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{{#Wiki_filter:* e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 Februarf 24, 1999 United States Nuclear Regulatory Commission Attention:
{{#Wiki_filter:*
Document Control Desk Washington, D. C. 20555-0001 Gentlemen:
e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 Februarf 24, 1999 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555-0001 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 Serial No. NAF/JRH Docket Nos. License Nos. 99-034 RO 50-280, 281 DPR-32, 37 SUPPLEMENT TO RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION (RAI) ON GENERIC LETTER 92-01, REVISION 1, SUPPLEMENT 1 By letter dated June 18, 1998, Virginia Electric and Power Company (Virginia Power) provided a response to an NRC Request for Additional Information (RAI) on Generic Letter 92-01, Revision 1, Supplement
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 Serial No.
: 1. The information provided was organized in a manner consistent with the NRC's draft RAI on Generic Letter 92-01, Revision 1, Supplement 1, and the B&W Owners Group (BWOG) Reactor Vessel Working Group (RVWG) generic response to the NRC RAI. The calculations which supported the information presented in these tables were performed in accordance with Regulatory Guide 1.99, Revision 2, the Pressurized Thermal Shock Rule in 10 CFR 50.61, and the regulatory guidance provided in the meeting minutes from the November 12, 1997 NRG/Industry meeting on reactor vessel integrity.
NAF/JRH Docket Nos.
During the preparation of a coordinated BWOG response to an NRC RAI regarding changes in reported transition temperature shift values, Framatome Technologies, Inc. (FTI) discovered errors in previously reported data. The errors occurred during the performance of hyperbolic tangent curve-fitting of Charpy test data from several analyzed surveillance capsules.
License Nos.
Framatome has since corrected the data errors and Virginia Power has incorporated the corrected transition temperature shift values (determined by hyperbolic tangent curve-fit) into calculations that confirm the conservatism of 1) the licensing basis heatup and cooldown limit curves, 2) the associated Low Temperature Overpressure Protection System (L TOPS) setpoint and enabling temperature, and 3) the 10 CFR 50.61 Pressurized Thermal Shock (PTS} screening calculations.
99-034 RO 50-280, 281 DPR-32, 37 SUPPLEMENT TO RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION (RAI) ON GENERIC LETTER 92-01, REVISION 1, SUPPLEMENT 1 By {{letter dated|date=June 18, 1998|text=letter dated June 18, 1998}}, Virginia Electric and Power Company (Virginia Power) provided a response to an NRC Request for Additional Information (RAI) on Generic Letter 92-01, Revision 1, Supplement 1. The information provided was organized in a manner consistent with the NRC's draft RAI on Generic Letter 92-01, Revision 1, Supplement 1, and the B&W Owners Group (BWOG) Reactor Vessel Working Group (RVWG) generic response to the NRC RAI. The calculations which supported the information presented in these tables were performed in accordance with Regulatory Guide 1.99, Revision 2, the Pressurized Thermal Shock Rule in 10 CFR 50.61, and the regulatory guidance provided in the meeting minutes from the November 12, 1997 NRG/Industry meeting on reactor vessel integrity.
A discussion of the changes to the previously reported surveillance results is provided in the attachment, and the resu~s-~ the-~vi:;
During the preparation of a coordinated BWOG response to an NRC RAI regarding changes in reported transition temperature shift values, Framatome Technologies, Inc.
:':~l~t: are reported in Appendix A to fue atta;m;~ 2, t I 1 ( ~ia 30~Ba~~ ii&aa~ao\  
(FTI) discovered errors in previously reported data.
' p PDR -*
The errors occurred during the performance of hyperbolic tangent curve-fitting of Charpy test data from several analyzed surveillance capsules. Framatome has since corrected the data errors and Virginia Power has incorporated the corrected transition temperature shift values (determined by hyperbolic tangent curve-fit) into calculations that confirm the conservatism of 1) the licensing basis heatup and cooldown limit curves, 2) the associated Low Temperature Overpressure Protection System (L TOPS) setpoint and enabling temperature, and 3) the 10 CFR 50.61 Pressurized Thermal Shock (PTS} screening calculations. A discussion of the changes to the previously reported surveillance results is provided in the attachment, and the resu~s-~ the-~vi:; :':~l~t: are reported in Appendix A to fue atta;m;~ 2, t I 1
,. This information supplements the information previously reported in the June 18, 1998 letter. noted above. Please contact us if you have any questions or require additional information.
(  
Very truly yours, ~rf L. N. Hartz Vice President  
~ia30~Ba~~ ii&aa~ao\\ '
-Nuclear Engineering and Services Attachment Commitments made in this letter: None. cc: US Nuclear Regulatory Commission Region II Atlanta Federal Center 61 Forsyth Street, S.W., Suite 23T85 Atlanta, Georgia 30303 Mr. R. A. Musser NRC Senior Resident Inspector Surry Power Station COMMONWEAL TH OF VIRGINIA COUNTY OF HENRICO ) ) ) e The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by L. N. Hartz, who is Vice President  
p PDR -*  
-Nuclear Engineering  
 
& Services, for J.P. O'Hanlon, who is Senior Vice President  
This information supplements the information previously reported in the {{letter dated|date=June 18, 1998|text=June 18, 1998 letter}}. noted above.
-Nuclear, of Virginia Electric and Power Company. She has affirmed before me that she is duly authorized to execute and file the foregoing document in behalf of that Company, and that the statements in the document are true to the best of her knowledge and belief. Acknowledged before me this d 4 T.bday of jJ.nuoNJc , 19 qq . 0 My Commission Expires: March 31, 2000. ~Tu~ Notary Public (SEAL)
Please contact us if you have any questions or require additional information.
. Attachment Supplement To Response To NRC Request For Additional Information (RAI) On Generic Letter 92-01 Revision 1 Supplement 1 Surry Power Station Units 1 and 2 Discussion of Changes to Previously Reported Surveillance Results Surveillance data was considered in Reference (1) for evaluation of reactor vessel beltline welds fabricated with the following weld wires:
Very truly yours,  
* 72445 (Surry Unit 1 weld materials SA-1.585 and SA-1650, and Surry Unit 2 weld material SA-1585),
~rf L. N. Hartz Vice President - Nuclear Engineering and Services Attachment Commitments made in this letter: None.
* 299L44 (Surry Unit 1 weld material SA-1526), and
cc:
* 0227 (Rotterdam-fabricated Surry Unit 2 weld material R3008). Surveillance data for weld wire 72445 was available from both Westinghouse and B&W irradiations.
US Nuclear Regulatory Commission Region II Atlanta Federal Center 61 Forsyth Street, S.W., Suite 23T85 Atlanta, Georgia 30303 Mr. R. A. Musser NRC Senior Resident Inspector Surry Power Station  
In the case of weld wire 72445, the Westinghouse data was considered more applicable to the plant, since it required fewer corrections for irradiation temperature and chemical composition differences.
 
The Westinghouse data was determined to be credible in accordance with RG 1.99, Revision 2 (5), as supplemented by Reference (7). After appropriate corrections for irradiation temperature and chemical composition differences, the Westinghouse data was used to evaluate the Surry Units 1 and 2 beltline materials fabricated with weld wire 72445 (i.e., SA-1585 and SA-1650).
COMMONWEAL TH OF VIRGINIA COUNTY OF HENRICO  
Surveillance data for weld wire 299L44 was also available from both Westinghouse and B&W irradiations.
)  
In the case of weld wire 299L44, the Westinghouse data (which was Surry Unit 1 plant-specific surveillance data) was again considered more applicable to the plant, since it required fewer corrections for irradiation temperature and chemical composition differences.
)  
However, the Westinghouse data was determined to be credible in accordance with RG 1.99, Revision 2 (5), as supplemented by Reference (7). Other possible combinations of Westinghouse and: B&W surveillance data were evaluated for credibility, but each combination was determined to be non-credible.
)
Since no credible data was identified, the Regulatory Guide 1.99, Revision 2, Position 1.1 chemistry factor was evaluated, and was determined to be conservative in accordance with guidance provided in Reference (7). Therefore, the Position 1.1 chemistry factor was used in the evaluation of the Surry Unit 1 beltline material fabricated from weld wire 299L44 (i.e., SA-1526).
e The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by L. N. Hartz, who is Vice President -
Surveillance data for weld wire 0227 was available only from the Surry Unit 2 specific surveillance program. The surveillance data was determined to be credible in accordance with RG 1.99, Revision 2 (5), as supplemented by Reference (7). For application of the surveillance data to the beltline weld material, no corrections for irradiation temperature or chemical composition differences were applied, since (a) the surveillance data were irradiated in the reactor vessel which was being evaluated (i.e., Surry Unit 2) and (b) the chemical composition of the surveillance specimens was Page 1 of 7 e e essentially the same as the best-estimate chemical composition of the beltline material being evaluated (i.e., weld R3008). :_ Based on a review of Reference (8), the following changes were incorporated into the data previously reported in Reference (1). For weld wire 72445 (weld materials SA-1585 and SA-1650):
Nuclear Engineering & Services, for J.P. O'Hanlon, who is Senior Vice President  
* The fluence values for Westinghouse (i.e., Point Beach Unit 1) irradiations have been changed to those reported in Reference (8) (The fluence values presented in Reference (8) were obtained from Reference (11 ).)
- Nuclear, of Virginia Electric and Power Company. She has affirmed before me that she is duly authorized to execute and file the foregoing document in behalf of that Company, and that the statements in the document are true to the best of her knowledge and belief.
* The 30 ft-lb transition temperature shift value for Point Beach Unit 1 Capsule R (PB1-R) has been changed from 181°Fto 155°F.
Acknowledged before me this d 4 T.bday of jJ.nuoNJc, 19 qq.
* The 30 ft-lb transition temperature shift value for Capsule CR3-LG1 has been changed from 141 °F to 139 °F.
0 My Commission Expires: March 31, 2000.  
* The 30 ft-lb transition temperature shift value for Capsule CR3-LG2 has been changed from 156°F to 164°F. For weld wire 299L44 (weld material SA-1526):
~Tu~
* The 30 ft-lb transition temperature shift value for Capsule CR3-LG1 (BWOG CR-3 irradiation) has been changed from 205°F to 202°F. For weld wire 0227 (Rotterdam weld material R3008):
Notary Public (SEAL)  
* The 30 ft-lb transition temperature shift value for Capsule X (Surry Unit 2 irradiation) has been changed from 95°F to 96°F.
 
* The 30 ft-lb transition temperature shift value for Capsule V (Surry Unit 2 irradiation) has been changed from 145°F to 140°F. Impact of Surveillance Data Changes on Calculated Chemistry Factor The aforementioned changes to surveillance data for weld wire 72445 (weld materials SA-1585 and SA-1650) caused the Westinghouse surveillance data set, previously
~.
* determined to be credible, to become non-credible. (One of the four data points exceeded the 1cr (28°F) credibility criterion by 2°F.) When the combined Westinghouse and B&W data were evaluated for credibility, five of the six data points were within the 1 cr (28°F) credibility criterion.
Attachment Supplement To Response To NRC Request For Additional Information (RAI) On Generic Letter 92-01 Revision 1 Supplement 1 Surry Power Station Units 1 and 2 Discussion of Changes to Previously Reported Surveillance Results Surveillance data was considered in Reference (1) for evaluation of reactor vessel beltline welds fabricated with the following weld wires:
This data set is considered credible in accordance with NRC guidance provided in Case 5 of Reference (7). Therefore, this data was used to evaluate the Surry Units 1 and 2 SA-1585 and SA-1650 beltline weld materials.
72445 (Surry Unit 1 weld materials SA-1.585 and SA-1650, and Surry Unit 2 weld material SA-1585),
Corrections for chemical composition and irradiation temperature differences between the surveillance and beltline materials were applied in accordance with guidance provided in Reference (7). A . correction for irradiation temperature difference was applied to a measured value of transition temperature shift only if application of the correction increased the transition temperature shift value. Page 2 of 7
299L44 (Surry Unit 1 weld material SA-1526), and 0227 (Rotterdam-fabricated Surry Unit 2 weld material R3008).
* e The aforementioned change to surveillance data for weld wire 299L44 (weld material SA-1526) had virtually no impact on the RG 1.99, Revision 2, Position 2.1, chemistry fact~r calculations.
Surveillance data for weld wire 72445 was available from both Westinghouse and B&W irradiations. In the case of weld wire 72445, the Westinghouse data was considered more applicable to the plant, since it required fewer corrections for irradiation temperature and chemical composition differences. The Westinghouse data was determined to be credible in accordance with RG 1.99, Revision 2 (5), as supplemented by Reference (7). After appropriate corrections for irradiation temperature and chemical composition differences, the Westinghouse data was used to evaluate the Surry Units 1 and 2 beltline materials fabricated with weld wire 72445 (i.e., SA-1585 and SA-1650).
The possible combinations of Westinghouse and B&W surveillance  
Surveillance data for weld wire 299L44 was also available from both Westinghouse and B&W irradiations. In the case of weld wire 299L44, the Westinghouse data (which was Surry Unit 1 plant-specific surveillance data) was again considered more applicable to the plant, since it required fewer corrections for irradiation temperature and chemical composition differences. However, the Westinghouse data was determined to be non-credible in accordance with RG 1.99, Revision 2 (5), as supplemented by Reference (7).
*. data -were evaluated for credibility, but each combination was determined to be credible.
Other possible combinations of Westinghouse and: B&W surveillance data were evaluated for credibility, but each combination was determined to be non-credible.
Since no credible data was identified, the Regulatory Guide 1.99., Revision 2, Position 1.1, chemistry factor was evaluated, and was determined to be conservative in accordance with guidance provided in Reference (7). Therefore, the Position 1.1 chemistry factor was used in the evaluation of the Surry Unit 1 beltline material fabricated from weld wire 299L44 (i.e., SA-1526).
Since no credible data was identified, the Regulatory Guide 1.99, Revision 2, Position 1.1 chemistry factor was evaluated, and was determined to be conservative in accordance with guidance provided in Reference (7).
The aforementioned changes to surveillance data for weld wire 0227 (Rotterdam weld material R3008) caused the RG 1.99, Revision 2, Position 2.1, chemistry factor to change from 128.0°F to 125.2°F. Evaluation of Existing Prr Limits and L TOPS Setpoints Appendix A presents Reactor Vessel Material Data Tables for Surry Units 1 and 2 which include consideration of the corrected transition temperature shift values and neutron fluences presented in BAW-2325, Supplement 1 (8). The information in the Appendix A data tables is organized in a manner consistent with the NRC's draft RAI on Generic Letter 92-01, Revision 1, Supplement 1 (3), and the B&W Owners Group (BWOG) Reactor Vessel Working Group (RVWG) generic response to the NRC RAI on Generic Letter 92-01, Revision 1, Supplement 1 (4). The calculations which support the information presented in these tables were performed in accordance with Regulatory Guide 1.99, Revision 2 (5), the Pressurized Thermal Shock Rule in 10 CFR 50.61 (6), and the regulatory guidance provided in the meeting minutes from the November 12, 1997 NRG/Industry meeting on reactor vessel integrity (7). The existing Surry Units 1 and 2 Prr limits and L TOPS setpoints (9)(10) are based on a limiting %-thickness
Therefore, the Position 1.1 chemistry factor was used in the evaluation of the Surry Unit 1 beltline material fabricated from weld wire 299L44 (i.e., SA-1526).
(%-T) RT NDT of 228.4°F. This value of RT NDT was determined to bound all Surry Units 1 and 2 reactor vessel beltline materials at end-of-license (EOL) fluences corresponding to 28.8 EFPY and 29.4 EFPY for Surry Units 1 and 2, respectively (9)(10). After consideration of the aforementioned changes to previously reported surveillance data, the most limiting %-T RTNoT vaiue for Surry Units 1 and 2 is 215.7°F. This value of RT NDT was determined on the basis of fluence values corresponding to 29.6 EFPY and 30.1 EFPY for Surry Units 1 and 2, respectively (12). On the basis of the results presented in Appendix A, it is concluded that the existing RCS Prr limits and L TOPS setpoints (2)(3) remain valid and conservative.
Surveillance data for weld wire 0227 was available only from the Surry Unit 2 plant-specific surveillance program. The surveillance data was determined to be credible in accordance with RG 1.99, Revision 2 (5), as supplemented by Reference (7).
Evaluation of PTS Screening Calculations PTS screening calculations were previously transmitted to the NRC by letter dated April 1, 1996 (13). All Surry Units 1 and 2 reactor vessel beltline materials demonstrated margin to the 10 CFR 50.61 screening criteria at end-of-license (EOL) fluences corresponding to 28.8 EFPY and 29.4 EFPY for Surry Units 1 and 2, respectively (13). On the basis of the results presented in Appendix A, it is concluded that all Surry Units 1 and 2 beltline Page 3 of 7
For application of the surveillance data to the beltline weld material, no corrections for irradiation temperature or chemical composition differences were applied, since (a) the surveillance data were irradiated in the reactor vessel which was being evaluated (i.e.,
Surry Unit 2) and (b) the chemical composition of the surveillance specimens was Page 1 of 7  
 
e e
essentially the same as the best-estimate chemical composition of the beltline material being evaluated (i.e., weld R3008).
:_ Based on a review of Reference (8), the following changes were incorporated into the data previously reported in Reference (1). For weld wire 72445 (weld materials SA-1585 and SA-1650):
The fluence values for Westinghouse (i.e., Point Beach Unit 1) irradiations have been changed to those reported in Reference (8)
(The fluence values presented in Reference (8) were obtained from Reference (11 ).)
The 30 ft-lb transition temperature shift value for Point Beach Unit 1 Capsule R (PB1-R) has been changed from 181°Fto 155°F.
The 30 ft-lb transition temperature shift value for Capsule CR3-LG1 has been changed from 141 °F to 139 °F.
The 30 ft-lb transition temperature shift value for Capsule CR3-LG2 has been changed from 156°F to 164°F.
For weld wire 299L44 (weld material SA-1526):
The 30 ft-lb transition temperature shift value for Capsule CR3-LG1 (BWOG CR-3 irradiation) has been changed from 205°F to 202°F.
For weld wire 0227 (Rotterdam weld material R3008):
The 30 ft-lb transition temperature shift value for Capsule X (Surry Unit 2 irradiation) has been changed from 95°F to 96°F.
The 30 ft-lb transition temperature shift value for Capsule V (Surry Unit 2 irradiation) has been changed from 145°F to 140°F.
Impact of Surveillance Data Changes on Calculated Chemistry Factor The aforementioned changes to surveillance data for weld wire 72445 (weld materials SA-1585 and SA-1650) caused the Westinghouse surveillance data set, previously
* determined to be credible, to become non-credible. (One of the four data points exceeded the 1cr (28°F) credibility criterion by 2°F.) When the combined Westinghouse and B&W data were evaluated for credibility, five of the six data points were within the 1 cr (28°F) credibility criterion. This data set is considered credible in accordance with NRC guidance provided in Case 5 of Reference (7). Therefore, this data was used to evaluate the Surry Units 1 and 2 SA-1585 and SA-1650 beltline weld materials. Corrections for chemical composition and irradiation temperature differences between the surveillance and beltline materials were applied in accordance with guidance provided in Reference (7).
A  
. correction for irradiation temperature difference was applied to a measured value of transition temperature shift only if application of the correction increased the transition temperature shift value.
Page 2 of 7  
 
e The aforementioned change to surveillance data for weld wire 299L44 (weld material SA-1526) had virtually no impact on the RG 1.99, Revision 2, Position 2.1, chemistry fact~r calculations. The possible combinations of Westinghouse and B&W surveillance  
*. data -were evaluated for credibility, but each combination was determined to be non-credible. Since no credible data was identified, the Regulatory Guide 1.99., Revision 2, Position 1.1, chemistry factor was evaluated, and was determined to be conservative in accordance with guidance provided in Reference (7).
Therefore, the Position 1.1 chemistry factor was used in the evaluation of the Surry Unit 1 beltline material fabricated from weld wire 299L44 (i.e., SA-1526).
The aforementioned changes to surveillance data for weld wire 0227 (Rotterdam weld material R3008) caused the RG 1.99, Revision 2, Position 2.1, chemistry factor to change from 128.0°F to 125.2°F.
Evaluation of Existing Prr Limits and L TOPS Setpoints Appendix A presents Reactor Vessel Material Data Tables for Surry Units 1 and 2 which include consideration of the corrected transition temperature shift values and neutron fluences presented in BAW-2325, Supplement 1 (8). The information in the Appendix A data tables is organized in a manner consistent with the NRC's draft RAI on Generic Letter 92-01, Revision 1, Supplement 1 (3), and the B&W Owners Group (BWOG) Reactor Vessel Working Group (RVWG) generic response to the NRC RAI on Generic Letter 92-01, Revision 1, Supplement 1 (4).
The calculations which support the information presented in these tables were performed in accordance with Regulatory Guide 1.99, Revision 2 (5), the Pressurized Thermal Shock Rule in 10 CFR 50.61 (6), and the regulatory guidance provided in the meeting minutes from the November 12, 1997 NRG/Industry meeting on reactor vessel integrity (7).
The existing Surry Units 1 and 2 Prr limits and L TOPS setpoints (9)(10) are based on a limiting %-thickness (%-T) RT NDT of 228.4°F. This value of RT NDT was determined to bound all Surry Units 1 and 2 reactor vessel beltline materials at end-of-license (EOL) fluences corresponding to 28.8 EFPY and 29.4 EFPY for Surry Units 1 and 2, respectively (9)(10). After consideration of the aforementioned changes to previously reported surveillance data, the most limiting %-T RTNoT vaiue for Surry Units 1 and 2 is 215.7°F.
This value of RT NDT was determined on the basis of fluence values corresponding to 29.6 EFPY and 30.1 EFPY for Surry Units 1 and 2, respectively (12). On the basis of the results presented in Appendix A, it is concluded that the existing RCS Prr limits and L TOPS setpoints (2)(3) remain valid and conservative.
Evaluation of PTS Screening Calculations PTS screening calculations were previously transmitted to the NRC by {{letter dated|date=April 1, 1996|text=letter dated April 1, 1996}} (13). All Surry Units 1 and 2 reactor vessel beltline materials demonstrated margin to the 10 CFR 50.61 screening criteria at end-of-license (EOL) fluences corresponding to 28.8 EFPY and 29.4 EFPY for Surry Units 1 and 2, respectively (13). On the basis of the results presented in Appendix A, it is concluded that all Surry Units 1 and 2 beltline Page 3 of 7  
 
materials continue to meet the 10 CFR 50.61 screening criteria at end-of-license fluence values corresponding to 29.6 EFPY and 30.1 EFPY for Surry Units 1 and 2, respectively (12),,
Revised Reactor Vessel Beltline Neutron Fluence Values The revised reactor* vessel beltline neutron fluence values were calculated using the Virginia Power Reactor Vessel Fluence Methodology Topical Report (12).
The methodology described in that report was developed in accordance with Draft Regulatory Guide DG 1053 (14). The vessel fluence calculational methodology was benchmarked using a combination of Virginia Power surveillance capsules, pressure vessel simulator measurements, and Surry Unit 1 ex-vessel cavity dosimetry measurements. Surry Unit 1 Capsule X (15) was not used to validate the calculational methodology because the capsule data were not available during the methodology development. The table below presents the calculated neutron fluences.
Location Fluence (n/cm~)
Surry 1 Surry 2 Peak Vessel Fluence, End of License 3.53E19 3.52E19 Peak Vessel Fluence, End of Life Extension 5.40E19 5.34E19 Peak Beltline Weld Fluence, End of License 3.20E19 3.52E19 Peak Beltline Weld Fluence, End of Life 4.70E19 5.34E19 Extension Peak Upper Longitudinal Weld Fluence, End 6.00E18 6.97E18 of License Peak Upper Longitudinal Weld Fluence, End 9.14E18 1.08E19 of Life Extension Peak Lower Longitudinal Weld Fluence, End 5.40E18 6.97E18 of License Peak Lower Longitudinal Weld Fluence, End 7.90E18 1.08E19 of Life Extension Peak Nozzle to Intermediate Shell Circ. Weld 3.07E18 2.98E18 Fluence, End of License Peak Nozzle to Intermediate Shell Circ. Weld 4.96E18 4.71E18 Fluence, End of Life Extension Revised Reactor Vessel Beltline Neutron Fluence Values Surry Units 1 and 2 Page 4 of 7
 
