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{{#Wiki_filter:* e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 Februarf 24, 1999 United States Nuclear Regulatory Commission Attention:
{{#Wiki_filter:*
Document Control Desk Washington, D. C. 20555-0001 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 e
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
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:
: 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.
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.
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.
During the preparation of a coordinated BWOG response to an NRC RAI regarding changes in reported transition temperature shift values, Framatome Technologies, Inc.
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.
(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:
A discussion of the changes to the previously reported surveillance results is provided in the attachment, and the resu~s-~ the-~vi:;
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
:':~l~t: are reported in Appendix A to fue atta;m;~ 2, t I 1 ( ~ia 30~Ba~~ ii&aa~ao\  
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' p PDR -*
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,. 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.
PDR   -*
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  
This information supplements the information previously reported in the June 18, 1998 letter. noted above.
& Services, for J.P. O'Hanlon, who is Senior Vice President  
Please contact us if you have any questions or require additional information.
-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)
Very truly yours,
. 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:
~rfL. 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
 
e COMMONWEALTH OF VIRGINIA               )
                                      )
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
- 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 .
My Commission Expires: March 31, 2000.
0
                                                  ~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),
* 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). Surveillance data for weld wire 72445 was available from both Westinghouse and B&W irradiations.
* 0227 (Rotterdam-fabricated Surry Unit 2 weld material R3008).
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.
Surveillance data for weld wire 72445 was available from both Westinghouse and B&W irradiations. In the case of weld wire 72445, the Westinghouse data was considered more applicable to the plant, since it required fewer corrections for irradiation temperature and chemical composition differences. The Westinghouse data was determined to be credible in accordance with RG 1.99, Revision 2 (5), as supplemented by Reference (7). After appropriate corrections for irradiation temperature and chemical composition differences, the Westinghouse data was used to evaluate the Surry Units 1 and 2 beltline materials fabricated with weld wire 72445 (i.e., SA-1585 and SA-1650).
The 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.
Other possible combinations of Westinghouse and: B&W surveillance data were evaluated for credibility, but each combination was determined to be non-credible.
In the case of weld wire 299L44, the Westinghouse data (which was Surry Unit 1 plant-specific surveillance data) was again considered more applicable to the plant, since it required fewer corrections for irradiation temperature and chemical composition differences.
However, the Westinghouse data was determined to be credible in accordance with RG 1.99, Revision 2 (5), as supplemented by Reference (7). Other possible combinations of Westinghouse and: B&W surveillance data were evaluated for credibility, but each combination was determined to be non-credible.
Since no credible data was identified, the Regulatory Guide 1.99, Revision 2, Position 1.1 chemistry factor was evaluated, and was determined to be conservative in accordance with guidance provided in Reference (7). Therefore, the Position 1.1 chemistry factor was used in the evaluation of the Surry Unit 1 beltline material fabricated from weld wire 299L44 (i.e., SA-1526).
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 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):
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.,
* 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 ).)
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 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. For weld wire 299L44 (weld material SA-1526):
* 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-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 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 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
* The 30 ft-lb transition temperature shift value for Capsule V (Surry Unit 2 irradiation) has been changed from 145°F to 140°F.
* 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.
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
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.
* 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
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
  . 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.
Page 2 of 7
The possible combinations of Westinghouse and B&W surveillance  
* 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 credible.
*. 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). 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 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
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).
(%-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.
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.
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 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.
*
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.
* 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),,
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
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.
* 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.
Location                                               Fluence (n/cm~)
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.
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
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  
Conclusions
-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
* 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).
* -(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 *
Page 5 of 7
* 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:
References
B& W and Rotterdam Dockyard Best-Best-Assigned Est i mate Estimate EOLID Materia l RPV Weld W i re H ea t Copper Nickel Fluence Chemistry or Mater i al ID (1) Location (wt%) (wt%) (x1E19) Factor 122V109VA1 Nozzle Shell Forging 0.11 0.74 0.307 76.1 C4326-1 Intermediate Shell 0.11 0.55 3.53 73.5 C4326-2 Intermediate Shell 0.11 0.55 3.53 73.5 4415-1 Lower Shell 0.11 0.50 3.53 85.0 4415-2 Lower Shell 0.11 0.50 3.53 73.0 J72 6/25017 Nozzle to Int Sh e ll Gire Weld 0.33 0.10 0.307 152.0 SA-1585/72445 Int. to Low Sh. Gire (ID 40%) 0.22 0.54 3.2 139.8 SA-1650/72445 Int. to Low Sh. Circ (OD 60%) 0.22 0.54 3.2 139.8 SA-1494/8T1554 Int Shell Long. Welds L3 & L4 0.16 0.57 0.6 143.9 SA-1494/8T1554 Lower Shell Long. Weld L 1 0.16 0.57 0.54 143.9 SA-1526/299L44 Lower Shell Long. Weld L2 0.34 0.68 0.54 220.6 (1) or the material i dent i fication number of the limiting material as requested in Section 1.0 (1.) (2) determined from tables or from surveillance data Method of Determ i ning CF (2) Tables Tables Tables Surv. Data Tables Tables Surv. Data Surv. Data Tables Tables Tables Summary (Surry) Inner Surf. Current ART o r Licens i ng Initial RT(PTS) at 1/4-T Bas i s 1/4-RT(NDT) Sigma(!) Sigma(delta)
* 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.
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
(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.
* 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:
(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.
Surry Unit 2 Vessel Manufacturer:
(4)   "Response to Request for Additional Information (RAI) Regarding Reactor Pressure Vessel Integrity," BAW-2325, dated May, 1998.
B&W and Rotterdam Dockyard Best-B est-Assigned Estima te Estimate EOLID Material RPV Weld Wire Heat C opper Nickel Fluence Chemistry or Material ID (1) Location (wt%) (wt%) (x1E19) Factor 123V303VA1 Nozzle Shell Forging 0.11 0.72 0.298 75.8 C 433 1-2 Intermediat e Shell 0.12 0.6 0 3.520 83.0 C 4 339-2 Intermed iate Shell 0.11 0.54 3.520 73.4 C4208-2 Lower Shell 0.15 0.55 3.520 107.3 C 4339-1 Lower Shell 0.11 0.54 3.520 68.4 L737/4275 No zz le t o Int Shell Gir e Weld 0.35 0.10 0.298 160.5 A3008/0227 Int. to Lower Shell Gire Weld 0.19 0.55 3.520 125.2 WF-4/8T1762 Int. Shell Long. L4 (ID 50%) 0.19 0.57 0.697 152.4 SA-1585/72445 Int. Sh. L3 (100%), L4 (OD 50) 0.22 0.54 0.697 139.8 WF-4/8T1762 LS L2 (ID 63%), L1 (100) 0.19 0.57 0.697 152.4 WF-8/8T1762 LS Long. Weld L2 (OD 37%) 0.19 0.57 0.697 152.4 (1) or the mater i al i dentification number of the limi ting material as requested in Section 1.0 (1.) (2) determined from tab l es or from surveillance data Method of D etermining CF(2) Tables Tables Tabl es Tables Surv. Data Tabl es Surv. Data Tabl es Surv. Data T ables Tab l es Summary (Surry) Initial RT(ND T) 30 2 0 1 0 0 0 5 5 Inner Surf. Current ART or Licensing RT(PTS) at 1/4-T B asis 1/4-S i gma(I) Sigma(delta)
(5)   Regulatory Guide 1.99 Revision 2, "Radiation Embrittlement of Reactor Vessel Materials," dated May, 1988.
Margin EOL ART TART* 0.0 17.0 34.0 114.7 105.5 100.4 e 0.0 17.0 34.0 134.2 12 4.2 123.9 0.0 17.0 34.0 111.5 102.6 10 2.4 0.0 17.0 34.0 146.4 133.5 133.1 0.0 8.5 17.0 97.8 89.6 89.3 20.0 28.0 68.8 176.1 156.6 169.6 20.0 14.0 48.8 215.0 200.0 202.9 19.7 28.0 68.5 200.4 179.6 181.0 19.7 14.0 48.3 168.9 149.9 158.5 19.7 28.0 68.5 200.4 179.6 181.0 19.7 28.0 68.5 200.4 179.6 181.0
(6)   Title 10, Code of Federal Regulations, Part 50.61, "Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events."
* 1/4-T ART value of 228.4 F was used i n the determination of Prr limits Page 2 of 18 ET-NAF-990006 Tables.xi s Table 2: Surry Unit 1 and 2 Weld Material SA-1585 (Point Beach 1 Data Only) Data Used In Irradiation Assessing Temperature Measured Delta-Vessel? (Yes or Capsule ID (Including Source) Copper (wt%) Nickel (wt%) (F) Fluence (x1E19) RT(NDT) (F) No) Point B eac h Uni t 1 Capsule T 0.230 0.615 533.4 2.230 181 Yes Point B eac h Unit 1 Capsule R 0.230 0.615 541.6 2.190 155 Yes Po i nt B e ach Unit 1 Capsule S 0.230 0.615 542.0 0.829 165 Yes Point B each Un it 1 Cap sule V 0.230 0.61 5 542.0 0.634 107 Y es Capsule CR3-LG2 (BWOG CR-3 lrrad.) 0.220 0.590 556.0 1.670 164 No Capsule CR3-LG1 (BWOG CR-3 lrrad.) 0.220 0.590 556.0 0.510 139 No -------------e ----------------------------Table 3: Surry Unit 1 and 2 Weld Material SA-1585 (Point Beach 1 Data Only) Irradiation Temperature Measured Delta-Adjusted Delta-Adjusted -Pred icted Capsule ID (Including Source) C o pper (wt%) Nickel (wt%) (F) F lu ence Factor RT(NDT) (F) RT(NDT) (F)
(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.
* D elt a-RT(NDT) (F)
(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.
* Point B eac h Unit 1 Ca ps ul e T 0.230 0.615 533.4 1.2173 181 181 7 Point B each U nit 1 Capsule R 0.230 0.615 541.6 1.2126 155 155 -18 Point B eac h Un it 1 Capsule S 0.230 0.615 542.0 0.9474 165 165 30 Point Bea c h Unit 1 Capsule V 0.230 0.615 542.0 0.8723 107 107 -------e I --------------------------------------------------------* For credib ilit y ch eck , measured shift values a re adj usted to average survei llance material c hemistry and irradiat io n tempe rature as required. See Table 4. Page 3 of 18 Summary (SA-1585)
(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.
-Corrected L
Page 6 of 7
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*
(10)
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.
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
If Surv. Data Non-Credible, Verify Conservatism of Applied Position 1.1 CF** Conservative
    *. Curves (TAC Nos. M92537 and M92538)," Serial No. 96-020, dated December
** Measured shift values are adjusted to the average surveillance material chemistry and irradiation temperature , and are verified to be within 2 sigma of the trend curve based on Posit i on 1. 1. Credibility Assessment e Conservatism Check for Pos. 1.1 CF when Surv. Data Non-Credible (3) (1) (2) Temperature Correction (4) Temperature Chemistry Surveillance Applied to Cred i ble Chemistry Correction Correction Correction Data Credible Surv. Data for Applied to C r edible Surv. Are adjusted surveillance Applied for Applied for or Non-Applicat ion to Beltline Data for Application to Adjusted Delta-Adjusted -Predicted data within 2 sigma of the Capsule ID (Inc lud ing Source) Credibility?
  *
Credibility?
* 28, 1995.
Credible?
(11)   WCAP-12794 Revision 3, "Reactor Cavity Neutron Measurement Program for Wisconsin Electric Power Company Point Beach Unit 1," dated December 1995.
Material?
(12)   Virginia Power Topical Report VEP-NAF-3, "Reactor Vessel Fluence Analysis Methodology," dated November, 1997.
Beltline Material?
(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.
RT(NDT) (F) ** Delta-RT(NDT) (F) ** applied CF trend curve? ** Point Beach Unit 1 Capsule T No No Credible --181 -2 8 Point Beach Unit 1 Capsule R No No Credible --155 -53 Point B eac h Unit 1 Capsule S No No Non-Credible
(14)   Draft Regulatory Guide DG-1053, "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence," dated June 1996.
--165 2 Point Beach Un it 1 Capsule V No No Credible --107 -43 Capsule CR3-LG2 (BWOG CR-3 lrrad.) -------Capsule CR3-LG1 (BWOG CR-3 lrrad.) -------------------------------------------------------(1) For the credi bility determination, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in a single reactor (i.e., were irradia ted at a s i milar temperature
(15)   BAW-2324, "Analysis of Capsule X, Virginia Power Surry Unit No. 1, Reactor Vessel Material Surveillance Program," dated April, 1998.
). (2) For the credibility determination , a chemistry c orrection is not applied to measured values of transition t em peratu re shift if applicable surveillance data were obtained from a single source (i.e., were machined from the same block of material).
Page 7 of 7
(3) For determination of the beltline material chemistry factor , a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irr adiated i n the reactor vessel which is being evaluated (i.e., were irradiated at a similar temperature).
 
