ML17354B036

Forwards Response to NRC 980407 RAI Re GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity. Evaluation Re Addl Weld Chemistry Data for Reactor Pressure Vessels Fabricated by B&W Obtained from Framatome Technology,Encl

ML17354B036
Person / Time
Site:	Turkey Point
Issue date:	07/13/1998
From:	Hovey R FLORIDA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-92-01, GL-92-1, L-98-155, TAC-MA0579, TAC-MA0580, TAC-MA579, TAC-MA580, NUDOCS 9807210331
Download: ML17354B036 (19)

Text

CATEGORY 1 REGULA'I Y INFORMATION DXSTRXBUTXO SYSTEM (RIDS)

ACCESSION NBR:9807210331 DOC.DATE: 98/07/13 NOTARIZED: NO DOCKET FACIL:50-250 Turkey Point Plant, Unit 3, Florida Power and Light C 05000250 50'-251 'Turkey Point Plant, Unit 4, Florida Power and Light C 05000251 AUTH. NAME AUTHOR AFFILIATION HOVEY,R.J. Florida Power & Light Co.

RECIP.NAME RECIPIENT AFFILIATION Records Management Branch (Document Control Desk)

SUBJECT:

Forwards response to NRC 980407 RAI re GL 92-01,Rev 1,Suppl 1, "Reactor Vessel Structural Integrity." Evaluation re addi weld chemistry data for reactor pressure vessels A fabricated by B&W obtained from Framatome Technology, encl.

I T DISTRIBUTION CODE: A028D COPIES RECEIVED:LTR 1 ENCL SIZE:

TITLE: Generic Letter 92-01, Rev 1, Suppl 1 Responses (Reactor Vessel NOTES: Structa,'ECIPIENT COPIES ' RECIPIENT COPXES ID CODE/NAME LTTR ENCL XD CODE/NAME LTTR ENCL PD2-3 PD 1 1 JABBOUR,K 1 1 XNTERNA . FILE E 1 NRR/DE/EMCB 1 1 OCS-ABSTRACT 1 1 OGC/HDS3 1 0 RES/DET/EMMEB 1 1 EXTERNAL: NOAC 1 1 NRC PDR 1 1 D

N NOTE TO ALL NRIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 9 ENCL 8

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JUL 18 1998 II-I%4. 1 L-98-155 10 CFR 50, Appendix G U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555-0001 Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Response to Request for Additional Information Generic Letter 92-01, Revision 1, II V ri ll On April 7, 1998, the NRC issued "Request for Additional Information Regarding Reactor Pressure Vessel Integrity at Turkey Point Units 3 and 4 (TAC Nos. MA0579 and MA0580)rn requesting that Florida Power and Light Co. (FPL) evaluate the additional weld chemistry data for reactor pressure vessels fabricated by Babcok & Wilcox Company obtained from Framatome Technologies, and determine if the additional data identified affects previous reactor pressure vessel integrity analyses.

In accordance with the NRC request, attached is the FPL response to the NRC's questions, for Turkey Point Units 3 and 4.

Should there be any questions, please contact us.

Very truly yours, R. J. Hovey Vice President Turkey Point Plant OIH Attachments cc: Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant 98072i0331,980713 PDR ADOCK 05000250 P PDR an FPL Group company

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f to L-'98-$ 55 Page 1 Turkey Point Units 3 and 4 Response to Request For Additional Information 0 neri L t r 2-01 Revi ion 1 1 mn 1 The following information is provided in response to "Request for Additional Information Regarding Reactor Pressure Vessel Integrity at Turkey Point Units 3 and 4 (TAC NOS. MA0579 and MA0580)," issued by the NRC on April 7, 1998.

NRC Question 1 The NRC requests an evaluation of the information forwarded by letters from Matthew Devan of Framatome Technologies to Barry Elliot the NRC and an assessment of its applicability to the of determination of best-estimate chemistry for all your reactor pressure vessel (RPV) beltline welds. Based on this reevaluation, supply the information necessary to completely fill out the data requested in Table 1 for each RPV beltline weld material. Also provide a discussion of the copper and nickel values chosen for each weld wire heat noting which heat-specific data were included and excluded from the analysis and the analysis method chosen for determining the best-estimate copper and nickel values.

