L-PI-05-082, Request for Relief No. 21, for the Plant 3rd 10-Year Interval Inservice Inspection Program

Request for Relief No. 21, for the Plant 3rd 10-Year Interval Inservice Inspection Program

ML052560277
Person / Time
Site:	Prairie Island
Issue date:	09/08/2005
From:	Thomas J. Palmisano Nuclear Management Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-PI-05-082
Download: ML052560277 (83)

Text

Committed to NucearExellen Nuclear Management Company, LLC Prairie Island Nuclear Generating Plant 1717 Wakonade Dr. East

• Welch MN 55089 SEP 0 8 2005 L-PI-05-082 10 CFR 50.55a U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Unit 2 Docket No. 50-306 License No. DPR-60 Request for Relief No. 21, for the Unit 2 3rd 10-year Interval Inservice Inspection Program On November 15,1994 we submitted for review our third 10-year Inservice Inspection Examination Plan for Unit 2 and, on April 19,1995, relief request revisions associated with that plan. The NRC issued its evaluation of the 3rd 10-year Interval Program Plan on February 22, 1996.

The purpose of this letter is to submit a relief request for 'limited examinations" associated with that plan. Attached is Unit 2 Relief Request No. 21, Revision 0 which addresses those limited examinations. We are requesting relief pursuant to 10 CFR Part 50, Section 50.55a(g)(5)(iv) due to the impracticality of obtaining "100%"

examination coverage for the affected items.

Summary of Commitments This letter contains no new commitments and no revisions to existing commitments.

Thomas J. Palmisano Site Vice President, Prairie Island Nuclear Generating Plant cc: (see next page) 2047 1717 Wakonade Drive East

• Welch, Minnesota 55089-9642 Telephone: 651.388.1121

Document Control Desk Page 2 cc:

Regional Administrator, USNRC, Region Ill Project Manager, Prairie Island Nuclear Generating Plant, USNRC, NRR NRC Resident Inspector - Prairie Island Nuclear Generating Plant Chief Boiler Inspector, State of Minnesota Enclosure

omtNu Committed to Nu~erxcle Nuclear Management Company, LLC Prairie Island Nuclear Generating Plant 1717 Wakonade Dr. East

• Welch MN 55089 L-PI-05-082 10 CFR 50.55a U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Unit 2 Docket No. 50-306 License No. DPR-60 Request for Relief No. 21, for the Unit 2 3rd 10-year Interval Inservice Inspection Program On November 15, 1994 we submitted for review our third 10-year Inservice Inspection Examination Plan for Unit 2 and, on April 19, 1995, relief request revisions associated with that plan. The NRC issued its evaluation of the 3rd 10-year Interval Program Plan on February 22, 1996.

The purpose of this letter is to submit a relief request for "limited examinations" associated with that plan. Attached is Unit 2 Relief Request No. 21, Revision 0 which addresses those limited examinations. We are requesting relief pursuant to 10 CFR Part 50, Section 50.55a(g)(5)(iv) due to the impracticality of obtaining "100%"

examination coverage for the affected items.

Summarv of Commitments This letter contains no new commitments and no revisions to existing commitments.

Thomas J. Palmisano Site Vice President, Prairie Island Nuclear Generating Piant cc: (see next page) 1717 Wakonade Drive East

• Welch, Minnesota 55089-9642 Telephone: 651.388.1121

Document Control Desk Page 2 cc:

Regional Administrator, USNRC, Region Ill Project Manager, Prairie Island Nuclear Generating Plant, USNRC, NRR NRC Resident Inspector - Prairie Island Nuclear Generating Plant Chief Boiler Inspector, State of Minnesota Enclosure

ENCLOSURE September 2005 ISI Relief Request No. 21 (Rev. 0), Prairie Island Unit 2, 3rd Interval This enclosure consists of a 7 page write-up, entitled, 'ISI Relief Request No. 21 (Rev.

0), Prairie Island Unit 2, 3rd Interval" and the following attachments:

• Attachment 1, Drawing No. 2-ISI-40, 1 page

• Attachment 2, Inspection Report No. 2005VE019, 8 pages

• Attachment 3, Inspection Report No. 2005VE021, 10 pages

• Attachment 4, Inspection Report No. 2005VE023, 12 pages

• Attachment 5, Inspection Report No. 2005VE024, 10 pages

• Attachment 6, Drawing No. 2-ISI-33A, 1 page

• Attachment 7, Inspection Report No. 2005U036, 5 pages

• Attachment 8, Drawing No. 2-ISI-1OA, 1 page

• Attachment 9, Inspection Report No. 2005U024, 5 pages

• Attachment 10, Drawing No. 2-ISI-47B, I page

• Attachment 11, Inspection Report No. 2005U023, 4 pages

• Attachment 12, Prairie Island Procedure SWI NDE-LTS-1, Rev. 1 'Limitations to NDE" 13 pages 78 pages follow

ISI Relief Request No. 21 (Rev. 0), Prairie Island Unit 2, 3rd Interval Limited Examination SYSTEM:

Various CLASS: 1 and 2 CATEGORY: Various ITEM NO: Various Impractical Examination Requirements:

American Society of Mechanical Engineers (ASME) Section Xl (1989 Edition, no addenda)

Code requires full examination coverage of inservice inspection (ISI) components per Table IWB-2500-1, and IWC-2500-1. NRC Regulatory Guide 1.147 endorses the use of Section Xl Code Case N-460, "Alternative Examination Coverage for Class 1 and Class 2 Welds." This code case allows greater than 90% coverage of a weld to meet the "essentially 100%"

requirement.

In addition, NRC Information Notice 98-42 "Implementation of 10 CFR 50.55a(g) Inservice Inspection requirements" dated Dec. 1, 1998, states, "The NRC has adopted and further refined the definition of 'essentially 100 percent' to mean 'greater than 90 percent' in 10 CFR 50.55a(g)(6)(ii)(A)(2) for required examination coverage of reactor pressure vessel welds.

This standard has been applied to all examination of welds or other areas required by ASME Section Xl."

The Prairie Island construction permit was issued in 1967. This facility was designed and constructed with limited accessibility due to component configurations and/or physical barriers for which 100% examination coverage is not achievable on some ISI components examined for the Third Ten Year Interval.

Basis for Relief:

This request is submitted pursuant to 10 CFR 50.55a(g)(5)(iv) which states, 'Where an examination requirement by the code or addenda is determined to be impractical by the licensee and is not included in the revised inservice inspection program as permitted by paragraph (g)(4) of this section, the basis for this determination must be demonstrated to the satisfaction of the Commission."

The regulation further states in 10 CFR 50.55a(g)(1) that, "For a boiling or pressurized water-cooled nuclear power facility whose construction permit was issued before January 1, 1971, components (including supports) must meet the requirements of paragraphs (g) (4) and (g)(5) of this section to the extent practical." 10 CFR 50.55a(g)(4) states, "Throughout the service life of a boiling or pressurized water-cooled nuclear power facility, components (including supports) which are classified as ASME Code Class 1, Class 2, and Class 3 must meet the requirements, except design and access provisions and preservice examination requirements, set forth in Section Xl of editions of the ASME Boiler and Pressure Vessel Code... to the extent practical within the limitations of design, geometry and materials of construction of the components."

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ISI Relief Request No. 21 (Rev. 0), Prairie Island Unit 2, 3rd Interval Prairie Island was designed and constructed prior to development of ASME Xl, therefore design for accessibility and inspection coverage is not in many cases, sufficient to permit satisfying the current Code requirements. Limitations to inspections are primarily due to design obstructions, component configurations and interference. In the case of circumferential welds a limitation from ultrasonic examination may exist simply because of weld joint configuration as with a pipe to valve or fitting weld.

A summary of the limited examinations are described below and also included in Table 1, "Limited Examinations - Prairie Island Unit 2 - 2005 Refueling Outage."

Part A: Category B-D, "Full Penetration Welds of Nozzles in Vessels" Reactor Vessel (RV) Nozzle (N-7), Outlet Nozzle to Vessel Loon A:

The Reactor Vessel Nozzle-to-Vessel weld is subject to a volumetric examination.

The volumetric examination was performed using personnel and procedures qualified in accordance with Appendix Vill, Supplements 4,6 and 7. The examination was conducted using 45-degree transducers. The nozzle and vessel material are SA 508.

The examination was limited in both the parallel and perpendicular scans from the vessel ID to 78.56% due to the proximity of the outlet nozzle protrusion to the nozzle to shell weld. As an alternative to the ultrasonic examination, radiography was considered and determined to be an unacceptable substitute due to no outside access and weld configuration.

The following supporting documentation has been provided:, ISI Drawing 2-ISI-40, Examination Report Number 2005VE019 and WesDyne report Reactor Vessel (RV) Nozzle (N-10), Outlet Nozzle to Vessel Loop B:

The Reactor Vessel Nozzle-to-Vessel weld is subject to a volumetric examination.

The volumetric examination was performed using personnel and procedures qualified in accordance with Appendix Vil, Supplements 4, 6, and 7. The examination was conducted using 45-degree transducers. The nozzle and vessel material are SA 508.

The examination was limited in both the parallel and perpendicular scans from the vessel ID to 78.56% due to the proximity of the outlet nozzle protrusion to the nozzle to shell weld. As an alternative to the ultrasonic examination, radiography was considered and determined to be an unacceptable substitute due to do outside access and weld configuration.

The following supporting documentation has been provided:, ISI Drawing 2-ISI-40, Examination Report Number 2005VE021 and WesDyne report 2 of 7

ISI Relief Request No. 21 (Rev. 0), Prairie Island Unit 2, 3rd Interval Reactor Vessel (RV) Nozzle (N-8), SI Nozzle to Vessel Loop A:

The Reactor Vessel Nozzle-to-Vessel weld is subject to a volumetric examination.

The volumetric examination was performed using personnel and procedures qualified in accordance with Appendix VIII, Supplements 4, 6, and 7. The examination was conducted using 45-degree transducers. The nozzle and vessel material are SA 508.

The examination was limited in both the parallel and perpendicular scans from the vessel ID to 59.26% due to the proximity of the outlet nozzle protrusion to the nozzle to shell weld. As an alternative to the ultrasonic examination, radiography was considered and determined to be an unacceptable substitute due to no outside access and weld configuration.

The following supporting documentation has been provided:, [SI Drawing 2-lSI-40, Examination Report Number 2005VE023 and WesDyne report Reactor Vessel (RV) Nozzle (N-I1), SI Nozzle to Vessel Loop B:

The Reactor Vessel Nozzle-to-Vessel weld is subject to a volumetric examination.

The volumetric examination was performed using personnel and procedures qualified in accordance with Appendix ViII, Supplements 4, 6, and 7. The examination was conducted using 45-degree transducers. The nozzle and vessel material are SA 508.

The examination was limited in both the parallel and perpendicular scans from the vessel ID to 59.26% due to the proximity of the outlet nozzle protrusion to the nozzle to shell weld. As an alternative to the ultrasonic examination, radiography was considered and determined to be an unacceptable substitute due to no outside access and weld configuration.

The following supporting documentation has been provided: ISI Drawing ISI-40, Examination Report Number 2005VE024 and WesDyne report Part B: Category B-F, "Pressure Retaining Dissimilar Metal Welds" Reactor Coolant (RC) Weld (W-5), Nozzle to Safe End:

This dissimilar metal weld joint configuration is not currently covered by the demonstrated samples at the Electric Power Research Institute (EPRI) Perf6rmance Demonstration Initiative (PDI) center. Due to the design of the joint, no mockup could be created to examine this ultrasonically to meet Appendix VIII, Supplement 10.

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ISI Relief Request No. 21 (Rev. 0), Prairie Island Unit 2, 3rd Interval Therefore a supplemental ultrasonic (UT) exam was performed with the following results:

The Elbow to Safe End weld is subject to a volumetric examination and surface examination. The volumetric examination was performed using personnel and procedures qualified in accordance with Appendix ill. The examination was conducted using 45-degree refracted longitudinal transducers. The elbow and safe end material are SA 351-CF8 cast austenitic stainless and 308L stainless (this joint contains no Alloy 82/182 or 600). The examination was limited to 78.46% due to the OD profile of the cast stainless steel elbow. The UT examination is further hindered from the elbow side of the weld for obtaining meaningful ultrasonic data because of the elbow material being cast austenitic stainless steel. UT sound beam attenuation and propagation properties in cast stainless steel are extremely difficult. The ASME Code Committee and the industry Performance Demonstration Initiative (PDI) recognized that such examinations are difficult. ASME Section Xl, Appendix VIII, Supplement 9 has been in "course of preparation" for several years, hence, there are no qualified examination procedures or personnel to conduct the required examinations. As an alternative to the ultrasonic examination, radiography was considered and determined to be an unacceptable substitute due to radiological constraints, the reactor vessel level would be required to be at reduced inventory below the center line of the hot leg, weld configuration, and the undue hardship imposed without offering any commensurate increase in safety with cost benefit.

The required surface examination was performed using liquid penetrant and was not limited. 100% of the required surface area was inspected (Inspection Report No.

2005P032). No relevant indications were detected.

The weld is included in the boundary examined by VT-2 during pressure testing (SP 2070, Reactor Coolant System Integrity Test, completed on 619/2005). No leakage was identified in the vicinity of the weld.

The following supporting documentation has been provided:, ISI Drawing 2-lSI-33A, Examination Report Number 2005U036 Part C: Category B-J, "Pressure Retaining Welds in Piping" Residual Heat Removal (RH) Weld (W-11) Valve to Pipe:

This piping weld is subject to be examined by both volumetric and surface examination methods. The volumetric examination was performed using personnel and procedures qualified in accordance with Appendix VIII, Supplement 2. The examination was conducted using 45 and 60-degree transducers. The valve and piping material are austenitic stainless steel. The examination is limited to 50% in both the axial and circumferential directions from the piping side of the weld due to the weld joint configuration connection to the valve. The credited volumetric examination of the Weld 4 of 7

ISI Relief Request No. 21 (Rev. 0), Prairie Island Unit 2, 3rd Interval Required Volume (WRV) was limited to 47.77% and only a single-sided examination could be performed. It should be noted that the volumetric examination was performed through 100% of the Code WRV; however, the PDI Appendix Vill procedure used is not qualified for the detection of flaws on the far side of single sided access examinations on austenitic stainless steel piping welds. The techniques employed for the examination provide for a best effort examination. As an alternative to the ultrasonic examination, radiography was considered and determined to be an unacceptable substitute due to radiological constraints, weld configuration, and the undo hardship imposed without offering any commensurate increase in safety with cost benefit.

The required surface examination was performed using liquid penetrant and was not limited. 100% of the required surface area was inspected (Inspection Report No.

2005P019). No relevant indications were detected.

The weld is included in the boundary examined by VT-2 during pressure testing (SP 2070, Reactor Coolant System Integrity Test, completed on 6/9/2005). No leakage was identified in the vicinity of the weld.

The following supporting documentation has been provided:, ISI Drawing 2-ISI-1 OA, Examination Report Numbers 2005U024 Part D: Category C-F-2 "Pressure Retaining Welds in Carbon or Low Alloy Steel Piping" Main Steam (MS) Weld (W-14), Tee to Flange:

This tee to flange pipe weld is subject to be examined by both volumetric and surface examination methods. The reducer tee and pipe materials are carbon steel. The volumetric examination was performed using personnel and procedures qualified in accordance with Appendix VilI, Supplement 3. The examination was conducted using 45 and 60-degree transducers. The piping materials are A155 KC70. The credited volumetric examination of the WRV was limited to 74.85%. As an alternative to the ultrasonic examination, radiography was considered and determined to be an unacceptable substitute due to radiological constraints, weld configuration, and the undo hardship imposed without offering any commensurate increase in safety with cost benefit.

The required surface examination was performed using Dye Penetrant and 95.8% of the required surface area was inspected (Inspection Report No. 2005P043). No relevant indications were detected.

