ML20128B790
| ML20128B790 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 01/22/1993 |
| From: | ATI, SARTREX CORP. |
| To: | |
| Shared Package | |
| ML19303F252 | List: |
| References | |
| GL-92-01, GL-92-1, NUDOCS 9302030177 | |
| Download: ML20128B790 (101) | |
Text
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I.IJ l ATTACHMENT E San Onofre Nuclear Generating Station, Unit 3 Response to Generic letter 92-01 Revision 1 i
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L San Onofre Nuclear Generating Station, Unit 3 Response to Generic Letter 92-01 Revision 1 January 22,1993 Prepared by:
ATI Consulting San Ramon, CA and Sartrex Corporation Rockville, MD Prepared for:
Southern California Edison Irvine, CA
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CONTENTS -
Section Eage 1 INTRODUCTION 11 2 REACTOR PRESSURE VESSEL SURVEILLANCE 21 PROGRAM COMPLIANCE WITH APPENDIX 11 ,
3 FRACTURE MECHANICS 31 3.1 COMPLIANCE WITH APPENDIX G 31 3.2 BELTLINE MATERIALS IN SONGS, UNIT 3 31 3.2.1 1.ocation 31 3.2.2 }{ eat Treatment 32 3.2.3 Key Residual and Alloying Element Contents 32 3.3 FRACTURE TOUGliNESS RELATED DATA 33 3.3.1 Beltline Plate Material 33 3.3.2 Beltline Welds 35 4 ISSUES RELATED TO GENERIC LETTER 88-11 41 4.1 VESSEL TEMPERATURE DURING OPERATION 4-1 4.2 APPLICABILITY OF SURVEILLANCE DATA 41 4.3 SillFTS AT THE CHARPY V-NOTCil 30 FT-LB ENERGY LEVEL 42 4.4 UPPER SHELF ENERGY DROP 43 5 ' UPPER SHELF ENERGY EVALUATION FOR CIRCUMFERENTIAL 51
- WELD 8-203 5.1 EVALUATION PROCEDURE 51-5.2 RESULTS 52-6 REFERENCES :6-1
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i CONTENTS (cont'd)
SEllen Pagt APPENDIX A SONGS, UNIT 3: EVALUATION OF COMPLIANCE A1 WITH ASTM E185-73 AND E185 82 j 1
APPENDIX B SONGS, UNIT 3: BASES FOR PLATE CHEMISTRY D-1 !
MEASUREMENTS (Proprietary) ,
l APPENDIX C SONGS, UNIT 3: BASES FOR WELD C-1 )
CilEMISTRY MEASUREMENTS (Proprietary)
APPENDIX D SONGS, UNIT 3: WMCs FOR DELTLINE D1 MATERIALS (Proprietary)
APPENDIX E SONGS, UNIT 3: MCRs FOR DELTLINE E1 MATERIALS (Proprietary) )
APPENDIX F SONGS, UNIT 3: UNIRRADIATED Cm DATA. F1 FOR PLATES AND WELDS APPENDIX G SONGS, UNIT 3: ilAZ TEST RESULTS G1 APPENDIX H SONGS, UNIT 3: IRRADIATED Cm DATA FROM H1 CAPSULE 97 i
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t ILLUSTRATIONS fisc PRC 3-1 SONGS, Unit 3: Location and Identification of 3-6 Beltline Plates and Welds 3-2 SONGS, Uriit 3: Data and Least Squares Fit Curve 37 forCm versus Ti mperature, Plate C68021, TL Orientation, MCR Data 3-3 SONGS, Unit 3: Data and Least Squares Fit Curve for 38 Cm versus Temperature, Plate C6802 2, TL Orientation, MCR Data 3-4 SONGS, Unit 3: Data and Least Squares Fit Curve for 39-Cvu versus Temperature, Plate C6802 3, TL Orientation, MCR Data 35 SONGS, Unit 3: Data ruid Least Squares Fit Curve for 3 10 Cm versus Temperature, Plate C6802-4, TL Orientation, MCR Data 3-6 SONGS, Unit 3: Data and least Squares Fit Curve for 3-11 Cm versus Temperature, Plate C6802-5, TL Orientation, MCR Data 3-7 SONGS, Unit 3: Data and Least Squares Fit Curve for 3-12 Cm versus Temperature, Plate C6802-6, TL Orientation, MCR Data 3-8 SONGS, Unit 3: Data and Least Squares Fit Curve for _ 3-13 Cm versus Temperature, Plate C6802-1, TL Orientation, Surveillance Baseline Data 3-9 SONGS, Unit 3: Data and Least Squares Fit Curve for 3 14 Cm versus Temperature, Plate C6802-1 TL Orientation, Combined MCR and Surveillance Baseline Data 3-10 SONGS, Unit 3i Data and Least Squares Fit Curve for 3-15 Cm versus Temperature, Plate C6802-1, LT Orientation, Surveillance Baseline Data
1 ILLUSTRATIONS (cont'd)
EiELLtc HEC 3-11 SONGS, Unit 3: Data and Least Squares Fit Curve for 3 16 Cvu versus Temperature, Plate C6802-1, LT Orientation, MCR Data 3-12 SONGS, Unit 3: Data and Least Squares Fit Curve for 3 17 Cvu versus Temperature, Weld 3-203, WMC Data 3-13 SONGS, Unit 3: Data and Least Squares Fit Curve for 3 18 Cvu versus Temperature, Weld 9-203 (Heat No. 90069), WMC Data 3-14 SONGS, Unit 3: Data and least Squares Fit Curve for 3 19 Cvu versus Temperature, Weld 9 203 (Heat No. 90144), WMC Data l 3 15 SONGS, Unit 3: Data and Least Squares Fit Curve for 3 20 Cvu versus Temperature, Survd11ance Weld, Surveillance Baseline Data 4-1 SONGS, Unit 3: Comparison of the Least Squares Fit for the 4-4 Unitradiated Baseline Data with the Irradiated Cvu Data and Least Squares Fit for the Data from Capsule 97, Plate C6802-1, TL Orientation 4-2 SONGS, Unit 3: Comparison of the Ixast Squares Fit for the 4-5 Unirradiated Baseline Data with the Irradiated Cvu Data and Least Squares Fit for the Data from Capsule 97, Surveillance Weld 5-1 SONGS, Unit 3: Material J-R Curve for Upper Shelf Toughness 5-4 Evaluation of Circumferential Weld 8-203 5-2 SONGS, Unit 3: Applied and Material J/T Plots for Upper Shelf 5-5 Toughness Evaluation of Circumferential Weld 8-203
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TABLES IaMc .Page 3.1 SONGS, Unit 3: . Compliance with 10CFR50, Appendix G - L3-21:
3.2 SONGS, Unit 3: Plate and Corresponding Heat Numbers for. 23 --
Beltline Plates. -
3.3 SONGS, Unit 3: Weld Wire and Flux Combinations for Beltline 3-241 and Surveillance. Welds-3.4 :;3NGS, Unit 3: Key Residual and Alloying Element Contents 3-25' for. Beltline Plates 3.5 SONGS, Unit 3: Key Residual and Alloying Element Contents = 3-26 for Beltline Welds.
3.6 SONGS, Unit 3:-- Beltline Plate Material Unitradiated Fracture - 3-27 J Toughness Tests Results Summary, TL Orientation 3.7 SONGS, Unit 3: Charpy Absorbed Energy Values at 20*F for Weld 28 :
Seams 2 203 A, B, and C -
3.8 SONGS, Unit 3: Beltline Weld Material Unirradiated Fracture :3-29 Toughness Tests Results Summary 41 SONGS, Unit 3: Surveillance Capsule Shift Results '4 4.? SWGS, Unit 3: . ART Estimates at the Inner Surface' Location - E4-71 a for Be!tline Materials on.12/16/91 and at 32 EFPY 4.3 SONGS,-_ Unit-3f Surveillance Capsule Upper Shelf Results- '4-8-_
4.4 - SONGS, Unit 3: -Upper Shelf Estimates at the Quarter-Thickness 9 -- .
< Location'for Beltline Materials on 12/16/91 and at 32 EFPY~.-
'l SONGS, Unit 3: Evaluation of Appendix X : 0.1' inch Flaw - 5-6'-
5.1=
1 Extension Criterion for Circumferential Weld 8-203 g 5.2- ; SONGS, Unit 3: Evaluation _of Appendix'X Instability S-7 Criterion for Circumferential Weld 8-203-
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Section 1 INTRODUCTION The Nuclear Regulatory Cor Won (NRC) in Generic Letter 92-01 (GL 92-01) requested all holders of operating licen_ e construction permits for nuclear power plants to submit information needed to assess compliance with requirements and commitments _regarding reactor-vessel integrity. Revision 0, June 24,1992, of this report was preparea in response to GL 92-01 for San Onofre Nuclear Generating Station (SONGS), Unit 3. It identified additional information needed to resolve fae following issues: (1) inconsistencies in copper (Cu) and nickel -
(Ni) contents and Charpy impact properties reported for beltline Weld 9-203 and the surveillance weld, (2) locating material certification reports to confirm beltline weld properties, (3) identifying the Charpy impact properties, chemistry, and fluence for Weld S-203, and (4) resolving inconsistencies between Charpy impact properties reported in the materials certification report and the materials surveillance program for the longitudinal orO , < tion in Plate C6802-1.
This revision (Revision 1) incorporates additional materials data obtained from the SONGS, Unit 3, Nuclear Steam Supply System (NSSS) vendor, ABB-Combustion Engineering (ABB-CE), the results of calculations performed by Southern California Edison Company (SCE) to better characterize fluence conditions a' Weld 8-203, and the results from calculations performcd to evaluate the upper shelf toughness for Weld 8-203.
Based on a review of the information: (1) inconsistencies in the Charpy. impact properties reported for beltline Weld 9-203 and the surveillance weld have been resolved, (2) the beltline weld properties have been confirmed except for circumferential Weld 8-203 and for chemistry values reported for a girth weld that was not clearly identified in documents supplied by ABB-CE, (3) evaluations for Weld 8-203 have been completed, and (4) an evaluation of- the inconsister.cies between Charpy impact properties reported in the materials certification report and mat: rials surveillance program for Plate C68021 has been completed. To complete the response to GL 92-01, additional information will be required to confirm heat numbers for the surveillance weld material and to identify the weld heat number for the unidentified girth weld chemistry. SCE will continue to work with ABB-CE to obtain the additional information.
Section 2 of this report addresses compliance with 10 CFR Part 50 (10CFR50), Appendix H, for the surveillance program at SONGS, Unit 3. Compliance with 10CFR50, Appendix G, is described in Section 3 along with a description of the location, her.t treatment, residual and alloying element contents, and upp<r shelf and transition temperature fracture toughness for the.
beltline materials in the SONGS, Unit 3, reactor vessel. Section 4 addresses embrittlement effects, including irradiation temperature and adjusted reference temperature for evaluation of .
the beltline materials relative to GL 88-11 and 10CFR50.61. Section 5 preser/s the upper shelf toughness evaluation performed fer circumferential Weld 8-203.
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l Section 2 REACTOR PRESSURE VESSEL SURVEILLANCE PROGRAM COMPLIANCE WITH APPENDIX H The American Society of Mechanical Engineers (ASME) Code of record for the SONGS, Unit 3, reactor pressure vessel is the 1971 Edition through the Summer 1971 Addenda. Consequently, the applicable version of American Society for Testing and Materials (ASTM) E185 is the 1970 version (ASTM E185-70). However, the surveillance program for SONGS, Unit 3, was updated - l to the later 1973 version which is in more complete agreement with the intent of 10CFR50, l Appendix H. Appendix A to this report provides a detailed review of ASTM E185-73 along !
with validation that ASTM E185-73 requirements were satisfied for the surveillance program l design. With respect to capsule testing and reporting requirements, the latest version of ASTM l E185 is required, and these requirements have been updated as listed in Appendix A following ASTM E185-82 (the current approved version).
As stated in the SONGS, Units 2 and 3 Final Safety Analysis Report (FSAR), Appendix H,. .
requirements were met (with one exception) through compliance with ASTM E185-73. The one l exception to meeting Appendix H requirements had to do with the method of attachment of the holders for the six surveillance capsules in each SONGS unit. ABB-CE was the vessel-l manufacturer and the NSSS vendor; ABB-CE attached the capsule holders directly to the cladding on the inside of the vessel in the beltline region (as they did for all ABB-CE NSSS-designed vessels), and this approach violated the requirements in the early 1970's version of 10CFR50, Appendix H. NRC reviewed a ABB-CE Topical Report (CENPD-155-P, C-E Procedure for the Desien. Fabrication. Installation. and Insoection of Surveillance Holder Assemblies) and found the practice and procedures acceptable.
The current version of Appendix H does not treat this method of attachment of the capsule holders as a noncompliance issue. The wording in the current Appendix H,Section I.A.2, is:
"If the capsule holders are attached to the vessel wall or to the vessel cladding, construction and in-service inspection of the attachments and the attachment welds must be done according to requirements for permanent structural attachments to reactor vessels given in Sections III and XI of the ASME Code. The design and location of the capsule holders shall permit insertion of replacement capsules."
This wording was derived from the ABB-CE Topical Report, and the SONGS units have met the additional ASME Code, Sections III and XI, design and inspection requirements. Therefore, there are no deviations or exceptions needed from the current Appendix H of 10CFR50.
The details of the SONGS, Unit 3, surveillance program have been described in the FSAR and subsequent surveillance program testing reports, baseline m and irradiated.m The first capsule results have been evaluated for a low fluence following ASTM E185-82 testing and reporting 2-1 L
requirements. Later sections of this report will discuss these results as compared to regulatory prediction methods. -
The update of ASTM E185 for 1992 (E185 93) is about to be approved and issued. One significant change from El85-82 is the removal of the requirements for testing heat-affected-zone (HAZ) material. This change has resultec from the difficulty in interpreting HAZ results due to the degree of scatter ar.d the ability to define the usefulness of blunt notch Charpy V-notch absorbed energy (C,,w) HAZ data. NRC has been involved in making this change to E185 through ASTM standards participation. Because of this forthcoming change to ASTM E185, this report does not evaluate HAZ results for SONGS, Unit 3; however, the raw data from prior HAZ testing on the SONGS, Unit 3, beltline material has been reported previously,H 'l and is provided for reference in a subsequent section of this report.
