ML022060297
| ML022060297 | |
| Person / Time | |
|---|---|
| Site: | Salem  (DPR-070) |
| Issue date: | 07/12/2002 |
| From: | Salamon G Public Service Enterprise Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML022060297 (121) | |
Text
Relief Request: S1-RR-BO1 Second Ten-Year Interval Inservice Inspection NDE Exam Limitations Salem Unit I Attachment I
Relief Request: S1-RR-B01 Second Ten-Year Interval Inservice Inspection NDE Exam Limitations Salem Unit 1 NRC Approved (Yes or No):
Date:
Ref:
NOTE:
Salem Unit 1 - Second Ten-Year Interval Inservice Inspection (ISI) inservice inspection examinations were performed between February 27, 1988 (start) and May 19, 2001 (end). During this time Salem Unit 1 was shutdown for an extended period (April 4, 1995 through April 17, 1998 - 36 months and 10 days).
Component Description Salem Unit 1 NDE exam limitations of Class 1 bolting components and welds located upon pressure vessels and piping systems ASME Section XI Class:
Class 1 Code Requirement Salem Unit 1 Second Ten-Year Interval Inservice Inspection (ISI) inservice inspection examinations were performed in accordance with the requirements of ASME Boiler and Pressure Vessel Code Section Xl, 1983 Edition up through and including Summer 1983 Addenda Article IWB-2500 to the extent practical. Table IWB-2500-1 defines examination requirements for Class 1 components. The table contains information associated with the identification of components to be examined by nondestructive examination; this includes the applied nondestructive examination (NDE) method, acceptance standard, and extent of exam coverage and exam frequency.
The 1999 Edition of 10CFR50.55a "Codes and Standards" was revised by a Federal Register Notice dated September 22, 1999 (64FR51400) that defined new requirements for coverage and examination demonstrations. These requirements affected both class 1 and 2 bolting, piping system welds, and reactor pressure vessel nondestructive examinations.
ASME, Section Xl, 1983 Edition, Summer 1983 Addenda, requires volumetric and/or surface and visual examinations be performed upon components and welds identified within Table IWB-2500-1 Exam Categories B-A, B-B, B-F, B-G-I, B-J, and B-K-I.
A. Exam Category B-A Pressure Retaining Welds in Reactor VesselsSection XI Exam Category B-A required volumetric weld examinations be performed upon the accessible length of one beltline region circumferential and longitudinal weld (Item Numbers B1.11 and B1.12 respectively); closure 1
Relief Request: SI-RR-B01 Second Ten-Year Interval Inservice Inspection NDE Exam Limitations Salem Unit I head circumferential and meridional welds (Item Numbers B13.21 and B13.22 respectively) and the associated reactor pressure vessel flange welds (Items B1.30 and B1.40).
B. Exam Category B-B Pressure Retaining Welds in Vessels Other Than Reactor Vessels Section Xl Exam Category B-B required volumetric weld examinations be performed essentially 100% of the weld length upon circumferential and 12 inches of intersecting longitudinal pressure retaining welds, as necessary within various pressure vessels. The examinations may be limited to one vessel among the group of vessels performing a similar function.
C. Exam Category B-D Full Penetration Welds of Nozzles in Vessels Inspection Program B Section Xl Exam Category B-D required volumetric examinations be performed upon all nozzle to vessel welds and nozzle inside radius sections.
D. Exam Categories B-J, and B-F Retaining Piping Welds Section Xl Exam Categories B-J, and B-F required surface and volumetric weld examinations be performed upon welds greater than 4" diameter.
Piping long seams were conducted in accordance with the requirements of ASME Section Xl Code Case N-524, Alternative Examination Requirements for Longitudinal Welds in Class I and 2 Piping.
E. Exam Category B-G-1 Pressure Retaining Bolting, 2 in. And Less In Diameter Section Xl Exam Category B-G-1 required volumetric examinations be performed upon studs greater than 2" diameter.
F. Exam Category B-K Welded Integral Attachments PSEG Nuclear conducted welded integral attachment weld exams in accordance with the requirements imposed by ASME Section Xl Code Case N-509, Alternative Rules for the Selection and Examination of Class 1,2 and 3 Integrally Welded Attachments. Category B-K, Integral Attachments for Class 1 Vessels, Piping, and Pumps and Valves require surface examinations be conducted.
2
Relief Request: S1-RR-BO1 Second Ten-Year Interval Inservice Inspection NDE Exam Limitations Salem Unit 1 The attached table contains detailed information related to the explanation of those components demonstrating inadequate code exam coverage extent due to inaccessibility, physical limitation or obstruction.
Basis for Relief:
Pursuant to 10CFR50.55a (g)(5)(iii), relief is requested from ASME Xl examination requirements for the performance of the following bolting, piping and vessel welds due to exam limitations. The table herein identifies those 2 nd Ten Year Interval ISI inservice inspection nondestructive examinations, contained within the Salem Unit 1 ISI Program Long Term Plan, whose NDE exams were found to be inaccessible, physically limited or partially obstructed and therefore incapable of fully meeting code coverage requirements for examination extent.
These components are identified within the attached table and supplemented by additional descriptive details (sketches, illustrations, and/or drawings) enclosed within Appendix A.
Subject components contained herein have received inservice inspection NDE examinations to the "extent practical" within the limitations of design, geometry and materials of construction of the components as allowed by Code. These components have also undergone necessary volumetric examination by radiography and/or surface examinations during fabrication, in accordance with approved construction/fabrication code requirements providing adequate assurance for the structural integrity of the components prior to plant operation.
In addition, these components have been subjected to a visual examination for leakage after completion of each refueling outage.
PSEG Nuclear utilizes approved technical procedures written in accordance to applicable ASME Code section/paragraph criterion for area/volume requirements. Plant procedures require the documentation of the location and cause of the limitation.
A. Exam Category B-A Pressure Retaining Welds in Reactor Vessels Reference applicable sections of this category within the table attached to identify specific component information and explanation of the limitation(s) encountered.
Full Code required coverage is impractical for the identified subject components since the Reactor Pressure Vessel (RPV) would require design modifications that would impose a significant burden to PSEG Nuclear.
PSEG Nuclear has elected to examine the subject components to the extent practical and has determined them to be acceptable with no observed signs of degradation. In addition, other RPV welds have been examined to the extent required by the Code and also found to be acceptable with no 3
Relief Request: S1-RR-B01 Second Ten-Year Interval Inservice Inspection NDE Exam Limitations Salem Unit 1 observed signs of degradation. Also, VT-2 visual examinations performed in conjunction with system pressure testing after each refueling outage found these welds to be acceptable with no leakage observed.
B. Exam Category B-B Pressure Retaining Welds in Vessels Other Than Reactor Vessels Reference applicable sections of this category within the table attached to identify specific component information and explanation of the limitation(s) encountered.
Full Code required coverage is impractical for the subject components since these vessels would require design modifications that would impose a significant burden to PSEG Nuclear. PSEG Nuclear has examined these component welds to the extent practical and determined them to be acceptable with no observed signs of degradation. In addition, other similar vessel welds have been examined to the extent required by the Code and also found to be acceptable with no observed signs of degradation. Also, VT 2 visual examinations performed in conjunction with system pressure testing after each refueling outage found these welds to be acceptable with no leakage observed.
C. Exam Category B-D Full Penetration Welds of Nozzles in Vessels Inspection Program B Reference applicable sections of this category within the table attached to identify specific component information and explanation of the limitation(s) encountered.
Full Code required coverage is impractical for the subject components since the nozzle identified within the table would require design modifications that would impose a significant burden to PSEG Nuclear. PSEG Nuclear has examined these component welds to the extent practical and determined them to be acceptable with no observed signs of degradation. In addition, other similar vessel welds have been examined to the extent required by the Code and also found to be acceptable with no observed signs of degradation.
Also, VT-2 visual examinations performed in conjunction with system pressure testing after each refueling outage found these welds to be acceptable with no leakage observed.
D. Exam Category B-J and B-F Retaining Piping Welds Reference applicable sections of this category within the table attached to identify specific component information and explanation of the limitation(s) encountered.
4
Relief Request: S1-RR-B01 Second Ten-Year Interval Inservice Inspection NDE Exam Limitations Salem Unit 1 Required Code coverage is impractical for the subject welds since the piping system would require design modifications that would impose a significant burden to PSEG Nuclear. PSEG Nuclear has examined these welds to the extent practical and determined them to be acceptable with no observed signs of degradation. In addition, other similar piping welds have been examined to the extent required by the Code and also found to be acceptable with no observed signs of degradation. Also, VT-2 visual examinations performed in conjunction with system pressure testing after each refueling outage found these welds to be acceptable with no leakage observed.
Code required volumetric examinations are conducted by ultrasonic examination from both the upstream and downstream directions of piping welds. Ultrasonic examination of certain terminal ends and structural discontinuities are considered to be impractical due to their configuration and material acoustic properties.
The EPRI Performance Demonstration Initiative (PDI) is in agreement with the NRC's September 22, 1999 Final Rule regarding single side access for piping. The Final Rule requires if access is available, austenitic steel welds shall be scanned in each of the four directions (parallel and perpendicular to the weld) where required.
PDI has not been able to qualify a single side examination procedure technique that is capable of demonstrating equivalency for a two-sided examination procedure technique on austenitic piping welds. Current technology is not capable of reliably detecting or sizing flaws on the far side of an austenitic weld for configurations common to nuclear applications. Ultrasonic examination of ferritic steel welds requires scanning in the two axial scan directions. Circumferential scanning is required in the remaining two directions only when axial indications were noted during preservice inspections. Coverage credit may be taken for single side exams on ferritic piping. However, for austenitic piping, a procedure must be qualified with flaws on the inaccessible side of the weld.
As stated earlier, current technology is not capable of reliably detecting or sizing flaws on the far side of austenitic weld for configurations common to US nuclear applications. To demonstrate that the best available technology was applied, PDI provides a best effort qualification instead of a complete single sided qualification. PDI Performance Demonstration Qualification Summary (PDQS) austenitic piping certificates list the limitation that single side examination is performed on a best effort basis. When performing single side access of austenitic stainless steel piping welds the best available techniques are used from the accessible side of the weld, as qualified through the PDI.
5
Relief Request: S1-RR-BO1 Second Ten-Year Interval Inservice Inspection NDE Exam Limitations Salem Unit I When the examination area is limited to one side of an austenitic weld, examination coverage does not comply with 1 OCFR50.55a(b)(2)(xv)(A) or the ASME Section Xl requirements and proficiency demonstrations do not comply with 10CFR50.55a(b)(2)(xvi) and full coverage credit may not be claimed.
PSEG Nuclear considers exams accessed from a single side of an austenitic piping welds to be fully examined to the extent practical.
E. Exam Category B-G-1 Pressure Retaining Bolting, > 2 in. In Diameter Reference applicable sections of this category within the table attached to identify specific component information and explanation of the limitation(s) encountered.
Full Code required coverage is impractical for the subject components since access to some bolting is obstructed. This would require design modifications and would impose a significant burden to PSEG Nuclear. PSEG Nuclear has examined several of these components contained within the same location and determined them to be acceptable with no observed signs of degradation.
Also, similar bolting located on other pumps has been examined to the extent required by the Code and also found to be acceptable with no observed signs of degradation. In addition, a VT-2 visual examination is performed upon each stud in conjunction with the system pressure testing after each refueling outage. This bolting has been found to be acceptable with no leakage observed. Further, a visual examination is conducted of each installed stud to ensure no physical damage that may have resulted from the presence of boric acid and has been found to be acceptable with no damage observed.
F. Exam Category B-K Welded Integral Attachments Reference applicable sections of this category within the table attached to identify specific component information and explanation of the limitation(s) encountered.
Full Code required coverage is impractical for the subject welds since the integral attachment would require design modifications and would impose a significant burden to PSEG Nuclear. In addition, removal of the component support attached to pump would result in the need to redesign the system's configuration in order to achieve access to the area obstructed. PSEG Nuclear has examined these welds to the extent practical and determined them to be acceptable with no observed signs of degradation. In addition, other similar vessel welds have been examined to the extent required by the Code and also found to be acceptable with no observed signs of degradation.
In addition, VT-2 visual examinations performed in conjunction with system 6
Relief Request: S1-RR-B01 Second Ten-Year Interval Inservice Inspection NDE Exam Limitations Salem Unit I pressure testing after each refueling outage found these welds to be acceptable with no leakage observed.
Alternative Examination For the 3 rd Ten-Year ISI Interval, inservice inspection examinations will be performed in accordance with the Final Rule requirements and ASME Section XI 1995 Edition up through and including 1996 Addenda Article IWB-2500 and NRC approved RI-ISI requirements to the extent practical.
PSEG Nuclear proposes to perform NDE examinations upon the components identified in the exam categories below using the current state of the art techniques as demonstrated through the EPRI PDI Program to the extent practical.
A. Exam Category B-A Pressure Retaining Welds in Reactor Vessels Where the component will not allow an ultrasonic angle beam examination from both sides of the weld, the following will be performed using the best available technology as demonstrated through the EPRI PDI program:
Similar metal welds, will be examined to the extent practical using personnel and techniques qualified and demonstrated through the EPRI PDI, as necessary.
"* System pressure test examinations will be performed per ASME Xl requirements B. Exam Category B-B Pressure Retaining Welds in Vessels Other Than Reactor Vessels Where the component will not allow an ultrasonic angle beam examination from both sides of the weld, the following will be performed using the best available technology as demonstrated through the EPRI PDI program:
Similar metal welds, will be examined to the extent practical using personnel and techniques qualified and demonstrated through the EPRI PDI, as necessary.
"* System pressure test examinations will be performed per ASME Xl requirements 7
Relief Request: S1-RR-BO1 Second Ten-Year Interval Inservice Inspection NDE Exam Limitations Salem Unit I C. Exam Category B-D Full Penetration Welds of Nozzles in Vessels Inspection Program B Where the component will not allow an ultrasonic angle beam examination from both sides of the weld or upon the nozzle inner radius section, the following will be performed using the best available technology as demonstrated through the EPRI PDI program:
" Similar metal welds and inner radius sections will be examined to the extent practical using personnel and techniques qualified and demonstrated through the EPRI PDI, as necessary.
"* System pressure test examinations will be performed per ASME XI requirements D. Exam Category B-J, and B-F Retaining Piping Welds Where the component will not allow an ultrasonic angle beam examination for axial scans (upstream and downstream), the following will be performed using the best available technology as demonstrated through the EPRI PDI program:
Similar metal welds will be examined in at least one axial direction and two circumferential scans adjacent to the weld and upon the weld using personnel and techniques qualified and demonstrated through the EPRI PDI program for single sided access relating to the material type to be examined.
" Austenitic-to-Inconel dissimilar metal welds will be examined in at least one axial direction and two circumferential scans adjacent to the weld and upon the weld using personnel and techniques qualified and demonstrated through the EPRI PDI program for single sided access relating to the material type to be examined
"* The code required surface and system pressure test examinations will be performed per ASME Xl requirements.
PSEG Nuclear is currently preparing its submittal for a Risk Informed Inservice Inspection (RI-ISI) Program in accordance with NRCs EPRI approved methodology for both Salem Units class 1 and 2 systems for NRC approval. During the conduct of RI-ISI program preparation, PSEG Nuclear will consider the non-selection of those components that have been deemed inaccessible, physically limited or partially obstructed portions provided the NRCs approved RI-ISI EPRI methodology allows.
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Relief Request: S1-RR-BO1 Second Ten-Year Interval Inservice Inspection NDE Exam Limitations Salem Unit I E. Exam Category B-G-1 Pressure Retaining Bolting, 2 in. And Less In Diameter NDE personnel will utilize the single side access straight beam ultrasonic exam technique having been satisfactory demonstrated at the PDI. PSEG Nuclear has since elected to perform straight beam (0- degree) examinations from the accessible surface of the studs using PDI qualified individuals to perform these exams. PSEG Nuclear did not re-perform previous exams (for the 11 and 12 Reactor Coolant Pump studs) using the current state of the art technique that would have resulted in 100% code coverage being achieved.
These exams are scheduled for November 2005 during RFO17. Straight beam UT examinations were conducted upon the 13 and 14 Reactor Coolant Pump studs using this technique and determined to be satisfactory.
Surface and system pressure test examinations will be performed per ASME XI requirements F. Exam Category B-K Welded Integral Attachments These examinations will be performed in accordance with the requirements of ASME Section XI 1995 Edition up through and including 1996 Addenda Article IWB-2500.
Applicability This Relief Request is applicable to the following:
0 Salem Unit 1 - Second Ten-Year Inservice Inspection Interval 9
Document Control Desk LRN-02-0255 Table I Relief Request SI-RR-B01 Salem Unit 1 - 2nd Inseervice Inspection Ten-Year NDE Exam Limitations Summary Interval/
Outage Exam Date System Component Geometric ASME Item Sketch Exam Completed Code Required Exam Information Augmented No.
Period/
Name Identification Configuration Category No.
No.
Method Exam Volume and Limitation Description Exam Outage No.
IRXX Limited Amount 000900 2-3-2 14 5/14/01 RPV 1-RPV-1042B Upper Long Seam @ 7 B-A B1. 12 19 & 1 UT 66%
IWB-2500-3 This UT exam was performed in May 2001 using No degrees approved PDI exam techniques. 45-degree shear and 45-and 70-degree Refracted Longitudinal (RL) transducers were used. The UT exam was limited due to the outlet nozzle being located immediately adjacent to the long seam. The location of the outlet nozzle's boss prevented scanning in the areas adjacent to the weld and contributed to the examination being limited.
Recordable indications were noted. The total estimated coverage achieved was 66%. Evaluation of the indications were determined to be acceptable LAW with ASME XI IWB-3000. VT-3 exams of the vessel's internals and external VT-2 exams conducted during 1 R14 (May 2001) did not identify any signs of leakage, or loss of structural integrity.
001200 2-3-2 14 5/14/01 RPV 1-RPV-10042 Lower Shell to Bottom B-A B1.11 19 & 1 UT 56%
IWB-2500-1 This UT exam was performed in May 2001 using No Head (Circ Weld) approved PDI exam techniques. 45-degree shear and 45 and 70-degree Refracted Longitudinal (RL) transducers were used. The UT exam was limited due to the six (6) core guide lugs being integrally attached to the vessel wall and interfering with scan access. The UT exam was performed with recordable indications noted and evaluated to be acceptable per the requirements of ASME Xl IWB-3000. The total estimated coverage achieved was 56%. VT-3 exams of the vessels internals and external VT-2 exams conducted during 1 R14 (May 2001) did not identify any signs of leakage, loss of structural integrity within this area.
001300 2-3-2 14 5/14/01 RPV 1-RPV-4043 Lower Head Disc to B-A B1.21 19 & 1 UT 14%
IWB-2500-3 This UT exam was performed in May 2001 using No Peel Segments approved PDI exam techniques. 45-degree shear and 45-and 70-degree Refracted Longitudinal (RL) transducers were used. The UT exam was limited due to the incore instrument penetrations that are located within the lower head (reference attached sketch) interfering with scan access. The total estimated coverage achieved was 14%. The UT exam was performed with no recordable indications noted. VT-3 of the vessels internals and external Vr-2 exams conducted during 1 R14 (May 2001) did not identify any signs of leakage, loss of structural integrity within this area.
1
Document Control Desk LRN-02-0255 Table I Relief Request S1-RR-BO1 Salem Unit 1 - 2nd Inseervice Inspection Ten-Year NDE Exam Limitations 1-RPV-6046B Dollar Plate Closure Weld B-A B1.21 UT I
9 I.
t 1-PV-1I043-A Mendional Weld @ 270 degrees in Lower Head B-A B1.22 19&1 UT 40%
[Note: Due to personnel exposure concerns coverage was estimated.]
59%
IWB-2500-3 IWB-2500-3 This UT exam was performed in April 2001 using approved PDI exam techniques A 60-degree Refracted Longitudinal (RL) UT Exam was performed with no recordable indications noted The head's shroud was raised to achieve maximum access to the weld. The examination was performed above and below the weld axially and circumferentially in the accessible areas between the CRD penetrations.
Due to the dose rates on the head being in excess of 1R/hr, precise measurement of the weld length examined was not possible. Therefore, only an estimation of the coverage was provided. The total estimated code coverage achieved was 40%. There have been no problems identified to date associated with Salem Unit 2 reactor pressure vessel closure head. A'VT2 examination for the detection of boric acid deposits during 1R14 (May 2001) did not identify any signs of leakage or loss of structural integrity within this area. System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld.
These UT exams were performed in May 2001 using approved PDI exam techniques. 45-degree shear and 45-and 70-degree Refracted Longitudinal (RL) were used. The lower head meridional weld exam was restricted due to the inaccessibility caused by the the lower heads in core instrument penetrations which interfered with scanning access. The examination was conducted from both sides of the weld in the axial and circumferential directions for the entire accessible length.
The total estimated weld length equals 53.5'. The thickness is approximately 7.0". Approximately 31.5" of weld length was examined full volume. The total estimated coverage achieved was 59%. The exam were performed with no recordable indications noted. VT-3 of the vessels internals and exteranl VT-2 exams conducted during 1 R14 (May 2001) did not identify any signs of leakage, loss of structural integrity within this area. System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage.
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2 14 4/23/01 RPV 004400 001400 2-3-2 2-3-2 14 5/14/01 RPV No NO 1
Document Control Desk LRN-02-0255 Table I Relief Request S1-RR-BO1 Salem Unit 1 - 2nd Inseervice Inspection Ten-Year NDE Exam Limitations Meridional Weld @ 330 degrees in Lower Head B-A B1.22 19& 1 UT 59%
IWB-2500-3 These UT exams were performed in May 2001 using approved PDI exam techniques. 45-degree shear and 45-and 70-degree Refracted Longitudinal (RL) were used. The lower head meridional exam was restricted due to the accessibility issues associated with the lower head in core instrument penetrations. The examination was conducted from both sides of the weld in the axial and circumferential directions for the entire accessible length. The total estimated weld length equals 53.5".
The thickness is approximately 7.0". Approximately 31.5" of weld length was examined full volume. The total estimated coverage achieved was 59%. The exam were performed with no recordable indications noted. VT-3 of vessel internals and external VT-2 exams conducted during 1R14 (May 2001) did not identify any signs of leakage, loss of structural integrity within this area.
System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage.
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i Meridional Weld @ 30 degrees in Lower Head B-A B1.22 19&1 UT 5954 IWVB-2500-3 These UT exams were performed in May 2001 using approved PDI exam techniques. 45-degree shear and 45-and 70-degree Refracted Longitudinal (RL) were used. The lower head meridional exam was restricted due to the accessibility issues associated with the lower head in core instrument penetrations. The examination was conducted from both sides of the weld in the axial and circumferential directions for the entire accessible length. The total estimated weld length equals 53.5".
The thickness is approximately 7.0". Approximately 31.5" of weld length was examined full volume. The total estimated coverage achieved was 59%. The exam were performed with no recordable indications noted. VT-3 of vessel internals and external VT-2 exams conducted during 1 R14 (May 2001) did not identify any signs of leakage, loss of structural integrity within this area.
System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage.
3 2-3-2 14 5/14/01 RPV 1 -RPV-1-043-B 001500 001600 2-3-2 14 No 5/14/01 RPv 1-RPV-1043-C No
Document Control Desk LRN-02-0255 Table I Relief Request S1-RR-B01 Salem Unit 1 - 2nd Inseervice Inspection Ten-Year NDE Exam Limitations Meridional Weld @ 90 degrees in Lower Head Meridional Weld @ 150 degrees in Lower Head B-A B-A B1.22 B1.22 19&1 19&1 UT UT 59%
59%
IWB-2500-3 IWB-2500-3 These UT exams were performed in May 2001 using approved PDI exam techniques. 45-degree shear and 45-and 70-degree Refracted Longitudinal (RL) were used. The lower head meridional exam was restricted due to the accessibility issues associated with the lower head in core instrument penetrations. The examination was conducted from both sides of the weld in the axial and circumferential directions for the entire accessible length. The total estimated weld length equals 53.5".
The thickness is approximately 7.0. Approximately 31.5" of weld length was examined full volume. The total estimated coverage achieved was 59%. The exam were performed with no recordable indications noted. VT-3 of vessel internals and external VT-2 exams conducted during 1 R14 (May 2001) did not identify any signs of leakage, loss of structural integrity within this area.
System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage.
These UT exams were performed in May 2001 using approved PDt exam techniques. 45-degree shear and 45-and 70-degree Refracted Longitudinal (RL) were used. The lower head meridional exam was restricted due to the accessibility issues associated with the lower head in core instrument penetrations. The examination was conducted from both sides of the weld in the axial and circumferential directions for the entire accessible length. The total estimated weld length equals 53.5'.
The thickness is approximately 7.0". Approximately 31.5" of weld length was examined full volume. The total estimated coverage achieved was 59%. The exam were performed with no recordable indications noted. VT-3 of vessel internals and external VT-2 exams conducted during 1 R14 (May 2001) did not identify any signs of leakage, loss of structural integrity within this area, System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage.
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4 001700 001600 2-3-2 2-3-2 14 14 5/14/01 5/14/01 RPV RPV 1-RPV-1043-D 1-RPV-1043-E No No
Document Control Desk LRN-02-0255 Salem Unit 1 - 2nd 1-RPV-1043-F 1 -RPV-1046A Meridional Weld @ 210 degrees in Lower Head Closure Head Meridional Weld @ 300 degrees Table I Relief Request S1-RR-BO1 Inseervice Inspection Ten-Year NDE Exam Limitations B-A B-A 81.22 B1.22 19 &1 UT UT 59%
83%
IWB-2500-3 IWB-2500-3 These UT exams were performed in May 2001 using approved PDI exam techniques. 45-degree shear and 45-and 70-degree Refracted Longitudinal (RL) were used. The lower head meridional exam was restricted "due to the accessibility issues associated with the lower head in core instrument penetrations. The examination was conducted from both sides of the weld in the axial and circumferential directions for the entire accessible length. The total estimated weld length equals 53.5".
The thickness is approximately 7.0". Approximately 31.5" of weld length was examined full volume. The total estimated coverage achieved was 59%. The exam were performed with no recordable indications noted. VT-3 of vessel internals and external VT-2 exams conducted during 1 R14 (May 2001) did not identify any signs of leakage, loss of structural integrity within this area.
System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage.
These UT exams were performed in April 2001 using approved PDI exam techniques. A 60-degree Refracted Longitudinal (RL) UT exam was performed with no recordable indications noted. The head's shroud was raised to achieve maximum access to the weld. The exam was partially restricted due to the closure head's transition area where the flange weld transitions to the head peel segment. The examination was conducted from both sides of the weld in the axial and circumferential directions for the entire accessible length not covered by the shroud. The total estimated weld length equals 53.5". The thickness is approximately 7.0". Approximately 44.5" of weld length was examined full volume. The total estimated coverage achieved was 83%. System leakage tests (vI'2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld.
No No 5
001900 004500 2-3-2 2-3-2 14 14 5/14/01 4/20/01 RPV RPV 1
Document Control Desk LRN-02-0255 Table I Relief Request S1-RR-BO1 Salem Unit 1 - 2nd Inseervice Inspection Ten-Year NDE Exam Limitations I
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T 7
7
.... ---7 1-RPV-1046B Closure Head Meridional Weld @ 0 degrees B-A B1.22 1
UT 68%
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-
1-RPV-1046C Closure Head Meridioanl Weld @ 60 degrees B-A B1.22 1
UT 83%
IWB-2500-3 These UT exams were performed in April 2001 using approved PDI exam techniques. A 60-degree Refracted Longitudinal (RL) UT exam was performed with no recordable indications noted. The head's shroud was raised to achieve maximum access to the weld. The exam was partially restricted due to the closure head's transition area where the flange weld transitions to the head peel segment. In addition, the examination was limited 3-5/8' to 9-5/8' (6") due to presence of lifting lugs attached to the closure head located at 0, 120 and 240 degrees. The total estimated weld length equals 53.5'. The thickness is approximately 7.0'.
Approximately 27" of weld length was examined full volume. The total estimated coverage achieved was 68%. System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld.
