ML20081J864

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RPV Surveillance Matls Testing & Analysis
ML20081J864
Person / Time
Site: LaSalle Constellation icon.png
Issue date: 03/22/1995
From: Branlund B, Carey R, Dias K
GENERAL ELECTRIC CO.
To:
Shared Package
ML20081J858 List:
References
GE-NE-523-A166, GE-NE-523-A166-1294, NUDOCS 9503280229
Download: ML20081J864 (67)
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{{#Wiki_filter:r i i e GE Nuclear Energy TechnicalServices Business GE-NE-523-Al66-1294 i GeneralElectric Company DRF 137-0010-7 175 Curtner Avenue, San Jose, CA 95125 March 1995 LASALLE UNIT 1 RPV SURVEILLANCE MATERIALS TESTING AND ANALYSIS u 4W 3 /22/95 Prepared by: I R. G. Carey, Engineer Engineering Senices Verified by: !).- J2 95 i K. P. Dias, Engineer Engineering Services Approved by:Q h %d. uz2A5 B. J. Branlund, Senior Engineer ~ RPV Integrity i 9503280229 950323 PDR ADOCK 05000373 P PDR +

r; ' lsj GE-NE-523-A166-1294 DRF 137-0010-7 + IMPORTANT NOTICE REGARDING CONTENTS OF THIS REPORT PLEASE READ CAREFULLY This report was prepared by General Electric solely for the use of Commonwealth Edison Company. The information contained in this report is believed by General Electric to be an accurate and true representation of the facts known, obtained, or provided to General Electric at the time this report was prepared. The only undertakings of the General Electric Company respecting information in this document are contained in the contract between the customer and General Electric Company, as identified in the purchase order for this report and nothing contained in this document shall be construed as changing the contract. The use of this information by anyone other than the customer or for any purpose other than that for which it is intended, is not authorized; and with respect to any unauthorized use, General Electric Company makes no representation or warranty, and assumes no liability as to the completeness, accuracy, or usefulness of the information contained in this document. - ii -

r. GE-NE-523-A166-1294 DRF 137-0010-7 TABLE OF CONTENTS P.Agt ABSTRACT vii ACKNOWLEDGMENTS siii 1. INTRODUCTION I 2.

SUMMARY

AND CONCLUSIONS 2 2.1 Summary ofResults 2 2.2 Conclusions 4 3. SURVEILLANCE PROGRAM BACKGROUND 5 3.1 Capsule Recovery 5 3.2 RPV Materials and Fabrication 5 3.2.1 Fabrication History 5 3.2.2 Material Properties ofRPV at Fabrication 6 3.2.3 Smveillance Capsule Specimen Chemical Composition 6 3.3 Specimen Description 6 3.3.1 Charpy Specimens 6 3.3.2 Tensile Specimens 7 4. PEAK RPV FLUENCE EVALUATION 13 4.1 Flux Wire Analysis 13 4.1.1 Procedure 13 4.1.2 Results 14 4.2 Determination ofLead Factor 14 4.2.1 Procedure 14 4.2.2 Results 15 4.3 Estimate of 32 EFPY Fluence 15 5. CHARPY V-NOTCH IMPACT TESTING 18 5.1' Impact Test Procedure 18 5.2 Impact Test Results 19 5.3 Irradiated Versus Unitradiated Charpy V-Notch Properties 19 5.4 Comparison to Predicted Irradiation Effects 20 5.4.1 Irradiation Shift 20 5.4.2 Change in USE 21 6. TENSILE TESTING 39 6.1 Procedure 39 6.2 Results 40 6.3 Irradiated Versus Unitradiated Tensile Properties 40 7. ADJUSTED REFERENCE TEMPERATURE AND 46 UPPER SHELF ENERGY 7.1 Adjusted Reference Temperature at 32 EFPY 46 7.2 Upper ShelfEnergy at 32 EFPY 47 8. REFERENCES 50 - iii -

r I.ik i;;:iI - GE-NE-523. A 166-1294. l DRF 137-0010-7 t a t . TABLE OF CONTENTS 1 APPENDICES A. IRRADIATED CHARPY SPECIMEN FRACTURE SURFACE A-1 PHOTOGRAPHS 1 B. LASALLE UNIT 1 VERSUS MAINE YANKEE AND KEWAUNEE B-1 i SURVEILLANCE PROGRAM MATERIAL ~ l 7 I t l l } I ? l l i l l 1 i 1 4 i - iv -

i-ll GE-hT-523-A166-1294 DRF 137-0010-7 TABLES Table Title Pagt 3-1 Chemical Composition of RPV Beltline Materials from 8 Fabrication CMTR Records 3-2 Mechanical Properties of Beltline and Other Selected 9 RPV Materials 3-3 Chemical Composition ofIrradiated Surveillance Specimens 10 4-1 Summary ofDaily Power History 16 4-2 Surveillance Capsule Flux and Fluence for 17 Irradiation from Start-up to 2/1/94 5-1 Vallecitos Qualification Test Results Using NIST Standard 22 Reference Specimens 5-2 Irradiated Charpy V-Notch Impact Test Results 23 5-3 Unirradiated Charpy V-Notch Impact Test Results 24 5-4 Significant Results ofIrradiated and Unitradiated Charpy 26 V-Notch Data 6-1 Tensile Test Results for Irradiated RPV Materials 41 6-2 Comparison of Unirradiated and Irradiated Tensile Properties at 41 Room Temperature 7-1 Beltline ART Values for LaSalle Unit 1 48 7-2 Upper Shelf Energy Analysis for LaSalle Unit 1 Beltline Material 49 -v-

r 1 GE-NE-523-A 166-1294 DRF 137-0010-7 ILLUSTRATIONS Ficure Title Page 3-1 Surveillance Capsule Holder Recovered from LaSalle Unit 1 11 3-2 Schematic of the RPV Showing Identification 12 of Vessel Beltline Plates and Welds 5-1 LaSalle Unit 1 Unirradiated Base Metal Impact Energy 27 5-2 LaSalle Unit 1 Irradiated Base Metal Impact Energy 28 5-3 LaSalle Unit 1 Irradiated and Unirradiated 29 Base MetalImpact Energy 5-4 LaSalle Unit 1 Unirradiated Base Metal Lateral Expansion 30 5-5 LaSalle Unit 1 Irradiated Base Metal Lateral Expansion 31 5-6 LaSalle Unit 1 Unirradiated Weld Metal Impact Energy 32 5-7 LaSalle Unit 1 Irradiated Weld Metal Impact Energy 33 5-8 LaSalle Unit 1 Irradiated and Unirradiated Weld Metal 34 Impact Energy 5-9 LaSalle Unit 1 Unirradiated Weld Metal Lateral Expansion 35 5-10 LaSalle Unit 1 Irradiated Weld Metal Lateral Expansion 36 5-11 LaSalle Unit 1 Irradiated HAZ Metal Impact Energy 37 5-12 LaSalle Unit 1 Irradiated HAZ Metal Lateral Expansion 38 6-1 Typical Engineering Stress-Strain for Irradiated 42 RPV Materials 6-2 Fracture Location, Necking Behavior and Fracture 43 Appearance for Irradiated Base Metal Tensile Specimens 6-3 Fracture Location, Necking Behavior and Fracture 44 Appearance for Irradiated Weld Metal Tensile Specimens 6-4 Fracture Location, Necking Behavior and Fracture 45 Appearance for Irradiated HAZ Metal Tensile Specimens l

  • N"

d GE-NE-523-A166-1294 DRF 137-0010-7 s ABSTRACT The surveillance capsule at 300 azimuth location was removed from the LaSalle Unit I reactor in Spring 1994. The capsule contained flex wires for neutron fluence measurement and Charpy and tensile test specimens for a material property evaluation. The flux wires were evaluated to determine the fluence experienced by the test specimens. Charpy V-Notch impact testing and uniaxial tensile testing were perfonned to establish the properties of the irradiated surveillance materials. Unirradiated Charpy base metal data was obtained from the manufacturers fabrication records and unirradiated Charpy weld metal data was obtained from fabricated specimen data together with two other plants with the same surveillance weld material; thus, applicable baseline data for base and weld metal was available. The irradiated Charpy data for the plate and weld specimens were compared to the unirradiated data to determine the shift in Charpy curves due to irradiation. The results are within the predictions of the Regulatory Guide 1.99 Revision 2. The irradiated tensile data for the plate and weld specimens are summarized. The room temperature irradiated data is compared with the unirradiated data to determine the effect of irradiation on the stress-strain relationship of the materials; only room temperature baseline data was available. The flux wire results, combined with the lead factor determined from the last fuel cycle, were used to estimate the 32 EFPY fluence. The resulting estimate was about 6% lower than the previous estimate of nominal 32 EFPY fluence. - vii -

f ,i. l a t GE-NE-523-A166-1294 - I f DRF 137-0010-7 I ACKNOWLEDGMENTS l The author gratefully acknowledges the efforts of other people towards completion of the l contents of this report. I Charpy testing was completed by G. P. Wozadio and G. E. Dunning. Tensile specimen j testing was done by S. B. Wisner and chemical composition analysis was performed by P. Wall. r Flux wire testing was performed by R. Kmger and R. Reager. i i I t .i L f i t l l t P - viii -

~. i ~,. j GE-NE-523-A166-1294 DRF 137-0010-7

1. INTRODUCTION Pan of the effon to assure reactor vessel integrity involves evaluation of the fracture j

toughness of the vessel ferritic materials. The key values which characterize a material's fracture toughness are the reference temperature of nil-ductility transition (RTNDT) and the upper shelf energy (USE). These are defined in 10CFR50 Appendix G [1] and in Appendix G of the ASME Boiler and Pressure Vessel Code, Section XI [2]. l l Appendix H of 10CFR50 [3] and ASTM E185-70 establish the methods to be used for surveillance of the LaSalle Unit I reactor vessel materials. In addition, compliance with ASTM E185-73 [4] has been established in the Final Safety Analysis Repon [5]. The first vessel l surveillance specimen capsule required by 10CFR50 Appendix H [3] was removed from LaSalle Unit 1 in Spring 1994. The irradiated capsule was sent to the GE Vallecitos Nuclear Center (VNC) for testing. The surveillance capsule contained flux wires for neutron flux monitoring and Charpy V-Notch impact test specimens and uniaxial tensile test specimens fabricated using I materials from the vessel materials within the core beltline region. The impact and tensile j specimens were tested to establish propenies for the irradiated materials. The results of the surveillance specimen testing are presented in this repon, as required per 10CFR50 Appendices G and H [1 & 3]. The irradiated material propenies are compared to i P ~ the unirradiated propenies to determine the effect ofirradiation on material toughness, through j Charpy testing. Irradiated tensile testing results are provided and a comparison with room temperature unirradiated data is performed to determine the effect ofirradiation on the i stress-strain relationship of the materials; only room temperature tensile baseline data was j available. l l -

GE-hT 523-A166-1294 [ DRF 137-0010-7 l

2.

