ML20100L355
| ML20100L355 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 02/29/1996 |
| From: | Caine T, Drendel D, Sleight E GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20100L346 | List: |
| References | |
| GE-NE-B1301786, GE-NE-B1301786-01-R0, GE-NE-B1301786-1-R, NUDOCS 9603040181 | |
| Download: ML20100L355 (62) | |
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O GENuclear Energy TechnicalServices Business GE-NE-B1301786-01 GeneralElectric Company 175 Curtner Avenue, San Jose, CA 95125 Revision 0 February 1996 LASALLE UNIT 2 RPV SURVEILLANCE MATERIALS TESTING AND ANALYSIS Prepared by: < E. W. Sleight, Engineer Engineering Services Verified by: ( C D. B. Drendel, Principal Engineer Mechanical Design Engineering Approved by: T. A. Caine, Principal Engineer Engineering Services
I GE-NE-B1301786-01 Revision 0 IMPORTANT NOTICE REGARDING ) CONTENTS OF THIS REPORT PLEASE READ CAREFULLY This repon was prepared by General Electric solely for the use of Commonwealth
)
Edison Company. The information contained in this repon 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 repon 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 repon and nothing contained in this document shall be constmed 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. ) l ? ) } l 1 iI L______________________________
i GE-NE-B1301786-01 Revision 0 TABLE OF CONTENTS PJULC ABSTRACT vii ACKNOWLEDGMENTS viii
- 1. INTRODUCTION 1
- 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 6 3.2.1 FabricationHistory 6 3.2.2 MaterialProperties ofRPV at Fabrication 6 3.2.3 Surveillance Capsule Specimen Chemical Composition 6 3.3 Specimen Description 7 3.3.1 Charpy Specimens 7 3.3.2 Tensde Specimens 8
- 4. PEAK RPV FLUENCE EVALUATION 15 4.1 Flux Wire Analysis 15 4.1.1 Procedure 15 4.1.2 Results 16 4.2 Determination ofLead Factor 16 4 2.1 Procedure 17 4.2.2 Results 17 4.3 Estimate of 32 EFPY Fluence 17
- 5. CHARPY V-NOTCHIMPACT TESTING 22 5.1 Impact Test Procedure 22 5.2 Impact Test Results 23 5.3 Irradiated Versus Unirradiated Charpy V-Notch Properties 23 3 5.4 Comparison to Predicted Irradiation Effects 24 4
5.4.1 Irradiation Shift 24 l 5.4.2 ChangeinUSE 25 . 6. TENSILE TESTING 36 6.1 Procedure 36 6.2 Results 36 6.3 Irradiated Versus Unirradiated Tensile Properties 37
- 7. ADJUSTED REFERENCE TEMPERATURE AND :43 UPPER SHELF ENERGY 4
7.1 Adjusted Reference Temperature at 32 EFPY 43 7.2 . Upper ShelfEnergy at 32 EFPY 44
- 8. REFERENCES 47 iii
GE-NE-B 1301786-01. ! Resision 0 l TABLE OF CONTENTS : APPENDICES ! A. ' IRRADIATED CHARPY SPECIMEN FRACTURE SURFACE A-1 l
- PHOTOGRAPHS
., l
]
t b i 1 i
)
i b t I I h .- e iV
I )I GE-NE-B1301786-01 Revision 0 TABLES ) Iabh Title Egge 3-1 Chemical Composition of RPV Beltline Materials from 9 Fabrication CMTR Records 3-2 Mechanical Properties ofBeltline and Other Selected 10 RPV Materials ) 3-3 Chemical Composition ofLaSalle 2 Surveillance Materials From Surveillance Specimen Chemical Tests 11 4-1 Summary ofDaily Power History 19
,4-2 Summary ofLaSalle 2 Irradiation Periods 20 4-3 Surveillance Capsule Flux and Fluence for '21 Irradiation from Start-up to 2/18/95 5-1 Vallecitos Qualification Test Results Using NIST Standard 26
)- Reference Specimens 5-2 Irradiated Charpy V-Notch Impact Test Results 27 5-3 Unitradiated Charpy V-Notch Impact Test Results 28 ) 5-4 Significant Results ofIrradiated and Unirradiated Charpy 29 V-Notch Data 6-1 Tensile Test Results for Irradiated RPV Materials 38 6-2 Comparison ofUnirradiated and Irradiated Tensile Properties at 38 ). Room Temperature 7-1 Beltline ART Values for LaSalle Unit 2 45 7-2 Upper ShelfEnergy Analysis for LaSalle Unit 2 Beltline Material 46 ) ) ) ? v
GE-NE-B1301786-01 Revision 0 ILLUSTRATIONS Figure Illk Eage ) 3-1 Surveillance Capsule Holder Recovered from LaSalle Unit 2 12 3-1(a) Tensile Specimen Capsule Identification 12 )- 3-1(b) Charpy Specimen Capsule Identification 13 3-2 Schematic of the RPV Showing Identification 14 of VesselBeltline Plates and Welds 5-1 LaSalle Unit 2 Irradiated Base Metal Impact Energy 30 n 5-2 LaSalle Unit 2 Irradiated Base Metal Lateral Expansion 30 5-3 LaSalle Unit 2 Unirradiated Weld Metal Impact Energy 31 5-4 LaSalle Unit 2 Unirradiated Weld Metal Lateral Expansion 31 5-5 LaSalle Unit 2 Irradiated Weld Metal Impact Energy 32 5-6 LaSalle Unit 2 Irradiated Weld Metal Lateral Expansion 32 5-7 LaSalle Unit 2 Irradiated HAZ Metal Impact Energy 33 5-8 LaSalle Unit 2 Inadiated HAZ Metal Lateral Expansion 33 5-9 LaSalle Unit 2 Uninadiated and Irradiated 34 Weld MetalImpact Energy 5-10 LaSalle Unit 2 Unirradiated Transverse Base Metal 35 ) Impact Energy 6-1 Typical Engineering Stress-Strain for Irradiated 39 RPV Materials 6-2 Fracture Location, Necking Behavior and Fracture 40 3 Appearance for Irradiated Base Metal Tensile Specimens 6-3 Fracture Location, Necking Behavior and Fracture 41 Appearance for Irradiated Weld Metal Tensile Specimens 6-4 Fracture Location, Necking Behavior and Fracture 42
)
Appearance for Irradiated HAZ Metal Tensile Specimens p vi
4
. GE-NE-B1301786-01
~ Revision 0 i ABSTRACT The surveillance capsule at the 300' azimuthal location (which had 120 capsule identification and contents) was removed at 6.98 EFPY from the LaSalle Unit 2 reactor in Spring . ~ 1995. The capsule contained flux wires for neutron fluence measurement and Charpy and tensile j test specimens for material property evaluations. The flux wires were evaluated to determine the j fluence experienced by the test specimens. Charpy V-Notch impact testing and uniaxial tensile
- testing were performed to establiah the properties of the irradiated surveillance materials.
The irradiated Charpy data for the weld specimens were compared to the unirradiated data l
. to determine the shift in Charpy curves due to irradiation. Unirradiated Charpy base plate data was only available for transverse specimens whereas the surveillance specimens are oflongitudinal
]
- orientation. Thus, evaluation of shifts was not possible for the plate material. The shift results for the weld material are within the predictions of the Regulatory Guide 1.99 Revision 2. ;
" The irradiated tensile data for the plate and weld specimens were summarized. The room temperature irradiated data was 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. l l ! The flux wire results, combined with the lead factor determined from the first fuel cycle, l were used to estimate the 32 EFPY fluence. The resulting estimate was in good agreement with the previous nominal 32 EFPY fluence estimate. t e b 4 vii
GE-NE-B1301786-01 : Revision 0 ACKNOWLEDGMENTS i The author gratefully acknowledges the efforts of other people towards completion of the contents of this report. Charpy testing was completed by G. P. Wozadio, G. E. Dunning and B. D. Frew. Tensile specimen testing was done by S. B. Wisner and chemical composition analysis was performed by - P. Wall. Flux wire testing was performed by L. Kessler, R. Kniger and R. Reager. Project management was conducted by Betty Branlund. viii
r GE-NE-B1301786-01 Revision 0
- 1. INTRODUCTION i
Part of the effort to assure reactor vessel integrity involves evaluation of the fracture ! 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]. Appendix H of 10CFR50 [3] and ASTM E185-70 establish the methods to be used for surveillance of the LaSalle Unit 2 reactor vessel materials. In addition, compliance with ASTM El85-73 [4] has been addressed in the Final Safety Analysis Report [5]. The first vessel surveillance specimen capsule required by 10CFR50 Appendix H [3] was removed from LaSalle Unit 2 in Spring 1995. 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 materials from the vessel materials within the core beltline region. The impact and tensile specimens were tested to establish properties for the irradiated materials. The results of the surveillance specimen testing are presented in this report, as required l per 10CFR50 Appendices G and H [1 & 3]. The irradiated material properties are compared to the unirradiated properties to determine the effect ofirradiation on material toughness for the weld material, through Charpy testing. Irradiated tensile testing results are provided and are compared with room temperature unirradiated data to determine the effect ofirradiation on the stress-strain relationship of the materials; only room temperature baseline tensile data was available for the plate. 1 i l l 1
GE-NE-B1301786-01 Revision 0 ;
- 2.
SUMMARY
AND CONCLUSIONS l
)
2.1
SUMMARY
OF RESULTS The 300 azimuth position surveillance capsule was removed and shipped to VNC. The l flux wires, Charpy V-Notch and teni 'e test specimens removed from the capsule were tested according to ASTM E185-82 [6]. The methods and results of the testing are presented in this report as follows: Section 3: Surveillance Program Background e RPV Materials and Fabrication e MaterialProperties e Surveillance Specimen Chemical Composition
- Specimen Description Section 4: Peak RPV Fluence Evaluation 4
Section 5: Charpy V-Notch Impact Testing Section 6: Tensile Testing Section 7: Adjusted Reference Temperature and Upper Shelf Energy i
- The significant results of the evaluation are below
l
- a. The 300 azimuth position /120* capsule was removed from the reactor after 6.98 EFPY of operation. The capsule 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 heat affected zone (HAZ) material. The 8 tensile specimens removed consisted of 3 plate,3 weld and 2 HAZ metal specimens.
