Text

Forwards Info to Support Determination That It Is Impractical to Comply W/Exam Requirements of ASME Section XI for Plant,Unit 1.Info to Support Determination & Request for Relief from Applicable ASME Section Requirements,Encl
	ML20198S365
Person / Time
Site:	McGuire
Issue date:	01/15/1998
From:	Barron H; DUKE POWER CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	NUDOCS 9801260168
	Download: ML20198S365 (88)
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{{#Wiki_filter:. -s 1 -- [~~S Duke Power Company i an~v vv c uLJ McGuirr Nwlear Station - = d ** a, % Mco1yp 12700 Ilagers Ferry Rd. _ lluntenville, NC 28078-9340 H. B. Berton We kident McGuire (7N) 875-4800 omct Nwlear Generation [kprement (?M) 875-4809 tar a January 15, 1998 U.S. Nuclear Regulatory Commisicn Attention: Document Control Desk Washington, D.C. 20555

Subject:

Duke Energy Corporation McGuire Nuclear Station, Unit 1 Docket No. 50-369 Request for Relief, 97-004 Duke has determined that it is impractical to comply with the examination requirements of ASME Section XI for McGuire Nuclear Station Unit 1. Pursuant to 10CFR50.55a(g) (5) (iii), please find enclosed information to support this determination and a request for relief from the applicable ASME Section XI requirement (s). Should you have any questions regarding this issue, please contact Michael Cash at (704) 875-4117. Very truly yours, f d U-f / g H.B. Barr n h Enclosures womV P

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e U.S. Nuclonr R gulatory Commiccion January 15, 1998 Page 2 x c t. L.A. Reyes -Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 F. Rinauldi, Project Manager Office of Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 9H3 Washington, D.C. 20555 S.M. Shaeffer Senior NRC Resident Inspector McGuire Nuclear Station

e n i U.S. Nucicar Rcgulatory Commission January 15, 1998 Page 3 bxc: J.O. Barbour ELL l File: Relief Request 97-004

... =. i - l -Serial No. 97-004 - Page 1 of 12_ Duke Energy Corporation Station McGuire_ Unit.L 2 9 FIRST.10-YEAR INTERVAL REQUEST FOR RELIEF NO. 97-004 4 Pursuant to 10CFR50.55a (g)(5)(iii), Duke Energy Corporation has determined that compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the . level of quality and safety. Conformance with examination requirements of ASME Section XI is not practical for McGuire Nuclear Station Unit 1. Information is therefore being submitted in support of this determination and a request is being sought for relief from the applicable ASME Section XI requirement (s). 1. System / Components (s) for Which Relief is Requested: Reactor Vessel _ eld Numbers item Numbers Description W I 1RPV10-442 B01.011.003 Lower Shell to Bottom Head IRPVl-442A B01.012,001 Upper Shell Long Seam @ 60 degrees 1RPVl-442B B01.012.002 Upper Shell Long Seam 180 @ degrees 1 RPV l-442C - B01.012.003 Upper Shell Long Seam @ 300 degrees 1RPV3-442A B01.012.007 Lower Shell Long Scam @ 60 degrees -i IRPV3-442B - B01.012.008 Lower Shell Long Scam - @ l80 degrees IRPV3-442C B01.012.009 Lower Shell Long Scam @ 300 degrees I RPV4-469 ' B01.021.002 Bottom Head IRPV7-442 _ B01.030.002 Nozzle Belt to Flange q 'IRPVS 445A B03.090.001 Inlet Nozzle to Shell @ 67 degrees 4 m 'cv-e w ,ev y gyw pa1-+-wa -r,9 r y.- g+a.,' w A t p 4

i Serial No. 97-004 Page 2 of 12 System / Comnonents(s) for V'hich Relief is Reauested: Continued Reactor Vessel Weld Numl>ers ljem Numliers Description IRPV5-445 A B03.090.001 A Inlet Nozzle to Shell @ 67 degrees IRPV5 445B B03.090.002 Inlet Nozzle to Shell @ l13 degrees 1RPV5-445B B03.090.002A Inlet Nozzle to Shell @ l13 degrees 1RPV5 445C B03.090.003 Inlet Nozzle to Shell @ 247 degrees IRPV5-445C B03.090.003A Inlet Nozzle to Shell @ 247 degrees IRPV5-445D B03.090.004 Inlet Nozzle to Shell @ 293 degrees IRPV5-445D B03.090.004A Inlet Nozzle to Shell @ 293 degrees IRPV5 445E B03.090.005 Outlet Nozzle to Shell @ 22 degrees IRPV5-445E B03.090.005A Outlet Nozzle to Shell @ 22 degrees IRPV5-445F B03.090.006 Outlet Nozzle to Shell @ 158 degrees IRPV5-445F B03.090.006A Outlet Nozzle to Shell @ 158 degrees IRPV5-445G B03.090.007 Outlet Nozzle to Shell @ 202 degrees IRPV5-445G B03.090.007A Outlet Nozzle to Shell @ 202 degrees IRPV5-44511 B03.090.008 Outlet Nozzle to Shell @ 338 degrees IRPV5-44511 B03.090.008A Outlet Nozzle to Shell @ 338 degrees IRPV5-445AR B03.100.001 Inlet Nozzle to Shell @ 67 degrees IRPVS-445BR B03.100.002 Inlet Nozzle to Shell @ 113 degrees

7 Serial No. 97 004 Page 3 of 12 Weld Numbers item Numbers Description iRPV5-445CR 303.100.003 Inlet Nozzle to Shell @ 247 degrees 1RPV5-445DR B03.100.004 Inlet Nozzle to Shell @ 293 degrees 1RPV5-445ER B03.100.005 Outlet Nozzle to Shell @ 22 degrees IRPVS-445FR B03.100.000 Outlet Nozzle to Shell @ 158 degrees IRPVS-445GR B03.100.007 Outlet Nozzle to Shell @ 202 degrees IRPV5-445HR B03.100.008 Outlet Nozzle to Shell @ 338 degrees II. Code Reauirement: " Examination Category B-A, Pressure Retaining Welds in Reactor Vessel per Table IWB-2500-1, Figure Nos. IWB 2500-1,IWB 2500-2,IWB 2500-3 and IWB 2500 4" Note (2) adds the words " Includes essentially 100% of the weld length." " Examination Category B-D, Full Penetration Welds of Nozzles in Vessels Inspection Program B" per Table IWB-2500-1, Figure No. IWB-2500-7 111. Code Reouirement from which Reliefis Reauested: Reliefis requested from the requirement of examining essentially 100% of the weld length. Due to part geometry and actual physical barriers, obtaining greater than 90% of the weld volume as outlined in Code Case N-460, which is utilized by Duke Energy is not possible. ASME Section V, Article 4, T441.4.4 Scanning Requirements,1980 Edition !hrough winter 1980 Addenda as (modified by Code Case N-460) requires scanning of the examination volume (s) using three angle beams and a straight beam from both sides of the weld. When scanning for reflectors parallel to the weld, the angle beams shall be aimed at right angles to the weld axis, with the search unit (s) 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 both angle beams, but need not be completely scanned by both angle beams from both directions (any combination of two angle beams will satisfy the requirement).

t Serial No. 97-004 Page 4 of 12 When scanning for re0cctors 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 other to the extent possible. Areas blocked by geometric conditions shall be examined from at least one direction. Code Case N-460 allows credit for full volumc coverage if it can be shown that greater than 90% of the required volume has been examined. IV. Basis for Relief: During the ultrasonic examination of the Reactor Vessel welds during Refueling Outage 7, the minimum coverage requirement of ASME Section XI,1980 Edition through Winter 1980 Addenda, clarified by Code Case N-460, could not be met. Due in part to geometry and actual physical barriers this coverage was unattainable. A combination of multiple beam angles was used to obtain the maximum coverage possible. The attached examination reports document the actual amount of examination coverage obtained. Drawings showing details of the affected welds including calculation methods are included as Attachment 2. Request for Relief 97 004, Part 1 Examination Category H A, Pressure Retaining Welds in Reactor Vessel. The Reactor Vessel Lower Shell to Bottom llead Weld (IRPV10-442) (Item Number 801.0!1.003) was limited to 59.00% aggregate coverage of the required weld volume. The principal limitation for this weld is the presence of six core guide lugs, which limit scanning in the axial and circumerential directions. The Reactor Vessel Upper Shell Long Seam Weld (1RPVI-442A)(Item Number B01.012.001) was limited to 90.00% aggregate coverage of the required weld volume. The principal limitation for this weld is due to nozzle location which splits the weld into two sections. The Reactor Vessel Upper Shell Long Seam Weld (IRPVl-4428) (Item Number B01.012.002) was limited to 31.00% aggregate coverage of the required weld volume. The principal limitation for this weld is due to nozzle location on both sides of the weld.

o i Serial No. 97-004 Page 5 of 12. The Reactor Vessel Upper Shell Long Seam Weld (IRPVI-442C)(Item Number B01.012.003) was limited to 90.00% aggregate coverage of the required weld volume. The principal limitation for this weld is due to nozzle location, which splits the weld into two sections. The Reactor Vessel Lower Shell Long Seam Welds at 60,180 and 300 degrees (IRPV3-442A, IRPV3-442B, IRPV3 442C)(Item Numbers B01.012.007, B01.0!2.008 and B01.012.009) were limited to 84.00% aggregate coverage of the required weld volume. The principal limitations for these welds were the presence of the core guide lugs located at the bottom end of the welds. r The Reactor Vessel Bottom licad Weld (IRPV4-469) (Item Number B01.021.002) was limited to 29.00% aggregate coverage of the required weld volume. The principal limitation for this weld is the presence of the incore nozzles. The Reactor Vessel Nozzle Belt to FlangS Weld (IRPV7-442) (Item Number B01.030.002) was limited to 82.00% aggregate coverage of the required weld volume. The principal limitation for this weld is the presence of keyway and specimen tube cutouts and the flange configuration itself. Request for Relief 97-004 Part 2, Examination Category H D, Full Penetration Welds of Nozzles in Vessels, Inspection Program H The Reactor Vessel Inlet Nozzle to Shell Welds at 67,113,247 and 293 degrees. (IRPV5-445A, IRPV5-4458, IRPV5-445C and IRPV5-445D)(Item Numbers B03.090.001, B03.090.001 A; B03.090.002, B03.090.002A; B03.090.003, B03.090.003A; and B03.090.004, B03.090.004A) were limited to 85.00% aggregate coverage of the required weld volume, The four Inlet Nozzle to snell Welds were limited due to the reactor vessel nozzle configuration. The Reactor Vessel Outlet Nozzle to Shell Welds at 22,158,202 and 338 degrees (IRPV5-445E, IRPV5-445F, IRFV5-445G and IRPV5-445H)(Item Numbers B03.090.005, B03.090.005A; B03.090.006, B03.090.006A: B03.090.007, B03.090.007A; and B03.090.008, B03.090.008A) were limited to 43.00% - aggregate coverage of the required weld volume. The four Outlei Nozzle to Shell Welds were limited due to the reactor vessel nozzle configuration. T-

s Serial No. 97-004 Page 6 of 12 The examinations of the inner radius of the Reactor Vessel inlet Nozzles at 67, 113,247 and 293 degrees (IRPV5-445AR, IRPV5-445BR, IRPVS-445CR a.sd IRPV5-445DR) Item Number 803.100.001, B03.100.002, B03.100.003 and B03.100.004 were limited to 58.00% aggregate coverage of the required volume. The four inlet Nozzle Inner Radius Sections are limited due to the reactor vessel nozzle configuration. The examinations of the inner ndius of the Reactor Vessel Outlet Nozzles at 22, 158,202 and 338 degrees (IRPV5 445ER, IRPV5-445FR, IRPV5-445GR and 1RPV5-44511R) (Item Number B03.100.005, B03.100.006, B03.100.007 and. B03.100.008) were limited to 74.00% aggregate coverage of the required volume. The four Outlet Nozzle Inner Radius Sections are limited due to the reactor vessel nozzle con 0guration. V. Alternate Examination or Testing: In addition to the volumetric examination that has been performed on the McGuire reactor vessel, Duke Energy has performed a visual examination of the internals and the inside of the reactor vessel as required by ASME Section XI, Table IWB 2500-1. This visual examination did not identify any rejectable conditions per ASME Section XI acceptance standards. The use of radiography as an alternate volumetric examination method is not feasible due to component thickness and restrictions from physical barriers which prohibit access for the placement of source, image quality indicators, film, etc. In addition, the background radiation levels would not allow for a radiographic examination that would render meaningful results. Performing the ultrasonic examination from the outside of the reactor vessel is not a viable option. The design of McGuim's reactor building prohibits access for the equipment and personnel from outside the vessel. Duke Energy Corporation will continue to perform ultrasonic examinations of all reactor vessel welds to the maximum extent practical in accordance with the requirements of ASME Section V, Article 4,1989 Edition and Regulatory Guide 1.150, Revision 1, Appendix A. Ccde Case N-460 will be utilized in all cases where less than 100% but greater than 90% weld coverage is obtained. In cases where weld coverage of 90% or less is obtained, a request for relief from ASME Section XI Code requirements will be. submitted per the requirements of 10CFR50.55a.

e ,n Serial No. 97-004 - Page 7 of 12 -Duke Energy Corporation proposes in lieu of the greater than 90% coverage requirement of Code Case N-460 that the examination coverage obtained on the welds listed in Attachment I be considered to provide an acceptable level of quality and safety. No additional examinations will be performed. VI. Justification for the Granting of Relief Part 1: -The Reactor Vessel Lower Shell to Bottom llead. Upper Shell Long Seam, Lower Shell Long Seams at 60,180 and 300 degrees, and the Bottom Head Welds were examined to the maximum extent practical using ultrasonic techniques in accordance with the requirements of Section V, Article 4 of the 1980 Edition thru Winter 1980 Addenda of the ASME Boiler and Pressure Vassel Code. Duke Energy Corporation will continue to ultrasonically examine the welds, including inside radius sections, to the extent practical within the limits of original. design and construction. This will provide reasonable assurance of weld / component integrity. Thus, an acceptable level of quality and safety will have been achieved and public health and safety will no: be endangered by allowing relief from the aforementioned Code requmments. The Reactor Vessel Lower Shell to Bottom IIcad Weld (.L V10442)(Item Number B01.011.003): The principal limitation for this weld is the presence of six core guide lugs welded to the vessel IDjust above the weld on the lower shell section. These lugs are approximately 19 inches tall,27 inches wide and extend 8 inches radially toward the center of the vessel, each positioned every 60 degrees around the vessel circumference. These dimensions include the attachment weld radius which physically limits the contact transducer head travel. The weld was-scanned in two directions, perpendicular (axial) and parallel (circumferential) to - the weld between the six guide lugs. Some physical limitations also exists due to the surface pronle where the hemispherical head and lower shell cylinder meet. Therefore, the 100% volumetric examination is impractical for this weld. The imposition of this requirement would create a considerable burden on Duke - Energy Corporation. During the examination of this weld, the Utilized Wall-

Transducer Head process was used to obtain the maximum possible coverage.