SUMMARY

AND CONCLUSIONS 2.1

SUMMARY

OF RESULTS The 300" azimuth surveillance capsule was removed and shipped to VNC. The flux wires, f Charpy V-Notch and tensile test specimens removed from the capsule were tested according to i ASTM E185-82 [6]. The methods and results of the testing are presented in this report as j follows: a. Section 3: Surveillance Program Background i f b. Section 4: Peak RPV Fluence Evaluation f b. Section 5: Charpy V-Notch Impact Testing - i c. Section 6: Tensile Testing I f d. Section 7: Adjusted Reference Temperature and Upper Shelf Energy l 1 The significant results of the evaluation are below: i a. The 300' azimuth position capsule was removed from the reactor. The capsule j contained 9 flux wires: 3 copper (Cu),3 iron (Fe), and 3 nickel (Ni). There were 36 Charpy V-Notch specimens in the capsule: 12 each of plate material, weld material, and hcat affected zone (HAZ) material. The 6 tensile specimens removed { consisted of 2 plate,2 weld and 2 HAZ metal specimens. b. The chemical composition of copper (Cu) and nickel (Ni) for the irradiated f surveillance materials were determined from a chemical composition analysis. The values for the irradiated surveillance plate are 0.16% Cu and 0.64% Ni. The j values for the irradiated surveillance weld are 0.32% Cu and 0.99% Ni. I The purpo' e of the flux wire testing was to determine the neutron flux at the ] c. s surveillance capsule location. The flux wire results show that the fluence (from ) E >l MeV flux) received by the surveillance specimens was 0.897x1017 n/cm at 2 ] removal. 1 \\ \\ GE-NE-523-A166-1294 DRF 137-0010-7 i d. A neutron transport computation had been performed based on the performance of the first fuel cycle. Relative flux distributions in the azimuthal and axial directions were previously developed in Reference 19. The lead factor was 0.98, relating the surveillance capsule flux to the peak inside surface flux. e. The surveillance Charpy V-Notch specimens were impact tested at temperatures selected to defme the transition of the fracture toughness curves of the plate, weld, and HAZ materials. Measurements were taken of absorbed energy, lateral expansion and percentage shear. From absorbed energy and lateral expansion curve-fit results (f jlate and weld metal only), the values of USE and ofindex temperature for 30 ft-lb, 50 ft-lb and 35 mils lateral expansion (MLE) were obtained (see Table 5-4). Fracture surface photographs of each specimen are presented in Appendix A. f. The cmves ofirradiated Charpy specimens and unirradiated Charpy specimens established the 30 ft-lb index temperature irradiation shift and the decrease in USE. The surveillance plate material showed a measured 28.4 F shift and USE decrease of12.8 ft-lb (8% decrease). The weld materia showed a 34.9 F shift and a 12.0 ft-lb decrease in USE (10% decrease). 1 g. The measured shifts of 28.4 F for plate and 34.9 F for weld, for a fluence of O.897x1017 n/cm2, were within their respective Reg. Guide 1.99 [7] range predictions (ARTNDT 20) of-22*F to 46 F, and -29 F to 83 F. The chemical compositions for the irradiated surveillance materials were used for this calculation. h. The irradiated tensile specimens were tested at room temperature (70 F) and reactor operating temperature (550 F). Only room temperature unirradiated tensile test data were available for comparison. As expected the room temperature results show that in comparison to unitradiated data the irradiated data has increasing strength and decreasing ductility typical for irradiation embrittlement. i. The 32 EFPY fluence prediction is 4.5x1017 2 n/cm, based on the flux wire test and lead factor. This is about 6% lower than the previously established nominal 32 EFPY fluence prediction (4.8x1017 n/cm2 [19]) -

.. - ~.. _. I g GE-NE-523-A166-1294 l w DRF 137 0010-7 j. The adjusted reference temperature (ART = initial RTNDT + ARTNDT + Margin) l was predicted for each beltline material, based on the methods of Reg.. Guide 1.99, Rev. 2. The ART for the limiting material, weld heat 1P3571, at 32 EFPY is 84.6'F. i k. An update of the beltline material USE values at 32 EFPY was performed usmg .f the Reg. Guide 1.99, Rev, 2 methodology. The irradiated USE for all belthne materials will remain well above 50 ft-lbs through 32 EFPY. l l

2.2 CONCLUSION

S The requirements of 10CFR50 Appendix G [1] deal basically with vessel design life conditions and withlimits of operation designed to prevent brittle fracture. However, based on the evaluation of surveillance testing results, and the associated analyses, the following f conclusions are made: i i a. The 30 ft-lb shifts and decreases in USE measured are less than Regulatory Guide - f 1.99 Revision 2 predictions with associated deviations. I b. ' The values of ART and USE for the reactor vessel beltline materials are expected j to remain within limits in 10CFR50 Appendix G [1] for at least 32 EFPY of operation. i t 1 i l i l l ! t l

ll GE-NE-523-A 166-1294 DRF 137-0010-7

3. SURVEILLANCE PROGRAM BACKGROUND 3.1 CAPSULE RECOVERY The reactor pressure vessel (RPV) surveillance program consists of three surveillance capsules at 30,120*, and 300* azimuths at the core midplane. The specimen capsules are held against the RPV inside surface by a spring loaded specimen holder. Each capsule is expected to receive equal irradiation because of core symmetry. During the Spring 1994 outage, the 300*

positioned capsule was removed. The capsule was cut from its holder assembly and shipped by cask to the GE Vallecitos Nuclear Center (VNC), where testing was performed. Upon arrival at VNC, the capsule basket was examined for identification. The hole patterns stamped on the basket corresponded to basket number 1 and reactor number 41, as specified by GE drawings 117C4942 (drilled hole pattern) and 117C4936 (holder) for the LaSalle Unit 1300 surveillance capsule materials. The general condition of the basket as received is shown in Figure 3-1. The basket contained three impact (Charpy) specimen capsules and three tensile specimen capsules. Each Charpy specimen capsule contained 12 plate, weld, or HA2 Charpy specimens and 3 flux wires (one iron, one copper, and one nickel) in a sealed helium environment. Each tensile specimen capsule contained two tensile specimens. 3.2 RPV MATERIALS AND FABRICATION 3.2.1 Fabrication Historv The LaSalle Unit 1 RPV is a 251 inch diameter BWR/5 design. Construction was performed by Combustion Engineering (CE) to the Winter 1969 Addenda of the 1968 edition of the AShE Code [21]. The shell and head plate materials are AShE SA533, Grade B, Class 1 low alloy steel (LAS) [23]. The nozzles and closure flanges are AShE SA508 Class 2 LAS, and the closure flange bolting materials are AShE SAS40 Grade B24 LAS [23] Submerged arc or shielded metal arc welding of plates was followed by post-weld heat treatment at i I50 F for at least one hour per inch of thickness. The fabrication impact test specimens were given a j simulated post weld heat treatment at 1150 F for 40 hours, followed by furnace cooling to below 600'F,then air cooled. The identification of plates and welds in the beltline region is shown m Figure 3-2. 1.

i l l GE-NE-523-A166 1294 DRF 137-0010-7 3.2.2 Material Propenies of RPV at Fabrication Material cenification records were retrieved from GE Quality Assurance (QA) records to determine chemical and mechanical properties of the vessel materials. The retrieved information is documented in the FSAR [5] and in GE P-T Curve report [15]. Table 3-1 [21] shows the j chemistry data for the beltline materials. Properties of the beltline materials and materials at other I locations ofinterest are presented in Table 3 2. i 3.2.3 Surveillance Caosule Soecimen Chemical Comoosition l l Samples were taken from the surveillance plate and weld tensile specimens after they were l tested. Chemical analyses were performed using a Spectraspan III plasma emission spectrometer. [ Each sample was dissolved in an acid solution to a concentration of 40 mg steel per mi solution. [ The spectrometer was calibrated for determinatien of Mn, Ni, Mo, Cr, and Cu by diluting f NationalInstitute of Standards and Technology (NIST) Spectrometric Standard Solutions. The j phosphorus calibration involved analysis of four reference materials from NIST with known phosphorus levels. Analysis accuracies are.+0.005% (absolute) of reported value for phosphorus and 5% (relative) of reported value for other elements. The chemical composition results are given in Table 3-3 for the surveillance plate and weld materials. 3.3 SPECIAEN DESCRIPTION i The surveillance capsule holder contained 36 Charpy specimens: base metal (12), weld metal (12), and HAZ (12). There were 6 tensile specimens: base metal (2), weld metal (2), and HAZ (2). The holder contained 9 flux wires: 3 iron,3 nickel, and 3 copper. The chemistry and fabrication history for the Charpy and tensile specimens are described in this section. Surveillance l program design information is discussed in GE report [11]. 3.3.1 Charov Specimens l The fabrication of the Charpy specimens is described in the CE drawings [8] on the surveillance test program. All materials used for surveillance were beltline materials. The base metal specimens were cut from Heat C6345-1. The test plates received the same heat treatment as the fabrication specimens for Heat C6345-1, including the post-weld heat treatment for 40 hours at 1150 F +/- 25'F. The Charpy specimens were removed from -

GE-NE-523-A 166-1294 DRF 137-0010-7 Heat C6345-1 and machined as described in Section 2.2 of GE report [11]. Specimens were machined from the 1/4 T and 3/4 T positions in the plate, in the longitudinal orientation (long axis l parallel to the rolling direction). The base metal Charpy specimens from the surveillance capsule had been stamped on one end with the fabrication codes designated to LaSalle Unit 1. These unique specimen identifications are among those listed in GE repon [11]. The weld metal and HAZ Charpy specimens were fabricated by welding together two pieces of the surveillance test plates Heat C6345-1 and C6318-1 with the same weld procedure that was used to produce the limiting beltline longitudinal weld. Actual welding records obtained i from CE show the surveillance weld to be submerged arc weld with heat IP3571, Linde 1092 Flux, and Lot 3958. The welded test plate for the weld and HAZ Charpy specimens each received stress relief heat treatment at 1150'F +/- 25'F for 40 hours to simulate the fabrication specimen conditions. The weld specimens and HAZ specimens were cut from the material as shown in Figure 2-1 of GE report [11] at various depths through the thickness avoiding the volume near the root of the welds. The base metal orientation in the weld and HAZ specimens was longitudinal. The specimens were stamped on one end with the correct fabrication code. These unique identifications are among those listed in GE report [11]. 3.3.2 Tensile Soecimens Fabrication of the surveillance tensile specimens is also described in the CE surveillance specimen drawings [8]. The materials, and thus the chemical compositions and heat treatments for the base, weld, and HAZ tensiles are the same as those for the corresponding Charpy specimens. The identifications of the base, weld, and HAZ tensile specimens and a summary of [ the fabrication methods can be found in GE report [11]. l a

y GE-NE-523-A166-1294 DRF 137-0010-7 Table 3-1 CHEMICAL COMPOSITION OF RPV BELTLINE MATERIALS FROM FABRICATION CMTR RECORDS' ComDosition by Weight Percent i

identificatlee Hest /imt No. _,C,,, Mn J,,, S Si .29, JL, ,Cg, lewer Shell Plates: G-5683 1 C5978-1 0.21 1.42 E012 R913 0.19 RSS 6.53 9.11 G-5643-2 C5970-2 9.29 1.40 9.910 0.013 0.26 0.59 0.55 S.11 G-5683-3 C5979-I 0.22 1.35 0.014 0.913 0.29 9.66 E56 0.12 lewer-Intermediate Shell Plates: G-56041 C6345-1 0.14 1.24 1 911 ROIS 6.20 0.49 e.46 9.15 G-5644 2 C6318-1 0.20 1.22 E012 0.914 0.18 8.51 9.46 9.12 G-5604 3 C6345-2 8.17 1.23 0.012 0.014 0.20 0.51 0.47 0.15 Middle Plates: G-5605-I A5333-1 0.22 1.34 Etli Rel2 0.24 9.54 R49 0.12 G-5645-2 B0078-1 0.20 1.32 0.011 0.015 0.19 8.54 147 0.15 G-5605-3 C6123 2 0.20 1.34 E919 0.015 0.20 E68 0.49 8.13 Surveillence Plate: C6345-1 see above for the plate with the same heat number l WELDS Middle Vertical 3-308 A,B,C 395424, Flus 1992,let 3889 e.13 1.46 S.013 0.010 0.18 8.64 0.52 0.30 IP3571.Mui 1992.let 3958 0.12 1.31 0.017 0.011 R23 0.75 0.51 0.37 Lewer-Inter. Vert. 4' 4-308 A,B.C 305414, Flus 1992,let 3947 0.14 1.45 Rel2 Role 0.18 9.59 8.51 0.33 12908 Flusit92let3947 0.12 1.32 e.012 Roll 0.18 8.74 8.50 0.28 Lower Vertical 2-307 A,B,C 21935, Flus 1992,1e4 3889 0.13 1.33 E916 0.011 0.14 0.68 E55 0.21 12006, Run 1992,let 3889 8.11 1.81 0.0 011 0.009 0 04 1.0 0.46 0.27 f Mid to lewer-Inter. 6-308 6329637, Flus 1092,1st 3999 0.14 1.15 0.011 0.014 0.19 1.t* 9.53 0.24 lower to fewer-Inter. 1-313 AP6519, Flus IU92,let 0653 0.12 1.35 0.999 0.009 0.16 0.96 0.47

