ML20064N730

Forwards Relief Request 94-01 from ISI Requirement.Basis for Request Explained in Section III

ML20064N730
Person / Time
Site:	Catawba
Issue date:	03/24/1994
From:	Rehn D DUKE POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9403300110
Download: ML20064N730 (80)

Text

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11 1 Duke her Company ~ D. L Rrm

- Catawba kudear Generation [kpartment Vice hesident }

4800 Concord Road (803)&Ul3205 Office i York.SC29743 (803)8313426 Far j DUKEPOWER i

March 24,1994 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

Subject:

Catawba Nuclear Station, Unit 1 Docket No. 50-413 Relief Request 94-01 1EOC7 Inservice Inspection Report Please find attached, Catawba's Request for Relief 94-01. The basis for this request is explained in Section III.

Any questions concerning this request should be directed to L. J. Rudy at (803) 831-3084.

Very truly yours, fdith [. dbt5Y) OG D. L. Rehn KEN /IEOC71SI . RLF i Attachment xc: S. D. Ebneter, Regional Administrator R. J. Freudenberger, SRI R. E. Martin, ONRR f

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U. S. Nuclear Regulatory Commission March 24,1994 Page 2 bxc: K. E. Nicholson J. O. Ilarbour  !

ELL -EC050 NCMPA-1 NCEMC PMPA SREC Master File: CN-801.01 Group File: CN-801.01 -: ,

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Serial No. 94 01 Page1of4 DUKE POWER COMPANY I

Request for Relief From Inservice Inspection Requirement 1

Station: Catawba Unit: 1 Requesting Department: Nuclear Generation Department Reference Code: ASME Boiler and Pressure Vessel Code,Section XI 1980 Edition through Winter 1981 Addenda  ;

1 I. Component for which exemption is requested: I

a. Name and Identification Number: ,

l ReactorVessel Weld Numbers Item Numbers l 1RPV-WO3 B01.011.001 l 1RPV-WOG B01.011.004 l 1RPV-W01 B01.021.001 1RPV-WO2 B01.022.001 1RPV-WO2-03 B01.022.003 ,

1RPV-WO2-04 B01.022.004 l 1RPV-WO2-05 B01.022.005 1RPV-WO2-06 B01.022.006 1RPV-W11 B03.090.001 4 1RPV-W11 B03.090.001A I 1RPV-W12 B03.090.002 l 1RPV-W12 B03.090.002A 1RPV-W13 B03.090.003 l 1RPV-W13 B03.090.003A 1RPV-W14 B03.090.004 '

1RPV-W14 B03.090.004A 1RPV-W15 B03.090.005 1RPV-W15 B03.090.005A 1RPV-W16 B03.090.006 1RPV-W16 B03.090.006A  !

1RPV-W17 B03.090.007 )

1RPV-W17 B03.090.007A  !

1RPV-W18 B03.090.008 1RPV-W18 B03.090.008A  ;

1RPV-W11 B03.100.001 1RPV-W12 B03.100.002 4

Serial No. 94-01 Page 2 of 4 ReactorVessel Weld Numbers Item Numbers II'PV-W13 B03.100.003 1RPV-W14 B03.100.004 1RPV-W15 B03.100.005 1RPV-W16 B03.100.006 1RPV-W17 B03.100.007 1RPV-W18 B03.100.008 Pressurizer Weld Numbers Item Numbers IPZR-W4A B03.110.004 1PZR-W4B B03.110.005 1PZR-W4C B03.110.006 1PZR-W4A .B03.120.004 1PZR-W4B B03.120.005 1PZR-W40 B03.120.006 1PZR-W4ASE B05.040.004 IPZR-W4BSE B05.040.005 1PZR-W4CSE B05.040.006 Steam Generator Weld Numbers Item Numberg 1SGC-INLET B03.140.005 ISGC-OUTLET B03.140.006 ISGC-INLET-SE B05.070.005 ISGC-OUTLET-SE B05.070.006 i l

Reactor Coolant System (NC) l Weld Numbers Item Numbers 1NC25-02 B05.130.014 1NC25-03 B05.130.015 1NC22-WN8 B09.031.003  ;

1

b. Function: )

i Reactor Vessel - Houses the fuel assemblies, control rods, and vessel l internals, also directs the flow of reactor coolant.

Pressurizer - Maintains reactor coolant system pressure within set limits  :

and provides a surge volume for the reactor coolant system.

Steam Generator - Acts as a heat exchanger in the reactor coolant system.

1 Reactor Coolant System - Transports heat energy from reactor core to steam  ;

generator.

J

Serial No. 94-01 Page 3 of 4

c. ASME Section XI Code Class: Class 1

d. Construction Code and Class (If Applicable):

ASME Section III,1974 Edition through Summer 1974 Addenda, Class 1

c. Valve Category (If Applicable): NA II. Reference Code Requirement that has been determined to be impractical:

Examination Category B-A, Pressure 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, Table IWB-2500-1, Figure No. IWB-2500-7; 100%  !

examination coverage.  !

l Examination Category B-F, Pressure Retaining Dissimilar Metal Welds, Table i IWB-2500-1, Figure No. IWB-2500-8; 100% examination coverage.

l Examination Category B-J, Pressure Retaining Welds in Piping, Table IWB-2500-1, i Figure No. IWB 2500-11;" Note 3: Includes essentially 100% of the weld length". l I

III. Basis for Requesting Relief: l l

During the ultrasonic examination of the welds shown in Attachment 1, the -

minimum 90% coverage requirement of ASME Section XI,1980 Edition through l Winter 1981 Addenda, clarified by Code Case N-460, could not be obtained due to l part geometry and actual physical barriers. A combination of multiple angles and UT techniques was used to obtain maximum coverage possible. The attached '

examination reports document the actual amount of examination coverage obtained.

Although the coverage requirements of ASME Section XI could not be met, the amount of coverage obtained for these examinations provides an acceptable level of quality and integrity. Based on these evaluations, the limited coverage will in no way endanger t% health and safety of the general public.

No additional examinations are required.

