ML082100458
| ML082100458 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 07/31/2008 |
| From: | Entergy Nuclear Operations |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| BWRVIP-135, Rev 1, JAFP-08-0067 | |
| Download: ML082100458 (18) | |
Text
Proprietary Information Withhold from Public Disclosure Pursuant to 10 CFR 2.390(a)(4)
ATTACHMENT 7 to JAFP-08-0067 Entergy Nuclear Operations, Inc.James A. FitzPatrick Nuclear Power Plant BWR Vessels and Internals, Project<.. i"'Ilntegrated Surveillance Program (ISP) Data ifor FitzPatrick" (Excerpted from BWRVIP-135, Revision 1)July, 2008 (Non-,proprietary Version)Attachments 2, 6, and 8 contain proprietary information as described in 10 CFR 2.390.When separated from these attachments this letter and its contents are non-proprietary.
Proprietary Information Withhold from Public Disclosure Pursuant to 10 CFR 2.390(a)(4)
ATTACHMENT 7 to JAFP-08-0067 CONTENTS 1) FitzPatrick BWRVIP-135 Excerpt (Non-proprietary Version)Cover Page BWRVIP-135 Pages 2-22 thru 2-23 BWRVIP-135 Pages A-18-1 thru A-18-7 BWRVIP-135 Pages B-13-1 thru B-13-6 16 Pages Attachments 2, 6, and 8 contain proprietary information as described in 10 CFR 2.390.When separated from these attachments this letter and its contents are non-proprietary.
BWR Vessel and Internals Project Integrated Surveillance Program (ISP) Data for FitzPatrick July 2008 Proprietary information is marked with margin bars Excerpted from BWRVIP-135, Revision 1 Proprietary Content Deleted Plant-Specific Evaluations FitzPatrick Representative Surveillance Materials The ISP Representative Surveillance Materials for the FitzPatrick vessel target weld and plates are shown in the following table.Table 2-31 Target Vessel Materials and ISP Representative Materials for FitzPatrick Target Vessel Materials ISP Representative Materials Weld Plate Summary of Available Surveillance Data: Plate The representative plate material-------
is contained in the following ISP capsules: Specific surveillance data related to plate heat ------- are summarized in Appendix A-7. One capsule containing this plate heat has been tested. The Charpy V-notch surveillance results are as follows: Table 2-32 T 3 0 Shift Results for Plate Heat -------No surveillance-based chemistry factor will be available until a second capsule is tested in 2010.Conclusions and Recommendations Because the representative plate material is not the same heat number as the target plate in the FitzPatrick vessel, the utility should use the chemistry factor from the Regulatory Guide 1.99, Rev. 2 tables (Regulatory Position 1.1) to determine the projected ART value for the target vessel plate. Recommended guidelines for evaluation of ISP surveillance data are provided in Section 3 of this Data Source Book.Excerpted from BWRVIP-135, Revision I Proprietary Content Deleted 2-22 Plant-Specific Evaluations Although the FitzPatrick surveillance plate ------- is not the representative plate material for the FitzPatrick plant, test data for the heat are available both from tested FitzPatrick surveillance capsules and from Supplemental Surveillance Program (SSP) capsules.
The irradiated data for------- from the --------------
capsules and SSP Capsules ----------
have been evaluated in Appendix A-18. The surveilldnce data should be considered when a revised ART is calculated for heat -.------ However, scatter in the surveillance data exceeds credibility criteria.
Also, the fitted CF- -, based on surveillance data) is higher than the Table CF------- , from the Reg. Guide 1.99 Rev. 2 tables). Therefore, the higher (fitted) CF should be used, along with a full margin term (the reduced margin term normally permitted withfa surveillance-based CF should not be used because credibility criteria are not satisfied).
