ML20112H496

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Forwards Relief Request 96-003 for NRC Review & Approval. Request Seeks Relief from 1980 Section XI of ASME Boiler & Pressure Vessel Code Through Winter 1980 Addenda as Modified by Code Case N-460
ML20112H496
Person / Time
Site: Mcguire
Issue date: 06/06/1996
From: Mcmeekin T
DUKE POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9606180225
Download: ML20112H496 (41)
v • d • e


Text

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- Duke PbtverCompany T.CArctfrms

. McGuire Nuclear Generation Department Vice President 12700flagers TerryRoad(MG0lW) (704)8754800 .

Iluntersville.NC280l&S985 (704)8754809 fax  :

DUtXPOWER' June 6,.1996 j i

Document-Control Desk i U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Subject McGuire Nuclear Station, Unit 2 Docket No 50-370 Relief Request,96-003

Dear Sir:

i Pursuant to 10 CFR50.55a (a) (3) (ii), I am submitting the attached relief request for NRC review and approval. This request seeks relief from the 1980 Section XI of the ASME Boiler and Pressure Vessel Code through winter 1980 addenda as modified by Code Case N-460.  :

Complete coverage of the subject welds was not obtained during Unit 2 end-of-cycle 8 refueling outage due to obstructions, interference by other components or geometric  ;

conditions. These welds have been examined to the maximum i extent possible within the limits of original design and construction. An acceptable level of quality and safety has been achieved. Public health and safety will not be compromised by granting relief from the referenced code requirements. i Should there be any questions regarding this matter, please contact John M. Washam at (704) 875-4181.

Very truly yours, I

d &  !

T.C. McMeekin 9606180225 960606 . A

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'p PDR ADOCK 05000370  ;

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e U.S. Nuclear Regulatory Commission June 6, 1996 page 2 xc: Mr. S.D. Ebneter Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta St., NW, Suite 2900 Atlanta, Ga. 30323 Mr. Victor Nerses U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D.C. 20555 Mr. George Maxwell Senior NRC Resident Inspector, McGuire McGuire Nuclear Station

e Serial No.96-003 Page 1 of 3 J l

Duke Power Company Station McGuire. Unit 2 FIRST 10-YEAR INTERVAL REQUEST FOR RELIEF NO 964XB .

I. System / Components (s) for Which Relief is Reaueste11.;

Reactor Vessel Weld Numbers hem Numbers Description 2RPV-WO3 1101.011.003 Lower Shell to Lower Head 2RPV WO6 B01.011.004 Upper Shell to Nozzle Belt 2RPV-WOI B01.021.002 Lower llead to Bottom llead 2RPV-WO2-0! B01.022.001 Lower licad 210 Deg.

2RPV-WO2-02 B01.022.002 Lower Head 150 Deg.

2RPV-WO2-03 B01.022.003 Lower Head 90 Deg.

, 2RPV-WO2-04 1101.022.004 Lower llead 30 Deg.

2RPV-WO2-05 B01.022.005 Lower IIcad 330 Deg.

j 2RPV-WO2-06 1101.022.006 Lower lies.J 2 O Deg.

2RPV-WI1 B03.090.001 Inlet Noz. to Shell 67 Deg.

2RPV-Wli B03.090.001 A Inlet Noz. to Shell 67 Deg.

j 2RPV-W12 B03.090.002 Inlet Noz. to Shell 113 Deg.

2RPV-W12 B03.090.002A Inlet Noz. to Shell i13 Deg.

2RPV-W13 B03.090.003 Inlet Noz. to Shell 247 Deg.

t 2RPV-W13 B03.090.003A Inlet Noz. to Shell 247 Deg.

2RPV-W14 B03.090.0(M Inlet Noz. to Shell 293 Deg.

2RPV-W14 B03.090.(XMA Inlet Noz. to Shell 293 Deg.

2RPV-W15 B03.090.005 Outlet Noz. to Shell 22 Deg.

. 2RPV-W15 B03.090.005A Outlet Noz. to Shell 22 Deg.

2RPV-W16 1103.090.006 Outlet Noz to Shell 158 Deg.

2RPV W16 B03.090.006A Outlet Noz. to Shell 158 Deg.

.I 2RPV-Wl7 B03.090.007 Outlet Noz. to Shell 202 Deg.

2RPV-W17 B03.090.007A Outlet Noz. to Shell 202 Deg.

2RPV-Wl8 B03.090.008 Outlet Noz. to Shell 338 Deg.

2RPV-W18 B03.090.008A Outlet Noz. to Shell 338 Deg.

1 2RPV-Wl1 B03.100.001 Inlet Noz. to Shell 67 Deg.

j 2RPV-W12 B03.100.002 Inlet Noz. to Shell 113 Deg.

2RPV-W13 B03.100.003 Inlet Noz. to Shell 247 Deg.

2RPV-W14 B03.100.004 Inlet Noz. to Shell 293 Deg.

2RPV-W15 B03.100.005 Outlet Noz. to Shell 22 Deg.

l 2RPV W16 B03.100.006 Outlet Noz. to Shell 158 Deg.

2RPV-W17 B03.100.007 Outlet Noz. to Shell 202 Deg.

2RPV-W18 B03.100.008 Outlet Noz. to Shell 338 Deg.

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Serial No.96-003 Page 2 of 3

11. Gdt.Renuirement:

Examination Category B-A, Pressua Retaining Welds in Reactor Vessel, Table IWB-2500-1, Figure Nos. IWB-2500-1 and IWB-2500-3; Note 2:" Includes essentially 100% of the weld length."

Examination Category B-D, Full Penetration Welds of Nozzles in Vessels. Inspection Program B, i Figure No. IWB-2500-7.

III. Code Requirement from which Reliefis Requested:

Reliefis requested from the requirement of examining essentially 100% of the weld length. Due to part geometry and actual physical barriers, obtaining at least 90% of the weld length as outlined in Code Case N-460 is not possible.

ASME Section V, Article 4,T441.4.1 Scanning Requirements,1980 Edition through winter 1980 Addenda as modified by Code Case N-460.

This Paragraph 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. De adjacent base metal in the examination volume must be completely scanned by both angle beams, but neeJ not be completely scanned by both angle beams from both directions (any combination of two angle beams will satisfy the requirement).

When scanning for reflectors transverse to the weld, the angle beam search units shall be aimed parallel to the axis of longitudinal and circumferential welds. He 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 volume coverage if it can be shown that at least 90% of the required volume has been examined.

IV. Basis for Relief:

During the ultrasonic examination of the welds shown in Attachment I for Refueling Outage 8, the minimum 90% coverage requirement of ASME Section XI,1980 Edition through Winter 1980 Addenda, clarified by Code Case N-460, could not be obtained due in part to geometry and to actual physical barriers. A combination of multiple angles and UT techniques 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.

4 Serial No.96-003 Page 3 of 3 V. Alternate Examination or Testine:

The use of radiography as an alternate volumetric examination is not practical due to component thickness and geometric configurations. Other restrictions making radiography impractical are the use of double wall techniques and physical barriers prohibiting access for placement of source, film, number bands, etc. As a result of the irnpractical use of radiography Duke Power Company will continue to use the most corrent ultrasonic techniques available for future examinations of the item Numbers shown in Attachment 1.