e Conclusions After consideration of the aforementioned changes to previously reported surveillance data,*. it is concluded that the existing Surry Units 1 and 2 Prr limits and L TOPS setpoints remain valid for cumulative core burnups up to 29.6 EFPY and 30.1 EFPY for Surry Units 1 and 2, respectively. It is further concluded that all Surry Units 1 and 2 beltline materials continue to meet the 10 CFR 50.61 screening criteria for cumulative core burnups up to 29.6 EFPY and 30.1 EFPY for Surry Units 1 and 2, respectively. The evaluations that support these conclusions utilize fluence values determined in accordance with the Reference (12) topical report, which was transmitted to the NRC under separate cover. In addition, the evaluations which support these conclusions were performed in accordance with Regulatory Guide 1.99, Revision 2 (5), 10 CFR 50.61 (6), and the November 12, 1997 NRG/Industry meeting notes (7). The tables presented in Appendix A supplement the previous Virginia Power response (1) to the NRC RAI documented in Reference (2).
Page 5 of 7
 
e References (1)
Letter from J. P. O'Hanlon to USNRC, "Virginia Electric and Power Company, Surry and North Anna Power Stations Units 1 and 2, Surry 1 Reactor Vessel Surveillance Capsule X Analysis Report, GL 92-01, Rev. 1, Supplement 1, Response to Request for Additional Information, and Topical Report on Reactor Vessel Fluence Analysis Methodology," Serial No. 98-252, dated June 18, 1998.
(2)
Letter from G. E. Edison to J. P. O'Hanlon, "Surry Nuclear Power Station Units 1 and 2, Request for Additional Information Related to Reactor Vessel Structural Integrity (Generic Letter 92-01, Revision 1, Supplement 1)'(TAC Nos. MA0576 and MA0577)," dated April 20, 1998.
(3)
Letter from G. C. Lainas (USNRC) to D. J. Modeen (NEI), "Request for Additional Information Regarding Reactor Pressure Vessel Integrity," dated February 5, 1998.
(4)
"Response to Request for Additional Information (RAI) Regarding Reactor Pressure Vessel Integrity," BAW-2325, dated May, 1998.
(5)
Regulatory Guide 1.99 Revision 2, "Radiation Embrittlement of Reactor Vessel Materials," dated May, 1988.
(6)
Title 10, Code of Federal Regulations, Part 50.61, "Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events."
(7)
Memorandum from K. R. Wichman to E. 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.
(8)
BAW-2325, Supplement 1, "Supplement to the Response to Request for Additional Information (RAI) Regarding Reactor Pressure Vessel Integrity, B&W Owners Group - Reactor Vessel Working Group," dated December 1998.
(9)
Letter from R. F. Saunders to USNRC, "Virginia Electric and Power Company, Surry Power Station Units 1 and 2, Request for Exemption - ASME Code Case N-514, Proposed Technical Specifications
: Change, Revised Pressure/Temperature Limits and L TOPS Setpoint," Serial No. 95-197, June 8, 1995.
Page 6 of 7
 
(10)
Letter from B. C. Buckley to J. P. O'Hanlon, "Surry Units 1 and 2 - Issuance of Amendments Re: Surry Units 1 and 2 Reactor Vessel Heatup and Cooldown Curves (TAC Nos. M92537 and M92538)," Serial No. 96-020, dated December
*
*
* materials continue to meet the 10 CFR 50.61 screening criteria at end-of-license fluence values corresponding to 29.6 EFPY and 30.1 EFPY for Surry Units 1 and 2, respectively (12),, Revised Reactor Vessel Beltline Neutron Fluence Values The revised reactor* vessel beltline neutron fluence values were calculated using the Virginia Power Reactor Vessel Fluence Methodology Topical Report (12). The methodology described in that report was developed in accordance with Draft Regulatory Guide DG 1053 (14). The vessel fluence calculational methodology was benchmarked using a combination of Virginia Power surveillance capsules, pressure vessel simulator measurements, and Surry Unit 1 ex-vessel cavity dosimetry measurements.
* 28, 1995.
Surry Unit 1 Capsule X (15) was not used to validate the calculational methodology because the capsule data were not available during the methodology development.
(11)
The table below presents the calculated neutron fluences.
WCAP-12794 Revision 3, "Reactor Cavity Neutron Measurement Program for Wisconsin Electric Power Company Point Beach Unit 1," dated December 1995.
Location Fluence (n/cm~) Surry 1 Surry 2 Peak Vessel Fluence, End of License 3.53E19 3.52E19 Peak Vessel Fluence, End of Life Extension 5.40E19 5.34E19 Peak Beltline Weld Fluence, End of License 3.20E19 3.52E19 Peak Beltline Weld Fluence, End of Life 4.70E19 5.34E19 Extension Peak Upper Longitudinal Weld Fluence, End 6.00E18 6.97E18 of License Peak Upper Longitudinal Weld Fluence, End 9.14E18 1.08E19 of Life Extension Peak Lower Longitudinal Weld Fluence, End 5.40E18 6.97E18 of License Peak Lower Longitudinal Weld Fluence, End 7.90E18 1.08E19 of Life Extension Peak Nozzle to Intermediate Shell Circ. Weld 3.07E18 2.98E18 Fluence, End of License Peak Nozzle to Intermediate Shell Circ. Weld 4.96E18 4.71E18 Fluence, End of Life Extension Revised Reactor Vessel Beltline Neutron Fluence Values Surry Units 1 and 2 Page 4 of 7
(12)
* e Conclusions After consideration of the aforementioned changes to previously reported surveillance data,*. it is concluded that the existing Surry Units 1 and 2 Prr limits and L TOPS setpoints remain valid for cumulative core burnups up to 29.6 EFPY and 30.1 EFPY for Surry Units 1 and 2, respectively.
Virginia Power Topical Report VEP-NAF-3, "Reactor Vessel Fluence Analysis Methodology," dated November, 1997.
It is further concluded that all Surry Units 1 and 2 beltline materials continue to meet the 10 CFR 50.61 screening criteria for cumulative core burnups up to 29.6 EFPY and 30.1 EFPY for Surry Units 1 and 2, respectively.
(13)
The evaluations that support these conclusions utilize fluence values determined in accordance with the Reference (12) topical report, which was transmitted to the NRC under separate cover. In addition, the evaluations which support these conclusions were performed in accordance with Regulatory Guide 1.99, Revision 2 (5), 10 CFR 50.61 (6), and the November 12, 1997 NRG/Industry meeting notes (7). The tables presented in Appendix A supplement the previous Virginia Power response (1) to the NRC RAI documented in Reference (2). Page 5 of 7
Letter from J. P. O'Hanlon to USNRC, "Virginia Electric and Power Company, Surry and North Anna Power Stations Units 1 and 2, Pressurized Thermal Shock (PTS) Screening Calculations," Serial No. 96-084, dated April 1, 1996.
* e References (1) Letter from J. P. O'Hanlon to USNRC, "Virginia Electric and Power Company, Surry and North Anna Power Stations Units 1 and 2, Surry 1 Reactor Vessel Surveillance Capsule X Analysis Report, GL 92-01, Rev. 1, Supplement 1, Response to Request for Additional Information, and Topical Report on Reactor Vessel Fluence Analysis Methodology," Serial No. 98-252, dated June 18, 1998. (2) Letter from G. E. Edison to J. P. O'Hanlon, "Surry Nuclear Power Station Units 1 and 2, Request for Additional Information Related to Reactor Vessel Structural Integrity (Generic Letter 92-01, Revision 1, Supplement 1)'(TAC Nos. MA0576 and MA0577)," dated April 20, 1998. (3) Letter from G. C. Lainas (USNRC) to D. J. Modeen (NEI), "Request for Additional Information Regarding Reactor Pressure Vessel Integrity," dated February 5, 1998. (4) "Response to Request for Additional Information (RAI) Regarding Reactor Pressure Vessel Integrity," BAW-2325, dated May, 1998. (5) Regulatory Guide 1.99 Revision 2, "Radiation Embrittlement of Reactor Vessel Materials," dated May, 1988. (6) Title 10, Code of Federal Regulations, Part 50.61, "Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events." (7) Memorandum from K. R. Wichman to E. 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. (8) BAW-2325, Supplement 1, "Supplement to the Response to Request for Additional Information (RAI) Regarding Reactor Pressure Vessel Integrity, B&W Owners Group -Reactor Vessel Working Group," dated December 1998. (9) Letter from R. F. Saunders to USNRC, "Virginia Electric and Power Company, Surry Power Station Units 1 and 2, Request for Exemption
(14)
-ASME Code Case N-514, Proposed Technical Specifications Change, Revised Pressure/Temperature Limits and L TOPS Setpoint," Serial No. 95-197, June 8, 1995. Page 6 of 7 
Draft Regulatory Guide DG-1053, "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence," dated June 1996.
* -(10) Letter from B. C. Buckley to J. P. O'Hanlon, "Surry Units 1 and 2 -Issuance of Amendments Re: Surry Units 1 and 2 Reactor Vessel Heatup and Cooldown *. Curves (TAC Nos. M92537 and M92538)," Serial No. 96-020, dated December *
(15)
* 28, 1995. (11) WCAP-12794 Revision 3, "Reactor Cavity Neutron Measurement Program for Wisconsin Electric Power Company Point Beach Unit 1," dated December 1995. (12) Virginia Power Topical Report VEP-NAF-3, "Reactor Vessel Fluence Analysis Methodology," dated November, 1997. (13) Letter from J. P. O'Hanlon to USNRC, "Virginia Electric and Power Company, Surry and North Anna Power Stations Units 1 and 2, Pressurized Thermal Shock (PTS) Screening Calculations," Serial No. 96-084, dated April 1, 1996. (14) Draft Regulatory Guide DG-1053, "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence," dated June 1996. (15) BAW-2324, "Analysis of Capsule X, Virginia Power Surry Unit No. 1, Reactor Vessel Material Surveillance Program," dated April, 1998. Page 7 of 7 e Appendix A Supplemental Reactor Vessel Material Data Tables Calc98d (SM-1008 Rev. 0 Addendum C).xls Facility:
BAW-2324, "Analysis of Capsule X, Virginia Power Surry Unit No. 1, Reactor Vessel Material Surveillance Program," dated April, 1998.
Surry Unit 1 Vessel Manufacturer:
Page 7 of 7  
B& W and Rotterdam Dockyard Best-Best-Assigned Est i mate Estimate EOLID Materia l RPV Weld W i re H ea t Copper Nickel Fluence Chemistry or Mater i al ID (1) Location (wt%) (wt%) (x1E19) Factor 122V109VA1 Nozzle Shell Forging 0.11 0.74 0.307 76.1 C4326-1 Intermediate Shell 0.11 0.55 3.53 73.5 C4326-2 Intermediate Shell 0.11 0.55 3.53 73.5 4415-1 Lower Shell 0.11 0.50 3.53 85.0 4415-2 Lower Shell 0.11 0.50 3.53 73.0 J72 6/25017 Nozzle to Int Sh e ll Gire Weld 0.33 0.10 0.307 152.0 SA-1585/72445 Int. to Low Sh. Gire (ID 40%) 0.22 0.54 3.2 139.8 SA-1650/72445 Int. to Low Sh. Circ (OD 60%) 0.22 0.54 3.2 139.8 SA-1494/8T1554 Int Shell Long. Welds L3 & L4 0.16 0.57 0.6 143.9 SA-1494/8T1554 Lower Shell Long. Weld L 1 0.16 0.57 0.54 143.9 SA-1526/299L44 Lower Shell Long. Weld L2 0.34 0.68 0.54 220.6 (1) or the material i dent i fication number of the limiting material as requested in Section 1.0 (1.) (2) determined from tables or from surveillance data Method of Determ i ning CF (2) Tables Tables Tables Surv. Data Tables Tables Surv. Data Surv. Data Tables Tables Tables Summary (Surry) Inner Surf. Current ART o r Licens i ng Initial RT(PTS) at 1/4-T Bas i s 1/4-RT(NDT) Sigma(!) Sigma(delta)
 
Margin EOL ART TART* 40 0.0 17.0 34.0 125.5 116.1 112.5 10 0.0 17.0 34.0 141.6 132.8 135.2 0 0.0 17.0 34.0 131.6 122.8 125.2 20 0.0 8.5 17.0 149.9 139.7 147.6 0 0.0 17.0 34.0 131.0 122.2 124.6 0 20.0 28.0 68.8 171.6 153.0 169.8 -5 19.7 14.0 48.3 225.8 208.6 228.4 * -5 19.7 14.0 48.3 225.8 208.6 228.4 * -5 19.7 28.0 68.5 186.8 167.4 181.4 -5 19.7 28.0 68.5 182.6 163.4 181.4 -7 20.6 28.0 69.5 245.1 215.7 207.0
e Appendix A Supplemental Reactor Vessel Material Data Tables
* 1/4-T ART value of 228.4 F was used in the determination of PIT limits Page 1 of 18 e Calc98d (SM-1008 Rev. 0 Addendum C).xls Facility:
 
Surry Unit 2 Vessel Manufacturer:
Calc98d (SM-1008 Rev. 0 Addendum C).xls Facility: Surry Unit 1 Vessel Manufacturer: B& W and Rotterdam Dockyard Best-Best-Assigned Estimate Estimate EOLID Material RPV Weld Wire Heat Copper Nickel Fluence Chemistry or Material ID (1)
B&W and Rotterdam Dockyard Best-B est-Assigned Estima te Estimate EOLID Material RPV Weld Wire Heat C opper Nickel Fluence Chemistry or Material ID (1) Location (wt%) (wt%) (x1E19) Factor 123V303VA1 Nozzle Shell Forging 0.11 0.72 0.298 75.8 C 433 1-2 Intermediat e Shell 0.12 0.6 0 3.520 83.0 C 4 339-2 Intermed iate Shell 0.11 0.54 3.520 73.4 C4208-2 Lower Shell 0.15 0.55 3.520 107.3 C 4339-1 Lower Shell 0.11 0.54 3.520 68.4 L737/4275 No zz le t o Int Shell Gir e Weld 0.35 0.10 0.298 160.5 A3008/0227 Int. to Lower Shell Gire Weld 0.19 0.55 3.520 125.2 WF-4/8T1762 Int. Shell Long. L4 (ID 50%) 0.19 0.57 0.697 152.4 SA-1585/72445 Int. Sh. L3 (100%), L4 (OD 50) 0.22 0.54 0.697 139.8 WF-4/8T1762 LS L2 (ID 63%), L1 (100) 0.19 0.57 0.697 152.4 WF-8/8T1762 LS Long. Weld L2 (OD 37%) 0.19 0.57 0.697 152.4 (1) or the mater i al i dentification number of the limi ting material as requested in Section 1.0 (1.) (2) determined from tab l es or from surveillance data Method of D etermining CF(2) Tables Tables Tabl es Tables Surv. Data Tabl es Surv. Data Tabl es Surv. Data T ables Tab l es Summary (Surry) Initial RT(ND T) 30 2 0 1 0 0 0 5 5 Inner Surf. Current ART or Licensing RT(PTS) at 1/4-T B asis 1/4-S i gma(I) Sigma(delta)
Location (wt%)
Margin EOL ART TART* 0.0 17.0 34.0 114.7 105.5 100.4 e 0.0 17.0 34.0 134.2 12 4.2 123.9 0.0 17.0 34.0 111.5 102.6 10 2.4 0.0 17.0 34.0 146.4 133.5 133.1 0.0 8.5 17.0 97.8 89.6 89.3 20.0 28.0 68.8 176.1 156.6 169.6 20.0 14.0 48.8 215.0 200.0 202.9 19.7 28.0 68.5 200.4 179.6 181.0 19.7 14.0 48.3 168.9 149.9 158.5 19.7 28.0 68.5 200.4 179.6 181.0 19.7 28.0 68.5 200.4 179.6 181.0
(wt%)
* 1/4-T ART value of 228.4 F was used i n the determination of Prr limits Page 2 of 18 ET-NAF-990006 Tables.xi s Table 2: Surry Unit 1 and 2 Weld Material SA-1585 (Point Beach 1 Data Only) Data Used In Irradiation Assessing Temperature Measured Delta-Vessel? (Yes or Capsule ID (Including Source) Copper (wt%) Nickel (wt%) (F) Fluence (x1E19) RT(NDT) (F) No) Point B eac h Uni t 1 Capsule T 0.230 0.615 533.4 2.230 181 Yes Point B eac h Unit 1 Capsule R 0.230 0.615 541.6 2.190 155 Yes Po i nt B e ach Unit 1 Capsule S 0.230 0.615 542.0 0.829 165 Yes Point B each Un it 1 Cap sule V 0.230 0.61 5 542.0 0.634 107 Y es Capsule CR3-LG2 (BWOG CR-3 lrrad.) 0.220 0.590 556.0 1.670 164 No Capsule CR3-LG1 (BWOG CR-3 lrrad.) 0.220 0.590 556.0 0.510 139 No -------------e ----------------------------Table 3: Surry Unit 1 and 2 Weld Material SA-1585 (Point Beach 1 Data Only) Irradiation Temperature Measured Delta-Adjusted Delta-Adjusted -Pred icted Capsule ID (Including Source) C o pper (wt%) Nickel (wt%) (F) F lu ence Factor RT(NDT) (F) RT(NDT) (F)
(x1E19)
* D elt a-RT(NDT) (F)
Factor 122V109VA1 Nozzle Shell Forging 0.11 0.74 0.307 76.1 C4326-1 Intermediate Shell 0.11 0.55 3.53 73.5 C4326-2 Intermediate Shell 0.11 0.55 3.53 73.5 4415-1 Lower Shell 0.11 0.50 3.53 85.0 4415-2 Lower Shell 0.11 0.50 3.53 73.0 J726/25017 Nozzle to Int Shell Gire Weld 0.33 0.10 0.307 152.0 SA-1585/72445 Int. to Low Sh. Gire (ID 40%)
* Point B eac h Unit 1 Ca ps ul e T 0.230 0.615 533.4 1.2173 181 181 7 Point B each U nit 1 Capsule R 0.230 0.615 541.6 1.2126 155 155 -18 Point B eac h Un it 1 Capsule S 0.230 0.615 542.0 0.9474 165 165 30 Point Bea c h Unit 1 Capsule V 0.230 0.615 542.0 0.8723 107 107 -------e I --------------------------------------------------------* For credib ilit y ch eck , measured shift values a re adj usted to average survei llance material c hemistry and irradiat io n tempe rature as required. See Table 4. Page 3 of 18 Summary (SA-1585)
0.22 0.54 3.2 139.8 SA-1650/72445 Int. to Low Sh. Circ (OD 60%)
-Corrected L
0.22 0.54 3.2 139.8 SA-1494/8T1554 Int Shell Long. Welds L3 & L4 0.16 0.57 0.6 143.9 SA-1494/8T1554 Lower Shell Long. Weld L 1 0.16 0.57 0.54 143.9 SA-1526/299L44 Lower Shell Long. Weld L2 0.34 0.68 0.54 220.6 (1) or the material identification number of the limiting material as requested in Section 1.0 (1.)
Table 4: Beltline Material ID SA-1585/72445 ET-NAF-990006 Tables.xis Surry Unit 1 and 2 Weld Material SA-1585 (Point Beach 1 Data Only) CF Determination Chemistry Beltline Beltline Irradiation Surveillance Data Factor Applied Material Material Temperature Position 1.1 Chemistry Credible or Non-to Beltline Copper (wt%) Nickel (wt%) (F) Factor Credible?
(2) determined from tables or from surveillance data Method of Determining CF (2)
Tables Tables Tables Surv. Data Tables Tables Surv. Data Surv. Data Tables Tables Tables Summary (Surry)
Inner Surf.
Current ART or Licensing Initial RT(PTS) at 1/4-T Basis 1/4-RT(NDT)
Sigma(!)
Sigma(delta)
Margin EOL ART TART
* 40 0.0 17.0 34.0 125.5 116.1 112.5 10 0.0 17.0 34.0 141.6 132.8 135.2 0
0.0 17.0 34.0 131.6 122.8 125.2 20 0.0 8.5 17.0 149.9 139.7 147.6 0
0.0 17.0 34.0 131.0 122.2 124.6 0
20.0 28.0 68.8 171.6 153.0 169.8
-5 19.7 14.0 48.3 225.8 208.6 228.4 *
-5 19.7 14.0 48.3 225.8 208.6 228.4 *
-5 19.7 28.0 68.5 186.8 167.4 181.4
-5 19.7 28.0 68.5 182.6 163.4 181.4
-7 20.6 28.0 69.5 245.1 215.7 207.0
* 1/4-T ART value of 228.4 F was used in the determination of PIT limits Page 1 of 18 e
 
Calc98d (SM-1008 Rev. 0 Addendum C).xls Facility: Surry Unit 2 Vessel Manufacturer: B&W and Rotterdam Dockyard Best-Best-Assigned Estimate Estimate EOLID Material RPV Weld Wire Heat Copper Nickel Fluence Chemistry or Material ID (1)
Location (wt%)
(wt%)
(x1E19)
Factor 123V303VA1 Nozzle Shell Forging 0.11 0.72 0.298 75.8 C4331-2 Intermediate Shell 0.12 0.60 3.520 83.0 C4339-2 Intermediate Shell 0.11 0.54 3.520 73.4 C4208-2 Lower Shell 0.15 0.55 3.520 107.3 C4339-1 Lower Shell 0.11 0.54 3.520 68.4 L737/4275 Nozzle to Int Shell Gire Weld 0.35 0.10 0.298 160.5 A3008/0227 Int. to Lower Shell Gire Weld 0.19 0.55 3.520 125.2 WF-4/8T1762 Int. Shell Long. L4 (ID 50%)
0.19 0.57 0.697 152.4 SA-1585/72445 Int. Sh. L3 (100%), L4 (OD 50) 0.22 0.54 0.697 139.8 WF-4/8T1762 LS L2 (ID 63%), L1 (100) 0.19 0.57 0.697 152.4 WF-8/8T1762 LS Long. Weld L2 (OD 37%)
0.19 0.57 0.697 152.4 (1) or the material identification number of the limiting material as requested in Section 1.0 (1.)
(2) determined from tables or from surveillance data Method of Determining CF(2)
Tables Tables Tables Tables Surv. Data Tables Surv. Data Tables Surv. Data Tables Tables Summary (Surry)
Initial RT(NDT) 30
-10
-20
-30
-1 0 0
0  
-5  
-5
-5
-5 Inner Surf.
Current ART or Licensing RT(PTS) at 1/4-T Basis 1/4-Sigma(I)
Sigma(delta)
Margin EOL ART TART*
0.0 17.0 34.0 114.7 105.5 100.4 e 0.0 17.0 34.0 134.2 124.2 123.9 0.0 17.0 34.0 111.5 102.6 102.4 0.0 17.0 34.0 146.4 133.5 133.1 0.0 8.5 17.0 97.8 89.6 89.3 20.0 28.0 68.8 176.1 156.6 169.6 20.0 14.0 48.8 215.0 200.0 202.9 19.7 28.0 68.5 200.4 179.6 181.0 19.7 14.0 48.3 168.9 149.9 158.5 19.7 28.0 68.5 200.4 179.6 181.0 19.7 28.0 68.5 200.4 179.6 181.0
* 1/4-T ART value of 228.4 F was used in the determination of Prr limits Page 2 of 18
 
