ML20128B776

Response to GL 92-01,Rev 1

ML20128B776
Person / Time
Site:	San Onofre
Issue date:	01/22/1993
From:	ATI, SARTREX CORP.
To:
Shared Package
ML19303F252	List: ML20128B711 ML20128B776 ML20128B790
References
GL-92-01, GL-92-1, NUDOCS 9302030173
Download: ML20128B776 (97)

Text

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ATTACHMENT D San Onofre Nuclear Generating Station, Unit 2 Response to Generic Letter 92-01 Revision 1 0

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l San Onofre Nuclear Generating Station, Unit 2 Response to Generic Letter 92-01 Revision 1 January 22,1993

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Prepared by:

ATI Consulting San Ramon, CA and Sartrex Corporation Rockville, MD Prepared for:

Southern California Edison Irvine, CA

CONTENTS Satinn Pac 1 INTRODUCTION 1-1 2 REACTOR PRESSURE VESSEL SURVEILLANCE 2-1 PROGRAM-COMPLIANCE WITH APPENDIX H 3 FRACTURE MECH ANICS 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 Treatment 3-2 3.2.3 Key Residual and Alloying Element Contents 3-2 3.3 FRACTURE TOUGHNESS RELATED DATA 3-3 3.3.1 Beltline Plate Material 3-3 3.3.2 Beltline Welds 3-5 4 ISSUES RELATED TO GENERIC LETTER 88-11 4-1 4.1 VESSEL TEMPFRATURE 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 43 5 UPPER SHELF ENERGY EVALUATION FOR CIRCUMFERENTIAL 5-1 WELD 8-203 5.1 EVALUATION PROCEDURE 5-1 5.2 RESULTS 5-2 6 REFERENCES 6-1

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CONTENTS (cont'd)

Section Eage 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 l MEASUREMENTS (Proprietary) i i l APPENDIX C SONGS, UNIT 2: BASES FOR WELD CHEMISTRY C-1 MEASUREMENTS (Proprietary)  ;

I APPENDIX D SONGS UNIT 2: WMCs FOR BELTLINE ' D-1 MATERIALS (Proprietary)

APPENDIX E SONGS UNIT 2: MCRs FOR BELTLINE E-1 i MATERIALS (Proprietary) l APPENDIX F SONGS, UNIT 2: UNIRRADIATED Cm DATA F l FOR PLATES AND WELDS l

APPENDIX G SONGS, UNIT 2: HAZ TEST RESULTS G-1 APPENDIX H SONGS, UNIT 2: IRRADIATED Cm DATA FROM H-1 CAPSULE 97 I

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ILLUSTRATIONS Figure h 3-1 SONGS, Unit 2: _ Location and Identification of 3-6 Beltline Plates and Welds 3-2 SONGS, Unit 2i Data and least Squares Fit Curve 3-7 for C m versus Temperature, Plate C6404-1, TL Orientation, MCR Data 3-3 SONGS, Unit 2: Data and Least Squares Fit Curve for 3-8 Cvy versus Temperature, Plate C6404-2, TL Orientation, MCR Data ,

34 SONGS, Unit 2: Data and Least Squares Fit Curve for 3-9 Cm versus Temperature, Plate C6404-3, TL Orientation, MCR Data 3-5 SONGS, Unit 2: Data and Least Squares Fit Curve for 3-10 Cm versus Temperature, Plate C6404-4, TL Orientation, MCR Data 3-6 SONGS, Unit 2: Data and Least Squares Fit Curve for 3-11 Cm versus Temperature, Plate C6404-5, TL Orientation, l MCR Data l

3-7 SONGS, Unit 2: Data and Least Squares Fit Curve for 3-12 Cm versus Temperature, Plate CMM-6, TL Orientation, MCR Data 3-8 SONGS, Unit 2: Data and Least Squares Fit Curve for 3-13 Cvu verses Temperature, Plate C6404-2, TL Orientation, Surveillancc Baseline Data i

3-9 SONGS, Unit 2: Data and Least Squares Fit Curve for. 3-14 l

l Cm versus Temperature, Plate C6404-2, TL Orientation, l Combined MCR and Surveillance Baseline Data i

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ILLUSTRATIONS (cont'd)

Figure Eage-3-10 SONGS, Unit 2: Data and Least Squares Fit Curve for - 3 Cm versus Temperature. Plate C6404-2, LT Orientation, Surveillance Baseline Data 3-11 SONGS, Unit 2: Comparison of Least Squares Fit Cu versus 3-16 Temperature Curve for the Surveillance Plate with MCR Data for Plate C6404-2, LT Orientation 3-12 SONGS, Unit 2: Data and Least Squares Fit Curve for 3-17 Cm versus Temperature, Weld 9 203, WMC Data 3-13 SONGS, Unit 2: Data and Least Squares Fit Curve for 3-18 Cm versus Temperature, Surveillance Weld, Surveillance Baseline Data -

4-1 SONGS, Unit 2: Comparison of the Least Squares Fit for the 4-4 Unitradiated Baseline Data with the Irradiated Cm Data and Least Squares Fit for the Data from Capsule 97, Plate C6404-2, LT Orientation-4-2 SONGS, Unit 2: Comparison of the Irast Squares Fit for the 4 Unirradiated Baseline Data with the Irradiated Cm Data ,

and Least Squares Fit for the Data from Capsule 97, Plate C6404-2, TL Orientation 4-3 SONGS, Unit 2: Comparison of the Least Squares Fit for the 4-6 Unirradiated Baseline Data with the Irradiated Cm Data and Least Squares Fit for the Data from Capsule 97, Surveillan'ce Weld 5 SONGS, Unit 2: Material J-R Curve for Upper Shelf Toughness 5-4 Evaluation of Circumferential Weld 8-203 5-2 SONGS, Unit 2: Applied and Material J/T Plot for Upper Shelf 5-5 Toughness Evaluation of Circumferential Weld 8-203

O TABLES Table Egge 3.1 SONGS, Unit 2: Compliance with 10CFR50, Appendix G 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 for Beltline Surveillance Welds 3.4 SONGS, Unit 2: Rey 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 i 3.6 SONGS, Unit 2: Beltline Plate Material Unirradiated 3-25 Fracture Toughness Tests Results Summary, TL Orientation 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 3.8 SONGS, Unit 2: Beltline Weld Material Unirradiated 3-27 ,

Fracture Toughness Tests Results Summary 4.1 SONGS, Unit 2: Surveillance Capsule Shift Resul : 4-7 4.2 SONGS, Unit 2: ART Estimates at the Inner Surface 4-8 7 acation for Beltline Materials on 12/16/91 and at 32 EFPY 4.3 SONGS, Unit 2: Surveillance Capsule Upper Shelf Results 4-9 4

4.4 SONGS, Unit 2: Upper Shelf Estimates at the Quarter-Thickness 4 Location for Beltline Materials on 12/16/91 and at 32 EFPY 5.1- SONGS, Unit 2: Evaluation of Appendix X 0.1 inch Flaw 5-6 Extension Criterion for Circumferential Weld 8-203

[' 5.2 SONGS, Unit 2: Evaluation of Appendix X Instability 5-7  ;

Criterion for Circumferential Weld 8-203 i

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I Section 1 INTRODUCTION  :

The Nuclear Regulatory Commission (NRC) in Generic 12tter 92-01 (GL 92-01) requested 211 l holders of operating licenses or construction permits for nuclear power plants to submit j' 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 -j 8 203.

This revision (Revision 1) incorporates 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 Company (SCE) to better ,

characterize fluence conditions at Weld 8-203, and the results from calculations performed to .I evaluate the upper shelf toughness for Weld 8-203.

L Based on a review of the information, the evaluation for Weld 8-203 has been completed, and 1 the beltline wcld properties have been confirmed with the exception of beltline Welds 2-203 A, B, C and 8-203. Upper shelf toughness evaluations for Weld 8-203 have also been completed.

j To complete the response to GL 92-01, addi ,nal information will be required to confirm heat -

l numbers for Welds 2-203 A, B, C and the surveillance weld material. SCE will continue to i work with ABB-CE to obtain the additional information.

-Section 2 of this report addresses compliance with 10 CFR Part 50 (10CFR50), Appendix H,

'for the surveillance program at SONGS, Unit 2, Compliance with 10CFR50, Appendix G, is described in Section 3 along with a' description of the location, heat treatment, residual and - i 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 cmbrittlement effects, including inadiation temperature s'd adjusted reference temperature for evaluation of the beltline materials relative to GL 88-11 and 10CFR50.61. Section 5 presents the upper shelf l

toughness evaluation performed for circumferential Weld 8-203.

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Section 2 i REACTOR PRESSURE VESSEL SURVEILLANCE PROGRAM COMPLIANCE WITH APPENDIX H 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. Coasequently,-

the applicable version of American Society for Testing and Materials (ASTM) E185 is the 1970 version (ASTM E185-70). However, the surveillance program for SONGS, Unit 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 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 Appendix H requirements had to do with the method of attachment of the holders for the six surveillance capsules in each SONGS unit. ABB-CE was the vessel manufacturer and the NSSS vendor; ABB-CE attached the capsule holders directly' to the cladding on the inside of the vessel in the beltline region (as they did for all ABB-CE NSSS-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 Design. Fabrication. Installation. and Inspection of Surveillance Holder

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/Lssemblies) and found the practice and procedures acceptable.

The current version of Appendix H does not treat this method of attachment of the capsule holders as a noncompliance issue. The wording in the current Appendix H, S,ection I.A.2,'is:

"If the capsule holders are attached to the vessel wall or to the vessel cladding, construction and in-service inspection of the attachments and the attachment welds must be done according to requirements for permanent structural attachments to reactor vessels

given in Sections III and XI of the ASME Code. The design and location of the capsule holders shall permit insertion of replacement upsules."

This wording was derived from the ABB-CE Topical Report, and the SONGS units have met L the additional ASME Code, Sections III and XI, design and insp n requirements. Theccfore, L there are no deviations or exceptions needed from the currem Appendix H of 10CFR50.

The details of the SONGS, Unit 2, surveillance program have been described in the FSAR and subsequent surveillance program testing reports, baseline N and irradiated.A' The first capsule results ' nave been ovaluated for a low fluence following ASTM E185-82 testing and reporting 2-1

requirements. Later sections of this report will discuss these results as compared to regulatory prediction methods, The update of ASTM E185 for 1992 (E185 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 ci ange 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 (Cm) 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 2; however, the raw data from prior HAZ testing on the SONGS, Unit 2, beltline material has been reported previously,"'l and is provided for reference in a subsequent section of this report.

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Section 3 i

FRACTURE - MECHANICS This section evaluates compliance with 10CFR50, Appendix G, and identifies the location, heat treatment, key residual and alloying element contents, and unirradiated _ fracture. ,

toughness properties for plates and welds in the SONGS, Unit 2, 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 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,N and the_ irradiated material in the 97* location surviillance capsule (Capsule 97), which was removed from Unit 2 at the end of the third fuel cycle.A 3.1 COMPLIANCE WITH APPENDIX G The materials in the beltline region of SONGS,- Unit 2, comply with the requirements of Appendit G,10CFR50. A summary of compliance with Appendix G,10CFR$0, as specified in the FSAR for SONGS, Units 2 and 3,and updated during preparation of this report, are listed in Table 3.1.

3.2 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 ideatifies 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 ? 2.

The weld wire and flux combination for the beltline welds shown in Figure 3-1 and the sur >eillance welds are presented in Table 3.3 Source; documentation has been obtained to confirm the properdes of beltline plates and welds with the exception of Welds 2-203 A, B,- ,

C and 8 203 and the surveillance weld material. - Work is continuing with ABB-CE to obtain the source documentation for the 2-203 A, B, C and surveillance welds.

