ML20217B843

Requests NRC Review & Approval of ASME Code Relief Requests That Were Identified in Plant Second 10-yr ISI Interval for Both Units.Encl 3 Provides Util Procedure for Calculation of ASME Code Coverage for Section XI Nondestructive Exams

ML20217B843
Person / Time
Site:	Sequoyah
Issue date:	10/05/1999
From:	Salas P TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9910130089
Download: ML20217B843 (123)

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~ VA tenneswe veey wudy. Post Otke Rw ZM SMdy-Daisy Tenneuee 37379 October 5, 1999 1

10 CFR 50.50a (g) (5) (iii) l l

U. S. Nuclear Regulatory Commission j' ATTN: Document Control Desk Washington, D. C. 20555 Gentleman:

I In the Matter of ) Docket Nos. 50-327 i Tennessee Valley Authority ) 50-328 SEQUOYAH NUCLEAR PLANT (SQN) -

AMERICAN SOCIETY OF l MECHANICAL ENGINEERS (ASME) SECTION XI INSERVICE INSPECTION (ISI) PROGRAM RELIEF REQUESTS I

References:

1. TVA letter to NRC dated November 17, 1998, "Sequoyab Nuclear Plant (SON) - American Society of Mechanical Engineers (ASME)Section XI Inservice Inspection (ISI) Program Relief Requests"

2. NRC letter to TVA dated April 27, 1998,

" Evaluation of the Second 10-Year Interval Inspection Program Plan and Associated Requests for Relief for Sequoyah Nuclear Plant, Units 1 and 2 (TAC Nos. M94115 and M94116) "

3. NRC letter to TVA dated August 7, 1998,

" Safety Evaluation of Relief Requests for the Pump and Valve Inservice Testing Program -

13 ! . , i G r,< Sequoyah Nuclear Plant Units 1 and 2 (TAC Numbers MA0417, MA0418, MA1595, and MA1596) "

The purpose of this letter is to request NRC review and approval of six ASME code relief requests that were identified in SQN's second 10-year ISI interval for both units. The relief requests are based on limitations that  ;

9910130009 991005 PDR ADOCK 05000327 099 tI G PDR u .

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U.S.LNuclear Regulatory Commission Page.2 October 5,'1999 preclude. full code examination of-ASME Class 1 and 2 welds.

Code examination of the welds is limited due to design configuration or material properties.

SON's ISI' Program has been evaluated and found acceptable by NRC in the; referenced letters (References 2 and 3). Five relief . requests -(1-ISI-9, -10, 2-ISI-8, -9, and -10) are

. currently undergoing NRC. review and were provided by the Reference 1 letter.. Following ISI activities during SON's Unit 2 Cycle 8 and Unit 1 Cycle 9 refueling outages, six additional ISI relief requests have been identified (1-ISI-11,. -12, -13, 2-ISI-11, -12, and -13). The relief requests are dubmitted in accordance with J 10 CFR 50.55a (g) (5) (iii) . TVA requests that NRC provide approval in accordance with 10 CFR 50.55a (g) (6) (i) .

We.are currently _ planning our inspections for the second I

period.of SON's 10-year interval (i.e., Cycle 11 refueling ,

outages for both units). NRC_ response is requested for the subject' relief requests-by November'2000. This date will support TVA's schedule for planning inspections during SON's

-Cycle 11 refueling' outages.

Enclosure 1 provides the Unit 1 relief requests. Enclosure 2 provides the Unit 2 relief requests. Enclosure 3 provides TVA's procedure for calculation of the ASME code coverage for j Section XI nondestructive examinations.

' If you~have any. questions regarding this response, please contact me at extension (423) 843-7071 or J. D. Smith at extension -(423) 843-6672. ,

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Salas i ensing and Industry Affairs Manager

• Enclosures cc: See Page 3 l

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i U.S. Nuclear Regulatory Commission Page 3 October 5, 1999  !

Enclosures cc (Enclosures):  ;

Mr. R. W. Hernan, Project Manager 1 Nuclear Regulatory Commission l One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739

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NRC Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy-Daisy, Tennessee 37379-3624 Regional Administrator U.S. Nuclear Regulatory Commission Region II Atlanta Federal Center 61 Forsyth Street, SW, suite 23T85 Atlanta, Georgia 30303-3415 l

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ENCLOSURE 1 SEQUOYAH NUCLEAR PLANT UNIT 1 ASME REQUESTS FOR RELIEF 1-ISI-11, 1-ISI-12, AND 1-ISI-13 l i

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ENCLOSURE 1 SEQUOYAH NUCLEAR PLANT UNIT 1 ASME REQUESTS FOR RELIEF 1-ISI-11, 1-ISI-12, AND 1-ISI-13 I

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REQUEST FOR RELIEF 1-ISI-11 Executive Summary:

This request for relief addresses the residual heat removal

(RHR) heat exchanger (1A) nozzle-to-shell weld RHRW-14-A.

The design configuration of the nozzle-to-shell weld precludes a 100% ultrasonic examination of the required volume for the nozzle-to-shell weld. These physical l examination limitations occur when the 1989 Code examination requirements are applied in areas of components constructed and fabricated to early plant physical designs. Based on the date of SON's construction permit (May 27, 1970), SON is {

exempt from the code requirements for examination access as allowed in 10 CFR 50.55a (g) (4) .

l A liquid penetrant surface examination was performed on 100%

of the subject weld. An ultrasonic examination was performed on accessible areas to the maximum extent practical given the physical limitations of the subject weld. The design configuration limits ultrasonic examination to approximately 32% of weld RHRW-14-A.

Performance of an ultrasonic examination of essentially 100%

of full penetration welds in the nozzle-to-shell weld, RHRW-14-A is impractical. A surface examination and the maximum extent practical ultrasonic examination of the subject weld provide reasonable assurance of an acceptable level of quality and safety because the information and data j obtained from the weld surface and the weld volume examined l provide sufficient information to judge the overall integrity of the weld.

Therefore, pursuant to 10 CFR 50.55a (g) (5) (iii), it is requested that relief be granted for the second inspection

' interval.

Unit: 1 System: RHR - System 74 i Components: RHR Heat Exchanger (1A) Nozzle-to-l i

Shell Weld, Full Penetration Weld ASME Code Class: ASME Code Class 2 (Equivalent)

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l l Section XI Edition: 1989 Edition Code Table: IWC-2500-1 Examination Category: C-B, Pressure Retaining Nozzle Welds in Vessels l

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I Examination Item Number: C2.21, Nozzle-to-Shell (or Head)

Weld )

Code Requirement: ASML bection XI, Table IWC-2500-1, Examination Category C-B, Item i Number C2.21, Requires Surface and Volumetric Examinations {

Code Requirement From Which Relief 4 Is Requested: Volumetric Examination Coverage of l Essentially 100% of Nozzle-to-Shell l Weld I I

List Of Items I Associated )

With The Relief Request: RHRW-14-A, Nozzle-to-Shell Weld Basis For Relief:

The design configuration of the RHR heat exchanger nozzle, shell, and component support precludes an ultrasonic examination of the required volume for the following nozzle-  !

to-shell weld RHRW-14-A. The design configuration limits ultrasonic examination to approximately 32%, as calculated in accordance with TVA procedure N-GP-28 (enclosed), of the required examination volume of the weld.

Alternative Examination:

In lieu of the code required 100% ultrasonic examination, an ultrasonic examination was performed on accessible areas to the maximum extent practical given the physical limitations of the nozzle-to-shell weld. The code required surface examination (liquid penetrant) of 100% of the nozzle-to-shell weld was also performed. Refer to Attachment 1 for examination data reports.

Justification For The Granting Of Relief:

The design configuration of the subject nozzle-to-head welds precludes ultrasonic examination of essentially 100% of the required examination volume. In order to examine the weld in accordance with the code requirement, the RHR heat l exchanger would require extensive design modifications. The j l physical arrangement of weld RHRW-14-A, in conjunction with '

! the small radius of curvature of the outside wall surfaces L of the nozzle, precludes ultrasonic examination from the nozzle side. For scans normal to the weld on the vessel shell side, examinations are limited circumferential1y due l to large support pads attached by fillet welds at two locations (90 and 270 degree nozzle azimuths) and the close  !

pr'oximity of heat exchanger weld RHRW-16-A (tube sheet-to-El-2 L

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head weld at 0 degree nozzle azimuth) and heat exchanger l weld RHRW-17-A (bottom head-to-shell weld at 180 degree j nozzle azimuth). The axial scan area is limited due to the i close proximity of the support pad fillet weld. A total of )

four areas (24% of total circumference) are unrestricted for i one side examination coverage. Total ultrasonic examination coverage for weld RHRW-14-A was approximately 32% of the i required code coverage for the weld.

Radiographic examination from the outside surface as an alternate volumetric examination method was determined to be impractical due to the component thickness and a divider plate inside the component head affecting radiographic quality. Performing radiographic examination from the inside surface of the heat exchanger would require placing a radiographic source near the center of the head. This would require extensive modifications in order to gain access to ,

the inside for source placement. The heat exchanger would require disassembly at the tube-sheet and .ne component moved in an upward direction for approximately two feet.

Thus, additional radiography and/or ultrasonics examinations j from the inner surface, to gain any additional coverage, are j also impractical. '

Performance of an ultrasonic volumetric examination of J essentially 100% of the required volume of the RHR heat i exchanger full penetration nozzle-to-shell weld RHRW-14-A would be impractical. In addition, it is impractical to perform other volumetric examinations which may increase examination coverage. The surface examination of 100% of the weld areas and adjacent metal, and a maximum extent '

practical ultrasonic examination of the subject weld provide reasonable assurance of an acceptable level of quality and safety. Significant degradation, if present, would have been detected during the surface and ultrasonic examinations that were performed on the subject weld. As a result, assurance of structural integrity for this weld is provided j by the examinations that were performed.

Therefore, pursuant to 10 CFR 50.55a (g) (5) (iii), it is l requested that relief be granted for the second inspection interval.

Implementation Schedule: )

This request for relief is applicable to the second inspection interval for SON Unit 1. Weld RHRW-14-A was

examined during the first period of the second 10-year l inspection interval.

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g-Background Information:

A request for relief for volumetric examination coverage i limitations on RHRW-14-A was submitted as ISI-13 for Unit 1 in SON's first 10-year interval and was approved in the Reference 1 letter below with no additional augmented requirements.

References:

1. Letter from F. J. Hebdon, NRC, to 0. D. Kingsley, TVA, dated February 7, 1991.

2. Nondestructive Examination Procedure N-GP-28

" Calculation of ASME Code Coverage for Section XI NDE Examinations," Revision 1.

Attachment 1 - Examination Data Reports: R-7150 and R-7151 Attachment 2 - ISI Program Drawing: ISI-0290-C-02 l

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REQUEST FOR RELIEF 1-ISI-12 Executive Summary:

This request for relief addresses integrally welded attachments on the centrifugal charging pump (lA-A). The design configuration of the subject attachment welds precludes 100% surface examination of the required area for weld CCPH-1A-A-IA (four integrally welded lug attachments to the pump casing). These physical examination limitations occur when the 1989 Code examination requirements are applied in areas of components constructed and fabricated to early plant physical design. Based on the date of SON's construction permit (May 27, 1970), SON is exempt from code requirements for examination access as allowed in 10CFR

50. 55a (g) (4) .

A liquid penetrant surface examination was performed on accessible areas to the maximum extent practical, given the physical limitations of the subject welds. The design configuration limits surface examination to approximately 77% of integrally welded attachments CCPH-1A-A-IA.

Performance of a surface examination of essentially 100% of the integrally welded attachments CCPH-1A-A-IA is impractical. The maximum extent practical surface examination of the subject integrally welded attachments provides reasonable assurance of an acceptable level of quality and safety because the information and data obtained from the area examined provides sufficient information to judge the overall integrity of the integrally welded attachments.

Therefore, pursuant to 10 CFR 50.55a (g) (5) (iii), it is requested that relief be granted for the second inspection interval.