ET-NAF-990006 Tables.xis Table 2:
Surry Unit 1 and 2 Weld Material SA-1585 (Point Beach 1 Data Only)
Data Used In Irradiation Assessing Temperature Measured Delta-Vessel? (Yes or Capsule ID (Including Source)
Copper (wt%) Nickel (wt%)
(F)
Fluence (x1E19)
RT(NDT) (F)
No)
Point Beach Unit 1 Capsule T 0.230 0.615 533.4 2.230 181 Yes Point Beach Unit 1 Capsule R 0.230 0.615 541.6 2.190 155 Yes Point Beach Unit 1 Capsule S 0.230 0.615 542.0 0.829 165 Yes Point Beach Unit 1 Capsule V 0.230 0.61 5 542.0 0.634 107 Yes Capsule CR3-LG2 (BWOG CR-3 lrrad.)
0.220 0.590 556.0 1.670 164 No Capsule CR3-LG1 (BWOG CR-3 lrrad.)
0.220 0.590 556.0 0.510 139 No e
Table 3:
Surry Unit 1 and 2 Weld Material SA-1585 (Point Beach 1 Data Only)
Irradiation Temperature Measured Delta-Adjusted Delta-Adjusted - Predicted Capsule ID (Including Source)
Copper (wt%) Nickel (wt%)
(F)
Fluence Factor RT(NDT) (F)
RT(NDT) (F)
* Delta-RT(NDT) (F)
* Point Beach Unit 1 Capsule T 0.230 0.615 533.4 1.2173 181 181 7
Point Beach Unit 1 Capsule R 0.230 0.615 541.6 1.2126 155 155
-18 Point Beach Unit 1 Capsule S 0.230 0.615 542.0 0.9474 165 165 30 Point Beach Unit 1 Capsule V 0.230 0.615 542.0 0.8723 107 107
-17 e
* For credibility check, measured shift values are adjusted to average surveillance material chemistry and irradiation temperature as required. See Table 4.
Page 3 of 18 Summary (SA-1585) - Corrected L
 
Table 4:
Beltline Material ID SA-1585/72445 ET-NAF-990006 Tables.xis Surry Unit 1 and 2 Weld Material SA-1585 (Point Beach 1 Data Only)
CF Determination Chemistry Beltline Beltline Irradiation Surveillance Data Factor Applied Material Material Temperature Position 1.1 Chemistry Credible or Non-to Beltline Copper (wt%) Nickel (wt%)
(F)
Factor Credible?
Material*
Material*
0.220 0.540 542.0 158.0 Non-Credible 158.0
0.220 0.540 542.0 158.0 Non-Credible 158.0
* If surveillance data are determined to be non-credible , the Position 1. 1 chemistry factor is applied to the beltline material.
* If surveillance data are determined to be non-credible, the Position 1. 1 chemistry factor is applied to the beltline material.
If Surv. Data Non-Credible, Verify Conservatism of Applied Position 1.1 CF** Conservative  
If Surv. Data Non-Credible, Verify Conservatism of Applied Position 1.1 CF **
** Measured shift values are adjusted to the average surveillance material chemistry and irradiation temperature , and are verified to be within 2 sigma of the trend curve based on Posit i on 1. 1. Credibility Assessment e Conservatism Check for Pos. 1.1 CF when Surv. Data Non-Credible (3) (1) (2) Temperature Correction (4) Temperature Chemistry Surveillance Applied to Cred i ble Chemistry Correction Correction Correction Data Credible Surv. Data for Applied to C r edible Surv. Are adjusted surveillance Applied for Applied for or Non-Applicat ion to Beltline Data for Application to Adjusted Delta-Adjusted -Predicted data within 2 sigma of the Capsule ID (Inc lud ing Source) Credibility?
Conservative  
** Measured shift values are adjusted to the average surveillance material chemistry and irradiation temperature, and are verified to be within 2 sigma of the trend curve based on Position 1. 1.
Credibility Assessment e
Conservatism Check for Pos. 1.1 CF when Surv. Data Non-Credible (3)
(1)
(2)
Temperature Correction (4)
Temperature Chemistry Surveillance Applied to Credible Chemistry Correction Correction Correction Data Credible Surv. Data for Applied to Credible Surv.
Are adjusted surveillance Applied for Applied for or Non-Application to Beltline Data for Application to Adjusted Delta-Adjusted - Predicted data within 2 sigma of the Capsule ID (Including Source)
Credibility?
Credibility?
Credibility?
Credible?
Credible?
Material?
Material?
Beltline Material?
Beltline Material?
RT(NDT) (F) ** Delta-RT(NDT) (F) ** applied CF trend curve? ** Point Beach Unit 1 Capsule T No No Credible --181 -2 8 Point Beach Unit 1 Capsule R No No Credible --155 -53 Point B eac h Unit 1 Capsule S No No Non-Credible  
RT(NDT) (F) **
--165 2 Point Beach Un it 1 Capsule V No No Credible --107 -43 Capsule CR3-LG2 (BWOG CR-3 lrrad.) -------Capsule CR3-LG1 (BWOG CR-3 lrrad.) -------------------------------------------------------(1) For the credi bility determination, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in a single reactor (i.e., were irradia ted at a s i milar temperature
Delta-RT(NDT) (F) **
). (2) For the credibility determination , a chemistry c orrection is not applied to measured values of transition t em peratu re shift if applicable surveillance data were obtained from a single source (i.e., were machined from the same block of material).
applied CF trend curve? **
(3) For determination of the beltline material chemistry factor , a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irr adiated i n the reactor vessel which is being evaluated (i.e., were irradiated at a similar temperature).
Point Beach Unit 1 Capsule T No No Credible 181  
(4) For determination of the beltline material chemistry factor, a chemistry correction (i.e., ratio procedure) is not applied to measured values of transition temperature shift if the chemical composition of applicable surveillance data is essentially identical to the best-es timate chemical composition of the beltline material being evaluated. Credible Credible Credible Credible --------Page 4 of 18 Summary (SA-1585)  
-28 Point Beach Unit 1 Capsule R No No Credible 155  
-Corrected ET-NAF-990006 Tables.xis Table 2: Surry Unit 1 and 2 Weld Material SA-1585 (All Available Data) Data Used In Irradiat i on Assessing Temperature Measured Delta-Vessel? (Yes or Capsule I D (Including Source) Copper (wt%) Nickel (wt%) (F) Fluence (x1E19) RT(NDT) (F) No) Point Beach Unit 1 Capsule T 0.230 0.615 533.4 2.230 181 Yes Point Beach U nit 1 Capsule R 0.230 0.615 541.6 S\ c, 2.190 c: .. it 155"' Yes Point Beach Unit 1 Capsule S 0.230 0.615 542.0 0.829 165 Yes Point Beach Unit 1 Capsule V 0.230 0.615 542 .. 0 ", 0.634 107 Yes C a psule CR3-LG2 (BWOG CR-3 lrrad.) 0.220 0.590 556.0 1.670 164 Yes Capsule CR3-LG1 (BWOG CR-3 lrrad.) 0.220 0.590 556.0 0.510 139 Yes ------------------------------------------Table 3: Surry Unit 1 and 2 Weld Material SA-1585 (All Available Data) Irradiat i on Temperature Meas u red Delta-Adjusted Delta-Adjusted -Predicted C aps ule ID (Includ ing S o u rce) Copper (wt%) Nicke l (wt%) (F) Fluence Factor RT(NDT) (F) RT(NDT) (F)
-53 Point Beach Unit 1 Capsule S No No Non-Credible 165 2
Point Beach Unit 1 Capsule V No No Credible 107  
-43 Capsule CR3-LG2 (BWOG CR-3 lrrad.)
Capsule CR3-LG1 (BWOG CR-3 lrrad.)
(1) For the credibility determination, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in a single reactor (i.e., were irradiated at a similar temperature).
(2) For the credibility determination, a chemistry correction is not applied to measured values of transition temperature shift if applicable surveillance data were obtained from a single source (i.e., were machined from the same block of material).
(3) For determination of the beltline material chemistry factor, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in the reactor vessel which is being evaluated (i.e., were irradiated at a similar temperature).
(4) For determination of the beltline material chemistry factor, a chemistry correction (i.e., ratio procedure) is not applied to measured values of transition temperature shift if the chemical composition of applicable surveillance data is essentially identical to the best-estimate chemical composition of the beltline material being evaluated.
Credible Credible Credible Credible Page 4 of 18 Summary (SA-1585) - Corrected  
 
ET-NAF-990006 Tables.xis Table 2:
Surry Unit 1 and 2 Weld Material SA-1585 (All Available Data)
Data Used In Irradiation Assessing Temperature Measured Delta-Vessel? (Yes or Capsule ID (Including Source)
Copper (wt%) Nickel (wt%)
(F)
Fluence (x1E19)
RT(NDT) (F)
No)
Point Beach Unit 1 Capsule T 0.230 0.615 533.4 2.230 181 Yes Point Beach Unit 1 Capsule R 0.230 0.615 541.6 S\\ c, 2.190 c:
it 155 "'
Yes Point Beach Unit 1 Capsule S 0.230 0.615 542.0 0.829 165 Yes Point Beach Unit 1 Capsule V 0.230 0.615 542.. 0 0.634 107 Yes Capsule CR3-LG2 (BWOG CR-3 lrrad.)
0.220 0.590 556.0 1.670 164 Yes Capsule CR3-LG1 (BWOG CR-3 lrrad.)
0.220 0.590 556.0 0.510 139 Yes Table 3:
Surry Unit 1 and 2 Weld Material SA-1585 (All Available Data)
Irradiation Temperature Measured Delta-Adjusted Delta-Adjusted - Predicted Capsule ID (Including Source)
Copper (wt%) Nickel (wt%)
(F)
Fluence Factor RT(NDT) (F)
RT(NDT) (F)
* Delta-RT(NDT) (F)
* Delta-RT(NDT) (F)
* P oi nt Bea c h Unit 1 Cap s ule T 0.230 0.615 533.4 1.2173 181 167 -10 Point Beach Unit 1 C a psul e R 0.230 0.615 541.6 1.2126 155 150 -27 Point Beach Unit 1 C a psule S 0.230 0.615 542.0 0.9474 165 160 22 Point Beach U n i t 1 Ca p sule V 0.230 0.615 542.0 0.8723 107 103 -24 Capsule CR3-LG2 (BWOG CR-3 l rra d.) 0.220 0.590 556.0 1.1413 164 179 13 Capsule CR3-LG1 (BWOG CR-3 lrrad.) 0.220 0.590 556.0 0.8120 139 153 35 -----------------------------------------------* For credibility check , m ea sured shift va lue s ar e adjusted to average surveillance material chemistry and irradiation temperature as required. See Table 4. Page 5 of 18 Summary (SA-1585 , Alt. 1) L __ ----
* Point Beach Unit 1 Capsule T 0.230 0.615 533.4 1.2173 181 167  
Table 4: Beltline Material ID SA-1585n2445 ET-NAF-990006 Tables.xis Surry Unit 1 and 2 Weld Material SA-1585 (All Available Data) CF Determination Beltline Beltline Irradiation Surveillance Data Material Material Temperature Position 1.1 Chemistry Credible or Non-Copper (wt%) Nickel (w1%) (F) Factor Credible?
-10 Point Beach Unit 1 Capsule R 0.230 0.615 541.6 1.2126 155 150  
-27 Point Beach Unit 1 Capsule S 0.230 0.615 542.0 0.9474 165 160 22 Point Beach Unit 1 Capsule V 0.230 0.615 542.0 0.8723 107 103  
-24 Capsule CR3-LG2 (BWOG CR-3 lrrad.)
0.220 0.590 556.0 1.1413 164 179 13 Capsule CR3-LG1 (BWOG CR-3 lrrad.)
0.220 0.590 556.0 0.8120 139 153 35
* For credibility check, measured shift values are adjusted to average surveillance material chemistry and irradiation temperature as required. See Table 4.
Page 5 of 18 Summary (SA-1585, Alt. 1)
L  
 
Table 4:
Beltline Material ID SA-1585n2445 ET-NAF-990006 Tables.xis Surry Unit 1 and 2 Weld Material SA-1585 (All Available Data)
CF Determination Beltline Beltline Irradiation Surveillance Data Material Material Temperature Position 1.1 Chemistry Credible or Non-Copper (wt%) Nickel (w1%)
(F)
Factor Credible?
0.220 0.540 542.0 158.0 Credible
0.220 0.540 542.0 158.0 Credible
* If suNei/lance data are determined to be non-credible , the Position 1. 1 chemistry factor i s applied to the beltline material.
* If suNei/lance data are determined to be non-credible, the Position 1. 1 chemistry factor is applied to the beltline material.
If Surv. Data Non-Chemistry Credible, Verify Factor Applied Conservatism of to Beltline Applied Position 1.1 Material*
If Surv. Data Non-Chemistry Credible, Verify Factor Applied Conservatism of to Beltline Applied Position 1.1 Material*
CF** 139.8 -** Measured shift values are adjusted to the average suNeillance material chemistry and irradiation temperature, and are verified to be within 2 sigma of the trend cuNe based on Position 1. 1. Credibility Assessment e Conservatism Check for Pos. 1.1 CF when Surv. Data Non-Credible (3) (1) (2) Temperature Correction (4) Temperature Chemistry Surveillance Applied to Credible Chemistry Correction Correction Correction Data Credible Surv. Data for Applied to Credible Surv. Are adjusted surveillance Applied for Applied for or Non-Application to Beltline Data for Application to Adjusted Delta-Adjusted -Predicted data within 2 sigma of the Capsule ID (Including Source) Credibility?
CF**
139.8  
** Measured shift values are adjusted to the average suNeillance material chemistry and irradiation temperature, and are verified to be within 2 sigma of the trend cuNe based on Position 1. 1.
Credibility Assessment e
Conservatism Check for Pos. 1.1 CF when Surv. Data Non-Credible (3)
(1)
(2)
Temperature Correction (4)
Temperature Chemistry Surveillance Applied to Credible Chemistry Correction Correction Correction Data Credible Surv. Data for Applied to Credible Surv.
Are adjusted surveillance Applied for Applied for or Non-Application to Beltline Data for Application to Adjusted Delta-Adjusted - Predicted data within 2 sigma of the Capsule ID (Including Source)
Credibility?
Credibility?
Credibility?
Credible?
Credible?
Material?
Material?
Beltline Material?
Beltline Material?
RT(NDT) (F) ** Delta-RT(NDT) (F) ** applied CF trend curve? ** Po i nt Beach Unit 1 Capsule T Yes Yes Credible Yes Yes --Point Beach Unit 1 Capsule R Yes Yes Credible Yes Yes --Point Beach Unit 1 Capsule S Yes Yes Credible Yes Yes --Point Beach Unit 1 Capsule V Yes Yes Credible Yes Yes --Capsule CR3-LG2 (BWOG CR-3 lrrad.) Yes Yes Credible Yes Yes --Capsule CR3-LG1 (BWOG CR-3 lrrad.) Yes Yes Non-Credible Yes Yes --------------------------------------------------(1) For the credibility determination, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in a single reactor (i.e., were irradiated at a similar temperature). (2) For the credibility determination , a chemistry correction is not applied to measured values of transition temperature shift if applicable surveillance data were obtained from a single source (i.e., were mach ined from the same block of material).
RT(NDT) (F) **
Delta-RT(NDT) (F) **
applied CF trend curve? **
Point Beach Unit 1 Capsule T Yes Yes Credible Yes Yes Point Beach Unit 1 Capsule R Yes Yes Credible Yes Yes Point Beach Unit 1 Capsule S Yes Yes Credible Yes Yes Point Beach Unit 1 Capsule V Yes Yes Credible Yes Yes Capsule CR3-LG2 (BWOG CR-3 lrrad.)
Yes Yes Credible Yes Yes Capsule CR3-LG1 (BWOG CR-3 lrrad.)
Yes Yes Non-Credible Yes Yes (1) For the credibility determination, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in a single reactor (i.e., were irradiated at a similar temperature).
(2) For the credibility determination, a chemistry correction is not applied to measured values of transition temperature shift if applicable surveillance data were obtained from a single source (i.e., were machined from the same block of material).
(3) For determination of the beltline material chemistry factor, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in the reactor vessel which is being evaluated (i.e., were irradiated at a similar temperature).
(3) For determination of the beltline material chemistry factor, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in the reactor vessel which is being evaluated (i.e., were irradiated at a similar temperature).
(4) For determination of the beltline material chemistry factor, a chemistry correction (i.e., ratio procedure) is not applied to measured values of transition temperature shift if the chemical composition of applicab l e surveillance data is essentially identical to the best-estimate chemical composition of the beltline material being evaluated. ------------Page 6 of 18 Summary (SA-1585, Alt. 1)
(4) For determination of the beltline material chemistry factor, a chemistry correction (i.e., ratio procedure) is not applied to measured values of transition temperature shift if the chemical composition of applicable surveillance data is essentially identical to the best-estimate chemical composition of the beltline material being evaluated.
ET -NAF-990 006 Tables.xis Table 2: Surry Unit 1 Weld Material SA-1526 (Surry Unit 1 Data Only) Data Used In Irradiation Assessing Temperature Measured Delta-Vessel? (Yes or Capsule ID (Including Source) Copper (wt%) Nickel (wt%) (F) Fluence (x1E19) RT(NDT) (F) No) Capsu l e TMl2-LG1 (BWOG CR-3 lrrad.) 0.370 0.700 556.0 0.830 216 No Capsule CR3-LG1 (BWOG CR-3 lrrad.) 0.360 0.700 556.0 0.779 202 No Capsule TMl2-LG1 (BWOG CR-3 lrrad.) 0.330 0.670 556.0 0.968 226 No Three Mile Island Unit 1 Capsule C 0.330 0.670 556.0 0.866 166 No Three Mile Island Unit 1 Capsule E 0.330 0.670 556.0 0.107 74 No Surry Unit 1 Capsule T 0.230 0.640 533.9 0.281 171 Yes Surry Unit 1 Capsule V 0.230 0.640 538.8 1.940 250 Yes Surry Unit 1 Capsule X 0.230 0.640 542.0 1.599 234 Yes . . . . . . . . . . . . . . . . . . . . . . . . . . . . Table 3: Surry Unit 1 Weld Material SA-1526 (Surry Unit 1 Data Only) Irradiat ion Temperature Measured Delta-Adjusted Delta-Adjusted -Predicted Capsule ID (Including Source) Copper (wt%) Nickel (wt%) (F) Fluence Factor RT(NDT) (F) RT(NDT) (F)
Page 6 of 18 Summary (SA-1585, Alt. 1)  
* Delta-RT(NDT) (F) * . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . e Surry Unit 1 Capsule T 0.230 0.640 533.9 0.6535 171 171 29 Surry Unit 1 Capsule V 0.230 0.640 538.8 1.1811 250 250 -6 Surry Unit 1 Capsule X 0.230 0.640 542.0 1.1296 234 234 -11 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
 
* F or cr e dibility check, me a sur e d shift values are adjusted to average surveillance material chemistry and irradiation temperature as required. See Table 4. Page 7 of 18 Summary (SA-1526)
ET -NAF-990006 Tables.xis Table 2:
Table 4: Beltline Mater ial ID SA-1526/299L44 ET-NAF-990006 Tables.xis Surry Unit 1 Weld Material SA-1526 (Surry Unit 1 Data Only) CF Determination Beltline Beltline Irradiation Surveillance Data Material Material Temperature Position 1.1 Chemistry Credible or Non-Copper (wt%) Nickel (wt%) (F) Factor Credible?
Surry Unit 1 Weld Material SA-1526 (Surry Unit 1 Data Only)
Data Used In Irradiation Assessing Temperature Measured Delta-Vessel? (Yes or Capsule ID (Including Source)
Copper (wt%) Nickel (wt%)
(F)
Fluence (x1E19)
RT(NDT) (F)
No)
Capsule TMl2-LG1 (BWOG CR-3 lrrad.)
0.370 0.700 556.0 0.830 216 No Capsule CR3-LG1 (BWOG CR-3 lrrad.)
0.360 0.700 556.0 0.779 202 No Capsule TMl2-LG1 (BWOG CR-3 lrrad.)
0.330 0.670 556.0 0.968 226 No Three Mile Island Unit 1 Capsule C 0.330 0.670 556.0 0.866 166 No Three Mile Island Unit 1 Capsule E 0.330 0.670 556.0 0.107 74 No Surry Unit 1 Capsule T 0.230 0.640 533.9 0.281 171 Yes Surry Unit 1 Capsule V 0.230 0.640 538.8 1.940 250 Yes Surry Unit 1 Capsule X 0.230 0.640 542.0 1.599 234 Yes Table 3:
Surry Unit 1 Weld Material SA-1526 (Surry Unit 1 Data Only)
Irradiation Temperature Measured Delta-Adjusted Delta-Adjusted - Predicted Capsule ID (Including Source)
Copper (wt%) Nickel (wt%)
(F)
Fluence Factor RT(NDT) (F)
RT(NDT) (F)
* Delta-RT(NDT) (F)
* e Surry Unit 1 Capsule T 0.230 0.640 533.9 0.6535 171 171 29 Surry Unit 1 Capsule V 0.230 0.640 538.8 1.1811 250 250  
-6 Surry Unit 1 Capsule X 0.230 0.640 542.0 1.1296 234 234  
-11
* For credibility check, measured shift values are adjusted to average surveillance material chemistry and irradiation temperature as required. See Table 4.
Page 7 of 18 Summary (SA-1526)  
 
