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 DOCKET I FACIL:50-315.Donald C.
Cook Nuclear Power Plant, Unit 1, Indiana M
05000315 AUTH.NAME AUTHOR AFFILIATION RENCHECK,M.W.
RECIP.NAME RECIPIENT AFFILIATION Records Management Branch (Document Control Desk)
SUBJECT:
Provides response to 981116
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.
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Power Company 500 Circle Drive Buchanan, Ml 49107 1373 INNING NICHISAN POWER June 28, 1999 Docket No.: 50-315 C0699-01 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 PDR ADOCKi>OS00031S
U.
S. Nuclear Regulatory Commission Page 2
C0699"01 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:
(.'ttachments JAN WATSON NOTARYPUBUC, BERRIEN COUNlY,Ml MYCOhMSSION EXPIRES FEB. 10, 2003 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
Attachment 1 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
Attachment 1 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, it may be appropriate to consider all chemistry samples from that 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
Attachment 1 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
Attachment 1 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
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).
Attachment 1 to C0699-01 Re uest for Additional Information Item 3 Page 5
- 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
- 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.
Attachment 2
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).
Attachment 1 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:
Table 6:
CEOG Chemistry Data for Weld Wire Heat No.
1P3571.
Evaluation of Chemistry for Weld Wire Heat No.
1P3571.
Attachment 1 to C0699-01 References Page 7
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
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/ocladding): 8.5 inches.
32 EFPY Peak (ID)Fluence: 1.41xl0'/cm 32 EFPY Peak (I/4t) Fluence: 8.46x10'/cm 32 EFPY AxialWeld {ID)Fluence: 9.5x10'/cm 32 EFFY Axial Weld (I/4t) Fluence: 5.7x10'/cm RPV Mfeld %fire or Plate Heat Number"'est-Estimate Copper (wt%)
Best-Estimate Nickel (wt%)
I/4t Fluence (x 10' (n/cm )
Assigned Material Chemistry Factor (CF)
('F)
Method of Determining CFt'>
('F)
Initial RT~
(RTNDT(U))
('F)
('F)
(F)
Margin
('F)
('F) 13253/12008 weld IP3571 weld C3506 late 0.21 0.873 0.57 0.15'.49 0.846 0.287 0.756 0.846 208.7 218.d" 119.6 Tables Surv. Data Surv. Data
-56
-56 40 17 28 17 14 0
17 66 17 185.9 196.3 171.0 (I) weld heat number or the material identification ofthe limitingmaterial (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 ofthe Anal sis Method nd Data Used for E ch Weld tre Heat Weld Wire He 13253/12008 IP3571 Discussion Simple mean Cu and Ni (see Table 4)
Coil-weighted Cu, simple mean Ni (see Table 6)
Table 2: Surveillance Data for Weld Heat No. 1P3571 Plant Capsule ID (including source)
Cu (i~a%)
Ni (wt%)
Irradiation Fluence Measured Temperature (x10'/cm )
MTNoz
('F)
('F)
Data Used in Assessing Vessel (Yor N)
Kewaunee Kewaunee V
.0.219 0.219 0.724 0.724 532 532 597<'75 <'>
1.81 <'l 235 <'l Y
Kewaunee Kewaunee P
0.219 S
0.219 0.724 0.724
. 532 532 274 '30
'50<'>
Y Maine Yankee W263 0.351 Maine Yankee W253 0.351 Maine Yankee A25 0.351 Maine Yankee A35 0.351 0.771 0.771 0.771 0.771 533 542 522 533 1.25 <'60'>
1.76 "
270 <'>
7.13" 345 <'>,
.567 <')
222 <'l 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 (including source)
Cu.
Ni (at%)
(wt%)
Irradiation Fluence Temperature Factor t'~
('F)
Measured Adjusted hRTNor hRTNDp~
('F)
( F)
Predicted (F)
(Adjusted-Predicted) hRTNor
('F)
Kewaunee V
0.219 0.724 532 0.856 175 198.4 185.2 13.2 Kewaunee Kewaunee Kewaunee P
0.219 0.724 0.219 0.724 0.219 0.724 532 532 532 1.163 1.269 1.317 235 230 266.3 260.7 250 283.3 251.7 274.7 285.1 14.6
-14.0
-1.9 Maine Yankee W263 0.351 0.771 533 0.841 222 197.5 182.1 15.4 Maine Yankee W253 Maine Yankee A25 Maine Yankee A35 0.351 0.771 0.351 0.771 0.351
.0.771 542 522 533 1.062 1.155 1.466 260 222.5 270 251.4 345 307A.
229.9 250.1 317.3
-7.5 1.3
-9.9
'luence Factor (FF) = fluence'"~"
"forfluence values shownin Table2 Table CFM~
"'djusted dRTNDT =
~ Measured dRTNDT + {TirrM
- Tirrc,~,)
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 ofProperties 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 13253/12008 Linde 1092 13253/12008 Linde 1092 13253/12008 Linde 1092 13253/12008 Linde 1092 13253/12008 Linde 1092 13253/12008 Linde 1092 13253/12008 Linde 1092 13253/12008 Linde 1092 13253/12008 Linde 1092 13253/12008 Linde 1092 3791 3791 3791 3791 3791 3791 3791 3791 3791 3791 3791
.22
.22
.22
.22
.22
.22
.22
.20
.20
.20
.76
.76
.77
.77
.78
.78
.78
.78
.86
.86
.87 C.E.
CEOG Database WDC4155 CEOG Database WDC4156 C.E.
C.E.
C.E.
C.E.
C.E.
C.E.
