ML17227A829
| ML17227A829 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 02/16/1993 |
| From: | ASEA BROWN BOVERI, INC., C-E OPERATING PLANTS OWNERS GROUP |
| To: | |
| Shared Package | |
| ML17227A830 | List: |
| References | |
| CE-NPSD-906-NP, NUDOCS 9302240414 | |
| Download: ML17227A829 (66) | |
Text
COMBUSTION ENGINEERING OWNERS GROUP CE NPSD-906-NP CEOG PROGMAl TO EVALVATE CHEMICALCONTENT OF WELD DEPOSITS FABRICATKDVSING HEATS AS746 Ale 34B009 CEOG TASK 747 Prepared for the C-E OWNERS GROUP February 1993 ABB Combustion Engineering Nuclear Power llew QDQD liQQDQD
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TABLE OF CONTENTS Section No.
Title
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Introduction
Background
III Scope IV Results Conclusions References 10
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LIST OF TABLES Number Title Copper Analysis Results for Weld Wire Heat ¹A8746 Weld Deposit Copper Content for [
] Wire Heats Nickel Content for Coiled Wire Electrode Weld Deposits Weld Seams and Consumables Using [
] Heat ¹A8746 P~ae 12 13 14 Weld Seams and Consumables Using [.
] Heat ¹34B009 15
'opper Content Analysis Results for Weld Wire Heat ¹34B009 16 Weld Deposit Nickel Content with Cold Nickel Feed Nickel Content for Heat ¹34B009 with Cold Nickel Feed and Linde 1092 Flux'7 18 Best Estimate Copper and Nickel Content for Vessel Welds 19
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INTRODUCTION This report presents the results of a task undertaken for the Combustion Engineering Owners Group (CEOG) to provide the basis for the copper and nickel content of reactor pressure vessel welds made using two specific heats of weld wire.
These heats are common to beltline welds in several reactor vessels fabricated by ABB/CE in Chattanooga, Tennessee.
The as-deposited welds were not always analyzed explicitly for copper or nickel during fabrication because the significance of those chemical elements to irradiation embrittlement was not then recognized.
Subsequent efforts to estimate the as-deposited weld chemistry from limited data sometimes have resulted in different values for the same weld consumables.
The purpose of this evaluation is to utilize a broad set of chemical analysis results in conjunction with information from material specifications to establish a consistent and viable basis for the as-deposited weld chemical content for four specific reactor pressure vessels involving two heats of weld wire.
II.
BACKGROUND Submittals were made in December 1991 to the Nuclear Regulatory Commission (NRC) in response to 10 CFR 50.61, "Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock (PTS) Events" (Federal Register, v.5694, page 22304, May 15, 1991).
The NRC expressed concern regarding the consistency and credibility of data used as the basis for PTS submittals, especially with respect to chemical content.
Two or more licensees have reported different copper or nickel contents for reactor vessel welds for which an identical heat of weld wire was used.
These differences arose in part because of the way multiple analyses were handled, the type of estimation methods used by licensees, or the degree to which data traceability was established.
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The PTS submittal of one CEOG licensee was questioned by the NRC regarding the copper and nickel content of a vessel beltline weld formed using weld wire heat number A8746.
This same weld wire heat was also used for two other CEOG licensees'essel beltline welds.
The same copper content (a single measurement, not an average) was reported by all three licensees, but different nickel contents were reported.
An initial response to the question was prepared based on a review of fabrication records, procedures and specifications as described in the results section.
This report builds upon that initial review using chemical analysis data representative of weld wire specifications and weld procedures employed by ABB/CE.
NRC guidance for determination of copper and nickel content is contained in 10 CFR 50.61, "Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events".
Four alternatives are available to obtain best-estimate copper and nickel values for the plate or forging, or for weld samples made with the weld wire heat number that matches the critical vessel weld as follows:
(1)
The mean of the measured values, or, ifthese values are not available, (2) the upper limiting values in the material specifications to which the vessel was built, or ifnot available, (3) 'onservative estimates (mean plus one standard deviation) based on generic data from reactor vessels fabricated in the same time period to the same material specifications, ifjustification is provided.
(4)
Ifnone of the first 3 alternatives are available, 0.35% copper and 1.0% nickel must be assumed.
The preceding guidance was employed in this evaluation.
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III.