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Section 3 FRACTURE MECHANICS This section evaluates compliance with 10CFR50, Appendix G, and identifies the location, heat treatment, key residual and alloying element contents, and unirradiated fracture toughness propenies for plates and welds in the SONGS, Unit 3, reactor pressure vessel beltline region.
The information presented in this section has been obtained from the materials certification reports (MCRs), welding materials certifications (WMCs), the FSAR for SONGS, Unit 3, and from additional information supplied by ABB-CE to prepare this response, in some instances, additional information was obtained from the unirradiated baseline. surveillance material report,m and the irradiated material in the 97* location surveillance capsule (Capsule 97), which was removed from Unit 3 at the end of the fourth fuel cycle.A 3.1 COMPLIANCE WITH APPENDIX G The materials in the beltline region of SONGS, Unit 3, comply with the requirements of.
Appendix G,10CFR50. A summary of compliance with 10CFR50, Appendix G, as specified in the FSAR for SONGS, Units 2 and 3,and updated during preparation of this report, is listed in Table 3.1.
3.2 BELTLINE MATERIALS IN SONGS, UNIT 3 3.2.1 Location Figure 3-1 is a representation of the SONGS, Unit 3, reactor pressure vessel, and identifies the plates and welds and their location in the beltline region.
The heat numbers for the: beltline plates shown in Figure 3-1 are presented in Table-3.2.
The weld wire and flux combination for the beltline welds shown in Figure 3-1 and the surveillance welds are presented in Table 3.3. Source documentation has been obtained to -
confirm the properties of beltline plates and welds, with the exception of circumferential Weld 8-203 and for chemistry values provided in one document ' for a girth weld that was unidentified. Source documentation has not yet been obtained for the sutveillance weld.
Work is continuing with ABB-CE to obtain source documentation for the surveillance weld and the unidentified girth weld.
Source documentation material has not been located to confirm the chemical composition.-
and upper shelf energy properties for Weld 8 203. Because it is unlikely that source-materials will be obtained for Weld 8-203, conservative analyses have been performed to 3-1
determine adjusted reference temperature (see Section 4.3) and demonstrate adequate upper shelf toughness (see Section 5) for circumferential Weld 8-203.
3.2.2 Heat Treatment' The heat treatme,t for the plate materials consisted of austenitization at 1575 iS0"F for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; water quenched and tempered at 1225 i 25'F for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. For ASME Code qualification, the plates were stress relieved at 1150 i 25'F for 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> and then were furnace cooled to 600"F at a rate of 100 F/hr. The actual time at temperature for a specific l weld or a plate in the vessel depended upon the sequence of vessel fabrication; intermediate d and final stress relief times were selected such that the total did not exceed 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> for any particular portion of the vessel. Longitudinal weld seams would see stress relief ilmes near the 40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> maximum, while the closing girth weld in the beltline region would see i approximately half this amount of time maximum. All of the testing of plate materials was performed on pieces with essentially an identical heat treatment as the actual reactor vessel.
The surveillan:e weldment received a final 41-hour and 45-minute stress relief at 1100"F to 1150"F. I 3.2.3 Kev Residual and Allovine Element Contents )
i The copper (Cu), nickel (Ni), phosphorus (P) and sulfur (S) contents reported for each j beltline plate are presented in Table 3.4. The plate Cu, Ni, P,and S contents were obtained j by averaging two measurements made by ABB-CE. The first measurement was made when ABB-CE received the plate from Lukens, and the second measurement was made when the surveillance program was defined. The bases for the Cu, Ni, P,and S contents reported by CE and listed in Table 3.4 are presented in Appendix B.
A second set of data is included for Plate C6802-1. This set was obtained from broken i surveillance specimens when the first irradiated surveillance capsule from Unit 3 was tested.A )
Table 3.5 contains the Cu, Ni, P, and S contents reported for the beltline welds. With the exception of Weld 8-203, the source documents for the information in Table 3.5 are presented in Appendices C and D. Because Cu and Ni were not measured for beltline Weld 8-203, conservative values of 0.35 wt% and 1.0 wt%, respectively, have been assumed (see :
Regulatory Guide 1.99, Revision 2). Three chemistry measurements have been made for j the surveillance weld and also are reported in Table 3.5. The first chemistry measurement !
was made as part of the original baseline m , while the second and third were obtained from broken Charpy specimens from Capsule 97m, The surveillance weld was reported by ABB-CE to have been fabricated using one of the -
wcld wire and flux combinations in Weld 9-203 (see Table 3.3) -Because the source documentation necessary to confirm the heat number for the surveillance weld has not been i obtained from ABB-CE, the surveillance weld and beltline Weld 9-203 are listed and y
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evaluated separately in the report. ABB-CE is continuing their investigation to obtain this
- documentation.
Tables 3.4 and 3.5 also include the chemistry factors determined for each reported set of Cu and Ni contents using Regulatory Guide 1.99, Revision 2.
3.3 FRACTURE TOUGHNESS RELATED DATA This section presents the results from the Cm tests, and summarizes the upper shelf energies (USE) and the results from the drop weight nil ductility temperature (NDT) tests for the unirradiated beltline plate and weld materials in SONGS, Unit 3. The unirradiated reference temperature (RTum) values were determined from the Cm and NDT test results in accordance with the most recent version of ASME Section III, NB-2331. The upper shelf energies were determined using the definition specified in ASTM E185-93 (to be issued).
The data included in the USE determination were the Cm values for those tests (at least
- 3) where the percent shear on the fracture surfaces was equal to and greater than 95E The fracture toughness data for the plate were obtained from the MCRs (see Appendix E of this report) and baseline surveillance program.N The fracture toughness data for the beltline welds were obtained from the FSAR and confirmed by WMCs (see Appendix D of this report), and the data for the surveillance weld was obtained from the baseline surveillance program. For convenience, the Cm, lateral expansion, and fracture appearance
(% shear) data for the unirradiated beltline and surveillance plate and weld materials are listed in tabular form in Appendix F of this report.
As discussed earlier in Section 2, the results for HAZ material are not evaluated in this report because upcoming ASTM standard E185-93 willnot require HAZ material to be part of the surveillance program. The raw Cm data for the past HAZ testing are attached in Appendix G of this report.
3.3.1 Beltline Plate Material Because fracture toughness requirements for reactor pressure vessels are based on requirements to test specimens oriented transverse to the rolling direction, the data presented here are for the transverse (TL) orientation with one exception. The exception -
is for the beltline Plate C6802-1,which was included in the surveillance program. Because the surveillance program for SONGS, Unit 3,was reported to contain longitudinally (Ur) oriented specimens, data obtained from the MCRs and the baseline surveillance program for specimen reported to be in the LT orientation are presented for completeness.
The transverse Cm data as a function of test temperature for beltline Plate numbers C6802-1, -2, -3, -4, -5, and -6 are presented in Figures 3-2 through 3-7, respectively. For convenience, an average curve through the data is also shown in each figure. The average curves were determined using a least squares fit to the data and a hyperbolic tangent functional form, where the lower shelf was fixed at 2.2 ft-lb and the upper shelf was fixed 3-3 i
l at the value determined using the definition in ASTM E185-93 for specimens having fracture surfaces with 95% and greater shear. For convenience, the figures also indicate the values of NDT, USE, the temperature at which a minimum Cyne quals to 50 ft-lb (T @ 50 ft-lbs) _'
is achieved consistent with the applicable method of ASME, Section Ill, NB-2331, and ~
RTym.
- As part of the surveillance program, additional Cvy versus temperature data were generated for Plate C6802-1;V3t hese data are presented in Figure 3 8 along with a least squares fit .
curve. Because there was a relatively wide gap in the test temperatures near the 50 ft-lb level for the surveillance baseline data set in Figure 3-8,the graphical method of NB-2331 h)(4) was used to determine RTum. The 50 ft-lb temperature was determined - by the intersection of the dashed line and the 50 ft lb level as shown in Figure 3 8. The dashed l line was drawn parallel to the least squares fit line at 50 ft-lb so that it was on, or to the j right of, all data points in the transition region. ;
The data obtained when the plate material was purchased (Figure 3-2) and the surveillance baseline data (Figure 3-8) were combined as shown in Figure 3-9. The combined data set presented in Figure 3-9 was used to determine RTum and the USE for the TL orientation i in Plate C6802-1. The average curve through the combined data set in Figure 3-9 also was j used as the unirradiated baseline to evaluate the results for the irradiated surveillance tests '
(see Section 4).
Table 3.6 is a summary of the unirradiated NDT, RTum, and US values for the TL orientation for each of the beltline plates in SONGS, Unit 3. The NDT for Plate C6802-1 also was determined twice. One value was measured when the material was purchased, while the second value was determined from the unirradiated baseline tests. The higher of these values is listed in Table 3.6.
The methods used to determine RTum from the NDT and Cyg data also are identified in -l Table 3.6. The method of NB-2331 (a)(3) was used to determine RTum for all plates except for the combined data set of Plate C6802-1 (see Figure 3-9), where the graphical method .l of NB-2331 (a)(4) was used because there is a relatively wide spread in the test temperatures near the 50 ft-lb level.
Figure 3-10 shows the data and least squares fit line for the LT orientation for surveillance Plate C6802-1,HI while Figure 3-11 shows the data and least squares fit line for the LT l orientation reported in the MCR for Plate C6802-1. A comparison of the information in i Figures 3-10 and 3-11 indicates a significant difference in the Cyn versus temperature curves l' obtained from the MCR and surveillance program in the LT orientation for Plate C6802-l.
An additional review of the Cv3 versus temperature curves for the beltline plates in SONGS, Unit 3,was performed to assess the source'of the difference in the Charpy curves obtained ;
in the LT orientation for Plate C6802-1 from the MCRs and surveillance program. A j comparison of the data-reported in the MCRs for the LT orientation for all other beltline plates indicated relatively large differences between the MCR and surveillance program 4
3-4 ,
. data.' This result indicates that the surveillance plate was not made from one of the other plates in the SONGS, Unit 3, beltline.
Based on these comparisons, the baseline and' irradiated surveillance data- for the LT orientation are not used for assessing the SONGS, Unit 3, beltline plate because: (1) source material indicate surveillance specimens reported to be in the LT orientation are not representative of the LT orientation of any of the beltline plates, and (2) adequate surveillance specimens for the required TL direction currently are available to satisfy Appendix H to 10CFR50. Although the results for the LT orientation are not used in Section 4 for assessing irradiation response, the tabulated data for irradiated LT data are included for reference in Appendix H to 10CFR50.
3.3.2 Beltline Welds A full Cm versus temperature curve was obtained for the material in Weld Seams 3-203 A, B, C, and the data points and least squares hyperbolic tangent fit through the data are presented in Figure 3-12. A full Cm versus temperature curve was obtained for the Type Mil B-4 Wire, Heat No. 90069, Linde Type 124 Flux, Lot No. 0951 and Heat No. 90144, H Linde Type 124 Flux, Lot No.1061 in beltline Weld Seam 9-203; the Cm data and least squares hyperbolic tangent fits through the data are presented in Figures 3-13 and 3-14, respectively. The material in beltline Weld Seams 2-203 A, B, C was tested to obtain three Cm data points at 20 F. The results from these tests are presented in Table 3.7.
Figure 3-15 presents the Cm data and least squares hyperbolic tangent curve. fit for the surveillance weld material. A comparison of Figures 3-14 and 3-15 indicates that the impact energy versus temperature curves for wire Heat No. 90144 and the surveillance weld are in relatively close proximity.
Table 3.8 geser.ts a summary of the unirradiated NDT, RTu, and USE values for each' of the beltline welds in SONGS, Unit 3. For Welds 2-203 A, B, C,3-203 A, B, C, and 9-203 (wire Heat Nos. 90069 and 90144), available Cm data indicate that .there is a minimum of 50 ft-lb absorbed energy at 60 F above NDT and, consequently, RTm equals NDT. No NDT data are available for Weld 8-203,and RTm was taken as the' generic value of-56"F -
for ABB-CE fabricated vessels (see 10CFR50.61).
Because fewer than three specimens were tested at each temperature, the graphical method of NB-2331 (a)(4) was used to determine RTm for the surveillance weld as shown by the intersection of the dashed line and the 50 ft-lb Cm level in Figure 3-14.
The upper shelf energies listed in Table 3.8 for Welds 3-203 A, B, C,9-203, and the 1
- surveillance weld were obtained by averaging the test results where 95% shear or greater was exhibited. The USE for Welds 2-203 A, B, C was obtained from the data in Table 3.7 l by averaging the three C data points obtained at 20*F. ~Because it is unlikely that upper .
shelf Cm data willbe found for Weld 8-203,an evaluation has been performed to determine if Weld 8-203 has upper shelf toughness equivalent to that required by Appendix G of the-ASME Code. This evaluation is presented in Section -5.
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Figure 31. SONGS, Unit 3: Location and Identification of Beltline Plates and Welds.
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. MCF Data
_ Material: Plate C6802-1, A53381
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-200 :-100 LO 100- 200' 300 ,400 500J Temperature'in Degrees F ,
1:
Figure 3-2. - SONG.S, Unit 3: Data'and Izast' Squares Fit Curve for Cm versus Temperature;-
l1.: Plate C6802-1, TL Orientation, MCR Datac >
l 37-
-r
-1 . r a 1-_' ~----l. ,, _
p ..
k .
=
4 200 -
San Onofre Unit 3 MCRpata
. Material: Plate' No. CG80242, A533B1 150 -- n adon:
-QIje.l- K4 115 ft-lb'
. 4 __
USE s-NDT -20 'F T @ !50 ft-lbs = 70'F
- 3, RTnd't = 10 SF ,
u.
p ..!
- I - ~ . -_
@ 10o . - -_
e.
C. .
Lu 2
~
(= 2 a i
Ji
[- O g @
l O --
-50 - -
{-
O O. . Measured O
t "
Calculated .
j.
