ML20211H174
| ML20211H174 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, Catawba, McGuire  |
| Issue date: | 08/30/1999 |
| From: | Tuckman M DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-92-01, TAC-MA0534, TAC-MA0535, TAC-MA0550, TAC-MA0551, NUDOCS 9909020034 | |
| Download: ML20211H174 (30) | |
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- # +~w, Duke Power Company
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- 526 South Church Street P.O. Box 1006 Charlotte. NC 28201 1006 M. S. Tuckman Executin Vice President (704) 382-2200 omCE Nuclear Generation (704) 382-4360 fax August 30, 1999 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 i
Subject:
Catawba Nuclear Station Units 1 & 2 Docket Nos. 50 -413, 414 TAC Nos. MA0534, MA0535 McGuire Nuclear Station Units 1 & 2 Docket Nos. 50 -369, 370 TAC Nos. MA0550, MA0551 Generic Letter 92-01, Revision 1, Supplement i 1: Reactor Vessel Integrity Database, Version I 2
By letters dated June 24, 1999 and June 29, 1999 for the Catawba and McGuire Nuclear Stations, respectively, the staff requested that licensees review the information contained in the Reactor Vessel Integrity Database (RVID),
i Version 2. The purpose of this submittal is to provide comments on the Catawba Nuclear Station Units 1 and 2, and .
McGuire Nuclear Stat 2cn Units 1 and 2 specific reactor l vessel information contained in the RVID database.
I If you have questions or need additional information, please contact Allison Jones-Young at (704) 382-3154.
Very truly yours, l
- b. b. W " l l M.S. Tuckman Attachments ,
9909020034 990830
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l xc: l L.A. Reyes Regional Administrator, Region II F. Rinaldi, ONRR P.S. Tam, ONRR S.M. Shaeffer Senior Resident Inspector (MNS)
D.J. Roberts Senior Resident Inspector'(CNS)
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AEIby FOR INFORMATION ONLY { i![s',{'" "
Huntersville, NC 28078 9340 M. B. Barron (704) 875-4800 omct sq,, p,,,y,,,, (704) 8754809 ux l'
l 1
I'
- l. January 7, 1999 l
U. S. Nuclear Regulatory' Commission Document Control Desk Washington, D.C. 20555
Subject:
McGuire Nuclear Station, Unit 1 Docket No. 50-369 Reactor Vessel Radiation Surveillance Program By letter dated April 22, 1998, McGuire provided the
- analysis of capsule Y (WCAP-14993) from the McGuire Unit 1 reactor vessel radiation surveillance program. The l surveillance weld data set credibility was questioned due to one point exceeding Regulatory Guide 1.99, Revision 2 criteria of 28 degrees F. The NRC guidelines for assessing credibility provided at the November 17, 1997 and February 12, 1998 meetings on-RPV Integrity Assessment were applied
, to assess the credibility of the McGuire Unit 1 surveillance weld data. Based on the attached evaluation, it has been determined that the McGuire Unit 1 surveillance data meets the credibility criteria; therefore, the basis for the current PT limit curves for McGuire Unit 1 continue to be valid.
Questions should be directed to Kay Crane, McGuire Regulatory Compliance at-(704) 875-4306.
! Very truly yours, Y kawn-- -
)
l 'H. B. Barron, Vice President l McGuire Nuclear Station
$kOlM k5h M __
j U. S. Nuclear Regulatory Commission FOR INFORMAT10N ON Document Control Desk l January 7, 1999 Page 2 cc: F. Rinaldi, Project Manager U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D.C. 20555 Luis A. Reyes U. S. Nuclear Regulatory Commission Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, GA 30303 f
Scott Shaeffer Senior Resident Inspector McGuire Nuclear Station
U. S. Nuclear Regulatory Commission Document (ontrol Desk January 7, 1999 Page 3 bxc: W. Brady ECO50-ELL RGC File I
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Evaluation of McGuire Unit 1 Surveillance Weld Data Credibility Technical Report No. ATI-98-012-T005 Revision i November 1998 Prepared by:
Date: /lf 2dg Timothy J. GlidbMh Reviewed by:
O ._
Date: 2M N Timothy C. Ha -din
(
ATI Consulting 3860 Blackhawk Rd., Suite 160 Danville, CA 94506 l
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_ % c4GuOlS7 nere j
4 FOR INFORMATl0N ON Evaluation of McGuire 1 Surveillance Weld Data Credibility Introduction Five surveillance capsules have been removed from the McGuire 1 plant. Of these five capsules, only capsules U, X, V, and Y have Charpy test results for the surveillance weld material [1,2,3,4). In the McGuire I surveillance capsule V report [2], the embrittlement (i.e., ART values) of the vessel beltline welds 2-442 A,B&C (heat number 20291/12008) was predicted using three surveillance capsule weld (heat number 20291/12008) results ,
from McGuire 1. The Westinghouse calculation of ART values for determination of the P-T limit curves showed that the limiting vessel material is the lower shell longitudinal welds 3-442 A&C (weld heat 21935/12008), and this formed the basis for the current (16 EFPY)
P-T limit curves.
Subsequently, in the McGuire I surveillance report for Capsule Y [4], a new evaluation of the surveillance weld data was performed by Westinghouse using Position C.2 ofRegulatory f
Guide 1.99, Revision 2 [5]. A best-fit to the four McGuire I weld data points was performed, and the credibility criteria were applied. The scatter in the surveillance weld data was found to exceed 28 *F for one of the data points, and the credibility of the McGuire 1 surveillance weld data was questioned.
ATI Consulting has performed a reassessment of the surveillance weld data credibility. This reevaluation considers additional information for evaluating weld heat 20291/12008, including data from multiple sources and recent guidance from NRC for surveillance data evaluation. The NRC guidelines for assessing credibility provided at the November 17,1997 and February 12,1998 meetings on RPV Integrity Assessment [6,7] were applied to assess the credibility of the McGuire I surveillance weld data. As a result, it is determined that the McGuire 1 surveillance data meets the credibility criteria and, thus, the basis for the current P-T limit curves for McGuire 1 [2] continues to be valid.
McGuire 1 Surveillance Weld Data Credibility In the February 12,1998 Industry /NRC Workshop on RPV Integrity Assessment, topics related to surveillance data credibility were discussed in depth. The NRC stafTpresented a number of preferred approaches when assessi,ng weld chemistry data and surveillance data results [7]. These approaches incorporate methods to address weld chemistry variability and the handling of data from multiple sources. For example, the staff has concluded that the CEOG analysis [8] provides an accurate determination of RPV weld best-estimate chemistries for a specific weld heat. In considering surveillance data, the staff recommends that the chemistry should be based on the chemistry data for that specific weld rather than the heat best-estimate chemistry. Also, examples were provided to correct fo'rchemical composition and irradiation environment, to provide guidance with appropriate normalizing parameters for surveillance data when assessing credibility, and to determine best-fit chemistry factor based on all available data. At the Febmary Workshop, NRC focused on several issues regarding use of surveillance data, including:
ATI Consulting 11/24/98
FOR INF0m,lu e ONLy McGuire I Suaveillance Weld Credibility Studv
. Using a CF determined from non-credible surveillance data
. Correcting for chemical composition (ratio procedure)
- Correcting for irradiation environment (temperature)
. Appropriate chemical composition for multiple surveillance capsules from a single source
. Appropriate normalizing parameters for surveillance data when assessing credibility and determining CF.
