ML20082G700
| ML20082G700 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 11/30/1993 |
| From: | ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY |
| To: | |
| Shared Package | |
| ML20082G697 | List: |
| References | |
| CEN-612, NUDOCS 9504130361 | |
| Download: ML20082G700 (114) | |
Text
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; % 3Ei J CEN-612 REACTOR VESSEL WELD 1
MATERIALS FOR CALVERT CLIFFS UNIT 1 i SUPPLEMENTAL SURVEILLANCE PROGRAM i 1
- i NOVEMBER 1993 COMBUSTION ENGINEERING, INC.
Windsor, Connecticut 9504130361 950411 PDR ADOCK 05000317 p PDR
u ,. c-904(8913).00C/ref-2. Reactor Vessel Weld Materials for Calvert Cliffs Unit 1 Supplemental Surveillance Program Report No. 02987-NCC-002, Revision 00 Nuclear Power Businesses COMBUSTION ENGINEERING, INC. - Windsor, Connecticut p-Prepared By: U .' / < /m>M Date: / 2 -/2 P F S. T. Byrne, Ca(sultant - Approved By: WS hM W. R. Gahwiller, Supervisor, Date:'Az/As/rf Materials Technology Approved By: /5 N Date: /2.[/3 /ff S. M. Schloss, Manager, . Materials and Chemical Technology 0A Status: Verified The safety related design information contained in this document has been reviewed and satisfies (where applicable) the items contained on checklist (s) f, - , and of the Quality Assurance Procedures Manual. This review is so certified. Independent Reviewer [f M L _ Date 2:r- /2 77 Aw. 00 Issue Date: 12/18/89 Page 1 of 43
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'904(8913).00C/ref-3 TABLE OF CONTENTS .
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. SECTION TITLE .PAGE NO.
I Introduction 5 II- Tandem Arc Welds 7 III Equivalence of Calvert Cliffs and McGuire Welds 9 IV Weld Chemical Content 17-- I Initial RTNDT- 21 VI McGuire Archive Material Traceability 28 VII - Surrogate Weld Material Traceability 31 VIII Calvert Cliffs Unit 1 Reactor Vessel Beltline 36 Materials ' IX Conclusions 40 X References 41 APPENDIX A Calvert Cliffs Unit 1 Weld Records A-1 APPENDIX B McGuire Unit 1 Weld Records 8 - 1. APPENDIX C Surrogate Weld Records- C-1 l i 1 j i I Report No. 02987-MCC-002, Rev. 00 Page 2 of 43
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904(8913). DOC /ref-4 LIST OF TABLES TABLE NO. TITLE PAGE NO. 1 Comparison of Weld Process Details 12 2 Expected Effects of Flux Type on'the As-Deposited , 13 Weld Properties Using the Same Weld Wire ; 3 As-Deposited Weld Chemistries as a Function of 14 Flux Type - 4 As-Deposited Weld Chemistries as a Function of Flux Lot 15 . 5 ' Weld Deposit Analysis Source Data .18 6 McGuire Unit 1 Surveillance Weld Chemical Content . 19 , 7 Supplemental Analysis.of McGuire Unit.1 Archive 20 Weld Block 8 McGuire Unit 1 Test Plate B Weld Impact Properties '23 9 McGuire Unit 1 Pre-Irradiation Surveillance Weld 24 Impact Properties 10 Surrogate Weld Process Details 33 11 Supplemental Analysis of Surrogate Weld Block 34 , , 12 Calvert Cliffs Unit 1 Beltline Plates 37 13 Calvert Cliffs Unit.1 Beltline Welds 38 Report No. 02987-MCC-002, Rev. 00 Page 3 of 43 1
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g .. 904(8913). DOC /ref-5' a. LIST OF FIGURES FIGURE NO. TITLE ~PAGE NO. 1 J-Groove Weld Configuration '16 2A McGuire Weld Impact Properties, Charpy Energy 25 2B McGuire Weld Impact Properties, Lateral Expansion 26 2C McGuire Weld Impact Properties, Shear' Fracture 27 3 McGuire Archive Surveillance Weld Block 30 4 Surrogate Weld Block 35 5 Calvert Cliffs Unit.1 Pryssure Vessel View 39 Report No. 02987-MCC-002, Rev. 00 Page 4 of 43
y% q 904(8913).00C/ref-6 { I. INTRODUCTION The reactor vessel surveillance program for Calvert Cliffs UnitL1 was designed to monitor the radiation induced property changes of the beltline materials. One plate and one weld material were selected for inclusion in the program to represent the beltline and obtain data for use in verifying predictions of irradiation embrittlement. Based on current understanding of embrittlement, the weld material selected for the Unit I surveillance program-is not the : controlling weld (i.e., that beltline weld presently predicted to exhibit the greatest sensitivity to neutron irradiation). Recognizing this situation, Baltimore Gas & Electric (BG&E) searched for material or data which would provide better information for evaluating irradiation embrittlement of the Unit I controlling weld. It'was established that the controlling weld in Calvert Cliffs Unit I was fabricated using the same weld consumables as the surveillance weld for McGuire Unit 1. With the cooperation of Duke Power Company and Westinghouse, the McGuire surveillance archive weld was located and a portion was provided for BG&E use. Additionally, a " surrogate" weldment was located .which has essentially identical material properties to the McGuire surveillance weld. The purpose of this report is to compile the documentation associated with the weld materials included in the Calvert Cliffs Unit 1 supplemental surveillance program, and to establish the traceability " nd a the known physical properties of those weld materials. , Section II provides information establishing that the controlling weld seam in Calvert Cliffs Unit I was fabricated using two specific weld wire heats in tandem. Section III demonstrates that both the Calvert Cliffs weld and the McGuire Unit I surveillance weld were fabricated using the same process and the < same weld wire heats, thereby establishing the validity of using data from the McGuire surveillance weld in vessel integrity evaluation efforts for Calvert Cliffs. Sections IV and V review the available materials property data Report No. 02987-MCC-002, Rev. 00 Page 5 of 43
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the: chemical . content and initial reference temperature' of that weld. Section- l VI traces the McGuire surveillance. weld-from initial fabrication through i ' delivery to Combustion Engineering Lfor the purpose of establishing the pedigree of the material used for test- specimens: encapsulated in a Calvert-Cliffs Unit -1 replacement surveillance capsule. - Section VII provides similar-documentation behind the " surrogate" weldment used to augment'the NcGuire 3 material. L Section VIII summarizes and documents' the' source' of information 'for i all the plates and welds in the beltline of the Calvert Cliffs Unit I reactor ' , 1 vessel. Selected documents referenced in'the report are included in' the Appendices.
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q < II. TANDEM ARC WELDS o The purpose of this section is to establish that weld seams 2-203 A,- 8 and C (also identified as 2-203 A/C) in the Calvert Cliffs Unit I reactor vessel j were fabricated using weld wire heats #12008 and #20291 in tandem. Conversely, ~! it is the intent to show that wire heat #12008 was'not used on both the front j and rear weld heads at the same time. This information is needed to establish ' the chemical content and initial toughness properties of the reactor vessel beltline welds. The. weld inspection record form (WIF) for seam 2-203 A/C.shows that Weld Procedure TSAA-2-(1)(ALT), weld wire heats #20291 and #12008, and Linde 1092 flux lot 3833 were used to fabricate' the three longitudinal seam welds. C-E ! Drawing E-233-405-9 (Pressure Vessel Welding and Machining, 17'2" ID PWR) calls out a straight-sided weld for seam 2-203, and a "J-weld" as the alternate; the
" ALT" on the WIF indicates the J-weld configuration was used. (See also C-E Drawing A-230-225-12, Weld Procedure Assignment for Dwg. E-233-405, Contract !
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According the B. G. Carlton, C-E Chattanooga Welding Engineering (Meeting, January 12-13, 1988, Chattanooga, Tennessee), the preceding records clearly show that weld seams 2-203 A/C were prepared with a J-weld configuration in the following sequence: '
- 1) manual arc weld for fit-up :
ii) tandem are weld the outside diameter (00) section of the weld i iii) backgroove the manual arc joint to sound weld metal iv) tandem arc weld the inside diameter (ID). Carlton also stated that wire heat #12008 was low in carbon, and controls -".re placed on its use at the time to use it only in tandem with a second wire heat to assure the combined carbon content of the deposited weld was high enough to l meet minimum tensile strength requirements. Wire heat #12008, therefore, Report No. 02987-MCC-002, Rev. 00 Page 7 of 43
904(8913).00C/rcf-9 could not be used for single arc welds or as the wire feed for both welding heads in a tandem arc weld. (No such constraints were put on wire heat
- 20291, so that wire heat could be used alone in both single and tandem arc welds.)