O o
- - =j j'
um- M s a e's il e a e a l' e' s a n 1 s a e a Il a e e e 11 a a e a 1
-200 -100 o 1'00' 200- '300. 400 -500'
. Temperature in Degrees 4F- o
- 1. '
Figure 3 3. SONGS, Unit 3: Data and Least Squares Fit Curve for Cw versus Temperature, Plate C6802-2, TL Orientation, MCR Data. ;
3-8 :
m 3
.,,,-.& , g , 4 4
.~
I J
e 4'
200 -
.j ;
. San Onofre Unit-3 MCR Data -
Material:' Plate No. C6802-3, AS33B1 Orlerration: TL ,
150 -- USE_p..105_tt-lha 4 t-
~
NDT y -10 'F l
, 50 ft-lbs = Ilo 'F ,
.c T
T @ k = 20 SF RTnd
-X . ,
~
i B .
E 100 = " O- + ~4 --
o-c -; ;
tu
~
Z 9 0
O ,
50 =
t A M:
-- . - --O- M'essured O :.
- 3 oO Calculated-
+
.. m a e a a a 1l e 's
~
n n H # a e a I a e' a n-I e a a a-II-a a~an8
--200 -100 'o 100 200 300- 4001 500-Temperature In' Degrees F ,
Figure 3-4. - SON.GS, Unit 3: Data and Irast Squares Fit Curve for Cm versus Temperature,-
,. Plate C6802-3, TL Orientation, MCR Data.
-'}
9
% r- y + % .- ________.________.___________.______._______j____._____m___.__l...____
Y J
-j 4
l 200 -
- San Onofre Unit 3
. MCR Data-Mateital: Plate 140. C6802+4, A533B1 Orien'tation: ~ TL 150 ---- USE N118-ft4bs--- +
t.
NDT h -30 SF -
m ~ T @ $0 ft-lbs = 70 SF RTndt = 10 'F o ---
E
.. . o &
N w -100 =
O O e
C .
5 til u Z' o i b'.
n d
50 = 4 "O y - t- -
i l :-
~
-O MeasuredT
. Calculated. ,
o-sh
.. a u a e a a l! n a e a l' s a a n 11 n a a e U 's a a a 1 e s' a'n 1
-200 -100 0 :100' 200 300 -400 500'-
Temperature in- Degrees F? ,
Figure 3-5, SONGS, Unit 3: Data and Least Squares Fit Curve for Cm versus Temperature,--- 7 Plate C6802-4, TL Orientation, MCR Data.
10 :
,.t
, .c, , , , -
t 1 200 -
San Onofre Unit 3
.- MCR D'ata 4 Materidt: Plate No C6802-5 A533B1 7 =t Orientation: TL '
~ ~ " ~~~
150 -~'~USET110 "ft4b s'
~~~~
t
- NDT =DI 'F m ' T @ 50 ft-lbs = 70 'F RTndt L 10 'F I E 8 8 g -
o O
. E. - 10 0 .
C . ..
g =i
~
z ob
~
7 50 = ~
- r-O- -
Measured '
0 o- Calculated ,
6
. ..n a a n n !! e a n' e l' a a n ll a'a na l' s a e 's i 's"e e a' 11
-200' -100. 0 100 .200: 300. 400 500-Temperature inl Degrees F -
Figure 3-6. SONGS, Unit 3: Data and Least Squares Fit Curve for Cm versus Temperature,- ;
Plate C6802-5, TL Orientation, MCR Data.
3-11 6 ,
u.
I r
t gj l
200' -
. San Onofre Unit -3 Mater lal: Plate No. C6802-B, A533B1 l 150 - OrienLation:.._TL l +. _ -._. 4- y._ _.
USE = 92 ft-lbs
, NDT * -40 'F -
- 9 T @ 50 ft-lbs = Bo 'F i - RTndi = 20 'F -
. -o
- A.
9 m
100 -
O
[
c . o y tu Z
O 9,. .-
+ I O -Q 50 =-
O
- O Measured Calculated --
""'''''''''''''l '''''l *
o
-200 -100 o. .100 200- 300 400 500
. Temperature in ' Degrees F Figure 3-7.. . SONGS, Unit 3: Data and Least Squares Fit Curve for Cm versus Temperature,-
. Plate C680.2-6, TL Orientation, MCR Data. '
3-12
. - - . _ - - - ~ .- ,.- - . .. .
200 --
T-
~ ' ~ ~ ' - - - ~ ~ ' '
T-'
1 = 0.0 l.
I - - - + - - - - -
150 ; -- 4 - -
San On$i fro Unit 3 Surveillance Program
. Material: Plate No. 6802 1, . SA53381 m
.o - OrientatI,on: TL r
g USE .= 92 ft-lbs O D
g NDT = -10 'F D g 100 --T-@ 50 ft-ibs4145 *F - ;
O C RTndt = 75'F >.
W .
DO 0 z !
-0 0 .
_$Q . . 0 ~.. .. ..- . .),-
. a /.
i /
~ / *
.O.
l . a' O
O g- ..=n a e a e'i a n 'n-a l s a e a l '
a a a e il a a n'e 'n 'n ~n a' 1 200 100- 0: 100 200- 300: 400 500 l Temperature in Degrees F '
l:
i p Figure 3-8.' SONGS, Unit 3: Data and Least Squares Fit Curve for Cm versus Temperature, l,
Plate C6802-1,-TL. Orientation, Surveillance Baseline Data.
l.
l 3 .
'f
- a-
200 -
~
San Onofre Unit 3 Combined MCR A Unitradiated Baseline Data Materl'al: Plate No C6802-i, SA533BI 15o Orienthtlon:.. TL.~[ ! . . . _-
USE d 94 ft-lbs f..
3
.._ . 7.. 3
~
NDT k -10 'F S T @ 50 ft-Ibs = 145 6F ;
d -
RTndt = 75 SF s "
o 0 100 --
g- a c .
W 9o O 3
~
~ O z ! O
>
- 9<
o ,
-? o Measured 50 --
0- - h-/--+ - Calculated
. o6/
'o r3 o
-o O l
......... .... n....t . . . .u .... u .... e o
-200 -100 o 100 200 soo 400 soo Temperature in Degrees F Figure 3-9. SONGS, Unit 3: Data and Least Squares Fit Curve for Cw versus Temperature, Plate C6802-1, TL Orientation, Combined MCR and Surveillsnec Baseline Data, 3-14
b I
-j
.l.
r 200 -
p- -- ---
f = 0.0
- j l
150
= " -+
- ) m San Onofre Unil3 Surveillance P{ogram a Matdrial: Plate ;No. C6802r1, SA53381-4 -
Orle'ntation: LTl E , USd = 91- ft-lb$ -
NDT = 0 SF -l+~
$-100 g = --
t T D
~ ~~
s: --
B -
Z O O- ,
D- l
.t 50 -
F .- - .10 j- --
-O O +
f -.
L
=
m d
' '" '^' ' ' ' ' '
O 200 -100 0 '100 -200' "300- 400 500:-
Temperature in Degrees _F-
' Figure 3-10. ' SONGS, Unit 3: l Data and Least Squares Fit Curve for Cm versus Temperature, . 3 ~
Plate C6802-1, LT Orientation, Surveillance Baseline' Data.
15 '
h
- ~
-200 -
, San Onofre Unit 3 _
MCR Data 'i Material: Plate jNo.- C6802-1. SA533B1 i Oriebtation: LTi ! ,
150 -- USE!.= 131. ft-16s .--h H NDT = -10 'F I en
.o - S r "
E
@-100 --
r @ ~ ~
e C / '
c .
tu Z
> ~
0
-O Measured .
~
50 - -
Calculated:
- .o
. O
- O O
~
0 .
.... . . n a ia a a a l' s a a a l' a a a a 11 a a a'~ n 1 a a a a I
-200 -100: O. 100 200 30'O -400: 2500'-
Temperature in: Degrees'F Figure 3-11. SONGS, Unit 3: . Data and ~Least Squares Fit Curve for Cm versus Temperature,-
- Plate C6802-1, LT Orientation, MCR Data.
3-16 -
N
- o. -
g -- _
'l
.i I
-)
20o =
. 1 i
o
. 0 0 ! I l 150 ---------i +---- -7 .;
t so ~
o E g San Onofre : Unit 3
-- - 8 WMC Data _ l--
E-1C3 =-
1 - - l- - - atedah_M_M._ Seam _hh203 8
C. ,
l----- USE = 161 ' ft-lbs I
w NDT ='-70 Sf Z
o i @ So ft-lys = -40 *F
> . RTndt = -70 'F 0
5o --- r-- T ----4 -
i .I_
- O--
Measured
-i O Calculated'-
- d 1
''' "'''' "' ^
"l '
.o-
-200 -100 o- 100 200 300 400 500 Temperature in Degrees F:
Figure 3-12. : SONGS, Unit 3: Data and least Squares Fit Curve for C versus Temperature, Weld 3-203, WMC Data .l 3-17
-f
< , m -- .- - ,
l 200 = ,
i i
1
. i
~
San Onofre Unit :3 WMC Data f j l Mater lal: Weld Seam 9-203 150 -- -
--f ;f * -- - T "-- ""- - - -- 1 NDT 5 -Go 'F 0
j T @ fo it-lbs = F40 0 SF
~
j,, RTndt. = -60 'F dL G u.
I 6 y J, i j i
@ 100
. 7 C .
- 6 z i)
O 0 ,
- I .l l 32 --- - ' ' ~ ~
50 " ~- --- - -
-l O Measured Calculated
) j i
0 ,
t 0 ! i
,,,,,,,,,i,,,, u ,,,, u, , , ,i , ,,, u ,,,, c o
-200 -100 0 100 200 300 400 500 Temperature in Degrees F Figure 3-13. SONGS, Unit 3: Data and Izast Squares Fit Curve for Cm versus Temperature, Weld 9-203 (Heat No. 90069), WMC Data. l 3-18
N 200 -
San Onofre Unit -3 -!
4
" o WMC Data
- Materiat: Weld Seam 9-203 150 - . . . .. Healtio. 90144 USE:: 91 ft-lbs
, NDT= -50'F :j g "
T@2 0 ft-lbs = -10'F ,
p . RTndt = 50'F-
- - l
@ 100~ -
-o
- p- 0
.- y -
O O
50 -
~
_o-
. Measured -
-O _._ Calculated
"" " ' ' ' ' ' ' 'l '
O'
-200- -100 0 100- 200- :300 400-- ---5001 f
Temperature in Degrees = F
' Figure 3,14. = SONGS, Unit 3: - Data and Least Squares Fit Curve for_Cm versus Temperature,1
_ Weld 9-203 (Heat 90144), WMC Data,-
i-
.- y 3-19 1
J
?
.n-'
, + - . , -
w.-- - .......m..m-... . . . . . .
- e. ...y.,...
I
- : l i
t = 0.0
- + - - - -
150 - - - - - - - - - --
F ---
San Onofro Unit 3 l
" I Surveillance! Program
- tjaterial: W41d
-Q -
dSE = 82 ft'-lbs r
E NDT = -60 SF
~
> T @ S0 ft-lb) = 30 SF cm +
g 100 RTndt = -30!SF-t - g - g---
c w -
n z O 0 iu O
- l0 O i~
D
. y 50 . .- -_.
./ 1
. i
/
O 9
/t
. O
/'
O
, ,,i9,,, n ,,, , u ,,,,i,,,, o ,, , , u ,,,,i o
-200 100 0 100 200 300 400 500 Temperature in Degrees F Figure 3-15. SONGS, Unit 3: Data and Least Squares Fit Curve for Cm versus Temperature, Surveillance Weld, Surveillance Baseline Data.
3-20 i
l
g su i
Table 3.1 SONGS, Unit 3: Compliance with 10CFR50, Appendix G.
Paragraph Description of Non-Compliance Comment II.B Series 4xx stainless steels are Consistent with ASME Code in effect.
purchased and treated to Code requirements. No RTer or drop weight Tum temperatures are determined, III.B.5.a Records of fracture toughness Appendix G was not applicable at the -
testing do not include a time tests were performed. Cenification certification that tests were to the applicable ASME Code is performed in accordance with included. The intent of Appendix G is Appendix G. met.
III.C. " Reactor Vessel Beltline", as The baseline tests of the surveillance defined by Paragraph II.H, program include weld and HAZ material includes the weld heat- from the most limiting plate. Results affected-zones.Section III.C available for SONGS Unit 3 indicate is not complied with in that that the intent of Appendix G has been only base plate and represent- met (Note: the HAZ results are not active welds in the beltline presented in this report)'
region were considered for the required testing.
III.C.1 Only single-temperature testing Consistent with ASME Code in effect.
was performed for some weld I. materials.
Only the heat-affected-zone i from the most limiting plate was tested over an extended temperature range.
III.C.2 Excess material for test The same combinations of a specific j specimen weldment is not heat of filler wire and a specific lot of l necessarily from the actual flux welded under the same production production plate, although conditions ~ as those used in joining the it is the same P-number. corresponding shell materials were used.
(Section IX, ASME Code) 3-21 i
ll l
L . .
.x Table 3.1 (Continued)
Paragraph Description of Non-Compliance Comment IV. A.4 Charpy V-notch tests were The ASME Code in effect -
not conducted at "the required test temperature of 60*F-preload temperature or at below the lowest service the lowest service temperature. All bolting material temperature, whichever is was tested a: 10'F and met the 35 lower". ft-lb minimum requirement of the pplicable ASME Code. All beltline plate materials and two-beltline welds were tested to meet the current (1989) Code requirements -in NB-2331. One beltline weld as tested at 20*F and has Cm in excess of 100 ft lb.-
- These results indicate that the intent of Appendix G has been met.' One weld located away from the core region has been classified as a beltline weld because the Cu and Ni contents are currently not documented and high values have been assumed.
In addition, no Cm data are currently available for this weld.
An evaluation performed to assess-the upper shelf toughness for this weld demonstrated that the weld toughness provides margins equivalent to those of Appendix G of the ASME Code;. ;
consequently, the requirements of- l Appendix G have been met.
]
3-22 i
Table 3.2- SONGS, Unit 3: Plate and. Corresponding Heat- Numbers for the Beltline Plates.
Lukens Plate Number Heat Number C6802-1 C9195-2 C6802-2 C9218-2 C6802-3 C9195-1 C6802-4 C9220-1 C6802-5 C9218-1 C6802-6 B3388 !