(4) For determination of the beltline material chemistry factor, a chemistry correction (i.e., ratio procedure) is not applied to measured values of transition temperature shift if the chemical composition of applicable surveillance data is essentially identical to the best-es timate chemical composition of the beltline material being evaluated. Credible Credible Credible Credible --------Page 4 of 18 Summary (SA-1585)
e Appendix A Supplemental Reactor Vessel Material Data Tables
-Corrected ET-NAF-990006 Tables.xis Table 2: Surry Unit 1 and 2 Weld Material SA-1585 (All Available Data) Data Used In Irradiat i on Assessing Temperature Measured Delta-Vessel? (Yes or Capsule I D (Including Source) Copper (wt%) Nickel (wt%) (F) Fluence (x1E19) RT(NDT) (F) No) Point Beach Unit 1 Capsule T 0.230 0.615 533.4 2.230 181 Yes Point Beach U nit 1 Capsule R 0.230 0.615 541.6 S\ c, 2.190 c: .. it 155"' Yes Point Beach Unit 1 Capsule S 0.230 0.615 542.0 0.829 165 Yes Point Beach Unit 1 Capsule V 0.230 0.615 542 .. 0 ", 0.634 107 Yes C a psule CR3-LG2 (BWOG CR-3 lrrad.) 0.220 0.590 556.0 1.670 164 Yes Capsule CR3-LG1 (BWOG CR-3 lrrad.) 0.220 0.590 556.0 0.510 139 Yes ------------------------------------------Table 3: Surry Unit 1 and 2 Weld Material SA-1585 (All Available Data) Irradiat i on Temperature Meas u red Delta-Adjusted Delta-Adjusted -Predicted C aps ule ID (Includ ing S o u rce) Copper (wt%) Nicke l (wt%) (F) Fluence Factor RT(NDT) (F) RT(NDT) (F)
 
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 -
or Material ID (1) 122V109VA1 C4326-1 Location Nozzle Shell Forging Intermediate Shell (wt%)
0.11 0.11 (wt%)
0.74 0.55 (x1E19) 0.307 3.53 Factor 76.1 73.5 CF (2)
Tables Tables RT(NDT) 40 10 Sigma(!)
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
* 112.5 135.2 e
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
* 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
* 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 .)
* 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)
Page 1 of 18
 