Source documentation material has not been located to confirm the chemical composition and upper shelf energy. properties for Weld 8-203. Because it is-unlikely that source-materials will be obtained for Weld 8-203, conservative analyses have been performed to determine adjusted reference temperature (see Section 4.3) and demonstrate adequate -

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upper shelf toughness (see Section 5) for circumferential Weld 8 203.

l 3.2.2 Heat Treatment The heat treatment for thc plate materials consisted of austenitization at.1575150 F for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; water quenched and tempered -at 122512fF for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. For ASME Code qualincation, the plates were stress relieved at 1150125T for 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> and then were furnace cooled to 600T at a rate of 100T/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 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> for any particular portion of the vessel. Longitudinal weld seams would see stress relief times near the 40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> maximum, while the closing girth weld in the beltline region would see approximately half this amount of time maximum. All of the testing of plate materials was performed on pieces with essentially an identical heat treatment as the actual reactor vessel.

The surveillance weldment received a final 42-hour and 15-minute stress relief at 11007 to 1150 F.

3.2.3 Kev Residual and Alloying 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 ob:ained 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.A Table 3.5 contains the Cu, Ni, P, and S contents reported in the FSAR for the beltline welds. With the exception of-Weld 8-203, 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 and 9-203 is presented in Appendix D. Because Ni was not measured for -

Weld Seam 8-203,a value of 1.0wt% has been assumed (see Regulatory Guide 1.99,Rev.

2); also, because no source documentation has been obtained to validate the reported-copper content of 0.31 wt% in Table 3.5, a conservative value of 0.35 wt% ha' been assumed (see Regulatory Guide _1.99, Revision 2) to : determine adjusted reference temperature in Section 4.3. 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 baselineN, while the- second was obtained from a broken-Charpy specimen from Capsule 97A.-

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The surveillance weld and beltline Weld 9 203 are reported by ABB-CE to have been fabricated using the same weld wire and flux combination-_ (see Table 3.3). Because the source docuraentation_ necessary to confirm the heat number of the surveillance as is has not been obtained from ABB-CE, the surveillance weld and beltline Weld 9-203 are listed and ,

evaluated separately in this report. ABB-CE is continuing their investigation to obtain' this documentation.

Tables 3.4 and 3.5 also include the chemistry factors determined for each reported set of Cu and Ni contents using Regulatory Guide 1.99, Revision 2.

3.3 FRACTURE TOUGHNESS RELATED DATA This section presents the results from the Cvu tests and summarizes the upper shelf energies (USEs) and the results from the drop weight nil ductility temperature - (NDT) tests for the unitradiated beltline plate and weld materials in SONGS, Unit 2. The unitradiated-reference temperature (RTum) values were determined from the Cvu and NDT test results in accordance with the most recent version of ASME Section Ill, 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 for those tests (at least

3) where the percent shear on the fracture surfaces was equal to and greater than 95%.

The fracture toughness data for the plates were obtained from the MCRs (see Appendix E .

of this report) and baseline surveillance program.N The fracture toughness data for the beltline welds were obtained from the FSAR. The source documents for Welds 3 203 A,

, B, C and 9-203 are presented in Appendix D of this report. ABB CE is continuing ~ their investigation to obtain source documentation for the remaining welds. The data for the surveillance weld were obtained from the baseline surveillance program. For convenience, the Cvu, lateral expansion, and fracture appearance (% shear) data for the ur, irradiated beltline and surveillance plate and weld materials are listed in tabular form in Appendix-F of this report.

As discussed earlier in Section 2, the results for HAZ material- are not evaluated in this report because upcoming ASTM standard E185-93 willnot require HAZ material to be part -

of the surveillance program. The raw Cvu 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 C6404-2, which was included in the surveillance progtm. Because 3-3 l

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the surveillance- program for SONGS, Unit 2, also contains longitudinally.(LT) oriented

. specimens,- the unirradiated Cm data are presented for completeness for the LT orientation.

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 through 3-7, respectively. For convenience, an average curve through the data is also shown in each figure. The average curves were determined using a least squares fit to the data and a hyperbolic tangent functional form, where the lower shelf was fixed at 2.2 ft-lb and the upper shelf was fixed 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 Cmequal to 50 ft-lb (T @ 50 ft-lb) is achieved consistent with the applicable method of ASME, Section Ill, NB-2331, and RTer.

As part of the surveillance program, additional Cm versus temperature data were generated for Plate C6404-2;m these data are presented in Figure 3-8 along with a least squares fit curve. Because fewer than three specimens were tested at each temperature, the graphical method of NB-2331 (a)(4) was used to determine initial RTer for the surveillance plate weld as shown by the intersection of the dashed line and the 50 ft-lb Cm level in Figure 3 8.

The dashed line was drawn parallel to the least squares fit line at 50 ft-lb so that it was on, or to the right of, all the data points in the transition region.

The data obtained when the plate material was purchased (Figure 3-3) and the surveillance baseline data (Figure 3-8) were combined as shown in Figure 3-9. The combined data set presented in Figure 3-9 was used to determine RTer and the USE for the TL orientation in Plate C6404-2. The average curve through the combined data set in Figure 3-9 also was used as the unirradiated baseline to evaluate the results for the irradiated- surveillance tests (see Section 4).

Table 3.6 is a summary of the unirradiated NDT, RTm7, and USE values- for the TL orientation for each of the beltline p'ates in SONGS, Unit 2. The NDT for Plate C6404-2 also was determined twice. One value was measured when the material was purchased, while the second.value was determined from the unirradiated baseline. tests. The higher of these values is listed.in Table 3.6.

The methods used to determine 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 RTmr for the plates.

Figure 3-10 shows the data and least squares fit line for the LT crientation for surveillance Plate C6404-2.m Figure 3-1I shows a comparison of the best l't line for the LT orientation-for the surveillance plate (see Figure 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 LT orientation in Plate C6404-2 from the MCRs produce essentially the same Cm versus temperature relationship as was obtained for the LT orientation surveillance plate material.

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l Therefore, the baseline surveillance LT curve fit can be used to assess shift and upper shelf toughness changes.

3.3.2 Beltline Welds A full Cru versus temperature curve was obtained for the material in Weld Seam 9 203,and 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 scams were tested to obtain three Cvu data points at 10"F. The results from these tests are presented in Table 3.7. Figure 3 -

13 presents the Cvu data and least squares hyperbolic tangent curve fit for the surveillance weld material. A comparison of the Cvu versus temperature curves for beltline Weld 9-203 -

and the surveillance weld in Figures 3-12 and 3-13, respectively, show that the impact .

energies as a function of temperature are essentially the same for both materials.

Table 3.8 presents a summary of the unirradiated NDT, RTum, and USE values for each of the beltline welds in SONGS, Unit 2. For Welds 3-203 A, B, C and 9-203,available Cvu data indicate that there is a minimum of 50 ft-lb absorbed energy at 60#F above NDT and, consequently, RTum equals NDT. For Welds 2-203 A, B, C, the available Cvu data are 70'F above NDT; however, since the data all have absorbed energies greater than 100 ft-lb, RTym was taken as equal to NDT because it is unlikely that the absorbed energy would be less than 50 ft-lb at 0"F when it is in excess of 100 ft lb at 10*F. No NDT data are available for Weld 8-203, initial RTum was taken as the generic value of-56*F for ABB-CE fabricated vessels (see 10CFR50.61).

The upper shelf energies shown in Table 3.8 for Weld 9-203 and the surveillance weld were obtained by aveiaging the test results where 95% shear or greater was exhibited, The upper shelf energies for Welds 2-203 A, B, C and 3-203 A, B, C were obtained from the data in -

Table 3.7 by averaging the three Cyu data points obtained at 10"F for each of the listed welds. Even.though three Cvu data points were reported in the FSAR for Weld 8-203,no.

documentation for these data have been obtained. Therefore, an evaluation has been performed to determine ifWeld 8-203 has upper shelf toughness equivalent to that required by Appendix G of the ASME Code. This analysis was performed even though the average energy at 10"F, as reported in the FSAR, is equal to 113 ft lb (see Table 3.7).- The upper shelf toughness evaluation is presented in Section 5.

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RE ACTOR VFRSEL DELTLINE MATERl ALS NOTSHOWN INTERMEDIATE SHELL I

, YO WELD SEAM NO.2 203C LOWER SHELL Q ~

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1 Figure 3-1. SONGS, Unit 2: Location and Identification of Beltline Plates and Welds.

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{"~~~ ' ~ O i tu z -

l i  ; i og O i C

i  ; i l

!  ! I i i .

-  !  ;  ;  !  ! j I  !

50

^t -

3 O Measured ~

! i i f Calculated

t

.i, 0

- i .

i })

. .l . . . . .i . . . . n ....!

i

.... n.. .. n . . . . n 100 0 100 200 300 400 500

-200 Temperature in Degrees F Figure 3-3. SONGS, Unit 2: Data and Least Squares Fit Curve for Cm versus Temperature, Plate C6404-2, TL Orientation, MCR Data.

3-8

200 E

l l'

~

'I Sar) Onofre Urjit 2 i

. MCR Data i Majorial: Plat $ C6404-3, A533B1 Orientation: TL ~~+'

~ ~ ~ ' ~ ~ ~ ~ ~ ' ~ " ' ~ ~

150 -

USE~E 99~ft-165~ ~t~

. NDT = -20 'F i

m T @ 50 ft-Ibs p 80 'F i  :

h RThdt = 20 'F c -

V, - - N- b:

I -

? 100 i

. 4 c .

i W i i

i

~  !

t- Z O+

0  ;

j 0 d- _

Measured _ __

50 --

Calculated l

• _

Oo 0 i '

0

-200 -100 0 100 200- 300 40t 500 Temperature in Degrees F ,

L Figure 3-4. SONGS, Unit 2: Data and Least Squares Fit Curve for CW versus Temperature, Plate C6404-3, TL Orientation, MCR Data.

l 3-9

I Y

200 -

San, Onofro Unit 2 MCR Data

. Material:

i Plat 9 C6404-4, A533B1 i Orientation:- TL

--- -- I- ~~ --- - - ~ - -

- ft !--

- --+

150 USE = 104 bs NDT = 10 'F j . T @ 50 ft lbs 4 80 'F 2

u.

, RTridt = 20 'F '

0 .

- - ~ ~- n

? 100 - . -

e g .

O Z >

O 0 }

-- - -~~- U- - -- -- u-50 *-- ---

O- '

' O O Measured '

I. )

• --- Calculated l J

'"""l- ''''''! "' '

0

-200 -100 0 100 200 300 -400 500 .

Temperature-In Degrees F ~

Figure 3-5. SONGS, Unit 2: Data and least Squares Fit Curve for Cm versus - ,

Ternperature, Plate C6404-4, TL Orientation, MCR Data.

A 3 10

• r".- T

, - ~ ,

.,a.,n- -. a.r,,..,,,,~Nm,e .- - - ,r.l~,, .i.~,- . - , ,-,...nw. > n .r n

i

?

I t

200 -

i

" q San pnofro Unit 2 a

. MCR Data C6404 5, BA533B1 Mate'[lal: Plate Orlerltation: TL l 150 ---- ggg ,gygg, .

NDT = 20'F

-t j T@ 50 ft-lbs = 70 'F 2 ,,

RTndt = 10 'F - o E o- r u 100 -- --9 e

c .

Lu Z

> . O .t

.O c.

. O OJ --- +-

50 -- --

o ' Measured Calculated

. B:

d a y '1 ' ' ' ' '!' ' "' l' O -

200 -100 0- 100 200 300 400' .500 Temperature in Degrees F Figure 3 6. SONGS, Unit 2: ' Data and' Least Squares Fit Curve.for Cm versus-Temperature, Plate C6404-5, TL Orientation, MCR Data.~

3 11 i

, _ . . , ~ . . . .,_~ . _

1

)

1 i

~

200 -

=T

- ~~T " ~~ T ~ ~ ~~ l i

l San Onofre Unit 2 MCR bata Materlial: Plats C6404 6, A533B1 Orienhation: TL l

-....._...._m.._ _ . - . _ . . ._ . . _ .

