ML20101N127
| ML20101N127 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 06/23/1992 |
| From: | ATI CONSULTING, SARTREX CORP. |
| To: | |
| Shared Package | |
| ML13302B853 | List: |
| References | |
| GL-92-01, GL-92-1, NUDOCS 9207090170 | |
| Download: ML20101N127 (94) | |
Text
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! Southern California Edison
- San Onofre Nuclear Generating Station, Unit 3 l
Response to Generic Letter 92-01
- (Non-Proprietary Version) l i
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9 ATI Consulting - Sartrex Corporation l-i I 9207090170 920706 l PDR ADOCK 05000361 .
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San Onofre Nuclear Generating Station, Unit 3 .
Response to Generic Letter 92-01 .
- Final Report
- June 23,1992 (Non-Proprietary Version) i .
, Prepared by: -
3 ATI Consulting.
San Ramon', _CA j
- a and Sartrex Corporation j:
Rockville,-MD Prepared for:
Southern California Edison -
- Irvine, CA' I
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CONTENTS Section Pace 1 INTRODUCTION 11 2 REACTOR PRESSURE VESSEL SUAVEILLANCE 21 PROGRAM COMPLIANCE WITil APPENDIX 11 3 FRACTURE MECliANICS 31 3.1 COMPLIANCE WITil APPENDIX 0 3.
3.2 BELTLINE MATERIALS IN SONOS, UNIT 3 31 3.2.1 Location 3-1 3.2.2 llent Treatment 31 3.2.3 Key Residual and Alloying Element Contents 3-2 3.3 FRACTURE TOUOllNESS RELATED DATA 33 3.3.1 Beltline Plate M tcrial 3-3 3.?.2 Beltline Welds 3-4 4 ISSUES RELATED TO OTwCRIC LETTER C8-11 41 4.1 VESSEL TEMPERATURE DURING OPERATION 4-1 4.2 APPLICABILrrY OF SURVEILLANCE DATA 41 4.3 SillFTS AT Tile CilARPY V-NOTCll 30 IT LB ENEROY LEVEL 4-2 4.4 UPPER SIIELF ENEROY DkvP 4-3 5 REFERENCES 51 APPENDIX A SONOS, UNIT 3: EVALUATION OF COMPLIANCE A-1 WITil ASTM E185 73 AND E185-82 APPENDIX B SONOS, UNIT 3: BASES FOR PLATE CilEMISTRY B MEASUREMENTS APPENDIX C SONOS, UNIT 3: MCRs FOR BELTLINE C-1 MATERIALS (Proprietary)
4 CONTENTS (cont'd)
Section Pas APPENDIX D SONGS, UNIT 3: UNIRRADIATED Cw DATA D1 FOR PLATES AND WELDS APPENDIX E SONGS, UNIT 3: IIAZ TEST RESULTS E1 '
APPENDIX F SONGS, UNIT 3: IRRADIATED Cw DATA FROM F1 CAPSULE 97 i
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s
g ILLUSTRATIONS Ficure Pace 31 SONGS, Unit 3: location and Identification of 3-6 Beltline Plates and Welds 32 SONGS, Unit 3: Data and Least Squarca Fit Curve 3-7 for Cm versus Temperature, Plate C68021, TL Orientation, MCR Data 1
33 SONGS, Unit 3: Data and Least Squarco Fit Curve for 3-8 Cw versus Temperature, Plate C6802 2, TL Orientation, MCR Data 3-4 SONGS, Unit 3: Data and Least Squares Fil Curve for 3-9 C versus Temperature, Plate C6802-3, TL Orientation, MCR Data 35 SONGS, Unit 3: Data and Least Squares Fit Curve for 3 10 Cm versus Temperature, Plate C6802-4, TL Orientation,
, MCR Data 34 SONGS, Unit 3: Data and least Squares Fit Curve for 3 11 Cm versus Temperature, Plate C6802 5, TL Orientation, MCR Data 3-7 SONGS, Unit 3: Data and least Squares Fit Curve for 3 12 Cm versus Temperature, Plate C6802-6, TL Orientation, MCR Data 3-8 SONGS, Unit - Data and least Squares Fit Curve for 3 13 Cw versus Temperature, Plate C68021, TL Orientation, Surveillance Baseline Data 39 SONGS, Unit 3: Data and Least Squares Fit Curve for 3-14 Cm versus Temperature, Plate C6802-1, TL Orientation, Combined MCR and Surveillance Baseline Data 3-10 SONGS, Unit 3: Data and least Squares Fit Curve for 3 15 Cw versus Temperature, Plate C68021, LT Orientation, Surwillance Baseline Data
ILLUSTRATIONS (cont'd)
Ficure fac 3 11 SONGS, Unit 3: Data and least Squarcs Fit Curve for 3 16 Cm versus Temprcature, Plate C6802-1, LT LT Orientation, MCR Data 3 12 SONGS, Unit 3: Data and least Squares Fil Curve for 3 17 Cm versus Tempreature, Weld 3 203, FSAR Data 3 13 SONGS, Unit 3: Data and Least Squares Fit Curve for 3-18 Temperature, Weld 9 203, WMC Data 3 14 SONGS, Unit 3: Data and least Squares Fit Curve for 3-19 Cm versus Temperature, Surveillance Weld, Surveillance Baseline Data 41 SONGS, Unit 3: Comparison of Irradiated Cm Data from 4-4 Capsule 97 with Unirradiated Baseline Data, Plate C6802-1, LT Orientation 42 SONGS, Unit 3: Comparison of Irradiated Cm Data from 4-5 Capsule 97 with Unirradiated Baseline Data, Plate C6802-1 TL Orientation 4-3 SONGS, Unit 3: Comparison of irradiated Cm Data from 4-6 Capsule 97 with Unitradiahd Baselb:: Data, Surveillance Weld
TABLES Tabig .tagg 3.1 SONGS, Unit 3: 10CFR50 Appendix G - Areas of Non Compliance 3 20 3.2 SONGS, Unit 3: Plate and Corresponding IIcat Numbers for 3 22 Beltline Plates 3.3 SONGS, Unit 3: Weld Wire and Flux Combinations for Beltline 3-23 and Suiveillance Welds 3.4 SONGS, Unit 3: Key Residual and Alloying Element Contents 3 24 for Beltline Plates 3.5 SONGS, Unit 3: Key Residual and Alloying Element Contents 3 25 Beltline Welds 3.6 SONGS, Unit 3: Beltline Plate Material Unitradiated Fracture 3 26 Toughness Tests Results Summary 3.7 SONGS, Unit 3: Charpy Absorbed Energy Values at 20F for Weld 3 27 Scams 2-203 A, B, and C 3.8 SONGS, Unit 3: Beltline Wcid Material Unirradiated Fracture 3-28 Toughness Tests Results Summary 4.1 SONGS, Unit 3: Surveillance Capsule Shift Results 47 4.2 SONGS, Unit 3: ART Estimates for Beltline Materials 4-8 on 12/16/91 and at 32 EFPY
\
4.3 SONGS, Unit 3: Surveillance Capsule Upper Shelf Results 4-9 4.4 SONGS, Unit 3: Upper Shelf Estimates for Ucitline Materials 4-10 on 12/16/91 and at 32 EFPY b __ - - - _ _ - - __
Section 1 INTRODUCTION The Nuclear Regulatory Commission (NRC) in Generic letter 92-01 (OL92 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. This report has been prepared in resporv i to OL92 01 for San Onofre Nuclear Generating Station (SONOS), Unit 3.
Section 2 of this report addresses compliance with 10 CFR Pan 50 (10CFR50), Appendix 11 for the surveillance program at SONOS, Unit 3. Compliance with 10CFR50, Appendix 0 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 SONOS, Unit 3 reactor vessel. Section 4.0 addresses embrittlement effects, including irradiation temperature and adjusted reference temperature for evaluation of the beltline materials relative to GL8811 and 10CFR50.61.
Additionalinformation is needed to complete the response to OL92-01 for_ SONOS, Unit 3. This information includes: (1) resolving inconsistencie lh s. nd 72 <ontents and Charpy impact propenics reported for beltline weld 9 203 and the adh , eld, 'th have been reported to have been fabricated using some of the same cok v.vtsa i * %p; meterial certification i repons to confirm beltline weld properties, (3) lownffg: us4 Chary / mpact i properties, chemistry, and fluence for weld 8 203, and (4) resolving incoraistencies between Charpy impact propenies reported in the materials cenificatior, report and th: msterials surveillance program for the longitudinal orientation in plate C68021.
11
l l
Section 2 REACTOR PRESSURE VESSEL SURVEILLANCE PROGRAM COMPLIANCE WITil APPENDIX 11 The ASME Code of record for the San Onofre Nuclear Generating Station (SONGS), Unit 3 reactor pressure vessel is the 1971 Edition through the Summer 1971 Addenda. Consequently, the applicabic version of ASui E185 is the 1970 version (ASTM E185-70). Ilowever, 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 II. Appendix A to this report provides a detailed review of ASTM E185 73 along with validation that ASTM E185 73
- requirements were satisfied for the surveillance program 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 cunent approved version).
As stated in the SONGS, Units 2 and 3 Final Safety Analysh Report (FSAR), Appendix 11 requirements were met (with one exception) through compliance with ASTM E185 73. The one exception to meeting Appendix 11 requirements had to do with the method of attachment of the holders for the six surveillance capsules in cach SONGS unit. Combustion Engineering (CE) was the vessel manufacturer and the nuclear steam st'pply system (NSSS) vendor; CE attached the
, capsule holders directly to the cladding on the inside of the vessel in the beltline region (as they did for all CE NSSS. designed vessels), and this approach violated the requirements in the early 1970's version of 10CFR50, Appendix H. The NRC reviewed a CE Topical Report (CENPD-155 P, C E Procedure for the Desinn. Fabrication. Installation, and Insocction of Surveillance lloider Assemblics) and found the practice and procedures acceptable.
The current version of Appendix 11 does not treat this method of attachment of the capsule holders as a noncompliance issue. The wording in the current Appendix 11,Section I.A.2 is:
"If ihe capsule holders are attached to the vessel wall or to the vessel cladding, construction and in-service inspection of the attachments and the attachmt it welds must be donc according to requirements for permanent structural attachments to reactor vessels given in Sections 111 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 CE Topical Report, and the SONGS units have met the additional ASME Code, Sections 111 and XI design and inspection requirements. Therefore, there are no deviations or exceptions needed from the current Appendix }{ of 10CFR50.
The details of the SONGS, Unit 3 surveillance program have been described in the FSAR and subsequent surveillance program testing reports, baseline 01 and -irradiated.121 The first capsule results have been evaluated for a low fluence following ASTM E185-82 testing and reporting 1
requirements. Later sections of this report will discuss these results as compared to regulatory prediction methods.
The update of ASTM E185 for 1992 (E185 92) is about to be approved and issued. One significant change from E185-82 is the removal of the requirements for testing heat affected zone (llAZ) material. This change has resulted from the difficulty in interpreting IIAZ results due to the degree of scatter and the ability to define the usefulness of blunt notch Cm IlAZ data. NRC has been involved in making this change to E185 through ASTM standards panicipation.
Because of this forthcoming change to ASTM E185 this report does not eva!.iate llAZ results for SONOS, Unit 3; however, the raw data from prior IIAZ testing on the SONGS, Unit 3 beltline material has been reponed previously,l"1 and is provided for reference in a subsequent section of this report.
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Section 3 FRACI URE MECilANICS This sect!on evaluates compliance with 10CFR50, Appendix 0 and identifies the location, heat treatment, key residual and alloying element contents, and unitradiated fracture toughness properties for plates and welds in the SONOS, Unit 3 reactor pressure vessel beltline region.
Generally, the information presented in this section has been obtained from the materials certification reports (MCRs) and the FSAR for SONOS, Unit 3, and from additional information supplied by Combustion Engineering (CE) to prepare this response, in some instances, additional information was obtained from the unirradiated baseline surveillance material report,UI and the irradiated material in the 97* location surveillance capsule (Capsulc 97), which was removed from Unit 3 at the end of the fourth fuel cycle.irj 3.1 COMPLIANCE WITil APPENDIX 0 Ocnerally, the materials in the beltline region of SONGS, Unit 3 comply with the requirements of Appendix 0,10CFR50. Areas of non compliance with Appendix 0,10CFR50, as specified in the FSAR for SONGS, Units 2 and 3 and updated during preparation of this report, are listed in Table 3.1.
