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{{#Wiki_filter:Tennessee Valley Authority, Post Office Box 2000, Soddy Daisy, Tennessee 37384-2000 February 19, 2009 10CFR50.50a(g)(5)(iii)
U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Gentleman:
In the Matter of                            )                                            Docket Nos. 50-327 Tennessee Valley Authority                  )                                                        50-328 SEQUOYAH NUCLEAR PLANT (SQN) - AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) SECTION XI INSERVICE INSPECTION (ISI) PROGRAM - RELIEF REQUESTS Pursuant to 10 CFR 50.55a(g)(5)(iii), TVA is submitting 11 requests for relief from ASME code requirements. The relief requests are associated with ISI activities performed and identified during the third period of SQN's ASME Section XI Second 10-Year Inservice Inspection Interval. The relief requests are based on limitations that preclude full code examination coverage for ASME code welds and components. Full code examination of the welds and components is limited because of design configurations.
The relief requests are submitted in accordance with 10 CFR 50.55a(g)(5)(iii). TVA requests that NRC provide approval in accordance with 10 CFR 50.55a(g)(6)(i). The original relief request was prepared for submittal on January 27, 2007; however, the request was inadvertently not submitted to NRC.
TVA has no specific milestones or schedule for requesting NRC review and approval of the enclosed relief requests. The enclosed relief requests are being submitted solely for the closure of SQN's Second 10-Year Inservice Inspection Interval that completed on May 31, 2006. SQN's Third 10-year inspection interval started on June 1, 2006. provides five requests for relief for both units and a single relief request specific to Unit 2 (2-ISI-33). Enclosure 2 provides examination data reports for 2-ISI-33. provides ISI drawings. Enclosure 4 provides TVA's procedure for calculation of the ASME code coverage for Section XI nondestructive examinations. Enclosure 5 provides examination data reports (area coverage) for the balance of relief requests involving volumetric examination.
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U.S. Nuclear Regulatory Commission Page 2 February 19, 2009 There are no commitments contained in this letter.
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If you have any questions about this change, please telephone me at (423) 843-7170.
Sincerely,
: a. i Beth A. Wetzel Manager, Site Licensing and Industry Affairs Enclosures cc (Enclosures):
Mr. Brendon T. Moroney, Senior Project Manager U.S. Nuclear Regulatory Commission Mail Stop 08G-9a One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2739


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U.S. Nuclear Regulatory Commission Page 3 February 19, 2009 BAW:JWP:SKD cc (Enclosures):
G. Arent, EQB 1B-WBN T. J. Bradshaw (NSRB Support), LP 4K-C C. R. Church, POB 2B-SQN T. P. Cleary, OPS 4A-SQN D. E. Jemigan, LP 3R-C K. R. Jones, OPS 4A-SQN R. M. Kerwin, OPS 4A-SQN M. J. Lorek, LP 3R-C L. E. Nicholson, LP 3R-C M. A. Purcell, LP 4K-C P. D. Swafford, LP 3R-C L. E. Thibault, LP 3R-C S. A. Vance, ET10A-K E. J. Vigluicci, ET10A-K WBN Site Licensing Files, ADM 1L-WBN EDMS, WT CA-K l:License/ASME - ISI/ISI Weld Limitations from 3rd period of 2nd ISI Interval


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ENCLOSURE 1 SEQUOYAH NUCLEAR PLANT (SQN)
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AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME)
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INSERVICE INSPECTION PROGRAM (ISI)
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REQUESTS FOR RELIEF UNITS 1 AND 2 1/2-ISI-28 1/2-ISI-29 1/2-ISI-30 1/2-ISI-31 1/2-ISI-32 2-ISI-33 El-1


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Request For Relief 1/2-ISI-28 Summary:
TVA is requesting relief from the ASME Section XI Code to address the Units 1 and 2 reactor pressure vessel (RPV) bottom head-to-lower shell welds. The design configuration of the RPV core support lugs precludes a 100 percent ultrasonic examination of the required examination volume of each bottom head-to-lower shell weld. These physical examination limitations occur when the 1989 Edition Section XI Code examination requirements are applied in areas of components constructed and fabricated to early plant physical designs. Based on the date of Sequoyah Nuclear Plant's (SQN) construction permit (May 27, 1970), SQN is exempt from the code requirements for examination access as allowed in 10 CFR 50.55a(g)(4).
An inservice ultrasonic examination was performed on accessible areas to the maximum extent practical, given the physical limitations of the RPV bottom head-to-lower shell weld (W02-03) on both units. The design configuration limits the best effort ultrasonic examination to approximately 77 percent of the RPV bottom head-to-lower shell weld on both units.
Performance of an ultrasonic examination of essentially 100 percent of the full penetration welds is impractical because of the location of the reactor vessel core support lugs. The best effort ultrasonic examination and the required VT-3 visual examination of the interior of the RPV (Examination Category B-N-1) provides reasonable assurance of an acceptable level of quality and safety, because the information and data obtained from the volume examined provides sufficient information to judge the overall integrity of the weld.
Therefore, pursuant to 10 CFR 50.55a(g)(5)(iii), it is requested that relief be granted for the second inspection interval.
Units:                            1 and 2 System:                            Reactor Coolant System - System 68 Components:                        RPV Bottom Head-to-Lower Shell Weld, Full Penetration Weld ASME Code Class:                    ASME Code Class 1 (Equivalent)
Section XI Edition:                1989 Edition (1995 Edition with 1996 Addenda for Non-Destructive Examination (NDE)
Code Table:                        IWB-2500-1 Examination Category:              B-A, Pressure Retaining Welds in Reactor Vessel Examination Item Number:            B1.11, Circumferential Shell Welds Code Requirement:                  ASME Section XI, Table IWB-2500-1, Examination Category B-A, Item Number B1.11, Requires Volumetric Examination of the RPV Bottom Head-to-Lower Shell Weld Code Requirement From              Volumetric Examination of Essentially Which Relief Is Requested:          100 percent of the RPV Bottom Head-to-Lower Shell Weld List of Items Associated            W02-03 RPV Bottom Head-to-Lower Shell With The Relief Request:            Welds on Units 1 and 2 El-2
 
Request for Relief 1/2-ISI-28 (continued)
Basis for Relief:
The design configuration of the RPV precludes a complete volumetric examination of the required volume for the bottom head-to-lower shell weld W02-03 on both units. The limitation is due to the location of the reactor vessel core support lugs. This design configuration limits the volumetric (ultrasonic) examination to approximately 77 percent of the weld on both units.
The calculated results are provided in Enclosure 5.
Alternative Examination:
In lieu of the code required 100 percent volumetric examination, an ultrasonic examination will be performed on accessible areas to the maximum extent practical given the physical limitations of the bottom head-to-lower shell weld. Refer to Enclosure 5 for the Units 1 and 2 examination area coverage reports.
Justification for the Granting of Relief:
The design configuration used in the fabrication of the RPV bottom head-to-lower shell weld and location of the reactor vessel core support lugs precludes volumetric examination of essentially 100 percent of the required examination volume. In order to examine the weld in accordance with the code requirement, the RPV would require extensive design modifications.
The physical arrangement of bottom head-to-lower shell weld W02-03 and location of the reactor vessel core support lugs limit access for a complete volumetric examination. A total of six-core support lugs are welded to the reactor vessel equally spaced circumferently adjacent to the weld along the axial direction of the reactor vessels. Each core support lug attachment is approximately 15.75 inches in width and 23.78 inches in length (plus the weld blend radius) and covers the examination areas adjacent to the bottom head-to-lower shell weld. The design configuration of the RPV limits the ultrasonic examination to approximately 77 percent for both welds. Examinations were performed using qualified performance demonstration initiative (PDI) techniques.
Radiographic examination as an alternative volumetric examination method was determined to be impractical because of the inaccessibility from the inside diameter (ID) and the presence of water in the vessel.
Performing an ultrasonic volumetric or a surface examination from the RPV outside surface was determined to be impractical because of the physical design of the building. The physical limitations include the biological shield and insulation, which does not allow access to the weld without significant modification of the structure.
Performance of an ultrasonic volumetric examination of essentially 100 percent of the required volume of the bottom head-to-lower shell weld W02-03 on each RPV is impractical. As previously discussed, TVA determined that it would be impractical to attempt other volumetric examinations in order to increase examination coverage. The percentage (77 percent) of a volumetric (ultrasonic) examination of the subject weld and adjacent basemetal volumes and a code required VT-3 visual examination of the interior of the RPV (Examination Category B-N-
: 1) provides reasonable assurance of an acceptable level of quality and safety. Significant degradation, if present, would be detected during the ultrasonic and VT-3 examinations that are performed on the subject welds. As a result, reasonable assurance of structural integrity of these welds is provided by the performance of these examinations.
El-3
 
Request for Relief 1/2-ISI-28 (continued)
Therefore, pursuant to 10 CFR 50.55a(g)(5)(iii), it is requested that relief be granted for the second inspection interval.
Implementation Schedule:
This request for relief is applicable to the second inspection interval for SQN Units 1 and 2.
The examinations of weld W02-03 for both Units 1 and 2 were performed in the third period.
Background Information:
Requests for relief for volumetric examination coverage limitations was submitted for SQN's RPV bottom head-to-lower shell welds in SQN's first ISI interval (Relief Request 1-ISI-25 for Unit 1 and Relief Request 2-ISI-30 for Unit 2) and was approved by the reference letter below.
 
==References:==
: 1) Letter from David E. LaBarge, NRC, to O.D. Kingsley, Jr., TVA, dated February 7, 1996 (TAC Nos. M92454 and M92455)
: 2) Enclosure 3 - SI Program Drawing: ISI-0504-C-02 for Unit 1 and ISI-0298-C-02 for Unit 2
: 3) Enclosure 5 - ISwT Examination Area Coverage Reports for SQN Units 1 and 2 El-4
 
Request for Relief 1/2-1 SI-29 Summary:
TVA is requesting relief from the ASME Section XI Code to address the Units 1 and 2 RPV bottom head welds. The design configuration of the RPV instrumentation tubes, which penetrate the bottom head, precludes a 100 percent ultrasonic examination of the required examination volume of each bottom head weld. These physical examination limitations occur when the 1989 Edition Section XI Code examination requirements are applied in areas of components constructed and fabricated to early plant physical designs. Based on the date of SQN's construction permit (May 27, 1970), SQN is exempt from the code requirements for examination access as allowed by 10 CFR 50.55a(g)(4).
An inservice ultrasonic examination was performed on accessible areas to the maximum extent practical, given the physical limitations of the RPV bottom head weld (W01-02) on both units. The design configuration limits the best effort ultrasonic examination to approximately 52 percent (Unit 1) and 54 percent (Unit 2) of the RPV bottom head weld. Performance of an ultrasonic examination of essentially 100 percent of the full penetration welds are impractical due to the location of the of the reactor vessel instrumentation tubes, which penetrate the bottom head. The best effort ultrasonic examination and the required VT-3 examination of the interior of the RPV (Examination Category B-N-1) provides reasonable assurance of an acceptable level of quality and safety, because the information and data obtained from the volume examined provides sufficient information to judge the overall integrity of the weld.
Therefore, pursuant to 10 CFR 50.55a(g)(5)(iii), it is requested that relief be granted for the second inspection interval.
Units:                              1 and 2 System:                            Reactor Coolant System - System 68 Components:                        RPV Bottom Head Weld, Full Penetration Weld ASME Code Class:                  ASME Code Class 1 (Equivalent)
Section XI Edition:                1989 Edition (1995 Edition with 1996 Addenda for NDE)
Code Table:                        IWB-2500-1 Examination Category:              B-A, Pressure Retaining Welds in Reactor Vessel Examination Item Number:            B1.21, Circumferential Head Welds Code Requirement:                  ASME Section XI, Table IWB-2500-1, Examination Category B-A, Item Number B1.21 Requires Volumetric Examination of the RPV Bottom Head Weld Code Requirement From              Volumetric Examination of Essentially Which Relief Is Requested:          100 percent of the RPV Bottom Head Weld List of Items Associated          W01-02 RPV Bottom Head Welds on Units 1 With The Relief Request:          and 2 El-5
 
Request for Relief 1/2-ISI-29 (continued)
Basis for Relief:
The design configuration of the RPV precludes a complete volumetric examination of the required volume for bottom head weld W01-02 on both units. The limitation is due to instrumentation tubes, which penetrate the bottom head. This design configuration limits the volumetric (ultrasonic) examination to approximately 52 percent (Unit 1) and 54 percent (Unit
: 2) of the weld. The calculated results are provided by Enclosure 5.
Alternative Examination:
In lieu of the code required 100 percent volumetric examination, an ultrasonic examination will be performed on accessible areas to the maximum extent practical given the physical limitations of the bottom head weld. Refer to Enclosure 5 for the Units 1 and 2 examination area coverage reports.
Justification for the Granting of Relief:
The design configuration used in the fabrication of the RPV bottom head weld and location of the reactor vessel instrumentation, which penetrate the bottom head, precludes volumetric examination of essentially 100 percent of the required examination volume. In order to examine the weld in accordance with the code requirement, the RPV would require extensive design modifications. The physical arrangement of bottom head weld W01-02 and location of the reactor vessel instrumentation tubes, which penetrate the bottom head, limits access for a complete volumetric examination on each weld. A total of 58 instrumentation tubes penetrate the bottom head. These instrumentation tubes limit the access to the bottom head weld. The design configuration limits the best effort ultrasonic examination to approximately 52 percent (Unit 1) and 54 percent (Unit 2) of the welds. The subject welds were examined using application of the qualified PDI techniques.
Radiographic examination as an alternative volumetric examination method was determined to be impractical because of the inaccessibility from the outside diameter (OD) of the vessel and also because of the presence of water in the vessel.
Performance of an ultrasonic volumetric examination of essentially 100 percent of the required volume of bottom head weld W01-02 on each RPV is impractical. As previously discussed, TVA determined that it would be impractical to attempt other volumetric examinations in order to increase examination coverage. The percentage (52 percent Unit 1 and 54 percent Unit 2) of a volumetric (ultrasonic) examination of the subject weld and adjacent basemetal volumes and a code required VT-3 visual examination of the interior of the RPV (Examination Category B-N-1) provides reasonable assurance of an acceptable level of quality and safety. Significant degradation, if present, would be detected during the ultrasonic and VT-3 examinations that are performed on the subject welds. As a result, reasonable assurance of structural integrity of these welds is provided by the performance of these examinations.
Therefore, pursuant to 10 CFR 50.55a(g)(5)(iii), it is requested that relief be granted for the second inspection interval.
El-6
 
Request for Relief 1/2-1 SI-29 (continued)
Implementation Schedule:
This request for relief is applicable to the second inspection interval for SQN Units 1 and 2.
The examinations of weld W01 -02 for both units were performed in the third period.
Background Information:
A request for relief for volumetric examination coverage limitations was submitted for W01-02 as 1-ISI-5 for Unit 1 and 2-ISI-5 for Unit 2 in the first inspection interval and was approved by the reference letters below.
 
==References:==
: 1) Letter from Frederick J. Hibdon, NRC, to Oliver D. Kingsley, Jr., TVA, dated February 7 1991 (TAC No. 59457)
: 2) Letter from Suzanne Black, NRC, to Oliver D. Kingsley, Jr., TVA, dated April 19 1990 (TAC No. 59458)
: 3) Enclosure 3 - ISI Program Drawing: ISI-0504-C-02 for Unit 1 and ISI-0298-C-02 for Unit 2
: 4) Enclosure 5 - ISwT Examination Area Coverage Reports for SQN Units 1 and 2 El-7
 
Request for Relief 1/2-ISI-30 Summary:
TVA is requesting relief from the ASME Section XI Code to address the Units 1 and 2 RPV outlet nozzle-to-vessel welds. The design configuration of the RPV, the outlet nozzle integral extensions, and the location of the adjacent nozzles preclude a 100 percent ultrasonic examination of the required examination volume of the outlet nozzle-to-vessel welds. These physical examination limitations occur when the 1989 Edition Section XI Code examination requirements are applied in areas of components constructed and fabricated to early plant physical designs. Based on the date of SQN's construction permit (May 27, 1970), SQN is exempt from the code requirements for examination access as allowed in 10 CFR 50.55a(g)(4).
An inservice ultrasonic examination was performed on accessible areas to the maximum extent practical, given the physical limitations of the RPV outlet nozzle-to-vessel welds. The design configuration limits the best effort ultrasonic examination to approximately 81 percent (Unit 1) and 72 percent (Unit 2) of each of the RPV outlet nozzle-to-vessel welds.
Performance of an ultrasonic examination of essentially 100 percent of the full penetration welds is impractical because of the integral extensions and the location of the adjacent nozzles. The best effort ultrasonic examination and the required VT-3 visual examination of the interior of the RPV (Examination Category B-N-1) provide reasonable assurance of an acceptable level of quality and safety, because the information and data obtained from the volume examined provides sufficient information to judge the overall integrity of the weld.
Therefore, pursuant to 10 CFR 50.55a(g)(5)(iii), it is requested that relief be granted for the second inspection interval.
Units:                            1 and 2 System:                            Reactor Coolant System - System 68 Components:                        RPV Outlet Nozzle-to-Vessel Weld, Full Penetration Weld ASME Code Class:                  ASME Code Class 1 (Equivalent)
Section XI Edition:                1989 Edition (1995 Edition with 1996 Addenda for NDE)
Code Table:                        IWB-2500-1 Examination Category:              B-D, Pressure Retaining Welds in Reactor Vessel Examination Item Number:          B3.90, Reactor Vessel Nozzle-to-Vessel Welds Code Requirement:                  ASME Section XI, Table IWB-2500-1, Examination Category B-D, Item Number B3.90 Requires Volumetric Examination of the Outlet Nozzle-to-Vessel Welds Code Requirement From              Volumetric Examination of Essentially Which Relief Is Requested:        100 percent of the Outlet Nozzle-to-Vessel Welds List Of Items Associated          N-15, N-16, N-17, and N-18 Outlet With The Relief Request:          Nozzle-to-Vessel Welds on Units 1 and 2 El-8
 
Request for Relief 1/2-ISI-30 (continued)
Basis for Relief:
The design configuration of the RPV precludes a complete volumetric examination of the required volume for outlet nozzle-to-vessel welds N-15, N-16, N-17, and N-18 on both units.
The limitation is because of the physical arrangement of outlet nozzle-to-vessel weld, nozzle integral extensions and the location of the adjacent nozzles. This design configuration limits the volumetric (ultrasonic) examination to approximately 81 percent (Unit 1) and 72 percent (Unit 2) for these welds. The calculated results are provided in Enclosure 5.
Alternative Examination:
In lieu of the code required 100 percent volumetric examination, an ultrasonic examination will be performed on accessible areas to the maximum extent practical given the physical limitations of the outlet nozzle-to-vessel welds. Refer to Enclosure 5 for the Units 1 and 2 examination area coverage reports.
Justification for the Granting of Relief:
The design configuration used in the fabrication of the RPV outlet nozzle-to-vessel weld, the outlet nozzle integral extensions, and the location of the adjacent nozzles precludes volumetric examination of essentially 100 percent of the required examination volume. In order to examine the weld in accordance with the code requirement, the RPV would require extensive design modifications. The physical arrangement of outlet nozzle-to-vessel welds N-15, N-16, N-17, and N-18; the nozzle integral extensions; and the location of the adjacent nozzles limit access for a complete volumetric examination. Because of the design of the RPV nozzle-to-vessel weld configuration, ultrasonic examination conducted from the vessel interior surface provides more examination coverage than if conducted from the vessel exterior surface due to limited access. The design configuration limits the best effort ultrasonic examination to approximately 81 percent (Unit 1) and 72 percent (Unit 2) for these welds. The subject welds were examined using application of the qualified PDI techniques.
Radiographic examination as an alternative volumetric examination method was determined to be impractical because of the inaccessibility from the OD of the vessel and also due to the presence of water in the vessel-Performance of an ultrasonic volumetric examination of essentially 100 percent of the required volume of outlet nozzle-to-vessel welds N-15, N-16, N-17, and N-18 on each RPV is impractical. As previously discussed, TVA determined that it would be impractical to attempt other volumetric examinations in order to increase examination coverage. The percentage (81 percent Unit 1 and 72 percent Unit 2) of a volumetric (ultrasonic) examination of the subject weld and adjacent basemetal volumes and a code required VT-3 visual examination of the interior of the RPV (Examination Category B-N-1) provides reasonable assurance of an acceptable level of quality and safety. Significant degradation, if present, would be detected during the ultrasonic and VT-3 examinations that are performed on the subject welds. As a result, reasonable assurance of structural integrity of these welds is provided by the performance of these examinations.
Therefore, pursuant to 10 CFR 50.55a(g)(5)(iii), it is requested that relief be granted for the second inspection interval.
El-9
 
Request for Relief 1/2-ISI-30 (continued)
Implementation Schedule:
This request for relief is applicable to the second inspection interval for SQN Units 1 and 2.
The examination of welds N-15, N-16, N-17, and N-18 for both Units 1 and 2 were performed in the third period.
Background Information:
A request for relief for volumetric examination coverage limitations was submitted for welds N-15, N-16, N-17 and N-18 as 1-ISI-27 for Unit 1 and 2-ISI-29 for Unit 2 in the first inspection interval and was approved with the reference letter below.
 
==References:==
: 1) Letter from David E. LaBarge, NRC, to O.D. Kingsley, Jr., TVA, dated February 7, 1996 (TAC NOS. M92454 and M92455)
: 2) Enclosure 3 - ISI Program Drawing: ISI-0504-C-02 for Unit 1 and ISI-0298-C-02 for Unit 2
: 3) Enclosure 5 - ISwT Examination Area Coverage Reports for SQN Units 1 and 2 El-10
 
Request for Relief 1/2-ISI-31 Summary:
TVA is requesting relief from the ASME Section XI Code to address the Units 1 and 2 reactor pressure vessel (RPV) bottom head meridional welds. The design configuration of the RPV instrumentation tubes, which penetrate the bottom head, precludes a 100 percent ultrasonic examination of the required examination volume of the bottom head weld. These physical examination limitations occur when the 1989 Edition Section XI Code examination requirements are applied in areas of components constructed and fabricated to early plant physical designs. Based on the date of SQN's construction permit (May 27, 1970), SQN is exempt from the code requirements for examination access as allowed in 10 CFR 50.55a(g)(4).
An inservice ultrasonic examination was performed on accessible areas to the maximum extent practical, given the physical limitations of the RPV bottom head meridional welds. The design configuration limits the best effort ultrasonic examination of the meridional welds.
Performance of an ultrasonic examination of essentially 100 percent of the full penetration welds are impractical due to the location of the of the reactor vessel instrumentation tubes, which penetrate the bottom head. The best effort ultrasonic examination and the required VT-3 visual examination of the interior of the RPV (Examination Category B-N-1) provide reasonable assurance of an acceptable level of quality and safety, because the information and data obtained from the volume examined provide sufficient information to judge the overall integrity of the weld.
Therefore, pursuant to 10 CFR 50.55a(g)(5)(iii), it is requested that relief be granted for the second inspection interval.
Units:                            1 and 2 System:                            Reactor Coolant System - System 68 Components:                        Reactor Pressure Vessel Bottom Head Meridional Welds, Full Penetration Weld ASME Code Class:                  ASME Code Class 1 (Equivalent)
Section XI Edition:                1989 Edition (1995 Edition with 1996 Addenda for NDE)
Code Table:                        IWB-2500-1 Examination Category:              B-A, Pressure Retaining Welds in Reactor Vessel Examination Item Number:          B1.22, Head Meridional Welds Code Requirement:                  ASME Section XI, Table IWB-2500-1, Examination Category B-A, Item Number B1.22 Requires Volumetric Examination of the RPV Bottom Head Meridional Welds Code Requirement From              Volumetric Examination of Essentially Which Relief Is Requested:        100 percent of the RPV Bottom Head Meridional Welds List of Items Associated          W2C RPV Bottom Head Weld on Unit 1 Only With The Relief Request:          W2E and W2F RPV Bottom Head Welds on Units 1 and 2 El-ll
 
Request for Relief 1/2-ISI-31 (continued)
Basis for Relief:
The design configuration of the RPV precludes a complete volumetric examination of the required volume for the bottom head meridional welds (W2E and W2F) on both units and W2C (Unit 1 only). The limitation is due to instrumentation tubes, which penetrate the bottom head.
This design configuration limits the volumetric (ultrasonic) examination to approximately 87 percent (Unit 1 only) for W2C, 86 percent (Unit 1) and 90 percent (Unit 2) for W2E and 81 percent (Unit 1) and 80 percent (Unit 2) for W2F, as calculated by TVA approved vendor procedures (Enclosure 5).
Alternative Examination:
In lieu of the code required 100 percent volumetric examination, an ultrasonic examination will be performed on accessible areas to the maximum extent practical given the physical limitations of the bottom head meridional welds. Refer to Enclosure 5 for the Units 1 and 2 examination area coverage reports.
Justification for the Granting of Relief:
The design configuration used in the fabrication of the RPV bottom head meridional welds and location of the reactor vessel instrumentation, which penetrates the bottom head, precludes volumetric examination of essentially 100 percent of the required examination volume. In order to examine the weld in accordance with the code requirement, the RPV would require extensive design modifications. The physical arrangement of bottom head meridional welds W2C (Unit 1 only), W2E, and W2F and location of the reactor vessel instrumentation tubes, which penetrate the bottom head, limits access for a complete volumetric examination. A total of 58 instrumentation tubes penetrate the bottom head. The design configuration limits the best effort ultrasonic examination to approximately 87 percent for W2C (Unit 1 only), 86 percent (Unit 1) and 90 percent (Unit 2) for W2E, and 81 percent (Unit 1) and 80 percent (Unit
: 2) for W2F welds. The subject welds were examined using application of the qualified PDI techniques.
Radiographic examination as an alternative volumetric examination method was determined to be impractical because of the inaccessibility from the vessel ID and also because of the presence of water in the vessel.
TVA performed a review in order to assess the differences in the percent of coverage between Units 1 and 2. Even though the head configurations are designed to be the same, some of these welds are limited on the upper end by the core barrel support lugs, some are limited on the lower end by the lower head penetrations, and some are limited on both ends.
Performance of an ultrasonic volumetric examination of essentially 100 percent of the required volume of bottom head meridional welds W2E and W2F on each RPV and W2C on Unit 1 only are impractical. As previously discussed, TVA determined that it would be impractical to attempt other volumetric examinations in order to increase examination coverage. The percentage (87 percent [Unit 1 only] on W2C, 86 percent [Unit 1] and 90 percent [Unit 2] on W2E and 81 percent [Unit 1] and 80 percent [Unit 2] on W2F) of a volumetric (ultrasonic) examination of the subject weld and adjacent basemetal volumes and a code required VT-3 visual examination of the interior of the RPV (Examination Category B-N-1) provide reasonable assurance of an acceptable level of quality and safety. Significant degradation, if present, El-12
 
Request for Relief 1/2-ISI-31 (continued) would be detected during the ultrasonic and VT-3 examinations that are performed on the subject welds. As a result, reasonable assurance of structural integrity of these welds is provided by the performance of these examinations.
Therefore, pursuant to 10 CFR 50.55a(g)(5)(iii), it is requested that relief be granted for the second inspection interval.
Implementation Schedule:
This request for relief is applicable to the second inspection interval for SQN Units 1 and 2.
The examination of weld W2C (Unit 1 only), and welds W2E and W2F for both Units 1 and 2, were performed in the third period.
 