These UT exams were performed in April 2001 using approved PDI exam techniques. A 60-degree Refracted Longitudinal (RL) UT exam was performed with no recordable indications noted. The head's shroud was raised to achieve maximum access to the weld. The exam was partially restricted due to the closure head's transition area where the flange weld transitions to the head peel segment. The examination was conducted from both sides of the weld in the axial and circumferential directions for the entire accessible length not covered by the shroud. The total estimated weld length equals 53.5". The thickness is approximately 7.0.
Approximately 44.5" of weld length was examined full volume. The total estimated coverage achieved was 83%. System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld.
6 2-3-2 14 4V21/01 RPV 004600 004700 2-3-2 14 4/20/01 RPV No No
Document Control Desk LRN-02-0255 Table I Relief Request S1-RR-BO1 Salem Unit 1 - 2nd Inseervice Inspection Ten-Year NDE Exam Limitations Closure Head Meridioanl Weld @ 120 degrees B-A 81.22 UT 68%
IWB-2500-3 These UT exams were performed in April 2001 using approved PDI exam techniques. A 60-degree Refracted Longitudinal (RL) UT exam was performed with no recordable indications noted. The head's shroud was raised to achieve maximum access to the weld. The exam was partially restricted due to the closure head's transition area where the flange weld transitions to the head peel segment. In addition, the examination was limited 3-5/8" to 9-5/8' (6") due to presence of lifting lugs attached to the closure head located at 0, 120 and 240 degrees, The total estimated weld length equals 53.5". The thickness is approximately 7.0".
Approximately 27' of weld length was examined full volume. The total estimated coverage achieved was 68%. System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld.
t I
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4,-I 4
I I-----------------t...
4 Closure Head Meridional Weld @ 180 degrees B-A B1.22 UT 83%
IWB-2500-3 These UT exams were performed in April 2001 using approved PDI exam techniques. A 60-degree Refracted Longitudinal (RL) UT exam was performed with no recordable indications noted. The head's shroud was raised to achieve maximum access to the weld. The exam was partially restricted due to the closure head's transition area where the flange weld transitions to the head peel segment. The examination was conducted from both sides of the weld in the axial and circumferential directions for the entire accessible length not covered by the shroud. The total estimated weld length equals 53.5". The thickness is approximately 7.0".
Approximately 44.5" of weld length was examined full volume. The total estimated coverage achieved was 83%. System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld.
7 004800 2-3-2 14 4/20/01 RPV 1-RPV-1046D 004900 2-3-2 14 4/20/01 RPV No 1-RPV-1046E No 1
1-
Document Control Desk LRN-02-0255 Salem Unit 1 - 2nd Table I Relief Request S1-RR-BO1 Inseervice Inspection Ten-Year NDE Exam Limitations Closure Head Meridional Weld @ 240 degree B-A B1.22 UT 68%
IWB-2500-3 These UT exams were performed in April 2001 using approved PDI exam techniques. A 60-degree Refracted Longitudinal (RL) UT exam was performed with no recordable indications noted. The head's shroud was raised to achieve maximum access to the weld. The exam was partially restricted due to the closure head's transition area where the flange weld transitions to the head peel segment. In addition, the examination was limited 3-5/8" to 9-5/8" (6") due to presence of lifting lugs attached to the closure head located at 0, 120 and 240 degrees. The total estimated weld length equals 53.5". The thickness is approximately 7.0".
Approximately 27" of weld length was examined full volume. The total estimated coverage achieved was 68%. System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld.
I -
1 44 44 I
Upper Head to Shell J B-B B2.10 3
UT 88%
IWB-2500-1 These UT exams were performed in May 1992. The following transducers: 0, 45, 60-degree shear wave were used to conduct UT examination. There were no recordable indications noted. The exam was limited due to the presence of 4 welded pads, and insulation. This area of the pressurizer cubicle is high radiation area and highly congested. Removal of remaining insulation required the removal additional panels and insulation support rings in order to grant additional needed access.
No exams were able to be performed from the head side between 289"- 1.0", and 144"- 146" (available scan area 3-5" above weld). No exams were performed from the shellside between 289"- 1.0", and 144" - 146" (available scan area 2.5" - 4.5" above weld).
In addition no exams were able to be performed between 65.25" 87.25" and 98.5" -120", 169.5" - 222" due to the presence of insualtion. The thickness is approximately 5.0".
Approximately 5' of weld length was examined full volume. The total estimated coverage achieved was 88%. Examined 100% of the PZR weld in at least one direction with 75% of the weld being examined in 2 directions as required by Code. System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld.
8 14 4/20/01 RPV 1-RPV-1-046F 005000 006850 2-3-2 2-2-1 10 5/18/92 No PZR 1-PZR-21 No 1
Document Control Desk LRN-02-0255 Table I Relief Request S1-RR-B01 Salem Unit 1 - 2nd Inseervice Inspection Ten-Year NDE Exam Limitations Longitudinal Weld Shel J
B-B B2.11 3
UT 42%
IWB-2500-2 These UT exams were performed in April 2001 using PDI approved techniques. The following transducers: 0, 45, 60-degree shear wave were used to conduct UT examination. There were no recordable indications noted. The exam was limited due to the presence of two 3/2 (7" total) insulation support rings (belly band) located over the top of the weld. The removal of the insulation rings (belly band) would require extensive removal of the adjoining insulation attached to the ring so that the ring could be removedfreplaced; erection/removal of additional scaffolding would be needed, this would result in an increase in overall personnel exposure. There have been no previous indications or problems noted associated with this or other similar pressurizer welds.
System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld.
4 A-1-4 44-1--
I-1--.1-.-
- 1 I--
Lower Head to Tube Sheet B-B B2.40 4
UT 70%
IWB-2500-6 Tnese UT exams were performed in April 2001 using PDI approved techniques. The following transducers: 0, 45, 60-degree shear wave were used to conduct UT examinations. There were no recordable indications noted. The exam was limited due to the presence of four lower vertical steam generator vessel supports, a code data plate welded to the vessel, outer blend radius of the channelhead and the actual tubesheet configuration that caused a scanning interference. There have been no problems noted associated with this or other similar welds The examination was performed from both sides of the weld axially and circumferentially for the entire accessible length where accessible.
No examination could be performed at the following approximate locations due steam generator supports: 34" - 581N, 140"- 166%', 247" - 271" and 355" - 378". In addition, no exam was performed on the channelhead side from 701W - 78W for a 31A4" distance from the weld due to a code plate welded to the vessel.
In addition, the examination conducted from the tubesheet side was limited to 9W from the weld centerline due to the tube sheet's OD configuration. The examination was performed from both sides of the weld axially and circumferentially for the entire accessible length where accessible. The total weld length requiring examination was 426*/.".
The thickness is approximately 51W. Approximately 314" of weld length was examined full volume. The total estimated coverage was 70%. System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld.
9 2-3-2 14 4/24/01 PZR 1 -PZR-20 006325 UU00U1 14 No 4/19/01 13-STG 13-STG-11 No I
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2-3-2
Document Control Desk LRN-02-0255 Table I Relief Request S1-RR-BO1 Salem Unit 1 - 2nd Inseervice Inspection Ten-Year NDE Exam Limitations Lower Head to Tube Sheet B-B B2.40 4
UT 75%
IWB-2500-6 These UT exams were performed in February 1997.
The following transducers: 0, 45, 60-degree shear wave and SLIC 20 and 40 transducers were used to conduct UT examinations. Recordable indications were noted with the 60-degree shear wave transducer and evaluated to be acceptable with the SLIC 20 and 40 transducers. The exam was limited due to the presence of four lower vertical steam generator vessel supports, a code data plate welded to the vessel, outer blend radius of the channelhead and the actual tubesheet configuration that caused a scanning interference.
Indications were noted and evaluated to be acceptable based upon ASME XI code requirements (1983 Ed. With Addenda through Summer 1983). Indications possessed no measurable through-wall dimension.
There have been no problems noted associated with this or other similar welds. The examination was performed from both sides of the weld axially and circumferentially for the entire accessible length where accessible.
No examination was able to be performed a the following locations due steam generator supports: 34" - 58%",
140" - 166W", 247" - 271" and 355"- 378". In addition, no exam was performed on the channelhead side from 7011 - 781N for a 3%" distance from the weld due to a code plate welded to the vessel. In addition, the examination conducted from the tubesheet side was limited to 9 Y." from the weld centerline due to the tube sheet's OD configuration. The total weld length requiring examination was 4261". The thickness is approximately 511. Approximately 329/4 of weld length was examined full volume. The total estimated coverage was 75%. System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld.
10 008801 2-2-3 12 2/20/97 14-STG 14-STG-1 1 No
Document Control Desk LRN-02-0255 Table I Relief Request S1-RR-BO1 Salem Unit 1 - 2nd Inseervice Inspection Ten-Year NDE Exam Limitations 2/20/97 12-STG 2/20/97 11-STG 12-STG-11 1 1-STG-11 Lower Head to Tube Sheet Lower Head to Tube Sheet B-B B-B B2.40 B2.40 4
4 UT UT 78%
77%
IWB-2500-6 IWB-2500-6 These UT exams were performed in February 1997. The following transducers: 0, 45, 60-degree shear wave transducers were used to conduct UT examinations. No recordable indications were noted. The exam was limited due to the presence of four lower vertical steam generator vessel supports, a code data plate welded to the vessel, outer blend radius of the channelhead and the actual tubesheet configuration that caused a scanning interference.
There have been no problems noted or associated with this or other similar welds.
The examination was performed from both sides of the weld axially and circumferentially for the entire accessible length where accessible. No examination could be performed at the following locations due steam generator supports: 48" - 72", 156" - 180", 264" - 288" and 37Cr - 394".
In addition, no exam was performed on the channelhead side from 193"- 201" forea 4" distance from the weld due to a code plate welded to the vessel. In addition, the examination conducted from the tubesheet side was limited to 9* from the weld centerline due to the tube sheet's OD configuration. The total weld length requiring examination was 4261N. The thickness is approximately 5.5". Approximately 330A" of weld length was examined full volume. The total estimated coverage was 78%. System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld.
These UT exams were performed in February 1997. The following transducers: 0, 45, 60-degree shear wave were used to conduct UT examination. No recordable indications were noted. The exam was limited due to the presence of four lower vertical steam generator vessel supports, a code data plate welded to the vessel, outer blend radius of the channelhead and the actual tubesheet configuration that caused a scanning interference. There have been no problems noted associated with this or other similar welds. The examination was performed from both sides of the weld axially and circumferentially for the entire accessible length where accessible. No examination could be performed at the following locations due steam generator supports: 31" - 55", 138" - 162", 245" - 268" and 352"- 375". In addition, no exam was performed on the channelhead side from 66" - 73" for a84" distance from the weld due to a code plate welded to the vessel.
In addition, the examination conducted from the tubesheet side was limited to 9" from the weld centerline due to the tube sheet's OD configuration.
11 009701 010601 2-2-3 2-2-3 12 12 No No
Document Control Desk LRN-02-0255 007400 023400 Table I Relief Request S1-RR-BO1 Salem Unit 1 - 2nd Inseervice Inspection Ten-Year NDE Exam Limitations The total weld length requiring examination was 4271".
The thickness is approximately 5.5". Approximately 333%" of weld length was examined full volume. The total estimated coverage was 77%. System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld.
I 4
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I 2-1-2 09 2/21191 PS 4-PSN-1131-IRS Pressurizer Spray Nozzle Inside Radius B-D B3.120 19 &1 UT 78%
IWB-2500-7(b)
These UT exams were performed in February 1991. A 53-degree shear wave transducer was used to conduct UT examinations. There were no recordable indications noted. The exam was limited due to the presence of a code identification plate physically attached to the head of the PZR vessel. The identification plate is located between 59" - 7" clockwise where the plated caused a scanning interference.
There have been no problems noted associated with this or other similar welds The examination was performed from the blend radius. This configuration has been modeled for the use of 53 degrees. The total weld length requiring examination was 66.5" The thickness is approximately 51W. The total estimated coverage was 78%. System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld.
4 4
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I 2-3-2 14 4/21/01 PR 6-PR-1i104-1 Nozzle to Safe-End B-F B5.40 5
34%
IWB-2500-8 These exams were performed in April 2001. A PT and 30-degree Refracted Longitudinal (RL) UT exam was performed with no recordable indications noted. A 30 degree angle was used to compensate for the small bore piping diameter while ensuring the beam reached the ID of the pipe. No examinations were performed from the upstream side of the weld due to the nozzle configuration. In addition, no examinations were performed from the downstream side of the weld due to the safe-end configuration. Exams were conducted on the weld only and in the clockwise and counter clockwise directions. The total estimated weld length equals 243/".
The thickness is approximately 1.2". The total estimated code coverage achieved was 34% for UT and 100% for the PT exams completed. System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld.
12 No No
Document Control Desk LRN-02-0255 Table I Relief Request S1-RR-BO1 Salem Unit 1 - 2nd Inseervice Inspection Ten-Year NDE Exam Limitations 13 024600 2-3-2 14 4/21/01 PR 6-PR-1103-1 Nozzle to Safe-End B-F B5.40 6 & 3 PT 100%
IWB-2500-8 These exams were performed in April 2001. A PT and No UT 38%
30-degree Refracted Longitudinal (RL) UT exam was performed with no recordable indications noted. A 30 degree angle was used to compensate for the small bore piping diameter while ensuring the beam reached the ID of the pipe. No examinations were performed from the upstream side of the weld due to the nozzle configuration. In addition, no examinations were performed from the downstream side of the weld due to the safe-end configuration. Exams were conducted on the weld only and in the clockwise and counter clockwise directions. The total estimated weld length equals 241".
The thickness is approximately 1.2". The total estimated code coverage achieved was 38% for UT and 100% for the PT exams completed. System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld.
025900 2-3-2 14 4/21/01 PR 4-PR-1100-1 Nozzle to Safe-End B-F B5.40 27 PT 100%
IWB-2500-8 These exams were performed in April 2001. A PT and No UT 34%
30-degree Refracted Longitudinal (RL) UT exam was performed with no recordable indications noted. A 30 degree angle was used to compensate for the small bore piping diameter while ensuring the beam reached the ID of the pipe. No examinations were performed from the upstream side of the weld due to the nozzle configuration. In addition, no examinations were performed from the downstream side of the weld due to the safe-end configuration. Exams were conducted on the weld only and in the clockwise and counter clockwise directions. The total estimated weld length equals 151,T.
The thickness is approximately 0,625". The total estimated code coverage achieved was 34% for UT and 100% for the PT exams completed. System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld.
Document Control Desk LRN-02-0255 Table I Relief Request S1-RR-BO1 Salem Unit 1 - 2nd Inseervice Inspection Ten-Year NDE Exam Limitations Safe-End to Nozzle Nozzle to Elbow B-F It,'(U U&4 P1 1uU'yo B-F B5.40 7&3 PT UT UT I 00%
IVWB-^,^^ I8 100%
34%
105%
25%
These exams were performed in April 2001. A PT and NO These exams were performed in April 2001. A PT and 30-degree Refracted Longitudinal (RL) UT exam was performed with no recordable indications noted, A 30 degree angle was used to compensate for the small bore piping diameter while ensuring the beam reached the ID of the pipe. No examinations were performed from the downstream side of the weld due to the nozzle configuration. In addition, no examinations were performed from the upstream side of the weld due to the safe-end configuration. Exams were conducted on the weld only and in the clockwise and counter clockwise directions. The total estimated weld length equals 15WA.
The thickness is approximately 0.75'. The total estimated code coverage achieved was 34% for UT and 100% for the PT exams completed. System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld.
+
rhese exams were performed in October 1599. A PT riu These exams were performed in October 1999. A PT and 45-degree Dual Transducer Refracted Longitudinal CRL) UT exam was performed to enhance examination beam penetration. There were no recordable indications noted. The exam is performed from the exterior surface of the pipe. Salem's Reactor Coolant system's piping elbows consist of cast stainless steel (A-352, GR CF8M) connected to Steam Generator short radius nozzles (reference sketch 8). It is an industry known phenomena that cast stainless steel does not allow for optimum inspection due to the material's course grain structure that attenuates sound. Examinations of other similar welds located on these lines have not identified any signs of leakage or loss of structural integrity or discontinuities. No axial UT examinations were performed from the upstream side of the weld due to the nozzle configuration or from the downstream side due to the elbow being cast stainless. Exams were conducted on the weld and nozzle side only in the clockwise and counter clockwise directions. The total estimated weld length equals 83W (3W) and 76.4' (29") respectively.
14 PS 033500 039200 2-3-2 2-3-1 14 13 4/21/01 10118/99 4-PS-1131-29 31-RC-1130-2R1
-r
-I_
-F -?Jý IWB250-No FB54-0
-NozzletoElo B-F B5.70 8&4 IWB-2500-8 No
Document Control Desk LRN-02-0255 Table I Relief Request S1-RR-BO1 Salem Unit 1 - 2nd Inseervice Inspection Ten-Year NDE Exam Limitations r
-~-4 61-
- 4.
C 1:3 10/18/99 RC; 29-RC-1 130-5R1 Elbow to Nozzle B-F B5.70 8 & 4 PT UT 100%
25%
IWB-2500-8 The thickness is approximately 2.312". The total estimated code coverage achieved was 25% for UT and 100% for the PTaexams completed. System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld. Surface exams are not required to be completed upon this weld per the
'equirements of ASME XI. In response to industry events S.C.
Summer) regarding the presence of through wall leakage of reactor coolant piping, PSEG Nuclear conducted various NDE exams during the 10-year outage (April 2001). These exams included a visual sxamination upon the ID surface of the eight-reactor pressure vessel nozzle to safe-end and safe-end to pipe welds located on the reactor coolant piping lines. No indications were noted. In addition, remotely operated ultrasonic examinations were conducted upon these same welds from the ID using 50- and 70-degree refracted longitudinal wave transducers.
Again, no indications were noted. In addition, surface (PT) examinations were conducted of these same welds fram the OD after removal of the sandbox covers to support access. Again, no indications were noted.
These exams were performed in October 1999. A PT and 45-degree Dual Transducer Refracted Longitudinal (RL) UT exam was performed to enhance examination beam penetration. There were no recordable indications noted. The exam is performed from the exterior surface of the pipe. Salem's Reactor Coolant system's piping albows consist of cast stainless steel (A-352, GR CF8M) connected to Steam Generator short radius nozzles reference sketch 8). It is an industry known phenomena that cast stainless steel does not allow for optimum inspection due to the material's course grain structure that attenuates sound. Examinations of other similar welds located on these lines have not identified any signs of leakage or loss of structural integrity or discontinuities.
No axial UT examinations were performed from the upstream side of the weld due to the nozzle configuration or from the downstream side due to the elbow being cast stainless. Exams were conducted on the weld and nozzle side only in the clockwise and counter clockwise directions.
15 U0U21U No 2-3-1
Document Control Desk LRN-02-0255 Table I Relief Request S1-RR-BO1 Salem Unit 1 - 2nd Inseervice Inspection Ten-Year NDE Exam Limitations I
1" 13 10118/99 RC; ElboW tO Nozzle PT UT 100%
25%
IWB-2500-8 The total estimated weld length equals 83%" (31") and 76.4" (29") respectively. The thickness is approximately 2.312". The total estimated code coverage achieved was 25% for UT and 100% for the PT exams completed.
System leakage tests (Vr2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld. Surface exams are not required to be completed upon this weld per the requirements of ASME X1. In response to industry events (V.C. Summer) regarding the presence of through wall leakage of reactor coolant piping, PSEG Nuclear conducted various NDE exams during the 10-year outage (April 2001). These exams included a visual examination upon the ID surface of the eight-reactor pressure vessel nozzle to safe-end and safe-end to pipe welds located on the reactor coolant piping lines. No indications were noted.
In addition, remotely operated ultrasonic examinations were conducted upon these same welds from the ID using 50- and 70-degree Refracted Longitudinal wave transducers. Again, no indications were noted. In addition, surface (PT) examinations were conducted of these same welds from the OD after removal of the sandbox covers to support access. Again, no indications were noted.
These exams were performed in October 1999. A PT and 45-degree Dual Transducer Refracted Longitudinal (RL) UT exam was performed to enhance examination beam penetration. There were no recordable indications noted. The exam is performed from the exterior surface of the pipe. Salem's Reactor Coolant system's piping elbows consist of cast stainless steel (A-352, GR CF8M) connected to Steam Generator short radius nozzles (reference sketch 8). It is an industry known phenomena that cast stainless steel does not allow for optimum inspection due to the material's course grain structure that attenuates sound. Examinations of other similar welds located on these lines have not identified any signs of leakage or loss of structural integrity or discontinuities.
No axial UT examinations were performed from the upstream side of the weld due to the nozzle configuration or from the downstream side due to the elbow being cast stainless, Exams were conducted on the weld and nozzle side only in the clockwise and counter clockwise directions.
16 U05bUU NO 2-3-1 29-RC5-1 120-5R1 B-F B5.70 8&4
Document Control Desk LRN-02-0255 Table I Relief Request S1-RR-B01 Salem Unit 1 - 2nd Inseervice Inspection Ten-Year NDE Exam Limitations i
-- I i
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1iI
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-mI i
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'I'm-AA---
054300 2-3-1 13 10118/99 RC 29-RG-1110-4R1 Elbow to Nozzle B-F B5.70 PT UT 100%
25%
IVBW-2500-The total estimated weld length equals 83!" (31") and 76.4" (29') respectively.
The thickness is approximately 2.312". The total estimated code coverage achieved was 25% for UT and 100% for the PT exams completed.
System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld. Surface exams are not required to be completed upon this weld per the requirements of ASME XI. In response to industry events (V.C. Summer) regarding the presence of through wall leakage of reactor coolant piping, PSEG Nuclear conducted various NDE exams during the 1 0-year outage (April 2001). These exams included a visual examination upon the ID surface of the eight-reactor pressure vessel nozzle to safe-end and safe-end to pipe welds located on the reactor coolant piping lines. No indications were noted.
In addition, remotely operated ultrasonic examinations were conducted upon these same welds from the ID using 50-and 70-degreeRefracted Longitudinal wave transducers. Again, no indications were noted. In addition, surface (PT) examinations were conducted of these same welds from the OD after removal of the sandbox covers to support access. Again, no indications were noted.
These exams were performed in October 1999. A PT and 45-degree Dual Transducer Refracted Longitudinal (RL) UT exam was performed to enhance examination beam penetration. There were no recordable indications noted. The exam is performed from the exterior surface of the pipe. Salem's Reactor Coolant system's piping elbows consist of cast stainless steel (A-352, GR CF8M) connected to Steam Generator short radius nozzles (reference sketch 8). It is an industry known phenomena that cast stainless steel does not allow for optimum inspection due to the material's course grain structure that attenuates sound. Examinations of other similar welds located on these lines have not identified any signs of leakage or loss of structural integrity or discontinuities.
No axial UT examinations were performed from the upstream side of the weld due to the nozzle configuration or from the downstream side due to the elbow being cast stainless. Exams were conducted on the weld and nozzle side only in the clockwise and counter clockwise directions.
17 No
Document Control Desk LRN-02-0255 Table I Relief Request S1-RR-BO1 Salem Unit 1 - 2nd Inseervice Inspection Ten-Year NDE Exam Limitations The total estimated weld length equals 831/ (31") and 76.4" (29") respectively.
The thickness is approximately 2.312". The total estimated code coverage achieved was 25% for UT and 100% for the PT exams completed.
System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld. Surface exams are not required to be completed upon this weld per the requirements of ASME XI. In response to industry events (V.C. Summer) regarding the presence of through wall leakage of reactor coolant piping, PSEG Nuclear conducted various NDE exams during the 10-year outage (April 2001). These exams included a visual examination upon the ID surface of the eight-reactor pressure vessel nozzle to safe-end and safe-end to pipe welds located on the reactor coolant piping lines. No indications were noted.
In addition, remotely operated ultrasonic examinations were conducted upon these same welds from the ID using 50 and 70-degree Refracted Longitudinal wave transducers.
Again, no indications were noted. In addition, surface (PT) examinations were conducted of these same welds from the OD after removal of the sandbox covers to support access. Again, no indications were noted.
4
+
I 4
4 4
4
+
4 4"
4
+
4" 5/14/92 1
11-RCP I11-PMP-Bolts 1-24 Pump Bolts B-G-1 I B6.180 2
UT 70%
IWB-2500-12 These examinations were conducted during May 1992 in accordance with code requirements using available state of the art technology. Exams were conducted upon 17 of 24 bolts (70%) using a 60-degree shear wave transducer and an 88-degree shear wave transducer from the stud's heater hole using an extension pole.
The remaining 7 studs (30%) were unable to be examined due to inaccessibility resulting from permanently installed miscellaneous piping (oil pans, CVCS piping and Instrumentation Lines) located approximately 4" - 10" over the top of the stud that prevented access to the studs heater holes 3, 4, 5, 6, 13, 22 and 23. No indications were noted. Studs were examined in place and under tension. No maintenance was performed that supported removal of the studs.
System leakage tests (VT2) are conducted at the conclusion of each outage to detect evidence of leakage No leakage has been noted in this area of the weld.
Surface exams are not required to be completed upon this weld per the requirements of ASME XI.
No 18 190800 2-2-1 10 I
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4I.I
Document Control Desk LRN-02-0255 Table I Relief Request S1-RR-BO1 Salem Unit 1 - 2nd Inseervice Inspection Ten-Year NDE Exam Limitations I
4 4
4
.+
I 4*
I 4
-1 4-
-I.
5/12/92 I112-RCP tI12-PMP-Bolts 1-24 Pump Bolts B-G-1 I B6.180 2
UT 67%
IWB-2500-12 Since 2000, NDE personnel have successfully demonstrated the single side access straight beam ultrasonic exam technique upon a stud at the PDI. PSEC Nuclear has since elected to perform straight beam (0 degree) examinations from the accessible surface of the studs using PDI qualified individuals to perform these exams.
PSEG Nuclear failed to re-perform these exams using the current state of the art technique that would have resulted in 100% code coverage being achieved. These exams are currently scheduled to be performed November 2005 during RFO17. Straight beam UT examinations were conducted upon the 13 anc 14 Reactor Coolant Pump studs using this technique with the studs being determined as satisfactory.
These examinations were conducted during May 1992 ir accordance with code requirements using available state of the art technology. Exams were conducted upon 16 of 24 bolts (67%) using a 60-degree shear wave transducer and an 88-degree shear wave transducer from the stud's heater hole using an extension pole.
The remaining 8 studs (33%) were unable to be examined due to inaccessibility resulting from permanently installed miscellaneous piping (oil pans, CVCS piping and Instrumentation Lines) located approximately 4' - 10* over the top of the stud UT inspection heater holes for studs 3, 4, 5, 6, 13, 14 and
- 23. No indications were noted. Studs were examined in place and under tension. No maintenance was performed that supported removal of the studs. System leakage tests (V1"2) are conducted at the conclusion of each outage to detect evidence of leakage. No leakage has been noted in this area of the weld. Surface exams are not required to be completed upon this weld per the requirements of ASME XI.
Since 2000, NDE personnel have successfully demonstrated the single side access straight beam ultrasonic exam technique upon a stud at the PD1.
PSEG Nuclear has since elected to perform straight beam (0- degree) examinations from the accessible surface of the studs using PDI qualified individuals to perform these exams. PSEG Nuclear failed to re-perfom these exams using the current state of the art technique that would have resulted in 100% code coverage being achieved. These exams are currently scheduled to be performed November 2005 during RF017. Straight beam UT examinations were conducted upon the 13 anc 14 Reactor Coolant Pump studs using this technique with the bolting determined as satisfactory.
19 191600 2-3-2 14 No
Document Control Desk LRN-02-0255 Table I Relief Request S1-RR-BO1 Salem Unit 1 - 2nd Inseervice Inspection Ten-Year NDE Exam Limitations Elbow to Pipe B-J B9.11 11 PT UT 100%
47%
IWB-2500-8 These exams were performed in October 1999. APT and UT examination was performed upon the pipe to elbow configuration with no recordable indications identified. The UT examinations were conducted using a IT 45-degree shear wave and refracted longitudinal transducers. UT examinations were unable to be performed from the downstream side, due to the penetration wall obstruction. The wall penetration does not allow sufficient access to support scanning of the weld from the pipe side located within the wall. A refracted longitudinal transducer was used to improve beam penetration through the base material and weld.