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o Serial No. 97-004 Page 8 of 12 The Reactor Vessel Upper Shell Long Seam Welds (IRPVI-442A,lRPVI-4428,1RPVl-442C)(Item Number B01.012,001, B01.012.002, B01.012.003): The long seam welds join sections of the upper reactor shell (nozzle belt) to each other. The principal limitation for these welds is the present nozzle geometry. Due to the nozzle geometry,100% volumetric examination is impractical for these welds. The imposition of this requirement would create a considerable burden on Duke Energy Corporation. During the examination cf these welds, the Utilizcd Wall Transducer Head process was used to obtain the maximum possible coverage. Reference drawing 1213926D for scan coverage. The Reactor Vessel Lower Shell Long Seam Welds at 60,180 and 300 degrees (IRPV3-442A, IRPV3-442B.lRPV3 442C)(item Numbers B01.012.007, 801.012.008 and B01.012.009): These longituanal seam welds join the lower circumferential shell sections in the core region of the reactor vessel. The principal limitations for these welds were the presence of the core guide lugs welded to the vessel ID above the weld (weld 10-442) on the lower shell section. These lugs are approximately 19 inches tall,27 inches wide, and extend 8 inches radially toward the center of the vessel, and are positioned every 60 degrees around the vessel circumference. These dimensions include the attachment weld radius. These guide lugs interfere with the axial and circumferential scans. These welds were scanned in two directions, perpendicular (axial) and parallel (circumferential) to the weld. Scan coverage from the perpendicular (axial) and parallel (circumferential) scans in the vicinity of the six guide lugs is limited due to interfetence with the contact transducer head. Therefore, the 100% volumetric examination is impractical for these welds. The imposition of this requirement would create a considerable burden on Duke Energy Corporation. During the examination of these welds the Utilized Wall Transducer Head process was used to obtain the maximum possible coverage. The Reactor Vessel Bottom Ilead Weld (IRPV4-469)(Item Number B01.021.002): This circumferential weld joins the reactor vessel transition ring (lower head) to bottom head. The principal limitation for this wcld is the presence of the incore nozzles. Therefore, the 100% volumetric examination is impractical for this weld. The imposition of this requirement would create a considerable burden on Duke Energy Corporation. During the examination of this weld, the Utilized Wall Transducer llead process was utilized to obtain the maximum possible coverage. Reference drawing 12139276D for scan coverage.

~ 4. Serial No. 97-004 ' Page 9 of 12. t The Reactor Vessel Nozz!: Belt to Flange Weld (IRPV7-442)(Item Number ~ B01.030.002): This weld joins the reactor vessel llange to the upper shell (nozzle belt). The principal limitation for this weld is the presence of keyway and - specimen tube cutouts and the flange configuration itself, Therefore, the 100% - volumetric examination is impractical for this weld. The imposition of this requirement would create a considerable burden on Duke Energy Corporation. During the examination of this weld, the Utilized Wall Transducer Head process. was used to obtain the maximum possible coverage. Reference drawing 4 1213923D for scan coverage. Pursuant to 10 CFR 50.55a(g)(6)(i), granting this relief for the Reactor Vessel Lower Shell to Bottom Head, Upper Shell Long Seam, Lower Shell Long Seams at 60,180 and 300 degrees, and the Bottom llead welds will provide reasonable assurance _ f weld / component integrity, and is authorized by law. In addition, the o requested relief will not endanger life or property or the common defense and - security and is otherwise in the public interest giving due consideration to the burden upon the licensee that could resul,t if the requirements were imposed on the 1 facility. - Justification for the Granting of Relief Part 2: The four Reactor Vessel Inlet Nozzle to Shell Welds and the Inner Radius Exams at 67,113,247 and 293 degrees, the four Reactor Vessel Outlet Nozzle to Shell Welds and the inner Radius Exams at 22,158,202 and 338 degrees were examined to the maximum extent practical using ultrasonic techniques in accordance with the requirements of Section V, Article 4 of the 1980 Edition thru Winter 1980 Addenda of the ASME Boiler and Pressure Vessel Code. The Reactor Vessel Inlet Nozzle to Shell Welds at 67,1IA 247 and 293 degrees (IRPV5-445A, IRPV5-445B, IRPV5-445C and IRPV5-445D)(Item Numbers i B03.090.001, B03.090.001 A; B03.090.002, B03.090.002A; B03.090.003, B03.090.003A; and B03.090.004, B03.090.004A): The four Inlet Nozzle to Shell Welds were limited due to the reactor vessel nozzle configuration. Therefore, the g 100% volumetric examination is impractical for this weld. The imposition of this - requirement would create a considerable burden on Duke Energy Corporation. During the examination of this weld, techniques were utilized to obtain the maximum possible coverage. Reference drawing 1213931D for scan coverage. 1 ..g.. y

Serial No. 97 ON Page 10 of 12 The Reactor Vessel Outlet Nozzle to Shell Welds at 22,158,202 and 338 degrees (IRPV5-445E, IRPV5-445F, IRPV5-445G and IRPV5-445H)(Item Numbers 803.090.005, B03.090.005A: B03.090.006, B03.090.006A; B03.090.007, 803.090.007 A; and B03.090.008, 803.090.008A): The four Outlet Nozzle to Shell Welds were limited due to the reactor vessel nozzle configuration. Therefore, the 100% volumetric examination is impractical for this weld. The imposition of this requirement uould create a considerable burden on Duke Energy Corporation. During the examination of these welds, techniques were to utilized to obtain the maximum possible coverage. Reference drawing 1213930D for scan coverage. The Reactor Vessel Inlet Nozzle Inner Radius Exam (IRPV5-445AR, IRPV5-445BR, IRPV5-445CR and IRPV5 445DR)(Item Number 803.100.001, B03.100.002, B03.100.003 and B03.100.004): The four inlet Nozzle Inner Radius Sections are limited due to the reactor vessel nozzle configuration. Therefore, the 100% volumetric examination is impractical for this weld. The imposition of this requirement would create a considerable burden on Duke Energy Corporation. During the examination of these welds, techniques were done to utilized to obtain the maximum possible coverage. Reference drawing 1213931D for scan coverage. The Reactor Vessel Outlet Nozzle Inner Radius Exams (IRPV5-445ER, IRPV5-445FR, IRPV5-445GR and 1RPVS-44511R)(Item Number B03.100.005, B03.100.006, B03.100.007 and B03.100.008): T',e four Outlet Nozzle Inner Radius Sections are liraited due to the reactor vessel nozzle configuration. Therefore, the 100% volumetric examination is impractical for this weld. The imposition of this requirement would create a considerabic surden on Duke Energy Corporation. During the examination of these welds, techniques were utilized to obtain the maximum possible coverage. Reference drawing 1213930D for scan coverage. Pursuant to 10 CFR 50.55a(g)(6)(i), granting this relief for the four Reactor Vessel Inlet Nozzle to Shell Welds and the Inner Radius Exams at 67,113,247 and 293 degrees, the four Reactor Vessel Outlet Nozzle to Shell Welds and the Inner Radius Exams at 22,158, 202 and 338 degrees will provide reasonable assurance of weld / component integrity, and is authorized by law. In addition, the requested relief will not endanger life or property or the common defense and security and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility.

Serial No. 97-004 Page 11 of 12 A Weld Ihamination Summary The reactor vessel welds were examined from the vessel inside surface using automated ultrasonic examination equipment. The examinations were done with vanous contact head arrangements to optimize the maximum examination coverage. This allowed each transducer to scan as close as possible to any obstruction around the area examined. Although the greater than 90% coverage requirements of the Code Case N-460 could not be met, the examinations were performed with modified equipment and tooling designed to obtain the maximum coverage possible. As a result of inspections performed, the greater that 90% requirement has been determined to create a hardship for McGuire Nuclear Station. The reactor vessel welds were examined to the maximum extent practical to the requirements of Section V Article 4 of the 1980 Edition through the Winter 1980 Addenda of the ASME Boiler and Pressure Vessel Code and the additional requirements of Regulatory Guide 1.150. To meet the examination coverage requirements, design modifications would be necessary to gain access to the welds in order to obtain complete coverage. The design modifications are impractical due to the vast scope of work that would be required. Imposition of this requirement would cause a considerable burden on Duke Energy with no commensurate safety benefit realized. Vll. Implementation Schedule: These examinations will continue to be scheduled in accordance with the requirements of ASME Section XI for future inspection intervals at McGuire Nuclear Station Unit 1, utilizing the examination techniques in use by Duke Energy Corporation at that time.

[- I L Serial No. 97-004 1 Page 12 of 12- / Attachments:

1. Detailed listing of welds with limited ultrasonic coverage.

'_. Drawings of affected weld details including calculation methods. 2

3. History of limited ultrasonic examinations of reactor vessel welds.

t 12 /2 [9 7 Evaluated By: .and b lld wu.066 Date Technical Review B - e a Date /S/3/97 I /a,/7,/97 Reviewed By: 1 Date i Date 1L B 97 _0_nXAt-Approved By: 9 i

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? - ASME Class i NDE Inservice inspection Request For Relief Serial No. 97-004 Attachment I For McGuire Unit i Based On ASME XI - 1980 Code "Ihrough Winter 1980 Addenda Page e of 3 lem No. Emmn Categoryf System Or Functum Area To Be Reawm for Request %cM ID % Lacensee Prtymed iP'egure No. Component Exammed Alsemane Examensma B01.01I.003 B-A Reactor Vessel He=ses the fact assemtdes. cawml umer shen to beed scan dae w geomeme iRPV10 442 None mA arul *enel unerna!s. aim B nan Head conSgw n m IWB-2500-I ereen the h of teactor cxxdann weu Actual enmge <eamed. 59 orn B01.012.001 B-A Reactor Vesse] Homes the fuel assemNes. corarol l'pper SheH to bnused sem due so remerx IRPVl-442A Ncae U"8 *** **'d "*"d"*"'"***83" 5

"*'8"'*'""

8 IWB-2500-2 drects the h of reactcv celars 60 Derwes Actual covmge obramed = 90 0rrs B01.012.002 B-A Reactor Vessel Homes the fuel auenddes. cmemi Upper Shen to bnused sca ese to geometnc 1 RPVI-442B None IWB-2500-2 "A *"d *"*' ""*'"*k *8" L""8 *** **'d 5

"6"*'"

8 orects the h cf remetar coolant iso Dertees Actual camee <hamns = 31 an B01.012.003 B-A Reactor Vessel Hees the fuel anemNes, mrumi Upper shcH m Unned scan due to geometne 1RPVI-442C None IWB-2500-2 mA and venet unemals, aim Long Seam %end =6gwarm erects the h of reactnr crmlare V10 Dernes Actual coversge obtamed = 90 Of*5 B01.012.007 B-A Reactor Vessel Homes the fact assemNes, contml ImerShen to brnned scan due to geomemc IRPV3-442A None-IWB-2500-2 """d**"*"""*"'" 1""8 *** **W S

"6"*'"

8 deerts the ihm of react <w coolant 60iks Actusi cowrage obtamed = 84 RN B01.012.008 B-A Reactor Vessel Homes the fuel auenddes, control tewerShell to Unused sca due to geometnc IRPV3-4423 None "d' *"d '***' ""*** 83" 1""8 **" ***'l =6s===n 5 IWB-2500-2 dween the h of reacmr coolant Isotkr Actual coverare etwamed = 84 an B01.012.009 B-A Reactor Vessel umses the ruei assemNes. cornml to m tsher to heed sem due m ge==mc IRPV3-442C None "d'*"d'*"*""'***3'*'" L""8 5*** ***d "6 """ 8 IWB-2500-2 arecu the flow of reactor enotant 300 tkg ? Actual cmerage ottamed = 84 GM i B01.021.002 B-A Reactor Vessel Hases the fuel anembles. cmeml Bean Head I rated scan due m gemetnc !RPV4-469 None IWB-2500-3 mi5h *enet ruemais. aim =6

==<=n 8 direen the h of reactor etmlant Actaal cmerage obtamed = 29 0rS i B01.030.002 B-A Reactor Vessel Houses the fuel auembhes corsrul Nozzle Belt to bnuted scan due to geertrx 1RPV7-442 None IWB-2500-4 "d' *"d '*"*h"'"*#'" "'"8'

"6"""

8 d*retts the Ibra of reactor crxdant Actual coverage chamed = 82 0rn B03.090.001 B-D Reactor Vessel Hases t!r fuel anemNes, control inict Nonle to beed scan due m gemenc 1RPV5-445A None IWB-2500-7 ' d' *"d '*"el miemals. also sheli 67 Deg UT ct=figwarm directs the ik,w of teactor coolant frem Venel ID Actual coverage ottamed = 85 OLFE B03.090.00l A B-D Reactor Vessel Houses the fuel anemNes. corarol Inlet Noule to Unned sca due e gememe 1RPV5-445A None IWB-2500-7 " *"d**"*' " '*'" Shen 67 Deg UT con 6gurarm directs the fdw of reactor coolant f.oru Nozzle ID Actual cmcrage nttamed = 85 Orn B03.090.002 B-D Reactor Vessel Houws the fuel aswmNies. control Inlet Norrie to Umsed scan due to gewrme IRPV5-445B None IWB-2500-7

k ""d **"*' ""*"*8' *I" shen H3 tkg cmrigwarm dreen the h of reactor coolant UT fmm venel Actual coverage otgamed = s5 orn I

