RS-09-046, Relief Request I2R-50, Inservice Inspection Program Relief Regarding Examination Coverage for Second 10-Year Inservice Inspection Interval
| ML090960468 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 03/31/2009 |
| From: | Simpson P Exelon Corp, Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RS-09-046 | |
| Download: ML090960468 (150) | |
Text
Exelon Nuclear www.exeloncorp.com Exekln 4300 Win*ield Road Nuclear Warrenville, IL60555 RS-09-046 10 CFR 50.55a March 31, 2009 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN 50-456 and STN 50-457
Subject:
Relief Request 12R-50, Inservice Inspection Program Relief Regarding Examination Coverage for Second 10-Year Inservice Inspection Interval In accordance with 10 CFR 50.55a, "Codes and standards," paragraph (g)(5)(iii), Exelon Generation Company, LLC, (EGC) requests NRC approval to use a proposed alternative to the existing American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section Xl, "Rules for Inservice Inspection of Nuclear Power Plant Components," on the basis that compliance with the.specified requirements is impractical due to plant design. EGG is submitting this relief request for those ASME Section Xl weld examinations performed during the Second 10-Year Inservice Inspection (ISI) Interval where the inspection coverage achieved was less than or equal to 90%. The reduced examination coverage is due to the original design of these welds, physical obstructions, and geometric interferences.
The relief request supports the second ISI interval for both Unit 1 and Unit 2. The second ISI interval for Unit 1 began on July 29, 1998, and will end July 28, 2009. The second interval for Unit 2 began October 17, 1998, and ended October 16, 2008.
EGG requests approval of this relief request by March 31, 2010.
There are no regulatory commitments contained in this letter. If you have any questions concerning this letter, please contact Ms. Lisa A. Schofield at (630) 657-2815.
Respectfully, Patrick R. Simpson Manager - Licensing
Attachment:
10 CFR 50.55a Relief Request 12R-50
ATTACHMENT 10 CFR 50.55a Relief Request 12R-50
ISI ProgramPlan Braidwood Station Units 1 & 2, Second Interval 10 CFR 50.55a RELIEF REQUEST 12R-50 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)
Braidwood Station Limited Examinations Revision 0 (Page 1 of 4) 1.0 ASME CODE COMPONENTS AFFECTED:
Code Class: 1 and 2
Reference:
IWB-2500, Table IWB-2500-1, IWC-2500, Table IWC-2500-1, Code Case N-460 Examination Category: B-A, B-D, C-A, and R-A Item Number: B1.40, B3.110, C1.10, C1.30, and R1.20
Description:
Limited Examination Coverage Component Number: See Attachments 1 and 2 Drawing Number: See Attachments 1 and 2 2.0 APPLICABLE CODE EDITION AND ADDENDA:
The Second 10-Year Interval Inservice Inspection (ISI) program is based on the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV)
Code, Section Xl, 1989 with no Addenda. The 1989 Edition requires essentially 100%
examination coverage of required surfaces and volumes of various Class 1 and Class 2 components.
3.0 APPLICABLE CODE REQUIREMENT:
ASME Section Xl, 1989 Edition requires a volumetric and/or surface examination, which includes essentially 100% of the weld and the applicable base metal, for the affected examination categories.
Braidwood Station has invoked ASME Section Xl Code Case N-460, "Alternative Examination Coverage for Class 1 and Class 2 Welds, Section Xl, Division 1 ." Code Case N-460 states, in part, "...when the entire examination volume or area cannot be examined.., a reduction in examination coverage... may be accepted provided the reduction in coverage for that weld is less than 10%."
NRC Information Notice 98-42, "Implementation of 10 CFR 50.55a(g) Inservice Inspection Requirements," termed the reduction in coverage of less than 10% to be "essentially 100 percent." Information Notice 98-42 states, in part, "The NRC has adopted and further refined the definition of "essentially 100 percent" to mean "greater than 90 percent," which has been applied to all examinations of welds or other areas required by ASME Section XI."
4.0 IMPRACTICALITY OF COMPLIANCE:
Pursuant to 10 CFR 50.55a(g)(5)(iii), relief is requested on the basis that conformance with the specified Code requirement has been determined to be impractical. Due to the original design, physical obstructions, and geometric interferences associated with these
ISI ProgramPlan Braidwood Station Units 1 & 2, Second Interval 10 CFR 50.55a RELIEF REQUEST 12R-50 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)
Braidwood Station Limited Examinations Revision 0 (Page 2 of 4) welds, it is not feasible to effectively perform examinations of 100% of the volume of these welds. Therefore, relief is requested on the basis that the Code requirements to examine essentially 100% of the welds' volume are impractical. Attaining the geometry required to achieve the Code required examination coverage would require major modifications to existing components without providing a corresponding increase in the level of quality and safety.
Attachments 1 and 2 detail the limitations for examination coverage encountered for Braidwood Station, Unit 1 and Unit 2, respectively.
5.0 BURDEN CAUSED BY COMPLIANCE:
Compliance with the examination requirements of ASME Section XI would require significant modification of plant components to remove obstructions, redesign of plant systems/components, and/or replacement of components where geometry is inherent to the component design.
6.0 PROPOSED ALTERNATIVE AND BASIS FOR USE:
In accordance with 10 CFR 50.55a(g)(5)(iii), relief is requested on the basis that the required "essentially 100%" coverage examination is impractical due to physical obstructions and limitations imposed by design, geometry, and/or physical obstructions for the components listed in Attachments 1 and 2.
Braidwood Station proposes to perform the Code required volumetric examinations to the maximum extent possible. Because of the original design of these welds, there are no alternative examination techniques currently available to increase the examination volume. There were no cases in any of the listed examination components where outside diameter surface features (i.e., weld crowns, weld shrinkage, surface roughness, etc.) could have been conditioned to maximize the coverage attained without major modification to the components.
As a minimum, all components received the required volumetric examination to the extent practical due to limited or lack of available access. There were no recordable indications requiring further evaluation noted in any of the volumetric examinations performed. For single-sided examinations of stainless steel or inconel welds, shear wave inspections were supplemented through additional scans that employed refracted longitudinal (RL) wave techniques. The examinations were conducted, and satisfactory results were confirmed, even though "essentially 100%" coverage was not attained.
Additionally, multiple VT-2 examinations were performed on the subject components throughout the interval during the required system pressure tests (examinations required by ASME Section XI and Generic Letter 88-05) and no evidence of leakage was observed at these components, providing additional assurance that the structural integrity of the subject components was maintained throughout the interval.
ISI ProgramPlan Braidwood Station Units 1 & 2, Second Interval 10 CFR 50.55a RELIEF REQUEST 12R-50 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)
Braidwood Station Limited Examinations Revision 0 (Page 3 of 4)
In addition to the periodic visual inspections performed under ASME Section XI and Generic Letter 88-05, reactor coolant pressure boundary leakage is monitored through a number of other activities, which provide a high level of confidence that in the unlikely event that leakage did occur, it would be detected and proper action taken. Specifically, system leak rate limitations imposed by Technical Specification 3.4.13, "RCS Operational Leakage," as well as the reactor makeup control system, reactor cavity and containment floor drain sump monitoring, containment radiation monitoring, and containment atmospheric monitoring, provide additional assurance that any leakage would be detected prior to gross failure of these components.
7.0 DURATION OF PROPOSED ALTERNATIVE:
Relief is requested for the Second 10-Year Inservice Inspection (ISI) Interval for Braidwood Station Units 1 and 2. For the examination categories under this relief, the Second Interval for Braidwood Unit 1 began on July 29, 1998, and will end on July 28, 2009 (interval end date was adjusted as allowed by IWA-2430(d)). The Second Interval for Braidwood Unit 2 began on October 17, 1998, and concluded on October 16, 2008.
8.0 PRECEDENTS
Similar relief requests for limitations resulting in examination coverage less than 90%
have been approved for other operating units throughout the Braidwood inspection interval. Attachments 1 and 2 reference other units where similar limitations existed and the achieved examination coverage was less than 90%.
9.0 ATTACHMENTS
Attachment 1: Braidwood Station Unit 1 Limited Examinations Attachment 1-1: Braidwood Station Unit 1 Limited Examinations (1 page total)
Attachment 1-2: Weld 1 RV-03-001 (22 pages total)
Attachment 1-3: Weld 1 PZR-01 -N2 (13 pages total)
Attachment 1-4: Weld 1 PZR-01 -N3 (19 pages total)
Attachment 1-5: Weld 1 RC-1 7-13 (7 pages total)
Attachment 1-6: Weld 1 SG-05-SGSE-02 (9 pages total)
Attachment 2: Braidwood Station Unit 2 Limited Examinations Attachment 2-1: Braidwood Station Unit 2 Limited Examinations (1 page total)
ISI ProgramPlan Braidwood Station Units 1 & 2, Second Interval 10 CFR 50.55a RELIEF REQUEST 12R-50 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)
Braidwood Station Limited Examinations Revision 0 (Page 4 of 4) -2: Weld 2RV-03-001 (13 pages total) -3: Weld 2PZR-01 -N2 (24 pages total) -4: Weld 2PZR-01 -N3 (29 pages total) -5: Weld 2SG-01-SGC-02 (7 pages total)
ATTACHMENT 1 Braidwood Station Unit 1 Limited Examinations
ISI Program Plan Braidwood Station Units 1 & 2, Second Interval 10 CFR 50.55a RELIEF REQUEST 12R-50 Attachment 1-1 Braidwood Station Unit 1 Limited Examinations Revision 0 (Page 1 of 1)
Component ID Outage Cumulative Reference Remarks Code Category Examined Examination Sketch/Coverage Code Item Month/ Coverage Plot Year Achieved 1RV-03-001 Al R07 88.65% Attachment 1-2 Reactor Vessel Upper Head-to-Flange Category B-A (9/1998) weld. Examination coverage for surface Item B1.40 examination (magnetic particle) was 100%
with no recordable indications, no recordable indications noted in any of the ultrasonic scans.
1PZR-01-N2 Al R07 69.84% Attachment 1-3 Pressurizer Spray Nozzle-to-Shell Weld.
Category B-D (9/1998) Nozzle bore geometry recorded on 70 Item B3.110 degree scan.
1PZR-01-N3 Al R07 73.6% Attachment 1-4 Pressurizer Relief Nozzle-to-Shell Weld.
Category B-D (9/1998) Nozzle bore geometry recorded on Item B3.110 70 degree scan.
1RC-17-13 A1R12 50% Attachment 1-5 Pipe-to-Valve weld under Risk Informed Category R-A (4/2006) Program; single-sided examination from Item R1.20 pipe side only. No recordable indications noted in any of the ultrasonic scans performed.
1SG-05-SGSE-02 A1R13 79% Attachment 1-6 Steam Generator Aux Feedwater Nozzle-to-Category R-A (10/2007) Safe End weld; scanning limitation on Item R1.20 nozzle side axial scans due to nozzle geometry. No recordable indications noted in any of the ultrasonic scans performed.
ISI ProgramPlan Braidwood Station Units 1 & 2, Second Interval 10 CFR 50.55a RELIEF REQUEST 12R-50 Attachment 1-2 Braidwood Station Unit 1 Limited Examinations Revision 0 (Page 1 of 19) 1.0 Component Weld Number: 1 RV-03-001 Code Category / Item: B-A / B1.40 Configuration: Reactor Vessel Head-to-Flange Weld
2.0 Applicable Code Edition and Addenda
ASME Section Xl 1989 Edition with no Addenda (including Mandatory Appendices)
3.0 Applicable Code Requirement
Table IWB-2500-1, Examination Category B-A, requires volumetric examination of Item B1.40 (Head-to-Flange welds). Table IWB-2500-1 Note (2) states essentially 100% of the weld length shall be examined.
Figure IWB-2500-5 depicts the required examination volume (A-B-C-D), which includes the circumferential weld and the adjacent base metal on either side of the weld extending to a distance of one-half the thickness of the wall from the extremities of the weld crown.
ASME Section Xl Mandatory Appendix I requires ultrasonic examination of vessel welds greater than 2" thick to be conducted in accordance with ASME Section V, Article 4.
ASME Section V, Article 4 requires:
T-441.3.2.4 Extent of Scanning: Wherever feasible, the scanning of the examination volume shall be carried out from both sides of the weld on the same surface. Where the configuration or adjacent parts of the component are such that scanning from both sides is not feasible, this fact shall be included in the report of the examination.
T-441.3.2.5 Angle Beam Scanning: Wherever feasible, each examination shall be performed in two directions, i.e., approaching the weld from the opposite directions and parallel to the weld from opposite directions.
T-441.3.2.6 Scanning for Reflectors Oriented Parallel to the Weld: The angle beam search units shall be aimed at right angles to the weld axis, with the search unit manipulated so that the ultrasonic beams pass through the entire volume of weld metal.
The adjacent base metal in the examination volume must be completely scanned by two angle beams, but need not be scanned by both angle beams from both directions.
Code Case N-460, which accepts a reduction in examination coverage provided the reduction is less than 10%.
ISI ProgramPlan Braidwood Station Units 1 & 2, Second Interval 10 CFR 50.55a RELIEF REQUEST 12R-50 Attachment 1-2 Braidwood Station Unit 1 Limited Examinations Revision 0 (Page 2 of 19) 4.0 Impracticality/Burden The reactor vessel head-to-flange weld has a nominal thickness of 7.0" and is clad with stainless steel on the inside diameter surface. The surface geometry of the flange obstructs the ultrasonic transducer movement that is needed to examine the Code required volume from the flange side. The propagation for the ultrasonic beam was in the shear mode. Normally this mode would allow the ultrasonic beam to reflect off the inside surfaces and create a two-beam axis at right angles to each other; however, the presence of the stainless steel cladding precludes the ultrasound beams from reflecting at the inside diameter from the head/cladding interface. In addition to the examination limitations encountered due to the flange configuration and inside diameter cladding, additional examination restrictions are caused by the presence of three lifting lugs located on the reactor vessel head. These limitations preclude complete coverage of the full volume for the required scanning directions mandated by ASME Section V and Section XI. These limitations are inherent to the original design of the reactor vessel head. Conformance with the ASME Section Xl requirements for essentially 100% of the volumetric coverage would require extensive structural modifications to the reactor vessel head.
5.0 Alternative Examinations or Testing In addition to performing the 0, 45, and 60 degree ultrasonic scans required by Appendix I, additional 30 and 40 degree ultrasonic scans were performed in lieu of the 70 degree scan as permitted by Section V, Article 4, T-441.3.2.1, to supplement coverage. The calculated volumetric coverage achieved for all combined scans was documented as 88.65%.
The Code required surface examination area (B-E as depicted in Figure IWB-2500-5) was fully achieved (100% coverage) utilizing the magnetic particle method. In addition to the required surface examination, numerous system leakage tests (ASME Section XI Category B-P and Generic Letter 88-05) at nominal system operating pressure (2235 psig) and temperature (5570 F) as well as bare metal visual examinations of the upper reactor head associated with the First Revised Order EA-03-009 have been completed with no evidence of leakage associated with the reactor vessel head-to-flange weld noted during the course of the interval.
Radiography (RT) is not a desired option because RT is limited in the ability to detect expected degradation mechanisms such as service induced cracking. Additionally, RT has not been qualified through performance demonstration.
ISI ProgramPlan Braidwood Station Units 1 & 2, Second Interval 10 CFR 50.55a RELIEF REQUEST 12R-50 Attachment 1-2 Braidwood Station Unit 1 Limited Examinations Revision 0 (Page 3 of 19) 6.0 Justification for Granting Relief No additional examinations were completed during the inspection interval; however, the aggregate examination coverage achieved (88.65%) along with the results of the completed surface examination, system pressure tests, and bare metal visual inspections performed throughout the inspection interval provide reasonable assurance that pressure boundary integrity has been maintained for this component. There were no recordable indications (other than geometric conditions) noted during any of the examinations (surface, volumetric, and visual) performed during the course of the interval.
7.0 Precedents Similar examination limitations for reactor head-to-flange welds were encountered and similar examination coverage was accepted for the following units:
Byron Station Units 1 and 2:
Letter from R. Gibbs (U. S. NRC) to C. G. Pardee (Exelon Generation Company, LLC),
"Byron Station, Unit Nos. 1 and 2 - Inservice Inspection Program Second Interval Relief Requests 12R-22, 12R-23, 12R-25, and 12R-53 (TAC Nos. MD4099, MD4100, MD4101, MD4102, MD4103, MD4104, MD4105, and MD4106)," dated January 15, 2008
Relief Request 12R-50 Attachment 1 - 2 NOT-C-30 Component: 1RV-03-001 Page 22 of 25 REV. 05 Sheet 4 of - February, T998 EXAMINATION DATA SHEET Stauon: * ,2*iD%..oj - Unit L Data: IJI-h9 Page.L.of Calibration Sht*#:00 B4 (<.~ Circ. qgpMt -tA,':- yj)AData Sht# le.-AL- 1 System C-I g_£ 0 Component* .I V- 03 "*o Weld-Type AfAcTalz H40E - 4'4 Component Size !2 .. ScheduleiThicknesa '7 i. Material C-5/s" c £A0 Component Temp. / 1.0.0 7501 Z It 2 is coupaiant UL7/ZAe~;Ix Batch#, !jK2;M Scan Gain: Axlial 1/ Circ. / Straight Beam 9.3 d&
Lo Reference Point: ... We Reference Point: *.
PerfomedI Indircaonh YES NO 1JO YES I. Base Metal Straight Beam IYI
- 2. Angle BeMr-Normal-Against Flow
- 3. Angle Beamn.Nomal-Wtt Flow 'V/A
- 4. Angle Beam-Along Weld-CW VI/A
- 5. Angle Beam-Along Weld-CCW boll,
- 6. Stisaght Beam of Weld
- 7. Thickness Across Weld and Base Metal UP STRM1 WELD ON STRM Additional Comments N'O gEo dbALS- 4rICTav Examiner~s): Level: D Date: 9//'//9B Reviewer Level: J Date: )o-4-9S
.AI'ersý _____. Date: L Oate: /
Relief Request 12R-50 Attachment 1 - 2 NOT-C-30 Component: 1RV-03-001 Page 22 of 2 REV. 05 Sheet 5 of .'.,j*, .ebruarv. 199 EXAMINATION DATA SHEET Station: 524 .1,0 A Unit 1. Oats: '?I f/92ý Page of Calibration Sht#t Axial39Ms& Circ. jq -'~sr 54Ds Sht# ýIsa-System R
£C,5I , Component#0 1 V9 100( WeldType RE..A.ThV/.- q4, Component Size " SchsouleaThickness 7.4 Matenal C/S$ Ic ,4J0 component Temp. /10 . it o 4 " _S Coupiant uk' 6tl,'kt 8at=
Scan Gain: Axial ./.i Circ. L Stuight Beam ,
Lo Reference Point:_________________ Wo Reference Point: wx A, Performed lndcaUons YES NO NO YES
- 1. Bsed mews Sbvight Beam
- 2. Angle Beam-Nomai.Againh: Flow 4 -
- 3. Angle 8eam-Nomiai-With Flow . A
- 4. Angle Seam-Along VOWM~dC
- 5. Angle Beam-Along Weld-CCW ..--
- 6. Sbtight Beiam of Weld I 'I
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~dhers:Level: 7T Date:
__ _ _ _ __ _ _ _ _ __ _ _ _ _ __ _ _ _ _ 4,3n ate:
Relief Request 12R-50 Attachment 1 - 2 NDT-C-30 Component: 1RV-03-001 Page 22 of 2t REV. 05 Sheet 6 of 1q February, 199:
EXAMINATION DATA SHEET Station: ________unit Date: '711 *49i PagejfofI System C t P, Component# JAV-o3 -*O WeldType -,-'CTC/a-4l) -)e4 Component Size 4ý!R SchedulaeThicxness ___7 ___a Matenai C-5 A44 Component Temp. I1.o.# ?
_75ý/ 12 1 .. copiam y A6.Ift4 r Bathrsaco Scan Gain: Axial 70 a& .clP .... it SbigstBeam N.A Lo Reference Point: Wo Reference Point:
YES NO NO YES
- 1. ese MeM taight seam N/A
- 2. Angle Seam-Normwa-Aganst Flow 4
- 3. Angle ,eam-NormaihFo-w Alow
- 4. Angle Seamn-Along Weld-CW -N
- 5. ANV141 Sear-Along Weld-CCW 2 S. Straight Seam of Weld
- 7. Thicnwess Across Weld and Base Metal * -
UP STRM WELD I ON STRM Additional Comments
.... V o fF" V, A84k114 ,,",-,-
b t 77o j t 1 Examiner(s): Level: ]- Oate: </'/"8 evwe ___________________ _Level: D Date: /-'0 4 ..LL... ... . .