3.2 DELTi.INE MATERIALS IN SONGS, UNIT 3 3.2.1. Incation Figure 31 is a representation of the SONGS, Unit 3 reactor pressure vessel, and identifies the plates and welds and their location in the beltline region.
'The heat numbers for the beltline plates shown in Figurc 3-l' arc presented in Table 3.2. The weld wire and Dux combination for the beltline welds shown in Figure 31 and the surveillance welds are presented in Table 3.3.
3.2.2 Heat Treatment The heat treatment for the plate materials consisted of austenitization at 157515(TF 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 v 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 10(rF/hr. The actual time at temperature for a specific wcld or a plate in the vessel l depended upon the sequence of vessel fabrication; intermediate 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.
3-1
longitudinal wcld 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
, 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 the l identical heat treatment as the actual reactor vessel. The surveillance weldment received a final l 41 hour4.74537e-4 days <br />0.0114 hours <br />6.779101e-5 weeks <br />1.56005e-5 months <br /> and 45 minute stress relief at 1100"F to 1150'F.
3.2.3 Key Residual and Allovine Element Contents l The copper (Cu), nickel (Ni), phosphorus (P) and sulfur (S) contents reported for each beltline plate are presented in Table 3.4. De plate Cu and Ni contents were obtained by averaging two measurements made by CE. The first measurement was made when CE received the plate from
~
Lukens and the second measurement was made when the surveillance program was defined. The bases for the Cu and Ni contents reported by CE and listed in Table 3.4 are presented in Appendix B. The plate P and S contems were obtained from the MCRs, which are included as Appendix C.
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.t2
~
Table 3.5 contains the Cu, Ni, P and S contents reported in the FSAR for the beltline welds.
Two additional chemistry measurements are reported for beltline weld 9 203. One additional value was obtained from the welding material certification (WMC) for Type Mil B-4 Wire, ficat No. 90069, Linde Type 124 Flux, Lot No. 0951 (see Appendix C), while a second preliminary value has been provided by CE l '1 for Typc Mil B 4 Wire, IIcat No. 90144, Linde Type 124 Flux, Lot No.1061. Three chemistry measurements have been made for the surveillance weld and also are reported in Table 3.5. He first chemistry measurement was made as part of the original baselineUl , while the second and third were obtained from broken Charpy specimens from Capsule 97(21 Because Cu was not measured for beltline weld 8-203, a value of 0.35 wt% has been assumed (sec Regulatory Guide 1.99, Revision 2). Because Ni was not measured for beltline welds 8-203 and 2 203, a vaine of 1.0 wt % has been assumed (see Regulatory Guide 1.99, Revision 2).
The surveillance weld was reported by CE to have been fabricated using one of the weld wire and flux combinations in weld 9 203 (see Table 3.3). The information in Table 3.5 indicates a distinct difference between the Cu and Ni contents reported for the surveillance weld and weld 9 203. Because of the differences in reported Cu and Ni contents and differences in the Cw curves (see Section 3.3.2) the surveillance weld and beltline weld 9 203 are listed and evaluated separately in the report. CE is continuing their investigation to resolve these inconsistencies.
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.
32
3.3 FRACTURE TOUGliNESS RElATED DATA This section presents the results from the Charpy V notch absorbed energy (Cw) tests, and summarizes the upper shelf energies ('USE) and the results from the drop weight nil ductility temperature (NDT) tests for the unirtadiated beltline plate and weld materials in SONGS, Unit
- 3. The unirradiated reference temperature (RTmn) values were determined from the Cw and NDT test results in accordance with the most recent version of ASME Section 111, NB 2331. The upper shelf energies were determined using the definition specified in ASTM E185 92 (to be issued). The data included in the USE determination were the Cw values for those tests (at least
- 3) where the percent shear on the fracture surfaces was equal to and greater than 95%
The fracture toughness data for plate were obtained from the MCRs (see Appendix C) and baseline surveillance program. The data for weld 9 203 were obtained from the WMC (see Appendix C). The fracture toughness data for the remaining beltline welds were obtained from the FSAR, and the data for the surveillance weld was obtained from the baseline surveillance program. For 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 D.
As discussed earlier in Section 2, the results for heat affected zone (HAZ) material are not evaluated in this report because upcoming ASTM standard E185 92 will not require IIAZ I material to be part of the surveillance program. The raw Cm data for the past liAZ testing are attached in Appendix E.
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, ne exception is for the beltline plate C68021, which was included in the surveillance program. Because the surveillance program for SONGS, Unit 3 also contains longitudinally (LT) oriented specimens the uni tradiated Cm data are presented for completeness for the LT orientat'on.
De transverse Cm data as a function of test temperature for beltline plate numbers C68021, -2, 3, -4, 5, and -6 are presented in Figures 3 2 through 3 7, respectively. For convenience, an average curve through the data also is shown in each figure. The average curves were determined using a least squares fit to the data and a hyperbolic tangent functional form, where the low r shelf was fixed at 2.2 ft lb and the' upper shelf was fixed at the value determined using the definition in ASTM E185 92 for specimens having fracture surfaces with 95% and greater shear. For convenience, the figures also indicate the values of NDT, USE, the temperature at which a minimum Cm qual e to 50 ft lb (T @ 50 ft lbs) is achieved consistent with the appl! cable method of ASME,Section III, NB 2331, and RTunt, 33
As part of the surveillance program additional Charpy absorbed energy versus temperature data were generated for plate C68021;I1 these data are presented in Figure 3 8 along with a least squares fit curve. Because there was a relatisely wide gap in the test temperatures near the 50 ft lb level for the surveillance baseline data set in Figure 3 8, the graphical method of NB 2331 (a)(4) was used to determine RTuor The 50 ft lb temperature was determined by the intersection of the dashed line and the 50 ft lb level as shown in Figure 3 8. The dashed line was drawn parallel to the least squares fit line at 50 ft lb so that it was on, or to the right of, all data points in the transition region.
The data obtained when the plate material was purchased (Figure 3 2) and the surveillance baseline data (Figure 3 8) were combined as shown in Figure 3 9. The combined data set presented in Figure 3 9 was used to determine RTm and the USE for the transverse orientation in Plate C68021. The average curve through the combined data set in Figure 3 9 also was used as the unitradiated baseline to evaluate the results for the irradiated surveillance tests (see Section 4).
Table 3.6 is a summary of the unitradiated NDT, RTm and USE values for the transverse orientation for each of the beltline plates in SONOS, Unit 3. The NDT for plate C68021 also was determined twice. One value was measured when the material was purchased, while the second value was detennined from the unirradiated baseline tests. The higher of these values is listed in Table 3.6.
The methods used to determine RTm from the NDT and Cm data also are identified in Table 3.6. %c method of NB 2331 (a)(3) was used to determine RTm for all plates except for the combined data set of plate C68021 (see Figure 3 9), where the graphical method of NB 2331 (a)(4) was used because there is a relatively wide spread in the test temperatures near the 50 ft lb level.
Figure 310 shows the data and least squares fit line for the longitudinal (LT) orientation for surveillance plate C68021,1 I 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 310 and 311 indicate a significant difference in the Cm versus temperature curves obtained from the MCR and surveillance program for the LT orientation for plate C68021. CE is continuing their investigation to resolve this inconsistency.
3.3.2 Beltline Welds A full Cm versus temperature curve was obtained for the material in weld seam 3-203, and the data points and least squares hyperbolic tangent fit through the data are presented in Figure 312.
A full Cm versus temperature curve was obtained for the Type Mil B-4 Wire, Heat No. 90069, Linde Type 124 Flux, tot No. 0951 combination in beltline weld scam 9 203; the cmdata and least squares hyperbolic tangent fit through the data are presented in Figure 313. The material in beltline weld scam 2 203 was tested to obtain three Cw data points at 20 F. De results from these tests are presented in Table 3.7.
3-4
J l
Figure 314 presents the Cw aata and least squares hyperbolic tangent curve fit for the surveillanec weld material. A comparison of Figures 313 and 314 indicates a significant difference in the Cw versus temperature curves for the surveillance weld and beltline weld 9 203.
This difference is not consistent with what would be expected from independent testing of the same weld wire heat. The source of this inconsistency is under investigation by CE.
Table 3.8 presents a summary of the unitradiated NDT, RTmn and USE values for each of the beltline welds in SONGS, Unit 3. For welds 2 203,3 203, and 9 203 available Cw data indicate that there is a minimum of 50 ft lb absorbed energy at 60'F above NDT, and consequently RTmn equals NDT. No NDT data are available for weld 8 203, and RTmn was taken as the generic l value of 56 F for CE fabricated vessels (see 10CFR50.61). l l
Because fewer than three specimens were tested at each temperature the graphical method of NB.
2331 (a)(4) was used to determine RTun for the surveillance weld as shown by the intersection of the dashed line and the 50 ft lb Cw level in Figure 314.
The upper shelf energies listed in Table 3.8 for welds 3 203, 9 203 (liect 90069), and the surveillance weld were obtained by averaging the test results where 95% shear or greater was exhibited. The upper shelf energy for weld 2 203 was obtained from the data in Table 3.7 by averaging the threc Cm data points obtained at 20'F. Currently, no C, data have been identified for welds 9 203 (l{ cat 90144) and 8 203, and CE is continuing their investigation to
- identify the Cw values.
35
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3!!!!!!!!!!!!!!!!i}!!!!!!!$ Figure 31. SONGS, Unit 3: Location and IdCntification of Beltline Plates and Welds. 36 4 5
200 San;Onofre Unit 3
. MCR Data
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Material: Plate C68021 A533B1 Orientation: TI., 150 ----OSI m 98 ft-ith-~- - + --- -- ---- --
. NDy = 20 'F e "
T @; 50 ft-Ibs = 100 'F
#- RTnh = 40 'F
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E w 100 =- ~~---- - - - - - -- n-e 6 - . -- c . Lu Z O 0 50 - - - - - h- O Measured ~1
. O
[ g Calculated
. P
.{
o --.........i....n ,,,,n ,,,, u ,,,, ,,,,,i
*200 -100 0 100 200 300' 400 500 Temperature In Degrees F Figure 3-2. SONGS, Unit 3: Data and Least Squares Fit Curve for C, versus Temperature, Plate C6802-1, TL Orientation, MCR Data.
37
200 -- San Onofre Unit.3 I " ' MCR Data
- Mateklal: Plate No. C680242, A533B1 150 ----@ntappm _ K1, ______ . , _ _ _ __ _ _ _ _ _
USE = 115 ft lbs NOT = 20 'F T @ !50 ft lbs = 70 'F
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4 . RTnd't = 10 'F
. . b
@ 100 --- ---- -- --- - ---- --
b
- 2
> ~
U ob 50 - - - - - L D- -+- - - - - -
. O O Measured
. O 1
Calculated
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O '''''i 200 100 0 100 '200- 300 400 500 Temperature in Degrees F Figure 3-3. SONGS, Unit 3: Data and Least Square: Fit Curve for Cm versus Temperature - Plate C6802-2, TL Orientation, MCR Data.' -- 8
- . -_-- -- NJ
1 1 200 - San Onofre Unit;3 . MCR Data l
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l Mater lal: Plate No. C6802 3, A53381 1 - Orienlation: TL l i 150 ~~~ USE1 105..ft@s - ... . l ,, NDT h -10 'F l l , T @ $0 ft-lbs = 80 'F f .o - RTndt = 20 'F
- r g .