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ISI Relief Request No. 21 (Rev. 0), Prairie Island Unit 2, 3rd Interval The weld is included in the boundary examined by VT-2 during pressure testing (SP 2168.1 1, completed 9/13/2003). No leakage was identified in the vicinity of the weld.

The following supporting documentation has been provided: 0, ISI Drawing 2-lSI-47B 1, Examination Report Number 2005U023 Additional Means of Establishing Component Integrity:

System integrity is monitored during normal operation by many direct and indirect methods, e.g., containment radiation monitoring, containment air monitoring, containment sump monitoring, containment temperature monitoring, system walk downs, surveillance testing, etc.

Alternate Examination:

The limitations have been noted on the ISI examination reports and are included in the 2005 ISI Outage Summary Report. NMC will continue to document limitations.

All in-service inspections at Prairie Island Unit 2 have been completed to the greatest extent practical. When limitations to required inspections are encountered, Prairie Island's "Limitations to NDE" procedure SWI NDE-LTS-1 was applied. SWI NDE-LTS-1 (Attachment

12) is used when an ASME Section XI Code required examination results in less than 90%

coverage. It requires a review of the procedures to obtain maximum coverage and documentation of the limitation. The procedure also examines whether an alternative method could be used to obtain better coverage as allowed by the Code. This procedure was used for all the items identified above and the maximum inspection coverage was achieved.

Limitations are due to design, geometry, and materials of construction of the components.

NMC will continue to utilize the most current techniques available for future examinations.

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IS[ Relief Request No. 21 (Rev. 0), Prairie Island Unit 2, 3rd Interval Table 1. Limited Examinations - Prairie Island Unit 2 - 2005 Refueling Outage CSYSTEM Comp

,Method Io verage Rep ritatlonrt#-':

Cate~orpltem'N~.p;;.

ummary,#j~.sr~inj~~~-~~t¶iait~~

B-D 83.90 Reactor Vessel 2-ISI-40 N-7 Outlet Nozzle UT 78.56%

2005VE019 Limited due to 505018 to Vessel Weld configuration.

Loop A B-D B3.90 Reactor Vessel 2-ISI-40 N-10 Outlet Nozzle UT 78.56%

2005VE021 Limited due to 505020 to Vessel Weld configuration.

Loop B B-D B3.90 Reactor Vessel 2-ISI-40 N-8 Si Nozzle to UT 59.26%

2005VE023 Limited due to 505727 Vessel Weld configuration.

Loop A B-D B3.90 Reactor Vessel 2-ISI-40 N-11 SI Nozzle to UT 59.26%

2005VE024 Limited due to 505726 Vessel Weld configuration.

_ Loop B B-F B5.70 Reactor Coolant 2-ISI-33A W-5 50 degree UT

• 0%

2005U036

• No Demonstrated 501137 Elbow to 58.84%

technique at PDI for PI Nozzle configuration B-J B9.11 Residual Heat 2-lSI-10A W11 Valve to Pipe UT 44.77%

2005U024 Single side access Removal 501953 C-F-2 C5.80 Main Steam 2-lSI-47B W-14 Tee to Flange UT 74.85%

2005U023 Flange configuration and 500818 support adjacent to weld 7 of 7

,.;i 0

CONT. ON 2-ISI-33C T 2700 = Z no C

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I CONT. ON 2-ISI-32C REACTOR VESSEL NOZZLES REF:

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( M&SP ) - P 1 -2 1 2 I DWN: DMN CHKD:

Q, APPD:

SYSTEM:REACTOR VESSEL NOZZLES LINE: NA DWG:

2-ISI-40 REV: 06 0

NM7ij' Ultrasonic Examination Site/Unit:

Summary No.:

Workscope:

PINGP /

P12 505018 Procedure:

Procedure Rev.:

Work Order No.:

UT-Vendor 0

0406670 Outage No.:

E031 Report No.:

2005VE019 Page:

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'SI Code:

1989 Edition Cat./Iltem:

B-D/B3.90 Location:

Drawing No.:

2-ISI-40

==

Description:==

Outlet Nozzle to Vessel Weld Loop A System ID:

RV Component ID: N-7 Size/Length:

NA Thickness/Diameter:

9.17"153" Limitations:

See WesDyne exam report Comments:

See supplements and Refer to the applicable WesDyne report found in the book:

Prairie Island Nuclear Power Plant I Unit 2 10-Year Reactor Vessel Inservice Examinations Interval 3, Period 3, Outage RF023 2005

^ 78.56%, See WesDyne final report Results:

NAD E IND i GEO E]

Indications allowable by Code Percent Of Coverage Obtained > 90%:

No Reviewed Previous Data:

Yes Examiner Level li Signature Date Reviewer Ig Signature Date VENDOR, WESDYNE 5/15/2005 Jones, Thomas Examiner Level N/A Signature Date Site Review Signature},.

r Date N/A Wren, Jerry P 5,i Other Level N/A Signature Date ANII Review Signature Date N/A Daly, Gerald tek)6*E

NM ')

Supplemental Report Report No.:

2005VE019 Page:

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Summary No.: 505018 Examiner: VENDOR, WESDYNE Examiner:

NIA Other:

NIA Level:

II Reviewer Jones, Thomas Level:

N/A Site Review: Wren, Jerry P Level:

N/A ANII Review: Daly, Gerald CPZJ1-Date:

Date:

5 '.vij Date: ISALrr,cS Comments:

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Summary No.: 505018 Examiner: VENDOR, WESDYNE Examiner:

N/A Other: NIA Supplemental Report Report No.:

2005VE019 Page:

3 of 5

Level:

II Reviewer, Jones, Thomas Level:

N/A Site Review: Wren, Jerry P Level:

N/A ANII Review: Daly, Gerald C_

Date: _ _ _ _ _ _ _

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Supplemental Report Report No.:

2005VE019 Page:

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Summary No.: 505018 Examiner: VENDOR, WESDYNE Examiner: NIA Other: NIA Level:

II Level:

N/A Si Level:

NIA AN Reviewer: Jones, Thomas. CiM te Review: Wren, Jerry P 97-Ill Review: Daly, GeraldA Date:

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Supplemental Report Report No.:

2005VE019 Page:

5 of 5

Summary No.: 505018 Examiner: VENDOR, WESDYNE Examiner: N/A Other: NIA Level:

II Reviewer: Jones, Thomas Level:

N/A Site Review: Wren, Jerry P Level:

NIA ANII Review: Daly, Gerald CV4, 5 Date:

41_/_

5 Date:,-ec+/-'o

=

_ Date:

tiAU&65 Comments:

Sketch or Photo:

J:\\lSIDataJSI\\PI2 05 outage\\Scans\\WeDyne Vessel Flaws\\505018 N-7\\law Disposition 2.bmp NMio Site/Unit.

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fi Sunirnary No:

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_ O I 8 Workscope:

ISI Flaw Disposition Worksheet Procedure:

-Xs5-2ZS-Z Procedure Rev.:

O Work Order No.:

O L O Co Co 7 0 Outage No.:

rZ2

? Zz7 Report No.:

VcY15 L'

0 9

Page:

or

1) Flaw Nuinber

2) lIn& Numnber B

1.

. q I tAr z til

^_ -

3) ISI Interval

4) Code Edition & Addenda S) Acceptance Standard

6) Catculullons (See eolo-)

/F8 9 "ale' 40a.

• OK Reviewer 52fJ N

OK Reviewer e~sXkJ I

OK Reviewer Z

4 OK Reviewer ai 09

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7) Rrcs.ulls 0 OK Reviewer C;t) rnt -

D9. /0 Code ellowable eWt% -

~

Calculated tJ Y._ /

09 Laminar flaw tsurface area: (0.75 1 w) *

/) Table used for onalystn OK Revilwer ZD _e -

3 5

i

_t j

-2

0) Was linear interpolation usod?

C) Yes 0

No If no. why?

A-uo 7

"?e.2 c, l &=

10) Was IWA-3200 Significant Digits For Limiting Values followod?

0 Yes C)

No Ifrno. why?

1t) The correct Code Edition and Addenda was available and used.

Yes Preparer 7

0 O

OK Reviewer

12) Statement or auceptability or rojoctobility with basis.

D OK Reviewer (0' Accept C) Reject 1I (aft) Codo atlowahle > (WIt) calculated

• i OEM flaw evaluation, handbook (see attached analysis)

C)

(a/1)

Code llowoable * (a0t) calculated 13J by annd o

Thle rjlsulls are correct and the methodology used Is In accordance with applicable codes, standards. specifications and procedures.

date Yhis l'ew v

sStres that the results are correct and the meth odology used is in accordance with applIcable codes.

standards. specifications nnd procedures.

15) Ap!v=d by t d\\

d ale f

v This approval assures that all lsr0tved witA thlis navw sizing and flaw disposition were aware of the necessity that the results and the methodology are correct and In accordance with Vippilcable codes. standards, specifications and procedures.

Adieonel - ISI Flow D09position.edit from Selup-Additional - Supplemental Reports <edit from Setup>

REACTOR VESSEL WELD RESULTS

SUMMARY

PLANT NAME Prairie Island Unit 2

WELD NO.

N7 (505018)

COMPONENT Outlet Nozzle to Shell @ 28.50 LIMITATIONS:

NO F-1 YES 3j 78.56 % Complete See Coverage Breakdown Sheet RESULTS NO. OF INDICATIONS 2

NI STATUS Code Allowable RI X

EXAM DOCUMENTATION INDICATION DOCUMENTATION Lf PARAGON ANALYSIS LOG IEIASSESSMENT SHEET FxII PARAGON ACQUISITION LOG mK PARAGON HARD COPY EKI SCAN PRINT OUT

=II OTHER (Specify)

ELl COVERAGE BREAKDOWN Comments:

Coverage calculation is based on the Bore and Star scan (combined) as perpendicular, and the Tan Scan (parallel). Figure 1 illustrates the obstruction.

Analyst //,

Date:

e

R.V. COVERAGE ESTIMATE BREAKDOWNS PLANT NAME Prairie Island WesDyne WELD NO.

N7 (505018)

International COMPONENT Outlet Nozzle to Shell @ 28.50 BEAM ANGLE BREAK DOWN BEAM DIRECTION l 45 Shear l

45 L Single 45 L Dual l Combined Bore/Star

_ WELD I VOLUME.

WELD I VOLUMEj WELD I VOLUME] WELD I VOLUME TAN Scan l

l______

Parallel 54.33 28.52 64.28 56.90 71.82 69.79 Combined Bore&Star l

l Perpendicular Il l

l

60.

99.68 l

99.35 AVERAGE 41.42 60.59 70.80 99.52 Comments:

Combined Perp.

Coverage calculation is based on the Bore and Star scan (combined) as perpendicular, and the Tan Scan (parallel). Figure 1 illustrates the obstruction.

I 99.52 fAX Combined Para.

Analyst

/

/

1_7

/

57.61 Combined Average 78.56 Date

_//

/

/

/

/

/

/

6'

/

/

/

/

6'

/

(9.18)

WALL

/

/

6'

/

1/

/

/

<6

//

/

//

//

//

//

X

//

R66.00 to Transdlucer CIO.I Sled x

Package X~/'

Figure 1 26.53 Tar Coverae Illustration Primary Uuttet Nozzle Protrusion Limitation

NM -

Site/Unit:

PINGP

/

Summary No.:

5t Workscope:

Ultrasonic Examination P12

)5020 Procedure:

Procedure Rev.:

Work Order No.:

UT-Vendor 0

0406670 Outage No.:

E031 Report No.:

2005VE021 Page:

I of 7

IS' Code:

1989 Edition Cat./ltem:

B-DIB3.90 Location:

Drawing No.:

2-ISI-40

==

Description:==

Outlet Nozzle to Vessel Weld Loop B System ID:

RV Component ID: N-10 Size/Length:

NA Thickness/Diameter 9.1r153" Limitations:

See WesDyne exam report Comments:

See supplements and Refer to the applicable WesDyne report found in the book:

Prairie Island Nuclear Power Plant / Unit 2 10-Year Reactor Vessel Inservice Examinations Interval 3, Period 3, Outage RF023 2005

&78.56%, See Wesdyne final report for details.

Results:

NAD D]

IND R GEO D Indicaitons allowable by Code Percent Of Coverage Obtained > 90%:

'No Reviewed Previous Data:

NJA Examiner Level II Signature Date Reviewer (Signature Date VENDOR, WESDYNE 5/15/2005 Jones, Thomas

/

..Jo2df Examiner Level II Signature Date Site Review Signature Date Auer, Robert G.

Wren, Jerry P "g-e-os Other Level NIA Signature Date ANII Review Signature Date N/A Daly, Gerald 7eIQ.

sSo0r.

NM)

Supplemental Report Report No.:

2005VE021 Page:

2 of 7

Summary No.: 505020 Examiner: VENDOR, WESDYNE Examiner: Auer, Robert G.

Other:

NIA Level:

II Reviewer: Jones, Thomas Level:

II Site Review: Wren, Jerry P Level:

NIA ANII Review: Daly, Gerald C_ _

Date:

_S ____

q Date: £ --

7S

&Q Date: 1&4 I )

Comments:

Sketch or Photo: J:ISIData\\lSl\\PI2_05 outage\\Scans\\WeDyne Vessel Flaws\\50502O N-10\\Flaw Sizing 1.bmp Site/Unit:

P1>

, J Stimniary No.:

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7 SX ISI Flaw Sizing Worksheet Procedure: 2br-l.ri- ;tS4/

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1) Flaw Number

/

2) Itein Number 2

3. 9 o

3) ISI Interval

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4) Code Edition a Addenda

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5) Method

6) Flaw Sketch (See Below)

Flaw View

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Outlao No.:

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Page:

of 9

OK Reviewer 1

0 OK Reviewer OK Reviewer

= d9 n O i

i I

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7) Calculations 4D OK Reviewer Show dctlrmninalion of Surface or bs 3

Show,latcrrnination or type of a

to use j

f-

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_R ft t was used tP) Yes Preparer

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3 0

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7

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11) Flaw Characterization Figure W OK Reviewer 4 -

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12) Flaw Charactoriznlton Figure Number a

I

13) Was IWA-3300 Flaw Characterization followed?

SW Yes 0 No It no. why?

A OK Reviewer C

L

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nr -

/

14) The correct Code Edition and Addenda was available end used.

0W Yes Preparer r10 OK Reviewer t S _

/

v S

16), ~

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and d LA,-v The results are correct and the methodology used is In accordance The re4 ssures that the results are correct and the with applicable codos. standards. specifications and procedures.

methodology used Is In accordance With applicable codes.

standards. speclfications and procedures.

A"idt.Or,0

• ISI Flaw SizE *eddt Imron Setoup Additional - Supplemental Reports <edit from Setup>

NM)

Summary No.: 505020 Examiner: VENDOR,WESDYNE Examiner: Auer, Robert G.

Other: N/A Supplemental Report Report No.:

2005VE021 Page:

3 of 7

Level:

_I Reviewer: Jones, Thomas Level:

_1 Site Review: Wren, Jerry P Level:

N/A ANII Review: Daly, Gerald c-jrt, 1

Date: _______

Date: g-5 -;S 4

Date:

IsAiydg-(U Comments:

Sketch or Photo: J.ISIDataUSI\\P12_05 outagelScanslWeDyne Vessel Flaws\\505020 N-101Flaw Disposition 1.bmp NME>

Site/Unit:

P Z:

%Z Summary No.:

50 S0 A 0 Worksrope:

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2) Item Number Ei

. q 0

uae0, H-AJ X -

J Procedure: P xs4r-2 s5f-z Procedure Rev.:

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4) Code Edition & Addenda

/,98 9

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5) Acceptance Standard g-

$ 5'/ *;>

6) Calculations (See Below)

Outage No.:

/2Z-:Z g2 0s-Report No.:

V2rs* ViE P

/

Page:

d of es OK Reviewer OK Reviewer 4C OK Reviewer 6R OK Reviewer a

=4o Oe, J=/,

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7) Results Q

OK Reviewer DA -

. 0 77 Code allowable avtY 2,1.