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Surveillance Weld: IPJ571, Flus 1992,let 3958 see shove for the weld with the some heat number I l l

  • Data from 92-Ol l21)
  • Assesmed value, since Ni content was mit recorded i

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,L-b y GE-hT-523-A166-1294 ~ f DRF 137-0010-7 Table 3-2 l MECHANICAL PROPERTIES OF BELTLINE l AND OTHER SELECTED RPV MATERIALS Initial ID. Heat RTwar Location h Number _( E) { Belthne ; a ) Lower Shell Plates G-5603-1 C5978-1 14 i G-5603-2 C5978-2 23 f G-5603-3 C5979-1 10 LowerIntermediate G-5604-1 C6345-1 -20 ShellPlates G-5604-2 C6318-1 -20 G-5604-3 C6345-2 -20 i' Middle G-5605-1 A5333-1 -10 G-5605-2 B0078-1 -10 i G-5605-3 C6123-2 -10 i Venical Welds 3-308 305424 -50 t IP3571 -30 4-308 305414 -50 t 12008 -50 2-307 21935 -50 l 12008 -50 l Girth Welds 6-308 6329637 -50 l-313 AP6519 : i Non-Beltline ; { a Vessel Flange 2V-659ATF 20 l Feedwater Nozzle Q2Q14VW 40 Bottom Head Dollar Plate C6003-3 58 Closure Studs 14716 LST = 70 a Test data information from the 92-01 [21) l l

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..l' GE-NE-523-A166-1294 DRF 137-0010-7 Table 3-3 l CHEMICAL COMPOSITION OF 1RRADIATED SURVEILLANCE SPECIMENS Comoosition by Weinht Percent 'i Identification ._hia_ P __Cr_ Ni _Ma _Cy_ PLATE: Charpy B-417 1.82 0.015 0.30 0.64 0.57 0.16 Charpy B-433 1.86 0.015 0.38 0.77 0.58 0.19 - Charpy B-435 1.90 0.016 0.34 0.62 0.60 0 15 Charpy B-411 0.60 0.16 i Charpy B-4J1 0.61 0.16 Charpy B-436 0.60 0.15 i Charpy B-437 0.60 0.15 Charpy B-4J5 0.62 0.15 Charpy B-4JC 0.62 0.16 Charpy B-4J6 0.67 0.17 Charpy B-43B 0.65 .0.17 Charny B-413 0.65. 0 17 Average 0.64 0,16 l WELD Charpy W-443 2.00 0.017 0.15 1.40 0.94 0.40 Charpy W-44A 2.23 0.016 0.12 0.90 0.80 0.32 l Charpy W-45E 1.91 0.014 0.10 1.00 0.77 0.30 i Charpy W-444 0.93 0.31 Charpy W-44M 1.03 0.32 Charpy W-45K 0.90 0.30 Charpy W-45M 0.92 0.30 Charpy W-45D 1 13 0.36 Charpy W-447 0.90 0.30 i Charpy W-44F 0.94 0.30 Charpy W-44U 0.90 0.30 Charov W-4LD 0.90 0.30 Average 0.99 0.32 I 1

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?! GE-NE-523-A166-1294 DRF 137-0010-7 Vessel Flange l Upper Shell l s G i G l Upper s Intermediate 1 Shell fi///////////i> iiiiiiiiiiiiir risi risi l { Middle Shell f Plate Heats: A5333-1 B0078-1 @@ ] C6123-2 ' ) ( <//////////////////iiisibiisi,11,iii, !\\ ongitudinal Wel!ls Plate Heats: C6345-1 L Core j 3-308,4-308,2-307 l C6318-1 Beltline Lower Intermediate Shell Region C6345-2 s rCircumferential Girth; 1 I j f Welds: 6-308,1-313 u Lower Shell l Plate Heats: C5978-1 @ !@ h @@ l ) C5"'~2 C5979-1 Welds 5/lfif/17, / JJff //ffliff '/////////; Bottom Head Enclosure Figure 3-2. Schematic of RPV Showing Identification of Vessel Beltline Plates and Welds

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GE-NE-523-A166-1294 DRF 137-0010-7

4. PEAK RPV FLUENCE EVALUATION Flux wires removed from the 300 capsule were analyzed, as described in Section 4.1, to determine flux and fluence received by the surveillance capsule. The lead factor, determined as described in Section 4.2, was used to establish the peak vessel fluence from the flux wire results.

Section 4.3 includes 32 EFPY peak fluence estimates. 4.1 FLUX WIRE ANALYSIS 4.1.1 Procedure The surveillance capsule contained 9 flux wires: 3 iron,3 copper and 3 nickel. Each wire was removed from the capsule, cleaned with dilute acid, weighed, mounted on a counting card, and analyzed for its radioactivity content by gamma spectrometry. Each iron wire was analyzed for Mn-54 content, each nickel wire for Co-58 and each copper wire for Co-60 at a calibrated 4-cm or 10-cm source-to-detector distance with 170-cc Ge and 100-cc Ge(Li) detector systems. To properly predict the flux and fluence at the surveillance capsule from the activity of the flux wires, the periods of full and partial power irradiation and the zero power decay periods were considered. Operating days for each fuel cycle and the reactor average power fraction are shown in Table 4-1. Zero power days between fuel cycles are listed as well. From the flux wire activity measurements and power history, reaction rates for Fe-54 (n,p) Mn-54, Cu-63 (n,n) Co-60, and Ni-58 (n,p) Co-58 were calculated. The E >l MeV fast flux reaction cross sections were determined from past testing at Browns Ferry 3 [10), also a 251 inch,764 bundle plant, using multiple dosimeter and spectmm unfolding techniques. The cross sections for the iron, copper, and nickel wires are 0.213 barn,0.00374 barn, and 0.274 barn; respectively. These values are consistent with other measured cross section functions determined at GE's Vallecitos Nuclear Center from more than 65 spectral determinations for BWRs and for the General Electric Test Reactor using activation monitors and spectral unfolding techniques. These data functions are applied to BWR pressure vessel locations based on water gap (fuel to vessel wall) distances. The cross sections for >0.1 MeV flux were determined from the measured 1-to-0,1 MeV cross section ratio of 1.6..

e, il. i GE-NE-523-A166-1294 i DRF 137-0010-7 i . 4.1.2 Results f The measured activity, reaction rate and full-power flux results for the 300 surveillance i capsule are given in Table 4-2. The E >l MeV flux values were calculated by dividing the wire i reaction rate measurements by the corresponding cross sections, factoring in the local power. n/cm (E >l MeV), was obtained by l history for each fuel cycle. The fluence result,0.897x1017 2 multiplying the full-power flux value for copper by the operating time and full power fraction, j shown in Table 4-1. The accuracies of the values in Tables 4-2 for a 2o deviation are estimated j to be: i t 1 5% for dps/g (disintegrations per second per gram) i 110% for dps/ nucleus (saturated) j 30% for flux and fluence E >l MeV i 130% for flux and fluence E >0.1 MeV i 4.2 DETERMINATION OF LEAD FACTOR i i The flux wires detect flux at a single location. The wires will therefore reflect the power fluctuations associated with the operation of the plant. However, the flux wires are not necessarily at the location of peak vessel flux. A lead factor is required to relate the flux at the { wires' location to the peak flux. The lead factor is the ratio of the flux at the surveillance capsule j ~ to the flux at the peak inside surface location. The lead factor is a function of the core and vessel l geometry and of the distribution of bundles in the core. The lead factor that will be used was generated in GE report [19] for the vessel geometry, using a first cycle dosimetry analysis to j determine power shape and void distribution. The methods used to calculate the lead factor are mentioned below but discussed in detailin GE report [19]. No recent determination oflead factor has been performed making [19] the current analysis. 4.2.1 Procedure Determmation of the lead factor in I19] for the RPV inside wall was made using a combination of a two-dimensional and a ow mensional finite element computer analyses. The two-dimensional analysis of these establish. ^.ie relative azimuthal variation of fluence at the j vessel surface and 1/4 T depth. The one-dimensional analysis determined the relative variation of flux with elevation. The azimuthal and axial distribution results were combined to provide the f f ratio of flux, or the lead factor, between the surveillance capsule location and the peak flux locations. The procedure is discussed in more detail in [19]. l i i \\ } l,

Il GE-NE-523-A166-1294 DRF 137-0010-7 I 4.2.2 BgsyJls The lead factor for the peak location inside surface was determined in [19] to be 0.98. 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. 4.3 ESTIMATE OF 32 EFPY FLUENCE The inside surface fluence (f urf) at 32 EFPY is determined from the flux wire fluence s for 6.5 EFPY of 0.9x1017 n/cm2 (0.9 is.897 rounded up), using the lead factor of 0.98. The time period 32 EFPY is based on a 40-year operation at an 80% capacity factor. The resulting 32 EFPY fluence value at the peak vessel inside surface is: fsurf = 0.9x1017'(32/6.5)/0.98 = 4.5x10 17 /cm2 at the peak location n 2 i The peak surface fluence at 32 EFPY is about 6% lower than the nominal value (4.8x1017 n/cm ) that was calculated from the first cycle dosimetry as reported in GE report [19]. This may be due ~ to differences between the initial and current peripheral fuel. But in any case, this is within the 30% accuracy expected as reported in section 4.1.2. The 1/4 T fluence (f) is calculated according to the Reg. Guide 1.99 [7] equation: f= f urf(e-0.24x), (4.i) s where x = distance, in inches, to the 1/4 T depth. The vessel beltline lower-intermediate shell is 7.38 inches thick ordered,6.13 inches minimum requirement. The corresponding depth x taken from the minimum required thickness is 1.53 inches. Equation 4-1 evaluated for this value of x gives the 1/4 T value of 32 EFPY fluence: 17 n/cm2 Lower-Int. f = (0.6927)fsurf = 3.1x10 l i ll GE-NE-523-A166-1294 DRF 137-0010-7 Table 4-1