4 A 8 e E 100 -- -- r- - + - - - -
- - - ---~ ~ ~ - --
i g . . z - 6' O O 50 -- A- -~ ~L - -- - - - 0 Measined lo Calculated l a 4
! j o .........i....n ....i ....i . . . . . . . . -
200 100 0 100 200 300 400 500 Temperature in Degrees F-J Figure 3-4. SONGS, Unit 3: Data and least Squares Fit Curve for Cm versus Temperature, Plate C6802-3, TL Orientation, MCR Data. 39-
_.._. . _ _ __ ~ . . . _ _____ i j J , 200 -
- San Onofre Unit,3
. MCR Data
- Material: Plate No. C680244, A53381 Orion'tation: TL 150 -'
USE ~118-ft tbs ~ ~ ~ -" - -- NOT , 30 'F se
~ T @ ;50 ft-lba = 70 'F
$ RTndt = 10 'F o '
c - e
. . i w 100 = O o e
b ~ z - i mo o O 50 -- L- - b-0 ' - - - - - - ,--- -- -- o Measured g Calculated j. o
. . .......n . ...n ....l . . . .. ....i - ,....
200 -100 0 100 200 300 400 500
. Temperature in Degrees F Figure 3 5. SONGS, Unit 3: Data and least Squares Fit Curve for Cw _versus Temperature, Plate C6802-4, TL Orientation, MCR Data.-
3 10
-___mr_ __m_ _ _ _ _ ____.m__m_- __ .. _.__ _ -. _- ___ _
200 --
. l San Onofre Unit 3
. MCR Data l
, Material: Plate No. C6802 5, A533B1 Orientation: TL 150 -
OSE Y116~ft-ibt
~~""~~~ " ~ " ~ ~ " ~"~~~~~~
NDTmOY to ~ T @ 5b ft lbs = 70 Y k RTndt 'm 10 Y E " 8 8 o w 100 = -- - - - --- e - - $ ~ Z > ~ 0 o 50 = J-- '-- --
, O Measured
- o Calculated o ...... #... i
....n ....r . ..n .........i 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 Tempenture,
. Plate C6802-5, TL Orientation, MCR Data.-
3 11
200 -
. San Onofre Unit '3 MCRDak i' Mater lal: Plate No. C6802 B, A533B1 150 --
Ortenfation: TL+ . - . - -.--- -
, USE = 92 ft lbs
, NOT = 40 'F g "
T @ 50 ft lbs = 80 'F d - RTndt. = 20 'F
@ joo .- - ,._ _ _ ,__, ---+__
e o j - O z - o - l &9 50 - - - ' - ,-
-- 0 --
- o o ' Measured
. D
" l !
! Calculated i . !
I i 9.....l....n. ........! .... o .....
~
-200 100 0 100 200 ,300 400 500 Temperature in Degrees F.
Figure 3 7. SONGS, Unit 3: Data and Least Squares Fit Curve for Cm versus Temperature, Plate C6802 6, TL Orientation, MCR Data. 3-12
. . _ - - - - - - - - - - - - - - - - - 1
200 - -
~
\
f = 0.0 i
- ! , i i' !
. 2 150 -
" San Onofre Unit 3 l i Surveillance Program a
- Materialj Plate No. 68021, SA53381-
$ , Orientatlon: TL g USE = 92 ft Ibs
" a NDT = JO Y ' O ;U 100 --T-@- flesme1454 -
r - y . RTnot = 75 Y ! 'O' l -i' 1 - l 0 ! U i h " l l0 { O l O , O j'
=
1
/ 4 4
50 ------J U- --
,f --
! I
. j O/
I i
. ! !/ !
i { O l;
" O O
= U ,
i )
- t i 0 ' ''''''''''''''' '''''''''
200 100 0 100 200 300 400 500 Temperature in Degrees F Figure 3-8. SONGS, tinit 3: Data and Least Squan:s Fit Curn br Cw versus Temperature, Plate C68021, TL Orientation, Surveillance Baseline Data. 3 13 2, . . . , .
1 1 l l ) 200 1 . 4 San Onotre Unit 3 Combihed MCR d Unirradiated Baseline Data Materl'al: Plate No. C68021, SA533B1 - 15o - Orientation: TLI.- - - -_ --
- " USE = 94 ft-lbs NDT k 10 'F B T @ 50 ft lbs = ' 45'F d -
RTndt = 75 'F
" 0
$ o O 100 --- + --
+ - - - - --
c . I '
- W Do O Z O O
> " 0 i
O } / ' / O Measured 50 -- -+- O_ _ Q_ f..___ O o ,/ Calculated 10
. @ O O
. O 1
i o
. .. .. .i....i....i....n ....n ....i 200 100- 0 100 200 300 400 500 Temperature in Degrees F-Figure 3-9. SONGS, Unit 3: Data and Least Squares Fit Curve for Cm versus Temperature, Plate C6802-1, TL Orientation, Combined MCR and Surveillance Baseline Data.
3-14
, =. , .
200 - - - + 7 q f = 0.0 San. Onofre Unit 3 150 . Surseillance Pjogram - --- -
~
Material: Plate :No. C68021, SA53381
" Orle'ntation: Lf g -
USE$ = 91 ft lbs 3 u. N D Tl = 0 V
. T @ 50 ft-lbs a 170 V
$ ooi . RTnbt 4
= 110 Tl - _ _ _ _ .
l O g O U .
.O
. /
/
50 = - - * - - - & -U/ - '
~
I / i o,/ i A 0 '""" "' ''' h '''''''''' ' 200 100 0 100 200 300- 400' 500 Temperature in Degrees F Figure 3-10.. SONGS, Ur.h 3: Data and least Squares Fit Curve for Cw versus Ternperature,- Plate Co802-1, LT Orientation, Surveillance Baseline Data. 3-15 _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ __ _ - l
200 -- San ,Onofre Unit 3 MCficata Matdrial: Plate No. C68021, SA53381
- Orlehtation: LT; 150 = - - - -
+-- + -+-
NDT l
"' T @j a 10 'F50 ft-lb = ho 'F $r -
RTn = 20 'F b E
@ too .___ , __8 _ __
e Z 0 O Measured 50 - - - - 6-+--
]'
O Calculated , O O
!O
~
0 0)'
''''''k''''l
\ '
\
-200 -100 0 100 200 -300 -400 500 Temperature in Degrees F Figure 311.- SONGS, Unit 3: Data and Least Squares Fit Curve for C,versus Temperatute, Plate C68021, LT Orientation, MCR Data.
3 16
200 - o
. 0 150 -
M " o E San Onofte ' Unit 3
- . 8g SAR Data @ joo . _ _ - . __.+.______MatedalL. Weld Seam 3 2.04____
- OSE = 161 ft-Ibs c .
tu NOT = 70 'F Z o T @ 50 ft-lbs = 40 Y
> . RTndt = 70 'F O
i 50 +- * - --
-- -- -t--
- o. Measured i
", 'o Calculated i
a a a i a e a a Il a a a a H n a a a i a a a n L a a a a 11 m a a a 1 200 100 0 100 200 300 400 500 Temperature in_ Degrees F Figure 3-12. ' SONGS, Unit 3: Data and Least Squares Fit Curve for Cm versus Temperature, Weld 3 203, FSAR Data 3-17 1j
T 200 . i San Onofre Unit .3 l M C R D ata !
. Material: Weld Seam 9-203 Heat No. 90069 l 150 -"
" ' ~ ~ " " ' ~
U55YIE3 ft ibs
~
NDT E -60 'F j . T @ $0 ft Ibs = +40 'F 0 0 Z , RTndt = 60 'F 6 0 - -g y a l A 100 =- c c . Lu i l
" C +
Z 6; i
> i' o -
0 - 50 * *' L O i Measured i
. ! Calculated
. +
- 0 4 C i !
0 ''''''''''''''''''' "'''' "
-200 100 0 100 200 300 400 500 Temperature in Degrees F Figure 313. SONGS, Unit 3: Data and least Squares Fit Curve for Cw versus Temperature, Weld 9-203, MCR Data.
3 18
f i 1 200 = 7 -- 4
+
) j l f = 0.0 i i- +- - - - 150 -- - - - i San Onofre Unit 3-- Surveillancel Program I - Material: W$ld ! Ir - d.SE = 82 ft.-Ibs g
- NDT = 60 y
, g T @ 50 ft-Iba a 30 'F A w 100 =- qTndt =- 30 8F ~ O O
~~~
n 2 O
> - O u O U - 0 0 0
/
/ i 50 -- --
-r - -+- -
---+
/
<f
'O~
- 0 0
0
' 9'''' ' ' ' ' ' ' ' ' '' ' i 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 Cm versus Temperature, :
Surveillance Weld, Surveillance Baseline Data. 3 19 l
4 1 l Table 3.1 SONGS, Unit 3: 10CFR50 Appendix 0 Areas of Non Compliance. 1 j Paragraph Description of Non-Compliance Comment
. II.B Series 4xx stainless stects are Consistent with ASME Code in effect.
} purchased and treated to Code requirements. No RTm or drop weight T,cr temperatures
- are determined.
4 III.B.S.a Records of fracture toughness Appendix 0 was not applicable at the testing do not include a time tests were performed. Certification certification that tests were to the applicable ASME Cc.ie is
- , performed in accordance with included. The intent of Appadix 0 is j Appendix 0. met.
lil.C. " Reactor Vessel Beltline", as The baseline tests of the surveillance defined by Paragraph 11.11, program include weld and ilAZ material j includes the wcld heat- from the most limiting plate. Results . affected zones. Section Ill.C available for SONGS Unit 2 indicate that is not complied with in that the intent of Appendix 0 has been met.- only base plate and represent- (Note: the llAZ results are not i active welds in the beltline presented in this report) region were considered for the required testing. Ill.C.1 Only single-temperature testing Consistent with ASME Code in effect. , was performed for some wcld materials. Only the heat affected zone from the most limiting plate was tested over an extended temperature range. Ill.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 r ' er, corresponding shcIl materials were used. (Section IX, A% dxle) 3 20
Table 3.1 (Continue"- Paragraph Description of Non-Compliance Comment IV. A.4 Charpy V-notch test were The ASME Code in effect required not conducted at 'the test temputature of 60F below the preload temperature or at the lowest service temperature. All bwest service temperature, bH'ing material was tested at 10F whichever is lower". t..J met the 35 ft-lb minimum requirement of the applicable ASME Code. All beltline plate materials and two beltline welds were tested to meet the current (1989) Code requirements in NB-2331. One beltline weld as tested at 20F and has C w in excess of 100 ft-lb. These results indicate that the intent of Appendix G has been met. One weld located away from the core region has been classified as a beltline weld because the Cu and Ni contents are currently not documented and high values have been assumed; these assumed Cu and Ni values result in. the second largest shift, for the beltline materials. In addition, no Cw data are currently available for this weld. Additional chemistry, fluence, and Cm energy data will be required to complete the evaluation of wcld 8-203 for compliance with Appendix G. _~ 3 21 { .. - _ _ _ _ _ - _ _
Table 3.2 SONGS, Unit 3: Plate and Corresponding IIcat Numbers for the Beltline Plates. Lukens Plate Number IIcat Number-C6802-1 C9195-2 C6802 2 C9218-2 4 C6802 3 C9195-1 1 i C6802-4 C9220-1 4 C6802-5 C9218-1 C6802-6 B3388-1
+
22
. _.. -- ~ _ - . . . . . ~ -- .- . . -. . . . . . = - - .-
l. 4 e Table 3.3 SONGS, Unit 3: Weld Wire and Flux Combinations for Beltline and , Surveillance Welds. Weld Scam Weld Wire and Flux i U 2 203 A, B, and C Type Mil B-4 Wire, l' eat No. 83650 Linde Type 0091 Flux, Lot No.1122 { I 3-203 A, B, pnd C Type Mil B-4 Wire, Heat No. 88114,- . Linde Type 0091 Flux, Lot No. 0145 i 9-203 Combination of (1) Type Mil B-4 Wire,- + 21 eat 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 Presently not available. Surveillance _ Presently not available. Currently reported - 4 by CE to be one of the weld wire heats i used to fabricate beltline weld 9-203 l'l. 4 4 4 i 9 }1- 3-23 7 y . .- , y g, , Ls'...,,,,'.,. . _ , , -e, m. . .,-.#. w
-..-g a Table 3.4 SONGS, Unit 3: Key Residual and Alloying Element Contents for Beltline Plates.
