ML17309A716

Forwards Response to 930728 Request for Addl Info Re GL 92-01,Rev 1,including New Mean Chemistry Valves for Unit 1 Lower Longitudinal Welds,Changes to TS Bases Table B 3/4. 4-1 & CE-NPSD-906-P & CE-NPSD-906-NP.CE-NPSD-906-P Withheld

ML17309A716
Person / Time
Site:	Saint Lucie
Issue date:	11/15/1993
From:	SAGER D A FLORIDA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17228A369	List: ML17228A368 ML17309A716
References
GL-92-01, GL-92-1, L-93-286, NUDOCS 9311300069
Download: ML17309A716 (110)

Text

REG g ORY INFORMATION DISTR IBU N SYSTEM (BIDS~)ACCESSION NBR: 9311300069 DOC.DATE: 93/11/15 NOTARIZED:

NO DOCKET 0 FACIL: 50-335 St.Lucie Planti Unit ii Florida Poujer&Light Co.05000335 50-389 St.Lucie Planti Unit 2i Florida Poujer 5 Light Co.05000389 AUTH.NAME AUTHOR AFFILIATION SAGER'.*.Florida Poeer 5 Light Co.REC I P.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Forwards response to 930728 request for addi info re I GL 92-OIi Rev Ii including new mean chemistry valves for Unit I loujer longitudinal ujelds~changes to TS Bases Table B 3/4.D 4-1 5 CE-NP SD-906-P Zc CE-NPSD-906-NP.

CE-NPSD-906-P e i t h h e 1 d.S DISTRIBUTION CODE: A028D COPIES RECEIVED: LTR ENCL SIZE: TITLE: Generic Letter 92-01 Responses (Reactor Vessel Structural Integritg NOTES: REC IP IENT ID CODE/NAME PD2-2 PD COPIES LTTR ENCL 1 1 RECIPIENT ID CODE/NAME NORRIS'COP IES LTTR ENCL 2 2 INTERNAL: ACRS NRR/DORS/OGCB NRR/DRPW OC/LFDCB EXTERNAL: NRC PDR 01 NRR/DE/EMCB NRR/DRPE/PDI-1 NUDOCS-ABSTRACT OGC/HDS3 RES/DE/MEB 1+P, NSIC 2 2 1 1 1 1 0 1 1~P NOTE TO ALL RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK.ROOM Pl-37 (EXT.504-2065)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 21 ENCL 19 8 1 I' P.O.Box 128, Ft.Pierce, FL 34954-012$

November 15, 1993't0 CFR 2.790 fNFORMATJON EXEMPT FROM DlSCLOSURE L-93-286 10 CFR 50.4 10 CFR 50.54 (f)U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555 RE: St.Lucie Units 1 and 2 Docket No.50-335 and 50-389 Generic Letter 92-01 Revision 1 Res onse to Re uest for Additional Information The additional information and clarifications requested by NRC letter dated July 28, 1993, are provided in attachments 1 and 2 to this letter.Attachment 1 also provides new mean chemistry values for St.Lucie Unit 1 lower longitudinal welds.Attachment 3 and enclosures 1 through 4 provide supporting information for the , response.The preparation of the response required review of the reactor vessel fabrication records by the original equipment manufacturer (Combustion Engineering) as background for part of the response.FPL letter (L-93-232) dated September 10, 1993, provided the schedule for responding to the subject RAI.Attachment 3 provides changes to the Technical Specification Bases Table B 3/4.4-1 for each unit.The changes were identified during the preparation of this response and were reviewed pursuant to 10 CFR 50.59.The review determined the changes were not an unreviewed safety question and do not require a change to their respective Technical Specifications.

Enclosures 1 and 2 are proprietary and non-proprietary versions of ABB Combustion Engineering letter (F-MECH-93-050) dated September 28, 1993.This letter provides the upper shelf energy (USE)information on beltline welds for the St.Lucie Unit 1 and Unit 2 reactor vessels.Enclosure 3, CE NPSD-906-P, and Enclosure 4, CE NPSD-906-NP, are proprietary and non-proprietary versions of the ABB Combustion Engineering report"CEOG Program to Evaluate Chemical Content of Weld Deposits Fabricated Using Heats A8746-and 34B009" prepared for the Combustion Engineering Owners Group (CEOG).This report provides the basis for the copper and nickel content of reactor vessel welds for two (2)of the weld wire heats used in the fabrication of the St;Lucie Unit 1 reactor vessel.Enclosures 1 and 3 to this the disclosure of which PDR ADOCK 05000335 P PDR, an FPL Group company letter=contain proprietary information, could compromise trade secrets or~/5 j 4 7~J=<-AJSQD JetQ PZ~Gr'i-l>"..>>.H I k~J' commercial information considered by ABB Combustion Engineering, Inc.as privileged and confidential.

Pursuant to 10 CFR 2.790(a)(4), FPL requests that proprietary versions of the Combustion Engineering letter and report be withheld from public disclosure.

The affidavits required by 10 CFR 2.790 (b)(1)executed by ABB Combustion Engineering supporting this request are included.Please contact us if there are any questions about this submittal.

Very truly yours, D.A.ger Vice r sident St.L'e Plant DAS/GRM/kw DAS/PSL 11014-93 cc: Stewart D.Ebneter, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, St.Lucie Plant St.Lucie Units 1 and 2 Docket No.50-335 and 50-389 Generic Letter 92%1 Revision 1 FPL Letter L-93-286 Attachment AFFIDAVIT PURSUANT TO 10 CFR 2.790 Combustion Engineering, Inc.)State of Connecticut

)County of Hartford)SS.: I, S.A.Toelle, depose and say that I am the Manager, Nuclear Licensing, of Combustion Engineering, Inc., duly authorized to make this affidavit, and have reviewed or caused to have'eviewed the information which is identified as proprietary and referenced in'the paragraph immediately below.I am submitting this affidavit.

in conjunction with the Florida Power and Light Company and in conformance with the provisions of 10 CFR 2.790 of the Commission's regulations for withholding this information.

The information for which proprietary treatment is sought is contained in the following document: ABB Letter F-MECH-93-050

.-/L-MECH-93-015,"Upper Shelf Energy Information Pertaining to the St.Lucie Unit 1 and Unit 2 Reactor Vessel Weld," September 28, 1993.This document has been appropriately designated as proprietary.

I have personal knowledge of the criteria and procedures utilized by Combustion Engineering in designating information as a trade secret, privileged or as confidential commercial or financial information.

Pursuant to the provisions of paragraph{b){4)of Section 2.790 of the Commission's regulations, the following is furnished for p1 2 consideration by the Commission in determining whether the information sought to be withheld from public disclosure, included in the above referenced document, should be withheld.1~2.3~4.The information sought to be withheld from public disclosure, which is owned and has been held in confidence by Combustion Engineering, is specific material and mechanical properties pertaining to the welds in reactor vessels fabricated by Combustion Engineering.

The information consists of test data or other similar data concerning a process, method or component, the application of which results in substantial competitive advantage to Combustion Engineering.

The information is of a type customarily held in confidence by Combustion Engineering and not customarily disclosed to the public.Combustion Engineering has a rational basis for determining the types of information customarily held in confidence by it and, in that connection, utilizes a system to determine when and whether to hold certain types of information in confidence.

The details of the aforementioned system were provided to the Nuclear Regulatory Commission via letter DP-537 from F.M.Stern to Frank Schroeder dated December 2, 1974.This system was applied in determining that the subject document herein is proprietary.

The information is being transmitted to the Commission in confidence under the provisions of 10 CFR 2.790 with the understanding that it is to be received in confidence by the 0~r Commission.

5.The information, to the best of my knowledge and belief, is not 6.available in public sources, and any disclosure to third parties has been made pursuant to regulatory provisions or proprietary agreements which provide for maintenance of the information in confidence.

Public disclosure of the information is likely to cause substantial harm to the competitive position of Combustion Engineering because: a~b.c~d.A similar product is manufactured and sold by major pressurized water reactor competitors of Combustion Engineering.

Development of this information by C-E required hundreds of manhours and hundreds of thousands of dollars.To the best of my knowledge and belief, a competitor would have to undergo similar expense in generating equivalent information.

In order to acquire such information, a competitor would also require considerable time and inconvenience to ascertain the specific material and mechanical properties pertaining to the welds in reactor vessels fabricated by Combustion Engineering.

The information required significant effort and expense to obtain the licensing approvals necessary for application of'I the information.

Avoidance of this expense would decrease a competitor's cost~in applying the information and marketing the product to which the information is applicable.

e.The information consists of specific material and mechanical properties pertaining to the welds in reactor vessels fabricated by Combustion Engineering, the application of which provides a competitive economic advantage.

The availability of such information to competitors would enable them to modify their product to better compete with Combustion Engineering, take marketing or other actions to improve their product's position or impair the position of Combustion Engineering s product, and avoid developing similar data and analyses in support of their processes, methods or apparatus.

f.-In pricing Combustion Engineering's products and services, significant research, development, engineering, analytical, manufacturing, licensing, quality assurance and other costs and expenses must be included.The ability of Combustion Engineering's competitors to utilize such information without similar expenditure of resources may enable them to sell at prices reflecting significantly lower costs.g.Use of the information by competitors in the international marketplace would increase their ability, to;market nuclear steam supply systems by reducing the costs associated with their technology development.

