Mark I plants. This assumption is supported by the

observation that the condensation rate is fixed by local conditions at the

vent exit, such as steam mass flow rate, noncondensibles, and thermodynamic

conditions. These local conditions will vary only slightly between plants.

The only plant characteristics which are changed in a plant-unique

calculation are the ratio of drywell volume to main vent area and the pool

submergence. All lengths, areas and system flow and pool parameters are

retained at their FSTF values in a plant-unique calculation. Thus, gross

depressurization, controlled by drywell volume, is corrected on a plant-unique

basis, while high frequency ring out at the vent natural frequency is not

plant-unique and is essentially taken to be that of the FSTF. The plant

drywell may be treated as a capacitance or as an acoustic volume composed of

two right circular cylinders standing end to end. The acoustic volume model

results in a more conservative forcing function for Duane Arnold.

The plant characteristic parameters given in Table 2-1 were used to

compute the differential pressure time history across the vacuum breakers in

Duane Arnold. Figure 2-5 shows the resulting differential pressure time

history, without addition of the pressure resulting from the submergence head.

2-7

Page 12: Attachment to NG-86-1181 - Nuclear Regulatory CommissionAttachment to NG-86-1181 C.D.I. TECH NOTE NO. 84-19 ... Figure 2-2. Schematic model of the vent system depicted by 12 dynamic

S 0

TABLE 2-1

Plant Characteristic Parameters for Duane Arnold Energy Center Unit 1

FSTF Parameter

Main vent area/downcomer area ratio

.Main vent length

Header area/downcomer area ratio

Header length

Downcomer area

Downcomer length

Vent/pool area ratio

Plant-Specific Parameter

Drywell volume/main vent area ratio

Submergence head

Lower drywell volume length

Lower drywell volume area

Upper drywell volume length

Upper drywell volume area

775.72

3.0

50.21

1724.0

51.90

373.6

2-8

0.99

37.32 ft

1.47

15.0 ft

3.01 ft 2

10.8 ft

0.045

ft

ft water

ft

ft2

ft

ft2

Page 13: Attachment to NG-86-1181 - Nuclear Regulatory CommissionAttachment to NG-86-1181 C.D.I. TECH NOTE NO. 84-19 ... Figure 2-2. Schematic model of the vent system depicted by 12 dynamic

C-2 -1

0~

0 1 2 3 4 5 JvR TIME CSECJ

Figure 2-5. Differential pressure time history predicted across a vacuum breaker at the main vent-ring head junction in Duane Arnold. Submergence head has not been added. a) 0 - 5 seconds.

Page 14: Attachment to NG-86-1181 - Nuclear Regulatory CommissionAttachment to NG-86-1181 C.D.I. TECH NOTE NO. 84-19 ... Figure 2-2. Schematic model of the vent system depicted by 12 dynamic

ED Uf)

rk ni

DUARORY

Figure 2-5b. 5 - 10 seconds.

C)3

5 6 7 8 9 10 TIME CSEC)

Page 15: Attachment to NG-86-1181 - Nuclear Regulatory CommissionAttachment to NG-86-1181 C.D.I. TECH NOTE NO. 84-19 ... Figure 2-2. Schematic model of the vent system depicted by 12 dynamic

10

CL 1

CL -2 (f) tLi n

10 11 12 13 14 15

-vADR TIME CSEC)Figure 2-5c. 10 - 15 seconds.

Page 16: Attachment to NG-86-1181 - Nuclear Regulatory CommissionAttachment to NG-86-1181 C.D.I. TECH NOTE NO. 84-19 ... Figure 2-2. Schematic model of the vent system depicted by 12 dynamic

i,

CO CL. L

CL

DU- R

Figure 2-5d. 15 - 20 seconds.

I-'

15 16 17 TIME

18 CSEC)

19 20

Page 17: Attachment to NG-86-1181 - Nuclear Regulatory CommissionAttachment to NG-86-1181 C.D.I. TECH NOTE NO. 84-19 ... Figure 2-2. Schematic model of the vent system depicted by 12 dynamic

i

0 CC)

w/ nl

CC)DR

Figure 2-5e. 20 - 25 seconds.

20 21 22 23 TIME CSEC)

25

Page 18: Attachment to NG-86-1181 - Nuclear Regulatory CommissionAttachment to NG-86-1181 C.D.I. TECH NOTE NO. 84-19 ... Figure 2-2. Schematic model of the vent system depicted by 12 dynamic

II

ID CO CO t' LU

-1

0-0

25 26 27 28 29 30 R TIME CSECD

Figure 2-5f. 25 - 30 seconds.