3-23
Table 3.3 SONGS, Unit 3: Weld Wire and Flux Combinations for Beltlin'e and Surveillance Welds.
Weld Seam Weld Wire and Flux 2-203 A, B, C Type Mil B-4 Wire, Heat No. 83650, Linde Type 0091 Flux, Lot No.1122 3-203 A, B, C Type Mil B-4 Wire, Heat No. 88114, Linde Type 0091 Flux, Lot No. 0145 9-203 Combination of (1) Type Mil B-4 Wire, Heat No. 90069, Linde' Type 124 Flu..,
Lot No. 0951, and (2) Type Mil B-4 Wire, Heat No. 90144, Linde Type 124 Flux, Lot No.1061 8-203 Not available Surveillance
- a. Work is ongoing with ABB-CE to obtain the source documentation 3-24
l Table 3.4 SONGS, Unit 3: Key Residual and Alloying Element Contents for lleltline Plates.'
l I
Plate Allll-CE i Number Lab No. Cu Ni P S Cl* -
i C68021 P14214 0.06 0.58 0.Or' O.013 37 P18195 C6802 P 0.06 0.58 0.009 0.014 37 l C6802 -2 P14244 0.04 0.57 0.009 0.013 26 P18196 C6802 3 P14223 0.06 0.58 0.005 0.013 37 P18197 C5802 4 P14452 0.05 0.56 0.007 0.010 31 P15391 C6802-5 P14453 0.04 0.55 0.011 0.013 26 P15392 C6802-6 P14454 0.06 0.62 0.007 0.009 37 P15393
- a. Average values (see Appendix B)
- b. Chemistry factors from Regulatory Guide 1.99, Revision 2 l c. Measured when the surveillance tests-were performed for Capsule 97m 3-25
i Table 3.5 SONGS, Unit 3: Key Residual and Alloying Element Contents for lleltline
+
Weld AllB-CE Scam Lab No. Cu Ni P S CP 2 203A D17360 0.N 0.17 0.011 0.012 41 2 20311 D17361 0.05 0.21 0.011 0.013 51 2-203C D17362 0.N 0.08 0.010 0.012 32 3 203A D22245 0.04 0.21 0.012 0.008 44 3 203B D22246 0.04 0.19 0.012 0.008 42 3 203C D22247 0.04 0.21 0.011 0.008 44 9 2036 D23985 0.06 0.04 0.010 0.009 34 9-203' D28503 0.05 0.04 0.007 0.011 31 d
8 203 0.35' i N/A N/A 272 Sun >cillance' D30342 0.03 0.08 0.004 0.009 27 Surveillance' O 03 0.11 0.014 0.008 29 Surveillance' O.03 0.09 0.011 0.008 28
- a. Chemistry Factors determined from Regulatory Guide 1.99, Revision 2
- b. Values- from WMC for Type Mit B-4 Wire, Heat No. 90069, Linde Type 124 Flux, let No. 0951--see Appendix D
- c. Values from WhtC for Type hiil B-4 Wire, Heat No. 90144, Lic.de Ty}c 124 Flux, Lot No.1061--see Appendix D d .' Cu and Ni contents were not measured and 0.35 wt% and I wt% have been assumed, respectively, per Regulatory Guide 1.99, Revision 2
- e. hicasured when surveillance program was developedDI
- f. hicasured when the surveillance tests were performed for Capsule 97A 3 26 m.-- g , .,
w
I Table 3.6 SONGS, Unit 3: lleltline Plate Material Unirradiated Fracture Toughness Tests Results Summary, TL Orientation.
initial Plate NDT RTm,1 Procedure to USE Number ('F) ('F) Determine RTmir (ft lbs)
C6802l* 10 6
75 ND2331 (a)(4) 94 C6802 2 -20 10 NB2331 (a)(3) 115 C6802-3 -10 20 NB2331 (a)(3) 105 C6802-4 -30 10 NH2331 (a)(3) 118 C6802-5 0 10 NB2331 (a)(3) 116 C6802-6 -40 20 NH2331 (a)(3) 92
- a. This plate is included in the surveillance program, RTmir and USE values are based on the combined data sets from the MCRs and unirradiated surveillance baseline (see Figure 3 9)
- b. Higher of 2 transverse values (i.e.,-20*F determined when plate was purchased, and -10"F from surveillance baseline) 3 27
Table 3.7 SONOS, Unit 3: Charpy Absort>ed Energy Values at 20*F for Weld Scams 2 203 A. B and C.
l
.l Charpy Energy Weld Seam (ft lb) .j i
2 203 A, B, C 125,138,145
-t 2
t b
T h
3 28 m e _- ,w- ,- ,-w .-e v-e, . , ~ ~ ,c.,w y w- w.w, , . m o ve, .m,-r., e + ,.m.ww -s- w ..
,rt-W-r
l Table 3,8 SONGS, Unit 3: Beltline Weld hiaterial Unirradiated Fracture Toughness Tests Results Summary.
i initial -
NDT RTunt Procedure to USB Weld Seam ('F) ('F) Determine RTunt (ft lbs) 2 203 A, B, C -40' -40 NB 2331 (a)(2) 136' -
3-203 A, B, C -70' -70 NB 2331 (a)(2) 161 8 203 N/A -56 e N/A d
9 203 (90069) 60 60 Nil 2331 (a)(2) 123 9 203 (90144) -50' 50 ND-2331 (a)(2) 91 Surveillance 60 -30 Nil 2331 (a)(4) 82 ,
a, NDT values obtained from the FSAR and documented in Appendix D b, Estimated using the average of Cydvalues obtained at +20"F (see Table.3.7)
- r. Generic value for ABB CE fabricated vessels using Linde 0091,1092,and 124 fluxes (see 10CFR50.61)
- d. Value obtained from the WhtC, for Type hill B-4 Wire, Heat No. 90069, Linde Type 124 Flux, Lot No. 0951 -- see Appendix D ,
- e. Value obtained from the WhiC for Type hill B-4 Wire, Heat No 90144, Linde Type 124 Flux,let No,1061 -- see Appendix D 3-29
Section 4 ISSUES RELATED TO GENERIC LETTER 8811 NRC issued Generic 1.ctter 8811 (GL 88 ll) in July 1988. GL 8811 letter revised the methodology used forestimating radiation embrittlement ofreactor pressure vessel materials to be consistent with the guidelines in Regulatory Guide 1.99, Revision 2. Several technical issues have recently emerged which indicate a need to address some of the application assumptions used in Regulatory Guide 1.99, Revision 2. The pertinent issues brought out in GL 92 01 are addressed in this section.
4.1 VESSEL ^;WWAATURE DURING OPERATION The methodology in R:gulatory Guide 1.99, Revision 2,is specined to be applicable for-operating temperatures in the range of $25 to 590"F. Concern is expressed in GL 92-01 that power operation may occur at temperatures below 525"F. For SONGS, Unit 3,the reactor coolant cold leg temperature (Tc) is never below 545"F during power operation and rises to about 553"F at full power. Thus, there is no time during normal power operation that the SONGS, Unit 3, vessel or surveillance capsules experience temperatures below 545"F.
4.2 APPLICABILITY OF SURVEILLANCE DATA To properly assess the measured surveillance results and to project irradiation embrittlement '
trends for the vessel, Huence projections, validated through the dosimetry contained in the surveillance capsules tested to date, are needed. Both SONGS, Units 2 and 3, have identical core designs and essentially the same past and projected operation history.
Therefore, the fluence projections from Units 2 and 3 surveillance data willbe used for each unit. The fluence as a function of effective ful power years (EFPY) was obtair.e4 from the results of the Grst capsules pulled from Units 2 and 3.
The Unij 2 cap:ule was pulled at the end of the third fuel cycle which corresponds to 2.85 EFpY.15 These daR represent the original core for both units and the best estimate value of peak fluence at the vessel inner surface is 4.34 x 10 18 n/cmd (E > 1 MeV); the capsule Buence was about 20% higher at 5.07 x 10 18 n/cm2, At the start of the fourth cycle for each unit, the core was reconfigured in a-low leakage loading pattern which reduced the vessel and capsule Ouxes. The first capsule taken out of Unit 3 was after the fourth fuel cycle at 4.33 EFPY and represents the combined results of the standard and low leakage' core designs.12) The peak fluence value at the vessel inner -
surface is 6.6 x 1018 n/cm 2, and the associated capsule fluence is 8.0 x 10 l8 n/cm2, 4-1 a
I The projection of fluence forward in time is based upon an extrapolation of the dosimetry information obtained from the two SONGS capsules. The pro ected peak fluence at the-vessel inner surface at the end of 32 EFPY is 4.2 x 10 l ' n/cm2
,21 At the point in time of December 16,1991, the estimated EFPY is 5.63, and the projected peak fluence at the !
1 2
vessel inner surface is 8.5 x 10 18 n/cm ,
As indicated in Figure 31,there is a weld identified as 8 203 which is well outside the core region of the vessel (i.e.,approximately 2 feet above the top of the core). This weld is conservatively considered a beltline material because of a large chemistry factor associated with the unreported Cu and Ni contents. Because Cu was not retvarted. 0.35 wt% was conservatively assumed; and, because Ni was not reported, Ni was assumed at I wt1 The i fluence at this location above the core has reported in the FSAR to be about 1/37 that of l j
the peak fluence location within the vessel. Recent calculations performed at SCE16]
indicate that the Cuence at Weld 8 203 is 1/108 that of the peak fluence location within the j vessel. The SCE Ouence calculations have been used in the evaluation of Weld 8-203. I Within Regulatory Guide 1.99, Revision 2,there are fivecredibility criteria that must be met ;
in order to utilize surveillance data in adjusting the predicted embattlement trends and/or i I
reducing the assigned margin terms. Three of the criteria are met (proper limiting materials, dennitive measurements of shift and upper shelf, and a match between the capsule and vessel temperatures within 125"F), but the other two have not been satisfied since only one capsule from each vessel has been pulled and evaluated, To satisfy these last i
two requirements, the second capsules (which will not be pulled until about 15 EFPY) must be evaluated to supply two valid data sets for the vessel surveillance materials, and testing ;
of the correlation monitor material contained in the second capsules must be evaluated against the available data for that material, in the subsequent portion of this section, the available results from the first capsules willbe compared to the regulatory prediction approaches, and projections based upon the regulatory approaches will be made.
4.3 - SHIFTS AT THE CHARpY V-NOTCH 30 FT-LB ENERGY LEVEL Capsule 97 from the SONGS Unit 3 surveillance program was tested in 1991. The Cyg results from this capsule are shown in Figures 41 (Plate C6802-1/TL), and 4 2 (surveillance weld). Appendix H contains, in tabular form, the absorbed energy, lateral expansion, and fracture appearance (% shear) for the irradiated surveillance materials.
The results computed during this work for the shift at the 30 ft lb energy level are tabulated in Table 4.1 as " current" and compared to the Regulatory Guide 1.99, Revision 2, mean shift predictions (RG1.99R2):
RGl.99R2 = CF (chemistry factor) x ff(Duence function),
p 4-2
The results obtained by Westinghouset2] are also shown for comparison. The differences between the current values for shift versus those from Westinghouse are due to small differences in the curve fit to the Cyg data and the different data set used for unirradiated Plate C6802-1/TL (i.e., Figure 3 8 for Westinghouse and Figure 3-9 in the current study).
The measured shift result for Plate C6802-1 are higher than the mean prediction from Regulatory Guide 1.99, Revision 2, but are within the mean plus two standard deviation value of 69"F (i.e.,35"F + 34"F = 69"F as compared to 55 - 58"F). The measured shift for the surveillance weld is much less than the mean shift prediction using Regulatory Guide 1.99, Revision 2. Until another capsule is tested, there is no way to definitively evaluate that the CFs should be adjusted to reflect menured behavior, rather than that predicted from the Regulatory Guide.
Table 4.21ists the predicted estimates of adjusted RTNtyr (ART) at the vessel inner surface for the two time periods of December 16,1991 (as requested in GL 92-01) and at the end of the current license (32 EFPY). Note that the Regulatory Guide 1.99, Revision 2, shift (CF x ff) with the appropriate margin terms have been used; the initial RTNtyrs were taken from Tables 3.6 and 3.8. The results in Table 4.2 show that the plate material C68021, which is the plate material in the surveillance program, is the limiting material in the vessel beltline. Note the low levels of ART for all welds. The results in Table 4.2 show that the degree of radiation embrittlement in the SONGS, Unit 3 reactor vessel beltline materials is relatively low even at end-of design life fluence.
4.4 UPPER SHELF ENERGY DROP Capsule 97 from the SONGS, Unit 3, surveillance program was evaluated in 1991. Tr.c USE results are shown in Figures 4-1 and 4 2,and are tabulated in Table 4.3as an absolute drop in USE (ft-lb). Also listed in Table 4.3are the predicted drops from Regulatory Guide 1.99, Revision 2. The measured drop for the surveillance weld is slightly below the value predicted using Regulatory Guide 1.99, Revision 2. The measured upper shelf drop for Plate C6802-1 is essentially the same as that predicted using the Regulatory Guide.
Predictions of USE levels at the quarter thickness location after neutron irradiation exposure are shown in Table 4.4 for all the SONGS, Unit 3, beltline rnaterials. At the end of 32 EFPY, none of the materials are projected to even approach the NRC screening limit of 50 ft-lb specified in 10CFR50, Appendix G. Because there are no upper shelf values for Weld 8-203,an evaluation was performed to demonstrate that the upper shelf for Weld 8-203 has toughness equivalent to that required by Appendix G to the ASME Code; this evaluation is presented in Section 5.
4-3 i
l
200 -
)
i
~
San Onofro Unit 3 Surveillanco Pro' gram Matoritil: Plato SA533B1
. Heat No. C0002 j - - - - - 1 = 0.0 150 -~ .OdoMU_om 3-- -- ~- -
t = 0.00+10 " - -
. i i O f = 0.00+10
~
.a Z
u.
5 u 100 -
.~ --- - - -
L - - J - -- - - .