IV. Alternate Examination:

The use of radiography as an alternate volumetric examination method is not practical due to component thicknesses 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.

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Serial No. 94 01 Page 4 of 4 We will continue to use the most current ultrasonic techniques available for future examinations of the Item Numbers shown in Attachment 1.

V. Implementation Schedule:

These examinations will continue to be scheduled in accordance with the requirements of ASME Section XI for future Inspection Intervals at Catawba Nuclear Station, Unit 1.

Evaluated By: /.__ [/ . s , CWn Date: /

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ASME Class 1 NDE inservice Inspection Request For Relief Serial No. 94-01 For Catawba Unit 1 Based On ASME Section XI- 1980 Code Through Winter 1981 Addenda Attachment 1 (

Page 1 of 6 Ucensee item No. Exam Category System Or Function Area To Be Reason For Request Proposed Attemate

/ Figure No. Component Examined Examination 801.011.001 B-A Reactor Vessel Houses the fuel assembhes, Lower Head to Limited scan cue to geometro conhguraton. None IWB-2500-1 control rods, and vessel Shell Weld Actual coverage obtained -43.60%

intemals, also directs the flow of reactor coolant B01.011.004 B-A Reactor Vessel Houses the fuel assemblies, Shell to Nozzle Ltmsted scan due to geometre conhguraten. None IWB-2500-1 control rods, and vessel Belt Weld Actual coverage obtained -48.20%

internals, also directs the fiow of reactor coolant B01.021.001 B-A Reactor Vessel Houses the fuel assembhes, Lower Head Limited scan due to geometric configuration. None IWB-2500-3 control rods, and vessel Weld Actual coverage obtained -53.40%

internals, also directs the flow of reactor coolant B01.022.001 B-A Reactor Vessel Houses the fuel assembhes. Lower Head Limited scan due to geometro conhguraten. None IWB-2500-3 control rods, and vessel Meridbnal Actual coverage obtained -68.20%

intemais, also directs the flow Weld 302 Deg.

of reactor coolant B01.022.003 B-A Heactor Vessel Houses the fuel assembbes. Lower Head Limited scan due to geometro configuraton. None IWB-2500-3 control rods, and vessel Meridiona! Actual coverage obtained =77.10%

intemals, also directs the flow Weld 182 Deg.

of reactor coolant 801.022.004 B-A Reactor Vessel Houses the fuel assemblies, Lower Head Limited scan due to geometric conhguraten. None IWB-2500-3 control rods, and vessel Meridional Adual coverage otstained -77.10%

internals, also directs the flow Weld 122 Deg.

of reactor coolant 801.022.005 B-A Reactor Vessel Houses the fuel assembhes, Lower Head Limited scan due to geometre conhguraton. None IWB-2500-3 control rods, and vessel Meridiona! Actual coverage obtained -50.00% ,

internals, also directs the flow Weld 62 Deg.

of reactorcoolant B01.022.006 B-A Reactor Vessel Houses the tuel assembhes, i.ower Head Limited scan due to geometro configuraton. None IWB-2500-3 control rods, and vessel Meridional Actual coverage obtained -77.10%

internals, also directs the flow Weld 2 Deg.

of reactor coolant B03.090.001 B-D Reactor Vessel Houses the fuel assemblies, Inlet Nozzle to Limited scan due to geometre conhguraton. None IWB-2500-7 control rods, and vessel Shell 67 Deg. Actual coverage obtained -69.20%

internals, also directs the flow UT from of reactor coolant Vessel ID 303.090.001A B-D Reactor Vessel Houses the fuel assembises, Inlet Nozzle to Limrted scan due to geometre centsuraton. None IWB-2500-7 control rods, and vessel Shell 67 Deg. Actual coverage obtained -69.20%

internals, also directs the flow UT from of reactor coolant Nozzle ID

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ASME Class 1 NDE inservice inspsetion Request For Relief Serial No. 94-01 For Catawba Unit 1 Based On ASME Section XI- 1980 Code Through Winter 1981 Addenda Attachment 1 '

Page 2 of 6 Item No. Exam Category System Or Funcien Area To Be Reason For Request Lcensee

/ Figure No. Component Examined Proposed Afternate Examination B03.090.002 6-D Reac'.or Vessel Houses the fuel assemblies, Inlet Nozzle to Limited scan due to geometre contguration. None IWB-2500-7 control rods, and vessel Shell 113 Deg. Actual coverage obtained -69.20%

intemals, also directs the flow UT from of reactor coolant VesselID 103.090.002A B-D Paactor Vessel Houses the fuel assemblies, Inlet Nozzle to Limited scan due to geometro conf guration. None IWB-2500-7 control rods, and vessel Shell 113 Deg. Actual coverage obtained =69.20%

intemais, also directs the flow UT from i of reactor coolant Nozzle ID B03.090.003 8-D Reactor Vessel Houses the fuel assemblies, Inlet Nozzle Lim:ted scan due to geometre contguration. None IWB-2500-7 control rods, and vessel to Shell 247 Actual coverage obtained -69.20% ,

internals, also directs the flow Deg. UT from of reactor coolant VesselID 103.090.003A B-D Reactor Vessel Houses the fuel assemblies, Inlet Nozzle Limited scan due to geometre ontguration. None IWB-2500-7 control rods, and vessel to Sheli 247 Actual coverage obtained -69.20%

intemals, also directs the flow Deg. UT from of reactor coolant Nozzle ID 803.090.004 B-D Reactor Vessel Houses the fuel assemblies, Inlet Nozzle Limited scan due to geometro contguration. None IWB-2500-7 control rods, and vessel to Shel1293 Actual coverage obtained -69.20%

intemals, also directs the flow Deg. UT from of reactor coolant VesselID 103.090.004A B-D Reactor Vessel Houses the fuel assemblies, Inlet Nozz!e Limited scan due to geometre confguration. None IWB-2500-7 control rods, and vessel to Shell 293 Actual coverage obtained -69.20%

