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

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 D Lf 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 i n the enclosure. The attachment to the enclosure provides additiona l 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 i nterval for WBN Unit 1. 1 O 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 i s 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 i n coverage for that weld is less than 10%." Therefore , TVA is requesting relief only for those welds that were inspected and received Code exam i nation 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 l evel of quality and safety was achieved and public health and safety was not endangered by allowing the proposed alternat i ve examination coverage in lieu of the Code requ i rement. 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 quest i ons regarding this request to Edward D. Schrull at 423-751-3850. Respectfully , -~-.fl, ) .. ) (tf 1l L.-._ Erin ~;fr~t1ije+lan Director , Nuclear Regulatory Affairs Enclosure cc: See Page 3 U.S. Nuc l ear Regulatory Commiss i on CNL-18-078 Page 3 May 25 , 2018

Enclosure:

Watts Bar Nuclear Plant (WBN) Un i t 1 Request for Relief Number 1-ISl-2 1 cc (w/Enc l osure): NRC Reg i onal Adm i n i strator -Reg i on II NRC Sen i or Res i dent Inspector

-Watts Bar Nuc l ear P l ant NRC Project Manage r -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 .1 1 100% 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 examinat i ons performed i n 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 i s 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 Un i t 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 w elds. CNL-18-078 E2 of 58 Enclosure Examinations performed per Table IWC-2500-1 , Examination Category C-B , " Pressure Retaining Nozzle Welds i n 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 i nspection 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 p i pe-to-tee butt weld in the chemical and volume contro l 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 l isted 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 w i th conditions resulting i n examination li mitations (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 , th i s relief request addresses those condit i ons. An example of such a condition i s 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 enc l osure. When exam i ned , 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 accessib l e 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 i nterrogated 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 i s enclosure by the represented angles. However , no addit i onal coverage is cred i ted. Burden Caused by Compliance To comply w i th 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 des i gn. Components and fittings associated with the welds listed in this request are constructed of standard designed i tems and materials meeting typical national standards that specify required configurations and dimensions. To replace these items w i th 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 I WC-2500-1. 3) UT examinations are conducted to the maximum extent possible using demonstrated techniques as requ i red by ASME Section XI or the RI-ISi Programs. Basis for Use 10 CFR 50.55a(g)(4) r ecognizes that throughout the service l i fe of a nuclear power fac ili ty , components wh i ch are classified as ASME Code Class 1 , Class 2 , and C l ass 3 must meet the requirements set forth i n the ASME Code to the extent practical with i n the limitations of design , geometry and materials of construction of the welds and items described in the attachment to this enclosure. When a component i s found to have conditions that limit the r equired examination volume or surface area , TV A is requ i red to subm i t this informat i on to the enforcement and regulatory authority having jurisd i ct i on at the plant site. Th i s request for relief has been wr i tten to address areas where these types of cond i tions exist and where the required amount of coverage was reduced be l ow the m i nimum acceptable. TVA has performed the weld examinations l isted in this request to the maximum extent possible for each of the welds identified with l im it ations in the attachment to th i s enclosure. The Class 1 Exam i nation Category B-D Pressur i zer Nozzle Welds and the Class 1 risk-i nformed piping welds i n the scope of this request are all l ocated inside the conta i nment. Even though their exam i nation did not meet the essentially 100% Code requ i red volume coverage requ i rement , each of these locations i s subject to a system pressure test each refueling outage. In addition , there is continuous monitor i ng instrumentation i n p l ace to assure that ear l y detection of any reactor coolant system (RCS) pressure boundary leakage is i dent i fied. This i s accomplished by leakage detect i on i nstrumentation inside the WBN Un i t 1 containment , where the RCS leakage detection instrumentation is required to be operable by WBN Unit 1 Technical Specificat i on (TS) 3.4.1 5. WBN Un i t 1 TS 3.4.15 requires that the follow i ng RCS leakage detect i on i nstrumentat i on sha ll be operable:

