ML20080K727
| ML20080K727 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 12/15/1983 |
| From: | Ely J NORTHEAST UTILITIES SERVICE CO. |
| To: | |
| Shared Package | |
| ML20080K715 | List: |
| References | |
| 82-196-247GP, PA-82-196, PA-82-196-R, PA-82-196-R00, TAC-51997, NUDOCS 8402160117 | |
| Download: ML20080K727 (16) | |
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PAGE 1 OF k g
NORTHEAST UTILITIES SERVICE COMPANY NUCLEAR ENGINEERING AND OPERATIONS GROUP GENERATION MECHANICAL ENGINEERING ASME SECTION lil CLASS 2 AND 3 AND ANSI 831.1.0 PIPING ANALYSIS PROJECT AS$!GNMENT: PA 82-196 CALCULATION NUMBER:
82-196-247GP PLANT:
MILLSTONE UNIT NO. 2 TITLE:
Ultrasonic Indications in Steam
+
Generator Top Head Dome Weld l
QA CATEGORY 1 REVISION 0 j
DATE
(( %[
[
DATE MA/[d.
Yfs/py PREPARED BY REVIEWED gY
'f.
11/23/83 J. F. Ely f
/
AP OVED DATE REYlEw METHOD Full MM (2./Z3/13 REVISION 1 PREPARED BY DATL REVIEWED BY DATE REYlEW METHOD APPROVED BY DATE l
REVISION 2 l
PREFAEED BY DATE REVIEWED BY DATE l
REVIEW METHOD APPROVED BY DATE l
8402160117 831230 PDR ADOCK 05000336 G
cosas7 sao NORTHEAST UTILITIES SERVICE COMPANY sdenct Ultrasonic Indications in Steam SY Is b #e' RATE 12/15/83
(
Generator Top Head Dome Weld -*
CHr.0. SY M[
- DATE ## I Millstone Unit No. 2 cate,no,82-M - N P O
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M suggy no, op TAsts or corrrwTs Page Title i
Table of Contents 11 t
Background
1 Objective 1
Summary and Conclusions 1
Analysis 1
References 8
h
NORTHEAST UTILITIES SERVICE COMPANY go, wo suancy Ultrasonic Indications in Steaa cv 6"f 84 eave 12/15/83 J
Generator Top Head Dome Weld --
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BACxcROUND An ultrasonic indication was discovered in the top head dome weld, SG1-TES-2 during the 1982 Millstone Unit II in-service inspection. The indication was sized and evaluated to the criteria of the ASME Boiler and Pressure vessel Code,Section XI through the Winter 1980 Addenda. The indication was smaller than the allowable flaw sizes in that document. Bowever, geometry and surface preparation limited the accuracy of that examination and an internal commitment to reinspect that area was made. The 1983 examination has resulted in the discovery j
of more extensive indications which must be evaluated.
OBJECTIVE The top head done indications will be evaluated by the methods of Appendix A of Section XI of the B&PV Code and compared to the criteria of Section XI IwB 3600, through the 1980 Winter Addenda.
SUMMARY
AND CONCLUSION 1.
The indications exceed the size of allowable indications as defined in IwB-3500.
2.
Evaluation of the indications shows that they are acceptable to the end of service lifetime of the component.
3.
A pressure-temperature limit curve for noneal and test
[
conditions has been developed and must be used for continued operation of the ccaponent.
f~
ANALYSIS Description The steam generator is a Combustion Engineering Series 67 vertical U-tube design. The area of interest, welds SG-1-THS-2 and SG-2-THS-2, is the juncture of a 5.o" thick SA 533GrB C1.1 plate and a 3.5" thick SA 516Gr70 plate which have been formed into a 116.25" hemispherical done. The details of the area are shown on Combustion Engineering drawing E-233-643 Rev. o4. A sketch is shown in Figure 1.
Flaw Location k
The indications, as defined by NUSCO Examination Record
{
NU-UT-001, are on the SA 533GrB plate side of the weld-base metal interface. Multiple indications as shown in Figure 2, extend around the welds. For analysis, P
the indication will be conservatively treated as a continuous circumferential flaw. All through wall dimensions have been " collapsed" into one cross-section j
l
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and will be treated as a flaw of 1-b/16" depth, perpendicular to the meridional stress direction. The flaw is located 1-3/16" from the inner surface of the done and the wall thickness at the flaw location is 4-1/16".
This data is shown in Figures 3 and 4.
As defined in Fig. IWA-3320-1 of the Winter 1980 Addenda of the ASME B&PV Code Section XI, the appropriate parameters are:
1.
