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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 e
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:
Februarf 24, 1999 United States Nuclear Regulatory Commission                 Serial No.      99-034 Attention: Document Control Desk                             NAF/JRH        RO Washington, D. C. 20555-0001                                 Docket Nos. 50-280, 281 License Nos. DPR-32, 37 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 Serial No.
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 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.
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|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.
During the preparation of a coordinated BWOG response to an NRC RAI regarding changes in reported transition temperature shift values, Framatome Technologies, Inc.
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 (LTOPS) setpoint and enabling temperature, and 3) the 10 CFR 50.61 Pressurized Thermal Shock (PTS} screening calculations. A discussion of and the resu~s-~ the-~vi:;     :':~l~t:
(FTI) discovered errors in previously reported data.
the changes to the previously reported surveillance results is provided in the attachment, are reported in Appendix A to fue atta;m;~ 2, t I 1
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
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This information supplements the information previously reported in the June 18, 1998 letter. noted above.
This information supplements the information previously reported in the {{letter dated|date=June 18, 1998|text=June 18, 1998 letter}}. noted above.
Please contact us if you have any questions or require additional information.
Please contact us if you have any questions or require additional information.
Very truly yours,
Very truly yours,  
~rfL. N. Hartz Vice President - Nuclear Engineering and Services Attachment Commitments made in this letter: None.
~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
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  


e COMMONWEALTH OF VIRGINIA               )
COMMONWEAL TH OF VIRGINIA COUNTY OF HENRICO
                                      )
)  
COUNTY OF HENRICO                      )
)  
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
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.
- 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   4T.bday of jJ.nuoNJc ,19 qq .
Acknowledged before me this d 4 T.bday of jJ.nuoNJc, 19 qq.
My Commission Expires: March 31, 2000.
0 My Commission Expires: March 31, 2000.  
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                                                  ~Tu~     Notary Public (SEAL)
Notary Public (SEAL)  


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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:
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),
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
299L44 (Surry Unit 1 weld material SA-1526), and 0227 (Rotterdam-fabricated Surry Unit 2 weld material R3008).
* 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 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).
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.
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).
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.,
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).
Surry Unit 2) and (b) the chemical composition of the surveillance specimens was Page 1 of 7
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).
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):
:_ 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 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 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 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-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.
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):
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.
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):
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 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.
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
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 1cr (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
* 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).
  . 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.
A  
Page 2 of 7
. 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.
* 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
Page 2 of 7  
*. 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 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.
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 LTOPS 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).
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 existing Surry Units 1 and 2 Prr limits and LTOPS setpoints (9)(10) are based on a limiting %-thickness (%-T) RTNDT of 228.4°F. This value of RTNDT 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.
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).
This value of RTNDT 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 LTOPS setpoints (2)(3) remain valid and conservative.
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.
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
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),,
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.
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).
Location                                               Fluence (n/cm~)
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.
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
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  


Conclusions
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).
* e 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 LTOPS 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  
Page 5 of 7


References
e References (1)
* e (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.
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.
(2)
(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.
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.
(4)   "Response to Request for Additional Information (RAI) Regarding Reactor Pressure Vessel Integrity," BAW-2325, dated May, 1998.
(3)
(5)   Regulatory Guide 1.99 Revision 2, "Radiation Embrittlement of Reactor Vessel Materials," dated May, 1988.
Letter from G. C. Lainas (USNRC) to D. J. Modeen (NEI), "Request for Additional Information Regarding Reactor Pressure Vessel Integrity," dated February 5, 1998.
(6)   Title 10, Code of Federal Regulations, Part 50.61, "Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events."
(4)  
(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.
"Response to Request for Additional Information (RAI) Regarding Reactor Pressure Vessel Integrity," BAW-2325, dated May, 1998.
(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.
(5)
(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 LTOPS Setpoint," Serial No. 95-197, June 8, 1995.
Regulatory Guide 1.99 Revision 2, "Radiation Embrittlement of Reactor Vessel Materials," dated May, 1988.
Page 6 of 7
(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)
(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
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  
    *. Curves (TAC Nos. M92537 and M92538)," Serial No. 96-020, dated December
*
  *
* 28, 1995.
* 28, 1995.
(11)   WCAP-12794 Revision 3, "Reactor Cavity Neutron Measurement Program for Wisconsin Electric Power Company Point Beach Unit 1," dated December 1995.
(11)
(12)   Virginia Power Topical Report VEP-NAF-3, "Reactor Vessel Fluence Analysis Methodology," dated November, 1997.
