ML110830037

American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, Inservice Inspection Program, Third Ten-Year Inspection Interval, Request for Relief 3-ISI-26

ML110830037
Person / Time
Site:	Browns Ferry
Issue date:	03/21/2011
From:	Krich R Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
3-ISI-26
Download: ML110830037 (24)

Text

Tennessee Valley Authority 1101 Market Street, LP 3R Chattanooga, Tennessee 37402-2801 R. M. Krich Vice President Nuclear Licensing March 21, 2011 10 CFR 50.4 10 CFR 50.55a ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Unit 3 Facility Operating License No. DPR-68 NRC Docket No. 50-296

Subject:

American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section Xl, Inservice Inspection Program, Third Ten-Year Inspection Interval, Request for Relief 3-1S-26 In accordance with 10 CFR 50.55a(g)(5)(iii), the Tennessee Valley Authority (TVA) is requesting relief from weld examination coverage requirements specified in the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section Xl, 2001 Edition, 2003 Addenda as amended by 10 CFR 50.55a(b)(2)(xv)(A)(2), for one full penetration weld due to access limitations caused by design. This relief is requested for the Browns Ferry Nuclear Plant (BFN), Unit 3, third ten-year inspection interval which began November 19, 2005, and ends November 18, 2015.

Specifically, this request for relief addresses one reactor pressure vessel nozzle-to-vessel (head) full penetration weld. Ultrasonic examinations were performed on the accessible areas of this weld to the maximum extent practical for the design configuration of the weld.

The enclosure to this letter contains the BFN, Unit 3, Request for Relief 3-1SI-26, for NRC review and approval.

printed on recycled paper

U.S. Nuclear Regulatory Commission Page 2 March 21, 2011 This request for relief is consistent with the BFN, Unit 3, Request for Relief 3-ISI-23 submitted by TVA letters dated August 24, 2007 and April 9, 2008. The NRC approved this request by letter dated September 24, 2008.

TVA requests approval of this request for relief within one year from the date of this letter.

There are no new regulatory commitments in this letter. If you have any questions, please contact Tom Matthews at (423) 751-2687.

Respectfully, R. M. Kri ih

Enclosure:

American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, Inservice Inspection Program, Third Ten-Year Inspection Interval, Request for Relief 3-ISI-26 cc (Enclosure):

NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant

Enclosure Tennessee Valley Authority Browns Ferry Nuclear Plant Unit 3 American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, Inservice Inspection Program, Third Ten-Year Inspection Interval Request for Relief 3-ISI-26 E-1

Enclosure Tennessee Valley Authority Browns Ferry Nuclear Plant Unit 3 American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, Inservice Inspection Program, Third Ten-Year Inspection Interval Request for Relief 3-1S-26 Executive Summary: In accordance with 10 CFR 50.55a(g)(5)(iii), the Tennessee Valley Authority (TVA) is requesting relief from weld examination coverage requirements specified in the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section Xl for one Reactor Pressure Vessel (RPV) nozzle-to-vessel (head) full penetration ultrasonic (UT) weld examination performed during the Browns Ferry Nuclear Plant (BFN),

Unit 3, Cycle 13 Refueling Outage in the first period of the third ten-year interval.

The design configuration of the RPV Head nozzle-to-vessel (head) weld precludes a 100 percent UT examination of the required volume for the full penetration weld of the nozzle listed in Table 1 of this enclosure. These examination limitations occur when the ASME Section Xl, 2001 Edition, in accordance with 10 CFR 50.55a(b)(2)(xxiv) and, as amended by Sections 10 CFR 50.55a(b)(2)(xv)(B) through 10 CFR 50.55a(b)(2)(xv)(G), and 10 CFR 50.55a(b)(2)(xvi)(A), examination requirements are applied in areas of components constructed and fabricated to early plant designs. Based on a construction permit date prior to January 1, 1971, BFN is exempt from meeting certain provisions of the ASME Code requirements for examination access, to the extent practical, within the limitations of design, geometry, and materials of construction of the components in accordance with 10 CFR 50.55a(g)(4).

