ML20084C631

Rev 2 to Songs,Unit 2 Response to GL 92-01

ML20084C631
Person / Time
Site:	San Onofre
Issue date:	05/19/1994
From:	ATI CONSULTING, SARTREX CORP.
To:
Shared Package
ML20084C411	List: ML20084C406 ML20084C631 ML20084C643
References
GL-92-01, GL-92-1, NUDOCS 9505310556
Download: ML20084C631 (140)

Text

F'

\\m.

'L

=

l Attachment A E

(

San Onofre Nuclear Generating Station, Unit 2 Response to Generic Letter 92-01 Revision 2 May 19,1994 I

l Prepared by:

1 r

ATI Consulting San Ramon, CA l

and Sartrex Corporation I

Rockville, MD I

g Prepared for:

Southem California Edison Irvine, CA I

<t 950531o556 95o523 ADOCKc5oogi DR I

I CONTENTS Section P_agt 1

INTRODUCTION 1-1 l

2 REACTOR FRESSURE VESSEL SURVEILLANCE 2-1 PROGRAM-COMPLIANCE WITH APPENDIX H 3

FRACTURE MECHANICS 3-1 3.1 COMPLIANCE WITH APPENDIX G 3-1 3.2 BELTLINE MATERIALS IN SONGS, UNIT 2 3-1 i

3.2.1 location 3-1 3.2.2 Heat Treatment 3-1 3.2.3 Key Residual and Alloying Element Contents 3-2 3.3 FRACTURE TOUGHNESS RELATED DATA 3-3 t

3.3.1 Beltline Plate Material 3-3 3.3.2 Beltline Welds 3-4

(

4 ISSUES RELATED TO GENERIC LETTER 88-11 4-1 4.1 VESSEL TEMPERATURE DURING OPERATION 4-1 4.2 APPLICABILITY OF SURVEILLANCE DATA 4-1 4.3 SHIFTS AT THE CHARPY V-NOTCH 30 FT-LB ENERGY LEVEL 4-2 4.4 UPPER SHELF ENERGY DROP 4-3 5

REFERENCES 5-1 I

i

(

\\

CONTENTS (cont'd)

Section Pane APPENDIX A SONGS, UNIT 2: EVALUATION OF COMPLIANCE A-1 WITH ASTM E185-73 AND E185-82 APPENDIX B SONGS, UNIT 2: BASES FOR PLATE CHEMISTRY B-1 MEASUREMENTS APPENDIX C SONGS, UNIT 2: BASES FOR WELD CHEMISTRY C-1 MEASUREMENTS APPENDIX D SONGS, UNIT 2: WMCs FOR BELTLINE D-1 MATERIALS APPENDIX E SONGS, UNIT 2: MCRs FOR BELTLINE E-1 MATERIALS APPENDIX F SONGS, UNIT 2: UNIRRADIATED Cyn DATA F-1 FOR PLATES AND WELDS APPENDIX G SONGS, UNIT 2: HAZ TEST RESULTS G-1 APPENDIX H SONGS UNIT 2: IRRADIATED Cyn DATA FROM H-1 CAPSULE 97

ILLUSTRATIONS Figure Eagn 3-1 SONGS, Unit 2: Location and Identification of 3-6 Beltline Plates and Welds 3-2 SONGS, Unit 2: Data and Least Squares Fit Curve 3-7 for Cvu versus Temperature, Plate C6404-1, TL i

Orientation, MCR Data 3-3 SONGS, Unit 2: Data and least Squares Fit Curve for 3-8 Cvu versus Temperature, Plate C6404-2, TL Orientation, i

MCR Data 3-4 SONGS, Unit 2: Data and 12ast Squares Fit Curve for 3-9 i

Cvu versus Temperature, Plate C6404-3, TL Orientation,

^

MCR Data 3-5 SONGS, Unit 2: Data and least Squares Fit Curve for 3-10 Cvu versus Temperature, Plate C6404-4, TL Orientation, MCR Data

(

3-6 SONGS, Unit 2: Data and I2ast Squares Fit Curve for 3-11 Cvu versus Temperature, Plate C6404-5, TL Orientation, MCR Data 3-7 SONGS, Unit 2: Data and Least Squares Fit Curve for 3-12 Cvu versus Temperature, Plate C6404-6, TL Orientation, MCR Data 3-8 SONGS, Unit 2: Data and Least Squares Fit Curve for 3-13 Cvu versus Temperature, Plate C6404-2, TL Orientation, Surveillance Baseline Data 3-9 SONGS, Unit 2: Data and I2ast Squares Fit C'2rve for 3-14 Cvu versus Temperature, Plate C6404-2, TL Orientation, Combined MCR and Surveillance Baseline Data l

(

ILLUSTRATIONS (cont'd)

Eigurq Pace 3-10 SONGS, Unit 2: Data and Least Squares Fit Curve for.

3-15 Cys versus Temperature, Plate C6404-2, LT Orientation, Surveillance Baseline Data 3-11 SONGS, Unit 2: Comparison of Least Squares Fit Cvu 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 Cvu versus Temperature, Weld 9-203, WMC Data 3-13 SONGS, Unit 2: Data and Least Squares Fit Curve for 3-18 Cys versus Temperature, Surveillance Weld, Surveillance Baseline Data 4-1 SONGS, Unit 2: Comparison of the least Squares Fit for the 4-4 Unirradiated Baseline Data with the Irradiated Cv3 Data and least Squares Fit.'or the Data from Capsule 97, Plate C6404-2, LT Orientation 4-2 SONGS, Unit 2: Comparison of the least Squares Fit for the 45 Combined MCR and Unirradiated Baseline Data with the Irradiated Cvu 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 Cvy Data and least Squares Fit for the Data from Capsule 97, Surveillance Weld l

f

t i

TABLES Table P_agn 3.1 SONGS, Unit 2: Compliance with 10CFR50, Appendix G 3-19 i

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 Coinbinations 3-22 for Beltline Surveillance Welds 3.4 SONGS, Unit 2: Key Residual and Alloying Element Contents for 3-23 Beltline Plates 3.5 SONGS, Unit 2: Key Residual and Alloying Element Contents for 3-24 Beltline Welds 3.6 SONGS, Unit 2: Beltline Plate Material Unitradiated 3-25 Fracture Toughness Tests Results Summary, TL Orientation l

3.7 SONGS, Unit 2: Charpy Absorbed Energy Values at 10'F 3-26 t

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 l

4.1 SONGS, Unit 2: Surveillance Capsule Shift Results 4-7 4.2 SONGS, Unit 2: ART Estimates at the Inner Surface 4-8 Location for Beltline Materials on 12/16/91 and at 32 EFPY 4.3 SONGS, Unit 2: Surveillance Capsule Upper Shelf Results 4-9 4.4 SONGS, Unit 2: Upper Shelf Estimates at the Quarter-Thickness 4-10 location for Beltline Materials on 12/16/91 and at 32 EFPY i

Section 1 INTRODUCTION The Nuclear Regulatory Commission (NRC) in Generic Letter 92-01 (GL 92-01) requested all holders of operating licenses or construction permits for nuclear power plants to submit information needed to assess compliance with requirements and commitments regarding reactor vessel integrity. Revision 0, June 24,1992, of this report was prepared in response to GL 92-01 for San Onofre Nuclear Generating Station (SONGS), Unit 2. It identified additional information needed to resolve the following issues: (1) inconsistencies noted in copper (Cu) and nickel (Ni) contents for beltline Weld 9-203 and the surveillance weld, (2) locating material certification reports to confirm beltline weld properties, and (3) verifying the fluence at Weld 8-203.

Revision 1 of this report (dated January 22,1993) incorporated additional materials data obtained from the SONGS, Unit 2 Nuclear Steam Supply System (NSSS) vendor, ABB-Combustion Engineering (ABB-CE), and the results of calculations performed by Southern California Edison Company (SCE) to better characterize fluence conditions at Weld 8-203, and the results from calculations performed to evaluate the upper shelf toughness for Weld 8-203. It also indicated that: (1) the beltline weld properties had been confirmed with the exception of beltline Welds 8-203 and 2-203 A, B, and C, and (2) additional information would be required to confirm heat numbers for the surveillance weld material and Welds 2-203 A, B, and C.

i In previous versions of this report the initial RTer for the vessel beltline material with the highest end of life adjusted reference temperature (i.e., the plate material used in the surveillance program) was determined using a combined data set obtained from the materials certification report (MCR) and the baseline surveillance program. In Revision 2, the initial RTor for this material is determined using only the data from the MCR. This change was made to be consistent with SCE's interpretation of the Code requirement for defining initial RTer, which is that data to be used in accordance with paragraph NB-2331 of Section III of the ASME Code are the data obtained by the vessel manufacturer to assess the toughness properties at the time of vessel fabrication. This MCR data thus established the initial RTer by satisfying paragraph NB-2331(a)(3) of the ASME Code, Section Ill. This change also was made so that this initial RTer is defined in a manner consistent with that for other beltline materials where surveillance baseline data were not available. Consistent with the previous revisions of this report, the combined set of MCR and surveillance data were used to establish the unirradiated upper shelf energy and the temperature at 30 ft-lb Charpy absorbed energy for purposes of assessing the irradiation effects on the surveillance plate material.

This revision (Revision 2) incorporates additional materials data and information obtained from the SONGS, Unit 2 NSSS vendor, ABB-CE. These data provide: (1) the heat number, chemistry and Charpy data for Welds 2-203 A, B, and C, (2) the weld wire and flux combinations, chemistry, and Charpy data for Weld 8-203, and (3) the weld wire and flux combinations for the surveillance weld. Based on a review of the information supplied by ABB-CE, the chemistry and i

1-1

1 8

f Charpy energies have been confirmed for the materials in the SONGS, Unit 2 pressure vessel beltline, and the response to GL 92-01 is now complete.

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

Compliance with 10CFR50, Appendix G, is described in Section 3 along with a description of the location, heat treatment, residual and alloying element contents, and upper shelf and transition temperature fracture toughness for the beltline materials in the SONGS, Unit 2, reactor vessel. Section 4 addresses embrittlement effects, including irradiation temperature and adjusted reference temperature for evaluation of the beltline materials relative to GL 88-11 and 10CFR50,61.

(

l-2

Section 2 REACTOR PRESSURE VESSEL SURVEILLANCE PROGRAM COMPLIANCE WITH APPENDIX H The American Society of Mechanical Engineers (ASME) Code of record for the SONGS, Unit 2, reactor pressure vessel is the 1971 Edition through the Summer 1971 Addenda. Consequently, the applicable version of American Society for Testing and Materials (ASTM) E185 is the 1970 version (ASTM E185-70). However, 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 10CFR50, Appendix H requirements had to do with the method of attachment of the holders for the six surveillance capsules in each SONGS unit. ABB-CE was the vessel manufacturer and the NSSS vendor; ABB-CE attached the capsule holders directly to the cladding on the inside of the vessel in the beltline region (as they did for all ABB-CE NSSS-designed vessels), and this approach violated the requirements in the early 1970's version of 10CFR50, Appendix H.

NRC reviewed a ABB-CE Topical Report (CENPD-155-P,.C-E Procedure for the Desien. Fabrication. Installation. and Inspection of Surveillance Holder Assemblies) and found the practice and procedures acceptable.

The current version of 10CFR50, Appendix H does not treat this method of attachment of the capsule holders as a noncompliance issue. The wording in the current Appendix H,Section I. A.2, is:

"If the capsule holders are attached to the vessel wall or to the vessel cladding, construction and in-service inspection of the attachments and the attaciunent 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 capsules."

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

2-1 l

The details of the SONGS, Unit 2, surveillance program have been described in the FSAR and

- ~

subsequent surveillance program testing reports, baseline l'1 and irradiated.t23 The first capsule results have been evaluated for a low fluence following ASTM E185-82 testing and reporting requirements. Later sections of this report will discuss these results as compared to regulatory prediction methods.

The update of ASfM E185 for 1992 (E185-93) is about to be approved and issued. One significant change from E185-82 is the removal of the requirements for testing heat-affected-zone (HAZ) material. This change has resulted from the difficulty in interpreting HAZ results due to *he degree of scatter and the ability to define the usefulness of blunt notch Charpy V-notch absorbed energy (Cys) HAZ data. NRC has been involved in making this change to E185 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,t.21 and is provided for reference in a subsequent section of this report.

1 1

s l

t 2-2

4 Section 3 i

,x 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,l'1 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.t21 3.1 COMPLIANCE WITH APPENDIX G The materials in the beltline region of SONGS, Unit 2, comply with the requirements of Appendix G,10CFR50. A summary of compliance with 10CFR50, Appendix G, as specified in the FSAR for SONGS, Units 2 and 3, and updated during preparation of this report, 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 identifies the plates and welds and their location in the beltline region.

The heat numbers for the beltline plates shown in Figure 3-1 are presented in Table 3.2. The weld wire and flux combination for the beltline welds shown in Figure 3-1 and the surveillance welds are presented in Table 3.3. Source documentation has been obtained to confirm the properties of all beltline plates and welds and the surveillance weld.

3.2.2 Heat Treatment The heat treatment for the plate materials consisted of austenitization at 1575 i 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 1225125'F for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

For ASME Code qualification, the plates were stress relieved at 1150125'F for 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> and then were furnace cooled to 600 F at a rate of 100'F/hr. The actual time at temperature for a specific weld or a 3-1

plate in the vessel depended upon the sequence of vessel fabrication; intermediate and final k.

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 1100"F to 1150"F.

i 3.2.3 Kev Residual and Allovine Element Contents The copper (Cu), nickel (Ni), phosphorus (P), and sulfur (S) contents reported for each belthne plate are presented in Table 3.4.

The plate Cu, Ni, P, and S contents were obtained by averaging two measurements made by ABB-CE. The first measurement was made when ABB-CE received the plate from Lukens, and the second measurement was made when the surveillance program was defined. The bases for the Cu, Ni, P, and S contents are presented in Appendix B.

A second set of data is included for Plate C6404-2. This set was obtained from broken surveillance specimens when the first irradiated surveillance capsule from Unit 2 was tested.t2j Table 3.5 contains the Cu, Ni, P, and S contents for the beltline welds. The source documents for the information in Table 3.5 are presented in Appendix C. Additional information from the

/

WMCs for Welds 3-203 A, B, C,8-203, and 9-203 is presented in Appendix D. Because Ni was not measured for Weld Seam 8-203, a value of 1.0 wt% has been assumed (see Regulatory Guide 1.99, Rev. 2). Two chemistry measurements have been made for the surveillance weld and also are reported in Table 3.5. The first chemistry measurement was made as part of the Ul original baseline, while the second was obtained from a broken Charpy specimen from Capsule 97t21, Tables 3.4 and 3.5 also include the chemistry factors determined for each reported set of Cu and Ni contents using Regulatory Guide 1.99, Revision 2.

3.3 FRACTURE TOUGHNESS RELATED DATA This section presents the results from the Cw tests and summarizes the upper shelf energies (USEs) and the results from the drop weight nil ductility temperature (NDT) tests for the unirradiated beltline plate and weld materials in SONGS, Unit 2. The unirradiated reference temperature (RTm) values were determined from the Cw and NDT test results in accordance with the most recent version of ASME Section III, NB-2331. The USEs were determined using the definition specified in ASTM E185-94 (to be issued). The data included in the USE determination were the Cm values for those tests (at least 3) where the percent shear on the fracture surfaces was equal to and greater than 95%.

I 3-2

g The fracture toughness data for the plates were obtained from the MCRs (see Appendix E of this report) and baseline surveillance program.14 The source documents for Welds 2-203 A, B, C,3-203 A, B, C,8-203, and 9-203 are presented in Appendix D cf this report. The data for the surveillance weld were obtained from the baseline surveillance program.

For convenience, the Cw, lateral expansion, and fracture appearance (% shear) data for the unirradiated beltline and surveillance plate and weld materials are listed in tabular form in Appendix F of this report.

As discussed earlier in Section 2, the results for HAZ material are not evaluated in this report because upcoming ASTM standard E185-94 will not require HAZ material to be part of the l

surveillance program. The raw Cm data for the past HAZ testing are attached in Appendix G of this report.

)

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 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 Cm data as a function of test temperature for beltline Plate numbers C6404-1,

-2, -3, -4, -5, and -6 are presented in Figures 3-2 through 3-7, respectively. For convenience, 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 E185-94 for specimens having fracture surfaces with 95% and l

greater shear. For convenience, the figures also indicate the values of NDT, USE, the temperature at which a minimum Cm equal to 50 ft-lb (T @ 50 ft-lb) is achieved consistent with the applicable method of ASME,Section III, NB-2331, and RTer. As part of the surveillance program, s.dditional Cw versus temperature data were generated for Plate C6404-2;IO hese data are presented in Figure 3-8 along with a least squares fit curve.

t 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 average curve through the combined data set in Figure 3-9 was used as the unirradiated baseline to evaluate the results for the irradiated surveillance tests (see Section 4).

Table 3.6 is a summary of the unirradiated NDT, RTur, and USE values for the TL orientation for each of the beltline plates in SONGS, Unit 2. The NDT for Plate C6404-2 also was determined twice. One value was measured when the mater'al was purchased (-20 F), while

(

3-3

~.

the second value was determined from the unirradiated baseline tests (+10*F). The value k

measured when the plate was purchased (i.e., the MCIt data) is listed in Table 3.6.

The methods used to determine RTw7 from the NDT and C, data also are identified in Table j

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

Figure 3-10 shows the data and least squares fit line for the LT orientation for surveillance Plate C6404-2.W Figure 3-1I shows a comparison of the best fit line for the LT orientation for the arveillance 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.

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 Cw 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 seams were tested to obtain three Cm data

{

points at 10 F. The results from these tests are presented in Table 3.7. Figure 3-13 presents the Cm data and least squares hyperbolic tangent curve fit for the surveillance weld material.

A comparison of the Cm 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 sets of data. Therefore, the baseline surveillance curve fit can be used to assess shift and upper shelf toughness changes.

Table 3.8 presents a summary of the unirradiated NDT, RTur, and USE values for each of the beltline welds in SONGS, Unit 2. For Welds 3-203 A, B, C 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, RTer quals NDT. For Welds 2-203 A, B, C, the available Cm data are 70*F e

above NDT; however, since the data all have absorbed energies greater than 100 ft-lb, RTur 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 fl-lb at 10 F. Since no NDT data are available for Weld 8-203, the initial RTer was taken as the generic value of-56*F for ABB-CE fabricated vessels (see 10CFR50.61).

The USEs shown in Table 3.8 for Weld 9-203 and the meillance weld were obtained by averaging the test results where 95% shear or greater was exhibited. The USEs for Welds 3-203 A, B, C and 8-203 were obtained from the data in Table 3.7 by averaging the three Cm data points obtained at 10*F for each of the listed welds. The USEs for Welds 2-203 A, B, C

(

3-4

J 4

' ('

were obtained from the data in Table 3.7 by averaging the nine C, data points obtained at 0

\\

and 10*F.

q 9

5 9

(

t 3-5 k

' REACTOR VESSEL BELTLINE MATERIALS NOT SHOWN INTERMEDIATE SHELL I

T WELD SEAM NO.2 203C Q

Q' i ~

LOWER SHELL

~

"a WELD SEAM NO.3 2038 WELD SEAM NO. 3-203C

/,-

gg' s\\

PLATE NO. C-6404-5 Ls 6

cp "g'3 f

k I

i

)

f--

42"ID 30"1D OUTLET INLET NOZZLE L

NOZZLE UPPER TO INTERMEDI ATE I =

=

SHELL GIRTH bE p lNTER.$1EDIATE SHELL WEL D NO. 8-203 p

LONGITUDINAL WE LD SEAM NO.2 2038 INTERMEDIATE SHELL PLATE NO. C 64041 p INTERMEDIATE SHELL PLATE NO.C4404 2 w

INTERMEDIATE SHELL LONGITUDIN AL W f

INTERMEDIATE TO-LOWER SEAM NO.2-203A SHELL GIRTH SEAM

=

WELD NO.9 203 INTERMEDIATE SHELL PLATE NO. C 6404 3 LOWER SHELL LOWER SHELL PLATE

~

NO. C-6404 6 -

LOWER SHELL

/ *,#

$ AM NO.3-203A C7 e

T 4

!!!!!!!!!!!!!!!!!iii!!!!!!!!!!

d Figure 3-1.

SONGS, Unit 2: location and Identification Of Beltline Plates and Welds.

t b

3-6

~

'\\

e a

l e

200

=

Sag Onofre Unit 2 MCR Data Material: Plate No. C6404-1. A503B1 Orldntation: Tl.

)

g USE = 119 ft 'bs NDT = -30 'F T@ 50 ft-lbs := 80 'F j

"3 RTrdt = 20 'F r

E N

g 100

{

,c Z

oA o

O 50 O

Measured O O Calculated j

e a a a 1.

n a a a 11e a a a 11 a a a a 1 a a a a !! n a a a 11

-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 Cw versus Temperature, Plate C6404-1, TL Orientation, MCR Data.

[

3-7 4

e e

-~,

<-.2 v -.

4 e

200

=

Sarj Onofre Urit 2 MCR Data Mahrial : Plate No. C6404 2, A5331 31 Orientation: T YOUE UN8 150

=

l NDT = -20 'F T @ 50 ft lbs a80'F RTridt = 20 'F j

O "i"5 O

1 100

=

(

8 o

tu Z

>0 j

i O

Measured Calculated

..m a e a Il a a a a I a a a a U a a a a It a a e a l'

a e a a 1

-200

-100 0

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

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

(

3-8 r

-.m-_.-

• - k.

b e

200 Sari Onofre Ur it 2 MCR Data Maierial: Plate C6404 3, A53381

~

Orlantation: TL 150 Uspaggft105

=-

NDJ = -20 'F e

T @ 50 ft-lbs = 80 'F

~

h RTndt = 20 'F r

c$

w 100

=

e

{

c uJ

~

Z>

O 0

t 1

O Measured Calculated O o p

m a a a l'a a a a l'

a e a a 1: a a a e I a a e a ll a a a e 1

-200

-100 0

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

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

3-9 i

a k.

