Text

Forwards Request for Relief 99-01,which Provides Results of Limited Weld Exams for End of Cycle 9 Refueling Outage,For Welds Where Complete Coverage Could Not Be Obtained
	ML20199L492
Person / Time
Site:	Catawba
Issue date:	01/18/1999
From:	Gordon Peterson; DUKE POWER CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	NUDOCS 9901280024
	Download: ML20199L492 (57)
	v • d • e

h Duke Energy Corporation

((b.

Catawba Nudear Station

=

4800 Concord Road York, SC 29745

' (803) 831-4251 OH7CE l

Gary R. Peterson Vice hident (803) 8313426rax January 18, 1999 U.S. Nuclear Regulatory Commission Attention:

Document Control Desk Washington, D.C.

20555

Subject:

Catawba Nuclear Station, Unit 2 Docket Number 50-414 Request for Relief 99-01 Limited Weld Examination Results for End of Cycle 9 Refueling Outage Please find attached the subject request for relief.

This request provides the results of limited weld examinations from the subject outage, for those welds where complete coverage could not be.obtained.

Please approve this request for relief at your earliest convenience.

If you have any questions concerning this information, please contact L.J.

Rudy at (803) 831-3084.

Very truly yours,

,Peterson e ary LJR/s Attachment i

\\*b 00 95,0 9901280024 990118 A

PDR ADOCK 05000414 Y

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a U.S. Nuclear Regulatory Commission.

Page 2 January 18, 1999 i

xc,(with attachment):

L.A.

Reyes

.U.S.; Nuclear Regulatory Commission Regional Administrator, Region II o

Atlanta Federal Center I

!61 Forsyth St.,

SW, Suite 23T85

' Atlanta, GA 30303 t

.D.J.

Roberts

'I Senior Resident Inspector (CNS)

U.S. Nuclear Regulatory Commission Catawba Nuclear Station I

P.S. Tam NRC Senior Project Manager (CNS)

U.S. Nuclear Regulatory Commission l

Mail Stop O-14H25 Washington, D.C. 20555-0001 l

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Request for Relief Serial No. 99-01 Page 1 of 8 DUKE ENERGY CORPORATION STATION: CATAWBA NUCLEAR STATION UNIT 2 10-YEAR INTERVAL REQUEST FOR RELIEF NO. 99-01 1.

System / Component (s) for Which Relief is Requested:

I ASME Section XI Code Class 1 Examination Category : B-D Full Penetration Welds Of Nozzles in Vessels - Inspection Program B, ASME Section XI Code Class 2 Examination Category : C-A Pressure Retaining Welds in Pressure Vessels and ASME Section XI Code Class 2 Examination Category : C-B Pressure Retaining Nozzle Welds in Vessels.

Weld Number item Number 2PZR-W2 B03.120.002 2PZR-W4C B03.120.006 2ARHRHX-5-9 C01.010.007 2ARHRHX-5-A C02.021.006 2ARHRHX-5-B C02.021.007 11.

Code Requirement:

ASME Section XI 1989 Edition; Examination Category : B-D Full Penetration Welds Of Nozzles in VesseIs - Inspection Program B, Table IWB-2500-1, l

Item Number 803.120; Examination Category : C-A Pressure Retaining Welds in Pressure Vessels, Table IWC-2500-1, item Number C01.010; and Examination Category : C-B Pressure Retaining Nozzle Welds In Vessels, Table IWC-2500-1, item Number CO2.021 require a volumetric examination of essentially 100% of the weld volume. Duke Energy Corporation, with NRC approval, has adopted Code Case N-460 which defines " essentially 100%"

as greater than 90% coverage.

Request for Relief Serial No. 99-01 Page 2 of 8 Ill.

Code Requirement from which Relief is Requested:

Relief is requested for the above identified Weld ID Numbers:

Class 1 Pressurizer Spray and Safety Nozzle Inner Radius, from meeting the coverage requirements as defined in 1989 ASME Section i

XI, No Addenda; Figure IWB-2500-7 (b), Examination Volume M-N-O-P.

Class 2 Residual Heat Removal Heat Exchanger 2A Shell To Flange Weld, from meeting the coverage requirements as defined in 1989 ASME Section XI, No Addenda; Figure IWC-2500-1(a), Examination Volume A-B-C-D.

Class 2 Residual Heat Removal Heat Exchanger 2A Inlet and Outlet Nozzle to Shell Welds, from meeting the coverage requirements of 1

Appendix lil, Paragraph lll-4420 of 1989 ASME Section XI, No i

Addenda, as modified by Code Case N-460.

IV.

Basis for Relief During the ultrasonic examination of the Pressurizer Spray Nozzle Inner Radius 2PZR-W2 (item No. B03.120.002) and Pressurizer Safety Nozzle Inner Radius 2PZR-W4C (item Number B03.120.006) shown in Attachment 1, greater than 90% coverage of the required examination volume could not be obtained. Limitations caused by the ratio of the nozzle OD to the vessel thickness resulted in 66.14%

coverage of the required volume. When the nozzle OD is smallin relation to the vessel thickness, more coverage can be obtained when nanning from the vessel side. Conducting examinations from the nozzle boss and OD blend radius using compound angles, determining which angles to use and metal paths to calibrate the areas of coverage 4

are not accurate with manual calculations. Duke Energy is investigating the use of computer modeling to solve the limitation problems. Radiography is not practical because of the geometry of the component, which prevents placement of the film and exposure source.

Nozzle inner radius sections are examined with the ultrasonic method to the extent practical from the vessel wall. Calibration blocks and procedures are in accordance with ASME Section V, Article 4.

i

Request for Relief Serial No. 99-01 Page 3 of 8 During the radiographic examination of the Residual Heat Removal Heat Exchanger 2A Shell to Flange Weld 2ARHRHX-5-9 (Item No.

j C01.010.007) shown in Attachment 1, greater than 90% coverage of j

the required examination volume could not be obtained. The radiographic examination coverage was limited to 62% due to the shell-to-flange configuration and intemal divider plates. In order to achieve greater than 90% coverage of the required volume, all flange bolting would have to be removed, the weld re-designed to allow access from both sides, and ultrasonic examination techniques employed.