Page 19: Attachment to NG-86-1181 - Nuclear Regulatory CommissionAttachment to NG-86-1181 C.D.I. TECH NOTE NO. 84-19 ... Figure 2-2. Schematic model of the vent system depicted by 12 dynamic

O 0

CL

C

CL ra_

DU)RR

Figure 2-5g. 30 - 35 seconds.

L-,

30 31 32 33 34 35 TIME CSEC)

S

0

Page 20: Attachment to NG-86-1181 - Nuclear Regulatory CommissionAttachment to NG-86-1181 C.D.I. TECH NOTE NO. 84-19 ... Figure 2-2. Schematic model of the vent system depicted by 12 dynamic

IiI

CT) cL

LL) 0

-11 LLJ

-2.

-3I 35 36 37 38 39 40

-M TIME CSECJ Figure 2-5h. 35 - 40 seconds.

Page 21: Attachment to NG-86-1181 - Nuclear Regulatory CommissionAttachment to NG-86-1181 C.D.I. TECH NOTE NO. 84-19 ... Figure 2-2. Schematic model of the vent system depicted by 12 dynamic

3. VACUUM BREAKER METHODOLOGY

This section of the report summarizes the methodology used to construct

the Mark I vacuum breaker valve dynamic model including hydrodynamic

effects. Additional details of the analysis may be found in Ref. 6.

During the Mark I shakedown tests, the vacuum breaker displacement time

history was recorded. A methodology was developed that uses the differential

pressure forcing function across the VB (computed by the vent dynamic model)

and includes the effect of torque alleviation as a consequence of fluid flow

through the opened valve. With the valve in an open position, the

differential pressure acting across the valve disc is less than the applied

pressure, because of flow across the face and around the edges of the open

disc. The purpose of the analysis is to take credit for the reduction of

static pressure across the valve disc as a consequence of flow.

Hydrodynamic torque reduction is estimated using the following procedure:

1) A linear analysis for the flow field on either side of an arbitrarily

moving disc permits the solution for the local pressure and velocity

in the vicinity of the valve disc.

2) The flow is modeled as a mathematical combination- of sources and

sinks around the circumference of the open disc, with the local

pressure obtained in step 1 used to evaluate the strength of the

sources and sinks.

3) The complete response of the valve to this resulting flow and to the

applied differential pressure obtained from the vent dynamic model is

then calculated. In all cases, the inclusion of the hydrodynamic

torque tends to reduce the actual differential pressure and hence

load acting on the valve disc.

3-1

Page 22: Attachment to NG-86-1181 - Nuclear Regulatory CommissionAttachment to NG-86-1181 C.D.I. TECH NOTE NO. 84-19 ... Figure 2-2. Schematic model of the vent system depicted by 12 dynamic

Comparison of the valve dynamic model with Mark I FSTF test data from blowdown SDA allows validation of the valve dynamic model (Ref. 6) since both

valve disc displacement and differential pressure across the valve disc were measured. Results from Ref. 6 demonstrate a conservatism of over 12% in maximum predicted impact velocity and a slope of 1.39 from a least squares fit

of the measured and predicted data to a straight line, with a Bernoulli torque

factor of 2.25 (Figure 3-1). By increasing the Bernoulli torque factor

slightly, to 2.55, the conservatism in maximum predicted impact velocity is

reduced to :5% and the least squares fit slope is reduced to 1.24 (Figure 3-2). The larger value of Bernoulli torque factor is used in the Duane Arnold

application.

The characteristics of the VB valve in Duane Arnold are given in Table 3-1. An application of the valve dynamic model with these characteristics and

the differential pressure forcing function determined in Section 2 results in

the computed valve response shown in Figure 3-3 for valve disc angle and Figure 3-4 for valve disc velocity. A summary of results appears in Table

3-2.

3-2

Page 23: Attachment to NG-86-1181 - Nuclear Regulatory CommissionAttachment to NG-86-1181 C.D.I. TECH NOTE NO. 84-19 ... Figure 2-2. Schematic model of the vent system depicted by 12 dynamic

U.. 50(

c-J

CD 0

C)40

-LJ

CD 0 200

CD

0 100

0.

0

Figure 3-1.

