NG-99-1192, Forwards marked-up Copies of Affected Tables & Ref Matl Which Supports Changes Re DAEC Reactor Vessel Integrity Database (Rvid),As Requested in GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity

Forwards marked-up Copies of Affected Tables & Ref Matl Which Supports Changes Re DAEC Reactor Vessel Integrity Database (Rvid),As Requested in GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity

ML20216E625
Person / Time
Site:	Duane Arnold
Issue date:	09/08/1999
From:	Peveler K IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT
To:	NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-92-01, NG-99-1192, NUDOCS 9909150199
Download: ML20216E625 (12)

Text

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FM A L L1 A N T EsM PTILITIES its uunne. inc.

IES Utilities E277i)A Palo. IA 52324 9785 a: 19.8

-minanoconcem.

NG-99-1192 Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station 0-PI-17 Washington, DC 20555-0001

Subject:

Duane Arnold Energy Center Docket No: 50-331 Op. License No: DPR-49 NRC Generic Letter (GL) 92-01, Revision 1, Supplement 1

Reference:

Letter dated June 25,1999, to E. Protsch (IES Utilities) from B. Mozafari (NRC), Closure Regarding Response to the Request for Additional Information to Generic Letter 92-01, Revision 1, Supplement 1,

" Reactor Vessel Structural Integrity," Duane Arnold Energy Center File: A-10lb, B-11 The referenced letter requested that IES Utilities review information in the Reactor Vessel Integrity Database (RVID) concerning the Duane Arnold Energy Center (DAEC). Our review has determined that some entries in the RVID require revision to reflect new data obtained from the surveillance capsule which was withdrawn during Refueling Outage 14 in October of 1996. Marked-up copies of the affected tables are provided in the attachment, along with reference material which supports the changes.

Should you have any questions regarding this matter, please contact this office.

Sincerely, M

Kenneth E. Peveler Manager, Regulatory Performance Attachment cc: C. Rushworth

. Igg' E. Protsch (w/o)

D. Wilson (w/o)

B. Mozafari (NRC-NRR) f J. Dyer (Region III) , O}

NRC Resident Office DOCU 9909150199 99090s PDR ADOCK 05000331 P PDR

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• Attachment to NG-99-1192 Page 4 of II GE-NE-D i l00716-01 Revision 0 Table 3-1 Chemical Composition of RPV Beltline Materials from Fabrication CMTR Recordsa Composition by Weight Percent Identification Heat / Lot No. Cu- NI - C Mn P- S Si Mo PLATES:

Lower-Intermediate Shell Plates:

1-20 B0436-2 0.15 0.64 0.19 1.33 0.008 0.010 0.18 0.50 1-21 B0673 lb 0.15 0.61 0.20 1.37 0.011 0.014 0.18 0.55 Lower Shell Plates:

1-18 C6439-2 0.09 0.51 0.21 1.25 0.012 0.012 0.18 0.48 1-19 B0402-1 0.13 0.47 0.20 1.35 0.012 0.015 0.16 0.45 WELDSc; 1 ower and Lower-Intermediate Shell Plate Vertical:  ;

DI, D2, El, E2 432Z4521, 0.01 0.98 0 06 1.20 0.018 0.017 0.42 0.54 Lot B020A27A 432Z0471, 0.03 0.91 0.077 0.92 0.017 0.019 0.33 0.52 Lot B003 A27A Girth Weld:

DE 09L853, 0.03 0.88 0.036 1.07 0.014 0.017 0,44 0.55 Lot L017A27A DE 07L669, 0.03 1.02 0.05 1.24 0.014 0.016 0.48 0.54 Lot K004A27A

.DE CTY538, 0.03 0.83 0.066 1.06 0.02 0.018 0.46 0.49 l Lot A027A27A l a Data from GE QA Records [9]

b Surveillance Plate c Records do not specify which heat was tined for weld surveillance specimens 9

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- Attachment to NG-99-1192 Page 6 of 11 GE-hT-B1100716-01 Revision 0 4.2.2 Results The two-dimensional transport calculations indicate that flux maxima occur at azimuthal locations which are displaced by 0.25' from the RPV quadrant references (0*,90', etc.), at an elevation about 104 inches above the bottom of the active fuel. The capsule from which the surveillance samples and flux wires were retrieved was located at 36' The angular distribution of flux vs. azimuthal angle is shown in Figure 4-2. The relative distribution of flux versus elevation at the RPV inside surface is shown in Figure 4-3. The calculated core midplane flux at the (R,0) coordinates corresponding to the capsule position war multiplied by the ratio of flux at the capsule elevation to flux at midplane, as determined from the (R,Z) calculation. The lead factor based on the 36' azimuth dosimeter results calculated in [8b] was 0.72. The resulting flux at the 14.7 EFPY 36' azimuth surveillance capsule is 2.63x109 n/cm2-s. The peak flux at the vessel surface was similarly obtained by multiplying the midplane flux at the peak azimuth by an axial adjustment factor derived from the (R,Z) calculation. The resulting peak flux is 3.86x109 n/cm 2-s. Therefore. the lead fsetor is 2.63/3.86=0.68.

