*STINGHOUSE NON-PROPRIETARY CA S 3

WCAP-14042 Revision 1

KEWAUNEE WELD DROP WEIGHT TEST

PROGRAM RESULTS

JANUARY 1995

PREPARED BY:

REVIEWED BY:

APPROVED:

M.Pe , Senior Engineer Metallurgical & NDE Analysis

C. Kim, Senior'Engineer Metallurgical & NDE Analysis

R. D. Rishel, Manager Metallurgical & NDE Analysis

Work Performed Under OCS9249509

@1995 Westinghouse Electric Corporation All Rights Reserved

m:\1661w.wpf:1d-01 1895

9501310220 950123 PDR ADOCK 05000305 P PDR

Westinghouse Energy Systems

1.0 INTRODUCTION

This report provides the results from the drop weight test program conducted to determine the nil ductility transition temperature (NDT) of a reactor vessel test weld representative of a circumferential weld in the Kewaunee reactor vessel. The technique used to determine the NDTT is the drop weight test and is defined in ASTM E208 "Standard Test Method for Conducting Drop-Weight Test to Determine Nil-Ductility Transition Temperature of Ferritic Steels." The drop-weight test gives a break or no-break temperature for the NDTT. The NDTT has been correlated with Charpy V-notch impact test results for steel of various strengths. The data is useful in establishing the conditions required for initiation of brittle fractures in structural steels.

A detailed procedure, prepared specifically for this program, is provided in Appendix I. The procedure includes criteria from ASTM E208 and supplemental steps used in the fabrication and testing of the drop-weight specimens. The details from the test program as well as the results are presented in the following sections.

2.0 MATERIAL EVALUATED

Two blocks of weldment were supplied to Westinghouse Electric Corporation by Combustion Engineering in 1970; one block was used to fabricate weld specimens for the Kewaunee surveillance capsule program and the second block remained stored and was used for this test program. The material supplied by Combustion Engineering consisted of sections from the intermediate shell (B6306-1, heat 122X208VAl) and lower shell (B6307-1, heat 123XI67VAl) ring forgings welded together using 3/16 inch diameter B-4 wire, heat number IP3571, and Linde 1092 flux, lot number

3958, by a submerged arc process. The photographs in Figure 1 illustrate the condition of this material prior to any machining. The weld wire used to fabricate these blocks is representative of that used to fabricate the intermediate shell to lower shell circumferential weld seam of the Kewaunee reactor vessel. The heat treatment records were reviewed and it was established that the weld used from which the drop-weight specimens were fabricated was stress relieved at 1150 +/- 25F for 19 and 1/4 hours, shown by the record provided in Appendix II. This is comparable to the stress relief given to the Kewaunee intermediate shell to lower shell circumferential weld seam which was 1150 +/- 25F for 21 hours.

The sectioning sequence used in this process is described in Appendix I. Figures 2 through 4 are photos of the material throughout the sectioning sequence. Initially, a 3/4 inch thick section was removed from one end of the as supplied block. The cut face of the first section and the mating surface of the block were macroetched with a 2% nital solution, shown in Figure 2 to identify the weld profile. To fabricate the 15 drop-weight test specimens three 2 and 1/4 inch thick sections were removed and identified as block 1, 2 and 3 shown in Figure 3. Block 1, 2 and 3 were macroetched and are illustrated in Figure 4. Sketches 1, 2 and 3 in Appendix I illustrate each block and the location of each test specimen.

2

3.0 TEST SPECIMEN FABRICATION

The details for specimen fabrication are described in the procedure provided in Appendix I. Specimen fabrication consists of machining blanks of a specified size and laying a crack-starter weld in the center of the test blank. The crack-starter weld is a centrally located weld bead, approximately 2 and 1/2 inches long and 1/2 inch wide, from a specified hardfacing weld electrode. A notch is then placed at the center of the bead length with a thin abrasive disc. The qualification of the weld set-up is accomplished by fabricating three test specimens and performing an actual drop-weight test at 100'F or more above the expected NDTT. If the test demonstrates that the weld notch is always cracked upon deflection of the specimen tension surface to the maximum amount permitted by the anvil stop, the weld is qualified per ASTM E208.

