ML20101N124

Nonproprietary SCE Songs,Unit 2 Response to GL 92-01 Final Rept

ML20101N124
Person / Time
Site:	San Onofre
Issue date:	06/24/1992
From:	ATI CONSULTING, SARTREX CORP.
To:
Shared Package
ML13302B853	List: ML20101N124 ML20101N127
References
GL-92-01, GL-92-1, NUDOCS 9207090168
Download: ML20101N124 (91)

Text

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Southern California Edison Saa Onofre Nuclear Generating Station, Unit 2 Response to Generic Letter 92-01 (Non Proprietary Version) 5 A

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ATI Consulting Sartrex Corpora' tion l

9207090168 920706 ADOCK0500g1 DR

San Onofre Nuclear Generating Station, Unit 2 Response to Generic Iztter 92-01 Final Report June 24,1992 -

(Non-Proprietary Version)-

Prepared by:

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

Southern California Edison '

- Irvine, CA

= _.. _ _ _ _ _ _ _ - _ - _

____ _ __._-.~- _ _ _ _... _ _.. _ _.

i CONTENTS l

Section Pase a

1 INTRODUCrlON 11 2

REACTOR PRESSURE VESSEL SURVEILLANCE 21 PROGRAM COMPLIANCE WITli APPENDIX 11 3

FRACTURE MECHANICS 31 j

3.1 COMPLIANCE WITH APPENDIX G 3-1

[

3.2 BELTLINE MATERIALS IN SONGS, UNIT 2 5-1 3.2.1 location 3-1 3.2.2 Heat Treatment 31 3.2.3 Key Residual and Alloying Element Contents 32 l

3.3 FRACTURE TOUGHNESS RELATED DATA 3-2 l

. 3.3.1 Beltline Plate Material 3 3.3.2 Beltline Welds-3-4 4-ISSUES RELATED.'IO GENERIC LETTER 88-11 41 l

f 4.1 VESSEL TEMPERATURE DURING OPERATION-4-1 4

4.2 APPLICABILITY. OF SURVEILLANCE DATA 4-1 4.3 SHIFTS AT THE CIIARPY V-NOTCH 30 FT-LB ENERGY LEVEL. - -

42-4.4 UPPER SHELF ENERGY DROP '

431 i

' 5 REFERENCES 5 l'-

APPENDIX A-SONGS, _ UNIT 2: EVALUATION OF COMPLIANCE A-1 :

.Wrril ASTM E185-73 AND E185-82 y

l APP NDIX B l SONGS, UNIT 2: BASES' FOR PLATE CHEMISTRYJ B-1

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L MEASUREMENTS -

' APPENDIX C

SONGS, UNIT-2

1MCRs FOR BELTLINE

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MATERIALS (Proprietary) y e

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CONTENTS (cont'd)

Section Eggg APPENDIX D SONGS, UNIT 2: UNIRRADIATED Cm DATA D1 FOR PLATES AND WELDS APPENDIX E SONGS, UNIT 2: HAZ TEST RESULTS E.1 APPENDIX F SONGS, UNIT 2: IRRADIATED Cm DATA FROM F1 CAPSULE 97 i

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ILLUSTRATIONS Figyte Pace 31 SONGS, Unit 2: Location and Identification of 3-6 Beltline Plates and Welds 32 SONGS, Unit 2: Data and Least Squares Fit Curve 3-7 for Cw versus Temperature, Plate C64041, TL Orientation, MCR Data 3-3 SONGS, Unit 2: Data and Least Squares Fit Curve for 38 Cm versus Temperature, Plate C6404 2, TL Orientation, MCR Data 3-4 SONGS, Unit 2: Data and 1.xast Squaru Fit Curve for 3-9 Cw versus Temperature, Plate C6404 3, TL Orientation, MCR Data 35 SONGS, Unit 2: Data and Least Squares Fit Curve for 3-10 Cw versus Temperature, Plate C6404-4, TL Orientation, MCR Data 36 SONGS, Unit 2: Data and Least Squares Fit Curve for 3 11 C versus Temperature, Plate C6404 5, TL Orientation, MCR Data 3-7 SONGS, Unit 2: Data and Least Squares Fit Curve for 3 12 Cm versus Temperature, Plate C6404-6, TL Orientation, MCR Data 3-8 SONGS, Unit 2: Data and Least Squares Fit Curve for 3 13 Cw versus Temperature, Plate C6404-2, Orientation, Surveillance Baseline Data 3-9 SONGS, Unit 2: Data and Least Squares Fit Curve for 3-14 Cm versus Temperature, Plate C6404 2, TL Orientation, Combined MCR and Surveillance Baschne Data

ILLUSTPATIONS (cont'd)

Ficure Pace 3 10 SrNGS, Unit 2: Data and Least Squares Fit Curve for 3 15 C versus Temperatur., riate C6404 2, LT Orientation, m

?4urveillance Baseline Data 3 11 SONGS, Unit 2: Comparison of least Squares Fit Cm 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 Sqaares Fit Curve for 3 17 Temperature, Weld 9 203, FSAR Data 3-13 SONGS, Unit 2: Data and least Squares Fit Curve for 3 18 C versus Temperaturc, Surveillance Baseline Data m

41 SONGS, Unit 2: Comparison of Irradiated Cw Data from 4-4 Capsule 97 with Unitradiated Baseline Data, Plate C6404-2, LT Orientation 42 SONGS, Unit 2: Comparison of Irradiated Cw Data from 45 Capsule 97 with unitradiated Baseline Data, Plate C6404-2 TL Orientation 4-3 SONGS, Unit 2: Comparison of Irradiated Cm Data from 4-6 Capsule 97 with Unirradiated Baseline Data, Surveillance Weld

I TAHLES Table Page t1 SONGS, Unit 2: 10CFR50 Appendix 0 - Arcas of Non-3 19 Compliance

/

3.2 SONGS, Unit 2: Plate and Corresponding licat Numbers 3 21 for the Beltline Plates 3.3 SONGS, Unit 2: Weld W!re aN Flux Combinations 3-22 for Beltline Smcillance Welds 3.4 SONGS, Unit 2: Key Residual and Alloying Element Contents for 3 23 Beltline Plates 3.5 SONGS, Unit 2: Key Residual and Alloying Element Contents for 3 24 Beltline Welds 3.6 SONGS, Unit 2: Beltline Plate Material Unirradiated 3 25 Fracture Toughness Tests Results Summary 3.7 SONGS, Unit 2: Charpy Absorbed Energy Values at 10F 3 26 for Weld Scams 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 Results 4-7 4.2 SONGS, Unit 2: ART Estimates for Beltline Materials 4-8 on 12/16/91 and at 32 EFPY 4.3 SONGS, Unit 2: Surveillance Capsule Upper Shelf Results 4-9 4.4 SONGS, Unit 2: Upper Shelf Estimates for Beltline Materials 4-10 on 12/16/91 and at 32 EFPY

b Section 1 INTRODUCTION

'Ihc Nuclear Regulatory Commission (NRC) in Generic Letter 92 01 (GL92 01) requested all holders c f operating licenses or construction permits for nuclear power plants to submit information needed to assess compliance with requirements and commitments regarding reactor vessel integrity. This report has been prepared in response to GL92-01 for San Onofre Nuclear Generating Statior' (SONGS), Unit 2.

Section 2 of this report addresses compliance with 10 CFR Part 50 (10CFR50), Appendix 11 for the surveillance program at SONGS, Unit 2.

Compliance with 10CFR50, Appendix 0 is described in Section 3 along with a description of the location, heat treatment, residual and alloying element contents, and upper shelf and transition temperature fracture toughness for the beltline materials in the SONGS, Unit 2 reactor vessel. Section 4.0 addresses embrittlement effects, including irradiation temperature and adjusted reference temperature for evaluation of the beltline materials relative to GL88-11 and 10CFR50.61.

Additional information is needed to complete the response to GL92-01 for SONGS, Unit 2. This information includes: (1) resolving inconsistencies noted in Cu and Ni contents for Lettline wcld 9 203 and the surveillance weld, which have been reported to have been fabricated using the same consumables, (2) locating material certification reports to confirm beltline wcld properties, and (3) verifying the fluence at wcld 8 203.

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Section 2 REACTOR PRESSURE VESSEL SURVEILLANCE PROGRAM COMPUANCE WITil APPENDIX 11

%c ASME Code of record for the San Onofre Nuclear Generating Station (SONGS), Unit 2 reactor pressure vessel is the 1971 Edition through the Summer 1971 Addenda. Consequently, the applicable version of ASTM E185 is the 1970 version (ASTM E185-70). Ilowever, 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 11. 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, se 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 11 requirements were met (with one exception) through compliance with ASTM E185-73. The one exception to meeting Appendix 11 requirements had to do with the method of attachment of the holders for the six surveillance capsules in cach SONGS unit. Combustion Engineering (CE) was the vessel manufacturer and the nuclear steam supply system (NSSS) vendor; CE attached the capsule holders directly to the cladding on the inside of the vessel in the beltline reg!on (as they did for all CE NSSS-designed vessels), and this approach violated the requirements in the early 1970's version of 10CFR50, Appendix 11. %c NRC reviewed a CE Topical Report (CENPD-155 P, C-E Procedure for the Deslen. Fabrication. Installation, and insocction of Surveillance lloider Assemblies) and found the practice and procedures acceptable.

%c current version of Appendix 11 does not treat this method of attachment of the capsule holdets as a noncompliance issue. The wording in the current Appendix 11,Section I.A.2 is:

"If the capsule holders are attached to the vessel wall or to the vessel cladding, construction and in-service inspection of the attachments and the attachment welds must be donc according to requirements for permanent strucmral attachments to reactor vessels given in Sections til and XI of the ASME Code. The design and location of the capsule holders shall permit insertion of replacement capsules."

His wording was derived from the CE Topical Report, and the SONGS units have met the additional ASME Code, Sections til and XI design and inspection requirements. Therefore, there are no deviations or exceptions needed from the current Appendix II of 10CFR50.

The details of the SONGS, Unit 2 surveillance program have been described in the FSAR and-subsequent surveillance program testing reports, baseline I'l and irradiated.ial %c first capsule results have been evaluated for a low fluence following ASTM E185-82 testing and reporting 2-1

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requirements. Later sections of this report will discu i these results as compared to regulatory prediction methods.

The update of ASTM E185 for 1992 (E 185 92) is about to be approved and issued. One significant change fa m E185-82 is tl e terr. oval of the requirements for testing heat-affected-zone (HAZ) material. This change has reusted from the difficulty in interpreting HAZ results due to the degree of scatter and the ability t i define the usefulness of blunt notch Cm uAZ 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 beltiine material has been reported previously,I"1 and is provided for reference in_ a subsequent section of this report.

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Section 3 FRACTURE MECHANICS This section evaluates compliance with 10CFR50, Appendix G and identifies the location, heat treatment, key residual and alloying element contents and unirradiated fracture toughness properties for plates and welds in the SONGS, Unit 2 reactor pressure vessel beltline region.

Generally, the information presented in this section has been obtained from the materials certification reports (MCRs) and the FSAR for SONGS, Unit 2, and from additional information supplied by Combustion Engineering (CE) to prepare this response. In some instances, additional information was obtained from the unirradiated baseline surveillance material report,N and the irradiated material in the 97* location surveillance capsule (Capsule 97), which was removed from Unit 2 at the end of the third fuel cycle.A 3.1 COMPLIANCE WITH APPENDIX G Generally, the materials in the beltline region of SONGS, Unit 2 comply with the requirements of Appendix G,10CFR50. Areas of non compliance with Appendix G,10CFR50, as specified in the FSAR for SONGS, Units 2 and 3 and updated during preparation of this report, are listed in Table 3.1.