• one containment pocket sump l evel mon i t or

• one l ower conta i nment atmosphere part i cu l ate rad i oactiv i ty mon i to r The above instruments are used to quantify any un i dentified l eakage from the RCS and to meet WBN Un i t 1 TS 3.4.13 that states that RCS operational leakage shall be limited to: a) No pressure boundary leakage; b) One gallon per m i nute (gpm) un i dent i fied l eakage; c) 1 O gpm identi fi ed leakage; and d) 1 50 gallons per day primary-to

-secondary leakage through any one steam generator The Class 2 boron injection tank welds and seal w ater injection filter hous i ng weld in the scope of this re l ief r equest are located outside containment , i n the Aux i liary Build i ng. While these examinations did not meet the Code required vo l ume coverage requirements , each of these locations i s subject to a system pressure test and VT-2 visua l examination each ISi per i od. Based upon the extent of the requ i red UT exam i nation volume achieved for each of the welds within t h i s request for relief , and coupled with applicable leakage monitor i ng and requ i red system pressure tests wi th VT-2 v i sual examinat i ons , no further action can be taken by TVA at CNL-18-078 E6 of 58 Enclosure th i s 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 integr i ty. VII. Duration of Proposed Alternative This request for relief i s 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 lim i ted weld exam i nations are common and are filed by all licensees. Some of the more recent NRC approvals of requested rel i ef that are aligned with Reference 1 are:

• NRC SER , " Sequoyah Nuclear P l ant , Units 1 and 2-Re l ief Request No. 17-ISl-1 Regarding the Requirements of the American Society of Mechanica l Engineers Code (CAC Nos. MF9690 AND MF9691; EPID L-2017-LLR-0025)

," dated January 26 , 2018 (ML18008A068)

• NRC SER , " Surry Power Stat i on Unit No. 2 -Requests for Relief LMT-SS01 , LMT-CS01, LMT-P01 , LMT-C0 1, 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 , " D i ablo Canyon Power Plant , Un i t No. 1 -Re li ef Reques t NDE-SIF-U 1 to Allow Use of Alternate American Society of Mechan i cal Engineers Boiler and Pressure Vessel Code Section XI Examination Requirements for the Third lnservice Inspection Interval (CAC No. MF7552)," dated Ju l y 27 , 2016 (ML16207A397)

• NRC SER , " Millstone Power Station , Unit No. 2 -Relief Requests for Limited Coverage Exam i nat i ons Performed In the Fourth 10-Year lnservice Inspection In t erval (CAC Nos. MF6567 , MF6568 , and MF6569)," dated July 1 3 , 2016 (ML16172A135)

• NRC SER , " Susquehanna Steam Electric Stat i on , Units 1 and 2 -Rel i ef Requests for the Third 10-Year lnservice Inspect i on Interval (CAC Nos. MF6302 , MF6303 , MF6304 , MF6305 , MF6306 , and MF6307)," dated May 10 , 2016 (ML16069A199) IX References

1. NRC presentat i on " Coverage Re l ief Requests", lndustry/NRC NOE Technical Informat i on Exchange Public Meeting January 1 3-15 , 2015 (ML15013A266)

2. EPRI Topical Report T R-112657 , " Revised Risk-Informed lnservice Inspection Evaluation Procedure (PWRM RP-05)," Revision B-A , December 1999 (ML013470102) 3. NRC l etter to TVA , " Watts Bar Nuclear P l ant , Unit 1, Rel i ef Request-American Soc i ety of Mechan i cal Engineers , Sect i on XI , Alternate lnservice Inspection Program -Risk-Informed lnserv i ce Inspect i on Program (TAC No. MD9596)," dated January 22 , 2009 (ML083590038)

4. NRC l etter to Electric Power Research Institute , " Safety Evaluat i on Report Related to EPRI R i sk-I nformed lnserv i ce Inspect i on Evaluation Procedure (EPRI TR-112657 , Revis i on B , July 1999)," dated October 28 , 1 999 (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 -2 ig 5! 4 10 9 t~ Ci) 3 \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 CNL-18-078 *

• c---~-S * "