VI. Justification for the Grantine of Relicf:

Duke Power Company 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 weki/ component integrity. Thus, an acceptable level of quality and safety will have been achieved and public health and safety will not be endangered by allowing relief from the aforementioned Code requirements.

VII. Implementation Schedule; These examinations will continue to be scheduled in accordance with the requirements of ASME Section XI for future inspection intevals at McGuire Nuclear Station Unit 2, utilit.ing the examination techniques in use by Duke Power Company at that tirne.

Anaghments:

1. Detailed listing of welds with limited ultrasonic coverage.
2. Drawings of affected weld details including calculation methods.
3. Ilistory of limited ultrasonic examinations of reactor vessel welds.

Evaluated By: Y Ond4JWC Date 5i H5l%

Reviewed By: 4 (di Date E.b5/9h

ASME Class i NDE Inservice Inspection Retluest For Relief Serial No. 9M)03 Attachment I For McGuire Unit 2 Based On ASME XI - 1980 Code Through Winter :980 Addenda Page 1 of 3 Item No Exam Category / System or Function Area To Be Reason For Request WeM ID No bcensee Proposed Figure No. Componem Examined Alternate Exammarion B01.011.003 B-A Reactor Vessel Houm the fuct assembhes, cetrol Lower Shen to Umited scan due to geertnc 2RPV-WO3 None IWB-2500-1 mds and unclinianals, is bwer Head m6gumon directs the Nw of rextor coolant Weld Actual coverage obtamed = 43 60%

B01.011.004 B-A Reactor Vessel Hmses the fuel suembin, cmtml Upper Shell to Unuted scan due to geonetnc 2RPV-WO6

& and venciintemis, aim None IWB-2500-1 Nozzle Belt con 6gwatim directs the flow of reactor coolam Weld Actual coverage obtained = 48.20%

B01.021.002 B-A Reactor Vessel Houses the fuel assembhes, contml 1 ower Head to Urruted scan due ta geometnc 2RPV-WOI None IWB-2500-3 mdt and venchntemals, aim B u rn Head em6gummon directs the now of reactor coolant Weld Actual coversee obtained = 53 40%

B01.022.001 B-A Reactor Vessel H=ses the fuel assembhes, control imwer Head Umited scan due to geometnc 2RPV-WO2-01 None 1WB-2500-3 "#' *"d ""*""'*"l5 "'" M*"d' mal weM c n6gumin ihrects the Onw of reactor coolant 210 Deg Actual coverage obtained = 86 6oi B01.022.002 B-A Reactor Vessel HN5c5 the fuct auembhes, mntrol Le*er Head Urnited scan due to geometnc 2RPV-WO2-02 None IWB-2500-3 ' d' 2"d *** 3 i"" *' 5 M*"d' n21 weld configuration directs the flow of rextor coolant 150 Der Actual coverage obiained = 83 00%

B01.022.003 B-A Reactor Vessel Hases the fuel assembles, control Lower Head Umited scan due to geometnc 2RPV-WO2-03 None IWB-2500-3 "#"d**"*""'**^l'*'" M*"d*"*3**M * "68 "*i "

directs the hw of reactor coolan 90 Deg Actual coverage obtained = 86 6M B01.022.004 B-A Reactor Vessel liouses the fuel assembbes, control tower Head Umited scan due to geometne 2RPV-WO24M None IWB-2500-3 "d' *"d **"*""'* " ^'* M*"d' n I wcid c n6 8umion.

directs the now of reactor coulant 30 Deg. Actual coversee obtamed = 76 40%

B01.022.005 B-A Reactor Vessel Houses the fuct assembhes,contml Lower Head Umited scan due to geometne 2RPV-WO2-05 None IWB-2500-3 ** "d "cl intem 15 Im Metidi nal Weld c nfiguration.

directs the Nw of reactor coolant 3110 Deg Acrual coverage obtained = 86 60'I B01.022.006 B-A Reactor Vessel Houses the ruel assembhes, control lower Head umined scan due io geometnc 2RPV-WO2-06 None IWB-2500-3 **- "d **"*""'"" 15 "I" M*'idi n I weu em6 gum >=.

directs the now of reactor coolant 270 Der Actual coverage obtained = 86 60%

B03.090.001 B-D Reactor Vessel Hases the fuel assembhes, control inlet Nozzle to Umited scan due to geometnc 2RPV-WII None IWB-2500-7 me. nd venchntemis, alm SheH 67 DegE con 6gumion.

directs the flow of reactor coolant from Vessel ID Actual coverage obtamed = 7210%

B03.090.001 A B-D Reactor Vessel Hases the fuel anembhes, consmi Inlet Nozzle to Unuted scan due to geometric 2RPV-WII None IWB4500-7 r A, nd veuct iniemals aiso Shetl 67 Deg. UT configuration.

directs the Nw of rextor coolant from Nozzle ID Actual coverage obtained = 7210%

B03.090.002 B-D Reactor Vessel Hases the fuel suembhes, control inlet Nozzle to Umited scan due to geometnc 2RPV-W12 Nonc mA,and venchntan is, alm Shen H3 Deg con 6gumion.

IWB-2500-7 directs the now of reactor coolant UT from Vessel Actual coverage obtained = 7210%

ID B03.090.002A B-D Reactor Vessel Hases the fuel assembhes, mntml Inlet Nozzle to Umited scan due to geometric 2RPV-W12 None IWB-2500-7 "# ""d ""*""'*"I' alm Shen H3 Deg. con 6gumion directs the Nw of reactor cuotant UT from Nozzle Actual coverage obtained = 72.10%

ID

ASME Class 1 NDE Inservice inspection Request Ibr Rr. lief Serial No.96-003 Attachment 1 For McGuire Unit 2 Based On ASME XI - 1980 Code Through Wir.ter 1980 Addenda Page 2 of 3 tiem No Exam Category / System or Function Area To Be Rea on l'or Request Weld ID No beenwe Proposed Figure No. Component Examined Atrernate Examinanor.

B03.090.003 B-D Reactor Vesse? Houses the fuel assembbes.commi inlet Nozzle to bnuted scan due to geometne 2RPV-WI 3 None IWB-2500-7 mds.and vewiimemak aim shen 247 Deg conguranon directs the flow of reactor coolant UT from Vessel Actual coverage obtamed = 72.10%

ID B03.090.003A B-D Reactor Vessel liouses ihe fuel assembbes, control intet Nozzle io bmned scan due io scometnc 2RPV-WI3 None IWB-2500-7 mas. and vessel intern k also shen 247 Deg. connguration directs the flow of rexte e coolant UT from Nozzle Actual coverage obt.uned = 72.10%

ID B03.090.0(M B-D Reactor Vessel liases the fuel assembbes, control Inlet Nozzle to bnuted scan due to geometnc 2RPV-W14 None IWB-2500-7 mds. and vessel internals. also shen 293 Deg. configuranon directs the flow of rextor coolant UT from Vessel Actual coverage obtamed = 7210%

ID B03.090.004A B-D Reactor Vessel Huses the fuel assembhes, control Inlet Nozzle to bmited scan due to geometric 2RPV-WI4 None IWB-2500-7 mas,and esselimem is,als shen 293 Deg. cm6guranon directs the flow of reactor ccolant UT from Nozzle Actual coverage obtained = 72.t0%