3.2 BELTLINE MATERIALS IN SONGS, UNIT 2 3.2.1 Imation Figure 3-1 is a representation of the SONGS, Unit 2 reactor pressure vessel, and ideutifies the plates and welds and their location in the beltline region.

The heat numbers for the t:.tline plates shown in Figure 3-1 are presented in Table 3.2. The-weid wire and flux combination for the beltline welds shown in Figure 3-1 and the surveillance.

welds are presented in Table 3.3.

3.2.2 Heat Treatment The heat treatment for the plate materials copsisted of austenitization at 1575 50 F for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; water quenched and tempered at 1225 25'F for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. For ASME Code qualification, the plates were stress relieved at 1150i 25 F for 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> and then were furnace cooled to 600 F at a rate of 100 F/hr. 'Ile 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 time were selected such that the total did not exceed 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> for any particular portion of the vessel.

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Longitudinal weld seams would see stress relief times near the 40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> maximum, while the closing girth weld in the beltline region would see approximately half this amount of time maximum. All of the testing of plate materials was performed on pieces with essentially the identical heat treatment as the actual reactor vessel. The surveillance weldment received e final 42-hour and 15-minute -tress relief at 1100 F to 1150 F.

3.2.3 Kev Resideal and Allovina 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 and Ni contents were obtained by averaging two measurements made by CE. The first measurement was made when CE received the plate from Lukens and the second measurement was made when the surveillance program was defined. The bases for the Cu and Ni contents reported by CE and listed in Table 3.4 are presented in Appendix B. The plate P and S contents were obtained from the MCRs, which are attached as Appendix C.

A second set of data is included for Plate C6404-2. This set was obtained from broken rarveillance specimens when the first irradiated surveillance capsule from Unit 2 was tested.t21 -

Tabic 3.5 contains the Cu, Ni, P and S contents reported in the FSAR for the beltline welds.

Because Ni was not measured for weld seam 8-203, a value of 1.0 wt % has been assumed (see Regulatory Guide 1.99 Rev. 2).

Two chemistry measurements have been made for the surveillance weld and also are reported in Yable 3.5. The first chemistry measurement was made N

as part of the original baseline, while the second was obtained from a broken Charpy specimen from Capsule 97(2),

Although the surveillance weld and beltline weld 9-203 are reported by CE to have been fabricated using the same weld wire and flux combination (see Table 3.3), the surveillance weld and beltline weld 9-203 are listed and evaluated separately in this report because of the relatively large difference in reported Cu and Ni contents. CE is continuing their investigation to resolve -

this inconsistency in reported chemistry.

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 Charpy V-notch absorbed energy (Cw) tests, and-summarizes the upper shelf energies (USE) and the results from the drop weight nil ductility temperature (NDT) tests for the unirradiated beltline plate and weld materials in SONGS, Ucit

2. The unirradiated reference temperature (RTu) values were determined from the Cm and NDT test results in accordance with the most recent version of ASME Section III, NB-2331. The upper shelf energies were determined using the definition specified in ASTM E185-92 (to be 3-2

r-issued). The data included in the USE determination wem the C, values for those tests (at least

3) where the percent shear on the fracture surfaces was equal to and greater than 95E The fracture toughness data for plate were obtained from the MCRs (see Appendix C) and baseline surveillance program. The fracture toughness data for the belthne welds were obtained from the FSAR, while the data for the surveillance weld were obtained from the baseline surveillance program. For convenience, the Cw, lateral expansion, and fracture appe.rance (%

shear) data for the unirradiated beltline and surveillance plate and weld materials are listed in tabular form in Appendix D.

As discussed earlier in Section 2, the results for heat affected zone (HAZ) material are not evaluated in this report because upcoming ASTM standard E185-92 will not require HAZ material to be part of the surveillance program. Tue raw Cm data for the past IIAZ testing are attached in Appendix E.

3.3.1 Beltline Plate Material Because fracture toughness requirements for reactor pressure vessels are based on requirements to test specimens oriented transverse to the rolling direction the data presented here are for the transverse (TL) orientation with one exception. The exception is for the beltline plate C6404-2, which was included in the surveillame program. Because the surveillance program for SONGS, Unit 2 also contains longitudinally (LT) oriented specimens the unirradiated Cw data are presented for completeness for the LT orientation.

The transverse Cw data as a function of test temperature for beltline plate numbers C6404-1, -2,

-3, -4, -5, and -6 are presented in Figures 3-2 through 3-7 respectively. For convenience, an average curve through the data also is shown in each figure.

The average curves were determined using a least squares fit a the data and a hyperbe"c 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 E185-92 for specimens having fracture surfaces.with 95% and greater shear. For convenience, the figures also indicate the values of NDT, USE, the temperatiire at which a minimum Cm qual to 50 ft-lb (T @ 50 ft-lb) is achieved consistent with the applicable e

method of ASME, Section IU, NB 2331, and RTm.

As part of the surveillance program additional Charpy absorbed energy versus temperature data were generated for Plate C6404-2;14 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 RTm for the surveillance plate weld as shown by the intersection of the dashed line and the 50 ft lb C, 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.

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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 RT and the USE for the transverse orientation sm in Plate C6404 2. The average curve through the combined data set in Figure 3 9 also was used as the unitradiated baseline to evaluate the results for the irradiated surveillance tests (see Section 4).

Table 3.6 is a summary of the unirradiated NDT, RTsm and USE values for the transverse orientation for each of the beltline plates 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 RT m from the NDT and Cm data also are identified in Table s

3.6. The method of either NB-2331 (a)(2) or NB-2331 (a)(3) was used to determine RTsm for the plates.

Figure 310 shows the data and least squares fit line for the longitudinal (LT) orientation for surveillance plate C6404-2.II Figure 3-11 shows a' comparison of the best fit 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 ir Figure 3-11 indicates that the data for the

-LT orientation in plate C6404-2 from the MCRs produce essentially the same Cm versus tempera:ure relationship as was obtained for the LT orientation surveillance plate material.

3.3.2 Beltline Welds A full Cm versus temperature curve was obtained for the material in weld seam 9 203, and %

data points and least squares hyperbolic tangent fit through the data are presented in Figure 3-12.

The materials in the remaining beltline weld seams were tested to obtain three Cw data points at 10"F. The results from these tests are presented in Table 3.7. Figure 3-13 presents the Cw data and least squares hyperbolic tangent curve fit for the surveillance weld material. A comparison of the Cw versus temperature curves for beltline. weld 9-302 and the surveillance weld in Figures 3-12 and 3-13, respectively, show that the impact energies as a function of temperature essentially are the sarne for both materials.

Table 3.8 presents a summary of the unitradiated NDT, RTer and USE values for each of the beltline welds in SONGS, Unit 2. For welds 3-203 and 9-203 available Cw data indicate that '

there is a minimum of 50 ft-lb absorbed energy at 60'F above NDT, and consequently RT m 3

equals NDT For weld 2-203 the available Cm data are 70 F above NDT; however, because the data all have absorbed energies greater than 100 ft lb RT m was taken as equal to NDT because 8

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 RTsm was taken as the generic value of -56 F for CE fabricated vessels (see 10CFR50.61).

3-4

The upper shelf energies shown in Table 3.8 for weld 9-203 and the saveillance weld were obtained by averaging the test results where 95% shear or greater was exhibited. he upper shelf energies for welds 2-203,3 203 and 8-203 were obtained from the data in Table 3,7 by averaging the three C, data points obtained at 10"F for each of the listed welds, l

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REACTOR VESS_E_L BELTLINE MATERIALS NOT SHOWN INTERME01 ATE SHELL 0000YOOOFM WELD SEAM NO. 2 203C LOWER SHELL

,N WELO SE AM NO. 3 2038 WELD SE AM NO,3-203C

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LATE NO. C 64041 p INTERMEDIATE SHELL PLATE NO.C 6404-2 INTERMED%TE SHELL LONGITUDIN AL W INTER M EDI AT E-TO-LOW E R SEAM NO. 2-203A SHELL GIRTH SEAM INTERMEDIATE SHELL PLATE NO. C 6404 3 y LOWER SHELL LOWER SHE LL PLATE PLATE NO. C-6404-4 NO. C-6404 p LOWER SHELL LONGITUDIN AL WE LD SEAM NO. 3-203A g

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SONGS, Unit 2: Location and Identification of Beltline Plates and Welds.

3-6

200

=

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San Onofre Unit 2 MCR Data l

Material: Platei No. C64041, A53381 rkntation: N f

150

=-

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T @ 50 ft ibs

• 80 'F 2,

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-200

-100 0

100 200 300 400 500 Temperature in Degrees F Figure 3-2.

SONGS, Unit 2: Data and least Squares Fit Curve for Cm versus Temperature, Plate C6404-1, TL Orientation, MCR Data.

3-7

.200 s

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. San Orectre Unit 2 MCR Dato Mat'erial : Piate No. C6404 2, A533B1 Orientation: Tl- --

U0 -.= 105_Adbs 150 NDT = -20 'F T @ 50 ft-lbs = 80 'F RTridt = 20 'F r

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-200

-100 0

100

-200 300 400

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Temperature in Degrees F-1 Figure 3-3.

SONGS, Unit 2i Data and Least Squares Fit-Curve for<C,versus Temperature, Plate C6404-2, TL Orientation, MCR Data.

3-8

200 San Onofre Unit 2 MC;R Data Material: Plate C6404-3, A533B1

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-200

-100 0

100 200 300 400 500 Temperature _in Degrees F Figure 3-4.

SONGS, Unit 2: Data and Ixast Squares Fit Curve for Cm versus Temperature, Plat:: C6404-3, TL Orientation, MCR Data.

3-9

4 200 San Onofre Unit 2 MCR Data Mat'erlat: Plate C0404-4, A533B1 i

150

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USE = 104 ft-lbs NDT = -10 'F T @ So ft-!bs = 80 'F 2

RTridt = 20 'F i u.

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-200

-100 o

100 200 300 400 500 Temperature in Degrees F Figure 3-5.

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

3-10

200 i

San Onofre Unit 2 MCR' Data Mate' rial: Plate C6404-5, SA533B1 0:!entation: TL i

150

-- tSli = 118'it !ds

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NDT!= 20 'F I

j T@ So ft-lbs = 70SF RTndt = 10 'F o

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-200

-100 o

100 200 300 400 Soo 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

200 San Onofre Unit 2 MCR Data Material: Plate C6404-6, A533B1 Orientation: TL

--.USE1 124 ft-lbs-150 NDT k -10 'F T @ [50 ft-lbs =.50 'F

.o RTndt = -10 'F c

@ 100 ec tu

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8 O

t 50

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Calculated 8

....W.,,...i....

n.

... o.... u.,.. n o

-200

-100 0

100 200 300' 400 500 Temperature in Degrees F Figure 3-7.

SONGS, Unit 2: Dats and Least Squares Fit Curve for Cm versus Temperature, P' ate C6404-6, TL Orientation, MCR Data.