Relief Request 12R-50 Attachment 1 - 2 NOT4C5 Component: I RV-03-001 Page 22 of 251:
REV. 05 Sheet of I February; 199S J I II I I JI I II I I I I IIII I Illlll i I m II EXAMINATION DATA SHEET Stat~on: ___________oP__ Unit.... Date: 111-4,1? L Page of I~
Calibration Sht* Axial 0 -Z-- "SCi*4rc,. 1S-W- 0.Data Sht# . -*-c, System . Component # &V- Weld'Type .. /, - ,4,V Component Size .~..SclheauleThickness ? Material cS/9$4'0 Component Temp. i i.0., ?. / Ii 5,,. Couplant U Batcl6,# 0 sa=
Scan Gain: Axial 3d . Ckm- 3JR2 _ soight Seami L~o Reference Palm:. d Wo Reference Palm: A,
- 1. Base Metal Straight Beam Angle Sw-oilAantFkow
- 3. Angle Beam-onal-Wth Plow
- 4. Angle Seam-A" Weld-CW
- 5. Angle Seam-Along Weld-CCW
E.xain~ercsi A/AýJ ~ ~ : Ž Level: Date: _ .______
Level: o ate: yo-L9A
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rRelief Request 12R-50 Attachment 1 - 2 Component: 1RV-03-001
.A, Sheet i of IOj Attachment 1 Report # 98BRI-UTD-052 PAGE, 2OF 13 Coverage Summary SITE: Braidwood UNIT.- ONE SYSTEM: Reactor Vessel ELD I: 1RV-03-01 Examiner: Level:: Z-COPFIG: to Flange Examiner:,'. N Ael:
,s-d I ý FLOW Procedure # NDT-Z-1 Calibration Sht. # 988R1-UTC- 53,54,55,58 &57 NDE METHOD
SUMMARY
Wag.45" (2.25"WELD CROWN AND 3.60" (T) SIDE 3.60' (B) SIDE) .T.= 7.201WELD LENGTH = 525.15. .
otal Weld Metal Volume 5823.91 In.. as Metal Volume- 31503.81 i1W Bsota WVELD METAL EXAMINATION . .'BASE METAL EXAMINATiON*
SCAN EXAM VOLUME I TOTAL VOLUME = % EXAM SCAN EXAM VOLUME / TOTAL VOLUME % EXAM 5823.91"/ 5823.91s 100.00% 0. 25180.00 Ini/,,31503.81 Ini 79.88%.
0 (BS 4721.08"I/ 5823.91" 81.07% 46' 30789.61 ir / 31503.81 inr 97.73%
30'M 5823.91"s 15823.91"- 100.00% ,0° 30939.27 in"/ 31503.81 In' 98.21%...
40* (8) 2883.07"/ 15823.91"' 49.50% 45" CW 25180.00 In"131503.81 Inri 79.86%
3 4 5817.97"15823.913 99.90% 45' CCW 25180.00 in' , 31503.81in 79.8i%
45° CW 5823.91"' 15823.91"3 100.00% 60' CW 25160,00 In' 131503.81 In . 79.86%
.5' 582191". /5823.91"' 100.00% 50- CCW 25180.00 in31503.81In' 79188%
80° CW 5823.91"2 / 5823.91"2 100.00% TOTAL 595.24% + 7 -85.03% BMV EXAMINED 60' CCW 5823.91"' /5823.91"' 100.00% 1......."..... .......
TOTAL 830.47 %+ 9 =92.27 % WMV EXAMINED, (92.27 % + 85.03 % + 2 = 88.65 %.EXAMINATION COVERAGE r " _* : . ... ~ * . .: :.1 ...
L.~A-~
I IRV-03-01 W.:a material Percent Calculated Comments 0" 100%
81.07% 30' used to.supplement 45%, % coverage was based on 30" See sketch Coy. 2 45' T 100% 30" used to supplement 45", % coverage was based on 300 60, B 49.50% 40" used to supplement 60", % coverage was based on 40" See sketch Cov. 1 60* T 99.90% 40" used to supplement 60", % coverage was based on 40" See sketch Cov. 3 45" CW 100% B C 45" CCW 100% 0 600 CW 100% Average 60" CCW 100% 92.27%
0*
SooD Base Material Percent Calculated Comments 0* 0 79.86% See sketch Cov. 6 43.' 97.73% See sketch Cov. 4 60" 98,21% See sketch Coy. 5 45' CW 79.86% See sketch Coy. 6 C0 45" CCW 79.86% See sketch Coy. 6 60" CW 79.86% Average See sketch Coy. 6 60" CCW 79,86% 85.03% See sketch Coy. 6 "B" Flange side of weld "T' head side of weld Total Weld Metal 92.27%
Tolal Base Material 85.03%
Total Examination Coverage 88.65%
Signed By: /Z - Reviewed By: ./ , t ." -. ar . .
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...... EXAMINATION DDATA SSHEET EXAMINATION.
Station, _____________a Unit ~..Dte /q/ ~ P geo Calitration Sht
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- 2. Angie Beam-NgfrmalAgamnst Flow
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- 4. Angle Beam-Along Weld-CW
- 5. Angie Beam-Along Weld-CCW
- 8. Staight Beas of Welda -V /
- 7. Thkclness Across Weld ana lBase Metal UP STRM WELD ON STRM Additional Comments Ia1V 'Fr"bAd1WS 4ýVZ1G4AT7aVS - /V-Cl 4LET X4AM PEy1Z~oX~1"iD2 reAIVrApj£U7 L~
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ISI ProgramPlan Braidwood Station Units 1 & 2, Second Interval 10 CFR 50.55a RELIEF REQUEST 12R-50 Attachment 1-3 Braidwood Station Unit 1 Limited Examinations Revision 0 (Page 1 of 13) 1.0 Component Weld Number: 1PZR-01-N2 Code Category/ Item: B-D / B3.1 10 Configuration: Pressurizer Spray Nozzle-to-Vessel Weld
2.0 Applicable Code Edition and Addenda
ASME Section Xl 1989 Edition with no Addenda (including Mandatory Appendices)
3.0 Applicable Code Requirement
Table IWB-2500-1, Examination Category B-D requires volumetric examination of Item B3.1 10 (Pressurizer Nozzle-to-Vessel welds).
Figure IWB-2500-7(b) depicts the required examination volume (A-B-C-D-E-F-G-H), which includes the actual circumferential weld and adjacent base metal on either side of the weld extending to a distance of one-half the thickness of the wall from the extremities of the weld crown.
ASME Section Xl Mandatory Appendix I requires ultrasonic examination of vessel welds greater than 2" thick to be conducted in accordance with ASME Section V, Article 4.
ASME Section V, Article 4 requires:
T-441.3.2.4 Extent of Scanning: Wherever feasible, the scanning of the examination volume shall be carried out from both sides of the weld on the same surface. Where the configuration or adjacent parts of the component are such that scanning from both sides is not feasible, this fact shall be included in the report of the examination.
T-441.3.2.5 Angle Beam Scanning: Wherever feasible, each examination shall be performed in two directions, i.e., approaching the weld from the opposite directions and parallel to the weld from opposite directions.
T-441.3.2.6 Scanning for Reflectors Oriented Parallel to the Weld: The angle beam search units shall be aimed at right angles to the weld axis, with the search unit manipulated so that the ultrasonic beams pass through the entire volume of weld metal.
The adjacent base metal in the examination volume must be completely scanned by two angle beams, but need not be scanned by both angle beams from both directions.
T-441.3.2.7 Scanning for Reflectors Oriented Transverse to the Weld: The angle beam search units shall be aimed parallel to the axis of the longitudinal and circumferential welds. The search unit shall be manipulated so that the ultrasonic beams pass through
ISI ProgramPlan Braidwood Station Units 1 & 2, Second Interval 10 CFR 50.55a RELIEF REQUEST 12R-50 Attachment 1-3 Braidwood Station Unit 1 Limited Examinations Revision 0 (Page 2 of 13) of the examination volume. Scanning shall be done in two directions 180 degrees to each other to the extent possible. Areas blocked by geometric conditions shall be examined from at least one direction.
Code Case N-460, which accepts a reduction in examination coverage provided the reduction is less than 10%.
4.0 Impracticality/Burden The pressurizer vessel spray nozzle-to-vessel weld is approximately 2.7" thick. The pressurizer nozzle and vessel are clad with stainless steel on the inside diameter surface. The geometry of the nozzle along with the presence of the cladding on the inside diameter of the pressurizer result in limited access to the entire examination volume. The propagation for the ultrasonic beam was in the shear mode. Normally this mode would allow the ultrasonic beam to reflect off the inside surfaces and create a two-beam axis at right angles to each other; however, the presence of the stainless steel cladding precludes the ultrasound beams from reflecting at the inside diameter from the shell/cladding interface. The nozzle geometry tapers away from the weld resulting in limited scanning surfaces available for transducer coupling on the nozzle side of the weld resulting in additional examination limitations. These factors result in limited examination coverage from the scan directions required by ASME Section V and Section XI. These limitations are inherent to the original design of the pressurizer vessel. Conformance with the ASME Section Xl requirements for essentially 100% of the volumetric coverage would require extensive structural modifications to the pressurizer vessel.
5.0 Alternative Examinations or Testing In addition to performing the 0, 45, 60, and 70 degree scans to the extent practical as required by Appendix I, additional 30 and 40 degree scans were performed to supplement coverage. The aggregate examination coverage achieved was 69.84%.
In addition to completing the required volumetric examination to the extent practical, numerous system leakage tests (ASME Section Xl Category B-P and Generic Letter 88-05) at nominal system operating pressure (2235 psig) and temperature (5570 F) as well as the bare metal visual examinations associated with NRC Bulletin 2004-01 of the upper pressurizer vessel head were completed with no evidence of leakage associated with the pressurizer spray nozzle-to-vessel weld noted during the course of the interval.
Radiography as an alternative is not feasible because access is not available for film placement. No alternative examinations are planned for the weld during the current inspection interval.
ISI ProgramPlan BraidwoodStation Units 1 & 2, Second Interval 10 CFR 50.55a RELIEF REQUEST 12R-50 Attachment 1-3 Braidwood Station Unit 1 Limited Examinations Revision 0 (Page 3 of 13) 6.0 Justification for Granting Relief No additional examinations were completed during the inspection interval; however, the examination coverage of 69.84% along with the results of the pressure test and bare metal visual inspections provide reasonable assurance that pressure boundary integrity has been maintained for this component throughout the interval.
7.0 Precedents Similar examination limitations for pressurizer spray nozzle-to-shell welds were encountered and similar examination coverage was accepted for the following units:
Byron Station Units 1 and 2:
Letter from R. Gibbs (U. S. NRC) to C. G. Pardee (Exelon Generation Company, LLC),
"Byron Station, Unit Nos. 1 and 2 - Inservice Inspection Program Second Interval Relief Requests 12R-22, 12R-23, 12R-25, and 12R-53 (TAC Nos. MD4099, MD41 00, MD4101, MD4102, MD4103, MD4104, MD4105, and MD4106)," dated January 15, 2008 Callaway Unit 1:
Letter from D. Terao (U. S. NRC) to C. D. Naslund (Union Electric Company), "Callaway Plant, Unit 1 - Relief Request ISI-41 for the Second 10-Year Inservice Inspection Interval (TAC No. MD3437)," dated January 18, 2007 Wolf Creek Unit 1:
Letter from D. Terao (U. S. NRC) to R. A. Muench (Wolf Creek Nuclear Operating Corporation), "Wolf Creek Generating Station - Relief Request 12R-34 for the Second Ten-Year Interval Inservice Inspection (TAC No. MD0288)," dated November 20, 2006 Catawba Unit 1:
Letter from E. C. Marinos (U. S. NRC) to D. Jamil (Catawba Nuclear Station), "Catawba Nuclear Station, Unit 1, Request for Relief 05-CN-004, Limited Weld Examinations During End-of-Cycle 15 Refueling Outage (TAC Nos. MC8337, MC9171, MC9172.
MC9199, MC9173, MC9202, MC9174, MC9175, MC9176, MC9177, MC9178 and MC9179)," dated September 25, 2006
ISI ProgramPlan Braidwood Station Units 1 & 2, Second Interval 10 CFR 50.55a RELIEF REQUEST 12R-50 Attachment 1-3 Braidwood Station Unit 1 Limited Examinations Revision 0 (Page 4 of 13)
Catawba Unit 2:
Letter from E. C. Marinos (U. S. NRC) to D. Jamil (Catawba Nuclear Station), "Catawba Nuclear Station, Unit 2, Request for Relief from the Requirements of the ASME Code (TAC Nos. MC7004, MC9197, MC9198. MC9199, MC9200, MC9202, MC9203, MC9204, MC9205, MC9206 and MC9207)," dated April 3, 2006
- 24 ol 25
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,LV.J EXAMINATION DATA SHEET STATION: L2 *-*I1 v~oot UNIT: J._ SYSTEM: PRa5uL4v4ZA DATE: 'j/Lq/29 DATA SHEET #: 2/10-- vb-S (,s b"J *Is =I** **..
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Relief Request 12R-50 Attachment 1 - 3 Report# 98BR1-UTD-764 Ciumt Component: 1PZR-01-N2 PAGE 7OF 7 Sheet 11 of 13 Coverage Summary SITE: Braidwood UNIT: ONE SYSTEM: Pressurizer WELD ID: 1PZR-01-N2 Examiner: , Level:
CONFIG: Spray Nozzle to Pressurizer Examiner Level:
FLOW Procedure # NDT-Z-1 Calibration Sht. # 98BR1-UTC- 69,70,71,72,73,74 & 75 NDE METHOD X UT _ PT MT Notes: Suoplemental Exams 30°, 400, 600 & 700 VESSEL COVERAGE
SUMMARY
W = 4.1" (1.60" WELD CROWN AND 1.30" ON EACH SIDE) T = 2.52" WELD LENGTH = 40.0""
3 Total Base Metal Volume = 306 in3 Total Weld Metal Volume = 130 in.
WELD METAL EXAMINATION BASE METAL EXAMINATION SCAN j EXAM VOLUME I TOTAL VOLUME % EXAM SCAN EXAM VOLUME / TOTAL VOLUME %EXAM 00 130.0 in3 /130.0 in3 = 100% 0° 306.0 in'/ 306.0 in3 100%
45° (B) 127.5 in 3 /130.0 ins = 98.07% 60°LB 260.8 in' /306.0 in3 85.23%
30° T) 60.0 in 3/130.0 in' = 46.15% 700 (B) 268,6 in' / 306.0 in" 87.77%
3 60"(B) 128.95 in' / 130.0 in = 99.19% 45 CW 148.2 in' / 306.0 in 3 48.40%
40° (B) 44.0 in' / 130.0 in' = 33.84% 450 CCW 148.2 in3 / 306.0 in'3 48.40%
45" CW 91.0 in' / 130.0 ins = 70.00% 600 CW 148.2 in / 306.0 in'3 48.40%
450 CCW 91.0 in/3 130.0 in' = 70.00% 60" CCW 148.2 in1/ 306.0 in3 48.40%
600CW 91.0 in' / 130.0 in' = 70.00% TOTAL 466.6 % + 7 = 66.65 % BMV EXAMINED 600 CCW 91.0 in 3
/130.0
/ in' 70.00%
TOTAL 657.25 % + 9 = 73.03 % WMV EXAMINED (73.03 % + 66.65 % ) + 2 = 69.84 % EXAMINATION COVERAGE NOTES: 300 (B) SUPPLEMENTAL FOR 450 (B) 400 (B) SUPPLEMENTAL FOR 600 (B) 60° (B) SUPPLEMENTAL FOR 450 (B) 700 (B) SUPPLEMENTAL FOR 600 (B),
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Relief Request 12R-50 Attachment 1 - 3 NDT-C-59 Component: 1PZR-01-N2 Page 17 of 19 Rev. 1 Sheet 12 of 13 Sept., 1996 EXAMINATION DATA SHEET Station: 13R/? Ib .gao Unit: I Page _ of System: PzE55$ , zw Nozzle # I PRo/-012,.A Nozzle Diameter -0 Nozzle Material: C5/ 55 cL-Ab Nozzle Temp.: ,L 1121zt Coupiant: ULMC 7r Batch # 22_ZZ Calibration Sheet# . 4 UTC,- 07 f*, Data Sheet#09 Bfe,- UrA - 0o65 g¶et- _:k t.A.T - &0W r i~ :,e Comments: "42/dA 1/MY/ '/ iI, 4 *o*,1,je"' ?"aF-1..ta7A, tP-o'* "1,18--Z*'e A.
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ISI ProgramPlan BraidwoodStation Units 1 & 2, Second Interval 10 CFR 50.55a RELIEF REQUEST 12R-50 Attachment 1-4 Braidwood Station Unit 1 Limited Examinations Revision 0 (Page 1 of 19) 1.0 Component Weld Number: 1PZR-01 -N3 Code Category / Item: B-D / B3.1 10 Configuration: Pressurizer Relief Nozzle-to-Vessel Weld
2.0 Applicable Code Edition and Addenda
ASME Section XI 1989 Edition with no Addenda (including Mandatory Appendices)
3.0 Applicable Code Requirement
Table IWB-2500-1, Examination Category B-D requires volumetric examination of Item B3.1 10 (Pressurizer Nozzle-to-Vessel welds).
Figure IWB-2500-7(b) depicts the required examination volume (A-B-C-D-E-F-G-H),
which includes the actual circumferential weld and adjacent base metal on either side of the weld extending to a distance of one-half the thickness of the wall from the extremities of the weld crown.
ASME Section Xl Mandatory Appendix I requires ultrasonic examination of vessel welds greater than 2" thick to be conducted in accordance with ASME Section V, Article 4.
ASME Section V, Article 4 requires:
T-441.3.2.4 Extent of Scanning: Wherever feasible, the scanning of the examination volume shall be carried out from both sides of the weld on the same surface. Where the configuration or adjacent parts of the component are such that scanning from both sides is not feasible, this fact shall be included in the report of the examination.
T-441.3.2.5 Angle Beam Scanning: Wherever feasible, each examination shall be performed in two directions, i.e., approaching the weld from the opposite directions and parallel to the weld from opposite directions.
T-441.3.2.6 Scanning for Reflectors Oriented Parallel to the Weld: The angle beam search units shall be aimed at right angles to the weld axis, with the search unit manipulated so that the ultrasonic beams pass through the entire volume of weld metal.
The adjacent base metal in the examination volume must be completely scanned by two angle beams, but need not be scanned by both angle beams from both directions.
T-441.3.2.7 Scanning for Reflectors Oriented Transverse to the Weld: The angle beam search units shall be aimed parallel to the axis of longitudinal and circumferential welds.
The search unit shall be manipulated so that the ultrasonic beams pass through all of the examination volume. Scanning shall be done in two directions 180 degrees to each
ISI ProgramPlan Braidwood Station Units 1 & 2, Second Interval 10 CFR 50.55a RELIEF REQUEST 12R-50 Attachment 1-4 Braidwood Station Unit 1 Limited Examinations Revision 0 (Page 2 of 19) other to the extent possible. Areas blocked by geometric conditions shall be examined from at least one direction.
Code Case N-460, which accepts a reduction in examination coverage provided the reduction is less than 10%.
4.0 Impracticality/Burden The pressurizer vessel relief nozzle-to-vessel weld is approximately 2.7" thick. The pressurizer nozzle and vessel are clad with stainless steel on the inside diameter surface. The geometry of the nozzle along with the presence of the cladding on the inside diameter of the pressurizer result in limited access to the entire examination volume. The propagation for the ultrasonic beam was in the shear mode. Normally this mode would allow the ultrasonic beam to reflect off the inside surfaces and create a two-beam axis at right angles to each other; however, the presence of the stainless steel cladding precludes the ultrasound beams from reflecting at the inside diameter from the shell/cladding interface. The nozzle geometry tapers away from the weld resulting in limited scanning surfaces available for transducer coupling on the nozzle side of the weld resulting in additional examination limitations. These factors result in limited examination coverage from the scan directions required by ASME Section V and Section Xl. These limitations are inherent to the original design of the pressurizer vessel. Conformance with the ASME Section Xl requirements for essentially 100% of the volumetric coverage would require extensive structural modifications to the pressurizer vessel.