In addition, disclosure would have an adverse"economic ,impact on Combustion f Engineering's potential for obtaining or maintaining l r', St.Lucie Units 1 and 2 Docket No.50-335 and 50-389 Generic Letter 92-01 Revision 1 FPL Letter L-93-286 Attachment AFFIDAVIT PURSUANT TO 10 CFR 2.790 Combustion Engineering, Inc.)State of Connecticut

)County of Hartford)SS.: I, S.A.Toelle, depose and say that I am the Manager, Nuclear Licensing, of Combustion Engineering, Inc., duly authorized to make this affidavit, and have reviewed or caused to have reviewed the information which is identified as proprietary and referenced in the paragraph immediately below.I am submitting this affidavit in conjunction with the Florida Power and Light Company and in conformance with the provisions of 10 CFR 2.790 of the Commission's regulations for withholding this information.

The information for which proprietary treatment is sought is contained in the following document: ABB Letter F-MECH-93-050

/L-MECH-93-015("Upper Shelf Energy Information Pertaining to the St.Lucie Unit 1 and Unit 2 Reactor Vessel Weld," September 28, 1993.This document has been appropriately designated as proprietary.

I have personal knowledge of the criteria and procedures utilized by Combustion Engineering in designating information as a trade secret, privileged or as confidential commercial or financial information.

Pursuant to the provisions of paragraph (b)(4)of Section 2.790 of the Commission s regulations, the following is furnished for 2 of the Commission s regulations, the following is furnished for consideration by the Commission in determining whether the information sought to be withheld from public disclosure, included in the above referenced document, should be withheld.The information sought to be withheld from public disclosure, which is owned and has been held in confidence by Combustion Engineering, is the reactor pressure vessel weld material specifications and procedures.

2~The information consists of test data or other similar data concerning a process, method or component, the application of which results in substantial competitive advantage to Combustion Engineering.

3~The information is of a type customarily held in confidence by Combustion Engineering and not customarily disclosed to the public.Combustion Engineering has a rational basis for determining the types of information customarily held in confidence by it and, in that connection, utilizes a system to determine when and whether to hold certain types of information in confidence.

The details of the aforementioned system were provided to the Nuclear Regulatory Commission via letter DP-537 from F.M.Stern to Frank Schroeder dated December 2, 1974.This system was applied in determining that the subject document herein is proprietary.

The information is being transmitted to the Commission in confidence under the provisions of 10 CFR 2.790 with the understanding that it is to be received in confidence by the Commission.

The information, to the best of my knowledge and belief, is not available in public sources, and any disclosure to third parties has been made pursuant to regulatory provisions or proprietary agreements which provide for maintenance of the information in confidence.

Public disclosure of the information is likely to cause substantial harm to the competitive position of Combustion Engineering because: a.A similar product is manufactured and sold by major pressurized water reactor competitors of Combustion Engineering.

b.-Development of this information by C-E required hundreds of c~thousands of manhours and millions of dollars.To the best of my knowledge and belief, a competitor would have to undergo similar expense in generating equivalent information.

In order to acquire such information, a competitor would also require considerable time and inconvenience to ascertain the reactor pressure vessel weld material specifications and procedures.

The information required significant effort and expense to obtain the licensing approvals necessary for application of the information.

Avoidance of this expense would decrease a competitor's cost in applying the information and marketing the product to which the information is applicable.

e.The information consists of the details concerning the reactor pressure vessel weld material specifications and procedures, the application of which provides a competitive economic advantage.

The availability of such information to competitors would enable them to modify their product to better compete with.Combustion Engineering, take marketing or other actions to improve their product's position or impair the position of Combustion Engineering's product, and avoid developing similar data and analyses in support of their processes, methods or apparatus.

In pricing Combustion Engineering's products and services, significant research, development, engineering, analytical, gi manufacturing, licensing, quality assurance and other costs and expenses must be included.The ability of Combustion Engineering's competitors to utilize such information without similar expenditure of resources may enable them to sell at prices reflecting significantly lower costs.Use of the information by competitors in the international marketplace would increase their ability to market nuclear steam supply systems by reducing the costs associated with H'

their technology development.

In addition, disclosure would have an adverse economic impact on Combustion Engineering's potential for obtaining or maintaining foreign licensees.

Further the deponent sayeth not.s.8.S.A.Toelle Manager Nuclear Licensing Sworn to before me this~d+day of 1993 04M~o ary Pub c'-My commission expires: 3 8(-~

0 J I J l'l foreign licensees.

Further the deponent sayeth not.S.A.Toelle Manager Nuclear Licensing Sworn to before me this~9 dsy of 1993 I y'I o ary Publ c ,"" My.commission expires:

P t/

St.Lucie Units 1 and 2 Docket No.50-335 and 50-389 Generic Letter 92-01 Revision 1 Response to Request for Additional Information (RAI)ATTACHMENT 1 RESPONSE FOR ST.LUCIE UNIT 1 Ori inal GL 92-01 uestion 2.a Certain addressees are requested to provide the following information regarding Appendix G to 10 CFR Part 50: Addressees of plants for which the Charpy upper shelf energy is predicted to be less than 50 foot-pounds at the end of their licenses using the guidance in Paragraph C.1.2 or C.2.2 in Regulatory Guide 1.99, Revision 2, are requested to provide to the NRC the Charpy upper shelf energy predicted for December 16, 1991, and for the end of their current license for the limiting beltline weld and the plate or forging and are requested to describe the actions taken pursuant to Paragraphs IV.A.1 or V.C of Appendix G to 10 CFR Part 50.uestion 2.a in GL 92-01 RAI The response indicates that the initial upper shelf energy (USE)values for welds 2-203A, B, C are not known.Either provide the Charpy USE values for each beltline weld with no documented initial USE value or provide the Charpy USE and analysis from welds that were fabricated using the same vendor, fabrication time frame, fabrication process, and material specification to demonstrate that all beltline welds with no documented initial USE values will meet the USE requirements of Appendix G, 10 CFR 50.If this cannot be provided, then submit an analysis which demonstrates that lower values of USE will provide margins of safety against fracture equivalent to those required by Appendix G of the ASME Code.The response indicates that the initial USE value for the limiting plate, C-8-2, is 103 ft-lb.The staff believes that this initial USE value of 103 ft-lb is from longitudinal Charpy specimens, mistakenly reported as from transverse Charpy specimens.

Two sources support this conclusion:

pages 57 and 58 of report TR-F-MCM-004 labelled this USE value as"longitudinal," and Table B 3/4.4-1 of the plant's Technical Specification listed 78 ft-lb as the"transverse" USE value of this plate.Confirm this and update the EOL USE value for this plate.If the updated EOL USE is below 50 ft-lb based on NRC criteria, then submit an analysis which demonstrates that lower values of USE will provide margins of safety against fracture equivalent to those required by Appendix G of the ASME Code.

P I k~.)N Res onse to RAI uestion 2.a The response to GL 92-01+did not include the upper shelf energy (USE)values for the St Lucie Unit 1 intermediate shell longitudinal welds (2-203A, B, C), because these welds were not considered"limiting" based on their relatively low estimated copper (Cu)and nickel (Ni)content and low RT~~.The unirradiated Charpy USE value for welds 2-203A, B&C was not obtained during fabrication.

These weld seams were all fabricated using the same weld wires A8746 and 34B009 with Linde 124 flux noted in Table 1.Combustion Engineering (CE)performed an analysis of USE values for 68 other CE fabricated welds using Mil B-4 wire and Linde 124 flux+.The average USE value of this data set is 102.3 ft-lbs with a standard deviation of 9.4 ft-lbs.The analysis concluded this average USE value of 102.3 ft-lbs.is applicable for the St Lucie Unit 1 welds 2-203A, B, C.Since the response to GL 92-01, a better estimate for Cu and Ni has been developed for welds 2-203A, B, C.The weld process was a single wire process without the use of additional Ni wire.Two wire heats and flux lots (Table 1)were used indicating a change during fabrication to another heat/lot combination.

An analysis of the best estimates of generic data for the time period for these types of wires was performed by CE+.This analysis concluded that the best estimate (mean plus one standard deviation)

Cu and Ni value for the A8746 weld deposits and 34B009 weld deposits are 0.16%Cu and 0.194 Cu respectively and 0.10%Ni for both welds.Since the exact location of the weld wire switch is not known, the conservatively high 0.194 Cu and 0.104 Ni values are considered the best estimate values for the intermediate longitudinal welds (2-203A, B, C)and will be used to make the decrease in USE value projections.