C.E.
CEOG Database WDC4159 CEOG Database WDC4160 CEOG Database WDC4 161 CEOG Database WDC4162 CEOG Database WDC4163 CEOG Database WDC4165 CEOG Database WDC4 166 CEOG Database WDC4167 C.E.
CEOG Database WDC4158 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 13253/12008 Lindc 1092 13253/12008 Linde 1092 13253/12008 Linde 1092 3791 3791 3791 3791
.20
.22
.20
.21
.87
.87
.88
.88 C.E.
C.E.
C.E.
C.E.
CEOG Database WDC4168 CEOG Database WDC4169 CEOG Database WDC4170 CEOG Database WDC4171 13253/12008 13253/12008 13253/12008 13253/12008 13253/12008 13253/12008 13253/12008 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 3791 3791 3791 3791 3791 3791 3791
.21
.21
.22
.22
.22
.20
.20
.88
.88
.88
.88
.89 C.E.
CEOG Database WDC4172 C.E.
CEOG Database WDC4173 C.E.
CEOG Database WDC4174 C.E.
CEOG Database WDC4175 C.E.
CEOG Database WDC4176 C.E.
CEOG Database WDC4177 C.E.
CEOG Database WDC4178 b
13253/12008 Linde 1092 13253/12008 Linde 1092 13253/1200$
Lindc 1092 13253/1200S Linde 1092 13253/12008 Linde 1092 3791 3791 3791 3791 3791
.21
.21
.21
.21
.89
.89
.89
.89
.89 C.E.
C.E.
C.E.
CEOG Database WDC4179 CEOG Database WDC4180 CEOG Database WDC4181 CEOG Database WDC4182 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 13253/12008 Linde 1092 13253/1200&
Linde 1092 13253/12008 Linde 1092 13253/12008 Linde 1092 13253/12008 Linde 1092 13253/12008 Linde 1092 13253/12008 Linde 1092 13253/12008 Linde 1092 13253/12008 Linde 1092 13253/)2008 Linde 1092 13253/12008 Linde 1092 13253/12008 Lindc 1092 13253/12008 Linde 1092 3791 3791 3791 3791 3791 3791 3791 3791 3791 3791 3791 3791 3791 3791
.21
.22
.22
.20
.20
.20
.20
.21
.21
.21
.22
.20
.20
.89
.89
.89
.90
.90
.90
.90
.90
.90
.90
.90
.90
.91
.91 C.E C.E.
C.E.
C.E.
C.E.
C.E.
C.E.
C.E.
C.E C.E.
CEOG Database
%DC4184 CEOG Database
%DC4185 CEOG Database WDC4186 CEOG Database WDC41&7 CEOG Database WDC4 188 CEOG Database WDC4189 CEOG Database WDC4190 CEOG Database WDC4191 CEOG Database WDC4192 CEOG Database WDC4193 CEOG Database WDC4194 CEOG Database WDC4195 CEOG Database WDC4196 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 13253/1200S 13253/12008 13253/1200 S 13253/12008 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 13253/12008 l,inde 1092.
13253/12008 Linde 1092 3791
.20
.91 3791 3791
.20
.91
.92 3791
.20 3791
.21
'.92 3791; 3S33
.24
.875 3791
.20
.91
'I C.E.
C.E.
C.E.
C.E.
C.E.
C.E.
C.E.
CEOG Database WDC4199 CEOG Database WDC4200 CEOG Database WDC4201 CEOG Database WDC4202 CEOG Database WDC4203 CEOG Database WDC4204-
'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 forWeld Wire Heat No. IP3571 Summary ofProperties 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 IP3571 IP3571 IP3571 IP3571 IP3571 IP3571 IP3571 Linde 1092 Linde 1092 Lindc 1092 Linde 1092 Linage 1092 Linde 1092 Linde 1092 Linde 1092 IP3571 IP3571 IP3571 IP3571 Linde 1092 Linde 1092 Linde 1092 Linde 1092 IP3571 Linde 1092 3958 3958 3958 3958 3958 3958 3958 3958 3958 3958 3958 3958 3958
.17
.51
.15
.17
.61
.17
.64
.18
.67
.19
.67
.22
.73
.19
.67
.186
.689
.20
.70
.19
.71
.172'717
.34
.72 KWE, Supp. "V'PS, 8/21/95 WDC4426 b
KWE, Supp. "P" WPS, 8/21/95 WDCM27 b
KWE, Supp. "V'PS, 8/21/95 WDCW428 b
KWE, Supp. "R" WPS, 8/21/95 KWE, Supp. "R" WPS, 8/21/95 WDC<429 b
WDCW430 b
KWE, Supp. "V'PS, 8/21/95
%DC%431 b
KWE, Supp. "P" WPS, 8/21/95
%DC%432 b
KWE, Supp. "S" WPS, 8/21/95
%DC<433 b
KWE, Supp. "V'PS, 8/2)/95 WDCM34 b
KWE, Supp.
V'WE, SC "P" WPS, 8/21/95 WDC4435 b
WCAP-13257 WDC4436 b
KWE, Supp. "R"
%CAP<<13257 WDC4437 b
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 FlllxLof Pct. Cu Pct. NI Data Source Reference Source LD.
Group Tag IP3571 IP3571 IP3571.