Perpendicular to the Meridional Plane:
2a = 1-5/16" a = 0.656" l = 270.0" t = 4-1/16" a/t = 0.161 S = 1-3/16" y
a/1 = 0.0074 S = 1-9/16" O
S>a Indication is subsurface 2.
Perpendicular to the Circumferential Direction:
2a = 1-5/16" a = 0.656" l = 15/16" t = 4-1/16" I
a/t = 0.161 S = 1-3/16" a/l = 0.699 S = 1-9/16" O
S>a subsurface Loads The flaw analysis is performed for the normal, upset, emergency, and test conditions as defined in the original steam generator equipment specification, Ref.1.
It is assumed for the purposes of the flaw growth analysis l
that the distribution of transients is in order of their
- severity, i.e.,
all ten hydrostatic tests are done then l
all leak tests, etc.
All design transients for the plant 40-year life will be used.
i The individual transients considared are given in Table 1.
The transients are grouped into 11 loading cycles as shown in Table 2.
This grouping provides the maximum values of stress range for a conservative flaw growth analysis and the order of the transients does not affect flaw growth.
Flaw Crowth Analysis The stress intensity factor is determined from section XI Appendix A equation A-3300-1.
________.___m_
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o, Kg = 0, Prt. /n Ja/Q + o M
"/E g b For transient cycle A (from Table 2): o from ref. 1 pg. A-67.
g KIain = 0 P=0 K,,, = 1.25(17.21) Mm /n J.656/Q + 1.25(21.03-17.21) M x f(a g
b Q from Fig. A 3300-1, where a/1 = 0.0024 (o, + o )/8 = 0.42 b
y Q = 0.98 M, from Fig. A 3300-2, e = 3/16" 2e/t = 0.09 - 0 negligible e - 0, 2a/t = 0.292 M,= 1.06 M from Fig. A 3300-4 3
Mb = 20.15 K,,, = 33.02 11.03 = 34.05 g
AKg1 = 34. 05 Al(A2
- 31
- 99 da/dN =.0267 x 10'3 AK.726 (x10-6 in) 3 da/dNy = 13.65 x 10-6 in.
da/dN2 = 10.819 x 10-6 gg = 2ag + 10 (da/My + da/M I a
2 2
gg =.656 f 1.22 x 10
=.656122 a
For transient cycle B -
KImin = 0 K
= 17.21 (g) f(a) + 3.82 Mb II"I Imax K,,, = 26.4 1 0.829 g
Ag1 e 27.22 Ab2
- 25.57
-6
-6 da/dNg = 5.92 x 10 da/dNy = 4.69 x 10 Bf " kf+ 200 x AaB =.
+. 0106 a
2 ABf = 0.65718
Cosas7 s.so NORTHEAST UTILITIES SERYlCE COMPANY su'BJE CT Ultrasonic Indications in Steam 7.[dh 12/15/83 ny oATE Generator T0p Head Dome Weld --
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or Transient C To evaluate K for pressure and temperature loadings, g
peak stresses at the surfaces, regardless of orientation, will be used. This will increase peak and membrane stresses and will be conservative. Stresses are from Ref. 1, pg. A-87.
o at ID = -P, o at OD = 0:
r r
- 16 Cooldown o,e [3.92 - (-2.45)) 1/2 = 3.18 b = 3.92 -o,'= 0.73 o
f(a) = Vn I.657/Q = 1.45 KImin = 3.18(1.06)1.450 + 0.73(1.15)1.450 4.89
+ 1.158 K,y
= 5.05, KIm2
- 4*74 g
- 7 Loss of flow o,= 11.12 + 23.58 = 17.35 2
b = 23.58 - o,= 6.23 o
KImu = 1.06(17.35)1.45 + (16.23)(.15)1.45
= 26.7 1 1.35 KIm ul = 29.05 K,,2 = 25.35 g
AKC1 = 29.05 - 5.05 = 24.0 AKC2 = 25.35 - 4.74 = 20.61 j
da/dNy = 3.7 x 10-6 da/dNy = 2.1 x 10-6 gg = 24f + 40 Aa =.657 + 116 x 10-6 =.65729" a
l Transient D E Tygngignt C pf = gf + 40 aa =.65740 a
2 Transient E K,=KImDI 5.05, KIm2 = 4.74 e
g l
- 4 Reactor Trip o,= 11.48 + 23.36 = 17.42 I
b = 23.36 - o,= 5.94 o
l l
l l
l
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or K,,, = 1.06(17.42)1.45 1 5.54(.15)1.454 g
26.8 1 1.29 K,,3 = 28.09, KInu2 = 25.51 g
AKE1 = 28.09 - 5.05 = 23.04 AKE2 = 25.51 - 4.74 = 20.77 da/dNg = 3.18 x 10-6 da/dNy = 2.16 x 10~0
,Ef = g g + 400 AaE =.657 +.0010 =.658 2