5.0 Alternative Examinations or Testing In addition to performing the 0, 45, 60, and 70 degree scans to the extent practical as required by Appendix I, additional 30 and 40 degree scans were performed to supplement coverage. The aggregate examination coverage achieved was 73.6%.
In addition to completing the required volumetric examination to the extent practical, numerous system leakage tests (ASME Section Xl Category B-P and Generic Letter 88-05) at nominal system operating pressure (2235 psig) and temperature (5570 F) as well as the bare metal visual examinations associated with NRC Bulletin 2004-01 of the upper pressurizer vessel head were completed with no evidence of leakage associated with the pressurizer relief nozzle-to-vessel weld noted during the course of the interval.
Radiography as an alternative is not feasible because access is not available for film placement. No alternative examinations are planned for the weld during the current inspection interval.
ISI ProgramPlan Braidwood Station Units 1 & 2, Second Interval 10 CFR 50.55a RELIEF REQUEST 12R-50 Attachment 1-4 Braidwood Station Unit 1 Limited Examinations Revision 0 (Page 3 of 19) 6.0 Justification for Granting Relief No additional examinations were completed during the inspection interval; however, the examination coverage of 73.6% along with the results of the pressure test and bare metal visual inspections provide reasonable assurance that pressure boundary integrity has been maintained for this component throughout the interval.
7.0 Precedents Similar examination limitations for pressurizer relief nozzle-to-shell welds were encountered and similar examination coverage was accepted for the following units:
Byron Station Units 1 and 2:
Letter from R. Gibbs (U. S. NRC) to C. G. Pardee (Exelon Generation Company, LLC),
"Byron Station, Unit Nos. 1 and 2 - Inservice Inspection Program Second Interval Relief Requests 12R-22, 12R-23, 12R-25, and 12R-53 (TAC Nos. MD4099, MD4100, MD4101, MD4102, MD4103, MD4104, MD4105, and MD4106)," dated January 15, 2008 Callaway Unit 1:
Letter from D. Terao (U. S. NRC) to C. D. Naslund (Union Electric Company), "Callaway Plant, Unit 1 - Relief Request ISI-41 for the Second 10-Year Inservice Inspection Interval (TAC No. MD3437)," dated January 18, 2007 Wolf Creek Unit 1:
Letter from D. Terao (U. S. NRC) to R. A. Muench (Wolf Creek Nuclear Operating Corporation), "Wolf Creek Generating Station - Relief Request 12R-34 for the Second Ten-Year Interval Inservice Inspection (TAC No. MD0288)," dated November 20, 2006 Catawba Unit 1:
Letter from E. C. Marinos (U. S. NRC) to D. Jamil (Catawba Nuclear Station), "Catawba Nuclear Station, Unit 1, Request for Relief 05-CN-004, Limited Weld Examinations During End-of-Cycle 15 Refueling Outage (TAC Nos. MC8337, MC9171, MC9172.
MC9199, MC9173, MC9202, MC9174, MC9175, MC9176, MC9177, MC9178 and MC9179)," dated September 25, 2006
ISI ProgramPlan Braidwood Station Units 1 & 2, Second Interval 10 CFR 50.55a RELIEF REQUEST 12R-50 Attachment 1-4 Braidwood Station Unit 1 Limited Examinations Revision 0 (Page 4 of 19)
Catawba Unit 2:
Letter from E. C. Marinos (U. S. NRC) to D. Jamil (Catawba Nuclear Station), "Catawba Nuclear Station, Unit 2, Request for Relief from the Requirements of the ASME Code (TAC Nos. MC7004, MC9197, MC9198. MC9199, MC9200, MC9202, MC9203, MC9204, MC9205, MC9206 and MC9207)," dated April 3, 2006
Page 24 of 25 REV.3 ly,
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1996 EXAMINATION DATA SHEET 'DI~J- i,ý1 --
STATION: jWQ4iMI/oOD UNIT: L SYSTEM: _ -_______DATE: ?-;f DATA SHEET #:Ejl-Og$
(0y")
S 98841-urc-obo COMPONENT i.D.: J*LA 3.- THICKNESS: ... *.1 MATERIAL: -3115 9_At. CALIB. SHEET 8(S): 09 q*r-ob 451$-4 COMPONENT SERIAL M: J- Oj. COMPONENT TEMP.: *F COUPLANT: Z 6Q f-,085, 709&&t-ý (Wom'l 9se..1vaot (Z?) Ol (II9') "9800-"8- cw7 0~(b, VERTICAL VESSEL UP p --
iD ~-saC-oas WELD TYPE: GIRCUMFERENTIAL LONGITUDINAL OTHER_ L o X Y &
N --
EXAMINATIONS PERFORMED GW S S 30 ta~J~ ~or I E I I fb S.q~.feA~'.} ~
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Relief Request 12R-50 Attachment 1 - 4 Report# 98BR1-UTD-066 If h
Component: 1PZR-01-N3 Sheet 17 of 19 II .. Coverage Summary Page 13 of 13 IONE SYSTEM: Pressurizer SITE: Braidwood WELD ID: 1PZR-01-N3 UNIT: ... . .
Examiner -Xy - Level:
CONFIG: Pressurizer to Relief Nozzle Examiner: dagf-* , Level:
FLOW =:/-/
Procedure # NDT-Z-1 Calibration Sht. # 98BR1-UTC- 80,81, 82, 83, 84& 85 NDE METHOD X UT PT MT Notes: Supolemental Ex-ams 300 400 &70° 46oo" VESSEL COVERAGE
SUMMARY
4.1" .1.70 WELD CROWN.AND 1.20.ON EACH SIDE) T =2 50" WELD LENGTH,= 47.10" Total Weld Metal Volume = 164.9 in. 3 Total Base Metal Volume = 319.3 in r WELD METAL EMINATION BASE, METAL EXAMINATION SCAN EXAM VOLUME / TOTAL VOLUME = % EXAM SCAN EXAM VOLUME / TOTAL VOLUME % EXAM 00 164.9 Mn 164.9 in3 = 100% 0° 319.3 in3 ./319.3,in3 . 100%=
45 (B)_ 159.1 in3 1864.9 in3
= 96.50% 60* B 257.5 in3 l 319.3 in2 80.60%
/ 164.9 in3 280.8 in' 1319.3 in3 3
30- AT)- 51.8 in= = 31.40% 70* (B) 87.70%
700 B t 162.1 in I 164.9 in3 = 98.30% 450 CW 3 155.8 in / 319.3 in' 48.80%
40° T , 42.4 in3 1164.9 in3 . 25.70% 45" CCW 155.8 in3 / 319.3 in3 48.80%
450 CW 155.5 in3 /164.9 in3 = 94.30% 60" CW 155.8 in`3 /319.3 in3 48.80%
450 CCW 155.5 in' 1 164.9 in3 = 94.30% 60- CCW 155.8 in3 / 319.3 in3 48.80%
60°CW 155.5 in3/I164.9 in' = 9430% TOTAL 463.5% + 7=66.2% BMV EXAMINED 600 CCW 155.5 in'I 164.9 in' = 94.30%
TOTAL 729,1 %+981.0.% WMVM EXAMINED (81.0 % + 66.2 % ) + 2 = 73.6 % EXAMINATION COVERAGE NOTES: 30° (D SUPPLEMENTAL FOR 45- (T) 40" (T) SUPPLEMENTAL FOR 60"(U).
60- (B) SUPPLEMENTAL FOR 45" 6B_
70"(B3) SUPPLEMENTAL FOR 600 (Y ... .7..
4 ft l*,A-,L jiIWd1 kV..
Relief Request 12R-50 Attachment 1 - 4 NDT-C-59 Component: 1 PZR-Q1 -N3 Page 17 of 19 Rev. 1 Sheet 18 of 19 Sent.. 1996 EXAMINATION DATA SHEET Station: BIRA,Lb oo b Unit: I Page 1 of -
System: _ _ _-E_ ___ u /Z _ __.E_ _ Nozzle # / Pz/Z. o- - Al3 Nozzle Diameter: 6. o Nozzle Material: C S / 5S CA b4f Nozzle Temp.:.... ?4"p/i*,//
'...... )5
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Aft - o,* ('ZVoTUQ-7"TAG-F- Z Couplant: Batch # 7S ,2.,5 Calibration Sheet# ý788_t- U Data Sheet # 4 /-'rbV88 - -7 ...
Comments: l9k~diwiz/ 0/ ai-f A 0aft &~5=11f 9f$ - TO Af4 bc,# :56o .i48-Tar ~ 67 -e20.Z EXAM. IND. AZIMUTH / DISTANCE SCAN MAX. SWEEP 0/V°) EVALUATION NO. NO. LENGTH (L-) AXIAL (W*) CW/CCW AMP. START MAX. STOP COMMENTS 7D / V
____________A(_____ tam__________________________1 6 M d M__________________
Examiner(s):~
J4.7,
~ Z2~d. Level: 4 Date: q7/' 1 0 // 7 &
Reviewer: 2T~ /ýý49 Level: D7 Date: '9-z 0-&
F I Others: /I Level: ff Date: l o-z-Tr Station: Date: A-4.f P ANII: Date: - -2!,-
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ISI ProgramPlan Braidwood Station Units 1 & 2, Second Interval 10 CFR 50.55a RELIEF REQUEST 12R-50 Attachment 1-5 Braidwood Station Unit 1 Limited Examinations Revision 0 (Page 1 of 7) 1.0 Component Weld Number: 1 RC-17-13 Code Category / Item: R-A / R1.20, Elements not Subject to a Damage Mechanism Configuration: Pipe-to-Valve Circumferential Weld
2.0 Applicable Code Edition and Addenda
ASME Section Xl 1989 Edition with no Addenda
3.0 Applicable Code Requirement
Table IWB-2500-1, Examination Category B-J, Figure IWB-2500-8(c) as supplemented by Figure 4-3 of EPRI TR-112657 Revision B-A (Reference 8.1).
Figure 4-3 of Reference 8.1 depicts the required examination volume (A-B-C-D), which includes the lower 1/3 thickness of the circumferential weld. There was no counterbore detected, so the volume 1/2" each side of the weld toes (shown in Figure 4-2 of Reference 8.1) was use to define the required examination volume.
As required by 10 CFR 50.55a, ASME Section XI 1995 Edition with 1996 Addenda Appendix VIII, Performance Demonstration for Ultrasonic Examination System was used for examination procedures, equipment, and personnel.
Code Case N-460, which accepts a reduction in examination coverage provided the reduction is less than 10%.
4.0 Impracticality/Burden This austenitic stainless steel pipe-to-valve weld and associated base materials are 4" NPS with a nominal wall thickness of 0.531" (Schedule 160) and forms the break between the "RC" and "RY" subsystem for the pressurizer spray line. Under the Braidwood Risk-Informed ISI Program, the welds associated with this particular piping segment are considered Category R-A, Item R1.20 which are not subject to any specific degradation mechanisms. This weld had been examined during the first ISI inspection interval as a "structural discontinuity" and was reselected again in the second interval under the Risk-Informed ISI Program. These examinations were performed using examination procedures and personnel qualified under the Performance Demonstration Initiative (PDI) program administered through the EPRI NDE Center, specifically, PDI-UT-2 which is qualified for manual IGSCC detection and length sizing for austenitic stainless steel welds. The PDI procedure is not qualified for the detection of flaws on the far side of single sided access examinations on austenitic stainless steel piping welds. The valve geometry tapers away from the weld resulting in limited scanning
ISI ProgramPlan Braidwood Station Units 1 & 2, Second Interval 10 CFR 50.55a RELIEF REQUEST 12R-50 Attachment 1-5 Braidwood Station Unit 1 Limited Examinations Revision 0 (Page 2 of 7) surface available on the valve side. Volumetric examinations were also completed on five additional Category R-A, Item R1.20 welds upstream of this weld during the same refuel outage. The limited access of some welds or the presence of component supports adjacent to other welds on the line limited the population of welds for this particular segment.
5.0 Alternative Examinations or Testing In accordance with PDI-UT-2 requirements, axial and circumferential 45 degree shear wave scans and axial 60 degree refracted longitudinal wave (RL) scans of this weld were performed to the extent practical. The aggregate examination coverage achieved was 50%.
In addition to completing the required volumetric examination scans to the extent practical, numerous system leakage tests (ASME Section Xl Category B-P and Generic Letter 88-05) at nominal system operating pressure (2235 psig) and temperature (5570 F)
Were completed with no evidence of leakage associated with this weld noted during the course of the interval.
The required 100% coverage was attained for the remaining five welds with no recordable indications noted in any of the welds. Since all six of these welds experience the same system conditions without any known degradation mechanism, reasonable assurance exists that there is no adverse condition associated with population of welds including the weld where limited inspection coverage was achieved.
Radiography (RT) is not a desired option because RT is limited in the ability to detect expected degradation mechanisms such as thermal fatigue cracking and stress corrosion crack initiating at the pipe inside surface. Additionally, RT has not been qualified through the performance demonstration process.
6.0 Justification for Granting Relief No additional examinations were completed during the inspection interval; however, the examination coverage of 50% along with the results of volumetric examinations performed on the other five welds in the population, as well as the numerous pressure tests completed over the course of the interval provide reasonable assurance that pressure boundary integrity has been maintained for this component.
7.0 Precedents Similar single-side limitations and associated limited examination coverage on Risk-Informed welds were encountered and accepted for the following units:
ISI ProgramPlan Braidwood Station Units 1 & 2, Second Interval 10 CFR 50.55a RELIEF REQUEST 12R-50 Attachment 1-5 Braidwood Station Unit 1 Limited Examinations Revision 0 (Page 3 of 7)
Comanche Peak 2:
Letter from J. N. Donohew (U. S. NRC) to M. R. Blevins (Luminant Generation Company, LLC), "Comanche Peak Steam Electric Station, Unit 2 - Request for Relief B-2 for Second 10-Year Inservice Inspection Interval from 10 CFR 50.55a Inspection Requirements Due to Physical Interferences (TAC No. MD7527)," dated August 22, 2008 Prairie Island 1:
Letter from L. M. James (U. S. NRC) to M. D. Wadley (Prairie Island Nuclear Generating Plant), "Prairie Island Nuclear Generating Plant, Unit 1 - Relief Request 1-RR-4-6 for Piping Weld Examination Coverage for the Fourth Inspection Interval (TAC No.
MD5593)," dated May 9, 2008 8.0 References 8.1 EPRI TR-1 12657 Revision B-A, "Revised Risk-Informed Inservice Inspection Evaluation Procedure"
SZWestinghouse Calibration Data Sheet Plant I Unit BRAIDWOOD i 1 Data Sheet # A1R12-UT-046 Company EXELON Page 1 of 4 Comp I System RC Procedure No. EXE-UT-350 Cal. Checks Time Rev/ Chng. No. 1 Cal. Block No. 103471 0810 Initial Calib.
Cal. Block Temp. 75° Thermometer S/N: 104246 Initial Calib. Date 4121106 Size 4" Sch. 0.531" Es Ferritic 0 Austenitic Intermediate N/A Search Unit #1
\ Search Unit #2 Each Major CRT Div. = 010" Manufacture: KBA Intermediate N/A Serial No.: 57462976.3 C)-7 Cal. Direction: JoAxial S Circ. Eq Both Final Calib. 1206 No. of Elements: 2 o cD Size: 2 (3.5 x 10) Shape: Rect.
Scan Area: to Weld [ Freq. 4.0 MHz Style: MSEB4E CD Final Calib. Date 4/21/06 0 to Weld Exam Angle: 0° Mo .Long.
"(DC Couplant Measured Angle;.' N/A ULTRAGEL i1 =J = C Code Category: R-A Code Item: R01.20 Type: Wedge Style: Integral Batch: 04325 D FF -0 Search Unit Cable (D o:
Y Y --
Recordable Exam Access IndicatIons Type: RG-174 Sons.
Examination Area I Weld Yes, INo Geom Length: 6V No. of Con.: 0 IRC-17-13 Both Instrument Settings Instrument SAe Make I Model: Krautkramer USN 58L SW Serial No.: SAP 104391 Delay: 0.000 Range: 1.0" M'd Cal I Vel: 0.2262 Pulser: Square Damping: 500 Reject: 0%
Remarks I Reason for Incomplete Scan(s) COMPONENT TEMP: 60" Rep. Rate: Auto High Freq: 4.0 MHz 00 cal for thickness and contour only. Filter. Fixed Mode: Dual Rectify: Fullwave Voltage: 450 Pulse Width: 250 Examimner:,~ .rlNLk114 Level II Date 4EIlUb Reference Sensitivity (Sens.)
Level II Date 4/21/06 Axial: 34.0 Circ: NIA SDH Sensitivity: NIA Reviewers: Further Evasuation Required? IrN/es rXINo Zero: 9.3644_
TE/Jjd~
t~f-LONkVELaRCV"DATE / rIMEW DA '2 'd II
- H)Westinghouse Calibration Data Sheet Plant I Unit BRAIDWOOD / I Data Sheet # A1R12-UT-046 Company EXELON Page 2 of 4 Comp / System RC Procedure No. EXE-PDI-UT-2 Cat. Checks Time Rev / Chng. No. 4 Cal. Block No. 4654 1103434 Initial Calib. 0820 Cal. Block Temp. 75° Thermometer SIN: 104246 Initial Calib. Date 4121106 Size 4" Sch. 0.531" "1" Intenredfiate N/A Fenritic [] Austenitic Search Unit #1 Search Unit #2 Each Major CRT Div. = 0.15" Intermediate WA Manufacture: KBA Manufactu 0 M1 Serial No.: 009R21 Serial No.: \ _q >
Cal. Direction: r Axial 0 Circ. a Both Final Calib. 1215 No. of Elements: 1 No. of Elleme s: CU) -
CD Size: .25" Shape: Round Size: Shape (
Scan Area: .L to Weld rn Freq. 2.25 MHz Style: Comp-G Freq. Style: D 2D0ý Final Caiib. Date 4U21/08 II to Weld Exam Angie: 45" Mode: Shear Exam Angle. - 3.,CD coupl"n Measured Angle: 45" Measured Angle: 0 ". (D C,)
Code Category: R-A Code Item: R01.20 Type: ULTRAGEL II Wedge Style: MSWQC Wedge Style: -"
Batch: 04325 D Search Unit Cable Search nit Cab[ --4 CTI Recordable 0ý Exam CA)
Access Indications Type: RG-174 Type:
Yes NoGeom Sens.
i::aminatinn Area ! Weld Length: 6 No. of Con.: 0 Length: No. Con.:
1 RC-17-13 UPST X 40.0 dB Instrument Settings Instrument S n Make I Model: Krautkramer USN 58L SW Make / Model:
Serial No.: SAP 104391 Serial No.:
Delay: 0.000 Range: 1.5" Delay: Range,:
MtI Cal/Vel: 0.1248 Pulser. Sqare Mtl Cal / wI: Pulser Damping: 500 Reject 0% Damping: __ Reject:
Remarks / Reason for Incomplete Scan(s) COMPONENT TEM- 60 Rep. Rate: Auto High Freq: 2.25 Rep. Rate: Freq:
NRI. Scanned to maintain 5% - 20% ID roll or noise. No counterbore observed, Filter Fixed Mode: Dual Off Filter: Mode:
Rectify: Fullwave Voltage: 450 Rectify: Voltage:
50% Coverage.
Pulse Width: 220 Pulse Width:,
ExamInews Level Ii Date 4/21/06 Reference Sensitivity (Sens.) Reference Sensitivity (Sens.)
Level II Date 4121106 Axial: 26.0 Circ: 26.0 Axial: Circ:
SDH Sensitivity: Far SOH 6.7 @ 20% @ 26.0dB SDH Sensitivity:
Further Evaluation Required? IN- es M No Zero: 4.7631 Zero:
ReLNLvieL. e~WIA EfBIGl I(
Westinghouse Calibration Data Sheet Plant / Unit BRAIDWOOD I I Data Sheet # AIR12-UT-046 Company EXELON Page 3 of 4 Comp I System RC Procedure No. EXE-PDI-UT-2 Cal. Checks Time Rev / Chng. No. 4 Cal. Block No. 46541103775 Initial Calib. 0800 Cal. Block Temp. 72" Thermometer SIN: 104246 Initial Calib. Date 4/24106 Size 4" Sch. 0.531" "fT Intermediate N/A Femitic Austenitic Search lUnlt #1 \SearchUnit #2 Each Major CRT Div. = 0.2" Intermediate N/A Manufacture: Megrsonics Manufi Serial No.: G0121 Seral I Cal. Direction: rWAxial f Circ. fS Both No. of Elements: 2 No. of Final Calib. 0915 Size:
Size: 0.14"x0.30" Shape: Rect.
