ML20058G184

Nonproprietary Reactor Vessel Weld Matls for Calvert Cliffs Unit 1 Suppl Surveillance Program. Rept Issued as 02987-MCC-002 in 1989 as Internal Rept

ML20058G184
Person / Time
Site:	Calvert Cliffs
Issue date:	11/30/1993
From:	Byrne S ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY
To:
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ML19311B212	List: ML20058G166 ML20058G175 ML20058G184
References
CEN-612-NP, NUDOCS 9312090122
Download: ML20058G184 (108)

Text

I CEN-612-NP REACTOR VESSEL WELD MATERIALS FOR CALVERT CLIFFS UNIT 1 SUPPLEMENTAL SURVEILLANCE PROGRAM i

l NOVEMBER 1993 l

I COMBUSTION ENGINEERING, INC.

Windsor, Connecticut WY l

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9312090122 931129 PDR ADOCK 05000317 P

PDR

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i LEGAL NOTICE I

SPONSORED BY THIS REPORT WAS PREPARED AS AN ACCOUNT OF WORK!

NEITHER ABB. COMBUSTION ENGINEERING f

z ABB COMBUSTION ENGINEERING.

l NOR ANY PERSON ACTING ON ITS BEHALF:

ISKES ANY WARRANTY OR REPRESENTATION, EXPRESS OR IMPLIED INCERDING THE WARRANTIES OF FITNESS FOR A PARTIC A.

PURPOSE OR EERCHANTABILITY, WITH RESPECT TO THE ' ACCURACY, COMPLETENESS, OR USEFUIRESS OF THE INFORMATION CONTAINED IN THIS 4

APPARATUS, METHOC, REPORT, OR THAT THE USE OF ANY INFORMATION, OR PROCESS DISCICSED IN THIS REPORT MAY NOT INFRINGE PR OWNED RIGHTS T OR ASSUNES ANY LIABILITIES WITH RESPECT TO THE USE OR FO DAMAGES RESULTING FROM THE USE OF, ANY INFORMATION, APPARAnis,

B.

METHOD OR PROCESS DISCI 4 SED IN THIS REPORT.

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FORWARD.

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g This proprietary report, CEN-612-P was issued as 02987-MCC-002 in 1989 as an internal

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report. It is being reissued withor t.hange to the content for use external to Combustion Engineering, Inc.

This document contains proprietary information and is not to be transmitted or reproduced l

without specific written approval from Combustion Engineering, Inc.

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i 904(8913). DOC /rc7-2

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1 Reactor Vessel Weld Materials for Calvert Cliffs Unit I Supplemental Surveillance Program f

Report No. 02987-MCC-002, Revision 00 7

Nuclear Power Businesses COMBUSTION ENGINEERING, INC.

Windsor, Connecticut i

Prepared By:.

M Date: / 2 -/2 - P F

.l S. T. Byrne, Consultant j

Approved By: MM M

Date: M 4 5 /g 1 W. R. Gahwiller, Supervisor, j

Haterials Technology i

Date: /k/3 /f f Approved By:

M-N S. M. Schlost. Manager, Materials and Chemical Technology j

OA Statusi Verified The safety related design information contained in this document has been i

reviewed and satisfies (where applicable) the items contained on checklist (s) f,

, and of the Quality Assurance Procedures Manual.

l This review is so certified.-

IndependentReviewer[f? j[/L Date 12 12-79 Aw. 00 l

l Issue Date:

12/18/89 Page 1 of 43

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TABLE OF CONTENTS l

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SECTION TITLE PAGE NO.

1 I

Introduction 5

a II Tandem Arc Welds 7

i III Equivaleacs of Calvert Cliffs and McGuire Welds 9

IV Weld Chemical Content 17 V

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 B-1 APPENDIX C Surrogate Weld Records C-1 y

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i LIST OF TABLES TABLE NO. TITLE pAGE NO.