IP3571 IP3571 IP3571 IP3571 IP3571 IP3571 IP3571 IP3571 IP3571 IP3571 IP3571 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 395&
3958 3958 3958 3958 3958 3958 3958 3958 3958 3958 3958 3958 3958
.191
.734
.066
.736
.24
.74
.182
.742
.354
.742
.207
.769
.20
.77
.43
.78
.23
.79
.209
.795
.22
.80
.434
.80
.196
.803
.214
.816 KWE, SC "P" WCAP-13257 WDC4439 b
KWE, SC "R" WCAP-13257 WDC4440 b
KWE, Surv. Test WPS, 8/21/95 WDC4441 b
KWE, SC "P" KWE SC "P" KWE, SC "R" WCAP-13257 WDC4442 b
WCAP-13257 WDC4443 b
WCAP-13257 WDC4444 b
KWE, SC "V'CAP-13257 WDC4452 b
KWE, SC Unirr.
WCAP<107 WDC4445 b
KWE, Surv. Test WPS, 8/21/95 WDC4446 b
KWE, Surv. Test WPS, 8/21/95 WDC4447 b
KWE, Supp. "S" WPS, 8/21/95 WDC4448 b
KWE, Surv. Test WPS, 8/21/95 WDC4449 b
KWE, SC "V'CAP-13257 WDC4450 b
KWE, Supp. "S" WPS, 8/21/95 WDC4451 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 IP3571 IP3571 IP3571 IP3571 IP3571 IP3571 IP3571 IP3571 IP3571 IP3571 IP3571 IP3571 IP3571 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Lindc 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 395&
3958 395&
3958 3958 395&
3958 395S 3958 3958 3958 3958 3958 3958
.30
.76
.35
.76
.33
.77
.31
.78
.32
.78
-.223
.871
.25
.66
.25
.70
.33
.70
.33
.71
.356
.728
.432
.745
.365
.78
.34
.73 KWE, Supp. "S" WCAP-13257 MY, SC 263 deg.
BCL-585-21 WDC4453 WDC4454 MY,SC Unirr.
CR-75-269 WDC%463 MY, Supp. COW)1 WPS, 8/21/95 WDC4468 MY, Supp. C04-11 WPS, 8/21/95 WDC4469 MY, Supp. COW)2 WPS, 8/21/95 WDC4470 MY,Supp. C04-05 WPS, 8/21/95 WDC%471 MY, Supp. C0447 WPS, S/21/95 WDC4472 MY, Supp. C0448 WPS; 8/21/95 WDC4473 MY,SC263 deg.
BCL-585-21 WDC4455 MY,SC263deg.
BCL-585-21 WDC4456 MY, SC 263 deg.
BCL-585-21 WDC4457 MY, SC 253 deg.
WCAP-12&19 WDC%458 MY,SC253deg.
WCAP-12819 WDC4460 C
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 IP3571 IP3571 IP357l IP3571 IP3571 IP3571 IP3571 IP3571 IP3571 Linde 1092 Linde 1092 Linde 1092 Lindc 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde.1092 IP3571 IP3571 IP3571 Linde 1092 Linde 1092 Linde 1092 IP3571 Linde 1092 3958 3958 3958 3958 3958 3958 3958 3958 3958 3958 3958 3958 3958 3958
.32
.78
.32
.78
.33
.78
.37
.80
.38
.80
.52
.80
.53
.81
.21
.88
.75
.20
.20
.73
.22
.73
.20
.74
.20
.75 MY, Supp. C0449 WPS, 8/21/95 MY,Supp. C04-10 WPS, &/21/95
%DC%474 c
WDC4475 c
MY, Supp. C0441 WPS, 8/21/95 MY, Supp. C04-13
%PS, 8/21/95 MY, Supp. C04-15
%PS, 8/21/95 MY, Supp. C0449 WPS, 8/21/95 WDC4477 c
%DC4478 c
WDC4479 c
WDCA480 c
C.E.
CEOG Database WDC-04S I c
LSI, SC 44U GE-NE-A166-1294-Rl WDC4483 d
LSI, SC 44M GE-NE-AI66-.1294-RI
%DC@484 d
LSI, SC 44LD.GE-NE-A166-1294-Rl WDC4485 d
LSI, SC 443 GE-NE-A166-1294-Rl WDC-0486 d
LSI, SC 444 GE-NE-A166-1294-Rl WDC4487 d
LSI, SC 44A GE-NE-A166-1294-Rl WDC4488 d
MY, Supp. C04M WPS, 8/21/95 WDC-0476 c
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 1P3571 IP3571 IP3571 IP3571 IP3571 IP3571 IP3571 IP3571 IP3571 IP3571 IP3571 IP3571 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 395&
3958 3958 3958 3958 3958 3958 3958 3958 3958 3958 3958 3958
.22
.79
.21
.80
.21
.80
.22
.80
.23
.82
.22
.83
.21
.78
.76
.28
.76
.28
.76 0.32 0.82 0.32 0.87 0.32 0.87 LSI, SC Unirr.
HAI,SC HAI,SC 1
HAI,SC i
HAI,SC HAI,SC HAI,SC WPS, 8/21/95 WDC-0496 NEDC-30997 WDC4497 NEDC-30997 WDC4498 NEDC-30997 WDCM99 NE-B1100691%1 WDC-1879 NE-B1100691-01 WDC-18&0 NE-B1100691%1 WDC-1881 LSI, SC 447 GE-NE-A166-1294-Rl WDC-0490 LSI, SC 45K GE-NE-A166-1294-Rl WDC4491 LSI, SC 45M GE-NE-A166-1294-Rl WDC-0492 LSI, SC 45D GE-NE-A166-1294-Rl WDC-0493 LSI, SC 45E GE-NE-A166-1294-Rl WDC4494 LSI, SC 44F GE-NE-A166-1294-Rl WDC4495 d
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 1P3571 IP3571 Linde 1092 Linde 1092 Linde 80 3958 3958 0344
.37
.75
.40
.82
.22
.67 C.E., WQ M1.43 CEOG Database WDC4500 f
C.E., WQ M1.42 CEOG Database WDC4425 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 ofChemistry for Weld Wire Heat No. 1P3571 1P3571 CQ Ni wt%
wt%
CE PEDIGREE Linde 1092 Type Flux Flux Lot Number 3958 SOURCE LD.
