CNL-18-078, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Lnservice Inspection (ISI) Program, Second Ten Year Interval Request for Relief for 1-ISI-21
| ML18155A335 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 05/25/2018 |
| From: | Henderson E Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| CNL-18-078 | |
| Download: ML18155A335 (61) | |
Text
Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-18-078 May 25, 2018 10 CFR 50.55a ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington , D.C. 20555-0001 Watts Bar Nuclear Plant, Unit 1 Renewed Facility Operating License Nos. NPF-90 NRC Docket No. 50-390
Subject:
Watts Bar Nuclear Plant, Unit 1, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, lnservice Inspection (ISi) Program, Second Ten Year Interval Request for Relief for 1-ISl-21
Reference:
NRC letter to TVA, "Watts Bar Nuclear Plant, Unit 1, Relief Request - American Society of Mechanical Engineers,Section XI, Alternate lnservice Inspection Program - Risk-Informed lnservice Inspection Program (TAC No. MD9596),"
dated January 22 , 2009 (ML083590038)
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 50.55a, "Codes and Standards," paragraphs (g)(5)(iii) and (9)(6), Tennessee Valley Authority (TVA) is submitting a relief request (1 -ISl-21) for Nuclear Regulatory Commission (NRC) approval for the Watts Bar Nuclear Plant (WBN) , Unit 1 second ten-year inservice inspection (ISi) interval. The WBN Unit 1 second ten-year inspection interval ended on May 26 , 2017.
The enclosure to this letter provides relief request 1-ISl-21 that requests relief from the following requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section XI , "Rules for lnservice Inspection of Nuclear Power Plant Components":
- ASME Code Class 1, Table IWB-2500-1, Examination Category B-D , "Full Penetration Welded Nozzles in Vessels - Inspection Program B."
- ASME Code Class 2, Table IWC-2500-1, Examination Category C-A, "Pressure Retaining Welds in Pressure Vessels."
- ASME Code Class 2, Table IWC-2500-1 , Examination Category C-B , "Pressure Retaining Nozzle Welds in Vessels."
- Risk-Informed lnservice Inspection (RI-ISi) piping welds examinations in accordance with Electric Power Research Institute (EPRI) Topical Report (TR)-112657 Revision B-A.
EPRI TR-112657 Revision B-A applies ASME Code Case N-578-1, which provides risk-informed requirements for inservice inspection of Class 1, 2, or 3 piping . The use of EPRI TR-112657 Revision B-A for the WBN Unit 1 RI-ISi program was approved by the NRG in the referenced letter. ;4 DLf 1
µ/CA-
U.S. Nuclear Regulatory Commission CNL-18-078 Page 2 May 25, 2018 The specific item numbers from Tables IWB-2500-1 and IWC-2500-1 , for which relief is requested , are provided in the enclosure. The attachment to the enclosure provides additional information in support of the enclosed relief request.
The ASME B&PV Code,Section XI , 2001 Edition through 2003 Addenda was the code of record for the second ten-year ISi interval for WBN Unit 1.
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 the attachment to the enclosure. 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 . 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 requ irement.
TVA requests approval of these relief requests within 12 months from the date of this letter.
There are no new regulatory commitments associated with this submittal. Please address any questions regarding this request to Edward D. Schrull at 423-751-3850.
Respectfully,
- ~-.fl, ) .. )(tf1lL.-._
Erin ~;fr~t1ije+lan Director, Nuclear Regulatory Affairs Enclosure cc: See Page 3
U.S . Nuclear Regulatory Commission CNL-18-078 Page 3 May 25, 2018
Enclosure:
Watts Bar Nuclear Plant (WBN) Unit 1 Request for Relief Number 1-ISl-2 1 cc (w/Enclosure):
NRC Regional Administrator - Region II NRC Senior Resident Inspector - Watts Bar Nuclear Plant NRC Project Manager - Watts Bar Nuclear Plant
Enclosure Tennessee Valley Authority (TVA)
Watts Bar Nuclear Plant (WBN) Unit 1 American Society of Mechanical Engineers (ASME)Section XI 10 CFR 50.55a Request for Relief Number 1-151-21 In Accordance with 10 CFR 50.55a(g)(5)(iii)
--lnservice Inspection Impracticality--
I. ASME Code Components Affected The Watts Bar Nuclear Plant (WBN) Unit 1, Class 1 and 2 welds with limited examinations requiring relief during the second ten-year inservice inspection (ISi) interval are listed in the attachment to this enclosure. The content of this request includes the insights gained from guidance provided in Reference 1. The following Code Classes , Examination Categories, and Item Numbers apply.
Code Classes: 1 and 2 Examination Categories: B-D, C-A, C-B, and R-A Item Numbers: 83.110, C1 .20, C2.21, R1 .11 , and R1 .20 II. Applicable Code Edition and Addenda During the second ten-year ISi interval, the applicable American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code of Record (Code) was ASME Section XI, Rules for lnservice Inspection of Nuclear Power Plant Components ," 2001 Edition through 2003 Addenda, as modified by Title 10 of the Code of Federal Regulations (10 CFR)
.50.55a, "Codes and Standards." The Appendix VIII requirements and use of the performance demonstration initiative (POI) requirements at WBN were in accordance with the 2001 Edition through 2003 Addenda of Section XI for the limited examinations contained in this request, as conditioned by 10 CFR 50 .55a(b)(2)(xv) and 10 CFR 50.55a(b)(2)(xxiv).
The WBN Unit 1, second ten-year ISi Interval ended on May 26 , 2017. The limited examinations contained in this request are required to be submitted to the Nuclear Regulatory Commission (NRC) on or before 12 months after this date.
Ill. Applicable Code Requirements In accordance with 10 CFR 50 .SSa(g)(S)(iii) and (9)(6), Tennessee Valley Authority (TVA) is requesting relief from weld examination coverage requirements specified in the ASME B&PV Code ,Section XI for the following examination categories . The specific welds for which relief is requested are listed in Table 1 to the attachment to this enclosure. This relief is requested for the WBN Unit 1 second ten-year inspection interval that began May 27, 2007, and ended May 26, 2017 .
CNL-18-078 E1 of 58
Enclosure Exam Item No.
Class 1 Weld Examination Coverage Requirements Cat.
8-D 83.110 100 percent (%) examination of the pressurizer nozzle-to vessel welds per figure IWB-2500-?(a) through (d) as applicable .
Exam Item No.
Class 2 Weld Examination Coverage Requirements Cat.
C-A C1 .20 100% examination of the head circumferential welds per figure IWC-2500-1 .
C-8 C2 .21 100% examination of the nozzle to shell welds per figure IWC-2500-4(a), (b), or (d) as applicable .
Exam Item No.
Class 1 and Class 2 Piping Welds / Risk-Informed lnservice Cat.
Inspection Program Coverage Requirements R-A R1 .11 100% examination per figure IWB-2500-8(c), IWB-2500-9,-10 ,-11 ,
and or IWC-2500-?(a), as applicable , plus an additional 1h" beyond the R1 .20 base metal thickness transition or counterbore.
ASME Code Case N-460, as endorsed in Regulatory Guide 1.147, Revision 18, was invoked for the required coverage associated with the surface and volumetric examinations performed in the second ten-year ISi interval. ASME Code Case N-460 states that when the entire volume or surface 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 ten percent(%). The component examinations in the scope of this relief request are those for which greater than 90% of the required examination volume or surface area could not be achieved .
Limited Class 1 Welds Examinations performed per Table IWB-2500-1 , Examination Category 8-D , "Full Penetration Welded Nozzles in Vessels - Inspection Program B," Item No. 83.110, "Nozzle-to-Vessel Welds ," encountered limitations on six welds during the second ten-year ISi interval at WBN Unit 1. The welds include the pressurizer surge nozzle-to-head weld , the pressurizer spray nozzle-to-head weld , the pressurizer relief head-to-nozzle weld , and three pressurizer safety head-to-nozzle welds. These welds were examined to meet the volumetric requirements for pressurizer nozzle to vessel welds as depicted in Figure IWB-2500-?(b). Limited ultrasonic (UT) examinations have been determined to exist by demonstrated experience as documented in the attachment to th is enclosure when performing examinations of these six welds .