I Unit: 1 System: Chemical Volume Control - System 62 l

Components: Integral Welded Attachments for Centrifugal Charging Pump 1A-A I ASME Code Class: ASME Code Class 2 (Equivalent)

Section XI Edition: 1989 Edition (Code Case N-509)

Code Table: Table 2500-1 of Code ase N-509 Examination Category: C-C, Integral Attachments for Class 2 Vessels, Piping, Pumps, and Valves El-5 l

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Examination Item Nnmber: C3.30, Pumps, Integrally Welded Attachments Code Requirement: Code Case N-509, Table 2500-1, Examination Category C-C, Item Number C3.30, Requires Surface Examination Code Requirement From Which Relief Is Requested: Surface Examination Coverage of Essentially 100% of Integrally Welded Attachments List Of Items Associated With The Relief Request: CCPH-1A-A-IA, Integral Welded Attachments A Basis For Relief:

The design configuration of the centrifugal charging pump and integrally welded attachments precludes a surface examination of the required area of the integrally welded attachments.CCPH-1A-A-IA. The design configuration limits surface examination to approximately 77%, as calculated in accordance with TVA procedure N-GP-28, of the required area.

Alternative Examinations: l In lieu of the code required 100% surface examination, a liquid penetrant examination was performed on accessible areas to the maximum extent practical given the physical limitations of the subject integrally welded attachments.

Refer to Attachment 1 for the examination data report.

Justification For The Granting Of Relief

• l The design configuration of the subject attachment welds l

-precludes surface examination of essentially 100% of the I required examination area. In order to examine the welds in !

accordance with the code requirement, the centrifugal charging pump would require extensive redesign and modification to allow access to the bottom side of the attachment lugs. Connecting piping would have to be disconnected and the pump disassembled and lifted to allow .

access to the remaining 23% examination area. The weld l joint detail consists of a full penetration weld with fillet weld reinforcement. The attachment is circumferentially welded with a fillet weld. The bottom side of the attachment is inaccessible due to a support that bolts the pump to the. supporting. frame. The total surface examination

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coverage for integral attachment' welds CCPH-1A-A-IA was approximately 77% of the required code coverage. Other nondestructive examination (NDE) techniques were considered, but due to the location of the inaccessible area, the same limitations would be encountered.

Performing a surface examination of essentially 100% of the required area of integrally welded attachments CCPH-1A-A-IA would be impractical. In addition, it is impractical to perform other NDE examinations. The maximum extent practical surface examination of the weld area and adjacent metal of the subject weld provides reasonable assurance of an acceptable level of quality and safety. Significant degradation, if present, would have been detected during the surface examination that was performed on the subject integrally welded attachments. As a result, assurance of structural integrity for the integrally welded attachments is provided by the examination that was performed.

Therefore, pursuant to 10 CFR 50.55a (g) (5) (iii) , it is requested that relief be granted for the second inspection

' interval.

Implementation Schedule:

This request for relief is applicable to the second inspection interval for SON Unit 1. CCPH-1A-A-IA (four integrally welded lug attachments to pump) were examined during the first period of the second 10-year inspection interval.

References:

Nondestructive Examination Procedure N-GP-28 " Calculation of ASME Code Coverage for Section XI NDE Examinations,"

Revision 1.

Attachment 1 - Examination Data Report: R-7183 l

. Attachment 2 - ISI Program Drawing: ISI-0466-C-01 l

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p REQUEST FOR RELIEF 1-ISI-13 Executive Summary:

L This? request for relief addresses circumferential pressure retaining dissimilar metal welds on the steam generator.

nozzles. The design configuration and materials used in the fabrication of:the' subject. welds precludes an 100%

ultrasonic examination of the required. volume for the following. welds: RC-02-SE (pipe elbow to steam generator primary head casing) and RC-03-SE (steam generator' primary head. casing to pipe elbow). These physical examination limitations occur when the 1989 Code examination l requirements are applied in areas of components constructed l 'and fabricated to early plant physical designs. Based on L the'date of SON's construction permit (May 27, 1970), SON is exempt from the code requirements for examination access as

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allowed in 10 CFR 50.55a (g) (4) .

A liquid penetrant surface _ examination was performed on 100%

of the subject welds. An ultrasonic examination was performed on accessible areas to the maximum extent

. practical given the physical limitations and materials of the subject welds. The design configuration of the. steam generator nozzle safe-ends and materials used in fabrication of:the reactor coolant piping, limits ultrasonic examination to approximately 75% of weld RC-02-SE and'approximately 75%

of weld RC-03-SE. Performance of an ultrasonic examination of essentially 100% of the circumferential pressure 1 retaining welds RC-02-SE and RC-03-SE, is impractical. A surface examination and the maximum extent practical

. ultrasonic-examination of.the subject welds provide reasonable assurance of an acceptable level of quality and safety because the information and data obtained.from the weld surface and weld volume examined provide sufficient information to judge the overall integrity of the welds.

Therefore, pursuant to 10 CFR 50.55a (g) (5) (iii), it is requested that relief be granted for the second inspection 4 interval.. l Unit: 1 t

. System: Reactor Coolant - System 68 (Steam l Generator)

Components: Two Pressure Retaining Dissimilar j p Metal Welds j

-ASME Code Class: .ASME. Code Class 1 (Equivalent) l Section XI Edition: 1989 Edition El-8 L

Code Table: IWB-2500-1 Examination Category: B-F, Pressure Retaining Dissimilar Metal Welds Examination Item Number: B5.70, Nozzle-to-Safe End Butt Welds Nominal Pipe Size 4 Inches Or Larger Code Requirement: ASME Section XI, Table IWB-2500-1, Examination Category B-F, Item Number B5.70, Requires Surface And Volumetric Examinations Code Requirement From Which Relief Is Requested: Volumetric Examination Coverage of Essentially 100% of Pressure Retaining Dissimilar Metal Welds List Of Items Associated With The Relief Request: RC-02-SE, Steam Generator Nozzle-to-Safe End Butt Weld RC-03-SE, Steam Generator Nozzle-to-Safe End Butt Weld Basis For Relief:

The design configuration of the steam generator nozzle safe-ends and materials used in fabrication of the reactor coolant piping preclude an ultrasonic examination of the required volume of pressure retaining circumferential dissimilar metal welds RC-02-SE and RC-03-SE. The design configuration and materials used in fabrication limit ultrasonic examination to approximately 75% of weld RC-02-SE and approximately 75% of weld RC-03-SE, as calculated in accordance with TVA procedure N-GP-28.

Alternative Examinations:

l In lieu of the code required 100% ultrasonic examination, an ultrasonic examination was performed on accessible areas to the maximum extent practical given the physical limitations of the subject welds. A surface examination (liquid penetrant) of 100% of welds RC-02-SE and RC-03-SE was also

. performed. Refer to Attachment 1 for the examination data

reports.

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Justification For The Granting Of Relief:

The design configuration and materials used in the fabrication of the subject piping welds precludes ultrasonic examination of essentially 100% of the required examination volume. In order to examine the welds in accordance with the code requirement, the steam generator would require extensive redesign along with changing the piping material.

The weld joint detail for welds RC-02-SE and RC-03-SE consists of a pipe elbow welded to a steam generator primary head single piece casing. The pipe elbow is static cast CF8M material. The steam generator bottom head is a single piece casting (SA-216 GR WCC) with integral cast nozzles.

The nozzle safe end welds consist of approximately 0.5 inch layer of TY-308-L weld material (buttering) applied to the nozzle weld edge preparation surface. The examinations are limited due to the design configuration and the effects of the anisotropic coarse grain structure of cast stainless material and the weld joint configuration which limit search unit contact and movement.

The total ultrasonic examination coverage for RC-02-SE and RC-03-SE was approximately 75% of the required code coverage for each weld. Due to the anisotropic coarse grain structure of cast stainless CF8M materials, the examination was limited to the 1/2 vee technique using refracted longitudinal waves. Circumferential scans for both welds were unlimited. Both welds received 100% coverage from one side scanning in the axial direction with the sound beam directed toward the steam generator. No scans were performed from the steam generator side in the axial direction due to the steam generator nozzle weld taper interference; therefore, 0% coverage was obtained from this direction. It is reasonable to assume that circumferential flaws, if present, would be detected to the degree comparable with industry standards for such materials.

Radiographic examination, as an alternate volumetric examination method, was determined to be impractical due the high radiation doses that would be received while placing the radiography source inside the steam generator. It is estimated the NDE examiners would receive a dose of 2050 mrem per weld performing a radiographic examination (NDE examiners would receive a dose of 300 mrem per weld performing an ultrasonic examination). Radiography from the outside surface with a Co-60 source would be impractical due to high surface dose rates (150 to 200 mrem) . Long exposure times would cause an unacceptable fog level on the film.

Westinghouse plants have no history of pipe cracking failure in the reactor coolant primary loop. For stress corrosion cracking (SCC) to occur, the following three conditions must El-10 i-. .

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exist simultaneously: high tensile stresses, a susceptible material, and a corrosive environment. The potential for SCC is minimized in Westinghouse pressurized water reactor by material selection and prevention of a corrosive environment (Reference Westinghouse RCS Piping Flawbase Handbook, WCAP-13670).

The examination of the steam generator dissimilar metal butt welds during the inspection interval, in accordance with ASME Section XI Code, provides reasonable assurance that  !

significant degradation, if present, would be detected.

Performance of an ultrasonic volumetric examination of essentially 100% of the required volume of pressure retaining dissimilar metal welds RC-02-SE and RC-03-SE in the reactor coolant main loop piping is impractical. In addition, it is impractical to perform other volumetric examinations, which may increase examination coverage. The surface examination of 100% of the weld area, adjacent metal, and a maximum extent practical ultrasonic examination of the subject welds provide reasonable assurance of an acceptable level of quality and safety. Significant degradation, if present, would have been detected during the ultrasonic and surface examinations that were performed on the subject welds. As a result, assurance of structural integrity for these welds is provided by the examinations

.that were performed.

Therefore, pursuant to 10 CFR 50.55a (g) (5) (iii), it is requested that relief be granted for the second inspection interval.

Implementation Schedule:

This request for relief is applicable to the second inspection interval for SON Unit 1. Welds RC-02-SE and RC-03-SE were examined during the first period of the second .

10-year inspection interval.

Background Information:

A request for relief for volumetric examination coverage limitations was submitted for these welds as 1-ISI-22 for Unit 1 in SON's first 10-year interval and was approved in L the Reference 1 letter below with no additional augmented '

requirements.

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References:

J L 1.' Letter from David-E. LaBarge, NRC, to O. D. Kingsley,

[ .TVA, dated February _7, 1996.

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2. Nondestructive Examination Procedure N-GP-28

" Calculation of ASME Code Coverage for Section XI NDE

! Examinations," Revision 1.

Attachment 1 - Examination Data Reports: R-7212, R7213, R-7217 and R-7230 Attachment 2 - ISI Program Drawing: ISI-0399-C-01 l-i l

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[I ATTACHMENT 1 EXAMINATION DATA REPORTS R-7150 R-7151 R-7183 R-7212 R-7213 R-7217 R-7230 i

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TENNESSEE VALLEY RECORD OF LIQUID REPORT NO.

AUTIlORITY PENETRANT EXAM R-7/[8 PROJECT: SON UNIT: 1 CYCLE: 9 EXAMINATION DATE: 8-24-98 SYSTEM : RHRS START TIME: 13.07 END TIME: 13:56 WELD / COMPONANT 1.D.: RHRW -14 A ~ EXAM SURFACE: ID 0 OD @

CONFIG.: NOZZ. TO VESSEL PRESERVICE O INSERVICE @

PROCEDURE: N-PT- 9 REV 16 TC N/A REF. DRAWING NO.: ISI-0290 C-02 " 1 EXAMINATION CODE: ASME SECTION XI ACCEPTANCE CRITERI A CODE CLASS:2 CATEGORY: C-B N-PT-9 APPDX,A O APPDX. B @

OTHER: ,

METIIOD OF EXAMINATION l METilOD PENETRANT MATERIALS O WATER WASHABLE FLUORESCENT DYE BRAND NAME: MAGNAFLUX O POST-EMULS!FIABLE FLUORESCENT DYE PENETRANT SKL-SP BATCH 93 A02K '

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0 SOLVENT-REMOVABLE FLUORSECENT DYE RL .iOVER SKC-S BATCH 97H12K 0 WATER-WASH'ABLE VISIBLE DYE DEVELOPER SKD-S2 BATCH 97F0lK

.q O POST-EMULSIFIABLE VISABLE DYE BLACK LIGIIT METER S/N: N/A J CAL. DUE DATE: N/A

@. SOLVENT REMOVABLE VISIBLE DYE PART TEMP.: 84.9 'F PYROMETER S/N: 575367 CAL. DUE DATE: 10-08-98 EXAMINATION RESULTS: SATISFACTORY @ UNSATISFACTORY O NOlNO.: /  ;

EXPLANATION OF EXAM RESULTS:

COMMENTS / LIMITATIONS: / Eft,# Ffoe '41 2(,' To "l'- 3/ 'Aue 7D M/FLorb Supparr A0 ANRMb 7e hvEL)? ' TOTA suEQ lEM6He 15 ti'8' AS mensurEb eAlWEtJ B*35. WM47EE TW44 f6 $ CovEh46f MFllft!Eh. j EXAMINER:  % m LEVEL I EXAMINER: h* LEVEL 1 ATE:

REVIEWER.