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Comparison of Weld Process Details 12 t

2 Expected Effects of Flux Type on the As-Deposited 13 Weld Properties Using the Same Weld Wire i

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3 As-Deposited Weld Chemistries as a Function of 14 Flux Type s

4 As-Deposited Weld Chemistries as a Function of Flux Lot 15 5

Weld Deposit Analysis Source Data 18 l

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McGuire Unit 1 Surveillance Weld Chemical Content 19 l

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Supplemental Analysis of McGuire Unit 1 Archive 20 Weld Block

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McGuire Unit 1 Test Plate B Weld Impact Properties 23 9

McGuire Unit 1 Pre-Irradiation Surveillance Weld 24 j

Impact Properties r

f 10 Surrogate Weld Process Details 33 11 Supplemental Analysis of Surrogate Weld Block 34 12 Calvert Cliffs Unit 1 Beltline Plates 37 l

Calvert Cliffs Unit 1 Beltline Welds 38-13 l

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904(8913). DOC /ref-5 r

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LIST OF FIGURES t

FIGURE NO.

TITLE PAGE NO.

1 J-Groove Weld Configuration 16 2A McGuire Weld Impact Properties, Charpy Energy 25 28 McGuire Weld Impact Properties, Lateral Expansion 26 2C McGuire Weld Impact Properties, Shear Fracture 27 I

3 McGuire Archive Surveillance Weld Block 30 4

Surrogate Weld Block 35

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5 Calvert Cliffs Unit 1 Pressure Vessel View 39 l

-l Report No. 02987-MCC-002, Rev. 00 Page 4 of 43 j

t 904(8913).DDC/ref-6 I.

INTRODUCTION The reactor vessel surveillance program for Calvert Cliffs Unit I was designed I

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 l

archive weld was located and a portion was provided for BG&E use.

i Additiona!1y, 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 I supplemental surveillance program, and to establish the traceability and the known physical properties of tnose weld materials.

i Section II provides information establishing that the controlling weld seam in I

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 l

McGuire surveillance weld in vessel integrity evaluation efforts for Calvert i

Cliffs. Sections IV and V review the available materials property data j

Report No. 02987-MCC-002, Rev. 00 Page 5 of 43

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applicable to-the Calvert Cliffs controlling weld and provide the bases for the chemical content and initial reference temperature of that weld. Section.

l VI traces the McGuire surveillance weld from initial fabrication through delivery to Combustion Engineering for the purpose of establishing the pedigree of the material used for test specimens encapsulated in a Calvert

- Cliffs Unit I replacement surveillance capsule.Section VII provides similar documentation behind the " surrogate" weldment used to augment the McGuire material.Section VIII summarizes and documents the source of information for all the plates and welds in the beltline of the Calvert Cliffs Unit I reactor vessel.

Selected documents referenced in the report are included in the

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Appendices.

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II. TANDEM ARC WELDS The purpose of this section is to establish that weld seams 2-203 A, B and C 1

(also identified as 2-203 A/C) in the Calvert Cliffs Unit I reactor vessel were fabricated using weld wire heats #12008 and #20291 in tandem. [r.

i This information is needtd to establish the chemical content and initial toug'hness properties of the reactor vessel beltline welds.

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l In sumary, weld seams were fabricated using weld wire heats #12008 and #20291

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i Pertinent records supporting this conclusion are contained in AppendiiA.

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904(8913). DOC /ref-10 III. EOUIVALENCE OF CALVERT CLIFFS AND MCGUIRE WELDS 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.

