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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)
	v • d • e

{{#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

Browns Ferry Nuclear Plant, Unit 3 Inservice Inspection Program Third Ten Year Interval Request for Relief 3-ISI-28 Tennessee Valley Authority Browns Ferry Nuclear Plant Unit 3 Request for Relief 3-ISI-28 CNL-17-013 E1 - 1 of 6 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 Tennessee Valley Authority Browns Ferry Nuclear Plant Unit 3 Request for Relief 3-ISI-28 CNL-17-013 E1 - 2 of 6 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.

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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 Tennessee Valley Authority Browns Ferry Nuclear Plant Unit 3 Request for Relief 3-ISI-28 CNL-17-013 E1 - 3 of 6 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) Tennessee Valley Authority Browns Ferry Nuclear Plant Unit 3 Request for Relief 3-ISI-28 CNL-17-013 E1 - 4 of 6 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 - 5 of 6 Tennessee Valley Authority - Browns Ferry Nuclear Plant Unit 3 Request for Relief 3-ISI-28 Table 1 Weld Number (Description) Nominal Size (NPS) Sketch (Report Number) Examination Coverage Percent (Nearest %) Unit/Cycle Inspection Performed Nozzle Material Weld Material Comments N1B-NV (Recirc Outlet) 28 SK-B3017 (VE-12-010) 25 U3C15 (Spring 2012) A508 CL2 E9016G This ultrasonic examination was performed in accordance with the criteria of 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 (Feedwater) 12 SK-B3018 (VE-12-011) 32 U3C15 (Spring 2012) A508 CL2 E9016G This ultrasonic examination was performed in accordance with the criteria of 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 (Feedwater) 12 SK-B3018 (VE-12-013) 32 U3C15 (Spring 2012) A508 CL2 E9016G This ultrasonic examination was performed in accordance with the criteria of 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 (Feedwater) 12 SK-B3018 (VE-12-015) 32 U3C15 (Spring 2012) A508 CL2 E9016G This ultrasonic examination was performed in accordance with the criteria of 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 (Feedwater) 12 SK-B3018 (VE-12-017) 32 U3C15 (Spring 2012) A508 CL2 E9016G This ultrasonic examination was performed in accordance with the criteria of 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 (Feedwater) 12 SK-B3018 (VE-12-019) 32 U3C15 (Spring 2012) A508 CL2 E9016G This ultrasonic examination was performed in accordance with the criteria of 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 - 6 of 6 Tennessee Valley Authority - Browns Ferry Nuclear Plant Unit 3 Request for Relief 3-ISI-28 Table 1 Weld Number (Description) Nominal Size (NPS) Sketch (Report Number) Examination Coverage Percent (Nearest %) Unit/Cycle Inspection Performed Nozzle Material Weld Material Comments N4F-NV (Feedwater) 12 SK-B3018 (VE-12-021) 32 U3C15 (Spring 2012) A508 CL2 E9016G This ultrasonic examination was performed in accordance with the criteria of 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 (Jet Pump Instrumentation) 4 SK-B3019 (UT-14-057) 77 U3C16 (Spring 2014) A508 CL2 E9016G This ultrasonic examination was performed in accordance with the criteria of 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 (CRD) 4 SK-B3020 (VE-12-029) 27 U3C15 (Spring 2012) A508 CL2 E9016G This ultrasonic examination was performed in accordance with the criteria of 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 (SLC) 2 SK-B3022 (VE-12-030) 74 U3C15 (Spring 2012) A508 CL2 E9016G This ultrasonic examination was performed in accordance with the criteria of 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 (SLC) 2 SK-B3022 (VE-12-031) 90 U3C15 (Spring 2012) A508 CL2 E308/E309 Nozzle to vessel weld (SLC Nozzle Inside Radius) was examined using a 65 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.

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 CNL-17-013 E2 - 1 of 7 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

Enclosure 2 TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant, Unit 3 Request for Relief 3-ISI-29 CNL-17-013 E2 - 2 of 7 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.

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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.

Enclosure 2 TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant, Unit 3 Request for Relief 3-ISI-29 CNL-17-013 E2 - 3 of 7 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)

Enclosure 2 TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant, Unit 3 Request for Relief 3-ISI-29 CNL-17-013 E2 - 4 of 7 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 - 5 of 7 Enclosure 2 Tennessee Valley Authority - Browns Ferry Nuclear Plant, Unit 3 Request for Relief 3-ISI-29 Table 1 Weld Number (System) IGSCC Category Nominal Pipe Size (NPS) ISI Drawing Number (Weld Report) Examination Coverage Percent (Nearest %) Unit / Cycle Inspection Performed Joint Configuration Weld Material Comments DRHR-3-12 (RHR System) D 24" 3-ISI-0330-C-1 (UT-12-031) 30 U3C15 A182 F304 Flued Head to A351 CF8M Cast Valve. ER308 Examination coverage limitations are due to the physical configuration of a wrought fluted head penetration to a cast valve configuration that restricts the ultrasonic examination on both sides of the weld. This configuration limited the scan surface to 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. DRHR-3-19 (RHR System) C 20" 3-ISI-0330-C-1 (UT-14-039) 59 U3C16 A403 WP304 Tee to A358 GR304 Pipe ER308 Examination coverage limitations are due to the physical configuration of a tee to 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 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. DSRHR-3-5A (RHR System) C 24" 3-ISI-0330-C-1 (UT-14-027) 76 U3C16 A358 GR304 Pipe to A403 WP304 Elbow. ER308 Examination coverage limitations are due to the physical configuration of this pipe to 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. 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 - 6 of 7 Enclosure 2 Tennessee Valley Authority - Browns Ferry Nuclear Plant, Unit 3 Request for Relief 3-ISI-29 Table 1 Weld Number (System) IGSCC Category Nominal Pipe Size (NPS) ISI Drawing Number (Weld Report) Examination Coverage Percent (Nearest %) Unit / Cycle Inspection Performed Joint Configuration Weld Material Comments TRHR-3-191 (RHR System) C 20" 3-ISI-0330-C-1 (UT-14-031) 54 U3C16 A351 CF8M Valve to A234 GR WPB Elbow ER308 Examination coverage limitations are due to the physical configuration of a Cast Stainless Steel Valve to a Carbon Steel Elbow configuration that restricts the ultrasonic examination on both sides of the weld. This configuration limited the scan 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. GR-3-63 (RECIRC System) E 28" 3-ISI-0328-C-2 (UT-12-024) 50 U3C15 A358 TP 304 stainless steel Pipe to A351 CF8 Cast steel Valve. ER308 Examination coverage limitations are due to the physical configuration of this pipe to cast valve configuration that restricts the ultrasonic examination to one 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 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. RWCU-3-001-070 (RWCU System) A 6" 3-ISI-0332-C-1 (UT-14-036) 49 U3C16 A403 WP304 stainless steel Sweep-o-let to A351 CF8M Cast Valve. ER308L Examination coverage limitations are due to the physical configuration of a wrought piping branch connection to a cast valve configuration that restricts the ultrasonic examination on both sides of the weld. This configuration limited the scan surface to 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 - 7 of 7 Enclosure 2 Tennessee Valley Authority - Browns Ferry Nuclear Plant, Unit 3 Request for Relief 3-ISI-29 Table 1 Weld Number (System) IGSCC Category Nominal Pipe Size (NPS) ISI Drawing Number (Weld Report) Examination Coverage Percent (Nearest %) Unit / Cycle Inspection Performed Joint Configuration Weld Material Comments HPCI-3-019-018 (HPCI System) N/A 10 3-CHM-2407-C-2 (UT-14-001) 87 U3C16 SA106 GR B Pipe to SA105 Flange ER7056 Pre-Service Exam. Examination coverage limitations are due to the physical 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 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. HPCI-3-019-019 (HPCI System) N/A 10 3-CHM-2407-C-2 (UT-14-002) 78 U3C16 SA 216 WCB Valve to SA106 GR B Pipe ER70S6 Pre-Service Exam. Examination coverage limitations are due to the physical 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 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. RWCU-3-007-003 (RWCU System) N/A 4 3-ISI-0332-C-2 (UT-12-046) 58 U3C15 A420 GR WPL1 Tee to ASTM A333 GR 1 Pipe ER70S6 Pre-Service Exam. N-UT-76. Examination coverage limitations are due to the physical configuration of this valve to pipe weld that limits circumferential scanning to one side at the tee. RT and PT was acceptable. Voluntary pre-service UT performed. There were no recordable indications. RWCU-3-007-011 (RWCU System) N/A 4 3-ISI-0332-C-2 (UT-12-047) 89 U3C15 SA105 Valve to ASTM A333 GR 1 Pipe ER70S6 Pre-Service Exam. N-UT-76. PT Performed. Examination coverage limitations are due to the physical configuration of this valve to pipe weld that limits circumferential scanning to one side at the valve. RT and PT was acceptable. Voluntary pre-service UT performed. There were no recordable indications.

CNL-17-013 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

0 FLANGE COURSE 5 w I I I I J NOZZLE GROUP I DISTANCE TO MATING SURFACE N3X 86.5" N12X 146" N11X - 228" N4X - 246.5" N5X - 259.5" N9 296.5" N16X - 379" N2X - 564" N1X - 583.5" z N8X 610" 360 270 r-C-5-FLG 330° N3D N3C /0' I I \\ I \\ / ,.........--......'\\. /0' I I \\ I \\ / V-5-C I C-4-5 285° D D 210 ° V-5-B N12B D y 180 r MATING SURFACE { VESSEL STABILIZERS 165 ° D D 90 90° N3B N3A /0' I I \\ I \\ / V-5-A D REFERENCE DRAWINGS (GE) SKETCHES - RPV EXAMINATION PLAN (GE) SK-B3001 SK-B3005 SK-B301 0 SK-B3003 SK-B3007 SK-B3004 SK-B3006 LEGEND 0 VESSEL NOZZLE FULL PENETRATION NOZZLE WELD ASME CC-7 (EQUIVALENT) w 0 I 360 745" I I I I 706" I N12A 45° 0 COURSE I V-4-A V-4-C V-4-B 4 I COURSE 3 COURSE 2 COURSE 1 I N5A N9 ~ NOTES: ~

1. REFER TO RPV MANUAL FOR MATERIAL SPECIFICATIONS AND THICKNESS OF MATERIAL.

2. NOZZLES N-11A, N-11B, N-12A, N-12B, N-16A,)

AND N-168 ARE CATEGORY B-E. __/ V-3-C V-3-B V-3-A IC-2-3 285° 165° 45° 391 5" I N16B N16A I ~ ~~- ~ ~:~ ~Av/7~ ~v~~ v~~~~TsLINE REGION ~:i ~f7~;f;,~~ I I 1 N1A N2K N2J N2H N2G N2F N1B N2E N2D N2C N2B N2A 1 l--. r(j" r(j" r(j" r(j" r(j" .---~ r(j" r(j" r(j" r(j" r(j" .--J 001 1--A_o"'---'" _ _jl'-------_j__IRo_L.JLI _ _[I_N:_/A_L__I_-'------'-IN/_A.JLI_N:_/A_jl __ _j__l---1 P I ') 1,_) 1,_) N88 1,_) 1,_) 1,_) ( 0 ') 1,_) 1,_) N8A 1,_) 1,_) 1,_) (q: / I ~ ~6v CHANGEREF 1 DA1E IDF1RicHKRioscNIRvwcl';cccl';ccol';cccl'sso 1-_.. ~ ', _ _../ '.._.J IC-BH-1 ~) ~ 1 125.5" S TENNESSEE VALLEY AUTHORITY TANGENT LINE/LOWER HEAD WELD BOTTOM HEAD* ~ ) ) ~~ / J VESSEL 0.00" II ~ f--=--JL_B-,---R--,---O----WN-S------,F=-cE=-R--,--R--,-----,---Y----N-U-C,---L-E=A----R-P-,---L-A---N-----=T----1 I UN! T 3 REACTOR PRESSURE VESSEL (RPV) SHELL COURSE WELD/NOZZLE LOCATIONS (OUTSIDE VIEW) DRAWN* PHB I DATE 7 7 7 89 1--C-HE_CK_E_D __ ED_C_--jl APPROVED* !ES I GLB SUBM! TTED

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~6 INST8UMENTATION NOZZLE TOP HEAD VENT NOZZLE 4 w (J) (J) UF~~';.;<;_~~Al' Z- ~ -~~ ~~~-------------------~~ 745*~*--:~==========================~========= REFUEL SUPPORT------ iF===========I SKIRT ~ ~=!:!'" N3 STEAM OUTLET-- ~\\ ~JOZZLE --r-- 1 ~: Nl2 !NSTRUMENTAT:::ON---- CJOZZLE --~ 573" ~24.5"} __12. lJ2.; tt- :: - 4 s LBDJ STABILIZER BRACKET----- ~ I ~11.1. II~STRUME~HAT!ON/ A:C C-3 4510.8 NOZZLE -~~~di ~ @