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%)
0.11 0.12 (wt%)
0.72 0.60 (x1E19) 0.298 3.520 Factor 75.8 83.0 CF(2)
Tables Tables RT(NDT) 30
                                                                                                                            -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*
100.4 123.9 e
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 .)
* 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)
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
                    -
                    -
                                                  -
                                                  -
                                                  -
                                                                -
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                                                                                -
                                                                                -
                                                                                -
                                                                                                      -
                                                                                                      -
                                                                                                      -
                                                                                                                              -
                                                                                                                              -
                                                                                                                              -
                                                                                                                                                    -
                                                                                                                                                    -
                                                                                                                                                    -
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)
* P oi nt Bea c h Unit 1 Cap s ule T 0.230 0.615 533.4 1.2173 181 167 -10 Point Beach Unit 1 C a psul e R 0.230 0.615 541.6 1.2126 155 150 -27 Point Beach Unit 1 C a psule S 0.230 0.615 542.0 0.9474 165 160 22 Point Beach U n i t 1 Ca p sule V 0.230 0.615 542.0 0.8723 107 103 -24 Capsule CR3-LG2 (BWOG CR-3 l rra d.) 0.220 0.590 556.0 1.1413 164 179 13 Capsule CR3-LG1 (BWOG CR-3 lrrad.) 0.220 0.590 556.0 0.8120 139 153 35 -----------------------------------------------* For credibility check , m ea sured shift va lue s ar e adjusted to average surveillance material chemistry and irradiation temperature as required. See Table 4. Page 5 of 18 Summary (SA-1585 , Alt. 1) L __ ----
* Point Beach Unit 1 Capsule T             0.230           0.615           533.4               1.2173                     181                  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
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?
Point Beach Unit 1 Capsule V             0.230           0.615           542 .0             0.8723                     107                  107               -17
0.220 0.540 542.0 158.0 Credible
                    -                            -              -              -                    -                        -                    -                -
* If suNei/lance data are determined to be non-credible , the Position 1. 1 chemistry factor i s applied to the beltline material.
                    -                            -              -              -                    -                       -                     -                 -
If 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? ** Po i nt Beach Unit 1 Capsule T Yes Yes Credible Yes Yes --Point Beach Unit 1 Capsule R Yes Yes Credible Yes Yes --Point Beach Unit 1 Capsule S Yes Yes Credible Yes Yes --Point Beach Unit 1 Capsule V Yes Yes Credible Yes Yes --Capsule CR3-LG2 (BWOG CR-3 lrrad.) Yes Yes Credible Yes Yes --Capsule CR3-LG1 (BWOG CR-3 lrrad.) Yes Yes Non-Credible Yes Yes --------------------------------------------------(1) For the credibility determination, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in a single reactor (i.e., were irradiated at a similar temperature). (2) For the credibility determination , a chemistry correction is not applied to measured values of transition temperature shift if applicable surveillance data were obtained from a single source (i.e., were mach ined from the same block of material).
* 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
 
ET-NAF-990006 Tables.xis Table 4:                                      Surry Unit 1 and 2 Weld Material SA-1585 (Point Beach 1 Data Only)
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 **
SA-1585/72445                      0.220         0.540             542 .0               158.0               Non-Credible             158.0          Conservative
* If surveillance data are determined to be non-credible, the Position 1. 1 chemistry factor is applied to the beltline material.
** Measured shift values are adjusted to the average surveillance material chemistry and irradiation temperature, and are verified to be within 2 sigma of the trend curve based on Position 1. 1.
Credibility Assessment e
Conservatism Check for Pos. 1.1 CF when Surv. Data Non-Credible (3)
(1)           (2)                         Temperature Correction               (4)
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? **
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.)                 -              -                -                    -                        -                    -                    -                           -
Capsule CR3-LG1 (BWOG CR-3 lrrad .)                 -              -                -                    -                        -                    -                    -                          -
                        -                            -              -                -                   -                         -                   -                   -                           -
                        -                           -             -                 -                   -                         -                   -                   -                           -
                        -                           -             -                 -                   -                         -                   -                   -                           -
                        -                           -             -                 -                   -                         -                   -                   -                           -
                        -                           -             -                 -                   -                         -                   -                   -                           -
                        -                           -             -                 -                   -                         -                   -                   -                           -
(1) For the credi bility determination, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in a single reactor (i.e. , were irradiated at a similar temperature).
(2) For the credibility determination , a chemistry correction is not applied to measured values of transition temperature shift if applicable surveillance data were obtained from a single source (i.e. , were machined from the same block of material).
(3) For determination of the beltline material chemistry factor, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in the reactor vessel which is being evaluated (i.e., were irradiated at a similar temperature).
(3) For determination of the beltline material chemistry factor, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in the reactor vessel which is being evaluated (i.e., were irradiated at a similar temperature).
(4) For determination of the beltline material chemistry factor, a chemistry correction (i.e., ratio procedure) is not applied to measured values of transition temperature shift if the chemical composition of applicab l e surveillance data is essentially identical to the best-estimate chemical composition of the beltline material being evaluated. ------------Page 6 of 18 Summary (SA-1585, Alt. 1)
(4) For determination of the beltline material chemistry factor, a chemistry correction (i.e., ratio procedure) is not applied to measured values of transition temperature shift if the chemical composition of applicable surveillance data is essentially identical to the best-estimate chemical composition of the beltline material being evaluated .
ET -NAF-990 006 Tables.xis Table 2: Surry Unit 1 Weld Material SA-1526 (Surry Unit 1 Data Only) Data Used In Irradiation Assessing Temperature Measured Delta-Vessel? (Yes or Capsule ID (Including Source) Copper (wt%) Nickel (wt%) (F) Fluence (x1E19) RT(NDT) (F) No) Capsu l e TMl2-LG1 (BWOG CR-3 lrrad.) 0.370 0.700 556.0 0.830 216 No Capsule CR3-LG1 (BWOG CR-3 lrrad.) 0.360 0.700 556.0 0.779 202 No Capsule TMl2-LG1 (BWOG CR-3 lrrad.) 0.330 0.670 556.0 0.968 226 No Three Mile Island Unit 1 Capsule C 0.330 0.670 556.0 0.866 166 No Three Mile Island Unit 1 Capsule E 0.330 0.670 556.0 0.107 74 No Surry Unit 1 Capsule T 0.230 0.640 533.9 0.281 171 Yes Surry Unit 1 Capsule V 0.230 0.640 538.8 1.940 250 Yes Surry Unit 1 Capsule X 0.230 0.640 542.0 1.599 234 Yes . . . . . . . . . . . . . . . . . . . . . . . . . . . . Table 3: Surry Unit 1 Weld Material SA-1526 (Surry Unit 1 Data Only) Irradiat ion Temperature Measured Delta-Adjusted Delta-Adjusted -Predicted Capsule ID (Including Source) Copper (wt%) Nickel (wt%) (F) Fluence Factor RT(NDT) (F) RT(NDT) (F)
Page 4 of 18 Summary (SA-1585) - Corrected
* Delta-RT(NDT) (F) * . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . e Surry Unit 1 Capsule T 0.230 0.640 533.9 0.6535 171 171 29 Surry Unit 1 Capsule V 0.230 0.640 538.8 1.1811 250 250 -6 Surry Unit 1 Capsule X 0.230 0.640 542.0 1.1296 234 234 -11 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
 