3-12

200

=

f = 0.0 1

1H

=

O

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E E

~

O O

100 r

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C W

O Z

Sm Onofre Unit 2 j

j Surveillance Program fl Material: Plate No. C6404-2, SA53381

-1_i Orientation;.'O..!._

50

=

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USE = 126 ft-Ibs j

NOT = 10 'F l

T @ 50 ft Ibs = 80 'F O

RTndt = 20 'F O

,,,i,,,,,,,,,i,,,.

o,,,.i,,,,i o

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 Cw versus Temperature, Plate C6404-2, TL Orientation, Surveillance Baseline Data.

3-13

l 200 San !Onofre Unit 2 Com'bined MCR! & Surveillance Data

~

Matdrial: Plate !No. C640d-2, SA53381 Oriebtation: Tid USE = 113 ft-16s 150 NDIL=_10 'F i

l

_a T @l 50 ft-Ibs = 80 'F

~

RTndt = 20 'F

<n

~

o 8

o E

~

0 0 o [o- 0

@ 100

+

s 4

8 o

tu 2

O i

~

O o

O Measured 50

=

r Calculated O

o J

0

-200

-100 0

100 200 300 400 500 Temperature in Degrees F Figure 3-9.

SONGS, Unit 2: Data and Least Squares Fit Curve for Cw versus Temperature, Plate C6404-2, TL Orientation,' Combined MCR and Surveillance Baseline Data.

3-14

200 r

f = 0.0 O

O 150

=

+

r l

D 0

2 O

u.

@ joo

=

m 2>

O I

San Onofre Unit 2

/

Surveillance Program

' _ Plate Nb. C6404-2, SA53381

/,

Material:

-/ I --Orient' tiom-LT 4--

50

=-

a

/

USE - a 150 ft-Ibs:

/

NOT:210'F

.T @ 50 ft-Ibs = '/5 SF -

RTndt = 15 SF O

..i....i....i....i....-

o u.... n

-200 100 0-100 -

200

'300 400' 500 Temperature in Degrees F Figure 3-10.

SONGS, Unit 2: Data and. Least Squares Fit Curve for Cw versus Temperature, Plate C6404-2, LT Orientation, Surveillance Baseline Data.

3-15

200 San Onofre Unit 2 Compalison of MCR Data wi :h Surveillance Best Fit Line Materia:: Plate No. C6404-2, A533B1

~

Orienta.lon: LT O

150

~

O en

9 0

i

~

O E 100 E

I uJ Z

>0 O

MCR Data 50 Fit to Surveillance g

Data

/

Y

-200

-100 0

100 200 300 400 500 Temperature in Degrees F Figure 311. SONGS, Unit 2: Comparison of Least Squares Fit Cw versus Temperature Curve for the Surveillance Plate with MCR Data for Plate C6404-2, LT Orientation 3-16

4 200

=

~

San Onofre Unit 2 FSAR! Data I

Material: Weld Weld {9 203 USE 6144 ft Ibs l

O d

i t'