During the ultrasonic examination of the Residual Heat Removal Heat Exchanger 2A Inlet Nozzle to Shell Weld 2ARHRHX-5-A (Item Number CO2.021.006), and Residual Heat Removal Heat Exchanger 2A Outlet Nozzle to Shell Weld 2ARHRHX-5-B (Item Number CO2.021.007) shown in Attachment 1, greater than 90% coverage of the required examination volume could not be obtained. Single-sided access prevented scanning from the nozzle side of the weld. The reported coverage for these welds is 62%.

Austenitic metal weld characteristics mandate the use of refracted longitudinal waves. This type of ultrasonic wave produces mode conversion at the pipe inside surface, thus preventing the use of sound path distances beyond the first " leg". Therefore, coverage of the required examination volume in two-beam path directions is not practical. In order to achieve more coverage, the weld would have to be re-designed to allow scanning from both sides. Radiography is not practical because of the geometry of the component, which prevents i

placement of the film and exposure source.

Ultrasonic calibration blocks and procedures are in accordance with ASME Section XI, Appendix Ill.

1 Request for Relief Serial No. 99-01 Page 4 of 8 L

V.

Alternate Examinations or Testing:

L No additional examinations are planned during the current interval for Weld ID Numbers 2PZR-W2 and 2PZR-W4C. The use of radiography as an altemate volumetric examination method is not practical due to component thickness and geometric configurations.

l No additional examinations are planned during the current interval for l

Weld ID Number 2ARHRHX-5-9. The use of ultrasonic testing (UT) as an attemate volumetric examination was evaluated. With only a one-sided examination possible, it was determined that the maximum potential coverage obtainable with UT is 69%, a 7% increase over the radiographic results. However, to achieve the 7% increase, all 52 flange fasteners would have to be removed for weld access. See, Pages 1 through 4, for limited inspection calculations.

Site engineering evaluated the removal of the HX body flange bolting.

It was recommended that only 39 of the 52 total fasteners be removed due to the possibility that 13 fasteners, which are engaged in threaded tubesheet holes, could gall during removal and become immobilized.

Specialty procedures and drill equipment would be required for repairs of any immobilized fasteners. By limiting the number of fasteners that could be removed, maximum UT coverage achievable would be reduced below 69%.

Performing UT would require significant additional workforce resources to remove heat exchanger bolting and would increase radiation exposure. The small benefit derived from UT does not result in a

{

compensating increase in the level of plant safety or quality.

Therefore, UT is not a practical attemative.

No additional examinations are planned during the current interval for Weld ID Numbers 2ARHRHX-5-A and 2ARHRHX-5-B. The use of radiography as an altemate volumetric examination method is not practical due to component thickness and geometric configurations.

Duke Energy Corporation will continue to use the most current radiography and ultrasonic examination techniques that maximize coverage to the extent practical for the Weld ID Numbers referenced in Section 1 of this request for l-relief.

l

Request for Relief Serial No. 99-01 Page 5 of 8 VI.

Justification for the Granting of Relief :

i Pressurizer Sorav and Safety Nozzle Inner Radius Although the examination volume requirements as defined in ASME Section 3

XI 1989 Edition, Figure IWB-2500-7, Examination Volume M-N-O-P for Weld lD Number 2PZR-W2 (Item Number 803.120.002), and Weld ID Number 2PZR-W4C, (ltem Number B03.120.006) could not be met, the amount of coverage obtained for these examinations provides an acceptable level of J

quality and integrity. For results of the examinations, reference Attachment 2, Pages 1 through 5 and Attachment 3, Pages 1 through 5 respectively.

These nozzles are located inside containment and are part of the reactor coolant system pressure boundary. General Design Criterion 30, " Quality of Reactor Coolant Pressure Boundary," of Appendix A to 10 CFR Part 50,

" General Design Criteria for Nuclear Power Plants," mandates that means be provided for detecting and, to the extent practical, identifying the location of the source of reactor coolant leakage. If a leak were to develop at these weld locations discussed in this relief request the instrumentation available to the operators for detection and monitoring of leakage would provide a prompt and qualitative information necessary to permit them to take immediate corrective action. If a leak should develop in these aforementioned locations the only corrective action would be shutdown and depressurize the reactor coolant system since the welds are non-isolatable.

i Plant Technical Specifications dictate that a reactor coolant system water inventory balance be performed on a regular basis. A normal operating practice is to perform this computer based mass balance on a daily frequency and/or whenever the operators suspect any abnormal changes to other leakage detection systems. Plant Technical Specification requires that if the leak rate cannot be reduced below 1 gpm unidentified f. hat the plant be put in hot standby within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in cold shutdown within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . Leakage as a result of a failed weld discussed in this section would show up as unidentified leakage and subject to the 1 gpm limit.

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Request for Relief Serial No. 99-01 Page 6 of 8 Other leakage detection systems available to the operator and dictated per plant technical specifications are :

Containment Atmosphere Gaseous and Particulate Radioactivity Monitoring System (EMF monitors 38 & 39) which would detect airborne radiological activity; Containment Floor and Equipment Sump Level and Flow Monitoring e

Subsystern where unidentified accumulated water on the containment floor would be monitor m ond evaluated as sump level changes; Containment Ventilation Unit Condensate Drain Tank Level Monitoring Subsystem which collects and measures as unidentified leakage the moisture removed from the containment atmosphere.

Additionally, other indicators are also available to the operator that a leak exists or may be developing:

Containment Atmosphere lodine Monitor (EMF 40)

Charging / Letdown system mismatches; Containment humidity indications; e

Pre-Cycle walkdowns performed each outage while system is at operating temperature and pressure prior to criticality; Post-Cycle walkdowns performed at operating temperature and pressure performed during unit shutdown.

Residual Heat Removal Heat Exchanaer 2A Shell to Flanae Weld Although the examination volume requirements as defined in ASME Section XI 1989 Edition, Figure IWC-2500-1(a), Examination Volume A-B-C-D for Weld ID Number 2ARHRHX-5-9 (Item Number C01.010.007) could not be met, the amount of coverage obtained for this examination provides an acceptable level of quality and integrity. For results of the examinations, Reference Attachment 4, Pages 1 through 6.