WCAP-12794 Revision 3, "Reactor Cavity Neutron Measurement Program for Wisconsin Electric Power Company Point Beach Unit 1," dated December 1995.
(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.
(12)
(14)   Draft Regulatory Guide DG-1053, "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence," dated June 1996.
Virginia Power Topical Report VEP-NAF-3, "Reactor Vessel Fluence Analysis Methodology," dated November, 1997.
(15)   BAW-2324, "Analysis of Capsule X, Virginia Power Surry Unit No. 1, Reactor Vessel Material Surveillance Program," dated April, 1998.
(13)
Page 7 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.
(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
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                                                               Inner Surf.              Current Estimate   Estimate   EOLID           Material   Method of                                                    ART or                Licensing RPV Weld Wire Heat                                           Copper     Nickel   Fluence       Chemistry   Determining    Initial                                      RT(PTS) at    1/4-T    Basis 1/4 -
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)
or Material ID (1) 122V109VA1 C4326-1 Location Nozzle Shell Forging Intermediate Shell (wt%)
Location (wt%)
0.11 0.11 (wt%)
(wt%)
0.74 0.55 (x1E19) 0.307 3.53 Factor 76.1 73.5 CF (2)
(x1E19)
Tables Tables RT(NDT) 40 10 Sigma(!)
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%)
0.0 0.0 Sigma(delta) 17.0 17.0 Margin 34.0 34.0 EOL 125.5 141 .6 ART 116.1 132.8 TART
0.22 0.54 3.2 139.8 SA-1650/72445 Int. to Low Sh. Circ (OD 60%)
* 112.5 135.2 e
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.)
C4326-2                   Intermediate Shell           0.11       0.55       3.53           73.5       Tables          0        0.0        17.0        34.0        131 .6      122.8      125.2 4415-1                       Lower Shell             0.11       0.50       3.53           85.0     Surv. Data      20        0.0          8.5        17.0        149.9      139.7      147.6 4415-2                       Lower Shell             0.11       0.50       3.53           73.0       Tables          0        0.0        17.0        34.0        131 .0      122.2      124.6 J726/25017           Nozzle to Int Shell Gire Weld       0.33       0.10       0.307           152.0     Tables          0      20.0        28.0        68.8        171 .6      153.0      169.8 SA-1585/72445           Int. to Low Sh. Gire (ID 40%)       0.22       0.54       3.2           139.8     Surv. Data      -5      19.7        14.0        48.3      225.8        208.6      228.4
(2) determined from tables or from surveillance data Method of Determining CF (2)
* SA-1650/72445         Int. to Low Sh. Circ (OD 60%)       0.22       0.54       3.2           139.8     Surv. Data      -5      19.7        14.0       48.3      225.8        208.6     228.4
Tables Tables Tables Surv. Data Tables Tables Surv. Data Surv. Data Tables Tables Tables Summary (Surry)
* SA-1494/8T1554         Int Shell Long. Welds L3 & L4        0.16       0.57       0.6            143.9     Tables         -5       19.7         28 .0       68 .5       186.8       167.4      181.4 SA-1494/8T1554            Lower Shell Long. Weld L 1        0.16      0.57        0.54          143.9      Tables        -5       19.7         28.0       68 .5       182.6      163.4       181.4 SA-1526/299L44            Lower Shell Long. Weld L2          0.34      0.68       0.54          220.6     Tables        -7       20.6         28.0       69.5       245.1       215.7       207.0 (1) or the material identification number of the limiting material as requested in Section 1.0 (1 .)
Inner Surf.