Limited Class 2 Welds Examinations performed per Table IWC-2500-1 , Examination Category C-A, "Pressure Retaining Welds in Pressure Vessels," Item No. C1 .20, "Head Circumferential Welds,"
encountered limitations on three welds that were UT examined to meet the volume requirements of Figure IWC-2500-1 during the second ten-year ISi interval. The welds included one vessel shell-to-head weld on the WBN Unit 1 seal water injection filter and two vessel shell-to-head welds on the WBN Unit 1 boron injection tank. Limited UT examination coverage has been determined to exist by demonstrated experience as documented in the attachment to this enclosure when performing examinations of these three welds.
CNL-18-078 E2 of 58
Enclosure Examinations performed per Table IWC-2500-1 , Examination Category C-B , "Pressure Retaining Nozzle Welds in Vessels," Item No. C2.21 , "Nozzle-to-Shell (Nozzle to Head or Nozzle to Nozzle) Weld," encountered a limitation on the boron injection tank inlet nozzle-to-head weld at WBN Unit 1 during the second ten-year ISi interval. This location was examined to meet the volume requirements defined by Figure IWC-2500-4(b) for nozzle-to-shell welds. A limited UT examination has been determined to exist by demonstrated experience as documented in the attachment to this enclosure when performing the examination of this weld .
The surface examination of this nozzle-to-head weld , required by Table IWC-2500, was completed with no limitations.
Limited Class 1 and Class 2 Piping Welds/ Risk-Informed lnservice Inspection Programs Class 1 and Class 2 piping welds were selected for examination during the second ten-year ISi interval under the Risk-Informed lnservice Inspection (RI-ISi) Program in accordance with Electric Power Research Institute (EPRI) Topical Report (TR)-112657 Revision B-A (Reference 2). EPRI TR-112657 Revision B-A applies ASME Code Case N-578-1, which provides risk-informed requirements for inservice inspection of Class 1, 2, or 3 piping . The use of EPRI TR-112657 Revision B-A for the WBN Unit 1 RI-ISi program was approved by the NRC in Reference 3.
During performance of these Category R-A Risk-Informed ISi piping examinations, coverage limitations were encountered on the following five components:
- Two four-inch ferritic steel valve-to-pipe welds in the main feedwater system
- One two-inch stainless steel pipe-to-tee butt weld in the chemical and volume control system
- One six-inch stainless steel elbow-to-tee weld in the safety injection system
- One four-inch stainless steel pipe-to-elbow weld in the safety injection system.
The above components were examined to meet the volume requirements defined by ASME Code ,Section XI , Figure IWB-2500-8(c), with an additional length to 1/2" beyond each side of the base metal thickness transition or counterbore, as required by Code Case N-578-1.
Section 3.4 , "Implementation and Monitoring," of the NRC Safety Evaluation Report (SER) for EPRI TR-112657 Revision B-A (Reference 4) states:
"It is anticipated that the licensees will address alternatives on a case-by-case basis and that limited examinations will be identified and submitted to the NRC staff for review and approval in plant-specific applications. "
Section 6.4, "Relief Requests," of EPRI TR-112657 Revision B-A states :
"Accessibility is an important consideration in the element selection process . As such ,
locations will generally be selected for examination where the desired coverage is achievable. However, some limitations will not be known until the examination is performed, since some locations will be examined for the first time.
In addition, other considerations may take precedence and dictate the selection of locations where greater than 90 percent examination coverage is physically impossible."
CNL-18-078 E3 of 58
Enclosure IV. Reason for Request Pursuant to 10 CFR 50.55a(g)(5)(iii) and (9)(6), TVA has determined that compliance with the code requirements of achieving essentially 100% coverage of the welds listed in this request is impractical for WBN Unit 1. This request is based on actual demonstrated limitations experienced when attempting to comply with the code requirements in the performance of the examinations listed in this request.
V. Impracticality of Compliance The construction permit for WBN Unit 1 was issued on January 23, 1973 and falls under the provisions of 10 CFR 50 .55a(g)(2)(i), under these provisions, Code Class 1 and 2 components and their supports must be designed and be provided with the access necessary to perform the required preservice and inservice examinations set forth in ASME Section Ill and Section XI.
Although the design of WBN Unit 1 has provided access for examinations to the extent practical ,
component design configurations with conditions resulting in examination limitations (e.g., those from support interference, geometric configurations of welds and materials such as fitting or valve bodies made of cast stainless steel) may not allow the full required examination volume or surface area coverage with the latest techniques available. Therefore, this relief request addresses those conditions . An example of such a condition is a valve to pipe weld where essentially 100% of the code-required volume cannot be examined from the valve side of the weld and where a plant modification would be needed to provide this coverage. Details of examination restrictions and reductions in required examination coverage are provided in the attachment to this enclosure.
When examined , the welds listed in the attachment to this enclosure of this request did not receive the required code volume coverage due to their component design configurations or interference by other items. These conditions resulted in scanning access limitations that prohibited obtaining essentially 100% examination coverage of the required examination volumes. When this situation occurred , 100% of the accessible volumes of each weld were covered to the extent practicable .
The welds were examined as required by applicable procedures and regulations to the extent practicable. In those cases where UT examinations could potentially have interrogated additional area, such as the inside surface of cast stainless valves by looking through a stainless steel weld , these were considered a best effort examination . These best effort examinations are shown on the figures in the attachment to th is enclosure by the represented angles. However, no additional coverage is credited.
Burden Caused by Compliance To comply with the Code required examination volumes or surface areas for obtaining essentially 100% coverage for the welds listed in this request for relief, the welds and their associated components would have to be physically modified and/or disassembled beyond their current design. Components and fittings associated with the welds listed in this request are constructed of standard designed items and materials meeting typical national standards that specify required configurations and dimensions. To replace these items with items of alternate configurations or materials to enhance examination coverage would require unique redesign and fabrication . Because these items are in the Class 1 and 2 boundaries and for the Class 1 CNL-18-078 E4 of 58
Enclosure items that form a part of the reactor coolant pressure boundary, their redesign and fabrication would be an extensive effort based on the limitations that exist.
Specifically, for the Class 1, Examination Category B-D, Item No. B3.110, the limitations encountered were due to geometric nozzle design configurations. The six locations would require a design modification to obtain the required coverage.
For the Class 2, Examination Category C-A, Item No. C1 .20, the limitations encountered were due to the base material geometry on the nozzle side of the weld. This configuration would require a design modification to reduce the thickness of the nozzle base material to remove the taper.
For the Class 2, Examination Category C-A, Item No. C2.21, the limitations encountered were due to the cast stainless steel material on the vessel shell. The tank would have to be replaced with an alternative material to allow UT examination from the shell side of the welds.
For the Class 1 and Class 2 piping welds examined per the RI-ISi Programs the limitations listed in this request are typically limited by their design configurations or materials. The configurations of these welds or their materials only allow UT examination coverage from one side of the weld or limited coverage from a specific area or areas of one side of the weld . These would also require a design modification or replacement to obtain the required examination coverage .
For each weld in the scope of this request, it is not possible to obtain UT interrogation of greater than 90% of the required code examination volume or surface areas without extensive weld or component design modifications. Examinations have been performed to the maximum extent possible . Using radiography as an alternative would result in numerous work-related stoppages and increased radiation exposure due to the shutdown and startup of other work in the areas.
The water may need to be drained from systems or components where radiography is performed , which increases the radiation dose rates over a much broader area than the weld being examined . There is significant impracticality associated with the performance of weld or area modifications or the use of radiography in order to increase the examination coverage.
The UT examination techniques used for welds in this request for relief were reviewed to determine if additional coverage could be achieved by improving those techniques. No improvements could be identified and the examinations have been performed to the maximum extent possible. Therefore , TVA has determined that obtaining essentially 100% coverage is not feasible and is impractical without adding additional burden consisting of significant redesign work, increased radiation exposure, and/or potential damage to the plant or the component itself.