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CNL-17-013 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
]\\It\\ Ultrasonic Examination 000171 Site/Unit: BFN I 3 Procedure: N-UT-78 Outage No.: U3RF15 Summary No.: 00160-ISI-BFN3 Procedure Rev.: 5 Report No.: VE-12-010 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-DRYWELL Drawing No.: 3-ISI-0328-C-02
== Description:== SHL-NOZ System ID: 329 - Reactor Vessel Component ID: N1B-NV Size/Length: 28/ Thickness/Diameter: 6.6/28 Limitations: Llmitattions due to joint design and configuration 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 AREVA UT Coverage Data Sheet Radial Examination Coverage Radial Exam Coverage 100% t Total examination Area= 38.28 in2 1 51 Limitation= 24.68 in2 Area Covered = 13.60 in2 Total Examination Coverage= 35.53% LJe Report No.: 3-TVA-N18-NV Coverage Data Sheet No.: CDS-01 [)) Area o1 limitation Ill -60" RL co-ver-cge Page 8 of 10 0 0 0 ~ 00 ~ ( {'l 0 0
A AREVA UT Coverage Data Sheet Circumferential Examination Coverage Circ. Examination Coverage Outer 85%t exam coverage Total examination Area= 35.58 in2 Area of Limitation = 35.58 in2 Area Examined= 0.00 in2 Total Area Examined I Total Area= 0.00% Total Examination Coverage: 0.00 in2 / 35.58 in2 = 0. 00% Inner 15% Circ. Exam Coverage Total examination Area= 2.70 in2 Total Examination Coverage =2.70 in2 Total Examination Coverage =100% 0 Report No.: 3-TVA-N1B-NV Coverage Data Sheet No.: CDS-02 E] Anlo of lim"ilcrtlcm D-Page 9 of 10 0 0 "\\) => co ~ I ~ ch o-
A RPV Coverage Work Sheet Report Number: 3-TVA-N1B-NV AREVA Customer Information Component Information Utility: TVA Plant: BFN I Unit: 3 I Outage: 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) in2 38.28 Exam Area (ABC DE F G H I) in2 38.28 Inner 15% t area in2 2.70 Area Scanned in2 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 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-2007-266. Scanning was performed to the maximum extent possible. The total coverage achieved for exam ina lion 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. Examiner: Nathan Bauman 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/> _ Reviewe~ Victor Morto~ c::::::::::- Sign :
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Level: Ill Date: 04/19/12 Page 10 of 10 ',./ ~ "I-/. J 0 0 0 ~ 0 ~ J 0 0
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 AREVA UT Coverage Data Sheet Radial Examination Coverage Radial Exam Coverage 1 OO%t Total examination Volume= 2251.203 1 51 Limitation= 1130.953 2nd Limitation= 0.353 3rd Limitation = 3.163 Volume Covered = 1116.74 in3 Total Examination Coverage= 49.61% Report No.: 3-TVA-N4A-NV Coverage Data Sheet No.: CDS-01 _/llill [] Pn<J Df limttation
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A AREVA UT Coverage Data Sheet Radial Examination Coverage Limitation in N11 nozzle Area
~~see Page 9 for Volumetric Details~~
~~,*o Report No.: 3-TVA-N4A-NV Coverage Data Sheet No.: CDS-02 1:0>>1 [:;:;ill Area of limftatioo~~
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A AREVA Report No.: 3-TVA-N4A-NV UT Coverage Data Sheet Coverage Data Sheet No.: CDS-03 '¥';j:,~ ~~~ru~':'*,::' &~~~m;§~~:P:rcu$i~ Jrio~n** .: *~ '~ ~~;"; :;'~';~~'.t'%i;t:::f;~~~*~tl01\\~~,*~;!, .~; ~~~{~f'* Utility: TV A Circumferential Examination Coverage Circ. Examination Coverage 85%t Total examination Area= 24.38 in2 Area of Limitation = 24.38 in2 Area Examined = 0.00 in2 Total Area Examined I Total Area= 0.00% Total Examination Coverage: 0.00 in2 /24.38 in2 = 0.00% Lower 15% Circ. Exam Coverage Total examination Area= 1.73 in2 Total Examination Coverage =1.73 in2 Total Examination Coverage =100% _/M Circw~ 1"0 1" Configuration: Nozzle to Shell I r::::::::::1 ~ Area of I imitation 60" RL Ci rc coverage I -,._, I 0 ~ 0 0 "\\,;) ('\\) Page 11 of 12 N
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) in2 26.11 Exam Area (A B C D E F G H I) in3 2251.20 Exam Area (ABC DE F G H I) in2 26.11 Inner 15% I area in2 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 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 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.. Examiner: George,pman Level: II Date: 04/15/12 e~amiz=jsG~Q Level: II Date: 04/15/12 Sign: A_ ~~ S1gn:
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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 AREVA UT Coverage Data Sheet Radial Examination Coverage Radial Exam Coverage 100% t Total examination Volume = 2251.20 in3 1st Limitation = 1130.95 i n3 2"d Limitation = 0.35 in3 Volume Covered= 1119.90 in3 Total Examination Coverage= 49.75% Report No.: 3-TVA-N4B-NV Coverage Data Sheet No.: CDS-01 _/M ,*o [ill Artie of limit.r:J1ioo
~~60' RLCin::ccn,oaorG9'8 Page 9 of 11 rn~~
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A AREVA UT Coverage Data Sheet Utility: TVA Plant: Browns Ferry 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 in2 Total Area Examined I Total Area = 0.00% Total Examination Coverage: 0.00 in2 /25.06 in2 = 0.00% Inner 15% Circ. Exam Coverage Total examination Area= 1.73 in2 Total Examination Coverage =1.73 in2 Total Examination Coverage =100% Unit: 3 Weld ID: N4B-NV _/[ill Circ~ 1"0 1" Report No.: 3-TVA-N4B-NV Coverage Data Sheet No.: CDS-02 Configuration: Nozzle to Shell r:::0:0l ~ Area of limitation
~~60' RL Circ coverage Page 10 of 11 tn -~~
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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)in3 2251.20 Exam Area (A 8 C D E F G H I) in2 26.11 Inner 15% !area in2 1.73 Area Scanned in" 1119.90 Upper 85% t area in2 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. Exami:z:ge~man Level: II Date: 04/18/12 E~a~t\\mes <JrW Level: II Date: 04/18/12 Sign: .-ft. V S1gn* ....v~ V.-.. R~vie~£ 1~ ~ '-->" Level: Ill Date: 04/19/12 Page 11 of 11 S1gn: './~ t'i\\ - )ool ~ 0 w=> " ~ 01
T\\14 Ultrasonic Examination 000179 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 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 [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 AREVA Utility: TV A Radial Examination Coverage Radial Exam Coverage 100% t Total examination Volume= 2251.20 in3 1 51 Limitation= 1130.95 in3 2nd Limitation= 0.35 in3 Volume Covered= 1119.90 in3 Total Examination Coverage= 49.75% Report No.: 3-TVA-N4C-NV Coverage Data Sheet No.: CDS-01 _/M ""'~
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A AREVA UT Coverage Data Sheet Utility: TVA Plant: Browns Ferry 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 in2 Total Area Examined I Total Area= 0.00% Total Examination Coverage: 0.00 in2 / 24.38 in2 = 0.00% Inner 15% Circ. Exam Coverage Total examination Area= 1.73 in2 Total Examination Coverage =1.73 in2 Total Examination Coverage =100% Unit: 3 Weld ID: N4C-NV ~~M Circ~ 1"0 1" Report No.: 3-TVA-N4C-NV Coverage Data Sheet No.: CDS-02 Configuration: Nozzle to Shell I Inner 15% r::::::::::1 ~ Area af li mitatian
~~60' R L Ci rc coverage Page~~
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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) in3 2251.20 Exam Area (ABC DE F G H I) in2 26.11 Inner 15% t area in2 1.73 Area Scanned in3 1119.90 Upper 85% I area in2 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. Examiner: Nath::luman Level: II Date: 04/14/12 Examin4 Davi~~~ Level: HI Date: 04/14112 Sign:~ Sign: ~{!? Reviewed z;::rctor Morto~ Level: Ill Date: 04/14/12 /f Page 11 of11 Sign:
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1\\14 Ultrasonic Examination 00018.2 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 Size/Length: 12/ Thickness/Diameter: Limitations: Limitatlon=s due to joint design and configuration Comments: See Original report book for UT data. 32.31% coverage attained. No recordable indications noted. Results: Accept 1~ Reject lJ Percent Of Coverage Obtained > 90%: Examiner Level nature Gatica, James Level N/A Signature Level N/A Signature Yes Info [l Reviewed Previous Data: Date ANII Review Daniel Williams Yes Signature 6.6/12 Date 4121/2012 Date 5n/2012 Date 4/21/2012
A AREVA UT Coverage Data Sheet Radial Examination Coverage Radial Exam Coverage 100o/ot Total examination Volume= 2251.2()3 1st limitation= 1130.953 2nd Limitation = 0.353 3rd Limitation = 3.163 Volume Covered= 1116.74 in3 Total Examination Coverage= 49.61% Report No.: 3-TVD-N4D-NV Coverage Data Sheet No.: CDS-01 Configuration: Nozzle to Shell _/[ill EJ Area of limitation
~~60' RL Circ cova.raoa~~
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UT Coverage Data Sheet A ARE VA Radial Examination Coverage Limitation in N11 nozzle Area
see Page 9 for Volumetric Details
D Report No.: 3-TVA-N4D-NV Coverage Data Sheet No.: CDS-02
~~[] Area of limitation * -60" RL Ci rc cover-cge 11' \\ - \\ ~ - -l 0,::, '\\:>~~
~~0 Page 10 of 12 00~~
A AREVA UT Coverage Data Sheet Circumferential Examination Coverage Circ. Examination Coverage 85%t Total examination Area= 24.38 in2 Area of Limitation = 24.38 in2 Area Examined= 0.00 in2 Total Area Examined I Total Area= 0.00% Total Examination Coverage: 0.00 in2 /24.38 in2 = 0.00% Lower 15% Circ. Exam Coverage Total examination Area= 1.73 in2 Total Examination Coverage =1.73 in2 Total Examination Coverage =100% _/kill I Crew~ 1"0 1" Report No.: 3-TVA-N4D-NV Coverage Data Sheet No.: CDS-03 lj Inner 15% ~ ~ Area of limitation 60" RL Circ coverage ~ t"T\\ l -tJ I c:> - 0 0 => '-=' Page 11 of 12 00 <0
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) in2 26.11 Exam Area (ABC DE F G HI) in3 2251.20 Exam Area (ABC DE F G H I) in' 26.11 Inner 15% t area in' 1.73 Area Scanned in3 1116.74 Upper 85% I volume in2 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. 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.. Examiner:,.~ Sign:L Level: II Date: 04/18/12 ~amiL es "!fil S1gn: '- ( '\\ 'f--.... Level: II Date: 04/18/12 R~vi~d Btl.ct~ S1gn: Level: Ill Date: 04/19/12 Page 12 of 12 r ~ 1- ~ I 0 0 '\\) 0
1\\IJ\\ Ultrasonic Examination 000185 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 Size/Length: 12/ Thickness/Diameter: 6.6/12 Limitations: Limitations due to joint design and configuration Comments: See Original report book for UT data. 32.28% 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 AREVA UT Coverage Data Sheet Radial Examination Coverage Radial Exam Coverage 100% t Total examination Volume= 2251.20 in3 1 51 Limitation= 1130.95 in3 2nd Limitation = 0.35 in3 Volume Covered = 1119.90 in3 Total Examination Coverage= 49.75% Report No.: 3-TVA-N4E-NV Coverage Data Sheet No.: CDS-01 _/M [] kea cf limiltltion
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A AREVA UT Coverage Data Sheet 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 in2 Total Area Examined I Total Area= 0.00% Total Examination Coverage: 0.00 in2 I 24.38 in2 = 0.00% Inner 15% Circ. Exam Coverage Total examination Area= 1.73 in2 Total Examination Coverage =1.73 in2 Total Examination Coverage =100% _/M Circw~ 1"0, Report No.: 3-TVA-N4E-NV Coverage Data Sheet No.: CDS-02 Inner 15% ~ ~ Area of lim itotion
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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) in3 2251.20 Exam Area (A B C D E F G H I) in' 26.11 Inner 15% I area in2 1.73 Area Scanned in3 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 = 32.38% (See Radial and Circumferential coverage sheets for more detail.) Radial scans were performed INith 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 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. Examiner: Nathan Bauman Level: II Date: 04/14/12 ExamJ~r. David Kleinjan Level: Ill Date: 04/14/12 Sign:~~ Sign: tf./::R.4 L--- R~viewe/2~ Level: Ill Date: 04/15/12 /u Page 11 of 11 S1gn: ~<!; ---~ )...l ) C> - -a 0
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1\\14 Ultrasonic Examination 0001$8 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 Size/Length: 12/ Thickness/Diameter: 6.6/12 Limitations: Limitations due to joint design and configuration Comments: See Original report book for UT data. 32.28% 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 AREVA UT Coverage Data Sheet Radial Examination Coverage Radial Exam Coverage 100% t Total examination Volume= 2251.20 in3 1 51 Limitation = 1130.95 i n3 2nd Limitation= 0.35 in3 Volume Covered= 1119.90 in3 Total Examination Coverage= 49.75% Report No.: 3-TVA-N4F-NV Coverage Data Sheet No.: CDS-01 _/M []l Wee of flmitoOOn
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A AREVA UT Coverage Data Sheet 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 in2 Total Area Examined I Total Area = 0.00% Total Examination Coverage: 0.00 in2 /25.06 in2 = 0.00% Inner 15% Circ. Exam Coverage Total examination Area= 1.73 in2 Total Examination Coverage =1.73 in2 Total Examination Coverage =100% _/[ill! Circ~ ,**D 1" Report No.: 3-TVA-N4F-NV Coverage Data Sheet No.: CDS-02 Inner 15% r:::0:0i ~ Area of limitation 60" RL Circ coverage l'l 1 ~ t'l 0 =>