S1

100 200 300 400 500 600 EXPERIMENTAL UELOCITY (DEG/SEC) Comparison of experimental and predicted closing impact velocities for run SDA, Bernoulli torque factor = 2.25 (Ref. 6). The solid line is for minimized conservatism; the dashed line is the least squares linear fit.

w IA

Page 24: Attachment to NG-86-1181 - Nuclear Regulatory CommissionAttachment to NG-86-1181 C.D.I. TECH NOTE NO. 84-19 ... Figure 2-2. Schematic model of the vent system depicted by 12 dynamic

2.55

0 100 200 EXPERIMENTAL

300 400 UELOCITY

500 CDEG/SEC)

Figure 3-2. Comparison of experimental and predicted closing impact velocities for run SDA, Bernoulli torque factor = 2.55. The solid line is for minimized conservatism; the dashed line is the least squares linear fit.

4:-

w CO)

F

II

0)

U

-J w

S

600 ,

Page 25: Attachment to NG-86-1181 - Nuclear Regulatory CommissionAttachment to NG-86-1181 C.D.I. TECH NOTE NO. 84-19 ... Figure 2-2. Schematic model of the vent system depicted by 12 dynamic

TABLE 3-1

Vacuum Breaker Valve Characteristics

for Duane Arnold Energy Center Unit 1

Vacuum breaker type

System moment of inertia

System weight

System moment arm

Disc moment arm

Disc area

System rest angle

Seat angle

Body angle

Seat coefficient of restitution

Body coefficient of restitution

Magnetic latch set pressure

18" GPE

20.08

49.84

10.85

11.47

375.83

0.0

0.07

1.39

0.6

0.6

0.25

internal

in-lb-sec 2

lb

in

in

in 2

rad

rad

rad

psid

3-5

Page 26: Attachment to NG-86-1181 - Nuclear Regulatory CommissionAttachment to NG-86-1181 C.D.I. TECH NOTE NO. 84-19 ... Figure 2-2. Schematic model of the vent system depicted by 12 dynamic

rJ~LL,1

0.15

LL

a:-

0.10

0.05

0 0

DUAftUC Figure 3-3.

I A iII

I2 3 45 TIME CSEC)

Valve angle response to the differential pressure time history shown in Figure 2-5 for the vacuum breaker in Duane Arnold. a) 0 - 5 seconds.

Is

I

Page 27: Attachment to NG-86-1181 - Nuclear Regulatory CommissionAttachment to NG-86-1181 C.D.I. TECH NOTE NO. 84-19 ... Figure 2-2. Schematic model of the vent system depicted by 12 dynamic

I I I

0.15

0.10

l I1 I LATIME S CSECD

Figure 3-3b. 5 - 10 seconds.

C D

0.05

0-UAMLO 10

0-20

I I

Page 28: Attachment to NG-86-1181 - Nuclear Regulatory CommissionAttachment to NG-86-1181 C.D.I. TECH NOTE NO. 84-19 ... Figure 2-2. Schematic model of the vent system depicted by 12 dynamic

0.20

0.15

LJ

C 0.10

LL

D

0-05

0 15 20 -R TIME CSECJ Figure 3-3c. 15 - 20 seconds (no response between 10 - 15 seconds).

Page 29: Attachment to NG-86-1181 - Nuclear Regulatory CommissionAttachment to NG-86-1181 C.D.I. TECH NOTE NO. 84-19 ... Figure 2-2. Schematic model of the vent system depicted by 12 dynamic

-~ ~qi

0.20

0.150

CY

0.5

05 7-

20 2 2 2d 2 25 - TIME CSEC)Figure 3-3d. 20 - 25 seconds.

Page 30: Attachment to NG-86-1181 - Nuclear Regulatory CommissionAttachment to NG-86-1181 C.D.I. TECH NOTE NO. 84-19 ... Figure 2-2. Schematic model of the vent system depicted by 12 dynamic

0.20

0.15

C- 0.107-.

D

0.05

25 2 2? 28 29 30 -U TIME CSEC)Figure 3-3e. 25 - 30 seconds.

Page 31: Attachment to NG-86-1181 - Nuclear Regulatory CommissionAttachment to NG-86-1181 C.D.I. TECH NOTE NO. 84-19 ... Figure 2-2. Schematic model of the vent system depicted by 12 dynamic

0.20 II I *

0.150

<I LT w

0 0.10

0.05M S

0 30 31 32 33 34 35

TIME CSECDFigure 3-3f. 30 - 35 seconds (no response above 35 seconds).