FPL Response The Turkey Point Units 3 and 4 RPVs were fabricated by Babcock &

Wilcox (BEW) using ring forgings joined by submerged arc welds.

Therefore, there is only one beltline circumferential weld in the core midplane. The beltline circumferential weld for both vessels is designated SA 1101, fabricated from Page weld wire heat number 71249.

The copper and nickel values currently used for the Turkey Point Units 3 and 4 RPV circumferential limiting welds are 0.26% and 0.60-: respectively. These values were developed by FPL for weld wire number 71249 in 1984 and submitted to the NRC by FPL letter L-84-31, dated February 10, 1984. The NRC evaluated this submittal and approved the use of the current copper and nickel values by letter dated April 26, 1984. FPL developed these values from a database of 51 analyses for copper and 41 for nickel. The 0.26% copper and 0.60% nickel values are an arithmetic mean of all values in the population, consistent with

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to L-'98 3,55 Page 2 the guidance provided in Regulatory Guide (RG) 1.99, Revision 2.

Based on the information available at that time, all welds using Page weld wire heat number 71249 weld metal were included. These welds were identified as SA 1101, SA 1229, SA 1094 and SA 1769.

As a result of the May 1997 NRC inspection of Framatome Technologies, Inc. (FTI), additional weld chemistry data was identified for RPVs fabricated by Babcock & Wilcox (BSW). BAW-2325, "Response to Request for Additional Information (RAI)

Regarding Reactor Vessel Integrity," dated May 1998, was developed by FTI for the BSW Owners Group Reactor Vessel Working Group. BAW-2325 provides the most current materials and fabrication information available for the 15 vessels operated by members of the BGW Owners Group, and documents the methodology used to develop this data. This report was submitted to the NRC by the B6W Owners Group per letter OG-1707, dated May 28, 1998.

The BAW-2325 chemistry table pertaining to Turkey Point Units 3 and 4 contains 94 copper values (all of which are included in the reevaluation) and 80 nickel values (of which all but 6 are included in the reevaluation).

The following Table (Table 3-2 from BAW-2325) lists the source from which all the data were derived, and the mean of all sources.

TABLE 3-2 from BAW-2325 Weld ID Flux Source of No. of Observ. Source Mean Heat Number Number Lot No Weldment Cu Ni Cu Ni 71249 SA-1094 8457 eld Qualification 0.23 0.55 PQ RVSP Weld 0.29 0.60 A-1101 8445 eld Qualification 1 1 0.21 0.57 ONS-1 Nozzle Dropout 37 36 0.19 0.59 P-3 RVSP Weld 6 1 0.33 0.57 SA-1229 8492 eld Qualification 0.20 0.57 SA-1344 8504 eld Qualification 0.21 0.62 SA-1706 8669 eld Qualification 0.21 0.55 A-1769 8738 eld Qualification 1 1 0.19 0.66 Surv. Weld 41 36 0.28 0.62 Weld Wire Heat Best-Estimat 0.23 0.59 (Mean of the Sources)

~ ~ to L-'98-$ 55 Page 3 The best-estimate copper and nickel chemical compositions for the high-copper Linde 80 weld metals were determined by first establishing the mean for each particular material source, e.g.,

nozzle belt dropout, surveillance block/specimen, weld qualification, and weld qualification retest. These material source means were then used to calculate the mean for the weld wire heat. This method is preferred because it eliminates the possibility of skewing or misrepresenting data due to performing a large number of analyses based on a few sources.