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EXAMINATION REPORT No.

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TENNESSEE VAI I.FT DIGITAL ULTRASONIC REPORT NUM BER:

AUTilORITY CALIBRATION DATA SilEET PROJECT SON UNIT / CYCLE 1/9 CALIBRATION DATE: 8-24-199x PROCEDURE: N UT-18 REV:22 TC:97-233_g CALIBRATION BLOCK NO.: S0-15 TEMP: 79 1 i INSTRUMENT: KB DUE DATE:4-H *e SIMULATOR BLOCK NO: 6032-83 " I MODEL/ TYPE: USN-52 S/N: E-239468 THERMOMTER S/N: 573201 " DUE DATE: 6-4-99 TRANSDUCER MANUF: KBA COUPLANT ULTRAGELIl BATCH: 95125~

S/N J.L4!'/46 SIZE: 50 FREQ: 2 25 MHz EXAM TYPE: SHEAR @ LONGO RLO CABLE TYPE: RG174 LENGTH: 72" ANGLE VERIFICATION BLOCK TYPE: Rnmnm S/N: 6026-83 v DAC NOMINAL . ANGLE: 45 ACTUAL ANGLE: 45 INSTRUMENT SETTINGS j 100 -

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TENNESSEE VALLEY DIGITAL ULTRASONIC REPORT NUMBER:

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EXHIBIT C Analysis Technique Sheet '

Plant: Od unit: I Procedure: N ET-9 Rev: /

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NONDESTRUCTTVE EXAMINATION PRCCEDURE Procedure No. N-ET 9 TVA Nuclear Power Revision 1 Page 12 of 13

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Description:

M17.20A i

ETInstrument S/N: Edo3'N cii4c I-%9 ETinstrumentManufacturer: 2rA<c-Probe Manufacturer: 7 CEC Probe Coil Typ{:Dl u 5 'Dc)e n-f ProbeFrequencyRange: ch-&ys EH 2. Probe S/N: -MD' 2 C 82 P2.

t Examiner (s)/ Level (s): VLru M' L:%nmMIJ / ILW U

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Calibration Standard Identification: % 91012.0 Calibration Standard Thickness: ,5" Diameter (if applicable): NIA Calibration Standard Material: M4%

' Ernmination Material Thicknessi I" Diameter (if applicable): N /Pr '

Examination Material: D46S l .-

i l

ETInstrument Seninac-Frequencies: F1MN F2 N/A F3 N/A F4 N/A

>> Mode of Operation (if applicable): Differential / Absolute

.su '

Calibration discontiriui used for setup: .O/o# - . Ol,o" c/cotA

.< Phase: F123T F2 p/* F3 N/A F4 4/A '

screen divisions: F11-la F2 Initial Calibration Time: l'bO6 1

i Calibration Recheck Time Ir%o l 1420 l l l l --]  ;

Remarks: ___ tl /

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nowa.asdr N

o EXAMINATION REPORT NO.

TENNESSEE VALLEY AUTHORITY

SUMMARY

AND RESOLUTION SHEE1 R- g jg PROJECT: UNIT: EXAMINER .

k)b LV: N SYSTEM: &%b EXAMINER i i NA LV: M WELD I.D.: ' k * "' EXAMINER:

N L h R0 % bkD W tv: hM CONFIG: Md M k TO- Nk (MI EXAMINER: N A LV: Nkb PROCEDURE: N- k FLOW REV.: N 8 TC: N k dA NDE METHOD: O ur O PT O MT O vT NN 414 h Od 6MM 6Xhnidht00 IPC '

AhD N014Wird.tp 69disknod (Gt).

RAb t4Rt<GA 0.10" t y\T)@s\ D.0ZO" L A%0bikOlA f%b\ 4\t6f0t\n6mErdhMAtioL ' '

16 OMt9Ohi1M '

9'01AAinW 6QtAkG0M:

I46. (12.'T-0 9tl + tdo x t, Id t = lb2.- 9.tM + 100 x t O" ' tai.1(heluA t omwan % iwmit.td (tu-o.9x t.t too y t. (%.2 - 9.4il d 100 x l1 (IM-l.%\h 100147 [Lt- 3.l@ ' loo 111 A' O. lT" A1M&%l.6 1:~ l.l'M" ' AulA' A$lf l

@bl th tw4ffh% htm W @fxE hlb- %tB.'2. 40m 3

$ .L LEVEL: DATE:

EVALUATOR-u) CONCURRENCE:

'#d Level:  % DATE: 9 w ""#

-s,ir TVA 19670C (NP 7/92) , _ , , . _,

e L,7 d t: . i ; F , e,. :-

v TENNESSEE VALLEY RECORD OF LIQUID REPORT NO.

AUT110RITY PENETRANT EXAM R- 7 2. I A PROJECT: SON UNIT: 1 CYCLE: 09 EXAMINATION DATE: 9/12/98 SYSTEM : SG START TIME: 1350 END TIME: 1435 WELD / COMPONANT 1.D,; RC-03-SE EXAM SURFACE: ID 0 OD E CONFIG.: Nozzle TO Elbow PRESERVICE O INSERVICE @

PROCEDURE: N-PT- 9 REV 17 TC N/A REF. DRAWING NO.: ISI-0399-C-01 EXAMINATION CODE: ASMF SECTION XI ACCEPTANCE CRITERI A j CODE CLASS:1_

CATEGORY: B-F N-PT 9 APPDX. A O APPDX. B @

OTHER: N/A l METHOD OF EXAMINATION METHOD PFNETRANT MATERIALS O WATER WASHABLE FLUORESCENT DYE BRAND NAME: MAGNAFLUX 0 POST-EMULSIFIABLE FLUORESCENT DYE PENETRANT SKL-SP BATCH 93A02K y m$n W D SOLVENT-REMOVABLE FLUORSECENT DYE REMOVER SKC-S BATCH 97)(04K O WATER-WASFfABLE VISIBLE D'YE DEVELOPER SKD S2 BATCH 97J05K f: O POST-EMULSIFIABLE VISABLE DYE BLACK LIGilT )

METER S/N: N/A I s @ SOLVENT REMOVABLE VISIBLE DYE CAL. DUE DATE: N/A I l

PART TEMP.: 117 'F PYROMETER S/N: 575347 CAL. DUE DATE: 1/23/99 I

EXAMINATION RESULTS: SATISFACTORY @ UNSATISFACTORY O NOI NO.: N/A EXPLANATION OF EXAM RESULTS: ,

COMMENTS / LIMITATIONS:

h-w?'N 5M9ETiicnmhmL w y,i r 4 ft EXAMINER: LEVEL -44.

__ tie a s e _ - -

REVIEWER: & - LEVEL DATE: 7 PAG

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v TENNESSEE VALLEY RECORD OF LIQUID REPORT NO.

AUTHORITY PENETRANT EXAM R- 732-/3 PROJECT: SON UNIT: 1 CYCLE: 09 EXAMINATION DATE: 9/12/98 SYSTEM : SG START TlhE: 1315 END TIME: 1410 WELD / COMPONANT 1.D.: RC-02-SE EXAM SURFACE: ID C OD @ .

CONFIG.: Elbow TO Nozzle PRESERVICE O INSERVICE @ l PROCEDURE: N-PT- 9 REV 17 TC N/A REF. DRAWING NO.: ISI-0399-C-01 EXAMINATION CODE: ASMF SECTION XI ACCEPTANCE CRITERJ A CODE CLASS:1 CATEGORY: B-F N-PT-9 APPDX. A O APPDX. B @

OTHER: N/A METHOD OF EXAMINATION METHOD PENETRANT MATERIALS O WATER WASHABLE FLUORESCENT DYE BRAND NAME: MAGNAFLUX 0 POST-EMULSIFIABLE FLUORESCENT DYE PENETRANT SKL-SP BATCH 93A02K B n't l^ W D SOLVENT-REMOVABLE FLUORSECENT DYE REMOVER SKC-S BATCH 97)f64K O WATER-WASH'ABLE VISIBLE DYE DEVELOPER SKD-S2 BATCH 97105K g O POST-EMULSIFIABLE VISABLE DYE BLACK LIGHT )

MEER S/N: N/A l w @ SOLVENT REMOVABLE VISIBLE DYE CAL. DUE DATE: N/A

]

PART TEMP.: 117 'F PYROhETER S/N: 575347 CAL. DUE DATE: 1/23/99 EXAMINATION RESULTS: SATISFACTORY @ UNSATISFACTORY O NOI NO.: N/A EXPLANATION OF EXAM RESULTS:

COMMENTS / LIMITATIONS:

Pvrnmeter R/h! m ~ ' ""-C A r f M S-EXAMINER: Q _ LEVEL T _

EXAMINER: > 44_ LEVEL 'Tf~ DATE!

REVIEWER: LE\ DATE: 0 PA

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l TENNESSEE VALLEY EXAMINATION REPORT NUMBER )

AUTHORITY

SUMMARY

AND

] RESOLUTION SHEET R- 7.dl 7 s'ROJECT: SQN UNIT: 1 CYCLE: 09  !

SYSTEM: SG EXAMINER:[_gvro3f [ SuggLV: ~77-WELD / COMPONENT I.D.: RC-02-SE EXAMINER: Mwr b/. Kurw ng LV: *71- l CONFIG.: elbow TO: N'o z z/>

i PROCEDURE: N.tA*r- 3 3 REV A TC g/A EXAMINER: AI/A LV: /g 1 ,

EXAMINATION CODE 89E-02 EXAMINER: d,/A LV: M[A CODE CLASS: 1 CATEGORY: B-F EXPLANATION OF EXAM RESULTS  !

Ykr DATA t*n Al'1"A t Af/~n TAl THIM ~4 C Df O A T* I% A < 9 tY I A Tr n (1 J I T'N AM f I @ ta.u) "f'o f\l02 T L Y (1)f L n l n Al MrAM ITFNfRATo2 l r='X 4 M inf A Tso Af s Wr it' L PER f=*o R >f C D rN A ct~ n R R A rtt= f tA/ t 1*W A t M e" Are vic Al T ("o n t Pfot11>? t* MEA /75 >

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CA L L WD OuT At A .$ hff EAfh IJ ELb / S) *; f A d PLA Al-COMMENTS / LIMITATIONS A PP6 Y / M t1 ~1"E l 4' Y.E 2 of TNf Coor PC' O tJ t Pl~ n t")L A & t hl 4 7' e n t/nt rJryt r_ rs s A M /2 /* U l f t/t* tD .

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EVALUATOR: LEVEL: 2E DATE: j--/.2-[8 CONCURRENCE: h / LEVEL: '

8 DATE: 7 /IW

! ANH:

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LEVELN' DATE: k)M3 PAGE:

/ OF 4;'

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TENNESSEE VALLEY DIGITAL ULTRASONIC REPOJT NUMBER: l AUTHORITY CALIBRATION DATA SHEET ggg '

1

/ROJECT SON UNIT / CYCLE 1/9 CALIBRATION DATE:_ 9 / /2 /99 PROCEDURE: N-UT-33 REV:8 TC: N/A CALIBRATION BLOCK NO; S0-64 TEMP: /o C INSTRUMENT: KB DUE DATE: 6/17/99 SIMULATOR BLOCK NO: 6032-83 MODEl/ TYPE: USN-50 S/N: E24251 THERMOMTER S/N: 5V5W7 DUE DATE: / -a 3-99 TRANSDUCERMANUF: KBA COUPLANT Ultracel BATCH: 97325 l S/N#llel~/ / 4H819 SIZE: 10" FREQ: 1 MHz EXAM TYPE: SHEARO LONGO RL@ l CABLE TYPE: RG-58 LENGTH: 12' ANGLt., VERIFICATION BLOCK TYPE: D mm S/N: 6m2 83 DAC NOMINAL ANGLE: 45 ACTUAL ANGL'E: 45 I

INSTRUMENT SETTINGS 100 l l l A REFLECTOR REFERENCE MEMORY

, gjrshs r Err, M scan DIRECT. NTCH SDH SENS'r!TvTTY hDIBER 80

/\ l P A.mL @ @ g g dB 1 f \ y7" w L c:RC O O -

dB -

i v . ,. ' '\. I FREQ: FIXED MHz REJECT: 0  %

4g

'7' "

\ 3h d4/ T ANGLE: 15 deg DAMPING: FIXED ohms

\ 2 U DELAY: 13 22 mse: PULSER DUAL *

'O

~

\ mse: MRM *

\ E VELOCITY: .2317 mse: REP RATE: FDGD -

\ RANGE: 3 218 inches TOF: @ PEAK C FLANK i 0

@ 'h+gcIhspay FutL POWER- ON"

5. DISPLAY WIDTH: 8.218 DUAL: @ ON O OFF TCG: O ON @ OFF ,

REF. REFLECTOR: 2" Radius GAIN: '/ '/ dB CALIBRATION TIMES l l

AMPLITUDE: 80  % METAL PATH: 2.00 INITIAL TIME: /0 o'r FINAL TIME: /6 bo VERIFICATION TBIES l 1) /y,;oe fl 2) / cool 3) 4) l5) l 6) l7) l S) } 9)

• PDI QUALIFIED INSTRUMENT SETTINGS:

VERIFY INSTRUMENT SETTINGS AND CALIBRATION SEQUENCE ARE IN ACCORDANCE WITH TABLE 2 OF THE APPLICABLE PD1 QUALIFICATION BIPLEMENTATION PROCEDURE !

