ML20069Q279
| ML20069Q279 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 05/19/1994 |
| From: | ATI, SARTREX CORP. |
| To: | |
| Shared Package | |
| ML19304C292 | List: |
| References | |
| GL-92-01, GL-92-1, NUDOCS 9406270321 | |
| Download: ML20069Q279 (184) | |
Text
{{#Wiki_filter:. - . .. . - ..-._ ._ _- _ . - - . - - . i i i i, Attachment D. .
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i San Onofre Nuclear Generating Station, Unit 2 , Response to Generic Letter 92-01 r Revision 2 May 19,1994 ! l Prepared by: 1 ATI Consulting j ' San Ramon, CA and
; Sartrex Corporation l Rockville, MD l l <
1 Prepared for: $ Southern California Edison Irvine, CA
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(' 940627o321 940622 PDR ADOCK 0500o361 .l P
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I CONTENTS Section Pace i 1 INTRODUC'ITON 1-1 2 REACTOR PRESSURE VESSEL SURVEILLANCE 2-1 PROGRAM-COMPLIANCE WITH APPENDIX H 3 FRACTURE MECHANICS 3-1 3.1 COMPLIANCE WITH APPENDIX G 3-1 3.2 BELTLINE MATERIALS IN SONGS, UNIT 2 3-1 3.2.1 Location 3-1 3.2.2 Heat Trennent 3-1 3.2.3 Key Residual and Alloying Element Contents 3-2 3.3 FRACTURE TOUGHNESS RELATED DATA 3-3 3.3.1 Bettline Plate Material 3-3 3.3.2 Beltline Welds 3-4 4 ISSUES RELATED TO GENERIC I.ETTER 88-11 4-1 4.1 VESSEL TEMPERATUREDURING OPERATION 4-1 4.2 APPUCABillTY OF SURVELLLANCE 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 t e
1 l I CONTENTS (cont'd) 1 Section Page APPENDIX A SONGS, UNIT 2: EVALUATION OF COMPLIANCE A-1 WITH ASTM E185-73 AND E185-82 l' APPENDIX B SONGS, UNIT 2: BASES FOR PLATE CHEMISTRY B-1 MEASUREMENTS (Proprietary) APPENDIX C SONGS, UNIT 2: BASES FOR WELD CHEMISTRY C-1 l MEASUREMENTS (Proprietary) APPENDIX D SONGS UNIT 2: WMCs FOR BELTLINE D-1 MATERIALS (Proprietary) APPENDIX E SONGS UNIT 2: MCRs FOR BELTLINE E-1 MATERIALS (Proprietary) APPENDIX F SONGS, UNIT 2: UNIRRADIATED Cvu DATA F-1 FOR PLATES AND WELDS APPENDIX G SONGS, UNIT 2: HAZ TEST RESULTS G-1 APPENDIX H SONGS, UNIT 2: IRRADIATED Cvn DATA FROM H-1 CAPSULE 97 P 4 e
ILLUSTRATIONS Ficure Pace s 3-1 SONGS, Unit 2: Location and Identification of 3-6 Beltline Plates and Welds 3-2 SONGS, Unit 2: Data and Least Squares Fit Curve 3-7 for Cvu v ersus Temperature, Plate C6404-1, TL I Orientation, MCR Data 3-3 SONGS, Unit 2: Data and Least Squares Fit Curve for 3-8 Cvu versus Temperature, Plate C6404-2, TL Orientation, MCR Data 3-4 SONGS, Unit 2: Data and Least Squares Fit Curve for 3-9 Cvu versus Temperature, Plate C6404-3, TL Orientation, MCR Data 3-5 SONGS, Unit 2: Data and Least Squares Fit Curve for 3-10 Cvu versus Temperature, Plate C6404-4, TL Orientation, MCR Data i 3-6 SONGS, Unit 2: Data and Izast Squares Fit Curve for 3-11 Cvu versus Temperature, Plate C6404-5, TL Orientation,
' MCR Data 1
3-7 SONGS, Unit 2: Data and least Squares Fit Curve for 3-12 Cvu versus Temperature, Plate C6404-6, TL Orientation, MCR Data a 3-8 SONGS, Unit 2: Data and least Squares Fit Curve for 3-13 l Cvu versus Temperature, Plate C6404-2, TL Orientation, Surveillance Baseline Data 3-9 SONGS, Unit 2: Data and Ieast Squares Fit Curve for 3-14 Cvu versus Temperature, Plate C6404-2, TL Orientation, Combined MCR and Surveillance Baseline Data t* ). t-a
ILLUSTRATIONS (cont'd) Figure Pace 3-10 SONGS, Unit 2: Data and Izast Squares Fit Curve for 3-15 l
.I Cvu versus Temperature, Plate C6404-2, LT Orientation, Surveillance Baseline Data 1
3-11 SONGS, Unit 2: Comparison ofleast Squares Fit Cvu versus 3-16 l Temperature Curve for the Surveillance Plate with MCR Data for , Plate C6404-2, LT Orientation ,i 3-12 SONGS, Unit 2: Data and Least Squares Fit Curve for 3-17 ) Cvu versus Temperature, Weld 9-203, WMC Data 1 3-13 SONGS, Unit 2: Data and Least Squares Fit Curve for 3-18 Cvu versus Temperature, Surveillance Weld, Surveillance l Baseline Data l l 1 4-1 SONGS, Unit 2: Comparison of the least Squares Fit for the 4-4 ! [ Unitradiated Baseline Data with the Irradiated Cvu Data and Least Squares Fit for the Data from Capsule 97, Plate ; C6404-2, LT Orientation ' 4-2 SONGS, Unit 2: Comparison of the least Squares Fit for the 4-5 Combined MCR and Unirradiated Baseline Data with the Irradiated l Cvu Data and Irast Squares Fit for the Data from Capsule 97, Plate C6404-2, TL Orientation i f I -l 4-3 SONGS, Unit 2: Comparison of the Izast Squares Fit for the - 4-6
, Unitradiated Baseline Data with the Irradiated Cyu Data l and Izast Squares Fit for the Data from Capsule 97, Surveillance Weld :
1 1 i l 1 l [ , l R.
TABLES Table Page 3.1 SONGS, Unit 2: Compliance with 10CFR50, Appendix G 3-19 3.2 SONGS, Unit 2: Plate and Corresponding Heat Numbers 3-21 ' for the Beltline Plates 3.3 SONGS, Unit 2: Weld Wire and Flux Combinations 3-22 for Beltline Suneillance Welds 3.4 SONGS, Unit 2: Key Residual and Alloying Element Contents for 3-23 Beltline Plates 3.5 SONGS, Unit 2: Key Residual and Alloying Element Contents for 3-24 Beltline Welds 3.6 SONGS, Unit 2: Beltline Plate Material Unitradiated 3-25 Fracture Toughness Tests Results Summary, TL Orientation s 3.7 SONGS, Unit 2: Charpy Absorbed Energy Values at 10 F 3-26 , for Weld Seams 2-203 A, B, and C, and 8-203 I 3.8 SONGS, Unit 2: Beltline Weld Material Unirradiated 3-27 Fracture Toughness Tests Results Summary l
- l 4.1 SONGS, Unit 2
- Sun'eillance Capsule Shift Results 4-7 4.2 SONGS, Unit 2: ART Estimates at the Inner Surface 4-8 Location for Beltline Materials on 12/16/91 and at 32 EFPY f 4.3 SONGS, Unit 2: Surveillance Cspsule Upper Shelf Results 4-9 l l
4.4 SONGS, Unit 2: Upper Shelf Estimates at the Quarter-Thickness 4-10 l Location for Beltline Materials on 12/16/91 and at 32 EFPY l h s e
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Section 1 INTRODUCTION l The Nuclear Regulatory Commission (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 2. It identified additional information needed to resolve the following issues: (1) inconsistencies noted in copper (Cu) and nickel (Ni) contents for beltline Weld 9-203 and the surveillance weld, (2) locating material certification reports to confirm beltline weld properties, and (3) verifying the fluence at Weld 8-203. Revision 1 of this report (dated January 22,1993) incorporated additional materials data obtained from the SONGS, Unit 2 Nuclear Steam Supply System (NSSS) vendor, ABB-Combustion Engineering (ABB-CE), and the results of calculations performed by Southern California Edison l 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: (1) the beltline weld properties had been confirmed with the exception of beltline Welds 8-203 and 2-203 A, B, and C, and (2) additional information would be required to confirm heat numbers for the surveillance weld material and Welds 2-203 A, B, and C. In previous versions of this report the initial RTuor for the vessel beltline material with the highest end oflife adjusted reference temperature (i.e., the plate material used in the surveillance program) was determined using a combined data set obtained from the materials certification I ieport (MCR) and the baseline surveillance program. In Revision 2, the initial RTwor 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 RTuor, 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 rnanufacturer to assess the toughness properties at the time of vessel fabrication. This MCR data thus established the initial RTwor by satisfying paragraph NB-g 2331(a)(3) of the ASME Code, Section III. This change also was made so that this initial RTwor is defined in a manner consistent with that for other beltline materials where surveillance baseline I data were not available. Crristent with the previous revisions of this report, the combined set of MCR and surveillance om 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. - This revision (Revision 2) incorporates additional materials data and infarmation obtained from the SONGS, Unit 2 NSSS vendor, ABB-CE. These data provide: (1) the L:st number, chemistry and Charpy data for Welds 2-203 A, B, and C, (2) the weld wire and flux combinations, chemistry, and Charpy data for Weld 8-203, and (3) the weld wire and flux combinations for the surveillance weld. Based on a review of the information supplied by ABB-CE, the chemistry and 1-1
[
1 Charpy energies have been confirmed for the materials in the SONGS, Unit 2 pressure vessel beltline, and the response to GL 92-01 is now complete.
' Section 2 of this report addresses compliance with 10 CFR Part 50 (10CFR50), Appendix H, for the surveillance program at SONGS, Unit 2. Compliance with 10CFR50, Appendix G, is l 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 2, reactor vessel. Section 4 addresses embrittlement effects, including irradiation temperature and adjusted reference temperature for evaluation of the beltline materials relative to GL 88-11 and 10CFR50.61.
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Section 2 REACTOR PRESSURE VESSEL SURVEILLANCE PROGRAM i COMPL!ANCE WITH APPENDIX H l The American Society of Mechanical Engineers (ASME) Code of record for the SONGS, Unit 2, 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, tli surveillance program for SONGS, Unit 2, 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 requirements were satisfied for the surveillance program y 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). As stated in the SONGS, Units 2 and 3 Final Safety Analysis Report (FSAR), Appendix H, requirements were met (with one exception) through compliance with ASTM E185-73. The one 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 tl.e beltline region (as they did for all ABB-CE NSSS-designed vessels), and this approach violated the requirements in the early 1970's version of 10CFR50, Appendix H. NRC reviewed a ABB-CE Topical Report (CENPD-155-P, C-E Procedure for the Desien. Fabrication. Installation. and Inspection of Surveillance Holder
} Assemblig) 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 insenion 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. f i I 2-1 hI e
The details of the SONGS, Unit 2, surveillance program have been described in the FSAR and subsequent surveillance program testing reports, baseline DI and irradiated.t2j The first capsule 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 (Cys) HAZ data. NRC has been involved in making this change to E185 throogh ASTM standards participation. Because of this forthcoming change to ASTM E185, this report does not evaluate HAZ results for SONGS, Unit 2; however, the raw data from prior HAZ testing on the SONGS, Unit 2, beltline material has been reported previously,n 23 and is I provided for reference in a subseques action of this report. -la I. i I, s
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I i l Section 3 ; FRACTURE MECllANICS l 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 2, reactor pressure vessel beltline region. The infonnation presented in this section has been obtained from the materials certification reports (MCRs), welding materials certifications (WMCs), the FSAR for SONGS, Unit 2, and from additional information supplied by ABB-CE to prepare this response. In some instances, additional information. was obtained from the unirradiated baseline surveillance material
; report,IU and the irradiated material in the 97 location surveillance capsule (Capsule 97), which j l was removed from Unit 2 et the end of the third fuel cycle.r2j j l
l 3.1 COMPLIANCE WITH APPENDIX G The materials in the beltline region of SONGS, Unit 2, comply with the requirements of
- i. Appendix G,10CFR50. A summary of compliance with 10CFR50, Appendix G, as specified in the FSAR for SONGS, Units 2 and 3, and updated during preparation of this report, are 1 listed in Table 3.1.
1 I 3.2 BELTLINE MATERIALS IN SONGS, UNIT 2 3.2.1 Location Figure 3-1 is a representation of the SONGS, Unit 2, reactor pressure vessel, and identifies the plates and welds and their location in the beltline region. t 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 and the surveillance weld. 3.2.2 Heat Treatment The heat treatment for the plate materials consisted of austenitization at 1575 50'F for 4 hours; water quenched and tempered at 1225125'F for 4 hours. For ASME Code e qualification, the plates were stress relieved at 1150125"F for 40 hours and then were furnace 4 cooled to 600 F at a rate of 100'F/hr. The actual time at temperature for a specific weld or a b.( .
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plate in the vessel depended upon the sequence of vessel fabrication; intermediate and final stress relief times were selected such that the total did not exceed 40 hours for any particular portion of the vessel. Longitudinal weld seams would see stress relief times near the 40 hour 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 an identical heat treatment as the actual reactor vessel. The surveillance weldment received a final 42-hour and 15-minute stress relief at 1100*F to 1150 F. 3.2.3 Kev Residual and Allovinn Element Contents 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 are presented , in Appendix B. A second set of data is included for Plate C6404-2. This set was obtained from broken surveillance specimens when the first irradiated surveillance capsule from Unit 2 was tested.121 Table 3.5 contains the Cu, Ni, P, and S contents for the beltline welds. The source documents for the information in Table 3.5 are presented in Appendix C. Additional information from the WMCs for Welds 3-203 A, B, C,8-203, and 9-203 is presented in Appendix D. Because Ni was not measured for Weld Seam 8-203, a value of 1.0 wt% has been assumed (see Regulatory Guide 1.99, Rev. 2). Two 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!O, while the second was obtained from a broken Charpy specimen from Capsule 97t2), i 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. l 3.3 FRACTURE TOUGHNESS RELATED DATA This section presents the results from the Cvu tests and summarizes the upper shelf energies (USEs) and the results from the drop weight nil ductility temperature (NDT) tests for the ! unirradiated beltline plate and weld materials in SONGS, Unit 2. The unirradiated reference j temperature (RTum) values were determined from the Cyu and NDT test results in accordance with the most recent version of ASME Section III, NB-2331. The USEs were determined using the definition specified in ASTM E185-94 (to be issued). The data included in the USE determination were the Cvu values for those tests (at least 3) where the percent shear on the fracture surfaces was equal to and greater than 95%. i .( 3-2 l i
t i The fracture toughness data for the plates were obtained from the MCRs (see Appendix E of this report) and baseline surveillance program.I'l The source documents for Welds 2-203 A, B, C,3-203 A, B, C,8-203, and 9-203 are presented in Appendix D of this report. The data for the surveillance weld were 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 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 E185-94 will not require HAZ material to be part of the l surveillance program. The raw Cm data for the past HAZ testing are attached in Appendix G of this report. l 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 C6404-2, i which was included in the surveillance program. Because the surveillance program for SONGS, l Unit 2, also contains longitudinally (LT) oriented specimens, the unirradiated Cw data are presented for completeness for the LT orientation. 4 The transverse Cm data as a function of test temperature for beltline Plate numbers C6404-1,
-2, -3, -4, -5, and -6 are presented in Figures 3-2 through 3-7, respectively. For convenience, :
g an average curve through the data is also shown in each figure. The average curves were I determined using a least squares fit to the data and a hyperbolic tangent functional form, where the lower shelf was fixed at 2.2 ft-lb and the upper shelf was fixed at the value determined using the drinition in ASTM E185-94 for specimens having fracture surfaces with 95% and l greater shew. For convenience, the figures also indicate the values of NDT, USE, the temperature at which a minimum Cm equal to 50 ft-lb (T @ 50 ft-lb) is achieved consistent with the applicable method of ASME, Section III, NB-2331, and RTor. As part of the l surveillance program, additional Cm versus temperature data were generated for Plate C6404-t 2;I'l hese data are presented in Figure 3-8 along with a least squares fit curve. The data obtained when the plate material was purchased (Figure 3-3) and the surveillance l 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 fcr the irradiated surveillance tests (see Section 4). Table 3.6 is a summary of the unirradiated NDT, RTor, and USE values for the TL orientation ) for each of the beltline plates in SONGS, Unit 2. The NDT for Plate C6404-2 also was p- determined twice. One value was measured when the material was purchased (-20'F), while
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the second value was determined from the unitradiated baseline tests (+i0"F). The value measured when the plate was p-bced (i.e., the MCR data) is listed in Table 3.6. The methods used to determine RTer from the NDT and Cm data also are identified in Table 3.6. The method of either NB-2331 (a)(2) or NB-2331 (a)(3) was used to determine RTer for the plates. Figure 3-10 shows the data and least squares fit line for the LT orientation for surveillance Plate C6404-2.m pigure 3-11 shows a enmparien of the best fit line for the LT orientation for -l the surveillance plate (see Figtse 3-10) with the data reported in the MCR for the LT
- orientation for Plate C6404-2. The information in Figure 3-11 indicates that the data for the I LT orientation in Plate C6404-2 from the MCRs produce essentially the same Cw versus ,
temperature relationship as was obtained for the LT orientation surveillance plate material. l Therefore, the baselinc surveillance LT curve fit can be used to assess shift and upper shelf I toughness changes. 3.3.2 Bettline Welds ' t A full Cu versus temperature curve was obtained for the material in Weld Seam 9-203, and ; j the data points and least squares hyperbolic tangent fit through the data are presented in Figure 3-12. The materials in the remaining beltline weld seams were tested to obtain three Cm data
', points at 10 F. The resubs from these tests are presented in Table 3.7. Figure 3-13 presents the Cu data and least squares hyperbolic iangent curve fit for the surveillance weld material.