ID B03.090.005 B-D Reactor Vessel flouses the fuel assemblies, control Outlet Nozzle to bmued scan due to geometne 2RPV-W15 None mds, and vesschntemals, also shell 22 Deg. UT conGguranon IWB-2500-7 directs the flow of reactor c m ant from Vessel ID Actual coverage obtamed = 43.70%

B03.090.005A B-D Reactor Vessel Huses the fuel assembhes. contml Outlet Nozzle to Limited scan due to geometric 2RPV-W15 None IWB-2500-7 mds, and uneHntem 15.als shen 22 Deg. UT cmGguraum directs the flow of reactor coolant from Nozzle ID Actual coverare obtaiaed = 43 70%

B03.090.006 B-D Reactor Vessel finses the fuel assemNies. control Outlet Nozzle to Umned scan due to geometne 2RPV-W16 None IWB-2500-7 "d5 *"d '**5*' i"'em Is, als shen 158 Deg. configuranon directs the flow of reactor coolant UT from Vessel Actual coverage obtained = 43.70%

ID B03.090.006A B-D Re:ctor Vessel Huses the fuel assembhes, control Outlet Nozzle to bnuted scan due to geometric 2RPV-Wl6 None was, and vessehntemals, aJso shen 158 Deg connguranon IWB-2500-7 directs the flow of reactor coolant UT from Nozzle Actual coverage obtamed = 43.70%

ID B03.090.007 B-D Reactor Vessel Houses ihe fuel assembhes. controt Outlet Nozzle to bnuted scan due to geometnc 2RPV-W17 None IWB-2500-7 "d5 *"d **"*h"'em Is. also shen 202 Deg. conGrurawn directs the flow of reactor coolant UT from Vessel Actual coverage obtamed = 43.70%

ID B03.090.007A B-D Reactor Vessel linses the fuel embbes, cutml Outlet Nozzle to bmited scan due to geomeinc 2RPV-W17 None IWB-2500-7 "d' 2"d **"*""'*" I'. als shet 202 Deg. cmnguranon directs the flow of reactor coolant UT from Nozzle Actual coverage obramed = 43.70%

ID

! B03.090.008 B-D Reactor Vessel Houses the fuel assembhes, control Outlet Nozzle to bnused scan due to Feometnc 2RPV-WI8 None mds, and veneHntemais, also shen 338 Deg. em6guranon IWB-2500-7 directs the flw of reactor coolant UT from Vcssel Acual coverage obtamed = 43.70%

ID B03.0M008A B-D Reactor Vessel limses the fuel assembhes. entrol Octiet Nozzle to bmned can due to geometnc 2RPV-WI 8 None IWB-2500-7 nuts. and vessel intem 15. a % snen 338 Deg connguianon directs the flow of reactor wolant g UT fmm Nozzle Actual coverage ulnamed = 43 70%

l ID I

L_________ _____________ ____________ _ _ _ _______ ___________. -_

s ASME Claw I NDE Intervice Inspection Request For Relief Senal No.96-003 Attachment i For McGutre Unit 2 Based On ASME XI - 1980 Code Through Winter 1980 Addenda Page 3 of 3 -

Item No Exam Category / System Or Function Area To Be Reason For Reques Weld ID No Ucensee Proposed Figure No. Component Exarmned Altenute Examination B03.100.001 B-D Reactor Vessel liases the fuel assembhes, catml Inlet Nozzle to Umited scan due io geomeinc 2RPV-WI I None IWB-2500-7 "d' *"d '*"ci intemis alw Shen 67 Deg angumion.

directs the flow of reactor coolant inside Radius Actual coverage obtained = 64 60%

Section B03.100.002 B-D Reactor Vessel llouses the fuel assembhes, control inlet Nozzle to Unused scan due to geometnc 2RPV-W12 None IWB-2500-7 "d' *"d '*"cl imemis aim Sticu ll3 Deg. mngumen directs the flow of reactor coolant inside Radius Actual coverage obtatiwd = 64 601 Section B03.100.003 B-D Reactor Vessel flouses the fuel assembles, control Inlet Nozzle to Umsted scan due to geonrtnc 2RPV-W13 None r ds,and vesselinternals,als Shell 247 Deg. configuration.

IWB-2500-7 directs the flow of reactor coolant inside Radius Actual coverage obramed = 64 60%

Section B03.100.0(M B-D Reactor Vessel limses the fuel assembhes, cetrol inlet Nozzle to Unuted scan due to geometnc 2RPV-W14 None IWB-2500-7 tods nd venelintemis. alm SheU 293 Deg. m6guranon directs the flow of reactor coolant inside Radius Actual coverage obtained = 64 60%

Section B03.100.005 B-D Reactor Vessel liouses the fuel assembhes, control Outlet Nozzle to Umsted scan due to geonetnc 2RPV-W15 None rals, and vesse: intenuls, also Shell 22 Deg. con 6guration.

IWB-2500-7 directs the flow of reactor coolant inside Radius Actual coverage obtained = 87 70%

Section B03.100.006 B-D Reactor Vessel flouses the fuel assembhes, control Outlet Nozzle to Umited scan due to geometnc 2RPV-W16 None IWB-2500-7 "d' "d *** '"'emais, als SMH 158 Deg- engumion directs the flow of reactor coolant inside Radius Actual coverage obtained = 87.70+

Section B03.100.007 B-D Reactor Vessel liouses the fuel assembhes.contml Outlet Nozzle to Unured scan due to geomeinc 2RPV-W17 None IWB-2500-7 mds, nd venci intemls, alw Shen 202 Deg m6gumon directs the flow of reactor coolant inside Radius Actual coverage obtamed = 87 70%

Section B03.100.008 B-D Reactor Vessel flouses the fuel assembhes, control Outlet Nozzle to Umited scan due to geometnc 2RPV-W18 None IWB-2500-7 '* *"d **"el iniemis. als Shell 338 Deg. con 0guration directs the flow of reactor cuolant inside Radius Actual coverage obtained =87 7tM Section i

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LOWER SHELL TO LOWER HEAD WELD ITEN NO.: B01.011.003 I I.D. NO.: 2RPV-WO3 Total Exam Area = 53.32 in 2 (Near Surface + Weld + T/2)

Near Surface Area = 8.37 inz (Cross-Section)  !

Weld Area = 6.37 in 2 (Cross-Section) a T/2 Area = 38.58 in2 (Cross-Section)

BETWEEN LUGS CIRC 70*

Gets 6.24 in' of Near Surface Area (74.6 %)

O' Gets 9.07 in2 of Total Exam Area (17.0 %)

, 45' & 60' Get 31.79 in' of T/2 Area, .44 in' of Weld Area Total coverage = 31.79 + 0.44 + 0.44 = 63.7 %

38.58 + 6.37 + 6.37 AXIAL 70' Gets 8.24 in8 of Near Surface Area; however due to the Full-Node Exam, 100 % Coverage of the Near Surface Area is obtained by the 45' & 60*.