Equivalence implies that the welds will have the same chemical content, the same initial strength and toughness, and the same response to neutron irradiation.

l 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 j

McGuire Unit I surveillance weld (Test Plates B & C)

This information was extracted from Weld Inspection Record forms (WIF),

fabrication drawings and shop travelers generated by C-E Chattanooga at the time of manufacture. As noted in Table 1, 1

l All of the adjoining plates were SA-533B Class I 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 0.55 to 0.66% for the six plates (See Appendices A and B).

d Report No. 02987-MCC-002, Rev. 00 Page 9 of 43

l 904(8913). DOC /ref-11 The post-weld heat treatment (PWHT) requirement 1

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In summary, the design, fabrication and heat treatnent requirements for the three sets of welds were identical. The same two heats of weld wire (Mil i

B4-Mod. heats #12008 and #20291) were used with the same type of flux (Linde 1092), and the sanie type of base materials (SA-533B Class 1) for all three sets of welds. The only apparent differences between the Calvert Cliffs Unit I 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 flux:

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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 pri. nary 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 j

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.

1 Establishing the significance of this requires an understanding of flux types.

Linde 1092 flux is intended primarily to blanket the weld puddle Report No. 02987-MCC-002, Rev. 00 Page 10 of 43

i 904(8913). DOC /ref-12

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The effect of flux lot on weld deposit chemical content is illustrated in Table 4.

The data in Table 3, therefore, demonstrate that the effect of flux type is predictable. For welds fabricated using Linde 1092 flux, B

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l Specific to the case of the two lots of Linde 1092 described in Table 1, f

the copper and nickel content, therefore, can be expected to be t

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.

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Report No. 02987-MCC-002, Rev. 00 Page 11 of 43 f

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TABLE 1 i

l Comparison of Wald Process Data Calvert Cliffs Unit 1 McGuire Unit-1 McGuire Unit 1 Weldment 2-203 A/C 2-442 A/C Surveillance

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Contract No.

Weld Procedure No.

Reference Proc. No.

Flux Type Flux Lot No.

Wire Type Wire Heat Completion Date Weld Configuration Dwg. Reference Post-Weld Heat Treat 3

l Adjoining Plates

_ D-7206-1 B-5012-1 B-5012-2 0-7206-2 B-5012-2 B-5012-3

.i D-7206-3 B-5012-3 i

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TABLE 2 O

Expected Effect of Flux Type on the As-Deposited Weld a

Properties Using the Same Weld Wire k?

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Weld Chemical Content

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Linde flux Flux Basicity Ratio Non-Metallic n

y Type (Ca0/SiO )

Inclusion Oxygen Silicon Hanganese Sulfur Phosphorus 2

8 he

'a t;

0

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TABLE 3 e

As-Deposited Weld Chemistries as a Function of Flux Type l

l Weld Deposit Weld Deposit j

Weld Wire Linde 124 Linde 0091 Elements Heat #83637 (w/o)

Lot #1122 (w/o)

Lot #0951 (w/o)

Si S

P Mn C

4 Cr Ni Mo Cu V

Report No. 02987-MCC-002, Rev. 00 Page 14 of 43

Figure 1 J Groove Weld Configuration i

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TABLE 4 As-Deposited Weld Chemistries as a Function of Flux Lot (Weld Wire Heat #4P7869)

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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/o) i Si 4

S P

i Mn C

r Cr Ni r

Mo i

Cu V

h i

Report No. 02987-MCC-002, Rev. 00 Page 15 of 43 r -.

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904(8913). DOC /ref-18 l

IV. WELD CHEMICAL CONTENT The purpose of this section is to establish the chemical content o' th

..lds fabricated using weld wire heats #12008 and #20291 with Linde 1092 flux. The-copper and nickel 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 chemical content is summarized in Table 5.

The table is reproduced from

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Reference 7.

t 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 1 weld seams 2-203 A/C. (13)

Table 6 presents the full chemical analysis as reported for the McGuire Unit 1 l

surveillance weld (12)

Table 7 summarizes results of supplemental-analyses (27) performed on a portion of the McGuire surveillance weld archive block.

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904(8913).00C/ref-19 TABLE 5 Weld Deposit Analysis Source Data l

Wire Flux Flux Laboratory Source Heat No.

Type tot No.

Cu (w/o)

Ni (w/o)

Analysis No.