• 1 _, Enclosure Attachment llcH*l* '#'l--4 r..oo llln9 "****l (~a,,91'\ A-A) t 11.DK t A*A* *-:i.*i 1 111 ....... 17 ---.t.~ < 1.0 I FIGURE 1-2-SCANNING NOMENCLATURE IDENTIFICATION FOR VESSELS E10 of 58 Seq. Number Class Weld Description Weld Category Ident i ficat i on Item No. Cycle 1.1 1 Head -r-M 1 N = 2.55" WP-10 B-D Cladd i ng T TYP = 0.19 U1R 13 B 3.11 0 1.2 1 Head -r-M 1 N = 1.90" WP-1 1 B-D C l add i ng T TYP = 0.1 9 U1R11 B3.110 1.3 1 Head -r-M 1 N = 1.90" WP-12 B-D Cladd i ng T T Y P = 0.19 U1R 1 1 B3.110 1.4 1 Head -r-M 1 N = 1.90" WP-13 B-D C l add i ng T T Y P = 0.19 U1R11 B3.110 CNL-18-078 Enclosure Attachment Table 1 -WBN Unit 1 Welds With Limited Examinations Material 1 Material 2 Material 3 Code Coverage Product Form Weld Product Form Obtained 2 Nozzle: We l d: Head: UT= 53.0% A-508 Class 2 Ferritic SA-533 Class 2 A ll oy Stee l Steel Alloy Steel Plate Forg i ng w i th Austen i t i c Sta i nless Ste el C l adding Nozzle: Weld: Head: UT= 73.7% A-508 Class 2 Ferr i tic SA-533 C l ass 2 A ll oy Steel Steel Alloy Steel P l ate Forg i ng w i th Austen i tic Stainless Steel Cladding Head: Weld: Nozzle: UT= 56.4% SA-533 Class 2 Ferr i tic A-508 C l ass 2 Alloy Steel P l ate Steel Alloy Steel Forg i ng with Austen i t i c Stainless Steel Cladding Head: We l d: Nozzle: UT= 56.4% SA-533 Class 2 Ferrit i c A-508 Class 2 Alloy Steel Plate Steel Alloy Stee l Forg i ng w i th Austenit i c Sta i nless Steel Cladd i ng E11 of 58 Examination Limitations Applicable and Results Tables and Figures Geometric Nozzle Design Table1.1-1 Configuration and Head Side of Weld Due to Figur e s Heater Penetration 1.1-1 No zzl es through 1.1-6 No Recordab l e Indications Geomet ri c Nozzle Des i gn T a ble 1.2-1 Con fi gurat i on Lim i tation. F i gures No Recordable 1.2-1 Ind i cat i ons t h rough 1.2-4 Geometric Nozzle Design Table 1.3-1 Configurat i on Limitation F i gures No Recordable 1.3-1 Ind i cations through 1.3-4 Geometric Nozzle Des i gn Table 1.4-1 Configurat i on Lim i tat i on F i gures No Recordable 1.4-1 Indications through 1.4-4 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 Identification Item No. Product Form Weld Product Form Obtained 2 Figures Cycle 1.5 1 Head r1 1 N = 1.90" Head: Weld: Nozz l e: UT= 56.4% Geometr i c Nozzle Des i gn Table 1.5-1 Cladding T TY P = Configuration Limitation WP-14 B-D SA-533 Cla s s 2 Ferrit i c A-508 Class 2 Figures 0.1 9 A ll