The new chemistry values do not significantly effect the embrittlement predictions for these welds as they are the least"limiting" of all the St.Lucie Unit 1 beltline welds.The response to GL 92-01 reported that FPL has identified the Beaver Valley Unit 1 surveillance weld was fabricated by the same vendor (CE)using the identical weld wire heat and flux lot as the St.Lucie Unit 1 lower longitudinal welds (3-203A, B, C).The Beaver Valley surveillance weld chemical analysis and the CE qualification chemical analysis are the only two known sources of weld deposit data for this weld wire and flux lot according to the EPRI RMATCH data base.A mean value of Cu, Ni, P, and S are provided in Table 1 as the new chemistry values for this weld.The chemistry and Charpy USE values for all the beltline plates are shown in Table 2.Only the"limiting" surveillance plate was reported in the response to GL 92-01<'>.Using the Cu and USE values from Table 1 and the St.Lucie Unit 1 conservative maximum end of license (EOL)1/4 T vessel fluence (actual azimuthal fluence is less at these longitudinal weld locations)

, the welds 2-203A, B, C will not fall below the 10 CFR 50 Appendix G, 50 ft.-lb., limit within the license life.

I The new mean Cu value of 0.28 wt4, does not effect the previous EOL USE projection for the limiting 3-203A, B, C welds because the projection line for the new Cu value is at the upper limit on R.G.1.99 Rev.2, Figure 2.The projected EOL USE does not fall below the 10 CFR 50 Appendix G, 50 ft.-lb., limit within the license life.The same calculation was performed for two beltline plates that have the highest Cu value and lowest USE values from Table 2.Using these values and the maximum 1/4 T vessel fluence, the beltline plates will not fall below the 10 CFR 50 Appendix G, 50 ft.-lb., limit within the license life.Below are the end of life (EOL)USE projections for St Lucie Unit 1 reactor vessel beltline welds 2-203A, B, C;3-203A, B, C;and the lowest predicted USE beltline plates.Material Initial USE ft-lb (Transverse)

'%u EOL 1/4 T Fluence (n/cm)Reg Guide 1.99 Rev 2%Reduction EOL USE ft-lb Intermediate shell long welds (2-203Ai B, C)Lower shell long welds (3-203Ag B, C)Intermediate shell plate c-7-3 Lower shell plate C-8-1 102.3 112()76 81.9 0.19()0.28 0.11 0.15 2.01 x 1019 1.27 x 10 2.01 x 10~9 2.01 x 1019 39 44%23%28%62.4 62.7 58.5 59.7 The response to GL 92-01 Rev.1 indicated that the unirradiated USE for the limiting St.Lucie Unit 1 beltline plate, C-8-2, is 103 ft.-lb.taken in the transverse direction.

The data was obtained from the baseline surveillance program limiting plate.The specimens were oriented to provide transverse data.This value is also reported on pages 61 and 80 of TR-F-MCM-004().

Pages 57 and 58 of the same report that the Request for Additional Information refers to, is for irradiated data.Since the 103 ft.-lb.value reported in the GL 92-01 response is correct, no updated projection of end of license USE is necessary.

A change to the FSAR will be made to reflect this new data.Attachment 3 is the change to the Technical Specification Bases page.

TABLE 1 ST.LUCIE UNIT 1 REACTOR VESSEL BELTLINE WELD MATERIAL WELD LOCATION Intermediate Shell Long Seam (2-203A, B, C)Lower Shell Long Seam 3-203A, B, C Intermediate to Lower Shell Girth Seam (9-203)HEAT No.A8746/34B009 305424 90136 FLUX TYPE Linde 124 Linde 1092 Linde 0091 FLUX LOT 3878/3688 3889 3999%Cu 0 19c 0.28~0.23b Ni 0.10c 0.63 0.11b 0.018()0.0164 0 013b 0.017()0.0084 0.012b DROP WEIGHT TEST ('F-)NA-60(>>-60b RTNDT (F)-S6'60(>>-60b CHARPY USE (FT-LBS)102.3(2)112()144b NA-Not Available a-Generic data for CE submerged arc welds using Linde 0091, 1092 and 124 Flux per 10 CFR 50.6 b-Surveillance Program Data+c-Best estimated Cu and Ni content (low nickel type wire)@d-Mean value of weld deposit data from CE qualification<@

and the Beaver Valley Surveillance Weld@.

TABLE 2 ST.LUCIE UNIT 1 REACTOR VESSEL BELTLINE PLATE MATERIAL PLATE LOCATION't Cu%Ni DROP WEIGHT TEST (0F.)NDT ('F-)MINIMUM LONGITUDINAL CHARPY USE (FT-LBS)TRANSVERSE CHARPY USE()(FT-LBS)Intermediate Shell Heat No.A4567-1 Code No.C-7-1 Intermediate Shell Heat No.B9427-1 Code No.C-7-2 Intermediate Shell Heat No.A4567-2 Code No.C-7-3 Lower Shell Heat No.C5935-1 Code No.C-8-1 Lower Shell Heat No.C5935-2 Code No.C-8-2 Lower Shell Heat No.C5935-3 Code No.C-8-3 0.11 0.64 0.004 0.11 0.64 0.004 0.11 0.58 0.004 0.15 0.56 0.006 0.15 0.57 0.006 0.12 0.58 0.004 0.013 0.010 0.012 0.010 0.010 0.010-30-30-10 10b-10+10+20+20 126 126 124 126 139b 135 81.9 81.9 80.6 81.9 103b 87.8 Note: Data obtained from Tables 5.2-4A and 5.2-6 from the St Lucie Unit 1 FSAR()unless noted.a)Calculated value using 65%of longitudinal specimen data per MTEB Position 5.2 Paragraph 1.2 b)Surveillance Program Data()(average USE Data)

)8 REFERENCE LIST (1)FPL Letter, L-92-189, St.Lucie Units 1 and 2 Docket No.50-335 and 50-389, Generic Letter 92-01, Revision 1, Response, PT Limits and LTOP Analysis, W.H.Bohlke to NRC, July 7, 1992 (2)"Upper Shelf Energy Information Pertaining to the St.Lucie Unit 1 and Unit 2 Reactor Vessel Welds", ABB-Combustion Engineering, F-MECH-93-050/L-MECH-93-015, September 28, 1993 (3)"CEOG," Program to Evaluate Chemical Content of Weld Deposits Fabricated Using Heats A8746 and 34B009", Combustion Engineering Owners Group, February 1993, CE NPSD-906-P and CE NPSD-906-NP (4)"Florida Power&Light Co.St.Lucie Unit 1 Post Irradiation Evaluation of Reactor Vessel Surveillance Capsule W-97", Combustion Engineering, Inc., December 1983, TR-F-MCM-004 (5)"Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCA's with Loss of Feedwater for the Combustion Engineering NSSS", Combustion Engineering Owners Group, December 1981, CEN-189 and CEN-189 Appendix F (6)FPL Letter, L-77-308, St.Lucie Unit 1 Reactor Vessel Material Information, R.E.Uhrig to D.K.Davis, NRC, September 30, 1977 (7)"Florida Power&Light Co.St.Lucie Unit 1 Evaluation of Base Line Specimens", Combustion Engineering, Inc., October 1984, TR-F-MCM-005 (8)"Florida Power&Light Co., St.Lucie Unit 1 Updated Final Safety Analysis Report", Amendment 11, Chapter 5.0 (9)"Analysis of Capsule W from Duquesne Light Co.Beaver Valley Unit 1 Reactor Vessel Radiation Surveillance Program", Westinghouse Electric Corp., November 1988, WCAP-12005 St.Lucie Units 1 and 2 Docket No.50-335 and 50-389 Generic Letter 92-01 Revision 1 Response to Request for Additional Information (RAI)ATTACHMENT 2 RESPONSE FOR ST.LUCIE UNIT 2 Ori inal GL 92-01 uestion 2.a Certain addressees are requested to provide the following information regarding Appendix G to 10 CFR Part 50: Addressees of plants for which the Charpy upper shelf energy is predicted to be less than 50 foot-pounds at the end of their licenses using the guidance in Paragraph C.1.2 or C.2.2 in Regulatory Guide 1.99, Revision 2, are requested to provide to the NRC the Charpy upper shelf energy predicted for December 16, 1991, and for the end of their current license for the limiting beltline weld and the plate or forging and are requested to describe the actions taken pursuant to Paragraphs IV.A.1 or V.C of Appendix G to 10 CFR Part 50.uestion 2.a in GL 92-01 RAI The response indicates that the initial USE values for all beltline welds, except for the surveillance weld, are not known.Either provide the Charpy USE values for each beltline weld with no documented initial USE value or provide the Charpy USE and analysis from welds that were fabricated using the same vendor, fabrication time frame, fabrication process, and material specification to demonstrate that all beltline welds with no documented initial USE values will meet the USE requirements of Appendix G, 10 CFR 50.If this cannot be provided, then submit an analysis which demonstrates that lower values of USE will provide margins of safety against fracture equivalent to those required by Appendix G of the ASME Code.The response indicates that the initial USE value for the limiting plate, M-605-1, is 105 ft-lb.The staff believes that this initial USE value of 105 ft-lb is from longitudinal Charpy specimens, mistakenly reported as from transverse Charpy specimens.