Scan Area:* to Weld [M Freq. 4.0 MHz Style: CGD Freq.
Final Catib. Date 4124=06 toWeld Exam Angle: 60" Mode: Long. Exam Measured Angle: 60" Measu Couplant Code Category: R-A Code Item: RO1.20 Type: ULTRAGEL II Wedge Style: Integral Wedge Batch: 04325 D Search Unit Cable Recordable Indications Exam Type:
Access Type: RG-174 Yes I..No IGeom Sens.
Length: 6' No. of Con.: 0 Length:
Examination Area I Weld IRC-17-13 UPST X 58-5 d8 Instrument Settings Make I Model: Krautkrarner USN 52R Make I Model:
Serial No.: SAP 102282 Serial No.:
Delay: 0.000 Range: 2.0" Delay: Range:
Mit Cal / Vel: 0.2306 Pulser: Dual M1t Cal / Vel: Pulser: _ _
Damping: 1000 Reject: 0% Damping: _ Reject:
Remarks / Reason for Incomplete Scan(s) COMPONENT TEMP: 60" Rep. Rate: High Freq: 2-8 Rep. Rate: Freq:
NRI. Scanned to maintain 5% - 20% ID roll or noise. No counterbore observed. Filter. Fixed Mode: Fullwave Filter. Mode:
Reference Sensitivity (Sens.) Reference Sensitivity (Sens.)
50% Coverage Achieved. Exam performed from pipe side only due to valve E ,rJinn ennf*et: e ae.14 Axial: 58.5 dB Cire: NIA Axial:
SDH Sensitivity: Near SDH 3.0 ,8W%@43.5 SDH Sensitivity:
Levl 1I Date 4/24/06 Zero: 5.069 Zero:
Rnwnr Reviewers:
~ e~t Furthe Evaluation Required? MAiYes aZ~/-tv1JZ ITX No ft'Vwx I VATEE I
... *" ......... :i * :,; "'........... : :. ..."N UCL E.AR ' SERVICES * .... AAl.'
- R 12 -UT .0 r INSPECTION SERVICES Page 4 of 4 WWELD PROFILE I DATA PLANT BRAIDWOOD UNIT 1 SKETCH IRC-17. Rev. F SYST.ICOMP. RC PROCEDURE EXE-UT-350, Rev, 1 TooddGinder-and Martn Cr M,dlevell11 ...
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ISI ProgramPlan Braidwood Station Units 1 & 2, Second Interval 10 CFR 50.55a RELIEF REQUEST 12R-50 Attachment 1-6 Braidwood Station Unit 1 Limited Examinations Revision 0 (Page 1 of 9) 1.0 Component Weld Number: 1SG-05-SGSE-02 Code Category / Item: R-A / R1.20, Elements not Subject to a Damage Mechanism Configuration: Safe End-to-Nozzle Weld
2.0 Applicable Code Edition and Addenda
ASME Section Xl 1989 Edition with no Addenda
3.0 Applicable Code Requirement
Table IWB-2500-1, Examination Category C-F-i, Figure IWC-2500-7 as supplemented by Figure 4-3 of EPRI TR-112657 Revision B-A (Reference 8.1).
Figure 4-3 of Reference 8.1 depicts the required examination volume (A-B-C-D), which includes the lower 1/3 thickness of the circumferential weld. There was no counterbore detected, so the volume 1/2" each side of the weld toes (shown in Figure 4-2 of Reference 8.1) was use to define the required examination volume.
As required by 10 CFR 50.55a, ASME Section Xl 1995 Edition with 1996 Addenda Appendix VIII, Performance Demonstration for Ultrasonic Examination System was used for examination procedures, equipment, and personnel.
Code Case N-460, which accepts a reduction in examination coverage provided the reduction is less than 10%.
4.0 Impracticality/Burden The auxiliary feedwater safe end-to-nozzle weld and associated adjacent base materials are approximately 1.1" thick. This full penetration weld is Inconel 690 material but is not in contact with reactor coolant. This weld was shop fabricated and installed during the Unit 1 steam generator replacement during the Al R07 refuel outage (fall 1998). Under the Braidwood Risk-Informed ISI Program, the welds associated with this particular segment are considered Category R-A, Item R1.20, which are not subject to any specific degradation mechanisms. Due to the physical configuration of the carbon steel nozzle, which includes an adjacent taper running away from the circumferential weld, limitations preventing scanning (limitation calculated to be 35.5% for nozzle side circumferential scans) to attain coverage of 90% exist. In accordance with PDI-UT-10 requirements, 35, 40, 45, and 60 degree shear and 45 and 60 degree refracted longitudinal wave (RL) scans of this weld were performed to the extent practical. The aggregate examination coverage achieved was 79%.
ISI ProgramPlan Braidwood Station Units 1 & 2, Second Interval 10 CFR 50.55a RELIEF REQUEST 12R-50 Attachment 1-6 Braidwood Station Unit 1 Limited Examinations Revision 0 (Page 2 of 9) 5.0 Alternative Examinations or Testing These examinations were performed using examination procedures and personnel qualified under the Performance Demonstration Initiative (PDI) program administered through the EPRI NDE Center, specifically, PDI-UT-10 which is qualified for single or dual sided manual detection and circumferential length sizing for dissimilar metal welds.
In addition to performing the required volumetric examination to the extent practical, numerous system leakage tests performed at system nominal operating pressure (1005 psig) and temperature (4430 F) have been completed with no evidence of leakage associated with the auxiliary feedwater nozzle-to-safe end weld noted.
Radiography as an alternative is not feasible because access is not available for film placement. No alternative examinations are planned for the weld during the current inspection interval.
6.0 Justification for Granting Relief No additional examinations were completed during the inspection interval; however, the examination coverage of 79% along with the results of the pressure tests assure boundary integrity has been maintained for this component.
7.0 Precedents None.
8.0 References 8.1 EPRI TR-1 12657 Revision B-A, "Revised Risk-Informed Inservice Inspection Evaluation Procedure"
CAX~.C..
A Wesfllnghouse HOE Company Calibration Data Sheet Kff~'r7I.
,.Jo.Tt" Plant I Unit BRAIDWOOD / 1 Data Sheet # A1R13-UT-013 Company EXELON Page 1 of 7 Comp / System AUX FEEDWATIER Procedure No. EXE-PDI-UT-1 10 Cal. checks Time Rev I Chng. No. 0 / NtA Cal. Block No. BWD-141 Initial Calib. 08:20108:25 Cal. Block Temp. 74=F Thermometer SIN: SAP 10513' Size 6.0" Sch. 1.06' Initial Calib. Date Intermediate 10/13/2007 N/A f+_,H Ferritic Austenitic Search Unit #1 Search Unit #2 -
Each Major CRT Div. = 0.3" I 0., Intermediate N/A Manufacture: KBA Manufacture: KBA 0 Serial No.: 0X12M . Serial No.: 0OYJYT CaL Direction: A al In Circ. E ]Both Final Calib. 15:55/15:50 No. of Elements: 1 No. of Elements& 1 0 Size: 0.25" Shape: Round Size: 0.5" Shape: Round :3 Freq. 2.25 MHz Style: Comp.G Freq, 2.25 MHz Style:
(JYr:TCD)
Scan Area:. _ to Weld Comp-G Final Calib. Date 10/13/2007 to Weld Exam Angle: 35 Mode: Shear Exam Angle: 45* Mode 'Shear CD "
CD Couplant Measured Angle: 35° Measured Angle: 45° --
C.ode Category: R-A Code Item: R01.20 Type: ULTRAGEL I! Wedge Style: MSWQC Wedge Style: MSWOC Co Batch: 05325 05 G)
Search Unit Cable Search Unit Cable Recor~able Exam Access Indications Type: RG 174 Type: RG 174 C')
Sons.
Examination Area I Weld yes I No I Geo= Length: 6' No. of Con.: 0 Length: 6' No. of Con.: 0 C/)
- rI 1 SG-05-SGSE-02 (35°)
- I X 45.5 dB Instrument Settings Instnaunent Settings P*
1SG-05-SGSE-02 (45-)
- _ X 24.5 dB Make / Model: Kraururamer USN 58L SW Make / Model: Krautkramer USN 58L SW SerialaNo.: 104765 Serial No.: 104765 NIA t Probe Delay: 8.1622 Range: 3.0" Probe Delay: 6.5253 Range: 4.0" M'dCal/Vel: 0.1321Pulser. Square MflCallVel: 0.1233Pulser Square Damping: 500., Reject 0% Damping- 500 Reject: 0%
Remarks I Reason for Incomplete Scan(s) COMPONENT TEMP: SOF PRF: Auto High Freq: 2.25.MHz PRF: Auto High Freq: 2.25 MHz Scanned with a 5-20% ID roll. Transducer 0OX12M was used for Circ scan only. Filter: FIXED Mode: Shear Filter: FIXED Mode: Shear Transducer 0OYJYT was used for Ax scan only. Shear scan on upstream side only. No Rectify: Full Wave Voltage: 450 Rectify: Full Wave Voltage: 450 counterbori.detactd. ,NRI.
- Seq goverage plot for areas scanned.
1
- J *: _-j Pulse Width: 220 Pulse Width: 220 i
Examiners: .kLJ4~l Level !1 Data 10/13/2007 Reference Sensitivity (Sens.) Reference Sensitivity (Sens.)
Dauglas(Gronewold Axial: N/A Circ: 39.5 dB Axial. 18.5 dB Circ: N/A N/A Level N/A Date N/A SDH SenstivtyW. N/A SDH Sensitivity: N/A Display Delay: 0 Display Delay: 0 r
Reviewers: .- jAL ) M -1J5 a7 Furher Evaluation Required? fYes 9No Th
-V?
EXELON LEVEL Wi~~
REVIE RATE~~ ~V~
A Westinghouse NDE Company Calibration Data Sheet .8'ý'Mr S>14 El ElElUI hI AJOTWC-1!
1A, Plant I Unit BRAIDWOODI 1 Data Sheet# A1R13-UT-013 Company EXELON Page 2 of 7 Comp I System AUX FEEDWATI Procedure No. EXE-PDI-UT-1 1 Cal. Checks Time II Rev I Chng. No. 0 1 NIA Cal. Block No. BWD-141 Initial Calib. 13:35/113:40 Cal. Block Temp. 73°F I.- J.
Thermometer S/N: SAP 105131 Initial Calib. Date 10113/2007 Size 6.0" Sch. 1.06" Intermediate N/A Ferritic En Austenitic Search Unit #1 Search Unit #2 Each Major CRT Div. 0.2' / 0., Manufacture: RTD Manufacture: RTD O Intermediate N/A Serial No.: 06"871 Serial No.: 06"895 3
.al. Direction: 9]iaI NI circ E Both Final Calib. 14:55115:00 No. of Elements: 2 No. of Elements: 2 "a Rect 0 Size: 2(10x18)mm Shape: Rect Size: 2(15x25)mm Shape:
Scan Area: j to Weld rX Final Calib. Date 10113/2007 Freq. 2.0 MHz Style: TRL 2 Freq. '2.0 MHz Style: T-- 2 CD II to Weld Exam Angle: 45 Mode: RL Exam Angle: 60b Moe TTIO r Couplant Measured Angle: 45* Measured Angle: _D 60.
Code Category: R-A Code Item: ROl120 Type: ULTRAGEL II Wedge Style: Integral Wedge Style: Integral .p, Batch: 05325 Search Unit Cable Search Unit Cable L" Recordable oOG Exam Access Indicatlions Type: RG 174 Type: RG 174 0)
Examination Area I Weld Sees.
Length: 6' No. of Con.: 0 Length: 6 No. of Con.: 0 0C m
I SG-05-SGSE-02 (45°) X 54.0 d8 Instrument Settings Instrument Settings C N\)
I SG-05-SGSE-02 (60) __.. X 50.0 dB Make I Model: Krautkramer USN 58L SW Make I Model: Krautkramer USN 58L SW Serial No.: 104765 Serial No.: 104765 NIA Probe Delay. 9.902 Range: 2.0" Probe Delay: 12.064 Range: 2Z0 Mtl Cal/ Vel: 0.245 Pulser. Square MIlCallVel: 0.1370Pulser. Square Damping: 500 Reject: 0% Damping: 500 Reject 0%
Remarks I Reason for Incomplete Scan(s) COMPONENT TEMP: 86"F PRF: Auto High Freq: 2.0 MHz PRF: Auto Hqh Freq: 2.0 MHz
- See coverage plot for areas examined. Scanned with a 5-20% ID roll. No Filter FIXED Mode: RL Filter FIXED Mode: RL counterbore detected. No examination looking upstream due to configuration of Rectify: Full Wave Voltage: 450 Rectify: Full Wave Voltage: 450 nnT*l NR L - -1 , Aa Pulse Width: 250- Pulse Width: 250 Examinerw II Date 101i M200 7 Reference Sensitivity (Sens.) Reference Sensitivity (Sens,)
Axial: 48.0 dB Circ: N/A Axial: 44.0 dB Cirt, NIA
- N/A Level N/A Date N/A SDH Sensitivity: N/A SDH Sensitivity: N/A Display Delay: 0 Display Delay. 0 Revewrc~ ~ L. j ,.~Further EvaluatIon Req wred? N/yes I9No f ATLeva a j6xfsw04 .f r 7e~
='s> ADe A Westinghouse NDE Company Calibration Data Sheet - N-o-M-.)
IF F F IVI Plant I Unit BRAIDWOOD / 1 Data Sheet# AIR13-UT-013 Company EXELON Page 3 of 7 Comp I System REACTOR COOLANT Procedure No. EXE-PDI-UT-1 110 Cal. Checks rune Rev/ Chng. No. 0/ NIA CaL Block No. BWD-141 Initial Calib. 13:45 Cal. Block Temp. 73°F Thermometer S/N: SAP 10513:3 Initial Calib. Date 10/1312007 Size 6.0" Sch. 1.06" Intermediate N/A Fernft Austenitic Search Unit #1 Each Major CRT Div. = 02" Manufacture: Megasonics Manufa Intermediate N/A Serial No.: U1057 Serial h Cal. Direction: Axial E Circ. E5 Both Final Calib. 15:05 No. of Elements: 2 No. of E Size: 2(15x25)mm Shape: Rect Size: (D Scan Area: _ to Weld Freq. 1.5 MHz Style: CSS Freq, Final Calib. Data 10/13t2007 to Weld Exam A1gle: 40_ Mode:: FRE Exam A 0 M Couplant Measured Angle: 40° Measur Code Category: R-A Code Iter: R01.20 Type: ULTRAGEL If Wedge Style: Integral Wedge Batch: 05325 9-0 Search Unit Cable 0D1C Recorilabte, Exam 0D Access Indications Type: RG 174 Type:
Seng.
Examination Area I Weld Yen INo IGeom Length: 6' No. of Con.: 0 Length:
I SG-05-SGSE-02 X 56.5 dB Irntument Seting$ Instrument S n Make I Model: Kroutkramer USN 58L SW Make I Model:
Serial No.: 104765 Serial No.:
Probe Delay: 8.1622 Range: 2.0" Probe Delay: Range:
M'U CalI Vel: 0.2271 Pulser Square MII Cal I Vel: Pulser Damping:- 500 Reject: 0% Damping: Reject Remarks i Reason for Incomplete Scan(s) COMPONENT TEMP: 86F PRF: Auto High Freq: 2.03MHz PRF: Freq:
- See coverage plot for areas scanned. Scanned with a 5-20% ID roll. No Filter FIXED Mode: RL Filter: Mode:
counterbore detected. Used to perform Circ scans only. NRI. Rectify: Ful Wave Voltage: 450 Rectify: Voltage-:
Pulse Width: 330 Pulse Width:
Exarnmerm: Level 111 Date 1 /1 3/2007 Reference Sensitivity (Sens.) Reference Sensitivity (Sens)
Doug qffhewold Axiat , N/A Circ: 51.5 dB Axial: Circ:
N/A Level N/A Date N/A SDH Sensitivity: N/A SDH Sensitivity:
Display Delay: 0 Display Delay:.
Reviewers:7. c.L ,,r,,-Fur#We Evatuation Requird? IRYes 0UNO LMVMM~i-1G-'ff I AT
A Westinghouse NDE Company Calibration Data Sheet Plant I Unit
- Company, Comp I System Procedure No.
Rev I Chng. No.
BRAIDWOOD 11, EXELON REACTOR COOLANT EXE-UT-350 1 / N/A Data Sheet #
Page 4 Cal. Checks A1R13-UT-013 of Time 7
In¶4. LLLr, Cal. Block No. 4654 I_
4TM Initial Calib. 13:07 . . . . - 46 . . , -AA I I . . . . . .
Cal. Block Temp. 77°F Thermometer S/N: SAP 105133 Initial Calib. Date 1017/2007 Size 6.0" Sch. 1.06" "T" Intermediate N/A Fenific Austenitic Search Unit #1 Search Unit #2 S 0 Each Major CRT Div. 0.2" Manufacture: KBA Manufactur _ _
Intermediate N/A Serial No.: 57462976.8 Serial No.:
No. of Elemen.
0 (D Cal. Direction: Axiat 0 Ciro S Both Final Calib. 15:26 No. of Elements: 2 -
Size: (3.5xl0)mm Shape: Rect Size: Shape Scan Area: _ to Weld Freq. 4.0 MHz Style: MSEB4E Freq. Style: CD Final Calib. Date 10/7/2007 toWeld ExM Angle: O0 MoaFe' LN Exam) Mo8-1, Couplant Measured Angle: 0" Measured Angle:> CD Code Category: R-A Code Item: R01.20 Type: ULTRAGEL II Wedge Style: Integral Wedge Style: ci)
Batch: 05325 Search Unit Cable Recordable Exam iAccess indications Type: RG 174 Type: C>
Ses.
Examination Area I Weld Length: 6 No. of Con.: 0 Length:
S ingle . - 'A -
1SG-05-SGSE-02 Sided Instrument Settings Make I Model: Krautkramer USN 58L SW Make I Model: A Serial No.: 104765 Serial No.:
Probe Delay: 9.2203 Range: 2.0" Probe Delay: Range:
Mtl Cal I Vel: 0.227 Pulser Square Mtl Cal / Vel: Pulser Damping: 500 Reject: 0% Damping: __ Reject Remaf*l I Reason for Incomplete Scan(s) COMPONENT TEMP: 84"F PRF: Auto High Freq: 4.0 MHz PRF: Freq:
0* cal for thickness and contour only. No counterbore detected. Filter FIXED Mode: Lon Filter Mode:
Rectify: Fun Wave Voltage: 450 Rectify: Voltage:
Pulse Width: 130 Pulse Width:
-~~ ... A 1
~~44' . . 4 ljl*tl Reference Sensitivity (Sens.) Reference Sensitivity (Sans.)
Examiners: WLevel u1 Date ilv u 1v"uU ac,*n, Axial: 28.5 dB Circ: 28.5 dB Axial: Citv:
% Leve II Date 10/07/2007 SDH Sensitivity: NIA SDH Sensitivity:
Rouglas:jj EewoEu Display Delay: 0 Display Delay:
Reviewers:-' .AA-A&ýww vlainRqieB " wN I *AIM SEW" I DAM =
- AIR13-UT-013 LIMITATION TO EXAMINATION Page 5 of 7 A Westinghouse NDE Company PLANT BRAIDWOOD UNIT 1 PROCEDURE EXE-PDI-UT-110 REV. 0 SKETCH See pages 5 and 6 of report WELD # 1SG-05-SGSE-02 WELD TYPE Safe End - Aux Feedwater EXAMINER _ _ _ _ _ _ _ _ _ _ _ __.DATE 10/1512007 DouglajGrftnewold, Level HI The above referenced Dissimilar Metal Weld was examined in both the Axial and Circumferential directions. The Axial scans were performed utilizing 450 Shear, 450 and 600 RL search units. Due to the ID/OD ratio of the component, the Circ scans were performed with 350 Shear and 40° RL search units. No exam was performed looking upstream due to the nozzle configuration. The 350 Shear wave exam was performed on the nozzle side as a supplemental exam and no credit for coverage was taken on the nozzle side with this search unit.