1 /
z f
. /
. / O
/ O 50 -- - - -
l-o- --- -
. /
/ O
~
9
/
A 0
~
o.... e . . . . ...., ...., ....<
o 200 100 0 100 200 300 400 500 Temperature in Degrees F Figure 4-1. SONGS, Unit 3: _ Comparison of the Ixast Squares Fit for the Uninadiated Baseline Data with the Irradiated Cw Data and Least Squares Fit for the Data from Capsule 97, Plate C6802-1, TL Orientation.
44
l l
t t
t i
i 200 -
, Gan Onofre Unit 3, j Survell ance Program r Material: Weld ,
- - - - - f = 0.0
+"~--
150 - - - - - - ------ --
f = 8.oe+18 -"-"
O f = 8.0e+18
~
9 r g .
~
A
- - ~ ~ - - - - - +---
.E 100 c .
tu -----.-- - .
Z ,O o
> sT U
/0
/o o 1 50 -- --
--y'-- -
l O
/
/o
~
.M,
.f
.- y g -rr-r7i....@....n ....i ....i .... o . . , .- t
- 200 -100 l0 100 200 300- 400: 500 Temperature in Degrees 1F Figure 4-2. SONOS, Unit 3: Comparison of the least Squares Fit for the Unirradiated L Baseline -Data with the Irradiated Cm: Data and Least -
Squares Fit for the Data from Capsule 97, Surveillance Weld.
r 4-5
i Table 4.1. SONGS, Unit 3: Suiveillance Capsule Shift Results.
30 ft lb Shift (F)
Material / CF ff Orientation E ROl.99R2 Current C6802-1/TL 37' O 94 55 35 58' Surveillance 2 86 0.94 32 26 2d .!
i Weld
- a. See Table 3.4 (Cu = .06; Ni = .58)
- b. Based upon the average chemistries - see Table 3.5 (Cu = .03; Ni = .09)
- c. Based on the combined data set from the MCR and baseline surveillance program, see Figure 3 9
- d. Based on the baseline surveillance data, see Figure 315 a
4-6 40 se ,y-., -y-.- -,- ,,,y,h- _-m ---,_.w;. _
t Table 4.2. SONGS, Unit 3: ART Estimates at the Inner Surface location for Beltline Materials on 12/16/91 and at 32 EFPY.
Fluence Function ART (*F)*
Plate No./ CF at the Inner Surface at the Irmer Surfagg Weld Seam 12/16/91 32 EFPY 12/16/91 32 EFPY C6802-1 37' O.95 1.37 144 160 C6802-2 26 0.95 1.37 60 80 C6802-3 37 0.95 1.37 89 105 C6802-4 31 0.95 1.37 69 86 C6802-5 26 0.95 1.37 60 80 C6802-6 37 0.95 1.37 89 105 2 203 A, B, C 39' O.95 1.37 34 67 3 203 A, B, C 4 38 0.95 1.37 12 45 8 203 272 0.09' O.25' 12' 79' 34 0.95 1.37 5 33 9-203 (90069) 9-203 (90144) 31 0.95 1.37 9 35
- a. ART is the adjusted reference temperature equal to the predicted shift (CF x ff) plus the initial RTum plus a margin term equal to 34*F for plates or 56*F for welds (unless the predicted shift is less than the margin term, in which case the margin is equal to the predicted shift)
- b. Based upon measured chemistries for this plate (.06 Cu / .58 Ni)-- see Tables 3.4 and 4.1
- c. Based upon average chemistries for these welds (.04 Cu/.15 Ni) -- see Table 3.5
- d. Based upon average chemistries for these welds (.04 Cu/.20 Ni) -- see Table 3.5
- e. Fluence function is based upon the peak vessel fluence divided by 10814
- f. Since there is no measured initial RTum, an additional margin associated with the standard deviation (17'F) of the initial RTum has been used as described in Regulatory Guide 1.99, Rev. 2 4-7
\
Table 4.3. SONGS, Unit 3: Surveillance Capsule Upper Shelf Results.
Upper Shelf Drop (ft lb)
Material / Cu Fluence Orientation (wt%) (x 10 n/cm2) Battelle RGl .99R2 Current C6802-1/TL 0.06' O 80 16 17 18' Surveillance 0.0 36 0.80 12 15' 14' _
- a. See Table 3.4
- b. See Table 3.5
- c. Based upon the Regulatory Guide 1.99, Rev. 2, lowest percentage drop (18%) curve at the specined fluence times the measured unirradiated upper shelf determined in this report
- d. Based on the combined data set from the MCR and baseline surveillance program, see Figure 3-9
- c. Based on the baseline surveillance data, see Figure 3-15 _
48
- . = . - - _ . _- - - _ - . _ - _ - -. . - - - - -
f Table 4.4. SONGS, Unit 3: Upper Shelf Estimates at the Quarter Thickness location for Beltline Materials on 12/16/91 and at 32 EFPY.
fluence (x 10" n/cm2) Upper Shelf Energy (ft-lb)*
Plate No./ Cu at Ouarter-Thickness at Ouarter-Thickness Weld Scam (wt%) 12/16/91 32 EFPY 12/16/91 32 EFPY C6802-1 0.0 66 0.51 2.5 79 72 C6802 2 0.04 0.51 2.5 96 88 C6802-3 0.06 0.51 2.5 88 80 C6802-4 0.05 0.51 2.5 99- 90 C6802-5 0.04 0.51 2.5 97 89 C6802-6 0.06 0.51 2.5 77 70 ,
2-203 A, B, C 0.05' O.51 2.5 114 104 3-203 A, B, C 0.04' O.51 2.5 135 123 9 203 (90069) 0.06 0.51 2.5 - 102 92 9-203 (90144) 0.05 0.51 2.5 76 70
- a. The upper shelf energy is estimated from Regulatory Guide 1.99, Rev. 2, taking into account the projected fluences and measured chemistry
- b. - Based upon measured chemistry for this plate -- see Table 3.4
- c. Based upon average chemistries for these welds -- see Table 3.5 4-9
Section 5 ,
UPPER SHELF ENERGY EVALUATION FOR CIRCUMFERENTIAL WELD 8 203 I
r As indicated in Table 3.8, Cm data were not available to determine the USE for circumferential Weld Stam 8 203. In addition, Cu and Ni contents were not available for Weld Seam 8 203 and, as indicated in Table 3.5, conservative values of 0.35 wt% and 1.0 wt%, respectively, were assumed in accordance with Regulatory Guide 1.99, Revision 2.
Because it appears unlikely that source documentation will be obtained to confirm the chemical composition and USE for Weld 8 203, an evaluation was performed to demonstrate that the weld scam has an upper shelf toughness equivalent to that required by Appendix G of the ASME Code as specified in Appendix G to 10CFR50.
5.1 EVALUATION PROCEDURE The USE evaluation was performed using the analysis methods and acceptance criteria specified in Appendix X to Section XI of the ASME Code 'lr and a material J R curve determined using the procedures presented in [8]. The evaluation was performed for Level A and B Service loadings.
The acceptance criteria specified in [7] for Level A and B Service loadings are:
X-2200 Level A and B Service Loadings (a) When evaluating adequacy of the upper shelf toughness for the weld material for Level A and B Service loadings, an interior semi clliptical surface flaw with a depth one-quarter of the wall thickness and a length six times the depth shall be postulated, with the flaw's major axis oriented along the weld of concern, and the flaw plane oriented in the radial direction. When evaluating adequacy of the upper shelf toughness for the base material, both interior axial and circumferential flaws with depths one-quarter of the wall thickness and lengths six times the depth i I
shall be postulated, and toughness properties for the corresponding orientation shall be used. Smaller flaw sizes may be used when justified. Two criteria shall I be atisfied: [
(1) The rplied J-R integral evaluated at a pressure 1.15 - times the accunwlation pressure as defined in the plant-specific Overpressure -
Protection Report, with a factor of safety of 1.0 on thermal loading for the plant-specific heatup and cooldown conditions, shall be less than_ tb ,-
integral of the material at a ductile flaw extension of 0.10 in.
5-1
(2) Flaw extensions at pressures up to 1.25 times the accumulation prcssure of X 2200(1) shall be ductile and stable, using a factor of safety of 1.0 on thermal loading for the plant specific heatup and cooldown conditions.
(b) The J-integral resistance versus flaw extension curve shall be a conservative representation for the vessel material under evaluation.
The J R curve required for the Code analysis was obtained using the Cu fluence model specified in [8] for welds, a Cu content of 0.35 wt%, the fluence at the quarter thickness location for 32 EFPY (i.e.,2.3 x 10" n/cm ),2 and a temperature of 550"F. The Code evaluation procedure requires the use of a J-R curve that is a conservative representation of the material toughness. ,
To satisfy this requirement, the mean minus two standard deviation J R curve was used and was obtained from [8] by applying a factor of 0.566 to the mean J-R curves.
The mean minus two standard deviation J R curve determined from [8] for Weld Scam 8 203 ,
i is shown in Figure 5-1.
The computational procedures of Paragraphs X-4200 and X-4330 were used to evaluate compliance with the criteria in X 2200(a)(1) and (2), respectively. The analysis was performed using an accumulation pressure of 2,750 psi and a cooldown rate of 107F/h. ;
5.2 RESULTS I
The computational results obtained to assess the 0.1 inch crack extension criterion of [7] are ,
summarized in Table 5.1. The applied J integral value for a postulated 0.1 inch crack extension, l an accumulation pressure of 2,750 psi, and the required margin on pressure of 1.15 is 160 in-lb/in 2. From Figure 5-1, the value of the J-integral corresponding to a 0.1 inch crack extension in the irradiated vessel material at 32 EFPY is 740 in lb/in 2. Because the material J integral value is much greater than the applied J-integral value, the Code 0.1 inch crack extension criterion is satisfied by a wide margin, i
l The procedure of Paragraph X-4330 of the Code was used to assess the stability criterion. The L analysis results are summarized in Table 5.2. The value of the J integral at instability, J*, was obtained from the intersection of the applied and material J/T cun'es shown in Figure 5-2. The value of the crack extension at J' was obtained from Figure 5-1.
The results in Table 5.2 indicate that the pressure at which the Code stability criterion is satisfied is somewhat greater than 8,000 psi. This value is far in excess of the pressure required by the Code (1.25 x accumulation pressure) and indicates the stability criterion is met by a wide -
margin.
L Because the Code criteria for Level A'and 3 Service loadings were met by large margins and because experience indicates the Code Level A and B criteria are limiting compared to the Code 5-2
. , . . - -- .. - -- - , - ~ -
Level C and D criteria, upper shelf toughness evaluations were not performed for Ixvel C and D Service loadings.
Ihsed on the results of this evaluation, it can be concluded that the upper shelf toughness for Weld Seam 8 203 meets the Code criteria, provides margins equivalent to those in Appendix G of the ASME Code, and satisfies the requirements of Appendix G of 10CFR50.
5-3 i
=
~
Son Onofro Unit 3
. Motorlot: Wold 8 203
. Cu = 0.35%
. Fluenco O t/4 = 0.23E18 n/cm*2
- Temperatuio = $50 F u 1,000 -
s O
c -
Y ~
CD 2C -
r
' 500 -
n 0.00 0.20 0.40 0.60 0.80 1,00 delta A, Inch Figure 5-1. SONGS, Unit 3: Material J.R Curve for Upper Shelf Toughness Evaluation of Circumferential Weld 8-203, 5-4
I 2,000 =
Son Onofre Unit 3
, Materlot: Wold 8 2113
, Cua0.36% t
. s Fluence @ t/4 = 0.23E18 n/cm*2 -
' ' Temperature a 650 F s
1,500 =
p . .
s : ,
I c
- "~. 1 ,tXX)
=
\(N I F -
S .
4 :
500
= ~
x -
Material
- * -
- Applied
.- ....H -
. . .j . . . . , ....
o 0 5 10 15 20 ,
Teoring Modulus '
L Figure 5-2. . SONGS, Unit 3: Applied and Material J/T Plots for Upper Shelf Toughness Evaluation of Circumferential ' Weld 8-203.
5-5 1
l
[
f Table 5.1. SONGS, Unit 3: Evaluction of Appendix X 0.1 inch Flow Extension Criterion for Circumferential Wold 8 203 7 Input Thickness = 8.75 (inch)
E= 28000 (ksi)
E'= 30769 (ksi)
CR= 100 (deg. F/hr)
SF = 1.15 Ps = 2.75 (ksi)
RI = 86 (Inch)
Yleid Stress = 50 (ksi)
Results t
Step 1 A= 2.288 (Inch) '
A/t= 0.261 F2 = 0.969 Kip = 48.6 (ksi-in ^0.5)
F3 = 0.8m; Kit = 20.4 (ksi-in *0.5)
Step 2 Ae = 2.388 (inch)
As/t = 0.273 P2 = 0.974-K'Ip = 49.9 (ksi in ^0,5) >
F'3= 0.898 K'It = 20.3. (ksi-in ^0.5)
J @ 0.1 = 160 (In-lb/In *2) 5-6
~
l Table 5.2. SONGS, Unit 3: Evoluollon of Appendix X Instability l Criterion for Circumferential Weld 8-203 X-4330: J/T Procedure Input Thickness = 8.75 (Inch)
Flow Stress = 85 (ksi)
E= 28000 (ksi)
E'= 30769 (kst)
CR= 100 (deg. F/hr)
SF = 1.25 Ps = 2.75 (ksi)
R1 = 86 (Inch)
Yield Stress = 50 (ksi)
X-4331: J at Flow Instability W= 0.330 J/T = 746 X-4331: Results from J/T Plot and J-R Curve J
- r- 1250 (In-lb/in ^2) della A = 0.7 (Inch)
X-4332: Internal Pressure at instability A* e = 3.704 (Inch)
F*3 = 0.804 K*lt = 18.2 (ksi-in ^ 0.5)
K*lp = 177.9 (ksi in ^0.5)
F*2 = 1.045 P* = 8.4 (ksi) 6-7
Section 6 REFERENCES
[1] A. Ragl, Southern California Edison San Onofre Unit 3. Evaluation of B.aicJlDC Specimens. Reactor Vessel hinterials Irradiation Surveillance Program, Combustion Engineering TR-S h1CS 004, November 30,1979.
[2] E. Terck, E. P. Lippincott, A. hiadeyski, and bl. Ramirez, Analysis of the SouthcID California Edison Company San Onofre Unit 3 Reactor Vessel Surveillance Cap 3nic Removed from the 97* IEcallDD, Westinghouse WCAP-12920, Revision 1, November 1991.