- b. The chemical composition of copper (Cu) and nickel (Ni) for the irradiated surveillance materials were determined from a chemical composition analysis. The j best estimate values for the surveillance material chemistries were calculated as i 2 ,
l
3 4 i GE-NE-B1301786-01 . Revision 0 i
- averages of the available baseline and irradiated data. The best estimate values for ;
- the surveillance plate are 0.10% Cu and 0.48% Ni, and are 0.04% Cu and ;
- 0.89% Ni for the surveillance weld. !
;. n 1.
[ . c. The purpose of the flux wire testing was to determine the neutron flux at the survai%c4 capsule location. The flux wire results show that the fluence (from - E >l MeV flux) received by the surveillance specimens was 1.15x1017 n/cm 2 at i
!. removal.
.b
- d. A neutron transport computation had been performed based on the performance of I the first fuel cycle. Relative flux distributions in the azimuthal and axial directions j
. were previously developed in Reference 19. The lead factor was 0.98, relating the l [ surveillance capsule flux to the peak inside surface flux. l i i
- e. The surveillance Charpy V-Notch specinens were impact tested at temperatures
, selected to define the upper shelf energy (USE) and the transition of the Charpy V-l Notch curves for 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 (for plate and weld metal only), the
[ values of USE and ofindex temperature for 30 ft-lb, 50 fi-lb and 35 mils lateral expansion (MLE) were obtained (see Table 5-4). Fracture surface photographs of y each specimen are presented in Appendix A. i
- f. The curves ofirradiated and unirradiated Charpy specimens established the 30 ft-lb
)
- shifts. The weld material showed an 18.6*F shift and a 3.6 ft-lb increase in USE i (4.3% increase). The index temperature irradiation shift and the decrease in USE l for the plate material was not determined due to insuf5cient baseline data.
- g. The measured shift of 18.6*F for weld, for a fluence of 1.15x1017 n/cm2, was l within the Reg. Guide 1.99 [7] range prediction (ARTNDT 2c) of -49.6'F to
- 62.4*F. The best estimate chemical composition for the surveillance weld material
[ was used for this calculation. a h.- The irradiated tensile specimens were tested at room temperature (70 F), at L reactor operating temperature (550'F), and at 150*F for the additional base and ! weld specimens. Only room temperature unirradiated tensile test data were , i l 3 . l
GE-NE-B1301786-01 Revision 0 available for comparison. As expected, the room temperature results show that in comparison to unirradiated data the irradiated data has increased strength and decreased ductility typical for irradiation embrittlement.
- i. The 32 EFPY RPV peak fluence prediction is 5.38x10 17 n/cm2at the vessel wall, .
based on the flux wire test and lead factor. This is about 3% higher than the previously established nominal 32 EFPY fluence prediction (5.2x10 17n/cm 2[19]), The 32 EFPY fluence prediction is 3.7x1017 n/cm2 at 1/4 T.
- j. The adjusted reference temperature (ART = initial RTNDT + ARTNDT+ ,
Margin) was predicted for each beltline material, based on the methods of Reg. Guide 1.99, Rev. 2. The ART for the limiting material, plate heat C9404-2, at 32 EFPY is 73.8'F and is lower than the 200 F requirement of 10CFR50 Appendix G [1].
- k. An update of the beltline material USE values at 32 EFPY was performed using the Reg. Guide 1.99, Rev. 2 methodology. The irradiated USE for all beltline materials will remain above 50 ft-lbs through 32 EFPY as required in 10CFR50 Appendix G [1]. ;
2.2 CONCLUSION
S , i j The requirements of 10CFR50 Appendix G [1] deal with vessel design life conditions and l l l with limits of operation designed to prevent brittle fracture. Based on the evaluation of surveillance testing results, and the associated analyses, the following conclusions are made:
- a. The 30 ft-lb shifts and changes in USE are consistent with Regulatory Guide 1.99 Revision 2 predictions and associated deviations,
- b. The values of ART and USE for the reactor vessel beltline materials are expected to remain within limits of10CFR50 Appendix G [1] (< 200*F and > 50 ft-lbs, respectively) for at least 32 EFPY of operation.
1 9 4 l
- w= --
w e- ___P - m-_
) GE-NE-B1301786-01 R.evision 0
- 3. SURVEILLANCE PROGRAM BACKGROUND i
3.1 CAPSULE RECOVERY The reactor pressure vessel (RPV) surveillance program consists of three surveillance i- - capsules at 30',120', and 300* =Annhs 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 equalirradiation because of core symmetry. During the Spring 1995 outage, a surveillance capsule was removed from the 300 azimuthal location. The capsule was cut from its i holder assembly and shipped by cask to the GE Vallecitos Nucle:r Center (VNC), where testing was performed. Upon arrival at VNC, the capsule basket was examined for identification. The identification number stamped on the basket corresponded to basket number 2 and reactor number 51, as specified by GE drawings,131C7717 (Specimen Holder) and 105D4714G006 (Surveillance Program), for the LaSalle Unit 2120 surveillance materials. A comparison of capsule identification and actual capsule azimuthal location indicates that the capsule identified as
- , the 120 capsule was actually located in the 300' azimuthal location. _ LaSalle Unit 2 technical staff verified that the capsule was actually pulled from the 300 location per IVVI and work records for the outage. The discrepancy between capsule locations will in no way affect the results of surveillance testing due to symmetry ofirradiation in the vessel and presence of the i
same type of surveillance specimens in each capsule. The general condition of the basket as received is shown in Figure 3-1. The basket contained three impact (Charpy) specimen capsules and four tensile specimen capsules. During 1 the removal of the Charpy impact specimens from the specimen holders, the weld specimen holder was found to have leaked. The specimens were visually examined for features that could possibly affect test results. The specimens appeared somewhat darker in appearance than the other specimens. This uniform discoloration was most likely caused by the exposure of the specimen to the high temperature water environment. The surfaces of the discolored specimens were similar to the other specimens, i.e., no defects, pits, or detrimental corrosion was observed. Based on these observations, it is was concluded that the specimens were not affected by the exposure to water, and will give credible surveillance results.
i r
. GE-NE-B1301786-01 l Revision 0 !
t 3.2 RPV MATERIALS AND FABRICATION l
- i l
3.2.1 Fabncation History - ] . The LaSalle Unit 2 RPV is a 251 inch diameter BWR/5 design. Construction was 4 performed by CBI Nuclear Company (CBIN) under the 1968 edition of the ASME Code through i the 1970 Winter Addenda. The shell and head plate materials are ASME SA533, Grade B, i Class I low alloy steel (LAS). The nozzles and closure flanges are ASME SA508 Class 2 LAS, and the closure flange bolting materials are ASME SAS40 Grade B24 LAS [23]. Submerged arc l [ or shielded metal are welding of plates was followed by post-weld heat treatment at 1150 F. The
- fabrication impact test specimens were given a simulated post weld heat treatment at 1150'F plus (
25*F minus 50*F, held 50 hours followed by furnace cooling to below 600*F, then air cooled [11]. ,
- The identification of plates and welds in the beltline region is shown in Figure 3-2. ;
i 3.2.2 Material Properties ofRPV at Fabrication Material certification records were retrieved from GE Quality Assurance (QA) records to ! determine chemical and mechanical properties of the vessel materials. The retrieved information 2 is documented in the UFSAR [23] and in GE P-T Curve report (15]. Table 3-1 shoivs the
- chemistry data for the beltline materials. Properties of the beltline materials and materials at other locations ofinterest are presented in Table 3-2.
3.2.3 Surveillance Caosule Specimen Chemical Composition ) ) j Samples were taken from the irradiated base and weld specimens after they were tested. L 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 I
, spectrometer was calibrated for determination ofMn, Ni, Mo, Cr, Si and Cu by diluting National Institute of Standards and Technology (NIST) Spectrometric Standard Solutions. The l phosphorus calibration involved analysis of seven reference materials from NIST with known j phosphorus levels. Analysis accuracies are 0.005% (absolute) of reported value for phosphorus and 15% (relative) of reported value for other elements. The chemical composition results are
- given in Table 3-3 for both irradiated and baseline surveillance plate and weld materials. The
{ baseline data were taken from CBIN material certification records for the plate and weld 1
- - ' surveillance specimens [9].'
6 l l
i GE-NE-B1301786-01 i Revision 0 i 3.3 SPECIMEN DESCRIPTION ; i . 1 The surveillance capsule holder contained 36 Charpy specimens: base metal (12), weld metal (12), and HAZ (12). There were 8 tensile specimens: base metal (3), weld metal (3), and :
! HAZ (2). The holder contained 9 flux wires: 3 iron,3 nickel, and 3 copper. The chemistry and i i fabrication history for the Charpy and tensile specimens are described in this section. Surveillance !
I program design information is discussed in GE report [11]. Y 3.3.1 Charov SeAn=n= ; - i The fabrication of the Charpy spMn=ns is described in the CBIN drawings [10] of the
. surveillance test program. All materials used for surveillance were fabricated from material of the same heat as one of the beltline plates [9,10].