oy Steel P l ate Stee l Alloy Steel Forg in g No Recordab l e 1.5-1 U1R1 1 B3.1 1 0 w i th Austen i t i c Indicat i ons through Sta i nless Steel 1.5-4 Cladding 1.6 1 Head r1 1 N = 1.90" Head: Weld: Nozzle: UT= 56.4% Geometric Nozzle Design Table 1.6-1 Cladd i ng T TYP = Configuration Limitation WP-15 B-D SA-533 Class 2 Ferr i tic A-508 Class 2 Figures 0.19 A l loy Steel Plate Steel Alloy Steel Forging No Recordable 1.6-1 U1R 11 B3.1 1 0 w i th Auste n itic Ind i cations through Sta i nless Stee l 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 s i de F i gures Head T NoM= 2.0" Steel 1.7-1 U1R10 C1.20 No Recordable through Shell TN O M= 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 Sta i nless SA240 TP 304 s i de F i gures Head T NoM= 3.12" Steel 1.8-1 U1R10 C 1.20 No Recordable through Shell T N°M= 2.0" Ind i cations 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-3 1 2 Stain l ess SA-182 F 304 Lim i tation F i gures SWIFL TR-62-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 Seq. Number Class Weld Description Weld Category Identification Item No. Cycle 1.10 2 6" Boron Inject i on Tank Inlet Nozzle BIT-1 C-B to Head Weld U 1 R9 C2.2 1 Head T NOM= 2.0" 1.11 2 4" SCH X-HVY Pipe rN°M = 0.337 1-003D-R-A D012-13 R1 .11 U 1 R13 1.12 2 4" SCH X-HVY Pipe rNOM = 0.337 1-0030-R-A 0012-14 R1 .11 U1R13 1.13 1 2" SCH 160 P i pe TN OM = 0.344 CVCF-0036-R-A 14 3" X 3" X 2" Red R1 .11 Tee T MIN = 0.344 U1R12 1.14 1 6" SCH 1 60 P i pe T NOM = 0.719" SIF-D092-15 R-A 14" X 14" X 6" U1R10 R1.20 SCH 160 Red Tee T NoM = 0.719" CNL-18-078 Enclosure Attachment Table 1 -WBN Unit 1 Welds With Limited Examinations Material 1 Material 2 Material 3 Code Coverage Product Form Weld Product Form Obtained 2 Nozzle: Weld: Head: UT= 68.8% SA-182 Stainless SA-240 TP 304 PT= 100% F 304 Steel Va l ve: Weld: P i pe: UT= 46.5% SA 216 GR. Ferr i tic SA-333 Gr. 6 WCB Steel P i pe: Weld: Valv e: UT= 46.5% SA-333 G r. 6 Ferr i tic SA 216 GR. WCB Steel Tee: Weld: Pipe: UT= 58.3% SA403WP 3 04 Sta i n l ess SA 376 TP 304 Stee l Elbow: We l d: Tee: UT= 75.0% SA 403 WP 316 Sta i n l ess SA 403 WP 316 Steel E13 of 58 Examination Limitations Applicable and Results Tables and Figures Geometric Nozzle Design Table 1.10-1 Configuration Limitation F i gures 1.10-No Recordable 2 through Ind i cat i ons 1.10-4 Geometr i c Des i gn Table1.11-1 Limitation No Scans on Valve S i de of Weld. Figures 1.1 1-1 No