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j Request for Relief Serial No. 99-01 Page 7 of 8 Residual Heat Removal Heat Exchanoer 2A Inlet and Outlet Nozzle to Shell Welds l

Although the examination volume requirements as defined in ASME Section XI 1989 Edition, Appendix Ill, Paragraph lll-4420, for Weld ID Number 2ARHRHX-5-A (Item Number CO2.021.006) and Weld ID Number 2ARHRHX-5-B (l tem Number CO2.021.007) could not be met, the amount of coverage obtained for these examinations provides an acceptable level of l

quality and integrity. For results of the examinations, reference Attachment 5, Pages 1 through 13 and Attachment 6, Pages 1 through 13 respectively.

The ND Residual Heat Removal Hx is not used in power operations, but during normal Unit shutdown to cool NC system and to maintain NC system cooling during Unit refueling operations and'during emergency in the event of a LOCA. The ND Residual Heat Removal Hx is located in the Auxiliary Bldg in the ND and NS Hx Rooms for each train and Unit. During power operations and Unit refueling outages, the ND Hxs are accessible for visual inspections. When not in service during power operations and in ' standby i

readiness,' the ND Residual Heat Removal Hxs are isolated on the ND system tubeside from the NC system pressure by boundary check valves and t

static pressure is approximately 50 to 60 psig.

If a leak were to occur at the welds in question (channel barrel circumferential weld to the channel flange bolting ring or channel barrel inlet / outlet nozzles),

there are several periodic tests and evaluations that are performed by established procedures that should identify the leakage for prompt OPS /ENG evaluation:

in the ' Standby Readiness' mode, the Hx is isolated from the Reactor e

Coolant System (NC), and if a leak were to occur at the subject welds, the water would spill on floor in ND / NS Hx room and flow to floor drain and then to Floor Drain Tank. Our Chemistry department periodically monitors the tank level and evaluates unidentified leakage for correction.

Periodically, visual material condition inspections in accordance with NSD 104 are made in the Hx rooms by the site owner of the Aux Bldg Elev 577 l

area. Identified leakage would be reported for evaluation.

At a frequency of each refueling outage, visualleakage inspections of the RHR system with RHR Pumps in service are made per PT procedure PT/1 or 2/A/4202/002, " Leak Rate Determination for ND Systern." Any r

l RHR components identified with extemal leakage are documented for evaluation,' including the RHR Hxs.

i

Request for Relief Serial No. 99-01 Page 8 of 8 If a leak were suspected from the subject RHR Hx weld joint while Hx inservice during a normal plant cooldown, control room operated valves could be actuated to isolate the Hx and stop the leakage to maintain NC system inventory and Reactor protecnon.

Vll. 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 2.

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, Description Table UT Examination Data B03.120.002 UT Examination Data B03.120.006 RT Examination Data C01.010.007 UT Examination Data CO2.021.006 UT Examination Data C02.021.007 UT Limited Examination Coverage Worksheet C01.010.007

Request for R: lief Serial No. 99-01 Page 1 of 1 ASME Class 1 & 2 Inservice Inspection Request For Relief No. 99-01 For Catawba Unit 2 Based on ASME Section XI-1989 Code Ucensee item No.

Exam Category System Or Area To Be Reason For Request Proposed Altemate

/ Figure No.

Component Examined Examination B03.120.002 B-D Pressurizer Pressurizer Limited scan due to ratio of the nozzle OD to the None IWB-2500-7(b)

Spray Nozzle vessel thickness Inner Radius Actual coverage obtained = 66.14%

(See Attachment 2)

B03.120.006 B-D Pressurizer Pressurizer Umited scan due to ratio of the nozzle OD to the None IWB-2500-7(b)

Safety Nozzle vessel thickness inner Radius Actual coverage obtained = 66.14%

(See Attachment 3)

Residual C01.010.007 C-A Residual Heat Heat Limited radiographic examination due to shell to flange None IWC-2500-1 Removal Heat Removal configuration and intemal divider plates (a)

Exchanger Heat Actual coverage obtained = 62%

Exchanger (See Attachment 4) 2A Shell to Flange CO2.021.006 C-B Residual Heat RHR Heat Umited scan due to single sided access None Appendix Ill Removal Heat Exchanger Actual coverage obtained = 62%

Paragraph lil-Exchanger 2A Inlet (See Attachment 5) 4420 Nozzle to Shell CO2.021.007 C-B Residual Heat RHR Heat Umited scan due to single sided access None Appendix ill Removal Heat Exchanger Actual coverage obtained = 62%

Paragraph fli-Exchanger 2A Outlet (See Attachment 6) 4420 Nozzle to Shell

DUKE POWER COMPANY Exam Start:

1301 Form NDE-UT-2A ULTRASONIC EXAMINATION DATA SHEET FOR PLANAR RIFLECTORS Exam Finish:

1358 Revision 4 Station:

Catawba Unit:

2 Component / Weld ID: 2PZR-W2 Date:

9/25/98-Weld Length (in.):

N/A Surface Condition:

AS GROUND Lo:

9.2.3 Surface Temperature:

72

F Examiner James H. ResodQJevel:

11 Scans:

Pyrometer S/N:

MCNDE 27021 Examiner Winfred C. Leeper d Mvel{ 11 45 O dB 70 0 70.2 dB 7

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Configurat,on:

Inner Rad,ius i

Procedure: NDE-680 dev: 1 FC:

45T O dB 70T O dB N/A Flow N/A N/A 60 0 69 dB N/A to N/A Calibration Sheet No:

60T O dB 11,

"'I 9802082,9802083 E

Other dB Skew Angle:

Max Mp W

L Beam Exam IND# 4 Max Max Max L1 L2 W1 Mp1 W2 Mp2 Dir.

Surf.