A UT examination was performed on the accessible areas to the maximum extent practical given the physical limitations of the subject weld. The subject weld was examined with the latest ultrasonic techniques, procedures, equipment, and personnel qualified to the requirements of the Performance Demonstration Initiative (PDI) Program, as required by 10 CFR 50.55a(g)(4) and 10 CFR 50.55a(g)(6)(ii)(C).

TVA concludes that performance of a UT examination of essentially 100 percent of the RPV nozzle-to-vessel full penetration weld would be impractical. The performance of the UT examination of the subject weld to the maximum extent practical provides an acceptable level of quality and safety because the information and data obtained from the volume examined provides sufficient information to judge the overall integrity of the weld.

Therefore, pursuant to 10 CFR 50.55a(g)(5)(iii), TVA requests that relief be granted for the BFN, Unit 3, third ten-year inspection interval.

This relief is requested for the BFN, Unit 3, third ten-year inspection interval which began November 19, 2005, and ends November 18, 2015.

This request for relief is consistent with the BFN, Unit 3, Request for Relief 3-ISI-23 submitted by TVA letters dated August 24, 2007 and April 9, 2008. The NRC approved this request by letter dated September 24, 2008.

E-2

Unit: Browns Ferry Nuclear Plant, Unit 3 System: Reactor Pressure Vessel Head Nozzle, System 329 ASME Code Components Affected: One RPV nozzle-to-vessel full penetration weld as listed in Table 1 of this enclosure ASME Code Class: ASME Code Class 1 (Equivalent)

Section Xl Edition: 2001 Edition, 2003 Addenda in accordance with 10 CFR 50.55a(b)(2)(xxiv) and, as amended by Sections 10 CFR 50.55a(b)(2)(xv)(B) through 10 CFR 50.55a(b)(2)(xv)(G), and 10 CFR 50.55a(b)(2)(xvi)(A), by following the Electric Power Research Institute's (EPRI) PDI processes.

Code Table: IWB-2500-1 Code Examination Category: B-D, "Full Penetration Welds of Nozzles in Vessels" Code Examination Item Number: B3.90, "Reactor Vessel Nozzle-to-Vessel Welds" Code Requirement: ASME Section XI, Table IWB-2500-1, Examination Category B-D, Item No. B3.90 requires a volumetric examination of essentially 100 percent of the weld and adjacent base material as depicted in Figure IWB-2500-7(a).

Code Requirements from Which Relief Is Requested: Relief is requested from the requirement of ASME Section XI Code, Table IWB-2500-1, Examination Category B-D, Item No. B3.90 to perform essentially 100 percent volumetric examination of the weld and adjacent base material.

List of Components Associated with this Request for Relief: RPV head, nozzle-to-vessel weld (N6A-NV)

Reason for Request: The design configuration of the RPV nozzle-to-vessel (N6A-NV) weld area precludes a UT examination of essentially 100 percent of the required volume.

The component design configuration limits UT examination coverage of the weld to the percentage listed in Table 1.

Proposed Alternative and Basis for Use: In lieu of the Code require essentially 100 percent volume UT examination, on the nozzle-to-vessel weld, TVA proposes a UT examination of accessible areas to the maximum extent practical given the component design configuration of the RPV nozzle-to-vessel weld.

Justification for Granting Relief: (1) The design configuration of the subject nozzle-to-vessel weld (N6A-NV), precludes UT examination of essentially 100 percent of the required examination volume. In order to examine the weld in accordance with the ASME Code requirements the RPV would require extensive design modifications. The physical arrangement of the nozzle-to-vessel weld precludes UT examination from the nozzle side. The limitations are inherent to the barrel-type nozzle-to-vessel weld design.

