LR-N12-0085, Submittal of Relief Request Associated with the Third Ten-Year Inservice Inspection (ISI) Interval
| ML12125A152 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 04/24/2012 |
| From: | Duke P Public Service Enterprise Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LR-N12-0085 | |
| Download: ML12125A152 (122) | |
Text
{{#Wiki_filter:PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, NJ 08038-0236 APR 2-4-202 NuclearLLC 10 CFR 50.55a LR-N12-0085 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Salem Generating Station Unit 1 Renewed Facility Operating License No. DPR-70 NRC Docket No. 50-272
Subject:
Submittal of Relief Request Associated with the Third Ten-Year Inservice Inspection (ISI) Interval In accordance with 10CFR50.55a, "codes and standards," paragraph (g)(5)(iii), PSEG Nuclear LLC (PSEG) hereby requests NRC approval of the attached request for the third 10-year ISI interval for Salem Generating Station Unit 1 which ended on May 20, 2011. This request addresses limitations for examinations performed in accordance with the requirements of American Society of Mechanical Engineering (ASME) Boiler and Pressure Vessel Code, Section XI for Class 1 and 2 components. There are no regulatory commitments contained within this letter. Should you have any questions concerning this matter, please contact Mr. Brian Thomas at 856-339-2022. Sincerely, Paul R. Duke, Jr. Manager - Licensing PSEG Nuclear LLC
Enclosure:
10CFR 50.55a Relief Request S1-13R-1 14 7gL7
LR-N12-0085 APR 2 4 2012 Page 2 cc: W. Dean, Administrator, Region I, NRC NRC Senior Resident Inspector, Salem R. Ennis, Project Manager, Salem, USNRC P. Mulligan, Manager IV, NJBNE (w/o attachment) L. Marabella, Corporate Commitment Tracking Coordinator (w/o attachment) T. Cachaza, Salem Commitment Tracking Coordinator (w/o attachment)
Salem Nuclear Generating Station, Unit 1 Renewed Facility Operating License No. DPR-70 NRC Docket No. 50-272 10 CFR 50.55a Relief Request Number S1-13R-114 Relief Request in Accordance with 10 CFR 50.55a (g)(5)(iii) Inservice Inspection Impracticality NOTE: Salem Unit 1 - Third Ten-Year Interval Inservice Inspection (ISI) examinations were conducted between the time period May 20, 2001 (start) and May 20, 2011 (end). There were six refueling outages conducted during this ten-year interval that included RFO-1 5 through RFO-20.
- 1. ASME Code Components Affected Code Class 1 and 2
Reference:
IWB-2500, IWC-2500 Code Case N-578-1 Table -2500 Code Case N-460 Examination Categories: B-B, B-D, C-A, C-B, R-A Item Numbers: See Table 1
Description:
See Table 1 Component Number: See Table 1
- 2. Applicable Code Edition and Addenda The code of record for the Salem Unit 1 Third Ten-Year ISI Program Interval, First Period, First Outage (RFO-1 5) is American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components",
1995 Edition through the 1996 Addenda. PSEG updated the code of record for the remaining Salem Unit 1 Third Ten-Year ISI Program Interval with the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components", 1998 1
Edition through the 2000 Addenda, herein after referred to as the Code. The code update was approved by the NRC via Reference 1. During the Third Interval, First Period, Second Outage (RFO-16), PSEG implemented a Risk-Informed Inservice Inspection (RISI) program based on EPRI Topical Report TR-1 12657, Rev. B-A and Code Case N-578-1 as specified by TR-1 12657. The RISI program was approved by the NRC via Reference 2.
- 3. Applicable Code Requirement For welds, other than those in the RISI program, the required examination volume is specified in figures that are referenced by the Examination Category and Item Number in Table IWB-2500-1 for Class 1 and Table IWC-2500-1 for Class 2 of the Code.
For welds that are within the RISI program, the required examination volume is specified in Section 4 of EPRI TR-1 12657 (Reference 3) specific to the degradation mechanism. Additionally, PSEG has implemented ASME Section XI Code Case N-460, "Alternative Examination Coverage for Class 1 and Class 2 welds, Section XI Division 1". Code Case N-460 states in part, when the entire examination volume or area cannot be examined due to interference by another component or part geometry, a reduction in examination coverage on any Class 1 or Class 2 weld may be accepted provided the reduction in coverage for that weld is less than 10%." ASME Code Case N-460 is approved for use by the NRC in Regulatory Guide (RG) 1.147, Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1. The examination categories for this relief request are B-B, B-D, C-A, C-B, and R-A. The applicable requirements are as follows: A. Examination Category B-B, Pressure Retaining Welds In Vessels Other Than Reactor Vessels-Inspection Program B Code Requirement: Item Number B2.40 applies to the steam generator tubesheet to head weld and requires essentially 100% volumetric examination of weld length as defined by table IWB-2500-1 and figure IWB-2500-6. B. Examination Category B-D, Full Penetration Welds of Nozzles in Vessels-Inspection Program B 2
Code Requirement: The requirements for Item Number B3.120 are addressed in 10 CFR 50.55a(b)(2)(xxi)(A). The requirements of Table IWB-2500-1, Examination Category B-D, Full Penetration Welded Nozzles in Vessels, Item B3.120 (Inspection Program B) of the 1998 Edition must be applied when using the 1999 Addenda through the latest edition. Item B3.120 require essentially 100% volumetric examination, as defined by Figures IWB-2500-7 a through d, of the nozzle inside radius sections of the pressurizer and primary side of the steam generators. C. Examination Category C-A, Pressure Retaining Welds in Pressure Vessels Code Requirement: Item Number C1.10 applies to vessel circumferential shell welds with gross structural discontinuities as defined in NB-3213.2 and requires essentially 100% volumetric examination as defined by Figure IWC-2500-1. Item Number C1.20 includes head circumferential welds and requires essentially 100% volumetric examination as defined by Figure IWC-2500-1 D. Examination Category C-B, Pressure Retaining Nozzle Welds in Vessels Code Requirement: Item Number C2.21 applies to nozzle-to-shell or head welds and requires both surface and volumetric examinations. The requirements are defined by Figure IWC-2500-4(a) or (b) for Nozzle to Head welds, and includes only those piping runs selected for Examination under Examination Category C-F. E. Examination Category R-A, Risk Informed Piping Examinations EPRI TR-1 12657, Rev B-A, Requirements:
" For piping welds NPS 4 or larger with a degradation mechanism of thermal fatigue (N-578-1, Item Number 1.11), the examination volume is defined in Figure 4-2. " For piping welds NPS 4 or larger with a degradation mechanism of intergranular stress corrosion cracking (IGSCC) (N-578-1, Item Number 1.16), the examination volume is defined in Figure 4-11.
- For piping welds without a degradation mechanism (N-578-1, Item Number 1.20), EPRI TR-1 12657 does not address 3
examination volume, therefore the volumes required by N-578-1 are used. Required volumes for the welds without a degradation mechanism are defined by Figure IWB-2500-8(c) of the 1989 Edition of ASME Section XI, except that the length of the examination volume is increased to include 1/2 in. beyond each side of the base metal thickness transition or counterbore as specified in Note 1 to Table 1 of N-578-1.
- 4. Basis for Relief:
Pursuant to 10 CFR 50.55a(g)(5)(iii), relief is requested from examining essentially 100% (>90%) of the volume or surface required by the Code for welds other than those in the RISI program, and from examining essentially 100% (> 90%) of the alternative volumes required by EPRI TR-112657 for welds in the RISI program. Table 1 identifies the specific examinations that do not meet the examination requirements described in this relief request including a description of the limitation. Attachment A provides additional descriptive details (data reports, sketches, illustrations, and/or drawings) for these components. The welds and examination areas subject of this request have been examined to the "extent practical" within the limitations of design, geometry and materials of construction. The welds were volumetrically examined by radiography and/or surface examination during fabrication, in accordance with applicable construction/fabrication codes providing adequate assurance for their structural integrity prior to plant operation. In addition, the components, identified in Table 1, are visually examined for leakage in accordance with the Code during each refuel outage for Class 1 and once during each period for Class 2. A. Examination Category B-B, Pressure Retaining Welds In Vessels Other Than Reactor Vessels-Inspection Table 1, identifies specific information, description of limitation, and a Figure for the examination report with an explanation of the limitation(s) encountered. Basis for Relief: The steam generator lower head to tubesheet weld (Examination Category B-B, Item Number B2.40) described in Table 1 was examined to the extent practical in accordance with ASME Section V, Article 4 using the required Supplements of ASME Section XI, Appendix I as defined in Table 1-2000-1 of the Code. 4
Impracticality Compliance: Obtaining volumetric Code required coverage for weld 13-STG-1 1 is impractical due to portions of the weld being obscured at four locations by the lower steam generator supports. Burden Caused by Compliance: To increase volumetric examination coverage, the support connections at four locations would require a design modification. Proposed Alternative and Basis for Use: No alternative provisions are practical for the subject component. Examinations were performed to the maximum extent practical with no recordable indications. The subject components have been subjected to periodic visual leakage examinations. This provides additional assurance that the structural integrity of the subject components was maintained. B. Examination Category B-D, Full Penetration Welded Nozzles in Vessels- Inspection Program B Table 1, identifies specific information, description of limitation, and a Figure for the examination report with an explanation of the limitation(s) encountered. Basis for Relief: The four nozzle inner radii (Examination Category B-D, Item Number B3.120) described in Table 1 were examined from the outside surface to the extent practical in accordance with ASME Section V, Article 4 using the required Supplements of ASME Section XI, Appendix I as defined in Table 1-2000-1 of the Code. Impracticality Compliance: Obtaining Code required coverage is impractical for the subject examinations due to surface irregularities on the pressurizer head. The pressurizer head is a cast product and is mostly in the as-cast condition with localized grinding. The surfaces from which scanning is performed contain excessive waviness and are non-uniform including raised lettering adjacent to one nozzle. The portions of the inner radius that are scanned from surfaces where these conditions prevent adequate transducer contact are considered not examined. Burden Caused by Compliance: Altering the Pressurizer head configuration would require extensive grinding to achieve a level 5
surface to improve transducer contact. Because the head is a curved surface, manual grinding may actually result in worse conditions further decreasing obtainable coverage. Machine grinding would require special tooling with extensive development for deployment and application. Proposed Alternative and Basis for Use: No alternative provisions are practical for the subject component. Examinations were performed to the maximum extent practical with no recordable indications. The subject components have been subjected to visual leakage examinations after the completion of each refueling outage. This provides additional assurance that the structural integrity of the subject components was maintained. C. Examination Category C-A, Pressure Retaining Welds in Pressure Vessels Table 1, identifies specific information, description of limitation, and a Figure for the examination report with an explanation of the limitation(s) encountered. Basis for Relief: The five Examination Category C-A welds described in Table 1 were examined to the extent practical in accordance with Appendix III using the required Supplements of Appendix I, as defined in Table 1-2000-1 of the Code. Impracticality Compliance: Obtaining Code required coverage for welds 1-CVCT-2, 1CVE-18-SWIJ-2, 1-BIT-A and 1-BIT-B is impractical due to portions of each weld being obscured by support legs that are welded to the vessel shell. Obtaining Code required coverage for weld 1CVE-1 8-SWIJ-1 is impractical due to the flange configuration that prevents scanning from both sides of the weld and the location of an identification name plate that is welded to the vessel shell. Appendix III, Supplement 1 of the Code only requires scanning from both sides of the weld when practical, but because the vessel shell and flange are fabricated from austenitic material, PSEG does not consider this a complete examination unless the examination volume is scanned from both sides. 6
Burden Caused by Compliance: To increase examination coverage, the support connections for the three vessels would require a design modification and the flange on the seal water injection filter would have to be replaced with a uniquely designed and fabricated flange that would allow scanning from the flange side of the weld. Proposed Alternative and Basis for Use: No alternative provisions are practical for the subject components. Examinations were performed to the maximum extent practical with no recordable indications. The subject components have been subjected to periodic visual leakage examinations. This provides additional assurance that the structural integrity of the subject components was maintained. D. Examination Category C-B, Pressure Retaining Nozzle Welds in Vessels Table 1, identifies specific information, description of limitation, and a Figure for the examination report with an explanation of the limitation(s) encountered. Basis for Relief: Impracticality Compliance: The three nozzle-to-vessel welds described in Table 1 were volumetrically examined to the extent practical in accordance with ASME Section V, Article 4 using the required Supplements of ASME Section Xl, Appendix I as defined in Table 1-2000-1 of the Code. The one nozzle-to-vessel weld requiring magnetic particle examination was examined to the extent practical in accordance with ASME Section V, Article 7. Obtaining Code required volumetric coverage is impractical for weld 1-BIT-1 due to the nozzle configuration and surface condition, weld 1-BIT-2 due to weld crown and nozzle surface configuration and weld 16-BFN-21 11-1 due to steam generator insulation package support ring. Burden Caused by Compliance: To increase volumetric examination coverage, the head-to-nozzle configuration would require replacement with an altered configuration and the weld crowns removed. To increase volumetric and magnetic particle examination coverage, the head-to-nozzle configuration of 16-BFN-2111-1 would require removal or movement of the insulation ring. 7
Proposed Alternative and Basis for Use: No alternative provisions are practical for the subject components. Examinations were performed to the maximum extent practical with no recordable indications. The subject components have been subjected to periodic visual leakage examinations. This provides additional assurance that the structural integrity of the subject components was maintained. E. Examination Category R-A Risk Informed Piping Examinations Table 1, identifies specific component information, description of limitation, and a Figure for the examination report with an explanation of the limitation(s) encountered. Basis for Relief: PSEG has implemented Appendix VIII, "Performance Demonstration for Ultrasonic Examination Systems," of the ASME Code, Section XI, 1995 Edition with the 1996 Addenda in accordance with the schedule specified in 10 CFR 50.55a(g)(6)(ii)(C)(1). With the implementation of Appendix VIII, volumes that cannot be examined within the limits Of qualification are considered not examined. The achieved coverage provided in Table 1 is based on the volume examined by Appendix VIII qualified techniques. Impracticality Compliance: Obtaining Code required coverage is impractical for the ten examination Category R-A welds listed in Table 1 due to configurations and material properties as uniquely described for each Component ID. Burden Caused by Compliance: To increase volumetric examination coverage would require substantial design modification and the design, fabrication and installation of special fittings. Proposed Alternative and Basis for Use: It is Salem's normal practice to evaluate RISI selections for examination coverage in the planning process within the provisions of Code Case N-578-1. If during the evaluation it is determined that coverage will not be greater than 90%, then a substitution is selected, if available, that meets the requirements of Code Case N-578-1 and provides greater examination coverage. During the interval nine initial selection locations were identified as potentially not allowing greater than 90% coverage. These selection locations 8
were substituted within the requirements of Code case N-578-1 and essentially 100% examination coverage was obtained. Substitutions were not performed for the ten specific examinations listed in Table 1 for Category R-A. These selection locations were not identified in the planning process as requiring substitution. The examinations were performed to the maximum extent practical with no rejectable indications. The subject class 1 components have been subjected to visual leakage examinations after the completion of each refueling outage. The class 2 components have been subjected to periodic visual leakage examinations. This provides additional assurance that the structural integrity of the subject components was maintained. During the fourth interval RISI program update all except two (029700 and 022100) of the ten limited examinations from the third interval have been substituted. The two examinations that remain in the RISI schedule in the fourth ISI interval were maintained due to no suitable substitutions being available.
- 5. Duration of Proposed Alternative This relief is applicable to the Third Ten-Year Inspection Interval for Salem Unit 1 Generating Station, which ended on May 20, 2011.
- 6. Precedents As part of the submission of the Salem 1 Second 10-year interval ISI program plan, associated relief requests were submitted with the exception of Examination Category R-A, which was not implemented until the Third Interval, First Period, Second Outage (RFO-16). In the Safety Evaluation of this submission (reference 4), relief was granted for Salem 1 Second 10-year interval for Category B-B component 13-SGT-1 1, Category B-D component 4-PSN-1131-IRS, Category C-A components 1-CVCT-2, 1-BIT-A, 1-BIT-B, and Category C-B components 16-BFN-21 11-1, 1-BIT-1 and 1-BIT-2.
9
- 7. References
- 1. Salem Nuclear Generating Station, Unit No. 1 - Evaluation of Request To Utilize 1998 Edition With 2000 Addenda of The American Society of Mechanical Engineers Boiler And Pressure Vessel Code For The Third 10-Year Interval (TAC No. MC4990).