==References:==
: 1) Enclosure 3 - ISI Program Drawing: ISI-0504-C-02 for Unit 1 and ISI-0298-C-02 for Unit 2
: 2) Enclosure 5 - ISwT Examination Area Coverage Reports for SQN Units 1 and 2.
El-13
 
Request for Relief 1/2-ISI-32 Summary:
TVA is requesting relief from the ASME Section XI Code to address the Units 1 and 2 reactor pressure vessel support RVH-1. The design configuration of the subject support and the location preclude a 100 percent visual examination of the required support area. These physical examination limitations occur when the 1989 Edition Section XI Code examination requirements are applied in areas of components constructed and fabricated to early plant physical designs. Based on the issue date of SQN's construction permit (May 27, 1970), SQN is exempt from the code requirements for providing original design and examination access as allowed in 10CFR50.55a(g)(4).
An inservice VT-3 visual examination was performed on accessible areas to the maximum extent practical, given the design and location limitations of the subject support. The design configuration and location limit the visual examination to one side of the support. Performance of a visual examination of essentially 100 percent of the subject support would be impractical.
The maximum extent practical visual examination of the subject support provides reasonable assurance of an acceptable level of quality and safety, because the information obtained from the area examined provides sufficient information to judge the overall integrity of the support.
Therefore pursuant to 10 CFR50.55a(g)(5)(iii), it is requested that relief be granted, for the second inspection interval.
Units:                            1 and 2 System:                            System Reactor Coolant System - System 68 Component:                        RPV Support ASME Code Class:                  ASME Code Class 1 (Equivalent)
Section XI Edition:                1989 Edition (1995 Edition with 1996 Addenda for NDE)
Code Table:                        ASME Section XI Code Case N-491-1, Table 2500-1 Examination Category:              F-A, Supports Examination Item Number:          F1.40, Supports Other Than Piping Supports (Class 1, 2, 3, and MC)
Code Requirement:                  ASME Section XI, Code Case N-491-1, Table 2500-1, Examination Category F-A, Item F1.40, Requires VT-3 Visual Examination for the RPV Support Code Requirement From              VT-3 Visual Examination of Essentially Which Relief Is                    100 Percent of the RPV Support Requested:
List of Items                      RVH-1, RPV Support Associated With The Relief Request:
El-14
 
Request for Relief 1/2-IS1-32 (continued)
Basis for Relief:
The design configuration of the reactor vessel support and the support location precludes a VT-3 visual examination of the required area of the subject support RVH-1. A limited VT-3 visual examination was performed on the accessible portions of the subject support to the maximum extent practical. Removable portions of the insulation were removed from the piping and RPV nozzle areas in order to maximize the VT-3 visual examination of the RPV nozzle to support interface. Typical access for each support was determined to allow less than 50 percent of the support areas requiring examination to be examined. Insulation and flashing on the RPV nozzle and the RPV, which remained in place, would require extensive modifications to remove. However, a maximum extent VT-3 visual examination of the area was performed, which included an examination of the insulation for any evidence of disturbance or degradation that may be attributed to abnormal support disturbance.
Alternative Examinations:
In lieu of the Section XI essentially 100 percent VT-3 visual examination, a best effort VT-3 visual examination was performed on accessible areas to the maximum extent practical, given the location and configuration of the support.
Justification For The Granting Of Relief:
The support assembly at four of the eight reactor vessel nozzles consists of a nozzle pad and steel plates positioned between a steel support structure. Additionally, the majority of each support is encased in permanent insulation panels from the reactor vessel and vessel nozzles and piping. Insulation panels were removed around the piping and nozzles to the extent practical in order to access the support. These design features make the VT-3 visual examination of the reactor vessel supports impractical to perform to the extent required by Section XI. The design configuration restricts visual access to a majority of stiffener welds and structural steel.
However, structural and mechanical integrity was verified by observing no signs of mechanical or structural inservice related conditions of the accessible areas. To meet Section XI requirements, the permanent insulation would be required to be removed and redesigned to allow access for complete examination. The design configuration used in the fabrication of the subject support, in conjunction with the confined space to access the support, precludes visual examination of essentially 100 percent of the required examination area. The support is designed to function as a vertical restraint primarily loaded in compression. The majority of each support is encased in the permanent insulation panels of the RPV and RPV nozzles.
Portions of the steel support structure and associated welds are accessible for a limited VT-3 visual examination. In order to examine the support in accordance with Section XI requirements, extensive modification would be required to access all regions of the support.
Access to the RPV support is limited because of confined access below the nozzle inspection covers, nozzle insulation and the permanent liner steel plates for the cavity wall.
El-15
 
Request for Relief 1/2-ISI-32 (continued)
In addition to difficult access, radiation levels in the area are approximately 35- to 80-millirem per hour. It is estimated that the removal and reinstallation of the permanent insulation in this confined space would result in additional exposure of approximately 4.0 man-rem and achieve a minimum increase in examination coverage. Based on the access restrictions, high radiation levels and support design, relief is requested from performing the VT-3 visual examination of the inaccessible portions of these supports. The design configuration limits the best effort visual examination to the accessible side of the four nozzles for support RVH-1. The subject support was remotely examined using a video camera and direct visual examination in order to achieve maximum coverage.
Performance of a VT-3 visual examination of essentially 100 percent of the required area of RPV support RVH-1 is impractical. The maximum extent practical visual examination of the support will provide reasonable assurance of an acceptable level of quality and safety.
Significant degradation, if present, would have been detected during the visual examination on the subject support. As a result, reasonable assurance of structural integrity for this support is provided by the examination that was performed.
Therefore pursuant to 10 CFR 50.55a(g)(5)(iii), it is requested that relief be granted, for the second inspection interval.
Implementation Schedule:
This request for relief is applicable to SQN's second inspection interval for SQN Units 1 and 2.
The examinations of the RPV support, RVH-1, were performed for both units in the third period.
El-16
 
Request for Relief 2-ISI-33 Summary:
TVA is requesting relief from the ASME Section XI Code to address the circumferential pressure retaining piping weld SIF-170 in the safety injection system. The design configuration, elbow-to-valve, of the subject piping precludes a 100 percent ultrasonic examination of the required weld volume. These physical examination limitations occur when the 1989 Edition Section XI Code examination requirements are applied in areas of components constructed and fabricated to early plant physical designs. Based on the issue date of SQN's construction permit (May 27, 1970), SQN is exempt from the code requirements for providing original design and examination access as allowed in 10 CFR 50.55a(g)(4).
An inservice ultrasonic examination was performed on accessible areas to the maximum extent practical, given the physical limitations of the subject weld. The design configuration, elbow-to-valve, limits the best effort ultrasonic examination to approximately 50 percent.
Performance of an ultrasonic examination of essentially 100 percent of the subject circumferential pressure retaining weld would be impractical. The maximum extent practical ultrasonic examination of the subject weld provides reasonable assurance of an acceptable level of quality and safety because the information and data obtained from the volume examined provides sufficient information to judge the overall integrity of the welds.
Therefore pursuant to 10 CFR 50.55a(g)(5)(iii), it is requested that relief be granted, for the second inspection interval.
Unit:
System:                            Safety Injection System -xSystem 63 Component:                          One Pressure Retaining Circumferential Pipe Weld ASME Code Class:                  ASME Code Class 1 (Equivalent)
Section XI Edition:                1989 Edition (1995 Edition with 1996 Addenda for NDE), 10 CFR 50.55a(b)(2)(xv)(A), WCAP-14572, Revision 1-NP-A, and WCAP-14572, Revision 1-NP-A, Supplement 1 Code Table:                        WCAP-14572, Table 4.1-1 Examination Category:              R-A, Risk - Informed Piping Examinations Examination Item Number:            R1.11, Elements Subject to Thermal Fatigue R1.16, Elements Subject to Intergranular Stress Corrosion Cracking (IGSCC)
Code Requirement:                  WCAP-14572, Table 4.1-1, Examination Category R-A, Item Numbers R1.11 and R1.16, Requires Volumetric Examination of Elements Subject to Thermal Fatigue and IGSCC Code Requirement From              Volumetric Examination Coverage of Which Relief Is                    Essentially 100 Percent of Elements Requested:                          Thermal Fatigue and IGSCC El-17
 
Request for Relief 2-IS1-33 (continued)
List of Items                      SIF-170, Circumferential Pipe Weld Associated With The Relief Request:
Basis for Relief:
The design configuration, elbow-to-valve, of the safety injection piping precludes an ultrasonic examination of the required volume of the subject weld SIF-170 because of the design of the valve. The design configuration limits ultrasonic examination to approximately 50 percent of the required examination volume as calculated in accordance with TVA Procedure N-GP-28 (Enclosure 4).
Alternative Examinations:
In lieu of the code required 100 percent volumetric examination, a best effort ultrasonic examination was performed on accessible areas to the maximum extent practical given the physical limitations of the subject weld. Refer to (Enclosure 2) attached examination data report.
Justification for Granting Of Relief:
The design configuration, elbow-to-valve, precludes ultrasonic examination of essentially 100 percent of the required examination volume. In order to examine the weld in accordance with the code requirements, the safety injection system pipe-to-valve configuration would require extensive modification. SIF-170 is limited due to the elbow-to-valve configuration, which limits scanning on the elbow side only. The design configuration limits the best effort ultrasonic examination to approximately 50 percent for weld SIF-170. The subject weld was examined using application of PDI qualified techniques with PDI qualified examiners.
The risk informed segment, which includes weld SIF-170, is classified high safety significant.
The postulated failure mechanisms for the segment are thermal fatigue, thermal stratification/striping and stress corrosion cracking (SCC). All welds in this segment that are subject to SCC must be examined every 10 years. Weld SIF-170 is the only weld in this segment that is subject to SCC. Therefore, there are no welds available for substitution.
Performance of an ultrasonic volumetric examination of essentially 100 percent of the required volume of pressure retaining circumferential weld SIF-170 (pipe to valve) in the safety injection piping is impractical. As indicated above, this ultrasonic volumetric examination was performed in accordance with Performance Demonstration Initiative (PDI). The maximum extent practical ultrasonic examination of the weld and adjacent material and the code required VT-2 examination for leakage would provide reasonable assurance of an acceptable level of quality and safety. Significant degradation, if present, would be detected during the ultrasonic and VT-2 examinations that are performed on the subject weld. As a result, reasonable assurance of structural integrity for this weld is provided by the examinations that were performed.
El-18
 
Request for Relief 2-ISI-33 (continued)
Radiographic examination as an alternate volumetric examination method was determined to be impractical due the material thickness variation. The radiographic density variation does not lend for compliance with Section V requirements without extensive radiographic exposures to obtain the density for the base material on the valve side. Radiography required would increase personnel radiation exposure for minimal increase in examination coverage.
Therefore pursuant to 10 CFR 50.55a(g)(5)(iii), it is requested that relief be granted for the second inspection interval.
Implementation Schedule:
This request for relief is applicable to SQN's second inspection interval for SQN Unit 2. Weld SIF-170 for Unit 2 was examined in the third period.
 
==References:==
: 1) Enclosure 2 - Examination Data Report: R6693 and R6694
: 2) Enclosure 3 - ISI Program Drawings: ISI-0002-C-06
: 3) Enclosure 4 - Non Destructive Examination Procedure N-GP-28 "Calculation of ASME Code Coverage for Section XI NDE Examinations" El-19
 
ENCLOSURE 2 EXAMINATION DATA REPORTS Request for Relief        Examination Data Reports Number 2-ISI-33                  R6693 and R6694 E2-1
 
TENNESSEE                    EXAMINATION REPORT NUMBER:
VALLEY                        SUMiMARY AUTHORITY                          AND PROJECT: SQiV        UNIT:    2    CYCLE:  13      COMPONENT ID: SlF-170 DESCRIPTION/            ^
LOCATION:              /
EXAMINATION METHOD                    SYSTEM: SIS    jlSI DWG NO: 1S1-0002-C-06 MT    Q        PT              UT        vt                CONFIGURATION            CATEGORY PROCEDURE: N-UT-64            REV: 7      TC N/A                    TO    PE,EL            R-A EXAMINER:                      EXAMINER:              EXAMINER:                EXAMINER:
                                                                                              /v zz LEVEL:                        LEVEL: J££,            LEVEL:                    LEVEL:
Total coverage calculated to be approximately    SO The above mentioned weld was ultrasonically inspected. A 1/2 Vpath calibration with a primary angle of 45 shear wave. This was a single sided exam, due to valve configuration, and a 60 RL 1/2 V path calibration was also utilized.
Counterbore geometry was recorded with the 60 RL on the intradose of the elbow.
No rejectable indicatins observed.
This examination meet the requirments of Risk Informed item RLll RESOLUTION B                          REVIEWED BY                      ANII:
y DATE DATE                  LEVEL:      ATE                  Page:  I    OF ACCESS FORMS DATABASE R-3/18/03 EZ-Z
 
PROJECT: SQN                                UNIT/CYCLE CALIBRATION BLOCK NO.:                        TEMP:_
PROCEDURE:                        N-UT-64      REV:      7      TC:
SIMULATOR BLOCK:Rompas                  1^217 TRANSDUCER THERMOMETER S/N 573203                  DUE DATE    8-9-05 MANUFACTURER: KBA COUPLANT: Ultragel II                BATCH: 01225 MODEL: COMP-G                                          S/N:00D8KH ANGLE VERIFICATION SIZE:            .375"                              FREQ:        1.5      MH    BLOCK TYPE:        Rompas      S/N: 792770 SHAPE: Round                        U ELEMENTS: 1            #CONS:      0        NOMINAL ANGLE:45J                    ACTUAL ANGLE:        45 ° LENGTHS'                                                INSTRUMENT CABLE TYPE: RG-174 MANUFACTURER: KLrautkramer                DUE DATE: 7/28/05 EXAM TYPE                        0 SHEAR          LONG MODEL NO.:
DAC                                                        INSTRUMENT SETTINGS 100                                                                                  REFLECTOR REFERENCE          MEMORY SCA:\ DIRECT.                    SENSITIVITY        MMBER A                        NTC  SDH 80                                                                M        AXIAL            *  :  U              31          IttSS45 P        CIRC.                                N/A 60                                                                L      *FREQ_      2. o        MHz I      ANGLE:              J+/- deg        *DAMPlNC:/flflfl        ohms 40                                                                T      DELAY.            0.000 msec      *PULSER      SINGLE U      ZERO:            8.0469 msec 20                                                                D      VELOCITY,        .1257 msec        JOF:        PEAK E      RANGE: _            2A inches      POWER:      BATTERY
                                                                                    *DISP. MODE:F ^
TCG:  ON DISPLAY WIDTH                            2.9 inches FAR SDH      GAIN:          43 dB                        CALIBRATION TIMES REF. REFLECTOR:
METAL PATH:            1.096            INITIAL TIME:      1040        FINAL TIME: 1410 AMPLITUDE:
i m i * * * *-* >>
* i**r ^-^ ~^ -
55 %                                        i                              . i.
VERIFICATION TIMES                            l >>> 13
* 5" " 2>  N/a!3)      N/a!4)    N/aI 5)    N/A'6)    N//\l7)      N/aI8)    N/A w      N/A
                                                        *PDI QUALIFIED INSTRUMENT SETTINGS:
VERIFY INSTRUMENT SETTINGS AND CALIBRATION SEQUENCE ARE IN ACCORDANCE WITH TABLE 2 OF THE APPLICABLE PDI QUALIFICATION IMPLEMENTATION PROCEDURE!
LINEARITY CHECK WELD / ITEMS EXAMINED SIF-170
                                          \ P EXAMINER:                                                                                                      Fr f EXAMINER:
REVIEWER:                                                                              DATE S£lfOf            PAGE                OF ACCESS FORMS OATABASE
 
TENNESSEE                DIGITAL ULTRASONIC                                  REPORT NUMBER VALLEY                              CALIBRATION AUTHORITY                            DATA SHEET CALIBRATION HATE:          4/29/05 ROJECT: SQN            UNIT/CYCLE                2/.I3                                                              75 °F CALIBRATION BLOCK NO.j_i_Q_!l2_ TEMP:_
'ROCEDURE:    N-UT-64      REV:                TC:
SIMULATOR Rl.orK:Rompas TRANSDUCER THERMOMETER S/N 573203                DUE DATE 8-9-05 MANUFACTURER: RTD COI!PLANT: Ultragel II              BATCH: 01225 S/N: 99-431                                    ANGLE VERIFICATION MODEL: TRLA 8x14mm                    FREQ:                2 MH      BLOCK TYPE:      Rompas SIZE:
SHAPE: f&#xa3;cT      U ELEMENTS: 2              SCONS: 0_            NOMINAL ANGLE: 60&deg;                  ACTUAL ANGLEj___60_l INSTRUMENT CABLE TYPE: RG-174              LENGTHl6' MANUFACTURER: Krautkramer                DUE DATE: J^rllP EXAM TYPE      D SHEAR              LONG                RL MODEL NO.:        OSti' 6 0          _ M&TE:^63OI DAC                                                        INSTRUMENT SETTINGS 100                                                                  REFLECTOR                REFERENCE      MEMORY 1                                                          SENSITIVITY    NUMBER A        SCAN DIRECT. NTC ! SDH 80      1 1  '* o"                      M          AXIAL                                62        1USS60 P        CIRC.              i            i\/A dB L      *FREO      2<  o        MHz    ^REJECT:
60 ANC! Ft            60 deg      "DAMPING: 1QQQ      ohms I
40 i              T      DELAY            0.000  msec    *PULSER    DUAL U      ZERO:          8.5591  msec 20                                                  D      VELOCITY        .2329  msec    TOF:      PEAK 1
E      RANGE:          3.500 inches    POWER:    BATTERY 1                1 0                                                          *DISP. MODE: FW TCG: Q ON B"OFF 3.5 inches                                        H DISPLAY WIDTH, 62 dB                        CALIBRATION TIMES REF. REFLECTOR:          FAR SDH GAIN:.
INITIAL TIME:    1045          FINAL TIME:  1412 AMPLITUDE:        90 %  METAL PATHj_L12
: 2)        N/Ali)    N/A] 4)  N/A 5)    N/A  6)    N/A  7)                      N;A
                                    *PDl QUALIFIED INSTRUMENT SETTINGS:
VERIFY INSTRUMENT SETTINGS AND CALIBRATION SEQUENCE ARE IN ACCORDANCE WITH TABLE 2 OF THE APPLICABLE PDI QUALIFICATION IMPLEMENTATION PROCEDURE!
ATTENUATOR]      AMP WELD / ITEMS EXAMINED
[REVIEWER:
ACCESS FORM
 
TENNESSEE                    MANUAL ULTRASONIC                                REPORT NUMBER VALLEY                        PIPING EXAMINATION AUTHORITY A-U93 DATA SHEET UNIT/CYCLE          2 I 13          EXAMINATION HATE            4/29/05 ROJECT:      SQN SYSTEM      SIS                                                    START TIME:      1215            END TIME: 1345 EXREQ:      S9E-02      CAT: R-A          ITEM NO: Rl.II EXAM SURFACE:          DID WELD I.P.: SIT-170                                                                                  gSS      QCSCL    Q CCSS MATERIAL TYPE:
CONFIC:        PC.VLV              TO    PE.EL SURFACE TEMP.        80          PYRO NO. 573203 NlK                                            45  DEC      60RL  DEC PROCEDURE: N-UT-64            REV:      7    TC:                EXAMINATION ANGLE AXIAL SCAN SENSITIVITY                  43 dB          62 Wo RFFFRENCE:          WELD CENTER LINE Lo
 
==REFERENCE:==
TDC                                          CIRC. SCAN SENSITIVITY                  43 dB          N/A dB AT MAX AMP            MAX    EXAM                        INDICATION INFORMATION:
L (in) FROMIREF.                                                NOM.      NRI IND                                                  AMP    NO.
ANG.              TYPE, DAMPING, ETC.
NO. L1    LMax    L2    W MAX  MP MAX D MAX      % DAC    3-14 45 45 Counterbore 15"      18"  21"    1.10      1.1      N/A      100            60
 
45 REMARKS/LIMITATIONS No scan 3 due to Valve confa    atiot  Mainatined 10% ID roll    No Reject able Indications S &< (>
 
WALL THICKNeCY                                              REPORT NO:
TVA PROFILE          SHEET PROJECT:.            SON                                WELD NO:            S \F -HO UNIT:                                                    SYSTEM:
Weld
* Weld Edg Record  Thickness Measurements As Centerline Indicated,  Including  Weld Width, Edge-To-Edge    At 0/                                    -2.5"          [*<<          2.5M-Position            9 0* 180*  270*
                              \                      Side
                  \A            \
1.01 C3              I.OB        \                      y Flow,
                                  .'0                    DIAMETER:
10 CROWN    HEIGHT:
SH.
CROWN    WIDTH:_                                      WELD  LENGTH:.
FLOY/
ANII:
EXAMINER:.                                REVIEWED BY:.
LEVEL:_
LEVEL:            DATE:
DATE:
Ty            PAGE .      . OF_
TVA
 
                                                            /wmiL TENNESSEE                    EXAMINATION REPORT NUMBER:
VALLEY                         
 
==SUMMARY==
 
AUTHORITY                          AND PROJECT: SQ>\        UNIT:    2    CYCLE:  13    COMPONENT ID: SlF-170 DESCRIPTION/
LOCATION:
EXAMINATION METHOD                    SYSTEM: SIS      ISI DWG NO: ISI-0002-C-06 MT            PT            UT        VT                CONFIGURATION            CATEGORY PROCEDURE: N-UT-64            REV: 7      TC  N/A            PC,VLV TO      PE,EL            R-A EXAMINER:                      EXAMINER:              EXAMINER:                EXAMINER:
JLL 71 LEVEL:                      LEVEL:                LEVEL:                      LEVEL:
Total coverage calculated to be approximately The above mentioned weld was ultrasonically inspected. A 1/2 V path calibration with a primary angle of 45 shear wave. This was a single sided exam, due to valve configuration, and a 60 Rlr J/2_
Vpath calibration was also utilized.
Counterbore geometry was recorded with the 60 RL on the intradose of the elbow.
No rejectable indicatins observed.
This examination meet the requirments of Risk Informed item R1.16 RESOLUTION                            REVIEWED BY                      ANII:
c LEVEL          DATE                                                      Page:  /    OF ACCESS FORMS DATABASE R-3/18/03 EZ' 8
 
TENNESStE                          DIGITAL ULTRASONiO                                REPORT NUMBER VALLEY                                      CALIBRATION AUTHORITY DATA SHEET CALIBRATION DATE:          4/29/Q5 ROJECT: SQN                    UNIT/CYCLE                  2/ 13 CALIBRATION BLOCK NO.: ^                '*7 TEMP:      75 &deg;F ROCEDURE:          N-UT-64          REV:        ?      TC:
SIMULATOR BLOCK:Rompas                  7 277 0 TRANSDUCER MANUFACTURER: K.BA                                                        THERMOMETER S/N 573203                DUE DATE    8-9-05 COUPLANT: Ultragel II                BATCH: 01225 MODEL: COMP-G                                  S/N:00D8KH ANGLE VERIFICATION SIZE:    .375"                                FREQ:                MH    BLOCK TYPE:      Rompas        s/N: 792770 SHAPE: Round          # ELEMENTS: 1                    # CONS:    0_        NOMINAL ANGLE: 45&deg;                  ACTUAL ANGLE:      45&deg; CABLE TYPE: RG-174                          LENGTHl6'                                            INSTRUMENT MANUFACTURER: Krautkramer                DUE DATE: 7/28/05 EXAM TYPE              SHEAR                      LONG          D RL DAC MODEL NO.:                (, 0        M&TE:/r36302 INSTRUMENT SETTINGS 100                                                                            REFLECTOR i                                                                          REFERENCE      MEMORY A      SCAN DIRECT. NTC      SDH      SENSITIVITN    M'MBER 80 a"
S M                                u N  0Tcf<    l                        AXIAL                                31          1KSS45 P        CIRC          n                  N/A 60                                                            L      *FREO      2. O        MHz      *REJECT:          0 %
l 1
i I    ANHLF:                45 deg      'DAMPING:/000        ohms 40                                                              T      DELAY            0.000  msec      *PULSER    SINGLE U      ZERO:          8.0469  msec
                                                                                                              *PRR/PRF 20                                                              D      VELOCITY        .1257  msec TOF:      PEAK E      RANGE:              2.9 inches    POWER:    BATTERY J    i
                                          !    i                          *DISP. MODE \F W TCG: l_j ON DISPLAY WIDTH                              2.9 inches REF. REFLECTOR:                  FAR SDH          GAIN:          43 dB                      CALIBRATION TIMES AMPLITUDE:            35 %      METAL PATH:              1.096            INITIAL TIME:    1040          FINALTIME:    1410 VERIFICATION TIMES                j Xh2nS                N/A I      N/A  4'  n/a!5)    n/a!6>                          N/A l
                                                *PD1 QUALIFIED INSTRUMENT SETTINGS:
VERIFY INSTRUMENT SETTINGS AND CALIBRATION SEQUENCE ARE IN ACCORDANCE WITH TABLE 2 OF THE APPLICABLE PDI QUALIFICATION IMPLEMENTATION PROCEDURE!
LINEARITY CHECK COMMENTS                                                      WELD / ITEMS EXAMINED sir- no EXAMINER:                                                                                          ANil:
PAGE    ^L    OF ACCESS FORMS QATABASE 10-02-03 E2- 1
 