VI. Proposed Alternative and Basis for Use Proposed Alternative
- 1) Periodic system pressure tests and VT-2 visual examinations will continue to be performed on Class 1 pressure retaining welds and items during each refueling outage in accordance with Examination Category B-P of Table IWB-2500-1 .
CNL-18-078 E5 of 58
Enclosure
- 2) Class 2 pressure retaining welds and items will continue to receive system pressure tests and VT-2 visual examinations during each inspection period in accordance with Examination Category C-H of Table IWC-2500-1 .
- 3) UT examinations are conducted to the maximum extent possible using demonstrated techniques as requ ired by ASME Section XI or the RI-ISi Programs.
Basis for Use 10 CFR 50 .55a(g)(4) recognizes that throughout the service life of a nuclear power facility, components wh ich are classified as ASME Code Class 1, Class 2, and Class 3 must meet the requirements set forth in the ASME Code to the extent practical with in the limitations of design ,
geometry and materials of construction of the welds and items described in the attachment to this enclosure. When a component is found to have conditions that limit the required examination volume or surface area , TVA is requ ired to submit this information to the enforcement and regulatory authority having jurisdiction at the plant site. This request for relief has been written to address areas where these types of conditions exist and where the required amount of coverage was reduced below the minimum acceptable. TVA has performed the weld examinations listed in this request to the maximum extent possible for each of the welds identified with limitations in the attachment to th is enclosure.
The Class 1 Exam ination Category B-D Pressurizer Nozzle Welds and the Class 1 risk-informed piping welds in the scope of this request are all located inside the containment. Even though their exam ination did not meet the essentially 100% Code requ ired volume coverage requ irement , each of these locations is subject to a system pressure test each refueling outage.
In addition , there is continuous monitoring instrumentation in place to assure that early detection of any reactor coolant system (RCS) pressure boundary leakage is identified . This is accomplished by leakage detection instrumentation inside the WBN Unit 1 containment, where the RCS leakage detection instrumentation is required to be operable by WBN Unit 1 Technical Specification (TS) 3.4 .15. WBN Unit 1 TS 3.4.15 requires that the following RCS leakage detection instrumentation shall be operable :
- one containment pocket sump level monitor
- one lower containment atmosphere particulate rad ioactivity mon itor The above instruments are used to quantify any unidentified leakage from the RCS and to meet WBN Unit 1 TS 3.4 .13 that states that RCS operational leakage shall be limited to:
a) No pressure boundary leakage; b) One gallon per minute (gpm ) unidentified leakage; c) 1O gpm identified leakage; and d) 150 gallons per day primary-to-secondary leakage through any one steam generator The Class 2 boron injection tank welds and seal water injection filter housing weld in the scope of this relief request are located outside containment, in the Auxiliary Build ing . While these examinations did not meet the Code required volume coverage requirements, each of these locations is subject to a system pressure test and VT-2 visual examination each ISi period .
Based upon the extent of the requ ired UT examination volume achieved for each of the welds within this request for relief, and coupled with applicable leakage monitoring and requ ired system pressure tests with VT-2 visual examinations, no further action can be taken by TVA at CNL-18-078 E6 of 58
Enclosure this time to improve these examinations without applying impractical options. The proposed alternative in this request for relief will provide assurance of an acceptable level of quality and safety by providing reasonable assurance of structural integrity.
VII. Duration of Proposed Alternative This request for relief is for the WBN Unit 1 Second 10-Year ISi Interval, which began on May 27, 2007, and ended on May 26, 2017.
VIII. Precedents Note: Industry requests for relief due to impracticality associated with limited weld examinations are common and are filed by all licensees. Some of the more recent NRC approvals of requested rel ief that are aligned with Reference 1 are:
- NRC SER, "Sequoyah Nuclear Plant, Units 1 and 2- Relief Request No. 17-ISl-1 Regarding the Requirements of the American Society of Mechanical Engineers Code (CAC Nos.
MF9690 AND MF9691 ; EPID L-2017-LLR-0025)," dated January 26, 2018 (ML18008A068)
- NRC SER, "Surry Power Station Unit No. 2 - Requests for Relief LMT-SS01 , LMT-CS01, LMT-P01 , LMT-C01, LMT-C02, LMT-C03 , and LMT-C04 -for Limited Coverage Examinations Performed in the Fourth 10-Year lnservice Inspection Interval (CAC Nos. MF7718, MF-7719, MF7720, MF7721 MF7722, MF7723, MF7724 and MF7725), " dated February 17, 2017 (ML16365A118)
- NRC SER, "Diablo Canyon Power Plant, Unit No. 1 - Relief Request NDE-SIF-U 1 to Allow Use of Alternate American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Examination Requirements for the Third lnservice Inspection Interval (CAC No. MF7552)," dated July 27, 2016 (ML16207A397)
- NRC SER, "Millstone Power Station , Unit No. 2 - Relief Requests for Limited Coverage Examinations Performed In the Fourth 10-Year lnservice Inspection Interval (CAC Nos. MF6567, MF6568, and MF6569)," dated July 13, 2016 (ML16172A135)
- NRC SER, "Susquehanna Steam Electric Station , Units 1 and 2 - Rel ief Requests for the Third 10-Year lnservice Inspection Interval (CAC Nos. MF6302, MF6303, MF6304, MF6305, MF6306, and MF6307), " dated May 10, 2016 (ML16069A199)
IX References
- 1. NRC presentation "Coverage Relief Requests", lndustry/NRC NOE Technical Information Exchange Public Meeting January 13-15, 2015 (ML15013A266)
- 2. EPRI Topical Report TR-112657 , "Revised Risk-Informed lnservice Inspection Evaluation Procedure (PWRM RP-05) ," Revision B-A, December 1999 (ML013470102)
- 3. NRC letter to TVA, "Watts Bar Nuclear Plant, Unit 1, Relief Request-American Society of Mechanical Engineers,Section XI , Alternate lnservice Inspection Program - Risk-Informed lnservice Inspection Program (TAC No. MD9596)," dated January 22, 2009 (ML083590038) 4 . NRC letter to Electric Power Research Institute, "Safety Evaluation Report Related to EPRI Risk-Informed lnservice Inspection Evaluation Procedure (EPRI TR-112657, Revision B, July 1999)," dated October 28, 1999 (ML993190460)
CNL-18-078 E7 of 58
Enclosure Attachment Additional Supporting Information for WBN Unit 1 Request for Relief Number 1-ISl-21 Introduction This attachment contains the figures and tables that depict the limitations and calculations used for obtained coverage, materials and product forms, ultrasonic examination angles and wave modes used, and the examination results for the welds associated with this request for relief, including any applicable previous examination history used. Table 1 identifies the welds within the scope of this request and summarizes the extent of examination coverage achieved for each weld.
Many of the welds listed were examined with different TVA approved procedures and techniques during the span of the second ten-year ISi interval ; therefore, not all the coverage calculations used are identical, but they are based on the actual non-destructive examination (NOE) data reports that were provided for the examinations completed.
Frequently, UT scan numbers were used in the original NOE data sheets to determine and describe the examinations performed and coverage percentages obtained. In the detailed examination data that follows, UT scan number identifiers have been omitted for clarity, and replaced with specific descriptions of weld configurations and scan directions. When referring to NOE datasheets, the scan numbers, if used, have been applied as described in Figure 1-1 for piping and Figure 1-2 for vessels.