Recordable through Ind i cations 1.11-3 Geometric Design Table 1.12-1 Limitation No Scans on Valve S i de of Weld. F i gures 1.12-1 No Recordable through Indications 1.12-3 Geometr i c Tee to P i pe T a ble 1.13-1 Design Configuration Limitation. Figures 1 .13-1 No Recordable through Indicat i ons 1.13-3 Geometr i c Elbow to Tee Table 1.1 4-1 Design Configurat i on Limitation. F i gures 1.14-1 No Recordable through Ind i cat i ons 1.14-2 Seq. Number Class Weld Description Weld Category Identification Item No. Cycle 1.15 2 4" SCH 160 Pipe T NOM = 0.531 SIF-D084-04 R-A 4" SCH 160 U1R10 R1.20 ElbowT NOM = 0.531" NOTES: 1. Containment RCS Leakage Detection Applies Enclosure Attachment Table 1 -WBN Unit 1 Welds With Limited Examinations Material 1 Material 2 Material 3 Code Coverage Product Form Weld Product Form Obtained 2 Elbow: Weld: Pipe: UT= 89.6% SA-403 W P316 Stainless SA-376 TP 316 Steel 2. UT = Ultrasonic Examinatio n , PT = Liqu i d Penetra n t Examination CNL-18-078 E14 of 58 Examination Limitations Applicable and Results Tables and Figures Geometr i c Elbow to Pipe Table 1.15-1 Des i gn Configurat i on Limit a tion. Figures 1.15-1 No Recordable through Indicat i ons 1.1 5-2 Enclosure Attachment 1.1 Weld WP-10 -14" Pressurizer Surge Nozzle to Head Shell Weld WP-01 P-0 WP-07 I WP-06 WP-02 SURGE 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 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 1 R7 , 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 Artic l e 4 of Sect i on Vas supplemented by Table 1-2000-1 was used for this ultrasonic examination. 45' AXIAL HEAD S I DE ' *1 ., .. OZZLES I DE Figure 1.1-2 Weld WP-10 45° Ax i al Head Side Scan 60' AX I AL HEAD SIDE OZZLE S I DE F i gure 1.1-3 W eld WP-10 60° Axial Head Side Scan CNL-1 8-078 E16 of 58 I HEADSIOE I HEAD SIDE Enclosure Attachment 45' AX I A l O ZZlE SI DE O ZZLE S I OE Figure 1.1-4 Weld WP-10 45° Axial Nozzle Scan 60' AXIA L OZZLE S I DE ---.t.1!15*--, OZZI.E SIDE HEAD S I DE /-'/S' HEAD SIDE l Figure 1.1-5 Weld WP-10 60° Axial Nozzle Scan CNL-18-078 E17 of 58 CW&CCWC I R C SCA S , 45* & 50* OZZLES I OE Enclosure Attachment Figure 1.1-6 Weld WP-1 O 45° & 60° Circ Scans Table 1.1-1 Weld WP-10 Scan Coverage and Scan Summary CNL-18-078 SCANS %COVERAGE 45° Axial Head Side 60° Axial Head Side 45° Axial Nozzle Side 60° Axial Nozzle Side 45° Circ CW 60° Circ CW 45° Circ CCW 60° Circ CCW CUMULATIVE%