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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) in2 26.11 Exam Area (A 8 CD E F G H I) in3 2251.20 Exam Area (A 8 C D E F G H I) in2 26.11 Inner 15% t area i~ 1.73 Area Scanned in* 1119.90 Upper 85% t area in2 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. The exam/coverage area calculations were derived from a CAD drawing based on the available dimensions from TVA supplied drawing number 131840. Exami2~&:apman Sign: V Level: II Date: 04/18/12 ~:~amesf1ca-O g [/<{ \\. A Level: II Date: 04/18/12 Revie,:e-d B~or Morto~ \\._ ~ /~ Level: Ill Date: 04/19/12 Page 11 of 11 Sign:
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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.: 5 Report No.: VE-12-029 Workscope: 181 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 Size/Length: 4/ Thickness/Diameter: 6.6/4 Limitations: Limitations due to joint design and configuration. Comments: See Original report book for UT data. 27.96% coverage attained. No recordable indications 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 AREVA UT Coverage Data Sheet Radial Examination Coverage Radial Exam Coverage 100% t Total examination Area= 1412.29 in3 1st Limitation = 791.11 in3 2"d Limitation= 43.30 in3 Area Covered= 577.88 in3 Total Examination Coverage= 40.92% Report No.: 3-TVA-N9-NV Coverage Data Sheet No.: CDS-01 [ill Area of limitatioon
~~6(1~ Rl Cite: coverage TOial Exam Volume== 29.6665 Hea of Coverage= "8.4343 Page 10 12 0~~
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A ARE VA UT Coverage Data Sheet Circumferential Examination Coverage Circ. Examination Coverage Outer 85%t exam coverage Total examination Area= 29.67in2 Area of Limitation = 29.67in2 Area Examined= 0.00 in2 Total Area Examined I Total Area= 0.00% Total Examination Coverage: 0.00 in2 / 29.67in2 = 0.00% Inner 15% Circ Exam Coverage Total Examination Area= 2.61 in2 Total Examination Coverage= 2.61 in Total Examination Coverage= 100% Report No.: 3-TV A-N9-NV Coverage Data Sheet No.: CDS-02 Configuration: Nozzle to Shell [] Ani ~lmitalon ToW EJ:.am "'olJ~.2SI.ee55 .r..reaot~0-00 Page 11 of 12 7J c ).,) 0 => ~ ~Jl 0')
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)in3 1412.29 Exam Area (ABC DE F G HI) in' 29.67 Inner 15% I area in2 2.61 Area Scanned in3 577.88 Upper 85% t area in2 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 = 27.96% (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 '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 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 TV A supplied drawing number 131840. Examiner: Nathan Bauman Level: tl Date: 04/14/12 Exami:r= David Kleinjan Level: til Date: 04/14/12 Sign:~~ Sign:,k~ Reviewed ~ctor Mort~ Level: Ill Date: 04/14/12 /(,) Page 12 of 12 Sign:
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/., 1\\14 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 AREVA UT Coverage Data Sheet Radial Examination Coverage Radial Examination Coverage Weld Length = 18.64" Exam Area = 5. 78"x 2.83" Total examination Volume= 304.90.3 Volume of 1st Limitation = 13.05"3 Volume of 2nd Limitation= 6.16"3 Volume Examined = 285.74 in3 Total Volume Examined I Total Volume = 93.70% Total Examination Coverage: 285.7 4 in3 / 304.95 in3 = 93.70% 1"0 1" Report No.: 3-TVA-N10-NV Coverage Data Sheet No.: CDS-01 ~ ~ ~ ~ Area of limitation 60°RL Radial Coverage Examination volume Permanent ins.support bracket Nozzle Boss Centerline of nozzle IO \\\\ \\~) II ~ I 0,:) ".J:J
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~~A AREVA UT Coverage Data Sheet Report No.: 3-TVA-N10-NV Coverage Data Sheet No.: CDS-02~~
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<<< < ComPc>n8nt'rnt6fination Utility: TV A Plant: Browns Ferry Configuration: Nozzle to Shell Circumferential Examination Coverage Upper 85% Circ. Exam Coverage Total examination Area= 16.49"2 Area Covered= 7.75"2 Total Examination Coverage= 47% Lower 15% Circ. Exam Coverage Total examination Area= 2.49"2 Total Examination Coverage =2.42"2 Total Examination Coverage= 97% 1"0 1" + + + + + + + + + + + + + + + + + + + + + + + + + + + + + Area of limitation 60° RL Circ coverage Ill 50° Shear Circ coverage of inner 15%t Examination volume Page 8 of 9 0 ~
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A RPV Coverage Work Sheet Report Number: 3-TVA-N10-NV AREVA Customer Information Component Information Utility: TVA Plant: BFN I Unit: 3 I Outage: 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) in2 18.90 Exam Volume (ABC DE F G H) in3 304.95 Exam Volume (A B C D E F G H) in2 18.90 Inner 15% t area in* 2.49 Area Scanned in3 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. Examiner: Nathan Bauman Level: II Date: 04109/12 Examiner-david ~~~ Level: Ill Date: 04/09/12 Sign: ~/J"- Sign: t:? /'\\ ~ R~viewed By: Victor Mo~ JilL / j Level: 111 Date: 04109/12 ~u Page 9 of 9 S1gn: .. 7T/£ul/~ '---~~~ ~~.. ~ ~ ~ ~0 0 ~=> W".AJ 0~
TVJ\\ Ultrasonic Examination 000194 Site/Unit: BFN I 3 Procedure: VENDOR UT Outage No.: U3RF15 Summary No.: 00127-ISI-BFN3 Procedure Rev.: 000 Report No.: VE-12-031 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/83.100 Location: REACTOR BUILDING-DRYWELL Drawing No.: ISI-0445-C-01
== Description:== NOZ IR System ID: 329 - Reactor Vessel Component ID: N10-IR Size/Length: 1.5/ Thickness/Diameter: 6.6/1.5 Limitations: Limitations noted due to joint deisgn and configuration Comments: See Original report book for UT data. 90% coverage attained. No recordable Indications 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.: Page: 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
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.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 AREVA RPV Circumferential Scan Coverage Work Sheet Report Number: 3-TVA-NSA-NV N8 Nozzle to Shell Weld Circumferential Scan Coverage Calculations Total Area:= 14.57 in2 Total Area: 2.38" x 6.12" = 14.57 in2 Upper 85% t of Vessel Shell Coverage: = 44.82% 0.80" x 5.20" = 4.16 in2 0.91" x 5.20" 12 = 2.37 in2 4.16 + 2.37 = 6.53 in2 (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 AREVA RPV Coverage Work Sheet Report Number: 3-TVA-N8A-NV i.* Utility: TVA Plant: BFN I Unit: 3 J Outage: R16 Component 10: N8A-NV I Work Sheet Number: CWS-03 &o*RL Radial Scan (N-UT-78-0007) 100% t volume &o*RL Clrc Scan (N-UT 0007) Upper 85% t volume Thickness (ts) Inches 6.12 Thickness (ts) Inches 6.12 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 Area Scanned Sq. Inches 13.95 Upper 85% "T" Area Sq. Inches 12.38 Percentage of Area Scanned 95.74% Area Scanned 6.53 Percentage of Area Scanned 52.75% Percentage of Total Volume 95.74% Percentage of Total Volume 44.82% Coverage Radial Scan 100% t volume 95.74% Coverage Clrc Scan upper 85% t volume 44.82% Total Coverage Radial and Circ Scans: (95.74% + 44.82% + 15.000;1,) + 2 = 77.78% (See Radial and Circumferential coverage sheets for more detail.) so* :1:(15° to 45') Circ Scan (54-ISI-850-008) Inner 15% t volume (Modeled) Thickness (ts) Inches 6.12 Weld Width Inches 1.38 Exam Area (A BCD E F G H) Sq. Inches 14.57 Inner 15% "T" Area Sq. Inches 2.19 Area Scanned 2.19 Percentage of Area Scanned 100% Percentage of Total Volume 15.00% Coverage Clrc Scan Inner 15% t volume 15.00% 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. Page 9 of9 -C ' t1 ~------------------------------------------------------------------~--------~-l
CNL-17-013 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
NOTE.*
7.
PIPE SEGMENTS CONTAINING TWO LONGITUDINAL SEAMS WILL BE IDENTIFIED AS: (BASE WELD NO. )-LS-JD (BASE WELD NO. )-LS-2D (BASE WELD NO. )-LS-JU (BASE WELD NO. )-LS-2U (DOWNSTREAM) (DOWNSTREAM) (UPSTREAM) (UPSTREAM) THE -LS-7 SEAM WILL BE NUMERICALLY CLOSEST TO 0' ON THE PIPE, AND THE -LS-2 SEAM WILL BE NUMERICALLY FARTHERMOST FROM 0' ON THE PIPE. (e.g -LS-i AT 730', AND -LS-2 AT 370'~ 2 PIPE SEGMENTS CONTAINING ONLY ONE ~** . LONGITUDINAL SEAM WILL BE IDENTIFIED AS '): (BASE WELD NO. )-LS-D (DOWNSTREAM) (BASE WELD NO. )-LS-U (UPSTREAM) ADMIN ....._______ DSRHR-3 -06 ALL A/0 HISTORY RESEARCHED AT ROOD REFERENCE DRAWINGS 47NJ568 47W335-4 & 6 47W452 SERIES DRAVO [-2460-IC-37, 32, & 33 NOTE: THIS DRAWING SUPERCEDES CHM-2747-C ALL SHEETS. MATERIAL SPECIFICATION: A-358 GR 304 CL. 7, OR A-403WP304, OR A-706 GR.B, OR SA376 TP 376NG 24" X 7.279" NOM. WALL THK. SCH. 80 55 20" X 7. 037" NOM. WALL THK. SCH. 80 55 20" X 7. 037" NOM. WALL THK. SCH. 80 CS 6" X 0. 432" NOM. WALL THK. SCH. 805 55 FLUED HD 55 FORGING A782 F304 VALVES WITH THE EXCEPTION OF FCV-74-47 ARE 55 CASTINGS A357 CF8M ASME CC-7 (EQUIVALENT) DSRHR-3-07-LS-7 DSRHR-3-07-LS-2:>----__ DSRHR-3 ~ ' 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 CHECKED. J£5 SUBMI TT£0 EOC SCALf-NTS CADAM !SICMP SHEET 0 1 OF 0 1 REV 3-IS I -0330-C ooz ceo
GR-3-59 (OL) N18-SE GR-3-59-LS KR-3-50\\ KR-3-50-LS-1~ \\ N18 180o o KR-3-50-LS-2--- ~~~----_____.~"'-N18-IR '\\')0 GR-3-60 (OL)---. GR-3-60-LS~ GR-3-61 "\\ ~~tt_,.1\\< RWR-3-002-G013-....... 0 ~~ RWR-3-002-G015- - ~ RWR-3-002-G001 RWR-3-002-G003 N2A 30 a N2A-IR ::1 Hr------.. B - LOOP ADMIN REFERENCE DRAWINGS: TVA 47K7544-3 GE 153F754 KELLOGG BF 2-780 NOTE: THIS DRAWING SUPERSEDES CHM-2739-C ALL SHEETS MATERIAL SPECIFICATIONS:
~~A358, TP 304 4 II X 0. 337 II NOM WALL THK.~~
(SS) 28" X 1. 138 11 NOM. WALL THK. (SS) SUCTIO 28" X 7.322" NOM. WALL THK. (SS} DISCHARGE SA403 WP3 7 6NG 12 11 X 0. 602 11 MIN. WALL 22 11 INTEGRAL RED. TEE 0. 980" MIN. WALL 28 11 X 22 11 CROSS 0.980 11 MIN. WALL 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) GR-3-61-LS--- KR-3-51 ~ KR-3-51-LS-1~ KR-3-51-LS-2 ,;- RWR-3-002-G024 IRWR-3-002-G022 ~ RWR-3-002-G020~ k"" I 22" .----------.,, / ~ IRwR-3-oo2-G023 r ~ RWR-3-002-G021_/ SW-TPR-3-27~ RWR-3-002-G025~ I RWR-3-002-G018 ( -......._ RWR-3 -002-GO 7 7 2~-...__ BENT INTEGRAL TEE -......_ W/12 11X22 11 RED. (2 TYP.) SEE DETAIL A ~ RWR-3-002-G019 28 11 X 22" CROSS W/22 11 X 12 11 RED. SEE DETAIL 8 r KR-3-26 I; GR-3-33 KR-3-24-LS~ D51 I I IV) ___.-- KR-3-24 GR-3-62~ r GR-3-63A ~ 4 II Cl.. -fGR-3-638 I t:tJ ~ GR-3-29-LS-1 FCV68-77 GR-3-63 GR-3-63-LS KR-3-53~ 4" 4 11 DECONTAMINATION LINE ~~_/ ~ R8C-3-2~ KR-3-52 ~~, KR-3-52-LS-1 j KR-3-52-LS-2 GR 64 ~:-30 KR-3-23 (OL) ~ ""-...___ GR-3-29-LS-2 \\ "-.__ GR-3-29 ""'- FCV68-79 FCV68-79-BC GR-3-28 GR-3-27-LS XR-N-N K ~ KELLOGG SHOP WELD _j I ~ WELD G = GE FIELD WELD ~ UNIT NO. SYSTEM NO. DETAIL A - ONE PIECE SPECIAL FORGING DETAIL 8 - ONE PIECE SPECIAL FORGING SYMBOL: 002 RISK-INFORMED WELD ADMIN TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT UNIT 3 RECIRCULATION SYSTEM WELD LOCATIONS DRAWN: PHB SUBMITTED APPROVED SCALE NTS 7*30*/Z.. DATE D"Af£:4-4::S9-DA TE.:.J:::;_8-89 DALE_J=.}l_-89 SHEET 2 OF 2 SHEET S CHECKED: _}ES_ DATE: 5-8-89 EDC DRAWING NO. REV. GLB 3-ISJ-0328-C002 ALL A/D HISTORY RESEARCHED AT Rooo leAD MAINTAINED DRAWING I t-------C_C_D ____ ~
RWCU-3-00/-G0/6 _./ 1 ~RWCU-3-001-G0/7 -:_1 I--- RWCU-J-00 I-GO /8 ,..___RWCU-3-00 I-GO 19 ADMIN REFERENCE DRAWINGS RWCU-3-00/ (TVA WELD MAP) NOTE: THIS DRAWING SUPERSEDES A PORTION OF CHM-2144-C 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--------------------------- ASME CC-I (EQUIVALENT) 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 I RCIC I AND CRD WELD IDENTIFICATION DRAWN: PHB DATE: 5-17-89 SCALE: NTS j CADAH/ISICMP .-----r---~ -** SHEET 0 I OF 02 REV ceo 3-ISI-0332-C oo2 CHECKED: JES SUBMITTED: EDC APPROVED: GLB ALL A/D HISTORY RESEARCHED AT ROOO leAD MAINTAINED DRAWINGI I
REGION OF THERMAL FA TIGUE EXAMINATION PER NUREG-0619 ~ ~ THERMAL TEE CJ UPSTREAM OF VALVE ~ 3-FCV-69-629 RCRDS-3 TEE~ 8 "xB "x6" THERMAL TEE DET A NOMINAL WALL z*L..-0~--lf-RCRD-3-45 RCRDS-3-02 RCRDS-3-03 ~RCRD-3-44 R14 IDRWC-3-59 RWCU-3-007-003 8" TRCIC-3-005 ~ 0 120505 106 RCRD-3-49 (NUREC-0373) 85-577 '6,_/ (STAINLESS STEEL) \\J._ ___ RCRD-3-50 (NUREC-0313)
~~P----RCRD-3 -57~~
_ ~ RCRD-3-52 ~~ (NUREC-03!3) 85-576 (STAINLESS STEEL) R14 120505 106 R14 120119 105~ REFERENCE DRAWINGS TVA 47W335-14 TVA 47W335-17 RWC-3-004 (TVA WELD MAP) DRAVO E-2460-IC-49 NOTE: THIS DRAWING SUPERSEDES CHM-2143-C AND CHM-2144-C (ALL SHEETS) MATERIAL SPECIFICATIONS 4" X 0.337" NOM. WALL CS SCH. 80 A-333, GR1 (SEAMLESS) 6 " X 0.562 NOM. WALL CS, SCH. 8" X 0.593 NOM. WALL CS, SCH. CRD CAP 4 " X 0.674" NOM. WALL ss VALVE 69-629 SA 105, CS FORGING VALVES SS FORGINGS A182 F316 85-576' 85-577 120 100 NOTE: ALL FIELD WELDS WERE MAD£ BY TVA ASME CC-1 (EQUIVALENT) ~ N9-IR RCRD-3-33 / CRD RETURN LINE NOZZLE CAP DETAILS ALL A/0 HISTORY RESEARCHED AT ROOD SYMBOL: RISK-INFORMED WELD 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: f...--------; GLB SUBMITTED: JES SHEET 02 OF 02 REV ..3-IS I- 0..3..3 2-C oo7 CCD leAD MAINTAINED DRAWINGII------------~
~ THPCI-3-30 ..,....,_THPCI*!-29 < THPCI-3-28 ~ THPCI-3*27 K-~-...- THPCI-3-18 ..., THPCI-3-17 ~E--THPCI-3-25 K-...... -THPCI-3-24 4 f{,V 73-44 THPCI-3-23 "-.. THPCt-3-22 ,. FOI 73-34 THPCI*3-20 SHPCI*3-8 ----i.. .,.....~,.-.~-+---~SI:it1t~PCI-3-7 J "c~t -t SHPCt-3 -g 1c?Q ~ _U.. _ / THPC1*3-IO ~ -1411x to* REDUCER ~k--THPCt-3-11 ~,._..THPCI-3-12 THPCI-!-13 ~ THPCI*!-14---tlloV"'" ~.. ~C!~, ~... _,.. ... 12~~*t;'tf, ~ BOOSTER PUMP THPCI-!*gg-->...r~~THPCt-3-100 THPCI-3-98 ---il-7-- ~ THPCt-3-fR ~-....._ THPCt*!-100 0 THPCI-3-t OOA--)~ THPCI*!-1008__..,., 47W335-13 47W455 SERIES E-4707 2F*I238 SUPPRESSION POOL ~'""*-~- THPCI-3-101 THPCt-3*96 "<.. -"E--e -THPCI-3 -I 0 2 ..... """~~ ~~~ ~~~THPCI-3*136 THPCTHI PCI-3-134 --..-""' ~24"at6* REDUCER
~

