ML17326A028
| ML17326A028 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 06/28/1999 |
| From: | Rencheck M INDIANA MICHIGAN POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| C0699-01, C699-1, GL-92-01, GL-92-1, TAC-MA0539, TAC-MA539, NUDOCS 9907070181 | |
| Download: ML17326A028 (78) | |
Text
REGULA Y INFORMATION DISTRIBUTIO SYSTEM (RIDS)
ACCESSION NBR:9907070181 DOC.DATE: 99/06/28 NOTARIZED: YES FACIL:50-315.Donald C. Cook Nuclear Power Plant, Unit 1, Indiana M DOCKET 05000315 I
AUTH. NAME AUTHOR AFFILIATION RENCHECK,M.W. Indiana Michigan Power Co.
RECIP.NAME RECIPIENT AFFILIATION Records Management Branch (Document Control Desk)
SUBJECT:
Provides response to 981116 & 960228 RAIs re GL 92-01.
Revised pressurized thermal shock evaluation based on new weld chemistry info &. copy of W rept WCAP-15074, "Evaluation of 1P3571 Weld Metal from Surveillance Programss...," encl.
DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE:
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0 indiana Michigan Power Company
~
500 Circle Drive Buchanan, Ml 49107 1373 INNING NICHISAN POWER June 28, 1999 C0699-01 Docket No.: 50-315 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop 0-Pl-17 Washington, D.C. 20555-0001 Donald C. Cook Nuclear Plant, Unit 1 REQUEST FOR ADDITIONAL INFORMATION REACTOR PRESSURE VESSEL INTEGRITY (TAC NO. HA0539)
References:
(1) Letter, John F. Stang, Jr. to Robert P. Powers, "REQUEST FOR ADDITIONAL INFORMATION (RAI)
REGARDING REACTOR PRESSURE VESSEL INTEGRITY AT DONALD C. COOK NUCLEAR PLANT, UNIT 1, TAC MA0539", dated November 16, 1998.
(2) Letter, John Hickman to E. E. Fitzpatrick, "REQUEST FOR ADDITIONAL INFORMATION (RAI) ON REACTOR PRESSURE VESSEL INTEGRITY ASSESSMENT FOR D.C. COOK UNIT 1 (TAC NO. M92664)", dated February 28, 1996.
Gentlemen:
In accordance with 10 CFR 50.54(f), Indiana Michigan Power Company (1&M) herein provides the response to the NRC's request for additional information (RAI) regarding Generic Letter 92-01 (References 1 and 2). The responses are contained in the attachments to this letter, and they are based on the new reactor vessel weld chemistry properties information reported in Combustion Engineering Owners Group Report (CE NPSD-1039, Revision 02).
Attachment 1 contains the responses to the RAI noted in reference
- 1. Attachment 2 is the revised pressurized thermal shock evaluation based on the new weld chemistry information as requested in RAI item number 2. Attachment 3 is a copy of Westinghouse report WCAP-15074, "Evaluation of the 1P3571 Weld Hetal from the Surveillance Programs for Kewaunee and Maine Yankee", dated September 1998.
Attachments 1 and 2 also respond to the request for additional information noted in reference 2.
9907070i8i990628 PDR ADOCKi>OS00031S PDR
U. S. Nuclear Regulatory Commission C0699"01 Page 2 This submittal contains one commitment:
Revised heatup and cooldown operating limit curves and LTOP setpoints will be submitted for unit 1 by December 22, 2000.
Sincerely, M. W. Rencheck Vice President Nuclear Engineering Nrgv SWORN TO AND SUBSCRIBED BEFORE ME THIS Q8~ DAY OF 1999 NOTARY PUBLIC My Commission Expires: JAN WATSON NOTARY PUBUC, BERRIEN COUNlY, Ml MYCOhMSSION EXPIRES FEB. 10, 2003
.'ttachments
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J. E. Dyer, w/attachments MDEQ DW & RPD NRC Resident Inspector, w/attachments R. Whale
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Attachment 1 to C0699-01 RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION REGARDING REACTOR PRESSURE VESSEL STRUCTURAL INTEGRITY AT COOK NUCLEAR PLANT UNIT 1 O707Pi3 to C0699-01 Page 1
~Back round In May 1995, the NRC issued Generic Letter (GL) 92-01, Revision 1, Supplement 1, "Reactor Vessel Structural Integrity." This GL requested that a review of reactor pressure vessel (RPV) structural integrity assessments be performed in order to identify, collect, and report any new'ata pertinent to the analysis of the structural integrity of the RPV and to assess the impact of those data on RPV integrity analyses for Cook Nuclear Plant Unit 1. An interim response to this generic letter was submitted for Unit 1 on November 20, 1995 [1].
Since then, new information on reactor vessel materials has become available as a result of the Combustion Engineering Owners Group (GEOG) efforts to evaluate reactor vessel weld properties.
On November 16, 1998, a request for additional information (RAI)
[7] was issued to Indiana Michigan Power Company (1&M) requesting that a reevaluation of the RPV weld chemistry be performed in light of the information presented in the GEOG report [3]. The RAI also requests an evaluation on the use of surveillance data for determining embrittlement in vessel beltline materials. This response addresses the items in the latest NRC RAI and evaluates the effect on pressure-temperature (PT) limits for Cook Nuclear Plant Unit 1.
Re uest for Additional Information Item 1 "Based on this information, and in accordance with the provisions of Generic Letter 92-01, Revision 1, Supplement 1, the NRC requests the following:
- 1. An evaluation of the information in the reference above (e.g.
CE NPSD-1039, Revision 2) and an assessment of its applicability to the determination of the best-estimate chemistry for all of your RPV beltline welds. Based upon 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 for the copper and nickel values chosen for each weld wire heat noting what heat-specific data were included and excluded from the analysis and the analysis method chosen for determining the best-estimate. If the limiting material for your vessel's PTS/PT limits evaluation is not a weld, include the information requested in Table 1 for the limiting material also. Furthermore, you should consider the information provided in Section 2.0 of the RAI on the use of surveillance data when responding."
Furthermore, in the determination of best-estimate chemistry, the NRC requests that the response "should also consider what method should be used for grouping sets of chemistry data (in particular, those from weld qualification tests)'s being from 'one weld'r from multiple welds. This is an important consideration when a mean-of-the-means or coil-weighted average approach is determined to be the appropriate method for determining the best-estimate chemistry. If a weld (or to C0699-01 Page 2 welds) were fabricated as weld qualification specimens by the.
same manufacturer, within a short time span, using similar welding input parameters, and using the same coil (or coils in the case of tandem arc welds) of weld consumables, be appropriate to consider all chemistry samples from that it may weld (or welds) as samples from 'one weld'or the purposes of best-estimate chemistry determination. If information is not available to confirm the aforementioned details, but sufficient evidence exists to reasonably assume the details are the same, the best-estimate chemistry should be evaluated both by assuming the data came from 'one weld'nd by assuming that the data came from an appropriate number of
'multiple welds'. A justification should then be provided for which assumption was chosen when the best-estimate chemistry was determined."
Res onse to Item 1 The Cook Nuclear Plant Unit 1 reactor pressure vessel was fabricated by Combustion Engineering. The submerged arc weld heats in the reactor vessel beltline include heat numbers 13253/12008 and 1P3571. The limiting material for the Cook Nuclear Plant Unit 1 PT limits is currently identified as intermediate plate B4406-3 (heat number C3506) [2], with a projected 1/4t adjusted reference temperature (ART) value of 171 F at 32 effective full power years (EFPY). This reevaluation considers new information for the vessel beltline welds. The revised ART values for these beltline materials are given in Table 1.
The weld material property data were gathered from the CEOG report submitted to the NRC [3] including the recent update performed'y ABB-CE in June 1998[4]. ATI Consulting performed an additional review of the validity of the chemistry data to assure the accuracy and completeness of the CEOG evaluation. The search focused on the vessel beltline welds for Cook Nuclear Plant Unit 1.
The tandem weld wire 13253/12008, which is in the lower shell axial weld of the Unit 1 vessel, also exists in Fermi 2, Fitzpatrick, Maine Yankee, and Fort Calhoun vessels. For this tandem weld heat, there are 49 valid chemistry measurements in the CEOG database as shown in Table 4. The revised best-estimate chemistry is 0. 21 wt% Cu and . 873 wt% Ni based on a simple mean.
The corresponding chemistry factor (CF) is 208.7'F as determined from the tables in Regulatory Guide 1.99, Revision 2. The current licensing basis best-estimate chemistry for this weld heat is 0.28 wt% Cu and 0.74 wt% Ni, with a CF of 208.7'F. Note:
A CF of 184.7'F was used for the same axial welds in the prior PT limits evaluation of the Unit 1 vessel [2] based on plant-specific weld surveillance data.
Weld wire heat number 1P3571 exists in the circumferential weld of the Unit 1 reactor vessel, which is part of the beltline material for PT limits evaluation. This material exists in welds of the Kewaunee, Maine Yankee, and LaSalle reactor vessels. This to C0699-01 Page 3 heat also exists in the surveillance capsule at Kewaunee, Maine Yankee, LaSalle 1, and Hatch 1. The data from the CEOG report and the coil-weighted average best-estimate chemistries for weld heat 1P3571 are given in Table 5. The revised best-estimate chemistries aie determined to be: coil-weighted average Cu
- 0. 283 wt%, and simple mean Ni 0. 755 wt%, with a CF value of 212.2'F. By comparison, the current licensing basis best-estimate chemistry for this weld heat is 0.28 wt% Cu and 0.74 wt%
Ni, with a CF of 208.7'F. Note: A CF of 184.7'F was used for the circumferential weld in the prior PT limits evaluation of the Unit 1 vessel [2] based on plant-specific weld surveillance data.
A further evaluation of the best estimate chemistry for weld heat number 1P3571 is shown in Table 6. The analysis in Table 6 is similar to the CEOG database results in Table 5 with a few exceptions: 1) one data point from a Linde 80 flux weld (group tag g) was determined to be invalid because it was made with a different flux type; 2) several data points from the Maine Yankee weld material were found to be multiple measurements of the same material and these data were averaged to obtain two independent values; and 3) it includes the chemistry values from the Hatch 1 surveillance weld. The Hatch 1 data were determined to be valid measurements based on fabrication records from ABB-CE. The Hatch 1 data (Table 5, group tag e) were not previously considered for the best-estimate weld chemistry [1]) since the pedigree of the material had not yet been established. With these three modifications, the revised best-estimate chemistries are determined to be: coil-weighted average Cu 0.287 wt%, and simple mean Ni 0.756 wt%, with a CF value of 214.0'F. These results are consistent with the evaluation of weld heat 1P3571 given in Reference 8 (Table 2-3).