intemals, also directs the flow Deg. UT from of reactor coolant Nozzle ID B03.090.005 6-0 Reactor Vessel Houses the fuel assemblies. Outlet Nozzle Limited scan due to geometnc contguration. None IWB-2500-7 control rods, and vessel to Shell 22 Actual coverage obtained -43.70%

intemais, also directs the flow Deg. UT from of reactor coolant VesselID 103.090.005A B-D Reactor Vessel Houses the fuel assemblies, Outlet Nozzle Limited scan due to geometric contguration. None IWB-2500-7 control rods, and vessel to Shell 22 Actual coverage obtained -43.70%

intemals, also directs the flow Deg.UT from of reactorcoolant Nozzle 10 B03.090.006 B-D Reactor Vessel Houses the fuel assemblies, Outlet Nozzle Limited scan due to geometnc conf guration. None IWB-2500-7 control rods, and vessel to Shell 158 Actual coverage obtained -43.70%

intemais, also directs the flow Deg. UT from of reactor coolant VesselID

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ASME Class 1 NDE Inservice inspection Request For Relief Serial No. 94-01 For Catawba Unit 1 Based On ASME Section XI- 1980 Code Through Wimer 1981 Addenda Attachment 1 Page 3 of 6 trem No. Exam Category System Or Functon Area To Be Reason For Request Lcensee

/ Figure No. Component Examined Proposed Afternate -

Examination 103.090.006A B-D Reactor Vessel Houses the fuel assembbes. Outlet Nozzle Limited scan due to geomeinc contguraton. None IWB-2500-7 control rods, and vessel to Shell158 Actual coverage obtained -43.70%

internals, also directs the flow Deg. UT from of reactorcoolant Nozz!e ID B03.090.007 B-D Reactor Vessel Houses the fuel assembhes. Outlet Nozzle Limited scan due to geometre conf guraton. None IWB-2500-7 control rods, and vessel to Shell 202 Actual coverage obtained -43.70%

internals, also directs the flow Dag. UT from of reactorcoolant Vessel ID 103.090.007A B-D Reactor Vessel Houses the fuel assemblies, Outlet Nozzle Limited scan due to geometric con guraton. None IWB-2500-7 control rods, and vesset to Shell 202 Actual coverage obtained -43.70%

internals, also directs the flow Deg. UT from of reactorcoolant Nozzle ID B03.090.008 B-D Reactor Vessel Houses the fuel assembhes, Outlet Nozzle Limned scan due to geometrc conf guraton. None IWB-2500-7 control rods, and vessel to Shell 338 Actual coverage obtained -43.70%

internals, also directs the flow Deg. UT from of reactorcoolant Vessel ID 103.090.008A B-D Reactor Vessel Houses the fuel assembines, Outlet Nozzle Limrted scan due to geometre contguraton. None IWB-2500-7 control rods, and vessel to Shell 338 Actualcoverage obtained 43.70%

internais, also directs the flow Deg. UT from of reactor coolant Nozzle ID B03.100.001 B-D Reactor Vessel Houses the fuel assemblies, inlet Nozzle Limned scan due to geometnc contguraton. None IWB-2500-7 control rods, and vessel to Shell 67 Actual coverage obtained -64.60%

internals, also directs the flow Deg. Inside of reactor coolant Radius Section 803.100.002 B-D Reactor Vessel Houses the fuel assembhes, Inlet Nozzle Limited scan due to geomeinc contguraton. None IWB-2500-7 control rods, and vessel to Shell 113 Actual coverage obtained -64.60%

intemals, also directs the flow Deg. Inside of reactorcoolant Radius Section 803.100.003 B-D Reactor Vessel Houses the fuel assembhes, Inlet Nozzle Limited scan due to geometnc centguraton. None IWB-2500-7 cnntrol rods, and vessel to She!! 247 Actual coverage obtained -64.60%

internals, also directs the flow Deg. Inside of reactor coolant Radius Section C _. _ _ _ _ . ._

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ASME Class i NDE Inservice inspaction Request For Relief Serial No. 94-01 For Catawba Unit 1 Based On ASME Section XI- 1980 Code Through Winter 1981 Addenda Attachment 1 Page 5 of 5 Item No. Exam Category System Or Functon Area To Be Reason For Request Ocensee

/Fgure No. Component Examined Proposed Alternate Examination B03.120.004 B-D Pressunzer Maintains reactor coolant Safety Nozzle Limited scan due to geometric contguraten. None IWB-2500-7 system pressure within set to Upper Head Actual coverage obtained -66.10%

limits and provides a surge inside Radius volume for the reactor coolant Section system B03.120.005 B-D Pressunzer Mamtains reactor coolant Safety Nozzle Limrted scan due to geometnc contguration. None IWB-2500-7 system pressure within set to Upper Head Actual coverage obtained -66.10%

limits and provides a surge inside Radius volume for the reac*or coolant Section system 803.120.006 B-D Pressunzer Maintatns reactor coolant Safety Nozzle Limited scan due to geometnc contguraton. None IWB-2500-7 system pressure within set to Uppe- Head Actual coverage obtained -66.10%

limits and provides a surge inside Radius volume for the reactor coolant Section system B03.140.005 B-D Steam Generator Acts as a heat exchanger in the iniet Nozzle Limited scan due to geometnc conf guraton. None IWB-2500-7 reactor coolant system inside Radius Actual coverage obtained -55.25%

Section B03.140.006 B-D Steam Generator Acts as a heat exchanger in the Outlet Nozzle Limited scan due to geometnc contguraton. None IWB-2500-7 reactor coolant system inside Radius Actual coverage obtained -5525%