Fifteen drop-weight test specimens were cut from blocks 1, 2 and 3 in the locations noted in Figure 4 and sketches 1 through 3 in Appendix A. Each specimen was uniquely identified WPS-1 through WPS-15 and dimensions conformed to ASTM E208 specimen type P-2. Dimensions were checked for all specimens and are provided in Table 3-1. Three of the specimens, WPS-13 through WPS-15 were used as qualification for the crack-starter weld. A 3/16 inch diameter Murex Hardex N electrode was used for the crack-starter weld. Elements determined from chemical analysis of the electrode are provided in Table 3-2. WPS-13, -14 and -15 were tested with the setup described in Section 4.0 and at a temperature of 30'F. The results of the test, provided in Table 4-2, showed a cracked weld notch and no break for the specimens, thus the crack-starter weld was qualified and the remaining specimens were fabricated. A photograph of specimen WPS-13 is provided in Figure 5 illustrating the cracked weld notch following the test.

3

0

4

Table 3-1 Dimensions of Kewaunee Drop-Weight Test Specimens

Specimen Thickness Length Width Weld Weld ID (inch) (inch) (inch) Length Notch

(inch) Height (inch)

WPS-1 0.758 5.00 2.00 2.85 0.075

WPS-2 0.758 5.00 2.00 2.85 0.074

WPS-3 0.758 5.00 2.00 2.90 0.065

WPS-4 0.758 5.00 2.00 N/A N/A

WPS-5 0.758 5.00 2.00 2.80 0.072

WPS-6 0.758 5.00 2.00 2.80 0.077

WPS-7 0.758 5.00 2.00 2.90 0.070

WPS-8 0.758 5.00 2.00 2.90 0.075

WPS-9 0.758 5.00 2.00 2.85 0.077

WPS-10 0.758 5.00 2.00 2.85 0.075

WPS- 1l 0.758 5.00 2.00 2.80 0.078

WPS-12 0.758 5.00 2.00 2.90 0.076

WPS-13 0.758 5.00 2.00 2.85 0.075

WPS-14 0.758 5.00 2.00 2.90 0.076

WPS-15 0.758 5.00 2.00 2.85 0.074

ASTM 0.75 +/- 5.0 +/- 0.5 2.0 +/- 0.04 1.75 +/- 1.0 0.07 - 0.08 TYPE P-2 0.04

*Not detected (minimum detection limit of 0.002)

5

Table 3-2 Chemical Composition of Murex Hardex N Electrode

Composition (wt. percent)

C S P Mn Si Cr Ni Mo Cu Fe

0.052 0.015 0.014 0.40 * * 0.018 0.003 0.010 remainder

4.0 TEST SETUP AND RESULTS

The drop-weight testing is performed using a specific machine designed for this purpose. The principle components of a drop-weight machine are a vertically guided, free-falling weight, and a rigidly supported anvil which provides for the loading of the rectangular specimen as a simple beam under the falling weight. The dimensions for the anvil used for this evaluation are shown in Figure 6 and listed in Table 4-1.

The test was conducted by placing a specimen in a bath consisting of methanol and dry ice until the desired temperature was reached. The specimen was maintained at the specified temperature for at least 45 minutes prior to testing. The specimen was then placed with a minimum loss of time on the anvil and aligned where it was struck squarely by the weight. The specimen was then examined after the strike to determine its condition. Proper contact of the tension surface of the specimen was determined by the transfer of a scribed-wax pencil line from the tension side of the specimen to masking tape place on the top surface of the anvil deflection stop blocks. The specimen is struck by a free-falling weight having adequate energy to deflect the specimen. This process was repeated for each specimen until the NDTT was determined.

The test parameters and results of the testing performed are provided in Table 4-2. Interpretation of the test results and how the NDTT is determined is explained in the procedure provided in Appendix I. Each of the specimens used in determining the NDTT were photographed and are provided in Figures 7 and 8. The results showed a NDTT of -50F for the weld.

6

**Note: See Figure 6 for locations of dimensions.

*Note: Per ASTM E208

7

Table 4-1 Critical Anvil Dimensions for a P2 Specimen

**Critical Anvil Dimension Fixture *Required *Tolerance Descritpions Dimension Dimension

(inch) (inch) (inch)

Span (S) 4.002 4.000 0.050

Deflection (D) 0.060 0.060 0.002

Anvil Thickness (C) 1.975 1.500 minimum

Support Length (E) 3.007 2.00 minimum

Support Width (F) --------- not less than G--------

Support Height (G) 1.966 2.000 1.000

Support Radius (R) 0.075 0.075 0.025

Stop Width (H) 3.033 2.000 2.000

Weld Clearance (I) 0.995 0.900 0.100

Weld Clearance Depth (J) 1.889 0.400 minimum

Head Weight (H) 57.5 50 to 300 lbs.