A record stipulating that controls k placed on the use of wire heat #12008 could not be located. However, records are available regarding the low carbon content. C-E Purchase Specification No. N-P3W8(e) requires 0.15 to 0.18% carbon (+ 0.01% after check analysis). Adcom Metals Company certifications for wire heat #12008 report 0.13% carbon, and C-E wire analysis R-1990 reports 0.11% carbon. C-E wire analyses for wire heat #20291 (R-2248) and #13253 (R-2083) report 0.19% and 0.146% carbon, respectively. Therefore, the combination of the reported carbon content and the subsequently established (June 1974) specification limits supports Carlton's statement that the lower carbon content of wire heat #12008 should be used in tandem with a higher carbon content wire. In summary, weld seams were fabricated using weld wire heats #12008 and #20291 in tandem. This conclusion is based on a combination of weld fabrication records and indirect evidence that heat #12008 could only be.used with another wire heat in order to meet minimum carbon content requirements in the weld deposit. Pertinent records supporting this conclusion are contained in Appendix A. Report No. 02987-MCC-002, Rev. 00 Page 8 of 43
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904(8913)'. DOC /ref-10 4 III. E0VIVALENCE OF CALVERT CLIFFS AND MCGUIRE WELOS The purpose of this section is to establish the equivalence between Calvert Cliffs Unit I weld seam 2-203 A/C and the McGuire Unit I reactor vessel surveillance program weld. Demonstration of equivalence requires that the same weld wire, the same flux type, and the same welding procedure were used to fabricate the aforementioned welds,-and both were subjected to the same post-weld heat treatment. Equivalence implies that the welds will have the same chemical content, the same initial strength and toughness, and the same response to neutron irradiation. Table I summarizes key information pertaining to the fabrication of the following: Calvert Cliffs Unit I weld seams 2-203 A/C McGuire Unit I weld seams 2-442 A/C McGuire Unit I surveillance weld (Test Plates B & C) This information was extracted from Veld Inspection Record forms (WIF), fabrication drawings and shop travelers generated by C-E Chattanooga at the - time of manufacture. As noted in Table 1, all three welds were fabricated to the same detailed weld procedure (TSAA-2, Rev. 1) and Weld Procedure Qualification Record (SAA-33-27), and with the same weld configuration ("J" l groove as sketched in Figure 1) during the same March-April 1969 time period. All three welds were done with the tandem arc process using Mil B-4 (modified) wire heats #12008 and #20291, and Linde 1092 weld flux. Two different lots of Linde 1092 flux were employed as noted. All of the adfoining plates were : SA-5338 Class 1 material supplied by Lukens Steel Company; the copper content of the plates ranged from 0.10 to 0.13% and the nickel content ranged from l 0.55 to 0.66% for the six plates (See Appendices A and B). Report No. 02987-MCC-002, Rev. 00 Page 9 of 43
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904(8913).DUC/ref-11 The post-weld heat treatment (PWHT) requirement (as per DWP TSAA-2) was 1150*F 25'F held one hour per inch of weld thickness. For both the McGuire and Calvert Cliffs longitudinal vessel welds, the cumulative PWHT at 1150*F approximated 40 hours (i.e., accounting for the subsequent subassembly and main assembly heat treatments). The McGuire surveillance weld received-a 40 hour, 1150*F stress relief heat treatment. In summary, the design, fabrication and heat treatment requirements for the three sets of welds were identical. The same two heats of weld wire (Mil ~ B4-Mod. heats #12008 and #20291) were used with the same type of flux (Linde 1092), and the same type of base materials (SA-5338 Class 1) for all three sets of welds. The only apparent differences between the Calvert Cliffs Unit 1 longitudinal seam welds and the McGuire Unit I surveillance weld were in the heats of base metal surrounding the weld and in the lot of fiux:, i) Base Metal Difference - The difference in base metal heats is insignificant given the similarity in chemical content, especially copper and nickel, between the six plates. The factor of primary interest is the degree of base metal dilution immediately adjacent to the weld fusion line. Since the copper and nickel content of.the plates is lower than that of the weld wires, the small dilution zone would have a lower copper and nickel content than the bulk of the weld deposit. Therefore, the difference between base metals is both insignificant and inconsequential (i.e., the dilution zone should be less sensitive to irradiation than the bulk of the weld). ii) Flux Lot Difference - The same type of flux (Linde 1092) was used to fabricate both welds, but different lots of flux were involved. , Establishing the significance of this requires an understanding of flux types. Linde 1092 flux is intended primarily to blanket the weld puddle during deposition and solidification, but it also acts to remove certain elements from the weld puddle. As shown in Table 2 (based on References 1 through 6), the available " neutral" fluxes act on the weld puddle to varying degrees. The influence of weld flux type on chemical content is' Report No. 02987-MCC-002, Rev. 00 Page 10 of 43 1 u_-_ .
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!904(8913). DOC /ref 13 TABLE!1-y
; Comparison of Weld Process Data.
Calvert Cliffs Unit 1- McGuire Unit 1~ McGuise Unit l'
-- Weldment 2-203 A/C 2-442"A/C- Surveillance Contract No. 72167L 2167 -2167 Weld Procedure No. ISAA-2-(1)(ALT) TSAA-2-1 TSAA-2-1.
Reference Proc. No. SAA-33-27 SAA-33-27. SAA-33-27 Flux Type Linde 1092 Linde 1092 Linde 1092 Flux Lot No. 3833 3833 & 3854 3854 Wire Type B4-Mod. B4-Mod. 84-Mod. Wire Heat 12008 & 20291 12008 & 20291 12008 & 20291 Completion Date 3-27-69 4-22-69: 4-29-69 Weld Configuration J-Groove J-Groove J-Groove
'Dwg. Reference E-233-405-9 E-235-442-4 -234-454, Det. A
. Post-Weld Heat Treat. 40 hrs, 1150F 40 hrs, 1150F 40 hrs, 1150F (nominal) .(nominal)
Adjoining P1ates D-7206-1 ' B-5012-1 B-5012-2 D-7206-2 B-5012-2 B-5012-3 D-7206-3 -B-5012-3 Report No. 02987-MCC-002, Rev. 00 Page 12 of 43
p ! 904(8913).00C/ref-12 demonstrated in Table 3 where the same weld wire was used with two different types of flie. Linde 0091 flux produced lower amounts of silicon, manganese, sulfur and phosphorus compared to the weld deposited with Linde 124. The silicon content is actually increased relative to the weld wire, but Linde 0091 flux contributes less silicon than the Linde 124 flux. Copper and nickel (latter not shown in Table 3) content is essentially unchanged by flux type. The efficiency of the weld flux in cleansing the weld puddle, therefore, increases going from Linde 80 to Linde 0091 flux types as indicated in Table 2. '
. The effect of flux lot on weld deposit chemical content is illustrated in Table 4. 'Four different lots of Linde 124 flux used with the same heat of wire yie'lded essentially the same results with the exception of manganese and silicon which varied by 11% and 14%, respectively, from the average content. The variation in copper and nickel content for the four weld deposit's was negligible.
The data in Table 3, therefore, demonstrate that the effect of flux type is predictable. For welds fabricated using Linde 1092 flux, lower amounts of Si, Mn, S and P can be expected relative to a weld fabricated using Linde 124 or Linde 80 flux. The data in Table 4 demonstrate that the effect of flux lot differences is exhibited only in the manganese and silicon content, and the variation of those two elements is small. The variation in silicon would be expected to be less in a Linde 1092 flux weld than in a Linde 124 flux weld because the Linde 1092 adds less total silicon to the weld deposit. Both tables show that copper and nickel content are not significantly affected by variations in either flux type or lots of flux. Specific to the case of the two lots of Linde 1092 described in Table 1, the copper and nickel content, therefore, can be expected to be essentially the same for all three sets of welds, and it would be reasonable to conclude that the composition of the elements Si, S, P, Mn and 0 does not vary significantly between the three sets of welds. Report No. 02987-MCC-002, Rev. 00 Page 11 of 43 I
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904(8913) . DOC /rcf-14 5' E' 2 . O TABLE 2 a Expected Effect of Flux Type on the As-Deposited Weld Properties Using the Same Weld Wire k
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8 n2 Weld Chemical Content
- o Linde Flux Flux Basicity Ratio Non-Metallic y Type (Ca0/SiO2 ) Inclusion Oxygen Silicon Manganese Sulfur Phosphorus' O
0091 High Low Low Low Low Low Low a 1092 124 y _y v v v <r 80 Low High High High High High High'
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s - . 904(8913).00C/ref-15L TABLE 3 As-Deposited Weld Chemistries as a Function of F1'ux Type Weld Deposit -Weld Deposit Weld Wire Linde 124 Linde 0091 Elements Heat #83637 (w/o) Lot-#1122 (w/o)- Lot-#0951:(w/o)- Si 0.04- 0.42 0.15 . S 0.013 0.012 0.009 P 0.007 0.011 O.006 Mn 1.98 1.43 1.32. C- 0.16 0.094 0.16 Cr ---- 0.04 ----- Ni ---- 0.03 ----- Mo 0.55 0.51 0.62 Cu 0.05 0.06 0.04 V <.01 0.004 0.007 l h i Report No. 02987-MCC-002, Rev. 00 Page 14 of 43
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- As-Deposited Weld Chemistries as' a Function of Flux Lot (Weld. Wire Heat #4P7869)
Weld Deposit Weld-Deposit Weld Deposit Weld Deposit Linde 124 Linde 124 Linde 124; -Linde 124 Elements Lot #1061 (w/o) Lot #0871 (w/o) Lot #0171 (w/o) Lot #0281 (w/ol' Si 0.53 0.41 0.49 0.43 S 0.010 0.010 0.009 .0.010 . P 0.008 0.010 0.009 'O.007 Mn 1.38 1.70 1.51 1.63 l C 0.10 0.11 0.11- 0.11 l Cr 0.16 0.16 0.17 .0.16 ; l Ni 0.07 0.07 0. 06 -' O.07 I Mo 0.46 0.50 0.49 0.48 Cu 0.05 0.03 0.03 0.04 V 0.004 0.005 0.005 0.005, Report No. 02987-MCC-002, Rev. 00 Page 15.of 43
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904(8913). DOC /ref-18 l IV. WELD CHEMICAL CONTENT l The purpose of this section is to establish the chemical content of the welds { fabricated.using weld wire heats #12008 and #20291 with Linde 1092 flux. The copper and nick'el content is to be used as the basis for radiation induced shift-predictions for vessel integrity analyses and to evaluate measurements of shift from the McGuire Unit I surveillance weld. The source information for the two weld wire heats and tandem arc weld deposit I chemical content is summarized in Table 5. The table-is reproduced from Reference 7. The average nickel content based on analysis of the bare wires (R#) and weld deposits (D#) of the single wire heats (8-11) was .0.87%, whereas the tandem arc weld deposit analysis involving both heats (12) was 0.88%; similarly, the average copper content based on single wire weld deposit analyses (D#) was the same as the tandem arc analysis, 0.21%. The overall , average was- 0.87% Ni and 0.21% Cu as shown in the calculation in Table 5. I These results are the values previously reported for Calvert Cliffs Unit I l weld seams 2-203 A/C. (13) Table 6 presents the full chemical analysis as reported for the McGuire Unit 1 surveillance weld (12) Table 7 summarizes results of supplemental
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analyses (27) performed on a portion of the McGuire surveillance weld archive block. ! 1 l l l l l I Report No. 02987-MCC-002, Rev. 00 Page 17 of 43 l l l
p, . _. _ k+j 904(8913). DOC /ref-19 TABLE'5, Weld Deposit Analysis. Source' Data Wire. Fl ux .. Flux Laboratory- Source ' Type Lot No. Analysis No. Heat No. Cu (w/o) Ni (w/o) Reference 12008 -- -- -- 1.00 R-1990 8. 20291 -- -- -- 0.73 R-2248 '8 ,
.20291 -- -- --
0.74 R-2293 8 3692 1.01 120D8 1092 NA D-4907 8 12008 1092- 3869 0.22 NA D-7278 8 12008 1092 3869 0.20 NA D-7525 8 20291 1092 3833 0.21 0.74 NA- 9,10 20291 1092 3833 0.22* 0.73* NA. 11 12008 &
'20291 1092 3854 0.21 0.88 D-24117 12 CHEMISTRY CALCULATION Cu: ((0.22 + 0.20)/2 + (0.21 + 0.22)/2 + 0.21)/3 = 0.21 w/o Cu-Ni: ((1.00 + 1.01)/2 + (0.73 + 0.74 + 0.74 + 0.73)/4 + 0.88)/3 = 0.87 w/o Ni ESTIMATED CHEMISTRY ,
0.21 w/o Cu 0.87 w/o Ni
- Average of five analyses.