The transport calculation of surveillance capsule flux,2.63x109 n/cm2-s, is about 10%

higher than the dosimetry result of 2.4x109 n/cm2-s. This is considered to be good agreement in view of the significant uncertainties in the analytical model and in the experimental results. The difference may, in part, result from the use of nominal rather than as-built vessel radius.

However, it should be noted that the lead factor is not as sensitive to these differences as the magnitude of the flux. A difference in vessel radius has little, if any, effect on the calculated lead factor, since the difference would affect both capsule radius and vessel radius and would not significantly alter the ratio of fluxes at the two locations.

The fracture toughness analysis is based on a 1/4 T depth flaw in the beltline region, so the attenuation of the flux to that depth is considered. This attenuation is calculated according to Reg. Guide 1.99 requirements, as shown in the next section.

i l

l l

l 18

l Attachment to NG-99-1 i92 Page 7 of II GE-NE-B1100716-01 Revision 0 Table 5-5 Significant Results of Irradiated and Unirradiated Charpy V-Notch Data l Index Temp (*F) Index Temp (*F) Index Temp ('F) USE Material E=30 ft-lb E=50 ft-lb MLE=35 mil (ft-lb)

PLATE: Heat B%73-1 Unirradiated -35 6 -74 -23.3 158.1 Irr=*=tM (1st capsule)a 6.2" 42.4 19.0 158.8 Diference ilst caosule) 41.8 49 8 42.3 07(404%) l IrradiatM (2nd capsule)b 4 g.4 70.6 56.6 137.0 DiEerence (2nd capsule) 77 0 78.0 79.9 -21.1 (-13 3%) t 1st Capsule 2nd Capsule Difference Reg. Guide 1.99, Rev 2 ARTmC: 32*F 49'F 17'F Reg. Guide 1.99, Rev 2 (a+2o) c: -2*F to 66'F 15'F to 83'F Res. Guide 1.99, Rev 2 Decrease in USEd: 11.8% 14.3% 2.5%

. Index Temp ('F) Index Temp ('F) Index Temp ('F) USE Material E=30 ft-lb E=50 ft lb MLE=35 mil (ft-Ib)

HAZ: UnirradiatM -4 3 33 6 -0.1 116.3 IrradiatM (1st capsule)* -1.4 33.5 14.9 124.5 Diference (1st capsule) l 2.9 -01 15.0 8.2 (+71%)

IrradistM (2nd capsule)b 10.8 59.6 45.7 104.1 Diference (2nd capsule) 15 1 26 0 45.8 -12.2 (-10 5%)

. Index Temp ( F) Index Temp ('F) Index Temp ('F) USE Material E=30 ft-lb E=50 ft-lb MLE=35 mil (ft-lb)

WELD: Unirradiated -45 4 I -10 3 -271 l 99 0 Irradiated (1st capsule)* -42.9 -14.3 -36.7 101.7 DiEerence (1st capsule) 2.5 -4 0 -9.6 +2.7 (+2.7%)

Irradiated (2nd capsule)b -29.3 9.1 4.7 95.6 Diference (2nd capsule) 16.I 19 4 22.4 -3.4 (-3 4%)

First Capsule Second Capsule Difference Reg. Guide 1.99, Rev 2 ARTmc: 6'F 12'F 6'F Reg. Guide 1.99, Rev 2 (A12o) c: .$ooF to 62*F -44*F to 68'F Reg Guide 1.99, Rev 2 Decrease in USEd . 6.8% 8.1% 1.3%

a First capsule fluence = 4.9x10H n/cm2 at 5 9 EFPY b Second capsule fluence = 1.1x10 3 8 ,>cm2 at 14.7 EFPY n

c Determined in Secuan 5 ' hr 2nd capsule; same methodology used to calculate values for ist capsule d

Determined m Secuen 5.4.2 tor 2nd capsule: same methodology used to calculate values for 1st capsule I

1 I

35 ,

1

I~ N NG-99-l 192

• Page s of il GE-NE-B1100716-01 Revision 0 7.2 SURVEILLANCE CF ADJUSTMEhT I

The surveillance CF adjustment is based on a least squares fit of the surveillance data to the ARTer Equation 7-2, restated as:

ARTer = CF e FF where FF is the fluence factor shown in Equation 5-1.