$ The base metal specimens were cut from Heat C9481-1. The test plates received the same I
- - heat treatment as the fabrication specimens for Heat C9481-1, including the post-weld heat
, treatment for 50 hours at 1150T +257/-50T. The Charpy specimens were removed from
- Heat C9481-1 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 parallel to the rolling direction). The Charpy specimens had been stamped on one end with the fabrication codes as listed in GE report [11] for LaSalle Unit 2.
i i The weld metal and HAZ Charpy specimens were fabricated by welding together two pieces of the surveillance test plates Heat C9481-1 with the same weld procedure used to produce F welds in the beltline region. Welding records obtained from CBIN show the surveillance weld to l be submerged arc weld with heat SP7397, Linde 124 Flux, and Lot 0342. The filler heat number of the surveillance weld does not match that of a core region nam, however the filler material used meets the requirements of Reference [10] which indicates that a material representative of the core region longitudinal seams could be used [11]. The welded test plates received stress relief heat treatment at 1150T +25T/- SOT to simulate the RPV fabrication conditions. The weld and HAZ specimens were cut from the material as shown in Figure 2-1 of GE report (11] 1 , avoiding the volume near the root of the welds. The base metal orientation in the weld and HAZ
. specimens was longitudinal, f
a l 7 j I
0 GE-NE-B1301786-01 ' Resision 0 3.3.2 Tensile Snecimens O Fabrication of the surveillance tensile specimens is also described in the CBIN surveillance specimen drawings [10]. 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 surveillance specimens and a summary of the fabrication methods can be found in GE report [11]. O I D l D D D D P J 8
g , g , . . . . .- 9.. 9 . . ._.- GE-NE-B1301786-01 Revision 0 Table 3-1 CHEMICAL COMPOSITION OF RPV BELTLINE MATERIALS FROM FABRICATION CMTR RECORDS' Composition by Weight Percent
'Ideadfication : e Heat /let No. -
-Cu3 : NiE J C? Mn c 0P* *::/ S t ' Si : ': Mo
- PLATES.
Lower Shell Plates: 21-1 C9425-2 0.12 0.51 0.21 1.25 0.009 0.020 0.25 0.50 21-2 C9425-1 0.12 0.51 0.21 1.25 0.009 0.020 0.25 0.50 21-3 C9434-2 0.09 0.51 0.21 1.31 0.013 0.015 0.21 0.50 lower-Intermediate Shell Plates-22-1 C9481-1 0.11 0.50 0.21 1.27 0.008 0.018 0.23 0.50 22-2 C9404-2 0.07 0.49 0.22 1.38 0.008 0.020 017 0.50 22-3 C9601-2 0.12 0.50 0.21 1.28 0.015 0.019 0.23 0.53 Surveillance Plate:
- C9481-1 0.084 0.45 .291 1.28 0.003 0.023 9.19 0.34 WELDS.
Lower-Inter. Vert. BA,BB,BC 3P4000, Flux 124,Iot 3933 0.02 0.89 0.08 1.30 0.012 0.010 0.39 0.42 Lower Vertical BD, BE, BF 3P4966, Flux 124, Lot 1214 0.03 0.90 0.07 1.39 0.011 0.014 0.38 0.53 Girth Weld: Lower to Lower-Inter. AB $P6771 Flux 124, Lot 0342 0.04 0.95 0.06 1.30 0.013 0.011 0.45 0.57 6 Surveillance Weld: SP7397, Flux 124, Lot 0342 0.03 0.87 0.069 1.38 0.014 0.015 0.50 0.44 (Tandem Wire)
- Data fium GE Report [15l
- Data from CBIN CMTR values. Contract No. 8-CN203 (1980)[28]
9
GE-NE-B1301786-01 Revision 0 Table 3-2 Mechanical Properties of Beltline and Other Selected RPV Materials , 4 initial ID. Heat dTer ! Location _Mq., Number _( E) Beltlini: Lower ShellPlates 21-1 C9425-2 30 21-2 C9425-1 32 21-3 C9434-2 10 Lower Intermediate 22-1 C9481-1 10 ShellPlates 22-2 C9404-2 52 22-3 C9601-2 10 Venical Welds
- BA,BB,BC 3P4000 -50 BD,BE,BF 3P4966 -6 Girth Welds
- AB 5P6771 -34 i
Non-Beltlini Upper Shell 24-1 A-8453-1 26 Head Flange 30-1 BWK-446 10 Feedwater Nozzle 52-1-1/6 Q2Q25W -6 Bottom Head 13-3 C9306-2 44 6 Closure Bolts 35-1 82552 LST = 70 a Test data information from [15] I b nitial RT a = LST = 10'F (the lowest CVN test temp.) + 60 F c These are conservative bounding values from single and tandem wire qualifications. i 10
GE-NE-B1301786-01 Revision 0 Table 3-3 Chemical Composition of LaSalle 2 Surveillance Materials From Surveillance Specimen Chemical Tests
; Metal Sample IDi Metal Sample Cu (wt%)!( LNi.(wt%); . Mnl(wt%)f ?Mol(wt%)! Si(wt%); iCr(wt%)- ' P (wt%)]
4YPet ,. 3 . s
- n. y.;
28832 Base 0.11 0.49 1.24 0.52 0.20 0.13 0.011 28833 Base 0.11 0.51 1.22 0.55 0.23 0.14 0.014 28834 Base 0.10 0.47 1.17 0.50 0.17 0.13 0.011 Baseline A' Base 0.08 0.45 1.28 0.34 0.19 0.09 0.003 6 Baseline B Base 0.1 l' O.50 1.27 0.50 0.23 - 0.008
, DataAvg. 0.10 0.48 1.24 0.48 0.20 0.12 0.01
- Std. Dev. 0.01 0.03 0.04 0.08 0.03 0.02 0.00 __
28835 Weld 0.04 0.93 1.57 0.50 0.40 0.08 - 28836 Weld 0.04 0.96 1.62 0.51 0.37 0.08 - 28837 Weld 0.05 0.86 1.52 0.48 0.33 0.08 - 28838 Weld 0.05 0.88 1.52 0.49 0.38 0.08 - 28839 Weld 0.04 0.92 1.55 0.51 0.38 0.09 - 28840 Weld 0.04 0.85 1.46 0.47 0.33 0.08 - 28841 Weld 0.03 0.86 1.42 0.45 0.32 0.08 - 28842 Weld 0.03 0.87 1.41 0.45 0.34 0.08 - 28843 Weld 0.03 0.91 1.45 0.48 0.33 0.08 - 28844 Weld 0.04 0.73 1.23 0.35 0.37 0.07 0.015 l j 28845 Weld 0.04 0.96 1.45 0.49 0.32 0.09 0.011 28846 Weld 0.04 0.99 1.47 0.49 0.37 0.09 0.010 Baseline A' Weld 0.03 0.87 1.38 0.44 0.50 0.04 0.014 Data Avg. 0.04 0.89 1.47 0.47 0.37 0.08 0.01 Std. Dev. 0.01 0.07 0.10 0.04 0.05 0.01 0.00 ,
- See Table 3-1 6
, Baseline data from CB&l CMTR values (1971) l Value per Lukens Steel f II
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,. y Lr~ ~ .:: n = .=. .
Figure 3-1: Surveillance Capsule Holder Recovered From LaSalle Unit 2 0 (300 AzimuthalLocation)
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3 'O Figure 3-1(a): Tensile Specimen Capsule Identification (300 AzimuthalLocation) ..O 12
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.... g i Figure 3-1(b): Charpy Specimen Capsule Identification (300 AzimuthalLocation) n 13 I ,, , _ _ _ . . _ .
GE-NE-B1301786-01 Revision 0 Vessel Flange Longitudinal Welds f Upper Shell 1 y Girth Welds W I Upper Intermediate Shell f ; I l N Intermediate Shell _f-N
\
_f
#2 Shell Ring l LPCl Plate: Heat:
g Lower intermediate Shell da m(3)m g) 22-1 C9481-1 , (#2 Shell Ring) 22-2 C9404-2 Core 22-3 C9601-2 Beltline E " #1 ShellRing f V Lower Shell N Recire. Inlet (to) 2 -1 C942 R c. [ et Pump inst. p) 21-2 C9425-1 f i g) 1 21-3 C9434-2 i Bottom Head Enclosure f s l Figure 3-2. Schematic of RPV Showing Identification of Vessel Beltline Plates and Welds l 14
GE-NE-B1301786-01 Revision 0 l
- 4. PEAK RPV FLUENCE EVALUATION Flux wires removed from the 300' location /120 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 : 1 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 j 4-cm or 10-cm source-to-detector distance with 170-cc Ge and 100-cc Ge(Li) gamma spectrometers. ] To properly predict the flux and fluence at the surveillance capsule from the activity of j the flux wires, the periods of full and partial power irradiation and the zero power decay periods I were considered. Operating days for each fuel cycle and the reactor average power fraction were derived from records provided by Commonwealth Edison and are shown in Tables 4-1 and 4-2 , respectively. I From the flux wire activity measurements and power history, reaction rates for Fe-54 (n,p) Mn-54, Cu-63 (n,ct) 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 [29] which is also a 251 inch, 764 bundle plant, using multiple dosimeter and spectrum 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 spectrum
]
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 0.1 to 1 MeV cross section ratio of 1.6 [29].
15
.l
7 GE-NE-B1301786-01 ! Revision 0 ;
) 4.1.2 Results The measured activity, reaction rate and full-power flux results for the 300* location / ,
120* surveillance capsule are given in Table 4-3. The E > 1 MeV flux values were calculated by dividing the wire reaction rate measurements by the corresponding cross sections, factoring in the
) .
local power history for each fuel cycle. Thi fluence result,1.15x10 17 n/cm2 (E > 1 MeV), was obtained by using the following equation:
@co = @r, t i p, (4-1) ).
where, @c. = fluence measured by the Cu dosimeters
@r, = full power flux value for Cu l ti = operating time )
pi = fullpowerfraction as shown in Tables 4-1 and 4-2. The fluence was calculated using the Cu flux wire because it has a longer halflife and provides a more conservative result. The accuracies of the values in )_ Tables 4-3 for a 2o deviation are influenced by the following sources of error: 1 10.2 % relative error ) i 1% counting rates i 15 % power history i 10 % cross sections The overall 2e error is estimated to be about 20%. ) 4.2 DETERMINATION OF LEAD FACTOR The flux wires detect flux at a single location and thus reflect 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 to the flux at the peak inside surface location. The lead factor is a function of the core and vessel geometry and of the distribution of bundles in the core. The lead factor that will be used is discussed in GE report (19] for the LaSalle 2 vessel geometry and was generated by using a first cycle dosimetry analysis s 16
P
). !
GE-NE-B1301786-01 Revision 0 from a reactor having the same configuration as LaSalle 2. The methods used to calculate the lead factor are briefly summarized below but discussed in detail in GE report [19].
