ML20093E407

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Rev 0 to Calculation MD-Q3001-940005, Vessel Weld Flaw Evaluation for Browns Ferry Nuclear Plant Unit 3
ML20093E407
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 02/07/1994
From: Winters E
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20093E387 List:
References
MD-Q3001-940005, MD-Q3001-940005-R, MD-Q3001-940005-R00, NUDOCS 9510160196
Download: ML20093E407 (39)


Text

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ENCLOSURE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)

UNIT 3 i SUPPLENENTAL INFORMATION FOR i

REACTOR PRESSURE VESSEL (RPV)

SHELL WELDS AUGMENTED EXAMINATION AND INSERVICE INSPECTION (ISI) RELIEF REQUEST 3-ISI-2.7 4

i TVA CALCULATION MD-Q3001-940005 VESSEL WELD FLAW EVALUATION FOR BROWNS FERRY NUCLEAR PLANT UNIT 3 i

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TVA 10697 (DNE-0A-6-86)

QA Record DNE CALCULATIONS Pace i lVitle l Pl ant / Uni t l l UESSEL WELD FLAW EVALUATION FOR BROWNS FERRY NUCLEAR PLANT (BFN) UNIT 3 l BFN/ UNIT 3 l l t I l Preparing Organization l KEY NOUNS (Consult RIMS Descriptors List) l lNEMECM/NUC 1 Reactor Vessel . Weldina l l Branch / Project Identifiers lEach time these calculations are issued, preparers must ensure that the l l l original (RO) RIMS accession number is filled in. l lMD-Q3001-940005 lRev (for RIMS' use) RIMS ACCESSION NUMBER l l l RO ! lR14 '94 020 8 10 5 l l Applicable Design Document (s) l l l l l lR l l l lASMECodeSectionXI l l l l l _., IR l l l l$ARSection(s) l UNIO System (s) l l l l l l 001 lR l l l l Revision 0 i R1 l R2 l R3 I Safetv-rel a t ed? Yes (X) No ( ) l lECNNo.(or Indicate Not Applicable)l l l l$tatement of Problem l l N/A l l I l l lPreparod .

l l l l Evaluate Reactor Pressure Vessel weld flaws l l ./ x C i l l l as identified in GE Nuclear Nonconformance l Ch g l l Report NCR No. 1C7LA-05 for BFN Unit 3.

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l l l$ PACE lby this revision  ! l l l l l REQUIRED l List all pages changed l l l l ORIGINAL i j lbv this revision  ! I l l l lABSVRACV (These calculations contain an unverified assumption (s) that must be verified later. Yes ( ) No(X)]l l Calculation contains special requirements or limiting condition? Yes ( ) No (X) l l l l l l A structural flaw evaluation was performed in accordance with ASME Code Section XI IWB-3600 (1986 edition) on BFN l l Unit 3 RPV weld flaws identified in GE NCR No. IC7LA-05. All flaws were determined to meet the IWB-3600 acceptance l l criteria. Continued operation is justified up to 12 effective full power years. Re-inspection of weld flaws l l is required at next 10-year interval. l l l l l l l l 1 I I I I I I I I '

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l 1 l l ( ) Microfilm and store calculations in RIMS Service Center Microfilm and destroy. () l ,

lL Microfilm and return calculations to: Address: l l cc: E. R. Winters. E08 2A-BFN ElGNERE MES PMCESSM RIMS, ET SLP-K CALCLA.AT10N CON 1ROL EDB 1BWN PLDNE106/230/2

Fa ye li NEP 301 Attachment 6 Page 1 of 1 1

I CALCUIATION DESIGN VERIFICATION (INDEPENDENT REVIEW) FORM

/A D -9300 I- 9 40005 o Calculation No. Revision Method of design verification (independent review) used (check method used):

1. Design Review
2. Alternate Calculation
3. Qualification Test Commenta:

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CLASSIFICATION, CATECORIZATION AND MAINTENANCE M/NE-I-25.3.1  ;

0F DESIGN CALCULATIONS Attachment 1 l Page 1 of 2

, CALCULATION CLASSIFICATION & CATECORIZATION CALCULATION INFORMATION:

1 PLANT / UNIT GFN UN/T 3 IDENTIFIER M D- 6700/- M 6dCfREV. O {

RIMS NO. 8N#/#6o2Bf/B5 ISSUE DATE cP -/- 97 l

TITLE //es2,e f fl/eY kg u.s [ue.fva flos, for BM l

~uA.) / 7- 3 SYSTEM (S), COMPONENT, FEATURE OR SUBJECT OF CALCULATION SYSTEM / DESCRIPTION

( ) SAFETY SYSTEM SYSTEM NO. ,

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( ) SAFETY RELATED FEATURE

( ) NON-SAFETY SYSTEM SYSTEM NO.