The least squares approach uses the actual shifts of the 288* and 36* capsule Charpy specimens, combined with the fluence factors applicable to those capsule fluences.

CF = f(Shift 288*

• FF 288*) + (Shift 36' e FF 36*)1 (7-4)

[(FF 288*)2 + (FF 36*)2j The values for Equation 7-4 are discussed in Section 5.4.1 and Table 5-5. The chemistry for the surveillance plate is 0.15% Cu and 0.65% Ni, which has a Chemistry Factor from Table 2 of Reg. Guide 1.99, Rev. 2 [7] of 111. The chemistry for the surveillance weld is 0.02% Cu and

' 0.93% Ni, which has a Chemistry Factor from Table 2 of[7] of 27.

Capsules ;jFluence s Fluence Plate Plate Weld t Weld Location 2 Factor

[(n/cm ) Measured Shift CF from [7] Measured Shift CFfrom [7]

(*F) (*F) 288* 4.9x1017 0.29 42 not applicable 3 not applicable 36*- 1.1x1018 0.44 77 111 16 27 i

Substituting these values into Equation 7-4 results in a plate CF of 165.9 and a weld CF of 28.5 based on the surveillance data. The surveillance CF is compared to the Reg. Guide 1.99, Rev. 2 CF to establish the adjustment of generic Rev. 2 predictions to actual plarr. anditions:

Plate Adjustment .= 165.9 /111 = 1.49 Weld Adjustment = 28.5 / 27 = 1.06 67 i

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. NG-99-l 192 Page 10 of 11 GE-hT-B1100716-01 Revision 0 l Table 7-2 Plate Equivalent Margin Analysis PLANT APPLICABILITY VERIFICATION FORM j FOR Duane Arnold - BWR 4/MK I-Includine Unrated Power Condition BWR/3-6 PLATE l

Surveillance Plate (Heat B0673-1) USE:

%Cu = O.,H 1st Capsule Fluence = 4 9x1017 n/cm2 2nd Capsule Fluence - 1 1x10 18rtcm- /

I l

Unirradiated to Ist Capsule Measured % Decrease = M (Charpy Curves)

,Unirradiated to 2nd Capsule Measured % Decrease = H (Charpy Curves) l ist Capsule Rev 2 Predicted % Decrease = _12_ (Rev 2, Figure 2) 2nd Capsule Rev 2 Predicted % Decrease = _14_ (Rev 2, Figure 2)

Limitine Beltline Plate (Heat B0673-1) USE:

%Cu = 015 32 EFPY 1/4 T Fluence = 2.8x1018 n/cm2 Rev 2 Predicted % Decrease = 18 (Rev 2, Figure 2)

Adjusted % Decrease = N/A (Rev 2, Position 2.2) 18 % 5 21%, so vessel plates are bounded by equivalent margin analysis 71

r-Attachment to NG-99-i l92

,. Page 11 of 11 GE-hT B1100716-01 Revision Table 7-3 Weld Equivalent Margin Analysis PLANT APPLICABILITY VERIFICATION FORM FOR Duane Arnold - BWR 4/MK I-includine (forsted Power Condition BWR/2-6 WELD Suiveillance Weld (Heat Unknown) USE:

%Cu = Q,Q2 l

t 1st Capsule Fluence = 4 9x1017 n/cm2 2nd Capsule Fluence = 1 1x1018 n/cm2 Utstradiated to ist Capsule Measured % Decrease = Q.(Charpy Curves)

Unirradiated to 2nd Capsule Measured % Decrease = 1(Charpy Curves)

Ist Capsule Rev 2 Predicted % Decrease = 1(Rev 2, Figure 2) 2nd Capsule Rev 2 Predicted % Decrease = 1(Rev 2, Figure 2)

Limitina Beltline Weld (Heat 07L669 Lot K004 A27 A) USE:

%Cu = 0.03 l 32 EFPY 1/4 T Fluence = 2.8x1018 n/cm2 Rev 2 Predicted % Decrease = 12 (Rev 2, Figure 2)

Adjusted % Decrease = N_/_4 (Rev 2. Position 2.2) 12 % 5 34%, so vessel welds are bounded by cauivalent margin analysis 72 L