This current data base includes all data used in the 1984 analysis, and adds 42 new copper data points. The data base provides the basis needed for validation of one copper data point which was not used in 1984. The current data base also adds 39 new nickel data points. The majority of the new data comes from a series of samples tested by Oakridge National Laboratories, B&W (Barberton, Mt. Vernon, and Lynchburg), National Institute for Standards of Testing (formerly National Bureau of Standards), and JEL Steel; and Heavy Section Steel Technology material 61W which was recently identified as a 71249 material. Two new welds, SA 1344 and SA 1706, were located and identified as a Page weld wire heat number 71249. Table A-4 from BAW-2325 (Attachment 2 to this response), lists the individual data points and the specific reasons for exclusion, if applicable. The excluded data has no significant effect on the mean of means best-estimate chemistry data for Turkey Point Units 3 and 4 RPVs.

Based on the validation of the 1984 data, the sources of the new data, and the application of mean of the means averaging technique, FPL understands how the data was developed and is confident that the reported values of 0.23 0 copper and 0.59 nickel represent the best-estimate for the deposited 71249 weld metal. Table 1 is completed as requested.

Attachment 1 to L"98-$ 55 Page 4 TABLE 1 Turkey Point Units 3 and 4 Beltline Weld Material Weld %Ni EOL ID Chemis- Method Initial Sigma Sigma Margin ART/

Wire

%Cu Best Best Esti-Fluence try for CF RT~ Ini-tial Delta

('F)

('F) Re~i I Heat Esti- (E19) Factor ('F) EOL mate mate (CF) ('F) ('F)

('F) 71249 0.23 0.59 2.74 167.55 table 10 28 56 278.6 Table 1 Notes:

Turkey Point Units 3 and 4 have the same limiting weld, SA 1101 (weld wire 71249).

There are three Turkey Point specific surveillance data points for this weld wire.

The data is not credible using RG 1.99 Revision 2 criteria.

Initial RTNDT is based on 1 set "An drop weight and charpy data as documented in EPRI NP-373, Investigation of Mechanical Properties and Chemistry Within a Thick MnMoNi Submerged Arc Weldment," February 1977.

Best estimate chemistry is obtained from BAW-2325.

End of Life (EOL) fluence data was updated as per the Turkey Point Units 3 and 4 Uprating submittals, FPL letters L 245, dated December 18, 1995, and L-96-117, dated May 3, 1996.

The "ratio procedure" was not used other than to verify that the data is not "non-conservative" per NRC guidance of November 1997. Since the surveillance welds have higher copper values than the mean, not using the ratio procedure is conservative.

Attachment 1 to 4-98-155 Page 5 NRC Question 2 The NRC requests the following: that (1) the information listed in Table 2, Table 3, and the chemistry factor from the surveillance data be provided for each heat of material for which surveillance weld data are available ~n a revision of the RPV integrity analyses (i.e., current licensing basis) is needed or (2) a certification that previously submitted evaluations remain valid. Separate tables should be used for each heat of material addressed. If the limiting material for your vessel's PTS/PT limits evaluation is not a weld, include the information requested in the tables for the limiting material (if surveillance data are available for this material) .

FPL Response Table 2 summarizes the results of surveillance capsule testing using updated fluence from WCAP 14044, "Westinghouse Surveillance Capsule Neutron Fluence Reevaluation," April 1994, and measured data using the hyperbolic tangent fit from NUREG/CR-6551, Draft, for Reactor Vessel Steels."

"Improved Embrittlement Correlations TABLE 2 Turkey Point Units 3 and 4 Surveillance Results Capsule ID Ni Irr('F)

Temp Fluence Measured delta Data used Assessing in (Source) (819) RTrpr

('F) Vessel 3T(PTN3) 0.33 0. 57 546 166 Yes 3V (PTN3) 0.33 0.57 546 1.53 180 Yes 4T (PTN4) 0. 29 0. 60 546 .708 211 Yes Table 3 is a summary of the measured surveillance data from Turkey Point Units 3 and 4 calculated using the analytical treatment recently suggested by the NRC Staff, and referenced in the Request for Additional Information.