Below is the coverage calculation:
Axial Scans 93% 3 Circ Scans 65% "D 0 (D 158 /2=79% ja CD NOTE: See pages 6 of 7 of report for areas examined. -" 3"
-40 ( -f C/)
m 6
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... ... ... . . . : . . . . =. . .. . .. . . ...
FlINSPECTION SERVICES WELD PROFILE I DATA Page S of 7 A W*'tlnghouse ND Company PLANT BRAIDWOOD UNIT 1 SKETCH 1SG-05, Rev. 0 SYST,/COMP. RC LISG-05-SGSEM02 PROCEDURE EXE-UT-350, Rev, 1/ EXE-PDI-UT-110, Rev. 0 EXAMINER-~ DATE 10/7/2007 IDENT. ISG-05-SGSE-02 I I a £ I I I I . I I i
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FRI WES DyNE INSPECTION SERVICES Page 7 of 7 A Westtnghouw NDE Company WELD PROFILE I DATA PLANT BRAIDWOOD UNIT I SKETCH ISG-05, Rev. 0 SYST.iCOMP. RC I ISG-05-.SGSE-02 PROCEDURE EXE-UT-350, Rev. 1 I EXE-PDI-UT-1 10, Rev. 0 EXAMINERDT W20 IDENT. ISG-05-SGSE-02 I k0 1 "I 0 3
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ATTACHMENT 2 Braidwood Station Unit 2 Limited Examinations
ISI Program Plan Braidwood Station Units 1 & 2, Second Interval 10 CFR 50.55a RELIEF REQUEST 12R-50 Attachment 2-1 Braidwood Station Unit 1 Limited Examinations Revision 0 (Page 1 of 1)
Component ID Outage Cumulative Reference Remarks Code Category Examined Examination Sketch/Coverage Code Item Coverage Plot Achieved 2RV-03-001 A2R07 87.64% Attachment 2-2 Reactor Vessel Upper Head-to-Flange Category B-A (4/1999) weld. Examination coverage for surface Item B1.40 examination (magnetic particle) was 100%
with no recordable indications, no recordable indications noted in any of the ultrasonic scans.
2PZR-01-N2 A2R07 83.64% Attachment 2-3 Pressurizer Spray Nozzle-to-Shell Weld.
Category B-D (4/1999) No recordable indications noted in any of Item B3.110 the ultrasonic scans performed.
2PZR-01-N3 A2R07 80.9% Attachment 2-4 Pressurizer Relief Nozzle-to-Shell Weld.
Category B-D (4/1999) No recordable indications noted in any of Item B3.110 the ultrasonic scans performed.
2SG-01-SGC-02 A2R13 88.4% Attachment 2-5 Steam Generator Tube Sheet-to-Stub Category C-A (4/2008) Barrel weld; scanning limitations due to Item C1.30 adjacent plug/branch connections, weld pads and identification plate. No recordable indications noted in any of the ultrasonic scans performed.
ISI ProgramPlan Braidwood Station Units 1 & 2, Second Interval 10 CFR 50.55a RELIEF REQUEST 12R-50 Attachment 2-2 Braidwood Station Unit 1 Limited Examinations Revision 0 (Page 1 of 13) 1.0 Component Weld Number: 2RV-03-001 Code Category / Item: B-A / B1.40 Configuration: Reactor Vessel Head-to-Flange Weld
2.0 Applicable Code Edition and Addenda
ASME Section XI 1989 Edition with no Addenda (including Mandatory Appendices)
3.0 Applicable Code Requirement
Table IWB-2500-1, Examination Category B-A, requires volumetric examination of Item B1.40 (Head-to-Flange welds). Table IWB-2500-1 Note (2) states essentially 100% of the weld length shall be examined.
Figure IWB-2500-5 depicts the required examination volume (A-B-C-D), which includes the circumferential weld and the adjacent base metal on either side of the weld extending to a distance of one-half the thickness of the wall from the extremities of the weld crown.
ASME Section Xl Mandatory Appendix I requires ultrasonic examination of vessel welds greater than 2" thick to be conducted in accordance with ASME Section V, Article 4.
ASME Section V, Article 4 requires:
T-441.3.2.4 Extent of Scanning: Wherever feasible, the scanning of the examination volume shall be carried out from both sides of the weld on the same surface. Where the configuration or adjacent parts of the component are such that scanning from both sides is not feasible, this fact shall be included in the report of the examination.
T-441.3.2.5 Angle Beam Scanning: Wherever feasible, each examination shall be performed in two directions, i.e., approaching the weld from the opposite directions and parallel to the weld from opposite directions.
T-441.3.2.6 Scanning for Reflectors Oriented Parallel to the Weld: The angle beam search units shall be aimed at right angles to the weld axis, with the search unit manipulated so that the ultrasonic beams pass through the entire volume of weld metal.
The adjacent base metal in the examination volume must be completely scanned by two angle beams, but need not be scanned by both angle beams from both directions.
Code Case N-460, which accepts a reduction in examination coverage provided the reduction is less than 10%.
ISI ProgramPlan Braidwood Station Units 1 & 2, Second Interval 10 CFR 50.55a RELIEF REQUEST 12R-50 Attachment 2-2 Braidwood Station Unit 1 Limited Examinations Revision 0 (Page 2 of 13) 4.0 Impracticality/Burden The reactor vessel head-to-flange weld has a nominal thickness of 7.0" and is clad with stainless steel on the inside diameter surface. The surface geometry of the flange obstructs the ultrasonic transducer movement that is needed to examine the Code required volume from the flange side. The propagation for the ultrasonic beam was in the shear mode. Normally this mode would allow the ultrasonic beam to reflect off the inside surfaces and create a two-beam axis at right angles to each other; however, the presence of the stainless steel cladding precludes the ultrasound beams from reflecting at the inside diameter from the shell/cladding interface. In addition to the examination limitations encountered due to the flange configuration and inside diameter cladding, additional examination restrictions are caused by the presence of three lifting lugs located on the reactor vessel head. These limitations preclude complete coverage of the full volume for the required scanning directions mandated by ASME Section V and Section XI. These limitations are inherent to the original design of the reactor vessel head. Conformance with the ASME Section Xl requirements for essentially 100% of the volumetric coverage would require extensive structural modifications to the reactor vessel head.
5.0 Alternative Examinations or Testing In addition to performing the 0, 45, and 60 degree ultrasonic scans required by Appendix I, additional 30 and 40 degree ultrasonic scans were performed in lieu of the 70 degree scan as permitted by Section V, Article 4, T-441.3.2.1 to supplement coverage. The calculated volumetric coverage achieved for all combined scans was documented as 87.64%.
The Code required surface examination area (B-E as depicted in Figure IWB-2500-5) was fully achieved (100% coverage) utilizing the magnetic particle method. In addition to the required surface examination, numerous system leakage tests (ASME Section Xl Category B-P and Generic Letter 88-05) at nominal system operating pressure (2235 psig) and temperature (5570 F) as well as bare metal visual examinations of the upper reactor head associated with the First Revised Order EA-03-009 have been completed with no evidence of leakage associated with the reactor vessel head-to-flange weld noted during the course of the interval.
Radiography (RT) is not a desired option because RT is limited in the ability to detect expected degradation mechanisms such as service induced cracking. Additionally, RT has not been qualified through performance demonstration.
ISI ProgramPlan Braidwood Station Units 1 & 2, Second Interval 10 CFR 50.55a RELIEF REQUEST 12R-50 Attachment 2-2 Braidwood Station Unit 1 Limited Examinations Revision 0 (Page 3 of 13) 6.0 Justification for Granting Relief No additional examinations were completed during the inspection interval; however, the aggregate examination coverage achieved 87.64% along with the results of the completed surface examination, system pressure tests, and bare metal visual inspections performed throughout the inspection interval provide reasonable assurance that pressure boundary integrity has been maintained for this component. There were no indications noted during any of the examinations (surface, volumetric, and visual) performed during the course of the interval.
7.0 Precedents Similar examination limitations for reactor head-to-flange welds were encountered and similar examination coverage was accepted for the following units:
Byron Station Units 1 and 2:
Letter from R. Gibbs (U. S. NRC) to C. G. Pardee (Exelon Generation Company, LLC),
"Byron Station, Unit Nos. 1 and 2 - Inservice Inspection Program Second Interval Relief Requests 12R-22, 12R-23, 12R-25, and 12R-53 (TAC Nos. MD4099, MD4100, MD4101, MD41102, MD41103, MD4104, MD4105, and MD4106)," dated January 15, 2008
nwlili rl5:uv.,tl e-lin-ovu Attachment 2 - 2 Component: 2RV-03-O01 I IT-FXAM-.O1 R~v Rev 00 I Sheet 4 of 13 February.m I 1999 UT-EXAM-01
... ...... f ......
Februa 1999 ULTRASONIC EXAMINATION DATA Station: BRAIDWOOD Unit: 2 Procedure/ Rev.: NDT-C-30 / 7 Date: 4-30-99 Page 1 of I Calibration Report No.: Axial 99BR2-UTC-053 Circ.: N/A Exam. Report No.: 99BR2-UTD-048 System: REACTOR VESSEL Component #: 2RV-03-001 Weld Type: REACTOR AD- FLANGE Component Size: 48' Schedule / Thickness: N/A / 7.0" Material: CS / SS CLAD Component Temp. / I.D. # 710F / 193748 Couplant ULTRAGEL II Batch #: 99125 Scan Gain: 45.2 dB Axial: N/A Ciiu.: N/A Lo Reference Point: 0.0* Wo Reference Point: WELD CENTERLINE Perfomed Indications YES NO NO YES
.A
- 1. Anle Beam - Normal - Against Flow N/A X N/A N/A
- 2. Angle Beam - Normal - VCh Flow N/A X N/A N/A
- 3. Angle Beam - Along Weld - CW N/A X N/A N/A
- 5. Thickness Across Weld and Base Metal X N/A 7.00 7.00 7.00 ..
... UP STRM WELD DN STRM Comments:
- 00 EXAMINATION.
- NO RECORDABLE INDICATIONS.
- REFERENCE 99BR2-UTD-051 FOR THICKNESS AND COVERAGE INFORMATION.
- WELD AND BASE METAL STRAIGHT BEAM WAS PERFORMED.
- GAIN ADJUSTED TO MAINTAIN 80% BACK WALL.
- 45° INFORMATION REFERENCE 99BR2-UTD-051.
- 60, INFORMATION REFERENCE 99BR2-UTD-052.
Examiner: Level: 11 Date: 4-30-99 Reviewer: Level: -2V- Date:
Reviewer: Level: _ Date:
Others: Date: C 1 ANII: Date;
Attachment 2 - 2 Component: 2RV-03-001 Rev. 0 Sheet 5 of 13 February, 1999 ULTRASONIC EXAMINATION DATA Sttion: BRAIDWOOD Unit 2 Pto#cedual Rev.: NOT-C-30 Date: 4-30-99 Page 1 d 1 Calibration Report No.: Mal: 99BR2-UTC-054 Circ.: NIA Exam. Report No.: 99-9R2-UTD-049 Systew: REACTOR HEAD Conpon *t#: 2RV-03-001 Weld Type: REACTOR HEADTOFLANGE Component Si&: 48' Schedule / Thicknr N/Al 7.0" Material; CS Component TeMp./ ID. # 71 /193748 - Couplant: ULTRAGEL I! Batch # 99125 Scan Gain: 85dB Axial: X Circ.: NA Lo Rference Point: 0o Wo Refrence Pint: WELD CL Perforfned Indications YES NO NO YES
- 1. Angle Be= - Noma - Aaanert Flou X N/A X NIA 2 Angle Beam- Normal - WtRhFow X N/A X N/A
- 3. AngleBeam-Alon Weld-CW N/A X N/A N/A
- 4. Mqle Beam - Al Weild - CCW N/A X N/A N/A
- 5. Thickness Acam Weld and Base Matal _ X N/A *
- __ STRM UP WELD DN STRM Comments:
.NO RECORDABLE INDICATIONS - NRI
- REF 99BR2-UTD-051 FOR THICKNESS AND COVERAGE DATA.
MAINTAIN A 10% I0 ROLL LIMITED EXAM PERFORMED AGAINST FLOW DO TO FLANGE O0 INFORMATION REFERENCE 99BR2-UTD-048 450 INFORMATION REFERENCE 99BR2-UTD-051 600 INFORMATION REFERENCE 99BR2-UTD-052 400 INFORMATION REFERENCE 99BR2-UTD-050 300 / 2.25MHZ
-*7 JOSPH SERTH L.eve: I! Dale: 4-30-9 Reiewar- Lev: Date: _ _ _ _" _ _ _
Revvs~er Laet: Date: ___"
Date:
Q. 1 ANIL: Date - '.-.C
- -, .* 4 ,L IC.. IiJV Attachment 2 - 2 Component: 2RV-03-001
- JT.FXAM-O1 Sheet 6 of 13 RevO February, 1999 Sheeth~6evof10erur.9 ULTRASONIC EXAMINATION DATA Staijon: BRAIDWOOD Unit 2 Procedure/ Rev.: NDT-C-30 Date: 4-30-99 Page 1 of 1 Calbratien Report No.: AdAW: 998R2-UTC-055 Circ.: N/A Exam. Report No.: 99-R2-IJTD-05O Syptem: REACTOR HEAD C~monent ~Ift.2RVt)3-03401 Weld Type: REACTOR HEOD TOFLAN~GE Crnponent Size: 48' Schedule I Thicknes: N/A I 7O' Matsdal: CS Coipeat Ternp.lIl.0. # 71-1193748 Cauplart ULTRAGEL II Balcht. 99125 Scan Gain: 65dB Axia: X Circ.: NA Lo Rdererenc Poft 00 Wo Refawrce Point WELD CL Petfomned Indications YES NO NO YES
- 1. Angle Bern -Norrn -AoaflttFlow 1' X WA X W/A 2 ArBonn,- Nxomi- With .F.w X NIA x NWA
- 3. Angle Beam - ngWeld - CW N/A X N/A I N/A
____UP STRM WELD DN STRM Comrnsls:
.NO RECORDABLE INDICATIONS - NRI
- REF 99BR2-UTD-051 FOR THICKNESS AND COVERAGE DATA.
MAINTAIN A 10% ID ROLL LIMITED EXAM PERFORMED AGAINST FLOW DO TO FLANGE 0
"INFORMATION REFERENCE 99BR2-UTD-048 45° INFORMATION REFERENCE 99BR2-UTD-051 60r INFORMATION REFERENCE 99BR2-UTD-052 300 INFORMATION REFERENCE 99BR2-UTD-049 40( / 2.25MHZ Lasal: II Date: 4-30-99 Reviews- Lev:e: 0/. ' _ 5__ _
Renewer Others: Date:
AND:
Attachment 2 - 2 Component: 2RV-03-001 Sheet 7 of 13 UT-EXAM-01. Rev. 0 February. 1999 ULTRASONIC EXAMINATION DATA Staion: BRAJDWOOD Unit 2 Procedure/ Rev.: NDT-C-30 /7 Date: 4-3o-99 Page /_ t /2o-Calibration Report No.: AMal: 9gBR2-UTC-056 Circ.: 99BR2-UTC.-E056 Report No.: 99BR24JTD-051 System: REACTOR VESSEL Component #: 2RV-030Mi Weld Type: REACTOR HEAD - FLANGE Component Size: 48' Schedule f Thickness: N/A I 7,0" Material: CS/SS CLAD Ccnpwonnt Temp. / I.D. # 71*F I 193748 Couplant: ULTRAGEL II Batch M 99125 Scan Gain: N/A Axial: 59.4 dB circ.:59.4 dB Circ.: 59.4 dB L) Refermnce Point 0. Wo Reference Point WELD CENTERUNE 45° SHEAR Prformed indiaions YES NO NO YES
- 1. 622e aw -Normal -Against Flow X NA X NIA 2 Ale BSon - Normal - With Fk X N/A X N/A
- 3. Angle Bom-oM Weld- CW X NIA X N/A
- 4. Angl Beam - MA Wekl - CCW X N/A X N/A
- 1. THERE WERE NO RECORDABLE INDICATIONS.
- 2. EXAM WAS LIMITED AGAINST FLOW DUE TO FLANGE.
- 3. REFER TO ATTACHED SHEETS FOR THICKNESS AND COVERAGE INFORMATION.
- 4. THE ABOVE SCAN GAIN WAS USED TO MAINTAIN A 10% ID ROLL
- 5. FOR 00 INFORMATION REFER TO 99BR2-UTD-048.
- 6. FOR 60" INFORMATION REFER TO 99BR2-UTD-052.
,-F Examiner RONALD P. NIZIOL Level: II Date: 4-30-99 Level: ZZZE Date: " 7/- 2 Lem: ,;-0, DOWe _5-1____
Others: Date: 6~fj~
ANILl Data: S - %-"Rg ANII Date:
tieiieT hequest i1H-bU Attachment 2 - 2 Component: 2RV-03-001 NDE-COV-01, Rev. 0 Sheet 8 of 13 --- ,. February, 1999 EXAMINATION COVERAGE Station: BRAIDWOOD Unit: 2 Date: 5-3-99 Page 2 of 12 System: REACTOR VESSEL Comp. ID: 2RV-03-001 Exam. No.: 99BR2-UTD-051 Config: REACTOR HEAD to FLANGE Procedure/ Rev.: NDT-C-30 / &NDT-Z-1 /1 Examiner: RICH SCERINE Level: II Examiner: RON NIZIOL Level: II Notes: LIMITATION DUE TO 3 TENSIONING LUGS AND FLANGE NDE Method: UT X MT N/A PT N/A Comments: SEE ATTACHMENT I COVERAGE
SUMMARY
FOR EXAMINATION PERCENTAGE BREAK DOWN.
ASME Section XI Examination Volume Achieved: 87.64%
Attachments: Yes / No YES REVIEWER: fcA7/t4a: LEVEL: %2r DATE:
OTHERS: ' "*-"' 3 (q/ 1 LEVEL: 1T DATE: -i-'-
ANII: .- DATE: -'j~
K Relief Request 12R-50 Attachment 2 - 2 Component: 2RV-03-001 Sheet 9 of 13 I
Report # 99BR2-UTD.051 11 ii Page: 3OF 12 II I
Site: Braidwood Unit: 2 System: Reactor Vessel Examiner: Richard Scerine LEVEL: II Weld ID: 2RV-03-001 Config: REACTOR HEAD I FLANGE Examiner: Ron Niziol LEVEL: II FLOW Procedure # NDT-Z-1 / 1 Calibration Sheet # 99BR2-UTC-53,54,55,56,57 NDE METHOD X UT PT MT Notes: Supplemental Exams 300 & 400 VESSEL COVERAGE
SUMMARY
9.i (2.40" WELD CROWN AND 3.50- (T) SIDE 3.50 ( B) SIDE IT=7.00" WELD LENGTH= 525.15" Total Weld Metal Volume = 5881.68 cu. in. rotal Base Metal Volume = 29019.80 cuin.