NA - Not Available Report No. 02987-MCC-002, Rev. 00 Page 18 of 43
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TABLE 6-t McGuire Unit 1 Surveillance ~ Weld F Chemical Content (12) Chemical ' Content : Element (Weiaht %) Si 0.24- ' S 0.008 - . .C
. P. 0.011-Mn 1.36 ;
C 0.10 . Cr 0.04 Ni 0.88' , Mo 0.55- 1 Cu 0.21 V 0.04 Sn 0.007-
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- Supplemental . Analysis of..McGuire Unit-l' l a
Archive Weld Block (27) z 4
'I Chemical- . Content' Element 1weicht %)
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Cr 0.05 Ni - 0.89 - Ho 0.53 ; Cu 0.19 , V 0.005- , Sn 0.009. Co .0.017' r B 0.0002 Nb 0.002 Ti < 0.001 W 0.005 - As 0.015 N 0.0085 Zr ,
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Pb _< 0.002 Report No. 02987-MCC-002, Rev. 00 Page 20'of 43
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-904(8913).00C/ref-22 V. INITIAL RTNDT
--The purpose of this section is to provide the basis for the initial RTNDT of weld seams 2-203 A/C in Calvert Cliffs Unit 1.. Given the equivalence of'this weld to the McGuire Unit I weld seams 2-442 A/C and to the McGuire surveillance weld, the Charpy data generated for McGuire can be used to define the properties for Calvert Cliffs Unit 1.
There are two complete sets of Charpy impact test data for a full thickness
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weld seam fabricated using we wire heats #12008 and #20291 with Linde 1092 flux: i) Vessel Weld Qualification Test Report - Drop weight and Charpy tests (I4) on Test Plate "B" from McGuire Unit I were p'erformed to r'epresent weld seam 2-442 A/C. The data are reproduced in Table 8; they reflect a weld deposit fabricated using wire heats #12008 and #20291, and Linde 1092-
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flux lot #3854.
- 11) Surveillance Baseline Test Report - Charpy impact tests (12) were performed on the McGuire Unit 1 surveillance weld (Test Plates B & C).
The data reproduced in Table 9 reflect a weld deposit fabricated using wire heats #12008 and #20291, and Linde 1092 flux lot #3854. The Charpy and drop weight data from the weld qualification tests (Table 8) can be used to establish an initial RTNDT in accordance with the ASME Code, Section III, NB-2300. Given the drop weight NDTT = -60*F and the lower bound of the Charpy data yielding greater than 50 ft-lb and 35 mils lateral expansion at O'F (NDTT + 60*F), the resultant value of initial RTNDT = ,60*F is obtained. A full Charpy curve was also generated for the weld as part of the
. surveillance baseline evaluation (12) These data (from Table 9) are compared
. i to the weld qualification test data in Figures 2A, 2B and 2C (impact energy, l lateral expansion and percent shear fracture versus temperature, -
j l Report No. 02987-MCC-002, Rev. 00 Page 21 of 43
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F respectively). - The data are very consistent in t'.e region of the upper shelf (100*F to.210*F) and over the entire range of test temperatures for the shear-fracture: data (Figure 2C). However, the surveillance baseline impact energy and lateral expansion data are much more scattered than the weld qualification test data in the transition region (-40*F to 50*F). -This is unexpected because the material source was the same (both Test Plates B and C were from the same weldment 'and had the same.specified post-weld heat treatment), although different organizations prepared the specimens and performed the tests. It is possible that differences in laboratory practices and procedures ' contributed to the differences in test results in the transition region where impact properties are very sensitive to small variations in specimen dimensions, test temperature, and-testing procedures. Given the observed differences in impact properties between the,two sets of Charpy data, a more conservative approach for defining initial' RTNDT was selected for the Calvert Cliffs Unit I weld seams 2-203 A/C. Using both sets of Charpy data, the minimum temperature at which at least 50 ft-lb and 35 mils lateral expansion were exhibited by three test specimens is 10*F; i.e., T cv
- 10*F per NB2300. Accordingly, RTNDT is the higher of T cv - 60*F or NDTT:
T cv 10 -50*F NDTT = -60*F Therefore, the initial RTNDT is -50 *F. This is the same value as that previously reported (15) for the McGuire Unit I weld seam 2-442 A/C. The initial (preirradiation) upper shelf energy of the McGuire weld is 111.5 ft-lb; this is based on an average of the six tests exhibiting 100% shear fracture as reported in Tables 8 and 9. This value is typical for submerged arc welds fabricated using Linde 1092 flux and is well in excess of the 75 ft-lb minimum currently required (16) for reactor vessel beltline materials. (This requirement was imposed subsequent to fabrication of the Calvert Cliffs l and McGuire vessels and is provided only for reference.) - l l d i Report No. 02987-MCC-002, Rev. 00 Page 22 of 43 l l I I i l
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904(8913).00C/ref-24 TA8LE 8 = McGuire Unit 1 Test Plate B Weld Impact Properties Charov Imoact Tests Impact Energy Lateral Test Temp. (*F) (Ft/Lbs.) Shear (%) Expansion (mils)-
-80 15 0 12
-80 16 0 12
-40 49 30- 36
-40 38 30 32
-40 45 30 35
+10 71 40 52
+10 60 35 44
+10 73 40 49
+40 81 45 58
+40 90 50 63
+40 88 -50 64
+110 100 90 81
+110 93 95 83
+160 111 100 82
.+160' 110 100 -88 Droo Weicht Tests Test Temo. (*F) Test Result
-40 1 No-Fail
- -50 2 No-Fail
-60 1 Fail -
NDTT = -60*F Report No. 02987-MCC-002, Rev. 00 Page 23 of 43
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i TABLE 9I , s f McGuire Unit 1 Pre-Irradiation Surveillance ' Weld Impact Properties Impact Energy lateral. Test Temp. (*F) (Ft/Lbs.) Shear'(%) Expansion (mils)
-100 4.5 6 .1- ,
,-100 4.2 6 1.5
-35 11.5 23 11
-35 30 27 26 0 15 35 17 0 31 40 29 0 65 47 53 25 75 60 61 25 60 47 49?
50 74.5 60 63 50 58 ' 55 47 100- 105 93. 84 100 96- ~85 80-
-150 105 .92 86~
150 113 100 89 210 113 100 87 210 112 100 84 210 110 100 86 Report No. 02987-MCC-002, Rev. 00 Page 24 of 43
Figure 2A McGuire Weld Impact Properties Charpy Energy 125 l l : a q:: i:pi: i j 1 ! !
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Report No. 02987-MCC-002, Rev. 00 Page 25 of 43
Figure 2B i McGuire Weld Impact Prop;rties , Lateral Expansion L i' l l '
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Report No. 02987-MCC-002, Rev. 00 f Page 26 of 43
Figure 2C McGuire Weld Impact Properties Shear Fracture mA m 100 -
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904(8913).00C/ref-29 VI. MCGUIRE ARCHIVE MATERIAL ~ TRACEABILITY The purpose of this section is to document the source of the McGuire Unit I surveillance weld archive test block used to fabricate Charpy impact specimens for a Calvert Cliffs Unit I supplemental surveillance capsule (17) . C-E Nuclear Shop Traveler V-70333-017(18) established the fabrication requirements for Test Plates B and C. Reactor vessel plates B-5012-2 and B-5012-3 were joined following'C-E drawings SA-2067-27-1 (19) and SA-2067-28-0 (20) , where the base metals and weld consumables were identical for both test plates per the traveler. The materials were also recorded on the Weld Inspection Record form'(WIF) for Test Plates B and C (21) . One 12 inch section of Test Plate C (12" long, 8" wide, 9.625" thick) was designated for shipment to Westinghouse, and the. remaining 12 inch section was designated for heat treatment. Test Plate B (31" long,14" wide, 9.625" thick) was transferred to the Chattanooga Metallurgical Research and Development ! Department for mechanical testing of the weld and heat affected zone; the test results were provided subsequently in Reference 14. According to a Shipping Request dated 8/3/71, a portion of Test Plate B,13" x 14" x 9.625", was shipped to Westinghouse. The' transmittal record noted that
" Test Plate B (was) being substituted for Test Plate C" and that the Traveler I V-70333 was revised (Revision 1). The code "DAP" apparently added by ;
Westinghouse was also on the Shipping Request. A Westinghouse sketch labeled "DAP" shows two surveillance weld blocks. "Weldment D-1" has dimensions similar to the 12 inch length of Test Plate C designated in the Traveler; j "Weldment D-2" has dimensions similar to Test Plate B and identical to that I recorded on the Shipping Request. Weldment D-2 includes a piece designated i D2A, and a second Westinghouse sketch designates a piece of D2A approximately 7-3/4" long, 14" wide and 5.3 " thick to be saved. On March 23, 1988, C-E received from Westinghouse (via Duke Power) a weld block with dimensions approximately 6.75" long, 5.25" thick, and 6" wide. The block was labeled "D2A" on one edge,. The weld location and orientation were 4 Report No. 02987-MCC-002, Rev. 00 Page 28 of 43
,t __
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x .- 904(8913). DOC /ref , N
~
verified and a piece containing approximately two inches of the-weld length was removed-(see Figure 3). Twenty four. Charpy blanks-were machined from the two inch piece (see Reference.17),-and the remaining trim piece (approximately 0.25" thick, 2" long, and 6" wide) was sent to the BG&E Fort Smallwood Metals-Laboratory for chemical analysis. The; resultant data, Table 6, yielded values
. consistent with the chemical content reported for the McGuire Unit' IJ surveillance weld (15) ,
The available records,. therefore, connect the original fabrication records for . Test Plate B with weld block 02A. Since "D2A" was stamped on the block rec,eived by C-E, the block dimensions are in reasonabic agreement with C-E and Westinghouse records, and the supplemental chemical analysis results were consistent with previously reported values, there is then reasonable assurance' that weld block 02A is the same ' material as the McGuire Unit 1 archive : surveillance ~ weld block. Records pertinent to the archive material are . included in Appendix B. .