Per the NRC guidelines, the surveillance data credibility evaluation should consider other sources of data [7]. Data for weld heat 20291/12008 is available from other sources including the CEOG weld chemistry database [8], the Pilgrim surveillance program [9],
and the Eason (E900) database [10]. The Westinghouse Capsule Y report [4] calculated the scatter in the surveillance data results to be 38.32 F for one datapoint from a best fit to the McGuire I data. This ATI Consulting reevaluation considers the other sources of data for this weld heat, and includes information that was not considered previously by l Westinghouse. The study was performed to demonstrate how small changes in data input afTect the credibility of the weld data. In particular, the scatter can be reduced by using the ratio procedure to adjust for chemistry variability and by using the other information related to this weld heat.
Three specific examples are used to evaluate the parameters affecting scatter and data credibility. The examples applied to the McGuire I surveillance weld data follow NRC Example Case 4 (Suiveillance Data from Plant and Other Sources) and Case 5 (Surveillance Data from Other Sources Only). The examples are as follow:
Example 1: McGuire 1 Surveillance Data With Adjustments
- 1) Correct for Chemical Composition i Weld Heat No. 20291/12008 is contained in both the McGuire 1 and Pilgrim surveillance capsules. Chemistry differences have been observed for the individual capsule welds. All of the chemistry data for this weld heat (from the CEOG Report [8])is show,in Table 1. This includes data for weld heat 20291/12008 from a weld chemistry variability study performed for Baltimore Gas & Electric [11]. Copper and nickel measurements from the through-thickness weld variability study [11] are shown in Figures 1 and 2. This study concluded that weld heat 20291/12008 is inhomogeneous. The inhomogeneity is attributed to spool-to-spool variation in chemical composition, with each spool of weld wire having consistent composition.
This information is used to better understand the McGuire I surveillance data and to apply ,
i the surveillance results to the vessel. It is assumed that each group of specimens for a single capsule are from one spool, but that different spools could have been used for difTerent capsules. The weld in the vessel is represented by the average (i.e., mean) behavior based on many difTerent spools being used to fabricate the vessel.
ATI Consulting 11/24/98
, e
~ , .
1 A fcGuire I Sun eillance Il' eld Credibiliiv Study Weld Wire 20291/12008 FOR INFORMATION ONL; Weld Block VG 3,500 m 3,000 -
0) a3 2,500 -
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3 2,000 -
O 1,500 -
S E 1,000 -
c c 0 e c o e
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1 i f i i i v ID T/4 T/2 3T/4 OD BG Location Center Region Fusion De,ad Region HAZ Region 0 - d-(from Reference 1 I)
I i
Figure 1. Through-Wall Variability in Copper from Sample of Weld Heat 20291/12008 !
Weld' Wire 20291/12008 Weld Block V6 10,000
- 0) 0.000 -
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Figure 2. Through-Wall Variability in Nickel from Sample of Weld Heat 20291/12008 ATI Consulting 11/24/98
FOR INFORMATION ONIY McGuire I Surveillance IVeld Credibility' Study Given these observed ' chemistries for this weld heat, the chemistry adjustment to be applied per Regulatory Guide 1.99, Rev. 2, Position 2.1 is as follows:
"if there is clear evidence that the copper or nickel content of the surveillance weld differs from that of the vessel weld, i.e., differs from the average for the weld wire heat l number associated with the vessel weld and the surveillance weld, the measured values I of ARTuor hould s be adjusted by multiplying them by the ratio of the chemistry factor for the vessel weld to that for the surveillance weld" 3
' Tabic CFv ,"cha Ratio Adjusted ARTuor =
- Measured ARTuor Table CF3,mcam j The best estimate chemistry for this heat in the vessel (from the.CEOG report [8]) is:
Cu = 0.199 wt%, Ni = 0.846 wt%, CF = 200.37 F.
This adjustment is applied to the individual surveillance capsule results to obtain:
1 Plant Cu " Ni " Chemistry Fluence Measured Adjusted l 2
{ Capsule} (wt%) (wt%) Factor, CF (n/cm ) ARTmr ( F)* ARTwor ( F)
Pilgrim (1 } 0.16 0.79 176.55 2.37x10" 28.00 31.78 McGuire 1 (U} 0.20 0.91 209.95 4.45x 10" 161.32 153.96 McGuire 1 (X} 0.191 0.848 198 26 1.42x10" 170.69 172.51 McGuire 1 (V} 0.191 0.848 198.26 1.94x 10" 180.15 182.07 McGuire 1 (Y} 0.191 0.848 198.26 2.93 x 10" 190.42 192.45
- measured ARTsor based on TANH curve-fits to Charpy data
" measured /cstimated chemistries for individual capsule weld materials )
Note the differences in chemistry between the Pilgrim surveillance weld, and the weld material in McGuire Capsule U and Capsules X, V, and Y. (The Pilgrim surveillance capsule results are included for comparison with the McGuire 1 data). The measured chemistry for the Capsule U weld (Cu = 0.20 wt%, Ni = 0.91 wt%) is clearly higher than the other capsules.
These differences have been retained in the credibility assessment to normalize the surveillance data and to establish the embrittlement behavior of the vessel welds. The chemistry for the weld in McGuire Unit 1 Capsules X, V, and Y are assumed to be same (i.e., from the measured chemistry of Capsule V specimen DW-24) because of the similar embrittlement behavior for these three capsules. This effect is apparent in the plot of RTuor shift vs. fluence shown in Figure 3. The variability in chemistry is one reason for the surveillance data scatter.
Calculation of surveillance CF for best-fit to McGuire I surveillance data only is shown in Table 2. In this calculation, the chemistry adjustment calculated above is used, and capsule specific chemistries are included. However, no temperature adjustment is needed because of the narrow band ofirradiation temperatures for McGuire i plant operation.
ATI Consulting 11/24/98
. . . FOR INFORMATION ONtJ-McGuire 1 Surveillance IVeld Credibilitv Study RTNDTShift vs. Fluence 300 j
, MeanCr + 28 T
, , j
/ Mean Cl: = 158.7 Y (from (4 200 - / l Cap
.U /
/ gy C.p Y a ,30 C.p.x i 5 l J
" 100 - / a McGuireiSurveittarreWeldData
! (withod e4ustmerts)
[ Ref.: WCF.14993 [4] , 50 - l 0 0 1 2 3 4 18 2 Fluence (x10 n/cm ) Figure 3. RTuor Shif1 vs. Fluence for McGuire 1 Surveillance Weld Using the chemistry adjustment, Table 2 shows the scatter (i.e., (Adjusted - Predicted ARTuor)) for the low fluence (Capsule U) datapoint is 30.9 F, which is slightly greater than the 28 *F value required to meet the credibility criteria. However, other data exists that can improve the RTuor shift prediction and reduce the scatter.
- 2) Correct for RTuor Shift The best-fit to suiveillance results is sensitive to the Charpy curve-fit data input. For example, the measured ARTuor results for capsules U and X from the Eason (E900) database [10] are slightly different than the values calculated by Westinghouse, as shown belcw. The Eason results are used with chemistry factor adjustment to evaluate the McGuiie I weld data credibility. The Eason method uses a higher order curve-fitting techniques that is more accurate than the TANH method. The Eason technique is the currently accepted curve-fit method for use in developing improved embrittlement trend curves [10]. (Note: only two McGuire I capsule results were available in the Eason database; Capsule V and Y results have not yet been included in the database).