45' Gets 100 % of Weld and T/2 Area 60' Gets 100 % of Weld and T/2 Area BELOW LUGS AXIAL Due to the Full-Node Exam, 7.58 in2 of the Near Surface Area is obtained by the 60' (90.6 %).

45' Gets 3.79 in: of T/2 Area (0 % Weld Area)

Total Coverage = 3.79 + 0.00 + 0.00 = 7.4 %

38.58 + 6.37 + 6.37 60* Gets 9.11. in' of T/2 Area and 1.23 in of Weld Area Total Coverage = 9.11 + 1.23 + 0.00 =

20.1 % SER.90 9k 33 38.58 + 6.37 + 6.37 gg PN2E 4 OF 31

LOWER SHELL TO LOWER HEAD WELD CONTINUED There are six (6) segments between lugs, each 31.60* covered by the center of the head (O' and 60' Circ) . The outside transducers each cover an additional 2.06' which results in 35.72' covered by 7 0' , 60' & 45' Axial and 70' & 45' Circ. There are also six (6) segments below lugs, each covering the remaining 24.28' for Axial Scans. .

O' & 60' Circ Coverage = 189.60 x % Between 100 x 360 70' & 45' Circ Coverage = 214.32 x % Between 100 x 360 l Axial Coverage = 214m 32 x % Between + 145.68 x % Below 100 x 360 l

AXIAL CIRC NS 60 45 . 70 _69_ 45 0 96.2 67.7 62.5 44.4 33.5 37.9 9.0 Aggregate Coverage =

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+ 44.4 x 8.37 + (33.5 + 37.9) x (38.58 + 6.37 + 6.37)

+ 9.0 x 53.32 ]/

[ 8.37 x 2 + (38.58 + 6.37 + 6.37) x 4 + 53.32 )w -

43.6 %

SER, to %-003 Aggregate Coverage =

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"Z" = s45.36 *-- - -* -
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  • 4 "Z" = 149.10 -~~"~'""~P-i .

e "Z" e 152.28 ******'"****

.4

. N45.

'.* 70?

"Z" = 156.78

.'\ j 3

60*

"Z" = 159.00

, O 173.0 CLAD

.157 NOM 0.465 (T21 SER. NO._9/o-603 ATTACHMENT 2

! B01.011.004 NOTES' 2RPV-WO6

1. ALL "Z" DIMENSIONS REFERENCE THE DISTANCE DETWEEN PAGE THE MATING SUFFACE AND THE DOOM. THE CENTER OF 7 0F THE CONTACT HEAD IS OFFSET VERTICALLY FROM THE BOOM BY I4.94" USING THE 4-INCH OFFSET.
2. SPACING BETWEEN THE TRANSDUCERS IS 3.10" !N ALL DIRECTIONS.
3. HEASUREMENTS ARE IN INCHES AND DECIMAL DEGREES.

4 UT SCAN PATHS DESIGNATED BY. .. ... .., LINES.

S. ALL SCANS USE STANDARO HEAD EXCEPT FOR:

B6.1.2nA-4 & B-1 AND B6.2.2 A-2 & B-2 WHICH USE ALTERNATE HEAD.

E b' M *9b"OC3 AT MCh m G 2.

i l PEE 7 cF li

~ - i

l UPPER SHELL TO NOZZLE BELT WELD ITEM NO.: B01.011.004 l I.D. NO.: 2RPV-WO6 Total Exam Area = 93.65 in' (Near Surface + Weld + T/2)

Near Surface Area = 10.47 in8 (Cross-Section)

Weld Area = 11.38 in' (Cross-Section)

T/2 Area = 71.80 in 8 (Cross-Section)~

CIRC 70' Gets 3.82 in' of Near Surface Area (36.5 %)

O' Gets 6.08 in8 of Total Exam Area (6.5 %)

45' & 60* Get 28.50 in' of T/2 Area (0 % Weld)

Total Coverage = 28.50 + 0.00 + 0.00 = 30.1 %

71.80 + 11.38 + 11.38 j AXIAL 70' Gets 5.40 in' of Near Surface Area (51.6 %)

45' Gets 63.34 in of T/2 Area 8

4 5'-UP Gets 11.10 in2 of Weld Area 4 5'-DOWN Gets 4.74 in' of Weld Area Total Coverage = 63.34 + 11.10 + 4.74 = 83.7 %

71.80 + 11.38 + 11.38 60' Gets 67.39 in2 of T/2 Area 6 0*-UP Gets 9.87 in2 of Weld Area 6 0'-DOWN Gets 9.34 in8 of Weld Area Total Coverage = 67.39 + 9.87'+ 9 . 3_4, = 91.6 %

71.80 + 11.38 + 11.38 SER, t6c. 9 Goc 3

/iTkBh\ERT - 2.

PME E OF 3l

UPPER SHEIl TO NOZZLE BELT WELD CONTINUED 9

1 AXIAL CIRC 1

70 A 45 70 60 .45 0 1

i 51.6 91.6 83.7 36.5 30.1 30.1 6.5 4

Aggregate Coverage =

[ 51.6 x 10.47 +

a (91.6 + 83.7) x (71.80 + 11.38 + 11.38)

+ 36.5 x 10.47 +

(30.1 + 30.1) x (71.80 + 11.38 + 11.38)

+ 6.5 x 93.65 ]./

( 10.47 x 2 + (71.80 + 11.38 + 11.38) x 4 + 94.65 ]=

Aggregate Coverage = 48.2 %

J 1

SER. Rt %-66 ATTN.hmEwT-2 PEE 9 of 31

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SER. N0, % do3 i

90 ATTACHMENT 2 B01.021.002 2RPV-W01 NorES.

PAGE ll OF 3\

h gg TRANSOUCERS ($ 3.10" *N ALL 2, ME ASunEk(NTS AAE IN INCHES AND DECIMAL CEGFIEES.

3. yT SCAN PATHS DESIGNATED BY

. LINES.

4

  • t*_ !S EATENDED 7."*,

1 h

. 5.591 (T)

. ALPHA : 23.40

't .

t ALPHA : 25.41 -

377.18 RA01U5 : 88.194 .

TO FLANGE SURFACE (CLAD) ,'*. ".

.I57 .- 7 0 45,

= NDH .g t

. ALPHA 31.76 rn ALPHA : 33.77 . . ~ . . '" .

ALPHA : 34.64 .. .

s i ALPHA : 35.85 m N N

4 ALPHA : 36.65 m N ,

g VELD REFERENCE LINE .\ \/'

,' % 4

.. .' '5 's T/2

( ',  ?' N s

S i 4

.' s

. T/2 1

,r....-

SER. NO. % do.3 ATTACHMENT 2 B01.021.002 2RPV-WOI I

I N90VCERS 15 3.10* lN ALL O

PAGr" 12. OF _M

2. MOSUFEMENTS ARC IN [NCHES AM3 CECIMAL CEOREES.
3. uf SCAN PAfHS CESIGNATED BY L g gs .
o. *v* !S ExfEPCEO 7.!*.

~

1 i

. l l

. 1 I

l LOWER HEAD TO BOTTOM HEAD WELD ITEM NO.: B01.021.002 {

I.D. NO.: 2RPV-WO1 Total Exam Area = 41.68 in z (Near Surface + Weld + T/2)

Near' Surface Area = 7.27 in8 (Cross-Section)

Weld Area = 5.11 in' (Cross-Section)

T/2 Area = 29.30 in2 (Cross-Section)

CIRC 70' Getc 4.46 in2 of Near Surface Area (61.3 %)

O' Gets 7.73 in2 of Total Exam Area (18.5 %)

45' & 60' Get 16.02 in2 of T/2 Area (100 % Weld)

Total Coverage = 16.02 + 5.11 + 5.11 = 66.4 %

29.30 + 5.11 + 5.11 AXIAL 70'  !