Section 805.040.004 B-F Pressunzer Maintains reactor coolant Safety Nozzle Limited scan due to geometnc conf guration. None IWB-2500-8 system pressure within set to Upper Head Actual coverage obtained -75.00%

limits and provides a surge Safe End volume for the reactor coolant system 805.040.005 B-F Pressurizer Maintains reactor coolant Safety Nozzle Limited scan due to geometro contguration. None IWB-2500-8 system pressure within set to Upper Head Actual coverage obtained -75.00%

limits and provides a surge Safe End volume for the reactor coolant system B05.040.006 B-F Pressunzer Maintains reactor coolant Safety Nozzle Umsted scan due to geomeinc conf guraton. None IWB-2500-8 system pressure within set to Upper Head Actual coverage obtained -75.00%

limits and provides a surge Safe End volume for the reactor coolant system B05.070.005 B-F Steam Generator Acts as a heat exchanger in the inlet Nozzle Umited scan due to geometric cont:guration. None IWB-2500-8 reactor coolant system Safe End Actual coverage obtained -75.00%

B05.070.006 B-F Steam Generator Acts as a heat exchanger in the Outlet Nozzle Umited scan due to geometnc confguraton None IWB-2500-8 reactor coolant system Safe End Actual coverage obtained -75.00%

B05.130.014 B-F Reactor Coolant Transports heat energy from Pipeto Umited scan due to geometnc contguraton. None IWB-2500-8 System (NC) reactor core to steam generator Safe End Actual coverage obtained -75.00%

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'1 I

( W-03 I

i i

Total Exam Area = 53.32 in a (Near Surface + Weld + T/2)

Near Surface Area = 8.37 in' (Cross-Section)

Weld Area = 6.37 ina (Cross-Section)

T/2 Area = 38.58 ina (Cross-Section)

BETWEEN LUGS CIRC 70 Gets 6.24 in a of Near Surface Area (74.6 %)

0 Gets 9.07 in2 of Total Exam Area (17.0 %)

45 & 60 Get 31.79 in2 of T/2 Area, .44 ina of Weld Area Total Coverage = 31.79 + 0.44 + 0.44 = 63.7 %

38.58 + 6.37 + 6.37 f 70 Gets 8.24 ina of Near Surface Area; however due to the AXIAL

Full-Node Exam, 100 % Coverage of the Near Surface Area I is obtained by the 45 & 60 .

45 Gets 100 % of Weld and T/2 Area 60" Gets 100 % of Weld and T/2 Area DELOW LUGS AXIAL Due to the Full-Node Exam, 7.58 inn of the Near Surface Area is obtained by the 60 (90.6 %).

45 Gets 3.79 in of T/2 Area (0 % Weld Area) a 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 in2 2

of Weld Area Total Coverage = 9.11 + 1.23 + 0.00 = 20.1 %

( 38.58 + 6.37 + 6.37 Ssa..tda. % -0\

kTTAtumuT 2 Bot.o t t . 001 t RPV-WOS PG 2 0F G8

.(-

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 70 , 60 & 45 Axial and 70 & 4 5 Circ . There are also six (6)

Segments Below Lugs, each covering th'e remaining 24.28 for~ Axial Scans.

.i 0 & 60 Circ Coverage = 189.60 x % Between 100 x 360 70 & 45 Circ Coverage = 214.32 x % Between 100 x 360 Axial Coverage = 214.32 x % Between +-145.68 x'% Below 100 x 360

(

W-03 AXIAL CIRC NS 60 .45 70 60 45 0 96.2 67.7 62.5 44.4 33.5 37.9 9.0 Aggregate Coverage =

[ 96.2 x 8.37 + (67 7 + 62.5) x (38.58 + 6.37 + 6.37)

+ 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) x4 + 53.32 ] =

\ c,e,s ,Wo. 44-01 >

Aggregate Coverage = 43.6 % k r7AC.WmE*1T 2 Bot.on.co t igev Wes PG 3. 0 F GB -

u 8 / l a

JL

.157 N0H -

25.53 lLANGE SURFACE 9 173.0 CLAD 8.465 1

(TI)

"Z"  : 339.28 '

l J

4

)TTOM HEAD RADIUS CENTER "Z" 342.38 ,

j 3 , ',7 0,'

d I ,/ ,',45' I

s,/ ,

i  %

i ,

I

"Z" = 349.12 l

342.65 l TO FLANGE SURFACE "Z"  : 352.22 ,

I h-----' '

"Z" = 353.58 '

Tl/2

, ru 0

"Z" = 356.68 04 ~ m p% y

. h , ,w ~~

ALPHA : Il.09

w. ,

WELD REFERENCE LINE '

ALPHA = 13.17 ', , rn '

' ' 4,1 T2/2 ALPHA 13.90 -

', s ',

ALPHA : 15.18 ~.. . '

RADIUS : 88,189 , ; ,'. '"

ALPHA : 17.39 s ,-

', " ' r %. ,

(GUIDE LUG LIMIT) ALPHA= : 19.40

'I

20.13 , 7 0,s g._ ,' .gu &46 ALPHA

.#C~' y* s ,\ "

ALPHA = 22.14 ,' 60

ALPHA : 24.10 ,

.157 N0H 5.591

'(T2)

%n.M s.R ' -C l ATTAC.W rAE.MT Z 8 01.0) 001 RPV

<' MdN CLEAR CE :

2.06* PG 4 o u roo i N-N MIN CLEARANCE : 2.00" f

b W-06 Total Exam Area = 93.65 in2 (Near Surface + Weld'+ T/2)

Near Surface Area = 10.47'in2 (Cross-Section)

Weld Area = 11.38 ina (Cross-Section)

T/2 Area = 71.80 in' (Cross-Section)

CIRC 70 Gets 3.82 in2 of Near Surface Area (36.5 %)

0 Gets 6.08 in2 of Total Exam Area (6.5 %)

45 & 60* Get 28.50 in of T/2 Area (0 V Weld).

2 Total Coverage = 28.50 + 0.00 +- 0.00 = 30.1 %

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

-(

45 Gets 63.34 in of T/2 Area 2

45 -UP Gets 11.10 in n 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 '

l 60 Gets 67.39 in of T/2 Area n

60 -UP Gets 9. 87 'in' of Weld Area 6 0 -DOWN Gets - 9.34 ina of Weld Area Total Coverage = 67.39 + 9.87 + 9.34 = 91.6 %- 2 71.80 + 11.38 + 11.38 Se.a., bl o, k4 -o \

kTrncamocrf.