Capsule Fluence Measured Measured Adjusted (n/cm') ARTuor ( F) ARTuor ( F) ARTuor ( F) (West.)l'! (Eason)I' I (Eason) U .445x10 161.32 157 149.84 X 1.42x10 170.69 167 168.78 ATI Consulting 11/24/98 l
F0H liirukivlAHON ONLY McGuire I Surveillance li' eld Credibility Studv These adjusted ARTmr values are used in the best-fit calculation and the results are given in Table 3. As shown in this table, a revised CF of 157.39 'F is determined, and the scatter is - less'than 28 *F, This shows that with adjustment to the data for chemistry variability, and using improved curve-fit techniques, the scatter in the McGuire I surveillance weld data is reduced and the data is shown to be credible. Example 2: Consider Both McGuire 1 and Pilgrim Surveillance Weld Data One additional RTuor shift value for weld heat 20291/12008 is available from the Pilgrim surveillance program [9]. Although this is a low fluence point irradiated in a BWR vessel, the data is combined with the McGuire 1 data in this example to further validate the embrittlement trend for this weld heat. Table 4 shows the best-fit calculation for the McGuire I surveillance weld including the Pilgrim data. The ratio adjusted chemistry is used to determine the adjusted ARTsur, but no temperature adjustment is applied (see ! explanation in Example 3). For this case, the scatter is again less than 28 F, therefore the data is credible. A plot of the McGuire I and Pilgrim surveillance weld data results is given in Figure 4. I RTNoT Shift vs. Fluence f 300 250-l - Meso ctrve + 28 Y
#p Me.n C1' = 157.46 Y
/ Y c
5 / o, iso - e f S soo [ v uci .no et so,veinance weio o i. j sm.agim ny 50 - r 0 0 1 2 3 4 18 2 nu.nc. crio niem ) l Figure 4. RTuor vs. Fluence for McGuire I and Pilgrim Surveillance Weld Data It can be observed that four of the five datapoints are within 10 'F of the mean curve, ! and one point (Capsule U) lies close to the mean + 28 F curve. The McGuire 1 ) surveillance weld data arejudged to be credible (i.e., scatter is less than 28 F) using 1 cither Example 1 or 2. ATI Consulting -6' 11/24/98
F.0R AlcCiutre INF0RMyI I hurve:.Tlance e pylY re ibi ify Study Example 3: Consider Both McGuire I and Pilgrim Surveillance Weld Data with Mean Chemistries for Surveillance Materials . In addition to the above evaluations, the credibility of McGuire Unit I surveillance weld data was examined by the method of NRC example Case 5 [6). The measured ARTuor data j from all sources are adjusted to the mean chemical composition of the surveillance capsules i using Mean Cu = 0.191 wt% Mean Ni = 0.867 wt% CFuo, = 201.02 *F No temperature adjustment is needed since the irradiation temperatures for the McGuire 1 data are within a narrow range (i.e.,558 - 560 F). Temperature correction (i.e.,1 F/ F)is not appropriate for the Pilgrim BWR data since the absolute shif1 values are low in the BWR j
. fluence range (below 10'8 n/cm 2), and temperature correction is intended for data in the 2
PWR (10"- 10" n/cm ) fluence range. The adjusted values of ARTwor are shown below, 1 and are calculated from the equation Adjusted ARTxor =
' Table CF""
- Measured ARTsor l Table CFe .,a, , !
Plant Cu Ni CFora, Measured Adjusted { Capsule} (wt%) (wt%) (F) ARTwor ARTuor ( F) (F) Pilgrim { l } .163* .841* 184.23 28.0 30.55 McGuire 1 {U} .198** .874** 204.13 157 154.61 McGuire 1 {X} .198** .874'* 204.13 167 164.46 McGuire 1 {V} .198** .874** 204.13 180.15 177.41 i McGuire 1 (Y} .198** .874** 204.13 190.42 187.52 best estimate chemistry for Pilgrim surveillanc~e weld data from CEOG database [8]
" best estimate chemistry for McGuire I surveillance weld data from CEOG database (8]
These values of Adjusted ARTvor are applied to the CF/ credibility calculation in Table 5. From these results CF = 154.77 *F; 4 out of 5 datapoints are credible (scatter less than 28 F), and one point is 34.72 *F from the predicted ARTwor. Therefore the data set should be considered credible. The McGuire I surveillance weld data arejudged to be credible using the method of ; Example 1,2, or 3. Because the surveillance weld data is credible, a reduced margin l term (c a= 14 F) can'oc used for determining embrittlement in the vessel. All Consulting 11/24/98
FOR INFORMATION ONLY McGuire i Surveillance IVeld Credibilitv Study
~
Effect of Surveillance Credibility Evaluation on Current McGuire Unit 1 P-T Curves The weld surveillance data credibility evaluation discussed above yields a chemistry factor for welds 2-442A, B, & C slightly different from the CF used in the generation of the 16 EFPY P-T limit curves (2]. The Adjusted Reference Temperature (ART) for the McGuire 1 vessel welds 2-442A,B&C is determined using the surveillance data results from Example 2 2 with a CF = 157.46 F (from Table 4). A 1/4-t fluence value of 0.4348x10 n/cm was determined for weld seams 2 442B&C from the Westinghouse calculation of P-T limits at 16 EFPY [2] The revised ART value for weld seams 2-442B&C is calculated from the equation: ART = RTuor<u) + ARTuor + Margin
.where, RTuoT(v) = -50 F 2
1/4-t Fluence = 0.4348x10 n/cm (from Reference 2) FF = 0.768 CF = 157.46 F Margin = 28 *F ART = -50 + (157.46
- 0.768) + 28 F ART = -50 + 120.9 + 28 = 98.9 F A similar comparison for weld seam 2-442A computes a revised ART value for this weld seam:
ART = RTuor + ARTuor + Margin where, RTuor<u) = -50 F 2 1/4-t Fluence = 0.3971x10 n/cm (from Reference 2) FF = 0.744 CF = 157.46 F Margin = 28 F ART = -50 + (157.46
- 0.744) + 28 *F ART = -50 + 117.2 + 28 = 95.2 F This results are compared to the calculated ART values [2] at the 1/4-t location used to determine the existing (i.e.,16 EFPY) P-T limit curves for McGuire 1:
i ATI Consulting 11/24/98
I FOR INFORMATION ONLY McGuire i Surveillance IVeld Credibilitv Study Note: Data Reproduced from Table 8-4 in WCAP-13943121 for McGuire i Vessel at 16 EFPY Component 1/4t Fluence' FF CF IRTuor ARTi:or Margin ART x10" (*F) (*F) ('F) (*F) @ 1/4t (n/cm') (*F) W 52.4 17 Int. Shell Plate, B5012-1 .6008 .857 61(4 34 103.4 Int. Shell Plate, B5012-2 .6008 W .857 100.3 (d) 0 85.9 34 119.9 Int. Shell Plate, B5012 3 .6008 W .857 74.9 (d) -13 64.2 34 85.2 LwT. Shell Plate, U5013-1 .6008 W .857 99,1 (d) 0 85.0 34 119.0 LwT. Shell Plate, B5013-2 .6008 W .857 65 (d) 30 55.7 34 119.7 LwT. Shell Plate, B5013-3 .6008 W .857 65(d) 15 55.7 34 104.7 Int. Long. Welds,2-442 A .3971 .744 157.7(4 -50 117.6 28 95.6 Int. Long. Welds,2-442B&C 4348* .768 157.7(4 -50 121.4 28 99.4
'LwT. Long. Welds,3-442B .3971 .744 223.1(4 -50 166.0 28 144.0 LwT. Long. Welds,3-442 A&C .4348 N 768 223.l(4 -50 171.5 28 149.5(4 W -.857 -70 34.1 34.1 -1.8 Circ. Weld. 9-442 .6008 39.8 (d)
'dFluence, f, based on for ( 10" n/cm ,2 E > 1 MeV) = 1.008 at 16 EFPY for the intermediate and lower shell plates. The McGuire i vessel thickness = 8.625 inches. Thus, fue = for
- cxp( .24*(8.625/4)).