;..>~
~*~o~r :v 73-23 L__ **uft~ *-3.. IOIA ~THPCI-3-103 THPCI*3*133 HPC I 009-004 THPCI-3-132 3 CKV 7 3 603 HPCI-3-009-005 2Cfxl6" ~- HPC I 009-003 ~--E-- HPCI 009-009 .JJ~C-~THPCI-3-128 '-~~-THPCt*3-106 THPC1*3*107 THPCI-3-123 20"af6" REDUCER THPCI-3-122 ~-~THPCI*3*120C THPC1*3*1208 --ill._~ HPC I 01 9-009 ~THPCt-3-120A SHPCI.. 3*2 HPCI TURBINE DD4 ADMIN < THPCI-3-110 < IO"xiO"*IO" TEE <: THPCI-3-111 HPCI-3-019-011 ~ ~THPCt-3-II~O FCV 13-ra ~e ~ J MCFARLAND £./C /-loDGES REVISED PER RIMS MEMO R14 D4D521 1D1 REV CHANGE REF PREPARER CHECKER APPROVED DATE SYMBOL: RISK-INFORMED WELD TINNIIIR YAUIY AUTMOIIITY IMYIIION Of NW" 'AI..OMI BROWNS FERRY NUCLEAR PL~ UNIT -3 HIGH PRESSURE COOLANT INJECTION IYifEM WELD LOCATIONS ALL A/D HI sToRY RESEARCHED AT Rooo 1 cAD MAINTAINED DRAWING 11--___ c_c_o __ ___,
CNL-17-013 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
1m] UT Calibratio.-mination Site/Unit: BFN I 3 Procedure: N*UT-65 Outage No.: U3RF15 Summary No.: 05109-tsi*BFN3 ProceQ.Jre Rev.: 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: REACTOR 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 Slze/Leogth: 2B I Thickness/Diameter: 1.138/ 2B Umltations: NONE Start Time: 1130 Finish Time: 1150 lnstNment Settings Search Unit Cal. Axial Orientated Search Unit Time Date Serial No.: E37688 Serial No.: OOW3N2 Checks Manufacturer: KRAUTKRAMER lnlual Cal. 1030 411212012 Calibrati011 Signal Sweep Sound Path Manufacturer: KBA Ret lector Amplitude% Division Model: USN60 Unearity: L-to-412 Size: 0.5" Modei: CompG Inter. Cal. N/A NTCH NIA 3.1 .9 Delay. 7.77 Range: 3.0 Freq.: 2.25 MHz Center Freq.: NfA Inter. Cal. NIA NTCH N/A 6 1.8 M'li Cai/Vel: .1337 Energy: High Inter. Cal. NfA NTCH NIA 9 2.7 Exam Angle: 60 Squint Angle: N/A Final Cal. 1235 411212012 Damping: 10000hms Reject: 0 Measured Angle: 60 Mode: SHEAR NIA WA NIA NIA Couplant NIA NIA NIA NIA PRF Mode: Auto High SU Freq.: 2.25 MHz Elcit Polnt: NfA t ol Elements: 1 Oisp. Start: JP Rectify: FulL Wave Cal. Batch: 06125 Circumferential Orientated Search Unit Config.: SINGLE Focus: NIA lnst. Freq.: 2.25MHz Type: Ullnlgel II Calibrallon Signal Sweep Sound Path Shape: Round Contour: FLAT ReflectOr Amplitude% Dlvisioo Mfg.: Sonotech NIA NIA NIA Wedge Style: Non-Integral Exam Batch: N/A NIA N/A H/A NIA Ax. Ga1n (dB): N/A Circ. Gain (dB): NIA 1 Screen Div... .3 ln.ol Sound Path Cal. Block No.: Thickness: Cal. Blk. Temp.: Comp. Temp.: Results: Callbrallon Block WB-85 N/A Dla.: NIA 7J Temp. Tool: 558274 70 Temp. Tool: 558274 NAI 0 ~ AI ~ 0 Percent Of Coverage Obtained> 90%* N/A Search Unit Cable Type: N/A NIA N/A NIA Type: RG-174 Length: 6 No. Conn.: 0 M~. g.. N/A NIA NfA N/A Scan Coverage Upstream 0 Do.vnstream~ Scan dB:~ Reference Block Referenc&'Simulator Block CWO CCW 0 Scan dB: ~ Exam Surface: OD Surface Condition: As Found Info U THROUGH WALL SIZING Reviewed Previous Data: Yes ieport.) Serial No.: Type: Gain Signal 790662 dB Reflector AmPlitude% Rom pas 40 NSDH 80 NIA N/A NIA NIA NIA NIA Comments: 558274 DUE DATE 12*10.2012 E37688 DUE DATE0&-15-2012 Sweep Division 2.2 NIA NIA NIA NIA Sound Path .6 N/A N/A Examiner lellel 111-PDI~~~ Date Reviewer ture Date 1 Welch, Matthew C. 411212012 Damon Prteatley, Llll I Examiner l evel H/A Signature Date Site Review Date NIA II. '/I Otnef Level NfA Signature Date ANI! REMe.v Date NIA /JA(Iclf' C~/V'/1 I h '1/lr/1~ UT Calibraticn'Examlnallon 0 0 0 N N N
Supp Report Summary No.: 05109-ISI-BFN3 Sketch or Photo: O:\\lddeai_SeiVer\\Jddeai_BFN\\Documentation\\U3R18 Scanned Oata\\GR-3-63 TC.jpg THICKNESS AND CONTOUR PositiOn 0 90 180 270 I~ 2.5' z.s- - - .....a. Supplemental Report 1 M
2.
~~.ZJ .I v 3 ?/ ';/,. 4* ,t VPL__srDE s r.z.o /~~
~~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 ~=No lO~iU4f. A? &kh~ A~SIOE ~---1 /to Report No.: UT-12-024 Page: 5 of 7 C> 0 0 N N
0)
Supplem Report Summary No.: 05109-ISI-BFN3 Sketch or Photo: O:\\lddeai_Se!Ver\\lddeal_BFN\\DOCtJmentation\\U3R1B Scanned Oata\\GR-3.Q3 PLOT.jpg INDICATION PLOT Reviewer. Print name: Date: ~ CompOnent 10: ~ I( - ~-""3 'e::J 2-o/L RL-J?~uj ~ ... /,o /WE -7'Ju.,c:!J ~ M/tur-=. 7-- ~--t---- ".i:Jo ~ I IJ tllc:A"fbN tr I ~o* f.{} ~ T ~*~-J Set LJ-1" I N'D1U.T1CW ~4ciN~ RE'PoJat fOR v,o\\UJE"~. Supplemental Report Report No.: liT-12-024 Page: 6 of 7 0 0 0 f'\\.) N '-.l
Ultrasonic lndic-Sizing Report Site/Unit: BFN J 3 Procedure: N-UT-65 Outage No.: U3RF15 Summary No.: 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 Lo Location: TOC Start Time: 11:30 Weld Crown Width: 1.5 Measured Component Thickness: 1.2 Wo Location: WELDCL Finish Time: 11:50 lnd Angle dB 00 Length Remaining Thrv Intermittent or Recommendations or Remarks Used or No. Used Technique Ugament Wall Continuous Useful Used L1 L2 Total 1 60 NIA AATT 34.7 36.4 1.7 1.0 .2 CONT SEE BELOWW/MAX 1.6 N/A 1 45 NIA AATT 34.7 36.4 1.7 1.0 .2 CONT SEE BELOW W/MAX 1.1 WA Additional Remarks: THROUGH WALL SIZING OF EXJSnNG IGSCC REFLECTOR. THIS EXAM SATISFIES THE REQUIREMENT OF IWB-2420(c) FOR COMPONENTS PLACED IN THE ORIGINAL SCHEDULE AFTER SUCCESSIVE INSPEC110N PERIODS. NO CHANGE DETECTED Date I Reviewer 4/1212012 Damon Prresuy, Llll Examiner Level 111-PDI Welch, Matthew c. Examiner Level N/A Signature NIA I I Date 12-Date Other Level NJA Signature NIA Date I AN II Review ~vd c'AA1,* Date Y/I'J/12-- Ultrasonic lndicatlon Sizing Report 0 0 0 N (\\) OQ
UT Calihr~**~"~ mination ~ Site/Unit: BFN I 3 Procedure: N*UT-64 Outage No.: U3RF15 Procedure Rev.: 11 Report No.: UT-12..()31 Work Order No.: 3-SI-4.6.G Page: 1 ol 6 Code: Section Xl2001 EcU2003 Add Cat./ltem: R-AIR1.160 Location: REACTOR BUILDING-ACCESS ROOM Orawing No.: 3-1Sf.0330.C.01
== Description:== VLV-Ftl System ID: 074 - Rosldual Heat Removal System ComponentiO: DRHR-3-12 Sizetl.ength: 24 I Thickness/Diameter: 1.219/24 Limitations: YES-JOINT CONA G AND CAST SS COMPONENT SlartTime: 1155 Finish Time: 1225 Instrument Settings Seareh Unit Cal. Altlal Orien1ated Search Unit Time Date Serial No.: E:963Q2 Serial No.: 01FH9X Checks Caibralion Signal Sweep Manufacturer. KRAUTKRAMER Manufacturer: KBA Initial Cal. 0930 411412012 Reflector AmpiHude % DMsion Sound Path Model: USN60 Unearity: L-12-003 Size: 0.375" Model: CompG Inter. Cal. NIA 1.5 NOTCH 80% 6.6 3.958 Delay: 8.4278 Range: 6.0 Inter. Cal. 1215 411412012 NIA Freq.: 1-5 MHZ Center Freq.: N/A High Inter. Cal. N/A N/A M'tlCal/Vf!J.: .1262 Energy: Exam Angle: 70 Sql.int Angle: NIA Final Cal. 1244 411412012 NIA Damping: 10000hms Reject: 0 ~red Angle: 68 Mode: Shear Couptant N/A PRFMode: Aulotilgh SU Freq.: 1.5 MHz Exit Point: NA
~~of Elements:~~
1

