CNL-17-013, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program, Unit 3 Third Ten Year Interval Request for Relief for 3-ISI-28 and 3-ISI-29
| ML17031A351 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 01/31/2017 |
| From: | James Shea Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| CNL-17-013 | |
| Download: ML17031A351 (128) | |
Text
{{#Wiki_filter:Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-17-013 January 31, 2017 10 CFR 50.55a ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Unit 3 Renewed Facility Operating License No. DPR-68 NRC Docket No. 50-296
Subject:
Browns Ferry Nuclear Plant Unit 3, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program, Unit 3 Third Ten Year Interval Request for Relief for 3-ISI-28 and 3-ISI-29
Reference:
1.TVA letter to NRC, American Society of Mechanical Engineers, Code Section XI lnservice Inspection Program for the Unit 1 Second Ten-Year Inspection Interval, Unit 2 Fourth Ten-Year Inspection Interval and Unit 3 Third Ten-Year Inspection Interval, Request For An Alternative ISl-45, dated September 12, 2014 (ML14260A365) 2.NRC letter to TVA, Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Relief from the Requirements of American Association of Mechanical Engineers Code Section XI Inservice Inspection Program, Request for an Alternative ISI-45 (TAC Nos. MF4854, MF4855, and MF4856), dated August 6, 2015 (ML15191A372) In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 50.55a, "Codes and Standards," paragraphs (g)(5)(iii) and (g)(6), Tennessee Valley Authority (TVA) is submitting a relief request for Nuclear Regulatory Commission (NRC) approval for the Browns Ferry Nuclear Plant (BFN) Unit 3 third ten-year inspection (ISI) interval. The BFN Unit 3 third ten-year inspection interval ended on January 31, 2016. In References 1 and 2 the NRC approved a relief request to align the ISI interval dates for BFN Units 1, 2, and 3.
U.S. Nuclear Regulatory Commission CNL-17-013 Page 2 January 31, 2017 provides relief request 3-ISI-28 that requests relief from the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components, ASME Code Class 1, Table IWB-2500-1, which requires a volumetric examination of essentially 100 percent (%) of the volume. The specific item numbers from Table IWB-2500-1, for which relief is requested, are shown in Enclosure 1. Similarly, Enclosure 2 provides relief request 3-ISI-29 that requests relief from the requirements of the ASME B&PV Code, Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components, ASME Code Class 1, Table IWB-2500-1, ASME Code Class 2, Table IWC-2500-1, and Table 1 to Code Case N-577, Section N-577-2500 which require a volumetric examination of essentially 100% of the weld volume. The specific item numbers from Tables IWB-2500-1 IWC-2500-1, and Table 1 to Code Case N-577 for which relief is requested, are shown in Table 1 of Enclosure 2. The ASME B&PV Code, Section XI, 2001 Edition through 2003 Addenda is the code of record for BFN Unit 3. The definition of essentially 100% is provided by NRC Information Notice 98-42, Implementation of 10 CFR 50.55a(g) Inservice Inspection Requirements, and Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, Section XI, Division 1, which requires examination coverage of more than 90 percent of the specified examination volume in lieu of essentially 100%. 10 CFR 50.55a(g)(6) authorizes the NRC to grant relief for determinations under 10 CFR 50.55a(g)(5) when Code requirements are impractical. TVA is requesting relief on the basis that the Code-required essentially 100% examination coverage is impractical due to physical obstructions and limitations imposed by design, geometry, or physical obstructions for the welds and associated components listed in Table 1 to Enclosure 1 and Table 1 to Enclosure 2. As an alternative, TVA has invoked ASME Section XI Code Case N-460, which states: when the entire examination volume or area cannot be examined due to interference by another component or part geometry, a reduction in examination coverage on any Class 1 or Class 2 weld may be accepted provided the reduction in coverage for that weld is less than 10%. Therefore, TVA is requesting relief only for those welds that were inspected and received Code examination coverage of 90% or less. Examination coverage of greater than 90% was not achieved for the welds listed in the proposed relief requests and the applicable coverage percentage is specified in the relief request for each weld (Table 1 to Enclosure 1 and Table 1 to Enclosure 2). The examination coverage achieved for the subject welds in conjunction with acceptable examinations provides reasonable assurance that unallowable flaws do not exist in the subject component welds and that the welds are acceptable for service. Thus, an acceptable level of quality and safety was achieved and public health and safety was not endangered by allowing the proposed alternative examination coverage in lieu of the Code requirement.
U.S. Nuclear Regulatory Commission CNL-17-013 Page 3 January 31 , 2017 provides the supporting information for relief request 3-ISI-28. Enclosure 4 provides the supporting information for relief request 3-ISI-29. TVA requests approval of these relief requests within six months from the date of this letter. There are no regulatory commitments associated with this submittal. Please address any questions regarding this request to Edward D. Schrull at 423-751-3850. Respectfully,
.J. l \v ~ <(__ _
J. W . Shea ViC(e President, Nuclear Licensing
Enclosures:
- 1. Browns Ferry Nuclear Plant, Unit 3 lnservice Inspection Program Third Ten Year Interval Request for Relief 3-ISI-28
- 2. Browns Ferry Nuclear Plant, Unit 3 lnservice Inspection Program Third Ten Year Interval Request for Relief 3-ISI-29 3 Request for Relief 3-ISI-28, Attachment A- "Sketches," and Attachment B-
"Examination Data Reports" 4 Request for Relief 3-ISI-29, Attachment A- "lnservice Inspection Drawings,"
and Attachment B - "Examination Data Reports" cc (w/Enclosures): NRC Regional Administrator- Region II NRC Senior Resident Inspector- Browns Ferry Nuclear Plant NRC Project Manager- Browns Ferry Nuclear Plant
Enclosure 1 Browns Ferry Nuclear Plant, Unit 3 Inservice Inspection Program Third Ten Year Interval Request for Relief 3-ISI-28
Enclosure 1 Tennessee Valley Authority Browns Ferry Nuclear Plant Unit 3 Request for Relief 3-ISI-28 Summary In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 50.55a, "Codes and Standards," paragraphs (g)(5)(iii) and (g)(6), the Tennessee Valley Authority (TVA) is requesting relief from weld examination coverage requirements specified in the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, Section XI for nine reactor pressure vessel (RPV) nozzle-to-vessel full penetration weld and one inside radius section. Ultrasonic (UT) examinations were performed during the third ten-year interval. This relief is requested for the Browns Ferry Nuclear Plant (BFN) Unit 3 third ten-year inspection interval which began November 19, 2012 and ended January 31, 2016. ASME Code Components Affected: Relief is requested for the following RPV nozzle-to-vessel full penetration welds: N1B-NV N4A-NV N4B-NV N4C-NV N4D-NV N4E-NV N4F-NV N8A-NV N9-NV N10-NV Relief is also requested for the following RPV inside radius weld: N10-IR Refer to Table 1 of this enclosure for additional weld information. ASME Code Class: ASME Code Class 1 (Equivalent) Section XI Edition: 2001 Edition, 2003 Addenda Code Table: IWB-2500-1 CNL-17-013 E1 - 1 of 6
Enclosure 1 Tennessee Valley Authority Browns Ferry Nuclear Plant Unit 3 Request for Relief 3-ISI-28 Code Examination Category: B-D, Full Penetration Welds of Nozzles in Vessels Code Examination Item Number: B3.90, Reactor Vessel Nozzle-to-Vessel Welds and B3.100, Nozzle Inside Radius Section Code Requirements from Which Relief Is Requested: ASME Section XI, Table IWB-2500-1, Examination Category B-D, Item No. B3.90 and B3.100 requires a volumetric examination of essentially 100 percent (%) of the weld and adjacent base material and inside radius as depicted in Figure IWB-2500-7. Relief is requested from the requirement of ASME Section XI Code, Table IWB-2500-1, Examination Category B-D, Item No. B3.90 and B3.100 to perform essentially 100% volumetric examination of the weld and adjacent base material. As an alternative, TVA has invoked ASME Section XI Code Case N-460, which states: when the entire examination volume or area cannot be examined due to interference by another component or part geometry, a reduction in examination coverage on any Class 1 or Class 2 weld may be accepted provided the reduction in coverage for that weld is less than 10%. Therefore, TVA is requesting relief only for those welds that were inspected and received Code coverage of 90% or less.
Reason for Request
The design configuration of the RPV nozzle-to-vessel weld areas precludes a UT examination of greater than 90% of the required volume. It is not possible to perform the volumetric UT from both sides of each weld due to the configuration of these components. The component design configuration and single side access limits UT examination coverage of the welds to the percentages listed in Table 1 of this enclosure. The achieved examination coverage for these components ranged from 25% to 90% of the required examination volume. Proposed Alternative and Basis for Use: TVA performed the UT examinations of the welds listed in Table 1 to the maximum extent practical for the component design configuration of the RPV nozzle-to-vessel welds and inner radius sections. In order to examine the weld in accordance with the ASME Code requirements, the RPV would require extensive design modifications. The physical arrangement of the nozzle-to-vessel welds precludes UT examination from the nozzle side. The limitations are inherent to the nozzle-to-vessel weld design. UT scanning from the inner nozzle surfaces is ineffective due to the weld location and the asymmetrical inside surface where the nozzle and vessel converge. The blend radius of the weld restricts the scanning movement and/or transducer contact. The areas receiving little or no examination coverage are located toward the outside surface of the CNL-17-013 E1 - 2 of 6
Enclosure 1 Tennessee Valley Authority Browns Ferry Nuclear Plant Unit 3 Request for Relief 3-ISI-28 reactor vessel in the general area of the nozzle outside blend radius. Degradation, if present, at the inside surface or inner 15% volume would have been detected by the performed UT examinations. The welds were examined with the latest techniques, procedures, equipment, and personnel qualified to the requirements of the Performance Demonstration Initiative (PDI) Program, in accordance with the requirements of the 2001 Edition through 2003 Addenda of the ASME Code. UT examination of the subject areas to the maximum extent practical for the design of the nozzle-to-vessel weld joints provides an acceptable level of quality and safety. Since the inner 15% thickness was fully examined for nozzle to vessel welds and 90% of the N10 inner radius was fully examined detectable degradation, if present, would have been identified by the performed UT examinations. As a result, reasonable assurance of operational readiness of the subject welds has been provided by the performed UT examinations. Therefore, pursuant to 10 CFR 50.55a(g)(5)(iii), TVA requests that relief be granted for the BFN Unit 3 third ten-year inspection interval. Implementation Schedule: This request for relief is applicable to the Unit 3, third ten-year interval which began on November 19, 2012 and ended January 31, 2016. The welds and inner radius sections described above are listed in Table 1 of this enclosure. The welds and inner radius sections were examined during the second and third periods (Cycle 15 - Spring 2012 and Cycle 16 - Spring 2014 respectively) of the third ten-year internal. Precedent: This request for relief is similar to the following TVA relief requests for BFN and approved by the NRC: 3-ISI-23, NRC approved by letter dated September 24, 2008 (ML082480573) 3-ISI-26, NRC approved by letter dated March 14, 2012 (ML12018A086) 3-ISI-7, NRC approved by letter dated February 27, 2008 (ML080520006) 3-ISI-14 and 3-ISI-15, NRC approved by letter dated February 11, 2004 (ML040420355) 2-ISI-28, NRC approved by letter dated May 29, 2013 (ML13120A180) CNL-17-013 E1 - 3 of 6
Enclosure 1 Tennessee Valley Authority Browns Ferry Nuclear Plant Unit 3 Request for Relief 3-ISI-28 Attachments to Enclosure 3: Attachment A - Sketches: 3-ISI-0220-C-1, RPV Nozzle Locations SK-B3001, Reactor Pressure Vessel Assembly SK-B3017, Weld Detail Recirculation Outlet Nozzle N1 SK-B3018, Weld Detail Recirculation N2, N3, N4, &N5 Nozzles SK-B3019, Weld Detail Jet Pump Instrument Nozzle N8 SK-B3020, Weld Detail CRD Hydraulic Control Nozzle N9 SK-B3022, Weld Detail Differential Pressure and Liquid Control Nozzle N10 Attachment B - Examination Data Reports: The documents in Appendix B of Enclosure 3 consists of the data sheets that provide the examination volume calculations for the subject limited volume examinations and are taken from the below examination data reports are available for NRC review. N1B-NV N4A-NV N4B-NV N4C-NV N4D-NV N4E-NV N4F-NV N9-NV N10-NV N10-IR N8A-NV CNL-17-013 E1 - 4 of 6
Enclosure 1 Tennessee Valley Authority - Browns Ferry Nuclear Plant Unit 3 Request for Relief 3-ISI-28 Table 1 Weld Number Nominal Size Sketch Examination Unit/Cycle Nozzle Weld Material Comments (Description) (NPS) (Report Number) Coverage Inspection Material Percent (Nearest Performed
%)
N1B-NV 28 SK-B3017 25 U3C15 A508 CL2 E9016G This ultrasonic examination was performed in accordance with the criteria of (Recirc Outlet) (VE-12-010) (Spring 2012) 10 CFR 50.55a(b)(2)(xv)(G) and the minimum coverage requirements of 10 CFR 50.55a(b)(2)(xv)(K) was achieved to the maximum extent possible. The alternative examination volume defined in Code Case N-613-1 which reduces the area to be examined per IWB-2500-7 to the weld plus a 1/2 on each side was applied. Coverage obtained during radial scans was limited due to the nozzle and weld configuration. There were no recordable indications. N4A-NV 12 SK-B3018 32 U3C15 A508 CL2 E9016G This ultrasonic examination was performed in accordance with the criteria of (Feedwater) (VE-12-011) (Spring 2012) 10 CFR 50.55a(b)(2)(xv)(G) and the minimum coverage requirements of 10 CFR 50.55a(b)(2)(xv)(K) was achieved to the maximum extent possible. Code Case N-613-1 was applied which reduces the area to be examined per IWB-2500-7 to the weld plus a 1/2 on each side. Coverage obtained was limited due to nozzle configuration, proximity of N11A nozzle, and crown configuration of circumferential weld C-3-4 for a distance of 28.69 degrees. There were no recordable indications. N4B-NV 12 SK-B3018 32 U3C15 A508 CL2 E9016G This ultrasonic examination was performed in accordance with the criteria of (Feedwater) (VE-12-013) (Spring 2012) 10 CFR 50.55a(b)(2)(xv)(G) and the minimum coverage requirements of 10 CFR 50.55a(b)(2)(xv)(K) was achieved to the maximum extent possible. Code Case N-613-1 was applied which reduces the area to be examined per IWB-2500-7 to the weld plus a 1/2 on each side. Coverage obtained was limited due to nozzle configuration and crown configuration of circumferential weld C-3-4 for a distance of 28.69 degrees. There were no recordable indications. N4C-NV 12 SK-B3018 32 U3C15 A508 CL2 E9016G This ultrasonic examination was performed in accordance with the criteria of (Feedwater) (VE-12-015) (Spring 2012) 10 CFR 50.55a(b)(2)(xv)(G) and the minimum coverage requirements of 10 CFR 50.55a(b)(2)(xv)(K) was achieved to the maximum extent possible. Code Case N-613-1 was applied which reduces the area to be examined per IWB-2500-7 to the weld plus a 1/2 on each side. Coverage obtained was limited due to nozzle configuration and crown configuration of circumferential weld C-3-4 for a distance of 28.69 degrees. There were no recordable indications. N4D-NV 12 SK-B3018 32 U3C15 A508 CL2 E9016G This ultrasonic examination was performed in accordance with the criteria of (Feedwater) (VE-12-017) (Spring 2012) 10 CFR 50.55a(b)(2)(xv)(G) and the minimum coverage requirements of 10 CFR 50.55a(b)(2)(xv)(K) was achieved to the maximum extent possible. Code Case N-613-1 was applied which reduces the area to be examined per IWB-2500-7 to the weld plus a 1/2 on each side. Coverage obtained was limited due to nozzle configuration, proximity of N11B nozzle, and crown configuration of circumferential weld C-3-4 for a distance of 28.69 degrees. There were no recordable indications. N4E-NV 12 SK-B3018 32 U3C15 A508 CL2 E9016G This ultrasonic examination was performed in accordance with the criteria of (Feedwater) (VE-12-019) (Spring 2012) 10 CFR 50.55a(b)(2)(xv)(G) and the minimum coverage requirements of 10 CFR 50.55a(b)(2)(xv)(K) was achieved to the maximum extent possible. Code Case N-613-1 was applied which reduces the area to be examined per IWB-2500-7 to the weld plus a 1/2 on each side. Coverage obtained was limited due to nozzle configuration and crown configuration of circumferential weld C-3-4 for a distance of 28.69 degrees. There were no recordable indications. CNL-17-013 E1 - 5 of 6
Enclosure 1 Tennessee Valley Authority - Browns Ferry Nuclear Plant Unit 3 Request for Relief 3-ISI-28 Table 1 Weld Number Nominal Size Sketch Examination Unit/Cycle Nozzle Weld Material Comments (Description) (NPS) (Report Number) Coverage Inspection Material Percent (Nearest Performed
%)
N4F-NV 12 SK-B3018 32 U3C15 A508 CL2 E9016G This ultrasonic examination was performed in accordance with the criteria of (Feedwater) (VE-12-021) (Spring 2012) 10 CFR 50.55a(b)(2)(xv)(G) and the minimum coverage requirements of 10 CFR 50.55a(b)(2)(xv)(K) was achieved to the maximum extent possible. Code Case N-613-1 was applied which reduces the area to be examined per IWB-2500-7 to the weld plus a 1/2 on each side. Coverage obtained was limited due to nozzle configuration and crown configuration of circumferential weld C-3-4 for a distance of 28.69 degrees. There were no recordable indications. N8A-NV 4 SK-B3019 77 U3C16 A508 CL2 E9016G This ultrasonic examination was performed in accordance with the criteria of (Jet Pump Instrumentation) (UT-14-057) (Spring 2014) 10 CFR 50.55a(b)(2)(xv)(G) and the minimum coverage requirements of 10 CFR 50.55a(b)(2)(xv)(K) was achieved to the maximum extent possible. Code Case N-613-1 was applied which reduces the area to be examined per IWB-2500-7 to the weld plus a 1/2 on each side. Coverage obtained was limited due to nozzle configuration and nozzle blend radius. There were no recordable indications. N9-NV 4 SK-B3020 27 U3C15 A508 CL2 E9016G This ultrasonic examination was performed in accordance with the criteria of (CRD) (VE-12-029) (Spring 2012) 10 CFR 50.55a(b)(2)(xv)(G) and the minimum coverage requirements of 10 CFR 50.55a(b)(2)(xv)(K) was achieved to the maximum extent possible. Code Case N-613-1 was applied which reduces the area to be examined per IWB-2500-7 to the weld plus a 1/2 on each side. Coverage obtained was limited due to nozzle configuration and permanent insulation support ring for a distance of 92 degrees. There were no recordable indications. N10-NV 2 SK-B3022 74 U3C15 A508 CL2 E9016G This ultrasonic examination was performed in accordance with the criteria of (SLC) (VE-12-030) (Spring 2012) 10 CFR 50.55a(b)(2)(xv)(G) and the minimum coverage requirements of 10 CFR 50.55a(b)(2)(xv)(K) was achieved to the maximum extent possible. Code Case N-613-1 was applied which reduces the area to be examined per IWB-2500-7 to the weld plus a 1/2 on each side. Coverage obtained was limited due to nozzle configuration and permanent insulation support bracket. There were no recordable indications. N10-IR 2 SK-B3022 90 U3C15 A508 CL2 E308/E309 Nozzle to vessel weld (SLC Nozzle Inside Radius) was examined using a 65 (SLC) (VE-12-031) (Spring 2012) and 70 degree shear wave mode. The examination was conducted from the vessel outside diameter surface. Scanning was restricted due to nozzle configuration. This weld was examined using PDI qualified personnel, procedures, and equipment. There were no recordable indications. CNL-17-013 E1 - 6 of 6
Enclosure 2 Browns Ferry Nuclear Plant, Unit 3 Inservice Inspection Program Third Ten Year Interval Request for Relief 3-ISI-29
Enclosure 2 TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant, Unit 3 Request for Relief 3-ISI-29 Summary: In accordance with 10 CFR 50.55a, "Codes and Standards," paragraphs (g)(5)(iii) and (g)(6), TVA is requesting relief from weld examination coverage requirements specified in the ASME B&PV Code, Section XI for ten full penetration austenitic stainless piping welds. UT was performed during the third ten-year interval. This relief is requested for BFN Unit 3 third ten-year inspection interval which began November 19, 2012 and ended January 31, 2016. ASME Code Components Affected Welds: Relief is requested for the following welds: Four Residual Heat Removal (RHR) System full penetration piping welds; DRHR-3-12 DRHR-3-19 DSRHR-3-5A TRHR-3-191 One Reactor Water Recirculation (RECIRC) System full penetration piping weld: GR-3-63 Two High Pressure Coolant Injection (HPCI) full penetration piping welds: HPCI-3-019-018 (Pre-Service) HPCI-3-019-019 (Pre-Service) Three Reactor Water Cleanup (RWCU) System full penetration piping welds: RWCU-3-001-070 RWCU-3-007-003 (Pre-Service) RWCU-3-007-011 (Pre-Service) Refer to Table 1 of this enclosure for additional weld information. ASME Code Class: ASME Code Class 1 and Class 2 (Equivalent) Section Xl Edition: 2001 Edition, 2003 Addenda CNL-17-013 E2 - 1 of 7
Enclosure 2 TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant, Unit 3 Request for Relief 3-ISI-29 Code Tables: Code Case N-577, N-577-2500, Table 1 IWB-2500-1 IWC-2500-1 Code Examination Categories: R-A, Risk Informed Piping Examinations B-J, Pressure Retaining Welds in Piping C-F-2, Pressure Retaining Welds in Carbon or Low Alloy Steel Code Examination Item Numbers: R1.11, Elements Subject to Thermal Fatigue R1.16, Elements Subject to intergranular stress corrosion cracking (IGSCC) B9.11, Circumferential Welds C3.20, Circumferential Welds Code Requirements from Which Relief Is Requested: Code Case N-577-1, Section N-577-2500, Table 1, Examination Categories R1.11 and R1.16 require volumetric examination of 100% of the weld and adjacent base material as depicted in Figure IWB-2500-8(c), Tables IWB-2500-1 and IWC-2500-1 requires volumetric examination of essentially 100% of the weld length. Relief is requested from the requirement of ASME Section XI Code, Table IWB-2500-1, Examination Categories R-A, B-J, and C-F-2, Item Nos. R1.11, R1.16, B9.11, and C3.20 to perform essentially 100% volumetric examination of the weld and adjacent base material. As an alternative, TVA has invoked ASME Section XI Code Case N-460, which states: when the entire examination volume or area cannot be examined due to interference by another component or part geometry, a reduction in examination coverage on any Class 1 or Class 2 weld may be accepted provided the reduction in coverage for that weld is less than 10%. Therefore, TVA is requesting relief only for those welds that were inspected and received Code coverage of 90% or less.