200 Sag Onofre Unit 2 MCR Data Mat'erial: Platq C6404-4, A533B1 Oridntation: TL g

USE = 104 ft 'bs NDJ = -10 Y T @ 50 ft-Ibs ::: 80 'F j

RTridt = 20 'F

~4 u.

A O

E 100 I'

ec W

o Z>

o 0

50

=

g O

O Measured Calculated e a a a a 1: e a a a I a a a a l'

a a a a l'

a a a a l a a a a 1

-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 Cw versus Temperature, Plate C6404-4, TL Orientation, MCR Data.

(

3-10

k 200 4

.I 1

8 i

i i

i San Onofile Unit 2 l

l l

l MCR Datd l

l l

l l

Material: Plate C6404'5, SA5338,'I l

l l

t 0

I I

t

" Orientation: TL i.

i.

i.

i i

i i

150

- U S E- =- 1 1, 8 - f t -I b s - - - + - - - - - - - - -'- - - - - - - - - +. - - - - - - - - - - - - - - - - - - <i---------

i NDT = -20F

' T@ 50 ft-Ibs = 70F l l

l l

l RTndt = 30F l

l l

l l

i

,i un i

e

.i

,0

.o r

O J, V u.

i, 9

g;; 100 u,

---

s,--------6,--------'--

4,--------

a,---------

c l

l l

l l

l ua

{

Z l

l l

l l

i i

o O '

O ',

O i

i 50

---

<---------t--------l---------i---------l---------i---------

a e

6 I

I I

9 t

1 0

4 9

I 4

t, i

4 8

1 4,

i e

i I

t 1

I i

i l

i t

I t

0 I

I 0

4, 4,

t i

8

,.s 0

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 Cw versus Temperature, Plate C6404-5, TL Orientation, MCR Data.

i 3-11

y J

7' 200

=

San Onofre Unit 2 MCR Data Mate /lal: Plate C6404-6, A533B1

~

Orientation: TL 150 USE h 124 ft-lbs NDT:= -10 'F T@ 50 ft-Ibs = 50 'F

,.c RTnd'; = -10 'F 3

u.

hw 100

=

e c

ul Z>

0 0

8 O

50

=

O Measured 0

Calculated I

6 a a a a H m a e e l'

s a e a 1 e e a n 1 a a a a i

-...n a a e

l'

-200

-100 0

100 200 300 400 500 r

Temperature in Degrees F i

Figure 3-7.

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

(

3-12

)

]

l i

i t

)

i 200 t

i 1

1 I

i 1

t I

i I

e 6

0 t

I t

6 i

i 3

0 i

4 e

t I

I i

1 4

i t

i 1

i t

8 9

i i

.i i

e e

.i i

.i

,i e

i

. --------l---------l--------i-------'--------l---------

150 r

'f - 0.0

'0

,i i

i i

e i

i i

i O

e i

i

.o e

i i

i r

i i

i i

O' u.

i i

i i

i i

O i

i i

e i o i

i i

100 s-------

a-2-------

w g

l l

Sar( Onofre Unit l2 l

(

Lu l

Surve llance Pro 6 tam l

0 Z

l Material: Plate No. C6404-2,'SA533B 1 g

l l

l Ori(ntation: TL l l

l l

l US5 = 126 ft-lys l

NDT = 10F i

t 1

0 a

l I

i i

I I

9 0

4 0

0 I

i 50

---.--------+i i

i t

i 8

i i

i i

t I

i i

4 i

i t

i e

5 9

i 6

6 4

5 8

1 6

1 e

t i

i i

I t

i 4

0 i

l i

I t

e f

9 8

i i

t 6

1 6

O.

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

l 3-13

l 1

1 l

200 e

i

, San Onofre' Unit 2 l

l l

l l

Combined yCR & Surve,illance Data' l

l l

' Material: P!pte No. 0640,4-2, SA533,91 l

i i

, Orientation *sTL i

1 USE = 113. ft-lbs i

i i

f I

e I

I

---

'--------i.-------,'--------l--------l--------t,--------

150 i

io

,i

,i m

o

.n

.O i

.g i,

r G'

l l

l ol0 i

o i

io i

e i

>9 100

- - - - - - -,l- - - - - - - J, - - - - - - - ' - - o - - -l o e

e m

i z

l l

0 l

l l

c i

i

.i 9

i i

1 1

I

,I

---

l--------i.----o-'--------l---------l--------t--------

50 r

5 I

i i

1

.I a,

1 I

l l

l l

l o.

o 0

I---

1-

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

(

3-14 1

9

'l

+

.r I

200 e

1 f = 0.0 O

O 150 u

3 O

E 100

=

I E

5 o

San Onofre Unit 2 Surveblance Prohram Materihi:-Plate-M ).--G6404-2 -6 A533B 1-50

=

Orient' tion: LT a

USE d 150 ft-tbs NDT d 10 Y O

1 O

200

-100 0

100 200 300 400 500 Temperature in Degrees F

~

Figure 3-10.

SONGS, Unit 2: Dita and Izast Squares Fit Curve for Cm versus Temperature, Plate Q 404-2, LT Orientation, Surveillance Baseline Data.

(

3-15 9

g-

k 200 i

e.

.i i

San Onof,re Unit 2 i

i i

i i

Comparison of MCR D,ata with Suryeillance Best Fit Line l

l Material:l Plate No. CQ404-2, A53SB 1 l

l l

Orientatidn: LT l

l l

l l

i i

i i

.i

',g o

i 150

---

'---------'----------l-------

i i

i, 9

i t,

o t

i i.

i i

i i

i f

6 8

i o

a i

y) e i

i

_23 i

e, u.

g A

l l

l l

l l

En 100 -----.---p---------;.-.---.--;----------;----------;---------q--------.

C i

e oe i

uJ i

i i

I f

4 5

j-z 6,

o'

>O l

l l

t i

l 0

MCR Data l

l 0

i e

o i

---

;---------,L--------'-----

Fit to Surveillance l

50 l

l0 l

Data l

,i i

e i

1 a

i i

i e,

i

)

i i

i i

i i

i i

0 I

^

- I I

I ^

^

I - - - -

-200

-100 0

100 200 300 400 500 Ternperature in Degrees F 4

i Figure 3-11. SONGS, Unit 2: Comparison of Least Squares Fit Cm versus Temperature Curve for the Surveillance Plate with MCR Data for Plate C6404-2, LT Orientation.

I 3-16

k.

200

~

San Onofre Unit 2 WMo bsta Material: Weld Weld 9 203 USE y 145 ft-lbs 150 NDT 4 -6DF 00 T @ fo ft-Ibs =20'F j

RTndt! = -60 'F 0

3 O

u.

g 100 c

8, tu

~

06 o

50 0

Measured Calculated O

...Y r....i

.... c....i 1

.... o o

-200

-100 0

100 200 300 400 500 Temperature in Degrees F Figure 3-12.

SONGS, Unit 2: Data and least Squares Fit Curve for Cw versus Temperature, Weld 9-203, WMC Data.

I 3-17

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

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

purchased and treated to Code requirements. No RTer or drop weight Tor temperatures are determined.

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

met.

III.C.

" Reactor Vessel Beltline", as The baseline tests of the surveillance 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 is not complied with in that that the intent of Appendix G has been only base plate and represent-met. (Note: the HAZ results are not 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.

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

corresponding shell materials were used.

(Section IX, ASME Code) 3-19

e o

2h0

=

f = 0.0 150 C-O A

O 5

100

=

nu 5

/

/

San Onofre Unit 2 l

f Surveillance Prog' ram Matdial:Wald

~I USE = 146 ft-lbs

/

NDT= -50 Y T @ 50 ft-Ibs --10 9 g

RTndt = 50 9 O

M r.... r....,

e 200

-100 0

100 200 300 400 500 Temperature in Degree F

+

Figure 3-13.

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

(

3-18 l

)

i k

Table 3.1 (Continued)

Paragraph Description of Non-Compliance Comment I

IV. A.4 Charpy V-notch tests were The ASME Code in effect required test not conducted at "the temperature of 60*F below the lowest preload temperature or at

' service temperature. All bolting material the lowest service was tested at 10*F and met the 35 ft-lb temperature, whichever is minimum requirement of the applicable lower".

ASME Code. All beltline plate materials and one beltline weld were tested to meet the current (1989) Code requirements in NB-2331. The remaining beltline welds were tested at 10*F and/or 0*F and have an average Cm in excess of 90 ft-Ib.

These results indicate that the intent of Appendix G has been met.

i i

e 3 20

4

\\

N.

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

1 -

Lukens Plate Number Heat Number C6404-1 C7596-1 C6404-2 C7595-2 C6404-3 C7595-1 C6404-4 A6735-1 i

C6404-5 C7585-1 C6404-6 C7596-2 e

l 3-21

\\

Table 3.3 SONGS, Unit 2: Weld Wire and Flux Combinations for Beltline and Surveillance Welds.

t Weld Seam Weld Wire and Flux

~

2-203 A, B, C' E8018 C-3 Electrodes, Lot No. BOLA 3-203 A, B, C Type Mil B-4 Wire, Heat No. 83637, 6

Linde Type 0091 Flux, Lot No.1122 8-203' Combination of (1) Type Mil B-4 Wire, Heat No.10137, Linde Type 0091 Flux, Lot No. 3999 and (2) Type Mil B-4 Wire, Heat No. 90136, Linde Type 0091 Flux, Lot. No. 3999 9-203' Type Mil B-4 Wire, Heat No. 90130, Linde Type 0091 Flux, Lot No. 0842 Surveillance' Same consumables as Weld 9-203 a.

Weld wire heat number and flux type confirmed by ABB-CE letter dated November 4,1993 contained in Appendix D.

b.

Basis is SONGS Unit 2 FSAR and is consistent with handwritten note in Appendix D.

c.

Weld wire heat number and flux type confirmed by ABB-CE letter dated January 4, 1994. The applicable data are contained in App. C and D.

I 3-22

+~~

l Table 3.4 SONGS, Unit 2: Key Residual and Alloying Element Contents for Beltline Plates.'

t i'

a.

Plate ABB-CE Number Lab. No.

Cu Ni P

S CF6 i

C6404-1 P14445 0.10 0.56 0.007 0.009 65 P16921 C6404-2 P14446 0.10 0.59 0.008 0.010 65 P16922 C6404-2' O.10 0.59 0.011 N/A 65 i

C6404-3 P14447 0.10 0.56 0.008 0.011 65 P16923 C6404-4 P14105 0.10 0.62 0.006 0.009 65 Pl7110 C6404-5 P14068 0.11 0.64 0.007 0.010 75 i

Pl7405 C6404-6 P14106 0.10 0.58 0.006 0.010 65 i

Pl7111 m

a.

Average values (see Appendix B) b.

Chemistry factors from Regulatory Guide 1.99, Revision 2 Measured when the surveillance tests were performed for Cap.fe 97 )

t2 i

c.

4 3-23 4

-. ----.--.--4

., ~. - -

("

Table 3.5 SONGS, Unit 2: Key Residual and Alloying Element Contents for Beltline A

Welds.

Weld ABB-CE Number Lab No.

Cu Ni P

S CF*

1 2-203A D18153 0.03 0.90 0.009 0.017 41 2-203B D18154 0.03 0.91 0.009 0.016 41 7

2-203C D18155 0.03 0.95 0.010 0.016 41 l

3-203A D17025 0.05 0.12 0.011 0.011 40 l

3-203B D17026 0.04 0.06 0.010 0.011 30 3-203C D17027 0.06 0.11 0.010 0.011 42 6

8-203 (90136)D10255 0.31 1

0.012 0.010 260 i

(10137) D10600 0.23 1

0.016 0.010 236 6

,1 9-203 D23227 0.07 0.29 0.009 0.007 69 Surveillance

• D26761 0.03 0.12 0.003 0.009 30 i

Surveillance 0.03 0.15

<0.005 N/A 32 t

d t

a.

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

Ni content was not obtained and 1.0 wt% has been assumed (per Regulatory Guide 1.99, Rev. 2)

Measured when surveillance program was developedDI c.

d.

Measured when the surveillance tests were performed for Capsule 97 ]

t2 t'

\\

3-24

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

Initial Plate NDT RTer Procedure to USE Number

(*F)

('F)

Determine RTer (ft-lbs)

C6404-1

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

C6404-2*

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

-20 20 NB-2331 (a)(3) 99 C6404-4

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

-20 10 NB-2331 (a)(3) 118 C6404-6

-10

-10 NB-2331 (a)(2) 124

~.

This plate is included in the surveillance program. RTer is based on the MCR data a.

(see Figure 3-3) and the USE value is based on the combined data sets from the MCRs and unirradiated surveillance baseline (see Figure 3-9) i b.

An NDT value of -20'F was determined when the plate was purchased (+10 F was determined from the surveillance baseline program).

L p

l

)

.(

3-25 1

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

Test Temperature Charpy Energy Weld Seam

(*F)

(ft-lb) 2-203 A, B, C 10 69,87,74 10 106,108,105 0

82, 101, 108 3-203 A, B, C 10 153, 131, 125 8-203 (90136) 10 108, 112, 119 (10137) 10 101,108,107 i

t i

e t

f 3-26 s

u 4

. Table 3.8 SONGS, Unit 2: Beltline Weld Material Unirradiated Fracture Toughness Tests Results Summary.

i Initial NDT RTer Procedure to USE Weld Seam

('F)

('F)

Determine RTer (ft-lbs) 6 2-203 A, B, C

-60

-60 NB-2331 (a)(2) 93 d

3-203 A, B, C

-50'

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

8-203 (10137)

N/A

-56 c

105 d

8 203 (90136)

N/A

-56 c

113 9-203

-60'

-60 NB-2331 (a)(2) 145 i

Surveillance

-50

-50 NB-2331 (a)(4) 146 a.

NDT values were obtained from the FSAR and documented in Appendix D b.

Estimated using the average of Cm values obtained at +10'F and O'F (see Table 3.7) c.

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

Estimated using the average of Cm values obtained at +10*F (see Table 3.7) t I

3-27

Section 4 k

ISSUES RELATED TO GENERIC LETTER 88-11 NRC issued Generic Letter 88-11 (GL 88-11) in July 1988. GL 88-11 revised the methodology used for estimating radiation embrittlement of reactor pressure vessel materials to be consistent with the guidelines in Regulatory Guide 1.99, Revision 2. Several technical issues have recently emerged which indicate a need to address some of the application assumptions used in Regulatory Guide 1.99, Revision 2. The pertinent issues brought out in GL 92-01 are addressed in this section.

4.1 VESSEL TEMPERATURE DURING OPERATION The methodology in Regulatory Guide 1.99, Revision 2, is specified to be applicable for operating temperatures in the range of $25 to 590"F. Concern is expressed in GL 92-01 that power operation may occur at temperatures below 525'F. For SONGS, Unit 2, the reactor coolant cold leg temperature (T,) is maintained above the Technical Specification limiting condition for operation of $35'F which applies above 30% power. The normal operating band l

of T, ranges from 545'F at zero power to 553*F at 100% power with a tolerance ofi 2*F.

Thus, there is no time during normal power operation that the SONGS, Unit 2, vessel 6r surveillance capsules experience temperatures below 525'F.

l 4.2 APPLICABILITY OF SURVEILLANCE DATA l

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

The Unit 2 capsule was pulled at the end of the third fuel cycle which corresponds to 2.85 EFPY?l These data represent the original core for both units, and the best estimate value of peak fluence at the vessel inner surface is 4.34 x 10'8 n/cm (E > 1 MeV); the capsule fluence 2

2 2

was about 20% higher at 5.07 x 10 8 n/cm,

At the start of the fourth cycle for each unit, the core was reconfigured in a low leakage loading 3

pattern which reduced the vessel and capsule fluxes. The first capsule taken out of Unit 3 was i

after the fourth fuel cycle at 4.33 EFPY and represents the combined results of the standard and low leakage core designs?3 The peak fluence value for the vessel inner surface is 6.6 x 1028 2

2 g

n/cm, and the associated capsule fluence is 8.0 x 10ts n/cm,

I 4-1

1 The projection of fluence forward in time is based upon an extrapolation of the dosimetry

~k information obtained from the two SONGS capsules. The projected peak fluence at the vessel inner surface at the end of 32 EFPY is 4.2 x 10 n/cm ?1 At the point in time of December 2

16,1991, the estimated EFPY is 5.63, and the projected peak fluence at the vessel inner surface 2

is 8 5 x 10 n/cm.

As indicated in Figure 3-1, there is a weld identified as 8-203 which is well outside the core region of the vessel (i.e., approximately 2 feet above the top of the core). This weld is a

conservatively considered a beltline material because of a large chemistry factor associated with the high reported Cu content (0.31 wt%) in combination with a 1.0 wt% Ni content, which was t

conservatively assumed because Ni was not reported. The fluence at this location above the core was reported in the FSAR to be about 1/37 that of the peak fluence location within the vessel.

Recent calculations performed at SCEH1 indicate that the fluence at Weld 8-203 is 1/108 that of the peak fluence location within the vessel. The SCE fluence calculations have been used in the i

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, 1

definitive measurements of shift and upper shelf, and a match between the capsule and vessel temperatures within 125'F), but the other two have not been satisfied since only one capsule from each vessel has been pulled and evaluated. To satisfy these last two requirements, the second capsules (which will not be pulled until about 15 EFPY) must be evaluated to supply two valid data sets for the vessel surveillance materials, and testing of the correlation monitor material contained in the second capsules must be evaluated against the available data for that material.

In the subsequent 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 SIIIFTS 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 C6404-2/TL), and 4-3 (surveillance weld). Appendix H contains, in tabular form, the absorbed energy, lateral expansion, and fracture appearance (% shear) for the irradiated surveillance materials.

The results computed during this work for the shift at the 30 ft-lb energy level are tabulated in Table 4.1 as " current" and compared to the Regulatory Guide 1.99, Revision 2, mean shift predictions (RG1.99R2):

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

4-2

I i

9 m are also shown for comparison. The differences between the f

The results obtained by Battelle

(

current values for shift versus those from Battelle are due to small differences in the curve fit to the Cvy 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 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 l

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 RTas were taken from Tables 3.6 and 3.8. The results in Table 4.2 show that the adjusted RTm is essentially the same for 1

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.

i 4.4 UPPER SHELF ENERGY DROP s

Capsule 97 from the SONGS, Unit 2, surveillance program was evaluated in 1988. The USE r

results are shown in Figures 4-1,4-2, and 4-3, and are tabulated in Table 4.3 as absolute drop in USE (ft-lb). Also listed in Table 4.3 are the predicted drops from Regulatory Guide 1.99, l

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.

4 I

J.

4-3 s

4 i

200 San Onofre Unit 2 Surveilldnce Program Material l Plate SA'533B1

, No. C6404-2 Orientation: LT

=

15o

~-

/

/

o o

o e

/

B

/

C k

~

/

O

/

/

E 100 1

=

G I

(

h I

I Z

/

I O

I

,1 f = 0.0 50 1

=

/

f = 5.07e+18

/

l O

f = 5.07e+18 f

/

/

.m a a e n ll e a e a l'

s e e n l'

n a a a l'

a a a n 1

- :" 7.

-200

-100 o

100 200 300 400 500 Temperature in Degrees F Figure 4-1.

SONGS, Unit 2:

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, LT Orientation.

I 4-4

9 San Onofre Unit 2 Combin'ed MCR & Surveillance Data MaterlaI: Plate A533B1

~

~

Heat No. C6404-2 Orientatalon: TL d

150

=

e

.o I

U-e',

g 9

g 100 j

o

=

/

C

(

W

/

~

Z j

/

0 i

/

_ _ _ _ _ g, o,o So i

/

f = 5.07e+iB

/

,/ O o

f = 5.07e+18

/o

/

"'"""'7 o

i

-200

-100 o

too 200 300 400 500 Temperature in Degrees F s

)

i Figure 4-2.

SONGS, Unit 2: Comparison of the Least Squares Fit for the Combined MCR and Unirradiated Baseline Data with the Irradiated Cm Data and Least Squares Fit for the Data from Capsule 97, Plate C6404-2, TL Orientation.

.I 4-5 t

e l

j

l

(

i l

200 I

I San Onofre Unit 2 Surve{llance Prkram Material: Weld

__A_g____,_____

150

=

g/

=

O a

/

9

/ O

/

/

5 t

w 100

=

G i

C

,I tu 2>

I U

l

/

---

f=0.0

/

50 t-f = 5.07e+18

/

/

O f = 5.07e+18 O

M

.... r....,....

r....r r

-200

-100 o

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

SONGS, Unit 2:

Comparison of the Izast Squares Fit for the

^

Unitradiated Baseline Data with the Irradiated C, Data and Least Squares Fit for the Data from Capsule 97, Surveillance Weld.

[

4-6

I Table 4.1.

SONGS, Unit 2: Surveillance Capsule Shift Results.

s 30 ft-lb Shift ('F)

Material /

CF ff Orientation Battelle RG1.99R2 Current C6404-2/LT 65*

0.81 51 53 52' C6404-2/TL 65*

0.81 45 33 33d Surveillance 696 0.81 7

56 4'

Weld a.

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

Based upon the conservative 9-203 weld chemistry - see Table 3.5 i

c.

Based on the baseline surveillance de.ta, see Figure 3-10 d.

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

Based on the baseline surveillance data, see Figure 3-13 I

4-7

\\

-~

(

F s

k Table 4.2.

. SONGS, Unit 2: ' ART Estimates at the Inner Surface Location for Beltline Materials on 12/16/91 and at 32 EFPY.