A comparison ofthe C,w w.J curves for beltline Weld 9-203 and the surveillance l weld in Figures 3-12 and 3-13, revdvely, show that the impact energies as a function of temperature are essentially the same forboth sets of data. Therefore, the baseline surveillance curve fit can be used to assess shift and upper shelf toughness changes. ; i i Table 3.8 presents a summary of the unitradiated NDT, RTwr, and USE values for each of the beltline welds in SONGS, Unit 2. For Welds 3-203 A, B, C and 9-203, available Cu data l indicate that there is a minimum of 50 ft-lb absorbed energy at 60*F above NDT and, i consequently, RTer equals NDT. For Welds 2-203 A, B, C, the available Cu data are 70'F i above NDT; however, since the data all have absorbed energies greater than 100 ft-lb, RTer l l was taken as equal to NDT because it is unlikely that the absorbed energy would be less than 50 ft-lb at 0*F whenitis in enoess of100 ft-lb at 10'F. Since no NDT data are available for Weld 8-203, the initialRTer was taken as the generic value of-56'F for ABB-CE fabricated i vessels (see 10CFR50.61). The USEs shown in Table 3.8 for Weld 9-203 and the surveillance weld were obtained by z.veraging the test results where 95% shear or greater was exhibited. The USEs for Welds 3-203 A, B, C and 8-203 were obtained from the data in Table 3.7 by averaging the three Cw data points obtained at 10*F for each of the listed welds. The USEs for Welds 2-203 A, B, C ' 3-4 t
- . i
- +
2 were obtained from the data in Table 3.7 by averaging the nine Cm data points obtained at 0 i and 10 F. l-l0 a (. I! 1 7- >= 3-5 b
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- f. REACTOR VESSEL BELTLINE MATERIALS NOT SHOWN stdTERMEDI ATE SHELL WE LD SEAM NO. 2-203C I LOWER SHELL Q~ -
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WELO SEAM NO. 3-2038 / % WELD SEAM NO. 3-203C PLATE NO. C-6404-5
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30" ID OUTLET INLET NOZZLE NOZZLE 3 N ~f UPPER TO INTERMEDIATE i / j SHELL GIRTH SE Fp INTERMEDIATE SHELL
- WELD NO.8-203 p LONGITUDINAL WELD SEAM NO. 2-203B
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INTERMEDIATE SHELL PLATE NO. C 64041 " p INTERMEDIATE SHELL w 1 PLATE NO.C 6404 2 j EAM O.2-20 A ' E DN 9 203 INTERMEDIATE SHELL PLATE NO. C 6434 3 LOWER SHELL PLATE
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LONGITUDIN AL WELD SEAM NO. 3-203A ~~~~~"' N , a *
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v f Figure 3-1. SONGS, Unit 2: 1.oCation and Identification of Beltline Plates and Welds.
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l l l 200 = 1 San, Onofre Unit 2 MCR Data Material: Plate No. C6404-1 A53381 6 - 150 t US$ = 119 ft- bs
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i NDj = -30 'F i j - T @ 50 ft-lbs a 80 'F 2 . RTodt = 20 *F 8 u. l > i 100 c ~ , uJ i Z Oi 6 h .
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O 50 = 0 Measured g j , OO , Calculated , 0 t
-200 -100 0 100 200 300 400 500 Temperature in Degrees F l
Figure 3-2. SONGS, Unit 2: Data and least Squares Fit Curve for Cm versus ! Temperature, Plate C6404-1, TL Orientation, MCR Data. -l ( i 37 l l
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l I 1 1 200 San Onofre Unit 2 MCR Data Mat'erial : Plate No. C6404-2, A533B1 ! 1 i
- Orldntation: TL 150 = U- E E N D' t +
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NDT = -20 *F T @ So ft lbs = 80 8F j - RTridt = 20 SF O T ~ O E j > E 100 = 3 E O , i - l au ' z - O7 0 So = O Measured ,
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Calculated , I 1 O ) .i o
-200 -100 0 100 200 300 400 500 Temperature in Degrees F L Figure 3-3. SONGS, Unit 2: Data and Least Squares Fit Curve for Cm versus Temperature, Plate C6404-2, TL Orientation, MCR Data.
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1 i l k 200 Sar} Onofre Urtit 2
. MCR Data i
Ma(erial: Plate C6404-3, A53381
' Orientation: TL * * *
- 150 =
USiE~E 99 ft:Ib5
- NDT = -20 *F m T 8 50 ft-lbs t= 80 8F
$ RT$dt = 20 'F g =
E e 100 = 1 t i C .
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easurM 50 = -- l - Calculated l
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. N. . . e .... e.... , ...., ....,. .... r.
[ o 0 100 200 300 400 500
-200 -100 Temperature in Degrees F L Figure 3-4. SONGS, Unit 2: Data and Ie,ast Squares Fit Curve for Cm versus Temp imu, Plate C6404-3, TL Orientation, MCR Data.
l 3-9 i L. {
I , 200 San Onofre Unit 2 MCR Data ' Mst'erial: Plate C6404-4, A533B1
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150 = USE = 104 ft-:bs NDj = -10 'F j . T @ 50 ft-lbs ,= 80 'F 3 . RTodt = 20 'F u.
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100 - I> c .
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O t O 50 = g O O Measured ; h- .
" Calculated i- ,
- --=m 1l e e E i l' s A R A i R R R e l' R 3 m a l' e e a e l R e 3 a I
-200 -100 o 100 200 soo 400 500 Temperature in Degrees F Figure 3-5. SONGS, Unit 2: Data and Least Squares Fit Curve for C versus .
Temperature, Plate C6404-4, TL Orien'.ation, MCR Data. l
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I i 6 200 . . ,. ,
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San Onoft,o Unit 2 l l l l i MCR Datd l l l l l l Material: Plate C640445, SA5338 '1 l l l
, i . .
Orientatio,n: TL i . . . t l l . t i 150 - U S E- =- 1 1 8 - f t -I b s - - - + - - - - - - i- - - - - - - - - - .- * - - - - - - - - I- - - - - - - - - - <f--------- 0 4 NDT = -2,0F . , ', ', '. , T@ 50 ft-Jbs = 70F l l l l l RTndt = 30F l l ,' l l m , , , , . . D s so e n
?
w u,, ., i i i o .
. ., t
, , , .i . ,
i
, e .
8 , . , j 2 100 --------'--------'--------'------2.,--------'-------d,--------- e m - l l l l l l ! f; z l l l l l t > , i o ' ' O ', i i
-. i i o e i
1 . . . I o , f I i 1
.O . . , , ,
e 50 ---------l---------t,--------l---------i---------l----------l--------- I , 4
- , t, , , 4, 8 .
, l , . , ,
,8 , ,I ,t ,
, , . I t .
O -- - ' - -- ' - '--- '-- '- ' - ,
-200 -100 0 100 200 300 400 500 I Ternperature in Degrees F l--
Figure 3-6. SONGS, Unit 2: Data and Least Squares Fit Curve for Cm versus F Temperature, Plate C6404-5, TL Orientation, MCR Data, i.
.(-
3-11 6- 4 a
200 = , San Onofre Unit 2 MCRDate. - Mater!ial: Plate C6404-6 !A533B1 Orien'jatiom T1. ' 150
- --.USE j:;; 12(.ft-lb a
~
NDT b -10 V e T @ h fi-lbs = .50 V g - RTnd = -10 'F k = I $ .
@ 100 -
e , c . su Z .
'O > ~
O
. 8 o
50 = l - o Measured O Calculated i l 8
.r .... u.... t ....o .-. . .e .... i j o
-200 -100 0 100 200 300- 400 500 Temperature in Degrees F Figure 3-7. SONGS, Unit .2: Data sad I. east Squares Fat Curve for Cm versus T-:=y=-' --;Plaae C6404 6, TL Ori~adian. MCR Data. .
'~ 3-12 Y-
J L 200 , , 9 , 1
. . ,l .,
. . . . i t . , .
] 150 --------l---------l---------l--------f,--------f--------l---------
, 1 - 0.0 .' .' .'g t . . , , t o
m . . , o;. . . o.,
- u. s. D
, .i . ,
t 9 100 ------- '------ a------- s- ----- 2------- '------- '-------- g l : sad onotre unit'2 f; uJ l l D Sur eBance Pro 6 ram
. z l l , Material: Plate No. C6404-2.'SA533B-1 g
. 4w- ---- g i. .
1 l l USE = 12S ft-iljs l
.i NOT.
= 100 .i
. . . i , '
50
------- .--------.---- ---4.---
. l .
----+.-------
. .i i
I J , . . e
. +, .i .
, i a. . . .
- o. , .
0 -- *=-- '-- ^--- '--- ' - - - '- - l
-200 -100 0 100 M 300 400 500 Temperature in Degree F P
1 Figure 3-8. SONGS, Unit 2: Data and Least Squares Fit Curve for Cm versus - e Tesw ee, Phee C6404-2, TL Orientation, Surveillance Baseline Data. i l ..i- ; 3-13 ! i L
i i l i J l l i f t 200 . . . . !
. San Onofrel Unit 2 l l l , .,
Combined ifCR & Surve;illance Data l l l l
' Material: P!pte No. C6404-2, SA533B-1 . . '.
' ' ' +
. Orientation; TL i i USE = 113, ft Ibs ',
150 --------l-------i--------r--------l--------q-------t-------- i 1 1 1 i i i i .O .i i i i * . . O B f i, 8 g a . .
., O ,
- s. ., .
i
' i i E '
0;O
. . , , , O , ,
i O i ,
>. i e in
,l------- ,'------- '--------
9 e 100 --------l-------,------,'-- O-- 0 , , c . ,
.i ; w i e . . . .
i z ' ' 0 l l : l : ! t) - . . . , ,
,. , 9 . , ,
0 f 1 1 0 $ l . . . . i
- i. . . , , ,
50 - - - - - - - -l. - - - - - - - 4. - - - - o- - ;,. - - - - - - - ,-l- - - - - - - -, -l - - - - - - - - t, - - - - - - - - 3 8 # # # 6 j 9 0 i i I i 1
. i i !
i , 1 1 5 6 1 i
, 4 3 5 0 A 6 O i . .
i I 8 o 8 e 1 0, t i , , , 8 4 1 8
. . .I . .
. i i i . .
I 1- I - 1- - - I - - - I-- - 0- - - i 200 -100 0 100 200 300 400 500 i Temperature in Degrees F , Figure 3-9. SONGS, Unit 2: Data and Least Squares Fit Curve for Cw versus ;
- Temperature, Plate C6404-2, TL Orientation, Combined MCR and .
Surveillance Baseline Data. ( 3-14 s 1
f m = - 1 = 0.0 0 O , 150 y E " D 3 u. O N g 100 -
+
C -
, uJ Z
i O . I San Onofra Unit 2 Surve$ lance Prohram 50 -
"" der 6al.NM).--06404-2
.. -S A533B1- l
. Orientation: LT USE d 150 ft-lbs 1 NDT = 10 V j .
. o
, . . .. .. .r .. ..i ....r .. ..i ....i ....i '
., e , - . - -
L Temperaturein Degrees F Figure 310. SONG:., Unit 2: Data and Least Squares Fit Curve for Cm versus i T=-*==v., Plate C6404-2, LT Oh'6, Surveillance Baseline Data. 3 15
J i i 200 , , t , t . 6
' . . . t. .
San Onof.re Unit 2 . .. . . . Comparison of MCR D,ata with Surycillance Bes} Fit Line l l Material:l Plate No. CQ404-2, A53@B-1 l l l Orientation: LT l l l l l 8 9 1 . . . t 1 I t i g
. . I I E r
. ,I o
..--------l---------_l----.-----l--------_'g .
i . i 150 ,' i i . . . . i o .i t m as . o . u.
. S l l l l l l 9 1 0e . . . - - - - . . _ l- - _ _ . . . . - i- _ _ _ _ _ . _ l . . . - . - _ _ _l . . . . - - - _ - _l . - - _ - - _ - . _l - . . - - - . . . .
C ., . o ,. , , , . uJ . . . , , , z l l l l l l
. O l o l', l l .
' o'i O MCR Data
'. . o
, , i i ;
50 --------- - - . - - - - - - j- - - - ------{.--- Fit to Survelliance ------
. io . t i Data !
8 . ,i
. . . . i ., .
l . 1 4 9 4 6 I. I I e I . . l ( g . I t 1 ,
. . .i .I ,
0 I I I 1 I -
-200 130 0 100 200 300 400 500 Temperature in Degrees F i
- j. Figure 3-11. SONGS, Unit 2: Comparison of Least Squares Fit Cm versus Temperature Curve for the Surveillance Plate with MCR Data for Plate C6404-2, LT ,
Orientation. i i
.h 3-16 l
4 ! l
200 - i
~
San Onofre Unit 2 , WMC bata
- Material: Weld
. Weld 9-203 USE = 145 ft-Ibs 150 i
-- NDhe #F-~' 20 SFO0 i T @ 50 ft-Ibs =
j . RTndt = -60 'F 0 3 . O u.
~
*$ '3
=
.E 100
, C .
W 8;
~
Z oh 0 50 O Measured Calculated ' - O o
...<t ....i .... e ....i ....i ....i ....i
-200 -100 o 100 200 300 400 soo Temperature in Degrees F i Figure 3-12. SONGS, Unit 2: Data and least Squares Fit Curve for C, versus Temperature, Weld 9-203, WMC Data.
I 3-17
I b I l 200 = i
. l 1
. f = 0.0 l 150 =
0 g O A
. O '
e ; ir ~ A [100 = + + h 5 - C Z
/
j o "
/ San Onofre Unit 2 f Su:veillance Prog' ram Matdial: Weld
" ! USE*= 146 ft-lbs
- / NDT= -50 V l
. g T @ p0 ft-lbs = -10 Y l RTndt = -50 9 D
., d .... ...., .... ,,,,v .... ....
l 200 -100 0 100 200 300 400 500 Temperature in Degree F l Figure 3-13. SONGS, Unit 2: Data and Least Squares Fit Curve for Cm versus Temperature, Surveillance Weld, Surveillance Baseline Data. 3-18 . j i - 1
Table 3.1 SONGS, Unit.2: Compliwe 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 tre2reA la Code requirements. NoRTm or drop weight Tm temperatures are determined. III.B.5.a Records of fracture toughness Appendix G was not applicable at the testing do not include a time tests were performed. Certification certification that tests were to the applicable ASME Code is performed in hudanw with included. The intent of Appendix G is Appendix G. met. III.C. Reactor Vessel Beltline *, as The baseline tests of the surveillance defined by Paragraph II.H, program include weld and HAZ material includes the weld heat- from the most limiting plate. Results
; affected-zones. Section III.C available for SONGS Unit 2 indicate
[- is not co=Had with in that that the intent of Appendix G has been only base plateand 4.;- ='- met. (Note: the HAZ results are not
- ative welds in the beltline presented in this report)
! region a considered for the required testing.
l III.C.1 Only single-temperatme testing Consistent with ASME Code in effect. < was performed for some weld
; materials. 1 L l Only the heat-affected-zone from the most limiting plate was tested over an ernended temperstme tange.
III.C.2 Excess material for test The same combinations of a specific specimen weldmentis not heat of filler wire and a specific lot of necessarily from theactual flux welded under the same production production plate, although conditions as those used in joining the it is the same P-nner. correspor. ding shell materials were used. (Section IX, ASME Code) 3-19
1 I Table 3.1 (Continued) 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 temperaturs .sf 60*F below the lowest preload temperature or at service temperature. All Lolting 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 one beltline weld were tested to meet the current (1989) Code requirements in NB-2331. The remaining beltline welds ' were tested at 10 F and/or 0 F and have an average Cm in excess of 90 ft-lb. These results indicate that the intent of Appendix G has been met. l i i l P 3-20 I
Table 3.2 SONGS, Unit 2: Plate and Corresponding Heat Numbers for the Beltline Plates. Lukens Plate Number Heat Number i C64(M-1 C7596-1 C6404-2 C7595-2 C6404-3 C7595-1 C6404-4 A6735-1 C6404-5 C7585-1 C6404-6 C7596-2 i a e 3-21
Table 3.3 SONGS, Unit 2: Weld Wire and Flux Combinations for Beltline and Surveillance Welds. Weld Seam Weld Wire and Flux 2-203 A, B, C' E8018 C-3 Electrodes, Lot No. BOLA 3-203 A, B, C6 Type Mil B-4 Wire, Heat No. 83637, Linde Type 0091 Flux, Lot No.1122 8-203' Combination of (1) Type Mil B-4 Wire, Heat No.10137, Linde Type 0091 Flux, Lot No. 3999 and (2) Type Mil B-4 Wire, Heat No. 90136, Linde Type 0091 Flux, Lot. No. 3999 9-203' Type Mil B-4 Wire, Heat No. 90130, Linde Type 0091 Flux, IAt No. 0842 Ii Same consumables as Weld 9-203 Surveillance'
- a. Weld wire heat number and flux type confirmed by ABB-CE letter dated November 4,1993 contained in Appendix D.
- b. Basis is SONGS Unit 2 FSAR and is consistent with handwritten note in Appendix D.
- c. Weld wire heat number and flux type confirmed by ABB-CE letter dated January 4, 1994. The applicable data are contained in App. C and D.
-9 3-22
I Table 3.4 SONGS, Unit 2: Key Residual and Alloying Element Contents for Beltline Plates.' Plate ABB-CE Number Lab. No. Cu Ni P S CF 6 C6404-1 P14445 0.10 0.56 0.007 0.009 65~ P16921 . C6404-2 P14446 0.10 0.59 0.008 0.010 65 ) P16922 C6404-2* 0.10 0.59 0.011 N/A 65 C6404-3 P14447 0.10 '0.56 0.008 0.011 65 P16923 C6404-4 P14105 0.10 0.62 0.006 0.009 65 P17110 C6404-5 P14068 0.11 0.64 0.007 0.010 75 P17405 C6404-6 P14106 0.10 0.58 0.006 0.010 65 i P17111
- 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 97 t21
\
3-23
. . __ . _ _ ___ __ ~_ . . -__ - . _ _ . .. _ _ _
L f
}
Table 3.5 SONGS, Unit 2: Key Residual and Alloying Element Contents for Beltline [ Welds. , i j ! Weld ABB-CE Number Lab No. Cu Ni P S CP , i I' 2-203A D18153 0.03 0.90 0.009 0.017- 41 2-203B D18154 0.03 0.91 0.009 0.016 41 ! 2-203C D18155 0.03 0.95 0.010 0.016 '41 f 3-203A D17025 0.05 0.12 0.011 0.011 40 [ t 3-203B D17026 0.04 0.06 0.010 0.011 30 3-203C D17027 0.06 0.11 0.010 0.011 42 > 4 6 8-203 (90136)D10255 0.31 1 0.012 0.010 260 6 (10137) D10600 0.23 1 0.016 0.010 236 I 9-203 D23227 0.07 0.29 0.009 0.007 69 . Surveillance
- D26761 0.03 0.12 0.003 0.009 30 d i Surveillanced 0.03 0.15 <0.005 N/A 32 )
I i
- a. Chemistry Factors determined from Regulatory Guide 1.99, Revision 2
- b. Ni content was not obtained and 1.0 wt% has been assumed (per Regulatory Guide 1.99, Rev. 2) 1
- c. Measured when surveillance program was developedM i Measured when the surveillance tests were performed for Capsule 97A d.