Reason for Request
The design configurations of the listed welds preclude a UT examination of greater than 90% of the required volume. It is not possible to perform the volumetric UT from both sides of each weld due to the configuration of these components. The component design configuration limits UT examination coverage of the welds to the percentages shown in Table 1 based on limitations discussed in Table 1. The achieved examination coverage for these components ranged from 30% to 89% of the required examination volume. CNL-17-013 E2 - 2 of 7
Enclosure 2 TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant, Unit 3 Request for Relief 3-ISI-29 Proposed Alternative and Basis for Use: TVA performed the UT examination of the welds listed in Table 1 to the maximum extent practical for the component design configuration of the piping welds. The welds were examined with the latest UT techniques, procedures, equipment, and personnel qualified to the requirements of the PDI Program. These examinations were of the accessible areas to the maximum extent practical due to the design configuration of the weld joints. The "Comments" column of Table 1 of this enclosure describes coverage limitations due to the inability to examine welds from both sides, when applicable. These examinations provide an acceptable level of quality and safety because the information and data obtained provides sufficient information to judge the overall integrity of the piping welds. Additionally, these welds are part of a larger population of welds examined for which the required examination coverage is attained. When considered in aggregate with the entire sample population, an adequate level of inspection was performed to provide reasonable assurance that a pattern of IGSCC degradation that, if present, could affect the overall integrity of the components would be detected. The performed examinations provide an acceptable level of quality and safety. Therefore, pursuant to 10 CFR 50.55a(g)(5)(iii), TVA requests that relief be granted for the BFN Unit 3 third ten-year ISI inspection interval limited examinations. Implementation Schedule: This request for relief is applicable to the Unit 3, third ten-year Interval which began on November 19, 2005, and ended on February 1, 2016. The welds described above are listed in Table 1 of this enclosure. The welds were examined during the second inspection period (Cycle 15 - Spring 2012), and the third inspection period (Cycle 16 - Spring 2014) of the third ten-year inspection interval. Precedent: This request for relief is similar to the following TVA relief requests for BFN and approved by NRC: 3-ISI-25, NRC approved by letter dated January 20, 2012 (ML12003A081) 3-ISI-22, NRC approved by letter dated May 20, 2008 (ML080080524) 3-ISI-12, NRC Approved by letter dated August 3, 2006 (ML061560090) CNL-17-013 E2 - 3 of 7
Enclosure 2 TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant, Unit 3 Request for Relief 3-ISI-29 Attachments to Enclosure 4: Attachment A - Inservice Inspection Drawings: 3-ISI-0330-C-1 3-ISI-0328-C-2 3-ISI-0332-C-1 3-ISI-0332-C-2 3-CHM-2407-C-2 Attachment B - Examination Data Reports: The documents in Appendix B of Enclosure 4 consists of the data sheets that provide the examination volume calculations for the subject limited volume examinations and are taken from the examination data reports. Full copies of the examination data reports are available for NRC review. UT 12-024 UT-12-031 UT-14-039 UT-14-027 UT-14-031 UT-14-036 UT-14-001 UT-14-002 UT-12-046 UT-12-047 CNL-17-013 E2 - 4 of 7
Enclosure 2 Tennessee Valley Authority - Browns Ferry Nuclear Plant, Unit 3 Request for Relief 3-ISI-29 Table 1 ISI Drawing Examination Nominal Unit / Cycle Weld Number IGSCC Number Coverage Joint Pipe Size Inspection Weld Material Comments (System) Category Percent Configuration (NPS) Performed (Weld Report) (Nearest %) A182 F304 Flued ER308 Examination coverage limitations are due to the physical configuration of a wrought DRHR-3-12 D 24" 3-ISI-0330-C-1 30 U3C15 Head to A351 CF8M fluted head penetration to a cast valve configuration that restricts the ultrasonic Cast Valve. examination on both sides of the weld. This configuration limited the scan surface to (RHR System) (UT-12-031) only a portion of the fluted head side of the weld. Examinations were conducted in accordance with an ASME Section XI, Appendix VIII qualified generic PDI procedure, PDI-UT-2, for austenitic metal welds. The qualified procedure requires examination techniques be applied that are intended to interrogate the far side of the weld. However, the generic ultrasonic procedure (or any other existing procedure) is not qualified for detection of flaws on the far side of the weld in austenitic material. Therefore, no examination credit was applied for the far side of the weld that was inaccessible. The ultrasonic examination was conducted to the maximum extent practical. There were no recordable indications. A403 WP304 Tee to ER308 Examination coverage limitations are due to the physical configuration of a tee to DRHR-3-19 C 20" 3-ISI-0330-C-1 59 U3C16 A358 GR304 Pipe pipe configuration that restricts the ultrasonic examination on both sides of the weld. This configuration limited the scan surface to only a portion of the tee side of the (RHR System) (UT-14-039) weld. Examinations were conducted in accordance with an ASME Section XI, Appendix VIII qualified generic PDI procedure, PDI-UT-2, for austenitic metal welds. The qualified procedure requires examination techniques be applied that are intended to interrogate the far side of the weld. However, the generic ultrasonic procedure (or any other existing procedure) is not qualified for detection of flaws on the far side of the weld in austenitic material. Therefore, no examination credit was applied for the far side of the weld that was inaccessible. The ultrasonic examination was conducted to the maximum extent practical. There were no recordable indications. A358 GR304 Pipe to ER308 Examination coverage limitations are due to the physical configuration of this pipe to DSRHR-3-5A C 24" 3-ISI-0330-C-1 76 U3C16 A403 WP304 Elbow. elbow weld. This configuration limited the scan surface to a portion of the pipe side of the weld due to adjacent weld DSRHR-3-5 that limited axial coverage. (RHR System) (UT-14-027) Examinations were conducted in accordance with an ASME Section XI, Appendix VIII qualified generic PDI procedure, PDI-UT-2, for austenitic metal welds. There were no recordable indications. CNL-17-013 E2 - 5 of 7
Enclosure 2 Tennessee Valley Authority - Browns Ferry Nuclear Plant, Unit 3 Request for Relief 3-ISI-29 Table 1 ISI Drawing Examination Nominal Unit / Cycle Weld Number IGSCC Number Coverage Joint Pipe Size Inspection Weld Material Comments (System) Category Percent Configuration (NPS) Performed (Weld Report) (Nearest %) A351 CF8M Valve to ER308 Examination coverage limitations are due to the physical configuration of a Cast TRHR-3-191 C 20" 3-ISI-0330-C-1 54 U3C16 A234 GR WPB Stainless Steel Valve to a Carbon Steel Elbow configuration that restricts the Elbow ultrasonic examination on both sides of the weld. This configuration limited the scan (RHR System) (UT-14-031) surface to the Elbow side of the weld. Examinations were conducted in accordance with an ASME Section XI, Appendix VIII qualified generic procedure for dissimilar metal welds, EPRI-DMW-PA-1. The qualified procedure requires examination techniques be applied that are intended to interrogate the far side of the weld. However, the generic ultrasonic procedure (or any other existing procedure) is not qualified for detection of flaws on the far side of the weld in austenitic material. Therefore, no examination credit was applied for the far side of the weld that was inaccessible. The ultrasonic examination was conducted to the maximum extent practical. There were no recordable indications. A358 TP 304 ER308 Examination coverage limitations are due to the physical configuration of this pipe to GR-3-63 E 28" 3-ISI-0328-C-2 50 U3C15 stainless steel Pipe cast valve configuration that restricts the ultrasonic examination to one side of the to A351 CF8 Cast weld. Examinations were conducted in accordance with an ASME Section XI, (RECIRC System) (UT-12-024) steel Valve. Appendix VIII qualified generic PDI procedure, PDI-UT-2, for austenitic metal welds. The qualified procedure requires examination techniques be applied that are intended to interrogate the far side of the weld. However, the generic ultrasonic procedure (or any other existing procedure) is not qualified for detection of flaws on the far side of the weld in austenitic material. Therefore, no examination credit was applied for the far side of the weld that was inaccessible. The ultrasonic examination was conducted to the maximum extent practical. There was no change in the existing indication when compared to the previous examination for this IGSCC Category E weld. Two indications were identified. Both were acceptable by evaluation and subsequent examinations were performed. A403 WP304 ER308L Examination coverage limitations are due to the physical configuration of a wrought RWCU-3-001-070 A 6" 3-ISI-0332-C-1 49 U3C16 stainless steel piping branch connection to a cast valve configuration that restricts the ultrasonic Sweep-o-let to A351 examination on both sides of the weld. This configuration limited the scan surface to (RWCU System) (UT-14-036) CF8M Cast Valve. only a portion of the branch connection side of the weld. Examinations were conducted in accordance with an ASME Section XI, Appendix VIII qualified generic PDI procedure, PDI-UT-2, for austenitic metal welds. The qualified procedure requires examination techniques be applied that are intended to interrogate the far side of the weld. However, the generic ultrasonic procedure (or any other existing procedure) is not qualified for detection of flaws on the far side of the weld in austenitic material. Therefore, no examination credit was applied for the far side of the weld that was inaccessible. The ultrasonic examination was conducted to the maximum extent practical. There were no recordable indications. CNL-17-013 E2 - 6 of 7
Enclosure 2 Tennessee Valley Authority - Browns Ferry Nuclear Plant, Unit 3 Request for Relief 3-ISI-29 Table 1 ISI Drawing Examination Nominal Unit / Cycle Weld Number IGSCC Number Coverage Joint Pipe Size Inspection Weld Material Comments (System) Category Percent Configuration (NPS) Performed (Weld Report) (Nearest %) SA106 GR B Pipe to ER7056 Pre-Service Exam. Examination coverage limitations are due to the physical HPCI-3-019-018 N/A 10 3-CHM-2407-C-2 87 U3C16 SA105 Flange configuration of this pipe to flange weld that restricts the ultrasonic examination to one side of the weld. No examination on flange side could be performed due to the (HPCI System) (UT-14-001) configuration resulting in a single sided exam. Examinations were conducted in accordance with an ASME Section XI, Appendix VIII qualified generic PDI procedure, PDI-UT-1. RT was acceptable. Voluntary pre-service UT and MT were performed. There were no recordable indications. SA 216 WCB Valve ER70S6 Pre-Service Exam. Examination coverage limitations are due to the physical HPCI-3-019-019 N/A 10 3-CHM-2407-C-2 78 U3C16 to SA106 GR B Pipe configuration of this valve to pipe weld that restricts the ultrasonic examination to one side of the weld. No examination on flange side could be performed due to the (HPCI System) (UT-14-002) configuration resulting in a single sided exam. Examinations were conducted in accordance with an ASME Section XI, Appendix VIII qualified generic PDI procedure, PDI-UT-1. RT was acceptable. Voluntary pre-service UT and MT were performed. There were no recordable indications. A420 GR WPL1 Tee ER70S6 Pre-Service Exam. N-UT-76. Examination coverage limitations are due to the RWCU-3-007-003 N/A 4 3-ISI-0332-C-2 58 U3C15 to ASTM A333 GR 1 physical configuration of this valve to pipe weld that limits circumferential scanning to Pipe one side at the tee. RT and PT was acceptable. Voluntary pre-service UT performed. (RWCU System) (UT-12-046) There were no recordable indications. SA105 Valve to ER70S6 Pre-Service Exam. N-UT-76. PT Performed. Examination coverage limitations are RWCU-3-007-011 N/A 4 3-ISI-0332-C-2 89 U3C15 ASTM A333 GR 1 due to the physical configuration of this valve to pipe weld that limits circumferential Pipe scanning to one side at the valve. RT and PT was acceptable. Voluntary pre-service (RWCU System) (UT-12-047) UT performed. There were no recordable indications. CNL-17-013 E2 - 7 of 7
Enclosure 3 Tennessee Valley Authority Browns Ferry Nuclear Plant Unit 3 Request for Relief 3-ISI-28 Attachment A Sketches 3-ISI-0220-C-1, RPV Nozzle Locations SK-B3001, Reactor Pressure Vessel Assembly SK-B3017, Weld Detail Recirculation Outlet Nozzle N1 SK-B3018, Weld Detail Recirculation N2, N3, N4, & N5 Nozzles SK-B3019, Weld Detail Jet Pump Instrument Nozzle N8 SK-B3020, Weld Detail CRD Hydraulic Control Nozzle N9 SK-B3022, Weld Detail Differential Pressure and Liquid Control Nozzle N10 CNL-17-013
REFERENCE DRAWINGS (GE) SKETCHES - RPV EXAMINATION PLAN (GE) SK-B3001 SK-B3005 SK-B301 0 NOZZLE GROUP I DISTANCE TO MATING SURFACE SK-B3003 SK-B3007 N3X - 86.5" SK-B3004 SK-B3006 N12X - 146" N11X - 228" LEGEND N4X - 246.5" 0 VESSEL NOZZLE N5X - 259.5" FULL PENETRATION NOZZLE WELD r N9 - 296.5" N16X - 379" ASME CC-7 (EQUIVALENT) N2X - 564" w N1X - 583.5" z y w N8X - 610" MATING SURFACE 0 360 270 180 90 0 360 745" I I I I I FLANGE I I r- C-5-FLG I I 706" 330° 210 ° 90° N3D N3C N3B N3A I
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Enclosure 3 Tennessee Valley Authority Browns Ferry Nuclear Plant Unit 3 Request for Relief 3-ISI-28 Attachment B Examination Data Reports: VE-12-10, N1B-NV VE-12-11, N4A-NV VE-12-13, N4B-NV VE-12-15, N4C-NV VE-12-17, N4D-NV VE-12-19, N4E-NV VE-12-21, N4F-NV VE-12-29, N9-NV VE-12-30, N10-NV VE-12-31, N10-IR UT-14-057, N8A-NV CNL-17-013
Ultrasonic Examination
]\It\ 000171 Site/Unit: BFN I 3
Procedure: N-UT-78 Outage No.: U3RF15 Summary No.: 00160-ISI-BFN3 Procedure Rev.: Workscope: 5 Report No.:
-----VE-12-010 lSI Work Order No.: 3-SI-4.6.G Page: 1 of 1 Code: Section Xl2001 Ed/2003 Add Cat./ltem: B-D/83.90 Location: REACTOR BUILDING-DRYWELL Drawing No.: 3-ISI-0328-C-02
Description:
SHL- NOZ System ID: 329 - Reactor Vessel Limitations: Component ID: N1B-NV Llmitattions due to joint design and configuration Size/Length: 28/ Thickness/Diameter: 6.6/28 Comments: See Original report book for UT data. 25.27"/o coverage attained. No recordable Indications noted. Results: Accept r"1 Reject 1-1 Info ~---1 Percent Of Coverage Obtained > 90%: NO Reviewed Previous Data: YES Examiner Level 111 Date Signature Date Mazyck, Edward 4/19/2012 Damon Priestley 4/23/2012 Level N/A Signature Date Site Review Date F.W.Froscello Jr. 5n/2012 Level N/A Signature Date ANII Review Date Sam Flood 4/2412012
A UT Coverage Data Sheet Report No.: 3-TVA-N18-NV AREVA Coverage Data Sheet No.: CDS-01 Radial Examination Coverage [)) Area o1 limitation Ill
-60" RL co-ver-cge Radial Exam Coverage 100% t Total examination Area= 38.28 in2 51 1 Limitation= 24.68 in2 LJe Area Covered = 13.60 in 2 Total Examination Coverage= 35.53%
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A UT Coverage Data Sheet Report No.: 3-TVA-N1B-NV AREVA Coverage Data Sheet No.: CDS-02 Circumferential Examination Coverage Circ. Examination Coverage Outer 85%t exam coverage Total examination Area= 35.58 in 2 Area of Limitation = 35.58 in 2 E] Anlo of lim"ilcrtlcm Area Examined= 0.00 in 2 Total Area Examined I Total Area= 0.00% Total Examination Coverage: 0 0.00 in 2 / 35.58 in 2 = 0. 00% D-Inner 15% Circ. Exam Coverage 0 0 Total examination Area= 2.70 in 2 "\) Total Examination Coverage =2.70 in 2 => Total Examination Coverage =100% co
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A RPV Coverage Work Sheet Report Number: 3-TVA-N1B-NV AREVA Customer Information Component Information Utility: TVA Plant: BFN IUnit: 3 IOutage: U3R15 Weld ID: N1 B-NV Work Sheet Number: CWS-01 60°RL Radial Scan (N-UT-78-0005) 100% t volume 60°RL Circ Scan (N-UT-78-0005) 85% t volume Circ Scan (54-ISI-850-007) Inner 15% t volume (Modeled) Thickness (Is) Inches 6.60 Thickness (ts) Inches 6.60 Thickness (ts) Inches 6.60 Weld Width Inches 2.15 Weld Width Inches 2.15 Weld Width Inches 2.15 Code Case N-613-1 Code Case N-613-1 Exam Area (A 8 CD E F G HI) in* 38.28 Exam Area (A 8 CD E F G H I) in 2 38.28 Exam Area (ABC DE F G H I) in 2 38.28 Inner 15% t area in 2 2.70 Area Scanned in 2 13.60 Upper 85% t area in* 35.59 Area Scanned 2.70 Percentage of Area Scanned 35.53 Area Scanned 0.00 Percentage of Area Scanned 100.0 Percentage of Area Scanned 0.00 Coverage Radial Scan 100% t Volume 35.53 Coverage Circ Scan Upper 85% t Volume 0.00 Coverage Circ Scan Inner 15% t Volume 15.00 Total Coverage Radial and Circ Scans: (35.53% + 0.00% + 15.00%) + 2 = 25.27% (See Radial and Circumferential coverage sheets for more detail.) Radial scans were performed with a procedure qualified for the examination of vessel nozzle to shell welds (N-UT 0005). This procedure has been demonstrated for detection of flaws located throughout the entire weld thickness and base material when scanning in the perpendicular direction to the weld. Coverage obtained during radial scans was limited due to the nozzle and weld configuration. In the circumferential scan direction the outer 85%-t is examined with the same vessel procedure as mentioned above (N-UT-78-0005) and has been demonstrated for detection of flaws located in the upper 85%-t of the weld and base material when scanning in the parallel and tangential direction to the weld. Coverage was also limited due to nozzle configuration. To achieve additional coverage in the circumferential scan direction, examinations were also performed with a procedure (54-ISI-850-007) qualified for nozzle to shell weld inner 15% thickness region. This procedure 0 has been demonstrated for detection of flaws in the inner 15%-t only when scanning in the parallel and tangential direction as define by the modeling. The nozzle to shell weld inner 15%-t 0 examination techniques were performed in accordance with the scanning parameters identified in EPRI modeling report IR-2007-266. 0
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Scanning was performed to the maximum extent possible. The total coverage achieved for exam inalion scans performed, is a conservative estimate derived from the physical limitation caused the nozzle and weld configuration. by ....... 0 The exam/coverage area calculations were derived from a CAD drawing based on the available dimensions from TVA supplied drawing number 131840.