CNL-18-078 E8 of 58
Enclosure Attachment FIGURE 1-1-SCANNING NOMENCLATURE IDENTIFICATION FOR PIPING
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\4 13 l6 11 1 = Visual 2 = Base Material When Required Reference Arrow Flow 3-1 4 = Angle Beam 15-17 = 0° Weld and HAZ CNL-1 8-078 E9 of 58
Enclosure Attachment
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FIGURE 1-2-SCANNING NOMENCLATURE IDENTIFICATION FOR VESSELS CNL-18-078 E10 of 58
Enclosure Attachment Table 1 -WBN Unit 1 Welds With Limited Examinations Seq . Number Class Weld Description Material 1 Material 2 Material 3 Code Examination Limitations Applicable Weld Category Coverage and Results Tables and 2
Identification Item No. Product Form Weld Product Form Obtained Figures Cycle 1.1 1 Head -r-M 1N = 2.55" Nozzle: Weld: Head: UT= 53 .0% Geometric Nozzle Design Table1 .1-1 Configuration and Head WP-10 B-D Cladding TTYP = A-508 Class 2 Ferritic SA-533 Class 2 Side of Weld Due to Figures 0.19 Alloy Steel Steel Alloy Steel Plate Heater Penetration 1.1-1 U1R13 B3.11 0 Forg ing with Austenitic Nozzles through Sta inless Steel 1.1-6 Cladding No Recordable Indications 1.2 1 Head -r-M 1N = 1.90" Nozzle: Weld : Head: UT= 73 .7% Geometric Nozzle Design Table 1.2-1 Con figuration Limitation .
WP-11 B-D Cladding TTYP = A-508 Class 2 Ferritic SA-533 Class 2 Figures 0.19 Alloy Steel Steel Alloy Steel Plate No Recordable 1.2-1 U1R11 B3 .110 Forging with Austenitic Indications through Stainless Steel 1.2-4 Cladding 1.3 1 Head -r-M 1N = 1.90" Head : Weld : Nozzle: UT= 56.4% Geometric Nozzle Design Table 1.3-1 Configuration Limitation WP-12 B-D Cladding TTYP = SA-533 Class 2 Ferritic A-508 Class 2 Figures 0.19 Alloy Steel Plate Steel Alloy Steel Forging No Recordable 1.3-1 U1R11 B3.110 with Austenitic Indications through Stainless Steel 1.3-4 Cladding 1.4 1 Head -r-M 1N = 1.90" Head: Weld: Nozzle: UT= 56 .4% Geometric Nozzle Design Table 1.4-1 Configuration Lim itation WP-13 B-D Cladding TTYP = SA-533 Class 2 Ferritic A-508 Class 2 Figures 0.19 Alloy Steel Plate Steel Alloy Steel Forging No Recordable 1.4-1 U1R11 B3.110 with Austenitic Indications through Stainless Steel 1.4-4 Cladd ing CNL-18-078 E11 of 58
Enclosure Attachment Table 1 - WBN Unit 1 Welds With Limited Examinations Seq. Number Class Weld Description Material 1 Material 2 Material 3 Code Examination Limitations Applicable Weld Category Coverage and Results Tables and 2
Identification Item No. Product Form Weld Product Form Obtained Figures Cycle 1.5 1 Head r1 1N = 1.90" Head: Weld : Nozzle: UT= 56.4% Geometric Nozzle Design Table 1.5-1 Configuration Limitation WP-14 B-D Cladding TTYP = SA-533 Class 2 Ferritic A-508 Class 2 Figures 0.19 Alloy Steel Plate Stee l Alloy Steel Forging No Recordable 1.5-1 U1R1 1 B3 .110 with Austenitic Indications through Stainless Steel 1.5-4 Cladding 1.6 1 Head r1 1N = 1.90" Head: Weld : Nozzle: UT= 56.4% Geometric Nozzle Design Table 1.6-1 Configuration Limitation WP-15 B-D Cladding TTYP = SA-533 Class 2 Ferritic A-508 Class 2 Figures 0.19 Alloy Steel Plate Steel Alloy Steel Forging No Recordable 1.6-1 U1R11 B3 .110 with Austenitic Indications through Stainless Steel 1.6-4 Cladding 1.7 2 BIT Tank Head to Head: Weld : Shell : UT = 45 .2% Cast SS Shell to Head Table 1.7-1 Shell Weld design. No scan on Cast BIT-2 C-A SA240 TP 304 Stainless SA-351 CF8A side Figures Head TNoM= 2.0" Steel 1.7-1 U1R10 C1 .20 No Recordable through Shell TNOM= 3.12" Indications 1.7-3 1.8 2 Bit Tank Shell to Shell : Weld : Head: UT= 48 .2% Cast SS Shell to Head Table 1.8-1 Head Weld design. No scan on Cast BIT-3 C-A SA-351 CF8A Stainless SA240 TP 304 side Figures Head TNoM= 3.12" Steel 1.8-1 U1R10 C1.20 No Recordable through Shell TN°M= 2.0" Indications 1.8-3 1.9 2 Shell rN°M = Shell : Weld: Head: UT= 50.4% Geometric Housing Table 1.9-1 0.674" Design Configuration eves- C-A SA-312 Stain less SA-182 F 304 Limitation Figures SWIFL TR Head is Forged Type 304 Steel Forging 1.9-1 96 C.120 No Recordable through Indications 1.9-4 U1R12 CNL-18-078 E12 of 58
Enclosure Attachment Table 1 - WBN Unit 1 Welds With Limited Examinations Seq. Number Class Weld Description Material 1 Material 2 Material 3 Code Examination Limitations Applicable Weld Category Coverage and Results Tables and 2
Identification Item No. Product Form Weld Product Form Obtained Figures Cycle 1.10 2 6" Boron Injection Nozzle: Weld : Head: UT= 68 .8% Geometric Nozzle Design Table 1.10-1 Tank Inlet Nozzle Configuration Limitation BIT-1 C-B to Head Weld SA-182 Stainless SA-240 TP 304 PT= 100% Figures 1.10-F 304 Steel No Recordable 2 through U1R9 C2 .21 Head TNOM= 2.0" Indications 1.10-4 1.11 2 4" SCH X-HVY Valve : Weld : Pipe: UT = 46 .5% Geometric Design Table1 .11 -1 Pipe rN°M = 0.337 Limitation No Scans on 1-003D- R-A SA 216 GR. Ferritic SA-333 Gr. 6 Valve Side of Weld . Figures D012-13 WCB Steel 1.11-1 R1 .11 No Recordable through U1R13 Indications 1.11-3 1.12 2 4" SCH X-HVY Pipe: Weld : Valve: UT = 46 .5% Geometric Design Table 1.12-1 Pipe rNOM = 0.337 Limitation No Scans on 1-0030- R-A SA-333 Gr. 6 Ferritic SA 216 GR. WCB Valve Side of Weld . Figures 0012-14 Steel 1.12-1 R1 .11 No Recordable through U1R13 Indications 1.12-3 1.13 1 2" SCH 160 Pipe Tee : Weld : Pipe: UT = 58 .3% Geometric Tee to Pipe Table 1.13-1 TNOM = 0.344 Design Configuration CVCF-0036- R-A SA403WP 304 Sta inless SA 376 TP 304 Limitation . Figures 14 3" X 3" X 2" Red Stee l 1 .13-1 R1 .11 Tee TMIN = 0.344 No Recordable through U1R12 Indications 1.13-3
- 1. 14 1 6" SCH 160 Pipe Elbow: Weld: Tee: UT = 75 .0% Geometric Elbow to Tee Table 1.14-1 TNOM = 0.719" Design Configuration SIF-D092-15 R-A SA 403 WP 316 Stainless SA 403 WP 316 Limitation . Figures 14" X 14" X 6" Steel 1.14-1 U1R10 R1 .20 SCH 160 Red No Recordable through Tee TNoM = Indications 1.14-2 0.719" CNL-18-078 E13 of 58
Enclosure Attachment Table 1 - WBN Unit 1 Welds With Limited Examinations Seq. Number Class Weld Description Material 1 Material 2 Material 3 Code Examination Limitations Applicable Weld Category Coverage and Results Tables and 2
Identification Item No. Product Form Weld Product Form Obtained Figures Cycle 1.15 2 4" SCH 160 Pipe Elbow: Weld : Pipe: UT= 89 .6% Geometric Elbow to Pipe Table 1.15-1 TNOM = 0.531 Design Configuration SIF-D084-04 R-A SA-403 W P316 Stainless SA-376 TP 316 Limitation . Figures 4" SCH 160 Steel 1.15-1 U1R10 R1 .20 ElbowTNOM = No Recordable through 0.531 " Indications 1.15-2 NOTES:
- 1. Containment RCS Leakage Detection Applies
Enclosure Attachment 1.1 Weld WP 14" Pressurizer Surge Nozzle to Head Shell Weld WP-07 I WP-02 WP-01 WP-06 SURGE P- 0 NOZZLE Figure 1.1-1 Weld WP-10 This weld was UT examined in the third inspection period, during the U 1R13 refueling outage in 2015. The NOE data can be found on UT Report No. UT-15-024A. The ASME Code required volume was determined based on Section XI , Figure IWB-2500-?(b), Exam Volume A-B-C-0-E-F-G-H . The UT examination was limited from the nozzle side of the weld due to the geometric configuration of the nozzle and from the head side of the weld due to heater penetrations (recorded as heater rods on the NOE examination data sheets). The examination resulted in total UT coverage of 53.0% as described in Table 1-1-1 and combined with Figures 1.1-2 through 1.1-6.
