ML20245H627

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Suppl 1 to Addl Info in Support of Evaluation of Thermal Stratification for Beaver Valley Unit 2 Pressurizer Surge Line
ML20245H627
Person / Time
Site: Beaver Valley
Issue date: 02/28/1989
From: Antaki G, Coslow B, Palusamy S
WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:
Shared Package
ML20011C570 List:
References
WCAP-12094-S01, WCAP-12094-S1, NUDOCS 8903020440
Download: ML20245H627 (9)


Text

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Westinghouse Class 3 WCAP-12094 Supplement 1 ADDITIONAL INFORMATION IN SUPPORT OF THE EVALUATION OF THERMAL STRATIFICATION FOR THE BEAVER VALLEY UNIT 2 PRESSURIZER SURGE LINE l

l F. J. Witt February 1989 Verified by:

B.Jfoslow Approved by:

W. d ' Approved by:

/~ u m 5m G. A. Antaki, MprJ6ger

/ S'. 5. Palusamyg Manager Systems Struct #al Analysis Structural Materials Engineering WESTINGHOUSE ELECTRIC CORPORATION Nuclear and Advanced Technology Division P.O. Box 2728 Pittsburgh, Pennsylvania 15230-2728 m.-cuses to i'i f

8903020440 890224 PDR ADOCK 05000412 P

PDR L

1

1.0 INTRODUCTION

In WCAP-12093 (reference 1) the surge line of the Beaver Valley Unit 2 nuclear plant was evaluated for thermal stratification. The major conclusion was that thermal stratification has limited impact on the integrity of the pressurizer surge line of the Beaver Valley Unit 2 nuclear power plant and that the forty year design life is not impacted.

The reevaluation of leak-before-break for the surge line demonstrated large margins for all the stratification scenarios considered. Of specific interest was the faulted condition, case F, representing a [

Ja,c.e Duquesne Light Company requested that, in the leak-Defore-break analyses, additional calculations be provided for the [

]0 and for stable flaw

~

sizes for information purposes. This additional information is provided below. A familiarity with section 5.0 of reference 1 is assumed in the discussion.

2.0 ADDITIONAL INFORMATION The additional calculations for [

Ja,c.e were very conservatively made by assuming the [

Ja c.e The loads for this condition at the critical location Node 171 are given in table 1(a). This loading case is designated case FF. The corresponding leak-before-break cases are designated A/FF and B/FF. The temperatures and flaw sizes considered in the leak-before-break analyses are given in table 1(b). The J integral results are given in table 1(c). Large margins are still seen to exist even for this extreme condition.

Additional margins on flaw sizes were established by plotting the applied J versus crack length up to the maximum J value of [

Ja,c.e for the mi,-erim io 1

.g five LBB cases reported in reference 1, replacing cases A/F and B/F with A/FF and B/FF, respectively. The results are plotted in figures 1 through 4.

Much larger marging than the factor of 2 are demonstrated.

References:

1.

R. L. Brice-Nash et al., Evaluation of Thermal Stratification for the Beaver Valley Unit 2 Pressurizer Surge Line, WCAP-12093, December 1988

'i (Westinghouse Proprietary Class 2).

C' 4

e t

i Fe Ks?,-cr1we 90 2

Table 1.

Summary of Results Table 1(a) Loads and Stresses For Case FF Force Stress Moment Stress Total Node F (1bs) op (psi)

N-(in-lbs)'

og(psi) Stress (psi)

- a,c.e 171

. Table 1(b) Temperature and Leakage Flaw Sizes for LBB Cases A/FF and B/FF at Node 171 Temperature (*F)

Leakage Case Leak Rate Stability Flaw (in.)

a,c.e A/FF B/FF Table 1(c) J-Integral Results for LBB Cases A/FF and B/FF Criteria Crack J

J O

Ic max Length app Case (in-lb/in )

mat (in-lb/in)

(in)

(in-lb/in )

T,pp 2

T 2

2

_ a,c.e A/FF B/FF N.A. - not applicable, J,pp < JIc o

m,-mu in 3

,I 4

o a,c.e Figure 1.

J,pp Versus Flaw Size For Case A/D, Node 196 me, im to 4

'f O

a,c.e l

Figure 2.

J,pp Versus Flaw Size For Case B/E, Node 196 5

J

9 ;..

9 a,c e Figure 3.

J Versus Flaw Size For Cases A/FF and B/FF, Node 171 i

6

. 1,

\\

p

l:

l l

t 1

(;

s a,c.e

/:

(>

t)

/

Figure 4.

J Versus Flaw Size For Case C/G, Node 171 mov.-onm u 7

s