- Fluence, f, based on fot ( 10" n/cm ,2 E > 1 MeV) = 0.7295 at 16 EFPY for the int. shcIl long. welds 2-442B&C and lower shell long. welds 3-442 A&C. 1 (O I Fitted chemistry factors based on surveillance data results [2].
l (d) Chemistry factors based on tables from Reg. Guide 1.99, Rev. 2 l5j. (O Limiting vessel beltline material for McGuire I cooldown P-T limit curves at 16 EFPY (%t location). Review of this table yields the following observations:
- 1) the new ART (98.9 F) for welds 2-442B&C is slightly less than the calculated ART value (99.4 F) for these weld seams in the P-T curve analysis (2]. Also, the new ART for weld 2-442A (95.2 F) is less than the calculated ART value (95.6 F) for this weld seam in the P-T curve analysis.
- 2) the new ARTS for each of these weld seams are still significantly lower than the ART value (149.5 F) for weld seams 3-442A&C, which continue to be the limiting vessel beltline material for the McGuire 1 vessel. Therefore, the validity of the existing (i.e.,
16 EFPY) P-T limit curves for McGuire 1 is not affected by this evaluation. 1 Summary This evaluation demonstrates that the McGuire 1 surveillance weld data are credible using a number of methods recommended by the NRC for surveillance data evaluation. Data from all available sources have been considered, and appropriate adjustments made to account for chemistry variability. The current McGuire Unit 1 P-T limit curves [2] were based in part on the credibility of the surveillance weld data, and this study confirms that credib!!ity. ATI Consulting 11/24/98
E l ' * " FOR INFORMATION ONLY ' A(cGuire i Surveillance IVeld Credibility Studv l . References
- 1. " Analysis of Capsule U from the Duke Power Company McGuire 1 Reactor Vessel Radiation Surveillance Program," WCAP-10786, February 1985.
- 2. " Analysis of Capsule V Specimens and Dosimeters and Analysis of Capsule Z
! Dosimeters from the Duke Power Company McGuire Unit 1 Reactor Vessel l Radiation Surveillance Program," WCAP-13949, February 1994.
- 3. " Analysis of Capsule X from the Duke Power Company McGuire 1 Reactor Vessel radiation Surveillance Program," WCAP-12354, August 1989.
- 4. " Analysis of Capsule Y from the Duke Power Company McGuire Unit 1 Reactor ;
- Vessel Radiation Surveillance Program," WCAP-14993, February 1998. I
- 5. Regulatory Guide 1.99, Revision 2," Radiation Embrittlement of Reactor Vessel Materials," USNRC, May 1988.
- 6. Minutes from Industry /NRC Meeting on Generic Letter 92-01, Rockville, MD, l
November 17,1997. l 1
- 7. Minutes from Industry /NRC Workshop on RPV Integrity Issues, Rockville, MD, February 12,1998.
> 8. "Best Estimate Copper and Nickel Values in CE Fabricated Reactor Vessel Welds," ABB Combustion Engineering, Report No. CE NPSD-1039 Revision 02, June 1997,
- 9. Norris, E. B.," Pilgrim Nuclear Power Station Unit 1 Reactor Vessel Irradiation Surveillance Program," Final Report, SwRI Project No. 02-5951, July 1981.
- 10. Eason, E. D., Wright, J. E., and Odette, G. R., " Improved Embrittlement Correlations for Reactor Pressure Vessel Steels, NUREG/CR-6551, Draft Report, May 1997,
- 11. Fyfitch, S., and Pegram, J. W.," Reactor Vessel Weld Metal Chemical Composition Variability Study," B&W Nuclear Technologies, BAW-2220, June 1995, i
i l ATI Consulting 11/24/98
FOR Pirnona r.nc, ny AfcGuire 1 Surveillance Weld Credibility Study Table 1. Measured Cu and Ni Chemistries for Weld IIcat Number 20291/12008 Group Tag Analysis Cu Ni Avg.Cu Avg. Ni # of wi% wt% CE PEDIGREE DATA Group wt% wt% Colts SOURCE Tag 0.16 0.77 VALID SWRI-02 5951 a 0.1630 0.8410 1 0.16 0.77 VALID SWRI-02-5951 a 0.17 0.78 VALID SWRI-02-5951 a 0.16 0.79 VALID SWRI-02-5951 a 0.16 0.79 VALID SWRI-02-5951 a 0.17 0.8 VALID SWRI-02-5951 a 0.14 0.81 VALID SWRI-02-5951 a 0.16 0.81 VALID SWRI-02 5951 a 0.16 0.81 VALID SWRI-02-5951 a 0.17 0.81 VALID SWRI-02 5951 a 0.13 0.72 VALID BAW-2220 a J 0.13 0.74 VALID BAW-2220 a 1 0.14 0.74 INDETERMINATE NI BAW-2220 a 0.17 0.76 INDETERMINATE NI BAW-2220 a 0.16 0.79 INDETERMINATE NI BAW-2220 a 0.18 0.93 VALID BAW-2220 a 0.16 0.94 VALID BAW-2220 a 0.17 0.95 VALID BAW-2220 a . 0.16 0.96 VALID BAW-2220 a 0.17 0.97 VALID BAW-2220 a 0.17 0.98 VALID BAW-2220 a 0.19 0.83 VALID BAW-2220 a 0.19 0.86 VALID BAW-2220 a c l O.1978 l 0.87-12 l 1 l 0.2 0.91 VA. LID WCAP-10786 b l 0.21 0.88 VALID D24117 b 0.195 0.87 VALID WCAP-13949 b 0.191 0.848 VALID WCAP-13949 b 0.193 0.863 VALID WCAP-13949 b l l 0.2370 l 0.8226 l 1 l 0.15 0.69 INDETERMINATE NI BAW-2220 c 0.16 0.69 INDETERMINATE NI BAW-2220 c 0.18 0.71 INDETERMINATE NI BAW-2220 c 0.19 0.71 INDETERMINATE NI BAW-2220 c 0.22 0.71 INDETERMINATE NI BAW-2220 c 0.17 0.73 VALID BAW-2220 c 0.17 0.73 VALID BAW-2220 c 0.17 0.73 VALID BAW-2220 c . 0.3 0.73 VALID BAW 2220 c 0.3 0.73 VALID BAW-2220 c 0.33 0.73 VALID BAW-2220 c 0.33 0.74 VALID BAW-2220 c 0.27 0.78 VALID BAW-2220 c 0.27 0.8 VALID BAW-2220 c 0.23 0.84 VALID BAW-2220 c ATI Consulting 11/24/98
r, . FOR fNmr>ununn om AlcGuire i Surveillance Il' eld Credibility Stu v
~.