SCOPE The objective of this evaluation is to provide best estimate values of copper and nickel content for weld deposits produced using the following materials:
2.
flux
] weld wire heat A8746 and Linde 124 flux
] weld wire heat 34B009 and Linde 124 or 1092 3.
[
] weld wire heat 34B009 with Ni-200 cold wire feed and Linde 1092 flux The preceding materials were used to fabricate reactor vessel beltline welds in Calvert Cliffs Unit 2, St. Lucie Unit 1, Millstone Unit 1, and Millstone Unit 2.
The guidelines contained in 10 CFR 50.61 are followed to provide those best estimates.
The approach taken is to review ABB/CE welding procedures and specifications, to collect chemical analysis results specific to the three weld materials noted, and to collect chemical analysis results for comparable and contrasting weld materials.
This information is then evaluated to determine the best estimate value for:
2.
3.
the nickel content of [
¹A8746 and 34B009, the copper content of [
¹A8746 the copper content of [
the nickel content of [
feed weld deposits.
] wire weld deposits, specifically heats
] wire weld deposits, specifically heat
] heat ¹34B009 weld deposits, and
] heat ¹34B009 plus Ni-200 cold wire In this evaluation, chemical analysis results were obtained from weld deposits fabricated using Linde 0091, 1092, 124 and 80 fluxes.
The toughness properties of welds made using Linde 0091, 1092 and 124 fluxes have been previously shown to be I
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comparable"'.
[
] There is insufficient information from ABB/CE fabrication records to draw similar conclusions regarding Linde 80 flux welds.
Therefore, copper and nickel analysis results from Linde 80 flux welds willbe considered for information only.
IV.
RESULTS 1.
Welding Procedures and Specifications ABB/CE fabricated many reactor pressure vessels using automatic submerged
.arc welding.
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2.
Observed Nickel Content of [
Weld Deposits
,] Coiled Wire Electrode I,
3.
Copper Content of Weld Deposits Using Wire Heat PA8746 I
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4.
Copper Content of Weld Deposits Using Wire Heat ¹34B009 5.
Nickel Content of Weld Deposits Using Wire Heat ¹34B009 and a Cold Nickel Wire Feed
V.
CONCLUSIONS
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TABLE 1 Nickel Content for Coiled Wire Electrode Weld Deposits Supplier
~Desi nation Wire S~ntier Nickel
~Content e
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These best estimate chemical contents are summarized in Table 9 for the welds described in Tables 2 and 5.
VL REFERENCES 1.
"Evaluation of Pressurized Thermal Shock Effects due to Small Break LOCA's with Loss of Feedwater for the Combustion Engineering NSSS," Combustion Engineering Report CEN-189,. December 1981.
2.
"Application of Reactor Vessel Surveillance Data for Embrittlement Management,"
Combustion Engineering Owners Group Report CEN-405-P (Draft Revision 2),
December 1992.
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TABLE 2 Weld Seams and Consumables Using [
] ¹A8746 t
Reactor Vessel Calvert Cliffs Unit 2 St. Lucie Unit 1 Millstone Unit 2-Weld Seam No.
Note 1
2-203 A,B,C 2-203 A,B,C (Note 2) 2-203 A,B,C 3-203 A,B,C Weld Flux T e
Linde 124 Linde 124 Linde 124 Linde 124 Weld Procedure S *if Note 1:
Note 2:
Allof the weld seams listed were deposited without a cold nickel wire feed.
Weld wire heat ¹34B009 was also used with heat ¹A8746 to deposit the weld seams in a single arc process.
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TABLE 3 Copper Content Analysis Results for Weld Wire Heat 4A8746 j
of Anal sis Date Flux T
/Lot No.
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TABLE4 Weld Deposit Copper Content
, for [Adcom] Wire Heats Supplier
~Desi nation Flux T~
~Content Note A - From Table 3 Note B - Combination of two Adcom heats in weld deposit I
TABLE 5 Weld Seams and Consumables Using I
- ] Heat ¹34B009
]
Reactor Vessel Weld Seam No.
Weld Flux T Weld Procedure St. Lucie Unit I 2-203 A, B, C (Note 1)
Linde 124 Millstone Unit 1.
3-073 (Note 2)
Linde 1092 Note 1:
Weld wire heat ¹A8746 f
] was also used with heat ¹34B009 to deposit the weld seams in a single arc process.
A cold nickel wire feed was not used.
Note 2:
The weld process included the addition of a cold nickel wire feed.