ID B03.090.002A B-D Reactor Vessel Houses the fuel assenddn. cmemi inlet Nuje m Unwed sm due m geomeme 1RPV5-445B None IWB-2500-7 "d'*"d**"*h'"****'" Sh*" " 3 U'8' "I'8"*'"" arects the fkm of reactor coolant UT fran Nozzle Actual cmerage otewied = 85 ON ID

i ASME Class i NDE Inser ice Inspection Request For Rehef Serial No. 97-004 Attachment i I ' For McGuire Unit 2 Based On ASME XI-1950 Code Through Winter 1980 Addenda Page 2 of 3 tsem No Enarn Canegory/ sysseta Or Funcwon Asca To Be Reasco For Request Wekt ID N 1.scenwe htymmi Fsgure No Componcan Exammed Aleemase Emanunason B03.090.003 B-D Reactor Vessel Hases the fact aswmblaes,corumi laict Nonle to Unused sca due m geomeme IRPV5-445C None 'd'*"d"'""**h* She' 287 D'8 (""'i8"'*'o" IWB-25(Xb7 derects the !km of reactor coolant UT fm.n Veswl Actual coverage chamed = $$ OM ID B03.090.003A B-li Reactor Vessel Houses the fuel undes, cornrol iniet Nonk m bnued scas due m geomenc 1RPV5-445C None IWB-2500-7 "* **' "'enntanah, aim slan 247 mg engwam directs the ikm of reactru elant UT from Nonle Actual cmmge otumned = 85 GN ID B03fMLOO4 B-D Reactor Vessel Hm es the fuel umbles, caurol Inlet mule so unued scan due so swee-tnc IRPVS-445D Ntme nA and esciintemals al* slien 3 3 N g eng-mm IWB-25Mk7 directs the fkm of reactor contant UT from Vessel actual cmerage obtamed = 85 OA ID B03.0'"1004A B-D Reactor Vessel Hases th fuel assenNes, cawml Inlet Nonle no unned scan due so gemetnc IRPV5 445D None IWB-2500-7 "d**"d**h"'"**'" Sh*" "3 D*8- ""6 """ 8 duccts the fkm of reactor cmlant UT froen Nonle Actual coserage obtamed = 85 OL4 ID B03.090.005 B-D Reactor Vessel Houses the fuel assembles, cornmi Outlet No'rk to Umned scan due e geomeste IRPV5-445E None IWB-2500-7 "* *"d " '"'"" Is. mim shen 22 mg m emngwm-drrects the ihm of reactor ciclant from Vessel ID Actual cmermee obtamed = 43 GM B03.090.005A B-D Reactor Vessel Houses sie furt assernbies, control Outlet Nonle to Unwed scan due so getatic I RPV5-445E None "* *"d ""*' "acmals. ale strn 22 mg m cmsgwarm IWB-2500-7 derects the fLm of reactor coolant fmm Nonle ID Acreal cmerage etwamed = 43 Of4 B03.090.006 B-D Rt. actor Vesse] Houses the fuel aswmbles, contml Outlet Nonk to Unned scan due to gwmetnc IRPV5-44'.F None IWB-2500-7 mos.and msel t nemalt aim shen 158 Deg. wnngurata detects the fkm of reactor coolant UT frorn Veuct Actual coverage otmanned = 43 00% ID B03.090 006A B-D Reactor Vessel Hmses the fuel assenses, canml Outki Nele m Unned scan d e so swmeinc IRPV5-445F None gw g,7$g(p7 rods. and vessel erwernals, aho Shell 158 Deg configuration directs the fkm of reactor coolane UT from Nonle Actual coverage obtamed = 43 04 ID B03.090.007 B-D Reactor Vessel Hou*es tie fuel assembles, emtml Outlet Nonle m beweed scan due to geenetnc IRPV5-445G None IWB-2500-7 "d' *"d ""*' "wemais. alw shen 202 Des wnngww-directs the ikw of reacsor coolant UT from Vessel Actual cmcrage ottaned = 43 00* ID B03.090.007A B-D Reactor Vessel Hmws the fuel wmbles, wntml Ouelet Nonle m Unned scan due m gemanc IRPV5-445G Nome i IWB-25Wh7 nA and senet entern ts. alw shen 202 wg wnngwam derects the fkm of reactor coolane UT frorn Nonle Actual coserage ottamed = 43 00% !D B03.090.008 B-D Reactor Vessel Hases the fuel wmNet watml Oi Ict Nonk so bnned scan due so gwmetnc IRPV5-44511 None IWB-2500-7 rods, and esci unernals. also Shen 338 Des. confir=mm i duccts the (km of reactor ctolant UT from Vessel Actual coverage obtamed = 43 GM ID B03.090 008A B-D Reactor Vessel Hases the fuel auembi% warmi o nle Nonic to unused scan due to geomeme iRPV5-44511 None "d' *"d **" ""nals, aim Shen 338 Deg cangwam IWB-2500-7 directs the Ikm of resaw coulant UT from Nonle Actual coverage obtamcd = 43 un ID L_

t ASME Class 1 NDE Inservice Inspection Request For Relief Serial No. 97-(04 Attachment I ' For McGuire Unit 2 Based On ASME XI-1980 Code nrough Winter 1980 Addenda Page 3 of 3 leera No. Exare Category /. System Or Functme Area To fic Reason For Request Weld ID Na bcemre Propmed ' Figme No Componere Exarruned Attemase Etanunatum B03.100.001 B-D Reactor Vessel ' Houses the fuel assembles control inkt Nonle to Unused scan due so geometnc 1RPV5-445AR. None '*d"'i"'***3" wu 67 Des m.%. --. IWB 2500-7 dueces the kw d reactor coolant Insade Radnes Actual coverage obtained = 58 00% Section B03.100.002 B-D Reactor Vessel Hmes the fuel assemHrs. comol Inlet Nente m Umed scan due e geometnc 1RPV5-445BR None IWB-2500-7 "d' ""d ***' i""*'I'* *I"

" " 3 D"8
""6""

8 ds ects the ihm of reacaer coolant insiste Radies Actual coverage obtamed =58 0175 Sectwn B03.100 003 B-D Reactor Vessel liases the fuel assembles, cetrol inlet Nonle e beed scan due e gecrnetnc 1RPV5-445CR None "d' '"d * i"** alw slien 247 Des c=ngwama IWB-2500-7 directs the flow :.f reactor coolant inside Radms Actual coverage obtained = 58 00% Section B03.100.004 B-D. Reactor Vessel 18e=5es the fuel assembles.eemrol inlet Nonic w Unned scan due to geertne iRPV3445DR - None 'd**"d'*"*'i"""****

"
D'8

'"6"** IWB-2500-7 directs the fkm cf reacsta coolant imide Radres Actual coverrge ohtamed = $8 00% Section B03.100.005 B-D Reactor Vessel Houses the fuel assedet,conuel Outlet Nonle to Unused scan due to geometne 1RPV5445ER None i IWB-2500-7 ' d' *"d " i"iemais. sis shell 22 Deg. corJigwation dsrects the he of reacsor coolant inside Radius Actual coverage obtained = 74 00% Secnon B03.100.006 B-D Reactor Vessel Houses the fact assembles. connut Outlet Nonle to Unused scan due so geometne IRPV5445FR None "d" ""d ****I '"*I' *'" slien 158 Deg emngwatim IWB-2500-7 directs she fkm of reactor coolant Imide Rades Actual coverage obtamed = 74 Cf4 Secten B03.830.007 B-D Reactor Vessel Houses the fuel assembles, control Outlet Nonle te Unted scan due to geertne IRPV5-445GR None "d' ""d **' i""*I' "'" ' wn 202 Dez. cangwatun IWB-2500-7 directs the ihm of reactor coolant imide Radies Actual coserage obtamed = 74 00% Section Bt.' 100.008 B-D Reactor Vessel Houses the fuel assembhes. mnemi Niet Nonle so Unused scan due to geertnc 1RPV5445HR None '*i' *"d " '"'*"*b *l"

" 338 D'8

("6 ""'"* i IWB-2500-7 8 } directs the (km cf reartor coolant Imsde Radres Actual coverage obtamed =74 00% Section i

'g 90 .e- .e 2-4428 A g.442 J MCGUIRE UNIT l CMM CORE 0 100 = REGION WELD 2-442A INSPECTION 2-442C o e Z Z 270 SECTION Z-Z 'I, MIDDLE LONGITUDIN'L WELO 9-442 90 [ -442A J o 3-442s l90 O = y \\, s-442C N 10-442 270 l SECTION Y-Y LOWER LONGITUDINAL WELD Vessel Weld Layout Figure 1 SER NO. 97-004 l~ ATTACHMENT 2 REACTOR VESSEL OUTLINE PAGE 1 OF 68 L f

1 T .] DUKE POWER COMPANY -? =lic GUIRE UNIT 1 1 REACTOR VESSEL EXAMINATION .O i 5 445E-SE(22 degrees)9-] T -442 7 3-445F SE (158 degreesil \\ / / 5-445AR (67 degrees) e 3-4450-sE (202 degrees) 3-445H SE (338 degrees) 1-442A (60' degrees 5 !*N!g"g g[ees I s 1-4423 (180 degrees m, g.442C (300 degrees. 1 5-4450R (293' degrees) ^1NC1F-1-1 (22 degreu l,l 15C1F-2-1 (158 degre s) w j f3-445A-SR (67 degrees i 15C1F-3-1-(202 degrar) F f 1*4458-SE (113 degree i -1NC1F-4*1 (338 degrcas) ,0UTLET NosELE I / *[ M 1F-1-8 (67 degr 3-445C-st (247 degree ]4.f INLET NO3 ELE J-4450-SE (293 degree. ' 5-445ER (22 degress) 5-445FR (150 degrees g" m Y1NC1F-2-4 (113 degree t ~5-4450R (202 degrees) 8-442 I1NC1F-3-8 (247 degree 5-445MR (338 degrees) h1NC1F-4-8 (293 degree 5-4455 (21 degrees)$ "2-442A (0 degrees ~ I 5-445A (61 degrees) }5-4453-(113 degrees) 5-445F(158 degrees)(

- ' 2-4423 (120 degrees

,5-445C (247 degrees), 1-5-4450 (102 degrees) 1,2-442C (240 degrees 5-445D (293 degrees) l 5-445M-(338 degrees i

MIDDLE SHELL i

-454-02 i-l- 9-442 g 3-442A (60 degrees 3-4425 (180 degrees i l 3-442C (300 degrees)- IAMfER sEELL 454-03 ] 10-442 g -{ 1-202A (30 degrees) ' TRANs!TICH RING '1-2023 (90 degrees) 469-01 1-202C (150 degrees) 4-469 g 1-202D (210 degrees) 1-202E (270 degrees) 1-202r (300 degrees) IAMtER READ t: s SER NO. 97 004 ATTACHMENT 2 REACTOR VESSEL OUTLINE - PAGE 2 OF 68 L Figure 2 L u--

k t>* 90* I00* ?/r-e b

s. _

. - =.,. j r as a, 7-442 442 A 8 42 B 42 C i i i _.l }.. l l .{ l,{ l ; i ; i 8-442 I I 1 i l I i i i 21 ok 0* 120* 240* f G 2-442 A 2-442 8 2-442 C e (4 f. I i 1 9-442 1 442 A 3-28 9 M % Cf) 3 42 C ' O e g) N Mq 2 O k Ill !. l l ll .I !. ll ih !. ll ll)l k f .Il l l,! ^ 3 10-442 o< y MA IMS f C O ME r O 4-469 I g i l M T %9

l EXAMINATION COVERAGE FOR WELD: 10 442 LV.'M SHELL TO LWR HEA.D C:fto WIRD AGGREGATE COVERAGE OBTAINED: 89% SCAN M.AN DRAWWO: 18149390 42 Zone Goverage DM81ned Weid: 83% A(acent Base Molet 69% Near(10) Surface: 00% Wolf Lonelh 544 37J M ~ ' ' ) iGoe ":::n;;;; t Volume C:":2"':. Wold 7.61 sq. h Weed 4091.999 ou.k A4acent Base Mela! 43.88 sq. A A4eoent Base Metal 23908.98 m h Near Surfeos 8.68 sq. h Noet Surface 4876.002 ou. A j , ; ; m.ylu - t Exam. Area Len9th Volume Votumn Angle Beam Examined Examined Examined Required Percent Eniqr #. (deg.) Diroolion (eq. h) (h) (cu. in.) (ou.h) Examined 1 0 We 7.6 381.3 2714.0 3713.0 100% 2 0 We 0.0 183.8 0.0 1379.0 0% 3 46 1 7.A 334.1 2600,1 2600.1 100 % 4 i 4 4b 2 7.6 3M.1 2000.1 2600.1 100 % 6 46 1 0.0 210.8 0.0 1683.0 0% 6 46 2 0.0 210.8 0.0 1683.0 0% 7 45 3 7.5 300.8 2268.8 2268.8 100% 8 46 4 7.6 300.0 2268.8 2268.8 100% 9 46 3 0.0 244.1 0.0 1833.2 0% 10 46 4 0.0 244.1 0.0 1833.2 0% 11 60 1 7.6 334.1 2809.1 2609.1 100% 17 60 2 7.6 334.1 2609.1 2609.1 100% 13 60 1 7.6 310.8 1683.1 1683.1 100% 14 60 2 0.0 210.8 0.0 1683.1 0% 16 60 3 7.6 300.8 2268.8 2268.8 100 % 18 60 4 7.6 300.8 2268.8 2268.8 100 % 17 60 3 0.0 244.1 0.0 1833.2 0% 18 60 4 0.0 244.1 0.0 1833.2 0% Todele 23387.8 38828.4 83 % Aqacent Base Metel

Exw, Area Len9th Volume h ene

/ </ - Beam Examined Examhed Examined Required Percent Entry 8 (d% ; Dh>ction (eq. h) (in.) (ou. k) (m h) Examined 1 0 We 43.9 381.3 18861.7 16861.7 100% 2 0 Wa 0.0 183.8 0.0 8067.2 0% 3 46 1&2 419 3M.1 14680.3 14000.3 100% 4 46 1&2 0.0 2:18 0.0 9249.0 0% 6 46 3 43.9 -300.8 13197.8 13197.8 100% 6 46 4 43.9 300.8 13197.8 13197.8 100 % 7 46 3 0.0 244.1 0.0 10711.1 0% 8 46 4 0.0 244.1 0.0 10711.1 0% 9 60 1&2 43.9 334.1 14660.3 14660.3 100 % to 60 1&2 0.0 210.8 0.0 9249.9 0% 11 60 3 43.9 300.8 13197.8 13197.8 100% 12 60 4 43.9 300.8 13197.8 13197.8 100% 13 60 3 0.0 244.1 0.0 10711.1 0% 14 60 4 0.0 244.1 0.0 10711.1 0% ToLk 97983 4 t87384.0 69% %erDarseee Exem. Aw Len9th volume voeurne SER NO. 9? 004 An9 e Beam Examined Examined Examined Regulied Poveent 4 Enwy# (dog ) Dwoot6on (eq. In ) (h) (ou, h) (m h) Examined ATI'ACin(ENT 1 70 antal 8.8 298.6 2644.8 2644.8 100% B01.011.003 2 70 axlel 0.0 248.3 0.0 2130.2 0% 3 70 circ 8.8 381.3 3099.6 3099.6 100% 1RP\\,10 442 4 70 cerc. 0.0 183.8 0.0 1676.6 0% PAGE 4 OF 68 Tote lr 6644.3 9350.0 60%

o i i i t N \\ \\ M~. } i,, ~ + A N k Nh @k, 89 h I s' E 9 nu s e = u y "g -:G / 4 l ,/ ,/ SER NO. 97-004 A'ITACHMENT 2 B01.011.003 l 1RPV10-442 ) PAGE 5 0F 68 I .--.I

O --32 66 / 1 q, l p i {'\\ r U i.kl */

"h u

CT AXIAL SCAN O* COVERAGE ^ 70* NEAR SURFACE \\ / / \\' \\ / / --36.79- / i \\ b 'l'; Y* . u ~ i MdS>Z y eorOO [ AXIAL SCAN k 45' CCVERAGE y e m 60* COVERAGE \\ g i \\' I / u

e o e f i af 3 V 194t1A 04 959'ftt : # .. q ~ _t_ l e N .~~_'r l T ~~~7 ~s, C: l 4- ~~s [ .1y ] m ,J i ,in ___,~ N-3 = 4,8 P 5