Page 32: Attachment to NG-86-1181 - Nuclear Regulatory CommissionAttachment to NG-86-1181 C.D.I. TECH NOTE NO. 84-19 ... Figure 2-2. Schematic model of the vent system depicted by 12 dynamic

-r

4

2

Ii

-2

U

LU CO (E

U 0 L1 LU w

-LJ

C

1

Figure 3-4. Valve velocity response to the differential pressure time in Figure 2-5 for the vacuum breaker in Duane Arnold. a)

3 CSEC)

4 5

history shown 0 - 5 seconds.

k)

-4

S

e5 I

I2 TIME

Page 33: Attachment to NG-86-1181 - Nuclear Regulatory CommissionAttachment to NG-86-1181 C.D.I. TECH NOTE NO. 84-19 ... Figure 2-2. Schematic model of the vent system depicted by 12 dynamic

6 7 8 TIME CSECJ

Figure 3-4b. 5 - 10 seconds.

I~

U

Cy~

0

D wl <I

5Du-LkD

S

10

- I

Page 34: Attachment to NG-86-1181 - Nuclear Regulatory CommissionAttachment to NG-86-1181 C.D.I. TECH NOTE NO. 84-19 ... Figure 2-2. Schematic model of the vent system depicted by 12 dynamic

C I) w (I)

Li <I

0

-mj

DLJARLKD

I-. -Js

15 16 17 18 TIME CSEC)

Figure 3-4c. 15 - 20 seconds.

*

2019

Page 35: Attachment to NG-86-1181 - Nuclear Regulatory CommissionAttachment to NG-86-1181 C.D.I. TECH NOTE NO. 84-19 ... Figure 2-2. Schematic model of the vent system depicted by 12 dynamic

22 23 TIME CSEC)

24 25

Figure 3-4d. 20 - 25 seconds.

LA~

CY)

0

CD I

<I D

S

DU- &M

Page 36: Attachment to NG-86-1181 - Nuclear Regulatory CommissionAttachment to NG-86-1181 C.D.I. TECH NOTE NO. 84-19 ... Figure 2-2. Schematic model of the vent system depicted by 12 dynamic

U

LU (f)

O1 w

O) (

0 -J

D -LJ

DUARLKD

Figure 3-4e. 25 - 30 seconds.

tj.~

26 27 TIME

0

28 CSEC)

29 30

Page 37: Attachment to NG-86-1181 - Nuclear Regulatory CommissionAttachment to NG-86-1181 C.D.I. TECH NOTE NO. 84-19 ... Figure 2-2. Schematic model of the vent system depicted by 12 dynamic

LU

C)

-- -2 L~i <I0

.J LU -4

U o

-10 I I 30 31 32 33 34 35

TIME CSEC)Figure 3-4f. 30 - 35 seconds.

Page 38: Attachment to NG-86-1181 - Nuclear Regulatory CommissionAttachment to NG-86-1181 C.D.I. TECH NOTE NO. 84-19 ... Figure 2-2. Schematic model of the vent system depicted by 12 dynamic

TABLE 3-2

Vacuum Breaker Valve Response

for Duane Arnold Energy Center Unit 1

Maximum closing impact velocity 8.68 rad/sec

Maximum opening angle 0.156 rad

Number of closing impacts above 1 rad/sec 15

3-18

Page 39: Attachment to NG-86-1181 - Nuclear Regulatory CommissionAttachment to NG-86-1181 C.D.I. TECH NOTE NO. 84-19 ... Figure 2-2. Schematic model of the vent system depicted by 12 dynamic

4. REFERENCES

1. Safety Evaluation by the Office of Nuclear Reactor Regulation on the Acceptability of the Analytical Model for Predicting Valve Dynamics, issued by F. Eltawila, NRC, December 24, 1984.

2. "Mark I Containment Program; Mark I Wetwell to Drywell Vacuum Breaker Functional Requirements," General Electric Company Report No. NEDE 24802, April 1980.

3. "Mark I Wetwell to Drywell Vacuum Breaker Load Methodology, Revision 0," -Continuum Dynamics, Inc. Report No. 84-3, February 1984.

4. "Mark I Experimental Determination of External Line Losses for Definition of External Vacuum Breaker Loads, Revision 2," Continuum Dynamics, Inc. Report No. 81-2, September 1984.

5. "Responses to NRC Request for Additional Information on Mark I Containment Program Wetwell to Drywell Vacuum Breaker Load Methodology, Revision 0," Continuum Dynamics, Inc. Technical Note No. 84-11, October 1984.

6. "Mark I Vacuum Breaker Improved Valve Dynamic Model, Revision 0," Continuum Dynamics, Inc. Technical Note No. 82-31, August 1982.

4-1