Summary of Available Surveillance Data: Weld The representative weld material -------- is contained in the following ISP capsules:------- was recently identified as heat --.---- Specific surveillance data related to weld heat------- are presented in Appendix B-12 and the results are summarized below. Two capsules containing weld heat ------- have been tested. The Charpy V-notch surveillance results are as follows: Table 2-33 T 3 0 Shift Results for Weld Heat -------Cu NFlence Capsulen/cm 2 , E> I MeV) AT 3 0 (F)(wt%) j(wt%) (1017 unc e The results given in Appendix B-12 show a fitted chemistry factor (CF) of -------, as compared to a value of ------- from the chemistry tables in Reg. Guide 1.99, Rev. 2. The maximum scatter in the fitted data is well within the 1-sigma value of 28°F for welds as given in Reg. Guide 1.99, Rev. 2.Conclusions and Recommendations Because the representative weld material is not the same heat number as the target weld in the FitzPatrick vessel, the utility should use the chemistry factor from the Regulatory Guide 1.99, Rev. 2 tables to determine the projected ART value for the target vessel weld. However, ISP surveillance data for weld ------- (which has been identified as heat ------------
), provided in Appendix B-13, should be used to evaluate the ART for FitzPatrick vessel weld ------Recommended guidelines for evaluation of ISP surveillance data are provided in Section 3 of this Data Source Book.Excerpted from BWRVIP-135, Revision I Proprietary Content Deleted 2-23 ISP Plate Heat Evaluations A-18 Plate Heat -------Summary of Available Charpy V-Notch Test Data The available Charpy V-notch test data sets for plate heat ........ are listed in Table A-18-1.The' source documents for the data are provided, and the capsule designation and fluence values are also provided for irradiated data sets.Table A-18-1 ISP Capsules Containing Plate Heat -------Fluence Capsule (E> 1 MeV, 1017 n/cm 2) Reference______ I ______ [ ______The CVN test data for each set taken from the references noted above are presented in Tables A-18-7 through A-18-16. The BWRVIP ISP uses the hyperbolic tangent (tanh) function as a statistical curve-fit tool to model the transition temperature toughness data. Tanh curve, plots for each data set have been generated using CVGRAPH, Version 5 [A-18-5] and the plots are provided in Figures A-18-1 through A-18-10.Best Estimate Chemistry Table A- 18-2 details the best estimate average chemistry values for plate heat -------surveillance material.
Chemical compositions are presented in weight percent. If there are multiple measurements on a single specimen, those are first averaged to yield a single value for that specimen, and then the different specimens are averaged to determine the heat best estimate.Excerpted from BWRVIP-135, Revision 1 Proprietary Content Deleted A-18-1 ISP Plate Heat Evaluations Table A-1 8-2 Best Estimate Chemistry of Available Data Sets for Plate Heat----Cu Ni P S Si pcmn DSuc (Wt%) (Wt%)- (Wt%) (Wt%) (Wt.,)I Seie DSuc_____ I _____ _____ [ ____ I ____ I ___________________________
Calculation of Chemistry Factor (CF): The Chemistry Factor (CF) associated with the best estimate chemistry, as determined from U.S. NRC Regulatory Guide 1.99, Revision 2 [A-I 8-7], Table 2 (base metal), is:
...Effects of Irradiation The radiation induced transition temperature shifts for heat ------- are shown in Table A-18-3.The T 3 0 [30 ft-lb Transition Temperature], T 5 0 [50 ft-lb Transition Temperature], and T 3 5 mil [35 mil Lateral Expansion Temperature]
have been determined for each Charpy data set, and each irradiated set is compared to the baseline (unirradiated) index temperatures.
The change in Upper Shelf Energy (USE) is also shown. The unirradiated and irradiated values are taken from the CVGRAPH fits presented at the end of this sub-appendix (only CVN energy fits are presented).