Scanning from the nozzle surface is ineffective due to the weld location and the asymmetrical inside surface where the nozzle and vessel converge. Experience from the automated UT examination performed from the inside surface has shown that the E-3

nozzle-to-vessel weld coverage will not be greatly improved even if performed from the inside surface utilizing the current state-of-the-art techniques. The areas receiving little or no examination coverage are located toward the outside surface of the reactor vessel in the general area of the nozzle outside blend radius.

The blend radius of the weld restricts the scanning movement and/or transducer contact.

The reactor vessel inner-half of the thickness and inside surface are interrogated with the UT beam. Degradation located at the inside surface or inner-half of the vessel would be located.

The subject weld was examined with the latest ultrasonic techniques, procedures, equipment, and personnel qualified to the requirements of the PDI Program, in accordance with the requirements of the 2001 Edition, in accordance with 10 CFR 50.55a(b)(2)(xxiv) and, as amended by Sections 10 CFR 50.55a(b)(2)(xv)(B) through 10 CFR 50.55a(b)(2)(xv)(G), and 10 CFR 50.55a(b)(2)(xvi)(A), by following the EPRI's PDI processes.

(2) Radiographic examination as an alternate volumetric examination method was determined to be impractical due to the radiological concerns. Gaining access to the inside surface of the RPV to place radiographic film would require extensive personnel protection due to high radiation and contamination levels. Also, due to the varying thickness at the outside blend radius of the weld several radiographs may be required of one area to obtain the required coverage and/or film density. The additional ASME Code coverage gained by radiography is impractical when weighed against the radiological concerns.

Therefore, TVA concludes that performing a UT examination of essentially 100 percent of the nozzle-to-vessel full penetration weld would be impractical. Further, it would also be impractical to perform other volumetric examinations (i.e., radiography) which may increase examination coverage.

A maximum extent practical UT examination of the subject areas provides an acceptable level of quality and safety. IVA concludes that significant degradation, if present, would be detected during a UT examination performed to the maximum extent practical of the subject weld. As a result, reasonable assurance of operational readiness of the subject weld has been provided.

Therefore pursuant to 10 CFR 50.55a(g)(5)(iii), TVA requests that relief be granted for the BFN, Unit 3, third ten-year ISI inspection interval.

Implementation Schedule:

This request for relief is applicable to the third ten-year ISI inspection interval for BFN, Unit 3, which began on November 19, 2005, and will end on November 18, 2015. The weld described above is listed in Table 1 of this enclosure. The weld was examined during the first period (Cycle 13 - spring 2008) of the third ten-year inspection interval.

Precedent:

This request for relief is consistent with BFN, Unit 3, Request for Relief 3-ISI-23 submitted by TVA letters dated August 24, 2007, and April 9, 2008. The NRC approved this request by letter dated September 24, 2008.

E-4

Attachments:

Attachment A (Inservice Inspection Drawinqs) 3-1SI-0295-A, Revision 001 Sketch SK-B3001, Reactor Pressure Vessel Assembly Sketch SK-B3011, Attachments Map Top Head Assembly Sketch SK-B3016, Weld Detail Head Spray / Instrumentation Nozzle N6 Attachment B (Weld Examination Data Report)

Weld Examination Report, R-054 E-5

Table 1 Nominal Examination Weld Number I Pipe Size ISl Drawing Coverage Unit Comments (System)

(NPS)

Number Percent Cycle Nozzle-to-vessel weld (RPV Head Nozzle)

N6A-NV (RPV 6"

3-ISI-0295-A 58.9%

3 / 13 examined using a 26, 45, and 55 degree Instrumentation shear wave mode and a 60 degree refracted Head Nozzle)

(Spring longitudinal wave mode. Scanning was 2008) Nrestricted due to nozzle configuration.

2008)

Exams were performed from the head shell side and outer blend radius. This weld was examined using PDI qualified personnel, procedures, and equipment. The coverage claimed is 58.9%.