)
. 4.2.1 Procedure y . Determination of the lead factor in [19] for the RPV inside wall was made using a combination of a two-dimensional and a one-dimensional finite element computer analysis. The two-dimensional analysis established the relative azimuthal variation of fluence at the vessel surface and 1/4 T depth. The one-dimensional analysis determined the relative variation of flux y with elevation. The azimuthal and axial distribution results were combined to provide the 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].
4.2.2 Results
) ,
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 y the attenuation of the flux to that depth is considered. This attenuation is calculated according to i Reg. Guide 1.99 requirements, as shown in the next section. 4.3 ESTIMATE OF 32 EFPY FLUENCE y The inside surface fluence (fsurf) at 32 EFPY is determined from the flux wire fluence at a particular EFPY and lead factor according to h fa = (f ,* 32 EFPY)/(LF
- CEFPY) (4-2) where, fa = 32 EFPY fluence at the peak vesselinside surface j fe., = . capsule fluence measured at the CEFPY 32 EFPY = end oflife EFPY based on a 40-year operation at an 80% capacity factor CEFPY = the current EFPY for the capsule >
'LF = lead factor > The surveillance capsule was removed from LaSalle 2 at 6.98 EFPY as calculated in 2
Table 4-2,' the fluence at 6.98 EFPY.was determined to be 1.15x10" n/cm using Equation 4-1,
'17
t GE-NE-B1301786-01 Revision 0 and the lead factor was determined to be 0.98 as discussed in Section 4.2. Using this information 3 with Equation 4-2, the resulting 32 EFPY fluence value at the peak vessel inside surface is: 2 f r = (1.15x10"
- 32)/(0.98
- 6.98) = 5.38x10" n/cm at the peak location.
The peak surface fluence at 32 EFPY is about 3% higher than the nominal value (5.2x1017 n/cm2) that was calculated from the first cycle dosimetry as reported in GE report [19). This is well within the 20% accuracy expected as reported in section 4.1.2. 1 The 1/4 T fluence (f) is calculated according to the Reg. Guide 1.99 [7] equation: i f = f e(e-0.24x) , (43) where x = distance, in inches, to the 1/4 T depth. The vessel beltline lower-intermediate shell is 6.44 inches thick ordered,6.19 inches minimum requirement. The correspondir.g depth x taken j from the minimum required thickness is 1.55 inches. Equation 4-3 evaluated for this value of x ; 2 gives the 1/4 T value of 32 EFPY fluence, f= 3.7x10" n/cm for the lower intermediate shell ring. ; 1 i l 1 i } { 18
i l l GE-NE-B1301786-01 Revision 0 l l Table 4-1 1 Summary of Daily Power History bcycle N Edateeen Edges 1llKd Ml 1 $$sid(t) scydew 4 deed es? Edete offs days an (te) EMwd(t)s l 1 3/10/84 12/31/86 1027 1643179 6 12/28/93 12/31/93 4 7293 ; 2 7/16/87 10/15/88 458 1348380 1/1/94 1/31/94 31 57409 I 3 2/8/89 3/16/90 402 1081304 2/1/94 2/28/94 28 92703 ; 4 6/10/90 6/30/90 21 21988 3/1/94 3/31/94 31 101032 7/1/90 7/31/90 31 88855 4/1/94 4/30/94 30 92006 8/1/90 8/31/90 31 100301 5/1/94 5/31/94 31 100675 9/1/90 9/24/90 24 61928 6/1/94 6/30/94 30 81575 10/1/90 10/31/90 31 105602 7/1/94 7/31/94 31 102505 j 11/1/90 11/30/90 30 100934 8/1/94 8/31/94 31 83343 j 12/1/90 12/31/90 31 78916 9/1/94 9/30/94 30 93463 ] 1/1/91 1/31/91 31 104443 10/1/94 10/31/94 31 67105 2/1/91 2/28/91 28 92242 11/1/94 11/30/94 30 96659 , 3/1/91 3/31/91 31 102206 12/1/94 12/31/94 31 100713 I 4/1/91 4/30/91 30 97515 1/1/95 1/31/95 31 101050 5/1/91 5/31/91 31 101982 2/1/95 2/18/95 18 54409 6/1/91 6/30/91 30 97922 7/1/91 7/31/91 31 102157 total _ days sum 8/1/91 8/31/91 31 98657 3.35E + 03 8.48E + 06 9/1/91 9/24/91 24 48248 10/1/91- 10/31/91 31 82369 11/1/91 11/30/91 30 94903 12/1/91 12/31/91 31 96676 1/1/92 1/4/92 4 7541 5 4/20/92 4/30/92 11 27832 l 5/1/92 5/31/92 31 98989 6/1/92 6/30/92 30 94439 7/1/92 7/31/92 31 94912 8/1/92 8/27/92 27 80906 9/11/92 9/30/92 20 54361 l 10/1/92 10/31/92 31 98440 11/1/92 11/30/92 30 84777 i 12/1/92 12/31/92 31 99758 ; 1/1/93 1/31/93 31 100100 l 2/1/93 2/28/93 28 89053 I 3/1/93 3/31/93 31 100762 1 4/1/93 4/30/93 30 96212-5/1/93 5/29/93 29 92457 I 6/7/93 6/30/93 24 73391 j 7/1/93 7/31/93 31 102641 8/1/93 8/31/93 31 89013 l 9/1/93 9/3/93 3 8119 l l 19
GE-NE-B1301786-01 Revision 0 Table 4-2 Summary of LaSalle 2 Irradiation Periods
; cycle < 4 en s . y agra daysem? LMWd4 full power days 2 fpf,i 1 3/10/84 12/31/86 1027 1643179 494.5 0.481 2 7/16/87 10/15/88 458 1348380 405.8 0.886-3 2/8/89 3/18/90 402 1081304 325.4 0.809 4 6/10/90 1/4/92 574 1685386 507.2 0.884 5 4/20/92 9/3/93 502 1486163 447.2 0.891 6 12/26/93 2/18/95 420 1231540 370.6 0.882 TOTAL (EFPD)= 2550.7 TOTAL (EFPY) = 6.98 t
l I i 5 l
)
1 i 1 ./ 20 1
GE-NE-B1301786-01 Revision 0 Table 4-3 Surveillance Capsule Flux and Fluence For Irradiation From Start-up to 2/18/95 (6.98 EFPY) h Average */ !; Average ;FullPower Flus #& FullPowerFlusC::' 1%ence fluenceC r.Wirt i .. ;dps/g Eleinent " . 2 f(a/cm2.,)}; f(,7y3 2)9 f(,ggy,2)3[
. S Reaction Rate - . J('m/cm -s)i (Element) ' fat end ofirradiation) -
- Idos/naciens (saturated)1 - i E>1 MeV? E>0.1 MeV4 > E>I MeV - S E>0.1 MeV ?
Copper 6.68E03 1.95E-18 5.22E08 8.35E08 1.15E17 1.84E17 Iron 5.10E04 1.03E-16 4.86E08 7.78E08 1.07E17 1.71E17 Nickel 8.29E05 1.30E-16 4.77E08 7.52E08 1.05E17 1.67E17 Value used for fluenced: 1.15E17 1.84E17 a Obtained by R.D Reager and L.K. Kessler b Full power flux, based on thermal power of 3323 Mwt c 1.6 times the E >l MeV result d Only copper flux wires are used to determine the fluence 21
y . GE-NE-B1301786-01 l Revision 0 l
- 5. CHARPY V-NOTCH IMPACT TESTING ;
I . 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 l materials. Testing was conducted in accordance with ASTM E23-88 [12]. l'
)- -
5.1 IMPACT TEST PROCEDURE i The Vallecitos testing machine used for irradiated specimens was a Richle Model P1-2 f
)
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. . l l The test apparatus and operator were qualified dng NIST standard reference material ,
)
specimens. The Standard Reference Materials (SRMs) consist oi+hree sets of specimens which cover the energy range of the apparatus. Each set has a designated felure energy and a standard test temperature. According to ASTM E23-88 [12], the test apparatus averaged results must reproduce the NIST standard values within an accuracy ofiS% or 1.0 ft-lb, whichever is y greater. The qualification of the Richle machine and operator is summarized in Table 5-1. I Charpy V-Notch tests were conducted at temperatures between -100 F and 300 F. The ; cooling fluid used for irrr.diated specimens tested at temperatures at or below 50'F was ethyl y alcohol. At temperatures between 50*F and 200 F, water was used as the temperature j conditioning fluid. The specimens were heated in silicon oil for test temperatures 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 j temperatures. The fluid temperature was measured with a calibrated thermocouple. After equilibration at the test temperature for at least 5 minutes, the specimens were manually transferred with centering tongs to the Charpy test machine and impacted in less than 5 seconds. 3 For each Charpy V-Notch specimen the test temperature, energy absorbed, lateral expansion, and percent shear were determined. 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 g . Subsection 11.2.4.3 of ASTM E23-88 [12], which involved measuring the length and width of the cleavage surface in inches and determining the percent shear value from Table 2 of , ASTM E23-88 [12]. L 22 i
r ) i GE-NE-B1301786-01 ; Revision 0 5.2 IMPACT TESTRESULTS )l i Twelve Charpy V-Notch specimens each ofirradiated base, weld, and HAZ material l were tested at temperatures (-100*F to 300'F) selected to define the toughness transition and j )- upper shelfportions of the fracture toughness curves. The absorbed energy, lateral expansion, j i and percent shear data are listed for each material in Table 5-2. Plots of absorbed energy and lateral expansion for base, weld, and HAZ materials are presented in Figures 5-1 through 5-8. l The irradiated weld metal curve is plotted along with the corresponding unirradiated cuwe in : Figure 5-9. Due to insufficient baseline data for the unitradiated plate material, a baseline curve j )