* F or cr e dibility check, me a sur e d shift values are adjusted to average surveillance material chemistry and irradiation temperature as required. See Table 4. Page 7 of 18 Summary (SA-1526)
ET-NAF-990006 Tables.xis Table 2:                                   Surry Unit 1 and 2 Weld Material SA-1585 (All Available Data)
Table 4: Beltline Mater ial ID SA-1526/299L44 ET-NAF-990006 Tables.xis Surry Unit 1 Weld Material SA-1526 (Surry Unit 1 Data Only) CF Determination Beltline Beltline Irradiation Surveillance Data Material Material Temperature Position 1.1 Chemistry Credible or Non-Copper (wt%) Nickel (wt%) (F) Factor Credible?
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)
0.340 0.680 542.0 220.6 Non-Credible
Point Beach Unit 1 Capsule T             0.230         0.615          533.4                2.230                      181                  Yes S\ c,          c:        .. it 155 "'
* 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
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
** Measured shift values are adjusted to the average surveillance material chemistry and irradiation temperature , and are verified to be within 2 sigma of the trend curve based on Position 1. 1. Credibility Assessment e Conservatism Check for Pos. 1.1 CF when Surv. Data Non-Credible (3) (1) (2) Temperature Correction (4) Temperature Chemistry Surveil l ance Applied to Credible Chemistry Correction Correction Correction Data Cred i ble Surv. Data for Applied to Credible Surv. Are adjusted surveillance Applied for Applied for or Non-Application to Beltline Data for Application to Adjusted Delta-Adjusted -Predicted data within 2 sigma of the Capsule ID (Including Source) Cred i bility? Credibility?
                        -                           -               -               -                   -                       -                     -
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 Capsu le X No No Credible --234 35 --------------------------------(1) For the credibility dete rmina tion, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irra diated in a single reactor (i.e., were irradiated at a similar temperature). (2) Fo r the credibility determination , a chemistry correct ion is not applied to measured values of transition temperature shift if applicable surveillance data were obtained from a single source (i.e., were machined from the same block of material). (3) For determination of the be l tline material chem i stry factor, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irr adiated in the reactor vessel which is being evaluated (i.e., were irradiated at a similar temperature). (4) For determination of the beltline material chemistry factor, a chemistry correction (i.e., ratio procedure) is not applied to measured values of transition temperature shift if the chem ic al composition of applicable surveillance data is essentially identical to the best-estimate chemical composition of the beltline material being evaluated. ----Cred i ble Credible Credible ----Page 8 of 18 Summary (SA-1526)
                        -                           -             -               -                   -                       -                     -
ET-NAF-990006 Tables.xis Table 2: Surry Unit 1 Weld Material SA-1526 (All Available Data) Data Used In Irradiation Assessing Temperature Measured Delta-Vessel? (Yes o r Capsule ID (Including Source) Copper (wt%) Nickel (wt%) (F) Fluence (x1E19) RT(NDT) (F) No) Capsule TMl2-LG1 (BWOG CR-3 lrrad.) 0.370 0.700 556.0 0.830 216 Yes Capsule CR3-LG1 (BWOG CR-3 lrrad.) 0.360 0.700 556.0 0.779 202 Yes Capsule TM12-LG1 (BWOG CR-3 lrrad.) 0.330 0.670 556.0 0.968 226 Yes Three Mile Island Unit 1 Capsule C 0.330 0.670 556.0 0.866 166 Yes Three Mile I sland Unit 1 Capsule E 0.330 0.670 556.0 0.107 74 Yes Surry Unit 1 Capsule T 0.230 0.640 533.9 0.281 171 Yes Surry Unit 1 Capsule V 0.230 0.640 538.8 1.940 250 Yes Surry Unit 1 Capsule X 0.230 0.640 542.0 1.599 234 Yes -----------------. . . . ---. . . . -Table 3: Surry Unit 1 Weld Material SA-1526 (All Available Data) Irrad iation Temperature Measu r ed Delta-Adjusted Delt a-Adjusted
Table 3:                                   Surry Unit 1 and 2 Weld Material SA-1585 (All Available Data)
* Predicted Capsule ID (Including Source) Copper (wt%) Nickel (wt%) (F) Fluence Factor RT(NDT) (F) RT(NDT) (F)
Irradiation Temperature                                   Measured Delta-     Adjusted Delta- Adjusted - Predicted Capsule ID (Including Source)         Copper (wt%) Nickel (wt% )         (F)           Fluence Factor             RT(NDT) (F)         RT(NDT) (F)
* Delta-RT(NDT) (F)
* Delta-RT(NDT) (F)
* Capsule TMl2-LG1 (BWOG CR-3 lrrad.) 0.370 0.700 556.0 0.9477 216 195 *12 Capsule CR3-LG1 (BWOG CR-3 lrrad.) 0.360 0.700 556.0 0.9299 202 185 -17 Capsule TMl2-LG1 (BWOG CR-3 lrrad.) 0.330 0.670 556.0 0.9909 226 221 6 Three Mile I s land Unit 1 Capsule C 0.330 0.670 556.0 0.9597 166 164 .45 Three Mile Island Unit 1 Capsule E 0.330 0.670 556.0 0.4305 74 77 -17 Surry Unit 1 C aps ule T 0.230 0.640 533.9 0.6 535 171 181 39 Surry Unit 1 Capsule V 0.230 0.640 538.8 1.1811 250 279 22 Surry Unit 1 Capsule X 0.230 0.640 542.0 1.1296 234 264 18 . -. -. . . . -. . -. . . . . . . -. -. -. . . -. . --* For credibility check, measured shift values are adjusted to average surveillance material chemistry and irradiation temperature as required. See Table 4. Page 9 of 18 Summary (SA-1526, Alt. 1)
* 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
Table 4: Beltline Material ID SA-1526/299L44 ET-N A F-9 9000 6 Tables.x i s Surry U n i t 1 Weld Materia l SA-1526 (All Available Data) CF Determination Beltline Beltline Irradiation Surveillance Data Material Material Temperature Position 1.1 Chemistry Credib l e or Non-Copper (wt%) N i ckel (wt%) (F) Factor Cred i b l e? 0.340 0.680 542.0 220.6 Non-Credible
                        -                            -              -              -                    -                        -                    -                -
* If surveillance data are determined to be non-credible, the Position 1. 1 chemistry factor is applied to the beltline material. If Surv. Data Non-Chemistry Credib l e, Verify Factor App l ied Conservatism of to Beltline App l ied Position 1.1 Material* CF** 220.6 Conservative
                        -                            -              -              -                    -                        -                    -                -
** Measured shift values are adjusted to the average surveillance material chemistry and irradiation temperature , and are verified to be within 2 sigma of the trend c u rve based on Position 1. 1. Credibility Assessment  
                        -                            -              -              -                    -                        -                    -                -
-Conservatism Check for Pos. 1.1 CF when Surv. Data Non-Credible (3) (1) (2) Temperature Correction (4) Temperature Chemistry Survei ll ance Applied to Cred i b l e Chem i stry Correction Correction Correction Data Credible Surv. Data for Appl i ed to Credib l e Surv. Are adjusted surveillance Applied for Applied for or Non-Application to Be l tline Data for A p p l i cation to Adjusted De l ta-Adjusted -P r edicted data within 2 sigma of the Capsule ID (Includ i ng Source) Credibility?
                        -                            -              -              -                    -                        -                    -                -
Credibility?
                        -                            -              -              -                    -                         -                   -                 -
Credible?
                                                    -              -               -                   -                         -                   -                 -
Mater i a l? Be l tline M aterial? RT(NDT) (F) ** Delta-RT(NDT) (F) ** applied CF trend curve? ** Capsule TMl2-LG1 (BWOG CR-3 l rrad.) Yes Yes Credible --195 1 Capsule CR3-LG1 (BWOG CR-3 lrrad.) Yes Yes Credib l e --185 -5 Capsule TMl2-L G1 (BWOG CR-3 l rrad.) Yes Yes Credible --221 19 Three Mile Is l and Unit 1 Capsule C Yes Yes Non-Cred i ble --164 -32 Three Mile Is l and Unit 1 Capsule E Yes Yes Credible --77 -11 Surry Unit 1 Capsule T Yes Yes Non-Credible
* For credibility check, measured shift values are adjusted to average surveillance material chemistry and irradiation temperature as required. See Table 4.
--181 47 Surry Unit 1 Capsule V Yes Yes Credible --279 37 Surry Unit 1 Capsule X Yes Yes Credible --264 33 --------------------------------(1) For the credibility determination , a temperature correction is not applied to measured values of trans i tion temperature shift i f applicable surveillance data were irrad i ated in a single reactor (i.e., were irradiated at a similar temperature). (2) For the credib i l i ty determination , a chemistry correction is not applied to measured values of transition temperature shift if app l icable surveillance data were obtained from a single source (i.e., were machined from the same block of material). (3) For determination of the beltline material chemistry factor, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in the reactor vessel which i s being evaluated (i.e., were irradiated at a s i milar temperature). (4) For determination of the beltline material chemistry factor, a chemistry correction (i.e., ratio procedure) is not applied to meas u red values of transition temperature shift if the chemical composition of applicable surveillance data is essentially identical to the best-estimate chemical composition of the beltline material being evaluated. Cred i ble Credible Cred i b l e Credible Credible Credible Credible Credible ---Page 10 of 18 Summary (SA-1526, Alt. 1)
Page 5 of 18 Summary (SA-1585, 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) Capsu le TMl2-LG1 (BWOG CR-3 l r rad.) 0.370 0.700 556.0 0.830 216 No Capsule CR3-LG1 (BWOG CR-3 lrrad.) 0.360 0.700 556.0 0.779 202 Yes Capsule TMl2-LG1 (BWOG CR-3 lrrad.) 0.330 0.670 556.0 0.968 226 No Three Mile Island Unit 1 Capsule C 0.330 0.670 556.0 0.866 166 Yes Three Mile Island Unit 1 Capsule E 0.330 0.670 556.0 0.107 74 Yes Surry Unit 1 Capsule T 0.230 0.640 533.9 0.281 171 Yes Surry Unit 1 Capsule V 0.230 0.640 538.8 1.940 250 Yes Surry Unit 1 Capsule X 0.230 0.640 542.0 1.599 234 Yes -. . . . . . . . . . . . . . . . -. -. . . . . -. Table 3: Surry Unit 1 Weld Material SA-1526 (All Data Except TMl-2) Irradiation Temperature Measured Delta-Adjusted Delta-Adjusted -Predicted Capsule ID (Includ i ng Source) Copper (wt%) Nickel (wt%) (F) Fluence Factor RT(NDT) (F) RT(NDT) (F)
L__ ----
* Delta-RT(NDT) (F) * . . . . . . . . Capsule CR3-LG1 (BWOG CR-3 lrrad.) 0.360 0.700 556.0 0.9299 202 181 -18 . . . . . . . . Three Mile Island Unit 1 Capsule C 0.330 0.670 556.0 0.9597 166 161 -44 Three Mile Island Unit 1 Capsule E 0.330 0.670 556.0 0.4305 74 76 Surry Unit 1 Capsule T 0.230 0.640 533.9 0.6535 1 71 178 38 Surry Unit 1 Capsule V 0.230 0.640 538.8 1.1811 250 273 20 Surry Unit 1 Capsule X 0.230 0.640 542.0 1.1296 234 258 16 . . . . . -. . . . . . . -. -. -. . . ---. . . . . . --* For credibility check , measured shift values are adjusted to average surveillance material chemistry and irradiation temperature as required. See Table 4. Page 11 of 18 Summary (SA-1526, Alt. 2)
 