The plant's Technical Specifications support this conclusion, where all USE values in Table B 3/4.4-1 were labelled as"longitudinal," and the least USE value recorded there was 91 ft-lb for plate M-4116-1.The"transverse" USE value for plate M-4116-1, after applying a factor of 0.65, is 59.2 ft-lb.Confirm this and update the EOL USE value for this new limiting plate.If the updated EOL USE is below 50 ft-lb based on NRC criteria, then submit an analysis which demonstrates that lower values of USE will provide margins of safety against fracture equivalent to those required by Appendix G of the ASME Code.

I C M Res onse to RAI uestion 2.a.The initial response to Generic Letter 92-01+indicated that all the St Lucie Unit 2 upper shelf energy (USE)values for the beltline welds and plates were known and reported in the St Lucie Unit 2 FSAR").Table 1 is a summary of all the beltline weld data from the Tables 5.2-6 and 5.2-7a of the FSAR.The intermediate to lower shell girth seam (101-171)is the most limiting weld for predictions of USE at end of license (EOL).Table 2 is a summary of all the beltline plate data from the Tables 5.2-5 and 5.2-7 of the FSAR.The"limiting" beltline plate with respects to shift in RTND~is the M-605-1 plate and is contained in the St.Lucie Unit 2 Reactor Vessel Surveillance Program.The most limiting beltline plate from an USE prospective would be the lower shell plate M-4116-1 with 91 ft-lbs USE in the transverse orientation.

Using the data from Tables 1 and 2, the maximum vessel fluence and the Regulatory Guide 1.99, Revision 2 prediction for Charpy USE, all the beltline welds and the most limiting beltline plate (USE perspective) do not fall below 50 ft.-lbs USE at or before the end of the current operating license.Below is a table showing the predicted end of license USE at the 1/4 T location for the beltline welds and the limiting (USE)beltline plate requested in the RAI.Material Plate M4116-1 Inter.Shell Long Seams (101-124A, B, C())Lower Shell Long Seams (101 142Ag Bg C)Intermediate to Lower Shell Girth Weld (101-171)Initial USE ft-lb (Transverse) 91 116 136 96(')%Cu 0.06 0.04 0.05 0.07 EOL 1/4 T Fluence (n/cm)1.83 x 1019 1.83 x 10~9 1.83 x 10~9 1.83 x 10~9 Reg Guide 1.99 Rev 2%reduction 22 22 22't EOL USE ft-lb 71 90 106 75 Lowest USE value of the two weld wires used to fabricte this seam.The USE values reported for the St Lucie Unit 2 beltline plate materials are transverse Charpy values.Section 5.3.1.5 of the FSAR+indicates that the beltline material was tested in the weak (transverse) direction and reports that the lowest plate USE value is 91 ft-lbs.A search of the reactor vessel fabrication data package verified that the values reported in the FSAR and Technical Specification Bases are transverse data.A copy of the CMTR for the plate in question is shown in Figure 1 with the heat code and test direction noted.A change to the FSAR will be made to reflect the data as transverse.

Attachment 3 is the change to the Technical Specification Bases pages.

TABLE 1 ST.LUCIE UNIT 2 REACTOR VESSEL BELTLINE WELD MATERIAL WELD LOCATION HEAT NO FLUX TYPE FLUX LOT%Cu%Ni%P DROP WEIGHT TEST (oF)RTyD~CHARPY USE (FT-LBS)Inter.Shell Long Seam (101-124 A)Inter.Shell Long Seam 101-124 B Inter.Shell Long Seam (101-124 C)Lower Shell Long Seam (101-142A)

Lower Shell Long Seam (101-142B)

Lower Shell Long Seam 101-142C Intermediate to Lower Shell Girth Seam (101-171)83642 83642 83642/083637 83637 83637 83637 83637/3P7317 Linde 0091 Linde 0091 Linde 0091 Linde 0091 Linde 0091 Linde 0091 Linde 124 3536 3536 3536/1122 1122 1122 1122 0951 0.04 0.03 0.04 0.04 0.05 0.04 0.07 0.06 0.009 0.06 0.011 0.07 0.009 0.10 0.008 0.09 0.008 0.09 0.008 0.08 0.009 0.010 0.014 0.011 0.009 0.009 0.008 0.011-80-80-80/-50-50-50-50-70/-80-80-80-80/-50-50-50-50-70/-80 116 116 116/136 136 136 136 115/96 Note: Data obtained from Table 5.2-6 and 5.2-7a from the St Lucie Unit 2 FSAR+.

TABLE 2 ST.LUCIE UNIT 2 REACTOR VESSEL BELTLINE PLATE MATERIAL LOCATION (CODE f)HEAT NO%Cu%Ni DROP WEIGHT TEST ('F.)NDT ('F.)TRANSVERSE CHARPY USE (FT-LBS)Intermediate Shell (M405-I)Intermediate Shell (M%05-2)Intermediate Shell (M405-3)Lower Shell Plate (M4116-I)Lower Shell Plate (M4116-2)Lower Shell Plate (M4116-3)A-8490-2 B-3416-2 A-8490-2 B-8307-2 A-3131-1 A-3131-2 0.11 0.13 0.11 0.06 0.07 0.07 0.61 0.62 0.61 0.57 0.60 0.60 0.008 0.008 0.009 0.007 0.007 0.008 0.012 0.014 0.017 0.010 0.009 0.008-10-20-30-50-40+30+10+20+20+20 105 113 113 91 105 Note: Data obtained from Table 5.2-5 and 5.2-7 from the St Lucie Unit 2 FSAR@.

fl"'

JI, ll, Moss 55A I Clitht SI f CII ICAI Ilu VCIII)08 IICAT IIO.IAA TCI,'IAL OCSCI;!r Tlt)II Alh)l:Il)h).5 O,l'III'll:h Jll)II ill i'0)J)Itl:VISIJO)J

))I: 2-10-75'-P3 I'lg 0!)EOIITRACT ll(A 7II72 S.ukl!nn~!'trr.l C:n.IOII RO.72OIM2-OIII ll0307-7 COOC NO, M-4))G-)220-3/I" X 99-9/1 G" X 9-11/1G>>l.ower Shell LIILI.CIII'I!II:AI.

AIIAI.YGIG 7 5 Cil)LI C C I I A II I Ch I.1 I.ST 5 J Trf.~Jt<<23 A43 0 0 0 2!22 EE-TA.505 IC5T Itc.CAUOC TC5T TCUI'LRATIISIC of A.T.TICLO STRCIA~>>TIIA KSI 67 UL'I luh I C Tf IIS(LLT$1RCIIG'III, KSI 7 6 CLOIIO III 0'ŽA 26 0 RCOUCI IN!Of ARCA ni 6 6 EE-TB.505 68.3 88.4 2G.O-~61.5 IMPA5T*HO OM TRACTURP'tESTS'ITf C'TfLtts.Of VALltCS 1tu~.~F VAUKS Charpy impacts-40-40-40+30+30+30+60+60+60+70+70+70+80 80 0 10 0 10 0 26 10 36 lb 38 15 53 25 48 20 45 20 45 20 53 25 60 30 62>30 60+30 63 30 Mlitt TII:Mo 4 4 5 18 22 25 39 33 32 30 38 42 41'5~-40-30-20+100+100+100+160+160+160 62 69 68 93 94 91 40 40 40 100~100 100~DTO Wll lith tt 1 F 1 F.~2 NF 42 50 53 68 68 63-30'F AOOITIOIIAL OAT*RICLUOIIIO IIKAT TRCAT!2CIITI i(-(a)1600'F a 25'F 4hours.Water quenched.(b)122 F a 25'F 4hours.(c)1150'F k 50'F 40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> Jurnaco~co)cd to G00'F.Thc Impacts werc taken transverse to the maior rolling dlrcctlon oJ the plate at the 1/42 T lcvcl and notched pcrpcndlcular to thc plate surface.The dropwclght and tcnsllcs vicrc taken transverse to tho maJor rolling dlrcctlon.

Testing wns done In accordance vf 1th M f, P Spcclllcatlon N-5.5.2.11 (b).Add.1 (a).Fott<<C II50 I:c: P~Webb ll.Dlnwlddle T.U.lvlarston S.A.Lcvfl It.C.Jara!!tf., Jr, Lo LRTOLO Rttttlf tLot tl>>Iottlot<<0 Joto lt~ttw OOOO ol!LO At~IAO<<ltl>>(OS Lf tl>>IMOJWI<>I~ttt Oot 122>>>>l!<<tl>>CO<<AOSttO>>

llotOIIIRSttOI LOtOTOOOMO.