601.0u.00+

WPV-W oG 9G' 5 o F G B

W-06 AXIAL CIRC 70 60 45 70 60 45 0 51.6 91.6 83.7 36.5 30.1 30.1 6.5

't Aggregate Coverage =

[ 51.6 x 10.47 + (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) x4 + 94.65 ] =

Aggregate Coverage = 48.2 %

(

i e

r

(

Sct.14o. 94-6 )

[ r ratsme.u r. f 60t.o1\.004 1R9V-u)ob PG ' G OF GB

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1 TAPER DELOW OUTLET N0ZZLES I l

l l

"Z" s 124.30 )

1 138.11 "Z" = 127.40

.ANGE SURFACE IO,027 "Z" a 130.50 .

@ 170.87 ' O, CLAO

. I l

"Z" n 130.44 '

"Z" s 440,45 ~ ~ - - ~ ~ ~ Y -" A ,

l I

T1/2 I f .j L.____.___'.

y. , i 43,ge f n

, r.7 '".7." :- - .-

r.cr s - - ,<,. l

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• g "Z" a 150.06 . 1 "Z" s 150.00 ,

"2" = 153.99 *******%*~' .,

,%,7

.'5

\

"Z" = 159.52 ,

4

,' 60'

\

"Z" = 162.62

__ @ 173.0 CLAD ~~

.I57 NOM 0.465 (T2)

GENERAL NOTES:

1. AU vue u.v emDIMEN "Z" c. .SIO.N, S REFERENCE.wuTHEvue DISTANCE DETWEEN oe e on vue rewreo tw-6e,q, No. 9 4-0 \

"T'T ACHW M~T I 601.011.004

\@RPV b 9 09 W0(6 96

W-01 Total Exam Area = 41.68 in2 (Near Surface + Weld + T/2)

Near Surface Area = 7.27 in z (Cross-Section)

Weld Area = 5.11 in 2 (Cross-Section)

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

CIRC 70 Gets 4.46 ina of Near Surface Area (61.3 %)

0 Gets 7.73 in' of Total Exam Area (18.5 %)

45 & 60 Get 16.02'ina 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 in2 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 60 -UP Gets 100 % of Weld Area 60 -DOWN Gets 4.77 in 2 of' Weld Area Total Coverage = 29.30 + 5.11 + 4.77 = 99.1 %

29.30 + 5.11 + 5.11 I'

Se.a. Mo. 44-on

( Asx<<emm, z 60\.02.1 001 l R 9V- tac t PGBoreo

4 E

\ W-01 is Obstructed due to 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 & 45 Circ.

0 & 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 W-01 AXIAL CIRC NS 16 0 45 70 60 45 0 72.0 76.8 77.6 47.5 47.8 51.5 13.3 Aggregate Coverage = .

[ 72.0 x 7.27 + (76.8 + 77.6) x (29.30 + 5.11 + 5.11)

+ 46.5 x 7.27 + (4 7. 8 + 51. 5 ) x (29.30 + 5.11 + 5.11)

+ 13.3 x 41.68 ] /

( [ 7.27 x 2 + (29.30 + 5.11 + 5.11) x4 + 41.68 ) = Sea. Mo.94-on Aggregate Coverage = 53.4 % drmg g Ect.oz i. c o

\RPV wo1 PG 9 oF 48

4

~

'i 5 591.

(T) i-ALPHA = 23.62-I ALPHA = 25.63- i 60' RADIUS = 88.194 . , ' ' , -'

(CLAD)

,'+ 70i

.157 , 45' i

NOM. sg

.i s

i t

i ALPHA = 3I.99 rn,. ..

. ' , ~ . '- ' ' " -

ALPHA = 33.99

ALPHA = 34.86 ,- '..

, N-ALPHA = 36.07 .. N

- N ->

ALPHA =-36.87 3 , .N

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W-02 l

Total Exam Area = 221.51 in2 (Near Surface + Weld + T/2)

(Alpha Cross-Section) 4 i

Near Surface Area = 38.21 in2 (Alpha Cross-Section)

Weld & T/2 Area = 183.30 in 2 (Alpha Cross-Section)

The Weld Area occupies 1.30 and T/2 Area occupies 4.48 in the Circumferential or Theta Direction.

Coverage for the Weld & T/2 Areas is based on:

(4.48 + 1.30 + 1.30) / 5.78 or 122.5 % Area.

CIRC 70 Gets 28.58 in2 of Near Surface Area (74.8 %)

45 & 60 Get 136.38 in2 of Weld & T/2 Area (74.4 %)

AXIAL 70 Gets 30.32 in2 of Near Surface Area; however due to the Full Node Exam, 100 % of the Near Surface Area is

(. obtained with the 45 &.60 .

O Gets 137.45 in2 of Total Exam Area (62.1 %)

45 Gets 170.84 in2 of T/2 Area 4 5 -UP Gets 151.89 in2 of Weld Area 4 50-DOWN Gets 170.84 in2 of Weld Area Total Coverage = 170.84 x 4.48 + 151.89 x 1.30 + 170.84 x 1.30 183.30 x 4.48 + 183.30 x 1.30 + 183.30 x 1.30

= 91.3 %

60 Gets 175.32 in2 of T/2 Area 60 -UP Gets 147.48 in2 of Weld Area 60 -DOWN Gets 175.32 in2 of Weld Area Total Coverage = 175.32 x 4.48 + 147'48 x 1.30 + 175.32 x 1.30 183.30 x 4.48 + 183.30 x 1.30 + 183.30 x 1.30

( b'8 hlo94-03

= 92.9 % Ik rTAmme.N-r f.