LeJ-Calculatede/t/%

1 C)7 Leaminarflawsurface area:(0.75 I w)-

.AJ'4

8) Table used for analysis l;

OK Reviewer j

=Z, r3 _- 3.s-5 I

/

9) Was linear Interpolation used?

0 Yes a

No If no. why?

10)a W

ii gceit fo Lmi Z

a

-lu ed

/e o

f no 2 IO) Was IWA-3200 Significant Digits For Limit ng Values followed?

4D Yes O:: No It no. why?

I11) The correct Code Edition and Addenda was available and used.

PYes Preparer-.,_,..J

> OK Reviewer 5hW

12) Statement or acceptability or rejectability with basis.

0 OK Reviewer

( <

Accept Q Reject (a/t) Code allowable o (a/t) calculated 0

OEM flaw evaluation handbook (see attached analysis) 0 (a/J) Code allowable (aft) calculated

13) Prepared by and Oate 14,ngtneeing re y anddt The results are correct and the methodology used Is In accordance Thisyeview assures that the results are correct and the with applicable codes. standards, specifications and procedures.

methodology used Is In accordance with applicable codes.

standards. specifications and procedures.

IS) Apwvedby ary date This approval assures that ail Involved with this flaw sizing and flaw disposition were aware of the necessity that the results and the methodology are correct end In accordance with applicable codes. standards. specifications and procedures.

Additional -11S Flaw Disposilion -edit from Setup-Additional - Supplemental Reports <edit from Setup>

NMC)

Supplemental Report Report No.:

2005VE021 Page:

4 of 7

Summary No.: 505020 Examiner: VENDOR, WESDYNE Examiner: Auer, Robert G.

Other: N/A Level:

II Reviewer: Jones, Thomas Level:

II Site Review: Wren, Jerry P Level:

N/A ANII Review: Daly, Gerald C< 9 Date:_____

Date: S-r-c-dQ()

Date:

Ls5Afo.6 U

Comments:

Sketch or Photo: J:\\ISIData\\ISl\\PI2_05 outage\\Scans\\WeDyne Vessel Flaws\\505020 N-10\\Flaw Sizing 2.bmp Site/Unit:

P Z

I

.2_

Summary No.;

£54 0 p

) ° Workscope:

Z S

tSI Flaw Sizing Worksheet

1)

Flaw Number a_

2) Item Nurrmber a

9?O JA Ie/)-e Al-J O Flaw Viow Procedure:

lebr'-'

S-f'/-

A/Z Procedure Rev.:

0 Work Order No.:

2 6

?7 0

3) tSI intervat S

=5

4) Code Edition & Addenda

/ 9q'V r..

412 0

5) Method 1<J T O) Flow Sketch (See Below)

Outage No.: PXZ R f;S Report No.:

.OOS VC oC

/

Page:

of O

OK Reviewer

@ OK Reviewer

@ OK Reviewer 3.z

>O.- L t

>0.

O..

/

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>.tI(A4(.

3 n -

>.t sb4cf I

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7)

Calc,,lilions 0

OK Reviewer

.Show determination or Surface Show determination or type of a to use J.57t~?5

.5i-l - A.6 eO 7: Z s.-

8) 44 rE

. Paragrapla--

was used

9) Code Flaw Dimensions e

OK Reviewer

-I-r

• a 0S5t nominarl 9

Z

-t

10) Flaw Type (RD OK Reviewer 7

1) Vieaw Characterizaion Figuro 6C OK Reviewer.

I 2) Flaw Characterization Figure Number

ch /

13) Was IWA-3300 Flaw Characterization followed?

0 Yes MD Yes Prep aror 7s4t. J 4S OK Revlewer

'~---

fnwosurvd

/

-s- -

3..

Z S w- -

(

s b ----

l_ cen P Ir-^e

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S a

-/

O No If no, why?

14) The correct Code Edition and Addenda was available end used.

I r, Pr a

dbyaddae O 5 The results are correct and the methodology used Is in accordance with nppllcable codos. standards. specifications and procedures.

o Yes Preparer r

(,..J C

OK Reviewer

16) Re nd

=7'

-rZ 6

f 5-The revt

£t'assurcs that the results are correct and the methodology used Is In accordance with applicable codes.

standards, specifications and procedures.

Arddional. ISI Flaw Size *edil from Setupc Additional - Supplemental Reports <edit from Setup>

NM)

Supplemental Report Report No.:

2005VE021 Page:

5 of 7

Summary No.: 505020 Examiner: VENDOR, WESDYNE Examiner: Auer, Robert G.

Other: NIA Level:

II Reviewer: Jones, Thomas Level:

II Site Review: Wren, Jerry P Level:

NIA ANII Review: Daly, Gerald c

)

Date:

_/_/o__

Cate:ate:

8-

&Dat:

,kW.

Date: ijs-*

L.d (2

Comments:

Sketch or Photo: J:UlSIData\\lSl\\PI2_05 outage\\Scans\\WeDyne Vessel Flaws\\505020 N-10\\Flaw Disposition 2.bmp Ni\\MeT>

Site/Unit:

P X725 /

Summary No.:

7>

-o a

Workscope:

_- 25 S=

ISI Flaw Disposition Worksheat Procedure: P. t-.r5r-

-A/.Z Procedure Rev.:

C Work Order No.:

OL.

6 O

(, C 7 0 Outage No.:

Px>2 g<zS Report No.:

20S

-Vc' g%

/

Page:

of

1) Flaw Number

2) Item, Number C;2o 3)11S interval

4) Code Edition & Addenda

/ 98 9 IVO X.19.

5) Acceptance Standard

.Z'. V S

3

t

0) Calculations (Sue Bol-w)

@0 OK Reviewer 4

Ol< Reviewer

<if OK Revlewer IC OM OK Reviewer j

=

/, L7 V

t

=

K>>

/-

D

~

O

~

7) Results 0

OK Reviewer nA -

O. 033 Code allowable aWt% -

0 4-Calculated anY.

D Laminar (law tsurfoce area: (0.75 1 w)

0) Toble used for analysis P

OK Reviewer C

.Z

- 3 S '7

9) Was linear Interpolation used?

CD Yes 0' No If no, why?

ACz c

'.e 71 -

6 C'

0el C2 /e O

IOr 7--c 1O) Wes IWA-3200 Significant Digits For Urniting Values followed?

O Yes 0

No If no. why?

11) The correct Code Edition and Addenda was evailable end used.

O Yes Preperer 7-Z J

9 OK Reviewer

12) Statement of acceptability or rejectabifity with basis.

l OK Reviewer (1np Accept C> Reject C

(a/t) Code allowable (a/lt) calculated

°D OEM flaw evaluation handbook (see attached analysis)

C)

(sl/) Code allowable ~ (a/I) calculated

13) Prepared by and ate The results are correct and the methodology used is In accordance with applicable codes. standards. specifications and procedures.

IS rng r d date

'*s This w assures that the results are correct and the methodology used is In accordance with applicable codes.

standards. speciacantlons and procedures.

1S)

Arrv d hyad date 5.9 =...'to I

This approval assures that alffinvolved with this flaw sizing and ttaw disposition were aware of the necessity thai the results and the methodology are correct and In accordance with applicable codes, standards. specifications and procedures.

Add-lional - ISI Flaw DOspositton -edit fromi Setup-Additional - Supplemental Reports <edit from Setup>

NMC)

Summary No.: 505020 Examiner: VENDOR, WESDYNE Examiner Auer, Robert G.

Other: NIA Supplemental Report Report No.:

2005VE021 Page:

6 of 7

Level:

II Level:

II Level:

N/A Reviewer: Jones, Thomas

° Date: _______

Site Review: Wren, Jerry P

~ Date: _-2-;

ANII Review: Daly, Gerald 4M Date:

S5&

LI Comments:

Sketch or Photo:

J:ISIData\\ISI\\PI205 outage\\Scans\\WeDyne Vessel Flaws\\505020 N-10\\Flaw Sizing 3.bmp Site/Unit.

P

/

.,?.

Surrmary No.:

5 s

O LC.)

Workscope.

r S-L

1) Fiow Number 3

?1 Item Number E3 a.

9g0 ISI Flaw Sizing Worksheet Proceduro:

?r

-_Sf-r

&,Z Procedure Rev.:

a Work Order No.:

O e4 6

i7°

3) 1St Interval 3

4) Code Edition & Addenda

/ 9 I AC 14Q.

5) Method L

`-

6) Flaw Sketch (See Below)

Flaw e/

Flavv View J-lo Outage No.:

P F

Report No.:

tO&C Vt

)

/

Page:

of CY OK Reviowor (O

OK Reviewer OK Revitewer o -

Y-a')('

C2

,0 4V-n

,/0 0 -jo I

I 11' I

___J
__,_ -=_

7) Caklculwlio,,

(>

OK Rovicv..nr Show dolormination of Surface or.

ubsur Show determination of ot

'a' to use

-Ad~e->-essz 7_

1. i54.

8)i-FE 4 Preagraph..r--

_ _I l lthoJ was used

9) Code Flaw Oimonsions 4D OK Reviewer r.

I S

a l

10 t nonwno 22

-t

10) -law Type R

OK Reviewer <

i-

11) Flaw Charricterization Figure Q9 OK Reviewer y

12) Flaw Characterization Figure Number

/

13) Was IWA-3300 Flaw Characterization followed?

O Yes 6

Yes Preparer -

op-nmees,,e'd

/Li

-s- -

s b

eC Pl,_,

4-3 3z _,-

OK Reviewer

'5=

0 No If no. why?

14) The correct Codo Edition and Addenda was available end used.

1 5) Prer by rid 1 he results are correct and the methodology used Is In accordance with applicable codes, standards, specifications and procedures.

AXICI4,nal - 131 Fl-Size.e4i froan, setup.

m Yes Preparer 7

tY OK ReviOwerK i

i 1

e= :nd-17 6 9-The rik

, assures that the results are correct and the methodology used Is In accordance with applicable codes.

standards. specifications and procedures.

Additional - Supplemental Reports <edit from Setup>

NM)

Summary No.: 505020 Examiner: VENDOR, WESDYNE Examiner: Auer, Robert G.

Other: NIA Supplemental Report Report No.:

2005VE021 Page:

7 of 7

Level:

II Reviewer: Jones, Thomas aT.k

(

Date: __5_o_

Date:

S'-'

Level:

_1 Site Review: Wren, Jerry P Level:

N/A ANII Review: Daly, Gerald Date:,sr U

Comments:

Sketch or Photo: J:IlSlDataliSflP2o05 outageIScanslWeDyne Vessel FlawssO5502O N-10FIaw Disposition 3.bmp ImnhMa>

ISI Flaw Disposition Worksheet Site/Unit; P z..,

St.nmmnry No.:

C:-0 5: o. _n Workscope -

Procedure: P1 r-r-5'/-&'z Procedure Rev.:

C Work Order No.:

LvO G G 7 0 4TcD-I Outage No.-:

toZr pz f S

Report No.:

25co V'S

.2 /

Page:

of

1) Flaw Number

.3~

2) Item Number 1>'~. C90 Lu,.'

") AJ/ -/ 0 J

&-e'OI?

11

=

,7/'

/- 0.

'(

~

e1 3)151 Interval

4) Code Edition - Addenda

/ "989

.. /,4.0.0.

5) Acceptance Standard EZ i-

.5?

-/;

(3) Calculations (See Below) a?, 2'

/.

O0 <'5

<D OK Reviewer 1

OK Reviewer C

OK Reviewer a

OK Reviewer

7) Results C@ OK Reviewer aI f

Code allowable aWt%

a

2. Li-Calculated a/t%

-/_

07 Laminar flaw surface area: (0.75 1 w)

Aw B) Table used for analysis

!1 OK Reviewer

=1 J B0 - 3S'

-/

0) Was linear Inlerpolation used?

0 Yes No If no. why?

t0)

Was IWA-3200 Slgntiicanrt igilts For Linmiting Values followed?

I Yes 0 No Iflno. why?

11) Tho correct Code Editiorn and Addenda was available and used.

G Yes Preparer er77i*-

0 OK Reviewer

12) Statement of acceptability or rejoctabilltywith basis.

4 OK Reviewer 4

Accept 0

Reject (0

(all) Code allowable > (all) calculated 0

OEM flaw evaluation handbook (see attached analysis)

O (a/t) Code allowable (aWt) calculated 3I Prep bynd tal The results are correct and the methodology used Is In accordance with applicable codas. standards, specifications and procedures.

1tilnvaring Iv woy and date C) 6?L4'§' *g5 Thislaew assures that the results are correct and tha methodology used is in accordance with applicable codes.

standards. specifications and procedures.

15) A~roved byd dale.

I nle.zt 1

.3

..*vS This approval assures that alt involved with this flaw sizing and flaw disposition were aware of the necessity that the results and the nmethodology are correct and In accordance with applicable codes. standards, specifications and procedures.

Additlonal - 1tS Flaw Disposition radit fron, Setup-Additional - Supplemental Reports <edit from Setup>

REACTOR VESSEL WELD RESULTS

SUMMARY

PLANT NAME Prairie Island Unit 2

WELD NO.

N10 (505020)

COMPONENT Outlet Nozzle to Shell @ 208.50 LIMITATIONS:

NO E YES [I 78.56 % Complete See Coverage Breakdown Sheet RESULTS NO. OF INDICATIONS 3

NI STATUS Code Allowable RI X

EXAM DOCUMENTATION INDICATION DOCUMENTATION FU PARAGON ANALYSIS LOG

[K1ASSESSMENT SHEET LII PARAGON ACQUISITION LOG

[XI PARAGON HARD COPY m7I SCAN PRINT OUT

[I] OTHER (Specify)

LII COVERAGE BREAKDOWN Comments:

Coverage calculation is based on the Bore and Star scan (combined) as perpendicular, and the Tan Scan (parallel). Figure 1 illustrates the obstruction.

Analyst

/

j Date: 6

R.V. COVERAGE ESTIMATE BREAKDOWNS PLANT NAME Prairie Island WesDyne WELD NO.

N10 (505020)

International COMPONENT Outlet Nozzle to Shell @ 208.5° BEAM ANGLE BREAK DOWN BEAM DIRECTION 45 Shear 45 L Single 45 L Dual Combined Bore/Star WELD I VOLUME WELD IVOLUME WELD VOLUME WELD VOLUME TAN Scan Parallel 54.33 28.52 64.28 56.90 71.82 69.79 Combined Bore&Star Perpendicular 99.68 99.35 AVERAGE 41.42 60.59 70.80 99.52 Comments:

Coverage calculation is based on the Bore and Star scan (combined) as perpendicular, and the Tan Scan (parallel). Figure 1 illustrates the obstruction.

Combined Perp.