Comparison of Actual vs. Predicted Embrittlement A predicted shift in the 30 ft-lb transition temperature (AT 3 0) is calculated for each irradiated data set using the Reg. Guide 1.99, Rev. 2, Regulatory Position 1.1 method. Table A-1 8-4 compares the predicted shift with the measured AT 3 0 (7F) taken from Table A-18-3.Decrease in USE Table A-18-5 shows the percent decrease in upper shelf energy (USE). The measured percent.decrease is calculated from the values presented in Table A-18-3.Excerpted from BWRVIP-135, Revision I Proprietary Content Deleted A-18-2 ISP Plate Heat Evaluations Table A-18-3 Effect of Irradiation (E>1.0 MeV) on the Notch Toughness Properties of Plate Heat T 3 0 , 30 ft-lb Ts 0 , 50 ft-lb T 3 5 mii, 35 mil Lateral CVN Upper Shelf Energy Material Capsule Transition Temperature Transition Temperature Expansion Temperature (USE)Identity ID Unirrad Irrad AT 3 0 Unirrad Irrad AT 5 0 Unirrad Irrad AT 3 5mil Unirrad Irrad Change.(OF) (OF) (OF) (OF) (*F) (OF) (OF) (OF) (OF) (ft-lb) (ft-lb) (ft-lb)Excerpted from BWRVIP-135, Revision 1 Proprietary Content Deleted A-18-3 ISP Plate Heat Evaluations Table A-18-4 Comparison of Actual Versus Predicted Embrittlement for Plate Heat -Capsule Fluence1 Identity Material (xl018 Fluence Measured Shift RG 1.99 Rev. 2 RG 1.99 Rev. 2 Predicted n/cm2) Factor OF Predicted Shift 2*F Shift+Margin OF 4 .1 I.4 4 I.4 4 t 4 4 t I I.1. L £ I L Notes: 1. See Table A-1 8-3, AT 3 0.2. Predicted shift = CF x FF, where CF is a Chemistry Factor taken from tables from USNRC Reg. Guide 1.99, Rev. 2, based on each material's Cu/Ni content, and FF is Fluence Factor, flo 2 M.1o log 1, where f = fluence (1019 n/cm 2 , E > 1.0 MeV).3. Margin = 2'4(ui 2 + ort), where a, = the standard deviation on initial RTNDT (which is taken to be 0°F), and YA is the standard deviation on ARTNDT (28 0 F for welds and 17 0 F for base materials, except that oA need not exceed 0.50 times the mean value of ARTNDT). Thus, margin is defined as 34 0 F for plate materials and 56=F for weld materials, or margin equals shift (whichever is less), per Reg. Guide 1.99, Rev. 2.Excerpted from BWRVIP-135, Revision 1 Proprietary Content Deleted A-18-4 ISP Plate Heat Evaluations Table A-18-5 Percent Decrease in Upper Shelf Energy (USE) for Plate Heat --I Capsule Identity Material Fluence (xl 0le n/cM 2)Cu Content Measured Decrease in USE 1 (wt%) (%)4 i*1 _______ ________________
Notes: 1. See Table A-18-3, (Change in USE)/(Unirradiated USE).Excerpted from BWRVIP-135, Revision 1 Proprietary Content Deleted A-18-5 ISP Plate Heat Evaluations Credibility of Surveillance Data The credibility of the surveillance data is determined according to the guidance of Regulatory Guide 1.99, Rev. 2 and 10 CFR 50.61, as supplemented by the NRC staff [A-18-8].
The following evaluation is based on the available surveillance data for irradiated plate heat -------The applicability of this evaluation to a particular BWR plant must be confirmed on a plant-by-plant basis to verify there are no plant-specific exceptions to the following evaluation.
Per Regulatory Guide 1.99, Revision 2 and 10 CFR 50.61, there are 5 criteria for the credibility.assessment.
Criterion 1: Materials in the capsules should be those judged most likely to be controlling with regard to radiation embrittlement.
In order to satisfy this criterion, the representative surveillance material heat number must match the material in the vessel.Criterion 2: Scatter in the plots of Charpy energy versus temperature for the irradiated and unirradiated conditions should be small enough to permit the determination of the 30 ft-lb temperature and upper shelf energy unambiguously.