COVERAGE=

424.4% + 8 SCANS = 53.05% or TOTAL COVERAGE%=

53.0% 49.9% 33.7% 31.8% 16.6% 73.1% 73.1% 73.1% 73.1% Note: Wave Modes Used= 45° Shear and 60° Shear. E18 of 58 a.I ! HEAOS I DE Enclosure Attachment 1.2 Weld WP-11 -4" Pressurizer Spray Nozzle to Head Shell Weld WP-04 I W P-0 9 I WP-SPRAY NOZZLE Figure 1.2-1 Weld WP-11 P-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 rev i ew 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 Art i cle 4 of Section Vas supplemented by Table 1-2000-1 was used for this ultrasonic examination. CNL-18-078 E19 of 58 Axl~I Scan Nonie Sid4t: CNL-18-078

1. 52 N Enclosure Attachment 3.87 --1 --F i gure 1.2-2 Weld WP-11 , Head Side Ax i al Scans 3. 87 I .~ 1 . 31 N -----Figure 1.2-3 Weld WP-1 1 , Nozzle S i de Axial Scans E20 of 58 ccw~cwarc Scans 1.1. \ e ~o N Enclosure Attachment 3.8 7 1 . 18 Figure 1.2-4 Weld WP-11 CCW and CW Circ Scans Table 1.2-1 Weld WP-11 Scan Coverage and Scan Summary CNL-18-078 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. E21 of 58 Enclosu r e Attachment 1.3 Weld WP-12 -6" Pressurizer Relief Head-to-Nozz l e She ll Weld SAF£TY NOZZL£ PZRLUG-2 PZRLUG-J SAFE:TY NOZZLE: P-2 PZRLUG-1 1..... MAN W AY TOP VIEW F i gure 1.3-1 We l d WP-12 BRACKET This weld was UT examined in the second inspect i on per i od dur i ng the U1 R 1 1 refueling outage i n 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 , F i gure IWB-2500-?(b), Exam Volume A-B-C-0-E-F-G-H. The UT examination was limited from the nozzle side of the we l d due to the geometric configuration resu l t i ng in tota l UT coverage of 56.4% as described in Table 1.3-1 and combined with F i gures 1.3-2 thru 1.3-4. A rev i ew o f the TVA CAP d i d not no t e any fa i lures at this w eld. P r ev i ous examination data from U1R05 , UT report R-0876 was rev i ewed. No recordable ind i cat i ons were noted. This review did not note any laminat i ons on the head that could interfere w i th the angle beam exam i nations performed on this weld.Section XI Mandatory Appendix I , 1-2120 that implements Art i cle 4 of Section Vas supplemented by Table 1-2000-1 w as used for th i s ultrason i c exam i nation. CNL-1 8-078 E22 of 58 Hea d CNL-18-078 Enclosure Attachment F i gure 1.3-2 Weld WP-12 Head Side Ax i al Scans F i gure 1.3-3 We l d WP-12 Nozzle Side Axial Scans E23 of 58 Nozzle Nozzle Head Enclosure Attachment Nozz l e 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 Attac h ment 1.4 We l d WP-13 -6" Pressurizer Safety Head to Nozzle She ll Weld SAFE:TY NOZZLE: WP-12 _1 PZRLUG-1 _i I I I r-WP-14 .-PZRLUG-J r SAFE:TY NOZZLE. ~-SUPPORT BRACKET WP-15 '-MAN W AY TOP VIEW Figure 1.4-1 We l d WP-1 3 Th i s weld w as UT exam i ned in the second inspect i on per i od , dur i ng the U 1 R 1 1 refuel i ng outage i n 2012. The NDE data can be found on UT Report No. UT-12-025. The ASME Code requ i red volume w as determ i ned based on Section XI , F i gure 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 i n 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 rev i ewed. No recordable indications were noted. This review did not note any laminations on the head that could interfere wi th the ang l e beam exam i nations performed on this weld. Sect i on XI Mandatory Appendix I , 1-2120 that imp l ements Art i c l e 4 of Sect i on Vas supplemen t ed by Table 1-2000-1 was used for this ultrason i c examination. CNL-18-078 E25 of 58 OEV: 8.99 ln 1 Head CNL-18-078 Enclosure Attachment Figure 1.4-2 Weld WP-13 , Head Side Axial Scans cans E26 of 58 Nozzle Nozzle Head Enclosure Attachment Nozzle 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-14 -6" Pressurizer Safety Head to Nozzle Shell Weld SAF£TY NOZZL£ PZRLUG-2 PZRLUG-J SAFETY NOZZLE. R£L IE:.F NOZZLE:. -SUPPORT B RA CK E T \ L PZRLUG-4 '-MANW AY TOP V IE W F i gure 1.5-1 Weld WP-14 This weld was UT examined i n the second inspection period during the U1 R 1 1 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 Sect i on XI , Figure IWB-2500-?(b), Exam Volume A-B-C-0-E-F-G-H.