SUMMARY

OF DAILY POWER HISTORY l i date on date off days on full power fraction date on date off days on full power fraction [ l 4/1/84 2/28/85 334 0.563 4/1/90 4/30/90 30 0.9751 7/22/85 10/21/85 92 0.84 5/1/90 5/31/90 31 0.9913 { 12/24/85 6/1/86 160 0.749 6/1/90 6/26/90 26 0.9604 i 8/12/86 1/3/87 145 0.774 7/1/90 7/31/90 31 0856I l 9/18/86 9/30/86 13 0.2395 8/1/90 8/31/90 31 0 9364 10/1/86 10/31/86 31 0.8402 9/1/90 9/30/90 30 0.9441 l 11/1/86 11/30/86 30 0.9148 10/1/90 10/31/90 31 0 9902 12/1/86 12/31/86 31 0.8202 11/1/90 11/30/90 30 0.9687 1/1/87 1/31/87 31 0.7399 12/1/90 12S1/90 31 0.9744 2/1/87 2/28/87 28 0.4357 1/1/91 1/31/91 31 0.9726 f 3/1/87 3SI/87 31 0.3346 2/1/91 2/16/91 16 0.9102 4/1/87 4/30/87 30 0.585 3/1/91 3/31/91 31 0 5/1/87 5/31/87 31 0.5369 4/1/91 4/30/91 30 0 6/1/87 6/30/87 30 0 5/10/91 5/31/91 22 0.7058 7/1/87 7/31/87 31 0 6/1/91 6/30/91 30 0.9494 8/1/87 8/31/87 31 0 7/1/91 7/31/91 31 0.9713 9/14/87 9/30/87 17 0.533 8/1/91 8/31/91 31 0.9588 [ 10/1/87 10/31/87 31 0.8801 9/1/91 9/30/91 30 0.9837 11/1/87 11/30/87 30 0.8764 10/1/91 10/31/91 31 0821I i 12/1/87 12/31/87 31 0.6983 11/1/91 11/30/91 30 0.9696 1/1/88 1/31/88 31 0.9034 12/1/91 12S 1/91 31 0.9718 ( 2/1/88 2/29/88 29 0.9381 1/1/92 1/31/92 31 0.9745 1 3/1/88 3/13/38 13 0.8189 2/1/92 2/28/92 28 1.0138 4/1/88 4/30,88 30 0 3/1/92 3/31/92 31 0.836 l 5/1/88 5/J1/88 31 0 4/1/92 4/30/92 30 0.986 6/1/S8 6/30/88 30 0 5/1/92 5/31/92 31 0.9549 7n/88 7/31/88 25 0.39 6/1/92 6/30/92 30 0.9329 8/1/88 8/31/88 31 0.9133 7/1/92 7/31/92 31 0 8918 i 9/1/88 980/88 30 0.9486 8/1/92 8/31/92 31 0.8338 l 10/1/88 10/31/88 31 0.9681 9/1/92 9/30/92 30 0.7593 11/1/88 11/30/88 30 0.7576 10/1/92 10/31/92 31 0 l 12/1/88 12/31/88 31 0.8822 11/1/92 11/30/92 30 0 l 1/1/89 1/31/89 31 0.9645 12/1/92 12/31/92 31 0 5 2/1/89 2/28/89 28 0.983 1/1/93 1/31/93 31 0 j 3/1/89 3S 1/89 31 0.8365 2/2/93 2/27/93 26 0.5794 j 4/1/89 4/30/89 30 0.9677 3n/93 3 S 1/93 25 0.9339 5/1/89 5/31/89 31 0.9079 4/1/93 4/30/93 30 0.9056 L 6/1/89 6/30/89 30 0.9257 5/1/93 5/31/93 31 0.9475 l 7/1/89 7/31/89 31 0.9187 6/1/93 6/30/93 30 0.9536 j 8/1/89 8/31/89 31 0.9241 7/ID3 7/31/93 31 0.9644 j 9/1/89 9/15/89 15 0.9 8/1/93 8/31/93 31 0 9527 10/1/89 10/31/89 31 0 9/1/93 9/14/93 14 0.9355 l 11/1/89 11/30/89 30 0 10n/93 10/31/93 25 0.959 i 12/1/89 12/31/89 31 0 11/1/93 1180/93 30 0.9935 l 1/5/90 1/31/90 27 0.6555 12/li21 12/31/93 31 0.932 l 2/1/90 2/28/90 28 0.9595 1/1/94 1/22/94 22 0.9328 i 3/1/90 3/31/90 31 0.8785 2/1/94. 't/18/94 18 0.9214 i ! i i

.w 4 GE-NE-523-A166-1294 DRF 137-0010-7 Table 4-2 SURVEILLANCE CAPSULE FLUX AND FLUENCE FOR IRRADIATION FROM START-UP TO 2/1/94 Average Average Full Power Flux a Full Power Mux h Fluence Muenceh 2 2 2 Wire dps/g Element Reaction Rate (n/cm -s) (=/cm2-s) (n/cm ) (n/cm ) (Element) (at end ofIrradiation) Idos/ nucleus (saturated)1 E>l MeV E>0.1 MeV E>l MeV E>0.1 MeV Copper 0.538E04 16.520E-17 4.413E8 7.061E8 8.97E16 1.43E17 G1 i Iron G1 3.653E04 7.871E-17 3.703E8 5.925E8 7.52E16C 1.20E17C Nickel G1 51.740E04 9.140E-17 3.344E8 5.350E8 6.80E16C 1.09E17C Value used for fluence 8.97E16 1.43E17 a Full power flux, based on thermal power of 3323 Mwt b 1.6 times the E >l MeV result c Only copper is used to determine the fluence..-. ..~

.i c GE-NE-523-A166-1294 DRF 137-0010-7 l

5. CHARPY V-NOTCH D1 PACT TESTING The 36 Charpy specimens recovered from the surveillance capsule were impact tested at temperatures selected to establish the toughness transition and upper shelf of the irradiated RPV materials. Testing was conducted in accordance with ASTM E23-88 [12].

5.1 IMPACT TEST PROCEDURE The Vallecitos testing machine used for irradiated specimens was a Riehle Model PI-2 impact machine, serial number R-89916. The maximum energy capacity of the machine is 240 ft-lb, which produces a test velocity at impact of 15.44 ft/sec. The test apparatus and operator were qualified using NIST standard reference material specimens. The standards consist of sets of high and low energy specimens, each designed to fail at a specified energy at the standard test temperature of-40 F. According to ASTM E23-88 [12], the test apparatus averaged results must reproduce the NIST standard values within an accuracy of15% or 1.0 ft-lb, whichever is greater. The qualification of the Riehle machine and operator is summarized in Table 5-1. Charpy V-Notch tests were conducted at temperatures between -80 F and 300 F The cooling fluid used for irradiated specimens tested at temperatures below 70 F was ethyl alcohol. At temperatures between 70 F and 200 F, water was used as the temperature conditioning fluid. The specimens were heated in silicon oil above 200 F. Cooling of the conditioning fluids was done by heat exchange with liquid nitrogen; heating was done by an immersion heater. The bath of fluid was mechanically stirred to maintain uniform temperatures. The fluid temperature was measured with a calibrated thermocouple. After equilibration at the test temperature for at least 5 I minutes, the specimens were manually transferred with centering tongs to the Charpy test machine and impacted in less than 5 seconds. For each Charpy V-Notch specimen the test temperature, energy absorbed, lateral expansion, and percent shear were evaluated. In addition, for the irradiated specimens, photographs were taken of fracture surfaces. Lateral expansion and percent shear were measured according to specified methods [12]. Percent shear was determined using method number 1 of Subsection 11.2.4.3 of ASTM E23-88 [12], which involved measuring the length and width of the i i cleavage surface in inches and determining the percent shear value from Table 2 of ASTM E23-88 [12]. V GE-hT-523-A166-1294 DRF 137-0010-7 5.2 IMPACT TEST RESULTS Twelve Charpy V-Notch specimens each ofirradiated base, weld, and HAZ material were tested at temperatures (-80 F to 300 F) selected to define the toughness transition and upper shelf portions of the fracture toughness curves. The absorbed energy, lateral expansion, and percent shear data are listed for each material in Table 5-2. Plots of absorbed energy data for base, weld, and HAZ materials are presented in Figures 5-1 and 5-2; 5-6 and 5-7; and 5-11 respectively. Lateral expansion plots for base, weld and HAZ materials are presented in Figures 5-4 and 5-5; 5-9 and 5-10; and 5-12 respectively. The irradiated curves are plotted along with their corresponding unirradiated curve for base and weld metal in Figures 5-3 and 5-8. The fracture surface photographs and a summary of the test results for each specimen are contained in Appendix A. i The irradiated plate and weld energy and lateral expansion data and HAZ lateral expansion data are fit with the hyperbolic tangent function developed by Oldfield for the EPRI Irradiated Steel Handbook [13]: l Y = A + B

  • TANH [( T - To )/C),

where Y = impact energy or lateral expansion T = test temperature, and A, B, To and C are determined by non-linear regression. The TANH function is one of the few continuous functions with a shape characteristic oflow alloy steel fracture toughness transition curves. Typically the curve fits were generated by setting both shelves free. 5.3 IRRADIATED VERSUS UNIRRADIATED CHARPY V-NOTCH PROPERTIES Ideally, a shift in RTwr would be established by comparing the irradiated Charpy specimen data to baseline unirradiated Charpy data. This is possible for the LaSalle 1 surveillance 1 capsule plate (Heat C6345-1), where enough fabrication Charpy data exists to develop a full ] Charpy curve. This unirradiated plate data was fit to a TANH function as described in the previous section. - i