(ML050870179)
- 2. Salem 1 Generating Station - Implementation of a Risk-Informed Inservice Inspection Program (TAC No MB7537 and MB7538),
October 1, 2003. (ML032390034)
- 3. EPRI TR-1 12657, Revised Risk-Informed Inservice Inspection Evaluation Procedure, Revision B-A. (ML013470102)
- 4. Safety Evaluation of Relief Requests for the Second Ten-Year Interval Inservice Inspection Program Plan - Salem 1 Generating Station, Unit 1 (TAC No. MB3811). (ML030160750) 10
Table I Salem I Nuclear Generating Station RR# S1-13R-114 SumEnI Component ID F Description I]Eam Material Exam Third Interval Inservice Inspection Examination Limitations Exm Exam JceLimited~Examinetion Ctac Asme NDE Ite N. Exm Cas Reu Code Coiverage Exam F________ AtchetA teen Coverage x ae Limitation Description Axial scans were performed using a 45" and 60° shear wave and a 0" longitudinal wave. Circumferential scans were performed using a 45" and 60" shear wave. The 45°axial scan obtained 70.5% and the 60° axial scan obtained 70.5% of required coverage. The 450 circumferential scans 007901 13-STG-11 Steam Generator #13 Lower Carbon Steel with Stainless B-B B2.40 1 UT IWB-2500-6 67.0% RFO-20 obtained 64.2% and the 609 circumferential scans obtained 54.9% of required coverage. The 0" A-1 Head to Tube Sheet Steel Cladding longitudinal wave obtained 71.15% of required coverage. The combined total coverage for all scans achieved 67.0% of the required coverage. The total weld length is 439.75", the limitations are due to the four support obstructions restricting a total of 124" of metd length and the ID Plate restricting a total of 6" of weld length Examination was performed using a 458, 60° and 706 shear wave scan. The 45° shear wave scan achieved 100% code required coverage. The 60° and 70* shear wave scan each achieved 50% Precoorizer Relief Nozzle Carhon Steel with Stoinles code required coverage. The combined total of all scans achieved 66.7% of the code required 007106 6-PRN-1103-IRS Inside Radis Steel Cladding S B-D B3.120 1 UT IWB-2500-7 [b] 66.7% RFO-17 coveage0The60Pand70"1hee3manRconImreilmitdRdedtocsraSeeondtiCol(Cotieed coverage. The 60c and 70g shear wave scan were limited due to surface conditions (Cast Head) A-2 throughout the examination due to surface grinding, surface pilling and surface waviness along the required scanning areas. Examination was performed using a 45". 60" and 70" shear wave scan. The 45" shear wave scan achieved 100% code required co-mage. The 60" and 70" shean wave scan each achieved 500/6 007200 6-P 1Presurizer Relief Nozzle Carbon Steel with Stainleso B- B3.120 1 UT WB-2500-7[b] 66.7% RFO-17 code required coverage. The combined total of all scans achieved 66.7% of the code required A-3 06-PRN-1104-RS Inside Radius Steel Cladding coverage. The 60" and 70" shear wave scan were limited due to surface conditions (Cast Head) throughout the examination due to surface grinding, surface pitting and surface waviness along the required scanning areas. Examination was performed using a 45", 60" and 70" shear meve scan. The 45" shear wave scan achieved 100% code required o*overage.The 60" and 70" shear wave scan each achieved 50% 007300 Precurizer Relief Nozzle Carbon Steel with Stoinlecs B7code required coverage. The combined total of all scans achieved 66.7% of the code required A-4 RInssiide RedisN Steel Cladding 8-0 83.120 1 UT IWB-2500-7 [b] 66.7% RF0-17 coverage. The 60" and 70" shear wave scan were limited due to surface conditions (Cast Head) throughout the examination due to surface grinding. surface pitting and surface waviness along the required scanning areas. Examination was performed using a 50" and 70" shear wave scan which achieved a total of 84.6% of code required coverage. The 50" shear wave scan achieved 100% of code required coverage. 007400 4-PSN-1131-R Prerizer Spr Nozzle Carbon Steel with Sle B-D B3.120 1 UT IWB-2500-7 [bh 84.6% RFO-16 The 70" shear wave scan achieved 69.2% of code required coverage due to a 13"x6" area that was A-5 RInsideRadian Steel Cladding obstructed due to raised lettering in the casting located on the outside surface of vessel head between the spray nozzle and manway. Axial scans were performed using a 45" and 60" shear wave and a 00 longitudinal wave. Circumferential scans were performed using a 45eand 60" shear wave. The 45"axial scan obtained 88.1% and the 60" axial scan obtained 88.1% of required coverage. The 45" circumferential scans Boric Acid Injection Tank - Carbon Steel with Stal obtained 89.8% and the 60" circumferential scans obtained 77.35% of required coverage. The 0° 204400 1-BIT-A Lower Head To Transiton Carbon C-A C1.10 2 UT IWC-2500-1 86.59% RFO-20 longitudinal wave obtained 88.1% of required coverage. The combined total coverage for all scans A-6 Piece Steel Cladding achieved 86.59% of the required coverage. The total meld length is 179", the limitations are due to the close proximity of the 1-BIT-B meld the full length of the meld. The four welded support legs restricting a total of 35" of meld length and two branch connections restdctihg a total of 4" of meld length. Axial scans were performed using a 45" and 606 shear wave and a 0" longitudinal wave. Circumferential scans were performed using a 45d and 60" shear wave. The 45°axial scan obtained 80% and the 60" axial scan obtained 80% of required coverage. The 45" circumferential scans 204410 1-BIT-B Boric Acid Injection Tank- Carbon Steel with Stainless C-A C1.10 2 UT IWC-25OG-1 79.75% RFO-20 obtained 80% and the 60" circumferential scans obtained 78.5% of required coverage. The 0" A-7 T"ransiion Piece To Shell Steel Cladding longitudinal wave obtained 80% of required coverage. The combined total coverage for all scans achieved 79.75% of the required coverage. The total weld length is 179", the limitations are due to the four welded support legs restricting a total of 35" of meld length and the manway restricting a total of 6" of meld length for the 60° only. Axial and circumferential scans were performed using a 45" shear wave which achieved 61.6% of required coverage. The total length of the subject meld is 282.7". A total of 52" was inaccessible for 204800 1-CVCT-2 V Cotrol Tank Shell end Headl -SStainle C-A C1.20 2 UT IWC-2500-1 81.6% RFO-19 examination due to four welded supports that covered 13" of meld each. The 230.7" of meld that mos 22VCT)Shell To Laer Head Steel accessible was scanned from both sides of the meld in both the axial and circumferential directions A-8 for full Code coverage. Note: Indications identified and evaluated in previous exams were identified in this examination with no evidence of growth. Axial and circumferential scans were performed using a 45cshear wave from the shell side and across the mold. Axial scans were performed using a 70" shear wave from the shell side and across the weld and a scan with a 0" longitudinal wave was performed on both the shell and flange side. The combined coverage for all scans achieved 59.73% of the required coverage. The 45" scan 511506 1CVE 18-SWJ-1 Seal Water Injection Pilaer Shell and Plangel -Stainteoc C-A C1.10 2 UT IWC-2500-1 59.73% RFO-16 achieved 63.17% of the required coverage and the 70" scan achieved 56.3% of required coverage. A-9 Flange to Shell Weld Steel Both the 45" and 70" shear wave scan were limited by welded attachments that made 3.25" of meld length inaccessible and a welded nameplate that made 4" of mold length inaccessible. Additionally, the flange taper prevents angle beam scanning from the flange side of the weld. The vessel shell and flange are stainless steel.. Page 1
LiwitetionDescription Attachment A Sum # Component ID Description Material Exam Ca.Exam Exam Cat. Item CloseLimited No Acm Item_________ Ex.amlas Examination NDERequiremen.ts Code Oa Exam Outage CoeaetOtgFigure Achieved J Limiiremeet Axial and circumferential scans were performed using a 45" shear wave from the shell and head side of the weld. A 0° longitudinal scan was performed on the shell and head side of the weld. 1CVE1f-SWIJ-2 51150 Seal Water Injection Pillar Shell and Head-Stainless C-A CIA. 2 UT IWC-2500-1 64.0% RFO-16 Three support legs welded directly across the weld cause 12.25 inear inches of weld to he A-10 inaccessible for examination, The total for combined scans achieved 64% of required coverage. The vessel shell and flange are stainless steel. Direct contact Magnetic Particle examination was performed using two directions with the lines of 204601 16-BFN-2111-1 Steam Generator #11 Nozzle Carbon Steel SA-302B C-B C2.21 2 MT IWC-2500G-4[a 85.32% RFO-20 flux perpendicular to the line of flux in the first direction which achieved 85.32% of required A-il to Shell coverage. The total length of the subject weld is 109". A limitation total of 16" was inaccessible for examination due to Steam Generator insulation package support ring. Scans were performed using a 0" longitudinal wave and a 45° and 60" shear wave scan which achieved a total of 70.64% of code required coverage. The 0' longitudinal exam was limited to 204001 16-BFN-2111-1 Steam Generator #11 Nozzle Carbon Steel SA-302B C-B C2.21 2 UT IWC-2500-4 [a] 70.64% RFO-20 70.64% of required coverage. The 45" shear mave axial and circumferential scans were limited to A-12 to Shell 70.64% of required coverage. The 60" shear wave axial and circumferential scans were limited to 70.64% of required coverage. The total length of the subject weld is 109". A limitation total of 16" was inaccessible for examination due to Steam Generator insulation package support dng. Scans were performed using a 0" longitudinal wave and a 45° and 600 shear wave scan which achieved a total of 43.43% of code required coverage. The 0' longitudinal exam was limited to 23.47% of required coverage. The 450 shear wave axial scan is limited to 44.13% and the circumferential scan is limited to 49.77% of required coverage. The 60° shear wave axial scan is 204440 1-BIT-1 Boric Acid Injection Tank - Carbon Steel with Stainless C-f C2.21 2 UT IWC-2500-4 [b] 43.43% RF015 limited to 50% and circumferential scan is limited to 49.77% of required coverage. All scans are A-1 3 Inlet Nozzle to Head Steel Cladding performed from the head side of the weld only; scans from the nozzle side and from the weld are not performed due to nozzle configuration and surface conditions. A code required surface MT exam mas also performed at time of inspection that achieved 100% required coverage with acceptable results. Axial scans were performed using a 45" and 60" shear wave and a 0" longitudinal wave. Circumferential scans were performed using a 45° and 60" shear wave. The 450axial scan obtained 2Bn Acid Injection Tank - Carbon Steel with Stainless 958.% and the 60" axial scan obtained 100% of required coverage. The 450 and 60" circumferential 204450 1-BlT2 OutlAt Nozzje To Head Steel Cladding C-B C2.21 2 UT IWC-2500-4 [bJ 73.95% RFO-17 scans each obtained 50% of code required coverage, The combined total coverage for all scans A-14 achieved 73.95% of the required coverage. The limitations are due to weld crowe and nozzle surface configuration. A code required surface MT exam was also performed at time of inspection that achieved 100% code required coverage with acceptable exam results. Nozzle SA-216 Grade WCC Axial scans were performed using a 45" shear wave and a 0", 350, 45', and 60" longitudinal wave. with 309 Stainless Steel TR-1 12657 Circumferential scans were performed using a 45' shear wave and a 45" and 60' longitudinal wave. 029700 14-PS-1131-2 Nozzle To Safe-End Cladding, Safe End SA-182 R-A R1.11-2 1 UT Fig. 4-2 83.3% RFO-17 The combined coverage for all scans achieved 83.3% of required coverage. Limitations are due to A-15 Grade F316 and Weld Filler insulation lugs permanently welded on the Safe-End taper. Lugs are 2" wide and are located at 0" - 309 Stainless Stall, No 90", 1*60, and 270". No weld substitution due to this weld being the only weld in risk segment PS-Butteedng on Nozzle. 001. A Axial scan was performed using a 450 shear wove from the pipe side of the weld. Circumferential TR-112657 scans with a 45d shear wave was performed on the pipe side of the weld. The combined coverage Piping and Tee- Stainless 022100 2-CV-1175-36 Pipe To Tee R-A R1.11-2 1 UT Fig. 4-2 50.0% RFO-18 for all scans achieved 50% of required coverage. Scanning from the tee side of the weld is , A-16 Steel obstructed due to configuration of tee. No weld substitution due to this weld being the only but weld in this line and risk segment CV-064. The remainder of line contains socket welds and only would receive VT-2 examinations. Axial and circumferential scans using a 450 shear wave were performed on both sides of the weld. Axial scans using a 60" longitudinal wave and a 70" shear wave were performed on both sidec of thl weld. Circumferential scans achieved 100% coverage, and axial scans achieved 71.43% coverage 022700 6-PR-1105-6 Elbow To Elbow Elbows Stainless Steel R-A R1.20-4 1 UT See Note 1 85.72% RFO-17 for a total combined coverage of 85.72%. Six inches of weld length was not examined by the angle A-17 beam scans due to the configuration caused by the intrados of the two short radius elboem. No weld substitution in third internal but the weld has been substituted for in the subsequent fourth interval with the expectation of increased examination coverage. Axial scans were performed using a 450 Longitudinal wave and a 450 shear wave from the pipe side of the weld. Circumferential scans were performed using a 450 shear wave from the pipe side of the Elbow Cast Stainless Steel, meld. The combined coverage for all scans achieved 50% of required coverage. Scanning from the 037400 31-RC-1140-3 Elbow To Pipe Piping Stainless Steel R-A R1.20-4 1 UT See Note 1 50.0% RFO-16 elbow side of the weld is obstructed due to the acoustic properties of the cast stainless steel elbow. A-18 nNomeld substitution due to the remaining welds in the line and segment would also result in similar limitation due to fittings being cast austenitic stainless steel, Risk Informed update for the 4th interval identified substitution weld and this weld not scheduled in subsequent fourth interval. Axial scans were performed using a 450 longitudinal wave and a 450 shear wave from the pipe side of the weld. Circumferential scans were performed using a 45° shear wave from the pipe side of the Elbow Cast austenitic weld. The combined coverage for all scans achieved 50% of required coverage. Scanning from the 037500 31-RC-1140-4 Pipe To Elbow Stainless Steel, Piping R-A R1.20-4 1 UT See Note 1 50.0% RFO-16 elbow side of the weld is obstructed due to the acoustic properties of the cast stainless steel elbow. A-19 Stainless Steel No weld substitution due to the remaining welds in the line and segment would also result in similar limitation due to fittings being cast austenitic stainless steel, Risk Informed update for the 4th interval identified substitution weld and this weld not scheduled in subsequent fourth interval. Page 2
Sum# Component ID Description S I Mateal Exam Cat Exam Item No Asasm Limite NDE Class Exam Examination Examnatin Requirements 1 11.CgoI Exam Code Acveraed outage m OuageFiguren eqaiemeno Limitation Description D Figure A Axial and circumferential scans were performed using a 45° longitudinal wave and a 45* shear wave from the pipe side of the meld. The combined coverage for all scans achieved 50% of required Elbow Cast austenitic TR-1 12657 coverage. Scanning from the tee side of the metd is obstructed due to the acoustic properties of the 096750 10-SJ-1141-15 Tee To Pipe Stainless Sleet, Piping R-A RI.16-5 1 UT Fig. 4-11 50.0% RFO-16 cast stainless steel tee. No meld substitution due to the remaining welds in the line and segment SJ- A-20 Stainless Sleet 095 would result in greater limitations due to fittings being cast austenitic stainless steel and meld being to valves, Risk Informed update for the 4th interval identified substitution meld and this meld not scheduled in subsequent fourth interval. Axial scans were performed using a 45' and 60* shear wave and a 60° longitudinal wave from the pipe side of the weld. Circumferential scans with a 45* shear wave was performed on the pipe side TR-112657 of the weld. The combined coverage for all scans achieved 50% of required coverage. Scanning 101150 10-SJ-1121-16 Tee To Pipe R-A R1.16-5 1 UT Fig. 4-11 50.0% RFO-19 from the tee side of the meld is obstructed due to the acoustic properties of the cast stainless steel A-21 Steel, Piping Stainless Steal tee. No weld substitution due to the remaining welds in the line and segment SJ-087 would result in greater limitations due to fittings being cast austenific stainless steel and welds being to valves, Risk Informed update for the 4th interval identified substitution meld and this weld not scheduled in subsequent fourth interval. Axial and circumferential scans were performed using a 45° longitudinal wave and a 45° shear wave TR-112657 from the pipe side of the meld. The combined coverage for all scans achieved 50% of required 103500 10-SJ-1111-16 Tee To Pipe Tee Cast eustenitic Stainless R-A R1.16-5 1 UT Fig. 4-11 50.0% RFO-16 coverage. Scanning from the tee side of the meld is obstructed due to the acoustic properties of the A-22 Steel, Piping Stainless Steel cast stainless steel tee, Risk Informed update for the 4th interval identified substitution meld and this meld not scheduled in subsequent fourth interval. Axial and circumferential scans were performed using a 450 shear wave from the pipe side. Axial scans were performed using a 700 shear wave from the pipe side and a scan with a 0* longitudinal wave was performed on both the pipe and flange side. The combined coverage for all scans 279540 10-SW-2141-5 Flange To Pipe Flange and Piping AL-6XN R-A R1.20-4 2 UT See Note 1 50.0% RFO-16 achieved 50% of required coverage. Angle beam scanning from the flange side of the weld is A-23 (S8673 NC25-60) x1obstructeddue to the configuration of the flange. The pipe and flange material are SB673 INCO 25-
- 60. Risk Informed update for the 4th interval identified a substitution weld and this weld is not scheduled in subsequent fourth interval. The fourth interval substitution mold was examined in the first outage of the fourth interval with no limitations and no rejectable indications.
Axial and circumferential scans were performed using a 45° shear wave from the elbow side. Axial scans were performed using a 70° shear wave from the elbow side and a scan with a 0* longitudinal wave was performed on both the elbow and flange side. The combined coverage for all scans 270620 10-SW-21g3-3 Elbow To Flange Elbow and Flange AL-6XN (SB673 INCO 25-60) R-A R1.20-d 2 UT See Note 1 50.0% RFO-16 achieved 50% of required coverage. Angle beam scanning from the flange side of the weld is obstructed due to the configuration of the flange. The elbow and flange matedal are SB673 INCO A-24 25-60. Risk Informed update for the 4th interval identified substitution meld and this weld is not scheduled in subsequent fourth interval. The fourth interval substitution mold was examined in the first outage of the fourth interval with no limitations and no rejectable indications. Notes: For piping welds without a degradation mechanism (N-578-1, Item Number 1.20), EPRI TR-112657 does not address examination volume, therefore the volumes required by N-578-1 are used. Required volumes for the welds without a degradation mechanism are defined by Figure IWB-2500-8(c) of the 1989 Edition of ASME Section Xl, except that the length of the examination volume is increased to include Y in. beyond each side of the base metal thickness transition or counterbore as specified in Note 1 to Table 1 of N-578-1. Page 3
Attachment A-1I Page 1 of 4 W 13-STG-3, x z l8-BFN-IV "32-MSN-2131-IRS MSN-2131-1 Y 13-S NWAY AT 2700 PLAN VIEW 13-S 13-S TG-31 Y 30 29-RCN-1130
+ z 13-S
ý%-INLET MANWAY 13-S OUTET W
END VIEW STEAM GENERATOR NO. 13 WESTINGHOUSE SERIES "F'S/G S/NT 2171 IMPORTANT: THIS DWG IS FOR IDENTIFYING ISI/PSI WELD ID's ONLY. THIS OWG REPRESENTS THE SERIES "51"NOT THE SERIES 'F'S/G. ANY REVISON TO THIS DRAWING FIGURE: A-6 REVISION: 2 ATTENTION: SHALL BE MADE ONLY BY CAED PSEG Nuclear, LLC 2 REVISED PER ORDER No. 80008418. SALEM NUCLEAR GENERATING STATION SYSTEM: STEAM GENERATOR No. 13 REVISED DWG TO REFERENCE UNIT 1- WELD IDENTIFICATION FIGURE 1 1/19/98 NEW REPLACEMENT S/G's. INSEVC INTIONLINE: N/A REV. DATE DESCRIPTION INSERVICE INSPECTION DRAWING THIRD 10 YEAR INSPECTION INTERVAL
© 2000 PSEG Nuclear, LLC.AlI Rights Reserved.