~1 150

- NDT~E'%DF--'f 'F T @ ho ft-Ibs = *20 j

RTndt! = -60 'F 0

T O

X g

@ 100-

+___

+

eC m

8, cf z>

.g q

l 1

50

=

7-O Measured

-~

~~~~

Calculated.

o-o

-200 100 o

'100 200 300-400 500 Temperature in _ Degrees F Figure 3-12; SONGS, Unit -2: [ Data and 1. cast Squares Fit Curve.for Cw 'versus Temperature, Weld 9-203, FSAR Data.

_i 3-17 i

200

=

f = 0.0 4O g

h 4

150

=

0 1

i i

O

,.o u.

~

A j

{100 3-~

I 0

-t

~-

C tu 2

i

>0 I

Sm Onofte Unit 2 Surdila. ice Program Material: Weld i i

^

USE= 146 ft-lbs j

f NDT:[= -50 P g

T @ so ft-Ibs = -10 P RTndt = 50 Y U

M i....i.........i..

d....

o o....i

-200 100 0

100 200 300 400 500 Temperature in Degree F Figure 3-13.

SONGS, Unit 2: Data and Least Squares Fit Cuwe for Cm versus Temperature, Surveillance Weld, Surveillance Baseline Data.

3 18

Table 3.1 SONGS, Unit 2: 10CFR50 Appendix G - Areas of Non-Compliance.

Paragraph Description of Non-Compliance Comment II.B Series 4xx stainless steels are Consistent with ASME Code in effect.

purchased and treated to Code requirements. No RT, or drop weight Tu temperatures arc determined.

4 III.B.S.a Records of fracture toughness Appendix G was not applicable at the testing do not include a time tests were performed. Certificaiton certification that tests were to the applicable ASME Code is performed in accordance with included. The intent of Appendix G is Appendix G.

m et.

III.C.

" Reactor Vessel Beltline", as The baseline tests of the surveillance defined by Paragraph II.H, program include weld and HAZ material includes the wcld heat-from the most limiting plate. Results affected-zones.Section III.C available for SONGS Unit 2 indicate that is not complied with in that the intent of Appendix G has been met.

only base plate and represent-(Note: the IIAZ results are not ative welds in the beltline presented in this report) region were considered for the required testing.

III.C.1 Only single-temperature testing Consistent with ASME Code in effect.

was performed for some weld materials.'

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

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 wclded under the same pr_oduction production plate, although conditions as those used in joining the it is the same P-number.

corresponding shcIl materials were used.

(Section IX, ASME Ccxic) 3-19

= -.

4 n

t.

1 Table 3.1

- (Continued)

- 1 4

Paragraph Description of Non Compliance

- Comment i-IV.A.4 Charpy V notch test were

'Ihe ASME Code in effect required

- not conducted at "the

- test temperature of 60F below the l

preload temperature at at the

' lowest scrivce semperature.' All

- lowest cervice temperature,-

bolting material'was tested at 10F-

~

which ever is lower".

and met the:35 ft-Ib minimum'.

requirement of the applicable'

~

ASME Code. All beltline plate materials and one beltline' weld were tested to meet the current (1989) Code requirements in NB. - _

2331. The remaining beltline welds were tested at 10F and have C w in :

excess of 100 ft-Ib. These results indicate that the intent of Appendi.

- G has been met.

i i

k' 20 9

wh w

-g y se$+o4

• ew ivw-w -- sp

• w ww cit +nig w er t w y4 3 9-wee :g 9' ed C*'F

--W F%

'r W f p

fT

-P=W-4 V t' vm' vi 7r g"vy-T rr r

h ir 7

w r-

-w,e*-g r

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

Lukens Plate Number Heat Number C6404-1 C7596-1 C6404 2 C7595-2

j C6404 3 C7595-1 C6404-4 A6735-1 C6404-5 C7585-1 l

C6404-6 C75%-2 4

I 3-21.

4 4.

Table 3.3 SONGS, Unit 2: Weld Wire and Flux Combinations for Beltline and I --

Surveillance Welds.

e Weld Seam Weld Wire and Flux t

2-203 A, B, and C

' E8018 C-3 Electrodes, Lot No.- EOBC.

3-203 A, B, and C Type Mil B-4 Wire, Heat No. 83637,~

Linde Type 0091 Flux, Lot No.1122 i

l 9-203 Type Mil B-4 Wire, Heat No. 90130, Linde Type 0091 Flux, Lot No. 0842--

8-203 Presently not available -

Suncillance Reported by.CE to be the same' --

consumables as weld 9-203-1 4

1 1

EF M

. 3-22

~

--- N,

..v,--

wa e, a r.,

a y,-

w<'..&r n

~ ee n-

+-,.e m-o A

^

+r

=,v-

-gr w

--, y e

i i

l i

Table 3.4 SONGS, Unit 2: Key Residual an6 Alloying Element Contents for Beltline a

Plates.

4 L

i Plate Number Cu' Ni' '

I*

S*

CP r

i C6404-1 0.10

. 0.56 0.009 0.013-

- 65 C6404-2 0.10 0.59-0.010 0.015 65 i

d d

d d

j; C6404-2 0.10 0.59 0.012 '

N/A 65 l

j-C6404-3 0.10-0.56' O.008

. 0.014

' 65-o404-4 0.10 0.62 0.013 0.013 65-C6404-5 0.11

- 0.64 0.015 0.013'.

75 i-3 C6404-6 0.10 0.58 0.008.

0.012 65 a

Average Values reported by CE in Appendix B.

a.

i b.

Values reported in the MCRs.

ir i.

c.

Chemistry factors from Regulatory Guide 1.99, Revision 2 d.

' Measured when the surveillance tests were perfdrmed.for Capsule 97?3 -

i t

3 -

Nwy y

'e

-y-mu-9rrw-.- rs-ter--v3,..-.--

-w

.rw~,,

ai,-,

c p. +fe..=y.

v.-,

..,-+.m...,',,r,=.-

err-***

-*-+wewwr

-vw,.,-

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

Weld Number Cu Ni P

S CP 2-203A 0.03 0.90 0.009 0.017 41 2-203B 0.03 0.91 0.009 0.016 41 2-203C 0.03 0.95 0.010 0.016 41 3-203A 0.05 0.12 0.011-0.011 40 4

3-203B 0.04 0.06 0.010 0.011 30 3-203C 0.%

0.11 0.010 0.011 42 8-203 0.31 l'

O.012 0.010 260 9-203 0.07 0.29 0.009 0.007-69 d

Surveillance 0.03 0.12 0.003 0.009-30 Surveillance' O.03 0.15

<0.005 N/A 32 a.

Values reported in the FSAR except for the surveillance weld.

b.

Chemistry Factors determined from Regulatory Guide 1.99,' Revison 2 c.

Ni conten'. was not obtained and 1 wt% has been assumed d.

Measured when surveillance program was developedill -

Measured when the surveillance tests were performed for Capsule 97.121 e.

3-24

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

initial Plate NDT RTgn Procedure to USE Number C'F)

(*F)

Determine RTmn (ft lbs)

C64041

-30 20 NB-2331 (a)(3) 119 6

C6404-2*

+10 20 NB-2331 (a)(3) 113 C6404 3

-20 20 NB-2331 (a)(3) 99 i

C6404-4

-10 20 NB-2331 (a)(3) 104 C6404-5

-20 10 NB-2331 (a)(3) 118 i

C6404-6

-10

-10 NB-2331 (a)(2) 124 This plate is included in the surveillance program. RTgg and USE values are based a.

on the combined data sets from the MCRs and unitradiated surveillance baseline (sec Figure 3 9).

b.

Highest of 2 transverse values (i.e., -20"F c'. n miined when plate was purchased, and

+10 F from surveillance baseline).

~

3-25 f

(

p y

7

Table 3.7 SONGS, Unit 2: Charpy Absorbed Energy Values at 10 F for Weld Scams 2-203 A, B, and C; 3-203, A, B, and C; and 8-203.

Charpy Energy Weld Scam (ft-lb) 2-203 A 118,104,158 2-203 B and C 106,108,105 3-203 A, B, and C 153,131,125 8 203 108,112,119 3-26

~...

..=..

Table 3.8 SONGS, Unit 2: Beltline Weld Material Unirradinted Fracture Tonghness Tests Results Summary.

4-Initial NDT RTer Procedure to USB-l Weld Scam

('F)

("F)

Determine RTer (ft-lbs) i I

d 2203 A '

-60"

-60" NB 2331 (a)(2) 126 d

2 203 B and C

-60'

-60" NB-2331 (a)(2) '

106 l

d j

3-203 A, B, C

-50'

-50 NB-2331 (a)(2) 136 5

l d

8-203 N/A

-56 c

- 113 9-203

-60'

-60

- NB-2331 (a)(2) -

144-L Surveillance

-50

-50 NB-2331 (a)(4) -

146 l

NDT values were obtained from the FSAR.

a.

i b.

Estimated as equal to NDT hased'on three Cm data points above 100 ft-lb at NDT +

70"F (see Table 3.7).

c.

Generic value for CE fabricated vessels using Linde 0091,1092, and 124 fluxes (see.

10 CFR50.61).'

d.

Estimated using the average of Cm values obtained at +10"F (see Table 3.7).

4 3-27 1

-s,.1,y p--n.e--

.-,w=

pr y &

y

+m.,

y

---i, e,

-.r-----e--r

---

.-rr:

3

,ry-

--. -.,w,

,-yx-

,,w,

-..,.~.,-rme v

~_

-=

Section 4 F

ISSUES RE1ATED TO GENERIC LETTER 8811 NRC issued Generic Ixtter 88 11 (0128 11) in July 1988.

GL8811 letter revised the methodology used for estimating radiation embrittlement of reactor pressure vessel materials to be consistent with the guidelines in Regulatory Guide 1.99, Revision 2. Several technical issues have recently emerged which indicate a need to address some of the application assumptions used in segulatory Guide 1.99, Revision 2. De pertinent issues brought out in Generic letter 92 01 (GL92-01) 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 from $25 to 590'F. Concern is expressed in GL92 01 that power operation may occur at temperatures below 525'F. For SONOS, 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. Dus, there is no time during normal power operation that the SONOS, Unit 2 vessel or surveillance capsules experience temperatures below 545'F.

4.2 APPLICADILITY OF SURVEILLANCE DATA To properly assess the measured surveillance results, and to project irradiation embrittlement trends for the vessel, fluence projections, validated through the dosimetry contained in the surveillance capsules tested to date, are needed. Both SONGS, Units 2 and 3 have identical core designs and essentially the same past and projected operation history. Therefore, the fluence projections from Units 2 and 3 surveillance data will be used for each unit. The fluence as a function of EFPY was obtained from the results of the first capsules pulled fron Units 2 and 3.

nc Unit 2 capsule was pulled at the end of the third fuel cycle which corresnends L c.85 EFPY.I21 These data represent the original core for both units, and the best r'! mate vahe of 2

peak fluu cc at the vessel inner surface is 4.34 x 10 n/cm (E > 1 MeV): the (, pule fluence was about 20% higher at 5.07 x 10 n/cm,

2 At the start of the fourth cycle for each unit the core was reconfigured in a low leakage loading pattern which reduced the vessel and capsule fluxes. The first capsule taken out of Unit 3 was after the fourta fuel cycle at 4.33 EFPY and represents the combined results of the standard and low leakage core designs.I'l ne peak fluence value for the vessel inner surface is 6.6 x 10

2 n/cm, and the associated capsule fluence is 3.0.x 10 n/cm'.

4-1 l

l l

t The projection of fluence forward in time is based upon an extrapolation of the dosimetry information obtained from the two SONGS capsules. 'Ihc projected peak fluence at the vessel inner surface at the end of 32 EFPY is 4.2 x 10" n/cm.W At the point in time of December 16, 2

1991, the estimated EFPY is 5.63, and the projected peak fluence at the vessel inner surface is 8.5 x 10" n/cm'.

As indicated in Figure 31, there is a weld identified as 8 203 which is well outside the core region of the vessel (ie.. approximately 2 feet atmve the top of the core). 'Ihis weld is considered a behline material because of a large chemistry factor associated with the high reported Cu content (0.30 wt%) in combination with a I wt% Ni content, which was assumed because Ni wu not reported. The fluence at this location above the core has report c in the FSAP. to be about 1/37 that of the peak Duence location within the vessel.

Preliminary calculations performed at SCE indicate that the Duence at this weld location may be considerably lower than that indicated in the FSAR. Prior to final verification of the SCE Iluence calculation at wcld 8 203, the factor of 1/37 has been assumed to perform the evaluations in this report.