Transient F Iain = K,- E g
- 1a Beat up = #4 Reactor Trip Transient F = E Ff " UEf + 20 AaE =.658 +.000106 =.658 a
2 Transient c KIm u = Transient F KImin " "a = (16.55
.755) + 16.43 = 16.11 2
b = 16.43 - 16.11 = 0.32 o
KImin = (1.06)16.11(1.452) +.32(.15)1.452 24.79 1.070 K,3
= 24.85 KIm2 = 24.73 g
AK3 = 28.09 - 24.85 = 3.24 AK2 = 25.51 - 24.73 = 0.78 da/dNg = 2 x 10-8 da/dN2 = 1 x 10~ 1
KImax " 'm = (13.95
.86) + 21.26 = 17.17 2
b = 21.26 - o,= 4.069 o
K,,, = 1.06(17.17)1.452 1.15(4.089)(1.452 )
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14 sager uo, or Ky = 26.42 i.89 = 27.31, 25.53 AKy = 26.42 - 24.85 = 1.57 AK2 = 25.53 - 24.73 = 0.8 da/dNy = 1 x 10-10 da/dNy = 1.1 x 10-11 Hf
- k f + 15,000 aag =.658 + 7.5 x 10-7 a
2 Transient I K2 min = Transient G K
,,3
= 0, = 14.32
.85 + 20.57 = 17.02 y
2 b = 20.57 - o,= 3.55 o
K,,, = 1.06 17.02 1.452 1 3.55.15 1.452 y
26.19 i.77 = 26.96, 25.42 AKyy = 26.96 - 24.85 = 2.11 AKyy = 25.42 - 24.73 =.69 da/dNy = 4.3 x 10-10 da/dN2 = 6.6 x 10~12 6
yf = gg + 10 any =.658 x 2.1 x 10 a
2 Transien10J and K will be deleted. Values will be less than 10-and will not add to flaw growth.
g = W Flaw growth = 0.002" Flaw Acceptability Using the end of life flaw size, a, each of the transients f
of Table 1 is evaluated versus the criteria of Section P.I IWB 3612, Winter '80 Addenda.
From IWB 3612, For Normal, Upset, and Test Conditions:
y < K,W10 K
y where K is the maximum applied stress intensity y
factor using the end of life flaw sire, a.
f
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o, For Emergency and Faulted conditions Kg<KIc/42 K
tl$ and KandakEerialproperties. Ref. 2 established that are based on metal temperature at the cracx the maximum NDT in the steam generator secondary shell is 10*F.
From the WRC Bulletin 175, Ref. 3, KIR = 26.77 + 1.233 exp [n.0145 T-(NDT - 160))
IR
- Ia S K, = 200 T-(NDT - 160) = 341*F g
T = 341 - 150 = 191*F Since pressurization of the secondary side is limited to saturation pressure and temperature, except test conditions, the applied K will be evaluated versus a fixed K, of y
g 200 KSIJin.
Kg < 200/J10 applied Kg < 63.24 KSI Jin.
From Table 2, K
= 34.05 KSI Jin for hydro. Since I
temperatureforI%roandleaktestwasnotdevelopedby the methodology of Appendix G to Section III or Appendix A to Section XI a pressure-temperature limit curve is given in Figure 4.
This curve is the locus of points where K applied J10 = K Operation to the right of this culve insures negligl8e growth of this indication r
and conformance with this calculation.
[.
Ductile Failure From pg. A-3, Ref. I minimum wall thickness for Upper shell dome, Secondary Head - upper done.
t = P(Rg + C.A.) + C.A.
where P = 1000 psi r
Rg = 116.25" 2S" - P CA = 1/16" t = 2.219" S,= 26.7 KSI r
From Fig. 2 treasining = 4-4/16 5/16 = 2 *!/4" tremaining > t,g, code.
The through-wall dimension was conservatively determined by " collapsing" all indications into a single cross j
section. Thus determined, the maximum flaw size less i
i r
l l
co43., 4 NORTHEAST UTILITIES SERVICE COMPANY soa>EcT Ultrasonic Indications in St:am my 7.T* 8h CATE 12/15/83 Generator-Top Head Dome Weld --
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s the wall thickness is greater than the original code allowable minimum wall thickness. Therefore no concern for ductile failure of the region exists. Code allowable stress values are not exceeded in the region of interest.
REFERENCES 1.