( ) NON-SAFETY RELATED FEATURE

- ( ) PLANT ENVIRONMENT -

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( ) APPENDIX R

( ) CIVIL STRUCTURES

', ( ) INSTRUMENTATION l

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(X) OTilER CALCULATION CATECORY Ndd fC FINAL CLASSIFICATION -

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, CLASSIFICATION, CATECORIZATION AND MAINTENANCE M/NE-I-25.3.1 0F DESIGN CALCULATIONS Attachment 1 Page 2 of 2 CALCULATION CLASS!FICATION & CATECORIZATION IDENTIFIER: _fff d - 6.3 00 / - 9 f o c C r /f O PRELIMINARY CLASSIFICATION

(>O ESSENTIAL ( ) FILE ONLY,

( ) DESIRABLE ( ) SUPERSEDED CALCULATION CLASSIFICATION JUSTIFICATION:

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/?PV REVIEWER ( GREE WITil ( ) DISAGREE - COMMENTS CLASSIFICATION REQUIRED  !

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6 MD-Q3001-940005 RO Page 2 of 34-TABLE OF CONTENTS Title. Page Table of Contents 2 l

Purpose 3 References 3 Design Input Data 4

. Acceptance Criteria 12 Summary / Conclusion 15 j l

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Purpose A structural flaw examination was performed in accordance

-with ASME Code Section XI (1986) for all axial and circumferential welds in the BFN Unit 3 Reactor Pressure Vessel (RPV). A detected flaw is first evaluated in accordance with paragraph IWB-3500 of ASME Code Section XI.

If the flaw does not meet the requirements of IWB-3500, it is identified in a nonconformance report and evaluated per paragraph IWB-3600 for continued plant operation.

This calculation documents an evaluation of welds found in the BFN Unit 3 RPV examination not meeting the IWB-3500 requirements as identified in GE NCR No. 1C7LA-05 (Ref. 2).

Each weld flaw will be evaluated per paragraph IWB-3600 to justify continued operation up to 12 effective full power years (EFPY). Allowable flaw. curves developed as a function l of flaw depth (a or 2a) versus aspect ratio (a/1) will be used to determine the IWB-3600 acceptance. Flaw acceptance diagrams and developement methodology can be found in the GE .

Nuclear BFN Unit 3 Flow Evaluation Handbook (Ref. 1).  !

References j

1. Vessel Flaw Evaluation for BFN Unit-3, Calculation MD-Q3001-920553 RO
2. GE Nuclear Nonconformance Report on BFN Unit-3 RPV examination, NCR No: 1C7LA-05 Proj: CO387 i
3. BFNP Technical Specifications Unit 3, through Amendment 174, Section 3.6.A Bases
4. Reactor Thermal Cycles, GE drawing 729E762 RO Assumptions
1. GE Nuclear flaw acceptance diagrams have been adjusted to account for fatigue crack growth up to 12 EFPY at 10 cycles per year. (Ref. 1)

Documentaion of Assumptions

1. Initial vessel design was based on a fatigue crack growth analysis corresponding to 12 EFPY (Ref. 3) and

, 120 thermal startup cycles (Ref.4). The calculated j EFPY for BFN Unit 3, last run date of 5-09-85, is 4.75.

(per Reactor Engineering) i 1

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. Tcrm3 cnd Definiti:na for "GERIS 2000 Ex min:ti:n Summ:ry Sheet" Ind No.

Sequential number identification for the applicable indication Oriented Describes the orientation of the indication relative to the RPV (i.e. cire. is a indication oriented in the vessel circumferentialdirection)

Type.

Describes the type of indication (surface or subsurface) as determined by ASME Section XI, lWB-3500.

~ X Position .

The location of the flaw in the circumferential direction in inches from vessel O' azimuth.

Y Position The location of the indication relative to RPV 0"(inside surface of the RPV Bottem Head) in inches.

' Z Position ,

The location of the flaw relative to the RPV deposited clad surface.

"S" The separation distance from the upper flaw extremity to the clad / base material interface as defined by l ASME Section XI. '

T-Wall The total through wall dimension of the indication. This value is also the 2A dimension referenced by ASME Section XI and the Flaw Analysis Handbook.

