ML18079A725
| ML18079A725 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 03/17/2018 |
| From: | Lacal M Arizona Public Service Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 102-07669-MLL/TNW | |
| Download: ML18079A725 (22) | |
Text
10 CFR 50.55a A member of the STARS Alliance LLC Callaway
- Diablo Canyon
- Palo Verde
- Wolf Creek MARIA L. LACAL Senior Vice President, Nuclear Regulatory & Oversight Palo Verde Nuclear Generating Station P.O. Box 52034 Phoenix, AZ 85072 Mail Station 7605 Tel 623.393.6491 102-07669-MLL/TNW March 17, 2018 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station Unit 2 Docket No. STN 50-529 Renewed Operating License Number NPF-51 Relief Request 58 - Unit 2 Impractical Examinations for the Third 10-Year Inservice Inspection Interval Pursuant to 10 CFR 50.55a(g)(5)(iii), Arizona Public Service Company (APS) hereby requests NRC approval of the following request for the third ten-year interval for the In-Service Inspection (ISI) Program for Palo Verde Nuclear Generating Station (PVNGS),
Unit 2. Certain ultrasonic examinations of welds identified here-in required by Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, sub-articles IWB-2500 and IWC-2500 have been determined to be impractical, therefore, relief is requested from those requirements to achieve essentially 100 percent weld coverage while proposing the enclosed alternatives. The enclosed information supports the determinations of impracticality which are based on demonstrated limitations experienced while attempting to comply with the Code requirements for the identified interval. The details of the 10 CFR 50.55a request are enclosed.
By letter number 102-07604 [Agency Documents Access and Management System (ADAMS) Accession No. ML17318A472], dated November 10, 2017, APS submitted Relief Request 56, which sought an extension to the third 10-year ISI interval for PVNGS Unit 2, as an alternative that provided an acceptable level of quality and safety pursuant to 10 CFR 50.55a(z)(1). The requested extension was beyond the one year extension permitted in, the ASME Code,Section XI, IWA-2430. As part of that relief request, APS indicated that the impractical relief requests for the PVNGS Unit 2 third 10-year ISI interval would be submitted within 12 months of the expiration of the original third 10-year interval for PVNGS Unit 2 in accordance with 10 CFR 50.55a(g)(5)(iii). Relief Request 56 was approved by NRC letter dated March 9, 2018 (ADAMS Accession No. ML18067A073).
NRC approval of this relief request is requested by March 17, 2019.
No new commitments are being made in this submittal.
102-07669-MLL/TNW ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Relief Request 58 - Unit 2 Impractical Examinations for the Third 10-Year ISI Interval Page 2 If you have any questions about this request, please contact Matthew S. Cox, Licensing Section Leader, at (623) 393-5753.
Sincerely, MLL/TNW/MDD/sma
Enclosure:
Relief Request 58 - Unit 2 Impractical Examinations for the Third 10-Year Inservice Inspection (ISI) Interval cc:
K. M. Kennedy NRC Region IV Regional Administrator S. P. Lingam NRC NRR Project Manager for PVNGS C. A. Peabody NRC Senior Resident Inspector for PVNGS Lacal, Maria L(Z06149)
Digitally signed by Lacal, Maria L(Z06149)
DN: cn=Lacal, Maria L(Z06149)
Date: 2018.03.17 11:16:25 -07'00'
Enclosure Relief Request 58 Unit 2 Impractical Examinations for the Third 10-Year Inservice Inspection (ISI) Interval
Enclosure Relief Request 58 - Unit 2 Impractical Examinations for the Third 10-Year ISI Interval 1
10 CFR 50.55a Request Number 58 Relief Request in Accordance with 10 CFR 50.55a(g)(5)(iii)
Inservice Inspection Impracticality The Palo Verde Nuclear Generating Station (PVNGS), Unit 2, Class 1 and 2 welds with limited examinations are included in Table 1 of Attachment 1 of this relief request. The content of this relief request includes the insights gained from guidance provided in Reference 1.