TUP Radius (TR) 1 .000 1.000 -

0

Table 4-2 Drop Weight Test Results

Specimen ID Test Temperature (oF) Test Result

WPS-1 -70 Break

WPS-2 -30 No Break

WPS-3 Not Tested

WPS-4 Not Tested

WPS-5 **-50 Break

WPS-6 -40 No Break

WPS-7 -40 No Break

WPS-8 -50 No Test

WPS-9 **-50 Break

WPS-10 Not Tested

WPS-11 Not Tested

WPS-12 Not Tested

WPS-13 30 *No Break

WPS-14 30 *No Break

WPS-15 30 *No Break

*Note: Specimens tested to qualify crack starter weld.

**NDTT is -50oF

8

MACROPHOTOGRAPHS OF KEWAUNEE TEST WELD BLOCKS PRIOR TO SECTIONING.

9

FIGURE 1

FIGURE 2 WELD PROFILE OF KEWAUNEE TEST WELD BLOCK.

10

FIGURE 3 TEST WELD WITH LOCATIONS OF BLOCKS 1, 2 AND 3 NOTED.

11

(a) BLOCK 1

(b) BLOCK 2

(c) BLOCK 3

FIGURE 4 MACROPHOTOGRAPHS OF (a) BLOCK 1, (b) BLOCK 2 and (c) BLOCK 3 PRIOR TO SECTIONING. LOCATIONS OF TEST SPECIMENS NOTED ON EACH BLOCK.

12

MACROPHOTOGRAPH OF WPS-13 FOLLOWING DROP WEIGHT TEST FOR QUALIFICATION OF CRACK-STARTER WELD.

FIGURE 5

c-fl

1-Il

z (A A (0 A

Mo

77.

1T

R

C

V

ANVIL DIMENSIONS AND LOCATIONS.

14

FIGURE 6

MACROPHOTOGRAPH OF THE TOP SURFACE OF EACH TEST SPECIMEN FOLLOWING THE DROP WEIGHT TEST.

FIGURE 7

MACROPHOTOGRAPH OF ONE SIDE OF EACH TEST SPECIMEN FOLLOWING THE DROP WEIGHT TEST.

FIGURE 8

0

APPENDIX I PROCEDURE FOR DROP WEIGHT TESTING OF KEWAUNEE REACTOR VESSEL WELD

0 0MEM-MNA-082(94)

Page 1 of 5

WESTINGHOUSE ELECTRIC CORPORATION NUCLEAR TECHNOLOGY DIVISION

METALLURGICAL AND NDE ANALYSIS GROUP

PROCEDURE FOR DROP WEIGHT TESTING OF KEWAUNEE REACTOR VESSEL WELD

Work Performed Under OCS 9249509

February 1994

Prepared by:

Verified by:

Approved by:

Cynthia M. Pezze, Senior Engineer Metallurgical and NDE Analysis

Charlie Kim, Senior Engineer Metallurgical and/NDE Analysis

Rick Rishel, Manager Metallurgical and NDE Analysis

MEM-MNA-082(94) Page 2 of 5

1.0 Scope

This procedure defines the steps used in fabricating and testing of drop weight test specimens for the determination of the nil ductility transition temperature (NDTI) of a Kewaunee reactor vessel test weld expected to represent the beltline circumferential weld in the Kewaunee reactor vessel. The general requirements include those required by Westinghouse NTD engineering and those required by Wisconsin Public Service. The fabrication and testing requirements are extracted directly from ASTM E 208-91 and 69, "Standard Test Method for Conducting Drop-Weight Test to Determine Nil-Ductility Transition Temperature of Ferritic Steels," which is the standard used for this test program.

2.0 General Requirements

2.1 All available records relative to the critical Kewaunee surveillance weld and the test block material shall be gathered prior to implementation of this procedure. The specific data for the critical Kewaunee surveillance weld and the test block, including weld metal chemistry and heat treatment records, shall be reviewed by NTD engineering for compatibility.

2.2. The block shall be photographed prior to any sectioning.

23 A piece, 3/4 inch thick full cross section, of the block shall be removed from one end. This section shall be set aside and not used for this test program. The cut face of the block shall be macroetched with a 2% nital solution to reveal the weld contour through the block and photographed.