Attachment A-1 Page 2 of 4 ULTRASONIC EXAMINATION SCAN LIMITATiON REPORT AR E/A Customer Salem Component" 13-StG-l.111 Figure No.: N/A: Summary#,007901 Weld No.: Lower Head To Tube Sheet Percent Of Exam Completed: 67;0%$Coverage
.(Calculations Or Comments Below)
,Reference Point; 0"= ID Plate 45' UPST= 70.5% -Obstructed 130" due to supports and ID Plate. 1)Interfering Condition .See Bel0w 45" DNST- 57.9% - Obstructed 124" dueoto supports 45° CW = 70.5%;- Obstructed 130' due to supports and ID Plate Distance From Centerline N/A To N/A 450 CCW:= 70.5% -.Obstructed 130" due to supports and ID Plate Distance From Ref. Point N/A To N/A " UPST= 70.5% Obstructed 130" due to supports and IDPiate
- 2) Interfering Condition N/A 60* DNST= 39.3% -Obstructed 124" due to supports D.l60" cW =70.5% - Obstructed 130",due to supports and ID Plate 60* CCW = 70.5% - Obstructed 130" due to supports and ID Plate Distance From Ref. Point N/A To N/A 0" UPST= 70.5% - Obstructed 130" due to supports and ID Plate
- 3) interfering Condition N/A 0" DNST= 71.8% - Obstructed 124' due to supports Distance From Centerline NIA To N/A.
Distance From Ref. Point NA To N/A :45" Total = 67.35% Total % Obstructed includes the 60" Total = 6217% Tube Sheet Radius. (For,All Measurements Indicate: US, DS,OCW; CCW) 0 Total = Ti.15% -Sketch Of Limitation(s): Total weld Lengths= 439.75" Each Support Obstruction= 31" x 4"= 124.0" Weld Width 1.75" Both 45" & 60" limited on DNST Side due to Tube Sheet Radius. 45' limited to 80.7% 60" limited to 54.8% Obstruction from Tube Sheet Radius SII S I 4.2 5. DNST 0 U :180" U 270" U DNS.0 P P1 P P P P Center Line 0 O -- R R R R UPST T T T T ID Plat 3,W (INCLUDED THE EXTENT OF %COMPLETEL) OF EXAMAND REASON FOR LIMITED REPORT,AND.SKETCH SHOWING AREA OF LIMITATION.) EUam'ie G rge G. hap an Date: 04-08-2010 Exainerate Reviewert. Ro.be Wte .Kellerhall I _____S____________ Pate: Pg~f
Attachment A-1 Page 3 of 4
Attachment A-1 Page 4 of 4
IAttachment A-4-PRN-1100-IRS (RELIEF NOZZLE) 4-PSN-1131-IRS (SPRAY NOZZLE) Page 1 of 4
. MANWAY CIRCUMFERENTIAL LONGITUHDINAL 1-PZR-21 -
\6-PRN-1105-IRS (RELIEF NOZZLE) I-PZR- 20 I-PZR-19 6-PRN-1104-IRS (RELIEF NOZZLE) 18 I-PZR-17 16 1-PZR 14 I-PZR 12 1-PZR ELEV. 105' 10 1-PZR -8 I-PZR -6 I-PZR 4 1-PZR- 10-H 1-PZR 1-PZR-8 2 1-PZR -
1-PZR-10 - 1-PZR-1 I-PZR 1-PZR-IVS 1-PZR LINE A-3052 231 ATTENTION: ANY REVISON TO THIS DRAWING SHALL BE MADE ONLY BY CAED PSEG Nuclear, LLC FIGURE: A-3 I REVISION: 1 SALEM NUCLEAR GENERATING STATION SYSTEM: PRESSURIZER 1 REVISED PER ORDER No. 80008418. UNIT 1- WELD IDENTIFICATION FIGURE LINE: N/A REV. DATE DESCRIPTION INSERVICE INSPECTION DRAWING THIRD 10 YEAR INSPECTION INTERVAL (D 2000 PSEG Nuclear. LLC.AlI Rights Reserved.
O PSEG ULTRASONIC EXAMINATION SCAN LIMITATION REPORT
;uclear LLX Ustomer PSEG I Salem Unit I System: Pressurizer Summary No.: 007100 Component ID: 6-PRN411034RS Applicable Report No: UT-05-056, UT-05-057, UT-05-058 UT-0-059 Reference Point
- 1) Interfering Condition See Supplemental Report Distance From Centerline To 45I W 60-*(9 to 30) 700 +/-(5 to 21)-
Distance From Ref. Point To Coverage % 100% 50% 50%
- 2) Interfering Condition Distance From Centerline To Total Exam Coverage: 66.7%
Distance From Ref. Point To See Supplemental Report for Additional Information.
- 3) Interfering Condition Distance From Centerline To Distance From Ref. Point To (For All Measurements Indicate: US, DS, CW, CCW)
Supplemental Report 0 PSEG Report No.: UT-05-059 Page: .' of .*, 04 jo-;V-W Summary No.: 007100 Examiner: FlesneirBretz, - - Level: II-PDI Reviewer: Conti, Adiam Date: I Examiner: N/A Level: NIA Site'Review: John O'Nel Other: NWA Level: NIA ANII Review: /0/ Comments: Component ID: 6-PRN-11034RS Applicable Spreadsheet Tabe: 7 Probe Angie Probe Skew Scan Surface 45' *:37 "Bl96d 7W (Sto 21) Vessel 60' tp(9 to ý30) Vessel Coverage Calcula4lons: 450 (W37) Limitation: None. Coverage% Obtained: 100% Coverage Calculations: 70' +/-(5 to 21) Limitation: 1. Surface condition difficulties (Cast Head) were encountered throughout the examination due to surface grinding, surface pitting and'surface waviness along the required scanning areas, Precise locations could not be recorded as these conditions are numerous and Intermittent between probes and from Min R to Max R values. An estimate Is that 50% of the accessible scanning area provided adequate search unit contact. Coverage % Obtained: 50. 0% Coverage Calculations: 60' +/-(9 to 30)
- Limitation: 1. Surface conditlon difficultles (Cast Head) were encountered throughout the examination due to surface grinding, surface pitting and surface waviness along the required scanning areas. Precise locations could not be recorded as these conditions are numerous and Interittent between probes and from MIn Rto Max Rvalues. An estimate Is that 50%.of the accessible sca-nnlng area provided adequate search unit contact.
Coverage % Obtained: 50% Total Cmbined Coverage: 66.7% comments: Maintained 10% - 20% ID Clad Roll during all examinations. 45°S note: 2.0" of metal path delayed off screen to display 2.0" to 7.0" of metal path on A-scan. 70'S note: 5.0" of metal path delayed off screen to display 5.0" to 15.0" of metal path on A-scan. 70S note: 6.0" of metal path delayed off screen to display 6.0" to 11.0" of metal path on A-scan. Attachment A-2 Page 3 of 4
0~ 4-PRN-1100-IRS (RELIEF NOZZLE) IAttachment A-3 44-PSN-1131-IRS (SPRAY NOZZLE) Page 1 of 4 [ýum # 007200 MAN WAY 16-PRN-1104-IRS 0 LONGITUDINAL IRCUMFERENTIAL 1-PZR-21 -
--PRN-1105-IRS (RELIEF NOZZLE) 1-PZR-20 6-PRN-1103-IRS (RELIEF NOZZLE) 1-PZR-18 1-PZR-16 1-PZR-14 1-PZR-12 ELEV. 105' I-PZR-10 1-PZR-8 1-PZR-6 I-PZR-4 I-PZR-10 -H 1-PZR-8 I-PZR-2 1-PZR-4 1-PZR-10 -
I-PZR I-PZR L-PRESSURIZER SURGE LINE 14-PSN-1131-IRS A-3052 231 ANY REVISON TO THIS DRAWING PSEG Ncer LLC FIGURE: A-3 REVISION: 1 ATTENTION: SHALL BE MADE ONLY BY CAED P ,Nuclear, SALEM NUCLEAR GENERATING STATION SYSTEM: PRESSURIZER 1 REVISED PER ORDER No. 80008418. UNIT 1 - WELD IDENTIFICATION FIGURE LINE: N/A REV. DATE DESCRIPTION INSERVICE INSPECTION DRAWING THIRD 10 YEAR INSPECTION INTERVAL M 2000 PSEG Nuclear, LLC. Rights Reserved. AlI
O IPSEG ULTRASONIC EXAMINATION SCAN LIMITATION REPORT I ustomr. PSEG I Salem Unit i System: Pressurizer Summary No.: 007200 Component ID: 6-PRN-11044R8 Applicable Report No: UT-05-052, UT-05-053, UT-0504, UT-05-055 Reference Point:
- 1) Interfering Condition See Supplemental Report Distance From Centerline To Distance From Ref. Point To I I4 t I7 60.,(S to3o) 70. ,(5 to 21)
- 2) Interfering Condition Coverage% I 100% 50% 0%
Distance From Centerline To Total Exam Coverage: 66.7% Distance From Ref. Point To
- 3) Interfering Condition See Supplemental Report for Additional Information, Distance From Centerline To Distance From Ref. Point To (For All Measurements Indicate: US, DS, CW, CCW)
Sketch I Photo Of Limitation(s): AdamCon. 4 Customer:. John ONei Date: DOW:.
/11 Attachment A-3 46'.;1, Page2of4
0 PSEG Supplemental Report Report No.:, UT.05-055 Page: 15 of $4 Summary No,; .007200 Examiner: Flesher, Bret Level:* I-PDI Reviewer: Conti. Adam A Date;(4k Examiner: N/A Level: NIA Site Review: John O'Nelsz:: 0A Date. t Other: NIA Level: NIA At 11I Review: Date: Comments: I/ Component ID: 6-PRN-1104.1RS Applicable Spreadsheet Table: 7 Probe Angle Probe Skew .Scan Surface 45' 037 Bland 70* 1(5 to 21) vessel
'60'. *+/-(9 to30) Vessel Coverage Calculations:. 45' (+/-.37)
Limitation: None Coverage % Obtained: 100% Coverage Calculations: 70 :4(5 to 21) .Limitation: 1. Surface condition difficulties (Cast Head) were encountered throughout the examination due to surface grinding, surface pitting and surface waviness along the required scanning areas. Precise locations could not be recorded as these conditions are. numerous and Intermittent between probes and from Min R to Max R values. An estimate is that 50%0of the accessible .scanning area provided. adequate search unit contact. Coverage % Obtained: 50. 0% Coverape Calculations: 60' +/-(9 to 30) Limitation: 1. Surface condition difficulties (Cast Head)were encountered throughout the examination due to surface grinding, surface pitting and surface waviness along the required scanning areas. Precise locations could not be recorded as. these conditions are numerous and intermittent between probes and from Min R to Max.R values. An estimatelis.that 50%0 of the.accessible scannIng'area provided adequate search unit contact. Coverage % Obtained: 50% Total Combined Coverage: 66.7% Comments: Maintained 10% - 20% ID Clad Roll during all examinations. 45*S note: 2.0" of metal path delayed off screen to :display 2.0" to 7.0" of metal path on A-scan. 706S note: 5.0" of metaI path delayed off screen to display 5,0" to 15.0" of metal path on A-scan. 60°S note: 6.0' of metai path, delaved off screen to display 6.0" to 11.0" of metal path on A-scan. Attachment A-3 Page 3 of 4
urn vUUILUU -PRN-1 104-IRS Page 4 of 4
4-PRN-1100-IRS (RELIEF NOZZLE) Attachment A-4 4-PSN-1131-IRS (SPRAY NOZZLE) Page 1 of 4 Z/; MANWAY CIRCUMFERENTIAL LONGITUDINAL 1-PZR 1-PZR-20 6-PRN-1103-IRS (RELIEF NOZZLE) 1-PZR 6-PRN-1104-IRS (RELIEF NOZZLE) 1-PZR-18 1-PZR-17 - I-PZR-16 1-PZR 1-PZR-14 1-PZR 1-PZR-12 I-PZR ELEV. 105' I-PZR-10 1-PZR 1-PZR-8 1-PZR 1-PZR-6 I-PZR 1-PZR-4 1-PZR l-PZR-2 1-PZR-1 1-PZR-1VS
-- PRESSURIZER SURGE LINE 14-PSN-1131-IRS A-3052 231 A TTEN TION: SHALL ANY REVISON THIS BY TOONLY BE MA IDE CAED DRAWING PSEG uc le ar,LLC PS G Ncr LSY T FIGURE:
M PR A-3 SU I E REVISION: 1 SALEM NUCLEAR GENERATING STATION SYSTEM: PRESSURIZER 1 REVISED PER ORDER No. 80008418. UNIT 1 - WELD IDENTIFICATION FIGURE LINE: N/A REV. DATE DESCRIPTION INSERVICE INSPECTION DRAWING THIRD 10 YEAR INSPECTION INTERVAL 0 2000 PSEG Rights Reserved. Nuclear, LC. AlI
0 PSEG NitrlearLLC ULTRASONIC EXAMINATION SCAN LIMITATION REPORT ustomer: PSEG / Salem Unit I System: Pressurizer Summary No.: 007300 Component ID: 6-PRN-1105iRS __________ID:__-PRN-1_10_4RSUT.05-063 Applicable Report No: UT-05-060, UT-05-O61, UT-05-062 Reference Point:
- 1) Interfering Condition See Supplemental Report ------
Co4g % 1 00 50% 50% Distance From Centerline To Distance From Ref. Point To
- 2) Interfering Condition Total Exam Coverage: 66.7%
Distance From Centerline To Distance From Ref. Point TO See Supplemental Report for Additional Information.
- 3) Interfering Condition Distance From Centerline To Distance From Ref. Point To (For Al Measurements Indicate: US, DS, CW. CCW)
I I
C PSEG Supplemental Report Report No.:V UT-05-061 Page:- iS of 1 Summary NO.: 007300 Examiner, Fiesner, Bret .JLvel: ll-PDI Reviewer: .Conti,AdIam Da Ite: 616s Examiner NIA Levek N/A Site Review: John. O'Neil ,p ,,iDate; 4/0 r Other: NIA Level: N/A ANII Review: Date: 4 Comments: Component ID: 6oPRN-1105-IRS Applicable Spreadsheet Table: 7 Probe Angle Probe Skew Scan Surface 45* *37 Blend 700 +/-(5 to021) Vessel 600 k(9 to 30) Vessel Coverage-Calculations: 450 (*37) Limitation: None Coverage % Obtained: 100% . Coverage Calculations: 700 +/-(5 to 21) Limitation: 1. Permanently welded ID plate
- 2. Surface condition difficultiesl(Cast Head)were encountered throughout the examination .due to surface grinding, surface pitting and surface waviness along the required scanning areas. Precise locations could not be recorded as these conditions are numerous and Intermittent between probes and from MIn R to Max R values. An estimate Is that 50% of the accessible scanning area provided adequate search unit contact..
Coverage % Obtained: 50. 0% Coverage Calculations: 60- +/-(9 to 30) Limitation: 1. Surface conditiondifficultles (Cast Head) were encountered throughout the examination due to surface grinding, surface.pIttng .and surface waviness along the req ulred scanning aneas. Precise'locations could not be Irecorded as these conditions are numerous and Intermittent between probes and from Min R to Makx R values. An estimate is that 50% of the accessible scanning area provided adequate search unit contact. Coverage % Obtained: 50% Total Combined Coverage: 86.7% Comments: Maintained 10% - 20%iD Clad Roll during all examinations. 450S note: 2.0" of metal path delayed off screen to display,2.0" to 7.0" of metal path on A-scan. 70S note: 5.0" of metal path d elayd off screen to display 5.0",to 15.01' of metal path on A-scan. 600S note: 6.0" of metal path delayed offscr'een to display 6.0" to 11.0" of metal.path on A-scan. Attachment A-4 Page 3 of 4
ium 4 UU 730U
- -PRN-1 105-IRS mnent A-e4 of4
4-PRN-1100-IRS (RELIEF NOZZLE) Attachment A-5 77wY1 Page 1 of 4 CIRCUMFERENTIAL LONGITUDINAL I-PZR-21 - 1-PZR-20 X \\-PRN-1105-IRS (RELIEF NOZZLE) I-PZR-19 - 6-PRN-1103-IRS (RELIEF NOZZLE) 6-PRN-1104-IRS (RELIEF NOZZLE) 1-PZR-18 I-PZR 1-PZR-16 1-PZR 1-PZR-14 I-PZR I-PZR-12 1-PZR ELEV. 105' I-PZR-10 1-PZR 1-PZR-8 I-PZR 1-PZR-6 I-PZR I-PZR-4 1-PZR I-PZR-2 I-PZR-1 I-PZR-1VS
'-PRESSURIZER SURGE LINE 14-PSN-1131-IRS A-3052 231 ATTENTION:
ATTNTI N: AREVISON SHALL BE MADETOONLY THIS BYDRAWING CAED PSEG PSEG Nleruclear, LLCLSY FIGURE: T M A-3PR SU I E REVISION: 1 SALEM NUCLEAR GENERATING STATION SYSTEM: PRESSURIZER 1 REVISED PER ORDER No. 80008418. UNIT 1 - WELD IDENTIFICATION FIGURE LINE: N/A REV. DATE DESCRIPTION INSERVICE INSPECTION DRAWING THIRD 10 YEAR INSPECTION INTERVAL ( 2000 PSEG Nuclear, LLC, Rights Reserved. AII
Supple' ii Report W Su0EG Report No.: 3 UT-04O87 of 3 Page: Summary No.: 007400 Examiner: Examiner:WChapman, George '144f, Level: II Reviewer: M -) h ý .(-4 SD - Date: Examiner. NIA Level: NIA Site Review:. fAbaLjýý - - - Date: Other: NIA Level: NIA ANII Review: -/VS4ý4ý Date:~ 4 Comments: Ultrasonic Examination Scan Limitation Report (which only limits 700 transducer). Sketch or Photo: KNlDDEAL\Graphics\RFO1 6\UT-04-087b.jpg
-ULTRASONIC EXAMINATION SCAN LIMITATION REPORT AREA Customer PSEG Component: FlguweN°':
Weld No.: 4-PSN-11314RS Percent Of Exam Completed Reference Point Raised Lettering t
- 1) Interfering Condition Distance FromNozzle 6.51 To 12.5" Distance From Ref. Point 0 To 13"
- 2) Interferng Condition N/A obstruction is 13 x 0 area Distance From Centerifne NWA To NIA 13 x 6 - TV Obstructed Distance From Ref. Point N/A To N/A
- 3) Interlering Condition N/A 253 SfMS - 30.8% Obstructed Distance From Centerifne WA To N/A Distance From Ref. Point N/A To N/A Coverage achieved is calcutlated by O0. scan area that is obstructed.