,SME XI requires scanning be accomplished in two beam directions. Since longitudinal wave transmission does not lend itself to skipping scanning was only successfully accomplished in one direction. The use of a shear wave to investigate the opposite side of a weld has since been proven through the PDI initiative to be unreliable; therefore minimum credit is taken for achieving coverage for the far side of the weld.
The total estimated weld length equals approximately 27 3/8". The thickness is approximately 1.35".
Approximately one half of the weld was examined full volume. The total estimated code coverage was approximately 47% for the UT and 100% for the PT axam. System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld.
No 115300 2-2-1 10 5/19/92 SJ 6-SJ-1141-1 Reducer to Elbow B-J B9.11 12 PT 100%
IWB-2500-8 These examinations were performed in May 1992. A PT No UT 86%
and UT examination was performed upon the reducer to elbow configuration. Recordable PT and UT indications were identified and evaluated to be acceptable in accordance with ASME X1 IWB-3500 and ID geometry respectively. The UT examinations were conducted using a 45-degree shear wave transducer. The UT examination was limited to I/" from the weld centerline due to reducer's configuration. The total estimated weld length equals approximately 21'. The thickness is approximately W. The total estimated code coverage achieved was approximately 86% for the UT and 100%
for the PT exam. System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld.
20 100200 2-3-1 13 10/20/99 sJ 10-SJ-1 121-8
Document Control Desk LRN-02-0255 Table I Relief Request S1-RR-BO1 Salem Unit 1 - 2nd Inseervice Inspection Ten-Year NDE Exam Limitations These examinations were performed in October 1999 using an approved PDI technique. A PT and UT examination was performed upon the elbow to valve configuration with no recordable indications identified.
The UT examinations were conducted using 45-degree shear wave and Refracted Longitudinal (RL) transducers. The UT examination was performed from the elbow side due to the valve's OD configuration.
Attempts to utilize a shear wave to investigate the opposite side of a weld have been proven through the PDI initiative to be unreliable; therefore no credit is taken for the far side of the weld The use of a shear wave to investigate the opposite side of a weld has since been proven through the PDI initiative to be unreliable; therefore minimum credit is taken for achieving coverage fr the far side of the weld.
The total estimated weld length equals approximately 21*. The thickness is approximately '/". The total estimated code coverage achieved was approximately 64% for the UT and 100% for the PT exam. System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld.
These examinations were performed in May 1989. A PT and UT examination was performed upon the reducer to valve configuration with no recordable indications identified. The UT examinations were conducted using 45-degree shear wave transducer. The UT examination was performed from the reducer side due to the valve's OD configuration. The use of a shear wave to investigate the opposite side of a weld has since been proven through the PDI initiative to be unreliable; therefore minimum credit is taken for achieving coverage for the far side of the weld. The total estimated weld length equals approximately 21. The thickness is approximately 3/4'. The total estimated code coverage achieved was approximately 64% for the UT and 100%
for the PT exam. System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld.
122300 122700 2-3-1 2-1-1 13 09 10/15/99 5/5/89 sJ SJ 6-SJ-1 121-2 6-SJ-1 112-1 Elbow to Valve Reducer to Valve B-J B-J B9.11 B9.11 15 16 PT UT PT UT 100%
64%
100%
64%
IWB-2500-8 IWB-2500-8 No No 21
Document Control Desk LRN-02-0255 Table I Relief Request S1-RR-BO1 Salem Unit 1 - 2nd Inseervice Inspection Ten-Year NDE Exam Limitations 22 124100 2-2-1 10 5/19/92 SJ 6-SJ-1I111-1 Reducer to Valve B-J B9.11 21 PT 100%
IWB-2500-8 These examinations were performed in May 1992. A PT No UT 82%
and UT examination was performed upon the reducer to valve configuration. Recordable UT indications were identified and evaluated to be ID geometry. The UT examinations were conducted using a 45-degree shear wave transducer. The UT examination was performed from the reducer side due to the valve's OD configuration. The use of a shear wave to investigate the opposite side of a weld has since been proven through the PDI initiative to be unreliable; therefore minimum credit is taken for achieving coverage for the far side of the weld. The total estimated weld length equals approximately 21". The thickness is approximately W.
The total estimated code coverage achieved was approximately 82% for the UT and 100% for the PT exam System leakage tests (Vr2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld.
129400 2-1-2 09 2/21/91 SJ 4-SJ-1182-18 Pipe to Elbow B-J B9.11 22 PT 100%
IWB-2500-8 These examinations were performed in February 1991.
No UT 87%
A PT and UT examination was performed upon the pipe to elbow configuration. Recordable UT indications were identified and evaluated to be ID geometry. The UT examinations were conducted using a 45-degree shear wave transducer. The UT examination was performed from both sides of the weld. A 1' branch connection weld is located on the pipe side of the weld and interferes with the circumferential scanning of the pipe side between 5-8 1. since it is 1' away from the circumferential weld. The total estimated weld length equals approximately 171N. The thickness is approximately %/4*. The total estimated code coverage achieved was approximately 87% for the UT and 100%
for the PT exam. System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld.
Document Control Desk LRN-02-0255 Table I Relief Request S1-RR-BO1 Salem Unit 1 - 2nd Inseervice Inspection Ten-Year NDE Exam Limitations Tee to Reducer Branch Connection to Pipe B-J B-J B9.11 B9.11 23 9
86%
100%
75%
IWB-2500-8 IWB-2500-8 These examinations were performed in October 1992 with recordable indications identified. The indication was evaluated to be ID geometry. PT and UT examinations were performed satisfactorily. The UT examinations were conducted using a 45-degree shear wave transducer. The UT examination was performed from the reducer side only due to the tee's configuration and accoustic properties. The use of a shear wave to investigate the opposite side of a weld has since been proven through the PDI initiative to be unreliable; therefore minimum credit is taken for achieving coverage for the far side of the weld. The total estimated weld length equals approximately 171N. The thickness is approximately W.
The total estimated code coverage achieved was approximately 86% for the UT and 100%
for the PT exam.System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld.
These exams were performed in October 1999. A PT and UT examination was performed upon the branch connection to pipe connection with no recordable indications identified. The UT examination was performed using 45-degree shear wave and refracted longitudinal (RL) transducers. UT examinations were conducted from the pipe side and upon the weld due to the OD configuration of the branch connection. ASME Xl requires scanning be accomplished in two beam directions. The use of a shear wave to investigate the opposite side of a weld has since been proven through the PDI initiative to be unreliable; therefore minimum credit is taken for achieving coverage for the far side of the weld. The total estimated weld length equals 14.125". The thickness is approximately I".
The total estimated code coverage achieved was 75% for UT and 100% for the PT exams completed. System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld.
23 133800 030100 2-2-1 2-3-1 10 13 10/19/92 10/20/99 SJ PS 4-SJ-1 172-28 4-PS-1131-1 No No
Document Control Desk LRN-02-0255 Table I Relief Request S1-RR-BO1 Salem Unit 1 - 2nd Inseervice Inspection Ten-Year NDE Exam Limitations These exams were performed in February 1991. APT and UT examination was performed upon the branch connection to pipe connection with recordable indications identified. The indication was evaluated to be ID geometry. The UT examination was performed using a 45-degree shear wave transducer. UT examinations were conducted upon the weld in the clockwise and counterclockwise directions due to the OC configuration of the valve to tee weld. ASME Xl requires scanning be accomplished in two beam directions. The use of a shear wave to investigate the opposite side of a weld has since been proven through the PDI initiative to be unreliable; therefore minimum credit is taken for achieving coverage for the far side of the weld. The tota estimated weld length equals14-318".
The thickness is approximately 5/8". The total estimated code coverage achieved was 50% for the UT and 100% for the PT exams completed.
System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld. Surface exams are not required to be completed upon this weld per the requirements of ASME XI.
I 4
I
+
I 4
4 4
4 4
These exams were performed in March 1991. A PT and 45-degree shear wave exam was performed. There were no recordable indications noted. The exam is performed from the exterior surface of the pipe. Salem's Reactor Coolant system's piping elbows consist of cast stainless steel (A-352. GR CF8M) connected to Steam Generator short radius nozzles (Reference sketches 8 and 10). It is an industry known phenomena that cast stainless steel does not allow for optimum inspection due to the material's course grain structure that attenuates sound. Examinations of other similar welds located on these lines have not identified any signs of leakage or loss of structural integrity or discontinuities.
No axial UT examinations were performed from the pipe side of the weld due to the elbow being made of cast stainless steel. Axial and circumferential UT exams were conducted on the weld and pipe side and in the clockwise and counter clockwise directions.
2-1-2 09 2/23/91 PS 4-PS-1i111-23 Valve to Tee B-J B9.11 036500 037400 17 PT UT 100%
50%
IWB-2500-8 No 2-1-2 09 3/7191 RC 31-RC-1140-3 Elbow to Pipe B-J B9.11 8&4 PT UT 100%
76%
IWB-2500-8 No 24
Document Control Desk Table I LRN-02-0255 Relief Request S1-RR-BO1 Salem Unit 1 - 2nd Inseervice Inspection Ten-Year NDE Exam Limitations The total estimated weld length equals 97.4 ". The thickness is approximately 21". The total estimated code coverage achieved was 76% for the UT and 100%
for the PT exams completed.
System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld. In response to industry events (V.C. Summer) regarding the presence of through-wall leakage of reactor coolant piping, PSEG Nuclear conducted various NDE exams during the 10-year outage (April 2001). These exams included a visual examination upon the ID surface of the eight-reactor pressure vessel nozzle to safe-end and safe-end to pipe welds located on the reactor coolant piping lines. No indications were noted.
045600 2-3-1 13 10120/99 RC 31-RC-1 110-4 Pipe to Elbow B-J B9.1 1 10 PT 100%
IWB-2500-8 These exams were performed in October 1999. A PT No UT 38%
and 45-degree Dual Transducer Refracted Longitudinal (RL) UT exam was performed to enhance examination beam penetration. There were no recordable indications noted. The exam is performed from the exterior surface of the pipe. Salem's Reactor Coolant system's piping elbows consist of cast stainless steel (A-352, GR CF8M) connected to Steam Generator short radius nozzles (Reference sketches 8 and 10). It is an industry known phenomena that cast stainless steel does not allow for optimum inspection due to the material's course grain structure that attenuates sound. Examinations of other similar welds located on these lines have not identified any signs of leakage or loss of structural integrity or discontinuities. No axial UT examinations were performed from the pipe side of the weld due to the elbow being made of cast stainless steel. Axial and circumferential UT exams were conducted on the weld and pipe side and in the clockwise and counter clockwise directions.
The total estimated weld length equals 97.4". The thickness is approximately 21W. The total estimated code coverage achieved was 38% for the UT and 100%
for the PT exams completed. System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld. In response to industry events (V.C. Summer) regarding the presence of through wall leakage of reactor coolant piping, PSEG Nuclear conducted various NDE exams during the 10-year outage (April 2001). These exams included a visual examination upon the ID surface of the eight-reactor pressure vessel nozzle to safe-end and safe-end to pipe welds located on the reactor coolant piping lines. No indications were noted.
25 I
Document Control Desk LRN-02-0255 Table I Relief Request S1-RR-BO1 Salem Unit 1 - 2nd Inseervice Inspection Ten-Year NDE Exam Limitations 26 096700 2-2-2 11 10/26/93 SJ 10-SJ-1141-14 Valve to Tee B-J B9.1 1 18 PT 100%
IWB-2500-8 These exams were performed in October 1993. A PT No UT 0%
examination was performed upon the valve to tee configuration with no recordable indications identified.
No UT examination of the valve to tee configuration was performed due to the OD valve to tee configuration and the stainless steel acoustic properties. ASME Xl requires scanning be accomplished in two beam directions. The use of a shear wave to investigate the opposite side of a weld has since been proven through the PDI initiative to be unreliable; therefore minimum credit is taken for achieving coverage for the far side of the weld. The total estimated weld length equals35-118".
The thickness is approximately 1.7". The total estimated code coverage achieved was 0% for the UT and 100% for the PT exams completed. System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld. Surface exams are not required to be completed upon this weld per the requirements of ASME XI.
098500 2-2-3 12 10/26/95 SJ 10-SJ-1131-10 Pipe to Elbow B-J B9.11 20 PT 100%
IWB-2500-8 These exams were performed in October 1995. APT No UT 86%
and UT examination was performed upon the pipe to elbow configuration with no recordable indications identified. The UT examinations were conducted using a 45-and 60-degree shear wave transducer. UT examinations were limited from the downstream side, due to the elbow's intrados curvature that precludes transducer contact. UT examination was not permissible from the downstream for a distance of 4" within the intrados area between 15 - 19". The total estimated weld length equals approximately 39". The thickness is approximately 1.10*. Approximately 35" of the weld was examined full volume. The total estimated code coverage was 86% for UT and 100% for PT exams.
System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld.
I I.5.&I.
3I5.I5 I
3.I5.I3.I3..I
Document Control Desk LRN-02-0255 Table I Relief Request S1-RR-BO1 Salem Unit 1 - 2nd Inseervice Inspection Ten-Year NDE Exam Limitations 3-CV-1141-14 Valve to Elbow B-J B9.21 24 PT UT 100%
50%
IWB-2500-8 These examinations were performed in April 2001 using a PDI approved UT examination technique. A PT and UT examination was performed upon the valve to elbow configuration with no recordable indications identified.
The UT examinations were conducted using a 45-and 70-degree shear wave transducer. The UT examination was performed from the elbew side due to the OD valve configuration. No scanning could be performed from the valve side. The use of a shear wave to investigate the opposite side of a weld has since been proven through the PDI initiative to be unreliable; therefore minimum credit is taken for achieving coverage for the far side of the weld. The total estimated weld length equals approximately 9-118".
The thickness is approximately W. The total estimated code coverage achieved was approximately 50% for the UT and 100% for the PT exam. System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld.
Yes IEB 88-08 027800 2-1-2 09 2/20/91 PR 3-PR-1107-10 Pipe to Valve B-J B9.21 None PT 37%
IWB-2500-8 PT exams were performed February 1991. A PT exam No was performed upon the weld with no recordable indications noted. The PT examination was limited due to the presence of permanently attached restraints adjacent to the weld within the exam area between 2" 9" clockwise. The total estimated weld length equals approximately 11'*. The total estimated coverage achieved was approximately 37%. System leakage tests (V'r2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld.
054700 2-2-1 10 5/14/92 RC
-RC-1140-1/10-SJ-1 ipe to Branch Connectic B-J B9.31 14 PT 100%
IWB-2500-8 These examinations were performed in May 1992. A PT No UT 75%
and UT examination was performed upon the pipe to branch connection configuration with no recordable indications identified. The UT examinations were conducted using 39-and 45-degree shear wave transducers. The UT examination was performed from the pipe side due to the OD branch connection configuration. No scanning could be performed from the branch connection side. The use of a shear wave to investigate the opposite side of a weld has since been proven through the PDI initiative to be unreliable; therefore minimum credit is taken for achieving coverage for the far side of the weld. The total estimated weld length equals approximately 45.5". The thickness is approximately 2.60". The total estimated code coverage achieved was approximately 75% for the UT and 100%
for the PT exam. System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld.
27 016700 2-3-2 14 4/24/01 CVcs
Document Control Desk LRN-02-0255 Salem Unit 1 - 2nd Table I Relief Request S1-RR-BO1 Inseervice Inspection Ten-Year NDE Exam Limitations T
1 I
.I I
.I-.-
k--
I---
J
. I T--
1 1
I 1----.11---------7
-RC-111U-1/4-PI'-1jpe to Branch Connectic B-J B9.31 13 PT UT 100%
75%
WIW-2500-8 These examinations were performed in May 1992. APT and UT examination was performed upon the pipe to branch connection configuration with no recordable indications identified. The UT examinations were conducted using 32-and 45-degree shear wave transducers.
The UT examination was performed from the pipe side due to the OD branch connection configuration.
No scanning could be performed from the branch connection side. The use of a shear wave to investigate the opposite side of a weld has since been proven through the PDI initiative to be unreliable; therefore minimum credit is taken for achieving coverage for the far side of the weld. The total estimated weld length equals approximately 45.5". The thickness is approximately 2.60". The total estimated code coverage achieved was approximately 75% for the UT and 100%
for the PT exam. System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld.
No 161100 2-1-2 09 2/16/91 SJ 2-SJ-1 128-57 Coupling to Pipe B-J B9.40 26 PT 83%
IWB-2500-8 This examination was conducted May 1989. A PT No examination was performed upon the coupling to pipe connection with no recordable indications noted. The PT examination was limited due to the presence of a permanently welded support plate that interfered with the examination from 3Y." to 4W. The use of a shear wave to investigate the opposite side of a weld has since been proven through the PDI initiative to be unreliable; therefore minimum credit is taken for achieving coverage for the far side of the weld. The total estimated weld length equals approximately 7/4*. The thickness is approximately W. The total estimated code coverage achieved was approximately 83% for the PT exam.
System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld.
1.5-SJ-1 122-7 Tee to Pipe B-J B9.40 None PT 52%
IWB-2500-8 These examinations were conducted May 1989. A PT examination was performed upon the weld with no recordable indications noted. The PT examination was limited due to the presence of a permanently welded pipe support between (r - 2%' and 31W-6" that interfered with the exam area. The total estimated weld length equals approximately 9.5". The thickness is approximately 0.375". The total estimated code coverage achieved was approximately 52% for the PT exam. System leakage tests (VTI2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld.
No 28 u091UU 2-2-1 10 5/14/92 tRC 180900 2-1-1 08 5/9/89 SJ I
I___
__JI
__I
.I.
I JI __-
-r -.
1 -
Document Control Desk LRN-02-0255 Table I Relief Request S1-RR-BO1 Salem Unit 1 - 2nd Inseervice Inspection Ten-Year NDE Exam Limitations 191000 2-1-1 08 5/12/89 RCP 11-PMP-1LG Lug B-K-1 B10.20 2
PT 84%
IWB-2500-15 PT exams were performed May1989. APT exam was No performed upon the integral attachment with no recordable indications noted. The PT examination was limited due to the presence of the pump's permanently welded support structure that interfered with the exam upon the lower portion of the lug for approximately 18".
The total estimated weld length equals approximately 110". The thickness of the lug is approximately 2.0".
The total estimated coverage achieved was approximately 84%. System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld. Surface exams are not required to be completed upon this weld per the requirements of ASME XI.
191100 2-1-1 08 10/8/99 11-RCP 11-PMP-2LG Lug B-K-1 B10.20 2
PT 84%
IWB-2500-15 PT exams were performed October 1999. APT exam No was performed upon the integral attachment with no recordable indications noted. The PT examination was limited due to the presence of the pump's welded support structure that interfered with the exam upon the lower portion of the lug for approximately 18". The total estimated weld length equals approximately 110". The thickness of the lug is approximately 2.0". The total estimated coverage achieved was approximately 84%.
System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld.
192600 2-3-1 13 10/8/99 13-RCP 13-PMP-1LG Pump Lug B-K-1 B10.20 2
PT 84%
IWB-2500-15 PT exams were performed May 1989 and October 1999.
No A PT exam was performed upon the integral attachment with no recordable indications noted. The PT examination was limited due to the presence of the pump's welded support structure that interfered with the exam upon the lower portion of the lug for approximately 18". The total estimated weld length equals approximately 110". The thickness of the lug is approximately 2.0". The total estimated coverage achieved was approximately 84%. System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld.
29
Document Control Desk LRN-02-0255 Table I Relief Request S1-RR-BO1 Salem Unit 1 - 2nd Inseervice Inspection Ten-Year NDE Exam Limitations 192650 2-3-1 13 10/8/99 13-RCP 13-PMP-2LG Pump Lug B-K-1 B10.20 2
PT 84%
IWB-2500-15 PT exams were performed May1989 and Octoberl1999.
No A PT exam was performed upon the integral attachment with no recordable indications noted. The PT examination was limited due to the presence of the pump's welded support structure that interfered with the exam upon the lower portion of the lug for approximately 18". The total estimated weld length equals approximately 110". The thickness of the lug is approximately 2.(r. The total estimated coverage achieved was approximately 84%. System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld.
192700 2-3-1 13 10/8/99 13-RCP 13-PMP-3LG Pump Lug B-K-1 B10.20 2
PT 84%
IWB-2500-15 PT exams were performed May 1989 and October 1999.
No A PT exam was performed upon the integral attachment with no recordable indications noted. The PT examination was limited due to the presence of the pump's welded support structure that interfered with the exam upon the lower portion of the lug for approximately 18". The totaleastimated weld length equals approximately 110". The thickness of the lug is approximately 2.0". The total estimated coverage achieved was approximately 84%. System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld.
191150 2-1-1 08 5/12/89 11-RCP 11-PMP-3LG Lug B-K-1 B10.20 2
PT 84%
IWB-2500-15 PT exams wereaperformed Mayl1989. APT exam was No performed upon the integral attachment with no recordable indications noted. The PT examination was limited due to the presence of the pump's welded support structure that interfered with the exam upon the lower portion of the lug for approximately 18". The total estimated weld length equals approximately 110". The thickness of the lug is approximately 2.0". The total estimated coverage achieved was approximately 84%.
System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld.
191800 2-2-2 10 11/1/93 12-RCP 12-PMP-1LG Lug B-K-1 B10.20 2
PT 72%
IWB-2500-15 PT exams were performed November 1993. A PT exam No was performed upon the integral attachment with no recordable indications noted. The PT examination was limited due to the presence of the pump's welded support structure that interfered with the exam upon the lower portion of the lug for approximately 30". The total estimated weld length equals approximately 110". The thickness of the lug is approximately 2.0". The total estimated coverage achieved was approximately 72%.
System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld.
30
Document Control Desk LRN-02-0255 Table I Relief Request S1-RR-BO1 Salem Unit 1 - 2nd Inseervice Inspection Ten-Year NDE Exam Limitations 191900 2-2-2 10 11/1/93 12-RCP 12-PMP-3LG Lug B-K-1 B10.20 2
PT 76%
IWB-2500-15 PT exams were performed November1993. APT exam No was performed upon the integral attachment with no recordable indications noted. The PT examination was limited due to the presence of the pump's welded support structure that interfered with the exam upon the lower portion of the lug for approximately 25.5". The total estimated weld length equals approximately 110". The thickness of the lug is approximately 2.0. The total estimated coverage achieved was approximately 76%.
System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld.
193400 2-2-2 10 11/1/93 14-RCP 14-PMP-1LG Lug B-K-1 B10.20 2
PT 72%
IWB-2500-15 PT exams were performed November 1993. A PT exam No was performed upon the integral attachment with no recordable indications noted. The PT examination was limited due to the presence of the pump's welded support structure that interfered with the exam upon the lower portion of the lug for approximately 24.5". The total estimated weld length equals approximately 110". The thickness of the lug is approximately 2.0". The total estimated coverage achieved was approximately 72%.
System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld.
193450 2-2-2 10 11/1/93 14-RCP 14-PMP-2LG Lug B-K-1 B10.20 2
PT 74%
IWB-2500-15 PT exams were performed November 1993. A PT exam No was performed upon the integral attachment with no recordable indications noted. The PT examination was limited due to the presence of the pump's welded support structure that interfered with the exam upon the lower portion of the lug for approximately 27.5". The total estimated weld length equals approximately 110". The thickness of the lug is approximately 2.0". The total estimated coverage achieved was approximately 74%.
System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld.
193500 2-2-2 10 10/18/99 14-RCP 14-PMP-3LG Lug B-K-1 B10.20 2
PT 76%
IWB-2500-15 PT exams were performed November 1993. A PT exam No was performed upon the integral attachment with no recordable indications noted. The PT examination was limited due to the presence of the pump's welded support structure that interfered with the exam upon the lower portion of the lug for approximately 25.5". The total estimated weld length equals approximately 110". The thickness of the lug is approximately 2.0". The total estimated coverage achieved was approximately 76%.
System leakage tests (VT2) are conducted at the conclusion of each outage to detect presence of leakage. No leakage has been noted in this area of the weld.
31
Relief Request: S1-RR-CO1 Second Ten-Year Interval Inservice Inspection NDE Exam Limitations Salem Unit I Attachment II
Relief Request: S1-RR-C01 Second Ten-Year Interval Inservice Inspection NDE Exam Limitations Salem Unit 1 NRC Approved (Yes or No):
Date:
Ref:
NOTE:
Salem Unit 1 - Second Ten-Year Inservice Inspection (ISI) Interval inservice inspection examinations were performed between February 27, 1988 (start) and May 19, 2001 (end). During this time Salem Unit 1 was shutdown for an extended period (April 4, 1995 through April 17, 1998 - 36 months and 10 days).
Component
Description:
Salem Unit 1 NDE exam limitations of Class 2 bolting components and welds located upon pressure vessels and piping systems ASME Section XI Class:
Class 2 Code Requirement:
Salem Unit 1 second Ten-Year Interval Inservice Inspection (ISI) inservice inspection examinations were performed in accordance with the requirements of ASME Boiler and Pressure Vessel Code Section Xl, 1983 Edition up through and including Summer 1983 Addenda Article IWC-2500 to the extent practical. Table IWC-2500-1 defines examination requirements for Class 2 components. The table contains information associated with the identification of components to be examined by nondestructive examination; this includes the applied nondestructive examination (NDE) method, acceptance standard, and extent of exam coverage and exam frequency.
The 1999 Edition of 10CFR50.55a "Codes and Standards" was revised by a Federal Register Notice dated September 22, 1999 (64FR51400) that defined new requirements for coverage and examination demonstrations. These requirements affected both class 1 and 2 bolting, piping system welds, and reactor pressure vessel nondestructive examinations.
ASME, Section Xl, 1983 Edition, Summer 1983 Addenda, requires volumetric and/or surface and visual examinations be performed upon components and welds identified within Table IWC-2500-1 Exam Categories C-A, C-B, C-F-1 and C-F-2, and C-C.
A. Exam Category C-A Pressure Retaining Welds in Pressure Vessels Section Xl Exam Categories C-A requires volumetric weld examinations to be performed upon various pressure vessel shell circumferential, head and tube sheet welds (Item Numbers C1.10, C1..11 and C1.12, respectively); closure 1
Relief Request: S1-RR-CO1 Second Ten-Year Interval Inservice Inspection NDE Exam Limitations Salem Unit I head circumferential and meridional welds (Item Numbers B13.21 and B13.22, respectively) and the associated reactor pressure vessel flange welds (Items B13.30 and B13.40). The examinations may be limited to one vessel among the group of vessels performing a similar function.
B. Exam Category C-B Pressure Retaining Nozzle Welds in Vessels Section Xl Exam Categories C-B requires volumetric weld examinations to be performed upon pressure retaining nozzle to shell welds and nozzle inner radius sections contained within pressure vessels. The examinations may be limited to one vessel among the group of vessels performing a similar function.
C. Exam Category C-C Welded Integral Attachments Section Xl Exam Category C-C, Integral Attachments for Class 2 Vessels, Piping, and Pumps and Valves, requires surface examinations be conducted upon welded integral attachments attached to reactor coolant pump casings.
PSEG Nuclear conducted welded integral attachment weld exams in accordance with the requirements imposed by ASME Section Xl Code Case N-509, Alternative Rules for the Selection and Examination of Class 1,2 and 3 Integrally Welded Attachments.
D. Exam Category C-F-1 and C-F-2 Retaining Piping Welds PSEG Nuclear conducted class 2 piping exams in accordance with the requirements imposed by ASME Section Xl Code Case N-408 Alternative Rules for Examination of Class 2 Piping Exam Categories C-F-1 and C-F-2.
This code case required surface and volumetric weld examinations be performed upon welds greater than 4" diameter and 0.375" thickness (Item C5.10) and > 2" diameter but < 4" (Item C5.20). In addition, it required surface exams of socket welds (Item C5.30). Pipe branch connections of branch piping >2" diameters received surface examination (Item C5.40).
