ML20082T438
| ML20082T438 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 09/30/1991 |
| From: | Adamonis D, Witt F WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | |
| Shared Package | |
| ML19302F158 | List: |
| References | |
| WCAP-12834-S01, WCAP-12834-S1, NUDOCS 9109180246 | |
| Download: ML20082T438 (18) | |
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WCAP 12834 Supplement 1 ADDITIONAL INFORhtATION IN SUPPORT OF ELINilNATING PRESSURIZER SURGE LINE RUPTURE FROh! TliE STRUCTURAL DESIGN BASIS FOR JOSEPli h1. FARLEY PLANT UNITS 1 AND 2 September 1991 S. A. SWAhtY D. C. BliOWhilCK Y.S. LEE Verified by: .
. ([ J FQ. Witt, Fellow Engineer StFuctural hiechanics Technology
/0 p) ') # J .
Approved by _/#. -
N'8 D. C. Adamonis, N1anager Structural hiechanics Technology w
WESTINGilOUSE ELECTRIC CORPORATION i Ninlear and Advanced Technology Division P.O. Bos 2728 Pittsburgh, Pennwivania 15230 2728 l c 1991 Westinghouse Electric Corp.
WPF0646/090391:10
I r
l TABLE OF CONTENTS SECTION TITLE PAGE
1.0 INTRODUCTION
11 2.0 RESPONSE TO Tile REQUEST FOR 21 ADDITIONAL INFORMATION
3.0 REFERENCES
31 APPENDIX A - THE NRC REQUEST FOR ADDITIONAL A.1 INFORMATION WPF0646/090301:10
.-_..._ _.~._. .
l l
SECTION 1.0 l
- INTRODUCTION l Alabama Power Company contracted with Westhighouse Electric Corporation to develop a leak before break analysis for the Farley Units 1 and 2 pressurizer surge lines. The leak.
before break analysis is documented in Westinghouse Proprietary Class 7. Report WCAP.
12835 (Reference 1.1). WCAP 12834 is the associated Westinghouse Class 3 report. During !
the regulatory review process the Nuclear Regulatory Commission (NRC) issued a Request for AdditionalInformatica concerning the pressurizer surge line leak before break analysis for Joseph M. Farley nuclear plant Units 1 and 2 (Appendix A). This report addresses the NRC requests.
WPF0646/090391:10 1.; '
1 i
SECTION 2.0' i'
+.
RESPONSE TO TiiE REQUEST FOR ADDITIONAL INFORMNilON Recuest I CriticaLElaw sire Predicti.on 1.1 Provide the pressure for each of the fifteen limit moment flaw length curves shown in Figures 5 6 to 5 21. Based on the data supplied, the staff is unable to reproduce these curves.
)
1.2 Provide numerical values for all parameters appearing in Eq. (51) and (5 2) for generating the curve shown in Figure 5 6.
1.3 Provide the temperature range at the critical pipe location for each case shown in Figures 5 6 to 5 21. Justify the use of yield and ultimate stresses corresponding to the temperature closer to the low end of the temperature range for some cases ,
(especially those related to Cases F and G).
Resoonse:
1.1 The requested pressures are provided below:
1 Figure 5 6 P = 2250 psi Figure 5 7 P = 2250 psi Figure 5 8 P = 440 psi Figure 5 9 P = 440 psi Figure 510 - P = 2250 psi Figure 511 P = 2250 psi Figure 5-12 P = 440 psi Figure 513 - P = 440 psi Figure 514 P = 2250 psi Figure 515 P = 2250 psi Figure 516 P = 440 psi WPF0646/090.591:10 2-I.
-~ _ _ ._ _. . _ . _ _ . . . _ . _ _ . _ . . _ . . - _ . _ . _ . _ _ ~ . . _ _ , _ _ - . _ . .
Figure 517 P = 440 psi Figure 5 18 P = 2250 psi - >
Figure 519 P = 2250 psi Figure 5 20 P = 440 psi Figure 5 21 P = 440 psi r ,
Note that the total applied axial force = n R2,P + force from other loading conditions. The total applied axial force is provided in each of the Figures 5 6 ;
through 5 21.
1.2 A step by step procedure for generating Figure 5 6 is given below. The equations 51 and 5 2 are as follows: -
(51)
_ac.e (52)
Numerical values for all the parameters are provided below. Note that Ma is the dependent variable while a (semi crack angle) is the independent variable. # is an interim derived quantity.