~

t t :.' l j !i /~a Y4 M j e. i

A 1

m, - -~ G r W 8 to

e#

r a a-h W W i i o u o SER NO,97 004 XITACHMENT 2 D01.011.003 1RPV10-442 PAGE 7 OF 68

e e e W 3 Y li='.J 01 969'It! 8 I p _ E.- I E C: I l l _ Ikw , epe % .Ep ,g 4 y I ! i ./ 9 .I l g d 1 i $f N in:3 O W e O ?E 3 't 2 3 .8 e = w a '.: E. o O o N SER NO. 97-004 ATTACHMENT 2 B01.011.003 1RPV10-442

AGE 8 OF 68

e e l 6 e us 3y se= tie os ese ter, i - .U E-l t CA 9* * ~ M (, b s I g.y n + e c; i l l i j / l 1 il

. *4 i-mi

_3 L W 8c O df t cc e E

O w

d E O u = Ln v SER NO. 97 004 ATTACHAENT 2 B01.011.003 1RPV10-442 PAGE 9 OF 68 i 1 . +..

t er n - u.....,,,,, q ~ s

n..-

1 x ~~l~O T~_1% ~ es - _4.? f-s N g 't l l / a L l l: ?.g x < b.- _J L W '5% O t'$ 'T t ~ a# a O' l r w O O O O SER NO. 97 004 ATTACHMENT 2 B01.011.003 1RPV10-442 PAGE 10 0F 68

I f 3 Y .... u,,....,,,,, -E-I O = n:

=

l l1 I i1 / i _ TF ~ 3.,F,.,11r,.,-t as l7 s . 1311 l 'j1 Til / er 1 3 / / ($4 ;hy:J. 4,.3 e. / / j' f yy 3m m ;n s U S Vy E., 1 e L1 ?I

F 2 5 Z

g E [

d 5 U Ui u fr O SER NO.97 004 A'ITACHMENT 2 B01.011.003 1RPV10-442 PAGE 11 OF 68

u e m I l u 1: I ll a,

t a

.ill( ' l d ( e, *, I. )]_. L L _ _ in ~ 11 11 LU- :1-e ' l' 'y.,,.. l '... a I l..'1;.'.* ;, IL L J.-I % i 1 i ~,.... .t. w w ee t

r 4

hl l'l ion ror i ii r H' I g !l10 i ,1 01 ,j'lfll:l'1'l' 11 8li l igg ! il gg O! I i I if I il 1[ 10 O! i i i i i i i i i i i L i i i i r i t i i r r i i Il i t i l l f i l l f i l la g, 8 il I H it t l i t t i l le lit l' 1 1 1 1 11 1 1 1 11 1a u u ll-lllllll ll l ' I I ' ! ilWb r i i I t - j' m ~ u } 2 ) ! ! ! 2 ! !! gfh y $ g >:1 E ! ! ! I l l i l l i s a ll ll l ra o t !.lgn gIEa>3 1 ~ = s s s i i, s s i, i s i f; d.' '- l a i n n n o m !i I- } i o ___.4 l

: : E

! ! : 1 ffpJu b ; gaa I _. a 4 o I o

EXAMINATION COVERAEE FOR WELD: 1442 A,C UPPER LONOITUDINAL WELD AGGREGATE COVERAGE OBTAINED: 90 % SCAN PLAN DRAWING:1213938D 02 Zone Coverage Obtained Weld: 89% A4eoerit Base Metal 90% Near(10) Surface: 88% .g_.._ Area Measurement Volume Calculation Weld 14.78 sq. In. Wcld 364.1792 cu. in. Adjacent Base Met 124.08 sq. in. A4scont Base Metal 3057.331 cu In. Near Surface 12.23 sq. in. Near Sui 1 ace 301.3472 cu. in. W W enc. Exam. Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry # (deg.) Direction (sq. In.) (in.) (cu. in.) (cu. In.) Examined 1 0 n/a 14.8 24.6 364.2 364.2 100 % 2 45 1 14.8 18.7 276.5 276.5 100 % 3 45 2 14.8 18.7 276.5 276.5 100 % 4 45 1 0.0 5.9 0.0 87.6 0% 6 45 2 0.0 5.9 0.0 87.6 0% 6 45 3 14.8 24.6 364.2 364.2 100 % 7 45 4 14.8 24.6 364.2 364.2 100 % 8 60 1 14.8 18.7 276.5 276.5 100 % 9 60 2 14.8 18.7 276.5 276.5 100 % 10 60 1 0.0 5.9 0.0 87.6 0% 11 60 2 0.0 5.9 0.0 87.6 0% 12 60 3 14.8 24.6 364.2 364.2 100 % 13 60 4 14.8 24.6 364.2 364.2 100 % Totals: 2927.0 3277.6 89% l Adjacent Base Metal Exam. Area Length Volume Volume l Angle Beam Examined Examined Examined Required Percent Entry # (deg.) Direction (sq. in.) (in.) (cu. in.) (cu in.) Examined 1 0 n/a 124,1 24.6 3057.3 3057.3 100 % 2 45 1&2 115.7 18.7 2164.0 2321.5 93 % 3 45 1&2 0.0 5.9 0.0 735.8 0% 4 45 3 124.1 24.6 3057.3 3057.3 100 % 5 45 4 124.1 24.6 3057.3 3057.3 100 % 6 60 1&2 115.7 18.7 216d.0 2321.5 93 % 7 60 1&2 0.0 5.9 0.0 735.8 0% i 8 60 3 116.7 24.6 2849.9 3057.3 93% 9 60 4 115.7 24.6 2849.9 3057.3 93% \\ Totals: 19199.7 21401.3 90% Near 8urface Exem. Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent i Entry # (deg.) Direction (sq. in.) (in.) (cu. in.) (cu. in.) Examined 1 70 axial 12.2 18.7 223.8 228.8 100 % 2 70 axial 0.0 5.9 0.0 72.5 0% 70 cire. 12.2 24.6 301.3 301.3 100 % SER NO. 97-004 Totats: 530.2 602.7 88% ATI'ACUMENT 2 B01.012.001, B01.012.003 1RPVI-442A, IRPVI 442C PAGE 13 OF 68 l

EXAMINATION COVERAGE FOR WELD: 1-442 B UPPER LONOITUDINAL WELD AGGREGATE COVERAGE OBTAINED: 31 % SCAN PLAN ORAWINO:1213934D42 Zone Coverage Obtained Weld: 28% Aqacent Base Metal 31% Near(10) Surface: 43% ..eensweewme,;.w.aangesam - -r_^ - m_-_-_ x ?n en n = - - 7-"; - _ _ _ r Wold Ang h-74.265 in Art 'Aeasurement Volume CalculaUon Weld 14.78 sq. h Wold 1097.637 cu. h A4acent Base Metal 124.08 sq. h A4acent Base Metal 9214.801 cu. h Near Surface 12.23 sq. h Near Surface 908.261 w. h it.alsseu w e - 4 m.y-wx.auonpoyarage voiculauoneecssusne 44u*=usarsgemammtaleese Wold Exam. Area Length Volume Volume Angie Beam Examir:ed Examined Examined Required Percent Entry # (deg ) Directon (sq. h) (u) (cu. h) (cu. h) Examined '1 0 Na 14.8 20.4 302.0 302.0 100% 2 0 Na 0.0 53.8 0.0 795.7 0% 3 45 1 14.8 20.4 302.0 302.0 100% 4 45 1 0.0 53.8 0.0 795.7 0% 5 45 2 14.8 20.4 302.0 302.0 100% 6 45 2 0.0 53.8 0.0 795.7 0% 7 45 3 14.8 20.4 302.0 302.0 100% 8 45 3 0.0 53.8 0.0 795.7 0% 9 45 4 14.8 20.4 302.0 302.0 100 % 10 45 4 0.0 53.8 0.0 795.7 0% 11 60 1 14.8 20.4 302.0 302.0 100% 12 60 1 0.0 $3.8 0.0 795.7 0% 13 60 2 14.8 20.4 302.0 302.0 100% 14 60 2 0.0 53.8 0.0 795.7 0% 15 60 3 14.8 20.4 302.0 302.0 100% 16 60 3 0.0 53.8 0.0 795.7 0% 17 60 4 14.8 20.4 302.0 302.0 100% 18 60 4 0.0 53.8 0.0 795.7 0% Totals.' 2113.7 76835 28% Adjacent Base Metal Exam. Area Length Volume Volune Angle Beam Examined Examined Examined Required Percent Entry # (deg.) Dirocuon (sq. h) (h) (m. h) (cu. h) Examined 1 0 Wa 124.1 20.4 2535.0 2535.0 100 % 2 0 Wa 0.0 53.8 0.0 6679.8 0% 3 45 1&2 124.1 20.4 2535.0 2535.0 100% 4 45 1&2 0.0 53.8 0.0 6679.8 0% 5 45 3 124.1 20.4 2535.0 2535.0 100% 6 45 3 0.0 53.8 0.0 6679.8 0% 7 45 4 124.1 20.4 2535.0 2535.0 100 % 8 45 4 0.0 53.8 0.0 6679.8 0% 9 60 1&2 124.1 20.4 2535.0 2535.0 100% 10 60 1&2 0.0 $3.8 0.0 6679.8 0% 11 60 3 124.1 20.4 2535.0 2535.0 100% 12 60 3 0.0 $3.8 0.0 6679.8 0% 1 13 60 4 124.1 20.4 2535.0 2535.0 100% 14 60 4 0.0 $3.8 0.0 6679.8 0% Totals: 17744.7 578238 31% Near Surface Exam. Area length Volume Volume SER NO* 97 004 Angle Beam Examined Examined Examined Required Percent Entry 8 (deg.) Direction (sq. h) (h) (cu. h) (cu. h) Examined ATTACIIMENT 2 1 70 axial 12.2 20.4 249.9 249.9 100% B01.012.002 2 70 axial 0.0 53.8 0.0 658.4 0% 3 70 cire 12.2 20.4 249.9 249.9 100% 1RPVI-442B 4 70 c*c 0.0 53.e 0.0 658.4 0% PAGE 14 OF 68 Totals: 499.7 1158.1 43%

1' = j E = l L s = Z [n = C i Z / = ON = 2 /, 4 L = 4 AT = 3 CE PTS i ' L-'/ a 3 i I-i j-ILS s IIIIIIIIl p,8II ,f3hi = YUO !4 lIIlIlI a p1I B r TOB = !I IiII IIli s l 5iiI I IIII Il,l - il [ = E = N

e

= I T# L = R / n(3@yi = = E E / = G T t T A N = .r = i-E [ R = T C E = V D = O L h i =4 = E = s C W 2 = 4 D L MJ 3 E A. \\ FII C \\ II IIIili! T G i I l mIO,[9'_i = i M P \\ \\ l i l t WlI IIIi1i ' i i ,W FiII I Y i IIi1ili L T l lIIIIIilill' m 5I i = M 3 f 30 A = 21 E 3 = = 'U'\\ S I2 = 5 = G 5 Td' 41 = wJk N 6. = O 29 , B- = L 01 e = 3I = t N ' t' ';a 3 A 24 ~ 3 4 E . 4in(.[ge N 3 i 7I

^

iIIIIiili L t = i !I Z E,fII .lli!i ![. n y Z I qiaI i ', I !iil!i O 03 pI L LN 73 iIiIIlili! iI-6 = A 0. TIL 41) m%,Yi = CT 59 IE I5 2 PLP 89 YNI 2 f2 81 1 21 / L mMWyo $ I y O3g 8 m goP 8 8 ~. Enb q>cgwmCe.64wN44",g% w4<bn

I 1ABL[ [ CNM C00R0!NA7[ ~ ~~ ~ ~ -- t i I RANGES ExIENS10N RotAt804 INDEx SCAN FIGURE No. WELO NO. FILE NAME iMCHES DEGREES INCREMENT OIRECTION setup reA*%Et 808.012.005 tRPV 2-4428 M10LONGtY 138.29 2 225.42 113.42 8 126.58 .37' Anlat 4 a a 50s.082.005 IRPW 2-4428 NIOLONGIX 136.87 Z 226.48 114.70 8 825.30 .56' CIRC 4 l t - 6 Bot.082.006 1RPr 2-442C M10LONG2Y 438.29 2 225.82 233.42 8 246.58 .37* AxlAL 4 l t E h 80'.082.006 IRPr 2-442C MIOLONG2x 136.87 2 226.48 234.70 8 245.30 .56* CIRC 4 l

- 6 808.082.004 IRPV 2-442A MIOLONG3Y 438.29 Z 225.12 353.42 8 366.58

.37* l ArlAt 4 l e s i B08.012.004 tRPV 2-442A M I DL ONt:3X 136.87 Z 226.48 354.70 8 365.30 .56' CIRC 4 e - e 808.082.001 IRPV I-442A UPPRLONGsYA 43.06 I 59.33 ^ 52.68 8 67.32 ..F* Atlat / l r e 80s.082.0.8 IRPY t-442A UPPRLONGIXA 38.90 I 59.33 53.09 8 66.98 .56-CIRC 2 1 - G Bot.082.003 IRPV t-442A UPPRLONGtYB 188.92 I

84.36 52.68 8 67.32

.37* AXIAL 2 8 i 801.082 00: IRPy e-442A UPPRLONGerB (88.92 Z 886.13 53.09 8 66.98 .56* CIRC 2 - 8 B0s.082.002

PPV t-4428 UPPRLONG2YA 43.06 I

52.80 172.68 9 887.32 .37* AxlAL 2 - 8 B08.082.002 IRPV l-4428 UPPRL O;4G2x A 38.90 I 52 80 473.89 9 886.91 .56* CIRC 2 s b i i 808.082 003 IRPY t-442C UPPRLONG3YA 43.06 Z 59.33 292.68 8 307.32 .37* AxlAL 2 e - e 800.082.003 IRPV t-442C UPPFLONG3XA 38.90 I 59.33 ,293.09 8 306.98 .56* CIRC 2 s - e Bot.082.003 IRPv t a T UPPRLONG3YB ttt.92 I i84.36 292.68 8 307.32 .37* Axlat / -. 8 808.092.003

RPV t 4420 UPPRLONG3XS 338.92 I

B36.t3 293.09 8 306.91 .56-C ilit 2 e 801.082.007 IRPv 3-442A LO4RLONGtY 247.13 Z 33b.66 53.42 9 66.58 .37* AxlAL 4 . R B08.012.007 IRPY 3-442A LOWRLONGs1 245.78 Z 333.69 54.70 9 65.30' .56* CIRC 4 . e I B08.082.000 IRPY 3-4428 LOWRLONG2Y 247.83 Z 336.66 873.42 8 386.$8 .37* AXIAL e

. g 804.082.008 IRPY 3-4428 LOWRLONG2X 245.78 Z 333.69 874.70 8 185.30

.56* CIRC 4 - 8 Bot.082.009 IRPY 3-442C LOWRLONG3Y 247.83 Z 335.66 293.42 8 306.58 .37* AxlAL 4 e 6 804.082.009 tRPV 3-442C LOWRLONG3x 245.78 Z 333.69 294.70 8 305.30 .56* CIRC 4 1 8 SER NO.97-004 ATTACHMENT 2 ' B01.012.001,B01.012.002,B01.012.003 1RPVI-442A,1RPV1-442B,1RPVI-442C PAGE16 OF68 Y ~ = -e ,-a... - _.,