Total coverge achieved with the 50V scan was 100% Total coverage achieved with the 70* scan was 69 2% (For All Meamsurements hendicate: USt CW CI84 hS, Total volume coverage lot the n~ozzle Is 84.6%
Attachment:
A-5] Page 2 of 4
Report Report No.: UT4I-087 07SM Page: 2 of 3 Summary No.: 007400 A . - Examiner: Chapman, George Level: II Reviewer: týkb Date: L Examiner. NIA Level: NIA Site Review: Date: -/oo Other: NIA Level: NIA ANII Review:. Date:__ _ _ Comments: Umitation Sketch Sketch or Photo: K-\IDDEALaGraphics\RF016\U-O4-87a~jpg
-SPtf4IV NOZZLE Attachment A-5 Page 3 of 4
~ui I I iftvUI +VU 4-PSN-1 131-IRS
Attachment A-6 1-BIT-VS-4 Page 1 of 4 1-BIT-VS-3 1-BIT-D 1-BIT-C HFAD 2 SHELI MATF'RIAI SA-264 (ASTM A-516 GR. 70 57 MIN.
- 1.4" CLAD CLADDINfl ASTM 1-240 (TYPE 304L) 16 - 2 1/2" STUDS-I-BIT-STUD 16 -2 1/2" NUTS CA] IRRATION ALOCKS TO BE DETERMINED 1-BIT-B i Sum #2044001-1-BIT-A-I L 1-BIT-i BUILDING: LOCATION: ELEVATIONS:
AUXILIARY I MECHANICAL 78, BORON INJECTION TANK PENETRATION
- __ ... .BIT ROOM ANY REVISION T6 TfHISDRWN , -- ......................
ATTENTION: SHALLBF ADE i %C E L B PSEG Nuclear, SALEM NUCLEAR LLC STATION GENERATING
-IFI[;IIRF. R-IL4R FlIf'"017: Q-101Q I RF-VI'£11N.
DcVicifIN: 1 1 SYSTEMs BOBON_ JJECILONTAINK LINE N------------------- 1 _ REVISED PER ORDER No. 80008418. UNIT 1 WELD IDENTIFICATION FIGURE RV. OATE_. ........ .............DESCRIPTION INSERVICE INSPECTION DRAWING I THIRD 10 YEAR INSPECTION INTERVAL 020l0P1*lti, I.I.C.11ll1iighs imt.
Attachment A-6] Page 2 of 4 ULTRASONIC EXAMINATION SCAN LIMITATION REPORT
,A FZ E \/Z L*brmer: Salem Component: 1-BIT-A SnFgure No.: .N/A .Weld No.: i-;BIT-A Percent Of Exam Completed:. 86.59% Coverage (Calculations OrComments Below)
Reference Point: 0* of Bit Tank. 00 =88.1%
- 1) Interfering Conditin 450 CW =88.1%
See Below Distance Fromn NA o N
- 450 CCW =88.=/0%
To N/A ,45. UPST =97.6% Centerline "_NA DistancePontN/A From Ref.N To N/A 450ý DNST =82.0% Point 60o OW =88.1 %
- 2) Interfering Condition N/A 600.CCW"88.1 %
Distance From N/A To N/A 60" UPST.=98.7% i Centerline istance From Ref. 60" DNST =56.0% Point
- 13) Interfering Condition N/A 0'.=88.1%
Distance From N/A TO N/A 450 =88.9% Centerline. 600 = 82,75% Distance From Ref.: N/A To N/A Point. N/A* (For Al. Measurements indicate: US, DS, CW, CCW)
- Sketch Of Limitation(s):
T .tExam Area*=6375x!79 =1 i41A25 otal weldLength = 179" (2) Taper Limitalion 179" Length (3) 1" Branch Limitation 2" Length 1-Bit-B
.(4). Support Leg Limitation 35, Length 1-Bit-A 1" Branch 1" Branch Connection Connection 4" above weld 4" above weld Center Line Center.Line Manway (iNCLUDED THE EXTENT OF% COMPLETEDOF EXAM AND REASON FOR LIMITED REPORT,AND SKE TCH.$HOWING AREA OF LIMI.TAAT7ON.)
Enrn~PT7,eorG han Date: 04-01-2010 Examiner: ,.Date: I i~wer: Frobert Kell~rhaii r Customer: Dave Mora
Attachment A-6 rpm ~~ IZt-4.-7ý5x 179:f-L&(I Page 3 of 4 1 cD-ThpER LPi.TArioij /w'Lizr,? oAAk I04?ZOY.'A1 I *LUI -N!oi M71W2 w;rI 6-4Ci4k11V& 601L4 SrtA--4604
~£Oebi o~J s5r~eAFf,: 7 75, reAA~5~7
Attachment A-6 Page 4 of 4 nu BIT-
Oo I-BIT-VS-4 Attachment A-7 Page 1 of 3 1-BIT-VS-3
.. 1-BIT-2 1-I- PPRHA -2.00" MIN. *1.4" CLAD 1-BIT-D
- UPPER HEA 1-BIT-C -
HFA') R SHII MATFRIAL SA-264 (ASTM A-516 AASHELL __ _-4.157" MIN. o 1.4" CLAD rLADDINC SEL ASTM 1-240 (TYPE 304L) 2 1/2" STUDS-I-BIT-STUD 16 2 1/2" NUTS CALIRRATION BLOCKS TO BE DETERMINED 2 Sum # 204410 1-BIT-A LOWER HEj 1-BIT-B /1 1-BIT-1 BUILDINGi LOCATION: ELEVATIONS: AUXILIARY MECHANICAL 78' BORON INJECTION TANK PENETRATION BIT ROOM ATTENTION: SHALLREVISION ANY BE TLADE TOONLTHIS Y OW RAWIN PSEG Nuclear, LLC I FIGURE: B-1aB I REVISION: L_ SALEM NUCLEAR GENERATING STATION SYSTEM: BOBONlJECILON_ 1 IV I
'I Hgy.___L DATE R~Vl~Pfl fUAILI E P~R CWnFR Ala RflflflR4lR PER OE lIF IN...........
oUESCRIPIIDN .............................. UNIT 1 - WELD IDENTIFICATION FIGURE LINE: bIZ - INSERVICE INSPECTION *DRAWING 1* THIRD 10 YEAR TI*)*INSPECTION INTERVAL D2 F3PGlo",, LL{:,All IRlI~SkI~e'1.....
U LTRASONIC EXAMINATION SCAN LIMITATION REPORT A ER E VIA Customer: Salem l Component: 1 BIT-ýB Figure No.: N/A Summary#204410 Weld No.: I-BIT-B Percent Of Exam Completed: 79.75% Coverage (Calculations Or Comments Below) Reference Point: 0 of Bit Tank. 04 UPST =80% Increase in coverage over previous
- 1) Interfering Condition See Below 00 DNST =80% exams (65%) duet removal of 45°cW =80%: insulation ring.
Distance From centriedine N/A To NIA
* ~45*
45° C= W =80%: Distance From Ref. Point N/A To N/A 45" 'UPST =80%
- 2) Interfering Condition NIA 450 DNST =80%
600 CW =80% Distance From Cent.rline N/A To N/A 600°CCW=80% Distance From Ref. Point N/A To N/A 60" UPST =80%
- 3) Interfering Condition NiA 60"'ONST =77%
Distance From Centerline NIA To N/A Distance From Ref. Point N/A To, N/A 0 800 45' = 80% (For All Measurements indicate: US, DS, -CW, CCW) 600= 79.25%0. Sketch Of Limitation(s):. Total weld Lengths= 1790 Each Support Obstruction= 8.75" x 4= 35" 'Aanway Obstruction= 6.0' for 60* only. Manway P 6 0 0____ 0 R R, R T 1800 T 90" 0 0T 270" (INCLUDED THE EXTENT OF% COMPLETED OF EXAM.AND REASON FOR LIMITED REPORT,AND SKETCH SHOWING AREA OF LIMITA"TiON.), Examiner Ge rge G,. C apm an Date: 04-01-2010- Exami..ne:. Dat: Reviewer. abe 11 hall Date: stoae: Dave Mora8f Date:; Page Sof 8 Attachment A-7I Page 2 of 3
C 10 C 96ed~ L-V IUESw~llSV]
Attachment A-8 Page 1 of 3 CVCT-1 (L, = CENTERLINE OF MANWAY)
-WELD 1-CVCT-2VS-1 (TYP FOR 1-CVCT-2VS-3, 5, 7)
~F~-1-CVCT-MWY-BDLTS WELD DETAIL WELD DETAIL 1-CVCT-2VS-4 I-CVCT-2VS PL-SS-.250-97-SAM (VESSEL SHELL) 1.125-8-N-CS-101-SAM (NUTS) 1.125-8-B-CS-107-SAM (BOLTS)
CHEMICAL AND VOLUME CONTROL TANK BUILDING: LOCATION: ELEVATIONS: AUXILIARY CVCT ROOM 122' ATTENTION: SHALL BE MADETOONLY ANY REVISON THIS BY CAEDPSGNlerLL DRAWING SALEM NUCLEARPSEG Nuclear, LLC GENERATING STATION FIGURE: B-2 7 REVISION: 1 SYSTEM: CHEMICAL AND VOLUME CONTROL TANK 1 REVISED PER ORDER No. 80008418. UNIT 1 - WELD IDENTIFICATION FIGURE LINE: N/A REV. DATE DESCRIPTION INSERVICE INSPECTION DRAWING THIRD 10 YEAR INSPECTION INTERVAL
© 2000 PSEG Nuclear , LC.AlIRights Reserved.
Attachment A-8 2 ofage 3 Supplemental Report OPSEG Report No.i UT-08-065 Page::. 6 of 6 1imary No.' 204800 Sketch or Photo:: MAShaired\Outage Serces'6NDE ServicesV.Salem I\Sdlemn 1 RFO-1 §\Areva\Sedtion XI Datisheetsm24800\revious Outage Data Reporftage 3.jpg, UT COVERAGE PLOT 2 7 ZS . T-R. c:,Fkvrn 81-6% we:Lp~e~m upp~owvrs
*I 10 JO F'A L 6 ,S-uc-rioLV 8&F Vamdcor', PAWT,(LU4G~,e&ov5E No. :10 0.9 11 ý SLMM:Ry NO.* aLi 0,P WELD:
PAP E _.Lo -OF,
lEt 04r~ S ~ nETAlL~r
'Mot.
1,110 flel IspliYI snamI CL. UUXI* ILL 74 L tpxEN
.11 Us"1ISn011f HO)M '"%AVOis ftfanl 65304
=,=k.10 tM00OM.
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40104*11 301340 51*.W3.4 051 1-61. In kIlt 011Th
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.01114 won.twc MMo.*In00,1114q1011 w341110 04U0VJ0 -~ -~
- .'ei r ifl*I0.P*LCA 3 1t11 Us0.
, lC ,
(1114400)4*1044044)01mm 4450ta. Sol. 5111410 0.50, rus tw L Wn V4 MIIICI*15SAM*30WO41011 K A43 MW In4*tk I43IIM 134 1)4 3033 140 30011144*.letot ak"- I U aw6m l0assimI14111114I
&WIMA0 511 SWAM V01115111 "I@ 1410501)0 itwo401404.0 QA" loft s 5074010*0 movies.'
-* -= 0, " 61;*. n-* - '
APtachment A-Page 1 of 5 1CVE18-VS-TOP VIEW
\
Sum # 511506 1CVE-1 8-SWIJ-1 1CVEIB-SWIJ-2
~I--
ELEVATION BUILDING: LOCATION: ELEVATION: AUXILIARY SEAL WATER 84' INJECTION FILTER SEAL WATER INJECTION FILTER ROOM
- ANY REVISION TO THIS DRAWING FIGURE: B-6-1 REVISION: 0 ATTENTION: SHALL BE ADE ONLY BY CAED PSEG Nuclear, LLC SALEM NUCLEAR GENERATING STATION SYSTEM: M8 SEAL WTER INJECTION FILTER 0 ORIGINAL ISSUE PER ORDER No. 80008418. UNIT 1 - WELD IDENTIFICATION FIGURE LINE: N/A REV. DATE DESCRIPTION INSERVICE INSPECTION DRAWING THIRD 10 YEAR INSPECTION INTERVAL Nuclear, LLC.All Rights Reserved.
(D 2000 PSEIG
Report Report No.: UT-04-014 0OPMG Page: 2 of 2 Summary No.: 511506 Examiner. Chapman, George 'WIC Level: II Reviewer: Date: '6dt*4 Examiner N/A Level: NIA Site Review:. Date: 7- 4 -a Other N/A Level: N/A ANII Review. it~j Date: /,(1," Comments: Ultrasonic Examination Scan Limitation Report Sketch or Photo: K-\IDOEALXGraphics'\RF016\UT-04-014.jpg A " IULTRASONIC EXAMINATION SCAN UMITATION REPORT ARE \f A Customer PSEG Component se Wae FigurtIe No.: Filter Flange to Shell Weld Weld No.: ICVE14-SWIJ-1 Percent Of Exam Completed (Cakulaffor Or Corjemnts Belov4 Reference Point 0" 34WWeld Length 100% Coverage 281.52" Flange 2 W Width
- 1) Interfering Condition W.90 Weld Height
*Distance Fromn Centerline 1.r To uz 34" Weld Length 45° Obstructed due to Flange Ax Distance From Ref. Point 0 To 34" .5" Weld Height 70.38" Looking DS
- 2) Interfering Condition Welded Attachment .4" Weld Width 6.8' Looldng US 77.18 Total Distance From Centerline 0 To 4* 3.25" Weld Length Obstructed DuetoAttachment Distance From Ref. Point 4" To 7.25 .90"Weld Height Ax & Cir
- 3) ntererng Condition IIDPlate 2.30" Weld Width 6.272 x 4 25.08" 4.00" Weld Length Obstructed Due to ID Tag Distance Prom Centerline 1.85 To 4"*Wl eih xOl V5 Weld Height Ax Only Distance From Ref. Point 12" To 16" .7" Weld Width 1.4" 77.18 63.170 Coverage Achieved 25.08 CCW) 2.0 (For All Measurements Indicate: US, OS, CW, 103.66 Total Obstructed Attachment A-9 Page 2 of 5 1
J PG Report Report No.: Page: 2 UT-04-015 of 3 Summary No.: 511506 Examiner Chapman, George A,4.f Level: it Reviewer: Date: Examiner NA Level: NIA Site Review: Date: Other. NJA Level: WA ANU Review: Date:$ Comments: Weld Profile & Thickness Report Sketch or Photo: K:\lDDEALra~phics\RF016\UT..O4-015a.jpg 742 q I' S94% 1. Attachment A-9 Page 3 of 5
0 Suppi Report Report No.: Page: 3 UT-04-015 of 3 Summary No.: 511506 Examiner Chapman, George Level: II Reviewer-. Examiner NWA Level: NIA Site Review: Other. WA Level: NWA ANII Review: Comments: Ultrasonic Examination Scan Limitation Report Sketch or Photo: K:)JODEAL1GraphicsIRF0l86UT.04-015b.jpg ULTRASONIC EXAMINATION SCAN LIMITATION REPORT A R E VA c Component Seal Water Injection Figure No.:
,IFilter Flange to Shell Weld Percent Of Exam Compileed Weld No,: ICVE18*SWIJ-1 (Caculatiom Or Conenents Below)
Reference Point 00 34" Weld Length Flange 123R Weld Width Single Side Exam 1)stnte FromCentertion FTo us .90" Weld Height 100% - 70.38* Distance From CentePine 1.2" TO 4 .4" Weld Height 10.88" Obstructed dueto Flange Distance From Ref. Point 0 To 34" ." Weld Width *
- 2) Interfering Condition Welded Attachment 34V Weld Length Distance From Centerline 0 To 4" 3.2" Weld Length 8.727" Obstructed Due to
.90" Weld Height Attachment Distance From Re.L Point 4" To 7.25 2.30" Weld Width
- 3) Interfering Condition I0 Plate 4" Weld Length 2.,4" Obstructed due to tD Plate Distance From Centefne 185 To 4" .4" Weld Height Dlstn*e From Ref. Point 12" To 16" 1.5" Weld Wikh 56.3% Coverage Achieved 20.0 Total Obstructed due to Single Side Exam (For All Measurements Indicate: US, OS, OW, COW)
Attachment A-9 Page 4 of 5
OW Supplem Report Report No.: LJT-04-13 Page: 2 of 2 Summary No.: 511506 ^ I Examiner. Chapman, George Level: Level: II VA Reviewer: Site Review: Ný&L&Lw 7i)71 1L Date: Date: 4-k.A Examiner. NIA Other. MA Level: NIA ANII Review: -7T;7-'zý- 6
;4j f -
Date: Comments: ULmitation Sketch Sketch or Photo: K-iODEAL\GraphicsRFO16\UT-04-13.jpg PjArE Attachment A-91 Page 5 of 5
Attachment A-1i Page 1 of 3 1CVEIB-VS-TOP VIEW
-SWIJ-I BUILDING: LOCATION: ELEVATION:
AUXILIARY SEAL WATER 84' INJECTION FILTER ROOM ATTENTION. ANY REVISON SHALL BE MADETOONLYTHIS BY DRAWING CAEDPSGNcerLC SALEM PSEG Nuclear, NUCLEAR LLC STATION GENERATING FIGURE: B--1 I REVISION: 0 SYSTEM: 418 SEAL WATER INJECTION FILTER 0 ORIGINAL ISSUE PER ORDER No. 80008418. UNIT 1- WELD IDENTIFICATION FIGURE LINE: N/A REV. DATE DESCRIPTION INSERVICE INSPECTION DRAWING THIRD 10 YEAR INSPECTION INTERVAL 2000 PSEG (C) Nuclear,/ [C. AlI Rights Reserved.