                                                                                    ,#*,
Tennessee                      DIGITAL ULTRASOIW REPORT NUMBER VALLEY                                  CALIBRATION AUTHORITY DATA SHEET CALIBRATION DATE:          4/29/03 PROJECT: SQN                  UNIT/CYCLE CALIBRATION BLOCK NO,: S<2 - u7 TEMP:_                  75 &deg;F PROCEDURE:        N-UT-64            REV:      7 SIMULATOR BLOCK:Rompas                77277Q TRANSDUCER MANUFACTURER: RTD                                                    THERMOMETER S/N 573203                DUE DATE    8-9-05 MODEL: TRLA                                SAN: 99-43 I            COUPLANT: Ultragel II                BATCH: 01225 ANGLE VERIFICATION -
SIZE:  8xl4mm                            FREQ:            2 MH      BLOCK TYPE:        Rompas      s/N:  792770 SHAPE: \ZBct        U ELEMENTS: 2                # CONS: 0            NOMINAL ANGLE: 60&deg;                  ACTUAL ANGLE_:__60_&deg;.
CABLE TYPE: RG-174                      LENGTHl6"                                            INSTRUMENT MANUFACTURER: Krautkramer                DUE DATE: 7/28/05 EXAM TYPE        SHEAR                  LONG            B RL MODEL NO.:
DAC INSTRUMENT SETTINGS uu 1                                            REFLECTOR REFERENCE        MEMORY A      SCAN DIRECT. ,  NTC l SDH      SENSITIVITY      NUMBER 80                            t ' 0
* M 4
No]
AXIAL                                62        IUSS60*
P 1                                                          CIRC.                  D          N/A dB 60                                                        L      *FREQ          2. 0    MHz
* REJECT          0_ %
I      ANCLF:              60 deg      '*DAMPINC;/Q00        ohms 40                                                        T      DELAY            0.000  msec    *PULSER      DUAL U      ZERO:            8.5591 msec 20                                                        D      VELOCITY          .2329  msec    TOF:        PEAK E      RANGE:            3.500 inches    POWER:      BATTERY' 0
                                                                        *DISP. MODE: F W TCG:    ON DISPLAY WIDTH                          3.5 inches
                                                                                        \1\C~H REF. REFLECTOR:                FAR SDH        GAIN:_        62 dB                      CALIBRATION TIMES AMPLITUDE:          90 %      METAL PATH:            1.531          INITIAL TIME:      1045        FINAL TIME:    1412 VERIFICATION TIMES                I M>l3 3o 2)      N/a13>      N/a!4)  N/aI 5)    N/aI6)      N/a!7>    N/aI8>    N/A I9>    N/A
                                              *PDI QUALIFIED INSTRUMENT SETTINGS:
VERIFY INSTRUMENT SETTINGS AND CALIBRATION SEQUENCE ARE IN ACCORDANCE WITH TABLE OF THE APPLICABLE PDI QUALIFICATION IMPLEMENTATION PROCEDURE!
LINEARITY CHECK SIGNAL 2 GAIN l      SET AMP        80%
COMMENTS                                                    WELD /ITEMS EXAMINED SIF-170 p.sPiAY EXAMINER: LtAt-w/^^X-^
ACCESS FORMS DATABASE 1Q-O2-O3 IO
 
TENNESSEE                    MANUAL ULTRASONIC                                REPORT NUMBER VALLEY                        PIPING EXAMINATION AUTHORITY DATA SHEET PROJECT:        SQN              UNIT/CYCLE        2 I 13          EXAMINATION DATE            4/29/05 SYSTEM        SIS                                                  START TIME:      1315            END TIME:  1345 EXREQ:      89E-02        CAT: R-A          ITEM NO: RI.16 EXAM SURFACE:          Q'D      BOD WELD I.P.: SIF-170 MATERIAL TYPE: QCS              &#xa3;SS    QCSCL QCCSS CONFIG.:        PQVLV                  TO  PE.EL SURFACE TEMP.        80          PYRO NO. 573203 FLOW^
PROCEDURE: N-UT-64              REV:      7    TC:                EXAMINATION ANGLE                    45  DEC.      60 RL  DEC.
Wo
 
==REFERENCE:==
WELD CENTER LINE                            AXIAL SCAN SENSITIVITY                  43 dB            62 Lo
 
==REFERENCE:==
TDC                                        CIRC. SCAN SENSITIVITY                  43 dB            N/A L (in) FROM REF.            AT MAX AMP          MAX  EXAM IND                                                                    NOM.              INDICATION INFORMATION:
AMP    NO.              NRI NO. L1    L Max  L2    WMAX    MPMAX DMAX                        ANG.              TYPE, DAMPING, ETC.
                                                      % DAC    3-14 45 45 18"  21"      1.10      1.1    N/A      100 15"                                                                60 counterbore 45 REMARKS/LIMITATIONS No scan 3 due to Valve configuration. Mainatined 10% ID roll    No Reject able Indications EXAMINER:                                                                                      ANH: A.
(EXAMINER:                                                                                      DATE REVIEWED BY:          T7fi                          LEVEL:77T        DATE    S/j/of          PAGE      M    OF    &
ACCESS FORMS DATABASE 10/02/03 EZ -
 
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REPORT NO:
WALL THICKNESS PROFILE        SHEET PROJECT:,              SQN                                  WELD NO:          S If -
UNIT:                                                      SYSTEM:
Record Thickness Measurements As                                          Weld
* Weld Ed Indicated,    Including  Weld Width,                                  Centerllne Edge-To-Edge At 0*
Position              9 0* 18 0*  270*
                              \              T
                    \1    "lA    A
                          '.06        \
i.a CROWN      HEIGHT:                .'0 DIAMETER:            10' CROWN      WIDTH: _              I.I'                  WELD  LENGTH:.
3H. 15"'
V At-V &#xa3; EL&
FLOW
                                                        ?>                        ANII:
REVIEWEO BY: h LEVEL: <              rii/t>b^
oS                                                  PAGE ,  . OF.
TVA 196^8 (NP-5-89)
 
ENCLOSURE 3 ISI PROGRAM DRAWINGS Request for Relief Number      ISI Program Drawings 1-ISI-28                    ISI-0504-C-02 2-ISI-28                    ISI-0298-C-02 1-ISI-29                    ISI-0504-C-02
      . 2-ISI-29                    ISI-0298-C-02 1-ISI-30                    ISI-0504-C-02 2-ISI-30                    ISI-0298-C-02 1-ISI-31                    ISI-0504-C-02 2-ISI-31                    ISI-0298-C-02 2-ISI-33                    ISI-0002-C-06 E3-1
 
REFERENCE DRAWINGS A-7541 2-SI-507-1W 2-SI-510-1W 2-0R-63-552 SI-2093C SI-20930 SI-2O98 SI-2O97 63-634 SI-2096                                                                                                  63-634-9C SlS-273 SIF-153-POINT B FAN  ROOM NO, 4 3561 63-561-BC REACTOR BUI SIF-169  LOWER CONTAINMENT
                                                                                          ^SIS-280 J0X1QX6 8 mX8 mX6 '
REACTOR BUILDINC                                  RED. TEE ACCESS ROOM                                                SIF-173 SIS-4 1O FAN ROOM NO. 2 SIF-172A SIF-172 SI-2255B                                            B"X6m RED MATERIAL SPECIFICATIONS SI-225SA-1                                              SIS-266                          ^SIS-272 ACCUMULATOR  ROOM NO S1-22S5                                                                                  SIS-271        ASHE CC-2 (EQUIVALENT)
SI-2253 SIS-267 SI-2252-^,
                                                        -SIS-286              EL .71 8'-3 SI-225i                                              SIF-162              SIS-268 1-2250                                                -SIS-285 6'LSCHL160AktL 8'  SCH 140
                                                                                                                                          ~AS' *~40J TP~3n 63-632 3-                                                                              632-9C                                10* SCH 40S (WELDED)
FOR ADDITIONAL SPECS SEE SHFFT 4 SIS-269
                                                                          \ EL.7O2'-O' 2L_ L _-iBL _L    ciw    [_ kr* _j t-24-or
_.._    PIPING WAS EXEMPT
                                                                                        %MET%ECT-%N2xV-L71                      T&#xa3;*HTSSE&#xa3; VALLEY AUTHORtTY SI-2O99 WAS CUT OUT
          ^MADE OUR INC U2C12 O3-010248-000.                                        CONTINUED                                                                Nuclear plani AT  POINT C SAFETJ INJECTION SrSTEM WELD LOCATIONS SI-0OQ2-C-O6
 
REFERENCE DRAWINGS IS1-0297-A OUTLET NOZZLE I SI-0392-A INLET NOZZLE CONTRACT NO.            68C60-91934 (N2M-2-3)
FJG. 7-25 DWC NO.        306t6-t050(FlG 7.18)
MATERIAL SPECIFICAT 1ONS~\_                                      a W06                                                            THE VESSEL SHELL SECTIONS ARE MACHINED^
FORCINGS FABRICATED OF A-508. CLASS 2.
MANGANESE-MOLYBDENUM STEEL AND ARE CLAD WITH WELD DEPOSITED AUSTEN 1 TIC                                    1 STAINLESS STEEL.
OUTLET NOZZLE CLADDING                                    INLET NOZZLE CLADDING        THE VESSEL FLANGE SECTION IS FABRICATED '
N15CLAD                                    NttCLAD                      OF A-508, CLASS 2. MANGANESE-MOLYBDENUM
                                                                                                                                                                          )
Nt6CLAD                                    NI2CLAD                      STEEL AND IS CLAD INTERNALLY AND ON THE NI7CLAD      ^^^                  0ZZZT                                GASKET FACE WITH 'WELD DEPOSITED AUSTEN I TIC STAINLESS STEEL.
NtaCLAD THE LOWER-HEAD SECTIONS ARE FABRICATED s~ outlet nozzle welds. -                                                                OF A-533. GR.B. CLASS f, MANGANESE-(reactor vessel coordinates                                                              MOLYBDENUM STEEL.                AND ARE CLAD            WITH WELD
    ^^_^ N15 - 22&deg;                                                  INLET NOZZLE WELDS.,
DEPOSITED AUSTEN I TIC STAINLESS STEEL.
N16 - 158&deg;                    UPPER MIDDLE (REACTOR VESSEL COORDINATES N\7 - 202&deg;    W05                                                                  K        fjfl -- 67&deg; Ntt    67&deg; SHELL                                        THE NOZZLE FORCINGS ARE FABRICATED OF N18 - 338&deg;    SEE NOTE                                    N12 - 113&deg; Nt3 - 247&deg;          A-508.      CLASS 2.        MANGANESE-MOLYBDENUM N14 - 293&deg;          STEEL AND ARE CLAD WITH WELD DEPOSITED AUSTENITIC STAINLESS STEEL.
W04-05 SEE NOTE  I                                                    EACH NOZZLE SAFE END WELD IS A STAINLESS STEEL TYPE 304 WELD BUILD UP (BUTTERING) 00                                            LOWER MIDDLE                                    ASME CC-1          (EQUIVALENT)
SHELL WO3-04  -
SEE NOTE    f NOTES:
VESSEL INSIDE SURFACE )                t. W03-04. W04-05, St W05-06 ARE CLAD 0.157" NOMINAL    J                    8ELTLINE REGION WELDS W02                                                                                                        2. FOR UNIT          1 DWG. SEE CHM-2343-C.)
A  / SIX ORANGE PEEL  WELDS  ,
A (REACTOR VESSEL COORDINATES V        W2A - 0&deg; W2B -60&deg; W2C - 120&deg; W2D - 180&deg; WOI-02                                                                                                                                )
W2E - 240&deg; W2F - 300&deg; j_              I            [              [
OiAHGll DHAtlNG DHAtlNG NO. an0~SI/1 fftOU B W C. ADD VAl 'i SMCS, Cl AD OJUiHSlQH.
SlQH. AND ADD    -HlACtQfi  VfSsYl COOhOlHAllS'    10 HO/flf  it I OS
                                                                                                    ^"11                  _ JCC^      I    ClB_      [ _ ^2+/-'92 AND ADD NO//LC RlftfiiNCL      OHaHnCS suauur[D~\    APpRoveo    I    oaic 1CNNESSEE      VALLEY AUTHORITY SEQUOYAH              NUCLEAR            PLANT UNIT 2 Hi AC 1 OR    VESSEL btAM    Wf.LUS
[CAV UA IN 1A INtD ONA VINC
                                                                                                                                  -029d -C-0~2                    \02
 
REFERENCE DRAWINGS CONTRACT NO,        68C60-9f034          (N2M-2-3)
FIG. 7-25 DWG NO. 3O616-1O5O(F1G 7.18)
MA TERIAL    SPECIFICATIONS THE VESSEL      SHELL      SECTIONS ARE MACHINED FORGINGS FABRICATED OF A-509,                  CLASS 2.
MANGANESE-MOLYBDENUM STEEL AND ARE W06                                    CLAD WITH WELD DEPOSITED AUSTEN I TIC STAINLESS STEEL, THE VESSEL      FLANGE SECTION            IS FABRICATED OF A-508.      CLASS 2.      MANGANESE-MOLYBDENUM STEEL AND IS CLAD INTERNALLY AND ON                        THE INLET NOZZLE CLADDING      GASKET FACE WITH WELD DEPOSITED OUTLET NOZZLE CLADDING -                                      AUSTEN I TIC STAINLESS STEEL.
NltCLAD NI5CLAD NI2CLAD NI6CLAD                                        THE LOWER-HEAD SECTIONS ARE FABRICATED NI3CLAD NI7CLAD                                        OF A-533. GR.B. CLASS t, MANGANESE -
N14CLAD Nt8CLAD                                        MOLYBDENUM STEEL.          AND  ARE    CLAD    WITH    WELD DEPOSITED AUSTENITIC STAINLESS STEEL.
OUTLET NOZZLE WELDS.
REACTOR VESSEL COORDINATES                INLET NOZZLE WELDS. THE NOZZLE FORGINGS ARE FABRICATED OF Nt5 - 22&deg;                                              A-508. CLASS 2.      MANGANESE-MOLYBDENUM REACTOR VESSEL COORDINATES N16 - 158&deg;                            Nil - 67&deg;        STEEL AND ARE CLAD WITH WELD DEPOSITED N17 - 202&deg;    W05-06                                  AUSTENITIC STAINLESS STEEL.
NI2 - tf3&deg; Nt9 - 338&deg;                            Nt3  - 247&deg;      EACH NOZZLE SAFE END WELD                IS A STAINLESS N!4  - 293&deg;      STEEL    TYPE 304      WELD BUILD UP (BUTTERING)
ASME CC-f      (EQUIVALENT)
NOTES:
: 1. W03-04. W04-05. k W05-06 ARE VESSEL  INSIDE SURFACE              BEL TL1NE REGION WELDS CLAD  0.157' NOMINAL
: 2. FOR UNIT 2 DWG.          SEE ISI-0298-C
: 3. THIS DWG SUPERCEDES CHM-2343-C-02 SIX ORANGE PEEL WELDS REAC10R VESSEL COORDINATES W2A - 0&deg; W2B -60&deg; W2C - 120&deg;        WOt-02 W2D - 180&deg; W2E - 240&deg; W2F - 300&deg; BY  l  CHCCKFD  \SU&HlTUD\ APPROVED \
1ENNESSLL    VALLtr AU1H0H1TY SEQUOYAH            NUCLEAR          PLANT UNIT        1 REACIOR      VCSSEt SFAM  WELDS DA ft:          I    SCALf:  NO I  !O SCALE APPROVfD:        \Ca'J HdAlNlAUii'O QRAiTlNC\
J ~ST~- O 50 '4 -C -0 2              TOO
 
ENCLOSURE 4 TVA'S PROCEDURE FOR CALCULATION OF THE ASME CODE COVERAGE FOR SECTION XI REQUEST FOR RELIEF 2-ISI-33 E4-1
 
NONDESTRUCTIVE EXAMINATION PROCEDURE                      Procedure No. N-GP-28 TVA Nuclear Power                              Revision 4 Page 1 of 8 W47 031219 000                                                    QA RECORD CALCULATION OF ASME CODE COVERAGE FOR SECTION XI NDE EXAMINATIONS "QUALITY RELATED" Prepared By:      Robert E. Hardawav                                Date:      12/18/03 Technical Review:  Joel W. Whitaker NDE Level III, Date: 12/18/03 ISO Approval:          W. Ed Freeman                              Date:      12/18/03
 
NONDESTRUCTIVE EXAMINATION PROCEDURE                      Procedure No. N-GP-28 TVA Nuclear Power                                Revision 4 Page 2 of 8 Rev. No.      Date                  Description 0          4/3/96                Initial issue.
1          8/15/97              Incorporate TC 97-09.
2          10/18/00              General revision to incorporate 10CFR50.55a ruling change which implements Appendix VIII 5/24/01              Revised to upgrade procedure to ASME Section XI 1995 Edition with Addenda through 1996 12/18/03              Revised to incorporate corrective actions from PER 03-014859-000.
                                    &#xa3;4-3
 
NONDESTRUCTIVE EXAMINATION PROCEDURE                              Procedure No. N-GP-28 TVA Nuclear Power                                    Revision 4 Page 3 of 8 The scope of this procedure is to provide generic guidelines for calculating the ASME Section XI code coverage and augmented examination coverage obtained during volumetric and surface examinations. This procedure incorporates the requirements of Code Case N-460 and NRC Information Notice 98-42. This procedure is not applicable for calculating the examination coverage for RPV examinations performed in accordance with Appendix Vlll.
2.0 Purpose This procedure applies to the calculation of ASME Section XI Code coverage for vessel welds (excluding the RPV welds performed in accordance with Appendix Vlll) piping welds, and integral attachments. This procedure applies when performing surface, volumetric or visual examinations and may be used as a guide when calculating the examination coverage for preservice and inservice examinations. Coverage limitations may be due to an obstruction, interference, geometric configuration or other applicable reason.
3.0 References 3.1      ASME Code Case N-460 3.2      10CFR 50.55a, as amended by the Federal Register Notice, Vol. 64, No. 183, dated September 22, 1999 (Final Rule)- Implementation of Appendix Vlll as executed by the Performance Demonstration Initiative (PDI) Program Description Document, Rev. 1, Change 1.
3.3      Guideline for the Implementation of Appendix Vlll and 10CFR 50.55a, Rev. D, April 18,2000 3.4      NRC Information Notice 98-42 3.5      SQN PER 03-014859-000 4.0 Definitions 4.1      Examination Coverage- The percentage of the examination surface or volume obtained during the performance of the examination.
4.2      Examination Surface- The surface of the weld and base material required to be examined by ASME Section XI or other requirement using a surface and/or visual examination method as applicable.
4.3      Examination Volume- The volume of weld and base material required to be examined by ASME Section XI or other requirement using a volumetric examination method.
4.4      Scan Limitation- the inability to scan the surface(s) as required by procedure due to interferences.
4.5      Surface Limitation- the inability to perform a surface examination of the required surface(s) because of an interference.
                                              &#xa3;4-4
 
NONDESTRUCTIVE EXAMINATION PROCEDURE                            Procedure No. N-GP-28 TVA Nuclear Power                                  Revision 4 Page 4 of 8 4.6    Volumetric Limitation- the inability to examine the required volume because of the geometric configuration, a physical interference, or a metallurgical condition of the material being examined.
5.0 General 5.1    During the performance of inservice inspections, ASME Section XI requires examination coverage to be essentially 100% of the weld area or volume. For examination coverage less than 100%, TVA has implemented ASME Code Case N-460 which states that when the entire examination volume or area cannot be examined due to interference by another component or part geometry, a reduction in examination coverage for Class 1 or Class 2 welds may be accepted provided the reduction in coverage for that weld is less than 10%. (NRC Information Notice 98-42 further defines the >90% rule to include all welds and other areas required by ASME Section XL 5.2    Surface and/or visual examinations are typically conducted on the weld area plus a defined amount of base material on each side of the weld. Volumetric examinations specify a particular volume to be examined. The Section XI required examination volume or surface examination area for each type of weld is depicted in figures of IWB-2500, IWC-2500 and IWD-2500 as applicable. As depicted for piping welds, volume width generally constitutes the weld plus 1/4t on each side while volume thickness generally constitutes the lower 1/3 of the piping thickness for the length of the weld. The exception normally includes code category B-0 which includes the weld plus 1/2 inch and full volume for the length of the weld. As depicted, for vessel welds, the volume width generally constitutes the weld plus 1/2t on each side of the weld while volume thickness generally constitutes the entire component thickness (i.e. full volume). The volume changes with variations in weld configuration (e.g. transition between different pipe thickness or vessel weld configurations).
Note: Risk-Informed (Rl) programs require larger volumes in certain areas.
5.3    The required examination volume or area shall be verified prior to calculation of the limitation.
6.0 Documenting and Calculating Examination Coverage 6.1    While performing a visual, surface or ultrasonic examination, the NDE Examiner shall make every attempt to examine 100 percent of the examination area or volume.
6.2    When practical, the two beam path directions for ultrasonic examinations should be performed from two sides of the weld or additional angles employed in order to maximize coverage.
6.3    If 100% percent of the examination surface or volume cannot be examined, the NDE Examiner should perform the following under the direction of the inspection coordinator or the NDE Level III:
6.3.1    Perform additional examinations with higher angles in order to maximize cover for ultrasonic exams.
6.3.2    Perform another surface method (i.e., PT in lieu of MT) in order to maximize coverage.
 