L-I d 3-24 1
-l s
m ' , - n,,-~ n - - -.. ,, ,- - - - - - - - - , v - n -- - J
Table 3.6 SONGS, Unit 2: Beltline Plate Material Unirradiated Fracture Toughness Tests Results Summary, TL Orientation. Initial Plate NDT RTer Procedure to USE , Number (*F) ('F) Determine RTer (ft-lbs) C6404-1 -30 20 NB-2331 (a)(3) 119 ! C6404-2* -20 6 20 NB-2331 (a)(3) 113 C6404-3 -20 20 NB-2331 (a)(3) 99 ( C6404-4 -10 20 NB-2331 (a)(3) 104 C6404-5 -20 10 NB-2331 (a)(3) 118 C6404-6 -10 -10 NB-2331 (a)(2) 124 ; L l 1
- a. This plate is included in the surveillance program. RTer is based on the MCR data i (see Figure 3-3) and the USE value is based on the combined data sets from the MCRs and unitradiated surveillance baseline (see Figure 3-9)
- b. An NDT value of-20 F was determined when the plate was purchased (+10*F was l
[ determined fro.a the surveillance baseline program). 1
< \
r i
)
]
[ 3-25 I i l
Table 3,7 SONGS, Unit 2: Charpy Absorbed Energy Values for Weld Seams 2-203 A, , B, and C; 3-203 A, B, and C; and 8-203. l Test Temperature Charpy Energy Weld Seam ( F) (ft-lb) 2-203 A, B, C 10 69,87,74 10 106,108,105 0 82, 101, 108 3-203 A, B, C 10 153, 131, 125 8-203 (90136) 10 108, 112, 119 (10137) 10 101,108,107 i
-(
3-26 t
'i
I Table 3.8 SONGS, Unit 2: Bejdine Weld Material Unirradiated Fracture Toughness Tests Results Summary. initial NDT RTor Pmeedure to USE Weld Seam ('F) (*F) Determine RTer (ft-lbs) h 2-203 A, B, C -60 -60 NB-2331 (a)(2) 93 d 3-203 A, B, C -50' -50 NB-2331 (a)(2) 136 d N/A -56 e 105 ; 8-203 (10137) d 8-203 (90136) N/A -56 e ll3 9-203 -60' -60 NB-2331 (a)(2) 145 , i Surveillance -50 -50 NB-2331 (a)(4) 146 I
- a. NDT values were ahtained from the FSAR and documented in Appendix D
- b. Estimated using the average of Cu values obtained at +10 F and 0 F (see Table 3.7)
- c. Generic value for ABB-CE fabricated vessels using Linde 0091,1092, and 124 fluxes (see 10CFR50.61) ;
- d. Estimated using the average ofCw values obtained at +10 F (see Table 3.7)
I' l' e 3-27
Section 4 ISSUES RELATED TO GENERIC LETTER 88-11 NRC issued Generic letter 88-11 (GL 88-11) in July 1988. GL 88-11 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 2, the reactor coolant cold leg temperature (TJ is maintained above the Technical Specification limiting condition for operation of 535'F which applies above 30% power. The normal operating band of T, ranges from 545'F at zero power to 553*F at 100% power with a tolerance of i 2"F. Thus, there is no time during normal power operation that the SONGS, Unit 2, 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.tzl 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 1028 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 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 designs.m The peak fluence value for the vessel inner surfac: is 6.6 x 10'8 n/cm 2, and the associated capsule fluence is 8.0 x 1018 n/cm2, 4-1
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 2.131 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, j 1
As indicated in Figure 3-1, there is a weld identified as 8-203 which is well outside the core i region of the vessel (i.e., approximately 2 feet above the top of the core). This weld is conservatively considered a beltline material because of a large chemistry factor associated with ; the high reported Cu content (0.31 wt%) in combination with a 1.0 wt% Ni content, which was conservatively assumed because Ni was not reported. The fluence at this location above the core was reported in the FSAR to be about 1/37 that of the peak fluence location within the vessel. , Recent calculations performed at SCEW indicate that the fluence at Weld 8-203 is 1/108 that of l the peak fluence location within the vessel. The SCE fluence calculations have been used in the l evaluation of Weld 8-203. 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 125"F), but the other two have not been satisfied since only one capsule from each vessel has been pulled and evaluated. To satisfy these last 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 ponion of this section, the available results from the first capsules will be ! l compared to the regulatary prediction approaches, and projections based upon the regulatory j 1 approaches will be made, l l l 1 4.3 SHIFTS AT THE CHARPY V-NOTCH 30 FT-LB ENERGY LEVEL Capsule 97 from the SONGS Unit 2 surveillance program was tested in 1988. The Cyu results J from this capsule are shown in Figures 4-1 (Plate C6404-2/LT), 4-2 (Plate C6404-2/TL), and j 4-3 (surveillance weld). Appendix H contains, in tabular form, the absorbed energy, lateral expansion, and fracture appearance (% shear) for the irradiated surveillance materials. The results computed during this work for the shift at the 30 ft-Ib 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): e RG1.99R2 = CF (chemistry factor) x ff (fluence function). , ( i 4-2 1 l 1 l
The results obtained by Battellemare also shown for comparison. The differences between the current values for shift versus those from Battelle are due to small differences in the curve fit to the Cvs data and the different data set used for unirradiated Plate C6404-2/TL (i.e., Figure 4 3-8 for Battelle and Figure 3-9 in the current study). All of the measured shift results are less than the mean prediction from Regulatoly Guide 1.99, Revision 2. Until another capsule is tested, there is no way to definitively evaluate that 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 RTuor (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 RTuors were taken from Tables 3.6 and 3.8. The results in Table 4.2 show that the adjusted RTuor is essentially the same for all beltline plates, and that the plate material is the limiting material in the vessel beltline. Finally, the results in Table 4.2 show that the degree of radiation embrittlement in the SONGS, Unit 2, 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 2, surveillance program was evaluated in 1988. The USE 4 results are shown in Figures 4-1,4-2, and 4-3, and are tabulated in Table 4.3 as absolute drop
.in USE (ft-lb). Also listed in Table 4.3 are the predicted drops from Regulatory Guide 1.99, Revision 2. All of the measured drops in USE are below those predicted by the Regulatory Gu.ide.
Prediuions of USE levels at the quarter-thickness location after neutron irradiation exposure are : shown c1 Table 4.4 for all the SONGS, Unit 2, beltline materials. At the end of 32 EFPY, none l of the materials are projected to even approach the NRC screening limit of 50 ft-lb specified in 10CFR50, Appendix G. l l L _ r 4-3 l
i 1 l A 200 -
~
San Onofre Unit 2 Survellidnce Program Materialj Plate SA'533B1
, No. C64,04-2 Orientation: LT 150 = ' + + +-- - - - - - -
f
< O o to ~
/
9 / O g
. I
/ O
> I E 100
= / 4 I
i h
- I I
~
Z l
> . I ,
n
- / -----f=0.0 I
50 = t
~
I f = 5.07e+18 l
/ O f = 5.07e+18
~
/
/
#T' '' ' '
0
-200 -100 0 100 200 300 400 500 Temperature in Degrees F l
l Figure 4-1. SONGS, Unit 2: Comparison of the least Squares Fit for the Uninadiated Baseline Data with the Irradiated C, Data and least Squares Fit for the Data from Capsule 97, Plate C6404-2, LT Orientation.
'(' 4-4 L
200 - l San Oqofre Unit 2
. Combined MCR & Surveillance Data
~
Material: Plate A533B1 Heat No. C6404-2 Orienta' talon: TL
+ + +
150 = m r - - - - - - - - - - 100
~
j
' s']o O c .
/
10
' /
Z /
> . /
O /
- / -----g=o,o 50 -
i
/ f = 5.07e+18
~
/
- ,/ O O f = 5.07e+18
/
/0 :
- , 5) o
...., .T7.0....i .... n ....' ... 1 .... e
-200 -100 o 100 200 300 400 500 Temperature in Degrees F Figure 4-2. SONGS, Unit 2: Comparison of the Least Squares Fit for the Combined MCR and Unirradiated Baseline Data with the Irradiated Cvy Data and Least Squares !
Fit for the Data from Capsule 97, Plate C6404-2, TL Orientation. l l 4-5 1 I
l k 200 j g i San Onofre Unit 2i
. Survefilance Program a
Materi'al: W eld 150 = +-
} _ _ _ _t_ _ k _ {_ _ _ _ _ l_ _ _ _ _ ,
g'/ O j m ~
/
9 / O is
/
i E 100 I l
,' e f e .
W I
~
Z /
> ~ I O j
- I -----g,g,o
/
50
=
I
/
f = 5.07e+18 p -
/ O f = 5.07e+18 O
M
.... r ...., ...., ....r ...., .... o O
u
-200 -100 0 100 200 300 400 500 Temperature in Degrees F i
Figure 4-3. SONGS, Unit 2: Comparison of the least Squares Fit for the e Unitradiated Baseline Data with the Irradiated Cm Data and Least Squares Fit for the Data from Capsule 97, Surveillance Weld. ( 4-6
Table 4.1. SONGS, Unit 2: Surveillance Capsule Shift Results. l 30 ft-lb Shift (*F) Material / CF ff . Orientation Battelle RG1.99R2 Current C6404-2/LT 658 0.81 51 53 52' C6404-2/TL 65' O.81 45 53 33d Sun'eillance 696 0.81 7 56 4' Weld
- a. See Table 3.4 (Cu = .10; Ni = .59)
- b. Based upon the conservative 9-203 weld chemistry -- see Table 3.5 1
i~ c. 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 i Figure 3-9
- e. Based on the baseline surveillance data, see Figure 3-13 e
s [ 4-7 I i
Table 4.2. SONGS, Unit 2: ART Estimates at the Inner Surface Location for Beltline Materials on 12/16/91 and at 32 EFPY. I 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 C6404-1 65 0.95 1.37 116 143 C6404-2 656 0.95 1.37 116 143 C6404-3 65 0.95 1.37 116 143 C6404-4 65 0.95 1.37 116 143 C6404-5 75 0.95 1.37 115 147 i C6404-6 65 0.95 1.37 86 113 2-203 A, B, C 41' O.95 1.37 18 52 A 3-203 A, B, C 38d 0.95 1.37 22 54 8-203 (10137) 236 0.09' O.25' 5' 68' 8-203 (90136) 260 0.09' O.25' 8' 74' 9-203 69 0.95 1.37 62 90 l
- a. ART is the adjusted reference temperature equal to the predicted shift (CF x ff) plus the initial RTer plus a margin term equal to 34'F for plates or 56*F for welds (unless the predicted shift is less than the margin term, in which case the margin is equal to the predicted shift)
L
- b. Based upon average chemistries for this plate (.10 Cu/.59 Ni)--see Tables 3.4 and 4.1
- c. Based upon average chemistries for these welds (.03 Cu/.92 Ni)--see Table 3.5 d, Based upon average chemistries for these welds (.05 Cu/.10 Ni)--see Table 3.5 i
'. c. Fluence function is based upon the peak vessel fluence divided by 108H1 '
- f. Since there is not a measured initial RTor, an additional margin associated with the standard deviation (17'F) of the initial RTer has been used as described in Regulatory
].,' . l Guide 1.99, Rev. 2 4-8
1 Table 4.3. SONGS, Unit 2: Surveillance Capsule Upper Shelf Results l I i Upper Shelf Drop (ft-lb) Material / Cu Fluence 2 Orientation (wt%) (x 10 n/cm ) Battelle RG1.99R2 Current i C6404-2/LT 0.10' O.507 17 24 15d C6404-2/TL 0.10' O.507 21 18 14' j Surveillance 0.07 6 0.507 5 26' 4' Weld l
- a. See Table 3.4 l
- b. See Table 3.5 for weld 9-203
- c. Based upon interpolation of the Regulatory Guide 1.99, Rev. 2 curves.
- d. Based on the baseline surveillance data, see Figure 3-10
- e. Based on the combined data set from the MCR and baseline surveillance program, see Figure 3-9
- f. Based on the baseline surveillance data, see Figure 3-13 fI.
? u <( 4-9
. i u
Table 4.4. SONGS, Unit 2: 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 C6404-1 0.10 0.51 2.5 100 91 C6404-2 0.10' O.51 2.5 95 87 l C6404-3 0.10 0.51 2.5 83 76 i C6404-4 0.10 0.51 2.5 87 80 C6404-5 0.11 0.51 2.5 98 89 . i i C6404-6 0.10 0.51 2.5 104 95 , l 2-203 A, B, C 0.03* 0.51 2.5 78 71
;i 3-203 A, B, C 0.05d 0.51 2.5 114 103 ,
- I a
8-203 (10137) 0.23 0.005 0.023 94' 89' 8-203 (90136) 0.31 0.005 0.023 97' 88' ] 9-203 0.07 0.51 2.5 119 107
- 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 average chemistry for this plate-see Table 3.4 i
- c. Based upon average chemistry for this weld and the lowest measured upper shelf-see Tables 3.5 and 3.8
- d. Based upon average chemistry for this' weld-see Table 3.5
- e. Based upon an extrapolation of the curves in Regulatory Guide 1.99, Rev. 2 f 4-10
Section 5 REFERENCES [1] A. Ragi, Southern California Edison San Onofre Unit 2. Evaluation of Baseline Specimens. Reactor Vessel Materials Irradiation Surveillance Procram, Combustion Engineering S-TR-MCS-002, May 27,1978. [2] M. P. Manahan, L. M. Lowry, and E. O. Fromm, Examination. Testine. and Evaluation of Irradiated Pressure Vessel Surveillance Specimens from the San Onofre Nuclear Generatine Station Unit 2 (SONGS-21 Battelle Columbus, December 1988.
)
[3] 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 2, May 1994. [4] R. Chang, " SONGS 2/3 RPV Fluence Ratio at Weld 8-203", SCE Calculation No. N-1020-065, December 1992. 0 1 , i i' e
..( .
5-1 1 I
I i i l i l l , =I APPENDIX A l f : I
- j. i SONGS, UNIT 2: EVALUATION OF COMPLIANCE WITH ASTM E185-73 AND E185-82 4 i e
i i T. , l ff
i l Summary of Requirements San Onofre Unit 2 Program per ASTM E185-73 1.2 Surveillance tests are divided Compliance according to application into two l 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 5 X 10:s n/cm or less.
2 1.2.2 Case B - Where the predicted l increase in transition temperature of the reactor vessel steel is greater than 100'F or where the calculated peak neutron fluence (E l
> 1 MeV) of the reactor vessel is greater than 5 X 10' n/cm2 3
4.1 Test Material - Test specimens Compliance , shall be prepared from the actual materials used in fabricating the irradiated region of the reactor vessel. 1 4.1 Samples shall represent a Compliance minimum of one heat of the base metal and one butt weld and one weld heat-affected-zone (RAZ) if a weld occurs in the irradiated region. 4.1 The base metal and weld metal Compliance to be included in the program a should represent the material that may limit the operation of the reactor during its lifetime. 9 4 A-1 O
Summary of Requirements San Onofre Unit 2 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 (weld wire of rod, must come from
' one of the heats used in the irradiated region of the reactor vessel) and the same type of flux, j and (3) the heat-affected-zone associated with the base metal noted above.
l 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 retained with full
!4 documentation and identification. ; 4.1.2 Fabrication History -
The compliance 3 test material shall receive a fabrication history > (austenitizing, quench and 1 tempering, and post-weld heat I treatment) fully representative of the fabrication received by the material in the irradiated region of the reactor vessel. [ 4.1.3 Chemical Requiremencs - The Compliance 1 chemical composition required by the material specifications for j the test materials (base metal and f as deposited weld metal) shall be obtained and include, but not be ,, limited to phosphorus (P), sulfur l (S), copper (Cu), and vanadium I-(V). [ , A-2
Summary of Requirements San Onofre Unit 2 Program , per ASTM E185-73 4.2 Charpy V-notch impact Compliance 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 1 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 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 I affected zone at a standard distance of approximately 1/32 in. from the fusion line. Specimens representing the base metal l (tension and impact) and the weld l heat-affected zone shall be i removed from the quarter thickness ~ location. (per NB2300 of ASME Code , Section III) - (- A-3 l . l 6
+
i Summary of Requirements San Onofre Unit 2 Program ;
< per ASTM E185-73 !
\
)
4.4 Number of Specimens - The Compliance minimum number of test specimens i for each exposure shall be as l follows: Case A Case B Charpy Charpy Tension l Base Metal 12 12 2 4 Weld Metal 12 12 2 HAZ 12 12 - l l 4.4 At least 15 Charpy impact Compliance specimens shall be used to ; establish an unirradiated i I transition curve for each material. l '
! 4.4 For Case B (see above), three Not Applicable tension test specimens shall be
{i used to establish unirradiated
; 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 4 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.
I j A-4 r. y -
I l Summary of Requirements San Onofre Unit 2 Program per ASTM E185-73 5.1.2 Accelerated Irradiation Not Applicable Specimens (Optional) - Test j' specimens may be positioned at locations other than (5.1.1) for ; accelerated irradiation at a rate j 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 j neutron fluence as follows: 5.2.1 Dosimeters with the vessel Wall specimens (5.1.1). 1 5.2.2 Where accelerated Compliance irradiation specimens are used (5.1.2), dosimeters with the test specimens and dosimeters either in J a separate flux monitor capsule i s adjacent to the vessel wall or in a vessel wall capsule. 9 5.3 Test Oapsules - To prevent compliance deterioration of the surface of j the specimens during test, the j specimens should be maintained in an inert environment within a c corrosion-resistant capsule. 5.3 The temperature history of the compliance e specimens shall duplicate as l closely as possible the temperature experienced by the ,. reactor vessel. , g> A-5 L ! 1 j
Summary of Requirements San Onofre Unit 2 Program per ASTM E185-73 5.3 Surveillance capsules should Compliance be sufficiently rigid to prevent damage to the capsules by coolant pressure or coolant flow thus l hindering specimen removal or l 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. ] s 5.3 Consideration should be given Compliance 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. i 5.4 Specimen Withdrawal - A Compliance minimum surveillance program shall consist of three capsules for Case l A and five capsules for Case B. It is recommended that capsules be withdrawn as described in Table 1. l (See Table 1 of ASTM E185-73.) i 6.1 Radiation Environment - The Compliance . neutron flux, neutron energy spectrum, and irradiation temperature of surveillance specimens and the method of determination shall be documented. h r rw 1# A-6
summary of Requirements San Onofre Unit 2 Program per ASTM E185-73 l i 6.2 Neutron Flux Dosimeters - Flux Conpliance l dosimeters for a particular i program shall be determined by I referring to Method E 261. END END 4 1 4 t 1 I [ A.. A-7 O
l Summary of Requirements San Onofre Unit 2 Program per ASTM E185-82 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 between the observed and
~
the expected capsule exposure temperatures, an analysis of the operating conditions shall be conducted to determine the magnitude and duration of these differences. 8.2 Neutron Irradiation Compliance Environment: 8.2.1 The neutron flux density, , I neutron energy spectrum, and neutron fluence of the surveillance specimens and the corresponding maximum values for the re. actor vessel shall be determined in accordance with the I i guidelines in Guide E 482 and Recommended Pr='+4 r= 2 560. l 8. 2.2 The speci.fic mat-brvi of determination whn11 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: J 9.1.2.1 Unirradiated - Ttte test temperatures for each material shall include room temperature, service temperature, and one
. intermediate temperature to define the =L m yth versus ,
temperature relationship. t < A-8
Summary of Requirements San Onofre Unit 2 Program
- per ASTM E185-82 9.1.2.2 Irradiated - One specimen Compliance from each material shall be tested at a temperature in the j vicinity of the upper end of the Charpy energy transition region.
The remaining specimens from each material shall be tested at the service temperature and the midtransition temperature. 9.1.3 Measurements - For both Compliance unirradiated and irradiated materials, determine yield strength, tensile strength,
)
fracture load, fracture strength, fracture stress, total and uniform elongation, and reduction l of area. 9.2 Charpy Tests: Compliance 9.2.1 Method - Charpy tests shall l; be conducted in accordance with i Method E 23 and A370. 9.2.2 Test Temperature: Compliance 9.2.2.1 Unirradiated - Test r 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. 9.2.2.2 Irradiated - Specimens Compliance for each material will be tested at temperatures selected to define the full energy transition curve. Particular emphasis
- should be placed on defining the 41-J (30 ft-lb), 68-J (50 ft-lb),
f- and 0.89-mm (35 mil) lateral
,1 ~ expansion index temperatures and the upper shelf energy.
A-9 p. I.