~~Cal Batch:~~

06125 Circumferential Orientated Search Unit i FuHWave Disp. Start IP Rectify. Conf~g.: SINGLE Focus: NIA Type: Ultragetll Calibration Signal Sweep Sound Path 1 lnst. Freq.: 2.0 MHz Shape: Round Contour: NIA Reflector Amplitude% DMsi<ln Ax. Gain (dB): 51.3 Circ. Gain (dB): NIA 1 Screen Div. :o .6 in. of Sound Path CllllbraUon Block Cal. Block No.: SQ.123 Thickness: 1.5 Dia.: FLAT Cal. Blk. Temp.: 2!!. Temp. Tool: 558274 Comp. Temp.: I!:!, Temp. Tool: 558274 0 ~ Results: NRI ~ Rl :-; Percent Of Covetage Obtained > 90%: No Examine~ Level IJ(N) Rah, Edward W Examine~ Level NIA N/A Other Level NlA NIA l.JT Calibration/Examination Mfg.: Sonotech Wedge Style: Non..,ntegral NIA EXMI Batch: 06125 NIA Search Unit Cable RG*174 Length: Type: Ultragel ll N/A Type: 6 No. Conn.: 0 Ml. Sonotectl g.. NIA Scan Coverage Upstream 0 Downstream~ Scan dB:~ Reference Bto~ R~~~mu~lorB~k CW O CCW O Scan dB:~ Serial No.: Exam Surface: Surface ConditiOn: Info 0 Reviewed PfevlOliS Data: SIQ.nature. OD lSI Prep Report.) Yes Date 411412012 Date Type: Date I ANII Review Gain Signal 189631 dB Reflector I Amplitude % Rom pas 51.3 FSDH 39 N/A NIA Comments: E36302 DUE DATE IS 06-15-2012 558274 DUE DATE IS 1 2*1~2012 ~ature Signature 'vc/' e-:tM *'~t-h /3.. Sweep Division Sound Path 2.9 1.63 .H/~J. Date -v~/Z.. Date Date tt/lf/12-0 0 0 N ~ ~
Supplemental Report Summary No.: 05100..JSI*BFH3 Sketch or Photo: O:\\lddeal_Server\\lddeal_BFN1Documentation\\U3R18 Scanned Data\\DRHR-3-12.jpg THICKNESS AND CONTOUR Pos1mon I~J..Ioo 11J7z 2" IJ_y J 3 If,¥ I I/.... 4" 11.-1 I / 5 l"'l.t 1/ 'Wefdedge Examiner: Print name: S"P l=rSH Date: COMPONENT 10: DRJH~- ~ *12-CROWN WIDTH: f.p " CROWN HEIGHT: ,:;.~ /?6J.tuud~~: (i'.o~x..s) t{ 75.1-{ = 77. z.~s tAr3 tJ~~~: ~,;,?- /"J*S/7?.Z8$ :::, Z~~ ~- ZY/f /?1* l-SS c, :?1~ (c.n'l-f,ZU.)+'Z)xlofl "" ~o~ 14 2.5" z.s* ____... fi..~SlDE VA'-~SIOE m ~ OI:J#Rt.ter8l:> 1/0UJP. ~
t..A~/55 4