NONDESTRUCTIVE EXAMINATION PROCEDURE                              Procedure No. N-GP-28 TVA Nuclear Power                                      Revision 4 Page 5 of 8 6.3.3    Perform alternative NDE methods if applicable.
6.4    The examiner shall accurately document all limitations, obstructions, interferences, geometric configurations or other applicable reasons for not obtaining the required code coverage. This information shall be validated and verified by the assisting examiner or independent verifier and documented in the NDE data report.
6.5    The examiner shall document the limitation on a sketch. Examination coverage estimates may be performed by the examiner or the reviewer.
7.0 Calculation Basis 7.1    Volumetric Examinations- Piping Welds and Vessels 2 inches and less in thickness a)    Examination volume coverage may be increased as previously discussed or by use of refracted longitudinal wave techniques on stainless steel or dissimilar metal welds. Use of refracted longitudinal waves to penetrate stainless steel weld material will increase the examination volume coverage by the amount depicted on the examination coverage drawing.
b)    Estimates shall be derived by estimating coverage based on two-beam path direction coverage of the complete examination. Each scan direction equals 25% (downstream, up-steam, clockwise, counterclockwise.)
(Reference Figure 1) c)    The effects of adjacent component interferences (e.g. welded lug attachments) along the weld length are also taken into account with the reduction in coverage identified as a percentage of reduced volume.
8.0 Visual and Surface Examinations - Piping Welds And Integral Attachments 8.1    Examination area coverage calculations are based upon one of the following suppositions:
a)    The total examination area is calculated, typically length x width, then the total area of limitation or interference is subtracted from the total examination area.
b)    The area of achieved coverage is divided by the total examination area for percentage of examination achieved.
9.0 Ultrasonic Examinations - Vessel Welds
 
NONDESTRUCTIVE EXAMINATION PROCEDURE                              Procedure No. N-GP-28 TVA Nuclear Power                                    Revision 4 Page 6 of 8 NOTE: THIS IS NOT APPLICABLE FOR APPENDIX VIII EXAMINATIONS OF THE RPV WELDS.
9.1      Examination volume coverage calculations are based upon the following suppositions:
a)    To achieve full examination coverage nine different scans are required for a typical vessel weld or nozzle examination. The following may be .used for other vessel configurations:
: 1)      0 degree (weld metal scan)
: 2)    45 degree Transverse-scan from vessel side of the weld
: 3)    45 degree Transverse-scan from nozzle side of the weld
: 4)    60 degree Transverse-scan from vessel side of the weld
: 5)    60 degree Transverse-scan from nozzle side of the weld
: 6)    45 degree Parallel-scan CW direction
: 7)    45 degree Parallel-scan CCW direction
: 8)    60 degree Parallel-scan CW direction
: 9)    60 degree Parallel-scan CCW direction 9.2    The examination volume achieved for each above examination scan shall be obtained and documented on a percentage basis. This calculation considers the required examination volume required per the ASME Section XI Code.
a)  The total examination coverage may be calculated by averaging the exam volume coverage for all nine scans.
10.0 PDI Implementation for Piping Welds 10.1    Where examination from both sides is not possible, full coverage credit may be claimed from a single side for ferritic welds provided the examiner is qualified for single sided examination. Current technology is not capable of reliably detecting or sizing flaws on the far side of an austenitic weld for configurations common to US nuclear applications. Therefore, examination of austenitic material welds shall be performed from both sides or a scan limitation shall be documented.
10.2    The NDE Level III shall make an evaluation in the Weld Resolution document regarding total examination coverage (best effort) as calculated above in Section 7.0. In addition, a coverage evaluation which considers the PDI Implementation Guideline shall also be indicated in the Weld Resolution sheet. These two coverage evaluations shall be reported to the ISI Programs Engineer for incorporation into the Relief Request.
10.3    Typically a one-sided austenitic weld examination with no circumferential restrictions would be indicated as 75% examination coverage or 50% if circumferential scans were limited to one side.
NOTE: These requirements do not apply to augmented examinations of piping welds.
11.0 Responsibilities
 
NONDESTRUCTIVE EXAMINATION PROCEDURE                            Procedure No. N-GP-28 TVA Nuclear Power                                    Revision 4 Page 7 of 8 11.1  The examiner, assisting examiner or designee shall document the amount of code coverage obtained after all necessary steps to perform additional examinations has been completed in order to maximize coverage. The documentation including verification of limitations shall become part of the examination weld data package.
11.2  The documentation may be reviewed by another individual with the same or higher NDE certification.
11.3  The NDE Level III or data reviewer may review the calculations in order to verify that the information is accurate and correct.
11.4  The NDE Level Hi may recalculate the examination coverage to obtain a more accurate value of the examination surface or volume examined. The calculation shall be documented on the exam report.
11.5  The NDE Level III may require an alternate examination technique or method, or request that the interference be removed. For nozzle examinations, supplemental scans from the nozzle bore or flange face may provide complete coverage of the weld.
11.6  If the examination coverage indicates less than 90 percent of the required examination volume or surface, the site ISI Program Engineer shall be notified.
11.7  The site ISI supervisor shall- ensure that examination results are accurately documented and incorporate results into a Request for Relief if necessary.
                                        &#xa3;4-$
 
                                                                                            .^W^k NONDESTRUCTIVE EXAMINATION PROCEDURE                                                        Procedure No. N-GP-28 TVA Nuclear Power                                                          Revision 4 Page 8 of 8 IH-3230                                              APPENDIX IB  MANDATORY                                                          IH-3310 Interference between shoe and weld crown GENERAL NOTE:
For this example of interference with a VjV examination applied from both sides, only the E-F-G-H portion of the examination volume receives two direction coverage, while volumes C-G-F and H-D-E receive one direction coverage. In this case, the examination beam path shall be inaeased to HV {0.0. to 1.0. and back towards O.D. for V7t) to provide the required two direction coverage over the examination volume. Use of a %V examination beam path (O.D. to I.D. to Vif) provides additional beam path (past %f) to help in obtaining required coverage when examination part thickness f increases.
FIG. 111-3230-1 EXAMPLE OF PHYSICAL RESTRICTIONS TO THE WELD EXAMINATION Figure 1
                                                            &#xa3;4-
 
ENCLOSURE 5 ISwT EXAMINATION AREA COVERAGE REPORT FOR SON UNITS 1 AND 2 REACTOR VESSEL WELDS REQUESTS FOR RELIEF 1.2-ISI-28, 1.2-ISI-29, 1.2-ISI-30 AND 1.2-ISI-31 Request for Relief Number          Area of Coverage Report 1-ISI-28                            R8386 2-ISI-28                            R6761 1-ISI-29                            R8386 2-ISI-29                            R6761 1-ISI-30                            R8386 2-ISI-30                            R6761 1-ISI-31                            R8386 2-ISI-31                            R6761 E5-1
 
APPENDIX E RPV EXAMINATION COVERAGE REPORT ES-Z
 
EXAMINATION AREA COVERAGE REPORT FOR SEQUOYAH NUCLEAR PLANT UNIT 2 This  appendix    describes  examination  coverage  achieved    during  the  2005 in-service inspection of the Sequoyah Nuclear Plant Unit 2 (SQN2) reactor pressure vessel (RPV).              The examinations were performed using automated ultrasonic (AUT) scanning equipment and AUT data recording/analysis systems. The target scope of the RPV examinations included 100 percent of the accessible weld and/or component length of the following:
: 1)      Circumferential shell welds, including the vessel shell to flange weld
: 2)      Lower head meridional shell welds
: 3)    Nozzle to shell welds
: 4)    Nozzle to Safe End and Safe End to Nozzle Welds Limitations were encountered at SQN2 while examining the vessel, nozzle to shell, and lower head shell welds due to various physical conditions, such as the bottom head penetrations, the core barrel lugs, the outlet nozzle integral extensions, the inlet nozzle inner radii, and the flange configuration. Typically, limitations are not encountered on the nozzle to--safe end and safe end to nozzle welds, except for severe inside surface contour variations, which were not encountered at SQN2.
1        Examination Coverage Requirements for Vessel Circumferential and Meridional Welds The ISwT procedures for shell weld examinations are qualified for both single- and double-sided examinations. The double-sided technique, requiring two examination angles and four search units, is used when access is not restricted. The single-sided examination technique, requiring three examination angles and four search units, is utilized to provide additional coverage when access is restricted. The examination coverage requirements for these techniques are described below.
Single-Sided Examination (Reflectors Oriented Parallel and Transverse to the Weld)
: 1)  The inner 3.25 inches including the weld metal and adjacent base metal for lA t either side of the weld fusion line must be completely scanned with both SLIC40 (50 and 70 degrees, shear and longitudinal waves) search units.
: 2)  The weld metal and adjacent base material in the outer volume beyond 3.25 inches must be completely scanned with both 45&deg; and 55&deg; Duplex (45 and 55 degrees shear wave) search units.
Double-Sided Examination (Reflectors Oriented Parallel and Transverse to the Weld)
: 1) The inner 3.25 inches including the weld metal and adjacent base metal for lA t either side of the weld fusion line must be completely scanned with both SLIC 40 search units.
: 2)  The weld metal and adjacent base material in the outer volume beyond 3.25 inches must be completely scanned with both 55&deg; Duplex search units.
                                              &#xa3;- 3
 
r 2        Examination Co *erage Requirements for Nozzle to Shed Welds
      . Examination of the nozzle to shell welds is performed using the techniques described above from the vessel inside surface plus a PDI-qualified Phased Array examination performed from the nozzle bore. Coverage requirements for nozzle to shell weld examinations conducted from the vessel inside surface are similar to those described above, except that the weld metal and adjacent base material for !/z" beyond the weld fusion line must be scanned with the applicable search units. The Phased Array procedure was designed to sweep two sets of sound beam angles (5 through 40 degrees longitudinal wave and 35 through 45 degrees shear wave) through the examination volume from the nozzle bore and achieve full coverage.
3        Examination Coverage Requirements for Nozzle to Safe End and Safe End to Nozzle Welds (Dissimilar Metal Welds)
Examination of the Safe End (Dissimilar Metal) welds is performed using a PDI-qualified Phased Array procedure that is designed to sweep one set of sound beam angles (60-88 degrees longitudinal wave) through the examination volume from the inside surface of the weld to achieve full coverage in four directions.
EXAMINATION COVERAGE CALCULATION The following contains a description of the examination coverage calculation process:
: 1. Determine the examination scan ("x" and uy") coordinates necessary to obtain 100% of the required weld coverage (reference the examination planned "x" and "y" coordinates).
re
: 2. Multiply the delta difference of the planned "x" and "y" coordinates by each other to determine the planned scan area necessary to obtain 100% of the required weld coverage for both transverse and parallel examinations.
: 3. Multiply the delta difference of the actual "x" and "y" coordinates by each other to determine the actual scan area for both transverse and parallel examinations.
: 4. Divide the parallel actual scan area by the parallel planned scan area and the transverse actual scan area by the transverse planned scan area to determine the coverage percentage for each type of examination.
: 5. Compute the average of the parallel and the transverse examination values for the final coverage percentage.
 
Sequoyah Nuclear Power Station, Unit 2 2005 Reactor Vessel Inservice Examination UT Coverage Summary    :.;*..;: w&sect;id  ..,-.. Exam Area          BSifti V      Beam      Beam        Code
*fcUmbgrr;                    ^fidirttififcatioh 'j&                              Direction(s) Coverage                  Remirks /':...,' ' -/;s 000100              W03-04        Lower Shell -to-    SLIC 40/55&deg;      Parallel 2 directions  100%
Lower Middle Shell      SLIC 40/55&deg;    Transverse 2 directions  100%
Average      100%
000200              W04-05    Lower Middle Shell      SLIC 40/55&deg;      Parallel 2 directions  100%
                                  -to- Upper Middle    SLIC 40/55&deg;    Transverse 2 directions  100%
Shell                                    Average      100%
000300              W05-06    Upper Middle Shell      SLIC 40/55&deg;      Parallel 2 directions  82%    Limited examination due to the
                                    -to- Upper Shell    SLIC 40/55&deg;    Transverse 2 directions  100%    outlet nozzle integral extensions and Average      91%    inlet nozzle bore radii.
000400              W02-03        Bottom Head -to-    SLIC 40/55&deg;      Parallel 2 directions  79%    Limited examination due to the Lower Shell      SLIC 40/55&deg;      Parallel 2 directions  75%    proximity of the core barrel stabilizing Average      77%    lugs.
000500              W01-02      Bottom Head Cap      SLIC 40/55&deg;      Parallel 2 directions  51%    Limited examination due to the
                                    -to- Bottom Head    SLIC 40/55&deg;    Transverse 2 directions  57%    bottom head penetrations.
Spherical Ring                                Average      54%
000600              W06-07          Upper Shell      SLIC 40/55&deg;      Parallel 2 directions  91%    Limited examination due to the
                                        -to- Flange      SLIC 40/55&deg;    Transverse 2 directions  95%    flange design.
Average      93%
000900              W2A            Lower Head        SLIC 40/55&deg;      Parallel 2 directions  100%    Limited examination due to the Meridional @ 0&deg;    SLIC 40/55&deg;    Transverse 2 directions  85%    bottom head penetrations and core Average      93%    barrel stabilizing lugs.
001000              W2B            Lower Head        SLIC 40/55&deg;      Parallel 2 directions  100%    Limited examination due to the Meridional @ 60&deg;    SLIC 40/55&deg;    Transverse 2 directions  81%    bottom head penetrations and core Average      91%    barrel stabilizing lugs.
001100              W2C            Lower Head        SLIC 40/55&deg;      Parallel 2 directions  100%    Limited examination due to the Meridional 120&deg;      SLIC 40/55&deg;    Transverse 2 directions  81%    bottom head penetrations and core Average      91%    barrel stabilizing lugs.
001200              W2D            Lower Head        SLIC 40/55&deg;      Parallel 2 directions  100%    Limited examination due to the Meridional @ 180&deg;      SLIC 40/55&deg;    Transverse 2 direction^  83%    bottom head penetrations and core Average      92%    barrel stabilizing lugs.
001300              W2E            Lower Head        SLIC 40/55&deg;      Parallel 2 directions  94%    Limited examination due to the Meridional @ 240&deg;      SLIC 40/55&deg;    Transverse 2 directions  86%    bottom head penetrations and core Average      90%    barrel stabilizing lugs.
001400              W2F            Lower Head        SLIC 40/55&deg;      Parallel 2 directions  84%    Limited examination due to the Meridional @ 300c      SLIC 40/55&deg;    Transverse 2 directions  75%    bottom head penetrations and core Average      80%    barrel stabilizing lugs.
 
Sequoyah Nuclear Power Station, Unit 2 2005 Reactor Vessel Inservice Examination UT Coverage Summary    Weld          Exam Area            Beam            Exam            Beam      Code Number ; Number *  :,fdehtincation^^:^ i Angie(s) i                      Difiecti6h{s)  CbvefagS    '- :v': -      RefnSrks  '"--  ''^
001900    N-15      Outlet Nozzle          SLIC 40          Parallel    2 directions    78%    Limited examination due to the nozzle
                    -to- Shell @ 22&deg;      SLIC 40/55&deg;      Transverse      2 directions    54%    integral extension.
PA-16      Parallel (Bore)    1 direction  100%
Average      72%
001500    N-11        Inlet Nozzle        SLIC 40          Parallel    2 directions    84%    Limited examination due to the nozzle
                    -to- Shell @ 67&deg;      SLIC 40/55&deg;      Transverse      2 directions    100%    inner radius.
PA-16      Parallel (Bore)    1 direction  100%
Average      96%
001600    N-12        Inlet Nozzle        SLIC 40          Parallel    2 directions    84%    Limited examination due to the nozzle
                    -to-Shell 113&deg;        SLIC 40/55&deg;      Transverse    2 directions    100%    inner radius.
PA-16      Parallel (Bore)    1 direction    100%
Average      96%
002000    N-16        Outlet Nozzle        SLIC 40          Parallel    2 directions    78%    Limited examination due to the nozzle
                    -to-Shell 158&deg;        SLIC 40/55&deg;      Transverse    2 directions    55%    integral extension.
PA-16      Parallel (Bore)    1 direction  100%
Average      72%
002100    N-17      Outlet Nozzle          SLIC 40          Parallel    2 directions      78%    Limited examination due to the nozzle
                  -to- Shell @ 202&deg;      SLIC 40/55&deg;      Transverse    2 directions      55%    ntegral extension.
PA-16      Parallel (Bore)    1 direction    100%
Average      72%
001700    N-13        Inlet Nozzle        SLIC 40          Parallel    2 directions      88%    Limited examination due to the nozzle
                  -to- Shell @ 247&deg;      SLIC 40/55&deg;      Transverse    2 directions    100%    nner radius.
PA-16      Parallel (Bore)    1 direction    100%
Average      97%
001800    N-14        Inlet Nozzle        SLIC 40          Parallel    2 directions      82%    Limited examination due to the nozzle
                  -to- Shell @ 293&deg;      SLIC 40/55&deg;      Transverse    2 directions      90%    nner radius.
PA-16      Parallel (Bore)  1 direction    100%
Average      91%
002200    N-18      Outlet Nozzle        SLIC 40          Parallel    2 directions    78%    Limited examination due to the nozzle
                  -to- Shell @ 338&deg;      SLIC 40/55&deg;      Transverse    2 directions    55%    ntegral extension.
PA-16      Parallel (Bore)    1 direction    100%
Average      72%
 
Sequoyah Nuclear Power Station, Unit 2 2005 Reactor Vessel Inservlce Examination UT Coverage Summary    Weld      Exam Area        .:.;:  Beam  J  *;;:;-';v./Exam ., *,,,. ;-^.Ete<<fii;;.:r  Code
                                        ^ Angi&sect;(sj;'.                                            Sdverap ., . , . ' RSm^ks'.; ^.^:-\.
003500  RC-09-SE    Outlet Nozzle            PA 22            Parallel            2 directions    100%
                    -to-Pipe @ 22&deg;            PA 22          Transverse            2 directions    100%
Average        100%
003600  RC-16-SE  Elbow -to- Inlet          PA 22            Parallel            2 directions    100%
Nozzle @ 67&deg;            PA 22          Transverse            2 directions    100%
Average        100%
003700 RC-08-SE  Elbow -to- Inlet          PA 22            Parallel            2 directions    100%
Nozzle 113&deg;              PA 22          Transverse              2 directions    100%
Average      100%
003800 RC-01-SE    Outlet Nozzle            PA 22            Parallel            2 directions    100%
                  -to-Pipe @ 158&deg;            PA 22          Transverse            2 directions    100%
Average        100%
003900 RC-25-SE    Outlet Nozzle            PA 22            Parallel            2 directions    100%
                  -to-Pipe @ 202&deg;            PA 22          Transverse            2 directions    100%
Average        100%
004000 RC-32-SE  Elbow -to- Inlet          PA 22            Parallel            2 directions    100%
Nozzle @ 247&deg;              PA 22          Transverse            2 directions    100%
Average        100%
004100  RC-24-SE  Elbow -to- Inlet          PA 22            Parallel            2 directions    100%
Nozzle @ 293&deg;              PA 22          Transverse            2 directions    100%
Average        100%
004200  RC-17-SE    Outlet Nozzle            PA 22            Parallel            2 directions    100%
                  -to-Pipe @ 338&deg;            PA 22          Transverse            2 directions    100%
Average        100%
 
APPENDIX E RPV EXAMINATION COVERAGE REPORT
 
EXAMINATION AREA COVERAGE REPORT FOR SEQUOYAH NUCLEAR PLANT UNIT 1 This appendix describes examination coverage achieved during the 2006 in-service inspection of the Sequoyah Nuclear Plant Unit 1 (SQN1) reactor pressure vessel (RPV).              The examinations were performed using automated ultrasonic (AUT) scanning equipment and AUT data recording/analysis systems. The target scope of the RPV examinations included 100 percent of the accessible weld and/or component length of the following:
: 1)      Circumferential shell welds, including the vessel shell-to-flange weld
: 2)      Lower head meridional shell welds
: 3)      Nozzle-to-shell welds
: 4)      Nozzle-to-Pipe and Elbow-to-Nozzle Welds Limitations were encountered at SQN1 while examining the vessel, nozzle-to-shell, and lower head shell welds due to various physical conditions, such as the bottom head penetrations, the core barrel  lugs,  the outlet nozzle integral extensions, the inlet nozzle inner radii, and          the flange configuration. Typically, limitations are not encountered on the nozzle-to-pipe and elbow-to-nozzle welds, except for severe inside surface contour variations, which were not encountered at SQN1.
1        Examination Coverage Requirements for Vessel Circumferential and Meridional Welds The ISwT procedures for shell weld examinations are qualified for both single- and double-sided examinations. The double-sided technique, requiring two examination angles and four search units, is used when access is not restricted. The single-sided examination technique, requiring three examination angles and four search units, is utilized to provide additional coverage when access is restricted. The examination coverage requirements for these techniques are described below.
Single-Sided Examination (Reflectors Oriented Parallel and Transverse to the Weld)
: 1) The inner 3.25 inches including the weld metal and adjacent base metal for Vz t either side of the weld fusion line must be completely scanned with both SLIC40 (50 and 70 degrees, shear and longitudinal waves) search units.
: 2) The weld metal and adjacent base material in the outer volume beyond 3.25 inches must be completely scanned with both 45&deg; and 55&deg; Duplex (45 and 55 degrees shear wave) search units.
Double-Sided Examination (Reflectors Oriented Parallel and Transverse to the Weld)
: 1) The inner 3.25 inches including the weld metal and adjacent base metal for Vi t either side of the weld fusion line must be completely scanned with both SLIC 40 search units.
: 2) The weld metal and adjacent base material in the outer volume beyond 3.25 inches must be completely scanned with both 55&deg; Duplex search units.
 
2      Examination Coverage Requirements for Nozzle-to-Shell Welds Examination of the nozzle-to-shell welds is performed using the techniques described above from the vessel inside surface plus a PDI-qualified Phased Array examination performed from the nozzle bore. Coverage requirements for nozzle to shell weld examinations conducted from the vessel inside surface are similar to those described above, except that the weld metal and adjacent base material for V4" beyond the weld fusion line must be scanned with the applicable search units. The Phased Array procedure was designed to sweep two sets of sound beam angles (5 through 40 decrees longitudinal wave and 35 through 45 degrees shear wave) through the examination volume from the nozzle bore and achieve full coverage.
3        Examination Coverage Requirements for Nozzle-to-Pipe and Elbow-to-Nozzle Welds (Dissimilar Metal Welds)
Examination of the Pipe (Dissimilar Metal) welds is performed using a PDI-qualified Phased Array procedure that is designed to sweep one set of sound beam angles (60-88 degrees longitudinal wave) through the examination volume from the inside surface of the weld to achieve full coverage in four directions.                                                                                  &deg; EXAMINATION COVERAGE CALCULATION The following contains a description of the examination coverage calculation process:
: 1. Determine the examination scan ("x" and "y") coordinates necessary to obtain 100% of the required weld coverage (reference the examination planned "x" and "y" coordinates).
: 2. Multiply the delta difference of the planned "x" and "y" coordinates by each other to determine the planned scan area necessary to obtain 100% of the required weld coverage for both transverse and parallel examinations.
: 3. Multiply the delta difference of the actual "x" and "y" coordinates by each other to determine the actual scan area for both transverse and parallel examinations.
: 4. Divide the parallel actual scan area by the parallel planned scan area and the transverse actual scan area by the transverse planned scan area to determine the coverage percentage for each type of examination.
: 5. Compute the average of the parallel and the transverse examination values for the final coverage percentage.
 
Sequoyah Nuclear Power Station, Unit 1 2006 Reactor Vessel Inservice Examination UT Coverage Summary    Weld          Exam Area              Beam              Exam            Beam          Code Number  Number        Identification          Angle(s)            Type        Directions) 000100                                                                                          Coverage                    Remarks l*\
W03-04      Lower Shell -to-        SLIC 40/55&deg;          Parallel      2 directions      100.0%
Lower Middle Shell        SLIC 40/55&deg;      Transverse        2 directions      100.0%
Average        100.0%
000200  W04-05    Lower Middle Shell        SLIC 40/55c          Parallel    2 directions      100.0%
                      -to-upper Middle          SLIC 40/55&deg;    Transverse        2 directions      100.0%
Shell Average        100.0%
000300  W05-06  upper Middle Shell        SLIC 40/55&deg;          Parallel      2 directions      81.5%      Limited examination due to the
                      -to- Upper Shell        SLIC 40/55&deg;      Transverse        2 directions      100.0%      outlet nozzle integral extensions and Average        90.8%      inlet nozzle bore radii.
000400  WO2-O3    Bottom Head -to-          SLIC 40/55&deg;          parallel      2 directions      83.5%      Limited examination due to the Lower Shell          SLIC 40/55&deg;        Parallel      2 directions        69.6%      proximity of the core barrel stabilizing Average          76.6%      lugs.
000500  W01-02    Bottom Head Cap          SLIC 40/55&deg;          Parallel      2 directions        49.7%      Limited examination due to the
                    -to- Bottom Head        SLIC 40/55&deg;      Transverse        2 directions        53.5%      bottom head penetrations.
Spherical Ring Average        51.6%
000600  W06-07        Upper Shell          SLIC 40/55&deg;          Parallel      2 directions      95.8%      Limited examination due to the
                        -to- Flange          SLIC 40/55&deg;      Transverse      2 directions        90.1%      flange design.
Average        93.0%
000900    W2A          Lower Head          SLIC 40/55&deg;          Parallel      2 directions      100.0%      Limited examination due to the Meridional @ 0&deg;        SLIC 40/55&deg;      Transverse      2 directions        83.7%      bottom head penetrations and core Average          91.9%    .barrel stabilizing lugs 001000    W2B          Lower Head          SLIC 40/55&deg;          Parallel      2 directions      100.0%      Limited examination due to the Meridional @ 60&deg;        SLIC 40/55&deg;      Transverse      2 directions        80.1%      bottom head penetrations and core Average        90.1%      barrel stabilizing lugs 001100    W2C          Lower Head          SLIC 40/55&deg;          Parallel      2 directions        98.5%      Limited examination due to the Meridional @ 120&deg;        SLIC 40/55&deg;      Transverse      2 directions        75.7%      bottom head penetrations and core Average          87.1%    barrel stabilizing lugs.
001200    W2D          Lower Head          SLIC 40/55&deg;          Parallel      2 directions      100.0%      Limited examination due to the Meridional @18O&deg;          SLIC 40/55&deg;      Transverse      2 directions        80.9%      bottom head penetrations and core Average      1 90.5%      barrel stabilizing lugs.
001300    W2E          Lower Head          SLIC 40/55&deg;          Parallel      2 directions        95.4%      Limited examination due to the Meridional @ 240&deg;        SLIC 40/55&deg;      Transverse      2 directions        76.6%      bottom head penetrations and core Average          86.0%    barrel stabilizing lugs.
001400    W2F          Lower Head          SLIC 40/55&deg;          Parallel      2 directions        90.7%      Limited examination due to the Meridional @ 300&deg;        SLIC 40/55&deg;      Transverse      2 directions        71.6%      bottom head penetrations and core Average          81.2%    barrel stabilizing lugs.
 