* 1/4-T ART value of 228.4 F was used in the determination of PIT limits (2) determined from tables or from surveillance data Summary (Surry)
Current ART or Licensing Initial RT(PTS) at 1/4-T Basis 1/4-RT(NDT)
Page 1 of 18
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                                                           Inner Surf.              Current Estimate   Estimate   EOLID           Material   Method of                                                ART or                Licensing RPV Weld Wire Heat                                           Copper     Nickel   Fluence       Chemistry   Determining  Initial                                    RT(PTS) at    1/4-T  Basis 1/4-or Material ID (1) 123V303VA1 C433 1-2 Location Nozzle Shell Forging Intermediate Shell (wt%)
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)
0.11 0.12 (wt%)
Location (wt%)
0.72 0.60 (x1E19) 0.298 3.520 Factor 75.8 83.0 CF(2)
(wt%)
Tables Tables RT(NDT) 30
(x1E19)
                                                                                                                            -10 Sigma(I) 0.0 0.0 Sigma(delta) 17.0 17.0 Margin 34.0 34.0 EOL 114.7 134.2 ART 105.5 124.2 TART*
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%)
100.4 123.9 e
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%)
C4339-2                   Intermediate Shell           0.11       0.54     3.520           73.4      Tabl es    -20        0.0        17.0        34.0      111 .5      102.6      102.4 C4208-2                       Lower Shell               0.15       0.55     3.520           107.3     Tables      -30        0.0        17.0        34.0      146.4      133.5      133. 1 C4339-1                       Lower Shell               0.11       0.54     3.520           68.4     Surv. Data  -1 0      0.0          8.5        17.0        97.8      89.6        89.3 L737/4275           Nozzle to Int Shell Gire Weld       0.35       0.10     0.298           160.5     Tabl es      0        20.0        28.0        68.8      176.1      156.6      169.6 A3008/0227           Int. to Lower Shell Gire Weld       0.19       0.55     3.520           125.2     Surv. Data    0        20.0        14.0        48.8      215.0      200.0      202.9 WF-4/8T1762             Int. Shell Long. L4 (ID 50%)       0.19       0.57     0.697           152.4     Tables      -5      19.7        28.0        68.5      200.4      179.6      181 .0 SA-1585/72445         Int. Sh. L3 (100%), L4 (OD 50)       0.22       0.54     0.697           139.8     Surv. Data    -5      19.7        14.0        48.3      168.9      149.9      158.5 WF-4/8T1762               LS L2 (ID 63%), L1 (100)         0.19       0.57     0.697           152.4     Tables      -5      19.7        28.0        68.5      200.4      179.6      181 .0 WF-8/8T1762           LS Long. Weld L2 (OD 37%)           0.19       0.57     0.697           152.4     Tables       -5       19.7         28.0       68.5       200.4       179.6     181 .0 (1) or the material identification number of the limiting material as requested in Section 1.0 (1 .)
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.)
* 1/4-T ART value of 228.4 F was used in the determination of Prr limits (2) determined from tables or from surveillance data Summary (Surry)
(2) determined from tables or from surveillance data Method of Determining CF(2)
Page 2 of 18
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)
ET-NAF-990006 Tables.xis Table 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)
Surry Unit 1 and 2 Weld Material SA-1585 (Point Beach 1 Data Only)
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
Data Used In Irradiation Assessing Temperature Measured Delta-Vessel? (Yes or Capsule ID (Including Source)
Table 3:                                   Surry Unit 1 and 2 Weld Material SA-1585 (Point Beach 1 Data Only)
Copper (wt%) Nickel (wt%)
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)
(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)
* 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 e
* Point Beach Unit 1 Capsule T 0.230 0.615 533.4 1.2173 181 181 7
Point Beach Unit 1 Capsule V             0.230           0.615           542 .0             0.8723                     107                 107               -17
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.
* 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
Page 3 of 18 Summary (SA-1585) - Corrected L


ET-NAF-990006 Tables.xis Table 4:                                      Surry Unit 1 and 2 Weld Material SA-1585 (Point Beach 1 Data Only)
Table 4:
CF Determination If Surv. Data Non-Chemistry         Credible, Verify Beltline     Beltline         Irradiation                               Surveillance Data       Factor Applied     Conservatism of Material     Material       Temperature     Position 1.1 Chemistry     Credible or Non-         to Beltline   Applied Position 1.1 Beltline Material ID            Copper (wt%)   Nickel (wt%)           (F)               Factor                 Credible?             Material*            CF **
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)
SA-1585/72445                      0.220         0.540             542 .0               158.0               Non-Credible             158.0           Conservative
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 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.
** 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
Credibility Assessment e
Conservatism Check for Pos. 1.1 CF when Surv. Data Non-Credible (3)
Conservatism Check for Pos. 1.1 CF when Surv. Data Non-Credible (3)
(1)           (2)                         Temperature Correction               (4)
(1)
Temperature   Chemistry       Surveillance       Applied to Cred ible  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? **
(2)
Point Beach Unit 1 Capsule T               No             No           Credible                 -                        -                  181                 -28                       Credible Point Beach Unit 1 Capsule R               No             No           Credible                 -                        -                  155                 -53                       Credible Point Beach Unit 1 Capsule S               No             No         Non-Credible               -                        -                  165                 2                       Credible Point Beach Unit 1 Capsule V               No             No           Credible                 -                        -                  107                 -43                       Credible Capsule CR3-LG2 (BWOG CR-3 lrrad.)                 -              -                -                    -                        -                    -                    -                          -
Temperature Correction (4)
Capsule CR3-LG1 (BWOG CR-3 lrrad .)                 -              -                -                    -                        -                    -                    -                          -
Temperature Chemistry Surveillance Applied to Credible Chemistry Correction Correction Correction Data Credible Surv. Data for Applied to Credible Surv.