Gets 6.20 in of Near Surface Area; however due to the Full Node Exam, 100 % of the Near Surface Area is obtained with the 45' & 60'.

45' Gets 100 % of Weld and T/2 Area 60' Gets 100 % of T/2 Area 6 0'-UP Gets 100 % of Weld Area 6 0'-DOWN Gets 4.77 int of Weld Area Total Coverage = 29.30 + 5.11 + 4.77 =

99.1 %

29.30 + 5.11 + 5.11 W R % 94-oo3 ARAthmEKi- 2.

\

pac ta cv at l

l l

. I h

LOWER HEAD TO BCYfrOM HEAD WELD CONTINUED The Lower Head To Bottom Head Weld is obstructed due to the Instrument Nozzles. Six (6) angular portions of the weld are scanned.

Segments are: 16.42', 13.44', 59.84', 76.46', 49.46' & 43.44' The outside transducers each cover an additional 2.01' which increases coverage by 4.02' for the 60* & 45' Axial and 70* & 4 5' Circ .

O' & 60' Circ Coverage = 259.06 x % Between 100 x 360 70' & 45' Circ Coverage = 279.16 x % Between 100 x 360 70' Axial Coverage = 259.06 x % Between 100 x 360 60' & 45' Axial Coverage = 279.16 x % Between 100 x 360 AXIAL CIRC NS . 60 . 45 70_ 60 45 0 72.0 76.8 77.6 47.5 47.8 51.5 13.3 Aggregate Coverage =

1

( 72.0 x 7.27 + (76.8 + 77.6) x (29.30 + 5.11 + 5.11) I l

+ 46.5 x 7.27 + (47.8 + 51.5) x (29.30 + 5.11 + 5.11)

+ 13.3 x 41.68 ]/ -

l l

[_7.27 x 2 + (29.30 + 5.11 + 5.11) x 4 + 41.68 ]=

Aggregate Coverage = 53.4 % M M ' % C03 AIll\ChhBG 2 FA6E \4 CF ll

Tj F ALPHA = 25.40 I

60 DEGREE i CIRC COVERAGE 70 DEGREE I 45 DEGREE AXIAL COVERAGE (ALL ANGLES) AXIAL COVERAGE AXIAL COVERAGE i ALPHA = H.s4 " *N '

ALPHA = 5&J5 m Ahby5 m ~

/

I mpn s=F c> Q e

" il T b' N 6 vs

. 270 i 082-06

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v.2.., OUARTER SCALE 90 SER. NO. '%-00 3 ATTACE1ENT 2 B01.022.001 2RPV t402-01 CTEsi B01.022.002 2RPV WO2-02

,iggy.;g -Eg, P'***5 ;3 3 8' : au.

B01.022.003 2RPV WO2-03

. .s.ucers .ee :, : c>o cre:wt :::mes.

..r., ::::o..rs e 801.022.004 2RPV t'02-04

. 3: . ..w s .

. o. - :s 3. recs r.