[3] hi. P. hianahan and J. Garrabrandt, Testing and Analysis of Unirradiated Heat Effected Zone _.JJAZ) hialcIial from the San Onofre Nuclear Generating Station Unit 3 (SONGS 3), Battelle Columbus, hiay 31,1989.
[4] Telephone communication between S.Dyrne and C. Stewart, ADB-CE, and D. Pilmer and S. Gosselin, SCE, June 15,1992.
[5] hi. P. hianahan, L. ht. Iowry, and E. O. Fromm, Examination. Testing. and liYaluation of irradiated Pressure Vessel Surveillance Soccimens from the San Onofre Nuckat_ScDerating Station Unit 2 (SONGS 2), Battelle Columbus, December 1988.
[6] R. Chang, " SONGS 2/3 RPV Fluence Ratio at Weld 8-203", SCE Calculation No.
N 1020-065, December 1992,
[7] Appendix X, Assessment of Reactor Vessels With Low Upper Shelf Charpy impact Energy Levels, Revision 13, November 25,1992, Subgroup on Evaluation Standards,Section XI, ash 1B Code.
[8] E. D. Eason, J. E. Wright, and E. E. Nelson, "Multivariable Modeling of Pressure Vessel and Piping J R Data, NUREG/CR 5729, U.S. Nuclear Regulatory Commission, Washington, D.C.,hiay 1991.
6-1 l
4 APPENDIX A-SONGS, UNIT 3: EVALUATION OF COMPLIANCE WITH ASTM E185-73 AND E185 ,
l Summary of Requirements San Onofre Unit 3 Program per ASTM E185-73 1.2 Surveillance tests are compliance divided according to application into two cases:
~
1.2.1 Case A - Where both the piedicted increase in transition temperature of the reactor vessel steel is 100'F or less and the calculated peak neutron fluence (E > 1 MeV) of the reactor vessel is 5 X 10'8 n/cm or less.
2 1.2.2 Case B -
Where the predicted increase in transition temperature of the reactor vessel steel is greater than 100F or where the calculated peak neutron fluence (E > 1 MeV) of the reactor vessel is greater that 5 X 10 18 n/cm 2 4.1 Test Material -
Test To be confirmed upon receipt of specimens shall be preparedfrom source documentation which the actual materials used in verifies the heat number for fabricating the irradiated the surveillance wold material region of the reactor vessel. and the additional chemistries provided by ABB-CE for the girth weld.
4.1 Samples shall represent a compliance minimum of one heat of the base metal and one butt weld and one weld heat-affected-zone (HAZ) if a weld occurs in the irradiated region.
4.1 The base metal and weld Compliance metal to be included in the program should represent the material that may limit the operation of the reactor during its lifetime.
A-1
Summary of Requirements Dan Onofre Unit 3 Program per ASTM E185-73 4.1.1 Vessel Material Sampling To be confirmed upon receipt of
- A minimum test program shall source documentation which consist of specimens taken from verifies the heat number for the following locations: (1) the surveillance weld material base metal of one heat used in and the additional chemistries the irradiated region, (2) weld provided by ABB-CE for the metal, fully representative of girth weld.
the f abrication practice used for a weld in the irradiated region (weld wire of rod, must come from one of the heats used in the irradiated region of the reactor vessel) and the same type of flux, and (3) the heat-affected-zone associated with the base metal noted above.
4.1.1 Representative test stock Compliance to provide two additional sets of test specimens of the base metal, weld and heat-affected-zone shall be retained with full documentation and identification.
4.1.2 Fabrication History - The Compliance test material shall receive a fabrication history (austenitizing, quench and tempering, and post-weld heat treatment) fully representative of the fabrication received by the material in the irradiated region of the reactor vessel.
4.1.3 Chemical Requirements - Compliance The chemical composition required by the material specifications for the test materials (base metal and as deposited weld metal) shall be A-2 l
Summary of Requirements San Onofre Unit 3 Program per ASTM E185-73 obtained and include, but not compliance be limited to phosphorus (P),
sulfur (S), copper (Cu), and vanadium (V).
Compliance 4.2 Charpy V-notch impact specimens corresponding to the Type A specimen described in Methods E 23 shall be employed unless material thickness does I not permit. Both irradiated and unirradiated types of specimens shall be of the same size and shape.
4.3 Specimen Orientation and Compliance Location - For both tension and impact specimens from base metal, the major axis of the specimen shall be machined normal to the principal rolling direction for plates and normal to the major working direction for forgings. The length of the notch of the Charpy impact specimen shall be normal to the surface of the material. The recommended orientation of the impact and tension specimens with respect to the weld are shown in Fig. 1. Weld metal tension specimens may be oriented in the same direction as the Charpy specimens provided that the gage. length consists of all weld metal. No specimens are to be removed within 1/2 in, of the root or the surfaces of the wolds.
Sections of the weldment shall be etched to define the weld heat affected zones. Care shall be taken that the impact specimens from the weld heat af fected zones have their notch A-3 l
l Summary of Requirements San Onofre Unit 3 Program per ASTM Eiss-73 roots in the heat affected zone at a standard distance of approximately 1/32 in from the fusion line. Specimens representing the base metal (tension and impact) and the weld heat-affected zone shall be removed from the quarter thickness location. (per NB2300 of ASME Code Section III) 4.4 Number of Specimens - The Compliance minimum number of test specimens for each exposure shall be as follows:
Case A Case B charpy Charpy Tension Base Metal 12 12 2 Weld Metal 12 12 2 HAZ 12 12 -
4.4 At least 15 Charpy impact Compliance specimens shall be used to
-establish an -unirradiated transition curve for each material.
4.4 For Case- B (see above), Not Applicable three tension test specimens shall be used to establish unirradiated tensi1e properties.
5.1.1 . Vessel. Wall Specimens Compliance (Required) - Specimens shall be irradiated at a location in the reactor that duplicates as l.
A-4
Summary of Requirements San Onofre Unit 3 Program per ADTM E185-73 closely as possible the neutron-flux spectrum, temperature history, and maximum accum!alated neutron fluence experienced by the reactor vessel.
5.1.1 The instantaneous neutron Compliance flux at the location of the specimens shall not exceed three times the calculated maximum neutron flux at the inside wall of the reactor vessel.
5.1.2 Accelerated Irradiation Not Applicable Specimens (optional) -
Test specimens may be positioned at locations other than (5.1.1) for accelerated irradiation at a rate exceeding three times the calculated maximum neutron flux at the inside wall of the reactor vessel.
5.2 Flux Measurements - Compliance Pfovisions shall be made to measure the neutron fluence as follows:
5.2.1 Dosimeters with the vessel wall specimens (5.1.1).
5.2.2 Where accelerated compliance irradiation specimens are used (5.1.2), dosimeters with the test specimens and dosimeters either in a separate ' lux monitor capsule adjacent to the vessel wall or in a vessel wall A-5 I
I Summary of Requirements San Onofre Unit 3 Program per ASTM E185-73 capsule.
5.3 Test Capsules - To prevent Compliance deterioration of the surf ace of the specimens during test, the specimens should be maintained in an inert environment within a corrosion-resistant capsule.
5.3 The temperature history of Compliance the specimens shall duplicate as closely as possible the temperature exoerienced by the reactor vessel.
5.3 Surveillance capsules Compliance should be sufficiently rigid to prevent damage to the capsules by coolant pressure or coolant flow thus hindering specimen removal or causing inadvertent deformation of the specimens.
5.3 Irradiated capsules must Compliance not be bouyant to preclude serious radiation exposure to personnel if ttnder water handlr g ic employed.
5.3 consideration should be Compliance given to the design of the capsule and capsule attachments to permit insertion of replacement capsules into the reactor at a latGr time in the lifetime of the vessel.
A-6
a Summary of Requirements San Onofra Unit 3 Program per ASTM E185-73 5.4 Specimen Withdrawal - A minimum surveillance program shall consist of three capsules for case A and five capsules for Case B. It is recommended that capsules be withdrawn as described in Table 1. (See Table 1 of ASTM E185-73.)
6.1 Radiation Env ?cinment - The neutron flux, nwAron energy spectrum, and irradiation temperature of carveillance specimens and the method of determination shall be documented.
6.2 Neutron Flux Dosimeters -
Flux dosimeters for a particular program shall be determined by referring to Method E 261. ,
END A-7
Summary of-Requirements San Onofre Unit 3 Program-per ASTM E185-82 8.1 Temperature Environment - Compliance The maximum exposure temperature of the surveillance capsule materials shall be determined. If a discrepancy
(>14'c or 25'F) occurs between the observed and the expected capsule exposure temperatures, an analysis of the operating conditions shall be conducted to determine the magnitude and duration of these differences.
8.2 Neutron Irradiation Compliance Environment:
8.2.1 The neutron flux density, neutron energy spectrum, and neutron fluence of the surveillance specimens and the corresponding maximum values for the reactor vessel shall be determined in accordance with the guidelines in Guide E 482 and Recommended Practice E 560.
8.2.2 The specific method of determination shall be determined and recorded using both a calculated spectrum and an assumed fission spectrum.
9.1 Tension Tests: Compliance 9.1.1' Method - Tension testing shall be conducted in accordance with Methods E 8 and Recommended Practice E 21.
9.1.2 Test Temperature:
9.1.2.1 Unirradiated - The test temperatures for each material shall include room temperature, service temperature, and . one
-intermediate temperature to A-8 ,
I
Summary of Requirements San Onofre Unit 3 Program per ASTM E185-82 define the strength versus temperature relationship.
9.1.2.2 Irradiated -
One Compliance specimen from each material shall be tested at a temperature in the vicinity of the upper end of the Charpy energy transition region. The remaining specimens from each material shall be tested at the service temperature and the midtransition temperature.
9.1.3 Measurements - For both Compliance unirradiated and irradiated materials, determine yield strength, tensile strength, fracture load, fracture strength, fracture stress, total and uniform clongation, and reduction of area.
9.2 Charpy Tests: Compliance 9.2.1 Method -
Charpy tests shall be conducted in accordance with Method E 23 and A370.
9.2.2 Test Temperature: Compliance 9.2.2.1 Unirradiated -
Test temperature for each material shall be selected to establish a full transition temperature curve. One specimen per test temperature may be used to define the overall shape of the curve. Additional tests should be performed in the region A-9
i Summary of Requirements dan Onofre Unit 3 Program per ASTM E185-82 where the measurements described in 9.2.3 are made.
9.2.2.2 Irradiated - Specimens Compliance for each material will be tested at temperatures selected to define the full energy transition curve. Particular emphasis should be placed on defining the 41-J (30 f t-lb) ,
68-J (50 ft-lb), and O.89-mm (35 mil) lateral expansion index temperatures and the upper shelf energy.
9.2.3 Measurements -
For each Compliance test specimen, measure .the impact energy, lateral expansion, and percent shear fracture appearance. From the unirradiated and irradiated transition temperature curves determine the 41-J (30 f t-lb) ,
68-J (50 ft-lb), and 0 89 mm (35 mil) lateral expansion index temperatures and the upper shelf energy. The index temperatures and the upper shelf energy shall be determined from the averags curves.
9.2.3.1 Obtain from the Compliance material qualification test report the initial reference temperature (RTm) as defined in ASME Code, Section III, Subarticle NB 230 for unirradiated materials.
9.3 Hardness Tests (Optional) - Compliance A-10
Bummary of Requirements San Onofre Unit 3 Program per ASTM E185-82 Hardness tests may be performed Compliance on unirradiated and irradiated Charpy specimens. The measurements shall be taken in areas away from the fracture zone or the edges of the specimens. The tests shall be conducted in accordance with Methods A 370.
9.4 Supplemental Tests Not Applicable (Optional) - If supplemental fracture toughness tests are conducted (in addition to tests conducted on tension and Charpy specimens as described in 6.1) the test procedures shall be documented.
9.5 Calibration of Equipment - Compliance Procedures shall be employed assuring that tools, gages, recording instruments, and other measuring and tecting devices are calibrated and properly adjusted periodically to maintain accuracy within necessary limits. Whenever possible calibration shall be conducted with standards traceable to the National Bureau of Standards.
Calibration status shall be maintained in records traceable to the equipment.
10.1 Tension Test Data: Compliance 10.1.1 Determine the amount of radiation strengthening by comparing unirradiated test results with irradiated test.
results at the temperature A-11 )
Summary of Requirements San Onofre Unit 3 Program per ASTM E185-82 specified in 9.1.2.
10.1.2 The tensile strength data can be verified using the results from the hardness test (optional) described in 9.3.
10.2 Charpy Test Data: Compliance 10.2.1 Determine the radiation induced transition temperature shifts by measuring the difference in the 41-J (30 ft-lb), 68-J (50 ft-lb), and 0.89 mm (35 mil) lateral expansion index temperatures before and after irradiation. The-index temperatures shall be obtained from the average curves.
10.2.2 Determine the adjusted Compliance reference temperature by adding the shift corresponding to the 41-J (30 ft-lb) index determined in 10.2.1 to the initial reference temperature obtained in 9.2.3.1.
10.2.3 Determine the radiation Compliance induced change in the upper shelf energy (USE) from the measurements made before r.nd af ter irradiation using average value curves.
10.2.4 (Optional) - Determine Not Applicable the radiation induced change in temperature corresponding to 50% of the upper shelf energy before and after irradiation from average value curves.
A-12
Bummary of Requirements San Onofre Unit 3 Program per ASTM E185-82 10.3 Supplemental Test Data Not Applicable (Optional) -
If additional, supplemental tests are performed (9.4), the data shall be recorded to supplement the information from the tensile and Charpy tests.
10.4 Retention of Test Compliance Specimens -
It is recommended that all broken test specimens be retained until released by the owner in the event that additional analyses are required to explain ariomalous results.
11.1 Where applicable, both SI units and conventional units shall be reported.
11.2 Surveillance Program Compliance Description - Description of the reactor vessel including the following:
11.2.1 Location of the surveillance capsules with respect to the reactor vessel, reactor vessel internals, and the. reactor core.