Plots of Charpy energy versus temperature for the unirradiated and irradiated condition are presented in Figures A-18-1 through A- 18-10. Based on engineering judgment; the, scatter in these plots is small enough to permit the determination of the 30 ft-lb temperature and the upper shelf energy. Hence, this criterion is met.ýCriterion 3: When there are two or more sets of surveillance data from one reactor, the scatter of ARTNDT values about a best-fit line drawn as described in Regulatory Position 2.1 normally should be less than I7°F for plates. Even if the fluence range is large (two or more orders of magnitude), the scatter should not exceed twice that value. Even if the data fail this criterion for use in shift calculations, they may be credible for determining decrease in upper shelf energy if the upper shelf can be clearly determined, following the definition given in ASTM E185-82 [A-18-9].For plate material -----, there are surveillance capsule data sets currently available.
The functional form of the least squares fit method as described in Regulatory Position 2.1 is utilized to determine a best-fit line for this data and to determine if the scatter of these ARTNDT values about this line is less than 17°F for plates. Figure A-18-11 presents the best-fit line as described in Regulatory Position 2.1 utilizing the shift prediction routine from CVGRAPH, Version 5.0.2.The scatter of ARTNDT values about the functional form of the best-fit line drawn as described in Regulatory Position 2.1 is presented in Table A- 18-6.Excerpted from BWRVIP-135, Revision I Proprietary Content Deleted A-18-6 ISP Plate Heat Evaluations Table A-18-6 Best Fit Evaluation for Surveillance Plate Heat -------Note: 1.- ----Table A-18-6 indicates that the scatter is not within acceptable range for credible surveillance data. Therefore, plate heat ------- does not meet this criterion.
Criterion
- 4. The irradiation temperature of the Charpy specimens in the capsule should match the vessel wall temperature at the cladding/base metal interface within + / -25°F.BWRVIP-78
[A-18-11 ] established the similarity of BWR plant environments in the BWR fleet. The annulus between the wall and the core shroud in the region of the surveillance capsules contains a mix of water returning from the core and feedwater.
Depending on feedwater temperature, this annulus region is between 525°F and 535°F. This location of specimens with respect to the reactor vessel beltline is designed so that the reactor vessel wall and the specimens experience equivalent operating conditions such that the temperature will not differ by more than 25°F. Any plant-specific exceptions to this generic analysis should be evaluated.
Criterion 5: The surveillance data for the correlation monitor material in the capsule should fall within the scatter band of the database for that material.Few ISP capsules-contain correlation monitor material.
Generally, this criterion is not applicable.
For plate heat -----, the applicable credibility criteria are not satisfied.
However, because the fitted CF is higher than the CF from the Reg. Guide 1.99 Rev. 2 tables, this higher CF must le used, but the reduced margin term normally permitted with a surveillance-based CF should not be used.Excerpted from BWRVIP-135, Revision 1 Proprietary Content Deleted A-18-7 ISP Weld Heat Evaluations B-13 Weld Heat: ----------
Summary of Available Charpy V-Notch Test Data The available Charpy V-notch test data sets for weld heat ------- are listed in Table B-13-1.The source documents for the data are provided, and the capsule designations and fluence values are also provided for irradiated data sets.Table B-13-1 ISP Capsules Containing Weld Heat -------Capsule Fluence (E> 1 MeV, 1017 n/cm 2) Reference------- has been identified as a tandem submerged arc weld fabricated with weld wire Heats '---- and ----- and ---------------
[Reference B-13-9].The CVN test data for each set taken from the references noted above are presented in Tables B-13-7 through B-1 3-9. The BWRVIP ISP uses the hyperbolic tangent (tanh) function as a statistical curve-fit tool to model the transition temperature toughness data. Tanh curve plots for each data set have been generated using CVGRAPH, Version 5 [Reference B-13-3] and the'plots are provided in Figures B-13-1 through B-13-3.Best Estimate Chemistry Table B-13-2 details the best estimate average chemistry values for weld heat ---------surveillance material.