~-9-J Examiner: Nathan Bauman 0'
Level: II Date: 04/19/12 E~am~~dward P. Mayzck / Level: Ill Date: 04/19/12 Sign:~,;C.. S1gn: 'J...u:..-tf' j?_/'b.,M/> _ 0 c::::::::::- .... , Reviewe~ Victor Morto~ Sign :
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J\14 Ultrasonic Examination 000173, Site/Unit: BFN I 3 Procedure: N*UT-78 Outage No.: U3RF15 Summary No.: 00175-ISI*BFN3 Procedure Rev.: 5 Report No.: VE-12*011 Workscope: lSI Work Order No.: 3-SI-4.6.G Page: 1 of 1 Code: Section Xl2001 Ed/2003 Add Cat.lltem: B-D/83.90 Location: REACTOR BUILDING-DRVWELL Drawing No.: 3-ISI.0327-C-01
Description:
NOZ- SHL System ID: 329- Reactor Vessel Component ID: N4A-NV Size/Length: 12/ Thickness/Diameter: 6.6/12 Limitations: Limitations due to joint geometry and configuration. Comments: See Original report book for UT data. 32.31% coverage attained. No recordable indications noted. Results: Accept ['!([ Reject l___[ Info [j Percent Of Coverage Obtained > 90%: NO Reviewed Previous Data: YES Examiner Level II Signature Date Reviewer Date Gatica, James 4/15/2012 Damon Priestley 4/21/2012 Level NIA Signature Date Site Review Date F.W. Froscello Jr. Sn/2012 Level N/A Signature Date Review Date Daniel Williams 4/22/2012
A UT Coverage Data Sheet Report No.: 3-TVA-N4A-NV AREVA Coverage Data Sheet No.: CDS-01 _/llill Radial Examination Coverage [] Pn<J Df limttation Radial Exam Coverage 1OO%t flO" Rt Circ CO¥el'"tJ.:J'I
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Total examination Volume= 2251.203 51 3 1 Limitation= 1130.95 3 2nd Limitation= 0.35 3rd Limitation = 3.163 Volume Covered = 1116.74 in3 Total Examination Coverage= 49.61% < m I
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A UT Coverage Data Sheet Report No.: 3-TVA-N4A-NV AREVA Coverage Data Sheet No.: CDS-02 Radial Examination Coverage Limitation in N11 nozzle Area
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A UT Coverage Data Sheet Report No.: 3-TVA-N4A-NV AREVA Coverage Data Sheet No.: CDS-03 '¥';j:,~ ~~~ru~':'*,::' &~~~m;§~~:P:rcu$i~ Jrio~n** .: *~ '~ ~~;"; :;'~';~~'.t'%i;t:::f;~~~*~tl01\~~,*~;!, .~; ~~~{~f'* Utility: TVA Configuration: Nozzle to Shell _/M Circumferential Examination Coverage I Circ. Examination Coverage 85%t Total examination Area= 24.38 in 2 2 Area of Limitation = 24.38 in 2 Circw~ Area Examined = 0.00 in Total Area Examined I Total Area= 0.00% Total Examination Coverage: 2 2 0.00 in /24.38 in = 0.00% Lower 15% Circ. Exam Coverage < Total examination Area= 1.73 in2 Total Examination Coverage =1.73 in 2 r::::::::::1
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A RPV Coverage Work Sheet Report Number: 3-TVA-N4A-NV AREVA Customer Information Component Information Utility: TVA Plant: BFN j Unit: 3 j Outage: U3R15 Weld 10: N4A-NV Work Sheet Number: CWS-01 60°RL Radial Scan (N-UT-78-0005) 100% t volume 60°RL Circ Scan (N-UT-78-0005) 85% t volume Circ Scan (54-ISI-850-007) Inner 15% t volume (Modeled) Thickness (ts) Inches 6.60 Thickness (ts) Inches 6.60 Thickness (ts) Inches 6.60 Weld Width Inches 2.50 Weld Width Inches 2.50 Weld Width Inches 2.50 Code Case N-613-1 Code Case N-613-1 Exam Area (A 8 C D E F G H) in 2 26.11 Exam Area (A B C D E F G H I) in 3 2251.20 Exam Area (ABC DE F G H I) in 2 26.11 Inner 15% I area in 2 1.73 Area Scanned in' 1116.74 Upper 85% I volume in* 24.38 Area Scanned 1.73 Percentage of Area Scanned 49.61 Area Scanned 0.00 Percentage of Area Scanned 100.0 Percentage of Area Scanned 0.00 Coverage Radial Scan 100% t Volume 49.61 Coverage Circ Scan Upper 85% t Volume 0.00 Coverage Circ Scan Inner 15% t Volume 15.00 Total Coverage Radial and Circ Scans: (49.61 + 0.00% + 15.00%) + 2 = 32.31% (See Radial and Circumferential coverage sheets for more detail.) Radial scans were performed with a procedure qualified for the examination of vessel nozzle to shell welds (N-UT-78-0005). This procedure has been demonstrated for detection of flaws located throughout the entire weld thickness and base material when scanning in the perpendicular direction to the weld. Coverage obtained during radial scans was limited due to the nozzle and weld configuration. In the circumferential scan direction the outer 85%-1 is examined with the same vessel procedure as mentioned above (N-UT-78-0005) and has been demonstrated for detection of flaws located in the upper 85%-t of the weld and base material when scanning in the parallel and tangential direction to the weld. Coverage was also limited due to nozzle configuration. To achieve additional coverage in the circumferential scan direction, examinations were also performed with a procedure (54-ISI-850-007) qualified for nozzle to shell weld inner 15% thickness region. This procedure has been demonstrated for detection of flaws in the inner 15%-t only when scanning in the parallel and tangential direction as define by the modeling. The nozzle to shell weld inner 15%-t examination techniques were performed in accordance with the scanning parameters identified in EPRI modeling report IR-2003-19. <. Scanning was performed to the maximum extent possible. The total coverage achieved for examination scans performed, is a conservative estimate derived from the physical limitation caused by ~ the nozzle and weld configuration ..
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Ultrasonic Examination 000176 Site/Unit: BFN I 3 Procedure: N-UT-78 Outage No.:
------ U3RF15 Summary No.: 00176-ISI-BFN3 Procedure Rev.: 5 Report No.:
------VE-12-013 Workscope: lSI Work Order No.: 3-SI-4.6.G Page: 1 of 1 Code: Section XI 2001 Ed/2003 Add Cat./ltem: B-D/83.90 Location: REACTOR BUILDING-DRYWELL Drawing No.: 3-ISI-0327-C-01
Description:
NOZ - SHL System ID: 329 - Reactor Vessel Component ID: N4B-NV Size/Length:
----- 12/ Thickness/Diameter: 6.6/12 Limitations: Limitations due to joint design and configuration Comments:
See Original report book for UT data. 32.38% coverage attained. No recordable Indications noted. Results: Accept I~J Reject l_j Info LJ Percent Of Coverage Obtained > 90%: No Reviewed Previous Data: Yes Examiner Level II re Date Signature Date Gatica, James 4118/2012 Damon Priestley 4/21/2012 iner Level NIA Signature Date Site Review Date F.W. Froscello Jr. 5n/2012 Level NIA Signature Date ANII Review Date Daniel Williams 4/23/2012
A UT Coverage Data Sheet Report No.: 3-TVA-N4B-NV AREVA Coverage Data Sheet No.: CDS-01 _/M Radial Examination Coverage [ill Artie of limit.r:J1ioo Radial Exam Coverage 100% t 60' RLCin::ccn,oaorG9'8 Total examination Volume = 2251.20 in 3 ,*o,. 1st Limitation = 1130.95 in3 2"d Limitation = 0.35 in3 Volume Covered= 1119.90 in3 Total Examination Coverage= 49.75% rn
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A UT Coverage Data Sheet Report No.: 3-TVA-N4B-NV AREVA Coverage Data Sheet No.: CDS-02 Utility: TVA Plant: Browns Ferry Unit: 3 Weld ID: N4B-NV Configuration: Nozzle to Shell Circumferential Examination Coverage Circ. Examination Coverage Outer 85%t exam coverage Total examination Area= 24.38 in 2 _/[ill Area of Limitation= 24.38 in2 Area Examined= 0.00 in2 Circ~ Total Area Examined I Total Area
= 0.00%
Total Examination Coverage: 0.00 in2 /25.06 in2 = 0.00% Inner 15% Circ. Exam Coverage r:::0:0l
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Total examination Area= 1.73 in2 Area of limitation Total Examination Coverage =1.73 in2 Total Examination Coverage =100% < tn 60' RL Circ coverage
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A RPV Coverage Work Sheet Report Number: 3-TVA-N4B-NV AREVA Customer Information Component Information Utility: TVA Plant: BFN I Unit: 3 I Outage: U3R15 Weld 10: N4B-NV Work Sheet Number: CWS-01 60°RL Radial Scan (N-UT-78-0005) 100% t volume 60°RL Circ Scan (N-UT-78-0005) 85% t volume Circ Scan (54-ISI-850-D07) Inner 15% t volume (Modeled) Thickness (ts) Inches 6.60 Thickness (Is) Inches 6.60 Thickness {Is) Inches 6.60 Weld Width Inches 2.50 Weld Width Inches 2.50 Weld Width Inches 2.50 Code Case N-613-1 Code Case N-613-1 Exam Area (A 8 C D E F G H I) in" 26.11 Exam Area {ABC DE F G H l)in 3 2251.20 Exam Area (A 8 C D E F G H I) in 2 26.11 Inner 15% !area in 2 1.73 Area Scanned in" 1119.90 Upper 85% t area in 2 24.38 Area Scanned 1.73 Percentage of Area Scanned 49.75 Area Scanned 0.00 Percentage of Area Scanned 100.0 Percentage of Area Scanned 0.00 Coverage Radial Scan 100% t Volume 49.75 Coverage Circ Scan Upper 85% t Volume 0.00 Coverage Circ Scan Inner 15% t Volume 15.00 Total Coverage Radial and Circ Scans: (49.75% + 0.00% + 15.00%) + 2 = 32.38% (See Radial and Circumferential coverage sheets for more detail.) Radial scans were perfonned with a procedure qualified for the examination of vessel nozzle to shell welds (N-UT 0005). This procedure has been demonstrated for detection of flaws located throughout the entire weld thickness and base material when scanning in the perpendicular direction to the weld. Coverage obtained during radial scans was limited due to the nozzle and weld configuration. In the drcumferential scan direction the outer 85%-1 is examined with the same vessel procedure as mentioned above (N-UT-78-0005) and has been demonstrated for detection of flaws located in the upper 85%-1 of the weld and base material when scanning in the parallel and tangential direction to the weld. Coverage was also limited due to nozzle configuration. To achieve additional coverage in the circumferential scan direction, examinations were also performed with a procedure (54-ISI-850-007) qualified for nozzle to shell weld inner 15% thickness region. This procedure has been demonstrated for detection of flaws in the inner 15%-t only when scanning in the parallel and tangential direction as define by the modeling. The nozzle to shell weld inner 15%-1 examination techniques were performed in accordance with the scanning parameters identified in EPRI modeling report IR-2003-19. Scanning was performed to the maximum extent possible. The total coverage achieved for examination scans perfonned, is a conservative estimate derived from the physical limitation caused by the nozzle and weld configuration. The exam/coverage area calculations were derived from a CAD drawing based on the available dimensions from TVA supplied drawing number 131840. t'i\
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000179 T\14 Ultrason ic Examination Site/Unit: BFN I 3 Procedure: N-UT-78 Outage No.: U3RF15 Summary No.: 00177-ISI-BFN3 Procedure Rev.: 5 Report No.: VE-12-015 Workscope: lSI Work Order No.: 3-SI-4.6.G Page: 1 of 1 Code: Section Xl2001 Ed/2003 Add Cat./ltem: B-D/83.90 Location: REACTOR BUILDING-DRVWELL Drawing No.: 3-ISI-0327-C-01
Description:
NOZ- SHL System ID: 329 - Reactor Vessel Component ID: N4C-NV Limitations: Limitations due to joint design and configuratio n Size/Length:
------12/
- Thickness/Diameter:
6.6/12 Comments: See Original report book for UT data. 32.38% coverage attained. No recordable Indications noted. Results: Accept [V'I Reject 1 Info I_] Percent Of Coverage Obtained > 90%: No Reviewed Previous Data: Yes Examiner Level Ill Signature Date Reviewer Signature Date Kleljan, David 4/14/2012 Damon Priestley 4/23/2012 Level NIA Signature Date Site Review Date F.W.Froscello Jr. 5nl2012 Level N/A Signature Date ANII Review Date Daniel Williams 4/24/2012
A UT Coverage Data Sheet Report No.: 3-TVA-N4C-NV AREVA Coverage Data Sheet No.: CDS-01 Utility: TVA _/M
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Radial Examination Coverage
.r..r.c mJ cr limitotion.
Radial Exam Coverage 100% t W .RL Cire C<MirtiiJ8 3 Total examination Volume= 2251.20 in ,.
**0 151 Limitation= 1130.95 in3 3
2nd Limitation= 0.35 in Volume Covered= 1119.90 in3 Total Examination Coverage= 49.75%
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A UT Coverage Data Sheet Report No.: 3-TVA-N4C-NV AREVA Coverage Data Sheet No.: CDS-02 Utility: TVA Plant: Browns Ferry Unit: 3 Weld ID: N4C-NV Configuration: Nozzle to Shell Circumferential Examination Coverage
~~M Circ. Examination Coverage Outer 85%t exam coverage Total examination Area= 24.38 in2 2
Area of Limitation= 24.38 in Area Examined= 0.00 in 2 Circ~ Total Area Examined I Total Area= 0.00% Total Examination Coverage: 2 0.00 in / 24.38 in 2 = 0.00% Inner 15% Inner 15% Circ. Exam Coverage I r::::::::::1 2 ~ Total examination Area= 1.73 in Area af li mitatian Total Examination Coverage =1.73 in 2 Total Examination Coverage =100% 60' R L Ci rc coverage ~ 1"0 1" t-3~ c' o
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A RPV Coverage Work Sheet Report Number: 3-TVA-N4C-NV AREVA Customer Information Component Information Utility: TVA Plant: BFN I Unit: 3 I Outage: U3R15 Weld 10: N4C-NV Work Sheet Number: CWS-01 60°RL Radial Scan (N-UT-78-0005) 100% t volume 60°RL Circ Scan (N-UT-78-0005) 85% t volume Circ Scan (54-ISI-850-007) Inner 15% t volume (Modeled) Thickness (Is) Inches 6.60 Thickness (Is) Inches 6.60 Thickness (ts) Inches 6.60 Weld Width Inches 2.50 Weld Width Inches 2.50 Weld Width Inches 2.50 Code Case N-613-1 Code Case N-613-1 Exam Area (A B C D E F G H I) in* 26.11 Exam Area (ABC DE F G HI) in 3 2251.20 Exam Area (ABC DE F G H I) in 2 26.11 Inner 15% t area in 2 1.73 Area Scanned in 3 1119.90 Upper 85% I area in 2 24.38 Area Scanned 1.73 Percentage of Area Scanned 49.75 Area Scanned 0.00 Percentage of Area Scanned 100.0 Percentage of Area Scanned 0.00 Coverage Radial Scan 100% t Volume 49.75 Coverag_e Circ Scan Upper 85% t Volume 0.00 Coverage Circ Scan Inner 15% t Volume 15.00 Total Coverage Radial and Circ Scans: (49.75% + 0.00% + 15.00%) + 2 = 32.38% (See Radial and Circumferential coverage sheets for more detail.) Radial scans were performed with a procedure qualified for the examination of vessel nozzle to shell welds (N-UT 0005). This procedure has been demonstrated for detection of flaws located throughout the entire weld thickness and base material when scanning in the perpendicular direction to the weld. Coverage obtained during radial scans was limited due to the nozzle and weld configuration. In the circumferential scan direction the outer 85%-t is examined with the same vessel procedure as mentioned above (N-UT 0005) and has been demonstrated for detection of flaws located in the upper 85%-t of the weld and base material when scanning in the parallel and tangential direction to the weld. Coverage was also limited due to nozzle configuration. To achieve additional coverage in the circumferential scan direction, examinations were also performed with a procedure (54-ISI-850-007) qualified for nozzle to shell weld inner 15% thickness region. This procedure has been demonstrated for detection of flaws in the inner 15%-t only when scanning in the parallel and tangential direction as define by the modeling. The nozzle to shell weld inner 15%-t examination techniques were performed in accordance with the scanning parameters identified in EPRI modeling report I R-2003-19. Scanning was performed to the maximum extent possible. The total coverage achieved for examination scans performed, is a conservative estimate derived from the physical limitation caused by the nozzle and weld configuration. The exam/coverage area calculations were derived from a CAD drawing based on the available dimensions from TVA supplied drawing number 131840.
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Examiner: Nath::luman Level: II Examin4 Davi~~~ 0 Date: 04/14/12 Level: HI Date: 04/14112 Sign:~ 0 Sign:
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1\14 00018.2 Ultrasonic Examination Site/Unit BFN I 3 Procedure: N-UT-78 Outage No.: U3RF15 Summary No.: 00178-ISI-BFN3 Procedure Rev.: 5 Report No.: VE-12-017 Workscope: lSI Work Order No.: 3-SI-4.6.G Page: 1 of 1 Code: Section XI 2001 Ed/2003 Add Cat/Item: B-D/83.90 Location: REACTOR BUILDING-DRYWELL Drawing No.: 3-ISI-0327-C-01
Description:
NOZ- SHL System ID: 329- Reactor Vessel Component ID: N4D-NV Limitations: Size/Length: 12/
- Thickness/Diameter: 6.6/12 Limitatlon=s due to joint design and configuratio n Comments:
See Original report book for UT data. 32.31% coverage attained. No recordable indications noted. Results: Accept 1~ Reject lJ Info [l Percent Of Coverage Obtained > 90%: Yes Reviewed Previous Data: Yes Examiner Level nature Signature Date Gatica, James 4121/2012 Level N/A Signature Date 5n/2012 Level N/A Signature Date ANII Review Date Daniel Williams 4/21/2012
A UT Coverage Data Sheet Report No.: 3-TVD-N4D-NV AREVA Coverage Data Sheet No.: CDS-01 Configuration: Nozzle to Shell _/[ill Radial Examination Coverage EJ Area of limitation Radial Exam Coverage 100o/ot 60' RL Circ cova.raoa
,*o Total examination Volume= 2251.2()3 1st limitation= 1130.953 3
2nd Limitation = 0.35 ~ 3rd Limitation = 3.16 3 tT\ Volume Covered= 1116.74 in3 Total Examination Coverage= 49.61% p._) C>
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A UT Coverage Data Sheet Report No.: 3-TVA-N4D-NV ARE VA Coverage Data Sheet No.: CDS-02 Radial Examination Coverage Limitation in N11 nozzle Area
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[] 11' Area of limitation
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A UT Coverage Data Sheet Report No.: 3-TVA-N4D-NV AREVA Coverage Data Sheet No.: CDS-03 _/kill Circumferential Examination Coverage lj Circ. Examination Coverage 85%t I Total examination Area= 24.38 in 2 Area of Limitation = 24.38 in 2 Crew~ Area Examined= 0.00 in 2 Total Area Examined I Total Area= 0.00% Total Examination Coverage: 0.00 in 2 /24.38 in 2 = 0.00% Inner 15% Lower 15% Circ. Exam Coverage
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Total examination Area= 1.73 in2 ~ t"T\ Area of limitation Total Examination Coverage =1.73 in2 l Total Examination Coverage =100% tJ 60" RL Circ coverage I 1"0 c:> 1" 0 0
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A RPV Coverage Work Sheet Report Number: 3-TVA-N4D-NV AREVA Customer Information Component Information Utility: TVA Plant: BFN I Unit: 3 I Outage: U3R15 Weld 10: N4D-NV Work Sheet Number: CWS-01 60°RL Radial Scan (N-UT-78-0005) 100% t volume 60°RL Circ Scan (N-UT-78-0005) 85% t volume Circ Scan (54-ISI-850-007) Inner 15% t volume (Modeled) Thickness (ts) Inches 6.60 Thickness (ts) Inches 6.60 Thickness (ts) Inches 6.60 Weld Width Inches 2.50 Weld Width Inches 2.50 Weld Width Inches 2.50 Code Case N-613-1 Code Case N-613-1 Exam Area (A B C D E F G H) in 2 26.11 Exam Area (ABC DE F G HI) in 3 2251.20 Exam Area (ABC DE F G H I) in' 26.11 Inner 15% t area in' 1.73 Area Scanned in 3 1116.74 Upper 85% I volume in 2 24.38 Area Scanned 1.73 Percentage of Area Scanned 49.61 Area Scanned 0.00 Percentage of Area Scanned 100.0 Percentage of Area Scanned 0.00 Coverage Radial Scan 100% t Volume 49.61 Coverage Circ Scan Upper 85% t Volume 0.00 Coverage Circ Scan Inner 15% t Volume 15.00 Total Coverage Radial and Circ Scans: (49.61 + 0.00% + 15.00%) + 2 = 32.31% (See Radial and Circumferential coverage sheets for more detail.) Radial scans were performed with a procedure qualified for the examination of vessel nozzle to shell welds (N-UT 0005). This procedure has been demonstrated for detection of flaws located throughout the entire weld thickness and base material when scanning in the perpendicular direction to the weld. Coverage obtained during radial scans was limited due to the nozzle and weld configuration. In the drcumferential scan direction the outer 85%-1 is examined with the same vessel procedure as mentioned above (N-UT 0005) and has been demonstrated for detection of flaws located in the upper 85%-t of the weld and base material when scanning in the parallel and tangential direction to the weld. Coverage was also limited due to nozzle configuration. To achieve additional coverage in the circumferential scan direction, examinations were also performed with a procedure (54-ISI-850-007) qualified for nozzle to shell weld inner 15% thickness region. This procedure has been demonstrated for detection of flaws in the inner 15%-t only when scanning in the parallel and tangential direction as define by the modeling. examination techniques were performed in accordance with the scanning parameters identified in EPRI modeling report IR-2003-19. The nozzle to shell weld inner 15%-t Scanning was performed to the maximum extent possible. The total coverage achieved for examination scans performed, is a conservative estimate r derived from the physical limitation caused by ~ the nozzle and weld configuration .. 1-
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Ultrasonic Examination 000185 1\IJ\ Site/Unit: BFN I 3 Procedure: N-UT-78 Outage No.: U3RF15 Summary No.: 00179-ISI-BFN3 Procedure Rev.: 5 Report No.: VE-12-019 Workscope: lSI Work Order No.: 3-SI-4.6.G Page: 1 of 1 Code: Section X12001 Ed/2003 Add Cat./ltem: B-D/83.90 Location: REACTOR BUILDING-DRYWELL Drawing No.: 3-ISI-0327-C-01
Description:
NOZ - SHL System ID: 329- Reactor Vessel Component ID: N4E-NV Limitations: Limitations due to joint design and configuratio n Size/Length:
---- 12/
- Thickness/Diameter: 6.6/12 Comments:
See Original report book for UT data. 32.28% coverage attained. No recordable indications noted. Results: Accept I'll Reject 1-1 Info LJ Percent Of Coverage Obtained > 90%: No Reviewed Previous Data: Yes Examiner Level Ill Signature Date Reviewer Signature Date Kleijan, David 4/14/2012 Damon Priestley 4/23/2012 Level NIA Signature Date Site Review Date F.W. Froscello Jr. sn12012 Level NIA re Date ANII Review Date Daniel Williams 4124/2012
A UT Coverage Data Sheet Report No.: 3-TVA-N4E-NV AREVA Coverage Data Sheet No.: CDS-01 _/M Radial Examination Coverage [] kea cf limiltltion Radial Exam Coverage 100% t DO" RL Cire CO"o'B((Jge Total examination Volume= 2251.20 in 3 ,*o,. 51 3 1 Limitation= 1130.95 in 3 2nd Limitation = 0.35 in Volume Covered = 1119.90 in3 Total Examination Coverage= 49.75% ln9ulation SupFl9rt 'Bn:u:k'llt
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A UT Coverage Data Sheet Report No.: 3-TVA-N4E-NV AREVA Coverage Data Sheet No.: CDS-02 _/M Circumferential Examination Coverage Circ. Examination Coverage Outer 85%t exam coverage Total examination Area= 24.38 in2 Area of Limitation = 24.38 in2 Area Examined= 0.00 in 2 Circw~ Total Area Examined I Total Area= 0.00% Total Examination Coverage: 2 2 0.00 in I 24.38 in = 0.00% Inner 15% Inner 15% Circ. Exam Coverage
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A RPV Coverage Work Sheet Report Number: 3-TVA-N4E-NV AREVA Customer Information Component Information Utility: TVA Plant: BFN I Unit: 3 I Outage: U3R15 Weld 10: N4E-NV Work Sheet Number: CWS-01 60°RL Radial Scan (N-UT-78-0005) 100% t volume 60°RL Circ Scan (N-UT-78-0005) 85% t volume Circ Scan (54-ISI-850-007) Inner 15% t volume {Modeled) Thickness (Is) Inches 6.60 Thickness (ts) Inches 6.60 Thickness (ts) Inches 6.60 Weld Width Inches 2.50 Weld Width Inches 2.50 Weld Width Inches 2.50 Code Case N-613-1 Code Case N-613-1 Exam Area (A B C D E F G H I) in' 26.11 Exam Area (ABC DE F G HI) in 3 2251.20 Exam Area (A B C D E F G H I) in' 26.11 Inner 15% I area in 2 1.73 Area Scanned in 3 1119.90 Upper 85% t area in' 24.38 Area Scanned 1.73 Percentage of Area Scanned 49.75 Area Scanned 0.00 Percentage of Area Scanned 100.0 Percentage of Area Scanned 0.00 Coverage Radial Scan 100% t Volume 49.75 Coverage Circ Scan Upper 85% t Volume 0.00 Coverage Circ Scan Inner 15% t Volume 15.00 Total Coverage Radial and Circ Scans: (49.75% + 0.00% + 15.00%) + 2 (See Radial and Circumferential coverage sheets for more detail.)