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.904(8913). DOC /ref-32 VII. SURROGATE WELD MATERIAL TRACEABILITY The purpose of this section is to document the' source of the weldsent to be used to augment the McGuire Unit I surveillance weld material provided by Duke Power. A portion of the " surrogate weld" was used to fabricate Charpy specimens for inclusion in a Calvert' Cliffs. Unit I supplemental surveillance capsule (II) .
The surrogate weld was obtained from a nozzle cut-out from the Maine Yankee- '
, reactor vessel (as described in C-E Dwg. E-233-794, Rev. 3). The block is-shown schematically in Figure 4; it consists of plates D-8405-2 and.0-8405-3 and an included weld fabricated using weld wire heats #12008 and #13253 with Linde 1092 flux lots #3791 and #3833 by the tandem submerged are process (22) ,
The block had been identified in accordance with C-E Dwg. E-233-794, Rev. 3, and it has been stored at C-E's Windsor, Connecticut facility.. Table 10 summarizes key information pertaining to the fabrication of the surrogate weld and comparable information for Calvert Cliffs Unit I weld seams. 2-203 A/C (from Table 1). This information was extracted from Weld Information Record forms (WIF), fabrication drawings, and material certificatior.s generated by C-E Chattanooga. Both welds were fabricated in the same fashion. ' Note: Two different revisions of the detailed weld procedure were used, but both Revision 0 and I contain the same' reference procedures, welding conditions, and heat-treatment requirements.) Two different lots of Linde 1092 flux were used for the surrogate weld, 'one of . ; which was the same used for Calvert Cliffs. The principal difference is the use of weld wire heat #13253 (for the' surrogate weld) versus heat #20291_(for the Calvert Cliffs weld) in tandem with , weld wire heat #12008. All of the adjoining plates were SA-5338 Class 1 material supplied by Lukens Steel Company; the nickel contents of the plates adjoining the surrogate weld were 0.54% and 0.58% which is on the low end of the range for the Calvert Cliffs ! , . and McGuire plates (0.55 to 0.66%);, copper contents for the plates are not available but could be obtained if such information is subsequently found to .l be important. - Report No. 02987-MCC-002, Rev. 00 Page 31 of 43
'l i
l
904(8913).00C/ref-33 The block was removed from storage, and a 3/4" through-thickness slab was sent to the BG&E Fort Smallwood Metals Laboratory for chemical analysis (27); these results are given in Table 11. An adjacent'5-5/8" length of the block was used to fabricate the Charpy impact specimens as described in the capsule fabrication report III) . Comparison of Table 11 results with Tables 6 and'7 demonstrate that the surrogate weld chemical content is nearly identical to that of the McGuire Unit 1 surveillance weld. The similarity in chemical content and fabrication process demonstrates the potential for using the
-nozzle cut-out weld as a surrogate for the Calvert Cliffs surveillance .
program. Pertinent records on the surrogate weld.are included in Appendix C. 1 l'
.l Report No. 02987-MCC-002, Rev. 00 Page 32 of 43
904(8913). DOC /ref .
. TABLE 10 Surrogate. Weld Process Data Surrogate Weld Calvert Cliffs Unit 1 -
Maine Yankee 1-203A) 2-203 A/C Contract No. 70167 72167 Weld Procedure No. TSAA-2A-0 TSAA-2-(1) (ALT). , Reference Proc. No. SAA-33-27 SAA-33-27 Flux Type Linde 1092 Linde 1092 Flux Lot No. 3791 & 3833 3833 Wire Type B4-Mod. B4-Mod. Wire Heat 12008 & 13253 12008 & 20291 Completion Date 11/21/68 3-27-69 Weld Configuration J-Groove J-Groove Dwg. Reference E-233-794-3 E-233-405-9 Post-Weld Heat Treat. 40.5 hrs 40 hrs, 1150 F 1100-1175 F , (nominal) Adjoining Plates D-8405-2 D-7206-1 D-8405-3 D-7206-2 D-7206-3 i Report No. 02987-MCC-002, Rev. 00 Page 33 of 43
t I 904(8913). DOC /ref-35 TABLE 11 Supplemental Analysis of Surt ogate Weld ~ Block (27) ,. Chemical Content . Element (weicht %) 1
- Si 0.23 !
S .0.012
'P 0.012
^
Mn 1.16 ! C 0.09 Cr 0.05 - Ni 0.86 i Mo 0.49 ; Cu 0.21 V 0.004 Sn 0.008 Co 0.016 B 0.0001 ; Nb 0.001 Ti- 0.001 W 0.005 As 0.014 N 0.0096 Zr 0.001 Pb < 0.002 ! s 4 o Report No. 02987-MCC-002, Rev. 00 Page 34 of 43
, . , _ . , . .,. .- . _ . _ _ _ _ _ ~ _ . _ , , _ _ . _ . . _ _ . . . _ _ ___ _ .__. _
1
'a L.ft.as -1 M i;
E E'
~
hex Face- 54 [ ~
. ir, Mf ve e
,/ / //- ;r- ;f,,4.
s 's re'
, o 0
? f..._ * .
_ v ii O
- A o ___3
(( --/ / -=---$l?' m: s' $,' I)], [ j' 5
- p ,'~ ~ - -- -
/'x,h f,e Q, Y \f ms *yb;'Y ; 3y, '
$i Pi mq, /
n a ,/ .-
,.t
/ -
em j '/
.- \
/ '/ e**5 33 i
\ -ig . .,g_ \ \. .
- \
- s \
\ W"-:s
, dll \
\
's' f \ l l
- l IN \ /
\f i
. 8 %J f t
,\ )
r t,% l \ f--f.
/ .
ff
\
,1;- \ 2 '
s a.n .- 88 Sea m : !
\
3 -t=M j/ 4;,. ~ J
,\ .
~
m l
-sh erto,;g maito3 oirection
- y Thr -T6
- c ko.2, . S s:u.
i y From Th:s Fece V. < ! w Cham: c al a n.s y 4 :3
"" FIGURE 4
! +> Surrogate Weld Block , l A w I e _ - _ _ . - - . . . -.. ____ . _.____ __.__- - -___.--__--_____.- - - - - _ ________-- - _ , - - - - . . , _ - . . ..n . - . . ,
~
[ 904(8913) .00C/ref-37 , VIII.. CALVERT CLIFFS UNIT 1 REACTOR VFCSEL BELTLINE MATERIALS The purpose of this section is to describe the materials included in the beltline of the Calvert Cliffs Unit I vessel, including the initial RTNDT'and , chemical content (copper and nickel) of the plates and welds. The beltline consists of the six plates in the intermediate and lower shell-courses, the intermediate shell longitudinal seam welds (2-203A, B & C), the lower _ shell longitudinal seam welds (3-203A, B & C), and the intermediate to lower shell girth seam weld (9-203). The chemical content and initial RTNDT are given in Table 12 for the six beltline plates and in Table 13. for the beltline welds. The arrangement of plates and welds in the Calvert Cliffs Unit I reactor-vessel is shown in Figure 5. The locations of the primary coolant nozzles-and the extent of the active core are also indicated in the " flattened out" view of the vessel. L l Report No. 02987-MCC-002, Rev. 00 Page 36 of 43 l I
f
- 904(8913). DOC /ref-38 TABLE 12 Calvert Cliffs Unit 1 Beltline Plates Plate Cu(1) Ni (I) NDTT(2) RTNDT I3)
Number Heat Number (w/o) (w/o) (*F) (*F) D-7206-1 C4351-2 .11 .55 -10 +20 D-7206-2 C4441-2 .12 .64 -30 -30 D-7206-3 C4441-1 .12 .64 0 +10 D-7207-1 C4420-1 .13 .54 d . +10 0-7207-2 B8489-2 .11 .56 -10 D-7207-3 B8489-1 .11 .53 -20 -20 NOTES 1- Source is Reference 23 2- . Drop Weight NDTT from longitudinally oriented test specimens. l 3- RTNDT based on conversion of data from longitudinally oriented test. ! specimens using Reference 24. + ; ? Report No. 02987-MCC-002, Rev. 00 Page 37 of 43
904(8913)LDOC/ref-39 TABLE 13 Calvert Cliffs Unit 1 Beltline Welds Weld Weld Wire Weld Flux Flux Cu(I) Ni(I) NDTT- RTNDT Seam No. Heat No. Type Lot No. (w/o) (w/o)' (*F)- (*F) 2-203 A/C 20291_& 1092 3833 ;21 .87 .-60(2) -50(2)L 12008 3-203'A/C 21935 1092 .3869 .21 .69 N/A' -56(3): 9-203 33A277 '0091 3922 .23 .23 -80(4) -80(4)
~ NOTES.
(1) Source is Reference 7 (2) Sources are References 12 and 15 (3) Generic value based on Reference 25 a (4) Source is surveillance weld. data from Reference 26 Report No. 02987-MCC-002, Rev. 00 Page 38 of 43
=
a 1 FIGURE 5
- o tD u
O r+ s Calvert Cliffs 1 Pressure Vessel View 2 0 o
~
m . . .
. =
esitti suits ~.
. a
$. lutas tuttti 1
n smitt satar estter n. m tu re 8 I a.uses.: s.i ne s.i
~ O -
s.yses.: Z i.>..
- o H ,.,,,
e se ........
._____________________________ -_____________________________ 1 o . ______________________. .
O til d N
.. ....es., ..... ........ .
O Z .