Plate . Number Cu' Ni' P6' S6 CP i C6802-1 0.06 0.58 0.011 0.013 37 s C6802-1 0.06d 0.58d 0.009 d 0.014 d 37 j C6802-2 0.04 0.57 0.010 0.013 26 l C6802-3 0.06 0.58 0.011 0.012 37 1 I C6802-4 0.05 0.56 0.011 0.013 31-C6802-5 0.04 0.55 0.012 0.013 26 C6802-6 0.06 0.62 0.011 0.014 37-i a. Average values reported oy CE in Appendix B.
- b. Values reported in the MCR.
I c. Chemistry factors from Regulatory Guide 1.99, Revison 2
- d. Measured when the surveillance tests were performed for Capsule 97.i21 3 ,
n ,
-.--- - e
Table 3.5 SONGS, Unit 3: Key Residual and Alloying Element Contents for Beltline Welds ., Weld Scam Cu Ni P S CP 2-203A,B,C6 0.05 l' O.006 0.010 68 3 203A,B,C" 0.04 0.16 0.007 0.005 39 9-203 6 0.05 0.04 0.007 0.011 31 9-203 d 0.06 0.04 0.010 0.009 34 9-203* 0.05 0.04 N/A N/A 31 8-203 0.35' l' N/A N/A 272 Surveillance 8 0.03 0.08 0.004 0.009 27 Surveillance " 0.03 0.11 0.014 0.008 29 6 Surveillance 0.03 0.09 0.011 0.008 28
- a. Chemistry Factors determined from Regulatory Guide 1.99, Revison 2
- b. Values from FSAR i
- c. Ni content was not measured and I wt% has been assumed
- d. Values from WMC for Type Mil B-4 Wire, Heat No. 90069, Linde Type 124 Flux, Lot No. 0951.
- c. Preliminary information from CE for Type Mil B-4 Wire, Heat No. 90144, Linde Type 4 124 Flux, Lot No.1061 1*l.
- f. Cu content was not measured and 0.35% has been assumed
- g. Measured when surveillance program was developedDi
- h. Measured when the surveillance tests were performed for Capsule 97t2i 3-25 l
J
l i Table 3.6 SONGS, Unit 3: Beltline Plate Material Unitradiated Fracture Toughness Tests Results Summary, .TL Orientation. i Initial Plate NDT RTm Procedure to USE Number ("F) (*F) Determine RTm (ft-lbs) 6 C6802-l' -10 75 NB2331 (aX4) 94 C6802 2 -20 10 NB2331 (aX3) 115 C6802 3 -10 20 NB2331 (aX3) 105 C6802-4 -30 10 NB2331 (aX3) 118 C6802-5 0 10 NB2331 (aX3) 116 C5F5 -40 20 NB2331 (aX3) 92
- a. This plate is included in the surveillance program. RTm and USE values are based on the combined data sets from the MCRs and unirradiated surveillance baseline (see Figure 3-9)
- b. Higher of 2 transverse values (i.e., -20"F determined when plate was purchased, and -10"F from surveillance baseline) 3 l
.- l
Table 3.7 SONGS, Unit 3: Charpy Absorbed Energy Values at 207 for Weld Scams 2-203 A, B and C. Charpy Energy Weld Seam (ft-lb) 2 203 A, B, and C 125,138,145 4 3-27
Table 3.8 SONGS, Unit 3: Beltline Weld Material Unirradiated Fracture Toughness Tests Results Summary. Initial NDT RTsw Procedure to USE Weld Scam ('F) (*F) Determine RT,cr (ft lbs) 6 2-203 A, B, C -40' -40 NB-2331 (a)(2) 136 3-203 A, B, C 70' -70 NB-2331 (a)(2) 161 8-203 N/A -56 c N/A 9-203 -60d -60 NB-2331 (a)(2) 123 9 203* -50 -50 - N/A Surveillance -60 -30 NB-2331 (a)(4) 82
- a. Values obtained from the FSAR
- b. Estimated using the average of Cm values obtained at +20"F (see Table 3.7)
- c. Generic value for CE fabricated vessels using Linde 009,1097, and 124 fluxes (see 10CFR50.61)
- d. Value obtained from the WMC, for Type Mit B-4 Wire, Heat No. 90069, Linde Type 124 Flux, tot No. 0951.
- e. Preliminary values obtained from CE for Type Mil B4 Wire, Heat No. 90144, Linde Type 124 Flux, Lot No.1061 '1,l i
3-28 - i I 1
I 4 Section 4 ISSUES RELATED TO GENERIC LETTER 88-11 NRC issued Generic Letter 88-11 (GL88-11) in July 1988. GL8811 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 Generic Letter 92-01 (GL92-01) are addressed in this section. 4.1 VESSEL TEMPERATURE DURING OPERATION De methodology in Regulatory Guide 1.99, Revision 2 is specified to be applicable for operating temperatures in the range of from 525 to 590'F. Concern is expressed in GL92-01 that power operation may occur at temperatures below 525 F. For SONGS, Unit 3 the reactor coolant cold - leg temperature (TJ is never below 545*F during power operation and rises to about 553*F at full power. Rus, there is no time during normal power operation that the SONGS, Unit 3 vessel or surveillance capsules experience temperatures below 545 F. 4.2 APPLICABILITY OF SURVEILLANCE DATA To properly assess the measured surveillance results, and to project irradiation embrittlement trends for the vessel, 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. %e fluence as a function of 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?! These data represent the original core for both units, and the best estimate value of peak fluence at the vessel inner surface is 4.34 x 10 n/cm2 (E > 1 MeV); the cargule 11uence was about 20% higher at 5.07 x 10 n/cm'. At the start of the fourth cycle for each unit the core was reconfigured in a low leakage loading pattern which reduced the vessel and capsule 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 designsF: The peak fluence value at the vessel inner surface is 6.6 x 10
- 2 n/cm , and the associated capsule fluence is 8.0 x 10 n/cm 2, l
l 4-1 l
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'.I'l 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 31, there is a weld identified as 8-203 which is well outside the core region of the vessel (i.e., approximately 2 feet above the top of the core). This weld is considered a beltline material because of a large chemistry factor associated with the unreported Cu and Ni contents. Because Cu was not reported,0.35 wt % was conservatively assumed; and, because Ni was not reported, Ni was assumed at I wt E The fluence at this location above the i' core has reported in the FSAR to be about 1/37 that of the peak fluence location within the vessel. Preliminary calculations performed at SCE indicate that the fluence at this weld location may be considerably lower than that indicated in the FSAR. Prior to final verification of the SCE fluence calculation at weld 8 203, the factor of 1/37 has been assumed to perform the evaluations in this report. Within Regulatory Guide 1.99, Revision 2 there are five credibility criteria that must be met in order to utilize surveillance data in adjusting the predicted embrittlement trends and/or 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 25 F), but the other two have not been satisfied since only one capsule from each vessel has been pulled and evaluated. To satisfy these last two requirements, the second capsules 4 (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 Cm results from this capsule are shown in Figures 4-1 (Plate C6802-1/LT),4-2 (Plate C6802-1/FL), and 4-3 (surveillance weld). Appendix F contains in tabular form the absorbed energy, lateral expansion, and fracture appearance (% shear) for the irradiated surveillance materials. He 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 (RGl.99R2): RGl.99R2 = CF (chemistry factor) X ff (fluence function). 4-2
i The results obtained by Westinghouseta l 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 Cm data and the different data set used for Plate C6802-1/rL (i.e., Figure 3-8 for Westinghouse and Figure 3-9 in the current study). The measured shift result for plate C6802-1 are higher than the mean prediction from Regulatory Guide 1.99, Revision 2, but are within the mean plus two standard deviation value of 69 F (i.e., 35"F + 34'F = 69"F as compared to 45 - 58 F). The measured shift for the surveillance weld is much less than the mean shift prediction using Regulatory Guide 1.99, Revision 2. Until another
- capsule is tested, there is no way to definitively evaluate that the chemistry factors (CF) should be adjusted to tellect measured behavior, rather than that predicted from the Regulatory Guide.
- Table 4.2 lists the predicted estimates of adjusted RTwr (ART) at the vessel inner surface for the two time periods of December 16,1991 (as requested in GL92-01) 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 RTmr's were taken from Tables 3.6 and -
4 3.8. The results in Table 4.2 show that the plate material C6802-1 which is the plate material in the surveillance program, is the limiting material in the vessel beltline. For weld scam 9-203 the properties from the weld wire heat 90069 was used for the predictions in Table 4-21 if the other weld wire heat (90144) was evaluated, the results would be 10"F higher due to the higher initial RTer. 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 upper shelf energy results are shown in Figures 4-1,4-2, and 4-3, and are tabulated in Table 4.3 as an absolute drop in upper shelf energy (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 two measured upper shelf drops for plate C6802-1 are slightly higher than those predicted using the regulatory guide. The difference will be reassessed when additional surveillance capsule results are available (at about 15 EFPY); however, as shown in the following paragraph, current trends indicate an USE well above 50 ft-lb at 32 EFPY. Predictions of upper shelf energy 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. Because there are no upper shelf values for welds 8-203 and 9-203 (Heat 90144), these welds were not evaluated for drop in upper shelf. Since both of these welds were fabricated by CE using materials and procedures which produce initial upper shelves above 80 ft-lb, the upper shelf is projected to never drop below 50 ft-lb. 4-3
200 - M San Onofre Unit 3 Surveill'ance Program Materlal: Plate SA53381
, - Heat No. C68021 -----f=0.0 150 = ~
f = 8.0e+18 ta o f = 8.0e+18 r
~
E 100 = - L- -
=
0, a - ~ ~ ~ - ~ ~ ~ n z -
/
> f O U
,' e ;
/
/-
50 = f
/ O O- 8
/ O 0 o
=
/4
. /0
/
~
/
o 0 ' '''''''' l ' ' ' '* l' ''''' n '
-200- -100 0 -100 200 -300-400- . 500 Temperature lIn _ Degrees F Figure 4-1. SONGS, Unit 3:- Comparison._of Irradiated C, Data from Capule- 97' with Unitradiated Baseline Data, Plate C6802-1, LT Orientation. l
~4-4
200 ---
~
San Onofre Unit 3 SurveNiance Prog' ram Materi'l:-Plate a SA533B1 -----
. Heat Ao. C68021 f = 0.0 150 ---Quenla!!on: R- f = 8.0e+18
~
, O f a 8.0e+18
.c "
3 u.
~
-E 100 - 4 1 E . jk - w ,-
~
Z s' -O /
. O
/ O 50 -
- 4 -O- --
7 p
- /
/ O
,/ f.
. /
/
- O
.? I
...m u a e a a 1a a na Il e a a a N'e a e a Il n a a a ia a a n'i
-200 -100 0 :100- -200 300 400 500
-Temperature in Degrees F Figure 4-2. SONGS, Unit 3: Comparison of Irradiated Cm Data from Capsule 97..with Unitradiated Baseline Data, Flate C6802-1, TL Orientation.
4-5 1
~. _. -_ .- . - .
i 200 - 4 ;
- San Onofre Unit 3 Surveillance Prodram Material: Weld
_ _ _ _ _ g , o,o . i l 150 = - f = 8.0e+18 m o f = 8.0e+18
.O T "
C d.
@ 100 -
4 e- _ . - e c . tu z "
< ' 'O o O
/ ,' {og -O.
/
to 50 = r 77 f- - . 40 0 3
/!
/!
t
/
o' 3 / h ~ =~-I i e a e a a a a e ila a a a ia n a e Il e a a n'It a e a a ll
-200 -100 0 100 200 -300 400 500 Temperature in Degrees F Figure 4 3. ' SONGS, Unit 3: Comparison of Irradiated Cgdata from. Capsule 97 with Unitradiated Baseline Data, Surveillance Weld.