Sequoyah Nuclear Power Station, Unit 1 2006 Reactor Vessel Inservice Examination UT Coverage Summary    Weld        Exam Area              Beam            Exam Number Number      Identification        Angle(s)          Ty 001900    N-15      Outlet Nozzle            SLIC 40
                                                                                                              .''?. *: .Remarks '*<V?>0&#xa3; Parallel
                      -to-Shell @22&deg;        SLIC 40/55&deg; 2 directions    86.2%    Limited examination due to the" Transverse        2 directions    69.5%    integral extension.
PA-16    Parallel (Bore)      1 direction    100.0%
001500                                                                        Average      81.3%
N-11      inlet Nozzle          SLIC 40          Parallel      2 directions    100.0%
                    -to-shell @ 67&deg;        SLIC 40/55&deg;      Transverse        2 directions    100.0%
PA-16      Parallel (Bore)    1 direction    100.0%
001600                                                                        Average      100.0%
N-12        inlet Nozzle          SLIC 40        Parallel      2 directions    100.0%
                    -to-Shell @ 113&deg;      SLIC 40/55&deg;      Transverse        2 directions    100.0%
PA-16    Parallel (Bore)      1 direction    100.0%
002000                                                                        Average      100.0%
N-16      Outlet Nozzle          SLIC 40          Parallel      2 directions    86.2%    Limited examination due to the
                    -to-Shell @ 158&deg;      SLIC 40/55&deg;      Transverse        2 directions    69.5%    integral extension.
PA-16      Parallel (Bore)    1 direction    100.0%
Average      81.3%
002100    N-17      Outlet Nozzle            SLIC 40        Parallel      2 directions    86.2%    Limited examination due to the
                  *to- Shell @ 202&deg;      SLIC 40/55&deg;      Transverse        2 directions    69.5%    integral extension.
PA-16      Parallel (Bore)    1 direction    100.0%
Average      81.3%
001700    N-13      inlet Nozzle          SLIC 40          Parallel      2 directions    100.0%
                  -to- Shell (5) 247&deg;    SLIC 40/55&deg;      Transverse      2 directions    100.0%
PA-16      Parallel (Bore)    1 direction    100.0%
Average      100.0%
001800    N-14        inlet Nozzle          SLIC 40        Parallel      2 directions    100.0%
                  -to-Shell @293&deg;        SLIC 40/55&deg;      Transverse      2 directions    100.0%
PA-16      Parallel (Bore)    1 direction    100.0%
Average      100.0%
002200    N-18      Outlet Nozzle          SLIC 40          Parallel      2 directions      86.2%
                  -to-Shell @338&deg;                                                                    Limited examination due to the SLIC 40/55&deg;      Transverse      2 directions    69.5%    integral extension.
PA-16      Parallel (Bore)    1 direction      100.0%
Average      81.3%
 
Sequoyah Nuclear Power Station, Unit 1 2006 Reactor Vessel Inservice Examination UT Coverage Summary      Weld          Exam Area Number      Number                                                              Beam Identification Direction^
RC-O9-SE      Outlet Nozzle                                                            Remarks Parallel    2 directions    100.0%
to-Pipe @ 22&deg; Transverse    2 directions    100.0%
Average      100.0%
Elbow-to-inlet                        Parallel    2 directions    100.0%
Nozzle (q> 67&deg; Transverse      2 directions    100.0%
Average      100.0%
Elbow -to- inlet Parallel    2 directions    100.0%
Nozzle @ 113&deg; Transverse    2 directions    100.0%
Average      100.0%
Outlet Nozzle Parallel    2 directions    100.0%
to-Pipe @ 158&deg; Transverse      2 directions    100.0%
Average      100.0%
Outlet Nozzle Parallel    2 directions    100.0%
                        -to-Pipe @ 202&deg; Transverse    2 directions    100.0%
Average      100.0%
Elbow-to-inlet                        Parallel    2 directions    100.0%
Nozzle @ 247&deg; Transverse    2 directions    100.0%
Average      100.0%
Elbow-to-inlet                        Parallel    2 directions    100.0%
Nozzle @ 293&deg; Transverse    2 directions    100.0%
004200                                                                      Average      100.0%
RC-17-SE      Outlet Nozzle Parallel    2 directions    100.0%
                      -to-Pipe @ 338&deg; Transverse    2 directions    100.0%
Average      100.0%
Prepared by:
SNT Level:
Date:}}

Revision as of 08:48, 14 November 2019

American Society of Mechanical Engineers (ASME)Section XI Inservice Inspection (ISI) Program - Relief Requests
ML090500848
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 02/19/2009
From: Wetzel B
Tennessee Valley Authority
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML090500848 (61)
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Text

Tennessee Valley Authority, Post Office Box 2000, Soddy Daisy, Tennessee 37384-2000 February 19, 2009 10CFR50.50a(g)(5)(iii)

U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Gentleman:

In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 SEQUOYAH NUCLEAR PLANT (SQN) - AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) SECTION XI INSERVICE INSPECTION (ISI) PROGRAM - RELIEF REQUESTS Pursuant to 10 CFR 50.55a(g)(5)(iii), TVA is submitting 11 requests for relief from ASME code requirements. The relief requests are associated with ISI activities performed and identified during the third period of SQN's ASME Section XI Second 10-Year Inservice Inspection Interval. The relief requests are based on limitations that preclude full code examination coverage for ASME code welds and components. Full code examination of the welds and components is limited because of design configurations.

The relief requests are submitted in accordance with 10 CFR 50.55a(g)(5)(iii). TVA requests that NRC provide approval in accordance with 10 CFR 50.55a(g)(6)(i). The original relief request was prepared for submittal on January 27, 2007; however, the request was inadvertently not submitted to NRC.

TVA has no specific milestones or schedule for requesting NRC review and approval of the enclosed relief requests. The enclosed relief requests are being submitted solely for the closure of SQN's Second 10-Year Inservice Inspection Interval that completed on May 31, 2006. SQN's Third 10-year inspection interval started on June 1, 2006. provides five requests for relief for both units and a single relief request specific to Unit 2 (2-ISI-33). Enclosure 2 provides examination data reports for 2-ISI-33. provides ISI drawings. Enclosure 4 provides TVA's procedure for calculation of the ASME code coverage for Section XI nondestructive examinations. Enclosure 5 provides examination data reports (area coverage) for the balance of relief requests involving volumetric examination.

E5-1

U.S. Nuclear Regulatory Commission Page 2 February 19, 2009 There are no commitments contained in this letter.

If you have any questions about this change, please telephone me at (423) 843-7170.

Sincerely,

a. i Beth A. Wetzel Manager, Site Licensing and Industry Affairs Enclosures cc (Enclosures):

Mr. Brendon T. Moroney, Senior Project Manager U.S. Nuclear Regulatory Commission Mail Stop 08G-9a One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2739

U.S. Nuclear Regulatory Commission Page 3 February 19, 2009 BAW:JWP:SKD cc (Enclosures):

G. Arent, EQB 1B-WBN T. J. Bradshaw (NSRB Support), LP 4K-C C. R. Church, POB 2B-SQN T. P. Cleary, OPS 4A-SQN D. E. Jemigan, LP 3R-C K. R. Jones, OPS 4A-SQN R. M. Kerwin, OPS 4A-SQN M. J. Lorek, LP 3R-C L. E. Nicholson, LP 3R-C M. A. Purcell, LP 4K-C P. D. Swafford, LP 3R-C L. E. Thibault, LP 3R-C S. A. Vance, ET10A-K E. J. Vigluicci, ET10A-K WBN Site Licensing Files, ADM 1L-WBN EDMS, WT CA-K l:License/ASME - ISI/ISI Weld Limitations from 3rd period of 2nd ISI Interval

ENCLOSURE 1 SEQUOYAH NUCLEAR PLANT (SQN)

AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME)

INSERVICE INSPECTION PROGRAM (ISI)

REQUESTS FOR RELIEF UNITS 1 AND 2 1/2-ISI-28 1/2-ISI-29 1/2-ISI-30 1/2-ISI-31 1/2-ISI-32 2-ISI-33 El-1

Request For Relief 1/2-ISI-28 Summary:

TVA is requesting relief from the ASME Section XI Code to address the Units 1 and 2 reactor pressure vessel (RPV) bottom head-to-lower shell welds. The design configuration of the RPV core support lugs precludes a 100 percent ultrasonic examination of the required examination volume of each bottom head-to-lower shell weld. These physical examination limitations occur when the 1989 Edition Section XI Code examination requirements are applied in areas of components constructed and fabricated to early plant physical designs. Based on the date of Sequoyah Nuclear Plant's (SQN) construction permit (May 27, 1970), SQN is exempt from the code requirements for examination access as allowed in 10 CFR 50.55a(g)(4).

An inservice ultrasonic examination was performed on accessible areas to the maximum extent practical, given the physical limitations of the RPV bottom head-to-lower shell weld (W02-03) on both units. The design configuration limits the best effort ultrasonic examination to approximately 77 percent of the RPV bottom head-to-lower shell weld on both units.

Performance of an ultrasonic examination of essentially 100 percent of the full penetration welds is impractical because of the location of the reactor vessel core support lugs. The best effort ultrasonic examination and the required VT-3 visual examination of the interior of the RPV (Examination Category B-N-1) provides reasonable assurance of an acceptable level of quality and safety, because the information and data obtained from the volume examined provides sufficient information to judge the overall integrity of the weld.

Therefore, pursuant to 10 CFR 50.55a(g)(5)(iii), it is requested that relief be granted for the second inspection interval.

Units: 1 and 2 System: Reactor Coolant System - System 68 Components: RPV Bottom Head-to-Lower Shell Weld, Full Penetration Weld ASME Code Class: ASME Code Class 1 (Equivalent)

Section XI Edition: 1989 Edition (1995 Edition with 1996 Addenda for Non-Destructive Examination (NDE)

Code Table: IWB-2500-1 Examination Category: B-A, Pressure Retaining Welds in Reactor Vessel Examination Item Number: B1.11, Circumferential Shell Welds Code Requirement: ASME Section XI, Table IWB-2500-1, Examination Category B-A, Item Number B1.11, Requires Volumetric Examination of the RPV Bottom Head-to-Lower Shell Weld Code Requirement From Volumetric Examination of Essentially Which Relief Is Requested: 100 percent of the RPV Bottom Head-to-Lower Shell Weld List of Items Associated W02-03 RPV Bottom Head-to-Lower Shell With The Relief Request: Welds on Units 1 and 2 El-2

Request for Relief 1/2-ISI-28 (continued)

Basis for Relief:

The design configuration of the RPV precludes a complete volumetric examination of the required volume for the bottom head-to-lower shell weld W02-03 on both units. The limitation is due to the location of the reactor vessel core support lugs. This design configuration limits the volumetric (ultrasonic) examination to approximately 77 percent of the weld on both units.

The calculated results are provided in Enclosure 5.

Alternative Examination:

In lieu of the code required 100 percent volumetric examination, an ultrasonic examination will be performed on accessible areas to the maximum extent practical given the physical limitations of the bottom head-to-lower shell weld. Refer to Enclosure 5 for the Units 1 and 2 examination area coverage reports.

Justification for the Granting of Relief:

The design configuration used in the fabrication of the RPV bottom head-to-lower shell weld and location of the reactor vessel core support lugs precludes volumetric examination of essentially 100 percent of the required examination volume. In order to examine the weld in accordance with the code requirement, the RPV would require extensive design modifications.

The physical arrangement of bottom head-to-lower shell weld W02-03 and location of the reactor vessel core support lugs limit access for a complete volumetric examination. A total of six-core support lugs are welded to the reactor vessel equally spaced circumferently adjacent to the weld along the axial direction of the reactor vessels. Each core support lug attachment is approximately 15.75 inches in width and 23.78 inches in length (plus the weld blend radius) and covers the examination areas adjacent to the bottom head-to-lower shell weld. The design configuration of the RPV limits the ultrasonic examination to approximately 77 percent for both welds. Examinations were performed using qualified performance demonstration initiative (PDI) techniques.

Radiographic examination as an alternative volumetric examination method was determined to be impractical because of the inaccessibility from the inside diameter (ID) and the presence of water in the vessel.

Performing an ultrasonic volumetric or a surface examination from the RPV outside surface was determined to be impractical because of the physical design of the building. The physical limitations include the biological shield and insulation, which does not allow access to the weld without significant modification of the structure.

Performance of an ultrasonic volumetric examination of essentially 100 percent of the required volume of the bottom head-to-lower shell weld W02-03 on each RPV is impractical. As previously discussed, TVA determined that it would be impractical to attempt other volumetric examinations in order to increase examination coverage. The percentage (77 percent) of a volumetric (ultrasonic) examination of the subject weld and adjacent basemetal volumes and a code required VT-3 visual examination of the interior of the RPV (Examination Category B-N-

1) provides reasonable assurance of an acceptable level of quality and safety. Significant degradation, if present, would be detected during the ultrasonic and VT-3 examinations that are performed on the subject welds. As a result, reasonable assurance of structural integrity of these welds is provided by the performance of these examinations.

El-3

Request for Relief 1/2-ISI-28 (continued)

Therefore, pursuant to 10 CFR 50.55a(g)(5)(iii), it is requested that relief be granted for the second inspection interval.

Implementation Schedule:

This request for relief is applicable to the second inspection interval for SQN Units 1 and 2.

The examinations of weld W02-03 for both Units 1 and 2 were performed in the third period.

Background Information:

Requests for relief for volumetric examination coverage limitations was submitted for SQN's RPV bottom head-to-lower shell welds in SQN's first ISI interval (Relief Request 1-ISI-25 for Unit 1 and Relief Request 2-ISI-30 for Unit 2) and was approved by the reference letter below.

References:

1) Letter from David E. LaBarge, NRC, to O.D. Kingsley, Jr., TVA, dated February 7, 1996 (TAC Nos. M92454 and M92455)
2) Enclosure 3 - SI Program Drawing: ISI-0504-C-02 for Unit 1 and ISI-0298-C-02 for Unit 2
3) Enclosure 5 - ISwT Examination Area Coverage Reports for SQN Units 1 and 2 El-4

Request for Relief 1/2-1 SI-29 Summary:

TVA is requesting relief from the ASME Section XI Code to address the Units 1 and 2 RPV bottom head welds. The design configuration of the RPV instrumentation tubes, which penetrate the bottom head, precludes a 100 percent ultrasonic examination of the required examination volume of each bottom head weld. These physical examination limitations occur when the 1989 Edition Section XI Code examination requirements are applied in areas of components constructed and fabricated to early plant physical designs. Based on the date of SQN's construction permit (May 27, 1970), SQN is exempt from the code requirements for examination access as allowed by 10 CFR 50.55a(g)(4).

An inservice ultrasonic examination was performed on accessible areas to the maximum extent practical, given the physical limitations of the RPV bottom head weld (W01-02) on both units. The design configuration limits the best effort ultrasonic examination to approximately 52 percent (Unit 1) and 54 percent (Unit 2) of the RPV bottom head weld. Performance of an ultrasonic examination of essentially 100 percent of the full penetration welds are impractical due to the location of the of the reactor vessel instrumentation tubes, which penetrate the bottom head. The best effort ultrasonic examination and the required VT-3 examination of the interior of the RPV (Examination Category B-N-1) provides reasonable assurance of an acceptable level of quality and safety, because the information and data obtained from the volume examined provides sufficient information to judge the overall integrity of the weld.

Therefore, pursuant to 10 CFR 50.55a(g)(5)(iii), it is requested that relief be granted for the second inspection interval.

Units: 1 and 2 System: Reactor Coolant System - System 68 Components: RPV Bottom Head Weld, Full Penetration Weld ASME Code Class: ASME Code Class 1 (Equivalent)

Section XI Edition: 1989 Edition (1995 Edition with 1996 Addenda for NDE)

Code Table: IWB-2500-1 Examination Category: B-A, Pressure Retaining Welds in Reactor Vessel Examination Item Number: B1.21, Circumferential Head Welds Code Requirement: ASME Section XI, Table IWB-2500-1, Examination Category B-A, Item Number B1.21 Requires Volumetric Examination of the RPV Bottom Head Weld Code Requirement From Volumetric Examination of Essentially Which Relief Is Requested: 100 percent of the RPV Bottom Head Weld List of Items Associated W01-02 RPV Bottom Head Welds on Units 1 With The Relief Request: and 2 El-5

Request for Relief 1/2-ISI-29 (continued)

Basis for Relief:

The design configuration of the RPV precludes a complete volumetric examination of the required volume for bottom head weld W01-02 on both units. The limitation is due to instrumentation tubes, which penetrate the bottom head. This design configuration limits the volumetric (ultrasonic) examination to approximately 52 percent (Unit 1) and 54 percent (Unit

2) of the weld. The calculated results are provided by Enclosure 5.

Alternative Examination:

In lieu of the code required 100 percent volumetric examination, an ultrasonic examination will be performed on accessible areas to the maximum extent practical given the physical limitations of the bottom head weld. Refer to Enclosure 5 for the Units 1 and 2 examination area coverage reports.

Justification for the Granting of Relief:

The design configuration used in the fabrication of the RPV bottom head weld and location of the reactor vessel instrumentation, which penetrate the bottom head, precludes volumetric examination of essentially 100 percent of the required examination volume. In order to examine the weld in accordance with the code requirement, the RPV would require extensive design modifications. The physical arrangement of bottom head weld W01-02 and location of the reactor vessel instrumentation tubes, which penetrate the bottom head, limits access for a complete volumetric examination on each weld. A total of 58 instrumentation tubes penetrate the bottom head. These instrumentation tubes limit the access to the bottom head weld. The design configuration limits the best effort ultrasonic examination to approximately 52 percent (Unit 1) and 54 percent (Unit 2) of the welds. The subject welds were examined using application of the qualified PDI techniques.

Radiographic examination as an alternative volumetric examination method was determined to be impractical because of the inaccessibility from the outside diameter (OD) of the vessel and also because of the presence of water in the vessel.

Performance of an ultrasonic volumetric examination of essentially 100 percent of the required volume of bottom head weld W01-02 on each RPV is impractical. As previously discussed, TVA determined that it would be impractical to attempt other volumetric examinations in order to increase examination coverage. The percentage (52 percent Unit 1 and 54 percent Unit 2) of a volumetric (ultrasonic) examination of the subject weld and adjacent basemetal volumes and a code required VT-3 visual examination of the interior of the RPV (Examination Category B-N-1) provides reasonable assurance of an acceptable level of quality and safety. Significant degradation, if present, would be detected during the ultrasonic and VT-3 examinations that are performed on the subject welds. As a result, reasonable assurance of structural integrity of these welds is provided by the performance of these examinations.

Therefore, pursuant to 10 CFR 50.55a(g)(5)(iii), it is requested that relief be granted for the second inspection interval.

El-6

Request for Relief 1/2-1 SI-29 (continued)

Implementation Schedule:

This request for relief is applicable to the second inspection interval for SQN Units 1 and 2.

The examinations of weld W01 -02 for both units were performed in the third period.

Background Information:

A request for relief for volumetric examination coverage limitations was submitted for W01-02 as 1-ISI-5 for Unit 1 and 2-ISI-5 for Unit 2 in the first inspection interval and was approved by the reference letters below.

References:

1) Letter from Frederick J. Hibdon, NRC, to Oliver D. Kingsley, Jr., TVA, dated February 7 1991 (TAC No. 59457)
2) Letter from Suzanne Black, NRC, to Oliver D. Kingsley, Jr., TVA, dated April 19 1990 (TAC No. 59458)
3) Enclosure 3 - ISI Program Drawing: ISI-0504-C-02 for Unit 1 and ISI-0298-C-02 for Unit 2
4) Enclosure 5 - ISwT Examination Area Coverage Reports for SQN Units 1 and 2 El-7

Request for Relief 1/2-ISI-30 Summary:

TVA is requesting relief from the ASME Section XI Code to address the Units 1 and 2 RPV outlet nozzle-to-vessel welds. The design configuration of the RPV, the outlet nozzle integral extensions, and the location of the adjacent nozzles preclude a 100 percent ultrasonic examination of the required examination volume of the outlet nozzle-to-vessel welds. These physical examination limitations occur when the 1989 Edition Section XI Code examination requirements are applied in areas of components constructed and fabricated to early plant physical designs. Based on the date of SQN's construction permit (May 27, 1970), SQN is exempt from the code requirements for examination access as allowed in 10 CFR 50.55a(g)(4).

An inservice ultrasonic examination was performed on accessible areas to the maximum extent practical, given the physical limitations of the RPV outlet nozzle-to-vessel welds. The design configuration limits the best effort ultrasonic examination to approximately 81 percent (Unit 1) and 72 percent (Unit 2) of each of the RPV outlet nozzle-to-vessel welds.

Performance of an ultrasonic examination of essentially 100 percent of the full penetration welds is impractical because of the integral extensions and the location of the adjacent nozzles. The best effort ultrasonic examination and the required VT-3 visual examination of the interior of the RPV (Examination Category B-N-1) provide reasonable assurance of an acceptable level of quality and safety, because the information and data obtained from the volume examined provides sufficient information to judge the overall integrity of the weld.

Therefore, pursuant to 10 CFR 50.55a(g)(5)(iii), it is requested that relief be granted for the second inspection interval.

Units: 1 and 2 System: Reactor Coolant System - System 68 Components: RPV Outlet Nozzle-to-Vessel Weld, Full Penetration Weld ASME Code Class: ASME Code Class 1 (Equivalent)

Section XI Edition: 1989 Edition (1995 Edition with 1996 Addenda for NDE)

Code Table: IWB-2500-1 Examination Category: B-D, Pressure Retaining Welds in Reactor Vessel Examination Item Number: B3.90, Reactor Vessel Nozzle-to-Vessel Welds Code Requirement: ASME Section XI, Table IWB-2500-1, Examination Category B-D, Item Number B3.90 Requires Volumetric Examination of the Outlet Nozzle-to-Vessel Welds Code Requirement From Volumetric Examination of Essentially Which Relief Is Requested: 100 percent of the Outlet Nozzle-to-Vessel Welds List Of Items Associated N-15, N-16, N-17, and N-18 Outlet With The Relief Request: Nozzle-to-Vessel Welds on Units 1 and 2 El-8

Request for Relief 1/2-ISI-30 (continued)

Basis for Relief:

The design configuration of the RPV precludes a complete volumetric examination of the required volume for outlet nozzle-to-vessel welds N-15, N-16, N-17, and N-18 on both units.

The limitation is because of the physical arrangement of outlet nozzle-to-vessel weld, nozzle integral extensions and the location of the adjacent nozzles. This design configuration limits the volumetric (ultrasonic) examination to approximately 81 percent (Unit 1) and 72 percent (Unit 2) for these welds. The calculated results are provided in Enclosure 5.

Alternative Examination:

In lieu of the code required 100 percent volumetric examination, an ultrasonic examination will be performed on accessible areas to the maximum extent practical given the physical limitations of the outlet nozzle-to-vessel welds. Refer to Enclosure 5 for the Units 1 and 2 examination area coverage reports.

Justification for the Granting of Relief:

The design configuration used in the fabrication of the RPV outlet nozzle-to-vessel weld, the outlet nozzle integral extensions, and the location of the adjacent nozzles precludes volumetric examination of essentially 100 percent of the required examination volume. In order to examine the weld in accordance with the code requirement, the RPV would require extensive design modifications. The physical arrangement of outlet nozzle-to-vessel welds N-15, N-16, N-17, and N-18; the nozzle integral extensions; and the location of the adjacent nozzles limit access for a complete volumetric examination. Because of the design of the RPV nozzle-to-vessel weld configuration, ultrasonic examination conducted from the vessel interior surface provides more examination coverage than if conducted from the vessel exterior surface due to limited access. The design configuration limits the best effort ultrasonic examination to approximately 81 percent (Unit 1) and 72 percent (Unit 2) for these welds. The subject welds were examined using application of the qualified PDI techniques.

Radiographic examination as an alternative volumetric examination method was determined to be impractical because of the inaccessibility from the OD of the vessel and also due to the presence of water in the vessel-Performance of an ultrasonic volumetric examination of essentially 100 percent of the required volume of outlet nozzle-to-vessel welds N-15, N-16, N-17, and N-18 on each RPV is impractical. As previously discussed, TVA determined that it would be impractical to attempt other volumetric examinations in order to increase examination coverage. The percentage (81 percent Unit 1 and 72 percent Unit 2) of a volumetric (ultrasonic) examination of the subject weld and adjacent basemetal volumes and a code required VT-3 visual examination of the interior of the RPV (Examination Category B-N-1) provides reasonable assurance of an acceptable level of quality and safety. Significant degradation, if present, would be detected during the ultrasonic and VT-3 examinations that are performed on the subject welds. As a result, reasonable assurance of structural integrity of these welds is provided by the performance of these examinations.

Therefore, pursuant to 10 CFR 50.55a(g)(5)(iii), it is requested that relief be granted for the second inspection interval.

El-9

Request for Relief 1/2-ISI-30 (continued)

Implementation Schedule:

This request for relief is applicable to the second inspection interval for SQN Units 1 and 2.

The examination of welds N-15, N-16, N-17, and N-18 for both Units 1 and 2 were performed in the third period.

Background Information:

A request for relief for volumetric examination coverage limitations was submitted for welds N-15, N-16, N-17 and N-18 as 1-ISI-27 for Unit 1 and 2-ISI-29 for Unit 2 in the first inspection interval and was approved with the reference letter below.

References:

1) Letter from David E. LaBarge, NRC, to O.D. Kingsley, Jr., TVA, dated February 7, 1996 (TAC NOS. M92454 and M92455)
2) Enclosure 3 - ISI Program Drawing: ISI-0504-C-02 for Unit 1 and ISI-0298-C-02 for Unit 2
3) Enclosure 5 - ISwT Examination Area Coverage Reports for SQN Units 1 and 2 El-10

Request for Relief 1/2-ISI-31 Summary:

TVA is requesting relief from the ASME Section XI Code to address the Units 1 and 2 reactor pressure vessel (RPV) bottom head meridional welds. The design configuration of the RPV instrumentation tubes, which penetrate the bottom head, precludes a 100 percent ultrasonic examination of the required examination volume of the bottom head weld. These physical examination limitations occur when the 1989 Edition Section XI Code examination requirements are applied in areas of components constructed and fabricated to early plant physical designs. Based on the date of SQN's construction permit (May 27, 1970), SQN is exempt from the code requirements for examination access as allowed in 10 CFR 50.55a(g)(4).

An inservice ultrasonic examination was performed on accessible areas to the maximum extent practical, given the physical limitations of the RPV bottom head meridional welds. The design configuration limits the best effort ultrasonic examination of the meridional welds.

Performance of an ultrasonic examination of essentially 100 percent of the full penetration welds are impractical due to the location of the of the reactor vessel instrumentation tubes, which penetrate the bottom head. The best effort ultrasonic examination and the required VT-3 visual examination of the interior of the RPV (Examination Category B-N-1) provide reasonable assurance of an acceptable level of quality and safety, because the information and data obtained from the volume examined provide sufficient information to judge the overall integrity of the weld.