E-6

Attachment A Inservice Inspection Drawings 3-1SI-0295-A, Revision 001 Sketch SK-B3001, Reactor Pressure Vessel Assembly Sketch SK-B301 1, Attachments Map Top Head Assembly Sketch SK-B3016, Weld Detail Head Spray / Instrumentation Nozzle N6 E-7

Of N?

9-7/16-REFERENCE ORAWINGS:

B&W 122876 BAW 122577 NOTE.

THIS DRAWING SUPERSEDES CWI-2102-A fUNIT.3 ONLY)

I MATERIAL SPECzFICA TIONS CLOSURE HEAD DOME/SEGMENTS CS MNA/M N-7 NOZZLE - A308 CL.2 (*W-AO)

LONG WELD NECK -

SA-105 GR.Ir CS N6A. N68 NOZZLE -

A5S0 CL.2 (MN-MO)

LONG WELD NECK -

SA-O15 GR.II CS 300' 270*

240" ec ASME CC-? (EQUJIVALE(NT)

120, RCH-3-ZC iSO.

0011 u

WM awl=N U IRS 1" 314 04013 tat LV I OM W

IV POMI I OW@

AMM 1 0*12 TEN2MSXE VALL(Y AUDWoarY BROWNS~ ?FERRY NUCLEAR~ ILAPJI UNI T 3 CL 0SURE HEAD ASSEAR Y WEL LOATON DETAIL C W-WnM~

g at-I' Q1-AMw I-I ALL A/D HISTORY RESEARCHED AT ROOD

6

I.,

..............4

Attachment B Weld Examination Data Report Weld Examination Report, R054

000232 C

TENNESSEE VALLEY EXAMINATION

SUMMARY

AUTHORITY AND REPORTNUMER:

RESOLUTION DATA SHEET R,05'*,

PROJECT: BFN UNIT: 3 CYCLE: 13 COMPONENT ID: N6A-NV EXAMINATION METHOD SYSTEM:

RPV ISI DWG. NO. 3-ISI-0295-A-01 MT Li PT Li UT VT CODE CLASS:

1 CATEGORY: B-D PROCEDURE: N-UT-78 REV:4 TC:NA COFIG.:

Nozzle TO Vessel EXAMINER: I-A0D EXAMINEJ EXAMINER:

EXAMINER:

2) 1,r,-*r, n

.f L I ta a

n LEVEL:

LEVEL: j2/-

LEVEL:

LEVEL:

The package contains the ultrasonic examination data for N6A-NV.

This exam meets the requirements of ASME Section XI, 2001 edition, 2003 Addenda for category B-D, item B3.90, EXREQ 03E-03.

The examination was performed using ASME Section X1, Appendix VII and Appendix VIII personnel, equipment and techniques as ammended by the 10CFR50.55a Final Rule The joint configuration is a 6" nominal diameter RPV Nozzle to Shell weld located on the RPV Head.

The examination was performed using TVA Procedure N-UT-78 for the Supplement 4/6 exam voloume and AREVA Procedure 54-ISI-850 for the Supplement 5 exam volume. The supplement 4/6 exam volume was examined using a 60 degree RL. The supplement 5 volume was examined using a 26, 45 and 55 degree shear wave as defined in EPRI modeling document IR-2003-17.

The achieved examination volumes are as follows:

Supplement 5 volume (inner 15%)=100%

Supplement 4/6 volume (outer 85%)= 57.5%

ASME Code Required Volume (Full volume)= 58.9%

RESOLUTION BDY:/Sj P0 REVIEWED BY:

ANII:

rLEVZE12 DýAýTE:-..i*/.,*

LEVEL:='

DATIE:

t'/'L*

PG.