Obstruction: 01 TENSION LUGS (3 EA.) 3" X W'WIDE FOR A TOTAL OBSTRUCTION OF 0.110A (18.0")
- 2 FLANGE (SEE BELOW FOR PERCENTAGES)
WELD METAL EXAMINATION BASE METAL EXAMINATION SCAN EXAM VOLUME /TOTAL VOLUME = % EXAM SCAN EXAM VOLUME /TOTAL VOLUME % EXAM 00 S 5881.68 cuin /15881.88 cu.ln. 100.00% 0° 23159.12 culn. 129019.80 cu.ln. 79.80%
30° B) 4180.19 cu.ln / 5881.68 cu.In. 71.07% 45° 28263.58 cu.In. /29019.80 cu.In. 97.40%
30° (T) 5881.68 cu.In / 5881.68 cu.In. 100.00% 600 28557.66 cu.In. / 29019.80 cu.In. 98.41%
400 (T) 2457.70 cu.ln 15881.68 cu.ln. 41.79% 450 CW 23159.12 cu.In. /29019.80 cu.,In. 79,80%
40 (B) 5875.24 cu.In /5881.68 cuIn. 9989% 45°CCW 23159.12 cu.In. / 29019.80 cu.In. 79.80%
450 CW 5881.68 cu.In / 5881.68 cu.In. 100.00% 600 CW 23159.12 cu.In. /29019.80 cu.In. 79.80%
450 CCW 5881.68 cu.in /5881.68 cu.ln. 100.00% 600 CCW 23159.12 cu.ln. /29019.80 cu.In. 79 80%
600 CW 5881.68 cu.In 15881.68 cu.In. 100.00% TOTAL 594.81% + 7 = 84.97% BMV EXAMINED 60 CCW 5881.68 cu.In / 5881.68 cu.In. Ln I00.00% 1 TOTAL 812.75% + 9 = 90.31%
TOTAL (90.31%+84,7% )+2=87.64 EXA It"TI6N COVERAGE PREPARED BY: 7 DATE: 5/%
REVIEWED BY: Af4L /A ~ tZ ~DATE: i 71 REVIEWED BY: 3X>V"LtA
- DATE: ____"__
JNIl: DATE: _ ___
I 2RV-03-001 I 99BR2-UTD-051 PAGE: 4 OF 12 WELD MATERIAL PERCENT CALCULATED COMMENTS 00 100.00%
300 B 71.07% 30" USED TO SUPPLEMENT 45¶, % COVERAGE BASED ON 30° 300 T 100.00% 301 USED TO SUPPLEMENT 45,. % COVERAGE BASED ON 30*
400 B 41.790/6 40 USED TO SUPPLEMENT 80°, % COVERAGE BASED ON 40*
40° T 99.89% 40° USED TO SUPPLEMENT 60°, % COVERAGE BASED ON 40° 450 CW 100.00%
450 CCW 100.00%
600 CW 100.00% AVERAGE 500 CCW 100.00% 90.31%
BASE MATERIAL PERCENT CALCULATED 0
79.80%
450 97.40% 0 CD 600 98.41% (D 7 45°CW 79.80% (rC 0 1 45°CCW 79.80%
60°CW 79.80% AVERAGE 600 CCW 79.80% 84.97%
TOTAL WELD METAL 90.31% "B"FLANGE SIDE OF WELD 84.97%/6 w"1HEAD SIDE OR WELD TOTAL BASE MATERIAL TOTAL EXAMINATION COVERAGE 87.64%
REFERENCE EXAMINATION VOLUME COVERAGE PLOT, PAGE 7 OF 12, FOR ALL ANGLES PERFORMED. THE ABOVE ANGLES WERE UTILIZED FOR TOTAL EXAMINATION COVERAGE CALCULATIONS.
PREPARED BY: DATE:
REVIEWED BY: DATE: f~./ 'z REVIEWED BY: DATE: S 1~1 ANII: L L~ DATE: __ -_\ _ __ _ _
Relief Request 12R-50 Attachment 2 - 2 NDE-ATTACH-O1, Rev o Component: 2RV-03-001 February, 1999 Sheet 11 of 13 STATION: BRAIDWIOOD UNIT: 2 PAGE 5 OF . .
PROCEDURE/ REV.: NDT-C-30 Rev. 7 & NDT-Z-1 Rev. I REPORT NO.: 99BR2-UTD-051 2RV-03-001 SYSTEM: REACTO R VESSEL COMPONENT: 2RV-03-001 UT SCANNING LIMITATIONS UT SCANNIN LIMITATIONS
- 1 0o FROM "L"TENSIONING LUG 6" WIDE
- 2 162" FROM *V TENSIONING LUG 6 "WIDE
- 3 324" FROM L TENSIONING LUG 6 WIDE
- .4 3M0 FANGE RAMINER. J -LEVEL~
-'-j-~ DATE:
REVIEWER: DATE:
LEVEL' REVIEWER: LEVEL.
DATE. -1994 OTHER: DATE.
ANII: DATE:
Relief Request 12R-50 Attachment 2 - 2 NDE-ATTACH-01, Rev 0 Component: 2RV-03-001 Febus19 999 Sheet 12 of 13 STATION: BRAIDWOOD UNIT: 2 PAGE 6 OF 12 PROCEDURE/ REV.: NDT-C-30 Rev. 7 & NDT-Z-1 Rev. 1 REPORT NO.,-. 99.'R2 .-UTD-051 NOTE: ...........
SYSTEM: REACTOR VESSEL COMPONENT: 2RV-03-001 Pages 7 of 12 through 12 of 12 are 1:1 scale drawings and are not included 95.12? ( OUTSIDE RADIUS ) - 87.85 (INSIDE RADIUS) = 7.27 72r + 2 = 363 or &3. 3.64"+ 878 = 91.4r C = (2r) (SIN -)
C - (2) (91.49) (SIN Or)
C a (2)(91.4f) (0.0136)
C a 187.l16W CIRCUMFERENCE d C ( 167.1r) =525.15 EXAMINER: DATE: _ __ _
REVIEWER: DATE: _ _ _ _
REVIEWER: DATE: SI-'
OTHER: OAT!:E. j ANtI:
r-ieie tiequest IGH-bU Attachment 2 - 2 Component: 2RV-03-001 UT-EXAM-01, Rev. 0 Sheet 13 of 13 February. 1999 ULTRASONIC EXAMINATION DATA Station: BRAIDWOOD Unit: 2 Procedure/Rev.: NDT-C-30 / 7 Date. 4-30-99 Page 1 of I Calibration Report No.: Axialý 99BR2-UTC-057 Circ,: 99BR2-UTC-057 Exam Report No.: 99BR2-UTD-052 System: REACTOR VESSEL Component # 2RV-03-001 Weld Type: REACTOR HEAD - FLANGE Component Size: 48' Schedule / Thickness: N/A 1 7.0' Material: CS / SS CLAD Component TemP 1.0, # 71OF 1 193748 Couplant: ULTRAGEL II Batch
- 99125 Scan Gain: N/A Adal: 63.0 dB Circ.: 63-0 dB Lo Reference Point: 0.0- Wo Reference Point WELD CI-NTERLINE Performed Indications YES NO NO YES 1, Angle Beam - Normal - Against Flow X N/A X NIA 2 Ane Beam - Normal -WIth Flow X N/A X N/A
- 3. Angle Beam -.AJong Wald- CW X N/A X N/A
- 60° EXAMINATION.
- NO RECORDABLE INDICATIONS.
-* REFERENCE 99BR2-UTD-051 FOR THICKNESS AND COVERAGE INFORMATION.
- LIMITED SCAN AGAINST DUE TO FLANGE.
- THE ABOVE SCAN GAIN WAS USED TO MAINTAIN A 10% ID ROLL.
- 00 INFORMATION REFERENCE 99BR2-UTD-048.
- 450 INFORMATION REFERENCE 99BR2-UTD-051.
Examiner Level: II Date: 4-30-99 Reviewer: ~a4W ~ Level: ZZ217 Date: le fp
~A714244 Reviewer Level: 11F__ Date:________
Others: c.
C). k.L~. Cx', L Date: 151 -,)fcjc ANII: Date:
ISI ProgramPlan Braidwood Station Units 1 & 2, Second Interval 10 CFR 50.55a RELIEF REQUEST 12R-50 Attachment 2-3 Braidwood Station Unit 1 Limited Examinations Revision 0 (Page 1 of 24) 1.0 Component Weld Number: 2PZR-01-N2 Code Category/ Item: B-D / B3.1 10 Configuration: Pressurizer Spray Nozzle-to-Vessel Weld
2.0 Applicable Code Edition and Addenda
ASME Section Xl 1989 Edition with no Addenda (including Mandatory Appendices)
3.0 Applicable Code Requirement
Table IWB-2500-1, Examination Category B-D requires volumetric examination of Item B3.1 10 (Pressurizer Nozzle-to-Vessel welds).
Figure IWB-2500-7(b) depicts the required examination volume (A-B-C-D-E-F-G-H),
which includes the actual circumferential weld and adjacent base metal on either side of the weld extending to a distance of one-half the thickness of the wall from the extremities of the weld crown.
ASME Section Xl Mandatory Appendix I requires ultrasonic examination of vessel welds greater than 2" thick to be conducted in accordance with ASME Section V, Article 4.
ASME Section V, Article 4 requires:
T-441.3.2.4 Extent of Scanning: Wherever feasible, the scanning of the examination volume shall be carried out from both sides of the weld on the same surface. Where the configuration or adjacent parts of the component are such that scanning from both sides is not feasible, this fact shall be included in the report of the examination.
T-441.3.2.5 Angle Beam Scanning: Wherever feasible, each examination shall be performed in two directions, i.e., approaching the weld from the opposite directions and parallel to the weld from opposite directions.
T-441.3.2.6 Scanning for Reflectors Oriented Parallel to the Weld: The angle beam search units shall be aimed at right angles to the weld axis, with the search unit manipulated so that the ultrasonic beams pass through the entire volume of weld metal.
The adjacent base metal in the examination volume must be completely scanned by two angle beams, but need not be scanned by both angle beams from both directions.
T-441.3.2.7 Scanning for Reflectors Oriented Transverse to the Weld: The angle beam search units shall be aimed parallel to the axis of the longitudinal and circumferential welds. The search unit shall be manipulated so that the ultrasonic beams pass through of the examination volume. Scanning shall be done in two directions 180 degrees to
ISI ProgramPlan Braidwood Station Units 1 & 2, Second Interval 10 CFR 50.55a RELIEF REQUEST 12R-50 Attachment 2-3 Braidwood Station Unit 1 Limited Examinations Revision 0 (Page 2 of 24) each other to the extent possible. Areas blocked by geometric conditions shall be examined from at least one direction.
Code Case N-460, which accepts a reduction in examination coverage provided the reduction is less than 10%.
4.0 Impracticality/Burden The pressurizer vessel spray nozzle-to-vessel weld is approximately 2.7" thick. The pressurizer nozzle and vessel are clad with stainless steel on the inside diameter surface. The geometry of the nozzle along with the presence of the cladding on the inside diameter of the pressurizer result in limited access to the entire examination volume. The propagation for the ultrasonic beam was in the shear mode. Normally this mode would allow the ultrasonic beam to reflect off the inside surfaces and create a two-beam axis at right angles to each other; however, the presence of the stainless steel cladding precludes the ultrasound beams from reflecting at the inside diameter from the shell/cladding interface. The nozzle geometry tapers away from the weld resulting in limited scanning surfaces available for transducer coupling on the nozzle side of the weld resulting in additional examination limitations. These factors result in limited examination coverage from the scan directions required by ASME Section V and Section XI. These limitations are inherent to the original design of the pressurizer vessel. Conformance with the ASME Section XI requirements for essentially 100% of the volumetric coverage would require extensive structural modifications to the pressurizer vessel.
5.0 Alternative Examinations or Testing In addition to performing the 0, 45 (recorded as 46 degrees in coverage calculation data), 60, and 70 degree scans to the extent practical as required by Appendix I, additional 30 and 40 degree scans were performed to supplement coverage. The aggregate examination coverage achieved was 83.64%.
In addition to completing the required volumetric examination to the extent practical, numerous system leakage tests (ASME Section XI Category B-P and Generic Letter 88-05) at nominal system operating pressure (2235 psig) and temperature (5570 F) as well as the bare metal visual examinations associated with NRC Bulletin 2004-01 of the upper pressurizer vessel head were completed with no evidence of leakage associated with the pressurizer spray nozzle-to-vessel weld noted during the course of the interval.
Radiography as an alternative is not feasible because access is not available for film placement.
ISI ProgramPlan Braidwood Station Units 1 & 2, Second Interval 10 CFR 50.55a RELIEF REQUEST 12R-50 Attachment 2-3 Braidwood Station Unit 1 Limited Examinations Revision 0 (Page 3 of 24) 6.0 Justification for Granting Relief No additional examinations were completed during the inspection interval; however, the examination coverage of 83.64% along with the results of the pressure test and bare metal visual inspections provide reasonable assurance that pressure boundary integrity has been maintained for this component throughout the interval.
7.0 Precedents Similar examination limitations for pressurizer spray nozzle -to-shell welds were encountered and similar examination coverage was accepted for the following units:
Byron Station Units 1 and 2:
Letter from R. Gibbs (U. S. NRC) to C. G. Pardee (Exelon Generation Company, LLC),
"Byron Station, Unit Nos. 1 and 2 - Inservice Inspection Program Second Interval Relief Requests 12R-22, 12R-23, 12R-25, and 12R-53 (TAC Nos. MD4099, MD4100, MD4101, MD4102, MD4103, MD4104, MD4105, and MD4106)," dated January 15, 2008 Callaway Unit 1:
Letter from D. Terao (U. S. NRC) to C. D. Naslund (Union Electric Company), "Callaway Plant, Unit 1 - Relief Request ISI-41 for the Second 10-Year Inservice Inspection Interval (TAC No. MD3437)," dated January 18, 2007 Wolf Creek Unit 1:
Letter from D. Terao (U. S. NRC) to R. A. Muench (Wolf Creek Nuclear Operating Corporation), "Wolf Creek Generating Station - Relief Request 12R-34 for the Second Ten-Year Interval Inservice Inspection (TAC No. MD0288)," dated November 20, 2006 Catawba Unit 1:
Letter from E. C. Marinos (U. S. NRC) to D. Jamil (Catawba Nuclear Station), "Catawba Nuclear Station, Unit 1, Request for Relief 05-CN-004, Limited Weld Examinations During End-of-Cycle 15 Refueling Outage (TAC Nos. MC8337, MC9171, MC9172.
MC9199, MC9173, MC9202, MC9174, MC9175, MC9176, MC9177, MC9178 and MC9179)," dated September 25, 2006
ISI ProgramPlan Braidwood Station Units 1 & 2, Second Interval 10 CFR 50.55a RELIEF REQUEST 12R-50 Attachment 2-3 Braidwood Station Unit 1 Limited Examinations Revision 0 (Page 4 of 24)
Catawba Unit 2:
Letter from E. C. Marinos (U. S. NRC) to D. Jamil (Catawba Nuclear Station), "Catawba Nuclear Station, Unit 2, Request for Relief from the Requirements of the ASME Code (TAC Nos. MC7004, MC9197, MC9198. MC9199, MC9200, MC9202, MC9203, MC9204, MC9205, MC9206 and MC9207)," dated April 3, 2006
Relief Request 12R-50 Attachment 2 - 3 Component: 2PZR-01-N2 NDE-COV-01, Rev. 0 I Sheet 5 of 24 February, 1999 EXAMINATION COVERAGE Station: BRAIDWOOD Unit: 02 Date: 04/27/99 Page I of z0 System: PRESSURIZER Comp. ID: 2PZR-01-N2 Exam. No.: 99BR2-UTD-025 Config: SPRAY NOZZLE to PRESSURIZER Procedure/ Rev.: NDT-C-5, REV. 4 NDT-Z-1, REV. 1 Examiner: MIKE KICKBUSCH Level: II Examiner: TIMOTHY GAHAN Level: II Notes: LIMITATION DUE TO NOZZLE CONFIGURATION NDE Method: UT X MT N/A PT N/A Comments:
Total weld metal examination volume (WMV) achieved : 90.41%
Total base metal examination volume (BMV) achieved : 76.86%
r.otal examination volume achieved : 83.64% ( 90.41 + 76.86 = 167.27 /2 = 83.64)
Reference attached examination coverage calculation sheet for details.
ASME Section Xl Examination Volume Achieved: 83.64%
Attachments: Yes / No YES REVIEWER: x. -0v LEVEL: DATE: &---gq drHERS: W -
N C?LEVEL: JZZ" DATE: 6-"-/" -F ANIL: ANII: DATE:
DATE: -V~-~A
2PZR-0I-N2 2PZR.0-N2 9SR24ITfl-h7R PERCENT PERCENT WELD MATERIAL (WMV) ACHIEVED UTILIZED COMMENTS 0o 100.00%/0 100.00%
30" X 72.79% 72.79% 30* (X) USED TO SUPPLEMENT 460, % COVERAGE BASED ON 30' 30' Y 100.00% 100.00% 30* (Y) USED TO SUPPLEMENT 46', % COVERAGE BASED ON 30° 40° X 40.88%/0 40.88% 40' (X) USED TO SUPPLEMENT 60°, % COVERAGE BASED ON 400 40° Y 100.00%
460 X 28.96%
460 Y 100.00% 100.00%
60" X 12.80%
60' Y 99.78%
70* Y 99.49%
465 CW 100.00% 100.00%
460 CCW 100.00% 100.00%
60° CW 100.00% 100.00%
600 CCW 100.00% 100.00%
813.67% TOTAL 813.6719= 60.A1% WMV ACHIEVED 3 D PERCENT PERCENT BASE MATERIAL (BMV) ACHIEVED UTILIZED COMMENTS 'C v. C 0.
80.00% 79.96%
3f)° X 0 48 09 A SCD 0 -0 :3 (n 30o y 77.43%
40° X 43.58%
N 40° Y 84.13% r' 46° X 36.40%
460 Y 86.26%
600 X 19.81%
60' Y 88.70% 88.70%
70, Y 90.87% 90.870/ 70' (Y) USED TO SUPPLEMENT 46*, % COVERAGE BASED ON 70*
46° CW 69.62% 69.62%
460 CCW 69.62% 69.62%
60° CW 89.62% 69.62%
60° CCW 69.62% 69.62%
638.01% TOTAL 638.01 17= (76.8887t) 76.86% BMV ACHIEVED tOTAL WELD METAL 90.41%
FOTAL BASE MATERIAL 76.86% TOTAL EXAMINATION COVERAGE 83.64%
EXAMINER: -A ,xr PREPARED BY:
REVIEWED BY: ,~ g%~ANII:L L..-
Attachment 2 - 3 Component: 2PZR-01-N2 UT-EXAM-02. Rev. 0 Sheet 7 of 24 February. 1999 ULTRASONIC EMINATION DATA Stabton: BRAIDWOOD Unit 2 ProcedurefRev.: NDT-C-5/REV4 Date: 4-27.99 Page 5 of ZO Caribration Report No.: WHAZ 998R2-UTC-028 BM 99BR2-UTC-028 Exam. Report No.: 99BR2-UTD-025 System: PRESSURIZER Component#. 2PZR-01-N2 Weld Type: IPRESSURIZE SPRAY WOZ21Z Component Size: WA Schedule I Thinmess: N/A / 2.0625" Material CARBON STEEL Component Temp. I I.D. # 0 F/ 159175 Couplant: ULTRAGEL II Batch* 99125 Scn Gain: N/A WHAZ 25.6 dB eM*
- BM Lo Reference Point: STAMPED ZERO Wo Reference Point: WELD CENTERLINE Performed Indications YES NO NO YES
- 1. L-Wawe - BaseMVtal & Weld X N/A X N/A 2 Angle Bean - Pependcula to Weld Clockwse Side N/A X NWA WA
- 4. Angle Beam - Parallel to Weld Cocwise N/A X N/A WA
- 5. Angle Beam - Parallel to Weld Counterclockwise N/A X N/A N/A
- 6. L-W Asw Thickmess X N/A 2.71' 2.67 , 2.77 wXSide WELD "Y Side Garenft: 0* SCAN *GAIN ADJUSTED TO MAINTAIN 80% BACKWALL NO RECORDABLE INDICATIONS TOTAL EXAM COVERAGE 83.64%
REFERENCE COVERAGE SHEET FOR THE PERCENT OF COVERAGE FOR THIS ANGLE, Examnmer- 4~v-'Mv 00-0 L L2 Level 11/11 Dete: __/13/ _ __9 Reviewer. i2~ ;e,/2;; Law: 7 Datea 1 LeD: DOate: 5"-//-
Otrs:
ANII: V ANII: Ki~J Date: vi-q --
w PRESSURIZER NOZZLE COVERAGE PLOT PAGE. '-ii REPORT t C2ŽV1L-o-t-3 "" T " wm4cS
.... w U>
2"0:,* molz-1-1 YLP6.i 1D. l94 g p c.-1 Wk V 3-4 ~.S 51 C>rq~
I, PRE-%UPIZER NOZZLE COVERAGE PLOT REPOR' 9RMC!J e? VO LU-c 03 or C)
(D0 aeswplAzIrp.(
cnE oozL..- () ~.~Cl i..
N-2 NOZZLE.
