ML20084C643
| ML20084C643 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 05/19/1994 |
| From: | ATI CONSULTING, SARTREX CORP. |
| To: | |
| Shared Package | |
| ML20084C411 | List: |
| References | |
| GL-92-01, GL-92-1, NUDOCS 9505310559 | |
| Download: ML20084C643 (140) | |
Text
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Attachment B San Onofre Nuclear Generating Station, Unit 3 k:/ Response to Generic Letter 92-01 l
Revision 2 May 19,1994 1
Prepared by:
ATI Consulting San Ramon, CA t' '
and Sartrex Corporation
- Rockville, MD Prepared for:
Southern California Edison Irvine, CA h
t 95o531o559 95o523 PDR ADOCK 0500o361 P PDR
- _ _________ _ ___ _ _ __--.._ .-___ _________ -- __a
4- 4 CONTENTS 1
\ Section Eggg 1 INTRODUCTION 1-1 2 REACTOR PRESSURE VESSEL SURVEILLANCE 2-1 PROGRAM-COMPLIANCE WITH APPENDIX H L .
3 FRACTURE MECHANICS 3-1
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3.1 COMPLIANCE WITH APPENDIX G 3-1 3.2 BELTLINE MATERIALS IN SONGS, UNIT 3 3-1 3.2.1 Location 3-1 3.2.2 Heat Treatment 3-2 3.2.3 Key Residual and Alloying Element Contents 3-2 1 3.3 FRACTURE TOUGHNESS RELATED DATA 3-2 l l 3.3.1 Beltline Plate Material 3-3 !
3.3.2 Beltline Welds 3-4 l 4 ISSUES RELATED TO GENERIC LETTER 88-11 4-1
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4.1 VESSEL TEMPERATURE DURING OPERATION 4-1 ,
l 4.2 APPLICABILITY OF SURVEILLANCE DATA 4-1 4.3 SHIFTS AT THE CHARPY V-NOTCH 30 FT-LB ENERGY LEVEL 4-2 4.4 UPPER SHELF ENERGY DROP 4-3 5 REFERENCES 5-1 e
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l CONTENTS (cont'd)
Section Eage
. APPENDIX A SONGS, UNIT 3: EVALUATION OF COMPLIANCE A-1 i WITH ASTM E185-73 AND E185-82 ;
APPENDIX B SONGS, UNIT 3: BASES FOR PLATE CHEMISTRY B-1 MEASUREMENTS APPENDIX C SONGS, UNIT 3: BASES FOR WELD CHEMISTRY C-1 ,
MEASUREMENTS APPENDIX D SONGS, UNIT 3: WMCs FOR BELTLINE D1 MATERIALS APPENDIX E SONGS, UNIT 3: MCRs FOR BELTLINE E-1 MATERIALS APPENDIX F SONGS, UNIT 3: UNIRRADIATED Cvn DATA F-1 FOR PLATES AND WELDS APPENDIX G SONGS, UNIT 3: HAZ TEST RESULTS G-1 APPENDIX H SONGS, UNIT 3: IRRADIATED Cyn DATA FROM H-1 CAPSULE 97 :
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, - - - - - , . , - - ----e , _ _ - - - - - . - - . - - - - - -
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ILLUSTRATIONS
( Figure Eagt 3-1 SONGS, Unit 3: location and Identification of 3-6 Beltline Plates and Welds -
3-2 SONGS, Unit 3: Data and Least Squares Fit Curve 3-7 for Cvu versus Temperature, Plate C6802-1, TL I Orientation, MCR Data 3-3 SONGS, Unit 3: Data and least Squares Fit Curve for 3-8 Cvu versus Temperature, Plate C6802-2, TL Orientation, MCR Data 3-4 SONGS, Unit 3: Data and Least Squares Fit Curve for 3-9 Cvu versus Temperature, Plate C6802-3, TL Orientation, l
MCR Data 3-5 SONGS, Unit 3: Data and Least Squares Fit Curve for 3-10 Cvu versus Temperature, Plate C6802-4 TL Orientation, MCR Data
, ! 3-6 SONGS, Unit 3: Data and Least Squares Fit Curve for 3-11 Cvu versus Temperature, Plate C6802-5, TL Orientation, l
MCR Data 3-7 SONGS, Unit 3: Data and Least Squares Fit Curve for 3-12 ,
Cvu versus Temperature, Plate C6802-6, TL Orientation, '
MCR Data 3-8 SONGS, Unit 3: Data and Least Squares Fit Curve for 3-13 Cvu versus Temperature, Plate C6802-1, TL Orientation, Surveillance Baseline Data 3-9 SONGS, Unit 3: Data and Least Squares Fit Curve for 3-14 Cvu versus Temperature, Plate C6802-1, TL Orientation, Combined MCR and Surveillance Baseline Data 3-10 SONGS, Unit 3: Data and Least Squares Fit Curve for 3-15 Cvu versus Temperature, Plate C6802-1, LT Orientation, Surveillance Baseline Data
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ILLUSTRATIONS (cont'd)
(- Figure Eage 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 Temperamre, Weld 9-203 (Heat No. 90069), WMC Data 3-14 SONGS, Unit 3: Data and I2ast Squares Fit Curve for 3-19 Cvu versus Temperature, Weld 9-203 (Heat No. 90144), WMC Data 3-15 SONGS, Unit 3: Data and least Squares Fit Curve for 3-20 Cvu versus Temperature, Surveillance Weld, Surveillance Baseline Data 4-1 SONGS, Unit 3: Comparison of the least Squares Fit for the 4-4 Combined MCR and Unirradiated 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 least Squares Fit for the 4-5 Unirradiated Baseline Data with the Irradiated Cyu Data and Least Squares Fit for the Data from Capsule 97, Surveillance Weld l
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TABLES Table East 3.1 SONGS, Unit 3: Compliance with 10CFR50, Appendix G 3-21 3.2 SONGS, Unit 3: Plate and Corresponding Heat Numbers for 3-23 Beltline Plates
. 3.3 SONGS, Unit 3: Weld Wire and Flux Combinations for Beltline 3-24 and Surveillance Welds 3.4 SONGS, 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 Toughness Tests Results Summary, TL Orientation 3.7 SONGS, Unit 3: Charpy Absorbed Energy Values for Weld 3-28 Seams 2-203 A, B, and C and Weld Seam 8-203
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3.8 SONGS, Unit 3: Beltline Weld Material Unirradiated Fracture 3-29 Toughness Tests Results Summary 4.1 SONGS, Unit 3: Surveillance Capsule Shift Results 4-6 4.2 SONGS, Unit 3: ART Estimates at the Inner Surface Location 4-7 for Beltline Materials on 12/16/91 and at 32 EFPY 4.3 SONGS, Unit 3: Surveillance Capsule Upper Shelf Results 4-8 4.4 SONGS, Unit 3: Upper Shelf Estimates at the Quarter-Thickness 4-9 l IAcation for Beltline Materials on 12/16/91 and at 32 EFPY
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Section 1
( INTRODUCTION
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The Nuclear Regulatory Conunission (NRC) in Generic Letter 92-01 (GL 92-01) requested all holders of operating licenses or 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 prepared in response to GL 92-01
, for San Onofre Nuclear Generating Station (SONGS), Unit 3. It identified additional information needed to resolve the 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 8-203, and (4) resolving inconsistencies between Charpy impact properties reported in the materials certification report and the materials surveillance program for the longitudinal orientation in Plate C6802-1.
Revision 1, January 22,1993, incorporated additional materials data obtained from the SONGS, Unit 3, Nuclear Steam Supply System (NSSS) vendor, ABB-Combustion Engineering (ABB-CE),
i the results of calculations performed by Southern California Edison Company (SCE) to better characterize fluence conditions at Weld 8-203, and the results from calculations performed to ,
evaluate the upper shelf toughness for Weld 8-203. It also indicated that additional information was required to confirm heat numbers for the surveillance weld material and to identify the weld I heat number for an unidentified girth weld chemistry.
This revision (Revision 2) incorporates additional materials data and information obtained from the SONGS Unit 3 NSSS Vendor, ABB-CE. These data provide the heat number for the surveillance weld, and the weld wire and flux combination, chemistry, and Charpy data for Weld 8 203. Based on a review of the information supplied by ABB-CE, the chemistry and Charpy energies have been confirmed for the materials in the SONGS, Unit 3 pressure vessel beltline, and the response to GL 92-01 is complete. There is still an inconsistency with regard to the surveillance weld data and its association with the weld seam 9-203. A comparison of the impact energy versus temperature curves in the transition and upper shelf regions for Weld 9-203 (wire heat 90069) with the surveillance weld data indicates a relatively large difference. But a comparison of the impact energy versus temperature curves for Weld 9-203 (wire heat 90144) with the surveillance weld data are in close proximity. Currently, no information is available to explain the difference in the impact data for the surveillance weld and Weld 9-203, wire heat 90069. However, based on the chemistry and impact properties of the surveillance weld, the t surveillance weld does provide a conservative representation of Weld 9-203 overall, and is adequate to assess the shift in reference temperature and drop in upper shelf energy for the SONGS, Unit 3 surveillance program.
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In previous versions of this report the initial RTm for the vessel beltline material with the highest end oflife adjusted reference temperature (i.e., the plate material used in the surveillance 1-1 l
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program) was determined using a combined data set obtained from the materials certification 4
report (MCR) and the baseline surveillance program. In Revision 2, the initial RTor for this material is determined using only the data from the MCR. This change was made to be {
consistent with SCE's interpretation of the Code requirement for defining initial RTer, which is that data to be used in accordance with paragraph NB-2331 of Section III of the ASME Code are the data obtained by the vessel manufacturer to assess the toughness properties at the time of vessel fabrication. This MCR data thus established the initial RTor by satisfying paragraph NB-2331(a)(3) of the ASME Code,Section III. This change also was made so that this initial RTer is defined in a manner consistent with that for other beltline materials where surveillance baseline ;
data were not available. Consistent with the previous revisions of this report, the combined set '
of MCR and surveillance data were used to establish the unirradiated upper shelf energy and the temperature at 30 ft-lb Charpy absorbed energy for purposes of assessing the irradiation effects on the surveillance plate material.
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, heat treatment, residual and alloying element contents, and upper shelf and transition temperature fracture toughness for the !
beltline materials in the SONGS, Unit 3, reactor vessel. Section 4 addresses embrittlement j effects, including irradiation temperature and adjusted reference temperature for evaluation of the beltline materials relative to GL 88-11 and 10CFR50.61.
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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 to the later 1973 version which is in more complete agreement with the intent of 10CFR50, Appendix H. Appendix A to this report provides a detailed review of ASTM E185-73 along with validation that ASTM E185-73 requireinents were satisfied for the surveillance program
, design. With respect to capsule testing and reporting requirements, the latest version of ASTM E185 is required, and these requirements have been updated as listed in Appendix A following ASTM E185-82 (the current approved version).
l 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 F185-73. The one exception to meeting 10CFR50, 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 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-I 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 10CFR50, 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 stmetural 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.
I The details of the SONGS, Unit 3, surveillance program have been described in the FSAR and i
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l subsequent surveillance program testing repons, baseline in and irradiated.rzi The first capsule 4
results have been evaluated for a low fluence following ASTM E185-82 testing and reporting 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 E185-82 is the removal of the requirements for testing heat-affected-zone (HAZ) material. This change has resulted from the difficulty in interpreting HAZ results due to the degree of scatter and the ability to define the usefulness of blunt notch Charpy V-notch
, absorbed energy (Cvu) 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,U 31 and is provided for reference in a subsequent section of this report. '
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~[ Section 3 FRACTURE MECHANICS 6.
This section evaluates compliance with 10CFR50, Appendix G, and identifies the location, heat
, treatment, key residual and alloying element contents, and unirradiated fracture toughness ,
properties 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, i additional information was obtained from the unirradiated baseline surveillance material report,l'1 and the irradiated material in the 97* location surveillance capsule (Capsule 97), which was I
removed from Unit 3 at the end of the fourth fuel cycle.121 1
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3.1 COMPLIANCE WITH APPENDIX G The materials in the beltline region of SONGS,. Unit 3, comply with the requirements of i- ) Appendix G,10CFR50. A summary of compliance with 10CFR50, Appendix G, as specified in i
the FSAR for SONGS, Units 2 and 3, and updated during preparation of this report, is listed in ,
Table 3.1.
'[( e 3.2 BELTLINE MATERIALS IN SONGS, UNIT 3 3.2.1 Location i
i 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.
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[ 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 all beltline plates and welds.
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- 3.2.2 Heat Treatment The heat treatment for the plate materials consisted of austenitization at 1575150 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 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 1150125'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 weld or a plate in the vessel j depended upon the sequence of vessel fabrication; imermediate 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.
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Longitudinal weld seams would see stress relief times 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
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closing girth weld in the' beltline region would see approximately half this amount of time maximum. All of the testing of plate materials was performed on pieces with essentially an i
identical heat treatment as the actual reactor vessel. The surveillance weldment received a fimal l 41-hour and 45-minute stress relief at 1100 F to ll50*F.
3.2.3 Kev Residual and Allovinn Element Contents 1
i The copper (Cu), nickel (Ni), phosphorus (P) and sulfur (S) contents reported for each beltline plate are presented in Table 3.4. The plate Cu, Ni, P, and S contents were obtained 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.
4 A second set of data is included for Plate C6802-1. This set was obtained from broken
, surveillance specimens when the first irradiated surveillance capsule from Unit 3 was tested.12)
Table 3.5 contains the Cu, Ni, P, and S contents reported for the beltline welds. The source documents for the information in Table 3.5 are presented in Appendices C and D. Three chemistry measurements have been made for the surveillance weld and also are reported in Table 3.5. The first chemistry measurement was made as part of the original baseline l '1, while the second and third were obtained from broken Charpy specimens from Capsule 97'l. !
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The surveillance weld was reported by ABB-CE to have been fabricated using one of the weld wire and flux combinations in Weld 9-203 (see Table 3.3). ,
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 Cw 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 (RTmn) 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 95%.
' i The fracture toughness data for the plate were obtained from the MCRs (see Appendix E of this .
report) and baseline surveillance program.tu 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
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t data for the surveillance weld was obtained from the baseline surveillance program. For
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convenience, the Cw, 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 will not require HAZ material to be part of the surveillance program. The raw C, 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 (LT) 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 Cw 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 l average curve through the data is also shown in each figure. The average curves were determined l using a least squares fit to the data and a hyperbolic tangent functional form, where the lower i I shelf was fixed at 2.2 ft-lb and the upper shelf was fixed at the value determined using the l definition in ASTM El85-93 for specimens having fracture surfaces with 95% and greater shear. l For convenience, the figures also indicate the values of NDT, USE, the temperature at which a minimum C, equals to 50 ft-lb (T @ 50 ft lbs) is achieved consistent with the applicable method of ASME, Section 111, NB-2331, and RT 7. As part of the surveillance program, additional Cm versus temperature data were generated for Plate C6802-1;N these data are presented in Figure 3 8 along with a least squares fit curve.
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 average curve through the combined data set in Figure 3-9 was 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, RTm7, and USE 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 (-20 F), while the second value was determined from the unirradiated baseline tests (-10*F). The value measured when the plate was purchased (i.e., the MCR data) is listed in Table 3.6.
The methods used to determine RTer from the NDT and Cw data also are identified in Table 3.6. The method of NB-2331 (a)(3) was used to determine RTm7 for all plates.
I 3-3
Figure 3-10 shows the data and least squares fit line for the LT orientation for surveillance Plate g C6802-1,N while Figure 3-11 shows the data and least squares fit line for the LT orientation reported in the MCR for Plate C6802-1. A comparison of the information in Figures 3-10 and 3-11 indicates a significant difference in the Cm versus temperature curves obtained from the MCR and surveillance program in the LT orientation for Plate C6802-1. An additional review of the Cw 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 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 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 Cw versus temperature curve was obtained for the material in Weld Seams 3-203 A, B, a 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, 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 C, data and least squares hyperbolic tangent curve fit for the surveillance weld material, which was repo*ed by ABB-CE to be wire heat 90069 (see Table 3.3). However, a comparison of Figure 3-13 (Weld 9-203, wire heat 90069) with Figure 3-15 indicates a relatively large difference between the impact energy versus temperature curves in the transition and upper shelf regions. But a comparison of Figure 3-14 (Weld 9-203, wire heat 90144) with Figure 3-15 indicates the impact energy versus temperature curves are in close proximity. Currently, no information is available to explain the difference in the impact data for the surveillance weld and Weld 9-203, wire heat 90069. However, based on the chemistry and impact properties of the surveillance weld, the surveillance weld does provide a conservative representation of Weld 9-203 overall, and is adequate to assess the shift in reference temperature and drop in upper shelf energy for the SONGS, Unit 3 surveillance program.
Table 3.8 presents a summary of the unirradiated NDT, RTym, 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, 8-203 and 9-203 3-4
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r (wire Heat Nos. 90069 and 90144), available C, data indicate that there is a minimum of 50 ft-l lb absorbed energy at 60*F above NDT and, consequently, RTerequals NDT. I I '
Because fewer than three specimens were tested at each temperature, the graphical method of NB-2331 (a)(4) was used to determine RTm7 for the surveillance weld as shown by the intersection of the dashed line and the 50 ft-lb Cm level in Figure 3-15.
. The upper shelf energies listed in Table 3.8 for Welds 3-203 A, B, C,9-203, and the 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 by averaging the three Cm data points obtained at 20 F. The USE for Weld 8-203 was obtained from the data in Table 3.7 by averaging the three C, data points obtained at +10*F. It was determined that the CVN data at -10*F were not on the Upper Shelf.
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Figure 3-1. SONGS, Unit 3: Location and Identification of Beltline Plates and Welds.
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e 200 -
. - San Onofre UnR 3
, MCFlData Material: Plate C6802-1, A533B1 Orieltation: TL 150 =
USE - G814bs ~ -+
. NDI = -20 'F e 50 ft-lbs = 100 5F
~
T @l; t = 40 'F RTnd r
100 8
, c .
i tu
~
Z O 0
50 -b o Measured O
Criculated O
r- ...m a a a a l' n a a a I e a a a l' a a a a ll a a a a 11 a a a a 1
-200 -100 0 100 200 300 400 500 Temperature in Degrees F I
i Figure 3-2. SONGS, Unit 3: Data and Least Squares Fit Curve for Cw versus Temperature, Plate C68021, TL Orientation, MCR Data.
I 1 1
3-7
k 200 -
~
San Onofre Unit 3 MCRData
. Material: Plate No. C680242, A533B1 150 = Orle$ation: A f USE = 115 ft-lbs t NDT
$ - T @j50 p -20 ft lbsV= 70 V 3 . RTndt = 10 Y
. b I 100 -
I .
l (- lu 1
2 O
g h 0
l 50 =
O o Measured Calculated O
j g . . . .m ....i ....n ....i ....n ....r .... e i
-200 -100 0 100 200 300 400 500 I
[ Temperature in Degrees F 1
l Figure 3-3. SONGS, Unit 3: Data and Least Squares Fit Curve for Cw versus Temperature, l f Plate C6802-2, TL Orientation, MCR Data.
l
[ 3-8 l .
k 200 N
, San Onofre Unit 3 MCR Data Mater lal: Plate No. C6802-3, A533B1 Orien':ation: TL
"# " 105_Mn 150 = --
NDT = -10 'F
, T@150 ft-lbs = S0 'F
.o RTndt = 20 'F
~
g O-8 C
w 100 =
e h
~
{
Z 9 0
d 50 =
- o Measured o
o Calculated
~
g . ........r ....r ....i ....i ....i .... o
-200 -100 o 100 200 300 400 500 Temperature in Degrees F Figure 3-4. SONGS, Unit 3: Data and least Squares Fit Curve for Cm versus Temperature, Plate C6802-3, TL Orientation, MCR Data.
[
3-9
M k.
I t
200 -
- San Onofre Unit 3
. MCR Data l Material: Plate No. C6802-4, A533B1 Orientation: TL 150 --USE r118 d tits
. NDT = -30 'F e ~ T @ jSo ft Ibs = 70 'F E RTndt = 10 'F o j t 1 h O O g 100 =
c .