=32.38%
Radial scans were performed INith a procedure qualified for the examination of vessel nozzle to shell welds (N-UT-78-0005). This procedure has been demonstrated for detection of flaws located throughout the entire weld thickness and base material when scanning in the perpendicular direction to the weld. Coverage obtained during radial scans was limited due to the nozzle and weld configuration. In the circumferential scan direction the outer 85%-t is examined with the same vessel procedure as mentioned above (N-UT 0005) and has been demonstrated for detection of flaws located in the upper 85%-t of the weld and base material when scanning in the parallel and tangential direction to the weld. Coverage was also limited due to nozzle configuration. To achieve additional coverage in the circumferential scan direction, examinations were also performed INith a procedure (54-ISI-850-007) qualified for nozzle to shell weld inner 15% thickness region. This procedure has been demonstrated for detection of flaws in the inner 15%-t only when scanning in the parallel and tangential direction as define by the modeling. The nozzle to shell weld inner 15%-t examination techniques were performed in accordance INith the scanning parameters identified in EPRI modeling report IR-2003-19. Scanning was performed to the maximum extent possible. The total coverage achieved for examination scans performed, is a conservative estimate derived from the physical limitation caused by the nozzle and weld configuration. The exam/coverage area calculations were derived from a CAD drawing based on the available dimensions from TVA supplied drawing number 131840.
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Level: II Date: 04/14/12 ExamJ~r. David Kleinjan Level: Ill Date: 04/14/12 Sign:~~ Sign:
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0001$8 1\14 Ultrasonic Examination Site/Unit 8FN I 3 Procedure: N-UT-78 Outage No.: U3RF15 Summary No.: 00180-ISI-8FN3 Procedure Rev.: 5 Report No.: VE-12-021 Workscope: lSI Work Order No.: 3-SI-4.6.G Page: 1 of 1 Code: Section Xl2001 Ed/2003 Add Cat./ltem: 8-D/83.90 Location: REACTOR 8UILDING-DRYWELL Drawing No.: 3-ISI-0327-C-01
Description:
NOZ- SHL System ID: 329 - Reactor Vessel Component ID: N4F-NV Limitations: Size/Length:
----- 12/ Thickness/Diameter: 6.6/12 Limitations due to joint design and configuration Comments:
See Original report book for UT data. 32.28% coverage attained. No recordable Indications noted. Results: Accept 1'111 Reject r-1 Info [] Percent Of Coverage Obtained > 90%: No Reviewed Previous Data: Yes Examiner Level II Signature Date Reviewer Signature Date Gatica, James 4/18/2012 Damon Priestley 4/21/2012 Level N/A Signature Date Review Date F.W. froscello Jr. 5n/2012 Level NIA Signature Date ANII Review Date Sam Flood 4/23/2012
A UT Coverage Data Sheet Report No.: 3-TVA-N4F-NV AREVA Coverage Data Sheet No.: CDS-01 _/M Radial Examination Coverage []l Wee of flmitoOOn Radial Exam Coverage 100% t lSD" RL tirr;: ccveroge Total examination Volume= 2251.20 in 3 ,*o,. 151 Limitation = 1130.95 in3 2nd Limitation= 0.35 in3 Volume Covered= 1119.90 in3 Total Examination Coverage= 49.75% rte
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A UT Coverage Data Sheet Report No.: 3-TVA-N4F-NV AREVA Coverage Data Sheet No.: CDS-02 _/[ill! Circumferential Examination Coverage Circ. Examination Coverage Outer 85%t exam coverage Total examination Area = 24.38 in 2 Area of Limitation= 24.38 in2 Area Examined= 0.00 in 2 Circ~ Total Area Examined I Total Area
= 0.00%
Total Examination Coverage: 2 2 0.00 in /25.06 in = 0.00% Inner 15% Inner 15% Circ. Exam Coverage r:::0:0i Total examination Area= 1.73 in2
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A RPV Coverage Work Sheet Report Number: 3-TVA-N4F-NV AREVA Customer Information Component Information Utility: TVA Plant: BFN I Unit: 3 I Outage: U3R15 Weld 10: N4F-NV Work Sheet Number: CWS-01 60°RL Radial Scan (N-UT-78-0005)100% t volume 60°RL Circ Scan (N-UT-78-0005)85% t volume Circ Scan (54-lSI-850-007) Inner 15% t volume (Modeled) Thickness (ts) Inches 6.60 Thickness (Is) Inches 6.60 Thickness (ts) Inches 6.60 Weld Width Inches 2.50 Weld Width Inches 2.50 Weld Width Inches 2.50 Code Case N-613-1 Code case N-613-1 Exam Area (A8 CD E F G HI) in 2 26.11 Exam Area (A 8 CD E F G H I) in 3 2251.20 Exam Area (A 8 C D E F G H I) in 2 26.11 Inner 15% t area i~ 1.73 Area Scanned in* 1119.90 Upper 85% t area in 2 24.38 Area Scanned 1.73 Percentage of Area Scanned 49.75 Area Scanned 0.00 Percentage of Area Scanned 100.0 Percentage of Area Scanned 0.00 Coverage Radial Scan 100% t Volume 49.75 Coverage Circ Scan Upper 85% t Volume 0.00 Coverage Circ Scan Inner 15% t Volume 15.00 Total Coverage Radial and Circ Scans: (49.75% + 0.00% + 15.00%) + 2 = 32.38% (See Radial and Circumferential coverage sheets for more detail.) Radial scans were performed with a procedure qualified for the examination of vessel nozzle to shell welds (N-UT 0005). This procedure has been demonstrated for detection of flaws located throughout the entire weld thickness and base material when scanning in the perpendicular direction to the weld. Coverage obtained during radial scans was limited due to the nozzle and weld configuration. In the circumferential scan direction the outer 85%-t is examined with the same vessel procedure as mentioned above (N-UT 0005) and has been demonstrated for detection of flaws located in the upper 85%-t of the weld and base material when scanning in the parallel and tangential direction to the weld. Coverage was also limited due to nozzle configuration. To achieve additional coverage in the circumferential scan direction, examinations were also performed with a procedure (54-ISI-850-007) qualified for nozzle to shell weld inner 15% thickness region. This procedure has been demonstrated for detection of flaws in the inner 15%-t only when scanning in the parallel and tangential direction as define by the modeling. The nozzle to shell weld inner 15%-t examination techniques were performed in accordance with the scanning parameters identified in EPRI modeling report IR-2003-19. Scanning was performed to the maximum extent possible. The total coverage achieved for examination scans performed, is a conservative estimate derived from the physical limitation caused by the nozzle and weld configuration. < fT' The exam/coverage area calculations were derived from a CAD drawing based on the available dimensions from TVA supplied drawing number 131840.
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Level: Ill Date: 04/19/12 Page 11 of 11
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Ultrasonic Examination 000191 Site/Unit: BFN I 3 Procedure: N-UT-78 Outage No.: U3RF15 Summary No.: 00188-ISI-BFN3 Procedure Rev.: Workscope: 181 5 Report No.: VE-12-029 Work Order No.: 3-SI-4.6.G Page: 1 of 1 Code: Section X12001 Ed/2003 Add Cat./ltem: B-D/83.90 Location: REACTOR BUILDING-DRYWELL Drawing No.: 3-ISI-0220-C-01
Description:
SHL - NOZ System ID: 329 - Reactor Vessel Component ID: N9-NV Limitations: Size/Length: Limitation s due to joint design and configurat ion.
---- 4/
- Thickness/Diameter: 6.6/4 Comments:
See Original report book for UT data. 27.96% coverage attained. No recordable indication s noted. Results: Accept 1;11 Reject Info L.l Percent Of Coverage Obtained > 90%: No Reviewed Previous Data: Yes Examiner Level Ill Signature Date Reviewer Signature Date KLEINJAN, DAVID R 4/16/2012 Damon Priestley 4/23/2012 ner Level NIA Signature Date Site Review Date F.W. Froscello Jr. sn12012 Level N/A Signature Date ANII Review Date Sam Flood 4/23/2012
A UT Coverage Data Sheet Report No.: 3-TVA-N9-NV AREVA Coverage Data Sheet No.: CDS-01 Radial Examination Coverage [ill Area of limitatioon 6(1~ Rl Cite: coverage Radial Exam Coverage 100% t Total examination Area= 1412.29 in3 TOial Exam Volume== 29.6665 Hea of Coverage= "8.4343 1st Limitation = 791.11 in3 2"d Limitation= 43.30 in3 Area Covered= 577.88 in3 Total Examination Coverage= 40.92% 0 0
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A UT Coverage Data Sheet Report No.: 3-TVA-N9-NV ARE VA Coverage Data Sheet No.: CDS-02 Configuration: Nozzle to Shell Circumferential Examination Coverage Circ. Examination Coverage Outer 85%t exam coverage Total examination Area= 29.67in 2 Area of Limitation = 29.67in 2 Area Examined= 0.00 in2 [] Total Area Examined I Total Area= 0.00% Ani ~lmitalon Total Examination Coverage: 2 0.00 in / 29.67in 2 = 0.00% ToW EJ:.am "'olJ~ .2SI.ee55
.r..reaot~0-00 Inner 15% Circ Exam Coverage Total Examination Area= 2.61 in2 Total Examination Coverage= 2.61 in Total Examination Coverage= 100%
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Page 11 of 12
A RPV Coverage Work Sheet Report Number: 3-TVA-N9-NV AREVA Customer Information Component Information Utility: TVA Plant: BFN j Unit: 3 j Outage: U3R15 Weld ID: N9-NV Work Sheet Number: CWS-01
&O~RL Radial Scan (N-UT-78-0005) 100% t volume 60°RL Circ Scan (N-UT-78-0005) 85% t volume Circ Scan (54-ISI-850-007)
Inner 15% t volume (Modeled) Thickness {Is) Inches 6.60 Thickness (Is) Inches 6.60 Thickness {Is) Inches 6.60 Weld Width Inches 1.28 Weld Width Inches 1.28 Weld Width Inches 1.28 Code Case N-613-1 Code Case N-613-1 Exam Area (A B C D E F G H I) in' 29.67 Exam Area (ABC DE F G H l)in 3 1412.29 Exam Area (ABC DE F G HI) in' 29.67 Inner 15% I area in 2 2.61 Area Scanned in 3 577.88 Upper 85% t area in 2 27.05 Area Scanned 2.61 Percentage of Area Scanned 40.92 Area Scanned 0.00 Percentage of Area Scanned 100.0 Percentage of Area Scanned 0.00 Coverage Radial Scan 100% t Volume 40.92 Coverage Circ Scan Upper 85% t Volume 0.00 Coverage Circ Scan Inner 15% t Volume 15.00 Total Coverage Radial and Circ Scans: (40.92% + 0.00% + 15.00%) + 2 (See Radial and Circumferential coverage sheets for more detail.)
=27.96%
Radial scans were performed with a procedure qualified for the examination of vessel nozzle to shell welds (N-UT 0005). This procedure has been demonstrated for detection of flaws located throughout the entire weld thickness and base material 'Nhen scanning in the perpendicular direction to the weld. Coverage obtained during radial scans was limited due to the nozzle and weld configuration. In the circumferential scan direction the outer 85%-t is examined with the same vessel procedure as mentioned above (N-UT-78-0005) and has been demonstrated for detection of flaws located in the upper 85%-1 of the weld and base material when scanning in the parallel and tangential direction to the weld. Coverage was also limited due to nozzle configuration. To achieve additional coverage in the circumferential scan direction, examinations were also performed with a procedure (54-ISI-850-007) qualified for nozzle to shell weld inner 15% thickness region. This procedure has been demonstrated for detection of flaws in the inner 15%-t only 'Nhen scanning in the parallel and tangential direction as define by the modeling. The nozzle to shell weld inner 15%-1 examination techniques were performed in accordance with the scanning parameters identified in EPRI modeling report IR-2006-236. Scanning was performed to the maximum extent possible. The total coverage achieved for examination scans performed, is a conservative estimate derived from the physical limitation caused by the nozzle and weld configuration. The exam/coverage area calculations were derived from a CAD drawing based on the available dimensions from TVA supplied drawing number 131840.
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)-)Q Examiner: Nathan Bauman Level: tl Date: 04/14/12 Exami:r= David Kleinjan Level: til Date: 04/14/12
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!it Reviewed ~ctor Mort~ Level: Ill Date: 04/14/12
/(,) Page 12 of 12
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Ultrasonic Examination 000193 Site/Unit: BFN I 3 Procedure: N*UT-78 Outage No.: U3RF15 Summary No.: 00158-ISI-BFN3 Procedure Rev.: 5 Report No.: VE-12-030 Workscope: lSI Work Order No.: 3-SI.4.6.G Page: 1 of 1 Code: Section XI 2001 Ed/2003 Add Cat./ltem: 8-D/83.90 Location: REACTOR BUILDING*DRYWELL Drawing No.: 3-ISI*0445-C*01
Description:
NOZ- SHL System ID: 329 - Reactor Vessel Component ID: N10*NV Size/Length: Thickness/Diameter: Limitations: Limitations due to joint design and configuration Comments: See Original report book for UT data. 74.10% coverage attained. No recordable Indications noted. Results: Accept ~I Reject [I Info ! Percent Of Coverage Obtained > 90%: No Reviewed Previous Data: Yes Examiner Level Ill Signature Date Reviewer Signature Date Kleijan, David 4/9/2012 Damon Priestley 4/13/2012 Level N/A Date Date 5n12o12 Level N/A Signature Date ANII Review Date Daniel Williams 4117/2012
A UT Coverage Data Sheet Report No.: 3-TVA-N10-NV AREVA Coverage Data Sheet No.: CDS-01 Radial Examination Coverage
~ ~
~ ~
Area of limitation 60°RL Radial Coverage Radial Examination Coverage Examination volume Weld Length = 18.64" Exam Area = 5. 78"x 2.83" Permanent ins.support bracket Total examination Volume= 304.90.3 Volume of 1st Limitation = 13.05"3 Volume of 2nd Limitation= 6.16" 3 3 Volume Examined = 285.74 in Total Volume Examined I Total Volume = 93.70% Total Examination Coverage: 3 3 285.74 in / 304.95 in = 93.70% Nozzle Boss
---- \\ \~) II Centerline of nozzle IO ::>
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- D Ul Page 7 of 9
A UT Coverage Data Sheet Report No.: 3-TVA-N10-NV AREVA Coverage Data Sheet No.: CDS-02
- ,::""E::<~::~<T'~~~ntorm~~::~,<< << < <ComPc>n8nt'rnt6fination Utility: TVA Plant: Browns Ferry Configuration: Nozzle to Shell Circumferential Examination Coverage
+ + + + +
+ + + + +
+ + + + +
+ + + + +
+ + + + +
+ .... + + +
Upper 85% Circ. Exam Coverage Area of limitation 2 Total examination Area= 16.49" Area Covered= 7.75" 2 Total Examination Coverage= 47% 60° RL Circ coverage Lower 15% Circ. Exam Coverage Total examination Area= 2.49"2 Total Examination Coverage =2.42"2 Total Examination Coverage= 97%
------- ----- Ill 50° Shear Circ coverage 1"0 of inner 15%t 1" 0
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Examination volume <~ (jj) Page 8 of 9
A RPV Coverage Work Sheet Report Number: 3-TVA-N10-NV AREVA Customer Information Component Information Utility: TVA Plant: BFN IUnit: 3 IOutage: U3R15 Weld ID: N10-NV Work Sheet Number: CWS-03 60°RL Radial Scan (N-UT-76-0005) 100% t volume 60°RL Circ Scan (N-UT-76-0005) 85% t volume 50° +/-(13° to 40°) Circ Scan (54-ISI-850-007) Inner 15% t volume (Modeled) Thickness (ts) Inches 6.80 Thickness {Is) Inches 6.80 Thickness {ts) Inches 6.80 Weld Width Inches 1.80 Weld Width Inches 1.80 Weld Width Inches 1.80 Code Case N-613-1 Code case N-613-1 Exam Volume (ABC DE F G H) in 2 18.90 Exam Volume (ABC DE F G H) in 3 304.95 Exam Volume (A B C D E F G H) in 2 18.90 Inner 15% t area in* 2.49 Area Scanned in 3 285.74 Upper 85% t volume in' 16.49 Area Scanned 2.42 Percentage of Area Scanned 93.70 Area Scanned 7.75 Percentage of Area Scanned 97.0 Percentage of Area Scanned 47.0 Coverage Radial Scan 100% tVolume 93.70 Coverage Circ Scan Upper 85% t Volume 47.0 Coverage Circ Scan Inner 15% t Volume 12.80 85% t (85% X 47%) = 39.95% 15% t (15% X 97%) = 14.55% Total Coverage Radial and Circ Scans: (93.70% + 39.95% + 14.55%) + 2 = 74.1% (See Radial and Circumferential coverage sheets for more detail.) Radial scans were performed YJith a procedure qualified for the examination of vessel nozzle to shell welds (N-UT 0005). This procedure has been demonstrated for detection of flaws located throughout the entire weld thickness and base material when scanning in the perpendicular direction to the weld. Coverage obtained during radial scans was limited due to the nozzle and weld configuration. In the circumferential scan direction the outer 85%-t is examined YJith the same vessel procedure as mentioned above (N-UT 0005) and has been demonstrated for detection of flaws located in the upper 85%-t of the weld and base material when scanning in the parallel and tangential direction to the weld. Coverage was also limited due to nozzle configuration. To achieve additional coverage in the circumferential scan direction, examinations were also performed YJith a procedure (54-ISI-850-007) qualified for nozzle to shell weld inner 15% thickness region. This procedure has been demonstrated for detection of flaws in the inner 15%-t only when scanning in the parallel and tangential direction as define by the modeling. The nozzle to shell weld inner 15%-t examination techniques were performed in accordance YJith the scanning parameters identified in EPRI modeling report IR-2003-31. Scanning was performed to the maximum extent possible. The total coverage achieved for examination scans performed, is a conservative estimate derived from the physical limitation caused by the nozzle and weld configuration.