Piping long seams were conducted in accordance with the requirements of Code Case N-524, Alternative Examination Requirements for Longitudinal Welds in Class I and 2 Piping.
The attached table contains detailed information related to the explanation of those components demonstrating inadequate code exam coverage extent due to inaccessibility, physical limitation or obstruction.
2
Relief Request: S1-RR-CO1 Second Ten-Year Interval Inservice Inspection NDE Exam Limitations Salem Unit 1 Basis for Relief:
Pursuant to 1 OCFR50.55a (g)(5)(iii), relief is requested from ASME XI examination requirements for the performance of the following bolting, piping and vessel welds due to exam limitations. The table herein identifies those inservice inspection nondestructive examinations contained within the Salem Unit 1 ISI Program Long Term Plan for the Second Ten-Year Interval whose NDE exams were found to be inaccessible, physically limited or partially obstructed and not capable of fully meeting code coverage requirements for examination extent.
These components are identified within the attached table and supplemented by additional descriptive details (sketches, illustrations, and/or drawings) enclosed within Appendix A.
Subject components contained herein have received inservice inspection NDE examinations to the "extent practical" within the limitations of design, geometry and materials of construction of the components as allowed by Code. These components have also undergone necessary volumetric examination by radiography and/or surface examinations during fabrication, in accordance with approved construction/fabrication code requirements providing adequate assurance for the structural integrity of the components prior to plant operation.
In addition, these components have been subjected to a visual examination for leakage after completion of each refueling outage.
PSEG Nuclear utilizes approved technical procedures written in accordance to applicable ASME Code section/paragraph criterion for area/volume requirements. Plant procedures require the documentation of the location and cause of the limitation.
A. Exam Category C-A Pressure Retaining Welds in Pressure Vessels Reference applicable sections of this category within the table attached to identify specific component information and explanation of the limitation(s) encountered.
Full Code required coverage is impractical for the subject welds since the vessel would require design modifications that would impose a significant burden to PSEG Nuclear. PSEG Nuclear has examined these welds to the extent practical and determined them to be acceptable with no observed signs of degradation. In addition, other RPV welds have been examined to the extent required by the Code and also found to be acceptable with no observed signs of degradation. In addition, VT-2 visual examinations performed in conjunction with system pressure testing have found these welds to be acceptable with no leakage observed.
3
Relief Request: S1-RR-CO1 Second Ten-Year Interval Inservice Inspection NDE Exam Limitations Salem Unit I B. Exam Category C-B Pressure Retaining Nozzle Welds in Vessels Reference applicable sections of this category within the table attached to identify specific component information and explanation of the limitation(s) encountered.
Full Code required coverage is impractical for the subject welds since the vessel would require design modifications and would impose a significant burden to PSEG Nuclear. PSEG Nuclear has examined these welds to the extent practical and determined them to be acceptable with no observed signs of degradation. In addition, other similar vessel welds have been examined to the extent required by the Code and also found to be acceptable with no observed signs of degradation. In addition, VT-2 visual examinations performed in conjunction with system pressure testing have found these welds to be acceptable with no leakage observed.
C. Exam Category C-F-1 and C-F-2 Retaining Piping Welds Reference applicable sections of this category within the table attached to identify specific component information and explanation of the limitation(s) encountered.
Required Code coverage is impractical for the subject welds since the piping system would require design modifications and would impose a significant burden to PSEG Nuclear. PSEG Nuclear has examined these welds to the extent practical and determined them to be acceptable with no observed signs of degradation. In addition, other similar piping welds have been examined to the extent required by the Code and also found to be acceptable with no observed signs of degradation. Further, VT-2 visual examinations performed in conjunction with system pressure testing have found these welds to be acceptable with no leakage observed.
Code required volumetric examinations are conducted by ultrasonic examination from both the upstream and downstream directions of piping welds. Ultrasonic examination of certain terminal ends and structural discontinuities are considered to be impractical due to their configuration and material acoustic properties.
The EPRI Performance Demonstration Initiative (PDI) is in agreement with the NRCs September 22, 1999 Final Rule regarding single side access for piping. The Final Rule requires that if access is available, austenitic steel weld shall be scanned in each of the four directions (parallel and perpendicular to the weld) where required. PDI has not been able to qualify a single side examination procedure technique that is capable of demonstrating equivalency for a two-sided examination procedure technique on austenitic 4
Relief Request: S1-RR-CO1 Second Ten-Year Interval Inservice Inspection NDE Exam Limitations Salem Unit I piping welds. Current technology is not capable of reliably detecting or sizing flaws on the far side of an austenitic weld for configurations common to nuclear applications. Ultrasonic examination of ferritic steel welds requires scanning in the two axial scan directions. Circumferential scanning is required in the remaining two directions only when axial indications were noted during preservice inspections. Coverage credit may be taken for single side exams on ferritic piping. However, for austenitic piping, a procedure must be qualified with flaws on the inaccessible side of the weld.
As previously stated, current technology is not capable of reliably detecting or sizing flaws on the far side of austenitic weld for configurations common to US nuclear applications. To demonstrate that the best available technology was applied, PDI provides a best effort qualification instead of a complete single sided qualification. PDI Performance Demonstration Qualification Summary (PDQS) austenitic piping certificates list the limitation that single side examination is performed on a best effort basis. When performing single side access of austenitic stainless steel piping welds the best available techniques are used from the accessible side of the weld, as qualified through the PDI.
When the examination area is limited to one side of an austenitic weld, examination coverage does not comply with 1 OCFR50.55a(b)(2)(xv)(A) or the ASME Section Xl requirements and proficiency demonstrations do not comply with 10CFR50.55a(b)(2)(xvi) and full coverage credit may not be claimed.
PSEG Nuclear considers exams accessed from a single side of an austenitic piping welds to be fully examined to the extent practical.
D. Exam Category C-C Welded Integral Attachments Reference applicable sections of this category within the table attached to identify specific component information and explanation of the limitation(s) encountered.
Full Code required coverage is impractical for the subject welds since the integral attachment would require design modifications and would impose a significant burden to PSEG Nuclear. In addition, removal of the component support attached to pump would result in the need to redesign the system's configuration in order to achieve access to the area obstructed. PSEG Nuclear has examined these welds to the extent practical and determined them to be acceptable with no observed signs of degradation. In addition, other similar vessel welds have been examined to the extent required by the Code and also found to be acceptable with no observed signs of degradation.
Also, VT-2 visual examinations performed in conjunction with system pressure testing after each refueling outage found these welds to be acceptable with no leakage observed.
5
Relief Request: S1-RR-CO1 Second Ten-Year Interval Inservice Inspection NDE Exam Limitations Salem Unit 1 Alternative Examination:
For the 3rd Ten-Year ISI Interval, inservice inspection examinations will be performed in accordance with the Final Rule requirements and ASME Section Xl 1995 Edition up through and including 1996 Addenda Article IWC-2500 and NRC approved RI-ISI requirements to the extent practical.
PSEG Nuclear proposes to perform NDE examinations upon the components identified in the exam categories below using the current state of the art techniques as demonstrated through the EPRI PDI Program to the extent practical.
A. Exam Category C-A Pressure Retaining Welds in Pressure Vessels Where the component will not allow an ultrasonic angle beam examination from both sides of the weld, the following will be performed using the best available technology as demonstrated through the EPRI PDI program:
"* Similar metal welds, 100% of the required volume will be examined to the extent practical using personnel and techniques qualified and demonstrated through the EPRI PDI, as necessary.
"* The code required system pressure test examinations will be performed per ASME XI requirements B. Exam Category C-B Pressure Retaining Nozzle Welds in Vessels Where the component will not allow an ultrasonic angle beam examination from both sides of the weld, the following will be performed using the best available technology as demonstrated through the EPRI PDI program:
"* Similar metal welds, 100% of the required volume will be examined to the extent practical using personnel and techniques qualified and demonstrated through the EPRI PDI, as necessary.
"* The code required system pressure test examinations will be performed per ASME Xl requirements C. Exam Category C-F-1 and C-F-2 Retaining Piping Welds Where the component will not allow an ultrasonic angle beam examination for axial scans (upstream and downstream), the following will be performed using the best available technology as demonstrated through the EPRI PDI program:
6
Relief Request: S1-RR-CO1 Second Ten-Year Interval Inservice Inspection NDE Exam Limitations Salem Unit 1 "Similar metal welds, 100% of the required volume will be examined in at least one axial direction and two circumferential scans adjacent to the weld and upon the weld will be conducted by ultrasonic examination using personnel and techniques qualified and demonstrated through the EPRI PDI program for single sided access relating to the material type to be examined.
" Austenitic to Inconel dissimilar metal welds, 100% of the required volume will be examined in at least one axial direction and two circumferential scans adjacent to the weld and upon the weld will be conducted by ultrasonic examination using personnel and techniques qualified and demonstrated through the EPRI PDI program for single sided access relating to the material type to be examined
"* The code required surface and system pressure test examinations will be performed per ASME Xl requirements PSEG Nuclear is currently preparing its submittal for a Risk Informed Inservice Inspection (RI-ISI) Program in accordance with NRCs EPRI approved methodology for both Salem Units class 1 and 2 systems for NRC approval. During the conduct of RI-ISI program preparation, PSEG Nuclear will consider the non-selection of those components that have been deemed inaccessible, physically limited or partially obstructed portions provided the NRCs approved RI-ISI EPRI methodology allows.
D. Exam Category C-C Welded Integral Attachments These examinations will be performed in accordance with the requirements of ASME Section Xl 1995 Edition up through and including 1996 Addenda, Article IWC-2500.
Applicability This Relief Request is applicable to the following:
Salem Unit 1 - Second Ten-Year Inservice Inspection Interval 7
Document Control Desk LRN-02-0255 Table II Relief Request S1-RR-CC1 Salem Unit 1 - 2nd Inservice Inspection Ten-Year NDE Exam Limitations Summary Interval!
Outage Exam Date System Component Geometric ASME item Sketch No.
Exam Method Limited Completed Code Required Volume Exam Augment u Eam No.
Period/
Name Identification Configuration Category No.
Exam Information and Limitation Descdption Outage No.
IRXX Amount 204400 2-3-2 14 4127101 BIT 1-BIT-A Shell Circ. Weld C-A C1.10 25 UT 86%
IWC-2500-1 Thise
,.onw oowasconduclated vl 2001 urng approve4 P0O exam techniques. The follovwng UT exama -e cormpleted using 0,4s, and 60 degree srear mane tmraeducers va th io re ordable rdiatons noted. The exarnrinaon waeslimired d
to the -esel epporre and trenrrchororieoton lines Oretinterfered with eeinrg. The totl estimated weld lanr equale epProxi lY 179-, The thickness is approximtelly 1.0 Approxiately t139Y
""the "ed weaexoerrned OdI volura. The I total nted code oemrge achlewed wes approximately 86% ton Ore UTnema Systam Ileakage tsts (VT2) am conducted ech period to detect presence ofleakagn. No leakage ha rinoted in re area of Ore eld. Surfaoe oexam are not required to be conrdetbd upon rse weld per the retrererre of ASME 0.
204410 2-2-2 14 4)27101 BIT 1-BIT-B Tror~itrion Piece to C-A C110 25 UT 66%
IWC-2500-1 rhiTheee i-atoim s cwaonduted AprilQ2t oI1ulngtaproned P01 No Shel4e10 25m tetedques, The olowing UT exama were ompleted using Shell0.
- 45. and 00 degree ahearoeh.
and-.o..Krwi no recordabla rndicatnon nrated The exarmintion-we linited due tooa 22 Wideinsulation rng parbally coreeng Or weld. branch ome and welde lug. The lotal nmated weld l-ngr
- "Ils approximately 179% The
.ickne-s of the orrreionP pece nares betene3.0"- 4.4'. Aproxinretely 11 6-3" of tre weld e eoamiNed ful ool uni The total es d-ated code coverage achieved was approxolryeW % tforthe UT eamnsm Systmn leakage teots (M)2..are iducted each period to detect peen*ru of leakage. No leakage has been noted in Ors area of re wlid.
205030 2-2-2 11 10/13/93 RCF I-RCF-2 Flange to Shell C-A C1.10 28 UT 73%
IWC-2500-lTh s
.taaeea onwbo onee ducsted Octber 1003. UT eransducNe no recordabe indicadlono noted. The exaerminaon wa irated due to n*or ange corpo rgton end a bsell iede melded eupport The scan wee limited between 17'- 201a l(3') woth tre anai.hle ancrrng area llnted to 31" The total estratid weld length eq"als approoxltel 43-71r. The thickness is
".e Approximately 34" ofte weld mas exanined full volre. The total estirrted code conenrge aleed wee,,as ppoxintely 73%
for ore UT coam. System leakagee tnads(VT2) a2m nordoted each period to detect presence of leakage. No leakage has been noted in Itl-area of re teld.
205150 2-1-1 08 5/6/89 RHRHEX 11-RHRHEX-1 Flange to Shell C-A C1.10 29 UT 75%
IWC-2500-1 hil aeeninaton a
-rconduc May 100e. LrrUNeoama CMVptWedusing a 0. and 45-dereeshWeiar wew eraiducer with recordeble irreted rons noted. Recordabeelendweberr were ealuateddto be ID geometr. Nh noxrrinm*os were perforned from the Oange side (operm) due to the enges corfiguration.
No eoarn trne were conducted between 12, to5.cWi arid 52-Wclekisode de toOre fergee onWguration.
The total treated mel lengr hqu1le ePProolmay 12, The trcknel et 1W0.. Approximately 31 of te weld wee non exarrnied ful lobLrm. The total esbreted code crnerage eddeoed wee approximately 75% forthe UT exam. System leakage tnste lVT2) ar mon.doWed each period to deted presence of Noelage a
n lkage has been noted in "aa wdof Ore weld.
1
Document Control Desk LRN-02-0255 Table 11 Relief Request S1-RR-CO1 Salem Unit 1 - 2nd Inservice Inspection Ten-Year NDE Exam Limitations 29 UT 16%
IWC-2500-1 Time, noonabon -
wondooted 4114r2001 uigPOI appmoed No e.... technique.0UT ea..- 0-.-Plat0ed uwing -.45-d.01.
sne1.r 0m0eand OU0deleoRefraoted Long.o0itudinal tranid-with 01reoootebl. cl.,oatiO0.noted. Reoondab01 rnd0.00ons-e0.e0.lut~d to be IDgeomey. Noexumninations
-performe~dfromnthewflong.
side (upstream) due to ft tong.. oo nfiguniti0 nard v0.0001.10ort.
11No.01.0000000n
-m,.d-W ted bem i 12't. 5itoc5km000en rd 5T- 0W Uooto dueO do.tohoe lng.Oondgunitlo Th.Wt.otes titnated weld lengto equaI.lo~l.PPmtety I Z -Th. d000ns10.0011.0' Aoononltly 19-oftne wid wwa coenned full volume. The foal estm.Wted 0
g010. d.v0ed wee. PP.,d-t.eIy 160%
for 01. UT enan, Systen 00109. Notests 1T2) 0m oonduootd been noted in Inis am of thol"Id I IT 82%
IWC-2500-1 The oo.aninaon --e nduted Oetben 1000UT eette.No with1-o000100000ei0m00-no.0Tw orno~dable indica0000
-eo touel nd s
en~loeted te wwn~oeldabde inenacord-noewid, ASME 1FVM-351 1.The.mli0.000100.01 leobduled d ton
..0o.
r n
In o n
o..dooe 01 tASME A TIC-.02420 dong IR10 (Fall 2002). Tb1,a.000100010000-00.0ondllctad
-aWene 01 lnrled do.to N lona e-tehddooo-1 I odpW
&tee 000 interleled 0with0.r0n2.R.
Exam -apetoned I-bow 1001.de ofthe weld Tb. 0000n 0m is0010000100 10r ppOmoimltely 1't3*
4100.00(45. 135. 25end 3104000000). The totl e.Onootd
..001001000, 1 q e. pp-in-~tWlY 282W. Th.O00000e.
i020.2.
App-oinwtaly 2MOW 01of weld n wasexarranad il,A-w.Th Wt.te e o rn at e d d0 4 0 0. 1 0- 0 * " - 'o d w o e ep po o n-ti 0 0 2 %
tor the UT...
- n. Systenn 1-". t0 Nte (/02).O rle 0000.
.000 penod W00401.01pr--
eow 01 0.oeNo0.lkoge.
been WinoIted a-,rof01000.10~
204870 2-3-1 13 10/12M99 EUIEX 1-EU-iEX-2 Shellto Lower Head C-A C1.20 31 UIT 72%
00//-2500-1 TH. exarnonoon ws noodoted Ocbeber 1999.OTnoexamter No oooVkted oeng. 40-dgo-e Ihsarwne wdno tt f r..ordebleimtiododoenoted Tb..nondable 000000 en enlot-td to be ID goonteoy.
Tb..dbioreotoeterninobono oonidooo ware.of. dzlootd dee' the mtoen otn of01to0 oran0 000.0w00001.1 ntet eoed w,01 seooiro. gTh~ere ware0 scanning 0000000001 located 0 on hehead "d.of the woleldOne brnchoboonpis l0 01bootadt ti, W ent00001Oer fno Vseol (4Y.')
and ft ooft,01.
Ioted 10.5' 14.05'toolwneo(4W.).
Th. total ee"tontd weld 0lengthlln"I.plW.I.I.Wey 3W. The.Onolwno 01 W. Approxinnetly 21 W of bne weld wasexe noneed fLO nob..
Th. WW.-
W. 0 onttd.ooe--n"ngaictned 000 oW..o1-taly 72% fonthe UT eoeen. Oywtan 1leakage.in%
(V12) am.
noold oodeson pwW Wdetect eop-t oflooo p 1
.000.No Wa000. e.hasbeoo notedin 0N.otareeof ftweld 205020 2-2-2 11 10/13/93 RCF 1 -RCF-1 Upper Headto Flonge C-A C1.20 28 LIT 48%
00/2-25001 TH. -rnooo*on wa..ndoted Ootbe 1 W 3
. UT examnwerseN ocanpl0ed owsing a 40-f.00.0.1,00, onew boned-enofte reoteblo incokbone bIang noted so doe to ID geotnetr.ThTb ulinio.4Uoi exangr0no noedooted waeoknied 04doe 100ft 00000.0.000 oftneoobeedandNotoeflnge.'0001010.00.
The c~1scan a-
-000ionited tW Wdo,th e ad N
-t boee.
Tbene -en.no.Owex oomdoorted fbone Nolng.e "du de b, oonOrabw. Scn nieng wa, pedonned.oronothe0wild tonten in.0 dirvdonoTh.extotebW Wl ortewendgth01 "I.0 appnoximlely 44*.The. 00000.0moW. The 1WWI1 odntotd code 000.P000 oUond wos.pp0.00iteY 48% for OwUT exam.
Syetn ennkage00toote (VT2)e.. onodoted.each pedtodote det presen0. 0leakage. N0o lokoge abee 1.0notend InOd,sf0 Noleeld.
2 UT 82%
Document Control Desk LRN-02-0255 Table It Relief Request S1-RR-CO1 Salem Unit 1 - 2nd Inservice Inspection Ten-Year NDE Exam Limitations 205040 2-3-2 14 4/10/01 RCF 1-RCF-3 Shell to Lower Head C-A C1.20 28 UT 57%
IWC-2500-1 Tons ex,.mibon mae onUoot0exAm0l 2 001 uenguapproved POI-No degree shear -
e traneduoer with no recoedahle inderebon noted. The ul wtaur.coarrnnabon conduted wemre l-imb1 due to toe conflgi-reho et of*e nozle onfiguraio ad attadhed Ige.
The
.m area we elinsted on the up*.sea i due td O lUg.
and noae conoigegton and on the doorrotnam rsde due to the lugs The total esenaatd wald length egoals appionximatly 44.
The dekness is
,ippmeim.y 0,28'. The total estinmted cede oversage a eved a approximsey 57% for te UT exam.
Syptem leakage te,( l)T.)
are ondutoed.0-h period to detect p-en-e of leakage. No leakage han been notedi In es are.of theweld.
205095 2-1-2 09 2/27/91 RHE 1-RHE-3 Tubesheet to Shell C-A C1.30 30 UT 68%
IWC-2500-2 Thexasminats i-on was oonduatad Feltary 1991. UT examsxewre No ompleted uwng a 0.. 45-and 0-degee helm waee hseeaduo swith nmouodable lnccatoenetedW.
The indkaoifore were enaluted to be I0 geomeey. The ua fiomv exminatso oonduofed were hmntd due to ten branh m
oule ions. hanger and restaint The exam eelimeted to,"
oler o
, shell ede tbwaeen 2T -2W and from 12w"IT-due to bnch conretiona.
The examt wee al limitedto 1'- 2%" froOr thhe e reet side ue sto hang*e and pipe rese*inret,fih intefered rothit e available eyearea. Nocenxamu-Ad ha perotoned flowe 15' 2r dwn to morurtoog plate support The total eelnted weld length egxuel approximately
- 29. The thknese is 0.94d. The total ehotmated ogde o-ermge
,ahieaed was approximately 68%
eo the UT exam. Sys t leakageNte t(VT2) anrenoduok d each perod to deteot pneseneo of leakage. No leakage hse been noted inthis area of the weld.
204001 2-3-2 14 4/27/01 11-STG 16-BFN-2111-1 Nozzle to Shell C-B C2.21 33 &4 UT MT 71%
NVC-2500-4(a)
Th-eexanxnat*aowere performed*n*nApdl 2001.UgVNo 85%
appo-.d PD seI m tedei.oe, A MT end UT e.. dneitrn wene pedweord pn the nozza to Wehef Oot-gbonwnirth roeudelbe Indcanion s
0ded, "The UT exaundnareon wem conuctrted m-Ing a 0-, 45-and 00-degreeherea wreOewdmon.
The UT examination wes pertormed foro the shllslIde. The exam-weli ted 1r due to One p*oeance ofU neain iaon ring covering tIe weld. Th.e rewal offto. midetonnring (belly b") d)e d require extense removal of toe adjoiern iruleuon ftteosto the rirng so t the ring couldd be osrvadln/mp4ed; einsdduhenthe erecooteronamol of adcltonal sueffokldng welid haenesded, this wenid result Iv an Increaee in ere1llperetoenl opexiweum.There have beeenenpoPeviouis indkoeatmu re urpteleere noed asuoated withis o0 other *simlar teeamo geremtor nozzleWo than weld. The total e rmated weld egktl eqth wl sppoutr.xil 08
- 1. T. Thre Olunc1e ls appoei-rtey 3.88'.
The total estnm ed code* o*verge eceeaed was pproximrtely 71 % for te UT00nd 85% for ft MT exam.Sn stem leakage teets 1T2 ran cornducted atthe cldusion of ead aO.toge to detec preesnce of leakage. No leakage hbee Us.ncoted in O"e a a of ft wed.
Document Control Desk LRN-0-0255Table 11 LRN.0.025sRelief Request S1-RR-CO1 Salem Unit 1 - 2nd Inservice Inspection Ten-Year NDE Exam Limitations 204450 I
2.3-1 10F79 BIT 1
-BI I Nozzle to Shell fI C-B I J C2 1 j250-2013 211 j 08 29 HHX UMT 20518:I2-32I I4 II/2/01
,RH HEX I
a11-I loEX-ou1 I :I 21.2%
IWC.2500.4(a) 100%
23%-20.da 3.%IWC-25G0-41e1 Th...sosnaxa onsit we,.-pstWmad in Oot,,sn 180 A MIT and U.O~nfignaboo Wih M.m-dantnnodtaiksn. idntifiedto Th,1 UT congn.
.n
.00d.no _g.oo,Isfad
_,onnm4. da14 T. U sOxn~nsinabon Cnnducted.9.4using a 0-, 45-. arid 0 0
-4.Or.
smar Waf ao d-04...The UT,xfnamin at~ s pertonn, OwnO t-h had -.;d..Ti.ns0exama-linom,,.
touOb V.0,a,.'.
00 oonfiguralio. The total estimated weld Isogon Squgle apynootottly 36.9. Th. 0*1,... nI-pn-liat.Iy 20*. Tb.
lbton* UT and 100% ton ft MT ea.o S ystemnleakage teats (M2) am oondwed.4at Ona wawrglo. o f eachnowage. dto ed1o a
0001f ob.0.-NlO leakge has beennomted in 0t"
-. 0 fln. weld. SY-t nnn 604,gte1s1s 100).an. 000401.4 et,
.0.0105w,,
nI of, eachs 98to detacrt onas-anwoflleakage.
4o leakage he. been.W s1. VI.n...1f.twe _d.
IThs, e... orsenon.wman. ntnn.d In May 1980. A PT and UT
_oN~natkm _.. Osnonnd wonft -.
10d~
- o.
a, aa ooollWaoo.nM no r-rdoon idatoc0at0.. ldrinbbid. Th. UT
.on~aosWan.
000,10.10using.a 45-dognse.1-r
.n-o 5anamducen Th. PT senx am s limitedduto. tohOeno O D~0 nongo"na"s dioes. Pmn* Id t t h.1sond eanngen eld. 11 009802-1.and I -RHRHEX.2 baen I-...2% Sr..Sir-and 28'- 32. The UT sarr00an atm
-psntonned OwnOw the
&,.4" S "a limiesld due oW 00 Mn DlsOD onfigwanw..on'ka I'm"" Wthe t
oh.5.
in-ial aid.lInts 11E-8101.asd iti 0896021-2 betes..o 527. a-0100*1.. 0nd26- - 344. dcka..
TheIntoal asnbnated weld lenng~th equals apprnoximtely 071y.-Th.
tnoknesas Is aPPnoximantely 0.9138-2.6. Tb. total estimated code wo n
--. do 54wa. sppmxi-wsIY 23% frthe wUT and 87%
w1w PT exam. yalam s1akag. t1.00 IVT2) am5W 0
a0 t In aoloelon of os ad, 010.to 4.1.01 nsane,,o f laskag.. No leakage has0 0001.4 not45 an ttam oftseww.1 1,...sos4.s "mns W
or.med Innt.4 10 0D0001using pOnoond PDIlexam.todosiqoss A PT and UT soaNnnatin nws, Pntononod nw~ondOw 00aals to-5-"1 onflgnes w0ll10w r-0n4.tastln-oaden 4ntified.Th. UT e.Osmnlbon e,.m on*-doo us inga454-s,"
h-rs-.on ane0.04.0,,and.a 80 d"I'm n.8.ot.4 lengitodin,.l wane Ons4osnTb.PT nxan limited 4due.tofwix,
.. 00 -oon tnowa dos00.
wmn~ntYto heat eoxootnge weld. I I-RI4RIEX-I snd It RHRH21.2and the wpp~n juglog 6001400 Owine.Osant
.4aioe ftWald. Tb. UTeos4nniabco was penfottnad Imm theW.11W.14 eann "asli0t41.44001. Owno-sOD W.000nfouns.00n'.
do..s nonty to hosts dnanxsngrwkle I I-RHRHEX-1.nd11 4911021.2 bh-tWe~ 2-8,ololootaand 26..W'lolo.
Th-t1.1 sesntimtd!weld tangv,,-Is pa1 prnoxiaa, 57.-y51.
Tb.
SYslsontaaha. -. 0 IT2I, 0n00.
t O Oft ooo 0.nnowted in 84.5,.. of w weld.
4 No No
Document Control Desk LRN-02-0255 Table II Relief Request S1-RR-CO1 Salem Unit 1 - 2nd Inservice Inspection Ten-Year NDE Exam Limitations 204440 2-1-2 09 3/1/91 BIT 1-BIT-1 Inlet Nozzle to Shell C-B C2.21 25 UT 36%
IWC-2500-4(a)
This exarninantonnwxconducted Mamh 1s91. UTexam we-No cox*pleted u.ing a 0-, 45-and 60-dwree shear ma-e tansd*xet with no tecnlable indxcasom notedl The examinaton was limited due to the inlet n-.1t to head shell figurtor i-The UT exam we hlirn e duet to thexzle's o-figuraton. The UT exam ws peritomsd from the anell side xonlwity exam abe t x e srfloned between 0- 3/4" hfrm the eld due xt the
-Wzvle dlowed Ican, The total aimanted Wd lengt equals approximately 43-718.i The itacknesi a 2Y. Th tbl es-irted ncde x
.ge.
ciened wea pproxinntely 36% fun te UT exam. System leage tats (VT2). ae xduxtd eaxO pexd tx detact ma eofn la.gex. No lakage bea been n-tWd In tuie aa ofth ewld.