- 1. ASME Code Component(s) Affected The following Code Classes, Examination Categories, and Item Numbers apply.
Code Classes:
1 and 2 Examination Categories:
B-D, C-B, and C-F-1 Item Numbers:
B3.110, C2.22, and C5.11
2. Applicable Code Edition and Addenda
The Code of Record for the third 10-year Inservice Inspection interval is the 2001 Edition of ASME,Section XI, through the 2003 Addenda.
3. Applicable Code Requirement
The applicable Code Classes, Item, and Examination Categories are included in of this enclosure for each of the welds and areas limited. Table 1 is organized utilizing a sequence number that refers directly back to the specifics for each of the limitations for which relief is being sought.
4. Impracticality of Compliance
Arizona Public Service Company (APS) has determined that compliance with the Code requirements of achieving essentially 100 percent coverage of the welds listed in this request is impractical for Unit 2. In accordance with 10 CFR 50.55a(g)(5)(iii), this relief request is based on actual demonstrated limitations when evaluating or attempting to comply with the Code requirements in the performance of the examinations listed in Table 1.
The design of the plant has provided access for examinations, however, component design configurations with conditions resulting in examination limitations, such as geometric configurations of components or their welds, do not allow full required examination volume and/or coverage and thus this relief request addresses those conditions. Details for examination limitations in required examination coverage are provided in Attachment 1 of this enclosure.
5. Burden Caused by Compliance
Components and welds associated with the items listed in this relief request are constructed of standard design items meeting typical national standards that specify required configurations and dimensions including Class 1 Category B-D, Class 2 Category C-B and Class 2 Category C-F-1.
Enclosure Relief Request 58 - Unit 2 Impractical Examinations for the Third 10-Year ISI Interval 2
For the Class 1 Category B-D Nozzle-to-Vessel Welds of the pressurizer, the design configurations of these welds and obstructions do not allow for the required examination coverage.
For the Class 2 Category C-B Nozzle Inside Radius Sections, the design configuration of these nozzles does not allow for ultrasonic testing (UT) of the inside radius sections of these nozzles from the outside surface of the steam generator (SG) nozzles. The only way these limitations could be improved would be to modify the nozzle design.
The Class 2 Category C-F-1 Piping Welds are Pipe-to-Valve and Elbow-to-Valve welds.
Examinations are limited as the UT examination area is only accessible from the pipe, or elbow side of the weld.
Examinations have been performed to the maximum extent possible. Therefore, APS has determined that obtaining essentially 100 percent coverage is not feasible and is impractical without adding undue burden, increased radiation exposure, and/or potential damage to the plant or the component itself.
6. Proposed Alternative and Basis for Use
Proposed Alternative
- 1) Periodic system pressure tests and VT-2 visual examinations will continue to be performed in accordance with ASME Section Xl, Examination Category B-P, for Class 1 pressure retaining welds and items each refueling outage and Examination Category C-H for Class 2 pressure retaining welds and items each inspection period of Table IWB-2500-1 and Table IWC-2500-1, respectively.
- 2) Ultrasonic testing examinations will continue to be conducted to the maximum extent possible, and when required by ASME Section XI, will perform a 100 percent surface examination as noted in Attachment 1 of this enclosure.
Basis for Use 10 CFR 50.55a(g)(4) recognizes that throughout the service life of a nuclear power facility, components which 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 within the limitations of design, geometry and materials of construction of the welds and items described in Attachment 1 of this enclosure.
There is no plant-specific, or industry operating experience regarding potential degradation specific to the subject welds in this relief request.
For the Class 1 and 2 welds located inside the Containment of Unit 2, with limited examinations listed in Attachment 1 of this enclosure, operational leakage is monitored in accordance with the Technical Specification requirements. In addition, during outages, engineers perform walk-downs of systems inside the containment. This walk-down is performed to look for evidence of leakage accumulation and boric acid as well as system abnormalities that could affect plant performance. Also, system pressure tests are performed as required by the ASME Code,Section XI.