150 ---.USE..h 124..ft lbs. .

NDT i = 10 'F n T @ 50 ft lbs = 50 'F m

RTnd'; = 10 'F es r .

} E

--- - ~ ~ " "

s. 100 --

e ir C . )

Y )

~

Z t.

g .

0 1 . 8 O -~- -----'

50 - - - " - - ~

'----j-------- ' - -

- o Measured 0 Calculated 8

.. a a a e u a a n'a a I a a a a Il a a a n l< n a a n 1, a a nn 1

-200 -100 0- 100 200 300'- 400 500 i

L Temperature in; Degrees F l Figure 3 7.  : SONGS, IJnit ' 2: Data and Izast Squares Fit Curve for.Cyrversas Temperature, Plate C6404-6, TL Orientation, MCR Data. -i L: +

l l

3 12 l

_. .- ... . - -. - - . . . ..- , . ._~___. . . . - __

1

-a

'(

i 200 - - - - --- - -- ----------------------4-+--,--------

l f=0.0 j I

150 - - - -- - =- - --

i

- O j O t1 g . O O

R 100 ---- -

-r- ~ ~ ~ ~J -- -

/ .:

O 2

E /-

o ~

3d g San Onofra Unit 2 Stirveillanco Program

- / Material: Plate No. C6404 2, SA53381 50 - - ~ - -

-- -/. . . . . .

OrlentationLTL)

USE = 126 ft-lbb-

• I NDT = 10 Y l

. J/ T E 50 ft-Iba = B0 Y D RTndt = 20 Y

. C 0

200 100 0 100 200 '300 400 500 ,

- Temperature in Degree F Figure 3 8. SONGS, Unit 2: Data and. Least Squares Fit Curve for Cm- versus Temperature, Plate C6404-2, TL Orientation, Surveillance Baseline Data.

3-13

~ . , .~ --v-r., ...r_,_,.-,,,,,.# ,,,,...,_..__.,,,.,,r....,,- , , . . ,. . ~ , _ _ , . - 4 _ _ , , . . . _, . ,

_ __ _ _.._._ ._ _. - _ . _ _.__.._m._.. _..... _ _ _ _ . . _ _ _ _ _ _ . _ _ . _ . . .

'1 1

i 200 -

i I

. San jonotre Unit 2 '

Combined i

MCRi & Survoillanco Data Material: Plato 'No. C6404-2, SA533B1  !

Oriehtation: TL

- USE = 113 ft les 150 -

ND_T,=RE__..f_80 'F T @,50 ft-lbs =

~ "

RTndt = 20 'F 0

en "

o

1. a .

8 a E oo

. o- .

> 0 0 E

100 - - - - - - - ~

=0 - ---

c .

O W J  ;

Z O

> d o "

o

'O ' Measured '

50 -- - - - - --

- - [-

Calculated l'

O o l

....i n a a a ll a a a a l a a a a I aa n' a ll n a a a a a a a 0

-200 -100 -0 .100-- 200 .300. '400 500 Temperature in Degrees F-

-SONGS, Unit 2; ' Data and least Squares _ Fit Curve for Cm versus -

' Figure 3 9. - -

Temperature, . Plate C6404-2, TL _ Orientation, Combined .MCR _' and ~

~ Surveillance Baseline Data.

3-14  :.

$.II - -. L . , , ._ , ,. , 4 , ,.c.. , e

Fj,

/

200 ------r- -----r--- -r- -----r--- ~ - - - - - - --- --

I f = 0.0 O O 150 --- I -- -- -- -

E ~

a 2

A O

g 100 - + - -

c a tu -

2

> ~

O .

San Onofro Unit 2

~

Surveillance Prohram-50 -- - - - ---

--Material-Plate-Nor 06404 2r SA533B1 -

. a Orienthtlon: LT USE A 150 ft lbs l NDT d 10 SF 9

0

' I' ' "' h 200 100 0 100 200 300 400 500 Temperature in Degrees F Figure 310. SONGS, Unit 2: Data and least Squares Fit Curve for Cm _versus Temperature, Plate C6404-2, LT Orientation, Surveillance Baseline Data.

3-15

200 - -

- San Or otto Unit 2

. Comparison of M R Data with Survoillt nce Best fit Lino Material: P5ato . C0404 P, A53301 Orienta:lon: LT o

150 - -

O m ~

.)

u.

. O 3

[100 C

W Z

0

• C c 0 MCR Data 50 =

~

Fit to Survoillance

• Data g

/

o

-200 -100 o 100 200 300 400 500 Temperature in Degrees F Figure 311. 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 3-16 a

i l

-)

i 200 - - -- - - - - ' -

-- - q -

T

~

San Onofro Unit 2 l WMCbata

. Material: Weld

. Weld 9 203 USE = 144 ft itn 150 --~gyq;6dF 0 ~V ~~~~~

~ ~~~~'

r  ;

T @ $0 ft lbs = +20 'F

1. RTndt' = 60 'F 0 n .

T ed . O '

h y jQQ . . . . . _ . . . , _ . ...

._(

3 mm . . . ~ ~ . ... , . - . . , . - . . .-

F E .

w 8

.z od -

0 50 =

0

~ ~ ~

Measured '-

. g Calculated

- o -

O

^""'' ' ' '

l

200 - 100 0 100 .200 300 400' . 500:

Temperature in- Degrees F-Figure 312.- - SONGS, Unit =2: Data and Izast Squarcs Fit Curve for Cwversus. ;

- Temperature, Weld 9-203, WMC Data. l.l.

l' 3 17 i -

1 5

h -r -- r-w sw, *s e

P i

r e

i ggg . . . . . ~ ~ . , --, - . . . . - - - - . , - . --- - = ..--~~---:

. -i

. f = 0.0 i 150 - - - - --

r"--- "- O- A

" ~ ' " " " ' " ~ ~ ~ " ~ "

O

. U

-b 2

u.

w 100 ---l----- - - -"-~~ - ~~~~ --

h

• 2

/

O -~

/ San Onofre Unit 2 f'i Surveillance Program Matdial: Wold 50 -

--/1 ---- - - -

g3j'gg .

/

NDT'= 50 P'

. g T @ p0 ft-lbs = 10 Y RTndt=.50 Y ,

~

O

-r- 10,f, 1. , , . - . i , ,n .1 ....It n iin I ie e i1: a n . -

I 200 100 0 100 200 . 300. 400 500-Temperature in Degree F Figure 313. SONGS, Unit 2: Data and Least. Squares Fit Curve for Civersus-_ ,

Temperature, Surveillance Weld, Surveillance Baseline Data.

3-18 q g-. ----gig e y eg ig+ w ,p .m. er-- Ny

Table 3.1 SONGS, Unit 2: Compliance with 10CFR50, Appendix G.

Paragraph Description of Non-Compliance Comment l l

II.B Series 4xx stainless steels are Consistent with AS;iE Code in effect.

purchased and 11:ated to Coue requirements. No RTuct or drop weight Tyor 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 1 certification that tests were to the applicable ASME Code is performed in accordance with included. The intent of Appendix G is Appendix G. ** met.

Ill.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 Ill.C available for SONGS Unit 2 indicate j' is not complied with in that that the intent of Appendix, G has been only base plate and represent- met. (Note: the HAZ results am not ative welds in the beltline presented in'this report) region were considered for the required testing.

III.C.1 Only sing!c-temperature testing Consistent with ASMB Code in effect.

was perfermed for some weld materials.

Only the heat-affected zone from the most limiting plate was tested over an extended temperature range.

Ill.C.2 ~ Excess material for. test The same combinations of a specific specimen weldment is not . heat of filler wire and a specific lot of necessarily- from the actual flux welded under the same production production plate, although conditions as those used in joining the .

it is the same P-number, corresponding shell materials were used.

(Section IX, ASME Code) 3-19

. - . ...,~,..-. - .

Table 3.1 (Continued)

Paragraph Description of Non-Compliance Comment IV.A.4 Charpy V-notch tests were The ASME Code in effect not conducted at "the required test temperature of 60'F preload temperature or at below the lowest service the lowest service temperature. All bolting material temperature, whichever is was tested at 10*F and met the 35 lower". ft-lb minimum requirement of the applicable ASME Code. All beltline plate materials and one beltline weld were tested to meet the current (1989) Code requirernents in NB-2331. The remaining beltline welds were tested at 10'F and have Cv3 in excess of 100 ft-lb. These results indicate that the intent of Appendix G has been met.

.3 20

Table 3.2 SONGS, Unit 2: Plate and Corresponding Heat Numbers for the Beltline Plates.

Lukens '

Plate Number Heat Number C6404-1 C7596-1  !

i C6404-2 C7595 2 C6404 3 C7595-1 C6404-4 A6735-1 C6404 5 C75851 C6404-6 C7596-2 ,

p e

l i

l 3-21 l

. - .___ - - _- - =.

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. EOBC l 3-203 A, B, C Type Mil B-4 Wire, Heat No. 83637, Linde Type 0091 Flux, Lot No. I122 9 203 Type Mil B-4 Wire, Heat No. 90130, Linde Tym 0091 Flux, Lot No. 0842 8-203 Not available l Surveilluce' Reported by ABB-CE to be the same consumables as Weld 9-203

a. Work is continuing with ABB-CE to obtain the source documentation l I

L l

l 3-22 e - < M

. _ _ . ~ . _ . _ .. __ . _ _ _ .. _ _ _ _ . _ _ __

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 CM041 P14445 0.10 0.56 0.007 0.009 65 P16921 l C M 04-2 P14446 0.10 0.59 0.008 0.010 65 P16922 C64N-2' O.10 0.59 0.012 N/A 65 CM04-3 P14447 0.10 0.56 0.008 0.011 - 65 ,

P16923 C6404-4 P14150 0.10 0.62 0.006 0.009' 65 Pl7110 C M 04-5 P14068 0.I1 0.64 0.007 0.010 75 Pl7405 +

C64N-6 P14106 0.10 0.58 0.006 0.010 65 Pl7111

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 97m I

3 23

% ,w,. er y, - -

Table 3.5 SONGS, Unit 2: Key Residual and Alloying Element Contents for Ikilline Welds.

Weld ABB-CE Number Lab No. Cu Ni P S C F' 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 _

3-203A D17025 0.05 0.12 0.011 0.011 40 3-203B D17026 0.04 0.06 0.010 0.011 30 3-203C D17027 0.06 0.I1 0.010 0.011 42 d

8-203 0.31 (0.35)6 l' O.012 0.010' 272 9 203 D23227 0.07 0.29 0.009 0.007 69 Surveillance' D26761 0.03 0.12 0.003 0.009 30 Surveillanec' O.03 0.15 < 0.005 N/A 32

a. Chemistry Factors determined from Regulatory Guide 1.99, Revision 2

b. A measured Cvu chemistry of 0.31 wt% was reported in the PSAR, but no drumentation has been obtained to validate this value. Therefore, the Cu content has been assumed at 0.35 wt% per Regulatory Guide 1.99, Revision 2

c. Ni content was not obtained and I wt% has been assumed (per Regulatory Guide, Rev. 2)

d. As reported in the FSAR

e. Measured when surveillance program was developed"I

f. Measured when the surveillance tests were performed for Capsule 97m 3 24 l

l Table 3.6 SONGS, Unit 2: Beltline Plate Material Unirradiated Fracture Toughness Tests Results Summary, TL Orientation.