Supplem Report OIFiG Report No.: Page: 4 UT-04-017 of 4 Summary No.: 511507 Examiner: Chapman, George cC.- Level: Level:
!1 NIA Reviewer Site Review:
(bJ-oL~ Date: Examiner:. NA Other:. NIA Level: WA ANII Review: Date: Comments: Ultrasonic Examination Scan Limitation Report Sketch or Photo: K:XIDDEALIGraphics'RFO16kUT-O4-17b.jpg pULTRASONIC EXAMINATION SCAN UMITATION REPORT A ag E VA Custome PSEG Compone: sl Wer Injection Figure Na: Filter Shell to Lower Head Weld Weld No.: 1CVE18-SWIJ-2 Percent Of Exam Completed (Cwlcuaions Or Coament Reew) Refetence Point V 34- Weld Length 100% Coverage - 288.552 2.16" Weld Width IntegralAttimhnent 296"Weld Height
- 1) tnterfering Condition Distance From Centerlgne 0 To 2.15" OBSTRUCTED Distance Frot Ref. Point 3.25" To 7-25" 12.2b" Weld Length 103243" Obstructed -36.02%
- 2) Interfering Condition Integral Attachment 2.15" Weld Width Distance From Centedine 0 To 2.15" g9" Weld Height Distance From Ref Point 14" T 18" 84% Coverage Achieved
- 3) Interfering Condition Integral Attachment Distance From Centerflne 0 To 2.15" Distance From Ref. Point 26" To 30.25" (For ADlMeasurements Indicate: US. DS, CW, CCW)
Attachment A-10 Page 2 of 3
U I Report 4 Report No.: UT-04-016 Page: 2 of 2 Summary No.: 511507 Examiner. Chapman, George Level: I! Reviewer ~\2ýj0u Sca Date: Examiner /A . Level: WA Site Review: Date: e/o Other N/A Level:. NWA ANII Review: Date:4 4 Comments: LUmitation Sketch" Unable to scan on either side of the weld in areas of welded attachments. Sketch or Photo: l(MDOEALXGraphicsRF016XUTO04-016.jpg
+
I I i .. m I I I iv " S II It I SX14L*t __it I I___ 11 1 40mr-4 4446 a ______________________________ i Attachment A-10 Page 3 of 3
Attachment A-1 1 Page 1 of 4 z
"*,X*.,* *SECTION, 32-MSN-2111-IRS 32-MISN-2111-1 11-STG-24: TRANSITION AT 2700 VIEW --3 SHELL SECTION 0
- 111 RCN 3 1-
,7 SHELL SECTION UIz11-STG-22*
UTLET MANWAY 11-STG-21 STUB BARREL [11-S TG-1iT, I A2
'IEW ;12. TUBE ýSHEE T I[EW STEAM GENERATOR NO. 11 WESTINGHOUSE SERIES "F" S/
S/N#2174 IMPORTANT: THIS OWG IS FOR IDENTIFYING ISI/PSI WELD IO's ONLY. THIS DWG REPRESENTS THE SERIES '51' NOT THE SERIES 'F' S/G. ATTENTION: ANY SHALLREVISON BE MADETOONLY THIS BY DRAWING CAED S NUCLEAPSEG Nuclear, LLC FIGURE: A-4 SYSTEM: STEAM I REVISION: GENERATOR 2 No. 11 2 REVISED PER ORDER No. 80008418. SALEM NUCLEAR GENERATING STATION REVISED DWG TO REFERENCE UNIT 1 - WELD IDENTIFICATION FIGURE LINE: N/A 1 1/19/98 NEW REPLACEMENT S/G's.I TIRN/ 1 A REV. DATE DESCRIPTION INSERVICE INSPECTION DRAWING THIRD 10 YEAR INSPECTION INTERVAL (D2000 PSEG Nuclear, LLC.All Rights Reserved.
Attachment A-i 1
@ PSEG SUPPlemrenftf Report Report No.:
Page 2of 4 MT.40-O00i Page: 2 of 5 Summary No.:' 204001: Examinec Med22 Paulo el:' il Reviewer:: Mora,-.David. Level 11 Date: 3/ Examiner: N/A Level: N/A, Site, Review: Giles, Tim Dater:
- Other* N/A Level: N/A ANI I Review.: Howlett, Aro ~L ate:
Corn nent's:1 Limitations SWeth or Photo: Mn~hared~oitage Services\NDE ServMeUSaliemVSalem VIaaIem 1r2OUIDDEAL\UT Exam T&CsQ0400i\2O04O0I-Scan II pg
$RrACE CXAMINATIONCOVERAGE RP3PORT CUSTOME.StA 3NfATf jEiC5 R EXAM~NA'r1oti GFM10tExmtJ411m Area Vma3Ul X VMW AI) 1S X,2I.73n .3O 4 2.9~.7 O 3(~hN ALCVLAT sRA A. x ,
(Die aum tAmu:, A +C 0 -Ap) 361 Catc*A PMORMe ofAiahIOA9Exx%*n1I0 (l3Oi , datp y_____________ area Ih~thd Ly inafJwfo~fiD.
Agr Sum # 204001 16-BFN-21 11 -1 Nozzle to Shell 4?' M: 4 Ik AO W
-wa 1ý1
icnment A-lI Page 4 of 4
Attachment A-12 Page 1 of 9 16-BFN-2111
-MANWAY IMPORTANT: THIS OWG IS FOR IDENTIFYING ISI/PSI WELD ID's ONLY.
THIS DWG REPRESENTS THE SERIES '51" NOT THE SERIES "F" S/G. ATTENTION: ANY SHALLREVISION BE MADETOONLY THIS BY DRAWING CAED PSEG Nuclear, LLC SYSTEM: A-4 FIGURE: STEAM REVISION: GENERTOR 2 No. 11 2 REVISED PER ORDER No. 80008418. SALEM NUCLEAR GENERATING STATION REVISED DWG TO REFERENCE UNIT 1- WELD IDENTIFICATION FIGURE N/A 1 1/19/98 NEW REPLACEMENT S/G's. LINE: N EA REV. DATE DESCRIPTION INSERVICE INSPECTION DRAWING THIRD 10 YEAR INSPECTION INTERVAL 0 2000 PSEG Nuclear, LLC. All Rights Reserved.
Attachment A-12 Page 2 of 9 Supplemental Report
.0PSEG Report No-: UT-10-046 Page: 4 of 6 Sumimary No.: 204001 'Examiner: Jasken, Richard Level: i-PDI" Reviewer' Mora, David Level Ii * " Date:
E an,. .* .: . 'S ite,*R eview: es..,t.i m , .D ae . Ot~,, t!aII Lrke 1 III-~Tp ANIL Review:Dtv/s.
>'Ycrments: I, I Co Imments ArtIle 45- ,_,I Dynhamic scan performed on'callbration reflectors at scanning speed & sensitV.iti. ID Notch 8Q% 36.2dB. rk.,
Material Type: CS SDCN# 30-9135200-000. No change since last examination. Coveragetakeh from previous data. ,Comments Angle 60: F Dynamic scan performed on calibration reflectors at scanning speed & sensitivity. ID Notch 80% 54,3dB. Material Type: Cs SDCN#30,91335200-000. No change since last examination. Coverage taken from previous data. Comments Angle 0: Dynamic scan performed on calibration reflectors at scanning speed & sensitivity. BW 80% 5.2dB. Material Type: CS SDCN# 30-9135200-000. No change since last examination. Coverage taken from previous data.
[FTVESS-V0LRP 07M61.00 F MATOMEzA VESSEL VOLUMETRIC EXAMINATION COVERAGE REPORT A CUSTOMER: SYSTEM: SALEM 1. RFO-1 4 STEAM GENERATOR. 1
SUMMARY
NO: COMPONENTID: 204001 16-BFNW21 11-1 1.0 CALCULATE REQUIRED EXAM VOLUME FOR STRAIGHT BEAM PLANAR FLAWS 1.1 1.33 :X 2.25 X 109.00 = .326.18 cu.in Exam Height X Exam Width X Exam Length = Exam 2.0 CALCULATE'REQUIRED EXAM VOLUME FOR STRAIGHT BEAM LAMINAR FLAWS X X cu.in 2.1 Exam Height X Exam Width X Exam Length= Examh 3.0 CALCULATE REQUIRED PARALLEL EXAM VOLUME FOR 450 AND 600
- 3.1 Exa~m:Height X Exam Width X Examh.Length = Exam 1 .33 X :2.25 X 109.o0 = 326.18 cu.in 4.0 :CALCULATE REQUIRED TRANSVERSE EXAM VOLUME FOR 450 AND 600 1.33 X 2.25:X 10900 = :326.18 cu.in 4.1 Exam Height X Exam Width X Exam Length, Exam 15.0 CALCULATE STRAIGHT BEAM PLANAR EXAM COVERAGE 5.1 Limited above / CW exam volume Height of Width of. Length of Volumewith~no Obstructed Volume Obstructed Area Obstructed Area Exam Coverage 2,25 X 16 ,47.88
.133 X -
5.2 Limited Below I CW exam volume. Height of 'Width:0f Length of Volume with no Obstructed Volume Obstructed Area Obstructed Area Exam Cowverage 1.33 X 2,25 X 16.00 , 47.88 Total.straight beam planar-exam ivoludme not examined 95.76 5.3 Percent Volume;Examined Total 0 vol Total 0 PercentVolume w/No Coverage Exam Volume Examined 100- H9576 326.18 ] xX 100} = 70.64 % Attachment A-12 1 1 Page 3 of 9
riFVESS.VOLAP 07115100 VESSEL VOLUMETRIC EXAMINATION COVERAGE REPORT I 6.0 CALCULATE STRAIGHT BEAM LAMINAR EXAM COVERAGE 6.1 Limited above / cW exam volume Height of' Width of Length of Volume with no Obstructed Volume Obstructed.Area Obstructed Area Exam Coverage X X = 6.2 Limited Below /.CW. exam volume Height of .Width. of Length of Volumewith no Obstructed Volume Obstructed Area Obstructed Area Exam Coverage X X = Total straight beam planar exam volume not examined 6.3 Percent Volume Examined Total 0o v01 Total 0o ýPercent Volume w/No Coverage Exam Volume. Examined 100- / ] :X 100. = 7.0 CALCULATE PARALLEL 450 EXAM COVERAGE 7.1 Limited above /c W exam volume Height of Width of Lengthof: Volume with no Obstructed Volume Obstructed Area Obstructed Area Exam Coverage 16.00 1.33 X 2.25 X 47.88
*7.2 Limited Below ICOW exam volume Lenghthof Height of Width of Volumewith no 1bstructed Volume Obstructed Area. Exam Coverage Obstructed Area:
1.33 X 2.25, X 16.00 47.88 95.76; Total 450 pai*alel exam .voumenot examined 7.3 Percent VoIume Examined, Percent Volume Total 450 parallel Total .450'p arallel vol w/No Coverage Exam Volu me Examined 100- { 95.76 1 326.1.8 i x 1001 = 70.64 % Attachment A-12 Page 4 of 9
V O§SyO.F qp O7)16/0 Fu1 VESSEL VOLUMETRIC EXAMINATION COVERAGE REPORT AMV r 8.0 CALCULATE PARALLEL '600 EXAM COVERAGE 8.1 Limited above /CW exam volumem Above / CW exam Height of Width of Length:of Vol.mewith no Obstructed Volume Obstructed Area Obstructed Area Exam Coverage 1..'33 X 2.25 X 16.00 = 47,88 8.2 Limited Below I CCW exam volumeý Below /CCW exam Height of Width of Length of Volume with no Obstructed'Volume Obstructed Area Obstructed Area. Exam Coverage 1M33 X 2.25 X 16.00 -
,47.88 Total 60* parallel exam 'volume not examined 95.76 8.3 Percent Volume Examined Total 60, parallel Total 600 parallel Percent Volume Vol w/No Coverage Exam Volume .Examiied 100- 95.76 1 326.18 ] x 100} = 7064 %
9.0 CALCULATE TRANSVERSE 450 EXAM COVERAGE 9.1 Limited Clockise exam volume CW Exam Height of: Width of Length.of Volume with no ObstructedVolume Obstructed Area Obstructed Area Exam Coverage 1.33 X 2.25 X 16.00 47.88 9,2 Limited Below Counter clockwise exam volume CCW Exam Height of Width of Length of Volumewith no Obbstructed Volume obstructed Area Obstructed Area ,Exam ,Coverage 1331 X 2.25 X 16.00 = 470.88 Total 450triansverse exam vol'urme nnotexamined 195.76 9.3 Percent Volume Examined Percent Volume' total 450 parallel Total.450 parallel Exam Volume Examined 100 {[ ' 95.76 / 326.18 . x .00} = 70.64 % I Attachment A-12
'Attachment Page 5 o-12f of 99 I ,.k..
FTI VESSLVOLFSP 0.715o1 5 FJ;,AMAT* .N : VESSEL VOLUMETRIC EXAMINATION COVERAGE REPORT 10.0 CALCULATE TRANSVERSE 600 EXAM COVERAGE 10,1 Limited Clockwi.se. exam Volume C W exam: Height of Width of Length of Volumewith no Obstructed Volume Obstructed Area Obstructed Area Exam Coverage 1.33 ) 2.25 X 16.00 = "47.88 10.2 Limited CounterclockwIse exam volume CCW.exam Height of Width of Length of Volume With-no Area Obstructed Volume Obstructed Area Obstructed Exam Coverage x 166.00 1.33 C 2.25 = 47.88 Total 60tiransverse exam volumnenot examined -= 95.76 1.0i3 Percent.Volume Examined Total 600 Trans Vol Total .600 Trans Percent Volume w/NoCoverage Exam Volume Examined 100o- {1 ,95.76 I 326.18 x 100} %70.64 % 11.0 CALCULATE PERCENT'OF TOTAL VOLUME EXAMINED 11.1 Sum of Exam Volumes % Steps 5 Thur. 10 No- Of Exams (6) Examination Coverage r 351.21 5.00 = 70.64 % Limited due to insulation support ring on shell side. Examiner: George chapman Level: II .D101 Reviewer: Level:ae:
,~
Sign:Sgn \ 3 Attachment A-12 Page 6 of 9 01
Attachment A-12 Page 7 of 9 Supplemental Report
.0PSEG Report No.: .UT-.0-046 Page: 6, of 6 surmmary No.: 204001 2
Examiner: Jasken, Richard - Level: iI-PDI Reviewer Mora, David Level II o // 'hDate: 1Vi0 Examn& eIr: .Steinbauer; y&11vel: I-PDi Site Review. Giles, Tim Date: other', Kft all,02Rn Levet: IU4IDI A~N Revew. 4 &Atbs Oate: D-~Ste ____ Comments:: Coverage Plot Sketch or Photo: M:\Shared\Outage ServicesMNDE Service\lSaMem\ISaleam e ~atr2MOVDIEAL\UT Exam T&C20400t1\U\2.0400t-2jjpg
*J*";*" I**J'*ft ! I'age4 o Sum #204001 16-BFN-21 11 -1 Nozzle to Shell Z
-. ... d i Z+
P:age1 1I I It9 9 - I Page 9 of 9
Attachment A-13 Page 1 of 7 1-BIT-VS-4 1-BIT-VS-i 1 -MANIWAY 1-BIT-VS-3 1-BIT-VS-2 I" MIN.
- 1.4" CLAD 1-BIT-D I-BIT-C HFAD & SHFLL MATFRIAL SA-264 (ASTM A-516 GR. 70 4.157" MIN.
- 1.4" CLAD CLADDINfl 16 - 2 1/2" STUDS-I-BIT-STUD ASTM 1-240 (TYPE 304L) 16 - 2 1/2" NUTS CALIBRATION RLOCKS TO BE DETERMINED 1-BIT-B 1-BIT-A BUILDING. LOCATION: ELEVATIONS: i1, -
AUXILIARY MECHANICAL 78' BORON INJECTION TANK PENETRATION SIT ROOM . ANY R VISION TO THIS DRAW ATTENTION: SHALL%... MADE . .....ONLY BY CAE8 PSEG Nuclear, LLC FIGURE: B-108 SYSTEM, I ON- ]'ANK L B0BObI_ L.lJ E CREVISION: -------
- . SALEM NUCLEAR GENERATING STATION S.STE.. - 00 L-JE---------- -
1 / _ REVISED PER ORDER No. 80006415 UNIT 1 - WELD IDENTIFICATION FIGURE LINE: NZA .... RE.IDATE I.. . DESCRIPTION ... INSERVICE INSPECTION DRAWING THIRD 10 YEAR INSPECTION INTERVAL 2M PSIGLCIm'. LIC. AllI iOIS heWvd.