Attachment 1 to I("98-155 Page 6 TABLE 3 Turkey Point Units 3 and 4 Surveillance Results Capsule Ni CF Irradia- Fluence Measured Ad)usted Predicted (Ad)usted-ID

('F) tion Temp Factor delta RT mr Delta Predicted)

('F) RT mr ('F) ('F) RT mr ('F) Delta RT mr

('F) 3T .33 .57 201.3 546 0.915 166 163 172 -9 3V .33 .57 201.3 546 1. 12 180 177 210 -33 4T .29 .60 191 546 0.903 211 219 170 AVG. 198 The adjusted RTNDT was calculated by averaging the chemistry factors (CFs) of the capsule chemistries, dividing the average by each individual capsule chemistry data, and multiplying this ratio by the measured delta. The predicted delta was calculated by multiplying the CF determined from best fit of measured data and fluence factors, by the fluence factor.

All previously submitted reactor vessel integrity evaluations remain conservative. Revisions to existing submittals are not needed at this time.

NRC Question 3 If the limiting material for your plant changes or if the adjusted reference temperature for the limiting material increases as a result of the above evaluations, provide the revised RTpt, value for the limiting material in accordance with 10CFR50.61. In addition, if the adjusted RtNDT value increased, provide a schedule for revising the PT and LTOP limits.

FPL Response As a result of these evaluations, the best estimate chemistry data for reactor vessel weld wire number 71249 has changed. The new copper and nickel values for the Turkey Point Units 3 and 4 RPVs are 0.23% and 0.59%, respectively. This determination was made using the mean of the means for all sources. All 94 known

A to 4-'98-3,55 Page 7 copper values and all but 6 of the 80 nickel sources were used.

The following comparison best demonstrates the effects of this reduction in chemistry data:

TABLE 4 Comparison of Effects of Existing and New Chemistry Data Application RTws at EOL 1/4 T Rt~ at 3/4 T RT~ at

( F) 19 EFPY ('F) 19 EFPY ('F)

Last Submittal Value* 295 252.5 200.4 Using New Best Estimate 279 244.5 199.9 Chemistry**

The last P/T curve submittal was made per FPL letter L 424, dated September 21, 1988. The last 10CFR50.61(PTS) submittals were made per FPL letters L-95-245, dated December 18, 1995, and L-96-117, dated May 3, 1996.

As defined in Section 1 of this response (0.23% Cu, 0.59%

Ni) .

The adjusted reference temperature has decreased since the copper and nickel values have been reduced. Therefore, the current PTS and P/T curves are still conservative.

The current P/T curves will expire at 19 EFPY. FPL will be submitting new P/T curves for Turkey Point Units 3 and 4 prior to 19 EFPY. The Units are currently at approximately 16.75 EFPY.