Re uest for 'Additional Information Item 2 The CEOG report [2] includes updated chemistry estimates for heats of weld metal in CE fabricated vessels. This report not only provides a suggested best estimate value but also includes the source data used in estimating the chemical composition of the heat of material. This permits the determination of the best estimate chemical composition for the various sources of data including surveillance welds. Since the evaluation of surveillance data rely on both the best estimate chemical composition of the RPV weld and the surveillance weld, the information in these reports may result in the need to revise previous evaluations of RPV integrity (including LTOP setpoints and PT limits) per the requirements of 10 CFR 50.60, and Appendices G and H to 10 CFR Part 50.
"Based on this information and consistent with the provisions of Generic Letter 92-01, 'Revision 1, Supplement 1, the NRC requests the following:
- 2. that (1) the information listed in Table 2, Table 3, and the CF from the surveillance data be provided for each heat of material for which surveillance weld data are available and a revision in the RPV integrity analyses (i.e., current to C0699-01 Page 4 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.
Xf the limiting material for 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)."
Res onse to Item 2 The measured surveillance data from the available capsule analyses for weld heat number 1P3571 are provided in Table 2 [8].
Four irradiated capsules are available from Kewaunee, and four irradiated capsules are available from the Maine Yankee surveillance programs. The measured fluence, measured change in the reference temperature (ARTNDq, i.e., 30 ft-lb temperature shift), and irradiation temperatures are provided for each of these capsules. The chemistries for the surveillance weld materials are also provided in Table 2. Based on the information in this table, the best-fit CF can be determined and the credibility of the surveillance data can be evaluated. The surveillance data evaluation with adjustments for chemistry and temperature follows the methodology outlined in "Example Case 5 Surveillance Data not Available from Plant but Available from Other Sources" (6]. First, the data are normalized to the mean copper and nickel chemistry of the surveillance specimens, and then they are adjusted to the mean irradiation temperature using the equation:
Adl'bated ARTrat T~able Cr MeaSured ARTrar + (Tirra.,Tirrt,a,-)
Table CF<,>>q, Table 3 shows the x'esults of the Kewaunee and Maine Yankee surveillance data including adjustments. A best fit to the adjusted surveillance data fox weld heat number 1P3571 is determined to be 216.5'F. The predicted bRTs~ values are determined for the appropriate fluences for each capsule, and the Adjusted Predicted hRT>>T values are given in Table 3. The scatter in the data falls within the required 28'F (1-sigma) for weld data; therefore, the data is credible and, according to Reference 5, a smaller margin term (cia 14'F for welds) can be used. Further adjustments were made to the vessel CF value using the ratio procedure to account for chemistry differences between the capsule materials and the vessel as follows:
Ratio Adjusted CF"'16.5* CF>>z> v<<> ~e. 216.5
- 214e0 218.6'F CFTable,stirv, Cheba 211.9 (a) ratio adjusted CF calculated for weld 1P3571 in D. C. Cook 1 vessel from available surveillance data These credible surveillance weld results are included in the calculation of ART at the 1/4t location for weld heat number 1P3571 (as shown in Table 1).
to C0699-01 Page 5 Re uest for Additional Information Item 3
- 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 RTp>> value for the limiting material in accordance with 10 CFR 50.61. In addition, if the adjusted RT>p> value increased, provide a schedule for revising the PT and LTOP limits. The schedule should ensure that compliance with 10 CFR 50 Appendix G is maintained."
Res onse to Item 3 The evaluation provided here shows that with the revised best-estimate chemistry and use of available surveillance data for the Cook Nuclear Plant Unit 1 vessel beltline welds, the limiting material for PT limits becomes circumferential weld heat 1P3571, not beltline plate heat C3506. This change corresponds to an increase of 25.3'F in the calculated 1/4t ART value for limiting beltline material at 32 EFPX. Revised heatup and cooldown operating limit curves and LTOP setpoints will be submitted for Unit 1 by December 22, 2000. The current heatup/cooldown curves in the Unit 1 Technical Specifications are valid for approximately 3.92 EFPY from the day Unit 1 is restarted. shows the effect of revised RTp>> for the Unit 1 vessel. The effect of including the new weld data is an 11.2~F decrease in the RTp>> value for the limiting weld heat 1P3571 (from 238.6'F to 227.4'F). The revised RTp>> value of 227.4'F is well below the PTS screening criteria limit of 300'F for circumferential welds. The prior PTS assessment for the Unit 1 vessel (9] remains valid, and this new evaluation shows that the previous analysis is conservative. Thus, there is no impact of this additional weld data on the projected RTp>> for the Unit 1 vessel at end-of-life fluence (32 EFPY).
to C0699-01 Page 6 The following tables are included as a part of this attachment:
Table 1: information Requested on RPV Weld and/or Materials for P-T Limits Evaluations.
Table 2: Surveillance Data for Weld Heat No. 1P3571 Table 3 Adjustments to Surveillance Data for Weld Heat No.
1P3571.
Table 4: CEOG Chemistry Data for Weld Wire Heat No. 13253/12008.
Table 5: CEOG Chemistry Data for Weld Wire Heat No. 1P3571.
Table 6: Evaluation of Chemistry for Weld Wire Heat No. 1P3571.
to C0699-01 Page 7 References
- 1. Letter AEP:NRC:1173F, "Donald C. Cook Nuclear Plant Units 1 and 2, Response to NRC Generic Letter 92-01, Revision 1, Supplement 1, Reactor Vessel Structural Integrity," dated November 20, 1995.
- 2. "Analysis of Capsule U from the American Electric Power Company D. C. Cook Unit 1 Reactor Vessel Radiation Surveillance Program," WCAP-12483, January 1990.
- 3. "Best Estimate Copper and Nickel Values in CE Fabricated Reactor Vessel Welds," CE NPSD-1039, Revision 2, Final Report, Prepared for CE Owners Group, June 1997.
- 4. "Updated Analysis for Combustion Engineering Fabricated Reactor Vessel Welds, Best Estimate Copper and Nickel Content," CE NPSD-1119, Revision 1, Prepared for CE Owners Group, July 1998.
- 5. 10 CFR 50.61, "Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events," Federal Register, Volume 60, Number 243, December 19, 1995.
- 6. Memorandum from Keith R. Wichman to Edmund J. Sullivan, "Meeting Summary fox November 12, 1997 Meeting with Owners Group Representatives and NEI Regarding Review of Responses to Generic Letter 92-01, Revision 1, Supplement 1 Responses,"
dated November 19, 1997.
- 7. "Request for Additional Information Regarding Reactor Pressure Vessel Integrity at Donald C. Cook Nuclear Plant, Unit 1, TAC No. MA0539," dated November 16, 1998.
- 8. "Evaluation of the 1P3571 Weld Metal from the Surveillance Programs for Kewaunee and Maine Yankee," WCAP-15074, dated September 1998.
- 9. Letter AEP:NRC:0561D, "Donald C. Cook Nuclear Plant Units 1 and 2, Updated Reference Temperature, Pressurized Thermal Shock Analyses, " dated August 7, 1990.
Table 1. Information Requested on RPV Weld and/or Materials for P-T Limits Evaluation Facility: D. C. Cook I Vessel Manufacturer: Combustion Engineering Plate and Weld Thickness {w/o cladding): 8.5 inches.
32 EFPY Peak (ID) Fluence: 1.41xl0'/cm 32 EFPY Peak (I/4t) Fluence: 8.46x10'/cm 32 EFPY Axial Weld {ID)Fluence: 9.5x10'/cm 32 EFFY Axial Weld (I/4t) Fluence: 5.7x10'/cm RPV Best- I/4t Assigned Method of Initial Margin I/4t ART Mfeld %fire or Estimate Estimate Fluence Material Determining RT~ at 32 EFPY Number"'est-Plate Heat Copper Nickel (x 10' Chemistry CFt'> (RTNDT(U)) ('F)
Factor (CF) ('F) ('F) (F) ('F)
(wt%) (wt%) (n/cm ) ('F)
('F) 13253/12008 0.21 0.873 0.57 208.7 Tables -56 17 28 66 185.9 weld IP3571 0.287 0.756 0.846 218.d" Surv. Data -56 17 14 196.3 weld C3506 0.15'.49 0.846 119.6 Surv. Data 40 0 17 17 171.0 late (I) weld heat number or the material identification of the limiting material (2) determined from tables or from surveillance data (3) ratio adjusted CF value to account for chemistry differences between the capsule materials and the vessel Discussion of the Anal sis Method nd Data Used for E ch Weld tre Heat Weld Wire He Discussion 13253/12008 Simple mean Cu and Ni (see Table 4)
IP3571 Coil-weighted Cu, simple mean Ni (see Table 6)
Table 2: Surveillance Data for Weld Heat No. 1P3571 Plant Capsule ID Cu Ni Irradiation Fluence Measured Data Used in (including Temperature (x10'/cm ) MTNoz Assessing source) (i~a%) (wt%) ('F) ('F) Vessel (Y or N)
Kewaunee V .0.219 0.724 532 597 <'75 <'>
<'l Kewaunee 0.219 .
0.724 532 1.81 235 <'l Y Kewaunee P 0.219 0.724 . 532 274 '30 Y
'50<'>
Kewaunee S 0.219 0.724 532
<') <'l Maine Yankee W263 0.351 0.771 533 .567 222 Maine Yankee W253 0.351 0.771 542 1.25 <'60'>
Maine Yankee A25 0.351 0.771 522 1.76 " 270 <'>
Maine Yankee A35 0.351 0.771 533 7.13" 345 <'>,
Mean: 0.285 0.748 532.3 Table CFy; = 187.2'F, Table CF~. q~ =237.3'F, Table CF = 211.9'F
'rom Ref. 8, "Evaluation ofthe IP3571 Weld Metal from the Surveillance Programs for Kewaunee and Maine Yankee," WCAP-15074, September 1998.