Therefore, pursuant to 10 CFR 50.55a(g)(5)(iii), it is requested that relief be granted for the second inspection interval.

Units: 1 and 2 System: Reactor Coolant System - System 68 Components: Reactor Pressure Vessel Bottom Head Meridional Welds, Full Penetration Weld ASME Code Class: ASME Code Class 1 (Equivalent)

Section XI Edition: 1989 Edition (1995 Edition with 1996 Addenda for NDE)

Code Table: IWB-2500-1 Examination Category: B-A, Pressure Retaining Welds in Reactor Vessel Examination Item Number: B1.22, Head Meridional Welds Code Requirement: ASME Section XI, Table IWB-2500-1, Examination Category B-A, Item Number B1.22 Requires Volumetric Examination of the RPV Bottom Head Meridional Welds Code Requirement From Volumetric Examination of Essentially Which Relief Is Requested: 100 percent of the RPV Bottom Head Meridional Welds List of Items Associated W2C RPV Bottom Head Weld on Unit 1 Only With The Relief Request: W2E and W2F RPV Bottom Head Welds on Units 1 and 2 El-ll

Request for Relief 1/2-ISI-31 (continued)

Basis for Relief:

The design configuration of the RPV precludes a complete volumetric examination of the required volume for the bottom head meridional welds (W2E and W2F) on both units and W2C (Unit 1 only). The limitation is due to instrumentation tubes, which penetrate the bottom head.

This design configuration limits the volumetric (ultrasonic) examination to approximately 87 percent (Unit 1 only) for W2C, 86 percent (Unit 1) and 90 percent (Unit 2) for W2E and 81 percent (Unit 1) and 80 percent (Unit 2) for W2F, as calculated by TVA approved vendor procedures (Enclosure 5).

Alternative Examination:

In lieu of the code required 100 percent volumetric examination, an ultrasonic examination will be performed on accessible areas to the maximum extent practical given the physical limitations of the bottom head meridional welds. Refer to Enclosure 5 for the Units 1 and 2 examination area coverage reports.

Justification for the Granting of Relief:

The design configuration used in the fabrication of the RPV bottom head meridional welds and location of the reactor vessel instrumentation, which penetrates the bottom head, precludes volumetric examination of essentially 100 percent of the required examination volume. In order to examine the weld in accordance with the code requirement, the RPV would require extensive design modifications. The physical arrangement of bottom head meridional welds W2C (Unit 1 only), W2E, and W2F and location of the reactor vessel instrumentation tubes, which penetrate the bottom head, limits access for a complete volumetric examination. A total of 58 instrumentation tubes penetrate the bottom head. The design configuration limits the best effort ultrasonic examination to approximately 87 percent for W2C (Unit 1 only), 86 percent (Unit 1) and 90 percent (Unit 2) for W2E, and 81 percent (Unit 1) and 80 percent (Unit

2) for W2F welds. The subject welds were examined using application of the qualified PDI techniques.

Radiographic examination as an alternative volumetric examination method was determined to be impractical because of the inaccessibility from the vessel ID and also because of the presence of water in the vessel.

TVA performed a review in order to assess the differences in the percent of coverage between Units 1 and 2. Even though the head configurations are designed to be the same, some of these welds are limited on the upper end by the core barrel support lugs, some are limited on the lower end by the lower head penetrations, and some are limited on both ends.

Performance of an ultrasonic volumetric examination of essentially 100 percent of the required volume of bottom head meridional welds W2E and W2F on each RPV and W2C on Unit 1 only are impractical. As previously discussed, TVA determined that it would be impractical to attempt other volumetric examinations in order to increase examination coverage. The percentage (87 percent [Unit 1 only] on W2C, 86 percent [Unit 1] and 90 percent [Unit 2] on W2E and 81 percent [Unit 1] and 80 percent [Unit 2] on W2F) of a volumetric (ultrasonic) examination of the subject weld and adjacent basemetal volumes and a code required VT-3 visual examination of the interior of the RPV (Examination Category B-N-1) provide reasonable assurance of an acceptable level of quality and safety. Significant degradation, if present, El-12

Request for Relief 1/2-ISI-31 (continued) would be detected during the ultrasonic and VT-3 examinations that are performed on the subject welds. As a result, reasonable assurance of structural integrity of these welds is provided by the performance of these examinations.

Therefore, pursuant to 10 CFR 50.55a(g)(5)(iii), it is requested that relief be granted for the second inspection interval.

Implementation Schedule:

This request for relief is applicable to the second inspection interval for SQN Units 1 and 2.

The examination of weld W2C (Unit 1 only), and welds W2E and W2F for both Units 1 and 2, were performed in the third period.

References:

1) Enclosure 3 - ISI Program Drawing: ISI-0504-C-02 for Unit 1 and ISI-0298-C-02 for Unit 2
2) Enclosure 5 - ISwT Examination Area Coverage Reports for SQN Units 1 and 2.

El-13

Request for Relief 1/2-ISI-32 Summary:

TVA is requesting relief from the ASME Section XI Code to address the Units 1 and 2 reactor pressure vessel support RVH-1. The design configuration of the subject support and the location preclude a 100 percent visual examination of the required support area. These physical examination limitations occur when the 1989 Edition Section XI Code examination requirements are applied in areas of components constructed and fabricated to early plant physical designs. Based on the issue date of SQN's construction permit (May 27, 1970), SQN is exempt from the code requirements for providing original design and examination access as allowed in 10CFR50.55a(g)(4).

An inservice VT-3 visual examination was performed on accessible areas to the maximum extent practical, given the design and location limitations of the subject support. The design configuration and location limit the visual examination to one side of the support. Performance of a visual examination of essentially 100 percent of the subject support would be impractical.

The maximum extent practical visual examination of the subject support provides reasonable assurance of an acceptable level of quality and safety, because the information obtained from the area examined provides sufficient information to judge the overall integrity of the support.

Therefore pursuant to 10 CFR50.55a(g)(5)(iii), it is requested that relief be granted, for the second inspection interval.

Units: 1 and 2 System: System Reactor Coolant System - System 68 Component: RPV Support ASME Code Class: ASME Code Class 1 (Equivalent)

Section XI Edition: 1989 Edition (1995 Edition with 1996 Addenda for NDE)

Code Table: ASME Section XI Code Case N-491-1, Table 2500-1 Examination Category: F-A, Supports Examination Item Number: F1.40, Supports Other Than Piping Supports (Class 1, 2, 3, and MC)

Code Requirement: ASME Section XI, Code Case N-491-1, Table 2500-1, Examination Category F-A, Item F1.40, Requires VT-3 Visual Examination for the RPV Support Code Requirement From VT-3 Visual Examination of Essentially Which Relief Is 100 Percent of the RPV Support Requested:

List of Items RVH-1, RPV Support Associated With The Relief Request:

El-14

Request for Relief 1/2-IS1-32 (continued)

Basis for Relief:

The design configuration of the reactor vessel support and the support location precludes a VT-3 visual examination of the required area of the subject support RVH-1. A limited VT-3 visual examination was performed on the accessible portions of the subject support to the maximum extent practical. Removable portions of the insulation were removed from the piping and RPV nozzle areas in order to maximize the VT-3 visual examination of the RPV nozzle to support interface. Typical access for each support was determined to allow less than 50 percent of the support areas requiring examination to be examined. Insulation and flashing on the RPV nozzle and the RPV, which remained in place, would require extensive modifications to remove. However, a maximum extent VT-3 visual examination of the area was performed, which included an examination of the insulation for any evidence of disturbance or degradation that may be attributed to abnormal support disturbance.

Alternative Examinations:

In lieu of the Section XI essentially 100 percent VT-3 visual examination, a best effort VT-3 visual examination was performed on accessible areas to the maximum extent practical, given the location and configuration of the support.

Justification For The Granting Of Relief:

The support assembly at four of the eight reactor vessel nozzles consists of a nozzle pad and steel plates positioned between a steel support structure. Additionally, the majority of each support is encased in permanent insulation panels from the reactor vessel and vessel nozzles and piping. Insulation panels were removed around the piping and nozzles to the extent practical in order to access the support. These design features make the VT-3 visual examination of the reactor vessel supports impractical to perform to the extent required by Section XI. The design configuration restricts visual access to a majority of stiffener welds and structural steel.

However, structural and mechanical integrity was verified by observing no signs of mechanical or structural inservice related conditions of the accessible areas. To meet Section XI requirements, the permanent insulation would be required to be removed and redesigned to allow access for complete examination. The design configuration used in the fabrication of the subject support, in conjunction with the confined space to access the support, precludes visual examination of essentially 100 percent of the required examination area. The support is designed to function as a vertical restraint primarily loaded in compression. The majority of each support is encased in the permanent insulation panels of the RPV and RPV nozzles.

Portions of the steel support structure and associated welds are accessible for a limited VT-3 visual examination. In order to examine the support in accordance with Section XI requirements, extensive modification would be required to access all regions of the support.

Access to the RPV support is limited because of confined access below the nozzle inspection covers, nozzle insulation and the permanent liner steel plates for the cavity wall.

El-15

Request for Relief 1/2-ISI-32 (continued)

In addition to difficult access, radiation levels in the area are approximately 35- to 80-millirem per hour. It is estimated that the removal and reinstallation of the permanent insulation in this confined space would result in additional exposure of approximately 4.0 man-rem and achieve a minimum increase in examination coverage. Based on the access restrictions, high radiation levels and support design, relief is requested from performing the VT-3 visual examination of the inaccessible portions of these supports. The design configuration limits the best effort visual examination to the accessible side of the four nozzles for support RVH-1. The subject support was remotely examined using a video camera and direct visual examination in order to achieve maximum coverage.

Performance of a VT-3 visual examination of essentially 100 percent of the required area of RPV support RVH-1 is impractical. The maximum extent practical visual examination of the support will provide reasonable assurance of an acceptable level of quality and safety.

Significant degradation, if present, would have been detected during the visual examination on the subject support. As a result, reasonable assurance of structural integrity for this support is provided by the examination that was performed.

Therefore pursuant to 10 CFR 50.55a(g)(5)(iii), it is requested that relief be granted, for the second inspection interval.

Implementation Schedule:

This request for relief is applicable to SQN's second inspection interval for SQN Units 1 and 2.

The examinations of the RPV support, RVH-1, were performed for both units in the third period.

El-16

Request for Relief 2-ISI-33 Summary:

TVA is requesting relief from the ASME Section XI Code to address the circumferential pressure retaining piping weld SIF-170 in the safety injection system. The design configuration, elbow-to-valve, of the subject piping precludes a 100 percent ultrasonic examination of the required weld volume. These physical examination limitations occur when the 1989 Edition Section XI Code examination requirements are applied in areas of components constructed and fabricated to early plant physical designs. Based on the issue date of SQN's construction permit (May 27, 1970), SQN is exempt from the code requirements for providing original design and examination access as allowed in 10 CFR 50.55a(g)(4).

An inservice ultrasonic examination was performed on accessible areas to the maximum extent practical, given the physical limitations of the subject weld. The design configuration, elbow-to-valve, limits the best effort ultrasonic examination to approximately 50 percent.

Performance of an ultrasonic examination of essentially 100 percent of the subject circumferential pressure retaining weld would be impractical. The maximum extent practical ultrasonic examination of the subject weld provides reasonable assurance of an acceptable level of quality and safety because the information and data obtained from the volume examined provides sufficient information to judge the overall integrity of the welds.

Therefore pursuant to 10 CFR 50.55a(g)(5)(iii), it is requested that relief be granted, for the second inspection interval.

Unit:

System: Safety Injection System -xSystem 63 Component: One Pressure Retaining Circumferential Pipe Weld ASME Code Class: ASME Code Class 1 (Equivalent)

Section XI Edition: 1989 Edition (1995 Edition with 1996 Addenda for NDE), 10 CFR 50.55a(b)(2)(xv)(A), WCAP-14572, Revision 1-NP-A, and WCAP-14572, Revision 1-NP-A, Supplement 1 Code Table: WCAP-14572, Table 4.1-1 Examination Category: R-A, Risk - Informed Piping Examinations Examination Item Number: R1.11, Elements Subject to Thermal Fatigue R1.16, Elements Subject to Intergranular Stress Corrosion Cracking (IGSCC)

Code Requirement: WCAP-14572, Table 4.1-1, Examination Category R-A, Item Numbers R1.11 and R1.16, Requires Volumetric Examination of Elements Subject to Thermal Fatigue and IGSCC Code Requirement From Volumetric Examination Coverage of Which Relief Is Essentially 100 Percent of Elements Requested: Thermal Fatigue and IGSCC El-17

Request for Relief 2-IS1-33 (continued)

List of Items SIF-170, Circumferential Pipe Weld Associated With The Relief Request:

Basis for Relief:

The design configuration, elbow-to-valve, of the safety injection piping precludes an ultrasonic examination of the required volume of the subject weld SIF-170 because of the design of the valve. The design configuration limits ultrasonic examination to approximately 50 percent of the required examination volume as calculated in accordance with TVA Procedure N-GP-28 (Enclosure 4).

Alternative Examinations:

In lieu of the code required 100 percent volumetric examination, a best effort ultrasonic examination was performed on accessible areas to the maximum extent practical given the physical limitations of the subject weld. Refer to (Enclosure 2) attached examination data report.

Justification for Granting Of Relief:

The design configuration, elbow-to-valve, precludes ultrasonic examination of essentially 100 percent of the required examination volume. In order to examine the weld in accordance with the code requirements, the safety injection system pipe-to-valve configuration would require extensive modification. SIF-170 is limited due to the elbow-to-valve configuration, which limits scanning on the elbow side only. The design configuration limits the best effort ultrasonic examination to approximately 50 percent for weld SIF-170. The subject weld was examined using application of PDI qualified techniques with PDI qualified examiners.

The risk informed segment, which includes weld SIF-170, is classified high safety significant.

The postulated failure mechanisms for the segment are thermal fatigue, thermal stratification/striping and stress corrosion cracking (SCC). All welds in this segment that are subject to SCC must be examined every 10 years. Weld SIF-170 is the only weld in this segment that is subject to SCC. Therefore, there are no welds available for substitution.

Performance of an ultrasonic volumetric examination of essentially 100 percent of the required volume of pressure retaining circumferential weld SIF-170 (pipe to valve) in the safety injection piping is impractical. As indicated above, this ultrasonic volumetric examination was performed in accordance with Performance Demonstration Initiative (PDI). The maximum extent practical ultrasonic examination of the weld and adjacent material and the code required VT-2 examination for leakage would provide reasonable assurance of an acceptable level of quality and safety. Significant degradation, if present, would be detected during the ultrasonic and VT-2 examinations that are performed on the subject weld. As a result, reasonable assurance of structural integrity for this weld is provided by the examinations that were performed.

El-18

Request for Relief 2-ISI-33 (continued)

Radiographic examination as an alternate volumetric examination method was determined to be impractical due the material thickness variation. The radiographic density variation does not lend for compliance with Section V requirements without extensive radiographic exposures to obtain the density for the base material on the valve side. Radiography required would increase personnel radiation exposure for minimal increase in examination coverage.

Therefore pursuant to 10 CFR 50.55a(g)(5)(iii), it is requested that relief be granted for the second inspection interval.

Implementation Schedule:

This request for relief is applicable to SQN's second inspection interval for SQN Unit 2. Weld SIF-170 for Unit 2 was examined in the third period.

References:

1) Enclosure 2 - Examination Data Report: R6693 and R6694
2) Enclosure 3 - ISI Program Drawings: ISI-0002-C-06
3) Enclosure 4 - Non Destructive Examination Procedure N-GP-28 "Calculation of ASME Code Coverage for Section XI NDE Examinations" El-19

ENCLOSURE 2 EXAMINATION DATA REPORTS Request for Relief Examination Data Reports Number 2-ISI-33 R6693 and R6694 E2-1

TENNESSEE EXAMINATION REPORT NUMBER:

VALLEY SUMiMARY AUTHORITY AND PROJECT: SQiV UNIT: 2 CYCLE: 13 COMPONENT ID: SlF-170 DESCRIPTION/ ^

LOCATION: /

EXAMINATION METHOD SYSTEM: SIS jlSI DWG NO: 1S1-0002-C-06 MT Q PT UT vt CONFIGURATION CATEGORY PROCEDURE: N-UT-64 REV: 7 TC N/A TO PE,EL R-A EXAMINER: EXAMINER: EXAMINER: EXAMINER:

/v zz LEVEL: LEVEL: J££, LEVEL: LEVEL:

Total coverage calculated to be approximately SO The above mentioned weld was ultrasonically inspected. A 1/2 Vpath calibration with a primary angle of 45 shear wave. This was a single sided exam, due to valve configuration, and a 60 RL 1/2 V path calibration was also utilized.

Counterbore geometry was recorded with the 60 RL on the intradose of the elbow.

No rejectable indicatins observed.

This examination meet the requirments of Risk Informed item RLll RESOLUTION B REVIEWED BY ANII:

y DATE DATE LEVEL: ATE Page: I OF ACCESS FORMS DATABASE R-3/18/03 EZ-Z

PROJECT: SQN UNIT/CYCLE CALIBRATION BLOCK NO.: TEMP:_

PROCEDURE: N-UT-64 REV: 7 TC:

SIMULATOR BLOCK:Rompas 1^217 TRANSDUCER THERMOMETER S/N 573203 DUE DATE 8-9-05 MANUFACTURER: KBA COUPLANT: Ultragel II BATCH: 01225 MODEL: COMP-G S/N:00D8KH ANGLE VERIFICATION SIZE: .375" FREQ: 1.5 MH BLOCK TYPE: Rompas S/N: 792770 SHAPE: Round U ELEMENTS: 1 #CONS: 0 NOMINAL ANGLE:45J ACTUAL ANGLE: 45 ° LENGTHS' INSTRUMENT CABLE TYPE: RG-174 MANUFACTURER: KLrautkramer DUE DATE: 7/28/05 EXAM TYPE 0 SHEAR LONG MODEL NO.:

DAC INSTRUMENT SETTINGS 100 REFLECTOR REFERENCE MEMORY SCA:\ DIRECT. SENSITIVITY MMBER A NTC SDH 80 M AXIAL *  : U 31 IttSS45 P CIRC. N/A 60 L *FREQ_ 2. o MHz I ANGLE: J+/- deg *DAMPlNC:/flflfl ohms 40 T DELAY. 0.000 msec *PULSER SINGLE U ZERO: 8.0469 msec 20 D VELOCITY, .1257 msec JOF: PEAK E RANGE: _ 2A inches POWER: BATTERY

  • DISP. MODE:F ^

TCG: ON DISPLAY WIDTH 2.9 inches FAR SDH GAIN: 43 dB CALIBRATION TIMES REF. REFLECTOR:

METAL PATH: 1.096 INITIAL TIME: 1040 FINAL TIME: 1410 AMPLITUDE:

i m i * * * *-* >>

  • i**r ^-^ ~^ -

55 % i . i.

VERIFICATION TIMES l >>> 13

  • 5" " 2> N/a!3) N/a!4) N/aI 5) N/A'6) N//\l7) N/aI8) N/A w N/A
  • PDI QUALIFIED INSTRUMENT SETTINGS:

VERIFY INSTRUMENT SETTINGS AND CALIBRATION SEQUENCE ARE IN ACCORDANCE WITH TABLE 2 OF THE APPLICABLE PDI QUALIFICATION IMPLEMENTATION PROCEDURE!

LINEARITY CHECK WELD / ITEMS EXAMINED SIF-170

\ P EXAMINER: Fr f EXAMINER:

REVIEWER: DATE S£lfOf PAGE OF ACCESS FORMS OATABASE

TENNESSEE DIGITAL ULTRASONIC REPORT NUMBER VALLEY CALIBRATION AUTHORITY DATA SHEET CALIBRATION HATE: 4/29/05 ROJECT: SQN UNIT/CYCLE 2/.I3 75 °F CALIBRATION BLOCK NO.j_i_Q_!l2_ TEMP:_

'ROCEDURE: N-UT-64 REV: TC:

SIMULATOR Rl.orK:Rompas TRANSDUCER THERMOMETER S/N 573203 DUE DATE 8-9-05 MANUFACTURER: RTD COI!PLANT: Ultragel II BATCH: 01225 S/N: 99-431 ANGLE VERIFICATION MODEL: TRLA 8x14mm FREQ: 2 MH BLOCK TYPE: Rompas SIZE:

SHAPE: f£cT U ELEMENTS: 2 SCONS: 0_ NOMINAL ANGLE: 60° ACTUAL ANGLEj___60_l INSTRUMENT CABLE TYPE: RG-174 LENGTHl6' MANUFACTURER: Krautkramer DUE DATE: J^rllP EXAM TYPE D SHEAR LONG RL MODEL NO.: OSti' 6 0 _ M&TE:^63OI DAC INSTRUMENT SETTINGS 100 REFLECTOR REFERENCE MEMORY 1 SENSITIVITY NUMBER A SCAN DIRECT. NTC ! SDH 80 1 1 '* o" M AXIAL 62 1USS60 P CIRC. i i\/A dB L *FREO 2< o MHz ^REJECT:

60 ANC! Ft 60 deg "DAMPING: 1QQQ ohms I

40 i T DELAY 0.000 msec *PULSER DUAL U ZERO: 8.5591 msec 20 D VELOCITY .2329 msec TOF: PEAK 1

E RANGE: 3.500 inches POWER: BATTERY 1 1 0 *DISP. MODE: FW TCG: Q ON B"OFF 3.5 inches H DISPLAY WIDTH, 62 dB CALIBRATION TIMES REF. REFLECTOR: FAR SDH GAIN:.

INITIAL TIME: 1045 FINAL TIME: 1412 AMPLITUDE: 90 % METAL PATHj_L12

2) N/Ali) N/A] 4) N/A 5) N/A 6) N/A 7) N;A
  • PDl QUALIFIED INSTRUMENT SETTINGS:

VERIFY INSTRUMENT SETTINGS AND CALIBRATION SEQUENCE ARE IN ACCORDANCE WITH TABLE 2 OF THE APPLICABLE PDI QUALIFICATION IMPLEMENTATION PROCEDURE!

ATTENUATOR] AMP WELD / ITEMS EXAMINED

[REVIEWER:

ACCESS FORM

TENNESSEE MANUAL ULTRASONIC REPORT NUMBER VALLEY PIPING EXAMINATION AUTHORITY A-U93 DATA SHEET UNIT/CYCLE 2 I 13 EXAMINATION HATE 4/29/05 ROJECT: SQN SYSTEM SIS START TIME: 1215 END TIME: 1345 EXREQ: S9E-02 CAT: R-A ITEM NO: Rl.II EXAM SURFACE: DID WELD I.P.: SIT-170 gSS QCSCL Q CCSS MATERIAL TYPE:

CONFIC: PC.VLV TO PE.EL SURFACE TEMP. 80 PYRO NO. 573203 NlK 45 DEC 60RL DEC PROCEDURE: N-UT-64 REV: 7 TC: EXAMINATION ANGLE AXIAL SCAN SENSITIVITY 43 dB 62 Wo RFFFRENCE: WELD CENTER LINE Lo

REFERENCE:

TDC CIRC. SCAN SENSITIVITY 43 dB N/A dB AT MAX AMP MAX EXAM INDICATION INFORMATION:

L (in) FROMIREF. NOM. NRI IND AMP NO.

ANG. TYPE, DAMPING, ETC.

NO. L1 LMax L2 W MAX MP MAX D MAX  % DAC 3-14 45 45 Counterbore 15" 18" 21" 1.10 1.1 N/A 100 60

45 REMARKS/LIMITATIONS No scan 3 due to Valve confa atiot Mainatined 10% ID roll No Reject able Indications S &< (>

WALL THICKNeCY REPORT NO:

TVA PROFILE SHEET PROJECT:. SON WELD NO: S \F -HO UNIT: SYSTEM:

Weld

  • Weld Edg Record Thickness Measurements As Centerline Indicated, Including Weld Width, Edge-To-Edge At 0/ -2.5" [*<< 2.5M-Position 9 0* 180* 270*

\ Side

\A \

1.01 C3 I.OB \ y Flow,

.'0 DIAMETER:

10 CROWN HEIGHT:

SH.

CROWN WIDTH:_ WELD LENGTH:.

FLOY/

ANII:

EXAMINER:. REVIEWED BY:.

LEVEL:_

LEVEL: DATE:

DATE:

Ty PAGE . . OF_

TVA

/wmiL TENNESSEE EXAMINATION REPORT NUMBER:

VALLEY

SUMMARY

AUTHORITY AND PROJECT: SQ>\ UNIT: 2 CYCLE: 13 COMPONENT ID: SlF-170 DESCRIPTION/

LOCATION:

EXAMINATION METHOD SYSTEM: SIS ISI DWG NO: ISI-0002-C-06 MT PT UT VT CONFIGURATION CATEGORY PROCEDURE: N-UT-64 REV: 7 TC N/A PC,VLV TO PE,EL R-A EXAMINER: EXAMINER: EXAMINER: EXAMINER:

JLL 71 LEVEL: LEVEL: LEVEL: LEVEL:

Total coverage calculated to be approximately The above mentioned weld was ultrasonically inspected. A 1/2 V path calibration with a primary angle of 45 shear wave. This was a single sided exam, due to valve configuration, and a 60 Rlr J/2_

Vpath calibration was also utilized.

Counterbore geometry was recorded with the 60 RL on the intradose of the elbow.

No rejectable indicatins observed.