Fluence Function

- ART (*F)*

Plate No./

CF at the Inner Surface at the Inner Surface

' Weld Seam 12/16/91 32 EFPY 12/16/91 32 EFPY '

C6404-1 65 0.95 1.37 116 143 C6404-2 656 0.95 1.37 116 143 C6404-3 65 0.95 1.37 116 143 C6404-4 65 0.95 1.37 116 143 C6404-5 75 0.95 1.37 115 147 C6404-6 65 0.95 1.37 86 113 2-203 A, B, C 41' O.95 1.37 18 52 3-203 A, B, C 38d 0.95 1.37 22 54 i

8-203 (10137) 236 0.09' O.25' 5'

68' 8-203 (90136) 260 0.09' O.25' 8'

74' 9-203 69 0.95 1.37 62 90 I

a.

ART is the adjusted reference temperature equal to the predicted shift (CF x ff) plus the initial RTer plus a margin term equal to 34*F for plates or 56'F for welds (unless the predicted shift is less than the margin term, in which case the margin is equal to the l

predicted shift) b.

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

Based upon average chemistries for these welds (.03 Cu/.92 Ni)--see Table 3.5 d.

Based upon average chemistries for these welds (.05 Cu/.10 Ni)--see Table 3.5 Fluence function is based upon the peak vessel fluence divided by 108W e.

f.

Since there is not a measured initial RTmr, an additional margin associated with the standard deviation (17"F) of the initial RTor has been used as described in Regulatory Guide 1.99, Rev. 2 i. I i

4-8 i

l

1 i

i N

Table 4.3.

SONGS, Unit 2: Surveillance Capsule Upper Shelf Results i

Upper Shelf Drop (ft-lb)

Material /

Cu Fluence 2

?

Orientation (wt%)

(x 10 n/cm )

Battelle RG1.99R2 Current C6404-2/LT 0.10' O.507 17 24 15d C6404-2/TL 0.10' O.507 21 18 14' Surveillance 0.076 0.507 5

26' 4'

Weld a.

See Table 3.4 b.

See Table 3.5 for wcld 9-203 Based upon interpolation of the Regulatory Guide 1.99, Rev. 2 curves, c.

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 4-9 I

k Table 4.4.

SONGS, Unit 2: Upper Shelf Estimates at the Quarter-Thickness Location for Beltline Materials on 12/16/91 and at 32 EFPY.

Fluence (x 10 n/cm2)

Upper Shelf Energy (ft-lb)*

Plate No./

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

12/16/91 32 EFPY 12/16/91 32 EFPY C6404-1 0.10 0.51 2.5 100 91 C6404-2 0.1 06 0.51 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 A, B, C 0.03' O.51 2.5 78 71 3-203 A, B, C 0.058 0.51 2.5 114 103 8-203 (10137) 0.23 0.005 0.023 94' 89' 8-203 (90136) 0.31 0.005 0.023 97' 88' 9-203 0.07 0.51 2.5 119 107 a.

The upper shelf energy is estimated from Regulatory Guide 1.99, Rev. 2, taking into account the projected fluences and measured chemistry b.

Based upon average chemistry for this plate-see Table 3.4 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 Based upon an extrapolation of the curves in Regulatory Guide 1.99, Rev. 2 e.

/

4-10

r Section 5 g

REFERENCES

[1]

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

~

[2]

M. P. Manahan, L. M. Lowry, and E. O. Fromm, Examination. Testine. and Evaluation of Irradiated Pressure Vessel Surveillance Soecimens from the San Onofre Nuclea.C Generatine 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 Comoany San Onofre Unit 3 Reactor Vessel Surveillance Caosule Removed from the 97* Location, Westinghouse WCAP-12920, Revision 2, May 1994.

[4]

R. Chang, " SONGS 2/3 RPV Fluence Ratio at Weld 8-203", SCE Calculation No.

N-1020-065, December 1992.

(

e e

9 4

5-1

't.

l k

-t

.t t

- i r

P APPENDIX A l

i l

t

'(

SONGS, UNIT 2: EVALUATION OF CC4MPLIANCE l

WITH ASTM E185-73 AND E185-82 l

l e

9 0

I s

I i

I

3 Summary of Requirements San Onofre Unit 2 Program

-(

per ASTM E185-73 1.2 Surveillance tests are divided Compliance according to application into two cases:

i Where both the 1.2.1 Case A predicted increase in transition temperature of the reactor vessel steel is 100'F or less and the calculated peak neutron fluence (E

> 1 MeV) of the reactor vessel is 2

5 X 10" n/cm or less.

1.2.2 Case B - Where the predicted increase in transition temperature of the reactor vessel steel is greater than 100*F or where the calculated peak neutron fluence (E

> 1 MeV) of the reactor vessel is 2

greater than 5 X 10" n/cm 4.1 Test Material - Test specimens compliance shall be prepared from the actual materials used in fabricating the irradiated region of the reactor vessel.

4.1 Samples shall represent 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 metal Compliance to be included in the program should represent the material that may limit the operation of the reactor du:?ing its lifetime.

I A-1 i

r Summary of Requirements San Onofre Unit 2 Program per ASTM E185-73 4.1.1 Vessel Material Sampling - A Compliance minimum test program shall consist of specimens taken from the following locations:

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

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

The Compliance 4.1.2 Fabrication History test material shall receive a

fabrication history i

(austenitizing, quench and tempering, and post-weld heat treatment) fully representative of the fabrication received by the material in the irradiated region of the reactor vessel.

4.1.3 Chemical Requirements - The Compliance chemical composition required by the material specifications for the test materials (base metal and as deposited weld metal) shall be obtained and include, but not be limited to phosphorus (P), sulfur (S),

copper (Cu),

and vanadium (V).

(

A-2

f..j-i Summary of Requirements San Onofre Unit 2 Program i..

per ASTM E185-73

^

' i 4.2 Charpy V-notch impact compliance specimens corresponding to the Type A

specimen described in Methods E 23 shall be employed l

unless material thickness does not t

permit.

Both irradiated and unlrradiated types of specimens shall be of the same size and shape.

4.3 Specimen Orientation and Compliance

~

Location For both tensAon and impact specimens from base metal, the major axis of the specimen shall be machined normal to the principal rolling direction for plates and normal to the major working direction for forgings.

The length of the notch of the charpy impact specimen shall be normal to the surface of the material.

The recommended

(

orientation of the impact and tension specimens with respect to the weld are shown in Fig.

1.

Weld metal tension specimens may i

be oriented in the same direction as the Charpy specimens provided that the gage length consists of all weld metal.

No specimens are to be removed within 1/2 in. of the root or the surfaces of the welds.

Sections of the weldment shall be etched to define the weld heat affected zones.

Care shall be taken that the impact specimens from the weld heat affected zones have their notch roots in the heat affected zone at a

standard distance of approximately 1/32 in.

J from the fusion line.

Specimens representing the base metal (tension and impact) and the weld

)

heat-affected zone shall be i*

removed from the quarter thickness I

location. (per NB2300 of ASME Code Section III)

.'I A-3

e.

l Summaary of Requirements San Onofra Unit 2' Program per ASTM E185-73 The Compliance 4.4 Number of Specimens minimum number of test specimens for each exposure shall be as follows:

Case A Case B Charpy Charpy Tension Base Metal 12 12 2

Wald Metal 12 12 2

HAZ 12 12 4.4 At least 15 Charpy impact Compliance specimens shall be used to establish an unirradiated transition curve for each material.

4.4 For Case B (see above), three Not Applicable tension test specimens shall be

(

used to establish unirradiated tensile properties.

5.1.1 Vessel Wall Specimens compliance Specimens shall be (Required)-

irradiated at a location in the reactor that duplicates as closely as possible the neutron-flux spectrum, temperature history, and maximum accumulated neutron fluence experienced by the reactor vessel.

5.1.1 The instantaneous neutron Compliance flux at the location of the specimens shall not exceed three times the calculated maximum neutron flux at the inside wall of the reactor vessel.

A-4

?

Summary of Requirements San onofre Unit 2 Prograa per ASTM E185-73 5.1.2 Accelerated Irradiation Not Applicable Specimens (Optional)

Test specimens may be positioned at locations other than (5.1.1) for accelerated irradiation at a rate exceeding three times the calculated maximum neutron flux at the inside wall of the reactor vessel.

5.2 Flux Measurements -

ovisions Compliance shall be made to measure the neutron fluence as follows:

5.2.1 Dosimeters with the vessel wall specimens (5.1.1).

4 5.2.2 Where accelerated Compliance irradiation specimens are used (5.1.2), dosimeters with the test specimens and dosimeters either in

(

a separate flux monitor capsule adjacent to the vessel wall or in a vessel wall capsule.

To prevent Compliance 5.3 Test Capsules deterioration of the surface of the specinens during test, the specimens should be maintained in an inert environment within a

corrosion-resistant capsule.

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

D p

i A-5

+'

summary of Requirements San Onofre Unit 2 Program

,, (

per ASTM E185-73 l

5.3 Surveillance capsules should Compliance be sufficiently rigid to prevent damage to the capsules by coolant pressure or coolant flow thus hindering specimen removal or i

causing inadvertent GMormation of the specimens.

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

5.3 Consideration should be given Compliance to the design of the capsule and capsule attachments to permit insertion of replacement capsules into the reactor at a later time in the lifetime of the vessel.

(

A Compliance 5.4 Specimen Withdrawal 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.

l (See Table 1 of ASTM F185-73.)

a The Compliance I

6.1 Radiation Environment neutron

flux, neutron energy l

spectrum, and irradiation temperature of surveillance I

specimens and the method of l

determination shall be documented.

4 4

I I

A-6 t

Summary of Requirements San Onofre Unit 2 Program per ASTM E185-73 6.2 Neutron Flux Dosimeters - Flux Compliance dosimeters for a

particular program shall be determined by referrina to Method E 261.

END END I

1 i

i A-7

i b

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

If a discrepancy (>14'C or 25'F) occurs between the observed and the expected capsule exposure temperatures, an analysis of the operating conditions shall be conducted to determine the magnitude and duration of these differences.

8.2 Neutron Irradiation Compliance Environment:

8.2.1 The neutron flux density, neutron energy spectrum, and neutron fluence of the surveillance specimens and the corresponding maximum values for the reactor vessel shall be determined in accordance with the I

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 define the strength versus temperature relationship.

(

A-8

t t

cUmmary of Requirements San Onofre Unit 2 Program yer ASTM E185-82 9.1.2.2 Irradiated - One specimen Compliance from each material shall be tested at a temperature in the vicinity of the upper end of the l

Charpy energy transition region.

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

9.1.3 Measurements - For both Compliance unirradiated and irradiated materials, determine yield strength, tensile strength, fracture load, fracture strength, fracture stress, total and uniform elongation, and reduction of area.

9.2 Charpy Tests:

Compliance 9.2.1 Method - Charpy tests shall I

be conducted in accordance with Method E 23 and A370.

9.2.2 Test Temperature:

Compliance 9.2.2.1 Unirradiated - Test temperature for each material shall be selected to establish a full transition temperature curve.

One specimen per test temperature may be used to define the overall shape of the curve.

Additional tests should be performed in the region where the measurements described in 9.2.3 are made.

9.2.2.2 Irradiated - Specimens 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.

A-9

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

(

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 41-0 (30 ft-lb),

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

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

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

Compliance 9.3 Hardness Tests (Optional)

Hardness tests may be performed on unirradiated and irradiated Charpy specimens.

The measurements shall be taken in areas away from the fracture zone or the edges of the specimens.

The tests shall be conducted in accordance with Hethods A 370.

9.4 Supplemental Tests (Optional)

Not Applicable

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

?

t

(

A-10

. Summary of Requirements San Onofre Unit 2 Program per ASTM E185-82 i

9.5 Calibration of Equipment -

Compliance 1

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 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.

A-11

summary of Requirements San Onofre Unit 2 Program per ASTM E185-82

+

k.

10.2.2 Determine the adjusted Compliance reference temperature by adding the shift corresponding to the 41-J (30 ft-lb) index determined

^

in 10.2.1 to the initial reference temperature obtained in 9.2.3.1.

10.2.3 Determine the radiation Compliance induced change in the upper shelf energy (USE) from the measurements made before and after irradiation using average value curves.

10.2.4 (optional) - Determine the Not Applicable radiation induced change in temperature corresponding to 50%

of the upper shelf energy before and after irradiation from average value curves.

10.3 Supplemental' Test Data Not Applicable (Optional) - If additional, supplemental tests are performed (9.4), the data shall be recorded to supplement the information from the tensile and Charpy tests.

10.4 Retention of Test Specimens Compliance

- It is recommended that all broken test specimens be retained until released by the owner in the event that additional analyses are required to explain anomalous results.

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

I A-12

i t

Summary of Requirements San Onofre Unit 2 Program per ASTM E185-82 11.2 Surveillance Program Compliance Description - Description of the reactor vessel including the following:

11.2.1 Location of the surveillance capsules with respect to the reactor vessel, reactor vessel internals, and the reactor Core.

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

11.2.3 Location (s) of the peak vessel fluence.

11.2.4 Lead factors between the specimen fluence and the peak vessel fluence at the I.D. and the 1/4T locations.

(

11.2.5 Surveillance Material Compliance Selection:

11.2.5.1 Description of all beltline materials including chemical analysis, fabrication history, Charpy data, tensi.le data, drop-weight data, and initial RTmn.

11.2.5.2 Describe the basis for selection of surveillance

^

materials.

(

l A-13

+

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

(

11.3 Surveillance Material Compliance Characterization:

1 11.3.1 Description of the surveillance material including fabrication history, material source (heat or lot), and any differences between the surveillance material history and that of the reactor vessel material history.

11.3.2 Location and orientation of the test specimens in the parent material.

11.3.3 Test Specimen Design:

Compliance 11.3.3.1 Description of the test specimens (tension, Charpy, and any other types of specimens used), neutron dosimeters, and temperature monitors.

11.3.3.2 Certification of calibration of all equipment and instruments used in conducting the tests.

A-14

r 9f.

Summary of Requirements San Onofre Unit 2 Program per ASTM E185-82 11.4.1 Tension Tests:

Compliance 11.4.1.1 Trade name and model of

+

i 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.

i

)

l 4

\\

(

A-15

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

(

11.4.2 Charpy Tests:

Compliance

r 11.4.2.1 Trade name and model of the testing machine, available

~

hammer energy capacity and striking velocity, temperature conditioning and measuring devices, and a description of the procedure used in the inspection and calibration of the testing machine.

11.4.2.2 Test data from each specimen as follows:

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

(3) Fracture appearance; l

(4) Lateral expansion; and (5) Specimen identification.

11.4.2.3 Test data for each

(

material as follows:

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

)

irradiation; (3) Initial reference temperature; and (4) Adjusted reference temperature.

11.4.3 Hardness Tests (Optional):

Compliance 11.4.3.1 Trade name and model of the testing machine.

11.4.3.2 Hardness data.

1 A-16

summary of Requirements San onofra Unit 2 Program per ASTM E185-82 11.4.4 Other Fracture Toughness Not Applicable Tests:

11.4.4.1 If additional tests are performed, the test data shall be reported together with the procedure used for conducting the tests and analysis of the data.

l 11.4.5 Temperature and Neutron Compliance Radiation Environment Measurements:

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

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

(1) Neutron flux density, neutron I

energy spectrum, and neutron fluence in terms of neutrons per square metre and neutrons per square centimetre (>0.1 and 1 MeV) for the surveillance specimens using both calculated spectrum and assumed fission spectrum assumptions.

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

b 9

4 R

A-17

Summary of Requirements San Onofre Unit 2 Program per ASTM E185-82 11.5 Application of Test Results:

Compliance j

l 11.5.1 Extrapolation of the neutron flux and fluence results to the surface and 1/4T locations

)

of the reactor vessel at the peak fluence location.

)

11.5.2 Comparison of fluence determined from dosimetry analysis with original predicted i

values.

11.5.3 Extrapolation of fracture toughness properties to the surface and 1/4T locations of the j

reactor vessel at the peak fluence location.

1 11.6 Deviations - Deviations or Compliance anomalies in procedure from this practice shall be identified and i

d**"*'*d!_"__?__*_"__*_h*?_*_P"*-

END END j

i

(

A-18

1 APPENDIX B SONGS UNIT 2: BASES FOR PLATE CHEMISTRY MEASUREMENTS

ADR 7% Hp June 8, 1992 S-MECH-92-050 Mr. Steve Gosselin Southern California Edison 23 Parker Street Irvine, CA 92718

SUBJECT:

VESSEL PLATE CHEMICAL ANALYSIS SOURCES

Dear Mr. Gosselin:

The purpose of this letter is to provide background information pertaining to beltline material chemistry data for the plates which were used in the fabrication of the SONGS Units 2 and 3 reactor vessel. Recently, differences were noted in the chemical analysis results reported for the SONGS 2 and 3 reactor vessel beltline plates. A review has been performed which identified that these differences arose from the fact that different source information was used. The source information is noted below:

SONGS 2 "CMTR" - Lukens Steel Mill analysis "FSAR" and "CEN-189" - Chattanooga analyses dated 3/20/70 and 11/26/73 SONGS 3 "CMTR" - Lukens Steel Mill analysis "FSAR" - Chattanooga analysis dated 1/25/74 and 3/20/74 "CEN-189" - RPV surveillance program Chattanooga analyses dated 7/16/75 and 5/4/78 In order to respond to the plate chemistry questions of NRC Generic Letter 92-01, pertinent background information is provided followed by a specific recommendation.

First, the Lukens chemical analysis data was provided with the CMTR for information only, whereas Chattanooga analyses were used as the basis for licensing transmittals.

This was done as a matter of C-E practice to maintain consistency of results.

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

ABB Combustion Engineering Nuclear Power Comen.sron Ervneenng, Inc.

P.O Ocm 500 feiephone (203) 688-1911 1000 Prospect He Road Fas (230) 285 9512 Wndsor, Connectcul 0695 0500

w..._..-

Mr. Steve Gosselin S-MECH-92-050 June 8, 1992 Page 2 of 3 Secondly, for both SONGS Unit 2 and 3, chemical analyses were required by both the C-E reactor pressure vessel specification and C-E surveillance program specification. Since these analyses were performed in two separate instances by the Chattanooga facility on the same material, it is ABB C-E's position that the average of these two analyses would be most representative of the plate chemical content.

(Note: For both units, the 'CE Analysis" value is an average of the chemical contents aquired in accordance with the vessel and surveillance program specification.)

Therefore, the recommended chemical composition for both SONGS vessels is the average of the two Chattanooga chemical analyses, provided in Table 1, and titled "CE Analysis".

Should there be any additional questions, please do not hesitate to contact me at (203) 285-3469.

Sincerely, COMBUSTION ENGINEERING, INC.

S. T. Byrne Supervisor, Reactor Vessel Integrity STB /CDS:cds cc:

D. Pilmer (SCE)

B. Chang W. Gahwiller C. Stewart M. Wade STB 060.WP

Mr. Steve Gosselin S-MECH-92-o5o June 8, 1992 Page 3 of 3 TABLE 1 L

ii l

U23 RV BELTLINE REGION PLATE COPPER AND NICKEL CONTENT l

l I

l l

Cu Content (wt %)

l Ni Content (wt %)

ll l

Plate l

l ll l

No.

l CMTR l CE Analysis l

CMTR l CE Analysis l i

l Unit 2 l

l ll l C-s4o4-1 l

o.11 l

o.1o l

o.si l

o.ss l

t l'

l l

l l

l C-s4o4-2 l

o.12 l

o.1o l

o.si l

o.ss l

ll l

l l

l l C-s4o4-3 l

o.12 l

o.10 l

o.s2 l

o.ss l

l l

l l

ll l

C-s4o4-4 l

o.12 l

o.1o I

o.s3 l

o.s2 ll l C-s4o4-s l

o.12 l

o.11 l

o.s3 I

o.s4 l

ll l

l l

ll l C-s4o4-c l

o.12 l

o.io l

o.s4 l

o.s8 l

C ll l

Unit 3 ll I;

l' l C-seo2-1 I

o.os I

o.os I

o.ss l

o.se l

11 l

l l

l ll l C-s8o2-2 l

o.o4 l

o.o4 l

o.se I

o.sv l

C l

l l

ll l C-sBo2-3 l

o.o6 l

o.os l

o.s7 l

o.s8 l

l l

l l

ll l C-s8o2-4 l

o.os l

o.os I

o.se I

o.ss ll C

l l

l l C-seo2-s I

o.o4 l

o.o4 l

o.s2 l

o.ss l

l l

l l

l l

ll

\\

l C-s8o2-s I

o.os I

o.os I

o.ss l

o.s2 l

l u

O

.c.g

.s 1 CDP.iB135TsDN.;G)MS]DN

_..I...

..:., 1;. n. Mos s Analyses' of Core Itc.glon Plates Metallurgical R & D i

l To Specification 00000-PE-110 Department Chattanooga Job No. A-90006,

.;r. R. E. Lorentz, Jr.

Contract 71170

. r. R. D. Bradford Project No. 960001

.. r. H. N. Dinwiddio

.:r. P. C. Kiefer

.:r. S. R. Lowls Iv,la,rch,2 0, 19 74 '

1.tas purchased from Lukens Steel on our P. O. Number 40-820G5 to

.... -is.iA-533. Grado B, Class I and to C. E. Purchase Specification P3F12(d).

-' three intermediate shcIl plates were purchased to specified size of

h!-3/4" x 109-5/16" x 9-11/16".

he !ollowing infonnation is relative to purchased material:

4 1.a b N o.

Heat No.

Item Code No.

Piece No.

I14445 C-7596-1 C-6404-1 215-03 P14446 C-7595-2 C-6404-2 215-03 P14447.