214910 2-2-1 10 5/14/92 FW 14-BF-2121-3PL-1 Pipe Lug C-C C3.20 34 MT 27%
IWC-2500-5 Theweeexarnxixnsxerx epettrm in May l9n A MT No exanation e was perfnrmd uponte Owpipe lug it xno reonenable indicxton identred. The exam wee limited due to inadequate aneseehetw-en On lug velds and On well penetrton. The yoke used was O-e.. llest sie axailable in the inducsy at thatOw O
The exam pertnoned incuded 6%*W Considewd*naon wnre given for PT examinatn nhowever Onft suace, of the arbon steel x-dd net be adequately cleued to Wsupport uaee deanlineuuneeds for PT examsntxon. The WtI e e*iated weld engo equals sypr..ion-tely 24W The
.ntol enomsed nede e1et.ge achieved webspproxirnitely 27%. System lakage testau(VT2) ame ooncdited atn te ontusuon of each outage to detect pVe-,noe efleagekt.
No leakage heb been noted In thi sae tof t.weld.
218050 2-1-1 08 5/12/89 BF
-BF-2111-3PL-1 Pipe Lug C-C C3.20 34 MT 67%
IWC-2500-5 The.eexamenatonsnwereperteoredlIn May 19M. A MT No exattnabone we perfored uine the ple lug Wh no recotrtdble indcaets Idanffhed. The ena wee Ielmted duet Kiadequate
-eWst On becxlslde ofte ets, lug. This asulted in ne 3
uneibla sides being axannead end patbal amount elms nmining aide whew xnt evd te hx adjoining aides.
E-xarneon access-eae ssxted duestW Te eedoseenmty of to pipe and stxctural steel and tn side of t yoke utlized. The yake used was the smallest swe avaable in tte industry at that time. CosideraOns wesr given for PT exaenation hwwenr Ot sinrance of the crbon stee
-1coud not he adequately cleaned to sppor tsurtfacedeanliness needs for PT examnation. The toet elematled weld ength equhalspproximtely 20".
poxirnatelty 13.4 ws ifully etamined. The total endnbated c odenreeage vd-wespp.ni.tely 67%. System lekage ttests (VT2)1 ate nd cted sntw "onecli*on of snh nutage to detect lnowen-s tfleakage. No lekage h euben noead int sa-of thO weld.
218060 2-1-1 08 5/12/89 BF
-BF-2111-3PL-2 Pipe Lug C-C C3.20 34 MT 67%
IWC-25D0-5 Thesetexarninabtw"esrkpented in Mdaypg19.
A MT No nrtionetne wee pe nnadwine Ow pipe slug wit h nonedrleta riftnionse dke T
e x,
a 1*
nit we e
n t
imed due to imadeqidte e-seto the btckside eofhte attacntd Iug. Ths ten/ted in me 3 e
esible skis being arinaed arid pi nlr enarmount&tt nemsning sida hne mnaxte*-d btheo adlbng Isdes*
Eeninsnaho ate-e weeweblted d ue ton hduses prxmitny of the pipe and txctel ste-irtd Ow asizn of the yoke utilized. Tha yea wend ws the smallest size en/able in t indluetsy at OWt Om.w Conlderionhu uwie gren for PT examen one huweven On siuace of n
he nbon steel xMid not he edeiately eanad to support suwtsx sreninisesees tn rPT sexaminatnone.
Th total se mated weld length equals epproximately 2(r.
pp*n*dmatsly 13.4" wfs uly exaid.
Thm total mated code ovteage axdeved weesapptoxltxtly 07%. System 1"hkade taste (VT2) ure u*xotujted at the ndusion oftuxo outage to detect preusoi, of leakage tNo leakage bes been nted*tna9se
-eof th weld.
Document Control Desk LRN-02-0255 Table II Relief Request S1-RR-CO1 Salem Unit 1 - 2nd Inservice Inspection Ten-Year NDE Exam Limitations 218070 2-1-1 00 5/12t89 BF
-BF-2111-3PL-3 Pipe Lug C-C C3.20 34 MT 67%
IWC-2500-5 The-e exaninaonoonmrn performed in May 19W A MT No examination wam performed upon Te pipe lug oith no recordable indratoos identied. The exa was limited due to inadequae accesa to the backside of Ore atacyred lug. The resulted in th 3 a
eiblae sid.s being examined and partal amolart of tne rermrrng side hefre connected to t o adoring dem.
Eor-ninat sces. e..am 1.reisttd din to Ote dose proximaty of fre pipe end s tIctUnl]steel and Ore size of fte yoke utiized. The yoke rued l Othe oirells size soailable Orthe indue*y at that timOe Consideratronefle gn for PT.. sinarion hronoer the surface of the carbon steecould not be W dately dteaned to support surface leardinean needs for PT easrninaton. The total estimated arld length equle eapproximately 20T Appreorityatly tIC ass fully soarned. Tia total esatiraetd code nc-erage teoed -
sapproximately 67%. Span leakage teen (vir2) re onducted atitd sh condlusaio ofentch oiitge to delent presue oftenge No eiragee bIe been noted in sf ix-of the -Id.
218080 2-1-1 08 5/12/89 BF
-BF-2111-3PL-4 Pipe Lug C-C C3.20 34 MT 67%
IVC-2500-5 Theseexanminations were per nowd in May 109. A MT No examinaton was perfotmed upon tOe pipe lug with no recordble Indlcatons identOfied. The exam was limoted due to int1de accessto,thbe kbcde of the atteled lug. Thu resu*ted in P0w3 acesible sides being exarirred nd prtial eamount ofth remairning de where connected to adorning Wdees Exsermnotron acues owesnetonted due 1to P0 nloa proxirrity of ft pipe and stoclia r steelend P0 six. of tie yoke utlized, The yoke rued a tsiermllett size sosil ble in Ote iondursty at trat tre+ Corederat giueo ton PT eaexnartuion fou the urfl s
fe ti of te rtono etel could not be adequately olned to b upport iurfel oleerdinee needs for PT examiation. The toal etiorrted edlid lengtfh eqiels approximetely
- 2.
Aronoximletelyy134'a-tuilyxrinerd, The tort1 eltorrated nodenwnerge somtemna-d ppxaimetely 07%.
System lleagkae teat (V2) are conducted at thP ono.slon of eachr otge to dete.t presence of lelkage. lNu leaag.he bee been noted in tis lea of the weld.
218090 2-1-1 00 5112/89 B F
-BF-2111-3PL-5 Pipe Lug C-C C3.20 34 MT 67%
IWC.-2500-5 Theseexeoinrrorewerepfofonrod in May 19. A MIT No exarninaton was petfonned upon Pt pipe ig wth no eordable indrcato*ns idrlentod. Thie exam we rlimited due to inadequate access to P0e baekeld of the attached lug. lD reeited in Ow,03 aecessible eidee being enanined aind portil al not ntof ft renmainrng ide dwhere connected to tvo adjoining sides.
Exanonbaton aoree we.rase restr doe dto P0 dose proxinsty of ft pipe and setomofal stle end P Osze of the yoke utilized, The yoke used we-the P0ieemt slie anelable infth indusWy at Pvit tne. Cotr*idrsto were given for PT exoination h-weter0 si.fau of0 te rbon steel could tnot be edequatoly cleaned to support -f-a n
airres seeds for PT exaorninaon. Th totale1sotated weld length equatl approxlmaotely 2T. Aiprooximately 13.4 was fully exanined. The totl estn.ated c code-ge achiered wee-ppoxioWrntloy 67%.
System leakage tests (VT2) are conduccted at thecorcluelon of each outageyto detect prsetlco of leakage. No leakage hee been noted In Ode are of P0 weld.
6
Document Control Desk LRN-02-0255 Table II Relief Request S1-RR-CO1 Salem Unit 1 - 2nd Inservice Inspection Ten-Year NDE Exam Limitations 218100 2-1-1 08 5112/89 BF
-BF-2111-3PL-6 Pipe Lug C-C C3.20 34 MT 67%
IWC-2500-58 TNe-examin eon-nme e performed in May 1989. A MT No exosnation "as performed upon the pipe lug wOth no ecrdabtoe indica-oo identfied. Th.e exam -
mited due to inaequfate aes to Orne backaide of Ohe atolred lug ai nesrNted in Ore 3 aceasiuble sidesbe*ng amined and peortl amo-rt of the remroanng side whre coeofd to to adcoirng aides.
Eoemineon 5ma eas w
esoted dme to Oreadome proximity of re pipe ard smchel steel and re loze of the yoke u*ieed.
The yoke teed a r sirrmlleal sloe a. il in O nir yat Oral 1tie. Consderateone flea osen for PToexanraton howrevenre sice of ore arbon steeal ood not be adequately cleaeed to sippqortlfte idesnlaeea neesde for PT somination IThe total sabroated weld loogth equsal approxirotely 217. AdproxJo tely 13.4" see fdly exatoined The total stirmated code cocerage =ch ed "as appooxlmately 67%
System leakage toate (T) are condueofd atmtse condclon of each outage to dabte prm-n of tlakage. No tlaaiage be been noted in Ots ares mof teaid.
218110 2-1-1 08 5112/89 BF
-BF-2111-3PL-7 Pipe Lug C-C C3.20 34 MT 67%
IWC-250G-5
.heoeexamnacnsow-reeperformedinoMay19.
A MT No examinationw*os performed upon hempipe lug st no recordable inducaons Ideotied* The acarnm se lirmted due to iladaquata accessto o backside ofethe eatched lug Thisresdtd in odo 3 ocassiblee idea being examined and portal amount of the remlrang side wheo coonnected to tw adjoining sides Examinraon eaoes case restricted de tot ledose pepoximity of thoapipe and s'uct-rI v"andths sieo idfe tho yoke utilized.
"The yoke osad -rOnea maositalslzoe
.e-lable nIndOnindalrehy at toatstme. Coniderations wire gloen for PT examnaobon hoomrethen udo ace of dbo carbon steel codd not be adaquafety cdanoed to rportsclraoce leearnines need efor PT
.oa.minaon ThOe total eW ted weld lengt ql apprsoiretely 20-, Approirntely 134.4w,fsdly eamrined. The total astr lte ode cc enge schieed was appop-aetly 67%.
Systar lea kage toete (IT2) ar monorduotads*nteOre noeduon of
,ch ouneg. to dated prasenarr of leakage. N taakags aIa be
.fnotedn
.i..sfaresoft3re Id.
218120 2-1-1 08 5/12/89 BF
-BF-2111-3PL-8 Pipe Lug C-C C3.20 34 MT 67%
IWC-2500-5 These examnaionse-msperformed in May1989. A MT No eceinaeon w"a peorormed upon do pipe lug t no recondable inications idanbiod. The exane was limited due to inadequate accese to the backaide of te attached lug. This resrttod in td e 3 acceossibl s being exnined and portal arnoretofitr rernrinng side w nere cted to twoa djoineng sides.
Exarndatoon sdaoa ws restricted den to do close
,poximity of doe pipe nad sutokel steel and dhosloe eof pftyoke utilized.
The yoke oed oeste onallost size emilablta in dtheo k
ey at dat irme. Coosideration w-re given fon PT exarrminoon ho-oeved aurf-o ofdOne c
on steel could notbe aeeqxately cleaned to support surflace leaniness nee efor PT exarnmnld..T The total estimatedweld lengtr equa approximately 20, fApproximateny 13,4 os efully exoemnnd. The total ssnated code coverage achievednwreapproxlmately 07%.
System leakage tests (VT2) are orducted atd thecorldoon of each outage to detect preosne of leakage. No leakage has been noted in hIs ones ofV isd.
7
Document Control Desk LRN-02-0255 Table II Relief Request S1-RR-CO1 Salem Unit 1 - 2nd Inservice Inspection Ten-Year NDE Exam Limitations 218130 2-3-1 13 10/15199 FW 14-BF-2111-3PS-1 Pipe Support C-C C3.20 34 MT 32%
IWC-2500-5 The-exanminnab-wre performed in October 199.0 AMT No exa tiun* -
r w performed xmoon ore pie iW Iour lro "*
recordabe inrdciboa ldenfied. The exam ass lmired due to iadeqmtmo acces rmedtng from adjacent a
rpenend trl cumpornonrso coiguntuio Conoideasbore wern goon for PT e rminetun rorec-r One se.ans of the carbon steel could not be edequafely leaned to support surface doamninesa raý eds for PT ecaminaio n The total estimated weld lengt equale approxinately 44. AAppoxiarrtely 14' was flly ecamined. The tota estinated code coverage acoced ores epprocinatoly 32W System leakage tests (012) am conducted at tre conclion of each ocutge to detect presence of leakage. No leakage he.
been noted n irluarea of fte weld.
223400 2-2-1 10 5/7192 MS 34-MS-2131-1-PL-Pipe Lug C-C C3.20 36 MT 75%
IWC-2500-5 Theee eoarminaboeerm performed in May 1992. A MT No 3
e....
no o weperformed upon the pipe ai rf lug wr rino recordable irdcatrone dtentied. The e.s... weiirted due to roadeqrarte aess remtoibg from adjacent simporte strutual steel and the orrlponent's conrrgratiron. Conrederesrrwere given for PT examinaton h-wneen the surface of tre carboo steel could not be adequately coteaned to supportsulface cleardiness needs forI PT excnmirSuon. The totel estimated weld length equale spproirrately 44'. Approximately 33" w fully exenined. The totel estimated code -ncerege acgheved was approoimately 75%. System leakage teat. (VT2) am cooducted at the corrcluior of each outege to detect prseence of leakage.
No leakage has been noted in thl. are of te weld.
223800 2-2-1 10 517/92 MS 34-MS-2131-1-PL-Pipe Lug C-C C3.20 36 MT 75%
IWC-2500-5 These examinatons wemrs performed in May 1992 AMaT No 7
exurni on was performed upon the pipe support lug with no recordable indications Idntied. The e"am wee hmoted due to iradequate access relng from adjacenot supports s ructal steel and the cornponentc conffuoradon. Correderaborrewere g00en foe PT exneinareon ower the surface of w carbon stee could not be adequately cloiaed to support surfaneoleonliness needs tfo PT exanlnatron. The toter esfirmaed weld length oquals approximately 44. Appoximately 33" was fully examined.
The totale) 6s
-ted c
o rage a d w.s approximately 75%. System leakage testt (V12) are cord-uctd at ee cornolud k of each outegeto defect ireserw of leakage. No leakage hes been noted in this arem of0ftweld 224020 2-2-1 10 58/7/92 MS 34-MS-2131-1-PL-Pipe Lug C-C C3.20 36 MT 75%
IWC-2500-5 Thseooernmtiuoatr eyo performedlIn May 1992 A MT No 13 exaniraiuon was performed upon the pipe support lugI wi*h recordable IndicatornsIdenbtified.
The ocam we. limited due to inadequate ac s reslting from adjacent supports srtwtrasl steel anrd theotrpocenirs configuration. Currldenad wwere given for PT exaonan to howeerw thesufa0e of tochearbon teel oulid not be adequamely cleared to
.spport e*-afte cleanliness reads fuo PT ecamir-natn. The totea lrn*ated weld length "erualsapproclmately 44". Approxlmately 33' was fuoaramined.
Thte otael esnrmaed code <onerage schlered we.-appro!iretely 75% System leakage to.t (0T2) amr cond4cted at 0ve corrolimon 0feach outege to detect dpresce of leakage. No leakage has bee rnoted In e area m
)of0t weld.
8
Document Control Desk LRN-02-0255 Table II Relief Request S1-RR-CO1 Salem Unit 1 - 2nd Inservice Inspection Ten-Year NDE Exam Limitations 224040 2-2-1 10 517/92 MS 34-MS-2131-1-PL.
Pipe Lug C-C C3.20 36 MT 75%
IWC-2500-5 Theweexaernna o*more performed in May 1992. A MT No 17 examinaton cas performed upon te pipe epport lug with no reoordatbe indication identified. The exam was lmited due to nadeq acm x v 0Latng0 f tram adjacent sapporta stroctural steel and *Or. 1o4enWe2 configrtabon. Cornederatona time gron for PT ex..
iarron ho mree the aureace of rhe carbon steel
-ouhd not be doqoately oceaned to0 pport ofa* le teanlines need. for PT e.a.i
.on.
The total eatmated weld length equal. appromately 44. Aproximntely 3 33" -.
uly. ea.mined.
The total eaernatod lode erge acteed o aWoiorrately 75%. SyOtern leakage foote (VI2) a.e
.ooduced at she corwtoaionnt eachr ou0,ge to dete-t omeoeo of leakage. No kagesh bee an noted In t area of 0, eld.
227900 2-1-2 09 3/12/91 MS 22-MS-2141-2PS-2 Pipe Support C-C C3.20 35 MT 50%
IWC-2500-5 Thru e.a.minabtooowareperformedrin March 1991. A MT No
.e.m"nation w. perfomed upoo rte pip. mpprt1 logo 0,th no meorsdbte inicatioI dentified. The exam "a limited due tW imadeqLate acces readting from instoruneoetoon lines in cro0 proximity to thoeweldand the componrentscondug-ton.
Consideratiore oe mgivenefor PT exarinaaton hownver Ore atoface of the carbon steel could not be adequately deaned to aupped rtoface dearniness need. for PT examinaton. No examnation conld be performod between 0"- " (14) clockw'oe, 2-31" (9'),43'-W0 (17)"end72-82 (107)d toe phyieoal reosrotiorr reerlong from Ore inotrnentaboO lines aed the lug.. The total esfinated-mld length eqoal approxrmately f100. Approximately 0
5Wasfully exaemined.
Tre tota1 estmated oode oonerage aclolied wee approximately SD%. Syetem leakage tents (VT2) are oonduoted atftOec00ncu0ion ofeach outage to detect peonce of leakag. No leakage has been noted in this a-of th weld.
228000 2-3-1 13 10/15/99 MS 32-MS-2141-2PL Pipe Lugs C-C C3.20 35 MT 65%
IWC-2500-5 Tte exaedom *lrtonwere pertomrodlinOctobertlt.
AMT No 1 thir 12 examlnaton we perfome upon the pipe aopport luge nwot no reordabtee ndications dentoTed.d The exam wee lmited de to Inodeoqrrte aees reedftng from adjacent componflnte and Or.
componentseorftgurmton.
Pipe lug welds 2PL-1. 2P1-5. 2PL-7 and 2PL-11 were not ae. e1leamned due tot*e* permanent obetrbon onro hte penetration well Correderawoo e
. ga for PT earination hoenr the r
r.face ofleth terbon teel corld not be adeq-atly o nod, stoupport artace fdeanrni needs for PT e..rnaicb.o Th. total et ad ld lengthq l.
approximately 15t, Appnxiortly 102p O
furly examined. Th.
total toed oded-
.ge ah-ed we apppoximrnetely 65%
Syptem leakage tas (VI2) am condcctad at the oor*dioaoof
.00h orrtge 0, deteo oreenr otloakage. No leakage bee beex noted in 0ts area m.,th weld.
229000 2-3-1 13 10/15/99 MS 32-MS-2131-2PL Pipe Lugs C-C C3.20 35 MT 65%
IWC-2500-5 The-exarminabonmwere perforned inoOctoWbe19. AMT No 1 thru 12 e*rteneo we
-performed upon Ore pipe upport luge withno recordable IdiconseIdetified. The exam w limitoed dle to Niadetqteaoces N resulig from dji cnt omponents and Ore componenteconfiguraton.
Pipe lug weld. 2PL-l. 2PI-0. 2PL-7 and 2PL-1t were not able examined due to re permanent obatfcton, from tee penetrton mall Consideraione were gftn or PT examinatio hon w
Oer the surface of te, carbon steatcould not be adeqontely clasned tos upport srfcerdaceanliness0 nead.
or PT examination. The total estmrated
ýwed lengtr equals appoximatel y 5I". Atdroximately 107 o-fuly exarrned. Tbe total eatnratd ode ergo achoed ma pp xirnrataly 65%.
Syatam leakage teata (V'I) am coodo-tfd at the cocndLWoa of each outage detdct ped l
e of lelakge No leakage bhe been noted In t*os... of the weld.
9
Document Control Desk LRN-02-0255 Table II Relief Request S1-RR-CO1 Salem Unit 1 - 2nd Inservice Inspection Ten-Year NDE Exam Limitations 230000 2-1-2 09 3112191 MS 32-MS-2121-2PS-2 Pipe Support C-C C3.20 35 MT 13%
IWC-2500-5 These inatuonsoe-e peituold In March 1991. A MT Yes-MIB 3-1 exaei*onto -spettorseod upon Ore ppe support lugs wit sno recordable indicat-o Identfed, The e.ar was limnitd due to irraderoate eessu resulting from inswcnertobon lines in dose proxiinty to re welds and the componeetls oofiguraton.
Consoderouns were given for PT exarriabon however tre srface of oe caronsteaeel oruld not be adsquately deaned to support eoaoe clearineso needs for PT exaninadon.
Exaruination cord be performed between.9" to 43" due to phypeical resnows eutrictosrslig fmthos Oe trtrsWrntation litnes and logs The total tnnmted weld engUrequals approiknately 100W.
Approkirately 13-1/4' eas fully exarined. The total estrrated sod. o-.erege eoieevd wees1npproirnrttly 13%. Sytew leakage tours (VT2) aem rontdcted atrte sonctusion ofleach outage to detect presenew oftleakage. No leakage has been noted in Od se-ofth Orweld.
230100 2-3-1 13 10119/99 MS 32-MS-2121-2PL Pipe Lugs C-C C3.20 35 MT 65%
IWC-2500-5 These exatrnaionr, were pere neOctobert1999. A MT No 1 thru 12 exmenamewas tperfornurd upon Ore pipe suppeot lugs wit sno recordablre ldicetins dkenlsed The exme we. limortd due to Iradequat accens resudtng fsrois dacent conrponen sant Othe coerpoents coniguration. Pipe lug welds 2PL-1, 2P-5, 2PL-7 and 2PL-11 were not able eoained dIue to Ore permanerd obsbrucron orne Ote penetrction wll. Conswreidsrutonsrss glvos for PT examrntos howeser Ore sautface dtof finebe steel oiuld not be ssdquately dnnesd ol to suip sus. oesadinea nseds for PT s.sed*neo. The toal sTeret-d e.t lehr equals cpprsuitsly 15T. Aiproxirntely 102t -w fully texeined Thie total stered cede onege audeced wd s appminsrataly 65%.
Systis leasikae e a (VT2) am cordusted sattre coidiumron of echr outege to datest presnce of leakage. No leakage hte been roted is i
ar-e of the s id.
231200 2-3-1 13 10115t99 MS 32-MS-2111-2PS-2 Pipe Support C-C C3.20 35 MT 36%
IWC-2500-5 Thesoexactinaoe's -wereprteomled in October 1999. AMT No setdrniabor was perfurerd upon Ore pipe support logs reftOrno recordable iidicabý otr dentfed. Thr esera wea limited duteto inade=prt a coweas reulting frome ineention bines Isdune proximity to Ore welds and Oe cosponers sconilguraeion.
Coneiderstone were given for PT earsnaton howeaver Ore isrface of Or carbon steel oDd notso be ndequately dcaned to support surface denldinee ne fow PT sorrinabor.
osrineton could be perossd duest poyihyc[
e rLoen reutibg frem the inenetebon fines, s lugs T.The t*l esertin d !asidles gfir quaels.cppmsduastlyp1t0.
dpleeeiintely 3s, weefullye enued Tb. tt al es d cods sover9ge vaced wee sppmsoira'aly 3e%. Syars leakage tast (VT2) am eesdurted.ster codcusio dofeac ou**e to detect pfeer of leakge. No leakage he. bee*s noWd in tue a dof Una Wd.
231300 2-3-1 13 10/15/99 MS 32-MS-2111-2PL Pipe Lugs C-C C3.20 35 MT 65%
tAC-2500-5 Theee exarninsonsowero performedins October 1999 A MT No I thti 12 eoanriraonseu perormed upon Ore pipe support lugssw irno rcordableo lndictorrs idenf
,ic The ecen,was limited due to Inadequrte aeos resitfrg r*o adjacent couponento and tOe oeiposnts coiguonfion Pipe lug welds 2PL-t, 2P1-5. 2PL-7 end 2PL-1It wee s ot e le exan*ied due to No pe neont obe*tucon fromt Oe penetaion well, Coneidestions were goven tor PT examinfion ho fverta surface doffth carbon eel could sot be adequately deaned to Wsuppo surface deatrir -
reeds ton PT oxacninaeon.
The total estemted weld lengtha quale approxirnete ly 1W. Approxinrtely lt(1 was fully exacioned.
Thettal estrated o covderages aesdo d was approxli*tely 65%. Sysftos leakage teotu (VT2) are aordocted stre condusiono deoe outage to detest preeae ofleakage. No leakage bee bees sobed in Sueseam odte weld 10
Document Control Desk LRN-02-0255 Table II Relief Request S1-RR-COI Salem Unit 1 - 2nd Inservice Inspection Ten-Year NDE Exam Limitations 263332 2-3-1 13 10/15/99 RHR 14-RH-2112-7PS-3 Pipe Support C-C C3.20 59 PT 67%
IWC-2500-5 Th.e.eeexarron st e-arfpmoanedlin Otobrrt1999, A PT No eomination wae performned upon t hpipe support welded attoolchnent wor no renmodabie indstions idented Tre exarn wee rioted due toe= pen-oent obboton tat note eieAn r1 oft thfar side of o eoarxmnatoi onotasce tIis adiacent to te penetration- -il. The total extimated reed e gequals approximately 24-. Appioximatety t16-e s lty exatined Trhe total esitialtd code coearge addend nme approximateiy 67%.Syetor leaskage i h(VT2) are condicted at tre oedusio o of each outage to detet prees*ee oftakokge tNo leakage tes beae noted in tI
-area of tinreed 263334 2-3-1 13 10/115/99 RHR 14-RH-2112-7P$-4 Pipe Support C-C C3.20 43 PT 67%
IWC-2500-5 Theseoexaminationsweemepefomed in Ootobert19%9 A PT No exnarnaotone e mperformed uponpthe pipe e*ppont nlded athtanentewt rth no irecordableI nrdiat*os Identfied. Tie exam es-limited de to.a permenent oblotoicon tt exists an to nt1" ofn tae fr side of toe exatninoon suton oat is adjaeoto toWte peneirateen wall. The total estimatedrweld le g encuals approximately 24.Appeproximately 16t nat-foly exaunned. The total estimated code -oaerge acieved approximately 67%.
System leakage tests (V92) are conrducted at the oonclusn Of nhb outage to detect pee-r of leakage No leakage has been noted in tts ueam offtte eld.
205280 2-3-2 14 4/10/01 CVCS 11-CHG/SI-PMP-I Integrally Welded C-C C3.30 38 PT 73%
IWC-2500-5 Thesesexamined-oe-oereperformnedin ApnL200D ouing No (1-4)
Suppers approoed PDI exam ertecnue.e A PT noemmneraonese pea'formed upon ft Integrally attached eelded
!pump lugs
- wit no re-oudene indna"b-erideol.d. Tir
.oam Ws lirted d* e *to a pe endy retailIed ebetrucn (pump euppoeft) and pump end cap deelgn. Tire total esimnved reed lga ep*.le sppeoimotely 24. AAppnoeiA elty 17.5'-
fully e.a.n.ed. The total siratd node roers-ge adhend we eprxesety 73%.
System leakoge tate (V'2) a-atdonted dae ýenotuslon of sean outage to detot p -e oftleaklge. No leakage toe eena notxad In.tINs area aofa rlewd.