The UT examination was lim i ted from the nozzle side of the weld due to the geometric configurat i on 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 TV A CAP did not note any failures at this weld. Previous examination data from U1R05 , UT report R-0878 was rev i ewed. No recordable ind i cations 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 Sect i on Vas supplemented by Table 1-2000-1 was used for this ultrasonic examination. CNL-18-078 E28 of 58 Head CNL-18-078 N Enclosure Attachment Figure 1.5-2 Weld WP-14 , Head Side Axial Scans Figure 1.5-3 Weld WP-14 , Nozzle Side Axial Scans E29 of 58 Nozzle Nozzle Head Enclosure Attachment Nozzle 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 TOT AL COVERAGE % = 56.4% Note: Wave Modes Used = 45° Shear and 60° Shear CNL-18-078 E30 of 58 Enclosure Attachment 1.6 Weld WP-15 -6" Pressurizer Safet Head to Nozzle Shell Weld SAFE.TY NOZZL£ PZRLUG-2 Rf.L1£F NOZZLE PZRL UG-.3 SAF£TY NOZZL£ -SUPPORT BRA.CKE T PZRLUG-4 l MAN W AY 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 supplemen t ed by Table 1-2000-1 was used for th i s ultrasonic examination. CNL-18-078 E31 of 58 Head CNL-18-078 Enclosure Attachment Figure 1.6-2 Weld WP-15 , Head Side Axial Scans Figure 1.6-3 Weld WP-15 , Nozzle Side Axial Scans E32 of 58 Nozz I e Nozzle Head Enclosure Attachment Nozzle F i gure 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% C i rcCW 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-2 -BIT Tank Head to Shell Weld OUTtET NOZZLE S£E O£r111L A l INLU NOZZLE 1 n SEE DETAIL A ill F i gure 1.7-1 Weld BIT-2 LEG ROiA.1ED INTO \ifEW This weld was UT examined i n the second inspect i on per i od , 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 determ i ned from Figure IWC-2500-1 (c) Exam Volume J-K-L-M. The UT exam i nation was li m i ted from the shell side of the weld due to the she ll material being SA-351 CF8A Cast Stainless Stee l resulting in total UT coverage of 45.2% as descr i bed i n Table 1.7-1 and comb i ned with Figures 1.7-2 an d 1.7-3. A review of the TVA CAP did not note any failures at this weld. Previous examination data from U 1 R03A , UT report R-0690 was rev i ewed. No recordable i nd i cations were noted. No CNL-18-078 E34 of 58 Enclosure Attachment laminations on the base material that cou l d 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 Sect i on 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 ----*-. .,,,., "","" ... Axial Head Side 60.3% Ax i al Shell Side 0.00% Circ CW 60.3% CircCCW 60.3% CUMULATIVE

% COVERAGE = 180.9% + 4 SCANS = 45.23% or TOTAL COVERAGE%=

45.2% i *-' Note: Wave Modes Used = 45° Shear and 60° Shear. 60° refracted longitud i nal used for far side examinat i on , not depicted in sketch and no coverage credited CNL-18-078 E36 of 58 Enclosure Attachment 1.8 We l d BIT-3 -Bit Tank Shell to Head Weld ouncr NOZ'ZLE. SEE DE r AI L ..4 \ \ l I N LET N OZ ZLE l b' SE E D£TA l 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 Sect i on 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 we l d. 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 Sect i on Vas supplemented by Table 1-2000-1 was used for this ultrasonic examination. Shell Side CNL-18-078 45' Shear Head Side Shell S ide Figure 1.8-2 Weld BIT-3 , Head Side Axial Scans 1rcum erent1a cans. E38 of 58 Head S i de Head S i de 60' Shear 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 long i tudinal 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-SWIFL TR-62-96 -4" Filter hous i ng Head to shell weld (FJLTER TB) Figure 1.9-1 Weld CVCS-SWIFLTR-62-96 This weld was UT examined i n the third inspect i on 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 tota l UT coverage of 50.4% as descr i bed 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 rev i ewed. No recordable indicat i ons 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. Reta n gu l ar B a se fil te r Ho u s in g Figure 1.9-2 Weld CVCS-SWIFL TR-62-96 , Filter Housing Side Axial Scans Rec:ta n g u l a r Bue Figure 1.9-3 Weld CVCS-SWIFL TR-62-96 , Rectangular Base Side Axial Scans CNL-18-078 E41 of 58 1'eda n g ulc1r Base Enclosure Attachment Fil er H o usin g Figure 1.9-4 Weld CVCS-SWIFL TR-62-96 , CCW and CW Circumferential Scans Table 1.9-1 Weld CVCS-SWIFL TR-62-96 Scan Coverage and Scan Summary I I SCANS %COVERAGE Axial Head Side 71.93% Axial Nozzle Side 42.22% CircCW 43.74% CircCCW 43.74% CUMULATIVE%