'a _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . .____4_tett x .. ::
O fr 11. tee til O Z . _ _ _ . 4 . 3 2e3 l l-- 8 7897.I __ ___ ____ . _ _ M Ife 8 7207 3 8'IIII*I H **II*I*I Q . y tes es s e tan s 33g ggg ! w - l e o attesJust $tggilgN , A _B t_ 8 4._t t_ s W
- O m.- _ __ +-i --_ -__ _____ .__ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ - _ _ - _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _
904(8913).00C/ref-41 . , IX. CONCLUSIONS A. Weld seams 2-203 A/C in the Calvert Cliffs Unit I reactor vessel were fabricated using weld wire heats #12008 and #20291 in tandem. B. The preceding weld is equivalent to the McGuire Unit I weld seam 2-442 A/C and to the McGuire surveillance weld - The chemical content and toughness properties of all three sets of welds should, therefore, not vary significantly from' weld to weld. C. The initial toughness properties and the chemical content of the Calvert Gliffs and McGuire welds have been evaluated and can be adopted for use in vessel integrity analyses. D. There is reasonable evidence available to assure that the McGuire Unit I surveillance archive weld is the same material as the block identified as "D2A" received from Westinghouse. E. The McGuire surveillance weld and the surrogate weld are very similar in chemical composition and fabrication process;.therefore, the surrogate weld should provide a reasonable means of obtaining data applicable to the Calvert Cliffs reactor vessel. Report No. 02987-MCC-002, Rev. 00 Page 40 of 43
.904(8913). DOC /ref-42 r
X .' REFERENCES ,
- 1. R. A. Kubhi'and W. B. Sharav, " Advancements in Submerged-Arc Welding of .;
High Impact Steels", Welding Journal, November,1961,, p. 497-s.
- 2. G. D. Uttrachi, " Selecting Fluxes for Submerged-Arc Welding", Welding '
Design & Fabrication, February 1978, p. 78.
- 3. - C. V. Prestowitz, " Selecting Fluxes for Submerged-Arc Welding: low alloy .l
~
steels", Welding Design & Fabrication, February 1978,- p. 82. !
- 4. T. H. North (and others),. " Slag / Metal Interaction, Oxygen and Toughness. l in Submerged-Arc Welding", Welding Journal, March 1978, p.: 62-s. ,
- 5. T. H. North (and others), " Oxygen Content, Aluminum and Notch Toughness ,
of Submerged-Arc Deposits",-Welding Journal, March 1978,.'p. 71-s. i l
- 6. T. W. Eager, " Sources of Weld Metal Oxygen Contamination During Submerged-Arc Welding", Welding Journal, March 1978, p. 76-s.
- 7. D. A. Wright, " Assumptions.and Calculation of RTPTS'at End of. License for. )
Materials in Calvert Cliffs Units 1 and 2 Reactor Vessel Beltline Region", Baltimore Gas & Electric Company, December 23, 1985 (ME & AU Job- ! No. MR-85-170). l
- 8. Letter- from P. Kruse (C-E) to L. E. -Titland (BG&E),- C-E Chattanooga i Metallurgical Records Search, BG&E-10577-437, January 11, 1982.
l 1
- 9. J. N. Kass, et al, " Radiation Effects in Boiling Water Reactor Pressure Vessel Steels", General Electric Company, NED0-21708, October 1977.-
I
; ,10, J. Strosnider, et al, " Computerized Reactor Pressure Vessel Materials '
~
Information System", NUREG-0688, U.S. NRC, October 1980. Report No. 02987-MCC-002, Rev. 00 Page 41 of 43 l
. 1
t > s c . , e {904(8913). DOC /ref-43 v s t
- 11. - Cooper Surveillance Weld Evaluation, General Electric, EPRI Contract RP2180-6, August'1983.
~
- 12. J. A. Davidson:and S.-E. Yanichko, " Duke Power. Company William B._McGuire
~
Unit No. 1 Reactor. Vessel Radiation Surveillance Program", WCAP-91995- i November 1977. ;
~
~
- 13. Letter from J. A. Tiernan-(BG&E) to A. C. Thadani (NRC), " Response-to Pressurized Thermal Shock-Rule", January 23,11986. - *
- 14. C-E Metallurgical-'Research and Development Department Vessel Weld. Test i-Report, Contract 2167,-Job. No. V-70333-017, Weld Seam No. 2-442,-dated March 2, 1970.
- 15. S. E. Yanichko, et al, " Analysis of Capsule U from the Duke Power Company ;
McGuire Unit 1 Reactor Vessel Radiation Surveillance Program", WCAP-10786,. February 1985.
' 16. 10CFR50, Appendix G, " Fracture Toughness Requirements", Federal Register, V. 48, No. 104, May 27, 1983.
S. T. Byrne, " Summary Report on Manufacture of.In-Vessel and Ex-Vessel-17. Surveillance Capsule Assemblies for Calvert Cliffs Unit 1 Reactor . Vessel", Combustion Engineering. Report-TR-2987-MCC-001, January 9, 1989.
- 18. C-E Nuclear Shop. Traveler V-70333-017, Rev. O, " Weld Test Plate B h c ,
Contract 2167, dated 3/11/69. . 19. C-E Drawing SA-2067-27-1, " Weld Test Plate for Middle Shell Course for Westinghouse Electric Corporation 175" I.D. Reactor Vessel", Revision 01 ; dated 3/16/69. Report No. 02987-MCC-002, Rev. 00 Page 42 of 43 , 4
, ..,-,r -, --..,-,,s ,a w +- .. .-,, , - . .-,e-, - . - - , - -# . = , -- m ,---
~
Il l Le. . *- . 904(8913). DOC /ref-44 ,
)
l 1
- 20. C-E Drawing SA-2067-28-0, " Surveillance Weld Test Plates Middle Shell
^
for Westinghouse Electric Corporation 173" I.D. Reactor Vessel", dated 6/27/67. .
- 21. Weld Inspection Record, Test Plates B & C, Job & Control Number 70333-017, Contract 2167, approved 4/29/69.
- 22. Weld Inspection Record, Weld Seam No. 1-203A, Job & Control Number 70617-012, Contract 70167, approved 11/21/68.
, {
l
- 23. ." Summary Report on Manufacture of Test Specimens and Assembly of Capsules i for Irradiation Surveillance of Calvert Cliffs Unit 1 Reactor Vessel !
l Materials", Combustion Engineering Report CENPD-34, February 4 1972.
- 24. U.S. NRC Standard Review Plan,- Section 5.3.2 Pressure-Temperature Limits, Branch Technical Position MTEB 5-2, " Fracture Toughness Requirements",
NUREG-0800, Revision 1, July 1981. 25.
" Evaluation of Pressurized Thermal Shock Effects due to Small Break LOCAs with Loss of Feedwater for the Combustion Engineering NSSS", Combustion Engineering Report CEN-189, December 1981.
- 26. S. T. Byrne et al, " Testing and Evaluation of Calvert Cliffs Units 1 and 2 Reactor Vessel Materials Irradiation Surveillance Program Baseline i
. Samples", Combustion Engineering Report TR-ESS-001, January 31, 1975.
- 27. " Chemical Analysis of Weld Metal Specimens for Baltimore Gas and Electric Company," Wyle Laboratories Report No. 40602-04, July 27, 1989.
l 1 Report No. 02987-MCC-002, Rev. 00 Page 43 of 43 O
904(8913). DOC /ref-45 APPENDIX A CALVERT CLIFFS UNIT'l WELD RECORDS Report No. 02987-MCC-002, Rev. 00 Page A-1 of A-36
r9MBUSTION EI;GINEERING, INC AppnOVED FOR , , S.L ? E ~d S E D E S D.V.".F. hr:, LEAR COMPONENTS DEPARTMEh.' FABRICATION BY L' . - m TED N-1 g 7 _ Chattanooga, Tennessee K 7gy;;-f , CONTRACT NO.: 70167 , DETAIL WELDING PROCEDURE DRAWING No.: E-234~112 NO.: TSAA-2(A) Rev. 0
. -WELD NO.: 1-203 A-C ,
_ E g g usg y ,968 REFEPINCES: M&P 6.1. 2 . 2 (c) , . M&P 4.3.8.5 ), SAA-3.i-27 @ w.y on-Destru'c l} M M
- t/
ivef* Testing: W. i 9fYNgQ ~ 7_ (
~ '
/
- P.T.. ,
M.T. M&P' 2.4.2.4(c) (BC,FF) ~ ' s @ R.T. M&P 2.4.~.1.3 (a) (F)
. g U.T. N" ,
' ~
. o . _, _ , _ . ,
. WELDING CONDITIONS: ;
. .' C' Electrode Type & Size See attached sheet.
Filler Metal Type 6 Size .' , Flux Type & Size .
< Welding Current & Polarity
- Arc Voltage NUCLEAR
- Travel Speed (in/ min.) Q[JQlly p,ng i Shield Gas Type & Flow . DEC9 1953
~ '
~ Gas Cup Size -
P. C. K. Gas Cup .to Work Distance other
. *+ 107. of Value or Range WELDING POSITIONS: Flat .
Preheat: 250- _F., Hold DMXfeUQU60% Until P.W .H.T.
- Interpass: 500 *F. -
Post-weld heat treatment: 1150 *+ 25 *F hold.one hour / inch thicknesslof weld. 7 . Intermediate b.W.H.T. 1100 *+ 50 *F, hold _ 15 minutes.
- e Report No. 02987r.MCC-002, Rev. 00 Page-A-2 of A-36 ,
1
3pi noVid) Nis
. .' pfg.11
. CAT 1oM DY DETAIL WELDING ~ PROCEDURE
_I' gj.y- - No.: .TSAA-2 (A) Rev.0 Sh.ee t : 2 of 2 WELDING SEQUENCE TRAVEL AMPS
- VOLTS-
*lst Pass - 0.D. 3/16"# Mil.B4 Mod. 13 IPM 700 AC 31 NOTE: Use copper backing bar Single Arc 1st Increment - 0.D. 3/16"5 Mil.B4 Mod. 13 IPM 650 AC 31-Single Arc (1) 0.D. to 1 " Level 13 I'PM 650 AC 31 3/16"5 Mil. B4 Mod. -
.. Single Arc (2) I.D. to 1" Level 22 IPM 600/550 AC- 31-3/16"5 Mil. B4 Mod. '
Tandem Arc (3)
- Remainder - I.D.. .