B01.022.005 2RPV-W02-05 801.022.006 2RPV-402-06 DAGE 16 0F M l

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9.04 68*

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. 78f 45' 4 5.96 ,'d ,

3.22 .43

., T/2

, 6  %

I VELO REFERENCE LINE

~~~q I.28 I 3.99 .. ' T/2 6 ..  ;

6.72 ~,' 7Y ~ ~ ,

7.88 9.88 .

( l.

.157 NOM RADIUS

  • 88.194 CLA0 .591 (T) j SEP.. NO.  % co3 ATTACH *1ENT 2 B01.022.001 2RPV-402-01 B01.022.002 2RPV 402-02 f;' inh.T 'E.L.""' ' '"3- m 'u-801.022.003 2RAV WO2-03 s.,g es ,, .n ri : o <s .,o :c::.ac : n ares.

3:.... ,c-, :::::ia rc . . .:.cs .

801.022.004 2RPV 02-04

. - i r. r.c c 2 . B01.022.005 2RPV-N02-05 801.022.006 29.PV-402-06 DArE l'1 0F 31

1 l

LOWER HEAD WELDS ,

ITEM NO.: B01.022.001 ITEM NO.: B01.022.003 I.D. NO.: 2RPV-WO2-01 I.D. NO.: 2RPV-WO2-03 ITEM.NO.: B01.022.005 ITEM NO.: B01.022.006 ,

I.D. NO.: 2RPV-WO2-05 I.D. NO.: 2RPV-WO2-06  !

l The Lower Head Welds listed above are obstructed and will recieve the  !

following coverage-Total Exam Area = 219.55 in2 (Near Surface + Weld + T/2)

(Alpha Cross-section)

Near Surface Area = 37.87 in2 (Alpha Cross-Section)

Weld & T/2 Area = 181.68 in' (Alpha Cross-Section) i i

The Weld Area occupies 1.30' out of 5.78' in the Circumferential or Theta Direction. Coverage for the l Weld & T/2 Areas is based on (1.30 + 5.78) / 5.78 I or 122.5 % Area.

CIRC 70' Gets 36.75 in' of Near Surface Area (97.0 %)

O' Gets 152.06 ins of Total Exam Area (69.3 %)

45' & 60' Get 175.03 in of Weld & T/2 Area (79.7 %)

2 AXIAL 70' Gets 37.80 ina of Near Surface Area; however due to the Full Node Exam, 100 % of the Near Surface Area is obtained with the 45' & 60'.

45' Gets 100 % of Weld and T/2 Area 60' Gets 100 % of Weld and T/2 Area '

SER94o. 96.cs ATTACRHENT- 2 PME 18 cF 31

LOWER HEAD WELDS CONTINUED CIRC AXIAL' NS __fD_ _di_ 70 60 45 0 97.0 79.7 79.7 100 100 100 69.3 Aggregate Coverage =

( 100 x 37.87 + ( 100 + 100) x (181.68 x 122.5 %)

+ 97.0 x 37.87 + (79.7 + 79.7) x (181.68 x 122.5 %)

+ 69.3 x 219.55 ] /

( 37.87 x 2 + (181.68 x 122.5 %) x 4 + 219.55 ] =

Aggregate Coverage = 86.6 %

i 1

1 l

1 l

l SER Mo %003 AT[AoimalT a P ME N cF 3)

k LOWER HEAD WELD ITEM NO.: B01.022.002 I.D. NO.: 2RPV-WO2-02 The Lower Head Wald listed above is partially obstructed due to the Instrument Nozzles.

One (1) of Two (2) CIRC Scans is Obstructed:

Total Coverage = 50 % x Unobstructed + 50 % x Obstructed 100 %

The AXIAL Scans are Obstructed for 2.03' of 10.74*:

Total Coverage =' 81.1 %'x Unobstructed + 18.9 % x Obstructed 100 %

The weld is covered in both directions (122.5 % Coverage).

CIRC _,

AXI17,

. NS. . 60 45 70 60 ii._ o 89.2 73.1 73.1 100 99.2 99.0 66.2 Aggregate Coverage =

[ 100 x 37.87 + (99.2 + 99.0) x (181.68 x 122.5 %)

+ 89.2 x 37.87 + (73.1 + 73.1) x (181.68 x 122.5 %)

+ 66.2 x 219.55 ] /

( 37.87 x 2 + (181.68 x 122.5 %) x 4 + 219.55 ]=

Aggregate Coverage = 83.0 %

3ER h %.g3 ATiAmmENT 2 PArJ 9 A 6c ]i

LOWER HEAD WEID ITEM NO.: B01.022.004 I.D. NO.: 2RPV-WO2-04 The Lower Head Weld listed above is obstructed due to the Instrument Nozzles. -

CIRC 70' Gets 30.79 in of Near Surface Area (81.3 %)

t O' Gets 116.17 in2 of Total Exam Area (52.9 %)

45' & 60' Get 145.71 in: of Weld & T/2 Area (66.4 %)

AXIAL 70' Gets 36.69 in' of Near Surface Area; however due to the Full Node Exam, 100 % of the Near Surface Area is obtained with the 45' & 6 0' .

i i

4 5'-UP Gets 180.96 in' of Weld & T/2 Area j 4 5'-DOWN Gets 167.81 in of Weld & T/2 Area t

Total Coverage = 180.96 + 167.81 = 96.0 %

' 181.68 + 181.68 l

6 0'-UP Gets 181.43 in8 of Weld & T/2 Area 6 0*-DOWN Gets 163.53 in: of Weld & T/2 Area 181.43 + 163.51 Total Coverage = = 94.9 %

181.68 + 181.68 i

CIRC AXIAL NS. 60 45 70 60 45 0 81.3 66.4 66.4 100 96.0 94.9 52.9 Aggregate Coverage =

[ 100 x 37.87 + (96.0 + 94.9) x (181.68 x 122.5 %)

+ 81.3 x 37.87 + (66.4 + 66.4) x (181.68 x 122.5 %)

+ 52.9 x 219.55 ]/

( 37.87 x 2 + (181.68 x 122.5 %) x 4 + 219.55 )=

S E L N O 9(a-CO3 Aggregate Coverage = 76.4 %

AWAQunEMI 2 PME 21 CF 31

J G

~

i CIRC COVEma0E 70 OE4REE (ALL ANGLES) 45 OEGREE 80 DEGREE AXIAL COVERA 8E ARIAL COYfRAGE AXIAL COVERaeE Matoe mWsEst ~

M nena e es.ee i

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atPsia e 20.04 RPsea e as.es .

m ,gg,gg RPsa e 34.84 * * *

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$N hu

SER, WO.

- ATTACHMENT 2 ,

803.090.001 B03.100.001 (2RPV-U11) 803.090.001A (2RPV-W11) ,

803.090.002 803.100.002 (2RPV-W12)

B03.090.002A (2RPV-W12)

B03.090.003 803.100.003 (2RPV-W13)

B03.090.003A (2RPV-W13)

B03.090.004 -

B03.100.004 (2RPV-W14) i B03.090.004A (2RPV-W14) -

1 . : 'e f f s ~5.Je* AOJACENT *: ; U r t. E T ".0 0 '-E 5 p g at 4

  • 42' 27*. 2:2* 1 3 4' 1

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HORIZONTAL SECTION vtEV car.4e

$9.13 13 7' A.e6E 1WAF ACE i

' I /ERTIC'.L IEC**0N /IEV

, ... . .,.7, e es.2s n es.sa

- . i.4e
  • 9' e 29,06 age e 57.64
      • s i9.64 -

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4 9gg ... , ;3,;3 Oy"R*

STANCE O!THSl(745 1N TW l'IEMIN TE VESSEL M3ZZLE CENTEM 1Pei SGIE' MO TW EM) RFE!4ME

!? '8 0 M -

  • 2 800M SUCH 44 R*

g, , , . .. .

2, *#* O!ENStG4B AL. CPG TW POZ2LE TAPE 70 VApr wITH t i . .' * -

      • $g *.!*..
  • a N IaN$NS?5*

E E M u~sTaeM """"" ' " ' ' '" ^"-

k 4 NEASLFDENT1 ARE IN [NCKS MC CECIMA4 OEOREES.

5. UT SCAN PATHi DES!0NATED BY . .1. ! PES .

- _ _ _ _ . _ _. _ _ __ _ _ -_ . __ ._._ _ _ __ _ . _ = - _ . _ .

l

\

, l INLET NOZZLE TO SHELL WELDS l ITEM NO.: B03.090.001/A ITEM NO.: B03.090.002/A l I.D. NO.: 2RPV-W11 I.D. NO.: 2RPV-W12  !

ITEM NO.: B03.090.003/A . ITEM NO.: BO3.090.004/A I.D. NO.: 2RPV-W13 l I.D. NO.: 2RPV-W14 l

CIRC 70' Gets 12.81 in' Coverage Lower Vertical Section 70' Gets 13.70 in2 Coverage Upper Vertical Section 70* Gets 10.72 in' Coverage Horizontal Section Covered Area =

( 12.81 + 13.70 + 10.72 + 10.71 ) x .25 13.87 13.87 13.62 13.62