Within Regulatory Guide 1.99, Revision 2 there are five credibility criteria that must be met in order to utilize surveillance data iii adjusting the predicted embrittlement trends and/or reducing the assigned r nrgin terms. "Ihree of the criteria are met (proper limiting materials, definitive measurements oishift and upper shelf, and a match between the capsule and vessel temperatures within125*F), but the other two have not been satisfied since only one capsule from each vessel has been pulled and evaluated. To satisfy these last two requirements, the second capsules (which will not be pulled until about 15 EFPY) must be evaluated to supply two valid data sets for the vessel surveillance materials, and testing of the correlation monitor material contained in the second capsules must be evaluated against the available data for that material, in the subsequent 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 SillFTS AT Tile CilARPY V NOTCII 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 C6404 2fl'L), and 4-3 (surveillance weld). Appendix F contains in tabular form the absorbed energy, lateral expansion,

'and fracture appearance (% shear) for the irradiated surveillance materials.

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

RG1.99R2 = CF (chemistry factor) X ff (fluence function).

4-2

The results obtained by Battelle M are also shown for consparison. The differences between the l

current values for shift versus those from Battelle are due to small differences in the curve fit to the C m data and the different data set used for Plate C6404 2/fL (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 dermitively evaluate that the chernistry factors (CF) should be adjusted to reDect measured behavior, rather than that predicted from the Regulatory Guide.

Table 4.2 lists the predicted estimates of adjusted RTm (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 RTm's were taken from Tables 3.6 and 3.8. The results in Table 4.2 show that the adjusted RT, 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 Duence.

4.4 UPPER SHELF ENERGY DROP Capsule 97 from the SONGS, Unit 2 surveillance program was evaluated in 1988. Tl.c upper shelf energy results are shown in Figures 41,4 2, and 4-3, and are tabulated in Table 4.3 as absolute drop in upper shelf energy (ft lb). Also listed in Table 4.3 are the predicted drops from Regulatory Guide 1.99, Revision 2. All of the measured drops in upper shelf energy are below those predicted by the Regulatory Guide.

Predictions of upper shelf energy levels at the quarter thickness location after neutron irradiation i

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 10CFR Part 50, Appendix 0.

l 43 l

e 200 San Onofre Unit 2 Surveilldnce Program Materialj Plate SA'53381 No. C64l04 2 Orientation: LT 150

,.+---~~

/

e o

o o

e

/

~

9 f

6

~

l

/

O

/

E 100 4

I I

h

/

I Z

/

I O

f

/

---

f=0.0 I--

50

=

t

/

f = 5.07e+18

/

l O

f a 5.07e+18 f

/

s

~

o

-::/9....

n....n

....n

....i

....n 200 100 0

100 200 300 400 500 Temperature in Degrees F Figure 41.

SONGS, Unit 2: Comparison ofIrradiated Cm Data from Capsule 97 with -

Unitradiated Baseline Data, Plate C6404 2. LT Orientation.

4-4

200 I

1 i

San On,ofra Unit 2,;

l Combined MCR &; Surveillance Data Material: Plate A53381 Heat Nh. C6404-2

~

Orientatalon: T1.

150

=

---

+-----------

as

,or E

j,____

- /--- I- '

w 100

=

e

/

c

/

id

/-

Z

[

>0

,/

/

-- - f = 0,0 50

-t-

/

f =.5.07e+18

/.

1. 0 0

f. = 5.07e+18.

f

/0

/

"""I

l

''''''''''h 0

200 100 0

100 200..

300 400 500 Temperature in Degrees F Figure 4-2.

SONGS, Unit 2: Comparison of Irradiated Cm Data from Capsule 97 with Uni Tadiated Baseline Data, Plate C6404-2 TL Orientation. -

45

}

i l

i f

200 San O,nofre Unit 2

.i Survel,Ilance Pro' gram Material: Weld l

l 150 j, _ _ _ _t_- _ A ; L. _ _ _ _ ? _

_ _,1

-~~

-- t-+

t yc

/

O

~

9

/ O g

/

i

/

N I

w 100 l---

--+-

e i f i

C Lu Z

1

/

l 0

f

/ i

_ _ f = 0.0

/

t ~~

-k 50 f = 5.07e+18

/

0 f = 5,07e+18 4

0

~

200 100 0

100 200

~300 400 500 Temperature in Degrees F Figure 4-3.

SONGS, Unit 2: Comparison ofIrradiated C, Data from Capsule 97 with Unitradiated Baseline Data, Surveillance Weld, i

4-6

I Table 4.1. SONOS, Unit 2: Surveillance Capsule Shift Results.

30 ft lb Shift (F)

Material /

CF rt Orientation Battelle RGl.99R2 Current j

C6404 2/LT 65*

0.81 51 53 52' d

C6404 2/fL 65' O.81 45 53 33 6

Surveillance 31 0 81 7

25 4'

Wcld See Table 3.4 (Cu =.10; Ni =.59)

Based upon the average chemistrics - see Table 3.5 (Cu =.03; Ni =.14)

Based on the baseline surveillance data, see Figure 310 d

Based on the combined data set from the MCR and baseline surveillance program, see Figure 3 9 Based on the baseline surveillance data, see Figure 3-13 l

l 4-7 l

i

Table 4.2. SONGS, Unit 2: ART Estimates at the Inner Surface location for Beltline Materials On 12/16/91 and at 32 EFPY ff ART (F) '

Plate No./

CF at the inner Surface at the Inner Surface Weld Scam 12/16/91 32 EFPY 12/16/91 32 EFPY C64041 65 0.95 1.37 116 143 6

C6404 2 65 0.95 1.37 116 143 C6404 3 65 0.95 1 37 116 143 j

C6404-4 65 0.95 1.37 116 143 C6404 5 75 0.95 1.37 116 147 C6404 6 65 0.95 1.37 116 143 2-203 41' O.95 1.37 18 52 d

3 203 38 0.95 1.37 23 54 8-203 260 0.19' O.44' 52' 125' 9 203 69 0.95 1.37 62 90 ART is the adjusted reference temperature equal to the predicted shift (CF x ft) plus the initial RTmrr plus a margin term equal to 34F for plates or 56F for welds (unless the predicted shift is less than the margin term, in which case the margin is equal to the predicted shift).

6 Based upon average chemistries for this plate (.10 Cu/.59 Ni) see Tables 3.4 and 4.1.

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.

ff is based upon the peak vessel fluence divided by 37 (as indicated in the FSAR).

Since there is a no measured initial RTun, an additional margin associated with the standard deviation (17"F) of the initial RTmg has been used as described in Regulatory Guide 1.99, Rev. 2.

4-8

J Table 4.3. SONOS, Unit 2: Surveillance Capsule Upper Shelf Results.

Upper Shelf Drop (ft lb)

Material /

Cu Fluence 2

Orientation (wt%)

(x 10" n/cm )

Battelle RO1.99R2 Current d

C6404 2/LT 0.10' O.507 17 24 15 C6404 2/fL 0.10' O.507 21 18 14' Surveillance 0.03 0.507 5

24' 4'

6 Weld See Table 3.4 6

See Table 3.5 Based upon the Regulatory Guide 1.99, Rev. 2 lowest percentage drop (16.1%) curve at the specified fluence times the measured unirradiated upper shelf determined in this repcut d

Based on the baseline surveillance data, see Figure 310 Based on the combined data set from the MCR and baseline surveillance program, see Figure 3 9 Based on the baseline surveillance data, see Figure 313 l

l 4-9 r

m

.m

.--p e-r - - - - -,, -

+,,,'

1. .'c.-

n w w r

vy

Table 4.4. SONOS, Unit 2: Upper Shelf Estimates at the Quaner-Thickness Imation for lleltline Materials on 12\\l6T91 and at 32 EFPY Fluence (x 10 n/cm)

Upper Shelf Energy (it lb)'

Plate No./

Cu at Ouarter Thickness at Ouarter-Thickness Weld Scam (wt%)

12/16/91 32 EFPY 12/16/91 32 EFPY C64041 0.10 0.51 2.5

?00 91 C6404 2 0.10' O.51 2.5 95 87 C6404-3 0.10 0.51 2.5 83 76 C6404-4 0.10 0.51 2.5 87 80 C6404 5 0.11 0.51 2.5 98 89 C6404 6 0.10 0.51 2.5 104 95 2 203 0.03*

0.51 2.5 89 81 d

3 203 0.10 0.51 2.5 108 95 8 203 0.31 0.01' O.07' 96 86 9 203 0.07 0.51 2.5 118 107 The upper shelf energy is estimated from Regulatory Guide 1.99, Rev. 2 taking into account the projected 11uences and measured chemistry 5

Based upon average chemistry for this plate-see Table 3.4.

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.

Fluence is based upon the peak vessel iluence divided by 37 (as indicated in the FSAR) 4 10

d Section 5 REFERENCES 1.

A. Ragt, Southern California Edison San Onofre Unit 2. Evaluation of Baseline Specimens. Reactor Vessel Materials irradiation Surveillance Procram. Combustion Engineering S-TR MCS-002, May 27,1978.

2.

M. P. Manahan, L M. Lowry, and E. O. Fromm, Examination. Testine, and Evaluatio,a of irradiated Pressure Vexsci Surveillance Sr,ecimens from the San Onofre Nuclear Generatine Station Unit 2 (SONGS-2), Dattelle Columbus, December 1988.

1 3.

E. Terck, E. P. Lippincott, A. Madcyski, and M Ramirez, Analysis of the Southern California Edison Company San Onofre Unit 3 Reactor Vessel Surveillance Cansule

.B.cmoved from the 97 location. Westinghouse WCAP 12920, Revision 1, November 1991.

T 5-1

APPENDIX A SONGS, UNIT 2: EVALUATION OF COMPLIANCE WITli ASTM E185-73 AND E185-82

i j

L suasnary of Requirements San Onofre Unit 2 Program per ASTN E185-73 l'

1.2 surve!11ance tests are compliance j

divided according to i

application into two cases i

)

1.2.1 Case A - Where both the

~

predicted increase in transition temperature of the i-reactor vessel steel is 100'F or less and the calculated peak i

neutron fluence (E > 1 MeV) of the reactor vessel is 5 X 10" n/cm or less.

2 Where the 1.2.2 Case B

t i

predicted increase in i

transition temperature ' of the reactor vessel steel is greater i

than 100'F or where the

]

calculated peak neutron fluence (E >

1 MeV) of the reactor vessel is greater that 5 X 10" 4

n/cm' i

4.1 Test Material Test To be cc,.irmed based on j

specimens shall be prepared resolving.' inconsistencies in from the actual materials used reported Cu and Ni contents for in fabricating the irradiated beltline and the surveillance region of the reactor-vessel,

welds, i-f l

4.1 Samples shall represent a.

Compliance minimum of one heat of the base metal and one butt' weld and one weld heat-affected-zone (HAZ) if a

weld occurs in the irradiated region.

i 4

4.1 The base metal and weld Compliance metal to be included in the program should represent-the material that may. limit the 4

operation of the reactor during its-lifetime.

A-1 l

1

+

Summary of Requirements Gan Ocofre Unit 2 Program per ASTM E185-73 4.1.1 Vessel Hatorial Sampling To be confirmed based on

- A minimum test program shall resolving inconsistencios in consist of specimens taken from reported Cu and Ni contents for the following locations:

(1) beltline and surveillance base metal of one heat used in wolds.

the irradiated region, (2 ) weld metal, fully representativo of the fabrication practico used for a weld in the irradiated region (weld wire of rod, must come from one of the heats used in the irradiated region of the reactor vessel) and the same type of flux, and (3) the heat-affected-zone associated with the base metal noted above.

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

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

Compliance 4.1.3 Chemical Requirements The chemical composition required by the material specifications for the test materials (base metal and as deposited weld metal) shall be A-2

I t

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 vanadium (V).