Table 4:
Beltline Material ID SA-1526/299L44 ET-NAF-990006 Tables.xis Surry Unit 1 Weld Material SA-1526 (Surry Unit 1 Data Only)
CF Determination Beltline Beltline Irradiation Surveillance Data Material Material Temperature Position 1.1 Chemistry Credible or Non-Copper (wt%) Nickel (wt%)
(F)
Factor Credible?
0.340 0.680 542.0 220.6 Non-Credible
0.340 0.680 542.0 220.6 Non-Credible
* If surveillance data are determined to be non-credible, the Position 1. 1 chemistry factor is applied to the belt/ine material. If Surv. Data Non-Chemistry Credible , Verify Factor Applied Conservatism of to Beltline Applied Position 1.1 Material* CF** 220.6 Conservative  
* If surveillance data are determined to be non-credible, the Position 1. 1 chemistry factor is applied to the belt/ine material.
** Measured shift values are adjusted to the average surveillance material chemistry and irradiation temperature , and are verified to be within 2 sigma of the trend curve based on Position 1. 1. Credibility Assessment e Conservatism Check for Pos. 1.1 CF when Surv. Data Non-Credible (3) (1) (2) Temperature Correction (4) Temperature Chemistry Surveil l ance Applied to Credible Chemistry Correction Correction Correction Data Cred i ble Surv. Data for Applied to Credible Surv. Are adjusted surveillance Applied for Applied for or Non-Application to Beltline Data for Application to Adjusted Delta-Adjusted -Predicted data within 2 sigma of the Capsule ID (Including Source) Cred i bility? Credibility?
If Surv. Data Non-Chemistry Credible, Verify Factor Applied Conservatism of to Beltline Applied Position 1.1 Material
* CF**
220.6 Conservative  
** Measured shift values are adjusted to the average surveillance material chemistry and irradiation temperature, and are verified to be within 2 sigma of the trend curve based on Position 1. 1.
Credibility Assessment e
Conservatism Check for Pos. 1.1 CF when Surv. Data Non-Credible (3)
(1)
(2)
Temperature Correction (4)
Temperature Chemistry Surveillance Applied to Credible Chemistry Correction Correction Correction Data Credible Surv. Data for Applied to Credible Surv.
Are adjusted surveillance Applied for Applied for or Non-Application to Beltline Data for Application to Adjusted Delta-Adjusted - Predicted data within 2 sigma of the Capsule ID (Including Source)
Credibility?
Credibility?
Credible?
Credible?
Material?
Material?
Beltline Material?
Beltline Material?
RT(NDT) (F) ** Delta-RT(NDT) (F) ** applied CF trend curve? ** Capsule TMl2-LG1 (BWOG CR-3 lrrad.) -------Capsule CR3-LG1 (BWOG CR-3 lrrad.) -------Capsule TMl2-LG1 (BWOG CR-3 lrrad.) -------Three Mile Island Unit 1 Capsule C -------Three Mile Island Unit 1 Capsule E -------Surry Unit 1 Capsule T No No Non-Credible  
RT(NDT) (F) **
--171 56 Surry Unit 1 Capsule V No No Credible --250 42 Surry Unit 1 Capsu le X No No Credible --234 35 --------------------------------(1) For the credibility dete rmina tion, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irra diated in a single reactor (i.e., were irradiated at a similar temperature). (2) Fo r the credibility determination , a chemistry correct ion is not applied to measured values of transition temperature shift if applicable surveillance data were obtained from a single source (i.e., were machined from the same block of material). (3) For determination of the be l tline material chem i stry factor, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irr adiated in the reactor vessel which is being evaluated (i.e., were irradiated at a similar temperature). (4) For determination of the beltline material chemistry factor, a chemistry correction (i.e., ratio procedure) is not applied to measured values of transition temperature shift if the chem ic al composition of applicable surveillance data is essentially identical to the best-estimate chemical composition of the beltline material being evaluated. ----Cred i ble Credible Credible ----Page 8 of 18 Summary (SA-1526)
Delta-RT(NDT) (F) **
ET-NAF-990006 Tables.xis Table 2: Surry Unit 1 Weld Material SA-1526 (All Available Data) Data Used In Irradiation Assessing Temperature Measured Delta-Vessel? (Yes o r Capsule ID (Including Source) Copper (wt%) Nickel (wt%) (F) Fluence (x1E19) RT(NDT) (F) No) Capsule TMl2-LG1 (BWOG CR-3 lrrad.) 0.370 0.700 556.0 0.830 216 Yes Capsule CR3-LG1 (BWOG CR-3 lrrad.) 0.360 0.700 556.0 0.779 202 Yes Capsule TM12-LG1 (BWOG CR-3 lrrad.) 0.330 0.670 556.0 0.968 226 Yes Three Mile Island Unit 1 Capsule C 0.330 0.670 556.0 0.866 166 Yes Three Mile I sland Unit 1 Capsule E 0.330 0.670 556.0 0.107 74 Yes Surry Unit 1 Capsule T 0.230 0.640 533.9 0.281 171 Yes Surry Unit 1 Capsule V 0.230 0.640 538.8 1.940 250 Yes Surry Unit 1 Capsule X 0.230 0.640 542.0 1.599 234 Yes -----------------. . . . ---. . . . -Table 3: Surry Unit 1 Weld Material SA-1526 (All Available Data) Irrad iation Temperature Measu r ed Delta-Adjusted Delt a-Adjusted
applied CF trend curve? **
* Predicted Capsule ID (Including Source) Copper (wt%) Nickel (wt%) (F) Fluence Factor RT(NDT) (F) RT(NDT) (F)
Capsule TMl2-LG1 (BWOG CR-3 lrrad.)
Capsule CR3-LG1 (BWOG CR-3 lrrad.)
Capsule TMl2-LG1 (BWOG CR-3 lrrad.)
Three Mile Island Unit 1 Capsule C Three Mile Island Unit 1 Capsule E Surry Unit 1 Capsule T No No Non-Credible 171 56 Surry Unit 1 Capsule V No No Credible 250 42 Surry Unit 1 Capsule X No No Credible 234 35 (1) For the credibility determination, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in a single reactor (i.e., were irradiated at a similar temperature).
(2) For the credibility determination, a chemistry correction is not applied to measured values of transition temperature shift if applicable surveillance data were obtained from a single source (i.e., were machined from the same block of material).
(3) For determination of the beltline material chemistry factor, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in the reactor vessel which is being evaluated (i.e., were irradiated at a similar temperature).
(4) For determination of the beltline material chemistry factor, a chemistry correction (i.e., ratio procedure) is not applied to measured values of transition temperature shift if the chemical composition of applicable surveillance data is essentially identical to the best-estimate chemical composition of the beltline material being evaluated.
Credible Credible Credible Page 8 of 18 Summary (SA-1526)  
 
ET-NAF-990006 Tables.xis Table 2:
Surry Unit 1 Weld Material SA-1526 (All Available Data)
Data Used In Irradiation Assessing Temperature Measured Delta-Vessel? (Yes or Capsule ID (Including Source)
Copper (wt%) Nickel (wt%)
(F)
Fluence (x1E19)
RT(NDT) (F)
No)
Capsule TMl2-LG1 (BWOG CR-3 lrrad.)
0.370 0.700 556.0 0.830 216 Yes Capsule CR3-LG1 (BWOG CR-3 lrrad.)
0.360 0.700 556.0 0.779 202 Yes Capsule TM12-LG1 (BWOG CR-3 lrrad.)
0.330 0.670 556.0 0.968 226 Yes Three Mile Island Unit 1 Capsule C 0.330 0.670 556.0 0.866 166 Yes Three Mile Island Unit 1 Capsule E 0.330 0.670 556.0 0.107 74 Yes Surry Unit 1 Capsule T 0.230 0.640 533.9 0.281 171 Yes Surry Unit 1 Capsule V 0.230 0.640 538.8 1.940 250 Yes Surry Unit 1 Capsule X 0.230 0.640 542.0 1.599 234 Yes Table 3:
Surry Unit 1 Weld Material SA-1526 (All Available Data)
Irradiation Temperature Measured Delta-Adjusted Delta-Adjusted
* Predicted Capsule ID (Including Source)
Copper (wt%) Nickel (wt%)
(F)
Fluence Factor RT(NDT) (F)
RT(NDT) (F)
* Delta-RT(NDT) (F)
* Delta-RT(NDT) (F)
* Capsule TMl2-LG1 (BWOG CR-3 lrrad.) 0.370 0.700 556.0 0.9477 216 195 *12 Capsule CR3-LG1 (BWOG CR-3 lrrad.) 0.360 0.700 556.0 0.9299 202 185 -17 Capsule TMl2-LG1 (BWOG CR-3 lrrad.) 0.330 0.670 556.0 0.9909 226 221 6 Three Mile I s land Unit 1 Capsule C 0.330 0.670 556.0 0.9597 166 164 .45 Three Mile Island Unit 1 Capsule E 0.330 0.670 556.0 0.4305 74 77 -17 Surry Unit 1 C aps ule T 0.230 0.640 533.9 0.6 535 171 181 39 Surry Unit 1 Capsule V 0.230 0.640 538.8 1.1811 250 279 22 Surry Unit 1 Capsule X 0.230 0.640 542.0 1.1296 234 264 18 . -. -. . . . -. . -. . . . . . . -. -. -. . . -. . --* For credibility check, measured shift values are adjusted to average surveillance material chemistry and irradiation temperature as required. See Table 4. Page 9 of 18 Summary (SA-1526, Alt. 1)
* Capsule TMl2-LG1 (BWOG CR-3 lrrad.)
Table 4: Beltline Material ID SA-1526/299L44 ET-N A F-9 9000 6 Tables.x i s Surry U n i t 1 Weld Materia l SA-1526 (All Available Data) CF Determination Beltline Beltline Irradiation Surveillance Data Material Material Temperature Position 1.1 Chemistry Credib l e or Non-Copper (wt%) N i ckel (wt%) (F) Factor Cred i b l e? 0.340 0.680 542.0 220.6 Non-Credible
0.370 0.700 556.0 0.9477 216 195  
* If surveillance data are determined to be non-credible, the Position 1. 1 chemistry factor is applied to the beltline material. If Surv. Data Non-Chemistry Credib l e, Verify Factor App l ied Conservatism of to Beltline App l ied Position 1.1 Material* CF** 220.6 Conservative  
*12 Capsule CR3-LG1 (BWOG CR-3 lrrad.)
** Measured shift values are adjusted to the average surveillance material chemistry and irradiation temperature , and are verified to be within 2 sigma of the trend c u rve based on Position 1. 1. Credibility Assessment  
0.360 0.700 556.0 0.9299 202 185  
-Conservatism Check for Pos. 1.1 CF when Surv. Data Non-Credible (3) (1) (2) Temperature Correction (4) Temperature Chemistry Survei ll ance Applied to Cred i b l e Chem i stry Correction Correction Correction Data Credible Surv. Data for Appl i ed to Credib l e Surv. Are adjusted surveillance Applied for Applied for or Non-Application to Be l tline Data for A p p l i cation to Adjusted De l ta-Adjusted -P r edicted data within 2 sigma of the Capsule ID (Includ i ng Source) Credibility?
-17 Capsule TMl2-LG1 (BWOG CR-3 lrrad.)
0.330 0.670 556.0 0.9909 226 221 6
Three Mile Island Unit 1 Capsule C 0.330 0.670 556.0 0.9597 166 164  
.45 Three Mile Island Unit 1 Capsule E 0.330 0.670 556.0 0.4305 74 77  
-17 Surry Unit 1 Capsule T 0.230 0.640 533.9 0.6535 171 181 39 Surry Unit 1 Capsule V 0.230 0.640 538.8 1.1811 250 279 22 Surry Unit 1 Capsule X 0.230 0.640 542.0 1.1296 234 264 18
* For credibility check, measured shift values are adjusted to average surveillance material chemistry and irradiation temperature as required. See Table 4.
Page 9 of 18 Summary (SA-1526, Alt. 1)  
 
Table 4:
Beltline Material ID SA-1526/299L44 ET-NAF-990006 Tables.xis Surry Unit 1 Weld Material SA-1526 (All Available Data)
CF Determination Beltline Beltline Irradiation Surveillance Data Material Material Temperature Position 1.1 Chemistry Credible or Non-Copper (wt%) Nickel (wt%)
(F)
Factor Credible?
0.340 0.680 542.0 220.6 Non-Credible
* If surveillance data are determined to be non-credible, the Position 1. 1 chemistry factor is applied to the beltline material.
If Surv. Data Non-Chemistry Credible, Verify Factor Applied Conservatism of to Beltline Applied Position 1.1 Material
* CF**
220.6 Conservative  
** Measured shift values are adjusted to the average surveillance material chemistry and irradiation temperature, and are verified to be within 2 sigma of the trend curve based on Position 1. 1.
Credibility Assessment Conservatism Check for Pos. 1.1 CF when Surv. Data Non-Credible (3)
(1)
(2)
Temperature Correction (4)
Temperature Chemistry Surveillance Applied to Credible Chemistry Correction Correction Correction Data Credible Surv. Data for Applied to Credible Surv.
Are adjusted surveillance Applied for Applied for or Non-Application to Beltline Data for Application to Adjusted Delta-Adjusted - Predicted data within 2 sigma of the Capsule ID (Including Source)
Credibility?
Credibility?
Credibility?
Credible?
Credible?
Mater i a l? Be l tline M aterial? RT(NDT) (F) ** Delta-RT(NDT) (F) ** applied CF trend curve? ** Capsule TMl2-LG1 (BWOG CR-3 l rrad.) Yes Yes Credible --195 1 Capsule CR3-LG1 (BWOG CR-3 lrrad.) Yes Yes Credib l e --185 -5 Capsule TMl2-L G1 (BWOG CR-3 l rrad.) Yes Yes Credible --221 19 Three Mile Is l and Unit 1 Capsule C Yes Yes Non-Cred i ble --164 -32 Three Mile Is l and Unit 1 Capsule E Yes Yes Credible --77 -11 Surry Unit 1 Capsule T Yes Yes Non-Credible  
Material?
--181 47 Surry Unit 1 Capsule V Yes Yes Credible --279 37 Surry Unit 1 Capsule X Yes Yes Credible --264 33 --------------------------------(1) For the credibility determination , a temperature correction is not applied to measured values of trans i tion temperature shift i f applicable surveillance data were irrad i ated in a single reactor (i.e., were irradiated at a similar temperature). (2) For the credib i l i ty determination , a chemistry correction is not applied to measured values of transition temperature shift if app l icable surveillance data were obtained from a single source (i.e., were machined from the same block of material). (3) For determination of the beltline material chemistry factor, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in the reactor vessel which i s being evaluated (i.e., were irradiated at a s i milar temperature). (4) For determination of the beltline material chemistry factor, a chemistry correction (i.e., ratio procedure) is not applied to meas u red values of transition temperature shift if the chemical composition of applicable surveillance data is essentially identical to the best-estimate chemical composition of the beltline material being evaluated. Cred i ble Credible Cred i b l e Credible Credible Credible Credible Credible ---Page 10 of 18 Summary (SA-1526, Alt. 1)
Beltline Material?
ET-NAF-990006 Tables.xis Table 2: Surry Unit 1 Weld Material SA-1526 (All Data Except TMl-2) Data Used In Irradiation Assessing Temperature Measured Delta-Vessel? (Yes or Capsule ID (Including Source) Copper (wt%) Nickel (wt%) (F) Fluence (x1E19) RT(NDT) (F) No) Capsu le TMl2-LG1 (BWOG CR-3 l r rad.) 0.370 0.700 556.0 0.830 216 No Capsule CR3-LG1 (BWOG CR-3 lrrad.) 0.360 0.700 556.0 0.779 202 Yes Capsule TMl2-LG1 (BWOG CR-3 lrrad.) 0.330 0.670 556.0 0.968 226 No Three Mile Island Unit 1 Capsule C 0.330 0.670 556.0 0.866 166 Yes Three Mile Island Unit 1 Capsule E 0.330 0.670 556.0 0.107 74 Yes Surry Unit 1 Capsule T 0.230 0.640 533.9 0.281 171 Yes Surry Unit 1 Capsule V 0.230 0.640 538.8 1.940 250 Yes Surry Unit 1 Capsule X 0.230 0.640 542.0 1.599 234 Yes -. . . . . . . . . . . . . . . . -. -. . . . . -. Table 3: Surry Unit 1 Weld Material SA-1526 (All Data Except TMl-2) Irradiation Temperature Measured Delta-Adjusted Delta-Adjusted -Predicted Capsule ID (Includ i ng Source) Copper (wt%) Nickel (wt%) (F) Fluence Factor RT(NDT) (F) RT(NDT) (F)
RT(NDT) (F) **
* Delta-RT(NDT) (F) * . . . . . . . . Capsule CR3-LG1 (BWOG CR-3 lrrad.) 0.360 0.700 556.0 0.9299 202 181 -18 . . . . . . . . Three Mile Island Unit 1 Capsule C 0.330 0.670 556.0 0.9597 166 161 -44 Three Mile Island Unit 1 Capsule E 0.330 0.670 556.0 0.4305 74 76 Surry Unit 1 Capsule T 0.230 0.640 533.9 0.6535 1 71 178 38 Surry Unit 1 Capsule V 0.230 0.640 538.8 1.1811 250 273 20 Surry Unit 1 Capsule X 0.230 0.640 542.0 1.1296 234 258 16 . . . . . -. . . . . . . -. -. -. . . ---. . . . . . --* For credibility check , measured shift values are adjusted to average surveillance material chemistry and irradiation temperature as required. See Table 4. Page 11 of 18 Summary (SA-1526, Alt. 2)
Delta-RT(NDT) (F) **
Table 4: Be l tline Material ID SA-1526/299L44 ET-N A F-99 0 006 Tables.xis Surry Unit 1 Weld Material SA-1526 (All Data Except TMl-2) CF Determination Beltline Beltline I rradiation S u rve ill ance Data Material Material Temperature Position 1.1 Chem i stry Credible or Non-Copper (wt%) Nicke l (wt%) (F) Factor Credib l e? 0.340 0.680 542.0 220.6 Non-Credible
applied CF trend curve? **
* If swveillance data are determined to be non-credible, the Position 1.1 chemistry factor is applied to the beltline mate r ial . If Surv. Data Non-Chemistry Credib l e, Verify Factor Applied Conservatism of to Beltline Applied Pos i tion 1.1 Material*
Capsule TMl2-LG1 (BWOG CR-3 lrrad.)
CF** 220.6 Conservative  
Yes Yes Credible 195 1
.. Measured shift values are adjusted to the average surveillance material chemistry and irradiation t emperature, and are verified to be within 2 sigma of the trend curve based on Position 1. 1. Credibility Assessment  
Capsule CR3-LG1 (BWOG CR-3 lrrad.)
-Conservatism Check for Pos. 1.1 CF when Surv. Data Non-Credible (3) (1) (2) Temperat u re Correction (4) Temperature Chemistry Surveillance Applied to Credible Chemistry Correction Correction Correction Data Credible Surv. D ata for Appl i ed to Cred i b l e Surv. Are adj u sted surveillance Applied for Applied for or Non-Applicatio n to Beltline Data for Ap p lication to Adjusted Delta-Adjusted -Predicted data within 2 sigma of the Capsu l e ID (Including Source) Credibility?
Yes Yes Credible 185  
-5 Capsule TMl2-LG1 (BWOG CR-3 lrrad.)
Yes Yes Credible 221 19 Three Mile Island Unit 1 Capsule C Yes Yes Non-Credible 164  
-32 Three Mile Island Unit 1 Capsule E Yes Yes Credible 77  
-11 Surry Unit 1 Capsule T Yes Yes Non-Credible 181 47 Surry Unit 1 Capsule V Yes Yes Credible 279 37 Surry Unit 1 Capsule X Yes Yes Credible 264 33 (1) For the credibility determination, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in a single reactor (i.e., were irradiated at a similar temperature).
(2) For the credibility determination, a chemistry correction is not applied to measured values of transition temperature shift if applicable surveillance data were obtained from a single source (i.e., were machined from the same block of material).
(3) For determination of the beltline material chemistry factor, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in the reactor vessel which is being evaluated (i.e., were irradiated at a similar temperature).
(4) For determination of the beltline material chemistry factor, a chemistry correction (i.e., ratio procedure) is not applied to measured values of transition temperature shift if the chemical composition of applicable surveillance data is essentially identical to the best-estimate chemical composition of the beltline material being evaluated.
Credible Credible Credible Credible Credible Credible Credible Credible Page 10 of 18 Summary (SA-1526, Alt. 1)  
 
ET-NAF-990006 Tables.xis Table 2:
Surry Unit 1 Weld Material SA-1526 (All Data Except TMl-2)
Data Used In Irradiation Assessing Temperature Measured Delta-Vessel? (Yes or Capsule ID (Including Source)
Copper (wt%) Nickel (wt%)
(F)
Fluence (x1E19)
RT(NDT) (F)
No)
Capsule TMl2-LG1 (BWOG CR-3 lrrad.)
0.370 0.700 556.0 0.830 216 No Capsule CR3-LG1 (BWOG CR-3 lrrad.)
0.360 0.700 556.0 0.779 202 Yes Capsule TMl2-LG1 (BWOG CR-3 lrrad.)
0.330 0.670 556.0 0.968 226 No Three Mile Island Unit 1 Capsule C 0.330 0.670 556.0 0.866 166 Yes Three Mile Island Unit 1 Capsule E 0.330 0.670 556.0 0.107 74 Yes Surry Unit 1 Capsule T 0.230 0.640 533.9 0.281 171 Yes Surry Unit 1 Capsule V 0.230 0.640 538.8 1.940 250 Yes Surry Unit 1 Capsule X 0.230 0.640 542.0 1.599 234 Yes Table 3:
Surry Unit 1 Weld Material SA-1526 (All Data Except TMl-2)
Irradiation Temperature Measured Delta-Adjusted Delta-Adjusted - Predicted Capsule ID (Including Source)
Copper (wt%) Nickel (wt%)
(F)
Fluence Factor RT(NDT) (F)
RT(NDT) (F)
* Delta-RT(NDT) (F)
* Capsule CR3-LG1 (BWOG CR-3 lrrad.)
0.360 0.700 556.0 0.9299 202 181  
-18 Three Mile Island Unit 1 Capsule C 0.330 0.670 556.0 0.9597 166 161  
-44 Three Mile Island Unit 1 Capsule E 0.330 0.670 556.0 0.4305 74 76  
-16 Surry Unit 1 Capsule T 0.230 0.640 533.9 0.6535 171 178 38 Surry Unit 1 Capsule V 0.230 0.640 538.8 1.1811 250 273 20 Surry Unit 1 Capsule X 0.230 0.640 542.0 1.1296 234 258 16
* For credibility check, measured shift values are adjusted to average surveillance material chemistry and irradiation temperature as required. See Table 4.
Page 11 of 18 Summary (SA-1526, Alt. 2)  
 