FF WI FXW,, FOrflo ,, 44 fEXAMINATION
SUMMARY
M MAIQ MANP
' MARY NO: 204440 DATA PACKAGEND: SIR15DP044 DATE: Oct 25 2002 SITE: SALEM 1, RFO-15 EXAMINAWr UT, MT METHOD:
SYSTEM I EXAMINATION PROCEDURES: COMPONENT ID. 1-BIT-I COMPONEN INLET NOZZLE TO SHELL 54-ISI-130-38 DESCRIPTION T EXAMINATION C2.21 54-ISI-270-41 CATEGORY, ISO 1DRAWNG: B-108 CA*IBRATION 00025 SHEET NO(S): 00026 00027 EXAMINATION M No Reportable Indications RESULTS: Reportable Indications Geometric A UT AND PT EXAMINATION WAS PERFORMED ON INLET NOZZLE TO SHELL, 1-BIT-1. THE ULTRASONIC EXAMINATION WAS PERFORMED WITH NO REPORTABLE INDICATIONS. THE EXAMINATION WAS MITED TO A TOTAL CODE COVERAGE OF 43.43%. NO SCAN FROM NOZZLE SIDE OR ON WELD DUE TO NFIGURATION. THE MAGNETIC PARTICLE EXAMINATION WAS PERFORMED WITH NO REPORTABLE INDICATIONS AND NO LIMITATIONS. THE CURRENT EXAMINATION RESULTS WERE COMPARED WITH THE PREVIOUS EXAMINATION DATA AND NO CHANGES WERE NOTED. PREVIOUS T'S AND C'S ATTACHED. FACTORY MUTUAL INSURANCE COMPANY 4 ST: Date, Do:Util Review By: Date:/ )-,(O - / Attachment A-13 Page 2 of 7
2fT VAd .OOL.,FRP 4TI[
*L FRAMAT ME ANP VESSEL VOLUMETRIC EXAMINATION COVERAGE REPORT I EU8TOMER:
SALEM 1, RFO 15 SYSTEM: BIT
SUMMARY
NO: 204440I COMPONENT 10: 1-BIT-1 20444 1 1 -BT-1.0 CALCULATE REQUIRED EXAM VOLUME FOR TRAI GHT BREA PLANAR FLAWS 0.75 X 2.13X 34.00 = 54.32 c.in 1.1 Exam Height X Exam Width X Exam Length = Exam 2.0 CALCULATE REQUIRIED EXAM VOLUME FOR TA IGHT BEAM LAMINAR FLAWS X X cu.in 2.1 Exam Height X Exam Width X Exam Length - Exam J ll IIII i 3.0 CALCULATE REQUIRED PARALLEL EXAM VOLUME FOR 45° AND 60' 0.75 X 2.13 X 68.00 = 108.63 culn 3.1 Exam Height X Exam Width X Exam Length - Exam 4.0 CALCULATE RFOUIREO TRANSVERSE PXAM VOLUME FOR "0 AND 600 i 4 4.1 Exam Height X Exam Width X Exam Length = Exam 0.75 X 2.13 X 6800 = 108.63 cW.in 6.0 CALCULATE STRAIGHT BEAM PLANAR EXAM COVERAGE 5.1 Limited above / CW exam volume Height of Width of Length of Volume with no Obstructed Volume Obstructed Area Obstructed Area Exam Coverage 0.76 X 1.63 X 34.00 = 41.57 5.2 Limited Below / CW exam volume Height of Width of Length of Volumewith no Obstructed Volume Obstructed Area Obstructed Area Exam Coverage 0.00 X 0.00 X 0.00 = 0.00 Total straight beam planar exam volume not examined - 41.57 5.3 Percent Volume Examined Total 0 vol Total 0 Percent Volume w/No Coverage Exam Volume Examined 100 - (E 41.57 54.32 x 100) X - 23.47 % Attachment A-13 Page 3 of 7 (4q\
Fr- VEssVOLFRP 07*Mo 4,
*RAANP VESSEL VOLUMETRIC EXAMINATION COVERAGE REPORT mu q F0.0 CALCULATE STRAIGHT BEAM LAMINAR EXAM COVERAGE 6.1 Limited above / CW exam volume Height of Width of Length of Volume with no Obstructed Volume Obstructed Area Obstructed Area Exam Coverage X X =
6.2 Limited Below I CW exam volume Height of Width of Length of Volume with no Obstructed Volume Obstructed Area Obstructed Area Exam Coverage X X = Total straight beam planar exam volume not examined = 6.3 Percent Volume Examined Total 0° vol Total 0° Percent Volume w/No Coverage Exam Volume Examined E 100-{[ x 100) = CAL CIJLATF: PAR AL i= S5XAM CAVPRAAE; 4Fl 7.0 7.1 Limited above / CW exam volume Height of Width of Length of Volumewith no Obstructed Volume Obstructed Area Obstructed Area Exam Coverage 0.75 X 2.13 X 34.00 54.32 7.2 Limited Below i CCW exam volume Length of Height of Width of Volumewith no Obstructed Volume Obstructed Area Obstructed Area Exam Coverage 0.75 X 0.25 X 34.00 6.38 Total 450 parallel exam volume not examined 60.69 7.3 Percent Volume Examined Total 45° parallel Total 450 arallel Percent Volume vol wiNo Coverage Exam Volu me Examined 100 - C 60.69 1 108o.3 L J x 100) = 44.13 % [ Attachment A-13 Page 4 of 7
Fri WES8VOL MW 7Rn&@4 FVRA ATOME ANPpVESSEL VOLUMETRIC EXAMINATION COVERAGE REPORT -U I F 8.0 CALCULATE PARALLEL W EXAM COVERAGE 8.1 Limited above / CW exam volume Above I CW exam Height of Width of Length of Volume with no Obstructed Volume Obstructed Area Obstructed Area Exam Coverage 0.75 X 2.13 X 34.00 = 54.32 8.2 Limited Below I CCW exam volume Below / CCW exam Height of Width of Length of Volume with no Exam Coverage Obstructed Volume Obstructed Area Obstructed Area 0.00 X 0.00 X 0.00 = 0.00 Total 60° parallel exam volume not examined 54.32 8.3 Percent Volume Examined Total 60° parallel Total 600 parallel Percent Volume Vol w/No Coverage Exam Volume Examined E 100- 54.32 I 108.63 1 x 100) = 50.00 % 9.0 CALCULATE TRANSVERSE 465 EXAM COVERAGE 9.1 Limited Clockwise exam volume CW Exam Height of Width of Length of Volumewith no Obstructed Volume Obstructed Area Obstructed Area Exam Coverage 0.75 X 1.07 X 34.00 = 27.29 9.2 Limited Below Counter clockwise exam volume CCW Exam Height of Width of Length of Volumewith no Obstructed Volume Obstructed Area Obstructed Area Exam Coverage 0.75 X 1.07 X 34.00 27.29 Total 450 transverse exam volume not examined 54.57 9.3 Percent Volume Examined Total 450 parallel Total 45° parallel Percent Volume Exam Volume Examined 100 {[ 54.57 1 108.63 ] x 100) = 49.77 % Attachment A-13 Page 5 of 7f /LI
Attachment A-13 '= f Page 6 of 7 ! T FnvEss.vOLJRP ofl;8wo
/FRAMAT0ME ANP VESSEL VOLUMETRIC EXAMINATION COVERAGE REPORT BE -
U 10.0 CALCULATE TRAN8aVERSE.60' EXAM COVERAGE 10.1 Limited Clockwise exam volume CW exam Height of Width of Length of Volume with no Obstructed Volume Obstructed Area Obstructed Area Exam Coverage 0.75 X 1.07 X 34.00 27.29 10.2 Limited Counterclockwise exam volume CCW exam Height of Width of Length of Volumewith no Obstructed Volume Obstructed Area Obstructed Area Exam Coverage 0.75 X 1.07 X 34.00 - 27.29 Total 60 transverse exam volume not examined 54.57 10.3 Percent Volume Examined Percent Volume Total 60' Trans Vol Total 600 Trans w/NoCoverage Exam Volume Examined 100 {[ 54.57 . 108.63 X 100) 49.77 % 11.0 -CALCULATEPERCENT OF TOTAL VOLUAME EXAMINED 11.1 Sum of Exam Volumes % Steps 5 Thur 10 No. Of Exams (6) Examination Coverage [ 217.14 1 5.00 ] - 43.43 % No scan from nozzle side or on weld due to configuration. Examiner, GEORGE 0. CHAPMAN Level: U Valee: Reate: 0:1 sip: 4& 4 ,ý I ~ FACTORY MUTUAL IJ4URANCE COMPANY
-o z.
I C- Attachmen Page 7
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Ij Attachment A-14 Page 1 of 5 2.00" MIN.
- 1.4" CLAD 1-BIT-D 1-BIT-C HEArD P, HFI I MATFRIAI SA-264 (ASTM A-516 GR. 70
-4.157" MIN. - 1.4" CLAD SHELL CLADDING
-16 - 2 1/2" STUDS-i-BIT-STUD ASTM 1-240 (TYPE 304L) 16 2 1/2" NUTS CAl IRRATION RI OCKS; TO BE DETERMINED 1-BIT-B 1-BIT-A BORON INJECTION TANK PSEG Nuclear, LLC SALEM NUCLEAR GENERATING STATION UNIT 1 - WELD IDENTIFICATION FIGURE INSERVICE INSPECTION DRAWING I-
O PSEG NudarLL;C ULTRASONIC EXAMINATION SCAN LIMITATION REPORT di tuomr SG/Slem Unit I System: CVC SmayN.: 204450 Component ID: 1-BIT-2 Applicable Report No: UT-05.020, UT-054)21, UT-05022 Reference Point:
- 1) Interfering Condition Nozzle
" TO Upstream Exam % Downstream Exam %
Distance From Center*lne A~~dal 1100%97% Distance From Ref. Point 0" To X90" Clr CW i 100% 0%
- 2) Interfering Condition Cire CCW 100% 0%
Distance From Centerline To Distance From Ref. Point To Total Exam Coverage: 73.95%
- 3) Interfering Condition See Supplemental Sheet for Coverage Calculations.
Distance From Centerline To Distance From Reft Point To (For All Measurements Indicate: US, DS, CW, CCW) Sketch I Photo Of Limitation(s): C Attachment A-14 Page 2 of 5 1
0 PE Supplemental Report Report No,.: UT-05-022 Page: of , e Summary.No.: 204450 Examiner: Chapman, Georgae Level: II-PDI .Reviewer: Conti, AdamJ4 &. 0*"V " . Date: 4l.411a/ les Examiner: Chalfant, Daniel ,. = Level:: I Site Review: John ONeil ate: Other: NIA Level: NIA ANII Review: / Date: L1 i i i ii iiiiiii Comments:
ýComments:
Component ID: I -BIT-2 Thickness: 2.25" Weld Length: 36.90" Weld Crown Width: 1.10" Exam Volume Width: 1.60" Exam Volume Height- 0.75". Exam Volume Square Area: 1.20" Coverage Caiculations: Reflectors Parallel to the Weld (Axial Scans) Examination Angle: 45' shear wave Limitation: Limited coverage on far side (nozzle) of examination volume due to weld crown and nozzle configuration (see coverage plot for additional information). Square Area of Limitation: 0.05" Coverage %Obtained: 95.8% ,E xaminatlon Angle: 60' shearWave W -imitation: None Square Area of Limitation: 0.00" Coverage % Obtained: 100 % Coverage % AxIal Scans: 97.9% Coverage Calculations: Reflectors Transverse to the Weld (Circ Scans) Examination Angle: 45' shear wave Limitation: No coverage on far side (nozzle) of examination volume due to weld crown and nozzle configuration. Square*Area of LimJtation- 0.60" Coverage % Obtained: I50% Examination Angle: 60,shear wave Limitation: No coverage on far side (nozzle) of examination volume due to weld crown and nozzle configuration. Square Area of Limitation: 0.60" Coverage-% Obtained: 50%": Coverage% Circ Scans: 50.0% Total Combined Volumetric Coverage:, 73.95% Attachment A-14 Page 3 of 5
OPSEG Supplemental Report Repo N.: UT-05.022 Page: .a1c of 4-5 Summary No.: 204450 Examiner' Chapman, George: 11ý6 Level: li-PDI Reviewer: Conti, Adam .,- Date: 15 C/og Examiner: Chalfant, DanIel. .Level: I SiteReview: John ONeil ý.,a O7 Other: NIA Level: NIA AN!I Review. ! Date-Comments: Exam'Comments .45° Exam limited duo to nozzle configuration onDeS side. CWICCW ID clad rollScans performed 4.5 screen with beam sufficiently skewed to.provide shell side coverage of weld and haz. divislonlcallbr atlon reflectors ve.rfied at scan speed &sensitivity. Exam Comments .600 Exam limitedodue to nozzle configuration-on DS side. CWICCW Scans performed with beam sufficiently skewed to provide shell side coverage.of weld and haz. ID clad roll 4.5 screen divisIon/calibration reflectors verifie at scan speed & sensitivity. Exam Comments- 00 Exam limited due to nozzle configuration on DS side. Calibration reflectors verified at scan speed &sensitivity. Attachment A-14 Page 4 of 5
-BIT-2 acflment A-Paae 5 of 5
Attachment A-15 Page 1 of 10 BUTTERED WELD S*ISum # 029700
- 14-PS-1131-2 4
1' Ný PRESSURIZER SURGE BUILDING: LOCATION: ELEVATIONS: 14-PS-1131 CONTAINMENT BIOSHIELD PSEG ISO RC-I-1A A 3052 117 98' ATTENTION. ANY REVISON SHALL BE MADETOONLY DRAWING THIS BY CAEDPSGNcerLC PSEG Nuclear, SALEM NUCLEAR LLC FIGURE: A-18I REVISION: 1 GENERATING STATION SYSTEM: PRESSURIZING SYSTEM PRESSURIZER SURGE REVISED PER ORDER No. 80008418 UNIT 1- WELD IDENTIFICATION FIGURE LINE: 14-PS-1131 REV. DATE DESCRIPTION INSERVICE INSPECTION DRAWING THIRD 10 YEAR INSPECTION INTERVAL (D2000 PSEG Nuclear, LLC. All Rights Reserved.
- O PSE ULTRASONIC EXAMINATION
SUMMARY
Customer: PSEGI Salem Unit1 System urizng System Summary No.* 029700
- Component ID:I4PS-11i31-2 Conflguratlon: Surge Une: Nozzleto Safe End I Examination Technique:
Axial scans were*performed using a 45 shear wave and 0, 35%, 45' and 60, longitudina wave search units. The anglebeam, longitudinal, wave search units were contoured forthe 15 diameter to optimize search unit contact. Specific parameters for each of these probes are identified in the following table* Scanning was performed from all accessible surfaces of the safe-end taper and across the weld with the sound beams directed towards the nozzle. Scanning with the sound beamsdirected towards the safe-end Wasý restricted due to the nozzle proximity:. Physical scan limitations (obstructions) and beam profiling is provided in the scan limitation reports for each search unit; Manufacturer Frequency Model Refracted Angle: Element Sizes Focus Focus % T. KBA 2.25 MHz Gamma .0° 0.50" NA NA KBA :1.5 MHz COMP-G 45° 0.50" NA NA Mega Sonics 1.5 MHz CSS, 350 (2) 15x25 mm FD 1,40 .. 93% MegaSonics 1.5 MHz CSS 450 (2) 1.5x25 mm FD 1.827 108%
.Mega Sonics .1.5: MHz.... CSS .60. (2) 15x25 mm FD 1.30* 87%
Circumferential scans were performed using a 45* shear wave and 450 and 60' longitudinal wave search units. The longitudinal wave search units were contoured for the 15" diameter to optimize search unit contact. Specific parameters for each of these probes are identifled inthe0 folowing table. Scanning was performed from all ýaccessible surfaces of the safe-end taper and across the weld with, the 4 ndbeams directed clockwise arid conter-clockwise. Physical scan limitations (obstructions) and beam profiling is provided in the scan limitation reports for each search unit. Manufacturer Frequency Model Refracted
,_(Note Angle Element Sizes Focus Focus % T 1)
KBA .1.5 MHz COMP-G 45- 0.50 . NA . NA RTD 1.5MHz TRL1.5-A 450 . (2) 15x25 mm FD 1.39' .79% Mega Sonics 1.5 MHz CSS 600 (2) 15x25 mm. FD O.90 50% All search units' Utilized for both axial and circumferential scans are qualified to Appendix Viii requirements of the ASM-E Code. Note I: T for circumferential scans includes additional sound. path uired for component curvature.
Conclusions:
As identified in:the beam profiling provided in the scan limitation reports for each search unit, effective volumetric coverage was provided
.in all accessible regions of the weld. No reportablekindications were identified.
This examination was limited in 4 areas where permanehtly welded insIulation lugs'are attached to the taper of the safe end. This limitation reduces the examination coverage to -.70% for axial scans and ~'90% coverage for each circumferential scan. No previous UT examination data was available for review prior to examination. Total Coverage = - 83.3%. Page 3 of 'I8 4 Attachment A-15 Page 2 of 10
.PSEG ULTRASONIC EXAMINATION
- i /rIX THICKNESS AND CONTOUR.
ustomer: PSEG /Salem Unit f system: Pressurizing system SNo,029700 Examination VolUme: ASME Code - Lower V/3 weld volume and base material for a distance of 025"from each weld toe. Procedure - In addition to the ASME Code volume, the complete weld volume,butter material and base material from each weld toe or butter interface. Risk Informed Program.- ASME Code volume extendingO.50' beyond the base metal thickness transition or counterbore on each side of the weld where accessible. Weld Circumference: 47.0(r Material Thickness:
- 1. Nozzle base material = 1.50"
- 2. Upstream Toe of Weld l_50W
- 3. Centerline 0fWeld = .50"
- 4. Downstream Toe of Weld = 116500
- 5. Safe End Thicknress readirgs usattainable due to~ O° Taper A\I I* . I ' I
. I ./ \
- I Attachment A-15 Page 3 of 10
.PSEG./Salem Unit i Component ID: 14-PS-I13 12 70%
- 1. .4 insulation lugs welded on safe-end taper. Lugs are 2.0" wide and located at O*,90*, 1SO, and 270°.
Limitation is lug width and %/of search unit width (0.80") in areas.where obstruction Interferes with scanning. Scanning performed from safe-end taper and across weld and butter material. Scans performed with beam directions looking towards and away from nozzle. I I I
/
% I SO COVORA&F-E AD~.6A Page 8 of I8 a
Attachment A-15 Page 4 of 10
o PSEGNucletat,I l
- r. PSEG / Salem Unit I Component ID: 14-PS-1131-2 Coverage: 70%
- 1. 4 insulation lugs welded on safe-end taper.. Lugs are 2.0" wide and located at Do, 90O, 1800, and 270.
Limitation Is lug widthand VIof search. unit width (0.80") in areas where obstruction Interferes with scanning. Scanning performed from safe-end taper and across weld and butter material.. Scans performed with beam directions looking towards and away from nozzle. A.
\ I No Cove~rv~e. Ai~ev Page 1.Oof 18 J
Attachment A-15 Page 5 of 10
0 PSEG Nw~u~o fLU* PSEG !Salem Unit 1 Component ID: 14.PS-1131-2 ml Coverage: 70%
- 1. 4 Insulation lugs welded on safe-end taper. Lugs are 2.0"wide and located at O, 900, 1806, :and 270*.
Limitation is jug width and A of search unit width (0.80") in areas where obstruction interferes with scanning. Scanning performed from safe-end taper and across weld and buter material. 9Scans performed with beam directions looking towards and away from nozzle.