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 l

specimen -shall be machined normal to the principal rolling direction for plates and normal to the major working direction for. forgings..

The length of the notch of the Charpy-impact i

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

. t shown in - Fig.

1.

Weld metal tension specimens may be.

oriented in the same direction 1

as the Charpy specimens provided that theEgage length consists of all. weld metal.

No-specimens are to be removed-within :l/2 in. of the root ~ or the surfaces of. the-welds.

Secti_ons of the weldment shall-r be. etched to - define" the weld p

~ heat-affected zones.

Care-shall be:taken that the impact specimens from the weld heat af fected zones have their notch A -

e-ir

---sny-y y e.rr- -,.. -

-a p---

-Wb er 4r

?-t-w e

a s.em

. rw w

.r ew3+w -r + ret 9---er--

y-

+ -

g-+ev -,e-r -

t-e - e a

t-?v

-r e1f

1 l

l Busunary of Requirements San Onofre Unit 2 Program j

per ASTM E185-73 a

J roots in the heat af fected zone at a

standard distance of approximately 1/32 in. from the.

7 i

fusion line.

Specimens i

representing the base metal (tension and impact) and the weld heat-affected zone shall J

be removed from the quarter thickness location. (per NB2300 l

of ASME Code Section III) 4.4 Number of Specimens - The compliance i

t minimum number of test-specimens for.each exposure i

i shall be as follows:-

i

- Case A Case-B

}

Charpy Charpy Tension t

t l

Base Metal 12 12 2

l Weld Metal 12 12 2

HAZ 12-12 l

i' 4.4 At least 15 Charpy impact Compliance specimens shall be used. to establish

-an unirradiated l

transition curve for-each material.

4.4 For Case B (see above),

Not Applicable-4 three tension test specimens ~

shall ~be used to establish unirradiated tensile properties.

i 5.1.1 Vessel Wall Specimens

. Compliance-4 (Required) - Specimens shall be

- irradiated at a location in the reactor that duplicates as-A ~ 4 4

C

...y...

.Imu.m n

,.n,.,.,,9..

,,..,y.wy.,

,,._.3

..,,,p..,__,.,g,..,

..g,-

yy gn..,

,,y.

g

,y.p.,

e.w p yy y

p

...p..,,

j 7

l

)

)

i suemary of Requirements San Onofre Unit 2 Program 4

per ASTN E185-73 i

closely

.as possible the neutron-flux

spectrum, temperature

history, and 4

j maximum accumulated neutron i

fluence experienced by the reactor vessel.

1 i

l 5.1.1 The instantaneous neutron Compliance flux at the location of the j

specimens._ shall not exceed i

three times the calculated maximum neutron flux at the j

inside wall of the reactor i

vessel.

t 1

5.1.2 Accelerated Irradiation Not Applicable Specimens (Optional 1 Test l

specimens may be positioned at j

locations other than (5.1.1) 2 for accelerated irradiation at a rate exceeding three_ timen the calculated maximum neutron i

flux at the inside wall of the j

reactor vessel.

5.2 Flux Heasurements Compliance F

Provisions shall be made to measure the neutron fluence as follows:

4

5. 2.1 -

Dosimeters with the vessel wall specimens (5.1.1).

l l

{-

5.2.2 Where accelerated Compliance irradiation a pecimens are used (5.1.2),

dosimeters with - the

' tat specimens and dosimeters -

l eAther in.

a>: separate flux monitor capsule adjacent to the vessel wall or in a vessel wall A-5

summary of Requirements san onofre Unit 2 Program per ASTN E185-73 capsula.

5.3 Test Capsules - To prevent Compliance deterioration of the surface of the specimens during test, the epocimens should be maintained in an inert environment within a corrosion-resistant capsule.

5.3 The temperature history of Compliance the specimens shall duplicato as closely as possible the temperature experienced by the reactor vessel.

5.3 Surveillance capsules compliance should be sufficiently rigid to prevent damage to the capsules by coolant. pressure or coolant flow thus hindering specimen removal or causing inadvertent deformation of the specimens.

5.3 Irradiated capsules must compliance not be bouyant to preclude serious radiation exposure to personnel if under water handling is employed.

l "3

Consideration-should be Compliance gaven to the design _' of the p

capsule and capsule attachments l-to -

permit insertion of-replacement capsules into the reactor at-a later-time in the

. lifetime of the vessel.

A-6 t

i e

i j

i summary of Requirements San onofra Unit 2 Program i

per ASTM E185.73

.l 5.4 Specimen Withdrawal A

Compliance j

minimum surveillance program shall consist of three capsules for Case A and five capsules for Case B..

It is recommended that capsules be ' withdrawn as described in Table 1.

(See i

Table 1 of ASTM E185-73.)

i t

t 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 END END t

I 1

i A-7 i

e

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

Sunuaary of Requirements San Onofre Unit 2 Program per ASTM E185-82 8.1 Temperature Environment compliance The maximum exposure temperature of the surveillance capsulo materials shall be determined.

If a discrepancy

(> 14"C or 2 5'F ) occurs between the observed and the expected capsule exposure temperatures, an analysis of the operating conditions shall be conducted to determine the ognitude and duration of those differences.

8.2 Neutron Irradiation Compliance Environment 8.2.1 The neutron flux density, neutron energy spectrum, and neutron fluence of the surveillance epecimens and the corresponding maximum values for the reactor vessel shall be determined in accordance with the guidelines in Guide E 482 and Recommended Practice E 560.

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

9.1 Tension Tests:

Compliance 9.1.1 Method - Tension testing shall be.

conducted in accordance with Methods E 8 and Recommended Practice E 21.

9.1.2 Test Temperaturet 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.

One Complianco 9.1.2.2 Irradiated specimen from each material shall be tested at a-temperature in the vicinity of the upper end of the - Charpy onergy transition region.

The remaining specimens from each material shall be tested at the service temperature and the midtransition-temperature.

9.1.3 Measurements - For both Compliance unirradiated and irradiated materials, determine yield

strength,

-tensile strength,-

strength,

- load, fracture fracture fracture

stress, total and - uniform elongation, and reduction of area.

9.2 Charpy Tests:

Compliance 9.2.1 Method- - 'Charpy tests-shall be

onducted in accordance with Method E 23 and A370.

9.2.2' Test. Temperature:

l Compliance 9.2.2.1 =Unirradiated Test temperature for each material-shall be selected to establish a _ f ull transition temperature curve.

Onecspecimen per test temperature may-be -used - to define the overall shape of the curve. - Additional tests should be performed in.the' region A-9

summary of Requirements San Onofre Unit 2 Program per ASTN E185 82 where the measurements described in 9.2.3 are made.

9.2.2.2 Irradiated - Specimens Compliance for each material will be tested at temperatures selected to define the full energy transition curve.

Particular emphasis should be placed on defining the 41-J (30 f t-lb),

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

w i

4.2 3 Measurements - For each Compliance test

specimen, measure the impact

energy, lateral expssnsion, and percent shear fracture appearance.

From the unirradiated and irradiated transition temperature curves determine the 41-J (30 ft-lb),

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

The index temperatures and the upper-shelf energy shall be determined from the average curves.

j 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 i

unirradiated materials.

ev---.~.......

f 9.5.-,t sess Tests (Optional) -

Compliance-A-10 t

L.-

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

i 2

i t

i summary cf Requirements San Onofre Unit 2 Program per ASTM E185 82 Hardness tests may be performed Compliance i

on unirradiated and irradiated i

Charpy specimens.

The i

measurements shall be taken in j

areas away from the fracture zone or the edges of the specimens.

The tests shall be conducted in accordance with j

Methods A 370 i

9.4 Supplemental Tests Not Applicable (Optional)

If supplemental i

fracture toughness tests are

]

conducted (in addition to tests conducted on tension and Charpy i

specimens as described in 6.1) the test procedures shall be documented.

9.5-Calibration of Equipment -

Compliance Procedures shall be employed l

assuring that

tools, gages,

~

recording instruments, and other measuring and testing devices are calibrated and i

properly adjusted periodically to maintain accuracy within l

necessary limits.

Whenever possible calibration shall be i

conducted with standards traceable to the National Bureau of Standards.

. Calibration status shall be maintained in records. traceable-to the equipment.

1 i

- 1 1

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 1

i

.--.y--.-

.mw 3

p.-,.,-

--wg~-.,y,.-

,.w-

..w%

-,g 2-c-

-,7.,---,-

,-..m,4,v.

--y

.,-,4

,w...

..m--

.p,,,..

,-.7pw,.w.,

.w-y,,

9,,

m---,

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

1 i

s f

Susanary of Requirements san Onofre Unit 2 Program 1

l per Ast: E185 82 l

i j

specified in 9.1.2.

i 4

10.1.2 The tensile strength data can be verified using the 4

results from the hardness test (optional) described in 9.3.

l 1

10.2 Charpy Test Data Compliance 10.2.1 Determine the radiation i

induced transition temperature shifts by measuring the j

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 i

after irradiation.

The index temperatures:shall be obtained from the average curves.

t-i 10.2.2 Determine the - adjusted compliance reference temperature by adding the shift corresponding to the a

i 41-J (30 ft-lb)'

index i

determined in 10.2.1 to the initial. reference temperature j

obtained in 9.2.3.1.

4 i

i 10.2.3 Determine the radiation Compliance induced change in the upper shelf energy (USE). from the:

measurements made ' before and af ter irradiation using average value curves.

- the. radiation induced change in

.Not'Applicabl'e 10.2.4 (Optional)7 - Determine.

temperature. corresponding 'to

.50% of the upper.. shelf' energy before and 'atter irradiation

.from average value curves..

A-12

=

i Summary of Requirements San Onofre Unit 2 Program per ASTM E185-82 10.3 Supplemental Test Data Not Applicable If additional, (Optional) cupplemental tests are performed (9.4 ), the data shall be recorded to supplement the information from the tensile end 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 resul to.

11.1 Where applicable, both SI units and conventional units chall be reported.

11.2 Surveillance Program Compliance Description Description of the reactor vessel including the following:

11.2.1 Location of the curveillance capsules with respect to the reactor vessel, reactor vessel internals, and the reactor core.

11.2.2 Location in the vessel of the plates or forgings and the welds.

11.2.3 Location (s) of the peak vessel fluence.-