22 IPM 600/550 AC '31 3/16"6 Mil. B4 Mod. Tandem Arc (4) 0.D. to 3" Level - 22 IPM 600/550 AC 31 3/16"5 Mil. B4 Mod.
. Tandem Arc (5)
- Remainder'O.D. .. 22 IPM 600/550 AC. ~ 31 3/16"5 Mil. B4 Mod. Tandem Arc Backweld if required -
1/4"$.-E-8018 C-3 (Fla t only) 325-375'DC-RP 25
. or 3/16"# E-8018 C-3 210-260 DC-RP 25 .
' Flux Linde 1092 65 x 200
~
~
4
. Report' No. 02987-MC.C-002, Rev. 00
.Page A-3 of A-36
., l l
L r COMBUSTION . ENGINEERING , INC.
, NUCLEAR COMPONENTS DEPARTMENA ,. ,.
f . 'CHATTANOCGA, TENNESSEE -
~
I CONTRACT NO.: DETAIL WELDING PROCEDURE
- -DRAWING NO.: NO.: 4TSAA-2 Rev. 1 L
UELD No.i. :, DATE:
, , 1
' REFERENCES i - N&P 6.1.1. 2 (c) ,,, ,
.. EP 4;3.8.5(b),. .
SAA-33-27,
~n- -
'QSAA-llA(3), . QMA-llA(l')F4 ' '
~7 Non-destructive Testing:. // m k -%s _.' ,
p_] .
]
P.T. ' ' s "2 U.T.. - *
/
/k%WN . -N .
, . e
. WELLING ' COIiDITIONS :
~ Single Arc Tandem Arc - :Backwdid Electrode Type & Size- '3/16 3/16"p 34 Mod..1/4"5 E-8018
, "5 B4 Mod. .
C . . Filler' Metal Type & Size i
. i Flux Type.& Size .
1092,65 x 200 1092,65 x 200 -
- Welding Current & Polarity 650-AC 600 4.C 325-375 550 AC DC-RP !
- Arc -Voltage -
31 31 25
- Travel Spe'ed(in/ min ) . 13 22 -
i Shield Gas, Type & Flow 8 - Cas. Cup Size .
- - . =
. Gas Cup to Work Distance -
~
1 Other -
*i 107. of Value or Range .
WILDING'EOSITION: Flat
- t
' Preheat: 250 *F. Hold Rnxnarxhnid. Until P.U.H.T.
*F.
Interpiss:_500 '
. . .l ,
Post-weld. heat treatment:1150 *+ 25 'F hold one hour / inch. . {
~ ~
Intermedi e 1.1 E .
. b *+ 50 .F, hold 15 minutas Report' No. 02987-MCC-002, Rev. 60. Page A-4 of A-36
.ew., w- m-m---
l e WEl. DING PROCEDURE QUA1.!FICATION RECORD / couuunTion cNclNCEftfMC. INc. , o.ee. JUE 12,1967 _
,,o.e,u,, a A- A r7_
[ SEETs 1 0F 2 Wek!.ng Peace NM.D 01C ANEC (TAW A@ jfgf/pf,,,,3,; Ell. Type ancf 5;we-_SAA-533 C:t D. CL 1 Qi? To SA-533 C11 B'CL.1 QLT ' pC_ 7, p%J 1hisiness (and D;a. If Pipei IN Thickness Rang; QuaGfiad 3$$."Thrv.I1.,' WELDING JAATERIA15 rm , u - WELDING PROCIDuti r.N _ - 3,,,, ,,3 A.u. we wr.a: FLAT gi
,3,,,,r. ItICC18193 T.iFE B-h UDD. & p,g p.,; _ FuT -
AFD1 A-31 ttPt E5IN c3 % ,, % ,, ymmv12 g w _LINDE 1092 65 x 200 Nwnhetof Aars:JD p, ,,e2.250*r tmr ::nn*r un twTuo,tn.,, ,,_
% we .
po.u.. :1150*F
- 2; F to fiota:s rtar:ACI Cc; TO 600*F.
I e FOR INFOP/AATION ONLY tand Name Fmee Mats: AM ad w.,e
% g, Asupeees Ars Wlas ledsa/M:n, 1-? . 1M 6 i ~ 650 11 11 (FRO *:7 *.
7,,, C.,,. ,,gg-JLC MA.D*:.M* EAL. 3/16 1 600 11 P2(FRC"? *0 j ,n Caate.ieru Si7, SKETCM TCLOV '
'A NCE: 40 il 22( REA.S._ *r.:)
l
' Es.9E,,, Ego,QTo hr a 125 25 !"A?CA.L _
( ALL WELD METAL AND/OR TRAH3Vit35 JOINT RfDUCIO SECTION TENLE 1EST5 Type seee- wwo.C_ N_:;tnen Aars So ta. U,s. mew Laaf** Uthmaee Si,ess.es. Ch.c La:ne aster Ar.s
. e# Faavre e"?T_t *;* C'M-y
CHARPY V. NOTCH IMPACT TESTS , Lacsi.o= Tene. Veiues Locat.sa Teens. Valwes VELD +10 65.0 54. 0.h
%T i:A2 +10 ILO.O. 8;6.0.106,0 Gut 0E0 EEND Tf575 Depe. Cwwi.ag Tne .J.7,LDI*'*, JLP!EGte"t.
h._ SIDE e,,, 5,us, ,_ACMANLJ se.4 7,ui, wesene J .PJmtDJi Tese Nt: 4206ht. a am Tem La ..!IntLU?.0! CAL EE.1R12 E.:.9 --
""*ff. DEVELOX7.' T_Lsi . s.CFAITAf Mi 7 2357
- e
~~
p3 ~ l we me.e, rius , .mo s P.'. . ma n a .<u. re .. .. e
.<.>< o.as.et.
.. a,ea m. ,ews ,,, er,w. ..e ut c .,.,
onut .n uww t cour.usti N Enctx!!tiNo. IN:. l..r- ' y.J T _- . s, .- ; . . . 12.) a '.' . e ~, l I Report No. 02987-MCC-002, Rev. 00 Page A-5 of A-36 i l I l 1 l l
n- l
- s. 4 N 1 W.P.Q.R. NO.: SAA-33-27 l DATE: JUNE 12, 1967
. j SIEET: 2 0F 2
. i I
i Reduce'd Section Transverse Tensions Area Ultimate Ultimate character and Width Thickness Sq. In. Load Psi Stress Psi Location of Failure 1.006". 2.165" 2.165" 179,000 - 82,700 Duetile in Weld' .
> 1.000" .1.618" 1.618" - 132,000. 81',900 Ductile in Veld 1.007" 1.72h" -1.736" 139,000 80,000 Duetile iri' Base Metal 1.010" 1.6h5" - 1.661" ,
136,000 '81,900 Ductile in Veld. 1.005" 1.816" 1.816" 150,000 82,600 Ductile in Weld 1.000" 2.165" 2.165" 179,000 82,700: Ductile in Veld 1.026" 2.002" 2.05h" 169,000 82,300 Ductile in Weld
- 1.017" 1.727" 1.756"' 1h3,000 81, LOO Ductile in-Weld 1.01h" 1.705" 1.729" 1h2,500' 82,h00 Ductile in Weld .
1 1.003" 1.686" 1.691" 139,500 82,500 Ductile in Yeld '
. l i
Report No. 02987-MCC-002, Rev. 00 Page A-6 of A-36
u vmu u o A A vil n11 tri.M E E nl.N G, IN C. l sumans.r -l- poeu - e m
;.. ~ Nuclear Manufacturing Welding Material Certification Superintendent. Nuclear Nuclear Welding 'and Release for Section III Quality Engineer I 1 .i Applications !
Bay 29 Rod Room '
; Inventory Control jl/
/ r d y p A 7s / f4 A Welding Inspection M "c:2 O';.t. i d . E:::'.; )
i i i i The following welding material has been tested in accordance with the requirements of SOP #100-23.31 and meets the requirements of the 1966 Winter on ASMEAddenda Code work only: to Section III of the ASME Code and is released for I. Coated Electrodes (MA) 9 TYPE SIZE ! HEAT # LOT # CONTROL 4 BRAND l i II. Bare Electrodes (CTA & GMA) TYPE Sp E HEAT # BRAND III. Flux Electrode Combinations (SAA) TYPE ELECTRODE SIZE HEAT # TYPE FLUX LOT # Goa Moo B-9 %"$ AAC. Nao 8-*/ 12coefw nma or2 y e3.2
~3l74 "Y ',
2.039/ fff N Non 8-V fgf l32.f} // wor /092. 'l 6 1.3 PCK:lr . 0CCE Report No. 02987-MCC-002, Rev. 00 M t IR_ Page A-7 of A-36
.f=. . M. -
COMBUSTION ENGINEERING, INC.
,ee,, .. I . - er - -om Mr. P. C. Kiefer Welding Material Qualification Metallurgical Research and To Requirements of ASME Development Department ca: Mr. R. E. Lorentz, Jr. Section III Mr. B. G. Carlton E-7062-A Chattanooga Mr. S. A. Lewis W-32255 Mr. S. R. Lewis October 11, 1968 The following test data is for 3/16" diameter bare wire, type Mod. B-4, heat number 13253, flux type Linde 1092, lot number 3833.
A weld deposit was made using the above heat of wire and lot of flux, welding was done in accordance with C.E. Welding Procedure Specification SAA-11S(2). The complete weldment was given a post weld heat treatment of 1150*F + 25'F for 40 )ours and furnace cooled to 600'F. CHARPY V NO'ICH IMPACTS ' Test Code Pt/Lbs @ +10*F Requirements JH 79, 79, 82 3C Ft/Ibs @.+10*F ALL WELD METAL .505 TDTSILE Yield Strength Ultimate Tensile Elongation Reduction KSI Str.ength KSI in 2" -% of Area-% 66.5 82.9 27.5 67.8 i A T-Bar test was performed on the above material combinations.
, The weld bead was MT tested after welding. Results satisfactory.
l$$QQ g Q/gi , William C. Riggs WCR:1c k'
% ? . . p. 3 b ,o /t l
i i Report No. 02987-MCC-002, Rev. 00 Page A-8 of A-36
.is'...'~al.. . ,-.