-t initial Plate NDT RTum Procedure to USB Number ('F) ('F) Determine RTum (ft lbs)

CM041 30 20 NB 2331 (a)(3) 119 C M 04 2' + 10'" 20 NB 2331 (a)(3) 113-C6404 3 -20 20 NB 2331 (a)(3) 99 C M 04-4 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

a. This plate is included in the surveillance program. RTuur and USE values are based en the combined data sets from the MCRs and unirradiated surveillance "

baseline (see Figure 3-9)

b. Highest of 2 transverse values (i.e.,-20*F determined when plate was purchased, '

and +10"F from surveillance baseline) t 3 25.

Table 3.7 SONGS, Unit 2: Charpy Absorbed Energy Values at 10*F for Weld Seams ,

2-203 A, B, and C; 3-203, A, II, and C; ud 8 203. l Charpy Energy i Weld Scam (ft lb) 2 203 A 118, 104, 158' 2 203 B, C 106, 108, 105' -

3 203 A, B, C 153,131,125 8-203 108,112,119' l

a. Vducs reported in the FSAR, but source documentation has not been obtained at this time. ABB-CE is continuing to pursue obtaining- the soutec material .

b. . Values reported in the FSAR, but source documentation is unlikely to be obtained 3-26 e

Table 3.8 SONGS, Unit 2: Beltline Weld Material Unitradiated Fracture Toughness Tests Results Summary, initial NDT RTuot Procedure to USE Weld Seam ("F) ('F) Determine RTuor (ft lbs) d 2 203 A -& 6(f NB 2331 (a)(2) 126 2 203 B, C -W 4(f Nil 2331 (a)(2) 106 d

3 203 A, D, C 50' 50 NH 2331 (a)(2) 136' d

8-203 N/A -56 c ll3 ' l 9 203 -@ 60 NB 2331 (a)(2) 144 Surveillance -50 50 NB 2331 (a)(4) 146

a. NDT values were obtained from the FSAR and documented in Appendix D (except for Welds 2-203 A, B, C)

b. Estimated as equal to NDT based on three Cvu data points above 100 ft-lb at NDT + 70*F (see Table 3.7)

c. Generic value for ABD-CE fabricated vessels using Linde 0091,1092, and 124 fluxes (see 10CFR50.61)

d. Estimated using the average of Cvu values obtained at +10*F (see Table 3.7)

c. Not used to assess upper shelf toughness drop since documentation is not expected 3 27

Section 4 -4 ISSUES RELATED TO GENERIC LETfER 8811 NRC isstal Generic Letter 8811 (GL 8811)in July 1988. GL 8811 revised the methodology used for estimatirg 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 59(TF 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 (T,) is never below 545"F during power operation and rises to about 553'F at full power. Thus, there is no time during normal power operation that the SONGS, Unit 2, vessel or surveilheice capsules experience temperatures below 545'F.

4.2 APPLICABILITY OF SURVEILLANCE DATA To properly assess the measured sarveillance 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 Huence as a function of effective full power years (EFPY) was obtained from the results of the nrst 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 Duence at the vessel inner surface is 4.34 x 10" n/cm (E > 1 MeV); the capsule fluence was about 20% higher at 5.07 x 10'? n/cm'.

At the start of the fourth cycle for each unit, the core was reenn6gured 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.N The peak Duence wlue for the vessel inner surface is 6,6 x 10" n/cm', and the associated capsule fluenec is 8.0 x 10" n/cm'.

41

The projection of Guence forward in time is based upon an extrapolation of the dosimetry ir. formation 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'.m 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'.

3 As irrJicated in Figure 31, there is a weld identified as 8 203 which is well outside the core region of the vessel (l.c., approximately 2 feet above the top of the core). This weld is conscnatively considered a beltline material because of a large chemistry factor associated with the high reported Cu content (0.31 wt%) in combination with a I wt% Ni content, which was caservatively assumed because Ni was not reported. Also, since the Cu content has not been MWaiJJ for this weld, a conservativo value of 0.35 wt% has been assumed. The fluence at this incation above the core has reported in the USAR to be about 1/37 that of the peak fluence r location within the vessel. Recent calculatu.as performed at SCEN indieete 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.

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 i25'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 cap:ules (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.

Ir 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 2 surveillance program was tested in 1988. The Cm results from this capsule are shown in Figures 4-1 (Plate C6404 2/LT),4-2 (Plate C64%2/TL), and 4 3 (surveillante weld). Appendix H contains, in tabular form, the absorbed energy, lateral expansion, and fracture appearance (% shear) for the irradiated surveillance materials.

The results computed during this work for the shift at the 30 ft lb energy level are tabulated in Table 4.1 as ' current" and compared to the Regulatory Guide 1.99, Revision 2, mean shift predictions (RGl.99R2):

4-2 l

l

[

1

RGl.99R2 = CF (chemistry factor) x ff(fluence fuaetion).

The resuits obtained by Ba".cllem are also shown for comparison. The differences between the current values for shift "ersus those from Battelle are due to small differences in the curve fit to the Cvu data and the different data set used for unirradiated Plate C6404 2/TL (i.e., Figure 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 Regulatory 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 RTmn (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 RTyms were taken from Tables 3.6 and 3.8. The results in Table 4.2 show that the adjusted RTmy 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 SilELF ENERGY DROP i

Capsule 97 from the SONGS, Unit 2, surveillance program was evaluated in 1988. The USE results are shown in Figures 41,4-2, 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 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 2, beltline materials. At the end of 32 EFPY, none of the materials are projected to even approach the NRC screening limit of 50 ft-lb specified in 10CFR50, Appendix G. Due to the lack of documentation for the Cvu energy values for Weld 8 203 (as reported in the FSAR), an evaluation was performed to demonstrate that the upper -

shelf for Weld 8 203 has toughness equivalent to that required by Appendix G to the ASME Code; this evaluation is presented in Section 5.-

43

_ m

20C -

. I San Ondfro Unit 2 I ,

~

Survollidnco Program  !

- Motorial! Plate SA533B1

- No. C6404-2 1

!; 4 i

Orientation: LT 150 --

t - j --

y h - - -- - - -- ~ ~ --- --

!  ! / l l / o 6 o a ~

/

f  ;

8  ! /O \

u, j  ?

/ O

> /

9 U

100 -- - --

~1- -

1 I c - 1 I

W  !

/ 1 Z / .i {

> ~ I i

O t

- I p -----

f = 0.0

/

50 --

' ~/~

/ f = 5.070+18

/

I o f = 5.070+18 I /

i 3

! ie f -

- - t -r 1- W16 J 9-r-t*FI)e a e a Il e a e a U e a e e i e e a e i a e a e Il

-200 -100 0 100 200 000 400 500 Temperature in Degrees F Figure 41, SONGS, Unit 2: Comparison of the Ixast Squares Fit for the Unitradiated Baseline Data with the Irradiated r'w Data and least Squares Fit for the Data from Capsule 97, Plate C6404-2, LT Orientation.

4-4

200 --

I ofre Unit 2

- San

. CombinOn'ed MCR &! Surveillance Data

~

Material: Plate AS33B1 Heat No, C6404 2 Orlentaf alon: . TL 150 -

F

--~~~

--t - - - -

. I e =

n.

"T "

E ,.____ _ . _ ._ - , _ _ _

y. s' g 100 - - - - -

y o- -d-c .

$ /

uJ /

~ /

Z /

>- <l o .

- / ______.-f=0.0L

-/

50 - ~ ~ ~ - - - --

~1"

, j 1 . f = 5.07e+18

- j :o/

'o f = 5.07e+18

. /O

'_,_._, d .c....i,..., ... < . . . . , .... -

o 200 -100. 0 100 - 200 300 400- -500 Temperature in Degrees F

~

Figure 4 2. SONGS,-- Unit 20 . . Comparison of. the -least Squares- Fit for : the Unirradiated Baseline-Data = with the: Irradiated C, Data and: Least:

=

Squares Fit for the Data from Capsule 97, Plate C6404 2, /IL Orientation.

4-5

'l l

200 -

I  ! '

San Onofro Unit 2,

. Survel'Ilanco Program ,

Matollal: Wold e.A,... ..,m.w... .m.......+,.... . ..m..- ++.+.r..-...+,. w ,a.mu . # e 4m.. r . . . - - .e.i, u ma. ..,mm,, ,..E,,#.w.2%,....i

_-eae.-

- r -. _ _ ,. _ _ ._

g 1,#], _

e /

O

/

/ O

u. / ,

. . /

> i E'100 --

--- j-/ ,/

g ,

W 5 z -

> ~ I U I .

I

. / _ _ -

~ f = 0.0

/ .;

50 ~'-

- - - - -'t

-}

/

I o f = 5.070+10 O

~'~ ' ' ' ' ' " " ' ' ' ' ' b O

-200' 100 0 100 290 300 f400  : 500 Temperature in Degrees F.

Figure 4 3. SONGS, Unit 2: ~ Comparison of the Least _ Squares. Fit for the--

Unitradiated ~ Baseline -Data zwith.the Irradiated- Cm Data and;least?

' Squares Fit for the Data from Capsule 97, Surveillance Weld. . .

46 r

i

..',,-~-.... V 'b . . .,-[+ .l _

. ,,.r--,, #_.,,, 4 .. ..s, _ . ' ._, i... h,._.. ..d-.~..-- .r.-- - . m

4 Table 4.1. SONGS, Unit 2: Surveillance Capsule Shift Results.

30 ft lb Shift ('F) ,

Material / CF ff Orientation llattelle ROl.99R2 Current C64(M-2/LT 65* 0.81 51 53 52' C6404 2/TL 65' O.81 45 53 33d Surveillance 3 16 0.81 7 25 4' Weld

a. See Table 3. (Lu = .10; Ni = .59)

b. 11ased upon the average chemistries -- see Table 3.5 (Cu = .03; Ni = .14)

c. 11ased on the baseline surveillance data, see Figure 3-10

d. Ilased on the combined data set from the MCR and baseline sun'cillance program, sec Figure 3 9 ,.

e. liased on the baseline surveillance data, see Figure 313 9

7 1

, * - , _ - . - - . ,_ .~..-,w,r.c_ , , , , - - - - - -,r.n , e

Table 4.2. SONOS, Unit 2: ART Estimates at the Inner Surface location for Bcitline Materials on 12/16/91 and at 32 EFPY.

Fluence Function ART (*F)'

Plate No./ CF at the Inner Surface at the Inner Surface Weld Scam 12/16/91 32 EFPY 12/16/91 32 EFPY CM04-1 65 0.95 1.37 116 143 CNN 2 656 0.95 1.37 116 143 C M 04-3 65 0.95 1.37 116 143 C6404-4 65 0.95 1.37 116 143 C64M-5 75 0.95 1.37 116 147 C6404 6 65 0.95 1.37 116 143 .