COVERAGE=

201.63% + 4 SCANS = 50.41 % or TOTAL COVERAGE%=

50.4% Note: Wave Modes Used = 45° Shear and 70° Shear. Bid i rect i onal coverage obtained on upstream side from 45° shear reflecting upward. 60° refracted longitudinal used for far s i de examination, not depicted in sketch and no coverage credited. CNL-18-078 E42 of 58 Enclosure Attachment 1.10 We l d BIT-1 -6" Nozzle to Head Shell Weld OU TtET NOlll.E S£E DErAIL A Figure 1.10-1 Weld BIT-1 This we l d was UT and PT examined in the first i nspection 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 l i mited from the nozzle s i de of the weld due to the geometric configuration resulting in to t al 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. No uteS1de She ll S 1 dE Figure 1.10-2 Weld BIT-1 , Shell Side Axial Scans CNL-18-078 E44 of 58 oiz l e S i de Enclosure Attachment S h e ll S i de 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 1 2-1 3-4" Va l ve to Pipe Weld 1-038-CKV-862 7-038-CKV-922 J-0030-0374-02

,--.JO.:, -D0i2-, ---7-003D-D012-14 1-003D-D374-03 I E:2879-3454-C Figure 1.11-1 Weld 1-0030-0012-13 This weld was UT exam i ned in the th i rd inspection period , dur i ng the U 1 R13 refueling outage in 2015 to meet the requ i rements 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 determ i ned 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 th i ckness transition or counterbore. The UT exam i nation was li mited across the weld due to a non-removable l ower ha l f of a support clamp resu l ting i n to t a l 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 fa i lures at this weld. Previous examination data was reviewed for the UT examinat i on per TVA procedures. No recordable i nd i cations were noted.Section XI , Mandatory Appendix I , 1-2220 that implements the Appendix VIII , Performance Demonstrat i on Program , for this ultrasonic examinat i on. CNL-18-078 E47 of 58 Enclosure Attachment Figure 1.11-2 Weld 1-003D-D012-13 , Weld Profile 45° & 70° Scan obstructe d 1-0030~0 0 12-13 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 CNL-18-078 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. 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 F i gure 1.12-1 We l d 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, F i gure 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 li mited across the weld due to a non-removable lower half of a support clamp resulting in total UT coverage of 46.5% as described i n Table 1.1 2-1 and comb i ned 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 indicat i ons were noted.Section XI , Mandatory Appendix I , 1-2220 that i mplements the Appendix VIII , Performance Demonstrat i on Program , for this ultrasonic exam i nation. CNL-18-078 ESQ of 58 Enclosure Attachment V4<..v:£.' " .1 . .,. Figure 1.12-2 Weld 1-003D-D012-14 , Weld Profile 45° & 70° Scan obst r ucte d 1-0030-0012-14 w e ld { ~~.Lim r\-r 47 A000-3-4 8 su p port Figure 1.12-3 Weld 1-003D-D012

-14 , Support interference. CNL-18-078 E51 of 58 Enclosure Attachment Table 1.12-1 Weld 1-003D-D012-14 Scan Coverage and Scan Summary CNL-18-078 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. E52 of 58

,..-----Enclosure Attachment 1.13 Weld CVCF-0036-14

-2" Tee to Pipe Weld CROSSOVER LEG LOOP .J C F-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 TV A 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 E53 of 58 r L Enclosure Attachment 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 CNL-18-078 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. E54 of 58

, Enclosure Attachment 1.14 Weld SIF-0092-15

-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. CNL-18-078 E55 of 58

( nBOWSIOf Enclosure Attachment TE E 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% C i rc CW 100.00% Circ CCW 100.00% CUMULATIVE

% COVERAGE = 300% + 4 SCANS = 75.00% o r TOT AL COVERAGE % = 75.0% Note: Wave Modes Used = Phased Array: 35°to 70° Shear Array and 40°to 70° Refracted Longitud i nal Array . CNL-18-078 E56 of 58 r-----I. ----------------------

Enclosure Attachment 1.15 Weld SI F-D084-04

-4" Elbow to Pipe Weld s,s-.3.34A s,s-.3.3.3 I / .....____

SIF-DO 4-04 s,s-.3.3 4 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.

CNL-18-078 E57 of 58

.II'\ Enclosure Attachment .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.

CNL-18-078 E58 of 58