2.4 A 2 1/4 inch thick piece, full cross section, shall be removed from the test block. The location and identification of each test blank shall be marked on this piece and photographed prior to sectioning. Fabrication of 15 test blanks will require at least three 2 1/4 inch thick pieces, each will be uniquely identified. The entire piece of material will be radiographed per Westinghouse Process Specification 84352 KM, Revision E, quality level A, prior to sectioning.

2.5 The ends of the test blanks will be stamped with a unique identification. All unused pieces of the test block shall be identified and retained.

2.6 A sketch is provided in Appendix A documenting the contour of the weld, the sectioning sequence, the location of test blanks, the identification of the test blanks, and the identification of plate materials within the block of material containing the weld.

2.7 All cutting on the test block shall be conducted using a saw and adequate cooling to prevent overheating.

3.0 Specimen Fabrication

The specimens shall be fabricated in accordance with the requirements defined in ASTM E 208. Specific details within the ASTM standard and other criteria are described below.

MEM-MNA-082(94) Page 3 of 5

3.1 The dimensions of the test specimen blanks shall be in accordance with ASTM E 208-91, specimen type P-2 (thickness of 0.75 +/- 0.04 inch, a length of 5.0 +/- 0.5 inch, width of 2.0 +/0.04 inch and a weld length of 1.75 +/- 1.0 inch). The dimensions shall be tabulated and submitted with data package released with the specimens.

3.2 The crack-starter weld, a centrally located weld bead, approximately 2 1/2 inches long and 1/2 inch wide, shall be deposited on the as-fabricated tension surface of the drop-weight specimen in a single pass. A copper template containing a 1 by 3 inch centrally positioned slot shall be used to center the weld deposit. The Murex Hardex N electrode or the McKay DWT 3/16 inch diameter electrode shall be used and qualified as described in the engineering justification provided in Appendix B. A current of 180 to 200 A, a medium arc length, and a travel speed that will result in a moderately high-crowned bead shall be used. The technique shall be demonstrated by fabricating three specimens and testing (as described in Section 4.0 of this procedure) at 10007 or more above the expected NDT temperatures. If the three tests demonstrate that the weld notch is always cracked upon deflection of the specimen tension surface to the maximum amount permitted by the proper anvil stop, the weld shall be qualified and considered to conform to the requirements of ASTM E 208-91 and -69.

3.3 The final preparation of the specimen consists of notching the deposited weld at the center of the bead length. The notch will be cut with a thin abrasive disc. The depth of the notch will be determined using a device for measuring the thickness of weld metal at the bottom of the notch. The critical dimensions are a notch width of 1/16 inch maximum and thickness of weld metal at the bottom of the notch of 0.07 to 0.08 inch. The measurements are to be performed using the standard device designed for this purpose; an adjustable dial indicator with bridge-support shown in ASTM E 208-91, Figure 10.

4.0 Specimen Testing

The specimens shall be tested in accordance with the procedure defined in ASTM E 208-91. The specific requirements to this program are described below.

4.1 Select a test temperature based on an estimate of a lower temperature where the specimen breaks and a upper temperature where it does not break, and then test at intervals between these temperatures until the temperature limits for break and no-break performance are determined within 10F. The NDIT is the highest temperature where a specimen breaks by this procedure. Test at least two specimens that show no-break performance and the temperature 10'F above that temperature is judged to be the NDTI point. The initial test temperature for this test is -70'F.

4.2 The specimen shall be placed in a cooling device until it is at the desired temperature. The specimen shall be held at temperature for 45 minutes prior to testing. Within 20 seconds of removing the specimen from the cooling device it must be placed on the anvil and align where it will be struck squarely by the drop-weight. Allow the weight to drop from a known preselected height on the specimen.

4.3 Strike the specimen by a free-falling weight having adequate energy, 300 ft-lb, to deflect the specimen sufficiently to crack the weld deposit and to make the tension surface contact the anvil

MEM-MNA-082(94) Page 4 of 5

stop. The specimens shall be tested with anvil dimensions per Figure 4 in ASTM E 208-91 for specimen Type P-2.

4.5 Proper contact of the tension surface of the specimen with the deflection stop shall be demonstrated using a wax-pencil line. Scribe a wax-pencil line on the tension surface of a specimen parallel to and in line with the notch cut in the crack starter. Apply clean tape to the top surface of the deflection stop blocks. Once the standard load has been applied, the wax line from the specimen is transferred to the tape indicating the specimen was properly bent. This shall be part of each drop-weight test to preclude a "No-Test" performance.