Table 4:
Beltline Material ID SA-1526/299L44 ET-NAF-990006 Tables.xis Surry Unit 1 Weld Material SA-1526 (All Data Except TMl-2)
CF Determination Beltline Beltline Irradiation Surveillance Data Material Material Temperature Position 1.1 Chemistry Credible or Non-Copper (wt%) Nickel (wt%)
(F)
Factor Credible?
0.340 0.680 542.0 220.6 Non-Credible
* If swveillance data are determined to be non-credible, the Position 1.1 chemistry factor is applied to the beltline material.
If Surv. Data Non-Chemistry Credible, Verify Factor Applied Conservatism of to Beltline Applied Position 1.1 Material*
CF **
220.6 Conservative  
.. Measured shift values are adjusted to the average surveillance material chemistry and irradiation temperature, and are verified to be within 2 sigma of the trend curve based on Position 1. 1.
Credibility Assessment Conservatism Check for Pos. 1.1 CF when Surv. Data Non-Credible (3)
(1)
(2)
Temperature Correction (4)
Temperature Chemistry Surveillance Applied to Credible Chemistry Correction Correction Correction Data Credible Surv. Data for Applied to Credible Surv.
Are adjusted surveillance Applied for Applied for or Non-Application to Beltline Data for Application to Adjusted Delta-Adjusted - Predicted data within 2 sigma of the Capsule ID (Including Source)
Credibility?
Credibility?
Credibility?
Cre d ible? Mater i a l? Be l tl i ne Material?
Credible?
RT(NDT) (F) ** Delta-RT(N D T) (F) ** applied CF trend curve? ** Capsu l e TM l 2-LG1 (BWOG CR-3 l rrad.) -------Capsule CR3-LG1 (BWOG CR-3 lrrad.) Yes Yes Credib l e --181 -3 Capsule TMl2-LG1 (BWOG CR-3 lrrad.} -------Three Mile Island Unit 1 Capsule C Yes Yes Non-Credible  
Material?
--161 -29 Three Mile Is l and Unit 1 Capsule E Yes Yes Credible --76 -9 Surry Unit 1 Capsule T Yes Yes Non-Credible . -178 48 Surry Unit 1 Capsule V Yes Yes Credible -. 273 38 Surry Unit 1 Capsule X Yes Yes Cred i ble . -258 34 --------------------------------(1) For the cred i bi l ity determination, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in a single reactor (i.e., were i rrad i ated at a similar temperature).
Beltline Material?
(2) For the credibility determination, a chemistry correction is not applied to measured values of trans i tion temperature shift if app l icable surveillance data were obtained from a single source (i.e., were machined from the same b l ock of materia l). (3) For determination of the beltline mater i al chemistry factor, a temperature correction is not applied to measured values of transition temperat u re shift if applicable surve i llance data were i rradiated in the reactor vessel which is being evaluated (i.e., were irradiated at a similar temperature).
RT(NDT) (F) **
(4) For determination of the beltline material chemistry factor, a chemistry correction (i.e., ratio procedure) is not applied to measured values of transition temperature shift if the chemical composition of applicable surve i llance data is essent i ally ident i cal to the best-estimate chemical composition of the be l tl i ne material being eva lu ated. -Credible -Credible Credible Credible Credible Credib l e ----Page 12 of 18 Summary (S A-1526, Alt. 2) -
Delta-RT(NDT) (F) **
ET-NAF-990006 Tables.xis Table 2: Surry Unit 1 Weld Material SA-1526 (All Data, No Adjustments)
applied CF trend curve? **
Data Used In Irradiation Assessing Temperature Measured Delta-Vessel? (Yes or Capsule ID (Including Source) Copper (wt%) Nickel (wt%) (F) Fluence (x1E19) RT(NDT) (F) No) Capsule TM12-LG1 (BWOG CR-3 lrrad.) 0.370 0.700 556.0 0.830 216 Yes Capsule CR3-LG1 (BWOG CR-3 lrrad.) 0.360 0.700 556.0 0.779 202 Yes Capsule TMl2-LG1 (BWOG CR-3 lrrad.) 0.330 0.670 556.0 0.968 226 Yes Three Mile Islan d Unit 1 Capsule C 0.330 0.670 556.0 0.866 166 Yes Three Mile Island Unit 1 Capsule E 0.330 0.670 556.0 0.107 74 Yes Surry Unit 1 Capsule T 0.230 0.640 533.9 0.281 171 Yes Surry Unit 1 Capsule V 0.230 0.640 538.8 1.940 250 Yes Surry Unit 1 Capsu l e X 0.230 0.640 542.0 1.599 234 Yes ----------------------------Table 3: Surry Unit 1 Weld Material SA-1526 (All Data, No Adjustments)
Capsule TMl2-LG1 (BWOG CR-3 lrrad.)
Irradiation Temperature Measured Delta-Adjusted Delta-Adjusted -Predicted Capsule ID (Including Source) Copper (wt%) Nickel (wt%) (F) Fluence Factor RT(NDT) (F) RT(NDT) (F)
Capsule CR3-LG1 (BWOG CR-3 lrrad.)
Yes Yes Credible 181  
-3 Capsule TMl2-LG1 (BWOG CR-3 lrrad.}
Three Mile Island Unit 1 Capsule C Yes Yes Non-Credible 161
-29 Three Mile Island Unit 1 Capsule E Yes Yes Credible 76  
-9 Surry Unit 1 Capsule T Yes Yes Non-Credible 178 48 Surry Unit 1 Capsule V Yes Yes Credible 273 38 Surry Unit 1 Capsule X Yes Yes Credible 258 34 (1) For the credibility determination, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in a single reactor (i.e., were irradiated at a similar temperature).
(2) For the credibility determination, a chemistry correction is not applied to measured values of transition temperature shift if applicable surveillance data were obtained from a single source (i.e., were machined from the same block of material).
(3) For determination of the beltline material chemistry factor, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in the reactor vessel which is being evaluated (i.e., were irradiated at a similar temperature).
(4) For determination of the beltline material chemistry factor, a chemistry correction (i.e., ratio procedure) is not applied to measured values of transition temperature shift if the chemical composition of applicable surveillance data is essentially identical to the best-estimate chemical composition of the beltline material being evaluated.
Credible Credible Credible Credible Credible Credible Page 12 of 18 Summary (SA-1526, Alt. 2)  
 
ET-NAF-990006 Tables.xis Table 2:
Surry Unit 1 Weld Material SA-1526 (All Data, No Adjustments)
Data Used In Irradiation Assessing Temperature Measured Delta-Vessel? (Yes or Capsule ID (Including Source)
Copper (wt%) Nickel (wt%)
(F)
Fluence (x1E19)
RT(NDT) (F)
No)
Capsule TM12-LG1 (BWOG CR-3 lrrad.)
0.370 0.700 556.0 0.830 216 Yes Capsule CR3-LG1 (BWOG CR-3 lrrad.)
0.360 0.700 556.0 0.779 202 Yes Capsule TMl2-LG1 (BWOG CR-3 lrrad.)
0.330 0.670 556.0 0.968 226 Yes Three Mile Island Unit 1 Capsule C 0.330 0.670 556.0 0.866 166 Yes Three Mile Island Unit 1 Capsule E 0.330 0.670 556.0 0.107 74 Yes Surry Unit 1 Capsule T 0.230 0.640 533.9 0.281 171 Yes Surry Unit 1 Capsule V 0.230 0.640 538.8 1.940 250 Yes Surry Unit 1 Capsule X 0.230 0.640 542.0 1.599 234 Yes Table 3:
Surry Unit 1 Weld Material SA-1526 (All Data, No Adjustments)
Irradiation Temperature Measured Delta-Adjusted Delta-Adjusted - Predicted Capsule ID (Including Source)
Copper (wt%) Nickel (wt%)
(F)
Fluence Factor RT(NDT) (F)
RT(NDT) (F)
* Delta-RT(NDT) (F)
* Delta-RT(NDT) (F)
* Capsule TMl2-LG1 (BWOG CR-3 lrrad.) 0.370 0.700 556.0 0.9477 216 216 14 Capsule CR3-LG1 (BWOG CR-3 lrrad.) 0.360 0.700 556.0 0.9299 202 202 4 Capsule TMl2-LG1 (BWOG CR-3 lrrad.) 0.330 0.670 556.0 0.9909 226 226 15 Three Mile Island Unit 1 Capsule C 0.330 0.670 556.0 0.9597 166 166 -38 Three Mile Island Unit 1 Capsule E 0.330 0.670 556.0 0.4305 74 74 -18 e Surry Unit 1 Capsule T 0.230 0.640 533.9 0.6535 171 171 32 Surry Unit 1 Capsule V 0.230 0.640 538.8 1.1811 250 250 -1 Surry Unit 1 Capsule X 0.230 0.640 542.0 1.1296 234 234 -------------------------------* For credibility check , measured shift values are adjusted to average surveillance material chemistry and irradiation temperature as required.
* Capsule TMl2-LG1 (BWOG CR-3 lrrad.)
See Table 4. Page 13 of 18 Summary (SA-1526, Alt. 3)
0.370 0.700 556.0 0.9477 216 216 14 Capsule CR3-LG1 (BWOG CR-3 lrrad.)
Table 4: ET-NAF-990006 Tables.xis Surry Unit 1 Weld Material SA-1526 (All Data, No Adjustments)
0.360 0.700 556.0 0.9299 202 202 4
CF Determination Chemistry Beltline Beltline Irradiation Surveillance Data Factor Applied Material Material Temperature Position 1.1 Chemistry Credible or Non-to Beltline Beltline Material ID Copper (wt%) Nickel (wt%) (F) Factor Credible?
Capsule TMl2-LG1 (BWOG CR-3 lrrad.)
0.330 0.670 556.0 0.9909 226 226 15 Three Mile Island Unit 1 Capsule C 0.330 0.670 556.0 0.9597 166 166  
-38 Three Mile Island Unit 1 Capsule E 0.330 0.670 556.0 0.4305 74 74  
-18 e
Surry Unit 1 Capsule T 0.230 0.640 533.9 0.6535 171 171 32 Surry Unit 1 Capsule V 0.230 0.640 538.8 1.1811 250 250  
-1 Surry Unit 1 Capsule X 0.230 0.640 542.0 1.1296 234 234  
-6
* For credibility check, measured shift values are adjusted to average surveillance material chemistry and irradiation temperature as required. See Table 4.
Page 13 of 18 Summary (SA-1526, Alt. 3)  
 
Table 4:
ET-NAF-990006 Tables.xis Surry Unit 1 Weld Material SA-1526 (All Data, No Adjustments)
CF Determination Chemistry Beltline Beltline Irradiation Surveillance Data Factor Applied Material Material Temperature Position 1.1 Chemistry Credible or Non-to Beltline Beltline Material ID Copper (wt%) Nickel (wt%)
(F)
Factor Credible?
Material*
Material*
SA-1526/299L44 0.340 0.680 542.0 220.6 Non-Credible 220.6
SA-1526/299L44 0.340 0.680 542.0 220.6 Non-Credible 220.6
* If surveillance data are determined to be non-credib le , the Position 1. 1 chemistry factor is applied to the beltline material. If Surv. Data Non-Credible, Verify Conservatism of Applied Position 1.1 CF** Conservative  
* If surveillance data are determined to be non-credible, the Position 1. 1 chemistry factor is applied to the beltline material.
.. Measured shift values are adjusted to the average surveillance material chemistry and irradiation temperature , and are verified to be within 2 sigma of the trend curve based on Position 1. 1. Credibility Assessment e Conservatism Check for Pas. 1.1 CF when Surv. Data Non-Credible (3) (1) (2) Temperature Correction (4) Temperature Chemistry Surveillance Applied to Credible Chemistry Correction Correction Correction Data Credible Surv. Data for Applied to Credible Surv. Are adjusted surveillance Applied for Applied for or Non-Application to Beltline Data for Application to Adjusted Delta-Adjusted -Predicted data within 2 sigma of the Capsule ID (Includ i ng Source) Credibility?
If Surv. Data Non-Credible, Verify Conservatism of Applied Position 1.1 CF**
Conservative  
.. Measured shift values are adjusted to the average surveillance material chemistry and irradiation temperature, and are verified to be within 2 sigma of the trend curve based on Position 1. 1.
Credibility Assessment e
Conservatism Check for Pas. 1.1 CF when Surv. Data Non-Credible (3)
(1)
(2)
Temperature Correction (4)
Temperature Chemistry Surveillance Applied to Credible Chemistry Correction Correction Correction Data Credible Surv. Data for Applied to Credible Surv.
Are adjusted surveillance Applied for Applied for or Non-Application to Beltline Data for Application to Adjusted Delta-Adjusted - Predicted data within 2 sigma of the Capsule ID (Including Source)
Credibility?
Credibility?
Credibility?
Credible?
Credible?
Material?
Material?
Beltline Material?
Beltline Material?
RT(NDT) (F) ** Delta-RT(NDT) (F) ** applied CF trend curve? ** Capsule TMl2-LG1 (BWOG CR-3 lrrad.) No No Credible --216 22 Capsule CR3-LG1 (BWOG CR-3 lrrad.) No No Credible --202 12 Capsule TMl2-LG1 (BWOG CR-3 lrrad.) No No Credible --226 23 Three Mile Island Unit 1 Capsule C No No Non-Credible  
RT(NDT) (F) **
--166 -30 Three Mile Island Unit 1 Capsule E No No Credible --74 -14 Surry Unit 1 Capsule T No No Non-Credible  
Delta-RT(NDT) (F) **
--171 37 Surry Unit 1 Capsule V No No Credible --250 8 Surry Unit 1 Capsule X No No Credible --234 3 --------------------------------(1) F o r the credibility determination, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in a single reactor (i.e., were irradiated at a similar temperature).
applied CF trend curve? **
(2) For the credibi li ty determination , a chemistry correction is not applied to measured values of transition temp erature shift if applicable surveillance data were obtained from a single source (i.e., were machined from the same block of material). (3) For determ i nation of the beltline material chemistry factor, a temperature correction is not appl i ed to measured values of transition temperature shift if applicable surveillance data were irradiated in the reactor vessel wh i ch is being evaluated (i.e., were irradiated at a similar temperature). (4) For determination of the beltline material chemistry factor, a chemistry correction (i.e., ratio procedure) is not applied to measured values of transition temperature shift if the chemical composition of applicable surveillance data is essentially identical to the best-estimate chemical composition of the beltline material being evaluated.
Capsule TMl2-LG1 (BWOG CR-3 lrrad.)
Credible Credible Credible Credible Credible Credible Cr edible Credible ----Page 14 of 18 Summary (SA-1526 , A l t. 3)
No No Credible 216 22 Capsule CR3-LG1 (BWOG CR-3 lrrad.)
ET-NAF-990006 Tables.xis Table 2: Surry Unit 1 Weld Material SA-1526 (All Data Except Surry Unit 1 Data) Data Used In Irradiation Assessing Temperature Measured Delta-Vessel? (Yes or Capsule ID (Including Source) Copper (wt%) Nickel (wt%) (F) Fluence (x1E19) RT(NDT) (F) No) Capsule TMl2-LG1 (BWOG CR-3 lrrad.) 0.370 0.700 556.0 0.830 216 Yes Capsule CA3-LG1 (BWOG CR-3 lrrad.) 0.360 0.700 556.0 0.779 202 Yes Capsule TMl2-LG1 (BWOG CA-3 lrrad.) 0.330 0.670 556.0 0.968 226 Yes Three Mile Island Unit 1 Capsule C 0.330 0.670 556.0 0.866 166 Yes Three Mile Island Unit 1 Capsule E 0.330 0.670 556.0 0.107 74 Yes Surry Unit 1 Capsule T 0.230 0.640 533.9 0.281 171 No Surry Unit 1 Capsule V 0.230 0.640 538.8 1.940 250 No Surry Un i t 1 Capsule X 0.230 0.640 542.0 1.599 234 No e ----------------------------Table 3: Surry Unit 1 Weld Material SA-1526 (All Data Except Surry Unit 1 Data) Irradiation Temperature Measured Delta-Adjusted Delta-Adjusted -Predicted Capsule ID (Includ i ng Source) Copper (wt%) Nickel (wt%) (F) Fluence Factor RT(NDT) (F) AT(NDT) (F)
No No Credible 202 12 Capsule TMl2-LG1 (BWOG CR-3 lrrad.)
No No Credible 226 23 Three Mile Island Unit 1 Capsule C No No Non-Credible 166
-30 Three Mile Island Unit 1 Capsule E No No Credible 74  
-14 Surry Unit 1 Capsule T No No Non-Credible 171 37 Surry Unit 1 Capsule V No No Credible 250 8
Surry Unit 1 Capsule X No No Credible 234 3
(1) For the credibility determination, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in a single reactor (i.e., were irradiated at a similar temperature).
(2) For the credibility determination, a chemistry correction is not applied to measured values of transition temperature shift if applicable surveillance data were obtained from a single source (i.e., were machined from the same block of material).
(3) For determination of the beltline material chemistry factor, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in the reactor vessel which is being evaluated (i.e., were irradiated at a similar temperature).
(4) For determination of the beltline material chemistry factor, a chemistry correction (i.e., ratio procedure) is not applied to measured values of transition temperature shift if the chemical composition of applicable surveillance data is essentially identical to the best-estimate chemical composition of the beltline material being evaluated.
Credible Credible Credible Credible Credible Credible Credible Credible Page 14 of 18 Summary (SA-1526, Alt. 3)  
 
ET-NAF-990006 Tables.xis Table 2:
Surry Unit 1 Weld Material SA-1526 (All Data Except Surry Unit 1 Data)
Data Used In Irradiation Assessing Temperature Measured Delta-Vessel? (Yes or Capsule ID (Including Source)
Copper (wt%) Nickel (wt%)
(F)
Fluence (x1E19)
RT(NDT) (F)
No)
Capsule TMl2-LG1 (BWOG CR-3 lrrad.)
0.370 0.700 556.0 0.830 216 Yes Capsule CA3-LG1 (BWOG CR-3 lrrad.)
0.360 0.700 556.0 0.779 202 Yes Capsule TMl2-LG1 (BWOG CA-3 lrrad.)
0.330 0.670 556.0 0.968 226 Yes Three Mile Island Unit 1 Capsule C 0.330 0.670 556.0 0.866 166 Yes Three Mile Island Unit 1 Capsule E 0.330 0.670 556.0 0.107 74 Yes Surry Unit 1 Capsule T 0.230 0.640 533.9 0.281 171 No Surry Unit 1 Capsule V 0.230 0.640 538.8 1.940 250 No Surry Unit 1 Capsule X 0.230 0.640 542.0 1.599 234 No e
Table 3:
Surry Unit 1 Weld Material SA-1526 (All Data Except Surry Unit 1 Data)
Irradiation Temperature Measured Delta-Adjusted Delta-Adjusted - Predicted Capsule ID (Including Source)
Copper (wt%) Nickel (wt%)
(F)
Fluence Factor RT(NDT) (F)
AT(NDT) (F)
* Delta-AT(NDT) (F)
* Delta-AT(NDT) (F)
* Capsule TMl2-LG1 (BWOG CR-3 lrrad.) 0.370 0.700 556.0 0.9477 216 205 7 Capsule CA3-LG1 (BWOG CR-3 lrrad.) 0.360 0.700 556.0 0.9299 202 195 1 Capsule TM12-LG1 (BWOG CA-3 lrrad.) 0.330 0.670 556.0 0.9909 226 233 26 Three Mile Island Unit 1 Capsule C 0.330 0.670 556.0 0.9597 166 171 -29 Three Mile Island Un i t 1 Capsule E 0.330 0.670 556.0 0.4305 74 76 --------------------------------------------------------* F or credibility check , measured shift values are adjusted to average surveillance material chemistry and irradiation temperature as required. See Table 4. Page 15 of 18 Summary (SA-1526, Alt. 4)
* Capsule TMl2-LG1 (BWOG CR-3 lrrad.)
Table 4: Beltline Material ID SA-1526/299L44 ET-NAF-990006 Tables.x i s Surry Unit 1 Weld Material SA-1526 (All Data Except Surry Unit 1 Data) CF Determination Chemistry Beltline Beltline Irradiation Surveillance Data Factor Applied Material Material Temperature Position 1.1 Chemistry Credible or Non-to Beltl i ne Copper (wt%) Nickel (wt%) (F) Factor Credible?
0.370 0.700 556.0 0.9477 216 205 7
Capsule CA3-LG1 (BWOG CR-3 lrrad.)
0.360 0.700 556.0 0.9299 202 195 1
Capsule TM12-LG1 (BWOG CA-3 lrrad.)
0.330 0.670 556.0 0.9909 226 233 26 Three Mile Island Unit 1 Capsule C 0.330 0.670 556.0 0.9597 166 171  
-29 Three Mile Island Unit 1 Capsule E 0.330 0.670 556.0 0.4305 74 76  
-13
* For credibility check, measured shift values are adjusted to average surveillance material chemistry and irradiation temperature as required. See Table 4.
Page 15 of 18 Summary (SA-1526, Alt. 4)  
 
Table 4:
Beltline Material ID SA-1526/299L44 ET-NAF-990006 Tables.xis Surry Unit 1 Weld Material SA-1526 (All Data Except Surry Unit 1 Data)
CF Determination Chemistry Beltline Beltline Irradiation Surveillance Data Factor Applied Material Material Temperature Position 1.1 Chemistry Credible or Non-to Beltline Copper (wt%) Nickel (wt%)
(F)
Factor Credible?
Material*
Material*
0.340 0.680 542.0 220.6 Non-Credible 220.6
0.340 0.680 542.0 220.6 Non-Credible 220.6
* If surveillance data are determined to be non-credible, the Position 1. 1 chemistry factor is applied to the beltline material. If Surv. Data Non-Credible, Verify Conservatism of Applied Position 1.1 CF** Conservative  
* If surveillance data are determined to be non-credible, the Position 1. 1 chemistry factor is applied to the beltline material.
** Measured shift v alues are adjusted to the average surveillance material chemistry and irradiation temperature, and are verified to be within 2 sigma of the trend curve based on Position 1. 1. Credibility Assessment e Conservatism Check for Pos. 1.1 CF when Surv. Data Non-Credible (3) (1) (2) Temperat u re Correction (4) Temperature Chemistry Surveillance Applied to Credible Chemistry Correction Correction Correction Data Credible Surv. Data for Applied to Credible Surv. Are adjusted surveillance Applied for Applied for or Non-Application to Beltline Data for Application to Adjusted Delta-Adjusted -Predicted data within 2 sigma of the Capsule ID (Includ i ng Source) Credibility?
If Surv. Data Non-Credible, Verify Conservatism of Applied Position 1.1 CF**
Conservative  
** Measured shift values are adjusted to the average surveillance material chemistry and irradiation temperature, and are verified to be within 2 sigma of the trend curve based on Position 1. 1.
Credibility Assessment e
Conservatism Check for Pos. 1.1 CF when Surv. Data Non-Credible (3)
(1)
(2)
Temperature Correction (4)
Temperature Chemistry Surveillance Applied to Credible Chemistry Correction Correction Correction Data Credible Surv. Data for Applied to Credible Surv.
Are adjusted surveillance Applied for Applied for or Non-Application to Beltline Data for Application to Adjusted Delta-Adjusted - Predicted data within 2 sigma of the Capsule ID (Including Source)
Credibility?
Credibility?
Credibility?
Credible?
Credible?
Material?
Material?
Beltline Material?
Beltline Material?
RT(NDT) (F) ** Delta-RT(NDT) (F) ** applied CF trend curve? ** Capsule TMl2-LG1 (BWOG CR-3 lrrad.) Yes Yes Credible --205 -5 Capsule CR3-LG1 (BWOG CR-3 lrrad.) Yes Yes Credible --195 -12 Capsule TMl2-LG1 (BWOG CR-3 lrrad.) Yes Yes Credible --233 13 Three Mile Island Unit 1 Capsule C Yes Yes Non-Credible . -171 -42 Three Mile Island Unit 1 Capsule E Yes Yes Credible --76 -19 Surry Unit 1 Capsule T -------Surry Unit 1 Capsule V -------Surry Unit 1 Capsule X ---------------------------------------(1) For the credibility determination, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in a single reactor (i.e., were irradiated at a similar temperature).
RT(NDT) (F) **
(2) For the credibility determination, a chemistry correction is not applied to measured values of transition temperature shift if applicable surveillance data were obtained from a single source (i.e., were machined from the same block of material). (3) For determination of the beltline material chemistry factor , a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in the reactor vessel which is being evaluated (i.e., were irradiated at a similar temperature).
Delta-RT(NDT) (F) **
(4) For determination of the beltline material chemistry factor, a chemistry correction (i.e., ratio procedure) is not applied to measured values of transition temperature shift if the chemical composition of appl i cable surveillance data is essentially identical to the best-estimate chemical composition of the beltline material being evaluated.
applied CF trend curve? **
Credible Credible Credible Credible Credib l e -------Page 16 of 18 Summary (SA-1526, Alt. 4)
Capsule TMl2-LG1 (BWOG CR-3 lrrad.)
ET-NAF-990006 Tables.xis Table 2: Surry Unit 2 Weld Material R3008 Data Used I n Irradiation Assessing Temperature Measured Delta-Ve ssel? (Yes or Capsule ID (Including Source) Copper (wt%) Nickel (wt%) (F) Fluence (x1 E 19) RT(NDT) (F) No) Surry Unit 2 Capsule X 0.190 0.550 534.9 0.302 # 96 ,, Yes Surry Unit 2 Capsule V 0.190 0.550 540.1 1.880 140 Yes ----------------------------------------------------------------------Table 3: Surry Unit 2 Weld Material R3008 Irradiation Temperature Measu red Delta-Adjusted Delta-Adjusted -Predicted Capsule ID (Including Sou r ce) Copper (wt%) Nickel (wt%) (F) Fluence Factor RT(NDT) (F) RT(NDT) (F)
Yes Yes Credible 205  
-5 Capsule CR3-LG1 (BWOG CR-3 lrrad.)
Yes Yes Credible 195  
-12 Capsule TMl2-LG1 (BWOG CR-3 lrrad.)
Yes Yes Credible 233 13 Three Mile Island Unit 1 Capsule C Yes Yes Non-Credible 171  
-42 Three Mile Island Unit 1 Capsule E Yes Yes Credible 76  
-19 Surry Unit 1 Capsule T Surry Unit 1 Capsule V Surry Unit 1 Capsule X (1) For the credibility determination, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in a single reactor (i.e., were irradiated at a similar temperature).
(2) For the credibility determination, a chemistry correction is not applied to measured values of transition temperature shift if applicable surveillance data were obtained from a single source (i.e., were machined from the same block of material).
(3) For determination of the beltline material chemistry factor, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in the reactor vessel which is being evaluated (i.e., were irradiated at a similar temperature).
(4) For determination of the beltline material chemistry factor, a chemistry correction (i.e., ratio procedure) is not applied to measured values of transition temperature shift if the chemical composition of applicable surveillance data is essentially identical to the best-estimate chemical composition of the beltline material being evaluated.
Credible Credible Credible Credible Credible Page 16 of 18 Summary (SA-1526, Alt. 4)  
 