i-GE-NE-523-A 166-1294 DRF 137-0010-7 The fabrication data for the LaSalle I surveillance weld (Heat IP3571, Linde 1092 Flux, Lot 3958) only contains Charpy data points at +10 F. This does not allow for development of a full Charpy curve for the unirradiated weld material. To develop this curve, a data search of other reactor vessel surveillance programs containing welds fabricated with the same filler wire heat, flux, and flux lot was performed. The Maine Yankee [24] and Kewaunee [22] programs were found to contain unitradiated weld Charpy data meeting these conditions (Appendix B). This data along with the LaSalle +10'F data was fit to a TANH function as shown in Figure 5-6 and will be used as the baseline Charpy Energy curve for the LaSalle 1 surveillance weld. Chemical composition of the irradiated surveillance specimens was determined by taking samples from the surveillance plate and weld tensile and charpy specimens aner they were tested. The average chemical composition given in Table 3-3 for the irradiated surveillance plate and weld materials will be used for the comparison ofirradiation effects. Additional chemistry data exists for the surveillance weld, IP3571 in the Main Yankee and Kewaunee surveillance programs (see Appendix B). If all known data is used, the calculated chemistry factor for weld IP3571 is 231. If only the LaSalle I surveillance data is used, the calculated chemistry factor is 261. To be conservative, this report will use the higher chemistry factor (261) for determination ofirradiation effects. t The irradiated and unirradiated Charpy V-Notch data curves were used to estimate the values given in Table 5-4: 30 ft-lb,50 fl-lb and 35 MLE index temperatures, and the USE for the sets of base and weld metal irradiated material data and for the base and weld metal unirradiated [ material data. Transition temperature shin values are determined as the change in the temperature at which 30 n-lb impact energy is achieved, as required in ASTM El85-82 (6]. The resulting shifts in Charpy curves are discussed in the next section. 5.4 COMPARISON TO PREDICTED IRRADIATION EFFECTS i 5.4.1 Irradiation Shin The measured transition temperature shifts for the plate and weld materials were compared to the predictions calculated according to Regulatory Guide 1.99, Revision 2 [7]. The inputs and calculated values for irradiated shift are as follows: _i GE-NE-523-A166-1294 l DRF 137-0010-7 l i Plate: Copper = ' O.16 % i Nickel = 0.64 % l CF = 119 fluence = 0.9x1017 n/cm2 Reg. Guide 1.99 ARTNDT= 12 F Reg. Guide 1.99 ARTNDT 12cA(34 F) = 46*F max, -22 F min Measured 30 ft-Ib shift = 28.4 F Weld: Copper = 0.32 % Nickel = 0.99 % CF = 261 fluence = 0.9x1017 n/cm2 Reg. Guide 1.99 ARTNDT= 27 F t Reg. Guide 1.99 ARTNDT 2cA(56 F) = 83 F max, -29 F min Measured 30 ft-lb shift = 34.9 F The weight percents of Cu and Ni are based on averaging from Table 3-3. CF shown t above is the chemistry factors from Tables 1 or 2 of Reg. Guide 1.99. The fluence factor is 0.102. l The measured shifts from Table 5-4 of 28.4 F for the plate and 34.9*F for the weld are both l above the predicted shifts of 12"F and 27 F respectively, but are within the bounds (46*F max. -22 F min and 83'F max, -29 F min; respectively), of the Reg. Guide 1.99 prediction including uncertainty of 20). i 5.4.2 Gange in USE i Using the copper and fluence data above with Figure 2 ofReg. Guide 1.99, decreases m i USE of 9% are predicted for the plate and decreases in USE of 18% are expected for the weld. l The measured decrease in the USE value was 8% for the plate and 10% for the weld. The base and weld materials show (see Table 5-4) decrease in the USE value less than the Reg. Guide 1.99 j prediction. i i I.

i GE-NE-523-A166-1294 DRF 137-0010-7 j Table 5-1 VALLECITOS QUALIFICATION TEST RESULTS USING NIST STANDARD REFERENCE SPECIMENS l Test Energy Acceptable Specimen Bath Temperature Absorbed Range j klgntification Medium ( F1 (ft-lb) (ft-lb) Vallecitos HH-40 229 Ethyl Alcohol -40 75.0 Riehle Machine HH-40 384 Eth 1 Alcohol -40 74.5 (tested 6/28/94) HH-40 980 Eth 1 Alcohol -40 70.5 HH-401152 Eth 1 Alcohol -40 72.5 HH-401172 Ethyl Alcohol -40 210 Average 73.5 74.913.7 pass LL-39 080 Ethyl Alcohol -40 13.5 LL-39 095 Ethyl Alcohol -40 13.0 LL-39 631 Ethyl Alcohol -40 13.5 LL-39 775 Ethyl Alcohol -40 13.5 LL-39 930 Ethyl Alcohol 13 0 l Average 13.3 13.211.0 pass 4 i 1 i i.. i

-- ) . GE-NE-523-A 166-1294 DRF 137-0010-7 Table 5-2 IRRADIATED CHARPY V-NOTCH LMPACT TEST RESULTS. Test Fracture Lateral Percent Shear Specimen Temperature Energy Expansion (Method 1) Ic entification ("F) (ft-lb) (mils) (%) Base: 411 0 17.5 21.5 15 Heat C6345-1, 413 40 90.5' 75.5 38 Longitudinal, 417 -40 18.5 13.5 8 i f=0.9x1017 n/cm2 433 -20 19.0 15.5 14 435 -80 ' 6.0 8.0 4 436' 300 138.5 95.0-100 437 80 98.0 78.0 58 43B 30 69.0 61.0 28 4J1 120 129.5 82.0 81 4J5 10 50.0 42.0 25 4J6 200 140.0 84.0 100 4JC 60 58.0 51.0 35 Weld: 443 -40 19.5 19.5 20 Heat IP3671, 444 40 35.0 38.0 39 f=0.9x10f7 n/cm2 447 80 65.5 62.0 45 44A -80 5.5 9.5 9 44F 120 89.5 71.0 93 44M 300 107.0 84.0 100 l 44U 0 41.0 39.0 32 i 45D 200 101.0 84.0 100 45E -10 40.0 36.0 31 45K 20 48.0 37.0 43 45M 60 74.0 65.0 75 4LD 100 86.5 89.0 83 HAZ: 47A -30 51.0 39.0 27 f=0.9x1017 n/cm2 47B -80 26.5 17.5 19 47P 40 130.0 85.0 95 47U -40 38.5 34.0 29 473F 80 117.5 81.0 85 -4A3 30 89.0 60.0 84 4AA 300 123.5 92.0 100 4AB 120 131.5 87.0 100 4AD 10 86.0 66.0 53 l 4AU 200 140.0 88.0 100 4B2 -10 117.5 81.5 76 t 4B4 0 113.0 79.0 60 1

l

t 7 wi. GE-NE-523-A166-1294 DRF 137-0010-7 Table 5 UNIRRADIATED CHARPY V-NOTCH IMPACT TEST RESULTS l Test Fracture Lateral Percent Shear Specimen

  • Temperature Energy Expansion (Method 1)

Identification ( F) (ft-lb) (mils) (%) l Base:# 1 -80 8 4 0-Heat C6345-1, 2- -80 6 4 0 Longitudinal 3 -40 29 21 5 4 -40 15 13 0 5 -40 23 16 1 6 10 109 76 50 7 10 88 58 35 8 10 77 56 35 9 40 103 68 45 10 40 96 65 40 I1 40 122 77 60 12 110 147 84 100 13 110 147 82 100 14 160 151 87 100 15 160 165 94 100 Weld: Main Yankee

  • 1

-320 2.2 2 0 r 2 -150 3.4 3 1-3 -100 7.3 8 10 f 4 -75 14.9 14 10 5 -50 28.0 30 30 6 -35 32.9 39 30 l 7 -20 45.5 43 40 8 0 45.2 41 40 9 10 50.4 49 50 i 10 10 52.6 53 50 11 10 42.7 43 40 l 12 30 78.9 67 60 13 30 59.2 46 50 14 30 59.8 50 50 15 71 90.3 83 90-16 150 105.0 90 99 17 250 106.8 88 99 18 350 109.4 92 99 l 6 Weld: LaSalle 1 1 10 79 2 10 68 i 3 10 64 ' I.D.'s are listed for numbering only, i.e.1.D.'s were not preassigned Fabrication Charpy specimen data from Materials Cenification Report

  • parameters for hyperbolic tangent function are obtained from [13,24] for Maine Yank :',

Material Certification Report data for LaSalle 1, and [22] for Kewaunee

i .l i _4 GE-NE-523-A166-1294 DRF 137-0010-7 Table 5-3 Continued UNIRRADIATED CHARPY V-NOTCH IMPACT TEST RESULTS i l Test Fracture Lateral Percent Shear Specimen

  • Temperature Energy Expansion (Method 1)

Identification (*F) (ft-lb) (mils) (%) Weld: Kewaunee* 1 -200 3.0 3 3 2 -200 5.5 6 5 3 -200 7.0 6 5 4 -150 36.0 34 34 5 -150 15.0 16 17 6 -150 32.0 31 27 7 -100 11.5 13 9 8 -100 13.0 12 13 9 -100 20.0 18 14 10 -40 40.0 37 38 11 -40 41.0 37 43 12 -40 29.5 29 37 13 10 66.0 60 55 14 10 67.0 62 64 15 10 55.5 50 43 16 40 79.0 71 81 17 40 83.0 72 Si 18 40 45.0 73 66 19 75 97.5 82 90 i 20 75 92.0 77 89 21 75 102.5 87 96 22 210 125.0 98 100 23 210 126.5 98 100 24 210 126.0 99 100 t " 1.D.'s are listed for numbering only, i.e. I.D.'s were not preassigned b Fabrication Charpy specimen data from Materials Certification Repon 4

  • parameters for hyperbolic tangent function are obtained from [13 24] for Maine Yankee Material Certification Repon data for LaSalle 1, and [22] for Kewaunee

E to GE-NE-523-A166-1294 DRF 137-0010-7 Table 5-4 t SIGNIFICANT RESULTS OF 1RRADIATED AND UNIRRADIATED CHARPY V-NOTCH DATA I Index Index Temperature Temperature Index Upper Shelf a l ( F) ( F) Temperature Energy Material E=30 fi-lb E=50 fi-lb MLE=35 mil (ft-lb) PLATE: Heat C6345-1, Longitudinal Unitradiated -37.51 -15.40 -17.05 153.3 / 99.7 Irradiated (f=0.9x10"n/cm ) -9.09 20,52 7.87 140.5/91 3 2 DifTerence 28.42 35.92 24.92 12.8 / 8.3 (8%) Reg. Guide 1.99, Rev 2 ARTer b: 12 1.99, Rev 2 % Decrease in USE c: (9%) Reg. Guide 1.99, Rev 2 (A12c) b: -22 to 46 WELD: Heat IP3571 'Unitradiated -48.85 -4.62 -30.25 119.2 l Irradiated (f=0.9x10"n/cm2) -13.93 31.95 4.61 107.2 Difference 34.92 36.57 34.86 12.0 (10 %) b Reg. Guide 1.99, Rev 2 ARTer : 27 1.99, Rev 2 % Decrease in USE C-(18%) Reg. Guide 1.99, Rev 2 (A 20) b: -25 to 83 HAZ: Heat C6345-1, Longitudinal i Irradiated (f=0.9x10"n/cm2) -66.27 -28.78 -34.89 132.6/ 86.2 l a USE values from longitudinal / transverse oriented Charpies; values are equal for weld metal. Longitudinal USE from data shown in Figure 5-3. Transverse plate USE is taken as 65% of the longitudinal USE, per USNRC MTEB 5-2 [17). b Determined in section 5.4.1 i c See section 5.4.2

.C 01 $f e ' be?UT U 8EL 0 0 4 00 3 00 y 2 gren a E t c F a p f ,e m ru I ta l 0 r 0 e a / 1 p t m e M eT e tse s T aB a ) d a t e a t d a a i n d e t i* 0 a m ri c r e i p n s U y p 1 ra t h i nC Un i o ei t l a 0 l 0 c ai 1 r S b a a L (F 1 -5 er u g i 00 F 2-o 0 0 0 0 0 0 0 0 t 6 4 2 0 8 6 4 f l 1 1 1 1 k5 v $ ;t E. .U*

L. I 180 160 140 120 g g b {100 U 0 t 80 - E. ^ 60 40 g O T 20 - 7 O mu a5 200 -100 0 100 200 300 100 p. g o os Test Temperature, *F S.' ?O au Figure 5-2. LaSalle Unit 1 Irradiated Base Metal Impact Energy

O m* h,d'd, egg n s U$ gs 00 4 0

lII, I!