~ A-e-n+- 2- + ..A O l I e 9 a lW Y.# l l 1 i i i f. 4 1 i g 5 lg 4 l g g 's LtJ N k l l c. O: * ,,i s, s gO s i g i s 1_L 's L1J $ J-n .b N i h N C 1 z =, ~* iE w 4 O h <C 4 C W E ! i1 O

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O \\ ,c '. ' ~ 1,- . ~. -. ~. ~ ~ L 8_ - 60 COVERAGE ,1, - a" ... s t r-i< u ___J. t, I r 8 5k %c L i a5 3 5t oy -a i n.,,... g" e 4a .g. h gP L$ g Tg nozzle REGION i-442 k,. a

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O N SER NO. 97 004 A'1TACHMENT 2 B01.012.001, B01.012.002, B01.012.003 1RPVI 442A, IRPVI 442B, IRPV1442C PAGE 20 0F68

l EXAMINATION COVERAGE FOR WELD: 3 442 A,B,C LOWER LONO(TUDINAL WELD AGGREGATE COVERAGE OBTAINED: 84 % 8CAN PLAN DRAWWOr 1318828042 Zone Coverage Obtained Wend: 84% A4acont Base Metat 84% Near(10) SuTace: 64 % Area Measurement Volume Calculation Weld 11.86 sq. h Wold 1144.846 ou. In: A4acent Base Metal 78 69 eq. h A4eoent Base Metal 7695.948 cu. h Near Surface 10,06 sq. h Near Surfoos 971.0918 ou.h j & 'lXE'.T:C. e ...ICL m t li! r. Exam. Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Cntry # (deg ) Direction (sq. h) (h) (ou. h) (ou.h) Examined 1 0 de 11.9 80.8 957.7 957.7 100% 2 0 Wa 0.0 15.8 0.0 187.2 0% 3 45 1 11.9 80.8 957.7 957.7 100 % 4 45 2 11.9 80.8 957.7 957.7 100% 6 45 1 0.0 16.8 0.0 187.2 0% 6 45 2 0.0 15.8 0.0 187.2 0% 7 45 3 11.9 80.8 957.7 957.7 100% 8 45 4 11.9 80.8 957.7 957.7 100 % 9 45 3 0.0 16.8 0.0 187.2 0% 10 45 4 0.0 16.8 0.0 187.2 0% 11 60 1 11.9 80.8 957.7 957.7 100 % 12 60 2 11.9 80.8 957.7 957.7 100 % 13 60 1 0.0 16.8 0.0 187.2 0% 14 60 2 0.0 16.8 0.0 187.2 0% 15 60 3 11.9 80.8 957.7 957.7 100 % 18 60 4 11.9 80.8 957.7 957.7 100 % 17 60 3 0.0 16.8 0.0 187.2 0% 18 60 4 0.0 16.8 0.0 187.2 0% Totals: 8819.3 10303 8 84% Adjacent Base Metal Exam. Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry # (dog.) Drechon (eq. h) (h) (ou. h) (ou,h) Examined 1 0 We 78.7 80.8 6354.2 6354.2 100% 2 0 de 0.0 16.8 0.0 1241.7 0% 3 45 1&2 78.7 80.8 6354.2 6364.2 100% 4 45 1&2 0.0 18.8 0.0 1241.7 0% 6 45 3 78.7 80.8 6354.2 6354.2 100% 6 45 4 78.7 80.8 6364.2 6354.2 100 % 7 45 3 0.0 15.8 0.0 1241.7 0%- U 8 45 4 0.0 15.8 0.0 1241.7 0% R 9 60 1&2 78.7 80.8 6354.2 6354.2 100 % 5 10 60 1&2 0.0 15.8 0.0 1241.7 0% e4 11 60 3 78.7 80.8 6354.2 6354.2 100 % E 12 60 4 78.7 80.0 6354.2 6354.2 100% 4% 13 00 3 0.0 16.8 0.0 1241.7 0% 14 60 4 0.0 16.8 0.0 1241.7 0% Totals: 44479.5 63171.6 84 % Near Surface i Exam. Area Longm Volume Volume d Angle Beam Examined Examined Examined Required Percent C? Entry # (deg ) 06rectbn (sq. h) (in.) (m.h) (cu.h) Examined g 4 on 1 70 axial 10.1 80.8 812.3 812.3 100% p; ", A 2 70 axial 0.0 16.8 0.0 158.7 0% w 1 3 70 circ 10.1 80.6 812.3 812.3 100% S plh*+ 4 70 ch 0.0 15.8 0.0 168.7 0% Totals: 1824.T 1942.2 84% e ( C 4 l M4MM b l t

OW ,f. O O N ._) 4 LLI 4 I O J t <CZ H O O O D 4 3 Q l N ~ k <C O N-N O 4 4 g 4 4 h3O _J O SER NO. 97404 NITACHMENT 2 B01.012.007, B01.012.008, B01.012.009 1RPV3-442A,1RPV3 442B,1RPV342C PAGE 22 OF 68 -

o _m I A m w U) @37 R M e e m N 5 b 00 M M .J.J

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b

1 3

247.I3 .2..s i r AXIAL 69.8t e9.53 >ze)M mg w g t m O *U." N md*Oo >2 1 g P i 8 si6.94 w Om $.M M Iu E~8 W si <ew 'i s'C* e. t i Iklp S?R] y 8 1 336.66 EE $2/ LOWER -:e r G LONG SEAM '5 0

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Lu C.D CC en a U E i b-h 2- _3-3 o I l y) ~ ~ a ~

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~ ~ Qw}f.$ l .+ 5 N g\\ $.I. ' ' e \\ \\ i 4 l j ii I Qu k; -H ,Y d ? + -r cf L3 kl l ~ .' x =4 SER NO. 97-004 ATTACHMENT 2 B01.012.007, B01.012.008, B01.012.009 1RPV3-442A, IRPV3-442B, IRPV3-442C PAGE 27 OF 68

9 i 7 i (1 1 5 4 o i 3 1 2 l 8 i { d. ) ) 1 .H-- - f~'l I 1 O c .g-. -- 1 ~1,. ~,.,. _, ~ .. ~ =l r. r. .~ y, n ~ lI I ~ =- ~ l c ~ ~. ~ ~. - j ci = [ ,,r,-.- ~. ~ o- 'a. e i 4 4. m s a . _. = ~ er vm ) ". O.~A*O ?-Y.e.Y $% _ p f_ Y &Y l . _ _,,_ _ _ _ _ _ _ n n _ _ _ _-. \\ J J _ _ _-,I QQQQ I il 1 - IliI c__. III1 y-Iili i11I IIll IIII I11I IIiI 'a D_ _ b _ _ & _ _ b _ _M _ _ Mk _ _d

== ~ n n i a min u "'.'i ' " -~ ~ ~.. = _ _ _,,, n A ,mnmE wut t __ w. o w on=n .m E.>:---- i ......o .,.,,.,,,,d.,.- a 1 i i = l s 2_ 4 i -s 2 I i SER NO.97 004 ATTACHMENT 2 i B01.012.007, B01.012.008, B0LS12.009 1RPV3-442A,1RPV3 442B,1RPV3-442C PAGE 2R OF 62 i

e o EXAMINATION COVERAGE FOR WELD: 4 469 (FULL NODE) LOWER HEAD TO40TTOM HEAD AGOREGATE COVERAGE OBTAINED: 29 % 6CAN PLAN ORAWING NO.1218827 M2 Zone Coverage O Hained Wokl: 31% A4acerd Base Metal 29% Near (ID) Surface' 29% . VAdd ength-426 37 h ' ' ' ~ Area 94easuromoed Vo6p mo C h i. Wekt FA1 sq h Wald 3161.992 cu.h A4aomrd Base Metal 29.86 sq h A4acerd Base mew 12697.29 cu h Near Gurface 6.66 sq. A Near Surfeos 2813.786 cu. A new Exam. Area tan 9th Volume Volume Ante Beam Examined Czemined t.zamined Required Percord l Cidry # (deg) D6recson (sq. h) (h) (ou. h) (ou.h) Examined 1 0 We FA 8.8 f5.6 66.6 100% 8CAN 'A' 2 0 We FA 7J $3.2 63.2 100% 8CAN T 3 0 We 7A 8.8 66.6 66.6 100% SCAN'C' 4 0 We 7A 18.9 138.8 139.8 100% SCAN'D' 6 0 We FA 0.9 73.2 73.2 100% 8CAN T C 0 We 7.4 21.9 162.1 162.1 100 % SCAN T* 7 0 We 7.4 38.1 282.1 282.1 100% SCAN'G* 8 0 We 7A 8.8 66.6 65.6 100% 8CAN T 9 0 We 0.0 303.0 0.0 2248.1 0% NOT USED 10 46 1 7A 8.8 66.6 66.6 100% SCAN 'A' 11 45 1 7A 7.2 63 2 63.2 100% 8CAN T 12 46 1 7A 8.8 65.6 66.5 100% 8CAN'C' 13 48 1 FA 18.9 138.8 139.8 100% 8CAN 'D" 14 45 1 7A 9.9 73.2 73.2 100% 8CAN T 16 45 1 FA 21.9 162.1 162.1 100% 8CAN 'I' 17 4$ 1 7A 38.1 282.1 282.1 100% SCAN'G* 18 45 1 7A 8.8 66.6 66.6 100% SCANY 1P 45 1 0.0 303.0 0.0 2246.1 0% NOTUSED 20 45 2 7A 8.8 66.6 65.6 100% SCAN *A* 21 45 2 7A 7.2 63.2 63.2 100% SCAN'B' 22 45 2 7A 8.8 66.6 66.5 100% SCAN'C' 23 45 2 7A 18.9 139.8 139.6 100% SCAN 'D' 24 46 2 7A $_9 73.2 73.2 100% SCAN T 26 45 2 7A t't4 182.1 162.1 100% SCAN'P 28 45 2 7A 44.5 282.1 282.1 100% SCAN V 27 45 2 7.4 0.6 66.6 66.6 100 % 8CAN T 28 45 2 0.0 T&2.0 0.0 2246.1 0% NOT USED 29 45 3 7A 8.6 66.6 65.6 100 % SCAN *A* 30 46 3 7A 7.2 63.2 63.2 100 % SCAN 'B' 31 46 3 7A 8.8 66.6 66.6 100% SCAP1'C' 32 46 3 7A 18.9 139.8 139.8 100 % SCAN'D' 33 45 3 7.4 9.9 73.2 73.2 100 % 8CAN T 34 46 3 7A 21.9 182.1 162.1 100% SCAN'P 36 45 3 7.4 38.1 262.1 282.1 100 % 8CAN 'O' 36 45 3 7A 8.8 66.6 66.5 100 % 8 CANT 37 45 3 0.0 303.0 0.0 2245.1 0% NOT USED 38 45 4 0.0 8.8 0.0 66.6 0% SCAN 'A' 39 45 4 7A 7.2 63.2 63.2 100% SCAN 'B' 40 46 4 7A 8.6 65.6 S$.6 100 % SCAN'C' 41 45 4 7A 18,9 139.8 139.8 100% SCAN 'D' 42 45 4 7A 8.9 73.2 73.2 100% SCAN T 43 45 4 7A 21.9 162.1 162.1 100% SCAN T* 44 45 4 7.4 38.1 282.1 282.1 100% SCAN 'G* SER NO. 97-004 NITACIIMENT 2 B01.021.002 1RPV4-469 PAGE 29 0F 68

e ra9e z 46 45 4 7.4 88 65.6 65.6 100% SCANY 46 46 4 0.0 303.0 0.0 2246.1 0% NOT USED 47 60 1 7.4 88 65.6 66.5 100% SCAN *A* 48 60 1 7.4 7.2 63.2 63.2 100% SCAN T* 49 60 1 7.4 8.8 65.6 66.6 100% SCAN 'C' 60 60 1 7.4 18.9 1398 139.8 100% SCAN v 61 60 1 7.4 0.9 73.2 73.2 100% SCAN T 62 60 1 7.4 21.9 162.1 162.1 100% SCAN P 63 60 1 7.4 38.1 282.1 282.1 100% SCAN v 64 60 1 7.4 8.8 65.5 66.6 100% SCAN T 65 60 1 0.0 303.0 0.0 2245.1 0% NOT USED 66 60 2 7.4 8.8 66.6 65.6 100% SCAN *A* $7 60 2 7,4 7.2 63.2 63.2 100% SCAN T 68 60 2 7.4 8.8 65.6 65.5 100% SCAN'C' 73 60 2 7.4 18.9 139.8 139.8 100% SCAN 'D* 69 60 2 7.4 0.9 73.2 73.2 100% SCAN'E' 60 60 2 7.4 21.9 162.1 182.1 100% SCAN P 61 to 2 7.4 38.1 242.1 282.1 100% SCAN'G* 62 80 2 7.4 8.8 65.6 65.6 100% SCANY 63 60 2 0.0 303.0 0.0 2246.1 0% NOT USED 64 60 3 7.4 8.8 66.6 66.6 100% SCAN *A* 66 60 3 7.4 7.2 63.2 63.2 100% SCAN'D' 66 60 3 7.4 8.8 65.6 66.5 100% SCAN 'C' 87 60 3 7.4 18.9 139.8 139.8 100% SCAN 'D' 68 60 3 7.4 9.9 73.2 73.2 100% bCAN T 69 60 3 7.4 21.9 162.1 162.1 100% SCAN T* 70 60 3 7.4 38.1 282.1 282.1 100% SCAN'G* 71 60 3 7.4 8.8 65.6 65.6 100% SCAN Y 72 60 3 0.0 303.0 0.0 2246.1 0% NOT USED 73 60 4 7.4 8.8 65.6 65.6 100% SCAN *A* 74 60 4 7.4 7.2 63.2 63.2 100% SCAN T 75 60 4 7.4 8.8 65.6 66.6 100% SCAN'C' 76 to 4 7.4 18.9 139.8 139.8 100% SCAN 'D' 77 60 4 7.4 9.9 13.2 73.2 100% SCAN T 78 60 4 7.4 21.9 182.1 162.1 100% SCAN P 79 60 4 7.4 38.1 282.1 282.1 100% SCAN *G* 60 00 4 7.4 8.8 65.6 66.6 100% SCAN T 81 60 4 0.0 303.0 0.0 2246.1 0% NOT USED Totets 7109 8 22970 9 St% Agnevnt seee testal Exam. Area Lan9th volume volume An9 e Beam Examined Examined Examined Required Potoont 6 E*y9 Me9 ) 06**on (eq h) (h) (m h) (m h) Examined 1 0 Wa 29.9 8.8 263.0 263.9 100% SCAN *A* 2 0 We 29.9 7.2 214.3 214.3 100% SCAN T 3 0 Wa 29.9 8.8 263.9 263.9 100% SCAN 'C' 4 0 We 29.9 18.9 663.0 863.0 100% SCA'4 *D' 6 0 Wa 29 9 9.9 294.9 294.9 100% SCAN T 6 0 We 29.9 21.9 663.1 663.1 100% SCAN P 7 0 We 29.9 38.1 1136.4 1136.4 100% SCAN'G* 8 0 Wa 29.9 8.8 263.9 263.9 100% SCAN T 9 0 We 0.0 303.0 0.0 9044.0 0% NOT USED to 45 1&2 29.9 8.8 263.9 263.9 100% SCAN *A* 11 45 1&2 29.9 7.2 214.3 214.3 100% SCAN T 12 45 i&2 29 9 8.8 263.0 263.0 100% SCAN 'C' 13 45 1&2 29.9 18.9 663.0 663.0 100% SCAN 'D" 14 45 1&2 29 9 9.9 294.9 294.9 100% SCAN T 15 45 1&2 29.9 21.9 653.1 653.1 100 % SCAN P 16. 45 1&2 29.9 38.1 1136.4 1136 4 100% SCAN v 17 45 1&2 29.9 8.8 263.0 163.9 100% CAN T 18 45 1&2 0.0 303.0 0.0 9044.0 0% NOT USED 19 46 3 29.9 88 263.9 263.9 100% SCAN W 20 45 3 29.9 7.2 214.3 214.3 100 % SCAN'B' 21 45 3 29,9 8.8 263.9 263.9 100 % SCAN'C* 22 45 3 29.0 18.9 663.0 663.0 100% SCAN v 23 45 3 29.9 9.9 294.9 294.9 100% SCAN T SER NO. 97-004 24 45 3 29.9 21.9 653.1 653.1 100% SCAN 'F* 28 45 3 29.9 38.1 1136.4 1136.4 100% SCAN v ATTACHMENT 2 36 45 3 29.9 88 263.0 2e3.9 100% SCAN T B01.021.002 2r as 3 00 303 0 00 00u.0 0% NoT Usco IRPV4 469 PAGE 30 0F 68