277900 2-2-1 10 5/20/92 MS 12-MS-167-VS-1 Vatve Support C-C C3.40 37 MT 82%
IWC-2500-5 Thimeeminaneretor-tperformedlin May t992. A MT No exapimbon Wac petonired upoete nave espports welded attachmerents rno reordele Indicateons Idernied. Tim exam Welimuitedue to fie smro..d ng support etnituen. No exandreInonsWere able to be pereormed VS-i1iS-t5I-rdueto ntsurTrOunding supportlrp
. The tota estimated weld lengthe".Ile approxmirtalpy
- 21. Ap*roxinoaelp 17 wr eo.ully examrned. The total estimated node ounerage adrlimed approximately 02%. Syptem leakage testo (IT) arem ndrtad atln oreitrolon of each outage to detoft pnraenoxe of leakage, No leakiag* *as *ben noted Inthis area ofli,weld.
277940 2-2-1 10 5/20/92 MS 12-MS-167-VS-1A Valn Support C-C C3.40 37 MT 82%
IWC-2500-5 These nxaminone were pentormaed in May 1992. A MT No exarren n nwas performed upon n valest upportsnwelded atuantrments rt no recordable indicreionr identfied. The exam
-at linmted dun to intsu *undinirg stpport astoutes. No exarnindonso were able to be pIped VS-I 15 -19' Ode to in urrToinding espport itaxes. The totfa loarted weld klnot ipols approxiom*oye 2V.Approximotely 17 e lofuy exanmned.
Thr total e"rna oD conerage anwened sW appr.innirtely 82%. Systen leakage tste (M2) ate nomndktod atmdw condcluion of eah outage to deteodtponvre ooleakage.
No lekge.. h.been noted in0e a-re of r.-d.
11
Document Control Desk LRN-02-0255 Table II Relief Request S1-RR-CC1 Salem Unit 1 - 2nd Inservice Inspection Ten-Year NDE Exam Limitations 277960 2-2-1 10 520/92 MS 12-MS-167-VS-1B Valve Support C-C C3.40 37 MT 64%
IWC-250G-5 Theo exarmnatons;were peorofned in May 1992 A MT No eoaronuabon was performed upon ther.ive supports welded attaotrmentawothnooo reooodabl, Irrndcaons Identofied.
The e. a was lirrod due tot se surroundig support strutues. No exariratiorns "r able to be perfnorred VS-18 18" -29.5 due ton o eurrounrdog support strutes. Thr total ea*t-ated Weld length equals approxiootely 21 -. Appoximrately t13.5 was fity exanured. Th. total estimatd e
od.ed verage actieved was apnroxrirtaly 64%. Systemrr fakag tes (VT2)arm oronducted at ts oolwauoron of each outage to dotedt presenrro ofleakage.
No leakage has been noted I rthis area oft hewld.
278140 2-1-1 00 514/89 MS 13-MS-167-VS-1A Valve Support C-C C3.40 37 MT 82%
IWC-2500-5 Those exaroinanonsower performed in May1992. A MT No examinaton was performed upon fr evavet supports wlded attaolomera odir no roordable indicaaons identified. The exam ws limteed de to tse surrounding support sttous. No exaossinarioewerabletobaperformed VS-1 15-19dweto the susoewnag support structures.nThe total esti.ratd weld lengthor euals approximately 21¶". Approxioataly 17' was fully examined. The total estimatd oode coverage ac.ueved was approximatelyr 2. System leakage tosts (VT2) are omrdduted ats. onueion ofah eavr outage to detdot prasera of leakage No leakage h6. been noted in fs area
-of the wld.
278240 2-1-1 08 5/4/89 MS 13-MS-167-VS-2A Valve Support C-C C3.40 37 MT 82%
IWC-2500-5 Theus erarosuwere performed In May 1989. A MIT No examination was performed uponft" vae supporfts welded atuohments with no eoosrdatle Indisbons identi/ed. The.exam was limboted de to esurrounding support structures. No examinationso o
e able to be performed V.S-2Az to -9 ds to th srenwodrng upport stuwturs. The total estimated weld lengtho equals approximately 2t. Approxlmately t7 was fuly exardned. The total oefsitated code overaev achieved was approxiately 82%. Sysemn leakage tests (T2/)am ronoduted at tse concluwion of each outage to deteot pmeanoa of leakage.
No leakage 4st beesnwoted In th/s ama of the weld 278340 2-3-1 13 10/15/99 MS 14-MS-167-VS-1A ValveSupport C-C C3.40 37 MT 0%
IWC-2500-5Thesaeoaniearo rwereporomaedin Otobert9ISM. A MT No examirntion was atre*pted totbe operformed upon the vaeve upport's welded atacdwrt. No examinatons could be oompleted due to an obtsnttion from t e14 Main Steam Header permantentnpports that prevent aoesstoths area of oerminaao Th"e exam as linmted due to thesurrounding support sstuoturas.
The totai estimated weld lao/Pr equals approximately 12. Appaoxin*0taly " a ofully examined. The total estreated code coverage edltaved wae approxlmately 0%.
System tlakage testa (VT2) are mconrrded at tet oonuslon of each outage to detect pre*ence of lakage. No leakge h64 bean noted In ths are
-of*t weld.
278440 2-3-1 13 10/15/99 MS 14-MS-167-VS-2A Valve Support C-C C3.40 37 MT 0%
IWC-2500-5 These exarrrinaorrewere performed in October w
- 9. A MT No ex raid.on w-s attorriptod to be pearformed 4pon0 ts vaw e suppodts welded ataulsoen. No exa/rinarow*soould be corpletedA to an obe-bonf from the 14 Mtin Steam Header permanent supportsd*fip rnevented -
w tot.area of exorination. The exam was limited dse to the surromng support ht.t.r
.mTha total earntad Wd lengthr equals approximately tIT Approximately ( was OUly examined. Th.
total asumated and. aoverage da d was approximately 0%.
System leakage t*ost (M2)are onur tsld aats thcouculurio of sash outage to datoet presre oft lakage. No leakage h4a beaen rayd is f.s area oflt*
W s
12
Document Control Desk LRN-02-0255 Table II Relief Request S1-RR-CO1 Salem Unit I -2nd Inservice Inspection Ten-Year NDE Exam Limitations 263422 2-3-1 1
10/20/99 RHR 8-RH-2173-2 Valve to Elbow C-F-1 A-E<3/8 44 PT UT 100%
IWC-2500-7 Th.. exanir.tonowere peonoed In Octobe. 1999. A PT and Yes NRC RAI 111/9/88 57%
UT exa inxton was performed upon fte vlve to elbow core00on0 onfigorao n with no recordabe, indicatorn sdentfied.
The UT exrinalion were conducted ua*ng.45-and 70-degree she.,r we-- "n0d-,
Th LUT e..nnan wa performed fror reelboww ide due Wf to OD valve onnmlgreon. No scannong couldb e performed fromft e velv Ode. The ue of ebsear w-ve to inmeiptafe te opptosie 0sde of a weld has 0toe been pro"en throughf te PDI rtiative to be uneisbte;. terefore 000mum credit is taken tor eoheevrng wege ffort* 1W side of ire weld The totel estnmated weld length equals approximaewly 21'.The 0tkne., oapproximantely 0.432. The totsl eorimated code ooenage onheed wex
.approximately 57% for 0ie UT and 100% f.o he PT enm. Sytome leakge fet. ('r2t)..
conduted at the concluson of each outage t detect presence of leakage. No leakage has been noted in this are of the weld.
263616 2-3-1 13 10/29/99 RHR 8-RH-2116-2 Vale to Pipe C-F-I A-E<318 48 PT UT 100%
IWC-2500-7 Thaeefexamina.on were perfomad in October 1999. A PT end Yes NRC RAI 11/9188 57%
UT examnnatione ws perforned upon te a de to pipe connetoon omfguraio witO no recordable indicions Identifd.
The UT examn.oeo wetwrs conducted using a 45-and 70-dege shear waye transducer.. Te UT eoxmineOon was penformed from
, ealbow edue 0toft0.0 IOvhone onfigunton. NO No rewng 0o0ld be performed fromth0 -I-e id.e Th 0.- of.a ebW-reo to inveotigate On oppoiteo doe of a weld *hassinhe been pronen Orooughbthe POI itftitr, to be unrebialee; Oerefone
- minimum credit is taken tor acaening coveragetor thefarside/ of fte weld.
The to0tal
.eted weld length equals pproirnately 25'. The tickns.s is approximately 0.432% "he o tt.e estinated code 00ovegeachived weapproximately 57% forthe IUT and 100%
for w PT exam. Systen leakage t0o d(VT2) are 00nduct4d at the co00u90 n of each ounw geto detect presenoe oftleakage. No leakage hae been noted in tisarem ofthweld.
263620 2-2-3 12 4/9/97 RH 6-RH-2116-4R1 Flange to Vale C-F-1 A-E<3/8 39 PT UT 100%
IWC-2500-7 Theae exaoinatons warwerpetforned in April 1*97. A PTand UT No 50%
oexaminaton was performed upon. tinlve to elbow confguraton with no recordable indatons dientifed. The UT examninaono wert onducted usng a 45-and 70-degree aber wa0e transducer. The UT evxrnmntion was performed from tn0 flange 0ide only to w ext.nt6 precnat due to the OD 0
e onfiguration. No scnning 0ouldb e performed fromon 0
0al0 ide. TO. use of. ahberwaven to im-tigate 0theopposei ede of
. weld he.
n.1 been pnovene 0gh0 f toe PDI millet.to be un0iwb.;; t0,1fore minnon imcrdit I.w. ton ofo.
- e**g
-o g.forIe*e. r aide of ft weld Th. tofel estimated ing 001 eIs approximately 27. Thb Oickness is approximately 0.375". The.total esmaod t
ode 0of-. e
.p hNaved w e approximately 50% for0to UT and IO% for. thPT exam.
Syte. leoakage t1st. (V12)/-con0educted t t.onedluon of each outage to d~e"t pnseoofe 01a1kage. No leakage has been noted inIf, am of the weld.
13
Document Control Desk LRN-02-0255 Table II Relief Request S1-RR-CO1 Salem Unit 1 - 2nd Inservice Inspection Ten-Year NDE Exam Limitations 354640 2-3-1 13 10/20199 CS 8-CS-2123-46 Valve to Elbow C-F-i A-Ev3/8 47 PT UT 100%
IWC-2500-7 ThesaexamnationsvwerpereordindOtober19W.
APT and Yes NRC RAI 11/9/88 50%
UT examination was perWfoned upon thee valeto elbow ovofiguab*o o ith no recordable cd~anon aideoSed. The UT exaronanonrbrnre condcred using a 45 and 70 degree shear wave tansducor. The UT examination was paformev d fromt ae elbow ead. due to tae ODw
-vale oefigraon. No sarnnag ould be peros*vied forn rte valve side. Thev ue of a saear wave lo ineasboal0.e opposte side aofa weld b.ee e.I been po-en through w.
PDI iniatve to be wsable:the:roeeoe
- Minindr, voedat is taken for adheving coverage for tow far a" of o. weld.
The oawl esbrneatad wald length equals approxivately 27W. The thickness is appo0ximoltaly 0.375U. The total estnited code coverege acheved was approximately 50% for Owe UT and 100%
for ot PT xaw. bSysrem leakage tests (VT2) are conducred at the coWusion of eavh voutage Wo ded preare, noof leakage. No leakage Ihw been cored In Is/area of the w
ld 356360 2-3-1 13 10/20/19 CS 8-CS-211446 Valve to Tee C-F-1 A-E<3/8 48 PT UT 100%
IWC-2500-7 These evarivabons were perkformed in October IS 9. A PT and Yes NRC RAI 11/9188 74%
UT examrenation we perefo d upon he valve Ot elbow conguwabondh -arn recoodabe. indabera identiied. The UT soendee-ta -were vonduvted aang a 45-and 70-dege sher wave seedwer. T heUT examnaiSon was performed fromwt lea aide, due tor he OD lve eanfgur*bie No snnrang ouldd be peraOrend efrom ohe vale aide.The eofa habr wae o
invsustge e oappeosaidae of.f A weld bheae n been proven theroughe PSI irateve Or be t-lable; thereowea rnisas wade le takae Orfoad-ering serage torothe far aids of1ew weld.
The total esMmaltd weld woergth equle approximately 27." The eskneisa aeppeximatlly 0.375". Th. towal eabnated cods
=v Wice ahevaed was
,aproximataly 74% for ow UT and 100%
oo PT exm.. Syltem leakage testa (VT2) are rda&td* at dow easduv of eachr ouage Or detdet poaneiw of leakage. No leakage baa been noted in on-arof t weld.
263110 2-3-2 14 4/20/01 PR 6-PR-2101-13 Pipe to Branch C-F-1 C5.11 58 PT UT 100%
IWC-2500.9 rhesexamivnabonn warespevrormd in Apll2001ausing No Connection 57%
approved PDI examrtohnvdo*a. A PT and UT examrneaionr as pearornmed iuponw valve toease conelguraton wit no recordsble rndicabors Idenbid. The UT examnations ww aondurad uiwng a 45-and 70-degree sndar wave
-nnedaaer.
TheUT evarninatio was per*ormed from the tee aisd due t ow teOD valve conogunabon. No scarning could be perlfonmed Snomwf alve side The a ebofishar wave to Inveligaeleh* oppoaste ade aofa weld ains ea-been proven through w PDI iS i iatavbto be unrelable;: therefremnimumcrditis taletkern lfora avng eoverageforthe lero side of the weld. Thelealfbiawed weld length equals alpximprealty 27W., Thes/tcknees is approumately 0,375. Th.
Mail autremtedvcode
-over"g evidened wa appeorretey 73.5% fos rai sUT and 100% for era PT roam. Syslymi leakage tea {(V`312) ev ondtead wowstt
.ondvuein e..
.ehiotgel datet peran of leakage. No leakage has been ratledline.sa eo thdev.Ms.
Surfa. ev-are ndreq*ired Or be vo**n*es<l i n 0i weld perow taquirements of ASME XA. Systler leakagetest s(VT2) are.ondreted st w roendainofe deach outegs to datedt preenve of leakage. No leakage has been noted ins 1heare of ow weld.
14
Document Control Desk LRN-02-0255 Table II Relief Request S1-RR-CO1 Salem Unit 1 - 2nd Inservice Inspection Ten-Year NDE Exam Limitations 263304 2-2-2 11 10119193 RH 14-RH-2114-18 Flange to Pump C-F-1 C5.1140 PT UT 100%
IWC-2500-7 These exarninas*onwere performed in October 1993 A.PToand No 50%
UT exrrnnanion was pantoreed upon ins flange to pump coniumcwr wtosn norreecondatbo indicaions identfied. The UT exanmnaton was conducted using a 45-degree shear woav raoasdaer. The UT oarminabon ass performed whsls scanning clockswie and counrendockce pe upon tes Ild and Heat Affectaed Zone O0 configuraon. No a=ial scaring could be pertoomnd tfmora e flange or pump side due to Ore OD confiburin.. The ofa shear -av to i etgata One uppousita ide of a weld hae msato been pe*ven through the PDI intisb e to be eneuliabla; thernsre einisumocreditis taken for asdesng covesnagrsoa theore t aide of the eld. The total eatonaed "eld length equsac aperoximrataly
- 44. The stickness is apresinrtely W Th tohtl ud*orated end, moer-ge uc.iemed "appmoxrataly 50% for the UT and 1 o% otreo ePT exam.
Sysrem leakage tta V(MT2) are condutedI at the conc.umion of each outaue to detaut praene of leakage. No leakage has been notedI in hsu a-a tofte mld.
263614 2-3-1 13 10/29/99 RHR 8-RH-2116-1 Pump to Valve C-F-1 C5.11 45PT UT 100%
IWC-2500-7 Thes exoaeinaeon mnrmpertormed in October,19,. A PT and No 23%
UT exmrinarton was petotmed upon sOe pernp to vame congatenswitOren o recordable indrcaionsidentied. The UT exoanrron was oendced using a 45-doegroe shear wave "naskdr-e 1The UTexarnnetisn was performed wiile scarning clocko*is and owuntencockl. ~upon Orewald and Heat Affectod Zone OD vale configurtin. No sca-ing could be pstonnd hfron or valve or Ome punp side due to Ore OD configu'ons T he use tofa sear wave to Ioe-bgete rte opposite aide of a waid has sine been proven trough Ore PD1 initiative to be wuabiaeie; eretors minimucn credit Is taken for achieving coserage for One for side of tte weld. The totol estimatedreid lsegt equals approximately 27W. The itcknaso is app-oln*otty 0.375* Thetotal es aemad tede aveamge achieved was approxirartely 23% for e UT and I OD% for the PT exam.
Syst*m leakage test (VT2) are conducted ante taconrdusion of each outage to detect presce of leakage, No leakage bas been
,noted indths irea te raidna
- d. Sfe eoa--a an. not rerpiredto be completed upon -aswadi perfte n.raumente of ASME Xl 264206 2-3-2 14 4/14/01 SJ 6-SJ-2104-4 Safe-End to Nozzle C-F-1 C5.11 None Available PT UT 100%
IWC-2500-7 Thess wan orae,-,"a rperforned InApil12001 ueing No 38%
appr-.ad PDI exam teotwique. A PT and UT eeerhrehone was perntomed rupon the featend to mnuzle configuration with no recordable eisiiosm Idaskued.
The UT examnartion was concuctad uing a 45-degae e"ar wa-e trarsducar. The UT exaoinataonb es perrenned t rm the ft-ei eis. The eam
-anarr itad uere tote mle*O DsI 0 egurallton and adpoernt weld 1(-SJ-2104-3) ed was too cdoset t allw tor adequate scanning epace. "lTe treeo ida.tear reeve to imegihte One oppositeadeaot ate reld h.esk ue been pr-en etrough te PDI Iintatieto be ureeliable; teortore ndriemum nda is takes tor aihdisng coverage fortetfar sideaoftfe weld. Tce tteal stirated legrth equaels pproximntoly 21". The
.tlck-ealhi apptolrtrtty 2. l.re total estimatad code
.oneehge acviesed eas approxlrmately 38% for the UT and 100% for te PT exam.
Systxm leakage tkast (VT2) -esdvcted atthe concdusion of each outage to detect predere atof leakage, No leakage ha.
bees noted inff"area oftte w-ld.
15
Document Control Desk LRN-02-0255 Table II Relief Request S1-RR-CO1 Salem Unit 1 - 2nd Inservice Inspection Ten-Year NDE Exam Limitations 360500 2-3-1 13 10120/99 CVCS 3-CV-2156-1 Tee to Pipe C-F-I C5.21 49 PT UT 100%
IWC-2500-7 Theea*s ex'r tionseare perforated in October 1999I APTaid No 58%
UT exantinnaonr was performed peon the fee to pipe oriliguration art hno recordable indioations iden*ified. The UT exarsonaton ivas conducted using a 45-and 70-degree shear rave transducer, Te UT examenation eat perforied fromtrhe pipe
.d.
.Th exm er. a tirelted due to re teas
.OD cornfguration.
The e of a hsar wave einvesigate Ore oppoeite oad ate wid shwa lrr.-
been pcoven through the PDI iniarie W to be uoelianbl. reretnre minirn
-n creit taken for achieving coverage for ea far side of fre eld. The Intel eamanted wveallength e iesls approxirnrrfly 11 "*.The thkkneore is approximaely 0.451', The total esornated code coverage achieved wae approximuately 58% for fre UT and 100% for tre PT ecam. System leakage tseats (VT2)eameconrduced at tm condusion of eachr ouage to detect preenerme of leakage. No leakage bhe been noted rnit*isa-of the weli.
384000 2-1-1 08 4/28/89 S9 4-SJ-2113-19 Tee to Valve C-F-1 C5.21 41 PT UT 100%
IWC-2500-7 Thesexaeminasoea saarar perfored in April 1989, APT and UT No 77%
exear/rsen me, perfaeed,eparer atee to v olv configuration it to reordaeble inriceboers kidenelde The UT e..r.reirsto wans elwdcted using a 45-and 60-degee esearwaoe beridvoer The UT e eaisin
-ws perferead fram the pipe side. The eeam wel heated due to the tbe anrd Ortevalve's OD conrgunreoe No N
exarration waa able it be perforred from Ore tee aide betberi V -6'c lockwaice due s tore te' airer rmdua Thre *-of idassrear wan Itoi Jnesite*the heopstes idle of i wdale be. W-been poent hrough the PDI iniiativea o be rlaeble, therefore trenieas dt h edd taken for chieving nrae for the far e
ide of the weld. The total aendisted wavld length rreiswa approxistately 13W. The thicknesshis approierataelyp. T total est rlnated code coaerage aahieved "was amerxiwnayp 77% for the UT and 100% for the PT exam.
SyOtem leakage b ets (VT2) am conductfd at ter ooncuion of ec/h outage to detect presence of leakage. No leakage hes been noted/in Oes amra ofre walde 385020 2-3-1 13 10/20/99 SJ 3-SJ-2121-2 Pipe to Valve C-F-i C5.21 50 PT UT 100%
IWC-2500-7 These exemrrnar n vere performedintOctober 1999. APT and No 57%
UT exrrnation was peformed upon a
ea pipe to valve cordgiatoon wth no recordble irdicaions identfed. The 0T exaosri/at/on was conducted osing a 45-and 70-degree shear wave viatrdaoero The UT eoxariritob was perfotrned fromto p/pa side The seam was ir.ted dre In Ore vavies OD ooifiguraeon. The ume of earsear wave to Iviestigate Ore oppee/te side oa s
/weldi a/oI-e been o p-troh ght he PDI Initiative to be unreiablte: hreefore ainirmu cedit is taken for adie/ving coverage tforthe farn atofeh e ai The tetal eiambated ald le*gtht epqais approximatey f11'.
The O klomee is epproximetely 0.451' "Te total eabtted! code oevage sob/axed was approimnateiy 57% for the UT and 100% for the PT em.
tSye leakage teast (V02)ea. conducted at the conoel of each owd tage to detect presee e of leakage. No leakage has been noted In ise are of toe weld.
16
Document Control Desk LRN-02-0255 Table II Relief Request S1-RR-CO1 Salem Unit 1 - 2nd Inservice Inspection Ten-Year NDE Exam Limitations 385040 2-2-3 12 8/15197 SJ 3-SJ-2121-3RI Valve to Valve C-F-i C5.21 None Available PT UT 100%
IWC-2500-7 These examinataonswere performed in August 1997T APT No 0%
examination wae perforeed apse the valve en valve onfiguranon withn-r i
idable idicatonsidentified. No UT e. na..ebncs could be completed due to the valve-tbalve OD configursion that pessesed inadequatoe uface area from waich to v
onduct the eva-.
Th etal easwmtd weld dlergth equalspp.r.niniseMy 11 %The,uckesis aapproximately 0.451'. The total estimated code scverage achieved was approximately 0%9 for te UT and 100% for the PT exam Syam leakage reatse (VT2) a conductedO at the conduelmn of nach ouiib to detect presence of leakage. No leakage hbeen noted ineis area of the weld.
385060 2-2-3 12 10122197 SJ 3-SJ-2121-4R1 Valve to Valve C-F-i C5.21 None Available PT UT 100%
IWG-2500-7 Thesaenaidrianns were performed in July 1997. A PT No 0%
exarinatone was perfermed upon the clve--uslve conflguration it recoratbleo Indica*in sdentosid inilislly, after mninor surface piepareateonre componentp se re-eaereined and found to be acceptoble. No UT exaarnitboneacould be coerplered duebto Oe valve-tba-Ocve 00 configurationt t pssesnad lsdeqrate suerace are Nr o
tlw to coeduct the ea.se l The total eserade weld leei eqls o
epproximetely 11'.The
- tckneais alpproxieately 0.451'. The total eeareted code coverage achved wae iimaer tely b for thee UT and 1O%
for the PTe.a.m. System leakage rMe (VT2) am conducted at the cno -
Fsc at eh outage en detect presence of leskage. No leakage has beev noted in this area ofrte eld.
222400 2-2-3 12 11/3/95 MS 34-MS-2131-1 Pipe to Pipe C-F-2 C5.51 None Available MT UT 100%
0WC-2500-7 Thesenexarninhaon wereperformedintNovemberl99S. A MT Yes-MEB 3-1 0%
and UT examrination was atterypd. The UT unabe to be completed due to thea pipe to pipw cofurataon due to pernsaseelyInsaltald 0-r-1eal ementns Th.e Wll esimrated weld length equrle sapproximately 11 TIr VThe clovess is approximietly 0.451.The total esteimated code coverage adiivedweas approximately 0% foivthe UT and 100% fortheN MT eam. System leakage tlush (VT2) ar conducteda at the conudeuson of each outage bdtoedact ppesence of lakage. No leakage ha been noted in "Od area of weld.
224100 2-2-3 12 11/7/95 MS 34-MS-2131-2 Pipe to Valve C-F-2 C5.51 53 MT UT 70%
IWC-2500-7 Tlhee examinatonsawere peomed in November 199. AMT Yes-MEB 3-1 19%
- exainse one ue performed upontOe pipe-to-valve confieua one with no recordable idincons idenefied. No UTexaminatbon ume ablebtoabe codoncted due to then Oebutral steel located adjacent to the weld are reich prevened physicalaocol-en weld ton llo tnfor canning. The MT exam wasalso tiad due en pareaneeedy crablled x
tnccal aleteredn and uime ftire rheathing.
These rews were inacosseb.e for MT due to the framn e rt e side n/
of the weld did rot arllow uderaete scones bor ts MT equipmentetoa cointe te axam rface.
Ca tidea oe were given for te perfeomcee ofa PT exam hoerver Ore ex asemlntion holw e vrowrfa coL eanot be adequately deatedtWsupportrexaminraion due to limited physical acoess. The totalb estiaed weld length equals approximately 1
00 W. The thOluna, Is approximately 214p
.The botable.ati ted coda Cove'aae eaved sae pproxiirteley 10%
birts
System leakage tests (VT2) are ionduced arthe concleuion of
-a ounage to detect pe of leakage, No leakage hae been noted in th aena/ of te weld.
17
Document Control Desk LRN-02-0255 Table II Relief Request S1-RR-CO1 Salem Unit 1 - 2nd Inservice Inspection Ten-Year NDE Exam Limitations 224200 2-2-3 12 1113/95 Ms 34-MS-2121-1 Pipe to Pipe C-F-2 C551 54 MT UT 18%
IWC-2500-7 Theo examimaonsawere performed in November 1995. A MT Yes-MEB 3-1 0%
esamrrtaon ens performed on the pip-to-vale configuraton th no remoordabe indications Idenaed. No UT examination was abs to be.o.duct*d due tothe sttvohal steal lo.ated adjaent to the weld ama shiho preventad physical aasoto weld to atlow for naronge TieN MT exam, was also liited ue to permmeasey installed sto toral elerent. These areas were inamsasile for MT due to the frames on ither side of tre weld did not allow adeq"at
-e f for the MT Oqpimentwto contact tfe exam surf-aCos idesratnos were ghoen tor fte pertormance ofta PT exam however the exarndatisn howeer ftie sudace oid not be adequately inaned to support exomination due to limited physloal am ss The total estimated weld length esqualsapproximatsly 106W* The taokness is approxioately 2W. The total esndmatad sods soverage achieved wasa pproxiatelyD 0% for ts UT and 18% for ehe MT exam.
System leakage taste (r2) are contaed st e t
oencl.to-n of each outos" to datect presanm of leakage. No leakage has beena oted In I.rea of the weld.
225800 2-2-3 12 11/2/95 Ms 34-MS-2111-1 Pipe to Pipe C-F-2 05.51 55 MT UT 50%
IWC-2500-7 The-e exaninat.s wensw performed in Nosets1995. A MT Yes-MEB 3-1 0%
exarrmnaton was performed upen the pp-t-,-ate configuratgon wita no morrdable indiatonsr identied. No UT exaninabon was able to be conductadd due tothe structual steel located adjacent tots weld a-a winhs p-resd phypmial amass to weld to anow for emareng. These areas were inacceaiblef ho MT tdu to tfrs trerrms on estrer ids of t weld did not allow adequsats a
fss oe the MT espatent to contact the exam srfane.
Consederatons were given for the prtoenme,n ofa PT exam howseer the exaninetn however the tsufan could not be adequateiy claned to support e mnsineot due to limitedd physical amass The total esumated wld length esqals approxirmatelyi t0
" ma th.h rtknes ls approximately 2Wa.