.
-=f tJ.t7HC1f/aL ~ ~ /,1/5 t./8 a~ss ,,o c *(IS<*I)i>>.tJD7<(tt1') \\. ~o ~f&tl.)A 1'5.-f !:- fl.5JMI *~116'16P AJCIIf~ .uTt\\ ' ~~ c.A~ ss 1~111 *-- .tn.-z.r>/-1.)- q~~u';. 15.'t):! ~1,.; ~cut Supplemental Report Report No.: UT-12..031 Page: 5 of 6 0 0 0 l\\) CJl
Report Summary No.: 05100-ISI-BFNl Sketch or Photo: O:\\Jddeai_Server\\JddeaLBFN\\Documentation\\U3R18 Scanned Data\\ORH R-3-121imltalion.jpg Supplemental Report 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 penetration llued head. POl Supplement 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 circurrtorential 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!~ Report No.: UT-12-031 Page: 6 of 6 0 0 0 N CJ1 N
1m UT Calibration/E:.... crmination BFN I 3 ProcEdUre: N-UT ~4/PDI-UT -2 05054-ISI-BFN3 Procedure Rev.: 131F Sit()I\\Jnlt: Summary No.: -------------- OulageNo. Report No: U3RF1& UT-14-039 ~ WorkscqJe: lSI Work Order No.. 114699848 Page of _.!__?~)( Cede: Section Xl2001 Ed/2003 Add Cat/Item: R-AIR1.11 location: REACTOR BUILDING-DRYWELL Drawing No.: 3-ISI-0330-C-01 De<>cription* TEE
~~P Sy.;tem 10:~~
~~074-Residual Heat Removal System Component ID: DRHR-3-19 Slzellength: 20 I Thickness/Diameter. 1.031/20~~

~~~-----------------------------------~~

See Coverage Plot - :5~ ~ ~ Limitations: Start Time: 0851 Finish Time: 1050 Instrument Sel1ings Search Unil car. Axial Orientated Search Unit Time Date Serial No.: E36302 Serial No.: 01YPH2 Checks Signal Sweep Initial Cal. Calibration Sound Path Manufacturer: KRAUTKRAMER Manufacturer: GE 0830 31512014 Reflector Amplitude % DMslon Model; USN60 Linearity: L-14-003 Size: 0.5" Medel: CompG Inter. Cal. 1.5 Notch 80 5.6 2.030 Delay: 7.6041 Range: 3.700 Inter. CaL Freq.: 1.5 MHz Center Freq : N/A Inter. Cal. M'IICaWef* 0.1249 Energy: High Exam Angle: 45 Squint Angle: NIA Final Cal. 1137 3/5f2014 Damping: 1000 Ohms Reject 0 Measured Angle: 43 Mode: Shear PRF MociP.* Auto High SU Freq.; 1.5MHz Couplant Exit Point* .5"
~~o1 Elements:~~
1 Cal Batch: 12H130 Circumferential Orlenlatod Search Unit Otsp. Start: IP Recrify: Full Wave Config.: Single Focus: NIA lnst. Freq.: 2.25MHz Type: Ultragelll Calibration Signal Sweep Sound Path Shape. Round Contour Flat RenectOf Amplitude % Divisim Mig.: Sonotech Wedge Sryte: Non-Integral Exam Bach: 12H130 1.5 Notch 80 5.6 2.030 Ax. Gain (dB): 23.4 Circ. Gotn (dB): 23.4 Search Unit Cable Type: Ullragel II 1 Sr.reen Div. = .3T in. ol Sound Path Type: RG-174 Length: 6 No Conn.: 0 Mfg.: Sonotech Calibration !:!lock Scan Coverage Upslleamli!J Downstreamli!J Scan dB: 37.0 Reference Block Roforence/Simulator Block cal. Block No.: WB-84 Gain Sign;~ I Sweep Thickness: 1.5 Ola: Flat CW2J CCW bZJ Scan dB: 37.0 Serial No: 790398 dB Reflector Amplitude % Di-Aslon Sound Path Cal. Blk. Temp.: 67.6 Temp. Too: 531993 EXam Surface: ID --Type: SS Rompas 43.3 FSDH 80 2.8 1.008 Comp. Ternp.: 76 Temp. Too: 531993 Surface Condition: Ground 0 tllrasonic lndlcatim RepOrt.) Results: NRI ~ [l Rt 0 Info O Comments: E36302 Cal Duo 10/2612014 531993 Cal Due 10/2612014 Pf!fcent Of COller age Obtained> 90%: £)(8miner Level Ill' KlEINJAN, DAVID R e-tliner Lll"!!! NIA NIA OUlE!f NIA LE!\\-el NIA UT C<llibr.tioniExamiOOiion 59.24 Review~'tl Previous Dala: Yes Date I Revtewer 3/512014 Mall Welch, Ull Date 1 S~e Review NIA Date a/o~f Date Signature Date
COVERAGE PLOT 1 Examiner: Print name:.s 'frn.~-<d r 1.,,.,.{ Date: Date: Date: J
~~TEE Flow..~~
~~Pipe AXIAL SCANNING oo TRANSVERSE SCANNING 1" 1" ~ Area of no coverage 1:).7/5 b~~
~~SUMMARY~~
NO: 05054-ISI-BFN3 _jsm: BROWNS FERRY j Umtlt3 DESCRIPnON ITEETOPIPE !IDENTIFICATION* DRHR-3-19 SYSTEM 10: RESIDUAL HEAT REMOVAL SYSTEM L/1-I '/--039 Prepared By: 1AVID 1~/' Reviewer By: MATIWELCH Signature: ,1?, ~~ - Signature: ~t{~?v~ Date: tJ5,Affi7l m/77 Date: o/co//y-Items# 1 Axial Required Exam volume for scan 3 ((0.375+0.406)/2)"0.931" 58.5= 21.2680 2 Axial Required Exam volume for scan 4 ((0.406+0.352)/2) *1.254" 58.5= 27.8031 3 Clockwise and CounterClockwise Required exam volume on the upstream side (scan 5 & 6) ((0.37S+0.406l/2J*o.931.58.5= 21.2680 4 Clockwise and Cou nterCio~kwisc Required exam volume on the downstream side (scan 5 & 6) (10.406+0.352)/2)"1.254" 58.5= 27.8031 5 Axlal Obstructed Volume Exam for sc<Jn 3 ((0.375+0.406)/2)"0.931" 58.5= 21.2680 6 Axial Obstructed Volume Exam for scan 4 0= 0.0000, 7 Clockwise and Counterclockwise Obstructed Volume Exam on the upstream side (scan 5 & 6) I 0.2292.58.5= 13.4082 8 Clockwise and Counterclockwise Obstructed Volume Exam on the downstream side (scan 5 & 6) Q: 0.0000 9 Axial Obtained Exam Volume for scan 3 Item l-Item 5 = 0.0000 10 Axial Obtained Exam Volume for scan 4 Item 2 - Item 6 = 7.7.8031 11 Clockwise and Counter Clockwise Obtained Volume Exam on the upstream side (scan 5 & 6) Item 3 - Item 7 = 7.8598 12 Clockwise and Counter Clockwise Obtained Volume Exam on the downstream side (scan 5 & 6) Item 4 - Item 8 = 27.8031 13 Axial Exam Volume Percentage for scan 3 (Item 9/(ltem 1))"100 =% 0.00% 14 Axial Exam Volume Percentage for scan 4 (Item 10/(ltem 2W100::% 100.00% 15 Clockwise and CounterClockwise Exam Volume Percentage on the upstream side (scan 5 & 6) (Item 11/{ltem 3W100 =% 36.96% 16 Clockwise and CounterClockwise Exam Volume Percentage on the downstream side (s~an 5 & 6) (Item n/(ltem 4W100 =% 100.00% 17 Full Exam Volume Percentage combining in the Axlal, Clockwise, and CounterClockwise Dircetions (Item 13 +Item 14 + Item 15 +Item 16)/4 : '1(. 59.24% ~~ ~ ~ I c- ~ d I "\\I ~ ~~~ ~ /?~/? o-
THICKNESS AND CONTOUR Position 0 90 180 270 1 N/A N/A N/A N/A
2.
~~1.105 N/A 1.104 Nil\\ 3 1.062 N/A 1.073 N/A - -~~
4.
~~1052 N/A 1.022 N/A 5 1.092 N/11 1.087 I N/A~~
~~weld Edge WT WT DRHR-3-19 DRHR-3-19 WT 1"~~
1" 2.5" 2.5" lEE PIP!: SIDE FLOW -v WELD LENGTH: 58.5" DIAMETER: 20 Flow WT WT DSRHR-3-08 1 I WT DSRHR 08 WT oo L/1-)J./-tJ37 Pipe 6.5/tfotJLW 180° J
UT Calibration/E.xamination Site/Unit BFN I 3 Pmce:lure: N-UT -64/PDI-UT -2 OUtage No.: U3RF1G ~ Surnmr~ry No.* 05094-151-BfNJ Prooedure Rev.: 13/F Rer11rt No
~~UT {)27 Works cope:~~
lSI Code: Section XI 2001 Ed/2003 Add Dra.,.~ng No.: 3-ISI-{)330-C-{)1 System 10: 074 - Residual Heal Removal System Compollenl 10. DSRHR-3-0SA Worl\\ OrdE!f No. 114699848 Cat.litem: R-.A/R1.16C Location: DescriptiOI'l P. EL oage* 1 REACTOR BUILDING..ORYWELL of
£ -

j t---VJ.,)*f Stzellength:
24 I Thicllness/Dlammef: 1.219 / 24 limitiltlons* Access limited on upstream side StartTfme: 1657 Finish Time: 1740 Instrument Settings Search Unit Cal. Axial Orientated Search Unil Time Date Serial No.: E37688 Sem!l No.: OOFCYR Checks lnhial Cal. Calibration Signal s~ Sound Path ManulaclUref": KRAUTKRAMER Manufacturer. KBA 1417 3/312014 Reflector Ampl"ude o/o Division Model: USN 60 Linearity: l 002 Size: o.5~ Medel: CompG Inter. Cal. 1657 3/312014 1.5" Notch BO 6 2.057 Delay: 6.4972 RMge. 3.411 Inter. Cal. Freq : 1.5 MHZ Cente~ Freq : N/A Inter. Cal. M'U CaiNel: 0.1230 Energy: High Elcarn Angle: 45 Squlnr Angle: HIA Final Cal. 1741 31312014 Damping: 1000 Ohms Reject: 0 MP.a.~ured Angle: 43 MOde: Shear Couplant PRF Mode: Auto High SU FrEq.: 1.5 MHZ Exit POint: Min
~~of Eiernents:~~
Circumferential Orlontated Search Unit 1 Cal. Batch: 13C002 Oisp. Start: IP Rectify. Full WaYe Conlig.: Single Focus: N/A lnst. Freq.: 2.0MHz Ax. Gain (dB): 24.2 Clrc. Gain (dB): 24.2 1 Semen Oiv. ; .34 it1. d Sound Path Calibration Block Cal. Block No : WB-85 Thickness: 1.5 Ola.: Cal Blk. T ef"OP : 67 Temp. fool: Comp. Temp.: 88 Temp. Tool: Results: NRI ~ Percent Of Coverage Obtained> 90%: Examiner Level Ill' N/A 531993 531993 n Rl fJ 0 88% Type: Ullragolll Calibration Signal SWeetJ Shape: Round Contour: Flat Mfg.: Reflector Amplilude% Olvisioo Sonotech Wedge Style: NON-INTEGRAl ExamBacch: 13C002 1.5" Notch 80 6 Search Unit Cable Type: Ullragelll l)pe: RG-174 Length* 6 No. Conn.: ~ Ml. Sonotech g.. Scan Coverage Upslream6ZJ DOYmstrearnjv'f Scan dB* ~ Reference Block Reference/Simulator Block CW0 CCW0 ScRn dB: 41.3 Se~lal No.: Exam Surface: 00 Type* Surface Condition: As Found lltrasonic lndcallon Reoort I Info 0 Re..;ewed Previous Data* Yes Signature Gain Signal 93-5728 dB Reflector Alllplitude % SS Rompas 22.0 2" R Comments: E3768B Cal Due 10/26-2014 531993 Cal Due 10/26/2014 80 Swe!!p Oivisior1 6 Sound Path 2.057 Sound Path 1.488 Maclean, Duncan J. \\::5 _) f'r\\;~ '-\\.,_ Dale! Re111ewer 3/4/2014 Mat1 Welch, Ull P'k£wA~~ / /_ Date ~1/17'- Examiner N/A OtheJ" NIA Level N/A Le'oiel N/A UT Calib<alion/El(31Tlin<Jioo SJQnature Signature Date 1 Site Re-<iew NIA Date I AN II Revtew ---14: ** ~~.. d Fr,N,f Sgnature Date Dale J/lo It~
Component ID: Ds R I+ R O 9;4 /;_.? ~ l ~ n UT-!J./-oz. 7 E~aminer: ~ fl..--- R~viewer : ~ rc-~*tt /t_:~/c /._ *- ~ ___{~ - *1&rr-{ _ ~ COVERAGE PLOT Pnnt_name: "==> ~A..C..LE:-~- --...! Pnnt _ name~~~rTtl ct_~/-;1 Pnnt _ nam~ :..(4,. t.,.e/ ~--(./*'./ Date. -s _ '--\\ - *' l._\\ Da~e. 3/ 6 7'- Date.
~~s;1oj 1Lf~~
~~\\ \\ 2 7 0° ----7' Fl-ovv 1 ;~'( N ~ ('J '>(..~ tt ~~' 1~" c p s ~ IIR *1-1*,_.) /--_, t to'ru. 4S' . r~~
r.
~~l./5" tg n __.-+- / 7- / > ~ -~ / ~-- I _/ I ~- I / \\/ -~ - ff) ~F~~ ~ ~/:~ . H~~
~
L L I . 1 - --------.L_, / -L --...+/-.._~-~ - RE v : I'(- I. q -------;> l (. H -r . 4 5").;.1 =. Yo ~*L+ ) -? ~ ~~-~ l Cov~ "~ -1! II . -to w L I. q X 7~ 7S - 7i Jo A)<,'Ot/ S7 57. ~ 3 /o o 'o C. rc. ( O'V-< -r~ --t-0 b ~ q 1 1 heel V o L.t WI c : i7 ~ ...!. 2. . ~S' x: ,l 0, 0/ ~~ ~ fYa.Vl-1 Vc> I~ Wil..Ach:ev{'J ,3~ )('. 3 -7 '2.
~~_ 0, 0511)~~
~~, 3 X~~
*t ~ 'l
-= G. 0 (, ~ 2.. l) X 7 5. 7 S :: I 3. ~U., " ' (I b 5 c. v. y ul 3Lf '2 0 o, 1-b I '/ tJ
THICKNE' AND CONTOUR Position 0 90 180 270 I ~ 2.5" 2.5" 1 ,, 31 i.1.3 l*l.5' 1* 2./ ' 2* I. 1.'t /. l. 3,, 2-1 ld3 3 I.U i."H 1.3 r I. ').l. 4* /.~$ J.ltO '* y"' i.17 U/--J'/-oZ7 PTPtSIDE fL/3ClW SIDE 5 I* 'II ~.~7 t*IJ s-
~~t. } 'I~~
~~Weld edge Reviewer:~~
Print name: _,Af/J.1/tJEUII WELD LENGTH: 7£. *7~""* DIAMETER: 1 't 1" oo qoo l'600' ~ J l ').70 17 OJG2J 1
~ Ultrasonic 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 Work Order No.. 114699848 Page: 1 ~'f. of ___L_3..3 Code: Section XI 2001 Ed/2003 Add Cat./ltem* R-AIR1.16C Location: REACTOR BUILDING-DRYWELL Draw1ng No.: 3-ISI-0330-C-01 Description VLV - EL System ID 074-Residual Heat Removal System Comoonent iD TRHR-3-191 S12e/Length* 20 I Thickness/Diameter. 1.031 / 20 Llmital1ons. Comments* This report contains the Manu at Phased Array examination data. Results: Accept RejeCI Info Percent Of Co11erage Obtained > 90%. Re111ewed Previous Data: Ex.aminer Level N/A ~ Date
~~tJM-0 QJL~~~~
Date 3/1/1'1 Exammer N/A Other N/A Level N/A Signature Date Signature Date Date IANII Rev1ew J\\11..~ 1-t.;r
TENNESSEE VALLEY EXAMINATION
~~SUMMARY~~
AUTHORITY AND REPORT NUMBER: RESOLUTION DATA SHEET UT--!LJ -£Y3! PROJF.C'f RFI\\. UNTT: 3 CYCLE: 16 COMPONENT TD: TRBR-3-191 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 EXAMINER: EXAMINER: EXAM INER:
~~~~-~~~
LE\\'EL: 1I LEVEL: LEVEL: LEVEL: r:,~.-~ ~;;**. = ~~. ~. - -- -.-;.. * -~'?*- -;::!~ TRHR-3-191 is a dissimilar metal weld consisting of a cast stainless ~ree l 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-DMW-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. '\\ RESOLUTION BY: #ft-rr IUELLJ/ REVJEWED BY: /lf,.q-r-rwE2cl-! ANII~~,rift~ ~4/dd-.. ~IV~ DATE: J /o[t'1_ LEVELed££ DATE: 3/;?lf LEVF.L: ZJ.r' DATE:.ill_4 __ r G. '2-OF??
/ Component 10: TRHR-3-191 Reviewer: 7ft::t&z'/v}?~ I A~~ _ ur- !t/-o5; COVERAGE PLOT 1" 1" Valve Print name: #-4.rr ;~-t=l.LI.,) Date: 3)7 )L! Flow* A = (Machined) boss to interface B = U/S Weld toe to interface C = Weld crown width D = Buttering width ___. Date: Elbow 0.400 D oo 1~/3?
THICKNESS AND CONTOUR 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 5 1.195 1.196 1.239 1.130~~
~~w eld Edge Examiner: e:::-~~
Print name~D FISH Date: COMPONENT 10: TRHR-3-191 CROWN WIDTH: 1.2" CROWN HEIGHT: FLUSH VALVE 1" 1" 2.5" VALVE FLOW....___,/ Reviewer: Print name: ct. 2.5" ELBOW SIDE WELD LENGTH: 62.8" DIAMETER: 20" Flow ---+-1------ oo goo 1 270° l.//-!l-c;5; ELBOW '7/3'.?
COVERAGE PLOT
~~SUMMARY~~
~~Component ID:TRHR-3-191 L/T-Jt./--031 £...(...__ 7 -:-T-7 Examiner: Reviewer: ?-'~Lfv,--?th ....r/tr-- Print name: ED FISH Print name: MAn WELCH Priht name:...n.....,,.(~ Date: 2 1 (£()~~
~~).o 1 c.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% Procedure required examination volume achieved-43.3% Full volume thickness, 1 12" beyond weld toe on each side of joint Refracted Longitudinal wave mode, axial scan direction-14 7% Refracted Longitudinal 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 Examination volume RIL= Refracted Longitudinal Axial Scan direction= upstream and downstream Circ Scan direction= Clock wise and Counter clock wise /.f/37 ~
Component ID: TRHR-3-191 \\ (!),.s UT-!'/-o3/ ~~-----.=----:---~""7'7--~ A . ~u ~ =j int name:.,('~.... '-1'~ f!?o,k( Date: J/ff,l/!;t' Valve Flow.. Elbow D R/L. V~t..L)~t .f--8 SHeA~. Vt.u.H*it" L------------------ ~ f~l oo 1"1~ /9/33
1*8 Component 10: TRHR-3-191 -~ UT-!t./-rJ3 J t..=..:..:=.:..:..:..:.:...:..:::.:.:.__~~=-:-~~!.-----t...:..R.:.::e-=-v:....:: ie....:...:w:....::e,;-:. r:_7_<<_z~ _v _:r ..:..-,'i-t_,k?';.L A * ~ ~ Print name: H8 TT 11/c--zLll Print name: Pw_r __ Date: 3/7 j!::J__ _ _ Date: J> lb/1~ _ COVERAGE PLOT
j f