LINEARITY CHECK VERTICAL SIGNAL 1 l 100 90 l 80 70 60l50l40 30l20  %'

W# W

> 34)M

-51GNAL 2 l50 '/5 40 39 3r l 26 l 20 /5 l lo 7 *W**rm" '

GAIN l SET l -6 dB -12 dB SET l +12 l SET l 4 ~;

ATTENUATOR AMP l 80% l 32 TO 48 16 TO 24 20 % l 64 TO 96 l 40 % l 64 TO 96 - [,MF M 37 9O RO R7 '

. 0, - *'

. 2 COMMENTS 1 >

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N EXA. M /2Avro4;[.8% LVL.~ E f-DATE: 10 6 CJv EXAMINER //./, h/ /$,g,,, p( gj[ LVL.-6',

RENEWER M -

w .v LVL b y DATE

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TENNESSEE VALLEY DIGITAL ULTRASONIC REPORT NUMBER:

_. AUTHORITY CALIBRATION f( g / Q DATA SHEET PROJECT SON' . UNIT / CYCLE 1/9 CALIBRATION DATE: '/ / /:2 /9W PROCEDURE: N-UT-33 REV:S TC: N/A CALIBRATION BLOCK NO.: 50-64 TEMP: lo $~

INSTRUMENT: KB DUE DATE: 6/17/99 SIMULATOR BLOCK NO: 6432-83 MODEL/ITPE: USN-50 S/N: E24251 THERMOMTER S/N: 4'75w7 DUE DATE: //n/19 TRANSDUCERMANUF KBA COUPLANT Ultneel BATCH: 97325 S/N d116d hna.zoSIZE: 1.0" FREQ: 1 MHz EXAM TYPE: SHEARO LONGO RL@

CABLE TYPE: RG-58 LENGTH: 12' ANGLE VERIFICATION l BLOCK TYPE: hm S/N: An;2.s; DAC NOMINAL ANGLE: 45

• ACTUAL ANGLE: 45 ' j INSTRUMENT SETTINGS 1 100

,R d F. l ko 4 A REFLECTOR REFERENCE ME.\ LORY dl SutBER

=f I l l M SCAN DIRECT. l NTCH l SDH SEN5ITIVTTY 8 '

i l l P ^=- IOl0 -

el -

60 l l l L C:RC l@lC 68 dBl 2 l l l l 1 FREQ: RXcD MHz P2 JECT: 0  %

l ' *E 40 l l l l l l l U DELAY: 16 11 mse: PULSER E3,L_

• I ****

'O l l l l l l E VELOCITY: .2317 mse: REP RATE: FIXED e l l l l l l l RANGE:. S 218 inches TOF.@ PEAK O'FLAbX 0

"rc M @ sP u y ! Fu d. POWER: ON~

DISPLAY WIDTH: 8.213 DUAL: @ ON O OFF TCG: O ON @ OFF P2F. REFLECTOR: 2" Radius GAIN: 4 3 dB CALIBRATION TDiES .

AMP!ITUDE: 30  % METAL PATH: 2.00 IbTr1AL TIME: /0 foo FINAL TIME: /6 o C VERIFICATION TBIES l 1) /v;r l 21 l 3) 4) { 5) l 6) l 7) l 3) l9)

• PDI QUALIFIED INSTRUMENT SETTINGS:

VERIFY INSTRUMENT SETTINGS AND CALIBRATION SEQUENCE ARE IN ACCORDANCE %TTH TABLE 2 OF THE APPLICABLE PDI QUALIFICATION DIPLEMENTATION PROCEDURE !

LINEARITY CHECK VERTICAL 1 100 l 90 l 30 l 70 } 60 50 l 40 l 30 l 20 ggf j{ , gg g^" g SIGNAL 2 fC ' , 3rr Mm1.Lw Gk. SMer7 ' F

Conna?G %e e< rare C,ec. Suas pc -c>t - se pr- M -SE - m ,p i / EXAMNERCam E S  ! yL, -rC- - A d exaena w nnbdedsvlis

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REVIEWER Ovu]% '/ tyt /L DArE 6 tfd s MANUAL ULTRASONIC REPORT NO. TENNESSEE VALLEY AUT110R]TY PIPING EXAMlNATlON DATA SilEET R- 7a/2 inOJECT: bOAf UMT: I heu f EX AMINATION DATE: /2 9f3 5YSTEM : 84 # 1 START TIME: li 10 END TIME: M-/O , WELD 1.D. : R C - 0 2'- Sl' EXAM SURFACE: C ID TOD i CONFIG.: EL An (21 TO Alo 7 2 L /E MATERIALTYPE: C ',5 C SS O CSCL FCCSS l h SURFACE TEMP: / / 7 'F PYRO NO.: 5753(7 l FLOW D ur: ' .n - 99 1 PROCEDURE:N-UT 33 REV.:1TC: AJ/A CALICRATION SIIEET NO. C. d/A C d/A Wo

REFERENCE:

LdELD 4 EXAMINATION ANGLE YS' DEC. - / CEO 7 CIRC SCAN SENSITIVITY 74 dB d /, an AX1AL SCAN SENSITIVITY 6/ dB /A dri t

IND L(in) FROM REF. AT MAX AMP MAX EXAM NOM INDICATION'INFORMATION:

NO-L1 lL Max L2 W MAX MP MAX l D MAX *e AC 3-

1. N 3 45' /  %

l} 5 g ./ 'T G di' f I m I t i J i  ;

q l l l f s

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REMARKS / LIMITATIONS: 6 EXAM n o W Af r;7 REM M StOf DU F_ 7o NoZ T lf

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Sc AbihlL'D AY + (N e- O T Al ROTH AX1AL C i!?C. D 1 R f' C T}O ^l 3 l t 1Mie H MAIN rat Air n Wz -ro 30 */ Aloist 2 e v' L L l \J m n EXAMINER:[ amin ELAM/{ EVEL: g ANil g i

EXAMINER : 4xrk/ktrm u! (M{ LEVEL: -

.-,,.----- ,DATE:(0-5Sh REVIEWED BY: // 8 h LEVE C M DATE:

PAGE */ OF.I L_ . . . . . . .

I yg WALL THICKNESS "'""'"

PROFILE SHEET N DI2 PROJECT: bO Af WED No: TC - 0 2 - SE-UNIT: I /CWLE 9 SYSTEM: Sm G ~

Record Thickness Measurements As Wold

• Weld Edge Indicated, including Weld Widh, Cen terline Edge To-Edge At 0*

AR

• We W4xp//VC l: 2.5" :l: 2.5"

l Position O' 90* 180* 270* } }

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CROWN HEIGHT: b u <M DIAMETER: 3/

CROWN WIDTH: 2 WELD LENGTH: /b T~DC Conv ou g g j:l

$ 1*HICHNESS l f READINGS in o e

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Tv4 isas oe.3.es r;espH-u l ..

TENNESSEE VALLEY EXAMINATION

SUMMARY

AND REPORT~ NUHN AUTHORITY R- 7IA 3 O RESOLUTION SHEET PROJECT: SQN UNIT: 1 CYCLE: 09 SYSTEM: SG EXAMINER:[L Avroo [. bH Au;LV: 1 WELD / COMPONENT 1.D.: RC-03-SE EXAMINER: bc M KtrittTAslLV: 1 CONFIG.: No z 2 e.c TO: Et soo PROCEDURE: A/.(/7 33 REV 8 TC n/p ._ EXAMINER: N/A LV: tJ /A EXAMINATION CODE 89E-02 EXAMINER: tl A LV: fjd CODE CLASS: 1 CATEGORY: B-F f <

,j EXPLANATION OF EXAM RESULTS Thr O4 YA t~e d YAl M r h /M 'rM M XfPC/Y /5 4 53 0et ATE b w ora A sfo z n r re Ez mu (SaveE;6d Mrch on s rra-m CrEMER A'roR l. Aw 2A *rten r f wrRf P'rz fo r M rh id slcrer3 A arcr w rs AGME~ <re riou 77~ eoor ree e u ,a c x c a r.s.

A es- ersen c ,r2> zoac,r2,nisse ,sA ve utrapson,rc TrcHHicuf. LJ A 5 M r/L /2 th JM edr Ds WFe 'rnd AX, ALLY { SUA

• Adh ra ' 'rxie De t.re rron < e/Reum rrarHTI A u v (sum C l 0. Wo read

• A% 1. .Ax verps Rsa rb ~D ss e- ro roMfo cu t a vron . Wrer e rser- M71-nceenbAste savreA nsa,c es.ss eve *h "Du n raa 7x" tss E vase t.

1 COMMENTS / LIMITATIONS l morr e Avr t y 7K % or rwr cent gro u irr'b Exw, us vr e a v'8 L UMF wAA AFAn-Vrh.

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EVALUATOR: LEVEL: E DATE: f-/.2-96 CONCURRENCE LEVEL: [DATE:  ?![ 97 ANII: L o g_ A LEVEL DATE: /0 9h PAGE:

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p 9 M 9Y TENNESSEE VALLEY DIGITAL ULTRASONIC REPQRT N1JMBER:

AUTHORITY CALIBRATION g,,_ - Kp 3 O l

DATA SHEET PROJECT _1GN UNIT / CYCLE I/9 CALIBRATION DATE: 'l / / 2 /99 PROCEDURE: N-UT-33 REV:8 TC: N/A CALIBRATION BLOCK NO.: S0-64 " TEMP: /c f INSTRUMENT: KB DUE DATE: 6/17/99 SIMULATOR BLOCK NO: 6032-83 '

MODEl/ TYPE: USN-50 S/N: E24251 ' "

THERMOMTER S/N: 575 W 7' DUE DATE: / 4 3-W TRANSDUCERMAfGF KBA COUPLANT Ultracel BATCH: 97325 '

S/N##Bt1/ 4:1819 SIZE: 1.0' FREQ: 1 MHz EXAM TYPE: SHEARO LONGO RL@

CABLE TYPE: RG-58 LENGTH: 12' ANGLE VEREICATION BLOCK TYPE: Rnmm S/N: 6032-0 /

DAC NOMINAL ANGLE: 45 ACTUAL ANGLE: 45 INSTRUMENT SETTINGS I 100 REFERENCE MEMORY A REFLECTOR I y 9,2, '/~ s :),/ f W- M SCAN DIRECT. NTCH SDH SENSITIVITY NUMBER A P AX1AL

@ @ g g dB 1 f ( yT so/< L CIRC

] ] -

dB -

% T I FREQ: FIXED MHz REJECT: 0  %

40

1. 1. d #E *

\ 2 U DELAY: 13 22 msec PULSER DUAL *

\ " ***

• 20

\ E VELOCITY: 2317 mse REP RATE: FDED

\ RANGE: 8.218 inches TOF: @ PEAK O FLANK g

• h DispayMuu. POWER- ON' DISPLAY WIDTH: 8.218 DUAL: @ ON O OFF TCG: O ON O OFF d REF. REFLECTOR 2" Radius GAIN: '/ f dB CALIBRATION TDIES AMPLITUDE: 80  % METAL PATH: 2.00 INITIAL TIME: /O :o s'- FINAL TIME /d:co VEREICATION TBIES l 1) /y;oyl 2) p, ool 3) 4) l 5) l 6) l 7) l 8) l 9) i

• PDI QUALEIED INSTRUMENT SETTINGS:

l VEREY INSTRUMENT SETTINGS AND CALIBRATION SEQUENCE ARE IN ACCORDANCE WITH TABLE 2 OF THE APPLICABLE PDI QUALEICATION IMPLEMENTATION PROCEDURE !