I W z "
o 0 ,
50 - O-O Measured Calculated O
a .. n I a a a a l' a a a a l'a a a a l' a a a a I a a a a 1 a a a a l' l
-200 -100 o 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, Plate C6802-4, TL Orientation, MCR Data.
I 3-10
(
200 -
~
=
San Onofra Unit 3
. MCR DE Materldl: Plate NO. C6802-5, A533B1
~
Orient $ tion: TL l
. 150 7 St: E~1TB~K@5' j
NDT = ,D P e ~ T @ 50 ft-lbs = 7D 'F
$ ~
RTndt = 10 Y E 6 6
~
100
( $ '
Z l o0
~
O
=
50 O Measured o Calculated
. ....a a a a F a a a a l a a a a l a a a a 0 a a a a 11 a a a a U
-200 -100 0 100 200 300 400 500 Temperature in Degrees F
. Figure 3-6. SONGS, Unit 3: Data and Least Squares Fit Curve for Cw versus Temperature, Plate C6802-5, TL Orientation, MCR Data.
9
, 3-11 i
t L
i I
T 200 --
. San Onofre Unit 3 MCR Data Mater lal: Plate No. C6802-S, A533 31 150 - Men 1 ado d
,, USE p 92 ft-lbs
, NDT y -40 'F g "
T @ p ft lbs = Bo 'F RTndt = 20 op d -
N g 100 =
g i 5 "
O
~
Z 0
O 1
50 =
O
- o Measured Calculated 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 C versus Temperature, Plate C6802-6, TL Orientation, MCR Data.
{
3-12
1 l
l 1
I 200
. . i i : ,
, f = 0.0 i 6 i
t i
i e
i e
i i
I . . 1 I $
4 4 I I I
. . , , , .I San Onofre Unit 3 '. . . '. .'
Surveillanca Program l l l l
' Material:' Plate No.'C68021,'SA533B 1 l l 150 . Orient ation :.TL - -, -.' - - - - - ,- ' - - - - - -. l - - - - - - '- - - - - - - '- - - - - - -
. USE = 92 ft-lbs .i i i
i
' ' ' i NDT = .10F . .' . i i
$$ I i I t .
. m .
i i
7 . . . ,. ,
h I 1
o I
. I
.O g, 100
.i .i
.------ --.----,-------.i------ i--.---
i
. O ,
i c.-----.. --.---.-
i o l o l c , l w '
l l ,
o , ;
. . o. O , ,
, Z . . . . .i o ,
g
. D i
- i . , , ,
- , . 9 ,
50 - - - - - -, l- - - - - - - ,l - D - - 4, - - - - - - - ;, - - - . - - *r - - - - - - - l- - - - - - - -
, I t l 1
. 1 -e I .
I . t . .i .
I l . 1 . .
l t Q.
8 B t
. O f I i
e o
n 1
. , D , , , . .
200 100 0 100 200 500 400 500 Temperature in Degrees F Figure 3-8. SONGS, Unit 3: Data and Least Squares Fit Curve for Cm versus Temperature, Plate C6802-1, TL Orientation, Surveillance Baseline Data.
3-13
l 200
' San Ono,fre Unit 3' ' ' ' '
5 , . I t Combined MCR & Unirradiated Baseline Data l l Material! Plate No.'C68021' SA5338-1 l l
, Orientatlon: TL l l l l .'
USE = 9 , , , , ,
150 - - - - - - -; 5 f t-lbs
l-------i-------t------F-------l--------
N , ,
.o ,l , , , ,
r , , , , , ,
i , , , , ,
W ' ' ' '
. .' ,' ' O '
'o g l 0 l l
(
u e
100 --------------~,~------,l-------.l8-------------,'--------
E l l oo : o l l 2 -
l o o
> l o,
l l l
l O ,i 9 . ,
so ------,'--------l-n--0-------i-------l--------l--------
l l l l
, , 0 6, , ,
l i ,
.o
, oi , , a ,
o e i i ,
o l l l l 200 100 0 100 200 300 400 500 Temperature in Degrees F i
Figure 3-9. SONGS, Unit 3: Data and Least Squares Fit Curve for Cw versus Temperature, l Plate C6802-1, TL Orientation, Combined MCR and Surveillance Baseline Data.
I 3-14
t i
I I
f' i- .
200 =
j f = 0.0 150 San Onofre Unit 3 ,
Surveillance Program g Material: Plate No. C68021, SA533B1
,r .
Orie'ptation: LT
- u. . USE = 91 ft lb4 NDT =0V 100 =
0 m .
B g . O o .
O
$O = M O
O 0 -'--""''''ll '''''' '
M 100 0 100 200 300 400 500 Temperature in Degrees F Figure 3-10. SONGS, Unit 3: Data and Least Squares Fit Curve for C versus Temperature, Plate C6802-1, LT Orientation, Surveillance Baseline Data.
I 3-15
L 4
'I.
4 .
200 -
. San Onofre Unit 3
~
MCR Data Material: Plate No. C68021, SA53361 Orlehtation: LT 150 '*E "13L N --+
NDT = -10 'F
= - 8
.o 3
h-g 100 =
e .
( W z -
0 o Measured l 50 =
0 O Calculated O
. O O
~
0 .
-a a ia a a a l' a a e a I! n a a a I e a e a 1 a a e a l'
-200 -100 0 100 200 300 400 500 Temperature in Degrees F Figure 3-11. SONOS, Unit 3: Data and least Squares Fit Curve for Cw versus Temperature, Plate C6802-1, LT Orientation, MCR Data.
I l 3-16 l
~
(
200 -
O
. O O
150 =
e O
E San Onofre Unit 3
- - 8g WMC Data ateti.all_Wp.l.d_ Seam 3-203 1oo =
g ~
ySE = 161lft-Ibs
( w NDT = -70 of 2
o T @ 50 ft-lhs = -40 9 g . RTndt = -7d 'F 50 -
O Measured
~
O Calculated i 1
~
l o I l
-200 -100 o 100 200 300 400 500 Temperature in Degrees F Figure 312. SONGS, Unit 3: Data and Least Squares Fit Curve for C versus Temperature, Weld 3-203, WMC Data j 1
3-17 1 l
i
e
. I f
200 -
I San Onotre Unit 3 WMC Data
)
. Mater,at: Weld Seam 9-203 Heat No.90069 150 -
USE := 123 ft-lbs NDT , -60 'F j . -40 'F 0 T @ fo ft-lbs = 0 0 3 . RTndt = -60 'F -G L 0 d 100 s .
t =
~ 4 z 6 o
- o 50 O g Measured
. Calculated p
a a a a i a e a a Il a a a a 11 e a a a l' a a e a I: a a a a Il e a a a l' i
-200 -100 o 100 200 300 400 500 Temperature in Degrees F i Figure 3-13. SONGS, Unit 3: Data and Least Squares Fit Curve for C m versus Temperature, Weld 9-203 (Heat No. 90069), WMC Data.
(
3-18
r e
'Pd
'l s.
l
\ -
200 -
~
San Onofre Unit 1 WMC Data
. Materiat: Weld Seam 9 203 Heat Plo.90144 150 USEa 91 ft-lbs
, NDT = -50ep g -
T@! 0 ft-lbs = lo'F RTndt = -50'F k -
li.
E 100
$ =
W e i g .
O 50 -
~
O Measured O
. Calculated n
...<\ ...\ ....\ .... ....\ ....e ... 1
-200 -100 0 100 200 300 400 500 Temperature in Degrees F Figure 3-14. SONGS, Unit 3: Data and least Squares Fit Curve for C versus Temperature, i Weld 9-203 (Heat 90144), WMC Data.
(
3-19
9 is r
200 =
l f = 0.0 San Onofre Unit 3 Elurveillance Program
. Material: W eld f ,
USE = 82 ftl-lbs g "
h0T = -60 Y T @ 50 ft-lbs = 30 V 100 -
FTndt -901 9 +
0 0 t au
. O n 0g u O U . O O O
so -
/ +
. ,/
O O
- /
~
/ 1 O
W ;9..., ...., ....r ...., ....r .... e
.aco -100 o too 200 soo 400 soo Temperature in Degress F Figure 3-15. SONGS, Unit 3: Data and Least Squares Fit Curve for Cm versus Temperature, Surveillance Weld, Surveillance Baseline Data.
3-20
h
( 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 RTmyr or drop weight Tm temperatures are determined.
III.B.S.a Records of fracture toughness Appendix G was not applicable at the testing do not include a time tests were performed. Certification 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 j defined by Paragraph II.H, program include weld and HAZ material ;
from the most limiting plate. Results includes the weld heat- l 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 materials.
Only the heat-affected-zone 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 specimen weldment is not heat of filler wire and a specific lot of 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
Table 3.1 (Continued) l
. 1 Paragraph Description of Non-Compliance Comment -
IV.A.4 Charpy V-notch tests were The ASME Code in effect required test
. not conducted at "the temperature of 60*F below the lowest preload temperature or at service temperature. All bolting material the lowest service was tested at 10*F and met the 35 ft-lb temperature, whichever is minimum requirement of the applicable lower". 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 was tested at !
10*F and another at 20*F and both had Cm in excess of 100 ft-lb. These results indicate that the intent of Appendix G has ,
been met.
l I
t l
1 4
a b
e 3-22
Y
( 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 B3388-1
(
I n e 3-23 1
- - - - -.. , - - - , , , , , , , , - ., --. --.-,-,..-,._,._..--.,-r~. .-- ,, - , - , - .
e Table 3.3 SONGS, Unit 3: Weld Wire and Flux Combinations for Beltline and
(- Surveillance Welds.
Weld Seam Weld Wire and Flux 2-203 A, B, C' Type Mil B-4 Wire, Heat No. 83650, l Linde Type 0091 Flux, Lot No.1122 3-203 A, B, C' Type Mil B-4 Wire, Heat No. 88114, l Linde Type 0091 Flux, Lot No. 0145 9-203 6 Combination of(1) Type Mil B-4 Wire, l Heat No. 90069, Linde Type 124 Flux, Lot No. 0951, and (2) Type Mil B-4 Wire, Heat No. 90144, Linde Type 124 Flux, Lot
. No.1061 8-203' Type Mil B-4 Wire, Heat No. 88118, Linde Type 0091 Flux, Lot No. 0145
/
Surveillance
- Type Mil B-4 Wire, Heat No. 90069, Linde Type 124 Flux, Lot No. 0951
- b. Basis is SONGS Unit 3 FSAR for weld wire heat 90069 and is consistent with handwritten note in Appendix D. Weld wire heat 90144 was provided by CE as the second weld wire used to fabricate this seam.
- c. Weld wire heat number and flux type confirmed by ABB-CE letter dated November 4, 1993 contained in Appendix D.
h 3-24
Table 3.4 SONGS, Unit 3: Key Residual and Alloying Element Contents for Beltline
( Plates.*
. Plate ABB-CE Number Lab No. Cu Ni P S CF6 C6802-1 P14214 0.06 0.58 0.005 0.013 37 P18195 i
C6802-l' O.06 0.58 0.009 0.014 37 C6802-2 Pl4244 0.04 0.57 0.009 0.013 26 '
P18196 C6802-3 P14223 0.06 0.58 0.005 0.012 37 P18197 C6802-4 P14452 0.05 0.56 0.007 0.010 31 P15391 i
( -
C6802-5 P14453 0.04 0.55 0.011 0.013 26 P15392 ;
C6802-6 P14454 0.06 0.62 0.007 0.013 37 P15393 ,
- a. Average values (see Appendix B)
- b. Chemistry factors from Regulatory Guide 1.99, Revision 2
- c. Measured when the surveillance tests were performed for Capsule 97t2 )
i 3-25 m.__ _ _ , - - - . . , . . , , .
l L r
r Table 3.5 SONGS, Unit 3: Key Residual and Alloying Element Contents for Beltline
( Welds.
- . Weld ABB-CE Seam Lab No. Cu Ni P S CF' 2-203A D17360 0.04 0.17 0.011 0.012 40 2-203B D17361 0.05 0.21 0.011 0.013 50 2-203C D17362 0.04 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 6
9-203 D23985 0.06 0.04 0.010 0.009 34 9-203* D28503 0.05 0.04 0.007 0.011 31 8-203 D17888 0.05 0.17 0.009 0.008 46 t
Surveillanced 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 Mil B-4 Wire, Heat No. 90069, Linde Type 124 Flux, Lot No. 0951-see Appendix D
- c. Values from WMC for Type Mil B-4 Wire, Heat No. 90144, Linde Type 124 Flux, Lot No.1061--see Appendix D ,
- d. Measured when surveillance program was developedVI i
- c. Measured when the surveillance tests were performed for Capsule 97[2] ]
l l
i f
3-26
% .- - - , . - ,. ~ - , . - - - , , ,
t
~
I( Table 3.6 SONGS, Unit 3: Beltline Plate Material Unirradiated Fracture Toughness Tests i Results Summary, TL Orientation.
Initial Plate NDT RTer Procedure to USE ,
Number ('F) ('F) Determine RTer (ft-lbs) m.
4 C6802-l* -206 40 NB2331 (a)(3) 95 C6802-2 -20 10 NB2331 (a)(3) 115 '
C6802-3 -10 20 NB2331 (a)(3) 105 C6802-4 -30 10 NB2331 (a)(3) 118 C6802-5 0 10 NB2331 (a)(3) 116 C6802-6 40 20 NB2331 (a)(3) 92
- a. This plate is included in the surveillance program. RTer is based on the MCR data (see Figure 3-2), and the USE value is based on the combined data sets from the MCRs and unirradiated surveillance baseline (see Figure 3-9) -
- b. An NDT value of -20*F was determined when the plate was purchased (-10 F was '
determined from the baseline surveillance program). ,
t h
e
(
,l 3-27 I
i W 7
L i,
\*- Table 3.7 SONGS, Unit 3: Charpy Absorbed Energy Values for Weld Seams 2-203 A, i B and C, and Weld Seam 8-203.
1 Test Temperature Charpy Energy l Weld Seam ('F) (ft-lb) t 2-203 A, B, C +20 125, 138, 145 8-203 -10 95, 84, 94
+ 10 137,118,119 I
l 3-28 i
r I
a
-( Table 3.8 SONGS, Unit 3: Beltline Weld Material Unirradiated Fracture Toughness Tests Results Summary.
L Initial NDT RTer Procedure to USE
- Weld Seam (*F) ('F) Determine RTer (ft-lbs) 2-203 A, B, C -40' -40 NB-2331 (a)(2) 136 6
3-203 A, B, C -70' -70 NB-2331 (a)(2) 161 i 8-203 -70 -70 NB-2331 (a)(2) 125' 9-203 (90069) -60 d -60 NB-2331 (a)(2) 123 9-203 (90144) -50' -50 .NB-2331 (a)(2) 91 Surveillance -60 -30 NB 2331 (a)(4) 82
- b. Estimated using the average of Cw values obtained at +20'F (see Table 3.7)
- c. Estimated using the average of Cm values obtained at +10*F (see Table 3.7)
- d. Value obtained from the WMC, for Type Mil B-4 Wire, Heat No. 90069, Linde Type 124 Flux, Lot No. 0951 -- see Appendix D
- e. Value obtained from the WMC for Type Mil B-4 Wire, Heat No. 90144, Linde Type 124 Flux, Lot No.1061 -- see Appendix D I
3-29
Section 4 k
ISSUES RELATED TO GENERIC LETTER 88-11 NRC issued Generic Ixtter 88-11 (GL 88-11) in July 1988.' GL 88-11 letter revised the methodology used for estimating radiation embrittlement of reactor 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 TEMPERATURE DURING OPERATION The methodology in Regulatory Guide 1.99, Revision 2, is specified to be applicable for operating temperatures in the range of 525 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 (T) is maintained above the Technical Specification limiting condition for operation of $35'F which applies above 30% power. The normal tsperating band of T ranges from 545'F at zero power to 553'F at 100% power with a tolerance of.i. 2*$.
Thus, there is no time during normal power operation that the SONGS, Unit 3, vessel or surveillance capsules experience temperatures below 525'F.
4.2 APPLICABILITY OF SURVEILLANCE DATA To properly assess the measured surveillance results and to project irradiation embrittlement trends for the vessel, fluence 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 will be used for each unit. The fluence as a function of effective full power years (EFPY) was obtained from the results of the first capsules pulled from Units 2 and 3.
The Unit 2 capsule was pulled at the end of the third fuel cycle which corresponds to 2.85 EFPY.m These data represent the original core for both units, and the best estimate value of 2
peak fluence at the vessel inner surface is 4.34 x 1018 n/cm (E > 1 MeV); the capsule fluence 2
was about 20% higher at 5.07 x 10'8 n/cm ,
At the start of the founh cycle for each unit, the core was reconfigured in a low leakage loading pattern which reduced the vessel and capsule fluxes. 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.r21 The peak fluence value at the vessel inner surface is 6.6 x 10'8 g n/cm2, and the associated capsule fluence is 8.0 x 1058 n/cm2, 4-1
r.
The projection 'of fluence. forward in time is based upon an extrapolation of the dosimetry.
information obtained from the two SONGS capsules. The projected peak fluence at the vessel
(- inner surface at the end of 32 EFPY is 4.2 x 10" n/cm 2,t21 At the point in time of December 16,1991, the estimated EFPY is 5.63, and the projected peak fluence at the vessel inner surface is 8.5 x 10" n/cm 2,
, As indicated in Figure 3-1, 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). In earlier versions of the report, Weld 8-203 was conservatively considered a beltline material because the Cu and
. Ni contents were unreported. Therefore, conservative values were assumed resulting in a very high chemistry factor. In addition, the fluence at Weld 8-203 had been reported in the FSAR to be about 1/37 that of the peak fluence in the vessel. This fluence, in combination with the high assumed chemistry factor, resulted in predicted stata in reference temperature as high as ;
~
those for materials directly surrounding the core. However, recently obtained documentation indicates that the Cu and Ni contents are 0.05 wt% and 0.17 wt%, respectively (see Table 3-5).
Also, recent calculations performed at SCEMI indicate that the fluence at Weld 8-203 is 1/108 that of the peak fluence location within the vessel. The SCE fluence calculations have been used i in the evaluation of Weld 8-203. Based on the revised chemistry and fluence values, Weld 8-203 need not be considered a beltline weld for SONGS, Unit 3, although shift in reference temperature and drop in upper shelf energy are provided for reference later in this section.
i -
Within Regulatory Guide 1.99, Revision 2, there are five credibility criteria that must be met l in order to utilize surveillance data in adjusting the predicted embrittlement trends and/or l
( reducing the assigned margin terms. Three of the criteria are met (proper limiting materials, definitive 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 l from each vessel has been pulled and evaluated. To satisfy these last 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 will be 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 Cvu results from this capsule are shown in Figures 4-1 (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.
1' l
4-2 j l
1
.-.-.---_-,.m.-, -
. .- - - -.--- -., ,- - _ _ - - , , - . - . m, .-
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):
RG1.99R2 = CF (chemistry factor) x ff (fluence function).
The results obtained by Westinghousem 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 Cvu 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 t 34 F = 69"F as compared to 55 - 58*F). The measured shift for the surveillance weld is essentially the same as 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 measured behavior, rather than that predicted from the Regulatory Guide.
Table 4.2 lists the predicted estimates of adjusted RTer (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 RT 7s were taken from Tables 3.6 and 3.8. The results in Table 4.2 show that the plate material C6802-1, which is the plate i
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. The USE results are shown in Figures 4-1 and 4-2, and are tabulated in Table 4.3 as an absolute drop in USE (ft-lb). Also listed in Table 4.3 are 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 materials. 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.
I 4-3
(
200 -
San Onofre Unit 3 Surveillance Program Material: Plate SA533B1 Heat No. C8802 '. -----f=0.0 150 -_ rientittion: A !
f = 8.0e+18 !
m O f = 8.0e+18
~
D
- T E ~
l N 1 g 100 c .
us ;
~
f'
( Z ' j y .