4.6 Examine the specimen after the strike to determine its condition. Repeat this process until the NDTT temperature has been determined. Interpretation of the test results is described in Section 5.0 of this procedure.

4.7 If a no test is experienced, then the initial drop-weight energy shall be increased by 50 ft-lb increments for the subsequent tests until the weld crack and anvil contact criteria are met.

4.8 Each specimen shall be photographed following testing.

5.0 Interpretation of Test Results

The conditions for interpretation of the test results can be classified as a Break, a No-Break or No-Test performance. Specifics associated with these are described in the following sections.

5.1 Break - A specimen is considered broken if fractured to one or both edges of the tension surface. Complete separation at the compression side of the specimen is not required for break performance.

5.2 No-Break - The specimen develops a visible crack in the crack-started weld bead that is not propagated to either edge of the tension surface.

53 No-Test - The test shall be considered not valid if either the weld-deposit notch is not visibly cracked after completion of a test, or if the drop-weight specimen is not deflected fully to contact the anvil stop as evidenced by transfer of the wax-pencil lines to the tape on the anvil deflection stop.

6.0 Report

A report shall be prepared following completion of the testing and shall include the following information:

o Macrophotographs of the test block prior to cutting. o Sketches illustrating the location of the weld within the test block, the location and

orientation of the test specimen blanks within the test block and the specimen identification.

o Table containing the specimen identification and measured critical dimensions.

MEM-MNA-082(94) Page 5 of 5

0 Table containing the test specimen identification, test temperature, results of test (break, no-break, or no-test), and NDT temperature.

o Photographs of the specimens after drop weight test. o Anvil dimensions. o Deviations, if any, from this procedure.

MEM-MNA-082(94)

APPENDIX A

MEM-MNA-082(94) Appendix A Page 1 of 3

Layout Block No. 1 Kewaunee Weldment B6307-1/B6306-1

Blank 5 Drop Weight Samples and Stamp with Identifications Noted

OD SURIPRCE RsfwovE, IDEOTIfY O,AM cS 9kv

1b SUORCERLROlE 190171X

1>E NT Ff ToTH4 E MOS

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S4hount -

LS 1r ulC. 02tf/ /99451<rTcA4 NKO.I

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MEM-MNA-082(94) Appendix A Page 2 of 3

Layout Block No. 2 Kewaunee Weldment B6307-1/B6306-1

Blank 5 Drop Weight Samples and Stamp with Identifications Noted

oZ SUPPCE RxovEa I I Ad S 4AE

-10 SuOFC1E8EMoVE IDETxi e"%A. % AV E

IDENT1f7 tro'TR E MOS OF SmAPLE

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BOWS

svkow Kl

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3K'ETC N Ao, 2

MEM-MNA-082(94) Appendix A Page 3 of 3

Layout Block No. 3 Kewaunee Weldment B6307-1/B6306-1

Blank 5 Drop Weight Samples and Stamp with Identifications Noted

oD SUAPaCE RsNwovE, IDE T IY oA.d S 9V

IDE NTk Ff -1oT4 5wO5 OF StWLE

BLw s As WPS -112 I1. 13, 14dm1 IS

OR W E-T

SOW 14

It SuORCE 1 OE IE %

0 Z/fy /9 14c.<ET'0q tw. 3

MEM-MNA-082(94)

APPENDIX B

Westinghouse Energy Systems Nuclear and Advanced

Electric Corporation Teconology Division Box 355

- Pittsburgh Pennsylvania 15230-0355

March 15, 1994

MEM-MNA-110(94)

Mr. Charles A. Tomes Nuclear Inservice Inspection Engineer Wisconsin Public Service Corporation 600 North Adams P. 0. Box 19002 Green Bay, WI 54307-9002

Subject: WPS P.O. 109750 for Reactor Vessel Weldment Drop Weight Testing

Dear Mr. Tomes:

Attached you will find an engineering justification for using commercial grade ASTM E-208 specified electrodes for performing drop weight testing of Kewaunee reactor vessel material.

In order to initiate the drop weight testing we need written concurrence from Wisconsin Public Service that the engineering justification is an acceptable approach. We recognize that the final acceptance will depend on the outcome of the functional tests as described in the justification and E-208, paragraph 7.10.