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TABLE 6 Copper Content Analysis Results for Weld Wire Heat 034B009 A
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ga C~C Source Weld Deposit Linde 1092 Weld Deposit Linde 124 Weld Deposit Linde 1092 0.180 HBR-2 Head Sample Weld Deposit Linde 1092 0.182 HBR-2 Head Sample Weld Deposit Linde 1092 0.1&3 HBR-2 Head Sample Weld Deposit III Weld Deposit Linde 1092 Linde 1092 0.202 0.18 HBR-2 Head Sample MP-1 Surveillance Weld (EPRI)
Weld Deposit Linde 1092 0.19 MP-1 Surveillance Weld (EPRI)
Weld Deposit Linde 1092 0.18 MP-1 Surveillance Weld (GE Report NEDC-30299) j f
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TABLE 7 Weld Deposit Nickel Content with Cold Nickel Feed Source Nickel Content o
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TABLE 8 Nickel Content for Heat P34B009 with Cold Nickel Feed and Linde 1092 Flux Nickel Content 0.75 0.32 0.84 0.43 0.81 0.98 1.03 Source HBR-2 Head Sample HBR-2 Head Sample HBR-2 Head Sample HBR-2 Head Sample MP-I Surveillance Weld (EPIU)
MP-1 Surveillance Weld (GE Report NEDC-30299)
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TABLE 9 Best Estimate Copper and Nickel Content for Vessel Welds Reactor Vessel Weld Seam No Content o
Cu Ni Calvert Cliffs Unit 2 2-203 A,B,C St. Lucie Unit 1 2-203 A,B,Ctu 2-203 A,B,Ct'i Millstone Unit 2 2-203 A,B,C 3-203 A,B,C Millstone Unit I 3-073 Notes (1)
Chemical content contribution from wire heat ¹AS746 (2)
Chemical content contribution from wire heat ¹34B009
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I,g St. Lucie Units 1 and 2 Docket No. 50-335 and 50-389 Generic Letter 92-01 Revision 1
FPL Letter L 93-286 Enclosure 2 ilk 9 it~
HLttdtL)'38 September 28, 1993 F-MECH-93-050 L-MECH-93-015 Mr. R. Scott Boggs Florida Power & Light Company P.O. Box 1400 Juno Beach, FL 33408-0420
Subject:
Upper Shelf Energy Information Pertaining to the St. Lucie Unit 1 and Unit 2 Reactor Vessel Welds.
Appendices:
Attachments:
A) Certified Material Test Reports Pertinent to St. Lucie Unit 2 "Atypical Weld Material In Reactor Pressure Vessel Welds; Information Requested by Nuclear Regulatory Commission Inspection &Enforcement Bulletin No. 78-12", Prepared By Combustion Engineering Inc.,
dated June 8, 1979.
Dear Mr. Boggs:
The purpose of this report is to provide upper shelf energy (USE) information on beltline welds for Florida Power and Light Company (FP&L), St. Lucie Units 1 and 2 reactor vessels, This information is required by FP&L in order to respond to a NRC request for additional information associated with Generic Letter 92-01 (Ref 1) as described in References 2 and 3.
Additionally, two copies of the Combustion Engineering Document "Atypical Weld Material In Reactor Pressure Vessel Weldsn are included as requested in Reference 3.
Please recognize that this letter report, including Appendix A, contains proprietary information and is not to be transmitted or reproduced without specific written approval from Combustion Engineering, Inc.
The Attachment "Atypical Weld Material In Reactor Pressure Vessels",
is not proprietary because it was publicly released in the past.
This letter report is a non-proprietary version.
1.0 St. Lucie Unit 1:
1.1
~Back round The St. Lucie Unit 1 reactor vessel intermediate shell longitudinal seam welds (2-203 A,B,C) were fabricated using wire heat numbers A8746 and 34B009 and Linde 124 Flux lots 3878 and 3688 respectively based upon input provided by FP&L and repeated in Reference 2.
The initial Charpy upper shelf energy (USE) for this weld was not ABB Combustion Engineering Nuclear Power Combustion Engineenng, Inc.
1000 Prospect Hill Road Post Ottice Box 500 Windsor, Connecticut 06095.0500 Telephone (203) 688 1911 Fax (203) 285.9512 Telex 99297 COMBEN WSQR
Mr. Scott Boggs September 28, 1993 F-MECH-93-050 L-MECH-93-015 Page 2 of 10 determined at the time ofmanufacture, nor is such data known to be available from other sources (e.g., surveillance program welds) for the aforementioned welding consumables.