Analyst w

I/

/

i

/

II

. I. i-I.1

/

/

/

/

/~

/~

/~

/

(9.18)

WALL

/

/

X/

R66O00 to

/

/

/

/

Cladl Sled

/

/

/

/

/

/

Transducer Package 11 Figure Tarn CoveraQe Primary ylutl Protrusion

? 1 26853 Illustration

%et Nozzle Limitation

NMl)

Ultrasonic Examination Site/Unit:

PINGP

/

Summary No.:

51 Workscope:

P12 D0727 Procedure:

Procedure Rev.:

Work Order No.:

UT-Vendor 0

Outage No.:

E031 Report No.:

2005VE023 Page:

1 of 9

ISI 0406670 Code:

1989 Edition Cat./ltem:

B-D/B3.90 Location:

Containment Drawing No.:

2-ISI-40

==

Description:==

SI Nozzle to Vessel Weld Loop A System ID:

RV Component ID: N-8 Size/Length:

NA Thickness/Diameter:

9.17"/11.58" Limitations:

See WesDyne exam report Comments:

See supplements and Refer to the applicable WesDyne report found in the book:

Prairie Island Nuclear Power Plant / Unit 2 10-Year Reactor Vessel Inservice Examinations Interval 3, Period 3, Outage RF023 2005

• 59.26%, See WesDyne final report for details Results:

NAD D]

IND i GEO L Indications allowable by Code Percent Of Coverage Obtained > 90%:

• No Reviewed Previous Data:

Yes Examiner Level II Signature Date Reviewer Sign ture Date VENDOR, WESDYNE 5/15/2005 Jones, Thomas Examiner Level N/A Signature Date Site Review SignatureLv C

Date NIA Wren, Jerry P

=AAJw-Other Level N/A Signature Date ANII Review LI Signature Date NIA Daly, Gerald Iydd/ md.QS IS-,uc-OS

NM)

Supplemental Report Report No.:

2005VE023 Page:

2 of 9

Sumnmary No.: 500727 Examiner: VENDOR, WESDYNE Examiner N/A Other: NIA I

Level:

11 Reviewer: Jones, Thoma Level:

NIA Site Review: Wren, Jerry P Level:

NIA ANII Review: Daly, Gerald S

I400 Date:

_/_ __S_

Date: F-&-'oS Date:

1

\\

U' Comments:

Sketch or Photo: J:\\lSIDatalSt\\P12_05 outage\\Scans\\WeDyne Vessel Flaws\\500727 N-8\\Flaw Sizing 1.bmp N lviYE-Site/Unit:

P I

.2 Summary No.:

5 e

e 7 i

'7 Worksrope:

5

1) Flow Nuitber

2) Item Number B

0o Flaw View ISI Flaw Sizing Worksheet Procedure:

ZS4/ ¢-Outogo No:

PX7,,-

1zt S

Procedure Rev.:

O Report No.:

soos V Work Order No.

S -7D 0

Page:

of

3) ISI Interval OK Reviewer

4) Code Edition & Addenda 19j

^/9, o gt4 OK Reviewer

5) Method T-r o) Flow Sketch (See Below) 4 0 OK Reviewer c&,

e v

/

,4,v s t%

2 /

0

• .,'..:.c

-Z/;

a?

5 vi

.:=.:

_=_

.c

,.3q2 j I I

f 4, I Ck tl e
OL U

7) Calculations O

OK Reviewer c_

J SI.1w det.nr liwation or Surface of ubaurfac

)

Show determination of type of -a to use

__~J

8) fZE-4 Paragraphh.1'-

ad wedwas used 0i Yes Preparer OK OReviewer

__-7>-

0) Code Flaw Dimensions 01<

OK Reviewer

. J 7-5

-a-Z o

-t noinrnoa- '

t measurod

/

s -

w NV A

10) Flaw Type 0 OK Reviewer S

h 5-.-

4,.

1t) Flaw Characterization Figure V

OK Reviewer

,4 3

S t

-/

12) Flow CharacterizatIon Flgurc Number

/

13) Was IWA-3300 Flaw Characterization followed?

< Yes 0

No If no why?

14) The correct Code Edition and Addenda was available and used.

15)

=

Fd by Aan=-,/L.-J

/

Sf >

The rSzfit aae correct and the methodology used Is In accordance with applicable codes. standards. specifications and procedures.

e Yes PreparererC.

0> Ol< RevIewer °_

1G) Rcve a

dal The review assures that the results are correct and the methodology used Is In accordance with applicable codes.

standards. specifications and procedures.

Add,60enat - 131 FI.- SIX.

radiI iro., S.WLu~

Additional - Supplemental Reports <edit from Setup>

NM Summary No.: 500727 Examiner: VENDOR, WESDYNE Examiner NIA Other: NIA Supplemental Report Report No.:

2005VE023 Page:

3 of 9

i Level:

_1 Reviewer: Jones, Thoma Level:

NIA Site Review: Wren, Jerry P Level:

NIA ANII Review: Daly, Gerald S

C8-;iJ Date:

_ _/_ __

Date: 2-c-s Date:

IS4t~x;-c~

Comments:

Sketch or Photo:

J:XlSlDataUSl\\Pl2 05 outage\\ScanstWeDyne Vessel Flawst500727 N-6Flaw Disposition 1.bmp NMC j Sile/Unit:

P Z

/

i Z_

SummaryNo.:

SOO 7,> ;L Workscope:

S ISI Flaw Disposition Worksheet procedure: Ptr-5 '/-sgr-iJ'.Outaoe No.:

P:=z. jep Procedure Rev.: __

Report No.:

_200i vC5 Work Order No.:

) Lb/

Lao 7 c>

Page:

of

1) Flaw Number

/

3) ISI Interval

2) lien, N,,nher EB 3

. q 0

4) Code Edition & Addenda

/ 58 9 A/4

,4..

5) Acceptance Standard ir r-5i s5/ ).;

J6 t

U

^/

6 i6) Calculations (See Below)

O OK Reviower C

OK R.vioar C> OK Review:er pJ O

OK Reviewer 6'

60. 7Q a/p.~ g. Z6-1 t_

-2 01te '%, =

? - / -7

= 5

=

J3-2-

Ce j

/-O

7) Results O OK Roviewcta29_1L.-

nAl -

t.24"7 Code allowable ei/t% -

S.

8 Lv0'-

Calculated &lt%

L

?

Laminar flaw surface nroa: (0.75 1 w)

13) Table used for analysis

• P OK Reviewer°

._1 Zw 3St P a 1f) Was linear Irnterpolation used?

CD Yea Ivl No If no. why?

e9 C C ec>+ P t<

4"z a

IC>'

6

l/

4e C-S 3-42E

10) Was IWA-3200 Significant Digits For Llniting Values (ollowed?

Yes 0 No If no. why?

11) The correct Code Edilion and Addenda was avallable and used.

4i Yes Prsearer 2R& t-

• Ot Reviewer

-T-AtJ

12) Sttlement of accoplability or rejoetabilily with basis.

OK Review-r 7A.

ID Accept 0 Roject 4V (alt) Code allowable (ant) calculated

) OEM flaw evaluation handbook (see attached analysis)

C)

(a/lt) Code allow-able - (alI) calculated 1qrnd by

't

14)

Ieyng and date PM E

-r rra C

JGf 7 /_z' 5-lsulls are correct and the methodology used is In accordance This review assures that thte results are correct and the with applicable codes. standards, specifications and procedures.

methodology used Is In accordance with applicable codes.

standards. specifications and procedures.

t5) Aqroved by anida This approval assures that all Invofvcd with this naw sizing and naw disposition were aware of the necessity that the results and the methodology are correct and In occordanco with applicable codes. standards. specifications and procedures.

Addllon.1 - ISI Fl-w Dlsrpe.llan -. dit *ron-S.top-Additional - Supplemental Reports <edit from Setup>

NM)

Supplemental Report Report No.:

2005VE023 Page:

4 of 9

Summary No.: 500727 Examiner: VENDOR, WESDYNE Examiner: NIA Other: NIA Level:

11 Reviewer: Jones, Thomas Level:

NIA Site Review: Wren, Jerry P Level:

NIA ANII Review: Daly, Gerald Date: 4k<1/os 9

t Date:

-5

-Cs a

Date: ISAL uff S L)

Comments:

Sketch or Photo: J:\\ISIDataXlSl\\PI2_05 outage\\Scans\\WeDyne Vessel Flaws\\500727 N-81Flaw Sizing 2.bmp INM Sitejunit:

P *-

i

.-2.

Summary No.:

So O.

7 Workscope:

S

1) Flaw Number

2) Item Number B

3, 9FO ISI Flaw Sizing Worksheet Procedure:

-Az

-utage No.:

PoXrz fQ S Procedure Rev.:

0 Report No.:

-?OS LEO OA5 Work Order No.:

' YD -

Page:

or

3) ISI Interval

____a O

OK Reviewer 1

4) Code Edition & Addenda

/0 9g0

,.4, O

OK Reviewer

_J

5) Method T

6) Flow Sketch (See t3elow) 0 OK Reviewer t

eI Flaw View A/-S2) s fio 3

=

7 C *.Ab

7) Calculatlons V OK Reviewer.'!S)1 Show deterninatlon of S~ure a

e-)

Show determination or type of 'a' to use

S-I e -.-

g 7-I, 7

8)-is4-FcE-4 Paragraph-r-.

.dW

' Mttj was used

9) Code Flaw Dimensions O

OK Revlewer J

-r

'7.

e' -

0V/0

't nominei

10) Flaw Type OKI Revieworc7 J

1t) Flaw Characterization Figure 4

OK Reviewerr W

12) Flaw Characterization Figure Number

$^ /

'13) Was IWA-3300 Flaw Characterization followed?

O Yes

• P Yes Preparer i0 OK Reviewer 7

t measured' - -

s4 -'_ 3.

2.

_ o s

.- > co

=='

_~ 3

.- /

0 O No If no. why?

14) The correct Code Edition and Addenda was available and used.

I K ebto(/-Uj a

a SfS 5

The Ivults are correct and the methodology used Is In accordance with applicable codes. standards. specfications and procedures.

AddifleOrI - 151 Fltw Si.. '.dit fr e Ct.ip.

• 9 Yes Preparer C

• OK RovilWewerI4.

16) Rw adeI The review assures that the results are correct and the methodology used Is In accordance With applicable codes.

standards. specifications and procedures.

Additional - Supplemental Reports <edit from Setup>

NM&)

Supplemental Report Report No.:

2005VE023 Page:

5 of 9

Summary No.: 500727 Examiner: VENDOR, WESDYNE Examiner: NIA Other: NIA Level:

11 Reviewer: Jones, Thomas Level:

N/A Site Review: Wren, Jerry P Level:

NIA ANII Review: Daly, Gerald

-=Tz
24-Date:

_/_/_s Date:

Y Date: 15SAu,4c Comments:

Sketch or Photo:

J:\\lSlData~lSltPl2_05 outage\\Scans\\WeDyne Vessel Flaws\\500727 N-8\\Flaw Disposition 2.bmp Site/Unit:

P :Z

/

Summary No.:

4 7

3 n Workscope:

2 S ISI Flaw Disposition Worksheet Procedure: P0-Zsr-5'!-s tPlOutaoo No.:

/4lo I

Procedure Rev.:

Report No.:

2Csa5 L/6- 0 Work Order No.:

O

-v 0 eo (, 7 0 Page:

of

1) Flaw Number

3)

ISI Interval

2) Item Number B 3. q? 0 A) Code Edilion & Addenda

5) Acceptance Standard f,

,. /6 ff

) -

6, e) Calculations (See Below)

/5989

"-Vo

.Z'-&V L-

% 5./ aR

• OK Roviawer 40 K Reviewer

-1 O OK Reviewer 4

OK Rnviewar 6'9 =9

~/ 0 j/=

e2,-'7 -

/'

/3.3 ef = 9 - :Z Vlt, = eq, t,/ 0 a 7 vle -Z' = /' 09

3. 7s-/0,

/,o S ~,7

~'-,Vcr

7) Results

• OK Revieer r¶i.

A a/t -

-.9

/ -3 Code allowable a/t% -

.?. 5-Z-s Calculated alrt

/. 09 Laminar flaw surface area: (0.75 1 w) _

I) Tablo used for analysis O

OK Revlewer-7%=

J J.,.

Bt - 3 1

t -,

9) Was linear Interpolation used?

) Yes 0

No If no, why?

xe eL -e

' Ak b Ce.

'e

ico, c

o _

/t.

.r S

C--

10) Wos IWA-3200 Significant Digits For Limiting Values followed?

<0 Yes 0 No If no. why?

11) Tho correct Code Edition and Addenda was avaliable and used.

a Yes Preparer 4P OK Reviewer

12) Statement of acceptability or rejectabilily with basis.

J0 OK Reviewer J

0 Accept O Reject Ql (n/) Code allowable > (n/t) caiculalOd 0 OEM flaw evaluation handbook (see attached analysis)

C) (a/t) Code allowable f (a/t) calculated t

mppred by anddato,

14) Enginooring revig by nnd date

4 d b y Cgd d a v.

__ _0__

The results are correct and the methodology used Is in accordance This review assures that the results are corroect and the with applicable codes. standards. speceficntions nnd procedures.

methodology used Is In accordance with applicable codes.

standards. specifications and procedures.

1 S) Areoved by nd date

• This approval assures that atl.nvolved with this naw sizing and flaw disposition were awaro of the necessity that the results and tho methodology are correct and in accordance with applicable codes. standards. specificatlions and procedures.

Adddhonal - 1t1 Flaw Olsposition "dit from Setup-Additional - Supplemental Reports <edit from Setup>

NM)

Supplemental Report Report No.:

2005VE023 Page:

6 of 9

Summary No.: 500727 Examiner: VENDOR, WESDYNE Examiner: N/A Other: N/A Level:

11 Reviewer: Jones, Thomas Level:

N/A Site Review: Wren, Jerry P Level:

N/A ANII Review: Daly, Gerald

_____),

Date:

Date:

IM Date:

IeSAL-&GqgS L)

Comments:

Sketch or Photo: J:MlSIDataXdS\\P12_05 outage\\Scans\\WeDyne Vessel Flaws\\500727 N-80Flaw Sizing 3.bmp SiteiUnlt:

p Z

/

Summary No.:

-:V O

9 a 7 Workscope:

.2 S

ISI Flaw Sizing Workshteet so I

Procedure:

r

/zOutage No.:

PXz

,-S Procedure Rev.:

o Report No.:

OO.S VI C--2 3

Work Order No.:

e eTg5-6P -7 ;0 Page.

of I

I

1) Flaw Number 3

2) Item Number B

23. 9o lw V w e

/t-S Flaw VI.-

3) ISt Interval S -e

4) Code Edition & Addenda 1 9i?

o/

As2.

5) Method

.4 T-

6) FIDw Sketch (See Oelow) 11 I C 1

It.

OK Reviewer

• OK Reviewer OK Reviewer

-f~e O0 0-3

-Z 0,

,, 5

' a O

^ - s, s

7) Calculations C OK Reviewer 7A. J Show dctermnlratlon of Surlflco orgftissurtac.g>

Show determination oft e oI 'n to use 5 3 S A b e7. '

X -

' 4 )

r.

- A

".A -

I

8)

-r-E-,

Paragraph7-a-4'o..a zrr i..t:

was used

@ Yes Preparer 5

tO OK Rerviewer

______J_

9) Code Flaw Dimensions v

OK Reviewer 4

, ;2 O

5

°

'a

'O.

10

-t nominal

'i1 measured' -

=

M

/

73 v-v-A/l

10) Flaw Type

• & OK Reviewer i

J b t

_.4&.

e-

.- P.

I1) Flaw Characterizatbon Figure C OK Reviewer

=

4 -

S 5:

12) Flaw Charecterization Figure Number a

/

13) Was IWA-3300 FIJw Choracterizatiorn followed?

0 Yes 0 No If no, why?

14) The correct Code Edition and Addonda was avaliable and used.

Q Yen Preparcer !5!e 1105Praparbd Oyd LiV.

e v

10) Review bysad date J The results are correct and the methodology used Is In accordance The review assures that the res with applicable codes. standards. speclncEllons and procedures.

methodology used is In occorda standards. spectficotions and p.

AIditlonal - IS Flaw Size *edt trfn. Setup' O OK Reviewer-=wie. A sults are correct and the inca with applicable codes.

rocoduras.