Table 4: Be l tline Material ID SA-1526/299L44 ET-N A F-99 0 006 Tables.xis Surry Unit 1 Weld Material SA-1526 (All Data Except TMl-2) CF Determination Beltline Beltline I rradiation S u rve ill ance Data Material Material Temperature Position 1.1 Chem i stry Credible or Non-Copper (wt%) Nicke l (wt%) (F) Factor Credib l e? 0.340 0.680 542.0 220.6 Non-Credible
ET-NAF-990006 Tables.xis Table 4:                                      Surry Unit 1 and 2 Weld Material SA-1585 (All Available Data)
* If swveillance data are determined to be non-credible, the Position 1.1 chemistry factor is applied to the beltline mate r ial . If Surv. Data Non-Chemistry Credib l e, Verify Factor Applied Conservatism of to Beltline Applied Pos i tion 1.1 Material*
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**
CF** 220.6 Conservative
SA-1585n2445                      0.220          0.540              542.0                 158.0                  Credible              139.8                  -
.. Measured shift values are adjusted to the average surveillance material chemistry and irradiation t emperature, and are verified to be within 2 sigma of the trend curve based on Position 1. 1. Credibility Assessment  
* If suNei/lance data are determined to be non-credible, the Position 1. 1 chemistry factor is applied to the beltline material.
-Conservatism Check for Pos. 1.1 CF when Surv. Data Non-Credible (3) (1) (2) Temperat u re Correction (4) Temperature Chemistry Surveillance Applied to Credible Chemistry Correction Correction Correction Data Credible Surv. D ata for Appl i ed to Cred i b l e Surv. Are adj u sted surveillance Applied for Applied for or Non-Applicatio n to Beltline Data for Ap p lication to Adjusted Delta-Adjusted -Predicted data within 2 sigma of the Capsu l e ID (Including Source) Credibility?
** 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?
e Credibility Assessment Conservatism Check for Pos. 1.1 CF when Surv. Data Non-Credible (3)
Cre d ible? Mater i a l? Be l tl i ne Material?
(1)           (2)                         Temperature Correction             (4)
RT(NDT) (F) ** Delta-RT(N D T) (F) ** applied CF trend curve? ** Capsu l e TM l 2-LG1 (BWOG CR-3 l rrad.) -------Capsule CR3-LG1 (BWOG CR-3 lrrad.) Yes Yes Credib l e --181 -3 Capsule TMl2-LG1 (BWOG CR-3 lrrad.} -------Three Mile Island Unit 1 Capsule C Yes Yes Non-Credible
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? **
--161 -29 Three Mile Is l and Unit 1 Capsule E Yes Yes Credible --76 -9 Surry Unit 1 Capsule T Yes Yes Non-Credible . -178 48 Surry Unit 1 Capsule V Yes Yes Credible -. 273 38 Surry Unit 1 Capsule X Yes Yes Cred i ble . -258 34 --------------------------------(1) For the cred i bi l ity determination, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in a single reactor (i.e., were i rrad i ated at a similar temperature).
Point Beach Unit 1 Capsule T              Yes           Yes             Credible                 Yes                      Yes                  -                   -                           -
(2) For the credibility determination, a chemistry correction is not applied to measured values of trans i tion temperature shift if app l icable surveillance data were obtained from a single source (i.e., were machined from the same b l ock of materia l). (3) For determination of the beltline mater i al chemistry factor, a temperature correction is not applied to measured values of transition temperat u re shift if applicable surve i llance data were i rradiated in the reactor vessel which is being evaluated (i.e., were irradiated at a similar temperature).
Point Beach Unit 1 Capsule R              Yes            Yes            Credible                Yes                     Yes                   -                   -                           -
(4) For determination of the beltline material chemistry factor, a chemistry correction (i.e., ratio procedure) is not applied to measured values of transition temperature shift if the chemical composition of applicable surve i llance data is essent i ally ident i cal to the best-estimate chemical composition of the be l tl i ne material being eva lu ated. -Credible -Credible Credible Credible Credible Credib l e ----Page 12 of 18 Summary (S A-1526, Alt. 2) -
Point Beach Unit 1 Capsule S              Yes           Yes             Credible                 Yes                      Yes                  -                   -                           -
ET-NAF-990006 Tables.xis Table 2: Surry Unit 1 Weld Material SA-1526 (All Data, No Adjustments)
Point Beach Unit 1 Capsule V              Yes            Yes            Credible                Yes                     Yes                   -                   -                           -
Data Used In Irradiation Assessing Temperature Measured Delta-Vessel? (Yes or Capsule ID (Including Source) Copper (wt%) Nickel (wt%) (F) Fluence (x1E19) RT(NDT) (F) No) Capsule TM12-LG1 (BWOG CR-3 lrrad.) 0.370 0.700 556.0 0.830 216 Yes Capsule CR3-LG1 (BWOG CR-3 lrrad.) 0.360 0.700 556.0 0.779 202 Yes Capsule TMl2-LG1 (BWOG CR-3 lrrad.) 0.330 0.670 556.0 0.968 226 Yes Three Mile Islan d Unit 1 Capsule C 0.330 0.670 556.0 0.866 166 Yes Three Mile Island Unit 1 Capsule E 0.330 0.670 556.0 0.107 74 Yes Surry Unit 1 Capsule T 0.230 0.640 533.9 0.281 171 Yes Surry Unit 1 Capsule V 0.230 0.640 538.8 1.940 250 Yes Surry Unit 1 Capsu l e X 0.230 0.640 542.0 1.599 234 Yes ----------------------------Table 3: Surry Unit 1 Weld Material SA-1526 (All Data, No Adjustments)
Capsule CR3-LG2 (BWOG CR-3 lrrad .)              Yes           Yes             Credible                 Yes                      Yes                  -                   -                           -
Irradiation Temperature Measured Delta-Adjusted Delta-Adjusted -Predicted Capsule ID (Including Source) Copper (wt%) Nickel (wt%) (F) Fluence Factor RT(NDT) (F) RT(NDT) (F)
Capsule CR3-LG1 (BWOG CR-3 lrrad .)              Yes            Yes          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)
 