,/
/ -
l i
/
50 -
j
/ OO
. / l 90
/
~
~ /
/ fa '
~
,9 O
- b. . . . , ....r ....r . . . . , - ....< ....,
l
-200 -100 0 100 200 300 400 500 l 1
Temperature in Degrees F \
j 1
l Figure 4-1. SONGS, Unit 3: Comparison of the least Squares Fit for the Combined MCR And Unitradiated Baseline Data with the Irradiated Cvu Data and !
Izast Squares Fit for the Data from Capsule 97, Plate C6802-1, TL Orientation.
I 4-4 4
i
. \
l 8
\
l 1
200 --
, San Onotre Unit 3 Survell ance Program Material: W eld
, f=0.0 150 = +
f = 8.0e+18
, o f = s.Oe+1s
.o -
- 7 E ~
w 100 = ~'
e c .
! tu
/ ,o 0
/
0 to W o
/
50 = y' O
jo
~
/
b
/
7 o err 7.....V....o ....l. ....i ....o .....
-200 -100 0 100 200 300 400 500 Temperature in Degrees F Figure 4-2. SONGS, Unit 3: Comparison of the least Squares Fit for the Unitradiated Baseline Data with the Irradiated Cm Data and least Squares Fit for the Data from Capsule 97, Surveillance Weld.
(
4-5
Table 4.1. SONGS, Unit 3: Surveillance Capsule Shift Results.
[
1 30 ft-lb Shift ('F)
!. Material / CF ff Orientation W RG1.99R2 Current l
l l .
l C6802-1/TL 37' O.94 55 35 58' l
l l Surveillance 2 86 0.94 32 26 30d l
Weld l
- a. See Table 3.4 (Cu = .06; Ni = .58) l 1
- b. Based upon the average chemistries - see Table 3.5 (Cu = .03; Ni = .09) l l
l
- c. Based on the combined data set from the MCR and baseline surveillance program, see l Figure 3-9
- d. Based on the baseline surveillance data, see Figure 3-15
)
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4-6
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 Inner Surface
! Weld Seam 12/16/91 32 EFPY 12/16/91 32 EFPY C6802-1 3 76 0.95 1.37 109 125 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 68 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 66
, 3-203 A, B, C 438 0.95 1.37 12 45
. 8-203 46 0.09' O.25' -62 -48
( 34 9-203 (90069). 0.95 1.37 4 34 9-203 (90144) 31 0.95 1.37 8 34 ;
- a. ART is the adjusted reference temperature equal to the predicted shift (CF x ff) plus the initial RTm plus a margin term equal to 34*F for plates or 56*F for welds (unless the j predicted shift is less than the margin term, in which case the margin is equal to the predicted shift) l
- b. Based upon measured chemistries for this plate (.06 Cu / .58 Ni) - see Tables 3.4 and 4.1 4
- 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 108W P
I 4-7 Y
t t
P
( 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) W RG1.99R2 Current C6802-1/TL 0.06' O.80 16 17 19d Surveillance 0.036 0.80 12 15* 14' Weld
- 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 specified 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 l
t 4-8 I
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i
.. y 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 Seam (wt%) 12/16/91 32 EFPY 12/16/91 32 EFPY l -
C6802-1 0.066 0.51 2.5 80 73 C6802-2 0.04 0.51 2.5 97' 89 C6802-3 0.% 0.51 2.5 88 81 C6802-4 0.05 0.51 2.5 99 91 C6802-5 0.04 0.51 2.5 97 89 C6802-6 0.06 0.51 2.5 77 71 1 2-203 A, B, C 0.05' O.51 2.5 114 105 1
3-203 A, B, C 0.04' O.51 2.5 135 122 8-203 0.05 0.005 0.023 119d 115d 9-203 (90069) 0.06 0.51 2.5 102 92 9-203 (90144) 0.05 0.51 2.5 76 70 l
- 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 1
- d. Based upon an extrapolation of the curves in Regulatory Guide 1.99, Rev. 2
(
4-9
Section 5 1
REFERENCES
[1] A. Ragt, Southern California Edison San Onofre Unit 3. Evaluation of Baseline Specimens. Reactor Vessel Materials Irradiation Surveillance Procram, Combustion Engineering TR-S-MCS-004, November 30,1979.
[2] E. Terek, E. P. Lippincott, A. Madeyski, and M. Ramirez, Analysis of the Southern California Edison Comnany San Onofre Unit 3 Reactor Vessel Surveillance Cansule Removed from the 97* Location, Westinghouse WCAP-12920, Revision 2, May 1994.
[3] M. P. Manahan and J. Garrabrandt, Testine and Analysis of Unirradiated Heat Effected-Zone (HAZ) Material from the San Onofre Nuclear Generatine Station Unit 3 (SONGS-21, Battelle Columbus, May 31,1989.
[4] Telephone communication between S. Byrne and C. Stewart, ABB-CE, and D. Pilmer and S. Gosselin, SCE, June 15,1992.
[5] M. P. Manahan, L. M. Lowry, and E. O. Fromm, Examination. Testine and Evaluation of Irradiated Pressure Vessel Surveillance Soecimens from the San Onofre Nuclear 2
Generatine Station Unit 2 (SONGS-2), Battelle Columbus, December 1988.
t
[6] R. Chang, " SONGS 2/3 RPV Fluence Ratio at Weld 8-203", SCE Calculation No.
N-1020-065, December 1992.
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APPENDIX A !
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SONGS, UNIT 3: EVALUATION OF COMPLIANCE 1
t WITH ASTM E185-73 AND E185-82 ,
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e Suannary of Requirements San Onofre Unit 3 Program per ASTM E185-73
(
, 1.2 Surveillance tests are divided Compliance according to application into two cases:
1.2.1 Case A -
Where both the predicted increase in transition temperature of the reactor vessel steel is 10 0'F or less and the calculated peak neutron fluence (E
> 1 MeV) of the reactor vessel is 5 X 10 ' 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 100 F or where the calculated peak neutron fluence (E ,
> 1 MeV) of the reactor vessel is l greater than 5 X 10 28 n/cm2 4.1 Test Material - Test specimens Compliance shall be prepared from the actual l
{
materials used in fabricating the !
irradiated region of the reactor vessel.
4.1 Samples shall represent a Compliance minimum of one heat of the base metal and one butt weld and one i weld heat-affected-zone (HAZ) if a !
weld occurs in the irradiated I region.
4.1 The base metal and weld metal Compliance to be included in the program ;
should represent the material that may limit the operation of the
. reactor during its lifetime.
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Summary of Requirements San Onofre Unit 3 Program per ASTM E185-73
( -
_ 4.1.1 Vessel Material Sampling - A Compliance minimum test program shall consist of specimens taken from the -
^
following locations: (1) base metal of one heat used in the irradiated region, (2) weld metal, fully representative of the fabrication practice used for a weld in the irradiated region i (weld wire of rod, must come from l one of the heats used in the
) irradiated region of the reactor
- vessel) ar.d the same type of flux, I and (3) the heat-affected-zone associated with the base metal l noted above.
4.1.1 Representative test stock to Compliance provide two additional sets of test specimens of the base metal, weld and heat-affected-zone shall be retalned with full
( documentation and identification.
i 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 - The Compliance chemical composition required by the material specifications for the test materials (base metal and as deposited weld metal) shall be obtained and include, but not be limited to phosphorus (P), sulfur (S), copper (Cu), and vanadium (V).
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1 A-2
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Sussiary of Requirements San Onofre Unit 3 Program' por ASTM E185-73 I
\ l 4.2 Charpy V-notch impact Compliance i specimens corresponding to the Type A specimen described in Methods E 23 shall be employed l
unless material thickness does not !
permit. Both irradiated and )
unirradiated types of specimens i shall be of the same size and '
shape.
I i
4.3 Specimen Orientation and Compliance Location -
For both tension and I 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. l The length of the notch of the Charpy impact specimen shall be' l i
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 j to be removed within 1/2 in, of the root or the surfaces of the welds. 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 affected zones have their notch roots in the heat affected zone at a standard I 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)
I A-3 l
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'- Susunary of Requirements San Onofre Unit 3 Program per ASTM E185-73
.b
, 4.4 Number of Specimens -
The Compliance minimum number of test specimens e for each exposure _ shall be as .
4 follows:
. Case A Case B Charpy Charpy Tension 12 Base Metal 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), three Not Applicable
, tension test specimens shall be used to establish unirradiated I tensile properties.
5.1.1 Vessel Wall Specimens Compliance (Required) -
Specimens shall be irradiated at a location in the reactor that duplicates as closely as possible the neutron-flux spectrum, temperature history, and maximum accumulated 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.
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Susumary of Requirassents San Onofre Unit 3 Program per ASTM E185-73 k l 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 - Provisions Compliance 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 Cottpliance irradiation specimens are used (5.1.2), dosimeters with the test specimens and dosimeters either in
, a separate flux monitor capsule 1 adjacent to the vessel wall or in a vessel wall capsule.
I 5.3 Test Capsules -
To prevent The specimens from the 97* Capsule deterioration of the surface of Location had corroded.
the specimens durin9 test' the Metallurgical evaluati n by ses specimens should be maintained in concluded form the corrosion (in the an inert environment within a insignificant, with a maximumtodepthbe of pitting) corrosion-resistant capsule. of 0.8 mils. The results of the charpy testing were deemed credible, and are therefore in compliance.
5.3 The temperature history of the Compliance
,. specimens shall duplicate as closely as possible the temperature experienced by the reactor vessel, i
A-5 l
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4 Summaary of Requirassents San Onofre Unit 3 Program per ASTM E185-73 1 I
-k I 5.3 Surveillance capsules should Compliance l 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 not- Compliance be bouyant to preclude serious radiation exposure to personnel if ;
under water handling is employed.
5.3 Consideration should be given Compliance to the design of the capsule and ;
capsule attachments to permit i insertion of replacement capsules into the reactor at a later time in the lifetime of the vessel. I
( 5.4 Specimen Withdrawal -
A Compliance l minimum surveillance program shall I consist cf three capsules for Case !
A and five capsules for Case B. l It is recommended that capsules be j withdrawn as described in Table 1. '
(See Table 1 of ASTM E185-73.)
l l
6.1 Radiation Environment -
The Compliance l neutron flux, neutron energy l spectrum, and irradiation l
.. temperature of surveillance ,
specimens and the method of '
determination shall be documented. l A
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A-6 I
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Susanary of Requirementr: San Onofre Unit 3 Program per ASTM E185-73 k.. <
6.2 Neutron Flux Dosimeters - Flux Compliance dosimeters for a particular program shall be determined by - ,
referring to Metho.1 E 261.
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summary of Requirements San Onofre Unit 3 Program !
per ASTM E185-82 l b
8.1 Temperature Environment - The Compliance ;
maximum exposure temperature of the surveillance capsule materials shall be determined. If a -
discrepancy (>14*C or 25'F) occurs l 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: ,
i 8.2.1 The neutron flux density, neutron energy spectrum, and i neutron fluence of the ;
surveillance specimens and the corresponding maximum values for ]
the reactor vessel shall be determined in'accordance with the g guidelines in Guide E 482 and Recommended Practice E 560.
l 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 define the strength versus temperature relationship.
(
A-8
7, r Summary of Requirements San Onofre Unit 3 Program i, per ASTM E185-82 i '
l 9.1.2.2 Irradiated - One specimen Compliance
... from each material shall be tested at a temperature in the vicinity of the upper and of the Charpy energy transition region. The remaining specimens from each material shall be tested at the
[L service temperature and the midtransition temperature.
I 9.1.3 Measurements -
For both Compliance k
unirradiated and irradiated materials, determine yield I
strength, tensile strength, fracture load, fracture strength, fracture stress, total and uniform elongation, 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 where the measurements )
described in 9.2.3 are made. 1 9.2.2.2 Irradiated - Specimens for Compliance 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 f t-lb) , and 0. 89-mm (35 mil) lateral expansion
[ index temperatures and the upper shelf energy.
A-9
Summary of Requirements San Onofre Unit 3 Program per ASTM E185-82
(
9.2.3 Measurements - For each test Compliance ,
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 ft-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 average curves.
9.2.3.1 Obtain from the material Compliance qualification test report the initial reference temperature (RT m) as defined in ASME Code,Section III, Subarticle NB 230 for unirradiated materials.
i 9.3 Hardness Tests (Optional) -
Compliance Hardness tests may be performed 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 (Optional) Not Applicable 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.
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summary of Requirements San Onofre Unit 3 Program per ASTM E185-82
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9.5 Calibration of. Equipment - Compliance
, Procedures shall be employed assuring that tools, gages, recording instruments, and other -
measuring and testing devices are ,
calibrated and properly adjusted ,
periodically to maintain accuracy l 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 specified in 9.1.2.
I 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 r 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. '
A-11
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4 Sulamary of Requirements San Onofre Unit 3 Program g per ASTM Eiss-s2 10.2.2 Determine the adjusted Compliance
, reference temperature by adding the shift corresponding to the 41-i r J (30 ft-lb) index determined in lI" 10.2.1 to the initial reference l temperature obtained in 9.2.3.1.
1 __..____.___ __ ._
1
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10.2.3 Determine the radiation Compliance g induced change in the upper shelf energy (USE) from the measurements made before and after irradiation using average value curves.
10.2.4 (Optional) - Determine the Not Applicable radiation induced change in temperature corresponding to 50%
of the upper shelf energy before and after irradiation from average value curves.
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 Specimens - Compliance 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 anomalous results.
5 11.1 Where applicable, both SI units and conventional units shall be reported.
O A-12
Summary of Requirements San Onofre Unit 3 Program per ASTM E185-82
(
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 factors between the specimen fluence and the peak vessel fluence at the I.D. and the 1/4T locations.
7 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 RTmn.
11.2.5.2 Describe the basis for selection of surveillance materials.
9
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Summary of Requirements San Onofre Unit 3 Program per ASTM E185-82 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.
11.3.3 Test Specimen Design: Compliance 11.3.3.1 Description of the test
, specimens (tension, Charpy, and.
any other types of specimens i used), neutron dosimeters, and temperature monitors.
11.3.3.2 Certification of calibration of all equipment and instruments used in conducting the tests.
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summary of Requirements San Onofre Unit 3 Program per ASTM E185-82
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11.4.1 Tension Tests: Compliance 11.4.1.1 Trade name and model of the testing machine, 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) Yield strength or yield point and method of measurement; (3) Tensile strength;
( (4) Fracture load, fracture strength, and fracture stress; (5) Uniform elongation and method of measurement; (6) Total elongation; (7) Reduction of area; and (8) Specimen identification.
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Summary of Requirements San Onofre Unit 3 Program per ASTM E185-82
.k 11.4.2 Charpy Tests: Compliance J
11.4.2.1 Trade name and model of the testing machine, available -
~
hammer energy capacity and striking . velocity, temperature conditioning and measuring devices, and a description of the procedure used in the inspection and calibration ;
of the testing 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 (optional): Compliance 11.4.3.1 Trade name and model of the testing machine.
i 11.4.3.2 Hardness data.
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- summary of Requirements aan Onofre Unit 3 Program
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11.4.4 Other Fracture Toughness Not Applicable
- Tests
l 11.4.4.1 If additional tests are
~
performed, the test data shall be reported together with the
, procedure used for conducting the tests and analysis of the data.
11.4.5 Temperature and Neutron Compliance 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 3 fluence in terms of neutrons per j
( 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 nuclear data.
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t Summary of Requirements San Onofre Unit 3 Program per ASTM E185-82
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11.5 Application of Test Results: Compliance
^
11.5.1 Extrapolation of the neutron flux and fluence results .
to the surface and 1/4T locations of the reactor vessel 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.
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- - _ _...,yr--m-.y .m w_-- -- - ----
l APPENDIX B SONGS UNIT 3: BASES FOR PLATE CHEMISTRY MEASUREMENTS l
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ABB June 8, 1992 S-MECH-92-050 Mr. Steve Gosselin Southern California Edison 23 Parker Street Irvine, CA 92718
SUBJECT:
VESSEL PLATE CHEMICAL ANALYSIS SOURCES
Dear Mr. Gosselin:
The purpose of this letter is to provide background information pertaining to beltline material chemistry data for the plates which were used in the fabrication of the SONGS Units 2 and 3 reactor vessel. Recently, differences were noted in the chemical analysis results reported for the SONGS 2 and 3 :
reactor vessel beltline plates. A review has been performed which identified !
that these differences arose from the fact that different source information was used. The source information is noted below:
SONGS 2 "CMTR" - Lukens Steel Mill analysis "FSAR" and "CEN-189" - Chattanooga analyses dated 3/20/70 and 11/26/73 SONGS 3 "CMTR" - Lukens Steel Mill analysis -
"FSAR" - Chattanooga analysis dated 1/25/74 and 3/20/74 "CEN-189" - RPV surveillance program Chattanooga analyses dated 7/16/75 and 5/4/78 In order to respond to the plate chemistry questions of NRC Generic Letter 92-01, pertinent background information is provided followed by a specific recommendation.
First, the Lukens chemical analysis data was provided with the CMTR for information only, whereas Chattanooga analyses were used as the basis for licensing transmittals. This was done as a matter of C-E practice to maintain consistency of results. (Lukens used both different equipment and analysis standards, which could yield different reported chemical contents than the Chattanooga laboratory.)
ABB Combustion Engineering Nuclear Power Comtusion Eng.neerrg inc P O Don 500 Tewohone (203) 688-1911 1000 Prospect HA Road Fax (230) 285-9512 ;
Windsor, Connecicul 0695M i
_n -
4 b I
I Mr. Steve Gosselin S-MECH-92-050 l June 8, 1992 Page 2 of 3 Secondly, for both SONGS Unit 2 and 3, chemical analyses were required by both i
the C-E reactor pressure vessel specification and C-E surveillance program i specification. Since these analyses were performed in.two separate instances '
by the Chattanooga facility on the same material, it is ABB C-E's position l that the average of these two analyses would be most representative of the plate chemical content. (Notes For both units, the "CE Analysis' value is an average of the chemical contents aquired in accordance with the vessel and surveillance program spe:ification.)
t Therefore, the recommended chemical composition for both SONGS vessels is the f average of the two Chattanooga chemical analyses, provided in Table 1, and ]
titled "CE Analysis".
Should there be any additional questions, please do not hesitate to contact me !
at (203) 285-3469.
Sincerely, ;
COMBUSTION ENGINEERING, INC.
l S. T. Byrne Supervisor, Reactor Vessel Integrity STB /CDSteds I
cca D. Pilmer (SCE) '
B. Chang i W. Gahwiller C. Stewart M. Wade l
)
STB 060.WP i
l i
I l
l
^
Mr. Steve Gosselin S-MECH-92-oso June 8, 1992 Page 3 of 3 TABLE 1 i, si l U23 RV BELTLINE REGION PLATE COPPER AND NICKEL CONTENT l E i i 2 l l Cu Content (wt %) l Ni Content (wt %) l l Plate F , l , ll l No. l CMTR l CE Analysis l CMTR l CE Analysis l i:
l Unit 2 l C . , , i ll l C-6404-1 l o.11 l o.10 l 0.si l 0.s6 l ll l l l l ll l C-6404-2 l o.12 l o.lo l 0.61 l 0.s9 l ll l l ; ; ll l C-64o4-3 l 0.12 l o.lo l o.62 l o.s6 l C l l l ; ll l C-64o4-4 l o.12 l 0.lo l o.63 l o.62 l C l l l l ll l C-6404-5 l o.12 l o.11 l 0.63 l o.64 l IF l l l l ll l C-64o4-6 l o.12 l o.10 l o.s4 l o.s8 l ll ll l Unit 3 l C . , , , ll l C-6802-1 l 0.o6 l 0.o6 l o.se l o.s8 l C ; l l ; ll l" C-68o2-2 l o.o4 l o.o4 l o.s8 l o.sv l' l l l l l" C-6802-3 l 0.o6 l o.06 l o.s7 l o.s8 ll l l ; I ll l C-68o2-4 l 0.os l o.os l o.s8 l o.s6 l C l l l l ll l C-6802-s l o.o4 l o.o4 l 0.s2 l o.ss l C ; ; l l ll l C-68o2-6 l 0.o6 l I
o.o6 l 0.65 l 0.62 l 11 t t , ,1 tl l
l l
l l
l
DATE 8ECEIVED
'..s
- .s . '
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'f,f;s.h)bbh.bbb.[$bbbb3b3bb 5
s Intermediato Shell - Metallurgical R & D Mr. D. R. Moss *
' ,: L Depa rtment Contract 72170 ,
- Chatta nooga Job No. A-98035 Project No. 960001, '
cc: Mr. R. D. Bradford .