60\.021.001 149V- W oz-o t 6o1.022 003 tR9V Woz,oS

'60s.022.004 j RPVa Wo2-04 So 4.0 22.00 S t R.PV4 w et . o S So l.022.d d 0 t g,9v Vo2,. 64

_ PG 11 0 9 68

'l

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< ; ,. g i t L i 1

, (

WO2-03, W2-04 & W2-06 are Unobstructed and Get the Following Coverages:

W-02 CIRC AXIAL v

70 60 45 NS 60 45 0 i 74.8 74.4 74.4 100 91.3 92.9 62.1 Aggregate Coverage as f ( 100 x 38.21 + (91.3 + 92.9) x (183.30 x 122.5 %)

+ 74.8 x 38.21 + (74.4 4 74.4) x (183.30 x 122.5 %)

+ 62.1 x 221.51 ] /

[ 3 8. 21 x 2 + (183.30 x 122.5 %) x4 + 221.51~) =

t Aggregate Coverage = 77.1 %

1, i

bit,9.. N o, C l4- 0 )

kTT6c.amicu-r f.

00\ 02'L.bol \R.H.weg..or 1501 022.003 I R9V-Wo2 43 Bol. 02 Z 0 04 g A9V- W o2- 04 60s.0 22.c os 1 R9v- u)cz.os ecs. 022.00ts t (1.PV- Wo2- oco P G 12 'osr (,8 if

1

( .,

l l

WO2-01 is Obstructed due to Instrument Nozzles. i l

> l I

l 2

CIRC 70 Gete 22.40 in of Near Surface Area (58.6 %) ,l 1

45 & 60 Get 106.02 in2 of Weld l& T/2 Area (57.8 %) I l

i AXIAL 70 Gets 25.89 in2 of Near Surface Area; however due to the l '

Full Node-Exam, 100 % of the Near Surface Area is obtained with the 45 & 60 . J 0 Gets 92.65 in2 of Total Exam Area (41.8 %).

1 45 Gets 169.70 in2 of T/2 Area 45 -UP Gets 147.82 in2 of Weld Area 4 5 -DOWN Gets 152.94 in 2 of. Weld Area

( Total Coverage = "l69.70 x 4.48 + 147.82 x 1.30 4 152.94 x 1.30'  !

183.30 x 4.48 + 183.30 x 1.30 + 183.30 x 1.30

='88.7 %

} !

60 Gets 175.48 in2 of T/2 Area 6 0 -UP Gets 156.66 in2 of Weld-Area 60 -DOVTN Gets 147.08 in2 of Weld Area  !

Total Coverage = 175.48 x 4.48 + 156.66 x 1.30 +-147.'08 x 1.30- =

1 183.30 x 4.48 + 183.30 x 1.30 + 183.30 x 1.30-

= 91.0 % ,

4

. b fL bdo. 0 4-o1. h kTvwummy 2 bl.022.. o o g ggpV-W02 ot s; k 6ot.or r. oop inev. w z. og s gn- woz. o 4 bot. o22.co4 ses.e12.oos tApt- Woz 0 5 .

R.PV- Wol - 0 G .

&#3h 0 22. 00 6 (

f G } $ ' O f~ b b .

=. . . . - . . . __ .

L WO2-01 CIRC AXIAL 70 60 45 NS 60 45 0 58.6 57.8 57.8 100 91.0 88.7 41.0 Aggregate Coverage =

{ 100 x 38.21 + (91.0 + 88.7) x (183.30 x 122.5 %)

g + 58.6 x 38.21 + (57.8 + 57.8) x (183.30 x_122.5 %)-

& 41.8 x 221.51 ) /

[ 38.21 x 2 + (183.30 x 122.5 %) x4 + 221.51 ) =

Aggregate Coverage = 68.2 %.

-(

Se.a.blo.94-og ATwomw.y 2. -

Nt.o22.co: _ gp,pv.wog, o i k b01 022. 003 IgPv woz. os 601.022. o'o4 i R pv. woz. c4

%.c22.oos tRev- woz.os Sol.or2.cos ingv wo2.or, PG 14 0F GS 7 < , , w - , _

. . . . - .-. .-~ - . . . ..

d 4

-(

WO2-05 CIRC 70 Gets 5.52 in 2of Near Surface Area (75.9 %)

45 Gets 22.45 in2 of T/2 Area 4 5 -DOWN Gets 100 % of Weld Area Total Coverage = 22.45 + 0.00 + 5.12 = 69.7 %

29.29 + 5.12 + 5,12 60 Gets 20.09 in2 of T/2 Area 60 -DOWN Gets 4.20 in2 of Weld Area Total Coverage = 20.09 + 0.00 + 4.20 = 61.4 %

29.29 + 5.12 + 5.12 AXIAL 70 Gets 3.78 in2 of Near Surface Area (52.0 %)

0 Gets 3.77 in2 of Total' Exam Area ( 9.0 %)

45 & 60 Get 14.57 in2 of T/2 Area 45 & 60 Get 3.30 in2 of T/2 Area Total Coverage = 14.57 + 3.30 + 3.30 = 53.6 t' 29.29 + 5.12 + 5.12 i

l h9-, N o . 94-01 A-twumer 2 T bl 072.co l I R.9V wez.og , )

60t.c22.003 \ gov- we2..as l

601 022. 00A \ RPV- WC2,- 04 I tbOL O22.005 \ tPV yJag.n$ ]

201.022.00G lRPV We2 06 PG t6 o 5' (> 8 -

(

WO2-05 CIRC AXIAL 70 60 45 70 60 45 0 d

75.9 61.4 69.7 52.0 53.6 53.6 9.0 Aggregate Coverage =

[ 52.0 x 7.27 + (53.6 + 53.6) x (29.29 + 5.12 + 5.12)

+ 75.9 x 7.27 + (61.4 + 69.7) x (29.29 + 5.12 + 5.12)

.+ 9.0 x 41.68 ] /

[ 7.27 x 2 + (29.29 + 5.12 + 5.12) x4 + 41. 68 ] =

Aggregate Coverage = 50.0 %

(-

Total Coverage = EQ.0 % x Unobstructed + 50.0 % x Obstructed 100.%

= 72.7 %

f 6ea.. l\1o. 94-0l AT ,rAc.4 m d -r 7-.-

bl . 072.OO L l ROV- W 02- ol i' ooi c22.003 i R9V-Wo2 c3

'\' P.>o s . 0T2 004 \lpv-wa2-04 thol. 022,005 ) KPV. W62 0S sol. 022. 06G l KPv- u)oz- OL PG w'oF 68

i,

~

hY i ,

9 60' 9.04 sf . . .-

} 3 pp "

6.31 - ' 70f 45'

's i 5.96 . .