COUOUST!fAI rlmR LCRRIO, lttc.OT Af no III Ith~ganuarst 31~1975 Figure 1: St Lucie Unit 2 Beltline Plate M4116-1 Certified Material Test Report (CMTR)

REFERENCE LIST (1)FPL Letter, L-92-189,"St.Lucie Units 1 and 2 Docket No.50-335 and 50-389, Generic Letter 92-01, Revision 1, Response, PT Limits and LTOP Analysis", W.H.Bohlke to NRC, July 7, 1992 (2)"Florida Power&Light Co., St.Lucie Plant Unit 2, Updated Final Safety Analysis Report", Amendment 8, Chapter 5.0 (3)"Analysis of Capsule W-83, Florida Power&Light Co., St.Lucie Plant Unit 2", Babcock&Wilcox, September 1985, BAW-1880 St.Lucie Units 1 and 2 Docket No.50-335 and 50-389 Generic Letter 92-01 Revision 1 Response to Request for Additional Information (RAg ATTACHEMENT 3 TECHNICAL SPECIFICATION BASES CHANGES UNIT 1 PAGE B 3/4 4-9 UNIT 1 PAGE 3/4 4-10 UNIT 2 PAGE 3/4 4-9 St+ucie Units 1 and 2 Docket No.50-335 and 50-389'eneric Letter 92%1 Revision 1 FPL Letter L-93-286 Attachment AFFIDAVIT PURSUANT TO 10 CFR 2.790 Combustion Engineering, Inc.)State of Connecticut

)County of Hartford)SS.: I, S.A.Toelle, depose and say that I am the Manager, Nuclear Licensing, of Combustion Engineering, Inc., duly authorized to make this affidavit, and have reviewed or caused to have reviewed the information which is identified as proprietary and referenced in the paragraph immediately below.I am submitting this affidavit in conjunction with the application of Florida Power&Light Company in conformance with the provisions of 10 CFR 2.790 of the Commission's regulations for withholding this information.

The information for which proprietary treatment is sought is contained in the following document: CE NPSD-906-P,"GEOG Program to Evaluate Chemical Content of Weld Deposits Fabricated Using Heats A8746 and 34B009," February 1993.This document has been appropriately designated as proprietary.

I have personal knowledge of the criteria and procedures utilized by Combustion Engineering in designating information as a trade secret, privileged or as confidential commercial of financial information.

Pursuant to the provisions of paragraph (b)(4)of Section 2.790

&f ,t 4 L s~J'"~II PROPRIETARY INFORMATION This Document contains proprietary information and is not to be transmitted or reproduced without specific written approval from Combustion Engineering, Inc.Copy No.6S CE NPSD-906-P OMBUSTtON ENGINEERING OWNERS GROUP CEOG PROGRAM TO EVALUATE CHEMICAL COXIKNT OF WELD DEPOSITS FABRICATED USING HEATS AS746 AZ'6)34B009 CEOG TASK 747'f0 CFR 2.790 fNFORMATlON EXEMPT FROM DISCLOSuRE Prepared for the C-E OWNERS GROUP February 1993 ABB Combustion Enaineering Nuclear Power P..9311300069 8D, QD (ID liQQDQD ASEA BROWN BOVERI I I i wary.)'I I P I Combustion Engineering, Inc.Proprietary Information TABLE OF CONTENTS Section No.Title~Pa e Introduction

Background

Scope IV V VI Results Conclusions References 10 I Q/i i I 4 I I I Combustion Engineering, Inc.Proprietary Information LIST OF TABLES Number Title~Pa e'Nickel Content for Coiled Wire Electrode Weld Deposits Weld Seams and Consumables Using[Adcom]Heat¹A8746 Copper Analysis Results for Weld Wire Heat¹A8746 Weld Deposit Copper Content for[Adcom]Wire Heats 12 13 Weld Seams and Consumables Using[Reid Avery]Heat¹34B009 15'opper Content Analysis Results for Weld Wire Heat¹34B009 Weld Deposit Nickel Content with Cold Nickel Feed Nickel Content for Heat¹34B009 with Cold Nickel Feed and Linde 1092 Flux 16 17 18 Best Estimate Copper and Nickel Content for Vessel Welds 19 I~4=f" II I v~4 C P, I Combustion Engineering, Inc.Proprietary Information I.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<eposited 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.

I I I I I I Combustion Engineering, Inc.Proprietary Information 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 bestmtimate 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)(2)(3)(4)The mean of the measured values, or, if these values are not available, the upper limiting values in the material specifications to which the vessel was built, or if not available, conservative estimates (mean plus one standard deviation) based on generic data from reactor vessels fabricated in the same time period to the same material specifications, if justification is provided.If none 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.

I ,l I I+c~I~l I I Combustion Engineering, Inc.Proprietary Information 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:

2.3.[Adcom HiMnMo]weld wire heat A8746 and Linde 124 fiux[Reid Avery HiMnMo]weld wire heat 34B009 and Linde 124 or 1092 flux[Reid Avery HiMnMo]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[HIMnMo]wire weld deposits, specifically heats¹A8746 and 34B009, the copper content of[Adcom]wire weld deposits, specifically heat¹A8746 the copper content of[Reid Avery]heat¹34B009.weld deposits, and the nickel content of[Reid Avery]heat¹34B009 plus Ni-200 cold wire feed weld deposits.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 sh~K a.1 I 8~r~L I 1 m't C+~r~.wl I I Combustion Engineering, Inc.Proprietary Information comparable'".

[Flux type is known to affect certain chemical elements, but nickel and copper contents in the weld deposit have not been found to be substantially affected by fiux'ype for Linde 0091, 1092 and 124 for a given heat of weld wire"'.]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 will be considered for information only.IV.RESULTS 1.Welding Procedures and Specifications ABB/CE fabricated many reactor pressure vessels using automatic submerged.arc welding.[Type Mil-B4 electrode wire specifications (see MIL-E-18193A, Military Specification,"Electrodes, Welding, Carbon Steel and Alloy Steel, Base, Coiled," July 23, 1957)were used as the basis for ABB/CE procurement of the filler wire.In this report, the terminology"wire type" is used to represent the broad classification of weld filler material: Mil-B4 of Mil-B4 Modified (Mil-B4 Mod).The terminology"specification" is used to represent I the specific classification of weld filler material: HIMnM, MnMoNi, MnMo, or Low Cu-P.The terminology"supplier designation" is used to represent the specific compositional classification of wire provided by the supplier to meet the CE specification:

HiMnMo, MnMoNi or Low Cu-P.ABB/CE purchase specifications in place between 1965 and 1971 called for several groups of coiled electrodes differentiated by the manganese (Mn), molybdenum (Mo)and nickel (Ni)content: k~Wire T e Mil-B4 Mod Mil-B4 Mod Mil-B4 Mil-B4 Mod Mil-B4 ABB/CE S~HiMnMo MnMoNi MnMo MnMoNi Low Cu-P Specified Nickel Content 0.90 to 1.10%0.65 to 0.85%Supplier~Desi nation HiMnMo MnMoNi HiMnMo MnMoNi Low Cu-P-4 L I I I Il I Combustion Engineering, Inc.Proprietary Information Only'n the case of the wire designation MnMoNi was any nickel required (specified by CE)to be included in the wire.Note also that Mil-B4 Modified was originally specified by CE as either HiMnMo or MnMoNi.In subsequent specifications, Mil-B4 Modified referred only to MnMoNi wires with nominally 0.75%or 1.00%nickel, and Mil-B4 referred only to HiMnMo, MnMo, or Low Cu-P wires which all had no nickel specified.

The suppliers of coiled wire electrodes typically used the designations as indicated above on their certiftcations.

Supplier certifications and weld material release reports (generated by ABB/CE upon receipt of the wire)included nickel content only for the MnMoNi wires, i.e., the nickel was determined only where it was specified.

Weld material certification tests (weld deposits)and actual vessel weld deposit analyses generally included an analysis for nickel only when MnMoNi wires were utilized or when the vessel equipment specification called for a nickel analysis, Nickel was not intentionally added to a heat because of the extra expense to the wire supplier.Therefore, the nickel content for a HiMnMo or a MnMo wire is expected to be low (significantly less than 0.75%).]2.Observed Nickel Content of[HiMnMo and MnMoNi]Coiled Wire Electrode Weld Deposits[The nickel content of welds deposited using HiMnMo heats"¹A8746 and¹34B009 is not available from ABB/CE weld deposit analysis records.However, nickel content was determined for other HiMnMo heats and for many MnMoNi heats.[Note: welds fabricated using a Ni-200 cold wire addition are not included in the discussion which follows.]A search was" performed of ABB/CE weld receipt and weld deposit analysis records for the years 1965 to 1971, and a list was compiled of each analysis that included nickel content.For each analysis with a reported value of nickel, the supplier I (I*.Pi~t i gi'Y, p I Combustion Engineering, Inc.Proprietary Information designation and wire supplier is noted as shown in Table I;multiple analyses on a single heat are grouped together.The mean and standard deviations described below are based on the average nickel for each heat, whereas the ranges reflect all reported nickel values within each set of wires.The MnMoNi wires fall within two ranges of nickel, 0.59 to 0.82%Ni and 0.89 to 1.10%Ni.The corresponding mean and standard deviation are: mean=0.706%Ni, o'0.051%Ni mean=0.990%Ni, u=0.069%Ni These correspond well to the two specification levels of 0.75%and 1.00%Ni discussed in the previous section.For the HiMnMo wires, nickel content is in the range of 0.01 to 0.16%.The mean nickel value for the 16 heats is 0.058%with a standard deviation of 0.037%Ni, It is clear from the HIMnMo data that nickel was not intentionally added to the original heats from which the electrode wires were drawn.Therefore, for the HiMnMo heats¹A8746 and¹348009, a conservative best estimate (mean plus one standard deviation) of the nickel in the weld deposit is 0.10%Ni.]3.Copper Content of Weld Deposits Using Wire Heat¹A8746[Weld wire heat¹A8746, a HiMnMo coiled electrode supplied by Adcom, was used to fabricate the weld seams described in Table 2.In each case, the submerged arc welding was performed using Linde 124 flux.Two separate weld deposit chemical analyses were performed which involved heat¹A8746 as described in Table 3.Only one of the analyses relates directly to the four weld deposits listed in Table 2.Each of the vessel welds were I II~

Combustion Engineering, Inc.Proprietary Information deposited using Linde 124 flux, whereas only one of the chemical analyses reflected a Linde 124 flux weld.Therefore, the Linde 80 weld deposit analysis can only be used for information.