Reference

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8-8 8

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20291 1092 3833 0.21 0.74 NA 9,10 20291 1092 3833 0.22*

0.73*

NA 11 i

12008 &

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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 O.21 w/o Cu 0.87 w/o Ni

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• Average of five analyses.

NA - Not Available Report No. 02987-MCC-002, Rev. 00 Page 18 of 43 e

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TABLE 6 McGuire Unit 1 Surveillance Weld i

Chemical Content (12)

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i Chemical Content i

Element (Weicht %)

r Si 0.24-h S

0.008 P

0.011

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Mn 1.36 r

C 0.10 t

Cr 0.04 l

Ni 0.88 j

Mo 0.55 t

Cu 0.21 V

0.04 Sn 0.007 l

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.i TABLE 7

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Supplemental Analysis of McGuire Unit 1 Archive Weld Block (27)

I Chemical Content l

Element (weicht ",')

l Si 0.24 S

0.011

]

P 0.014 l

Mn 1.28 C

0.10 i

Cr 0.05 Ni 0.89

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Mo 0.53 Cu 0.19 l

V 0.005

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Sn 0.009 j

1 Co 0.017 B

0.0002 Nb 0.002 Ti

< 0.001 W

0.005 As 0.015 N

0.0085 Zr

, < 0.001 Pb

<0.002 j

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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 i

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 weld wire heats #12008 and #20291 with Linde 1092 flux:

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i ii) 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 i

wire heats #12008 and #20291, and Linde 1092 flux lot #3854.

The Charpy and drop weight data from the weld qualification tests (Table 8)

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can be used to establish an initial RTNDT in accordance with the ASME Code,Section III, NB-2300.

i the resultant value of initial RTi!9T -,60'F 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 to.the weld qualification test data in Figures 2A, 28 and 2C (impact energy, lateral expansion and percent shear fract.ure versus temperature, Report No. 02987-MCC-002, Rev. 00 Page 21 of 43

904(8913). DOC /ref-23 respectively). The data are very consistent in the 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

- 10*F per NB2300. Accordingly, RTNDT is the higher of T

- 60*F or.

cv cv NDTT:

T 10 -50*F cv 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 and McGuire vessels and is provided only for reference.)

Report No. 02987-MCC-002, Rev. 00 Page 22 of 43

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l TABLE 8

't McGuire Unit 1 Test Plate B Weld Impact Properties I

Charov Impact Tests Impact Energy lateral l

Test Temp. (*F)

(Ft/lbs.)

Shear (%)

Expansion (mils) l

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-80

-80

-40 l

-40

-40

+10

+

+10

+10 i

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+40 J

+40 i

+40 i

+110

+110

+160 l

+160 l

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Dron Weicht Tests i

Test Temo. (*F)

Test Result

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TABLE 9 i

McGuire Unit 1 Pre-Irradiation Surveillance

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Weld Impact Properties

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Impact Energy lateral Test Temp. (*F)

(Ft/Lbs.)

Shear (%)

Expansion (mils)

-100 4.5 6

1

-100 4.2 6

1.5 t

-35 11.5 23 11 l

l

-35 30 27 26 0

15 35 17 0

31 40 29 O

65 47 53 l

25 75 60 61

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25 60 47 49 50 74.5 60 63 l

50 58 55 47

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100 105 93 84 l

t 100 96 85 80 150 105 92 86 4

150 113 100 89 l

]

210 113 100 87 210 112 100 84 210 110 100 86 l

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4 Report No. 02987-MCC-002, Rev. 00 Page 24 of 43

Figure 2A McGuire deld Impact Properties Charpy Energy L

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Figure 2B McGuire deld Impact Properties Lateral Expansion

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i Figure 2C McGuire Weld Impact Properties Shear Fracture I

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VI. MCGUIRE ARCHIVE MATERIAL TRACEABILITY l

Ihe 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

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l II7) l for a Calvert Cliffs Unit I supplemental surveillance capsule l

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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 Report No. 02987-MCC-002, Rev. 00 Page 28 of 43 l