Our intent is to perform the tests to ASTM E-208-69, wherever possible, which is consistent with the industry standard in effect when preirradiation surveillance capsule testing was done on the Kewaunee reactor vessel materials.

With high regards,

WESTINGHOUSE ELECTRIC CORPORATION

Rick D. Rishel, nager Metallurgical & NDE Analysis

/ts

cc: A. M. Pegze T. L. Rohosky

ENGINEERING JUSTIFICATION FOR USING COMMERCIAL GRADE ASTM E 208 SPECIFIED ELECTRODES FOR PERFORMING DROP WEIGHT TESTING

OF KEWAUNEE REACTOR VESSEL MATERIAL

Muzch 15, 1994

Prepared by:

Reviewed by:

Approved by:

SGATt E obl FIL.<. C. M. Pezze, Senior Engineer Metallurgical and NDE Analysis

T. L. Rohosky, ty Engineer

= . . 3- -1 Qjz R. D. Rishel, Senior Engineer Metallurgical and NDE Analysis

ENGINEERING JUSTIFICATION FOR USING COMMERCIAL GRADE ASTM E 208 SPECIFTED ELECTRODES FOR PERFORMING DROP WEIGHT TESTING

OF KEWAUNEE REACTOR VESSEL MATERIAL

March 15, 1994

Prepared by:

Reviewed by:

1 / /

C. M. Pezl$ Senior Engineer Metallurgical and NDE Analysis

T. L. Rohosky, Quality Engineer

Approved by: -,-

R. D. Rishel, Senior Engineer Metallurgical and NDE Analysis

* * ENGINEERING JUSTIFICATION FOR USING COMMERCIAL GRADE

ASTM E 208 SPECIFIED ELECTRODES FOR PERFORMING DROP WEIGHT TESTING OF KEWAUNEE REACTOR VESSEL MATERIAL

Background

Westinghouse, under contract from Wisconsin Public Service (WPS P.O. 109750) has been given the task to perform drop weight testing of unirradiated Kewaunee reactor vessel weld material to determine the nil-ductility transition (NDT) temperature. WPS has requested that such tests be performed under the following conditions:

1. The tests must be considered nuclear safety related services. 2. The test shall be conducted to reproduce as close as possible the conditions of

the drop weight testing standard coincident with the date (1970) when the preirradiation surveillance capsule tests were performed on the Kewaunee vessel material.

Westinghouse has historically performed drop weight testing in accordance with the current edition of ASTM Standard E-208, Standard Test Method for Conducting Drop-Weight Test to Determine Nil-Ductility Transition Temperature of Ferritic Steels. ASTM E-208 specifies the use of a particular brand name of electrodes for use in generating a crack starter weld. The ASTM E208-69 edition, in effect when the Kewaunee vessel material pre-irradiation surveillance capsule tests were conducted, specifies Murex Hardex-N electrodes. The current ASTM E208-91 edition specifies McKay DWT 3/16 inch diameter electrodes. The latter standard recognizes that the Murex Hardex-N electrodes source is no longer available. Both of these electrodes are available to Westinghouse in sufficient quantities to perform the required tests, however, both are considered commercial grade electrodes. The Murex Hardex Nelectrodes are Westinghouse stock from testing performed under previous E208 editions. They are contained in a sealed manufacturer's can (10 lbs) with clearly identifiable markings including lot number, heat number, size and type. The McKay DWT 3/16 inch diameter electrodes were recently purchased from a supplier. The sealed manufacturer's can (10 lbs) identifies the lot number, heat number, size and type.

Justification for Using Commercial Grades of Material

Westinghouse concurs with the E208 statement that the sole purpose of the electrode "is to provide a brittle material for the initiation of a small, cleavage crack-flaw in the specimen base material during the test." Any number of electrodes will satisfy this functional requirement and produce a valid test regardless of chemical composition and hardness, however, the most experience has been gained using the E208-specified electrodes. Westinghouse conducted such drop weight tests in the 1970's using Murex Hardex-N electrodes. Many other researchers have done the same without suggesting any impact on the choice of electrodes (reference: ASTM Special Technical Publication 919 - Drop Weight Test

0 * -for Determination of Nil-Ductility Transition Temperature - User's Experience with. ASTM

Method E208, November 1984). A local supplier (ITLS) uses the latter E-208 standard electrode, McKay DWT 3/16 inch diameter, Such hardfacing electrodes contain the weld qualities known to achieve valid drop weight tests, i.e. no cracks during weld deposit but will crack when the base metal is deformed, good metal to metal wear, good machinability, good buildup electrode (reference: Damian Kotecki of Lincoln Electric, telecommunication of March 11, 1994). The E208-specified electrodes, especially the Murex Hardex N-electrodes, also satisfy the WPS requirement that the drop weight tests be conducted under conditions similar to the timeframe in which pre-irradiation surveillance capsule tests were conducted on the Kewaunee reactor vessel materials.