2-203 A, B, C 4 l' O.95 1.37 18 52 3 203 A, B, C 38d 0.95 1.37 23 54-8-203 272 0.09' O.25' 12' 79' 9-203 69 0.95 1.37 62 90

a. ART is the adjusted reference temperature equal to the predicted shift (CF x ff) plus the initial RTw plus a margin term equal to 34'F for plates or 56'F for welds (unless the c...m.m sk,6 is less than the margin term, in which case the margin is equal to the.

picJicted shift)

b. Based upon aserage chemistrier 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

c. Fluence function is based upon the peak vessel fluence divided by 10893

f. Since there is a no' measured initial RTmn, an additional margin associated with the standard deviation (17'F) of the initial RTmn has been used as described in Regulatory Guide 1.99, Rev. 2 4-8

Table 4.3. SONGS, Unit 2: Surveillance Capsule Upper Shelf Results Upper Shelf Drop (ft lb)

Material / Cu Fhence ,

2 Orientation (wt%) (x 10" n/cm ) Battelle RGl.99R2 Current C6404 2/LT 0.10' O.507 17 24 158 ,

C6404-2/TL 0.10' O.507 21 18 14' Surveillance 0.036 0.507 5 24' 4' Weld

a. See Table 3.4 ,

b. See Table 3.5

c. Based upon the Regulatory Guide 1.99, Rev. 2 lowest percentage drop (16.1%) curve at the speciDed Duence times the measured unirradiated upper shelf determined in this report

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 i

l 1

I 49 l

\

1 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. I i

I Fluence (x 10" n/cm2) Upper Shelf Energy (ft lb)' l Plate No./ Cu at Ouarter-Thicknen at Ouarter-Thickness i Weld Seam (wt%) 12/16/91 32 EFPY 12/16/91 32 EFPY C6404-1 0.10 0.51 2.5 100 91 CM04 2 0.1 06 0.51 2.5 95 87 I C6404 3 0.10 0.51 2.5 83 76 C6404-4 0.10 0.51 2.5 87 80 ,

l C6404-5 0.I1 0.51 2.5 98 89 l

C6404-6 0.10 0.51 2.5 104 95 2-203 A, B, C 0.03' O.51 2.5 89 81 3-203 A, B, C 0.10d 0.51 2.5 108 95 9-203 0.07 0.51 2.5 118 107

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-

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 4-10  ;

Section 5 UPPER SHELF ENERGY EVALUATION FOR CIRCUMFERENTIAL WELD 8-203 Although the FS AR lists values of Cu content and energy values at 10 F for weld 8-203, source material to verify the FSAR values has not been located. Because it appears unlikely that source documentation will be obtained to confirm the chemical composition and upper shelf energy for l, weld 8-203, an evahiation was performed to demonstrate that the weld seam has an upper shelf  !

toughness equivalent to that required by Appendix G of the ASME Code as speci6ed in l Appendix G to 10CFR50. As indicated in Table 3.5, conservative values of 0.35 wt% and 1.0 wt% were assumed for chemical compositions for Cu and Ni, respectively, in accordance with Regulatory Guide 1.99, Revision 2.

i 5.1 EVALUATION PROCEDURE The upper shelf energy evaluation was performed using the analysis methods and acceptance I criteria specified in Appendix X to Section XI of the ASME Code m and a material J-R curve determined using the procedures presented in [6). The evaluation was performed for Level A and B Service loadings.

The acceptance criteria specified in [5] for Level A and B Service loadings are:

i X-2200 Level A and B Service Loadings (a) When evaluating adequacy of the upper shelf toughness for the weld material for Level A and B Service loadings, an interior semi-elliptical surface flaw with a depth one-quarter of the wall thickness and a length six times the depth shall be postulated, with the flaw's major axis oriented along the weld of concern, and the flaw plane oriented in the radial direction. When evaluating adequacy of the upper shelf toughness for the base material, both interior axial and circumferential flaws with depths one-quarter of the wall thickness and lengths six times the depth shall be postulated, and toughness properties for the corresponding orientation shall be used. Smaller flaw sizes may be used whenjustified. Two criteria shall -

be satisfied:

5-1

o (1) The applied J R integral evaluated at a pressure 1.15 times the accumulation pressure as defined in the plant-specific _ Overpressure Protection Report, with a factor of safety of 1.0 on thermal loading for the .

plant-specific heatup and cooldown conditions, shall be less than the J- l integral of the material at a ductile flaw extension of 0.10 in. I i

(2) Flaw extensions at pressures up to 1.25 times the accumulation pressure l of X-2200(1) shall be ductile and stable, using a factor of safety of 1.0 on i thermal loading for the plant-specific heatup and cooldown conditions.

(b) The J-integral resistance versus flaw extension curve shall be a conservative ,

representation for the vessel material under evaluation, j The J-R curve required for the Code analysis was obtained using the Cu-fluence model specified in [6] for welds, a Cu content of 0.35 wt%, the fluence at the quarter-thickness location for 32 EFPY (i.e.,2.3 x 10" n/cm ),tand a temperature of 550"F. The Code evaluation procedure l[

requires the use of a J-R curve that is a conservative representation of the material toughness.

To satisfy this requirement, the mean minus two standard deviation J-R curve was (4 sed and was obtained from [6] by applying a factor of 0.566 to the mean J-R curves.

The mean minus two c.andard deviation J R curve determined from [6] for weld seam 8-203 is shown in Figure 5-1.

The computational procedures of Paragraphs X-4200 and X-4330 were used to evaluate compliance with the criteria in X-2200(a)(1) and (2), respectively. The analysis was performed using an accumulation pressure of 2,750 psi and a cooldown rate of 100'F/h.

5.2 RESULTS The computational results obtained to assess the 0.1 inch crack extension criterion of [5] are summarized in Table 5.1. The applied J-integral value for a postulated 0.1 inch crack extension, an accumulation pressure of 2,750 psi and the required margin on pressure of 1.15 is 160 in-lblin 2. From Figure 5-1, the value of the J-integral corresponding to a 0.1 inch crack extension in the irradiated vessel material at 32 EFPY is 740 in-lb/in 2. Because the material J-integral value is much greater than the applied J-integral value, the Code 0.1 inch crack extension criterion is satisfied by a wide margin.

The procedure of Paragraph X-4330 of the Code was used to assess the stability criterion. The analysis results are summarized in Table 5.2. The value of the J-integral at instability, J*, was obtained from the intersection of the applied and material J/T curves shown in Figure 5-2. The value of the crack extension at J* was ebtained from Figure 5-1.

5-2 i

I l

The results in Table 5.2 indicate that the pressure. at which the Code stability criterion is .I satisfied is somewhat greater than 8,000 psi. This value is far in excess of the pressure required- I by the Code (1.25 x accumulation pressure) and indicates the stability criterion is met by a wide l margin. q Because the Code criteria for Level A and B Service loadings were met by large margins and because experience indicates the Code level A and B criteria are limiting compared to the Code Level C and D criteria, upper shelf toughness evaluations were not performed for Level C and l D Service loadings.

Based on the results of this evaluaticn, it can be concluded that the upper shelf toughness for weld seam 8-203 meets the Code criteria, provides margins equivalent to those in Appendix G l of the ASME Code, and satisfies the requirements of Appendix G of 10CFR50.  ;

5-3

l

]

-1 l

l

-l 1,500 =

San Onofre Unit 2 4 Materlot Wald 8 203

$ . Cu = 0.35% *

. Fluence @ t/4 = 0.23E18 n/cm *2

- Temperatuse = 550 F ,

~

/  :

e. - .

_c Y

a .

$r '

' 500 -

-i.,

~- ^ -

o , , - , , , , 1 , , , , , .-- . 1 , , .

0.00 ~ 0.20 0,40' . 0.60 0.80 ..l.00' delta A, Inch.

Figure 5-1, ' SONGS, Unit 2i Material J-RfCurve' for Upper . Shelf' Toughness ;

E/aluation of Circumferential Weld 8-203.

5-4 we -- -4 , - . . - _ _ _ __.___.._-_-________.___..____..____.__.___._____...___.____.__.___m....-_.c.m__. - _._ __.

,,, . . _ . , . ~ . .. . --

i

_ .-a I

2,000 =

Son Onofre Unit 2

~j Materlot: Wold 8 203-Cu = 0.35%

i- ~

s. Fluence O t/4 = 0.23E18 n/cm *2 Temperature = 550 F, e

1,500

~

= '

i. -  :

e a  ;

-N . #

C g  ;

E - .  :

s  : . 1

, ~ . o c - H

[-1.000 =

a

? -

.c -

300

=

N J '

Material l - - - - Applied

.n c.

20

~'

O 10 15 i

Tearing Modulus -

Figure 5-2. ';S'ONGS,7 Unit' 2:' jApplied _ and Material J/r Plots for'. Upper: Shelf.

Toughness Evaluation of Circumferential Weld 8-203.

5-5 l 1. . <

'i Ta ble 5.1. SONGS, Unit 2: Evoluotion of Appendix X 0.1 inch Flow l Extension Criterlon for Circumferential Weld 8-203 q Input

- Thickness = 8.75 (Inch)

E= 28000 (ksi)

E'= 30769 (ksi)

CR= 100 (deg. F/hr)

SF = 1.15 , .,

Ps = 2,75 (ksi)-

Rt = 86 (Inch)

Yield Stress = 50 (ksi)

Results Step 1 A= 2.288 (Inch)

A/t = 0.261.

F2 = 0.969 ,

Kip = 48.6 (ksi-In ^0.5)

F3 = 0.899 a

Kit = 20.4 (ksi-in 0.5)

Step 2 Ae = 2.388 (inch)

Ae/t = - 0.273 ~ ,

P2 = 0.974 ~

_. K'Ip = - 49.9- (ksi-In ^ 0.5)

P3 = 0.898 ~

K'It = 20.5 (ksi-in ^O.5)

J @ 0.1 = - 160 (lu-lb/in ^2) '

. 'I l 5-6

Table' 5.2. SONGS, Unit 2: Evaluation of Appendix X Instability. d

- Criterion for Circumferential Weld 8 203 -

-q X-4330: fJ/T Procedure ]

Input Thickness = 8.75 (inch)

Flow Stress = 85 (ksi) -

E= 28000 (ksi) -

-j E' = - 30769 (ksi)

CR= 100 (deg. F/hr)-  !

SF = 1.25 Ps = 2.75 (ksi)

RI = - 86 (inch)

Yield Stress = 50 (ksi)

X-4331: J of Flow Instability W= -0.330 J/T = 746

.X-4331: Results from J/T Plot and J-R Curve -

J* = '1250 (in-lb/in ^2):

- delta'A = 0.7 (lnch)

X-4332: Internal Pressure at Instability .

A*e = 3.704 (Inch)

F*3 = 0.804-K*lt" = .18.2 (ksi-In'^0.5) -

K*1p = - 177.9 (ksi-In ^0.5)

F*2 = 1.045- .

P* = - 8.4 (ksi) 5-7

.. = .

Section 6 l REFERENCES ,

[1] A. Ragi, Southern California Edison San Onofre LUnit 2. Evaluation of Baseline Specimens. Reactor Vessel Materials Irradiation Surveillance Program, Combustion-Engineering S-TR-MCS-002, May 27,1978.

[2] M. P. Manahan, L. M. Lowry, and E. O. Fromm, Examination. Testing. and Evaluation of Irradiated Pressure Vessel Surveillance Specimens from the San .

Onofre Nuclear Generating Station Unit 2 (SONGS-2), 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 Caosule Removed from the 97* Location, Westinghouse WCAP-12920, Revision 1, November 1991.

[4] R. Chang, " SONGS 2/3 RPV Fluence Ratio at Weld S-203",SCE Calculation No.

N-1020-065, December 1992.

[5] Appendix X, Assessment of Reactor Vessels With Low Upper Shelf Charpy Impact Energy Levels, Revision 13, November 25,1992, Subgroup on Evaluation Standards, Section _XI, ASME Code.

[6] E. D. Eason, J. E. Wright, and E. E. Nelson, "Multivariable Modeling of Pressure' Vessel and Piping J-R Data, NUREG/CR-5729, U.S. - Nuclear Regulatory _

Commission, Washington, D.C.,May 1991.

6-1 L

-l

'l 1

l l

APPENDIX A s

SONGS, UNIT 2: . EVALUATION.0F COMPLIANCE WITH ASTM E185-73 AND E185-82 i ..

i

a

-i

~ Summary of Requirements San Onofre Unit ~2_' Program:

par ASTM.E185-73

' 1. '2 . Surveill'ance ' tests: 'are Compliance" divided 'according- 'to- ,

]

applicationsinto 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 > l'MeV) of the reactor' vessel is 5 X.10 18 n/cm or less.-

2 1.2.2 Case B~ -

Where the predicted increase in transition temperature of the a 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 18 a

n/cm --

4.1 Test- Material -: Test. To be confirmed upon receipt'of-:

specimens shall be__ prepared source -documentation' twhich-

-verifies heat- numbers for Welds -

~

from the actual materials used in fabricating the --irradiated 203 A; B,eC and_ surveillance-region.of the reactor vessel. weld material.