ET-NAF-990006 Tables.xis Table 4:                                       Surry Unit 1 Weld Material SA-1526 (Surry Unit 1 Data Only)
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*
* SA-1526/299L44                      0.340         0 .680           542.0                 220.6                 Non-Credible             220.6          Conservative
* If surveillance data are determined to be non-credible, the Position 1. 1 chemistry factor is applied to the belt/ine material.
** Measured shift values are adjusted to the average surveillance material chemistry and irradiation temperature, and are verified to be within 2 sigma of the trend curve based on Position 1. 1.
Credibility Assessment e
Conservatism Check for Pos. 1.1 CF when Surv. Data Non-Credible (3)
(1)           (2)                         Temperature Correction               (4)
Temperature   Chemistry       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                      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) .
(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 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)
 
ET-NAF-990006 Tables.xis Table 4:                                      Surry Unit 1 Weld Material SA-1526 (All Available Data)
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**
SA-1526/299L44                      0.340        0.680            542.0                220.6                  Non-Credible              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.
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      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? **
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) .
(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 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 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
                                                                                                                                                    .
                                                                                                                                                                      -44
                                                                                                                                                                      -16 38 20 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)
 
ET-NAF-990006 Tables.xis Table 4:                                        Surry Unit 1 Weld Material SA-1526 (All Data Except TMl-2)
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 **
SA-1526/299L44                      0.340        0.680              542 .0                220.6                Non-Credible              220.6        Conservative
                                                                                                                                                                                                                      -
* If swveillance data are determined to be non-credible, the Position 1. 1 chemistry factor is applied to the beltline material .
.. Measured shift values are adjusted to the average surveillance material chemistry and irradiation temperature, and are verified to be within 2 sigma of the trend curve based on Position 1. 1.
Credibility Assessment 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    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? **
Capsule TM l2-LG1 (BWOG CR-3 lrrad.)                  -            -                  -                    -                        -                      -                  -                          -
Capsule CR3-LG1 (BWOG CR-3 lrrad.)                  Yes          Yes            Credible                  -                        -                    181                -3                      Credible Capsule TMl2-LG1 (BWOG CR-3 lrrad.}                    -            -                  -                    -                        -                      -                  -                          -
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).
(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).
(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 beltl ine material being evaluated.
Page 12 of 18 Summary (SA-1526, Alt. 2)
 
ET-NAF-990006 Tables.xis Table 2:                                    Surry Unit 1 Weld Material SA-1526 (All Data, No Adjustments)
Data Used In Irradiation                                                        Assessing Temperature                                  Measured Delta-      Vessel? (Yes or Capsule ID (Including Source)        Copper (wt% ) Nickel (wt%)          (F)          Fluence (x1E19)            RT(NDT) (F)              No)
Capsule TM12-LG1 (BWOG CR-3 lrrad .)            0.370          0.700          556.0                0.830                    216                  Yes Capsule CR3-LG1 (BWOG CR-3 lrrad .)            0.360          0.700          556.0                0.779                    202                  Yes Capsule TMl2-LG1 (BWOG CR -3 lrrad.)            0.330          0.670          556.0                0.968                    226                  Yes Three Mile Island Unit 1 Capsule C          0.330          0.670          556.0                0.866                    166                  Yes Three Mile Island Unit 1 Capsule E          0.330          0.670          556 .0              0.107                      74                  Yes Surry Unit 1 Capsule T                0.230          0.640          533.9                0.281                    171                  Yes Surry Unit 1 Capsule V                0.230          0.640          538 .8              1.940                    250                  Yes Surry Unit 1 Capsule X                0.230          0.640          542 .0              1.599                    234                  Yes
                      -                            -              -              -                    -                        -                    -
                      -                            -              -              -                    -                        -                    -
                      -                            -              -              -                    -                        -                    -
                      -                            -              -              -                    -                        -                    -
Table 3:                                   Surry Unit 1 Weld Material SA-1526 (All Data, No Adjustments)
Irradiation Temperature                                   Measured Delta-       Adjusted Delta- Adjusted - Predicted Capsule ID (Including Source)         Copper (wt% ) Nickel (wt%)           (F)           Fluence Factor             RT(NDT) (F)         RT(NDT) (F)
* Delta-RT(NDT) (F)
* Delta-RT(NDT) (F)
* Capsule TMl2-LG1 (BWOG CR-3 lrrad.) 0.370 0.700 556.0 0.9477 216 216 14 Capsule CR3-LG1 (BWOG CR-3 lrrad.) 0.360 0.700 556.0 0.9299 202 202 4 Capsule TMl2-LG1 (BWOG CR-3 lrrad.) 0.330 0.670 556.0 0.9909 226 226 15 Three Mile Island Unit 1 Capsule C 0.330 0.670 556.0 0.9597 166 166 -38 Three Mile Island Unit 1 Capsule E 0.330 0.670 556.0 0.4305 74 74 -18 e Surry Unit 1 Capsule T 0.230 0.640 533.9 0.6535 171 171 32 Surry Unit 1 Capsule V 0.230 0.640 538.8 1.1811 250 250 -1 Surry Unit 1 Capsule X 0.230 0.640 542.0 1.1296 234 234 -------------------------------* For credibility check , measured shift values are adjusted to average surveillance material chemistry and irradiation temperature as required.
* Capsule TMl2-LG1 (BWOG CR-3 lrrad .)           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
See Table 4. Page 13 of 18 Summary (SA-1526, Alt. 3)
                                                                                                                                                                      -38
Table 4: ET-NAF-990006 Tables.xis Surry Unit 1 Weld Material SA-1526 (All Data, No Adjustments)
                                                                                                                                                                      -18 32 e
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?
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
Material*
                      -                            -             -               -                   -                         -                   -                 -
SA-1526/299L44 0.340 0.680 542.0 220.6 Non-Credible 220.6
                      -                           -             -               -                   -                         -                   -                 -
* If surveillance data are determined to be non-credib le , the Position 1. 1 chemistry factor is applied to the beltline material. If Surv. Data Non-Credible, Verify Conservatism of Applied Position 1.1 CF** Conservative
                      -                           -             -               -                   -                         -                   -                 -
.. Measured shift values are adjusted to the average surveillance material chemistry and irradiation temperature , and are verified to be within 2 sigma of the trend curve based on Position 1. 1. Credibility Assessment e Conservatism Check for Pas. 1.1 CF when Surv. Data Non-Credible (3) (1) (2) Temperature Correction (4) Temperature Chemistry Surveillance Applied to Credible Chemistry Correction Correction Correction Data Credible Surv. Data for Applied to Credible Surv. Are adjusted surveillance Applied for Applied for or Non-Application to Beltline Data for Application to Adjusted Delta-Adjusted -Predicted data within 2 sigma of the Capsule ID (Includ i ng Source) Credibility?
                      -                           -             -               -                   -                         -                   -                 -
Credibility?
* For credibility check, measured shift values are adjusted to average surveillance material chemistry and irradiation temperature as required. See Table 4.
Credible?
Page 13 of 18 Summary (SA-1526, Alt. 3)
Material?
 