, was not generated. The fracture surface photographs and a summary of the test results for each }
specimen are contained in Appendix A. The irradiated plate and weld energy and lateral expansion data and HAZ lateral i ) expansion data are fit with the hyperbolic tangent function developed by Oldfield for the EPRI l Irradiated Steel Handbook [13): 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. l ) 5.3 IRRADIATED VERSUS UNIRRADIATED CHARPY V-NOTCH PROPERTIES Ideally, a shift in RTwrwould be established by comparing the irradiated Charpy specimen data to baseline unirradiated Charpy data. This is possible for the LaSalle 2 surveillance ) weld material (Heat SP7397, Linde 124 Flux, Lot 0342), where enough fabrication Charpy data exists to develop a full Charpy curve. This unirradiated weld data was fit to a TANH function as described in the previous section. } The fabrication data for the LaSalle 2 surveillance plate (Heat C9481-1) consists of only 6 Charpy data points at +40*F. This does not allow for development of a full Charpy curve for the l ) 23
i y . GE-NE-B1301786-01 -- Revision 0 unitradiated plate material by standard procedures. As a result, shifts in Charpy curves could only j t be determined for the weld material as discussed in the following section. j i 5.4 COMPARISON TO PREDICTED IRRADIATION EFFECTS 3 5.4.1 Irradiation Shift The measured transition temperature shift for the weld material was compared to the l predictions calculated according to Regulatory Guide 1.99, Revision 2 [7]. The inputs and ; y calculated values for irradiated shift for the weld material are as follows: Weld: Copper = 0.04 % Nickel = 0.89 %
,. CF = 54 fluence = - 1,15x1017 n/cm2
)
Reg. Guide 1.99 ARTNDT= 6.5 F ' Reg. Guide 1.99 ARTNDT 2aA(56'F) = 62.5'F max, -49.5'F min Measured 30 ft-lb shift = 18.6*F The weight percents of Cu and Ni are best estimates based on averaging (see Table 3-3). The CF shown above is the chemistry factor for the weld material obtained from Table 1 ofReg. Guide 1.99. The fluence factor for the Reg. Guide calculation of 30 ft-lb shift may either be calculated according to the Reg. Guide definition fluence factor = fn23.uowo (5-1) i or it may be obtained from the Reg. Guide Figure 1 [7]. Using equation 5-1, the fluence factor was calculated to be 0.12. These values are used to calculate the Reg. Guide 1.99 prediction for 30 ft-lb shift and USE decrease for comparison to the measured shift and USE decrease for the irradiated surveillance materials. The predicted 30 ft-lb temperature shift (ARTa) was also 1 calculated according to the Reg. Guide using the equation l i ART, = (CF) fa2s uowo. (5-2) h The measured 30 ft-lb temperature shift of 18.6 F (Table 5-4) for the weld is within the bounds of ; the' Reg. Guide prediction with the uncertainty of 2a. 1 24
M _- - +**e 4 -o . e a - __ . - GE-NE-B1301786-01 Revision 0 4 i 5.4.2 Channe in USE Using the copper and fluence data above with Figure 2 ofReg. Guide 1.99, decreases in
. USE of approxirnately 6.5% are predicted for the weld material. The actualimpact energy curves l ' for the weld show an increase in the USE value of 4.3%. Given the typical scatter in charpy data and the low fluence of the irradiated specimens, an increase in USE is not unexpected. As discussed in Section 5.3, a measured decrease in USE for the plate material could not be directly determined.
s 9 A l l l 25 l
GE-NE-B1301786-01 Revision 0
)
Table 5-1 VALLECITOS QUALIFICATION TEST RESULTS USING NIST STANDARD REFERENCE SPECIMENS l l x , . . ._ - . . . - . . < , 4 - . .< . 4Teste. fEnerg ?Acceptabler; , Temperature : Absor >yiedi- Rangei
- JSpecu, nen JBath;.
M: 4
! Identification? 9 Medium 1 'T('F) ! 3(ft-lb)d -
!(ft-Ib)?
Vallecitos HH-461 Ethyl Alcohol -40 74 Richle Machine HH-46 2 E Alcohol -40 72.5 (tested 8/95) HH-46 3 Eth Alcohol -40 75.5 HH-46 4 Eth Alcohol -40 73 HH-46 5 Eth 1 Alcohol -40 22 Average 74.4 74.313.7 pass LL-451 Et Alcohol -40 13 LL-45 2 Eth Alcohol -40 13 LL-45 3 Eth Alcohol -40 13 LL-45 4 E I Alcohol -40 13 LL-45 5 Et 1 Alcohol -40 J2 Average 13 12.8 0.64 pass ; , SH-51 1 Alcohol 70 170 i SH-5 2 Eth 1 Alcohol 70 170 SH-5 3 Eth Alcohol 70 162.5 1 SH-54 Eth Alcohol 70 161.5 l SH-5 5 Eth Alcohol 70 JM l Average 164.0 164.118.2 pass l h i 26
i GE-NE-B1301786-01 Revision 0 Table 5-2 IRRADIATED CHARPY V-NOTCH IMPACT TEST RESULTS
.... a . Testa; Fracture . Lateral; : Percent Shear.
- ct. jj6 -SLwirnent _ ; Temp" erat'ure; ;Energyg Expansioni !(Msthodfl)j 2_e :h entification9 F("F)4 ?(ft-lbb ;i(mdsTi M' id(%F Base: 28823 -60 7 5 0 Heat C9481-1, 28824 20 7.5 6 17.6 Longitudinal, 28825 0 23 21 49.4 28826 20 58 41.5 53.8 28827 30 32 30 44.3 28828 40 47.5 31.5 43.7 28829 50 44 36.5 40.2 28830 65 99.5 74 67.7 28831 80 101.5 59 70.3 28832 120 88.5 66 82.4 1 28833 200 126 84.5 100 l 28834 300 123.5 87.5 100 l
)
Weld: Heat 5P7397, Lot 0342, Linde 124 Flux 28835 -100 13.5 7 11.1 28836 -60 15 10 21.9 28837 -40 32 30.5 49 28838 -20 45 34.5 58.4 28839 0 55 45.5 67.4 28840 20 67 43.5 80.3 28841 30 43 37 50.6 28842 50 61.5 50.5 65.5 l 28843 80 78 50.5 91 : 28844 120 94 74.5 100 28845 200 82 73 100 l I 28846 300 85 85 100 HAZ: 28847 -60 22 21.5 30.1 28848 -20 27 25 47.2 28849 -10 45 42 54.5 28850 0 47 38.5 68.1 28851 20 106 66 91.5 28852 30 59 40.5 82.2 l 28853 50 71 54.5 87.3 28854 80 64 41.5 91.9 28855 100 86 64 100 28856 120 88 69 100 28857 200 81 68 100 28858 300 84.5 78.5 100 27
GE-NE-B1301786-01 Revision 0 Table 5-3 UNIRRADIATED CHARPY V-NOTCH IMPACT TEST RESULTS
~ . .. . Test ;
- LFracturec . ELateralf ;1 Percent Shear; '
iSpecimenW (Temperatuis? TEnergyi 1Expansiori! , . . . . . Identification? ' (*F)I !(ft-Ib)O 7(mils)2 4(%)4 D W_cli 1 -70 22 22 5 INMM 2 -70 16 18 5 Heat SP7397 3 -70 36 28 5 ; Tandem Wire 4 -10 58 54 25 l (Longitudinal) 5 -10 68 50 20 l 6 -10 61 47 20 7 10 76 60 30 8 10 73 65 45 9 10 75 60 50 10 10 75 58 35 11 10 69 56 35 12 40 91 75 80 13 40 84 63 85 l 14 70 79 73 90 l l 15 70 75 63 95 16 70 77 74 95 17 212 84 69 100 18 212 81 67 100 19 212 87 75 100 b Plate : 1 40 74 61 50 lient C9481-1 2 40 74 53 50 (Longitudinal) 3 40 81 60 50 l 4 40 103 48 40 l 5 40 61 66 50 l 6 40 85 72 60 ' BisA 12 -40 17.0 15.0 5 ; i Heat C9481-1, 10 10 23.5 21.0 10 (Transverse) 11 10 22.0 20.5 10 14 25 36.0 31.0 20-25 8 40 45.0 42.0 30-35 ; 9 40 35.0 34.2 30 13 40 42.0 38.0 30-35 15 51 40.5 35.0 30 1 70 51.0 44.5 40 2 70 50.0 42.5 40 7 93 71.0 58.5 70 3 120 93.0 69.5 90-95 4 200 93.5 74.0 95 5 200 100.0 72.0 95 4 6 200 93.0 69.0 95 I D.'s are listed for numbering only, i.e. I.D.'s were not preassigned b Fabrication Charpy specimen data from Materials Certification Reports in [28] i 28
)
GE-NE-B1301786-01 Revision 0 Table 5-3 J' UNIRRADIATED CHARPY V-NOTCH IMPACT TEST RESULTS gestQ. ;Fracturey ; 9 Lateral 3... :: Percent Shearx
;<-.~.-_
Speciment e; ;i Temperature; BEnergyi 4 Expansions . . - . _ . . Identification % <( W L(ft-lb)r t (mils)! - 4%)J '
) b F_ cit 1 -70 22 22 5 INMM 2 -70 16 18 5 Heat SP7397 3 -70 36 28 5 Tandem Wire 4 -10 58 54 25 (Longitudinal) 5 -10 68 50 20 ) 6 -10 61 47 20 7 10 76 60 30 8 10 73 65 45 9 10 75 60 50 10 10 75 58 35 11 10 69 56 35 i 12 40 91 75 80 13 40 84 63 85 14 70 79 73 90 15 70 75 63 95 16 70 77 74 95 17 212 84 69 100 18 212 81 67 100 19 212 87 75 100 6
Plate : 1 40 74 61 50 Heat C9481-1 2 40 74 53 50 (Longitudinal) 3 40 81 60 50 4 40 103 48 40 5 40 61 66 50 6 40 85 72 60 Bm 12 -40 17.0 15.0 5 Heat C9481-1, 10 10 23.5 21.0 10 (Transverse) 11 10 22.0 20.5 10 14 25 36.0 31.0 20-25 8 40 45.0 42.0 30-35 9 40 35.0 34.2 30 13 40 42.0 38.0 35 15 51 40.5 35.0 30 1 70 51.0 44.5 40 2 70 50.0 42.5 40 7 93 71.0 58.5 70 3 120 93.0 69.5 90-95 4 200 93.5 74.0 95 5 200 100.0 72.0 95 6 200 93.0 69.0 95
" I.D.'s are listed for numbering only, i.e. I.D.'s were not preassigned b
Fabrication Charpy specimen data from Materials Certification Reports in [28] 28
GE-NE-B1301786-01 Revision 0 Table 5-3 UNIRRADIATED CHARPY V-NOTCH IMPACT TEST RESULTS
~ .. rHTest e i Fracture; MLaterale 2 Percent Shear; 4 JSpecimen*J [ Temperature I Energy /I IExpansioni . . .