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Examiner: Nathan Bauman t:?.. Examiner-david ~~~
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Level: II Date: 04109/12 Level: Ill Date: 04/09/12 Sign: ~/J"-
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Sign:
~ W".AJ R~viewed By: Victor Mo~
S1gn: JilL
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/ j Level: 111 Date: 04109/12
~u Page 9 of 9 0~
'---~~~ ~~ .. ~ <!' .... *----
TVJ\ Ultrasonic Examination 000194 Site/Unit: BFN I 3 Procedure: VENDOR UT Summary No.: 00127-ISI-BFN3 Procedure Rev.: Outage No.: U3RF15 Workscope: lSI Work Order No.: 000 3*SI-4.6.G Report No.: Page: VE-12-031 1 of 1 Code: Section XI 2001 Ed/2003 Add Cat./ltem: B-D/83.100 Location: REACTOR BUILDING-DRYWELL Drawing No.: ISI-0445-C-01
Description:
NOZ IR System ID: 329 - Reactor Vessel Component ID: N10-IR Limitations: Size/Length: Limitati ons noted due to joint deisgn and configu ration
--- 1.5/
-- Thickness/Diameter: 6.6/1.5 Comments:
See Original report book for UT data. 90% coverage attained. No recorda ble Indicatio ns noted. Results: Accept 1"1 Reject 1-1 Info 1-1 Percent Of Coverage Obtained > 90%: No Reviewed Previous Data: Yes Examiner Level II Signature Signature Date Bauman, Nathan 4/10/2012 iner Level N/A Signature Review Date F.W. froscello Jr. 5{7/2012 Level N/A Signature Date ANII Review Date Daniel Williams 4/17/2012
Supple I Report Report No.: UT-12-023 Page: 3 of 3 Summary No.: 00077-ISI-BFNJ Sketch or Photo: O :\lddeai_Server\lddeai_BFN\Documentation\U3R18 Scanned Data\N10-1 TC.JPG lHIC~L . JS AND CONTOUR 2.5' 2.5' Positlon o
- 90 180 270 1 1.'?,1':! /
2' ~0 [7 3 ~0 1'1~ I&Ji
- SIDE ~SlOE
- 4. l.'lqD 1/11 5 .
- 2~ ..L
- weld edge L:)
ANII:* Examiner: *Oats: Print name: Print name: COMPONENT 10: CROWN WIDT .: WELD LENGTH:* 7.5 1 CROWN HEIGHT:! . .. : DIAMETER: . ::t .o g 1f£
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N Supplemental Report N
.IDl Ultrasonic Examination Site/Unit: BFN 3 Procedure: VENDORUT Outage No.: U3RF16 Summary No.: 00186-ISJ-BFN3 Procedure Rev.: 000 Report No.: UT-14.057 Workscope: lSI Work Order No.: 114699848 Page: 1 of 1 Code: Sec XI 2001 Ed/2003 Add Cat.! Item: B*D/83.90 Location: REACTOR BUILDJNG-DRYWELL Drawing No.: 3-ISI-0411-C-01
Description:
SHL - NOZ System ID: 329 -Reactor Vessel Component ID: NSA-NV Size/Length:
------4/ Thickness/Diameter:
6.6/4 Limitations: N/A Comments: See Attached Vendor Report Results: Accept [~l Reject Info Percent Of Coverage Obtained > 90%: N/A Reviewed Previous Data: N/A Examiner Level Signature Date Reviewer Signature Date N/A 3/11/2014 N/A Examiner Level N/A Signature Date Site Review Signature Date N/A N/A Other Level N/A Signature Date ANII Review Signature Date N/A N/A
A RPV Circumferential Scan Coverage Work Sheet Report Number: 3-TVA-NSA-NV AREVA N8 Nozzle to Shell Weld Circumferential Scan Coverage Calculations Total Area:= 14.57 in 2 Total Area: 2.38" x 6.12" =14.57 in 2 Upper 85% t of Vessel Shell Coverage: = 44.82% 0.80" x 5.20" =4.16 in 2 0.91" x 5.20" 12 =2.37 in 2 4.16 + 2.37 = 6.53 in 2 (6.53/14.57) X 100 =44.82 Lower 15% t of Vessel Shell Coverage:= 15.00% 0.92" x 2.38" =2.19 W (Modeled) (2.19 + 14.57) x 100 =15.00% ofTotal Area Total Circumferential Exam Coverage: = 44.82% + 15.00% = 59.82% Page 8 of9
A RPV Coverage Work Sheet Report Number: 3-TVA-N8A-NV AREVA i.* I JOutage: R16 IWork Sheet Number: CWS-03 Utility: TVA Plant: BFN Unit: 3 Component 10: N8A-NV so* :1:(15° to 45') Circ Scan (54-ISI-850-008)
&o*RL Radial Scan (N-UT-78-0007) 100% t volume &o*RL Clrc Scan (N-UT-78-0007) Upper 85% t volume Inner 15% t volume (Modeled)
Thickness (ts) Inches 6.12 Thickness (ts) Inches 6.12 Thickness (ts) Inches 6.12 Weld Width Inches 1.38 Weld Width Inches 1.38 Weld Width Inches 1.38 Exam Area (A B C D E F G H) Sq. Inches 14.57 Exam Area (A B C 0 E F G H) Sq. Inches 14.57 Exam Area (A BCD E F G H) Sq. Inches 14.57 Area Scanned Sq. Inches 13.95 Upper 85% "T" Area Sq. Inches 12.38 Inner 15% "T" Area Sq. Inches 2.19 Percentage of Area Scanned 95.74% Area Scanned 6.53 Area Scanned 2.19 Percentage of Area Scanned 52.75% Percentage of Area Scanned 100% Percentage of Total Volume 95.74% Percentage of Total Volume 44.82% Percentage of Total Volume 15.00% Coverage Radial Scan 100% t volume 95.74% Coverage Clrc Scan upper 85% t volume 44.82% Coverage Clrc Scan Inner 15% t volume 15.00% Total Coverage Radial and Circ Scans: (95.74% + 44.82% + 15.000;1,) + 2 (See Radial and Circumferential coverage sheets for more detail.)
=77.78%
Radial scans were performed with a procedure qualified for the examination of vessel nozzle to shell welds (N-UT-78-0007 (POI-UT-6 Rev H)). This procedure has been demonstrated for detection of flaws located throughout the entire weld thickness. Coverage obtained during radial scans was limited due to the nozzle and weld configuration. In the circumferential scan direction the outer 85%-t is examined with the same vessel procedure as mentioned above and coverage was also limited due to the nozzle configuration. To achieve additional coverage in the circumferential scan direction a second examination was performed with a procedure qualified for the nozzle to shell weld inner 15% thickness region (54-ISI-850-008). This procedure has been demonstrated for detection of flaws in the inner 15%-t only. The nozzle to shelf weld inner 15% thickness examination techniques were performed in accordance with the parameters identified in EPRI modeling report IR-2003-19. Scanning was performed to the maximum extent possible. The total coverage achieved for scans performed in accordance with procedure N-UT-78-0007 is a conservative estimate derived from the physical limitation caused by the nozzle configuration at the vertical sections of the nozzle and does not include additional volume obtained at the horizontal sections of the nozzle. Scanning with the 60" RL was also taken back to the limit of one half inch from the toe of the weld as measured from the 00 weld radius tip and projected to the 10 perpendicular to the surface. The total examination coverage differs from the previous examination coverage due to variances in calculating the examination coverage and utilizing single-sided access ..,.._ techniques and personnel qualified for single sided examination. -C ~------------------------------------------------------------------~--------~-l Page 9 of9 t1'
Enclosure 4 TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant, Unit 3 Request for Relief 3-ISI-29 Attachment A Inservice Inspection Drawings: 3-ISI-0330-C-1 3-ISI-0328-C-2 3-ISI-0332-C-1 3-ISI-0332-C-2 3-CHM-2407-C-2 CNL-17-013
REFERENCE DRAWINGS NOTE.* 47NJ568 47W335-4 & 6
- 7. PIPE SEGMENTS CONTAINING TWO LONGITUDINAL 47W452 SERIES SEAMS WILL BE IDENTIFIED AS: DRAVO [-2460-IC-37, 32, & 33 (BASE WELD NO. )-LS-JD (DOWNSTREAM) NOTE: THIS DRAWING SUPERCEDES (BASE WELD NO. )-LS-2D (DOWNSTREAM) CHM-2747-C ALL SHEETS.
(BASE WELD NO. )-LS-JU (UPSTREAM) MATERIAL SPECIFICATION: (BASE WELD NO. )-LS-2U (UPSTREAM) A-358 GR 304 CL. 7, OR A-403WP304, OR A-706 GR.B, OR SA376 TP 376NG THE -LS-7 SEAM WILL BE NUMERICALLY CLOSEST TO 0' ON THE PIPE, AND THE -LS-2 SEAM WILL BE 24" X 7.279" NOM. WALL THK. SCH. 80 55 NUMERICALLY FARTHERMOST FROM 0' ON THE PIPE. 20" X 7. 037" NOM. WALL THK. SCH. 80 55 (e.g -LS-i AT 730', AND -LS-2 AT 370'~ 20" X 7. 037" NOM. WALL THK. SCH. 80 CS 2 PIPE SEGMENTS CONTAINING ONLY ONE
. LONGITUDINAL SEAM WILL BE IDENTIFIED AS '):
~** ADMIN 6" X 0. 432" NOM. WALL THK. SCH. 805 55 FLUED HD 55 FORGING A782 F304 VALVES WITH THE EXCEPTION OF FCV-74-47 (BASE WELD NO. )-LS-D (DOWNSTREAM) ARE 55 CASTINGS A357 CF8M (BASE WELD NO. )-LS-U (UPSTREAM)
ASME CC- 7 (EQUIVALENT) DSRHR-3-07-LS-7 DSRHR-3-07-LS-2:>----__ DSRHR-3 ~
....._______ DSRHR-3 -06 ' DSRHR-J-06-LS SYMBOL:
002 ADMIN M. L. POOLE ~Cttm lJP/'6'/icr 7-3tNZ REVISED PER RIMS MEMO R14 120119 105 {R F: BFPER 443133) REV CHANGE REF PREPARER CHECKER APPROVED DATE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT UNIT 3 RESIDUAL HEAT REMOVAL SYSTEM WELD LOCATIONS DRAWN* PHB SCALf- NTS CADAM !SICMP CHECKED. J£5 SHEET 0 1 OF 0 1 REV SUBMI TT£0 EOC 3- IS I -0330-C ooz ALL A/0 HISTORY RESEARCHED AT ROOD ceo
REFERENCE DRAWINGS: TVA 47K7544-3 GE 153F754 KELLOGG BF 2-780 B - LOOP RWR-3-002-G001 NOTE: THIS DRAWING SUPERSEDES RWR-3-002-G003 CHM-2739-C ALL SHEETS GR-3-59 (OL) N18-SE GR-3-59-LS N2A 30 MATERIAL SPECIFICATIONS:
- 1 Hr------..
a KR-3-50\ A358, TP 304 N2A-IR 4 X 0. 337 NOM WALL THK. (SS) KR-3-50-LS-1~ \ N18 180o II II o 28" X 1. 138 NOM. WALL THK. (SS) SUCTIO 11 KR-3-50-LS-2--- ~~~----_____.~"'-N18-IR '\')0 28" X 7 .322" NOM. WALL THK. (SS} DISCHARGE
~~tt_,.1\<
GR-3-60 (OL)---. RWR-3-002-G013-....... 0 ~~ SA403 WP3 76NG RWR-3-002-G015- - ~ GR-3-60-LS~ ADMIN 12 X 0. 602 MIN. WALL 11 11 GR-3-61 " \ 22 11 INTEGRAL RED. TEE 0. 980" MIN. WALL 28 11 X 22 CROSS 0.980 MIN. WALL 11 11 28 11 X24 11 INEGRAL TEEX 1.272" MIN. WALL VALVES 55 CASTINGS A351 CF 8 PUMP CASING 55 CASTING A351 CF8M
" RWR-3-002-G076 ASME CC-7 (EQUIVALENT)
, ; - RWR-3-002-G024
~ IRWR-3-002-G018 ( ..........._
IRWR-3-002-G022 RWR-3-002-G020~ -......._ RWR-3 -002-GO 77 I 2~-...__ BENT INTEGRAL TEE
-......_ W/12 X22 RED. (2 TYP.)
11 11 GR-3-61-LS--- k"" 22" SEE DETAIL A DETAIL A - ONE PIECE SPECIAL FORGING IRwR-3-oo2-G023 r / RWR-3-002-G021_/
~
~ ~ RWR-3-002-G019 28 X 22" CROSS SW-TPR-3-27~
11 W/22 X 12 RED. 11 11 SEE DETAIL 8 RWR-3-002-G025~ r KR-3-26 KR-3-51 ~ I; GR-3-33 DETAIL 8 - ONE PIECE SPECIAL FORGING KR-3-24-LS~ D51 I r ___.-- KR-3-24 KR-3-51-LS-1~ I IV) KR-3-51-LS-2 GR-3-63A ~ SYMBOL: GR-3-62~ - 4 II fGR-3-638 Cl.. I t:tJ ~ GR-3-29-LS-1 RISK-INFORMED WELD
~
FCV68-77
'-.. ""-...___ GR-3-29-LS-2 GR-3-63 ' "-.__ GR-3-29 GR-3-63-LS ""'- FCV68-79 KR-3-53~ \ FCV68-79-BC
~:-30 4" GR-3-28 4
11 DECONTAMINATION LINE ~~_/ ~ GR-3-27-LS 002 ADMIN 7*30*/Z.. R8C-3-2~ KR-3-52 ~~, KR-3-23 DATE KR-3-52-LS-1 j TENNESSEE VALLEY AUTHORITY KR-3-52-LS-2 GR 64 (OL) XR-N-N BROWNS FERRY NUCLEAR PLANT UNIT 3 K ~ KELLOGG SHOP WELD _j I ~ WELD NO. RECIRCULATION SYSTEM WELD LOCATIONS G = GE FIELD WELD ~ UNIT NO. DRAWN: PHB SUBMITTED APPROVED SCALE NTS SYSTEM D"Af£:4-4::S9- DA TE.:.J:::;_8-89 DALE_J=.}l_-89 SHEET 2 OF 2 SHEET S CHECKED: _}ES_ DRAWING NO. REV. EDC DATE: 5-8-89 GLB 3-ISJ-0328-C002 ALL A/D HISTORY RESEARCHED AT Rooo leAD MAINTAINED DRAWING I t-------C_C_D____~
REFERENCE DRAWINGS RWCU-3-00/ (TVA WELD MAP) NOTE: THIS DRAWING SUPERSEDES A PORTION OF CHM-2144-C I MATERIAL SPECIFICATIONS FITTINGS 6u SA403 WP3/6NG SCH. 80 PIPING 6 ~~ SA376 TP3 16NG SCH. 80 ( VAL V£5 55 CASTINGS A351 CF BM "")
~*4---------------------------
ADMIN ASME CC-I (EQUIVALENT) RWCU-3-00/-G0/6 _./ 1~RWCU-3-001-G0/7 I---
-:_1 RWCU-J-00 I-GO /8
, ..___RWCU-3-00 I-GO 19 oo2 1 ADMIN 1M. L. PooLE l~ettmwetiiDP .KBJ~r 1 7-3o-;z REVISED PER RIMS MEMO R14 120119 105 (RtF: BFPER 443133) REV I CHANGE REF I PREPARER I CHECKER I APPROVED I DATE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT UNIT J REACTOR WATER CLEAN UP RCIC I I AND CRD WELD IDENTIFICATION DRAWN: PHB DATE: 5-17-89 SCALE: NTS j CADAH/ISICMP ceo 0 I OF 02
.-----r---~
CHECKED: JES APPROVED: SHEET REV SUBMITTED: EDC GLB 3-ISI-0332-C oo2 ALL A/D HISTORY RESEARCHED AT ROOO leAD MAINTAINED DRAWINGI
REFERENCE DRAWINGS TVA 47W335-14 REGION OF THERMAL TVA 47W335-17 FA TIGUE EXAMINATION RWC-3-004 (TVA WELD MAP) PER NUREG-0619 ~ ~ NOMINAL DRAVO E-2460-IC-49 z*L..-0~--lf-WALL THERMAL TEE CJ UPSTREAM OF VALVE ~ NOTE: 3-FCV-69-629 THIS DRAWING SUPERSEDES CHM-2143-C AND CHM-2144-C (ALL SHEETS) RCRDS-3 TEE~ MATERIAL SPECIFICATIONS RCRD-3-45 4" X 0.337" NOM. WALL - CS 8 "xB "x6" RCRDS-3-02 SCH. 80 A-333, GR1 (SEAMLESS) THERMAL TEE RCRDS-3-03 6 " X 0.562 NOM. WALL - CS, SCH. 120
~RCRD-3-44 8" X 0.593 NOM. WALL - CS, SCH. 100 CRD CAP 4 " X 0.674" NOM. WALL ss R14 120505 106 VALVE 69-629 SA 105, CS FORGING DET A R14 120119 105~ VALVES SS FORGINGS A182 F316 85-576' 85-577 NOTE: ALL FIELD WELDS WERE MAD£ BY TVA ASME CC-1 (EQUIVALENT)
R14 120505 106 RCRD-3-49 (NUREC-0373) RWCU-3-007-003 IDRWC-3-59 85-577
'6,_/ (STAINLESS STEEL)
\J._ ___ RCRD-3-50 (NUREC-0313) 8"
- P----RCRD-3 -57
_~ RCRD-3-52
~~
85-576 (NUREC-03!3)
~ N9-IR (STAINLESS STEEL)
RCRD-3-33 / CRD RETURN LINE NOZZLE CAP DETAILS TRCIC-3-005 SYMBOL:
~
RISK-INFORMED WELD 0 007 ADMIN K KING REVISED PER RIMS MEMO R14 120119 105 (REF: R 1 4 1 20505 1 06 REV CHANGE REF PRE PARER CHECKER APPROVED DATE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT UNIT 3 REACTOR WATER CLEAN UP, RCIC, AND CRD WELD IDENTIFICATION DRAWN: PHB DATE: 1-4-93 CHECKED: RPG APPROVED: SHEET 02 OF 02 REV f...--------; GLB SUBMITTED: JES ..3- IS I- 0..3 ..3 2- C oo7 ALL A/0 HISTORY RESEARCHED AT ROOD leAD MAINTAINED DRAWINGII------------~ CCD
47W335-13 47W455 SERIES E-4707 2F*I238 THPCI-!*gg-->...r~~THPCt-3-100
~-....._ THPCt*!-100 0 THPCI-3-98 ---il-7--
~ THPCI-3-30
..,....,_THPCI*!-29 THPCI-3-t OOA--)~ THPCI*!-1008__..,.,
< THPCI-3-28 ~ THPCt-3-fR
~ THPCI-3*27
~'""*-~- THPCI- 3-101 THPCt-3*96 SUPPRESSION "<.. -"E--e-THPCI-3 -I 02 POOL ....."""~~
IOIA
~~~ ~~~THPCI-3*136 ~THPCI-3-103 L__**uft~ *-3 ..