Scan Damps Ref 20%dac 20%dac 20%dac 20%dac 20%dac 20%dac DO NOT W31TE HMA HMA HMA HMA HMA HMA DO NOT WRIT s /oda s /.d 50%da 50%da 50%dac 50%dac IN THIS SPACE IN TilS S P' ACE 100%dac 100%dac 100%dac 100%dac 100%dac 100%dac NRI Remarks:

Limitations: (see NDE-UT-4) O 90% or greater coverage obtained: yes O no O Sheet /

of f Reviewed By:

Level:

Date:

Au orized Inspect.

Date:

Item No:

Larry Mauldin gfjggy.

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Limited Examination Coverage Worksheet h

I Examination Volume / Area Defined O Base Metal O w eld O Near Surface O Bolting El Inner Radius Area Calculation Volume Calculation Pi X Rad.sqdi 4-Pi X 1.2 sqd14 = 4.52=

Pi X 12.75" = 40 sq.in.

1.13 sq.in.

40 sq.in. X 2.54 sq.in.= 101.6 cu.in.

Pi X Rad.sqdi 4 = Pi X.5 sqd. / 4 =.785 / 4 =.196 =

.2 sq.in 1.13 sq.in..2 sq.in.=.93 sq.in.

.93 sq.in. + ( 2.3" X.7")= 2.54 sq.in.

Coverage Calculations Area Length Volume Volume in d hamined hadnM Rguired Scan # Angle Dr on Percent Coverage (sq.in.)

(in.)

(cu.in.)

1 60/70 cw 1.68 40 67.2 101.6 66.14 2

60/70 ccw 1.68 40 67.2 101.6 66.14 item No:

B03.120.002 Prepared By: W.C. Leeper

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DUKE POWER CLMPANY Exam Start 1301 Form NDE-UT-2A ULTRASONIC EXAMINATION DATA SHEET FOR PLANAR REFLECTORS Exam Finish: 1358 Revision 4 Station: Catawba Unit: 2 Component / Weld ID: 2PZR-W4C Date: 9/25/98 Weld Length (in.): N/A , Surface Condition: AS GROUND Lo: 9.2.3 Surface Temperature: 72 F Examinen James H. Reso ,Leel: ll Scans: Pyrometer S/N: MCNDE 27021 Examinen Winfred C. Leepef [v,el: 11 45 O dB 70 8 70.2 dB f sf Configuration: Inner Radius i Procedure: NDE-680 Rev: 1 FC: 45T O dB 70T O dB N/A Flow N/A N/A 60 G 69 dB N/A to N/A Calibration Sheet No: 60T O dB 9802082,9802083 App i s to ND 80 only Othec dB Skew Angle: 11' Max Mp W L Beam Exam IND# 4 Max Max Max L1 L2 W1 Mp1 W2 Mp2 Dir. Surf. Scan Damps Ref 20%dac 20%dac 20%dac 20%dac 20%dac 20%dac DO NOT WRITE HMA HMA HMA HMA HMA HMA DO NOT WRIT 5 /oda 50 /oda 50%d 5 %da 50%dac 50%dac IN THIS SPACE IN TilS S P'4CE 100%dac 100%dac 100%dac 100%dac 100%dac 100%dac NRI Remarks: Limitations: (see NDE-UT-4) O 90% or greater coverage obtained: yes O no O Sheet / of 3 ~ Reviewed By: Level: Date: A orized ins ctoc Date: Item No: Larry Mauldin gghg [ glA jf.jg,k lil 9/27/98 B03.120.006 AS=amprAe AeW W-o/ MMYevf 3 f 0 ^

tn DUKE POWER COMPANY NDE-91-1 Limited Examination Coverage Worksheet 3 Revision 0 1 Examination Volume / Area Defined j O Base Metal O weld O Near Surface O Bolting O Inner Radius Area Calculation Volume Calculation j Pi X Rad.sqdi4 = Pi X 1.2 sqdl4 = 4.52= Pi X 15" = 47.12 sq.in. 1.13 sq.in. 47.12 sq.in. X 2.54 sq.in.= 119.68 cu.in. Pi X Rad.sqdi 4 = Pi X.5 sqd. / 4 =.785 / 4 =.196 = .2 sq.in 1.13 sq.in..2 sq.in.=.93 sq.in. .93 sq.in. + ( 2.3" X.7")= 2.54 sq.in. Coverage Calculations Area Length Volume Volume d Scan # Angle D tion Percent Coverage sq in ( n. ui ui 1 60/70 CW 1.68 47.12 79.16 119.68 66.14 2 60/70 CCW 1.68 47.12 79.16 119.68 66.14 l l i l l item No: B03.120.006 Prepared By: W.C. Leeper Level: ll Date: 9/25/98 Reviewed By: Larry Mauldin 3 ggf Level: 111 Date: 9/27/98 h

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FORM NDE-RT1 REVISION 2 RADIOGRAPHIC EXAMINATION TECHNIQUES Material: O CS EISS O Diameter 43.750" Thickness -.875" Source: EdR192 OCo60 Size l4 o in. Curies Ff' 6 SFD 27." Exposure Time: Hrs. X

Min. M
Sec. M
Estimated Weld build-up

'/4 " IQI Size 20 [3 film Side OSource Side Shim Size (s) WA W Film Brand / Type: Front Mi so Center WA Back Mi Ko Screen Thickness: Front dio " Center NA Back . o'o " A B G ysource i 1 source lyl Film / \\ j ( \\[ I I f '/ f Msource i s j g \\ I I ./ \\ Ir i I 1 ( r i f film I Film Superimp sed C D (Double Wall View) _H s wrce source ,,,c, / \\ f / \\ I r\\ i / \\ l r i t/'///HMH///A l "'" \\ [f, / Film \\ l I i w g 2 F / Film l source source 11 /lf / 11 %_ l (Other) 11 / 1l r, 3 / w/ see A HacAes Film; i i i. Shee+ Film Offset Offset 7 m d'm<M M s (Single Wall View) (Double Wall View) Approved Sbr 2 of 6

FORM NDE-RT1 REVISION 2 RADIOGRAPHIC EXAMINATION TECHNIQUES Material: O CS ISS O Diameter 43750" Thickness 875 Source: [HIR192 OCo60 Size l'40 in. Curies 7 'f' 6 SFD 2 7_ " 1 Exposure Time: Hrs. X