Length This dimension represents the totaller.gth of the flaw.

T Meas Represents the actual wall thickness of the RPV in the area of the indication minus the deposited clad.

all The value of the required ASME Section XI, IWB-3500 calculation for flaw evaluation. This value is derived using the following formula [(T wall /2)/ Length)

% alt Calculated The value of the required ASME Section XI, IWB-3500 calculation for flaw evaluation. This value is derived using the following formula [(T wall /2)/T Meas)

% alt Allowed This value is the allowed alt percentage as identified in ASME Section XI, Table IWB-3510-1 " Allowable Planar Flaws". The value given is the linear interpolation of the percentage values for Table IWB-3510-1 as permissible and in accordance with IWA-3200.

NOTE: The final calculated values shown on the summary sheets have been rounded off in accordance with ASME Section XI, IWA-3200.

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Alt fL- IC~1 L A - of GERIS 2000 Examination GE Nuclear Energy i

Summary Sheet Project: TVA, Browns Ferry Nuclear Plant, Unit 3 System; Reactor Pressure Vessel W:IdID: V-4-8 ASME Code Category: B-A Cdibration Sheets: G-001 Supporting Data; Examinauon Data Sheets E-14-00 and E 14-01, Indication Data Sheets14-001 thru 14-005 and G-100 thru G-108, Indication Evaluation Sheets, Screen Prints, Exam Patch Location Map, Exam Coverage Plots and GERIS 2000 Setup Records.

Examination Summarv The ultrasonic examination of weld V-4-8 resulted in one (1) recorded indication that exceeds the allowable standards of IWB-3500 ASME Section XI,1986 Edition, No Addenda.

The ASME Section XI required examination volume was examined with the GERIS 2000 System from the RPV inside surface utilizing Procedure No. GE-UT 700, Rev. 2. This examination was limited due to the N11-A Nozzle at 40*. The total examination coverage was ca;culated to be 83%.

The u2RIS 2000 utilizes an array of search units arranged to effectively examine the weld and adjacent base matenal parallel and perpendicular to the weld axis in two directions. The transducer package consisted of 0* tongitudinal,45* and 60* shear wave, and 70*

refracted longitudinal (RL) wave search units.

The one indication evaluated as being reportable to IWB-3500, ASME Section XI,1986 Edition, No Addenda was mcorded and sized in i accordance with GE-UT 700, Rev. 2 and GE UT 701, Rev. 2. This indication was recorded dunng the examination of both welds V-4-8 as14-002 and C-3-4 as 12 015. The flaw dimensions were determined from weld C-3-4 Indication Data Sheet 12 015 with the results tIbulated below:

Ind. No. Onented Type X Pos Y Pos Z Pos "S* T wall Length T Meas all  % att  % att Calculated Allowed l,12-015 cire. subsurface 94.35' 525.43* 1.13* 0.94* .44* 1.75* 6.53' O.13 3.4 2.71 This indication was sized with the 70*RL utilizing the PATT technique. It wt 9 also recorded with the 45* and 60* shear waves.

, The GERIS 2000 also recorded an indication with the 0* weld metal scan dat was evaluated and found to be acceptable per the rzferencing Code section. Geometne indications from the stabilizer bracket at 45' were recorded with the O' weld metal,45* and 60*

shear wave scans.

No manual supplemental examination was performed from the RPV outside surface due to access restnctions.

Fabncation records and prev. ous examination results were reviewed prior to the completion of this examination summary.

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J GERIS Analyst:

{ GE Reviewer. pp LEVEL. I DATE. Icl -dI -M LEVEL: I DATE: /f 2 /

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& GE Nuclear Energy GERIS 2000 Examination l

( Summary Sheet Profeet: TVA, Browns Ferry Nuclear Plant. Unit 3 System: Reaetor Pressure Vessel WeldID: c63 AsafE Code Category: B-A Calibration Sheets: c-004 Supporting Data: Examination Data Sheets E 08-00 thru E 08-26, Indicauon Data Sheets08-001 thru 08-110.

Indication Evaluation Sheets. Screen Prints, Exam Patch Location Map, Exam Coverage Plots '

and GERIS 2000 Setup Records.