REPORT/ANALYSIS Kewaunee, Single Are Group Tag Avg. Cu wt%
0.219 New Evaluation Avg. Ni wt%
0.724
¹of Coib 0.2 0.77 0.43 0.78 0.23 0.79 0.209 0.795 0.22 0.80 0.434 0.80 0.196 0.803 0.21 0.816 0.223 0.871 0.17 0.51
.0.15 0.54 0.17 0.61 0.17 0.64 0.18 0.67 0.19 0.67 0.19 0.67 0.186 0.689 0.20 0.70 0.19 0.71 0.172 0.717 0.34 0.72 0.22 0.73 0.191 0.734 0.066 0.736 0.24 0.74 0.182 0.742 0.354 0.742 0.207 0.769
~ INDETERMNATENi INDETERMINATENi VALID VALID INDETERMNATECuf VALID VALID VALID WDC4426 WDC4427 WDC4428 WDC4429 WDC4430 WDC4431 WDC4432 WDC4433 WDC4434 WDC4435 WDC4436 WDC4437 WDC4438.
WDC4439 WDC4440 WDC4441 WDC-0442 WDC4443 WDC4444 WDC@445 WDC4446 WDC4447 WDC4448 WDC4449 WDG0450 WDC4451 WDC4452 WDC4453 MSE-MNA-229(95)
MSF MNA-229(95)
MSF MNA-229(95)
MS E-MNA-229(95)
WCAP-142&0 MSE-MNA-229(95)
MSE-MNA-229(95)
MS E-MNA-229(95)
Table 6. Evaluation ofChemistry 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 0.25~
0.66~
0.250 0.700 0.33~~
0.70~~
0.33~'.71~~
0.356 0.728 0.432 0.745 0.365 0.78 0.34 0.73 0.3 0.76 0.35 0.76 0.33 0.77 0.31 0.78 0.32 0.78 0.32 0.78 0.32 0.78 0.33 0.78 0.37 0.80 0.3&
0.80 0.52 0.80 0.53 0.81 0.21~~~
0.88 VALID VALID Maine Yankee, Single hrc WDC4454 WDC4455 WDC4456 WDC@457 WIXA458 WDC4460 WDC4463 WDC4468 WDC4469 WDC4470 WDC4471 WDC4472 WDC4473 WDC4474 WDC4475 WDC4478 WDC4479 WDC4481 BCI 5&5-21 BCL-585-21 BCI 585-21
~
BCL 585-21 WCAP-12819 WCAP-1 2819 D9693 D44441 D44449 D44440 D44443 D44446 D44447 D44439 D44451 D44453 D44452 0251 0.771 two measurements averaged to obtain single value for "best~mate" evaluation
" two measurements averaged to obtain single value for "best~imate" evaluation
"'easurement taken at interface with manual stick weld material
Table 6. Evaluation ofChemistry forbid Wire Heat No. 1P3571 1P3571 Cu Ni wt%
wt%
0.22 0.75 0.20 0.76 0.20 0.73 0.22 0.73 0.20 0.74 0.20 0.75 CE PEDIGREE VALID Linde 1092 Type Fluz Hux Lot Number 3958 SOURCE LD. 'EPORT/ANALYSIS LaSalle-1, Tandem Arc WDC4483 WDC4484 WDC4485 WDC4486 WDC4487 WDC4488 Group Tag hvg. Cu wt%
0.212 New Evaluation hvg. Nl wt%
0.775
¹or Colla 0.22 0.79 VALID WDC4490 0.21 0.21 0.80 0.80 0.76 0.28 0.76 0.2&
0.76 0.32 0.82 0.32 0.87 0.32 0.87 0.22 0.80 0.23 0.82 0.22 0.83 0.21 0.78 VALID VALID
- VAUD VALID VALID INDETERMINATE INDETERMNATE H
WDC4491 WDC4492 WDC4493 WDC4494 WDC4495 WDC4496 atch-l, Tandem Arc WDC4497 WDC4498 WDC4499 WDC-1879-WDC-1880 WDC-18SI D11 341 NEDC-30997 NEDC-30997 NEDC-30997 NE-B110069141 NE-B110069141 NE-BI10069141 0.304 0.807
Table 6. Evaluation ofChemistry for Weld %ire Heat No. 1P3571 1P3571 Linde 1092 Type Fluz New Evaluation Cu Ni Huz Lot Number 3958 hvg. Cu hvg. Nl ffof wt%
wt%
0.37 0.75 CE PEDIGREE SOURCE LD.
REPORTIANALYSIS Weld Qualification, Tandem Arc D8698 Weld Qualification, Single Arc Group Tag wt%
0.370 0.400 wt%
0.750 0.820 Coils 0.40 0.82 WDC4425 Weld Qualification, Llnde 80 Huz Type D8669 0.220 0.670 0.22 0.67 WDC4482 Dl9780 Note: Group Tag g data not used in anal@is Coll Weighted Avg.
Cu 0.287 wt%
Simple Mean Ni 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
Attachment 2 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
- 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
Attachment 2 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
Attachment 2 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 Cr *measured ARTssr
+ (Tires-Tirre,rem,)
Table 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,>> lch,.