Page 3 28 45 4 29.9 8.8 af3.9 263.9 100% SCAN *A' 29 46 4 29 9 7.2 214.3 214.3 100% SCAN *B* 30 45 4 29.9 8.8 263.0 263.9 100% SCAN 'C' 31 45 4 29 9 18.9 861 0 663.0 100% SCAN V 32 46 4 29 9 9.9 264.9 294 9 100% SCAN T 33 46 4 29 9 21.0 653.1 653.1 100% SCAN P $4 45 4 29 9 38.1 1136.4 1136.4 100% SCAN 7 3$ 45 4 29 9 8.8 263.9 263.9 100% SCANT 36 45 4 0.0 303.0 0.0 9044.0 0% NOT USED 37 60 1&2 29 0 8.8 263.9 263.9 100% SCAN *A' 38 60 1&2 29 9 7.2 214.3 214.3 100% BCAN T 39 60 1&2 29.9 8.8 203.9 263.9 100% SCAN *C* 40 60 1&2 29 9 18.9 663.0 663.0 100% SCAN'D' 41 60 1&2 29 9 9.9 294.0 294.9 100% SCAN T 42 60 1&2 29.9 21.9 663.1 663.1 100% SCAN T 43 60 1&2 29.9 38.1 1136.4 1136.4 100% SCAN 7 44 60 1&2 29.9 8.8 263.9 2639 100% SCAN T 45 60 1&2 0.0 303.0 0.0 9044.0 0% NOT USED 46 60 3 29.9 8.8 263.9 263.9 100% SCAN *A' e7 60 3 29.9 7.2 214.3 214.3 100% SCAN T 48 60 3 29.9 8.8 263.9 263.9 100 % SCAN 'C' 49 60 3 29.9 18.9 663.0 663.0 100% SCAN'D' 65 60 3 29 9 9.9 264.9 294.9 100% SCAN'C 60 60 3 29.9 21.9 653.1 653.1 100% SCAN P $1 60 3 29 9 38.1 1136.4 1136.4 100 % SCAN'G* 62 60 3 29.9 8.8 263.9 263.9 100% SCANY $3 60 3 0.0 303.0 0.0 9044.0 0% NOT USED 64 60 4 29.9 8.8 263.0 263.9 100% SCAN'A' 66 60 4 29.9 7.2 214.3 214.3 100% SCAN 'B' 66 60 4 29.9 8.8 263.9 263.0 100% SCAN 'C' 57 60 4 29.9 18.9 663.0 663.0 100% SCAN 'D' 66 60 4 29.9 9.9 294.9 294.9 100% SCAN T 69 63 4 29.9 21.9 653.1. 653.1 100% SCAN P 60 60 4 29.9 38.1 1136.4 1136.4 100% SCAN'O' 61 60 4 29.9 8.8 263.9 263.0 100% SCAN T 62 60 4 0.0 303.0 0.0 9044.0 0%. NOT USED 70tels: 26573 4 88881.1 29% Near Surtece Exem. Area Lan9th Volume Volume An96e Beam Examined Examined Examined Required Percent Entry # (dog.) Direciton (sq.h) (h) (m h) (cu.k) Examined 1 70 adel 6.9 84 60.6 60.0 100% SCAN *A' 2 70 axial 6.9 7.2 49.2 49.2 100% SCAN *B' 3 70 adel 6.9 8.8 60.6 60.6 100% SCAN 'C' 4 70 adel 6.0 18.0 129.2 129.2 100% SCAN'D' 6 70 adel 6.9 9.9 67.7 67.7 100% SCAN T 6 70 exlel 6.9 21.0 149.9 149.9 100% SCAN T 7 70 adel 6.9 38.1 260.8 260.8 100% SCAN 7 8 70 adel 6.9 6.8 60.6 60.6 100% SCAN Y 9 70 adct 0.0 303.0 0.0 2078.4 0% NOT USED 10 70 circ. 6.9 8.8 60.6 60.6 100% SCAN'A' 11 70 circ 6.9 7.2 49.2 49.2 100% SCAN T 12 70 onrc 6.9 8.8 60.6 60.6 100% SCAN'C' 13 70 circ. 6.9 18.9 129.2 129.2 100% SCAN 'D' 14 70 circ 6.9 9.9 67.7 67.7 100% SCAN T 15 70 circ 6.9 21.9 149.9 149.9 100% SCAN P 16 70 circ. 6.9 38.1 260.8 260.8 100 % SCAN'G* 17 70 circ. 6.9 8.8 60.6 60.6 100% SCANT 18 70 circ. 0.0 303.0 0.0 2076.4 0% NOT USED Totets-1676 7 6827.6 20% SER NO. 97 004 NITACHMENT 2 B01.021.002 1RPV4-469 PAGE 31 OF 68

I.- i 90 TABLE 1 Tl C s4 e eN Can CpNGES n 4@\\ 2 6 3 [,is - lj g EXIENSION ROTATION DEGREES DEGREES i g A SCAN

A*

7.86 9 .l5.34 I O W 58' I80 Sc^N s-s2.86 e s8.94 E SCAN "C" 74'.66 .0-82.14 I @f SCAN "D" 140.05 0 164.0 \\ A@. SCAM

E-879.73 9

108.09 I g SCAN

F" 203.81

'M 2 5 k . 222.33 SCAN *G" 238.05 e 27C.27 Ae / ~ SCAN i-344.66 8-3s2.i4 l E*R 270 s *$i;;j n e

ggda ~la 59 s.

w e

.'r ~ u I .?0'0*)- - 3.10 - TYP 10.00 2.00 ~ TYP k 'g TYP 60*S 70*L O' L 45'S -CH-5 CH-6 CH-7 CH-8 TRANSOUCER HEAD CONFIGURATTON (AXIAL SCANS) th 9~ ON SCAN SURFACE VIEWED FROM BACK OF HEAD M* AXIS 4 SET AT 180' 5% a ~

n ~ 3.10 - .TYP 10.00 i 2.00 TYP 4

2. 0 0

~ ~ ~ .T Y P 60*S 70*L O' L 45'S 9 CH-5 CH-6 CH-7 CH-8 TRANSDUCER HEAD CONFIGURATION j$ j iCIRC. SCANS) yIEng ON SCAN SURFACE VIEWED FROM BACK OF HEAD J IlI 3 AXIS 4' SET AT 180' a y ~

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/ t 8 p "%l ,1g f.u u j.- -C.4 4 s e N \\ +j - m~< x x 's ~ e' tg ~- J~ N s. #'$ +r SER NO. 97 004 ATTACHMENT 2 B01.021.002 1RPV4-469 PAGE 35 OF 68

e-su >1 =c. .l:,: :.:,:,:,:,: ~ y ~ I I, . cn nn i nn o g - a uo a c If L E 18 'e :R I = t r a t e u r e s 4'L g i i : : w ! ; i i i i-i i i, 8- ! ! E E i 0 i B 8! cl l -_s = n. j ) jj i i t t i ' l i i 53E@y l e gjhWg h I t p$h=

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p..

j / i., +: }i .i ,7 e ,/ o q =4 ( N <::.. j-l;, 1 ni,Il',i,;i e/e +_ eljj aj I -= li i } - 113! Il i .E n.: J.i:isi-3.1; i N.... is ::;.!!!.iial s t) sis'tIi!;I!j,l' i: s ti i }!. .+ -1 1);. il }}!1:l1li ,,i I SER NO. 97-004 ATTACHMENT 2 D m B01.021.002 1RPV4-469 PAGE 36 OF 68 -- o I o e

EXAMINATION COVERAGE FOR WELD: 7 442 PUUeOS TO UPPER SNEL CNtC WELD AGORSOATE OOVEMAGE OSTANeep: - 82% - SCAN PLMi DRAWB00 NO 1127 = Eene GoverSee obtaines Wow nw Agenese sees usw m% Near tipi Swiecen nw 4 4 j Art a " 7 Vetene Odetamen .W. . 1s.48 et h WeW 7344.078 et h QJord usee Melet 188Se et h Agesent Sees ustaf fee 0s.16 en h p Near Swims 12.31 og h Near Seteos ee n ise en h _ i }' .:: :m: r:.: Exam. Aree Longe volwne Voiwne Angie Seem Emenened Emamhed Emantwd Requhod Percent Envye leeg ) okochon eq h) k) ton N (ca N Esemhed 1 0 We 13.s 408 e s473 3 - 5473.3 - 100 % S.0. & AT NEWMYS 2 0 We 0.0 131 A 0.0 17700 0% AT SPECSEN CUTOUTS 4 s de 1 12.7 N0e 4316.3 esas 0 N% BETWEEN OS8TRUCTIONS 4 4s 2 13.s see 4ses 0 4ses.0 100 % sETWEEN OS8TRUCTIONS l 6 46 1 7.0 Es e18.7 005.4 Se% AT NEWmV8 i e 46 2 J2.e ne 7es.7 ees.4 se% ATsawvmVS 7 as 1 ee 1814 0.0 tr70.e e% AT SPECedEN CUT 4UTS a 4s 2 e.1 131.s 17.4 177e.e t% AT ePECeEN CUT 4UTS e 4s 3 1s.s Me.8 47os.8 470s.e 1e0% aETWEEN OS$TRUCTIONS to 46 4 18.5 846.e 470s.e 47es.8 100 % SETWEEN OS8TRUCTIONS 11 46 3 ISA 02.s 844.2 M6.2 100 % AT MEWMYS 12 48 4 13.8 82.8 N6J 846.2 100 % AT NEWMYS 13 46 3 e.0 1Es 0.0 1000.3 0% AT SPECeEN CUT OUTS 14 45 4 0.0 1ES 8.0 1400.3 0% AT SPECNEN CUT OUTS 18 40 1 e.1 340A 3072.4 4500.0 40 % BETWEEN OBSTRUCTIONS to e0 2 ' 13.5 H0.e 4ees.0 does.O 1e0% SETWEEN OSSTRUCTIONS 17 80 1 3.3 KS 214.0 806.4 M% AT NEWAYS it 90 2 12.7 Ke e8e.7 ee8.4 es% ATIE W AYS 1e 80 1 0.0 181A e.0 1770.0 0% AT SPECSEN CUT OUTS 30 to 2 8.7 tatA 7K5 17M.8 42% AT SPECNEN CUT OUTS 21 80 3 13.5 $48.e 4780 0 4700A 100%* GETWEENOS$TRUCTIONS 32 40 4 13.8 See 470s.6 4700.e 100 % BE1WE8N OS$TRUCT10NS 23 40 3 13.5 e2.0 0462 846 2 100 % AT NEYW4YS i N 00 4 18.5 82.0 e48.2 M6J 100 % MNEWMYS as to 3 0.0 1R8 0.0 - 1800.3 9% AT SPECNEN CUT OUTS 38 to 4 0.0 the e.0 1000.8 0% AT SPECSEN CUT OUTS Telehr MSfS F 47187.2 73 % Agasent Wees Metsi Emen Ama Lanem Vetene Valmne Ansee Beem Emmened Enemhed Submined Regidsed Pereent Easy 8 (dee) onomion mN k) seu N tonN Emneied 1 0 We tso.1 40s.e esses.e ebene 100% B.O. & AT NEWMYS 2 4-We 82.0 181.8 eestA 17118.8 41% ATSPE0mmN OUT OUTS 3 de 1&2 1M1 Set 8 44330.1 44330.1 100 % SETWEEN 00STRUCT10NS 4 46 1&2 11s.2 ES 7772A e000,7 St% AT NEWAYS S 46 1&2 R3 181A Seer.3 17118J ' 33 % AT SP80REN CUT OUTS e de 3 180.1.. 540A 40004.8 40e04.0. 100% SETWEEN OS$TRUCTIONS T 48 4-180.1 N0.0 40e04.0 40e04A 100 % BETWEEN 00STRUCT10N8 8 48 3 int 82.8 0107.7 8107.7 100% AT HEWAYS - 2 e 46-4 180.1 82.8 8107.7 4147.7 100 % AT NEW.'AYS to' 46 '3 us tase 0848.2 19838.4 41% AT SPECREN CUT OUTS 11 de 4-Ke 1ES 0843.2 18888.4 41% AT SPECREN CUT OUTS 12 - 00 - 142 122.3 H0.e 41400.e 44338.1 N% SETWEEN OSSI1tUCTIONS 13 80 16*.2 112.7 Se a 7411.4 80K7 87 % ATMEWMYS < 14 - 90 ^ 1&2 K4 131.s 7423.0 17118.3-48 % AT SPECNEN CUT OUTS 16 80 3 130,1 340.e 4e404.8 45004 s 1e0% BETWEEN OS8TRUCTIONS to to 4 130.1 See.e 4ssedA 406:14.0 100 % BETWEEN OBSTRUCTIONS 17 to ' 3 180L1 e2.0 0107.7 4147.7 100% AT NEWAYS is to 4 130.1 . He sie7.7 8107.7 100 % ATMEWMYS is 00 Re. 1Me 8043.2 18885.4 41% AT 8PECSEN CUT OUTS 30 00 _4* e2.0 tus es43J 1 eses.4 41% ATSMosENCUTOUTS ^ 14esh' nesteld 300MT.0 N% 4 New. _- Enem Emne.d seammed scenene Regned P sant Ame Langet Valene Vetene Aasm seem cawy e teos - onesean ces N k) een N ' tem N emnted -1 m adN 12.3 - 40s. sees.7 - sees.7 ie0% SETWEEN OSSTRUCTIONS SER NO. 97-004 2= n edel 8.e 40s.8 300s.e eso8.7 72%. ATNEWAYS 3-n .eN s.0 one time 00es.7 M% Ar aPECeEN CUTours ATTACHMENT 2 4 n :== - 4.0g.ie47.e. gee 2 12.3 es m a eess2 se0% stat & AT MaWmVS de% AT SPECeENCUT4UTS B01*030.002 ^n -' et un-w ar.2 menv n% 1RPV7 442 PAGE 37 OF 68 4 k 'l-- , -,,,,,, ~ m e-- ~ .w.-.- -r , - - -.- a.,, - ,a .,,-a-. --.m.aw