Min. M
Sec. M*

Estimated Weld build-up '//6 " IQI Size 2D [3 film Side O Source Side Shim Size (s) WA # Film Brand / Type: Front Eau 50 Center NA Back bli KG Screen Thickness: Front 080 " Center WA Back . o'o " _A _B _G yswrce I I source hfI / \\[ rilm / \\ j ( f / \\ M source l g y l \\, / \\ e rilm

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Superimp sed C D (Double Wall View) H s=rce ff swrce I \\ i' /\\ I r\\ i / \\, l r YMMMMMA / l. [,1 \\ 1 ,/ Film ' \\, / t g i / nlm ' smrce smrce f 11 /ll II / l11 11 (Other) / l is l l ,I / SeeALched x S4ect rilm; i rilm offset Offset ug,, gj.4 (Single wall view) (Double Wall View) Approved D l .SHT J of 6 0

l l l R:disgr phic Tcchniqu3 i l Item: C01.010.007 ID: 2ARHRHX-5-9 Date: 09/22/98 I Approved: /L/< M l l Film 1 Typical Film Placement 11 4 j/ 2;' i y,;-) g

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j 3 1 / s s )f 4 g), Typical Film Placement / l s Film ] , / Exoosure Times f s-J 0-1 6 Min. s s s s s u, 8 } ^ l 1-2 6 Min. 3 2-3 6 Min. s y a 3-4 6 Min. / 4-5 6 Min. s 5-6 6 Min. / 16.5 Min. 7 6-7 16.5 Min. 6 7-8 11 Min. Typical Film Placement 8-9 11 Min. 9-10 11 Min. 10 -11 11 Min. 11 -12 11 Min. 12-13 16.5 Min. 13-0 6 Min. /16.5 Min. l fl~ f Of h

l 1 1 DUKE POWER COMPANY NDE-91-1 Limite'd Examination Coverage Worksheet Revision 0 ? - = _w.-n__-~~_n--.. -. - - ~.. - - ~.. i Examination Volume / Area Defined l Base Metal [ Weld [ Near Surface'O Bolting O Inner Radius O. Area Calculation Volume Calculation i Reparolatest = 248.45 sq.!N. AFe4 ofco%e c (St/./ Sq. m, 154. I + E4 6.4.5 X100 = G 7-. % M.See No1es Coverage Calculations Area Length Volume Volume Beam Scan # Angle Examined Examined Examined Reqdred Percent Coverage Direct.on (sq.in.) (in) (cu.in.) (cu.in ) % No1es : 1. utred 4m Calcuhf[on: deld length = I41.9& " Qeld wnd% =.750" Bue mda.I = I" (. 6" cask sedc of weld ) I 41. 96 X I 75 " = 2 H S. 4 5 So. m.

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MARK S17.E SCH RATING P paq Ak CNM lzol, a 4 - CD 38

l DUKE POWER COMPANY Exam Start 1312 NDE-UT-3A -l l ULTRASONIC EXAMINATION DATA SHEET FOR LAMINAR REFLECTORS l Exam Finish: 1320 Revision 2 l Station: l Component / Weld ID: Catawba Unit 2 l 2ARHRHX-5-A Date: 10/5/98 l Nominal MaterialThickness (in): l Weld Length (in.): .375 71" Surface Temperature: 83 Deg F l l l Measured MaterialThickness (in): l Lo: .410 9.2.3 Pyrometer S/N: MCNDE 27010 l Surface Condition: AS GROUND Calibration Sheet No: Cal Due: 1/14/99 l Examiner B.DateJolly g fjf p/ l Configuration: VESSEL TO NOZZLE [ Level: II l Examiner: Winfred C. Leeper ',; /3Av,e{ 11 l S1 Flow S2 l Procedure: NDE-640 dev: FC] l VESSEL to NOZZLE Ampi L1 W1 Mp1 W2 Mp2 L2 W1 Mp1 W2 Mp2 0 2 rem 2 rem 2 rem 2 rem 2 rem 2 rem 2 rem 2 rem 2 rem a rem 2 rem Exam NO. 4 BW BW BW BW BW BW BW BW BW BW BW Surf. amps LOB LOB LOB LOB LOB LOB LOB LOB LOS LOB LOB { l"" l l l l I l \\ 1 [ i Remarks:

95-18,95-19 Limitations:

see NDE-UT-4 0 None: O Sheet / of /3 f Reviewed By: Level: Date: Au inspect f Date: ltem No: ' 111 10/7/98 JT/ ///f9h CO2.021.006 Larry Mauldin M L) [ &D[$$ lW f Y- + ?

.j~ _y DUKE POWER COMPANY _ NDE 6 5 UT PROFILE / PLOT SHEET Revision 1 i EXAMINATION SURFACE 1 EXAMINATION SURFACE 2 4 3 2 1 .t ,g$h 2 3

4. "

\\ N s N il i i I i.%g, s .5 'l l 1.5 ~[ 2 l 4 - 2.5 t 3 Component \\D/ Weld No. gg pyggy.pp U

Remarks:

Profile taken I 270! at: ou/r-A 90 l item No: 602.021, 66(, Examiner:///M[f(/dem Level: l[ Date:n 45 Reviewed By: # Ku ?f7tm,//m Level:Jp Date:/e 7-9# i 189 sheet 2 oyj l Authorized insp6ctor: 4 M Mgfh Date:u jf.Qi h' d i

L DUKE POWER COMPANY Exam Start 1339 Form NDE-UT-2A ULTRASONIC EXAMINATION DATA SHEET FOR PLANAR REFLECTORS Exam Finish: 1431 Revision 4 i Station: Catawba Unit: 2 Component / Weld ID: 2ARHRHX-5-A Date: 10/5/98 Weld Length (in.): 71" Surface Condition: AS GROUND Lo: 9.2.3 Surface Temperature: 83

' F Examiner: B.DaleJolly gff Q Level: ll Scans:

Pyrometer S/N: MCNDE 27010 - l I Winfred C. Leeper/f/,,k ge, vel: ll 45 8 48 dB 70 O dB Examiner: Configuration: Nozzle to Vessel Procedure: NDE-630 kev: 2 FC: 45T C 41.5 dB 70T O dB vessel Flow Nozzle N/A 60 O dB S1 to S2 Calibration Sheet No: 60T O dB i 9802121,9802122,9802124 Applies to NDE-680 only Other-30*L-49 dB Skew Angle: N/A Max Mp W L Beam Exam IND# 4 Max Max Max L1 L2 W1 Mp1 W2 Mp2 Dir. Surf. Scan Damps Ref l t 20%dac 20%dac 20%dac 20%dac 20%dac 20%dac DO NOT WRIT:.- DO NOT WRITE HMA -HMA-HMA HMA HMA HMA 5 Ma 50 M ac 50Mac 50 M ac 50Mac 50%dac IN THIS SPACE IN T ilS SP'4CE 100%dac 100%dac 100%dac 100%dac 100%dac 100%dac NRI r j. Remarks: Limitations: (see NDE-UT-4) B 90% or greater coverage obtained: yes O no B Sheet 3 of/3 i Reviewed By: Level: Date: A crized Ins f: Date: Item No: Larry Mauldin , f f,,l/d ill 10/7/98 jg /d/h CO2.02i.C')6 O h)

FORM NDE-UT DUKE POWER COMPANY ISI LIMITATION REPORT Revision 1 Component / Weld ID: 2ARHRHX-5-A Item No: CO2.021.006 Remarks: SURFACE BEAM DIRECTION DUE TO NOZZLE TO VESSEL G NO SCAN CONFIGURATION. O LIMITED SCAN O1 02 01G2 8 cw B ecw FROM L, _ _6f'_ _, to L _ 415" _ INCHES FROM WO,_ _.3"_ _, to _ B_E_ YOND,_ ANGLE: 8 o G 45 5 60 0 Other FROM, _ _ _ DEG to, _ _, _DEG O NO SCAN O LIMITED SCAN O1 02 0 10 2 O cw0 ccw FROM L to L INCHES FROM WO to ANGLE: O o O 45 0 60 0 Other FROM,_ _ _ DEG to _ _ _ _DEG O NO SCAN O LIMITED SCAN O1 02 0102 O cw O ccw FROM L toL INCHES FROM WO to ANGLE: O o O 45 O so O Other FROM. _ _ _ DEG to _ _ __._DEG O NO SCAN O LIMITED SCAN O1 02 0102 O cw 0 ccw l FROM L to L INCHES FROM WO, _ _ _ _ _, to _ _ _ _ _ _ ANGLE: O o O 45 0 so O Other FROM DEG to Prepared By: W.C. Leeper h g Level: 11 Date: 10/5/98 Sketch (s) attached @ yes O no Sheet t/ of/3 Authorized inspector: [ fyyh Date:f 37f,g Reviewed By: Larry Mauldin V, Date: 10/7/98 g

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DUKE POWER COMPANY NDE-91-1 n Limited Examination Coverage Worksheet Revision 0 g Examination Volume / Area Defined S Base Metal G Weld O Near Surface O Botting O Inner Radius Area Calculation Volume Calculation .125" X.7" =.09 sq.in. .09 sq.in.X 71" = 6.39 cu.in. 71" / 3 (Profiles) = 23.67" each 23.67" X.09 sq.in. = 2.13 cu.in for each profile Coverage Calculations Area Length Volume Volume d Req d Scan # Angle D rec on ql ) (. u in ) (eu i ) Percent Coverage Profile

3 0.00 1

45/60 1 .05 23.67 1.18 2.13 55.40 2 45/60 2 0 23.67 0 2.13 0.00 3 45 CW .04 23.67 0.95 2.13 44.60 i 4 45 CCW .04 23.67 0.95 2.13 44.60 (VOLUME EXAMINED) 15.85 / (VOLUME REQUIRED) 25.56 X 100 = 62% AGGREGATE COVERAGE i l I Item No: CO2.021.006 Prepared By: W.C. Leeper / Level: 11 Date: 10/6/98 Reviewed By: Larry Mauldin Level: 111 Date: 10/6/98 h

l l DUKE POWER COMPANY NDE-91-1 Q Limited Examination Coverage Worksheet b Rev..ision 0 p i l Examination Volume / Area Defined l 0 Base Metal O weld O Near Surface O Bolting - O Inner Radius Area Calculation Volume Calculation .125" X.7" =.09 sq.in. .09 sq.in.X 71" = 6.39 cu.in. 71" / 3 (Profiles) = 23.67" each l 23.67" X.09 sq.in. = 2.13 cu.in for each profile l Coverage Calculations Area Length Volume Volume d d d Scan # Angle D rec on Percent Coverage (sq.in.) (in.) (cu.in.) (cu.in.) I Profile

1 0.00 1

45/60 1 .08 23.67 1.89 2.13 88.73 2 45/60 2 0 23.67 0 2.13 0.00 l 3 45 CW 05 23.67 1.18 2.13 55.40 4 45 CCW .05 23.67 1.18 2.13 55.40 Profile

2 0.00 1

45/60 1 .09 23.67 2.13 2.13 100.00 2 45/60 2 .09 23.67 2.13 2.13 100.00 3 45 CW .09 23.67 2.13 2.13 100.00 ) l 4 45 CCW .09 23.67 2.13 2.13 100.00 (VOLUME EXAMINED) 15.85 / (VOLUME REQUIRED) 25.56 X 100 = 62% AGGREGATE COVERAGE Item No: CO2.021.006 Prepared By: W.C. Leeper h Level: ll Date: 10/6/98 Reviewed By: Larry Mauldin Level: lli Date: 10/6/98 g, v \\

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l DUKE POWER COMPANY Exam Start 1302 NDE-UT-3A ULTRASONIC EXAMINATION DATA SHEET FOR LAMINAR REFLECTORS l Exam Finish: 1310 Revisien 2 l Station: l Component / Weld ID: Catawba Unit 2 l 2ARHRHX-5-B Date: 10/5/98 l Nomina! MaterialThickness (in): l Weld Length (in.): 71" Surface Temperature: 83 Deg F l .375" l Measured MaterialThickness (in): lLo: .410 9.2.3 Pyrometer S/N: MCNDE 27010 l Surface Condition: l Calibration Sheet No: Cal Due: 1/14/99 AS GROUND l Configuration: NOZZLE TO VESSEL Examiner: B. Dale Jolly gg a /L Level: 11 l Examiner. Winfred C. Leeper/fh gg II l S1 Flow S2 l Procedure: NDE-640 Mev: 1 N: l VESSEL to NOZZLE Ampi L1 W1 Mp1 W2 Mp2 L2 W1 Mp1 W2 Mp2 IND 2 rem 2 rem 2 rem 2 rem a rem 2 rem 2 rem a tem a rem a rem 2 rem Exam NO. 4 BW BW BW BW BW BW BW BW BW BW BW Surf.

