ML20213F473
| ML20213F473 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 11/07/1986 |
| From: | Shepard J, Yoon K BABCOCK & WILCOX CO. |
| To: | |
| Shared Package | |
| ML20213F464 | List: |
| References | |
| 32-1165797, 32-1165797--R, 32-1165797-00, 32-1165797-00-R00, NUDOCS 8611140222 | |
| Download: ML20213F473 (22) | |
Text
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l Nb3 DOCUMENT
SUMMARY
SHEET mcoennett comm DOCUMENT IDENTIFIEp 32-1165797-00 TITLF Fracture Mechanics Analysis of N40-1 A Ptrup Case Indication PREPARID BY:
REVIEWED BY:
J. F. Shepard K. K. Yoon nur sur 0F $ Lum 3 SIGNATURr <K. W S;GNAMF
//,hb TITttSuperv sory E ineer om HITf 86_
Trrtr Advisory Ena eer
---oATE COST CENTEp 310 REF. PAGE(s)
I2 REV1 ER 0 CE PURPOSE AND
SUMMARY
OF RESULTS:
To perform a fracture mechanics evaluation of the indication found in ANO-1 reactor coolant pump case, according to Appendix A of the ASME Boiler and
'\\
Pressure Vessel Code,Section XI.
i Pertinent Co_nic_usions The flaw indication found in the vertical weld in the ptsnp case volute areas is found acceptable according to IWB-3512 criteria of Section XI, ASME Boilers and Pressure Vessel code.
THE FOLLOWING COMPUTER CODES HAVE BEEN USED IN THIS DOCUMENT:
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TABLE OF C0KTENTS 1.
FLAW DESCRIPTION 2.
MATERIAL PROPERTIES 3.
LOMS/ STRESSES 3.1 Normal and Upset Condition 3.2 Emergency and Faulted Condition 4.
FRACTURE MECHANICS EVALUATION 4.1 Stress Intensity Factor Calculation-4.2 Fatigue Flaw Growth Analysis 4.3 Safety Factor Assessment S.
CONCLUSIONS 6.
REFERENCES Appendix A.
Flaw Description
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GENERAL CALCULATIONS e uco.nnou comm 32-115 797-00 Nuclear Power Division occ. LD FRACTURE MECHANICS ANALYSIS OF ANO-1 "A" PUMP CASE INDICATION 1.
FLAW DESCRIPTION During the ANO-1 pump inspection, a flaw indication was found at the volute part of the reactor coolant pump A caso as shown in Figures 1 and 2 (Appendix A).
This indication shows one two inch long flaw and a number of small slag inclusion type flaws along the vertical weld seam.
The maximum depth of any of these flaw was determined to be 1.1 inch.
For the purpose of this analysis, this indication was conservatively represented by one single semi-elliptical ' surface flaw of 1.1 inch deep and 5.66 inch long.
2.
MATERIAL PROPERTIES The ANO-1 pump case was fabricated from ASTM A351-69, typo CF8M. Toughness and mechanical proporties for similar cast stainless steel and weld materials are available from reforonco 4.
The primary interest is in the weld material which contains this indication.
Typo CF8A base metal has slightly higher tensile strengths than type CF8M, however, Charpy values at room temperaturo are ap proximately equal.
For this evaluation, it is l
considered reasonable to assume that fracture toughness properties for type l
CF8M and CF8A weldments are equivalent.
i Touchness of Wold Material CF8A Stainless Steel Woldmont 2 3/8-inch thick compound-butt l
Filler metal - ER308L, E308L l
2 JIC = 1171 in-lb/in l
KJC =
179 ksifin.
Fatigue Flaw Growth Rato I
P rese ntly a fatigue crack growth rato equation for carbon steel is in l
Appendix A to Section XI, ASME B&PV code. The Metal Properties Council l
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proposed a unifiod fatiguo crack growth rate oquation for austonitic material including CF6k (referenco 1) and it is under the ASiE committee rovlew for potential inclusion into Appondix A of Soction XI.
The proposed equation is h = 0 F S (AK )
y where C - coef ficie nt, function of temperature (Figure 3)
F - frequency dependancy factor, unity for this application S
R-ratio correction factor S
- 1.0 R<0 S = 1.0 + 1.8 R 0<R<0.79 S = -43.35 t 57.97 R 0.79<R<1.0 0
At 570 F and R= 0, the above crack growth rate equation becomes as shown bel ow,
-10 l
= 1.8 x10
%K )
y whero da/dN is in inches / cyclo and KI in ksiflII.
It is noted that all dif ferorit types of' stainloss stool can be reprocented by a single fatiguo crack growth equation.
The fatigue data for CF8M in this reference is the samn MPC data reportod in roference 2.
3.
LOADS / STRESSES The applicablo stressos at tho flaw location are provided by reference 3.