Summary of Requirements San Onofre Unit 2 Program per ASTM E185-82 L 9.2.3 Measurements - For each Compliance test specimen, measure the impact energy, lateral expansion, and f percent shear fracture appearance. From the unirradiated and irradiated transition temperature curves determine the 41-J (30 ft-lb), 68-J (50 f t-lb) , and 0.89 mm (35 mil) lateral expansion index temperatures and the upper shelf t 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
- I qualificntion test report the initial reference temperature
[ (RTurn) as defined in ASME Code, 1 Section III, Subarticle NB 230 for unirradiated materials. i i 9.3 Hardness Tests (Optional) - Compliance Hardness tests may be performed on unirradiated and irradiated f 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. I __________________ __________________ l 9.4 Supplemental Tests (Optional) Not Applicable t
- If supplemental fracture toughness tests are conducted (in addition to tests conducted on tension and Charpy specimens as '
described in 6.1) the test L procedures shall be documented. W w A-10 i.
Summary of Requirements San Onofre Unit 2 Program l per ASTM E185-82 ! l 9.5 Calibration of Equipment - Compliance Procedures shall be employed , assuring that tools, gages, l recording instruments, and other j measuring and testing devices are ' calibrated and properly adjusted i ' periodically to maintain accuracy within necessary limits. Whenever possible calibration t 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 'i 10.1.1 Determine the amount of radiation strengthening by comparing unirradiated test results with irradiated test - results at the temperature 1 specified in 9.1.2. ! 10.1.2 The tensile strength data can be verified using the results from the hardness test (optional) , described in 9.3.
- 10.2 Charpy Test Data: Compliance 10.2.1 Determine the radiation induced transition temperature shifts by measuring the ;
difference in the 41-J (30 ft-lb), 68-J (50 ft-lb), and 0.89 mm (35 mil) lateral expansion index
- temperatures before and after irradiation. The index '
temperatures shall be obtained from the average curves. x
.c A-11 b
I
Summary of Requirements San Onofre Unit 2 Program per ASTM E185-92 10.2.2 Determine the adjusted Compliance reference temperature by adding the shift corresponding to the 41-J (30 ft-lb) index determined in 10.2.1 to the initial reference temperature obtained in 9.2.3.1. 10.2.3 Determine the radiation Compliance induced change in the upper shelf energy (USE) from the measurements made before and after irradiation using average .; value curves. 10.2.4 (Optional) - Determine the Not Applicable i 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.
11.1 Where applicable, both SI units and conventional units r shall be reported. l g A-12
I I Summary of Requirements San Onofre Unit 2 Program l per ASTM E185-82 11.2' Surveillance Program Compliance Description - Description of the j 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. ( 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. l d A-13 t
=
1 1 I 1 Summary of Requirements San Onofre Unit 2 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. 4 11.3.2 Location and orientation of the test specimens in the i 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 used), neutron dosimeters, and temperature monitors. 11.3.3.2 Certification of calibration of all equipment and instruments used in conducting o the tests. 1
.c ,
a I b i
.s>
t, Y A-14
I Summary of Requirements San Onofre Unit 2 Program per ASTM E185-82 .; r I 11.4.1 Tension Tests: Compliance . t 11.4.1.1 Trade name and model of I
.the testing machine, gripping devices, extensometer, and >
recording devices used in the j test. 11.4.1.2 Speed of testing and method of measuring the . controlling testing speed. ! P 11.4.1.3 Complete stress-strain curve (if a group of specimens exhibits similar stress-strain curves, a typical curve may be e reported for the group). : 1 1..<4.1.4 Test Data from each : specimen as follows: (1) Test temperature; (2) Yield strength or yield point ; and method of measurement; : f (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 l (8) Specimen identification. l I i 5 A-15
\
Summary of Requirements San Onofre Unit 2 Program per ASTM E185-82 l 11.4.2 Charpy Tests: Compliance 11.4.2.1 Trade name and model of l the testing machine, available hammer energy capacity and striking velocity, temperature conditioning and measuring devi 2s, 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: 4 (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:
i t (1) Charpy 41-J (30 ft-lb), 68-J (50 ft-lb), and 0.89 mm (35 mil) j lateral expansion index i temnerature of unirradiated material and of each set of irradiated specimens, along with the corresponding temperature d increases for these specimens; (2) Upper shelf energy (USE) absorbed before and after L 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. 11.4.3.2 Hardness data. ; c : 7 A-16
Summary of Requirements San Onofre Unit 2-Program per ASTM E185-82 11.4.4 Other Fracture Toughness Not Applicable Tests: 11.4.4.1 If additional tests are i performed, the test data shall be j reported together with the i procedure used for conducting the j 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 j maximum capsule exposure i temperature. ! 11.4.5.2 Neutron dosimeter ! measurements, analysis j -, techniques, and calculated l i results including the following-(1) Neutron flux density, neutron : 4 energy spectrum, and neutron l fluence in terms of neutrons per , square metre and neutrons per li square centimetre (>0.1 and 1 MeV) for the surveillance ; specimens using both calculated spectrum and assumed fission l
- spectrum assumptions. 1 (2) Description of the methods :
used to verify the procedures ! including calibrations, cross ! sections, and other pertinent nuclear data. i 1 l ;
+
l 9
.(
' es A-17 , l
Summary of Requirements San Onofre Unit 2 Program per ASTM E185-82 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 j fluence location. 11.6 Deviations - Deviations or Compliance , i anomalies in procedure from this practice shall be identified and described fully in the report. END END O ,. ( l A-18
P i h i i APPENDIX B s lI ! SONGS, UNIT 2: BASES FOR PLATE j e CHEMISTRY MEASUREMENTS (Proprietary) I
?
P l f (
- c. .
I' l
i l l t I i i APPENDIX C , I i i SONGS, UNIT 2: BASES FOR WELD CHEMISTRY MEASUREMENTS (Proprietary) 1 x was W d
i i APPENDIX D SONGS, UNIT 2: WMCs FOR BELTLINE MATERIALS (Proprietary) 4 Y
1 l APPENDIX E ( SONGS, UNIT 2: MCRs FOR BELTLINE MATERIALS-(Proprietary) I i i k i
l l I i APPENDIX F SONGS, UNIT 2: UNIRRADIATED Cvy DATA FOR PLATES AND WELDS i 4 I l ^ l
i Table F-1 Charpy V-Notch Test Results For Unit 2 Plate C6404-1 (TL), MCR Data SPECIMEN TEMP ENERCY IATERAL PRACT ] 1D TEST IMPACT ERP APPEAR i tr) (ft-lb) (mill (t) 1 -40.00 10.00 5.00 0.00 l l 2 -40.00 9.00 4.00 0.00 3 -40.00 7.00 3.00 0.00 , t 4 10.00 23.00 19.00 10.00 14.00 't 5 10.00 16.00 5.00 i t 6 10.00 20.00 15.00 10.00 lr 21.00 15.00
} 7 40.00 30.00 '
f s 40.00 35.00 25.00 15.00 9 40.00 43.00 30.00 20.00 3-h I 10 70.00 63.00 hii.88 4evee .55.00 gg j
\
a 11 70.00 60.00 46.00 35.00 ( r
, 12 70.00 44.00 31.00 20.00 ,
l
! 13 90.00 77.00 55.00 50.00 14 90.00 64.00 44.00 40.00 !
15 30.00 57.00 42.00 35.00 16 100.00 81.00 58.00 ,50.00 ; i, 17 100.00 72.00 56.00 50.00 le . 100.00 83.00 62.00 50.00 t 19 160.00 119.00 74.00 95.00 20 140.00 113.00 75.00 95.00 . 21 160.00 117.00 78.00 90.00
- 22 212.00 121.00 75.00 100.'30 U-23 212.00 120.00 75.00 10f, . 00 24 212.00 124.00 79.00 100.OG
- s. .
I F-1 ! ,- 1 i l l
Table F-2 Charpy V-Notch Test Results For Unit 2 Plate C6404-2 (TL), MCR Data
, SPECIMEN TEMP ENERCT 1ATERAL FRACT 2D TEST IMPACT ERP AP' PEAR (F) (ft-lb) (mil) (1) >
I 1 -40.00 6.00 3.00 0.00 2 40.00 7.00 3.00 0.00 3 -40.00 11.00 6.00 0.00 4' 10.00 10.00 13.00 10.00 5 10.00 16.00 11.00 5.00 > 6 10.00 13.00 0.00 5.00 , 7 40.00 37.00 25.00 15.00 S 40.00 23.00 17.00 10.00 9 40.00 35.00 24.00 15.00 i i 10 70.00 52.00 35.00 25.00 1 11 10.00 47.00 34.00 25.00 12 70.00 51.00 40.00 25.00 13 80.00 65.00 47.00 40.00 i 14 80.00 69.00 48.00 40.00 15 80.00 53.00 30.00 30.00 16 100.00 15.00 55.00 50.00 I 17 100.00 60.00 52.00 50.00 to 100.00 13.00 53.00 50.00 19 160.00 101.00 71.00 99.00 20 160.00 95.00 66.00 95.00 i 21 160.00 94.00 57.00 95.00 f l 22 212.00 105.00 74.00 100.00
- i i
23 . 212.00 123.00 00.00 100.00 l
,. 24 212.00 117.00 16.00 100.00 8 F-2 t I
1 l l
1 Table F-3 Charpy V-Notch Test Results For Unit 2 Plate C6404-3 (TL), MCR Data SPECIMEN TEMP ENERCY LATERAL TRACT l 20 l TEST IMPACT ERP APPEAR * (T) (ft-lb) tail) (t) i 1 40.00 8.00 5.00 0.00 2 40.00 10.00 6.00 0.00 06 3 40.00 9.00 4,00 7,06 0.00 y/lf 4 10.00 14.00 9.00 5.00 5 10.00 21.00 15.00 10.00 6 10.00 15.00 13.00 5.00 7 40.00 19.00 lb.bD Y 6 lif6 9thee- hj
- 8 40.00 33.00 22.00 20.00 21 160.00 93.00 61.00 95.00
) 10 70.00 4g.00 35.00 25.00 3 11 70.00 54.00 42.00 30.00 12 70.00 45.00 35.00 25.00 f 13 80.00 49.00 49.00 50.00 14 80.00 60.00 44.00 50.00 ; l 15 80.00 52.00 36.00 50.00 16 ~100.00 73.00 55.00 50.00 17 100.00 74.00 54.00 50.00 18 100.00 71 00 50.00 50.00
, l 19 160.00 97.00 62.00 99.00 1
20 160.00 94.00 64.00 95.00 9 40.00 30.00 1s.00 15.0b 4e,4e. Y3p/f/ j l 22 212.00 105.00 69.00 100.00 23 212.00 100.00 66.00 100.00 i 24 212.00 103.00 64.00 100.00 F-3 i
~
1 1
.l Table F-4 Charpy V-Notch Test Results For Unit 2 Plate C6404-4 (TL), MCR Data i
l i j SPECIMEN TEMP EMERCY LATERAt. FRACT TEST
, 'O IMPACT EXP AFFEAR (F) (ft-lb) (mil) (t) i 1 -40.00 9.00 6.00 0.00 2 -40.00 9.00 .7.00 0.00 3 -40.00 10.00 e.00 0.00 4 10.00 26.00 20.00 15.00 5 10.00 22.00 17.00 10.00 .i f 6 10.00 23.00 20.00 10.00 7 40.00 35.00 25.00 15.00 L
1 8 40.00 34.00 25.00
. 15.00 t
S 40.00 44.00 33.00 20.00 10 70.00 47.00 36.00 30.00
?
11 70.00 52.00 40.00 35.00 , 12 70.00 56.00 41.00 40.00 13 90.00 42.00 48.00 40.00 ' o 14 80.00 66.00 50.00 40.00 ' 15 80.00 68.00 $3.00 40.00 16 110.00 60.00 t 51.00 50.00 17 110.00 7s.00 56.00 50.00 18 110.00 85.00 60.00 60.00 19 160.00 108.00 18.00 100.00 i 20 160.00 107.00 75.00 100.00 21 160.00 96.00 11.00 100.00 P 1 i
.( F-4 i
t Table F-5 Charpy V-Notch Test Results . For Unit 2 Plate C6404-5 (TL), MCR Data P spectMrw nur ENtacr 1.ATrnAI. rnAct , ID TEST IMPACT EEP APPEAR (r) (ft-lbl (mill (t) 1 -40.00 10.00 5.00 0.00 , 2 -40.00 9.00 5.00 0.00 3 -40.00 e.00 4.00 0.00 4 20.00 18.00 1s.00 5.00 5 10.00 15.00 13.00 5.00 6 10.00 14.00 14.00 5.00 7 40.00 25.00 20.00 15.00 e 40.00 26.00 22.00 15.00 t 9 40.00 23.00 19.00 15.00 , Q 46.40 10 54,40 47.00 36.00 30.00 5 e $ld fro.00 44v96 54.00 42.00 35.00 11 46.cb 12 44v4+ 61.00 50.00 35.00 13 10.00 Es.00 4s.00 40.00 14 70.00 72.00 53.00 45.00 ; 15 70.00 55.00 44.00 35.00 [ 16 110.00 81.00 (0.00 50.00 , 17 120.00 84.00 59.00 50.00 l 18 110.00 87.00 41.00 50.00 19 160.00 103.00 85.00 90.00 20 140.00 105.00 10.00 90.00 , 21 160.00 115.00 12.00 90.00 22 212.00 122.00 81.00 100.00 23 212.00 116.00 14.00 100.00 24 ,12.00 11. 00 70.60 100.00 . lggy
.(
F-5
i l Table F-6 Charpy V-Notch Test Results l For Unit 2 Plate C6404-6 (TL), MCR Data ; 1 1 1
- I
[ SPECIMEN TEMP ENERCY 1ATERA1. FRACT , ID TEST IMPACT ERP APPEAR i (F) (ft-1b) (all) (g) 1 1 -40.00 4.00 4.00 0.00' 2 -40.00 9.00 6.00 0.00 l 3 -40.00 6.00 5.00 0.00 j 4 10.00 14.00 13.00 5.00 i 6 5 10.00 16.00 14.00 5.00 6 10.00 13.00 12.00 5.00 !
'l 7 40.00 20.00 23.00 15.00- i
.}
O 40.00 27.00 22.00 15.00 , 9 40.00 27.00 24.00 15.00 !
! 10 50.00 61.00 45.00 30.00 i 11 50.00 54.00 40.00 25.00 ,
12 50.00 65.00 47.00 30.00 ! 13 110.00 05.00 61.00 60.00' ; 14 110.00 73.00 52.00 50.00 .l 15 110.00 94.00 59.00 70.00 N 16 160.00 116.00 70.00 90.00 't 17 160.00 115.00 75.00 90.00 f le 160.00, 110.00 70.00 90.00 i 19 212.00 120.00 30.00 100.00 v 6 20 212.00 124.00 76.00 .100.00 ? 21 212.00 121.00 77.00 100.00 e i 3 b i t , I F.6 l w l
Table F-7 Charpy V-Notch Test Results For Unit 2 Weld Scam 9-203 (Heat #90130),-FSAR Data lAJ M t.
%A SPECIMEN TEMP ENERCY 1ATERAL FRACT ID TEST IMPACT EIP APPEAR (F) (ft-lb) (mill (t) 1 -60.00 16.00 9.00 0.30 2 -60.00 15.00 7.00 0.00 3 -60.00 19.00 11.00 0.00 4 -40.00 20.00 11.00 5.00 5 -40.00 20.00 16.00 10.00 6 -40.00 32.00 22.00 15.00 7 -20.00 85.00 53.00 50.00 8 -20.00 88.00 56.00 50.00 9 20.00 76.00 47.00 40.00 10 0.00 77.00 47.00 40.00 I
11 0.00 75.00 45.00 40.00 12 0.00 99.00 52.00 60.00 13 20.00 117.00 74.00 70.00 l 14 20.00 105.00 65.00 60.00 15 20.00 114.00 74.00 70.00
- 16 60.00 132.00 77.00 80.00
- 17 60.00 149.00 04.00 100.00 7 18 60.00 123.00 74.00 80.00 l
l 19 100.00 142.00 82.00 100.00 20 100.00 140.00 84.00 100.00 k 21 100.00 140.00 82.00 100.00 T i F-7 1 4 . (
Table F-8 Charpy V-Notch Test Results For Unit 2 Plate C6404-2 (LT), CE Baseline Data i 5 I SPEC 1 MEN TEMP ENERCT 1ATERAL TRACT ; ID TEST IMPACT ERP APPEAR ' I (F) (ft-1b) (all)" (t) 154 -80.00 4.50 2.00 0.co j 136 -80.00 e .,50 10.00 0.00 , 122 -40.00 5.00 6.00 0.00 132 -40.00 6.50 6.00 0.00 143 0.00 11.00 13.00 15.00 l 147 0.00 16.50 18.00 15.00
- 114 40.00 41.00 30.00 25.00 k 11A 40.00 56.50 40.00 25.00 !
12K 80.00 93.50 72.00 65.00 ii f 14A 90.00 124.50 83.00 75.00
' 156 120.00 119.00 70.00 30.00 l
11E 120.00 141.50 96.00 90.00
- b i 13T 160.00 146.50 90.00 100.00 i
11T 160.00 157.50 95.00 90.00 , 157 210.00 140.00 96.00 100.00 14L 210.00 155.00 94.00 100.00 9 h F-8 59 r l
}
Table F-9 Charpy V-Notch Test Results For Unit 2 Plate C6404 2 (TL), CE Baseline Data SPECIMEN TEMP ENERCT LATERAL FP.ACT ID TEST IMPACT EKP APPEAR (r) (ft-1b) (all) (t) 264 -80.00 4.50 2.00 0.00 25A -40.00 0.00 0.00 0.00 23D -40.00 8.00 9.00 0.00 21T 0.00 12.00 15.00 10.00 21Y 0.00 24.50 24.00 10.00 262 40.00 33.00 32.00 20.00 225 40.00 40.00 35.00 25.00
, 24J 80.00 68.50 58.00 30.00 l 40.00 t 24E 80.00 78.50 62.00 9 21E 120.00 87.00 56.00 75.00 24A 120.00 107.00 72.00 80.00 245 160.00 111.50 18.00 85.00 24T 160.00 127.50 84.00 90.00 216 190.00 115.00 80.00 100.00 24U 210.00 126.50 87.00 100.00 ,
e 231 210.00 137.50 91.00 100.00 i 1
- F-9 I
Table F-10 Charpy V-Notch Test Results
~ For Unit 2 Surveillance Weld, CE Baseline Data ENERCY 1ATERAL TRACT SPECIMEN TEMP TEST IMPACT ERP APPEAR ID tail) (t)
(F) (ft-lb)
-150.00 3.50 1.00 0.00 3 4r.