4-6
- i-
~
J e Table 4.1. SONGS, Unit 3: Surveillance Capsule Shift Results 4 30 ft-lb Shift ("F): - n Material / CF- ff , l Orientation . W - RG1.99R2 Current - o 4 I j: C6802-1/LT 37' - 0.94 50 35 45'- i .. d C6802-1/rL 37' O.94 55 35 ' 58 .- 6~ Surveillance -28 0.94. 32 . 26 ' -2*_ Weld - See Table 3.4 (Cu = .06; Ni e .58)L 6 Based upon the average chemistries -- see Table 3.5 (Cu = .03; Ni = .09); Based'on the baseline surveillance data, see Figure 3-10 d
- Based on the combined data set from the MCR and baseline surveillance program, see -
Figure 3 9 Based on the baseline surveillance data, see Figure 3-14. . 14-7 a
7 Table 4.2. SONGS, Unit 3: ART Estimates at the Inner Surface location for Beltline Materials on 12/16/91 and at 32 EFPY ff ART (F)
- Plate No./ CF at the Inner Surface at the inner Surface Weld Scam 12/16/91 32 EFPY 12/16/91 32 EFPY C68021 37 6 0.95 1.37 144 160 C6802-2 26 0.95 1.37 60 80 C6802-3 37 0.95 1.37 89 105 C6802-4 31 0.95 1.37 69 86 C6802-5 26 0.95 1.37 60 80 C6802-6 37 0.95 1.37 89 105 2-203 68 0.95 1.37 81 109 3-203 39 0.95 1.37 4 37 5
8-203 272 0.19' O.42* 56d 130 d 9-203 34 0.95 1.37 5 33 ART is the adjusted reference temperature equal to the predicted ' shift (CF x ff) plus the - initial RTmr P lus a margin term equal to 34F for plates or 56F for welds (unless the predicted shift is less than the margin term, in which case the margin is equal to the predicted shift) 6 Based upon measured chemistries for this plate (06 Cu /.58 Ni) -- see Tables 3.4 and 4.1. ff is based upon the peak vessel fluence divided by 37 (as indicated in the FSAR) d Since there is no measured initial RTsm, an additional margin associated with the standard deviation (17"F) of the initial RTer has been used as described in Regulatory-Guide 1.99, Rev. 2 4 - - _ _ _ -
Table 4.3. SONGS, Unit 3: Surveillance Capsule Upper Shelf Results Upper Shelf Drop (ft lb) Material / Cu Fluence Orientation (wt%) (x 10" n/cm) Battelle RGl.99R2 Current C6802-1/LT 0.06' O.80 22 17 22 d C6802-1/rL 0.06' O.80 16 17 18' Surveillance 0.036 0.80 12 15' 14' Weld See Table 3.4 l 6 See Table 3.5 Based upon the Regulatory Guide 1.99, Rev,2 lowest percentage drop (18%) curve at the specified fluence times the measured unitradiated upper shelf determined in this report d Based on the baseline surveillance data, see Figure 3-10 Based on the combined data set from the MCR and baseline surveillance program, see Figure 3 9 Based on the baseline surveillance data, see Figure 3-14 4-9 t
Table 4.4. SONGS, Unit 3: Upper Shelf Estimates at the Quarter Thickness location for Beltline Materials on 12/16/91 and 32 EFPY Ouence (x 10" n/cm) Upper Shelf Energy (ft-lb)' Plate No./ Cu at Ouarter-Thickness at Ouarter Thickness Weld Scam (wt%) 12/16/91 32 EFPY 12/16/91 32 EFPY C6802-1 0.066 0.51 2.5 79 72 C6802-2 0.04 0.51 2.5 96 88 C6802-3 0.06 0.51 2.5 88 80 C6802-4 0.05 0.51 2.5 99 90 C6802-5 0.04 0.51 2.5 97 89 C6802-6 0.06 0.51 2.5 77 70 2 203 0.05 0.51 2.5 114 104 3-203 0.04 0.51 2.5 135 123 9 203 0.06 0.51 2.5 102 92 The upper shelf energy is estimated from Regulatory Guide 1.99, Rev. 2 taking into account the projected fluences and measured chemistry > 6 Based upon measured chemistry for this plate - see Table 3.4 4 4-10 i
Section 5 REFERENCES
- 1. A. Ragi, Southem 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 Company San Onofre Unit 3 Reactor Vessel Surveillance Capsule Removed from the 97 location. Westinghouse WCAP-12920, Revision 1, November 1991.
- 3. M. P. Manahan and J. Garrabrandt, Testine and Analysis of Unitradiated Heat Effected-7ene (HA7A Material from the San Onofre Nuclear Generatine Station Unit 3 (SONGS-3,}, Battelle Columbus, May 31,1989.
- 4. Telephone communication between S. Byme and C. Stewart, CE, and D. Pilmer and S. -
Gosselin, SCE, June 15, 1992.
- 5. M. P. Manahan, L M. Lowry, and E. O. Fromm, Examination. Testing, and Evaluation of Irradiated Pressure Vessel Surveillance Specimens from the San Onofre Nuclear Generatine Station Unit 2 (SONGS-21 Battelle Columbus, December 1988.
Dran 1,6/1NN2 32 pm. 5-1 _ _ _ . _ . _ _ _ _ _ _ _ . _ _ _ - _ _ __ ]
4
.c APPENDIX A SONGS, UNIT 3: EVALUATION OF COMPLIANCE WITil ASTM E185-73 AND E185-82
Summary of Requirements San Onofre Unit 3 Program per ASTM E185-73 1.2 Surveillance tests are Compliance divided according to application into two cases: 1.2.1 Case A - Where both the predicted increase in transition temperature of the reactor vessel steel is 100 F or less and the calculated peak neutron fluence (E > 1 MeV) of the reactor vessel is 5X 10" n/cm2 or less. 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 greater that 5 X 10" n/cm2 4.1 Test Material - Test To be confirmed based on specimens shall be preparedfrom resolving inconsistencies in: the actual materials used in (1) Cu and Ni contents and C , fabricating the irradiated curves reported for beltline region of the reactor vessel, and surveillance welds, and (2 ) C o curves reported for the LT orientation in beltline and surveillance plate materials. 4.1 Samples shall represent a Compliance minimum of one heat of the base metal and one butt veld and one weld heat-affected-zone (HAZ) if a weld occurs in the irradiated region. 4.1 The base metal and weld Compliance metal to be included in the program should represent the material that may limit the operation of the reactor during its lifetime. A-1
-_-_--_-_-_0
Summary of RequirementL San Onofre Unit 3 Program per ASTM E185-73 4.1.1 Vessel Material Sampling To be confirmed based on
- A minimum test program shall resolving inconsistencies int consist of specimens taken from (1) Cu and Ni contents reported the following locations: (1) for beltline and surveillance base metal of one heat used in welds, and (2) C. curves the irradiated region, (2 ) weld reported for the LT orientation metal, fully representative of in beltline and surveillance the f abrication practice used plates.
for a weld in the irradiated region (weld wire of rod, must come from one of the heats usad in the irradiated region of the reactor vessel) and the same type of flux, and (3 ) the heat-affected-zone associated with the base metal noted above. 4.1.1 Representative t sat stock Congliance to provide two addit'.onal sets of test specimens ef the base metal, weld and heat-affected-zone shall be ratained with full docume: :stion and identification. 4.1.2 Fabrication History - The Compliance test material shall receive a fabrication history (austenitizing, quench and tempering, and post-weld heat treatment) fully representative of the fabrication received by the material in the irradiated region of the reactor vessel. 4.1.3 Chemical Requirements - Compliance The chemical composition required by the material specifications for the test materials (base metal and as deposited weld metal) shall be A-2
. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ i
Summary of Requirements San Onofre Unit 3 Program per ASTM E181-73 obtained and include, but not compliance be limited to phosphorus (P), sulfur (S), copper (Cu), and vanadium (V). Compliance 4.2 Charpy V-notch impact specimens corresponding to the Type A specimen described in Methods E 23 shall be employed unless material thickness does not permit. Both irradiated
- and unirradiated types of specimens shall be of the same size and shape..
4.3 Specimen Orientation and Compliance Location - For both tension and impact specimens from base metal, the major axis of the specimen shall be machined normal to the principal rolling direction for plates and normal to the major working direction for forgings. The length of the notch of the Charpy impact specimen shall be normal to the surface of the-material. The recommended orientation of the impact and tension specimens with respect to the weld are shown in Fig. 1. Weld metal tension specimens may be oriented in the same direction as the Charpy specimens provided that the gage length consists of all weld metal. No specimens are to be removed within 1/2 in, of the root or the surfaces of the welds. Sections of the veldment shall be etched to define the weld heat affected zones. Care shall be taken that the impact specimens from the weld heat af fected zones have their notch A-3 i
Summary of Requirements San-Onofre Unit 3 Program per ASTM E185-73 roots in the heat af fected zone at a standard distance of i approximately 1/32 in. , from the fusion line. Specimens representing the base metal (tension and impact) and the weld heat-af fected- zone shall be removed from the quarter thickness location. (per NB2300 of ASME Code Section III) 4.4 Number of Specimens - The Compliance minimum number- of- test-specimens- for each exposure shall be as follows: Case A Case B charpy Charpy Tension-Base Metal -12 12 2 i 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 Lfor- each <
material.- i 4.4 For Case . B (see above),- Not Applicable ' three tension test - specimens shall be used- to- establish unirradia: ed tensile properties. 5 . 1 . 11 Vessel- Wall Specimens, -Compliance (Required) - Specimens shall-be-irradiated at a location in the E reactor?that duplicates as ! A-4
.. _ _ _______o
e Summary of Requirements San Onofre Unit 3 Program per ASTM E185-73 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. 5.1.2 Accelerated Irradiation Not Applicable specimens (optional) - Test specimens may be positioned at locations other than (5.1.1)
-for accelerated irradiation at-a rate exceeding. three times the-calculated maximum neutron flux at the inside wall of-the-reactor. vessel.
5.2 Flux Measurements - Compliance Provisions shall be made to measure the neutron fluence as follows: 5.2.1 Dosimeters with the-vessel wall specimens (5.1.1). 5.2.2 Where accelerated Compliance . irradiation specimens-are used
-(5.1.2), dosimeters with the -test specimens and : dosimeters either in .a- separate' flux monitor capsule-adjacent to the vessel wall or in a vessel wall A-5
Summary of Requirements San Onofre Unit 3 Program per ASTM E185-73 capsule. 5.3 Test Capsules - To prevent compliance deterioration of the surface of the specimens during test, the. specimens should be maintained in an inert environment within a corrosion-resistant capsule. 5.3 The temperature history of Cortpliance the specimens shall duplicate as. closely as possible the temperature experienced by the reactor vessel. 5.3 Surveillance capsules Compliance should be auf ficiently rigid to prevent damage to the capsules by coolant pressure or coolant flow thus hindering specimen v' removal or causing inadvertent deformation of the specimens. 5.3 Irradiated capsules must Compliance not be bouyant to preclude serious radiation exposure to personnel if under water handling is employed. 5.3 Consideration ehould be Compliance given to the --design of. the capsule and capsule attachments to permit insertion of replacement capsules into the reactor at a later time in the lifetime of the vessel. A-6
Susumary of Requirements San Onofre Unit 3 Program per ASTM E185-73 5.4 Specimen Withdrawal - A minimum surveillance program shall consist of three capsules for Case A and five capsules for Case B. It is recommended that cr.nsules be withdrawn as described in- Table 1. - (See Table 1 of ASTM E185-73.) i i 6.1 Radiation Environment - The neutron flux, - neutron energy 4 spectrum, and irradiation i temperature of surveillance
- specimens and the method of i determination shall be documented.
- 6.2 Neutron Flux Dosimeters -
! Flux dosimeters for a. l particillar program shall be , determined by referring to
, Method E 261.
I I END l A-7 i i e-- m - - , r--m-- -+ w '= r '#%4 ese-e .e--+ - , - , . - a+e, , es - + --yw w- 'e-e-e
i-Summary of Requiremerts San Onofre Unit 3 Program per ASTM E185-82 l 8.1 Temperature Environment -- Compliance The ma'ximum exposure temperature of the surveillance capsule materials shall be determined. If a discrepancy (>14 C or 25 F) occurs between the observed- and - the expcoted . capsule exposure temperataes, an analysis of the operating j conditions shall be conducted l to determine the magnitude and
- duration of these differences. ,
l 8.2 Neutron Irradiation Compliance Environment: l 1 8.2.1 The neutron flux density, neutron energy spectrum, and neutron fluence of the
- surveillance specimens and the r corresponding maximum values for the reactor vessel shall be 4
determined in accordance with j the guidelines in Guide E 482
- and Recommended Practice E 560.