Table 3: Adjustments to Surveillance Data for Weld Heat No. 1P3571 Plant Capsule ID Cu. Ni Irradiation Fluence Measured Adjusted Predicted (Adjusted-(including Temperature Factor t'~ hRTNor hRTNDp~ Predicted)
(at%) (wt%) ('F) ('F) source) ( F) (F) hRTNor
('F)
Kewaunee V 0.219 0.724 532 0.856 175 198.4 185.2 13.2 Kewaunee 0.219 0.724 532 1.163 235 266.3 251.7 14.6 Kewaunee P 0.219 0.724 532 1.269 230 260.7 274.7 -14.0 Kewaunee 0.219 0.724 532 1.317 250 283.3 285.1 -1.9 Maine Yankee W263 0.351 0.771 533 0.841 222 197.5 182.1 15.4 Maine Yankee W253 0.351 0.771 542 1.062 260 222.5 229.9 -7.5 Maine Yankee A25 0.351 0.771 522 1.155 270 251.4 250.1 1.3 Maine Yankee A35 0.351 .0.771 533 1.466 345 307A. 317.3 -9.9
'luence Factor (FF) = fluence'"~" "forfluence values shownin Table2
"'djusted = Table CFM~ ~ Measured dRTNDT + { TirrM - Tirrc,~,)
dRTNDT Table CFG,~e
'l Predicted ARTNDT=FF 'F where CF = Z(FF~BRTNDT)+Z(FF) = 2326.78 : 10.749 = 216.5'F
Table 4. CEOG Chemistry Data for Weld Wire Heat No. 13253/1200S Summary of Properties for Weld Wire Heat No. 13253/12008 Source; CEOG CE NPSD-1039 Revision 2 Heat No. Aux Type Hux Lot Pct. Cu Pct. Ni Data Source Reference Source LD. Group Tag 13253/12008 Linde 1092 3791 .22 .76 CEOG Database WDC4155 13253/12008 Linde 1092 3791 .22 .76 C.E. CEOG Database WDC4156 13253/12008 Linde 1092 3791 .22 .77 C.E. CEOG Database WDC4158 13253/12008 Linde 1092 3791 .22 .77 C.E. CEOG Database WDC4159 13253/12008 Linde 1092 3791 .22 .78 C.E. CEOG Database WDC4160 13253/12008 Linde 1092 3791 .22 .78 C.E. CEOG Database WDC4 161 13253/12008 Linde 1092 3791 .78 C.E. CEOG Database WDC4162 13253/12008 Linde 1092 3791 .22 .78 C.E. CEOG Database WDC4163 13253/12008 Linde 1092 3791 .20 .86 C.E. CEOG Database WDC4165 13253/12008 Linde 1092 3791 .20 .86 C.E. CEOG Database WDC4 166 13253/12008 Linde 1092 3791 .20 .87 CEOG Database WDC4167 CEOG Database 9/10/97
Table 4. CEOG Chemistry Data for Weld Wire Heat No. 13253/1200S Heat No. Flux Type Flux Lot Pct. Cu Pct. Ni Data Source Reference Source LD. Group Tag 13253/12008 Linde 1092 3791 .20 .87 C.E. CEOG Database WDC4168 13253/12008 Lindc 1092 3791 .22 .87 C.E. CEOG Database WDC4169 13253/12008 Linde 1092 3791 .20 .88 C.E. CEOG Database WDC4170 13253/12008 Linde 1092 3791 .21 .88 C.E. CEOG Database WDC4171 13253/12008 Linde 1092 3791 .21 .88 C.E. CEOG Database - WDC4172 b 13253/12008 Linde 1092 3791 .21 .88 C.E. CEOG Database WDC4173 13253/12008 Linde 1092 3791 .22 C.E. CEOG Database WDC4174 13253/12008 Linde 1092 3791 .22 .88 C.E. CEOG Database WDC4175 13253/12008 Linde 1092 3791 .22 .88 C.E. CEOG Database WDC4176 13253/12008 Linde 1092 3791 .20 C.E. CEOG Database WDC4177 13253/12008 Linde 1092 3791 .20 .89 C.E. CEOG Database WDC4178 13253/12008 Linde 1092 3791 .21 .89 C.E. CEOG Database WDC4179 13253/12008 Linde 1092 3791 .21 .89 C.E. CEOG Database WDC4180 13253/1200$ Lindc 1092 3791 .89 C.E. CEOG Database WDC4181 13253/1200S Linde 1092 3791 .21 .89 CEOG Database WDC4182 13253/12008 Linde 1092 3791 .21 .89 CEOG Database WDC4183 CEOG Database 9/10/97
Table 4. CEOG Chemistry Data for Weld Wire Heat No. 13253/12008 Heat No. Flur Type Flur Lot Pct. Cu Pct. Ni Data Source Reference Source LD. Group Tag 13253/12008 Linde 1092 3791 .21 .89 C.E CEOG Database %DC4184 13253/12008 Linde 1092 3791 .22 .89 CEOG Database %DC4185 13253/1200& Linde 1092 3791 .22 .89 C.E. CEOG Database WDC4186 13253/12008 Linde 1092 3791 .20 .90 C.E. CEOG Database WDC41&7 13253/12008 Linde 1092 3791 .20 .90 C.E. CEOG Database WDC4 188 13253/12008 Linde 1092 3791 .20 .90 C.E. CEOG Database WDC4189 13253/12008 Linde 1092 3791 .20 .90 C.E. CEOG Database WDC4190 13253/12008 Linde 1092 3791 .21 .90 CEOG Database WDC4191 13253/12008 Linde 1092 3791 .21 .90 CEOG Database WDC4192 13253/12008 Linde 1092 3791 .21 .90 CEOG Database WDC4193 13253/)2008 Linde 1092 3791 .90 C.E. CEOG Database WDC4194 13253/12008 Linde 1092 3791 .22 .90 C.E. CEOG Database WDC4195 13253/12008 Lindc 1092 3791 .20 .91 C.E CEOG Database WDC4196 13253/12008 Linde 1092 3791 .20 .91 C.E. CEOG Database WDC4197 13253/12008 Linde 1092 3791 .20 .91 C.E. CEOG Database %DC4198 CEOG Database 9/10/97
0 Table 4. CEOG Chemistry Data for Weld Wire Heat No. 13253/1200S Heat No. Flux Type Flux Lot Pct. Cu 'ct. Ni Data Source Reference Source LD. Group Tag 13253/12008 l,inde 1092. 3791 .20 .91 C.E. CEOG Database WDC4199 13253/12008 Linde 1092 3791
.20 .91 C.E. CEOG Database WDC4200
'I 13253/12008 Linde 1092 3791 .91 C.E. CEOG Database WDC4201 13253/1200S Linde 1092 3791 .20 .92 C.E. CEOG Database WDC4202 13253/12008 Linde 1092 3791 .20 C.E. CEOG Database WDC4203 13253/1200 S Linde 1092 3791 .21 '.92 C.E. CEOG Database WDC4204-13253/12008 Linde 1092 3791; 3S33 .24 .875 C.E. 'CEOG Database WDC4205 Best Estimate Cu = 0.21 wt% Best Estimate Ni = 0.873 wt% Basis: Simple mean Cu and Ni Note: Using bestmtimate chemistry, CF = 208.7 'F from Reg. Guide 1.99, Rev. 2 Tables CEOG Database 9/10/97
Table 5. CEOG Chemistry Data for Weld Wire Heat No. IP3571 Summary of Properties for%eld%ire Heat No. IP3571 Source: CEOG CE NPSIh1039 Revision 2 Heat NL Flur Type Flur Lot Pct. Cu Pct. Ni Data Source Reference Source LD. Group Tag IP3571 Linde 1092 3958 .17 .51 KWE, Supp. "V'PS, 8/21/95 WDC4426 b IP3571 Linde 1092 3958 .15 KWE, Supp. "P" WPS, 8/21/95 WDCM27 b IP3571 Lindc 1092 3958 .17 .61 KWE, Supp. "V'PS, 8/21/95 WDCW428 b IP3571 Linde 1092 3958 .17 .64 KWE, Supp. "R" WPS, 8/21/95 WDC<429 b IP3571 Linage 1092 3958 .18 .67 KWE, Supp. "R" WPS, 8/21/95 WDCW430 b IP3571 Linde 1092 3958 .19 .67 KWE, Supp. "V'PS, 8/21/95 %DC%431 b IP3571 Linde 1092 3958 .19 .67 KWE, Supp. "P" WPS, 8/21/95 %DC%432 b IP3571 Linde 1092 3958 .186 .689 KWE, Supp. "S" WPS, 8/21/95 %DC<433 b IP3571 - Linde 1092 3958 .20 .70 KWE, Supp. "V'PS, 8/2)/95 WDCM34 b IP3571 Linde 1092 3958 .19 .71 KWE, Supp. WPS, 8/21/95 WDC4435 b 172'717 V'WE, IP3571 Linde 1092 3958 . SC "P" WCAP-13257 WDC4436 b IP3571 Linde 1092 3958 .34 .72 KWE, Supp. "R" %CAP<<13257 WDC4437 b IP3571 Linde 1092 3958 .22 .73 KWE, Surv. Test '%PS, 8/21/95 %DC~38 b CEOG Database 9/10/97 Note: WQ = Weld Qualification, SC = Surveillance Capsule, Supp. = Supplemental Test, Surv. = Surveillance Weld