Attachment 2 to L-98-155 TABLE AP FROM BAW-2325 Flux Wold Metal Analysis Source Cu Nl Weld ID Lot Source Reference wt% wt% Notes SA-1094 8457 Weld Qualification Barberton WQ 0.23 0.55 Source Mean 0.23 0.55 SA-1094 8457 TPA Surv. Weld RVSP Baseline Chemist 0.30 0.60 TPP Suiv. Weld CVN S edmen 0.27 TP-4 Suiv. Weld CVN S ecimen 0.29 TPP Surv. Weld CVN S ecimen 0.30 Source Mean 0.29 0.60 SA-1101 8445 Weld Qualification Barberton WQ 0.21 0.57 Source Mean 0.21 0.57 SA-1101 8445 ONS-1 Nozzle Dro out S edmen No. I 0.23 0.52 ONS-1 Nozzle Dro out S ecimen No. H 0.20 0.54 ONS-1 Nozzle Dro out S ecimen No. G 0.20 0.54 ONS-1 Nozzle Dro out S ecimen No. F 0.17 0.54 ONS-1 Nozzle Dro out S edmen No. E 0.15 0.55 ONS-1 Nozzle Dro out S ecimen No. D 0.19 0.54 ONS-1 Nozzle Dro out S ecimen No. C 0.18 0.55 ONS-1 Nozzle Dro out S ecimen No. B 0.15 0.54 ONS-1 Nozzle Dro out S ecimen No. A 0.16 0.55 ONS-1 Nozzle Dropout Round Robin Sample Mt. Vernon 0.19 0.63 Anal sis: Lab No. 28772 ONS-1 Nozzle Dropout Round Robin Sample Mt. Vernon 0.19 0.61 Anal sis ONS-1 Nozzle Dropout Round Robin Sample Mt. Vernon 0.17 0.62 Anal sis: Lab No. 28773 ONS-1 Nozzle Dropout Round Robin Sample Mt. Vernon 0.18 0.62 Anal sis ONS-1 Nozzle Dropout Round Robin Sample Barberton 0.16 0.60 Anal sis ONS-1 Nozzle Dropout Round Robin Sample Barberton 0.16 0.61 Anal sis ONS-1 Nozzle Dropout Round Robin Sample LRC 0.18 0.62 Anal sls ONS-1 Nozzle Dropout Round Robin Sample LRC 0.29 0.67 Anal sls ONS-1 Nozzle Dropout Round Robin Sample LRC 0.18 0.54 Anal sis ONS-1 Nozzle Dropout Round Robin Sample LRC 0.19 0.53 Anal sls ONS-1 Nozzle Dropout Round Robin Sample LRC 0.18 0.54 Anal sis ONS-1 Nozzle Dropout Round Robin Sample LRC 0.23 0.64 Anal sis ONS-1 Nozzle Dropout Round Robin Sample LRC 0.23 0.65 Anal sls ONS-1 Nozzle Dropout Round Robin Sample J8L Steel 0.17 0.62 Com an Anal is ONS-1 Nozzle Dropout Round Robin Sample ORNL 0.18 0.61 Anal sis ONS-1 Nozzle Dropout Round Robin Sample Y-12 0.18 0.65 Anal sis ONS-1 Nozzle Dropout Round Robin Sample Y-12 0.13 0.63 Anal sis ONS-1 Nozzle Dropout Round Robin Sample NBS 0.17 0.62 Anal sls-62W ONS-1 Nozzle Dropout Round Robin Sample NBS 0.17 0.61 Anal sis-62W ONS-1 Nozzle Dropout Round Robin Sample NBS 0.17 0.62 Anal sis-62W