Sinco IWB-3612 critoria has two separate classes, the stresses are discussed under the following categories.
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3.1 Normal and Upset Condition From reference 3, it was shown that the flaw lccation is in the area of View 3-5 in Figure 4.
Maxf r. urn stressos along olet.ent numbers 4176 through 4181 are as tabulated in Tablo 1.
The higiest tensile stresses are in the case of combined loading of rapfd cooldown transient load. Internal pressure, deadweight, preload and 15% thern.a1 expansion load. Tho highest compressive strossos are in combined load of hoatup, internal pressure, deadwight, proload and 15% thermal expansion caso.
f Tabla 1.
Rapid Cooldown Transient 5trosses t
Inside surface 15.9 ksi Midsurfaco 12.6 ksi Outside surfaco 9.4 ksi Tablo 2.
Heatup Transient Strossos l
Inside surface
-19.0 ksi Midsurface
-14.1 ksi
.Outside surface
-9.1 ksi l
From Table 1, the membrano stress is 12.6 ksi and the bonding stress is 3.3 ksi.
Combination of this c~ooldown and heatup transient stress forms the maj or cyclic loads which should be considorod for fatigue flaw g rowth-analysis.
The fluctuating stress rango is from -19.0 ksi to 15.9 ksi at tho insido surface of the caso, giving total span of 34.9 ksi.
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l 3.2 Emergoney and Faultod Conditions Maximum stresses for each omorgency and faulted conditions were extracted in reforenco 3 and combinod with the pressure stresses as shown in Table 3.
The results indicate that the maximum stresses for the errwrgency and faulted condition cases are only slightly higher than those for the normal and upset conditions.
Table 3.
Maximum Stresses for Emergency and Faulted Conditions Inside surface 17.5 ksi Mid-surfaco 15.0 ksi y
Outsido surfaco
.6 ksi 4.
FRACTURE MECHANICS EVALUATION l
4.1 Stress Intensity Factor Calculation From Appendix A, following input infornation it availa'ble.
Wall Thickness, t = 2.6 inches Semi-0111ptical surface flaw Flaw Depth, a=
1.1 in.
Flaw Length, /= 5.66 in.
a/l = 0.19
//a=
5.1.
i From Appendix A,Section XI, ASME B&PV code, l
a/t =
1.1/2.6 0.42 Mm =
1.30 l
Mb =
0.65 For normal and upset conditions, Membrano Stross, SIGm =
12.6 ksi Bending Stress, SIGb =
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calculating the stress intensity factor rango, twico tho tensilo stress rango will be used to be conservativo.
Since tho stress intensity factor for nortnal and upset canditions is 31.8 ksi rTn' from the procoding section, twico this value will be taken as tho 4KI rant,0.
AKI = 63.6 ksl {lT da/dN= 0.000160 N=
240 hoatup and cooldown cycles Assuming a constant dKI since the flaw grcath rate is so small, the amount of crack growth is oa*
0.039 inch.
- Honco, Initial crack depth =
1.1 inch and Final crack dopth 1.139 inch.
=
Since the amount of fl aw growth is very small (3.67, of the initial flaw depth) for tho entire design life, this is acceptable.
4.3 Safoty Factor Assessment for normal and upsot condition, IWB-3612 requires that KIa/KI > 6 = 3.16 t
Sinco this material is very ductile (33T, elongation - referonco 4), it can be assumed that Kla is equivalent to KIc at the operating ten >porature and the following ratio will be assessed.
KIc/KI " 179/3 2.4 - 5.5 >E0 - 3.16.
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Thoroforo, this flaw is accoptablo.
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Q-1.17 KI * (SIGmMm+SICmMb){1ta/Q (1) 31.8 ksiiiii~
=
This stress intensity factor value will be used in tho f attgue crack growth analysis in the following section. The resulting final flaw sizo is, af - 1.139 inch.
Substituting this flaw depth into tho above equation 1, 32.4 ksi 6......... Normal and upset concitionf.
K1 =
I For omorgoncy and faulted conditions, SIGm = 15.0 ksi SIGb = 2.5 ksi 0=
1.14 and the sarco Mm and Mb corrections factors yields, KI = 37.5 ksi k.......Faul ted condition.
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4.2 Fatiguo Flaw Growth Analysis Fatiguo crack growth rato is given in section 2 as da/dN = 1.8x10-10(4KI)3.3 j
whoro da/dN is in inch / cycle and AKI in kst$
The fluctuating aross l
range is 34.9 ksi, however, only 15.9 ksi is tensile.
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n-For the omorger.cy and faulted condtion, IWB-3612 reut res that i
KIc/KI > T = 1.414 i
and sinco KI for tho faulted condition is 37.4 ksi in, KIc. KI - 179/37.5 4.8
>1. 414.