Additional - Supplemental Reports <edit from Setup>

NMC)

Supplemental Report Report No.:

2005VE023 Page:

7 of 9

Summary No.: 500727 Examiner: VENDOR, WESDYNE Level:

_1 Reviewer: Jones, Thomas Examiner: N/A Other: NIA Level:

N/A Site Review: Wren, Jerry P Level:

N/A ANII Review: Daly, Gerald 9f4i_ &Date:

S_____

S )

Date: ___

JI Date: KA CS Comments:

Sketch or Photo: J:\\lSIData\\iSI\\P12_05 outage\\Scans\\WeDyne Vessel Flaws\\500727 N-8\\Flaw Disposition 3.bmp N

M PZ ISI Flaw Disposition Worksheet Site/Unit:

P Z

/

fit_

Procedure: P-.br :r-Z -5/-So-tV.Outage No.:

P.2f7s SummaryNo.:

s o

7a 7 Procedure Rev.:

__)

Report No.:

VOaS*Vt e'._

3 Workscope:

Z-5 Work Order No.:

6 L.o

(,( G 7 0 Page:

of

1) Flaw Number 3

3) [SI Interval OK Reviewer

2) Item NLumber B& 3..

0 o

4) Code Edition & Addenda

/ 989

/;

4O 0 0

OK Reviewer CJ

5) Acceptance Standard t

g-5 ST / ;

OK Rovtower

-_2 0

O) Calculations (See Below) b OK Reviewer c

l9 6

'!. / O t=

9 _'r =-

5 0

87 VXp =l O g,//{

o-

/

9 7 3 3,73/

, /o

=

3 7, 3

7) Results 0

OK Reviewer oD -

. 09' Code allowable at%

e 0

1A ZColcutalad a/t% -

L O

Laminar now surface area: (0.75 I w) -

8) Table used for analysis 0 OK RevIewor 2;;_

%t3-3

-,;R-,

.)) Was linear Inlorpolntlon used?

0 Yes O No if no. why?

10) Was IWA-3200 Significant Digits For Limiting Values followed?

C Yes O No It no. why?

1t) The correct Code Edition and Addenda was available and used.

0 Yes Preparer 5

Z2 7 OK Reviewor -7Z;J

12) Statement of acceptability or rejectability with basis.

0 OK Reviewer Q_ Accept C Reject Ot (C/t) Coda allowable C (alt) calculated 0 OEM nfw,valtuaton handbook (see attached analysis)

C)

(alt) Code allowable *c (Cat) calculated The TSults are correct and the methodology Used Is In accordance with applicable codes, standards, specifications and procedures.

14) Englnooino review bynd date This review assures that the results are correct and the methodology used Is In accordance with applIcable codes.

standards. specifications and procedures.

1S) Approveyd by ar

`

dale_

rO

_I I

i

- I!,

i)

^-.7

v<

This approval assures that all Inlved with this naw sizing and flaw disposition were aware or the necessity that the results and the nielhodology are correct and In accordance with applicable codes. standards, specifications and procodures.

Addillorwl - 151 Fle.v Disposition -edit freom SetuP-Additional - Supp!emental Reports <edit from Setup>

N M6)

Supplemental Report Report No.:

2005VE023 Page:

8 of 9

Summary No.: 500727 Examiner VENDOR, WESDYNE Examiner N/A Other: N/A Level:

11 Reviewer Jones, Thomas Level:

N/A Site Review: Wren, Jerry P Level:

N/A ANII Review: Daly, Gerald sZ 4 <<ii D ate: _ _ _ _ _/

2/7 Date:

P-s- -cr <5 Date:

ISA LI Comments:

Sketch or Photo: J:%ISIData\\lSl\\Pl2_05 outage\\Scans\\WeDyne Vessel Flaws\\500727 N-8\\Flaw Sizing 4.bmp NM >

SltefUnlt:

P 7

/

-2.

Summary No.:

5 0 7.l 7 Workscope:

S-2

[SI Flaw Sizing Workshect

1) Fln_ Number

2) Item Numher 411/

a~

3.90g Procedure:

.bE_-7

.-,fO tageNo.,

P: zJ/ f Procedure Rev.:

Report No.:

.oos V C2; 3

Work Order No.:

,:9 e i

70 Page:

of

3) JSI Inkerval S0 OK Reviewer

4) Cockd Edition & Addenda J

s4,

$4

_ Y OK Reviewer J

5) Method C4 -r

0) Flaw Sketch (See Feloew)

G) OK Reviewer LA,,-

0 Flaw View I

qjg.

f, %.0,

c

_f

/.0 O

25~

'/

r5 5., --c

7) Calculations O OK Reviewer Show determination of Surface o$&urracei)

Show determination of tye of a to use 7.2 syes prO..-

+

4 OKReviewor 8)-t4-FE-I ParagraphEC-S o -p -f' fi At-i-was used 6t Yes

____Rv e

9) Code Flaw Dimenslons 40 OK Reviewer -77XJ 1-

-n-O_

09. ' 0 t nominal

+/--I '

,s

.sured O

-w- _

t

10) Flaw Type O OK Reviewer T.°C-5 P

11) Flaw Characterization Figure C

OK Reviewer J

A -

5. 3

.2-

_ /

12) Flew Characteizatlion Figure Numbor

^

/

13) Was IWA-3300 Flow Characturizatioi followed?

a Yes 0 No If no. why?

14) The correct Code Edition and Addenda was avevllable and used.

15 r

b ad

-7 L.'J, l r

7 8 The r are correct and the methodology used Is in accordance with applicable codes, standards. specifications and procedures.

(

Yes Preparer f

• OK Reviewer 1-t--'..

1i) Revle k

dcat,!J4 X//2 The review ossures that the results are correct and tle methodology used Is In accordance with applicable codes.

standards. specifriations end procedures.

Addj,0 -

1~.

M5 Ftla, Six... d~t trol r S.I.,p.

Additional - Supplemental Reports <edit from Setup>

NM)

Supplemental Report Report No.:

2005VE023 Page:

9 of 9

Summary No.: 500727 Examiner: VENDOR, WESDYNE Examiner: NIA Other: N/A Level:

II Reviewer Jones, Thomas Level:

NIA Site Review: Wren, Jerry P Level:

N/A ANII Review: Daly, Gerald Date:

s d4M Date: iSAocct LI Comments:

Sketch or Photo: JAISIDatallSl\\P12_05 outage\\Scans\\WeDyne Vessel FlawsX500727 N-8\\Flaw Disposition 4.bmp Site/Unit:

P Z

/

Summary No.:

fTQQ -

7, 7

Workscopo:

.5

=-S ISI Flaw Disposition Worksheet e of0 I

Procedure: Pbz7-xsr-

. 5-s-- tPZOrta;i No PZr% eF -;

!S Procedure Rev.:

C)

Report No.:

Vc0s Vd/

e.) 3 Work Order No.:

O L/O C >

7 0 Page:

of I

i I

1) Flaw Numbor

2) tlem Nu1mber I/

'B
---5. - C? 40

3) ISI interval

_Q

4) Code Edition & Addenda

/98

" O/a d"

5) Acceptance Standard

& g'-

3 a'7.

6) Calculations (See Lietow) 0 OK Reviewer Q)

OK Reviewer J

oC OK Reviewer

-rnv, S

C0 OK Roviewer

-r7-,,, S) 16' =

9. /a Y

1=

- 0 aV/

1p -

./ Q 0/
' -Z e9- 0187 vle 7- =

/'

0
7 r(=

s/s' 0

o z

7) Results O OK Reviewer ai -

O.

/0 Code allowable a/t%

.5 Calculated o/t%

7...

Laminar flaw surfaco aren: (0.75 1 w) tt) Table used for analysis Qt OK Reviewer J

w a

-t - /

0) Was linear irlterpolation usod?

0 Yes V No If no. Why?

.- /6,-'

Re e C-.,

-- Z-elO

10) Was IWA-3200 Significant Digits For Limiting Values followed?

C) Yes 0 No Ir no, wtTy?

11) Tho correct Code Edition and Addenda was available and used.

t-Yes Preparer C ) OK Reviewer J

12) Staternent of acceptability or rojectabillty with basis.

0 OK Reviewer 4_

3 0

Accept 0 Reject 4

(a/t) Code allowable >- (a/t) calculated 0

OEM flow evaluation handbook (see attached analysis) 0 (tit) Corde nilawahble (sit) calculated

13) fby 8ng

,L....JL-

/

8-The r sare correct and the methodology used Is In accordance with applicable codes, standards. spocificatlons and procedures.

14) Enjiineorina review by and date

//

This review assuros that the results are correct and the methodology used Is In accordance with applicable codes.

standards, specifications and procedures

15) Apoved by ardate This approval assures that alfinvolved with this naw sizing and naw disposition were aware of the necessity that tlha results and the methodology are correct and In accordance with applicable codes, standards, specifications and procedures.

Addillonal - 151 Flaw DlsposItIon 'Odit fron Setup-Additional - Supplemental Reports <edit from Setup>

REACTOR VESSEL WELD RESULTS

SUMMARY

PLANT NAME Prairie Island Unit 2

WELD NO.

N8 (500727)

COMPONENT Safety Injection Noz-Shell @108.50 LIMITATIONS:

NO 1

YES 3j 59.26 % Complete See Coverage Breakdown Sheet RESULTS NO. OF INDICATIONS 4

NI STATUS Code Allowable RI X

EXAM DOCUMENTATION INDICATION DOCUMENTATION 37I PARAGON ANALYSIS LOG mEASSESSMENT SHEET El PARAGON ACQUISITION LOG EKII PARAGON HARD COPY FLE SCAN PRINT OUT

= OTHER (Specify)

LKII COVERAGE BREAKDOWN Comments:

Coverage calculation is based on the Bore and Star scan (combined) as perpendicular, and the Tan Scan (parallel).

Figure 1 illustrates the obstruction to scanning, the nozzle protrusion.

l t Analyst b,,

ate:

5

R.V. COVERAGE ESTIMATE BREAKDOWNS PLANT NAME Prairie Island WesDyne WELD NO.

N8 (500727)

International COMPONENT Safety Injection Noz-Shell @108.5° BEAM ANGLE BREAK DOWN BEAM DIRECTION 45 Shear 45 L Single 45 L Dual Combined Bore/Star WELD I VOLUME IWELD lVOLUME WELD I VOLUME WELD I VOLUME TAN Scan Parallel 15.55 57.14 0.00 53.66 0.00 28.10 Combined Bore&Star Perpendicular 97.40

88. 15 AVERAGE 36.35 26.83 14.05 92.78 Comments:

Coverage calculation is based on the Bore and Star scan (combined) as perpendicular, and the Tan Scan (parallel).

Figure 1 illustrates the obstruction to scanning, the nozzle protrusion.

Combined Perp.

92.78

_pObined Para.

I 25.74 Analyst

'- +1-I

Figure 1 Tan Coverage Illustration of the Safety Injection Nozzle

NM)

Ultrasonic Examination Site/Unit:

PINGP /

Summary No.:

5 Workscope:

P12 00726 Is' Procedure:

Procedure Rev.:

Work Order No.:

UT-Vendor 0

0406670 Outage No.:

E031 Report No.:

2005VE024 Page:

1 of 7

Code:

1989 Edition Cat./ltem:

B-DIB3.90 Location:

Containment Drawing No.:

2-ISI-40

==

Description:==

SI Nozzle to Vessel Weld Loop B System ID:

RV Component ID: N-11 Size/Length:

NA Thickness/Diameter 9.17"/11.58" Limitations:

None Comments:

See supplements and Refer to the applicable WesDyne report found in the book:

Prairie Island Nuclear Power Plant / Unit 2 1 0-Year Reactor Vessel Inservice Examinations Interval 3, Period 3, Outage RF023 2005

• 59.26%, See Wes Dyne final report for details.

Results:

NAD D IND i GEO Percent Of Coverage Obtained > 90%:

• No Reviewed Previous Data:

Yes Examiner Level II Signature Date Reviewer Signature Date VENDOR, WESDYNE 5/15/2005 Jones, Thomas i&1/ G.J-5/S Examiner Level N/A Signature Date Site Review Signature v

Date NIA Wren, Jerry P e

Vt/l-..--

Other Level N/A Signature Date ANII Review Signature Date N/A Daly, Gerald

NM)

Supplemental Report Report No.:

2005VE024 Page:

2 of 7

Summary No.: 500726 Examiner: VENDOR, WESDYNE Examiner: NIA Other: NIA Level:

_1 Reviewer: Jones, Thomas Level:

NIA Site Review: Wren, Jerry P Level:

NIA ANII Review: Daly, Gerald d 5 Date: _______

Date: ___

Date:

1 Comments:

Sketch or Photo: J:UlSIData\\ISI\\PI2_05 outage\\Scans\\WeDyne Vessel Flaws\\500726 N-1 1\\FIaw Sizing I.bmp N

Slte/Unit:

P

/

B.2 Summary No.:

-5 OO 7 a L.

Worksoope:

.Z*

ISI Flaw Sizing Worksheet Procedure:

X-Aot No.:

PX.<

Re fO-Procedure Rev.:

a Report No.:

?oC5 VF Work Order No.:

e SzO6,( 2;70 Page:

of

1) Flaw Number

2) Item Number a/ag 6: tj I

3) ISI Interval

4) Code Edition & Addenda J 9IVY

,v X.

6) Method ri

0) Flaw Sketch (See Delow)

Flaw View P OK Revlewer O

OK Reviewer

-W OK Reviewer

.L =0l ' ao

<O.

- 4A O.

=

'o.1 4' J'r

>D.Zz 4

o Z

R

,/

et. -

.3 0

7) Calculations O OK Reviewer Show determination of Surface 3

Show determination of t e or a to use

..J' I -AM1, e - #'e -' I

'Z gVg,;4ts.. 3 t 4.--

8)4B4-v-4Par 7-7 ;

-- 4PZ ws s

8) lMI FE. Paragrapha-7-.

Ir* r was used C

Yes Preparer !Z E

J

@) OKI

9) Code Flaw Dimensions M OK Reviewer

° r- _

'Q

'a' -

5 00 I nominal - -

_9..

-t

,rreasured -

q.

nZ

10) Flaw Type O

OK Reviewer rl4k

_5 b

'.. s -*

P

^_

t 1) Flaw Characterization Figure 0

OK Reviewer

-7 J,4 3

. S

- /

12) Flaw Characterization Figure Number a

/

13) Was IWA-3300 Flaw Characterization followed?

• " Yes 0 No If no. why?

Reviewer w

5ds

14) The correct Code Edition and Addenda was avaliable and used.

15) P by ar 7-/B -os'*

The resu 4 are correct and the methodology used is In accordance with applicable codes, standards, specifications and procedures.

Addftional - ISI Flaw Size -edit from Setup' Co Yes Preparer "ZjP4

'11 OK Reviewer -71% j

16) Reve bv a:~

7ate IO 5-The review assures that the results are correct and the methodology used Is In accordance with applicable codes.

standards. specifications ancd procedures.

Additional - Supplemental Reports <edit from Setup>

NM)

Summary No.: 500726 Examiner: VENDOR, WESDYNE Supplemental Report Report No.:

2005VE024 Page:

3 of 7

Level:

11 Reviewer: Jones, Thomas Examiner NIA Other: NIA 9-xs J Date: *6 A'17T a2E Date:,-a-c, Level:

NIA Site Review: Wren, Jerry P Level:

NIA ANII Review: Daly, Gerald Abr)

Date: ILAu&o U'

Comments:

Sketch or Photo:

J:ulSIData\\ISI\\P12 05 outage\\Scans\\WeDyne Vessel Flaws\\500726 N-i 1\\Flaw Disposition 1.bmp NFLVID SlterUnit:

P Z'

/

Summary No.:

goo 7

Worksoope:

ISI Flaw Disposition Worksheet Procedure: Pb r

5!

s-- tJOutage No.:

Pz'Z /ex Procedure Rev.: __

Roport No.:.0oos dVC 40 S/o Work Order No.:

4 C-`0 Co o 7 0

Page:

of

1) Flaw Number

/

2) Item Number B

2. ?

0 LA I-L_ *,

d t

3) ISI Interval

t

4) Code Edition & Addenda

/ 98 9 A/a '4"'

5) Acceptance Standard El 1

s.