Enclosure Relief Request 58 - Unit 2 Impractical Examinations for the Third 10-Year ISI Interval 3
For the ASME Class 2 welds examined in accordance with Appendix VIII, Supplement 2, Qualification Requirements for Wrought Austenitic Piping Welds, ASME Section XI required examination coverage is limited when the weld can only be scanned from one side. The Performance Demonstration Qualification Summary for the qualified Electric Power Research Institute procedure, PDI-UT-2, PDI Generic Procedure for the Ultrasonic Examination of Austenitic Pipe Welds PDI-UT-2, in part states, the austenitic single side qualification documented in this summary demonstrates application of best available technology, but does not meet the requirements of 10 CFR 50.55a(b)(2)(xvi)(B). It should be noted that UT was performed through the weld to obtain the maximum possible Code required volume and, as shown in Attachment 1 of this enclosure, the theoretical beam path extends into the far side for the UT examinations performed.
Therefore, the UT examinations conducted using the Appendix VIII, Supplement 2, qualified procedures, provide reasonable assurance for the detection of flaws on the far side of welds where the ultrasonic beam has been transmitted even though not presently qualified.
Based on the limited UT examinations achieved, surface examinations (where applicable), any applicable leakage monitoring, and required system pressure tests with VT-2 visual examinations, no reasonable action can be taken by APS at this time to improve these examinations without applying impractical options. Therefore, the proposed alternative in this relief request will provide assurance of an acceptable level of quality and safety by providing reasonable assurance of structural integrity.
7. Duration of Proposed Alternative
This relief request is applicable to the original PVNGS Unit 2 Third 10-Year ISI Interval which began on March 18, 2007 and ends on March 17, 2017 and covers all the limited exams that have been identified for the entire interval in Unit 2. It is recognized that Relief Request 56 authorized an extension of the Unit 2 Third 10-Year ISI Interval to October 31, 2018 (Reference 2).
8. Precedents
NRC SER, Surry Power Station Unit No. 2 - Requests for Relief LMT-R01, 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 Inservice Inspection Interval, dated February 17, 2017, (ADAMS Accession No. ML16365A118)
NRC SER, Diablo Canyon Power Plant, Unit No. 1 - Relief Request NDE-SIF-U1 To Allow Use of Alternate American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Examination Requirements for the Third Inservice Inspection Interval, dated July 27, 2016, (ADAMS Accession No. ML16207A397)
NRC SER, Millstone Power Station, Unit No. 2 - Relief Requests For Limited Coverage Examinations Performed In The Fourth 10-Year Inservice Inspection Interval, dated July 13, 2016, (ADAMS Accession No. ML16172A135)
Enclosure Relief Request 58 - Unit 2 Impractical Examinations for the Third 10-Year ISI Interval 4
- 9. References
- 1. NRC presentation Coverage Relief Requests, Industry/NRC NDE Technical Information Exchange Public Meeting January 13-15, 2015, (ADAMS Accession No. ML15013A266)
- 2. NRC letter dated March 9, 2018, Palo Verde Nuclear Generating Station, Units 1, 2, and 3-Relief Request No. 56 to Extend Third 10-Year Inservice Inspection Interval for Unit 2, and to Adopt 2013 Edition of the ASME Code,Section XI, for the Fourth 10-Year Interval for Units 1, 2, and 3 (ADAMS Accession No. ML18067A073)
Enclosure Relief Request 58 - Unit 2 Impractical Examinations for the Third 10-Year ISI Interval 5
Introduction This attachment contains figures and tables that are used to depict the applicable locations, limitations and calculations for obtained coverage, materials and product forms, with UT examination angles and wave forms used, and the examination results for the welds or items associated with this relief request, including any applicable previous examination history.