11.2.2 Location in the vessel of the plates or forgings and the welds.
11.2.3 Location (s) of the peak vessel fluence, 11.2.4 Lead f actors between the specimen fluence and the peak vessel fluence at the I.D. and A-13 )
Summary.of Requirements San Onofre Unit 3 Program per ASTM E185-82 the 1/4T locations.
11.2.5 Surveillance Material Compliance Selection:
11.2.5.1 Description of all beltline materials including chemical analysis, fabrication history, Charpy data, tensile data, drop-weight data, and initial RT,g.
11.2.5.2 Describe the basis for selection of surveillance materials.
11.3 Surveillance Material Compliance Characterization:
11.3.1 Description of the surveillance material including fabrication history, material source (heat or lot), and any ;
differences between the surveillance material history '
and that of the reactor vessel material history.
11.3.2 Location and orientation )
of the test specimens in the parent material.
i 11.3.3 Test Specimen Design: Compliance l
11.3.3.1 Description of the test specimens (tension, Charpy, and any other types of ;
specimens used), neutron .
dosimeters, and temperature j monitors.
11.3.3.2 Certification of calibration of all equipment A-14 ,
1
g Summary.of: Requirements'- . San-Onofre Unit 3 Program per ASTM E185-82
-and instruments .used in conducting-the' tests.
11.4.1 Tension Tests:. Compliance 11.4.1.1 Trade name and model of the testing machine, 3 gripping devices, extensometer, and recording devices used in the test.
- 11.4.1. 2- Speed - of testing and method of measuring. the controlling testing speed.
- 11'. 4.1. 3 Complete stress-strain
-curve (if a group.of specimens exhibits similar stress-strain curves, a typical curve may be reported for the group). .
11'.4.1.4 Test Data- from , each specimen as follows:
- (1)- Test temperature;.
(2) xYield strength or yield point and method of measurement; a (3): Tensile strength; (4 ). Fracture load, fracture strength, and fracture stress; (5). Uniform elongation Land method of measurement;
- (6)- Total elongation;-
(7) Reduction of area; and' (8) Specimen identification.
h 11.4.2-Charpy Tests-
- Compliance 11.4.2.1 Trade name:and model of' the. . testing-- -machine,-
available hammer- energy capacity.and striking velocity, temperature conditioning and' l
~
measuring devices,-'and a- -
description of'the' procedure -
A-15 r ---1 - - - y y-+-e,r w w g - h -'
Summary of Requirements San Onofre Unit 3 Program per ASTM E185-82 used in the inspection and calibration of the testir.g machine.
11.4.2.2 Test data from each specimen as follows:
(1)_ Temperature of test; (2) Energy absorbed by the specimen in breaking, reported in joules (and foot-pound-force);
(3) Fracture appearance; (4) Lateral expansion; and (5) Specimen identification.
11.4.2.3 Test data for each material as follows:
(1) Charpy 41-J (30 f t-lb) , 68-J (50 ft-lb), and 0.89 mm (35 mil) lateral expansion index temperature of unirradiated material and of each set of irradiated specimens, along with the corresponding temperature increases for these specimens; (2) Upper shelf energy (USE) absorbed before and after irradiation; (3) Initial reference temperature; and (4) Adjusted reference temperature.
11.4.3 Hardness Tests Compliance (Optiona1):
11.4.3.1 Trade name and model of the testing machine.
11.4.3.2 Hardness data.
11.4.4 Other Fracture Toughness Not Applicable Tests:
A-16
Summary of Requirements San Onofre Unit 3 Program per ASTM E185-82 11.4.4.1 If additional tests Not Applicable are performed, the test data shall be reported together with the procedure used for conducting the tests and analysis of the data.
T 11.4.5 Temperature and Neutron Compliance t Radiation Environment _
Measurements:
11.4.5.1 Temperature monitor results and an estimate of maximum capsule exposure temperature.
11.4.5.2 Neutron dosimeter measurements, analysis techniques, and calculated results including the following:
(1) Neutron flux density, neutron energy spectrum, and neutron fluence in terms of neutrons per square metre and neutrons per square centimetre
(>0.1 and 1 MeV) for the surveillance specimens using both calculated spectrum and assumed fission spectrum assumptions.
(2) Description of the methods used to verify the procedures including calibrations, cross sections, and other pertinent n*4 lear data.
11.5 Application of Test Compliance Results:
11.5.1 Extrapolation of the neutron flux and fluence results to the surface and 1/4T locations of the reactor vessel A-17
Summary of Requirements San Onofre Unit 3 Program per ASTM E185-82 at the peak fluence location.
11.5.2 Comparison of fluence determined from dosimetry analysis with original predicted values.
11.5.3 Extrapolation of fracture toughness properties to the surface and 1/4T locations of the reactor vessel at the peak fluence location.
-- -- -~~--- . . --- --------~~---
11.6 Deviations - Deviations or Compliance anomalies in procedure from this practice shall be identified and described fully in the report.
END A-18
APPENDIX B ,
i SONGS, UNIT 3: BASES FOR PLATE CHEMISTRY MEASUREMENTS (Proprietary)
I
APPENDIX C SONGS, UNIT 3: BASES FOR WELD CHEMISTRY MEASUREMENTS (Proprietary)
_-_ _-- -_- _. _ _ _ _ ___m_ ___ _ _ _ _ _ . _ _ _ . _ _ . _ _ _ - . _ . _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ - _ _ . - _ . _ - _ _ _ _ - _ _ _ _ _ _ . _ _ _ _ . _ . _ - - -
.J .J4L ) 5 A M l
l APPENDIX D -
BELTLINE MATERIALS (Proprietary)-
u d
e a ------_.L--__-_-- -.------,.--a._s-
APPENDIX E SONGS, UNIT 3: MCRs FOR BELTLINE MATERIALS (Proprietary)
__ __ __.___ _ _ - - . - _ - _ _ _ _ _ _ _ _ _ . - _ . _ _ _ _ . - . - _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ . - _ _ _ _ . _ _ _ _ -.__ _ _ _ _ . _ _ _ _ _ _ _ _______._________-_._.__-________-___J
i APPENDIX F s SONGS, UNIT 3: UNIRRADIATED Cys DATA FOR PLATES AND WELDS.
Table F-1 Chatpy V-Notch Test Results
. For Unit 3 Flate C68021 (TL), MCR Data LAltaAL (SACI SrtclMtu ltMr tutect Artt aa 40 1tSI IMract tiip (t) (ft tbl (mil) (1) 1 40.00 F.00 5.00 0.00 2 40.00 6.00 4.C3 0.00 3 40.00 5.00 4.00 0.00 20.00 10.00 l 4 10.00 29.00 l 5 10.00 23.00 17.00 10.00 ,
l 6 10.00 18.00 14.00 5.00 j 7 40.00 34.00 21.00 15.00 1 27.00 19.00 10.00 j 8 40.00 9 40.00 24.00 17.00 5.00 to 80.00 45.90 34.00 25.00 11 80.00 55.00 45.00 30.00 12 80.00 56.00 44.00 30.00 13 100.00 50.00 37,00 25.00 14 100.00 52.00 40.00 25.00 15 100.00 59.00 45.00 30.00 16 160.00 79.00 60.00 80.00 17 160.00 79.00 63.00 80.00 18 212.00 95.00 70.00 100.00 19 212.00 99.00 72.00 100.00 20 160.00 84.00 62.00 80.00 21 212.00 100.00 74.00 100.00' F-1
~. ,. -- -- . .-
3 Table F 2 Charpy V-Notch Test Results-For Unit 3 Plate C6802-2 (TL), MCR Data ;
. a=
tptRCY LATERAL' FRACT- ,
SPEC 1 HEN' TEMP
- 10. Tr.rf 1HPACT EIF APP EAA . :l (F) (ft-lb) (mil) (t) ,
.I
.' i 1 .40.00 9.00 4.00' .0.00 !
- l 2 .40.00 6.00 3.00 0.00 :
\
y 3 .40.00 0.00 4.00 - 0.00 4 10.00 26.00 19.00. 10.00 5 10.00 14.61 11.00 S.00 ;
6 10.00 20,00 24.00 10.00' f
7 40.00 32.00 26.00 15.00 0 40.00 40.00 30.00 20.00 9 40.00- 52.00 37.00 25.00 .
10 60.00 44.00-- 34.00 25.00 5 11 60.00 52.00 36.c0 ;30.00- ,
12 60.00 $4.00 37.00 - 30.00 13 70.00 55.00 30.00 .30.00 14 10.00 57.00 39.00 ,35.00 15 70.00 65.00- 45.00 40.00 16 100.00 66.00 -50.00 40.00 i r
17 100.00' 17.00 -59.00- 50.00 ^
49.00 54.00 40.00 3 18 =100.00_
19 160.00 114.00 77.00 90.00-
+
~
20 160.00 110.00 75.00 90.00
.: t 21 160.00 105.00 15.00 90.00_
~
22 212.00- .117.00 '00.00 .100.00 =
.23 212.00 116.00 - 92.00 ' 100.00 <
24- 212.00 113.00 19.00 '100.00- ,
F-2 1
w
Table F-3 Charpy V-Notch Test Results For Unit 3 Plate C6802-3 (IL), MCR Data SPtclMEN TEMP ENEROT LATERAL. FRACT ID TEST IMPACT ERP APPEAR qPt lit-lbl (mill til 1 40.00 0.00 4.00 0.00 2 40.00 1.00 3.00 0.00 3 -40.00 9.00 $.00 0.00 4 10.00 26.00 20.00 10.00 -
5 10.00 24.00 20.00 10.00 6 10.00 15.00 11.00 5.00 7 40.00 37.00 27.00 13.00 0 40.00 20.00 22.00 10.00 9 40.00 35.00 26.00 15.00 10 40.00 15.00 26.00 15.00 .
11 40.00 49.00 34.00 25.00 12 60.00 31.00 30.00 20.00 13 00.00 51.00 47.00 30.00 14 00.00 52.00 40.00 25.00 15 00.00 60.00 46.00 40.00 16 100.00 19.00 60.00 60.00 17 100.00 10.00 54.00 10.00 le 100.00 63.00 46.00 40.00 19 160.00 100.00 71.00 90.00 20 160.00 95.00 69.00 90.00 21 160.00 94.00 67.00 50.00 22 212.00 104.00 76.00 100.00 23 212.00 109.00 70.00 100.00 24 212.00 101.00 72.00 100.00 F-3 1
L Table F-4 Charpy V-Notch Test Results For Unit 3 Plate C6802-4 (IL), MCR Data SPECIHEN TEMP EMtpCT LATE RAL FRACT ID TEST IMPACT EIP APPEAR (F) (ft-lb) (mil) (t) 1 -40.00 10.c0 6.00 0.00 2 -40.00 14.00 0.00 0.00 3 -40.00 10.00 6.00 0.00 4 10.00 25.00 10.00 10.00 _
$ 10.00 20.00 20.00 10.00 4 10.00 19.00 13.00 S.00 7 40.00 35.00 30.00 20.00 0 40.00 39.00 32.00 20.00 9 40.00 St.00 37.00 25.00 10 60.00 40.00 35.00 20.00 11 60.00 $4.00 39.00 25.00 12 60.00 49.00 34.00 20.00 13 10.00 74.00 $3.00 $0.00 14 10.00 63.00 47.00 40.00 15 10.00 59.00 44.00 35.00 16 100.00 104.00 $3.00 40.00 17 100.00 69.00 $2.00 40.00 10 300.00 10.00 $4.00 40.00 19 160.00 124.00 00.00 93.00 20 160.00 112.00 .11.00 90.00 21 140.00 104.00 10.00 90.00 22 212.00 110.00 70.00 100.00 23 212.00 117.00 01.00 100.00 24 212.00 !!S.00 77.00 100.00 F-4
Table F-5 Charpy V-Notch Test Results
-For Unit 3 Plate C6802-5 (TL), MCR Data SPEC 1 HEN TEMP ENER07 LATERAL FRACT ID TEST IMPACT EXP. APPEAR (F) (ft.lbl (m!!) (t) 1 40.00 9.00 4.00 0.00 2 40.00 10.00 S.00 0.00 3 .40.00 9.00 3.00 0.00 4 10.00 10.00 12.00 5.00 S 10.00 27.00 30.00 10.00 4 10.00 15.00 .11.00 5.00 7 40.00 34.00 23.00 15.00 0 40.00 35.00 24.00 15.00 9 40.00 11.00 25.00 15.00 10 60.00 39.00 26.00 15.00 11 60.00 39.00 20.00 15.00 12 60.00 30.00 27.00 15.00 13 70.00 65.00 43.00 30.00 14 70.00 57.00 40.00 30.00 13 70.00 $1.00 37.00 25.00 16 100.00 64.00 41.00 10.00 17 100.00 70.00 49.00 35.00 10 100.00 79.00 $4.00 40.00 19 160.00 110.00 10.00 100.00 20 160.00 114.00 75.00 100.00 21 160.00 109.00 45.00 90.00 22 212.00 119.00 70.00 100.00 23 212.00 110.00 72.00 -100.to 24 212.00 117.00 74.00. 100.00 F-5