C-7595-1 C-6404-3 215-03

\\

i lealytical samp!cs were obtained e.t 1/4T below ID surface. Table I shows i

4mistry of submitted samples.

l l

/

h J. A. Kosik NJ':me C * '.a ch m ent

TABT.E I Chemir.trv of.ulnnitted Plates C N '\\ '4 C. M t s\\ s\\

q.as A..s 1.nb No. P14 4 47 Lab No. P14445 lab No. P14446 S1

.20

.2G

.27 Sul

.010

.011

.011 P

.009

.010

.009 Mn 1.33 1.39 1.40 C

.22

.20

.22 Cr

.15

.16

.15 Ni

.55

.58

.53 Mo

.57

'. 6 2

.63 9

B

.0001

.0002

.0002 Cb

(.01

,(.01'

(.01 T1

(.01

(.01' 4 01

• Co

.012

.012

.011 Cu

.10

.10

.10

/d

.049

.046

.054 N2

.009

.007

.006 V

.006

.005

.0'05 W

(.01

(.01 4 01 As

.013

.013

.012 I

Sn

.006

.006

.005 1

2r

.00)

.001

.001 lf

s e.J v$).

n fs f. f h /

J Vp D 1-i:

,.. l l r l

.pu. ;a Sd.5 COMBUSTIODJ DRilSSDiij

') Mr. Bill Moss Material Certification Metallurgical R 6 D Customer. Requiremont Depa rt ment fob No. A-90006 l '

Che ttonooga Contract No. 71170 cc: Mr. R. E. Lorentz, Jr.

Project No. 96000'1

/

S.T.B. FEB 2 4 1976

r. R D. Bro ord Mr. H. N. Dinwiddic

'), f,,* /.

Mr. P. C. Kiefer November 26, 1973 s

Lower shell material for the core region was purchased from Lukens Steel on our P. O. No. 40-82066 to ASME SA-533, Grade B,' Class I

~

Specification and to C. E. I. Purchase Specification P3F12(d).

Data relative to the purchased plates:

_La b No.

Heat No.

Item Code Piece No.

P-14068 C-7585-1 C-5404-5 215-02 P-14105 A-67h5-1 C-6404-4

'215-02

~

P-14106 C-7596-2 C-6404-6 215-02 The above plates were purchased to size 9-11/16" x 109-5/16"'x 220-3/4". Analytical sample was obtained from a location of 2" below ID surface of the plate thickness. Chemistry of a'bove material is shown'In

+

Table I.

t c J. A. l'osik IA)':mc attachment

)

TAIll.r.1 C - M b4 -(

C WA' $

q. g otg q

-)

1.ab No. P14060 Lab No. P14105 Iab No. P14106 S1

.22

.25

.21 Sul

.008

.009

.011 Phos

.006

.006

.007 Mn 1.27 1,43 1.38 Car

.20

.24

.20 Cr

.20

.09

.15 Ni

.62

.60

.57 Mo

.57

.59

.59 B

.0001

'.0002

.0002 Cb 4 01

(.01 4 01 V

.003

.003

.004 Co

.516

.016

.015

.11

.09

.10 Cu

0.. '

Al

.046

.037

.027 I

N2

.007

.010

.008 T1

(.01

(.01

(. 01 W

4 01

(.01

q. 01

.005

.006

.010 As S n'

.004

.005

.005 Zr

.001

.001

.001 cd

)','S' i,I' g $ v I Lf,g ho-t f.

c g g, c(%cgvy for tw 4 ~. W tl (su~. F 4 sm. W e.M

~

1.3 K.DEC 0 31976

/

Interoffice Correspondence s

POWER.

s. r.s UFC 0 sy~Io.-

7 SYSTEMS TO:

A. D. Emery SCE II Dds,ign Engineering Reactor Vessel cc:

R. W. DeVane Core Region Chemistry DRV-76-1405

[C-D.B.Grogan/

~

J. J. Koziol November 30, 1976 jpfj R. G. Williams

-sr8 Theattachedanalyses(2 sheets),1[.A.HousetoR.DionBradford,datedNovember 19, 1976 represent the chemical compositions of surveillance material of Codes

. C-6404-1, C-6404-2 and C-6404-3 and their weld seams. The only SCE II analyses

.no.d C-6404-6.t yet submitted are those.of surveillance mater,ial for Codes. C-6404-4, C-6904.,5 an Q

.JJ Dion Bradfo

.h.RDB/dl e

4 8

8 p

4 e

5 I

Interoffice Correspondence i

- f

,Y,-

i

[,5l SYSTEMS POWER cT;,.;.

Subject rrom i

R. Dion Bradford l

Surveillance Program Analysis *.

Metallurgical & Hatcrial:

//

Southern California Edison II Laboratory - Chattanooga Contract No. 71170' Job No. B-38069 Project No. 960001 November 19., 1976.'

Chemical Analysis 7

+.

Lab No'.

P16921 P16922 P16923 7.

Shell i

Intern,ediate Intermediate Intermediate Code

C6404-1 C6404-2* "-

C6404 -

. Neat C7596-1 C7595-2 C7595-1 4

,i l

Car 0.23 0.23 0.25

/

. w:.

Hn 1.38

, 1.43 1.45

.s

..P

.s,

. e..,

O.004 0.005

' r 0.006 s

,*.'.. l.. -l,.,

i

~ /s 0.008 O.009 0.010

.s

. < '. *l Si O.21 0.26

.0.27 Ni 0.58 0.60 s

. '.',

• 0.17,

O.60

.'..'..,'.,t

". i

.- Cr 0.18 0.18, Mo '

O.52 0.58 a ': 0.58

.' ' '. ' " ', ' ' ' ' ~ ' ' ' *: ' ' ',

'l

.y Y

0.00 0 0.003 C.003 Cb

<.01

<.01

<.01

.ll Ti

<.01

.<.01

<.01 j

,', * /

Co O.013 0.012 i

• 0.012

~:

r.

.s Cu 0.10 0.10 0.10

. Y.' "

Al Sol 0.026 0.033 0.032

" '. }..

Al Ins 0.002

'O.001

,',0.001.

/s -

'.,. ?

Al Total' O.028 0.034 0.033 i.

e,.. ? '..

B

<.001

<.001

<.001

,s

,7, W

<.01

<.01

<.01 l.

As 0.002

.0.001 0.002 i

" Sn 0.004 0.003

'O.004

,.i', '.

Zr

<.001

<.001

.<.001

~

Pb

<.001

<.001

.0.0025

~

<.001 Sb

~0.0025

.0.0025 N

0.007 0.005 0.005

\\

h. 0 bows l'

U. A. House WA!!/sh i

=

i L

b 5

t p

y.-.-,-

s -,.,

-,w.. - - - -,

,--.v

-.-v-e.

r-

~ - - - - - ~ + -

y-Interoffice Correspondence 1

em POWER SYSTEMS

.h]1JUL20D77 l To: Mr. J. J. Koziol /

. Contract 71170 Design Engineering i

Surveillance Program.

i cc: Mr. D. B. Grogan Plate Chemistry DRV-77-831 i

July 18, 1977

[C.

/

.h/W

.&Tl ADE Attachment (1): Memo, W. A. House to D. Bradford, dated 3/14/77.

Attachment (2): Memo, W. A. House to D. Bradford, dated 6/08/77.

The chemical analyses given by Attachments (1) and (2) are from the lower she1T plates. This completes all contract chemistry require-ments except for data from a special weldment which will supplement the surveillance program. That data will be forwarded when the

.weldment is completed.

S e

B. R. Moss BRM:mo 4

Interoffice' Correspondence 3

POWER iiEi1 SYSTEMS Sub$cet From To:

D. Bradford Surveillance Program Analysis Metallurgical & Materic Contract No. 71170.

Laboratory - Chattanoot Job No. B-38069 cc: Elaine White Project No. 960001 June 8, 1977

==

Description:==

Plate Code C-6404-5 Heat No. C-7585-1.

Lab No. P-17405 Analysis:

,/C-0.21

'Co 0.014 '

Hn -

1.33 Cu 0.11 P

0.008 A1 0.041 S

0.011 B

<. 001 Si 0.24 W

<. 01 Ni 0.67 Sb 0.0016 Cr 0.25 As 0.003 Mo 0.57 Sn 0.007 V

0.003 Zr

<.001 Cb

<.01

.Pb

<.001

'Ti

<.01 N2 0.009 W. A. House WAH/sh W

1

f.

~

&j ; POWER SYSTEMS

)

Subject

- Trom - Dat2 y,

lf

,c. sinegar Welding Material Certification Metallurgical 6 Materials

/

To pequirements of ASME Laboratory

/,, p, E. Lorentz, Jr.

Section III

"" s. R. Lewis Job Number K-32255 Chattanooga N. Wamack Project Number 960009 S. A. Lewis f-

' " ~ ~~ '

QQ

- 8 O 3 k-. __.

r The following test data is f'or 3/16" diameter bare wire, Type Lo-Co-Phos, Heat No. 90130, Flux Type 0091, Lot No. 0842 (Test No.1389).

\\

l A weld deposit was made using the above heat of wire and tot of flux. Weld-Ing was done in accordece with SAA-SMA-12.12-102. The completed weldment was given a post weld heat treatment of 1150*F for'40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> and furnace cooled m cnner itAPACT AND/OR FRACTURE TESTS TYPE T E t#, 'F VALUES TEMP.*F VALUES NOT CVN Ft/Lbs % Shear _MilsLatExp Drop Weight

-60 16' O

9

-60 1 F

-60*F

-60 15 0

7._

-50

'2 NF i

-60 19 0

11 '

-40 1 NF

-40 20 5

11

-40 28 10 16

-40 32 15 22

-20 85 50 53

+60 132 80 77

-20 88 50 56

+60 149 100 84

-20 76 40 47

+60 123 80 74 1

0 77 40 47

+100 142 100 82 0

75 40 45

+100 148 100 84 0

99 60 52

+100 140 100 82

+20 117 70 74

+20 LOS 60 65

+20 L14 70 74

.1 ALL WELD METAL.505 TENSILE

{

Lab Yleid Strength Ultimate Tensile Elongation Reduction of l

,,po<g ksi Strength ksi in 2"%

Area %

b 10 78.4 91.5

.0 70,0 Arn d l

IMA:Ob

Interoffice Correspondence

/'

PcJ POWER l

.=m i SYSTEMS Subject From

, ~.

i To: Dion Bradford Surveillance Test Metallurgical & Materi f

Projec t No. 960001, Laboratory - Chattanoc i

Job No. B-38069 cc: Peggy Webb Contract No. 71170 March 14, 1977 I

l

==

Description:==

Southern California Edison II, 9-11/16" Lukens Plate Analysis:

Lab No. P-17110 (Ref. P-14105)

P-17111 (Ref. P-14106)

Heat No. C-6735-1 C-7596-2 Code No. C-6404-4 C-6404-6 C

0.25 0.21 Hn 1.47 1.37 P

0.006 O.005 S

0.008 0.009

, Si 0.25 0.20-Ni 0.63 0.58 Cr 0.12 0.19 Ho 0.57 0.53 V

0.003 0.003 Cb

<.01

<.01 Ti

<.01

<.01 Co 0.013 0.011 Cu 0.10 0.10 Al 0.036 0.026 B

<.001

<.001 W

<.01

<.01 Sb 0.0025 0.0022 As 0.002 0.002 Sn 0.006 0.005 Zr

<.001

<.001 Pb

<.001

<.001 N2 0.011 0.009 1

o W. A. House WAH/sh

. =..

APPENDIX C SONGS UNIT 2: BASES FOR WELD CHEMISTRY MEASUREMENTS 1

cyg clu-lsh. 4 641% Wids

/~ C i

Interoffice Correspondence g

5/d

~

POWER

~

[I SYSTEMS S.T.B. APR 1 3 1976

" Design Engineering TO:

J. J. Koziol SCE II' Reactor' Vessel ec:

D. B. Grogsn Core Region Chemistry DRV-76-434 R. W. DeVane R. C. Williams April 6, 1976 Results are attached of the core region as-deposited wcld and chemical analyses required by General Specification No. 00000-PE-110.

i i

Seam No.

. Scam Plate Codes 2-203A Intermediate Long.

C-6404-2 to -3

B Intermediate Long.

C-6404-1 to -2 C

Intermediate Long.

C-6404-1 to -3

~ ~

9-203 Closing Cirth C-6404-1,

-2, -3 to C* 6404-4,

-5, -( !

3-203A Lower Long.

C-6404-4 to -6 B

Lower Long.

C-6404-5 to -6 g,

Lower Long.

C-6404-4 to -5 C

[.

t R. D. Bradfor J

.~

RDB/dl

.l a

O m

1 '

q.

[

9 w-.

, ~ - -., - -

f

/-l I.*

/

tab No.

0-18153 0 18154 D-18155 D-23227 0-17025 0-17026 0-17G

/

Seam No.

2-203A 2-203B 2-203C 9-203 3-203A 37f05B 3-20'l

~

/n M

.84

.91

.'88 1.34 1.27 1.17 1.33 Cr

<.01

<.01

<.01

.15

.05

.05

.06 i

Hi

. 90'

.91

.95

.29

.12

.06

.11 Mo

.23

.24

.25

.58

.52

.39

.54 Cb

<.01-

.01

<.01

.01

<.01

<.01

<.01 s

Cu

.03

.03

.03

.07

.05

, 04 '

.06 s

Phos

.009

.009

.010

.009

.011

.010

.010

_ Car

.065 '

.077

.074

.17

.14

.17

.18 Co

.014,

.017

.015

.016

.009

.007

.009 Si

.32

.36 36

.20

.13

.10

.12 i Sul

.017

.016

.016

.007

.011

.011

.011 B

.0005

.0005

.0005.

<.001

.0004

.0004

.0004 i

Ti

.01

.02

.01

<.01

<.01

<.01

<.01 Al

.001

.003

.002

.017

.004

.002

.004 H2

.017

.010

.008

.040

.008

.006

.005 V

.007

.008

.008

.006

.006

.004

.006 W

.01

.01

.01

.02

.01

.01-

.01

~

As

.012

.012

.011

.007

.013

.011

.014 Sn

.005

.005

.005

.004

.007

.005

.006 Zr

.002

.003

.003

<.001

.002

.002

.002 Pb HD NO NO

<.001 NO NO NO O

I

'I

C 6H. CthcAy 4r In4*

W'l ( b. ) 4 5m. Weld M.K.DEC 0 31576 p

Interoffice Correspondence c

POWER.

s.r.g DEC os g SYSTEMS TO:

A. D. Emery SCE II Dds,ign Engineering Reactor Vessel cc:

R. W. DeVane Core R.egion Chemistry DRV-76-1405 l'O D.B.Grogan/

/

J. J. Koziol November 30, 1976 jpfj R. G. Williams

~5Tb

=

The attached analyses (2 sheets), W. A. House to R. Dion Bradford, dated November 19, 1976 represent the chemical compositions of -surveillance material of Codes C-6404-1, C-6404-2 and C-6404-3 and their weld seams. The only SCE II analyses not yet submitted are those of surveillance mater,ial for Codes. C-6404-4, C-6404-5 and C-6404-6.

QL &

..JJ Dion Bradfo

. h RDB/dl e

f n

e 9

't e

O

=

w-r-

~

i, s

l c.

Lab No.

D26761

.D26762

. Seam 2-236A 236B Places Codes C6404-1 & 3 C6404-2 6 3 Car 0.17 0.17

. i..*

.. ti... ". *

' " ".,. './,.;i,.".

.Mn 1.34 1.38

.~

.Y.

0.003 0.004 l

,P 9 :..4 -

S 0.009 0.009

,i

s. :

• T!.*.e.$;.".v.,2. l

.* '~... *...V:::

.Si 0.21 0.22

.i

....i.

...'.t s:. '

NL O.12 0.07

-.?

• b....{:.' '

1

.Cr 0.09 0.10

.s....- Q;;:... ; ' p'.3:,.2.

,0.

Mo

.0.52 0.54 s,

'..,',.a

... V 0.005 0.005

, ;! f, : I.# :.".-

s

.. '. ~.n.>. '.A. <. /.

..8,,,:,y}.:

?! Cb.

.<.01

'. <. 01 1

'." '..I. ':. ' '.

'. '. '.'.k. 01

.x.T1

.01

" 's

... u :<. k':h ::M,,f' i}:i.;:

.'j.:Co.

l.

0.012 Da019

~ ; ". '.' l..

l*:: [}.4.: :i.'I.,[', ',;'.:6.f l'

.'O.03

. '.. y?. ~ *:

' IC.u

• . 0.04

',D 010

.VA1 So1

..'.. *. s :' m".1. c.S!'.t,..,.

.n. q...'

0.009 0.009

;.~.. '.; ;t.

I.*. i. f e

.l

~

s >

0.002

• Al Ins

. J.l l.",'" 'd~ I,Y:.' !<$s'... ".

-l ; M s'A1 Total O.012 O.012

.. ' ',,' / ') ',q.....'. y.,,, 3. $..'

.: (l.i

[.001 ~

T

.- l* 7 . I..<. 001 7..* B.

.1 v

".:, ?p.':. :,}'-l: ;.:

7.*.

, ' /t,...

. N. I.,;<.01

<.01 e.:;i

!"[y

/V:.:

t

' ^ '<. 0 01.

-N.2.'Q.003 As-

..f

.,.:M.,4.. 4.. e.,.~;s

.'a&z., l' %. 2.

4 < ' '-

".OSn'.

• A O.001

'<.001 0.002 s

1-

..k.001 E.'Ph. ' '

2r s

. W 'r '.. -

i i

• j f.

.r -

. > * '.,vl.%,0*.l <:

. '<.001

<.001 t

• C J." -

.. /2.'f.h[...,@.

'A.I.

'O.0013

^ -0.0014 f.'. /l.

I:.', Sb i.<*[.,,:l.,. ::..;'.:' ln"

• 0.004 0.005 N.

s..

y'..

.s q

s.

.r. -

c

..r.,,.;,T,Qj.h....n..M

,e.

4.....

. f,..

J y,-

f.., '. '

4_ r_.

35

.:,1; M. A. House

,.* l

.. y * *

.,c.;2;': ~. Y. *: ;

. ' s'F

,..e

. ;; ;,%.,.;;. c.,, ".

.s.

.t

.. z.

.. u Y.'. r. ;'.g :,.f ';x:.y+ ';.,

,. g.

s...

.MAU sh r*

. ~.' /..,-

..~.i.M.,. '* ?,,

.. :...?,y..

20 ;, ns.):.

1 a:.. :..

. s..<:"..i,.m

(.

n

. t.

.' :. :.s f,. l,r,5,. v.

'r

u... *..

r

. ;...r. v.

. 1. u *,.<,,.j 4.-

i8

, ~, l :

'.es:g::,..

.,.g.

e s.

,... > > t. o

... r

. s.

s s.

s,

s,

• s r. 5.. ?. -

.. +.'

.... v L. u.

...;.?f.*...

. ). 6 4. *:

t

..,.. y.l -

.f. f -

g.

=

4 a g' '.

e 6

g g

g

... to S MECil 94-001 Page 2 of 7 l.

• • .,/]

DATE

[

<Y, 7/

1 HETALLURGICAL llESEAPdH AilD i

DEVELOPflENT IlUCLEAR' WELDil1G APPL)CpTIONS SECTION 70:

i ATTENTI0ll

-id 'M v U <,, ~

~

f A E s '-

r^!

lc r C

o L

!'IGfe' CCt JOB flul40ER 'E D' /' &

1 CH ilCAL AtlALYSIS OF tilRE-FLUX

_ TEST WELD COUPON sal!PLE l10 (k

g.,g.

i LAB HO.

f7joj,$o TYPE tilRE g, s_

t SIZE tilRE Jgg,

_AT llo.

m,p,3 y,

(--

' FLUX y9 f

./j'jQ LOT H0

.v SI f4 S

e/o

~

r/ l.

HN

/.13 C

.20 H0

, 4,,

CU i

4 Nl i

i

)

W A#

.e-i

- to S MECH 94-001 Page 3 of 7 l

OATE

.5 ' Al ' If HETALLURGICAL RESEARCH AtID DEVELOPflElli TO: f4OCLEAR WELDING APPLICA OliS SECTION ATTENTIOil:

ARMl' oSF T A. Fos,A, DA Jth,Ya MALE.

CC o4 b fee JOB tlUMBER-N 3 2 3.5~ f CHEMICAL At!ALYSIS OF WIRE-FLUX

' TEST WELD COUPON

^

SAMPLE 110, 7g 4

(

LAB H0 Afoygg TYPE WIRE g g.

SIZE \\llRE

" EAT li0 cyoffg FLUX oo9f LOT H0 gyg 1

SI

,/f S

.0/D P

,of, MN j,o C

11 H0

.47 i

NI e

_r 4

i 1

APPENDIX D SONGS UNIT 2: WMCs FOR BELTLINE MATERIALS l

i l

4

r r,m.

/

. d:g CDP.0BUET!BN DDJiBIBM if. :

li -

"~

• .', Nuclear Manufacturin:;

Weldii36 Material Cer1;ification Nuclear Q.tality Superintendent

,and Release for Scotion III

, Engineering Nuclear Welding

• • 4*

• N !'5,'n..

.. c

..i Y

iD Applieations

• r ' * ' ' 'I.'# ' '

"E"'

!G.*!

Y

' ~.,'.,'..

Bay 29 Rod Roon

'l

I Inventory Control

' ' ' f,. [ ". '.,I U.i ^ ' "

/fv///Pf h,h:',, [D,'

. '. Welding Inspection E' );,. - l

' '.., j.'.

-Rod-Rocc-("ct. L b. Ca 1vu)

. '. '.h.. ': '. '. ' - l'

. ;.r..\\ *

.',-D&AT luupecaon~

~...

.s

.:ia.l l. '

, ?..,. '

. r.