' l Examination Summary j

! The ultrasonic examination of wekt C 2 3 resulted in two (2) recorded indications that exceed the allowable standards of IWB-3500. ASME Section XI,1986 Edition, No Addenda.

j The ASME Section XI required examinabon volume was examined with the GERIS 2000 System from the RPV inside surface utilizing Procedure No. GE-UT-700. Rev. 2. This examination was limited due to the core spray downcomers and surveillance specirnen brackets.

The total examination coverage was calculated to be 80%

4 i The GERIS 2000 utilizes an array of search units arranged to effectively examine the weld and adjacent base material parallel and

perpendicular to the weld axis in two directions. The transducer package consisted of 0* longitudinal,45' and 60* shear wave, and 70*

refracted longitudinal (RL) wave search units.

The two (2) unacceptable indications were recorded and sized in accordance with GE UT-700. Rev. 2 and GE UT-701, Rev. 2 with the l

g results tabulated below-Ind No. Onented Type X Pos Y Pos Z Pos "S" T wall Length T Meas all  % att  % att Calculated Allowed 2, 08426 cire, subsurface 198.50" 392.42" 1.77" 1.56' .41* 1.50" 6.60" .137 3.11 2.79

,08-067 circ. subsurface 558.25" 392.85" 1.65" 1.47" .37* 1.50" 6.55" .123 2.82 2.68 s,

Indication 08-026 was sized with 60* shear wave channel 11 utilizing the PATT technique. This indication was also recorded with 70*RL j

channel 3 as08-023 and seen with 45' shear wave channel 7.

Indication 08-067 was sized with 70*RL channel 3 utilizing the PATT technque. This indication was also recorded with 45' shear wave channel 7 as08-073 and seen with 60* shear wave channel 11.

The GERIS 2000 also recorded indications with the 0* weld metal scans, 70*RL,45' and 60* shear wave scans that were evaluated and found to be acceptable per the referencing Code section.

No manual supplemental examination was performed from the RPV outside surface due to access restnctions.

Fabncation recoras and previous examination results were reviewed pnor to the completion of this examination summary.

GERIS Analyst: g T) GE Reviewer. g [

LEVEL: k DATE: Ic')- N -93 LEVEL I DATE: /2 Z 4-7J UTILITY Review: ANil Review:

TITLE. DATE: TITLE: DATE:

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M e.ft- I c.w A o S GERiS 2000 Examination GE Nuclear Energy Summary Sheet l

l Pro /ect: TVA, Browns Ferry Nudear Plant. Unit 3 System: Reactor Pressure Vesse: f WeldID: C 3-4 ASME Code Category: B-A Calibrat/on Sheets: c 001, c-004, c.115, c 116, and c.117 Exammanon Data Sheets E 12-00 thru E-1215, Indication Data Sheets 12 001 thru 12163, Supporting Data; Indicadon Evaluabon Sheets Screen Pnnts, Exam Patch Location Map, Exam Coverage Plots , I GERIS 2000 Setup Records and Manual Data Sheets D-034,0 035, D-036, D-037, D-040, (

D-041,0-044and D-045.

Examination Summary The ultrasonic examination of weld C-3-4 resulted in six (6) recorded Indicadons that exceed the allowable standards of IWB-3500, ASME Secton XI,1986 Edition, No Addenda.

The ASME Secnon XI required exarmnation volume was exanuned with the GERIS 2000 System from the RPV inside surface utilizing Procedura No. GE4Jr 700, Rev. 2. TTus examination was limited due to the Guide Rods at 0* and 180**. The total exarnination coverage was calculated to be 97*'.. ,

The GERIS 2000 utilizes an array of search uruts arranged to effectvely examine the weld and adjacent base matettal parallel and perpendcular to the weld axis in twe #rections The transducer package consisted of 0* *.ongrtudinal,45' and 60* shear wave, and 70* refracted longitudinal (RL) wave search unit!

The sx (6) unacceptat 'e indications were recorded and sized in accordance with GE UT-700, Rev. 2 and GE-tTT 701, Rev. 2 uth the resutts tabulated below: l

  • T was Length T Meas a3  % ad M Ind. No. Oriented Type X Pos Y Pos Z Pos *S*

q Calculated Allowed

.444* 6.53' O.13 3.4 2.71 l,12-015 cire, subsurface 94.35' 525.43* 1.16 75* l 1.75*

424.65* 524.58* 2.30* .34* 1.75* 6.51* o.10 2.66 2.48 4 12 060 cire. subsurface 1.94* l 617.15' 526.14* 3.85* 2.6 .62* .75* 6.49' 021 4.81 3.50 (

,I"12-116 cire. subsurface 760.10* 525.11' .78* .75* .325* 2.00* 6.44* 0.10 2.45 2.39 12 144 cire. subsurface 4 .39' 2.40' 6.44' O.10 3.03 2.39 12 145 subsurface 763.85* 525.68* .80* 2.40* l

  • ). ctx.