i Table F 6 Charpy V-Notch Test Results For Unit 3 Plate C6802-6 (IL), MCR Data stretMEN TEMP EN FRCT LATE RAL TRACT-ID TEST IMPACT tur ApptAR (F) (ft lb) (m113 gg) 1 -40.00 10.00 3.00 0.00 2 +40.00 10.00 4.00 0.00 3 40.00 0.00 4.00 0.00 4 10.00 23.00 17.00 10.00 S 10.00 20.00 20.00 10.00 6 10.00 25.00 10.00 10.00 7 40.00 34.00 24.00 15.00 8 40.00 43.00 34.00 20.00 9 40.00 33.00 26.00 15.00 10 70.00 S0.00 39.00 2$.00 11 70.00 46.00 35.00 20.00 12 70.00 50.00 45.00 30.00 11 80.00 52.00 40.00 2$.00 14 80.00 51.00 45.00 30.00 15 80.00 33.00 41.00 25.00 14 100.00 50.00 42.00 30.00 17 100.00 45.'s0 *t.00 s 50.00 18 100.00 49.00 46.00 40.00 19 160.00 96.00 72.00 9$.00 20 140.00 10.00 49.00 90.00 21 160.00 41.00 65.00 90.00 22 212.00 90.00 70.00 100.00 23 212.00 92.00 71.00 100.00 24 212.00 92.00 70.00 100.00 F-6 nm u --
1 i
Table F-7 Charpy V-Notch Test Results For Unit 3 Weld Seam 9-203 (llcat #90069), WMC Data SPECIMEN TPNP ENERCT 1. ATE RA1. FRACT ID TEST 1HPACT ttr APPEAR (F) (ft-lb) tail) (t) 1 -100.00 13.00 0.00 0.00 2 -100.00 0.00 4.00 0.00 3 -100.00 13.00 S.00 0.00 4 -80.00 24.00 15.00 5.00 S -80.00 43.00 31.00 20.00 6 -80.00 25.00 17.00 5.00 7 -40.00 53.00 36.00 25.00 0 -40.00 69.00 S0.00 40.00 9 -40.00 43.00 44.00 35.00 -
10 0.00 01.00 40.00 50.00 11 0.00 74.00 $2.00 40.00 12 0.00 17.00 47.00 60.00 13 40.00 120.00 42.00 90.00 14 40.00 118.00 80.00 10.00 15 40.00 125.00 82.00 100.00 14 100.00 119.00 78.00 100.00 17 100.00 117.00 70.00 100.00 le 100.00 124.00 41.00 100.00 19 140.00 123.00 42.00 100.00 20 160.00 121.00 41.00 100.00 21 160.00 113.00 82.00 100.00 F-7
Table F 8 Charpy V. Notch Test Results f For Unit 3 Weld Scam 3 203 (llcat #88114),1 SAR Data SPECINEN TEMP ENERGY LATER AL FRACT ID TEFT IMPACT Ett APPEAR tri (ft lb) tell) (t) 1 304.00 13.00 7.00 0.00 2 304.00 11.00 4.00 0.00 1 304.00 20.00 13.00 5.00 4 -80.00 29.00 22.00 10.00 S -80.00 30.00 21.00 10.00 4 00.00 24.00 13.00 10.00 1 ~40.00 110.00 44.00 40.00 0 40.00 74.00 48.00 40.00 9 40.00 114.00 48.00 40.00 10 10.00 127.00 10.00 30.00 11 50.00 115.00 44.00 70.00 12 -10.00 111.00 48.00 10.00 13 10.00 124.00 70.00 40.00 14 10.00 151.00 St.00 100.00 13 10.00 IS4.00 84.00 100.00 It $0.00 174.00 94.00 100.00 17 $0.00 143.00 SS 00 100.00 18 $0.00 142.00 83.00 100.00 F-8
Table F-9 Charpy V-Notch Test Results For Unit 3 Plate C6802-1 (IL), Cil13aseline Data SPEC 1 HEN TEMP ENE9CY LATERAL FRACT 10 TEST !HPACT EIP APPEAA (P) Ift lbl (mill (t) 252 4t.00 13.00 12.00 0.00 23E 0.00 14.00 12.00 10.00 26J 0.00 22.00 24.00 0.00 22P 40.00 18.00 11.00 10.00 260 40.00 $2.00 45.00 20.00 22R 80.00 25.00 25.00 20.00 263 90.00 S7.00 30.00 40.00 23Y 100.00 42.00 40.00 20.00 25M 200.00 74.00 40.00 40.00 24T 100.00 0s.00 (5 00 50.00 2SE 120.00 85.00 12.00 S0.00 -
1 267 120.00 106.00 80.00 $0.00 22A 160.00 61.00 60.00 60.00 221 160.00 62.00 58.00 10.00 25Y 160.00 112.00 81.00 10.00 22P 210.00 96.00 14.00 10.00 255 210.00 109.00 92.00 100.00 21R 250.00 00.00 11.07 100.00 22A 250.00 87.00 72.00 100.00 F-9
-l
l I
t-Table F-10 Charpy V-Notch Test flesult For Unit 3 Plate C6802-1 (UF), CE Baseline Data srtCIMEN TEMP ENER0T !.ATERAL FSACT ID TEST IMPACT EIP APPEAR lP) (ft-lb) (allt (t) 131 0.00 6.50 S.00 0.00 144 40.00 15.00 13.00 10.00 127 40.00 16.00 15.00 10.00 11U 00.00 33.30 30.00 30.00 13H 00.00 39.50 36.00 30.00 14C 120.00 34.00 37.00 40.00 126 120.00 45.00 41.00 40.00 14B 160.00 $1.00 47.00 60.00 130 140.00 03.00 70.00 30.00 13E 210.00 44.00 62.00 70.00 14T 210.00 96.00 01.00 30.00 11L 250.00 10.00 80.00 100.00 11C 250.00 93.00 87.00 100.00 F-10
Table F.11 riarpy V. Notch Tc.st itesults For Unit 3 Survelliance Weld, Cl!11aselint Data GreclMen trMr Enraer t.At tRA t. react ID Test IMPAc7 Str APttAR trl tit.lbi taill itt IlY .00.00 '.00 $.00 0.00 3tc 00.00 11.00 19.00 30.00 33c 40.00 11.00 10.00 30.00 36M 40.00 36.00 31.00 30.00 36c 0.00 36.00 34.00 30.00 36T 0.00 40.00 41.00 40.00 g 37E 40.00 10.00 S3.00 40.00 3A3 40.00 63.00 $4.00 40.00 357 00.00 73.00 GS.00 00.90 34M 0V.00 00.00 03.00 100.00 376 130.00 11.00 85.00 00.00 33R 130.00 04.00 79.00 10.00 316 140.00 64.00 61.00 10.00 344 160.00 97.00 90.00 100.00 33R 310.00 30.00 05.00 90.00 alc 310 91.00 04.00 10.00 35M 250.00 11.00 69.00 100.00 313 350.00 10.00 13.00 100.00 34E 250.00 04.00 03.00 100.00 F.11 I
Table F-12 Chatpy V Notch Test it. Sits For Unit 3 Plate C68021 (111'), MCR Dnta Test im pact Lateral Fracturo Temperatuto Energy Erpansion Appearanco
('F) (f t lbs) (mils) (% Shont)
-40 0 3 0
-40 7 2 0
-40 7 2 0 10 10 10 5 10 21 13 5 10 27 10 10 40 40 27 15 40 20 17 10 40 31 23 10 00 33 25 15 00 34 25 15 00 35 24 15 00 50 39 20 00 52 40 25 80 50 38 20 100 102 05 70 100 104 01 70 100 90 63 60 100 120 81 100 100 132 84 100 100 135 83 100 F-12
Table F 13 Charpy V Notch Test flesults For Unit 3 Wehl Scain 9 203 (llcat #90144), WMC Data SI'! C IMI N t l Hr' (NiRGY LAlfRAL IRACI 10 It$1 (Hf'Att f Xf' Af l't AP tr) (ft th) (mit) (%)
1 80.00 7.00 3.00 0.00 2 80.00 9.00 6.00 0.00 '
3 -80.00 5.00 3.00 0.00 4 40.00 18.00 13.00 0.00 5 -40.00 19.00 13.00 0.00 6 40.00 34.00 ?6.00 1$,00 7 10.00 57.00 41.00 35.00 8 10.00 50.00 36.00 ?5.00 9 10.00 $3.00 40.00 30.00 10 60.00 87.00 60.00 80.00 11 60.00 81.00 60.00 80.00 12 60.00 76.00 $4.00 00.00 13 100.00 90.00 67.00 100.00 14 100.00 89.00 71.00 100.00 15 100.00 90.00 70.00 100.00 16 160.00 94.00 79.00 100.00 17 160.00 97.00 77.00 100.00 18 160.00 93.00 72.00 100.00 F-13 1
l
.i 1
I i
t i
APPENDIX G i
r i
SONGS, UNIT 3: HAZ TEST RESULTS 1
i 1
f k
i i
-i N' er h e=4. w<'B -Sb-e-me' s 4ewei n e+ eW e- w-e-w ata _ww w.m e% _ ,,, ,., ,,_, q
1 i
CH Haseline TestsDI OPECIMtp itMP tutRUT 1ATTPAL FPACT 10 TF07 IMPACT ORP APPEAR (F) tit.lb) total ill eft 00.00 4.00 4.00 0.00 450 +40.00 6.00 8.00 0.00 dif 40.00 30.00 24.00 10.00 434 .40.00 30.00 14.00 10.00 elJ 0.00 30.00 35.00 10 00 elf 0.00 48.00 31.00 30.00 43J 40.00 33.00 34.00 30.00 4it 40.00 35.00 33.00 10.00 430 00.00 13.00 40.00 00.00 454 00.00 19.00 83.00 $0.00 418 120.00 43.00 41.00 40.00 til 130.00 10.00 49.00 70.00 43C 160.00 St.00 43.00 00.00 430 180.00 07.00 73.00 90.00 465 110.00 91.00 $1.00 10.00 444 310.00 105.00 13.00 100.00 44A 250.00 63.00 64.00 100.00 427 150.00 15.00 40.00 100.00 46T 2$0.00 98.00 00.00 100.00 01
1 Westinghouse Capsule 9761 SPECIMEN ftMP BNFRCT LAftAAL FAACT C EAAf f 3RPAD ID TTtt SNPACT Stp APPEAM FLUtWCt TT MP .
(F) (ft.lbi teill til (m/coli (fl 441 .75.00 9.00 9.00 5.00 9.00t+10 550.00 431. 50.00 15.00 16.00 16.00 0.00t+10 110.00 49C 30.00 1.00 4.00 9.00 0.00t+14 110.00 417 0.00 26.00 33.00 15.00 0.00t+10 150.00 464 $5.00 35.00 31.00 45.00 0.00t+14 550.00 4tc 40.00 33.00 33.00 50.00 9.00t+10 150.00 478 99.00 43.00 44.00 15.00 0.00tell 110.00 46T 835.00 41.00 30.00 10.00 0.60t+10 $$0.00 4BN 14$.00 45.00 44.00 90.00 0.00tell lle.00 437 145.00 63,00 48.00 100.00 0.00t+16 150.00 04.00 49.00 100.00 0.00t+19 150,00 4SP 300.00 434 350.00 15.00 45.00 100.00 9.003+10 550.00 (3-2
j 11attelle Columbus Additional Uninadiated ilAZ ltesults!'l et tcl MPW TEMP entaCY LAftLAL FRACT ID Ttt? IMPACT ORP APPEAA (Pt lit.lbl taill ll) 301 +120.00 1.50 9.00 11.00 183 +120.00 9.90 3.30 9.30 1981 00.03 39.50 13.00 13 40 1813 00.00 14.00 14.40 11.00 1817 .40.00 27.50 18.00 33.10 3s4 40.00 17.00 34.30 31.30 lel 0.00 39.50 31.00 49.30 199 0.00 44.50 43 30 ll.40 tale 30.00 41.50 44.40 ti.00 let 30.00 14.40 49.00 $4.70 183 30.00 93.00 10.40 54.30 1910 40.00 13.00 43.00 43 10 1810 40.00 99.00 44.00 73.40 ist) 40.00 105.00 44.40 13.90 180 00.00 113.00 13.40 100.00 Set 90.00 115.00 45.00 100.00 184 120.00 122.00 03.40 100.00 1914 110.00 160.00 04.40 100.00 187 140 00 130.00 07.30 100.00 let 340.00 153.00 03.30 300.00 104 110.00 110.0* 70.00 100.00 1815 280.00 133.00 15.00 100.00 (1-3
t APPENDIX H SONGS, UNIT 3: IRRADIATED Cvu DATA FROM CAPSULE 97 1
1
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i Table 111 Charpy V. Notch Test flesults 170r Unit 3 l' late C68021 (111')
Irradiated (f = 8 x 10" n/cm')
SPECIMEN TFMP FNERGY LATERAL FRACT ID TEST IMPACT EXP APPEAA tr) (ft-lb) (mil) (t) 147 50.00 6.00 5.00 5.00 153 75.00 22.00 15.00 15.00 ISK 100.00 29.00 24.00 25.00 113 125.00 35.00 32.00 30.00 14Y 150.00 32.00 26.00 30.00 ISB 165.00 45.00 43.00 45.00 14A 175.00 30.00 27.00 45.00 14E 200.00 46.00 46.00 $5.00 11T 225.00 75.00 66.00 00.00 12K 250,10 45.00 40.00 00.00 12L 250.00 48.00 46.00 95.00 14H 275.00 90.00 76.00 100.00 11 1
l i
Table 112 Charpy V Notch Test Results For Unit 3 Plate C68021 (TL)
Irradiated (f = 8 x 10" n/cm')
l l
1 o
SPEctMEN TEMP ENERGT 1.hTERAL FRACT )
1D TEST 1HPACT EIP APPEAA l
(F) (ft-thi (alli (t) l 4
25U 0.00 19.00 18.00 10.00 23K 25.00 16.00 11.00 10.00 214 S0.00 9.00 12.00 10 00 2LL PS.00 21 00 20.00 15.00 22B 100.00 25.00 25.00 - 20.00 233 11*.00 55.00 40.00 45.00 201 130.00 $0.00 44.00 $0.00 247 150.00 33.00 33.00 50.00 223 165.00 36.00 37.00 65.00 25C 200.00 92.00 73.00 100.00 24S 225.00 62.00 59.00 100.00 23M 250.00 73.00 77.00 100.00 11 2 e pg . - - - - . * ,
_ - + e -
Table 113 Charpy V Notch Test flesults For Unit 3 Surveillance Wcld Irradiated (f = 8 x 10" n/cm')
SPECrMEN TCHP FNFRCY LATERAL FPACT ID TEST IMPACT EXP A* PEAR (r) tit-lb) tail) (t) 363 -50.00 23.00 20.00 15.00 33L -25.00 27.00 25.00 20.00 31D 0.00 5.00 4.00 S.00 378 10.00 42.00 34.00 50.00 367 25.00 42.00 44.00 65 00 331 $0.00 44.00 44.00 70.00 37U 60.00 61.00 $7.00 95.00 37A 80.00 65.00 59.00 95.00 3GS 105.00 47.00 60.00 100.00 34P 150.00 15.00 73.00 100.00 33D 190.00 77.00 76.00 100.00 377 225.00 63.00 St.00 100.00 11 3
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