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
Attachment 2 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.
Attachment 2 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.
Attachment 2 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
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 ofProperties 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 IP3571 IP3571 IP3571 IP3571 IP3571 IP3571 IP3571 IP3571 IP3571 IP3571 IP3571 IP3571 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 3958 3958 3958 3958 3958 3958 3958 3958 3958 3958 3958 3958 3958
.17
.51
.15
.17
.61
.17
.64
.18
.67
.19
.67
.19
.67
.186
.689'20
.70
.19
.71
.172
.717
.34
.72
.22
.73 KWE, SC "P" WCAP-13257 WDC4436 KWE, Supp. "R" WCAP-13257 WDCM37 KWE, Surv. Test WPS, 8/21/95-WDCA438 b
KWE, Supp. "V" WPS, 8/21/95 WDC%426 b
KWE, Supp. "P" WPS, 8/21/95 WDC4427 b
KWE, Supp. "V'PS, 8/21/95 WDC4428 b
KWE, Supp. "R" WPS, 8/21/95 WDC%429 b
KWE, Supp. "R" 'PS, 8/21/95 WDC4430 KWE, Supp. "V" WPS, 8/21/95 WDCA431 KWE, Supp. "P" WPS, 8/21/95 WDC%432 b
KWE, Supp. "S" WPS, 8/21/95 WDC4433 KWE, Supp. "V" WPS, 8/21/95 WDCM34 b
KWE; Supp. V'PS, 8/21/95 WDC4435 b
CEOG Database Note: WQ = Weld Qualification, SC = Surveillance Capsule, Supp. = Supplemental Test, Sutv. = Surveillance Weld 9/10/97
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 IP3571 IP3571 IP3571 IP3571 IP3571 IP3571 IP3571 IP3571 IP3571 IP3571 IP3571 IP3571 IP3571 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 3958 3958 3958 3958 3958 3958 3958 3958 3958 3958 3958 3958 3958 3958
.191
.734
.066
.736
.24
.74
.182
.742
.354
.742
.207
.769
.20
.77
.43
.78
.23
.79
.209
.795
.22
.80
.434
.80
.196
.803
.214
.816 KWE, SC "P" KWE, SC "R" WCAP-13257 WDC4439 b
WCAP-13257 WDCA440 b
KWE, Surv. Test WPS, 8/21/95 WDC4441 b
KWE, SC "P" WCAP-13257 WDC4442 b
KWE, Surv. Test KWE, Surv. Test WPS, 8/21/95 WPS, 8/21/95 WDC4446 b
WDCM47 b
KWE, Supp. "S" WPS, 8/21/95 WDCA448 b
KWE, Surv. Test WPS, 8/21/95 WDCM49 b
KWE, SC "V'CAP-13257 WDC<450 b
KWE, Supp. "S" WPS, 8/21/95 WDC451 b
KWE, SC "V'CAP-13257 WDC4452 b
KWE, SC "P" WCAP-13257 WDC443 b
KWE, SC "R"
. WCAP-13257 WDC4444 b
KWE, SC Unirr.
~
WCAP-8107 WDC4445 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 IP3571 IP3571 IP3571 IP3571 IP3571 IP3571 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 IP3571 IP3571 IP3571 IP3571 IP3571 IP3571 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 IP3571 Linde 1092 3958 3958 3958.
3958 3958 3958 3958 3958 3958 3958 3958 3958 3958 3958
.223
'.871
.25
.66
.25
.70
.33
.70
.33
.71
.356
.728
.432
.745
.365
.78
.34
.73
.30
.76
.35
.76
.33
.77
.31
.78
.32 '7&
KWE, Supp. "S"
=
WCAP-13257 WDC4453 MY, SC 263 deg.
BCL-585-21 WDC4454 MY,SC263deg.
BCL-585-21 WDC4455 MY, SC 263 deg.
BCL-585-21 WDC4456 MY, SC 263 deg.
BCL-585-21 WDC4457 MY, SC 253 deg.
WCAP-12819 WDCA458 MY, SC 253 deg.
'CAP-12819 MY, SC Unirr.
CR-75-269 WDC4460 WDCM63 MY, Supp. C0441 WPS, 8/21/95 WDC4468 MY, Supp. C04-11 WPS, 8/21/95 WDC4469 MY, Supp. C04%2 WPS, &/21/95 WDCA470 MY,Supp. C0445 WPS, 8/21/95 WDC4471 MY, Supp. C0447 WPS, 8/21/95 WDC4472 MY,Supp. C0448 WPS, &/21/95 WDCM73 CEOG Database Note: WQ = Weld Qualification, SC = Surveillance Capsule, Supp. = Supplemental Test, Surv. = Surveillance Weld 9/10/97
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 IP3571 IP3571 IP3571 lp357I IP3571 IP3571 IP3571 IP3571 IP3571 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Lindc 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 IP3571 Linde 1092 IP3571 Linde 1092 IP3571 Linde 1092 IP3571 Linde 1092 3958 3958 3958 3958 3958 3958 3958 3958 3958 3958 3958 3958 3958 3958
.38
.80
.52
.80
.21
.81
.88
.20
.73
.22
.73
.20
.20
.75
.22
.20 75
.76
.32
.78
- 32
.78
.33
.78
.37
.80 MY,Supp. C0449 WPS, 8/21/95 MY, Supp. C04-10 WPS, 8/21/95 MY, Supp. C0444 WPS, 8/21/95 MY, Supp. C0441 WPS, 8/21/95 MY, Supp. C04-13 WPS, 8/21/95 MY, Supp. C04-15 WPS, S/21/95 MY,Supp. C0449 WPS, 8/21/95 WDC4474 c
WDC4475 c
WDC4476 WDC<477 WDC4478 WDC4479 WDCA480 C.E.