4 8.2.2 The specific method of , determination shall be l determined and recorded using both a calculated spectrum and an assumed fission spectrum. 1 9.1 Tension Tests: Compliance- . 9.1.1 Method - Tension testing , shall be- conducted in accordance with Methods E 8 and o Recommended Practice'E 21. 9.1.2. Test Temperature:- 9.1.2.1 Unirradiated - The test . temperatures for each material 4 shall include room temperature,
- service temperature, and f one intermediate temperature to 4
A-8 1
+ y , w - w,-,-- 4 ._ t-e- ,em-r ---y.- -,m, si w4 + , ,p-- m ,e e- + + r v r.-wv - si-
Summary of Requirements San Onofre Unit 3 Program per ASTM c185 82 define the strength versus temperature relationship. 1 0.1.2.2 Irradiated - One Compliance specimen from each material shall be tested at a temperature in the vicinity of the upper end of the Charpy energy transition region. The remaining specimens from each material ahall be tested at the service temperature and the midtransition temperature. 9.1.3 Measurements - For both Compliance unirradiated and irradiated materials, dotarmine yield strength, tonalle strength, fracture load, fracture strength, fracture stress, total and uniform elongation, and reduction of area. 9.2 Charpy Tests: Compliance 9.2.1 Method - rpy tests shall be con ted in accordance with Het i E 23 and A370. 9.2.2 Test Temperattare: Compliance 9.2.2.1 Unirradiated - Test temperature for each material shall be selected to establish a full transition Mmporature curve. One specimon per test temperature may be used to define the overall shape of the curve. Additional t.sts should be performed in thn region A-9
, Summary of Requirements San Onofre Unit 3 Program l per ASTM E185 82 where the measuromants described in 9.2.3 are mado.
i
- 9.2.2.2 Irradiated . Specimens complianco for each material will 50 i testud at temperatures selected <
d to define the full energy , transition curve. Particular emphasis should be placed on defining the 41.J (30 ft-lb), 68-J (50 ft-lb), and 0.89.mm (35 mil) lateral expansion index temperatures and the upper sholf energy. 9.2.3 Measuromonts . For each compliance test specimen, measure the impact energy, lateral expansion, and percent shear fracture appearanco. From the unirradiated and irradiated transition temperature curves dotormine the 41.J (30 ft-lb), 6C.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 CurVos. 9.2.3.1 Obtain from the Compliance material qualification tect report the initial reference temperaturo (RTm) as defined in ASME Code, Section III, Subarticlo NB 230 for unirradiated materials. 9.3 Ilardness Tests (Optional) - Complianco A-10
Stummary of Requirements San Onofre Unit 3 Program per ASTM E185 82 Hardness tosts may be perf ormed Compliance on unirradiated and irradiated Charpy specimons. The measurements shall be taken in areas away from the fracturo zone or the edges of the specimons. The tests shall be conducted in accordance with Methods A 370. 9.4 Supplemental Tosts Not Applicablo (Optional) - If supplomontal fracturo toughness tests are conducted (in addition to tests conducted on tension and Charpy specimens as described in 6.1) the test proceduros shall be documented. 9.5 Calibration of Equipment - Complianco Procedures shall be employed assuring that tools, gages, recording instruments, and other measuring and testing devices are calibratoo and properly adjusted periodically to maintain accuracy within necessary limits. Whenever possible calibration shall be conducted with standards traceable to the National Bureau oS Standards. Calibration status shall be maintained in records traceable to the equipment. 10.1 Tension Test Data Complianco 10.1.1 Determine the amount of radiation strengthening by comparing unirradiated test results with irradiated test results at the temperaturo A-11
i summary of guirements San Onofre Unit 3 Program i per ASTM E185 82 j i specit.ied in 9.1.2. ; 10.1.2 The tensile strength ; data can be verified using the ; results from the hardness test (optional) described in 9.3. 10.2 Charpy Test Data: Compliance f 10.2.1 Determine the radiation - induced transition temperature shifts by measuring the difference in the 41-J (30-ft. I lb), 68-J (50 ft-lb), and 0.89 mm (35 mil) lateral expansion index temperatures before and after irradiation. The index , , temperatures shall be obtained from the average curves. 10.2.2 Determine the adjusted Compliance reference temperature by adding the shift corresponding to the 41-J- .(30 ft-lb) index determined in 10.2.1 to the - initial reference temperature
- obtained in 9.2.3.1. t I -+
...-_-...- --__. ---......___ --__ t L
i ~10.2.3 Determine the radiation compliance l- induced change in the upper shelf energy -(USE) f rom the
- measurements made before. and
, after irradiation using average ! value curves.. I
-10.2.4 -(Optional) Determine " Not Applicable "
l the radiation induced change in temperature- corresponding to 50% of .the upper ' shelf energy ; before - and af ter- irradiation Efrom average valuel curves. f A-12< L 4 p -n i s ,--en - , , e e, e-n . p- w , ,v,+- -,.g+ -,n a , ,p..,,,een -e+,-,,,, ~vw,en,,e,., n w w- v e,-w w-w ,-- p~%m-g,-----+ r n e- ;
t
\
l t { summary of Requirements San Onofre Unit 3 Program ! l per ASTN E185 82 i 10.3 Supplemental Test Data Not Applicable .; ! (optional) - If additional, !
; aupplemental tests are ;
- performed (9.4 ), the data shall ;
be recorded to supplement the _ ' 1 information from the tensile I and Charpy tests. t
................. ................. t i !
1 10.4 Retention of Test Compliance
- j. Specimens - It in recommended 4
that all broken test specimens be retained until- released by ..l the owner in the event that ! additional analyses dre j required to explain anomalous j results. 11.1 Where applicable, both SI i units and conventional units shall be reported. t [ ................. .................
- t. 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 4 of the plates or forgings and the welds. .
- 11.2.3 Location (s) of the peak vessel fluence.
11.2.4 Lead f actors. between the ! specimen fluence and the ' peak i vessel fluence-at the I.D. and- . I [ A-13
- - . an , - .n- --
.-....-e-. ,,,,,,,,~,,,,+.,,-.,--.,,--,.,--,,,,,n -a, - , , - , , . . . . , n .-+ , , . - - w ,
Summary of Requirements San Onofre Unit 3 Program per ASTM E185-82 the 1/4T locations. 11.2.5 Survoillanco Material complianco Selections
- 11.2.5.1 Description of all
] boltlino materials including chemical analysis, fabrication history, Charpy data, tensilo ,
- i. data, drop-weight data, and initial RTma 11.2.5.2 Describe the basis for 2
selection of survoillanco materials. i 11.3 Survo111anco Material compliance characterization: 11.3.1 Description of the survo111ance material including fabrication history, material source (heat or lot), and any differences betwoon the survoillance material history and that of the reactor vessel material history. 11.3.2 Location and orientation of the test specimens in tho l parent material. 11.3.3 Test Specimen Design: Compliance 11.3.3.1 Description of the test specimens (tonsion, Charpy, and-any other types of specimens used), neutron dosimoters, and temperaturo monitors. 11.3.3.2 Cortification of calibration of all equipment A-14
Summary of Requirements San Onofre Unit 3 Program per ASTM E185 82 and instruments used in conducting the tests. 11.4.1 Tonslon Tests Complianco 1
- 11.4.1.1 Trado namo and model of the testing machino, gripping devices, extensomotor, and recording devices used in the test.
11.4.1.2 Spood of testing and method of measuring tho
- controlling testing speed.
11.4.1.3 Completo stress-strain curvo (if a group of specimens .
- exhibits similar stress-strain curves, a typical curvo may be reported for the group).
11.4.1.4 Test Data from each specimen as follows: (1) Test temperaturo; (2) Yiold strength or yield point and method of measurement; ' (3) Tensilo strength; (4) Fracturo load, fracturo strength, and fracture stress; (5) Uniform alongation and method of measuromont; (6) Total olongation; (7) Roduction of area; and (8) Specimen identification. 11.4.2 Charpy Tests: Compliance 11.4.2.1 Trado namo and model of the testing machino, available hammer energy _ capacity and striking velocity, temperature conditioning and measuring devices, and a description of the procedure A-15
i i 1 Summary of Ingquirements san onofre Unit 3 Program j per ASTN E185 82 ! used in the inspection and
- calibration of the testing machine.
11.4.2.2 Test data from each l specimen as follows: (1) Temperature of test; , (2) Energy absorbed by the
- specimen in breaking, reported in joules (and foot-pound.
force); 4 (3) Fracture appearance; i (4) Lateral expansion; and j (5) Specimen identification. 1 11.4.2.3 Test data for each l material as follows: (1) Charpy 41.J (30 f t-lb), 68-
- J (50 ft-lb), and 0.89 mm (35 2 mil) lateral expansion index
] temperature of unirradiated
- material. and of each set of
- irradiated specimens, along with the corresponding
] temperature increases for these
, specimens; I (2) Upper shelf energy (USE)
{ absorbed before and after irradiation; 4 (3) Initial reference temperature; and ! (4) Adjusted reference
- temperature.
4 11.4.3 Hardness Tests Compliance (Optional): 11.4.3.1 Trade name and model of the testing machine. 2 11.4.3.2 Hardness data. a 4 11.4.4 Other Fracture Toughness Not. Applicable Tests: 4 A-16
Summary of Requirements San Onofre Unit 3 Program per ASTM E185-82 11.4.4.1 If additional tests Not Applicable are performed, tho test data shall be reported together with the proceduro used for conducting the tests and analysis of the data. 11.4.5 Temperature and Neutron Complianco Radiation Environment Hoasuromonts: 11.4.5.1 Temperaturo monitor results and an estimato of maximum capsule exposure temperaturo. 11.4.5.2 Neutron dosimotor measuromonts, analysis techniques, and calculated results including the followings (1) Houtron flux density, neutron energy spectrum, and neutron fluence in terms of neutrons por square metro and neutrons por square contimetro (>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 portinent nuclear data. 11.5 Application of Test Complianco Results: 11.5.1 Extrapolation of the neutron flux and fluence results to the surface and 1/4T locations of the reactor vossel A-17
Summary of Requirements San Onofre Unit 3 Program per ASTM E185-82 at the peak 11uence 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. Doviations - Deviations or Compliance anomalies in procedure from this practico shall be identified and described fully in the report. END A-18
i 1 APPENDIX B SONGS, UNIT 3: BASES FOR PIETE CllEMISTRY MEASUREMENTS
faya 90CWN SCvtsi June 8, 1992 3+NIQl 92 050 Kr. Steve Gosselin Southern California Edison 23 Parker Street Irvine, CA 92718 sms scTi vassEL P1. ATE QuDLICAL ANALYSIS SOURC18 Dear Mr. Gosselin The purpose or this letter is to provide background information pertaining to beltline material chemistry data for the plates which were used in the f abrication of the 8CNC8 Units 2 and 3 reactor vessel, ascently, differences were noted in the chemical analysis results reported for the SONGS 2 and 3 reactor vessel beltlins plates. A review has been performed which identified that these differences arose frcat the fact that different source information was used. The source information is noted below SONGS 2
'cMm . Lukans steel Mill analysis
'PSAR' and 'CEN=189'
- Chattanooga analyses dated 3/20/70 and 11/26/73 SCNos 3
*CKrR* . Lukans 8 teel Mill analysis
'FSAR* + Chattanooga analysis da,ted 1/25/74 and 3/20/74
'CEN.183 * . RFV surveillance program Chattanooga analyses dated 7/16/75 and 5/4/78 In order to respond to the plate chemistry questicuts of NRC Generic Letter 92 01, pertinent background information is provided followed by a specific recomendation.