• 1

.* ;,, s -l', E.

s

... ~ 'l %s 1.

.',...,.~,.:.a...*..'.r.

.3,~....

\\.

f,.,..

?

~,

The following velding caterial has been tested in accordance with the requirements of SOP,p100-23 31 and teets the recuirecents of the latest

,' ;.. Addenda to Sectica III cf the ASME Code and is released for use on ASME

. '.... Code work only:

...v.

.a

.e

..;: i:. :,;.;; w;.- -

... c...I.. Coated Electrodes (MA)

., '..,..'.4. :l.,

. f.

,'.a ~. t

?'

^

TYPE SIZE HEAT E IM E CONTROL d BRAND

.d 4... s.,;

L,. U$,.*.,..,'... $.'.,' e. %.,j,

• c^,..

. s.

f..

~.a.

r.;l-t.

i. a.

..t.......

3 t '.

,II.

Bare Electredes (OTA (4 G4A)

TYPE SIZE HEAT f BRAIO I

i r

s.

+

g y,

s:,*.

.s.

y r.

l III. Flux Electrode Co:bination (SAA)

. TYPE ELF.CTRODE SIZE HEATS TYPE FLUX IM E 8.- V #

fnO W/4]d-83Ho 4wde co7/

//z.t l

/y-y

• Mn e3m i

. 8-y

• p/w 2,g'/ ff duro

^

. i.

rcert g9

).

- sm/e A%.s ow n

m

. _..... - ~. v. w c m,e s

i.m

%IS CDMBUSTION Dil/ISION

..g T

Subject From - Date Mr. P. C. Kiefer Welding Material Qualification dr. R. Jay to Requirements of ASME Metallurgical Research and dr. S. A. LewisSection III

._.... Development Department dr. S. R. Lewis

._ Job Number D-32255_

Chattanooga dr. R. E. Lorentz, Jr.

Project Number 960009 February 8,1973 (r. G. Porter ir. R. E. Smith WL per

• The following test data is for 3/16" diameter bare wire, type low Cu Ph Heat No. 83637, Flux Type 0091, Lot No.1122

~

os.,

. A weld deposit was made using the above heat of wire and lot of flux was done in accordance with C-E Welding Procedure Specification SA-3 Welding

_ _ The completed weldment was given a post weld heat treatment of

)

for 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> and furnace cooled to 600*F.

~""

' ~ -

IMPACT AND/OR FRACTURE TESTS

)PE TEMP 'Fl VALUE5 i

./

1 TEMP.'F VALUE5

.CVN Ft./Lbs. _ Mils Lat.Exp.

HDT

_ Drop Weichts

+10 153 85

-50 1F 1

+10 131 81

-40 2 NF

+10 125 77

-50*F ALL WELD METAL.505 TENSILE _

L !

Lab Yield Strength -

Ultimate Tensile Elongation in Reduction of Code KSI Strength, KSI 2"

I )

77.2 89.1 29.5

_ Area, %

73.1

~

.. \\\\\\

flhe 1/

DATE / - U-73 I

HETALLURGICAL RT' ARCi AND DEVELOFnt.w.

10 NUCLEAR WELDING APPLICATIONS SECTION 1

ATTENTION:

IGN 4/

TE#

K,n me L

1. >sm ee, JOB NUMDER 9 3E 2 ff CHEMICAL ANALYSIS OF WIRE'-FLUX

- TEST NECD COUPdN;'

SAMPLE No.

j,,g ry jpg o LAB NO.

Jfgogg S/gogg TXPE WIRE g

f,.,, g, g,r.,,gs SIZE WIRE S/fg

,3)f,

• }TNO.

'gggy.~u g3ggo ww FLUX i

99 9 j

_n n oj LOT No.

,,ye jszy S l'

, /f"

, /f I

S.

V

. n o 'r

.oto

/

P..

, co c, -

coa HN j, gy Lp4 C

, n; if

~-

H0

.42

. z; /

Cu o d. V os-V

/

.00 7 -

.on6-g.

O m

INTER-OFFICE CORRESPONDENCE m,...,n.h.3 3

d5634 POWER SYSTEMS

.),

s.,

Nuclear Manufacturing Superintendent Nuclear Welding Applications Nuclear Quality Assurance Bay 29 Rod Room ~

Welding Haterial Control (c/o R. N. Fry)

Welding Inspection s..

a _ s oo *4,.._a_,

i WELDING MATERIAL CERTIFICATION ANDRELEASEFORO.$./df SECTIOd III -

The following welding material has been tested in accordance with the require-ments of SOP #100-23.31 and meets the requirements of the latest Addends to Section III of the ASME Code and is released for use on ASME Code work only:

I.

Coated Electrodes (MA)

TYPE SIZE HEAT #

LOT #

CONTROL #

BRAND

\\

II.

Bare Electrodes (CTA & GMA)

TYPE SIZE HEAT #

BRAND III. Flux Electrode Combination (SAA)

TYPE ELECTRODE SIZE HEAT #

TYPE FLUX LOT #

L.o Cu t o Ph.s Bf16 10l30 OW/

0292 g) ~

O.9f % ' ~

D. G. Binega 33.2 DGB/ap fi.5/Ylt.

gagg S ecrio u c (M_{}(})

i DATE 3*I f"7 C

/

HETALLURGICAL RESEARCH AND DEVELOPl4Elli in RUGA' F F G 't &

f**'tig

/'.3E25~ f

'~

)

n

/c

/

CHEMICAL ANALYSIS OF WIRE-FLUX. TEST WELD SAMPLE f,,. /L C IIO.

7/f'?

1./.D 110 3/ 9 P 9.s-

/-o w IYPE 11 IRE

[,e. pj,,,

SIZE tilRE k"

IIEAT H0

pofy, FLUX gg 9 f

~

LOT NO.

g pg

^ SI

. ig' S

f.)-

.Mo P

.ogg Hti jp.g C

CR

, of ill

,,4 14 0

, (d CD/TA

~

Tl CO CU g4 V

.o06

.)

N 2

FE 4

./

}",

DATE S ~ / 3 ' YJ"

/

REQUEST F0rJ1

'Y NCM QUALITY ASSURANCE t

T0: WAYNE TURflER, DON Bit!EGAR I

JOB NO.: E32255 WET CHE!41 CAL -ANALYSIS OF WIRE sal 4PLE y

R No.

3700 Type Hat').

/q Cus~/df% - 8 41 Size T0/de Ifeat Si

,o6 S

.0/0 P

.00 7 s.

Mn 2.04

• IS C

• 07 Cr

=

04 Ni Ho

.57 Cb/Ta Ti Co Cu

. 0M 1

V

.007 p-N2 s.

pg AL

.030

\\

p,> l t

i f $$1'/ Raw

A B ER M DED Mr. Keith Reeser November 4,1993 Southern California Edison Company S-MECH-93-062 Irvine Operations Center 23 Parker Street, MD 345 Irvine, CA 92718

Subject:

Material Information for SONGS 2 and 3 Reactor Vessel Welds

References:

1)

ABB/CE Letter No. S-MECH-93-049, " Proposal No. 93-241-C1A; Additional Reactor Vessel Material Information for SONGS 2 & 3", C.

Gimbrone, dated September 8,1993.

2)

ABB/CE Letter No. S-MECH-93-059, " Weld Fabrication Records for SONGS Units 2 and 3", D. Walker, dated November 2,1993.

Dear Mr. Reeser:

This letter provides weld wire heat numbers and flux types for the following welds as proposed in Reference 1:

1) The surveillance weld for SONGS Unit 2.

2) Welds 2-203 A, B, and C for the SONGS Unit 2 reactor vessel.

3) The surveillance weld for SONGS Unit 3.

4) Weld No. 8-203 for the SONGS Unit 3 reactor vessel.

The above information was researched using all of the available original fabrication records for these welds which were obtained from the Chattanooga facility (Ref. 2). The requested information is found in Table 1, and two major results of this effort are noted below:

1)

The above welds consisted of either filler metal type Mil B4 or E8018 electrodes as noted under " Filler Metal".

2)

It was determined that repairs were made to welds 2-203A and 8-203.

Informatiori regarding the consumables for the repair welds is included in Table

1. However, an investigation legarding the extent of these weld repairs was not within the scope of this effort.

ABB Combustion Engineering Nuclear Power C'*"'*"""S" Mo,5 P.*,We's?)57*

n cin. no.o Wresor. Comecteut 06954500

S-MECH-93-062 Page 2 of 2 Table 1 - Weld Consumables for SONGS 2 and 3 Reactor Vessel Welds Filler Vessel Weld metal Heat No.

Flux type Lot No.

SONGS Unit 2 surveillance

[ Mil-B4]

90130 Linde 0091 0842

[E8018]

AA0llP 2-203 A,B.C

[E8018]

BOLA 2-203 A (repair)

[E8018]

EOBC SONGS Unit 3 surveillance

[ Mil-B4]

90069 Linde 124 0951 8-203

[ Mil-B4]

88118 Linde 0091 0145

[E8018]

IIAAID 8-203 (repair)

[E8018]

GABFE and FAOJE l

This effort was performed in accordance with the CE Nuclear Services Quality Assurance Manual for Quality Class I work. The contents of this report have been reviewed to insure the accuracy ofits contents. If you should have any questions regarding this report, please contact me at (203) 285-5911 or Mr. Craig Stewart at (203) 285-2294.

Sincerely, Combustion Engineering, Inc.

/

Daniel Walker Staff Engineer

,VfFilFICATION STATUS: COMPLETf De ra!*lr4 Wad dzJgn Hcrmeikn cadrod h tJe $ntnerJ hr. tcon r.fiW to teconp bymese d:

si 4 o!QAM10l, g{ewmlig VcriGcalko o un0 TestFbportNJ.

kkrr.l.*llu, /).J~ [M/ht[

/0//tW//J IntbtnndenIResber

Nanr/Irgdurchio

S-MECH-93-062 Page 2 of 2

=

Table 1 - Weld Consumables for SONGS 2 and 3 Reactor Vessel Welds Filler Vessel Weld metal Heat No.

Flux type Lot No.

SONGS Unit 2 surveillance Mil-B4 90130 Linde 0091 0842 2-203 A,B,C E8018 BOLA 2-203 A (repair)

E8018 EOBC SONGS Unit 3 surveillance Mil-B4 90069 Linde 124 0951 8 203 MilB4 88118 Linde 0091 0145 8-203 (repair)

E8018 GABFE and FAOJE This effort was performed in accordance with the CE Nuclear Services Quality Assurance Manual for Quality Class I work. The contents of this report have been reviewed to insure the accuracy of its contents. If you should have any questions regarding this report, please contact me at (203)-285-5911 or Mr. Craig Stewart at (203)-285-2294.

Sincerely, Combustion Engineering, Inc.

Daniel Walker Staff Engineer y_5RIFICATION STATUS: COMPLEig n.samween-tmacu Y S ?l%wv&e % Li k chxustts1 # 9 olG%10s.

- - WJ Mik awa:nw D.x &JJahdfo ihm emoneuen em

..'.(

('-

. gg.

s:au5 COMBUSTION DIVISION b-Subject From - Date

.i Mr. P. C. Kiefer Welding Material Qualificatida Metallurgical Research and ci' Mr. R. Jay to Bequirem,ents of ASME Development Department l

Section III Chattanooga 1

Mr, S.' A. Lewis Job Ntimber E-32255 Mr. Sr. R. Lewis Project Number 960009 April 26,1973

. Mr. R. E. Lorentz, Jr.

',;. Mr. G. Porter

,... Mr. R. E. Smith s.

The following test dat'a is for 1/4" Electrode,. Type 8018, Lot No. BOli.

'; ' 2 A weld deposit was made using th.e above lot of electrodes., Welding was done

'. ' '..,

• in a'ccordance with C-E Welding' Procedure Specification MA-33B4.

.The, completed weldment was given a post weld heat treatment of 1150*F

• 25*F for 40 Hours and furnace cooled to 600*F.

IMPACT AND/OR FRACTURE TESTS 14 1

TYPE TEMP.*Fl VALUES TEMP.'F VALUE5 NDT l!

CVN FT/Lb Mils fatExp.

Drop Weight J.

+10 106 66

-60 1P

+10 108 72

-50 2 NF

{

+10 105 71

-40 I NF

-60*F i

.0 82 58

-20 0

101 70

'1 NF O

108 75 1

e

_ALL WELD METAL.505 TENSILE i.cb. Yield Strength Ultimate Tensile Elongation in Reduction of

_ Code KSI Strength, KSI 2 ", *A

' Area, %

h FW 66.0 80.5, 31.0 72.0 V f. ' in % n s as

/

h13EE5 CDMBUSTION DIVISION Mr. P. C.'Kiefer

• Weiding Material Qualifica, tion Metallurgical Research a to Requirements of ASME Development Department

c:

Mr. R. E. Lorentz, Jr.

Section III Chattano'oga Mr. S. A. Lewis B-32255 Mr. S. R. Lewis 810556 March 16,1971, Mr. L. Rose Mr. R. B'ryant The following test data is for 1/4" diameter electrodes, type 8018, lot number BOLA.

A weld deposit was made using the above lot of electrodes. Welding was done in accordance with C-E Welding Procedure Specification MA-33B4.

The completed weldment was given a post weld heat treatinent of 1150*F *25*F

~*

for 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> and furnace cooled to 600 F.

Charpy V-Notch Impacts Te'st Code Ft/Lbs. @ +10*F Recuirements JD 69, 87, 74 30 Ft/Lbs @ + 10 F All Weld Metal.505 Tensile I

Yield Strength Ultimate Tensile Elongation in Reduction of KSI

_ Strength, KSI 2 ", %

_ Area, %

73.1 85.6 27.5 69.5 QlV O.

' N.*

MAR 17 W/l

/J.'M. Arnold '

1 JMA:sl R C. K.

D

Attachment I to S MECll 94-001 Page 2 of 7 IIN I eM-UPHUt UUHHESI'UNUENCE s

"iS COMBUSTION DIVISION i

Mr. P. C. Klefer Welding Material Qualification Metallurgical Research and to Requirements of ASME Development Department ec:

Mr. R. E. Lorentz, Jr.

Section !!!

Chattanooga Mr. S. A. Lewis B-32255 Mr. S. R. Lewis

' 81055G Mr. L. Rose lune 8,1971 Mr. R. Bryant The following. test data is for 3/16" diameter bare wire, type B-4, heat number 30137, flux type 0091, tot number 3999.

A weld deposit was rnade using the above heat of wire and lot of flux. Welding was done in accordance with C-E Welding Procedure Specification SAA-33-34.

The completed weldment was given a post weld heat treatment of Il50'r *25'T for 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> and furnace cooled to 600*r.

Charoy V-Notch Impacts Test Code Pt/Lbs..@ +10'F Reautrements NZ 101, 108, 107 30 ft/Lbs @ +10* F i ' -

i All Weld Metal.505 Tens!!e Yleid Strength Ultimate Tensile Elongation in Reduction of KSI

_ Strencth, KSI _,,

2 ", %

Area, %

73.9 87.2 28.5 71.I i

. );f

.... (

J'. M.' Arnold iMA:s1

/

Attachment I to S-MECll-94 001 Page 3 of 7 INIER-OFFICE CORRESPONDENCE m-

"6E COMBUSTION DIVISION Mr. P. C. Kiefer Welding Material Qualification Metallurgical Research and to Require,ments of ASME Development Department cc:

Mr. R. E. Lorentz, Jr.

Section ll!

Chattanooga Mr. S. A. Lewis B-32255 Mr. S. R. Lewis 810556 March 23,1971 Mr. L. Rose Mr. D. Humble The following test data is for 3/16 diameter bare wire, type B-4, heat number 90136, flux type 009), lot number 3999.

A weld deposit was made using the above heat of wde and tot of flux. Welding was done in accordance with C-E Welding Procedure Specification SAA-33-34.

The completeq,weldment was given a post weld heat treatment of 1150'F *25'r for 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> and furnace cooled to 600*r.

$dd'~ h/?C

. Charoy V-Notch Impacts Test Code Tt/Lbs. @ +10'r Reautrement s lE 100, 112, 119 30 f t./Lbs. @ + 10* F All Weld Metal.505 Tensile Yleid Strength Ultimate Tensile Elongation in Reduction of KS1 Strenoth, KSI 2 ", %

Area, %

67.9 81.1 30.0 73.4 l

'49 6 fi n W. O. Norman WON:sl

_ - _ ~ ~. -

.---c 1

APPENDIX E SONGS UNIT 2: MCRs FOR BELTLINE MATERIALS 1

C USTION ENGINEERING, INC. O W. Rocers METALLURGICAL RESEARCH AND DEVELOPMENT DEPT MATERIALS CERTIFICATION REPORT MATERIAL SPECIFICATION _

P3F12(d)

CONTRACT NO. '71170 VENDOR Lukens Steel Company JOB NO. A-97986-001 BS HEAT NO.

C7596-1 CODE NO. C-64 04-1 MATERI AL DESCRIPTION 220-3/4 " x 109-5/16" x 9-11/16"'

Intermediate Shell MILL CHEMICAL ANALYSIS Typp r

M,,

P 5

58 Ni Cr Mo Cb Cu

.21

. l.30

.009 !.013

.21

.51

.47

.11 t

MECHANICAL TESTS I

ULTIMAT E TEST NO.

GAUGE TEST YlELD T EN5f LE ELONG.

REDUCTION I

TEMPERATURE 'F STRENGTH,K51 STRENGTH,K51 IN 2"%

OF AREA '&

i EDT-A

.505 R.T.

66.5 86.5,-

25.0 /

61.6 l

EDT-B

.505 R.T.

65.9 86.3 26.0 65:6 IMPACT AND/OR FRACTURE TESTS TYPE TEMP.'Fl VALUE5 TEMP.

• F VALUE5 NOT CVN Ft/Lbs % Shear Mils Lat.Exp.

Impacts

- 40 7

0 10

- 40 11 0

14

- 40 12 0

15

/

+ 10 56 30 38 Drop Welchts

+ 10 60 30 42 Os

+ 10 56 30 39 0

1F l

+ 40 39 25 3'6

+10 1F

+10*F

+ 40 68 35 54

+20 2 NF

+ 40 70 35 54

+110 105 60 74

+110 104 60 76

+110 117 80 83

+160 145 100 88

+160 134 90 84

+160 153 100 40 ADDITION AL DATA INCLUDlNG HEAT TREATMENT:

(A) 1600 F *25*F 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Water quenched.

(B) 1225 P *25 F 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

(C) 1150 F *25 P 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />. Furnace cooled to 600 P.

The impacts were taken parallel to the major rolling direction of the plate at the 1/4 T level and notched perpendicular to the plate surface.

The teristles were taken in accordance with ASTM A-20-68.

F.,

E-2120 ec: P. Webb (2)

We hereby certily that the foregolag dato is e true copy of the dofo S. R. Lewis s

,,,s,,,,6,,g,,,,,,,,, a i,,,g,,,,,,,,,,,,,i,,,,,,,,,,_

so, d in ih. Co,4 iion M.eollwegical Loboratory.

COMBUSTio:: ENGINEERING, IN R. E. Lorentz, Jr.

f//#~

DY A

f/ ' ' ' 6. %C Krnilid)

).

)

g...

. ',.. METALLURGICAL Hl 5EARCll AND DEYCLOl'MLill OLi'l

)

~.3 088.-

MATERIALS CERTIFICATION REPORT (RfAL 5PCClFICAT10Nyr12 (d).

CONTRACT No._ 71170

,NDOR tul:en : Steel Company

• J00 No.

A-97906-028 IIEAT No.

C7596-1 CODE No. C-6404-1 3.%1ERf AL DESCRIPTION 220-3/4" X 109-5/1G" X 9-11 AG" intermediato Shell (Test Plate

~

l MILL CllEMICAL ANALYSl5 mr e

e,.

P s

se we c.

u.

c6 c,

.21 - 1.30

.009

.013i

.21

.51 47

.11 MECHANICAL TESTS ULTis.u1 E 1EST Ho.

CAUCE TEST YlE LD T E N$lt.E E L O4C.

REDUCTION TEMPERATURE *F STREi.'CTH. K11 STR E t4GTil. KSI IN T*5 oF AREA *%

AY-TA

.505 R. T.

66.2

/

86.3 //

27.0 ', ' 65.2

/

AY-TB

.505 R. T.

65.3 /

86.6 '

27.0 /

65.4 IMPACT AND/OR FR ACTURE TESTS TYPE TEMP,*Fl VALUT5 l TEMP.*F VALUES NOT Charpy Ft/Lhs %Sficar Mils Lat Exo Dron Welohts

+30 46

• 25 34

-30 1 F

+30 37 15 26

-20 2 NT.#

-30*F

+80 58 /

30 4 3. '

1 NT

+30 41 20 30

-10

+80 79 /

45 55'/

+80

' 64 '

35 47

+212 143 100 84

+212 147 100 86

+212 156 100 87 A00lTIOr4 AL DATA INCLUOlnc HEAT TREATa' ANT:

(a) 1600*r

• 2S*r 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Water quenched.

(b) 1225'T

• 25'T 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

(c) 1,'150*r *25 *r 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> furnace cooled to 600*T.

The impacts were token parallel to th'e rnajor rolling direction of the plate at the 1/4T level and notched perpendicular to the plate surface.

The dropwel0 hts and tensiles were taken transverse to'the rnajor rolling direction.

Testin0 was done In accordance with M6P Specif! cotton N-5.5.2.11(b) Add.1 (a).

and Shop Crder A97006 Supplement No.17 F.

[ 2 to cc:

P'. Wcbb

• • "". Led.. L ik* r'*/ clas **llt. *e de's seivids

ui.