Mr. H. N. Dinwiddle .
January 25,1974 Mr. J. F. Lovelady Material for this contract was purchased from Lukens to SA-533, Grade B, Class I. This report is in compliance with specifi-cation requirement of subject job. Identification of material and chemistry of submitted sample,s is shown in Table 1.
Analytical samples were obtained at 1/4T of plate thickness.
4
< , n. :L
'/ J. A. Kosik .
t JAK:mc attachment
- 6 e _e .
- g 3.Y '
. e
?
s
-. . . -: .........u,-'
. , , . . . . ,i.: 4... -.-%.-.
l
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/ . FCE*3 . .
l ' -
n + v. J c.k.
TABLE,I_ '
C
/ , .
pg Lab No. P14214 Lab No. P14223 Lab No. P14244
) Heat No. C-919 5-2 Heat, No. C-9195-1 Ileat No. C-9218-2 Code No.' C-6802-1 Code No. C-0802-3 Code No. C-6002.-2 T est Sa mole W. C. . i Test Sample W.T. ' Test Snmple W.S.
S1 . 2 3. .. .23 . 2 3' .
Sul .th .' .014 .012 .013
][os , f .- .008 .008 . .011 .
Mn 1.38 1.37 1.30 Car .24 .23 .24 ..
Cr .07 -
.07 .10 .
N1 .57 .57 .55 Mo , . 58 .. .59 .56 B .0005 . .0005 .0005 Cb <. 01 g.01 4 01 -
Ti (.01 <.01 4 01 Go .010 .010 *
.008 Cu f.. . . .05- -
. 05 -
.04 Al .033 .028 .035
. N2 .010 .
.009 .010 V G'l .005 -
.005 .003 W
. (. 01 (. 01 4 01 As .009 .009 .008 Sn .005 .005, .003 .
Zr .002 . . 002 .001 4
+
~ . . - . . .... - . ....- . . . .-, _
cM4 . cu hy
- va 4,. ht,w P 645 L. "$ COMBUST 3DN BPJISSDN Mr. B. R. Moss Analyses of Core Region ,Pjates Metallurgical R & D To Specification 00000-PE -110 Department Job No. A-98035 Chattanooga c'c: Mr. R. E. Lorentz, Jr. Contract 72170 Mr. R. D. Dredford Project No. 960001 Mr. H' N. Dinwiddle
, Mr. P. C. Kiefer Mr.' S . R. Lewis -
. March 20,1974 Annie' Lower shell plates for the core rpilon were purchased from Lukens Steel on our P. O. Number 40-82267 to n'ST2.+SA-533, Grade;D, Class I specification and to C. E. Purchase Specification N-P3F19(a). The three plates were purchased'to
. 270-3/4" x 109-5/16" x 9-11/16" size. .
- Purchasedm ' aterial is identified as follows:
Lab No. Heat No. Code No: 7 Piece No.
P14452 C-9220-1 C6802-4 ,215-02
. P14453 C-9218-1 C6802-5 215-02
. g P14454 B-3388-1 C6802-6 215-02 Analytical samples were taken at 1/4T below ID surface Table I shows chemistry of submitted samples.
/
%M -
J. A. Kosik JAK:me :
attachment -
o
s, -
TABLE I
. Chemistry of Plate Material C - k U ~L M C hh l. - ( . . ,
C - b 91_' b Lab No. P14452 Lab No. P14453 . Esb'No. P14454 S1 .24' .23 .24 S .009 .013 .011 P .007 .011 .007 -
1.45 h4n 1.32
- 1.32 .- -
C .22 .25 .22 '
Cr .10 . .12 .03 Ni .57 .57 .62
.- Mo -
.57 61. .
- ; .59: .
. . , i /
. B ,a .0002 .
.'.0002 . '. 0002 i . - -
. Cb ( 01 ( 01 dO1 ,
~
Ti (. 01 (.01 4 01 Co . .010 '.008 '.006 Cu .05 ~
.05 .06 Al .046 .047 .023 N2 .010 .009 .000 V .005 .005 .005 W (.01 <.01 4 01 As .011 .009 .009 Sn .004 .003 .005 -
Zr .001 .001 .001
. . -. .a . . .. .
h___
I g \$urv.) 4 5 *V. Wilc/
cJo:tt. pg; (-o r 4'#
- Interot ce Correspondenco f
E POWER SYSTEMS To: B. R. Moss SurveillanceProgramAn'akysis Metallurgical & Mater:
1970-72 CENPD Pressure Vessel Laboratory - Chattanoc Southern California Feison III Contract U1R Job No. B38V7D Project No. 960001 cc: Elaine White May 4, 1978 I$MAY 04 gggg Chemical analyses and description of test plates and weld materials are noted in the attachment. Sampling for these analyses was taken at 1/4 wa.'.1 thickness.
W. A. House
- yg, t . . . s y $// '
.u. k W- ((p ,eoer :'
i
,! : 4)
(
.(,.,e.t!w - ( .i<*2 Y
/...,',., j,,.. $hh4 MNh*
I
I o , : i 0 )
./' \
**.. l' Lab No. P-18195 P-181.9 6
- P-18197 Plate Intermediate Intermediate Intermediate Code C6802-1 C6802-2 C6802-3 i Heat C9195-2 C9218'-2 C9195-1 C 0.25 J,44L o.ty 0.25 Mn 1.38 . 1.35 1.37 P 0.002 0.007 0.002 S 0.11 ' O.12' O.12 Si 0.24 0.25 0.24 Hi 0.58 0.59 0.59 Cr 0.06
- 0.12 0.06 Mo 0.55 0.56 0.54 V 0.004 0.003 0.004' Cb 40.01 40.01 ,
40.01 Ti <0.01 40.01 40.01 Co 0.009 0.010 0.009 ~
- Cu 0.06 0.05 0.06 A1 0.028 0.031 0.026 B 4 0.001 (0.001 <0.001 W 40.01 40.01 40.01 Sb 0.0027 0.0016 0.0026 As <0.001 40.001 40.001 Sn 0.004 0.003 0.004 Zr (0.001 (0.001 (0.001 Pb <0.001 40.001 (0.001 N2 0.009 0.008 0.009
- bWtEd ptr RRR 7 2 l 7 0 - S - 249 - l
- - gg,5 6 gr Lo wer 9 d C6"~.)
C intoroffice Corro.spondence 39 .
'is.ni? POW':Ri d SYSTET'alS
- snbicet i rom
- D.11. Moss Surveillance l>rogram Analysis Metallurgical 61.'atoric!!
1970-72 CCN1'D Pressure Vcssels Laboratory - Chatianooga Southern California Edison III
- R. E. Lorentz, Jr. Project No. 9G0001 July 16,1975 Contract No. 72170 Job No. B-30070 if: Shop Order A-98016, Lower Shall and Coro Supports '
f Chemical analysis and description of test plates are noted in the attachment. Sampling of these materials for analysis was taken at 1/4 wall thickness
. from I.D.
4"I i .WL.-z,p W. A. House WAH/sb . . di.'i.. .?. 6 !:h.'n
s - 121b No . . P15391 - l'15392 P15393 Co'Jo No. : C-0002-4 C-6002-5 C-Cit 02-6 linat No. CD220-1 C021t[.1 10303-1 S1 0.26 0.24 0.26 - f S 0.011 0.012 0.015 P 0.007
)
L . 0.010 0.006 l Mn 1.36 1.20 1.50 l C
- 0.24 ' O.24 0.24 Cr 0.09 0.09 0.01 Ni 0.56 0.53 0.61 i h4o 0.58 -
0.56 0.59 ' B < 001 <.001 <.001 l Cb < 01 <.01 <.01 . T1 (.01 (. 01 (. 01 Co 0.007 *0.005 0.002 Cu , 0.05 0.04 0.06
~'
Al-Sol . . 0.033 0.021 0.020 Al-Ins. , 0.001 0.002 0.002 V 0.004 0.003 0.003 W (.01 < 01 . <.01 As 0.000 0.004 0.002 Sn 0.004 0.003 - 0.004 Zr (.0 01 - 4.001 <. 001 Pb . 4.001 -(. 001 <.001 N2 0.010 0.008 0.007 s 02 0.003 0.005 0.003
.s g 0
APPENDIX C SONGS UNIT 3: BASES FOR WELD CHEMISTRY MEASUREMENTS
- s
. /
&f Cbw .W 6 r Mi" &clk Interoffice Correspondence 7
/ POWER SYSTEMS
.To: M. D. Turnmire Surveillance Program An'a' lysis Metallurgical 6 Mater:
1970-73 CENPD Pressure vessel Laboratory - Chattanoc Contract 72170-Job No. A'-98035 Project 960001 l l
, cc: Elaine White June 20, 1978 Chemical analyses and description are noted in the attachment. Samples - . for these analyses were taken at 1/4" wa'.1 thickness.
P W. A. House WAH/ps , I de 8
i { I,. : Lab No. D-17360 D-17361 D-17362 Weld 2-203A 2-203B 2-203C Plates C-6802 - 1 to 2 C-6802 - 2'to 3 C-6802 - 3 to 1 C 0.14 0.'15 0.11 Mn 1.33 1.31 1.20 P 0.011 0.011 0.010 S 0.012 0.013 0.012 Si 0.16 0.16 0.09 Ni 0.17 0.21 0.08 Cr 0.05 - 0.04 0.04 Mo 3.61 0.58 0.60 V 0.006 0.006 ' O.006 Cb 40.01 40.01 <0.01 , Ti <0.01 <0.01, <0.01 Co 0.010 0.010 0.009 i Cu - 0.04 0.05 0.04 A1 0.007 0.008 0.002 B 0.0003 0.0004 0.0003 V 0.01 0.01 Sb 0.01 As 0.013 0.014 Sn 0.013
- 0.005 0.006 0.005 Zr 0.002 .
0.002 0.002 ~ Pb N.D. N.D. N.D. N2 0.005 0.005 0.005 e e 3
o I
/ :
.+
Lab No. D-22245 D-22246 D-22247 Weld 3-203A D-28623 , 3-203B . 3-203C Cirth Plates C-6802 - 4 to 5 C-6802 - 5 to 6 C-6802 - 6 to 4 i C 0.12 0.14 0.13 Mn 1.28 0.12 1.26 1.28 1.24 P 0.012 . 0.012 0.011 S 0.008 0.008 0.008 0.008 0.009 Si 0.15 0.17 0.15 Ni 0.21 0.39 i 0.19 0.21 O.32 Cr 0.04 0.04 0.04 0.10 Mo 0.56 0.57 0.55 V ,0.55 0.004 0.005 0.004 Cb 40.01 0.004 Ti (0.01 40.01 <D3. 01 40.01 <.0.01 <0.01 Co 0.008 0.008 (0.01 0.008 0.013 Cu 0.04 0.04 0.04
~
- A1 0.04- ;
0.005, 0.008- 0.007 0.013 B 4 0.001 W (0.001 .
<0.001 <0.001 0.01 0.01 0.01 Sb 0.01 As 0.008 0.0016 0.008 0.007 0.004 . Sn 0.004 0.004 0.003 Zr 0.001 0.004 0.001 0.001 0.001 Pb 40.001 40.001 '
N2
<0.001 <0.001 0.010 0.005 , 0.008 0.008
~
4 P
1 t 4 sev. v4ta Q Fw W ^ 5 j % .)Interotnce g o g-ft, g g g; for Correspondenc@ f POWER - SYSTEMS . To: B. R. Moss Surveillance Program Analysis Metallurgical & Mater: 1970-72 CENPD Pressure Vessel Laboratory - Chattano< Southern Californi son III Contract 1 Job No. B3 Project No. 960001 cc: Elaine White. May 4, 1978 [
?$MAY Ua gg Chemical analyses and description of test plates and weld materials are noted it the attachment. Sat:pling for these analyses was taken at 1/4 vall thickness.
W. A. House
- WAH/ps 2
[4.A( 7F 6/r. ., . , . -
~ \
em
) .: '41 .
( . (. .', r . t lr.. ! ; .' i ' *<
- 2 '?
i . 6, . , j, . . WiMMMO
1
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/ ;
- WEl-D HA9 !
Lab No. D-30342 '.". D-30343 Weld 2-236A '2-236B Plates C6802-2 to 3 C6802-1 to 2
. i C 0.12
- 0.12 i Ha 1.54 P
1.55 0.004 0.003 S - 0.009 0.009 ' Si 0.39 0.40 Ni 0.08 0.09 Cr 0.05 0.03 Mo 0.55 V 0.55 , 0.005 0.005 Cb 40.01 20.01 - Ti 40f.01 40.01 Co 0.015 0.014 Cu 0.03 7 0.03 A1 0.006 0.005
~~
- B 0.001 W
0.001 0.01 0.01 Sb 0.0012 0.0010 As (0.001 40.001 Sn 0.002 . 0.001 Zr 4 0.001 (0.001 Pb *(0.001 3 N2 (0.001 0.006
- 0.005
- t e f I
e i e i 5 I l i
s Attachment 2 to S MECH 93-071 Page 4 of 6 DATE f- M 74 HETALLURGICAL RESEARCit At40 DEVELOPMElli , Tr At'in bbonsid* x1 S w-s ' J0D fluMDER # 52255"" , CHEMICAL At4ALYSIS OF WIRE-FLUX TEST WELD SAMPLE SAMPLE H0, f2,2 g-1 LAD 180, .Dn TSS - l L TYPE WIRE , r , . ps,3 i k "" 1 SIZE UlRE - 1 HEAT NO, ggff g , FLUX /s/s 9 / 1 LOT H0, n,4 g- - SI . fg S
,. _ .cos s.)
P _ oo 9' HH /3g C , /f CR ,
,a NI
} _f7 H0 ,_ ,g4 CB/TA -
TI CO CU ._ o_c . t
' ' OO $
l. N 2 - FE g1/km 4
APPENDIX D SONGS UNIT 3: WMCs FOR BELTLINE MATERIALS j i 4 1 J 4
..'. ', e e., ,.
. \
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sme
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'd L p n.n nwi.fhJ O 2 ' m e n o. g s -sMd tJJ d202U1J 3 .
** Nuclear Manufacturing Welding Material Cert.1.fication
.. Superintendent
- Nuclear Q2ali'ty Nuclear Welding
- il -
and Belease for Sect'on ' i III Engineerics
'4.*..
- '.;
- Applications '
'.; ' Q $l**
' *- '.' ,-, f * . ' ", ;.. . ,'. . '.
* \' '
Bay 29 Bod Boom *
':' " ' . ' ' ~ * * ' .
'I. Inventory Control **'
. ./ Us.
,. Welding Inspection * '
$/fu/f/Py h,k. []. .
Soa-Boco-h 'c t . L.b . L luu)
' ' . ? '. '.
..+...e. t.. .... . . ..-. ,. ' ... E' .O, . .'; .
m .s4. , _Auspeci.Ava . r
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..:.....,.....,.,,. . , - ,s. .
e , , g 3.. . - . v. 3 ~. ., ; . .': s. , . :,, < , : ,. .. . '
- .:v.., .t .. .. :, .. .. .
1 9, s. ., .-
..,,5. ' . . . .
The followin;; velding material has been tested in accordance vith the
. i requirements of SOP g100-23 31 and ceets the recuirements of the latest ;
,' .; .. Addenda to Section III cf the ASSE Code and is released for use on AS.G
. ' . . . . Code vork only:
' i. g .. ,; : .
- is
.. , ..+'......,
. - . . v. . .I.. Coated Electrodes (MA) ;..
. . ,4 :
.d -
., TYPE SIZE
.y' HEAT f IUT E. .
CONTROL J BRAliD E
.f>:5
- . , 2 .a. ...g. z . .:.c.;:. . . . . . i .* . . H. .,
- s. r . . .
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. . . ,qi .. . .* . .
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'.,'...<;.. II. Bare Eleetredes (CTA T4 GIA)
,i
' s.
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' TYPE SIZE HEAT f BRAND 9
. u. .-
.. . + ..
< . i.. .- . . . .
...-..,.. .. ~
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1 III. Flux Electrode Co .bination (SAA)
. t
'TrrE ru TacoE SIZE HEr$ TYPE FIUX IUP f B. y K OW
*%'{ 836Yo 4mde 007/ //z.t :
- y. y
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a 0=2a CDMBUSTIDRI DIVISIDn!
) Subject From - Date
- r. P. C. Kiefer Welding Material Qualification i
to Requirements of ASME Metallurgical Research and Wr. R. Jay Development Department Wr. S. A. Lewis Section III ' Chattanooga Ar. S. R. Lewis Job Number D-32255 , l ' Project Number 960009 February 8,1973 i dr. R. E. Lorentz, Jr. } (r. G. Porter *,,...- ! fr. R. E. Smith .
,toI
' gg)l' .
ans--
- The following test data is for 3/16" diametbr bare wire, Type Low Cu-Phos Heat No. 83650, Flux Type 0091, Int No.1122 A weld deposit was made using the above heat of wire and lot of .
flux Welding
- was done in accordance with C-E Welding Procedure Specification SA-33-34 '
. The completed weldment was given a pqst weld heat treatment of 1150*F A 25'F for 40 hours and furnace cooled to 600*F . _ s,
. l
, TPE TEMP.'F VA t.UE1 IMPACT AND/OR FRACTURE TESTS
, TEMP.
- F val.UES .
.CVN Ft./Lbs. Mils Lat.Exp. NDT
+10 _ Drop Weights '
117- 73 <
+10 120 76
+10 -40 1F 133 79 -30 -40*F
+20 125 2 NF 77
+20 138 81
+20 145 83 I
ALL WELD METAL .505 TENSILE , I I.ab Yield Strength Ultimate Tensile Elongation in
.E.P.d.? _- KSI _ Strength, KSI Reduction of 2", % Area , %
)
77.2 _ . . . . 87.4
.29.5 72.0 l I!
f
. ..:,, - m
**/...
DATE / - 22--73 I HETALLURGICAL RESEARCH AND , , DEVELOPMENT 4 108 NUCLEAR WELDING APPLICATIONS SECTION ' AT,TENTION: IJN4/ W , CCt l 'h' SA , . J00 NUMDER 9 32 2sT ' CHEMICAL
- ANALYSIS OF WIRE'-FLUX ' '
- TEST 3tECO COUPON ' '
SAMPLE NO. j,., g <y jgg , . LAB HO. fjgogg ,p/gog3 - I T.YPE WIRE g g., ,g j,,,, f .,_ ,jL
- SI.Z.E
-- - WIRE .?Ag " %, " '
pyw fpsc - i Y)TNo.
,s
*g3gy; g2ggg ' .
PLUX gj 9 f f ,., 9 / . LOT No. ,,jy j,y
- S l^ .
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./S-
- S. V
_ n o 'r . ns o P.. ,cos oog . HN .
. ), 3y jpg
- C , , ,g; if
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.00 7 on6' *
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sus pawss sysTsss .
\ >
i Nuclear Manufacturing Superintendent **
,, Nuclear Quality Nuclear Welding Applications .
Assurance Bay 29 Rod Room . Welding Material Control (c/c R. N. Try) ~~ l *2 ~~3 ~~ " ' Welding Inspection
~ ~
~ ~ ~ ~ " '
Red-Room- ('!e
- f_ ?b See t ha)
WELDING MATERIAL CERTIFICATION - AND RELEASE FOR Set-)-Jog E -- The following welding material has been tested in accordance with the require- , ments of SOP #100-23.31 and meets the requirenents of the latest Addenda.'to Section III of the ASME Code and is released for use on ASME Code work only: I. Coated Electrodes (MA) .