= 87.1 %

CIRC O' Gets 196.95 in2 Coverage Lower Vertical Section O' Gets 206.58 in: Coverage Upper Vertical Section O' Gets 98.40 in8 Coverage Horizontal Section Covered Area =

( 196.95 + 206.58 + 98.40 + 98.40 ) x . 25 209.57 209.57 164.09 164.09

= 78.1 %

i CIRC 4 5' & 60' Get 100 % Weld Coverage Vertical Section 167.93 in: T/2 Coverage Upper Vertical Section 4 5' & 60' Get i 45' Gets 153.64 in T/2 Coverage Lower Vertical Section 2 i 60' Gets 167.93 in2 T/2 Coverage Lower Vertical Section i 45' & 60' Get 11.74 in2 Weld Coverage Horizontal Section

45' & 60* Get 75.95 in' T/2 Coverage Horizontal Section Adjacent to Neighboring Inlet Nozzle
45' Gets 75.93 in2 T/2 Coverage Horizontal Section j Adjacent to Neighboring Outlet Nozzle 60' Gets 75.95 in' T/2 Coverage Horizontal Section Adjacent to Neighboring outlet Nozzle SE% % %-co)

' AMGmtnT-z PAGE 24oF 3i

e .

INLET NOZZLE TO SHELL WELDS CONTINUED 4

45' Covered Area =

[ ( 167.93 + 24.95 + 24.95 )

170.75 + 24.95 + 24.95

+( 153.64 + 24.95 + 24.95 )

170.75 + 24.95 + 24.95

+( 75.95 + 11.74 + 11.74 )

137.05 + 13.42 + 13.42

, +( 75.93 + 11.74 + 11.74 ) ]X .25 137.05 + 13.42 + 13.42 4 = 78.1 %

l 60' Covered Area =

[ ( 167.93 + 24.95 + 24.95 )

170.75 + 24.95 + 24.95

+( 167.93 + 24.95 + 24.95 )

170.75 + 24.95 + 24.95

+( 75.95 + 11.74 + 11.74 )

137.05 + 13.42 + 13.42

+( 75.95 + 11.74 + 11.74 ) ] x .25 137.05 + 13.42 + 13.42

= 79.7 %

AXIAL 45' Gets 11.61 in' Coverage Vertical Section Near Surf ace 45' Gets 2.78 in' Coverage Horizontal Section Near Surface 4

Covered Area =

( 11.61 + 2.78 ) x .50 = 52.1 %

13.87 13.62 AXIAL O' Gets 128.63 in' Coverage Vertical Section O' Gets 31.15 in' Coverage Horizontal Section Covered Area =

( 128.63 + 31.15 ) x .50 = 43.2 %

195.70 150.47

. AXIAL 45' Gets 158.01 in' Coverage Vertical Section 45' Gets 117.92 in2 Coverage Horizontal Section Covered Area =

( 158.01 + 117.92 ) x .50 = 79.6 %

195.70 150.47 SER R6. %co3 ATMGMENT-2 PAGE 2s cF 31

a INLET NOZZLE TO SHELL WELDS CONTINUED AXIAL CIRC NS 0 45 70 60 45 0 52.1 43.2 79.6 87.1 79.7 78.1 78.1 l

. Aggregate Coverage =

[ 52.1 x (13.87 + 13.62) + (43.2 + 79.6) x (195.70 + 150.47)

+ 87.1 x (13.87 + 13.62) + (79.7 + 78.1) x (170.75 + 24.95 + 24.95 + 137.05 + 13.42 + 13.42)
1 l

+ 78.1 x (209.57 + 164.09) ]/

[ (13.87 + 13.62) x 2 + (195.70 + 150.47) x2

+ (170.75 + 24.95 + 24.95 + 137.05 + 13.42 + 13.42) x 2

+ (209.57 + 164.09) ]

Aggregate Coverdge = 72.1 %

a 4

A l

SR lb #&cc3 ATCAtumWT-2.

PA6E 74 rc Ti

INLET NOZZLE TO SHELL WELDS & INLET NOZZLE INSIDE RADIUS t

Total Area = 209.57 in (Near Surface + Weld + T/2)

Near Surface Area = 13.87 in2 (Vertical. Cross-Section)

Weld Area = 24.95 in2 (Vertical Cross-Section) 1 T/2 Area = 170.75 in' (Vertical Cross-Section)

Inside Radius Area = 9.21 in' (Vertical Cross-Section)

Total Area = 164.09 in' (Near Surface + Weld + T/2) 2 Near Surface Area = 13.62 in (Horizontal Cross-Section)

Weld Area = 13.42 inz (Horizontal Cross-Section)

T/2 Area = 137.05 in2 (Horizontal Cross-Section)

Inside Radius Area = 5.56 in2 (Horizontal Cross-Section)

INLET NOZZLE INSIDE RADIUS

ITEM NO.: B03.100.001 ITEM NO.: B03.100.002 I.D. NO.: 2RPV-W11 I.D. NO.: 2RPV-W12 ITEM NO.: B03.100.003 ITEM NO.: BO3.100.004 I.D. NO.: 2RPV-W13 I.D. NO.: 2RPV-W14 I

CIRC 70* Gets 4.11 in: Coverage Vertical Section 70' Gets 3.10 in: Coverage Horizontal Section Covered Area =

( 4.11 + 3.10 ) x .50 = 50.2 %

9.21 5.56

. AXIAL 70' Gets 6.24 in' Coverage Vertical Section

70' Gets 5.01 in' Coverage Horizontal Section Covered Area =

( 6.24 + 5.01 ) x .50 = 78.9 %

9.21 5.56 70' TNSIDE RADIUS COVERAGE AXIAL CIRC -

j

'78.9 50.2 l

Aggregate Coverage = 64.6 % SR M % ec3 l ATNhb\bG - 2, l PatE 27 cp 31

SER. NO.

-ATTACHMENT 2 B03.090.005 B03.090.005A (2RPV-W15) B03.100.005 (2RPV-W15)

B03.090.006 B03.090.006A (2RPV-W16) 803.100.006 (2RPVH16) 1 803.090.007 I B03.090.007A (2RPV-W17) B03.100.007 (2RPV-W17)

B03.090.008 803.090.008A (2RPV-M18) -

__ 803.100.008 (2RPV.W18) l l

\

0 LIMIT = 24.3s' SETWEEN OUTLET NO2ZLES (AT 0 s 100* 4 368*I l 10.027.

7},

2.OG* .;, .- ~ ~ ~ ~~ ~ ~ ~

24.44* /

l\

T/2 IRT/3 ,

ze.44-r _____u______L__t

' ~ ~

~ ~

1 1 1 I I I I I I l i

n i23.e6 WELO ( l l

i HORIZONTAL SECT'!ON VIEW I

e7.~S e TO FLANGE SURFACE I VERTICAL SECTION '/ I E W I

n . is.ie n = s2.no ' n . se n = i s . e. , n zz.as n . .e.se I n . 27.se n . : .se n = 3.is ,  !

l f p.e57 None l f g .,% n g .-

to' ,,.;y G, . '

T/2 l

l n f/2 X g e- .,. , d __.,, i I

l/ I.*'6' 4

/

(73.666 *2

  • 427.le --

/

f SR h Mc3 ATihGMKT- 2 ve.se s : , .3..z. -[ri, PME. 28 cp 3l NOTES:

157 NOM

, , .R* O!MENSIONS (N T4 N0ZZLE OGIE FEFEFDCE M (67.668 i e33.2e l- _ _ _ _ _ _ _ _ _ _ . -.

OtSTAG eETWEN TW VESSEL CENTER 1E Ato THE E.A

  1. '[

c Ao 164.561 *:* s i36.3e . .

j' ,,

edbC*'IMI Nee'4M-!" " "

2. (

g gTj 'W TRAN50 LEERS 15 3. ig* IN ALL

3. MASUREMENTS ARE IN {NC)($ Arc CECIMAL CEGREES.

. . U T SCAN R.m,- .T . 4,45.

1

OUTLET NOZZLE TO SHELL WELDS ITEM NO.: B03.090.005/A ITEM NO.: B03.090.006/A I.D. NO.: 2RPV-W15 I.D. NO.: 2RPV-W16 ITEM No.: B03.090.007/A ITEM NO.: B03.090.008/A I.D. NO.: 2RPV-W17 I.D. NO.: 2RPV-W18 CIRC 70* Gets 6.17 in' Coverage Vertical Section 70* Gets 6.36 in* Coverage Horizontal Section Covered Area =

( 6.17 + 6.36 ) x .50 = 41.5 15.07 15.10 i'

O' Gets 33.28 in' Coverage Vertical Section 0' Gets 16.47 in: Coverage Horizontal Section Covered Area =

( 33.28 + 16.47 ) x .50 = 12.6 %

201.28 189.01 45' & 60* Get 3.75 in' Weld Coverage Vertical Section 45' & 60* Get 56.95 in' T/2 Coverage Vertical Section 4

4 5' & 60* Get 0.00 ina Weld Coverage Horizontal Section

, 45' & 60* Get 44.92 in' T/2 Coverage Horizontal Section 45* & 60* Covered Area =

[ ( 56.95 + 3.75 + 3.75 )

182.44 + 18.84 + 18.84

+( 44.92 + 0.00 + 0.00 ) ] x .50 175.93 + 13.08 + 13.08

= 25.8 %

i SEE h %cca ATMQ\MT-2.

PME 29 0F .3l

, , - ~ - -