LINEARITY CHECK

' ' l l N

VERTICAL SIGNAL 2 l50 */5 yo 3i l Ji 26 l 20 /5 l /o -

GAIN l SET l -6 dB -12 dB l SET l +12 l SET l +6 ,

ATTENUATOR AMP l 80% l 32 TO 48 16 TO 24 l 20 % l 64 TO 96 l 40% l 64 TO 96 @;

1 M 37 90

+'

M ^

Rn M R7 sCOMMENTS1 l tWELDS/ ITEMS EXAMINEDE Qroutes 34ees Fo K Anot Seuc l Rr-M-V l Rr - n3 -52 g ,

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%.JIEXAMINEP&m E.L/[MM/mt' 2 / DATE: l0 49@

EXAMINER //1 V L1,,, F d i LVL.- 7 REVIEWER N LVL. [ DATE { .m.

/ / . 2. , .-

TVA/ ISO REV1 04/01/1998

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I TENNESSEE VALLEY DIGITAL ULTRASONIC REPORT NUMBER:

l AUTHORITY CALIBRATION DATA SHEET p, y 3g PROJECT SON' UNIT / CYCLE 1/9 CALIBRATION DATE: '/ //2 /97 PROCEDURE: N-UT-33 REV:S TC: y/4 CALIBRATION BLOCK NO.: 50-64 TEMP: /o $~

INSTRUMENT: KB DUE DATE: 6/17/99 SIMULATOR BLOCK NO: 6032-83 MODE 17 TYPE: USN-50 S/N: E24251" THERMOMTER S/h: f 75w7 " DUE DATE: //23/97 l TRANSDUCERMANUF KBA COUPLANT Ultracel BATCH: 97325

]

S/N dilot9 hhta$ SIZE: 1.0" FREQ: 1 MHz EXAM TYPE: SHEARC LONGO RL@ l CABLE TYPE: RG-58 LENGTH: 12' ANGLE VERIFICATION BLOCK TYPE: Dmmm S/N: W 2-83 "

DAC NOMINAL ANGLE: 45

• ACTUAL ANGLE: 45 '

INSTRUMENT SETTINGS l 0 REFERENCE MEMORY

,7 g f.: L. - og 4 A REFLECTOR 47 M SCAN DIRECT. NTCH SDH SEN5mVrrY NUMBER '

80 = - /

P = 0 0 - e -

68 G 2 60 I FREQ: FOID MHz REJECT: o  %

T ANGLE: 45 deg DAMPING: FTXED ohms 40

• U DELAY: 16 11 mse: PULSER DUAL 20 E VELOCITY: 2317 mse: REP PATE: FLED RANGE:- 8 218 inches TOF;@ PEAK O FLAhX l 0

'l *M > t PuY I Fu u. POWER- ON- l J DISPLAY WIDTH: ~8.21S DUAL: @ ON O OFF TCG: O ON @ OFF REF. REFLECTOR: 2" Radius GAIN: f3 dB CALIBRATION TBIES .

AMPLITUDE: 80  % METAL PATH: 2.00 INITIAL TIME /Oroo FINAL TIME: //, o f VERIFICATION TDIES l 1) /Y2(l 2) l 3) 4) l5) l6) l7) l 8) l 9)

• PDI QUALIFIED INSTRUMENT SETTINGS:

VERIFY INSTRUMENT SETTINGS AND CALIBRATION SEQUENCE .GE IN ACCORDANCE %TTH TABLE 2 OF THE APPLICABLE PDI QUALIFICATION DIPLEMENTATION PROCEDURE !

LINEARITY CHECK S NAL1 100 i 90 80 70 l 60 j 50 l 40 30 20  ;< -

VERECAL SIGNAL 2 f0 l 3er 4m154 Chk.Suri- '

GAIN l SET -6 dB -12 dB SrT l +12 SET +6 -

+

ATTENUATOR AMP l 80% 32 TO 48 16 TO 24 1 ,~.0 % l 64 TO 96 40% 64 TO 96 M

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-ENCLOSURE 2 SEQUOYAH NUCLEAR PLANT UNIT 2 ASME REQUESTS FOR RELIEF 2-ISI-11, 2-ISI-12, AND 2-ISI-13 l

J

l; h

I REQUEST FOR RELIEF 2-ISI-11 l

l Executive Summary:

-This_ request.for relief-addresses the residual heat removal (RHR) heat exchanger (2A) nozzle-to-shell weld RHRW-14-A.

The design configuration of the nozzle-to-shell weld precludes a 100% ultrasonic examination of the required volume for-the. nozzle-to-shell weld. These physical-examination-limitations occur when-the 1989 Code examination requirements are. applied in areas of components' constructed

~

and fabricated to early plant physical designs. Based on the 'dat( of_ SON's construction permit (May 27, 1970), SQN is

. exempt.from the code requirements forLexamination access as allowed . in 10 CFR 50.55a (g) (4) . { 2 A liquid penetrant surface examination was performed on 100%

of the subject weld. An ultrasonic examination was performed on-accessible areas to'the maximum extent -

practical given the physical limitations of the subject

l. weld. The~ design configuration limits ultrasonic examination.to approximately 15% of weld RHRW-14-A.

Performance of an ultrasonic examination of essentially 100%

of full penetration welds in the nozzle-to-shell weld, RHRW-14-A is it : practical. A surface examination and the maximum extev, practical ultrasonic examination of the '

l subject weld provide reasonable assurance of an acceptable l -level of quality and safety _ because the information and data l obtained from the weld surface and the weld volume examined provides sufficient information to judge the overall integrity of the weld.

! Therefore, pursuant to 10 CFR 50.55a (g) (5) (iii), it is

! + requested that relief be granted for the second inspection

-interval.

-Unit: 2' L System: RHR - System 74 l'

-Components: RHR Heat Exchanger (2A) Nozzle-to-

, Shell Weld, Full Penetration Weld ASME~ Code Class: ASME' Code Class 2 (Equivalent) l Section XI' Edition: 1989 Edition Code-Table: IWC-2500-1 i ,

Examination Category: C-B, Pressure Retaining Nozzle ,

helds in Vessels li E2-1 t

I l L

l Examination Item Number: C2.21, Nozzle-to-Shell (or Head)

Weld l

Code Requirement: ASME Section XI, Table IWC-2500-1, Examination Category C-B, Item Number C2.21, Requires Surface and Volumetric Examinations l

Code Requirement From Which Relief Is Requested: Volumetric Examination Coverage of Essentially 100% of Nozzle-to-Shell i Weld l

List Of Items Associated With The Relief Request: RHRW-14-A, Nozzle-to-Shell Feld Basis For Relief:

1 1

! The design configuration of the RHR heat exchanger nozzle, shell, and component support precludes an ultrasonic examination of the required volume far the following nozzle-to-shell weld RHRW-14-A. The design configuration limits ultrasonic examination to approximately 15%, as calculated in accordance with TVA procedure N-GP-28, of the required examination volume of tha weld. This percent of coverage is J slightly different than tre Unit 1 32% of coverage for the i same weld area due to the physical "nnfiguration in the Unit 2 components.

Alternative Examination:

In lieu of the code required 100% ultrasonic examination, an ultrasonic examination was performed on accessible areas to the maximum extent practical given the physical limitations of the nozzle-to-shell weld. The code required surface examination (PT) of 100% of the nozzle-to-shell weld was ,

also performed. Refer to Attachment 1 for examination data I reports.

Justification For The Granting Of Relief:

The design configuration of the subject nozzle-to-head welds  ;

precludes ultrasonic examination of essentially 100% of the )

required examination volume. In order to examine the weld j in accordance with the code requirement, the RHR heat i exchanger would require extensive design modifications. The l physical arrangement of weld RHRW-14-A, in conjunction with  !

the small radius of curvature of the outside wall surfaces I of the nozzle, precludes ultrasonic examination from the l . nozzle side. For scans normal to the weld on the vessel E2-2 l

1

P shell siue, examinations are limited circumfere tially due to large srpport pads attached by fillet welds at t'o locations (90 and 270 degree nozzle azimuths) and the close proximatety of heat exchanger weld RHRW-16-A scube sheet-to-head weld at 0. degree nozzle azimuth) and heat exchanger weld RHRW-17-A (bottom head-to-shell weld at 180 degree nozzle azimuth). The axial scan area is limited due to the close proximity of the support pad fillet weld. A total of four areas (24% of toca; circumference) are unrestricted for one side examinatica cut. rage. Total ultrasonic examination coverage for weld RBxW-14-A was approximately 15% of the required code coverage for the weld.

Radiographic examination from the outside surface as an l alternate volumetric examination method was determined to be I impractical due to the component thickness and a divider plate inside the component head affecting radiographic quality. Performing radiographic examination from the inside sarface of the heat exchanger would require placing a radiograpnic source near the center of the head. This would require extensive modifications in order to gain access to the inside for source placement. The heat exchanger would require disassembly at the tube-sheet and the component moved in an upward direction for approximately two feet.

Thus additional radiography and/or ultrasonics examinations from the inner surface, to gain additional coverage, are also impractical.

Performance of an ultrasonic volumetric examination of essentially 100% of the required volume of the RHR heat exchanger full penetration nozzle-to-shell weld RHRW-14-A would be impractical. In addition, it is impractical to l perform other volumetric examinations which may increase

-examination coverage. The surface examination of 100% of the weld areas and adjacent metal, and a maximum extent practical ultrasonic examination of the subject weld provide reasonable assurance of an acceptable level of quality and safety. Significant degradation, if present, would have l been detected during the surface and ultrasonic examinations that were performed on the subject weld. As a result, assurance of structural integrity for this weld is provided i

by the examinations that were performed.

i Therefore, pursuant to 10 CFR 50.55a (g) (v, (iii) , it is requested that relief be granted for the second inspection interval.

1 i

E2-3 i

I

~ Implementation Schedule:

This request for relief is applicable to the second inspection. interval for SON Unit 2. Weld RHRW-14-A was examined during the first period of the second 10-year inspection interval.

a Background Information:

A request for relief for volumetric examination coverage limitations was submitted for RHRW-14-A as ISI-13 for Unit 2 in SON's first 10-year interval and was approved by the i reference 1 letter below with no additional augmented requirements.

References:

1. Letter from F. J. Hebdon, NRC, to O. D. Kingsley, TVA, dated February 7, 1991.

2. Nondestructive Evamination Procedure N-GP-28

" Calculation of ASME Code Coverage for Section XI NDE Examinations," Revision 1.

Attachment 1 - Examination Data Reports: R-5736 and R-5760 )

Attachment 2 - ISI Program Drawing: ISI-0289-C-02 E2-4 l

L

~

l F

~

REQUEST FOR-RELIEF 2-ISI-12.

Execut'ive: Summary:

This' request for-relief addresses integrally welded attachments on the l centrifugal charging pump. (2A-A) .

~

The

. design.' configuration'of~the subject attachment welds-precludes 100%; surface examination'of the-required area for weld:CCPH-2A-A-IA.(four integrally welded lug attachments to the pump. casing). 1These. physical. examination limitations

-occurLwhen~the 1989 Code examination requirements are applied in. areas.of-components constructed and fabricated to

~

i early. plant physical design. Based on the date of SON's construction permit (May 27, 1970), SQN is exempt from code requirements;for examination access as allowed in 10CFR

- 50.55a (g) (4) .

A liquid penetrant surface-examination was performed on accessible areas to the maximum extent practical, given the physical limitations of the subject 1 welds. The design configuration-limits surface examination to approximately 83.5%^of integrally welded attachments 1CCPH-2A-A-IA.

-Performance of a' surface examination of essentially 100% of the. integrally-welded attachments CCPH-2A-A-IA is

. imp 2 .cical. . The maximum extent practical surface i examination'of.the. subject integrally welded attachments providesfreasonable assurance of an acceptable level of quality and_ safety because the information and data obtained

-from the area examined provides sufficient information to judge'the overall integrity of the. integrally welded a ttachments '.

1Therefore, . pursuant to 10. CFR 50.55a (g) (5) (iii) , it is

-requested.thatLrelief be granted for~the second inspection

interval.

1 a

Unit: 2-s i

' System: -Chemical Volume Control - System 62  !