THPCTHI PCI-3-134 --..-""' ~24"at6* REDUCER
;~:;..>~ ~*~o~r :v 73-23 THPCI*3*133 HPC I 009-004 THPCI-3-132 3 CKV 7 3 603 HPCI-3-009-005 - - -
~E--THPCI-3-25 2Cfxl6" ~- HPC I 009-003
~--E-- HPCI 009-009 K-......-THPCI- 3-24
.JJ~C-~THPCI-3-128 4 f{,V 73-44 THPCI-3-23
'-~~-THPCt*3-106
"-..THPCt-3-22 THPC1*3*107
,. FOI 73-34
..: THPCI*3-20 THPCI-3-123 20"af6" REDUCER THPCI-3-122
~-~THPCI*3*120C THPC1*3*1208 --ill._~ HPC I 01 9-009 K-~-...- THPCI-3-18
~THPCt-3-120A
..., THPCI-3-17 SHPCI*3-8 ----i...,.....~,.-.~-+---~SI:it1t~PCI- 3-7 SHPCI..3*2
< THPCI-3-110 IO"xiO"*IO" TEE SYMBOL:
<: THPCI-3-111 RISK-INFORMED WELD 12~~*t;'tf, ~
"c~t 1 HPCI-3-019-011
-t SHPCt-3 -g c?Q ~ ~THPCt-3-II~O
~ BOOSTER
_U.. _ / PUMP FCV 13-ra ~e HPCI TURBINE THPC1*3-IO
~ -1411x to* REDUCER ~
~k--THPCt-3-11 J.-
~,._..THPCI-3-12 THPCI-!-13 ~ ~
~C!~, TINNIIIR YAUIY AUTMOIIITY THPCI*!-14---tlloV"'" ~
IMYIIION Of NW" 'AI ..OMI BROWNS FERRY NUCLEAR PL~ UNIT -3 HIGH PRESSURE COOLANT INJECTION IYifEM WELD LOCATIONS DD4 ADMIN J MCFARLAND £./C /-loDGES REVISED PER RIMS MEMO R14 D4D521 1D1 REV CHANGE REF PREPARER CHECKER APPROVED DATE ALL A/D HI sToRY RESEARCHED AT Rooo 1cAD MAINTAINED DRAWING 11--___c_c_o_____,
Enclosure 4 TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant, Unit 3 Request for Relief 3-ISI-29 Attachment B Examination Data Reports: UT 12-024 UT-12-031 UT-14-039 UT-14-027 UT-14-031 UT-14-036 UT-14-001 UT-14-002 UT-12-046 UT-12-047 CNL-17-013
1m] Site/Unit: Summary No.: BFN I 05109-tsi*BFN3 3 UT Calibra tio. -mi nation Procedure: ProceQ.Jre Rev.: N*UT-65 Outage No.: U3RF15 5 ReportNo.: UT-12-024 Wor1<scope: lSI Wor1< Order No.: 3-SI-4.6-G Page: ol 7 Code: Section Xi 2001 EcU2003 Add CatJitem: R-AIR1.16E Location: REACT OR BUILDING-DRYWELL Drawing No.: 3-ISI-0328-C-o2
Description:
VLV - P Sys!em ID: 068
- Reac:tor Water Recirculating System Component ID: GR-3-63 NONE .............................----------------------------------------------
........... Slze/Leogth: 2B I Thickness/Diameter:
Umltations: 1.138/ 2B Start Time: 1130 Finish Time: 1150 l nstNm ent Settings Search Unit Serial No.: E37688 Cal. Time Axial Orientated Search Unit Serial No.: OOW3N2 Date Check s Manufacturer: KRAUTKRAMER Calibrati011 Manufacturer: KBA lnlual Cal. 1030 Signal Sweep 411212012 Retlector Amplitude% Sound Path Model: USN60 Unearity: L-to-412 Division Size: 0.5" Modei: CompG Inter. Cal. N/A Delay. NTCH NIA 3.1 .9 7.77 Range: 3.0 Freq.: Inter. Cal. NIA 2.25 MHz Center Freq.: NfA NTCH M'li Cai/Vel: .1337 N/A 6 1.8 Energy: High Inter. Cal. NfA Exam Angle: 60 Squint Angle: N/A NTCH NIA 9 2.7 Damping: 10000 hms Reject: Final Cal. 1235 411212012 0 Measured Angle: 60 Mode: NIA WA NIA SHEAR NIA PRF Mode: Auto High SU Freq.: 2.25 MHz Couplant Elcit Polnt: NfA t ol Elements: NIA NIA NIA NIA Oisp. Start: 1 JP Rectify: FulL Wave - Cal. Batch: 06125 Circumferenti al Orientated Search Unit Config.: SINGLE Focus: NIA lnst. Freq.: 2.25MH z Type: Ullnlge l II Shape: Round Contour: Calibrallon Signal Sweep FLAT Sound Path Mfg.: Sonotech ReflectOr Amplitude% Dlvisioo Wedge Style: Non-Integral Ax. Ga1n (dB): Exam Batch: N/A NIA NIA NIA N/A Circ. Gain (dB): NIA Search Unit Cable NIA N/A 1 .3 Type: N/A H/A NIA Screen Div... ln.ol Sound Path Type: RG-174 Length: 6 No. Conn.: 0 M~ . NIA N/A NIA NIA
- g.. N/A Callbra llon Block Scan Coverage NIA NfA N/A NIA Cal. Block No.: WB-85 Upstream 0 Do.vnstream~ Scan dB: ~ Reference Block Referenc&'Sim ulator Block Thickness: N/A Dla.: NIA Gain Signal CWO CCW 0 Scan dB: ~ Serial No.: 790662 Sweep dB Reflector AmPlitude% Division Sound Path Cal. Blk. Temp.: 7J Temp. Tool: 558274 Exam Surface: Type:
OD Rom pas 40 NSDH Comp. Temp.: 70 Temp. Tool: 80 2.2 .6 558274 Surface Condition: As Found NIA N/A NIA NIA N/A
~ 0 ieport.) NIA NIA NIA NIA N/A Results: NAI 0 AI ~ Info U THROUGH WALL SIZING Comments: 558274 DUE DATE 12*10.2012 E37688 DUE DATE0&-15-2012 Percent Of Coverage Obtained> 90%* N/A Reviewed Previous Data: Yes Examiner lellel 111-PDI~~~ Date Reviewer Welch, M atthew C.
Examiner 411212012 Damon Prteatley, Llll ture
. Date 1
I 0 l evel H/A Signature Date Site Review 0 II. '/I NIA Date 0 Otnef Level NfA Signature Date ANI! REMe.v N NIA N . h Date UT Calibraticn'Examlnallon
/JA(Iclf' C~/V'/1 I
'1/lr/1~ N
Supp Report Report No.: UT-12-024 Page: 5 of 7 Summary No.: 05109-ISI-BFN3 Sketch or Photo: O:\lddeai_SeiVer\Jddeai_BFN\Documentation\U3R 18 Scanned Oata\GR-3-63 TC.jpg THICKNESS AND CONTOUR PositiOn 0 90 180 270 I~ 2.5' z.s- - - - .....a. 1 M
- 2. .ZJ .I v 3 ?/ ';/,.
,t VPL__srDE 4*
s r.z.o / A~SIOE
*weld edge
/)e:t;Ui-Ud' ~ v~:
.1sxt . 77x 'ff!== 7o. '1t~>J 3 o~~v~:
7a,q - (15>< .r1;<. 'tt) ~ 3§,b IN -y1o.r~ .5oz.xtoo-=- 5az.1o
,. ~---1
/to
~=No lO~iU4f.
A? &kh~ C> Supplemental Report 0 0 N N 0)
Supplem Report Report No.: liT-12-024 Page: 6 of 7 Summary No.: 05109-ISI-BFN3 Sketch or Photo: O:\lddeai_Se!Ver\lddeal_BFN\DOCtJmentation\U3R1B Scanne d Oata\GR-3.Q3 PLOT.jpg INDICATION PLOT CompO nent 10: ~ I( - ~- ""3 Reviewer. Print name: Date: 'e::J 2-o/L RL-J?~uj ~ ... /,o
/WE -7'Ju.,c:!J ~M/tur-= . 7--
~
~ I IJ tllc:A"fbN tr I
~ --t---- ".i:Jo
~o*
~ f.{}
T Set LJ-1" I N'D1U. T1CW ~4ciN~ RE'Po Jat fOR v,o\UJE"~.
~*~-J 0
0 Supplemental Report 0 f'\.) N
'-.l
Ultrasonic ln di c- Sizing Report Site/Unit: BFN J 3 Procedure: N-UT-65 Summary No.: Outage No.: U3RF15 05109-ISI-BFN3 Procedure Rev.: 5 Report No.: UT-12-Q24 Workscope: lSI Work Order No.: 3-SI-4.6.G Page: 7 o1 7 Item Identification: GR-3-63 Weld Crown Width: Lo Location: TOC Start Time: 1.5 11:30 I Measured Component Thickness: Wo Location: 1.2 WEL DCL Finish Time: 11:50 lnd Angle dB 00 Length Remaining Thrv Intermittent or I No. Used Technique Recommendations or Remarks Ugament Used or Wall Continuous Used L1 L2 Total Useful 1 60 NIA AATT 34.7 36.4 1.7 1.0 .2 1 CONT SEE BELO WW/M AX 1.6 45 NIA AATT 34.7 36.4 1.7 N/A 1.0 .2 CONT SEE BELO W W/MAX 1.1
- WA Additional Remarks:
THRO UGH WAL L SIZING OF EXJSnNG IGSC C REFLECTOR. THIS EXAM SATISFIES THE IN THE ORIG INAL SCHEDULE AFTER SUCC REQUIREMENT OF IWB-2420(c) FOR COM ESSIVE INSPEC110N PERIODS. NO CHAN PONENTS PLAC ED GE DETECTED Examiner Welc h , Matthew c. Level 111-PDI I Date Reviewer 4/1212012 Damo n Prresuy, Llll Date Examiner Level N/A Signature 12-NIA Date Other Level NJA Signature NIA Date IANII Review 0 Date 0 Ultrasonic lndicatlon Sizing Report ~vd c'AA1,* Y/I'J/12-- 0 N (\) OQ
UT Calihr~**~"~ min ation Site/Unit: BFN I 3 ~
--------------------------- Procedure:
Procedure Rev.: N*UT-64 Outage No.: U3RF15 11 Report No.: UT-12..()31 Work Order No.: 3-SI-4.6.G Code: Page: 1 ol 6 Section Xl2001 EcU2003 Add Cat./ltem: R-AIR1.160 Location: REACTOR BUILDING-ACCESS Orawing No.:
----------------------------ROOM 3-1Sf.0330.C.01
Description:
VLV - Ftl System ID: 074 - Rosldual Heat Removal System ComponentiO: DRHR-3-12 Limitations: -------------------- ------------------------------------- YES- JOINT CONA G AND CAST SS COMPONEN T Sizetl.ength: 24 I Thickness/Diameter: 1.219/ 24 SlartTime: 1155 Finish Time: 1225 Instrument Settings Seareh Unit Serial No.: E:963Q 2 Cal. Time Serial No.: Date Altlal Orien1ated Search Unit 01FH9X Check s Manufacturer. KRAUTKRAMER Caibralion Manufacturer: KBA Initial Cal. 0930 411412012 Signal Sweep Model: Reflector AmpiHude % DMsion Sound Path USN6 0 Unearity: L-12-003 Size: 0.375" Model: Comp G Inter. Cal. NIA Delay: 1.5 NOTCH 80% 6.6 8.4278 Range: 6.0 Inter. Cal. 1215 411412012 3.958 Freq.: 1-5 MHZ Center Freq.: N/A M'tlCal/Vf!J.: .1262 NIA Energy: High Exam Angle: Inter. Cal. N/A N/A Damping: 10000 hms 70 Sql.int Angle: NIA Final Cal. 1244 Reject: 0 411412012
~red Angle: 68 Mode: Shear NIA PRFMode: Aulot ilgh SU Freq.: 1.5 MHz Exit Point: NA # of Elements:
Couptant N/A Disp. Start 1 IP Rectify. FuHW ave - -- - Cal Batch: 06125 Ci rcumferential Orientated Search Unit lnst. Freq.: 2.0 MHz Conf~g.: SINGLE Focus: NIA Type: i Shape: Ultrag etll Calibration Round Contour: NIA Signal Sweep Mfg.: Reflector Sound Path 1 Sonot ech Amplitude% DMsi<ln Wedge Style: Non..,ntegral Ax. Gain (dB): 51.3 EXMI Batch: NIA Circ. Gain (dB): NIA Search Unit Cable 06125 NIA
- 1 Screen Div. :o
-.6- in. of CllllbraUon Block Sound Path Type: RG*174 Length:
6 No. Conn.: 0 Type: Ml . g.. Ultragel ll Sonotectl N/A Scan Coverage NIA Cal. Block No.: SQ.123 Upstream 0 Downstream~ Scan dB:~ Refere nce Bto~ R~~~mu~lorB~k Thickness: 1.5 Dia.: FLAT Gain CW O CCW O Scan dB: ~ Serial No.: 189631 Signal Sweep Cal. Blk. Temp.: 2!!. Temp. Tool: dB Reflector IAmplitude % Division Sound Path 558274 Exam Surface: Type: OD Rompas 51.3 FSDH Comp. Temp.: I!:!, Temp. Tool: 558274 Surface ConditiOn: 39 2.9 1.63 lSI Prep N/A 0 ~ Report.) NIA Results: NRI ~ Rl :-;
'-' Info 0 Comments: E36302 DUE DATE IS 06-15-2012 558274 DUE DATE IS 1 2*1~2012 Percent Of Covetage Obtained > 90%: No Reviewed PfevlOliS Data: Yes Examine~ Level IJ(N)
Date Rah, Edward W ~ature 411412012 .H/~J. Date Examine~ Level NIA Date
-v~/Z..
N/A Signature Date Other Level NlA SIQ.nature. 0 Date I ANII Review 0 NIA Date
'vc/ ' e-:tM *'~t-h 0 l.JT Calibration/Examination /3 .. tt/lf/12- N
~
~
Supplemental Report Report No.: UT-12..031 Page: 5 of 6 Summ ary No.: 05100..JSI*BFH3 Sketch or Photo: O:\ldde al_Serv er\lddeal_BFN1Documentation \U3R18 Scanned Data\DRHR-3-12.jpg THICKNESS AND CONTOUR Pos1mon 2" I~J..Ioo IJ_y 11J7z J 14 2.5" z.s* ___ _... 3 If,¥ I I/ .... 4" 11.-1 I / fi..~SlDE VA'-~SIOE 5 l"'l.t 1/
'Wefdedge Examiner:
Print name: S"P l=rSH Date: COMPONENT 10: DRJH~- ~ *1 2-CROWN WIDTH: f.p " CROWN HEIGHT: m
,:;.~
/?6J.tuud~~:
(i'.o~x..s) t{ 75.1-{ = 77. z.~s tAr3 ~ OI:J#Rt.ter8l:> 1/0UJP. ~ ; t..A~/55 tJ~~~: 4:.
-=f
~,;,?- /"J*S/ 7?.Z8 $ :::, Z~~
~- ZY/f/?1* l-SS c , :?1~ tJ.t7HC1f/aL ~ ~
(c.n'l-f,ZU.) +'Z)xlofl "" ~o~ /,1/5 t./8 a~ss
.uT t\ ' ~~ c.A~ ss ,,o 1~111
.t n.-z.r>/-1.)- q~~u';.
15.'t) :! ~1,.;~cut c *(IS<*I)i>>.tJD7<(tt1') . \. ~o
~f&tl.)A 1'5.-f !:- fl.5JMI *~116'16P AJCIIf~
0 Supplemental Report 0 0 l\)
.CJl
Report Report No.: UT-12-031 Page: 6 of 6 Summa ry No.: 05100-I SI-BFN l Sketch or Photo: O:\Jddeai_Server\JddeaLBFN\Documentation\U3R18 Scanned Data\OR H R-3-121im ltalion.jpg DRHR-3* 12 Discussion: Limitations due to joint oonf~guration and Cast SS Compc~nent:
- Joint collflguratlon oonsists of a cast stain leas steel valve to a penetratio n llued head.
- POl Supplem ent 2 ls not qualf"11d for detllction in Cast SS rr11tarial.
Joint geometry limits shear wave axial scan motion to o:zr Joint geometry li!Tlib> refradl!d longitudinal axial scan tTntion to 0.0'. o Wave fO<:USi'lg requirements defined in PDI-UT-2 , Rev. E. para. 6.8.2 .(b) reqUired the probe footprint to be too large for the avalable scanning surface.
- Nonparallel surfaces (00 vs. 10 of base mDierial) IIIT'ited tho circurrtore ntial scan ditodion to tho weld CfOIM1.
o PDI-UT-2 , Rev. E, para. 8.3.3 requires scan form the weld orown to be parallel to weld oenter line.
//(~~~ /_ZZZ::: ¥/7j!~
0 0 Supplemental Report 0 N CJ1 N
1m Sit()I\Jnlt: Summary No.: - - - - - W orkscqJe: BFN I 05054-ISI- BFN3 lSI 3 UT Calibration/E: .... crmination ProcEdUre: Procedure Rev.: Work Order No.. N-UT ~4/PDI-UT -2 131F 114699848 OulageNo. Report No: Page U3RF1& UT-14-039
~
of _.!__?~)( Cede: Section Xl2001 Ed/2003 Add Cat/Item: R-AIR1 .11 location: REACTOR BUILDING -DRYWEL L Drawing No.: 3-ISI-0330-C-01 De<>cription* T EE
- P Sy.;tem 10: 074- Residual Heat Removal System Component ID: DRHR-3-19 Slzellength: 20 I Thickness/Diameter. 1.031/20
----------------~------------------
Limitations: See Coverage Plot - :5~ ~ ~ ----------------- Start Time: 0851 Finish Time: 1050 Instrumen t Sel1ings Search Unil Serial No.: car. Time Date Axial Orientated Search Unit E36302 Serial No.: 01YPH2 C hecks Manufacturer: KRAUTKR AMER Calibration Signal Sweep Manufacturer: GE Initial Cal. 0830 31512014 Sound Path Reflector Amplitude % DMslon Model; USN60 Linearity: L-14-003 Inter. Cal. Size: 0.5" Medel: CompG 1.5 Notch 80 5.6 2.030 Delay: 7.6041 Range: 3.700 Inter. CaL Freq.: 1.5 MHz Center Freq : N/A M'IICaWe f* 0.1249 Energy: High Inter. Cal. Damping: 1000 Ohms Reject 0 Exam Angle: Measured Angle:
---43 45 Squint Angle:
Mode:
--- NIA Shear Final Cal. 1137 3/5f2014 PRF MociP.* Auto High SU Freq. ; 1.5MHz Couplant Exit Point* .5" # o1 Elements: 1 Otsp. Start: IP Recrify: Full Wave - - Cal Batch: 12H130 Circumfer ential Orlenlatod Search Unit Config.: Single Focus: NIA lnst. Freq.: 2.25MHz Type: Ultragelll Calibration Shape. Round Signal Sweep Contour Flat Sound Path Mig.: Sonotech RenectOf Amplitude % Divisim Wedge Sryte: Non-Integ ral 1.5 Notch 80 5.6 Ax. Gain (dB): 23.4 Circ. Gotn (dB):
Exam Bach: 12H130 2.030 23.4 Search Unit Cable Type: -- = Ullragel II 1 Sr.reen Div.
--.3T in. ol Calibratio n !:!lock Sound Path Type: RG-174 Length:
Scan Coverage
-6 No Conn.: 0 Mfg.: Sonotech cal. Block No.: WB-84 Upslleaml i!J Downstrea mli!J Scan dB: 37.0 Reference Block Roforence /Simulato r Block Gain CCW bZJ Scan dB: 37.0 Thickness : 1.5 Ola: Flat Serial No: Sign;~I Sweep CW2J 790398 Sound Path dB Reflector Amplitude % Di-Aslon Cal. Blk. Temp.: 67.6 Temp. Too: 531993 EXam Surface:
- - Type: SS Rompas ID 43.3 FSDH 80 2.8 1.008 Comp. Ternp.:
-- Temp.
76 Too: [l 531993 Surface Condition: Ground 0 tllrasonic lndlcatim RepOrt .) Results: NRI ~ Rt 0 Info O Comments : E36302 Cal Duo 10/2612014 531993 Cal Due 10/2612014 Pf!fcent Of COllerage Obtained> 90%: 59.24 Review~'tl Previous Dala: Yes
£)(8miner Level Ill' I Date Revtewer Date a/o~f KlEINJAN , DAVID R 3/512014 Mall Welch , Ull e-tliner Lll"!!! NIA Date 1S~e Review Signature NIA Date NIA OUlE!f LE!\-el NIA Date NIA UT C<llibr.tioniExamiOOiion
COVERAGE PLOT 1 Examiner: Print name: .s 'frn.~-<d r 1., ,.,.{ Date: Date: Date: J
- TEE Flow .. Pipe AXIAL SCANNING oo TRANSVERS E SCANNING 1"
1" ~ Area of no coverage 1:).7/5 b
SUMMARY
NO: 05054-ISI-BFN3 _jsm: BROWNS FERRY j Umtlt3 DESCRIPnO N ITEETOPIPE !IDENTIFICATION* DRHR-3-19 SYSTEM 10: Prepared By: RESIDUAL HEAT REMOVAL SYSTEM L/1- I '/--039 Reviewer By: 1AVID 1~/' MATIWELCH Signature: ,1?, ~~ - Signatu re: ~t{~?v~ Date : tJ5 ,Affi7lm/77 , Date: o/co// y-Items# Axial Required Exam volume for scan 3 1 ((0.375+0.40 6)/2)"0.931" 58.5= 21.2680 Axial Required Exam volume for s can 4 2 ((0.406+0.35 2)/2)
- 1.254" 58.5=
27.8031 Clockwise and Counte rClockwise Required exam volume on the upstream side (scan 5 & 6) 3 ((0.37S+0.40 6l/2J* o.931.58.5= 21.2680 Clockwise and Cou nterCio~kwisc Required exam volume on the downstream side (scan 5 & 6) 4 (10.406+0.35 2)/2)"1.254" 58.5= 27.8031 Axlal Obstructed Vo lume Exam for sc<Jn 3 5 ((0.375+0.40 6)/2)"0.931" 58.5= 21.2680 Axial Obstructed Volume Exam for scan 4 6 0= 0 .0000, Clockwise and Counterclock wise Obstructed Volume Exam on the upstream side (scan 5 & 6) 7 I 0.2292.58.5= 13.4082 Clo ckwise and Cou nterclockwis e Obstructed Volume Exam on the downstream side (scan 5 & 6 ) 8 Q: 0.0000 Axial Obtained Exam Volume for scan 3 9 Item l-Item 5 = 0.0000 Axial Obtained Exam Volume for scan 4 10 Item 2 - Item 6 = 7.7.8031 Clockwise and Counter Clockwise Obtained Volume Exam on the upstream side (scan 5 & 6) 11 Item 3 - Item 7 = 7.8598 Clockwise and Counter Clockwise Obtained Volume Exam on the downstream side (scan 5 & 6) 12 Item 4 - Item 8 = 27.8031 Axial Exam Volume Percentage for scan 3 13 (Ite m 9/(ltem 1))"100 =% 0.00% Axial Exam Volume Percentage for scan 4 14 (Item 10/(ltem 2W100::% 100.00% Clockwise and CounterCloc kwise Exam Volume Percentage on the upstream side (scan 5 & 6) 15 (Item 11/{ltem 3W100 =% 36.96% Clockwise and CounterCloc kwise Exam Volume Percentage on the downstream side 5 & 6) 16 (s~an (Item n/(ltem 4W100 =% 100.00% Full Exam Volume Percentage combining in the Axlal, Clockwise, and Co unterClockw ise Dircetions 17 (Item 13 +Item 14 + Item 15 +Item 16)/4 : '1(. 59.24%
~~
~ I
~c-
~ d
/?~/?