ET-NAF-990006 Tables.xis Table 2:
Surry Unit 2 Weld Material R3008 Data Used In Irradiation Assessing Temperature Measured Delta-Vessel? (Yes or Capsule ID (Including Source)
Copper (wt%) Nickel (wt%)
(F)
Fluence (x1 E 19)
RT(NDT) (F)
No)
Surry Unit 2 Capsule X 0.190 0.550 534.9 0.302 96 Yes Surry Unit 2 Capsule V 0.190 0.550 540.1 1.880 140 Yes Table 3:
Surry Unit 2 Weld Material R3008 Irradiation Temperature Measured Delta-Adjusted Delta-Adjusted - Predicted Capsule ID (Including Source)
Copper (wt%) Nickel (wt%)
(F)
Fluence Factor RT(NDT) (F)
RT(NDT) (F)
* Delta-RT(NDT) (F)
* Delta-RT(NDT) (F)
* Surry Unit 2 Capsule X 0.190 0.550 534.9 0.6720 96 96 12 Surry Unit 2 Capsule V 0.190 0.550 540.1 1.1 729 140 140 --------------------------------. ----------------------------------. ----------* For credibility check, measured shift values are adjusted to average surveillance material chemistry and irradiation temperature as required. See Table 4. Page 17 of 18 Summary (R3008)
* Surry Unit 2 Capsule X 0.190 0.550 534.9 0.6720 96 96 12 Surry Unit 2 Capsule V 0.190 0.550 540.1 1.1729 140 140  
Table 4: Beltline Material ID R3008 ET-NAF-990006 Tables.xis Surry Unit 2 Weld Material R3008 CF Determination Beltline Beltline Irradiation Material Material Temperature Position 1 .1 Chemistry Copper (wt%) Nickel (wt%) (F) Factor 0.190 0.550 543.1 149.3 Surveil)ance Data Credible or Non-Credible?
-7
Credible 'ff surveillance data are determined to be non-credible, the Position 1.1 chemistry factor is applied to the beltline material.
* For credibility check, measured shift values are adjusted to average surveillance material chemistry and irradiation temperature as required. See Table 4.
Page 17 of 18 Summary (R3008)  
 
Table 4:
Beltline Material ID R3008 ET-NAF-990006 Tables.xis Surry Unit 2 Weld Material R3008 CF Determination Beltline Beltline Irradiation Material Material Temperature Position 1.1 Chemistry Copper (wt%) Nickel (wt%)
(F)
Factor 0.190 0.550 543.1 149.3 Surveil)ance Data Credible or Non-Credible?
Credible  
'ff surveillance data are determined to be non-credible, the Position 1.1 chemistry factor is applied to the beltline material.
If Surv. Data Non-Chemistry Credible, Verify Factor Applied Conservatism of to Beltline Applied Position 1.1 Material*
If Surv. Data Non-Chemistry Credible, Verify Factor Applied Conservatism of to Beltline Applied Position 1.1 Material*
CF** 125.2 -** Measured shift values are adjusted to the average surveillance material chemistry and irradiation temperature, and are verified to be within 2 sigma of the trend curve based on Position 1.1. Credibility Assessment e Conservatism Check for Pos. 1.1 CF when Surv. Data Non-Credible (3) (1) (2) Temperature Correction (4) Temperature Chemistry Surveillance Applied to Credible Chemistry Correction Correction Correction Data Credible Surv. Data for Applied to Credible Surv. Are adjusted surveillance Applied for Applied for or Non-Application to Beltline Data for Application to Adjusted Delta-Adjusted -Predicted data within 2 sigma of the Capsule ID (Including Source) Credibility?
CF**
125.2  
** Measured shift values are adjusted to the average surveillance material chemistry and irradiation temperature, and are verified to be within 2 sigma of the trend curve based on Position 1.1.
Credibility Assessment e
Conservatism Check for Pos. 1.1 CF when Surv. Data Non-Credible (3)
(1)
(2)
Temperature Correction (4)
Temperature Chemistry Surveillance Applied to Credible Chemistry Correction Correction Correction Data Credible Surv. Data for Applied to Credible Surv.
Are adjusted surveillance Applied for Applied for or Non-Application to Beltline Data for Application to Adjusted Delta-Adjusted - Predicted data within 2 sigma of the Capsule ID (Including Source)
Credibility?
Credibility?
Credibility?
Credible?
Credible?
Material?
Material?
Beltline Material?
Beltline Material?
RT(NDT) (F) ** Delta-RT(NDT) (F) ** applied CF trend curve? ** Surry Unit 2 Capsule X No No Credible No No --Surry Unit 2 Capsule V No No Credible No No ----------------------------------------------------------------------------------(1) For the credibility determination, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in a single reactor (i.e., were irradiated at a similar temperature).
RT(NDT) (F) **
Delta-RT(NDT) (F) **
applied CF trend curve? **
Surry Unit 2 Capsule X No No Credible No No Surry Unit 2 Capsule V No No Credible No No (1) For the credibility determination, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in a single reactor (i.e., were irradiated at a similar temperature).
(2) For the credibility determination, a chemistry correction is not applied to measured values of transition temperature shift if applicable surveillance data were obtained from a single source (i.e., were machined from the same block of material).
(2) For the credibility determination, a chemistry correction is not applied to measured values of transition temperature shift if applicable surveillance data were obtained from a single source (i.e., were machined from the same block of material).
(3) For determination of the beltline material chemistry factor, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in the reactor vessel which is being evaluated (i.e., were irradiated at a similar temperature).
(3) For determination of the beltline material chemistry factor, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in the reactor vessel which is being evaluated (i.e., were irradiated at a similar temperature).
(4) For determination of the beltline material chemistry factor, a chemistry correction (i.e., ratio procedure) is not applied to measured values of transition temperature shift if the chemical composition of applicable surveillance data is essentially identical to the best-estimate chemical composition of the beltline material being evaluated.  
(4) For determination of the beltline material chemistry factor, a chemistry correction (i.e., ratio procedure) is not applied to measured values of transition temperature shift if the chemical composition of applicable surveillance data is essentially identical to the best-estimate chemical composition of the beltline material being evaluated.
------------Page 18 of 18 Summary (R3008)}}
Page 18 of 18 Summary (R3008)}}

Latest revision as of 20:06, 5 January 2025

Forwards Supplement to Response to NRC RAI Re GL 92-01,rev 1,suppl 1.Response Incorporates Framatome Corrected Transition Temp Shift Values Into Calculations That Confirm Conservatism of Listed Items
ML18151A211
Person / Time
Site: Surry  Dominion icon.png
Issue date: 02/24/1999
From: Hartz L
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RTR-REGGD-01.099, RTR-REGGD-1.099 99-034, 99-34, GL-92-01, GL-92-1, NUDOCS 9903030285
Download: ML18151A211 (29)
v • d • e


Text

e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 Februarf 24, 1999 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555-0001 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 Serial No.

NAF/JRH Docket Nos.

License Nos.99-034 RO 50-280, 281 DPR-32, 37 SUPPLEMENT TO RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION (RAI) ON GENERIC LETTER 92-01, REVISION 1, SUPPLEMENT 1 By letter dated June 18, 1998, Virginia Electric and Power Company (Virginia Power) provided a response to an NRC Request for Additional Information (RAI) on Generic Letter 92-01, Revision 1, Supplement 1. The information provided was organized in a manner consistent with the NRC's draft RAI on Generic Letter 92-01, Revision 1, Supplement 1, and the B&W Owners Group (BWOG) Reactor Vessel Working Group (RVWG) generic response to the NRC RAI. The calculations which supported the information presented in these tables were performed in accordance with Regulatory Guide 1.99, Revision 2, the Pressurized Thermal Shock Rule in 10 CFR 50.61, and the regulatory guidance provided in the meeting minutes from the November 12, 1997 NRG/Industry meeting on reactor vessel integrity.

During the preparation of a coordinated BWOG response to an NRC RAI regarding changes in reported transition temperature shift values, Framatome Technologies, Inc.

(FTI) discovered errors in previously reported data.

The errors occurred during the performance of hyperbolic tangent curve-fitting of Charpy test data from several analyzed surveillance capsules. Framatome has since corrected the data errors and Virginia Power has incorporated the corrected transition temperature shift values (determined by hyperbolic tangent curve-fit) into calculations that confirm the conservatism of 1) the licensing basis heatup and cooldown limit curves, 2) the associated Low Temperature Overpressure Protection System (L TOPS) setpoint and enabling temperature, and 3) the 10 CFR 50.61 Pressurized Thermal Shock (PTS} screening calculations. A discussion of the changes to the previously reported surveillance results is provided in the attachment, and the resu~s-~ the-~vi:; :':~l~t: are reported in Appendix A to fue atta;m;~ 2, t I 1

(

~ia30~Ba~~ ii&aa~ao\\ '

p PDR -*

This information supplements the information previously reported in the June 18, 1998 letter. noted above.

Please contact us if you have any questions or require additional information.

Very truly yours,

~rf L. N. Hartz Vice President - Nuclear Engineering and Services Attachment Commitments made in this letter: None.

cc:

US Nuclear Regulatory Commission Region II Atlanta Federal Center 61 Forsyth Street, S.W., Suite 23T85 Atlanta, Georgia 30303 Mr. R. A. Musser NRC Senior Resident Inspector Surry Power Station

COMMONWEAL TH OF VIRGINIA COUNTY OF HENRICO

)

)

)

e The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by L. N. Hartz, who is Vice President -

Nuclear Engineering & Services, for J.P. O'Hanlon, who is Senior Vice President

- Nuclear, of Virginia Electric and Power Company. She has affirmed before me that she is duly authorized to execute and file the foregoing document in behalf of that Company, and that the statements in the document are true to the best of her knowledge and belief.

Acknowledged before me this d 4 T.bday of jJ.nuoNJc, 19 qq.

0 My Commission Expires: March 31, 2000.

~Tu~

Notary Public (SEAL)

~.

Attachment Supplement To Response To NRC Request For Additional Information (RAI) On Generic Letter 92-01 Revision 1 Supplement 1 Surry Power Station Units 1 and 2 Discussion of Changes to Previously Reported Surveillance Results Surveillance data was considered in Reference (1) for evaluation of reactor vessel beltline welds fabricated with the following weld wires:

72445 (Surry Unit 1 weld materials SA-1.585 and SA-1650, and Surry Unit 2 weld material SA-1585),

299L44 (Surry Unit 1 weld material SA-1526), and 0227 (Rotterdam-fabricated Surry Unit 2 weld material R3008).

Surveillance data for weld wire 72445 was available from both Westinghouse and B&W irradiations. In the case of weld wire 72445, the Westinghouse data was considered more applicable to the plant, since it required fewer corrections for irradiation temperature and chemical composition differences. The Westinghouse data was determined to be credible in accordance with RG 1.99, Revision 2 (5), as supplemented by Reference (7). After appropriate corrections for irradiation temperature and chemical composition differences, the Westinghouse data was used to evaluate the Surry Units 1 and 2 beltline materials fabricated with weld wire 72445 (i.e., SA-1585 and SA-1650).

Surveillance data for weld wire 299L44 was also available from both Westinghouse and B&W irradiations. In the case of weld wire 299L44, the Westinghouse data (which was Surry Unit 1 plant-specific surveillance data) was again considered more applicable to the plant, since it required fewer corrections for irradiation temperature and chemical composition differences. However, the Westinghouse data was determined to be non-credible in accordance with RG 1.99, Revision 2 (5), as supplemented by Reference (7).

Other possible combinations of Westinghouse and: B&W surveillance data were evaluated for credibility, but each combination was determined to be non-credible.

Since no credible data was identified, the Regulatory Guide 1.99, Revision 2, Position 1.1 chemistry factor was evaluated, and was determined to be conservative in accordance with guidance provided in Reference (7).

Therefore, the Position 1.1 chemistry factor was used in the evaluation of the Surry Unit 1 beltline material fabricated from weld wire 299L44 (i.e., SA-1526).

Surveillance data for weld wire 0227 was available only from the Surry Unit 2 plant-specific surveillance program. The surveillance data was determined to be credible in accordance with RG 1.99, Revision 2 (5), as supplemented by Reference (7).

For application of the surveillance data to the beltline weld material, no corrections for irradiation temperature or chemical composition differences were applied, since (a) the surveillance data were irradiated in the reactor vessel which was being evaluated (i.e.,

Surry Unit 2) and (b) the chemical composition of the surveillance specimens was Page 1 of 7

e e

essentially the same as the best-estimate chemical composition of the beltline material being evaluated (i.e., weld R3008).

_ Based on a review of Reference (8), the following changes were incorporated into the data previously reported in Reference (1). For weld wire 72445 (weld materials SA-1585 and SA-1650):

The fluence values for Westinghouse (i.e., Point Beach Unit 1) irradiations have been changed to those reported in Reference (8)

(The fluence values presented in Reference (8) were obtained from Reference (11 ).)

The 30 ft-lb transition temperature shift value for Point Beach Unit 1 Capsule R (PB1-R) has been changed from 181°Fto 155°F.

The 30 ft-lb transition temperature shift value for Capsule CR3-LG1 has been changed from 141 °F to 139 °F.

The 30 ft-lb transition temperature shift value for Capsule CR3-LG2 has been changed from 156°F to 164°F.

For weld wire 299L44 (weld material SA-1526):

The 30 ft-lb transition temperature shift value for Capsule CR3-LG1 (BWOG CR-3 irradiation) has been changed from 205°F to 202°F.

For weld wire 0227 (Rotterdam weld material R3008):

The 30 ft-lb transition temperature shift value for Capsule X (Surry Unit 2 irradiation) has been changed from 95°F to 96°F.

The 30 ft-lb transition temperature shift value for Capsule V (Surry Unit 2 irradiation) has been changed from 145°F to 140°F.

Impact of Surveillance Data Changes on Calculated Chemistry Factor The aforementioned changes to surveillance data for weld wire 72445 (weld materials SA-1585 and SA-1650) caused the Westinghouse surveillance data set, previously

  • determined to be credible, to become non-credible. (One of the four data points exceeded the 1cr (28°F) credibility criterion by 2°F.) When the combined Westinghouse and B&W data were evaluated for credibility, five of the six data points were within the 1 cr (28°F) credibility criterion. This data set is considered credible in accordance with NRC guidance provided in Case 5 of Reference (7). Therefore, this data was used to evaluate the Surry Units 1 and 2 SA-1585 and SA-1650 beltline weld materials. Corrections for chemical composition and irradiation temperature differences between the surveillance and beltline materials were applied in accordance with guidance provided in Reference (7).

A

. correction for irradiation temperature difference was applied to a measured value of transition temperature shift only if application of the correction increased the transition temperature shift value.

Page 2 of 7

e The aforementioned change to surveillance data for weld wire 299L44 (weld material SA-1526) had virtually no impact on the RG 1.99, Revision 2, Position 2.1, chemistry fact~r calculations. The possible combinations of Westinghouse and B&W surveillance

  • . data -were evaluated for credibility, but each combination was determined to be non-credible. Since no credible data was identified, the Regulatory Guide 1.99., Revision 2, Position 1.1, chemistry factor was evaluated, and was determined to be conservative in accordance with guidance provided in Reference (7).

Therefore, the Position 1.1 chemistry factor was used in the evaluation of the Surry Unit 1 beltline material fabricated from weld wire 299L44 (i.e., SA-1526).

The aforementioned changes to surveillance data for weld wire 0227 (Rotterdam weld material R3008) caused the RG 1.99, Revision 2, Position 2.1, chemistry factor to change from 128.0°F to 125.2°F.

Evaluation of Existing Prr Limits and L TOPS Setpoints Appendix A presents Reactor Vessel Material Data Tables for Surry Units 1 and 2 which include consideration of the corrected transition temperature shift values and neutron fluences presented in BAW-2325, Supplement 1 (8). The information in the Appendix A data tables is organized in a manner consistent with the NRC's draft RAI on Generic Letter 92-01, Revision 1, Supplement 1 (3), and the B&W Owners Group (BWOG) Reactor Vessel Working Group (RVWG) generic response to the NRC RAI on Generic Letter 92-01, Revision 1, Supplement 1 (4).

The calculations which support the information presented in these tables were performed in accordance with Regulatory Guide 1.99, Revision 2 (5), the Pressurized Thermal Shock Rule in 10 CFR 50.61 (6), and the regulatory guidance provided in the meeting minutes from the November 12, 1997 NRG/Industry meeting on reactor vessel integrity (7).

The existing Surry Units 1 and 2 Prr limits and L TOPS setpoints (9)(10) are based on a limiting %-thickness (%-T) RT NDT of 228.4°F. This value of RT NDT was determined to bound all Surry Units 1 and 2 reactor vessel beltline materials at end-of-license (EOL) fluences corresponding to 28.8 EFPY and 29.4 EFPY for Surry Units 1 and 2, respectively (9)(10). After consideration of the aforementioned changes to previously reported surveillance data, the most limiting %-T RTNoT vaiue for Surry Units 1 and 2 is 215.7°F.

This value of RT NDT was determined on the basis of fluence values corresponding to 29.6 EFPY and 30.1 EFPY for Surry Units 1 and 2, respectively (12). On the basis of the results presented in Appendix A, it is concluded that the existing RCS Prr limits and L TOPS setpoints (2)(3) remain valid and conservative.

Evaluation of PTS Screening Calculations PTS screening calculations were previously transmitted to the NRC by letter dated April 1, 1996 (13). All Surry Units 1 and 2 reactor vessel beltline materials demonstrated margin to the 10 CFR 50.61 screening criteria at end-of-license (EOL) fluences corresponding to 28.8 EFPY and 29.4 EFPY for Surry Units 1 and 2, respectively (13). On the basis of the results presented in Appendix A, it is concluded that all Surry Units 1 and 2 beltline Page 3 of 7

materials continue to meet the 10 CFR 50.61 screening criteria at end-of-license fluence values corresponding to 29.6 EFPY and 30.1 EFPY for Surry Units 1 and 2, respectively (12),,

Revised Reactor Vessel Beltline Neutron Fluence Values The revised reactor* vessel beltline neutron fluence values were calculated using the Virginia Power Reactor Vessel Fluence Methodology Topical Report (12).

The methodology described in that report was developed in accordance with Draft Regulatory Guide DG 1053 (14). The vessel fluence calculational methodology was benchmarked using a combination of Virginia Power surveillance capsules, pressure vessel simulator measurements, and Surry Unit 1 ex-vessel cavity dosimetry measurements. Surry Unit 1 Capsule X (15) was not used to validate the calculational methodology because the capsule data were not available during the methodology development. The table below presents the calculated neutron fluences.

Location Fluence (n/cm~)

Surry 1 Surry 2 Peak Vessel Fluence, End of License 3.53E19 3.52E19 Peak Vessel Fluence, End of Life Extension 5.40E19 5.34E19 Peak Beltline Weld Fluence, End of License 3.20E19 3.52E19 Peak Beltline Weld Fluence, End of Life 4.70E19 5.34E19 Extension Peak Upper Longitudinal Weld Fluence, End 6.00E18 6.97E18 of License Peak Upper Longitudinal Weld Fluence, End 9.14E18 1.08E19 of Life Extension Peak Lower Longitudinal Weld Fluence, End 5.40E18 6.97E18 of License Peak Lower Longitudinal Weld Fluence, End 7.90E18 1.08E19 of Life Extension Peak Nozzle to Intermediate Shell Circ. Weld 3.07E18 2.98E18 Fluence, End of License Peak Nozzle to Intermediate Shell Circ. Weld 4.96E18 4.71E18 Fluence, End of Life Extension Revised Reactor Vessel Beltline Neutron Fluence Values Surry Units 1 and 2 Page 4 of 7

e Conclusions After consideration of the aforementioned changes to previously reported surveillance data,*. it is concluded that the existing Surry Units 1 and 2 Prr limits and L TOPS setpoints remain valid for cumulative core burnups up to 29.6 EFPY and 30.1 EFPY for Surry Units 1 and 2, respectively. It is further concluded that all Surry Units 1 and 2 beltline materials continue to meet the 10 CFR 50.61 screening criteria for cumulative core burnups up to 29.6 EFPY and 30.1 EFPY for Surry Units 1 and 2, respectively. The evaluations that support these conclusions utilize fluence values determined in accordance with the Reference (12) topical report, which was transmitted to the NRC under separate cover. In addition, the evaluations which support these conclusions were performed in accordance with Regulatory Guide 1.99, Revision 2 (5), 10 CFR 50.61 (6), and the November 12, 1997 NRG/Industry meeting notes (7). The tables presented in Appendix A supplement the previous Virginia Power response (1) to the NRC RAI documented in Reference (2).

Page 5 of 7

e References (1)

Letter from J. P. O'Hanlon to USNRC, "Virginia Electric and Power Company, Surry and North Anna Power Stations Units 1 and 2, Surry 1 Reactor Vessel Surveillance Capsule X Analysis Report, GL 92-01, Rev. 1, Supplement 1, Response to Request for Additional Information, and Topical Report on Reactor Vessel Fluence Analysis Methodology," Serial No.98-252, dated June 18, 1998.

(2)

Letter from G. E. Edison to J. P. O'Hanlon, "Surry Nuclear Power Station Units 1 and 2, Request for Additional Information Related to Reactor Vessel Structural Integrity (Generic Letter 92-01, Revision 1, Supplement 1)'(TAC Nos. MA0576 and MA0577)," dated April 20, 1998.