OUTLET NOZZLE TO SHELL WELDS CONTINUED AXIAL 45' Gets 12.77 in' Coverage Vertical Section of Near Surface 45' Gets 9.96 in' Coverage Horizontal Section of Near Surface Covered Area = ( 12.77 + 9.96 ) x .50 = 75.3 %

' 15.07 15.10 O' Gets 180.77 in' Coverage Vertical Section O' Gets 124.50 in* ' Coverage Horizontal Section Covered Area = ( _1_80.77 + 124.50 ) x .50 = 77.8 %

201.28 189.01 45' Gets 154.56 in' Coverage Vertical Section 45' Gets 155.82 in* Coverage Horizontal Section Covered Area =

( 154.56 + 155.82 ) x .50 = 79.6 %

201.28 189.01 AXIAL CIRC NS 0 45 70 60 45 0 75.3 77.8 79.6 41.5 25.8 25.8 12.6 Aggregate Coverage =

[ 75.3 x (15.07 + 15.10) + (77.8 + 79.6) x (201.28 + 189.01)

+ 41.5 x (15.07 + 15.10) + (25.8 + 25.8) x (182.44 + 18.84 + 18.84 + 175.93 + 13.08 + 13.08)

+ 12.6 x (216.35 + 204.11) )/

[ (15.07 + 15.10) x2+ (201.28 + 189.01) x2

+ (182.44 + 18.84'+ 18.84 + 175.93 + 13.08 + 13.08) x2

+ (216.35 + 204.11) )

Aggregate Coverage = 43.7 %

SER % %co3 ATihowTen t PAGE 36 cr 31

c .

4 OUTLET NOZZLE TO SHELL WELDS & OUTLET NOZZLE INSIDE RADIUS Total Area = 216.35 in' (Near Surface + Weld + T/2)

Near Surface Area = 15.07 in' (Vertical Cross-Section)

Weld Area = 18.84 in8 (Vertical Cross-Section)

T/2 Area = 182.44 in* (Vertical Cross-Section)

Inside Radius Area = 8.76 in' (Vertical Cross-Section)

Total Area = 204.11 in' (Near Surface + Weld + T/2)

Near Surface Area = 15.10 in' (Horizontal Cross-Section).

Weld Area = 13.08 in* (Horizontal Cross-Section)'

T/2 Area = 175.93 in' (Horizontal Cross-Section)

Inside Radius Area = 8.90 in a (Horizontal Cross-Section)

OUTLET NOZZLE INSIDE RADIUS l l

ITEM NO.: B03.100.005 ITEM NO.: B03.100.006 I.D. NO.: 2RPV-W15 I.D. NO.: 2RPV-W16 4

ITEM NO.: B03.100.007 ITEM NO.: B03.100.008 I.D. NO.: 2RPV-W17 I.D. NO.: 2RPV-W18 CIRC 70' Gets 7.82 in: Coverage Vertical Section 70* Gets 7.07 ina Coverage Horizontal Section l Covered Area =

( 7.82 + 7.07 ) x .50 = 84.4 %

8.76 8.90 AXIAL 70* Gets 8.40 in' Coverage Vertical Section

, 70' Gets 7.66 in' Coverage Horizontal Section i Covered Area =

( 8.40 + 2211 ) x .50 = 91.0 %

8.76 8.90 70' INSIDE RADIUS COVERAGE AXIAL CIRC ,

91.0 84.4 Aggregate Coverage = 87.7 % M M ' UN ATmtMhBW- 2 l PAGE 31 os 31 ;

1 l

, l ASME Class 1 NDE Inservice inspection Attachment 3 Request for Relief Serial No.96-003 For McGuire Unit 2 Based on ASME XI 1980 Code Through Winter 1980 Addenda April 25,1996 l

Subject:

Duke Power Company McGuire Unit 2. First Inservice Inspection Interval History of Limited Ultrasonic Examination of Reactor Vessel Welds During the first Inservice Inspection ( ISI ) interval at McGuire and Catawba, and the second ISI interval at Oconee, welds that had less than 90% Ultrasonic (UT) coverage were not identified on a Request for Relief to the NRC Welds that had limited UT coverage were indicated on ISI reports as limited, but the actual percentages of coverage obtained were not provided.

The practice of documenting the UT coverage as limited, but not documenting the actual percentage of coverage obtained, was based on an interpretation of a note in ASME Code Section XI. Tables IWB-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 100%, the inspection was reported as limited. The percentage of coverage obtained was not recorded in ISI Reports prior to January 1993.

ASME Code Case N-460 was published on July 27,1988 and approved by the NRC in Revision 8 to Regulatory Guide 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 less than 90% is a deviation from the Code and requires a Request for Relief.

Generic Request for Relief 93-GO-001 which requested relief for all welds identified as limited for Oconee, 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 and DPC representatives for the purpose of discussing Request for Relief 93-GO-001 and to clarify differences of interpretation pertaining to limited welds as defined by Code Case N.

460.

Based on discussion with NRC staff representatives during the January 11,1995 conference call, the NRC felt this issue 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. S. 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 j limited welds examined during the first ISI interval for McGuire and Catawba and the second ISI interval )

for Oconee. The limited weld information for McGuire, Catawba and Oconee veas sent to Mr. Economos on i March 30,1995. I i

I l

Page i of 2 l

L. N.

b

$ ASME Class 1 NDE Inservice Inspection Attachment 3 Request for Relief Serial No.96-003 For McGuire Unit 2 Based on ASME XI

} 1980 Code Drough Winter 1980 Addenda

April 25,1996 3

j included in the March 30,1995 submittal were the McGuire Unit 2 reactor vessel welds. During the NRC review of the reactor vessel welds, it was determined that additional information was necessary for the i technicaljustification. A meeting was held on April 6,1995 between B&W Nuclear Technologies j (BWNT) and DPC, and at this time DPC requested additional information in order to address the limited c

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 i

Framatome Technologies (formerly BWNT), provided additional information in response to DPC's i concerns of September 5,1995 relating to the Reactor Vessel Examination Evaluation Reports.

3 During Mr. Economos' visit to McGuire on January 16,1995, a meeting was held to discuss the evaluation i status of the limited examination welds on the Reactor Vessel 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 has since contracted with Framatome Technologies to provide

, percentage of coverage for all welds determined to have limited coverage for Unit 1. This is report is due at DPC by April 30,1996. Upon receipt of this report, DPC's NDE level III will review it and the results will i be discussed with Mr. Economos of NRC Region II.

i l

b R M*b Gary Underwood QA Technical Services Section Station Support Division 4

Nuclear General Office i

d L

l l

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