0.23 0.85 ' VALID BAW-2220 c 0.23 0.86 VALID BAW-2220 c 0.23 0.86 VALID BAW-2220 c 0.24 0.86 VALID BAW-2220 c 0.25 0.86 VALID BAW-2220 c 0.2 0.87 VALID BAW-2220 c 0.2 0.87 VALID B AW-2220 c 0.23 0.87 VALID BAW 2220 c 0.23 0.87 VALID BAW-2220 c 0.24 0.87 VALID BAW 2220 c 0.19' O.88 VALID BAW-2220 c 0.26 0.9 VALID BAW-2220 c 0.18 0.96 VALID BAW-2220 c Best Estimate Weighted Mean Vessel Chemistry [8]: Cu Ni 0.199 0.846 ATI Consulting 11/24/98
c> _ Te:o E Oa2do2O<- r v ) d F u . - 8 S t d ( - 9 e d 8 / v 9 0 6 4 t l t s e 0 1 2 l u c t 2 5 1 / i bi j i 3 - - I d d d I er A er C P d l e W d F) . e e "( 1 5 7 2 - c t c r n 3 4 7 4 _ i a i d e 2 7 8 0 l l e e T r 1 1 1 2 vr . P R _ u a A _ S t a ._ i _ e r D r _ i u d e 6 2 5 5 8 _ G l e T 2 4 0 3 0 c R 1 M W A 9 1 9 8 5 1 7 4 7 7 e F 1 1 2 2 c F n l a l i e ) vu0 r )8 d ( F e 6 1 7 5 F _ S0 t s r 9 5 0 4 2 u 2 2 1 1 j e 3 5 7 8 2 9 9 e/ d T 1 1 1 1 8 r1 A R 8 i u2 9 A 5 1 G0c2 = 3 1 2 l e Meob r 2 0 0 7 5 1 5 0 2 5 5 8 b t F 0 0 9 5 4 a t m F 6 2 3 6 8 T i u 4 + FN t 0 1 1 1 8 s t 0 e a e 1 _ B H 7 7 r 5 8 1 5 flod F 7 9 8 8 =
) e F 7 0 1 2 :
F
) _
FW C( 0 1 1 1 m u C x 2 F F ( S ( r F E o F t c ) = d + a f 2 ) n ) m F a r F , 7 y e c /c n n 4 4 3 3 "( 0, e t r e" 4 4 G. 9 9 r o T R i s l u 0 0 1 1 2 T ml
- 1 A
m F 1 0 e ( R - F' h A 8 F ( 2 C d e t 0 ( E
) c p 0 0 9 8 i
=
F 6 6 5 5 d , T *( 5 5 5 5 e r p F P p C g i n t l l e s u u s n p U X V Y e C o a r C e I h T w A
o P: 1 S 3$ %: y d 8 t u 9 S ) / 4 t y
- F 2 i
( / l i d I bi e d 2 5 3 5 s t e 9 0 8 8 I d t s t e r i F- ji u c 7 2 4- 3 9 C e d d dl v A er F e r P i u e c C ) m ] F l e 0 d
- l i 1 e t
( 9 8 9 3 e [ c r vr i 1 2 5 2 u n d e 2 7 8 0 S o s e T r 1 1 1 2 - i a P R i er E A u g G c n i M s r U T m 6 0 3 3 5 0 5 3 9 7 t a R 6 5 5 7 3 6 a A 1 8 1 4 7 2 2 D) d8 F F 1 1 l 0 e0 W2e/ 1 ) F F 9 c1 d 3 e ( '4 '8 7 5 n9 a2 t s r 8 7 0 4 7 5 l l 0 j u e 9 8 2 2 1 4 6 8 9 e 2 d T i 3 1 1 1 4 _ e vr r e A R 1
= 1 _
l ub A ) 5 b l 8 - a S mu i t a 4 T 1 e eN r 0 0 7 5 1 5 0 2 d r
+
i t
'F 0 9 5 5 o 9 u a e F 0
6 2 3 6 8. tf 7 G c H 0 1 1 1 4 xe t 3 6 7 Mle d e e s = i t oW t ( ( t a F C 2
)
F F 5 8 1 5 a F F 7 9 8 8 d x ( t F 7 0 1 2 o F s : F I e 0 1 1 1 mt s + d
'B ut Sf i
= n )
r - ) F a r f o e v 0 e r (
) ) u r s T e
F f 2 c el
- R C cm n A 7
( e c / 4 4 4 3 o T 1 0
- r n n 4 2 4 9 3 9 s a
R - F o e 4 1 A 8 F t u "0 0 1 2 E d 2 ( c l F e 0 I a 1 ( m t ( g F o r i c = y f d = r d e r p F t s e e P p C i l u i n g m s U X V Y a n e p b t e r i t a e l u h C O h s C
- w n
o C I T A
, 1O r
- g oxllED62 oz l
y de 8 t ~ i 9 S - / 4 y i t
) /
2 l i b - F 1 1 i d d ( e e d 2 7 2 1 4 r t e 8 1 9 9 C s u c t 7 7 4 3 9 d l
) ji 1 2 - - -
e m d d W i r A er e g P c l n i i a P l l e d ) v r n F i t a d e S 1 t ( 6 7 9 9 8 9 8 1 c r 0 2 3 e r e r id e 0 1 7 5 2 2 8 0 i u i u e T r 3 1 1 1 2 G G P R c c A M M ( t a r a e 6 3 5 5 6 D)8 T R 7 0 0 3 0 3 8 6 5 5 7 9 d 0 l A 6 1 8 1 4 6 F e0
- 1 1 2 2 7 W1 2 F F 6 4
e/ 1 7 c9 5 n2 ) 1 l a0 d F
=
4 l i e 2 e ( 8 '4 '8 7 5 5 ver t s r 7 8 7 0 4 9 1 e u m 9 8 2 2 8 l r b j 1 8 9 8 Su mu b d T 3 4 6 a A R 1 1 1 1 4 T l A + A N l _ t 6 t o a e 8 7 0 9 i t H 4 6 0 0 5 1 5 2 9 8 6 7 Ft l d 'F 3 0 0 6 0 2 9 3 5 6 8 F s e 0 0 1 1 1 4 = eW F ) B( r C 2 F x F f o ( F E
) : F F 9 5 8 1 5 mta = d n
+
C ( F F 0 9 7 7 9 0 8 1 8 2 ua Sd
)
F a ) r 1 , r 0 1 1 1 o ( 0 e t o 0 t s r g o T c i t el - R a f
- T 1 A
F e R 0
- y v - F r f 2
) r u A s F
( t c d 2 s cm 7 7 E i e 4 3 n e 0 ( c / 3 4 4 t g m n n 2 4 2 9 3 9 o c = e e 0 4 4 s i d h u 1 2 a e
=
"0 0 0 1
E r p F C l F ( 1 m P p C g or i n f l t
} } } } }
u e d l
}
U X V Y e s n t n a usp 1 { { { { ( i n a e o l I I I I r C P a L C C C C b t e I C P O T ( M M M M
- h w A
bm b5x s# 3 r<- v d o _ * &t - S . i n y t i l d ) m i bi o - *(F i d ht e d r e e d 1 2 0 0 1 4 C M t s e 0 7 5 4 d l j i u c t 1 4 3 5 5 1 1 _ e 5 d d - W e A er e c s P n a l l a C i e e ) vr l p F u d S m a t e ( 4 9 8 5 9 1 8 3 9 i c 5 e x i d m 9 9 2 8 i r u E e r T 9 2 1 1 6 1 8 1 9 1 G c C P R A M R N y B m 6 8 4 2 3 _ a T 3 7 5 5 0 7 t a)8 R 8 9 0 9 1 6 A D0
- F 5 1 1
8 1 0 2 4 2 5 7 F d 02 l F e1 7 W/e 9 1
)
7 4 5 c2 F 1 n0 a2 d e ( 5 1 6 1 2 = 4 5 t s 5 6 4 4 5 _ l r 9 t e l i e j u m 0 4 4 7 7 8 eb 5 6 7 8 l b v d T 3 1 1 1 1 8 _ a r m A R 4 T u u A SN _ + 1 t 3 e r e a 7 6 uH i 4 0 7 1 0 9 5 6 0 5 5 2 8 Gdcl 2 F 3 0 0 9 5 6 8 7 e F 0 6 2 3 4 = - MWo( 0 0 1 1 1 F C 2
)
F t x F ( t i F E F : F _ t 9 m = d + s 0 5 8 1 5 u n ) e F 9 7 9 8 8 S
) a F
B F 1 7 0 0 1 1 2 1 (
)
f m _ r 0 1 r g T o o R f
) T eI '
- l. A
_ F R 0 F' C ( f 2
) A 8 F
( r e
,m 7 7 d
e 2 0 E t o c /c 3 4 4 2 4 3 3 t c ( p c n e n 2 0 4 4 4 9 9 i d
=
a u "0 1 1 2 e
=
F l 0 0 r p F y F 1 ( P p C . r . t s :.. i
} } } } } i.