- E*

LOB LOB LOB LOB LOB LOB LOB LOB LOB LOB LOB i t Remarks:

95-18,95-19_

Limitations: see NDE-UT-4 @ None: O Sheet / of /3 f Reviewed By: Level: Date: A 'zedins or Date: Item No: I Larry Mauidin // p III 10/7/98 A7 /#./1r 9 ( CO2.021.007 Ll 'I ON[ b ~ l f:

s DUKE POWER COMPANY NDE-UT-5 UT PROFILE / PLOT SHEET - Revision 1 EXAMINATION SURFACE 4 3 7-EL EXAMINATION SURFACEg 2 1 4. . 1hff 2 3-4 # N [ T'~, ,,~~, .5 { I 1 l i 1.5 2 [ t 2.5 Component ID/ Weld No. g pppgy f.,3 0

Remarks:

l Profile taken 270 at: a kA-90 l item No: C(),2. t%2/,007 ' I Examiner://EIMB_f_ Level:X Date:/044f Reviewed By: #fffjjr C/fy'zygg Level: Y Date:/op.9/ Authorized In'spectop. M p%;2Q/ Date:101f.9d 180 sheet.2 of/3 i \\

' DUKE POWER COMPANY Exam Start: 1325 Form NDE-UT-2A' ULTRASONIC EXAMINATION DATA SHEET FOR PLANAR REFLECTORS Exam Finish: 1415 - Revision 4 Station: Catawba Unit 2 Component / Weld ID: 2ARHRHX-5-B Date: 10/5/98 Weld Length (in.): 71" Surface Condition: AS GROUND Lo: 9.2.3 Surface Temperature: 83 F Examiner: B. Dale Jolly g g~ Level: 11 Scans: Pyrometer S/N: MCNDE 27010 CalDue-1/14/99 Winfred C.Leeper/jU~ [fyyOl 45 B 48 dB 70 O dB ~ Examiner: Configuration: Nozzle to Vessel Procedure: NDE-630 kev: 2 FC: 45T E 41.5 dB 70T O dB y,,,,, 73,, g,,,,, N/A 60 O dB si to s2 Scan Surface: OD Calibration Sheet No: 60T O dB Applies to NDE-680 only 9802121,9802122,9802124 Other: 60*L-49 dB Skew Angle: N/A Max Mp W L Beam Exam IND# 4 Max Max Max L1 L2 W1 Mp1 W2 Mp2 Dir. Surf. Scan Damps Ref 20%dac 20%dac 20%dac 20%dac 20%dac 20%dac DO NOT WRIT : DO NOT WRITE HMA HMA HMA HMA HMA HMA 5 Ma 50Ma 5 %da 5 %da 5 Ma 5 %da IN THIS SPACE IN T ilS SP 4CE 100%dac 100%dac 100%dac 100%dac 100%dac 100%dac NRI i Remarks: Limitations: (see NDE-UT-4) B 90% or greater coverage obtained: yes O no G Sheet 3 of /T Reviewed By: Level: Date: A rized ins or. Date: Item No: h Larry Mauldin pM j',j/.g8 CO2.021.007 lil 10/7/98 d 0 \\ )

FOM Nm DUKE POWER COMPANY 1 ISI LIMITATION REPORT Revision 1 Component / Weld ID: 2ARHRHX-5-B ltem No: CO2.021.007 Remarks: SURFACE BEAM DIRECTION DUE TO NOZZLETO VESSEL 8 NO SCAN CONFIGURATION. O LIMITED SCAN 81 02 0182 8 m a em FROM L,_ 29f_ _, to L _ _6g_ _ INCHES FROM WO,_ _.3"_ _, to _ B_E_YO_ND_ _ ANGLE: 80 8 45 O 60 0 Other FROM,_ _ _ DEG to _ _ _ _DEG SURFACE BEAM DIRECTION OOM O LIMITED SCAN O1 02 0102 O m O em FROM L to L INCHES FROM WO to ANGLE-O o O 45 0 so O Other FROM, _ _ _ DEG to _ _ _ _DEG SURFACE BEAM DIRECTION OEM O LIMITED SCAN O1 02 0 10 2 O cw0 cm FROM L to L INCHES FROM WO to ANGLE-O o O 45 O so O Other FROM. _ _ _ DEG to _ _ _ _DEG SURFACE BEAM DIRECTION O W SN O LIMITED SC/;, O1 02 0102 O cw 0 ccw FROM L to L INCHES FROM WO to ANGLE-O o O 45 0 so O Other FROM, _ _ _ DEG to _ _ _ _ Prepared By: W.C. Leeperfj [L,evel: il Date: 10/5/98 Sketch (s) attached Q yes O no Sheet V of [3 Reviewed By: Larry Mauld [gjg, ate: 10/7/98 Authorized Inspector g' Date:/g,JQ 0 J

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m DUKE POWER COMPANY NDE-91-1 N Limited Examination Coverage Worksheet b Revision 0 Examination Volume / Area Defined B Base Metal 8 ' W eld O Near Surface O Bolting O Inner Radius Area Calculation Volume Calculation .125" X.7" =.09 sq.in. .09 sq.in.X 71" = 6.39 cu.in. 71"/ 3 (Profiles) = 23.67" each 23.67" X.09 sq.in. = 2.13 cu.in for each profile Coverage Calculations Area Length Volume Volume nd Examined Requked Scan # Angle D rect on Percent Coverage (sq.in.) (in.) (cu.in.) (cu.in.) Profile