,""OF

]

V,

Tennessee Valley Authority Ultrasonic Examination Data Sheet Nozzle-to-Shell Weld Examination Utility: TVA I Site: Browns Perry I Unit/Outage: 3 / Cycle 13 RFO Examination Data Sheet NumberI ISl Report Number XQGO Component ID: NBA-NV Component

Description:

N6 Nozzle-to-Closure Head Weld

-Examination.

infoirmation ISO / Drawing Number: 3-ISi-0295-A-01 Eo a Location: Nozzle Boss (Rnozzle)

I Lo Location: Nozzle TDC Examination Limited: 1Yes LjNo Coverage Sheet Number Scan Information Examination Procedure: 54-IS"-850-06 Applicable SDCN's: 30-9069955-000, & 30-9044520-000 Scan Surface: OD Nozzle Blend Angle/

Skew Calibration Sheet DThermometer Scan Gain Scan Umited Recordable Indication Examiner Mode Sii eae S/N:

Indication(s)

Data Sheet #

Initials 26'/s

+90° 3/27/08 0950 75F 531993 74.0dB 0yes s No IlYes No N/A 26"s

-90 3/27108 0950 75F 531993 74.0dB 1Yes ONo

-Yes jMNo N/A NIA°/

N/AI N/A N/A N/A WA °F N/A N/A dB rYes [No rYes

=

No N/A N/A N/A-/

N/A° N/A N/A N/A N/A F N/A N/AdB

(-es ONo rYes rNo N/A N/A Examination Procedure: 64-11-850-06 Applicable SDCN's: 30-9069955-000, & 30-9044520-000 Scan Surface: OD Closure Head Anglet Skew Calibration Sheet #

Data Time Temp Thermometer Scan Gain Scan Limited Recordable Indication Examiner Mode SeCirinhetem S/N:

Indication(s)

Data Sheet #

Initials 45'1s

+k25° to 80 3/27/08 1006 75*F 531993 64.0dB rYes ONo DlYes ONo N/A 55/13 t20" to 60° 3/27/08 1032 75°F 531993 68.0dB DYes ONo Dyes MNo N/A Examination Procedure: N-UT78 Rev 4 Applicable SDCN's: N/A Scan Surface: OD Closure Head Angle/

Zone Beam Direction Calibration Sheet #

Date Time Temp Thermometer Scan Gain Scan Limited Recordable Indication Examiner Mode S/N:

Indication(s)

Data Sheet #

Initials 60°/RL 1

ORadial rlcIrc 3/27/08 1345 75F 531993 95.0 dB IMYes ONo nYes IMNo N/A 60"/RL 2

MeRdlal lcIrc 3/27/08 1400 75°F 531993 95.0 dB aYes ONo rYes ONo N/A 60*/RL 1

ORadlal MCIrc 3/27/08 1345 75"F 531993 95.0dB WYes rNo rYes MNo N/A 60°/RL 2

eRadial MCOrc 3/27/08 1400 75*F 531993 95.0dB OYes rDN0

[Yes ONo N/A Comments:

Examiner Thomas Brown Level: II Date: 3/27/08 Examiner. N/A Level: N/A Date: N/A Sign*tuT 7

Signature:

Examiner: Samuel Al Zipperer Level: IIL Date: 3/27/08 Examiner N/A Level: N/A Date: N/A Signature-

• 9 Signature:

TVAR.Level:

III Date:

0P.476 Signature

/lO Page 2-of /~

000,234 I

Tennessee Valley Reactor Pressure Vessel Authority Manual Ultrasonic Calibration Data Sheet

.Utility: TVA Site: Browns Ferry Nuclear Plant Unit: 3 Outage: Cycle 13 RFO ISO/ Drawing Number ISI 0295-A-01 ISI Report Number:

94059P Component ID: N6A-NV Component

Description:

Nozzle - Closure Head Examination Procedure: 54-ISI-850 Rev.6 Applicable SDCN(s): 30-9069955-000 & 30-9044520-000 Ultrasonic Instrument Transducer.

Manufacture: Staveley Manufacture: KBA Model: Benchmark!!892O0 Z-4.M Model: Sonic 136 Serial Number: G4R-OI - l j Frequency: 2.25 Serial Number. 136-861K Via

,4; /I'/*o T01t' Angle:26 0 Measured Angle: 26*

Linearity Sheet No.:

Mode: Shear Size: 0.5"XO.5" InstrumentSettings.