Table S. CEOG Chemistry Data for Weld Wire Heat No. 1P3S71 Heat No. Flux Type Flllx Lof Pct. Cu Pct. NI Data Source Reference Source LD. Group Tag IP3571 Linde 1092 395& .191 .734 KWE, SC "P" WCAP-13257 WDC4439 b IP3571 Linde 1092 3958 .066 .736 KWE, SC "R" WCAP-13257 WDC4440 b IP3571. Linde 1092 3958 .24 .74 KWE, Surv. Test WPS, 8/21/95 WDC4441 b IP3571 Linde 1092 3958 .182 .742 KWE, SC "P" WCAP-13257 WDC4442 b IP3571 Linde 1092 3958 .354 .742 KWE SC "P" WCAP-13257 WDC4443 b IP3571 Linde 1092 3958 .207 .769 KWE, SC "R" WCAP-13257 WDC4444 b IP3571 Linde 1092 3958 .20 .77 KWE, SC Unirr. WCAP<107 WDC4445 b IP3571 Linde 1092 3958 .43 .78 KWE, Surv. Test WPS, 8/21/95 WDC4446 b IP3571 Linde 1092 3958 .23 .79 KWE, Surv. Test WPS, 8/21/95 WDC4447 b IP3571 Linde 1092 3958 .209 .795 KWE, Supp. "S" WPS, 8/21/95 WDC4448 b IP3571 Linde 1092 3958 .22 .80 KWE, Surv. Test WPS, 8/21/95 WDC4449 b IP3571 Linde 1092 3958 .434 .80 KWE, SC "V'CAP-13257 WDC4450 b IP3571 Linde 1092 3958 .196 .803 KWE, Supp. "S" WPS, 8/21/95 WDC4451 b IP3571 Linde 1092 3958 .214 .816 KWE, SC "V'CAP-13257 WDC4452 b CEOG Database 9/10/97 Note: WQ = Weld Qualification, SC = Surveillance Capsule, Supp. = Supplemental Test, Surv. = Surveillance Weld
0 Table 5. CEOG Chemistry Data for Weld %ire Heat No. 1P3571 Heat No. Flux Tpye Flux Lot Pct. Cu Pct. Ni Data Source Reference Source LD. Group Tag IP3571 Linde 1092 395& - .223 .871 KWE, Supp. "S" WCAP-13257 WDC4453 IP3571 Linde 1092 3958 .25 .66 MY, SC 263 deg. BCL-585-21 WDC4454 IP3571 Linde 1092 395& .25 .70 MY, SC263 deg. BCL-585-21 WDC4455 IP3571 Linde 1092 3958 .33 .70 MY,SC263deg. BCL-585-21 WDC4456 IP3571 Linde 1092 3958 .33 .71 MY, SC 263 deg. BCL-585-21 WDC4457 C IP3571 Linde 1092 395& .356 .728 MY, SC 253 deg. WCAP-12&19 WDC%458 IP3571 Linde 1092 3958 .432 .745 MY,SC253deg. WCAP-12819 WDC4460 IP3571 Linde 1092 395S .365 .78 MY, SC Unirr. CR-75-269 WDC%463 IP3571 Lindc 1092 3958 .34 .73 MY, Supp. COW)1 WPS, 8/21/95 WDC4468 IP3571 Linde 1092 3958 .30 .76 MY, Supp. C04-11 WPS, 8/21/95 WDC4469 IP3571 Linde 1092 3958 .35 .76 MY, Supp. COW)2 WPS, 8/21/95 WDC4470 IP3571 Linde 1092 3958 .33 .77 MY, Supp. C04-05 WPS, 8/21/95 WDC%471 IP3571 Linde 1092 3958 .31 .78 MY, Supp. C0447 WPS, S/21/95 WDC4472 IP3571 Linde 1092 3958 .32 .78 MY, Supp. C0448 WPS; 8/21/95 WDC4473 CEOG Database 9/10/97 Note: WQ = Weld Qualification, SC = Surveillance Capsule, Supp. = Supplemental Test, Surv. = Surveillance Weld
Table 5. CBOG Chemistg Data for Weld Wire Heat No. 1P3571 Heat No. Flux Type Flux Lot Pct. Cu Pct. Ni Data Source Reference Source LD. Group Tag IP3571 Linde 1092 3958 .32 .78 MY, Supp. C0449 WPS, 8/21/95 %DC%474 c IP3571 Linde 1092 3958 .32 .78 MY, Supp. C04-10 WPS, &/21/95 WDC4475 c IP3571 Linde 1092 3958 .33 .78 MY, Supp. C04M WPS, 8/21/95 . WDC-0476 c IP357l Lindc 1092 3958 .37 .80 MY, Supp. C0441 WPS, 8/21/95 WDC4477 c IP3571 Linde 1092 3958 .38 .80 MY, Supp. C04-13 %PS, 8/21/95 %DC4478 c IP3571 Linde 1092 3958 .52 .80 MY, Supp. C04-15 %PS, 8/21/95 WDC4479 c IP3571 Linde 1092 3958 .53 .81 MY, Supp. C0449 WPS, 8/21/95 WDCA480 c IP3571 Linde 1092 3958 .21 .88 C.E. CEOG Database WDC-04S I c IP3571 Linde 1092 3958 .20 .73 LSI, SC 44U GE-NE-A166-1294-Rl WDC4483 d IP3571 Linde.1092 3958 .22 .73 LSI, SC 44M GE-NE-AI66-.1294-RI %DC@484 d IP3571 Linde 1092 3958 .20 .74 LSI, SC 44LD .GE-NE-A166-1294-Rl WDC4485 d IP3571 Linde 1092 3958 .20 .75 LS I, SC 443 GE-NE-A 166-1294-Rl WDC-0486 d IP3571 Linde 1092 3958 .75 LSI, SC 444 GE-NE-A166-1294-Rl WDC4487 d IP3571 Linde 1092 3958 .20 LSI, SC 44A GE-NE-A166-1294-Rl WDC4488 d CEOG Database 9/10/97 Note: WQ = Weld Qualification, SC = Surveillance Capsule, Supp. = Supplemental Test, Surv. = Survei)lance Weld
Table 5. CEOG Chemistry Data for Weld Wire Heat No. 1P3571 Heat No. Flux Type Flux Lot Pct. Cu Pct. Ni DataSource Reference Source LD. Group Tag
. IP3571 Linde 1092 395& .22 .79 LS I, SC 447 GE-NE-A166-1294-Rl WDC-0490 1P3571 Linde 1092 3958 .21 .80 LSI, SC 45K GE-NE-A 166-1294-Rl WDC4491 IP3571 Linde 1092 3958 .21 .80 LS I, SC 45M GE-NE-A166-1294-Rl WDC-0492 IP3571 Linde 1092 3958 .22 .80 LSI, SC 45D GE-NE-A166-1294-Rl WDC-0493 IP3571 Linde 1092 3958 .23 .82 LSI, SC 45E GE-NE-A166-1294-Rl WDC4494 d IP3571 Linde 1092 3958 .22 .83 LS I, SC 44F GE-NE-A166-1294-Rl WDC4495 IP3571 Linde 1092 3958 .21 .78 LS I, SC Unirr. WPS, 8/21/95 WDC-0496 IP3571 Linde 1092 3958 .76 HAI, SC NEDC-30997 WDC4497 IP3571 Linde 1092 3958 .28 .76 HAI, SC NEDC-30997 WDC4498 1
IP3571 Linde 1092 3958 .28 .76 HAI, SC i NEDC-30997 WDCM99 IP3571 Linde 1092 3958 0.32 0.82 HAI, SC . NE-B1100691%1 WDC-1879 IP3571 Linde 1092 3958 0.32 0.87 HAI, SC NE-B1100691-01 WDC-18&0 IP3571 Linde 1092 3958 0.32 0.87 HAI, SC NE-B1100691%1 WDC-1881 CEOG Database 9/10/97 Note: WQ = Weld Qualification, SC = Surveillance Capsule, Supp. = Supplemental Test, Surv. = Surveillance Weld
Table 5. CEOG Chemistry Data for Weld Wire Heat No. 1P3571 Heat No. Flur Type Huz Lot Pct. Cu Pct. Ni Data Source Reference Source LD. Group Tag 1P3571 Linde 1092 3958 .37 .75 C.E., WQ M1.43 CEOG Database WDC4500 f 1P3571 Linde 1092 3958 .40 .82 C.E., WQ M1.42 CEOG Database WDC4425 IP3571 Linde 80 0344 .22 .67 Wire/Flux Qual. CEOG Database WDC4482 Best Estimate Cu = 0.283 wt% Best Estimate Ni = 0.755 wt% Basis: Coil weighted Cu, weighted Ni Note: Using best-estimate chemistry, CF = 212.2 'F from Reg. Guide 1.99, Rev. 2 Tables CEOG Database 9/10/97 Note: WQ = Weld Qualification, SC = Surveillance Capsule, Supp..= Supplemental Test, Surv. = Surveillance Weld
Table 6. Evaluation of Chemistry for Weld Wire Heat No. 1P3571 1P3571 Linde 1092 Type Flux New Evaluation CQ Ni Flux Lot Number 3958 Avg. Cu Avg. Ni ¹of wt% wt% CE PEDIGREE SOURCE LD. REPORT/ANALYSIS Group Tag wt% wt% Coib Kewaunee, Single Are 0.219 0.724 0.17 0.51 ~ INDETERMNATENi WDC4426
.0.15 0.54 INDETERMINATENi WDC4427 MSE-MNA-229(95) 0.17 0.61 VALID WDC4428 0.17 0.64 WDC4429 0.18 0.67 WDC4430 0.19 0.67 WDC4431 0.19 0.67 WDC4432 MSF MNA-229(95) 0.186 0.689 WDC4433 MSF MNA-229(95) 0.20 0.70 WDC4434 0.19 0.71 WDC4435 MS E-MNA-229(95) 0.172 0.717 VALID WDC4436 0.34 0.72 WDC4437 0.22 0.73 WDC4438.