Chemical compositions are presented in weight percent. If there are multiple measurements on a single specimen, those are first averaged to yield a single value for that specimen, and then the different specimens are averaged to determine the heat best estimate.Table B-13-2 Best Estimate Chemistry of Available Data Sets for Weld Heat -------Cu Ni P S Si Specimen ID Source (wt%) (wt%) (wt%) (wt%) (wt%)Excerpted from BWRVIP-135, Revision I Proprietary Content Deleted B-13-1 ISP Weld Heat Evaluations Calculation of Chemistry Factor (CF): The Chemistry Factor (CF) associated with the best estimate chemistry, as determined from U.S.NRC Regulatory Guide 1.99, Revision 2 [Reference B-13-5], Table I (weld metal), is: CF -----------
Effects of Irradiation The radiation induced transition temperature shifts for heat ------- are shown in Table B-13-3. The T 3 0 [30 ft-lb Transition Temperature], T 5 0 [50 ft-lb Transition Temperature], and T35mil [35 mil Lateral Expansion Temperature]
have been determined for each Charpy data set, and each irradiated set is compared to the baseline (unirradiated) index temperatures.
The change in Upper Shelf Energy (USE) is also shown. The unirradiated and irradiated values are taken from the CVGRAPH fits presented at the back of this sub-appendix (only CVN energy fits are presented).
Comparison of Actual vs. Predicted Embrittlement A predicted shift in the 30 ft-lb transition temperature (AT 3 0) is calculated for each irradiated data set using the Reg. Guide 1.99, Rev. 2, Regulatory Position 1.1 method. Table B-13-4 compares the predicted shift with the measured AT 3 0 ('F) taken from Table B-13-3.Decrease in USE Table B-13-5 shows the percent decrease in upper shelf energy (USE). The measured percent decrease is calculated from the values presented in Table B-13-3.I B-13-2 Excerpted from BWRVIP-135, Revision I Proprietary Content Deleted ISP Weld Heat Evaluations Table B-13-3 Effect of Irradiation (E>1.0 MeV) on the Notch Toughness Properties of Weld Heat--T 3 o, 30 ft-lb T 5 o, 50 ft-lb T 3 5mil, 35 mil Lateral Transition Transition Expansion
.USE)Material Capsule Temperature Temperature Temperature (USE)Identity ID Unirrad Irrad AT 3 0 Unirrad Irrad AT 5 o. Unirrad Irrad AT 3 smil Unirrad Irrad Change (OF) (OF) (OF) (OF) (OF) (OF) (OF) (OF) (OF) (ft-lb) (ft-lb) (ft-lb)Table B-13-4 Comparison of Actual Versus Predicted Embrittlement for Weld Heat Measured RG 1.99 Rev. 2 RG 1.99 Rev. 2 Fluence h Predicted Capsule Identity Material (x10 1' nicm 2) Shift1 Predicted Shift2 Shift+Margin 2 , 3 oF OF O Notes: 1. See Table B-13-3, AT 3 0.2. Predicted shift = CF x FF, where CF is a Chemistry Factor taken from tables from USNRC Reg. Guide 1.99, Rev. 2, based on each material's Cu/Ni content, and FF is Fluence Factor, tO.2 M-$J "0, 1, where f= fluence (101' n/cm 2 , E> 1.0 MeV).3. Margin = 24(oj'+ aA 2), where a( = the standard deviation on initial RTNDT (which is taken to be 0 0 F), and a& is the standard deviation on ARTNDT (28 0 F for welds and 17 0 F for base materials, except that (A need not exceed 0.50 times the mean value of ARTNDT). Thus, margin is defined as 34°F for weld materials and 56'F for weld materials, or margin equals shift (whichever is less), per Reg. Guide 1.99, Rev. 2.Excerpted from BWRVIP-135, Revision 1 Proprietary Content Deleted B-13-3 ISP Weld Heat Evaluations Table B-13-5 Percent Decrease in Upper Shelf Energy (USE) for Weld Heat -_Capsule Identity Fluence Measured Material (x1O" n/cm') Cu Content (wt%) Decrease in USE'1NU Notes: 1. See Table B-13-3, (Change in USE)/(Unirradiated USE).B-13-4 Excerpted from BWRVIP-135, Revision 1 Proprietary Content Deleted ISP Weld Heat Evaluations Credibility of Surveillance Data The credibility of the surveillance data is determined according to the guidance of Regulatory Guide 1.99, Rev. 2 and 10 CFR 50.61, as supplemented by the NRC staff [Reference B-13-6]The following evaluation is based on the available surveillance data for irradiated weld heat-.......-
The applicability of this evaluation to a particular BWR plant must be confirmed on a plant-by-plant basis to verify there are no plant-specific exceptions to the following evaluation.