CEOG Database WDC4481 c
LSI, SC 44U GE-NE-A166-1294-Rl WDC4483 d
LSI, SC 44M GE-NE-A166-1294-Rl WDC4484 d
LSI, SC 44LD GE-NE-A166-1294-Rl WDC-0485 d
LSI, SC 443 GE-NE-A166-1294-Rl WDC4486 d
LSI, SC 444 GE-NE-A166-1294-Rl WDC4487 d
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. = 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 IP3571 IP3571 Linde 1092 Linde 1092 Linde 1092 IP3571 Linde 1092 IP3571 IP3571 IP3571 IP3571 IP3571 Linde 1092 Linde 1092 Linde 1092
.Linde 1092 Linde 1092 IP3 571 IP3571 Linde 1092 Linde 1092 IP3571 Linde 1092 IP3571 Linde 1092 3958 3958 3958 395S 3958 3958 3958 3958 3958 3958 3958 3958 3958
.22
.79
.21
.80
.21
.80
.22
.80
.23
.82
.22
.83
.21
.78
.76
.28
.76
.28
.76 0.32 0.82 0.32 0.87 0.32 0.87 HAI,SC HAI,SC HAI,SC HAI,SC, HAI,SC HAI,SC NEDC-30997 WDCM97 NEDC-30997 WDC4498 NEDC-30997 WDC4499 NE-B1100691 I
%DC-1879 NE-BI100691%1 WDC-1880 NE-B1100691%1 WDC-1881 LSI, SC 447 GE-NE-A166-1294-Rl WDC4490 LSI, SC 45K
. GE-NE-A166-1294-Rl
%DC%491 LSI, SC 45M GE-NE-A166-1294-Rl WDC4492 LSI, SC 45D GE-NE-A166-1294-Rl WDC4493 LSI, SC 45E GE-NE-A166-1294-RI WDC4494 LSI, SC 44F GE-NE-A166-1294-Rl WDC4495 LSI, SC Unirr.
WPS, 8/21/95 WDC4496 d
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 IP3571 1P3571 Linde 1092 Linde 1092 Linde 80 3958 3958 0344
.37
.75
.22 C.E., WQ Ml.43 CEOG Database WDC4500 f
C.E., WQ Ml.42 CEOG Database WDC4425 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 ofChemistry for Weld Wire Heat No. IP3571 1P3571 Linde 1092 Type Fiux New Evaluation Cu wt%
0.17
'0.15 0.17 0.17 0.18 0.19 0.19 0.186 0.20 0.19 0.172 0.34 0.22 0.191 0.066 0.24 0.182 0.354 0.207 0.2 0.43
'.23 0.209 0.22 0.434 0.196 0.21 0.223 Ni wt%
0.51 0.61 0.64 0.67 0.67 0.67 0.689 0.70 0.71 0.717 0.73 0.734 0.736 0.74 0.742 0.742 0.769 0.77 0.78 0.79 0.795 0.80 0.80 0.803 0.816 0.&71 CE PEDIGREE INDETERMNATENi INDETHMINATENi VALID VALID VALID VALID VALID VALID INDETERMINATECu7 VALID VALID VALID Flux Lot Number 3958 SOURCE LD.
ewau ee S WDC4426 WDC4427 WDC4428 WDC4429 WDC4430 WDC4431 WDC4432 WDC4433 WDC4434 WDC4435 WDC4436 WDC-0437 WDC4438 WDC4439 WDC4440 WDC4441 WDC4442 WDC4443 WDC4444 WDC4445 WDC4446 WDC@447 WDC4448 WDC4449 WDC4450 WDC4451 WDC4452 WDC4453 REPORT/ANALYSIS MSE-MNA-229 95 MSE-MNA-229 95 MSE-MNA-229 95 MSE-MNA-229 95 WCAP-14280 MSF MNA-229 95 MSE-MNA-229 95 MSE-MNA-229 95 Group Tag Avg. Cu wt%
Avg. Ni wt%
O. 2 tt of Coib
Table 2. Evaluation, ofChemistry for Weld Wire Heat No. 1P3571 1P3571 Linde 1092 Type F1uz Flur LotNumber 3958 hvg. Cu New Evaluation Avg. Nl
¹of wt%
wt%
CE PEDIGREE SOURCE LD.
REPORT/ANALYSIS Maine Yankee, Single Are Group Tag wt%
0.351 0.771 Coils 0.25>>
0.25'.33>>>>
0.33'>>
0.356 0.432 0.365 0.34 0.3 0.35 0.33 0.31 0.32 0.32 0.32 0.33 0.37 0.38 0.52 0.53 021>>>>>>
0.70>>
0.70>>>>
0.71>>>>
0.728 0.745 0.78 0.73 0.76 0.76 0.78 0.78 0.78 0.78 0.78 0.80 0.80 0.80 0.81 0.88 INDETERMNATE VALID VAI.II)
VALID VALID VALID VALID VALID VALID VALID VALID VALID WDC4454 WDC4455 WDC4456 WDC4457 WDCM58 WDC4460 WDC4463 WDC4468 WDC4469 WDC4470 WDC4471 WDC4472 WDC4473 WDC4474 WDC4475 WDC4476 WDCM77 WDC4478 WDC4479 WDC4480 WDC4481 BC L-585-21 BCL-585-21 BC L-585-21 BCL-585-21 WCAP-12819 WCAP-12819 D9693 D44441 D44440 D44447 D44448 D44442 D44439 D44451 D44453 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 ofChemistry for Neld %ire Heat No. 1P3571 Cu NI IP3571 Linde 1092 Type Flux Flux Lot Number 3958 Avg. Cu New Evaluation Avg. NI tt of wt%
0.20 0.22 0.20 0.20 0.22 0.20 0.21 0.21 0.2?