-Components:: Integral Welded Attachments for i Centrifugal Charging Pump 2A-A  ;

ASME-Code Class: ASME Code ~ Class 2 (Equivalent)

'Section'XI' Edition: 1989 Edition ' (Code Case N-509)

Code Table: Table 2500-1 of Code Case ~N-509

/ Examination Category: C-C, Integral Attachments for Class l 2 Vessels, Piping, Pumps, and Valves E2-5

t.  !

Examination Item Number: C3.30, Pumps, Integrally Welded Attachments Code Requirement: Code Case N-509, Table 2500-1, Examination Category C-C, Item Number C3,30, Requires Surface Examination Code Requirement '

From Which Relief Is Requested: Surface Examination Coverage of Essentially 100% of Integrally Welded Attachments List Of Items Associated

)

With The Relief Request: CCPH-2A-A-IA, Integral Welded Attachments Basis For Relief: J The design cc iguration of the centrifugal charging pump and integral welded attachments precludes a surface examination or the required area of the integrally welded attachments CCPH-2A-A-IA. The design configuration limits surface examination to approximately 83.5%, as calculated in I accordance with TVA procedure N-GP-28, of the required area.

Alternative Examinations:

In lieu of the code required 100% surface examination, a liquid penetrant examination war performed on accessible areas to the maximum extent pract_ cal given the physical limitations of the subject integrally welded attachments.

Refer to Attachment 1 for examination data report.

l Justification For The Granting Of Relief:

! The design configuration of the subject attachment welds l precludes surface examination of essentially 100% of the requiredLexamination area. In order to examine the welds in accordance with the code requirement, the centrifugal charging pump would require extensive redesign and modification to allow access to the bottom side of the attachment lugs. Connecting piping would have to be disconnected and the pump disassembled and lifted to allow access to the remaining 16.5% examination area. The weld joint detail consists of a full penetration weld with fillet weld reinforcement. The attachment is circumferentially welded with a fillet weld. The bottom side of the attachment is inaccessible due to a support that bolts the E2-6

pump to the supporting frame. The total surface examination coverage for integral attachment welds CCPH-2A-A-IA was approximately 83.5% of the required code coverage. Other nondestructive examination (NDE) techniques were considered, but due to the location of the inaccessible area, the same

. limitations would be encountered.

Performing an surface examination of essentially 100% of the required area of integrally welded attachments CCPH-2A-A-IA would be impractical. In addition, it is impractical to perform other NDE examinations. The maximum extent practical surface examination of the weld area and adjacent metal of the subject weld provides reasonable assurance of an acceptable level of quality and safety. Significant degradation, if present, would have been detected during the surface examination that was performed on the subject integrally welded attachments. As a result, assurance of structural integrity for the integrally welded attachments is provided by the examination that was performed.

Therefore, pursuant to 10 CFR 50.55a (g) (5) (iii) , it is requested that relief be granted for the second inspection )

interval, j l

Implementation Schedule: I This request for relief is applicable to the second inspection interval for SON Unit 2. CCPH-2A-A-IA (four integrally welded lug attachments to pump) were examined during the first period of the second 10-year inspection interval.

References:

Nondestructive Examination Procedure N-GP-28 " Calculation of ASME Code Coverage for Section XI NDE Examinations,"

Revision 1. - Examination Data Report: R-5761 I - ISI Program Drawing: ISI-0467-C-01 l

I i

E2-7

p' a

REQUEST FOR RELIEF 2-ISI-13 Executive Summary.

This; request for relief addresses circumferential pressure

-retaining dissimilar metal welds.on'the steam generator nozzles. The design configuration and materials used in the fabrication offthe subject welds precludes an 100%

ultrasonic examination of the required volume for the ]

-following welds: RC-02-SE- (pipe elbow to steam generator primary head casing) and'RC-03-SE (steam _ generator primary head casing to' pipe' elbow). These physical examination limitations occur when the 1989 Code examination requirements are applied-in areas of components constructed and fabricated to early plant physical designs. Based on the date~of SON's construction permit (May 27, 1970), SON is exempt from-the code requirements for examination access as allowed in .10 CFR 50.55a (g)-(4) .

A liquid' penetrant surface examination was performed on 100%

of theLsubject welds. An ultrasonic examination was performed on accessible areas to the maximum extent practical given the_ physical limitations and materials of

'the subject welds.- The design configuration of the steam )

generator nozzle safe-ends and materials used in fabrication-of the1 reactor coolant piping limits, ultrasonic examination to approximately 75% of weld RC-02-SE and approximately 75%

ofLweld RC-03-SE. Performance of an ultrasonic examination of' essentially 100% of the circumferential pressure retaining welds RC-02-SE and RC-03-SE, is impractical. A surface-examination and the maximum extent practical ultrasonic examination of the subject welds provide reasonable assurance of an' acceptable level of quality and safety b1cause the information and data obtained from the weld surface and weld volume examined provides sufficient j information to judge the overall integrity of the welds. ]

Therefore, pursuant to 10 CFR 50.55a (g) (5) (iii), it is i requested that relief be granted for the second inspection l interval.

Unit:- 2  !

System: Reactor Coolant - System 68 (Steam Generator)

Components:, Two_ Pressure Retaining Dissimilar Metal Welds

[ASME Code Class: ASME Code Class 1 (Equivalent)

E2-8  !

1 Section XI Edition: 1989 Edition Code Table: IWB-2500-1

' Examination Category: B-F, Pressure Retaining Dissimilar Metal Welds j Examination Item Number: B5.70, Nozzle-to-Safe End Butt Welds Nominal Pipe Size 4 Inches Or I Larger I

Code Requirement: ASME Section XI, Table IWB-2500-1, j Examination Category B-F, Item Number B5.70,. Requires Surface And Volumetric Examinations Code Requirement From Which Relief ,

Is Requested: Volumetric Examination Coverage of i Essentially 100% of Pressure Retaining Dissimilar Metal Welds List Of Items Associated With The Relief Request: RC-02-SE, Steam Generator Nozzle-to-Safe End Butt Weld RC-03-SE, Steam Generator Nozzle-to-Safe End Butt Weld Basis For Relief:

The design configuration of the steam generator nozzle safe-ends and materials used in fabrication of the reactor coolant piping preclude an ultrasonic examination of the required volume of pressure retaining circumferential dissimilar metal welds RC-02-SE and RC-03-SE. The design ,

configuration and materials used in fabrication limit I ultrasonic examination to approximately 75% of weld RC-02-SE and approximately 75% of weld RC-03-SE, as calculated in accordance with TVA procedure N-GP-28.

Alternative Examinations:

In~ lieu of the code required 100% ultrasonic examination, an ultrasonic examination was performed on accessible areas to the maximum extent practical given the physical limitations of the subject welds. A surface examination (PT) of 100% of welds RC-02-SE and cC-03-SE was also performed. Refer to Attachment 1 for the examination data reports.

.E2-9

Justification For The Granting Of Relief:

The design configuration and materials used in the fabrication of the. subject piping welds preclude ultrasonic examination of essentially 100% of the required examination volume. In order to cxamine the welds in accordance with the code requirement, the steam generator would require extensive redesign along with changing the piping material.

The weld joint detail for welds RC-02-SE and RC-03-SE consists of a pipe elbow welded to a steam generator primary head single piece casing. The pipe elbow is static cast CF8M material. The steam generator bottom head is a single j piece casting (SA-216 GR WCC) with integral cast nozzles. l The nozzle safe end welds consist of approximately 0.5 inch layer of TY-308-L weld material (buttering) applied to the

-nozzle weld edge preparation surface. The examinations are limited due to the design configuration and the effects of the anisotropic coarse grain structure of cast stainless material and the weld joint configuration which limit search unit contact and movement.

The total ultrasonic examination coverage for RC-02-SE and RC-03-SE was approximately 75% of the required code coverage j for each weld. Due to the anisotropic coarse grain  !

structure of cast stainless CF8M materials, the examination j was limited to the 1/2 vee technique using refracted f longitudinal waves. Circumferential scans for both welds were unlimited. Both welds received 100% coverage from one side scanning in the axial direction with the sound beam directed toward the steam generator. No scans were performed from the steam generator side in the axial direction due to the steam generator nozzle weld taper interference; therefore, 0% coverage was obtained from this direction. It is reasonable to assume that circumferential j flaws would be detected to the degree comparable with I industry standards for such materials, j Radiographic examination, as an alternate volumetric examination method, was determined to be impractical due the high radiation doses that would be received while placing j the radiography source inside the steam generator. It is 1 estimated the NDE examiners would receive a dose of 1 2050 mrem per weld performing a radiographic examination (NDE examiners would receive a dose of 300 mrem per wald  ;

performing an ultrasonic examination). Radiography from the outside surface with a Co-60 source would be impractical due to high surface dose rates (150 to .200 mrem). Long exposure ,

times would cause an unacceptable fog level on the film. l i

E2-10

Westinghouse plants have no history of pipe cracking failure in the reactor coolant primary loop. For stress corrosion cracking (SCC) to occur, the following three conditions must exist simultaneously; high tensile stresses, a susceptible material, and a corrosive environment. The potential for SCC is minimized in Westinghouse pressurized water reactors by material selection and prevention of a corrosive environment (Reference Westinghouse RCS Piping Flawbase Handbook, WCAP-13670).

The examination of the steam generator dissimilar metal butt welds during the inspection interval, in accordance with ASME Section XI Code, provides reasonable assurance that significant. degradation, if present, would be detected.

Performance of an ultrasonic volumetric examination of essentially 100% of the required volume of pressure retaining dissimilar metal welds RC-02-SE and RC-03-SE in the reactor coolant main loop piping is impractical. In addition, it is impractical to perform other volumetric examinations, which may increase examination coverage. The surface examination of 100% of the weld area, adjacent metal, and a maximum extent practical ultrasonic enamination of the subject welds provides reasonable assurance of an acceptable level of quality end safety. Significant degradation, if present, would have been detected during the ultrasonic and surface examinations that were performed on the subject welds. As a result, assurance of structural integrity for these welds is provided by the examinations I

that were performed.

l Therefore, pursuant to 10 CFR 50.55a (g) (5) (iii) , it is requested that relief be granted for the second inspection interval.

Implementation Schedule:

j This request for relief is applicable to the second l inspection interval for SQN Unit 2. Welds RC-02-SE and

RC-03-SE were examined during the first period of the second 10-year inspection interval.

Background Information:

A request for relief for volumetriu maamination coverage limitations was submitted for the subject welds as 2-ISI-22 for Unit 2 in SQN's first 10-year interval and was approved by the reference 1 letter below with no additional augmented requirements.

E2-11 i

References:

1. Letter from David E. LaBarge, NRC, to O. D. Kingsley, TVA, dated February-7, 1996.

2. Nondestructive Examination Procedure N-GP-28

" Calculation of ASME Code Coverage for Section XI NDE Examinations," Revision 1. - Examination Data Reports: R-5790, R-5791, R-5819 and R-5820 - ISI Program Drawing: ISI-0401-C-01 1

l 1

E2-12

i ATTACHMENT 1 EXAMINATION DATA REPORTS R-5736 R-5760 R-5761 R-5790 R-5791 R-5819 R-5820 E2-13

/

RECORD OF REPORT NO.

TENNESSEE VALLEY AUTHORITY LIQUID PENETRANT

' EXAMINATION R- Q 3 lo

<ROJECT: 56G OOYAM UhTT: M EXAMINATION DATE: 9-/8'97 SYSTEM : 2ME3 - STARTTIME: /000 END TIME : /Y80 WELD / COMPONENT 1.D. : 2//fld- /i A l

- EXAM SURFACE: ID h OD CONFIO.: A/O FF LE TO V6 "6 L- ORIGINALEXAMINATION @ REEXAMINATION P j PROCEDURE:N PT- 9 REV.: /M 'TC: A//4 REFERENCE DRAWING NO. /s5/- ORB 9-d-O/ '

ASME SECTIONI h ASME SECTION XI Q . CODE CLASS / CATEGORY 8 /d3 ASME SECTION III $ ANSI B31.1 h ACCE TANCE CRITERIA )

ASME SECTION VIII ANSI B31.7 N-PT-9 APPENDIX A h APPENDIX B b AWS DI.1 @ OTHER NI i* OTHER N[A METHOD OF EXAMINATION METIIOD PENETRANT MATERIALS i h WATER-WASHABLE FLUORESCENT DYE BRAND NAME: MAGA / aft _OX

@ POST-EMULSIFIABLE FLUORESCENT DYE PENETRANT T"DE: Sff-S P BATCH NO. 98A02M REMOVER TYPE: S F d .5 BATCH NO. 6Ao1N '

h SOLVENT-REMOVABLEFLUORESCENTDYE ./

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. h POST-EMULSIFIABLE,VISIBIE DYE

@ SOLVENTREMOVEABLEVISIBLEDYE METE /N: rJ A CAL. DUE DATE: A/I

/ .