AXIAL .(4) KEYWAYS e lI = 44 ~ LENGTH 65.78" = (8) SPECIMEN TUBE CUTOUTS e Ii" SS" LENGTH 13I.56" = IL A.. g {. % __fi p% & y i i. i e i I +

!gPN g E3; oQ< o9 a

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. CIRC (4) KEYWAYS e i O.5 = 42 LENGTH = 62.79" ~ (8). SPECIMEN TUBE CUTOUTS e 10.5" 84" = LENGTH 125.58 = Em f;1f','k)y' f 7 t'ffl{'l q w 1 9p. ?1,ey@s l i Bg f,.G ea e e o o -um a.; U 10.5 ~- c4 M$r4x

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p-a w h 7 l } sentie Ja ti ci a f

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Y ZZ WO WH 3 f~ F-- O LLl'~) OE l-00 o 00 LO O SER NO. 97 004 ATTACHMENT 2 + B01.030.002 1RPV7 442-PAGE 41 OF 68

n i E ~ Q_.f............. j = 1. cut e... es 8 70' NEAR l ~ SURFACE- - - Ji BETWEEN ~- OBSTRUCTIONS l_ _ _ y _ O Oe >e w e o o e go g 9 9 .e.m, 9 e

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T i j 1 u- _ n --.g.-.

a

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Fe x x x L '=

LJ LJ = _J O 1 a. (.D y <t 3 LLJ x Q O 4 4 SER NO. 97-004 ATTACHMENT 2 B01.030.002 1RPV7-442 PAGE 44 OF 68 -

e Y = - T r.,,, y I 3

- I-i t

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i~ t,,. R-- - < - xy l i, TV [- = ,m ~t I i i i ,n p ~ Ltj M G O O (.O. SER NO. 97-004 ATTACHMENT 2 B01.030.002 1RPV7-442 PAGE 45 OF 68 4 1

l l t 5 l ..n.,.,..., L--; I - ; - $. I i r, 1I l gi 1 r Ei n i 11. I e- .. *\\ ll '\\... : ' i= t. ll..'1 y ...yhe. 3 ~ 2.1 9 8 e a i i g <C e =- LtJ M G O O b SER NO. 97-004 i ATTACHMENT 2 B01.030M2 1RPV7-442 PAGE 46 OF 68

1 - i er r i I ......u.,.,--- I-- ; I s s I N 1. l i i . i' !) l I - l "t. Ej il l. l, : '. e_ ,I l l 4 l , js *,p%.L-g g v m ,.l t s i t t W w ~ ~ E 3 i LL) M Q o O SER NO. 97-004 ATTACHMENT 2 B01.030.002 1RPV7-442 l PA'CE 47 OF 68

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== t '..rf i-l il I Y U; LJ e LJ 8, 2 f 3r t I t t t t ? tt t t a 3 1 a. e i li - -l 3 s s Ii -l-2 5 5-SER NO. 97-004 Ii! ATTACHMENT 2 lh!..___t-l - B01.030.002 i!' s 1RPV7 442 M PAGE 52 OF 68 o I' u o i

EXAMINATION COVERAGE FOR INLET NOZZLES 5-445A,B,C,&D INNER RADIUS 5-445AR,BR,CR,& DR SCAN PLAN DRAWING NO.:1213931D-02 AGGREGATE COVERAGE OSTAINED FOR WELD SS% I. AGGREGATE COVERAGE OBTAINED FOR INSIDE RADIUS: 58 % N C.__QiC T _I Wew and A4easet Bees Most e3% Near(ID)Swancet se% beide Radhm: Se% 1 W'IAL MkIKJN EVALAIMssun . VtMI~^'. MGIguN tvan **^ srun

EdYTfC A -

e _exr' _ rein *M7" -.m Arne - Wehmes Celesiegen 3 wene 14.19 og ht Wued seasA mLhL Wow 19Se og h Wald Aree - n - _._ Volumo " l A4mong base Ideemi 161.3 og ht AgosesdGenehieht 14442.1 eL bL aegnes,d Bees Metal 101.34 og DL A4 scent Some Meemt 142383 or k 1792.1 cat h 1 weer siren.m 11A4og h NearSwdnes 130t8 es.tt Near Swfece 15.4; og A Near Swance 1300.4 at kt imenee Ptoewe 5 T2 ht instes Aseus 247.1 en k insido modue 7 43 se. k heMeRedhe 3210 eaa k a ~ Musedand? 7. _ Base ""-^-' =^-o m_v s Emot Asse Depress Vuhase Vatsee ^ Emant Asse Degrees vnhone voeume Angle Seen Eammenad sh Esassened Requbed Poses,* Ecory a toes ) Omosses (se h) (he } (ema, h ) @at k) Bustead Erery S fdog ) Direcean tog h) (m ) (cas h ) (cw h) Enemhed Angie Senna Esemmed Esemined Emerreriod Requbed Persent 1 OM5 mese 17tA 1018 9391.3 9448.0 99 % i 1 445 ticre 201.0 180 0 17998.4 17998.4 100 % 2 OMS bere 0.0 74 2 0.0 8834J 0% 3 esto shears 179 5 105A 944sA SeesA 100 % 2 4540 shear 3 201.0 180 0 17998 4 179984 100 % 4 4540 sheer 3 EO 74 2 E0 SE34J 0% 5 4S40 shmeis 179 5 1M4 94es.O 9448.0 100 % 3 4540 sheEM 201 0 180 0 17998 4 17998 4 100 % s 4S40 shs44 EO 74.2 ELO 9024J 0% 4 7 0 anse 179 5 105.8 94460 944SA 100 % 4 0 she8 201.0 180.0 17998.4 17998 4 100 % 3 0 shes 0.0 74.2 RO 90341 0% reente 3rF3RJ 573EEf 8896 Isser - ",,,,, Taeore-Ff993.8 71981 8 18896 Near bM-Emmen. Asee Degreen Vahame Vemoso Emera. Asse Degreen Volume Volume Aesis same Emmsened Emesoned Eaemmed Regised Pommet Argbo Beem Esemhed Exemrud Ezemhed Required Percent Ens, e

Weg ) Omecaen (se in1 Ort )

(ma. en) (ma hi Enemhed [ 1 70 anser3.4 s4A 105 a 75& 2 756J 100 % tre.riruN1e AR) 1 70 sheat3.4

4 180.0 1380.6 1380 S 100% (PERPENCIC2 ant)

Ernry 8 (dog ) Direcean fee bj (W ) (cna. h ) (cua h ) Eamenhed 2 70 shear 3.4 00 74 2 aA 53eE 0% (PERPENDICUt.AR) j 3 45 tore 13.5 105 3 71R5 738.2 93% (PARAt.LEL) 2 45 bare 15.4 180 0 13808 13808 100 % (PARAufL) 4 45 tore 0.0 742 RO E3SA 0% (PARALLEL) reemar $drar 3eer.s Fr% leside Rague recole.- 2re u 2reu fes% l EmruL Arms Oeyees Muhase Vihose loside P" Emer'L Aree Degreen Volume Volume Argie seem easmied Esemmed Esmeemd negemed Poment Acelo Beem Ezemmed Enemrod Esemhed Regi*ed Percera Emmy e (dag ) Obecess (og ti) (m ) (ent be) fem h) Eemsened Emery 9 (dag i Dkecean (eg h) fin ) (cna h) (cas b) Emanteed I 1 70 auss 42 1018 107.1 145J 74 % 1 70 ames 54 1s0.0 232.0 321A 72 % 2 70 esimi RO 74.2 RO 1013 0% i 3 70 con 3.8 10E8 SEs 1412 83% 2 70 care 4.4 130 0 188J 321A 59% 4 70 sec e0 742 RO 101.9 0% remar =, 3u ass re ar 43a2 seu.es nom me,.e,en.e en o,,e,s.o.e e ierd is om e,ed e ns iw==s: 4s.e.n eme n w.w aw. New th. w secenn am-see, emord is coned-ed =:m 1w ansc 4s.eca.=m a r arw 1w. SER NO.97-004 ATTACHMENT 2 ~ B03.090.001,1A; B03.090.002,2A B03.100.UI,.002,.003,.004 B03.090.003,3A; B03.090.004,4A 1RPV5-445AR,445BR,445CR,445DR PAGE 53 OF 68 1RPV5-445A,445B,445C,445D

O 1 l l EXAMINATION COVERAGE FOR INLET TO SAFE END WELD: 1 SCAN PLAN DRAWING NO.: 1213931D.02 j AGGREGATE COVERAGE OBTAINED: 100 % Zone Coverage Obtained Weld & Adjacent Base Metal: 100 % Near(10) Surface: 100 % i!OiFli!EE E 1.L':.1.. 1~. _11~.11 Area Measurement Volume Calculation Weld & Adjacent Base Metal 1.9 sq. in. Weld & Adjacent Base Metal: 164.141 cu. in. Near Surface 1.9 sq. in. Near Surface 164.141 cu in. ~ ESTW3ETM _ b 20W10!EBC1 111.__i.1_i 11... Exam. Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry # (deg.) Direction (sq. in.) (in.) (cu. in.) (cu. in.) Examined 1 0 n/a 1.9 86.4 164.1 164.1 100 % 2 45 1&2 1.9 86.4 164.1 164.1 100 % 3 45 3 1.0 86.4 164.1 164.1 100 % 4 45 4 1.9 86.4 164.1 164.1 100 % Totals: 656.6 656.6 100% Near Surface Exam. Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent j Entry # (dog.) Direction (sq. in.) (in.) (cu. in.) (cu. in.) Examined 1 70 axial 1.9 86.4 164.1 164.1 100 % 2 70 cire 1.9 86.4 164.1 164.1 100 % Totals' 328.3 328.3 100% 2 J SER NO. 97-004 ATI'ACHMENT 2 B03.090.001,1A; B03.090.002,2A B03.090.003,3A; B03.090.004,4A 1RPV5-445A,445B,445C,445D B03.100.001,.002,.003,.004 1RPV5-445AR,44 SBR,445CR,445DR PAGE 54 OF 68

EXAMINATION COVERAGE FOR INLET SAFE END TO PIPE WELD: SCAN PLAN DRAWING NO.: 1213931D.02 AGGREGATE COVERAGE OBTAINED: 100 % Zone Coverage obtained Wold & Adjacent Base Metal: 100 % Near(ID) Surface: 100 % g w p niin m HKnE7hlii'rEnW1sfinHIh'n we d Length au 39 in. Area Measurement Volume Calculation Weld & Adjacent Base Metal 1.73 sq. in. Wold & Adjacent Base Metal: 149.4547 cu. In. Near Surface 1.73 sq. in. Near Surface 149.4547 cu in. 8WMmanllnAMDOS9X#JQagemalculA4oDET We d & Ad, acent Base Metal Exam. Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry # (dog.) Direction (sq. in.) (in.) (cu. In.) (cu. in.) ExarrJned 1 0 n/a 1.7 86 4 149.5 149.5 100 % 2 45 1&2 1.7 86.4 149.5 149.5 100 % 3 45 3 1.7 86.4 149.5 149.5 100 % 4 45 4 1.7 86.4 149.5 149.5 100 % Totals: 697.8 597.8 100 % Near Surface Exam. Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry # (deg.) Direction (sq. in.) (in.) (cu. in.) (cu. in.) Examined 1 70 axial 1,7 86.4 149.5 149.5 100 % 2 70 cite 1.7 86.4 149.5 149.5 100 % Totals: 298.9 298.9 100% i SER NO. 97-004 ATI'ACHMENT 2 B03.090.001,1 A; B03.090.002,2A B03.090.003,3A; B03.090.004,4A 1RPV5-445A,445B,445C,445D B03.100.001,.002,.003,.004 1RPV5-445AR,445BR,445CR,445DR PAGE 55 OF 68

i-t l l, \\. I I -m j . e-

- ~

.c ~ ~ ~ ' i .;,gy 1-t t l t a t 1 I 4 4 E /\\ n . ~ ~ _ - [NLET CIRC COVERAGt. FROM VESSEL I D-i [ ~* teLET var b 4 ,, 9% s 1 sua so.nm4 -] v Q xrrACHMWr2 i Y _.s 3 303.090.001,1A; BM M = i' -f.- ,,,ter orzte assiauc'38"5 Bo3.e90.003,3A; B03.090.004,4A : 1RFV5 445A,4458,445C,445D ~ Bos. lee.est, A M.008 - O 1RFV5 45AR,453R,445CR,445DR i praw u ou**. s .~, y- -_y--, .s,_ m i l'.' I

\\1 i 1 _1 t ] l' . J, ~ ~ TI RN OL ME / T \\ N 0A Zx Zt / LA \\ EL e 1 C O DV . E R A P1B133AS G AR0Rt0 E GP3F33TE ..TR EV1V60 50 599 A N 5 0 f 0.0 C O. O M' 1 7 0 00H t 0 S 00 9 64,0,A,3,1 M 7-F 31 E 0 .0 4AAN0 8 4 O,.20,B B B 2-5;; T4 n0 0 33 E,3 W a m M.pa.0 M,_,,0 2 _y y y

~~ .t.

3 1 _ _..

\\_ _ m.__ g...)....