Given the limited purpose of the electrodes (see above) and the fact that various types of electrodes may be used without affecting the test results provided the tests in paragraph 7.10 of ASTM E208 are performed, Westinghouse feels the weld electrodes may be considered non-nuclear safety related material.

In order to provide additional assurances that the weld electrodes are suitable, the following actions will be performed and documented:

1. A chemical analysis of the electrode lot shall be performed, and documented. 2. All manufacturer's markings on the can shall be documented in the final report. 3. The electrodes shall be checked for suitability in accordance with the

requirements of paragraph 7.10 of ASTM E208.

Only the functional tests of paragraph 7.10 of ASTM E208 will determine whether the electrodes are suitable and drop weight tests may be conducted.

Recommendation for Using Commercial Grade Electrodes

Westinghouse recommends that the Murex Hardex-N electrodes be used in the present drop weight tests. If for some reason the Murex Hardex-N electrodes are not suitable, e.g. they fail the functional tests, then the McKay DWT 3/16 inch diameter electrodes may be used provided the three conditions described above are performed.

APPENDIX II HEAT TREATMENT RECORDS

QCV-655

NUCLEAR ENERGY SYSTEMS PR Svstems Division

TO: E. Landerman

G. T. W. R. W. C. G. D. A.

Durfee Dressel Owens White Yanichko-e ~ Zula Skillern Pearsall Sepp

Quality Assurance

May 12, 1971 QUALITY ASSURANCE RECORDS FOR jPS, REACTOR VESSEL SURVEILLANCE PROGRAM

Ref.: PA-PME-1907, dated April 23, 1971

Attachment 1 identifies Quality Assurance record requirements and availability for the subject program. As indicated by material identifications with an (X) in the "Yes" column, all materials with impact test data have been furnished by the supplier (C.E.) to PWRSD. Exceptions are identified in the footnotes. This record identifies availability of (a) surveillance materials, (b) material identification for traceability, (c) fabricator thermal hisrory, and (d) impact test data with charpy curves in conformance to Reactor Vessel General E-Spec 676413, Rev. 1. Charpy V-notch test requirements for welding materials to assure compliance to ASMHE, Section III, is also given.

Based on the record information supplied for the subject vessel, Quality Assurance can verify acceptability of the following:

a. Charpy-V-notch test data conforms to Section III, para. N-421, requirements for SA508, Class 2, material at E-Spec target temperature (+10 0 F).

b. Charpy V-notch curves are available with transition temperature identified at "fix" ft/lbs.

s. Drop weight tests have been performed, as applicable, with NDTT values recorded.

Attachment 2 gives the charpy values recorded in the supplier's weld procedure qualification records, for Procedure No. SAA-MA-500, used in the core region girth weld. During review of this information it was learned that the supplier does not record lateral expansion and percent ductile fracture area as specified in para. N331.2. Materials Engineering is requested to

CC: C. N. W. C. S. G. C. R. H.

E. Landernan

confirm whether or not this data should be recorded, as applicable, to weld material testing in conformance to para. N511.3 and N541.3.

Your comments are requested on Attachment 1 format and completeness for use on other reactor vessel contracts. It is anticipated that modifications to the record form will be -required to satisfy material and impact test data variations specified in each of the revisions to the reactor vessel general E-Spec 676413.

N. -. -'Roose, Senior Engineer Q lity Assurance/Pressure Vessels

lek

Attachments: 1 - Reactor Vessel Surveillance/Core Weldment Material, Quality Assurance Record Status and Availability

2 - C.E. Weld Procedure Qualification Charpy Test Data

-2- QCV-655

2f44

Reference Sec.