- g" EIdentification? J('F)i *(ft-Ib)I ~ f(mils)B ?(%)?
b W_di 1 -70 22 22 5 1NMM 2 -70 16 18 5 Heat SP7397 3 -70 36 28 5 Tandem Wire 4 -10 58 54 25 (Longitudinal) 5 -10 68 50 20 6 -10 61 47 20 7 10 76 60 30 8 10 73 65 45 9 10 75 60 50 10 10 75 58 35 11 10 69 56 35 12 40 91 75 80 13 40 84 63 85 14 70 79 73 90 15 70 75 63 95 16 70 77 74 95 17 212 84 69 100 18 212 81 67 100 19 212 87 75 100 1 6 Plate : 1 40 74 61 50 i l Heat C9481-1 2 40 74 53 50 l (Longitudinal) 3 40 81 60 50 4 40 103 48 40 5 40 61 66 50 6 40 85 72 60 l Bmt 12 -40 17.0 15.0 5 Heat C9481-1, 10 10 23.5 21.0 10 (Transverse) 11 10 22.0 20.5 10 14 25 36.0 31.0 20-25 8 40 45.0 42.0 30-35 9 40 35.0 34.2 30 , 13 40 42.0 38.0 30-35 1 15 51 40.5 35.0 30 1 70 51.0 44.5 40 2 70 50.0 42.5 40 7 93 71.0 58.5 70 l 3 120 93.0 69.5 90-95 : 4 200 93.5 74.0 95 I l 5 200 100.0 72.0 95 6 200 93.0 69.0 95 I.D.'s are listed for numbering only, i.e. I.D.'s were not preassigned b Fabrication Charpy specimen data from Materi:ds Certification Reports in [28] ) 28 I
GE-NE-B1301786-01 Revision 0 Table 5-4 SIGNIFICANT RESULTS OFIRRADIATED AND UNIRRADIATED CHARPY V-NOTCH DATA > g !IndedTemp(*F)l )InddTimp( F); LInddx T5mp (*F)l #USET g;gg: pW e 3 pp;ggg jE=50h i6I[ ?ML8=3INill:I ' jfi-lbE i PLATE: Heat C9481-1, Longitudinal Irradiated 11.7 37.3 32.1 124.75 HAZ: Heat C9481-1, Longitudinal
, Irradiated -31.29 10.24 -5.27 84.6 WELD: Heat SP7397 Unirradiated -59.99 -32.10 -43.23 83.3 i Irradiated -41.40 4.12 -0.83 86.9 DifTerence 18.59 36.22 42.40 -3.6 (-4.3%)
Reg. Guide 1.99, Rev 2 ARTswa : 6.5 Reg. Guide 1.99, Rev 2 (Ai2a) a: -49.6 to 62.4
, 1.99, Rev 2. Decrease in USEb; 6.5 %
a Determined in section 5.4.1 b Determined in section 5.4.2 i i / 29
GE-NE-B1301786-01 Revision 0
, Figure 5-1 IRRADIATED CHARPY LS-2, BASE Energy 140 130-120 -
i 110 - 10 T 0-- / s j - , g 80 -
=
[ 70 -
.. /
50 R a. PA y- [A 20 - 10 - < A 0
-200 100 0 100 200 300 400 500 Test Temperature,'F i
Figure 5-2 IRRADIATED CHARPY LS-2, BASE Lateral Expansion p 3# 90 - m
+
80 -
~
70 - 1 A f 60
,0 -
O 40 - A
}3 M- [^
t 20 - 10 - iA 0
-200 -100 0 100 200 300 400 500 i Test Temperature. *F l
i 30 l i
i GE-NE-B1301786-01 Revision 0 ! 1 Figure 5-3 UNIRRADIATED CHARPY 1 ' LS-2, Wold Energy ! 100 i 30 A ; 80
! f l
y 70 ., r E 80 [ m a f,80 w
] 40 A
[
- E E 30 l
20 ;
>/A l a
10 W ! , 0 ,
-200 -100 0 100 200 300 400 500 Test Temperature (*F)
Figure 5-4 4 UNIRRADIATED CHARPY LS-2, Weld Lateral Expansion 100 90 80 - A A 7 A g 70
- 1 ,.
'[
( 50 a
'a ?
30 - ,
/
20 ' lo - >/' M 0
-200 .300 0 100 200 300 400 500 Test Temperature, 'F i
31 l
f b GE-NE-B1301786-01 Revision 0 Figure 5-5 , i IRRADIATED CHARPY ts-2, Wold Energy 3, A g. 80 - [ o , 70 - k A/. s 00 > g ,0 - e/
- g. #! A
} 30 /
l 20 -
,0 J '
0
-200 100 0 100 200 300 400 500 I
Test Temperature,'F l Figure 5-6 IRRADIATED CHARPY LS-2 Weld Lateral Expansion
' 100 90 -
" l 80 -
^
70 - 4 i w > l 50 -
- a. -f fA k ,
3 30
./
20 - l 10 -
' a 0
-200 100 0 100 200 300 400 500 Test Temperature,'F 32
) GE-NE-B1301786-01 Revision 0 . Figure 5-7 ) (RRADIATED CHARPY LS-2. HAZ Energy 120 Mmd , 110 - n TANH fk 4 100- ) 90 - n' "
$ 80 -
i 7 10- . / 40 - so
/
20 -- 10 ) - 0 200 -100 0 100 200 300 400 500 Test Temperature,'F ) Figure 5-8 l
\
IRRADIATED CHARPY LS-2, HAZ Lateral Expansion 100 ) 90 : 80 - n 7 Data not used j 7 70 - a in TANH fit 4 ) 50 -
- t. a
,/ -
M- ) 20 - , l 10 - " 0 200 100 0 100 200 300 400 500 ) Test Temperature. *F 4 33 )
)- - i GE-NE-B1301786-01 Revision 0 ) ) Figure 5-9 ) UNIRRADIATED AND IRRADIATED CHARPY E B.7_ Wald Fnarev 100 90 , y_ Unirradiated - [- --- ----' 70 i e /rradiated E 60 / I w Y SD f I la E /lJ l l
// USE Decrease: -3.6 ft-lbs.
g 30 ft-lb RTndt Shift: 18.6'F t I 20 10 d' - 0 i
-200 -100 0 300 400 500 100 200 Test Temperature, *F t
34
I i GE-NE-B1301786-01 Revision 0 i Figure 5-10 UNIRRADIATED CHARPY LS-2, BASE Energy (Transverse Data) 120 110 100 . A -
- 90 80
*f I
E g 70 g 60 au 50 v 8, 40 g-i E 30 20 10 , 0
-200 -100 0 100 200 300 400 Test Temperature (*F)
I I I 35 l
GE-NE-B1301786-01 Revision 0
- 6. TENSILE TESTING Eight round bar tensile specimens were recovered from the surveillance capsule.
Uniaxial tensile tests were conducted in air at room temperature (70'F) at RPV operating temperature (550*F) and at an intermediate temperature of 150'F for the two additional base and weld specimens. The tests were conducted in accordance with ASTM E8-89 [14]. 6.1 PROCEDURE I 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 by a chromel-alumel thermocouple spot-welded to an Inconel clip that was friction-clipped to the surface of the specimen at its midline. i 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 nominal 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 measured area 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. 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 36
) GE-NE-B1301786-01 - Revision 0 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 i temperature. Photographs of the fracture surfaces and necking behavior are given in Figures 6-2 through 6-4. t )- . 6.3 IRRADIATED VERSUS UNIRRADIATED TENSILE PROPERTIES Only unirradiated room temperature tensile test data was available for comparison. As 3 expected the trends are increasing YS and UTS and decreasing TE (see Table 6-2), characteristic ofirradiation embrittlement in most cases. i I )
)
37
GE-NE-B1301786-01 Revision 0 Table 6-1: Tensile Test Results For Irradiated RPV Materials
, 4 Test lt LYieldai fUltimeate : Uniforiall _ . -sTotal { . : Reduction .
, ; Specionen (Teenp,] Strength ? Strength - Elongation ? 4 Elessgation[ [of Area;:'
; c:Nassbers r(T)L L(ksi) J " (ksi)- c (%)4- 5(%)? F (%F Base: Pl-1 70 64.4 87.7 12.0 21.1 67.3 PI-3 150 63.1 85.7 11.0 20.0 70.1 PI-2 550 57.5 83.4 11.7 18.9 63.6 i
Weld: P2-1 70 69.4 86.2 12.5 21.9 66.6 P2-3 150 73.0 86.2 12.4 22.7 72.5 P2-2 550 66.6 82.7 11.1 18.5 64.6 HAZ: P3-1 70 61.4 86.0 10.8 19.3 71.4 P3-2 550 69.1 78.1 8.6 15.4 70.8 a Yield Strength is determined by 0.2% offset. Table 6-2: Comparison of Unirradiated and Irradiated ( Tensile Properties at Room Temperature YicidlSEreap !. Ultimate Strengthl STEtkl Elongationi SReduction hf Area 3 (ksi): ' (ksi) ? i(%)s 5(%)- 6 Base: Unitradiated 63.8 85.2 26.5 N/A ist Capsule 64.4 87.7 21.1 67.3 l Weld: Unitradiated 64.9 82.2 22.0 65.4 1st Capsule 69.4 86.2 21.9 66.6 b Values taken as average of data in the material certification reports. i l 38
GE-NE-B1301786-01 ; Revision 0 t i
,i 100.0 LaSALLE 2 ~
- i BASE P12 550 F l 75.0 -
~~
e
- m:
50.0 - F
- 25.0 -
F w f 0.0 , , , 0.0 5.0 10.0 15.0 20.0 Engineering Strain, % Figure 6-1. Typical Engineering Stress-Strain for Irradiated RPV Materials i i i 1 t a ! 39
l GE-NE-B1301786-01
,.;L 8 M ( - -' ?.,4 -
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- i& wW.w M O '
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- 6 7 S.9 d TEUFEFEC 5 e i-3 iso e 1 E 3 4 ~
E 7 6.9 1 2
'b' b6LlaLLLI.Lr LiJ J LI kLk t LLLui f Lt . .. . .. .. . i1 2 I n ; Figure 6-2: Fracture Location, Necking Behavior and Fracture Appearance i for Irradiated Base Metal Tensile Specimens.