771.35* 525.07* .87* .43* .511* 2.75* 6.44' O.10 3.97 2.46

,12-148 circ. subsurface Indicadon 12-015 was szed with 70* RL channel 5 utilizing the PATT techruque. This indicadon was also recorded as 12 016 and 12-020.

Indication 12-015 was also recorded within the exam volume of weld V-4-8.

Indication 12 069 was mzed with 45' shear wave channel 9 ublizing the SPOT techruque.

Indication 12-116 and 12117 is a combined indication in accordance with RWA-3390 and is included in the table above as 12116. Indication 12116 and 12117 were sized with 45' shear wave channel 7 utilzing the SPOT techruque.

Indicanon 12144 was mzed with 70* RL channel 5 utilizing the PATT techruque. This indication was also recorded as 12130,12150, and 12 157, GERIS Analyst GE Reviewer: .jg hbd LEVFL: DATE: /2/ / 3 LEVEL: ~[b DATE: IMI@

UTILITY Review: ANil Review-TITLF- OATE: TtTI c- OATF-Page 1 of 2

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' dest-lent A=Of GERIS 2000 Examination Summary (Continuation) indicadon 12145 was sized with 70* RL channel 4 utilizing the PATT tectnque. This indication was also recorded as 12 131,12 158,12-161,12-162 and 12163.

Indication 12148 was sized with 70* RL channel 5 utilizing the PATT technique. This indication was also recorded as 12132 and 12160.

The GERIS 2000 also recorded Indications with the 0* weld metal scans,70* RL,45' and 60* shear wave scans that were evaluated and found to be acceptable per tie referencing Code secton. Geometnc indcations from the 00 surface, Nozzles N11-A, N11-8 and N4-F were recorded with the 45' and 60* shear wave scans.

Selected areas were rescanned using 45' RL search units .

The manual technique utilized 0* longitudinal,45' and 60* sheer wave search ursts both parallel and perpendcular e the weid aMs in two drections to effecovely exarrune lhe weld and acqacent base rnatorial.

No indications were recorded with the manual techneque Fabrication records and previous examination results were reviewed pnor to the completion of this exarninadon summary.

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& GE Nuclear Energy GERiS 2000 Examination Summary Sheet Project: TVA, Browns Ferry Nuclear Plant, Unit 3 System; Reactor Pressure Vessel ASME Code Category: B-A WeldID: C-4-5 Calibration Sheets: c-001, c-004 Examination Data Sheets E-16-00 thru E 1612, indication Data Sheets16-001 thru 16-094, Support /ng Data Indication Evaluation Sheets. Screen Prints, Exam Patch Location Map. Exam Coverage Plots and GERIS 2000 Setup Records.

Examination Summary The ultrasonic examination of weld C-4-5 resulted in two (2) recorded indications that exceed the allowable standards of IWB-3500, ASME Section XI,1986 Edition, No Addenda.

The ASME Section XI required examination volume was examined with the GERIS 2000 System from the RPV inside surface utilizing Procedure No. GE UT-700, Rev. 2. This examination was limited due to the Guide Rods at 0* and 180** The total examination coverage was calculated to be 93%.

The GERIS 2000 utilizes an array of search units arranged to effectively examine the weld and adjacent base material parallel and perpendicular to the weld axis in two direcuons. The transducer package consisted of 0* longitudinal,45' and 60* shear wave, and 70*

refracted longitudinal (RL) wave search units.

The two (2) unacceptable indications were recorded and sized in accordance with GE-UT 700, Rev. 2 and GE-UT-701, Rev. 2 with the results tabulated below:

Z Pos "S* T wall Length T Meas all  % a/t  % alt Ind. No. Onented Type X Pos Y Pos Calculated Allowed 3.17* 2.83* .30" 2.75" 6.6* .055 2.27 2.23 1,16-075 cire. subsurface 603.30" 574.70" cire, 574.05* 3.85* 2.53' 44* 1.50* 6.6" .147 3.33 2.87 16 076 subsurface 617.50" g

Indication 16-075 was sized with 60* shear wave channel 13 utilizing the SPOT technique. This indication was also recorded with 45' shear wave channel 9 as16-072.