E-Spec IIII1 . " . I

4.3.18.2b

4 .3.18.2c

4 .3.18.2e

5.1.1.2

N511.3

Core Region: -Intermediate Shell 2.pcs. /&'K" &

4Z A-17-

'~' 7? ~r'Ref.: Hlt. No. -o/? V" ' I"t4/

Pc. MK. NO. -Lower Shell 4 pes . /~ -K / 4- ". , f49 Ref.: Ht. No. / y/47 /,4

Pc. MK No. '93D -Nozzle Shell Course

(2) Nozzle Cutouts j'"y 4t , Balance (-,#3. /' 2, " , a . Ref.: Ht. No. /? / S /

PC. MK. No.eldment

ii of

L

I

Core Region: -Weld Metal -Base Metal Heat Affected Zone Ref.: Electrode Ht. No. // 67/

Flux Lot No.__ _ __ _

ASME Code Weld Material Tests Electrode/Flux Combination Certification: Ref.: Electrode Ht. No. / / 5 7/

S Flx. 11Y. -,

FIP rn I ~fl*~ ~ A

~~JLJ 2 'Y~

FOOTNOTES: *Drop weight test data not required. N/R - Charpy curves not required. W - Preirradiation test data to be supplied

by PWRSD Materials Engineering. CE - Data available for review at supplier

facility.

Hirs.

11000F 1A4

Impact Test Data

Ref.: Ut. No. PC. iK.

N

0.0

0.0

21.0

.25

19.25

19.25 It - -

40.0

40.0

X.

X

X

U-

X It

CE*

N/

N/

I 5

\5 / n Z / zc

1W

I

_4*r, .4' -

P

9

4109 _

3 44

JAI.

Fc A%3~'*~\~~ R -~ W 5 41.

oF 9&k 1 T - 1t re a- LX

(L.x - C)

C ~A ~ \f-w0~4 71Ni'ActS

*v TA PoAT'4 4 EATJBU NFiCTCD *zE

14E.4 }'"'o-CI<V } .

q0 , So, El

q3, Sq, i9

Ve Ca--,w

Fo pr(. s

TES T 12CC .

~IjKA~' ~ 7~4'.

I~1 1~

5r~ ~ C3.

AS 6 1%<.C5A F ta d*

I* 64

0C

a,

C-,

WISCONSIN PUBLIC SERVICE CORP.

KEWAUNEE NUCLEAR-POWER PLANT REACTOR VESSEL RADIATION SURVEILLANCE PROGRAM

S. E. Yanichko D. J. Lege G. C. Zula

APPROVED:J. N. Chirigos

Work Performed Under WPS-106

WESTINGHOUSE PROPRIETARY DATA This document is the property of and contains proprietary information owned by the Westinghouse Electric Corporation, Nuclear Energy Systems, and is transmitted to you in confidence and trust and is to be returned upon request. No permission is granted to publish, reproduce, transmit or disclose to another any information contained in this document, in whole or in part, without the prior written permission, in each case, of an authorized employe of said corporation.

WESTINGHOUSE ELECTRIC CORPORATION Nuclear Energy Systems

P. 0. Box 355 Pittsburgh, Pennsylvania- 15230

I(of L.

APPENDIX A

KEWAUNEE REACTOR PRESSURE VESSEL MATERIAL

For the Reactor Vessel Surveillance Program, Combustion Engineering, Inc.

supplied Westinghouse sections of A508 Class 2 forgings used in the core

region of the Kewaunee reactor pressure vessel. The sections of material were

removed from the 6-1/2 inch-thick intermediate and lower shell rings

(forgings No. 122X208VAl and 123X167VAl, respectively) of the pressure vessel.

In addition, a weldment made from sections of the two forgings, using weld

wire representative of that used in the original fabrication, was also supplied by Combustion Engineering Inc. The forgings were produced by the

Bethlehem Steel Corp. The heat treatment history and chemical analysis of the vessel material are presented in Tables A-1 and A-2.

TABLE A-1

HEAT TREATMENT

Intermediate Shell Heated at 1550*F for 8 hours, water quenched

Heat 122X208VAl Tempered at 1230*F for 14 hours, air cooled

Stress-relieved at 1150*F for 21 hours, furnace cooled

Lower Shell Heated at 1550*F for 8 hours, water quenched

Heat 123X167VA1 Tempered at 1220*F for 14 hours, air cooled

Stress-relieved at 11500 F for 21 hours, furnace cooled

-Weldmuli"- ..... ~w','4 11 0F: fo 19-1/4 hours-

A-1

20 L