PARTTEMPERATURE: 1T 'F PYROMETER S/N: s 753(o# CAL. DATE DUE: 7-16-78 I RESULTS OF EXAMINATION: SATISFACTORY @ UNSATISFACTORY h NOINO.: N/A EXPLANATION OF UNS ATISFACTORY RESULTS: ,

. /

/

4 REMARKS / LIMITATIONS: A/- #fAMM/4770Al ##cM Z " 16 ' re Z

• 3 / DvE To 1AlfLOfA 30ffCW ' A0 ~7'A0EA)7~~ TC dA Lb l- A:r MEASUA'fe e Al 0 2' elk.

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TVA 7440 (NP 3/94) 1813,ai55

EXAMINATION REPORT NO.

TENNESSEE VALLEY AWHORITY

SUMMARY

AND

~'

RESOLUTION SHEET R- g 7 (,o 3

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PAGE TVA 19670C (NP 7/92) ,

ULTRASONIC SIZING WA DATA SHEET CAllBRATION NO.

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ULTRASONIC SIZING TM Call 8 RATION NO.

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ULTRASONIC SIZING TVA CALIBRATION NO.

C- R-57bo TENNESSEE VALLEY AUTHORITY DATA SHEET l I

UNIT : '~2.- CYCLE : B

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/

TM " "^ S " '

DATA SHEET S'z'" ^ ' ' " " ^ ' ' ""

C- (L- T7bo

• mTENNESSEE VALLEY AUTHORITY

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EXAMINER : ### LEVEL 8/f / ~7 REVIEWED BY : LEVEL :[ DATE : //-74 2 PAGE: I OF: O

USN-50 ULTRASONIC CALIBR ATION NO.

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5) N/A 7)

SIGNAL i 100 90 80 70 60 50 40 30 20 10 C VERTICAL .

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LEVEL: "JT" ANil:

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l USN-50 ULTRASONIC CALIBRATION NO.

TENNESSEE VALLEY AUTHORITY CALIBRATION l

DATA SIIEET C- g- T% O PROJECT: M/D on VAM UNrr: 2 CALIBRATION DATE: 9-/6-97 PRO'EDURE: N tTr. /6 RE'<.: 7A TC: A//A CALIBRATION BLOCK NO.: _NO-15 TEM P.: ~Z6.

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TRANSDUCER MANUF.: M . , _ .

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NOMINAL ANGLE: GO ACTUAL ANGLE: (, O*

INSTRUMENT SETTINGS 100 REFLECTOR REFERENCE DATA

1. D ORIENTATION SENSITIVITY SET M* D AXIAL 63 G 80 A:e: E CIRC N/A A//A P

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• DELAY: 9.359 uS 7,ERO: 9 3 8 9 uS

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TENNESSEE VALLEY AUTHORITY LIQUID PENETRANT ,

EXAMINATION R- 3'PfB l PROJECT : 8 h, A / UNIT: 4 !d [ EXAMINATION DATE: 7 DeT 97 SYSTEM : $b STARTTIME: / 4 :t ~7 END TIME : /#AS WELD / COMPONENT I.D. : QO-o3-R# EXAM SURFACE: ID OD X CONFIG.: A f o r 2 /o_ ._ TO $E' ORIGINAL EXAMINATION REEXAMINATION PROCEDURE: N-I'T- 9 REV.: /4/ TC: M/d REFERENCE DRAWING NO. /S J -oa o / - d- o /

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EXAMINATION REPORT NO.

TENNESSEE VALLEY AUTHORITY

SUMMARY

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if to f D 0 USN M ULTRASONIC CALIBRATION NO.

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TENNESSEE VALLEY AUTHORITY CALIBRATION DATA SIIEET C- *W --

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PAGE 1 OF TVA 19674D (NP 8/93) i

1 MANU AL ULTR ASONIC ltEPORT NO.

TENNESSEE VALLEY AUTilO]UTY PlPING EXhMINATION DATA SllEET N- b PROJECT: A f o Ut W M /4 UNIT: ""L EXAMINATION DATE: 9 CY 97

! S YSTEM : AG I START TIME: /o.* m END TIME : / / /f' WELD I.D. : MC X T- EXAM SURFACE: O ID EOD CONFIG.: _ M// .- E All) TO Ma2.1/'*- MATERIALTYPE: O CS O SS O CS:_. 2 CCss k SURFACETEMP:jd *F PYRO NO.: E M /e/

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' C / / PAGE OF TVA 19670C (NP 7S2)

Grp-fR) $.$

USN-BtIULTRASONIC CALIBRATION NO.

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TENNESSEE VALLEY AUTHORITY CALIBRATION

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DATA SHEET C- 9T A O ,

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LEVEL: I DATE: /# M PAGE b OF REVIEWED DY: ,

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TVA 19674D (NP 8/93)

r M ANUAL ULTRASONIC llEl' ORT NO.

TENNESSES VALLE)' AUT110Rl*1 T Vll'ING EXAMINATION /

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ENCLOSURE 3 TVA PROCEDURE FOR CALCULATION OF ASME CODE COVERAGE FOR SECTION XI NONDESTRUCTIVE EXAMINATIONS l

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NONDESTRUCTIVE EXAMINATION PROCEDURE ' Procedure No. N-GP-28 TVA Nuclear Power Revision 1 Page 1 of 16

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C A RE009D  !

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1 CALCULATION OF ASME CODE COVERAGE FOR SECTION XI NDE EXAMINATIONS

" QUALITY RELATED" l

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IlliIIIlliI 0352290533 CHAT ISDPM-SECO2 N-GP-28

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Prepared By: .

, Stdm Date: a -n- 9 ef Technical Review: A velIII, Date: F //- 9 ISO Approval: Date: 8 -/f-7 7

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NONDESTRUCTTVE EXAMINATION PRvCEDURE Procedure No. N-GP-28 TVA Nuclear Power Revision 1 Page 2 of 16 1

i; Rev. No Date Description f

0 4/3/96 Initial issue.

1 8/15/97 Incorporate TC 97-09.

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NONDESTRUCTIVE EXAMINATION PROCEDURE Procedure No. N-GP-28 TVA Nuclear Power Revision I Page 3 of 16

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rT t 1.0^ Scope The scope of this procedure is to prcvide generic gaidelines for calculating the ASME Section XI code coverage obtained during volumetric and surface'exanunations. This procedure incorporates -

' ' the requirements of Code Case N-460, 2.0 Purpose This procedure applies to the calculation of ASME Section XI Code coverage for vessel welds.

pipiing welds, and integral attachments. This procedure applies to personnel performing surface' or volumetric examinations and may be used as a guide when calculating the examination coverage for preservice and inservice examinations when the coverage is less than that required by ASME Section XI. Coverage limitations may be due to an obstruction, interference. geometric configuration or other applicable reason.

30. References 3.1 ASME Section XI 1989 Edition 3.2 ' ASME Code Case N-460 4.0 - Definitions 4.1 Examinat:on Coverage-The percentage of the examination surface or volume obtained

~ , . .

during the performance of the examination.

4.2 Examination Surface- The surface of the weld and base material required to examined by ASME Section XI using a surface examination method.

4.3 Examination Volume- The volume of well and base material required to be examined by

. ASME Section XI using a volumetric examination method.

4.4 ; Scan Limitation- A limit on the ability to scan the surface (s) as required by procedure.

4.5 Surface timitation ,A, limit on the ability to perform a surface examinatipa nf the required surface (s) because of an interference.

4.6 Volumetric Limitation- A limit on the abihty to scan the required examination volume because of the geometric configuration, a physical interference, or a metallurgical condition of the material being examined.

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m NONDESTRUCTIVE EXAMNATION PROCEDURE -

TVA Nuclear Power Procedure No. N-GP-28 Revision 1 Page 4 of 16 v:

5.0 ' General 5.1 During the performance ofinservice inspmions. ASME Section XI requires examination coverage to be essentially 100% of the weld area or volume. For examination coverage than 100%, TVA has implemented ASME Code Case N-460 which states that wl.en the entire examination volume or area cannot be examined due to interference by another component or part geometry, a reduction in examination coverage for Class 1 or Class 2 welds may be accepted provided the reduction in coverage for that weld is less than 10%

5.2 :

- Surface examinations are typically conducted on the weld area plus a defined amount of base material on each side of the weld. Volumetric examinations specify a particular

-  ; volume to be examined. The Section XI required examination volume or surface

. examination area for each type of weld is depicted in figures ofIWB 2500 or IWC-2500

., as applicable. As depicted for piping welds volume width generally constitutes the weld plus 1/4t on each side while volume thickness generally constitutes the lower 1/3 of the piping thickness for the length of the weld. The exception normally' includes code category B-O which includes the weld plus 1/2 inch and full volume for the length of the weld. As depicted, for vessel welds, the volume width generally constitutes the weld pl 1/2t on each side of the weld while volume thickness generally constitutes the entire componentthickness (i.e. full volume). The vohime changes with variations in weld

. configuration (e.g. transition between different pipe thickness or vessel weld Configurati]nS). '

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.c, 5.3 The Section XI required examination volume or area shall be verified prior to calculation

' of the limitation. -

7 6.0 i-Documenting and Calculatine Examinadon Coveraee 6.1

. While perfonning a surface or ultrasonic examination, the NDE Examiner shall make every attempt to examine 100 percent of the examination area or volume.

6.2 '

' When practical, the two beam path directions for ultrasonic examinations should be .

-s performed from two sides of the weld or additional angles employed in order to maximize coverage.

6.3 L If 100%p ' ercent of the examinatibn surface or volume cannot be examined, the NDE Examiner should perform the following under the direction of the inspection coordinator or the NDE LevelIII:

6.3.1 -

Perform additional examinations with higher angles in order to maximize cover for ultrasonic exams.

6.3.2 Perform another surface method (i.e.. PT in lieu of hff) in order to m coverage.

' t 6.3.3 . ' Perform alternative NDE methods if applicable.

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F 1 NONDESTRUCTIVE EXAMIN, CON PROCEDURE Procedure No. N-GP-28 TVA Nuclear Pou er Revision 1

. Page 5 of 16 6.4 The examiner shall accurnely document a!! limitations, obstructions. interferences, geometric configuration, or other applicable reasons for not obtaining the required code coverage. ,

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6.5 The examiner shall document the limitation on a sketch. Examination coverage estimates may be performed by the examiner or the reviewer.

7.0 . Calculation Basis 1 7.! Volumetric Examinations- Piping Welds and Vessels less than 2 inches in thickness a) For welds with access from both sides, each of the four required scans are equal to 25 %

b) For welds with access from one side only due to interference / configuration (e.g. I pipe to valve), the axial scan (scan 3 or 4) equals 5C% and the circumferential scans (scan 5 and 6) each equal 25% for total of 100%

'c) Examination volume coverage may be increased as previously discussed or by use of refmeted longitudinal wave techniques on stainless steel or dissimilar metal welds.

Use of refracted longitudinal waves to penetrate stainless steel weld material will j

increase the examination volume coverage by the amount depicted on the l examination coverage drawing; f

- -g d) The effects of adjacent component interferences (e.g. welded lug attachments) along J 1

_a the weld length are also taken into account with the reduction in coverage identified as a percentage of reduced volume.

l 7.2 A typical method for calculating coverage due to ultrasonic piping limitations is contained in Attachments 2 and 2A.

8.0 Surface Examinations - Pioine Welds And Integral Attachments 8.1 Examination area coverage calculations are based upon er

'the follov' : supr :tions:

s The total examination a'rea is calculated, typically length x width, then the total area a) l of limitation or interference is subtracted from the total examination area. I b) The area of achieved coverage achieved is divided by the total examination area for percentage of examination achieved.

8.2 A typical method for calculating surface examinations is contained in Attachment 4.  !

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NONDESTRUCTIVE EXAMINATION PROCEDURE - Procedure No. N-GP-28 TVA Nuclear Power l Revision 1 '

Page 6 of 16 9.0 Ultrasonic Examinations - Vessel Welds 9,1 Examination volume coverage calculations are based upon the following suppositions:

- a) To achieve full examination coverage nine different scans are required for a typical nozzle examination. The following may be used for other vessel configurations:

1) 0 degree (weld metal scan)

2) 45 degree Transverse-scan from vessel side of the weld

3) 45 degree Transverse-scan from nozzle side of the weld

4) 60 degree Transverse-scan from vessel side of the weld

5) 60 degree Transverse-scan from nozzle side of the weld

• 6) 45 degree Parallel-scan CW direction

7) 45 degiec Parallel-scan CCW direction

8) 60 degree Parallel-scan CW direction

9) 60 degree Parallel-scan CCW direction -

9.2 Attachment 3 describes ASME code compliance for full volume examination coverage for transverse scans in vessel applications.