/
t
/
No CovereAreo. Page 12 of 18 SAttachment A-15 Page 6 of 10
0%PSEw ULTRASONIC EXAMINATION SCANLIMITATION REPORT ustomer: PSEG ISalem Unit 1 Syt-em: ressuriingtSystem Summary No.: 029700 Component ID:ý 14-PS-1131-2 Limitations: (45 Shear wave) AXial Scans verage 70%
- 1. 4 Insulation lugs welded on safe-end taper.. Lugs are 2.0" wide and locatedat 0a,,90, 80w, and 270l..
Umitation is lug width and %A of search unit width (0.25") in areas where.obstruction'interferes with
,scanning, Scanning performedfrom safe-end taper and across weld and butter material. Scans performedwith beam, directions looking.
towards and away from nozzle. Coverage Plot-
'No. Covera ~Arre Examlner. Terry RockwýoL Date.11011,72005 Examiner. Jason Breza Level: 11 Date: 10/17/20Q5 Date:
eviewer. Adam Cont som frer.John O'Neii Date.,4A 4 P-age.1o 18 6*1 / / ?, Attachment A-15 Page 7 of 10
O PSEG ULTRASONIC EXAMINATION SCAN LIMITATION REPORT Nuckaer LLC
.u..m S em Unit 1 System: Pressurizing System Summary No.: 029700 1"S4131-2 Component ID imitations: (45°Shear waVe and 45/160" L.Wave Circ S Coverage: 90%
- 1. 4 insulation lugs welded on safe-end taper. Lugsare 2.0" wide and located at 0°, 900, 1800, and 270*.
Limitation Is lug width and I/ of search unit width In areas where obstrubtioh interferes with scanning.
- 2. The longitudinal wave probes are limited to a W distance of 0.80" fromweld centerline due to the proximity of the nozzle.
This illustration depicts the amount of coverage obtained during circumferential scanning performed across the weld and butter material and from the safe end taper.: The 100 taper skews the sound beam towards the area of interest Coverage Plot: 1,158 4 I / I I I j - I I ~ 1 1. A-/ I. I
-N I
Attachment A-15 Page 8 of 10
O PSEG ULTRASONIC EXAMINATION SCAN LIMITATION REPORT iI ustomer: PSEG IGSalem Unit 2 Pressurizing System Summary No.: 029700 Component ID: 14-PS.1 131-2 00% *
. ..... . ..... "Coverage!
Limitations: (45".Shear wav. and,457160 L Wave Cire ansg
- 1. 4 insulation lugs welded on safeend taper. Lugs are.
2.0' wide and located at 00, 901, 1800, and 2700. Limitation is lug width and %iof search unit width in areas where Obstruction interferes with scanning.
- 2. The longitudinal wave probes'are limited to a W.
distance of 0.80" from weld centerline due to the proximity of the nozzle. This Illustration.Identifies the circumferential scan Impingement angles. Coverage Plot: 4 Examiner: Jason Breza Date: 10117i2005 Examiner: NA Level: NA Date: NA eviewer: Adam Conti Date. 4
.Customer;.:John O'Nei. Date: f¢,/4
- Page 18 of 18 (7 Attachment A-15 Page 9 of 10 1
70 4-
-o C
U) ~- EU) C zm 0 a)U U, 5*
33 32 28 26 1$,'. TOP OF PRESSURIZER
't 01 23PS 130'FLOOR ELEV..
C-PRG-189 Attachment A-16 AUXILIARY SPRAY Page 1 of 7 2 CV 1175 BUILDING: LOCATION: ELEVATIONS: PSEG ISO RC-1-2B CONTAINMENT BIOSHIELD 84' TO 161' ATTENTION: PSEG Nuclear, LLC FIGURE: A-12 REVISION: 1 SYSTEM: CHEMICAL AND VOLUME CONTROL SALEM NUCLEAR GENERATING STATION AUXILIARY SPRAY UNIT 1 - WELD IDENTIFICATION FIGURE LINE: 2-CV-1175 (Cont'd) INSERVICE INSPECTION DRAWING THIRD 10 YEAR INSPECTION INTERVAL 0 2000 PSEIG Nuclear, LLC, All Rights Reserved,
Attachment A-16
.7 PS EI Weld Thickness & Contour Page 2 of 7 m# 022100 ComponentI.D., 2-CV-1175-36 1Decription PIPE TO TEE 7 Unitl []saleml1 I.Salem 2 [1]Hope .Creek Loato M. L] 900 1800ý[2700 Photograph Contour' Dimensions # Description Dim Comments Ti E] Pipe D Elbow El Vaive ElTee Upstream .0.313" Weld cannot be visually identified.
T2 Toe of weld upstream r N/A T3 Weld Thickness NIA T4 Toe of: weld downstream NIA T5 [I Pipe L] Elbow [nValve E[] Tee Downstream 0.4001. Limitations (ifyes attach photo), D] Yes l NO: Is Weld Identification Marked . M Yes,. [-No Is.LoMarked Diyes E No' Can weld be visually defined F]"No _ _ _ Examined By: D. N.Bryant Date: 04/04/07 NDE Specialist Review:. Victor Morton Date: ,04104/07
2-CV-1 175-36 Code Required Examination Volume Limitation
- During Salem unit # 1 RFO-18 an ultrasonic examination was performed on weld 2-CV-1 175-36 summary #022100. A review of the fabrication documents shows that the 2" branch connection: of the 4" X 2" reducing tee has a very small amount approximatlyl/4" of base metal adjacent to the weld. Reference VTD Drawing 157060
,located in DCRMS,. A review of the construction radiographs also supports this. This configuration does not support ultrasonic scanning on the downstream side of this weld. Ofthe 6 scas required to attain 100% weld coverage only 3 of the scans could be performed, Upstream axially and upstream clockwise, & counter clockwise. In conclusion this examination covered 50% of the ASME code required Examination volume. Public Service Electric and Gas
-Principal Ultrasonic Level II1 David Mora 1/13/2012 Attached Weld fabrication Drawing and Picture Attachment A-16 Page 3 of 7
r - PuBLic 5ERIaCi JEL~cTRIC AND OAS COMPANY ELECTrRIC ENG3INFERING DEPARTMENT' 93 PRINT NO, ruE1 1,57 60 twrtCzaR 0ENEIATUItG S3TAT2ION ISSUE UNIT I I 1.QCATION Oil AUTIORIZAT1ON.N'O, 7 CONT. NO. ,._______ .157133, BR-NO ___________ USED POR ~~trCn~ne tt p DESCRIPTION Pi eDt~j I1I SUPPLIER(MFR, 1LL*1a~nfrg 1o~ UTo~rmierW M.W. 12nv Ke:om o.1) MFR PRINT N6. 6t#20REV. MFR 0 OR DIEFNO. THIIS PRINT ýIS- 1J3 PRE LMiNAIOY lmiOFFICIAL 03AbDiTI0NAt. RFECV'lD VIA oril. Engr. jo/Vitale. LwnCaiotn.5-21 NP Ext. 237-1 uo_63/6
'ELECTRIC ENGINEERING DEPARTMENT rEVpIfW ENG*NEERING DIVISION DRESGN DIVISION DIVISIoNý CO-NT.__- -- -
REVIEW MECH, CONT. S'ýlwjC, ELEC. MECH.m . TUC. ARCH CH
..-. M C4.. ]LEC, AA.R(,; WD.ES. E.. N GR*
.. ... -.. - i. i 1 . . .. . * .
DATE INITIAL
/
I -
...... URCOMMENTS
- 1. NUMERICAL- 7-.Oi -or /D IPndex iList see PSB3P 126,440
- 2. MASTER FILE No. _________ or -P/M Inde.x List a etSPBP 126441
- t. ._For Rat* see Dwgs,: 2oS,4OT468 1
Ak4803
- 4. 2O 432-A-8843,
.,36300-A-31496 238301- "A-2,496.
t DIV. SYSTEM TYPE AREAk 238302-A-11496 238303-A A';:96: t i CODE OOD[ DWG., ELEVM 2383Q4--..96, E C E .23830,A-'1496 , 238306.-*A-4.9.6 R,60 4L2 .az 238307-A14§96: PS. .P. No. 3.o7 60 7A/"70./Thcc Attachment A-16 Page 4 of 7
en
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~LO
~c 00~
(U 4-I'
- 4. ii K I I -
1' r4 7. 771 I-i
Attachment A-16 Page 6 of 7 Sum # 022100 2-CV-1 175-36
Attachment A1 Page 7 of Sum#(
-CV-1 '
Attachment A-17 Page 1 of 5 8 PRESSURIZER RELIEF 6-PR-1105 PSEG ISO RC-1-2A BUILDING: LOCATION: ELEVATIONS: CONTAINMENT PRESSURIZER 155' BLOCKHOUSE ATTENTION: E T O : AY AT BE MA ETOONLY SHALLREVISMON THIS DRAWING BY CAED PSEG Nler LLC FIGURE: A-13 REVISION: SALEM NUCLEAR tSE ' GENERATING ucle ar, L CS STATION S E : PRESSURIZER SYSTEM: P E S R Z R RELIEFR L E 1 REVISED PER ORDER No. 80008148. UNIT 1 - WELD IDENTIFICATION FIGURE LINE: G-PR-1105 REV. DATE DESCRIPTION INSERVICE INSPECTION DRAWING THIRD 10 YEAR INSPECTION INTERVAL () 2000 PSEG Nuclear, LLC.AIl Rights Reserved.
O PE ULTRASONIC EXAMINATION SCAN LIMITATION REPORT NudearLLG ustomer PSEG I Salem Unit I System: Reactor Coolant Summary No.: 022700 Component ID: O.PR-1105-6 Applicable Report No: UT-05-070, UT.05-071, UT-05-072 Reference Point: Outside Radius of DS Elbow
- 1) Interfering Condition Elbow Intrados Exam % Downstream Exam %
Distance From CentelneDistnceFro 0"30 T Cenerlno To All DSUpstream Ai DAxial 71.43 71.43 Distance From Rof. Point 7.5" To 13.5" Circ CW 100 100
- 2) Interfering Condition Outside Radius of US Elbow Clrc CCW 100 100 Distance From Centerline 0" To All US Distance From Ref. Point 7.5" To 13.5" Total Exam Coverage: 85.72%
See Supplemental Report for Additional Information.
- 3) Interfering Condition Distance From Centerline To Distance From Ref. Point To (For All Measurements Indicate: US, DS, CW, CCW)
wIPSEG 0 PSEGAttachment Weld Thickness & Contour A-1 7 of 5 Page 3 of5 NitclarlI.C 0:2=700I 6-PR-I1054 Elbow to Elbow salem I [Salem 2 [J"opeCreek ] .o- Eo 9v 0 DE o Photograph Contour FL" . , Dimensions Description Dim-NI Comments Ti Elpipe (ZiElbow EjValve [JTee Upstream .77" T2 Toe of weld upstream No__ T3 Weld Thickness .74N T4 Toe of weld downstream .75" _
"IS C] Pipe Rl ebow F] Valve E]Tee Downstream .76" Limitations (ifyes attach photo) ,,Yes [f No Inside Radius of Elbow Is Weld Identification Marked .. ] Yes [] No Is L Marked E]yes M No Gan weld be visually defined 2Yes El No Examined By: Jason D.Breza j* .*l Date: 10/15/05 NDE Specialist Review: Adam Conti - I I ~llIrll
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Date: . edIt q
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0 Supplemental Report Reprt No.: UT-05-072 Page: /4' of 4 Summary No.: 022700 Examiner: Breza, Jason 4, Level: i-PDI Reviewer: Examiner: N/A " Level:, N/A Site Review: Other NIA Level: NIA ANII Review,
.Comments: 4.
Component iD: 6-PR-1105 Thickness: 0.756/0.80" Weld Length: 21.0" Weld Crown Width: 0.75" Exam Volume Width: 1.75" Exam Volume Height: 0.27" ExamVolume Square Area: 0.47" Coverage Calculations: Axial Scans Examination Limitation: NoAngle: 450 shear wave coverage for 6.0" weld length at Intrados of both short radius elbows Square Area of Umitatlon: 0.47" Coverage % Obtained: 71A3% . Coverage Calculations: Clrc Scans Examination Angle: 450 shear wave Limitation:, None Square Area of Limitation: 0.000" ACoverage % Obtained.: Coverage % Clrc Scans: 100% Total Combined Volumetric Coverage: 85.72% Commentsi
- Coverage calculated to risk informed examination volume. No counter bore detected (NCD). Inside surface geometry observed below recordable levels. Maintained 10% - 20% ID Roll/Material Noise level during all examinations. Supplemental toL and 70 0S searchunit examinations performed In area of limitations to enhance far side coverages. SDCN'30-9003461 Rev 000 and 5063069 Rev 00 utilized with examination procedure.,
Attachment A-17 Page 4 of 5
-PR-I 10-tahetA-1 7 Pae if 5
Attachment A-18 Page 1 of 3 STEAM WELD GENERATOR *14 2PL-I *
- NOTE: PIPE LUGS 2PL-I. 2PL-2, AND 2PL-3 HAVE BEEN GROUND FLUSH TO PIPE NO EXAMINATION REDUIRED Sum # 037400 31-RC-1 140-3
- 2PL-3
- 4BC-1 3'
/ 3/4' I4BC-3 3/4" 4BC-4 3/4"Z -
PUMP *14 5LU-0 5 I \ 6L0I ~ 7LU-0
-1140-5 /3-CV-1143 (FIGURE A-47) 6LD-0 31-RC-1140-5 / 3-RC-1143 MAIN REACTOR COOLANT
(*14 CROSS OVER LEG) 31-RC-1140, 3-RC-1143 BUILDING: LOCATION: ELEVATIONS: PSEG ISO RC-1-1B A 3052 114 CONTAINMENT BIOSHIELD 85- TO 97' ATNIN SHALL BE MAE Al REVISITO N: ONLY THIS BY CAED DRAWING PSEC Nuclear, LLC NucleTr, FIGURE: A-23 SYSEEM COOANREVISION: 02 2 REPACE WED SALEM REVISED PER ORDER No. 80008418. 3-RC114-2 NUCLEAR l~fli\ GENERATING STATION SYSTEM: REACTOR COOLGNT 14 CROSS OVER LEG REPLACED WELD 31-RC-1140-2 UNIT 1 - WELD IDENTIFICATION FIGURE LINE: 31-RC-1140, 3-RC-1143 E 120EDATE REV. DESCRI DESCRIPTION INSERVICE INSPECTION DRAW(ING INEVC NPCINDAIGTHIRD THR 1T 10 YEAR INSPECTION INTERVAL (D 2000 PSEG Nuclear, LLC. AlIRights Reserved,
Suppler Report OIWG Report No.: Page: 2 UT-04077 of 3 Summary No.: 037400 Examiner: Weeks, Paul R. Level: It Reviewer Date: Examiner: NWA Level: N/A Site Review:. Date: !V--Zi,-gý Other. NIA Level: NWA ANtI Review: Date: Comments: Limitation Sketch Sketch or Photo: K:-JDDEALXGraphicsNRF016XUT-04-077a~jpg ELIO3&j 2.4
.741
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I / 1t I Attachment A-18 Page 2 of 3
Supplemel Report 0 3IiLG Report No.: Page: 3 UT-04-077 of 3 Summary No.: 037400 Examiner Weeks, Paul R. Level: II Reviewer: Date: _4/4 Examiner NIA Level: N/A Site.Review: I-
- . ,-JA 7 = -1ft Date:
Other NIA Level: WA ANII Review: Date: Comments: Ultrasonic Examination Scan Umitation Report Sketch or Photo: lC'DODEAL\GraphicsXRF016\Ur.O4-077b~jpg PULTRASONIC EXAMINATION SCAN LIMITATION REPORT Customer PSEG ComonntFigure No.: Weld No.: 31-RC-1140-3 Percent Of Exam Completed (Calcuations Or Cormments Blow) Reference Point Outside Radius of Elbow
- 1) Interfedrng Condition Acoustic Properties of Elbow (Cast)
Distance From Centerline V To " usAll upstream scans obstructed due to acoustic properties of elbow (cast). Distance From Ref. Point 0" To 116*
- 2) Interfering Condition WA 50% Examination Coverage Achieved Distance From Centerline WA To NlA DistanceFrorn Ref. Point NIA To NIA
- 3) interfering Condition NWA Distance From Centedine N/A To NIA Distance From Ref. Point NWA To WA (For All Measurements Indicate: US, 0D, CW,.CCW) ttachment A-18 Page 3 of 3
Attachment A-1 9 Page 1 of 3 STEAM -BUTT RED WELD GENERATOR *14 2R 2PL-1 *
- NOTE: PIPE LUGS 2PL-I. 2PL-2. AND 2PL-3 HAVE BEEN GROUND FLUSH TO PIPE NO EXAMINATION REQUIRED 2PL-2
- 2PL-3
- 4LD-1 Sum # 037500 4BC-1 3A 31-RC-1140-4 4LO 4B-2B 4 A'
-4BC-3 N" 4BC-4 3/4' Z- - -4 PUMP #14
_ 5LU-I 5LU-0
--- 7LU-0 3::
"I 6LD-0 31-RC-1140-5 /3-RC-1143 MAIN REACTOR COOLANT
('14 CROSS OVER LEG) 31-RC-1140, 3-RC-1143 BUILDING: LOCATION: PSEG ISO RC-1-1IB A 3052 114 ELEVATIONS: CONTAINMENT BIOSHIELD 85' TO 97' ATTENTION: AN SHALLREVISIN BE MADETOONLY THIS BY DRAWING CAED PSEG Nuclear, LLC FIGURE: A-23 I REVISION: 02 SYSTEM RECTOR COOLNT 2 REVISED PER ORDER No. 80008418. SALEM NUCLEAR GENERATING STATION -SE 14 CROSS OVER LEG REPLACED WELD 31-RC-1140-2 UNIT 1- WELD IDENTIFICATION FIGURE LINE: 31-RC-1140, 3-RC-1143 1 12/10/96 PER (NEW S/G R) ITSELD INTIFCATON FIG REV. DATE DESCRIPTION INSERVICE INSPECTION DRAWING THIRD 10 YEAR INSPECTION INTERVAL (U 2000 PSEG Nuclear, L[C. All Righis Reserved.