0.191 0.734 WDC4439 WCAP-142&0 0.066 0.736 INDETERMNATECuf WDC4440 0.24 0.74 WDC4441 0.182 0.742 WDC-0442 0.354 0.742 WDC4443 0.207 0.769 WDC4444 0.2 0.77 WDC@445 0.43 0.78 VALID WDC4446 0.23 0.79 WDC4447 0.209 0.795 VALID WDC4448 MSE-MNA-229(95) 0.22 0.80 WDC4449 0.434 0.80 WDG0450 0.196 0.803 WDC4451 MSE-MNA-229(95) 0.21 0.816 VALID WDC4452 0.223 0.871 WDC4453 MS E-MNA-229(95)
Table 6. Evaluation of Chemistry for Weld Wire Heat No. 1P3571 1P3571 Linde 1092 Type Flux New Evaluation Cu Nl Flux Lot Number 3958 hvg. Cu hvg. Ni ¹of wt% wt% CE PEDIGREE SOURCE LD. REPORT/hNALYSIS Group Tag wt% wt% Coth Maine Yankee, Single hrc 0251 0.771 0.25~ 0.66~ WDC4454 BCI 5&5-21 0.250 0.700 WDC4455 BCL-585-21 0.33~~ 0.70~~ WDC4456 BCI 585-21 0.33~'.71~~ WDC@457 ~
BCL 585-21 0.356 0.728 WIXA458 WCAP-12819 0.432 0.745 WDC4460 WCAP-1 2819 0.365 0.78 WDC4463 D9693 0.34 0.73 WDC4468 D44441 0.3 0.76 WDC4469 D44449 0.35 0.76 VALID WDC4470 D44440 0.33 0.77 WDC4471 D44443 0.31 0.78 WDC4472 0.32 0.78 WDC4473 D44446 0.32 0.78 WDC4474 D44447 0.32 0.78 WDC4475 0.33 0.78 VALID 0.37 0.80 D44439 0.3& 0.80 WDC4478 D44451 0.52 0.80 WDC4479 D44453 0.53 0.81 D44452 0.21~~~ 0.88 WDC4481 measurements averaged to obtain single value for "best~mate" evaluation
" two two measurements averaged to obtain single value for "best~imate" evaluation
"'easurement taken at interface with manual stick weld material
Table 6. Evaluation of Chemistry forbid Wire Heat No. 1P3571 1P3571 Linde 1092 Type Fluz New Evaluation Cu Ni Hux Lot Number 3958 hvg. Cu hvg. Nl ¹or wt% wt% CE PEDIGREE SOURCE LD. 'EPORT/ANALYSIS Group Tag wt% wt% Colla LaSalle-1, Tandem Arc 0.212 0.775 0.20 0.73 WDC4483 0.22 0.73 WDC4484 0.20 0.74 WDC4485 0.20 0.75 WDC4486 0.22 0.75 WDC4487 0.20 0.76 VALID WDC4488 0.22 0.79 VALID WDC4490 0.21 0.80 VALID WDC4491 0.21 0.80 VALID WDC4492 0.22 0.80 WDC4493 0.23 0.82 - VAUD WDC4494 0.22 0.83 VALID WDC4495 0.21 0.78 WDC4496 D11 341 Hatch-l, Tandem Arc 0.304 0.807 0.76 WDC4497 NEDC-30997 0.28 0.76 VALID WDC4498 NEDC-30997 0.2& 0.76 WDC4499 NEDC-30997 0.32 0.82 INDETERMINATE WDC-1879- NE-B110069141 0.32 0.87 INDETERMNATE WDC-1880 NE-B110069141 0.32 0.87 WDC-18SI NE-BI 10069141
Table 6. Evaluation of Chemistry for Weld %ire Heat No. 1P3571 1P3571 Linde 1092 Type Fluz New Evaluation Cu Ni Huz Lot Number 3958 hvg. Cu hvg. Nl ff of wt% wt% CE PEDIGREE SOURCE LD. REPORTIANALYSIS Group Tag wt% wt% Coils Weld Qualification, Tandem Arc 0.370 0.750 0.37 0.75 D8698 Weld Qualification, Single Arc 0.400 0.820 0.40 0.82 WDC4425 D8669 Weld Qualification, Llnde 80 Huz Type 0.220 0.670 0.22 0.67 WDC4482 Dl9780 Note: Group Tag g data not used in anal@is Coll Weighted Avg. Simple Mean Cu Ni 0.287 wt% 0.756 wt%
Note: Using bestmtimate chemistry, CF = 214.0 'F from Reg. Guide 1.99, Rev. 2 Tables
Attachment 2 to C0699-01 FINAL RESPONSE TO NRC GENERIC LETTER 92-01, REVISION 1/
SUPPLEMENT 1 FOR PRESSURIZED THERMAL SHOCK to C0699-01 Page 1
~Back round The Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 92-01, Revision 1, Supplement 1, "Reactor Vessel Structural Integrity" on May 19, 1995. This supplement required that addressees identify, collect, and report any new data pertinent to analysis of the structural integrity of their reactor pressure vessels (RPVs) and assess the impact of this new data on their RPV integrity analysis. An interim response to this GL was submitted for Cook Nuclear Plant Unit 1 on November'0, 1995 [1].
Since then, the NRC reviewed this response and requested that Indiana Michigan Power Company (I&M) perform additional analyses to consider any new information on the vessel beltline welds, including the data from the Combustion Engineering Owners Group (CEOG) database, and, if necessary, to update the prior PTS evaluation for Unit 1 [2] using the coil-weighted method for best-estimate copper chemistry of weld heat 1P3571. This attachment documents the data for weld heats 1P3571, 13253, and 13253/12008, computes best-estimate chemistries for these welds in light of the new GEOG data, evaluates surveillance weld data for weld heat number 1P3571, and provides a revised pressurized thermal shock (PTS) assessment of the Unit 1 reactor pressure vessel.
Reevaluation of Unit 1 Vessel Welds for PTS The reactor vessel for Unit 1 was fabricated by Combustion Engineering. The weld material property data were gathered from the comprehensive GEOG database [3] including the recent update performed by ABB-CE [4]. ATI Consulting performed an additional review of the validity of the chemistry data to assure the accuracy and completeness of the CEOG evaluation. The database search focused on the vessel beltline and surveillance capsule welds for Unit 1. The welds of interest are heats 1P3571, 13253/12008, and 13253.
Weld wire heat number 1P3571 exists in the circumferential weld of the Unit 1 reactor vessel, which is part of the beltline material for PTS evaluation. This material also exists in welds of Kewaunee, Maine Yankee, and LaSalle reactor vessels. This heat also exists in the surveillance capsules at Kewaunee, Maine Yankee, LaSalle 1 and Hatch 1.
The valid chemistry data for 1P3571 from the CEOG report [3] are shown in Table 1. The assessment of all relevant data for heat 1P3571 shows the coil-weighted average of the 71 chemistry measurements to be 0.283 wt% Cu, and a simple mean value of 0.755 wt% Ni. The corresponding chemistry factor (CF) is 212.2'F as determined from the tables in Regulatory Guide 1.99, Revision 2.
An additional evaluation of weld heat number 1P3571 is shown in Table 2. The data are identical to the CEOG database results (shown in Table 1) with a few exceptions: 1) one data point from a Linde 80 flux weld was determined to be invalid because it was made with a different flux type; 2) several data points from the
to C0699-01 Page 2 Maine Yankee weld material were found to be multiple measurements of the same material and these data were averaged to obtain two independent values; and 3) the chemistry values from the Hatch 1 surveillance weld were included. The Hatch 1 data were determined to be valid measurements based on fabrication records from ABB-CE. The Hatch 1 data were not previously considered for the best-estimate weld chemistry evaluation [1] since the pedigree of the material had not yet been established. The coil-weighted averaging method for weld heat 1P3571 given in Table 2 is similar to the method in the GEOG database report [3], but includes the three modifications as noted above for 70 valid measurements. From this revised evaluation, best-estimate chemistries for this weld heat are determined to be: coil-weighted average Cu 0.287 wt%, and simple mean Ni 0.756 wt%,
with a CF value of 214.0'F. By comparison, the current licensing basis best-estimate chemistry for this weld heat is 0.28 wt% Cu and 0.74 wt% Ni, with a CF of 208.7'F.
The tandem weld wire 13253/12008, which is in the lower shell axial weld of the Unit 1 vessel, also exists in Fermi 2, Fitzpatrick, Maine Yankee, and Fort Calhoun vessels. For this tandem weld heat, there are 49 valid chemistry measurements in the CEOG database as shown in Table 3. The best-estimate chemistry is 0.21 wt% Cu and 0.873 wt% Ni based on a simple mean.
The corresponding CF is 208.7'F as determined from the tables in Regulatory Guide 1.99, Revision 2. The current licensing basis best-estimate chemistry for this weld heat is 0.28 wt% Cu and 0.74 wt% Ni, with a CF of 208.7'F. This is identical to the calculated CF for the axial welds in the prior PTS evaluation of the unit 1 vessel. [2]
Weld heat 13253 exists in the Unit 1 surveillance weld specimens and not in the vessel welds. Table 4 shows the eight available measured chemistry data points for weld heat 13253 from the CEOG database. These data do not have an effect on the welds in the Unit 1 vessel for PTS evaluations.
Evaluation and Use of Surveillance Data According to the NRC Request for Additional Information [5], all surveillance program results for the heats of material in the unit 1 vessel should be considered j.n evaluating its integrity regardless of source per 10 CFR 50.61. This includes the surveillance data for weld heat number 1P3571 which is contained in both the Kewaunee and Maine Yankee surveillance programs.
Whey assessing credibility of surveillance data that come from more than one source, adjustments to the surveillance data may be needed to account for'ifferences in the chemical composition and irradiation environment of the different sources consistent with the requirements in 10 CFR 50.61. A method for accounting for these differences is discussed in Reference 6.
The measured surveillance data from the available capsule analyses for weld heat number 1P3571 are provided in Table 5.
Four irradiated capsules are available from Kewaunee, and four to C0699-01 Page 3 irradiated capsules are available from the Maine Yankee surveillance programs. The measured fluence, measured DRTNpT (i.e., 30 ft-lb temperature shift), and irradiation temperatures are provided for each of these capsules. The chemistries for the surveillance weld materials are also provided in Table 5. Based on the information in this table, the best-fit CF can be determined and the credibility of the surveillance data can be evaluated. The surveillance data evaluation with adjustments for chemistry and temperature follows the methodology outlined in "Example Case 5 Surveillance Data not Available from Plant but Available from Other Sources" [6). First, the data are normalized to the mean copper and nickel chemistry of the surveillance specimens, and then they are adjusted to the mean irradiation temperature using the equation:
Adjusted ARTm ~Table Table Cr *measured ARTssr + (Tires-Tirre,rem,)
CFcapaule Table 6 shows the results of the Kewaunee and Maine Yankee surveillance data including adjustments. A best fit to the adjusted surveillance data for weld heat number 1P3571 is determined to be 216.5'F. The predicted hRT>> values are determined for the appropriate fluences for each capsule, and the Adjusted Predicted BRTNpT values are given in Table 6. The scatter in the data falls within the required 28'F (1-sigma) for weld data; therefore, the data is credible and, according to Reference 8, a smaller margin term (era 14'F for welds) can be used. Further adjustments were made to the vessel CF value using the ratio procedure to account for chemistry differences between the capsule materials and the vessel as follows:
Ratio Adjusted CF" 216.5* CFT,>> l ch,. 216.5
- 214.0 218.6'F Table,surv, cheat 211.9 la) ratio adjusted CF calculated for weld 1P3571 in the unit 1 vessel from available surveillance data These credible surveillance weld results are included in the calculation of RTpTs for weld heat number 1P3571 in the Unit 1 vessel beltline. (Note: no surveillance data exists for weld heat number 13253/12008). Table 7 provides calculations of the updated RTpTs values for these beltline welds at the vessel inside surface. Table 8 shows a comparison of the updated values for RTpTs with the results of the prior PTS analysis for Unit 1 [2].
~summer A reevaluation of the Unit 1 vessel beltline weld chemistry produced a slight change in the calculated best-estimate chemistries and CF value (from 208.7'F to 214.0'F) for weld heat number 1P3571. The available surveillance data for this weld heat were evaluated (including appropriate adjustments), a best-estimate CF of 216.5'F was calculated, and the scatter in the best fit to the data is determined to be within the required 28'F range for credible surveillance data. The surveillance data to C0699-01 Page 4 results for weld heat 1P3571 were used (with ratio adjustment) to determine a ratio adjusted CF value of 218.6'F, and a revised RTpgg value for the limiting vessel beltline weld was calculated to be 227.4'F. The effect of this updated CF is an 11.2'F decrease in the RT~zz value for the limiting weld heat 1P3571 (from 238.6'F to 227.4'F). This revised RT~~ value is well below the PTS screening criteria limit of 300'F for circumferential welds. The projected RT~, values for the other vessel welds and plates are unchanged from the previously submitted PTS evaluation
[2). The prior PTS assessment for the Unit 1 vessel [2j remains valid and is shown to be conservative. Thus, there is no impact of this additional weld data on the projected RT~> values for the Unit 1 vessel at end-of-life fluence, 32 effective full power years.
to C0699-01 Page 5 The following tables are included as a part of this attachment:
Table 1: GEOG Chemistry data for Weld Wire Heat No. 1P3571.