First, the Lukens chemical analysis data was provided with the ofrR for ingormation only, whereas chattanooga analyses were used as the basis for licensing transmittals. This was done as a matter of C.E practice to maintain consistancy of results. (Lukens used both different equipenent and analysis at ndards, which could yield different reported chemical contents than the chattanooga laboratory.) ABB Combustion Engineering Nuclear Power WNsoa tvwee c + c. m e.os,ne .s nm w et , m p s ,,,, OCW O* M 008 W F,s(.% .%94Q 6.~owtdw uvm*W .m w m ct sear % wo DI
Mr. Stevo Gosselin Juse 8, 1932 8 MECH.32 050 Page 2 of 3 secondly, for both Sorca Cnit 2 and 3, chamical analyses were required by both the C 3 reactor pressure vessel specif.ication and C E surveillance program specification. Since these analyses were performed in two separate instances by the Chattanooga facility on the same material, it is ARE C R's position that the average of these two analyses would be seat representative of the plate chemical content. (Notes For both units, the 'C3 Analysis' value is an average of the chemical contents aquired in accordance with the vessel and surveillance program specification.) Therefore, the recousmanded chemical composition for both SONGS vessels is the average of the two Chattanooga chemical analyses, provided in Table 1, and titled 'C3 Analysis'. Should there be any additional questicas, please 'do not besitate to contact me at (202) 285 3463.
- sincerely, COMBUSTICat RNGIN3XRING, INC.
- 8. T. Byrne Supervisor, Reactor Vesse:. Integrity ST15/CD8 cds cct D. Pilawr (SCI)
B. Chang W. dahwiller C. Stewart M. Wade STB 060.WP e B2
Mr. Steve Gosselin June 8, 1992 8 MIDI 92 oso Page 3 cf 3 TABLE 1 l- U23 RV EILTLINE R20Zott PIATE COPPEA AND NICKEL CONI 1DIT l l Cu content (vt %) { l Plate Ni centant (wt %) l l No. C2fTA CE Analysis l F l CMI1L CE Analysis l 1 l Unit 2 t l l c sto4 1 0.11 c.itt l o.si - o.ss l l Ces4o4 2 0.12 l o.10 o.s1 0.s9 E l I c sao4-2 o.12 c.10 : 0.s2 o.ss i R R C s404-4 o.12 0.lo o .'s3 ll , o.s2 l I c s4o4 s i o.1: o.11 o.s3 l o.s4 l 8 c.c4o4 s o.12 0.10 0.54 l " o.ss i l Unit 3 l ] R c-sao2 1 o.os o.os l o.se o.se I" C I c sno2 2 o.04 I o.o* o.se ! o.s7 i a c sac 2 a o.os o.ns o.s7 o.s g I c sson 4 ; o.os l o.os o.se l o.ss l 9 c sson s o.o* l o . e4. o.s2 l l o.ss v 1 [csso2s o.os i o.os 1 o.ss I' o.s2 l 1 B-3
1 l APPENDIX C SONGS, UNIT 3: MCRs FOR BELTLINE '4ATERIALS (Proprietary)
APPENDIX D SONGS, UNIT 3: UNIRRADIATED Cyn DATA FOR PLATES AND WELDS
Table D 1 Charpy V. Notch Test Results For Unit 3 Plate C68021 (TL), MCR Data
$rtt Mtu itNP tuttC1 L4ftRAL f8ACT 10 it$f Imr&CI tre Aretas (f) (ftelb) (alt) (1)
I 1 40.00 T.00 5.00 0.00 2 40.00 4.00 4.00 0.00 3 40.00 5.03 4.00 0.00 4 10.00 29.00 20.00 10.00 5 10.00 23.00 17.00 10.00 4 10.00 18.00 14.00 5.00 F 40.00 34.00 21.00 15.00 8 40.00 2T.00 19.00 10.00 9 40.00 24.00 1T.00 5.00 10 80.00 43.00 34.00 25.00 11 80.00 55.00 45.00 30.00 12 80.00 54.00 44.00 30.00 13 100.00 50.00 37.00 25.00 14 100.00 52.00 40.00 21.00 15 100.00 59.00 45.00 30.00 16 160.00 79.00 60.00 80.00 17 160.00 79.00 63.00 80.00 18 212.00 95.00 TO.00 100.00 19 212.00 99.00 T2.00 100.00 20 160.00 84.00 62.00 30.00 21 212.00 100.00 24.00 100.00 D1
Table D 2 Charpy V Notch Test Results For Unit 3 Plate C6802 2 (TL), MCR Data SPEC 1 MEN TEMP EWtRCY 1.AftRAL FRACT 1D TF.ST 1MPACT IIP APPEAA (P) tit lbi le111 (tl 1 40.00 9.00 4.00 0.k i 2 .40.00 4.00 3.00 0.00 3 40.00 0.00 4.00 0.00 4 10.00 26.00 19.00 10.00
$ 10.00 14.00 11.00 S.00 4 10.00 20.00 24.00 10.00 7 40.00 32.00 16.00 15.00 0 40.00 40.00 30.00 30.00 9 40.00 $2.00 37.00 25.00 10 40.00 44.00 34.00 25.00 11 40.00 $2.00 38.00 30.00 12 60.00 $4.00 37.00 30.00 13 70.00 $$.00 30.00 30.00 14 78.00 17.00 39.00 3$.00 15 70.00 65.00 45.00 40.00 16 100.00 64.00 $0.00 40.00 17 100.00 77.00 $9.00 50.00 le 100.00 49.00 $4.00 40.00 19 160.00 114.00 77.00 90.00 20 160.00 110.00 15.00 90.00 21 140.00 104.00 7$.00 90.00 22 212.00 117.00 00.00 100.00 23 212.00 116.00 32.00 100.00 24 212.00 113.00 19.00 100.00 D-2
1 1 Table D.3 Charpy V. Notch Test Results For Unit 0 Plate C6802 3 (TL), MCR Data
$PECIMEN TEMP INESCY LATTRAL FRAC 7 10 7t37 IMPACT 82P APPEAR (Fl (flalb) (ell) (tl 1 40.00 0.00 4.00 0.00 2 40.00 1.00 3.00 0.00 3 40.00 9.00 J.00 0.00 4 10.00 20.00 20.00 10.00 $ 10.00 36.00 20.00 10.00 6 10.00 !$.00 11.00 5.00 1 40.00 31.00 27.00 15.00 0 40.00 20.00 22.00 10.00 9 40.00 35.00 26.00 15.00 to 60.00 35.00 26.s0 15.00 !! 60.00 49.00 34.00 2$.00 12 60.00 35.00 20.00 20.00 12 00.00 $7.00 47.00 30.00 14 00.00 $2.00 40.00 25.00 Il 00.00 40.00 46.00 40.00 16 100.00 19.00 40.00 40.00 11 100.00 70.00 54.00 10.00 le 100.00 42.00 44.00 40.00 19 160.00 100.00 11.00 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 14.00 100.00 22 212.00 109.00 10.00 100.00 *4 212.00 101.00 12.00 100.00 D.3
Table D-4 Charpy V Notch Test Red For Unit 3 Plate C6802 4 (TL), MCR Data APECIMEW TEMP E1stmCT IJTtmAL FRACT ID TEST INPhCT EIP APPEAR (F) (ftetbl (mill (t) 1 40.00 10.00 4.00 0.00 2 40.00 14.00 0.00 0.00 3 .40.00 10.00 4.00 0.00 4 10.00 25.00 10.00 10.00
$ 10.00 20.00 30.00 10.00 6 10.00 19.00 13.00 3.00 7 40.00 3$.00 30.00 20.00 0 40.00 39.00 32.00 20.00 9 40.00 $1.00 31.00 25.00 10 40.00 40.00 35.00 20.00 11 40.00 $4.00 39.00 25.00 12 40.00 49.00 34.00 20.00 13 10.00 16.00 33.00 $0.00 le 70.00 43.00 47.00 40.00 15 10.00 59.00 44.00 35.00 16 100.00 104.00 85.00 40.00 17 100.00 40.00 52.00 40.00 le 100.00 10.00 f4.00 40.00 19 160.00 124.00 00.00 93.00 20 160.00 112.00 11.00 10.00 21 180.00 104.00 10.00 10.00 22 213.00 110.00 10.00 100.00 23 212.00 111.00 01.00 100.00 24 212.00 115.00 11.00 100.00 D-t
Table D.5 Charpy V. Notch Test Results For Unit 3 Plate C6802 5 (TL), MCR Data sPtc1HtN TEMP $Nt90f 1ATERAL FRACT ID TEST 1MPACT IIP atPEAA tri (ft.lbi (s111 (t1 1 .40.00 9.00 4.00 0.00 2 40.00 10.00 5.00 0.00 3 .40.00 9.00 3.00 0.00 4 10.00 10.00 12.00 5.00 S 10.00 27.00 30.00 10.00 4 10.00 15.00 11.00 5.00 7 40.00 34.00 23.00 15.00 0 40.00 35.00 24.00 15.00 9 40.00 35.00 25.00 15 00 10 6n.00 39.00 26.00 !$.00 11 60.00 39.00 20.00 15.00 12 60.00 20.00 27.00 15.00 13 10.00 45.00 43.00 30.00 14 10.00 $7.00 40.00 30.00 1$ 10.00 $1.00 37.00 25.00 16 100.0C 66.00 47.00 30.00 17 100.00 10.00 49.00 35.00 10 100.00 79.60 56.00 40.00 19 160.00 110.00 10.00 100.00 20 160.00 114.00 15.00 100.00 21 140.00 109.00 65.00 10.00 22 312.00 119.00 70.00 100.00 23 212.00 110.00 72.00 100.00 24 212.00 117.00 74.00 100.00 D.5
Ta' ale D-6 Charpy V. Notch Test Results For Unit 3 Plate C6802 6 (TL). MCR Data 7 SFte! MEN TFMP twr1tCT LAftRAL FRACT ID TrST IMt4CT RIP AFFEAA (F) lit.lb) (ell) (t) 1 40.00 10.00 5.00 0.00 2 40.00 10.00 4.00 0.00 2 40.00 0.00 4.00 0.00 4 10.00 13.00 17.00 10.00 S 10.00 20.00 20.00 10.00 4 10.00 2$.00 10.00 10.00 7 40.00 34.00 16.00 15.00 0 40.00 43.00 34.00 20.00 9 40.00 11.00 26.00 15.00 10 70.00 50.00 39.00 2$.00 11 70.00 44.00 25.00 20.00 12 70.00 $0.00 45.00 30.00 13 00.00 52.00 40.00 25.00 14 00.00 $1.00 45.00 30.00 s 15 00.00 $3.00 41.00 25.00 16 100.00 $0.00 42.00 30.00 17 100.00 4$.00 51.00 10.00 to 100.00 19.00 46.00 40.00 19 160.00 96.00 72.00 93.00 20 160.00 90.00 49.00 10.00 21 160.00 01.00 45.00 #0.00 22 212.00 90.00 70.00 100.00 23 212.00 92.00 11.00 100.00 24 212.00 92.00 70.00 100.00 D6 \
Table D.7 Charpy V. Notch Test Results For Unit 3 Weld Scam 9 203 (Heat #9006>;, WMC Data SPECIMEN TP8'P ENERCT LATERAL PRACT ID TEST IMPACT IIP APPEAA (F) (ft.lb) (all) (1) 1 100.00 13.00 0.00 0.00 2 300.00 0.00 4.00 0.00 3 -100.00 13.00 S.00 0.00 4 40.00 24.00 , 15.00 $.00
$ 00.00 43.00 31 00 20.00 6 23.00 90.00 17.00 S.00 7 40.00 $3.00 36.00 25.00 0 40.00 49.00 $4.00 40.00 9 40.00 43.00 44.00 35.00 to 0.00 81.00 60.00 50.00 11 0.00 16.00 $2.00 40.00 12 0.00 97.00 67.00 60.00 13 40.00 120.00 $2.00 90.00 14 40.00 110.00 40.00 10.00 15 40.00 125.00 82.00 100.00 16 100.00 119.00 78.00 100.00