2

0) CalculatIons (See Below) 0 OK Reviewer q-Z2k J 4D OK Reviewer c,

J I

OK Reviewer 7

Z OK Roviewer 6 -

0, J=

1,0

/,p 0'. 30 e-=

9-2...

-7e-=e9. 0-32 4 '

r K 1_7 t /,/

'/

K9.' 30 ~-_

L...es C_

- 0

7) Results 0

OK Reviewer

.-1 =

.0. 5 0 Code allowable a/t% -

C/, */

Celculated ent%

Z a) Table used (or analysts AW O< Reviower x

J J a-3S _,R I; i

fi) Was linear Interpolation used?

C) Yes 4

No If rno. why?

1 Ws A g avt itcr L mit-ng V o

ed 1

Ys

10) Was IWA-320z0 Signtricant Digits For Limiatingf Vniues followed?

til Yes O5 Lamninar nlw surface area: (0.75 I w) 4 No Ir no. why?

t 1) The correct Code Edition and Addenda was available and used.

O Yes Preparer

• 4 OK Reviewer J J

12) Statement of acceptability or rejectability with basis.

0 OK Reviewer -

J Accept I= Reject li (a/t) Code allowable > (alt) calculated C) OEM flaw evaluation handbook (see attached analysis)

CO (0/I) Code allowable.

(n/t) calculaled 13),Proppred by d P Ii g---,

12__ RI 5-Thresults are correct and the methodology used Is In accordance with applicable codes. standards. specilications end procedures.

14) Engineering rev w byan date 7

This review assures that the results are correct and the methodology used Is In accordance with applicable codes.

standards. specincatlons nnrt procedures.

15) Ap

pydbyarilda This approval assures that al involved with this flaw sizing end lnow disposition were aware of the necessity that the results and the methodology are correct and in accordance with applicable codes. standords. specificatIons and procedures.

Adictonal - ISI Flaw ilsposltion edal frrom Setup>

Additional - Supplemental Reports <edit from Setup>

NM)

Supplemental Report Report No.:

2005VE024 Page:

4 of 7

Summary No.: 500726 Examiner: VENDOR, WESDYNE Examiner:

N/A Other: N/A Level:

11 Reviewer: Jones, Thoma Level:

N/A Site Review: Wren, Jerry P Level:

N/A ANII Review: Daly, Gerald S

'=,

_J Date:

SZa Date:

A-&

--, S ffi Date:

%Aut,<§ L)

Comments:

Sketch or Photo: J:\\ISlData\\lSl\\PI2_05 outage\\Scans\\WeDyne Vessel Flaws\\500726 N-11\\Flaw Sizing 2.bmp Site/Unit:

p:

r-1 Summary No.:

00 e R

Workscxpe:

a 5:r ISI Flaw Sizing Workshicet Procedurc:

-r22/

Outage No.:

PX°2Z.

C F s~ s Procedure Rev.:

a ReportNo.:

.,0OS v 0r Work Order No.:

e9 D£<

70 Page:

of

1) Flaw Number

2) Item Number a

90

3) ISI interval

_g_ _

4) Code Edition & Addenda

/ 9q 4,,4,7Y

5) Method qt T (3) Flaw Sketch (See Below)

Fl w. /VQe Flaw vie_

A/-

//

I 1----..--.-
-.--....--

O,

I it

.=

O.

9, 1,9 "

I

--I 4

Is.

-g "

a

%V OK Reviewer-na,

& OK Qeviewer O

OK Reviewer ov-

/= z

7) Calculatlons O

OK Reviewer 7

Show determinatIon of Surface o

Show determination oftype oI Ia to use Ir -Ad6

'-C F-C

'6 s-4-...#

8)+40-FB-4 Paragraph-7cr. -

-f 1...I J was used

9) Coda Flow Dimonsions O OK Revlewer9f-..J

_1_

O" 7

n--

. Z It notmnai

-t

10) Flow Type C OK Reviewer 1 1) Flaw Characterizalion Figure O OK Reviewer C

j

12) riow Characterization Figure Number

/

13) Was IWA-3300 Flaw Characterization followed?

• Yes C

Yes Preparer C

0 OK Roviewor J tnens-rod l

a -r

.9 7

S -

C P

Ot-r C

2 4-3 3aBrt

/

0 No If no. why?

14) The co-reut Code Edition and Addenda was availablo e nd used.

15!

re rad by a1 y

iL L,_

1 The rAultS are correct and the methodology used Is In accordance with upplicutble codes, standards. specincations and procedures.

Arlrt-tionaI.

SI Flew Size <ed-l fon, Sehtup 41 Yes Preparer (

OK Reviewer z2-

/

16)

Revo Obv-dVt

-172,1/D5 The rerview assures that thlr results are correct and the methodology used Is In accordcance with rpplicable codes.

standards. specifications and procedures.

Additional - Supplemental Reports <edit from Setup>

NM)

Supplemental Report Report No.:

2005VE024 Page:

5 of 7

Summary No.: 500726 Examiner VENDOR, WESDYNE Examiner. NIA Other. NIA Level:

11 Reviewer: Jones, Thomas Date:

__/5 Level:

N/A Site Review: Wren, Jerry P Level:

NIA ANII Review: Daly, Gerald J4dC~

Date:

F_ ?:i b;

Date: I6AL64c U

Comments:

Sketch or Photo: JAISIData\\ISI\\PI2_05 outage\\Scans\\WeDyne Vessel Flaws\\500726 N-1 1XFlaw Disposition 2.bmp Pi M >

She/Unit:

P ZX i

Summary No.:

5 C;)

-7.A t Workscope:

2 ISI Flaw Disposition Worksheet Procedure:

P-..ra r-2 pJLOutago No.:

P 2 2e O Procedure Rev.:

Report No.:

l zo-5 Ve Od I Work Order No.:

O Z' 0 (z e 7 0 Page:

°'of

1) Flaw Number o;z

2) Item Number B3. 4? 0 6

C L d

4 ti I

3) 1SI Interval A) Code Edition a Addenda

/7 8 g o

AO

5) Acceptance Standard R-5!t $. / i

6) Calculations (See Below) 1 OK Reviewer Ct O

O1K Reviewer 7_

@ OK Reviewer C____

O OK Reviewor 6'2 -

J~ =

O-7.5 V/

33 3

Vlte'

=

2. -7 2-r

=

=

/7-5"7-a Z

15 e- "$c5

/-

'e

7) Rusults O

OK Reviewer J

?,-

.33 3 Code allowable n/t% -

V-. V 4Za4Calculated atl% -

.2' -7.2

13) labte used for analysis o

OK Reviewer'

Z-e

- 3 5_ I-

-I

9) Was linear Interpolation used?

o Yes O

No It no. why?

1 ) W.3 SC

- ig i i n Di gi C-eF o L m i V l e o Jl o e ?

es

10) Wns IWA.3200 Significant Digits For Limiting Values followed?

O0 Yes O)

Laminar naw surface area: (0.75 1 w).

^/4 ce -

4-/, '/

No It no. why?

11) The correct Coda Edition and Addenda was available end usad.

@ Yes Preparer 0

OK Reviewer c,

J

12) Statement of acceptability or rejectabilitywlth basis.

O OKRoviewer

-1

/

Accept 0 Reject

!L (alt) Codo allowable > (aft) calculated O

OEM flaw evaluation handbook (see attached analysis) o (alt) Code allowable e (Wit) calculated 13teaoared b sid crite a

Tl 1Msults are correct end the methodology used Is In accordance with applicable codes. standards. specifications and procedures.

14) Engineering reviewby nnd date This review assures that the results are correct and the methodology used Is In accordance with applicable codes.

standards. specifications and procedures.

1 5) Approved by ante t

• I o: t'4w _w b ° 0-This approval assures that all Innoived with this flaw sizing and flaw disposition were aware of the necessity that the results and the methodology are correct and In accordance with applicable codes. standards. specirications and procodures.

AOCtdtiorol - ISt Fta-DlsPoslltin -edit tram, 5*1uP-Additional - Supplemental Reports <edit from Setup>

NME )

Supplemental Report Report No.:

2005VE024 Page:

6 of 7

Summary No.: 500726 Examiner: VENDOR, WESDYNE Examiner:

N/A Other: NIA t

Level:

11 Reviewer: Jones, Thoma Level:

NIA Site Review: Wren, Jerry P Level:

N/A ANII Review: Daly, Gerald s

ti-Date:

Date: e-S; -L(.-

Date: _67AC66r A<n

"-1*rl C-Comments:

Sketch or Photo: J:\\lSlData\\ISl\\PI2_05 outage\\Scans\\WeDyne Vessel Flaws\\500726 N-1 1Flaw Sizing 3.bmp Site/Unit:

Op r

/

Summary Na.:

5C70 71 to Workscope:

Z

.1' 7

1) Flaw Number

.3

2) Item Number B

'j70 ISI Flaw Sizing Workslhieet Procedure:

PZ-1sr-C/-,5Z--NeOutage No.:

P:.2?-J rfAtoS Procedure Rev.:

O Report No.:

No V

t E f

Work Order No.:

e:

& -7 0 Page:

of

3) tSI lntervel S _R 0

OK Reviewer

4) Code Edition & Addkanda

/ 979 34 4

@ OK Reviewer c

J

5) Method tf

-r'

6) Flaw Sketch (See Below)

Vt OK Reviewer c

_t Flaw View A-. -

}/

I I_

i I

- _T q"t

.2 4

>1 0.

-/

Z_

-P =

y 0 -I/

../ X M. eq I 0 (a 1.

.r.'r.5 >. /.o -A.-

Z.,_-Zr
..

/.

&'/

>a.

0(' = '.

b

1. - c-e ck =.

X

CL ek

=

P,

-.5-

7) Calculations At OK Reviewer Show determination of Surface oiZubsufVe\\

Show determination of type of -a' to use J

IA s,

E) 44rr-FE-4 Paragraph-7-. -

R

-a

¶.:I J was used O Yes Preparer OK Reviewer

0) Coda Flaw Dtnmensions A0 OK Reviewer

____j___

7 a2 5_

Lt nons,7,t0

.2 --._

meepsured -

/

-w-

10) Flaw Type CD OK Reviewer I

S

1.

5.

..4,,..

P e-p

11) Flaw Characterization Figurr At OK Ravlower J

C Z

.o 4 _

3 3

/

12) Flaw Characterizaton Figure Number

/

13) Was IWA-3300 Flow Charactcrizalion fotlowed?

• Yes 0 No If no, why?

14) The correct Code Edition end Addenda was available and used.

!5Pp red bYd c,

,L

.7-2-

The results are correct and the methodology used Is In accordance with applicable codes, standards. specifications and procedures.

e Yes Preparer G0 OK RevIewer l7J.4

16) Revw bnnd dale C

J C7/_-2j,

/p The review assures that the results are correct and the methodology used Is In accordance with applicable codes.

standards. specifications end procedures.

Add~tienal - ISt Flws Sir* -edit Iron r-..P~

Additional - Supplemental Reports <edit from Setup>

NMC)

Supplemental Report Report No.:

2005VE024 Page:

7 of 7

Summary No.: 500726 Examiner: VENDOR, WESDYNE Examiner:

NIA Level:

11 Reviewer: Jones, Thomas c=r J

Date:

Level:

N/A Site Review: Wren, Jerry P 9 o)

Date: _ '__ __

Date: I 1AL,&6S Other: NIA Level:

NIA ANII Review: Daly, Gerald U-Comments:

Sketch or Photo: J:lSIDatalSl\\Pl2o05 outage\\ScansNWeDyne Vessel Flaws\\500726 N-1 1\\Flaw Disposition 3.bmp Site/Unit.

t

/

I Summary No.

5, O

o

a.

C-Workscope:

2-S ISI Flaw Disposition Workshect Proceduro: PbZ-.sl-As/f--

tJl-Outage No.: Prs Procodure Rev.:

C)

Report No.:

Voos_ VC eOJ V Work Order No.:

4 9

O Co te 7 0

Page:

of

1) Flaw Number

2) itemi Numbar 3;

'E

. C? o 3)tSt IInterval

4) Code Edition & Addenda

/ F89

./t /a AA7

5) Acceptance Standard Zt&V a-T S / E;2 G) Calculations (See s3olow) q9 OK Reviewer f

OK Reviewer C

J M

OK Reviewer e_l 7

OK Reviewer

~

O- / 7S J

-=

!V,-7 e-=

17 -

2)

-/Y

=- O.

O le,&-

/G3 g = -5/1, = /.(Oa3 /0,

=.

O,

/0I L. 5 C--

/.

C

7) Results OK Reviewer 3

n

- g 7. 2Z 0

Code allowable aft% -

3 - 3 Calculated a/t% -

/,

6 -3

0) Table used for analysis

'0, OK Reviewer

,J

zr e -

3 5-t

-/

0) Was linear interpolation used?

C Yes fP No Of no. why?

-AS i t a a

L i m i in a

u e f O sllo e dY

10) Was IWA^-3200 Significant Digits For Limitling Values followved?

a Yes C)

Laminar now surface area: (0.75 1 w) -

No If no. why?

I 1) The correct Code Edition and Addenda was available end used.

0 Yes Preparer r7_0

12) Statoment of acceptability or rejectability with basis.

0 OK Reviewer "

J a

Accept

@ (ant) Code allowable a (alt) calcultled 0

OEM flow evaluation handbook (see attached analysis)

C) (aft) Code allowable c (alt) calculated C OK Reviewer

-7 0

Reject

.,d.gy zv 7-IS-oS-results are correct and the methodology used is in accordance with applIcable codes. standards. specifications and procedures.

14) a Terin revie by and do te

.z 7

5 This review assures that the results are correct and the methodology used is In accordance with appiloble rodes.

standards. specifications and procedures.

15) Ap roved bynd dtol

/O

-1 t

nsl1 approval assures thatie involved with this law sizing and naw disposition were aware oo the necessity that the results and the methodology are correct and In accordance with applicable codes, standards. specifications and procedures.

Addt.t.l

- ISO Fla-DO,.posillo,, '-dil from Saluo4 Additional - Supplemental Reports <edit from Setup>

REACTOR VESSEL WELD RESULTS

SUMMARY

PLANT NAME Prairie Island Unit 2

WELD NO.

Ni1 (500726)

COMPONENT Safety Injection Noz-Shell @ 288.50 LIMITATIONS:

NO Fj YES [I 59.26 % Complete See Coverage Breakdown Sheet RESULTS NO. OF INDICATIONS 3

NI STATUS Code Allowable RI X

EXAM DOCUMENTATION INDICATION DOCUMENTATION

[!JPARAGON ANALYSIS LOG EXIASSESSMENT SHEET WE1PARAGON ACQUISITION LOG E-7IPARAGON HARD COPY 3Fl SCAN PRINT OUT

[=IOTHER (Specify)

WCOVERAGE BREAKDOWN Comments:

Coverage calculation is based on the Bore and Star scan (combined) as perpendicular, and the Tan Scan (parallel).

Figure 1 illustrates the obstruction to scanning, the nozzle protrusion.

Analyst Date:

PLANT NAME R.V. COVERAGE ESTIMATE BREAKDOWNS Prairie Island WesDyne WELD NO.

N11 (500726)

International COMPONENT Safety Injection Noz-Shell @ 288.50 BEAM ANGLE BREAK DOWN BEAM DIRECTION 45 Shear 45 L Single 45 L Dual Combined Bore/Star WELD VOLUME l WELD lVOLUME WELD IVOLUME l WELD lVOLUME TAN Scan l

l lllll Parallel 15.55 57.14 0.00 53.66 0.00 28.10 l ll Combined Bore&Star Perpendicular 97.40 88.15 AVERAGE 36.35 26.83 14.05 92.78 Coverage calculation is based on the Bore and Star scan (combined) as perpendicular, Comments:

and the Tan Scan (parallel).

Figure 1 illustrates the obstruction to scanning, the nozzle protrusion.