The NRC has stated that an acceptable approach for satisfaction of 10CFR50, Appendix G requirements for initial,USE is to use the average value from similarly fabricated welds (Ref 1); in this case, from USE measurements on submerged arc welds produced using MIL-B4wire and Linde 124 Flux.
1.2
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This report provides a basis for the initialupper shelf energy for weld wire heat numbers A8746 and 34B009 fabricated with Linde 124 fluxusing USE data from welds fabricated with Linde 124 flux.
1.3 Procedure Weld material certiflications (WMC) (Ref 4) at the ABB Combustion Engineering facility in Chattanooga, Tennessee were searched to obtain Charpy impact test data specific to Linde 124 flux welds.
The WMCs were compiled and the initial USE determined from the Charpy impact data in accordance with the definitions provided in ASTM E185-82 (Ref 5).
The primary definitions necessary to establish the upper shelf energy are provided as follows:
1.3.1 Upper Shelf Energy is defined as the average energy value for all Charpy specimens (normally three) whose test temperature is above the upper end of the transition region.
For specimens tested, in sets of three at each test temperature, the set having the highest average may be regarded as defining the upper shelf energy (Ref 5).
1.3.2 Charpy Transition Curve is defined as a graphic presentation of Charpy data, including absorbed energy, lateral expansion and fracture appearance, extending over a range including the lower shelf energy ((5% shear), transition region and the upper shelf energy () 95% shear) (Ref 5).
1.3.3 Transition Region is defined as the region on the transition temperature curve in which toughness increases rapidly with rising temperature.
In terms of fracture appearance, it is characterized by a rapid change from a primarily cleavage (crystalline) fracture mode to primarily shear fracture mode (Ref 5).
Charpy test data for each weld wire heat and flux lot combination showing a fracture appearance of 95% shear or greater were compiled.
The Charpy tests tended to be conducted in sets of three over a range of test temperatures.
This allowed each set of
Mr. Scott Boggs September 28, 1993 F-MECH-93-950 L-MECH-93-015 Page 3 of 10 three tests to be averaged to determine the USE at a given temperature.
The highest averaged USE for each weld wire heat and flux lot combination was taken to be the initial USE for the material and used to determine the best estimate (mean) and standard deviation for welds fabricated using Linde 124 flux. This best estimate can then be used as input for projecting USE after irradiation.
1.4 Results Charpy impact energy data was assessed for 68 different weld wire heat / flux lot combinations to determine the initialupper shelf energy in accordance with ASTME185-82 definitions (Ref 5).
67 USE values represented the average of three Charpy impact specimens usually tested at a single temperature.
The remaining one USE value comes from an average of two Charpy specimens tested at 100'F.
This USE value was judged to be adequate for the purposes of this analysis and would not significantly alter the results ifomitted.
All fracture specimens have a fracture appearance. showing no less than 95% shear.
The average upper shelf energy for the Linde 124 flux welds is [
.] The data ranges from [
.] This represents an average of 68 different weld wire heat / Linde 124 flux lot combinations presented in Table 1.
Table 1: Initial Upper Shelf Energy Values for Linde 124 Welds.
Count Wire Heat/ Flux Lot Initial USE It-ib 10
Mr. Scott Boggs September 28, 1993 F-MECH-93-950 L-MECH-93-015 Page 4 of 10 Count Wire Heat / Flux Lot Initial USE ft-ib 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39
P tA'
Mr. Scott Boggs September 28, 1993 F-MECH-93-950 L-MECH-93-015 Page 5 of 10 Count Wire Heat/ Flux Lot Initial USE ft-lb 40 41 42 43 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 65 66 67
Mr. Scott Boggs September 28, 1993 F-MECH-93-950 L-MECH-93-015 Page 6 of 10 Count 68 Wire Heat / Flux Lot c
j Average USE:
Standard Deviation:
Initial USE ft-lb 2.0 St. Lucie Unit 2:
2.1
~Back round The St. Lucie Unit 2 reactor vessel beltline welds were fabricated using the consumable presented in Table 2 based upon input provided by FP&L and repeated in Reference 2.
The basis for the initialupper shelf energy for these welds was weld material certification tests performed at the time of vessel manufacture (Ref 4).
Table 2:
Beltline Weld Wire Consumable used in St. Lucie Unit 2 Seam No.