,l 4.11. Samples shall represent _a< . Compliance-minimum of one-heat of the base metal and one butt weld;and one =

weld heat-affected-zone -(HAZ)

' if a- weld ~ occurs in the irradiated = region.

4.1 The ' . base metal and weld Compliance metal to be : included-: in the-program: should ' represent the-material? that- may~ limit' the cperation of the reactor 'during _ -.j its lifetime.

A-1

• I.

s _. -

Bummary of Requirements San Onofre Unit 2 Program per ASTM E185-73 4.1.1 Vessel Material Sampling To be confirmed upon receipt of.

- A minimum test program shall source -documentation . which consist of specimens taken from verifies heat numbers for Welds the following locations: (1) 2-203 A, B, C and surveillance base metal of one heat used in weld material, the irradiated region, (2) weld metal, fully representative of  !

the fabrication practice used i for a weld in the irradiated region (weld wire of rod, must l come from one of the heats used '

j in the irradiated region of the reactor vessel) and the same i type of flux, and (3) the heat- 1 affected-zone associated with the base metal noted above.

4.1.1 Representative test stock Compliance to provide.two additional sets of test specimens of the base metal, weld and heat-affected-zone shall be retained with full documentation and identification.

4.1.2 Fabrication History - The Compliance test material'shall receive a fabrication history (austenitizing, quench and tempering, and post-weld heat treatment) fully representative of the fabrication received by the material in the irradiated region of the reactor vessel.

4.1.3 Chemical Requirements -

Compliance The -chemical composition required by the' material specifications for. the test materials (base metal and _ as deposited weld metal) shall be A-2

I Summary of Requirements- San Onofre Unit 2 Program per ASTM E185-73 obtained and-include, but not Compliance -,

be-limited to phosphorus (P),

sulfur- (S), copper (Cu), and  !

vanaditt= (V).

1 1

Compliance 4.2 Charpy V-notch impact .

specimens corresponding to the  !

Type A specimen described in Methods E 23-shall be employed unless material thickness does

.not permit. Both irradiated and unirradiated types of specimens shall be of the same size and shape.

4.3 Specimen Orientation and Compliance Location - For both tension and impact specimens from base metal, the major axis of the specimen shall be machined normal.to the principal rolling direction for plates and normal to the major working direction for forgingc. 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 A-3

-: 4 Summaryfof_ s.g'4.rements-- San Onofre Unit-2' Program: >

per ASTM.E185-73 l

roots 'in the heat 'af fected zone at. a: standard distance- of approximately 1/32 in, from the fusion- line.- Specimens e representing the- base metal ,

-(tension and impact) _and the  ;-;

weld heat-affected zone shall

-be removed _from the quarter thickness location. (per NB2300 of ASME Code Section III) 4.4 Number of Specimens The Compliance minimum number of test specimens- for each- exposure shall be as folloen:

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 CcInpliance r specimens. shall_ be used- to -

t establish an- unirradiated-

' transition c u r v e -- for each material. --

+ - .

i! l4.4~ For Case' B .(see above), _Not Applicable- _.

k

- three . tension test specimens shall..be used to -establish'

- unirra'dlated tensile-properties.

k

. 5.1.1 -Vessel.

Wall)-Specimens  : Compliance-t _ . (Required)  : Specimens shall'be

= irradiated at a location in the

~reactbr that duplicates'as' A-4 F7 y -

e

- . .. - . ~ .

-- . - . . .. , ~ ~

Summary.of Requirements-San Onofre: Unit 2-Programi i

per. ASTM E185-73. ,

V

- closelyL ~as- 'possible the '

n e u t r o n - _ f l u x-. ' _ spectrum,

- temperature -history, and s

. maximum accumulated. neutron-fluence experienced- by the ,

reactor vessel ~.

- 5.1.1 The instantaneous neutron Compliance' -

- flux at -the - location of the

-specimer.s shall not'- exceed three times, the calculated maximum--neutron flux at the _ ,

inside ' wall of. the' reactor vessel.

5.1L2 Accelerated -Irradiation ' Not Applicable

. Specimens _ (Optional)- -

Test specimens-nayebe. positioned at locations other than . ( 5 ~.1.1) for. accelerated irradiation;at-a . r a t e _.e x c e e_d i n g ~. t h r e e times ,

the" calculated maximum neutron -

flux at-the11nside: wallof'the-reactor vessel..

L

-- 5. 2' Flux Measurements -

Compliance _

Provisions -shall-- be made to:

measure the neutron fluence as follows:-

-- 5 . 2 .1' Dosimeters. -with the vessel- walli specimens' ' (5.1.1) . .

}

- 5.2.2 - - Where- accelerated ' Compliance irradiatio'n specimens;are used (5.1.2) ,, fdosimeters - with !the:

test ; specimens and i dosimeters '

- either- ~ in: a separate flux' monitor; capsule adjacent to the vessel; wall)or in-a= vessel wall == 9 A-5 E

,' ~

S.

p .

. .m- -

. Summary of. Requirements San Onofre Unit 2-Program

-per ASTM'E185-73 capsule.:-

5.3' Test Capsules - To prevent lCompl-lance:

deterioration of the surface of the' specimens during test,.the specimens should be maintained in an inert environment.within a corrosion-resistant capsule.

5.3 The--temperature history of- Compliance the specimens . shall- duplicate 0 as closely as possible the =

a temperature experienced by the  ;

reactor vessel._. :l 4

5.3 Surveillance; . capsules Compliance should be sufficiently rigid'to prevent damage to the capsules by . coolant' pressure: or coolant-flow: thus : hindering . specimen removal or causing 1 inadvertent

deformation'of the-specimens.

Compliance-

' 5'. 3 Irradiated capsules must not be .bouyant;Jto preclude. '

serious radiation : exposure /to :

personnel:. if under ' water __

handling is employed.

5.3 Consideration. should be ' compliance, give~n, to the; design 'of the -

i capsule and capsule attachments-

-to- Lpermit insertion of La Lreplacement capsules- into: the-reactor-at-a-laterttimeiin the l lifetime'ofJthefvessel.,

J -

A-6'

~

.1

7 I

+

T Summary of-Requirements:

~

San'Onofre Unit-2'Progras',

per-ASTM E185-73 ,

- 5.4 Specimen Withdrawal - A Compliance minimum- surveillance' program shall consist.of three-capsules for Case - A'.1andf five: capsules '

- for Case B. It is recommended that capsules Hbe 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.

6.2 Neutron Flux Dosimeters - Compliance ,

- Flux ' dosimeters for. a --

particular program; shall .be determined by referring to Method E 261.-

i END > END E

l e

L A-7 l

.c

• . p

,w - , - -. . - . _..__________._m _ . . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _

Summary of=Requirskants San Onofre Unit 2 Program per ASTM E185-82

~

8.1 Temperature Environment - Compliance The maximum exposure temperature of the surveillance capsule materials shall be determined. If a discrepancy

( > l 4 *C or 25'F) occurs'between the observed and the expected.

capsule exposure temperatures, an analysis of tha 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 ar.d the

. corresponding- maximum values for the reactor vessel shall be determined in accordance with the guidelines in Guide E 482 and Recommended Practice E 560.

8.2.2 The ~ specific method of determination shall be determined and recorded using both a calculated spectrum and an assumed fission spectrum.

9.1 Tension Tests: Compliance 9.1.1 Method - Tension testing shall be conducted in-accordance.with Methods E 8 and Recommended Practice E 21, 9.1.2 Test Temperature:

9.1.2.1 Unirradiated - The test' temperatures for each material shall include room temperature, service temperature, and one intermediate temperature to A-8

Summary of Requirements San Onofre Unit 2 Program per ASTM E185-82 define the strength versus temperature relationship.

9.1.2.2 Irradiated -

One Compliance specimen from each material shall be tested at a temperature in the vicinity of the upper end of the Charpy energy transition region. The remaining specimens from each material shall be tested at the service temperature and the nidtransition temperature.

5 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 A-9

Suuumary of Requirements San Onofra Unit 2 Program per ASTM E185-82 where the measurements described in 9.2.3 are made.

9.2.2.2 Irradiated - Specimens Compliance for each material will be tested at temperatures selected to define the full energy transition curve. Particular emphasis should be placed on defining the 41-J (30 ft-lb),

68-J (50 ft-lb), and 0.89-mm (35 mil) lateral expansion index temperatures and the upper shelf energy.

9.2.3 Measurements - For each Compliance test specimen, measure the impact energy, lateral expansion, and percent shear fracture appearance. From the unirradiated and irradiated transition temperature . curves determine the 41-J (30 ft-lb),

68-J (50 ft-lb), and 0.89 mm (35 mil) lateral- expansion index temperaturer nd the upper shelf energy. 'ndex temperatures and thu apper shelf energy shall be determined from- the average Curves.

9.2.3.1 Obtain .from the Compliance material qualification test report the initial reference temperature (RTm) as defined in ASME Code, Section.- III, Subarticle NB- 230 for unirradiated materials.

9.3 Hardness Tests (Optional) - Compliance A-10

Summary of Requiremet.ts San Onofra Unit 2 Program per ASTM E195-82

~

Hardness' tests may be performII Compliance on unirradiated and irradiated Charpy specimens. The measurements shall be taken in areas away from the fracture zone or the edges of the specimens. The tests shall ba conducted in accordance with Methods A 370.

9.4 Supplemental Tests Not Applicable (optional) -

If suppleniental fracture toughness tests are conducted (in addition to tests conducted on tension and Charpy specimens as described in 6.1) the test procedures shall be documented.

9.5 Calibration of Equipment - Compliance Procedures shall be employed assuring that tools, gages, recording instruments, and other measuring and 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 shall be maintained in records traceable to the equipment.

10.1 Tension Test Data: Compliance 10.1.1 Determine the amount of radiation strengthening by comparing unirradiated test results with irradiated test results at the temperature A-11

c ,

Summary of Requirements San Onofre Unit 2 Program per ASTM E185-82 specified in 9.1.2.

10.1.2; The tensile strength data-can be verified using the results from the hardness test (optional) described in 9.3.

10.2 Charpy Test Data: Compliance 10.2.1 Determine the radiation induced transition temperature shifts by measuring the

-difference in the 41-J (30 ft-lb), 68-J (50 ft-lb), and 0.89 mm (35 mil) lateral expansion index temperatures before and after irradiation. The index temperatures shall be obtained from the average curves.

10.2.2 Determine the adjusted Compliance ,

reference temperature by adding i the shift corresponding to the l 41-J (30 f t-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 I measurements made before and after irradiation using average value curves.

10.2.4 -(Optional) - Deternine- Not Applicable the radiation induced change in temperature corresponding _ to 50% of the upper-' shelf energy.

before and af ter irradiation i

from average value curves.

A-12 ,

j

f f ?-'

summary'of-Requirements: 8an Onofre-Unit.2 Program -

pfx ASTM E185-82 r

-10.3 Supplemental Test- Data- Not Applicable (Optional) -

If additional, supplemental- tests- are-performed -(9(4) , the data shaL be: recorded to: supplement the informations from the tensile -

and Charpy-tests.  :

10,4' Retention of . Test Compliance-Specimens - It is recommended that all-broken test specimens be retained until released by the owner in the event that '

additional analyses. are required to - explain anomalous results.

11.1 Where applicable, both SI units land conventional units shall be~ reported..

12.2 Surveillance Program Compliance ~

Description Description of

-the reactor ' . vessel including the following:

-11.2.1 Location of. -the surveillance icapsules ;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'.3l Location (s)'of.the-peak ~

vessel fluence.