• k ' ' ""4 d* ' '"' "'*8 d * h * ""* "" ' ' ' ' ' '

twat s

H. DInwIddIe

,,,,, i,,6, c.,,6,,,,,, u,,,,,,,,,,, t,6,,,,,,,

R.E. Smith S.R. Lcwls couovsitore NCiwCEn 4 INc.

R.E. Lorent:, Jr.

)

[ '

March 21,1974 J.M. Arnold Det

~

v u

c 8IIW - uorcuedx3 IUJoin 9 spunod loof

).

s

]

~.

84ETALLt!RCICAL.1:115EAllCil AND DbYLLUl'MLNi Utl'1 D. R. Moss MATERIAL 5 CERTIFICATION REPORT

_AtATCRIAL SPCCIFICATION P3F12 (<!)

CONTRACT'HO._ 71170 VCt400R 1aiken;Lfiteel Company J00 NO.

A-079n6-028 HEAT NO.

C7596-1 CODE NO.

C-6404-1

{

MTERI AL DESCRIPTION _

220-3/4" X 109-5/l G"X 9;-11/1G" intermediate Shell (Test Plato "C")

MILL CilEMICAL Al4ALY515 tyrr

_ _r.,,,

rs e

s st Ni e,

u.

c6 to

.21 1.301.009-.013i

.21 i

.51

.47 I

.11 i

MECHAritCAL TESTS ULTWATE T($T NO.

cAUCE TEST Yl!LD l

T E N$lLE

[LONG.

REDUCT80 t T(MPERATURE 'F STRENGTil. Kil STR(NCTH. K51, (H TM j oF A R E A *.*

AY-TA

.505 R. T.

66.2

//

86.3 6 27.0 /.

65.2 AY-TB

.505 R. T.

65.3 86.6 #

27.0 /

65.4 IMPA.CT AND/OR FRACTURE TESTS l

Typt Trup. *F YA L UE 5 l TEMP.*F VALUIS l

NOT Charpy Ft/Lbs % Shear Mils Tat Exo Impacts

_ Drop Weights

/

-40 lo 0/

5

-30 1 F #

/

-40 9

0 4

-20 2 NT/

-30'r

-40 7

0 3

-10 1 NF

+10 23 10 19

+10 16 5.

14' Ft/Ibs % Shear _MilsietDeo

+10

./

+40

~20 10 15 3 6~'

15 21

+100 81 50 58

+40 35 15 25

+100 72 50 56 440

. 4 3..

2.0.

30

+100 83

.50 62

+70 63 35 48

+160 119 95

_ 74

+70 60 35 46

+100 113 95 76

+70 44 20 31

+160 117 50 78

+80 77 / 50 55

+212 121 100 75

+80 64 40 44

+212 120 100 75 L90 57 /

35 42

+212 124 100 79 AD0lisuNAL C%TA INCLtCWG HEAT TREATMENTS (a) 1600*F

• 25"r 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Water quenched.

(b) 1225*F

• 25'F 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

i (c) l'150*F *25 *F 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> furnace cooled to 600*F.

The impacts were takcntransverse to the major r'olling direction of the plate at the 1/4T level and notched perpendicular to the plate surface.

The dropwc!ghts and tensiles were taken transverse to'the major solling direction.

Testin0 was donc in occordanco with M&P Specification N-5.5.2.11(b) Add.1 (a),

and Shon Order A97086 Supplement No.17 D em L.2110 ec:

P'. Webb

• • "'.". 6, ii..,..J.,c l, a l.

4.....tu g I, "4"*'**'"'"'"d*"""""'"#*

~

11. D1nwIddIc s.i.44 R.E. Smith

,,,.4 i. 4, c.,,6,,, o, u,,, n,,,,,,,i t.S.....,,,

S.R. b ls C *"U5' '0" E "0"E E "'"

"'C' F

R.E.1.orent=, Jr.

j

/

-lH_

l or _.

//n <f

[

J. Th.' Arnold c4Tc March 21.1974

)

')

Cil Allo DEYCLOl'MCilT Utt'l METALLURGICAL HliSCAl

}

D. R. Moss MATERIALS CERTIFICATI0li REPORT MATERIAL SPECIFICATION,,P3r12 (d)

CONTRACT NO._ 71170 YE,NDOR Lukeng,_ Steel Compar;[.

JOO NO.

A-97986-026 HEAT NO.

C7595-2 CODE No. C-64 04 -2 MATERI AL DESCRIPTIO:4 220,-3/4" X 109-5/10" X 9-11 AG" intermedinto Shell (Test,, Plato

• MILL CllEuiCAL ANALYSIS y pr e

__ in.

vi 1

51 88 ce H.

ch c,.

i

.20 1.34

.010

.015

.29

.61

.58

.12 MECHANICAL TE5TS TEST NO.

cAUCE TEST YlELD r tg ELONc.

R(M@

1(MPERATURE 'F ST RE NGTit. Kit ST A(NGTH. KSI IN 2"'s or AttA t; A2-TA

.505 R. T.

66.8

/

88.0./

26.0 /

67.0 AZ-TB 505 R. T.

67.2

/

88.0 /

25.0 /

66.8 IMPACT A ND/O R FRACTLfRE TESTS Tyrt TtMP. 'F I V& TOES ll T EMP.

• F VALUES NOT i

Charpy Ft/Lbs %Slicar Mils lat Exof Drop Wolohts

$0*F.

Impacts

-40 6

0/

3

-20 1 F-

-40 7

0

• ,3

-10

2. NT/

-40 11 0

6

/ +10 18

'10 13

~

+10 16 5

11 Ft/Lbs % Sheer MilstatDec

+10 13 5

8~'

+100 75 50 55 I

.)

~ '7

'15 25 J +40' 3

+40 23 10 17

+100 68 50 52 f.40..._3 5,,,,,,15,

24

+100 73 50 53

+70 52

- 25 38

+160 101 99 71.

~

+70 47

~~ 2 5 34

+160 SS 95 66 MO.

51.'

2 5.,_i, 40

+160 94 95 67 7,,

.+80 65 40 47

+212 105 100 /

74

+B0 69 /

40 48 /

+212 123 100 80

+80 53 /

30 38 /

+212 117 100 76 ADDiflor4 AL DATA INCLUot#G llEAT TR(ATMENT:

(a) 1600'T A 25*F 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Water quenched.

(b) 1225'T

• 25*F 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

(c) 1,'150*F *25 *F 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> furnace cooled to 600*F.

The Impacts were taken transverse to the major rolling direction of the plate at the 1/4T level and notched perpendicular to the plate surface.

The dropweights and tensiles were taken transverse to'the major rolling direction.

Testing was donc in accordanco with M&P Specification N-5.5.2.11(b) Add.1 (a).

l and Shop C'rder A97986 Stinelement No.17 t.m t-Tito cc:

P'. Webb

• • ""4d"'"d'"""d

8.alik.i vi 6, ik. r. 44 sa, nr.. J.i... viny s,

i. o. 9,.

H. DInwIddIc s,, i,os, c,.6,,o.,, u...ii yi.,i t,i,,,,,,,,,

R.E. Sinith 3.,g, g g3 counumori (Nc stCnisc. Nc.

R.E. Lorentz, Jr.

)

g 'J.M. Kr~n'old oatc March 21.1974 W

,~,,

vw--,r

C $USTIO:-l EllGitlEERl!1G, lilC.

J..W. Its u,1< rn 1

METALLURGlCAL RESEARCil AtID DEVELOPl.tEH1 DEPT

=,, -,,

MATERIAL 5 CERTIFICATION REPORT MATERIAL SPECIFICATION P3F 12(d)

CONTRACT NO.

71170 VENDOR.

1.ul ens Steel Company

)HEATNO.

JOO NO.

A-97986-003 BS C7595-2 CODE NO. _C-6404-2 MATERI AL DESCRIPTION 220-3/4 " x 109-5/16 " x 9-11/16" intermediate Shell l

MILL CHEMICAL ANALYSIS TYPL_

c Ms P

5

$l Nl C,

he Cb Cu

.20 1.34

.010

.015

.29

.61

.58

.12 MECHANICAL TESTS ULTIMATE T,EST NO.

GAUG,E TEST YtE LD TENS tLE E LOi4G.

REDUCTION TEMPERATURE 'F STRENGTH,K51 STREHGTH, K51 IN 2"*3

. OF A R E A 'i EET-A

.505 R.T.

'70.1 90.5-

/

25.0 '

66.4 EET-B

.505 R.T.

69.2 89.8 25.0 66.4 IMPACT AND/OR FRACTURE TESTS TYPE TEMP.'Fl VALUE5 I

TEMP. 'F VALUES NOT l

CVN Ft/Lbs % Shear Mils Lat.E<p.

Impacts f

- 40 9

0 11

- 40 12 0

18

- 4 0.

8 0

10 ll h

N

_ Drop Wefohts

/

+ 10 26 15 21 f[

+ 40 42 25 31 0

1F 1 NF

-)

+ 40 60 40

.,4 4

-10 1 NF 0*F

+ 40 52 30

'46

+10 2 NF

+110 126 80 85

+110 111 70 78

+110 112 70 74

+160 145 95 85

+160 136 90 84

+160 155 100 90 ADDIT 10te At. DATA INCLUDING HEAT TREATMENT:

(A) 1600 F *25 F 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Water quenched.

(B) 1225 F *25 F 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

(C) 1150*F *25*P 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />. Furnace cooled to 600 F.

the Impacts were taken parallcl to the major rolling direction of the plate at the 1 level and notched perpendicular to the plate surface, rho tensiles were taken in accordance with ASTM A-20-68.

Faem E-2120 cc:

P. Webb (2)

We hereby ce, illy that the fo,egola3 dato is o teve c.py of the deio S. R. I.cwis g g,5,g,,6,,g,,,,,g g,,,ni,,,g,,,,,,,,,,y,,,,,,,,,,,,_

T. B. Burton tumed la ihe Combuivi.a Mei.itureic.1 L b..,y.

R. E. Lorentz, Jr.

oucusTios ENGINicRinG, INC.

/,

h

/

.w l

or W. Q. Arnold)

/

M

--r

m _ _.

~__._m____

l

')

METALLUltGICAL ltidliANUl AHU UtVLt.ui'auti uwi n n..Mws MATEftlALS CERTIFICATI0tt RCPORT

')

mTCHIAL 5!'CCirtCATiot1.f31'12 (<1)

CottTRACT 'NO._ 71170 VCNDOR_.

I.til: ens Stdel Qgmany.

' JOO NO.

A-97086-026 HEAT NO.

C7595-2 CODE NO.

C-6404-2 MTERI AL DE5 Cit PTION 220-3/4"X 100-5/lG"X 9-11/1G" intermediate ShcIl (Test Plate -

MILL CHEMICAL At1ALYS15

_nce c

,,f.

e s

sr Ni c,

p.

es c.

.20

1. 3,4

.0?O

.015

.29

.61

.58

.12 MECHANICAL TEST 5 ULTiMAT E lt37 No.

CAUCE Tf5T TIELD TENillt E L ONC.,

R(OuCTio:4 i

TEMPERATUrtE *F STRitfGill. K51 STRinGill. K$l IN 2t of ARI A 3 AZ-TA

.505 R. T.

66.6 4

88.0 /

26.0 4 67.0 AZ-TB

.505 R. T.

67.2

/

88.0 /

25.0 '

66.8 lMP ACT AND/OR FRACTURE TESTS TYPE TruP.*Fl YA(t,T 5 l TEMP.*F val VE S NOT Charpy Ft/Lbs % Shear Mils IAt Exo Drop Weights impacts

+40 41 20 30

-20 1 F

-20*F

+40 42 20 32

-10 2 NF

+40 38 15 27 480 63 40 45-

+80 92 60 62

+80 78 50 54

)

+212 155 100 87 100 [ 88

+212 156

+212 153

.,100 82 l

ADO (TioHAL DATA INCLUDING HEAT TREATMENT:

(a) 1600*F

• 25'T 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Water quenched.

(b) 1225'F * ?S*F 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

(c) 1l150*F *25 *r 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> furnace cooled to 600*F.

The Impacts were taken parallel to the moJor rolling direction of the plate at the 1/4T Icvel and notched perpendicular to the plate surface.

j The dropweights and tensile.9 were taken transverse to'the major rolling direction.

Testing was donc in accordance with M6P Specification N-5.5.2.11(b) Add.1 (a).

and Shop C'rder A97986 Supolement No. l{ 3, F.

t.2D0 ec:

P'. Wcbb

• • "'".". 6, ik.,,.sw im 'n'r.

J.i..... rag 1,.u. o.w,

""'d*'""'

1. 1. ' h ' '"' "" ' W'

whk.J

11. D1nw1ddIo R.E. Smith s.,

a i,, is, c.a,.,i u.i.u.,tu i L.6.....,.

S.R. Lowls coutwion inc minc. N.

R.E. Lorentz, Jr.

/

J. M.' Arnold orig March 21,1974

n

' 'I$.W. _. R'"Er n_

C TOSTI0tt EllCli'EEliiiid[l't15.

METALLURGlCAL RESEARCll At1D DEVELOPl.tEt4T DEPT MATERIALS CERTIFICATION REPORT MATERIAL SPECIFICATION P3P 12 (d)

CONTRACT NO._ 71170 VENDOR _

7.uhonn Steel Company I

JOB NO. A-97986-005 BS HEAT NO.

C7595-1

/

CODE NO. C-6404-3 MATERI AL DESCRIPTION _220-3/4 " x 109-5/16" x 9-11/1G" Intermodinte Shell MILL CHEMICAL ANALYSIS yf1_

C M+

P

$1 Ni C,

Me Ch C,

.22

. l.38

.008

.014

.29

.62

.58 1

.12 MECHANICAL TESTS ULTIMATE TEST NO.

GAUGE TEST YlE LD TEN 5tLE ELONG.

REDUC TIGil TEMPERATURE 'F STRENGTH, K51 STR ENGTH, K51 (N 7"*4 OF ARE A ';

EFT-A

.505 R.T.

73.1 93.3 24.0

..64.8 EFT-B

.505 R.T, 73.1 94.0' 25.0 65.2 IMPACT AND/OR FRACTURE TESTS TYPE TEl.9. 'F l VALUE5 l TEMP.*F VALUES NOT CVN Ft/Lbs % Shear Mils Lat.Ebo.

Impacts

- 40 13 0

14

- 40 15 0

10

- 40 44 20 31

+ 10 45 25 31

+ 10 30 15 20 Drop Wolahts v'

+ 10 41 25 26 0

IF

+ 40 63 40 43 o

+10

+ 40 45 30

'32 2 N.T

+ 40 72 45 49

+110 115 80 79

+110 100 60 73

+110 116 80 80

+160 131 100 83

+160 136 100 82

+160 148 100 83 ADOITION AL DATA INCLUQlNG ltEAT TREATMENT:

(A) 1600 F 25 P 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Water quenched.

(B) 1225 P *25 P 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

'C) 1150 P *25 P 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />. Furnace cooled to 600*P.

The impacts were taken parallel to the major rolling direction of the plate at the 1/

Jcvel and notched perpendicular to the plate surfacc.

Che tensiles were taken in accordance with ASTM A-20-GO.

Fa,m E-?!?0 (2)

We he,eby ce,tily that the lo,egoin.) dote is o t,ve copy el the dolo S. R. Lewis

,,,,,,s,g,,6,,s,,,,s,io,,ais,,,g,,,,,,,,,io,,,,,,,,,,,,,,_

ter.nea la ihe comsviiion Meiono,otcoi L.bo,eto,r.

on R. E. Lorentz, Jr.

COMDUSTiON CNGINCCRING, lHC.

DY

.,c D'? C4

g / / (J.'M. Arnold)'

)

I I ;-

o.

METALLUGCICAL lil0LAl(UI AHu utvta.urm.ro ucei R. Moss MATERIAL 5 CERTIFICATION REPORT

, MATCRIAL 5PECll'lCATIOtt __P31'12 (cl)

CONTRACT NO._ 71170 YC,NDOR.,

lasken: Ster:1 Goinpanyi JOB NO.

A-97906-027 HEAT NO.

C7595-1 CODE NO.

C-64 04 -3 3.MTERI AL DESCRIPTION 220-3/4" X 109-5/16*' X 9-11/1G" intermediate Shell (Test Plate

• l MILL CHEMICAL ANA L Y315 ggr e

M.

P 5

is Ni c.

• * +

c6 c.

.22 1.38

.008

.014

.29

.62 1.59

.12 l

MECHANICAL TESTS ULTIMATC TCST NO.

CAUCE TEST YlELD ytNs:LE ELONG.

Rf DUCitora 1EuPERATURE *F STRfitC1H. K51 STRENGTH.K51 IN 1"'t CF art A %

BA-TA

.505 R. T.

72.5 93.8 25.0 64.3 BA-TB

.505 R. T.

71.3 92.8 25.5 63.8 IMPACT AND/OR FRACTURE TESTS Tyre T r ue. 's F vatuts l TE MP.

• F VALUES HDT Charpy Pt/Lbs y, Shear Mils Dat Exo Drop Wefohts impa cts

-80 10 0

9

-30 1 P

-80 7

L 7

-20 1 NP 1 F

-2 0*F

-80 9

0

'7

-10 2 NF'

+40 39 25 35

+40 41 25 3 4'-

+40 42 25 35

")

+80 98 70 67

,/

480 75 50 54 480 51 30 38

~

ADDITION AL DATA INCLtoir#G HEAT TREATMENT:

(a) 1600*r

• 25'T 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Water quenched.

i 1

(

(b) 1225*r

• 25'T 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

(c) 1l150*r *25 *P 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> furnace cooled to 600*T.

The Impacts were taken parallel to the major rolling direction of the plate at the

[

1/4T level and notched perpend!cular to the plate surface.

The dropweights and tensiles were taken transverse to'the major rolling direction.

Testing was donc In accordance with M&P Specification N-5.5.2.11(b) Add.1 (a).

h and Shop erder A97986 Supplement No.17 r.,,,

F -. r-2170

{

CC.

cc:

P'. Wcbb

• • "",k, g,',"g, ak, p.g,' ;y a:l, g,"'",#*,h****",p",,,,

• • f "4 '"' ' "

g,,,g l

H. D1nwIddIe

,,,,tig, R.E. Smith s,, 3,,x, c 4,u i,,, u,,,is,,,,,,,i t,i,,,,,,,,

S.R. Icwls COM0U5110H [NCIN((SjNC. INC.

R.E. Lorentz, Jr.

i Y du ot_

l J.M. Arnold DAl[ _

Mn_rch 21.1074

__ j

"-- - E'Mrq

~

- - - e o,, y.

.,,,,,,,c,

2. Moos W

HlALS CERTIFICATION REPOR 6

rCHIAL 5PECIFICATION P3rI (d)

ONTRACT t40. 71170 4 IDOR _

Lukens Steel Company JOD NO.'

A-9790G-027 C7595-1 CODE NO.

C-64 04 -3

,T t10.

CRI AL DESCRIPTION _

220-3/4" X 109-5/1G" X 9-11/1G" fr)termediate Shell (Test Plato "C")

MILL CHEMICAL ANALY515 g

__r Mn P

$1 Nt C',

M.

Cb cs

.22 1.38

.008

.014.29

.62

.58

.12 i

)

MECHANICAL TESTS ULTIMATE REST NO.

GAUGE TEST YlE LD TENSILE ELONG.

RE DUC TION TEMPERATURC *F STRENGTH,K51 STRE NGTit. K51 IN 2"%

oF ARE A. !;

,lA-TA

.505 R. T.

72.5

/'

93.8 25.0 64.3 1A-TB

.505 R. T.

71.3 92.8 /

25.5 /

63.8 IMPACT AND/OR FRACTURE TESTS

,; rypt TEMP.*Fl YA LUE S l TEMP.*F VALUE5 NOT b harpy Pt/U)s % Shear Mils Lat Exo Drop Weights l

i pacts

-40 8

0 5

-30 1 F i

(

-40 10 0

6

-20 1 NF F /.

-20"P

/+40 9

0 5

-10 2 NF 10 14 5

9 j

+10 21 10 15~. -

Pt/Lbs' % Shear M11sLatDeo n

+10

.15 5

13 l

/ +40 19 10 14

+100 73 50 55 i

t40 33 20 22

+100 74 50 54

[

'j

+40 30 15 18

+100 71 50 50

+70 46 25 35

+160 97 99 6 2,,

+70 54 30 42

+160 9,4 95 64

~

l

+70 45 25 35

+160 93 95 61

)

,480 69 v' 50 49./

+212 105 100 /

69 l

+B0 60./

50 44 /

+212 100 100 66 i

+80 52 /

50 36 /

+212 103 100 64 4

jh00lT10N AL DATA INCLUotNG HEAT TREATMENT:

l 1

I(a) 1600*F

• 25"P 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Water quenched.

{

1 (b) 1225 *F i 25 *F 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

3 (c) l'150*F *25 'T 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> furnace cooled to '600*F.

HThe impacts were taken transverse to the major rolling direction of the plate at the d l/4T level and notched perpendicular to the plate surface.

The dropweights and tensiles were taken transverse to'the major rolling direction.

Testin0 war; done in accordance with M6P Specification N-5.5.2.11(b) Add.1 (a).

1nd_ Shoo Crder A9798G Soonlement No.17 m E-2110 j P. Wcbb

• • '"of '"oir ilai ihe f "plas 4.i. si. ov. un f ih. J.'.

i31. Dinwiddic

'"' #' # * * ' * * * " * # "' ' "u "' i tu a.4 i, n, c...bo o.a u..., "c.l L.t,.,'.i., r.' ** " '" "'-

R.E. Smith 0.R. Lowls counusitof t ENGINCERING INC.

- l E.E. Lorentz, Jr.