A review of the TVA corrective action program (CAP) did not note any failures at this weld.
Previous examination data from U 1R7 , UT report R-1178 was reviewed . No recordable indications were noted . No laminations were observed on the head that could interfere with the angle beam examinations performed on this weld.
CNL-18-078 E15 of 58
Enclosure Attachment Section XI Mandatory Appendix I, 1-2120 that implements Article 4 of Section Vas supplemented by Table 1-2000-1 was used for this ultrasonic examination .
45' AXIAL HEAD SIDE OZZLESIDE ' *1., ..
I HEADSIOE I
Figure 1.1-2 Weld WP-10 45° Axial Head Side Scan 60' AXIAL HEAD SIDE OZZLE SIDE HEAD SIDE Figure 1.1-3 Weld WP-10 60° Axial Head Side Scan CNL-1 8-078 E16 of 58
Enclosure Attachment 45' AXIAl OZZlE SIDE OZZLE SIOE HEAD SIDE Figure 1.1-4 Weld WP-10 45° Axial Nozzle Scan 60' AXIAL OZZLE SIDE
- - - . t .1!15* - - ,
OZZI.E SIDE
/-'/S' HEAD SIDE l
Figure 1.1-5 Weld WP-10 60° Axial Nozzle Scan CNL- 18-078 E17 of 58
Enclosure Attachment CW &CCWCIRC a!.I SCA S, 45* & 50*
OZZLESIOE HEAOS IDE Figure 1.1-6 Weld WP-1 O 45° & 60° Circ Scans Table 1.1-1 Weld WP-10 Scan Coverage and Scan Summary SCANS %COVERAGE 45° Axial Head Side 49.9%
60° Axial Head Side 33 .7%
45° Axial Nozzle Side 31 .8%
60° Axial Nozzle Side 16.6%
45° Circ CW 73 .1%
60° Circ CW 73 .1%
45° Circ CCW 73.1%
60° Circ CCW 73.1%
CUMULATIVE% COVERAGE=
424.4% + 8 SCANS = 53.05% or TOTAL COVERAGE%= 53.0%
Note: Wave Modes Used= 45° Shear and 60° Shear.
CNL-18-078 E18 of 58
Enclosure Attachment 1.2 Weld WP 4" Pressurizer Spray Nozzle to Head Shell Weld
~
WP-04 I
WP- 0 9 P-I WP-SPRAY NOZZLE Figure 1.2-1 Weld WP-11 This weld was UT examined in the second inspection period , during the U1 R11 refueling outage in 2012. The NOE data can be found on UT Report No. UT-12-023. The ASME Code required volume was determined based on Section XI, Figure IWB-2500-?(b), Exam Volume A-B-C-D-E-F-G-H. The UT examination was limited from the nozzle side of the weld due to the geometric configuration of the nozzle. The examination resulted in total UT coverage of 73. 7% as described in Table 1.2-1 and combined with Figures 1.2-2 thru 1.2-4.
A review of the TVA CAP did not note any failures at this weld . Previous examination data from U1 RS , UT report R-0875 was reviewed . No recordable indications were noted. This review did not note any laminations on the head that could interfere with the angle beam examinations performed on this weld .
Section XI Mandatory Appendix I, 1-2120 that implements Article 4 of Section Vas supplemented by Table 1-2000-1 was used for this ultrasonic examination .
CNL-18-078 E19 of 58
Enclosure Attachment 3 . 87 1 . 52
--1 N
--Figure 1.2-2 Weld WP-11 , Head Side Axial Scans Axl~I Scan Nonie Sid4t:
3 . 87 1 . 31 I .~
N Figure 1.2-3 Weld WP-1 1, Nozzle Side Axial Scans CNL-18-078 E20 of 58
Enclosure Attachment ccw~cwarc Scans 3 . 87 1 . 18
- 1. \ e
~o 1.
N Figure 1.2-4 Weld WP-11 CCW and CW Circ Scans Table 1.2-1 Weld WP-11 Scan Coverage and Scan Summary SCANS %COVERAGE Axial Head Side 93.67%
Axial Nozzle Side 51 .56%
CircCW 74.87%
CircCCW 74 .87%
CUMULATIVE % COVERAGE =
294.97% + 4 SCANS= 73.74% or TOTAL COVERAGE % = 73.7%
Note: Wave Modes Used = 45° Shear and 60° Shear.
CNL-18-078 E21 of 58
Enclosure Attachment 1.3 Weld WP 6" Pressurizer Relief Head-to-Nozzle Shell Weld SAF£TY NOZZL£ PZRLUG-2 PZRLUG-J SAFE:TY NOZZLE:
BRACKET P- 2 PZRLUG-1 1..... MAN WAY TOP VIEW Figure 1.3-1 Weld WP-12 This weld was UT examined in the second inspection period during the U1 R11 refueling outage in 2012. The NOE data can be found on UT Report No. UT-12-015. The ASME Code required volume was determined based on Section XI , Figure IWB-2500-?(b), Exam Volume A-B-C-0-E-F-G-H . The UT examination was limited from the nozzle side of the weld due to the geometric configuration resu lting in total UT coverage of 56.4% as described in Table 1.3-1 and combined with Figures 1.3-2 thru 1.3-4 .
A review of the TVA CAP did not note any failures at this weld . Previous examination data from U1R05, UT report R-0876 was reviewed . No recordable indications were noted. This review did not note any laminations on the head that could interfere with the angle beam examinations performed on this weld.
Section XI Mandatory Appendix I, 1-2120 that implements Article 4 of Section Vas supplemented by Table 1-2000-1 was used for this ultrasonic examination.
CNL- 18-078 E22 of 58
Enclosure Attachment Nozzle Figure 1. 3-2 Weld WP-12 Head Side Axial Scans Nozzle Hea d Figure 1.3-3 Weld WP-12 Nozzle Side Axial Scans CNL-18-078 E23 of 58
Enclosure Attachment Nozz l e Head Figure 1.3-4 Weld WP-12 CCW and CW Circ Scans Table 1.3-1 Weld WP-12 Scan Coverage and Scan Summary SCANS %COVERAGE Axial Head Side 90.96%
Axial Nozzle Side 25.23%
CircCW 54.74%
CircCCW 54.74%
CUMULATIVE % COVERAGE =
225.67% + 4 SCANS = 56.42% or TOTAL COVERAGE%= 56.4%
Note: Wave Modes Used = 45° Shear and 60° Shear.
CNL-18-078 E24 of 58
Enclosure Attachment 1.4 Weld WP 6" Pressurizer Safety Head to Nozzle Shell Weld SAFE:TY NOZZLE:
r- WP-14
.- PZRLUG-J r SAFE:TY NOZZLE.
~ - SUPPORT BRACKET WP-15 WP-12 _1 PZRLUG-1 _i I
I I
'- MAN WAY TOP VIEW Figure 1.4-1 Weld WP- 13 This weld was UT exam ined in the second inspection period , during the U1R11 refuel ing outage in 2012. The NDE data can be found on UT Report No. UT-12-025. The ASME Code requ ired volume was determined based on Section XI , Figure IWB-2500-?(b), Exam Volume A-B-C-D-E-F-G-H. The UT examination was limited from the nozzle side of the weld due to the geometric configuration resulting in total UT coverage of 56.4% as described in Table 1.4-1 and combined with Figures 1.4-2 thru 1.4-4.