101-124 A,B,C 101-124 C (Repair) 101-142 A,B,C 101-171 101-171 Wire Heat No.
83642 83637 83637 83637 3P7317 Flux Type Linde 0091 Linde 0091 Linde 0091 Linde 124 Linde 124 Flux Lot No.
3536 1122 1122 0951 0951 2.2
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Weld material certification test reports (WMCs) for the followingweld wire heat and fiux lots are provided:
Wire heat 83642, Linde 0091 flux lot 3536; wire heat 83637, Linde 0091 flux lot 1122; wire heat 83637, Linde 124 flux lot 0951; and wire heat 3P7317, Linde 124 flux lot 0951.
Upper shelf energy values for the aforementioned wire/flux combinations will be determined if sufficient information is presented in the WMC.
Where fully applicable information is not available, the degree of applicability will be addressed as per the project proposal (Ref 2).
Mr. Scott Boggs September 28, 1993 F-MECH-93-950 L-MECH-93-015 Page 7 of 10 2.3 Procedure Weld material certifications (WMC) at the ABB Combustion Engineering facility in Chattanooga, Tennessee were searched to obtain Charpy impact test data specific to the consumable presented in Table 2.
The WMCs were compiled and the initial USE determined, when possible, from the Charpy impact data in accordance with the definitions provided in ASTM E185-82 (Ref 5) and presented in sections 1.3.1 - 1.3.3.
Where fully applicable information was not available in the WMC (e.g., where percent shear fracture was not reported) the degree of applicability to the Unit 2 weld seam USE is addressed.
2.4 Results Weld material certification (WMC) reports for the weld wire heat / flux lot number combinations presented in Table 2 were obtained from records in possession of Combustion Engineering.
The WMCs pertaining to the Linde 124 welds contained enough information to fully determine the initial upper shelf energy values for the consumable used.
The WMCs pertaining to the Linde 0091 welds did not contain sufficient information;
- however, enough information was available to determine a
conservative (lower bound) upper shelf energy value relevant to the consumables used.
A copy of the WMCs for the consumables listed in Table 2 are provided in Appendix A.
A description of the process used to determine the USE is described for each weld wire heat / flux lot combination as follows:
2.4.1 Wire Heat 83637, Flux Type Linde 124, Flux Lot No. 0951:
The WMC pertaining to this combination of weld consumables contains a full array of Charpy tests over a range of temperatures.
[
2.4.2 Wire Heat 3P7317, Flux Type Linde 124, Flux Lot No. 0951:
The WMC pertaining to this combination of weld consumables contains a full array of Charpy tests over a range of temperatures.
[
2.4.3 Wire Heat 83642, Flux Type Linde 0091, Flux Lot No. 3536:
The WMC pertaining to this combination of weld consumables contains limited Charpy tests at two test temperatures and fracture appearance is not recorded.
[
Mr. Scott Boggs September 28, 1993 F-MECH-93-950 L-MECH-93-015 Page 8 of 10
]
This value does not represent an "official" upper shelf energy for these weld consumables because no measurement of the fracture appearance (i.e., % shear fracture) is available.
However, this value suggests very good fracture toughness characteristics for the material at 10'F and, therefore, may be used as a lower bound approximation to the initial USE.
2.4.4 Wire Heat 83637, Flux Type Linde 0091, Flux Lot No. 1122:
The WMC pertaining to this combination of weld consumables contains limited Charpy tests at 10'F and fracture appearance is not recorded.
[
]
This value does not represent an official upper shelf energy for these weld consumables because no measurement of the fracture appearance (i.e.,
% shear failure) is available.
However, this value suggests very good fracture toughness characteristics for the material at 10'F and, therefore, may be used as a lower bound approximation to the initial USE.
3.0 CONCLUSION
S:
No information is available to determine the initial upper shelf energy specific to the weld consumables used in the St. Lucie Unit 1 reactor'vessel 2-203 A,B,C weldments.
As an alternate approach, a best estimate value of initial USE was calculated using 68 welds fabricated with Linde 124 flux.
The best estimate initial USE of these welds fabricated with MIL-B4wire and Linde 124 flux was calculated to be [
.] This best estimate value can be used as input for projecting USE after irradiation.
Complete or partial information is available to determine the initial upper shelf energy specific to the consumable used in the St. Lucie Unit 2 beltline welds.