Per Regulatory Guide 1.99, Revision 2 and 10 CFR 50.61, there are 5 criteria for the credibility assessment.
Criterion 1: Materials in the capsules should be those judged most likely to be controlling with regard to radiation embrittlement.
In order to satisfy this criterion, the representative surveillance material heat number must match the material in the vessel.Criterion 2: Scatter in the plots of Charpy energy versus temperature for the irradiated and unirradiated conditions should be small enough to permit the determination of the 30 ft-lb temperature and upper shelf energy unambiguously.
Plots of Charpy energy versus temperature for the unirradiated and irradiated condition are presented in thissub-appendix.
Based on engineering judgment, the scatter in these plots is small enough to permit the determination of the 30 ft-lb temperature and the upper shelf energy. Hence, this criterion is met.Criterion 3: When there are two or more sets of surveillance data from one reactor, the scatter of ARTNDT values about a best-fit line drawn as described in Regulatory Position 2.1 normally should be less than 28°F for welds. Even if the fluence range is large (two or more orders of magnitude), the scatter should not exceed twice that value. Even if the data fail this criterion for use in shift calculations, they may be credible for determining decrease in upper shelf energy if the upper shelf can be clearly determined, following the definition given in ASTM E185-82[Reference B-I13-7].For weld material -----, there are surveillance capsule data sets currently available.
The functional form of the least squares fit method as described in Regulatory Position 2.1 is utilized to determine a best-fit line for this data and to determine if the scatter of these ARTNDT values about this line is less than 28°F for welds. Figure B-I 3-4 presents the best-fit line as described in RegulatoryPosition
2.1 utilizing
the shift prediction routine from CVGRAPH, Version 5.0.2.The scatter of ARTNDT values about the functional form of the best-fit line drawn as described in Regulatory Position 2.1 is presented in Table B-13-6.Excerpted from BWRVIP-135, Revision 1 Proprietary Content Deleted B-13-5 ISP Weld Heat Evaluations Table B-13-6 Best Fit Evaluation for Surveillance Weld Heat --------L Table B-I 3-6 indicates that the scatter is within acceptable range for credible surveillance data. Therefore, weld heat ------- meets this criterion.
Criterion 4.',The irradiation temperature of the Charpy specimens in the capsule should match the vessel wall temperature at the cladding/base metal interface within +/- 25°F.BWRVIP-78
[Reference B-13-8] established the similarity of BWR plant environments in the BWR fleet. The annulus between the wall and the core shroud in the region of the surveillance capsules contains a mix of water returning from the core and feedwater.
Depending on feedwater temperature, this annulus region is between 525°F and 535°F. This location of specimens with respect to the reactor vessel beltline is designed so that the reactor vessel wall and the specimens experience equivalent operating conditions such that the temperature will not differ by more than 25°F. Any plant-specific exceptions to this generic analysis should be evaluated.
Criterion
- 5. The surveillance data for the correlation monitor material in the capsule should fall within the scatter band of the database for that material.Few ISP capsules contain correlation monitor material.
Generally, this criterion is not applicable.
For weld heat-, these criteria are satisfied (or not applicable).
The surveillance data are nominally credible because the scatter criterion is met. Prior to application of the data, a plant should verify that no plant-specific exceptions to these criteria exist.Table B-13-7 Unirradiated Charpy V-Notch Results for Surveillance Weld -------Spec ID Temp (VF) CVN (ft-lb) LE (mils) %Shear 2 S 3*4 5 6 7 8 9*Percent shear not determined.
B-13-6 Excerpted from BWRVIP-135, Revision I Proprietary Content Deleted