It i=mw -r771 <-
Attachment 2 - 3 Component: 2PZR-01-N2 UT-EXAM-O,2, Rev. 0 Sheet 10 of..24 February, 1999 ULTRASONIC EXAMINATION DIATA Sto: BRAIDWOOD Unit 2 Procedurai Rev.: NDT-C-5 I REV 4 Date: 4-27-99 Page _U of 2,,)
Calbration Reporl No.: A~xW: 99PR2-UTC-029 Circ.: N/A Ewa. Report No.: 998R2-UTD-025 System: PRESSURIZER Component #- 2PZR-01-N2 Weld Type: SPRAYNOZ.ZLE IPRSSUR)ZER Component Size: N/A Schedule I Thickness: N/A 12.0625' Matsial: CARBON STEEL Coaponent Temp. I I.D. # 9001159175 Coulery ULTRAGELII Batch1 99125 Scan Gain: N/A Axial: 506dB Circ.: N/A La Reference Point: STAMPED ZERO Wo Reference Point WELD CENTERUNE Performed Indications YES NO NO YES
- 1. L-Wayse- Base Metal & Weld N/A X N/A N/A 2 Angle Beam - Ppendicular to Weld Clockwise WX Side X N/A X N/A
- 3. Afxl Beam - Perpendicular to Weld Clockwise "Y Side X N/A X N/A
- 4. Anale Beem - Parllel to Weld Clockwise N/A X N/A N/A
- 5. Angle Bean - Parallel to Weld Counterclockwise N/A X N/A N/A
- 8. L-Wm Aw8ae Thickness X WA 2.71'. 2.67" 2.72'
_ _ _xW Side WELD Y Side
- Comments, 30P SHEAR NO RECORDABLE INDICATIONS 10% ID ROLL MAINTAINED DURING SCAN 300 SUPPLEMENTS THE 450 FOR ADDITIONAL COVERAGE TOTAL EXAM COVERAGE 83.64%
REFERENCE COVERAGE SHEET FOR THE PERCENT OF COVERAGE FOR THIS ANGLE.
Examiner: Leval: 1111 Date:
Review LWol: iZt Date.
Reviewer at. : _ Dae _ "-__-_" _
Others:D ANII: Date:
PREcL URIZER NOZZLEL CJOVERAGE PLOT PAGE. - OF:
SHEAR TPANSDUCER REPORT
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Attachment 2 - 3 Component: 2PZR-01-N2 UT-EXAM-02, Rev. 0 Sheet 13 of 24 February. 1999 ULTRASONIC EXAMINATION DATA Station: 8RAIDWOOD Unit 2 Proced. rat Rev.: NOT-C-5 / REV 4 Date: 4-27-99 Page 9 of 20 Calibration Report No.: Axid: 998R2-lLJTC-030 Circ.: N/A Exam. Report No.: 99SR24JTD-025 System: PRESSURIZER Component #: 2PZR-01-N2 Weld Type: SPuRAYNOZZLERSSzER Component Size: N/A Schedule / Thickness: N/A / 2.025" Material: CARBON STEEL Component Temp. / I.D. # 90 /159175 Couplant ULTRAGEL II Batch , 99125 Scan Gain: N/A Axil: 43.6dB Circ.: N/A Lo Reference Point: STAMPED ZERO Wo Reference Point: WELD CENTiERLINE Perforned Indc:iob YES NO NO YES
- 1. L-Wae- Base Metal & Weld N/A X N/A N/A 2 Angle Bearn - Popendicular to Weld Clockwise X Side X N/A X N/A
- 3. A*naISea - Pwparler toWed Cockwise Side X N/A X N/A
- 4. Angle Bearn - Parallel to Weld Clockwise N/A X N/A N/A
- 5. Angle Beam - Parallel to Weld Counterclockwise N/A X N/A N/A
- 6. L-WawA Aýge Thickness X WA 2.71" 2.6.r 272"
-W Sid WELD r Side Commnts:
400 SHEAR NO RECORDABLE INDICATIONS 10% ID ROLL MAINTAINED DURING SCAN 400 SUPPLEMENTS THE 600 FOR ADDITIONAL COVERAGE TOTAL EXAM COVERAGE 83.64%
REFERENCE COVERAGE SHEET FOR THE PERCENT OF COVERAGE FOR THIS ANGLE.
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- 1. L-Wa - BasewMW & Weld. N/A X N/A N/A 2 Angle Beem - Perpendi.cul*r to Weld Clodwise "X Side X WA X N/A
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450 SHEAR NO RECORDABLE INDICATIONS 10% ID ROLL MAINTAINED DURING SCAN ADDITIONAL COVERAGE ACHIEVED WITH THE 300 TOTAL EXAM COVERAGE 83.64%
REFERENCE COVERAGE SHEET FOR THE PERCENT OF COVERAGE FOR THIS ANGLE.
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Calbstion Report No.: Aval: 9MR2-UTC-032 Circ.: 999R2-UTC-032 Exam. RiportNo.: 99MP2-UTD-025 System: PRESSURIZER component 2PZR-O1-N2 Weld Type: s*ou iz ga,z, Componert Size: N/A Schedule) Thickn: N/A / 2.0825 Matefal: CARBON STEEL CompornwtTemp.1/.D.# W01159175 Cou;aT ULTRAGEL II Batch
- 99125 Scan Gain: N/A AWWl: 56.0dB Circ.: 56.0dB Lo Reference Point: STAMPED ZERO Wo Reference Point WELD CENTERUNE Performed Indications YES NO NO YES
- 4. AngMe Beem - PMa to Weld Clockwse X N/A x WA
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- 6. L-WakeAwge
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60' SHEAR. NO RECORDABLE INDICATIONS 10% ID ROLL MAINTAINED DURING SCAN ADDITIONAL COVERAGE ACHIEVED WITH THE 400 AND 700.
TOTAL EXAM COVERAGE 83.64%
REFERENCE COVERAGE SHEET FOR THE PERCENT OF COVERAGE FOR THIS ANGLE.
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,wzzOw _Pn*ssUmZaR CoMoert Size. N/A Schedule / Thickness: N/A 12.0825" Material: CARBON STEEL Con~iop Temp. / I.D. # 90 /159175 Coulant ULTRAGEL II Batcht 99125 Scan Gain: N/A Ael: 884dB Circ.: N/A Lo Retesrnce Point STAMPED ZERO Wo Refveriec Point WELD CENTERUNE Perfonrd Inr YES NO NO YES
- 3. Angle Sen - Pewpendticu to Weld Clockwise Y Side X X WA A N/A
- 4. AngLe Bemn - Parallel to Weld Clocwtse N/A X WA MIA
- 5. Angle Beam - Parallel to Weld Counterokise N/A X N/A N/A
- 6. L-Wave Aveae Thickness X N/A 2.71" z.,7" 2.72' W"XSide WELD "Y Side 700 SHEAR NO RECORDABLE INDICATIONS 10% ID ROLL MAINTAINED DURING SCAN 700 SUPPLEMENTS THE 600 FOR ADDITIONAL COVERAGE TOTAL EXAM COVERAGE 83.64%
REFERENCE COVERAGE SHEET FOR THE PERCENT OF COVERAGE FOR THIS ANGLE.
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ISI Program Plan Braidwood Station Units 1 & 2, Second Interval 10 CFR 50.55a RELIEF REQUEST 12R-50 Attachment 2-4 Braidwood Station Unit 1 Limited Examinations Revision 0 (Page 1 of 29) 1.0 Component Weld Number: 2PZR-01-N3 Code Category / Item: B-D / B3.1 10 Configuration: Pressurizer Relief Nozzle-to-Vessel Weld
2.0 Applicable Code Edition and Addenda
ASME Section XI 1989 Edition with no Addenda (including Mandatory Appendices)
3.0 Applicable Code Requirement
Table IWB-2500-1, Examination Category B-D requires volumetric examination of Item B3. 110 (Pressurizer Nozzle-to-Vessel welds).
Figure IWB-2500-7(b) depicts the required examination volume (A-B-C-D-E-F-G-H),
which includes the actual circumferential weld and adjacent base metal on either side of the weld extending to a distance of one-half the thickness of the wall from the extremities of the weld crown.
ASME Section XI Mandatory Appendix I requires ultrasonic examination of vessel welds greater than 2" thick to be conducted in accordance with ASME Section V, Article 4.
ASME Section V, Article 4 requires:
T-441.3.2.4 Extent of Scanning: Wherever feasible, the scanning of the examination volume shall be carried out from both sides of the weld on the same surface. Where the configuration or adjacent parts of the component are such that scanning from both sides is not feasible, this fact shall be included in the report of the examination.
T-441.3.2.5 Angle Beam Scanning: Wherever feasible, each examination shall be performed in two directions, i.e., approaching the weld from the opposite directions and parallel to the weld from opposite directions.
T-441.3.2.6 Scanning for Reflectors Oriented Parallel to the Weld: The angle beam search units shall be aimed at right angles to the weld axis, with the search unit manipulated so that the ultrasonic beams pass through the entire volume of weld metal.
The adjacent base metal in the examination volume must be completely scanned by two angle beams, but need not be scanned by both angle beams from both directions.
T-441.3.2.7 Scanning for Reflectors Oriented Transverse to the Weld: The angle beam search units shall be aimed parallel to the axis of the longitudinal and circumferential welds. The search unit shall be manipulated so that the ultrasonic beams pass through of the examination volume. Scanning shall be done in two directions 180 degrees to
ISI ProgramPlan BraidwoodStation Units 1 & 2, Second Interval 10 CFR 50.55a RELIEF REQUEST 12R-50 Attachment 2-4 Braidwood Station Unit 1 Limited Examinations Revision 0 (Page 2 of 29) each other to the extent possible. Areas blocked by geometric conditions shall be examined from at least one direction.
Code Case N-460, which accepts a reduction in examination coverage provided the reduction is less than 10%.
4.0 Impracticality/Burden The pressurizer vessel relief nozzle-to-vessel weld is approximately 2.8" thick. The pressurizer nozzle and vessel are clad with stainless steel on the inside diameter surface. The geometry of the nozzle along with the presence of the cladding on the inside diameter of the pressurizer result in limited access to the entire examination volume. The propagation for the ultrasonic beam was in the shear mode. Normally this mode would allow the ultrasonic beam to reflect off the inside surfaces and create a two-beam axis at right angles to each other; however, the presence of the stainless steel cladding precludes the ultrasound beams from reflecting at the inside diameter from the shell/cladding interface. The nozzle geometry tapers away from the weld resulting in limited scanning surfaces available for transducer coupling on the nozzle side of the weld resulting in additional examination limitations. These factors result in limited examination coverage from the scan directions required by ASME Section V and Section XI. These limitations are inherent to the original design of the pressurizer vessel. Conformance with the ASME Section Xl requirements for essentially 100% of the volumetric coverage would require extensive structural modifications to the pressurizer vessel.
5.0 Alternative Examinations or Testing In addition to performing the 0, 45 (recorded as 46 degrees in coverage calculation data), 60, and 70 degree scans to the extent practical as required by Appendix I, additional 30 and 40 degree scans were performed to supplement coverage. The aggregate examination coverage achieved was 80.9%.
In addition to completing the required volumetric examination to the extent practical, numerous system leakage tests (ASME Section XI Category B-P and Generic Letter 88-05) at nominal system operating pressure (2235 psig) and temperature (557°F) as well as the bare metal visual examinations associated with NRC Bulletin 2004-01 of the upper pressurizer vessel head were completed with no evidence of leakage associated with the pressurizer relief nozzle-to-vessel weld noted during the course of the interval.
Radiography as an alternative is not feasible because access is not available for film placement.
ISI ProgramPlan Braidwood Station Units 1 & 2, Second Interval 10 CFR 50.55a RELIEF REQUEST 12R-50 Attachment 2-4 Braidwood Station Unit 1 Limited Examinations Revision 0 (Page 3 of 29) 6.0 Justification for Granting Relief No additional examinations were completed during the inspection interval; however, the examination coverage of 80.9% along with the results of the pressure test and bare metal visual inspections provide reasonable assurance that pressure boundary integrity has been maintained for this component throughout the interval.
7.0 Precedents Similar examination limitations for pressurizer relief nozzle-to-shell welds were encountered and similar examination coverage was accepted for the following units:
Byron Station Units 1 and 2:
Letter from R. Gibbs (U. S. NRC) to C. G. Pardee (Exelon Generation Company, LLC),
"Byron Station, Unit Nos. 1 and 2 - Inservice Inspection Program Second Interval Relief Requests 12R-22, 12R-23, 12R-25, and 12R-53 (TAC Nos. MD4099, MD4100, MD4101, MD4102, MD4103, MD4104, MD4105, and MD4106)," dated January 15, 2008 Callaway Unit 1:
Letter from D. Terao (U. S. NRC) to C. D. Naslund (Union Electric Company), "Callaway Plant, Unit 1 - Relief Request ISI-41 for the Second 10-Year Inservice Inspection Interval (TAC No. MD3437)," dated January 18, 2007 Wolf Creek Unit 1:
Letter from D. Terao (U. S. NRC) to R. A. Muench (Wolf Creek Nuclear Operating Corporation), "Wolf Creek Generating Station - Relief Request 12R-34 for the Second Ten-Year Interval Inservice Inspection (TAC No. MD0288)," dated November 20, 2006 Catawba Unit 1:
Letter from E. C. Marinos (U. S. NRC) to D. Jamil (Catawba Nuclear Station), "Catawba Nuclear Station, Unit 1, Request for Relief 05-CN-004, Limited Weld Examinations During End-of-Cycle 15 Refueling Outage (TAC Nos. MC8337, MC9171, MC9172.
MC9199, MC9173, MC9202, MC9174, MC9175, MC9176, MC9177, MC9178 and MC9179)," dated September 25, 2006
ISI ProgramPlan Braidwood Station Units 1 & 2, Second Interval 10 CFR 50.55a RELIEF REQUEST 12R-50 Attachment 2-4 Braidwood Station Unit 1 Limited Examinations Revision 0 (Page 4 of 29)
Catawba Unit 2:
Letter from E. C. Marinos (U. S. NRC) to D. Jamil (Catawba Nuclear Station), "Catawba Nuclear Station, Unit 2, Request for Relief from the Requirements of the ASME Code (TAC Nos. MC7004, MC9197, MC9198. MC9199, MC9200, MC9202, MC9203, MC9204, MC9205, MC9206 and MC9207)," dated April 3, 2006 8.0 References 8.1 EPRI TR-112657 Revision B-A, "Revised Risk-Informed Inservice Inspection Evaluation Procedure"
Attachment 2 - 4 Component: 2PZR-01-N3 t4JflF-COV-O1 Rev. 0
- Sheet 5 of 29 February, 1999 NDE-COV-01 Rev. 0 EXAMINATION COVERAGE Station: BRAIDWOOD Unit: 02 Date: 04/27/99 Page I of System: PRESSURIZER Comp. ID: 2PZR-01-N3 Exam. No.: 99BR2-UTD-026 Config: PERESSURIZER to RELIEF NOZZLE Procedure/ Rev.: NDT-C-5, REV. 4 NDT-Z-1, REV. 1 Examiner: MIKE KICKBUSCH Level: II Examiner: TIMOTHY GAHAN Level: II Notes: LIMITATION DUE TO NOZZLE CONFIGURATION NDE Method: UT X MT N/A PT N/A Comments:
Total weld metal examination volume (WMV) achieved : 88.13%
Total base metal examination volume (BMV) achieved: 73.67%
Total examination volume achieved: 80.90% (88.13 + 73.67 = 161.8Q'7 2 = 80.90)
Reference attached examination coverage calculation sheet for details.
ASME Section XI Examination Volume Achieved: 80.90%
Attachments: Yes / No YES LEVEL: 2 DATE: _____
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IW 1"kA- 5r/i j/jc LEVEL: ja DATE: 5-1/-?
ANII: DATE: "
2PZR-01-N3 .41 2PZR..Ol-N3 99OR2-UTD-026 992UD.2
.... e PERCENT PERCENT WELD MATERIAL (WMV) ACHIEVED UTILIZED COMMENTS 0o 100.00% 100.00%
30- (X) 57.30% 57.30% 30"(X) USED TO SUPPLEMENT 46-(X), % COVERAGE BASED ON 30" 300 (Y) 100.00%
40- (X) 35.90% 35.90% 40°(X) USED TO SUPPLEMENT 60"(X), % COVERAGE BASED ON 400 400 (Y) 100100%
468 (X) 30.70%
46° (Y) 100.00% 100.00%
600 (X) 8.50%
60°- 100.00% 100.00%
70- (Y) 99.70%
46- (CW) 100.00% 100.00%
40 (CCW) 100.00% 100.00%
60" (CW) 100.00% 100.00%
600 (CCVV) 100.00% 100.00%
793.20% TOTAL 793.2019 = 08.13% WMV ACHIEVED 0 0
3 PERCENT PERCENT BASE MATERIAL (BMV) ACHIEVED UTILIZED COMMENTS 0* 73.30% 73.30%
30" (X) 47.80%
30"(Y) 78.20%
40- (X) 42.20% CD 40' (Y) 84.50%
468 (X) 36.80%
468 (Y) 87.90% 87.90%
- 60. (X) 13.50%
600 (Y) 90.90% 90.90%
70" (Y) 90.70%
48" (cW) 85.90% 65.90%
46- (CcW) 65.90% 65.90%
60 (CW) 65.90W/ 85.90%
600 (CcW) 65.90% 65.90%
616.70% TOTAL 616.7017 r 73.67% BMV ACHIEVED TOTAL WELD METAL 88.13%
tOTAL BASE MATERIAL 73.67% TOTAL EXAMINATION COVERAGE IS 80.90%
EXAMINER: PREPAREDay: * .,
REVIEWED BY:
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Attachment 2 - 4 Component: 2PZR-01 -N3 UT-EXAM-02, Rev. 0 1 Sheet 7 of 29 DATA February, 1999 ULTRASONIC EXAMlNATaON ULTRASONIC EXAMINATION DATA Station: BRAIDWOOD Unit: 2 Procedurea Re,: NDT-C-5 / REV 4 Date: 4-27-99 Page 3 of Calibration Report No.: WHAZ 99BR2-UTC-028 SM 99BR2-UTC-028 Exam. Report No: 99BR2-UTD-026 System: PRESSURIZER Component t 2PZR-01-N3 WeUl Type: PRESSURZERRELEFNZZLE Component Size: N/A Schedule t Thijcmess: N/A /2.065" Masteijl CARBON STEEL ComponsnTemp,.I.D.# 90' F/159175 CoupWAnt: ULTRAGEL 11 Batcht 99125 Scan Gain: N/A WHAZ 25.6dB BM*
Lo Reference Point STAMPED ZER( Wo Reference Point WELD CENTERUNE Performad Indcations YES NO NO YES
- 1. L-Wave - Base Metal & Weld X N/A X NA 2 Anige Sewn - Perp*eicular to Weld Cloclfwae " Sie NA X N/A N/A
- 3. Angie Beam - Perpendicular to Weld Clockwise "Y Side N/A X NA N/A
- 4. AngIe Beam - Parallel to Weld Clockwise N/A x N/A WA
- 6. L-Wave mAgeThicimess X WNA 2.72r 2.81" 2.79"
"" Side WELD Y" Side Comments: O SCAN *GAIN ADJUSTED TO MAINTAIN 80% BACKWALL NO RECORDABLE INDICATIONS TOTAL EXAM COVERAGE 80.90%
REFERENCE EXAM COVERAGE SHEET FOR THE PERCENT OF COVERAGE FOR THIS ANGLE.
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component Size: N/A Schedule / Thickness: N/A I 2.0825' Wvedal: CARBON STEEL Component Temp. / I.D. # 90-1159175 COu~plrt ULTRAGEL 11 Batch # 99125 Scan Gain: PN/A AWiS: 50.6dB Clrc.: NIA Lo Reference Point STAMPED ZERO Wo Reference Pant: WELD CENTERUNE Perfomied Indtcafions YES NO NO YES
- 1. L-Wave- BaseMetal & Weld WA X N/A N/A 2 Andle Beam - PEMpendclv to Weld Clockmwe W Side X WA X N/A
- 3. Anle Beam - EMM'Lcu to Weld Clockwise -r Side X N/A X N/A
- 5. Angle Beem - Palel to Weld CounterckdWse
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X N/A N/A 2.72 . 2.81, N/A 2.79 0
.... ...... ")'Side WELD -Y Sid 300 SHEAR NO RECORDABLE INDICATIONS 10% ID ROLL MAINTAINED DURING SCAN 30* SUPPLEMENTS THE 450 FOR ADDITIONAL COVERAGE TOTAL EXAM COVERAGE 80.90%
REFERENCE EXAM COVERAGE SHEET FOR THE PERCENT OF COVERAGE FOR THIS ANGLE.