Table 1 Relief Request Sequence No Weld Identification Number and Zone System Weld Description Size/Thickness Materials Indications Detected Examination Code Coverage Obtained Examination Limitations Applicable Figures and Tables Category: B-D, Item: B3.110 Requirement: Essentially 100% examination of the weld length 1.1 5-9 Zone 005 RC PZR Surge Nozzle-to-Vessel Weld 5T x 12 Dia Ferritic UT - None UT = 65.2%
Geometric Nozzle Design Configuration Location Figure 1-1, Picture 1-1, Figure 1-1-1, 1-1-2, Table 1-1-1 1.2 5-10 Zone 005 RC PZR Spray Nozzle-to-Vessel Weld 5T x 4 Dia Ferritic UT-None UT = 80.8%
Geometric Nozzle Design Configuration Location Figure 1-2, Figure 1-2-1, Table 1 1 1.3 5-11, 12, 13 &
14 Zone 005 RC PZR Vessel-to-Nozzle Weld 5T x 6 Dia Ferritic UT-None UT = 74.7%
Geometric Nozzle Design Configuration Location Figure 1-3, Figure 1-3-1, Table 1 1 Category: C-B, Item: C2.22 Requirement: Essentially 100% examination of the weld length 1.4 42-114-IR 42-115-IR Zone 042 SG SG 2 Nozzle Inside Radius Section for Main Steam 4.3 T x 32 Dia Ferritic NA UT = Not Performed 0%
Geometric Nozzle Design Configuration Limitation Location/Design Figure 1-4 Category: C-F-1, Item: C5.11 Requirement: Essentially 100% examination of the weld length 1.5 76-14 77-14 & 16 Zone 091 SI Pipe-to-Valve Weld 12 x Sch. 140 Austenitic PT-None UT-None PT=100%
UT = 50%
No Scans From Valve Side Location Figures 1-5a and 1-5b, Figure 1-5-1 and Table 1 1 1.6 86-8 Zone 103 SI Elbow-to-Valve Weld, 20 x Sch. 20 Austenitic PT-None UT-None PT=100%
UT = 50%
No Scans From Valve Side Location Figure 1-6, Figure 1-6-1 and Table 1-6-1
Enclosure Relief Request 58 - Unit 2 Impractical Examinations for the Third 10-Year ISI Interval 1.1 Weld 5 B3.110: Pressurizer Surge Nozzle-to-Vessel Weld SKIRT B Location Figure 1-1 This weld is in Zone 005 and was examined in inspection period 3 during the 2R20 outage in 2017. The Code Required Volume (CRV) was determined based on Section XI, Figure IWB-2500-7(a) and the corresponding required examination volume is shown in the Figures 1-1-1 and 1-1-2. Note that during the scan of the pressurizer surge nozzle-to-vessel weld 0°, 45°,
and 60° scans were performed. The volumetric examination only credits the 45° and 60° scans as shown in Table 1-1-1. It should be noted that there is no scan from the nozzle side of the weld due to geometry of the nozzle. This weld was examined in interval 2, and no limitations were noted. The configuration of the adjacent area was changed during heater replacement modifications. The current configuration has additional limitations in the form of obstructions from pad welds (Picture 1-1). These pads limit the scan of the required volume that prevents full coverage from being obtained.
Enclosure Relief Request 58 - Unit 2 Impractical Examinations for the Third 10-Year ISI Interval Figure 1-1 Weld 5-9 Scan Coverage Diagram 0, 45 and 60 Weld Pads 8 inches from the Nozzle Figure 1-1 Weld 5-9 Scan Coverage Diagram 0, 45 and 60 Weld Pads 11.5 inches from the Nozzle
Enclosure Relief Request 58 - Unit 2 Impractical Examinations for the Third 10-Year ISI Interval Table 1-1 Examination Coverage Summary Weld 5 12" Pressurizer Surge Nozzle-to-Vessel Weld CRV'^> = 2624.48 in^
Circumferential Scan Volume = 1835.42 in*
45° Volume =
1514.30 in*
60° Volume' = 921.60 in*
(1589.62 in*)
Angle and Wave Mode Axial Scans Clockwise Circumferential Counterclockwise Circumferential 45° S 57.6%
69.9%
69.9%
60° S 35.1% (60.5%)<=>
69.9%
69.9%
Code Coverage Total
=
65.2%
NOTES:
(1) S = Shear Wave (2) Clockwise and counterclockwise circumferential scans use the same percentage coverage as a 0° scan. This percent calculation for the circumferential scans is considered conservative as it does not credit the skews typically used by examiners to obtain greater coverage in a nozzle to shell weld.