A review of the TVA CAP did not note any failures at this weld . Previous examination data from U1R05, UT report R-0877 was reviewed . No recordable indications were noted. This review did not note any laminations on the head that could interfere with the angle beam examinations performed on this weld.
Section XI Mandatory Appendix I, 1-2120 that implements Article 4 of Section Vas supplemented by Table 1-2000-1 was used for this ultrasonic examination .
CNL-18-078 E25 of 58
Enclosure Attachment OEV: 8.99 ln 1 Nozzle Figure 1.4-2 Weld WP-13 , Head Side Axial Scans Nozzle Head cans CNL-18-078 E26 of 58
Enclosure Attachment Nozzle Head Figure 1.4-4 Weld WP-13 , CCW and CW Circ Scans Table 1.4-1 Weld WP-13 Scan Coverage and Scan Summary SCANS %COVERAGE Axial Head Side 90.96%
Axial Nozzle Side 25.23%
Circ CW 54.74%
Circ CCW 54.74%
CUMULATIVE % COVERAGE =
225.67% + 4 SCANS = 56.42% or TOTAL COVERAGE%= 56.4%
Note: Wave Modes Used = 45° Shear and 60° Shear CNL-18-078 E27 of 58
Enclosure Attachment 1.5 Weld WP 6" Pressurizer Safety Head to Nozzle Shell Weld SAF£TY NOZZL£ PZRLUG-2 PZRLUG-J SAFETY NOZZLE.
R£L IE:. F NOZZLE:. - SUPPORT BRACKET L PZRLUG-4
\'- MANWAY TOP V IE W Figure 1.5-1 Weld WP-14 This weld was UT examined in the second inspection period during the U1 R11 refueling outage in 2012. The NOE data can be found on Report No. UT-12-027. The ASME Code required volume was determined based on Section XI , Figure IWB-2500-?(b), Exam Volume A-B-C-0-E-F-G-H. The UT examination was limited from the nozzle side of the weld due to the geometric configuration resulting in total UT coverage of 56.4% as described in Table 1.5-1 and combined with Figures 1.5-2 thru 1.5-4.
A review of the TVA CAP did not note any failures at this weld . Previous examination data from U1R05, UT report R-0878 was reviewed . No recordable indications were noted. This review did not note any laminations on the head that could interfere with the angle beam examinations performed on this weld .
Section XI Mandatory Appendix I, 1-2120 that implements Article 4 of Section Vas supplemented by Table 1-2000-1 was used for this ultrasonic examination .
CNL-18-078 E28 of 58
Enclosure Attachment Nozzle Figure 1.5-2 Weld WP-14, Head Side Axial Scans Nozzle Head N
Figure 1.5-3 Weld WP-14 , Nozzle Side Axial Scans CNL-18-078 E29 of 58
Enclosure Attachment Nozzle Head Figure 1.5-4, Weld WP-14 CCW and CW Circ Scans Table 1.5-1 Weld WP-14 Scan Coverage and Scan Summary SCANS %COVERAGE Axial Head Side 90.96%
Axial Nozzle Side 25.23%
CircCW 54.74%
CircCCW 54.74%
CUMULATIVE% COVERAGE=
225.67% + 4 SCANS = 56.42% or TOTAL COVERAGE % = 56.4%
Note: Wave Modes Used = 45° Shear and 60° Shear CNL-18-078 E30 of 58
Enclosure Attachment 1.6 Weld WP 6" Pressurizer Safet Head to Nozzle Shell Weld SAFE.TY NOZZL£ PZRLUG-2 PZRL UG-.3 SAF£TY NOZZL£ Rf.L1£F NOZZLE - SUPPORT BRA.CKE T PZRLUG-4 l MAN WAY TOP VI£W Figure 1.6-1 Weld WP-15 This weld was UT examined in the second inspection period , during the U1 R11 refueling outage in 2012. The NOE data can be found on UT Report No. UT-12-016. The ASME Code required volume was determined based on Section XI , Figure IWB-2500-7(b), Exam Volume A-B-C-D-E-F-G-H . The UT examination was limited from the nozzle side of the weld due to the geometric configuration resulting in total UT coverage of 56.4% as described in Table 1.6-1 and combined with Figures 1.6-2 thru 1.6-4 .
A review of the TVA CAP did not note any failures at this weld . Previous examination data from U1R05, UT report R-0879 was reviewed . No recordable indications were noted. This review did not note any laminations on the head that could interfere with the angle beam examinations performed on this weld .
Section XI Mandatory Appendix I, 1-2120 that implements Article 4 of Section Vas supplemented by Table 1-2000-1 was used for th is ultrasonic examination .
CNL-18-078 E31 of 58
Enclosure Attachment Nozz I e Figure 1.6-2 Weld WP-15, Head Side Axial Scans Nozzle Head Figure 1.6-3 Weld WP-15, Nozzle Side Axial Scans CNL-18-078 E32 of 58
Enclosure Attachment Nozzle Head Figure 1.6-4 Weld WP-15, CCW and CW Circ Scans Table 1.6-1 Weld WP-14 Scan Coverage and Scan Summary SCANS %COVERAGE Axial Head Side 90.96%
Axial Nozzle Side 25.23%
CircCW 54.74%
CircCCW 54.74%
CUMULATIVE% COVERAGE=
225.67% + 4 SCANS= 56.42% or TOTAL COVERAGE%= 56.4%
Note: Wave Modes Used = 45° Shear and 60° Shear CNL-18-078 E33 of 58
Enclosure Attachment 1.7 Weld BIT BIT Tank Head to Shell Weld OUTtET NOZZLE S£E O£r111L A LEG ROiA.1ED INTO \ifEW INLU NOZZLE l 1n SEE DETAIL A ill Figure 1.7-1 Weld BIT-2 This weld was UT examined in the second inspection period , during the U1 R1 O refueling outage in 2011. The NOE data can be found on UT Report No. UT-11-043A. The ASME Code required volume for this weld was determined from Figure IWC-2500-1(c) Exam Volume J-K-L-M. The UT exam ination was limited from the shell side of the weld due to the shell material being SA-351 CF8A Cast Stainless Steel resulting in total UT coverage of 45.2% as described in Table 1.7-1 and combined with Figures 1.7-2 and 1.7-3 .
A review of the TVA CAP did not note any failures at this weld . Previous examination data from U 1R03A, UT report R-0690 was reviewed. No recordable indications were noted. No CNL-18-078 E34 of 58
Enclosure Attachment laminations on the base material that cou ld interfere with the angle beam examinations being performed on this weld were observed.
Section XI Mandatory Appendix I, 1-2120 that implements Article 4 of Section Vas supplemented by Table 1-2000-1 was used for this ultrasonic examination.
Figure 1.7-2 Weld BIT-2, Head Side Axial Scans Head S i de She ll S i de Figure 1.7-3 Weld BIT-2, CCW and CW Circumferential Scans.
CNL-18-078 E35 of 58
r-Enclosure Attachment Table 1.7-1 Weld BIT-2 Scan Coverage and Scan Summary I
L
*- ..,,,., "",""... *- i Axial Head Side 60.3%
Axial Shell Side 0.00%
Circ CW 60.3%
CircCCW 60.3%
CUMULATIVE % COVERAGE =
180.9% + 4 SCANS = 45.23% or TOTAL COVERAGE%= 45.2%
Note: Wave Modes Used = 45° Shear and 60° Shear. 60° refracted longitudinal used for far side examination , not depicted in sketch and no coverage credited CNL-18-078 E36 of 58
Enclosure Attachment 1.8 Weld BIT Bit Tank Shell to Head Weld ouncr NOZ'ZLE.