[

DY_

U

/br.r/

l

~

y

/

J. th. Arnold /

DME _

March 21,1974

r

! JUN-04-1992 14843 FROM ABB/CE Chattenooga TO 912032855669 P.09 J. " " 8" METALLUR(

AL RESEARCH AND DEVELOPML DEPT MATERIAL 5 CERTIFICATION REPORT MATERIAL $PECIFICATION P3F12(d)

CONTRACT NO..

71170 VENDOR Lukens Steel Comnany JOB NO. A-9 79 8 7-001 E.S.

HEAT NO.

A 6735-1 CODE NO.C-6404-4 MATERI AL DESCRIPTloN 220-3/4" x 109-5/16" x 9-11/16" Lower Shell MILL CHEMICAL ANALYSIS TYPE C

_ Ma P

5 51 N!

Ce o

th to

.22 1.46

.013!.013

.28

.63

.55 i

.12 2

MECHANICAL TESTS ULTIMATE TEST No.

GAUGE TEST YtELD TEN 5tLd

. ELONG.

REDUCTION TEMPERATURE *F STRENGTH,K51

/ $TRENGTH,KSF IN 2"%

,0F A R E A 's

. MR-TA

.505 R. T.

70, s.// g3.0 ' f ps.0 /,. 64.7 MR-TB

.505 R. T.

70.8 93.0 /

75.0 /

69.7 IMPACT __ AND/OR FRACTURE TESTS TYPE TEMP.'Fl VALUES ITEMP.'Fi VALUE5 NOT CW Ft/Lbs_ % Shear Mils _Lat.Exp.

Impacts 4-40 11 0

6

- 40 17 0

9

- 40 10 /

0 5

Droo Weichts

+ 10 46/

25 32

,/' ;

V l

+ 10 42 20 29 0

1F

+ 10 50 25 35 0*F

+10 2NF

+ 40 67 40 45

+ 40 58 30 41

,+ 40 63 35 42

+110 101 70 72

+110 105 E0 74

+110 102 70 70

+160 124 100 80

+160 139 100 88

-~-

' ~

+160 133 100 84 ADDITION AL DATA INCLUDING HEAT TREATMENT:

A) 1600*F *25 F 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Water quenched.

B) 1225*F *25*F 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

C) 1150*F *25'F 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />. Furnace cooled to 600*F.

he impacts were taken parallel to the major rolling direction of the plate at the 1/4 T evel and notched perpendicular to the plate surface.

he tensiles were taken in accordance with ASTM A-20-68 Form E-2120 We h.e,by certify thet the foregoles dote la. true c py of th. al.te cc: F. Webb (2) furni h.d vi by th. producin miit, or dee reivivia, #ro,,..c sc.

S. R. Lew1s

**d '" 'h. combv.ii.n u..tiorce.t above.,r.

N. Wamack COMBUSTION ENGINEERING, INC.

j R. E. Lore nt z, Jr.

rp

/

&..lY Y.

(bfM BT g

U. M. Arnold) e.ne es j

l

g s

alt h.)

B.R. Moss COMBUSTION ENGINEERING, INC.

T METALLURGICAL RESEARCH AND DEVELOPMENT DEPT

~h 1

MATERIALS CERTIFICATJON REPORT MATERIAL $PECIFICA, TION _ P3P12 (d)

CO,NTRACT NO. _ 71170}./

VENDOR tukens Steel Company JOB NO.

A-97907-001 i

HEAT NO.

A6735-1 CODE NO.

C-64 04 -4_

MATERI AL DESCRIPTION. 220 3/4"X 109 5/16"X 911/16" Lower Shell (Test Plate "C')

MILL CHEMICAL ANALYSIS TYPF f

ps.

P

• $f Nt Cp its Ch C,

.22 1.46-.013

.013

.28

.63 55

.12 l

MECHANICAL TESTS es ULTIAuTE TEST Ho.

cAUCg TEST YlE LD T EN$f(E ELCNc.

REDUCTION TEMP!RATURg.F STR!tlGTH, K11 ST R ENGTH, K$1,.

IN 2"%

CF AREA %

{

TS-TA

.505 R. T.

60.3 V/

91.0 V /

26.0 V 64.4 TS-TB

.505 R. T.

70.1 V'

91.3 V 26.0 V 67.2 IMPACT AND/OR FRACTURE TESTS TYPE TEuP. *F ;

VALUES TEMP.

• F VALUf5 Plof Charpy Pt/Lbs % Shear Mlls Iat Exo

_ Drop Weichts Impacts

+50 39 25 28 0

2 NT

-10*F

. +50 52 30 38

-10

,1 F,

+50 48 30 35 460 58/

40 41.*

/

/

40 37/

+60 53

+60' 62/

50 44/

+70 58 40 41

+7,0 69 50 4a

+70 82-

~60 54 ADDITION AL DATA INCLL'otNG HEAT TREATMENT:

(a) 1600*F

• 25*F 4 hourp. Water quenched.

~

(b) 1225'T

• 25'T 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

(c) 1150*F

• 25'T 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> furnace cooled to 600*F.

The Impacts were taken parallel to the major rolling direction of the plate at the e

1/4T level and notched perpendicular to the plate surface.

t The dropweights and tens 11es were taken transverse to the major rollin ection.

Testing was done in accordance with M&P Specification N-5.5.2.11(b) dd.1 (a),

r E-2tro cc: PS Webb

' * * "'. '.*.f f "'"'I 'b'" ,'" *nt.

.,'e..' 'n. s n ", ",.... ~

' d * " "

• f ns i 4.. b y ik.,,.4,ci,,.

11. D1nwidd1e e

s., i,,w c.,,,6,,n.,, u,,.u.ia L.b.,.

,y.

R.E. Smith

- S.R. Imwls oueustioN E iMEtniNc; inc.'

', R.E. Lorentz, Jr.

9

{ Novem'ber J.M. Arnold 20, 1973 p4rg e

ee e e e enume. am. e enke.es.e e e en e.mesm emm.e -

ea

-,n-------.,v-v.,-

m --

~

JLN-04-1992 14:30 FROM ABB/CE Ch ttenoogs TO 912032853669 P.04 METALLURG' L RESEARCH AND DEVELOPMEb DEPT MATERIALS CERTIFICATION REPORT MATERIAL SPECIFICATION P3F12 (d)

CONTRACT NO. 71170 VENDOR Lukens Steel Company

. LOB NO.

A-97987-001 HEAT NO.

A6735-1 CODE NO.

C-6404-4 MATERI AL DESCRIPTION 220 3/4"X 109 5/16"X 911/16" Lower Shell (Test Plate "C'$

MILL CHEMICAL ANALYSIS TYPF c

M.

P

$1 NI Cr Me Cb Cu

.22 1.46

.013

.013

.28

.63

.55

.12

~

MECHANICAL TESTS ULTIMATE TEST No.

GAUGE TEST YlELD TEN 5 tLE ELONG.

REDUCTION TEMPERATURE 'F STRENGTH,K$l STRENGTH,K51 IN 2'%

OF AREA %

TS-TA

.505 R. T.

68.3 h

91.0 6 26.0 < _64. 4 '

TS-TB_

.5_05 R. T.

70.1 /

91.3 26.0 /

67.2 IMPACT _AND/OR FRACTURE TESTS

~

Type TEMP.or values TEup.0F VALUES NOT i

Charpy Pt/Lbs % Shear Mlls Lat Exo Drop Weights Impacts

' 40 9

0 V 6

-10 1 F

-10*F

-40 9

0 7

0 2 Nr

~

-40 10 0

8

+10 26 15 20

+10 22 10 17

+10 23 10 20

+40 35 15 25 Pt/Lbs % Shear M11slatExp

+40 34 15 25

+40 44 20 33

+110 68 50 51

+70 47 30 36

+110 78 50 56

+70 52 35 40

+110 85 60 60

+70 56 40 41

+160 108 100 #

78' 7

40 48V

+80 62 71T30 - ^107 -

100 75 Q

Q l

+160 96 100 71 ADDITION AL DATA INCLUDING HEAT TREATMENT:

~

(a) 1600 *F

• 25

• F 4 hourp. Water quenched.

(b) 1225"F

• 25*F 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

(c) 1150*F

• 25'T 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> furnace cooled to 600*F.

The impacts were taken transverse the maior rolling direction of the plate at the 1/4T level and notched perpendicu,lar to the plate surface.

The dropweights and tens 11es were taken transverse to the major rolling direction.

Testing was done in accordance with M&P Specification N,5.5.2.11(b) -Add.1 (a).

F.em E-2120 ec:

P'. Webb

• • ""h '"'H '*"" 8"*"las da I" * ** ' M d

f II Dinwiddle

", 'a'in #4 c'-boei u'.+."uurgical Labwomey.

d " b "* '"d * '

"'d*"'#"8"'"*'

f R.E. Smith coMauSTION ENOfNEERING, INC.

S.R. Lewis

, R.E. Lornntz, Jr. *

~

/ ']N

. M. Arnold ovember 20, 1973 DATg

JLN-04-1992 14:50 FR0f1 ABB/CE Chattcnoe a

,-. I. W. Rootrs

'"*"*""'"-*p'--"""'

TO 912032855669 P.16

~"

UURREUTED UUM METALLURC AL RESEARCH AND DEVELOPME DEPT May 25,1971 MATERIALS CERTIFICATION REPORT MATERIAL 5PECIFICATION P3F12(d)

CONTRACT NO. 71170 VENDOR Lukens_ Steel Company JOB NO.

A-97987-003 B.S,

HEAT NO.

C-7585-1 CODE NO. C-6404-5 MATERI AL DESCRIPTION 220-3/4" x 109-5/16" x 9-11/16" Lower Shell MILL CHEMICAL ANALYSIS TYPE f"

Ma P

58 N1 Cr W

Cb Cu

.19 1.35..015

.013,.23

.63

.56

.12 MECHANICAL TESTS ULTIMATE TEST No.

CAUGE TEST YtELD TEN $tLE ELONG.

REDUCTION TEMPERATURE 'F STRENGTH,K51 STRENGTH,K51 IN 2**T.

OF A R E A *.*

M S-TA

.505 R. T.

72.0

/

92.3 '

25.0 /

__6 7. 4 MS-TB

.505 R. T.

71.6

/

92.0 /

25.0 /

67.2 IMPACT AND/OR FRACTURE TESTS

[

TYPE TEMP.'F VALUE5

.l TEMP.*F VALUE5 NOT

~

Ft/Lbs % Shear Mils _ Lat.E:co.

CW Impacts

- 40 9

0 6

- 40 15 0

10

- 40 11 0

7 Drop Weights._

+ 10 26 15 18

+ 10 35 20 24

-20 IF

+ 10 24 15 19

-10 IF

-10 F

+ 40 62/

35 44 0

2NF

+.40 83/

40 58

+ 40 84/

40 60

+110 126 80 75

+110 116 70 74

+110 112 70 72

+160 141 100 84

+160 134 100 82

~~"~

~-

~

+160 127 95 80 ADDITION AL DATA INCLUDING HEAT TREATMENT:

A) 1600*F *25*F 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Water quenched.

B) 1225 F *25*F 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

C) 1150 F *25*F 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />. Furnace cooled to 600*F.

he impacts were taken parallel to the major rolling direction of the plato at the 1/4 T

evel and notched perpendicular to the plate surface.

Jhe tensiles were taken in accordance with ASTM A-20-68.

~~'

F.,m E-2120

w. h.e.by eertif y th., ih. s r...ine d t. i.. it con. ik. d.

cc: P. Webb (2) fel.hed v. by th.,r.ducia, miti..e deve e,..I,W h.. i > -

S. R. Lewis

** d '" ' h' C'*b "'"** *' *l 3 "'O ' *l '* 6' 7 -

g\\ [s N. Wamack coMausTies ENciN iNG Nc.

R. E. Lorentz, Jr.

k' BY t]. M. iU nO10)

Mav 7K. 1471

s B.R. Moss COMBU5 TION ENGINEERING. INC.

t i

METAll.URGICAL RESEARCH AND DEVELOPMENT DEPT MATERIAL 5 CERTIFICAJtDN REPORT

~

CONTRACT NO. 71170 MATERIAL SPECIFICATION P3F12 (d)

VENDOR Lukens Steel Company JOB NO.

A-97987-002

^

l HEAT NO.

C7585-1 CODE NO.

C-6404-5 MATERI AL DESCRIPTION 220 3/4"X 109 5/lG"X 911/16" Lower Shell (Test Plate "C")

MILL CHEMICAL ANALYSIS 1YPF f"

f.8 P

S St HI Cr 84 Ch ev

.19 1.35

.015

.013

.23

.63

.56

.12 MECHANICAL TESTS ULTIMATE TEST NO.'

CAUCE TEST TIELO TEN 5tLg E'.ONG.

R E DUCTION TEMPERATURE *F STREttcTil K51 STRENGTH.K11 IH 2"g of A R E A +.-

TT-TA

.505 R. T.

68.3 89.1 /

26.0 #

68.9 t

TT-TB

.505 R. T.

68.3

/

88.6 /

27.5 - '66.9 IMPACT AND/OR FRACTURE TESTS TYPE TEMP 'F!

VALU*$

TEMP.eF VALUES l

NDT j

?

Charpy Pt/Lbs % Shear Mils lat Exp Droo Welehts l

l Impacts A,

+40 33 15 20

-30 1 F

+40 38 20 21

-20 1 F 1 NT

-20*F 440 47 25 34

-10 2 NF

+60 54 / 25 39 /

37p 460 50/j 25

)

+60 62 30 42 g

l

+70 70 40 46

+70 93 50 64

.+70 83 45 54 f

ADDITION AL DATA R4CLUDING HE AT 1REATMENT:

(a) 1600*F

• 25'F 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.s. Water quenched.

(b) 1225'r

• 25'T 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

(c),1150*F

• 25'F 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> furnace cooled to 600*F.

The impacts were taken parallel o the major rolling direction of the plate at the 1/.4T level and.6otched perpendicular to.the plate surface.

[

The dropwelghts and tensiles were taken transverse to the major rolling direction.

Testing,was done In accordance with,M6P Specificatl,on N-5.5.2.11(b) Add.1 (a).

i Fam E-2120

. We hereby certily thet the leregeleg date la e teve cope el the Jefe p' g gg g

Iwnished vs by the peedweleg adll, ee Jefe saoulflag lese testa pee i.

II. D1nwiddie e,,

4 i,,,5, c 5,,,i,, u.,,ii.,;,,i t,g,,,,,,.

j R.E. Smith l

c@sV5TroH NGIN E E RI.

INC..

S.R. Iowl' r I s

, R,.E. Lorentz, 'Jr,.

gg

}. M. Arn,old November 20. 1973 og e

JUN-04-1992 14:48 FROM y - CE.C.hs.t.t.cno.o. 9 3... -_..

.TO 912032855669 P.14 ABB/

s.n. muoe METALLURGl L RESEARCH AND DEVELOPMEN DEPT MiTERIALS CERTIFICATION REPORT MATERIAL SPECIFICATION P3F12 (d)

C'ONTRACT NO. 71170 YENDOR Lukens Steel _ Company JOB NO.

A-97987-002 HEAT NO.

C7585-1 CODE No.

C-6404-5 MATERI AL DESCRIPTION 220 3/4"X 109 5/16"X 911/16" Lower Shell (Test Plate "C")

MILL CHEMICAL ANALYSIS

~

vv Pr_ _

e p-p s

si Ni ce ue cs cu l

.19 1.35

.015

.013

.23

.63

.56

.12 1

1

~

MECHANICAL TESTS IENLE ELONG.

REDUCTior TEST NO.

CAUGE TEST M LD TEMPERATURE *F STRENGTH, K11 STRENGTH, K$1 IN 2**%

OF AREA 1

~

TT-TA

.505 R. T.

68.3 //

89.1 C 26.0 /

68.9 TT-TB

.505 R. T.

68.3 /

88.6 '

27.5 /

66.9 IMPACT AND/OR FRACTURE TESTS TYPE TE MP. op l VALUES TEMP.*F I VALUES I

NOT Charpy Ft/Lbs % Shear M11s lat Exo Drop Welohts _

j Impacts

.-40 10 0-5

-30 1 F

-20*F

-40 9

0 5

-20 1 NF /1 F

-40 8

0 4

-10 2 NF j

+10 18 5

18

+10 15 5

13 Ft/Lb_s % Shear Mils Lat Ext

+10 14 5

14

+110 81 50 60

+40 25 15 20

+110 84 50 59

+40 26 15 22

+110 87 50 61

+40 23 15 19

+160 103 90 65

+60 47 30 3'6

+160 105 90 70

+60 54 35 42

+160 115 90 72

+60 61 35 50

+70 66V 40 48 /

.t.212_

122

,100 ' 81

~

~

+70 72 V 45 53 /

+212 116 100 74

+70 55 V 35 44 /

+212 116 100 71 ADDITION AL DATA INCLUDtNG NEAT TREATMENT:

(a) 1600 *F

• 25 *F 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.s. Water quenched.

(b) 1225*F

• 25'F 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

(c) 1150*F

• 25'F 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> furnace cooled to 600*F.

The impacts were taken transverse"to the major rolling direction of the plate at the 1/4T level and notched perpendicular to the plate surface.

The dropweights and tensiles were taken transverse to the major rolling direction.

Testing was done in accordance with M6P Specification N-5.5.2.11(b) Add.1 (a).

F E 2120 c c *-

P'.. Webb

• W7 """Y N " h* '*" "5 "' ' ' ' '" "" '" " "

furitish.d us by the pr.docing mill, er det. teanttleg (egm test pef-H. Dinwiddio

,,,,,,,a i,, th. combo.n.,i u.t.um.1 L.bo,

,y.

R.E. Smith

.S.R. Irwis C

Wl0N ENGlHEERING INC.

, R.E. Lorentz Jr.

g g T.Mr Arnold DATE V November 20, 1973

BUSTibN EbGlhEERING, INC.

/

C

. J. W. Rogerff, I

METALLURGICAL RESEARCH AND DEVELOPMENT DEPT MATERIALS CERTIFICATION REPORT MATERIAL SPECIFICATION P3F12(d)

CONTRACT NO.

71170 VENDOR Lukens Steel Company JOB NO A-97987-005 B.S.

HEAT NC.

C 7596-2 CODE NO.

C-6404-6 MATERI AL DESCRIPTION 220-3/4" x 109-5/16" x 9-11/16" Lower Shell MILL CHEMICAL ANALYSIS TYPF c

un P

5 51 NI Cr Me Cb Cu

.19 1.31

.008l.012

.23

.54

.52

.12 l

MECHANICAL TESTS ULTIMAT E TEST NO.

GAUGE TEST YlE LD TENSILE ELONG.

R E DUCTION TEMPERATURE *F STRENGTH, X51 STRENGTH,K51 IN 2"';

OF AR E A ti MT-TA

.505 R.T.

66.7 /5 R7_0 /.

76.0 / / 66.4 MT -T B

.505 R.T.

67.3 /

87.4 /

26.0 /

6'6.R IMPACT AND/OR FRACTURE TESTS TYPE TE MP. 'F l VALUES l TEMP.'F VA LUES NOT s

Shear Mils Lat.Eip.

CVN Impacts

- 40 9

0 8

- 40 12 0

12

- 40 19 0

14 Drop Weights 61[/5.

30 48

+ 10 70

+ 10 25 41

+ 10

-0 IF 64 25 44

+ 40 56 30 42 0

IF INF 0,F

+ 40 84 40 58

+10 2NF

+ 40 84 40 60 4110 136 80 85

+110 126 70 80

+110 128 80 82

+160 151 100 89

+160 167 100 92

+160 161 100 90 ADDITION AL DATA INCLUDING HEAT TREATMENT:

A) 1600 F *25 F 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Water quenched.

'B) 1225 F *25 F 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

'C) 1150 F *25 F 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />. Furnace cot.r.: u

'F.

.'he impacts were taken parallel to the major rol4irg direction of the plate at the 1/4 T evel and notched perpendicular to the plate surface.

he tensiles were taken in accordance with ASTM A-20-68.

Form E-21?O Fa hereby Cetilly that the foregolmg defe 13 e true copy of the date CC* F. W Cbb (2)

Iwnished us by the producl@HI, w dato resulting from te ste per-S. R. Lewis

"" d 3 " ' h' C '"'" ' "*" ""' U "' ' ' " I '* b " r -

N. Womack counU5 Tion ENGINEERING, INC.

R. E. Lorentz, Jr.

()Y N

ff

'(f.

.N I" % r tirilri l

~-

e"

• G) 4E!)

~

/

B.R. Moss COMBUSTION ENGlHEERING, INC.

METALLURGICAL RESEARCH AND DEVELOPMENT DEPT

.hv MATERIALS CERTIFICATION REPORT

,r MATERIAL SPECIFICATION P3F12 (d)

CONTRACT NO, 71170 i

VENDOR Lukens Steel Company JOB NO.

A-97907-003 HEAT NO.

C7596-2 CODE NO._ C-6404-6 MATERI AL DESCRIPTION 220 3/4"X 109 5/16"X 911/16" Lower Shell (Test Plate "C')

MILL CHEMICAL ANALYSIS YYPF r

M.

P 5

51 Nt Cr M.

rh Cu

.19 1.31

.008

.012

.23

.54

.52

.12 MECHANICAL TESTS ULTluAT E ELONG.

R E DUCTION TE57 YlELD 1EN51(E TEST NO.

CAUCE TEMPERATURE 'F STRENG1H,K51 ST RENGT H. K5I IN 2".

OF ARga r.

T U-TA

.505 R. T.

64.9

/

. 84.7

/

27.0 66.9 T U-TB

.505 R. T.

63.9

/

83.2 /

2 7. 0./.~66.1 IMPACT AND/OR FRACTURE TESTS TEMP..p' VALUE5 NOT TYPE TEup.*F' VALUE5 Charpy Ft/Lbs % Shear Mils lat Exp Droo Welohts

/*

' +50 83 y 40 56 '

-20 1 F

-10 1 Nr. d F

-10 F y

/j l

+50 76 35 51 7

+50 61 30 44 0

2 NF

+70 102 50 68

+70 66 30 44 n.