This examination meet the requirments of Risk Informed item R1.16 RESOLUTION REVIEWED BY ANII:

c LEVEL DATE Page: / OF ACCESS FORMS DATABASE R-3/18/03 EZ' 8

TENNESStE DIGITAL ULTRASONiO REPORT NUMBER VALLEY CALIBRATION AUTHORITY DATA SHEET CALIBRATION DATE: 4/29/Q5 ROJECT: SQN UNIT/CYCLE 2/ 13 CALIBRATION BLOCK NO.: ^ '*7 TEMP: 75 °F ROCEDURE: N-UT-64 REV:  ? TC:

SIMULATOR BLOCK:Rompas 7 277 0 TRANSDUCER MANUFACTURER: K.BA THERMOMETER S/N 573203 DUE DATE 8-9-05 COUPLANT: Ultragel II BATCH: 01225 MODEL: COMP-G S/N:00D8KH ANGLE VERIFICATION SIZE: .375" FREQ: MH BLOCK TYPE: Rompas s/N: 792770 SHAPE: Round # ELEMENTS: 1 # CONS: 0_ NOMINAL ANGLE: 45° ACTUAL ANGLE: 45° CABLE TYPE: RG-174 LENGTHl6' INSTRUMENT MANUFACTURER: Krautkramer DUE DATE: 7/28/05 EXAM TYPE SHEAR LONG D RL DAC MODEL NO.: (, 0 M&TE:/r36302 INSTRUMENT SETTINGS 100 REFLECTOR i REFERENCE MEMORY A SCAN DIRECT. NTC SDH SENSITIVITN M'MBER 80 a"

S M u N 0Tcf< l AXIAL 31 1KSS45 P CIRC n N/A 60 L *FREO 2. O MHz *REJECT: 0 %

l 1

i I ANHLF: 45 deg 'DAMPING:/000 ohms 40 T DELAY 0.000 msec *PULSER SINGLE U ZERO: 8.0469 msec

  • PRR/PRF 20 D VELOCITY .1257 msec TOF: PEAK E RANGE: 2.9 inches POWER: BATTERY J i

! i *DISP. MODE \F W TCG: l_j ON DISPLAY WIDTH 2.9 inches REF. REFLECTOR: FAR SDH GAIN: 43 dB CALIBRATION TIMES AMPLITUDE: 35 % METAL PATH: 1.096 INITIAL TIME: 1040 FINALTIME: 1410 VERIFICATION TIMES j Xh2nS N/A I N/A 4' n/a!5) n/a!6> N/A l

  • PD1 QUALIFIED INSTRUMENT SETTINGS:

VERIFY INSTRUMENT SETTINGS AND CALIBRATION SEQUENCE ARE IN ACCORDANCE WITH TABLE 2 OF THE APPLICABLE PDI QUALIFICATION IMPLEMENTATION PROCEDURE!

LINEARITY CHECK COMMENTS WELD / ITEMS EXAMINED sir- no EXAMINER: ANil:

PAGE ^L OF ACCESS FORMS QATABASE 10-02-03 E2- 1

,#*,

Tennessee DIGITAL ULTRASOIW REPORT NUMBER VALLEY CALIBRATION AUTHORITY DATA SHEET CALIBRATION DATE: 4/29/03 PROJECT: SQN UNIT/CYCLE CALIBRATION BLOCK NO,: S<2 - u7 TEMP:_ 75 °F PROCEDURE: N-UT-64 REV: 7 SIMULATOR BLOCK:Rompas 77277Q TRANSDUCER MANUFACTURER: RTD THERMOMETER S/N 573203 DUE DATE 8-9-05 MODEL: TRLA SAN: 99-43 I COUPLANT: Ultragel II BATCH: 01225 ANGLE VERIFICATION -

SIZE: 8xl4mm FREQ: 2 MH BLOCK TYPE: Rompas s/N: 792770 SHAPE: \ZBct U ELEMENTS: 2 # CONS: 0 NOMINAL ANGLE: 60° ACTUAL ANGLE_:__60_°.

CABLE TYPE: RG-174 LENGTHl6" INSTRUMENT MANUFACTURER: Krautkramer DUE DATE: 7/28/05 EXAM TYPE SHEAR LONG B RL MODEL NO.:

DAC INSTRUMENT SETTINGS uu 1 REFLECTOR REFERENCE MEMORY A SCAN DIRECT. , NTC l SDH SENSITIVITY NUMBER 80 t ' 0

  • M 4

No]

AXIAL 62 IUSS60*

P 1 CIRC. D N/A dB 60 L *FREQ 2. 0 MHz

  • REJECT 0_ %

I ANCLF: 60 deg '*DAMPINC;/Q00 ohms 40 T DELAY 0.000 msec *PULSER DUAL U ZERO: 8.5591 msec 20 D VELOCITY .2329 msec TOF: PEAK E RANGE: 3.500 inches POWER: BATTERY' 0

  • DISP. MODE: F W TCG: ON DISPLAY WIDTH 3.5 inches

\1\C~H REF. REFLECTOR: FAR SDH GAIN:_ 62 dB CALIBRATION TIMES AMPLITUDE: 90 % METAL PATH: 1.531 INITIAL TIME: 1045 FINAL TIME: 1412 VERIFICATION TIMES I M>l3 3o 2) N/a13> N/a!4) N/aI 5) N/aI6) N/a!7> N/aI8> N/A I9> N/A

  • PDI QUALIFIED INSTRUMENT SETTINGS:

VERIFY INSTRUMENT SETTINGS AND CALIBRATION SEQUENCE ARE IN ACCORDANCE WITH TABLE OF THE APPLICABLE PDI QUALIFICATION IMPLEMENTATION PROCEDURE!

LINEARITY CHECK SIGNAL 2 GAIN l SET AMP 80%

COMMENTS WELD /ITEMS EXAMINED SIF-170 p.sPiAY EXAMINER: LtAt-w/^^X-^

ACCESS FORMS DATABASE 1Q-O2-O3 IO

TENNESSEE MANUAL ULTRASONIC REPORT NUMBER VALLEY PIPING EXAMINATION AUTHORITY DATA SHEET PROJECT: SQN UNIT/CYCLE 2 I 13 EXAMINATION DATE 4/29/05 SYSTEM SIS START TIME: 1315 END TIME: 1345 EXREQ: 89E-02 CAT: R-A ITEM NO: RI.16 EXAM SURFACE: Q'D BOD WELD I.P.: SIF-170 MATERIAL TYPE: QCS £SS QCSCL QCCSS CONFIG.: PQVLV TO PE.EL SURFACE TEMP. 80 PYRO NO. 573203 FLOW^

PROCEDURE: N-UT-64 REV: 7 TC: EXAMINATION ANGLE 45 DEC. 60 RL DEC.

Wo

REFERENCE:

WELD CENTER LINE AXIAL SCAN SENSITIVITY 43 dB 62 Lo

REFERENCE:

TDC CIRC. SCAN SENSITIVITY 43 dB N/A L (in) FROM REF. AT MAX AMP MAX EXAM IND NOM. INDICATION INFORMATION:

AMP NO. NRI NO. L1 L Max L2 WMAX MPMAX DMAX ANG. TYPE, DAMPING, ETC.

% DAC 3-14 45 45 18" 21" 1.10 1.1 N/A 100 15" 60 counterbore 45 REMARKS/LIMITATIONS No scan 3 due to Valve configuration. Mainatined 10% ID roll No Reject able Indications EXAMINER: ANH: A.

(EXAMINER: DATE REVIEWED BY: T7fi LEVEL:77T DATE S/j/of PAGE M OF &

ACCESS FORMS DATABASE 10/02/03 EZ -

o z

o UJ O

>

CO o

l\

n Or j

Ui U

O

(

U 03

\

Z o

> E

REPORT NO:

WALL THICKNESS PROFILE SHEET PROJECT:, SQN WELD NO: S If -

UNIT: SYSTEM:

Record Thickness Measurements As Weld

  • Weld Ed Indicated, Including Weld Width, Centerllne Edge-To-Edge At 0*

Position 9 0* 18 0* 270*

\ T

\1 "lA A

'.06 \

i.a CROWN HEIGHT: .'0 DIAMETER: 10' CROWN WIDTH: _ I.I' WELD LENGTH:.

3H. 15"'

V At-V £ EL&

FLOW

?> ANII:

REVIEWEO BY: h LEVEL: < rii/t>b^

oS PAGE , . OF.

TVA 196^8 (NP-5-89)

ENCLOSURE 3 ISI PROGRAM DRAWINGS Request for Relief Number ISI Program Drawings 1-ISI-28 ISI-0504-C-02 2-ISI-28 ISI-0298-C-02 1-ISI-29 ISI-0504-C-02

. 2-ISI-29 ISI-0298-C-02 1-ISI-30 ISI-0504-C-02 2-ISI-30 ISI-0298-C-02 1-ISI-31 ISI-0504-C-02 2-ISI-31 ISI-0298-C-02 2-ISI-33 ISI-0002-C-06 E3-1

REFERENCE DRAWINGS A-7541 2-SI-507-1W 2-SI-510-1W 2-0R-63-552 SI-2093C SI-20930 SI-2O98 SI-2O97 63-634 SI-2096 63-634-9C SlS-273 SIF-153-POINT B FAN ROOM NO, 4 3561 63-561-BC REACTOR BUI SIF-169 LOWER CONTAINMENT

^SIS-280 J0X1QX6 8 mX8 mX6 '

REACTOR BUILDINC RED. TEE ACCESS ROOM SIF-173 SIS-4 1O FAN ROOM NO. 2 SIF-172A SIF-172 SI-2255B B"X6m RED MATERIAL SPECIFICATIONS SI-225SA-1 SIS-266 ^SIS-272 ACCUMULATOR ROOM NO S1-22S5 SIS-271 ASHE CC-2 (EQUIVALENT)

SI-2253 SIS-267 SI-2252-^,

-SIS-286 EL .71 8'-3 SI-225i SIF-162 SIS-268 1-2250 -SIS-285 6'LSCHL160AktL 8' SCH 140

~AS' *~40J TP~3n 63-632 3- 632-9C 10* SCH 40S (WELDED)

FOR ADDITIONAL SPECS SEE SHFFT 4 SIS-269

\ EL.7O2'-O' 2L_ L _-iBL _L ciw [_ kr* _j t-24-or

_.._ PIPING WAS EXEMPT

%MET%ECT-%N2xV-L71 T£*HTSSE£ VALLEY AUTHORtTY SI-2O99 WAS CUT OUT

^MADE OUR INC U2C12 O3-010248-000. CONTINUED Nuclear plani AT POINT C SAFETJ INJECTION SrSTEM WELD LOCATIONS SI-0OQ2-C-O6

REFERENCE DRAWINGS IS1-0297-A OUTLET NOZZLE I SI-0392-A INLET NOZZLE CONTRACT NO. 68C60-91934 (N2M-2-3)

FJG. 7-25 DWC NO. 306t6-t050(FlG 7.18)

MATERIAL SPECIFICAT 1ONS~\_ a W06 THE VESSEL SHELL SECTIONS ARE MACHINED^

FORCINGS FABRICATED OF A-508. CLASS 2.

MANGANESE-MOLYBDENUM STEEL AND ARE CLAD WITH WELD DEPOSITED AUSTEN 1 TIC 1 STAINLESS STEEL.

OUTLET NOZZLE CLADDING INLET NOZZLE CLADDING THE VESSEL FLANGE SECTION IS FABRICATED '

N15CLAD NttCLAD OF A-508, CLASS 2. MANGANESE-MOLYBDENUM

)

Nt6CLAD NI2CLAD STEEL AND IS CLAD INTERNALLY AND ON THE NI7CLAD ^^^ 0ZZZT GASKET FACE WITH 'WELD DEPOSITED AUSTEN I TIC STAINLESS STEEL.

NtaCLAD THE LOWER-HEAD SECTIONS ARE FABRICATED s~ outlet nozzle welds. - OF A-533. GR.B. CLASS f, MANGANESE-(reactor vessel coordinates MOLYBDENUM STEEL. AND ARE CLAD WITH WELD

^^_^ N15 - 22° INLET NOZZLE WELDS.,

DEPOSITED AUSTEN I TIC STAINLESS STEEL.

N16 - 158° UPPER MIDDLE (REACTOR VESSEL COORDINATES N\7 - 202° W05 K fjfl -- 67° Ntt 67° SHELL THE NOZZLE FORCINGS ARE FABRICATED OF N18 - 338° SEE NOTE N12 - 113° Nt3 - 247° A-508. CLASS 2. MANGANESE-MOLYBDENUM N14 - 293° STEEL AND ARE CLAD WITH WELD DEPOSITED AUSTENITIC STAINLESS STEEL.

W04-05 SEE NOTE I EACH NOZZLE SAFE END WELD IS A STAINLESS STEEL TYPE 304 WELD BUILD UP (BUTTERING) 00 LOWER MIDDLE ASME CC-1 (EQUIVALENT)

SHELL WO3-04 -

SEE NOTE f NOTES:

VESSEL INSIDE SURFACE ) t. W03-04. W04-05, St W05-06 ARE CLAD 0.157" NOMINAL J 8ELTLINE REGION WELDS W02 2. FOR UNIT 1 DWG. SEE CHM-2343-C.)

A / SIX ORANGE PEEL WELDS ,

A (REACTOR VESSEL COORDINATES V W2A - 0° W2B -60° W2C - 120° W2D - 180° WOI-02 )

W2E - 240° W2F - 300° j_ I [ [

OiAHGll DHAtlNG DHAtlNG NO. an0~SI/1 fftOU B W C. ADD VAl 'i SMCS, Cl AD OJUiHSlQH.

SlQH. AND ADD -HlACtQfi VfSsYl COOhOlHAllS' 10 HO/flf it I OS

^"11 _ JCC^ I ClB_ [ _ ^2+/-'92 AND ADD NO//LC RlftfiiNCL OHaHnCS suauur[D~\ APpRoveo I oaic 1CNNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT UNIT 2 Hi AC 1 OR VESSEL btAM Wf.LUS

[CAV UA IN 1A INtD ONA VINC

-029d -C-0~2 \02

REFERENCE DRAWINGS CONTRACT NO, 68C60-9f034 (N2M-2-3)

FIG. 7-25 DWG NO. 3O616-1O5O(F1G 7.18)

MA TERIAL SPECIFICATIONS THE VESSEL SHELL SECTIONS ARE MACHINED FORGINGS FABRICATED OF A-509, CLASS 2.

MANGANESE-MOLYBDENUM STEEL AND ARE W06 CLAD WITH WELD DEPOSITED AUSTEN I TIC STAINLESS STEEL, THE VESSEL FLANGE SECTION IS FABRICATED OF A-508. CLASS 2. MANGANESE-MOLYBDENUM STEEL AND IS CLAD INTERNALLY AND ON THE INLET NOZZLE CLADDING GASKET FACE WITH WELD DEPOSITED OUTLET NOZZLE CLADDING - AUSTEN I TIC STAINLESS STEEL.

NltCLAD NI5CLAD NI2CLAD NI6CLAD THE LOWER-HEAD SECTIONS ARE FABRICATED NI3CLAD NI7CLAD OF A-533. GR.B. CLASS t, MANGANESE -

N14CLAD Nt8CLAD MOLYBDENUM STEEL. AND ARE CLAD WITH WELD DEPOSITED AUSTENITIC STAINLESS STEEL.

OUTLET NOZZLE WELDS.

REACTOR VESSEL COORDINATES INLET NOZZLE WELDS. THE NOZZLE FORGINGS ARE FABRICATED OF Nt5 - 22° A-508. CLASS 2. MANGANESE-MOLYBDENUM REACTOR VESSEL COORDINATES N16 - 158° Nil - 67° STEEL AND ARE CLAD WITH WELD DEPOSITED N17 - 202° W05-06 AUSTENITIC STAINLESS STEEL.

NI2 - tf3° Nt9 - 338° Nt3 - 247° EACH NOZZLE SAFE END WELD IS A STAINLESS N!4 - 293° STEEL TYPE 304 WELD BUILD UP (BUTTERING)

ASME CC-f (EQUIVALENT)

NOTES:

1. W03-04. W04-05. k W05-06 ARE VESSEL INSIDE SURFACE BEL TL1NE REGION WELDS CLAD 0.157' NOMINAL
2. FOR UNIT 2 DWG. SEE ISI-0298-C
3. THIS DWG SUPERCEDES CHM-2343-C-02 SIX ORANGE PEEL WELDS REAC10R VESSEL COORDINATES W2A - 0° W2B -60° W2C - 120° WOt-02 W2D - 180° W2E - 240° W2F - 300° BY l CHCCKFD \SU&HlTUD\ APPROVED \

1ENNESSLL VALLtr AU1H0H1TY SEQUOYAH NUCLEAR PLANT UNIT 1 REACIOR VCSSEt SFAM WELDS DA ft: I SCALf: NO I !O SCALE APPROVfD: \Ca'J HdAlNlAUii'O QRAiTlNC\

J ~ST~- O 50 '4 -C -0 2 TOO

ENCLOSURE 4 TVA'S PROCEDURE FOR CALCULATION OF THE ASME CODE COVERAGE FOR SECTION XI REQUEST FOR RELIEF 2-ISI-33 E4-1

NONDESTRUCTIVE EXAMINATION PROCEDURE Procedure No. N-GP-28 TVA Nuclear Power Revision 4 Page 1 of 8 W47 031219 000 QA RECORD CALCULATION OF ASME CODE COVERAGE FOR SECTION XI NDE EXAMINATIONS "QUALITY RELATED" Prepared By: Robert E. Hardawav Date: 12/18/03 Technical Review: Joel W. Whitaker NDE Level III, Date: 12/18/03 ISO Approval: W. Ed Freeman Date: 12/18/03

NONDESTRUCTIVE EXAMINATION PROCEDURE Procedure No. N-GP-28 TVA Nuclear Power Revision 4 Page 2 of 8 Rev. No. Date Description 0 4/3/96 Initial issue.

1 8/15/97 Incorporate TC 97-09.

2 10/18/00 General revision to incorporate 10CFR50.55a ruling change which implements Appendix VIII 5/24/01 Revised to upgrade procedure to ASME Section XI 1995 Edition with Addenda through 1996 12/18/03 Revised to incorporate corrective actions from PER 03-014859-000.

£4-3

NONDESTRUCTIVE EXAMINATION PROCEDURE Procedure No. N-GP-28 TVA Nuclear Power Revision 4 Page 3 of 8 The scope of this procedure is to provide generic guidelines for calculating the ASME Section XI code coverage and augmented examination coverage obtained during volumetric and surface examinations. This procedure incorporates the requirements of Code Case N-460 and NRC Information Notice 98-42. This procedure is not applicable for calculating the examination coverage for RPV examinations performed in accordance with Appendix Vlll.

2.0 Purpose This procedure applies to the calculation of ASME Section XI Code coverage for vessel welds (excluding the RPV welds performed in accordance with Appendix Vlll) piping welds, and integral attachments. This procedure applies when performing surface, volumetric or visual examinations and may be used as a guide when calculating the examination coverage for preservice and inservice examinations. Coverage limitations may be due to an obstruction, interference, geometric configuration or other applicable reason.

3.0 References 3.1 ASME Code Case N-460 3.2 10CFR 50.55a, as amended by the Federal Register Notice, Vol. 64, No. 183, dated September 22, 1999 (Final Rule)- Implementation of Appendix Vlll as executed by the Performance Demonstration Initiative (PDI) Program Description Document, Rev. 1, Change 1.

3.3 Guideline for the Implementation of Appendix Vlll and 10CFR 50.55a, Rev. D, April 18,2000 3.4 NRC Information Notice 98-42 3.5 SQN PER 03-014859-000 4.0 Definitions 4.1 Examination Coverage- The percentage of the examination surface or volume obtained during the performance of the examination.

4.2 Examination Surface- The surface of the weld and base material required to be examined by ASME Section XI or other requirement using a surface and/or visual examination method as applicable.

4.3 Examination Volume- The volume of weld and base material required to be examined by ASME Section XI or other requirement using a volumetric examination method.

4.4 Scan Limitation- the inability to scan the surface(s) as required by procedure due to interferences.

4.5 Surface Limitation- the inability to perform a surface examination of the required surface(s) because of an interference.

£4-4

NONDESTRUCTIVE EXAMINATION PROCEDURE Procedure No. N-GP-28 TVA Nuclear Power Revision 4 Page 4 of 8 4.6 Volumetric Limitation- the inability to examine the required volume because of the geometric configuration, a physical interference, or a metallurgical condition of the material being examined.

5.0 General 5.1 During the performance of inservice inspections, ASME Section XI requires examination coverage to be essentially 100% of the weld area or volume. For examination coverage less than 100%, TVA has implemented ASME Code Case N-460 which states that when the entire examination volume or area cannot be examined due to interference by another component or part geometry, a reduction in examination coverage for Class 1 or Class 2 welds may be accepted provided the reduction in coverage for that weld is less than 10%. (NRC Information Notice 98-42 further defines the >90% rule to include all welds and other areas required by ASME Section XL 5.2 Surface and/or visual examinations are typically conducted on the weld area plus a defined amount of base material on each side of the weld. Volumetric examinations specify a particular volume to be examined. The Section XI required examination volume or surface examination area for each type of weld is depicted in figures of IWB-2500, IWC-2500 and IWD-2500 as applicable. As depicted for piping welds, volume width generally constitutes the weld plus 1/4t on each side while volume thickness generally constitutes the lower 1/3 of the piping thickness for the length of the weld. The exception normally includes code category B-0 which includes the weld plus 1/2 inch and full volume for the length of the weld. As depicted, for vessel welds, the volume width generally constitutes the weld plus 1/2t on each side of the weld while volume thickness generally constitutes the entire component thickness (i.e. full volume). The volume changes with variations in weld configuration (e.g. transition between different pipe thickness or vessel weld configurations).

Note: Risk-Informed (Rl) programs require larger volumes in certain areas.

5.3 The required examination volume or area shall be verified prior to calculation of the limitation.

6.0 Documenting and Calculating Examination Coverage 6.1 While performing a visual, surface or ultrasonic examination, the NDE Examiner shall make every attempt to examine 100 percent of the examination area or volume.

6.2 When practical, the two beam path directions for ultrasonic examinations should be performed from two sides of the weld or additional angles employed in order to maximize coverage.

6.3 If 100% percent of the examination surface or volume cannot be examined, the NDE Examiner should perform the following under the direction of the inspection coordinator or the NDE Level III:

6.3.1 Perform additional examinations with higher angles in order to maximize cover for ultrasonic exams.

6.3.2 Perform another surface method (i.e., PT in lieu of MT) in order to maximize coverage.

NONDESTRUCTIVE EXAMINATION PROCEDURE Procedure No. N-GP-28 TVA Nuclear Power Revision 4 Page 5 of 8 6.3.3 Perform alternative NDE methods if applicable.

6.4 The examiner shall accurately document all limitations, obstructions, interferences, geometric configurations or other applicable reasons for not obtaining the required code coverage. This information shall be validated and verified by the assisting examiner or independent verifier and documented in the NDE data report.

6.5 The examiner shall document the limitation on a sketch. Examination coverage estimates may be performed by the examiner or the reviewer.

7.0 Calculation Basis 7.1 Volumetric Examinations- Piping Welds and Vessels 2 inches and less in thickness a) Examination volume coverage may be increased as previously discussed or by use of refracted longitudinal wave techniques on stainless steel or dissimilar metal welds. Use of refracted longitudinal waves to penetrate stainless steel weld material will increase the examination volume coverage by the amount depicted on the examination coverage drawing.

b) Estimates shall be derived by estimating coverage based on two-beam path direction coverage of the complete examination. Each scan direction equals 25% (downstream, up-steam, clockwise, counterclockwise.)

(Reference Figure 1) c) The effects of adjacent component interferences (e.g. welded lug attachments) along the weld length are also taken into account with the reduction in coverage identified as a percentage of reduced volume.

8.0 Visual and Surface Examinations - Piping Welds And Integral Attachments 8.1 Examination area coverage calculations are based upon one of the following suppositions:

a) The total examination area is calculated, typically length x width, then the total area of limitation or interference is subtracted from the total examination area.

b) The area of achieved coverage is divided by the total examination area for percentage of examination achieved.

9.0 Ultrasonic Examinations - Vessel Welds

NONDESTRUCTIVE EXAMINATION PROCEDURE Procedure No. N-GP-28 TVA Nuclear Power Revision 4 Page 6 of 8 NOTE: THIS IS NOT APPLICABLE FOR APPENDIX VIII EXAMINATIONS OF THE RPV WELDS.

9.1 Examination volume coverage calculations are based upon the following suppositions:

a) To achieve full examination coverage nine different scans are required for a typical vessel weld or nozzle examination. The following may be .used for other vessel configurations:

1) 0 degree (weld metal scan)
2) 45 degree Transverse-scan from vessel side of the weld
3) 45 degree Transverse-scan from nozzle side of the weld
4) 60 degree Transverse-scan from vessel side of the weld
5) 60 degree Transverse-scan from nozzle side of the weld
6) 45 degree Parallel-scan CW direction
7) 45 degree Parallel-scan CCW direction
8) 60 degree Parallel-scan CW direction
9) 60 degree Parallel-scan CCW direction 9.2 The examination volume achieved for each above examination scan shall be obtained and documented on a percentage basis. This calculation considers the required examination volume required per the ASME Section XI Code.

a) The total examination coverage may be calculated by averaging the exam volume coverage for all nine scans.

10.0 PDI Implementation for Piping Welds 10.1 Where examination from both sides is not possible, full coverage credit may be claimed from a single side for ferritic welds provided the examiner is qualified for single sided examination. Current technology is not capable of reliably detecting or sizing flaws on the far side of an austenitic weld for configurations common to US nuclear applications. Therefore, examination of austenitic material welds shall be performed from both sides or a scan limitation shall be documented.