Or = 51.825 ksi R,,, = 6.3745 in t = 1.251 in
- P = 2250 psi
- F = 26.13 kips R, = 5.749 in
)
These parameters should be amplified by the Z factor for the associated weld.
(n R,2 P + F) = Total applied axial force = 259.753 kips WPF0646/000391:10 22
Since the weld associated withFigure 5 6 is an SMAW weld, the corresponding Z
, factor is found to be 1.30. For various postulated crack lengths, the allowable moments Ma are calculated using equations 51 and 5 2 as shown below, l
crack Allowable kanoth a B p.gndina Mgagnt
- a,c.e The applied bending moment at location 2203 for case D is 2577 in kips. Thus Z x
, (M,ppi,a) = 3350 in kips. The critical flaw size is found to be 13,16 by interpolating between the moment for 12.51 in and 13.761 in. The above results when plotted yield Figure 5 6.
1.3 The temperatures associated with Figures 5-6 through 5 21 are provided below, in addition, justification for the temperatures associated with the applicable cases is also provided below:
Applicable Physical o o, Temperature Figure # Case Location (ks'i) (ksi) (*F)
_a.c.e o-O I
WPF0646/083091: 10 2-3 ~
- + <,w- ,- ,a v
9 y Figure # Applicable Physical o, o, Temperature Case Location (ksi) (ksi) (
- F)
_a.c.e t
l t
The temperatures provided abos e essentially follow the definitions of cases described in Table 4 2 of WCAP.12S35. The following information is reproduced here from
- that Table.
CASE D: Tha is the faulted operating case at an llCS temperature of 653'F consisting of the absolute sum (every component load is taken as positive) of P, DW, TH and SSE.
. . -a,c.e Clearly, based on the above defmitions all the cases identified as D & E are associated with temperature of 6f.VF and the material properties are taken at that temperature. The temperatures for Case F is <Jetermined as follo vs: [
WPF0646/090391:10 2.a
.__ . _ _ . . . - . _ . . _ _ _ _ _ _ _ __ _ __ _ _.--. _ _ _._ _ -. _ -__._.-._ _.~.
i i
i i
i I
jau Reauest 2: l_enk Rate Calculation !
. 2.1 Provide an assessment of the accuracy of the calculated pressure drop AP:, for choked flow based on Fauske's method.
Resnonse:
The basic premise pertaining to the leak rate calculations as applied to the leak before.
break evaluations is to obtain realistic estimates of leak rates through postulated through ,
wall cracks and then apply a factor of 10 between the calculated leak rate and the leak ,
detection capability of the plant.
[
L
, WPF0646/090391:10 25
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I f
)..a Reauest 3 Fatigue Crack Growth Analysis !
3.1 The da/dn equation ured in Westinghouse report WCAP.12835, submitted by your April 26,1991 letter, is as follows: '
da/dn = 2.42 x 10 40 SAK" <
Where S = 1.0 for R = 0; S = 1 + 1.8R for 0 < R <.8; and S =.43.35 + 57.97R for R >.8.
The parameter R is defined as: R = imK ,n/Kim ,,
. A different fctigue crack growth formula for stainless steel is given in Westinghouse report WCAP.12825, " Technical Justification for Eliminating Large Primary Loop Pipe Rupture as the Structural Design Basis for the Joseph M. Farley Units 1 and _ ,
2 Nuclear Power Plants."- WCAP 12825 was submitted by your letter dated January 28,1991. In WCAP.i2825, the equation takes the following form:
d da/dn = 5.4 x10-in g ,4
.- where K,y = Km ,, (1.R) "
R = Km,,,/Km,,
T WPF0646/090391:10 %
l Explain your rationale in selecting the former equation as opposed to the latter one
.- in the current fatigue crack analysis. If the latter one was used instead, what will the results be?
Resoonse:
s The fatigue crack growth analysis of the pressurizer surge line was performed using the latest fatigue crcck growth law for stainless steels which became available in 1989 (Reference 3.1). Specifically, the following eqiiation for stainless steel fatigue crack i growth law represents the latest ASME Section XI recommendation and is l appropriate for the detailed fatigue crack growth analysis of the surge :,ne reported !
in WCAP 12835 submitted on April 26,1991.
b =2.42x10'NSAK)8 dn i
Where 5 = 1.0 for R = 0; S = l + 1.8R for 0< R < 0.8:
and S = -43.35 + 57.97R for R > 0.8 The parameter R is defined as R = Kim,n/K i ,m I l 1
3 leu ;
}
t WPF0646/090391:10 2-7
I 4 .