(3)

Letter from G. C. Lainas (USNRC) to D. J. Modeen (NEI), "Request for Additional Information Regarding Reactor Pressure Vessel Integrity," dated February 5, 1998.

(4)

"Response to Request for Additional Information (RAI) Regarding Reactor Pressure Vessel Integrity," BAW-2325, dated May, 1998.

(5)

Regulatory Guide 1.99 Revision 2, "Radiation Embrittlement of Reactor Vessel Materials," dated May, 1988.

(6)

Title 10, Code of Federal Regulations, Part 50.61, "Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events."

(7)

Memorandum from K. R. Wichman to E. 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.

(8)

BAW-2325, Supplement 1, "Supplement to the Response to Request for Additional Information (RAI) Regarding Reactor Pressure Vessel Integrity, B&W Owners Group - Reactor Vessel Working Group," dated December 1998.

(9)

Letter from R. F. Saunders to USNRC, "Virginia Electric and Power Company, Surry Power Station Units 1 and 2, Request for Exemption - ASME Code Case N-514, Proposed Technical Specifications

Change, Revised Pressure/Temperature Limits and L TOPS Setpoint," Serial No.95-197, June 8, 1995.

Page 6 of 7

(10)

Letter from B. C. Buckley to J. P. O'Hanlon, "Surry Units 1 and 2 - Issuance of Amendments Re: Surry Units 1 and 2 Reactor Vessel Heatup and Cooldown Curves (TAC Nos. M92537 and M92538)," Serial No.96-020, dated December

  • 28, 1995.

(11)

WCAP-12794 Revision 3, "Reactor Cavity Neutron Measurement Program for Wisconsin Electric Power Company Point Beach Unit 1," dated December 1995.

(12)

Virginia Power Topical Report VEP-NAF-3, "Reactor Vessel Fluence Analysis Methodology," dated November, 1997.

(13)

Letter from J. P. O'Hanlon to USNRC, "Virginia Electric and Power Company, Surry and North Anna Power Stations Units 1 and 2, Pressurized Thermal Shock (PTS) Screening Calculations," Serial No.96-084, dated April 1, 1996.

(14)

Draft Regulatory Guide DG-1053, "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence," dated June 1996.

(15)

BAW-2324, "Analysis of Capsule X, Virginia Power Surry Unit No. 1, Reactor Vessel Material Surveillance Program," dated April, 1998.

Page 7 of 7

e Appendix A Supplemental Reactor Vessel Material Data Tables

Calc98d (SM-1008 Rev. 0 Addendum C).xls Facility: Surry Unit 1 Vessel Manufacturer: B& W and Rotterdam Dockyard Best-Best-Assigned Estimate Estimate EOLID Material RPV Weld Wire Heat Copper Nickel Fluence Chemistry or Material ID (1)

Location (wt%)

(wt%)

(x1E19)

Factor 122V109VA1 Nozzle Shell Forging 0.11 0.74 0.307 76.1 C4326-1 Intermediate Shell 0.11 0.55 3.53 73.5 C4326-2 Intermediate Shell 0.11 0.55 3.53 73.5 4415-1 Lower Shell 0.11 0.50 3.53 85.0 4415-2 Lower Shell 0.11 0.50 3.53 73.0 J726/25017 Nozzle to Int Shell Gire Weld 0.33 0.10 0.307 152.0 SA-1585/72445 Int. to Low Sh. Gire (ID 40%)

0.22 0.54 3.2 139.8 SA-1650/72445 Int. to Low Sh. Circ (OD 60%)

0.22 0.54 3.2 139.8 SA-1494/8T1554 Int Shell Long. Welds L3 & L4 0.16 0.57 0.6 143.9 SA-1494/8T1554 Lower Shell Long. Weld L 1 0.16 0.57 0.54 143.9 SA-1526/299L44 Lower Shell Long. Weld L2 0.34 0.68 0.54 220.6 (1) or the material identification number of the limiting material as requested in Section 1.0 (1.)

(2) determined from tables or from surveillance data Method of Determining CF (2)

Tables Tables Tables Surv. Data Tables Tables Surv. Data Surv. Data Tables Tables Tables Summary (Surry)

Inner Surf.

Current ART or Licensing Initial RT(PTS) at 1/4-T Basis 1/4-RT(NDT)

Sigma(!)

Sigma(delta)

Margin EOL ART TART

  • 40 0.0 17.0 34.0 125.5 116.1 112.5 10 0.0 17.0 34.0 141.6 132.8 135.2 0

0.0 17.0 34.0 131.6 122.8 125.2 20 0.0 8.5 17.0 149.9 139.7 147.6 0

0.0 17.0 34.0 131.0 122.2 124.6 0

20.0 28.0 68.8 171.6 153.0 169.8

-5 19.7 14.0 48.3 225.8 208.6 228.4 *

-5 19.7 14.0 48.3 225.8 208.6 228.4 *

-5 19.7 28.0 68.5 186.8 167.4 181.4

-5 19.7 28.0 68.5 182.6 163.4 181.4

-7 20.6 28.0 69.5 245.1 215.7 207.0

  • 1/4-T ART value of 228.4 F was used in the determination of PIT limits Page 1 of 18 e

Calc98d (SM-1008 Rev. 0 Addendum C).xls Facility: Surry Unit 2 Vessel Manufacturer: B&W and Rotterdam Dockyard Best-Best-Assigned Estimate Estimate EOLID Material RPV Weld Wire Heat Copper Nickel Fluence Chemistry or Material ID (1)

Location (wt%)

(wt%)

(x1E19)

Factor 123V303VA1 Nozzle Shell Forging 0.11 0.72 0.298 75.8 C4331-2 Intermediate Shell 0.12 0.60 3.520 83.0 C4339-2 Intermediate Shell 0.11 0.54 3.520 73.4 C4208-2 Lower Shell 0.15 0.55 3.520 107.3 C4339-1 Lower Shell 0.11 0.54 3.520 68.4 L737/4275 Nozzle to Int Shell Gire Weld 0.35 0.10 0.298 160.5 A3008/0227 Int. to Lower Shell Gire Weld 0.19 0.55 3.520 125.2 WF-4/8T1762 Int. Shell Long. L4 (ID 50%)

0.19 0.57 0.697 152.4 SA-1585/72445 Int. Sh. L3 (100%), L4 (OD 50) 0.22 0.54 0.697 139.8 WF-4/8T1762 LS L2 (ID 63%), L1 (100) 0.19 0.57 0.697 152.4 WF-8/8T1762 LS Long. Weld L2 (OD 37%)

0.19 0.57 0.697 152.4 (1) or the material identification number of the limiting material as requested in Section 1.0 (1.)

(2) determined from tables or from surveillance data Method of Determining CF(2)

Tables Tables Tables Tables Surv. Data Tables Surv. Data Tables Surv. Data Tables Tables Summary (Surry)

Initial RT(NDT) 30

-10

-20

-30

-1 0 0

0

-5

-5

-5

-5 Inner Surf.

Current ART or Licensing RT(PTS) at 1/4-T Basis 1/4-Sigma(I)

Sigma(delta)

Margin EOL ART TART*

0.0 17.0 34.0 114.7 105.5 100.4 e 0.0 17.0 34.0 134.2 124.2 123.9 0.0 17.0 34.0 111.5 102.6 102.4 0.0 17.0 34.0 146.4 133.5 133.1 0.0 8.5 17.0 97.8 89.6 89.3 20.0 28.0 68.8 176.1 156.6 169.6 20.0 14.0 48.8 215.0 200.0 202.9 19.7 28.0 68.5 200.4 179.6 181.0 19.7 14.0 48.3 168.9 149.9 158.5 19.7 28.0 68.5 200.4 179.6 181.0 19.7 28.0 68.5 200.4 179.6 181.0

  • 1/4-T ART value of 228.4 F was used in the determination of Prr limits Page 2 of 18

ET-NAF-990006 Tables.xis Table 2:

Surry Unit 1 and 2 Weld Material SA-1585 (Point Beach 1 Data Only)

Data Used In Irradiation Assessing Temperature Measured Delta-Vessel? (Yes or Capsule ID (Including Source)

Copper (wt%) Nickel (wt%)

(F)

Fluence (x1E19)

RT(NDT) (F)

No)

Point Beach Unit 1 Capsule T 0.230 0.615 533.4 2.230 181 Yes Point Beach Unit 1 Capsule R 0.230 0.615 541.6 2.190 155 Yes Point Beach Unit 1 Capsule S 0.230 0.615 542.0 0.829 165 Yes Point Beach Unit 1 Capsule V 0.230 0.61 5 542.0 0.634 107 Yes Capsule CR3-LG2 (BWOG CR-3 lrrad.)

0.220 0.590 556.0 1.670 164 No Capsule CR3-LG1 (BWOG CR-3 lrrad.)

0.220 0.590 556.0 0.510 139 No e

Table 3:

Surry Unit 1 and 2 Weld Material SA-1585 (Point Beach 1 Data Only)

Irradiation Temperature Measured Delta-Adjusted Delta-Adjusted - Predicted Capsule ID (Including Source)

Copper (wt%) Nickel (wt%)

(F)

Fluence Factor RT(NDT) (F)

RT(NDT) (F)

  • Delta-RT(NDT) (F)
  • Point Beach Unit 1 Capsule T 0.230 0.615 533.4 1.2173 181 181 7

Point Beach Unit 1 Capsule R 0.230 0.615 541.6 1.2126 155 155

-18 Point Beach Unit 1 Capsule S 0.230 0.615 542.0 0.9474 165 165 30 Point Beach Unit 1 Capsule V 0.230 0.615 542.0 0.8723 107 107

-17 e

  • For credibility check, measured shift values are adjusted to average surveillance material chemistry and irradiation temperature as required. See Table 4.

Page 3 of 18 Summary (SA-1585) - Corrected L

Table 4:

Beltline Material ID SA-1585/72445 ET-NAF-990006 Tables.xis Surry Unit 1 and 2 Weld Material SA-1585 (Point Beach 1 Data Only)

CF Determination Chemistry Beltline Beltline Irradiation Surveillance Data Factor Applied Material Material Temperature Position 1.1 Chemistry Credible or Non-to Beltline Copper (wt%) Nickel (wt%)

(F)

Factor Credible?

Material*

0.220 0.540 542.0 158.0 Non-Credible 158.0

  • If surveillance data are determined to be non-credible, the Position 1. 1 chemistry factor is applied to the beltline material.

If Surv. Data Non-Credible, Verify Conservatism of Applied Position 1.1 CF **

Conservative

    • Measured shift values are adjusted to the average surveillance material chemistry and irradiation temperature, and are verified to be within 2 sigma of the trend curve based on Position 1. 1.

Credibility Assessment e

Conservatism Check for Pos. 1.1 CF when Surv. Data Non-Credible (3)

(1)

(2)

Temperature Correction (4)

Temperature Chemistry Surveillance Applied to Credible Chemistry Correction Correction Correction Data Credible Surv. Data for Applied to Credible Surv.

Are adjusted surveillance Applied for Applied for or Non-Application to Beltline Data for Application to Adjusted Delta-Adjusted - Predicted data within 2 sigma of the Capsule ID (Including Source)

Credibility?

Credibility?

Credible?

Material?

Beltline Material?

RT(NDT) (F) **

Delta-RT(NDT) (F) **

applied CF trend curve? **

Point Beach Unit 1 Capsule T No No Credible 181

-28 Point Beach Unit 1 Capsule R No No Credible 155

-53 Point Beach Unit 1 Capsule S No No Non-Credible 165 2

Point Beach Unit 1 Capsule V No No Credible 107

-43 Capsule CR3-LG2 (BWOG CR-3 lrrad.)

Capsule CR3-LG1 (BWOG CR-3 lrrad.)

(1) For the credibility determination, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in a single reactor (i.e., were irradiated at a similar temperature).

(2) For the credibility determination, a chemistry correction is not applied to measured values of transition temperature shift if applicable surveillance data were obtained from a single source (i.e., were machined from the same block of material).

(3) For determination of the beltline material chemistry factor, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in the reactor vessel which is being evaluated (i.e., were irradiated at a similar temperature).

(4) For determination of the beltline material chemistry factor, a chemistry correction (i.e., ratio procedure) is not applied to measured values of transition temperature shift if the chemical composition of applicable surveillance data is essentially identical to the best-estimate chemical composition of the beltline material being evaluated.

Credible Credible Credible Credible Page 4 of 18 Summary (SA-1585) - Corrected

ET-NAF-990006 Tables.xis Table 2:

Surry Unit 1 and 2 Weld Material SA-1585 (All Available Data)

Data Used In Irradiation Assessing Temperature Measured Delta-Vessel? (Yes or Capsule ID (Including Source)

Copper (wt%) Nickel (wt%)

(F)

Fluence (x1E19)

RT(NDT) (F)

No)

Point Beach Unit 1 Capsule T 0.230 0.615 533.4 2.230 181 Yes Point Beach Unit 1 Capsule R 0.230 0.615 541.6 S\\ c, 2.190 c:

it 155 "'

Yes Point Beach Unit 1 Capsule S 0.230 0.615 542.0 0.829 165 Yes Point Beach Unit 1 Capsule V 0.230 0.615 542.. 0 0.634 107 Yes Capsule CR3-LG2 (BWOG CR-3 lrrad.)

0.220 0.590 556.0 1.670 164 Yes Capsule CR3-LG1 (BWOG CR-3 lrrad.)

0.220 0.590 556.0 0.510 139 Yes Table 3:

Surry Unit 1 and 2 Weld Material SA-1585 (All Available Data)

Irradiation Temperature Measured Delta-Adjusted Delta-Adjusted - Predicted Capsule ID (Including Source)

Copper (wt%) Nickel (wt%)

(F)

Fluence Factor RT(NDT) (F)

RT(NDT) (F)

  • Delta-RT(NDT) (F)
  • Point Beach Unit 1 Capsule T 0.230 0.615 533.4 1.2173 181 167

-10 Point Beach Unit 1 Capsule R 0.230 0.615 541.6 1.2126 155 150

-27 Point Beach Unit 1 Capsule S 0.230 0.615 542.0 0.9474 165 160 22 Point Beach Unit 1 Capsule V 0.230 0.615 542.0 0.8723 107 103

-24 Capsule CR3-LG2 (BWOG CR-3 lrrad.)

0.220 0.590 556.0 1.1413 164 179 13 Capsule CR3-LG1 (BWOG CR-3 lrrad.)

0.220 0.590 556.0 0.8120 139 153 35

  • For credibility check, measured shift values are adjusted to average surveillance material chemistry and irradiation temperature as required. See Table 4.

Page 5 of 18 Summary (SA-1585, Alt. 1)

L

Table 4:

Beltline Material ID SA-1585n2445 ET-NAF-990006 Tables.xis Surry Unit 1 and 2 Weld Material SA-1585 (All Available Data)

CF Determination Beltline Beltline Irradiation Surveillance Data Material Material Temperature Position 1.1 Chemistry Credible or Non-Copper (wt%) Nickel (w1%)

(F)

Factor Credible?

0.220 0.540 542.0 158.0 Credible

  • If suNei/lance data are determined to be non-credible, the Position 1. 1 chemistry factor is applied to the beltline material.

If Surv. Data Non-Chemistry Credible, Verify Factor Applied Conservatism of to Beltline Applied Position 1.1 Material*

CF**

139.8

    • Measured shift values are adjusted to the average suNeillance material chemistry and irradiation temperature, and are verified to be within 2 sigma of the trend cuNe based on Position 1. 1.

Credibility Assessment e

Conservatism Check for Pos. 1.1 CF when Surv. Data Non-Credible (3)

(1)

(2)

Temperature Correction (4)

Temperature Chemistry Surveillance Applied to Credible Chemistry Correction Correction Correction Data Credible Surv. Data for Applied to Credible Surv.

Are adjusted surveillance Applied for Applied for or Non-Application to Beltline Data for Application to Adjusted Delta-Adjusted - Predicted data within 2 sigma of the Capsule ID (Including Source)

Credibility?

Credibility?

Credible?

Material?

Beltline Material?

RT(NDT) (F) **

Delta-RT(NDT) (F) **

applied CF trend curve? **

Point Beach Unit 1 Capsule T Yes Yes Credible Yes Yes Point Beach Unit 1 Capsule R Yes Yes Credible Yes Yes Point Beach Unit 1 Capsule S Yes Yes Credible Yes Yes Point Beach Unit 1 Capsule V Yes Yes Credible Yes Yes Capsule CR3-LG2 (BWOG CR-3 lrrad.)

Yes Yes Credible Yes Yes Capsule CR3-LG1 (BWOG CR-3 lrrad.)

Yes Yes Non-Credible Yes Yes (1) For the credibility determination, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in a single reactor (i.e., were irradiated at a similar temperature).

(2) For the credibility determination, a chemistry correction is not applied to measured values of transition temperature shift if applicable surveillance data were obtained from a single source (i.e., were machined from the same block of material).

(3) For determination of the beltline material chemistry factor, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in the reactor vessel which is being evaluated (i.e., were irradiated at a similar temperature).

(4) For determination of the beltline material chemistry factor, a chemistry correction (i.e., ratio procedure) is not applied to measured values of transition temperature shift if the chemical composition of applicable surveillance data is essentially identical to the best-estimate chemical composition of the beltline material being evaluated.

Page 6 of 18 Summary (SA-1585, Alt. 1)

ET -NAF-990006 Tables.xis Table 2:

Surry Unit 1 Weld Material SA-1526 (Surry Unit 1 Data Only)

Data Used In Irradiation Assessing Temperature Measured Delta-Vessel? (Yes or Capsule ID (Including Source)

Copper (wt%) Nickel (wt%)

(F)

Fluence (x1E19)

RT(NDT) (F)

No)

Capsule TMl2-LG1 (BWOG CR-3 lrrad.)

0.370 0.700 556.0 0.830 216 No Capsule CR3-LG1 (BWOG CR-3 lrrad.)

0.360 0.700 556.0 0.779 202 No Capsule TMl2-LG1 (BWOG CR-3 lrrad.)

0.330 0.670 556.0 0.968 226 No Three Mile Island Unit 1 Capsule C 0.330 0.670 556.0 0.866 166 No Three Mile Island Unit 1 Capsule E 0.330 0.670 556.0 0.107 74 No Surry Unit 1 Capsule T 0.230 0.640 533.9 0.281 171 Yes Surry Unit 1 Capsule V 0.230 0.640 538.8 1.940 250 Yes Surry Unit 1 Capsule X 0.230 0.640 542.0 1.599 234 Yes Table 3:

Surry Unit 1 Weld Material SA-1526 (Surry Unit 1 Data Only)

Irradiation Temperature Measured Delta-Adjusted Delta-Adjusted - Predicted Capsule ID (Including Source)

Copper (wt%) Nickel (wt%)

(F)

Fluence Factor RT(NDT) (F)

RT(NDT) (F)

  • Delta-RT(NDT) (F)
  • e Surry Unit 1 Capsule T 0.230 0.640 533.9 0.6535 171 171 29 Surry Unit 1 Capsule V 0.230 0.640 538.8 1.1811 250 250

-6 Surry Unit 1 Capsule X 0.230 0.640 542.0 1.1296 234 234

-11

  • For credibility check, measured shift values are adjusted to average surveillance material chemistry and irradiation temperature as required. See Table 4.

Page 7 of 18 Summary (SA-1526)

Table 4:

Beltline Material ID SA-1526/299L44 ET-NAF-990006 Tables.xis Surry Unit 1 Weld Material SA-1526 (Surry Unit 1 Data Only)

CF Determination Beltline Beltline Irradiation Surveillance Data Material Material Temperature Position 1.1 Chemistry Credible or Non-Copper (wt%) Nickel (wt%)

(F)

Factor Credible?

0.340 0.680 542.0 220.6 Non-Credible

  • If surveillance data are determined to be non-credible, the Position 1. 1 chemistry factor is applied to the belt/ine material.

If Surv. Data Non-Chemistry Credible, Verify Factor Applied Conservatism of to Beltline Applied Position 1.1 Material

  • CF**

220.6 Conservative

    • Measured shift values are adjusted to the average surveillance material chemistry and irradiation temperature, and are verified to be within 2 sigma of the trend curve based on Position 1. 1.

Credibility Assessment e

Conservatism Check for Pos. 1.1 CF when Surv. Data Non-Credible (3)

(1)

(2)

Temperature Correction (4)

Temperature Chemistry Surveillance Applied to Credible Chemistry Correction Correction Correction Data Credible Surv. Data for Applied to Credible Surv.

Are adjusted surveillance Applied for Applied for or Non-Application to Beltline Data for Application to Adjusted Delta-Adjusted - Predicted data within 2 sigma of the Capsule ID (Including Source)

Credibility?

Credibility?

Credible?

Material?

Beltline Material?

RT(NDT) (F) **

Delta-RT(NDT) (F) **

applied CF trend curve? **

Capsule TMl2-LG1 (BWOG CR-3 lrrad.)

Capsule CR3-LG1 (BWOG CR-3 lrrad.)

Capsule TMl2-LG1 (BWOG CR-3 lrrad.)

Three Mile Island Unit 1 Capsule C Three Mile Island Unit 1 Capsule E Surry Unit 1 Capsule T No No Non-Credible 171 56 Surry Unit 1 Capsule V No No Credible 250 42 Surry Unit 1 Capsule X No No Credible 234 35 (1) For the credibility determination, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in a single reactor (i.e., were irradiated at a similar temperature).

(2) For the credibility determination, a chemistry correction is not applied to measured values of transition temperature shift if applicable surveillance data were obtained from a single source (i.e., were machined from the same block of material).

(3) For determination of the beltline material chemistry factor, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in the reactor vessel which is being evaluated (i.e., were irradiated at a similar temperature).

(4) For determination of the beltline material chemistry factor, a chemistry correction (i.e., ratio procedure) is not applied to measured values of transition temperature shift if the chemical composition of applicable surveillance data is essentially identical to the best-estimate chemical composition of the beltline material being evaluated.

Credible Credible Credible Page 8 of 18 Summary (SA-1526)

ET-NAF-990006 Tables.xis Table 2:

Surry Unit 1 Weld Material SA-1526 (All Available Data)

Data Used In Irradiation Assessing Temperature Measured Delta-Vessel? (Yes or Capsule ID (Including Source)

Copper (wt%) Nickel (wt%)

(F)

Fluence (x1E19)

RT(NDT) (F)

No)

Capsule TMl2-LG1 (BWOG CR-3 lrrad.)

0.370 0.700 556.0 0.830 216 Yes Capsule CR3-LG1 (BWOG CR-3 lrrad.)

0.360 0.700 556.0 0.779 202 Yes Capsule TM12-LG1 (BWOG CR-3 lrrad.)

0.330 0.670 556.0 0.968 226 Yes Three Mile Island Unit 1 Capsule C 0.330 0.670 556.0 0.866 166 Yes Three Mile Island Unit 1 Capsule E 0.330 0.670 556.0 0.107 74 Yes Surry Unit 1 Capsule T 0.230 0.640 533.9 0.281 171 Yes Surry Unit 1 Capsule V 0.230 0.640 538.8 1.940 250 Yes Surry Unit 1 Capsule X 0.230 0.640 542.0 1.599 234 Yes Table 3:

Surry Unit 1 Weld Material SA-1526 (All Available Data)

Irradiation Temperature Measured Delta-Adjusted Delta-Adjusted

  • Predicted Capsule ID (Including Source)

Copper (wt%) Nickel (wt%)

(F)

Fluence Factor RT(NDT) (F)

RT(NDT) (F)

  • Delta-RT(NDT) (F)
  • Capsule TMl2-LG1 (BWOG CR-3 lrrad.)