I "\I
~ ~~~
~
o-
THICKNESS AND CONTOUR 0 2.5" 2.5" Position 90 180 270 1 N/A N/A N/A N/A
- 2. 1.105 N/A 1.104 Nil\
3 4. 1.062 1052 N/A N/A 1.073 1.022 N/A N/A lEE PIP!: SIDE 5 I 1.092 N/11
- weld Edge 1.087 N/A !
L/1- )J./-tJ37 FLOW -v WELD LENGTH: 58.5" DIAMETER: 20 Flow WT WT DRHR-3 -19 WT DSRHR- 3-08 WT Pipe 6.5/tf otJLW 1 I DRHR-3 -19 WT WT DSRHR 08 WT oo 1" 180° 1" J
~
UT Calibration/E.xamination Site/Unit BFN I 3 Pmce:lure: N-UT -64/PDI-U T -2 OUtage No.: U3RF1G Surnmr~ry No .* 05094-15 1-BfNJ Prooedur e Rev.: 13/F Rer11rt No
- UT {)27 Works cope: lSI
;£ -:j Worl\ OrdE!f No. 11469984 8 oage* 1 of Code: Section XI 2001 Ed/2003 Add Cat .litem: R-.A/R1 .16C Location : t---VJ.,)* f REACTO R BUILDING ..ORYWE LL Dra.,.~ng No.: 3-IS I-{)330-C-{)1 DescriptiOI'l P . EL System 10: 074 - Residual Heal Removal System
- 10. DSRHR-3 -0SA Compolle nl Stzelleng th: 24 I Thicllnes s/Dlamme f: 1.219 / 24 limitiltlon s* Access limited on upstream side StartTfme: 1657 Finish Time: 1740 Instrume nt Settings Search Unit Serial No.: Cal. Time Date Axial Orientate d Search Unil E37688 Sem!l No.: OOFCYR Checks ManulaclUref": KRAUTK RAMER Calibration Signal s~
Manufacturer. KBA lnhial Cal. 1417 3/312014 Sound Path Reflector Ampl"ude o/o Division Model: USN 60 Linearity: l 002 Inter. Cal . 1657 3/312014 Size: o.5~ Medel: CompG 1.5" Notch BO 6 2.057 Delay: 6.4972 RMge. 3.411 Inter. Cal . Freq : 1.5 MHZ Cente~ Freq : N/A M'U CaiNel: Energy: Inter. Cal.
---43 0.1230 High Elcarn Angle: 45 Squlnr Angle: HIA Damping: 1000 Ohms Final Cal. 1741 31312014 Reject: 0 MP.a.~ured Angle: MOde: Shear PRF Mode: Auto High SU FrEq.: 1.5 MHZ Couplan t Exit POint: Min # of Eiernents: 1 Oisp. Start: IP Rectify. Full WaYe - - Cal. Batch: 13C002 Circumfe rential Orlontate d Search Unit Conlig.: Single Focus: N/A lnst. Freq.: 2.0MHz Type: Ullragoll l Shape: Round Calibratio n Signal SWeetJ Contour: Flat Mfg.: Sonotech Reflector Amplilud e% Olvisioo Sound Path Wedge Style: NON-INT EGRAl ExamBac ch: 1.5" Notch 80 6 2.057 Ax. Gain (dB): 24.2 Clrc. Gain (dB): 24.2 13C002 Search Unit Cable Type: Ullragell l Semen Oiv. ;
--.34 it1. d Sound Path l)pe: RG-174 Length*
-6 No. Conn.: ~ Ml .
g .. Sonotech Calibra tion Block Scan Coverag e Cal . Block No : WB-85 Upslream6ZJ Referenc e Block Referenc e/Simul ator Block DOYmstrearnjv'f Scan dB* ~ Thicknes s: 1.5 Ola.: N/A Gain Signal Swe!!p Se~lal No.: CW0 CCW0 ScRn dB: 41 .3 93-5728 Sound Path dB Reflector Alllplitude % Oivisior1 Cal Blk. T ef"OP : 67 Temp. fool: 531993 Type* Exam Surface: 00 SS Rompas 22.0 2" R 6 80 1.488 Comp. Temp.: 88 Temp. Tool: 531993 Surface Condition : As Found n 0 lltrasonic lndcallon Reoort I Results: NRI ~ Rl fJ Info 0 Comments: E3768B Cal Due 10/26-201 4 531993 Cal Due 10/26/201 4 Percent Of Coverage Obtained > 90%: 88% Re..;ewed Previous Data* Yes Examiner Level Ill' Signature Maclean, Duncan J. \::5 _) f'r\;~ '-\.,_ Dale ! Re111ewer 3/4 /2014 M at1 Welch, Ull P'k£wA~~ / /_ Date Examiner Level N/A
~1/17'-
SJQnature Date 1 Site Re-<iew N/A Sgnature Date NIA OtheJ" NIA Le'oiel N /A Signature I Date AN II Revtew Dale UT Calib<alion/El(31Tlin<Jioo
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THICKNE' AND CONTOUR Position 0 90 180 270 1 ,, 31 i.1.3 l*l.5' 1* 2./ I
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- Weld edge Reviewer:
Print name: _,Af/J.1/tJEUII WELD LENGTH : 7£. *7~""* DIAMETER: 1 't 1" oo qoo l'600'
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Ultrasoni c Examination Site/Unit: _.::-.:_ BFN* .:...;___ _ _ _3_ __ Procedure: N-UT-a7/EPRI-DMW-PA-1 Outage No.: U3RF16 Summary No.: 05099-ISI-BFNJ Procedure Rev.: 3/4 Report No.: UT-14-031 Workscope: LSI ~'f. Work Order No.. 114699848 Page: 1 of ___L_3..3 Code: Section XI 2001 Ed/2003 Add Cat./ltem* R-AIR1.16C Location: REACTOR BUILDING-DR YWELL Draw1ng No.: 3-ISI-0330-C-01 Description VLV - EL System ID 074- Residual Heat Removal System Comoonent iD TRHR-3-191 S12e/Length* Llmital1ons.
---20---I Thickness/Di ameter. 1.031 / 20 Comments*
This report contains the Manuat Phased Array examination data. Results: Accept RejeCI Info Percent Of Co11erage Obtained > 90%. Re111ewed Previous Data: Ex.aminer Level Date QJL~~ Date N/A ~ *;tJM-0 3/1/1'1 Exammer Date Signature Date N/A Other Level N/A Signature Date IANII Rev1ew N/A J\11..~ 1-t.;r
TENNESSEE VALLEY EXAM INATION
SUMMARY
AUTHORITY AND REPORT NUMBER: RESOLUTION DATA SHEET UT--!LJ -£Y3! PROJ F.C'f RFI\. UNTT: 3 CYCLE: 16 COMPONENT TD: TRB R-3-19 1 EXAM INATION METHOD SYSTEM; RHR- lSI OWG. NO. 3-lSI-0330-C-01 MT 0 I PTO UT [g) I VT D CODE CLASS: I CATEGORY: PROC£DURE REV* Ire: COFJG.: I EL TO VLV EXAMINER : £_fj AsH EXAM INER: EXAM INER: EXAM INER:
#~~-~
LE\'EL: 1I LEVEL: LEVEL: LEVEL: r:,~.-~ ~;;**. =~~ . ~ . TRHR-3-191 is a dissimilar metal weld consisting of a cast stainless
* -~'?*- -;::!~
~reel valve to a carbon steel elbow.
This examination claims dual credtt:
-Category R-A, item R I .16 C
-Category C/NUREG-0313 for IGSCC The examination utilized Pha~ed Array Ultrasonics tor Dissimilar Metal Weld in accordance with EPRJ Generic Procedure EPRI-DM W-PA- 1. rev.4 as implemented through TVAIJSO Procedure;: N-UT-87. re' .3 Covergage limitations were associated with surface condittons and the ~.:ast stainless steel valve.
Scans \'<ere limited to the downstream side of the JOint Code covergage is reportc:d in two applications. ASME Section XI. 200 I Edition through the 2003 Addenda and Procedure Qualified coverage. Result<; are below: ASME Section XI: 54.3% Procedure coverage: 43.3% There were no rewrdable indications.
'\
RESOLUTIO N BY: #ft-rr IUELLJ/ REVJEWED BY: /lf,.q-r-rwE2cl-!
~4/dd-.. ANII~~,rift~
~IV~ J / o[t'1_
LEVELed££ - - - DATE: 3/;?lf LEVF.L: ZJ.r' DATE: .ill_4 __ DATE : r G. '2- OF??
COVERAGE PLOT
, / Compon ent 10 : TRHR-3-191 Reviewer: 7ft::t&z'/v}?~ I A~ ~ _ ur- !t/-o5; Print name: #-4.rr ;~-t=l.LI.,)
Date: 3)7)L! _ ___. Date: Valve Flow* Elbow 0.400 D A = (Machined) boss to interface B = U/S Weld toe to interface C = Weld crown width D =Buttering width oo 1" 1" 1~/3?
THICKNESS AND CO NTO UR 2.5" 2.5" Position 0 90 180 270 1 N/A N/A N/A N/A
- 2. N/A N/A N/A N/A 3 1.160 1.090 1.167 1.100 4.. 1.135 1.123 1.000 1.040 VALVE ELBOW SIDE 5 1.195 1.196 1.239 1. 130 l.//-!l-c;5;
- w eld Edge FLOW ....___,/
Examiner: e:::- Reviewer: Print nam e~D FISH Date: Print name: COMPONENT 10: TRHR-3-191 CROWN WIDTH : 1.2" WELD LENGTH : 62.8" CROWN HEIGHT: FLUSH DIAMETER: 20" ct. Flow VALVE ELBOW
---+-1 ------ oo goo 1"
1 270° 1"
'7/3'.?
COVERAGE PLOT
SUMMARY
Compon ent ID :TRHR-3-191 7 -:-T-7 L/T-Jt./--031 Examiner: £...(...__ Reviewer: ?-'~Lfv,--?th....r/tr-- Print name: ED FISH Print name: MAn WELCH Priht name:...n ... ..,,.(~ Date: 2 1 (£() ;).o 1c.r Date: -~ f , 't./ Date: 3//1/ly __ _ _, ASME Section XI coverage achieved - 54.3% Lower 1/3 of weld thickness , 1/2" beyond weld toe on each side of joint. Refracted Longitudinal wave mode, axial scan directiOn- 73.3% Refracted Longitudinal wave mode, circumferential scan direction- 44.3% Combined Refracted Longitudinal Wave mode coverage-50 8% Shear Wave mode coverage. axial scan direction-47 8% Shear Wave mode coverage , circumferential scan direction-47 8% Combined Shear Wave mode coverage- 47.8% Procedur e required examinat ion volume achieved -43.3% Full volume thickness, 112" beyond weld toe on each side of joint Refracted Longitudinal wave mode, axial scan direction- 14 7% Refracted Longitudi nal wave mode, circumferential scan direction- 20 9% Combined Refracted Longitudinal Wave mode coverage-17.8% Shear Wave mode coverage , axial scan direction-36.7% Shear Wave mode coverage. circumferential scan direction-49.9% Combined Shear Wave mode coverage- 43.3% Coverage Key : REV= Required examinat1on Volume OEV= Obtained Examinat ion volume RIL= Refracted Longitudinal Axial Scan direction= upstream and downstream Circ Scan direction= Clock wise and Counter clock wise
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\*1 Component 10: TRHR 191 UT-I l/-t:J 3; Examiner:
Print name: Ed Fish Reviewer: Print na~7~~ ~- , t,. /,.v.. -7 '
- I Date: 21 FEB 2014 Date: - //'/~ - _ _ _ _
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COVER AGE PLOT Examiner: Print name: Ed Fish I Date: 21 FEB 2014 ~uduu,., ~Ev' :. l ~ /.f3ni ; Valve Flow.. Elbow
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Date: 21 FEB 2014 Date: ~r/¥ _ Date: ::r/'rt-*;}~ _ _ R/t- XG'V:: (p~CJt.IJIJ ~ ~rA .I ~ ~at*t c-It u CMJ
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COVERA GE PLOT rint name: --s:4;-,.,., 44-1 Ne~ur Date: _!Lu~ *
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- =-;tJ-o 3; Exa miner:
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Ul] Slle!Unlt: Summary No.: BFN 01819*1SI*BFN3 3 UT Calib ratio n/L..amination Procedu re: Procedure Rev ; N*UT-64/PDI*UT -2 Outage No.: U3RF16 13/F Report No.: UT-14-03 WOfkscope: 6 lSI WC(k Order No.: 114699848 Page: 1 of J ~~;: Code:
¥It(-
Sec XI 2001 Ed/2003 Add CaiJitem: B.J/89.11 Location: REACTOR BUILDING*DRYWELL Drawing No.: 3. 3-ISI-0332-C.01
Description:
TEE - VLV System ID: 069 - Reactor Water Cleanup System Componoot 10* RWCU-3..001..070 slzell engItt: limitations: Single sided exam, see coverag e plot page for details
- --6 /- --0843 Start Time:
Thickness/Diameter; 0.432 / 6
- ~
Finish Time: 08 50 Instrument Settings Search Unit Serial No.: Cal. Timo Axial Orientat ed Search Unit E37688 Serial No.: SH0104 Date Che cks Manufacturer: KRAUT KRAME R Ci!libralion Signal Manufac turer: GE Initial Cal. 0746 3/5/2014 Swe~ Sound Path Model: USN SO Reflector Arnplituu e% Division Linearity: L-14-002 Size: 0.375" Mooa: CompG Inter. Cal. 0843 3/512014 Delay: 5.8291 Range: 1" Notch 80 9 1.343 1.5 Freq.: 1.5 MHz Center Freq.: Inter. Cal. N/A Mtl CaiNe!: 0.1219 Enef9Y: High l11ter. Cal Damping: 1000 Ohms Reject: 0 EU~mAngle:
--- 45 Squint Angle:
---NIA Final Cal. 0850 Measured Angle: 3/512014 PRF Mode: 45 Mode: Shear Auto High SU Freq : 1.5 MHz Exit Point: .4 Co uplant Dlsp. Start; IP of Elements: 1 Rectify; Full Wave Conflg.: Singl e N; ; - Cat Batch: 13C002 Circumf erential Orientat ed Search Unit Ins! Freq.: 2.0 MHZ Focus:
Type: Uttragel It Shape: Round Contour: Flat C..,ibration Signal Sweep Mfg.: Sonotec h Renee tor Amplilud a% DivisiOn Soond Path Ax. Gain (dB): Wedge Sty1e* Non-Inte gral 26.2 Circ. Gain (dB): 26.2 1" Notch Exam Batch: 13C002 80 9 1.343
-- =
1 .15 Search Unit Cable Screen Div.
- - ln. ol Sound Path Type: Type: Ultrage lll
-6 RG-174 Length: No. Conn
- 0 Calibrat ion Block - Mfg.: Sonotec h Scan Coverag e Cal Blodl No: WB-84 Thickness: 1" Dia.: NIA Upstream l!l 0o-Nnst ream0 Sr-.an dB: 46.2 Referen ce Block Reference/Simu lator Block Ca Btk. Temp.: CW 0 CCW 0 Scan dB: 46.2 Sefial No.: 790398 Gain Signal Sweep
-- 68 T 00'4l* Too: 558272 Exam Surface: 00 Type: SS Rompas dB Reftecfor Amplitude % DiVIsion Sound Path Con1p. Temp.: 76 Ternp. Tool: 558272 23.0 1" R 85 6.5 .999
~ * *rlt\l"'.o l""l"\l"'liilii'V1
- As found (s) n li(l Jltrasonic Indication Reoo-11 Results:
0 :=J fFP NRI ~ Rl Info Commen ts: 558272 Cnl Due 1/25/2015 Percent Of Coverage Obtained > 90%* 48.8% Reviewed Previous Data* Yes
~37t38e 1012612014 Examiner llml m* Signature Date Reviewer Maclean , Duncan J .
Elealnlner Level
~ 3/4/2014 Matt Welch, Lilt ~~~~~ ~
~* 6;1/~
- Date N/A Signature Date SkeReview N/A Signahlfe Date NIA Other level N/A Signature
' -)
Date ANI! Revew Slgnafure
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COVERA GE PLOT Component 10: R\N c. U - s - o01 - o 70 J-Jr-,;;; -~l3f:: Examiner: l~ 'i:Ac.___ _ Reviewer: / 777lc /?t' /7~--.::. ANII : ~ w 'V Print name: -~~-<'-c.t .....o -- Print name:/ ' 'li/Ti t ;_?~'-' Print '
'-l,lr--cf I Date: ~ ~ - 1 ' -\ Date: 3-1 ~.. 'it- Date :
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- Print name : ""l::)-:l ""' ""c t::CA.:--.1 -;-c, **4Date: I Print name:
a
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COMPON ENT ID: R we L{ - s- VO' 1 -O?o 1 . . .. .......... . . .,.,, , ......... ,'"' . 1 CROWN WIDTH : ,, cJ" WELD LENGTH: zl ;;_ 5' " CROWN HEIGHT: _ F/ us/, DIAME.::._T.::._E.::._R_:_ __t,_ c,_;__s-_'_ _ _ _ _ _ _ _ ____. 0(1
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[i!i]* Sate/Unit. Summary No.: WorkscqJe. BFN 06000-ISI-BFNJ PSI 3 UT Calibratio n.m inat ion Procedure: Procedure Rev.: Work Order No.: N*UT-76/PDI-UT*1 9!E 113331815 Outage No.. Report No.: Page: 1
*U3RF16 UT -14.001 of _{_7 ~t Code: Sec XI 2001 Ed/2003 Add Cal.lltem* C*F-2/C5.51 Locatia1: REACTOR BUILDING Drawlng No.:
J..CHM-2407-C-02
Description:
P . FLG System 10 : 073
- High Pressure Coolant lnj~tion System Compoo entiD: HPCI-3-019..018 Size/Length:
Limitations:
~-----------------------
No exam on the flange side due to configur ation --------------------- -Start-Time: 10" Thickness/Diameter: .59411 0" 08:35 Fanish Time: 09:35 Instrume nt Set1ings Search Unit Serial No.: Cal. Time Axial Orientate d Search Unit E37690 Serial No.: SE1640 Date Checks Manufacturer. KRAUT KRAMER Calibration Signal Sweep Manufacturer: KRAUT KRAMER Initial Cat 08:30 21412014 Renector Amplitud e% soond Path Model: USN 60 Linearity: L-14-001 Division Size: .5 Mcxlel: CompG Inter. Cal. Delay: 8.8697 1.0" NOTCH 80 7.2 Range: 2.000 Freq.: Inter. Cal. 1.44 2.25 MHz Center Freq. NJA M'll CaiNe!. 0. 1276 Energy: High Inter. Cal. Exam Angle* 45 Squint Angle; NJA Damping. 1000 Ohms Reject. 0 Final Cal. 09:43 2/412 014 PRF Mode: Auto High SUFreq.: 2.25MHz Measured Angle: E/Ut Pant: .5
-- 45 Mcxle: Shear
#of Elements : 1 Couplan t Disp. S tart: IP lnst. Freq,; 2.25 MHz Reclify: Full Wave Config.: Single Focus: Nl-,;:-- Cat, Batch: 12H130 Circumfe rential Orientate d Search Unit Type: Ultragel ll Calibration Shape: Round Contour: NIA Signal Sweep Mfg.: Sonotech ReRector Amplitude% Division Soond Palh Wedge Style; Non-Inte gral Ax. Gaan {dB): 24.6 Care. Gain (dB): N/A 1,0 Notch 80 7.2 1.44 Search Unit ~Batch: 12H130 1 .2 C;~ble Screen Div. "'
- - in. of Sound Path Type: RG-174 Type: Ultragel ll Calibrati on Bl ock Length:
-6 No Conn
- 0
- Mfg.: Sonotec h CaL Block No.: Scan Coverag e S0-115 Thickness:
Upstream~ DownstreamO Scan dB: 48 Referenc e Block Referenc eiSim ulator Block 1 .003 Oia.: FLAT 1-lJ Gain Signa Cal. Blk. Temp.: 51.8 cw~ CCW Scan dB: 48 SE!fiaNo.: 92-7615 Sweep Temp. Tool: E39055 dB Reflector AmPlitude% Division Sound Path EQm Surface: 00 Type: CS Rompas Comp. Temp.: 51 .8 Temp, Tool: E39055 24.6 FSDH 20 5.2 1.08
.C::11rf""" r.nnrtllinn* Ground
~ Jltrasonic lndicaticn Report.)