_' /_ '

,- ~j' i, ,,

3.22 ",, T/2

,43 s

\ u

{ ~

i l U 3

'-] -~'

hREFERENCE LINE '

L I.20 ,,

T/2 3.99 '/

I - :- - .' ' _

U 6.72 ,',

7.08 .' < ,

9

< } -

l '

9.80 ,

y 2

.I57 NOM - k_.

RADIUS:= 88.189 5'.591  %

CLAD (T)

Se.A.No.94-oi kTTacame.NT 2 i Rpv-woz.o]

60\.022.001 S01.022.00S IRPV-Woz. os bas.022.604 (RPV-tdo So t.022.co S I RPV-Woz bo t.0 22.o6 4 \ RPV-Woz.og PG1(1 -O F G8 -t

.(

W-IN NOZZLE-TO-SHELL WELD & INSIDE RADIUS Total Area = 209.57 in2 (Near Surface + Weld + T/2)

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

Weld Area = 24.95 in 2 (Vertical Cross-Section)

T/2 Area = 170.75 in z (Vertical Cross-Section)

Inside Radius Area = 9.21 in 2 (Vertical Cross-Section)

Total Area = 164.09 in 2 (Near Surface + Weld + T/2)

Near Surface Area = 13.62 ina (Horizontal Cross-Section)

Weld Area = 13.42 in2 (Horizontal Cross-Section)

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

Inside Radius Area = 5.56 in a (Horizontal Cross-Section)

INSIDE RADIUS CIRC 70 Gets 4.11 in2 Coverage Vertical Section 70 Gets 3.10 in' Coverage Horizontal Section Cos' red Area = ( 4.11 + 3.10 ) x .50 = 50.2 %

9.21 5.56 AXIAL 70 Gets 6.24 in2 Coverage Vertical Section 70 Gets 5.01 in' Coverage Horizontal Section Covered Area = ( 6.24 + 5.01 ) x .50 = 78.9 t J

9.21 5.56 S n .do. u -Oi 70 INSIDE RADIUS COVERAGE Arwe -r 2  !

EOSMO 001 lR pV. Win AXIAL CIRC- D M"'O I e,os.090.002 \Rpv Ul2. 1 g eqo.co2 A l

( -78.9 50.2 gg.,. cio. cob g g pV-W 13 93.090.c oSA ~

0 Aggregate Coverage = 64.6 % N } 'ffpek gI b8b.100. 001  % RPV- Wil (

i Sob. I oo. 002. I R Pv'- W L 2.

93,ioo 003 i f 96 W LS gg,too.044 iA9V-Wl4 PG,tB 0F (,6-

, ( NOZ7sLE-TO-SHELL WELD CIRC 70 Gets 13.70 in 2Coverage Verti. cal Section 70 Gets 10.72 in' Coverage Horizontal Section Covered Area = ( 13 70 + 10.72 ) x .5 =. 88.7 % 1 13.87 13.62 CIRC 0 Gets 144.35 in2 Coverage Vertical'Section 0 Gets 98.40 ina Coverage Horizontal Section Covered Area = ( 146.35 + 98.40 ) x .5 = 64.4 %

209.57 164.09 CIRC 45 & 60 Get 100 % Weld Coverage Vertical Section 45 & 60 Get 167.93 ina T/2 Coverage Upper Vertical Section k 45 Gets 145.24 in2 T/2 Coverage Lower Vertical Section 60 Gets 167.93 in' T/2 Coverage Lower Vertical Section 45 & 60 Get 11.74 in2 Weld Coverage Horizontal Section 45 & 60 Get 75.95 in 2 T/2 Coverage Horizontal Section Adjacent to Neighboring Inlet. Nozzle 45 Gets 75.93 in2 T/2 Coverage Horizontal Section Adjacent to Neighboring Outlet Nozzle G ..

60 Gets 75.95 ina T/2 Coverage Horizontal Section Adjacent to Neighboring Outlet Nozzle S e.g. N o. % -OL kTrAC.Am #

$3,090.001 12 PV-W Li 60g,o cto.0on A p,oqo.co2. g A9V, Wl?

60%.090 0

• A

p. o30.o 0 S ggpV,plS gos.o9o.coSA l g ,oqo.co4 1R9V Wlb Sog,cAo.004 A gas.tco.001 \ R 9V' N '\

0 1 oo 4-ec, s or c,

]

(' 45 Covered Area = [ ( 167.93 + 24.95 + 24.95 )

170.75 + 24.95 + 24.95

+ ( 145.24 + 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

= 77.1 %

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 1,, 137.05 + 13.42 + 13.42

= 79.7 %

AXIAL 45 Gets 11.61 ina Coverage Vertical Section Near Surface 45' Gets 2.78 ina Coverage Horizontal Section Near Surface Covered Area = ( 11.61 + 2.78 ) x .50 = 52,1 %

13.87 13.62 AXIAL 0 Gets 128.63 ina Coverage Vertical Section 0 Gets 31.15 inz Coverage Horizontal Section ,

i Covered Area = ( 128.63 + 31.15 ) x .50 = 43.2 %  ;

195.70 150.47 l l

l l

AXIAL 45 Gets 158.01 in' Coverage Vertical Section l l

45 Gets 117.92 in2 Coverage Horizontal Section Covered Area = ( 158.01 + 117.92 ) x .50 = 79.6 % l 195.70 150.47 $seg,do,qd_og Axx%mm, z PG 2one g, ogg*, e m I A PY-WM Tho3.o90 00 3 g gpV.W G M3.8 00.00 L i f PV- W H h12:!!himi2 @ $ ,i!Ad iov-w+ $ 3.78 75 $

(-

W-IN NOZZLE-TO-SHELL WELD AXIAL CIRC NS 0 45 70 60 45 0 52.1 43.2 79.6 88.7 79.7 77.1 64.4 Aggregate Coverage =

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

+ 88.7 x (13.87 + 13.62) + (79.7 + 77.1) x (170.75 + 24.95 + 24.95 + 137.05 + 13.42 + 13.42)

+ 64.4 x (209.57 + 164.09) ) /

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

+ (170.75 + 24.95 + 24.95 + 137.05 + 13.42 + 13.42) x2

+ (209.57 + 164.09) ]

Aggregate Coverage = 69.2 %

b .d. 94 01 kTTAcAmcuTf.