(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 irradiated at a similar temperature).
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)
(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).
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).
(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 4 of 18 Summary (SA-1585) - Corrected
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)
ET-NAF-990006 Tables.xis Table 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)
Surry Unit 1 and 2 Weld Material SA-1585 (All Available Data)
Point Beach Unit 1 Capsule T             0.230         0.615           533.4               2.230                     181                 Yes S\ c,          c:        .. it 155 "'
Data Used In Irradiation Assessing Temperature Measured Delta-Vessel? (Yes or Capsule ID (Including Source)
Point Beach Unit 1 Capsule R             0.230         0.615           541 .6               2.190                                           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)
Copper (wt%) Nickel (wt%)
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)
(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)
* Point Beach Unit 1 Capsule T             0.230           0.615         533.4               1.2173                     181                 167               -10 Point Beach Unit 1 Capsul e 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
* 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.
* 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)
Page 5 of 18 Summary (SA-1585, Alt. 1)
L__ ----
L


ET-NAF-990006 Tables.xis Table 4:                                      Surry Unit 1 and 2 Weld Material SA-1585 (All Available Data)
Table 4:
CF Determination If Surv. Data Non-Chemistry        Credible, Verify Beltline       Beltline         Irradiation                               Surveillance Data     Factor Applied    Conservatism of Material       Material       Temperature     Position 1.1 Chemistry     Credible or Non-         to Beltline    Applied Position 1.1 Beltline Material ID            Copper (wt%)   Nickel (w1%)           (F)               Factor                 Credible?             Material*            CF**
Beltline Material ID SA-1585n2445 ET-NAF-990006 Tables.xis Surry Unit 1 and 2 Weld Material SA-1585 (All Available Data)
SA-1585n2445                      0.220         0.540             542.0                 158.0                 Credible               139.8                  -
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 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.
** 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.
e Credibility Assessment Conservatism Check for Pos. 1.1 CF when Surv. Data Non-Credible (3)
Credibility Assessment e
(1)           (2)                         Temperature Correction             (4)
Conservatism Check for Pos. 1.1 CF when Surv. Data Non-Credible (3)
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? **
(1)
Point Beach Unit 1 Capsule T             Yes           Yes             Credible                 Yes                     Yes                   -                    -                          -
(2)
Point Beach Unit 1 Capsule R             Yes           Yes             Credible                 Yes                     Yes                   -                    -                          -
Temperature Correction (4)
Point Beach Unit 1 Capsule S             Yes           Yes             Credible                 Yes                     Yes                   -                    -                          -
Temperature Chemistry Surveillance Applied to Credible Chemistry Correction Correction Correction Data Credible Surv. Data for Applied to Credible Surv.
Point Beach Unit 1 Capsule V             Yes           Yes             Credible                 Yes                     Yes                   -                    -                          -
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)
Capsule CR3-LG2 (BWOG CR-3 lrrad .)               Yes           Yes             Credible                 Yes                     Yes                   -                    -                          -
Credibility?
Capsule CR3-LG1 (BWOG CR-3 lrrad .)               Yes           Yes           Non-Credible               Yes                     Yes                   -                    -                          -
Credibility?
(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).
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).
(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 6 of 18 Summary (SA-1585, Alt. 1)
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)
ET -NAF-990006 Tables.xis Table 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)
Surry Unit 1 Weld Material SA-1526 (Surry Unit 1 Data Only)
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)
Data Used In Irradiation Assessing Temperature Measured Delta-Vessel? (Yes or Capsule ID (Including Source)
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)
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)
* 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
* 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.