Indication 164)76 was sized with 60* shear wave channel 13 utiLzing the SPOT technique. This indication was also recorded with 45*

shear wave channel 9 as16-074.

The GERIS 2000 also recorded indications with the 0* weld metal scans,70* RL,45' and 60* shear wave scans that were evaluated and found to be acceptable per the referencing Code section. Geometric indications from the stabilizer brackets were recorded with the 0*

weld metal,45' and 60* shear wave scans. Geometnc indications from the CD surface were recorded with the 45'shttar wave scans.

No manual supplemental examination was performed from the RPV outside surfree due to access restnctions.

Fabncation records and previous examination results were reviewed prior to the completion of this examination summary.

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TITLE. DATE: TITLE: DATE:

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MD- G 300I- 94000S" fo 1 /99 /O-N C. A - IC T A - OS GERIS 2000 Examination

@l' GE Nuclear Energy Summary Sheet Project: TVA, Browns Ferry Nuclear Plant. Unit 3 l System: Reactor Pressure Vessel j WeldID: C 5-FLG AshfE Code Category: B-A Calibration Sheets; c401, c.104, c-107, c-108 and c 109 Examinahon Data Sheets E 20-00 and E 20-12, IndicaDon Data Sheets20-001 thru 20-110, G-115 and G-116, I

Supporting Data Indication Evaluauon Sheets, Screen Prints Exam Patch Location Map, Exam Coverage Plots GERIS 2000 Setup Records and Manual Examination Data Sheets D-001,0-002, D-007,D-008, D-009 and D-010.

Examination Summary The ultrasonic examination of weld C-5-FLG resulted in five (5) recorded indications that exceed the aHowable standards of IWB-3500 ASME Section XI,1986 Edition, No Addenda.

The ASME Section XI required examinanon volume was examined with the GERIS 2000 System from the RPVinside surface utilizing r

Procedure No. GE-UT-700 Rev. 2. This examination was limited due to a clad patch at 30*, the Guide Rods at 0* and 180* and four (4)

Main Steam plug lines at 74*,110*,250*, and 286*. Areas that could not be examined using the GERIS 2000 and accessible from the 4 outside were examined with the manual technique utilizing Procedure No. GE-UT-300 Rev. 6, FRR-004. The total examination coverage was calculated to be 82%. - -**

The GERIS 2000 utilizes an array of search units arranged to effectively examine the weld and adjacent base material parallel and perpendicular to the weld axis in two directions. The transducer package consisted of 0* tongitudinal,45' and 60* shear wave, and 70*

refracted longitudinal (RL) wave search units.

The five (5) unacceptable indications were recorded and sized in accordance with GE-UT 700, Rev. 2 and GE-UT 701, Rev. 2 with the results tabulated below-Type X Pos Y Pos Z Pos "S" T wall Length T Mess all  % a/t  % att Ind. No. Onented Calculated A!! owed subsurface 83.90* 706.42" 1.01" .82" .40* 3.25" 6.54" .061 3.05 2.27 y,20-007 carc.20-008 ore. subsurface 88.40" 706.44" 1.02" .83* .39* 1.50" 6.55' .130 2.98 2.74 g

20-009 subsurface 95.90* 706.44" 1.03" .84* .38" 2.25' 6.59" .085 2.91 2.41

, p cire, h 2.58 20-011 cire. subsurface 100.90* 706.37" 1.23" 1.04" .39" 1.75* 6.62* .111 2.92 yp,

.48" 1.50" 6.87* .159 3.47 2.97 lf,20-012 cire. subsurface 116.90* 706.40* 1.14" .95*

Indication 20 007 was sized with the 70*RL channel 3 utilizing the PATT techrnque. This indication was also recorded with 70*RL channel 5 as20-016.

l Indication 20-008 was sized with the 70*RL channel 3 utilizing the PATT technique. This indicatio.1 was also recorded with 45* shear  !

wave channel 7 as20-022.

Indication 20 009 was sized with the 70*RL channel 3 utilizing the PATT technique. This indication was also recorded with 70*RL channel 5 as20-017,45' shear wave channels 7 as20-023 and 9 as20-027.