m l e } U X V Y . e t n u l { { { { . h a sp { I I I e - r C l 1 P a L C C C C r e t C P - ( M M M M h w a
'. 1 1
WESTINGHOUSE NON-PROPRIETARY CLASS 3 WCAP-14995 FOR INFORMAIl0N ONLY Evaluation of Pressurized Thermal Shock for l McGuire Unit 1 S. L. Abbott February 1998 Work Performed Under Shop Order DlUP-108 Prepared by the Westinghouse Electric Company for the Duke Power Company Approved: , C. H . Boyd, Man %ger Equipment & Materials Technology Approved: D. M. Trombola, Acting Manager Mechanical Systems Integration WESTINGHOUSE ELECTRIC COMPANY Nuclear Services Division P.O. Box 355 Pittsburgh, Pennsylvania 15230-0355
@ 1998 Westinghouse Electric Company All Rights Reserved 4
FOR INFor""v nl9y, y EXECUTIVE
SUMMARY
The purpose of this report is to determine the RTers values for the McGuire Unit No.1 reactor vessel beltline based upon the results of the Surveillance Capsule Y evaluation. However, the surveillance capsule data is deemed not credible per Regulatory Guide 1.99, Revision 2 criteria. Therefore, the RTers values are calculated in accordance with Regulatory Guide 1.99, Revision
- 2 using the procedures and margins which give the most conservative results. Additionally, surveillance weld metal data from Diablo Canyon Unit No. 2, which is credible and applicable to the McGuire 1 intermediate shell longitudinal welds, is used. Based upon these conservative results, all of the beltline materials in the McGuire Unit No.1 reactor vessel have RTers values
, below the screening criteria values of 270'F for plates or forgings and longitudinal welds and 300*F for circumferential welds at EOL (34 EFPY). The RTers values remain below the screening criteria for extended life out to 50.3 EFPY.
l I l l l l Evaluaton of PTS for McGuire Uniti February 1998 1 I
, , , FOR INFORMAT10N ONty Tabic 1 McGuire Unit 1 Reactor Vessel Beltline Unirradiated Material Prcperties 1 Material Description Cu(%) Ni(%) RTwonuf' intermediate Shell Plate B5012-1 0.11 0.61 34'F Intermediate Shell Plate B5012-2 0.14 0.61 0*F 1 Intermediate Shell Plate 5012-3 0.11 0.66 -13'F l l Lower Shell Plate B5013-1 0.14 0.58 0*F Lower Shell Plate 85013-2 0.10 0.51 30'F Lower Shel! Plate B5013-3 0.10 0.55 15'F Intermediate Shell Longitudinal Welds 2-442A, B & CS) 0.199 0.846 -50*F Lower Shell Longitudinal Welds 3-442A, B, & CM) 0.213 0.867 -50 F Circumferential Weld 9-4429) 0.051 0.096 -70*F I McGuire 1: Surveillance Program Weld Metal 0.198 0.874 - Diablo Canyon 2: Surveillance Program Weld Metal 0.219 0.867 - Notes: (a) The initial RTwor ( I.e . RT wonu> ) values for the plates and welds are measured values. (b) The intermediate shell weld seams 2-442A, B & C were fabricated with weld wire heat number 20291
! & 12008, Flux Type 1092 Lot Number 3854. The intermediate to lower shell circumferential weld seam 9-442 was fabricated with weld wire heat number 83640 Flux Type 0091 Lot Number 3490. c The lower shell longitudinal weld seams 3-442A, B & C were fabricated with weld wire heat numbers {
21935 & 12008, Flux Type 1092 Lot Number 3889. The McGuire Unit 1 surveillance weld metal was ! made with the same weld wire heat as the intermediate shell longitudinal weld seams, while the Diablo Canycu Unit 2 surveillance weld metal was made with the same weld wire heat as the lower shell longitudinal weld seams (Justification in WCAP-13949, ref. 4). Per Regulatory Guide 1.99, Revision 2, ' weight percent copper" and " weight percent nickel" are the best-estimate values for the material, which will normally be the mean of the measured values for a plate or forging or for weld samples made with the weld wire heat number that matches the critical vessel weld. l l l l
' E r McGuire Unit 1 February 1998
FOR INFORMATION nm vatI 5 NEUTRON FLUENCE VALUES The calculated fast neutron fluence (E > 1.0 MeV) values at the inner surface of the McGuire Unit 1 reactor vessel for 34 EFPY and 50.3 EFPY are shown in Tables 2 and 3, respectively. These values were projected using the results of the Capsule Y radiation analysis. See Section 6.0 of the Capsule Y dosimetry analysis report, WCAP-14993Dl. Table 2 Fluence (E > 1.0 MeV) on the Pressure Vessel Clad / Base Interface for McGuire Unit 1 @ 34 EFPY (EOL) MATERIAL LOCATION FLUENCE Intermediate Shell Plate B5012-1 45' 1.96 x 1019 n/cm2 Intermediate Shell Plate B5012-2 45" 1.96 x 1019 n/cm2 Intermediate Shell Plate B5012-3 45' 1.96 x 101 9 n/cm2 Lower Shell Plate B5013-1 45* 1.96 x 1019 n/cm2 Lower Shell Plate E>5013-2 45* 151 x 1019 n/cm2 Lower Shell Plate B5013-3 45' 1.96 x 1019 n/cm2 Intermediate Shell Longitudinal 0* 1.23 x 1019 n/cm2 Weld Seam 2-442A (0* Azimuth) Intermediate Shell Longitudinal 30* 1.74 x 1019 n/cm2 Weld Seam 2-4428 (120* Azimuth) Intermediate Shell Longitudinal 30* 1.74 x 1019 n/cm2 , Weld Seam 2-442C j (240* Azimuth) Intermediate to Lower Shell Cirumferential 45* 1.96 x 1019 n/cm2 , Weld Seam 9-442 Lower Shell Longitudinal Weld 30* 1.74 x 1019 n/cm2 l Seams 3-442A & C (60* & 300* Azimuth) l Lower Sheh Longitudinal Weld