11.2.4 Lead factors between the specimen fluence . and the peak-

_ vessel fluence lat the I.D. and- ,

A-13

Summary of Requirements San Onofre Unit 2-Program.

per-ASTM.E185-82 the 1/4T locations.. l 11.2.5 Surveillance Material Compliance

• Selection:

11.2.5.1 Description of all beltline materials including chemical analysis, fabrication history, Charpy data, tensile 4 data ~, drop-weight data, and initial RT ,y. >

11.2.5.2 Describe the basis for selection of surveillance materials. ,

11.3 Surveillance Material ' Compliance-Characterization:

~

-11.3.1 ' Description- of the surveillance material including -

,_ f a b r i c a t i o n " h i s t o r y ,- m a t e r i a l

-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'materic1.

L '11.3.3 Test Specimen Design: Compliance-

'11.3.3.1' Description. of .the test specimens- _(tension, Charpy, Land.any;other.-types ofL L specimens used), Lneutron- .

K dosimeters, and 4 temperature i

monitors'.'

L 11.3.3.2 Certification of p . calibration of:all equipment -

A L:

L i

=&'

.4, i , _

1 . _ _ _ .

r summary of Requirements- san Onofre Unit 2 Prograaf -

per-ASTM E185-82 and instruments- _used -in d

. conducting,the tests..

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 (ifLa group of specimens exhibits similar stress-strain curves,.a-typical curve may:be reported for the group).

11.4.1.4 Test Data from each specimen as'follows:

(1) -~ Test _ temperature; .

(2) Yield'-strength- or yield point and- method of measurement;

=. ;

(3) Tensile' strength; (4) Fracture load,. fracture strength, and: fracture stress; (S) Uniform elongation- and

method of measurement; (6) Total-elongation;--

~(7)-Reduction of:. area;<and-(8) Specimen identification.-

a 11.'4.2 Charpy Tests:-

' Compliance:

.11. 4. 2.1 ' Trade s name - and ~ model

-ofE . the_ . testing -machine,

-available: . ~ hammer energy ,

capacity and striking velocity, .

temperatureL. conditioning and; measuring devices,_and a description of the procedure -

A' ,

m ._, _

.,.;._ .1 .- ,

Bummary of Requirements San Onofre Unit 2 Program per ASTM E185-82 used in the inspection and calibration of - the testing machine.

11.4.2.2 Test data from each specimen as follows:

(1) Temperature of test; (2) Energy absorbed by the specimen in breaking, reported in joules (and foot-pound-force);

(3) Fracture appearance; (4) Lateral expansion; and (5) Specimen identification.

11.4.2.3 Test data for each material as follows:

(1) Charpy 41-J (30 f t-lb) , 68-J (50 ft-lb), and 0.89 mm (35 mil) lateral expansion index temperature of unirradiated material and of each set of irradiated specimens, along with the corresponding temperature increases for these specimens; (2) Upper shelf energy (USE) absorbed before and after irradiation; (3) Initial reference temperature; and (4) Adjusted reference temperature.

11.4.3 Hardness Tests Compliance (Optional):

11.4.3.1 Trade name and model of the testing machine.

11.4.3.2. Hardness data.

11.4.4 Other Fracture Toughness Not Applicable Tests:

A-16  ;

I

m. _m . _ . ._ .,- . ._ _ ,

( l ,

Summary of Requirements- San Onofre Unit'2 Program -

per ASTM E185  ;

11.4.4.1 If - additional tests Not Applicable; are perf ormed, . .the test: data --

shall be reported together with a the procedure = used for I conducting. the- tests and-analysis of the' data.  !

i

...... .. . _.... ... . . ..- 1 11.4.5-Temperature and Neutron Compliance- 4 Radiation Environment i

Measurements

• i l

11.4.5.1 Temperature monitor  !

results and an estimate of maximum- capsule- exposure -i temperature.

11.4.5.2 Neutron dosimeter l 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 l' MeV) -for the

. surveillance - ' specimens using both calculated spectrum and assumed fission spectrum assumptions.

(2) Description of the methods

-used .to verify the procedures

-including _ calibrations, cross _

sections, and oMner pertinent . ~

nuclear data. .j

~

11.5  : Application of Test Compliance-Results:-

L11.5.1-. Extrapolation of- the

- neutron -fluxi and . fluence results to the surface and 1/4T -

-locations of the reactor vessel e

A-17 m

L ~ , . ,

Summary of Requirements San Onofre Unit 2 Program per ASTM E185-82 at the peak fluence location.

11.5.2 Comparison of fluence-determined from dosimetry analysis with original predicted values.

11.5.3 Extrapolation of fracture toughness properties to the surface and 1/4T locations of the reactor vessel at the peak fluence-location.

11.6 Deviations - Deviations or Compliance anomalies in procedure from this practice shall be identified and described fully in the report.

END A-18

e APPENDIX B SONGS, UNIT 2: BASES FOR PLATE .

..g

. CHEMISTRY MEASUREMENTS-(Proprietary) l :-

l t

r

.b: - ' - ~ '

i

(

1 APPENDIX C SONGS- UNIT 2: BASES FOR. WELD t C11EMISTRY MEASUREMENTS (Proprietary)

.-_; . _ _ . . . . _ _ _ _ _ ._:.__________=________________

i i

t i

l i

1 i

i APPENDIX D ,

SONGS, UNIT 2: -WMCs FOR BELTLINE MATERIALS (Proprietary) t

"*wwr -w'. &

APPENDIX E SONGS, UNIT 2: MCRs FOR BELTLINE MATERIALS (Proprietary)

t l

I h

i a

i i

APPENDIX F f

SONGS, UNIT 2: UNIRRADIATED Cvs DATA FOR PLATES AND WELDS l

I 6

t

1 1

?

Table F 1 Charpy V. Notch Test Results  !

For Unit 2 Plate C64041 (11), MCR Data l

I SPECIMEN TEMP ENEh0f 1ATERAL PRACT 3D TEST 1NPACT RIP APPEAR tri (ft.1b) (atti (t) 1 40.00 10.00 S.00 0.00 2 40.00 9.00 4.00 0.00 3 40.00 7.00 3.00 0.00 4 10.00 23.00 19.00 10.00

$ 10.00 16.00 14.00 $.00 6 10.00 20.00 15.00 10.00 7 40.00 30.00 21.00 15.00 l e 40.00 35 00 25.00 15.00 9 40.00 43.00 30.00 20.00 l to 10.00 63 00 35.00 40.00 11 10.00 40.00 46.0c 35.00 12 70.00 44.00 31.00 20.00 13 80.00 17.00 $5.00 $0.00 14 90.00 84.00 44.00 40.00 15 80.00 57.00 42.00 35.00 ,

16 100.00 81.00 50.00 50.00 ,

17 100.00 12.00 55.00 50.00 le 100.00 83.00 42.00 $0.00

.. 19 160 00 119.00- 14.00 95.00 20 140.00 113.00 14.00 95.00 21 160.00 117.00 10.00 90.00' 22 212.00 121.00 15.00 100.00 23 212.00 120.00 15.00 100.00 ,

100.00 .t 24 212.00 124.00- 19.00

-F1 v ==~, - -- , e w .. = v. -.vrgh #~,,, ,.s .r w

l I

Table F 2 Cliarpy V Notcli Test itesults  ;

For Unit 2 Plate C6404 2 (IL), MCR Data j l

i SPECIMEN TEMP ENERCT LATERA!. FRACT l ID TEST IMPACT ERP APPEAR l (F) (ft.lb) (mil) (%)

1 -40.00 6.00 3.00 0.00 2 40.00 7.00 -3.00 0.00i  !

3 -40.00 11.00 4.00 0.00 4 10.00 10.00 13.00 10.00 S 10.00 16.00 11.00 S.00 6 10.00 13 00 0.00 5.00 7 40.00 37.00 25.00 15.00 8 40.00 23.00 17.00 10.00 9 40.00 35.00 24.00 15.00 10 70.00 $2.00 30.00 2$ 00 11 70.00 47.00 34.00 25.00 12 70.00 St.00 40,00 2$.00 13 00.00 65.00 47,00 40.00 14 00,00 69.00 40.00 40.00 15 80.00 $3.00 30.00 30.00 18 100.00 75.00 $$.00 -'50.00 17 100.00 68.00 52.00 50.00 le 100.00 73.00 $3.00 50.00-19 160.00 101.00 11.00 99.00  ;

20 160.00 99.00 46.00 95.00 21 160.00 94.00 67.00 95.00 22 212.00 105.00 74.00 '100.00 23 212.00 123.00 40.00 100.00 24 212.00 117.00 14.00 100.00 F-2

l Table F.3 Charpy V. Notch Test Results For Unit 2 Plate CM04 3 (IL), MCR Data SPECIKEN TEMP fMERCT LATERAL TRACT 10 TtsT IMPACT Ekt APPEAR *

(rl (ft.1bl tail) (1) 1 40.00 0.00 5.00 0.00 2 40.00 10.00 6.00 0.00 3 40.00 9.00 0.00 0.00 4 10.00 14.00 f.00 5.00 5 10.00 31.00 15.00 10.00 6 10.00 15.00 13.00 5.00 7 40.00 19.00 34.00 30.00

• 0 40.00 33.00 22.00 20.00 21 160.00 93.00 61.00 95.00 to 70.00 45.00 35.00 25.00 11 10.00 54.00 42.00 30.00 12 10.00 45.00 35.00 25.00 13 80.00 69.00 49.00 $0.00 14 00.00 60.00 44.00 $0.00 1$ 80.00 $2.00 34.00 50.00 16 100.00 73.00 $5.00 $0.00 17 100.00 74.00 $4.00 50.00 18 100.00 71.00 50.00 $0.00 19 160.00 97.00 42.00 99.00 20 160.00 94.00 64.00 95.00 9 40.00 30.00 18.00 35.00 22 212.00 10$ 00 69.00 100.00 23 212.00 100.00 66.00 100.00 24 212.00 103.00 64.00 100.00 F-3

Table F-4 Cliarpy V-Notch Test Results For Unit 2 Plate C6404-4 (11), MCR Data l

SPECIMEN TYMP ENER07 LATTRAL FRACT 10 l

TEST IMPACT EXP A.PPEAR (r) (ft.lb) (mil) (y 1 40.00 1.00 6.00 0.00 l

2 .40.00 9.00 7.00 0.00 I l

3 40.00 10.00 e.00 0.00 l

4 10.00 26 00 20.00 15.00

$ 10.00 22.00 17.00 10.00 .