1 0.00 1

45/60 1 .08 23.67 1.89 2.13 88.73 2 45/60 2 0 23.67 0 2.13 0.00 3 45 CW .05 23.67 1.18 2.13 55.40 4 45 CCW .05 23.67 1.18 2.13 55.40 Profile

2 0.00 l

1 45/60 1 .09 23.67 2.13 2.13 100.00 2 45/60 2 .09 23.67 2.13 2.13 100.00 3 45 CW .09 23.67 2.13 2.13 100.00 4 45 CCW .09 23.67 2.13 2.13 100.00 (VOLUME EXAMINED) 15.85 / (VOLUME REQUIRED) 25.56 X 100 = 62% AGGREGATE COVERAGE l l i Item No: C02.021.007 Prepared By: W.C. Leeper { [ Level: 11 Date: 10/6/98 Reviewed By: Larry Mauldin Level: 111 Date: 10/6/98 o 4 s

1 DUKE POWER COMPANY NDE-91-1 Q f Limited Examination Coverage Worksheet b l ~ Revision 0 Examination Volume / Area Defined S Base Metal O Weld O Near Surface O Bolting O Inner Radius i Area Calculation Volume Calculation .125" X.7" =.09 sq.in. .09 sq.in.X 71" = 6.39 cu.in. 71" / 3 (Profiles) = 23.67" each 23.67" X.09 sq.in. = 2.13 cu.in for each profile l Coverage Calculations Area Length Volume Volume d Req l Scan # Angle D ecton Percent Coverage sqin. ( cuin. (e Profile

3 0.00 i

1 4550 1 .05 23.67 1.18 2.13 55.40 l 2 4560 2 0 23.67 0 2.13 0.00 3 45 CW .04 23.67 0.95 2.13 44.60 4 45 CCW .04 23.67 0.95 2.13 44.60 (VOLUME EXAMINED) 15.85 / (VOLUME REQUIRED) 25.56 X 100 = 62% AGGREGATE COVERAGE Item No: CO2.021.007 Prepared By: W.C. Leeper [ Level: 11 Date: 10/6/98 Reviewed By: Lany Mauldin Level: 111 Date: 10/6/98 g g

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L DUKE POWER COMPANY NDE-91-1 i 1 Limited Examination Coverage Worksheet Revision 0 'l y.............. .-.,.3.m w,3 - 47 m l l Examination Volume / Area Defined Base Metal E W ald E NearSurface O Bolting O Inner Radius O. Area Calculation Volume Calculation l

1. 7 I. 8W'+ ~ ~f "l' * " f, 7it.y,

l.7/s s.iu Y /3814. 2 Esf.98 /. 7/39./w. 2 3S' 78 c.u. m. l Coverage Calculations Beam Area Length Volume volume Scan # Angle ' Exammed Exammed Examined Required Percent Coverage (sq.in.) (in) (cu.in.) (cu.in.) / 66*l / .9 /38' /)7. 3 2.5S38 '2. 4LT / .82 . /3 V //1./G 2.13.9l' 3 V5' 2. .8 L /3b' // 3./c.

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6 78 % ca.ss 93.l. " + /.78 " ( uhra ( awuars) x tea = /soM - (n 2B 4 = J E. EY cr/ (,991 2 2 2. 27! 0 lM 7 M s. In/l20c.rs l0 ltem No: CA/.O/d od7 4 MfpfffM Prepared BY: jg Level: 7/7 Date: /. //. 99 Reviewed By: Level: T Date: l [199 f' 4/ MET / DF+ / Eat.Jesf* Fok SE2'/E/= 99-M $77"'M"/~ 7

t==~ I DUKE POWER COMPANY NN5 UT PROFILE / PLOT SP.EEr. Revision.1 l EXAMINATION SURFA 1 EXAMINATION SURFACE 2 w ri n 4 3 2 f q, l 2 3 4 N s s 11 [ b - q { ,y { u 1 1 ( .5 .t73

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Remarks:

1 Profile taken [ 270' at. O' 90 i; r Item No: CO/. 0/0, 007 i f) Examiner: M1/z W]/oalthz Level: B Date:b// 99 l Reviewed Byf ' dGmR Level: 3r Date: 1-H-H 180 Sheet 2of 4 l Authorized inspector: /I Date: t I

r-1 I t-DUKE POWER COMPANY NDE-LJr-5 UT PROFILE / PLOT SHEET Revision.1 EXAMINATION SURFACE 1 EXAMINATION SURFACE 2 wri n l 9,~1 4 3 2 1' q. 2 3 4 N N, l. 1 ~~,x 7, a r l s r .5 X, ,j7g, \\ l I [ 1 5 C ' A/ e v / \\ t 5 O*L Af/K leM* / A8cb f ADC1 z t ..s K. a 75 + errg ! s%.ggs g ig 2.5 t 3 I U Component ID/ Weld No. p g p jff //y - g. 9

Remarks:

Profile taken j 270 at. O' 90 f) j. Item No; 60/. O/O. 007 Afja %Wy/zc Level: /J/ Date:/-//99 Examiner: / Reviewed By: ' 0 DF h Level: # Date: 1-1149 180 sheet 5 of 4 Authorized I.6 pin,'wg / F'- Date: i

l .e - DUKE POWER COMPANY NDE-UT-5 I UT PROFILE / PLOT SHEET Revision.1 l EXAMINATION SURFACE 1 EXAMINATION SURFACE 2 wF n I'f,1 4 3 2 1' q. 2 3 4 j i N N' l l t - - s l , > t, t i f-t. j .5 t \\, .l73 7 L A I j s

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Remarks:

Profile taken i 270' at. O' 90 l /) Item No: 80/.0/O.007 l Examiner: A 9)j M )] dyM /is Level: 77r Date: }.//-99 Reviewed By:' ULh Level: IC Date: 1-11-59 180 Sheetdof4 Authorized inspector: (/ ' Date. 7 t - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -}}

ML20199L492

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