904(8913). DOC /ref-30 I

verified and a piece containing apprc..imately two inches of the weld length l

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was removed (see Figure 3). Twenty fotr Charpy. blanks were machined from the two inch piece (see Reference 17), and the remaining trim piece (approximately O.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 l

consistent with the chemical content reported for the McGuire Unit 1 surveillance weld (15)

The available records, therefore, connect the original fabrication records' for Test Plate B with weld block D2A. Since "D2A" was stamped en the block received by C-E, the block dimensions are in reasonable 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

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surveillance weld block. Recon ds 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 weldment 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 (17),

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 certifications generated by C-E Chattanooga. Both welds were fabricated in the same fashion.

d Report No. 02987-MCC-002, Rev. 00 Page 31 of 43 i

i

.i 904(8913).DCC/ref-33 i

t

?

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 l

used to fabricate the Charpy impact specimens as described in the capsule

~

fabrication report (17)

Comparison of Table 11 results with Tables 6 and 7 demonstrate that the surrogate weld chemical content is nearly identical to l

that of the McGuire Unit 1-surveillance weld. The similarity in chemical 7

content and fabrication process demoi trates the potential for using the l

nozzle cut-out weld as a surrogate for the Calvert Cliffs surveillance program. Pertinent records on the surrogate weld are included in Appendix C.

i i

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Report No. 02987-MCC-002, Rev. 00 Page 32 of 43

904(8913). DOC /ref*34 i

t TABLE 10 i

Surrogate Weld Process Data i

Surrogate Weld Calvert Cliffs Unit 1-2-203 A/C Contract No.

I Weld Procedure No.

Reference Proc. No.

Flux Type Flux Lot No.

i Wire Type i

Wire Heat Completion Date Weld Configuration Dwg. Reference i

Post-Weld Heat Treat.

Adjoining Plates

~

D-7206-1 D-7206-2 D-7206-3 1

t 1

Report No. 02987-MCC-002, Rev. 00 Page 33 of 43

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i TABLE 11 Supplemental Analysis of Surrogate Weld Block (27)

Chemical Content Element (weicht %)

S1 0.23 1

S 0.012 P

0.012 Mn 1.16 C

0.09 Cr 0.05 i

Ni 0.86 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-l N

0.0096 Zr 0.001 t

Pb

< 0.002

~

i i

Report No. 02987-MCC-002, Rev. 00 Page 34 of 43 I

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904(8913). DOC /ref-37 i

i VIII. CALVERT CLIFFS UNIT 1 REACTOR VESSEL 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 l

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 I

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 l

vessel is shown in Figure 5.

The locations of the primary coolant nozzles and l

the extent of the active core are also indicated in the " flattened out" view

\\

of the vessel.

i i

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i Report No. 02987-MCC-002, Rev. 00 Page 36 of 43

=

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904(8913).00C/ref-38 TABLE 12 Calvert Cliffs Unit 1 Beltline Plates II)

III NDTT(2)

RTNDT(3)

Ni Plate Cu Number Heat Number (w/o)

(w/0)

(*F)

(*F)

D-7206-1 C4351-2

.11

.55'

-10

+20 0-7206-2 C4441-2

.12

.64

-30

-30 D-7206-3 C4441-1

.12

.64 0

+10 l

D-7207-1 C4420-1

.13

.54 0

+10 D-7207-2 B8489-2

.11

.56

-10

-10 D-7207-3 88489-1

.11

.53

-20

-20 NOTES 1-Source is Reference 23 2-Drop Weight NDTT from longitudinally oriented test specimens.

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

l 904(8913). DOC /ref-39 i

i v

TABLE 13 i

Calvert' Cliffs Unit 1 Beltline Welds l

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)-

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) i NOTES (1) Source is Reference 7 (2) Sources are References 12 and 15 (3) Generic value based on Reference 25 (4) Source is surveillance weld data from Reference 26 n

9 i

i i

Report No. 02987-MCC-002, Rev. 00 Page 38 of 43 e

+

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FIGURE 5 n

mg Calvert Cliffs 1 Pressure Vessel view

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=

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l 904(8913).00C/ref-41 k

IX. CONCLUSIONS i

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.

t B.