Th total estimated sode covenge ahidved was approximttely 0%
tor tse UT and 50% horeta MT exam. System leakage tests (VT2) are mondouted at the oonclsisn of eans outage to deldct preemoe of leakage. No leakage has beene sted in tins area of the weld.
227500 2-2-32 12 1114/95 MS 34-MS-2111-2 Pipe to Valve C-F-2 C5.51 56 MT UT 50%
IWC-2500-7 These exoamnnebna weretperformed in Novemer 11. AMT Yes-MEB 3-1 58%
and UT exaarinsfon was performed opO te elbowto pipe configur*tion with o reoadabls irdindaone idened. The UT exarmnatien was ooediured usng ad45 -degree shear wave ransdos*cere maUT earniabon was pertonrmedfrom beth sida st fteweld. Th& exam was limited due to the perneently retalisd stos I elemena i
lotated adjancet to tse weld eat ntertfredwith canning area Th MTe.a..wean lmited due to ircemsnabiliy and an ability to plaet pe yoke in ontact wth ose aras Interfered by sýttanl steel located adjacentto tse fle weld amd a platfown aloamtd abeme ts weld. Conderoatas ware gientor thet petormanem of.a PT examr berwesats sxamination sram a ould not be adequately cleaned to support sxarirreto ne td to limited physial acmass. mT total steimated weld length equals apprnoximately 108 maThe Odckness is approxieately 14*.
Toe area unable to be exanined was appiroxrmately between8 6 3/4 and 22-114" domekle for UT and 81" to 27" docewe foh MT. mae total leegth of weld exammned ret MT was 43 and 54" he UT. The total entot ods soverageg adisved was approximately 58% oe r e UTaead 50% tor te MT examo System leakage teste TM) are m
ronructed atte sonclusisn of each sitage to detent presence of laskage. No leakage heas e noted in thi sta-ofrVe seId.
18
Document Control Desk LRN-02-0255 Table II Relief Request S1-RR-CO1 Salem Unit 1 - 2nd Inservice Inspection Ten-Year NDE Exam Limitations 230500 2-2-3 12 11/1195 MS 32-MS-2121-3 Pipe to Elbow C-F-2 C5.51 52 MT UT 87%
IWC-2500-7 Treseaeeansnra nsere pertcmnredinhNevemberl1995 A MT Yes-MEB 3-1 83%
andUTerarmmnatim n
aperormrnedupnthepe*Wto eibo confitiratwon iat i-recordatle indicatnons identied The UT exarrenabon wase onducted uing a45-degree shear weve transducr The UT exanmiation vis poseormed from both sides of ste wid Th. eeam r-aes imited between 6r -o-W due to pernemandy installed estrutral stee*i -Bar eupporte tat interfered wit h arsnng ard ne exare areas-The MT exem was looted due to Winae-eability sdan ability to piace Ohe yoke in contdct i0 teese areas intertened by stnuctral steel ocated adja-entto Orthe e weld ands. plaftoe elevated above Ore weld Conosderntinsereers given toforte perfonmance ofea PT exam trereer the exanrnintion surfac covldd not be adeq*atety Clased to support evamnonrv due to limited physical a s.
The total estmated weld legt "Ie.s pproimatey t1W. The hickness is approximately[2%*.
The total estimated code cverage achleved wras approximately 83% for the UT and 87%
tor te MT seam.
System leakage tests (VT2) are onducvted at the dcusion of each outage to detevt eserv etof leakage. No leakage has been noted Intesarme of the wald.
230600 2-2-3 12 11/7/95 MS 32-MS-2121-4 Elbowrto Pipe C-F-2 C5.51 51 MT UT 48%dI V
-2500-7 Thesexeanieabees reeperformed in N txmiert1995.
A MT Yes-MEB 3-1 81%
andoUT eeactnstona -performedeuponthepifpeotoelboew
-eeturgineeshr-n rnexrdable Indcstieo ldeetifed. The UT e.ae.n e se
-conducted usinog dO-dg-thear lee Ouneducer, The UIT ese.snse see pertorred tfrer bort sides f the b
eld The ee.m slimited between 7ir-toD-3O ctebres and 12 -3(rforto UT due to pU eaneely intalled strucural steel I Seam eWports withine10t t
of the sld and vitertesrin*t h Othe examres. The MT exam was limited de to ricaessabilty and an ability to place the yoke in act withthosee ereas rinrrteed by structuae l steel located adjacentto the One swld ands. platform locvated eab e n oweld.
Consrderaeons sets gven for te pederfmno eofta PT exammtre thener rt inerebnoerfaae rould not be edeteuxtsly deamnd to evepport exaninaton due to limted physical e ve
. The total estimatd weld length equals apomeitnetly n1r. The teickness is approximately 21W.
The tol estorrated code vemege eaeieved was approximately 81%tforeheUT and 48%tfor erMTtexam. System leakage taste (VT2) are vcnducted sts t
conclusion of each otagetoe doeatt sero eof leakage No eakage has been noted intl area of ts weld 231800 2-2-3 12 10/31/95 MS 32-MS-2111-4 Elbow to Pipe C-F-2 C5.51 42 (N.esketc or phototo&
IWC-2500-7 Theseexaemrnedto swomperereroed int rvnetre19
.A MT Yes-MEMS3-1 restoetee n
rxhft) 81%
and UT exesrnnaoe Was performed uothes iye to elbeW onfieratbone rth no recrdabhsindeationdisa blevtd. The UT examination*-te ondicted ueing a 45degree eh eawve etreder., Te UT examInation was performed bfrom bohtdes ef tte weld. The exam as mieted between 7r-to -Wr vlovksie° and 12-30 for UT due to pemanerntly installed stofuc al steel I-Beam rppe whip restaint being located sltin Inteof ts sowld and interfoing wiet th sexem ea. The total stiratedr*we ldegth"ies lpp-reiWly10r.
1CO The
.tickrees I epp-reimatley 2W'. The total estmatsLITe Ieam ede cover"ge achieved wasa pproximately 61% and 1O% for thet MT exam. Sytem leakage atst (VT2) am cnducted setsd idi etof each eutage etoetentprinens eofleaksge" No leakge has been noted in teI ens-of the ld.
19
Document Control Desk LRN-02-0255 Table II Relief Request S1-RR-CO1 Salem Unit I - 2nd Inservice Inspection Ten-Year NDE Exam Limitations 20 242000 2-2-1 10 5119192 MS 8-MS-2141-1 Weldolet to Elbow C-F-2 C5.51 60 MT UT 68%
IWC-2500-7 Thes-exato Sow perfore di n May 1992 A UT and MT No 100%
examinat0on was performad upon the weldoletoto elbow pipe weld winhno recordable indc*atorn identified
.Te exam was limited due to Windequata access resultng fr omadjacent suoports structural steel andt 0tecomponents$
onfiguration.
Considenboro weoregiven for PT examination however srface of One 0arbnM steet could not be adepuatoly yleared to supportui*toe cenli 00needs for PT examination. The total etmlti o0d weld length equals approximately 27. No MT examination could be perfoomnd bhoenr 24" to 5.5" co000e.
Ap*roximately 18.5-was fully exanined. The total estmatod code overageoachieved wao apptroximtely6 8%. 100% 0of0h code required coverage wa0. Ne-Wed for tOn UT...
w0th0no recordable ndicatons ilentified. Systm0 leakage t 0estsr2) ar ooedted at the 000nlus0on of ta0h outage to detoot pree*ecee of leakage. No keokage has been noted in 04. owe of te weld.
243500 2-2-1 10 5/19/92 MS 8-MS-2124-2 Elbow to Valve C-F-2 C5.51 61 MT UT 57%
IVVC-2500-7 TheseexaminatiSonswere performed in May 1992 A UTeand MT No 100%
0exaination was performed upon eo weld1eet to elbow pipe weld wt 0no reoodable indcation idertfed. The MT exam 0.as limited due to inadequate 0ccess resing from adjacent uopottos structul r
teel andOrte otponoot's cfiguratti n.
Contidertons weare given for PT examoontioe howeverhOre surface of fte awrbonesteel ould not he adepuately cleaned to support eofaoce 1aeniners neeads for PT exarinatfon. The total estimated weld leng1 t equals appfoxo mtelyV 2". No exeradonbw, asae04 b to he performed btween 2"-t.
Approximately 15.25"
-0 hidly examined. Th. total aestmated code o-erge wclaood 0a0 approximartely 57% 100% of the code rored coverage wa0c1reforethe UT exam with no recordable nldcations I; deetfitd Systemleakagematsr(VT2) -ne conducted at 018 coonluseon of each outage to detect presence of leakage No leakage hae been noted in 0000m of the weld.
229480 2-2-3 12 11/3/95 MS 32-MS-2131-4LU-Piping Longseam C-F-2 C5.52 51 MT UT 70%
IWC0-2500-7 These uexamnationsrwere performed in Noember1W. A Yes-MEB 3-1 0
100%
WoTrd UT examination was perormed upon w pipe weld with tO renordoble kdxisonsoI ldentled. The exam was limited due to Inadequate oacess resulting from adjacent supportsostructural steel 04nd *ornpooneef 0onrfguration. Tre total estimoted "wld dt05 eqouls approximately 2". Approxiateolyt 5" eed hone been examined h-wever de to tVa Interferene caused by ft whip restraint only 3."weeas fully examined. The total estimated code ovet ac hieved wam0approxlmately 65%.
PSEG Nuclear had Invoked Code Case N-524 pertaining to piping longeao tand only Itemected o*t enam djacoent to the circ ferent l weld with no Inicosno rated, System leakage 1ests (VT2) are oaucttdatd tt heconclusion of each outage to detot presentsofleakage. No leakage has been noted 100f eeof the weld.
Document Control Desk LRN-02-0255 Table II Relief Request S1-RR-CO1 Salem Unit 1 - 2nd Inservice Inspection Ten-Year NDE Exam Limitations 231720 2-2-3 12 11/3/95 MS 32-MS-2131-3LD-i Piping Longseam C-F-2 C5.52 62 MT IUT 65%
IWC-2500-7 Tbhese examinatirons re petonmed in November 1955 A Yes-MEB 3-1 100%
MTand UT examination w-o pe n upon the pip. weld wth no recordable indicatiov Idenified The exam was limited due to inadequate accessresulting from adjacent supports stractooal steel and the corponaent configuration. The total estiated old thickneas equals approxireately r2 Approximately 5' should have been exanmned honeever due to whe Interfeuencsm used by Ore whip teefint only 3.5-was tlly examined. The total estimated code coverage achieved was0 ppoximately 70%.
PSEG Nuclear had Invoked Code Case N-524 pertaining to piping longeims and ogy inspected Stat area adjacent to the erCt-erecntal weld woith n indications noted. System leakage teestm (02) am cotducted at ete conclusion of each outage to detect poeseoc ofleakage. No leakage hbs been noted in this area of the weld 231760 2-2-3 12 11114195 MS 32-MS-2111-4LU-I Piping Longseam C-F-2 C5.52 57 MT UT 0%
IWC-2500-7 Thesexesanmsiooawe-speoennedinNoavwbent N. A Yes-MEB 3-1 100%
MTand 0T es.irieons-s pedroned upont he pipe weld with no re-oedsbindicatosemi dentified. The exam w limited due to indedste ssa- -resuletng feen sa.dsent supporeta ssuctsal steel snd Ore components configunhon, The total estirmated wld thilewnes equals sipi*nnrsatey d2"eApoxirnstely
" should have been examined however due to the interdeonce omused by the whip re eintonly a egiular direci oof rageLabion was
=ed teerefore no credit nould be taken without having conducted Ore exam in new diector,. No credit co*ld be fully taken due to Ste whip we lint comtlelely coverng the weld and not allweing. The total etinated code coverage achieved wme approximately 0%. PSEG Nuclear had en-oked Code CaseSN 524 pertairnig to piping longeans and only incpected Stat area adjacent to Ste ernmfewntial weld wth no indice*etis noted by scneing on top of the weld and accessible surfaces adjacent to te weld.
System leakage tests (V02) ame oodulcu*d atl teocdeusIon of each outage to detect presence of leakage. No leakage has been noted Inthi s-a of thew-ld 21
Document Control Desk LRN 0255 II1. Appendix A Sketch No Pages 1
1-5 2
1-5 3
1-4 4
1-3 5
1 6
1 7
1 8
1-5 9
1-2 10 1-2 11 1
12 1
13 1
14 1
15 1
16 1
17 1
18 1
19 1-13 20 1-2 21 1
22 1
23 1
24 1
25 1-10 26 1
27 1
28 1-5 & 5A 29 1-8 30 1-4 & 4A 31 1-2 32 1-3 Sketch No Pages 33 1
34 1-4 35 1-5 36 1-4 37 1-5 38 1
39 1
40 1
41 1-2 42 1
43 1
44 1-2 45 1-2 46 1-2 47 1-2 48 1-2 49 1-2 50 1-2 51 1-4 52 1-3 53 1-2 54 1-2 55 1-2 56 1-2 57 1
58 1
59 1
60 1-2 61 1-2 62 1-2
31 WAI do
'Zi
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1-RPV-1046C 02 1-RPV-10461 RPV-1046D
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SALEM-1 APPENDIX VIII EXAMINATION COVERAGE FOR WELD:
LOWER SHELL-TO-BOTTOM HEAD SALEM WELD NO.:
1-RPV-10042 SCAN PLAN DRAWING NO.: 6007156E-01 AGGREGATE COVERAGE OBTAINED:
W13 56%
Zone Coverage Obtained Weld: 56%
Adjacent Base Metal: 56%
Examination Volume Definition Weld Length:
543.5 in.
Area Measurement Volume Calculation Weld: Near Surface 0.88 sq. in.
Weld: Near Surface 478.3 cu. in.
Weld: Balance of Volume 4.94 sq. in.
Weld: Balance of Volume 2684.9 cu. in.
Base Metal: Near Surface 7.86 sq. in.
Base Metal: Near Surface 4271.9 cu. in.
Base Metal: Balance of Volume 38.24 sq. in.
Base Metal: Balance of Volume 20783.4 cu. in.
Examination Coverage Calculations WELD Weld (Near Surface Region B-C-H-I)
Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry #
(deg.)
Direction (sq. in.)
(in.)
(cu. in.)
(cu. in.)
Examined 1
70L 11 0.88 307.00 270.2 270.2 100%
BETWEEN LUGS 2
70L 12 0.88 307.00 270.2 270.2 100%
BETWEEN LUGS 3
70L 3
0.88 307.00 270.2 270.2 100%
BETWEEN LUGS 4
70L 4
0.88 307.00 270.2 270.2 100%
BETWEEN LUGS 5
70L 11 0.00 236.50 0.0 208.1 0%
UNDER LUGS 6
70L 12 0.00 236.50 0.0 208.1 0%
UNDER LUGS 7
70L 3
0.00 236.50 0.0 208.1 0%
UNDER LUGS 8
70L 4
0.00 236.50 0.0 208.1 0%
UNDER LUGS Totals:
1080.6 1913.1 56%
Weld ( Balance of Volume Region G-H-l-J)
Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry #
(deg.)
Direction (sq. in.)
(in.)
(cu. in.)
(cu. in.)
Examined 1
45L 11 4.94 307.00 1516.6 1516.6 100%
BETWEEN LUGS 2
45L 12 4.94 307.00 1516.6 1516.6 100%
BETWEEN LUGS 3
45L 3
4.94 307.00 1516.6 1516.6 100%
BETWEEN LUGS 4
45L 4
4.94 307.00 1516.6 1516.6 100%
BETWEEN LUGS 5
45S 11 4.94 307.00 1516.6 1516.6 100%
BETWEEN LUGS 6
45S 12 4.94 307.00 1516.6 1516.6 100%
BETWEEN LUGS 7
45S 3
4.94 307.00 1516.6 1516.6 100%
BETWEEN LUGS 8
45S 4
4.94 307.00 1516.6 1516.6 100%
BETWEEN LUGS 9
45L 11 0.00 236.50 0.0 1168.3 0%
UNDER LUGS 10 45L 12 0.00 236.50 0.0 1168.3 0%
UNDER LUGS 11 45L 3
0.00 236.50 0.0 1168.3 0%
UNDER LUGS 12 45L 4
0.00 236.50 0.0 1168.3 0%
UNDER LUGS 13 45S 11 0.00 236.50 0.0 1168.3 0%
UNDER LUGS 14 45S 12 0.00 236.50 0.0 1168.3 0%
UNDER LUGS 15 45S 3
0.00 236.50 0.0 1168.3 0%
UNDER LUGS 16 45S 4
0.00 236.50 0.0 1168.3 0%
UNDER LUGS Totals:
12132.6 21479.1 56%
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BASE METAL W-13 SHEET-2 Adjacent Base Metal (Near Surface Region A-B-I-L and C-D-E-H)
Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry #
(deg.)
Direction (sq. in.)
(in.)
(cu. in.)
(cu. in.)
Examined 1
70L 11 7.86 307.00 2413.0 2413.0 100%
BETWEEN LUGS 2
70L 3
7.86 307.00 2413.0 2413.0 100%
BETWEEN LUGS 3
70L 4
7.86 307.00 2413.0 2413.0 100%
BETWEEN LUGS 4
70L 11 0.00 236.50 0.0 1858.9 0%
UNDER LUGS 5
70L 3
0.00 236.50 0.0 1858.9 0%
UNDER LUGS 6
70L 4
0.00 236.50 0.0 1858.9 0%
UNDER LUGS Totals:
7239.1 12815.7 56%
Adjacent Base Metal (Balance of Volume Region E-F-G-H and I-J-K-L)
Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry #
(deg.)
Direction (sq. in.)
(in.)
(cu. in.)
(cu. in.)
Examined 1
45L 11 38.24 307.00 11739.7 11739.7 100%
BETWEEN LUGS 2
45L 3
38.24 307.00 11739.7 11739.7 100%
BETWEEN LUGS 3
45L 4
38.24 307.00 11739.7 11739.7 100%
BETWEEN LUGS 4
45S 11 38.24 307.00 11739.7 11739.7 100%
BETWEEN LUGS 5
45S 3
38.24 307.00 11739.7 11739.7 100%
BETWEEN LUGS 6
45S 4
38.24 307.00 11739.7 11739.7 100%
BETWEEN LUGS 7
45L 11 0.00 236.50 0.0 9043.8 0%
UNDER LUGS 8
45L 3
0.00 236.50 0.0 9043.8 0%
UNDER LUGS 9
45L 4
0.00 236.50 0.0 9043.8 0%
UNDER LUGS 10 45S 11 0.00 236.50 0.0 9043.8 0%
UNDER LUGS 11 45S 3
0.00 236.50 0.0 9043.8 0%
UNDER LUGS 12 45S 4
0.00 236.50 0.0 9043.8 0%
UNDER LUGS Totals:
70438.1 124700.6 56%
NOTE: UNDER LUGS WERE NOT SCANNED DUE TO STAINLESS STEEL INSERT NOT DEPICTED ON CUSTOMER DRAWINGS SUPPLIED TO FTI-ANP.
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SALEM-1 APPENDIX VIII EXAMINATION COVERAGE FOR WELD:
W02 UPPER LONG SEAM @ 7 DEGREES SALEM-1 WELD NO.:
1-RPV-1042B SCAN PLAN DRAWING NO.: 6007158E-01 AGGREGATE COVERAGE OBTAINED:
66%
Zone Coverage Obtained Weld: 66%
Adjacent Base Metal: 66%
Examination Volume Definition Weld Length:
67.41 in.
Area Measurement Volume Calculation Weld: Near Surface 1.60 sq. in.
Weld: Near Surface 107.9 cu. in.
Weld: Balance of Volume 12.72 sq. in.
Weld: Balance of Volume 857.5 cu. in.
Base Metal: Near Surface 10.85 sq. in.
Base Metal: Near Surface 731.4 cu. in.
Base Metal: Balance of Volume 113.97 sq. in.
Base Metal: Balance of Volume 7682.7 cu. in.
Examination Coverage Calculations WELD Weld ( Near Surface Region B-C-H-I)
Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry #
(deg.)
Direction (sq. in.)
(in.)
(cu. in.)
(cu. in.)
Examined 1
70L 1
1.60 44.80 71.7 71.7 100%
2 70L 1
0.00 22.62 0.0 36.2 0%
3 70L 2
1.60 44.80 71.7 71.7 100%
4 70L 2
0.00 22.62 0.0 36.2 0%
5 70L 3
1.60 44.80 71.7 71.7 100%
6 70L 3
0.00 22.62 0.0 36.2 0%
7 70L 4
1.60 44.80 71.7 71.7 100%
8 70L 4
0.00 22.62 0.0 36.2 0%
Totals:
286.7 431.5 66%
Weld (Balance of Volume Region G-H-t.J)
Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry 8 (deg.)
Direction (sq. in.)
(in.)
(cu. in.)
(cu. in.) Examined 1
45L 1
12.72 44.80 569.9 569.9 100%
2 45L 1
0.00 22.62 0.0 287.7 0%
3 45L 2
12.72 44.80 569.9 569.9 100%
4 45L 2
0.00 22.62 0.0 287.7 0%
5 45L 3
12.72 44.80 569.9 569.9 100%
6 45L 3
0.00 22.62 0.0 287.7 0%
7 45L 4
12.72 44.80 569.9 569.9 100%
8 45L 4
0.00 22.62 0.0 287.7 0%
9 45S 1
12.72 44.80 569.9 569.9 100%
10 45S 1
0.00 22.62 0.0 287.7 0%
11 45S 2
12.72 44.60 569.9 569.9 100%
12 45S 2
0.00 22.62 0.0 287.7 0%
13 45S 3
12.72 44.80 569.9 569.9 100%
14 45S 3
0.00 22.62 0.0 287.7 0%
15 45S 4
12.72 44.80 569.9 569.9 100%
16 45S 4
0.00 22.62 0.0 287.7 0%
Totals:
4558.9 6860.7 66%
IBASE METAL Adjacent Base Metal (Near Surface Region A-BF--L and C-D-E-H)
Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry #
(deg.)
Direction (sq. in.)
(in.)
(cu. in.)
(cu. in.) Examined 1
70L 1
10.95 44.80 486.1 4865 1 100%
2 70L 1
0.00 22.62 0.0 245.4 0%
3 74L 3
10.95 44.80 486.1 486.1 100%
4 74L 3
0.00 22.62 0.0 245.4 0%
5 74L 4
10.85 44.80 486.1 486.1 100%
6 70L 4
0.00 22.62 0.0 245.4 0%
Totals.
1458.2 2194.5 66%
Adjacent Base Metal (Balance of Volume Region E-F-G-H and I-J-K-L)
Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent iEntry #
(deg.)
Direction (sq. in.)
(in.)
(cu. in.)
(cu. in.) Examined 1
45L 1
113.97 44.80 5105.9 5105.9 100%
2 45L 1
0.00 22.82 0.0 2578.0 0%
3 45L 3
113.97 44.80 5105.9 5105.9 100%
4 45L 3
0.00 22.62 0.0 2578.0 0%
5 45L 4
113.97 44.80 5105.9 5105.9 100%
6 45L 4
0.00 22.62 0.0 2578.0 0%
7 45S 1
113.97 44.80 5105.9 5105.9 100%
8 45S 1
0.00 22.62 0.0 2578.0 0%
9 45S 3
113.97 44.80 5105.9 5105.9 100%
10 45S 3
0.00 22.62 0.0 2578.0 0%
11 45S 4
113.97 44.80 5105.9 5105.9 100%
12 45S 4
0.00 22.62 0.0 2578.0 0%
Totals:
30635.1 46103.1 66%
k3
SALEM-1 APPENDIX VIII EXAMINATION COVERAGE FOR WELD:
BOTTOM HEAD (CIRC)
SALEM WELD NO.:
1-RPV-4043 SCAN PLAN DRAWING NO.: 6007157E-01 AGGREGATE COVERAGE OBTAINED:
W14 14%
Zone Coverage Obtained Weld: 12%
Adjacent Base Metal: 15%
Examination Volume Definition Weld Length:
424.3 in.
Area Measurement Volume Calculation Weld: Near Surface 0.99 sq. in.
Weld: Near Surface 420.1 cu. in.
Weld: Balance of Volume 4.84 sq. in.
Weld: Balance of Volume 2053.6 cu. in.
Base Metal: Near Surface 5.90 sq. in.
Base Metal: Near Surface 2503.4 cu. in.
Base Metal: Balance of Volume 25.48 sq. in.
Base Metal: Balance of Volume 10811.2 cu. in.
I Examination Coverage Calculations WELD Weld ( Near Surface Region B-C-H-I)
Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry #
(deg.)
Direction (sq. in.)
(in.)
(cu. in.)
(cu. in.)
Examined 1
70L 11 0.99 60.11 59.5 59.5 100%
2 70L 11 0.00 364.19 0.0 360.5 0%
3 70L 12 0.99 23.57 23.3 23.3 100%
4 70L 12 0.00 400.73 0.0 396.7 0%
5 70L 3
0.99 63.65 63.0 63.0 100%
6 70L 3
0.00 360.65 0.0 357.0 0%
7 70L 4
0.99 63.65 63.0 63.0 100%
8 70L 4
0.00 360.65 0.0 357.0 0%
Totals:
208.9 1680.2 12%
Weld ( Balance of Volume Region G-H-I-J)
Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry #
(deg.)
Direction (sq. in.)
(in.)
(cu. in.)
(cu. in.)
Examined 1
45L 11 4.84 60.11 290.9 290.9 100%
2 45L 11 0.00 364.19 0.0 1762.7 0%
3 45S 11 4.84 60.11 290.9 290.9 100%
4 45S 11 0.00 364.19 0.0 1762.7 0%
5 45L 12 4.84 23.57 114.1 114.1 100%
6 45L 12 0.00 400.73 0.0 1939.5 0%
7 45S 12 4.84 23.57 114.1 114.1 100%
8 45S 12 0.00 400.73 0.0 1939.5 0%
9 45L 3
4.84 63.65 308.1 308.1 100%
10 45L 3
0.00 360.65 0.0 1745.5 0%
11 45S 3
4.84 63.65 308.1 308.1 100%
12 45S 3
0.00 360.65 0.0 1745.5 0%
13 45L 4
4.84 63.65 308.1 308.1 100%
14 45L 4
0.00 360.65 0.0 1745.5 0%
15 45S 4
4.84 63.65 308.1 308.1 100%
16 45S 4
0.00 360.65 0.0 1745.5 0%
Totals:
2042.3 16428.9 12%
1134 (
BASE METAL W-14 SHEET 2 "Adjacent Base Metal (Near Surface Region A-B-l-L and C-D-E-H)
Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry #
(deg.)
Direction (sq. in.)
(in.)
(cu. in.)
(cu. in.)
Examined I
70L 11 5.90 60.11 354.6 354.6 100%
2 70L 11 0.00 364.19 0.0 2148:7 0%
3 70L 3
5.90 63.65 375.5 375.5 100%
4 70L 3
0.00 360.65 0.0 2127.8 0%
5 70L 4
5.90 63.65 375.5 375.5 100%
6 70L 4
0.00 360.65 0.0 2127.8 0%
Totals:
1105.7 7510.1 15%
Adjacent Base Metal (Balance of Volume Region E-F-G-H and I-J-K-L)
Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry #
(deg.)
Direction (sq. in.)
(in.)
(cu. in.)
(cu. in.)
Examined 1
45L 11 25.48 60.11 1531.6 1531.6 100%
2 45L 11 0.00 364.19 0.0 9279.6 0%
3 45S 11 25.48 60.11 1531.6 1531.6 100%
4 45S 11 0.00 364.19 0.0 9279.6 0%
5 45L 3
25.48 63.65 1621.8 1621.8 100%
6 45L 3
0.00 360.65 0.0 9189.4 0%
7 45S 3
25.48 63.65 1621.8 1621.8 100%
8 45S 3
0.00 360.65 0.0 9189.4 0%
9 45L 4
25.48 63.65 1621.8 1621.8 100%
10 45L 4
0.00 360.65 0.0 9189.4 0%
11 45L 4
25.48 63.65 1621.8 1621.8 100%
12 45L 4
0.00 360.65 0.0 9189.4 0%
Totals:
9550.4 64867.0 15%
SALEM-1 APPENDIX VIII EXAMINATION COVERAGE FOR WELD:
W35 MERIDIONAL @ 270 DEGREES SALEM-1 WELD NO.:
1-RPV-1043A SCAN PLAN DRAWING NO.: 6007161E-01 AGGREGATE COVERAGE OBTAINED:
69%
Zone Coverage Obtained Weld: 59%
Adjacent oase Metal: 59%
Examination Volume Definition Weld Length:
64S5 in.