* 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)
Page 7 of 18 Summary (SA-1526)  


ET-NAF-990006 Tables.xis Table 4:                                      Surry Unit 1 Weld Material SA-1526 (Surry Unit 1 Data Only)
Table 4:
CF Determination If Surv. Data Non-Chemistry        Credible, Verify Beltline     Beltline       Irradiation                                 Surveillance Data     Factor Applied    Conservatism of Material     Material       Temperature     Position 1.1 Chemistry       Credible or Non-         to Beltline    Applied Position 1.1 Beltline Material ID            Copper (wt%) Nickel (wt%)           (F)               Factor                   Credible?             Material
Beltline Material ID SA-1526/299L44 ET-NAF-990006 Tables.xis Surry Unit 1 Weld Material SA-1526 (Surry Unit 1 Data Only)
* CF*
CF Determination Beltline Beltline Irradiation Surveillance Data Material Material Temperature Position 1.1 Chemistry Credible or Non-Copper (wt%) Nickel (wt%)
* SA-1526/299L44                      0.340         0 .680           542.0                 220.6                 Non-Credible             220.6          Conservative
(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 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.
** 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
Credibility Assessment e
Conservatism Check for Pos. 1.1 CF when Surv. Data Non-Credible (3)
Conservatism Check for Pos. 1.1 CF when Surv. Data Non-Credible (3)
(1)           (2)                         Temperature Correction               (4)
(1)
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? **
(2)
Capsule TMl2-LG1 (BWOG CR-3 lrrad.)                   -            -                -                    -                          -                    -                    -
Temperature Correction (4)
Capsule CR3-LG1 (BWOG CR-3 lrrad .)                   -            -                -                    -                          -                    -                    -                          -
Temperature Chemistry Surveillance Applied to Credible Chemistry Correction Correction Correction Data Credible Surv. Data for Applied to Credible Surv.
Capsule TMl2-LG1 (BWOG CR-3 lrrad.)                   -            -                -                    -                          -                    -                    -                          -
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)
Three Mile Island Unit 1 Capsule C               -            -                -                    -                          -                    -                    -                          -
Credibility?
Three Mile Island Unit 1 Capsule E               -            -                -                    -                          -                    -                    -                          -
Credibility?
Surry Unit 1 Capsule T                 No             No         Non-Credible               -                          -                  171                 56                       Credible Surry Unit 1 Capsule V                 No             No           Credible                 -                          -                  250                 42                       Credible Surry Unit 1 Capsule X                 No             No           Credible                 -                          -                  234                 35                       Credible (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) .
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).
(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 8 of 18 Summary (SA-1526)
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)
ET-NAF-990006 Tables.xis Table 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)
Surry Unit 1 Weld Material SA-1526 (All Available Data)
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)
Data Used In Irradiation Assessing Temperature Measured Delta-Vessel? (Yes or Capsule ID (Including Source)
Irradiation Temperature                                   Measured Delta-       Adjusted Delta- Adjusted
Copper (wt%) Nickel (wt%)
* Predicted Capsule ID (Including Source)         Copper (wt%) Nickel (wt%)           (F)           Fluence Factor             RT(NDT) (F)         RT(NDT) (F)
(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 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
* 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.
* 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)
Page 9 of 18 Summary (SA-1526, Alt. 1)  


ET-NAF-990006 Tables.xis Table 4:                                      Surry Unit 1 Weld Material SA-1526 (All Available Data)
Table 4:
CF Determination If Surv. Data Non-Chemistry        Credible, Verify Beltline     Beltline       Irradiation                                 Surveillance Data       Factor Applied    Conservatism of Material     Material       Temperature     Position 1.1 Chemistry       Credible or Non-         to Beltline  Applied Position 1.1 Beltline Material ID            Copper (wt%) Nickel (wt%)           (F)               Factor                   Credible?             Material
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**
* CF**
SA-1526/299L44                      0.340        0.680            542.0                220.6                  Non-Credible              220.6         Conservative
220.6 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.
** 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)
Credibility Assessment Conservatism Check for Pos. 1.1 CF when Surv. Data Non-Credible (3)
(1)           (2)                         Temperature Correction               (4)
(1)
Temperature   Chemistry       Surveillance       Applied to Credible     Chemistry Correction Correction   Correction       Data Credible         Surv. Data for     Appl ied 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? **
(2)
Capsule TMl2-LG1 (BWOG CR-3 lrrad.)                 Yes           Yes           Credible                   -                        -                    195                 1                       Credible Capsule CR3-LG1 (BWOG CR-3 lrrad .)                 Yes           Yes           Credible                   -                        -                    185                 -5                       Credible Capsule TMl2-LG1 (BWOG CR -3 lrrad.)               Yes           Yes           Credible                   -                        -                    221                 19                       Credible Three Mile Island Unit 1 Capsule C             Yes           Yes         Non-Credible                 -                        -                    164               -32                       Credible Three Mile Island Unit 1 Capsule E             Yes           Yes           Credible                   -                        -                    77                 -11                       Credible Surry Unit 1 Capsule T                 Yes           Yes         Non-Credible                 -                        -                    181                 47                       Credible Surry Unit 1 Capsule V                 Yes           Yes           Credible                   -                        -                    279                 37                       Credible Surry Unit 1 Capsule X                 Yes           Yes           Credible                   -                        -                    264                 33                       Credible (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) .