Beltline Material?
ET-NAF-990006 Tables.xis Table 4:                                      Surry Unit 1 Weld Material SA-1526 (All Data, No Adjustments)
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  
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**
--166 -30 Three Mile Island Unit 1 Capsule E No No Credible --74 -14 Surry Unit 1 Capsule T No No Non-Credible  
SA-1526/299L44                     0.340           0.680             542 .0               220.6                 Non-Credible             220.6           Conservative
--171 37 Surry Unit 1 Capsule V No No Credible --250 8 Surry Unit 1 Capsule X No No Credible --234 3 --------------------------------(1) F o r the credibility determination, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in a single reactor (i.e., were irradiated at a similar temperature).
* If surveillance   data are determined to be non-credible, the Position 1. 1 chemistry factor is applied to the beltline material.
(2) For the credibi li ty determination , a chemistry correction is not applied to measured values of transition temp erature shift if applicable surveillance data were obtained from a single source (i.e., were machined from the same block of material). (3) For determ i nation of the beltline material chemistry factor, a temperature correction is not appl i ed to measured values of transition temperature shift if applicable surveillance data were irradiated in the reactor vessel wh i ch is being evaluated (i.e., were irradiated at a similar temperature). (4) For determination of the beltline material chemistry factor, a chemistry correction (i.e., ratio procedure) is not applied to measured values of transition temperature shift if the chemical composition of applicable surveillance data is essentially identical to the best-estimate chemical composition of the beltline material being evaluated.
.. 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.
Credible Credible Credible Credible Credible Credible Cr edible Credible ----Page 14 of 18 Summary (SA-1526 , A l t. 3)
e Credibility Assessment Conservatism Check for Pas. 1.1 CF when Surv. Data Non-Credible (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 Un i t 1 Capsule X 0.230 0.640 542.0 1.599 234 No e ----------------------------Table 3: Surry Unit 1 Weld Material SA-1526 (All Data Except Surry Unit 1 Data) Irradiation Temperature Measured Delta-Adjusted Delta-Adjusted -Predicted Capsule ID (Includ i ng Source) Copper (wt%) Nickel (wt%) (F) Fluence Factor RT(NDT) (F) AT(NDT) (F)
(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                     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) 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) .
(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) .
(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)
 
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 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
                      -                           -               -             -                   -                         -                   -
                      -                           -               -             -                   -                         -                   -
                      -                           -             -               -                   -                         -                   -
Table 3:                                   Surry Unit 1 Weld Material SA-1526 (All Data Except Surry Unit 1 Data)
Irradiation Temperature                                   Measured Delta-       Adjusted Delta- Adjusted - Predicted Capsule ID (Including Source)         Copper (wt%) Nickel (wt%)           (F)           Fluence Factor             RT(NDT) (F)         AT(NDT) (F)
* Delta-AT(NDT) (F)
* Delta-AT(NDT) (F)
* Capsule TMl2-LG1 (BWOG CR-3 lrrad.) 0.370 0.700 556.0 0.9477 216 205 7 Capsule CA3-LG1 (BWOG CR-3 lrrad.) 0.360 0.700 556.0 0.9299 202 195 1 Capsule TM12-LG1 (BWOG CA-3 lrrad.) 0.330 0.670 556.0 0.9909 226 233 26 Three Mile Island Unit 1 Capsule C 0.330 0.670 556.0 0.9597 166 171 -29 Three Mile Island Un i t 1 Capsule E 0.330 0.670 556.0 0.4305 74 76 --------------------------------------------------------* F or credibility check , measured shift values are adjusted to average surveillance material chemistry and irradiation temperature as required. See Table 4. Page 15 of 18 Summary (SA-1526, Alt. 4)
* Capsule TMl2-LG1 (BWOG CR-3 lrrad.)             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
Table 4: Beltline Material ID SA-1526/299L44 ET-NAF-990006 Tables.x i s Surry Unit 1 Weld Material SA-1526 (All Data Except Surry Unit 1 Data) CF Determination Chemistry Beltline Beltline Irradiation Surveillance Data Factor Applied Material Material Temperature Position 1.1 Chemistry Credible or Non-to Beltl i ne Copper (wt%) Nickel (wt%) (F) Factor Credible?
                      -
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 v alues are adjusted to the average surveillance material chemistry and irradiation temperature, and are verified to be within 2 sigma of the trend curve based on Position 1. 1. Credibility Assessment e Conservatism Check for Pos. 1.1 CF when Surv. Data Non-Credible (3) (1) (2) Temperat u re Correction (4) Temperature Chemistry Surveillance Applied to Credible Chemistry Correction Correction Correction Data Credible Surv. Data for Applied to Credible Surv. Are adjusted surveillance Applied for Applied for or Non-Application to Beltline Data for Application to Adjusted Delta-Adjusted -Predicted data within 2 sigma of the Capsule ID (Includ i ng Source) Credibility?
0.330 0.330
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).
0.670 0.670
(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 appl i cable surveillance data is essentially identical to the best-estimate chemical composition of the beltline material being evaluated.
                                                                  -
Credible Credible Credible Credible Credib l e -------Page 16 of 18 Summary (SA-1526, Alt. 4)
                                                                  -
ET-NAF-990006 Tables.xis Table 2: Surry Unit 2 Weld Material R3008 Data Used I n Irradiation Assessing Temperature Measured Delta-Ve ssel? (Yes or Capsule ID (Including Source) Copper (wt%) Nickel (wt%) (F) Fluence (x1 E 19) RT(NDT) (F) No) Surry Unit 2 Capsule X 0.190 0.550 534.9 0.302 # 96 ,, Yes Surry Unit 2 Capsule V 0.190 0.550 540.1 1.880 140 Yes ----------------------------------------------------------------------Table 3: Surry Unit 2 Weld Material R3008 Irradiation Temperature Measu red Delta-Adjusted Delta-Adjusted -Predicted Capsule ID (Including Sou r ce) Copper (wt%) Nickel (wt%) (F) Fluence Factor RT(NDT) (F) RT(NDT) (F)
                                                                  -
556.0 556.0
                                                                                  -
                                                                                  -
                                                                                  -
                                                                                  -
0.9597 0.4305
                                                                                                      -
                                                                                                      -
                                                                                                      -
                                                                                                      -
166 74
                                                                                                                                -
                                                                                                                                -
                                                                                                                                -
                                                                                                                                -
171 76
                                                                                                                                                      -
                                                                                                                                                      -
                                                                                                                                                      -
                                                                                                                                                      -
                                                                                                                                                                      -29
                                                                                                                                                                      -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)
 
ET-NAF-990006 Tables.xis Table 4:                                        Surry Unit 1 Weld Material SA-1526 (All Data Except Surry Unit 1 Data)
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**
SA-1526/299L44                      0.340         0.680             542.0                 220.6               Non-Credible             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.
e 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                 -                       -                   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                   -            -                 -                   -                       -                     -                   -                         -
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.
Page 16 of 18 Summary (SA-1526, Alt. 4)
 