Area Measurement Volume Calculaton Weld: Near Surface 1.68 sq. in.
Weld: Near Surface 108.4 cu. in.
Weld: Balance of Volume 6.02 sq. in.
Weld: Balance of Volume 388.3 cu. in.
Base Metal: Near Surface 5.43 sq. in.
Base Metal: Near Surface 350.2 cu. in.
Base Metal: Balance of Volume 24.67 sq. in.
Base Metal: Balance of Volume 1591.2 cu. in.
SExamination Coveragle CalculatIons WELD Weld ( Near Surface Region B-C-H-I)
Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent
,Entry #
(degl.)
Direction (sq. in.)
(in.)
(cu. in.&
(-. gL. Examined 1
70L 11 1.68 38.06 63.9 63.9 100%
2 70L 11 0.00 26.44 0.0 44.4 0%
3 70L 12 1.68 38.06 63.9 63.9 100%
4 70L 12 0.00 26.44 0.0 444 0%
5 70L 3
1.68 38.06 63.9 63.9 100%
6 70L 3
0,00 26.44 0.0 44.4 0%
7 70L 4
1.68 38.06 63-9 63.9 100%
8 70L 4
0.00 26.44 0.0 "A.
0%
Totals:
255.6 433ý4 59%
Weld (Balance of Volume Region G-H-1-J)
Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entn#
(deg.)
Direction (sq. in.)
(in.)
(cu. in.)
(cu. in.)
Examined 1
45L 11 6.02 38.06 229.1 229.1 100%
2 45L 11 0.00 26.44 0.0 159.2 0%
3 45L 12 6.02 38.06 229.1 229.1 100%
4 45L 12 0.00 26.44 0.0 159.2 0%
5 45L 3
6.02 38.06 229.1 229.1 100%
6 45L 3
0.00 26.44 0.0 159.2 0%
7 45L 4
6.02 38.06 229.1 229.1 100%
8 45L 4
0.00 26.44 0.0 159.2 0%
9 451 11 6.02 38.06 229.1 229.1 100%
10 45S 11 0.00 26.44 0.0 159.2 0%
11 45S 12 6.02 38.06 229.1 229.1 100%
12 45S 12 0.00 26.44 0.0 159.2 0%
13 45S 3
6.02 38.06 229.1 229.1 100%
14 45S 3
0.00 26.44 0.0 159.2 0%
15 45S 4
6.02 38.06 229.1 229.1 100%
16 45S 4
0.00 26.44 0.0 159.2 0%
Totals:
1833.0 3106.3 59%
BASE METAL Adjacent Base Metal (Near Surface Region A-B-I-L and C-D-E-H)
Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Enty#
(deg.)
Direction (sq. in.)
(in.)
(cu. in.)
cu. in.)
Examined 1
70L 11 5.43 38.06 206.7 20657 100%
2 70L 11 0.00 26.44 0.0 143.6 0%
3 70L 3
5.43 38.06 206.7 206.7 100%
4 70L 3
O.00 26.44 0.0 143.6 0%
5 70L 4
5.43 38.06 206.7 206.7 100%
6 70L 4
0.00 26.44 0.0 143.6 0%
Totals:
620.0 1050.7 59%
Adjacent Base Metal (Balance of Volume Region E-F-G-H and I-J-K-L)
Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry #
(deg.)
Direction (sq. in.)
(in.)
(cu. in.)
(cu. in.)
Examined 1
45L 11 24.67 38.06 938.9 938.9 100%
2 45L 11 0.00 26.44 0.0 652.3 0%
3 45L 3
24.67 38.06 938.9 938.9 100%
4 45L 3
0.00 26.44 0.0 652.3 0%
5 45L 4
24.67 38.06 938.9 938.9 100%
6 45L 4
0.00 26.44 0.0 652.3 0%
7 45S 11 24.67 38.06 938.9 938.9 100%
8 45S 11 0.00 26.44 0.0 652.3 0%
9 45S 3
24.67 38.06 938.9 938.9 100%
10 45S 3
0.00 26.44 0.0 652.3 0%
11 45S 4
24.67 38.06 938.9 938.9 100%
12 45S 4
0.00 26.44 0.0 652.3 0%
Totals:
5633. 7 9547.3 59%
%'13
SALEM-I APPENDIX VIII EXAMINATION COVERAGE FOR WELD:
W36 MERIDIONAL @ 330 DEGREES SALEM-I WELD NO.:
1-RPV-1043B SCAN PLAN DRAWING NO.: 6007161E-01 AGGREGATE COVERAGE OBTAINED:
59%
Zone Coverage Obtained Weld: 59%
Adjacent B
ase Metal: 59%
Examination Volume Definition Weld Len euh: 64.5 in.
Area Measurement Volume calculation
/eld: Near Surface 1.68 sq. in.
Weld: Near surface 108.4 cu. in.
End: Balance of Volume 6.02 sq. in.
Weld: Balance of Volume 388.3 cu. in.
Bas2 Metal: Near Surface 5.43 sq. in.
Base Metal: Near Surface 35002 cu. in.
Base Metal: Balance of Volume 24.67 sq. in.
IBase Metal: Balance Of Volume 1591.2 cuJ. in.
SExamination Coveragle Calculations WELD Weld ( Near Surface Region B-C-H-1)
Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Et #
(deg.)
Direction (sq. in.)
(in.)
(cu. in.)
(cu. in,)
Examined 3
70L 11 1.68 38.06 63.9 63.9 100%
2 70L 11 0.00 26.44 0.0 44.4 0%
3 70L 12 1.68 38.06 63.9 63.9 100%
4 70L 12 0.00 26.44 0.0 44.4 0%
5 70L 3
1.68 38.06 63.9 63.9 100%
6 70L 3
0.00 26.44 0.0 44.4 0%
7 70L 4
1.68 38.06 63.9 63.9 100%
8 70L 4
0.00 26.44 0.0 44.4 0%
Totals:
255 8 433.4 59%
Weld (Balance of Volume Region G-H-I-J)
Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Ent If#
(deg.)
Direction (sq. in.)
(in.)
(cu. in.)
(cu. in.)
Examined 1
45L 11 6.02 38.06 229.1 229.1 100%
2 45L 11 0.00 26.44 0.0 159.2 0%
3 45L 12 6.02 38.06 229.1 229.1 100%
4 45L 12 0.00 26.44 0.0 159.2 0%
5 45L 3
6.02 38.06 229.1 229.1 100%
6 45L 3
0.00 26.44 0.0 159.2 0%
7 45L 4
6.02 38.06 229.1 229.1 100%
8 45L 4
0.00 26.44 0.0 159.2 0%
9 45S 11 6.02 38.06 229.1 229.1 100%
10 45S 11 0.00 26.44 0.0 159.2 0%
11 45S 12 6.02 38.06 229.1 229.1 100%
12 45S 12 0.00 26.44 0.0 159.2 0%
13 45S 3
6.02 38.06 229.1 229.1 100%
14 45S 3
0.00 26.44 0.0 159.2 0%
15 45S 4
6.02 38.06 229.1 229.1 100%
16 45S 4
0.00 26.44 0.0 159.2 0%
Totals:
1833.0 3106.3 59%
BASE METAL Adjacent Base Metal (Near Surface Region A-B--L and C-D-E-H)
Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry #
(deg.)
Direction (sq. in.)
(in.)
(cu. in.)
(Cu. in.)
Examined 1
70L 11 5.43 38.06 206.7 206.7 100%
2 70L 11 0.00 26.44 0.0 143.6 0%
3 70L 3
5.43 38.06 206.7 206.7 100%
4 70L 3
0.00 26.44 0.0 143.6 0%
5 70L 4
5.43 38.06 206.7 206.7 100%
6 70L 4
0.00 26.44 0.0 143.6 0%
Totals:
620.0 1050.7 59%
Adjacent Base Metal (Balance of Volume Region E-F-G-H and I-J-K-L)
Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Ent (deg.
Direction (sq. in.)
(in.)
(Cu. in.)
'cu. in.
Examined 1
45L 11 24.67 38.06 93689 938.9 100%
2 45L 11 0.00 26.44 0.0 652.3 0%
3 45L 3
24.67 38.06 938.9 938.9 100%
4 45L 3
0.00 26.44 0.0 652.3 0%
5 45L 4
24.67 38.06 938.9 938.9 100%
6 45L 4
0.00 26.44 0.0 652.3 0%
7 45S 11 24.67 38.06 938.9 938.9 100%
8 45S 11 0.00 26.44 0.0 652.3 0%
9 45S 3
24.67 38.06 938.9 938.9 100%
I1D 45S 3
0.00 26.44 a0.0 652Z3 0%
I1I 45S 4
24.67 38.06 938.9 938.9 100%
12 45S 4
0.00 26.44 0.0 652.3 0%
Totals:
5633.7 9547.3 59%
2g/3
SALEM-1 APPENDIX VIII EXAMINATION COVERAGE FOR WELD:
W31 MERIDIONAL @ 30 DEGREES SALEM-1 WELD NO.:
l-RPV-1043C SCAN PLAN DRAWING NO.: 6007161E-01 AGGREGATE COVERAGE OBTAINED:
59%
Zone Coverage Obtained Wetd: 59%
Adjacent Base Metal: 59%
Examination Volume Definution Weld Len erSfa 64.5 in.
Area Measurement Volume Calculation Weld: Near Surface 1.68 sq. in.
Weld: Near Surface 108.4 cu. in.
iWend:
Balance of Volume 6.02 cq.
in.
Weld: Balance of Volume 388.3 cu. in.
2ase Metal: Near Surface 5.43 sq. in.
Base Metal: Near Surface 350.2 cu. in.
Base Metal: Balance of Volume 24.67 sq. in.
Base Metal: Balance of Volume 1591.2 cu. in.
Examination Coveragle Calculations IWELD Weld ( Near Surface Region B-C-H-I)
Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent lEntr,/#
(deg.)
Direction (sq. in.)
(in.)
(cu. in.q (cu-inj., Examined 1
70L 11 1.68 38.06 63.9 63.9 100%
2 70L 11 0.00 26.44 0.0 44.4 0%
3 70L 12 1.68 38.06 63.9 63.9 100%
4 70L 12 0.00 26.44 0.0 44.4 0%
5 70L 3
1.68 38.06 63.9 63.9 100%
6 70L 3
0.00 26.44 0.0 44.4 0%
7 70L 4
1.68 38.06 63.9 63.9 100%
a 70L 4
0.00 28.44 0.0 44.4 0%
Totals.
255.8 433.4 59%
Weld (Balance of Volume Region G-H-4-J)
Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent En(i#
(deg.)
Direction (sq. in.)
(in.)
(cu. in.)
(cu. in.)
Examined 1
45L 11 6502 38.06 229.1 229.1 100%
2 45L 11 0.00 26.44 0.0 159.2 0%
3 45L 12 6.02 38.06 229.1 229.1 100%
4 45L 12 0.00 26.44 0.0 159.2 0%
5 45L 3
6.02 38.06 229.1 229.1 100%
6 45L 3
0.00 26.44 0.0 159.2 0%
7 45L 4
6.02 38.06 229.1 229.1 100%
8 45L 4
0.00 26.44 0.0 159.2 0%
9 45S 11 6.02 38.06 229.1 229.1 100%
10 45S 11 0.00 26.44 0.0 159.2 0%
11 45S 12 6.02 38.06 229.1 229.1 100%
12 45S 12 0.00 26.44 0.0 159.2 0%
13 45S 3
6.02 38.06 229.1 229.1 100%
14 45S 3
0.00 26.44 0.0 159.2 0%
15 45S 4
6.02 38.06 229.1 229.1 100%
16 45S 4
0.00 26.44 0.0 159.2 0%
Totals.
1833.0 3106.3 59%
'BASE METAL Adjacent Base Metal (Near Surface Region AB-F--L and C-D-E-H)
Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry #
(deg.)
Direction (sq. in.)
(in.)
(cu. in.)
cu. in.)
Examined 1
70L 11 5.43 38.06 206.7 206.7 100%
2 70L 11 0.00 26.44 0.0 143.6 0%
3 70L 3
2.43 38.06 206.7 206.7 100%
4 70L 3
0.00 26.44 0.0 143.6 0%
5 70L 4
5.43 38.06 206.7 206.7 100%
6 70L 4
0.00 26.44 0.0 143.6 0%
Totals:
620.0 1050.7 59%
Adjacent Base Metal (Balance of Volume Region E-F-G-H and I-J-K-L)
Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry #
(deg.)
Direction (sq. in.)
(in.)
(cu. in.) i(cu. in.)
Examined 1
4AL 11 24.67 38.06 938.9 938.9 100%
2 45L 11 0.00 26.44 0.0 652.3 0%
3 45L 3
24.67 38.06 938.9 938.9 100%
4 45L 3
0.00 26.44 0.0 652.3 0%
5 45L 4
24.67 38.06 938.9 938.9 100%
6 45L 4
0.00 26.44 0.0 652.3 0%
7 45S 11 24.67 38.06 938.9 938.9 100%
8 45S ill 0.00 26.44 0.0 652.3 0%
9 45S 3
24.67 38.06 938.9 938.9 100%
10 45S 3
0.00 26.44 0.0 652.3 0%
11 45S 4
24.67 38.06 938.9 938.9 100%
12 45S 4
0.00 26.44 0.0 652.3 0%
Totals:
5633.7 9547.3 59%
8f/2
SALEM-1 APPENDIX VIII EXAMINATION COVERAGE FOR WELD:
W32 MERIDIONAL @ 90 DEGREES SALEM-1 WELD NO.:
1.RPV-1043D SCAN PLAN DRAWING NO.: 6007161E-01 AGGREGATE COVERAGE OBTAINED:
59%
Zone Coverage Obtained Weld: 59%
Adjacent Base Metal: 59%
Examination Volume Definition Weld Length:
64.5 in.
Area Measurement Volume Calculation Weld: Near Surface 1.68 sq. in.
Weld: Near Surface 108.4 cu. in.
Weld: Balance of Volume 6.02 sq. in.
Weld: Balance of Volume 388.3 cu. in.
Base Metal: Near Surface 5.43 sq. in.
Base Metal: Near Surface 350.2 cu. in.
Base Metal: Balance of Volume 24.67 sq. in.
Base Metal: Balance of Volume 1591.2 cu. in.
Examination Coverage Calculations WELD Weld (Near Surface Region B-C-H-I)
Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry #
(deg.)
Direction (sq. in.)
(in.)
(cu. in.,
(cu. in.)
Examined 1
70L 11 1.68 38.06 63.9 63.9 100%
2 70L 11 0.00 26.44 0.0 44.4 0%
3 70L 12 1.68 3806 63.9 63.9 100%
4 70L 12 0.00 26.44 0.0 44.4 0%
5 70L 3
1.68 38.06 63.9 63.9 100%
6 70L 3
0.00 26.44 0.0 44.4 0%
7 70L 4
1.68 38.06 63.9 63.9 100%
8 70L 4
0.00 26.44 0.0 44.4 0%
Totals:
255.8 433.4 59%
Weld (Balance of Volume Region G-H-I-J)
Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry#
(deg.)
Direction (sq. in.)
(in.)
(cu. in.)
(cu. in.)
Examined I
45L 11 6.02 38.06 229.1 229.1 100%
2 45L 11 0.00 26.44 0.0 159.2 0%
3 45L 12 6.02 38.06 2291 229.1 100%
4 45L 12 0.00 26.44 0.0 159.2 0%
5 45L 3
6.02 38.06 229.1 229.1 100%
6 45L 3
0.00 26.44 0.0 159.2 0%
7 45L 4
6.02 38.06 229.1 229.1 100%
8 45L 4
0.00 26.44 0.0 159.2 0%
9 45S 11 6.02 38.06 229.1 229.1 100%
10 45S 11 0.00 26.44 0.0 159.2 0%
11 45S 12 6.02 38,06 229.1 229.1 100%
12 45S 12 0.00 26.44 0.0 159.2 0%
13 45S 3
6.02 38.06 229.1 229.1 100%
14 45S 3
0.00 26.44 0.0 159.2 0%
15 45S 4
6.02 38.06 229.1 229.1 100%
16 45S 4
0.00 26.44 0.0 159.2 0%
Totals:
1833.0 3106.3 59%
BASE METAL Adjacent Base Metal (Near Surface Region A-B-4-L and C-D-E-H)
Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry #
(deg.)
Direction (sq. in.)
(in.)
(cu. in.)
(cu. in.)
Examined 1
70L 11 5.43 38.06 206.7 206.7 100%
2 70L 11 0.00 26.44 0.0 143.6 0%
3 70L 3
543 38.06 206.7 206.7 100%
4 70L 3
0.00 26.44 0.0 143.6 0%
5 70L 4
5.43 38.06 206.7 206.7 100%
6 70L 4
0.00 26.44 0.0 143.6 0%
Totals:
620.0 1050 7 59%
Adjacent Base Metal (Balance of Volume Region E-F-G-H and I-J-K-L)
Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry #
(deg.)
Direction (sq. in.)
(in.)
(cu. in.)
(cu. in.)
Examined 1
45L 11 24.67 38.06 938.9 938.9 100%
2 45L 11 0.00 26.44 0.0 652.3 0%
3 45L 3
24.67 38.06 938.9 938.9 100%
4 45L 3
0.00 26.44 0.0 652.3 0%
5 45L 4
24.67 38.06 938.9 938.9 100%
6 45L 4
0.00 26.44 0.0 652.3 0%
7 45S 11 24.67 38.06 938.9 938.9 100%
8 45S 11 0.00 26.44 0.0 652.3 0%
9 45S 3
24.67 38.06 938.9 938.9 100%
10 45S 3
0.00 26.44 0.0 652.3 0%
11 45S 4
24.67 38.06 938.9 93B.9 100%
12 45S 4
0.00 26.4" 0.0 652.3 0%
Totals:
5633.7 9547.3 59%
$XdcL /'
jyI
SALEM-1 APPENDIX VIII EXAMINATION COVERAGE FOR WELD:
W33 MERIDIONAL @ 150 DEGREES SALEM-1 WELD NO.:
1-RPV-1043E SCAN PLAN DRAWING NO.: 6007161E-01 AGGREGATE COVERAGE OBTAINED:
59%
Zone Coverage Obtainea Weld: 59%
Adjacent Base Meta 38 59%
Examination Volume Definition Weld Length:
64.5 in.
Area Measurement Volume Calculatin Weld: Near Surface 1.68 sq. in.
WVeld: Near Surface 108.4 cuJ. in.
W/eld: Balance of Volume 6.02 sq. in, Weld: Balance of Volume 388.3 cu. in.
Base Metal: Near Surface 5.43 sq. in.
Base Metal: Near Surface 350.2 cu. in.
Base Metal: Balance of Volume 24.67 sq. in.
Base Metal: Balance of Volume 1591.2 cu. in.
Examination Coverage Calculations WELD Weld (Near Surface Region B-C-H-I)
Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry #
(deg)
Direction (sq. in.)
(in.)
(cu. in.)
(cu. in.)
Examined 1
70L 11 1.68 38.06 63.9 63.9 100%
2 70L 11 0.00 26.44 0.0 44.4 0%
3 70L 12 1.68 38.06 63.9 63.9 100%
4 70L 12 0.00 26.44 0.0 44,4 0%
5 70L 3
1.68 38.06 63.9 63.9 100%
6 70L 3
0.00 26.44 0.0 44.4 0%
7 70L 4
1.68 38.06 63.9 63.9 100%
8 70L 4
0.00 26.44 0.0 44.4 0%
Totals:
255.8 433.4 59%
Weld (Balance of Volume Region G-H-4-J)
Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry #
(deg).
Direction (sq. in.)
(in.)
(cu. in (cu. in.)
Examined 1
45L 11 6.02 38.06 229.1 229.1 100%
2 45L 11 0.00 26.44 0.0 159.2 0%
3 45L 12 6.02 38.06 229.1 229.1 100%
4 45L 12 0.00 26.44 0.0 159.2 0%
5 45L 3
6.02 38.06 229.1 229.1 100%
6 45L 3
0.00 26.44 0.0 159.2 0%
7 45L 4
6.02 38.06 229.1 229.1 100%
8 45L 4
0,00 26.44 0.0 159.2 0%
9 45S 11 6.02 38.06 229.1 229.1 100%
10 45S 11 0.00 26.44 0.0 159.2 0%
11 45S 12 6.02 38.06 229.1 229.1 100%
12 45S 12 0.00 26.44 0.0 159.2 0%
13 45S 3
6.02 38.06 229.1 229.1 100%
14 45S 3
0.00 26.44 0.0 159.2 0%
15 45S 4
6.02 38.06 229.1 229.1 100%
16 45S 4
0.00 26.44 0.0 159.2 0%
Totals:
1833.0 3106.3 59%
BASE METAL Adjacent Base Metal (Near Surface Region A-B-i-L and C-D-E-H)
Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entrm #
(deg.)
Direction (sq. in.)
(in.)
(cu. in.)
(cu. in)
Examined 1
70L 11 5.43 38.06 206.7 206.7 100%
2 70L 11 0.00 26.44 0.0 143.6 0%
3 70L 3
5.43 38.06 206.7 206.7 100%
4 70L 3
0.00 26.44 0.0 143.6 0%
5 70L 4
5.43 38.06 206.7 206.7 100%
6 70L 4
0.00 26.44 0.0 143.6 0%
Totals:
620.0 1050.7 59%
Adjacent Base Metal (Balance of Volume Region E-F-G-H and I-J-K-L)
Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Enb (deg.)
Direction asq. in.)
(in.)
(cu. in.)
(cu. in.)
Examined 1
45L 11 24.67 36.06 938.9 938.9 100%
2 45L 11 0.00 26.44 0.0 652.3 0%
3 45L 3
24.67 38.06 938.9 938.9 100%
4 45L 3
0.00 26.44 0.0 652.3 0%
5 45L 4
24.67 38.06 938.9 938.9 100%
6 45L 4
0.00 26.44 0.0 652.3 0%
7 45S 11 24.67 38.06 938.9 938.9 100%
8 45S 11 0.00 26.44 0.0 652.3 0%
9 45S 3
24.67 38.06 938,9 938.9 100%
10 45S 3
0.00 26.44 0.0 652.3 0%
11 45S 4
24.67 38.06 938.9 938.9 100%
12 45S 4
0.00 26.44 0.0 652.3 0%
Totals:
5633.7 9547.3 59%
10ý 4
SALEM-1 APPENDIX VIII EXAMINATION COVERAGE FOR WELD:
MERIDIONAL @ 210 DEGREES SALEM-1 WELD NO.:
1-RPV-1043F SCAN PLAN DRAWING NO.: 6007161E-01 AGGREGATE COVERAGE OBTAINED:
Zone Coverage Obtained Weld: 59%
Adjacent Base Metal: 59%
Examination Volume Definition Weld Length:
64.5 in.
Area Measurement Volume Calculation Weld: Near Surface 1.68 sq. in.
Weld: Near Surface 108.4 cu. in.
Weld: Balance of Volume 6.02 sq. in.
Weld: Balance of Volume 388.3 cu. in.
Base Metal: Near Surface 5.43 sq. in.
Base Metal: Near Surface 350.2 cu. in.
Base Metal: Balance of Volume 24.67 sq. in.
Base Metal: Balance of Volume 1591.2 cu. in.
Examination Coverage Calculations WELD Weld (Near Surface Region B-C-H-I)
Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent En (deg.)
Direction (sq. in.)
(in.)
(cu. in.)
(cu. in.)
Examined 1
70L 11 1.68 38.06 63.9 63.9 100%
2 70L 11 0.00 26.44 0.0 44.4 0%
3 70L 12 1.68 38.06 63.9 63.9 100%
4 70L 12 0.00 26.44 0.0 44.4 0%
5 70L 3
1.68 38.06 63.9 63.9 100%
6 70L 3
0.00 26.44 0.0 44.4 0%
7 70L 4
1.68 38.06 63.9 63,9 100%
8 70L 4
0.00 26.44 0.0 44.4 0%
Totals:
255.8 433.4 59%
Weld (Balance of Volume Region G-H4-I-J)
Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry #
(deg.)
Direction asq.
In.)
(in.)
(cu. in.)
(cu. in.)
Examined 1
45L 11 6.02 38.06 229.1 229.1 100%
2 45L 11 0.00 26.44 0.0 159.2 0%
3 45L 12 6.02 38.06 229.1 229.1 100%
4 45L 12 0.00 26.44 0.0 159.2 0%
5 45L 3
6.02 38.06 229.1 229.1 100%
6 45L 3
0.00 26.44 0.0 159.2 0%
7 45L 4
6.02 38.06 229.1 229.1 100%
8 45L 4
0.00 26.44 0.0 159.2 0%
9 45S 11 6.02 38.06 229.1 229.1 100%
10 45S 11 0.00 26.44 0.0 159.2 0%
11 45S 12 6.02 38.06 229.1 229.1 100%
12 45S 12 0.00 26.44 0.0 159.2 0%
13 45S 3
6.02
-38.06 229.1 229.1 100%
14 45S 3
0.00 26.44 0.0 159.2 0%
15 45S 4
6.02 38.06 229.1 229.1 100%
16 45S 4
0.00 26.44 0.0 159.2 0%
Totals:
1833.0 3106.3 59%
BASE METAL Adjacent Base Metal (Near Surface Region A-B-1-L and C-D-E-H)
Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Enry #
(deg.)
Direction (sq. in.)
(in.)
(cu. in.)
(cu. in.)
Examined 1
70L 11 5.43 38.06 206.7 206.7 100%
2 70L 11 0.00 26.44 0.0 143.6 0%/
3 70L 3
5.43 38.06 206.7 206.7 100%
4 70L 3
0.00 26.44 0.0 143.6 0%
5 70L 4
5.43 38.06 206.7 206.7 100%
6 70L 4
0.00 26.44 0.0 143.6 0%
Totals:
620.0 1050.7 59%
Adjacent Base Metal (Balance of Volume Region E-F-G-H and I-J-K-L)
Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry #
(deg.)
Direction (sq. in.)
(in.)
(cu. in.)
(cu. in.)
Examined 1
45L 11 24.67 38.06 938.9 938.9 100%
2 45L 11 0.00 26.44 0.0 652.3 0%
3 45L 3
24.67 38.06 938.9 938.9 100%
4 45L 3
0.00 26.44 0.0 652.3 0%
5 45L 4
24.67 38.06 938.9 938.9 100%
6 45L 4
0.00 26.44 0.0 652.3 0%
7 45S 11 24.67 38.06 938.9 938.9 100%
8 45S 11 0.00 26.44 0.0 652.3 0%
9 45S 3
24.67 38.06 938.9 938.9 100%
10 45S 3
0.00 26.44 0.0 652.3 0%
11 45S 4
24.67 38.06 938.9 938.9 100%
12 45S 4
0.00 26.44 0.0 652.3 0%
Totals:
5633.7 9547.3 59%
5I6c1, y W34 69%
-CORE GUIDE LUG W/13 70° WELD AREA (NEAR SURFACE)
=0.88 SQ IN, BASE METAL (NEAR SURFACE)
-7.86 SQ IN.
NOTE: UNDER LUGS WAS NOT SCANNED DUE TO STAINLESS STEEL INSERTS NOT SHOWN ON CUSTOMER DRAWINGS SUPPLIED TO FTI-ANP, ec l
W13 45°L & 45°S WELD AREA (BALANCE OF VOLUME)
=4,94 SQ IN.
BASE METAL (BALANCE OlF VOLUME) =38,24 SQ IN, NOTE, UNDER LUGS WAS NOT SCANNED DUE TO STAINLESS STEEL INSERTS NOT SHOWN ON CUSTOMER DRAWINGS SUPPLIED TE FTI-ANP, GUIDE LUG A
d c4l 1
/-s 7I3
-,5k I--