SEE DErAIL ..4
\
\
INLET NOZZLE l l b' SEE D£TAl A ill Figure 1.8-1 Weld BIT-3 This weld was UT examined in the second inspection period , during the U1R10 refueling outage in 2011 . The NOE data can be found on UT Report No. UT-11-044A. The ASME Code required volume was determined based on Section XI , Figure IWC-2500-1(c), Exam Volume J-K-L-M. The UT examination was limited from the shell side of the weld due to the shell material being SA-351 CF8A Cast Stainless Steel resulting in total UT coverage of 48.2% as described in Table 1.8-1 and combined with Figures 1.8-2 and 1.8-3.
A review of the TVA CAP did not note any failures at this weld. Previous examination data from U1 R03A, UT report R-0691 was reviewed . No recordable indications were noted. No CNL-18-078 E37 of 58
Enclosure Attachment laminations on the base material that could interfere with the angle beam examinations being performed on this weld were observed .
Section XI Mandatory Appendix I, 1-2120 that implements Article 4 of Section Vas supplemented by Table 1-2000-1 was used for this ultrasonic examination .
45' 60' Shear Shear Head Side Shell Head Side Side Figure 1.8-2 Weld BIT-3 , Head Side Axial Scans Head Si de Shell Side 1rcum erent1a cans.
CNL-18-078 E38 of 58
Enclosure Attachment Table 1.8-1 Weld BIT-3 Scan Coverage and Scan Summary Axial Head Side 64.3%
Axial Shell Side 0.00%
CircCW 64.3%
CircCCW 64.3%
CUMULATIVE% COVERAGE=
192.9% + 4 SCANS = 48.23% or TOTAL COVERAGE % = 48.2%
Note: Wave Modes Used= 45° Shear and 60° Shear. 60° refracted longitudinal used for far side examination , not depicted in sketch and no coverage credited CNL-18-078 E39 of 58
Enclosure Attachment 1.9 Weld CVCS-SWIFLTR-62 4" Filter housing Head to shell weld (FJLTER TB)
Figure 1.9-1 Weld CVCS-SWIFLTR-62-96 This weld was UT examined in the third inspection period , during the U1R12 refueling outage in 2014. The NOE data can be found on UT Report No. UT-14-043A. The ASME Code required volume was determined based on Section XI , Figure IWC-2500-1(a), Exam Volume A-B-C-D .
The UT examination was limited from the rectangular base side of the weld due to the geometric configuration resulting in total UT coverage of 50.4% as described in Table 1.9-1 and combined with Figures 1.9-2 thru 1.9-4.
A review of the TVA CAP did not note any failures at this weld . Previous examination data from U1R01 , UT report R-0331 was reviewed. No recordable indications were noted.
CNL-18-078 E40 of 58
Enclosure Attachment Section XI Mandatory Appendix I, 1-2120 that implements Appendix Ill as supplemented by Table 1-2000-1 was used for this ultrasonic examination .
Retangular filter Base Housing Figure 1.9-2 Weld CVCS-SWIFLTR-62-96, Filter Housing Side Axial Scans Rec:ta ngula r Bue Figure 1.9-3 Weld CVCS-SWIFLTR-62-96, Rectangular Base Side Axial Scans CNL-18-078 E41 of 58
Enclosure Attachment 1'edangulc1r Fil er Base Housing Figure 1.9-4 Weld CVCS-SWIFLTR-62-96, CCW and CW Circumferential Scans Table 1.9-1 Weld CVCS-SWIFLTR-62-96 Scan Coverage and Scan Summary SCANS %COVERAGE Axial Head Side 71 .93%
Axial Nozzle Side 42.22%
CircCW 43.74%
I CircCCW 43.74%
I CUMULATIVE% COVERAGE=
201 .63% + 4 SCANS = 50.41 % or TOTAL COVERAGE%= 50.4%
Note: Wave Modes Used = 45° Shear and 70° Shear. Bidirectional coverage obtained on upstream side from 45° shear reflecting upward. 60° refracted longitudinal used for far side examination, not depicted in sketch and no coverage credited.
CNL-18-078 E42 of 58
Enclosure Attachment 1.10 Weld BIT 6" Nozzle to Head Shell Weld OUTtET NOlll.E S£E DErAIL A Figure 1.10-1 Weld BIT-1 This weld was UT and PT examined in the first inspection period , during the U1 R9 refueling outage in 2009. The NOE data can be found on UT Report No. R-1637 A and PT Report No. R-1638. The ASME Code required surface area was determined based on figure IWC-2500-4(a), Exam Surface A-B. The ASME Code required volume was determined based on ASME Section XI figure IWC-2500-4(a), Exam Volume C-0-E-F . The UT examination was limited from the nozzle side of the weld due to the geometric configuration resulting in total UT coverage of 68 .8% as described in Table 1.10-1 and combined with Figures 1.10-2 thru 1.10-4.
CNL-18-078 E43 of 58
Enclosure Attachment A review of the TVA CAP did not note any failures at this weld . Previous examination data from U1R03A, UT report R-0689 was reviewed . No recordable indications were noted.
Section XI Mandatory Appendix I, 1-2120 that implements Appendix Ill as supplemented by Table 1-2000-1 was used for this ultrasonic examination .
NouteS1de She ll S1dE Figure 1.10-2 Weld BIT-1 , Shell Side Axial Scans CNL-18-078 E44 of 58
Enclosure Attachment oizle Side She ll Side Figure 1.10-3 Weld BIT-1, CCW and CW Circumferential Scans VE:.5 l ~ --
~(.' ,u.
.L - - -
Figure 1.10-4 Weld BIT-1, Nozzle Side Scan CNL-18-078 E45 of 58
Enclosure Attachment Table 1.10-1 Weld BIT-1, Scan Coverage and Scan Summary Axial Head Side 100.0%
Axial Nozzle Side 0.0%
CircCW 87.5%
CircCCW 87.5%
CUMULATIVE% COVERAGE=
275.0% + 4 SCANS= 68.75% or TOTAL COVERAGE%= 68.8%
Note: Wave Modes Used= 45° Shear and 60° Refracted Longitudinal used for far side, depicted in Figure 1.10-4 below and no coverage credited .
CNL-18-078 E46 of 58
Enclosure Attachment 1.11 Weld 1-0030-00 12- 13-4" Valve to Pipe Weld J-0030-0374-02 1-038-CKV-862 , --.JO.:, -D0i2-,
--- 7-003D-D012-14 7-038-CKV-922 1 -003D-D374-03 I
E:2879-3454-C Figure 1.11-1 Weld 1-0030-0012-13 This weld was UT examined in the third inspection period , during the U1R13 refueling outage in 2015 to meet the requirements of the RI-ISi Program under EPRI TR-112657 and ASME Code Case N-578-1 . The weld was examined under Item No. R1 .11 for thermal fatigue. The NOE data can be found on UT Report No. UT-15-037. Per Code Case N-578-1 , the required volume was determined based on ASME Section XI , Figure IWB-2500-B(c), Exam Volume C-0-E-F with an additional RI-ISi requirement to increase the volume to include Y:z in . beyond the base metal thickness transition or counterbore. The UT examination was limited across the weld due to a non-removable lower half of a support clamp resulting in total UT coverage of 46.5% as described in Table 1.11-1 and combined with Figures 1.11 -2 and 1.11-3.
A review of the TVA CAP did not note any failures at this weld . Previous examination data was reviewed for the UT examination per TVA procedures. No recordable indications were noted.
Section XI , Mandatory Appendix I, 1-2220 that implements the Appendix VIII , Performance Demonstration Program , for this ultrasonic examination .
CNL-18-078 E47 of 58
Enclosure Attachment Figure 1.11-2 Weld 1-003D-D012-13, Weld Profile 45° & 70° Scan obstructed 1-0030~0 012-13 4 7 A060 3-4 support CNL-18-078 E48 of 58
Enclosure Attachment Table 1.11-1 Weld 1-003D-D012-13 Scan Coverage and Scan Summary Upstream Side 46.49%
Downstream Side 46.49%
Circ CW 46.49%
CircCCW 46.49%
CUMULATIVE % COVERAGE =
185.96% + 4 SCANS= 46.49% or TOTAL COVERAGE%= 46.5%
Note: Wave Modes Used= 45° Shear and 70° Shear.