11.2.4 Lead f actors between the specimen fluence and the peak vessel fluence at the I.D. and A-13

)

i l

i i

Summary of Requirements San Onofre Unit 2 Program j

per ASTM E185 82 l

the 1/4T locations.

e l

1 j

11.2.5 Surveillance Material Compliance Selections s

t i

11.2.5.1 Description of all a

beltline materials including j

chemical analysis, fabrication j

history, Charpy data, tensile-j

data, drop-weight

data, and i

initial RTm.

i 11.2.5.2 Describe the he cis for selection of surve Llance 1

materials.

l

)

q 11.3 Surveillance

. Material compliance

]

Charecterization:

11. ~. 1 Description of the j

surveillance material incJ uding l

fabrication history, material l

source (heat or lot), and_any j

differences between the i

. surveillance :. material history and that of the reactor vessel.

material history.

11.3.2-Location and orientation' of the test specimens in the i

parent material.

I i

11.3.3 Test Specimen Denign:

Compliance 4

11.3.3.1 Description of the test specimens (tension, j_

Charpy, and any_other types of-specimens used),

neutron dosimeters, and-temperature l

monitors.

11.3.3.2 Certification of-calibration of all' equipment-1

. A-14.

i

.J.~...--.,w

.e

,,,__,,,....._;_,.m.,,

,,-,...e

,,_.__..,r..

s..

_, -,., e i.-.

i summary of Regitirements san Onofre Unit 2 Program per ASTM E185 82 i

and instruments used in conducting the tests.

.i 11.4.1 Tension Tests:

Compliance 11.4.1.1 Trade name and model of the testing

machine, gripping devices, extensometer, and recording devices used in the test.

11.4.1.2 Speed of testing and method of measuring the controlling testing speed.

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

11.4.1.4 Test Data from each specimen as follows:

(1) Test temperature; (2)

Yield strength or yield point and method of measurement; (3) Tensile strength; (4)

Fracture

load, fracture strength, and fracture stress; (5)

Uniform elongation ~ 'and method of measurement; (6) Total elongation; (7) Reduction of area; and (8) Specimen identification.

j 11.4.2 Charpy Tests:

Compliance 11.4.2.1 Trade name and model of the testing-cachine,-

available hammer energy capacity and striking velocity, temperature conditioning and measuring devices, and a description of the procedure

-A-15 l

= - -

~

summary of Requirements san unofra 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 follotts:

(1) Temperature of test; (2)

Energy absorbed by the specimen in breaking, reported in joules (and foot-po nd-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 1

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 D

Summary of Requirements San Onofre Ulit 2 Progrx per ASTM E185-82 4

11.4.4.1 If additional tests Not Applicable a"e performed, the test data ill be reported together with tLe procedure used for Jonducting the tests and 4

analysis of the data.

11.4.5 Temperature and Neutron Compliance Radiation Environment Heasurements:

11.4.5.1 Temperature monitor results and an estimate of maximum capsule exposure temperature.

11.4.5.2 Neutron dosimeter measurements, analysis techniques, and calculated results including the following:

(1)

Neutron flux

density, neutron energy spectrum, and neutron fluence in terms of neutrons per square metre and neutrons per square centimetre

(>0.1 and 1

HeV) for the surveillance specimens using both calculated spectrum and assumed fission spectrum assumptions.

(2) Description of the methods used to verify the procedures including calibrations, cross sections, and other perti nent nuclear data.

11.5 Application of Test Compliance Results:

11.5.1 Extrapolation of the neutron flux and fluence l

results to the surface and 1/4T l

locations of the reactor vessel I

l A-17

t 1

2 5

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

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

1 11.5.3 Extrapolation of fracture toughness properties a

to the surface end-1/4T locations of the reactor vessel at the peak fluence location.

l 11.6 Deviations _ Deviations or-Compliance anomalies in procedure from this practice shall be j

identified and described fully in the report.

l END i

i I

i k

i E

P-l 1

i 4

I 1

i '

A_18

.. ~, -...

~.

APPENDIX B SONGS, UNIT 2: BASES FOR PLATE CHEMISTRY MEASUREMENTS l

I

' BDCwN 80Vtti June 8, 1332 S MECH 92 050 i

Mr. Steve Gosselin Southern California Edison 23 Parker Street Irvine, CA 92718 sms3ECT:

vassEL PLATE CZEKICAL ANALYSIS SCC 5tC18 Dear Mr Gosselin f

The purpose of this letter is to provide background information pertaining to beltline material chemistry data for the pistes which were used in the-fabrication of the SONGS Units 2 and 3 reactor vessel.

Recently, differences were noted in the chemical analysis retults reported for the SONCS 2 and 3 reactor vessel beltline plates. A review has been perfoz1med which identified th t theae diffarences arose frces the fact that different source information au used. The source information is noted below SC293S 2 acurR*. Lukens steel Mill analysis

'FSAR' and 'CEN 189* - Chattanooga analyses dated 3/20/70 and 11/26/73 l

somoS 2 1

=CurR* - Inkens Steel Mill analysis

'FSAR". Chattanooga analysis da,ted 1/25/74 and 3/20/74

• CEN.1838. RPV surveillance program Chattanooga analyses dated 7/16/75 and 5/4/78 In order to respond to the piste chemistry questicas of NRC Generic Letter-$2-01, pertinent background information is provided followed by a specific reconnendation.

First, the Lukens chemical analysis data was provided with the CNTR for information only, whereas Chattanooga analyses were used se the basis for licensing transmittals. This was done as a matter of C E practice to maintain l

consistency of resul' %

(Lukans used both different equipment and analysis etandards, which could yield different reported chemical contents than the Chattanooga laboratory.)

ABB Combustion Engineenrg Nuclear Power e

Go D r C*:e Bon Sc3 e

r., (2c12159M Aao or Cy e-ar w$ aye.

... M M* m,2ar, we l

B-1

=

Mr. Stcv3 Go:s3113 S* MECH 32 050 June 8, 1992 Page 2 of 3 Secondly, for both SONGS Cait 2 and 3, chemical analyses were required by both the C.E reactor pressure vessel specification and C.E suzvoi1Muce program specification.

Since these analyses were performed in two separate lustances by the Chattanooga facility on the same material, it is AES C.E's position that the average of these two analyses would be most representative of the plate chemical content.

(Note s For both units, the 'C3 Analysis' value -is an everage of the chemical contents aquired in accordance with the vessel and surveillance program specification.)

Therefore, the rec - adad chemical oceposition for both SopGS vessels is the cveragu of the two Chattanooga chemical analyses, provided in Table 1, and titled 3C3 Analysis'.

Should there be any additional questions, please *do not hesitate to contact me et (202) 285 3433.

• Sincerely, CtasBUSTICat,INGINEERI210, IRC.

5. T. Byrne Supervisor, Reactor Vessel Integrity

{

Sill /CDS:cds I

l cc:

D. Pilmer (SCI)

3. Chang W. Gahwiller C. Stewart l

M. Wade STB 060.WP 1

I B-2

l Mr. Steve Gossella 3.MBCH.32 050 j

June 8, 1992 Page 3 of 3 i

-I t

a l

TMM 1 4

l U23 RV BELTLINI RROICW P! ATE COPPER AND NICKIL CONTINF l

J m

E l

Cu Content (vt %)-

Ni Content (wt %)

l-l Plate f

l No.

l Camt CE Analysis C3trR CE Analysis l-l Unit 2 l

i.

W d

M l C 6404 1 0.11 0.10-0.51 0.56 l

I e

a l C.6404 2 l

0.12 0.10

0. 61 --

l 0.59-

'l' I

W l.

l C.6404 3 0.12

. l 0.10 0.63 0.56-l H

l C.6404 4 0.13 0.10 0.63

. l.

0.62

.l

=

r n

l C.6404 5 l

0.12 0.11 0.63'

.0.64-l m-l C.6404 6 0.12 0.10 0.54 l

0.58 l

E f

j u

l Unit 3 l

a i

n j

u j-l C 6802 1

- 0.06 0.04 0.58 0.58-l a

i l

l C 6802 2 0.04 l

0.04 0.54L l.

. 0.57-

-l u

^

i u

l C 5402 3 0.06 0.06 0.57' O.58~

- l l.

l C 6402 4 l

' O.05 l

0.05 l-0.54 0.56 l

~

f l C.6802 5 0.04 l

0. 04. -

l

= 0.52 0.55' "l-i a

. f i

s a

i l

C.6802 6 0. 0 6 --

l.

l

. 0.65 l.

m 0.06 0.62 Il I

h.'

i,-

8 B-3

i-

[-

k s

,e r-s n-, ---

-e e-

,e e,v, au,,

c,>w

,<<,,,w, e,.,

e s

-p

---e m

--e,,.s u

,y yy ge m pp-y-.,r.ssym><-m-yw,*4 w y,-e n y, s.

J t

N_

+

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

f I

APPENDIX D SONGS, UNIT 2: UNIRRADIATED Cm DATA -

FOR PLATES AND WELDS w

v

4 Table D-1 Charpy V-Nctch Test Results For Unit 2 Plate C6404-1 (TL), MCR Data SPECIHEN TEMP ENER0Y LATERAL TRACT ID NST IMPACT ERP_

APPEAR (F)

(ft-lb)

(mill (U

1

-40.00 10.00 5.00 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 5

10.00-16.00 14.00 5.00 6

10.00 20.00 15.00 10.00 7

40.00 30.00 21.00 15.00 8

40.00 35.00 25.00 15.00 9

40.00 43.00 30.00 20.00 10 10.00 63.00 35.00 40.00 11 70.00 60.00 45.00 35.00 12 10.00 44.00 31.00 20.00 13 80.00 77.00 55.00 50.00 14 80.00 64.00 44.00 40.00 15 80.00 57.00 42.00 35.00 16 100.00 81.00

.58.00 50.00 17 100.00 72.00 56.00 50.00 18 100.00 83.00

- 62.00 50.00 19 160.00 119.00 74.00 95.00 20 160.00 113.00 76.00 95.00 21 160.00 117.00 78.00 90.00 22 212.00 121.00 75.00 100.00 23 212.00 120.00 75.00 100.00 24 212.00 124.00 79.00 100.00 D.1

- Table D-2 Charpy V-Notch Test Results For Unit 2 Plate C6404-2 (TL), MCR Data 4

SPECIMEN TEMP

,ENERCY 1ATERAL FRACT ID TEST IMPACT EXP APPEAR (F)

(ft-lb)

(mil)

'(t) l 1

40.00 6.00 3.00 0.00 1

2

-40.00 7.00 3.00 0.00 6

3 40.00 11.00 6.00 0.00 1

4 10.00.

18.00--

13.00 10.00 1

5 10.00 16.00 11.00 5.00 10.00 13.00 0.00 5.00 1.

j.

7 40.00 37.00 25.00 15.00 i

T e

- 40.00 23.00 17.00 10.00

- 9 40.00 35.00 24.00 15.00 a

10 70.00~

52.00 30.00 25.00-1 l

11 70.00

.47.00 34.00 25.00 -

4-J --

12 70.00 51.00 40.00

~ 25.00-j 13 80.00 65.00 47.00 40.00~

14 80.00 69.00 40.00

'40.00 15-80.00

.53.00_

38.00

_30.00

_ 75.00 55.00 50.00 14 100.00=

17 100.00 48.00 52'.00 f50.00; 4

18 100.00

.73.00 53.00 50.00' 1.

19 160.00 101.00 71.00

-99.00 20 160.00' 95.00-66.00 95.00-

' 21

.160.00 94.00 67.'00 95.00-4

'22 212.00 105.00'

14.00

-100.00 23

. 212.00 123.00 80.00

-- 200.00

-24=

. 212.00-117.00-76.00 100.00-D-2 g

v

,->,,.r,-

m a.

y

,- vr-e - w ww a

w++,e 3

e

+ --

v.w w-

4 Table D.3 Charpy V-Notch Test Results L

For Unit 2 Plate C6404-3 (TL), MCR Data -

.. S P ECIMEN TEMP ENERCY LATERA1.

FRACT

+

j 20 TEST IMPACT-

- EXP APPEA4..

+

(F)

(f*.lb)

(mil)

( t ) L-t 4

1

-40.00 0.00 3.00 0.00 4

)

2 40.00 10.00 6.00 8.00 1

3 40.00 9.00 8.00 0.00 i

f 4

10.00 14.00 9.00 5.00 i

5 10.00-21.00 15.00 10.00

)

6 10.00 15.00 13.00 5.00 i

l 7

40.00-.

19.00 34.00-30.00 I

a 40.00

.33.0'0 22.00 20.00 -

4 21 160.00-93.00

-61.00' 95.00-10 70.00 46.00 35.00 25.00, t

+

+

11 70.00 54.00 42.00 30.00 i

j 12 70.00' 45.00 35.00 25.00

).

13 so.00 69.00 49.00-So.00 14 30.00 60.00 44.00-

.50.00 15 80.00 52.00

36.00 50.00 16 100.00 73.00 55.00

'50. 00 --

17 100.00 74.00

- 5 4. 0 0 --

~50.00 4

18 100.00 71~00 50.00 50.00-i 19 ~

'160.00 97.00

'62$00~

99.00'

'20-

'160.00-

-94.00<-

64.00 -