COMBUSTION' ENGINEERING, INC. 1
.see. } evasser l mou - oAft Mr.'P. C. Kiefer. Welding Material Qualification Metallurgical Research and ' To Requirements of ASME Development Department cc: Mr. R.:E. Lorentz, Jr. Section III Mr. B. G. Carlton -E-7062-A i Chattanooga Mr. S. A. 14wis W-32255 Mr. S. R. Lewis -
October 11, 1968
)
The following test data is for 3/16" diameter bare wire, type-Mod B-4, heats 2p291 and 12008,'and Linde 1092 flux, lot number 3833. 48 [N A weld deposit was made using the above heats of wire and lot of flux. Welding was~ done in accordance with C.E. Welding Procedure Specification SAA-11S(2). The completed weldment was given a post weld heat treatment of 1150*F + 25'F for 40 hours and furnace cooled to 600*F. ~ CHARPY V NO"ICH IMPACTS Test Code Pt/Ibs @ +10*F Recuirements JI 62, 47, 62 30 Ft/Ias @ +10*F ALL WELD METAL .505 TENSILE Yield Strength Ultimate Tensile Elongation in . Reduction KSI Strencrth KSI 2" -% of Area-% - 70.3 86.5 25.0 63.6 A T-bar test was performed on the above material combinations. The weld head was MT tested after welding. Results satisfactory. W2L William C. Riggs O
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.he requirements of the 1966 Winter Addenda 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 4' BRAND II. Bare Electrodes (CTA & GMA) TYPE SIZE HEAT # BRAND III. Flux Electrode Combinations (SAA) TYPE ELECTRODE SIZE HEAT # TYPE FLUX LOT # B-VMoo y,s 202s/ sna-/o,2 ;e,,
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. COMBUSTION ENGINEERING, INC.
,oo.esscs j suaaner l rnow - oar Mr. P. C. Kiefer Welding Material Qualification Metallurgical Research and To Requirements of ASME Development Depart:nent cct Mr. R. E. krentz, Jr. Section III Mr. B. G. Carlton E-7062-A Chattanooga Mr. S. A. Lewis W-32255 Mr. S. R. 14wis October 11, 1968 The following test data is for 3/16" diameter wire type B-4 Mod. heat number 202.91, and Linde 1092 flux, lot number-3833.
A weld deposit was made using the above heat of wire and lot of flux, Welding was done in accordance with C.E. Welding Procedure Specification SAA-11S(2) . The above weldment was given a post weld heat treatment of 1150*F + 25' for 40 hrs and furnace cooled to 600*F. - CHARFf V NOTCH IMPACTS Test Code Pt/Lbs @ +10*F _ Requirements JC 35, 50, 48 30Ft/Ibs @+10*F ALL ' ELD METAL .505 TENSILE Yield Strength Ultimate Tensile Elongation Reduction KSI Strenerth KSI in 2"-% of Area -% 70.5 88.0 25.5 67.1 i A T-Bar test was performed on the above material combinations. i The veld head was MT tested after welding. Results were i satisfactory. . j
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- 904(8913).00C/ref-46 APPENDIX B MCGUIRE UNIT I WELD RECORDS 1
I l 4 l l l l Report No. 02987-MCC-002, Rev. 00 Page B-1 or R-19 l
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COMBUSTION ENGINEERING, INC. '
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1 T PJ> NUCLEAR COMPONENTS DEPARTMENT p( CHATTANOOGA, TENNESSEE l fl 6 CONTRACT NO.: DETAIL WELDING PROCEDURE DRAWING NO.: NO.: TSAA-2 Rev. 1.
, WELD NO.! . . DATE: ,
REFERENCES i N&P 6.1.1.2(c),,,
. EP 4.3.8.5(b), ,.
SAA-33-27, ~
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U.T. WELLING CONDITIONS: Single Arc Tandem Are Backwsid Electrode. Type & Size 3/16"O B4 Mod. 3/16"E 34 Mod. 1/4"C E-8018 C-3 Filler Metal Type & Size - - - Flux Type.& Size 1092,65 x 200 1092,65 x 200 -
- Welding Current & Polarity 650 AC 600 AC 325-375 550 AC DC-RP
- Arc Voltage 31 31 25
- Travel Speed (in/ min.) 13 22 -
Shield Gas Type & Flow ' - Gas Cup Size - - - Gas Cup to Work Distance - Other
*+ 107. of Value or Range WELDING FOSITION: Flat
. Preheat: 250 *F. Hold Raxantxkmid. Until P.W.H.T.
Interpass: 500 *F. Post-weld heat treatment:1150 *+ 25 *F hold one hour / inch. thickness of weld. Intermediate F.U.H.T. 1100.
*+ 50 *F, hold _ 15 minutes
' Report No. 02987-MCC-002, Rev. 00 Page B-3 of B-19
f I i p 3 * *g ,-t i l nl V j WE!.DgTa4fMINSPECTION 15-RECORD g, g# ,3 ;
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d4 A- 3 ? ~ A 7 Ad-nA(s) PROCEDURE REQUIREMENTS #4 34f)(p BASE METAL TYPE ~3 FILLER METAL TYPE M //Od. dar/de m FILLER METAL $l2E PREHEAT & INTERPA$$ RANGE O f8***8** MAINTAIN d5 l CTHER REQUIREMENTS - I 5 Nc/t. /09.L , ta5 ) to o - 3 t 3 INSPECTION RESULTS FILLER METAL TYPE ?V 7- Y for y FILLER METAL $1ZE
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- NJ' MAINTAIN 7fS OTHER REQUIREMENTS O' .d .') ';$O /,5 J .t . r ff I IN$PECTION RESULT 5 FILLER METAL TYPE /3 Y d -il f( vi g l FILLER METAL SIZE -
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WELD INSPECTION RECORD
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==[/ eve /8 ' /0 9. y (+6 k l o 3 - -7 - 3E[
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- REMARKS tNSPECTOR & CATES S G. y I 'r 1 m. 4 1-4 ; E 'l- I-G i C 2 4. -04 M.s * ? [4-:- A ff. 4 3-l,1 m. V- i-G 7 A & - Sei /. f. 7. c. 7 m. /. *r 3 7 / /-T-3 7 ril /-f. .,1 0 -%'t & -; S6-4.1o.49 m. 4. t o-t. 4 SM II-4? P1-f-//~59 sic / /:~t M ht3 41 A V-11-A So-t/~/1 l,7 f.-U-/ B- 61 Cfb Vvf G1 M-VM 4 9 E '/-tV<.1 $G-o'-/Ri
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APPeovEo 4 oATE /-se-of 1 Report No. 02987-MCC-002, Rev. 00 Page B-6 of B-19 l l l l
p p, 8 L Mr'. J. S. Meek - Conl8UST10H ENGINEERlHG, INC. Page 1 of 3 , cc: Mrs; P. Webb (2) NFTAI 31 CAL RESEARCH AND DEVEL g'T DEPT, Mr. J. Brasfield . VE5SEL WFLD TEST REPORT Corrected Cor Mr. S. R. Lewis Mr. R. E . Lorentz, Jr.
$5'TodE Westin-Souse CONTRACT NO. 2167 MATERIAL SA-533. Gr. B. Ct.1 Jos No. V-T0333-017 DtG. MO _ E-215-454 SA-2067-27 & 28 SEAM NO. 2-442 DETAll DELD PROCEDURE NO. TSAA-2-1 TK S-5/8 Codes B-5012-2 & 3 Test Plate *B" ;
, FILLER METAL (TTPE, HT. AND SIZE) 3/16" dia. B-4. Ht. No. 20291 & 12008 FLUX (TTPE AND LCT) CR CAS 1092 - 65 x 200 Lot No. 3854 POST WELD HEAT TREATMENT: TEMP._1150* F *2 5' H RS. 40 ALL WELD METAL AND/OR TRAN5VER$E JolNT REDUCED $ECTION TENilLE TEST 5 TYPE DudN530M5 AREA VLTIM&Tt ULTasATE CHARACTER AND S*!CWEN W1DTM TMICENti$ SQ. Bd LOAD LS$ STRESS P5: LCKATION OF FAFLLTI I
bLL ATTAGhLD 5tiLUE i i CHARPY V-NOTCH IMPACT TEST 1 Locatics tras* vAtuts Location i True. watUrs
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. 1 a
Report No. 02987-MCC-002, Rev. 00 Page B-7 of B-19 -
;. .n . . m .
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All Weld Metal CVN Impacts
% Mils "
Temp. Pt/Lbs .__ Shear I,at . Exp .
-80 15 0 12
-80 . 16 0_ 12
-40 49 30 36
-40 38 30 32
.. -40 - 45 30 35
+10' 71 40 52
+10 60 35 44
+10 , 73 40 49
+40 81 45 58
+40 90 50 63
+40 , 88 50 64
+110 100 90 81
+110 , 93 95 83
+160 111 100 82
+160 110 100 88 -
All Weld Metal .505 Tensiles Yield Strength Ultimate Tensile Elongation Reduction Test Code KSI Strenoth KSI in 2" % of Area % NIWA 65.4 82.1 28.5 69.1 NIWB 65.3 81.2 30.0 68.5 Drop Weichts F
~
-40*F
- 1 NF
-50*F -
2 NF
-60*F -
1F . NDT = -60 F , l' i s t Report No. 02987-MCC-002, Rev. 00 Page B-8 of B-19
II - - -- - - -' ' - - - ' ' - - - ' - '- v -
^
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. .. ja 3 cf 3 Heat Affected Zone Charov Mus Temp. Ft/Lbs. Shear _ Lat . Exp .
-80 21 1 14
-80 19 1 12 .
-40 25 20 22
-40 37 25 28
-40 43 30 32
+10 43 35 34
+10 40 30 33
+10 95 60 61
+40 -58 40 42
+40 61 . 45 .. 45
+40 62 40 46
+110 94 90 67 .