31H -120.00 7.00 6.00 15.00 333 -120.00 14.00 12.00 15.00 346 -80.00 16.00 15.00 25.00 37A -80.00 29.50 25.00 30.00 31K -40.00 43.50 37.00 35.00 35T 0.00 63.50 53.00 65.00 34T 0.00 10.00 68.00 15.00 335 40.00 132.00 90.00 90.00 324 40.00 146.00 97.00 100.00 35L 80.00 135.50 95.00 100.00 326 80.00 140.00 96.00 100.00 331 120.00 145.50 95.00 100.00 34J 120.00 153.00 98.00 100.00 35J 160.00 151.00 96.00 100.00 335 160.00 152.00 100.00 100.00 o I f [ , F-10 t
Table F-11 Charpy V-Notch Test Results ., For Unit 2 Plate C6404-2 (LT), MCR Data t Test im pact Lateral Fracture l Temperature Energy Expansion Appearance ! ('F) (f t-lbs) (mils) (% Shear) i
-40 9 11 0
-40 12 18 0 ,
-40 8 10 0 10 25 19 10 '
10 44 30 25 10 26 21 15 - 40 42 31 25 ! 40 60 44 40 , 40 52 46 30 110 126 85 80 110 111 78 70 110 112 74 70 ,{i 160 145 85 95
'i 160 136 84 90 160 155 90 100 <
l a l f i 1 l i J I 1 F-11 : h I L. : i i e - - ,, ,
APPENDIX G SONGS, UNIT 2: HAZ TEST RESULTS l 4 e r : l As
l l l CE Baseline Tests"I SPECIMEN TEMP ENERCY 1.ATERJ.l. FR.ACT 3D TEST IMPACT trP APPEAR (F) (ft-lb) (sil) (1) 45J 150.00 5.00 3.00 0.00 43C 120.00 9.50 6.00 0.00
, 41M 00.00 23.50 19.00 25.00 415 00.00 35.00 20.00 30.00 466 40.00 30.00 24.00 30.00 ,
46K 40.00 40.00 34.00 30.00 l 478 0.00 82.00 56.00 50.00 41Y 0.00 101.00 70.00 10.00 44C 40.00 104.50 71.00 90.00 432 40.00 115.50 30.00 100.00 461 00.00 135.50 06.00 90.00 I 425 30.00 153.00 92.00 100.00 k l 79.00 90.00 43K 120.00 100.00 421 120.00 144.50 04.00 100.00 451 160.00 139.00 05.00 100.00 442 160.00 151.50 es.00 100.00 i I [ ( G-1
._m q
Battelle Capsule 97 t21 SPECIMEN TEMP ENERCY 1.ATERAL TRACT CRARPT IRRAD ID Tr.sT IMPACT EXP APPEAR FLUENCE TEMP. (F) (ft-lb) (ell) (t) (n/cm2) (r) 17.00 5.07E618 500.00 f 476 -79.00 12.00 9.80 41A -79.00 14.10 10.20 13.00 5.07E+10 500.00 41C -40.00 20.00 14.00 27.00 S.07E+10 500.00 , 413 -40.00 28.20 26.00 30.00 S.07E+10 $80.00 43U 0.00 38.30 30.40 45.00 S.07E+1e 500.00 4 42J 0.00 77.50 54.80 54.00 S.07E+18 500.00 42T 72.00 103.00 81.20 89.00 5.07E+18 $80.00 42C 72.00 114.20 84.40 93.00 5.07E+10 $50.00 444 160.00 130.00 07.00 100.00 5.07E*18 S40.00 i 100.00 S.07E+18 $80.00 412 140.00 132.40 05.60 44P 250.00 133.70 02.20 100.00 S.07E+18 $50.00 , 424 250.00 145.30 89.80 100.00 5.07E+10 500.00 i i e I I e h G-2 4 w e er O
1 I 1 l l l APPENDIX H c SONGS, UNIT 2: IRRADIATED Cvu DATA FROM CAPSULE 97 m {. l [' ) 4
Table H-1 Charpy V-Notch Test Results For Unit 2 Plate C6404-2 (LT) bradiated (f= 5.07 x 10) SPECIMEN TEMP THERGT , IJt1 TRAL TFACT ID TEST IMPACT EIP APPEAR (F) (ft-lb) (all) (g) 141 >0.00 6.08 4.44 4.00 111 0.00 8.10 6.40 5.00 15M 40.00 12.50 7.30 11.00 24T 72.00 23.50 23450 9.00 13M 72.90 27.49 26.40 13.00 [ 123 100.00 59.50 53.50 18.00 17E "IgnaDO 74.25 33.30 20.00 11M '350.00 123.40 W3.00 7 00 15E ~160.00 130.50 99.40 100.00 11U 200.00 127.30 93.40 100.00 1 124 200.00 136.20 105.80 100.00 i 12, . 0.00 1,. . . ....e ,00.00 ) I ( 1 l I
Table H-2 Charpy V-Notch Test Results For Unit 2 Plate C6404-2 (TL) Irradiated (f = 5.07 x 10")
~
SPECIMEN TEMP ENERGY LATERAL TRACT ID , TEST IMPACT EIP APPEAR (F) (ft-lb) (mil) (t) 214 0.00 4.00 10.00 4.00 23J 0.00 11.00 11.00 s.00 , 223 40.00 22.00 19.60 11.00 22K 72.00 27.90 32.80 15.00 22T 62.00 32.10 31.80 15.00 25U 100.00 44.10 42.80 42.00 23p 100.00 50.00 44.00 49.00 215 160.00 82.00 60.40 85.00 221 200.00 93.00 71.00 100.00 25L 200.00 98.00 (8.60 100.00 , 256 260.00 101.90 83.40 100.00
- t 211 260.00 103.00 83.00 100.00 ,
i I h
~
H-2
- a. i r
Table 11-3 Charpy V-Notch Test Results For Unit 2 Surveillance Wcld Irradiated (f = 5.07 x 10) SPECIMEN TEMP ENERGY IATERAL FRACT ID TEST IMPACT EXP APPEAR * (F) (ft-lb) (mil) (t) 37M -79.00 15.00 14.40 18.00 37L -79.00 18.40 20.00 13.00 1 3A3 -40.00 25.00 23.60 36.00 36M -40.00 45.40 36.60 40.00 36P 0.00 78.00 65.20 68.00 36K 0.00 82.40 64.60 70.00
! 31E 72.00 126.90 95.00 92.00 33P 72.00 138.20 102.20 100.00 ,
c 342' 160.00 134.00 99.80 100.00 36E 160.00 142.50 97.80 100.00 i 32P 260.00 147.90 97.60 100.00 341 260.00 149.00 100.40 100.00 i i L
+
a l l
.. - )
( H-3 L .
s i J Attachment E 1 1 San On~ofre Nuclear Generating Station, Unit 3 1 Response to Generic Letter 92-01 3
; Revision 2 i
..,- May 19,1994
'I J
Prepared by:
- AT! Cer:cding ;
San Ramon, CA and Sartrex Corporation Rockville, MD i
.s
)
Prepared for: 1 - Southern Califomia Edison ; 1 Irvine, CA ' 1 e* u k s' i a
.I u
I
=
CONTENTS Section _P_ ale 1 INTRODUCTION 1-1 2 REACTOR PRESSURE VESSEL SURVEILLANCE 2-1 PROGRAM-COMPLIANCE WITH APPENDIX H 3 FRACTURE MECHANICS 3-1 3.1 COMPLIANCE WITH APPENDIX G 3-1 3.2 BELTLINE MATEPJALS 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 3.3 FRACTURE TOUGHNESS RELATED DATA 3-2 l
, 3.3.1 Beltline Plate Material 3-3 j 3.3.2 Beltline Weld.s 3-4 l ., 4 ISSUES RELATED TO GENERIC LETTER 88-11 4-1 4.1 VESSEL TEMPERATURE DURING OPERATION 4-1 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 l
l ll ( Id (' I
l CONTENTS (cont'd) Section Pace APPENDIX A SONGS, UNIT 3: EVALUATION OF COMPLIANCE A-I ! WITH ASTM E185-73 AND E185-82 APPENDIX B SONGS, UNIT 3: BASES FOR PLATE CHEMISTRY B-1 MEASUREMENTS (Proprietary) APPENDIX C SONGS, UNIT 3: BASES FOR WELD C-1 CHEMISTRY MEASUREMENTS (Proprietary) APPENDIX D SONGS, UNIT 3: WMCs FOR BELTLINE D-1 MATERIALS (Proprietary) APPENDIX E SONGS, UNIT 3: MCRs FOR BELTLINE E-1 MATERIALS (Proprietary) APPENDIX F SONGS, UNIT 3: UNIRRADIATED Cvu DATA F-1 FOR PLATES AND WELDS APPENDIX G SONGS, UNIT 3: HAZ TEST RESULTS G-1 APPENDIX H SONGS, UNIT 3: IRRADIATED Cvu DATA FROM H-1 CAPSULE 97 l 1 l 1 I 1 1 l l C
l ILLUSTRATIONS
, Ficure Pace !
l 3-1 SONGS, Unit 3: Imcation and Identification of 3-6 l Beltline Plates and Welds ' t 3-2 SONGS, Unit 3: Data and Izast Squares Fit Curve 3-7 for Cvu versus Temperature, Plate C6802-1, TL 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 Tempc .huc, Plate C6802-3, TL Orientation, - MCR Data 3-5 SONGS, Unit 3: Data and 12ast Squares Fit Curve for 3-10 Cvu versus Temperature, Plate C6802-4, TL Orientation, MCR Data i
< 3-6 SONGS, Unit 3: Data and Iract Squares Fit Quve for 3-11
( Cvu vemos T r, Thee EtiBG2-5, ~11 Orientation, MCR Data i 3-7 SONGS, Unit 3: Data and Imast Squares Fit Curve for 3-12 l Cvu versus Temperanne, Plate C68EE-6, TL Orientation, MCR Data g 3-8 SONGS, Unit 3: Data and least Squares Fit Curve for 3-13 U Cvu versus To.or .u c, Plate C6802-1, TL Orientation, l Surveillance Baseline Data 3-9 SONGS, Unit 3: Data and1 mast Squares Fit Curve for 3-14 Cvu vernis Temperstme, Plate C6802-1, TL Orientation, Combined MCR and Surveillance Rameline Data
- 3-10 SONGS, Unit 3: Data and least Squares Fit Curve for 3-15 Cvu versus Tesig.nare, Plate C6802-1 LT Orientation, Surveillance Baseline Data
[ T
l ILLUSTRATIONS (cont'd)
, Ficure Pace j
3-11 SONGS, Unit 3: Data and least Squares Fit Curve for 3-16 Cvy 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 Izast Squares Fit Curve for 3-18 Cvs versus Temperature, Weld 9-203 (Heat No. 90069), WMC Data i 3-14 SONGS, Unit 3: Data and Izast Squares Fit Curve for 3-19 I. Cvu versus Temperature, Weld 9-203 (Heat No. 90144), WMC Data 3-15 SONGS, Unit 3: Data and Izast Squares Fit Curve for 3-20 Cvu versus Temperature, Surveillance Wcid, Surveillance Baseline Data 4-1 SONGS, Unit 3: Comparison of the Izast Squares Fit for the 4-4 4 Conibined MCR and Unirradiated Baseline Data with the Irradiated Cvy 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 Cvu Data and Izast Squares Fit for the Data from Capsule 97, Surveillance Weld p m' N h
1 TABLES Table Pace 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 Unirradiated 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 > 4 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 Location for Beltline Materials on 12/16/91 and at 32 EFPY l I
Section 1 INTRODUCTION The Nuclear Regulatory Commission (NRC)in Generic Letter 92-01 (GL 92-01) requested all holders of operating licenses or crmmetion permits for nuclear power plants to submit information needed to assess compliance with requirements and commitments regarding reactor vessel integrity. Revision 0, .fune 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 WeJd 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), the esults of calculations performed by Southern Califomia Edison Company (SCE) to better characterize fluence conditions at Weld 8-203, and the results from calculations performed to evaluate the upper shelf toughness far Weld 8-203. It also indicated that additional information was required to couGuu heat numbers forthe surveillance weld material and to identify the weld heat number for an nnWnt&d girth weld hetry. This revision (Revision 2)incor;-=f~ =M*i=1 -+mi=le data and information obtained from the SONGS Unit 3 PSSS Tendor, ABB-CE. Dese data pmvide the heat number for the surveillance weld, and the weld wireand flux camhinatina, 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 materialsin 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 typer 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 surmillance weW dass are inciese proxhnity. Cumstly, no information is available to explain the difference in the impact data for the surveilkmce weld and Weld 9-203, wire heat 90069. However, based on the chemi*y and impact properties of the surveillance weld, the surveillance weld does provide a enneervative 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 pog-u. l In previous versions of this report the initial RE.,r for the vessel beltline material with the highest end oflife adjusted reference temperature (i.e., the plate material used in the surveillance ((~ 1-1 a
program) was determined using a combined data set obtained from the materials certification report (MCR) and the baseline surveillance program. In Revision 2, the initial RTer 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 RTor, 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 i
vessel fabrication. This MCR data thus established the initial RTer 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 te 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 suneillance 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 I effects, including irradiation temperature and adjusted reference temperature for evaluation of the beltline materials relative to GL 88-11 and 10CFR50.61. i 1-2
i l l Section 2 REACTOR PRESSURE VESSEL SURVEILLANCE PROGRAM COMPLIANCE WITH APPENDIX H i 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 Ame+== 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 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 current approved version). As stated in the SONGS, Units 2 and 3 Final Safety Analysis Report (FSAR), Appendix H, { requirements were met (with one ,rceprian) through compliance with ASTM E185-73. The one exception to meeting 10CFR50, Appendix H requirements had to do with the method of attachment of the holders for the six sur "'~e 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 vesselin the beltline region (as they did for all ABB-CE NSSS-l designed vessels), and.2his ===nach vialaneet 2he requirements in the early 1970's version of L 10CFR50, Appendix H. NRC K./M a ABBCE Topical Report (CENPD-155-P, C-E i Procedure for the Desien Fabricati= Instalh - and Inspection of Surveillance Holder Assemblies) and found thepractice and procodmus acceptable. l The current version of 10CFR50, A==tix H does not treat this method of attachment of the capsule holders as a nonnamplinane 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, constmetion and in-service impection of the attachments and the attachment welds must be done according to seguirements for permanent stmetural attachments soitacant vessels givenin Sections HI and XI of the ASME Code.
The design and location of the capsule holders shall permit insertion of j replacement capsules." i i l I This wording was derived from the ABB-CE Topical Report, and the SONGS units have met the additional ASME Code, Sections IH and XI, design and inspection requirements. Therefore, there are no deviations or exceptions == led from the current Appendix H of 10CFR50. 4 The details of the SONGS, Unit 3, seveillance program have been described in the FSAR and ]( 2-1
i subsequent surveillance program testing reports, baseline I I and irradiated.[2j The first capsule ; 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, i i 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,I8-33 and is provided for reference in a subsequent section of this report. S 4 1 h ~ 2-2
l
\
Section 3 FRACTURE MECHANICS i This section evaluates compliance with 10CFR50, Appendix G, and identifies the location, heat l l treatment, key residual and alloying element contents, and unirradiated fracture toughness l 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, additional information was obtained from the unirradiated baseline surveillance material report)U ,
and the irradiated material in the 97* location surveillance capsule (Capsule 97), which was removed from Unit 3 at the end of the fourth fuel cycle?l 3.1 COMPLIANCE WITH APPENDIX G The materials in the beltline region of SONGS, Unit 3, comply with the requirements of Appendix G,10CFR50. A summary of compliance with 10CFR50, Appendix G, as specified in the FSAR for SONGS, Units 2 and 3, and updated during preparation of this report, is listed in Table 3.1. 3.2 BELTLINE MATERIALS IN SONGS, UNIT 3 3.2.1 Location t Figure 3-1 is a representation of the SONGS, Unit 3, reactor pressure vessel, and identifies the plates and welds and their location in the beltline region. < The heat numbers for the beltline plates shown in Figure 3-1 are presented in Table 3.2. The weld wire and flux combination for the beltline welds shown in Figure 3-1 and the surveillance ! welds are presented in Table 3.3. Source documentation has been obtained to confirm the properties of all beltline plates and welds. I 3.2.2 Heat Treatment The heat tratment for the plate materials consisted of austenitization at 1575150'F for 4 hours; water quenched and tempered at 1225 i 25'F for 4 hours. For ASME Code qualification, the plates were stress relieved at Il50125'F for 40 hours 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 depended upon the sequence of vessel fabrication; intermediate and final stress relief times were ( selected such that the total did not exceed 40 hours for any particular portion of the vessel. 3-1
Longitudinal weld seams would see stress relief times near the 40 hour maximum, while the closing girth weld in the behline region would see approximately half this amount of time maximum. All of the Mg of plate matenals was performed on pieces with essentially an identical heat treatment as the actual reactor vessel. The surveillance weldment received a final 41-hour and 45-minute stress relief at 1100'F to 1150"F. 3.2.3 Kev Residual and A11 ovine Element Contents 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 I 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. t A second set of data is included for Plate C6802-1. This set was obtained from broken surveillance specimens when the first irraduted willance capsule from Unit 3 was tested.I21 Table 3.5 contains the Cn, Ni, P, and S contents reported for the beltline welds. The wurce documents for the information in Table 3.5 are presented in Appendices C and D. Three chemistry measurements have becu made for the suneillance weld and also are reported in Table 3.5. The first chemistry measurement was made as part of the original baseline ul , while the j- second and third were cbtained from broken Charpy specimens from Capsule 97t2), I 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 incbde the chemistry factors determined for each reported set of Cu and l Ni contents using Regulatory Guide 1.99, Revision 2. 3.3 FRACTURE TOUGHNESS RELATED DATA i This section presents the results from the Cy, tests, and summarizes the upper shelf energies (USE) and the results from the drop weight nil de:tility temperature (NDT) tests for the unirradiated beltline plate and weld materials in SONGS, Unit 3. The unirradiated reference temperature (RTm) values were dets +1 from the Cvu 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 Cvu values fer those tests (at least 3) where the percent shear on the fracture surfaces was equal to and greater than 95%. l l
\ The fracture tonghnece data for the plate mere obtained from the MCRs (see Appendix E of this I report) and baseline surveillance program.m The fracture toughness data for the beltline welds I were obtained from the FSAR and confirmed by WMCs (see Appendix D of this report), and the j data for the surveillance weld was obtained from the baseline surveillance program. For 3-2
[
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 i surveillance program. The raw Cm data for the past HAZ testing are attached in Appendix G of this report. 3.3.1 Beltline Plate Material
' Because fracture toughness requirements for reactor pressure vessels are based on requirements to test specimens oriented transverse to the rolling direction, the data presented here are for the transverse (TL) orientation with one exception. The exception is for the beltline Plate C6802-1, which was included in the surveillance program. Because the surveillance program for SONGS, Unit 3, was reported to contain longitudinally (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 Cm data as a function of test temperature for beltline Plate numbers C6802-1, -2,
-3, -4, -5, and -6 are presented in Figures 3-2 through 3-7, respectively. For convenience, an average curve through the data is also shown in each figure. The average curves were determined ,~ using a least squares fit to the data and a hyperbolic tangent functional form, where the lower shelf was fixed at 2.2 ft-Ib and the upper shelf was fixed at the value determined using the definition in ASTM E185-93 for specimens having fracture surfaces with 95% and greater shear.