0.370 0.700 556.0 0.9477 216 195

  • 12 Capsule CR3-LG1 (BWOG CR-3 lrrad.)

0.360 0.700 556.0 0.9299 202 185

-17 Capsule TMl2-LG1 (BWOG CR-3 lrrad.)

0.330 0.670 556.0 0.9909 226 221 6

Three Mile Island Unit 1 Capsule C 0.330 0.670 556.0 0.9597 166 164

.45 Three Mile Island Unit 1 Capsule E 0.330 0.670 556.0 0.4305 74 77

-17 Surry Unit 1 Capsule T 0.230 0.640 533.9 0.6535 171 181 39 Surry Unit 1 Capsule V 0.230 0.640 538.8 1.1811 250 279 22 Surry Unit 1 Capsule X 0.230 0.640 542.0 1.1296 234 264 18

  • For credibility check, measured shift values are adjusted to average surveillance material chemistry and irradiation temperature as required. See Table 4.

Page 9 of 18 Summary (SA-1526, Alt. 1)

Table 4:

Beltline Material ID SA-1526/299L44 ET-NAF-990006 Tables.xis Surry Unit 1 Weld Material SA-1526 (All Available Data)

CF Determination Beltline Beltline Irradiation Surveillance Data Material Material Temperature Position 1.1 Chemistry Credible or Non-Copper (wt%) Nickel (wt%)

(F)

Factor Credible?

0.340 0.680 542.0 220.6 Non-Credible

  • If surveillance data are determined to be non-credible, the Position 1. 1 chemistry factor is applied to the beltline material.

If Surv. Data Non-Chemistry Credible, Verify Factor Applied Conservatism of to Beltline Applied Position 1.1 Material

  • CF**

220.6 Conservative

    • Measured shift values are adjusted to the average surveillance material chemistry and irradiation temperature, and are verified to be within 2 sigma of the trend curve based on Position 1. 1.

Credibility Assessment Conservatism Check for Pos. 1.1 CF when Surv. Data Non-Credible (3)

(1)

(2)

Temperature Correction (4)

Temperature Chemistry Surveillance Applied to Credible Chemistry Correction Correction Correction Data Credible Surv. Data for Applied to Credible Surv.

Are adjusted surveillance Applied for Applied for or Non-Application to Beltline Data for Application to Adjusted Delta-Adjusted - Predicted data within 2 sigma of the Capsule ID (Including Source)

Credibility?

Credibility?

Credible?

Material?

Beltline Material?

RT(NDT) (F) **

Delta-RT(NDT) (F) **

applied CF trend curve? **

Capsule TMl2-LG1 (BWOG CR-3 lrrad.)

Yes Yes Credible 195 1

Capsule CR3-LG1 (BWOG CR-3 lrrad.)

Yes Yes Credible 185

-5 Capsule TMl2-LG1 (BWOG CR-3 lrrad.)

Yes Yes Credible 221 19 Three Mile Island Unit 1 Capsule C Yes Yes Non-Credible 164

-32 Three Mile Island Unit 1 Capsule E Yes Yes Credible 77

-11 Surry Unit 1 Capsule T Yes Yes Non-Credible 181 47 Surry Unit 1 Capsule V Yes Yes Credible 279 37 Surry Unit 1 Capsule X Yes Yes Credible 264 33 (1) For the credibility determination, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in a single reactor (i.e., were irradiated at a similar temperature).

(2) For the credibility determination, a chemistry correction is not applied to measured values of transition temperature shift if applicable surveillance data were obtained from a single source (i.e., were machined from the same block of material).

(3) For determination of the beltline material chemistry factor, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in the reactor vessel which is being evaluated (i.e., were irradiated at a similar temperature).

(4) For determination of the beltline material chemistry factor, a chemistry correction (i.e., ratio procedure) is not applied to measured values of transition temperature shift if the chemical composition of applicable surveillance data is essentially identical to the best-estimate chemical composition of the beltline material being evaluated.

Credible Credible Credible Credible Credible Credible Credible Credible Page 10 of 18 Summary (SA-1526, Alt. 1)

ET-NAF-990006 Tables.xis Table 2:

Surry Unit 1 Weld Material SA-1526 (All Data Except TMl-2)

Data Used In Irradiation Assessing Temperature Measured Delta-Vessel? (Yes or Capsule ID (Including Source)

Copper (wt%) Nickel (wt%)

(F)

Fluence (x1E19)

RT(NDT) (F)

No)

Capsule TMl2-LG1 (BWOG CR-3 lrrad.)

0.370 0.700 556.0 0.830 216 No Capsule CR3-LG1 (BWOG CR-3 lrrad.)

0.360 0.700 556.0 0.779 202 Yes Capsule TMl2-LG1 (BWOG CR-3 lrrad.)

0.330 0.670 556.0 0.968 226 No Three Mile Island Unit 1 Capsule C 0.330 0.670 556.0 0.866 166 Yes Three Mile Island Unit 1 Capsule E 0.330 0.670 556.0 0.107 74 Yes Surry Unit 1 Capsule T 0.230 0.640 533.9 0.281 171 Yes Surry Unit 1 Capsule V 0.230 0.640 538.8 1.940 250 Yes Surry Unit 1 Capsule X 0.230 0.640 542.0 1.599 234 Yes Table 3:

Surry Unit 1 Weld Material SA-1526 (All Data Except TMl-2)

Irradiation Temperature Measured Delta-Adjusted Delta-Adjusted - Predicted Capsule ID (Including Source)

Copper (wt%) Nickel (wt%)

(F)

Fluence Factor RT(NDT) (F)

RT(NDT) (F)

  • Delta-RT(NDT) (F)
  • Capsule CR3-LG1 (BWOG CR-3 lrrad.)

0.360 0.700 556.0 0.9299 202 181

-18 Three Mile Island Unit 1 Capsule C 0.330 0.670 556.0 0.9597 166 161

-44 Three Mile Island Unit 1 Capsule E 0.330 0.670 556.0 0.4305 74 76

-16 Surry Unit 1 Capsule T 0.230 0.640 533.9 0.6535 171 178 38 Surry Unit 1 Capsule V 0.230 0.640 538.8 1.1811 250 273 20 Surry Unit 1 Capsule X 0.230 0.640 542.0 1.1296 234 258 16

  • For credibility check, measured shift values are adjusted to average surveillance material chemistry and irradiation temperature as required. See Table 4.

Page 11 of 18 Summary (SA-1526, Alt. 2)

Table 4:

Beltline Material ID SA-1526/299L44 ET-NAF-990006 Tables.xis Surry Unit 1 Weld Material SA-1526 (All Data Except TMl-2)

CF Determination Beltline Beltline Irradiation Surveillance Data Material Material Temperature Position 1.1 Chemistry Credible or Non-Copper (wt%) Nickel (wt%)

(F)

Factor Credible?

0.340 0.680 542.0 220.6 Non-Credible

  • If swveillance data are determined to be non-credible, the Position 1.1 chemistry factor is applied to the beltline material.

If Surv. Data Non-Chemistry Credible, Verify Factor Applied Conservatism of to Beltline Applied Position 1.1 Material*

CF **

220.6 Conservative

.. Measured shift values are adjusted to the average surveillance material chemistry and irradiation temperature, and are verified to be within 2 sigma of the trend curve based on Position 1. 1.

Credibility Assessment Conservatism Check for Pos. 1.1 CF when Surv. Data Non-Credible (3)

(1)

(2)

Temperature Correction (4)

Temperature Chemistry Surveillance Applied to Credible Chemistry Correction Correction Correction Data Credible Surv. Data for Applied to Credible Surv.

Are adjusted surveillance Applied for Applied for or Non-Application to Beltline Data for Application to Adjusted Delta-Adjusted - Predicted data within 2 sigma of the Capsule ID (Including Source)

Credibility?

Credibility?

Credible?

Material?

Beltline Material?

RT(NDT) (F) **

Delta-RT(NDT) (F) **

applied CF trend curve? **

Capsule TMl2-LG1 (BWOG CR-3 lrrad.)

Capsule CR3-LG1 (BWOG CR-3 lrrad.)

Yes Yes Credible 181

-3 Capsule TMl2-LG1 (BWOG CR-3 lrrad.}

Three Mile Island Unit 1 Capsule C Yes Yes Non-Credible 161

-29 Three Mile Island Unit 1 Capsule E Yes Yes Credible 76

-9 Surry Unit 1 Capsule T Yes Yes Non-Credible 178 48 Surry Unit 1 Capsule V Yes Yes Credible 273 38 Surry Unit 1 Capsule X Yes Yes Credible 258 34 (1) For the credibility determination, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in a single reactor (i.e., were irradiated at a similar temperature).

(2) For the credibility determination, a chemistry correction is not applied to measured values of transition temperature shift if applicable surveillance data were obtained from a single source (i.e., were machined from the same block of material).

(3) For determination of the beltline material chemistry factor, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in the reactor vessel which is being evaluated (i.e., were irradiated at a similar temperature).

(4) For determination of the beltline material chemistry factor, a chemistry correction (i.e., ratio procedure) is not applied to measured values of transition temperature shift if the chemical composition of applicable surveillance data is essentially identical to the best-estimate chemical composition of the beltline material being evaluated.

Credible Credible Credible Credible Credible Credible Page 12 of 18 Summary (SA-1526, Alt. 2)

ET-NAF-990006 Tables.xis Table 2:

Surry Unit 1 Weld Material SA-1526 (All Data, No Adjustments)

Data Used In Irradiation Assessing Temperature Measured Delta-Vessel? (Yes or Capsule ID (Including Source)

Copper (wt%) Nickel (wt%)

(F)

Fluence (x1E19)

RT(NDT) (F)

No)

Capsule TM12-LG1 (BWOG CR-3 lrrad.)

0.370 0.700 556.0 0.830 216 Yes Capsule CR3-LG1 (BWOG CR-3 lrrad.)

0.360 0.700 556.0 0.779 202 Yes Capsule TMl2-LG1 (BWOG CR-3 lrrad.)

0.330 0.670 556.0 0.968 226 Yes Three Mile Island Unit 1 Capsule C 0.330 0.670 556.0 0.866 166 Yes Three Mile Island Unit 1 Capsule E 0.330 0.670 556.0 0.107 74 Yes Surry Unit 1 Capsule T 0.230 0.640 533.9 0.281 171 Yes Surry Unit 1 Capsule V 0.230 0.640 538.8 1.940 250 Yes Surry Unit 1 Capsule X 0.230 0.640 542.0 1.599 234 Yes Table 3:

Surry Unit 1 Weld Material SA-1526 (All Data, No Adjustments)

Irradiation Temperature Measured Delta-Adjusted Delta-Adjusted - Predicted Capsule ID (Including Source)

Copper (wt%) Nickel (wt%)

(F)

Fluence Factor RT(NDT) (F)

RT(NDT) (F)

  • Delta-RT(NDT) (F)
  • Capsule TMl2-LG1 (BWOG CR-3 lrrad.)

0.370 0.700 556.0 0.9477 216 216 14 Capsule CR3-LG1 (BWOG CR-3 lrrad.)

0.360 0.700 556.0 0.9299 202 202 4

Capsule TMl2-LG1 (BWOG CR-3 lrrad.)

0.330 0.670 556.0 0.9909 226 226 15 Three Mile Island Unit 1 Capsule C 0.330 0.670 556.0 0.9597 166 166

-38 Three Mile Island Unit 1 Capsule E 0.330 0.670 556.0 0.4305 74 74

-18 e

Surry Unit 1 Capsule T 0.230 0.640 533.9 0.6535 171 171 32 Surry Unit 1 Capsule V 0.230 0.640 538.8 1.1811 250 250

-1 Surry Unit 1 Capsule X 0.230 0.640 542.0 1.1296 234 234

-6

  • For credibility check, measured shift values are adjusted to average surveillance material chemistry and irradiation temperature as required. See Table 4.

Page 13 of 18 Summary (SA-1526, Alt. 3)

Table 4:

ET-NAF-990006 Tables.xis Surry Unit 1 Weld Material SA-1526 (All Data, No Adjustments)

CF Determination Chemistry Beltline Beltline Irradiation Surveillance Data Factor Applied Material Material Temperature Position 1.1 Chemistry Credible or Non-to Beltline Beltline Material ID Copper (wt%) Nickel (wt%)

(F)

Factor Credible?

Material*

SA-1526/299L44 0.340 0.680 542.0 220.6 Non-Credible 220.6

  • If surveillance data are determined to be non-credible, the Position 1. 1 chemistry factor is applied to the beltline material.

If Surv. Data Non-Credible, Verify Conservatism of Applied Position 1.1 CF**

Conservative

.. Measured shift values are adjusted to the average surveillance material chemistry and irradiation temperature, and are verified to be within 2 sigma of the trend curve based on Position 1. 1.

Credibility Assessment e

Conservatism Check for Pas. 1.1 CF when Surv. Data Non-Credible (3)

(1)

(2)

Temperature Correction (4)

Temperature Chemistry Surveillance Applied to Credible Chemistry Correction Correction Correction Data Credible Surv. Data for Applied to Credible Surv.

Are adjusted surveillance Applied for Applied for or Non-Application to Beltline Data for Application to Adjusted Delta-Adjusted - Predicted data within 2 sigma of the Capsule ID (Including Source)

Credibility?

Credibility?

Credible?

Material?

Beltline Material?

RT(NDT) (F) **

Delta-RT(NDT) (F) **

applied CF trend curve? **

Capsule TMl2-LG1 (BWOG CR-3 lrrad.)

No No Credible 216 22 Capsule CR3-LG1 (BWOG CR-3 lrrad.)

No No Credible 202 12 Capsule TMl2-LG1 (BWOG CR-3 lrrad.)

No No Credible 226 23 Three Mile Island Unit 1 Capsule C No No Non-Credible 166

-30 Three Mile Island Unit 1 Capsule E No No Credible 74

-14 Surry Unit 1 Capsule T No No Non-Credible 171 37 Surry Unit 1 Capsule V No No Credible 250 8

Surry Unit 1 Capsule X No No Credible 234 3

(1) For the credibility determination, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in a single reactor (i.e., were irradiated at a similar temperature).

(2) For the credibility determination, a chemistry correction is not applied to measured values of transition temperature shift if applicable surveillance data were obtained from a single source (i.e., were machined from the same block of material).

(3) For determination of the beltline material chemistry factor, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in the reactor vessel which is being evaluated (i.e., were irradiated at a similar temperature).

(4) For determination of the beltline material chemistry factor, a chemistry correction (i.e., ratio procedure) is not applied to measured values of transition temperature shift if the chemical composition of applicable surveillance data is essentially identical to the best-estimate chemical composition of the beltline material being evaluated.

Credible Credible Credible Credible Credible Credible Credible Credible Page 14 of 18 Summary (SA-1526, Alt. 3)

ET-NAF-990006 Tables.xis Table 2:

Surry Unit 1 Weld Material SA-1526 (All Data Except Surry Unit 1 Data)

Data Used In Irradiation Assessing Temperature Measured Delta-Vessel? (Yes or Capsule ID (Including Source)

Copper (wt%) Nickel (wt%)

(F)

Fluence (x1E19)

RT(NDT) (F)

No)

Capsule TMl2-LG1 (BWOG CR-3 lrrad.)

0.370 0.700 556.0 0.830 216 Yes Capsule CA3-LG1 (BWOG CR-3 lrrad.)

0.360 0.700 556.0 0.779 202 Yes Capsule TMl2-LG1 (BWOG CA-3 lrrad.)

0.330 0.670 556.0 0.968 226 Yes Three Mile Island Unit 1 Capsule C 0.330 0.670 556.0 0.866 166 Yes Three Mile Island Unit 1 Capsule E 0.330 0.670 556.0 0.107 74 Yes Surry Unit 1 Capsule T 0.230 0.640 533.9 0.281 171 No Surry Unit 1 Capsule V 0.230 0.640 538.8 1.940 250 No Surry Unit 1 Capsule X 0.230 0.640 542.0 1.599 234 No e

Table 3:

Surry Unit 1 Weld Material SA-1526 (All Data Except Surry Unit 1 Data)

Irradiation Temperature Measured Delta-Adjusted Delta-Adjusted - Predicted Capsule ID (Including Source)

Copper (wt%) Nickel (wt%)

(F)

Fluence Factor RT(NDT) (F)

AT(NDT) (F)

  • Delta-AT(NDT) (F)
  • Capsule TMl2-LG1 (BWOG CR-3 lrrad.)

0.370 0.700 556.0 0.9477 216 205 7

Capsule CA3-LG1 (BWOG CR-3 lrrad.)

0.360 0.700 556.0 0.9299 202 195 1

Capsule TM12-LG1 (BWOG CA-3 lrrad.)

0.330 0.670 556.0 0.9909 226 233 26 Three Mile Island Unit 1 Capsule C 0.330 0.670 556.0 0.9597 166 171

-29 Three Mile Island Unit 1 Capsule E 0.330 0.670 556.0 0.4305 74 76

-13

  • For credibility check, measured shift values are adjusted to average surveillance material chemistry and irradiation temperature as required. See Table 4.

Page 15 of 18 Summary (SA-1526, Alt. 4)

Table 4:

Beltline Material ID SA-1526/299L44 ET-NAF-990006 Tables.xis Surry Unit 1 Weld Material SA-1526 (All Data Except Surry Unit 1 Data)

CF Determination Chemistry Beltline Beltline Irradiation Surveillance Data Factor Applied Material Material Temperature Position 1.1 Chemistry Credible or Non-to Beltline Copper (wt%) Nickel (wt%)

(F)

Factor Credible?

Material*

0.340 0.680 542.0 220.6 Non-Credible 220.6

  • If surveillance data are determined to be non-credible, the Position 1. 1 chemistry factor is applied to the beltline material.

If Surv. Data Non-Credible, Verify Conservatism of Applied Position 1.1 CF**

Conservative

    • Measured shift values are adjusted to the average surveillance material chemistry and irradiation temperature, and are verified to be within 2 sigma of the trend curve based on Position 1. 1.

Credibility Assessment e

Conservatism Check for Pos. 1.1 CF when Surv. Data Non-Credible (3)

(1)

(2)

Temperature Correction (4)

Temperature Chemistry Surveillance Applied to Credible Chemistry Correction Correction Correction Data Credible Surv. Data for Applied to Credible Surv.

Are adjusted surveillance Applied for Applied for or Non-Application to Beltline Data for Application to Adjusted Delta-Adjusted - Predicted data within 2 sigma of the Capsule ID (Including Source)

Credibility?

Credibility?

Credible?

Material?

Beltline Material?

RT(NDT) (F) **

Delta-RT(NDT) (F) **

applied CF trend curve? **

Capsule TMl2-LG1 (BWOG CR-3 lrrad.)

Yes Yes Credible 205

-5 Capsule CR3-LG1 (BWOG CR-3 lrrad.)

Yes Yes Credible 195

-12 Capsule TMl2-LG1 (BWOG CR-3 lrrad.)

Yes Yes Credible 233 13 Three Mile Island Unit 1 Capsule C Yes Yes Non-Credible 171

-42 Three Mile Island Unit 1 Capsule E Yes Yes Credible 76

-19 Surry Unit 1 Capsule T Surry Unit 1 Capsule V Surry Unit 1 Capsule X (1) For the credibility determination, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in a single reactor (i.e., were irradiated at a similar temperature).

(2) For the credibility determination, a chemistry correction is not applied to measured values of transition temperature shift if applicable surveillance data were obtained from a single source (i.e., were machined from the same block of material).

(3) For determination of the beltline material chemistry factor, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in the reactor vessel which is being evaluated (i.e., were irradiated at a similar temperature).

(4) For determination of the beltline material chemistry factor, a chemistry correction (i.e., ratio procedure) is not applied to measured values of transition temperature shift if the chemical composition of applicable surveillance data is essentially identical to the best-estimate chemical composition of the beltline material being evaluated.

Credible Credible Credible Credible Credible Page 16 of 18 Summary (SA-1526, Alt. 4)

ET-NAF-990006 Tables.xis Table 2:

Surry Unit 2 Weld Material R3008 Data Used In Irradiation Assessing Temperature Measured Delta-Vessel? (Yes or Capsule ID (Including Source)

Copper (wt%) Nickel (wt%)

(F)

Fluence (x1 E 19)

RT(NDT) (F)

No)

Surry Unit 2 Capsule X 0.190 0.550 534.9 0.302 96 Yes Surry Unit 2 Capsule V 0.190 0.550 540.1 1.880 140 Yes Table 3:

Surry Unit 2 Weld Material R3008 Irradiation Temperature Measured Delta-Adjusted Delta-Adjusted - Predicted Capsule ID (Including Source)

Copper (wt%) Nickel (wt%)

(F)

Fluence Factor RT(NDT) (F)

RT(NDT) (F)

  • Delta-RT(NDT) (F)
  • Surry Unit 2 Capsule X 0.190 0.550 534.9 0.6720 96 96 12 Surry Unit 2 Capsule V 0.190 0.550 540.1 1.1729 140 140

-7

  • For credibility check, measured shift values are adjusted to average surveillance material chemistry and irradiation temperature as required. See Table 4.

Page 17 of 18 Summary (R3008)

Table 4:

Beltline Material ID R3008 ET-NAF-990006 Tables.xis Surry Unit 2 Weld Material R3008 CF Determination Beltline Beltline Irradiation Material Material Temperature Position 1.1 Chemistry Copper (wt%) Nickel (wt%)

(F)

Factor 0.190 0.550 543.1 149.3 Surveil)ance Data Credible or Non-Credible?

Credible

'ff surveillance data are determined to be non-credible, the Position 1.1 chemistry factor is applied to the beltline material.

If Surv. Data Non-Chemistry Credible, Verify Factor Applied Conservatism of to Beltline Applied Position 1.1 Material*

CF**

125.2

    • Measured shift values are adjusted to the average surveillance material chemistry and irradiation temperature, and are verified to be within 2 sigma of the trend curve based on Position 1.1.

Credibility Assessment e

Conservatism Check for Pos. 1.1 CF when Surv. Data Non-Credible (3)

(1)

(2)

Temperature Correction (4)

Temperature Chemistry Surveillance Applied to Credible Chemistry Correction Correction Correction Data Credible Surv. Data for Applied to Credible Surv.

Are adjusted surveillance Applied for Applied for or Non-Application to Beltline Data for Application to Adjusted Delta-Adjusted - Predicted data within 2 sigma of the Capsule ID (Including Source)

Credibility?

Credibility?

Credible?

Material?

Beltline Material?

RT(NDT) (F) **

Delta-RT(NDT) (F) **

applied CF trend curve? **

Surry Unit 2 Capsule X No No Credible No No Surry Unit 2 Capsule V No No Credible No No (1) For the credibility determination, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in a single reactor (i.e., were irradiated at a similar temperature).

(2) For the credibility determination, a chemistry correction is not applied to measured values of transition temperature shift if applicable surveillance data were obtained from a single source (i.e., were machined from the same block of material).

(3) For determination of the beltline material chemistry factor, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in the reactor vessel which is being evaluated (i.e., were irradiated at a similar temperature).

(4) For determination of the beltline material chemistry factor, a chemistry correction (i.e., ratio procedure) is not applied to measured values of transition temperature shift if the chemical composition of applicable surveillance data is essentially identical to the best-estimate chemical composition of the beltline material being evaluated.

Page 18 of 18 Summary (R3008)

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