ET-NAF-990006 Tables.xis Table 2:                                   Surry Unit 2 Weld Material R3008 Data Used In Irradiation                                                         Assessing Temperature                                   Measured Delta-     Vessel? (Yes or Capsule ID (Including Source)         Copper (wt%) Nickel (wt%)           (F)           Fluence (x1 E 19)           RT(NDT) (F)               No)
Surry Unit 2 Capsule X                 0.190           0.550           534.9               0.302               #     96     ,,           Yes Surry Unit 2 Capsule V                 0.190           0.550           540.1               1.880                     140                 Yes
                      -                           -             -               -                   -                         -                   -
                      -                           -             -               -                   -                         -                   -
                      -                           -             -               -                   -                         -                   -
                      -                           -             -               -                   -                         -                   -
                      -                           -             -               -                   -                         -                   -
                      -                           -             -               -                   -                         -                   -
                      -                           -             -               -                   -                         -                   -
                      -                           -             -               -                   -                         -                   -
                      -                           -             -               -                   -                         -                   -
                      -                           -             -               -                   -                         -                   -
Table 3:                                   Surry Unit 2 Weld Material R3008 Irradiation Temperature                                   Measured Delta-       Adjusted Delta- Adjusted - Predicted Capsule ID (Including Source)         Copper (wt%) Nickel (wt% )           (F)           Fluence Factor             RT(NDT) (F)         RT(NDT) (F)
* Delta-RT(NDT) (F)
* Delta-RT(NDT) (F)
* Surry Unit 2 Capsule X 0.190 0.550 534.9 0.6720 96 96 12 Surry Unit 2 Capsule V 0.190 0.550 540.1 1.1 729 140 140 --------------------------------. ----------------------------------. ----------* For credibility check, measured shift values are adjusted to average surveillance material chemistry and irradiation temperature as required. See Table 4. Page 17 of 18 Summary (R3008)
* Surry Unit 2 Capsule X                 0.190           0.550           534.9               0.6720                     96                   96                 12 Surry Unit 2 Capsule V                 0.190           0.550           540.1               1.1729                    140                   140               -7
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).
                      -                           -             -               -                   .                         -                   -                 -
                      -                           -             -               -                                             -                   -                 -
* 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)
 
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**
R3008                        0.190         0.550             543.1                 149.3                   Credible               125.2                  -
'ff 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.
e 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? **
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)}}

Revision as of 00:31, 21 October 2019

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

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 e

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 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 (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:

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

( ~ia p

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

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,

~rfL. 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

e COMMONWEALTH OF VIRGINIA )

)

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

- 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 .

My Commission Expires: March 31, 2000.

0

~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 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

. 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 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).

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.

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.

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

Conclusions

  • 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

References

  • 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.

(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 LTOPS 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

  • 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 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) 122V109VA1 C4326-1 Location Nozzle Shell Forging Intermediate Shell (wt%)

0.11 0.11 (wt%)

0.74 0.55 (x1E19) 0.307 3.53 Factor 76.1 73.5 CF (2)

Tables Tables RT(NDT) 40 10 Sigma(!)

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

  • 112.5 135.2 e

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

  • 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
  • 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 .)
  • 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)

Page 1 of 18

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%)

0.11 0.12 (wt%)

0.72 0.60 (x1E19) 0.298 3.520 Factor 75.8 83.0 CF(2)

Tables Tables RT(NDT) 30

-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*

100.4 123.9 e

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 .)

  • 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)

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 e

Point Beach Unit 1 Capsule V 0.230 0.615 542 .0 0.8723 107 107 -17

- - - - - - - -

- - - - - - - -

- - - - - - - -

- - - - - - - -

- - - - - - - -

- - - - - - - -

- - - - - - - -

- - - - - - - -

  • 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

ET-NAF-990006 Tables.xis Table 4: Surry Unit 1 and 2 Weld Material SA-1585 (Point Beach 1 Data Only)

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 **

SA-1585/72445 0.220 0.540 542 .0 158.0 Non-Credible 158.0 Conservative

  • If surveillance data are determined to be non-credible, the Position 1. 1 chemistry factor is applied to the beltline material.
    • Measured shift values are adjusted to the average surveillance material chemistry and irradiation temperature, and are verified to be within 2 sigma of the trend curve based on Position 1. 1.

Credibility Assessment e

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

(1) (2) Temperature Correction (4)

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? **

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.) - - - - - - - -

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

- - - - - - - - -

- - - - - - - - -

- - - - - - - - -

- - - - - - - - -

- - - - - - - - -

- - - - - - - - -

(1) For the credi bility determination, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in a single reactor (i.e. , were 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 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 S\ c, c: .. it 155 "'

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)

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 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

- - - - - - - -

- - - - - - - -

- - - - - - - -

- - - - - - - -

- - - - - - - -

- - - - - - -

  • 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__ ----

ET-NAF-990006 Tables.xis Table 4: Surry Unit 1 and 2 Weld Material SA-1585 (All Available Data)

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**

SA-1585n2445 0.220 0.540 542.0 158.0 Credible 139.8 -

  • If suNei/lance 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 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)

(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)

ET-NAF-990006 Tables.xis Table 4: Surry Unit 1 Weld Material SA-1526 (Surry Unit 1 Data Only)

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*
  • SA-1526/299L44 0.340 0 .680 542.0 220.6 Non-Credible 220.6 Conservative
  • If surveillance data are determined to be non-credible, the Position 1. 1 chemistry factor is applied to the belt/ine material.
    • Measured shift values are adjusted to the average surveillance material chemistry and irradiation temperature, and are verified to be within 2 sigma of the trend curve based on Position 1. 1.

Credibility Assessment e

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

(1) (2) Temperature Correction (4)

Temperature Chemistry 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 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) .

(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 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

  • 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)

ET-NAF-990006 Tables.xis Table 4: Surry Unit 1 Weld Material SA-1526 (All Available Data)

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**

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

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 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? **

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) .

(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 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 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

.

-44

-16 38 20 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)

ET-NAF-990006 Tables.xis Table 4: Surry Unit 1 Weld Material SA-1526 (All Data Except TMl-2)

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 **

SA-1526/299L44 0.340 0.680 542 .0 220.6 Non-Credible 220.6 Conservative

-

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

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

Credibility Assessment 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 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? **

Capsule TM l2-LG1 (BWOG CR-3 lrrad.) - - - - - - - -

Capsule CR3-LG1 (BWOG CR-3 lrrad.) Yes Yes Credible - - 181 -3 Credible Capsule TMl2-LG1 (BWOG CR-3 lrrad.} - - - - - - - -

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).

(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).

(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 beltl ine material being evaluated.

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 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

-38

-18 32 e

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)

ET-NAF-990006 Tables.xis Table 4: Surry Unit 1 Weld Material SA-1526 (All Data, No Adjustments)

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**

SA-1526/299L44 0.340 0.680 542 .0 220.6 Non-Credible 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.

e Credibility Assessment 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 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) 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) .

(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) .

(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)

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 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

- - - - - - -

- - - - - - -

- - - - - - -

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 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

-

-

-

-

-29

-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)

ET-NAF-990006 Tables.xis Table 4: Surry Unit 1 Weld Material SA-1526 (All Data Except Surry Unit 1 Data)

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**

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

e 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 - - 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 - - - - - - - -

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.

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

- - - - - - - -

- - - - - - - -

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- - - - - - - -

- . - - - - - -

- - - - - - - -

- - - - - - - -

- - - - - - - -

- - - - . - - -

- - - - - - -

  • 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)

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**

R3008 0.190 0.550 543.1 149.3 Credible 125.2 -

'ff 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.

e 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? **

Surry Unit 2 Capsule X No No Credible No No - - -

Surry Unit 2 Capsule V No No Credible No No - - -

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(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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