The preceding weld is equivalent to the McGuire Unit I weld seam 2-442 l

A/C and to the McGuire surveillance weld. The chemical content-and i

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 Cliffs 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 1 surveillance archive weld is the same material as the block. identified as "D2A" received from Westinghouse.

~

T 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.

l i

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i 1

Report No. 02987-MCC-002, Rev. 00 Page 40 of 43

904(8913). DOC /ref-42 i

X.

REFERENCES 4

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 l

Design & Fabrication, February 1978, p. 78.

I i

3.

C. V. Prestowitz, " Selecting Fluxes for Submerged-Arc Welding: low alloy

~

steels", Welding Design & Fabrication, February 1978, p. 82.

4.

T. H. North (and others), " Slag / Metal Interaction, Oxygen and Toughness 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 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 j

No. MR-85-170).

i 8.

Letter from P. Kruse (C-E) to L. E. Titland (BG&E), C-E Chattanooga Metallurgical Records Search, BG&E-10577-437, January ll,1982.

9.

J. N. Kass, et al, " Radiation Effects in Boiling Water Reactor Pressure Vessel Steels", General Electric Company, NED0-21708, October 1977.

a 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 904(8913).00C/ref-43

11. Cooper Surveillance Weld Evaluation, General Electric, EPRI Contract RP2180-6, August 1983.

l 12.

J. A. Davidson and S. E. Yanichko, " Duke Power Company William B. McGuire Unit No. 1 Reactor Vessel Radiation Surveillance Program", WCAP-91995 November 1977.

13. Letter from J. A. Tiernan (BG&E) to A. C. Thadani (NRC), " Response to Pressurized Thermal Shock Rule", January 23, 1986.

14.

C-E Metallurgical Research and Development Department Vessel Weld Test 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.

17.

S. T. Byrne, " Summary Report on Manufacture of In-Vessel and Ex-Vessel 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 & 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" 1.D. Reactor Vessel", Revision 01 dated 3/16/69.

Report No. 02987-MCC-002, Rev. 00 Page 42 of 43 l

904(8913).00C/ref-64 l

20.

C-E Orawing SA-2067-28-0, " Surveillance Weld Test Plates Middle Shell I

for Westinghouse Electric Corporation 171 1.D. Reactor Vessel", dated 6/27/67.

l'

21. Weld Inspection Record, Test Plates B & C, Job & Control Number 70333-017, Contract 2167, approved 4/29/69.

j

22. Weld Inspection Record, Weld Seam No.1-203A, Job & wontrol Number 70617-012, Contract 70167, approved 11/21/68.

23.

" Summary Report on Manufacture of Test Specimens and Assembly of Capsules for Irradiation Surveillance of Calvert Cliffs Unit 1 Reactor Vessel j

Materials", Combustion Engineering Report CENPD-34, February 4,1972.

i 24.

U.S. NRC Standard Review Plan, Section 5.3.2 Pressure-Temperature Limits, l

Branch Technical Position MTEB 5-2, " Fracture Toughness Requirements",

[

NUREG-0800, Revision 1, July 1981.

l 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.

l 26.

S. T. Byrne et al, " Testing and Evaluation of Calvert Cliffs Units 1 and f

2 Reactor Vessel Materials Irradiation Surveillance Program Baseline Samples", combustion Engineering Report TR-ESS-001, January 31, 1975.

E 27.

" Chemical Analysis of Weld Metal Specimens for Baltimore Gas and Electric Comnany," Wyle Laboratories Report No. 40602-04, July 27, 1989.

b Report No. 02987-MCC-002, Rev. 00 Page 43 of 43_

t

e APPENDIX A

+

t l

i CALVERT CLIFFS UNIT 1 WELD RECORDS i

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