CNL-18-078 E49 of 58
Enclosure Attachment 1.12 Weld 1-0030-0012-14-4" Pipe to Valve Weld
1-0030-0374-02 1-038-CKV-862 1-0030-0072-13 7-038-CKV-922
- -- 1 -0030-0374-03 I
£2879-3454-C Figure 1. 12-1 Weld 1-0030-0012-14 This weld was UT examined in the third inspection period , during the U1R13 refueling outage in 2015 to meet the requirements of the RI-ISi Program under EPRI TR-112657 and ASME Code Case N-578-1. The weld was examined under Item No. R1 .11 for thermal fatigue . The NOE data can be found on UT Report No. UT-15-038. Per Code Case N-578-1 , the required volume was determined based on ASME Section XI, Figure IWB-2500-B(c), Exam Volume C-D-E-F with an additional RI-ISi requirement to increase the volume to in~lude % in. beyond the base metal thickness transition or counterbore. The UT examination was limited across the weld due to a non-removable lower half of a support clamp resulting in total UT coverage of 46.5% as described in Table 1.12-1 and combined with Figures 1.12-2 thru 1.12-3.
A review of the TVA CAP did not note any failures at this weld . Previous examination data was reviewed for the UT examination per TVA procedures. No recordable indications were noted.
Section XI , Mandatory Appendix I, 1-2220 that implements the Appendix VIII , Performance Demonstration Program , for this ultrasonic examination .
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Enclosure Attachment V4<..v:£. '
.1 . .,. "
Figure 1.12-2 Weld 1-003D-D012-14, Weld Profile 45° & 70° Scan obstructed 1-0030-0012-14 w eld
~ ~ .Limr\-
{ r 47 A000-3-4 8 support Figure 1.12-3 Weld 1-003D-D012-14, Support interference.
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Enclosure Attachment Table 1.12-1 Weld 1-003D-D012-14 Scan Coverage and Scan Summary Upstream Side 46.49%
Downstream Side 46.49%
CircCW 46.49%
CircCCW 46.49%
CUMULATIVE% COVERAGE=
185.96% + 4 SCANS= 46.49% or TOTAL COVERAGE % = 46.5%
Note: Wave Modes Used = 45° Shear and 70° Shear.
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Enclosure Attachment 1.13 Weld CVCF-0036 2" Tee to Pipe Weld CROSSOVER LEG LOOP .J CF- D 36 -14 Figure 1.13-1 Weld CVCF-0036-14 This weld was UT examined in the third inspection period , during the U1R12 refueling outage in 2014 to meet the requirements of the RI-ISi Program under EPRI TR-112657 and ASME Code Case N-578-1 . The weld was examined under Item No. R1 .11 for thermal fatigue. The NOE data can be found on UT Report No. UT-14-038. Per Code Case N-578-1 , the required volume was determined based on ASME Section XI, Figure IWB-2500-B(c), Exam Volume C-0-E-F with an additional RI-ISi requirement to increase the volume to include Yz in. beyond the base metal thickness transition or counterbore. The UT examination was limited across the weld due to a non-removable lower half of a support clamp resulting in total UT coverage of 58 .3% as described in Table 1.13-1 and combined with Figures 1.13-2 and 1.13-3.
A review of the TVA CAP did not note any failures at this weld . Previous examination data was reviewed for the UT examination per TVA procedures . No recordable indications were noted.
Section XI, Mandatory Appendix I, 1-2220 that implements the Appendix VIII , Performance Demonstration Program, for this ultrasonic examination .
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r Enclosure Attachment L
Figure 1.13-2 Weld CVCF-D036-14, Weld Profile 45° & 70° Scan Figure 1.13-3 Weld CVCF-D036-14, Weld Circumferential Scans Table 1.13-1 Weld CVCF-D036-14 Scan Coverage and Scan Summary SCANS %COVERAGE Upstream Side 00.00%
Downstream Side 100.00%
Circ CW 66.66%
CircCCW 66.66%
CUMULATIVE% COVERAGE=
233.32% + 4 SCANS = 58.33% or TOTAL COVERAGE%= 58.3%
Note: Wave Modes Used= 45° Shear and 70° Shear.
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Enclosure Attachment 1.14 Weld SIF-0092 6" Elbow to Tee Weld IF - 9 -1 5 Figure 1.14-1 Weld SIF-0092-15 This weld was UT examined in the second inspection period, during the U1 R10 refueling outage in 2011 to meet the requirements of the RI-ISi Program under EPRI TR-112657 and ASME Code Case N-578-1. The weld was examined under Item No. R1 .20, Elements Not Subject to a Degradation Mechanism . The NOE data can be found on UT Report No. UT-11-031 . Per Code Case N-578-1 , the required volume was determined based on ASME Section XI , Figure IWB-2500-8(c), Exam Volume C-0-E-F with an additional RI-ISi requirement to increase the volume to include~ in. beyond the base metal thickness transition or counterbore . The UT examination was limited across the weld due to a non-removable lower half of a support clamp resulting in total UT coverage of 75.0% as described in Table 1.14-1 and combined with Figure 1.14-2.
A review of the TVA CAP did not note any failures at this weld. Previous examination data from U1R06, UT report R-0960 was reviewed . No recordable indications were noted .
Section XI , Mandatory Appendix I, 1-2220 that implements the Appendix VIII , Performance Demonstration Program , for this ultrasonic examination.
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Enclosure Attachment
(
nBOWSIOf TEE S10£ Figure 1.14-2 Weld SIF-D092-15, Weld Profile Axial Scan Table 1.14-1 Weld SIF-D092-15 Scan Coverage and Scan Summary SCANS %COVERAGE Upstream Side 100.00%
Downstream Side 00.00%
Circ CW 100.00%
Circ CCW 100.00%
CUMULATIVE % COVERAGE =
300% + 4 SCANS = 75.00% or TOTAL COVERAGE % = 75.0%
Note: Wave Modes Used = Phased Array: 35°to 70° Shear Array and 40°to 70° Refracted Longitud inal Array .
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Enclosure Attachment 1.15 Weld SI F-D084 4" Elbow to Pipe Weld s,s-.3.34A s,s-.3.3.3 I
s,s-.3.3 4
/ .....____ SIF-DO 4-04 Figure 1.15-1 Weld SIF-D084-04 This weld was UT examined in the second inspection period, during the U1R10 refueling outage in 2011 to meet the requirements of the RI-ISi Program under EPRI TR-112657 and ASME Code Case N-578-1 . The weld was examined under Item No. R1.20, Elements Not Subject to a Degradation Mechanism . The NOE data can be found on UT Report No. UT-11-010. Per Code Case N-578-1 , the required volume was determined based on ASME Section XI, Figure IWB-2500-B(c), Exam Volume C-D-E-F with an additional RI-ISi requirement to increase the volume to include~ in. beyond the base metal thickness transition or counterbore . The UT examination was limited across the weld due to a non-removable lower half of a support clamp resulting in total UT coverage of 89.6% as described in Table 1.15-1 and combined with Figure 1.15-2.
A review of the TVA CAP did not note any failures at this weld . Previous examination data was reviewed for the UT examination per TVA procedures. No recordable indications were noted .
Section XI, Mandatory Appendix I, 1-2220 that implements the Appendix VIII, Performance Demonstration Program, for this ultrasonic examination.
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Enclosure Attachment
.II'\ .UJ Figure 1.15-2 Weld SIF-D084-04, Weld Profile Axial Scan Table 1.15-1 Weld SIF-D084-04 Scan Coverage and Scan Summary SCANS %COVERAGE Upstream Side 72.2%
Downstream Side 86.11%
CircCW 100.00%
CircCCW 100.00%
CUMULATIVE % COVERAGE =
358.31 % + 4 SCANS = 89 .58 % or TOTAL COVERAGE % = 89 .6%
Note: Wave Modes Used = 45° Shear, 60° Shear, and 60° Refracted Longitudinal.
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