Temperature Correction (4)
(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) .
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).
(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 10 of 18 Summary (SA-1526, Alt. 1)
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)
ET-NAF-990006 Tables.xis Table 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)
Surry Unit 1 Weld Material SA-1526 (All Data Except TMl-2)
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)
Data Used In Irradiation Assessing Temperature Measured Delta-Vessel? (Yes or Capsule ID (Including Source)
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)
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)
* 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 Three Mile Island Unit 1 Capsule E Surry Unit 1 Capsule T Surry Unit 1 Capsule V Surry Unit 1 Capsule X 0.330 0.330 0.230 0.230 0.230 0.670 0.670 0.640 0.640 0.640 556.0 556.0 533.9 538 .8 542.0 0.9597 0.4305 0.6535 1.1811 1.1296 166 74 171 250 234 161 76 178 273 258
* Capsule CR3-LG1 (BWOG CR-3 lrrad.)
                                                                                                                                                                      -44
0.360 0.700 556.0 0.9299 202 181  
                                                                                                                                                                      -16 38 20 16
-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.
* 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)
Page 11 of 18 Summary (SA-1526, Alt. 2)  


ET-NAF-990006 Tables.xis Table 4:                                        Surry Unit 1 Weld Material SA-1526 (All Data Except TMl-2)
Table 4:
CF Determination If Surv. Data Non-Chemistry      Credible, Verify Beltline     Beltline         Irradiation                               Surveillance Data         Factor Applied  Conservatism of Material     Material       Temperature     Position 1.1 Chemistry     Credible or Non-           to Beltline  Applied Position 1.1 Beltline Material ID              Copper (wt%) Nickel (wt%)           (F)               Factor                 Credible?               Material*          CF **
Beltline Material ID SA-1526/299L44 ET-NAF-990006 Tables.xis Surry Unit 1 Weld Material SA-1526 (All Data Except TMl-2)
SA-1526/299L44                      0.340       0.680             542 .0               220.6                 Non-Credible               220.6        Conservative
CF Determination Beltline Beltline Irradiation Surveillance Data Material Material Temperature Position 1.1 Chemistry Credible or Non-Copper (wt%) Nickel (wt%)
* If swveillance data are determined to be non-credible, the Position 1. 1 chemistry factor is applied to the beltline material .
(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.
.. 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)
Credibility Assessment Conservatism Check for Pos. 1.1 CF when Surv. Data Non-Credible (3)
(1)           (2)                         Temperature Correction               (4)
(1)
Temperature   Chemistry       Surveillance       Applied to Credible   Chemistry Correction Correction   Correction       Data Credible         Surv. Data for     Appl ied to Cred ible Surv.                                           Are adjusted surveillance Applied for   Applied for         or Non-       Application to Beltline Data for Ap plication to Adjusted Delta-   Adjusted - Predicted     data within 2 sigma of the Capsule ID (Including Source)             Credibility? Credibility?       Credible?             Material?           Beltl ine Material?     RT(NDT) (F) ** Delta-RT(N DT) (F) **   applied CF trend curve? **
(2)
Capsule TM l2-LG1 (BWOG CR-3 lrrad.)                   -            -                  -                    -                        -                      -                  -                          -
Temperature Correction (4)
Capsule CR3-LG1 (BWOG CR-3 lrrad.)                   Yes         Yes             Credible                   -                        -                    181               -3                     Credible Capsule TMl2-LG1 (BWOG CR-3 lrrad.}                   -            -                  -                    -                        -                      -                  -                          -
Temperature Chemistry Surveillance Applied to Credible Chemistry Correction Correction Correction Data Credible Surv. Data for Applied to Credible Surv.