Table 2: Evaluation of Chemistry for Weld Wire Heat No. 1P3571.
Table 3: GEOG Chemistry Data for Weld Wire Heat No. 13253/12008.
Table 4: CEOG Chemistry Data for Weld Wire Heat No. 13253.
Table 5: Surveillance Data for Weld Heat No. 1P3571.
Table 6: Adjustments to Surveillance Data fox Weld Heat No.
1P3571.
Table 7: Information Requested on RPV Weld Materials for PTS Evaluation. r Table 8: RT~< Values for D. C. Cook 1 Vessel Beltline Materials.
to C0699-01 Page 6 References
- 1. Letter AEP:NRC:1173F, "Donald C. Cook Nuclear Plant Units 1 and 2, Response to NRC Generic Letter 92-01, Revision 1, Supplement 1, Reactor Vessel Structural Integrity," dated November 20, 1995.
- 2. Letter AEP:NRC:0561D, "Donald C. Cook Nuclear Plant Units 1 and 2, Updated Reference Temperature, Pressurized Thermal Shock Analyses," dated August 7, 1990.
- 3. "Best Estimate Copper and Nickel Values in CE Fabricated Reactor Vessel Welds," CE NPSD-1039, Revision 2, Final Report, Prepared for CE Owners Group, dated June 1997.
- 4. "Updated Analysis for Combustion Engineering Fabricated Reactor Vessel Welds, Best Estimate Copper and Nickel Content," CE NPSD-1119, Revision 1, Prepared for CE Owners Group, July 1998.
- 5. "Request for Additional Information Regarding Reactor Pressure Vessel Integrity at Donald C. Cook Nuclear Plant, Unit 1, TAC No. MA0539," dated November 16, 1998.
- 6. Memorandum from Keith R. Wichman to Edmund J. Sullivan, "Meeting Summary for November 12, 1997 Meeting with Owners Group Representatives and NEI Regarding Review of Responses to Generic Letter 92-01, Revision 1, Supplement 1 Responses,"" dated November 19, 1997.
- 7. "Evaluation of the 1P3571 Weld Metal from the Surveillance Programs for Kewaunee and Maine Yankee," WCAP-15074, September 1998.
- 8. 10 CFR 50.61, "Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events," Federal Register, Volume 60, 'Number 243, dated December 19, 1995.
Table 1. CEOG Chemistry data for Weld Wire Heat No. 1P3571 Summary of Properties for Weld Wire Heat No. 1P3571 Source: CEOG CE NPSD-1039 Revision 2 Heat No. Flux Type Flux Lot Pct. Cu Pct. Ni Data Source Reference Source LD. Group Tag IP3571 Linde 1092 3958 .17 .51 KWE, Supp. "V" WPS, 8/21/95 WDC%426 b IP3571 Linde 1092 3958 .15 KWE, Supp. "P" WPS, 8/21/95 WDC4427 b IP3571 Linde 1092 3958 .17 .61 KWE, Supp. "V'PS, 8/21/95 WDC4428 b IP3571 Linde 1092 3958 .17 .64 KWE, Supp. "R" WPS, 8/21/95 WDC%429 b IP3571 Linde 1092 3958 .18 .67 KWE, Supp. "R" 'PS, 8/21/95 WDC4430 IP3571 Linde 1092 3958 .19 .67 KWE, Supp. "V" WPS, 8/21/95 WDCA431 IP3571 Linde 1092 3958 .19 .67 KWE, Supp. "P" WPS, 8/21/95 WDC%432 b IP3571 Linde 1092 3958 .186 KWE, Supp. "S" WPS, 8/21/95 WDC4433
.689'20 IP3571 Linde 1092 3958 .70 KWE, Supp. "V" WPS, 8/21/95 WDCM34 b IP3571 Linde 1092 3958 .19 .71 KWE; Supp. V'PS, 8/21/95 WDC4435 b IP3571 Linde 1092 3958 .172 .717 KWE, SC "P" WCAP-13257 WDC4436 IP3571 Linde 1092 3958 .34 .72 KWE, Supp. "R" WCAP-13257 WDCM37 IP3571 Linde 1092 3958 .22 .73 KWE, Surv. Test WPS, 8/21/95- WDCA438 b CEOG Database 9/10/97 Note: WQ = Weld Qualification, SC = Surveillance Capsule, Supp. = Supplemental Test, Sutv. = Surveillance Weld
Table 1. CEOG Chemistry data for Weld Wire Heat No. 1P3571 Hea't No. Flux Type Flux Lot Pct. Cu Pct. Ni Data Source Reference Source LD. Group Tag IP3571 Linde 1092 3958 .191 .734 KWE, SC "P" WCAP-13257 WDC4439 b IP3571 Linde 1092 3958 .066 .736 KWE, SC "R" WCAP-13257 WDCA440 b IP3571 Linde 1092 3958 .24 .74 KWE, Surv. Test WPS, 8/21/95 WDC4441 b IP3571 Linde 1092 3958 .182 .742 KWE, SC "P" WCAP-13257 WDC4442 b IP3571 Linde 1092 3958 .354 .742 KWE, SC "P" WCAP-13257 WDC443 b IP3571 Linde 1092 3958 .207 .769 KWE, SC "R" . WCAP-13257 WDC4444 b IP3571 Linde 1092 3958 .20 .77 KWE, SC Unirr. ~
WCAP-8107 WDC4445 b, IP3571 Linde 1092 3958 .43 .78 KWE, Surv. Test WPS, 8/21/95 WDC4446 b IP3571 Linde 1092 3958 .23 .79 KWE, Surv. Test WPS, 8/21/95 WDCM47 b IP3571 Linde 1092 3958 .209 .795 KWE, Supp. "S" WPS, 8/21/95 WDCA448 b IP3571 Linde 1092 3958 .22 .80 KWE, Surv. Test WPS, 8/21/95 WDCM49 b IP3571 Linde 1092 3958 .434 .80 KWE, SC "V'CAP-13257 WDC<450 b IP3571 Linde 1092 3958 .196 .803 KWE, Supp. "S" WPS, 8/21/95 WDC451 b IP3571 Linde 1092 3958 .214 .816 KWE, SC "V'CAP-13257 WDC4452 b CEOG Database 9/10/97 Note: WQ = Weld Qualification, SC = Surveillance Capsule, Supp. = Supplemental Test, Surv. = Surveillance Weld
e Table 1. CEOG Chemistry data for Weld Wire Heat No. 1P3571 Heat No. Flux Type Flux Lot Pct. Cu Pct. Ni Data Source Reference Source LD. Group Tag IP3571 Linde 1092 3958 .223 '.871 KWE, Supp. "S" =
WCAP-13257 WDC4453 IP3571 Linde 1092 3958 .25 .66 MY, SC 263 deg. BCL-585-21 WDC4454 IP3571 Linde 1092 3958. .25 .70 MY,SC263deg. BCL-585-21 WDC4455 IP3571 Linde 1092 3958 .33 .70 MY, SC 263 deg. BCL-585-21 WDC4456 IP3571 Linde 1092 3958 .33 .71 MY, SC 263 deg. BCL-585-21 WDC4457 IP3571 Linde 1092 3958 .356 .728 MY, SC 253 deg. WCAP-12819 WDCA458 IP3571 Linde 1092 3958 .432 .745 MY, SC 253 deg. 'CAP-12819 WDC4460 IP3571 Linde 1092 3958 .365 .78 MY, SC Unirr. CR-75-269 WDCM63 IP3571 Linde 1092 3958 .34 .73 MY, Supp. C0441 WPS, 8/21/95 WDC4468 IP3571 Linde 1092 3958 .30 .76 MY, Supp. C04-11 WPS, 8/21/95 WDC4469 IP3571 Linde 1092 3958 .35 .76 MY, Supp. C04%2 WPS, &/21/95 WDCA470 IP3571 Linde 1092 3958 .33 .77 MY, Supp. C0445 WPS, 8/21/95 WDC4471 IP3571 Linde 1092 3958 .31 .78 MY, Supp. C0447 WPS, 8/21/95 WDC4472 IP3571 Linde 1092 3958 .32 '7& MY, Supp. C0448 WPS, &/21/95 WDCM73 CEOG Database 9/10/97 Note: WQ = Weld Qualification, SC = Surveillance Capsule, Supp. = Supplemental Test, Surv. = Surveillance Weld
Table 1. CEOG Chemistry data for Weld Wire Heat No. 1P3S71 Heat No. Fluz Type Fluz Lot Pct. Cu Pct. Ni Data Source Reference Source LD. Group Tag IP3571 Linde 1092 3958 .32 .78 MY, Supp. C0449 WPS, 8/21/95 WDC4474 c IP3571 Linde 1092 3958 ;32 .78 MY, Supp. C04-10 WPS, 8/21/95 WDC4475 c IP3571 Linde 1092 3958 .33 .78 MY, Supp. C0444 WPS, 8/21/95 WDC4476 IP3571 Linde 1092 3958 .37 .80 MY, Supp. C0441 WPS, 8/21/95 WDC<477 lp357I Lindc 1092 3958 .38 .80 MY, Supp. C04-13 WPS, 8/21/95 WDC4478 IP3571 Linde 1092 3958 .52 .80 MY, Supp. C04-15 WPS, S/21/95 WDC4479 IP3571 Linde 1092 3958 .81 MY, Supp. C0449 . WPS, 8/21/95 WDCA480 IP3571 Linde 1092 3958 .21 .88 C.E. CEOG Database WDC4481 c IP3571 Linde 1092 3958 .20 .73 LSI, SC 44U GE-NE-A166-1294-Rl WDC4483 d IP3571 Linde 1092 3958 .22 .73 LSI, SC 44M GE-NE-A166-1294-Rl WDC4484 d IP3571 Linde 1092 3958 .20 LS I, SC 44LD GE-NE-A166-1294-Rl WDC-0485 d IP3571 Linde 1092 3958 .20 .75 LSI, SC 443 GE-NE-A166-1294-Rl WDC4486 d IP3571 - Linde 1092 3958 .22 75 LSI, SC 444 GE-NE-A166-1294-Rl WDC4487 d IP3571 Linde 1092 3958 .20 .76 LS I, SC 44A GE-NE-A166-1294-Rl WDC4488 d CEOG Database 9/10/97 Note: WQ = Weld Qualification, SC = Surveillance Capsule, Supp. = Supplemental Test, Surv. = Surveillance Weld