(~.-CJf/5-r; ~,'( ;,~.3s).;-z)y. ~:,z.e';. / &:,?
I DEV rei'-~ ;t-~.e-t,~s :; ~~/Jr.f*. ~ ~, ~ 9. ~
~~~~ *~%~~~
~~/t;tt~ "5chc1' ~d.r.,.J't/y,/ Valve Flow a. Elbow if? <I 0~~
t!J ;;s

-----~~~-------
oo 1" Zc:J/33
\\*1 Component 10: TRHR-3-191 UT-I l/-t:J 3; Examiner: Print name: Ed Fish Date: 21 FEB 2014 Reviewer: - I Print na~7~~ ~-, t,. /,.v.. -7' Date: - //'/~ - )2/L. IJYJ$f' ~ ((,3J<. SB) -;-z,) ~o /,z.e = '7.1fu fl/L-- 081--. I 'iB -~. 4 ~ ~ 'f. 3"1 j1t/, ~ ~.lo?j.: t. 3./1, . Valve Flow.._ Elbow c2y';A./ ?~ A!u.tt~l11"11 goo '1' 1"1 ~ 1
( ) 1 - * *-* * *.. *-*
c~
~~- r "='=i' Reviewer: . r. I Print name: #,qL L hlcl.£:::AI~~
~~-~.

~~........ I 1
~~1 Date: 3/7 -?t.L ~~~
~~_L,....;___ _____ _~~
~~( IJQ\\<;i, (/1//Ji' R/L o/!J!.T =((": 3 -a x.&.5)-: z) x /d,8 ~ (p/i1J P../tr o£1/ -:. 11. t -t,. ~ 7 :: ~*zr/; y, ~ ~ ~!1 ~ ~ * '1% Flow.. Elbow~~
~~. /~~
~~Valve c:fp./.U SU:Ut- ~ncnt --~ 1" ~~~

~~1800~~

"'r- -z~/?3 ,,~
Component to: TRHR-3-1 91 Reviewer: ~~~ IJ}T-/<z/-1?:3/ Print name: #-?7T WEt-C!l Dale: 35/T/Ilf R/L tJ~'S/:;; (r, IB'x I '3fs)~t ))( ~z. f3 =- z I 1~ * ~f,oEY =- 1 J./1~ -l*JS -::; JZ.~P~/ !'-/. B ~, &'55 ::: gs,s% Valve Flow.. Elbow t/2f.t ~ '5Uut du-u !ton 270° 1 II 1" ,,b
Examiner: 'Print name: Ed Fish Date: 21 FEB_2014 l?tREV:: )~8 1" 1~ 1" ,lft o~sr u£L. ~*~/ /?l/2c.=?/7{11'/ ~ ~~~~ Valve Flow.. r------ ~.$ ?.J ' * ?S/l /pz..rr ~ ~ *~ ~ ~~~ *8 Elbow oEV ~ lfL!. 3 7t' oc z'l/??
Component 10: Tf3tlR-3-191 '-/~-cl3/ A PHnt name: ::.S ~~..:e~:t=/..:u(" Date: .J t0 o;c /f5MF I?E'/ ~11Eitf2 ~~;, tJ~?'/: ((. ; s ~< cn) r- ((. J7~. ;4);, z):~. f4.B- ~ 1~,q11 f£V ~;;q~/z1,11P-:. tre 1" Valve Flow~ Elbow i?-!3/c ~ad AUitJ'W C."'SS ' ~!~.~.~U- ?~ cl ;,.u_, fic?t s oo fiZ-s/7? 16
COVERAGE PLOT Examiner: Print name: Ed Fish Date: 21 FEB 2014 ~uduu,., ~Ev' :. l ~ /.f3ni ; Valve Flow.. Elbow ~Itt( ~e:v :: / 3;, e - r.:,~.q.; ~ ~~. t?" D f<L VD!--VMt II1ll11 "714i;M~ \\JDUJH 1" 1" I oo
~~~~~~~,~------~R~e-v~ie_w_e-r:~-~?7o*~~~w~~~----.. A~':--r~r~~ t~v Print name: Ed Fish Print name: J4/?7T;, 'ELCH Print name :...__r;a""' ~J/R~/"~~
~~Date: 21 FEB 2014 Date: ~r/¥ Date:~~
~~r /'rt-*;}~ _~~
~~R/t-XG'V:: (p~CJt.IJIJ ~ ~rA.I ~ ~at* t c-It u CMJ~~
?i cdSr.

= Sf.IB 1
~~~o~ 3 Valve Flow* ((/.o~/.'1)~ z_) -(tt.l-b )J< bl ~ = S /./8 R/L oEY::: ".s. 7'1-t;/.1 g :: It/. 7t,/c, 5.<fy =, z r-L/ = zz. 'f% /,0 1~ \\~....~~
r
\\ ~ ~ {5.v. ~5) -;-f: :, ('5lS 1" J... /::! .c ~* ~ - L' ,... :;;: L',;;:> r * :._ * -.:. - /) 17 "" t£. t.b ~ (}./:J 5 1" ~- Elbow ~ OBS/RVC..TC[) ~ I)Ot.,tJHE 270° /.6
Reviewer: - *Print name: ;W.17-7T 11/62271 Date: _:::1?1',d¥ I'~ Re-v': (;.5,t:f¥,, :1 ~da/ '$CA.H d~c trr.:..,, ~'- O/?.:$T-; S7,Cf 01 ~ Valve Flow_. ({t*OX' Z*l)~l)"" '(~Arb)~ {pf, 8-;: t?1,t} I R/t OEV-= t,5.1~-SJ.1=- &'*oti/tpS.1if :::, /zz -=-/z.z.% 1" 1" /,~ C:S5 1*' J ~ = (3 x. 3SJ-z.. -- o 5t7 p;. (_. 3.., ~)~z.. -:: . ()"].!. tt, t-b ; r /"t-7~ Elbow oo ~ o6'11R\\X.T£'P ~ VOW)Mt

~~hf:?,IL--Z:J/3'3 f/r~~

Component 10: T HR-3-191 ~ /~_.... - / - Y-o3/ Examiner: ZV --:-/-v~ Reviewer: 7/t:T'C"-Cr~ -= Print name: Ed Fish Print name: /f?_,stff ~~ Date: 21 FEB 2014 _ Date: _ ~1t~-____ _ .<ji K'EJI: &,>.<tr~n 3 ~"-' ?CAAL cltuchl'lt ~ OBE>/1< ucrrv ~ Vot..uME K/L o5sr-:- t5.7.7 Valve Flow / ~ ({!toKZ*!);z){~fb)x t.z.& =- 57,7 R/L-oEV.., (p~. 11-S7* 7..... ~.J. +/~~.r.J ;-.. z.~., = 12 5 ?u 1" ~ 05
,/
~~Z* 1 a_-; (55; Z!))...-2 ~. 0~~ b: ( Z.S>' 7)"7"2~~

~~o81S c;..r-b-::: 0*131 $~~
Elbow goo Z9/?3 /.7
i Component iD: TRHR-3-191 /. /;j-o3/ I R-e-vt,..-*ew_e_r_: -A'?":zr:?,s~.,..~~~ A b; ~...,../ Print name:.J747r!AlE/L/-I Print name:~ .. -::ev Pvoc( Date: ~7 /1-' __ pate: _ .3/1'~<7 X/L kll= ~5~'7~ ~tA/' ~u:t*~rt. G-lc ftc.h/'7-t R/L Ol35r:. s8,Z.$ Valve Flow.. {(;,o-sx;,&J)~z.) -(a.+b) J uz.g-= S8. zs R/'- tJE v :- to ~~C1 'I-~~~~ 7/ h'tj &,'S.C-J1:; I 117 -= //1 7 (c. (.5.5 1" 111 ~ ~/ \\~ e:::L. -;(~"~' z.)~z. -~,o; p ~(zy t~)-z =-.o+ A- 'f-P-. I 07 ,..}
~~. \\(~~
~ OBSTRUCTtD Elbow ~:j VuLUH.£ - -----:j8Qo _, 3o/33 /,,
COVERAGE PLOT ~/t-P[V-=- ~ 6.'r'i1n 3 (}M.c, ~+v-d.t.~ue;~:,., ~/L 06Sr ~ ~?.,;117
~~Valve Flow..~~
i:,G. qt{~* [_b.;-<l*~'_.:,t)x. t/)1'. t,z,s;:. /?.tt-/~P'5,1i~.zD' ~ zo.q;~o -f -- 1* 1 -t z,5 ~- j .'t I r---t-*1 1" rint name: --s:4;-,.,., 44-1 Ne~ur Date: _!Lu~ Elbow ~~ og7~TFD ~ v'ct.tJMt oo
COVERAGE PLOT 1 Examiner:.?4:Z~ 1 Reviewer: 1 ~ ~ / 1 Print name: Ed Fish A ::n* Date: 21 FEB 2014
~~5/r..t.a.<. /<EV:: ~1-t'",, 1 ~P.I ~~~
d1tr'r lrt s.~ oiJsr; L/l*'t0111-s Valve Flow.. ~ 5, ~b -{a.rb~c) ~ L.//,bB *
5~
~~t}t; V ~ tJ,£/tJ e( t:,~ V' ::."~/el 7 ::- ~ t.~~
7%
~~~7~ 1" 111 rJ ~== (~x.,)+z ~.to$ b :;;. I ~I( I 'i =:~~
~~z'{~~
L ~ (.sf )1, Z) ~,: -=-. D t1 A,- b t-C- :::..1t:t5 >< ~z. B =- 2t/,18 Elbow ~ o~?TRUt,TCD Vot-LJ,..{ E" oo
COVERAGE PLOT Examiner: Print name:~ EO Fish Date: 21 FEB 2014 5)te~ REV-= /:,S, ~6'" 3.eu.L-- ~.(.{ ~~~~J -?)"-~ OISS r ~ '$t'17,~Valve (.~ +-b )x (pz,8 =r-3~t!!f 7M 3 Flow.. Component 10: TRHR-3-191 - =-;tJ-o3; Print name.:.f o< h,t.-. ~r" Date: Y//~
~~Elbow 6~~~
~~0 '1 -:. &:.S.it,.- ~z.-17 ~ 32' * ~<f/ ~5, &, ::.*'19q =t 'f?,Cfro ~ D P;,$""71? LK-T£"P VOl.-lJMt c:s? .~, tl-,4 oo~~
~~o. ::. f,o~x. z ~ =. Zt,--z,..~~
~~b :.. ql {) ~ y ' 5).,;. 2 ~~~
~~z b 1-1"~~
.a.. -rb ::., sz s
UT Calibration/L.. amination Slle!Unlt: BFN 3 Procedure: N*UT -64/PDI*UT -2 Outage No.: U3RF16 Ul] Summary No.: 01819*1SI*BFN3 Procedure Rev ; 13/F Report No.: UT-14-036 WOfkscope: lSI WC(k Order No.: 114699848 Page: 1 of J ~~;: Sec XI 2001 Ed/2003 Add CaiJitem: B.J/89.11 Location: REACTOR BUILDING*DRYWELL
~~3. ¥I t(-~~
Code: Drawing No.: 3-ISI-0332-C.01
== Description:== TEE - VL V System ID: 069 - Reactor Water Cleanup System Componoot 10* RWCU-3..001..070 s lzell eng Itt: 6 / Thickness/Diameter; 0.432 / 6 limitations: Single sided exam, see coverage plot page for details Start Time: 0843 Finish Time: 0850 - ~- Instrument Settings Search Unit Cal. Axial Orientated Search Unit Timo Date Serial No.: E37688 Serial No.: SH0104 Checks Initial Cal. Ci!libralion Signal Swe~ Sound Path Manufacturer: KRAUT KRAMER Manufacturer: GE 0746 3/5/2014 Reflector Arnplituue% Division Model: USN SO Linearity: L-14-002 Size: 0.375" Moo a: CompG Inter. Cal. 0843 3/512014 1" Notch 80 9 1.343 Delay: 5.8291 Range: 1.5 Freq.: 1.5 MHz Center Freq.: N/A Inter. Cal. Mtl CaiNe!: 0.1219 Enef9Y: High NIA l11ter. Cal EU~mAngle: 45 Squint Angle: Damping: 1000 Ohms Reject: 0 Final Cal. 0850 3/512014 Measured Angle: 45 Mode: Shear PRF Mode: Auto High SU Freq : 1.5 MHz Couplant Exit Point: .4
~~of Elements:~~
1 Dlsp. Start; IP Rectify; Full Wave N;;- Cat Batch: 13C002 Circumferential Orientated Search Unit Ins! Freq.: 2.0 MHZ Ax. Gain (dB): 26.2 Circ. Gain (dB): 26.2 1 Screen Div. = .15 ln. ol Sound Path Calibration Block Cal Blodl No: WB-84 Thickness: Ca Btk. Temp.: Con1p. Temp.: Results: 1" Dia.: 68 -- T 00'4l* Too: 76 Ternp. Tool: (s) NRI ~ Percent Of Coverage Obtained> 90%* Examiner llml m* NIA 558272 558272 n Rl 0 li(l 48.8% Conflg.: Single Focus: Type: Uttragel It C..,ibration Signal Sweep Shape: Round Contour: Flat Renee tor Ampliluda% DivisiOn Soond Path Mfg.: Sonotech Wedge Sty1e* Non-Integral 1" Notch 80 9 1.343 Exam Batch: 13C002 Search Unit Cable Type: Ultragelll Type: RG-174 Length: 6 No. Conn
~~0 Mfg.:~~
Sonotech Scan Coverage Upstream l!l 0o-Nnstream0 Sr-.an dB: 46.2 Reference Block Reference/Simulator Block Gain Signal Sweep CW0 CCW 0 Scan dB: 46.2 Sefial No.: 790398 dB Reftecfor Amplitude % DiVIsion Sound Path Exam Surface: 00 Type: SS Rompas 23.0 1" R 85 6.5 .999 ~ *
rlt\\l"'.o l""l"\\l"'liilii'V1