. 5 3 d d e e e a il't t t s i ia a h e d d r S a a c t r r e d r r D n i I 0 n T 0 E U 3 R SU F '4 8 8 y 2 g - 0 r 5 e 2 n E t ca I it1. 0 p 0 m. 2 I la te M 0 ,j 5 1 F es [ a o e B / r u t a d 0 r e / 0 e t / p a - 1 m i e d / T a t. r sc r / T I 0 i / 5 d n / a o d l e t a / i 0 l d a r / r i n U 0 5 1 t inU _ e 0 l 0 l 1 a 1 S a L 0 3 5 1 5 1 erug i 0 F 0 2 G 0 0 0 0 0 0 0 0 N 6 4 2 0 8 6 4 I 1 1 1 1 ,@5 b:w j E-b? f I l.l1i ll

L a e 120 100 - [ ^ go. m .4 5 L g o g 60 - 0 I; 9 a Jo - 20 - -~~ O m es kU n C> -200 -100 0 IIMI 200 300 400 ? g Test Temperature,*F 8? (data at 60 'F was not used to generate cune) otj au Figure 5-4. LaSalle Unit 1 Unirradiated Base Metal Lateral Expansion (Fabrication Charpy specimen data)

  • L On,E suY >~ ?,' u s

t oWTOF8,?a 0 0 4 00 f i ilIi 3 n 00 o 2 is nap A x E F l ar ,r e ru t a t a L 0 r 0 ep l 1 m a e t y T e M tseT e s a B d e 4 j!.i, I ~ ta o i da rr I 1 t in U ^ e l 0 l 0 a 1 S 1 a L 5-5 e rug i 0 F 0 2 2 0 8 6 4 2 0 0 0 0 0 0 0 1 1

=

C3.E g 0 'Sn4 w e-a e e

1 i 140 0 120 - A A A 100 - s r c: e d 80 - sr as B E TANHFIT 60 - 3 g [$ e Kcwaunce a Maine Yankee 40 - 4-us LaSalle i e e l O 20 - l I ; A US i ' A i kO. a, O CI > -400 -300 -200 -100 0 100 200 300 400 y5 om Test Temperature, *F S' oO Figure 5-6. LaSalle Unit 1 Unirradiated Weld Metal Impact Energy 4*

L OH$aUi>5e' eu e$ GyoSoa 00 4 00 3 r' B H ( 2 y g r e n E 0 t 0 ca 1 p F m I 4 e l ru a A t t a e r M 0 e y i p a m d e l T -a e W t se T d e 0 t 0 a s 1 i da r r I 1 t 0 i 0 n 1 2 U e l la Sa L 0 03 7 5 e rug i 00 F 4 0 0 0 0 0 0 0 0 4 2 0 8 6 4 2 1 1 1 22t:Dt 5I~ . ww ' Il (

f k O1 .$5g?C$ T t agcy8g0 0 0 4 b l - tf 0 3 d - t e-d e a t e s a t t a f i a r i d l 1 h e i H c S r a I t t .O J e r r t i D d n r I n U y - E T g S R U r 'F e. n 9 94 E. 9 3 0 t 0 c 2 ap m. I la - teM. 0 0 d 1 le W F', d - e e - r t u a ta i [ r d 0 e p a m r e r T I d ts e n T a de 0 t .0 a. J' 1 ida - r.. r - in - U. 1 00 t 2 i nU e l la S a - L.. 0 03 8 - 5. e rug i F 00 4-0 0 0 0 0 0 0 O 4 2 0 8 6 4 2 1 1 1 2 nU$ 5I 4 4!' j

I 100 g [ A 90 - 80 - e 70 - g A =5 60 - a a j E 50 - -a ra E A TANIIFIT E 40 - d' a e Kcwaunce ~ e j e A Maine Yankee 30 - ^ 20 - y o I go _ m C 0 o W w, A A l

  • r! u U

C $> -400 -300 -200 -100 0 100 200 300 400 ?E oe Test Temperature,*F i PW vs Figure 5-9. LaSalle Unit 1 Unirradiated Weld Metal Lateral Expansion

- L.,. L 100 tk s Jb 80 - A O .= A h 60 - .g i 2 W W s. 40 - ag 5 A A J 20 - - -} o i 9 A ea EU 0 C; > -400 -300 -200 .IIm 0 100 200 300 400 yg oo Test Temperature,*F C.' ?!$ au Figure 5-10. LaSalle Unit 1 Irradiated Weld Metal Lateral Expansion

i L 004 0 03 0 2 y 0 g r en E t F c ap ,e m ru t I a 0 r l 0 e a p 1 t m e e T M ts Z eT / A i* H n d d eit sF e U t H a a f toN f i h A o 0 d )/ T a a r ta r D I 1 t i n U e l l a 0 S 0 a 1 - L 1 1 -5 er ug i 0 F 0 2-0 0 0 0 0 0 0 0 0 6 4 2 0 8 6 4 2 1 1 1 1 2 E@gM0EE i .t' l l ,!;ll.ll 1\\

s Om sd5EeLOu e$ c?oS?a ~ 004 003 n 6 0 o 0 i 4 a 2 s n p x E l F a r ,e e r t g u a ta L 0 r 0 e l p a 1 m t e e ^ T M ts e T Z A 4 I I d e ^ t r a 0 i d arr I 1 t in U 4 e l l 0 a 0 S 1 - a L 2 1 -5 e ru g i 00 F 2-0 0 0 0 g 0 0 0 0 o a 0 9 8 7 5 4 3 2 t 1 O=5 c9.EE0,tMa ewm' 2

.c of i GE-NE-523-A166-1294 DRF 137-0010-7

6. TENSILE TESTING Six round bar tensile specimens were recovered from the surveillance capsule. Uniaxial tensile tests were conducted in air at room temperature (70 F), and RPV operating temperature (550 F). The tests were conducted in accordance with ASTM E8-89 [14).

6.1 PROCEDURE All tests were conducted using a screw-driven Instron test frame equipped with a 20-kip load cell and special pull bars and grips. Heating was done with a Satec resistance clamshell furnace centered around the specimen load train. The test temperature was monitored and controlled by a chromel-alumel thermocouple spot-welded to an inconel clip that was friction-clipped to the surface of the specimen at its midline. Before the elevated temperature tests, a profile of the furnace was conducted at the test temperature ofinterest using an unirradiated steel specimen of the same geometry. Thermocouples were spot-welded to the top, middle, and bottom of a central 1 inch gage of this specimen. In addition, the clip-on thermocouple was attached to the midline of the specimen. When the target temperatures of the three thermocouples were within 5'F of each other, the temperature of the clip-on thermocouple was noted and subsequently used as the target temperature for the irradiated specimens. ~ All tests were conducted at a calibrated crosshead speed of 0.005 in/ min until well past yield, at which time the speed was increased to 0.05 inch / min until fracture. Crosshead displacement was used to monitor specimen extension during the test. The test specimens were machined with a minimum diameter of 0.250 inch at the center of the gage length. The yield strength (YS) and ultimate tensile strength (UTS) were calculated by dividing the nominal area (0.0491 in') into the 0.2% offset load and into the maximum test load, respectively. The values listed for the uniform and total elongation were obtained from plots that recorded load versus specimen extension and are based on a 1.5 inch nominal gage length. Reduction of area (RA) values were determined from post-test measurements of the necked specimen diameters using a calibrated blade micrometer and employing the following formula: RA = 100% * (Ao - Ar)/Ao After testing, each broken specimen was photographed end-on, showing the fracture surface, and lengthwise, showing the fracture location and local necking behavior. .a-GE-NE-523-A166-1294 DRF 137-0010-7 6.2 RESULTS Irradiated tensile test properties of Yield Strength (YS), Ultimate Tensile Strength (UTS), Reduction of Area (RA), Uniform Elongation (UE), and Total Elongation (TE) are presented in Table 6-1. A stress-strain curve for a 550 F base metal irradiated specimen is shown in Figure 6-1. This curve is typical of the stress-strain characteristics of all the tested specimens. The surveillance materials generally follow the trend of decreasing properties with increasing temperature. Photographs of the fracture surfaces and necking behavior are given in Figures 6-2 through 6-4. 6.3 IRRADIATED VERSUS UNIRRADIATED TENSILE PROPERTIES Only unirradiated room temperature tensile test data was available for comparison. As expected the trends are increasing YS and UTS and decreasing TE and RA (see Table 6-2), characteristic ofirradiation embrittlement in most cases.

d GE-NE-523-A166-1294 DRF 137-0010-7 Table 6-1: TENSILE TEST RESULTS FOR IRRADIATED RPV MATERIALS Test Yielda Ultimate Uniform Total Reduction i Specimen Temp. Strength Strength Elongation Elongation ofArea Number ( F) (ksi) (ksi) (%) (%) (%) Base: 4CB 70 65.1 85.4 11.3 20.9 70.4 4CK 550 57.9 83.4 9.2 17.9 67.4 Weld: 4DC 70 76.4 92.2 10.7 20.2 66.6 4DB 550 66.9 83.8 8.3 13.3 39.5 HAZ 4EE 70 66.1 87.7 8.2 '17.6 67.8 i 4E6 550 61.0 81.2 6.0 13.9 61.9 i a Yield Strength is determined by 0.2% offset. 7 TABLE 6-2 COMPARISON OF UNIRRADIATED AND IRRADIATED TENSILE PROPERTIES AT ROOM TEMPERATURE t Yield Strength Ultimate Strength Total Elongation Reduction of Area (ksi) (ksi) (%) (%) Base: Unirradiated' 61.8 81.9 28.3 64.9 Ist Capsule 65.1 85.4 20.9 70.4 Weld: Unirradiated 70.5 86.8 27.0 67.0 f 1st Capsule 76.4 92.2 20.2 66.6

  • Values taken as average of data in the material certification reports.

l h a

u 100.0 LASALLE RPV BASE 4CK 550* F 75.0 - h I E 50.0 - 1 .F m -I _c E w 25.0-O rn h 0.0 b 0.0 5.0 10.0 15.0 20.0 25.0 $w Engineering Strain, % yb 6E ea PO Figure 6-1. Typical Engineering Stress-Strain for Irradiated RPV Materials

GE-NE-523-A166-1294 DRF 137-0010-7 i a L], e

en a.

e - ~ -.. a

,.,Je

+ "t~ w w u u navr M Qy2ha g"A& w:4 m a :.,. .j p- -{ .] l 4CB 70 F 1 i ] ,.,:.e,n,to.i n,..m.- ~. ~,", . ~,.- I i ) 4CK 550cF a J U Figure 6-2 Fracture Location, Necking Behavior and Fracture Appearance il 1 for Irradiated Base Metal Tensile Specimens i _43 - )