Skew Angle:+/- 90 Measured Skew Angle: +/-90" Range:* OSound Path ODepth

1. of Elements: 1 Shape: Rect.

Configuration:: Single.

Delay:0.342" Cable Type: RG-1 74 Length: 12' Intermediate Connectors: 0 Velocity: 127 verificationBlock Display: IP Type: Rompas S/N: 5100 o

Frequency: 2.25 Reflector 0.7 SDH 1" Radius Reject: Off Sweep:

0.8 1.6 Pulse Width: 222nS Amplitude:

50%

65%

Damping: 5000 Gain:

42.4 42.4 Mode: SPulse Echo E"Dual BasictCalibration Block.

0 Rep Rate: 2kHz Filter: 2 Block ID: BF-18 Material:Clad/ CS I

Pulser: E1 50V 0-300V (*Sonic 137 only)

Thickness: 6.0" with 0.125" Clad Diameter: Flat

• Probe voltage is adjustable with the Sonic 137 Instrument The Temperature: 72 °F Therm. SN: 531993 Oi IZ7A7/1Zvt Sonic 135 has a fixed pulser voltage.

Couplant: Ultra Gel II Batch Njf O532S*

Reference SensitivityInformation Reflector 3/4T Hole Sweep: 5.0 div.

Amplitude: 80 %FSH Gain: 62.2 dB Cal In: Date: 3/27/08 Time 0813 Check: Date:3/27/08 Time 0950 Check: Date N/A lime N/A Out Date:3/27/08 Time 1005 Comments Used the longitudinal wave to hit the one inch radius, and the shear wave to hit the.7 side drilled hole. Reference EPRI Examination of Browns Ferry Closure Head Nozzle-to-Shell Welds Modeling # IR-2003-17.

I J

000235 Tennessee Valley Reactor Pressure Vessel Authority Manual Ultrasonic Calibration Data Sheet Utility: TVA Site: Browns Ferry Nuclear Plant I Unit: 3 Outage: Cycle 13 RFO ISO / Drawing Number: 3-1S,-0295-A-01 ISI Report Number:

906f Component ID: N6A-NV Component

Description:

Nozzle - Closure Head Examination Procedure: 54-ISI-850 Rev.6 Applicable SDCN(s): 30-9069955-000 & 30-9044520-000 Ultrasonic Instrument

.'Transducer..

Manufacture: Staveley Manufacture: KBA Model: Benchmark892-600 Model: Sonic 136 Serial Number: 0111 PK Frequency: 2.25 Serial Number: 136-861K 50da.4:

4,1

• S Angle:45 Measured Angle: 47*

Linearity Sheet No.:

Mode: Shear Size: 0.5"X1.0" Instrument Settings::,

Skew Angle: +/-25° to 800 Measured Skew Angle: N/A Range:" 0Sound Path QDepth

1. of Elements: I Shape: Rect.

Configuration:: Single CD Delay:0.609' Cable Type: RG-174 Length: 12' Intermediate Connectors: 0 Velocity: 126 Verification Block Display: IP Type: Rompas S/N: 5100 n

Frequency: 2.25 Reflector.

1" Radius 2" Radius Reject: Off Sweep:

1.0 2.0 Pulse Width: 222nS Amplitude:

70%

80%

Damping: 5000 Gain:

23.0 23.0 Mode: 0Pulse Echo l-Dual Basic Calibration Block' WI,

!) PRR: 2kHz Filter 2 Block ID: BF-18 Material:Clad/ CS Pulser: E1150V 0]300V (*Sonic 137ory)

Thickness: 6.0" with 0.125" Clad Diameter: Flat S

Temperature: 72 "F Therm. SN: 531993 pp az/,//'/c*'

• Probe voltage is adjustable whhl the Sonic 137 bnstnnent The Tmeaue 2O hr.S:519 Sonic 136 hasa fied pulser voltage.