For convenience, the figures also indicate the values of NDT, USE, the temperature at which a minimum C, equals to 50 ft-lb (T @ 50 ft-lbs) is achieved consistent with the applicable method of ASME, Section III, NB-2331, and RTer. 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 unitradiated baseline to evaluate the results for the irradiated surveillance tests (see Section 4). Table 3,6 is a summary of the unirradiated NDT, RT w r, 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 RTer for all plates. 3-3
Figure 3-10 shows the data and least squares fit line for the LT orientation for surveillance Plate C6802-1,10 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 C, 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 cur ently 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. l ) ' 3.3.2 Beltline Welds I 1
. A full Cw versus temperature curve was obtained for the material in Weld Seams 3-203 A, B, l C, and the data points and least squares hyperbolic tangent fit through the data are presented in Figure 3-12. A full Cw 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 j 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.
y Figure 3-15 presents the Cm data and least squares hyperbolic tangent curve fit for the [ surveillance weld material, which was reported 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 j , impact properties of the surveillance weld, the surveillance weld does provide a conservative j representation of Weld 9-203 overall, and is adequate to assess the shift in reference temperature l and drop in upper shelf energy for the SONGS, Unit 3 surveillance program. l Table 3.8 presents a summary of the unitradiated NDT, RTm, 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
(wire Heat Nos. 90069 and 90144), available Cvy data indicate that there is a minimum of 50 ft-h, absorbed energy at 60*F above NDT and, consequently, RTym equals NDT. Because fewer than three specimens were tested at each temperature, the graphical method of NB-2331 (a)(4) was used to deterndne RTmg for the surveillance weld as shown by the intersection of the dashed line and the 50 ft-lb Cvy level in Figure 3-15. The upper shelf energies listed in Table 3.8 for Welds 3-203 A,11, C,9-203, and the surveillance wcld were obtained by avenging the test results where 95% shear or greater was exhibited. The i USE for Welds 2-203 A, B, C was obtained from the data in Table 3.7 by averaging the three Cvy 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 Cm data points obtained at +10"F. It was determined that the CVN data at -10 F were not on the Upper Shelf. I i, [ 35 I
I RE ACTOO VESSEL SELTLINE MATERIALS NOTSHOWN M 7 "lM 7 NI"1 7 "1!"lO INTERMEDIATE SHELL WELD SEAM NO.2 203C
~
C-LOWER SHELL C,hk N WELD SEAM NO.3 2038 WELD SEAM NO. 3-203C O\ ) l PLATE NO. C-6802-6 j C 0 -' C"-'l ~="3 E 5 t i t 42 *10 \T f
~~""
30" lD OUTLET INLET NOZZLE NOZZLE n [ UMK TO MEWEDMTE r SHELL C32H 5EAM WELD NO. 8-282 - 4
- N,K ,_, /
7 INTERMEDIATE SHELL LONGITUDINAL WELO l
)
/ SEAM NO.2 2038 INTERMEDI ATE SHELL -
PLATE NO. C-6802 INTERMEDIATE SHELL I y PLATE NO. C-6802-2 { INTERMEDIATE SHELL LONGITUDINAL WE LD "# INTERMEDI ATE-TO-LOW ER SEAM NO.2 203A ,
- SHELL GIRTH SEAM I- /
WELD NO 4-203
~ ~
INTERMEDIATE SHELL PLATE NO. C-6802 3 ' l LOWER SHELL PLATE - LOWER SHELL o NO. C-6802 , /' PLATE NO. C4802-5 LOWERSHELL LONGITUDINAL WE LD - SEAM NO.3 203A i _ pu },m_ [ - g/ I!!!!!!!!!!!i5i!!!!!!!!!!!!!! k Figure 3-1. SONGS, Unit 3: I.ocation and Identification of Beltline Plates and Welds. 4 3-6
200 -
. San Onofre Unit 3 MCF; Data Material: Plate C6802-1, A533B1 Orle'ptation: TL 150 =
USE =18 bitis + + + NDTl = -20 'F e " T @; 50 ft-lbs = 100 8F . RTnht = 40 8F r
~
E 100 =
- j
. e d - ) >i c .
tu
~
Z O [ t O l 50 - b o Measured i O Calculated O i 0 ,
-200 -100 0 100 200 300 400 500 Temperature in Degrees F ;
1 i
- Figure 3-2. SONGS, Unit 3
- Data and Least Squares Fit Curve for C versus Ternperattue, Plate C6802-1, TL Orientation, MCR Data.
I'
l l i l I t 200
~
3an Onofre Unit 3 MCRbata
. Material: Plate No. C680242, A533B1 150 =
' "" " + +- '
USE = 115 ft-lbs NDT m -20 SF T @ f50 ft-Ibs70= SF
- 4. . RTndt = 10 'F
.1 . a E 100 e
=
C ji u! , 1 " Z
> ~ '
O o @'
~
i 0 50 = O O Measured Calculated
' ' " " 'l '''''" ''''''''''''''''''l 0
-200 -100 0 100 200 300 400 500 n
Temperature in Degrees F Figure 3-3. SONGS, Unit 3: Data and Least Squares Fit Curve for Cm versus Temperature, Plate C6802-2, TL Orientation, MCR Data. , I 1 l (# l
. 3-8 .m
i l I 200
. San Onofre Unit 3 ,
MCR Data Mater lal: Plate No. C6802-3, A533B1 Orien':ation: TL 150 -- USE_x_105. ft-lbs
~
NDT -1 0 'F e T @ bo i ft-lbs = Bo 'F a " RTndt = 20 'F r i 8 ' E 100 -- 0 -- - C - W > z O' O O l 50 = - -'
- O Measured o
o Calculated
..- m a e a a l' s e e a l' s a e a l' s e a e I e a e a L e a e a 1
-200 -100 o 100 200 300 400 500 f Temperature in Degrees F Figme 3-4. SONOS, Unit 3: Data and Least Squares Fit Cuive for Cm versus Temperature, Plate C6802-3n TL Orientation, MCR Data.
~, 3-9
-l
l i 5 200 - San Onofre Unit 3
. MCRData Matelial: Plate No. C6802-4, A53381
~
Or!en!t ation: TL 4 150 - - US 'er118ttbs "
. NDT -30 8F ,
a ~ o ft-Ibs = 70 'F
$ T RTn@dt = 10 'F o , c -
h g 100 C o 1 e . nu
. 5 .
A i O , 3 . 50 - 0-Q v r o ~ Measured Calculated !
.I ~
o l g .........v .... e . ...i ....i ....i ....e L
-200 -100 0 100 200 300 400 500 Temperature in Degrees F Figure 3-5. SONGS, Unit 3: Data and Izast Squares Fit Curve for Cm versus Temperature, Plate C6802-4, TL Orientation, MCR Data.
E 3-10
200 San Onofre Unit 3
. MCR D'ata Materidi: Plate No. C6802-3, A533B1
~
Orientdtion: TL 150 USt: elTTB ft;Iti8 1 NDT = p T m T @ 50 ft-lbs = 70 'F h RTndt 's 10 Y E 8 8
- T g 100 f
E / Z
> ~
U o 50 = O Measured o Calculated o
-200 -100 o 10o 200 300 400 500 Temperature in Degrees F Figure 3-6. SONGS, Unit 3: Data and Izast Squares Fit Curve for Cm versus Temperature, Plate C6802-5, TL Orientation, MCR Data.
L L 3-11 f L
i i l 200 --
, , San Onofre Unit 3 MCR Data
~
Mater lal: Plate No. C6802-B, A533B1 150 - Orientatiort: TL_. .-. + i
~
USE != 92 ft-Ibs
, NDT y -40 8F
.o -
T @ 50 ft-Ibs = B0 SF A - RTndt' = 20 'F
~
@ 100 -
. o
( y - 0 l z -
, > ~
i 0 -t
, 50 -
O o Measured } Calculated O L ,
-200 -100 0 100 200 300 400 500 f
Temperature in Degrees F Figure 3-7. SONGS, Unit 3: Data and Izast Squares Fit Curve for Cw versus Temperature, Plate C6802-6, TL Orientation, MCR Data. c . i
- 3-12
1 i
?
2oo .
, f = 0.0 i > > .
. 4 . . *
, ,i , . . f
, San Onofre Unit 3 ; ; ; ; l Surveillance Program l l l l
' Material:l Plate No.lC6802-1,lSA533B-1 l l I , I iso . Orientatio.n : TL - - -,, - - - - - - - a - - - - - - - +d,------ ,------.--------
. USE = 9'2 ft-Ibs !,
i
, .i .
i , NDT = ,10F '
,o. .
s., . t g , , . . . ,
, . O .
s ' l lc ? i l e l 9 e 1oo .----- ----------
. ;------ t------ t------ ,--------
c l l :o l l m - . a, O , o ; ; z,, o , O . o . t
, 9 , .
, f . ,
so - - - - - - -, l- - - - - - - -l - D . c t
-4.-------?.------.'------.l--------
., . o. . ., ,
l . .
, D, ,
, 0 ,
, ,i e, i
,. o
' D ' '
, , . .' .' i ,
, ... . . . .. .: .. . . . 2 . ..: ....
20o 10o o 100' 2o0 soo soo soo 1 l Temperature in Degrees F i, i i
?
t Figure 3-8. SONGS, Unit 3: Data and Least Squares Fit Curve for Cm versus Temperature, Plate C6802-1, TL Orientation, Surveillance Baseline Data. ' 1 3-13 i a r~ l l
T 200 '
, . , i . .
, . . , , , i
' San Ono,fre Unit 3,' ,' .' ,' '
Combined MCR & JJnirradiated Baseline Data
. Material! Plate No 'C6802-1' SA533B .1 l l Orientation: TL-l l l l l USE = 95 ft-Ibs e i i , i 150
-------;--------l-------i.------t,-------F-------l--------
e t i 4 . , N ,
.o ,1 4
I f e
*T e e .
- , , , .i ,i
- u. . . . . ,
. , . e O ' '
io .'O . i a 100 i .
,-------,------+j----------------------
f w -------.-------- i a, , c . . . . . . W l l O O O l l l 2 l O
> i l
i l O l i l l O . , . O.
, ,i
.i .
,t 9 .,
8 50
- - - - - - -l- - - - - - - -l - n - - - - - - t - - - - - - - l- - - - - - - -l- - - - - - - -
l l
. , 06, l l
l 1 , , t 1 I
' 'O ' '
8 O .' I 4 e' I . O ' ' ' 5 i O g i
, ,a e' 3 i ,
e i i i . ; o . . . . . i.. ....: ...: .. .: ... 200 -100 0 100 200 500 400 500 Temperature in Degrees F Figure 3-9. SONGS, Unit 3: Data and Least Squares Fit Curve for Cw versus Temperature, ; Plate C6802-1, TL Orientation, Combined MCR and Surveillance Baseline Data, i O 3-14 1 i l l
200 - f = 0.0 150 - San Onofre Unij 3 Surveillance Program
~
a Material: Plate No. C68021, SA533B1 f - Orie'h tation: LT u- . USE = 91 ft-lb4 ,
. $ 100 NDY = 0 8F e g i
, D 0 .
O so -
--c -
a g
, ... ...........i ....e ....i ....i ....i 200 -100 0 100 200 300 400 500 Temperature in Degrees F 1
Figure 3-10. SONGS, Unit 3: Data and Least Squares Fit Curve for Cm versus Temperature, , Plate C6802-1, LT Orientation, Surveillance Baseline Data. ' r n 3-15
200
. San Onofre Unit 3 MCR Data
~
Mate' rial: Plate No. C6802-1, SA53381 Oriebtation: LTl 150 - USE!.=_131_&lbs . NDT = -10 'F
= ' 8 r -
100 = b ( c . SU Z 0
~
O Measured , 50 = 6 O Calculated
~
O
- O O
Oj o
-200 -100 0 100 200 300 400 soo Temperature in Degrees F Figure 3-11. SONGS, Unit 3: Data and Least Squares Fit Curve for Cm versus Temperature, Plate C6802-1, LT Orientation, MCR Data.
t 3-16
i 200 - O
. O O
l l 150 -
+ 4
" ~
l
@ 'o E "
g San Onofre Unit 3 g - 8 WMC Data ;
@ 100 = -, yaterial: Weld Seam 3-203 g ,
OSE = 161 ft-lbs ; W NDT = -70 'F 2 o i @ 50 ft-lbs = -40 'F y . RTndt = -70' 'F , 50 -
~
O Measured ) o Calculated . ...r ....i ....l ....i ....r ....e ....r o
-200 -100 0 100 200 300 400 500 '
Temperature in Degrees F i Figure 3-12. SONGS, Unit 3: Data and Least Squares Fit Curve for Cm versus Temperature, Weld 3-203, WMC Data 3-17
i l l i I 200 - San Gnotre Unit .3 WMC bata !
. Mater at: Weld Seam 9-203 ;
Heat No.90069l 150 - USE = 123 ft-lbis NDT = -60 8F 4 j 0 T @ ho ft-Ibs = e40 0 *F0 "J, RTndt = -60 'F G 8 m
~
i
,E 100 =
i c . m i
~ O Z 6
> o o "
50- O g Measured
. Calculated
~
" o O
O
"E '''''' **
-200 -100 0 100 200 300 400 500 '
Temperature in Degrees F Figure 3-13. SONGS, Unit 3: Data and least Squares Fit Curve for C versus Temperature, Weld 9-203 (Heat No. 90069), WMC Data. ] l
. l 3-18 l L . _ _ . _ ___ _ _ _ __ _ _ - __
200 --
~
San Onofre Unit 3 WMC Data
- Materiat: Weld Seam 9-203 150 Heat No. 90144 USE: 91 ft-lbs
, NDT = -50'F g "
T @ !!o ft-Ibs = 'lo'F g - RTndt = -50'F A , E 100 I E . O i Z U o ~ O Measured O
. Calculated
, L..< ...., ...., ...., ...., ...., ....,
-200 -100 o 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, Weld 9-203 (Heat 90144), WMC Data.
't 4-L 3-19 M
l 200 = l 5 f = 0.0
~
San Onofre Unit 3
~
Survelliance Program daterial: Weld y , USE = 82 ft;-lbs ' E " FfDT = -60 'F g T @ 50 ft-lbs = 30 8F g 100 - RTndteS0! "i + 0 o E
!. . 1 z o n a u a
- U i
. O O
- . O
, s0 -/ { - i
/
O O
/
f . o / O j , M 19..., ...., ....r ....e ...., . . . . r 200 -100 0 100 200 300 400 s00 l Temperature in Degrees F Figure 3-15. SONGS, Unit 3: Data and Izast Squares Fit Cutve for Cw versus Temperature, Surveillance Weld, Surveillance Baseline Data. i ('. 3-20
~
e
I I l Table 3.1 SONGS, Unit 3: Compliance with 10CFR50, Appendix G. j Paragraph Description of Non-Compliance Comment l II.B Series 4xx stainless steels are Consistent with ASME Code in effect. ! purchased and treated to Code - requirements. No RTer or l drop weight Tor temperatures are determined.. III.B.5.a Records of fracture toughness Appendix G was not applicable at the testing do not include a time tests were performed. 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 defined by Paragraph II.H, program include weld and HAZ material includes the weld heat- from the most limiting plate. Results 4 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. HI.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 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 temperatur.: 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 C,in excess of 100 ft-lb. These results indicate that the intent of Appendix G has been met. 7 i f i 3-22 f
i Table 3.2 SONGS, Unit 3: Plate and Corresponding Heat Numbers for the Beltline Plates.
)
Lukens Plate Number Heat Number i C6802-1 C9195-2 C6802-2 C9218-2 C6802-3 C9195-1 C6802-4 C9220-1 C6802-5 C9218-1 C6802-6 B3388-1
=
e 3-23
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
- a. Basis is SONGS Unit 3 FSAR and is consistent with handwritten note in Appendix D.
- 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.
r e 3-24
I l Table 3.4 SONGS, Unit 3: Key Residual and Alloying Element Contents for Beltline Plates.* d k Plate ABB-CE Number Lab No. Cu Ni P S CF6 C6802-1 P14214 0.06 0.58 0.005 0.013 37 - P18195 C6802-l* 0.06 0.58 0.009 0.014 37 C6802-2 P14244 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 g P15391 C6802-5 P14453 0.04 0.55 0.011 0.013 26 P15392 C6502-6 P14454 0.06 0.62 0.007 0.013 37 P15393 1.
- a. Average values (see Appendix B) l
- b. Chemistry factors from Regulatory Guide 1.99, Revision 2
- c. Measured when the surveillance tests were performed for Capsule 97t2 j l
I, 3-25 I~ ~ l. A
Table 3.5 SONGS, Unit 3: Key Residual and Alloying Element Contents for Beltline Welds. I Weld ABB-CE Seam Lab No. Cu Ni P S CF' 2-203A Dl?360 0.04 0,17 0.011 0.012 40 2-203B D17361 0.05 0.21 0.011 0.013 50 1 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 1 9-203* D28503 0.05 0.04 0.007 0.011 31 8-203 D17888 0.05 0.17 0.009 0.008 46 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. l Values from WMC for Type Mil B-4 Wire, Heat No. 90069, Linde Type 124 Flux, i 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 developedV3
- c. Measured when the surveillance tests were performed for Capsule 97M
~ I ( 3-26 i
Table 3.6 SONGS, Unit 3: Beltline Plate Material Unitradiated Fracture Toughness Tests Results Summary, TL Orientation. Initial l Plate NDT RTe r Procedure to USE Number (*F) ('F) Determine RTer (ft-lbs) l C6802-l* -20 6 40 NB2331 (a)(3) 95 j 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) e
- b. An NDT value of -20*F was determined when the plate was purchased (-10'F we determined from the baseline surveillance program).
I L B IC 3-27
Table 3.7 SONGS, Unit 3: Charpy Absorbed Energy Values for Weld Seams 2-203 A, B and C, and Weld Seam 8-203. Test Temperature Charpy Energy Weld Seam (*F) (ft-lb) . i 2-203 A, B, C +20 125, 138, 145 8-203 -10 95, 84, 94
+ 10 137, 118, 119 i
i 1 5 l 3-28 T
Table 3.8 SONGS, Unit 3: Beltline Weld Material Unirradiated Fracture Toughness Tests Results Summary. ' i i Initial NDT RTm Procedure to USE Weld Seam (*F) ( F) Determine RTm ' (ft-lbs) 2-203 A, B, C -40' -40 6 NB-2331 (a)(2) 136 3-203 A, B, C -70' -70 NB-2331 (a)(2) 161 8-203 -70 -70 125' NB-2331 (a)(2) 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
\
- a. NDT values obtained from the FSAR and documented in Appendix D ;
1
- b. Estimated using the average of Cm 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) l
- 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 l l i ~ 3-29
I Section 4 ISSUES RELATED TO GENERIC LETTER 88-11 , NRC issued Generic Letter 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 535'F which applies above 30% power. The normal operating band of T, ranges from 545'F at zero power to 553*F at 100% power with a tolerance of 2*F. Thus, there is no time during normal power operation that the SONGS, Unit 3, vessel dr surveillance capsules experience temperatures below 525'F. 4.2 APPLICABILITY OF SURVEILLANCE DATA 1 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 i 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 10 8 n/cm (E > 1 MeV); the capsule fluence 2 was about 20% higher at 5.07 x 1058 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 espsule 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.l23 The peak fluence value at the vessel inner surface is 6.6 x 1028 > n/cm 2, and the associated capsule fluence is 8.0 x 10 8 n/cm2, 4-1
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/cm2 j2j 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/cm2, 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 shifts 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 SCEN 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 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. 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 125'F), but the other two have not been satisfied since only one capsule from each vessel has been pulled and evaluated. To satisfy these last two requirements, the second capsules (which will not be pulled until about 15 EFPY) must be evaluated to supply two val.1 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), ar.a 4-2 (surveillance weld). Appendix H contains, in tabular form, the absorbed energy, lateral expansion, and fracture appearance (% shear) for the irradiated surveillance materials. ~ ( 4-2
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 Reylatory 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 + 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 RTm7 (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 RTers were taken from Tables j 3.6 and 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. Note the low levels of ART for all welds. The results in Table 4.2 show that the degree of radiation
; embrittlemeni in the SONGS, Unit 3 reactor vessel beltline materials is relatively low even at j 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 I 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-Ib specified in 10CFR50, Appendix G. 4-3 i4
l l 200
~
San Onofre Unit 3 Survel.llance Pro' pram Material: Plate SAS3381 Haat Eo. C6Bo2-1 f=0.0 150 =_ rienthliom R f = 8.oe+18 ~
, O f = 8.oe+18 g .