0.23 0.22 wt%
0.73 0.73 0.74 0.75 0.75 0.76 0.79 0.80 0.80
.0.80 0.82 0.83 CE PEDIGREE VALID VALID VALID VALID VALID SOURCE LD.
REPORT/ANALYSIS LaSaile-1, Tandem Arc WDC4483 WDC4485 WDC4486 WDC4487 WDC4488 WDC4490 WDC4491 WDC4492 WDC4493 WDC4494 WDC4495 Group Tag d
wt%
0.212 wt%
Coils 0.21 0.28 0.28 0.32 0.32 0.32 0.78 0.76 0.76 0.76 0.82 0,87 0.87 VALID INDETERMINATE INDETERMNATE
%DC4496 H
WDC4499 WDC-1879
%DC-1880 WDC-1881 atch-I, Tandem Arc WDC4497 WDC4498 D11341 NEDC-30997 NEDC-30997 NEDC-30997 NE-B110069141 NE-B110069141 NE-B1 10069141 0.304 0.807
Table 2. Evaluation ofChemistry for Weld Wire Heat No. 1P3571 1P3571 Nl Linde 1092 Type Flui Flux Lot Number 3958 hvg. Cu New Evaluation Avg. Nl
¹or wt%
0.37 wt%
0.75 CE PEDIGREE SOURCE LD.
REPORT/ANALYSIS Group Tag Weld Qualificatlon, Tandem Arc D8698 Weld Quafificatlon, Single Arc wt%
0.370 0.400 wt%
0.750 0.820 Coils 0.40 0.22 0.82 0.67 WDC4425 Weld Qualification, Llnde 80 Flux Type WDC4482 D8669 D19780 0.220 0.670 I
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:
'I Heat No.
Flux Type Flux Lot, Pct. Cu Pct. Ni Data Source Reference Source LD.
Group Tag 13253/12008 13253/12008 Linde 1092, Linde 1092 3791 3791
,.22
.22
.76
.76 C.E.
CEOG Database WDCAI55 CEOG Database WDCW156 13253/12008 Linde 1092
'3253/12008 Linde 1092, 13253/12008 Linde 1092, 13253/12008 Linde 1092 13253/12008 Linde 1092 13253/12008 Linde 1092 13253/12008 Lindh 1092 13253/12008 Linde 1092 13253/12008 Linde 1092 3791 3791 3791 3791 3791 3791 3791 3791 3791
.22
.22
.22
.22
.22
.22
.20
.20
.20
.77
.77
.78
.78
.78
.78
.86
.86 C.E.
C.E.
C.E.
C.E.
C.E CEOG Database WDC-0158 CEOG Database WDC-0159 CEOG Database WDC-0160 CEOG Database WDCW161 CEOG Database WDC162 CEOG Database WDCWI63 CEOG Database WDCW165 CEOG Database WDCA166 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 13253/1200&
Linde 1092 13253/12008 Linde 1092 13253/12008 Linde 1092 13253/12008 l.inde 1092 13253/12008 Linde 1092 13253/12008 13253/12008 Linde 1092 Linde 1092 13253/12008 Linde 1092 13253/12008 Linde 1092 13253/12008 Linde 1092 13253/12008 Linde 1092 13253/1200&
Linde 1092 13253/12008 Linde 1092 13253/1200&
Linde 1092
- 13253/12008 Linde 1092 CEOG Database 3791 3791 3791 3791 3791 3791 3791 3791 3791 3791 3791 3791 3791 3791 3791 3791
.20
.22
.20
.21
.21
.21
.22
.22
.22
.20
.20
.21
.21
.21
.21
.21
.87
.87
.88
.&8
.88
.&8
.88
.88
.88
.89
.&9
.89
.89
.89
.89
.89 C.E.
C.E.
C.E.
C.E.
C.E.
C.E.
C.E.
C.E.
C.E.
C.E.
C.E.
C.E.
C.E.
C.E.
CEOG Database WDC4168 CEOG Database WDC4169 CEOG Database WDC4170 CEOG Database WDC4 171 CEOG Database WDC4 172 CEOG Database WDC4173 CEOG Database WDC4174 CEOG Database WDC4175 CEOG Database WDC4176 CEOG Database WDC4177 CEOG Database WDC4178 CEOG Database WDC4179 CEOG Database WDC4180 CEOG Database WDC4181 CEOG Database WDC4182 CEOG Database WDC4183 b
9/10/97
Table 3. CEOG Chemistry Data forNeld 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 13253/12008 Linde 1092 13253/12008 Linde 1092 13253/12008 Linde 1092 13253/12008 Linde 1092 13253/12008 Linde 1092 13253/IZ008 Linde 1092 13253/12008
, Linde 1092 13253/12008 Linde 1092 13253/12008 Linde 1092 13253/12008 Linde 1092 13253/12008 Linde 1092 13253/12008 Linde 1092 13253/12008 Linde 1092 13253/12008 l.inde 1092 3791 3791 3791 3791 3791 3791 3791 3791 3791 3791 3791 3791 3791 3791 3791
.21
.22
.22
.20
.20
.20
.20
.21
.21
.21
.22
.22
.20
.20
.20
.89
.89
.90
.90
.90
.90
.90
.90
.90
.90
.91
.91
.91 C.E.