The Linde 124 flux weld deposit analysis resulted in a copper content of 0,12%using Adcom weld wire heat A8746.In order to judge the viability of the 0.12%copper value, a compilation was made of weld deposit copper contents of other Adcom heats which is given in Table 4.Treating each copper analysis as independent (i.e., assuming that each reflects results from a unique coil), the mean copper content is 0.20%, the standard deviation is 0.036%, and the range is 0.12 to 0.27%.The data include seven different heats or combinations of heats, four different types of flux, two different wire specifications, and a 29 month time period over which wire was procured and analyses were performed.

Therefore, the 0.036%standard deviation for copper reflects heat-to-heat and coil-to-coil variations as well as the influence t of weld flux and the time dependence of the copper coating process on weld deposit copper content.In other words, since the standard deviation represents many Adcom wire heats and other factors, the 0.036%copper (one standard deviation) should conservatively represent the copper variability of welds deposited using a single heat of Adcom wire, heat PA&746.Comparison of the data from Table 3 and Table 4 indicates that the range of available measurements specific to heat PA8746, 0.12 to 0.17%copper, is within the range of the seven different Adcom supplied heats and combinations of heats.Furthermore, the mean of the two A8746 analyses, 0.145%Cu, is within one standard deviation of the single Linde 124 weld deposit analysis (0.036%plus 0.12%equals 0.156%Cu).Therefore, a conservative best It ,e L I Combustion Engineering, Inc.Proprietary Information estimate of the copper content of the welds described in Table 2 is 0.16%based on the heat-specific measurement and the standard deviation for generic Adcom wire heat data.]4.Copper Content of Weld Deposits Using Wire Heat¹348009[Weld wire heat¹348009, a HiMnMo coiled electrode supplied by Reid Avery, was used to fabricate the weld seams described in Table 5, The submerged arc welding was performed using either Linde 124 or Linde 1092 flux.Nine chemical analyses involving heat¹348009 are described in Table 6.The first two entries are laboratory experiment results and, therefore, are not representative of production weld deposits.Four entries are analysis results from samples extracted from a H.B.Robinson Unit 2 (HBR-2)reactor vessel head weld.Three entries are analysis results for the Millstone Unit 1 (MP-1)surveillance weld performed for EPRI and General Electric.The seven representative measurements were from welds deposited using Linde 1092 flux, and the two experimental analysis results were from welds deposited using Linde 1092 or Linde 124.The Linde 1092 flux weld deposit analyses resulted in a mean copper content of 0.19%.This mean of measured values is directly applicable to the Millstone Unit 1 weld described in Table 5.Given that the weld flux does not affect the copper content significantly (see Section III), the 0.19%mean copper is also applicable to the St.Lucie Unit 1 weld described in Table 5 which was deposited using Linde 124 flux.]5.Nickel Content of Weld Deposits Using Wire Heat¹348009 and a Cold Nickel Wire Feed[The Millstone Unit 1 weld described in Table 5 was fabricated using a cold nickel f I~~t I r~v~1'd I I Combustion Engineering, Inc.Proprietary Information wire feed in addition to the electrode wire heat¹34B009.Therefore, the nickel 4 content of that weld would be greater than normal for a HiMnMo wire weld deposit without the nickel feed wire (as discussed in Section IV.2).Table 7 presents 24 sets of data on the nickel content of welds deposited using RACO-3 (Reid Avery)wires, Ni-200 wire (cold nickel feed)and Linde 1092 flux.Only two different wire heats, singly or in tandem, were used.The mean nickel content is 1.065%and the range is 0.72%to 1.21%Ni.Table 8 presents nickel content associated with the Table 6 data in which heat¹34B009 was used with Ni-200 wire and Linde 1092 flux.All but two of the nickel contents specific to heat¹34B009 are within the range of the data from Table 7.The average of the three MP-1 surveillance weld values is 0.94%Ni, and the range is 0.81 to 1.03%Ni.The average of the MP-1 and the two in-range HBR-2 values is 0.88%Ni, and the range is 0.75 to 1.03%Ni for the welds deposited with heat¹34B009.The 0.88%Ni represents the mean of measured values for weld deposits formed using heat¹34B009 with a cold nickel wire feed.However, given the higher mean of the generic data (Table 7), a more conservative estimate of the heat-specific weld nickel content is 1.03%, the upper bound of the data from Table 8.]V.CONCLUSIONS PVelds deposited by Combustion Engineering using HiMnMo coiled wire electrodes yield a mean nickel content of 0.058%with a standard deviation of 0.037%.Therefore, a conservative estimate (mean plus one standard deviation) of nickel content in such welds is 0.10%Ni.]2.[Welds deposited using Adcom Heat¹A8746 (HiMnMo)and Linde 124 flux are conservatively estimated to contain 0.16%Cu and 0.10%Ni.]

I tI I I I I Combustion Engineering, Inc.Proprietary Information

[The welds deposited using Reid Avery Heat¹34B009 (HiMnMo)with Linde 124 or Linde 1092 flux are estimated to contain 0.19%Cu based on the mean of measured values, and conservative estimates of nickel content are 1.03%Ni with a Ni-200 wire addition and 0.10%Ni without a Ni-200 wire addition.]

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.

l Combustion Engineering, Inc.Proprietary Information TABLE 1 Nickel Content for Coiled Wire Electrode Weld Deposits Supplier~Desi nation HiMnMo HiMnMo HiMnMo HiMnMo HiMnMo HiMnMo (Not Reported)HiMnMo HiMnMo HiMnMo HiMnMo HiMnMo HiMnMo HiMnMo HiMnMo HiMnMo Wire~Sn lier Page Page Page Page Page Page Page (Not Reported)Page Reid Avery Reid Avery Reid Avery Reid Avery Reid Avery Reid Avery Reid Avery Nickel~Content e 0.03, 0.05 0.02, 0.02 0.01, 0.03, 0.03 0.03, 0.03, 0.04, 0.04, 0.05, 0.07, 0.11 0.02, 0.03, 0.03, 0.03, 0.03, 0.04, 0.04, 0.05 0.02, 0.03, 0.03, 0.03 0.03, 0.03 0.05 0.06 0.08, 0.09 0.07, 0.08, 0.12 0.16, 0.16 0.04 0.03, 0.06, 0.07 0.10, 0.11 0.05, 0,05, 0.06 MnMoNi MnMoNi MnMoNi MnMoNi MnMoNi MnMoNi MnMoNi MnMoNi MnMoNi MnMoNi MnMoNi Adcom Adcom Page Adcom Reid Avery.Reid Avery Adcom (Not Reported)Reid Avery Reid Avery Reid Avery 0.74 0.73, 0.74 0.64, 0.68, 0.68, 0.59, 0.61, 0.72, 0.59, 0.60, 0.62, 0.64, 0.64, 0.64, 0.73 0.69 0.73, 0.74 0.69, 0.72, 0.72, 0.75, 0.78, 0.79, 0.70, 0.71 0.72 0,64, 0.64 0.66 0.73, 0.74, 0.76, 0.81 0.80, 0.82 MnMoNi MnMoNi MnMoNi MnMoNi Adcom Adcom Adcom (Not Reported)1.00, 1.01 1.02, 1.03, 1.03, 1.04, 1.04, 1.05, 1.05, 1.05, 1.08 0.96, 1.00(4), 1.02(2), 1.06(2), 1.10 0.89 I I I Combustion Engineering, Inc.Proprietary Information TABLE 2 Weld Seams and Consumables Using[Adcom Heat]PA8746[(HiMnMo)]

Reactor Vessel Calvert Cliffs Unit 2 St.Lucie Unit 1 Millstone Unit 2 Weld Seam No ote 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~Sufi SAA-4-0 SAA-4-0 SAA-4-0 SAA-MA-501-2 Note 1: Note 2;All of the weld seams listed were deposited without a cold nickel wire feed.Weld wire heat¹34B009[(Reid Averyi]was also used with heat¹A8746 to deposit the weld seams in a single are process.