1 ii' - E 100 = ! a c . Ja tu ,- i j
/
50 jo / _ v f
' /
/ O
/ O
/ Q (f
/
m a e e a I
,p o e e e a I e e a a 1 e a e a I e e a a l' s e e e l'
-200 -100 o 100 200 300 400 500 Temperature in Degrees F Figure 4-1. SONGS, Unit 3: Comparison of the least Squares Fit for the Combined MCR And Unitradiated Baseline Data with the hdiated Cm Data and least Squares Fit for the Data from Capsule 97 PJw t ' 5802-1, TL Onentation.
.(. 4-4 8 _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - - - - - - - - - - - - - - - - -- o
L i 200 - i !
, San Odofre Unit 3, i Survell ance Program ,
Material: W eld l
. f=0.0 '
150 = ~
- f = 8.oe+18
- O f = 8.oe+18 E '
i 9 100 -- c . t W .
? ,r" o O
- / l i . /O
/oD O
/ ,
50 --
/
i , /c O
- I /
/ l f'b '
i
. ,/ 1
,/t
~m u a R l B R R R I f R S S lI R R R R l t R R R l A R R R l' R R R R j l .
-200 -100 o too 200 300 400 500 Temperature in Degrees F I
.1 Figure 4-2. SONGS, Unit 3: Comparison of the least Squares Fit for the~ -
' Unitradiated Baseline Data with the hradiated Cm Data and Least Squares Fit for the Data from Capsule 97, Surveillance Weld. ,
4-5 1
i Table 4.1. SONGS, Unit 3: Surveillance Capsule Shift Results. 30 ft-lb Shift ( F) Material / CF ff Orientation W RG1.99R2 Current C6802-1/TL 37' O.94 55 35 58' Surveillance 2 86 0.94 32 26 30d Weld t
- a. See Table 3.4 (Cu = .06; Ni = .58)
- b. Based upon the average chemistries - see Table 3.5 (Cu = .03; Ni = .09)
- c. Based on the combined data set from the MCR and baseline surveillance program, see
. Figure 3-9
- d. Based on the baseline surveillance data, see Figure 3-15 i .
i
~
( l 4-6 L
Table 4.2. SONGS, Unit 3: ART Estimates at the Inner Surface Location for Beltline Materials on 12/16/91 and at 32 EFPY. l Fluence Function ART (*F)* Pine No./ CF at the Inner Surface at the Inner Surface Weld Seam 12/16/91 32 EFPY 12/16/91 32 EFPY , C6802-1 37b 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 l C6802-5 26 0.95 1.37 60 80 ' l C6802-6 37 0.95 1.37 89 105 l 2-203 A, B, C 39c 0.95 1.37 34 66 ;
, 3-203 A, B, C 43d 0.95 1.37 12 45 -
t 8-203 46 0.09' O.25' -62 -48 :
\
9-203 (90069) 34 0.95 1.37 4 34 l 9-203 (90144) 31 0.95 1.37 8 34- j l 1 i i
- a. ART is the adjusted reference temperature equal to the predicted shift (CF x ff) plus the l
initial RTm plus a margin term equal to 34'F for plates or 56*F for welds (unless the ! predicted shift is less than the margin term, in which case the margin is equal to the ; predicted shift) i
- b. Based upon measured chemistries for this plate (.06 Cu / .58 Ni) - see Tables 3,4 and 4.1
- c. Based upon average chemistries for these welds (.04 Cu/.15 Ni) - see Table 3.5 [
- d. Based upon average chemistries for these welds (.04 Cu/.20 Ni) - see Table 3.5 l
\
- e. Fluence function h based upon the peak vessel fluence divided by 108W t i
(w 4-7 I
- m. l 1
l
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) E 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 1 e. Based on the baseline surveillance data, see Figure 3-15 1
I J x 4-8 - . l
i l l
\
Table 4.4. SONGS, Unit 3: Upper Shelf Estimates at the Quaner-Thickness Location for l 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 C6802-1 0.0 66 0.51 2.5 80 73 C6802-2 0.04 0.51 2.5 97 89 C6802-3 0.06 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 2-203 A, B, C 0.05" 0.51 2.5 114 105 3-203 A, B, C 0.04* 0.51 2.5 135 122 8-203 0.05 0.005 0.023 119d 1158 9-203 (90069) 0.06 0.51 2.5 102 92 9-203 (90144) 0.05 0.51 2.5 76 70
- a. The upper shelf energy is estimated from Regulatory Guide 1.99, Rev. 2, taking into account the projected fluences and measured chemistry
- b. Based upon measured chemistry for this plate -- see Table 3.4
- c. Based upon average chemistries for these welds - see Table 3.5
- d. Based upon an extrapolation of the curves in Regulatory Guide 1.99, Rev. 2
( 4-9
I l l 1 Section 5 i l REFERENCES [1] A. Ragi, Southern California Edison San Onofre Unit 3. Evaluation of Baseline Speeimens. 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 Cansule Removed from the 97* Location, Westinghouse WCAP-12920, Revision 2, May 1994. [3] M. P. Manahan and J. Garrabrandt, Testine and Analysis of Unitradiated Heat Effected-Zone (HAZ) Material from the San Onofre Nuclear Generatine Station Unit 3 (SONGS-2}, 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 Specimens from the San Onofre Nuclear
, Generatine Station Unit 2 (SONGS-2). Battelle Columbus, December 1988.
[6] R. Chang, " SONGS 2/3 RPV Fluence Ratio at Weld 8-203", SCE Calculation No. N-1020-065, December 1992. 1 i t 9 L ( g 5-1 ! F ( l
l i I i I t APPENDIX A ! i SONGS, UNIT 3: EVALUATION OF COMPLIANCE i WITH ASTM E185-73 AND E185-82 -: l c .. 1
)
6 q ee' d i 1 n.
Summary 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 100 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 greater than 5 X 10" n/cm2 4.1 Test Material - Test specimens Compliance shall be prepared from the actual 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
, weld heat-affected-zone (HAZ) if a weld occurs in the irradiated region.
h 4.1 The base metal and weld metal Compliance I to be included in the program should represent the material that may limit the operation of the reactor during its lifetime. l ( 1 J. A-1 E
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 (weld wire of rod, must come from one of the heats used in the irradiated region of the reactor vessel) and the same type of flux, and (3) the heat-affected-zone associated with the base metal noted above. 4.1.1 Representative test stock to Compliance provide two additional sets of test specimens of the base metal, weld and heat-affected-zone shall be retained with full documentation and identification.
, 4.1.2 Fabrication History - The Compliance test material shall receive a fabrication history (austenitizing, quench and tempering, and post-weld heat } treatment) fully representative of the fabrication received by the ; material in the irradiated region j of the reactor vessel.
4.1.3 Chemical Requirements - The Compliance 7 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).
( A-2 I
Summary of Requirements San Onofre Unit 3 Program per ASTM E185-73 4.2 Charpy V-notch impact Compliance 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 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
. 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) l A-3 b
Summary of Requirements San Onofre Unit 3 Program per ASTM E185-73 4.4 Number of Specimens - The Compliance minimum number of test specimens for each exposure shall be as follows: Case A Case B Charpy Charpy Tension Base Metal 12 12 2 Weld Metal 12 12 2 HAZ 12 12 - 4.4 At least 15 Charpy impact Compliance spacimens 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 g used to establish unirradiated tensile properties. 5.1.1 Vessel Wall Specimens Compliance i (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. u 6 4 A-4 J ..
Summary of Requirements San Onofre Unit 3 Program per ASTM E185-73 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. 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 capsule.
f 5.3 Test Capsules - To prevent The specimens from the 97* Capsule ! deterioration of the surface of Location had corroded. , the specimens during test, the Metallugical evaluati n by SCE { specimens should be maintained in concluded the corrosion (in the form of pitting) to be an inert environment within a insignificant, with a maximum depth . corrosion-resistant capsule, of 0.8 mila. The results of the l ! Charpy testing were deemed credible, and are therefore in compliance. l 5.3 The temperature history of the Compliance 1 specimens shall duplicate as ; closely as possible the temperature experienced by the reactor vessel. tr'- A-5
Summary of Requirements San Onofre Unit 3 Program per ASTM E185-73 5.3 Surveillance capsules should Compliance 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 insertion of replacement capsules into the reactor at a later time in the lifetime of the vessel. i 5.4 Specimen Withdrawal - A Compliance minimum surveillance program shall consist of three capsules for case A and five capsules for Case B. It is recommended that capsules be withdrawn as described in Table 1. (See Table 1 of ASTM E185-73.) 6.1 Radiation Environment - The Compliance neutron flux, neutron energy spectrum, and irradiation temperature of surveillance specimens and the method of determination shall be documented. ( 4 A-6 d
Summary of Requirements San Onofre Unit 3 Program per ASTM E185-73 6.2 Neutron Flux Dosimeters - Flux Compliance dosimeters for a particular program shall be determined by referring to Method E 261. END I l I i (. - U.~ A-7 l_ ,
Summary of Requirements San Onofre Unit 3 Program per ASTM E185-82 8.1 Temperature Environment - The Compliance maximum exposure temperature of the surveillance capsule materials shall be determined. If a discrepancy ( >14 *C or 2 5'F) occurs between the observed and the expected capsule exposure temperatures, an analysis of the operating conditions shall be conducted to determine the magnitude and duration of these differences. 8.2 Neutron Irradiation Compliance Environment: 8.2.1 The neutron flux density, neutron energy spectrum, and neutron fluence of the surveillance specimens and the-corresponding maximum values for the reactor vessel shall be determined in accordance with the guidelines in Guide E 482 and Recommended Practice E 560. 8.2.2 The specific method of determination shall be determined and recorded using both a calculated spectrum and an assumed fission spectrum. 9.1 Tension Tests: Compliance 9.1.1 Method - Tension testing shall be conducted in accordance with Methods E 8 and Recommended Practice E 21. 9.1.2 Test Temperature: 9.1.2.1 Unirradiated - The test temperatures for each material ! shall include room temperature, I service temperature, and one ! intermediate temperature to define the strength versus temperature ) relationship. A-8
Summary of Requirements San Onofre Unit 3 Program per ASTM E185-82 9.1.2.2 Irradiated - One specimen Compliance from each material shall be tested at a temperature in the vicinity of the upper end of the Charpy energy transition region. The remaining specimens from each material shall be tested at the service temperature and the midtransition temperature. 9.1.3 Measurements - For both Compliance unirradiated and irradiated materials, determine yield strength, tensile strength, fracture load, fracture strength, fracture stress, total and uniform 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. 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 ft-lb), 68-J (50 ft-lb), and 0.89- ' um (35 mil) lateral expansion
-I- ~
index temperatures and the upper shelf energy. A-9
1 i i 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 i percent shear fracture appearance. From the unirradiated and irradiated transition temperature l 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 ! "I unirradiated materials. . 9.3 Hardness Tests (Optional) - Compliance Hardness tests may be performed on
, unirradiated and irradiated Charpy
- l4 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. I D ( O A-10
i l t Summary of Requirements San Onofre Unit 3 Program l per ASTM E185-82 ' 9.5 Calibration of. Equipment - Compliance Procedures be :' shall employed assuring that tools, gages, recording instruments, and other measuring and testing devices are calibrated and properly adjusted periodically to maintain accuracy
- within necessary limits. Whenever possible calibration shall be conducted with standards traceable to the National Bureau of Standards. Calibration status l 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. 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 4 10.2.1 Determine the radiation induced transition temperature i shifts by measuring the difference in the 41-J (30 f t-lb) , 68-J (50 ft-lb), and O.89 mm (35 mil) lateral expansion index temperatures before and after , irradiation. The index ! temperatures shall be obtained from the average curves. ' l '( . 1 I A-11 1
.1
Summary of Requirements San Onofre Unit 3 Program per ASTM E185-82 10.2.2 Determine the adjusted Compliance reference temperature by adding the shif t corresponding to the 41-J (30 ft-lb) index determined in 10.2.1 to the initial reference temperature obtained in 9.2.3.1. 10.2.3 Determine the radiation Compliance induced change in the upper shelf energy (USE) from the measurements made before and after irradiation using average value curves. 10.2.4 (Optional) - Determine the Not Applicable radiation induced change in 4 temperature corresponding to 50% of the upper shelf energy before
- and after irradiation from average 1 value curves.
10.3 Supplemental Test Data Not Applicable
. (Optional) -
If additional, supplemental tests are performed a (9.4), the data shall be recorded j to supplement the information from the tensile and Charpy tests. 10.4 Retention of Test Specimens - Compliance
- It is recommended that all broken l' test specimens be retained until released by the owner in the event that additional analyses are required to explain anomalous results.
11.1 Where applicable, both SI units and conventional units shall be reported. O A-12
. _. .= . . _. - . _ _
Summary of Requirements San Onofre Unit 3 Progra? 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. T 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. i 11.2.5 Surveillance Material Compliance , Selection t 11.2.5.1 Description of all beltline materials including chemical analysis, fabrication , history, Charpy data, tensile data, drop-weight data, and initial RTo.r* 11.2.5.2 Describe the basis for selection of surveillance materials. t i S A-13 I s--
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 used), neutron dosimeters, and temperature monitors. i 11.3.3.2 Certification of calibration of all equipment and
; instruments used in conducting the
'l. tests. ! 1 I -) l f A-14
Summary of Requirements San Onofre Unit 3 Program per ASTM E185-82 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; 4 (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. i a
,f l
A-15 f I
~
I l l l Summary of Requirements San Onofre Unit 3 Program per ASTM E185-82 11.4.2 Charpy Tests: Compliance ! 11.4.2.1 Trade name and model of ! the testing machine, available hammer energy capacity and striking velocity, temperature- ; conditioning and 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) by Energy absorbed the l specimen in breaking, reported in :
, joules (and foot-pound-force); I (3) Fracture appearance; ;
(4) Lateral expansion; and (5) Specimen identification. i 11.4.2.3 Test data for each material as follows:
!$ (1) Charpy 41-J (30 ft-lb), 68-J ' l (50 ft-lb), and 0.89 mm (35 mil) l lateral expansion index ,
j 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. 11.4.3.2 Hardness data.
'( j A-16
i Summary of Requirements San Onofre Unit 3 Program per ASTM E185-82 I 11.4.4 Other Fracture Toughness Not Applicable i Tests: 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 fluence in terms of neutrons per square metre and neutrons per square centimetre (>0.1 and 1 MeV) for the surveillance specimens
, using both calculated spectrum and assumed fission spectrum assumptions. ; (2) Description of the methods i used to verify the procedures including calibrations, cross sections, and other pertinent nuclear data.
} i. i [ A-17 { 1
, . ~ _ . . - . - - - . .
t Summary of Requirements San Onofre Unit 3 Prograin per ASTM E185-82 i 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 i practice shall be identified and i described fully in the report. , t __________________ __________________ END END e b i 4 e-A-18 k 4
. .. .. . - _ = _ . . .__ _ _ . _ _ .
l l APPENDIX B i l i t SONGS, UNIT 3: BASES FOR PLATE r CHEMISTRY MEASUREMENTS (Proprietary) - l 1 l I I. -
l i C APPENDIX C i SONGS, UNIT 3: BASES FOR WELD j CHEMISTRY MEASUREMENTS (Proprietary) , 1 f t C e i tJ. l i
l APPENDIX D l'i SONGS, UNIT 3: WMCs FOR BELTLINE MATERIALS (Proprietary) I 1 i l I l i ,, 8 f 1
1 i j APPENDIX E t SONGS, UNIT 3: MCRs FOR 7 BELTLINE MATERIALS (Proprietary) f I l l ( I 1 L. l
9 i 6 APPENDIX F 4 SONGS, UNIT 3: UNIRRADIATED Cv,, DATA FOR PLATES AND WELDS 4 9 (.- vs
l l I Table F-1 Charpy V-Notch Test Results : For Unit 3 Plate C6802-1 (TL), MCR Data SPECIMEN ttMP tutDCT LAltRAL TSACI . 80 ftst IMPACf tur aPPf aa (f) (ft lb) (mit) (El ; r 1 4 do T.00 5.00 0.00 ; 2 40.L1 6.00 4.00 0.00 3 -40.00 5.00 4.00 0.00 .
. 4 10.00 29.00 20.00 10.00 >
f 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 , 8 40.00 2T.00 19.00 10.00 9 40.00 24.00 17.00 5.08 ( 10 40.00 43.00 34.00 25.00 si .0.00 55.00 45.00 30.= ; i 12 80.00 56.00 44.00 30.e0 -
\
i 13 100.00 50.00 37.00 25.00 '; e i 14 100.00 52.00 40.00 25.00 r 15 100.00 59.00 45.00 30.00 16 160.*)0 79.00 60.00 80.00 1T 160.00 Ft.00 63.00 30.00 , 1
-18 212.00 95.00 70.00 100.00 19 212.00 99.00 72.00 100.00 l 20 i.0.00 04.00 62.00 m.= .
21 212.00 100.00 74.00 100.00 l 1 l I
'l F-1
_p ,
1 Table F-2 Charpy V-Notch Test Results . For Unit 3 Plate C6802-2 (TL), MCR Data SPECIMEN TEMP EMERCY IATERA1, FRACT ID TEST IMPACT ERP AFFEAR (F) Ift-lb) (sil) (t) P 1 40.00 9.00 4.00 0.00 ,
. 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 5 10.00 14.00 11.00 5.00 4 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 52.00 37.00 25.00 I 10 40.00 44.00 34.00 25.00 11 40.00 52.00 34.00 30.00 12 60.00 54.00 37.00 30.00 .