~ ,
TYPE SIZE HEAT # CONTROL # BRAND
'. LOT #
.~.
z i
., ")
~
- s , .,
II. Bare Electrodes (CTA & GMA) TYPE SIZE HEAT # BRAND ' ' ' s
.. 1 I
III. Flux Electrode Combination (SAA)
. TYPE ELECTRODE SIZE HEAT # TYPE FLUX LOT #
fo~ C L o 'PA.s .
'IS *
*9l O'IVE ;.
s. D'.'C. Binegar
.$ " ~
* '{,. 'j ; f 3
'DCB/ap
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=
. il5s POWER SYSTEMS ,
To - Subject From - Date yp D. G. B!negar Welding Material Certification Metallurgical & Material's
'l , To Requirements of ASME Laboratory cc: R. E. Lorentz, Jr. Section III S. R. Lewis Job Number H-32255 Chattanooga S. A. Lewis Project Number 960009 T. U. Marston
. N. Wamack 16, 1974 M./c/ 6 r 3-20) ,
O
,C ctober .
g The following test data is for 3 16" diameter bare wire, Type Low Cu-Phos, Heat # 88114, Flux Type 0091, Lot # 0145. (Test # 1286)
- A' weld deposit was made using the above lot of electrodes. Welding was done in accordance with SAA-SMA-12.12-102 Th'e completed weldment was given a post weld heat treatment of 1150*F
- 50*F for
. 40 hours and furnace cooled to 600*F. -
IMPACT AND/OR FRACTURE TESTS TYPE TEMP *Fl VALUES TEMP.*F' VALUES NOT l tt/Lbs % Shear MilstatExp Ft/Lbs % Shear MilstatExp t
-104 13 0 7.
-10 127 80 70 . ;
-104 11 0 6' -10 115 70: 64 {
-104 20 5 13 -10 117 70 68
- l
. -80 29 '10 22, +10, 126 80 78
?
-80 30 10. 21 +10 151, 100 81
-80 24 10 13 +10 156 100 84
-40 110 60 66 +50 174 100 86
-40 76 40 48 +50 163 100 85
-40 114 60 68 -
+50 162 100 83 Droo Weights
-70 1 F -70*F
-60 2 NF ,
-50 1 NF ALL WELD METAL .505 TENSILE Lab Yield Strength Ultimate Tens!!e Elongation Reduction of
. Code KSt Strength KSI in 2"%
g) Area % ! d- am. ' WL 77.1 2 (88.8 , 5 71.9 s . .. . .- J rno JMA:gb l I
#7 - 7 b
- DATE '8
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~ HETALLURGICAL RESEARCH At40 ' DEVELOPMEllT i 1*O: WA Wf R Alin .
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CHEM [ CAL A14ALYSIS OF WIRE-FbbX TEST SAMPLE,NO. / 3_ F 4 LAD NO. h / f 7+4
.4. .s *
. TYPE WIRE /St -p/<c.5 SIZE WIRE he.
HEAT NO.- 8 F// V-
- FLUX oo9/
LOT NO.- o /./ f
. ( ~ * .
Si 18 s
.. . S .002 .
g HN /, /C" C
. / 5' O
CR c3 ' HI *
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p)euu.unsiv.c Resenaca 1 wo u.sauaphenr Laa. f rr~ 7f
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. s ao. c .3 2 ~- : s.-.- _ -..
i . - - . . . . . - _ _
. . . . - .-. NG 7'. Oil &tA!CA L t$NALYS/3_h.F Y/lRE & A m Pl.E'..
l . . R No. Y $/.$"" , ...' l .. TYFEIAf7'Lll4 Os FA e.s l l . . . . . . - . size l %. , " l Heir 188 //# . l . ... ._
. _ . _ . . _ Si . 05 , ,_
S O . oof *0 p .ooa #,> * . o , , 1
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INTER-OFFICE CORRESPONDENCE .
'. Q FG a
Eiidj POWER SYSTEMS -
) -
Nuclear Manufacturing Superintendent
- Nuclear Welding Applications Nuclear Quality Bay 29 Rod Room .
Assurance - Welding Materini Control (c/o R. N. Fry) Welding Inspection Rod Room (Met Lab Section) hgQ/p%*
-
- WELDING MATERIAL'CERTIFICAIION AND RELEASE FORg)[,72)g g
ThefollowingveldihgmaterialhasbeentestedinaccordancewiththerequiEe-ments of QCP 7.1 and meets the requirements of the latest Addenda to , Section III of the ASME Code and is released for use on ASME Code work only:
.. I. Coated E1cetrodes (MA) ,
TYPE SIZE REAT # L'OT # CONTROL # BRAND
> .)
II. _ Bare Electrodes (CTA (, CMA) TYPE SIZE HEAT # BRAND - III. Flux Electrode Combination (SAA) - TYPE ELECTRODE SIZE HEAT # TYPE FLUX LOT # 6 U tl0 5 ) h0dhf /kf 8Y [ , ) .
/h POWER SYSTEMS
~
Go 'p_ Subject From - Da to
'd Welding Material Certificatlop., Metallurgical 6 Materials --
J. McDowell To Requirements of ASME
- Laboratory cc: R. E. Lorentz, Jr. .
.. Section III ,
S. R. Lewis Job Number M-32255 Cha ttanoog, a S. A. Lewis Project Number 960009
- 8. Golns OdJ wm 7-ao 3 <-22-'s So C~l The following test da)Ils for 3/16"d r bare wi Type Low Cu-Phos, Heat No. 900[, Flux Type 124, Lot No. 0951 (Test No.1825).
A weld deposit was made using the above heat of wire and lot of flux. Weld 12.e ~"as done in accordance with SAA-SMA-511-0. The completed weldment was given a post weld heat treatment of 1150'F 5'0*F for 40 hours and furnace cooled to 600'F.
- s .
IMPACT AND/OR FRACTURE TESTS vrr TEw.'Fl VALUE5 l TEMP.*F VALUES I .dyn HDT Ft/Lbs % Shear MilsLatExo _ Drop Weight /
-100 13 0 8 -70 1 F
-100 8 0
, -60*F 4 -60 1 F
-100 13 0 5 -50 2 NF
-80 24 5 15 -40 1 NF
-80 43 20 31
-80 25 5 17 '/.
~ -
-40 53 25 36 .+100 119 100 ./ 78
-40 69 40 50 +100 '
100
-40['
0 63/ 83 / 35 50 44 60
/ +100
+160 117 / ' 10 124 123 100 78[h 83 Il 0/ , 82 0/ 97 76 / 40 60 52 67 [7 +160
+160 121 133 1,00 100 81 82
+40 120 90 82 ,
+40 118 90 80 .-
+40 125 100 82 ALL WELD METAI. 505 TENSILP ab Yleid Strengthf
>d a KS! Ultimate Tenstic[ Elon0ation Reduction of
/ Stronoth l'.St / _ in 2"% Arca *t.
68.3 /. 84.7 30.0 69.6 JYM4%f , J MA:Ob
./ - * *
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..' DATE - / 9 - 76
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'HETALLURGICAL RESEARCH Al40
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CHEMICAL ANALYSIS IOF\ NtRE-FLUX' TEST WELD SAMPLE '
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3AMPL'E NO. /g,q,r LAB HO. .R237ff Law . . TYPE WIRE /% p4,3 . SIZE WIRE 7,fg; HEAT NO. 90049 . FLUX
*/A4 .
LOT No. 09s/
/ .
St V _42 .
. S , co ?
) P y
. .0/0 MM j f 4.g C v ,//
- CR y ,oc
/
Hl d .Of MOh . , 4. &
. CD/TA . .
TI CD '
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- . DATE 8"/3' I '
j ) -
.,,.,....... . . REQUEST FORM :.
l j' NCH QUALITY ASSURArtCE
, 1
. ... . . . ... . ,:~,:_ . . . . ,
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-* 4- WET CilEHICAL AllALYSIS OF HIRE SAMPLE -
. . . 7~~ " ... .
^ t ; . !
R llo. 8 7 .7 (?. . Type Hat'1. /o Cu, ! Size #dt, lleat -
%.m di 7 ,
Si , a 4 .. , s .D
) . ., .o g p, IT .uy /
Mn ./. 9 9 't / O ./7 cr . /,' o P/ Hi
./.. o b /
MO .b7 , Cb/Ta . . Ti N.' iY
. -)
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l Fe ll
. Ab .D 20 . ,
4 I
INTER-OFFICE CORRESPONDQNCE
. ../. . ..
mVE3 '
$$$$ FGWER SYSTGEU33 . ' %)-
Nucicar Manufacturing Superintendent .- Nuclent Quality Nuclear Welding Applications Assurance Bay 29 Rod Room ' Welding Material Control (c/o R. N. Fry). Welding Inspection Rod Room (tiet Lab Section) g/d,/f7J WELDING MATERIAL CERTIFICATI0
~
AND RELEASE FOR [ p /f8 gt.=.C y.3d jy The following welding material ha's been tested in accordance with the require-ments'of QCP 7.1 and meets the requirements of the latest Addenda to Section III.of t..he ASME Code and is released for use on ASME Code work oniv: I. Coated Ele' trodes (MA) . . . . TYPE ' SIZE HEAT # LOT # CONTROL # BRAND
*' * ' ~ ~ ~ ~ ~ ~
II. Bare Electrodes (CTA & CMA) . . TYPE SIZE HEAT # BRAND III. Flux Elcetrode Combination (SAA)
. TYPE ELEC; TRODE SIZE HEAT # TYPE FLUX LOT #
YY0 //r,nf/s f//f,lV /W .
/dbl .
O.
. . eg a .g.D...a ..yW. ...M.s M.= g -
.y p.. . *
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- Subject From w Date -
, POWER 3 SYSTEMS .. ... . . y, McDowell Welding Material Certificati,on Metallurgical & Materials to Requirements of ASME', Laboratory - Section III cc:R. E. Lorentz, Jr. Job Number P-32255 Chattanooga S. R. Lewis *
- S. A. Lewis Project Number 960009 D. Butler 5-9-77 The following test data is for 3/16" diameter bare wire, Type Low Cu-Phos, '
Heat No. 90144, Flux Type 124, Lot No.1061 (Test No. 2094). . A weld deposit was made using the above heat of wire and lot of flux. Welding was done in accordance with SMA-SAA-3.3-1.18. The completed weldment was . given a post weld heat treatment of 1150*F 50*F for 40 hours and furnace cooled to 600*F. ,
~
IMPACT AND/OR FRACTURE TESTS ..
. TYPE TEMP 'F VALUES T EMP.
- F VALUES - NDT Ft/Ibs % Shear MilstatExp Drop Weights .. - . . . . . .
, CVN
. ' 80
- 7. 0 3 -60 1 F -50*F
-80 9 0 6. - -50 1 NF 1 F
-80 5 0 3, -40 2 NF
-40 18 0 13
. -40 19 0 13 i
-40 34 15 26 .
+10 57 35 41 +100 90 100 67 )
'+10 50 25 36 +100 89 100 71 l
+10 53 30 40 +100 90 100 70 1
+60 82 80 60 +160 94 100 79
+60 81 80 60 +160 92 100 77 460 76 80 54 +160 93 100 72 ALL WELD METAL .505 TENSILE Lab Yield Strength Ultimate Tensile Elongation Reduction of Code ksi Strength ksi in 2"% ' Area % -
l AN 72.8 87.4 '25.0 ' 33'. 8' ik.k?n JMA:gb
.... - - ,. /
METALLURGICAL & MATERI,Al..S LABORATORY . r {nn s/ S b nm /fll. E Y
~
rfb ' ' (
, ,yuMBER fE2 2SS * '
CHEMICAL AllALYSIS OF WIRE-FLU.X TEST WELD SAMPL i e i-
,JIPL'E H.O. ,,go pp i LAB 110, 7)Nfgos 1-ow TYPE WIRE gu,.pf,,
, SIZE WIRE 3,//g " '
-HEAT NO. .
9o)gg-
. FLUX y'y LOT M0 /O(;}
ej -
.o74 .
. . .- MN J /3o
- P -
.00 7
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REQUEST FORM l . . , , ., ,.:,,. ,,:.. u . :. u . ,::m .._j; _. .,,yg
. p. .
.HCM QUAllTy ASSURANCE
, , ' - ',-.--..-s.:..:.....--.~..-....--..
..:..r ? . m .:- : . ..... .+ .. q.. s . , .
y pf( gj g .
.,......s, y..%.
... . .p.. .-. .d..*.t." .~ . . ...n...a. .. . . ... c.. .
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. ". WET CHEMICAL ANALYSIS OF WIRE. S Al.iPLE_ . . . ;.. ,.: .
*g i *
. . . , i R Ho. Nb ,
. Type Hat'1. , .lo 09 Fla .
j Size . 3 4 "/ \ 1 s a Heat - 90/ W ' ; i s .
, o .3 / l
. Si . <
.' .t .S
... I s
.6/5 V l P \ 006 V Hn l, 9 9 C
. /5 /
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09 Cr Hi \ .06 Ho , I'7 'A CblTa . di l} s l
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. . Cu .o3 V -
0 0b . D'). n2 Ye. . a ..-.. AL .926 .
. . __._ _. m .m ABR MNp Mr. Keith Reeser November 4,1993 Southern California Edison Company S-MECH-93-062 Irvine Operations Center 23 Parker Street, MD 345 Irvine, CA 92718
Subject:
Material Information for SONGS 2 and 3 Reactor Vessel Welds
References:
- 1) ABB/CE Letter No. S-MECH-93-049, " Proposal No. 93-241-C1A; Additional Reactor Vessel Material Information for SONGS 2 & 3", C.
Gimbrone, dated September 8,1993.
- 2) ABB/CE Letter No. S-MECH-93-059, " Weld Fabrication Records for SONGS Units 2 and 3", D. Walker, dated November 2,1993.
Dear Mr. Reeser:
This letter provides weld wire heat numbers and flux types for the following welds as proposed in Reference 1:
- 1) The surveillance weld for SONGS Unit 2.
- 2) Welds 2-203 A, B, and C f : the SONGS Unit 2 reactor vessel.
- 3) The surveillance weld for SONGS Unit 3.
- 4) Weld No. 8-203 for the SONGS Unit 3 reactor vessel.
l The above information was researched using all of the available original fabrication records for , these welds which were obtained from the Chattanooga facility (Ref. 2). The requested 1 information is found in Table 1, and two majorresults of this effort are noted below:
- 1) The above welds consisted of either filler metal type Mil-B4 or E8018 electrodes as noted under " Filler Metal". l l
- 2) It was determined that repairs were made to welds 2-203A and 8-203. l Information regarding the consumables for the repair welds is included in Table
- 1. However, an investigation regarding the extent of these weld repairs was not within the scope of this effort.
l 1 ABB Combustion Engineering Nuclear Power l 1
* ~ ~ ~ ~ $ $ee mw
~ c- musx
??E5n???" l
S-MECH-93-062 Page 2 of 2 1 Table 1 - Weld Consumables for SONGS 2 and 3 Reactor Vessel Welds Filler Vessel Weld metal IIcat No. Flux type Lot No. SONGS Unit 2 surveillance [ Mil-B4] 90130 Linde 0091 0842 [E8018] AA0llP -- -- l 2-203 A,B,C [E8018] BOLA -- -- 2-203 A (repair) [E8018] EOBC -- -- SONGS Unit 3 surveillance [ Mil-B4] 90069 Linde 124 0951 l 8-203 [ Mil ll4] 88II8 Linde 0091 0145 [E8018] IIAAID -- -- 8-203 (repair) i [E8018] GABFE and FAOJE -- -- This effort was performed in accordance with the CE Nuclear Services Quality Assurance Manual for Quality Class I wt.tk. The contents of this report have been reviewed to insure the accuracy of its contents. If you should have any questions regarding this report, please contact me at (203)-285-5911 or Mr. Craig Stewart at (203)-285-2294. Sincerely, Combustion Engineering, Inc.
/
l Daniel Walker Staff Engineer
,V.ERIFICAT!ON STATUS: COMPLETf i n.su r uuemen, mar,u 0edewuiligCrorMWs1 # 9 of 0Wl01.
@T 21.% MarA o w a:nw D.x P A d d L i h m iaa,- n.., woe.. <
. . _ . ~ _ _ - ..
Attachment I to S-MECH 93 071 Page 4 of 5
,3 . ... . ..
ww u ,annh ccm, :, w, W;..%,,.. 4G:4ek<< rv. m 6 m ,n o,r i9m r 8"ra.naa
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L
- IMPACT AND/OR FRACTURE TESTS .
vrw. r vaums trw.*r vAuses .' ( _ wn ~ar mm not cw . mar. ss., sez<,;r
-t* fl W -7* ,,c
-r# /f^
V'
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APPENDIX E SONGS UNIT 3: MCRs FOR BELTLINE MATERIALS
[icp:j.. METALLURGICAL HliSEARCil Allu DLVLLOlw H L vu' 6 gayg.;gg, p i .
.AATERIAL5 CERTIFICATION REPG . January 24, 1974 v(. CONTRACT NO. 72170 T'ERIAL SPCCIFICATIONf3 l'19 (n) x <*: m LOO,R L3i.llparu Steel C_o_i.ligr1y ,
J00 NO. A-90015-001 N,If5'NO. C0195-2 CODE NO. C-6002-1 t
,)
nk b'NI AL OC5CRIPTION 2 20-3/4 " X 109-5/l G" X 9-11/16". - Intermediate ShcIl ~ E&a Ot * 'l MILL CHEMICAL ANALY515 hy,1, __ c _pa t' s si m c, su c6 c, V
.003 gic'ch .22 1.35 .011 .013 .22 .50 .55 .0G 1 -< :v:n , .
4% .D'~! , MECHANICAL TESTS j' .y."i
~
ULTIMATE TEST YlELD ELCNG. REDUCitON
) T NO. GAUGE STREttGTit, Kil T Et45tt.E ST RENGTit, K51 IN 7"'r, OF ARE A ?;
- 9. . ,. . -;9 TEMPERATURE 'F M7C'-TA .505 R. T. 64.3 / ,
85.9 ' ., 28.0 # 66.5
,s i WC-TB
- .505 R. T. 63.2 / 84.6 26.5 / G4.0 a
i W} #:' . IMPACT AND/OR FRACTURE TESTS HDT UME T El.P. 'F l VALUES l TEMP.*F VALUE5 { ;bliarpy Drop Welahts
- g, ,. Pt/Lbs % Shear Mlls Lat Exo ,
acts
, -40 8 0 3 -20 1 F '
- i. - -40 7 0 . 2 -10 1 F 1 NF " -10*F E.-
<-40 7 n ? -
0 2 NF
+1U 1b 5 10 3
+10 J 3 21 5 13 -
,i M r,
5.1.L_ 1 8_ _. _. , 5
-. / +40 _274F .___1_0 15 27 J' +40 26 d 10 17 Ft/Lbs % Shear MilsLatExp '%
,.j,j g 31 / .__1.0 - _
21
+100 102 70 65
./ l xv: +60 33 15 25
. I'!J +60 34 15 25 +100 104 70 61 < ,
E i i6. 0_..
+80 357..
50 1520
. . 24 y, 39
, +,LO O_
+160 126 96 nn - nt ' ' _
100 81
$7W 52 /
+80 25 40 / +160 132 100,, / 84 38 /
@p${
{ +80 50 / 20 +160 135 100 83 MW, -
.p N?;@, ADL': TION AL DATA INCLUDING ltEAT TREATMENT:
'k' .',. f(c) 1600*F
- 25'F 4 hours. Water quenched.
KX: 1225 *F i 25 P 4 hours. . h[- .(b) {c) 1l150*F *25 *F '4'O hours furnace cooled to G00*F. .
"lho impacts were taken .nar 1 to the major rolling direction of the plato at the h{j' 'l/lT level and notched perpendicular to the plate surfacc.
pp # 1 Th.1 dropwc!0h ts were tchen parallel to the major rollirig direction. Testing was donc In accordance with M6P Specification N-5.5.2.11(b) Add.1 (a). J' Tenslles were tchen transverso to rolling direction.