I l Combustion Engineering, Inc.Proprietary Information TABLE 3 Copper Content Analysis Results for Weld Wire Heat¹A8746 KAdcom HiMnMo)]of Anal sis Date Flux/Lot No.~Co euro Weld Deposit Weld Deposit.8/27/69 Linde 124/¹3878 8/19/69 Linde 80/¹8651 0.17 0.12 I l n, l Combustion Engineering, Inc.Proprietary Information TABLE 4 Supplier~Desi nation Flux~Te Weld Deposit Copper Content for[Adcom]Wire Heats'Copper~Content o HiMnMo HiMnMo MnMoNi MnMoNi MnMoNi MnMoNi MnMoNi MnMoNi Linde 124 Linde 80 Linde 0091 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 0.12 (Note A)0.17 (Note A)0.16 0.16, 0.20 0.18, 0.19, 0.20(2), 0.21(2), 0.22(2), 0.24, 0.25 0.22 0.22 (Note B)0.27 (Note B)Note A-From Table 3 Note B-Combination of two Adcom heats in weld deposit I I l Combustion Engineering, Inc.Proprietary Information TABLE 5 Weld Seams and Consumables Using[Reid Avery]Heat¹34B009[(HiMnMo)]

eactor Vessel Weld Seam No.Weld Flux T Weld Procedure S N St.Lucie Unit 1 2-203 A, B, C (Note 1)Linde 124 SAAMO Millstone Unit 1 3-073 (Note 2)Linde 1092 SAA-33-J(1)

Note 1: Weld wire heat¹A8746[(Adcom)]was also used with heat¹34B009 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.

5 b~4 I l l I l Combustion Engineering, lnc.Proprietary Information TABLE 6 Copper Content Analysis Results for Weld Wire Heat 434B009 T~IA I I Tl~T C~C Source Weld Deposit Linde 1092 0.15 CE Lab Experiment Weld Deposit Weld Deposit Linde 124 Linde 1092 0.17 0.180 CE Lab Experiment HBR-2 Head Sample Weld Deposit Linde 1092 0.182 HBR-2 Head Sample Weld Deposit Linde 1092 0.183 HBR-2 Head Sample Weld Deposit Linde 1092 0.202 HBR-2 Head Sample Weld Deposit Linde 1092 0.18 MP-1 Surveillance Weld (EPRI)Weld Deposit Linde 1092 0.19 MP-1 Surveillance Weld (EPRI)II Weld Deposit Linde 1092 0.18 MP-1 Surveillance Weld (GE Report NEDC-30299)

~~~(g y5~~~~~~

Combustion Engineering, Inc.Proprietary Information TABLE 7 Weld Deposit Nickel Content with Cold Nickel Feed Source Nickel Content o Mixed Reid Avery Heats, Linde 1092 flux and Ni-200 wire 1.06, 1.03, 1.15, 1.16, 1.15, 1.08, 1.03, 1.06, 1.06, 1.04, 1.10, 1.01, 1.04, 1.15, 1.07 Single Reid Avery Heat, Linde 1092 fiux and Ni-200 wire 0.99, I.12, 0.92, 0.94 (Note 1), 1.115 (Note 2), 1.05, 1.20, 0.97 Note 1: Average of 20 analyses from single weld, with a range of 0.72 to 1.08%Ni.Note 2: Average of 2 analyses from one surveillance program weld (1.02 and 1.21%Ni).

)~~~~'1~~I~~~~~

Combustion Engineering, Inc.Proprietary Information TABLE 8 Nickel Content for Heat 0'34B009 with Cold Nickel Feed and Linde 1092 Flux Nickel Content Source 0.75 0.32 0.84 0.43" 0.81 0.98 1.03 HBR-2 Head Sample HBR-2 Head Sample HBR-2 Head Sample HBR-2 Head Sample MP-1 Surveillance Weld (EPRI)MP;1 Surveillance Weld (EPRI)MP-1 Surveillance Weld (GE Report NEDC-30299)

I l~l~~~

Combustion Engineering, Inc.Proprietary Information TABLE 9 Best Estimate Copper and, Nickel Content for Vessel Welds Reactor Vessel Calvert Cliffs Unit 2 Weld Seam No.2-203 A,B,C~Content e Cu Ni 0.16" 0.10 St.Lucie Unit 1 2-203 A B Ctt)2-203 A,B,Ct')0.16 0.10 0.19 0.10 Millstone Unit 2 2-203 A,B,C 3-203 A,B,C 0.16 0.10 0.16 0.10 Millstone'nit 1 3-073 0.19 1.03 Notes e (1)Chemical content contribution from wire heat PA8746 (2)Chemical content contribution from wire heat 034B009 I~1I~I

,"St.Lucie Units 1 and 2 Docket No.50-335 and 50-389 Generic Letter 92%1 Revision 1 FPL Letter L-93-286 Enclosure 1 iL Il)IR~~~meme 10 CFR 2.7SO INFORMATION EXEMPT FROM DISCLOSURE Cobol ol September 28, 1993 F-MECH-93-050

.I 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 Welds" 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.1.0 St.Lucie Unit 1: 1.1 Barrack 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 Engineering, tnc.1000 Prospect Hitl Road Post Otfice Box 500 Windsor, Connecticut 060954500 Telephone (203)688 1911 Fax (203)285-9512 Tetex 99297 COMBEN WSOR

PROPRIETARY INFORMATION COMBUSTION ENGINEERING, INC.Mr.Scott Boggs September 28, 1993 F-MECH-93-050 I MECH-93-015 Page 2 of 10 determined at the time of manufacture, 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-B4 wire and Linde 124 Flux.1.2~Sco e This report provides a basis for the initial upper shelf energy for weld wire heat numbers A8746 and 34B009 fabricated with Linde 124 flux using USE data from welds fabricated with Linde 124 flux.1,3 Procedure Weld material certifications (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 PROPRIETARY INFORMATION COMBUSTION ENGINEERING, INC.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 initial upper shelf energy in accordance with ASTM E185-82 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 if omitted.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[102.3 ft-lbs with a standard deviation of 9.4 ft-lbs.]The data ranges from[82.7 ft-lb to 125.7 ft-lb.]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 ft-lb 1 30502/0342 2 3P7150/0662 3P7150/1061 3P7246/0662 3P7246/0951 3P7246/1061 7 3P7317/0281 3P7317/0662 3P7317/0951 104.3 97.0 86.0 97.3 108.0 103.7 94.0 98.3 102.7 10 3P7317/1061 3P7802/0171 103.0 109.7

\~

Mr.Scott Boggs September 28, 1993 PROPRIETARY INFORMATION COMBUSTION ENGINEERING, INC.F-MECH-93-950 L-MECH-93-015 Page 4 of 10 Count 12 13 14 15 16 17 18 19 20 21 22 23 25 26 27 28 30 31 32 33 34 35 36 37 38 39 Wire Heat/Flux Lot 3P7802/0281 3P8013/0281 3P8013/0871 CU3P8013/0281 4P6524/0951 4P7656/0951 4P7656/1061 4P7869/0171 4P7869/0281 4P7869/0871 4P7869/1061 4P7927/0662 4P7927/1061 4P8632/0281 SP7388/0662 SP8866/0171 SP8866/1061 SP9028/0281 651A708/0281 651A708/0871 90071/0951 83637/0951 83646/1061 83653/1061 87005/1061 89408/0751 89476/1061 89827/0951 Initial USE ft-Ib 104.7 93.7 110.0 104.7 106.3 88.0 91.3 107.7 104.7 93.7 97.3 115.7 116.3 109.3 107.7 91.3i 107.7 96.7 94.0 96.3 112.7 116.7 106.0 106.7 90.3'110.7 100.0 118.3 0~4,>>e l H 1 1t PROPRIETARY INFORMATION COMBUSTION ENGINEERING, INC.Mr.Scott Boggs September 28, 1993 F-MECH-93-950 L-MECH-93-015 Page 5 of 10 Count 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 Wire Heat/Flux Lot 89828/0281 89828/0951 89828/1061 89833/0871 89833/0951 89833/1061 90067/0951 90069/0951 90069/1061 90077/0951 90077/1061 90128/0951 90132/0951 90144/1061 90146/1061 90149/1061 90154/0951 90157/1061 90159/0951 90209/1061 90211/1061 91762/0662 91762/1061 E56906/0662 F69025/0171 69025/1061 LP2P8374/0597 LPSP9744/0281 Initial USE ft-lb 96.0 109.3 104.3 113.3 105.3 95.7 124.3 125.7 97.6 115.7 112.3 99.3 115.0 93.0 96.7 94.0, 102.3 98.0 112.7 100.7 82.7 88.0 100.3 89.3 91.0 88.6 98.3 109.0 PROPRIETARY INFORMATION COMBUSTION ENGINEERING, INC.Mr.Scott Boggs September 28, 1993 F-MECH-93-950 L-MECH-93-015 Page 6 of 10 Count 68 Wire Heat/Flux Lot PSP73Sg/0342$Average USE: Standard Deviation:

Initial USE ft-lb 97.7 102.3 (ft-Ib)9.4 (ft-ib)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 FP8rL and repeated in Reference 2.The basis for the initial upper 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~Sco e Weld material certification test reports (WMCs)for the following weld wire heat and flux 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)~

PROPRIETARY INFORMATION COMBUSTION ENGINEERING, INC.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.

[The initial upper shelf energy was determined from a set of three Charpy specimens tested at 160'F.All three specimens show a fracture appearance of 100%shear failure and the initial upper shelf energy calculated to be 116.7 ft-lb.]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.

[The initial upper shelf energy was determined from a set of three Charpy specimens tested at 160'F.All three specimens show a fracture appearance of 100%shear failure and the initial upper shelf energy was calculated to be 102.7 ft-lb.]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.[An average PROPRIETARY INFORMATION COMBUSTION ENGINEERING, INC.Mr.Scott Boggs September 28, 1993 F-MECH-93-950 L-MECH-93-015 Page 8 of 10 Charpy energy at 10'F was calculated from three specimens to be 116.3 ft-lbs.]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.[An average Charpy energy was calculated from three specimens to be 136.3 ft-lb.]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 MII B4 wire and Linde 124 flux was calculated to be[102.3 ft-lb with a standard deviation of 9.4 ft-lb.]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[102.7 ft-lb.]Weld wire heat 83637 with Linde 124 flux lot 0951 has a calculated initial upper shelf energy value of[116.7 ft-lb.]Weld wire heat 83637 with Linde 0091 flux lot 1122 has an average Charpy energy at 10'F of[136.3 ft-lb;]weld wire heat 83642 with Linde 0091 flux lot 3536 has an average Charpy energy at 10 F of[116.3 ft-lb.]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.

PROPRIETARY INFORMATION COMBUSTION ENGINEERING, INC.Mr.Scott Boggs September 28, 1993 F-MECH-93-950 I MECH-93-015 Page 9 of 10 If you 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, COMBUSTION ENGINEERING, INC Davi J.Woodilla Project Engineer Enclosure VERlFlCATION STATUS: COMPLETE atro Saloty8ctatod dostgnMormatton

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'tOAMigL Ogosssss Oosiogs-Coco asac coo.Vsllg scil co To so os.Toss go sag Soo.~Pwarc D.Srrrm~n,v Indopondont RoNtowon Narno/SignaturolOato Mr.Scott Boggs September 28, 1993 PROPRIETARY INFORMATION COMBUSTION ENGINEERING, INC.F-MECH-93-950 L-MECH-93-015 Page 10 of 10

References:

1.Letter from J.A.Norris (NRC)to J.H.Goldberg (FP&L), 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 Light Company Purchase Order No.B93633-30016, dated August 31, 1993.4.5.ABB/CE Letter No.MECH-93-1214,"Weld Material Certification Reports", S.T.Byrne, dated October 14, 1993.ASTM Designation E 185-82,"Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels," Annual Book of ASTM Standards, Vol.12.02, ASTM, Philadelphia, PA.

Mr.Scott Boggs September 28, 1993 PROPRIETARY INFORMATION COMBUSTION ENGINEERING, INC.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 PROPRIETARY INFORMATION COMBUSTION ENGINEERING, INC.F-MECH-93-050 L-MECH-93-015 Page A2 of A10 Contents of Appendix A~Pa e A4 A6 A8 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 PROPRIETARY INFORMATION COMBUSTION ENGINEERING, INC.F-MECH-93-050 I MECH-93-015 Page A3 of A10 Certified Material Test Re ort for Weld Wire Heat No.83637 Linde Flux e 124 Flux Lot No.0951 Mr.Scott Boggs September 28, 1993 PROPRIETARY INFORMATION COMBUSTION ENGINEERING, INC.F-MECH-93-050 I MECH-93-015 Page A4 of A10"~PQQJFR SYSTEMS To J.McDowell cc: R.E.Lorentz, Jr.S.R.Lewis S.A.Lewis B.Goins Sub ject Welding Material Certlficatlon To Requirements of, ASME Section III Job Number M-32255 Project Number 960009'rom-Date Metallurgical

&Materials Laboratory Chattanooga 4-22-76 The following test dat s for 3/16" dl eter bare're, Type Low Cu-Phos, Heat No.83637, Flux Type 124, Lot No.09 (Test No.1824).A weld deposit was made using the above heat of wire and lot of flux.Welding was done in accordance with SAA-SMA-511-0.

The completed weldment was given a post weld heat treatment of 1150'F+50'F for 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> and furnace cooled to 600 F.IMPACT AND/OR F RACTUR E TESTS TYPE TEMP OF VALUE TEMP.0F VALUES NOT CVN-80-80:-80'40-40-40\-108-1oi+60+60+60~tJ bs~her 21 26 S~52 35 40.'0 55 35 6Fg 60 9 80 94 70 105 80 106 80~108 80 ilsLatEx 21 18 17 42 32 40~72+78 75 77-70-60-50+100+100+100+160+160+160 Dro We laht 1 F 2 NF 1 NF 112/116'17 120 113 100 84~100/8&.100 90 100 86 100 86-70 F ALL'WELD METAL.505 TENSILE Lab C;ode.i'P Yie ld Streng th KS[69.0 Ultimate Tensile Strenath KS 84.3 Elongation 2 41n/Reduction of Area%69.2 JMA:gb

Mr.Scott Boggs September 28, 1993 PROPRIETARY INFORMATION COMBUSTION ENGINEERING, INC.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 PROPRIETARY INFORMATION COMBUSTION ENGINEERING, INC.Mr.Scott Boggs September 28, 1993 pj444'<<<<I~Žt~".==a PGQfEH SVS7tr.MS F-MECH-93-050 L-MECH-93-015 Page A6 Of A10 To Subject From-Date Metallurgical 6, Material Laboratory Welding Material Certification To Requirements of ASME Section III Job Number M-322SS Prospect Number 960009 J.McDowell cc: R.E.Lorentz, Jr.S.R.Lewis Chattanooga Phos, Heat No.3P7317, Flux Type 124, Lot No.0951.(Test No.1859)S.A.Lewis B.Goins PROPRIETARY The following test data s for 1/8" dia er bare wier ype Low Cu-A weld deposit was made using the above heat of wire a lot of faux.Welding was done in accordance with SAA-SMA-104-0 The ciafpletdtfŽ weldment was given a post weld heat treatment of 1150'F+50'F for 40~hours and furnace cooled to 600'F.IMPACT AND/OR F RACTUR E TESTS TYPE TEMP oF VALUES TEMP.0F VALUES NOT CVN-80-80-80-40-40-40-20-20 ,-20>+20+20+20+60+60+60 goths'ea 15 0~23 5 21 5 42 30 40 30 33/'0 51~30 50 30 52>3O 72 60 75.60 77 60 97 100 102 100 99 100~111aLatEx 10 13 12 26 25 20'1 48 S3~51 66 70 68-90-80-70-60+100+100+100+160+160+160 1 F 1 NF 1 F 2 NF 1 NF 94'00 93+~100+100<100>96 100 104 100 108 100 6 63 70 68 73 79-80'LL WELD METAL.505 TENSILE Lab Code Yield Strengt KS[69.5 Ultimate Tensi Streneth K.p 85.5 Elongation in 2"%28.5 4-"JA'mold (r Reduction of Area%69.0 JMA:gb Mr.Scott Boggs September 28, 1993 PROPRIETARY INFORMATION COMBUSTION ENGINEERING, INC.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 e 0091 Flux Lot No.3536