6 10.00 23.00 20.00 10.00 7 40.00 35.00 25.00 15.00 0 40.00 34.00 . 25.00 15.00 9 40.00 44.00 33.00 20.00 10 70.00 47.00 36.00 30.00 11 70.00 $2.00 40.00 35.00 12 70.00 $4.00 41.00 40.00 13 80.00 62.00 48.00 40.00 14 00 00 66.00 $0.00 40.C0 15 80.00 68.00 53.00 40.00 le 110.00 40.00 $1 00 50.00 11 110.00 70.00 $4.00 50.00 le 110.00 85.00 60.00 40.00 19 160.00 100.00 78.00 100.00 20 160.00 107.00- 75.00 100.00 21 160.00- 96.00 -71.00 100.00 F-4

.a

l I

l Table F 5 Charpy V-Notch Test Results For Unit 2 Plate C6404 5 (IL), MCR Data l

8FECINEN TEMP ENt#CT LATERA!. FRACT 10 TEST IMPACT EIP APP EAA (F) (italbl (mill (t) 1 .40.00 10.00 S.00 0.00 ,

2 .40.00 9.00 S.00 0.00 3 .40.00 0 00 4.00 0.00 4 30.00 18.00 10.00 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 13.00 4 40.00 26.00 22.00 13.00 9 40.00- 23.00 19.00 15.00 to 50.00 41.00 36.00 30.00 11 50.00 34.00 42.00 35.00 12 $0.00 41.00 50.00 15.00 13 10.00 66.00 40.00 40.00 14 10.00 72.00 $3.00 45.00 15 70.00 35.00 44.00 35.00 16 110.00- 01.00 60.00 50.00 -

17 110.00 84.00 39.00 $0.00 le 110.00 07 00 4 41.00 $0.00 19 160.00 103.00 65.00 90.00 20 160.00 105.00 10.00 90.00 21 160.00 115.00 72.00 90.00 22 212.00 122.00 31.00 -100.00 23 212.00 116.00 74.00 100.00 24 212.00 116.00 14.00 100.00-F-5

l 1

l Table F.6 Charpy V-Notch Test Results For Unit 2 Plate C6404 6 (IL), MCR Data 4

SPECIMEN TEMP ENERG7 LATERA1. FRACT 20 TEST IMPACT EXP APPEAR (F) (ft-lb) (mil) (t) ,

1 1 -40.00 4.00 4.00 0.00 2 -40.00 9.00 6.00 0.00 3 -40'.00 6.00 5.00 0.00 l

4 10.00 14.00 13.00 5.00 ,

5 10.00 16.00 14.00 5.00 l 4 10.00 13.00 12.00 5.00 7 40.00 28.00 23.00 15.00 8 40.00 27.00 22.00 15.00 9 40.00 27.00 24.00 15.00 10 50.00 61.00 46.00 30.00 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.C0 15 110.00 94.00 59.00 70.00 16 150.00 116.00 70.00 90.00 17 160.00 115.00 75.00 90.00 18 -160.00 118.00 78.00 . 90.00 l

212.00 120.00 80.00 -100.00 19 20 212.00 124.00 76.00 100.00 21 212.00 121.00- 77.00 100.00-F-6

- _ - . _ , _ m. . , . . ,.

Table F.7 Charpy V-Notch Test Results .

For Unit 2 Weld Scam 9-203 (llcat #90130), FSAR Data l l

SPECIMEN TEMP ENERGY .IATERAL FRAC 7 ID TEST IMPACT EIP APPEAR (F) (ft-lb) (mil) (t) 1 40.00 16.00 9.00 0.00 2 60.00 15.00 7.00 0.00 3 40.00 19.00 11.00 0.00 4 40.00 20.00 11.00 5.00

$ 40.00 20.00 16.00 10.00 '

6 40.00 32.00- 22.00 15.00 7 20.00 05.00 S3.00 $0.00 0 20.00 -80.00 $6.00 $0.00 9 20.00 76.00 47.00 40.00 10 0.00 77.00 .47.00 40.00 ,

11 0.00 75.00 45.00 40.00 12 0.00 99.00 St.00 60.00 13 20.00 117.00 74.00 70.00 14 20.00 105.00 45.00 60.00 15 20.00 114.00 74.00 10.00 16 60.00 132.00 77.00 00.00 17 60.00 149.00 04.00 100.00-10 60.00 123.00 76.00 30.00 ,

4 19 100.00 142.00 02.00 100.00 20 -100.00 140.00 04.00 100.00 21 100.00 140.00 02.00, 100.00 F-7

,-. = m..__mm._ _ _ _ _ _ _ _ - _ _ _ _ _ - - - - _ . _ _ _ _ . . . . . _ _

1 Table F 8 Charpy V Notch Test Results 1 For Unit 2 Plate C6404-2 (LT), CE Baseline Data I

l l

i i

SPECIMF.N TFMP ENERCY 1.ATERAL FRACT )

10 TFST IMPACT ERP APPEAR (F) (ft-lb) (sti)' (t) 154 80.00 4.50 2.00 0.00 136 00.00 0.50 10.00 0.00 122 40.00 S.00 6.00 0.00 132 40.00 6.50 6.00' O.00 143 0.00 11.00 13.00 15.00 147 0.00 16.50 18.00 15.00 114 40.00 41.00 30.00 25.00 ,

11A 40.00 56.S0 40.00 25.00 12K 00.00 93.50 72.00 85.00 14A 90.00 124.50 83.00 75.00 1$6 120.00 118.00 10.00 30.00 11E 120.00 141.50 96.00 90.00 137 160.00 146.50 90.00- 100 00 11T 160.00 157.50 95.00 90.00 1$7 210.00 148.00 96.00 100.00-14L 210.00 1SS.00 94.00 100.00-F-8

.2 . _ .2 . . - - . .

Table F-9 Charpy V-Notch Test Results For Unit 2 Plate C6404-2 (TL), CB Haseline Data SPECIMEN TEMP EMPRGY 1.hTERA1, FRACT ID TEST I MPAC"T EXP AFFEAR (r) (ft-lbl (m11) (1) 264 -80.00 4.50 2.00 0.00 25A -40.00 0.00 0.00 0.00 22D -40.00 0.00 9.00 0.00 21T 0.00 12.00 15.00 10.00 liv 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 B0.00 68.50 58.00 30.00 24E 80.00 78.50 42.00 40.00 21E 120.00 07.00 42.00 75.00 24A 120.00 107.00 72.00 80.00 245 160.00 111.50 70.00 05.00 247 160.00 127.50 84.00 90.00 216 190.00 116.00 90.00. 100.00 24U 210 00 126.50 87.00 100.00 231 210.00 137.50 91.00 100.00 -

i l

a l

F-9 l --

i Ii l-

l

Tal;le F 10 Ciiarpy V Notch Test itesults l

For Unit 2 Stineillance Weld, CE 11ascline Data .

1 l

l SPEC 1 HEN TEMP ENERCT LATERAL FRACT ID TEST IMPACT EIP APPEAR I (P) (ft.lb) (mill (t) 34A 150.00 3.50 1.00 0.00 31M 120.00 7.00 15.00 333 120.00 14.00 12.00 15.00

. 346 00.00 16.00 1$.00 25.00 37A -80.00 29.50 25.00 10.00 l

31K 40.00 43.30 37.00 35.00 3ST 0.60 63.50 $3.00 65.00 347 0.00 90.00 69.00 ?S.00 40.00 132.00 90.00 90.00 338 324 40.00 146.00 97.00 100.00 3SL 80.00 135.50 95.00 100.0C 326 80.00 140.00 95.00 100.00 331 120.00 145.50 95.00 100.00 34J 120.00 153.00 90.00 100.00 3SJ 160.00 151.00 96.00 100.00 l-L 335 160.00 152.00 100.00 100.00

\.

I 1

l l

( ,-

i. F-10 1

i.

l.'

L

-y4%g ,m

l Table F-11 Charpy V Notch Test Results For Unit 2 Plate C6404 2 (llr), MCR Dota i

l Test impact Lateral Fracture Temperature Energy Expansion Appearance

('F) (It lbs) (mils) (% Shear)

-40 9 11 0 40 12 18 0 40 0 10 0 10 25 19 10 10 44 30 25 10 20 21 15 ,

40 42 31 25 40 00 44 40 40 52 40 30 110 126 85 00 110 111 78 70 110 112 74 70 100 145 85 95 160 -136 84 90 ,

160 155 90 100-l.

l 5

F-11 k.

i f

i i

i APPENDtX G SONGS, UNIT 2: HAZ TEST RESULTS i

u 1

Am. w .-~,.,,- ...,ea ,s,--. .e n s.,, .- , ,

CII Ilaseline Testsu l i

specfHen TEMP rpract 1.AfrRAL rRACT ID TEST 1MPAC7 Str APPEAR IF) tit.lb) (ell) (t) 4SJ +150.00 5.00 3.00 0.00 43C 120.00 9.50 6.00 0.00 41H -80.00 23.$0 19.00 25.00 415 40.00 35.00 20.00 30.00 464 40.00 30.00 24.00 30.00 46R 40.00 40.00 34.00 30.00 478 0.00 83 00 $4.00 50.00 417 0.00 101.00 10.00 70.00 dec 40.00 104.50 11.00 10.00 432 40.00 115.$0 08.00 100.00 461 00.00 135.50 96.00 90.00 428 80.00 153.00 92.00 100.00 43K 120.00 100.00 79.00 90.00 421 120.00 144.50 08.00 100.00 451 160.00 139.00 05 00 100.00 442 160.00 151.50 46.00 100.00

_ G.1

Hattelle Ca[ mule 971'l SPECIHtH TEMP FNERCT LATERAL FRACT CMARPT 1RRAD ID Tr8T IMPACT RIP Ar re AR FLUrNes 7tHr.

(P) (ft.lb) (stil (t) In/ent) tr) 476 .10.00 12.00 0.00 17.00 $.07t618 500.00 elA 78.00 14.10 10.20 13.00 5.072610 $80.00 4tc 40.00 20.00 34.00 27.00 5.07261e $e0.00 413 40.00 28.30 28.00 30.00 8.07t610 500.00 430 0.00 38.30 20.40 48.00 S.07 tete $e0.00 42J 0.00 77.50 94.60 14.00 S.078+1e 500.00 42T 72.00 103.00 et.20 80.00 S.07t+1e 500.00 43e 12.00 114 20 e4.40 91.00 S.072618 500.00 444 160.00 130.00 07.00 100.00 S.012618 500.00 412 160.00 132.40 83.80 100.00 5.07t*18 500.00 44F 260.00 133.10 02.20 100.00 5.01248e $80.00 424 240.00 143.30 08.00 100.00 S.078618 500.00 G-2

l 4

i I

J i

I

+

5 APPENDIX H

.i SONGS, UNIT 2: IRRADIATED Cvu DATA FROM CAPSULE 97 t

P t

- n- + + . . - , - , , ,

1 Tuble 111 Charpy V-Notch Test flesults For Unit 2 Plate C6404 2 (UI')

Irradiated (f = 5.07 x 10") l l

l l

SPEC! HEN TEMP ENERGY 1ATERAL TRACT 2D TEST !HPACT EXP APPEAR i (r) (ft-lb) (all) (t) 141 0.00 6.00 6.80 4.00 '

111 0.00 8.10 6.40 5.00 15H 40.00 12.50 7.80 11.00 14T 72.00 23.50 23.60 9.00-13H 72.00- 27.40 26.60 13.00 123 '100.00 59.50 53.40 18.00 13E 100.00 74.20 58.80 20.00 11H 160.00 113.40 83.00 77.00 15E 160.00 138.50 99.40 100.00 11U 200.00 127.30 93.40 100.00 124 200.00 136.20 10$.80 100.00 137 260.00 137.30 95.40 100.00 4

11 1-t r r--, - * ,

Table 112 Charpy V-Notch Test flesults For Unit 2 Plate C6404 2 (FL)

Irrad!ated (f = 5.07 x 10")

SPECIHEN TEHF ENERCf 1.ATERAL TRACT ID , TEST IMPACT EIP APPEAR (r) (tt-ib) (mil) (t) 214 0.00 4.00 10.00 4.00 23J 0.00 11.00 11.00 6.00 223 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 49.00 218 160.00 82.00 48.40 85.00 221 200.00 93.00 71.00 100.00 25L 200.00 98.00 68.60 100.00 256 ,

260.00 101.90 83.40 100.00 211 260.00 103.00 83.80 100.00 11-2

Table " 3 Charpy % Notch Test Itcsults 1 - Unit 2 Surveillance Weld inadiated (f = 5,07 x 10")

SPECIMEN TEMP ENERGY LATERAL FftACT ID TEST IMPACT EIP APPEAR (r) (ft-ib) (rail) (g) 37H ~79.00 15.00 14.40 38.00 37L -79.00 18.40 20.0n 13.00 3A3 -40.00 2$.00 23.60 36.00 36M -40.00 45.40 36.60 40.00 36P 0.00 78.00 85.20 48.00 36K 0.00 82.40 64.60 70.00 31E 72.00 126.90 95.00 92.00 33P 72.00 138.20 102.20 100.00 342 160.00 134.00 99.80 100.00 3GE 160.00 142.50 97.80 100.00 32P 260.00 147.90 97.60 100.00 341 260.00 149.00 100.40 100.00 11-3 4

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