Three Mile Island Unit 1 Capsule C               Yes         Yes           Non-Credible                 -                        -                    161               -29                     Credible Three Mile Island Unit 1 Capsule E               Yes         Yes             Credible                   -                        -                    76                 -9                     Credible Surry Unit 1 Capsule T                 Yes         Yes           Non-Credible                 .                        -                    178               48                     Credible Surry Unit 1 Capsule V                 Yes         Yes             Credible                   -                        .                    273               38                     Credible Surry Unit 1 Capsule X                 Yes         Yes             Credible                   .                        -                    258               34                     Credible (1) For the cred ibility 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 irrad iated at a similar temperature).
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)
(2) For the credibility determination, a chemistry correction is not applied to measured values of trans ition temperature shift if applicable surveillance data were obtained from a single source (i.e., were machined from the same block of material).
Credibility?
(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).
Credibility?
(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 beltl ine material being evaluated.
Credible?
Page 12 of 18 Summary (SA-1526, Alt. 2)
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)
ET-NAF-990006 Tables.xis Table 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)
Surry Unit 1 Weld Material SA-1526 (All Data, No Adjustments)
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)
Data Used In Irradiation Assessing Temperature Measured Delta-Vessel? (Yes or Capsule ID (Including Source)
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)
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 Three Mile Island Unit 1 Capsule E Surry Unit 1 Capsule T 0.330 0.330 0.230 0.670 0.670 0.640 556.0 556 .0 533.9 0.9597 0.4305 0.6535 166 74 171 166 74 171
* Capsule TMl2-LG1 (BWOG CR-3 lrrad.)
                                                                                                                                                                      -38
0.370 0.700 556.0 0.9477 216 216 14 Capsule CR3-LG1 (BWOG CR-3 lrrad.)
                                                                                                                                                                      -18 32 e
0.360 0.700 556.0 0.9299 202 202 4
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
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.
* 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)
Page 13 of 18 Summary (SA-1526, Alt. 3)  


ET-NAF-990006 Tables.xis Table 4:                                      Surry Unit 1 Weld Material SA-1526 (All Data, No Adjustments)
Table 4:
CF Determination If Surv. Data Non-Chemistry       Credible, Verify Beltline       Beltline         Irradiation                                 Surveillance Data       Factor Applied     Conservatism of Material       Material       Temperature     Position 1.1 Chemistry       Credible or Non-         to Beltline Applied Position 1.1 Beltline Material ID           Copper (wt%)   Nickel (wt%)             (F)               Factor                   Credible?           Material*            CF**
ET-NAF-990006 Tables.xis Surry Unit 1 Weld Material SA-1526 (All Data, No Adjustments)
SA-1526/299L44                     0.340           0.680             542 .0               220.6                 Non-Credible             220.6           Conservative
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%)
* If surveillance   data are determined to be non-credible, the Position 1. 1 chemistry factor is applied to the beltline material.
(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.
.. 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.
e Credibility Assessment Conservatism Check for Pas. 1.1 CF when Surv. Data Non-Credible (3)
Credibility Assessment e
(1)             (2)                         Temperature Correction               (4)
Conservatism Check for Pas. 1.1 CF when Surv. Data Non-Credible (3)
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? **
(1)
Capsule TMl2-LG1 (BWOG CR-3 lrrad.)                 No             No             Credible                 -                          -                  216                 22                     Credible Capsule CR3-LG1 (BWOG CR-3 lrrad .)                 No             No             Credible                 -                          -                  202                   12                   Credible Capsule TMl2-LG1 (BWOG CR-3 lrrad.)                 No             No             Credible                 -                          -                  226                 23                     Credible Three Mile Island Unit 1 Capsule C             No             No           Non-Credible               -                          -                  166                 -30                   Credible Three Mile Island Unit 1 Capsule E             No             No             Credible                 -                          -                  74                 -14                   Credible Surry Unit 1 Capsule T                 No             No           Non-Credible               -                          -                  171                 37                     Credible Surry Unit 1 Capsule V                 No             No             Credible                 -                          -                  250                   8                     Credible Surry Unit 1 Capsule X                 No             No             Credible                 -                          -                  234                   3                     Credible (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)
(2) For the credibi li ty 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) .
Temperature Correction (4)
(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 wh ich is being evaluated (i.e. , were irradiated at a similar temperature) .
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.