!? 100.00 117.00 78.00 100.00 10 100 00 124.00 03.00 100.00 19 160.00 123.00 82.00 100.00 20 160.00 121.00 41.00 100.00 21 160.00 133.00 82.00 100.00 D.7
Table D 8 Charpy V. Notch Test Results For Unit 3 Weld Seam 3 203 (11 eat #88114), FSAR Data seterntw Trxe tNtact 1.httRAX. FRAer ID TEST IMPACT tre UrtAA (r) (ft.lbi (mill (t) 1 304.00 13.00 7.00 0.f4 2 304.00 11.00 6.00 0.00 3 404.00 20.00 13.00 S.00 4 00.00 30.00 22.00 10.00 5 00.00 30.00 21.00 10.00 6 00.00 24.00 13.00 10.00 7 40.00 110.00 46.00 40.00 0 40.00 76.00 40.00 40.00 9 40.00 114.00 60.00 60.00 10 30.00 127.00 10.00 00.00 11 10.00 113.00 64.00 10.00 12 40.00 117.00 40.00 70.00 13 10.00 126.00 10.00 00.00 14 10.00 151.00 31.00 100.00 15 10.00 154.00 04.00 100.00 16 10.00 174.00 06.00 100.00 17 $0.00 163.00 05.00 100.00 10 $0.00 162.00 03.00 100.00 D-8
Tabic D 9 Charpy V Notch Test Results For Unit 3 Plate C68021 (TL), CE Baseline Data $PEC1 HEN TEMP ENEROY 1.hTTRAL FRACY ID TTST INFACT IIP APPEAR tr) (ft.1bl (mill til 252 40.00 13.00 12.00 0.00 232 0.00 14.00 12.0 0 10.00 26J 0.00 22.00 24.00 9.00 22P 40.00 10.)0 17.00 10.00 240 40.00 52.00 45.00 20.00 22K 00.00 25.00 25.00 20.00 261 00.00 57.00 30.00 40.00 23Y 100.00 42.00 40.00 30.00 2SM 100.00 74.00 60.00 40.00 24T 100.00 46.00 45.00 $0.00 2SE 120.00 05.00 73.00 $0.00 267 120.00 106.00 00.00 40.00 22A 160.00 61.00 40.00 60.00 221 160.00 43.00 50.00 70.00 25Y 160.00 113.00 01.00 90.00 23P 210.00 96.00 14.00 90.00 2SS 210.00 109.00 02.00 100.00 21R 250.00 40.00 11.00 100.00 22A 250.00 07.00 72.00 100.00 D-9
Table D-10 Charpy V. Notch Test Result For Unit 3 Plate C68021 (LT), CE Baseline Data SPECIMEN TEMP ENER07 1.hTERAL P1tA7 ID TE$T IMPACT EIP APPEAR tri (ft.1bl (mil) til 151 0.00 6 10 S.00 0.00 146 40.00 1$.00 13.00 10.00 127 40.00 16.00 15.00 10.00 110 e0.00 33.50 30.00 30.00 13H 80.00 39.30 34.00 30.00 14c 120.00 36.00 37.00 40.00 124 120.00 45.00 41.00 40.00 145 160.00 $1.00 47.00 40.00 13U 140.00 93.00 70.00 80.00 13E 210.00 66.00 42.00 70.00 14T 210.00 96.00 01.00 80.00 11L 2$0.00 90.00 00.00 100.00 11C 250.00 93.00 47.00 100.00 D 10
Table D.11 Charpy V. Notch Test Results For Unit 3 Surveillance % Id, CE Baseline Data SPECIMEN TEMP ENERCf lATERA1. FRACT 10 TEST IMPACT SIP AFFEAR (F) (ft.1bl (mill (t) 31Y 00.00 S.00 9.00 0.00 37c 00.00 31.00 19.00 30.00 33c 40.00 17.00 II.00 30.00 36M 40.00 36.00 31.00 30.00 36c 0.00 36.00 36.00 30.00 36T 0.00 4e.00 45.00 40.00 37: 40.00 Se.00 33.00 40.00 3A3 40.00 43.00 $6.00 40.00 337 80.00 73.00 65.00 30.00 34M 00.00 80.00 83.00 100.00 376 130.00 71.00 $$.00 80.00 33K 130.00 04.00 19.00 90.00 316 160.00 44.00 47.00 10.00 344 160.00 97.00 90.00 100.00 33R 310.00 80.00 85.00 90.00 31C 310.00 97.00 84.00 90.00 35M 350.00 71.00 69.00 100.00 373 350.00 78.00 73 00 100.00 348 150.00 04.00 83.00 100.00 D.11
Table D 12 Charpy V Notch Test Results For Unit 3 Plato CG802-1 (LT), MCR Data Test impact Latorrl Fracturo Temperature finergy Expansion Appearance ('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 20 17 10 40 31 23 10 60 33 25 15 60 34 25 15 60 35 24 15 80 50 39 20 80 52 40 25 80 50 30 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 D-12
- _ _ _ - _ - - - _ - = _ - _ - _ - _ _ _ - - - - - - - _ -
(4\ APPENDIX. E SONGS, UNIT 3: HAZ TEST RESULTS i
CE Baseline TestsD I ; sPEcInes tinP ErracY 1ATrnAL FRACT TO TWST IMPACT REP APPEAA (F) (it.lb) (mill (4) 47L 00.00 4.00 4.00 0.00 455 -80.00 4.00 4.00 0.00 42Y 40.00 30.00 26.00 10.00 436 .40.00 30.00 26.00 10.00 45J 0.00 30.00 25.00 20.00 4ST 0.00 44.00 37,00 30.00 42J 40.00 33.00 34.00 20.00 42K 40.00 35.00 32.00 20.00 42U 80.00 73.00 48.00- 80.00 454 80.00 '79.00 42.00 30.00 471 120.00 42.00 41.00 60.G0 47S 120.00 50.00 49.00 70.00 43C 340.00 41.00 42.00 00.00 43R 140.00 47.00 72.00 90.00 44K 210.00 57.00 57.00 70.00 444 210.00 105.00' 13.00 100.00 44A 250.00 43.00 46.00 100.00 42T 250.00 75.00 40.00 100.00 def 250.00 90.00 80.00 100.00 E-1
_ _ _ .- . _- - . . . _ _ . _ . . ~ . . _ _ . _ . _ _ . _ _ _.. f
- Westinghouse Capsule 97I23 -
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t ) i-Stac1 Map Tsw spracY 1ATsaAL tancT caARPY lanAD l, 10 Tsst 1MPact arr APPsAR : F1.USNc3 TEM. i_ (F) (ft lbt- (alll' (5)- ita/ cat) (F) i 441 75.00 9.00 0.00 5.00 0.000+10; $50.00 [ 42L 50.00 18.00 14.00 15.00 e.00s+10 '550.00
.to.00 4.00 5.00 0.00t+1e -- 550.00 45c 3.00 437 0.00 34.00 33.00 35.00 e.00s+10 550.00 0'- 444 35.00 35.00 - 37.00 45.00 e.00s+1e 550.00 -f
-+'
j- .. . ] 5 '.00 33.00 33.00 50.CJ .0.00e+10 .550.00 r. t. 43.00 44.00 75.00 a.CJe+10 '550.00 l , 46F 41.00 35.00 70.00 0.00t+18 550.00 i i ) 45.00 44.00- 80.00_-~8.00E+18 550.00-- J 43.00 41.00 100.00 0.005518. : 550.00 4.00 e4.00 48.00 100.00 0.00t+18 350.00 f 434 250.00 75.00 45.00 100.00 0.005+18 550.00 3 b' r A
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'E Battelle Columbus Additional Unitradiated HAZ Results!31 spac1Msw Tzwe' rasact 1AfrRAL . FRACT' 1D TEST - IMP AcT - SIP - APP 5kR -
- tr) tit.1bl t ail) .- (t) 351 130.00 7.50 S.00 - 11.00 a
383 - 120.00 9 50 3.20 9.30 f 1811 40.00 23.50- -13.00 12.40 1812 40.00 26.00 15.60 17.00 ! _1817 40.00 27.50 21.00 13.10 - i $ 3s4 40.00 57.00 36.30 - 31.10 3
<- -385 0.00 39.50' 31.00' 49.30 ~ -
g_ 43.20 -$$.40 E1 3 -1st 0.00 44.50 -
. late I 20.00 41.50 46.40 $2.00
{ 185- 20.00 -74.00 49.00 54.70 2 183 20.00 42.00 _$0.40 54.30 E 1810 - 40.00- 93.00 63.00 63.10 l 4
-1818 40.00- 99.00 64.00 73.40' l 1813 40.00 105.00 64.40' ~72.90
< 154- 80.00 - 113.00 .72.40 100.00 1 , ' 184 00.00 -115.00 65.00- 100.00 184 120.00 122.00 83.40 - 100.00-1814 l120.00 -160.00 '94.60- 100.00 - 4. 187 160.00 120.00 87.30 100.00-
!!s2- 160.00- 153.00- .82.20 100.00
- 384 210.00 110.00 - 70.80 100.00' 1815 ' 210.00 132.00 - 75.80 100.00.-
5 4 4 [ E : e
- y .- ,--- . - . , , , . , , _..r,w.. [, ., d , - , , , - ...o -ey-
i APPENDIX F SONGS, UNIT 3: IRRADIATED Cw DATA FROM CAPSULE 97 e
. . . - . . - . -. .~. - --. . - . . .- .. - . . . . ~ , . . . . . - - -
4 Table F-1 Charpy V Notch Test Results For Unit 3 Plate C68021 (LT) 2 2 Irradiated (f = 8 'x 10 ' n/cm )' SPECIMEN TEMP '*NERGY LATRRA1. FRACT ID TEST IMPACT EXP APPBAA (F) {ft-lb) '(mil)- (%) {' , 147 50.00 6.00 5.^0 S.00 I . 153- 7$.00 22.00 15.00 15.00
- ISK 100.00 29.00 24.00- 25.00 113 125.00 35.00 32.00 '
30.00 . i
}
14Y 150.00 32.00 26.00 30.00 155 165.00 45.00 43.00 45.00 1 -14A -175.00 30.00 27.00 - 45.00 14E 200.00 46.00 .46.00 55.00 11T 225.00 ~ 75.00' ~66.00 00.00 12K 250.00 45.00- 48.00- 80.00 12L 250.00 40.00 46.00 . 95.00
~
14M 275.00 90.00 76.00 100.00. l. l-l t I I F-1:
^
- , _ , . . . , . _.4-. _ , - . - .,_,m. . . _ . . . ~ . , . . . ,
Table F-2 Charpy V-Notch Test Results For Unit 3 Plate C68021 (TL) 2 Irradiated (f = 8 x 10
- n/cm )
SPECIMEN TEMP ENERGY LATERAL FRACT ID TtsT IMP At"r EXP APPEAR (r) (ft-lb) (mil) (t) 250 0.00 19.00 18.00 10.00 23K 25.00 16.00 11.00 10.00 21A 50.00 9.00 12.00 10.00 23L 75.00 21.00 20.00 15.00 22B 100.00 25.00 25.00 20.00 25J 115.00 55.00 48.00 45.00 25L 130.00 50.00 44.00 50.00 247 350.00 33.00 33.00 50.00 223 165.00 36.*0 37.00- 65.00 25C 200.00 $2.00 73.00 100.00 4 245 225.00 $2.00 59.00 100.00 23M 250.00 73.00 77.00 100.00 i T F-2
-. . .. - . . - - -- . - . . . . . = - . . . . - - .. ._- - . ...
v m Table F.3 Charpy V Notch Test Results For Ur.it 3 Surveillance Weld Irradiated (f = 8 x 10** n/cmD 4 . t 1 d.
- j. SPECIMEN -TEMP ENERCY 1ATERAL FitACT.
! ID TEST IMPACT IIP APPEAR (F). (ft.lb) (mil) (t) 3 363 50.00 23.00 20.00 ' 15.00 33L 25.00 27.00 25.00 20.00 j 31D 0.00 S.00 6.00 - 5.00 4
4 375 10.00 42.00 34.00 60.00 367 25.00 42.00 44.00. 65.00
- 1 331 50.00 44.00 44.00. 70.00 37U 60.00- 61.00 57.00 '95.00:
3 371 90.00 65.6s 59.00 .93.00 365 105.00 47.00 -60.00 100.00 l 4 34P 150.00 75.00 13.00- ' 100.00
-330 190.00 77.00 76.00 100.00 a
377 225.00 63.00 -50.00 100.00 R i t 5 F-3 ' j e
'I
. 3
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