I Specifically, the crack growth law was defined as-
$ S.4x10 d2Aj)'inchestcycle dn where K n. " Km,, (1 Rf 8 e
R u K,,,,,/ K,,,,,
I i
f t
1
. Ja.C t 4
3
.WPF004ti/090391:10- 2.x l -
l Summary: i 1
Detailed FCG analysk of the pressurizer surge line was performed and documented in WCAP 12835 using the fatigue crack growth law of Reference 3.1. For current applications it is appropriate to use this law since it represents the latest information and conforms to the recommendation of AShiE section XI.
f 1 I
i i
). c l l
i t
i
[
a WPF0646/090391:10 ..o
. m _, ,
.o .
Table 2-1 Comparison of Aquitance II Experimental Data with Calculated Values t
Crack Geometry :
and Conditions Crack la Plate Crack in Tube Crack in Tube I -- a,c,e ;
t I
t i
t P
i t
f i
i I
t t
t i
t I
< - . _ t
- +
i WI'I:Or 46/US3091:10 2-10 I
. .. . . . - . . ,-. . - - . . . . , .. - ., . - - - . . . _ - - _ - - _ - - ____l_
, , i i
SECTION 3.0 !
- REFERENCE!,
1.1 WCAP-12835, " Technical Justification for Eliminating Pressurizer Surge Line i Rupture from the Structural Design Basis for Farley Units 1 and 2," April,1991 Westinghouse Proprietary Class 2.
{
2.1 [
pu .
3.1 - . ASME Code Section XI, Appendix C,1989 Edition. ,
l 3.2 Bamford, W,11.," Fatigue Crack Growth of Stainless Steel Piping in a Pressurized
)
Water Reactor Environment,"Trans. ASME Journal of Pressure VesselTechnology, -
Vol.101, Feb.1979.
s.
L l
L l WPF0646/090391:10. ti L -
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APPENDIX A
. THE NRC REQUEST FOR ADDITIONAL INFORMATION After reviewing WCAP 12835, the NRC submitted to Alabama Power Company a Request for Additional Information. The request is reproduced on the followirig page.
l WPF0646/090391:10 .s . i
REOUEST FOR ADDITIONAL INFORMATION
. PRESSURIUR SURGE LINE LEAK-BEFORE BILEAK ANALYSIS JOSEPH M. FARI EY NUCLE AR PLANT. UNITS 1 AND 2 e
Critical Flaw Size Prediction 1.1 Provide the pressure for each of the fifteen limit moment-tlaw 1:ngth curves shown in Figures 5-6 to 5 21. Based on the data supplied, the staff !s unable to reproduce these curves.
1.2 Provide numerical values for all parameters appearing in Eq. (51) and (5 2) for generating the curve shown in Figure 5 6, 1.3 Provide the temperature range at the critical pipe location for each case shown in 3 Figures 5 6 to 5 21. Justify the use of yield and ultimate stresses corresponding to the temperature closer to the low end of the temperature range for some cases (especially those related to Cases F and 9.
Leak Rate Calculation 2.1 Provide an assessment of the accuracy of the calculated pressure drop AP:, for choked flow based on Fauske's method.
Fatigue Crack Growth Analysis 3.1 The da/dn equation used in Westinghouse report WCAP 12835, submitted by your April 26,1991, letter, is as follows:
da/dn = 2.42 x 10' SAK 33 Where S = 1.0 for R = 0; S = 1 + 1.8R for 0 < R c .8; and S = 43.35 + 57.97R for R >.8.
The parameter R is defined as: R=K,ma,/K,,,,,
WPF0646/090391:10 a.2
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A different fatigue crack growth formula for stainless steel is given in Westinghouse
, report WCAP 12825, ' Technical Justification for Eliminating Large Primary leop Pipe Rupture as the Structural Design Basis for the Joseph M. Farley Units 1 and 2 Nuclear Power Plants." WCAP 12825 was submitted by your letter dated January 28, 1991.- In WCAP 12825, the equation takes the following form:
i da/dn = 5.4x10'" Ajj'
- where Ke rt " Km,, (1 R) 3 R = K,io/Km,,
Explain your rationale in selecting the former equations as opposed to the latter one '
in the current fut.igue crack analysis. If the latter one was used instead, what will the
, results be?
s WTF0646/090391:10 a.3
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