- o. 1.23 x 1019 n/cm2 f Seam 3-442B (180* Azimuth) l I
l i Evaluation of PTS for McGuire Unit 1 February 1998 l
il . FOR It:rogdATION ONLY Table 3 Fluence (E > 1.0 MeV) on the Pressure Vessel Clad / Base Interface for l McGuire Unit 1 @ 60.3 EFPY MATERIAL LOCATION FLUENCE Intermediate Shell Plate B5012-1 45* 2.88 x 1019 n/cm2 Intermediate Shell Plate B5012-2 45* 2.88 x 1019 n/cm2 l Intermediate Shell Plate B5012-3 45* 2.88 x 1019 n/cm2 Lower Shell Plate B5013-1 45* 2.88 x 1019 n/cm2 Lower Shell Plate B5013-2 45* 2.88 x 1019 n/cm2 Lower Shell Plate 85013-3 45* 2.88 x 1019 n/cm2 Intermediate Shell Longitudinal 0* 1.81 x 1019 n/cm2 Weld Seam 2-442A (0* Azimuth) Intermediate Shell Longitudinal 30* 2.56 x 1019 n/cm2 i Weld Seam 2-4428 (120* Azimuth) Intermediate Shell Longitudinal 30* 2.56 x 1019 n/cm2 Weld Seam 2-442C (240* Azimuth) . Intermediate to Lower Shell Cirumferential 45* 2.88 x 1019 n/cm2 Weld Seam 9-442 Lower Shell Longitudinal Wold l 30* 2.56 x 1015 n/cm2 Seams 3-442A & C (60* & 300* Azimuth) Lower Shell Longitudinal Weld O' 1.81 x 1019 n/cm2 Seam 34428 (180* Azimuth) _ l Evaluation of PTS for McGuire Unit 1 February 1998
I FOR INFORMATinN n10mY
~
6 DETERMINATION OF RTers VALUES FOR ALL BELTLINE REGION MATERIALS Using the prescribed PTS Rule methodology, RTers values were generated for all beltline region materials of the McGuire Unit 1 reactor vessel for fluence values at the EOL (34 EFPY) and for life extension at 50.3 EFPY. Each plant shall assess the RTets values based on plant-specific surveillance capsule data. For McGuire Unit 1, the related surveillance program results have been included In this PTS evaluation. In addition, surveillance weld data from Diablo Canyon Unit 2 has been included based on the justification performed in Reference 4. Specifically, the McGuire Unit 1 plant- , specific surveillance capsule data for the intermediate shell plate B5012-1 and weld metals and the Diablo Canyon Unit 2 weld metal data is provided for the following reasons: ! I
- 1) There have been five capsules removed from the McGuire Unit 1 reactor vessel.
- 2) The full margin term is used (for the McGuire Unit 1 surveillance capsule data only) since the surveillance capsule data is not credible (per Appendix of Reference 5).
y l
- 3) The Diablo Canyon Unit 2 surveillance weld data is credible (See Appendix D of g g.
Reference 5). % 'g M bQ As presented in Table 4, chemistry factor values for McGuire Unit 1 based on average copper and nickel weight percent were calculated using Tables 1 and 2 from 10 CFR 50.61N. Additionally, chemistry factor values based on credible surveillance capsule data are calculated in Table 5. Tables 6 and 7 contain the RTers calculations for all beltline region materials at EOL , (34 EFPY) and 50.3 EFPY. l l luatio.i of PTS for McGuire Unit 1 February 1998
FOR INFORMAT1AN Table 4 Interpolation of Chemistry Factors Using Tables 1 and 2 of 10 CFR Part 50.61 Material Ni, wt % Chemistry Factor, 'F gtermediate Shell Plate 85012-1 0.61 74.2*F Given Cu wt% = 0.11 intermediate Shell Plate B5012-2 0.61 100.3*F Given Cu wt% = 0.14 intermediate Shell Plate B5012-3 0.66 74.9'F Given Cu wt% = 0.11 l Lower Shell Plate B5013-1 0.58 99.1*F I Given Cu wt% = 0.14 Lower Shell Plate 85013-2 0.51 65.0*F Given Cu wt% = 0.10 Lower Shell Plate B5013-3 0.55 65.0'F Given Cu wt% = 0.10 Intermediate Shell Longitudinal Welds,2-442A, B & C 0.65 201.3*F Given Cu wt% = 0.20 Lower Shell Longitudinal Welds 3-442A, B, &C 0.87 208.2*F Given Cu wt% = 0.21 CircumferentialWeld 9-442 0.10 37.5'F Given Cu wt% = 0.05 McGuire 1 Surveillance Weld Metal 0.87 204.2*F Given Cu wt% = 0.20 l Diablo Canyon 2 Surveitlance Weld Metal, 0.87 211.2*F Given Cu wt% = 0.22 t i I 1
.m 1 EvaluaSon of PTS for McGuire Unit 1 February 1998 '
)
- 12 FOR INFORMATION ONLY i Table 5 Calculation of Chemistry Factors Using Surveillance Capsule Data Per Regulatory Guide 1.99, Revision 2, Position 2.1
_ Material Capsule Capsule f 4 FFr2) ARTuorm FF2 FF*ARTuor intermediate Shell Plate U 0.4447 0.775 30.95 23.99 0.60 I B5012-1 X 1.424 1.098 33.51 36.79 1.21 i j V 1.94 0 1.181 81.01 95.67 1.39 (Longitudinal) Y 2.933 1.285 93.10 119.63 1.65 Intermediate Shelt Plate U 0.4447 0.775 48.44 37.54 0.60
! B5012-1
.X 1.424 1.098 60.69 66.64 1.21 V 1.940 1.181 74.60 88.10 1.39 granwse)
Y 2.933 1.285 108.58 139.53 1.65 SUM 607.89 9.70 CFasoi2., = UFF
- RTa) + UFF2) = (607.89) + (910) = 62.7'F latermediate Sheli U 0.4447 0.775 159.71(4) 123.77 0.60 Longitudinal Welds X 1.424 1.098 168.98(4) 185.54 1.21 242A B & C V 1.940 1.181 178.35(4) 210.63 1.39 Y 2.933 1.285 188.52(4) 242.25 1.65 SUM 762.19 4.85 CFm 942 = UFF
- R ruer) + UFF2) = (762.19) + (4.85) = 157.15'F Intermediate Shell U 0.357 0.716 172.10(44 123.22 0.51 Longitudinal Welds X 0.866 0.960 202.20ms) 194.11 0.92 3442A, B & C Y 1.32 1.077 210.40(44 226.00 1.16 (Using Diablo Canyon 2 SUM 543.93 2.59 Surveillance Data)
CFw u42 = UFF
- rte) + UFF2) = (543.93) + (2.59) = 210.01*F
'D (1) f = Measured fluence from capsule Y dosimetry analysis results, (x 10 n/cm2, E > 1.0 MeV).