Couplant: UltraGel II Batch No.:.96 01-7O62 Reference Sensitivity Information Reflector 3/4T Hole Sweep: 6.6 div.

Amplitude: 80%FSH Gain: 52.2 dB Cal In: Date: 3/27/08 Time 0810 Check: Date:3/27/08 Time 1005 Check: Date N/A Time N/A Out: Date:3/27/08 lime 1028 Comments Reference EPRI Examination of Browns Ferry Closure Head Nozzle-to-Shell Welds Modeling # IR-2003-17.

00023'6

[Tennessee Valley Reactor Pressure Vessel Authority Manual Ultrasonic Calibration Data Sheet Uffilty: TVA Site: Browns Ferry Nuclear Plant Unit: 3 Outage: Cycle 13 RFO ISO I Drawing Number 3-ISI-0295-A-01 ISI Report Number:

906f Component ID:

N6A-NV Component

Description:

Nozzle - Closure Head Examination Procedure: 54-1SI-850 Rev.6 Applicable SDCN(s): 30-9069955-000 & 30-9044520-000 Ultrasonic Instrument Transducer Manufacture: Staveley Manufacture: KBA Model: Benchmark892-600 Model: Sonic 136 Serial Number: 0OX08P Frequency: 2.25 Serial Number: 136-861 K Angle:55 Measured Angle: 55 Linearity Sheet No.:

Mode: Shear Size: 0.5"X1.0" Instrument Settings Skew Angle: +/-20° to 60' Measured Skew Angle: N/A Range:"

OlSound Path

-Depth

1. of Elements: I Shape: Rect.

Configuration:: Single z

Delay:0.790" Cable Type: RG-174 Length: 12' Intermediate Connectors: 0 Velocity: 126 Verlfication Block Display: IP Type: Rompas IS/N: 5100 G

Frequency: 2.25 Reflector:

1" Radius 2" Radius Reject: Off Sweep:

1.0 2.0 Pulse Width: 222nS Amplitude:

70%

80%

Damping: 5000 Gain:

27.0 27.0 Mode: ZPulse Echo

[]Dual Basic Calibration Block WU o3 PRR: 2kHz Filter: 2 Block ID: BF-18 Material:CladI CS I.

Pulser: I]150V

[--300V (Soic 137 only)

Thickness: 6.0" with 0.125" Clad Diameter: Flat Probe voltage is adjustable with the Sonic 137 Itent.

Temperature: 72 eF Term. SN: 531993 Sonic 136 has a fixed pulser voltage.

Couplant: UltraGel II Batch No.: 94

• 2&

Reference Sensitivity Information Reflector: 3/4T Hole Sweep: 7.6 div.

Amplitude: 80 %FSH j Gain: 56.8 dB Cal In: Date: 3/27/08 Time 0819 Check: Date:3/27/08 Time 1031 Check: Date N/A Time N/A Out Date:3127108 Time 1045 Comments Reference EPRI Examination of Browns Ferry Closure Head Nozzle-to-Shell Welds Modeling # IR-2003-17.

I

000237

[Tennessee Valley Reactor Pressure Vessel

] Authority Manual Ultrasonic Calibration Data Sheet Utility: TVA Site: Browns Ferry Nuclear Plant Unit: 3 Outage: Cycle 13 RFO ISO / Drawing Number 3-,S,-0295-A-01 I1I Report Number:

R 54 Component ID: N6A-NV Component

Description:

Nozzle-to-Closure Head Examination Procedure: N-UT-78 Revision 4 Applicable SDCN(s): N/A Ultrasonic Instrument Transducer Manufacture: GE Manufacture: RTD Model: TRL2-Aust Model: Sonic USN 80 Serial Number: 01-887 Frequency: 2 MHz Serial Number: E34054 d

AU: IaIt at Angle: 60° Measured Angle: 60° Linearity Sheet No.:

Mode: Refracted Longitudinal Size: 2(24x42)mm i nstrumentSettings....