(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 14 of 18 Summary (SA-1526, Alt. 3)
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)
ET-NAF-990006 Tables.xis Table 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)
Surry Unit 1 Weld Material SA-1526 (All Data Except Surry Unit 1 Data)
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 Surry Unit 1 Capsule X 0.230 0.230 0.640 0.640 538 .8 542.0 1.940 1.599 250 234 No No e
Data Used In Irradiation Assessing Temperature Measured Delta-Vessel? (Yes or Capsule ID (Including Source)
Table 3:                                   Surry Unit 1 Weld Material SA-1526 (All Data Except Surry Unit 1 Data)
Copper (wt%) Nickel (wt%)
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)
(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 Three Mile Island Unit 1 Capsule E 0.330 0.330 0.670 0.670 556.0 556.0 0.9597 0.4305 166 74 171 76
* Capsule TMl2-LG1 (BWOG CR-3 lrrad.)
                                                                                                                                                                      -29
0.370 0.700 556.0 0.9477 216 205 7
                                                                                                                                                                      -13
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.
* 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)
Page 15 of 18 Summary (SA-1526, Alt. 4)  


ET-NAF-990006 Tables.xis Table 4:                                        Surry Unit 1 Weld Material SA-1526 (All Data Except Surry Unit 1 Data)
Table 4:
CF Determination If Surv. Data Non-Chemistry       Credible, Verify Beltline     Beltline         Irradiation                               Surveillance Data       Factor Applied   Conservatism of Material     Material       Temperature     Position 1.1 Chemistry     Credible or Non-         to Beltline   Applied Position 1.1 Beltline Material ID            Copper (wt%)   Nickel (wt%)           (F)               Factor                 Credible?           Material*            CF**
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)
SA-1526/299L44                      0.340         0.680             542.0                 220.6               Non-Credible             220.6         Conservative
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 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.
** 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.
e Credibility Assessment Conservatism Check for Pos. 1.1 CF when Surv. Data Non-Credible (3)
Credibility Assessment e
(1)           (2)                         Temperature Correction             (4)
Conservatism Check for Pos. 1.1 CF when Surv. Data Non-Credible (3)
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? **
(1)
Capsule TMl2-LG1 (BWOG CR-3 lrrad.)                 Yes           Yes           Credible                 -                        -                    205                 -5                     Credible Capsule CR3-LG1 (BWOG CR-3 lrrad .)                 Yes           Yes           Credible                 -                        -                    195                 -12                     Credible Capsule TMl2-LG1 (BWOG CR-3 lrrad.)                 Yes           Yes           Credible                 -                        -                    233                 13                     Credible Three Mile Island Unit 1 Capsule C               Yes           Yes         Non-Credible               .                        -                    171                 -42                     Credible Three Mile Island Unit 1 Capsule E               Yes           Yes           Credible                 -                        -                    76                 -19                     Credible Surry Unit 1 Capsule T                   -            -                -                    -                        -                    -                    -                          -
(2)
Surry Unit 1 Capsule V                   -            -                -                    -                        -                    -                    -                          -
Temperature Correction (4)
Surry Unit 1 Capsule X                   -            -                -                    -                        -                    -                    -                          -
Temperature Chemistry Surveillance Applied to Credible Chemistry Correction Correction Correction Data Credible Surv. Data for Applied to Credible Surv.
(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).
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)
(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) .
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).
(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 16 of 18 Summary (SA-1526, Alt. 4)
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)
ET-NAF-990006 Tables.xis Table 2:
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)
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               1.1729                     140                   140               -7
* 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.
* 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)
Page 17 of 18 Summary (R3008)  


ET-NAF-990006 Tables.xis Table 4:                                    Surry Unit 2 Weld Material R3008 CF Determination If Surv. Data Non-Chemistry        Credible, Verify Beltline       Beltline       Irradiation                                 Surveil)ance Data      Factor Applied    Conservatism of Material       Material       Temperature     Position 1.1 Chemistry       Credible or Non-        to Beltline    Applied Position 1.1 Beltline Material ID            Copper (wt%)   Nickel (wt%)           (F)               Factor                   Credible?            Material*              CF**
Table 4:
R3008                        0.190         0.550             543.1                 149.3                   Credible               125.2                  -
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.
'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.
** 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.
e Credibility Assessment Conservatism Check for Pos. 1.1 CF when Surv. Data Non-Credible (3)
Credibility Assessment e
(1)             (2)                         Temperature Correction               (4)
Conservatism Check for Pos. 1.1 CF when Surv. Data Non-Credible (3)
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? **
(1)
Surry Unit 2 Capsule X                 No             No           Credible                 No                       No                   -                    -                          -
(2)
Surry Unit 2 Capsule V                 No             No           Credible                 No                       No                   -                    -                          -
Temperature Correction (4)
(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).
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).
(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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