i 40 i
1 i O GE-NE-B1301786-01 3 unamumenf$' $'
&cfyptigk&
P 'll f W c 6'7 8 9
' l f ll f N' ll f .; lf W 1 2 3 4 bE -
. .h.hf 0fh[I OINIk% $ Ef f' ~
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/ ASS.U S A 5
d IEUFEFEC c D 6 7 6 9 2 2 3 4 " E e : - 9 P~?- l 70oF g tW!)NNk!Ilbh
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a rEve m e 5
.g 6 7 5..s Id L! M khld!!ld did tld!ild ddd d WI M b $ b 'E 12 3'4 f6 7(9 j P2-3 150=F o
, Figure 6-3: Fracture Location, Necking Behavior and Fracture Appearance i l
i for Irradiated Weld Metal Tensile Specimens. i j 41 _.,.m. , , _ . - _ - . . . . _ _ . , , _ , . . _ _ . , _ - r . ,, _ - - _ . , . . _ . ,
GE-NE-B1301786-01 e ,, ,g e - 1 l I}Ij]Nfli[jii!jpjljjf
,I yQjplyj'; jj]yp[jpfjfj'Mijffh r "
7- i - g S 9 -[ 1 2^ 3 4
~
E t A W- J 3 P3-1 70 F ! 5 5.U.S.A 'i TEf/F EF EC - Q ! 67 6 9 1 2 3'4 E " E 9 ~1 E'? l dddhhhN NI iInNS: li;S!E f' ' b t i
- f. *;~$$Q e, y ee: + y 364 g I 'y i dL@M-l MWnewn:ew r.# nh Mwan WmhjdNjf 17lififj'ilflflfjlfllPj'l}fiffHf!fl1lflfffIIfiI 7 r '
W{Ni
-6. v .C 0 ' -
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i SU.SA P3 2 550 F [ TE!/F EF E0 y l 67 E P L3 -; i 6 - e - J , d!!hfShds,!Q)ddddidli! [ ' ' ' A'u@i O:n Ok! M " I i i l jr I A j 4 i Figure 6-4: Fracture Location, Necking Behavior and Fracture Appearance for inadiated HAZ Tensile Specimens. 42 4
- GE-NE-B1301786-01 Revision 0
- 7. ADJUSTED REFERENCE TEMPERATURE AND UPPER SHELF ENERGY The 32 EFPY peak fluence value of 5.38x10 17 n/cm2in Section 4.3 is used to calculate the 32 EFPY 1/4 T fluence value of 3.7x10 17 n/cm2. The 32 EFPY 1/4 T fluence is used in this section to calculate adjusted reference temperatures (ARTS) and upper shelf energy (USE) j- decrease for the beltline materials.
. 7.1 ADJUSTED REFERENCE TEMPERATURE AT 32 EFPY
; The effect on adjusted reference temperature (ART) due to irradiation in the beltline I
materials is determined according to the methods in Reg. Guide 1.99, Rev. 2 [7], as a function of neutron fluence and the element contents of copper (Cu) and nickel (Ni). The specific !~ relationship from Reg. Guide 1.99, Rev. 2 [7] is: ! 1 ART = InitialRT, + ART, + M argin (7-1) ~ where: ART, = CF f*23-owo (7-2) M argin = 2do' + c 2 (7-3) CF = chemistry factor from Tables 1 or 2 ofReg. Guide 1.99, Rev. 2 [7], f= 1/4 T fluence (n/cm2) divided by 1019, c1 = standard deviation on initialRTNDT. cA = standard deviation on ARTNDT,is 28'F for welds and 17 F for base material, except that oA need not exceed 0.50 times the ARTNDT value. The ART values are calculated based upon best estimate chemistry data as described in Section 5.4.1. The chemistry for weld 5P7397 is 0.04% Cu and 0.89% Ni, which has a corresponding chemistry factor of 54. The chemistry for plate C9481-1 is 0.10% Cu and 0.48% Ni, which has a chemistry factor of 65. 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 Initial RTNDT, ARTNDT and Margin are added to get the 43
)-
GE-NE-B1301786-01 Revision 0 ART of the material. The 32 EFPY ART values for all of the beltline plates and several of the .
- most limiting beltline welds are shown in Table 7-1. The ART for the limiting beltline material, plate heat C9404-2, at 32 EFPY is 73.8'F.
7.2 UPPER SHELF ENERGY AT 32 EFPY i Paragraph IV.B of 10CFR50 Appendix G [1] sets limits on the upper shelf energy (USE) ; i of the beltline materials. The USE must be above 50 A-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 values for initial USE were obtained from ;
_ [20] for all but the surveillance plate (C9481-1) where baseline transverse USE data was l available. l t i 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 l transverse / longitudinal correction because weld metal has no orientation effect. The USE i decrease prediction values from Reg. Guide 1.99 [7] were used for the beltline plates and welds in '
- i. Table 7-2. Based on the above results, the beltline materials will have USE values above 50 A-lb !
at 32 EFPY, as required in 10CFR50 Appendix G [1]. The lowest USE predicted for 32 EFPY is 52.1 A-lb (for plate heat C9434-2). Most of the initial weld upper shelf energy data was based on 10*F measurements. ) However, enough Unitradiated Charpy data was available for the surveillance weld (SP7397) to generate a hyperbolic tangent curve fit. From this curve fit the Initial USE of 83.3 ft-lb was determined (Figure 5-5). )- Since USE and ART requirements are met, irradiation effects are not severe enough to necessitate additional analyses. Because adequate USE data is available and all 32 EFPY USE values are above 50 A-lb, adoption of the BWROG equivalent margin analysis [18] is not necessary, ahhough that analysis is applicable and bounding for LaSalle 2. i 44
GE-NECl301786-01 Revision 0 Table 7-1 BELTLINE 1/4 T ART VALUES FOR IASAI.LE UNIT 2 GE Method for Calctdating Initial RTndt Plate Plate Thickness - 6.19 inches 32 EFPY Peak I.D. fluence - 536E+17 32 EFPY Peak 1/4 T fluence - 3.70E+17 wekt weld Thickness = 6.19 inches 32 EFPY Peak LD. fluence = 536E+17 32 EFPY Peak I/4 T fluence = 3.70E+17 Initial 32 EFPY 32 EFPY 32 EFPY COMPONENT IIEATORIIEAT/ LOT %Cu %Ni CF RTndt A RTndt Margin Shift ART T T T T T PLATES: Lower 21-1 C9425-2 0.12 0.51 81 30.0 20.06 20.06 40.13 70.13 21-2 C9425-1 0.12 0.51 81 32.0 20.06 20.06 40.13 72.13 21-3 C9434-2 0.09 0.51 58 10.0 1437 1437 28.73 38.73 Lower-Inemed 22-1 C9481-1 0.11 0.50 73 10.0 18.08 18.08 36.16 46.16 22-2 C9404-2 0.07 9.49 44 52.0 10.90 10.90 21.80 73.80 22-3 C9601-2 0.12 0.50 81 10.0 20.06 20.06 40.13 50.13 Surveillance Pfate(a) C9481-1 0.084 0.45 54 10.0 1338 1338 26.75 36.75 VERTICAL WELDS: LowerIntermediate BA,BB,BC 3P4000 0.02 0.89 27 -50 b 6.7 6.7 13.4 -36.6 Lower BD.BE,BF 3P4966 0.03 0.90 41 6.0 b 10.2 10.2 203 14 3 GIRTilWELD: I lower to Lower-Int. AB 5P6771 0.04 0.95 54 -34.0 b 13.4 13.4 26.8 -7.2 l Surveillance Wekl(a) SP7397 tTandem Wire) 0.03 0.87 41 -70.0 10.2 10.2 203 -49.7 a) Data from CBIN CMTR values. Contract No. 8-CN2% (1980)[2tj (' trutsal RTndt assumed the same as for plate 22-i ) b) These are conservative bounding values from ringle and tandem wire qualifications. 45 _ _ - - - - .- - , . ~ - _ _ _ . _ . _ . . _ . . - . ._ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
4 GE-NE-B1301786-01 Resision 0 Table 7-2 8 Upper Shelf Energy Analysis for LaSalle Unit 2 Beltline Material INITIAL INITIAL
- 32 EFPY*
TEST LONGIT. TRANS %DECR.6 TRANS. 4 LOCATION HEAT TEMP. USE USE %Cu USE USE PLATES: Lower: 21-1 C9425-2
- 102 66.3 0.12 11 57.7 e 21-2 C9425-1 94 61.1 0.12 11 53.2 21-3 C9434-2 40 91 59.2 0.09 9 52.1 Low-Int:
d 22-1 C9481-1 40 - 95.5 0.10' 9.5 86.4 22-2 C9404-2
- 116 75.4 0.07 8 67.5 g 22-3 C9601-2 40 107 69.6 0.12 11 60.6 WELDS:
Low-Int. Vertical: BA,BB,BC 3P4000 10 - 99 0.02 8 91.1 Lower Vertical: BD,BE,BF 3P4966 10 - 84 0.03 8.5 76.9 Girth Welds: Lower to Low.-Int. O AB 5P6771 10 - 61 0.04 9 55.5
- USE values estimated from statistical evaluation in Appendix B of[20]
- Values obtained from (20]
6 2 Values obtained from Figure 2 of[7] for 32 EFPY fluence = 5.38x10" n/cm , O ' 32 EFPY Trans USE = Initial Trans USE * {1 - (% Decrease USE /100)} d Value obtained from baseline transverse data set [28]
- Value obtained from best estimate surveillance chemistry results (Table 3-3)
D D 46
,_- . _ . . . - - - . - - -. - - . . . = -.- - .. . . - - - -.