=
Therefore, this flaw is acceptable for the erneroency and faulted conditions, i
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CO?CLUSIONS The results of this fracture mechanics analysis using a very conservative flaw size show that the finw indication found in the voluto wold of the ANO-.
1 A pump case is acceptable for the continued operatton no por 11/8-3612 procoduro.
The results *re sumurized in the following table.
Stress Intensity Factor Load Cat.
Max. Stress KI KIC/KI Codo Critorion Chock A&B
& = 12.6 (P ' 3.3 32.4 5.5 3.16 OK o
C&D gg= 15.0 fg 2.5 37.5 4.8 1,41 OK f
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Edigno Elaw Growth No.
Initial Flaw Final Flaw Cycles Size Size 240 1.1 inch 1.139 in t
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6.
REFEREllCES 1.
L. A. Janos and D.
P. Jones, "Fatiguo Crack Growth Corrolations for Austenitic Stainl++ss Stool in Ai r,"
ASf'E PVP Vol. 99, November 1985.
2 E.
I. Landerman and W.
H.
Bamford, " Fracture Toughness and FAtiguo Characteristics of Contrifugally Cast Type 316 Stainless Steel Pipe after Simulated Thermal Service Conditions," ASME MPC-8, 1978.
3.
B&W Docurront 32-1165602-01, "ANO-1 Pump Caco Stross," 11/07/06.
4.
M. G. Vassilaros et al., "Stainioss Steel Compact Data," NRC Piping Matorial Program at David Taylor Naval Ship Roccarch ano Developmenf Center, presented to ASME Section XI, -Task Group on Pipe Flak Evaluation, San Antonio, June 1984.
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P ARKANSAG POWEER & LIGHT COMPANY Arkansas Nuclear One P. O. Box 608 Russellville, Arkansas 72801 November 5, 1986
//gy g g 1986 ANO 86-14311 Mr. Bill Jones ty, E /c,p' Babcock & Wilcox Co.
Nuclear Power Division 3315 Old Forest Rd.
P.O. Box 10935 Lynchburg, Virginia 24506-0935
SUBJECT:
Arkansas Nuclear One - Unit Ons Revi_ sed Request For RCP Flaw Analysis
REFERENCE:
ANO-86 13461 Dated October 20, 1985
{
Dear Mr. Jones:
The purpose of this letter is to ravise data transmitted to you by the referenced letter and to request additional analyses of both the ANO 1 "A" and "B" reactor coolant pomp casings.
In the "A" pump refined measuremants now indicate that the wall thick-ness in the area of interest is approximately 2.6 inches. Other dimensions are unchanged.
In the "B" pump a radiographic indication which cay be slag or incomplete fusion exists in the same vertical weld as in "A".
The indication is approximately 1.5 inches in length and begins approximately 1.5 inches No infor-below the pump horizontal centerline and continues downward.
mation is available regarding depth or throughws11 extent for the indication. The pump casing is approximately I ; inches thick in this area by UT measurement.
We request that the "A" analysis be repeated ut ng the above revised For the B" RCP we request that an ana13'is be performed assuming data.
that the indication extends from OD to 10 and v*ich would show accept-ability for one cycle of operation.
As before, please contact me if you have any questions about this request.
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f AAKANSAS PCM/EA & UGHT COMPANY Arkansas Nuclear One P. o. Box 608 Aussellville, Arkansas 72801 October 20, 1986 ANO 86 13461 Mr. Bill Jones Babcock & Wilcox co.
Nuclear Power Division 3315 Old Forest Rd.
P. o. Box 10935 1110 cod Fellows Road 1,ynchburg, Virginia 24506-0935 Deer Hr. Jones This letter transmits to you the detailed location and size of a radiographic indication in the ANO-1 "A" reactor ecolant pe p casing. This indication has been the subject of numerous telephone conversations between us this weekend.
The indication is descrlhed as a series of ' slag inclusions having an effective length per ASME Section XI criteria of 5.66 inches. The indication is located in the vertical veld which ties together the two scroll velds of the pump casing, and begins at the intersection of the upper scroll and vertical welds. A sketch of the radiographic indlestions is attached for your use.
Radiographic parallax techniques indicate that the top of the indicatten is at least 1.5 inches below the outside surface of the weld. Ultrasonic measurement l
indicates a well thickness of approxiestely 2.2 inches in this area. No measurement of throughwall extent of the indication has been made.
We request that an analysis be perfomed per A5ME section XI to determine the acceptability of operatiin with this defect present,for the balance of plant life. If you have any questions about this request or about the data contained herein, please do not hesitate to call me at (501) '164-3118.
A Since, rely f
s Alexander B. McGregor Attachment ABM/ cmc cci I. C. Ewing
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