95.00 -

-9 40.00 30.00

18.00

.35.00' 22 212.00 105.00

69.00 ~

100.00 2 3..

212.00 100.00 6 6. 0 0 ---

100.00'

24

212.00

.103.00 64.00' 100'.00 '-

D 1 l

l

~. 7 -

a 1

i Table D-4 Charpy V Notch Test Results=

i For Unit 2 Plate C6404-4 (TL), MCR Data 4

4 i

i SPECIMEN TEMP ENEROY

1ATERA1, FRACT-l-.

ID

-TEST-IMPACT-EIP

-APPEAR tr)

(ft-lb)

(mil)

(t)

[

4-1-

-40.00 9.00 6.00 0.00

+

E 2

.40.00 9.00 7.00-0.00 l

3

-40.00 10.00 s.00 0.00

-.i 4

10.00 26.00 20.00 15.00 1

5 10.00 22>o0 17.00 10.00 6

10.00 23.00 20.00

-10.00

.[

7 40.00-35.00 25.00 15.00

/

9 e

40.00-34.00-25.00 15.00 i

!=

9-40.00-

.44.00 33.00 20.00 1

10 10.00 47.00 36.00 30.00' i

11 70.00 52.00 40.00 35.00 1

12 70.00 58.00 41.00 40.00 t

13 80,00

$2.00 40.00-40.00 i

a 14 80.00 84.00 30.00 40.00' J

l 15 80.00 68.00

$3.00

?40.00 l

I :-

14

-110.00 48.00'-

51.00 50.00 i-t

.17-110.00..

76.00.

54.00'.

50.00 ai f

18-110.00 85.00 60.00-60.00 a

b' 19 160.00

'100.00 78.00 100.00 4.

20 160.00

.107.00.

75.00 100.00-t-

21 150.00 36.00 71.00--

-100.00 4

h.

h l

i:

4 s

D-4 7-i 4

w p

4,

,,4,,-

...._,4, e n

..=,,,,,

,e,..,v w ~., + +.,

4

'f ln:j' Table D 5 Charpy V Notch Test Results For Unit 2 Plate C6404-5 (TL), MCR' Data 5'

SPECIMEN TEMP RWEACY 1.ATsaAI.

' F1 TACT ID-TtsT IMPACT EXP.

APPEAA 4-(T)

(ft-1b)

(mill-(t) f-t 4

1 40.00 10.00' 5.00 0.00

)-

2 40.00 9.00 5.00 0.00-r Z.

3 40.00 0.00 4.00 0.00 4

10.00 18.00 18.00 5.00 i

13.00-5.00'.

i l

5 10.00 15.00 -

r 6

-10.00 14.00 14.00

5. 0 0 --

7 40.00 25.00 20.00 15.00 f-e 40.00

- 26.00 27.00.

15.00 g

i

.g 9

40.00-23.00-19.00-15.00 10 50.00 47.00

.36.00-3 0. 0 0 --.

11-50.00-54.00 42.00 35.00 12 50.00 61.00

'50.00

-35.00 f

13 70.00~

66.00 40.00 40.00 l-14 10.00 72.00 53.00 J45.00 t

i; 15 10.00 55.00 44.00

+35.00 16' 110.00-81.00 40.00--

50.00 4

4 17 110.00-84.00 59.00 50.00 '

L' le 110.00-

-07.00 61.00--

50.00 a'

19.

160.00

-103.00 65.00 90.00 i

- 20.

160.00 105.00

-10.00 -

90.00-21 160.00

'115.00:

.72.00

-90.00-1 4

22

-212.00-122.00 :

51.00-100.00' 23-

.212.00.

116.00_.

14.00:

'100.00-241 212.00'-

.114'.00' 74.00

100.00

- D-5 i

'7 y

y

-, _y

.c-r

.,,..y,

,,y..-...e e'w.wwww.w.w.+.,.e.,,,,

---

,t,Q,,--

-,w,e w g v. -w g

• y

s, 4:

.f Table D-6 Charpy V-Notch Test Results l

For Unit 2 Plate C6404 6 (TL), MCR Data l

1

- t SPECIMEN TEMP ENERGY

- LATERAL FRACT I

ID TEST

- IMPACT EIP APPBAR (F)

{ft.1b)

-(all)

(0 t

.i 1

40.00 4.00 4.00 0.00 I

2 40.00 9.00 6.00 0.00 fa-3 40.00 6.00 5.00 0.00 il 4

10.00.

14.00

'13.00 5.00 5

10.00 16.00 14.00 5.00 4

1-

- 6 10.00

~13.00 12,00 5.00-7 40.00 20.00 23.00

'15.00 -

a 0

40.00 27.00

.22.00 15.00 9

40.00 27.00 24.00:

15.00 i'

. 46.00.

- 30.00 l

10 50.00--

61.00 1

11 10.00-54.00 -

'40.00

- 25.00 12 50.00 65.00~

47.00 30.00-13

~110.00 05.00' 61.00

' 60.00 1

50,00-L 14-

'110.00 73.00 52.00 I-

~

1 I'

15

-110.00 94.00

.59.00

- 70.00'

+

16 160.00'

116.00 170.00 90'.00 I

j 17

-160.00-115.00-75.00-790.00:

i le-160.00-

110.00-

-70.00'

= 9 0. 0 0. -

~

f:

19

-- 2 D ; !0 120.00'

'00.00 100.00 212.00

-124.00 76.00-100.00'-

21 l.212.00[

121.001

77.00 :.

100.00'-

v v

P I -6; D

4 WN

'9"Wp w

ynr-Wqy=t py y y y'

tv g y wg g y

v ytgT*

p+y,vg-T*7F r-

'WY-T g

v8P'

'Tf f*-ifm*F

'rud-

• -Y*W#FT--

V w='9V V

a

. ~

t

. Table D-7 Charpy V. Notch Test Results.

For Unit 2 Weld Scam 9 203 (Heat #90130), FSAR Data c-l 6

j.--

SPECIMEN TEMP ENERCY'_

- 1ATR8tAL FRACT' l

ID TEST IMPACT

- ERP.

APPEAR-

- (F)

(ft-lb)-

(mil)

(t) i 9.00 0.00-l-

1

--60.00 16.00 1-I 2

-60.00 15.00

.7.00 0.00 l

j-3

-60.00

. 19.00 11.00--

0.00 i

4

-40.00 20.00 11.00

- 5.00 t

i 5

-40.00 20.00 16.00 10.00-4 3

6

-40.00-12.00 22.00-15.00-.

t l

7

-20.00.

85.00

-53.00.

50.00 -

l.

8

-20.00 36.00 56.00-,

50.00.-

i' 9

-20.00 76.00 47.00 40.00 10 0.00 77.00'

'47.00' 40;00-11 0.00 15.00

-45.00 40.00 4

12.

0.00 99.00 52.00 60.00 13 20.00 117.00

--74.00 70.00 l

14 20.00 105.00-65.00 60.00 j

15 20.00

114.00'

~ 7 4.'00.

70.00' 16 60.00 132.00

-77.00-80.00 17 '

60.00

-149.00'

-84.00'

- 100.00 i-i 18 60.00 123.00:

74.00 00.00-19 100.00 142.00 02.00 100.00-

+

i 20 100.00 140.00.

84.00-

' 100.00'21-100.00

'140.00 02.00-100.00:

I.

I D-7 V

c E+r%

..'3,,.

y 3-,,,-

,,~<-,

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

,,.m

_:n,

+ g

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

c

.y+,--,y,,,e w

.o

Table D 8 Charpy V Notch Test Results.-

For Unit 2 Plate C6404-2 (LT), CE Baseline Data SPECIMEN TEMP-ENERCY 1ATERAL FRACT ID TEST-IMPACT-ENP APPEAA (F)

(ft-lb)

(mil)

-(H 154

-80.00 4.50 2.00 0.00 136

-80.00 e.50 10.00

~0.00 122

-40.00 5.00 6.00 0.00 132

-40.00-6.50 6.00 0.00 -

143 0.00 11.00

~13.00 15.00 147 0.00

-16.50 18.00 15.00 114 40.00 41.00' 30.00 25.00 11A 40.00 56.50 40.00 25.00

.12K 00.00 93.50 72.00 65.00

-i 14A 00.00 1124.50 03.00 75.00 I

156 120.00 11s 00

-7e.00 so.00 j

lit 120.00-141.50 96.00 90.00-.

13T 160.00 146.50

~90.00i 100.00.

11T.

160.00 157.50

' 9 5. 00_-

90.06 l

157 210.00 140.00-96.00 100.00~

• 4L-210.00 155.00

'94.00 -

100.00 i

f

-a

--j D :j j

k i

j Table D-9 Charpy % Notch Test Results For Unit 2 Plate C6404-2 (TL), CE Baseline Data -

d i

4 i

l' SPECIMEN TEMP ENEAGY IATERAL '

FRACT.

ID TEST-1MPACT EXP APPEAR i

tr) tit-lb)

(mil)

(t) 264

- -e0.00 4.50 2.00 0.00-25A

-40.00-e.00

's.00 0.00 3

s.00 9.00 0.00 j

-- 220

--40.00 21T.

0.00 12.00 15.00 10.00 21Y 0.00 24.50 -

24.00.

_10.00 262 40.00 33.00 32.00

-20.00 i

25.00 228 40.00.

40.00 35.00

-~

4 24J 80.00 60.50' 50.00-30.00 i

. 24E 80.00

.78.50 62.00 40.00 i

21E 120.00 07.00 66.00 75.00.-

24A 120.00 107.00

'72.00 90.00 245 160.00 111.50 70.00 05.00-24T 140.00 127.50 84.00-90.00 i

216 190.00 116.00 80.00 s100.00.

I' 240-210.00 126.50 87,00

-100.00-

~

231 210.00:-

137.50

'91.00

-100.00 i

D-9 i

wy p

e~

r es,

-st--v-m- -.-N m -

e n n,

s+,v-e sy

,ee, o r - + A n s-w ee -~ w - + t-'+

- e e su v

4 en--s

1 1

Table D 10 Charpy V Notch Test Results For Unit 2 Surveillance Weld, CE Baseline Data i

s i

j a

'e L

- 3 SPECTMEN TEMP RNERGY LATWRAL' FRACT 3

ID TEST-IMPACT _

ERP APPEAR tri (ft ibi (mil)

(U E

t e-J4A 150.00 2.50 1.00 0.00 31M 120.00 7.00 6.00

-15.00 3

4 333

-120.00 14.00 12.00 15.00 i

j 346 00.00

- 16.00 35.00-25.00 I

37A 00.00 29.50 25.00 30.00-i 31R 40.00 43.50 37.00-35.00 357 0.00 63.50 53.00

-65.00 4

1.

4 34T 0.00-

- 90.00 60.00 75.00.

f-338 40.00

- 132.00 90.00-

' 90.00 324 40.00-

.. 146.00 97.00-100.00 I

(

35L 80.00 135.50 95.00 100.00

~.

326

- 80.00 140.00 96.00 100.00

~

331 120.00 145.50 95.00

. 100.00 34J 120.00 153.00 90.00 100;005

~

i i

35J -

160.00

- 151.00-

-96.00 100.00:

335 160.00 152.00-100.00

. 100.00 4.

+

F 4

e i

h

(

4 4

D F-f

(

+

m-gu

'y.i y

e-hPg-5 s-e?,w

+y.

er p

W up.

wy-%.e ey b

is r-~

g&.c3 p

rfW3M"+

4 T

%'4U WT' 9"

1 i.

}

Table D-11 Charpy V Notch Test Results

{-

For_ Unit 2 Plate C6404-2 (LT), MCR Data

. Test.

Impact Lateral Fracture.

]

Temperature Energy -

. Expansion -

Appearance r-('F)

(it lbs)-

' (m ils)

(% Shear)

- 1 5

-40 9

11

~0-

[

-40 12 18-0 4 (*

8 10-0 l

1b 25 19-10-

-10 44-30-25 l

10-26 21 11 5--

40 42' 31.

-25 4

l

'40 60.

44 40-i.---

'4 0 -

52

._ 4 6 -

30 -

110

'126 85-

.80-110 111 78-

'70

[

110 112 74 70 l-160 145 85 95.

i 160 136

.84;,

J.

160 155 9 0 =.

100 b

n' 4

h _.

h-v 3

C D-11 4 -

,--.2,.e.

,..u 2, -a,..... ;~ ::..

..a- -

r...,,

i APPENDIX E SONGS, UNIT 2: HAZ TEST RESULTS 5

I CE Baseline TestsDI j-SPECIMEN TEMP ENERCY 1ATERAL FRACT a

ID TEST IMPACT RRP

~ APPEAR (F)

(ft-lb).

(all)

( 13 --

i 45J 300.00 5.00 3.00 0.00 43C 120.00 9.50 6.00 0.00 41M 00.00 23.50 19.00

.25.00 e

l 415 00.00 35.00 20.00

'30.00 5

466 40.00 31.00 24.00

.30.00 I

46K 40.00 40.00 34.00--

~

30.00 478-0.00-82.00 56.00-

'50.00--

41Y 0.00.

101.00 70.00.

10.00 y

44C 40.00 ~

104.50 11.00 50.00 1

432 40.00 115.50?

00.00-100.00:

461 00.00

'135.50 96.00.

-90.00 5

428 80.00 153.00 92.00

'100.00, i

1 43K 120.00 100.00 79.00 90.00 421 120.00 144.50'

-84.00

-100.00f s

451:

160.00 139.00 85.00.

'100.00' 442 160.00

~ 151.50 84.00

'100.00~

1 4..

E -

y

d Westinghouse Capsule 9y2 a

4

'e l-SPECIMEN TEMP ENERGY 1ATERAL FFACT CHARPY IRRAD ID TEST IMPACT REP APPEAR FLUENCE TEMP.

(F)

(ft.lb)

(all)

(t)-

(n/cm2)

(F) 476 79.00 12.00 9.80 17.00 5.07E+18 500.00 41A 79.00 14.10 10.20 13.00 5.075+10-580.t:0 i

41C 40.00 20.00 14.00 27.00 5.07E41e 580.00 413 40.00 25.20 24.00 38.00 5.078+1e 500.00 J

430 0.00 38.30 30.40 46.00 5.07E618 500.00.

42J 0.00 11.50 54.80 54.00 5.075+10 500.00 42Y 72.00 103.00 81.20 49.00 5.078+18 580.00 42C 72.00 114.20

-84.40 93.00

- 5.075+10 500.00 444

_160.00

-130.00' 07.00 100.00- 5.075+18

-500 M 412 140.00 132.60 95.60 100.00 5.01E+1B' 500.00 44P 260.00 133.70 02.20 100.00 5.073+10 500.00 424 260.00 145.30 89.80 100.00 5.07E+18 580.00 i

4 4

6 E-2 9

e q

wm 4

f APPENDIX F SONGS, UNIT 2: IRRADIATED C, DATA FROM CAPSULE 97 -

Table F-1 Charpy V-Notch Test Results For Unit 2 Plate C6404-2 (LT)

Irradiated (f = 5.07 x 10")

f i

i i

SPECIMEN TEMP ENERCY LATERAL TRACT ID TEST IMPACT-EXP APPEAR l

-(F)

(ft-lb)

(mil)-

(4 f

141 0.00 6.00 6.80 4.00 i

f 111 0.00

, 0.10 6.43 5.00 4

15M 40.00 12.50 7.30 11.00-14T

- 72.00 23.50' 23.60 9.00 9

13M 72.00 27.40-26.60 13.00 123

'100.00 59.50 53.60 18.00-13E 100.00

-74.20-58.80 20.00 4

11M 160.00 113.40 03.00 77.00-15E 160.00 138.50 99.40 100.00-11U 200.00-127.30 93.40-100.00-

. 124 200.00 134.20 105.80-100.00-4 137-260.00 137.30 95.40.

100.00-4 F-1

-g

--~e-n-

4emwr >

r.g,r.

~~w~

" w 4

s

+e a

a-e+-

s em ~

'~,*n n~

-=

d Table F.2 Charpy V Notch Test Results For Unit 2 Plate C6404 2 (TL)

Irradiated (f = 5.07 x 10")

I SPECIMEN TEMP ENERGY IATERAL TRACT ID TEST IMPACT EXP APPEAR l

(F)

(ft-lb)

.(mil)

(%)

i 214 0.00 4.00 10.00 4.00 h

l 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 i

25U 100.00 44.10 42.40 42.00 23P 100.00 50.00 44.00 49.00 1

21B 160.00 82.00 68.40.

. 85.00~

221 200.00-93.00 71.00 100.00:

l 25L 200.00 98.00 68.60 100.00 256 260.00 101.90-03.40 100.00 211-260.00-103.00.

83.80

~ 100.00 t

~

1 4

i F-2 t

p g

.m~p r-

• y-y ew nwyn 4

e ayywy y

y w z a -p

>wq r

..e-y

Table F-3 Charpy V-Notch Test Results For Unit 2 Surveillance-Weld Irradiated (f = 5.07 x 10 ')

1 1

SPECIMEN TEMP ENERGY LATERAL FRACT ID-TEST IMPACT EXP APPEAR

]

(F)-

- (ft-lb)-

(mil)

-(t) a 37M

-79.00

'15,00 14.40 18.00 i

1 37L

-79.00 19.40 20.00 13.00 3A3

-40.00 25.00 23.60 36.00 36M--

-40.00

- 45.40-36.60 40.00.

2 s

'36P 0.00 78.00-45.20 60.00 36K 0.00 02.40' 64.60-70.00 31E 72.00 126.90 95.00 92.00 l

33P 72.00

138.20 102.20 100.00

. 342 160.00 134.00 99.00 100.00 36E 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 I

1

+

. I t

F3-m

,.n.

~

,.--,.,---,,m-e..

-, ~

y p.