13 70.00 55.00 30.00 30.00 14 10.00 57.00 39.00 35.00 n 15 10.00 45.00 45.00 40.00 18 100.00 44.00 50.00 40.00 l 17 100.00 77.00 59.00 50.00 r 10 100.00 69.00 54.00 40.00 i 19 160.00 114.00 77.00 90.00 20 360.00 110.00 75.00 90.00 21 160.00 104.00 75.00 90.00 22 212.00 117.00 00.00 100.00 23 212.00 114.00 02.00 100.00 24 2 2.00 ,,3.00 ,,.00 100.00 p F-2
I t Table F-3 Charpy V-Notch Test Results l For Unit 3 Plate C6802-3 (TL), MCR Data ; f f SPECIMEN TEMP EftESCT LATE 1Ud. FRACT ID TEST IMPACT EIP APPEAR trl tit-Ibi taill (t1 1 -40.00 0.00 4.00 0.00 2 -40.00 7.00 3.00 0.00 3 -40.00 9.00 5.00 0.00 ! 4 10.00 26.00 20.00 10.00 ! S 10.00 26.00 20.00 10.00 i 6 10.00 15.00 11.00 S.00 7 40.00 31.00 27.00 15.00 0 40.00 20.00 22.00 10.00 9 40.00 35.00 26.00 13.00 le 40.00 35.00 26.00 13.00 1 11 60.00 49.00 34.00 25.00 12 60.00 35.00 30.00 20.00
? 23 00.00 57.00 47.00 30.00 h'
14 00.00 S2.00 40.00 25.00 3 15 00.00 60.00 46.00 40.00 1. 16 100.00 79.00 60.00 60.00 e 17 100.00 70.00 $4.00 50.00 to 100.00 63.00 44.00 40.00 l 19 160.00 100.00 71.00 90.00 1 20 160.00 95.00 69.00 90.00 1 21 160.00 94.00 67.00 90.00 22 212.00 106.00 76.00 . 100.00 23 212.00 109.00 70.00 100.00 24 212.00 101.00 72.00 100.00
^
i ;
.~ F-3 m .
i
dj u Table F-4 Charpy V-Notch Test Results For Unit 3 Plate C6802-4 (TL), MCR Data Grec! MEN TEMP rwepcf IATERAL TRACT ID TEST IMPACT RIP APPEAR tri (ft-th) (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 6.00 0.00 4 10.00 25.00 10.00 10.00
$ 10.00 20.00 20.00 10.00 6 10.00 19.00 13.00 5.00 7 40.00 35.00 30.00 20.00 0 40.00 39.00 32.00 20.00 9 40.00 51.00 37.00 25.00 ,
10 40.00 40.00 35.00 20.00 j 11 40.00 S4.00 39.00 25.00 f 12 40.00 49.00 34.00 20.00 13 10.00 16.00 $3.00 $0.00 34 70.00 43.00 47.00 40.00 15 10.00 59.00 44.00 35.00 16 100.00 104.00 65.00 60.00 17 100.00 69.00 $2.00 40.00 le 100.00 10.00 S4.00 40.00 19 160.00 124.00 00.00 95.00 20 160.00 112.00 11.00 90.00 21 180.00 104.00 10.00 90.00 22
- 212.00 110.00 70.00 100.00 23 212.00 117.00 01.00 100.00 24 212.00 115.00 77.00 , 100.00
~ ' F-4 l l _ _ _ _ _ _ _ _ . . _ . _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _l
Table F-5 Charpy V-Notch Test Results For Unit 3 Plate C6802-5 (TL), MCR Data artc1 MEN TEMP anenct LATEstAL rRACT ID TEST 1MPACT ERP APPEAR frp (ft-lb1 (mill ($1 1 -40.00 9.00 4.00 0.00 2 40.00 10.00 5.00 0.00 3 -40.00 9.00 3.00 0.00 4 10.00 10.00 12.00 5.00 5 10.00 27.00 30.00 10.00 6 10.00 15.00 11.00 5.00 g 7 40.00 34.00 23.00 15.00 F .3f. ta 5lttffY * ***** " **'** ** ' p 35.00 40.00 25.00 15.00 10 60.00 39.00 26.00 15.00 r l 11 60.00 39.00 20.00 15.00 12 60.00 30.00 27.00 15.00 13 70.00 65.00 43.00 30.00 14 70.00 57.00 40.00 30.00
- 15 70.00 31.00 37.00 25.00 16 100.00 66.00 47.00 30.00 17 100.00 70.00 49.00 35.00 10 100.00 79.00 56.00 40.00 19 160.00 110.00 70.00 100.00 20 160.00 116.00 15.00 100.00 21 160.00 109.00 65.00 90.00 22 212.00 119.00 70.00 100.00 22 212.00 110.00 72.00 100.00 24 212.00 117.00 74.00 100.00 F-5 4,
l Table F-6 Charpy V-Notch Test Results For Unit 3 Plate C6802-6 (TL), MCR Data SPECIMEN TEMP EWE 1tCT !.ATERAL FRACT ID TEST IMPACT ERP APPEAR IF) (ft.lb) (all) (93 I 1 -40.00 10.00 5.00 0.00 2 ~40.00 10.00 4.00 0.00 2 -40.00 e.00 4.00 0.00 4 10.c0 23.00 17.00 10.00 5 10.00 20.00 20.00 10.00 6 10.00 25.00 10.00 10.00 7 40.00 34.00 26.00 15.00 e 40.00 43.00 34.00 20.00 ! 9 40.00 33.00 26.00 15.00 f 10 70.00 50.00 39.00 2$.00 i 11 70.00 46.00 35.00 20.00 6 12 70.00 58.00 4$.00 30.00 13 80.00 52.00 40.00 25.00 14 80.00 $7.00 45.0 30.00 15 e0.00 $3.00 41.00 25.00 1 100.00 16 S0.00 42.00 30.00 17 100.00 65.00 51.00 50.00 I le 300.00 $9.00 46.00 40.00 l 19 160.00 96.00 72.00 93.00 ! 20 160.00 90.00 49.00 90.00 l 21 160.00 S3.00 65.00 90.00 . f 22 212.00 90.00 l 70.00 100.00 j 22 212.00 92.00 71.00 100.00 24 212.00 92.00 70.00 100.00 I' (.. F-6 I ~0 J
i Table F-7 Charpy V-Notch Test Results For Unit 3 Weld Seam 9-203 (Heat #90069), WMC Data I l artc1MEM Trne EMERGY 1ATERA1. FRACT 10 TEST IMPACT IEP APPEAR ' trl tit-lbs (mil) (t) i 1 -100.00 13.00 e.00 0.00 2 -100.00 8.00 4.00 0.00 3 -100.00 13.00 S.00 0.00 7 4 -80.00 24.00 15.00 5.00 5 -80.00 43.00 31.00 20.00 25.00 ' 6 -90.00 17.00 5.00 7 -40.00 S3.00 36.00 25.00 0 -40.00 49.00 $0.00 40.00 i' 9 -40.00 63.00 44.00 35.00 , 10 0.00 83.00 40.00 $0.0c j 11 0.00 16.00 52.00 40.00 ' 12 0.00 97.00 87.00 50.00 13 40.00 120.00 82.00 90.00 . 14 40.00 110.00 00.00 90.00 15 40.00 125.00 82.00 100.00 o 16 100.00 119.00 10.00 100.00 g 17 100.00 117.00 70.00 100.00 10 100.00 124.00 33.00 100.00 19 160.00 123.00 02.00 100.00 20 160.00 121.00 81.00 100.00
- 6. 21 160.00 133.00 02.00 100.00
( F-7 <1 .
Table F-8 Charpy V-Notch Test Results For Unit 3 Weld Scam 3-203 (Heat #88114),fSAR Data !,(o
*l WMC sPsctMew TrwP EwencY 1artaAL rmAcT ID TtsT IMPACT ERP APPEAR (F) {ft-Ibl (mill (ll 2 -104.00 13.00 7.00 0.00 2 -104.00 11.00 6.00 0.00 j 3 -104.00 20.00 13.00 5.00 4 -80.00 29.00 22.00 10.00
$ -80.00 30.00 21.00 10.30 6 -80.00 24.00 13.00 10.00 7 -40.00 110.00 66.00 60.00 0 -40.00 14.00 40.00 40.00
( 9 -40.00 114.00 60.00 50.00 10 -10.00 127.00 10.00 00.00 '
~
11 -10.00 115.00 66.00 70.00 12 -80.00 117.00 68.00 70.00 i 13 10.00 126.00 78.00 00.00 l 14 10.00 131.00 s1.00 100.00 15 10.00 156.00 e4.00 100.00 16 $0.00 174.00 96.00 100.00 17 50.00 163.00 05.00 100.00 10 50 80 162.00 83.00 100.00 l I e k
I l Table F-9 Charpy V-Notch Test Results For Unit 3 Plate C6802-1 (TL), CE Baseline Data
' I spectMrs TEMP rpencT 1.ATrnAL PmacT
#D TEST IMPAc7 ERP APPEAR tr) (ft-lbf tell) (t) 252 40.00 12.00 12.00 0.00 l 22t 0.00 14.00 12.00 10.00 26J 0.00 23.00 24.00 0.00 t 22P 40.00 10.00 17.00 10.00 240 40.00 $2.00 45.00 20.00 '
22K 00.00 25.00 25.00 20.00 263 80.00 57.00 30.00 40.00 237 100.00 42.00 40.00 30.00 i 2SM 100.00 74.00 60.00 40.00 24T 100.00 80.00 65.00 50.00 2SE 120.00 05.00 13.00 $0.00 261 120.00 106.00 80.00 00.00 23A 160.00 61.00 40.00 60.00 221 140.00 63.00 50.00 10.00 2ST 160.00 113.00 81.00 90.00 23P 210.00 96.00 14.00 90.00 235 210.00 109.00 02.00 100.00 2tt 250.00 00.00 71.00 100.00 22A 250.00 87.00 73.00 100.00 1 I
. 1 (i.., ,
F-9 6
1 l i l Table F-10 Charpy V-Notch Test Result ! For Unit 3 Plate C6802-1 (LT), CE Baseline Data 1 l
- Spec 1 MEN TrHP rwency 1.nTenAL rnAct ID TEST IMPACT Etr APPEAR (P) (ft-lb) (sing (t3 151 0.00 s.50 5.00 0.00 148 40.00 15.00 13.00 10.00 .
127 40.00 1s.00 13.00 10.00 110 00.00 33.30 30.00 30.00 13M 00.00 39.50 34.00 30.00 i 14C 130.00 34.00 37.00- 40.00
$ 124 120.00 45.00 41.00 40.00 las 150.00 51.00 47.00 50.00 13U 150.00 03.00 70.00 00.00 13E 210.00 46.00 62.00 10.00 14T 210.00 94.00 01.00 30.00 l l
11L 250.00 90.00 30.00 100.00 i 11C 350.00 93.00 07.00 100.00 l d' F-10 l 1
- - . I
= l
l l I Table F-11 Charpy V-Notch Test Results I For Unit 3 Surveillance Weld, CE Baseline Data SPECIMEN TEMP EMERCT 3.ATERAI. FRACT ID TEST IMPACT IIP APPEAR (r) (ft-th) (all) (n P 31T -80.00 S.00 5.00 0.00
+
37C -80.00 21.00 19.00 20.00 32C -40.00 17.00 18.00 20.00 36M -40.00 34.00 31.00 30.00 34C 0.00 36.00 34.00 30.00 34T 0.00 40.00 45.00 40.00 37E 40.00 $0.00 53.00 40.00 3A2 40.00 63.90 54.00 40.00 a 3ST 00.00 72.00 85.00 80.00 34M 90.00 00.00 92.00 100.00 376 120.00 11.00 65.00 00.00 ' 33K 120.00 84.00 19.00 90.00 316 160.00 64.00 57.00 70.00 344 160.00 97.00 90.00 100.00 32K 210.00 00.00 85.00 90.00 31C 210.00 97.00 94.00 90.00 3SM 250.00 71.00 89.00' 100.00 372 250.00 70.00 73.00 100.00 34E 250.00 04.00 82.00 100.00
'(
l- F-11 l. 1
. i N l
Table F-12 Charpy V-Notch Test Results
., For Unit 3 Plate C6802-1 (LT), MCR Data I 4
Test impact Lateral Fractur9 l Temperature Energy Expansion Appearsnce ('F) (f t-lbs) (mils) (% Shear)
-40 8 3 0 t
-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 i 40 31 23 10 60 33 25 15 i 60 34 25 15 60 35 24 15 - 80 50 39 20 80 52 40 25 80 50 38 20 100- 102 65 70 l l 100 104 61 70
- n. 100 96 63 60 160 126 81 100 160 132 84 100 J 160 135 83 100 l i 1 F-12 q
1
Table F-13 Charpy V-Notch Test Results . For Unit 3 Weld Seam 9-203 (Heat #90144), WMC Data l l SPECIMEN TEMP ENERGY LATERAL rRACT ID 1EST IMPACT EXP APPEAR (r) (ft th) (mit) (%) 1 -80.00 7.00 3.00 0.00 } 2 -80.00 9.00 6.00 0.00 3 -80.00 5.00 3.00 0.00 , 4 -40.00 18.00 13.00 0.00
. 5 -40.00 19.00 13.00 0.00 ,
i l 6 40.00 34.00 26.00 15.00 ' 1 7 10.00 57.00 41.00 35.00 t 8 10.00 50.00 36.00 25.00 9 10.00 53.00 40.00 30.00 ;
- 10 60.00 82.00 60.00 80.00 i '
60.00 81.00 60.00 80.00 11
. 12 60.00 76.00 54.00 80.00 13 100.00 90.00 67.00 100.00 .
t 14 100.00 89.00 71.00 100.00 i > 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 .l
,18 160.00 93.00 72.00 100.00 c 1 F-13
]
. l
. . ~ . _ . . . _ _ , , _ _ _ . . _ i
1 i APPENDIX G 4 SONGS, UNIT 3: HAZ TEST RESULTS 1 5 e e-( i i 2
CE Baseline Tests"I I I i l l 1 SPEC 2fetW Tit 9F ENERCY IATERAL PRACT 2D TSST IMP &t.T RIP APPEAR (FI itt.1b) (all) (t) ; I 47L 00.00 4.00 4.00 0.00 I 450 .00.00 4.00 4.00 0.00 i i 427 .40.00 30.00 26.00 10.00 436 40.00 30.00 34.00 10.00
- 4SJ 0.00 30.00 25.00 20.00 -
457 0.00 46.00 37.00 30.00 423 40.D0 33.00 34.00 20.00 P 42K 40.00 3S.00 32.00 20.00 420 00.00 73.00 40.00 00.00 4S4 00.00 79.00 43.00 30.00
- 471 130.00 42.00 41.00 40.00 1 47S 120.00 S0.00 49.00 70.00 43C 160.00 $1.00 62.00 30.00 43R 360.00 07.00 72.00 00.00 44K 210.00 37.00 $7.00 10.00 i 444 210.00 105.00 73.00 300.00 den 250.00 63.00 46.00 100.00 l
42T 250.00 73.00 60.00 100.00 46T 250.00 90.00 00.00 100.00 l . a.-
Westinghouse Capsule 97!23 l l l l l l l I i SPECIMEN TBMP RWERGY 1ATERAL FRACT CRARPT IRRAD 2D TEST IMPACT SIP APPEAR FLUENCE TEMP. (F) (ft-lb) (mil) (S) (a/cm2) (F) 441 79.00 9.00 8.00 S.00 8.00E*18 550.00 42L 50.00 18.00 16.00 15.00 8.00t+18 350.00 4SC 30.00 3.00 4.00 S.00 0.00E+18 550.00 43P 0.00 26.00 23.00 35.00 0.00E+10 350.00 4 464 28.00 35.00 37.00 45.00 0.00B+10 $50.00 41C 40.00 33.00 33.00 $0.00 0.00s+1e 350.00 478 95.00 43.00 44.00 75.00 0.00B+10 330.00 44T 125.00 41.00 30.00 70.00 0.008+18 550.00 4SM 145.00 45.00 44.00 30.00 0.00B+10 350.00 437 155.00 43.00 41.00 100.00 0.00E+18 550.00 4SP 200.00 84.00 40.00 100.00 0.005+10 350.00 , 434 250.00 75.00 45.00 100.00 0.00B+10 550.00 5 (- (3-2 i . i l
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Battelle Columbus Additional Unirradiated HAZ Results t') sesC1 sew Tre arsac7 1AretA1. FaacT 2D TEST IWACT SEP APrtAR (F1 (ft 16) (mil) (53 381 -120.00 7.$0 S.00 11.00 i 353 -120.00 9.50 3.20 9.30 , 1811 -80.00 23.50 13.00 12.40 1812 -90.00 26.00 16.40 17.00 1817 -40.00 27.50 21.00 13.30 ) 3s4 -40.00 $7.00 36.20 31.10 i 3s5 0.00 39.50 31.00 49.20 189 0.00 44.50 43.20 SS.40 t l 1816 20.00 41.90 46.60 St.00 + k 185 20.00 76.00 40.00 S4.70 153 30.00 02.00 30.60 S6.30 1 1810 40.00 93.00 63.00 63.30 1810 40.00 99.00 64.00 73.40 - 8813 40.00 105.00 64.40 72.90
, ISO 90.00 113.00 72.60 100.00 i
106 00.00 115.00 .S.00 100.00 . 14 120.00 122.00 03.40 .. 00 8 1.i. no.00 160.00 .6.80 1 0.00 l l fi i 157 160.00 120.00 07.20 100.00 l l 102 160.00 151.00 02.20 100.00 306 210.00 110.00 70.00 100.00 1815 210.00 132.00 75.00 100.00 4 G-3
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i 1 i APPENDIX H SONGS, UNIT 3: IRRADIATED C DATA FROM CAPSULE 97 l i l . i i 1 (..
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Table 11-1 Charpy V-Notch Test Results t For Unit 3 Plate C6802-1 (LT) 2 Irradiated (f = 8 x 10" n/cm ) ' a spec 1 Men TEMP Ewency LArtmAL rmAct ID TEST IMPACT ERP APPEAR (r) (ft-lb) (mil) (t) 147 50.00 6.00 5.00 5.00 153 75.00 22.00 15.00 15.00 15K 200.00 29.00 24.00 25.00 113 125.00 25.00 32.00 30.00 14Y 150.00 32.00 26.00 30.00
'158 165.00 45.00 43.00 45.00
{ 14A 175.00 30.00 27.00 45.00 let 200.00 46.00 46.00 55.00 11T 225.00 75.00 66.00 80.00 l 12K 250.00 45.00 40.00 30.00 12L 250.00 40.00 48.00 95.00 14M 275.00 90.00 76.00 100.00
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Table H-2 Charpy V-Notch Test Results
- For Unit 3 Plate C6802-1 (TL) .
2 Irradiated (f = 8 x 10 n/cm ) i 1 SPECIMEN TEMP ENERCT LATERAL TRACT , ID TEST IMPACT EKP 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 15.00 228 200.00 25.00 25.00 20.00 25J 115.00 55.00 40.00 45.00 f 25L 130.00 50.00 44.00 50.00 247 150.00 33.00 33.00 50.00 223 165.00 36.00 37.00 65.00 t 25C 200.00 92.00 73.00 100.00 i 245 225.00 62.00 59.00 100.00 23M 250.00 73.00 77.00 100.00 )
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l l l l l Table H-3 Charpy V-Notch Test Results For Unit 3 Surveillance Weld Irradiated (f = 8 x 10 n/cm') ; SPECIMEN TEMP ENERGY 1ATERAL FRACT ID TEST IMPACT EXP APPEAR (F) (ft.1b) (all; (t) 363 -50.00 23.00 20.00 1!.00 33L -25.00 27.00 25.00 20.00 31D O.00 5.00 6.00 5.00 4 378 10.00 42.00 34.00 60.00 367 25.00 42.00 44.00 65.00 331 50.00 44.00 44.00 70.00 f 37U' 60.00 61.00 57.00 95.00
; 371 00.00 65.00 59.00 95.00
.i. l' 365 105.00 47.00 60.00 100.00 34P 150.00 75.00 73.00 100.00 330 190.00 77.00 76.00 100.00 377 225.00 63.00 50.00 100.00 l , I
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H-3 Y 4 j 4}}