Table 1. CEOG Chemistry data for Weld Wire Heat No. 1P3571 Heat No. Flux Type Flux Lot Pct. Cu Pct. Ni Data Source Reference Source LD. Group Tag IP3571 Linde 1092 3958 .22 .79 LS I, SC 447 GE-NE-A166-1294-Rl WDC4490 IP3571 Linde 1092 3958 .21 .80 LSI, SC 45K . GE-NE-A 166-1294-Rl %DC%491 IP3571 Linde 1092 3958 .21 .80 LS I, SC 45M GE-NE-A166-1294-Rl WDC4492 IP3571 Linde 1092 395S .22 .80 LS I, SC 45D GE-NE-A166-1294-Rl WDC4493 IP3571 Linde 1092 3958 .23 .82 LSI, SC 45E GE-NE-A166-1294-RI WDC4494 IP3571 Linde 1092 3958 .22 .83 LS I, SC 44F GE-NE-A166-1294-Rl WDC4495 IP3571 Linde 1092 3958 .21 .78 LS I, SC Unirr. WPS, 8/21/95 WDC4496 d IP3571 .Linde 1092 3958 .76 HAI, SC NEDC-30997 WDCM97 IP3571 Linde 1092 3958 .28 .76 HAI, SC NEDC-30997 . WDC4498 IP3 571 Linde 1092 3958 .28 .76 HAI, SC NEDC-30997 WDC4499 IP3571 Linde 1092 3958 0.32 0.82 HAI, SC, NE-B 1100691 I %DC-1879 IP3571 - Linde 1092 3958 0.32 0.87 HAI, SC NE-BI 100691%1 WDC-1880 IP3571 Linde 1092 3958 0.32 0.87 HAI, SC NE-B1100691%1 WDC-1881 CEOG Database 9/10/97 Note: WQ = Weid Qualification, SC = Surveillance Capsule, Supp. = Supplemental Test, Surv. = Surveillance %eld
Table 1. CEOG Chemistry data for Weld Wire Heat No. 1P3571 Heat No. Hux Type. Flux Lot Pct. Cu Pct. Ni Data Source Reference Source LD. Group Tag 1P3571 Linde 1092 3958 .37 .75 C.E., WQ Ml.43 CEOG Database WDC4500 f IP3571 Linde 1092 3958 C.E., WQ Ml.42 CEOG Database WDC4425 1P3571 Linde 80 0344 .22 Wire/Flux Qual. CEOG Database WDC482 Best Estimate Cu = 0.283 wt% Best Estimate Ni ~ 0.755 wt% Basis: Coil weighted Cu, weighted Ni Note: Using best~imate chemistry, CF = 212.2 'F from Reg. Guide 1.99, Rev. 2 Tables CEOG Database 9/10/97
Table 2. Evaluation of Chemistry for Weld Wire Heat No. I P3571 1P3571 Linde 1092 Type Fiux New Evaluation Cu Ni Flux Lot Number 3958 Avg. Cu Avg. Ni tt of wt% wt% CE PEDIGREE SOURCE LD. REPORT/ANALYSIS Group Tag wt% wt% Coib ewau ee S O. 2 0.17 0.51 INDETERMNATENi WDC4426
'0.15 INDETHMINATENi WDC4427 MSE-MNA-229 95 0.17 0.61 WDC4428 0.17 0.64 VALID WDC4429 0.18 0.67 WDC4430 0.19 0.67 VALID WDC4431 0.19 0.67 VALID WDC4432 MSE-MNA-229 95 0.186 0.689 WDC4433 MSE-MNA-229 95 0.20 0.70 VALID WDC4434 0.19 0.71 WDC4435 MSE-MNA-229 95 0.172 0.717 WDC4436 0.34 VALID WDC-0437 0.22 0.73 VALID WDC4438 0.191 0.734 WDC4439 WCAP-14280 0.066 0.736 INDETERMINATECu7 WDC4440 0.24 0.74 VALID WDC4441 0.182 0.742 VALID WDC4442 0.354 0.742 WDC4443 0.207 0.769 WDC4444 0.2 0.77 VALID WDC4445 0.43 0.78 WDC4446
'.23 0.79 WDC@447 0.209 0.795 WDC4448 MSF MNA-229 95 0.22 0.80 WDC4449 0.434 0.80 WDC4450 0.196 0.803 WDC4451 MSE-MNA-229 95 0.21 0.816 WDC4452 0.223 0.&71 WDC4453 MSE-MNA-229 95
Table 2. Evaluation, of Chemistry for Weld Wire Heat No. 1P3571 1P3571 Linde 1092 Type F1uz New Evaluation Flur Lot Number 3958 hvg. Cu Avg. Nl ¹of wt% wt% CE PEDIGREE SOURCE LD. REPORT/ANALYSIS Group Tag wt% Coils Maine Yankee, Single Are 0.351 0.771 0.25>> INDETERMNATE WDC4454 BC L-585-21 0.70>> VALID WDC4455 BCL-585-21 0.25'.33>>>>
0.70>>>> WDC4456 BC L-585-21 0.33'>> 0.71>>>> WDC4457 BCL-585-21 0.356 0.728 WDCM58 WCAP-12819 0.432 0.745 VAI.II) WDC4460 WCAP-12819 0.365 0.78 VALID WDC4463 D9693 0.34 0.73 VALID WDC4468 D44441 0.3 0.76 VALID WDC4469 0.35 0.76 WDC4470 D44440 0.33 VALID WDC4471 0.31 0.78 WDC4472 0.32 0.78 VALID WDC4473 0.32 0.78 VALID WDC4474 D44447 0.32 0.78 WDC4475 D44448 0.33 0.78 WDC4476 D44442 0.37 0.80 VALID WDCM77 D44439 0.38 0.80 WDC4478 D44451 0.52 0.80 VALID WDC4479 D44453 0.53 0.81 WDC4480 021>>>>>> 0.88 VALID WDC4481 ttvo measurements averaged to obtain single value for "bestmtimate" evaluation two measurements averaged to obtain single value for "bestmtimate" evaluation
"'easurement taken at interface with manual stick weld material =-
Table 2. Evaluation of Chemistry for Neld %ire Heat No. 1P3571 IP3571 Linde 1092 Type Flux New Evaluation Cu NI Flux Lot Number 3958 Avg. Cu Avg. NI tt of wt% wt% CE PEDIGREE SOURCE LD. REPORT/ANALYSIS Group Tag wt% wt% Coils LaSaile-1, Tandem Arc 0.212 0.20 0.73 VALID WDC4483 d 0.22 0.73 VALID 0.20 0.74 WDC4485 0.20 0.75 WDC4486 0.22 0.75 WDC4487 0.20 0.76 WDC4488 0.79 WDC4490 0.21 0.80 WDC4491 0.21 0.80 VALID WDC4492 0.2? .0.80 WDC4493 0.23 0.82 VALID WDC4494 0.22 0.83 VALID WDC4495 0.21 0.78 %DC4496 D11341 Hatch-I, Tandem Arc 0.304 0.807 0.76 VALID WDC4497 NEDC-30997 0.28 0.76 WDC4498 NEDC-30997 0.28 0.76 WDC4499 NEDC-30997 0.32 0.82 WDC-1879 NE-B110069141 0.32 0,87 INDETERMINATE %DC-1880 NE-B110069141 0.32 0.87 INDETERMNATE WDC-1881 NE-B1 10069141
Table 2. Evaluation of Chemistry for Weld Wire Heat No. 1P3571 1P3571 Linde 1092 Type Flui New Evaluation Nl Flux Lot Number 3958 hvg. Cu Avg. Nl ¹or wt% wt% CE PEDIGREE SOURCE LD. REPORT/ANALYSIS Group Tag wt% wt% Coils Weld Qualificatlon, Tandem Arc 0.370 0.750 0.37 0.75 D8698 Weld Quafificatlon, Single Arc 0.400 0.820 0.40 0.82 WDC4425 D8669 Weld Qualification, Llnde 80 Flux Type 0.220 0.670 I 0.22 0.67 WDC4482 D19780 Note: Group Tag g data not used in analysis Coil Weighted Aqp Simple Mean 0.287 wt% 0.756 wt%
Note: Using best~mate chemistry, CF = 214.0 'F from Reg. Guide 1.99, Rev. 2 Tables
Table 3. CEOG Chemistry Data for Weld Wire Heat No. 13253/1200&
Summary of Properties for %eld Wire Heat No. 13253/12008 Source: CEOG CE NPSD-1039 Revision 2
'I Heat No. Flux Type Flux Lot, Pct. Cu Pct. Ni Data Source Reference Source LD. Group Tag 13253/12008 Linde 1092, 3791 ,.22 .76 CEOG Database WDCAI55 13253/12008 Linde 1092 3791 .22 .76 C.E. CEOG Database WDCW 156 13253/12008 Linde 1092 3791 .22 .77 C.E. CEOG Database WDC-0158 Linde 1092, '3253/12008 3791 .22 .77 C.E. CEOG Database WDC-0159 13253/12008 Linde 1092, 3791 .22 .78 C.E. CEOG Database WDC-0160 13253/12008 Linde 1092 3791 .22 .78 CEOG Database WDCW 161 13253/12008 Linde 1092 3791 .22 .78 CEOG Database WDC162 13253/12008 Linde 1092 3791 .22 .78 C.E. CEOG Database WDCWI63 13253/12008 Lindh 1092 3791 .20 .86 CEOG Database WDCW165 13253/12008 Linde 1092 3791 .20 .86 C.E CEOG Database WDCA166 13253/12008 Linde 1092 3791 .20 CEOG Database %DC'67 CEOG Database 9/10/97
Table 3. CEOG Ckemistry Data for Weld Wire Heat No. 13253/12008 Heat No. Flux Type Flux Lot Pct. Cu Pct. Ni Data Source Reference Source I.D. Group Tag 13253/12008 Linde 1092 3791 .20 .87 C.E. CEOG Database WDC4168 13253/1200& Linde 1092 3791 .22 .87 C.E. CEOG Database WDC4169 13253/12008 Linde 1092 3791 .20 .88 CEOG Database WDC4170 13253/12008 Linde 1092 3791 .21 .&8 C.E. CEOG Database WDC4 171 13253/12008 . l.inde 1092 3791 .21 .88 C.E. CEOG Database WDC4 172 13253/12008 Linde 1092 3791 .21 .&8 C.E. CEOG Database WDC4173 13253/12008 Linde 1092 3791 .22 .88 C.E. CEOG Database WDC4174 13253/12008 Linde 1092 3791 .22 .88 C.E. CEOG Database WDC4175 13253/12008 Linde 1092 3791 .22 .88 C.E. CEOG Database WDC4176 13253/12008 , Linde 1092 3791 .20 .89 C.E. CEOG Database WDC4177 13253/12008 Linde 1092 3791 .20 .&9 C.E. CEOG Database WDC4178 13253/12008 Linde 1092 3791 .21 .89 C.E. CEOG Database WDC4179 13253/1200& Linde 1092 3791 .21 .89 CEOG Database WDC4180 13253/12008 Linde 1092 3791 .21 .89 C.E. CEOG Database WDC4181 b 13253/1200& Linde 1092 3791 .21 .89 C.E. CEOG Database WDC4182