(3) Code Coverage Total refers to the maximum percentage of the required examination volume that is effectively examined with the qualified examination procedures used. The total volume scanned for axial scans Is credited to 50% of the code coverage total and the other 50% of the scan volume is credited towards the two circumferential directions.
(4) Drawings used to build CAD models for the volumetric calculations are part of the Combustion Engineering Analytical Report for the Unit 2 pressurizer, Document ID NOOl-0604-00074.
(5) Note that the percent coverage of the 60° 35.1% coverage; however, the 45° and 60° scans are being credited for the total axial scan volume. The combined volume scanned for the 45° and 60° axial scans is 1589.62 in^ or 60.5% volume for the axial scan contribution to the Code Coverage Total.
1.2 Weld 5 B3.110: Pressurizer Sorav Nozzle-to-Vessel Weld MANWAY TOP VIEW Location Figure 1-2 This weld is in Zone 005 and was examined in Inspection Period 2 during the 2R16. The CRV was determined based on Section XI, Figure IWB-2500-7(a) and the corresponding required examination volume is shown in Figure 1-2-1. Note that during the scan of the pressurizer
Enclosure Relief Request 58 - Unit 2 Impractical Examinations for the Third 10-Year ISI Interval spray nozzle-to-vessel weld 0°, 45° and 60° scans were performed. The volumetric examination only credits the 45° and 60° scans as shown in Table 1-2-1. It should be noted that no scan was performed on nozzle side of weld due to geometry.
Figure 1-2 Weld 5-10 Scan Coverage Diagram 0°, 45° and 60° Scans
Enclosure Relief Request 58 - Unit 2 Impractical Examinations for the Third 10-Year ISI Interval 11 Table 1-2 Examination Coverage Summary Weld 5 4 Pressurizer Spray Nozzle-to-Vessel Head Weld (4)
CRV(4) = 1148.13 in3 Circumferential Scan Volume = 807.40 in3 45° Volume =
1023.73 in3 60° Volume = 1048.60 in3 Angle and Wave Mode (1)
Axial Scans Clockwise Circumferential (2)
Counterclockwise Circumferential (2) 45° S 89.1%
70.3%
70.3%
60° S 91.3%
70.3%
70.3%
Code Coverage Total (3) =
80.8%
NOTES:
(1) S = Shear Wave (2) Clockwise and counterclockwise circumferential scans use the same percentage coverage as a 0° scan. This percent calculation for the circumferential scans is considered conservative as it does not credit the skews typically used by examiners to obtain greater coverage in a nozzle to shell weld.
(3) Code Coverage Total refers to the maximum percentage of the required examination volume that is effectively examined with the qualified examination procedures used. The total volume scanned for axial scans is credited to 50%
of the code coverage total and the other 50% of the scan volume is credited towards the two circumferential directions.
(4) Drawings used to build CAD models for the volumetric calculations are part of the Combustion Engineering Analytical Report for the Unit 2 pressurizer, Document ID N001-0604-00074.
Enclosure Relief Request 58 - Unit 2 Impractical Examinations for the Third 10-Year ISI Interval 1.3 Weld 5-11. 5-12, 5-13 and 5 B3.110: Pressurizer Safety Nozzle-to-Vessel Weld MANWAY TOP \\TEW Location Figure 1-3 Welds 5-11, 5-12, 5-13 and 5-14 are all pressurizer safety nozzle-to-vessel welds located in Zone 005. Weld 5-11 was examined in inspection period 1 during the 2R15 outage; Weld 5-12 was examined in inspection period 3 during the 2R20 outage; Weld 5-13 was examined in inspection period 2 during the 2R16 outage and Weld 5-14 was examined in inspection period 3 during the 2R20 outage.