'.}ro.c.7:70 gg ~4 Ve l'eeIby certily iliet the fue golag dote is o true copy of the date furnished vi by t'io paedwclag enill, or dote eesulling leo,n tests per-p H D1nwIddIo <
j y gy ,,,a i,,i,, c.,,6 ,,,i ,, m ,,ii ,,,i,,i t ,t,,,,,,,,, V
- f. R.E. Srnith 'g
(, Jc} g.['h 'S , R . 14 w! S hp@h/ couoUnion EnGinEEniNG. iNC. s "J jh)rj R.C. Lorents, Jr. V g/ j . M . Arliold
. nor Doct:mber 19, 1973 , , _ , _ _
~
D. IC Mons COMilV5 TION EtIGillEERING. lilC. Revision # 1
, METALLU ICAL RF.5EARCll AND DEVEL0l'u T DEPT January 24, 1974 p MATERIALS CERTIFICATION REPORT
~
. 6%1EnlAL SPECIFICATION,f 3 fl 9 (a) .
CONTRACT NO._ 72170 l YENDOR _ [Aih. pig._ste el _Q,p_mjp_n,y JOD NO., A-90015 -001 HEAT NO. C9195-2 ' CODE NO. C-G002-1 MATERI AL DESC:'FalON 220-3/4" v 109-5/l G" X 9-11/10" Intermedlote Shel_1 MILL CHEMICAL ANALYSIS
.tIEf _ e . s .. r- 5 u ne r, u. ci, e,, y
,g,he ck .72 1.35 .011 .013 .22 50 .55 .06 .003 MECHANICAL TESTS itsi No. CAUCg TEST W LD Yg htg (LONG. RtDUC110N iturtRAtunt er sintHcTH.K$1 STRtt4GTH, Kil, IN 2"4 /07AR[A q i
~
WC-TA _ _ .505 R. T. 64.3 */ 85.9 s// 28.0 O 66.5 WC-TB .505 R. T. 63.2 _/ 84.6 / 2 6. 5 /- 64.0 IMPACT AND/OR FRACTURE TESTS Typt T FMP. 'F l vat. tit s _l TEMP.*F val.Uf$ NOT Charpy Ft/Lbs EShear, Mils Iat Exo Drop Welohts - Impacts -40 0' -30
~-
-40 7
0 S
-20 1 F [ ,
6 4 1 F 1 NF -20*F l /-40 .._S__ 0 4 -10 2 NP - 9 +10 29 _..'0l ~ 2 F .
+10 23 10 17 .
, + 18 . . 5.._ _ l.L p,pf c 34 15 21
+40
~14.0~
27 24 10 _S._ 19 17 Ft/Lbs % Shear MilstatExn [
+80 "43 25 37~ +160 84 80 62 '
1 -
+80 55 30 45 +160 79 80 - 60 l +80. 5 6__ in +160 79
4100 25 - 37 41_Y. T2T2- TOT-~ _.lLO._ 100 __
74 .6'L '
+100 s50 52 / /.' 25 40// +212 99 100 72
+)00 59 / 30 45 j
+212 95 100 j 70 AD0litor4 AL DAT A INCLUoING llE AT TRE ATM(HT:
(a) 1G00*F
- 25*F 4 hours. Water quenched.
(b) 1225*F
- 25'f 4 hours.
(c) 1150*F
- 25'r 40 hours furnaco cooled to 600*F.
s The impacts were taken tr,ansverse to the major rolling direction of the plate at the
)/4T level and notched perpendicular to the plate surface.
Tbc dropweights and tensiles were token transverse to the major rolling direction. Testing was done In accordance with M&P Specificotton N-5.5.2.ll(b) Add.1 (o).
, t... t-mo
, we beeley teetliv 8%i 16 fweg.1*g Jose in a teve serv of 14 dere Iweal 4J vs by al., peedvslag mill, se dele re soleles Item eeers p.e.
ll. Dinwiddic ., 4 io .w c .i.viii u.i.it.,pe.t L.1,.,.i.,v. g h Count 47aott it CitittRINC. ItIC. f . R.F.. Lorentz, Jr. g j/ J . M , 'Arn old oAir __ __. December 19, 1973 i St uc -%q , l
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B.11. Mons COMBUSTION ENGttlEERING tilC. gavision p 3 s l.lETALLO..,1 CAL' RESEARCH AND DEVELOPk . iT DEPT January 24, 1974 U . MATERIALS CERT'lFICATl0tl REPORT 72170
. M~ATERIAL $PECITICATION l'3 F19 (3) ', CCNTRACT t:0.
VEi: DOR I,ithenn Stoct Company JOP NO. A-9 f:015 -003
~
- HEAT NO. CD210-2 CODE NO. C-GCO2-2 MATERI AL DESCRIPTIO:l 220-3/4" X 109-5/l G" X 9-11/16" Intermedlare Shell u.lLL CHEMICAL ANALYSIS l
e I e s si c, e, cs c., y m er _ re. tii Chcct .24 1.27 l . 010 .013 .24- .58 -
'55'
. .04 .003 MECHANICAL TESTS ULTil. TAT E TEST YIELD TENitLE CLCNG. REDUCT0:1 TEST I;O* CAUCE TEMPERATUtE *7 STRENGTH, K31 STREt;GT tt. K51 til ?"% OF AREA t:
/ # 2G.0 /
WS-TA ,,_ 505 R . T. 66.8 89.4 .- 6 (.,j__ WS-TB .505 H. T. 68.3 ./ 90.8 / 26.0 / 65.8 fMPACT ann /OR FRACTURE TESTS Tyre TEia.'Fl vAtuEs TEus.*F VALL'!S l t:0T Charpy Ft/Lb % Shear MilstatExp Drop Welchts
.. Impa ct s . -40 7 0' 3 -20 1 F / -10*F
-40 9 0 5 -10 1 NF 7 F. "~
-40 R 0 A 0 2 Ir k ,+10 16 5 14 3 *
- +10 32 10 24 T .K '
4
,+10 31 10 - -tf 3 l
- sf
*j
+40 f'
4
~2h m.4 0 , _
hi Ftg % Shear MilstatExp W 50 50 .- -25 ~ 37' +1GO 125 95 80 .
- +50 450 57)/
59 30
'n 39 an _
+160 grn 124 1 27 95 95 82
>g
+100 88 60 60 +212 334 100 85*
+100 108 70 75 +212 125 100 -
80
+100 70 50 54 +212 128 100 f/ -
81
-l/ .
AD0fflori AL DATA INCLU3:::3 llEAT TRf ATv!NT: (a) 1600*F
- 25*F 4 hours. Water quenched.
(b) 1225'F *25'F [y :. / - p" s l (c) 1150*F
- 25*F[4 0 hours furnace hours. cooled to G00*F.
~
N\ ' The impacts were taken parallel /o the t major rolling direction of the plate tit the l 1/4T level and notched perpendicular to the plate surfacc. . The dropwcights were taken parallel to the moJor rolling direction. - - Testing was done in accordance with M6P Specification N-5.5.2.11(b) Add.1 (a). i Tcnstles were taken transverse to rolling direction. l
' F. E-2120
** b5 7" ir iksi ih tu.,.t+2 4i. I, . ... u,y .: in 4 cc: p. Webb ' 'lj
*k '# ' *3 ' ' . d
11* Dinwid:lle ."*'.'J
- f. s n c'.'.'w' '.'ii "u.uu,",,m.1 L.'w'm'das l'a int.
I t- 4 i ,,,,,y. i l
. R.E. Smith of 4i couausTics Es,cwEEnisc, inc.
S.R. Irwis % 's R.E. Lorentz, Jr. [^) v
' nY_ * .Nl. & t 9 J. M . Arnold D AT ,- Tanuary 7,1974
. d g _5s -
t
. . . ~.. . . , . . . . - ~ _ - JUN-11-199"4 13:31 FROM ABB/CE Chattanooga TO 912032855669
- u. n. r< sues P.06/16 aw e 4 w s ,r 4 METALLU..d? -
RE5EARCH AND DEVELOPM_.('OEPT January 24, 1974
. MATERIALS CERTIFICATION REPORT MATERIAL SPECIFICATION P3 F19_ (a) CONTRACT ND. 72170 __
VENDOR Lukens Steel Company
.* JOB NO. A-98015-003 C9218-2 HEAT NO.
CODE NO. C-6802-2 MATERI AL DESCRIPTION 2 2 0-3/4 " X 109-5/16" X 9-11/16" Interinediate Shell
~:
MILL CHEMICAL ANALYSIS TYPE r M, P 5 5t Ni Cr Me Cb Cu V Q eck .24 1.27i .010 .013 .24 .58 .55 .04
.003 MECHANICAL TESTS TEST
] 1 TEST NO. GAUGE YlELD E LE ELONG. REDUCTl01
, , TEMPERATURE *F STRENGTH,K5! STRENGTH,KS!
, 1N 2"% , e OF AREA
- WS-TA .505 R. T. 66.8 V/ 89.4 [ 26.0
/ 66.5 WS-TB .505 R . T. 68.3 / 90.8 2 6 . 0 65i8 '
IMPACT AND/OR FRACTURE _ TESTS _ TYPE TE up.
- F VALUE5 TEMP.
- F VALUES HDT Charpy Pt/Lb % Shear MilsIatExp Drop Weights
- . Impacts /
-40 9 0 4 -20 1F
-40 6 0
-20*F '
3 -10 2 NF
-40 8 0 4 0 1 NF V +10 26 10 19
+10
-) +10 14 28 10 5 11 24 Ft/Lb % Shear MilslatExp V +40 32 15 26. +100 66 40
+40 50 40 20 30 +100 27 50 59
+40 52 25 37 +100 69 40 54
+60 44 25 34 +160 114 90 77
+60 52 30 36 +160 110 90 75
+60 54 30 37 +160 106 90 75
+70 55/ 30 38 ' +212 117 100 j 80
+70 57/ 35 3 9./
+70 65/ 40 45 /
+212
+212 116 113 100 100 / 82 79 l
ADolTION AL DATA INCLUDING HEAT TREATMENT: (a) 1600*F a 25 F 4 hours. Water quenched. - (b) 1225'F *p"F 4 hours. (c) 1150*F E25'T 40 hours furnace cooled to 600*F.
/
The impacts were taken transverse to the major rolling direction of the plate at the 1/4T level and notched perpendicular to the plate surface. - The dropweights and tensiles were taken transverse to the major rolling direction. Testing was done in accordance with M&P Specification N-5.5.2.11(b) Add.1 (a). Form E-2170
*p We leereby certify thol the foregolag Jote le e Itpe copy of the e le
/ H. Dinwiddle R.E. Smith e
/g 6
I furfilshed us by the prodwelen mill, or 4000 tesultleg from fests of-so,ma in the ce,,s.,ti , u.ieno,, ice: tc6,,,,,,,. g g 'ir COM8U5 TION hlGINEEAls C.
~
R. E . Lore ntz , Jr . j p j p , 1.u . arnole
- _. - ,._~ ~ ~- -. . . - . METALLURGICAL RESEARCll AND DEvCLOPurHT DEPT D* R
- Mor.s RCVI5lon 0 l
,, .AATERIAL5 CERTIFICATI0tt REPG..'. January 24, 1974 l J p MATERIAL ST'ECIFICATl0N,{'3 T19 (a) CONTRACT NO. 72170 l l
VENDOR 1,u)irnGtect Corngany. . JOB NO. A-90015-005 HEAT No. C0195-1 CODE No. C-G802-3 [ MATERI AL OESCRIPTION 2 2 0-3/4"X 109-5/l G" X 9-I I/l G" Intermediate Shelll l MILL CllEMICAL ANALY515 J yrg_, _c ur P 5 S'
- C' "' e6 c., V gheck .23 1.37 .011 .012 .22 .57 .50 .0G .003 MECllANICAL TESTS ULTluAT C 1[5T No. CAUCE 1EST TIElo TCHtu.E E L OHC. RED W 10N 1(kteERATURf 'F STREttCTH. K51 ST R EttCT et. Kit IH 2'* 6 or AR( A T WT-TA .505 R . T. 67.8 #
9 0.1 26.5 65.0 _WT-TD .505 R . T. 68.3 / 89.1 / 26.5 / 64.5 IMPACT ANDiOR FRACTURE TESTS Tvrf f t er. 'F I VALUF5 lTCup.'F YALUES #80 7 Charpy Ft/Lbs % Shear Mils Tat Exn Drop Wolohts impacts -40 7 0' 3 -10 1 F /
-40 0*r 8 0 4 0 1 F
.-40 ,
6 0 3 - ,+10 2 NF
.F 10 21 5 14
+10 16 5 11 -
'+_10 . . 2 3 _.10-----.-17 .
+40 47 ' 20 34
)- +40 35/ 15 27 ;'t/Lbs % Shear MllstatExo
. +40 _
28 __1Q_ . . 2 0. .. .
+60 39 -
15 30 +100 103 70 72
+60 37 15 27 +100 100 60 . 68 *
,460. .60 30 . 44 .
11.00. .9 8._. - 6 01 6 9.- -- .
+80 74/ 60 55 ' +160 128 100 83 480 71 / 60 55 / +160 130 100 84
+80 80 60 50 / +160 120 100/ 78 ADolTIOHAL DATA INCLUotNG HEAT TREATMENT:
(a) 1600*r i 25'r 4 hours. Water quenched. (b) 1225'r
- 25'T 4 hours. *
(c) l'150*r A 25'r 40 hours furnace cooled to 600*F. . The impacts were taken Parallel to the major rolling dlrcetion of the plate at the 1/4T level and notched perpendicular to the ploto surface. , The dropwel0h ts were taken parallcl to the major rollin0 direction. Testing was donc in accordance with M6P Speelflection N-5.5.2.11(b) Add.1 (a). Tenciles taken transverse to rolling direction.
. F.e. E-2120 cc: P'. Webb ' d ****"**d*'*
***"'""'''''*",.".n'"i,,'s..,',.'orH,s,.'...,...
r .t.k.6. L, sk. ,. 4 i I! D!nwIddIc to 4i.eh.c 6..H u..n sic.it.6.....,. R.E. Smith / . S.R. Lewis k'P C0"'*51 '0" E" '"lC"*0 *C' R.E. Lorents, Jr. 3 jh
' J. M . Arnold 6C E - ( DAtt December 19, 1973 e *
. 8
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- n. R. Mons HETALLU' 'ICAL RESEARCil ANI) DEVELOl'A 'T DEPT R': vision # 1 January 24, 1974
.} MTERIAL 5PECIFICATION,_P3 Pl'1 fa)
MATERIALS CERTIFICATI0tt REPORT CONTRACT NJ _72170 VENDOR (tdr.tyLf.t0Cl C.omjlgn) - JOG NO. A-90015-005 HEAT NO. C9105-1 CODE NO. C-G002-3 MATERI AL DE5CRIPilON _ 270-3/4 X 109-5/l G X 9-11/1 G" Intermediate ShcIl Mit.L CHEMICAL ANALYSIS Jyr[__ _C __ __n. e t si He e, u, c6 c, V gcck .23 1.37 .011 . 012' l .22 .57 .50 .06 .003 MECHANICAL TESTS ULiikMT E 1(1T NO. CAUCE TE1T YlC LO TCHstL F. (LordG. RC OUC TION T[Mf'[RATURE 'F STRCidGill, K11 $1 R t idGill. Kil . IN 7"". Or A n t A ". WT-TA .505 90.1 / R. T. 67.8 ./ 26.5 / 65.0 WT-TB .505 R . T. 68.3 / 89.1 / 26.5 / 64.5 (MPACT AND/OR FRACTURE TESTS Tyrc trap . rl vAtut s lTrup.*F VALUss NOT Charpy Ft/lbs % Shear, Mils Lit Expl Droo Welc1 hts / Impacts -40 0' -10
-40
-40 7
9 8 0 n
- 4 3
5 0 1 F V 2 NF - i.- '+10 26 10 20 *
+10 26 10
- 20
_ +_ 10 15 5 11
/ +40 37' 15 27 '
W n8 Jt? H ll
. +60 35 49 15 25 26 34 Ft/Lbs % Shear MilstatExp r[' f.
b ~h N h~~~~~ +160 100 90 71
+80 52 h 25 e0y s +160 95 90 69
. +80 6 0._ 4.0 - 4 6 __ +160 .. .S 4 _ ._.9.0.. . 67
+100 79 60 60 .+21'2 106 100 76 4100 70 50 54
+100 63 40
+212 109 100 y 78 '/
46 +212- 101 100 72 ,j k / ADolilCH AL DATA IHOLUDING lt(AT 1RE ATMENT 4" (a) 1600*r
- 25'r 4 hours. Water quenched. O (b) 1225'T
- 25*r 4 hours.
(c) F150*F
- 25'r 40 hours furnace cooled to 600*F.
/*
The impacts were taken transverse to the rnajor rolling dlrcetion of the plate at the 1/4T level and notched perpendicular to the p* ate surfacc. The dropweights and tonsllcs were taken transverse to the major rolling direction. Testing was donc in accordance with M6P Speelficotton N-5.5.2.11(b) Add.1 (a). r t-217o cc: P'. Wcbb ' d 1I. D1nwIddIc
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s .i k J . 6, ik. e.. <.,c% ..s ti. ., 4... .. .. .i., r
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R.E. Smith f S.R. Irwis /, counustioN EHciNttniNc INc R.E. Lorentz, Jr. hp # or ./- / , , ,, c; W / w r ,/
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/ oArg
[ J.M. Arnold December 19, 1973 bC Q _ ~~
Jt.N-11-1992 13:36 FROM ABB/CE Chattc.neoea TO 912032855669 i P.13/16 9 N ' M""" METALLURG % Rl!5tiARCll AtID DEVEL0htEl' :DLPT MATERIAL 5 CERTIFICATION REPORT
)MA TC Rf AL SPECIFICA flON_f_1.F1.9 (a)_,,._ _ _ ,
CONTRACT NO. 72170 , vCNDon , ., __ Lukens Ste_,el Company __ JOB No. A98016-044 tilAT NO. C9220-1 -
- , CODE NO. ,_ C-6802-4 _
MATrRI AL DC',CRIPTION 220-3/4"X 109-5/16"X 9-11/16 Lower Shell (Test Plate "B'1 MILL CHEMICAL ANALY',15
.I Yrt. . ._ .C_.__ _Ea_ . 5 'l N' e, u. cs c., y I Chock .21 1.32 .011 .013 .28 ._5 8 .52 .05 .003 MECHANICAL TESTS
}
Test No. GAUCE TEST YlELD ENS E ELONG. RE DUCTION TEMPERATURE *F STRENGTH, KS! STRENGTit, K$l IN 2"':; 0F AREA % TE-TA .505 R. T. 69.3 // 90.3 / , 27.5 / , 66.9 ~ TE-TB .505 R. T. 70.4 / 91.3 / 26.0 / 66.1
~
(MPACT AND/OR FRACTURE TESTS e TYPE TEMP,*F val _UE S TEMP.'F VALUES ' NDT Charpy Ft/Lbs % Shear M11sLatExp Drop Weights / I _ Impacts -40 9 Of 4 -30 1 F' -30*F
-40 10 0 5 -20 2 NF#
40 11 0 5 7 ,
/ +10 31 10 20 l ") +10 37 15 25 "
- +10 21 5 14 Pt/Lbs % Shear M11si.atDer
,+4 0 47 / 20 38 +100 91 50 63
< +40 25 / 10 19 +100 113 70 72
+40 48/ 25 38 +100 112 70 .74
+50 43 20 31 +160 135 95 82
+50 52 25 37 +160 133 95 82
+50 54 25 37 +160 141 95 85
+60 51 25 39 +212 140 100 j 82
+60 68 35 47 : +212 140 100 84
+60 63 30 44 +212 142 100 80
~
ADDITION AL DATA INCLVOING HEAT TREATMENT: (a) 1600*P
- 25'F 4 hours. Water Quenched. (Twice)
(b) 1225'F
- 25*F 4 hours. (Twice) [
(c) 1150*F AT5'F 40 hours furnace cooled to 600 F. J [V The impacts were taken pardel to the major rolling direction of the plate at the 1/4 level and notched perpendicular to the plate surface. The dropweights were taken parallel to the major rolling direction and the tensiles were taken transverse to the major rolling direction. Testing was done in accordance with M 6 P Specification N-5.5.2.11 (b) Add.1 (a) r.,m E.2tm and Shop Order A98016 Supplement No.10. ' we h...ty c.itify tho' ike for.solas de'. Is e tev. ce9r .8 the d.ti
-)cc:P. Webb '""'
- d b ' ' h ' P' *d *8 '' " *' d*' ' '" "l""8 h *"' '"' ' P' fe,vand in the Combvillon Metellwgicol Lebmetery.