Flux Weld Metal Analysis Source Cu Ni Weld fD Lot Source Reference wt% Wt% Notes SA-1101 8445 ONS-1 Nozzle Dropout Round Robin Sample NBS 0.18 0.62 Anal is - 62W ONS-1 Nozzle Dro out HSST S ecimen ID: 62W-309 0.17 0.52 ONS-1 Nozzle Dro ut HSST S ecimen ID: 62W-359 0.17 0.48 ONS-1 Nozzle Dro out HSST S ecimen ID: 62W-202 0.18 0.57 ONS-1 Nozzle Dro out HSST S ecimen ID: 62W-223 0.18 0.58 ONS-1 Nozzle Dro out HSST S ecimen ID: 62W-223 0.15 0.62 ONS-1 Nozzle Dro out HSST S ecimen ID: 62W-276 0.19 0.59 ONS-1 Nozzle Dropout HSST Specimen ID: 62W-276 0.32 1.03 Ni content higher than expected range and analyses on same production weld; Ni content not used in source mean calculation Source Mean 0.19 0.59 SA-1101 8445 TP-3 Suiv. Weld RVSP Baseline Chemist 0.31 0.57 TP-3 Surv. Weld Retest RVSP Baseline Chemist 0.33 TP-3 Surv. Weld Retest RVSP Baseline Chemist 0.32 TP-3 Surv. Weld CVN S ecimenlD: W-17 0.35 TP-3 Surv. Weld CVN S ecimen ID: W-19 0.34 TP-3 Surv. Weld CVN S ecimen ID: W-20 0.32 Source Mean 0.33 0.57 SA-1229 8492 Weld Qualification Barberton WQ 0.20 0.57 Source Mean 0.20 0.57 SA-1344 8504 Weld Qualification Barberton WQ 0.21 0.62 Source Mean 0.21 0.62 SA-1706 8669 Weld Qualification Barberton WQ Lab No. E-70325 0.21 0.55 Source Mean 0.21 0.55 SA-1769 8738 Weld Qualification Barberton WQ Lab No. E-76488 0.19 0.66 Source Mean 0.19 SA-1769 8738 W Surv. Weld Mt Vernon Lab No. 29652 0.29 0.63 W Surv. Weld Mt Vernon Lab No. 29651 0.31 0.63 W Surv. Weld Mt Vernon Lab No. 29650 0.31 0.63 W Surv. Weld Mt Vernon Lab No. 29649 0.27 0.63 W Surv. Weld Mt Vernon Lab No. 29648 0.28 0.63 W Surv. Weld Mt Vernon Lab No. 29647 0.28 0.62 W Surv. Weld Mt Vernon Lab No. 29646 0.31 0.62 W Surv. Weld Mt Vernon Lab No. 29645 0.29 0.62 W Surv. Weld Mt Vernon Lab No. 29644 0.28 0.62 W Surv. Weld Mt Vernon Lab No. 29643 0.34 0.63 W Surv. Weld Mt Vernon Lab No. 29642 0.30 0.63 W Suiv. Weld Mt Vernon Lab No. 29641 0.29 0.63 W Surv. Weld Mt Vernon Lab No. 29640 0.27 0.62 W Surv. Weld Mt Vernon Lab No. 29639 0.28 0.62 W Suiv. Weld Mt Vernon Lab No. 29638 0.28 0.62 W Surv. Weld Mt Vernon Lab No. 29637 0.24 0.62 W Suiv. Weld Mt Vernon Lab No. 29636 0.26 0.62 W Surv. Weld Mt Vernon Lab No. 29635 0.27 0.63 W Surv. Weld Mt Vernon Lab No. 29634 0.28 0.63 W Suiv. Weld Mt Vernon Lab No. 29633 0.28 0.64 W Surv. Weld Mt Vernon Lab No. 29632 0.31 0.64 W Sunr. Weld Mt Vernon Lab No. 29631 0.28 0.64 W Surv. Weld Mt Vernon Lab No. 29630 0.28 0.64 W Surv. Weld Mt Vernon Lab No. 29629 0.27 0.64 W Surv. Weld Mt Vernon Lab No. 29628 0.27 0.64 W Surv. Weld Mt Vernon Lab No. 29627 0.31 0.64

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Flux Weld Metal Analysis Source Cu Nl Weld ID Lot Source Reference wt% Wt% Notes SA-1769 8738 W Surv. Weld Weld HSST<1W Westinghouse 0.31 0.63 Anal sis W Surv. Weld Weld HSST<1W Westinghouse 0.28 0.62 Anal sls W Surv. Weld Weld HSST-61 W Westinghouse 0.26 0.62 Anal sis W Surv. Weld Weld HSST-61W Westinghouse 0.28 0.64 Anal sis W Surv. Weld Weld HSST-61W Westinghouse 0.27 0.64 Anal sls W Surv. Weld HSST Specimen ID: 61W-232 0.39 0.47 Ni content lower than expected range and analyses on same production weld; Nl content not used In source mean calculation W Surv. Weld HSST S ecimen ID: 61W-276 0.24 0.59 W Surv. Weld HSST Specimen ID: 61 W-246 0.21 0.45 Ni content lower than expected range and analyses on same production weld; Ni content not used in source mean calculation W Surv. Weld HSST Specimen ID: 61W-225 0.35 0.44 Ni content lower than expected range and analyses on same production weld; Ni content not used in source mean calculation W Surv. Weld HSST S ecimen ID: 61W-222 0.24 0.52 W Surv. Weld HSST S ecimen ID: 61W-270 0.24 0.54 W Surv. Weld HSST S ecimen ID: 61W-270 0.28 0.62 W Surv. Weld HSST S ecimen ID: 61W-270 0.26 0.59 W Surv. Weld HSST Specimen ID: 61 W-270 0.36 0.97 Nl content higher than expected range and analyses on same production weld; Ni content not used In source mean calculation W Surv. Weld HSST Specimen ID: 61W-234 0.19 0.43 Ni content tower than expected range and analyses on same production weld; Ni content not used in source mean calculation Source Mean 0.28 0.62

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