i 4 .I GE-hT-523-A 166-1294 i DRF 137-0010-7 i I i E -93:$ ? ,% ct- ' I -t. r ,_ay,. -. _,__ _ 4.;i, .-.{ ,}

~~~

4DC 70:F 1 3 5 4 ) l .i i i i f .....a g p,~. e 3 W/A=m. +,.,. i f 4DB 4 5'); F i a i Figure 6-3 Fracture Location, Necking Behavior and Fracture Appearance 1 ) for Irradiated Weld Metal Tensile Specimens i J. I,____.__

.'l GE-NE-523-A 166-1294 DRF 137.n010.7 1 l l ~ 9.u, .;, 5 p. i 4.- 4. , jba F L ,-t ~.a.w,'.rp 4 W. 4 Iy4pgigspappo' 'in!npmppTf en:t +p!"optppin p I j . 47 l ~ ~. T ~ ' ,} . : 5. ~ :- j g g g% i ^" j .s 4EE ~0 F '4 1 ) J 1 - ?., -a i T '!' W, i 7{---- _1 ,7 ~. n. 25

a

./ p j ~, .? 's wvs [ ai R 1 I I i i Figure o-4 Fract 2re Locatien. Nechng Behavior and Fracture Appearance for Irradiated HAZ Metal Tensile Specimens - d

1 GE-NE-523-A166-1294 DRF 137-0010-7

7. ADJUSTED REFERENCE TEMPERATURE AND UPPER SilELF ENERGY The revised fluence value of 4.5x1017 2

n/cm in Section 4, which is about 6% lower than the current nominal fluence value of 4.8x1017 n/cm2 [19), is used in this section to revise the adjusted reference temperatures (ARTS) and upper shelf energy (USE). The new 32 EFPY fluence prediction at the 1/4 T location of 3.1x1017 2 n/cm is about 20% lower than that previously established of 3.9x1017 n/cm2 [19] in the GE P-T Curve repon [15]. This difference is high because an upper bound fluence was conservatively used in the previous analysis. 7.1 ADJUSTED REFERENCE TEMPERATURE AT 32 EFPY The impact on adjusted reference temperature (ART) due to irradiation in the beltline materials is determined according to the methods in Reg. Guide 1.99, Rev. 2 [7], as a function of l neutron fluence and the element contents of copper (Cu) and nickel (Ni). The specific relationship from Reg. Guide 1.99, Rev. 2 [7] is: ART = Initial RTNDT + ARTNDT + Margin (7-I) where: ARTNDT = [CF]*f(0.28 - 0.10 log f) (7-2) 2 2 Margin = 2*(oI + og )l/2 (7 3) CF = chemistry factor from Tables I or 2 of Reg. Guide 1.99, Rev. 2 [7], 2 f= 1/4 T fluence (n/cm ) divided by 1019, c1 = standard deviation on initial RTNDT. cA = standard deviation on ARTNDT,is 28 F for welds and 17 F for base material, except that og need not exceed 0.50 times the ARTNDT value. Once two sets of surveillance capsule data are available, the CF values in Reg. Guide 1.99, Rev. 2 [7] can be modined to reflect the results. However, this is only the first set of surveillance data from Unit 1, so only the results of the flux wire tests and the additional chemical analysis results for the surveillance capsule materials are factored into new beltline ART calculations. Each beltline plate and weld ARTNDT value is determined by multiplying the CF from Reg. Guide 1.99, Rev. 2 determined for the Cu-Ni content of the material, by the fluence factor for the EFPY being evaluated. The Margin term and initial RTNDT are added to get the ART of the material. The 32 EFPY ART values for all of the beltline plates and several of the most i GE-NE-523-A166-1294 DRF 137-0010-7 limiting beltline welds are shown in Table 7-1. The ART for the limiting beltline material, weld heat IP3571, at 32 EFPY is 84.6 F. 7.2 UPPER SHELF ENERGY AT 32 EFPY Paragraph IV.B of 10CFR50 Appendix G [1] sets limits on the upper shelf energy (USE) of the beltline materials. The USE must be above 50 fl-lb at all times during plant operation, assumed here to be up to 32 EFPY. Calculations of 32 EFPY USE, using Reg. Guide 1.99, Rev. 2 methods, are summarized in Table 7-2. The initial USE of the plates were obtained from [20]. The equivalent transverse USE of the plate material is taken as 65% of the longitudinal USE, according to USNRC MTEB 5-2 (17]. Unlike the plate, the weld metal USE has no transverse / longitudinal correction because weld metal has no orientation effect. Although the weld surveillance data shows the decrease in USE to be considerably less than the prediction for the corresponding copper content, the USE decrease prediction values from Reg. Guide 1.99 [7] l were used for the beltline welds and plates in Table 7-3. Based on the above results, the beltline materials will have USE values above 50 fl-lb at 32 EFPY, as required in 10CFR50 Appendix G [1]. The lowest USE predicted for 32 EFPY is 60.0 ft-lb (for weld heat IP3571). Most of the initial weld upper shelf energy data was based on 10*F measurements, however, since the USE 32 EFPY predicted from the unirradiated specimen USE TANH fit is 90.6 ft-lb (Table 7-3), the actual USE of the material is expected to be considerably higher. Since USE and ART requirements are met, irradiation effects are not severe enough to necessitate additional analyses or preparations for RPV annealing before 32 EFPY. Because adequate USE data is available and no 32 EFPY USE values approach 50 fl-lb, an equivalent margin analysis in accordance with BWR Owners' Group program [18] is not necessary. l i t

sf e

~ Table 7-1 I BELTLINE ART VALUIS FOR LASALLE UNIT I Middle end Imer-Intmed. Place Thicleerse = 6.13 inches 32 EFPY Peak I.D. fhsence = 4.5eE+ 17 n/cm' 32 EFPY Peak t/4 T thsence = 3.12E+ 17 m/cm' I m er Weld Thiciseess = 6.13 inches 32 EFPY Peak I.D. fhsence = 4.54E+ 17 nrem' 32 EFPY Peak 1/4 T fhsence = 3.12E+17 m/em' E Initial 32 EFPY 32 EFPY 32 EFPY l COMPONENT I.D. IIEAT OR HEAT / LOT %Os %Ni CF RTndt IMta RTndt Marghi shift ART 'F 'F 'F 'F 'F e PLATES: I m er G-5683-1 G-5683-1 C5978-1 9.11 9.58 74 14.0 16.6 16.6 33.2 47.2 G-5683-2 G-5603-2 C5978-2 0.11 0.59 74 23.0 16.6 16.6 33.2 56.2 - G-560&3 G-5603J (3979-1 e.12 0.66 84 10.0 18.9 18.9 37.7 47.7 e Imer-Inensed g C-5604-1 G-5604-1 C6345-1 0.16 9.64 119 -20.0 26.7 26.7 53.4 33.4 G-5604-2 G-5604-2 C6318-1 0.12 0.51 81 -29.0 18.2 18.2 36.4 16.4 - G-56044 G-5604J C6345-2 0.15 9.51 105 -29.0 23.6 23.6 47.1 27.1 Middle G-5605-1 G-5605-I A5333-1 e.12 0.54 32 -10.0 18.4 18.4 -36.8 26.8 G-5605-2 G-5605-2 B0078-l 0.15 0.50 105 -10.0 23.6 23.6 47.1 37.1 G-56054 G-56854 C6123-2 0.13 e.68 93 -10.0 20.9 20.9 41.8 31.8 I VERTICAL i WELDS: Middle Middle 395424 e.34 e.64 200 -58.9 44.9 44.9 89.8 39.8 g 3J00 3Je8 IP3571 0.32 261 -30.0 58.6 56.9 114.6 84.6 - m 9.99 Imer-Intmed lower-Intmed 395414 e.33 - e.59 204 -50.0 45.8 45.8 91.6 41.6 4J08 4J08 12988 8.28 e.74 209 -50.0 46.9 . 46.9 93.8 43.8 Lower Imwer 21935 0.21 0.68 177 -50.0 39.7 39.7 79.5 29.5 O& hd. 2J07 2J07 12006 e.27 1.00 249 -50.0 55.9 55.9 111.8 61.8 C> GIRTH WELD: pg 6J00 6-308 6329637 0.24 1.90 239 -50.0 53.7 53.7 107.3 57.3 o ch 1J13 1-313 AP6519 0.18 0.06 84 . 60.0 18.9 18.9 37.7 -22.3 '3E ?U M4

  • Chemical C, - Tshen from (hemistry Survestsace Capaule Specmeen Analysis in Section 3.2.3.Tshie 3J.

_.... - _ _. _ _.. _, _.,. -. _. -, _. ~. _.. _ -.... -. _ -, _. _ _ _ - _ _. - ~

.1 ! [ GE-NE-523-A166-1294 l DRF 137-0010-7 Table 7-2. UPPER SHELF ENERGY ANALYSIS FOR LASALLE UNIT I BELTLINE MATERIAL i INITIAL INITIAL

  • 32 EFPY8 l

TEST LONGIT. TRANS %DECR." TRANS. [ LOCATION HEAT TEMP. USE USE %Cu USE USE PLATES: Lower C5978-1 160 136 88.4

0. I 1 9.5 80.0 I

C5978-2 160 120 78.0 0.I1 9.5 70.6 C5979-1 160 136 88.4 0.12 10.0 80.0 Low-Int. C6345-1 160 165 107.3' O.16' 12.0 94.4 C6318-1 160 140 91.0 0.12 10.0 81.9 C6345-2 160 161 104.7 0.15 12.0 92.1 Middle A5333-1 160 155 100.8 0.12 10.0 90.7 l B0078-1 160 151 98.2 0.15 12.0 86.4 C6123-2 160 151 98.2 0.13 11.0 87.4 WELD: l Vertical j 3-308 305424 10 92 0.30 22.0 71.8 I d IP3571 10 79 0.32 24.0 60.0 4-308 305414 10 92 0.33 25.0 69.0 12008 10 92 0.28 21.0 72.7 2-307 21935 10 97 0.21 17.5 80.0 i 12008 10 97 0.27 20.5 77.1 i Unirradiated IP3571 USE I19.2* 0.32 24.0 90.6 l d { -TANH FIT Girth l 6-308 10137 10 108 0.23 18.0 88.6 i 6329637* 10 108 0.24 19.0 87.5 SP5622 10 112 0.13 13.0 97.4 1 2P5755 10 114 0.18 16.0 95.8 6329637* 10 103 0.19 16.5 86.0 51874 10 89 0.18 16.0 74.8 l-313 4P6519* 10 116 0.05 9.0 105.6 4P6519 ' 10 126 0.10 12.0 110.9 4P6519* 212 127 0.18 16.0 106.7 l

  • Values obtained from [20]
  • Values obtained from Figure 2 of[7] for 32 EFPY fluence = 4.5x10" n/cm,

2

  • Submerged arc welds with same heat but different flux.

d Chemical Composition taken from Chemistry Surveillance Capsule Specimen Analysis in i Section 3.2.3, Table 3-3.

  • Unirradiated Charpy V-Notch Data, Section 5.4.2, Table 5-4.

' This value is 65% of the highest 160*F data from the CMTR's. 8 32 EFPY Trans USE = Initial Trans USE * { l -(% Decrease USE /100)).

s ._i GE-NE-523-A166-1294 DRF 137-0010-7

8. REFERENCES