T. U. Marston couaUsTiotl ENO NEERING, INC. S. B. Lowls R. E. Lorontz, Jr . ny jp, _ J . M . Arnold
. . . . . cnmensn , r. 1nu
- s. -
b
- II* "
- j.tA ll.lilf.l.S (.*l.lilll'llM llO!! I?!'l'UIE l' g s ul l.ltlA t SPI Cil ICA liit:1 P.1 l't 9 (.il CO:411:ACT 110. - - 72 r% i
.170 _ _ . , . vttipott ....= Lukens Steel Com;)any JOll NO. A90010-Oi4 ntA T (40 -
C9220-1 Conc i:0. C-G002-4 t.611 illot. Ot5Ct:IP11N r-_-1 2 2 0-3 /4" X 109-5/16" r 9- 11 /1.6 "-. Lowc r S.h._c.Il (T.e s..t..P 1.tll l. Clll f.'.lC Al. #' < l '- lirt , C . . t if, ,, t' t as ne r. ; . , ,i _,,, , ,,r s. r- ,,,,,,_V 21 ,_ l.32 fl..s 4:
.0111 013 .20
.50 .52 .05 .003
=
_ nl: Cit ANIC A L 11. LT S. TC5T ut.t a.w t t-itst #:o. c a.vi .t Y8!LD Trvnl C L C#'G* f DL' "0;' 1 rt'r1 gat tN! 'r 51R(t: Oles. Es8 51kLt: Gin e.>l 1:4 2"*; cf A r( A *. TE-TA _,_ .505 R. T. 69.3 / 9 0. 3 /', 2 7. 5 ./ ,65.9 T r-T!) .505 It . T. 70.4 / 91.3 / 26.0 4 66.1 luPACT A t:0,04 PACTUM TESTS j tyrt tr e..n. 91 vai.r5 ITcun.*rl vAuffs I scr- l Charpy rt/t.b !".Shr.nr Mils t.a tD:n impcets -40 .Droo wciohts, s 10 0' 6 -30 F'
-40 1
-30*T 14 'O 8 -20 2 Nr # .
-40 10 0_ 6 .
/
+10 ~'i'5 11, 18
- Ft/Lbs %Shaar Mils t.atr:<e -
+10 28 10 20 +100 104, 60 65
+10 19 5 2 13. +100 69 40- g,
- +40 35 20 30 .
+100 _. . 7. 0. . .. . 4.0 52 g 54 x
_ +40 39 20 32 +16F 124, 95 80 6 .
+40 D' ~i6'0~
51
.48~~
25' 20 37 +160 112 90 71
~~3 5 +100 104 .._9 0.-.-
+60 54 25 39 +21) 118 ' 10 0 ', ,. 7_0 78
. . . .+ 6.0. . 49
. 34 +212 117 100 81
+70 7 6 ,,/ .2. 50 0 ... ~ 5 3 ,. . +212 115 10.0 77
+70 63 / 40 47/ -
- -' +
+70 59 35 44 /
Acasitt u.t. otrA LscLLc:::: nt At TRIAinist: l (a) 1000*r 125*T 4 hours. Water quenched.' (Twice) '^~ (b) 1225*r 25'r 4 hour::. (Twice) # p. l c 7f (c) 1150*r a 25 *T 40 hours l'urnace cooled to G00*F. ?- The impacts were teken trcnsverse to the rnajor rolling direction of the plate et the 1/4 T level and notched perpendicular to the plate surface. , 1 [ The dropweights and tenst!c: were taken transverse to the major rolling directjen. '
- Ter. tin') was donc in accordar.cc with M 6 P Specification H-5.5.2.11 (b) A:id.1 (a),
and Shop Order A900!G Supplernent No.10 f.- C-t a n . cet P. Wcbb sc.4.mLri.,ot,ikii% tuosu s a.. n .no.<o.. 6.tr. 1.ut.>.. d ,s t r iu ,,3 4.::y , m. u a ., . ,,in, #.... . o . ,.. .
!!. Dir.widdic l* d 8
- C* t < o iaa ui'* " * ) < 'I t
- t** *> r-T. U. Meir: ton S. ft. Iowl: co3 wn ,o.4 (4. aca.nc, u .
- 11. 1:. l.or en t 7. , Jr. -
g , ,, g ,/' 7f / Sep'erf J. M . Arr.old Sgg pag [ er 1 f., i f;74 0 9-4. Po e.
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- METALLURC IL RESEARCf.! AND DEVELOPMEP DEPT SC6 N3
, MATERIALS CERTIFICATION REPORT-MATERIAL SPECIFICATION _ P3 F19 (a) -
CONTRACT NO.- 72170 VENDOR _ Lukens Steel Company
~ JOB NO. A-98016-009
, etEAT NO. C9218-1 CODE NO. C-6802-5 MATERI AL DESCRIPTION 220-3/4"X 109-5/16" X 9-11/16"
. Lower Shell MILL CHEMICAL ANALYSIS TYPF C W P $ St Nt C, Mo Cb Cu V Q eck .24 1.30 .012 .013 .24' .52 .53 .04
.003 MECHANICAL TESTS TEST NO. TEST ULTIMATE GAUGE YlELD ELONG.
TEN 5tLE RE DUCTION TEMPERATURE *F STRENGTH,K51 STRENGTH,K$l IN 2**4 OF AREA n AF-TA .505 R. T. 66.4 / AP-TB .505 88.3 # 26.0 "
' 64.8 R. T. 66.3 / 88.1 - 26.0 / 64.6 IMPACT AND/OR FRACTURE TESTS TYPE TEMP.*FI VALUE5 TEMP.
- F VALUES NOT Charpy Pt/Lb % Shear MilstatExp Impacts Drop Weights
-40 10 Of 4 -20 1 F i
. -40 10 0 4 -10 ,1 F
-40 10 1 NF -10*F 0 . 5 0 2 NF 0 22 10 16 '
+10 15 5 10 Ft/Lb % Shear MilsLatExp g . 4 10 16 5 10
+100 81 50 55
. 4,40 25 /' 10 18 +100 97 60 67
/+4 0 41 20 2'8 +100
~
84 50 60 440 32 15 20 +160 133 100 81
+60 69 35 44 +160, .
+60 47 25 33 132 100' - 82
+60 53 30 +.18/ 127 100# 78 35 +212 146 100,
+70* 81 .- 35 54 / 83 '
+0 76 30 +212 133 100 77 50 /
+70 63 / 35 42 / +212 147 100 82 AD0! TION AL DATA INCLUDING HEAT TREATMENT:
(a) 1600*F
- 25 *F 4 hours. Water quenched.
(b) 1225*F 25 *F 4 hours. ' (c) 1150*F t 25 F 40 hours furnace t./ cooled to 600*F. ! The impacts were taken parallel to the major rolling direction of the plate at the
)
1/4 T level and notched perpendicular to the plate surface. l The dropweights were taken parallel ; and the tensiles were taken transverse to i 1 the major rolling direction. Testing was done in accordance with M & P Specifica-tion N-5.5.2.11(b) Add.1 (a) and Shop Order A-98016 Supplement No.10. cc: P. Webb We hereby certify that the foregoing dato la e teve copy of the dote g H. Dinwiddle R. E. Smith -
~'I i nl.h.4 v'. by ihe ,,. swing wil. ., d.i. ,e.ultaan f<= te sti e.'-
lad la th. comboitton Mei.llurgical Leborofory. , S. R. Lewis . COMBUSTION ENGINEERING. INC. R. E. Lorentz, Jr. gg i I nave l1!is. Arnold h43rch ?? 107A
MATERIALS CERTIFICATION REPORT MTERIAL SPECIFICATION _ P3 F19 (a) CONTRACT NO. 72170 VENDOR _ Lukens Steel Company JOB NO. A-98016-009 HEAT NO. C9218-1 CODE NO. C-6802-5 MTERI AL DESCRIPTION 22 0-3/4" X 109-5/16" X 9-11/16" Lower Shell MILL CHEMICAL ANALYSIS' TYPE C Mn lP 5 St Ni Cr Mo Cb Cu V _Q_he ck .24 1.301 .012 .013 .24 .52 l
.53 .04 .003 MECHANICAL TESTS ULTIMATE TEST NO. GAUGE TEST YlE LD ELONG. REDUCTION TEN 5tLE TEMPERATURE 'F STRENGTH, K51 STRENGTH,KSI IN 2"4 0F A R E A *s AF-TA .505 R. T. 66.4 / , 88.3. ,.- 26.0 ' 64.8 AF-TB .505 R. T. 66.3 /
~
88.1. - 2 6 . 0 <- - 64.6 IMPACT AND/OR FRACTURE TESTS TYPE TEMP.'Fl VALUES TEMP.*F VALUES NOT Charpy Pt/Lb % Shear MilstatExp Drop Welghts
. impacts
-40 9 0/ 4 -10 1 F '
-40 10 0 v' 5 . 0 1 F 0F
'1 , - 0 __. 9 _.0 3 +10 2 NF
-+10 18 5- 12 0 27 10 20 Ft/Lbs % Shear MilsLatExp
--)
- O _15 5 li +100 66 30 47
, 0 34 15 23 ~ +100 70 35 49 i
, 3 40 4 40 34 35 15 15 24 25~ ~ ~ '
+100
' +1'60- - 118 79~
100 40 .. 5.6 . 78
.[ I f.Typ7
+60 39 15' ~ 26 +160 116 100 ~/5
+60 39 15 28 +160 _109. . 9 0.. /c F
. + 6.0 ,~ ~. . 3 8 .. 27 +212 119 100 / .65 78
+70 65/ ~3015_. .. '43' F +212 110 100/ 72
+70 5 7 30 40 /.
470 51 / 25 37 p - +212 117 100 / 74 AD0lTION AL DATA INCLUDING HEAT TREATMENT: (a) 1600 F
- 25 F 4 hours. Water quenched.
(b) 1225 P 253F. 4 hours . - (c) 1150*Fi 5 *F 40 hours furna,,ce cooled to 600*F. The impacts were taken transverse to the major rolling direction of'the plate at the 1/4 T leve'l and notched perpendicular to the plate surface. The dropweights were taken transverse ; and the tensiles were taken transverse to the major rolling direction. Testing was done in accordance with M & P Specifica-tion N-5.5.2.11(b) Add.1 (a) and Shop Order A-98016 Supplement No. '10. Form E-2120 We hereby certily that the foregola; doto l's o true copy el the dato Cc: P. Webb fuished us by the producing mm, or dato reividng fro <n tests per-
- 11. D1nwIddIe
/ ] R. E. Smith Scw - ._(
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COMBUSTION ENGINEE RING, INC. S. R. Lewis . R. E. Lorentz, Jr. g [ 'J. M. Arnold' oATE March 27,1974 __, e, e a cn u) a_
JLN-11-1992 13:33 FROM ABB/CE Chattcnooga TO 912032855669 P.09/16
, . 31 + H M"3" MI,1 AI,1,llRC. AI, RI:$1 ARLil AND DEVl!I.Ol'Mt.P *, DI.'I'T hATURIAL5 CERTIFICATION REPOR1 T MA T C RIAI SI'ECll ICAll0N P3 F19 (a) CONTRACT NO. 72_170 _
VENDOR . Lukens Steel Company JOB NO. A98016-046 Hi AI N0.........._._ B3388-1 _ . CODE No. C-6802-6 u41rn AL rWr.c h'll': DN , ,,,, 2 20-3/4" X 109-5/16" X 9-11/16" Lower S,hgl,,(To,st ,P1, ate,,','D MILL CHUMICAL ANALYSIS
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- c. heck. .22 1.44 .011 .014 .27 .65 J .53 .06 ,,_,,J .00
~~ ~ ~ ~ ~~~~ '
MECHANICAL TESTS ULTIAWT E TEST NO. GAUGC TEST YlE LD TEN $1LE ELONG. REDUCT* 4 TEMPERATURE 'F STRENG1H.K$l STRENGTH.K51 IN 2**'t OF ARE/ !;
.505 R. T. ' '
TF-TA 56.0 *$ 80.8 - 29.0 ' 60. TF-TB .505 R. T. 56.4 / 81.2 .' 31.0 ' 62. IMPACT AND/OR FRACTURE TESTS / TYPE TE MP. 'F VALUES TEMP.'F VALUES NDI Charpy Ft/Lbs % Shear MilsLatExo Drop Welchts ,,. Impacts -40 21 5' 13 -40 1F -3'O F ,
-40 12 0 7 -30 1 NF 1 F'
-40 15 0 8 -20 2 NF/ i j +10 40 20. 29
" } +10
+10 ,
38 29 20 15 28 19 Ft/Lbs *4 Shear MilstatExt
'+40 50- +160 113 95 78 25 ,38
+40 +160 123 95 81 i 50 g. 25 40
+40 45 20
+160 117 95 80 I
+50 66 30 32 46
+212 113 100 / '77 '
+50 53
+212 115 100 78 25 37
+212 140 100 81
+50 61 30 44
+100 76 40 56
+.10 0 74 40 5 3 .'
&100 73 40 57 l ADDITION AL DATA i:4CLUDING HEAT TREATMENT:
(a) 1600*F 25 *F 4 hours. Water Quenched. (Twice) - i (b) 1225'r
- 25'FJ hours. (Twice) gf /'I (c) 1150*F
- 25'F 40 hours furnace cooled to 600*F. V, 5 \
/
The Imr acts were taken parallel to the major rolling direction of the plate et the 1 '4T ! level and notched perpendicular to the plate surface. ; The dropweights were taken parallel to the major rolling direction and the tensiler l were taken transverse to the major rolling direction. 1 Testing was done in accordanco with M 6 P Specifica,t.Lon N-5.5.2.11 (b) Add.1 'i) F.,va E-2120 and Shop Order A98010 Supplement No.10 ' w h.c.by c.nitr ih. th. In.e.ie, d i. i. . i,.. c.,y .# the lee.
,i cc: P. Webb '""b'd "' by th. ,wducing min. . d.i. n.uiong ime, ini re-
./ 1 a in ih. comt,vsit..i u.iottvrate.1 L bc.i.,y.
H. Dinwiddic T. U. Marston co'mUsTioH ENGINEERING. INC. S. R. Lowls ' R. C. Lorentz, Jr . riy - 4/ 4 a, -_
' 'J .' K1.' Arnold September I G.1974 I DAt t. i i
l a
D . II . El": 'i Mall:l lAl.'. t:l.In trirATIOli l'l:l'UN.I'
#dAll s::At. wi t.it f(A1 ort.p3,,r_1.i. (o) _
CO:ITI:ACT lip. 72170 7, Jolt 110. AO:1016-OiG
'y9 '
yL,,pm; Lukens Stect Company - fir.AT ric. . _ _n.33__08_ _1 . . - , ,
. CODC i:0.C- S n.0 2 - G ..- ._ --
s.tATI: :I Al. Dr!CI:ll'llt :: 220-3/4" X 100-5/1G" X 9 11v'1Ga 1,ower Shell (Tcst Pla:c "D'i
. _ . . . . _ . _ .M. i.!. t. O :t ".i.C. A I. ..A t: A1. Y_5_: 5. --
. rj; ., _,__@
S- . .* L.. I . .*.". ., ..f' "' , j ,,, ,, ,, _v
.I Ti'i . . C ... f ': _ . .8....
Chi.e t .22.il.44 .011 .014 .27 l .65 .53 _
.06 _ } ,, 00 ut! Cit Ar tir AI. 1 t Ft 5 v.' 1 >.s4 f f ifl1 Yif to irnm r (t esc. nr ou.i:c::
Itst ::o. cAuct it s.it:G a ii. cl 1:e r"; or Arct A . trurt u.ite:t er st at;:::si. rsi TF-TA a .505 R. T. 56.0 / 00.8 / 2 9 . 0 60.1
- TP-TB 503 L R.T. 5G.4 61.2 / 31.0 /i G2.2 IMPACT At:D.OR FRACTtlRE T ELTS l tyre i rur. *s i
. vAters lien.*F w ttcs kor' I Charpy Pt/I,b NSher.r f.4tisi.ntExn Droo Wele: hts '.d' l Imp::2:ts -40 10 0/ 5 -40 1 r ' -40*r
-30
-40 10 'O 4 2 Nre' '
- -40 8 0 4 .
~+10 23 10
/ 17 f
+10 28 10 ,
20 . 25 IB Pt/T,5d *t. Sheer MilstatEx: '\
+10 10 5,
' 'T40 34 15 W +100 50 30 42 /
g +40 43 20 .34 +100 65 50 51 Q
. 33 it 1 +100 59 40 46 f Q-*
.,14 0_.,
+70 50 25 39 ~~II'6F_ v6 95 . 72 I
+70 46 20 35
+160 90 90 69
+70 58 in 45 +160 03 90 65 M0 25 W 45 /
W
+212 90 92 100 '
100 70 71 57 /
+SO 30
^
+SO 53 / 25 41 / +212 92 100 70 A00lllOti Al,' OAT A i tr.tt'Dt'fG it! AT ti:CAf t.t! li (a) 1600*r
- 25'r 4 hours. Water quenched. (Twlec) ,\
'g b (b) 1225'T
- 25'r 4 hours. (Twice) \ l (c) ll50*r 25 *r 40 hours furnaceyoled to 600*T.