Table 3. CEOG Chemistry Data for Neld Wire Heat No. 13253/12008 Heat No. Flu'x Type Flux Lot Pct. Cu Pct. Ni Data Source Reference Source LD. Group Tag 13253/12008 Linde 1092 3791 .21 .89 C.E. CEOG Database WDC4184 13253/12008 Linde 1092 3791 .22 CEOG Database WDC4185 13253/12008 Linde 1092 3791 .22 .89 C.E. CEOG Database WDC4186 13253/12008 Linde 1092 3791 .20 .90 C.E. CEOG Database WDC4187 13253/12008 Linde 1092 3791 .20 .90 C.E. CEOG Database WDC4188 13253/12008 Linde 1092 3791 .20 .90 C.E. CEOG Database WDC4189 13253/IZ008 Linde 1092 3791 .20 .90 C.E. CEOG Database WDC4190 13253/12008 , Linde 1092 3791 .21 C.E. CEOG Database WDC4191 13253/12008 Linde 1092 3791 .21 .90 C.E. CEOG Database WDC4192 13253/12008 Linde 1092 3791 .21 .90 C.E. ~
CEOG Database WDC4193 13253/12008 Linde 1092 3791 .22 .90 C.E. CEOG Database WDC4194 13253/12008 Linde 1092 3791 .22 .90 C.E. CEOG Database WDC4195 13253/12008 Linde 1092 3791 .20 .91 C.E CEOG Database WDC4196 13253/12008 Linde 1092 3791 .20 .91 C.E. CEOG Database WDC4197 13253/12008 l.inde 1092 3791 .20 .91 C.E. CEOG Database WDC4198 CEOG Database 9/10/97
Table 3. CEQG Chemistry Data for Weld Wire Heat No. 13253/12008 Heat No. Flux Type Flux Lot Pct. Cu Pct. Ni Data Source Reference Source LD. Group Tag 13253/12008 Linde 1092 3791 .20 .91 C.E. CEOG Database WDC4199 13253/1200& Linde 1092 3791 .20 .91 C.E. CEOG Database WDC4200 13253/12008'inde 1092 3791 .21 .91 C.E. CEOG Database WDC4201 b 13253/12008 Linde 1092 3791 .20 .92 C.E. CEOG Database WDC4202 13253/12008 Linde 1092 3791 .20 .92 C.E. CEOG Database WDC4203 13253/12008 Linde 1092 3791 .92 C.E. CEOG Database WDC4204 13253/12008 Linde 1092 3791; 3833 .24 .875 C.E. CEOG Database WDC4205 Best Estimate Cu ~ 0.21 wt% Best Estimate Ni ~ 0.873 wt% Basis: Simple mean Cu and Ni Note: Using best-estimate chemistry, CF = 208.7 'F from Reg. Guide 1.99, Rev. 2 Tables CEOG Database 9/10/97
Table 4. CEOG Chemistry Data for Weld Wire Heat No. 13253 Summary of Properties for %etd %ire Heat No. 13253 Source: CEOG CE NPSD-1039 Revision 2 Heat No. Flux Type Flux Lot Pct. Cu Pct. Ni Data Source Reference Source LD. Group Tag 13253 Linde 1092 3774, 3883 .23 .71 PR-EDB CEOG Database WDC-0399 13253 Linde 1092, 3774, 3883 .247 .728 PR-EDB CEOG Database WDC-0400 13253 Linde 1092 3774, 3&83 .267 .728 PR-EDB CEOG Database WDC4401 13253 Linde 1092 3774, 3883 .283 .732 PR-EDB CEOG Database WDC<402 13253 Linde 1092 3774, 3883 .244 .734 PR-EDB CEOG Database WDCA403 13253 Linde 1092 3791 .14 .72 C.E. CEOG Database WDCW404 13253 Linde 1092 3791 .14 .74 C.E. CEOG Database WDC<405 13253 Linde 1092 3791 .27 PR-EDB CEOG Database WDCO406 Best Estimate Cu ~ 0.221 wt% Best Estimate Ni 0.732 mt% Basis: Weighted mean Cu and Ni Note: Using bestmtimate chemistry, CF = 189.1 'F from Reg. Guide 1.99, Rev. 2 Tables CEOG Database 9/10/97
Table 5. Surveillance Data for Weld Heat No. 1P3571 Plant Capsule ID. CG Ni Irradiation Fluence Measured Data Used in
{including (wt%) (i>%%)
Temperature (x10'/cm') AT~ Assessing source) (F) (F) Vessel (Y or N)
Kewaunee V 0.219 0.724 532 597 <'75 Kewaunee R 0.219 0.724 532 <'35" <'.81
(>) (<)
Kewaunee P 0.219 0.724 532 2 74 230 Kewaunee S 0.219 0.724 532 3.36 <'50 <'
<') <')
Maine Yankee W263 0.351 0.771 533 .567 222
<')
Maine Yankee W253 0.351 0.771 542 1.25 1.76<'60<')(I)
Maine Yankee A25 0.351 0.771 522 270 Maine Yankee A35 0.351 0.771 533 7.13" 345
<'ean:
0.285 0.748 532.3 Table CFK~~ = 187.2 'F, Table CF~~ y,~~ = 237.3;F, Table CF = 211.9 'F
{') from Ref. 7, "Evaluation of the 1P3571 Weld Metal from the Surveillance Programs for Kewaunee and Maine Yankee," WCAP-15074, September 1998.
Table 6. Adjustments to Surveillance Data for Weld Heat No. 1P3571 Plant Capsule ID (including source) (et%)
Ni (a>1%)
Irradiation Temperature
( F)-
Fluence Factor 'T~ Measured
('F)
Adjusted hRT~z+
('F)
Predicted MTNoz'F)
(Adjusted-Predicted) hRTNoz (F)
Kewaunee V 0.219 0.724 532 0.856 175 198.4 185.2 13.2 Kewaunee 0.219 0.724 532 1.163 235 266.3 251.7 14.6 Kewaunee 0.219 0.724 532 1.269 230 260.7 274.7 -14.0 Kewaunee 0.219 0.724 . 532 1.317 250 283.3 285.1- -1.9 Maine Yankee %263 0.351 0.771 533 0.841 222 197.5 182.1 15.4.
Maine Yankee W253 0.351 0.771 542 1.062 260 222.5 229.9 ~
-7.5 Maine Yankee A25 0.351 0.771 522 1.155 270 251.4 250.1 1.3 Maine Yankee A35 0.351 0.771 533 1.466 345 307.4 317.3 -9.9
'luence Factor(FF) = fluence
' "'~" "for fluencevalues shown in Table 5
= Table CFM~
- Measured hRTNoz + (Tirrt,t.- Tirrc,~,)
+'djusted hRTNDz Table CFG,~I,
'retjicted hRTNDT = FF
Table 7. Information Requested on RPV Weld Materials for PTS Evaluation Facility: D. C. Cook 1 Vessel Manufacturer: Combustion Engineering 32EFPYPeak(ID) Fluence: 1.41x10'/crn 32 EFPY Axial Weld (ID) Fluence: 9.5x10" n/cm RPV
"'est-Weld Wire Estimate Best-Estimate EOL ID Fluence Assigned Material Method of Determining Initial RTrior a> Margin RTFrs at EOL Heat Copper Nickel (x10 ) Chemistry CFt'>- (RTiinr(U))
Factor (CF) ('F) ('F)
(wt%) (wt%) {n/cm') ('F) = ('F) ('F)
('F) 13253/12008 0.21 0.873 0.95 208.7 Tables -56 17 28 66 215.7
'56 1P3571 0.287 0.756 1.41 218.6~i Surv. Data 17 14 44 227.4 (1) weld heat number or the material identification of the limiting material (2) determined from tables or from surveillance data
{3) ratio adjusted CF value to account for chemistry differences between the capsule materials and the vessel:
Ratio Adjusted CF = 21 CF CFTable, Surv. Chem.
216.5 ~
214.0 21 1.9
= 218.6 'F Discu'ssion ofthe Anal si Method and Da a Used forE ch Weld Wire Heat Weld Wire Heat Discussion 13253/12008 Simple mean Cu and Ni (see Table 3)
IP3571 Coil-weighted Cu, simple mean Ni (see Table 2)
e Table 8. RTFrs Values for D. C. Cook I Vessel Belt)inc Materials UtilityPTS Summary Report for D. C. Cook 1 Basis for Calculation ofRT~ Values fn Reactor Vessel Beltline Materials Material Beltline LD. Heit No. IRTqnr{Fj CF (F) EOL'luence FF hRTunq (Fl MARGIN (F) RTPTS (Fl Int. Shell Axial Welds 2442 A,B&C 13253/12008 -56 208.7 9.5E+18 0.9856 205.7 66 215.7 Int. Shell Plate B4406-I C1260 81.4 1.41E+19 1.095 89.2 128.2 Int. Shell Plate B4406-2 C3506 33 104.5 1.41E+19 1.095 114.5 181.5 Int. Shell Plate B4406-3 C3506 40 104 1.41E+19 1.095 113.9 187.9 218.6>> 239.4>> 44>> 227.4>>
Int. to Lovver Shell Circ. Weld 9442 I F3571 -56 2@% 1.41E+19 1.095 2M6 66 238-.6 Louver Shell Axial Welds 3142 A,B&C 13253/12008 -56 208.7 9.5E+18 0.9856 205.7 66 215.7 Lower Shell Plate B4407-I C3929 28 97.8 1.41E+19 1.095 107.1 169.1 Lower Shell Plate B4407-2 C3932 -12 82.8 1.41E+19 1.095 34 112.7 Lower Shell Plate B4407-3 C3929 38 95.5 1.41E+19 1.095 104.6 34 176.6
>> rev'ised values
Attachment 3 to C0699-Ol WESTINGHOUSE REPORT WCAP-15074