Indication 20-011 was sized with the 70*RL channel 3 utilizing the PATT technique. This indication was also recorded with 70*RL channel 5 as20-018 GERIS Analyst: GE Reviewer f h { l LEVEL: DATE. 19 N LEVEL: DATE: /2. Z/ 3 i

UTILITY Review: ANil Revw. l TITLE: DATE: TITLE: DATE:

Page 1 of 2

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? /?ID- Q 3co t ~ 99 ccos Ro ,

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GERIS 2000 Examination Summary (Continuation)

Indication 20-012 was sized with the 70*RL channel 3 utilizing the PATT technique. This indication was also recorded with 45* shear wave channel 7 as20-024.

4 The GERIS 2000 also recorded indications with the 0* weld metal scans, 70*RL,45' and 60* shear wave scans that were evaluated and  !

found to be acceptable per the referencing Code section. Geometnc indications from the flange radius were recorded with tne 45* and 60*

shear wave scans, j

The manual technique utilized O' longrtudinal,45' and 60* shear wave search unrts both parattei and perpendicular to the weld axis in two J directions to effectively examsne the weld and adjacent base materials, 1

No indications wet 4 recorded with the manual technique.

l 1 Fabrication records and previous examination results were reviewed prior to the completion of this examination summary.

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Page 2 of 2

. __ .e. .. _. ..-

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kc.c e nt/9 NCG~ (R r T GR 1 r1 GENE-523-120-0992 01 THW2 Top Head ' T MK-202

/

f I

K- THWL we[4s Head Flange iHFWI '

MK-209


l-- Head Flange Weld Vessel Flange VFW h Vessel Flange Weld j

MK-48 i

............ .T- *g-Course #5 II Flaws within 10" of MK-60 el VFw are limited

>; by VFW analysis, y I H45 J-T--

Course #4 ,

>g MK-16 H34 l

--'-'T------- Non-beltline Welds i

1 Course #3 3g MK-59 >g i

I H23

.___A____7_ _

. ca .i .

Course #2 , ;jyg . .

MK-58

.Ic
  • th
  • Beltline XE Region

-:H12 >' Welds 71_/,1;-

T -

Course #1 -l MK-57 > l I

BHW1 1

' 1 ~

d Bottom Head MK-2 Welds

.g _ _ .L _ _ -.

Bottom Head

' d- BHW2 MK-1 y 4

l NOTE: Not to scale. l 1

FIGURE I l l

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Browns Ferry III weld regions selected for flaw evaluation. l l

2

C Flaw Acceptance Criteria BFN III VESSEL FLANGE WELD VFW 2.5 . ,

Subsurf' ace Flaw Evaluation  :

7 1/3 Limij g.o

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s:

.= = = = = = = - -

========:=---------...I.......... .

O  !  !

e i i N Ciret mferential j 0 1*5 -------------------------- ------------------- -------- ------------ - - - - --- ------ 5--- -- --- - - --

g grg g ,

IWB-3600 Evaluation Q IWB-3p00 Evaluation i

ts. ,

. 1.0 - - - - - - - - - - - - - - - - - - - - - - - -------------------------- -------------------------- ----------------- ------ -'-- ------------------ -- -(

w e .a ,.,.-

e '. -

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O e e e 2o-- 008 ~~ .- O 2o- oo9 -- s b

. %b

- o 0 0 o.'o s- 0.1 0.2 0.3 0.4 0.5 h ~N 0 Flaw Aspect Ratio (a/L) $

% i w A

. . ,o FIGURE 3-10. Allowable subsurface flaw sizes for vessel flange weld. C o G e+

O e T D e

" ba o

+ 9 m

O

1

(

Flaw Acceptance Criteria .

BFN III NON-BELTLINE WELDS H23, H34, H45 2.5 . . .

Subsurf'pce Flaw Evaluation i i  :

I  !

1/3 1.imit  !

I 2.0 - - - - - - ------ -- - - - - - - - - - ---- - - - - ---- - -----

-l-- -- - --- - --- ------ ; ---- - - --- -- ---- - -

a

= l  !

$ NOTE: IWB- 3600 evalution for axial and circumfqrential  !

g flaws bounded by 1/3 l imit. l j a 1.5 ----------- --------- ------ - ----- --- -

--- - ----- -------- ;- l- - - ------:- - -- - - - - -

c. -

I o .

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k .

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~.

ta .

, 1.0 ---------------- ---- ----------- ---- ----- - ------------ --- -~~~ ~ - - - --- - - ---- - + - - - - ----- --- -- - " ,,

..,.s...

w w 3e f

  • o IWB-2 500 Evaluation

~ O 12-ItG ".