The impacts were taken transverse to the major rolling direction of the plato at the 1/4 T level and notched perpendiculer to the plate surface. The dropwc!ghts and tens!!cs were token tron: verse to the major rol,1jp0 direction. Testing was donc in accordance with M 6 P Spectilection N-5.5.2.11 (b) Add.1 (c). ;
.' and Shep Crder A00016 Supplemen: No.10. .
t.. t.:tn
- r. h e.4, c..iir, iwi it. ru . : i 3 s c. i, , . .. ..,, .r it. , ..
cc: P. Wcbb , pui i , ,,. t , ,s. , ,,, u i,3 ,,g ;, ,, ,,, , ,, , g ,., ; ,,,,, ,, ,, , , ,,,, i faa< d la i% C+.4 id H ei.% i.t t.w..i.. ,. l
!!. D!nwiddIe t T. U. Mart: ton coutur,1 ut (r:c:uttsan:.. iv ,.
fy S. R. l.cwl::
- R. E. I.orent:.. Jr. . ,
, /
'//J . 14. 'Ar n old DA1r Se. ptemba:r. I G.1974 . . . . . . . . - . -
,C-1iL ~ Q q *
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l l
. s l
c. l s . APPENDIX F ( SONGS, UNIT 3: UNIRRADIATED.Cvy DATA FOR PLATES AND WELDS 5 n h (-
Table F-1 Charpy V-Notch Test Results For Unit 3 Plate C6802-1 (TL), MCR Data ( SPEClosta itser tutRCf LAltRAL fBAC1 le illt 184PAtt Eur APPEAR (t) (ft lb1 tell) (1) 1 40.00 T.00 5.00 0.00 2 40.00 6.00 4.00 0.00 3 40.00 5.00 4.00 0.00 4 10.00 29.00 20.00 10.00 5 10.00 23.00 17.00 10.00 6 10.00 18.00 14.00 5.00 F 40.00 34.00 21.00 15.00 S 40.00 27.00 19.00 10.90 9 40.00 24.00 17.00 5.00 10 00.00 43.00 54.00 25.80 i 11 00.00 55.00 45.00 30.00 12 80.00 $6,00 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 to 160.00 79.00 60.00 80.00 1T 160.00 79.00 63.00 80.90 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 14.00 100.00 l i F-1
I Table F-2 Charpy V-Notch Test Results ( For Unit 3 Plate C6802-2 (TL), MCR Data l OPSCIMtti TEMP WWen0T IATRAAL FRACT l ID TEST IMPACT tRF APPEAR l (F) (ft-lb) (all) (t)
- 1 .40.00 9.00 4.00 0.00 2 40.00 6.00 3.00 0.00 3 -40.00 0.00 4.00 0.00 4 10.00 24.00 19.00 10.00 - S 10.00 14.00 11.00 S.00 8 10.00 20.00 24.00 10.00 7 40.00 32.00 26.00 15.00 0 40.00 40.00 30.00 20.00 9 40.00 S2.00 37.00 25.00 10 40.00 44.00 34.00 25.00 11 40.00 $2.00 34.00 30.00 12 60.00 $4.00 37.00 30.00 13 70.00 $$.00 30.00 30.00 14 70.00 $7.00 39.00 33.00 15 70.00 65.00 45.00 40.00 16 100.00 64.00 30.00 40.00 17 100.00 77.00 59.00 $0.00 le 100.00 69.00 $4.00 40.00 19 160.00 114.00 77.00 90.00 20 180.00 110.00 75.00 90.00 21 160.00 106.00 75.00 90.00 22 212.00 117.00 00.00 100.00 23 212.00 116.00 02.00 100.00 24 212.00 113.00 79.00 100.00 f
F-2 9
Table F-3 Charpy V-Notch Test Results For Unit 3 Plate C6802-3 (TL), MCR Data speelnew True twenCT 3.ATrnA1. FRACT ID Tr0T IMPACT DNP APPEAR trl tit-lbf (m!!) It) 1 -40.00 0.00 4.00 0.00 2 -40.00 7.00 3.00 0.00 2 40.00 9.00 S.00 0.00 4 10.00 24.00 20.00 10.00 5 30.00 26.00 20.00 10.00 4 20.00 15.00 11.00 S.00 7 40.00 37.00 27.00 1$.00 0 40.00 20.00 22.00 10.00 9 40.00 35.00
- 26.00 1$.00 10 40.00 35.00 26.00 15.00 11 60.00 49.00 24.00 25.00 f
12 60.00 25.00 20.00 20.00 12 00.00 $1.00 47.00 30.00 14 00.00 52.00 40.00 25.00 15 00.00 60.00 44.00 40.00 16 100.00 79.00 60.00 60.00 17 100.00 70.00 $4.00 S0.00 le 100.00 83.00 46.00 40.00 b 19 160.00 100.00 71.00 90.00 20 160.00 95.00 69.00 90.00 21 160.00 94.00 47.00 90.00 22 212.00 106.00 74.00 100.00 22 212.00 109.00 10.00 100.00 24 212.00 101.00 72.00 100.00 ( F-3 I I
.r Table F-4 Charpy V-Notch Test Results For Unit 3 Plate C6802-4 (TL), MCR Data
( l erselMan TEMP speecT 1AtenA1. rmACT In Test Impact tar APPEAR tri (ft-lbl (mil) - (t) 1 -4e.00 le.se 8.0e e.00 2 -40.00 14.ee 8.00 e.00 i* 3 -40.00 10.0e 4.00 e.00 l . 4 10.00 2$.se 10.00 19.0e S 10.00 20.00 20.00 10.00 8 10.00 19.00 13.00 S.Se 7 40.00 35.es 30.00 20.00 ; i e 40.00 39.ee 32.00 20.00 9 40.00 $1.00 37.00 25.00 I le 60.00 40.0e 35.00 20.00 11 60.00 $4.00 39.00 25.00 ( 12 40.00 49. ee 34.00 20.00 13 70.00 76.00 $3.00 S0.00 34 10.00 43.0e 4#.00 40.00 15 70.00 59.00 44.00 35.00 , 18 100.00 104.00 65.00 60.00 17 100.00 49.00 52.00 40.00 le 100.00 70.00 S4.00 40.00 19 160.00 124.00 00.00 93.00 20 160.00 112.00 71.00 90.00 21 160.00 104.04 10.00 90.00 22
- 212.00 110.00 10.00 100.00 23 312.00 181.00 31.00 100.00 24 212.00 185.00 17.00 100.00 F-4
Table F-5 Charpy V-Notch Test Results For Unit 3 Plate C6802-5 (TL), MCR Data { spectMEN TEMP t#BRCT LAftRAL F1 TACT
, ID Test InPACT tsp APPSAA IFl (ft-lb) (mill til 1 40.00 9.00 4.00 0.00 s 2 -40.00 10. 90 S.00 0.00 3 -40.00 0.se 3.00 0.00 4 10.00 10.00 12.00 S.00 S 10.00 27.90 20.00 10.00 4 10.00 15.00 11.00 5.00 7 40.00 24.00 23.00 15.00 h 0 40.00
]Nb
-99.90 24.00 15.00 Ylfff 9 40.00 35.00 25.00 15.00 10 40.00 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 GS.00 43.00 30.00 14 70.00 57.90 40.00 30.00 15 10.00 $1.00 37.00 25.00 16 100.00 46.00 47.00 30.00 17 100.00 70.00 49.00 35.00 le 100.00 79.90 $6.00 40.00 10 160.00 110.00 70.00 100.00 1
20 160.00 116.00 75.00 100.00 l l 21 160.00 109.00 45.00 90.00 23 212.00 139.00 70.00 100.00 23 212.00 110.00 72.00 100.00
, 24 212.00 117.00 74.00 100.00 I
F-5 1 l
r 4 i Table F-6 Charpy V-Notch Test Results For Unit 3 Plate C6802-6 (TL), MCR Data { SPECTME86 TEMP E580907 LATERAL PRACT
~
29 TEST IMPACT ERP APPEAA (F) (ft-lb) (m113 (t)
- 1 40.00 10.00 S.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 8 10.00 25.00 10.00 10.00 7 40.00 34.00 26.00 15.00 0 40.00 43.00 34.00 20.00 9 40.00 33.00 28.00 15.00 10 70.00 30.00 39.00 25.00 11 10.00 44.00 35.00 20.00 12 70.00 50.00 43.00 30.00 13 00.00 52.00 40.00 25.00 14 00.00 51.00 45.00 30.00 1S 00.00 $3.00 41.00 25.00 16 100.C0 S0.00 42.00 30.00
!? 200.00 45.00 51.00 $0.00 10 200.00 $9.00 46.00 40.00 19 140.00 94.00 72.00 95.00 20 160.00 90.00 69.00 90.00 21 160.00 93.00 65.00 90.00 .
22 212.00 90.00 70.00 100.00 23 212.00 92.00 11.00 100.00 24 212.00 92.00 10.00 100.00 I F-6
)
.t
. Table F-7 Charpy V-Notch Test Results For Unit 3 Weld Seam 9 203 (Heat #90069), WMC Data
(.. SPOC1 MEN TPMP BMtflCT IATEftAL PRAc"r
. ID TEST IMPACT BIP APPEAR (PI tit-1bf leill sti 1 -100.00 13.00 0.00 0.00 2 -100.00 0.00 4.00 0.00 3 -100.00 12.00 9.00 0.00 4 -80.00 24.00 , 15.00 S.00 S 00.00 43.00 31.00 20.00 4 -80.00 25.00 17.00 S.00 7 40.00 53.00 36.00 25.00 0 40.00 89.00 S0.00 40.00
( 9 -40.00 43.00 44.00 25.00 10 0.00 03.00 00.00 30.00 11 0.00 74.00 $2.00 40.00 12 0.00 97.00 47.00 40.00 13 40.00 120.00 02.00 90.00 . 14 40.00 110.00 00.00 90.00 15 40.00 125.00 02.00 100.00 16 100.00 119.00 70.00 100.00 17 100.00 117.00 10.00 100.00 le 100.00 124.00 03.00 100.00
, 19 160.00 123.00 02.00 100.00 20 160.00 121.00 01.00 100.00 21 160.00 133.00 02.00 100.00 f
F-7
2 Table F-8 Charpy V-Notch Test Results For Unit 3 Weld Scam 3-203 (Heat #88114), f*SAR Data WMC [h spectnew Trnr OwencT 3.mTenAt. rnacT 30 Tas? IneACT sur Arr0Aa (P) (ft-lb) (ell) (t) 1 304.00 13.00 1.00 0.00 2 104.00 11.00 6.00 0.00 3 -104.00 20.00 13.00 S.00 I . 4 400.00 29.00 22.00 10.00 5 =00.00 30.00 21.00 10.00 4 =00.00 24.00 13.00 10.00 7 40.00 110.00 86.00 40.00 0 40.00 76.00 40.00 40.00 9 40.00 114.00 40.00 80.00 I f 10 10.00 127.00 10.00 00.00 4 11 -10.00 115.00 64.00 10.00 j 12 30.00 117.00 40.00 70.00 13 10.00 136.00 70.00 00.00 14 10.00 151.00 01.00 100.00
),
15 10.00 154.00 04.00 100.00 la 50.00 174.00 04.00 100.00 1 17 $0.00 163.00 $$.00 300.00 le St.00 142.00 93.00 100.00 4 I F-8
~~ - , . , , , , , , - - - - - - . - . . , . . . .. .-a
Table F-9 Charpy V-Notch Test Results 4 For Unit 3 Plate C6802-1 (TL), CE Baseline Data
'\ .
1 I l
. erectnew Trwr twencY 1ATemm1. ramer ID TEST IMPACT REP APPEAR tr) (ft-lbi tulit sti 252 -40.00 12.00 12.00 e.00 '
22e e.00 14.00 12.00 10.00 26J e.00 22.00 24.00 l 0.00
. l 22P 40.00 10.00 17.00 10.00 260 40.00 52.80 43.00 20.00 22R 00.00 25.ee 25.00 20.00 i
262 se.00 S7.e6 S0.00 40.00 22Y 100.00 42.00 40.00 20.00 2SM 100.00 74.00 de.00 40.00 24T 100.00 08.00 65.00 $0.00 2SE 120.00 SS.00 72.00 30.00 267 120.00 104.00 00.00 00.00 i l 224 160.00 61.00 40.00 40.00 I 221 160.00 42.so se.go yo,oo 2$Y 160.00 112.00 e1.00 90.00 l 22P 210.00 96.00 74.00 90.00 j 2SS 210.00 109.00 e2.00 100.00 21R 250.00 00.00 71.00 100.00 22A 230.00 07.00 72.00 100.00 ( F-9
l i l Table F 10 Charpy V-?4tch Test Result For Unit 3 Plate C6802-1 (LT), CE Baseline Data ( I a OPECIMEW TEMP BWERCT LATWRAL FRACT ID TEST IMPACT ORP APPEAA (Pl (ft.th) ge113 (t) 151 0.00 6.50 S.00 0.00 148 40.00 15.00 13.00 10.00 - 137 40.00 18.00 15.00 10.00 11U 00.00 33.30 30.00 30.00 13H 00.00 39.30 34.00 30.00 14e 130.00 36.00 37.00 40.00 134 130.00 45.00 41.00 40.00 { 140 180.00 St.00 47.00 40.00 130 160.00 83.00 10.00 00.00 138 310.00 64.00 63.00 10.00 14T 310.00 96.00 01.00 00.00 11L 350.00 90.00 00.00 100.00 11C 250.00 93.00 07.00 100.00 a y l F-10
l
+
l [ Table F-11 Charpy V-Notch Test Results For Unit 3 Surveillance Weld, CE Baseline Data senCinew TrnP awency s.nTenAs, nac7 i 10 TEST IMPACT WIP APPEAR trl ift-lbl (e11) tel 31T -80.00 S.ee 5.00 0.00 37C -80.90 31.98 10.00 20.00 32C -40.00 17.00 10.00 30.00 3dM -40.00 34.00 31.00 30.00 34C S.00 34.00 34.00 30.00 34T 0.00 40.96 45.00 40.00 378 40.00 $8.00 S3.00 40.00 3A2 40.00 43.00 S4.00 40.00 { 3ST 00.04 73.90 83.00 00.00 34M 00.00 00.00 02.00 100.00 378 130.00 71.00 65.00 00.00 33R 120.00 04.00 79.00 90.00 116 180.00 44.90 67.00 70.00 344 140.00 97.90 90.00 100.00 32R 310.00 40.00 0$.00 90.00 3tc 310.00 97.90 04.00 90.00 4 35M 250.00 71.00 89.00 100.00 373 250.00 10.00 73.00 100.00 348 350.00 44.00 02.00 300.00 1 F-11
~ 1 Table F-12 Charpy V-Notch Test Results ( For Unit 3 Plate C6802-1 (LT), MCR Data Test Impact Lateral Fracture Temperature Energy Expansion Appearance J ('F) (f t-lbs) (mils) (% Shear)
-40 8 3 0 )
-40 7 2 0 ;
-40 7 2 0 10 16 10 5 10 21 13 5 10 27 18 10
)
40 40 27 15 ' 40 26 17 10 40 31 23 10 60 33 25 15 60 34 25 15 I 60 35 24 15 80 50 39 20 80 52 40 25 80 50 38 20 100 102 65 70 100 104 61 70 100 96 63 60 160 126 81 100 160 132 84 100 160 135 83 100 f F-12
Table F-13 Charpy V-Notch Test Results . '( For Unit 3 Weld Seam 9-203 (Heat #90144), WMC Data SPECIMEN TEMP ENERGY LAltRAL FRACT ID TEST IMPACT EMP APPEAR (F) (ft th) (mil) (%) 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 26.00 15.00
? 10.00 57.00 41.00 35.00 8 10.00 50.00 36.00 25.00 $- 9 10.00 53.00 40.00 30.00 to 60.00 82.00 60.00 80.00 11 60.00 81.00 60.00 80.00 12 60.00 76.00 54.00 80.00 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 92.00 77.00 100.00 18 160.00 93.00 72.00 100.00 r
f F-13
( APPENDIX G I, SONGS, UNIT 3: HAZ TEST RESULTS i 1 l l l i
)
( l l l l i l
a l CE Baseline Tests")
\
spectsem Taw susagY 1ATsRAL FRACT 19 Tsef twAcT Ese APPEAA (F) (ft-th) (all) (t) erL 0e.00 4.00 4.00 e.se ese .se.ee s.00 4.e0 e. 00 ear .ee.ee 30.e0 36.00 10.00 ; 434 .44.00 30.00 34.00 10.00 4SJ e.De 30.00 38.00 30.00 1 1 1 est e.es 44.e6 37.00 30.00 1 423 40.pe 33.00 34.00 30.00 42R 40.00 35.00 33.00 30.00 429 80.00 73.00 4e.00 00.00 454 90.0e 79.00 43.00 54.00
- k 471 130.00 42.00 41.00 40.e0 I l
475 120.00 50.00 49.00 70.00 4)C 160.00 61.00 82.00 00.00 438 140.00 of.00 73.00 90.00 46R 210.00 97.00 $7.00 70.00 444 310.00 105.00 13.00 100.00 46A 250.00 83.00 48.00 100.00 42T 194.00 ?$.00 50.00 100.00 467 350.00 90.00 00.00 1e0.00 m - l 1 (3-1
)
1
+ Westinghouse Capsule 9723 W SPEC!pWN TEMP BWBRGY 1ATBRAL PRACT CAAAPT IMAD 10 TEST Il#ACT BIP APPSAR F1#ENCE TEMP. (F1 (ft-1b1 (alli ($1 (n/sm3) (F1 441 75.00 0.00 0.00 S.00 0.00B+10 550.00 43L 50.00 te.00 16.00 15.00 0.008+10 SSO.00 tSC 30.00 3.00 4.00 S.00 0.00B+10 5S0.00 43P 0.00 34.00 33.00 39.00 0.00E+10 550.00 444 39.00 3S.00 37.00 45.00 0.008+10 $50.00 41C 40.00 33.00 33.00 50.00 0.00E+10 S50.00 a 478 95.00 43.00 44.00 75.00 0.005+10 950.00 { 447 138.00 41.00 30.00 10.00 0.008+10 $$0.00 4SM 145.00 45.00 44.G4 00.00 0.008+10 950.00 437 16S.00 83.00 61.00 100.00 0.00E*10 550.00 esp 200.00 04.00 40.00 100.00 0.00R+10 $$0.00 434 350.00 ?$.00 65.00 100.00 0.000610 550.00 ( O-2 l l e-
l 1 Battelle Columbus Additional Unirradiated HAZ Resultst'l ( l i I SPsC18eBN TussP surener 1A;taAI. rnact 20 TBST 18EPACT SEP APPSAA tr) Ift.1b) tail) (S) l 30 1 120.00 7.50 S.00 11.00 383 120.00 9.50 3.30 9.30 , 1811 00.00 33.50 13.00 12.40 l 1812 00.00 34.00 18.40 17.00 j 1817 40.00 27.50 31.80 13.10 384 40.00 St.D0 34.30 31.10 58 9 0.00 29.90 31.00 49.20 let 0.00 64.50 43.30 55.40 1814 20.00 $1.50 46.60 S2.00 ISS 20.00 76.D0 49.80 S4.10 i l 183 20.00 02.D0 50.40 54.30 I isle 40.00 93.00 83.00 63.10 l 1810 40.00 99.90 64.00 73.40 1883 40.00 10$.D0 44.40 72.90 ist 90.00 113.80 72.60 1D0.00 186 00.00 115.00 65.00 1D0.00 1 1 184 120.00 123.00 83.40 160.00 1834 130.00 140.00 88.80 100.00 187 140.00 120.00 87.30 SDO.00 183 160.00 153.00 02.30 300.00 Set 210.00 110.00 70.00 1D0.00 l 1stS 210.o0 132.e4 TS.e6 100.00 ! 1 I l 1 I l I (33 I J l l l l I l
( APPENDIX H I SONGS, UNIT 3: IRRADIATED Cm DATA FROM CAPSULE 97 i I ( i l 4
)
T Table H-1 Charpy V-Notch Test Results For Unit 3 Plate C6802-1 (LT) ( Irradiated (f = 8 x 10" n/cm') SPECIMEM TEMP ENERCf 1ATERAL FRACT ID TEST IMPACT ERP APPEAR (F) (ft.lb) (all) (t) 147 50.00 5.00 5.00 5.00 153 75.00 22.00 15.00 15.00 15R 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 15s 165.00 45.00 43.00 45.00 14A 175.00 30.00 27.00 45.00 14E 200.00 48.00 44.00 55.00 11T 225.00 75.00 54.00 30.00 12K 250.00 45.00 40.00 30.00 12L 250.00 40.00 46.00 95.00 14M 275.00 90.00 76.00 100.00
- I 1
l H-1
l 1 i Table H-2 Charpy V-Notch Test Reac" . For Unit 3 Plate C6802-1 (TL) l Irradiated (f = 8 x 10 n/cm') l I l spectnsu TenP BNERST IATERAL FRACT l ID TEST IfrACT RTP APPEAR (P) (ft-1b3 (mil) (t) 25U c.00 19.00 1s.00 10.00 23K 25.00 16.00 11.00 10.00 21A S0.00 p.00 12.00 10.00 23L 75.0c 21.00 20.00 15.00 1 225 200.00 25.00 25.00 20.00 j 25.7 115.00 35.00 4e.00 45.00 J t 25L 130.00 50.00 44.00 50.00 247 150.00 33.co 33.co so.oo 223 1s5.00 36.0c 37.00 s5.00 25c 200.00 92.00 73.00 100.00 245 225.00 42.00 59.00 100.00 23M 250.00 73.00 77.00 too.co H-2
b t~ Table H 3 Charpy V-Notch Test Results g For Unit 3 Surveillance Weld Irradiated (f = 8 x 10 n/cm') spec 1 Men 7tMP tutRCT LATERAL FRACT ID TEST IMPACT RIP APPEAR (r) tit.1b) (mil) (t) 363 50.00 23.00 20.00 15.00 33L 35.00 27.00 25.00 30.00 310 0.00 5.00 6.00 5.00 37s 10.00 43.00 34.00 60.00 367 25.00 42.00 44.00 65.00 331 50.00 44.00 44.00 70.00 37U 60.00 41.00 57.00 95.00 371 00.00 65.00 59.0c 95.00 365 105.00 67.00 60.00 100.00 34P 150.00 75.00 73.00 100.00 330 190.00 77.00 76.00 100.00 1 377 235.00 63.00 50.00 100.00 ( ' H-3
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