Fxeriner .tQ \ U.Qp Q ,::- 1l. d Leve: 11/I11 DOW,: CL101____
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Attachment 2 - 4 Component: 2PZR-01 -N3 UT-EXAM-02, Rev. 0 Sheet 14 of 29 February, 1999 ULTRASONIC EXAMINATION DATA StaUion: BRAIDWOOD Unit 2 ProcdurW Rev.: NDT-C-5 / REV4 Date: 4-27-99 Page to of u1 Calbration Report No: Axial: 99BR2-UTC-030 Circ.: N/A Exam. Report No.: 998R2-UTD-026 System: PRESSURIZER Component #: 2PZR-0 1-N3 Weld Type: PRESSURIZER I RFLEF NOZZLE Cknponent Stm: N/A Schedule / Thickness: N/A/ 22,W825' Mateial: CARBON STEEL Corniponr Terp. / I.D.# 90W/159175 Ccuplt ULTRAGEL II Batch #: 99125 Scan Gain: N/A Axial: 43.6dB Owe.: NIA~
Lo Refernom Point STAMPED ZERO Wo Rereruice Point WELD CENTERUNE Performed Indications YES NO NO YES
- 1. L-Wave - BaseMtal & Weld N/A X N/A N/A 2 Angle Bawn - Perpenxdculur to Weld Clockwise WXSide X N/A X N/A
- 4. Angle Beam - Parallel to Weld Clockwise N/A X W/A N/A
- 5. Angle Bewn - Parallel to Weld Counterclockwise N/A X N/A N/A 6, L-Wav Aver* e Thbckmss X N/A 2z72 2.81' 2.79W L"_X" Side WELD -C Side Cmwnnts:
400 SHEAR NO RECORDABLE INDICATIONS 10% ID ROLL MAINTAINED DURING SCAN 400 SUPPLEMENTS THE 60° FOR ADDITIONAL COVERAGE TOTAL EXAM COVERAGE 80.90%
REFERENCE EXAM COVERAGE SHEET FOR THE PERCENT OF COVERAGE FOR THIS ANGLE.
T~v-.~O\ Levl: 1l/11 Date: ",11!
Revlkur. L.m: Data: ,/a" !
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Attachment 2 - 4 Component: 2PZR-01-N3 UT-EXAM-02. Rev. 0 Sheet 18 of 29 February, 1999 ULTRASONIC EXAMINATION DATA Sta*on; BRAIDWOOD Unit 2 Procedumf Rev.: NDT-C-51 REV 4 Date: 4-27-99 Page %L4 of -
"-i Calbation Report No.: AAM: 9BR24UTC.031 Circ.: 99BR24UTD-031 Exam. Report No.: 99BR2-UTD-026 System: PRESSURIZER Caoponent t 2PZR-01-N3 Weld Type: PRESWIZERIRjUEFHOMZZ CaTionent Size. NIA Schedule I Thickness: N/A I 2.0625' Material: CARBON STEEL Cornonent Temp. I I.D. # 9(g / 159175 Couplant ULTRAGEL II Ba"
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YES NO NO YES
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- Y Side X N/A X N/A
- 4. An8e Beam - Parae to Weld Clockise X N/A X N/A S. Angle Beam - Parallel to Weld Counterlocimise x N/A x WA
- 6. L-Wa 8Ays e Thickness X N/A 2.72" 2.81' 2.79" wXSide WELD "Y Side 450 SHEAR NO RECORDABLE INDICATIONS 10% ID ROLL MAINTAINED DURING SCAN ADDITIONAL COVERAGE ACHIEVED WITH THE 300 TOTAL EXAM COVERAGE 80.90%.
REFERENCE EXAM COVERAGE SHEET FOR THE PERCENT OF COVERAGE FOR THIS ANGLE.
Lamlr: 111/11 Date. & /uO/
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Attachment 2 - 4 Component: 2PZR-01-N3 UT-EXAM-02. Rev. 0 Sheet 23 of 29 February, 1999 ULTRASONIC EXAMINATION DATA Staion: BRAIDWOOD Unit 2 Proceduref Rev.: NDT-C- IREV 4 Data: 4-27-99 Page !ft of --
Calibxraion Report No.: Axial: 99BR2-UTC-032 Circ.: 99BR2-UTD-032 Ea. Report No.: 99SR24UTD-026 Systemr PRESSURIZER Corncwnt
- 2PZR-01-N3 Weld TAWe: PRESSURIZER IREEFNOZZU Componet Size: N/A Schedule / Thickness: N/A I 2.0=25 Material: CARBON STEEL Caqinn Terrp. lI.D. # 9 1159175 Corp*ant ULTRAGEL 11 Batch k 99125 Scan Gain: N/A Axial: 560dB Circ.: 56.0dB Lo Rateeance Point: STAMPED ZERO Wo Reference Point WELD CENTERUNE Peorfmaed Idwtions YES NO NO YES
- 1. L-Wave- BaseMta & Weld N/A X N/A NIA 2 Angle Beam - Perpendiclar to Weld Cokwise X Sie X WA X NIA
- 3. An6l Beam - Papencloular to Weld Clockdse -Y Side X NIA X N/A 4.ArdlDBewn-Pard.toWeld C *oc~se X N/A X NIA
- 5. Angl Bearn - Parallel to Weld
- X N/A X NIA
- 6. L-WaveAerae Thinmes X N/A 2.72* 2.81 . 2.79"
-X Side WELD -Y Side Comments:
600 SHEAR, NO RECORDABLE INDICATIONS 10% FSH ID ROLL MAINTAINED DURING SCAN.
ADDITIONAL COVERAGE ACHIEVED WITH THE 400 AND 70*
TOTAL EXAM COVERAGE 80.90%.
REFERENCE EXAM COVERAGE SHEET FOR THE PERCENT OF COVERAGE FOR THIS ANGLE.
1i1Il Dole: C 10 /q9 Reiriemer hF- DatW.
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Attachment 2 - 4 Component: 2PZR-01-N3 UT-EXAM-02, Rev. 0 Sheet 27 of 29 February, 1999 ULTRASONIC EXAMINATION DATA Station: BRAJWOOD Unit 2 Procedurl Rem.: NDT-C-5 I REV 4 Date 4-27-99 Pape ja f ý Celibrtlon Report No.: Axl: 99SR2-UTC-033 Circ.: WA -Ex R.ooteNo.: 998R24JTD-System: PRESSURIZER Component #. 2PZR-01-N3 Weld Type! P*EsumzE-RIrzEuu mOZZtE Component Siw: NIA Schedule / ThiCMness: NA 12.0825" Material: CARBON STEEL Cai~pentTenmp./I .D. # 90Pl159175 CouCNt ULTRAGEL 11 Batcht 99125 Scae Gain: NIA AiAW: 68.4dB Circ.: NIA LA)Referenc Point STAMPED ZERO Wo Reference Point- WELD CENTERUNE Performed Indlcabons YES NO NO YES
- 1. L-Waw- Base Mtal &Weld NA X N/A WA 2 Anl Bewn - P *dlcvW to Weld Clowise W Side WA X WA WA
- 4. Angle Bearn - Parael to Weld Clocwise N/A X WA .NA
- 5. Seem - Para..e to Weld C.ounterd.owie WA X NWA WA
- 6. L-WMv A bTickness X WA 2.72" 2.81" 2.7W
...... _ _ _= "X"Sift WELD . Y Side Commenits:
700 SHEAR NO RECORDABLE INDICATIONS 10% ID ROLL MAINTAINED DURING SCAN 700 SUPPLEMENTS THE 600 FOR ADDITIONAL COVERAGE TOTAL EXAM COVERAGE 80.90%.
REFERENCE EXAM COVERAGE SHEET FOR THE PERCENT OF COVERAGE FOR THIS ANGLE.
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ISI ProgramPlan Braidwood Station Units 1 & 2, Second Interval 10 CFR 50.55a RELIEF REQUEST 12R-50 Attachment 2-5 Braidwood Station Unit 1 Limited Examinations Revision 0 (Page 1 of 7) 1.0 Component Weld Number: 2SG-01-SGC-02 Code Category / Item: C-A / C1.30 Configuration: Steam Generator Tube Sheet-to-Stub Barrel Weld
2.0 Applicable Code Edition and Addenda
ASME Section XI 1989 Edition with no Addenda (including Mandatory Appendices)
3.0 Applicable Code Requirement
Table IWC-2500-1, Examination Category C-A requires volumetric examination of Item C1.30 (Tube Sheet-to-Shell welds). Table IWC-2500-1 Note (1) states essentially 100%
of the weld length shall be examined.
Figure IWC-2500-2 depicts the required examination volume (E-F-G-H), which includes the actual circumferential weld and adjacent base metal 1/2" on either side of the weld from the extremities of the weld crown.
ASME Section Xl Mandatory Appendix I requires ultrasonic examination of vessel welds greater than 2" thick to be conducted in accordance with ASME Section V, Article 4.
ASME Section V, Article 4 requires:
T-441.3.2.4 Extent of Scanning: Wherever feasible, the scanning of the examination volume shall be carried out from both sides of the weld on the same surface. Where the configuration or adjacent parts of the component are such that scanning from both sides is not feasible, this fact shall be included in the report of the examination.
T-441.3.2.5 Angle Beam Scanning: Wherever feasible, each examination shall be performed in two directions, i.e., approaching the weld from the opposite directions and parallel to the weld from opposite directions.
T-441.3.2.6 Scanning for Reflectors Oriented Parallel to the Weld: The angle beam search units shall be aimed at right angles to the weld axis, with the search unit manipulated so that the ultrasonic beams pass through the entire volume of weld metal.
The adjacent base metal in the examination volume must be completely scanned by two angle beams, but need not be scanned by both angle beams from both directions.
T-441.3.2.7 Scanning for Reflectors Oriented Transverse to the Weld: The angle beam search units shall be aimed parallel to the axis of the longitudinal and circumferential welds. The search unit shall be manipulated so that the ultrasonic beams pass through of the examination volume. Scanning shall be done in two directions 180 degrees to
ISI ProgramPlan Braidwood Station Units 1 & 2, Second Interval 10 CFR 50.55a RELIEF REQUEST 12R-50 Attachment 2-5 Braidwood Station Unit 1 Limited Examinations Revision 0 (Page 2 of 7) each other to the extent possible. Areas blocked by geometric conditions shall be examined from at least one direction.
Code Case N-460, which accepts a reduction in examination coverage provided the reduction is less than 10%.
4.0 Impracticality/Burden The steam generator tube sheet-to-stub barrel weld is approximately 3.3" thick. Access to scanning the complete circumference of this weld in all required directions is limited by a number of inspection covers, branch connections, a weld pad, and a vessel identification plate. These factors result in limited examination coverage from the scan directions required by ASME Section V and Section XI. These limitations are inherent to the original design of the steam generator vessel. Conformance with the ASME Section XI requirements for essentially 100% of the volumetric coverage would require extensive structural modifications to the steam generator vessel.
5.0 Alternative Examinations or Testing The required 0, 45, and 60 degree scans required by Appendix I, were completed to the extent practical. The location and extent of the noted limitations precludes any additional scanning angles increasing examination coverage. The aggregate examination coverage achieved was 88.4%.
In addition to completing the required volumetric examination to the extent practical, numerous system leakage tests (ASME Section XI Category B-P and Generic Letter 88-05) at nominal system operating pressure (885 psig) and temperature (4450 F) were completed with no evidence of leakage associated with the tube sheet-to-shell weld noted during the course of the interval.
Radiography as an alternative is not feasible because access is not available for film placement.
6.0 Justification for Granting Relief No additional examinations were completed during the inspection interval; however, the examination coverage of 88.4% along with the results of the completed pressure tests provide reasonable assurance that pressure boundary integrity has been maintained for this component throughout the interval.
ISI ProgramPlan Braidwood Station Units 1 & 2, Second Interval 10 CFR 50.55a RELIEF REQUEST 12R-50 Attachment 2-5 Braidwood Station Unit 1 Limited Examinations Revision 0 (Page 3 of 7) 7.0 Precedents Similar limitations (structural limitations) on a Category C-A steam generator shell circumferential weld were encountered and accepted for the following unit:
Catawba Unit 2:
Letter from E. C. Marinos (U. S. NRC) to D. Jamil (Catawba Nuclear Station), "Catawba Nuclear Station, Unit 2, Request for Relief from the Requirements of the ASME Code (TAC Nos. MC7004, MC9197, MC9198. MC9199, MC9200, MC9202, MC9203, MC9204, MC9205, MC9206 and MC9207)," dated April 3, 2006 8.0 References 8.1 EPRI TR-1 12657 Revision B-A, "Revised Risk-Informed Inservice Inspection Evaluation Procedure"
(Z Westinghouse Calibration Data Sheet Plant I Unit BRAIDWOOD 12 Data Sheet# A2R13-UT-037 Company EXELON Page 1 of 4 Comp I System Tube Sheet - Stub Barrel / SG Procedure No. EXE-ISI-210 Cal. Checks rime Rev I Chng. No. Rev0 Cal. Block No. BWD 062 Initial Calib. 07:32 Cal. Block Temp. 75°F Thermometer SIN: 105537 Initial Calib. Date 4/24/08 Size NIA Sch. NIA 13.95'"1-m Fernitic Austenitic Intermediate N/A Search Unit #1 Each Major CRT Div. 0.60, Manufacture: KBA Intermediate N/A Serial No.: 01 BTJR Cal. Direction: WAxial [ Circ. fS Both No. of Elements: I Final Calib. 14:15 Size: 1.0* Shape: Round Scan Area:
II L to Weld toWeld m Final Calib. Date 4t24/08 Freq. .2.25 MHz Style:
Exam Angle: 0° Mode:
Gamma Long Couplant Measured Angle: N/A Code Category: C-A Code Item: C01.30 Type: ULTRAGEL II Wedge Style: NIA Batch: 06225 Search Unit Cable Recordable Exam Access Indications Sens. Type: RG-174 Examination Area / Weld Yes INo Geom Length: 6 No. of Con.: 0 Tube sheet 2SG-01-SGC-02 Stub Barre X 44.0 d8 Instrument Settings Make I Model: Krautkramer USN 58L SW Serial No.: 104765 Delay: 1.0241 Range: 6.0" MtI Cal / Vel: 0.2326 Pulser. SQUARE Damping: 500 Reject: 0%
Remarks I Reason for Incomplete Scan(s) COMPONENT TEMP: 89*F Rep. Rate:AUTO HIGH Freq: 2.25 MHz Scanned +14dB over reference sensitivity. See attached sheet for limitations. Filter FIXED Mode: DUAL OFF 88.4% Code coverage obtained. NRI Rectify: FULLWAVE Voltage: 450 N 1 1__ .. . Pulse Width: 100 Examiners: r Level II Date 4V24/08 Reference Sensitvity (Sens.)
"eiws , _ . ?urtLevel au atio 4/24/08 Axial: N/A Circ: N/A SDH Sensitivity: 30.0 Zero: N/A ELOYAUEVEL 0 AMEW 7 VA,17 r r wm=
A, AO~~~
- Weesinghouse Calibration Data Sheet A-. 4 - - - -
Plant I Unit BRAIDWOOD 12 Data Sheet # A2RI3-UT-037 V I--
Company EXELON Page 2 of 4 Camp i System Tube Sheet - Stub Barrel I SG Procedure No. EXE-ISI-210 Cal. Checks Time Rev I Chng. No. Rev 0 Cal. Block No. BWD 062 Initial Caib0. 07:36107:41 Cal. Block Temp. 75°F Thermometer S/N: 105537 Initial Calib. Date 4/24/08 Size N/A Sch. N/A /3.95" "T" Intermediate N/A M] Ferritic 2 Austenitic Search Unit #1 Search Unit #2 Each Major CRT Div. = 0.90" 11.2" Intermediate N/A Manufacture: KBA facture: KBA Serial No.: 009XBK No.: H2500 Cal. Direction: E]Axal E Circ. E3 Both Final Calib. 14:18114:22 No. of Elements: 1 Elements: 1 -, > F' Scan Area: to Weld to Weld M Final Calb. Date 4/24/08 Size: 0.5" x 1.0" Freq. 2.25 MHz Style:
Exam Ane Shape:
45." Mode:
Gamma Rect Shear 0.5"xlX U ShCape 2.25 MHz Style:o SModeiu60r MoTe'TU Rec*=r :
aDCnj 5 e D
Couplant Measured Angle: 45" ired Angle: 55 cCD (D Code Category: C-A Code Item: C01.30 Type: ULTRAGEL II Wedge Style: Non Integral e FStye: NonIntegral Batch: 06225 -4 Search Unit Cable Search Unit Cable U/)
Recordable Exam Access Indications Type: RG-174 RG-174 IGeom Soks.
Examination Area I Weld Yes No Length: 6' No. of Con.: o hi: 6U No. of Con.. 50 Tube Sheet 2SG-01-SGC-02 (45* AX) swb aaei X 55.5 dB Instrument Settings Instrument Settings Tube Sheet 2SG-01-SGC-02 (45* CW/CCW) s& Bamwe X 55.5 dB Make I Model: Kraulkraimer USN 58L SW Make I Model: Krautkcrarner USN 581 SW Tube Sheet Serial No.: 104765 Serial No.: 104765 G,-01-SGC-02 (60- AX) 1Stub Barel X 59.5 dB Delay:. 12.6662 Range: 9.0" Delay: 152038 Range. 12.0" Tube Shteet M' Cal IVel: .1269 Pulser SQUARE Mti C4at / WIl: .1270 Pulser. SQUARE 2SG-1-SGC-02 (60- CWC Stubae_
& X 59.5 dB Damping: 500 Reject: 0% Damp ing: 500 Reject: 0%
Remarks / Reason for Incomplete Scan(s) COMPONENT TEM: OBF Rep. Rate:AUTO HIGH Freq: 2.25 MHz Rep. Flate:AUTO HIGM Freq: 2.25 MHz Scanned +14dB over reference sensitivity. See attached sheet for limitations. Filter: FIXED Mode: DUAL OFF Filter FIXED Mode: DUAL OFF 88.4% Coj coverage obtained. NRI Rectify: FULLWAVE Voltage: 450 Recti, ~:FLLLWAVE Voltage: 450 Pulse Width: 100 Pulse Width: 100 Reference Sensitivity (Sens.) Referf nce Sensitivity (Sens.)
Lentl If Date 4N24/08 Axial: N/A Ciro: N/A Axial: N/A Circ: NIA SDH Sensiti : 41.5 SDH 1Sensitivity: 45.5 Rev , Fuither Evaluation Required? rN7lYes iTINo Zero: N/A Zero: N/A Ie~o InniY DATE 0EB k
-1ýO 0 0 r rNWEODATE& A - 6
INSPECTION SeRVCES Pag 3 of 4 We..tnghouse WELD PROFILE I DATA PLANT BRAIDWOOD UNIT 2 SKETCH 2SG-01 SYST. COP. SG I sRm01BA PROCEDURE EXE-ISI-210, Rev. 0
~E.XMINER JDATE 4124f2008
.. ,' IDENT.
,... 2SG-O-SGC-02
- ,~_, ~ ~ ** uof Mrfcw-w .L~11.: ,*,,',,...,
WELD CROWN 1.7" 112 SCALE UP 0-0 o M~
r 45450 WS (40
- r3 0 r?. o~
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- Westinghouse LUMITArTION TO EXAMINATION PLANT BRIDWOOD UNiT 2 SKETCH 2.SG-01 SYSTEMUIOPONENT SG /Stea en 2RC01BA PROCEDURE EXE-4SI-210, Sev- 0 EKAW"' 4-b DATE 4124100 Owpas fmawm, Levet II RELATED TO: LIT I FT _ WI _ _ r IDENT. 100. 2SG-O1-SGC-02 PROVIDE GENERAL INPORMATION TO DESCRIDE APPROXIMATE SIE, LOCATION AND TYPE OF LMOTAT1ON.
0 Wea Lmigl -427.W a8.4% Coverage LUmbfnim on,stud ban W -68.0' (84.1%) 0 umltagor* tor tube tl swie -57.0 (887%)
4j?
÷ Lkn8d irtm scams - 37.0r (91.3%) x 2 oaT.
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