C.E.
C.E.
C.E.
C.E.
C.E.
C.E.
CEOG Database WDC4184 CEOG Database WDC4185 CEOG Database WDC4186 CEOG Database WDC4187 CEOG Database WDC4188 CEOG Database WDC4189 CEOG Database WDC4190 CEOG Database WDC4191 C.E.
~
C.E.
C.E.
C.E C.E.
C.E.
CEOG Database WDC4193 CEOG Database WDC4194 CEOG Database WDC4195 CEOG Database WDC4196 CEOG Database WDC4197 CEOG Database WDC4198 C.E.
CEOG Database WDC4192 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 13253/1200&
Linde 1092 13253/12008'inde 1092 13253/12008 Linde 1092 13253/12008 Linde 1092 13253/12008 Linde 1092 13253/12008 Linde 1092 3791
.20 3791
.20 3791
.21 3791
.20 3791
.20 3791 3791; 3833
.24
.91
.91
.91
.92
.92
.92
.875 C.E.
C.E.
C.E.
C.E.
C.E.
C.E.
C.E.
CEOG Database WDC4199 CEOG Database WDC4200 CEOG Database WDC4201 CEOG Database WDC4202 CEOG Database WDC4203 CEOG Database WDC4204 CEOG Database WDC4205 b
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 13253 13253 13253 13253 13253 13253 13253 Linde 1092 Linde 1092, Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 Linde 1092 3774, 3883 3774, 3883 3774, 3&83 3774, 3883 3774, 3883 3791 3791 3791
.14
.74
.27
.23
.71
.247
.728
.267
.728
.283
.732
.244
.734
.14
.72 PR-EDB PR-EDB PR-EDB PR-EDB PR-EDB CEOG Database WDC-0399 CEOG Database WDC-0400 CEOG Database WDC4401 CEOG Database WDC<402 CEOG Database WDCA403 C.E.
PR-EDB CEOG Database WDC<405 CEOG Database WDCO406 C.E.
CEOG Database WDCW404 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 forWeld Heat No. 1P3571 Plant Capsule ID.
{including source)
CG (wt%)
Ni (i>%%)
Irradiation Fluence Measured Temperature (x10'/cm')
AT~
(F)
(F)
Data Used in Assessing Vessel (Yor N)
Kewaunee Kewaunee Kewaunee Kewaunee V
0.219 R
0.219 P
0.219 S
0.219 0.724 0.724 0.724 0.724 532 532 532 532 597<'75
<'.81
<'35" 2 74 (>)
230 (<)
3.36 <'50 <'
Maine Yankee W263 0.351 Maine Yankee W253 0.351 Maine Yankee A25 0.351 Maine Yankee A35 0.351 0.771 0.771 0.771 0.771 533 542 522 533
.567 <')
222 <')
1.25 <')
1.76<'60<')
270 (I) 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 ofthe 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 Measured Adjusted Factor 'T~
hRT~z+
('F)
('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 Kewaunee Maine Yankee Maine Yankee 0.219 0.219
%263 0.351 W253 0.351 0.724 532 0.771 533 0.771 542 0.724
. 532 1.269 230 260.7 1.317 250 283.3 1.062 260 222.5 0.841 222 197.5 274.7 285.1-182.1 229.9
-14.0
-1.9 15.4.
~-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
"'~"
"forfluencevalues shown in Table 5
+'djusted hRTNDz =
Table CFM~
- Measured hRTNoz + (Tirrt,t.-Tirrc,~,)
Table CFG,~I,
'retjicted hRTNDT = FF
- 10.749 = 216.5'F
Table 7. Information Requested on RPV Weld Materials forPTS Evaluation Facility:
D. C. Cook 1
Vessel Manufacturer:
Combustion Engineering 32EFPYPeak(ID) Fluence:
1.41x10'/crn 32 EFPY AxialWeld (ID)Fluence: 9.5x10" n/cm RPV Weld Wire Heat"'est-Estimate Copper Best-Estimate Nickel (wt%)
(wt%)
EOL ID Fluence (x10 )
{n/cm')
Assigned Material Chemistry Factor (CF)
('F)
Method of Determining CFt'>-
('F)
=
Initial RTrior (RTiinr(U))
('F)
('F) a>
Margin
('F)
RTFrs at EOL
('F) 13253/12008 1P3571 0.21 0.287 0.873 0.756 0.95 1.41 208.7 218.6~i Tables Surv. Data
-56
'56 17 17 28 66 14 44 215.7 227.4 (1) weld heat number or the material identification ofthe limitingmaterial (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 ~
= 218.6 'F 214.0 21 1.9 Discu'ssion ofthe Anal si Method and Da a Used forE ch Weld Wire Heat Weld Wire Heat 13253/12008 IP3571 Discussion Simple mean Cu and Ni (see Table 3)
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 AxialWelds 2442 A,B&C 13253/12008
-56 208.7 9.5E+18 0.9856 205.7 66 215.7 Int. Shell Plate B4406-I Int. Shell Plate B4406-2 C1260 C3506 81.4 1.41E+19 33 104.5 1.41E+19 1.095 1.095 89.2 114.5 128.2 181.5 Int. Shell Plate B4406-3 C3506 Int. to Lovver Shell Circ. Weld 9442 IF3571 40 104 1.41E+19 1.095 113.9 218.6>>
239.4>>
-56 2@%
1.41E+19 1.095 2M6 44>>
66 187.9 227.4>>
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