As found Jltrasonic Indication Reoo-11 Info :=J Reviewed Previous Data*
~~Yes Comments: 558272 Cnl Due 1/25/2015 fFP ~37t38e 1012612014 Signature Date Reviewer Maclean, Duncan J. ~ 3/4/2014 Matt Welch, Lilt ~~~~~ ~~~
~~Date~~
~* 6;1/~ Elealnlner Level N/A Signature Date SkeReview Signahlfe Date N/A NIA ' - ) Other level N/A Signature Date ANI! Revew Slgnafure Date N/A -.S'~..... d.L£!,; t9 ~1 l &. -.it. " . 3f_t li.rlf C-.--* ---***--**~--- _X.(.v-.. <... UT Calihration/~xamnilloo
COVERAGE PLOT Examiner: l~ 'i:Ac.____ Print name: -~~-<'-c.t..... o -- Date: ~ ~ - 1 '-\\ KE:Q\\_11/Z0 il.. X I A L E )GAl\\'\\ '\\ H vv .l-X I, IC.
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~~. o, l 2 Component 10: R \\N c. U - s - o 01 - o 70 J-Jr-,;;; -~l3f::~~
Reviewer: / 777lc /?t' /7~--.::. Print name:/' 'li/Tit ;_?~'-' Date: 3-1 ~ .. 'it-ANII: ~ w 'V '-l,lr--cf I Print ' Date: 9o" fL OW 4 5 :> t.b" to'~L 1.,<->,..~L I _ I \\ ~ I \\\\'~ - "_*-.: I.:_ _ _j_J-v------- / ~CJ;:;<v
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THICKNE:..,.., AND CONTOUR Posi1ion 0 90 180 270 1 L.57.77 I
2.
~~N/.~~ *.sr fill 3~~
~~(, 5~~
~~-/A-rftL ' $'f~~
4.
,Cjg 'S/ 5 ). 0 ~ . ~(, I '--*Weld edge 2.5 )'w HP SIDE (;-L r-I 2 5" IIA LAfSIDE Lll.Jt/ -(J.5r;, FLOW Y Weld Centerline 1-;E=:x~a::-:m=in::-:e::-:r::-: --:b::::,
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~~~ ~~~
~~Print name: ""l::)-:l ""' ""c t::CA.:--.1~~
-;-c, **4Date: I Print name: ;tf;J :rl ~*t ~u J.f-Date: 1. ............. ~ * * ~'~"".. '... 1 COMPONENT ID: R we L{ - s-VO' 1 -O?o CROWN WIDTH: ,, cJ" a WELD LENGTH: zl ;;_ 5' " CROWN HEIGHT: _ F/ us/, DIAME.::._T.::._E.::._R_: ___ t,_c,_;__s-_' _________ 0(1 1o* ~ ~ /be'"... )_/l)c~ / -~~ ~~~--------- -?1 #71-v
[i!i]* UT Calibration.mination Sate/Unit. BFN 3 Procedure: N*UT-76/PDI-UT *1 Outage No.. U3RF16 Summary No.: 06000-ISI-BFNJ Procedure Rev.: 9!E Report No.: UT -14.001 WorkscqJe. PSI Work Order No.: 113331815 Page: 1 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 CompooentiD:~~
HPCI-3-019..018 Size/Length: 10" Thickness/Diameter: .59411 0" ~-------------------------------------------- Limitations: No exam on the flange side due to configuration Start Time: 08:35 Fanish Time: 09:35 Instrument Set1ings Search Unit Cal. Axial Orientated Search Unit Time Date Serial No.: E37690 Serial No.: SE1640 Checks Signal Initial Cat Calibration Sweep soond Path Manufacturer. KRAUT KRAMER Manufacturer: KRAUT KRAMER 08:30 21412014 Renector Amplitude% Division Model: USN 60 Linearity: L-14-001 Size: .5 Mcxlel: CompG Inter. Cal. 1.0" NOTCH 80 7.2 1.44 Delay: 8.8697 Range: 2.000 Freq.: 2.25 MHz Center Freq. NJA Inter. Cal. M'll CaiNe!. 0.1276 Energy: High Squint Angle; NJA Inter. Cal. Exam Angle* 45 Damping. 1000 Ohms Reject. 0 Final Cal. 09:43 2/412014 Measured Angle: 45 Mcxle: Shear PRF Mode: Auto High SUFreq.: 2.25MHz Couplant E/Ut Pant: .5
~~of Elements:~~
1 Disp. Start: IP Reclify: Full Wave Nl-,;:-- Cat, Batch: 12H130 Circumferential Orientated Search Unit Con fig.: Single Focus: lnst. Freq,; 2.25 MHz Type: Ultragelll Calibration Signal Sweep Soond Palh Shape: Round Contour: NIA ReRector Amplitude% Division Mfg.: Sonotech Wedge Style; Non-Integral 80 1,0 Notch 7.2 1.44 Ax. Gaan {dB): 24.6 Care. Gain (dB): N/A ~Batch : 12H130 Search Unit C;~ble 1 Screen Div. "' .2 in. of Sound Path Calibration Block CaL Block No.: S0-115 Thickness: 1.003 Oia.: Cal. Blk. Temp.: 51.8 Temp. Tool: Comp. Temp.: 51.8 Temp, Tool: Results* NRI 0 Percent Of Coverage Obtained > 90%: Examiner Level IW KLEINJAN. DAIIID R Examiner N/A Level NIA Other N/A Level N/A UT Calibration/E~CWT~ination FLAT E39055 E39055 ~ Rl 0 No Type: Ultragelll Type: RG-174 Length: 6 No Conn
~~0 Mfg.:~~
Sonotech Scan Coverage Upstream~ DownstreamO Scan dB: 48 Reference Block ReferenceiSimulator Block cw~ CCW 1-lJ Scan dB: 48 SE!fiaNo.: EQm Surface: 00 Type: .C::11rf""" r.nnrtllinn* Ground Jltrasonic lndicaticn Report.) Info 0 Reviewed Pre~ous Data: None Signature Date I ReiiiE!wer 2/4/2014 Matt Welch, Llll D<ie I S~e Review Date Gain Signa 92-7615 dB Reflector AmPlitude% CS Rompas 24.6 FSDH Comments; E37690 DUE 811412014 E39055 DUE 6/2412014 ~?t/.dU_ Signature Signature 20 Sweep Division 5.2 Sound Path 1.08 Date Date
!suMMARY NO: 06001-ISI-BFN3 I siTE: BROWNS FERRY Unit 113 !DESCRIPTION I PIPE TO FLANGE IIDENTIFICA TION: SYSTEM 10: HIGH PRESSURE COOLANT INJECTION SYSTEM Prepared By: Reviewer By: MATI WELCH Signature: 4"a.u---z;J~ Signature: Date: Items II 1 2 3 4 5 6 7 8 9 Axial Required Exam volume 34
~~1.670. ((.214+.230)/2)=~~
Clockwise and CounterClockwise Required exam volume 34 " 1.670" ((.214+.230)/2)= Date: Axial Obstructed Volume Exam 0= (Coverage was achieved by scanning across the weld) Clockwise and Counterclockwise Obstructed Volume Exam 34".434.((.214+.230)/2)= Axial Obtained Exam Volume Item 1 - Item 3 = Clockwise and Counter Clockwise Obtained Volume Exam Item 2 - Item 4 = Axial Ellam Volume Percentage (Item 5/(ltem 1))" 100 =% Clockwise and CounterClockwise Exam Volume Percentage (Item 6/(ltem 2))"100 =% Full Exam Volume Percentage combining in the Axial, Clockwise, and CounterClockwise Dircetions (Item 7 + Item 8)/2 =% HPCI-3-019-018 12.6052 12.6052 0.0000 3.2758 12.6052 9.3293 100.00% 74.01% e 87.01%
e e e 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 _ _ _ COVERAGE PLOT 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
~~weld Edge 82.5" l-PIPE FLANGE~~
~~__ SIDE Position 0 90 '180 270 1 NR NR .630 NR~~
2.
~~NR NR ,646 NR~~
~~i NR NR~~
~~.671 NR 4* NR NR .676 NR 5 r-- ~ _NR NR NR 2.5" t.fr-J 7--co) FLOW ~ Weld Centerline Examiner: J)-?~ Reviewer: -~~~
~~~-.---~~
, A-N-ir;;Z -* --/-,~VI- ' ~---,:Je,;_ -e:= 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" CROWN HEIGHT: FLUSH Valve Flow* 0 ('(') 180° (0 1" WELD LENGTH : 34.0" DIAMETER: 10" ct ('(') 1.{) 1'-- (I') (0 T"" N -.;t (0 (0 co Pipe (0 (0 p~?/5
UT Calibration/.mination Site/Unit: BFN 3 Procedure: N*UT*761PDI*UT*1 Outage No.: U3RF16 ~
~~Summary No.:~~
06001*ISI*BFN3 Procedure Rev.: 9/E Report No.: UT*14*002 .t7 t;;;1( Workscope: PSI Work Order No.: 113331815 Page: 2 of 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: HPCI*3-o19-o19 Size/Length: 10" Thickness/Diameter: .594/10" Limitations: NO EXAM ON THE VALVE SIDE DUE TO CONFIGURATION Start Time: 08:35 Finish Time: 09:35 Instrument Settings Search Unit Serial No.: E37690 Serial No.: SE1640 Manufacturer: KRAUTKRAMER Manufacturer: KRAUTKRAMER Model: USN 60 Linearity: L*14-o01 Size: .5 Model: Delay: 8.6731 Range: 2.5 Freq.: 2.25 MHz Center Freq.: M't1CaINel: 0.1275 Energy: High Exam Angle: 61 Squint Angle: Damping: 1000 Ohms Reject: 0 Measured Angle: 61 Mode: PRF Mode: Auto High SU Freq.: 2.25 MHz Exit Point: .5
~~of Elements:~~
Disp. Start: IP Rectify: Full Wave Config.: SINGLE Focus: Ins!. Freq.: 2.25 MHz Shape: Round Contour: Wedge Style: Non*lntegral Ax. Gain (dB): 38.0 Circ. Gain (dB): N/A Search Unit Cable 1 Screen Div. = .25 in. of Sound Path Type: RG*174 Length: 6 Calibration Block Scan Coverage Cal. Block No.: SQ*115 Upstream 0 Downstream ~ Scan dB: Thickness: 1.003 Dia.: FLAT CWO CCWO Scan dB: Cal. Blk. Temp.: 51.8 Temp. Tool: E39055 Exam Surface: 00 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 Percent Of Coverage Obtained> 90%: N Reviewed Previous Data: None Reviewer Date Examiner Level ure Date III' fW~ture Matt Welch, LIII KLEINJAN, DAVID R 214/2014 9f~~~ Site Review Signature Date N/A N1A Examiner Level N/A Date Date Other Level N/A Datel ANII rview ~ture N/A ~~~ ~J;;.c .u--::k.JLJ .;</oMI~Cf UT Calibration/Examination Cal. Axial Orientated Search Unit Time Date Checks Calibration Signal Sweep Sound Path Initial Cal. 0824 21412014 Reflector Amplitude % Division CompG Inter. Cal. 1.0" NOTCH 80 7.4 1.854 N/A Inter. Cal. Inter. Cal. N1A Final Cal. 0950 2/4/2014 Shear Couplant 1 -- Cal. Batch: 12H130 Circumferential Orientated Search Unit N/A Type: Ultragelll Calibration Signal Sweep Sound Path N/A Reflector Amplitude % Division Mfg.: Sonotech N/A Exam Batch: 12H130 No. Conn.: 0 Type: Ultragelll Mfg.: Sonotech 59.0 Reference Block Reference/Simulator Block Gain Signal Sweep Serial No.: 92*7615 dB Reflector Amplitude % Division Sound Path CS Rompas Type: 38.0 FSDH 60 5.8
~~1.4 Comments~~
E37690 DUE 8/14/2014 E39055 DUE 6/2412014 Signature
2 5 4 3 6 1 7
~~ISUMMARY~~
NO: 06001-ISI-BFN3 ISITE: BROWNS FERRY I Unitlt3 IDESCRIPTION IVALVE TO PIPE IIDENTIFICATION: HPCI-3-019-019 Items It SYSTEM ID: Prepared By: Date: Reviewer By: Signature: Date: Axial Required Exam volume 34*1.648*<<.297+.208)/2)= 14.1481 Clockwise and CounterClockwise Required exam volume 34*1.648*<<.297+.208)/2)= 14.1481 Axial Obstructed Volume Exam (Coverage was achieved by scanning across the weld) 0= 0.0000 Clockwise and Counterclockwise Obstructed Volume Exam 34*.729*<<(.297+.208)/2)= 6.2585 Axial Obtained Exam Volume Item 1-Item 3 = 14.1481 Clockwise and Counter Clockwise Obtained Volume Exam Item 2 - Item 4 = 7.8896 Axial Exam Volume Percentage (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 ANII:~~
Prin Date: UT-Iif-(}(jZ-Reviewer: Print name:,MA-ffI1IEld/ Date: Z~?ft¥- Print name: Davfd Kleinjan Date: 04 FEB 2014 Examiner:.. ~., Valve Flow.. Pipe Axial Scanning 60' 45' D Area of obstruction Transverse Scanning 1" ~ Area of obstruction 1 11 fJtj Lf1:3 ~
Jif-eoz, THICKNESS AND CONTOUR Position 0 90 180 270 1 NR NR NR NR 2* NR NR .799 NR 3 NR NR .748 NR 4* NR NR .627 NR 5 NR NR .630 NR 2.5" 2.5" VALVE PIPE SIDE
~~Weld Edge FLOW~~~
~~Weld Centerline~~
~~.n.,~~
Examiner: d.//."j"- ~. Zltfller I Reviewer: Y~A/"'/' /..f 2;/,/9'//~ I AN II: Print name: DAVIt>(tLEINJAN Date: I Print name: #hrrPvf:u:::.;/- Date: COMPONENT ID: HPCI-019-019-CORO CROWN WIDTH: 1.15 11 WELD LENGTH: 34.0 11 CROWN HEIGHT: FLUSH DIAMETER: 10" .....~~/:..u; .Y I Print name: G,,J "J---IAJ,;;r Date:2/.:tJ1 ~ Flow.. Valve Pipe ct <.0 ~ co 0') - co co o 0') ('f) ~ C\\J ~ 180 0 <.0 <.0 <.0 1 11 1" j>J~/3 \\l
[ii1 nation UT Cali"'...... :.... ~ Slle'Unit: BFN I 3 Sum1Tl8ry No.: ()538S.ISI-BFN N-UT-76 Outage No.: U3RF15 ReportNo.: UT-12-046 Procedure: Procedure Rev.: 7 Wo~: PSI WOtk Order No.: 113331595 Page: 1 of 2 Code: Sec XI 2001 Ed/2003 Add CatJitem: &oJ/99.11 Locallon: REACTOR BUILCING-DRYWEU Drawil"o No.: 3-ISI-0332.C.02
== Description:== PIPE-REO TEE System ID: 069 - Reactor W.ter Cleanup Syatem Component to: RWCU.3-007-003 Size/Length: 4 / 14.25 Thlekness'Diameter: 0.337/4 Umitations: YES-PARnAL SINGLE ~DE ACCESS ON TEE-SEE COVERAGE PLOT Start Time: 0930 Finish Time: 0945 Instrument Seltfngs Searc.h Unit Cal. AJdal Orfea~tated Search Unit Time Date Serial No.: E33669 Serial No.: OOF62P Checq Cal brat! on Signal Sweep Manufacturer: KRAUTKRAMER Manufacturer: KBA Initial Cal. 0910 4129f2012 Reflector Amplitude o/o Division Sound Path Model: USN60 Linearity: L-1HJ07 Size: 0.25 Model: CompG Inter. Cal. 0930 412912012 0.5" NOTCH 80 4.0 .705 Delay: 3.5247 Range: 1.783 Center Freq.: Inter. Cal. NA NA Freq.: 5,0MHz NA Inter. Cal. NA NA M'tlCaVVel: .1275 Energy: High E!Cam Angle: 45 SqUint Angle: NA Final Cal. 1021 4129f201 2 NA Damping: 10000hms RejeCt: 0 Measured Angle: 45 Mode: SHEAR Couplent NA PRF Mode: Auto High SUFreq.: S.OMHz Exit Point: .35" tt of Banents: 1 Cal. Batch: 11425 Circumferential Ortentated Searcfl Unit Disp. Start: IP RecUiy: FuD Wave Config.: Single Focus: NA lnst. Freq.: S.ONHz Ax. Gain (dB): 28.6 Clrc. Gain (dB): 28.6 1 SaeenDrv.= .178 ln. of Sound Path Calibration Block Cal. Block No.: SCH19 Thickness: 0.5" Dia.: Cal. Blk. Temp.: ~ Temp. Tool: Comp. Temp.: ~ Temp. Tool: Results: NRI ~ Pet"cent Of C011e1age Obtained > 90%: ExarMler l.eYel Welch,Nat1hew C. Examiner l.eYel NIA Other WA Le.e UT calibnl~llon UI-PDI NIA NIA FLAT 558275 558275 0 Rl 0 Mo ~ Type: Ultragelll Calibration Signal Sweep Sound Path Shape: Round Contour: FLAT Reflector Amplitude% Division Mfg.: Sonotec:ll Wedge Style: NON-INTEGRAL O.S" NOTCH 80 4 .705 Exam Batch: 11425 Seereh Unit Cable NA Type: Ultragef II Type: RG*174 Length:..!.. No. Conn.: 0 Mt
~~NA Sonotech g..~~
NA Scan Coverage Upstream !Ill Downstream !ilj Scan dB:~ Reference Block ~rencfiiSimulator Bloctc Gain Signal Sweep cw~ ccw~ Scan dB:~ Seria No.: 5100 dB Refleclor I_AfnPjtude 'Yo DMsiat Sound Path Exam Surface: 00 Type: Rompu 36.8 FSDH 50 5.6 1.D03 Surface Condition: Flutih NA NA Info 0 Aepolt.) Comments: E33669 DUE DATE8115112, 558275 DUE DATE 12*10.12 Reviewed Previous Data: None ~te I R~Me.o.er >.lith< Z.IP,E-UJl Signature Dalal Site Review Signature Dale h ~ lgnature Signature f', ~~) Date qf1-IJ;. Date Date 5/J/12.... ' ~ I 0 a f\\S'*, ~
PLOT Examiner: Print name: MA1T \\tJ£1£1-{ Date: ~z..l Reviewer:.ss: ~---- Print name: Date: (/',h,;) //-r.- Component 10: RW~U-( .... 001-00 3 u-#~;rz... AN II: Print name: dJf~ ~;,.A1,!-';, Date:.>/111.,_ l¥QuriZEJ2 ~MM ioL.JJ~L 3*~11N ~ [{(~11-t~z.t}.;.ri-);1(. 1~~))( 1'/,15 ~ r IJ~O t"><AM \\}ouJMf. '; ZclZ, IN ~ /5% gs%
~~oB~~TEt> ~altlfA4E-== IJ7%~~
(1¥*'l-S* "f*7S) ~ /Gf,zS ::-,1:11 ~ A1JA~ ~ e /~- ild::: hi;,~ ' ~f ~G eft~ ~ I ().fi -'5l*t, -;If?. 'f (!oe,?Jt 'fr. If)-+ z== ~r-es ~ ~* ~ \\ ~~ ~0 v~, ~ ----~ - ~~ -- _f\\~ ___ _ _ f;;: --~' /.D.. 0.1~ r~-~ f
~~z..~1"~~
~~/.1). 0 ~At>Jf. oo Q,~ o~a.*..t~~
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~~d.U" ~-& 11#" ~ r _,,.._. ...J...,1,_+ I*"JP o* ~.w 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<WaJ-lr001-0// 51fow1J {:'()tt ~EFcKEI\\JCE" p~ 3~) w 0 Q{)
THIC AND CONTOUR Position 0 90 180 270 ~ 2.5" ~- 2.5" 1 / 2"' I</ \\jtd_stDE 3 /"".. 4* v n 'Pl~SIOE 5 /
~~Weld edge FLowL::)~~
Weld. Centerline Examiner: WELD LENGTH: 14-* Z5 DIAMETER: Lf, 53 ([) WaD RWC.u-t-oo7 -011 ~;laWN~ Re!="Ell~ '"J' ~ - t'-- ~ H\\~r-1~ C) ....) tc' .. ~ * \\1\\ ~.,. Vh~~~ 1~o VAL\\/r3 ?l?s ~ 75' J.o ~.c ... 0 ~ ys57 ~ rl (\\ 0 If\\ Iff 0'0 ~ -~--~~ .,, 'f ~ 5
THICK AND CONTOUR lOIII 2.5" 2.5" Position 0 90 180 2]9 1 I / / 2.. JJ / 3 / A-4... / ~~SIDE V'ltLSIDE 5 /
~~Weld edge FLOwq Weld Cente!'line Examiner:~~
~~vG{ztii?~ Sj~fz--1 Reviewer: ANII: /.3-Print name: Mttrr \\tJel.L;.~ _.._ Date: I Print name:.t":. t!i-< V~~ COMPONENT 10: ;<~:..r-tXJ7-co3 CROWN WIDTH:~~
~~(q '"-"f'J'n~~~
~~WELD LENGTH: /Lf,z ~ CROWN HEIGHT: ~1-u~>>- DIAMETER: L/.S3 ~ ~ 0 W5l..J:> f?W<;(./ 0o7- <9// $~IvA/ HJK f?[;l:CRBVcc:- /ko6 VAr.>!S 4-~~
~~PlPE:~~
1.0 ZJ(JD 0 0 Q (.,-.) v~.~..ve ~ r-~ cf_ "'PfPE Ia: .__ ____ -l /;(} () Q ba 'P, ~ 4-5 0
[im Ut VGIIUI ~ nation Sit&' Unit BFN I 3 Procedure: N-UT-76 Outage No.: 03RF15 Summaty No.: 03534000-ISI-BFN Procecilre Rev.: 7 ReportNo.: UT-12-o47 Workscope: PSI Work Order No.: 113331595 Page: 1 or 2 Code: Section XI 2001 Ed'2003 Add Cat/Item: fhVB9.11 Location: REACTOR BUlLDING*DRVWELL DrcwAng No.: 3-ISI-0332*C~
== Description:== VLV
~~REO TEE System 10:~~
069 - RMCtor Wltef Cleanup System Component 10: RWCU.3-G07411 Sizdlenglh: 4114.25 Thlckness'Oiamelef: 0.337/ 4 Umitalicns: YE~ CIRC SCAN ON VALVE SIDE-SEE COVERAGE PLOT Stan Time: 0930 Flfllsh Time: 0946 Instrument Settings Search Unit CaL Axial Orientated Search Unit Time Date Serial No.: E33669 Serial No.: OOF62P Check$ Signal Initial Cal. calibfatlon Sweep Sound Path Manufacturer: KRAUTKRAMEA Manufacturer: KBA 0710 4mt'2012 A ell ector Ampitude% Oivlslcn Model: USN60 uneartty: L-12~ Size: 0.25" Model: Comp G Inter. Cal. 0930 412912012 O.S" NOTCH ao 4.0 .1f15" Delay: 3..5247 Range: 1.783 Inter. Cal. NA NA Freq.: S.OMHz Center Freq.: NA M'tl CaVVel: .1275 Inter. Cal. NA NA Energy: High Exam Angle: 45 Squint Angle: NA Final Cal. 1021 412M012 NA Damping: 10000hms Reject 0 Measured Angle: ~ Mode: SHEAR Couptant NA PRFMode: .Auto High SU Freq.: S.OMHz ElCitPolnt: .35 1 of Bernents: 1 Cal. Batch: 11425 Clrcumf.,..,tlll Orientated Search Unit D lsp. Start: IP RecUiy: Full Wave Conlig.: SIJ\\91e Focus: NA lnst Freq.: S.OMHz Ax. Galft (dB): 28.6 Circ. Gan (dB): 28.6 1 Screen Oiv. =.178 ln. ol Sound Path Calibration Block Cal. Block No.: SQ-119 Thickness: 0.5 Dia.: Cal. Blk. Temp.:.!!.:!. Temp. Tool: Comp. Temp.: ~ Temp. Tool: Results: NRI ~ Percent Of Coverage Oblained > 90%* ~ L.e.tel IIJ.PDI Welch, Matthew C. Eaniner Level N/A NIA Other LeYel NIA NIA UT Call>ratic:lniExantnation FLAT 568275 558275 0 AI 0 No [,ll Type: Utngelll ca!ibrtlllon Signal Sweep Sound Path 1 Shape: Round CcniOur. FLAT Reflector Amplitude% DMslon Mfg.: Sonotech Wedge Style: N~I NTEGRAL 0.5" NOTCH 80 4.0 .705 Exam Batch: 11425 Search Unit Cable NA RG*174 Type: Ultregel B NA Type: Length:..!:.. No. Conn.: o Mf. Sonolech g.. NA Scan Coverage Upstream 0 Downstream !ill Scan dB: 46 Ref-nee llock Refenlf'lceiSimulator Block Signal -- Seslal No.: Gain s~ Sound Path cw~ CCW 5lJ Scan dB: ~ 5100 dB Reflector Amplitude% Di'tisi<rl Exam Surface: 00 Type: Roq)IIS 36.8 FSDH 50 5.6 1.003 Surlace Condition: Rush NA NA Info 0 Report.) Comments: E33669 DUE DATE8115f12, 558275 DUE DATE12/10112. Reviewed P~s Data: None Calle //- ?bl ~ ~ Signature Date Site RevieW Date Signature Date ANU R8'1iew Date / I ), /3. 5/.J.}/3. Ve;~ ~"A/J?I 0 0 Q c...> 0 ~
THICK AND CONTOUR Position 2.5" 2.5" 1 2'" 3 "W SIDE 4* 5 '" Weld edge FLow y Examiner: V't/' Reviewer-Print name: MA* ~\\.al Date* I Print name: COMPONENT iD: RWGU- 001-Oil CROWN WIDTH: CROWN HEIGHT: Fw -s~ 1o ~ ~~~-~~l~~--- / </{!> z:1o 0 ~ "'1-.._ 1---...j~--- y...,."' f'l?t: ~ v~ fifl[SIDE Weld Cen1erline WELD LENGTH: Jli, z~ DIAMETER: ~~ 3 i'?e&Lii/Z@ e-XAM \\}owJM ~ "3-*D~ * ~ 3 (. 1z.x. I *~) /C Jtf,Z.!.-= ~. og CJBIAJIJED F XM1 Va.U!iG:. & g,{p1b AX/A'- :.No t..ti1.1TA71oNS :: l"o~ oKG: L.JI.-*JJrh"ftQIJ ~ "?2. z.% 00
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v t e Letter Sequence Request
CAC:MF9257, (Open)
Initiation Request Acceptance... Administration Questions 8 June 2017 Answers 30 June 2017 Results Approval... Other: ML17261A036
MONTHYEAR2017-10-06 [Table View]

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

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1.4 Comments

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