Focus: FS-125mm Squint Angle: 30 Range:5.0" ZSound Path

[]Depth

1. of Elements: 2 Shape: Rect.

Configuration:: Dual - SBS 02 Probe Delay: 10.8012 uS Cable Type: RG-174 Length: 6' Intermediate Connectors: 0 Velocity: 0.2127 uS

!Veifidation Block Display Delay: 0.000 Type: CS Rompas S/N: 5100 Frequency: 2 - 25 MHz Reflector 1" Radius 2" Radius Reject. Off Sweep:

2.0 div.

4.0 div.

Energy:. High Amplitude:

25 %FSH 80 %FSH Damping: 1 KQ Gain:

52.0 dB1 52.0 dB Mode:

-]Pulse Echo NDual Basic calibration BIock.

! PRRIPRF: Autohigh Block ID: BF-19 Material: CS I.

Thickness: 4.2" Diameter: Flat Temperature: 72° F Therm. SN: 531993 ip p

17/7_,6 Couplant UltraGel II Batch No.: 961142.

D65Z5 f'I, Reference Sensitivity informat!on Reflector: 1/4T SDH Sweep: 4.2 div.

j Amplitude: 80% FSH j Gain: 79.5 dB Cal In: Date 3/27/08 Time 0807 Check: Date 3/27/08 Time 1442 Check: Date 3/27/08 Time 1543 Out: Date 3!27/08Time 1607 Comments:

Zone 1: Near Surface Examination. Reference EPRI Examination of Browns Ferry Closure Head Nozzle-to-Shell Welds Modeling

1. IR-2003-17.

I 11

000238 ITennessee Valley Reactor Pressure Vessel Authority Manual Ultrasonic Calibration Data Sheet dtility: TVA Site: Browns Ferry Nuclear Plant I Unit: 3 Outage: Cycle 13 RFO ISO / Drawing Number: 3-ISI-0295-A-01 ISI Report Number:

Component ID: N6A-NV Component

Description:

Nozzle-to-Closure Head Examination Procedure: N-UT-78 Revision 4 Applicable SDCN(s): NIA Ultrasonic.Instrument Transducerr Manufacture: GE Manufacture: RTD Model: TRL2-Aust Model: USN 60 Serial Number: 01-887 Frequency: 2 MHz Serial Number.4'54

• A.

• I t/)

/

Angle: 60° Measured Angle: 60° Linearity Sheet No.:

Mode: Refracted Longitudinal Size: 2(24x42)mm Instrument Settings Focus: FS-125mm Squint Angle: 3*

Range:12.0" ZSound Path

[lDepth

1. of Elements: 2 Shape: Rec.

Configuration:: Dual - SBS z

Probe Delay: 10.8012 uS Cable Type: RG-174 Length: 6' Intermediate Connectors: 0 Velocity: 0.2127 uS

..Verification Block Display Delay: 0.000 Type: CS Rompas S/N: 5100 Frequency: 2-25 MHz Reflector:

1" Radius 2' Radius Reject: Off Sweep:

0.8 div.

1.7 div.

Energy: High Amplitude:

25 %FSH 80 %FSH Damping: 1K1<

Gain:

52.0 dB 52.0 dB Mode: []Pulse Echo 0Dual Basic Calibration Block P3 PRRIPRF: Autohigh Block ID: BF-19 Material: CS

0.

Thickness: 4.0" Diameter. Flat Temperature: 720 F Therm. SN: 531993 pD 12/17/utC' Couplant: UltraGel II Batch No.: 9642& 05 3 Z5 A*../

ReferenceSensitivity Information Reflector: ID Notch Sweep: 6.5 div.

Amplitude: 80% FSH Gain: 80.5 dB Cal In: Date 3/27/08 Time 0810 Check: Date 3/27/08 Time 1410 N/A Out: Date 3/27/08Time 1605 Comments Zone 2: Full Volume Examination. Reference EPRI Examination of Browns Ferry Closure Head Nozzle-to-Shell Welds Modeling

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