The CRV was determined based on Section XI, Figure IWB-2500-7(a) and the corresponding required examination volume is shown in Figure 1-3-1. Note that during the scan of the pressurizer safety nozzle-to-vessel welds, 0°, 45° and 60° scans were performed. The volumetric examination only credits the 45° and 60° scans as shown in Table 1-3-1. It should be noted that there was no scan performed on nozzle side of weld due to geometry.
Enclosure Relief Request 58 - Unit 2 Impractical Examinations for the Third 10-Year ZSl Interval Figure 1-3 Weld 5-11, 5-12, 5-13 and 5-14 Scan Coverage Diagram
^AFE_n VALVE '
NOZZLE
Enclosure Relief Request 58 - Unit 2 Impractical Examinations for the Third 10-Year ISI Interval 14 Table 1-3 Examination Coverage Summary Weld 5-11, 5-12, 5-13, 5 6 Pressurizer Safety Nozzle-to-Vessel Head Welds (4)(5)
CRV(4) = 1096.43 in3 Circumferential Scan Volume = 695.79 in3 45° Volume =
915.02 in3 60° Volume =
944.1 in3 Angle and Wave Mode (1)
Axial Scans Clockwise Circumferential (2)
Counterclockwise Circumferential (2) 45°S 83.4%
63.4%
63.4%
60°S 86.1%
63.4%
63.4%
Code Coverage Total (3) =
74.7%
NOTES:
(1) S = Shear Wave (2) Clockwise and counterclockwise circumferential scans use the same percentage coverage as a 0° scan. This percent calculation for the circumferential scans is considered conservative as it does not credit the skews typically used by examiners to obtain greater coverage in a nozzle to shell weld.
(3) Code Coverage Total refers to the maximum percentage of the required examination volume that is effectively examined with the qualified examination procedures used. The total volume scanned for axial scans is credited to 50% of the code coverage total and the other 50% of the scan volume is credited towards the two circumferential directions.
(4) Drawings used to build CAD models for the volumetric calculations are part of the Combustion Engineering Analytical Report for the Unit 2 pressurizer, Document ID N001-0604-00074.
(5) Due to the complex geometry of the pressurizer safety nozzle-to-vessel head weld, the lower portion of the weld and the upper portion were both modeled and rotated about an axis for volumes. Averages of the two volumes were used for the credited examination volumes.
Enclosure Relief Request 58 - Unit 2 Impractical Examinations for the Third 10-Year ISI Interval 1.4 Weld 42-114-IR and 42-115-IR - C2.22: Steam Generator No. 2 Head-to-Nozzle Inside Radius Section n.ST! ITT
<< Tiai.c iiMi wREn Location Figure 1-4-1 The steam nozzles on the Palo Verde steam generators protrude into the vessel by approximately 13 inches and do not have a typical inside radius (IR) area as depicted in ASME Section XI, Figures IWC-2500-4(a)-(d). Rather, the Palo Verde steam nozzle design is similar to the design depicted in the annulled Code Case N-311, Alternative Examination of Outlet Nozzle on Secondary Side of Steam GeneratorsSection XI, Division 1. Code Case N-311 provided an alternate IR surface examination where part of the surface would only be accessible from the inside of the secondary side of a steam generator. Code Case N-311 was to be incorporated in ASME Section XI when annulled in 2004; however, the alternate examination provided in N-311 has not been included in recent versions of ASME Section XI.
Scan plans were discussed within Palo Verde and with vendors to ultrasonically examine the alternate area identified in N-311. No ultrasonic methods were determined to be practical, so no relief was sought for an alternative ultrasonic examination volume.