F
). !
GE-NE-B1301786 ')1 ! Revision 0 -
- 8. REFERENCES !
)- !
[1] " Fracture Toughness Requirements," Appendix G to Part 50 of Title 10 of the Code of Federal Regulations, July 1983. ! i [2] " Protection Against Non-Ductile Failure," Appendix G to Section XI of the 1992 ASME Boiler & Pressure Vessel Code. j [3] " Reactor Vessel Material Surveillance Program Requirements," Appendix H to Part 50 j' of Title 10 of the Code of Federal Regulations, July 1983, t t
'[4] " Surveillance Test for Nuclear Reactor Vessels," Annual Book of ASTM Standards, ;
E185-73, March 1973 [ T , [5] LaSalle Unit 2 Steam Electric Station Final Safety Analysis Report, Section 5.3 i [6] " Conducting Surveillance Tests for Light Water Cooled Nuclear Power Reactor Vessels," Annual Book of ASTM Standards, E185-82, July 1982. 7 [7] " Radiation Embrittlement ofReactor Vessel Materials," USNRC Regulatory Guide 1.99, Revision 2, May 1988. !
)
[9] CBIN, QA Records for LaSalle 2 Replacement Surveillance Test Specimens, Contract Number 8-CN203, General Electric VPF# 6078-017-1 April 1980. [10] CBIN, " Surveillance Test Specimen Preparation Plan for Contract: LaSalle 2 RPV",
)
Contract 8-CN203, General Electric VPF# 6078-014-4, November 1979. [11)- R. G. Carey, "LaSalle County Unit 2 Surveillance Program Evaluation," GENE, San Jose, CA, January 1996, (GE Report GE-NE-523-155-1292). [12] " Standard Methods for Notched Bar Impact Testing ofMetallic Materials," Annual Book of ASTM Standards, E23-88 [13] " Nuclear Plant Irradiated Steel Handbook," EPRI Report NP-4797, September 1986. 47
, _ , , , , -_4.
l GE-NE-B1301786-01 ) Revision 0 f i [14] ." Standard Methods ofTension Testing ofMetallic Materials," Annual Book of ASTM i j Standards, E8-89. l r [15] T. A. Caine, " LaSalle County Station Units 1 and 2 Fracture Toughness Analysis Per ! 10CFR50 Appendix G," GENE, San Jose, CA, March 1988,(GE Number SASR 88-10). j
) : - [16] internonallyleft blank i
i
' [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 Report NEDO-32205, Revision 1, '10CFR50 Appendix G Equivalent Margin l y Analysis for Low Upper ShelfEnergy 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 2", GENE, San Jose, CA, October 1987, (GE Report SASR 87-59). ) [20] T. A. Caine, " Upper ShelfEnergy Evaluation for LaSalle Units 1 and 2," GENE, San Jose, CA, June 1990, (GE Report SASR 90-07). ) [21] intentionallyleft blank [22]. intentionally left blank ) [23] LaSalle Unit 2 Steam Electric Station Updated Final Safety Analysis Report, Section 5.2. 1 [28] Letter, dated 3/16/94, G.W. Contreras, GE San Jose, to R. Willems, GE Oak Brook, ! subject LaSalle RPV Archive Material Records Search. l [29] Martin, G.C., " Browns Ferry Unit 3 In-Vessel Neutron Spectral Analysis," GENE, San Jose, CA, August 1980, (GE Report NEDO-24793). ) 48
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O GE-NE-B1301786-01 Revision 0 l
- 3. APPENDIX A j IRRADIATED CHARPY SPECIMEN FRACTURE SURFACE PHOTOGRAPHS 1 i
Photographs of each Charpy specimen fracture surface were taken per thic requirements of g ASTM E185-82. The pages following show the fracture surface photographs along with a summary of the Charpy test results for each irradiated specimen. The pictures are arranged in the : order of base, weld, and HAZ materials. 9 D k D l t b D D A-1
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, GE-NE-B1301786-01 i BASE: 28823 . BASE: 28824 Temp: -60 F Temp: -20 F
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Energy: 7 fl-lb c f. ; Energy: 7.5 fi-lb MLE: 5 mils _ ] MLE: 6 mils Shear: 0% Shear: 17.6 % BASE: 28825 BASE: 28826
- '7.f f
~
j Temp: 0F . Temp: 20 F Energy: 23 ft-lb 1. . Energy: 58 ft-lb MLE: 21 mils ,
--. 4 , MLE: 41.5 mils
~
~
Shear: 49.4 %
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j 2 Shear: 53.8 % ) ( 1 j l l BASE: 28828 [ B ASE: 28827 [ i Temp: 30 F - Temp: 40 F ( 1 Energy: 32 ft-lb Energy: 47.5 ft-lb l MLE: 30 mils MLE: 31.5 mils l Shear: 44.3 % . Shear: 43.7 % l BASE 28829
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BASE: 28830 l Temp: 50 F . Temp: 65*F ( Energy: 44 ft-lb ; , Energy: 99.5 ft-lb ! MLE: 36.5 mils - MLE: 74 mils I i ! Shear: 40.2 % D- . s Shear: 67.7 %
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/ i I A-2 1
l O i GE-NE-B1301786-01 lO ! i B ASE: 28831 , , , BASE: 28832 jo Temp: 80'F , Temp: 120 F
- Energy: 101.5 ft-lb Energy: 88.5 ft-lb MLE: 59 mils MLE: 66 mils Shear: 70.3 % -
. Shear: 82.4 %
O . BASE: 28833 .- BASE: 28834 l l Temp: 200 F . ~Qf . Temp: 300 F
- 9 Energy
- 126 ft-lb ..$ Energy: 123.5 ft-lb MLE: 84.5 mils MLE: 87.5 mils my. t.
Shear: 100 % , . .
' Shear: 100 %
!O WELD: 28835
.- p WELD: 28836
!O Temp: -100 *F :
.-} f Temp: -60 F
{ Energy: 13.5 ft-lb .' - Energy: 15 ft-lb MLE: 7 mils i MLE: 10 mils l . J..' l Shear: 11.1 % - Shear: 21.9 % j
'~
lO - WELD: 28837 - WELD: 28838 l l , Temp: -40 F J ' Temp: -20 F I Energy: 32 ft-lb - Energy: 45 ft-lb
'O MLE: 30.5 mils .
MLE: 34.5 mils Shear: 49 % '> Shear: 58.4 % 1 iO l i iO
- A-3 i
i i....__.. -- . - _ - . _ . . , , - . _ . - . . _ . _ . - _ . _ _ - _ _ - _ _ _ _ _ __
,0 ! GE-NE-B1301786-01 ! l 'O . l i l WELD: 28839 g, . - WELD: 28840 l lO Temp.O F '
.@,i Temp: 20 F Energy: 55 ft-lb k Energy: 67 R-lb l .
MLE: 45.5 mils Y: MLE: 43.5 mils l ' Shear: 67.4 % - Shear: 80.3 % l
,O WELD: 28841 ,
WELD: 28842 ! Temp: 30'F .
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Temp: 50'F fo Energ,y: 43 R-lb (. Energy: 61.5 ft-lb i MLE: 37 mils c: MLE: 50.5 mils
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l Shear: 50.6 % :- . Shear: 65.5 % l Q l WELD: 28843 - WELD: 28844 f Temp: 80 F - Temp: 120 F o Energy: 78 ft-lb Energy: 94 R-lb { MLE: 50.5 mils ,
- e. . MLE: 74.5 mils 2 . ,
Shear: 91 % Shear: 100 %
- O l WELD: 28845 g WELD: 28846 j Temp: 200 F .1.' . .
Temp: 300 F Energy: 82 fl-lb ,. 7.; ',r: :1
*,.p
, Energy: 85 ft-lb MLE: 73 mils l.7 i 4, -! MLE: 85 mils
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i Shear: 100 % h. Shear: 100 % __1 l l l h , A-4
GE-hT-B1301786-01 i HAZ: 28847 - .. HAZ: 28848 7 Temp: -60 F , Temp: -20 F Energy: 22 ft-lb ;- . Energy: 27 n-lb MLE: 21.5 mils : MLE: 25 mils
~- h Shear: 47.2 %
Shear: 30.1 % . i HAZ: 28849 HAZ: 28850 l Temp: -10 F - i Temp: 0F Energy: 45 ft-lb . Energy: 47 ft-Ib l MLE: 42 mils . MLE: 38.5 mils l Shear: 54.5 % ~, E .' Shear: 68.1 % l HAZ: 28851 p- HAZ: 28852 i Temp: 20 F ' Temp: 30 F l Energy: 106 n-lb . ,
~
Energy: 59 n-lb l MLE: 66 mils MLE: 40.5 mils Shear: 91.5 % Shear: 82.2 % l , r HAZ: 28853 . HAZ: 28854 Temp: 50 F - Temp: 80 F Energy: 71 n-lb Energy: 64 A-lb l ' l MLE: 54.5 mils .. i MLE: 41.5 mils ! Shear: 87.3 % ! - Shear: 91.9 % , c . l i A-5
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GE-NE-B1301786-01
)
HAZ: 28855 , HAZ: 28856 4
) Temp: 100 F ,
Temp: 120 F Energy: 86 n-lb - p ,, Energy: 88 R-lb MLE: 64 mils .. i: .i' MLE: 69 mils
~
Shear: 100 % - Shear: 100 %
) > ,
HAZ: 28857 HAZ: 28858 Temp: 200 *F '. -
+ Temp: 300 F )
Energy: 81 n-lb , '.- Energy: 84.5 R-lb MLE: 68 mils r -
- MLE: 78.5 mils Shear: 100 % - 1. ,
Shear: 100 % l r I ) ! I L l A-6
- u. . . _ . . . - .- ..
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