CENC-1176, " Analytical Report for Northeast Utilitires Service Co., Millstone Point Station Unit No. 2 Steam Generator", Combustion Engineering, Feb. 1972.
2.
G/ME-79-389 M. Kupinski to E. C. Farrell dated 3/19/79.
3.
WRC Bulletin 175, "PVRC Recommendations on Toughness Requirements for Ferritic Materials", Welding Research Council, August 1972.
t t
9 i
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sosas7 s.so NORTHEAST UTILITIES SERYlCE COMPANY susJacT Ultrasenic Indicatiens in Steam 77.[4 ey DaTe 12/15/83 a
Generator T0p Head Dome Weld --
curo, my #1-DaTe nAa/4'4 Millstone Unit NO. 2 82-196-247GP O
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or TABLE 1 TRANSIENTS Normal and Upset conditions Pressure Temp.
Time Occurances 1.
Beat up 900 Sat.
4.62 hr.
500 Cooldown 0
RT 4.62 hr.
500 2.
Plant Loading 815 Sat.
15,000 Unloading 868 15,000 3.
10% Step Load Increase 815 Sat.
2,000 Decrease 820 Sat.
2,000 4.
Reactor Trip 900 Sat.
400 5.
Cold Feed Transient 900 Sat.
14 min.
15,000 6.
Plant variations:
6 Up 855 Sat.
10 Down 775 Sat.
10 7.
Loss of Flow 900 Sat.
40 8.
Loss of Load 900 Sat.
40 Eneroency Conditions 9.
Loss of Secondary Pressure (MSLB)
O 535 5
10.
Loss of Feed Flow 0
535 8
Testino Conditions 11.
Secondary Side Leak Test 1,000 200 12.
Secondary Side Hydro Static 1,250 10
- At Limit Curve Pg.19
const neo NORTHEAST UTILITIES SERVICE COMPANY
'sus >r cy Ultrasonic Indications in Steam 7,/~E4 my oave 12/15/83 enno. y ##I -, pave / vss M Generator Top Head Dome Weld --
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or TABLE 2 TRANSIENT CYCLES X,,,
Weles KImin g
A.
- 12 Seendary Hydro Test 0
34.05 34.05 10 B.
- 11 Secondary Leak Test 0
27.22 27.22 200 C.
- 7 Loss of Flow-#1b Cooldown 5.35 29.05 24.0 40 D.
- 8 Loss of Load-#1b Cooldown 5.05 29.05 24.0 40 E.
- 4 Reactor Trip-#1B Cooldown 5.05 28.09 23.04 400 F.
- 1a Beat up-#1b Cooldown 5.05 28.09 23.04 20 G.
- 1a Beat up-#6b 24.85 28.09 3.24 460 H.
- 2b Flant Unloading-#6b 24.85 26.42 1.57 15,000 I.
- 6A-Plant Var. Up - Plant 6
l Var. Down 24.85 26.96 2.11
-10 J.
- 5 Cold e'eed - #2a Plant Loading Negligible 15.C00 K.
- 3h Step Decrease - #3a Step Increase Negligible 2,000
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- f. 0 "
M E !N F0 M C EM EN 7" FOM STRAM 097465" Not SA.123 = GM. 8 class /
Zd i-ry,12 t a ).f
l 3ECONDABY NRAD h
SA= f/C
- GM. TO Ri ' lic. E S" WPPER $1CONDRAY C YLIND E M 34-333=&M.D CLR$3 l Mi * !! f O" w g, y, y,g g l
1 --
29'21' l
COME 3M-533 = &M. 6 C LASS /
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t e r.CE S' Risir.125"
, 4,3 7g *!
l LOWEM SECO NDA B Y CYLtWDEM M
urren sec muur - sn-r> s - c M.a ci 3
- 4. e WE A 3 CO MENY ~ 38 ~ flC = GM. 70 9
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FIGURE 2 FLAW LOCATION Reference NU-UT-Oo1 Examination Record 3
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FIGtJRE 3 FLAW LOCATION ustJ I
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or FIGURE 4
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l I.
4 g4
. I I
- ' - - _,. - - - l i Pressure-Temperature Limit l w.
Curve-1 u
Steam Generator Secondary Shell
~
1-- - ~ - ~ ~ - - ' Material Properties NDT = 10*F I < K, (/10)
K
_-pm.
g No allowance for instrument t
error.
Pressure Temperature l
- F w-s._
1250 138 A.
820 96 570 50
}fm g
1-_._--..
Ib
. _. ~.. _ -, - -
. -.. _. ~
A
$1:
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O y
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g a
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Temperature
- F 5