(2) FF = fluence factor = f m2e.oiwo (3) ARTuorvalues are the measured 30 ft-lb shift values. (4) The surveillance weld metal ARTuorvalues have been adjusted by a ratio factor of 0.99. (5) Fluences and pre-adjusted ARTuoi values update per reference 7.
) Evaluation of PTS for McGuire Unit 1 February 1998
t i FOR INFORMATinN vrut n2 y 4 i Table 6 RTns Calculations for McGuire Unit 1 Beltline Region Materials at EOL (3A EFPY) Material f FF CF RTeam ARin3A Margin RTmm Intemi (*F) (*F) W (*F)
-_ _ _ _ _ediate Shell__Rate B501_2 _1_ _
, g _-- . .
. - _g _.-_g__ ______ .-_g__ _ _g __% _ _ g_ _ _ .
intermediate Shell Rate 85012 2 r1 n.s-1g 1.18 100.3 0 118.4 34 152 InteiiiMate ShellRate B5012 3 1E 1.18 74.9 -13 88.4 34 109 Lower Shell Rate B5013-1 12 1.18 99.1 0 116.9 34 151 Lower Shell Rate B5013-2 1.96 1.18 65.0 30 76.7 34 141 lower Shell Rate B5013-3 1.96 1.18 65.0 15 76.7 34 126 Intermediate shell tongitudinal Weid 1.23 1.06 201.3 -50 213.4 56 219 Seam 2-442A
-___ _ (0* Azimuth) intermediate Shell Longitudinal Weld u mr 1.74 1.15 201.3 50 231.5 56 238 Seams 2-4428 & C (1
-_ __ __ _20' Azimuth) intermediate to Lower Shell 1 wa 1.96 1.18 37.5 -70 44.3 44.3 19 Circumferential Weld Seam 9442 Lower Shell 1.ongitudinal Weld Seams 1.74 1.15 208 2 -50 239.4 56 245 3 442A & C(60* & 300* Azimuth
________________)_.- Using S/C Data _ 1.74 _ _ _ _ --1.15 ____ .-_____-_____.-_____-_ _ _ _ _ .._____. 210.0t9 -50 241.5 28 220 Lower Shell LongitudinalWeld Seam 1.23 1.06 208 2 -50 220.7 56 __ _ _ H2B y_ Azimuth [_ _ _ , , Using S/C Data 123 1.06 210.0i9 -50 222.6 28 _ _227 201 b9191 (1) (2) inital RTer values are rneasured values (see Table 1) RTns = RTeru + ARTns + Margin (*F) (3) ARins = CF
- FF.
(4) Based on Diablo Canyon Unit 2 surveillance capsule data (See Table 5).
-(5)
Since the {cGuire Surveillance Data is not credible,, a margin of 34*F for base rnetal and 56*F for welds will be used. t.A dM %\ L CM Nk *) \ 6dAh G5dk valuation of PTS for McGuire Unit 1 February 1998
l
'. 'o l
FOR INFnrmn. .14
~~'nnifuft()Qy Table 7 RTm Calculations for McGuire Unit i Beltline Region Materials at 50.3 EFPY !
Siatorial (al FF8' CF m Margin RTm" RTeru ARTmA (*F) (*F) (*F) j
. 128 74.2 34 95.0 34 163 I>
int
-_-_ermediate Shell P_ _______ late 85012-1
_ _ gg - _ _ _ __g__ _ _ _ _ _____________ ____ __ n 13J intermediate ShellPlate B5012-2 2.t.S 1.28 100.3 0 128.4 34 162 Intermediate Shell Plate B50124 2.88 128 74.9 -13 95.9 34 117 Lower Shen Plate B5013-1 2.88 1.28 99.1 0 126.8 34 161 Lower Shell Plate B5013-2 2.88 1.28 65.0 30 83.2 34 147 Lower Shen Plate B5013-3 2.88 1.28 65.0 15 83.2 34 132 Intermediate Sheh Longitudinal Weld 1.81 1.16 201.3 -50 233.5 56 240 Seam 2442A (0* Azimuth) Using S/C Data 1.81 1.16 157.2 -50 182.4 m i 1 intermediate Shen Longitudinal Weld 2.56 125 201.3 -50 251.6 56 258 l Seams 2 4428 & C l
~ (120* Azimuth)
-d n4 Intermediate to Lower Shell 2.88 128 37.5 -70 48.0 48.0 26 i Circumferential Weld Seam 9442 Lower Shell Longitudinal Weld Seams 2.56 1.25 208.2 -50 260.3 56 266 3442A & C(60* & 300* Azimuth)
I Using S/C Data 2.56 125 210.0W -50 262.5 28 241 i Lower ShelllongitudinalWeld Seam 1.81 1.16 208.2 -50 241.5 56 248
-____--____-__-)---_-
34428(180* Azimuth -__ _________--_____--..____________ - _ - _ - . Using S/C Data _ .81 1 1.16 210D9 -50 243.6 28 222 1 H91er (1) Inital RTet values are measured values (See Table 1) (2) RTm = RTmin + ARTm + Margin (*F) 2 0) ARTm = CF
- FF.
- 4) Based on Diablo Canyon Unit 2 surveillance capsule data (See Table 5).
Qk< 1
-((5) Since the McGuire Surveillance Data is not credible, a margin of 34*F for base metal and 56*F for welds will be used.
luation of PTS for McGuire Unit 1 February 1998
4 FOR INFORMATION ONIY15 4 7 CONCLUSIONS As shown in Table 6, all of the beltline region materials in the McGuire Unit i reactor vessel have EOL RTers values below the screening criteria values of 270*F for plates or forgings and longitudinal welds and 300*F for circumferential welds at EOL (34 EFPY). The RTers values remain below the screening criteria at 50.3 EFPY as shown in Table 7. i 1 l i
< ~ l
! Evaluation of PTS for McGuire Unit 1 February 1998 j
c FOR tuenn.. . is
" umv1ATION om y 8 REFERENCES
- 1. 10 CFR Part 50.61, " Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events," Federal Register, Volume 60, No. 243, dated December 19,1995.
- 2. Regulatory Guide 1.99, Rev;sion 2, " Radiation Embrittlement of Reactor Vessel Materials," U.S. Nuclear Regulatory Commission, May 1988.
- 3. WCAP-9195, " Duke Power Company William B. McGuire Unit 1 Reactor Vessel Radiation Surveillance Program," J. A. Davidson, et, al., November 1977.
- 4. WCAP-13949," Analysis of Capsule V Specimens and Dosimeters and Analysis of Capsule Z Dosimeters from the Duke Power Company McGuire Unit 1 Reactor Vessel Radiation Surveillance Program," Ed Terek, et. al., February 1994.
- 5. WCAP-14993, " Analysis of Capsule Y for Duke Power McGuire Unit 1 Reactor Vessel Radiation Surveillance Program," T. J. Laubham, et. al., December 1997.
- 6. WCAP-10786.," Analysis of Capsule U from the Duke Power McGuire Unit 1 Reactor Vessel Radiation Surveillance Program," S. E. Yanichko, et. al., February,1985.
- 7. WCAP-14363, " Analysis of Capsule Y for Pacific Gas and Electric Diablo Canyon Unit 2 Reactor Vessel Radiation Surveillance Program," P. A. Peter, et. al., August 1995.
I i I I g. 3 Evaluation of PTS for McGuire Unit 1 February 1998 , i ! L __ .__ I}}