~~~~'~~~4~'~0~~s o g~~o~I s~~I I~~~o~~~--~~~-~~~~~~~~'I II'~~~~~~~~~~~~~~~o~~~~~~~~~~~~~~~~~~~~~~~~0'0 o~~~~~~I I~~-~~~~I~I~~~~~~~~~~~

Mr.Scott Boggs September 28, 1993 PROPRIETARY INFORMATION COMBUSTION ENGINEERING, INC.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 e 0091 Flux Lot No.1122.

Mr.Scott Boggs September 28, 1993 F-MECH-93-050 PROPRIETARY INFORMATION L-MECH-93-015 COMBUSTION ENGINEERING, INC.Page A10 of A10 ill I CM-Uf I IUD UUHVCEDl UIM!.)I..I I'Est l CONIHUSYIQM DIVISIIGM Sub ect E-f PROPRf From-Date Mr.P.C.Kiefer:c: Mr.R.Jay Mr.S.A.Lewis Mr.S.R.Lewis Mr.R.E.Lorentz, jr.Mr.G.Porter Mr.R.E.Smith Welding Material Qualification to Requirements of ASME Section III Job Number D-32255 Project Number 960009 Metallurgical Research and Development Department Chattanooga February 8, 1973The following test data is for 3/16" diameter bare wire, type low Cu-Phos., Heat No.83637, Flux Type 0091, Lot No.1122.A weld deposit was made using the above heat of wire and lot of flux.Welding was done in accordance with C-E Welding Procedure Specification SA-33-34.The completed weldment was given a post weld heat treatment of 1150'F+25 F for 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> and furnace cooled to 600'F.IMPACT AND OR FRACTURE TESTS TYPE TEMP oF VALUES~Ft.Lbs.Mils Lat.Exn.TEMP.oF VALUES Dro Wei hts NOT+10"+10+10 153 131 125 85 81 77-50-40 1F 2 NF-50 F ALL WELD METAL.505 TENSILE Lab Yield Strength Code KSI Ultimate Tensile Strength.KSI Elongation in 2" Reduction of Area/o BC 77~2 29.$73.1.Arnold