Weld material certification reports for these materials are provided in Appendix A.
Weld wire heat 3P7317 with Linde 124 flux lot 0951 has a calculated initial upper shelf energy value of
[
.] Weld wire heat 83637 with Linde 124 flux lot 0951 has a calculated initial upper shelf energy value of [
.] Weld wire heat 83637 with Linde 0091 flux lot 1122 has an average Charpy energy at 10'F of[;]weld wire heat 83642 with Linde 0091 flux lot 3536 has an average Charpy energy at 10'F of [
.] These average energies can be conservatively assumed to be a lower bound approximation of the initial upper shelf energy for the two Linde 0091 flux welds.
Mr. Scott Boggs September 28, 1993 F-MECH-93-950 L-MECH-93-015 Page 9 of 10 Ifyou have any questions or concerns regarding this information, please feel free to contact me at (203) 285-3794 or Steve Byrne at (203) 285-3469.
Sincerely, COMBUSTIONENGINEERING, INC Enclosure David J. Woodilla Project Engineer
Mr. Scott Boggs September 28, 1993 F-MECH-93-950 L-MECH-93-015 Page 10 of 10
References:
Letter from J. A. Norris (NRC) to J. H. Goldberg (FPAL), dated July 28, 1993, Docket No. 50-335, 50-389.
Subject:
St. Lucie Units 1 and 2 - Request for Additional Information - Generic Letter 92-01, Revision 1 (TAC NOS. M83505 and M83506).
2.
ABB/CE Letter No. F-MECH-93-042, "St. Lucie Upper Shelf Energy Evaluation, Proposal No. 93-241-A6A," S. T. Byrne, dated August 27, 1993.
3.
Florida Power and LightCompany Purchase Order No. B93633-30016, dated August 31, 1993.
4.
ABB/CE Letter No. MECH-93-1214, "Weld Material Certification Reports",
S. T.
Byrne, dated October 14, 1993.
5.
ASTM Designation E 185-82, "Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels," Annual Book ofASTM Standards, Vol. 12.02, ASTM, Philadelphia, PA.
Mr. Scott Boggs September 28, 1993 F-MECH-93-050 L-MECH-93-015 Page A1 of A10 APPENDIX A Certified Material Test Reports Pertinent to St. Lucie Unit 2
Mr. Scott Boggs September 28, 1993 F-MECH-93-050 L-MECH-93-015 Page A2 of A10 Contents of Appendix A
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A4 A6 A10 Title Certified Material Test Report for Weld Wire Heat No. 83637 Linde Flux Type 124, Flux Lot No. 0951 Certified Material Test Report for Wire Heat No. 3P7317, Linde Flux Type 124, Flux Lot No. 0951 Certified Material Test Report for Weld Wire Heat No. 83642, Linde Flux Type 0091, Flux Lot No. 3536 Certified Material Test Report for Weld Wire Heat No. 83637, Linde Flux Type 0091, Flux Lot No. 1122.
Mr. Scott Boggs September 28, 1993 F-MECH-93-050 L-MECH-93-015 Page A3 of A10 Certified Material Test Re ort for Weld Wire Heat No. 83637 Linde Flux T e 124 Flux Lot No. 0951
Mr. Scott Boggs September 28, 1993 F-MECH-93-050 L-MECH-93-015 Page A4 of A10
Mr. Scott Boggs September 28, 1993 F-MECH-93-050 L-MECH-93-015 Page AS of A10 Certified Material Test Re ort for Wire Heat No. 3P7317 Linde Flux T e 124 Flux Lot No. 0951
Mr. Scott Boggs September 28, 1993 F-MECH-93-050 L-MECH-93-015 Page A6 of A10
Mr. Scott Boggs September 28, 1993 F-MECH-93-050 L-MECH-93-015 Page A7 of A10 Certified Material Test Re ort for Weld Wire Heat No. 83642 Linde Flux T e 0091 Flux Lot No. 3536
Mr. Scott Boggs September 28, 1993 F-MECH-93-050 L-MECH-93-015 Page AS of A10
Mr. Scott Boggs September 28, 1993 F-MECH-93-050 L-MECH-93-015 Page A9 of A10 Certified Material Test Re ort for Weld Wire Heat No. 83637 Linde Flux T e 0091 Flux Lot No. 1122
Mr. Scott Boggs September 28, 1993 F-MECH-93-050 L-MECH-93-015 Page A10 of A10
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