9.3 Typical niethods for calculating coverage due to ultrasonic vessel limitations is contained in Attachments 3 A,3B,3C, and 3D.

i 10.0 Responsibilities

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10.1 The examiner or designee shall document the amount of code coverage obtained on Attachment I after all necessary steps to perform additional examinations has been (  ;

completed in order to maximize coverage.

10.2 Attachment I shall be reviewed by another individual with the same or higher NDE certification.

. s 10.3 The NDE Level III or da'a reviewer shall review Attachment 1 in order to verify that the information is accurate and correct.

. 10.4 The NDE Level III may recalculate the examination coverage to obtain a more accurate value of the examination surface or volume examined. The calculation shall be documented on the exam repon.

10.5 The NDE Level III may require an alternate examination technique or method, or request  ;

that the interference be removed. For nozzle examinations, supplemental scans from the j nozzle bore or flange face may provide complete coverage of the weld..

10.6 If the examination coverage indicates less than 90 percent of the required examination _

volume or surface, the site ISI supervisor shall be notified.  ;

10.7 The site ISI supe visor shall ensure that examination results are accurately documented and incorporate results into a Request for Reliefif necessary. .

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NONDESTRUCTIVE EXAMINATTON PROCEDURE 'Precedure No. N-GP-23 TVA Nuclear Power Revision 1

, Page 7 of 16 ATTACHMENT 1 EIAMINATION EportNo*

sm FAUR AumarrrY

SUMMARY

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k, ' NONDESTRUCTIVE EXAMINATION PROCEDURE Procedure No. N-GP-28 h TVA Nuclear Power Revision :

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ATTACHMENT 2 I s

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12" Schedule 140 n Outside Diameter- 12.75" Wall thickness- 1.125" 13/4"  !

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. Circumference- 40.05"  !

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. ... . i, TOTAL VO.LUME- (.375)(1.75)(40.05) l TOTAL VOLUME- 26.28 cu. inches e

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~ i NONDESTRUCTIVE EXAMINATION PROCEDURE *Precedure No. N-GP-28  !

TVA Nuclear Power Revision 1 l Page 9 of 16 I ATTACHMENT 2A ,

i ATTACHENT 2A - PPNG/ VESSELS 4.ESS

.875"- A THAN 2 NCHES N THICKNESS EXAMPLE 2 ,

NO COVERAGE FOR 6 NCHES N m c:mmz 45 DEGREE

.375" Rn trmm / COVERAM LENGTH DUE TO ATTACHMENT NNSTREAM h .

A .2578 SQ.IN VOL.-(.2578)(6")

.5 00"-B VOL-1.5468 CU.!N.

45 DEGREE NO COVERAGE-1.5468/26.ZB

( i COVERAGE UPSTREAM NO COVERAGE .0525(100)-5.88%

COVERAGE-100-5.25-94.75%

1.75"

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45 ORC SCAN-100%

45 CIRC SCAN-100%

EXANPLE 1 98E9% TOTAL COVERAGE NO CCVERAGE, FULL LENGTH ASSUME ALL OTER SCANS =100%

- 100b100b100%60.74-360.74 A H/2(A+B) 360.74/4- 90.185% TOTAL EXAM COVERAM A=.375/2(.675+.5)

EXANPLE 1 A=.25 78 VOL.-(.2578)(40.05) FULL COVERAGE-(.375)(1.75)(40.05)=26.28 CU.N.

VOL-10.32CUJN.

NO COVERAGE-10.32/26.28 -

NO COVERAGE =.3926 (100)=39.26%

COVERAGE-100-39.26-60.74%

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NONDESTRUCTIVE EXAMINATION PROCEDURE . Procedure No. N4P.28 TVA Nuclear Power Revision 1

, Page 10 of 16 ATTACHMENT 3 s

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45 DEGREE-100% ASME SECDON XI COVERAGE (T-SCAN) l t

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! 60 DEGREE-100% ASME SECTION XI COVERAGE (T-SCAN)

THE ASME SECTON XI CODE REQUIRES THE W' ELD TO BE COMPLETELY EXAMINED IN TWO DIRECTONS. THE ABOVE ARE EXAMPLES OF100% BIDIRECTIONAL COVERAGE (T-SCANS). .

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NONDESTRUCTIVE EXAMINA7lON PROCEDURE Procedure No. N-GP-28 TVA Nuclear Power Revision 1 Page 11 of 16 ATTACHMEbTT 3A s

1/2 T-1.5" l

5 L 3/16" LENGTH-85"

/ - 1.2 5" 4 k T

- V .25" )J

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, 60 D 2.75" 3.0"

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45 DEG TOTAL VOLUME- (L)(W)(H) -

TCTAL VOLUME- (85)(4.25)(3) 41/4-TOTAL VOLUME- 1083.75 CU. INCHES EXAMPLE 1-45T AND 60T SCANS AS SHOWN UMITED FOR FULL LENGTH.

'. ..~ EXAMPLE 2 45T AND 60T SCANS AS SHOWN LIMITED FOR A LENGTH OF 12 INCHES. -

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NONDESTRUCITVE EXAMINATION PROCEDURE Procedure No. N-GP 28

. TVA Nuclear Power Revision 1 Page 12 of 16 {

l ATTACHMENT 3B ,

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s. EXAMPLE 1 AREA 1 1.5" /

A H-2.7 5" p 3.0" B-2.75" 4.25" AREA 2 1.0-DETERM ..E AREA EXAMINED.

TOTAL AREA =(3)(4.25)-12.75 A-1/2(2 7 ) .75)=3.78 SQ.IN. VOL-(12.75)(85)-1083.75 IN VOL=(3.78)(851N.)= 321.3 CUBC IN. DETERMINE AREA REQUIRED TO BE EXAMINED BY THE CODE. _

0 AREA 1-1/2BH-1/2(1.5)(1.5)-1.125 AREA 2= TOTAL AREA-AREA 1 AREA 2- 12.75-1.125 - 11.625 SQ,N.

VOLUME AREA 2- (11.625)(85)

.. VOLUME AREA 2- 988.125 CU.IN.

2.0 DETERMINE 45 DEGREE COVERAGE

^1 COW. RAGE = VOLUME COVERED / VOLUME REQUIRED 45 DEGREE COVERAGE-321.3/988.125 .3251(100)- 32.51%  !

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p NONDESTRUCTIVE EXAMINATION PROCEDURE TVA Nuclear Power -

l Procedure Revision i No. N-GP-28

.. j Page 13 of16 n-ATTACHMElfT 3C EXAMPLE 1 AREA 1 x

1.5" / ;c 2.75"

• ! DETERMINE TOTAL

~T EFFECTIVE 866 i COVERAGE A=.375 B-2.8125"

. 3.0" o.100%

45T-29.76%

/ 45T-100%

' H-4.2 5" 4.25" \ 60T-55.9%

AREA 2 60T-100%

TOTAL AREA-(3)(4.25)-12.75 45Pcw-100%

1.0-DETERMINE REA EXAMINED.

VOL=(12.75)(85)-1083.75 CU.IN. 45Pccw-100%

A=H/2(A+B) 60Pcw-100%

DETERMINE AREA REQUIRED TO BE 60Pccw-100%

A-4.25/2(.375+2.8125)=6.77 SQ.lN.

EXAMINED BY THE CODE.

j' VOL=(6.77)(851N.)- 575.45 CUBC IN. TOTAL-785.66 AREA 1 -1/2BH-1/2(.866)(1.5)= ~

AVERAGE-785.66/9 AREA .649 SQ.IN. AVERAGE.87.29%

VOL-(.649)(85)=55.165 CU.IN.

AREA 2- TOTAL AREA-AREA 1 AREA 2- 12.75 SQ.IN. .649 SQ.IN.- 12.10 SQ.IN.

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2.0 DETERMINE 45 DEGREE COVERAGE COVERAGE-VOLUME COVERE,,D/ VOLUME REQUIRED

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45 DEGREE COVERAGE-575.45/1028.585 .559(100)- 55.9%

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EXAMPLE 2 45 DEGREE DETERMINE TOTAL l

AREA NOT COV ERED- (AREA 2)-(AREA EXAMINED) COVERAGE FOR l AREA NOT COVERED- 11.625 SQ.IN.-3.78 SQ.lN-7.845 SQ.lt). . WELD VOLUME NOT COVERED- (7.845 SQ.lN.)(12iN.)-94.14 CU.IN. ,

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45 DEG. (NO COVERAGE)= 94.14/1083.75*100-8.68% O- 100%

60 DEG. (NO COVERAGE)='67.44/1083.75*100-6.22% 45T-91.32%

.- 45T-100 45 DEG. (COVERAGE)= 100-8.68-91.32% 60T-93.78% )

60 DEG. (COVERAGE)-100-6.22-93.78% ~

60T-100%

45Pcw-100%

45Pccw-100% .

60Pcw-100% 1 i

60Pcew=100%

TOTAL -885.1 i TOTAL AVERAGE-88.5.1/9 I TOTAL AVERAGE-98.34%

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77-NONDESTRU'*TIVE EXAhENATION PROCEDURE Procedure No. N-GP-28 YA Nuclear Power Revision 1

, Page 15 of 16 ATTACHMENT 4 Examples for calculating code coverage when examining integral attachments:

s EXAMPLE 1: Luc welded on Two sides!

l l 1/2* ." ~l 1/2*

lLi L2 La!

l j j Hanger clamp around lL4 Ls Ls: pipe on this side of l 3* Lug Lug.

l l I L Area to be examined j l  ;' "

for ASME code coverage.

Total weld length to be examined = Lt + L2. L3 +L4 + Ls + Le 3 Total weld length to be examined = 1/2 + 3 + 1/2 + 1/2 + 3 + 1/2 = 8'

)

Total weld length inaccessible =.La + Le Total weld length inaccessible = 1/2 + 1/2 = 1

• Therefore 7 inches were examined out of 8 giving a "per cent coverage" of 7/8 = 87.5%

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, EXAMPLE 2: Luc welded on Three sides!

1/2* ," ~ ,1/2*

l Lt L2 La j

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{ lL7 j clamp around pipe on this side of lug!

1/8* 3* Lug l l l  ! -

l l Total weld length t'o be examined = Lt + L2. La +L7 + L4 + Ls + Le Total weld length to be examined = 1/2 + 3 + 1/2 + 1/8 + 1/2 + 3 + 1/2 = 81/8' (8.125*)

- Total weld length inaccessible = L3 + Ls Total weld length inaccessible = 1/2 + 1/2 = 1*

Therefore,8.125

• were examined out of 9'so code coverage is 8.125/9 = 90.28%

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NONDES1RUCITVE EXAMINATION PROCEDURE Procedure No. N-GF-28 TVA Nuclear Power I Revision I

! Page 16 of 16

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I ATTACHMENT 4 A Examples for calculating code coverage when exarnining integral attachments (cont.):

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Example 3 Full penetration lucs

.!l2 lM l Clamp around

! L1 L2 L3 l pipe-this side

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Total weld length to be examined = L1 + L2. L3 +L7 + L4 + Ls + Ls + Le Total weld length to be examined = 1/2 + 4 + 1/2 + 2 + 1/2 + 4 + 1/2 + 2 = 14' f

Total weld length inaccessible = L3 + Le + Le Total weld length inaccessible = 1/2 + 2 + 1/2 = 3*

Therefore,11* were examined out of 14*, so code coverage is 11/14 = 78.57%

Examole 4 Luo coveraae comoutation usino area ersus ler.cth Use measurements in example 1 abovel M

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!  ! Hanger around pipe l this side only.

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with 1/4' fillet weld. l I l From first example, totallength = 8' The width of weld face for this example is .350* plus 1/2* above and below weld toes, for a total

, of 1.350' weld width.

The required area of examination is then 8 fong x 1.350 wide = 10.8 sq. in. -

l The length inaccessible is ( %* + %* = 1* length) so total area that is inaccessible is 1* x 1.350*

(wicth) = 1.350 sq. in. ,

Therefore, calculate code coverage by dividing total area examined (9 45 sq in) by total area which should be examined (10.8 sa. in.) equals 87.5%. Same as in first example usirnytength.