Access to the inside surface of the steam nozzles is not readily available due to the internal design of the replacement steam generators. Access requires removal of multiple components and removal of welds internal to the secondary side of the steam generator. The work would expose the steam generator to foreign material risks. In addition, internal access to the steam nozzles poses a potential risk to employees as egress by the examiner, and/or immediate emergency retrieval efforts by response personnel, would be delayed due to the tortuous access path.
Enclosure Relief Request 58 - Unit 2 Impractical Examinations for the Third 10-Year ISl Interval From a design standpoint, an anaiysis in ANSALDO PV-RPM-13-000012 Rev. 2, Structural and fatigue analysis of the steam outlet nozzle, has been performed on this nozzle. The results of this analysis shows that the nozzie including its IR Section do not exceed ASME Class 1 or 2 requirements.
1.5 76-14, 77-14 and 77 C5.ll: Low Pressure Safety Injection, Pipe-to-Valve Weld 76-13 76-14 Location Figure l-5a Weld 76-14 is in Zone 091 and was examined in Inspection Period 3 during the 2R20 outage.
The CRV was determined based on Section XI, Figure IWC-2500-7(a) and the corresponding required examination volume shown in Figure 1-5-1. The 45° and 60° degree shear wave scan was conducted on weld 76-14 as well as a 60° refracted longitudinal wave examination due to the limited access of the weid.
77-16 I 77-14 Location Figure l-5b Welds 77-14 and 77-16 are located in Zone 091 and were both examined in Inspection Period 3 during the 2R20 outage. The CRV was determined based on Section XI, Figure IWC-2500-7(a) and the corresponding required examination volume shown in Figure 1-5-1.
Enclosure Relief Request 58 - Unit 2 Impractical Examinations for the Third 10-Year ISI Interval Figure 1-5 Weld 76-14, 77-14 and 77-16 Coverage Diagram 4Sdeg.
of Required Exam Vol.
Table 1-5 Examination Coverage Summary Weld 76-14, 77-14, 77 Pipe-to-Valve Pipe 12" Sch. 140 - 1.125" Angle and Wave Mode Upstream Axial Upstream Circumferential Downstream Axial Downstream Circumferential 45-> S 100%
100%
0%
0%
60° S 100%
N/A 0%
N/A 60° RL 100%
N/A 0%
N/A N/A N/A N/A N/A N/A Code Coverage Total =
50%
NOTES:
(1) S = Shear Wave, or RL = Refracted Longitudinal Wave.
(2) Code Coverage Total refers to the maximum percentage of the required examination volume that is effectively examined with the qualified examination procedures used.
Enclosure Relief Request 58 - Unit 2 Impractical Examinations for the Third 10-Year ISI Interval 1.6 Weld 86 C5.ll: Refuelinq Water Suction "A" Train. Elbow-to-Valve Weld Location Figure 1-6 Weld 86-8 is in Zone 103 and was examined in Inspection Period 3 during the 2R20 outage.
The CRV was determined based on Section XI, Figure IWC-2500-7(a) and the corresponding required examination volume shown in Figure 1-6-1. The 45° and 60° shear wave scans were conducted on weld 86-8 as well as a 70° shear wave scan due to the limited access.
Figure 1-6 Weld 86-8, Coverage Diagram 60 deg.
70 deg.
45 deg.
I I = Required Exam Vol.
Enclosure Relief Request 58 - Unit 2 Impractical Examinations for the Third 10-Year ISI Interval 19 Table 1-6 Examination Coverage Summary Weld 86 Elbow-to-Valve Pipe 20 Sch. 20 - 0.375 Angle and Wave Mode (1)
Upstream Axial Upstream Circumferential Downstream Axial Downstream Circumferential 45° S 100%
100%
0%
0%
60° S 100%
N/A 0%
N/A 70° S 100%
N/A 0%
N/A N/A N/A N/A N/A N/A Code Coverage Total (2) =
50%
NOTES:
(1) S = Shear Wave (2) Code Coverage Total refers to the maximum percentage of the required examination volume that is effectively examined with the qualified examination procedures used.