Combined Perp.

Analyst 92.78 Combined Para.

AA In

-1 f

e 25.74 Combined Average 59.26 Date

• /) 5kS

Figure 1 Tan Coverage Illustration of the Safety In jection Nozzle

REV.

TRF.O 4-0o 1 8 NORTH

1. 22 STEAM GENERATOR CONT ON DWG 2-ISI-33C l

CONT ON DWG 2-ISI-33B CONT ON DWG 2-IS1-31 so.

CONT ON DWG 2-ISI-19 ON DWG 1-20A WELD 5 DETAIL WELD 1 DETAIL WEST

= WELD NO.

REACTOR COOLANT LOOP

//B //

XH-1 XH-1 REF: XH-1 001-388 001 -1182 106-7028 IFILE NO:2133ARO1 NS'P(M&SP)-PI-2 l:-

sd' DWN: DMN CHKD k, B APPD: Y6MUjt SYSTEM:REACTOR COOLANT LINE: 29 2RC-1B IDWG:

2-ISI-33AI REV: 02

N)

Site/Unit:

PINGP /

Summary No.:

Workscope:

UT Pipe Weld Examination P12 501137

[SI Procedure:

Procedure Rev.:

Work Order No.:

SWI NDE-UT-11 0

0406678 Outage No.:

E031 Report No.:

2005U036 Page:

1 of 5

Code:

1989 Edition Cat./ltem:

B-F/B5.70 Location:

Containment Drawing No.:

2-ISI-33A

==

Description:==

50 Red Elbow-Nozzle System ID:

RC Component ID: W-5 Size/Length:

2.0"/110" Thickness/Diameter:

2.9"/29"ID Limitations:

See Supplements StartTime:

15:20 Finish Time:

16:08 Examination Surface:

Inside M Outside i Surface Condition: Blended Lo Location:

TDC Wo Location:

Centerline of Weld Couplant:

Sonotrace 40 Batch No.:

1. 02243 Temp. Tool Mfg.:

PTC Instruments Serial No.:

P11l Surface Temp.:

86

• F Cal. Report No.:

2005CA034, 2005CA035, 2005CA036 AngleUsed 0

45 1 45T 1 60 N/A l

N/A Scanning dB 42.0 84.0 80.0 N/A NIA N/A Indication(s):

Yes D No i Scan Coverage:

Upstream i Downstream a CW Ri CCW i Comments:

Scanned at reference due to excessive noise @ +6 dB. 0° exam performed by J. Timm - Exam start 00:23, exam end 04:00 on 5123105 Results:

NAD i IND a GEO Percent Of Coverage Obtained > 90%:

No Reviewed Previous Data:

Yes Examiner Level Ill Signature Date Reviewer Signature Date Blechinger, Todd P.

512212005 Hailing, David A.

Examiner Level II Signature Date Site Review Signature Date Timm, Jeremy T.

5/23/2005 Wren, Jerry Other Level N/A Signature Date ANII Review Signature Date N/A Daly, Gerald

NM) 0

`0 -

O Determination of Percent Coverage for UT Examinations - Pipe Site/Unit:

PINGP /

P12 Summary No.:

501137 Workscope:

ISI Procedure:

SWI NDE-UT-11 Procedure Rev.:

0 Work Order No.:

0406678 Outage No.:

E031 Report No.:

2005U036 Page:

2 of 5

45 deg Scan 1 Scan 2 Scan 3 Scan 4 100.000 0.000 100.000 100.000

% LengthX

% LengthX

% Length X

% Length X 100.000 0.000 67.690 67.690

% volume of length / 100 =

% volume of length / 100 =

% volume of length / 100 =

% volume of length / 100 =

100.000 0.000 67.690 67.690

% total for Scan I

% total for Scan 2

% total for Scan 3

% total for Scan 4 Add totals and divide by # scans =

78.460

% total for 45 deg Other de- -

(to be used for supplemental scans)

The data to be listed below is for coverage that was not obtained with the 45 deg scans.

Scan 1 Scan 2 Scan 3 Scan 4

% LengthX

% LengthX

% LengthX

% LengthX

% volume of length / 100 =

% volume of length / 100 =

% volume of length / 100 =

% volume of length / 100 =

% total for Scan 1

% total for Scan 2

% total for Scan 3

% total for Scan 4 Percent complete coverage Add totals for each scan required and divide by # of scans to determine; 78.460

% Total for complete exam Site Field Supervisor Date:

Additional - Calculation Pipe <edit from Setup>

Supplemental Report Report No.:

2005U036 Page:

3 of 5

Summary No.: 501137 Examiner: Blechinger, Todd P.

Level:

Ill Reviewer Halling, David A.

Date:

Examiner: Timm, Jeremy T.

Level:

Ill Site Review: Wren, Jerry Date:

Other: NIA Level:

NIA ANII Review: Daly, Gerald Date:

Comments: W-5 Coverage Plot Sketch or Photo: J:\\lSIData\\lSI\\Pl2_05 outage\\Scans\\2005U036 501137 coverage plot.jpg

~~~~~~~~~~&1- :- :,.:. -.-:.--:

'- ' ~/..

I.'

Additional - Supplemental Reports <edit frm Setup>

..,..7.:

NMP-Supplemental Report Report No.:

Page:

Summary No.: 501137 Examiner: Blechinger, Todd P.

Examiner: Timm, Jeremy T.

Other NIA 2005U036 4

of 5

Date:

Date:

Date:

Level:

IlIl Reviewer. Hailing, David A.

Level:

IlIl Site Review: Wren, Jerry Level:

NIA ANII Review: Daly, Gerald Comments: Limitation sketch W-5. No scans on nozzle side due to configuration.

Sketch or Photo: J:AISIData\\ISI\\P12_05 outage\\Scans\\2005U036 Limitation Sketchjpg W.

PKi

edr i

Additional - Supplemental Reports <edit from Setup>

NMC)

Supplemental Report Report No.:

Page:

Summary No.: 501137 Examiner: Blechinger, Todd P.

Examiner: Timm, Jeremy T.

Other: N/A 2005U036 5

of 5

Date:

Date:

Date:

Level:

Ill Reviewer: Halling, David A.

Level:

Ill Site Review: Wren, Jerry Level:

N/A ANII Review: Daly, Gerald Comments: W-5 Limitation Photo SketchorPhoto:

J:\\ISIData\\ISIXP12 05outage\\Photos\\TODD\\5-25\\DSCO1640.JPG Additional - Supplemental Reports <edit from Setup>

.Mmv.

H.U4-l CONT ON DWG 2-ISI-10B EL. 699'-O 1/4" as EL. 718'-9 5/8" NORTH INTEGRAL ATTACHMENT WES 0

I EL1

= HANGER NO.

= WELD NO.

= BOLT NO.

= VALVE NO.

REF: XH-1 106-2550 IFILE NO:2110AR05 8" RHR TAKEOFF LOOP "A" HOT LEG 1\\S(

MSP)-P1-2 I S.I DWN: CADWorksCHKD: UL-APPD:

9, SYSTEM:RHR TAKEOFF L INE: 8-2RH-lA. 8-2RC-15A

_DWG:

2-ISI-10A IREV: 06

'MC >

Site/Unit:

PINGP /

Summary No.:

UT Pipe Weld Examination P12 Procedure:

Procedure Rev.:

SWI NDE-UT-16A Outage No.:

E031 Report No.:

2005U024 501953 1

Workscope:

ISI Work Order No.:

0406678 Page:

1 of 5

Code:

1989 Edition Cat./ltem:

B-J/B9.11 Location:

Containment Drawing No.:

2-ISI-10A

==

Description:==

Valve to Pipe System ID:

RH Component ID: W-11 Size/Length:

.9" /27" Thickness/Diameter:

.812" /8" Limitations:

See Supplements Start Time:

14:20 Finish Time:

14:40 Examination Surface:

Inside E Outside i Surface Condition: Flat Topped Lo Location:

TDC Wo Location:

Centerline of Weld Couplant:

Sonotrace 40 Batch No.:

1. 02243 Temp. Tool Mfg.:

PTC Instruments Serial No.:

Pill Surface Temp.:

71

°F Cal. Report No.:

2005CA025, 2005CA026, 2005CA027 Angle Used 0

45 45T 60 60 RL l NIA Scanning dB NIA 36.0 36.0 43.0 59.0 N/A Indication(s):

Yes El No i Scan Coverage:

Upstream E Downstream ia CW i CCW i Comments:

Single sided exam - exam performed through 100% of code volume, however procedure not qualified for detection on far side. Best effort exam on far side volume.

No scans on valve side due to configuration.

Results:

NAD i IND []

GEO C Percent Of Coverage Obtained > 90%:

No Reviewed Previous Data:

N/A Examiner Level Ill Signature Date Reviewer Signature Date Blechinger, Todd P.

5/19/2005 Hailing, David A.

5/23/2005 Examiner Level II Signature Date Site Review Signature Date Jensen, Arlen 5/19/2005 Wren, Jerry 5/2412005 Other Level N/A Signature Date ANII Review Signature Date N/A Daly, Gerald 5/27/2005

NM7I) aN.M Determination of Percent Coverage for UT Examinations - Pipe Site/Unit:

PINGP /

P12 Summary No.:

501953 Workscope:

ISI Procedure:

Procedure Rev.:

Work Order No.:

SWI NDE-UT-16A 1

0406678 Outage No.:

E031 Report No.:

2005U024 Page:

2 of 5

45 den Scan 1 88.920

% Length X 44.460 Scan 2 88.920

% Length X 44.460 Scan 3 100.000

% Length X 50.000 Scan 4 100.000

% Length X 50.000

% volume of length / 100 =

% volume of length / 100 =

% volume of length / 100 =

% volume of length /100 =

39.534

% total for Scan 1 39.534

% total for Scan 2 50.000

% total for Scan 3 50.000

% total for Scan 4 Add totals and divide by # scans =

44.767

% total for 45 deg Other deg -

(to be used for supplemental scans)

The data to be listed below is for coverage that was not obtained with the 45 deg scans.

Scan I Scan 2 Scan 3 Scan 4

% LengthX

% LengthX

% LengthX

% LengthX

% volume of length /100 =

% volume of length /100 =

% volume of length / 100 =

% volume of length / 100 =

% total for Scan 1

% total for Scan 2

% total for Scan 3

% total for Scan 4 Percent complete coverage Add totals for each scan required and divide by # of scans to determine; 44.767

% Total for complete exam Site Field Supervisor Date:

Additional - Calculation Pipe <edit from Setup>

Am,,Supplemental Report Report No.:

2005U024 Page:

3 of 5

Summary No.: 501953 Examiner Blechinger, Todd P.

Examiner. Jensen, Arlen Other: N/A Level:

Ill Reviewer Halling, David A.

Level:

11 Site Review: Wren, Jerry Level:

N/A ANII Review: Daly, Gerald Date:

5/2312005 Date:

512412005 Date:

5/27/2005 Comments: W-11 coverage plot Sketch or Photo: J:lSIData\\ISI\\P12_05 outage\\Scans\\2005UO24 501953 coverage plot.jpg L.

b.......

. L.

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N -)

Supplemental Report Report No.:

Page:

Summary No.: 501953 Examiner: Blechinger, Todd P.

Examiner: Jensen, Arlen Other: NIA 2005U024 4

of 5

Date:

5/2312005 Date:

5124/2005 Date:

5/27/2005 Level:

IlIl Reviewer: Hailing, David A.

Level:

II Site Review: Wren, Jerry Level:

NA ANII Review: Daly, Gerald Comments:

No upstream exams due to valve body taper. Integral attachment limits downstream exam @ 2700 for 3".

Sketch or Photo: J:%lSlData\\lSI\\Pl2_05 outage\\Scans\\2005U024 501953 limitation diagram.jpg

,. 0

.: 0 3-?".-V...

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,I 1.

Additional - Supplemental Reports <edit from Setup>

NMl6)

Supplemental Report Report No.:

Page:

Summary No.: 501953 Examiner: Blechinger, Todd P.

Examiner: Jensen, Arlen Other:

N/A 2005U024 5

of 5

Date:

5123/2005 Date:

5124/2005 Date:

5/27/2005 Level:

Ill Reviewer: Halling, David A.

Level:

II Site Review: Wren, Jerry Level:

N/A ANII Review: Daly, Gerald Comments: W-11 limitation photo Sketch or Photo:

J:lSIData\\ISI\\P12 05 outage\\Photos\\TODD\\5-19\\DSCO1549.JPG Additional - Supplemental Reports <edit from Setup>

flE'V'A TRF 4-018 NORT

\\

t,

/ 7 INTEGRAL ATTACHMENT

= HANGER

= WELD NO.

• 3L 7ST7 M)

I cU) l co REF:XH-1 106-48 IFILE NO:2147BRO4 ISP(M&sp-PI-2 ISI DWN: DMN CHKD:LC o APPD:

SYSTEM:MAIN STEAM LINE: 6-2MS-2. 30-2MS-2.

31-2MS-2 DWG:

2-ISI-47B IREV: 05

NMC-Site/Unit:

PINGP /

Summary No.:

Workscope:

UT Pipe Weld Examination P12 500814

[Si Procedure:

Procedure Rev.:

Work Order No.:

SWI NDE-UT-1A 1

0406679 Outage No.:

E031 Report No.:

2005U023 Page:

1 of 4

Code:

1989 EditIon Cat./item:

C-F-21C5.80 Location:

Aux Bldg Drawing No.:

2-ISI-47B

==

Description:==

Tee to Flange System ID:

MS Component ID: W-14ILSU Size/Length:

1.8" /68" Thickness/Diameter:

1.75" I N/A Limitations:

See supplements Start Time:

10:15 Finish Time:

10:30 Examination Surface:

Inside E Outside i Surface Condition: Ground Flush Lo Location:

TDC East Side Wo Location:

Centerline of Weld Couplant:

Sonotrace 40 Batch No.:

1. 02243 Temp. Tool Mfg.:

PTC Instruments Serial No.:

P111 Surface Temp.:

62

¶F Cal. Report No.:

2005CA021, 2005CA022 Angle Used 0

45 45T 60 N/A N/A Scanning dB N/A l44.0 44.0 48.0 NIA NIA Indication(s):

Yes El No 0 Scan Coverage:

Upstream i Downstream n CW R CCW i Comments:

No downstream scan on flange side due to configuration.

Results:

NAD Ej IND El GEO a_

Percent Of Coverage Obtained > 90%:

No Reviewed Previous Data:

Yes Examiner Level Ill Signature Date Reviewer Signature Date Blechinger, Todd P.

5117/2005 Tlmm, Jeremy 5/25/2005 Examiner Level Il Signature Date Site Review Signature Date Jensen, Arlen 5/17/2005 Wren, Jerry 512512005 Other Level N/A Signature Date ANII Review Signature Date N/A Daly, Gerald 6121/2005

....7..

Nmr,,-

Determination of Percent Coverage for UT Examinations - Pipe Site/Unit:

PINGP /

P12 Summary No.:

500814 Workscope:

ISI Procedure:

Procedure Rev.:

Work Order No.:

SWI NDE-UT-IA 1

0406679 Outage No.:

E031 Report No.:

2005U023 Page:

2 of 4

45 deg Scan 1 Scan 2 Scan 3 Scan 4 52.900

% Length X 52.900

% LengthX 100.000

% Length X 100.000

% LengthX 100.000 100.000 96.800 96.800

% volume of length / 100 =

% volume of length /100 =

% volume of length /100 =

% volume of length / 100 =

52.900

% total for Scan 1 52.900

% total for Scan 2 96.800

% total for Scan 3 96.800

% total for Scan 4 Add totals and divide by # scans =

74.850

% total for 45 deg Other deg -

(to be used for supplemental scans)

The data to be listed below is for coverage that was not obtained with the 45 deg scans.

Scan I Scan 2 Scan 3 Scan 4

% LengthX

% LengthX

% LengthX

% LengthX

% volume of length / 100 =

% volume of length /100 =

% volume of length / 100 =

% volume of length / 100 =

% total for Scan 1

% total for Scan 2 total for Scan 3

% total for Scan 4 Percent complete coverage Add totals for each scan required and divide by # of scans to determine; 74.850

% Total for complete exam Site Field Supervisor:

Date:

Additional - Calculation Pipe <edit from Setup>

Supplemental Report Report No.:

2005U023 Page:

3 of 4

Summary No.: 500814 Examiner. Blechinger, Todd P.

Level:

Ill Reviewer: Timm, Jeremy Date: 5/25/2005 Examiner. Jensen, Arlen Level:

II Site Review: Wren, Jerry Date: 5/25/2005 Other. N/A Level:

N/A ANII Review: Daly, Gerald Date:

6/2112005 Comments: W-14 Coverage plot Sketch or Photo: J:%lSlDataISl\\Pl2_05 outage\\Scans\\2005U023 500814 coverage plot.jpg

- S l

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Supplemental Report Report No.:

2005U023 Page:

4 of 4

Summary No.: 500814 Examiner: Blechinger, Todd P.

Examiner: Jensen, Arlen Other: N/A Level:

liI Level:

II Level:

N/A Reviewer: Timm, Jeremy Site Review: Wren, Jerry ANII Review: Daly, Gerald Date:

5125/2005 Date:

5/25/2005 Date:

6/21/2005 Comments: W-14 Limitation photo No downstream scan due to Flange configuration.

Upstream exam limited for 17" at 0° & 15" at 180° due to support interference.

CW & CCW scans limited for 12" at 0° due to support Interference.

Sketch or Photo: J:\\lSIData~ISI\\PI2_05 outage\\Photos\\TODD05-17 TB\\DSC01443.JPG J:\\lSIData\\ISl\\PI2_05 outage\\Photos\\TODDN05-17 TB\\DSC01444.JPG Additional - Supplemental Reports <edit from Setup>

PRAIRIE ISLAND NUCLEAR GENERATING PLANT SECTION WORK INSTRUCTION I>PX t

a

-?NFO AT1

- S-X Procedure may be performed from memory.

Userremains responsible forprocedure adherence.

Procedure should be available, but not necessarily at the work location.

O.C. REVIEW DATE:

OWNER:

EFFECTIVE DATE NR T. Downing 4/19105

PRAIRIE ISLAND NUCLEAR GENERATING PLANT SECTION WORK INSTRUCTION NUMBER:

LIMITATIONtS To NDESWI NDE-LTS-1

,LIMITATIONS TO NDEREV:

I

.;..Page 2 of 13 1.0 PURPOSE This procedure provides instruction for identifying, quantifying and recording of limitations encountered while performing NDE examinations under the ISI program.

2.0 REFERENCES

This procedure complies with the applicable portions of the following referenced documents:

2.1 Nuclear Regulatory Commission Regulatory Guide - 1.150 "Ultrasonic Testing of Reactor Vessel Welds during Preservice and Inservice Examinations", (Rev. 1 dated Feb. 1983).

2.2 Code case N-460 - Alternative Examination Coverage for Class 1 and Class 2 Welds - Section Xl, Division 1.

2.3 Procedure SWI NDE-NDE-1, 'Equipment, Personnel and Material Reporting."

2.4 5AWI 14.6.0 "ISI Examination Program" 3.0 APPLICABILITY 3.1 This procedure is applicable to examinations performed at Prairie Island Nuclear Generating Plant.

3.2 This procedure is to be followed when it has been determined that there is a limitation which prevents obtaining full coverage of an area or volume as stated by the applicable examination procedure.

For ultrasonic examinations, this would mean less than all of the required scans and/or a reduction of required scan path for one or more scans.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT SECTION WORK INSTRUCTION NUMBER:

SWI NDE-LTS-1 LIMITATIONS TO NDE REV:

1

-iPage 3 of 13 4.0 DEFINITIONS 4.1 Limitation - something that limits, restraint: An obstacle to the performance of an examination procedure.

4.2 Evaluation - to determine the significance, worth, or condition of, usually by careful appraisal and study.

4.3 Practical -" of, relating to, or manifested in practice or action: not theoretical or ideal; concerned with voluntary action and ethical decisions. Useful." For this application this is interpreted to mean, for a specific case the benefits of a proposed action outweigh the negative aspects of that action.

5.0 PREREQUISITES Personnel Requirements 5.1 Examination personnel certification and eye examinations SHALL be documented in accordance with SWI NDE-NDE-1.

5.2 Nondestructive examination personnel SHALL be certified to a minimum of Level I in the appropriate method to operate equipment and Level II to interpret test results.

6.0 EQUIPMENT This item is not applicable to this procedure. If alternate methods are required to augment coverage, that work SHALL be done under a separate procedure.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT SECTION WORK INSTRUCTION PRAIRIE ISLAND NUCLEAR GENERATING PLANT SECTION WORK INSTRUCTION r

T NUMBER:

SWI NDE-LTS-1 LIMITATIONS TO NDEREV:

Page 4 of 13 7.0 INSTRUCTIONS 7.1 Initial Examination Where the examiner is not able to complete a full examination as dictated by applicable procedure, the following steps SHALL be taken:

7.1.1 Complete original examination on accessible portions.

7.1.2 Make sketch which includes dimensions defining location and size of limitations using a report format similar to that shown in Figure 3.

7.1.3 Describe the limitation including what it is and how it interferes with the exam. State what appears to be required to remove the limitation using a report format similar to that shown in Figure 3.

7.1.4 For volumetric examinations, construct a surface profile using a surface contour gauge and perform a thickness profile (typically one reading each 1/2" in a line) of the area that encompasses the code required volume. For UT that would include the available scanning surface.

7.1.5 Record radiation field information on the report (this may require assistance from the health physics group).

7.1.6 Sign and date the data sheet then forward it to the NDE Level IlIl.

7.2 Evaluation 7.2.1 The data gathered by the initial examiner SHALL be reviewed by the NDE Level Ill or/ designee to determine if alternate methods may be used to achieve additional coverage.

7.2.2 If alternate methods would provide additional coverage, a review of the benefit versus the required resources (radiation dose, time, cost etc.) to achieve that coverage SHALL be performed by the NDE Level Ill to determine if that action is practical (see Step 7.3).

PRAIRIE ISLAND NUCLEAR GENERATING PLANT SECTION WORK INSTRUCTION SWI NDE-LTS-1 REV:

I

_P a g e 5 o f 1 3 7.2.3 If it is determined that the entire examination volume or area cannot be examined due to interference by another component or part geometry, a reduction in examination coverage on any Class 1 or Class 2 weld may be accepted provided the reduction in coverage for that weld is less than 10%.

The applicable examination records SHALL identify both the cause and percentage of reduced examination coverage (see Step 7.4).

7.3 Alternate Methods to Achieve Coverage 7.3.1 For surface examinations, MT and PT may be interchanged / intermixed as appropriate to the material and the conditions.

7.3.2 For volumetric examinations, RT may be substituted for or augment UT assuming the ability to drain the line, and that the wall thickness / diameter is within a practical range.

7.3.3 For UT, use of other angles, full node or node and one half calibrations, skewed scans or approach from another surface to achieve additional coverage SHALL be considered.

7.4 Determining Coverage Achieved When evaluation of initial and alternate examination methods results in examinations, which do not provide full coverage, a determination of percent coverage SHALL be made. The required examination coverage is defined by applicable figures in ASME Sect Xl.

7.4.1 For surface examinations, a worksheet similar to that shown in Figure 4 SHALL be completed.

i For ASME Section Xl appendix Vill exams, code coverage

,may be limited by what the procedure has been demonstrated.

7.4.2 For volumetric examinations, a worksheet similar to that shown in Figure 5 or Figure 6 (ultrasonic examinations) SHALL be completed.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT SECTION WORK INSTRUCTION SWI NDE-LTS-1 REV:

1 Page 6 of 13 7.5 Should the evaluation show that 90% weld coverage has been achieved, attach all related information to the original NDE report and no further action is required.

7.6 Contractor procedures for performing examinations utilizing automated equipment (e.g. reactor vessel and nozzle safe-end exams) SHALL be reviewed by an NDE Level IlIl in the appropriate method to ensure the requirements for identifying, quantifying and recording of limitations encountered are adequately addressed.

7.7 When it has been determined that the maximum examination coverage practically achievable for a code required item is less than required; a relief request is required to be submitted to the NRC (5AWI 14.6.0).

8.0 ACCEPTANCE CRITERIA This item is not applicable to this procedure.

9.0 REPORTING 9.1 Information addressed in Figures 3, 4, 5 and 6 (as applicable) SHALL be reported.

9.2 Information for examinations that are required to meet Reg. Guide 1.150 SHALL also include the following from Appendix A - Alternate Method:

7.c

'The best estimate of the portion of the volume required to be examined by the ASME Code that has not been effectively examined such as volumes of material near each surface because of near-field or other effects, volumes near interfaces between cladding and parent metal, volumes shadowed by laminar material defects, volumes shadowed by part geometry, volumes inaccessible to the transducer, volumes affected by electronic gating, and volumes near the surface opposite the transducer. Sketches and/or descriptions of the tools, fixtures and component geometry which contribute to incomplete coverage should be included."

9.3 Reference System Recording of limitations SHALL be based on the reference system shown in the original examination procedure.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT SECTION WORK INSTRUCTION 9.4 Documentation A picture of the limitation should be taken and added to the description, preferably in a digital format.

10.0 RECORDS 10.1 Inservice inspection examinations SHALL be incorporated in the ISI records. See UISI Examination Program."

10.2 Records of other examinations SHALL be the responsibility of the organization requesting the examination.

11.0 ATTACHMENTS 11.1 Figure 1 - Example of UT Scan Coverage 11.2 Figure 2-Example of UT, One Sided Exam, Supplemental Coverage 11.3 Figure 3 - Limitation Data Sheet 11.4 Figure 4 - Determination of Percent Coverage for Surface Examinations 11.5 Figure 5 - Determination of Percent Coverage for UT Examinations -Pipe 11.6 Figure 6 -

Determination of Percent Coverage for UT Examinations -Vessels 12.0

SUMMARY

OF SIGNIFICANT CHANGES 2.1 Deleted ASME Code year, covered with 5AWI 14.6.0.

5.1 Changed SWI NDE-0 to SWI NDE-NDE-1.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT SECTION WORK INSTRUCTION Figure 1 - Example of UT scan coverage I--

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PRAIRIE ISLAND NUCLEAR GENERATING PLANT SECTION WORK INSTRUCTION Figure 2 - Example of UT, One Sided Exam, Supplemental Coverage 0

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PRAIRIE ISLAND NUCLEAR GENERATING PLANT SECTION WORK INSTRUCTION stt.-

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^NUMBER:

SWI NDE-LTS-1 LIMITATIONS TO NDEREV:

I Page 10 of 13 Figure 3 -Limitation Data Sheet TITLE:

Limitations to NDE NUMBER:

SWI NDE-LTS-1 Revision 0 Figure 3 Limitation Data Sheet Initial exam report #

ISO #

Procedure #

Item #

Description of Limitation Sketch of Limitation Limitation removal requirements Radiation field ExaminerD Date:

PRAIRIE ISLAND NUCLEAR GENERATING PLANT SECTION WORK INSTRUCTION Figure 4 -Determination of Percent Coverage for Surface Examinations TITLE:

Limitations to NDE NUMBER:

SWI NDE-LTS-1 Revision 0 Figure 4 Determination of Percent Coverage for Surface Examinations This is a sample form only Initial exam rpt #

Procedure #

ISO #

Item#_

Applicable Code figure #

Area Required (as shown in applicable code reference drawing)

Length

• Width

= Total area required square inches Coverage Achieved Area examined sq. in. /Total area required (100%)

sq. in.

= Percent coverage

% (area required - area of limitations = area examined)

To determine length of a circumferential weld Note - Diameter refers to actual external diameter not pipe size (see table below)

Diameter

• (Pi) 3.1416

= Length inches Pipe Actual (Length)

Pipe Actual (Length)

Size Diameter Circumference Size Diameter Circumference 2

2.375 7.46 12 12.75 40.06 2.5 2.875 9.03 14 14.0 43.98 3

3.5 11.0 16 16.0 50.27 3.5 4.0 12.57 18 18.0 56.55 4

4.5 14.14 20 20.0 62.83 5

5.563 17.48 22 22.0 69.12 6

6.625 20.81 24 24.0 75.40 8

8.625 27.10 30 30.0 94.25 10 10.75 33.77 I

NDE Level IlIl:

Date:

PRAIRIE ISLAND NUCLEAR GENERATING PLANT SECTION WORK INSTRUCTION NUMBER:

SWI NDE-LTS-1 LIMITATIONS TO NDE REV:

v Page 12 of 13 Figure 5 - Determination of Percent Coverage for UT Examinations -Pipe TITLE:

Limitations to NDE NUMBER:

SWI NDE-LTS-1 Revision 0 Figure 5 Determination of Percent Coveraqe for UT Examinations - Pipe This Is a sample form onlv Initial exam rpt #

Procedure #

ISO #

Item #

Applicable Code figure #

45 deg Scan 1

% length X

% volume of length /100 =

% total for Scan 1 Scan 2

% length X

% volume of length /100 =

% total for Scan 2 Scan 3

% length X

% volume of length /100 =

% total for Scan 3 Scan 4

% length X

% volume of length / 100 =

_ % total for Scan 4 Add totals and divide by # scans =

% total for 45 deg Other deg -

(to be used for supplemental scans)

The data to be listed below is for coverage that was not obtained with the 45 deg scans.

Scan I

% length X

% volume of length / 100 =

% total for Scan 1 Scan 2

% length X

% volume of length / 100 =

% total for Scan 2 Scan 3

% length X

% volume of length / 100

% total for Scan 3 Scan 4

% length X

% volume of length /1 00 =

% total for Scan 4 Percent complete coverage Add totals for each scan required and divide by # of scans to determine;

% total for complete exam Example -45 deg scan 1 = 63% plus supplemental 60 deg scan I = 28% (of remaining required scan volume) for total of 91% coverage for scan 1 volume. Repeat for the remaining scans, add together and divide by the # of scans (typically 4).

NDE Level III:

Date:

NDE Level Ill:

Date:

PRAIRIE ISLAND NUCLEAR GENERATING PLANT SECTION WORK INSTRUCTION Figure 6 - Determination of Percent Coverage for UT Examinations -Vessels TiTLE:

Limitations to NDE NUMBER:

SWI NDE-LTS-1 Revision 0 Figure 6 Determination of Percent Coverage for UT Examinations - Vessels This is a sample form only Initial exam rpt #

Procedure #

ISO #

Item Applicable Code figure #

0 deq Planar Scan

% length X

% volume of length / 100 -

% total for 0 deg 45 deg Scan 1

% length X

% volume of length /100 =

% total for Scan 1 Scan 2

% length X

% volume of length /100 =

% total for Scan 2 Scan 3

% length X

% volume of length / 100 =

% total for Scan 3 Scan 4

% length X

% volume of length / 100 =

% total for Scan 4 Add totals and divide by # scans =

% total for 45 deg 60 deg Scan I

% length X

% volume of length / 100 =

% total for Scan I Scan 2

% length X

% volume of length / 100 =

% total for Scan 2 Scan 3

% length X

% volume of length / 100 =

% total for Scan 3 Scan 4

% length X

% volume of length /100 =

% total for Scan 4 Add totals and divide by # scans =

% total for 60 deg Percent complete coverage Add totals for each angle and scan required and divide by # angles to determine;

% total for complete exam Note: Supplemental coverage may be achieved by use of other angles / methods. When used, the coverage for volume not obtained with angles as noted above shall be calculated and added to the total to provide the percent total for the complete examination.

NDE Level III:

Date:

NDE Level Ill:

Date:

-