Results* NRI 0 Rl 0 Info 0 Commen ts; E37690 DUE 811412014 E39055 DUE 6/2412014 Percent Of Coverage Obtained > 90%: No Reviewed Data: I Pre~ous None Examiner Level IW Date
~?t/.dU_
ReiiiE!wer Signature K LEINJAN. DAIIID R 2/4/2014 Matt Welch, Llll Examiner Level NIA D<ie I S~e Review Signature N/A Date Other Level N/A Signature Date N/A Date UT Calibration/E~CWT~ination
!suMMARY NO: 06001-ISI-BFN3 IsiTE: BROWNS FERRY Unit 11 3 !DESCRIPTION IPIPE TO FLANGE IIDENTIFICATION: HPCI-3-019-01 8 SYSTEM 10: HIGH PRESSURE COOLANT INJECTION SYSTEM Prepared By: Reviewer By: MATI WELCH Signature: Signature: 4"a.u---z;J~ Date: Date: Items II Axial Required Exam volume 1 34
- 1.670. ((.214+.230)/2) =
12.6052 Clo ckwise and CounterClockw ise Required exam volume 2 34 " 1.670" ((.214+.230)/2) = 12.6052 Axial Obstructed Volume Exam (Coverage was achieved by scanning across the weld) 3 0= 0.0000 Clockwise and Counterclockw ise Obstructed Volume Exam 4 34" .434.((.214+.2 30)/2)= 3.2758 Axial Obtained Exam Volume 5 Item 1 - Item 3 = 12.6052 Clockwise and Counter Clockwise Obtained Volume Exam 6 Item 2 - Item 4 = 9.3293 Axial Ellam Volume Percentage 7 (Item 5/(ltem 1))" 100 =% 100.00% Clockwise and CounterClockw ise Exam Volume Percentage e 8 (Item 6/(ltem 2))"100 =% 74.01% Full Exam Volume Percentage combining in th e Axial, Clockwise, and CounterClockw ise Di rcetions 9 (Item 7 + Item 8)/2 =% 87.01%
e e e COVERAGE PLOT Component ID : HPCI-3-019-018-CORO _L/------= -LJ_ Ul-i '/-c() I Examiner: d,,R:~ _ Reviewer: ?:u22?{7/f.:/2b£ 1 ANII ~'3Zn.;;J, ~* Print name: oii7ta'kleinjan Print name: )A/ITT' 'El.Of Print flam8CSC~~~t-t (-=-;,;., ( Date: 04 FEB 2014 Date: z 'I '/ Date: d--c/1..~:$~/'-~..'1_ _ _ Pipe Flow .. Flange Axial Scan 45' Transverse Scan l_ I "" I / ,;;,;/;; 0.214 r------1.670 I 1"
~ Area of obstruction 1"
f? 11~
THICKNESS AND CONTOUR Position 0 90 '180 270 82.5"
- 2.5" 7-l-
1 NR NR .630 NR t.fr-J -co)
- 2. NR NR ,646 NR NR NR
;i 4*
- NR NR
.671
.676 NR NR FLANGE _ _SIDE NR r--
NR PIPE 5 ~ _NR - - -
- weld Edge
~
e := FLOW Weld Centerline Examiner: J)-?~ _ _ Reviewer: -~ #;~-.---,A- N-ir;;Z -* --/-,~VI-
' ~---,:Je,;_
Print name: DAVI6kiEINJAN Date:t"J"~ Print name: #/?/1' ELL!-/ Date: PriAt name:..&J~;w.,{ Date: COMPONENT ID: HPCI-019-018- C RO I ~/A rs ft. CROWN WIDTH: 1.15" WELD LENGTH : 34.0" CROWN HEIGHT: FLUSH DIAMETER: 10" Valve Flow* Pipe ct ('(') 1.{) 1'- 0 ('(') (I') N (0
-.;t ,.._
T"" (0 180° (0 (0 (0 co (0 1" p~?/5
~
- Site/Unit:
Summary No.: Works cope: BFN 06001*ISI*BFN3 PSI 3 UT Calibration/.mination Procedure: Procedure Rev.: Work Order No.: N*UT*761PDI*UT*1 9/E 113331815 Outage No.: Report No.: Page: 2
*U3RF16 UT*14*002
--------. of .t 7 t;;;1(
Code: Cat./ltem: C*F*2/C5.51 Location: REACTOR BUILDING Drawing No.: 3*CHM*2407*C*02
Description:
VLV* PIPE System 10: 073* High Pressure Coolant Injection System Component 10: Size/Length: 10" Thickness/Diameter: .594/10" HPCI*3-o19-o19 NO EXAM ON THE VALVE SIDE DUE TO CONFIGURATION
-Start-Time:
- - - -08:35 Finish Time:
Limitations: 09:35 Instrument Settings Search Unit Cal. Time Date Axial Orientated Search Unit Serial No.: E37690 Serial No.: SE1640 Checks Calibration Signal Sweep Manufacturer: KRAUTKRAMER Initial Cal. 0824 21412014 Sound Path Manufacturer: KRAUTKRAMER Reflector Amplitude % Division Model: USN 60 Linearity: L*14-o01 Size: .5 Model: CompG Inter. Cal. 1.0" NOTCH 80 7.4 1.854 Delay: 8.6731 Range: 2.5 Inter. Cal. Freq.: 2.25 MHz Center Freq.: N/A Inter. Cal. M't1CaINel: 0.1275 Energy: High Exam Angle: 61 Squint Angle: N1A Final Cal. 0950 2/4/2014 Damping: PRF Mode: 1000 Ohms Auto High Reject: SU Freq.: 0 2.25 MHz Measured Angle: Exit Point: .5
-- # of Elements:
61 Mode: Shear 1 Couplant Disp. Start: IP Rectify: Full Wave - - Cal. Batch: 12H130 Circumferential Orientated Search Unit Config.: SINGLE Focus: N/A Ins!. Freq.: 2.25 MHz Type: Ultragelll Calibration Signal Sweep Shape: Round Contour: N/A Reflector Amplitude % Division Sound Path Mfg.: Sonotech Wedge Style: Non*lntegral N/A Ax. Gain (dB): 38.0 Circ. Gain (dB): N/A Exam Batch: 12H130 Search Unit Cable Type: Ultragelll --1 Screen Div. = .25 in. of Sound Path Calibration Block Type: RG*174 Length:
-6 No. Conn.: 0
- Mfg.: Sonotech Scan Coverage Cal. Block No.: SQ*115 Upstream 0 Downstream ~ Scan dB: 59.0 Reference Block Reference/Simulator Block Thickness: 1.003 Dia.: FLAT -- Serial No.: 92*7615 Gain Signal Sweep Sound Path CCWO Scan dB:
CWO
-- dB Reflector Amplitude % Division Cal. Blk. Temp.:
51.8 Temp. Tool: E39055 Exam Surface: 00 Type: CS Rompas 38.0 FSDH 60 5.8 1.4 Compo Temp.: 51.8 Temp. Tool: E39055 Surface Condition: Ground Recordable Indication(s): Yes 0 No~ (If Yes, Ref. Attached Ultrasonic Indication Report.) Results: NRI ~ RIO Info Comments: E37690 DUE 8/14/2014 E39055 DUE 6/2412014 Percent Of Coverage Obtained> 90%: N Reviewed Previous Data: None Examiner Level ure Date Reviewer Date III' fW~ture KLEINJAN, DAVID R 214/2014 Matt Welch, LIII 9f~~~ Examiner Level N/A Date Site Review Signature Date N/A N1A Other Level N/A Signature Datel ANII rview ~ture Date N/A ~~~ ~J;;.c .u--::k. JLJ .;</oM I~Cf UT Calibration/Examination
ISUMMARY
NO: 06001-ISI-BFN3 ISITE: BROWNS FERRY I Unitlt3 IDESCRIPTION IVALVE TO PIPE IIDENTIFICATION: HPCI-3-019-019 SYSTEM ID: Prepared By: Reviewer By: Signature: Date: Date: Items It Axial Required Exam volume 1 34*1.648*<<.297+.208)/2)= 14.1481 Clockwise and CounterClockwise Required exam volume 2 34*1.648*<<.297+.208)/2)= 14.1481 Axial Obstructed Volume Exam (Coverage was achieved by scanning across the weld) 3 0= 0.0000 Clockwise and Counterclockwise Obstructed Volume Exam 4 34* .729*<<(.297+.208)/2)= 6.2585 Axial Obtained Exam Volume 5 Item 1- Item 3 = 14.1481 Clockwise and Counter Clockwise Obtained Volume Exam 6 Item 2 - Item 4 = 7.8896 Axial Exam Volume Percentage 7 (Item 5/(ltem 1>>*100 =% 100.00% Clockwise and CounterClockwise Exam Volume Percentage 8 (Item 5/(ltem 2>>*100 =% 55.76% Full Exam Volume Percentage combining in the Axial, Clockwise, and CounterClockwise Dircetions 9 (Item 7 + Item 8)/2 =% 77.88%
COVERAGE PLOT
- Component 10: HPCI-3-019-019-CORO UT-I if-(}(jZ-Examiner: .. ~., Reviewer: ANII:
Print name: Davfd Kleinjan Print name: ,MA-ffI1IEld/ Prin Date: 04 FEB 2014 Date: Z~?ft¥- Date: Flow .. Valve Pipe Axial Scanning 60' 45' D Area of obstruction Transverse Scanning 1" ~ Area of obstruction 111 fJtj Lf1:3
~
Position 1 THICKNESS AND CONTOUR NR 0 90 NR 180 270 NR NR 2.5"
- 2.5" Jif-eoz, 2* NR NR .799 NR 3 NR NR .748 NR 4* NR NR .627 NR VALVE PIPE SIDE 5 NR NR .630 NR
- Weld Edge FLOW~ Weld Centerline Examiner: d.//."j"- .,
*.n
~.
Zltfller I Reviewer: Y~A/"'/' /..f 2;/,/9'//~ I AN II: .....~~/:..u; .Y Print name: DAVIt>(tLEINJAN Date: I Print name: #hrrPvf:u:::.;/- Date: I Print name: G, ,J "J---IAJ,;;r Date:2/.:tJ1 ~ COMPONENT ID: HPCI-019-019-CORO CROWN WIDTH: 1.1511 WELD LENGTH: 34.0 11 CROWN HEIGHT: FLUSH DIAMETER: 10" Valve Flow.. Pipe ct
<.0
~
co 0') co ,..... co o('f) 0')
,..... C\J 180 0 ~ ~
<.0 <.0 <.0 1 11 1"
j>J~/3
\l
[ii1 Slle'Unit: Sum1Tl8ry No.: BFN I ()538S.ISI-BFN 3 UT Cali"'......:....~ Procedure: nation N-UT-76 Outage No.: U3RF15 ~ Procedure Rev.: 7 W o~: Report No.: PSI UT-12-046 WOtk Order No.: 113331595 Code: Sec XI 2001 Ed/2003 Add Page: 1 of 2 CatJitem: &oJ/99.11 Drawil"o No.: 3-ISI-0332.C.02 Locallon: REA CTO R BUILCING-DR YWE U
Description:
PIPE - REO TEE System ID: 069 - Reac tor W.te r Clea nup Syat em Component to: RWCU.3-007-003 Umitation s: YES- PAR nAL SINGLE ~DE ACC Size/Length: 4 / 14.25 ESS ON T EE- SEE COV ERA GE Thlekness'Diam eter: 0.337 / 4 PLOT Start Time: 0930 Finish Time: Instr ume nt Seltfngs 0945 Searc.h Unit Serial No.: E33669 Cal. Serial No.: OOF62P Time Date AJdal Orfea~tated Search Unit Manufacturer: Che cq KRAUTKRAMER Manu facturer: KBA Initial Cal. 0910 Calbrat!on Signal Sweep Model: USN 60 Linearity: 4129f2012 Reflector Sound Path L-1HJ07 Size: Amplitude o/o Division Delay: 0.25 Model: Com pG Inter. Cal. 0930 412912012 3.5247 Range: 0.5" NOTCH 1.783 Freq.: 5,0M Hz Inter. Cal. NA 80 4.0 .705 M'tlCaVVel: Center Freq.: NA
.1275 Energy: High NA E!Cam Angle: Inter. Cal. NA Damping: 1000 0hms 45 SqUint Angle: NA NA RejeCt: 0 Final Cal. 1021 4129f201 2 Measured Angl e: 45 Mode:
PRF Mode: Auto High SHEAR NA SUFreq.: S.OMHz Coup lent Exit Point: .35" tt of Banents: NA Disp. Start: IP 1 RecUiy: FuD Wav e - Cal. Batch : Conf ig.: Sing le Focus: 11425 Circu mfer entia l Orte ntate d Sear cfl lnst. Freq.: S.ON Hz NA Unit I Shape: Type: Ultra gelll Rou nd Contour: FLA T Calibration Signal Mfg.: Sweep Wedge Style: Sonotec:ll Reflector Amplitude% Division Sound Path NON-INTEGRAL Ax. Gain (dB): 28.6 Clrc. Gain (dB): O.S" NOTCH 28.6 Seer eh Unit Cabl e Exam Batch: 11425 80 4 .705
- 1 SaeenDrv. =
.178 ln. of Calib ration Bloc k Sou nd Path Type: RG*1 74 Length: ..!.. No. Conn.: 0 Type:
Mt
- g ..
Ultra gef II Sono tech NA NA Scan Cove rage Cal. Block No.: NA SCH 19 Upstream !Ill Downstream !ilj Scan Reference Bloc k Thickness: dB: ~ ~rencfiiSimulator Bloctc 0.5" Dia.: FLAT cw~ ccw~ Scan dB: ~ Seria No.: 5100 Gain Signal Sweep Cal. Blk. Temp.: ~ Temp. Tool: 558275 Exam Surface: dB Refleclor I_AfnPjtude 'Yo DMs iat Sound Path Comp. Temp.: ~ Temp. Tool: 00 Type: Rom pu 558275 36.8 FSDH 50 5.6 Surface Condition: Flutih 1.D03 NA 0 ~ Aepolt.) NA Results: NRI ~ Rl 0 Info 0 Comments: E33669 DUE DATE8115112
, 558275 DUE DATE 12*10.12 Pet"cent Of C011e1age Obtained > 90%
- Mo Reviewed Previous Data:
Non e ExarMler l.eYel I UI-PDI Welch,Nat1hew C. ~te R~Me.o.er ~lgnature Date Examiner l.eYel >.lith< Z.IP,E-UJl NIA NIA Signature Dala l Site Review Signature qf1-IJ; . Other Date Le.e a NIA Signature WA Dale 0 Date UT calibnl~llon h 5/J/12.... ' f\S'*, f', ~~) ~
PLOT Component 10: RW~U-(. . 001 -00 3 Examiner: ~z..l Reviewer:.ss: u-#~;rz... Print name: MA1 T \tJ£1£1-{
~---- AN II:
Print name : Print name : dJf~ ~;,.A1,!-';, Date: Date : (/',h,;) //-r.- Date: .>/111.,_ l¥QuriZEJ2 ~MM ioL.JJ~L 3*~11N ~ ~ rIJ~O t"><AM \}ouJMf. '; ZclZ, IN ~ /5% gs% [{(~ 11-t~z.t}.;.ri-);1(. 1~~))( 1'/,15 # oB~~TEt> ~altlfA4E-== IJ7% (1¥*'l-S* "f*7S) ~ /Gf,zS ::-,1:11
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I*"JP o* 11#" MM-L- 5:;4N oesm:~nC)N ~ '31 t I% ~~ ~ O~SfRIJGTI ~ ;;: 5z, &, ~ ((.l/Sx,z)+~ -~(,2 1t,t)f1.)X.35] :, r-z- ;,,.";-((,~~*)>< t'f.-z.s) =z.~)(.~1 ~J,1J+ ~b7 3,"7- ((t~ZJ<t'f~z s)x. "'):::~I'I -f-.3.1.7; ~ 3/f (j) ;./nD f<Wa J- lr00 1-0/ / 51fow1J {:'()tt ~EFcKEI\JCE" w p~ 3~) 0 Q{)
THIC AND CON TOU R Position 0 90 180 270 ~ 2.5" ~- 2.5" 1 / 2"' I</ 3 /""n.. 4* v \jtd_stDE 'Pl~SIOE 5 /
*Wel d edge FLo wL: :) Weld. Centerline Exam iner:
WELD LENGTH: 14-* Z5 DIAMETER: Lf, 53 ([) WaD RWC. u-t-o o7 -011 ~;laWN~ Re!
="Ell~
~ - t'--
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. __ _ _ _ _... 0 0'0
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THIC K AND CONTOUR lOIII 2.5" Position 0 90 180 2]9 2.5" 1 I /
/
2 .. JJ / 3 / A-4... / V'ltL SIDE
~~SIDE 5 /
- We ld edge FLOwq Weld Cente!'line Examiner: vG{ztii?~ Sj~fz--1 Reviewer:
Print name: Mtt rr \tJel.L;.~ _.._ Date: I Print name: .t":. ANII : /.3 - t!i-< V~~ COM PON ENT 10: ;<~:..r-tXJ7-co3 CRO WN WID TH: * (q '"-"f'J'n~ CRO WN HEIGHT : WELD LENGTH: /Lf,z ~
~1-u~>>- DIAMETER: L/.S 3 0 W5l..J:> f?W<;(./ 0 o7- <9// $~IvA/ HJK f?[; -
~ - ~ - -
l:CR BVc c:-
/ko6 VAr.>!S 4- :PlPE:
1.0 v~.~..ve ~ r-~ ZJ(J D cf_ - "'PfPE
.___ _ _ _-l /;(} Ia: 0
() 0 Q (.,-.) Q ba
'P, ~ 4-5 0
[im Sit&'Unit Summaty No.: ---------------------- BFN I 03534000-ISI-BFN 3 Ut VGI IUI Procedure: nation N-UT-76 Outage No.: 03RF15
~
Procecilre Rev.: 7 Workscope: ReportNo.: UT-12 -o47 PSI Work Order No.: 113331595 Code: Section XI 2001 Ed'2003 Add Page: 1 or 2 Cat/Item: fhVB9.11 DrcwAng No.: Location: REACTOR BUlLDING*DRVWELL 3-ISI-0332*C ~
Description:
VLV
- REO TEE System 10: 069 - RMCt or Wltef Cleanup Syste m Component 10: RWCU.3-G07411 Umitalicns: Sizdle nglh: 4114.25 Thlckness'Oiamelef:
YE~ CIRC SCAN ON VALVE SIDE-SEE COVERAGE 0.337 / 4 PLOT Stan Time: 0930 Flfllsh Time: 0946 Instru ment Settin gs - - - Search Unit Serial No.: E33669 Serial No.: CaL Time Date Axial Orientated Search Unit OOF62P Check$ Manufacturer: KRAUTKRAMEA Manufacturer: Initial Cal. calibfatlon Signal Sweep KBA 0710 4mt'2012 Sound Path Model: USN6 0 uneartty: Aell ector Ampi tude% Oivlslcn L-12~ Size: Inter. Cal. 0930 0.25" Model: Comp G 412912012 Delay: 3..5247 Range: 1.783 Freq.: S.OMHz Inter. Cal. NA O.S" NOTCH ao 4.0 .1f15" Center Freq.: NA NA M'tl CaVVel: .1275 Energy: Inter. Cal. High Exam Angle: 45 Squint Angle: NA NA Damping: 10000 hms NA Reject 0 Final Cal. 1021 412M012 Measured Angle: ~ Mode: SHEAR NA PRFM ode: .Auto High SU Freq.: S.OMH z ElCitPolnt: Couptant NA
.35 1 of Bernents: 1 Dlsp. Start: IP RecUiy: Full Wave - Cal. Batch: 11425 Conlig .: SIJ\91e Focus: Clrcu mf.,.. ,tlll Orien tated Search Unit lnst Freq.: S.OMHz NA Type: Utngelll Shape: Round CcniOur. FLAT ca!ibr tlllon Signal Sweep Mfg.: Sonot ech Reflector Amplitude% DMslon Sound Path 1 Wedge Style: N~I NTEG RAL Ax. Galft (dB): 28.6 Circ. Gan (dB): Exam Batch: 0.5" NOTCH 80 4.0 28.6 Search Unit Cable 11425 .705 NA Screen Oiv. =
1 .178 Type: ln. ol Sound Path Type: RG*174 Length: ..!:.. No. Conn.: o Mf . Ultreg el B NA Calibr ation Block - g.. Sonol ech Scan Coverage NA Cal. Block No.: SQ-11 9 Upstream 0 Thickness: 0.5 Dia.: FLAT cw~ Downstream !ill Scan dB:
-- 46 CCW 5lJ Scan dB: ~ Seslal No.:
Ref-nee llock Gain Refenlf'lceiSimulator Block Signal Cal. Blk. Temp.: .!!.:!. Temp. Tool: 568275 Exam Surface: Type: 5100 dB s~ Reflector Amplitude % Di'tisi<rl Sound Path 00 Roq)I IS Comp. Temp.: ~ Temp. Tool: 558275 36.8 FSDH 50 5.6 1.003 Surlace Condition: Rush NA 0 [,ll Report.) NA Results: NRI ~ AI 0 Info 0 Comments: E33669 DUE DATE8115f12, 55827 5 DUE DATE 12/10112. Percent Of Coverage Oblained > 90%* No Reviewed P~s Data: None
~ L.e.tel IIJ.PDI Welch, Matthew C.
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