Supplem Report W 0OPTEG Report No.: UT-04-079 Page: 3 of 3 Summary No.: 037500 Examiner Weeks, Paul R. Level: II Reviewer Date:___ Examiner WA Level: NIA Site Review:. Date:J6-a-v Other WA Level: NIA ANII Review: Date: /j Comments: Ultrasonic Examination Scan ULmitation Report Sketch or Photo: K:.lDDEAL\GraphiCs1RFO16\UT..O4..79b.jpg A ULTRASONIC EXAMINATION SCAN UMITATION REPORT A FREVA Customerc PSEG componet UrN: Weld No.: 31-RC.1140-4 PercentOf Exam Completed (CaulatonsOr Consnents Below) Referece Point Outside Radius of Elbow
- 1) lnterfedng Condition OS ElbowAcoustfC Properties (Cast) All downsfteam scans obstructed due to acoustic Distance From Centerline 0" To 5" ds properties of elbow (castq.
Dlstance FromRel. Point 0V To 116"
- 2) Inteifeitng Condltioc MA 50% Coverage Achieved Distance From Centerlne NA To NIA Distance From Ret. Point WA To WA
- 3) interfering Condition NIA Distance From Centertine WA To MA Distance From Ref. Point XWA To NWA (For All teasurements Indicate: US. DS, CW, CCW}
Attachment A-19 Page 2 of 3 T991
JI Supplen Report Report No.: UT4)4079 0o01 Page: 2 of 3 Summary No.: 037500 Examiner: Weeks, Paul R. Level: HI Reviewer: Date: Examiner. NIA Level: NIA Site Review: Date: Other: NWA Level: NIA ANII Review: Date: Comments: Limitationi Sketch Sketch or Photo: K:MlDDEALGraphicrs\F1FO6xtJT-04-079a.jpg
- q. + 4. 2.
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Attachment A-19 Page 3 of 3
Attachment A-20 Page 1 of 3 1 Sum # 096750 1O-SJ-1 141-15 12 6-SJ-1142 (FiGURE A-64) 7,OO 9 ~-8 7 01 3
.L 14SJ54 TO ACCUMULATOR NO. 14 SAFETY INJECTION 10-SJ-1141 PSEG ISO RH-1-3A A 3052 162 PSEG Nuclear, LLC SALEM NUCLEAR GENERATING STATION UNIT 1 - WELD IDENTIFICATION FIGURE INSERVICE INSPECTION DRAWING
Supplei Report W AEG Report No.: Page: 2 UT-04-040 of 3 Summary No.: 096750 Examiner Weeks, Paul R. Level: 11 Reviewer: Q Date: Examiner: Brelje, Tim Level: IA(N) Site Review. ,,4 Date-.- Other: N/A Level: NIA ANIH Review: -4 4k s* - 0 Date Comments: Single Sided Access Due to Configuaration and Cast Tee Sketch or Photo: K:\IDDEAL\Graphics\RF016\UT.O4-O40a.jpg P9-
- 1. S
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'7 FrUO W..
Attachment A-20 Page 2 of 3
0@I1 WG IS1 Report Report No.: uqT4WPM4 Page: 3 of 3 Summary No.: 096750 Examiner: Weeks, Paul R Level: 11 Reviewer~ Date: Examiner. BrIJ, TIM TN/ Level: UN) Site Review:. Date:~/~ Othier~ WA Report rrrrrr *..... Level: N/A ANU Review: Date: 44
,,,,,,,,,L Scan Limitation Ultrasonic . . . .......
Comments: Examination Comments: Ultrasonic Examination Scan Limitation Report Sketch or Photo: K:UIDDEALIGrapcsRFOI86UT-04-O4Ob.jPg JA ULTRASONIC EXAMINATION SCAN LIMITATION REPORT AR EVA Customer PSEG colmponent Figure No.: Weld No.: 10.-0J-1141-15 percent Ofr Exan Compieted (Catualons or Commws tw uo"J Referece Point MC
- 1) Ird*edng Condition Tee Cont gUrtton All upsreamn exms obstructe&
Distance From Centeirm 0 To 2.1" us Percent of exam compie*la 50% Dista4ce From Ret. Point 0 To 34* cw
- 2) lnteredng Condition WA Distance From C;enterkw NA To IVA Distance From Ref. Point WA To WA
- 3) Inter*fr* Co*Wdon WA Distance From Centeine N/A To WA Distance From Rf. Point NIA To MIA (For Atl easurements Indlcate US. DS, CW. ccw)
PAttachment Page 3 of A-203
Attachment A-21 Page 1 of 4 Sum # 101100 110-SJ-1 121-16 C ]" 20 . C, 0111ý 6 3. 0 3 3A 2 01 Z' V 12SJ54 TO ACCUMULATOR NO. 12 ACCUMULATOR DISCHARGE (SAFETY INJECTION) 10-SJ-1121 PSEG ISO RH-1-3A A 3052 126 PSEG Nuclear, LLC FIGURE: A-56 REVISION: 13 SALEM NUCLEAR GENERATING STATION SYSTEM: SAFETY INJECTION ACCUMULATOR DISCHAR UNIT 1 - WELD IDENTIFICATION FIGURE LINE: 10-SJ-1121 INSERVICE INSPECTION DRAWING THIRD 10 YEAR INSPECTION INTERVAL 0 2000 PSEG Vuclear, LLC. MlIRights Reserved.
NotOut Attachment A-21 Page 2 of 4 Reported .By.:Gies227.1 IINotification #: IM8148 ~PriiitEhjs e~ FLOC: Is .Short
Description:
.i~ SI, Weld -Exam Limitations
-91R How: .1Ho27S-Identified Issue
Description:
I During. 1R19 ISI Ultrasonic (UT)weld'examinaýion performed onASME Class I Safety lnjecýtin Piping Weld SUmmt*ary -. 101100, componentlIO 1o-SJ-1121-16, was Limited to 50% of theASME:Section X1 code required examination coverage. Limitation wai due to.the cast material composition of the TEE Which has Door acoustical.g erties thf.ore tao. n rduring poR19 ISI UYtra sonint( welda examination, performeda n AScIVE.Class 2 CheoamicalandVolumesCottroo lank' (SI CVC:!.CVE6)..I 0dwer shell to~head weld (I-CVCT-2) ISI-summary #204800.was als0 Uimited to 81.6%'ASME$*C~o X! code required 50104940 examinati-n Procedure: c6r~b6. 54-1SI-136:.12 Lienetadh Procedure wIas due to 4 sAppo.rt Constlruc ER-AA-3830-,O02:Original tionEtank. legs padsEon Sv Ua T Exa minapion underyorden configjuration.Reqiuired.ASME c0d4 ' ' coverage 'not obtain~ed, Exam limitation pro~cess with 16ISI R .rogram Process allows for.Limitations. and provides additional. req'uired adtions.ASME S0t6n XIIIWB -2500 &'C'ode Case:N4W0, th~ese exam limitationis do notfeffect oparability,-NoneEd Mlaloney Kerry 6olville. ANII - ,Scott Hewitt Ed. Maloney Tony Oiiveri7T.his is a repeait condition, sa i e: a amin't On rhibib~tor wvere~ide'ntifiediduridg prior.1SU.1 0 Year Interita (2nd lfnterval).Immediate Action, Review prior-examination. results for consistenc Initiate Not~ification..Recommen t; ded Actions Assign ACI Ty. to S7EEp06 to Ev*aluatef6r compernsatory.actions. Assign ACITto Outage Services to d evelop -1Ri9Limitation package to-be used during end- of hterval NRC Relief R6qtest. for ExamLimit'ations. 0 0 http'-iinji7bttap's15/CteateNot/NofOut.'aspx I2920 10/29/2008
Weld Thickness & Contour Attachment A-21 Page 3 of 4 O-SJ-1121-16 Desciptinj*n Tee to Pipe Lodation 2o- 0 go- 'O'i8o? El 270-PhotogrAph T 1.E.
# Description Dim Comments E f]j Elbow: []*Valve.. 0 Tee Upstream 1705" "Weld Width 1.45" TI Pipe.
T2 Toe of weld upstream 1.107" Tapper 0.74" T3 Weld Thickness 1.299" T4 rToe of weld downstream .. 1.179", T5 Il Pipe E] Elbow E] Valve [l Tee DoWnstream , 1154" I rLimitations (ifyesattach photo) r.Yes [-'No _
"sWeld Identification Marked "yes _e__[-_N6_......._.____.
Is Lo Marked yes NO. jCan wedbe visually defined OlY1s5 i No Examnined By:- Edward P Mazyck -Date: 10/22108 NDE Specialist Review: Dave Mora D0e:810/23108
Attachment A-21 3/4" Line Page 4 of 4 Sum# 101100 10-SJ-1 121-16 Cast Tee Tee Bevel 10" Pipe
1",,., Sum # 103500 Attachment A-22 10-SJ-1111-16 Page 1 of 3
-1 '\r-..
6-SJ-1112 (FIGURE A-70) 13 I ;LY / 12 8A 8ýA 8sC-IISIA-12 (INTEGRAL-ATrACHMENT) 09i 7 5 4 3 I? 1ISJ54 TO ACCUMULATOR NO. 11 ACCUMULATOR DISCHARGE ELEVATIONS: (SAFETY INJECTION) BUILDING: LOCATION: CONTAINMENT BIOSHIELD 78' TO 112' 10-SJ-I1l1 ANNULUS PSEG ISO RH-1-3Au A 3052 133 ATTENTION IO: ANY REVISIN TO THIS DRAWING SHALL BE MADE ONLY BY CAED PSEG Nuclear, LLC FIGURE: A-57 REVISION: 1 SALEM NUCLEAR GENERATING
- STATION SYSTEM: SAFETY INJECTION WELDACCUMULATOR OISCHAR 1 REVISED PER ORDER No. 80008418. UNIT 1- WELD IDENTIFICATION FIGURE LINE: 10-SJ-1111 REV. DATE DESCRIPTION INSERVICE INSPECTION DRAWING THIRD 10 YEAR INSPECTION INTERVAL All Rights Reserved, Nuclear, LLC.
(C2000 PSEG
Supplem Report W O0PIG Report No.: UT-04-038 Page: 3 of 3 Summary No.: 103500 Examiner Weeks, Paul R. Examiner Breje, Tim TTD Level: Level: II I(N) Reviewer: Site Review:. QA &ý" Date: i*&ýi o* Date: Other: WA Level: N/A ANII Review: w6tý a Date:e&0 Comments: Ultrasonic Examination Scan Limitation Report Sketch or Photo: K:XIDDEAL\Graphics\RFO16OUT-04-038b.jpg AULTRASONIC EXAMINATION SCAN LIMITATION REPORT AI E VA . Customa. PSEG component'. Figure No.: Weld No.: 10%SJ41t146 Pe ent Of Exam Comnpled lsctidbons orCmome"eBaoum Referene Point TDC
- 1) lnterfed ng Condition Tee ConfiguraWuen All upstram exms obstrcte.
Ol*tance From CenteriLne 0 TO 2.3 us Percent of exami onipleted WS0% Distance From Ref. Point 0 To 3W cw
- 2) Inteferdng Conditlon WA Distance From centemne WA To WA Distamc From Re 1 Point NIA To WA
- 3) Intedeing Condition W/A Distance From Centerine N/A To NWA Dstn From Ref. Point NWA To WA (For All Measurenents lndit: 18US, S% CW, CCWM Attachment A-22 Page 2 of 3
0 xiS I Report Report No.: 1 UT-04-038 Page: 2 of 3 Summary No.: 103500 Examiner Weeks, Paul R. Level: 1 Reviewer. Date:_ __ Examiner: Brelje, Tim TTb Level: Site Review: Date: Other NIA Level: N/A ANII Review: Date: Comments: Single Sided Access Due to Configuration and Cast Tee Sketch or Photo: KIDDEALkGraphics\RF016\UT-04-O$8a.jpg 1.7i q-_1 to J~5 FLOW~ Attachment A-22 Page 3 of 3
Attachment A-23 Page 1 of 3 1 3 N.48 CONTAINMEN No. CONTAINMENT PENETRATION PE E-RATION 56 SPACER (iP-SWA-PS-4B) ANCHOR (1P-SWA-PS53) No. 13 FCU SUPPLY No. 13 FCU RETURN 10-SW-2196 10-SW-2141 (PENETRATION 48) (PENETRATION 53) No. 13 FCU SUPPLY (10-SW-2196) BUILDING: LOCATION: ELEVATIONS: & RETURN (10-SW-2141) LINES CONTAINMENT MECHANICAL 85' PSEG ISO SW-I-lB Sh. 8 PENETRATION ANNULUS AREA 0
- NANY FIGURE: B-111 REVISION:
ATTENTION: SHALLLREVISH THIS DRAWING BE MADETOONLY SALEM NUCLEAR GENERATING BY CAED PSEG Nuclear, LLC STATION SYSTEM: SERVICE WATER No. 13 FCU SUPPLY LINE: 10-SW-2196 ORIGINAL ISSUE PER ORDER 80008418 UNIT 1 - WELD IDENTIFICATION FIGURE No. 13 FCU RETURN LINE: 10-SW-2141 REV. DATE DESCRIPTION INSERVICE INSPECTION DRAWING THIRD 10 YEAR INSPECTION INTERVAL (D 2000 PSEG Nuclear, LLC. Rights Reserved. Ail
0 Supplei 0 PM2G Report Report No.: Page: 3 UT-04-063 of 3 Summary No.: 279540 Examiner: ExmnrChapman, George zo*(!ý Level: It Reviewer: Date: 44L\) 1 tf Examiner. WA Level: NIA Site Review: Date: 4/-/. y Other: WA Level: WA ANIl Review: Date: i-/ Comments: Ultrasonic Examination Scan Umitation Report Sketch or Photo: K:1JDOEALGraphics\RF016\JT-04-063b.jpg Afk ULTRASONIC EXAMINATION SCAN LIMITATION REPORT Customer: PSEG Component: Figure No.: Percent Of Exam Completed Weld No.: 10-SW-2141-5 (Calculati*ns Or Comments Below) Reference Point TDC
- 1) Interfering Condition Flange
~
De e s etdln nc e F r o m C T o 3 u sc 0 " To3All fi g udr a ti o n exams o nupstream . obstructed due to flange Distance From Centeine Distance From Ref, Point 0" To 32"
- 2) Interfering Condition N/A Examination Coverage 60%
Distance From Centerline NIA To NIA Distance From Ref. Point NIA To WiA
- 3) Interfering Condition NIA Distance From CentedlIne N/A To WA Distance From Ref. Point NIA To NIA (For All Measurements Indicate. US, DS, CW, CCW)
Attachment A-23 Page 2 of 3 1
4?PSEG Suppleme* I Report Report No.: 0 UT-04-063 Page: 2 of 3 Summary No.: 279540 Examiner. Chapman, George ,4qc Level: II Reviewer: (ý,I ý i eTV Date: Examiner N/A Level: WA Site Review:. Date: Other WA Level: N/A ANII Review:. Date. Comments: Limitation Sketch Sketch or Photo: K:\lDDEAIACraphiCSIRF016\UT-04O3.jpg PIME. j 4w Attachment A-23 Page 3 of 3 1
Attachment A-24 Page 1 of 3 9s'SPACER _4'Z. 0,9"
-P-14SWH-21 ANCHOR (IP-SWA-PS52)
No. 14 FCU SUPPLY No. 14 FCU RETURN 10-SW-2183 10-SW-2121 (PENETRATION 47) (PENETRATION 52) No. 14 FCU SUPPLY (10-SW-2183) BUILDING: LOCATION: ELEVATIONS: & RETURN (10-SW-2121) LINES CONTAINMENT MECHANICAL 88' ISO SW-I-lB Sh. 9 PENETRATION ANNULUS AREA ANYSHALBE ADETOONLY REVISVN THIS BY ATTENTION:_SHALLBE_____ONLYBY______SALEM DRAWING CAEDPSGucerLC PSEG Nuclear, LLC FIGURE: B-112 I REVISION: 0 NUCLEAR GENERATING STATION SYSTEM: SERVICE WATER No. 14 FCU SUPPLY LINE: 10-SW-2183 REV. DATE ORIGINAL ISSUE PER P ORDER 80008418 DESCRIPTION UNITINSERVICE 1 -WELD INSPECTION IDENTIFICATION FIGURE DRAWING - THIRD No. 1410 FCU YEAR RETURN INSPECTIONLINE: INTERVAL 10-SW-2121 0 2000 PSEG Nuclear, LLC. All Rights Reserved,
S1 Report 01 Report No.: Page: 3 0ý UT-04-069 of 3 Summary No.: 279620 Examiner: Chapman, George Level: II .Reviewer. Date: iI/L-L r
- Examiner: NA Level: N/A Site Review: Date:,//2. ?
Other: NA Level: NIA ANII Review., Date: 4L Comments: Ultrasonic Examination Scan Umitation Report Sketch or Photo: K.-lDDEAtkGraphicsRFO16ýUT..04-069b.jpg ULTRASONIC EXAMINATION SCAN UMITA11ON REPORT A-R~EVA Cuslonwr PSEG TCo "Mponet Figure No.: Weld No.: 10-SW-2183-3 Percent Of Eram Completed (Cakulstions Or Comnents Be"oW) Reference Point Outside Radius of Elbow
- 1) Intarfeing Condition Flange All downstream "scansobstructed due to flange.
Distance From Centsline 01 To 3' dis configuration. Distance From'Ref. Point 0" To 32
- 2) Interfeing Condition NA 50% Coverage Achleved Distance FromCenterlne WA To WA Distance From Ref. Point WA To WA 3} Interfering Condition NIA Distance From Centerline WA To WA Distance From Ref. Point MIA To WA (For All Measurements Indicate: US, OW. CCW)
CS, Attachment A-24 Page 2 of 3
RepTort M 0 Report No.: UT-04-069 Page: 2 of 3 Summary No.: 279620 Examiner: Chapman, George Level: II Reviewer: Examiner: WA Level: MIA Site Review: Other: WiA Level: W/A ANII Review: * .*lv - ,,* v w Comments: Limitation Sketch Sketch or Photo: KzIJDDEkLXGraphisRFOI$\UT-O4-069a~jpg LA~jvev
'a2oth/
-3 Attachment A-24 Page 3 of 3}}