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W-OUT NOZZLE-TO-SHELL WELD & INSIDE RADIUS Total Area = 216.35 in2 (Near Surface + Weld + T/2)

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

Weld Area = 18.84 ina (Vertical Cross-Section)

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

Inside Radius Area = 8.76 ina (Vertical Cross-Section)

Total Area = 204.11 in a (Near Surface + Weld + T/2)

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

Weld Area = 13.08 ina (Horizontal Cross-Section)

T/2 Area = 175.93 in 2 (Horizontal Cross-Section)

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

INSIDE RADIUS CIRC 70' Gets 7.82 in' Coverage Vertical Section 70 Gets 7.07 in' Coverage Horizontal Section Covered Area = ( 7.82 + 7.07 ) x .50 = 84.4 %

8.76 8.90 AXIAL 70 Gets 8.40 in2 Coverage Vertical Section 70 Gets 7. 66 in' Coverage Horizontal Section Covered Area = ( 8.40 + 7.66 ) x .50 = 91.0 %

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Covered Area = ( 12.77 + 9.96 ) x .50 = 75'.3 %

15.07 15.10 0 Gets 180.77 ina Coverage Vertical Section 0 Gets 124.50 ina Coverage Horizontal Section Covered Area = ( 180.77 + 124.50 ) x .50 = 77.8 %

201.28 189.01 45 Gets 154.56 ina Coverage Vertical Section 45 Gets 155.82 in2 Coverage Horizontal Section Covered Area = ( 154.56 + 155.82 ) x .50 = 79.6 %

201.28 189.01 W-OUT k

N0ZZLE-TO-SHELL WELD AXIAL CIRC NS 0 .,_( L 70 60 45 0 75.3 77f8 79.6 41.5 25.8 25.8 12 '.'6 Aggregate Coverage =

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+ 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. 3 5 + 204.11) } /

{ (15.07 + 15.10) x2+ (201.28 + 1'89.01) x2

+ (182.44 + 18.84 + 18.84 + 175.93 + 13.08 + 1 ') .08) x2

( + (216.35 + 204.11) )

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NOZZLE-TO-SHELL WELD CIRC 70 Gets 6.17 in2 Coverage Vertical Section 70 Gets 6.36 ina Coverage Horizontal Section Covered Area = ( 6.17 + 6.36 ) x .50 = 41.5 15.07 15.10 0 Gets 33.28 ina 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 in2 Weld Coverage Vertical Section 45 & 60 Get 56.95 ina T/2 Coverage Vertical Section 45 & 60 Get 0.00 in* Weld Coverage Horizontal Section 1'

45 & 60 Get 44.92 in2 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 %

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, Limited Exam Data Sheet Station 8ANw6A Unit / I.D. # //U#" M m l By .W ud.cfV Date //~O V W lte m M 003 /IO

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Total Cross Sectional Area /1 x (Number of Scans) 7 = /6f (% Factor)

Vessels:

Area Loss : Zone #1 1 oG Zone #2 2. a3 Zone #3 7 77 -

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Total Loss //. 72- %

100% - (Total Loss) //.72 - Pis.2,% of Coverage

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Qualifies for Request for Relief O'Yes O No Pining: (-

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Total Cross Sectional Area /E x (Number of Scans) 7 = /0 f (% Factor) y_essels:

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By: Date:

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Unit I 1.D. # t FM - WA By bcu tJ ,96 Date N-N C Item # BoS 180 ' O 4 Chec d By 28< d/ N Date /A2f 93 Page 2 Of 5

, DETERMINING THE CUMULATIVE TOTAL OF WELD VOLUME INSPECTED

j (in percentage)

Total Cross Sectional Area 3 SS x (Number of Scans) 1 = 3" (% Factor)

Vessels:

Area Loss : Zone #1 nlA Zone #2 n1+

Zone #3 n1+

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Total Loss  %

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bdulbk Date //O f' 91 Page 3 of L DETERMINING THE CUMULATIVE TOTAL OF WELD VOLUME INSPECTED (in percentage)

Total Cross Sectional Area I 91 x (Number of Scans) 1 = 3" (% Factor)

Vessels:

Area Loss : Zone #1 nl+

Zone #2 nl+

Zone #3 nl*

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Vessels:

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DETERMINING THE CUMULATIVE TOTAL OF WELD VOLUME INSPECTED (in percentage)

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Vessels:

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DETERMINING THE CUMULATIVE TO'l/.1 OF WELD VOLUME ; INSPECTED (in percent; a Total Cross Sectional Area l'% x (Number of Scans) A = / E (% Factor)

Vessels:

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Total Cross Sectional Area T/// x (Number of Scans) =

(% Factor) 2 Vessels:

Area Loss : Zone #1 Zone #2 3

Zone #3 Total Zone Loss /(% Factor) x 100 =  % of Loss Lump Sum Loss Fro'm Other Limitations +  %

Total Loss  %

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( Additional So of Partial Coverage)

Qpallfles for Request for Relief O Yes O No Pining: (

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DI?rERMINING THE CUMULATIVE TOTAL OF WELD VOLUME INSPECTED (in percentage)

Total Cross Sectional Area [# x (Number of Scans) =

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Total Cross Sectional Area'/ 76 x (Number of Scans) J = 3 51 (% Factor)

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DETERMINING TIIE CUMULATIVE TOTAL OF WELD VOLUME INSPECTED (in percentage)

Total Cross Sectional Area I 74 x (Number of Scans) 2 = 3,61- (96 Factor)

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