\\~/

+70 88 40 60 I

I f

6 ADDITION AL DATA INCLUOfNG HEAT TREATMENT:

(a) 1000*F

• 25'T 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.s. Water quenched.

(b) 1225'T A 25'F 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

(c) 1150*r

• 25'T 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> furnace cooled to 600*F.

The Impacts were taken parallel to the major rolling direction of the plate at the f

1/4T level and notched perpendicular to the plate sur ace.

The dropwelChts and tonslies were taken transverse to the major rolling direction.

Testing was donc in accordance with M6P Specificati.on N-5.5.2.11(b) Add.1 (a).

i

'd

F.,. E-2170

'"'"4****'*'.'**d''"'

• * "*"'4. 6, ih. r,'.4., i,"3,'ni..,'4

.....In ", ", '. =.e. P cc:

P'. Webb e

1 s,.i.i II. Dinwiddic s.,

4i. 6. C 6..n u...ti,,r..t L.6 t

R.E. Smith c wTion ENGIN E RlNC, ]N j'

S.R] Lewis g

, R.E. Lorentz, Jr; J. M. Arnold November 20. 1973 OATE j

i l

r,

(h (f-i B.R. Mrs COMBUSTION ENGINEERING, INC.

METALLURGICAL RESEARCH AND DEVELOPMENT DEPT a

MATERIALS CERTIFICATION REPORT MATERIAL $PECIFICATION_ P3F12 (d)

CONTRACT NO._ 71170 VE,NDOR Lukenn Steel Company JOB NO.

A-97987-003 *

~

HEAT NO.

C7596-2 CODE NO.

C-G 4 04-6 MATERI AL DESCRIPTION 220 3/4"X 109 5/16"X 911/16" Lower ShcIl frost Plate "C1 a

MILL CHEMICAL ANALYSl5 TYPF r

m P

1 51 Ni ce M,

ch c,,

.19 1.31

.000

.012

.23

.54

.52

.12

(

MECHANICAL TESTS TEST No.

GAUCE TEST YlELD ENS LE ELONG.

R E DUCTION TEMPERATURE *F STREllGTH. Kil STRENGTH.K51 IN 2**%

OF ARE A %

T U-TA

.505 R. T.

64.9 84.7

27.0 -

66.9 i

T U-TB

.505 R. T.

63.9

/

83.2 '

27.0 e 66.1 IMPACT AND/OR FRACTURE TESTS TYPE TEMP *Fl VALUES TEMP.*F vat.UES NbT Charpy Ft/Lbs % Shear Mils lat Exp Drop Wolghts l

Impacts

. 40 4

0 7 4

-20 1 F f

p *F

-40 9

0 6

-10 1 NF 1F

-10

-40 6

0 5.

0 2 NF

+10 14 5

13 l

+10 16 5

14 E

+10 13 5

12 f

+40' 28 15 23

[

22 Ft/Lhs % Shear Mils lat Ext i

+40 27 15

+40 27 15 24 I

+50 617 '30 46

+160 116 90 78

~

+50 54V 25 40 '

+160 115 90 75 5

+50 65 v 30 47 '

+160 118 90 78 3'

+110 85 60

• 61

+212 128 100 80 5

j

+110 73 50 52

+212 124 100 76 i-

+110 94 70 59

+212 121 100 77 R

ADDITION AL DATA INCLU0iNG HEAT TREATMENT:

[

(a) 1600*F

• 25'r 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Water quenched.

ji

~

(b) 1225'F A 25'T 4 hows.

E l

(c) 1150*F

• 25*F 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> furnace cooled to 600*F.

i The impacts were taken transverse to the major rolling direction of the plate at the 5

1/4T level ar}d notched perpendicular to the plate surface.

1 The dropweights and tensiles were taken transverse to the major rolling direction.

ll Testits was done in accordance,wlth M&P Specification N-5.5.2.11(b) Add.1 (a).

{

r. E-2iro 8:

cc:

P'. Webb

• • "*"""'"*""*""8'*"""d

5 f

i.h.4 n by sh.,,.4.ci, ; sil,., 4

!!. D!nwiddie 3,

4 i.h. C,,6 g.,,ii.,,;,,,.......i i., s,

.... e.,-

-2 t,6,,,,,,,

1

~

.I

. R.E. Smith

]f.

l cotASU5 flora ENGIN E 4 tNG, INC.

3 g g3 j'

, R.E., Lorentz. Jr.

'J. M.' Arnold f

I DATE

• November 20, 1973

4

\\

- 1 (m

3 i

APPENDIX F 1

i.

SONGS, UNIT 2: UNIRRADIATED C DATA

' FOR PLATES AND WELDS I

9 I

(

2 k

- - - ~ -

---

a---e e -

.,n.,

x.--

a r,-

a u-m-r,

-m-r-,,

l Table F-1 Charpy V-Notch Test Results For Unit 2 Plate C6404-1 (TL), MCR Data spec 1 Men TEMP rwenct

1ATrnA1, FRAct ID TEST IMPAc7 ERP APPEAA (F)

(ft-lb)

(ell)

(1) 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 5

10.00 18.00 14.00 S.00 6

10.00 20.00 15.00 10.00 7

40.00 30.00 21 00 15.00 0

40.00 35.00 25.00 15.00 9

40.00 43.00 30.00 20.00 Ab 10 70.00 ss.00

.mee4P.08 4e,+0 35.00 g/97 t

11 70.00 60.00 48.00 35.00 12 70.00 44.00 31.00 20.00 13 00.00 77.00

$$.00 50.00 14 00.00 64.00 44.00 40.00 15 00.00

$1.00 42.00 35.00 16 100.00 01.00 St.00 50.00 17 100.00 72.00 S6.00 50.00 10

. 100.00 03.00 62.00 50.00 19 160.00 119.00 74.00 95.00 20 160.00 113.00 76.00 95.00 21 180.00 117.00 70.00 90.00 x

22 212.00 121.00 15.00 100.00 23 212.00 120.00 75.00 100.00 24 212.00 124.00 19.00 100.00 F-1

Table F-2 Charpy V-Notch Test Results

(.

For Unit 2 Plate C6404-2 (TL), MCR Data SPECIMEN TEMP ENERCY LATERAL FRACT

+

ID.

TEST IMPACT EXP APPEAR (F)

(ft-1b)

(mil).

(t) 1

-40.00 6.00 3.00 0.00 2

-40.00 7.00 3.00 0.00 3

-40.00 11.00 6.00 0.00 4

10.00 18.00 13.00 10.00 S

10.00 14.00 11.00 S.00 6

10.00 13.00 8.00 5.00 7

40.00 37.00 2$.00 15.00 0

40.00 23.00 17.00 10.00 9

40.00 35.00 24.00 15.00 10 70.00 S2.00 30.00 25.00 f

11 70.00 47.00 34.00 25.00 l

12 70.00

$1.00 40.00 25.00 13 80.00 65.00 47.00 40.00 14 90.00 69.00 40.00 40.00 15 80.00 53.00 30.00 30.00 16 100.00 75.00 SS.00 S0.00 17 100.00 60.00 S2.00

$0.00 le 100.00 73.00 53.00

$0.00 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 22 212.00 105.00 74.00 100.00 23 212.00 123.00 40.00 100.00 24 212.00 117.00 76.00 100.00

(

F-2

.W f

Table F-3 Charpy V-Notch Test Results

(

For Unit 2 Plate C6404-3 (TL), MCR Data EPECIMEN TEMP ENEACY 1ATERAL FRACT 10 TEST IMPACT EIP APPEAR (r)

(ft-1b)

(all)

(t) 1

-40.00 0.00 5.00 0.00 2

40.00 10.00 6.00 0.00 id lyfsyN 3

-40.00 9.00 4,*0 5'.06 0.00 4

10.00 14.00 9.00 5.00 5

10.00 21.00 15.00 10.00 6

10.00 15.00 13.00 5.00

10. bb Y

7 40.00 19.00 8+r*0 Jj,td 9thee-fj o

40.00 33.00 22.00 20.00 21 140.00 93.00 61.00 95.00 1

10 70.00 46.00 35.00 2$.00 l

f 11 70.00 54.00 42.00 30.00 12 70.00 45.00 35.00 25.00 13 00.00 69.00 49.00 50.00 14 00.00 40.00 44.00 50.00 i

15 00.00 52.00 34.00 30.00 1

16 100.00 73.00

$5.00 50.00 j

17 100.00 74.00 54.00 50.00 10 100.00 71 00 S0.00 30.00 19 160.00 97.00 62.00 99.00 20 160.00 94.00 44.00 95.00 fff 9

40.00 30.00 10.00 22 212.00 10$.00 49.00 100.00 23 212.00 100.00 66.00 100.00 24 212.00 103.00 44.00 100.00 l

F-3

Table F-4 Charpy V-Notch Test Results

(

For Unit 2 Plate C6404-4 (TL), MCR Data sFECIMEN TEMP EWERCT LATERAL FRACT 10 TEST IMPACT EMP APPEAR (F)

(ft-1b)

(all)

(t) 1

-40.00 9.00 6.00 0.00 2

-40.00 9.00 7.00 0.00 3

-40.00 10.00 0.00 0.00 4

10.00 26.00 20.00 15.00 5

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 52.00 40.00 35.00 12 70.00 56.00 41.00 40.00 13 00.00 42.00 40.00 40.00 14 00.00 66.00 50.00 40.00 15 30.00 60.00 53.00 40.00 16 110.00 60.00 51.00 50.00 17 110.00 70.00 56.00 50.00 is 110.00 05.00 60.00 60.00 19 160.00 100.00 10.00 100.00 1

20 160.00 107.00 75.00 100.00 21 160.00 98.00 11.00 100.00 F-4

)

~

Tabic F-5 Charpy V-Notch Test Results f

\\

For Unit 2 Plate C6404-5 (TL), MCR Data l

1

+

1 sPsctMtw Tswr twencY 1AtanAr.

PRACT ID TEST IMPACT E2P,

APPEAR (F)

(ft-lb)

(mil)

(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

10.00 10.00 10.00 3.00 5

10.00 15.00 13.00 S.00 4

10.00 14.00 14.00 S.00 7

40.00 25.00 20.00 15.00 0

40.00 26.00 22.00 15.00 9

40.00 23.00 19.00 15.00 M

46.46 I

10 54,40 47.00 36.00 30.00

$l 40.00 11 84190 34.00 42.00 35.00 40.0b l

12 44349 61.00 50.00 35.00 13 70.00 66.00 40.00 40.00

)

14 10.00 72.00 53.00 45.00 1

15 70.00 SS.00 44.00 35.00 16 110.00 31.00 60.00 50.00 17 110.00 04.00 19.00 50.00 10 110.03 07.00

$1.00 S0.00 l

19 150.00 103.00 85.00 90.00

)

20 160.00 10$.00 70.00 90.00 21 160.00 115.00 72.00 90.00 22 212.00 122.00 01.00 100.00 23 212.00 116.00 74.00 100.00 l

11.60 24 212.00 116.00

+e,44 100.00 visi

(

F-5 i

i

}

Table F-6 Charpy V-Notch Test Results For Unit 2 Plate C6404-6 (TL), MCR Data t

SPECIMEN TEMP ENERCY LATERAL PRACT ID TEST IMPACT EXP APPEAR (P)

(ft-1b)

(mil)

(t) 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 4

10.00 14.00 13.00 5.00 5

10.00 16.00 14.00 5.00 6

10.00 13.00 12.00 5.00 7

40.00 20.00 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 45.00 30.00 11 50.00 54.00 40.00 25.00 12 50.00 85.00 47.00 30.00 13 110.00 05.00 61.00 60.00 14 110.00 73.00 52.00 50.00 15 110.00 94.00 59.00 70.00 16 160.00 116.00 70.00 90.00 17 160.00 115.00 75.00 90.00 le 160.00 110.00 78.00 90.00 19 212.00 128.00 00.00 100.00 20 212.00 124.00 76.00 100.00 1

21 212.00 121.00 77.00 100.00 l

F-6

Table F-7 Charpy V-Notch Test Results

(-

For Unit 2 Weld Scam 9-203 (Heat #90130),MrAR Data w,4c, i v4 i

SPse! MEN TEstP twencY 1ATEnAL rnAc7 ID TEST IMPACT IIP APPEAR (F)

(ft-1b)

(mil)

(t) 1

-60.00 16.00 9.00 0.00 l

2

-60.00 15.00 7.00 0.00 3

-60.00 19.00 11.00 0.00 4

-40.00 20.00 11.00 S.00

-40.00 20.00 16.00 10.00 6

-40.00 32.00 22.00 11.00 7

-20.00 05.00 S3.00

$0.00 4

0

-20.00 90.00

$6.00 50.00 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 52.00 60.00 13 20.00 117.00 74.00 70.00 14 20.00 105.00 65.00 40.00 15 20.00 114.00 74.00 70.00 16 60.00 132.00 77.00 00.00 17 60.00 149.00 84.00 100.00 18 60.00 123.00 74.00 00.00 19 100.00 142.00 02.00 100.00 20 100.00 140.00 94.00 100.00 21 100.00 140.00 92.00 100.00 1

I F-7

e Table F-8 Charpy V-Notch Test Results

(

For Unit 2 Plate C6404-2 (LT), CE Baseline Data

~

SPre!Mtw TEMP Ewencf 1ATERAL FRACT ID TEST IMPACT ENP APPEAA (F)

(ft-1b)

(mil)"

(t) 154

-80.00 4.Sc 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 0.00 143 0.00 11.00 13.00 15.00 147 0.00 16.50 10.00 15.00 114 40.00 41.00 30.00 25.00 11A 40.00

$6.30 40.00 25.00 12K 00.00 93.50 72.00 65.00 14A 00.00 124.S0 03.00 75.00 l

154 120.00 110.00 70.00 00.00 11E 120.00 141.50 96.00 90.00 13T 160.00 144.50 90.00 100.00 11T 160.00 157.50 95.00 90.00 l

157 210.00 140.00 96.00 100.00

)

i 14L 210.00 155.00 94.00 100.00 i

l l

l 1

lt F4

Table F-9 Charpy V-Notch Test Results

(

For Unit 2 Plate C6404-2 (TL), CE Baseline Data s

1 SPECIMEN TEMP ENERCT LATERAL FRACT ID TEST IMPACT ERP APPEAR (r)

(ft-1b)

(mil)

(t) 284

-e0.00 4.50 2.00 0.00 2SA

-40.00 e.00 e.00 0.00 23D

-40.00 0.00 9.00 0.00 217 0.00 12.00 15.00 10.00 21Y 0.00 24.50 24.00 10.00 262 40.00 33.00 32.00 20.00 228 40.00 40.00 25.00 25.00 24.7 30.00 68.50

$9.00 20.00 1

24E 80.00 70.S0 42.00 40.00 21E 120.00 87.00 48.00 75 00 24A 120.00 107.00 72.00 00.00 245 160.00 111.50 70.00 05.00 247 160.00 127.50 34.00 90.00 216 190.00 116.00 30.00 100.00 24U 210.00 126.50 87.00 100.00 1

231 210.00 137.30 91.00 100.00 f

l t

F-9

7 Table F-10 Charpy V-Notch Test Results g

For Unit 2 Surveillance Weld, CE Baseline Data h

SPECIMEN TEMP EMERCT LATERAL FRACT 2D TEST IMPACT EXP APPEAR (P)

(ft-lb)

(mil)

(t) 34A

-150.00 3.50 1.00 0.00 31M 120.00 7.00 6.00 15.00 333

-120.00 14.00 12.00 15.00 346

-80.00 16.00 15.00 25.00 37A

-80.00 29.50 25.00 30.00 31K 40.00 43.50 37.00 35.00 3ST 0.00 63.50 S3.00 65.00 34T 0.00 90.00 60.00 15.00 1

338 40.00 132.00 90.00 90.00 324 40.00 146.00 97.00 100.00 35L 00.00 135.50 95.00 100.00 326 00.00 140.00 96.00 100.00 231 120.00 145.50 95.00 100.00 34J 120.00 153.00 90.00 100.00 35J 160.00 151.00 94.00 100.00 I

335 160.00 152.00 100.00 100.00 F-10

r

~

Table F-11 Charpy V-Notch Test Results For Unit 2 Plate C6404-2 (LT), MCR Data Test impact Lateral Fracture Temperature Energy Expansion Appearance

('F)

(f t-lb s)

(mils)

(% Shear)

-40 9

11 0

40 12 18 0

-40 8

10 0

10 25 19 10 10 44 30 25 10 26 21 15 40 42 31 25 40 60 44 40 40 52 46 30 110 126 85 80 110 111 78 70 110 112 74 70

('

160 145 85 95 160 136 84 90 160 155 90 100 4

)

e F-11

i I

L i

h 3

APPENDIX G

(

SONGS, UNIT 2: HAZ TEST RESULTS e

4 CE Baseline Tests"3 a

SPECTMEN TEMP EPeltCY IATERAL,

FPACT ZD TTST IMPACT RIP APPEAR (F)

(ft-1b)

(mil)

(1) 4SJ 150.00 5.00 3.00 0.00 43C 120.00 9.50 s.00 0.00 41M 00.00 23.50 19.00 25.00 415 00.00 35.00 20.06 30.00 464 40.00 30.00 24.00 30.00 46K 40.00 40.00 34.00 30.00 470 0.00 02.00 54.00 50.00 41Y 0.00 101.00 70.00 70.00' 44C 40.00 104.50 71.00 90.00 432 40.00 115.50 09.00 100.00 441 00.00 135.50 04.00 90.00 420 00.00 153.00 92.00 100.00 43K 12 0..'^

100.00 79.00 90.00 421 120.00 144.50 09.00 100.00 451 160.00 139.00 05.00 100.00 442 160.00 151.S0 06.00 100.00 e9

+

t C)-1

1

(

Battelle Capsule 97(23 SPECIMEN TEMP ENERGY LATERAL FRACT CHARPT IRAAD ID TEST IMPACT EIP APPEAA FLUENCE TEMP.

(F)

(ft.1b)

(mil)

(1)

(n/cm2)

(F) 47F

-79.00 12.00 S.00 17.00 5.07E610 500.00 41A

-79.00 14.10 10.20 13.00 S.075+10 S00.00 41C

~40.00 20.00 14.00 27.00 S.07E+10 500.00 413

.40.00 20.20 26.00 20.00 S.07E*10 500.00 43U 0.00 30.30 30.40 44.00 S.07E610

$80.00 42J 0.00 77.50

$4.00 S4.00 S.078610

$80.00 1

42Y 72.00 103.00 31.20 09.00 S.07E*10 500.00 42C 72.00 114.20 04.40 93.00 S.07E+10 500.00 444 160.00 130.00 07.00 100.00 S.07E*10 500.00

)

412 160.00 132.60 05.40 100.00 5.07E+10 500.00 44P 260.00 133.70 02.30 100.00 5.078610 500.00 424 260.00 14S.30 09.00 100.00 S.075+10 S00.00 i

G-2

(.

.~

t r

J

(

r, t

7.:

' i.

i 1

APPENDIX H i

i s

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

I t

4.

I I

1

(

I i

?

i

?

Table H-1 Charpy V-Notch Test Results k

For Unit 2 Plate C6404-2 (LT)

Irradiated (f = 5.07 x 10")

e SPECIMEN TEMP ENEPCT IATERAL TRACT ID TEST IMPACT EXP APPEAR (r)

(ft-1b)

(mil)

(t) 141 0.00 6.00 6.00 4.00 111 0.00 0.10 6.40 5.00 I5H 40.00 12.50 7.00 11.00 14T 72.00 23.50 23.60 9.00 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 11M 160.00 113.40 83.00 77.00 15E

.360.00 130.50 99.40 100.00 11U 200.00 127.30 93.40 100.00 124 200.00 136.20 105.80 100.00 137 260.00 137.30 95.40 100.00 t

4 H-1

r Table H-2 Charpy V-Notch Test Results

(,

For Unit 2 Plate C6404-2 (TL)

Irradiated (f = 5.07 x 10")

,e SPECIMEN TEMP ENERCY 1ATERAL TRACT ID

, TEST IMPACT EIF APPEAR (r)

(ft-lb)

(mil)

(t) 214 0.00 4.00 10.00 4.00 23.7 0.00 11.00 11.00 6.00 223 40.00 22.00 19.60 11.00 22K 72.00 27.90 32.00 15.00 22T 62.00 32.10 31.80 15.00 25U 100.00 44.10 42.80 42.00 i

(

23P 100.00 50.00 44.00 49.00 218 160.00 02.00 60.40 85.00 221 200.00 93.00 71.00 100.00 25L 200.00 98.00 (0.60 100.00 256 260.00 101.90 83.40 100.00 211 260.00 103.00 83.00 100.00 t

9

(

H-2

l i

Table H-3 Charpy V-Notch Test Results

(

For Unit 2 Surveillance Weld Irradiated (f = 5.07 x 10")

i

)

SPECIMEN TEMP ENERCY LATERAL FRACT ID TEST IMPACT EEP APPEAR (r)

(ft-lb)

(mil)

(g) 37M

-79.00 15.00 14.40 18.00 37L

-79.00 18.40 20.00 13.00 3A3

-40.00 25.00 23.60 36.00 36M

-40.00 45.40 36.60 40.00 36P 0.00 78.00 65.20 68.00 36K 0.00 02.40' 64.60 70.00 31E 72.00 126.90 95.00 92.00 33P 72.00 130.20 102.20 100.00 342 160.00 134.00 99.00 100.00 36E 160.00 142.50 97.00 100.00 32P 260.00 147.90 97.60 100.00 341 260.00 149.00 100.40 100.00 k

H-3

.