10.2 The NDE Level III shall make an evaluation in the Weld Resolution document regarding total examination coverage (best effort) as calculated above in Section 7.0. In addition, a coverage evaluation which considers the PDI Implementation Guideline shall also be indicated in the Weld Resolution sheet. These two coverage evaluations shall be reported to the ISI Programs Engineer for incorporation into the Relief Request.

10.3 Typically a one-sided austenitic weld examination with no circumferential restrictions would be indicated as 75% examination coverage or 50% if circumferential scans were limited to one side.

NOTE: These requirements do not apply to augmented examinations of piping welds.

11.0 Responsibilities

NONDESTRUCTIVE EXAMINATION PROCEDURE Procedure No. N-GP-28 TVA Nuclear Power Revision 4 Page 7 of 8 11.1 The examiner, assisting examiner or designee shall document the amount of code coverage obtained after all necessary steps to perform additional examinations has been completed in order to maximize coverage. The documentation including verification of limitations shall become part of the examination weld data package.

11.2 The documentation may be reviewed by another individual with the same or higher NDE certification.

11.3 The NDE Level III or data reviewer may review the calculations in order to verify that the information is accurate and correct.

11.4 The NDE Level Hi may recalculate the examination coverage to obtain a more accurate value of the examination surface or volume examined. The calculation shall be documented on the exam report.

11.5 The NDE Level III may require an alternate examination technique or method, or request that the interference be removed. For nozzle examinations, supplemental scans from the nozzle bore or flange face may provide complete coverage of the weld.

11.6 If the examination coverage indicates less than 90 percent of the required examination volume or surface, the site ISI Program Engineer shall be notified.

11.7 The site ISI supervisor shall- ensure that examination results are accurately documented and incorporate results into a Request for Relief if necessary.

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.^W^k NONDESTRUCTIVE EXAMINATION PROCEDURE Procedure No. N-GP-28 TVA Nuclear Power Revision 4 Page 8 of 8 IH-3230 APPENDIX IB MANDATORY IH-3310 Interference between shoe and weld crown GENERAL NOTE:

For this example of interference with a VjV examination applied from both sides, only the E-F-G-H portion of the examination volume receives two direction coverage, while volumes C-G-F and H-D-E receive one direction coverage. In this case, the examination beam path shall be inaeased to HV {0.0. to 1.0. and back towards O.D. for V7t) to provide the required two direction coverage over the examination volume. Use of a %V examination beam path (O.D. to I.D. to Vif) provides additional beam path (past %f) to help in obtaining required coverage when examination part thickness f increases.

FIG. 111-3230-1 EXAMPLE OF PHYSICAL RESTRICTIONS TO THE WELD EXAMINATION Figure 1

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ENCLOSURE 5 ISwT EXAMINATION AREA COVERAGE REPORT FOR SON UNITS 1 AND 2 REACTOR VESSEL WELDS REQUESTS FOR RELIEF 1.2-ISI-28, 1.2-ISI-29, 1.2-ISI-30 AND 1.2-ISI-31 Request for Relief Number Area of Coverage Report 1-ISI-28 R8386 2-ISI-28 R6761 1-ISI-29 R8386 2-ISI-29 R6761 1-ISI-30 R8386 2-ISI-30 R6761 1-ISI-31 R8386 2-ISI-31 R6761 E5-1

APPENDIX E RPV EXAMINATION COVERAGE REPORT ES-Z

EXAMINATION AREA COVERAGE REPORT FOR SEQUOYAH NUCLEAR PLANT UNIT 2 This appendix describes examination coverage achieved during the 2005 in-service inspection of the Sequoyah Nuclear Plant Unit 2 (SQN2) reactor pressure vessel (RPV). The examinations were performed using automated ultrasonic (AUT) scanning equipment and AUT data recording/analysis systems. The target scope of the RPV examinations included 100 percent of the accessible weld and/or component length of the following:

1) Circumferential shell welds, including the vessel shell to flange weld
2) Lower head meridional shell welds
3) Nozzle to shell welds
4) Nozzle to Safe End and Safe End to Nozzle Welds Limitations were encountered at SQN2 while examining the vessel, nozzle to shell, and lower head shell welds due to various physical conditions, such as the bottom head penetrations, the core barrel lugs, the outlet nozzle integral extensions, the inlet nozzle inner radii, and the flange configuration. Typically, limitations are not encountered on the nozzle to--safe end and safe end to nozzle welds, except for severe inside surface contour variations, which were not encountered at SQN2.

1 Examination Coverage Requirements for Vessel Circumferential and Meridional Welds The ISwT procedures for shell weld examinations are qualified for both single- and double-sided examinations. The double-sided technique, requiring two examination angles and four search units, is used when access is not restricted. The single-sided examination technique, requiring three examination angles and four search units, is utilized to provide additional coverage when access is restricted. The examination coverage requirements for these techniques are described below.

Single-Sided Examination (Reflectors Oriented Parallel and Transverse to the Weld)

1) The inner 3.25 inches including the weld metal and adjacent base metal for lA t either side of the weld fusion line must be completely scanned with both SLIC40 (50 and 70 degrees, shear and longitudinal waves) search units.
2) The weld metal and adjacent base material in the outer volume beyond 3.25 inches must be completely scanned with both 45° and 55° Duplex (45 and 55 degrees shear wave) search units.

Double-Sided Examination (Reflectors Oriented Parallel and Transverse to the Weld)

1) The inner 3.25 inches including the weld metal and adjacent base metal for lA t either side of the weld fusion line must be completely scanned with both SLIC 40 search units.
2) The weld metal and adjacent base material in the outer volume beyond 3.25 inches must be completely scanned with both 55° Duplex search units.

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r 2 Examination Co *erage Requirements for Nozzle to Shed Welds

. Examination of the nozzle to shell welds is performed using the techniques described above from the vessel inside surface plus a PDI-qualified Phased Array examination performed from the nozzle bore. Coverage requirements for nozzle to shell weld examinations conducted from the vessel inside surface are similar to those described above, except that the weld metal and adjacent base material for !/z" beyond the weld fusion line must be scanned with the applicable search units. The Phased Array procedure was designed to sweep two sets of sound beam angles (5 through 40 degrees longitudinal wave and 35 through 45 degrees shear wave) through the examination volume from the nozzle bore and achieve full coverage.

3 Examination Coverage Requirements for Nozzle to Safe End and Safe End to Nozzle Welds (Dissimilar Metal Welds)

Examination of the Safe End (Dissimilar Metal) welds is performed using a PDI-qualified Phased Array procedure that is designed to sweep one set of sound beam angles (60-88 degrees longitudinal wave) through the examination volume from the inside surface of the weld to achieve full coverage in four directions.

EXAMINATION COVERAGE CALCULATION The following contains a description of the examination coverage calculation process:

1. Determine the examination scan ("x" and uy") coordinates necessary to obtain 100% of the required weld coverage (reference the examination planned "x" and "y" coordinates).

re

2. Multiply the delta difference of the planned "x" and "y" coordinates by each other to determine the planned scan area necessary to obtain 100% of the required weld coverage for both transverse and parallel examinations.
3. Multiply the delta difference of the actual "x" and "y" coordinates by each other to determine the actual scan area for both transverse and parallel examinations.
4. Divide the parallel actual scan area by the parallel planned scan area and the transverse actual scan area by the transverse planned scan area to determine the coverage percentage for each type of examination.
5. Compute the average of the parallel and the transverse examination values for the final coverage percentage.

Sequoyah Nuclear Power Station, Unit 2 2005 Reactor Vessel Inservice Examination UT Coverage Summary  :.;*..;: w§id ..,-.. Exam Area BSifti V Beam Beam Code

  • fcUmbgrr; ^fidirttififcatioh 'j& Direction(s) Coverage Remirks /':...,' ' -/;s 000100 W03-04 Lower Shell -to- SLIC 40/55° Parallel 2 directions 100%

Lower Middle Shell SLIC 40/55° Transverse 2 directions 100%

Average 100%

000200 W04-05 Lower Middle Shell SLIC 40/55° Parallel 2 directions 100%

-to- Upper Middle SLIC 40/55° Transverse 2 directions 100%

Shell Average 100%

000300 W05-06 Upper Middle Shell SLIC 40/55° Parallel 2 directions 82% Limited examination due to the

-to- Upper Shell SLIC 40/55° Transverse 2 directions 100% outlet nozzle integral extensions and Average 91% inlet nozzle bore radii.

000400 W02-03 Bottom Head -to- SLIC 40/55° Parallel 2 directions 79% Limited examination due to the Lower Shell SLIC 40/55° Parallel 2 directions 75% proximity of the core barrel stabilizing Average 77% lugs.

000500 W01-02 Bottom Head Cap SLIC 40/55° Parallel 2 directions 51% Limited examination due to the

-to- Bottom Head SLIC 40/55° Transverse 2 directions 57% bottom head penetrations.

Spherical Ring Average 54%

000600 W06-07 Upper Shell SLIC 40/55° Parallel 2 directions 91% Limited examination due to the

-to- Flange SLIC 40/55° Transverse 2 directions 95% flange design.

Average 93%

000900 W2A Lower Head SLIC 40/55° Parallel 2 directions 100% Limited examination due to the Meridional @ 0° SLIC 40/55° Transverse 2 directions 85% bottom head penetrations and core Average 93% barrel stabilizing lugs.

001000 W2B Lower Head SLIC 40/55° Parallel 2 directions 100% Limited examination due to the Meridional @ 60° SLIC 40/55° Transverse 2 directions 81% bottom head penetrations and core Average 91% barrel stabilizing lugs.

001100 W2C Lower Head SLIC 40/55° Parallel 2 directions 100% Limited examination due to the Meridional 120° SLIC 40/55° Transverse 2 directions 81% bottom head penetrations and core Average 91% barrel stabilizing lugs.

001200 W2D Lower Head SLIC 40/55° Parallel 2 directions 100% Limited examination due to the Meridional @ 180° SLIC 40/55° Transverse 2 direction^ 83% bottom head penetrations and core Average 92% barrel stabilizing lugs.

001300 W2E Lower Head SLIC 40/55° Parallel 2 directions 94% Limited examination due to the Meridional @ 240° SLIC 40/55° Transverse 2 directions 86% bottom head penetrations and core Average 90% barrel stabilizing lugs.

001400 W2F Lower Head SLIC 40/55° Parallel 2 directions 84% Limited examination due to the Meridional @ 300c SLIC 40/55° Transverse 2 directions 75% bottom head penetrations and core Average 80% barrel stabilizing lugs.

Sequoyah Nuclear Power Station, Unit 2 2005 Reactor Vessel Inservice Examination UT Coverage Summary Weld Exam Area Beam Exam Beam Code Number ; Number *  :,fdehtincation^^:^ i Angie(s) i Difiecti6h{s) CbvefagS '- :v': - RefnSrks '"-- ^

001900 N-15 Outlet Nozzle SLIC 40 Parallel 2 directions 78% Limited examination due to the nozzle

-to- Shell @ 22° SLIC 40/55° Transverse 2 directions 54% integral extension.

PA-16 Parallel (Bore) 1 direction 100%

Average 72%

001500 N-11 Inlet Nozzle SLIC 40 Parallel 2 directions 84% Limited examination due to the nozzle

-to- Shell @ 67° SLIC 40/55° Transverse 2 directions 100% inner radius.

PA-16 Parallel (Bore) 1 direction 100%

Average 96%

001600 N-12 Inlet Nozzle SLIC 40 Parallel 2 directions 84% Limited examination due to the nozzle

-to-Shell 113° SLIC 40/55° Transverse 2 directions 100% inner radius.

PA-16 Parallel (Bore) 1 direction 100%

Average 96%

002000 N-16 Outlet Nozzle SLIC 40 Parallel 2 directions 78% Limited examination due to the nozzle

-to-Shell 158° SLIC 40/55° Transverse 2 directions 55% integral extension.

PA-16 Parallel (Bore) 1 direction 100%

Average 72%

002100 N-17 Outlet Nozzle SLIC 40 Parallel 2 directions 78% Limited examination due to the nozzle

-to- Shell @ 202° SLIC 40/55° Transverse 2 directions 55% ntegral extension.

PA-16 Parallel (Bore) 1 direction 100%

Average 72%

001700 N-13 Inlet Nozzle SLIC 40 Parallel 2 directions 88% Limited examination due to the nozzle

-to- Shell @ 247° SLIC 40/55° Transverse 2 directions 100% nner radius.

PA-16 Parallel (Bore) 1 direction 100%

Average 97%

001800 N-14 Inlet Nozzle SLIC 40 Parallel 2 directions 82% Limited examination due to the nozzle

-to- Shell @ 293° SLIC 40/55° Transverse 2 directions 90% nner radius.

PA-16 Parallel (Bore) 1 direction 100%

Average 91%

002200 N-18 Outlet Nozzle SLIC 40 Parallel 2 directions 78% Limited examination due to the nozzle

-to- Shell @ 338° SLIC 40/55° Transverse 2 directions 55% ntegral extension.

PA-16 Parallel (Bore) 1 direction 100%

Average 72%

Sequoyah Nuclear Power Station, Unit 2 2005 Reactor Vessel Inservlce Examination UT Coverage Summary Weld Exam Area .:.;: Beam J *;;:;-';v./Exam ., *,,,. ;-^.Ete<<fii;;.:r Code

^ Angi§(sj;'. Sdverap ., . , . ' RSm^ks'.; ^.^:-\.

003500 RC-09-SE Outlet Nozzle PA 22 Parallel 2 directions 100%

-to-Pipe @ 22° PA 22 Transverse 2 directions 100%

Average 100%

003600 RC-16-SE Elbow -to- Inlet PA 22 Parallel 2 directions 100%

Nozzle @ 67° PA 22 Transverse 2 directions 100%

Average 100%

003700 RC-08-SE Elbow -to- Inlet PA 22 Parallel 2 directions 100%

Nozzle 113° PA 22 Transverse 2 directions 100%

Average 100%

003800 RC-01-SE Outlet Nozzle PA 22 Parallel 2 directions 100%

-to-Pipe @ 158° PA 22 Transverse 2 directions 100%

Average 100%

003900 RC-25-SE Outlet Nozzle PA 22 Parallel 2 directions 100%

-to-Pipe @ 202° PA 22 Transverse 2 directions 100%

Average 100%

004000 RC-32-SE Elbow -to- Inlet PA 22 Parallel 2 directions 100%

Nozzle @ 247° PA 22 Transverse 2 directions 100%

Average 100%

004100 RC-24-SE Elbow -to- Inlet PA 22 Parallel 2 directions 100%

Nozzle @ 293° PA 22 Transverse 2 directions 100%

Average 100%

004200 RC-17-SE Outlet Nozzle PA 22 Parallel 2 directions 100%

-to-Pipe @ 338° PA 22 Transverse 2 directions 100%

Average 100%

APPENDIX E RPV EXAMINATION COVERAGE REPORT

EXAMINATION AREA COVERAGE REPORT FOR SEQUOYAH NUCLEAR PLANT UNIT 1 This appendix describes examination coverage achieved during the 2006 in-service inspection of the Sequoyah Nuclear Plant Unit 1 (SQN1) reactor pressure vessel (RPV). The examinations were performed using automated ultrasonic (AUT) scanning equipment and AUT data recording/analysis systems. The target scope of the RPV examinations included 100 percent of the accessible weld and/or component length of the following:

1) Circumferential shell welds, including the vessel shell-to-flange weld
2) Lower head meridional shell welds
3) Nozzle-to-shell welds
4) Nozzle-to-Pipe and Elbow-to-Nozzle Welds Limitations were encountered at SQN1 while examining the vessel, nozzle-to-shell, and lower head shell welds due to various physical conditions, such as the bottom head penetrations, the core barrel lugs, the outlet nozzle integral extensions, the inlet nozzle inner radii, and the flange configuration. Typically, limitations are not encountered on the nozzle-to-pipe and elbow-to-nozzle welds, except for severe inside surface contour variations, which were not encountered at SQN1.

1 Examination Coverage Requirements for Vessel Circumferential and Meridional Welds The ISwT procedures for shell weld examinations are qualified for both single- and double-sided examinations. The double-sided technique, requiring two examination angles and four search units, is used when access is not restricted. The single-sided examination technique, requiring three examination angles and four search units, is utilized to provide additional coverage when access is restricted. The examination coverage requirements for these techniques are described below.

Single-Sided Examination (Reflectors Oriented Parallel and Transverse to the Weld)

1) The inner 3.25 inches including the weld metal and adjacent base metal for Vz t either side of the weld fusion line must be completely scanned with both SLIC40 (50 and 70 degrees, shear and longitudinal waves) search units.
2) The weld metal and adjacent base material in the outer volume beyond 3.25 inches must be completely scanned with both 45° and 55° Duplex (45 and 55 degrees shear wave) search units.

Double-Sided Examination (Reflectors Oriented Parallel and Transverse to the Weld)

1) The inner 3.25 inches including the weld metal and adjacent base metal for Vi t either side of the weld fusion line must be completely scanned with both SLIC 40 search units.
2) The weld metal and adjacent base material in the outer volume beyond 3.25 inches must be completely scanned with both 55° Duplex search units.

2 Examination Coverage Requirements for Nozzle-to-Shell Welds Examination of the nozzle-to-shell welds is performed using the techniques described above from the vessel inside surface plus a PDI-qualified Phased Array examination performed from the nozzle bore. Coverage requirements for nozzle to shell weld examinations conducted from the vessel inside surface are similar to those described above, except that the weld metal and adjacent base material for V4" beyond the weld fusion line must be scanned with the applicable search units. The Phased Array procedure was designed to sweep two sets of sound beam angles (5 through 40 decrees longitudinal wave and 35 through 45 degrees shear wave) through the examination volume from the nozzle bore and achieve full coverage.

3 Examination Coverage Requirements for Nozzle-to-Pipe and Elbow-to-Nozzle Welds (Dissimilar Metal Welds)

Examination of the Pipe (Dissimilar Metal) welds is performed using a PDI-qualified Phased Array procedure that is designed to sweep one set of sound beam angles (60-88 degrees longitudinal wave) through the examination volume from the inside surface of the weld to achieve full coverage in four directions. ° EXAMINATION COVERAGE CALCULATION The following contains a description of the examination coverage calculation process:

1. Determine the examination scan ("x" and "y") coordinates necessary to obtain 100% of the required weld coverage (reference the examination planned "x" and "y" coordinates).
2. Multiply the delta difference of the planned "x" and "y" coordinates by each other to determine the planned scan area necessary to obtain 100% of the required weld coverage for both transverse and parallel examinations.
3. Multiply the delta difference of the actual "x" and "y" coordinates by each other to determine the actual scan area for both transverse and parallel examinations.
4. Divide the parallel actual scan area by the parallel planned scan area and the transverse actual scan area by the transverse planned scan area to determine the coverage percentage for each type of examination.
5. Compute the average of the parallel and the transverse examination values for the final coverage percentage.

Sequoyah Nuclear Power Station, Unit 1 2006 Reactor Vessel Inservice Examination UT Coverage Summary Weld Exam Area Beam Exam Beam Code Number Number Identification Angle(s) Type Directions) 000100 Coverage Remarks l*\

W03-04 Lower Shell -to- SLIC 40/55° Parallel 2 directions 100.0%

Lower Middle Shell SLIC 40/55° Transverse 2 directions 100.0%

Average 100.0%

000200 W04-05 Lower Middle Shell SLIC 40/55c Parallel 2 directions 100.0%

-to-upper Middle SLIC 40/55° Transverse 2 directions 100.0%

Shell Average 100.0%

000300 W05-06 upper Middle Shell SLIC 40/55° Parallel 2 directions 81.5% Limited examination due to the

-to- Upper Shell SLIC 40/55° Transverse 2 directions 100.0% outlet nozzle integral extensions and Average 90.8% inlet nozzle bore radii.

000400 WO2-O3 Bottom Head -to- SLIC 40/55° parallel 2 directions 83.5% Limited examination due to the Lower Shell SLIC 40/55° Parallel 2 directions 69.6% proximity of the core barrel stabilizing Average 76.6% lugs.

000500 W01-02 Bottom Head Cap SLIC 40/55° Parallel 2 directions 49.7% Limited examination due to the

-to- Bottom Head SLIC 40/55° Transverse 2 directions 53.5% bottom head penetrations.

Spherical Ring Average 51.6%

000600 W06-07 Upper Shell SLIC 40/55° Parallel 2 directions 95.8% Limited examination due to the

-to- Flange SLIC 40/55° Transverse 2 directions 90.1% flange design.

Average 93.0%

000900 W2A Lower Head SLIC 40/55° Parallel 2 directions 100.0% Limited examination due to the Meridional @ 0° SLIC 40/55° Transverse 2 directions 83.7% bottom head penetrations and core Average 91.9% .barrel stabilizing lugs 001000 W2B Lower Head SLIC 40/55° Parallel 2 directions 100.0% Limited examination due to the Meridional @ 60° SLIC 40/55° Transverse 2 directions 80.1% bottom head penetrations and core Average 90.1% barrel stabilizing lugs 001100 W2C Lower Head SLIC 40/55° Parallel 2 directions 98.5% Limited examination due to the Meridional @ 120° SLIC 40/55° Transverse 2 directions 75.7% bottom head penetrations and core Average 87.1% barrel stabilizing lugs.

001200 W2D Lower Head SLIC 40/55° Parallel 2 directions 100.0% Limited examination due to the Meridional @18O° SLIC 40/55° Transverse 2 directions 80.9% bottom head penetrations and core Average 1 90.5% barrel stabilizing lugs.

001300 W2E Lower Head SLIC 40/55° Parallel 2 directions 95.4% Limited examination due to the Meridional @ 240° SLIC 40/55° Transverse 2 directions 76.6% bottom head penetrations and core Average 86.0% barrel stabilizing lugs.

001400 W2F Lower Head SLIC 40/55° Parallel 2 directions 90.7% Limited examination due to the Meridional @ 300° SLIC 40/55° Transverse 2 directions 71.6% bottom head penetrations and core Average 81.2% barrel stabilizing lugs.

Sequoyah Nuclear Power Station, Unit 1 2006 Reactor Vessel Inservice Examination UT Coverage Summary Weld Exam Area Beam Exam Number Number Identification Angle(s) Ty 001900 N-15 Outlet Nozzle SLIC 40

.?. *: .Remarks '*<V?>0£ Parallel

-to-Shell @22° SLIC 40/55° 2 directions 86.2% Limited examination due to the" Transverse 2 directions 69.5% integral extension.

PA-16 Parallel (Bore) 1 direction 100.0%

001500 Average 81.3%

N-11 inlet Nozzle SLIC 40 Parallel 2 directions 100.0%

-to-shell @ 67° SLIC 40/55° Transverse 2 directions 100.0%

PA-16 Parallel (Bore) 1 direction 100.0%

001600 Average 100.0%

N-12 inlet Nozzle SLIC 40 Parallel 2 directions 100.0%

-to-Shell @ 113° SLIC 40/55° Transverse 2 directions 100.0%

PA-16 Parallel (Bore) 1 direction 100.0%

002000 Average 100.0%

N-16 Outlet Nozzle SLIC 40 Parallel 2 directions 86.2% Limited examination due to the

-to-Shell @ 158° SLIC 40/55° Transverse 2 directions 69.5% integral extension.

PA-16 Parallel (Bore) 1 direction 100.0%

Average 81.3%

002100 N-17 Outlet Nozzle SLIC 40 Parallel 2 directions 86.2% Limited examination due to the

  • to- Shell @ 202° SLIC 40/55° Transverse 2 directions 69.5% integral extension.

PA-16 Parallel (Bore) 1 direction 100.0%

Average 81.3%

001700 N-13 inlet Nozzle SLIC 40 Parallel 2 directions 100.0%

-to- Shell (5) 247° SLIC 40/55° Transverse 2 directions 100.0%

PA-16 Parallel (Bore) 1 direction 100.0%

Average 100.0%

001800 N-14 inlet Nozzle SLIC 40 Parallel 2 directions 100.0%

-to-Shell @293° SLIC 40/55° Transverse 2 directions 100.0%

PA-16 Parallel (Bore) 1 direction 100.0%

Average 100.0%

002200 N-18 Outlet Nozzle SLIC 40 Parallel 2 directions 86.2%

-to-Shell @338° Limited examination due to the SLIC 40/55° Transverse 2 directions 69.5% integral extension.

PA-16 Parallel (Bore) 1 direction 100.0%

Average 81.3%

Sequoyah Nuclear Power Station, Unit 1 2006 Reactor Vessel Inservice Examination UT Coverage Summary Weld Exam Area Number Number Beam Identification Direction^

RC-O9-SE Outlet Nozzle Remarks Parallel 2 directions 100.0%

to-Pipe @ 22° Transverse 2 directions 100.0%

Average 100.0%

Elbow-to-inlet Parallel 2 directions 100.0%

Nozzle (q> 67° Transverse 2 directions 100.0%

Average 100.0%

Elbow -to- inlet Parallel 2 directions 100.0%

Nozzle @ 113° Transverse 2 directions 100.0%

Average 100.0%

Outlet Nozzle Parallel 2 directions 100.0%

to-Pipe @ 158° Transverse 2 directions 100.0%

Average 100.0%

Outlet Nozzle Parallel 2 directions 100.0%

-to-Pipe @ 202° Transverse 2 directions 100.0%

Average 100.0%

Elbow-to-inlet Parallel 2 directions 100.0%

Nozzle @ 247° Transverse 2 directions 100.0%

Average 100.0%

Elbow-to-inlet Parallel 2 directions 100.0%

Nozzle @ 293° Transverse 2 directions 100.0%

004200 Average 100.0%

RC-17-SE Outlet Nozzle Parallel 2 directions 100.0%

-to-Pipe @ 338° Transverse 2 directions 100.0%

Average 100.0%

Prepared by:

SNT Level:

Date:

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