[1] " Fracture Toughness Requirements," Appendix G to Part 50 of Title 10 of the Code of Federal Regulations, July 1983. [2] " Protection Against Non-Ductile Failure," Appendix G to Section XI of the 1992 ASME Boiler & Pressure Vessel Code. [3] " Reactor Vessel Material Surveillance Program Requirements," Appendix H to Part 50 of Title 10 of the Code ofFederal Regulations, July 1983. [4] " Surveillance Test for Nuclear Reactor Vessels," ASTM El85-73, March 1973 [5] LaSalle Unit 1 Steam Electric Station Final Safety Analysis Repon, Section 5.3 [6] " Conducting Surveillance Tests for Light Water Cooled Nuclear Power Reactor Vessels," Annual Book of ASTM Standards, E185-82, July 1982. [7] " Radiation Embrittlement of Reactor Vessel Materials," USNRC Regulatory Guide 1.99, Revision 2, May 1988. [8] "LaSalle Unit 1 Surveillance Test Specimens", CE Drawing, VPF Numbers 2029-300-2. [9] Intentionally not used [10] Manin, G.C., " Browns Ferry Unit 3 In-Vessel Neutron Spectral Analysis," GENE, San Jose, CA, August 1980, (GE Repon NEDO-24793). [11] R. Carey, "LaSalle County Unit 1 Surveillance Program Evaluation," GENE, San Jose, CA, February 1995, (GE Repon GE-NE 523-154-1292). [12] " Standard Methods for Notched Bar Impact Testing of Metallic Materials," Annual Book of ASTM Standards, E23-88 [13] " Nuclear Plant Irradiated Steel Handbook," EPRI Report NP-4797, September 1986 [ GE-NE-523-A166-1294 DRF 137-0010-7 [14] " Standard Methods of Tension Testing ofMetallic Materials," Annual Book of ASTM Standards, E8-89. t [15] T. A. Caine, " LaSalle County Station Units 1 and 2 Fracture Toughness Analysis Per 10CFR50 Appendix G," GENE, San Jose, CA, March 1988, l i (GE Number SASR 88-10). [16] Intentionally not used [17] " Fracture Toughness Requirements," USNRC Branch Technical Position MTEB 5-2, Revision 1, July 1981. [18] Letter from James T. Wiggins to Mr. Lesley A. England, " Acceptance for Referencing of Topical Repon NEDO-32205, Revision 1, '10CFR50 Appendix G Equivalent Margin Analysis for Low Upper Shelf Energy in BWR/2 through BWR/6 Vessels," USNRC, Washington, D.C., December 8,1993. [19] T. A. Caine, " Flux Wire Dosimeter Evaluation for LaSalle Nuclear Power Station, Unit 1", GENE, San Jose, CA, July 1986, (GE Repon MDE-89-0786). [20] T. A. Caine," Upper ShelfEnergy Evaluation for LaSalle Units 1 and 2," GENE, San Jose, CA, June 1990, (GE Repon SASR 90-07). i [21] " CECO Response to Generic Letter 92-01, LaSalle County Station Units 1 and 2," Attachment C, June 15,1992. [22] Letter from C. R. Steinhardt to U.S. Nuclear Regulatory Commission, " Docket 50-305, Operating License DPR-43, Kewaunee Nuclear Power Plant, Reactor Vessel Structural Integrity," Wisconsin P6" rvice Corporation, Green Bay, WI, July 2,1992, (NRC-92-081). [23] LaSalle 1 Technical Specification. [24] Unirradiated Mechanical Properties ofMaine Yankee Nuclear Pressure Vessel Material," Effects Technology Inc., February 1975. GE-NE-523-A166-1294 DRF 137-0010-7 APPENDIX A 1RRADIATED CHARPY SPECIMEN FRACTURE SURFACE PHOTOGRAPHS i I Photographs of each Charpy specimen fracture surface were taken per the requirements of ASTM ) E185-82. The pages following show the fracture surface photographs along with a summary of i the Charpy test results for each irradiated specimen. The pictures are arranged in the order of i t base, weld, and HAZ materials. I r l i I l l l l J f ? i ? [ i A-1 I =

..'I GE-NE-523-A166-1294 DRF 137-0010-7 .r_.s BASE:435 BASE: 417 a Temo: -80 F Temp: -40 F Energy: 6 R-lb Energy: 18.5 R-lb MLE: 8 mils MLE: 13.5 mils Shear: 4% Shear: 8% BASE: 433 BASE: 411 Temp: -20 F Temp: 0 'F Energy: 19 R-lb Energy: 17.5 R-lb MLE: 15.5 mils ,m MLE: 21.5 mils Shear: 14 % b ~ y ,r Shear: 15 % BASE: 4J5 Temp: 10 F 5~ . gc + 3 EASE: 43B b ,T Temp: 30*F Energy: 50 R-lb f Energy: 69 R-lb i MLE: 42 mils 'A i MLE: 61 mils 1 Shear: 25 % Shear: 28 % B ASE: 413 BASE: 4JC (d Temp: 40 F 5 Temp: 60 F Energy: 90.5 R-lb [ Energy: 58 R-lb ~~'- MLE: 51 mils MLE: 75.5 mils Shear: 38 % -S Shear: 35 % ~ ' * ..-~ A-2

'i GE-NE-523-A166-1294 DRF 137-0010-7 i BASE:437 l' '[ ~ BASE: 4J1 Temp: 80 F 7 f Temp: 120 F j Energy: 98 ft-lb i' Energy: 129.5 ft-lb MLE: 78 mils MLE: 82 mils Shear 58 % Shear: 81 % 1 BASE: 4J6 BASE: 436 Temp: 200 F Temp: 300 F Energy: 140 R-lb J: Energy: 138.5 fl-lb MLE: 84 mils MLE: 95 mils Shear: 100 % eC~ Shear: 100 %

g. _ ~

._ ~ WELD: 44A 4 WELD: 443 Temp: -80 'F Temp: -40 *F Energy: 5.5 n-lb Energy: 19.5 ft-lh MLE: 9.5 mils MLE: 19.5 mils Shear: 9% Shear: 20 % WELD: 45E WELD: 44U Temp: -10 F ~ ' Temp: 0F Energy: 40 ft-lb Energy: 41 fl-lb s-c MLE: 36 mils Y,, MLE: 39 mils Shear: 31 % f '*h Shear. 32 % i A-3

J

GE-NE-523-A166-1294 DRF 137-0010-7 WELD: 45K Y ~ ) Temp: 20 F Temp: 40'F Energy: 48 ft-lb Energy: 35 ft-lb MLE: 37 mils Shear: 43 % Shear: 39*/o WELD: 45M Temp: 60 F 6/f Temp: 80 F Energy: 74 ft-lb Energ C M { MLE: 65 mils 62 mHs Shear: 75 % ~[* Shear: 45 % ~ WELD: 4LD ~ ^ w ,. < ' ' ' ~ ~, ELD: M 83 ~ 93 / l WELD: 450 MLD: 44M i 8 5 0 ' A-4

. _ - = / GE-NE-523-A166-1294 DRF 137-0010-7 '~ HAZ: 47B .;. 3,' ~ HAZ: 47U Temp: -80 F Temp: -40 *F Energy: 26.5 ft-lb Energy: 38.5 fi-lb MLE: 17.5 mils We ~, Ai MLE: 34 mils g_ Shear: 19 % Shear: 29 % HAZ: 47A HAZ: 4B2 Temp: -30 F ',f;g{c.f Temp: -10 *F ' [7 ,/ Energy: 51 ft-lb E Energy: 117.5 ft-lb i 'd[b MLE: 81.5 mils MLE: 39 mils Shear: 27 % w' m-Shear: 76 % .+. / HAZ: 4B4 HAZ: 4AD b Temp: 10*F Temp: 0F Energy: 86 ft-lb Energy: 113 ft-lb i MLE: 79 mils i MLE: 66 mils Shear: 60 % Shear: 53 % I 1 HAZ: 4A3 HAZ: 47P j Temp: 30 F Temp: 40'F Energy: 89 ft-lb Energy: 130 ft-lb MLE: 60 mils g;p MLE: 85 mils Shear: 84 % Shear: 95 % l t ) i A-5

._ ~ 'l GE-hT-523-A166-1294 DRF 137-0010-7 l ~ ~ ' HAZ 47V ^ HAZ 4AB Temp: 80*F Temp: 120 F Energy: 117.5 ft-lb h.'i Energy: 131.5 ft-lb MLE: 81 mils MLE: 87 mils Shear: 85 % Shear: 100 % HAZ 4AU HAZ: 4AA Temp: 200 F gp. Energy: 123.5 ft-lb Temp: 300 F fp. Energy: 140 ft-lb y %I MLE: 92 mils l MLE: 88 mils Q. Shear: 100 % Shear: 100 % s A-6 4

= - ?!I. GE-NE-523-A166-1294 i DRF 137-0010-7 l APPENDIX B l LASALLE UNIT 1 VERSUS MAINE YANKEE AND KEWAUNEE f SURVEILLANCE PROGRAM MATERIAL I i LaSalle Unit 1 Base Metal: t

1. Material: ASTM SA-533 Grade B, Class 1 l
2. Heat Treat:

Austenitized - 1550'F-1625'F for 4 hrs and water quenched Tempered - 1200*F-1300'F for 4 hrs and air cooled Post Weld (stress relieve) - 1150*F+/- 25'F for 40 hrs and furnace cooled to 600'F

3. Orientation: Longitudinal specimens were required (L-T)

Weld Metal

1. Material:

Wire: B-4 Mod Heat No. IP3571 Flux: Linde 1092 Lot No. 3958

2. Heat Treat:-same as above-I
3. Type: Submerged arc Maine Yankee i

Base Metal: I

1. Material: ASTM SA 533 Grade B, Class 1 i
2. Heat Treat:

Austenitized - 1550 F-1650'F for 4 hrs and water quenched Tempered - 1225'F+/- 25'F for 4 hrs and air cooled L Post Weld (stress relieve) - 1150'F+/- 25'F for 40 hrs and furnace cooled to 600*F

3. Orientation: Longitudinal specimens (L-T) l Weld Metal
1. Material:

Wire: B-4 Mod Heat No. IP3571 f Flux: Linde 1092 Lot No. 3958

2. Heat Treat:-same as above-l
3. Type: Submerged arc l

Kewaunee

1. Weld Material:

Wire: 0 3/16 B-4 Heat No. IP3571 l Flux: Linde 1092 Lot No. 3958

2. Heat Treat:

Post Weld (stress relieve) - 1150*F for 19.3 hrs and furnace cooled

3. Type: Submerged are j

i l 1 B-1 l

d i GE-NE-523-A166-1294 o DRF 137-0010-7 CHEMICAL ANALYSIS MEASUREMENTS FOR WELDS FABRICATED WITil Tile IP3571 WIRE HEAT, LINDE 1092 FLUX, AND 3598 FLUX LOT l22,24l Source Cu Ni (wt %) (wt %) Additional Data Kewaunee Surveillance Capsule "V" 0.214 0.816 Kewaunee Surveillance Capsule "V" 0.434 0.800 Kewaunee Surveillance Capsule "R" 0.066 0.736 Kewaunee Surveillance Capsule "R" 0,207 0.769 Maine Yankee Surveillance Capsule 253" 0.432 0.745 Maine Yankee Surveillance Capsule 253" 0.356 0.728 Kewaunee Surveillance Capsule "P" 0.18 0.74 Kewaunee Surveillance Capsule "P" 0.35 0.74 Kewaunee Surveillance Capsule "P" 0.19 0.73 Kewaunee Surveillance Capsule"P" 0.17 0.72 Kewaune,e lfnirradiated Surveillance Weld 0.20 0.77 CE Weld Qualification M 1.42 (Sirnple Wire) 0.40 0.82 CE Weld Qualification M 1.43 (Tandem Wire) 0.37 0.75 Maine Yankee Surveillance (ETI Report CR 75-269) 0.36 0.78 i Maine Yankee Surveillance Capsule 263" (BCL Rpt. 585-21) 0.25 0.66 Maine Yankee Surveillance Capsule 263" (BCL Rpt. 585-21) 0.25 0.70 Maine Yankee Surveillance Capsule 263" (BCL Rpt. 585-21) 0.33 0.71 Maine Yankee Surveillance Capsule 263" (BCL Rpt. 585-21) 0.33 0.70 AVERAGE OF 18 MAINE YANKEE + KEWAUNEE POINTS 0.28 0.75 AVERAGE OF 12 LASALLE SURVEILLANCE PROGRAM POINTS' O.32 0.99 AVERAGE OF ALL 30 KNOWN DATA POINTS 0.30 0.84

  • Data from Table 3-3 Chemistry Factor Using all Known Data Points = 231 Chemistry Factory Using only LaSalle Data Points = 261 B-2}}
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