71
+110 98 90
+160 82 100 70 '
+160 80 100, 70 Heat Affected Zo[se .505 Tensile Yield Strength Ultimate Tensile Elongation Reduction Test. Code KST Strencth KSI in 2" % of Area %
NIZ-A 64.9 82.1 22.0 69.1 NIZ-B 65.6 82.9 22.5 69.3 i Drop Weichts
-40*F -
2 NF
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1F NDI = -50*F. NOTE: Center of tensile was located in the heat affected zone. 4 9 *
- 4
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4 POWER SYSTEMS Subject From
. Tag = A. B. Harper ' Westinghouse Electric Corp. Metallurgical & Mate.. ,
Surveillance Test Materials Laboratory - Chattan Contract No. 2167 ces.. . Peggy Webb- Job No. (V-70351) K-41095. May 12, 1976 Project No. 960001 ;
. t Attached: '
Chemical analysis including all elements listed under ASTM E-350 and - description of subject materials. k ' 'n , W. A. Hou'se ' WAH/sh . Enc. i f-&/W- > g-s& d- 3 f tW7 r i Report No. 02987-MCC-002 Rev. 00 Page B-10 of 8-19
p
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l Base Materials
, Lab No. P16376 P16377 Code No. B-5012-2 B-5012-3 Si 0.22 0.22 S 0.010 0.006 P 0.007 0.006 Mn- 1.37 1.42 ;
C 0.22 0.19 i Cr 0.07 0.05 Ni 0.62 0.70 i Mo 0.61 0.58 3 <.001 <.001 Cb <.01 <.01 T1 <.01 <.01 Co 0.016 0.012 Cu 0.13 0.10 A1 0.020 0.022 . N2 0.005 0.007 V 0.003 0.002 W < . 01' <.01 As 0.005 - 0.003 Sn 0.006 0.004 Zr <.001 <.001 Sb 0.0021 0.0014 Pt <.001 <.001 Report No. 02987-MCC-002, Rev. 00 Page B-11 of B-19
rt
, ~. .
Weld Nkterial Lab No. D24117 Si 0.24 S' O.008 P '0.011 Hn 1.36 ' ' C 0.10 Cr 0.04'
-Ni 0. 88 --
Ho 0.55 B <.001 Cb <.01 T1 <.01 Co - 0.014 Cu 0.21 A1 0.003 N2- 0.008 . . V 0.04 W <.01 As 0.009 Sn 0.007 . Zr <.001 Sb 0.0022 Pb <.001 .
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Table 2 Mil-B4 Mod. Wire Heat 13253 ' chemical Analyses (w/o) Wire Deposit III chemical MML Wire cert. Element R-2083 Adcom (7/19/67) C 0.146 0.15 Mn 1.87 1.83 P 0.013 0.013 - S 0.012 d.015 Si <.05 0.06 Ni 0.73 0.72 Cr 0.04 Mo 0.51 0.45 Cu 0.07 Notes:
'1) MML - Metallurgical and Materials Laboratory (chattanooga), Lab Reports -
i l i i Report No. 02987-MCC-002, Rev. 00 Page C-5 of C-8
' = ,.'
Table 3 M11-B4 Mod. Wire Heat 12008 Chemical Analyses (w/o) Wire Deposit III
~
Chemical MML Wire Cert. Element R-1990 Adcom (7/19/67) C ' O.11 0.13 Mn - 1.81 1.92 P 0.008 0.010 S 0.009 0.015 Si 0.09 , 0.05 r N1 1.,00 0.99 , Cr 0.06 Mo. - 0.46 0.51 Cu 0.13 Notes: '
- 1) MML - Metallurgical and Materials Laboratory (Chattanooga), Lab Reports ,
Report No. 02987-MCC-002, Rev. 00 Page C-6 of C-8
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+160 117.0 100 81' AcorflCNAL DATA NCLLO:N. NEAT TEIATHENT: i (c ) 1550-1650*r for 4 hours - L'ater quenched.'
' [b) 1225'r + 25'r 4 hours.
(c) 1150*r { 25'r for 40 hours. furnace cool'ed to 600*P. The specimens were taken parallel to the major rolling direction ef the, plate et ths }/47,l oel. The impacts were notched perpendicular to the plate surface. f = t-2m
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.tiily 31, 1963
-p Report NO. 02987-MCC-002. Rev. 00 Page C-8 Of C-8
ATTACIIMENT (2) COMBUSTION ENGINEERING DOCUMENT:
" RESPONSE TO USNRC QUESTION ON DIFFERENCES IN REPORTED NICKEL CONTENT MAY 14,1992" l
i Baltimore Gas and Electric Company 1 Docket Nos. 50-317 & 50-318 April 11,1995 l y-- - - _
e e e COMBUSTION ENGINEERING, INC. RESPONSE TO USNRC QUESTION ON , DIFFERENCES IN REPORTED NICKEL CONTENT MAY 14, 1992 t ABB COMBUSTION ENGINEERING NUCLEAR POWER , COMBUSTION ENGINEERING, INC. WINDSOR, CONNECTICUT
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Combustion Engineering,.Inc. May 14, 1992 Response to USNRC Question on Differences in Reported Nickel Content Question 1: Section 1.0 of "Calvert Cliffs Unit No. 1 and No. 2 Reactor Vessel Beltline Materials," Revision 2, indicates MIL B-4 Modified weld wire with nickel in the range of 0.6 to 1.1 wt. % was used to fabricate the reactor vessels. Heats No. 33A277 and No. 10137 are reported to have 0.23 wt. % and 0.05 wt. %, respectively. If MIL B-4 Modified weld wire was used to fabricate the welds in the Calvert Cliffs reactor vessels, why do welds using Heats No. 33A277 and No. 10137 wire have less than 0.6 wt. t nickel?
Response
Heats No. 33A277 and No. 10137 were not MIL B-4 Modified, they were designated MIL B-4 (Hi-Mn-Mo) without a specified nickel content. Heat No. A8746 was also a MIL B-4. The following statement in Section 1.0 of "Calvert Cliffs Unit No. 1 and No. 2 Reactor Vessel Beltline Materials," Revision 2 (Attachment A to BG&E's December 13, 1991 PTS submittal,' Reference b) is incorrect:
"For the Calvert Cliffs Vessels, CE employed a submerged arc welding process using MIL B-4 Modified (Mn-Mo-Ni) wire with nickel in the range of 0.6 to 1.1 wt. %. The MIL B-4 Modified (Mn-Mo-Ni) welds were produced with either a Linde 1092, 0091 or 124 flux."
l The statement should be replaced in its entirety with: i, "For the Calvert Cliffs Vessels, CE employed a submerged arc welding process using wire designated in supplier certifications as MIL B-4 and MIL B-4 Modified. The designation " MIL B-4 Modified" was used for Mn-Mo-Ni electrodes with nickel specified as 1% or 0.75%. The designation MIL B-4 was used for Mn-Mo electrodes with no specified nickel content. The MIL B-4 Modified welds were made with Linde 1092 flux. The MIL B-4 welds were made with Linde 0091 flux or Linde 124 flux."
a Combustion Engineering, Inc. May 14, 1992 Discussion - BG&E commissioned ABB/CE to review welding electrode purchase specifications between November, 1965 and February, 1971. Weld material certifications and release reports spanning the period between October, 1968 and June, 1971 were also reviewed. The electrode specifications were reviewed for terminology and ] required nickel content. The results indicate that whenever the designation ;
" MIL B-4" was used, the electrode was Manganese-Molybdenum (Mn-Mo) without a l nickel content specified. Whenever the designation " MIL B-4 Modified" was ;
used, the electrode was Manganese-Molybdenum-Nickel (Mn-Mo-Ni) with Nickel l specified as 1% or 0.75%. The weld material certification and release reports functioned to officially j release the electrode / flux combinations for use on ASME Code Section III work. Several identification documents were attached to the reports including CE laboratory tests and the electrode supplier's certifications. The supplier certifications refer tc: Hi-Mn-Mo Mn-Mo-Ni Mn-Mo-1%Ni j 3/4%Ni-Mn-Mo j i Where: Hi - High, Mn = Manganese, Mo = Molybdenum, and Ni - Nickel ! The CE laboratory tests and the supplier certifications reported nickel ; contents for the three types of Mn-Mo-Ni materials but not for the Hi-Mn-Mo ! materials. We expect Ni to be low in the Hi-Mn-Mo materials because it was l l not an intentional alloying addition. The CCNPP Units No. 1 and No. 2 beltline welds are listed in Table 1 below. For each weld seam, the nickel content reported in BG&E's December 13, 1991 ; PTS submittal, the specified weld wire type (per weld procedure), the wire heat number (s), and the weld wire type given in the supplier certification l (where known) are indicated. The reported nickel content and the wire type are consistent in all cases except for Unit No. 2 Welds No. 2-203 A, B, C; for these welds the nickel content was conservatively estimated in the December 13 submittal. Based on the results of this records review and pending QA verification of the records, BG&E expects to revise its estimate of upper bound nickel content for Unit No. 2 Weld Seams No. 2-203 A, B, C to approximately 0.20% Ni.
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- ,; ~e Combustion Engineering, Inc.
May 14, 1992 TABLE 1 CCNPP BELTLINE WELD WIRES Reported Specified Wire CCNPP Nickel Weld Heat Certified Weld l Unit Weld Seam Content Wire Type No. Wire Type l [ 1 2-203 A/C 0.88 B4 Mod 12008 B4 Mod (Mn-Mo-1%Ni) B4 Mod 20291 B4 Mod
- l 1 3-203 A/C 0.69 B4 Mod 21935 B4 Mod
- 1 9-203 0.23 B4 33A277 B4-(Hi-Mn-Mo) 2 2-203 A/C 1,01 B4 A8746 B4*
2 3-203 A/C 0.23 B4 33A277 B4 (Hi-Mn-Mo) 2 9-203 0.05 B4 10137 B4 (Hi-Mn-Mo)
- Supplier Certification Designation not verified.
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ATTACHMENT (3) COMilUSTION ENGINEERING DOCUMENT:
"CE-NPSD-906 CilEMICAL CONTENT OF WELD DEPOSITS FABRICATED USING 11 EATS A8746 AND 34B009
. PREPARED FOR TIIE COMBUSTION ENGINEERING OWNERS GROUP FEBRUARY 1993" i
Baltimore Gas and Electric Company Docket Nos. 50-317 & 50-318 April 11,1995 4 a _____ ____ _______}}