--"l 4

0.5 --- - -- - - -----------12-1489- 12-085 --g e oe g------0 76 -- ";.:. w "--

- o:L. . -

0.25 - IG- 075 ~2-1++ O_/ 2-0 0o .9

- 08-og7 s 2-I95 y O

o.

0.0  ;

0 o, oS 0.1 0. t5 0.2 Flaw Aspect Ratio (a/L) 0.3 0.4 0.5 l 0,

g u

-U FIGURE 3-14. Allowable subsurface flaw sizes for non-beltline horizontal welds. b d -@

? (t 3 8

~ 9

" ++

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MD-Q3001-940005 R0 Page /r of 34 Summary An analysis was performed in accordance with ASME Code Section XI IWB-3600 for all axial and circumferential weld flaws identified in GE NCR No;.1C7LA-05. Fifteen (15) subsurface weld flaws were found during the BFN Unit 3 RPV examination that did not meet IWB-3500 acceptance criteria.

Flaw depth (Twall or 2a) versus aspect ratio (a/1) was plotted for each flaw on the Ge Nuclear flaw allowable diagrams. Each diagram consists of allowable flaw curves based on IWB-3500, IWB-3600 & 1/3 thru wall thickness limit for membrane stress for selected weld regions and flaw orientations. Each curve is reduced to account for fatigue crack growth and irradiation embrittlement for up to 12 EFPY.(See figures 3-10 & 3-14)

Conclusion The weld flaws identified during the Unit-3 RPV examination and documented in NCR No. 1C7LA-05 were evaluated and found to be acceptable per IWB-3600 criteria. The margin of safety, based of the maximum IWB-3600 allowable, is greater ,

than 5:1. Continued unit operation is justified up to 12 EFPY. Reinspection is required.at the regular 10 year l interval.

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A m eA ne d a.aboo,.,ucosa l

Q Nonconformance Report 7 4 cf3+

Project BFN UNIT 3 RPV EXAMINATION Project No. C0387 NCR No. 1C7LA-05 Reference Documents: WO# 9245636-01, ASME SECTION XI,1986 EDITION, NO ADDENDA Desenption of Nonconformance: ( State Cause ) NCR Code 045 Cause Code C04 ULTRASONIC EXAMINATION THE RPV, HAS REVEALED INDICATIONS EXCEEDING THE ALLOWABLE STANDARDS OF rWB-3510.1 OF THE REFERENCED ASME CODE. SEE ATTACHED

SUMMARY

SHEETS AND TVA INSPECTION REPORT (IR) initiated Dy: Date /7 - 2 8 'U OC Superviso * ~ 1M.3 10CFR21 Review: Is (X ) is Not ( ) Reportable Signature: 2 ate > t-F/-9 F

///

Proposed Disposition and Technical Justification: ( Attach Extra Sheets, Sketches, Etc. as Necessary )

Accept-As-Is ( ) Repair ( ) Rework () Reject ( ) Other if Not Mat. Or items ( )

TVA NUCLEAR ENGINEERING TO DISPOSITION PER TVA IR BF-T930110 Project Manager -

Date /2 28 U OC Supervisor 1' 4 /#- N W

/ ,9 1

Final Disposition l Accept-As-Is & Repair Dispositions, Design Verificaten is Provided Per i FINAL DISPOSITION SHALL BE EVALUATED AND INITIATED PER TVA IR BF-T930110

  • Client MM/ 6 Date IJ/"/YJ
  • ANil Review M MDate //-//-7.J Pr j ct M nager . Date / L
  • MW3 QC Supervisor wM /t 2 V f

~///

Preventative Action:

NONE REQUIRED OC Approval -' to # "##" U

/ 'f Disposition Completed And i Nonconformance Closed OC Supervisor Date

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ATIR No(s) UNSAT CONDlil0N CORRECTIVE ACTION RESP ENGR /DATE H&TE No. CAUSE C/A IIEM PROC No DESCRIPTION DESCRIPIION RESP FRMN/DAIE DUE DATE CODE S/U/C [QQ[ DC INSP/LVL/DATE G E-uT-lo o S*

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$E MANAGER OR DESIGNEE SIGNATURE / DATE WIE: ACCEPI-AS-IS/ REPAIR - ASME SECTION XI RELATED ACTIVITY.

MI! REVIEW / DATE REJECTED IR RECEIVED BY/DATE REVIEWED 8Y (QC SUPERVISOR)/DATE ADDED TO DATABASE _fDAIE1 RETCNTION PERIOD: LIFEllHE RESPONSIBILITY: RECORDS HANAGEMENT

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