.... y*

I s ,. s.u ~ n, v. t- /\\ n INLET INNER RADIUS AXIAL COVERAGE f.,, , '.p, ~~ .. ~. g, - - y,- - _, SER NO. 97-004 ATTACHMENT 2 {;.w I. B03.090.001, IA; B03.090.002,2A ] B03.090.003,3A; B03.090.004,4A I.T T - 1RPV5-445A,445B,445C,445D B03.100.001,.002,.003,.004 1RPV5-445AR,445BR,445CR,445DR.' 4 PAGE58 OF68

~~ l - - x L,. 1,*,. -;l...a ) ~. 9f ~, s. /\\ n INLET NEAR SURfACC C~--,---- - ;-~~.' AND INNEA RADIUS CIRC COVERAGE r, , ---'j'a \\.' SER NO. 97-004 P'.-- - - 1 ATTACHMENT 2 C,7 q B03.090.001, IA; B03.090.002,2A-

- 7 L_ __,_

1 B03.090.003,3A; B03.090,004AA - 1RPV5-445A,445B,445C,445D g-_ ~_f. B03.100.001,'.002,.003,.004 1RPV5-445AR,445BR,/.15CR,445DR PAGE59 OF68 O,. T 1

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e EXAMINATION COVERAGE FOR OUTLET NO771 ES 5-445E,F,G,&H INNER RADIUS 5-445ER, FR, GR & HR l l SCAN PLAN ENtAVWor.300.* 12tm N ) AGGREGATE COVERAGE OSTANED FOR WWELD: 43% ? AGMTE COWERAGE OSTABED FOR WWWE RA{ MAS: 74% [ coweteorenons someesesu u Zoste8% _- Obtaisted was ow Astmours amme namist 41% 1ener(Eg Swament ses hmmes menset 74 % l t r e _---- ,m. a.m.mm ewium uva f Wa**Tr*357=wM, 61egy"'eeW=*F::rf-r Te** ""*.FM sum,mani,m-u. sAnnum.

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+ emies aimaner ss et w see canmaar 25 as ,r-Q, r,**?"gr*Jrye*** seus iaummer ss a u usein.samer as et name 18.1e og to immed tSt3A en.tt med the og DL 9Mrts 183B 4 en km. 1 haqueue same temass 17137 og DL Agummse Some names 149erftam WL Adgmeme Somehammes 1983F et bL Agmuse Omme tumes 19eEE.4 eut OL humr SwEmme SE12 at ti. 90ser Surtame 12MA et tt Maar Swtame MSG og at enmar Sumemme te0E1 en et huse8ts8mm SSe se he sumido 8tmens 31e 0 es h >meo Restas Sge og te. smade Ames 300e es > l-u-4 mA 1 as e umans aus Asqmment game sumen _ me.e #... Iw w,- - % se _ [ ]- Esmut Area Dmymme vehene veheme & _esa -h ummad and Angummut emme manus i [ t Emes Asem Depume Vetene Wehene Asques samm Emmnemme Emement Enummed fangend Penmut ]' ErewS tems) rt==.m== tme h) (m) ten h) too m) Esensued E.ery a seus } Deenman tus m) en) tue m) tem > ) Emmmend Aceno amam Enemme Emmunes Emmumme Roomed Pomme j 1 08e5 hee 1943 10s.1 setsis 6s2eL7 sg% 1 was ese 2164 1sta 175:2.0 ungas 1ess i 2 t>es two 0A 73 3 0.0 emeL7 WE 6 3 defes ensWS

40 6 105 1 24333 9308 7 2e%

2 900 shm00 77J 198D Se745 17503 8 37 % + 4 ages snes3 OD 73 s em esos 7 0% ( S Ames snuse es 1os 1 24333 stes 7 2e% 3 4e0 unmes FTA 1ste e474 5 17503 s 37 % I e sees sheet 00 73 3 00 0808 7 0% 7 0 anus as6 tott 24335 82str Jeg 4 0 same 77A 1eES 94743 17501 3 P'% { s O somme SA 73 3 00 Sees.7 0% i roman-fasess sesse2 ap% I lamar -- L Ter er-asses s 7essae arm s pesar : J_ i Emen Aree Dw vatsme vienne Emmut Asse Dupeme veemme vetene Anges amam Emmusur Emmseems Emmmenos maqubed Desemat Erey# feeg) Ogemme seg m) P) (at h) (em M) Esamesed Erey e Ampe Sears Ensumed Emeseed Esemand Augumed Paese 1 70 asemam,4 53

0s s 111.4 742.1 42% c cre troscul.Af%

1 _ feeg) Omemann faq m} p) tut h) qua W) Eimmemme m unm63,4 72 tems Justi 1488.1 43%,. _,,,. -. a aug i 2 10 naus3.4 04 73 s em star 0% PEursescuudg 3 45 too 12.1 tett 9e57 747 1 som PARAuEU 2 4 two 16 e teRO 140E1 ?40E1 100 % FA48ufu 4 as to. 0A 73 s a0 Estr 0% PARAuEU Taman-ser.f Joses does mesen utmeme Tee-h-assas auf23 h4 huutos utmene Esmet Asse Deposo Vetens Vamme I Erwn. e Depues W%eme Wuhase Asges amen Emenmed h Ensumed Roomed Poemme 1 . Every9 (dag ) Obseman (og m) P9-fat h) tem 6 ) Essiend Erary e fees) Omecean tog >1 m) fem h) (em W) Esemmed Anste Dese Emmanov Esemmes Enemme Roomme poemse I l 1 m amas 53 .8s.1 153.s 1s73 s2% 1 70 eum et7 tee 0 Jets 3082 sus 2 70 mamp EO 73A OD 1303 0% 3 1.73 19 esc SE 105.1 156 0 18 83% 2 70 .c 11 10E0 231.4 309 8 75 % = .c co r3. O, 4 { y r.e,w mu au m rw ans e,oa .s. i .0m= =o m.e.mm.m.-,s.s.ex .m e..te 1w.= er es..so.w d ur. ,emoes m.ema -.m es.md.e.,mim d..e 1.eme.re .r.ed 1.r. i p SER NO.M-004 ATTACHMENT 2 B03.100.005,'.006,.007,.008 B03.090.005,5A; B03.090.006,6A 1RFV5-445ER,445FR,445GR,445HR B03.090.007,7A; B03.090.000,8A FAGE61OF65 e, esse..,..

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. - - - _ - _ - - - ~ _. EXAMINATION COVERAGE FOR OUTLET NOZZLE TO SAFE END WELD: SCAN PLAN DRAWING NL.:12139300 02 AGGREGATE COVERAGE OBTAINED: 100% Zone Coverage Ot,tained Weld & Adjacent Base Metal: 100 % Near(10) Surface: 100 % wec tengn: e. % in. Area Measurement Volume Calculation Weld & Adjacent Base Metal 1.94 sq. in. Weld & Adjacent Base Metal: 176.7534 cu. in. Near Surface 1.94 sq. In. Near Surface 176.7534 cu. In. Weld & Adjacent Base Metal Exam. Area Length Volume Volut s Angle Beam Examined Examined Examined Requli Percent Entry # (deg.) Direction (sq. in.) (in.) (cu. in.) (cu. In.) Examined 1 0 n/a 1.94 91.11 176.8 176.8 100 % 2 45 1&2 1.94 91.11 176.8 176.8 100 % 3 45 3 1.94 91.11 176.8 176.8 100 % 4 45 4 1.04 91.11 176.8 176.8 100 % Totals: 707.0 707.0 100% Near Surfa:e Exam. Area Length Volume Volume Angle Ocam Examined Examined Examined Required Percent Entry # (deg.) Direction (sq. In.) (in.) (cu. in.) (cu In.) Examined 1 70 axial 1.94 91.11 176.8 176.0 100 % 2 70 cire 1.94 91.1T 176.8 176.8 100 % Totals: 353.5 353.5 100% SER NO. 97-004 l ATI'ACIIMENT 2 l '90.005, SA; B03.090.006,6A u.. l B03.090.007,7A; B03.090.008,8A 1RPV5-445E,445F,445G,445H B03.100.005,.006,.007,.008 l 1RPV5 445ER,44SFR,445GR,44511R PAGE 62 0F 68 s .,w,-

EXAMINATION COVERAGE FOR OUTLET SAFE END TO PIPE WELD: SCAN PLAN DRAWING NO.: 1213930042 AGGREGATE COVERAGE OBTAINED: 100 % Zone Coverage Obtained ~ Wold & Adjacent Base Metal: 100 % Near (ID) Surface: 100 % Area Messunment Volume Calculation Wold & Adjacent Basoanal 1.94 sq. in. Weld & Adjacent Base Metal: 176.7534 cu. In. Near Surface 1.94 sq. In. Near Surface 176.7534 cu. in. Weld & Adjacent Base Metal '~' Exam. Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry # (deg.) Directbn (sq. In.) (in.) (cu. In.) (cu. In.) Examined 1 0 n/a 1.9 91.11 176.8 176.8 100% 2 45 1L 1.9 91.11 176.8 176.8 100 % 3 45 3 1.9 91.11 176.8 176.8 100 % 4 45 4 1.9 91.11 176.8 176.8 100 % Totals: 707.0 707.0 100% Exam. Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry # (deg.) Direction (sq. in.) (in.) (cu In.) (cu. In.) Examined 1 70 axla! 1.9 91.11 176.8 176.8 100 % 2 70 ciro 1.9 91.11 176.8 176.8 100 % Totab: 353.5 353.5 100% SER NO. 97-004 A'ITAClIMENT 2 B03.090.005, SA; B03.090.006,6A B03.090.007,7A; B03.090.008,8A 1RPV5-445E,445F,445G,44511 B03.100.005,.006,.007,.008 1RPV5-445ER,445FR,445GR,44511R - PAGE 63 OF 68 i

+ t 7.- i _1 1 E ( ~~ ' ' ' ~ ... ~ /r> w N,f,-Aw i t 4 1 ] i j 4' t ~. ~ ' - g ~ / ', ii, OUTLET AXIAL COVERAGE N 4 FROM N0ZZLE I.D. ) 1 r 1 SER NO.97404 ATTACHMENT 2 B03.090.005, SA; B03.090.006,6A : 3 B63.090.097,7A; B03.090.006,8A 1RPVS-445E,445F,445G,445H i E03.100.005,.006,.007,.008 1RPV5 445ER,445FR,445GR,445HR PAGE 64 OF 68 '

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OUTLET INNER RADIUS 8 AXIAL COVERAGE ..*,\\ i e ~ CUTLET NEAR SURFACE f AXIAL COVERAGE _j I SER NO. 97-004 l ATTACHMENT 2 .'. T.? y B03.090.005,5A; B03.090.006,6A' ..T " B03.090.007,7A; B03.090.008,RA IRPV5 445E,445F,445G,445H B03.100.005,.006,.0M,.008 1RPV5-445ER,445FR,445GR,445HR PAGE 65 OF 68

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B03.090.005,5A; B03.090.006,6A ,...". "j 7 B03.090.007,7A; B03.39a ama,nr 1RPV5-445E,415F,445G,445H B03.100.005,.006,.007,.006 ' 1RPV5-445ER,445FR,445GR,445HR I PAGE E OF M

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a b ASME Class ! NDE Inservice inspection Request for Rehef Serial No. 974104 For McGuire Unit i Ilased on ASME XI 1980 Code hrough Winter 1980 Addenda September 9,1997

Subject:

Duke Power Company McGuire Unit 1. Fir 6 Inservice inspection Interval flistory of Limited Ultrasonic Examination of Reactor Vessel Welds Dusng the first Inservice inspection ( 151 ) interval at McGuire and Catawba, and the second ISI interval at Oconce, welds that had 90% and less Ultrasonic (UT) coverage were not identified on a Request for Relief to the NRC. Welds that had limited UT coveruge were indicated on ISI reports as limited, but the actual percentages of coverage obtained were not provided, ne practice of documenting the UT coverage as litnited, but not documenting the actual percentage of coverage obtained, was based on an interpretation of a note in ASME Code Section XI Tables IWil-2500 and IWC 2500, which requires volumetric inspection of" essentially 100% of weld length. When only a limited inspection was possible, Duke Power (DPC) interpreted this note to mean that a best effort must be made to cover as much of the weld as possible with the techniques and technology available at the time. If coverage was less than 10Wk, the inspection was reported as limited. %e percentage of coverage obtained was not recorded in ISI Reports prior to January 1993 ASME Code Case N-460 was published on July 27,19814 and approved by the NRC in Revision 8 to Regulatory Guioe 1.147 in November 1990. This Code Case defines the statement " Includes essentially 100% of weld length" as obtaining at least 90% examination coverage of the weld. Based on Code Case N-460, coverage of 90% and less is a deviation from the Code and requires a Request for Relief. Generic Request for Rehef 93 GO-001 which requested relief for all welds identified as limited for Oconce, McGuire and Catawba was submitted to the NRC on December 2,1993 and it was subsequently denied. (Reference NRC letter dated October 26,1994 to M.S. Tuckman). On January 11,1995 a conference call was held between the NRC ara DPC representatives for the purpose of discussing Request for Relief 93 004101 and to clarify differences of interpretation pertaining to limited welds as defined by Code Case N-460. Ilased on discussion with NRC staff representatives during the January ll,1995 conference call, the NRC felt this hsue could be best handled through the NRC Enforcement / Inspection program pending concurrence by appropriate NRC management. On February 8,1995 the acceptability of the proposed . approach was confirmed to J. d. Warren. Duke Power by V Nerses, ONRR during a phone conference. (Reference February 28,1995 Duke letter M. S. Tuckman to S. D. Ebneter, Regional Administrator, Region 11). During the week of March 20,1995, Mr. N. Economos, USNRC Region 11 Inspector, made a site visit to McGuire. (Reference McGuire Inspection Report No. 95-09). During this visit, a meeting was held with Mr. Economos and DPC representatives, where it was agreed that Duke Power would provide a listing of limited welds examined during the first ISI interval for McGuire and Cataw ba and the second ISI interval for Oconee. De limited weld information for M Guire, Catawba and Oconee was sent to Mr. Economos on March 30,1995. PageIof2 a

3 a J -I 1 ASME Class i NDE Inservica inspection Request for helief Serial No. 97-(XM For McGuire Unit i Based on ASME XI 1980 Code Through Winter 1980 Addenda September 9,1997 included in the March 30,1995 submittal were the McGuire Unit I reactor vessel welds. During the NRC review of the reactor vessel welds. it was determined that additionalinformation was necessary for the technicaljustification. A meeting was held on April 6,1995 between B&W Nuclear Technologies (BWNT) and DPC, and at this time DPC requested additional information in order to address the limited welds on the reactor vessel. In response to this request, BWNT completed their Reactor Vessel Limited Examination Evaluation Reports for McGuire, Catawba and Oconee in late August,1995. On September 5, 1995. DPC notified BWNT that corrections were necessary to their reports. On January 12,1996 Framatome Technologies,(formerly BWNT), provided additional information in response to DPC's concerns of September 5,1995 relating to the Reactor Vessel Examination Evaluation Reports. During Mr. Economos' visit to McGuire on January 16.1996, a meeting was held to discuss the evaluation status of the limited examination welds on the Reactor Wssel for Unit 1. It was determined at that time that the reports provided to DPC by BWNT did not contain sufficient information to describe the percentage of coverage of the limited examinations. DPC contracted Framatome Technologies to provide the percentage of coverage for all welds determined to have limited coverage for Unit 1. This report was received by DPC on May 30,1996 On January 9,1997 a meeting was held with Mr.Economos to review the results of the Reactor Vessel welds, the conclusion reached during this meuing was that this issue could now be closed with the issuance of this request for relief. Gary Underwood QA Technical Services Section Station Support Division Nuclear General Office Page 2 of 2 .}}

ML20198S365

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