ML14056A268

ASME,Section XI Code, Inservice Inspection Program for Unit I Second Ten-Year Inspection Interval, Unit 2 Fourth Ten-Year Inspection Interval, and Unit 3 Third Ten-Year Inspection Interval, Request for Relief ISI-44

ML14056A268
Person / Time
Site:	Browns Ferry
Issue date:	02/11/2014
From:	Polson K Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
IR-13-011
Download: ML14056A268 (116)

Text

Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 February 11, 2014 10 CFR 50.55a ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Units 1, 2, and 3 Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, and 50-296

Subject:

American Society of Mechanical Engineers,Section XI Code, Inservice Inspection Program for the Unit I Second Ten-Year Inspection Interval, Unit 2 Fourth Ten-Year Inspection Interval, and Unit 3 Third Ten-Year Inspection Interval, Request for Relief ISI-44

Reference:

1. Letter from NRC to TVA, "Browns Ferry Nuclear Plant - NRC Supplemental 95003 Inspection Report 05000259/2013011, 05000260/2013011, and 05000296/2013011," dated August 22, 2013

[ML13234A539]

In accordance with Title 10 of the U.S. Code of Federal Regulations (CFR) Part 50, Section 55a Specification (g)(5)(iii), the Tennessee Valley Authority (TVA) is requesting relief from the weld examination coverage criterion associated with American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, for 27 full penetration welds included in the intergranular stress corrosion cracking (IGSCC)

Augmented Inspection Program for the Browns Ferry Nuclear Plant (BFN). The reduction in obtained weld examination coverage is due to access limitations caused by design, geometry, or materials of construction of the components. Although these are non-Code examinations, WVA has determined a request for relief in accordance with 10 CFR 50.55a(g)(5)(iii) is the most appropriate method to resolve the issue raised during an NRC inspection, as discussed below. Therefore, relief is requested for the BFN Units 1, 2, and 3 Ten-Year Inspection Intervals, which began June 2, 2008, May 25, 2011, and November 19, 2005, respectively.

On August 22, 2013, the NRC issued an Inspection Report (Reference 1) that identified a non-cited violation (NCV) associated with the examination of one of the welds (i.e.,

DRHR-2-12) for which relief is being requested. The NCV was associated with TVA's failure to perform a 10 CFR 50.59 evaluation for a departure from the IGSCC inspection methodology on an ASME Code Class 1 piping weld. This weld, and the others

U.S. Nuclear Regulatory Commission Page 2 February 11, 2014 included in this request for relief, is inspected as part of the BFN Non-Code Augmented Inspection Program.

The ASME Section XI Code of record for the BFN Units 1, 2, and 3 for the current ten-year Inservice Inspection intervals are the 2001 Edition with the 2003 Addenda, the 2004 Edition, and the 2001 Edition with the 2003 Addenda, respectively, as amended by 10 CFR 50.55a(b)(2)(xv)(A)(2).

Specifically, this request for relief addresses 27 welds included in the BFN Augmented Inspection Program associated with Generic Letter 88-01, "NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping," and BWRVIP-75P-A, "BWR Vessel and Internals Project Technical Basis for Revisions to Generic Letter 88-01 Inspection Schedules." Ultrasonic examinations were performed on the accessible areas of these welds to the maximum extent practical given the design configuration or materials of the weld.

The enclosure to this letter contains the BFN Units 1, 2, and 3, Request for Relief ISI-44 for NRC review and approval. Table 1 of the enclosure contains specific information associated with each weld for which TVA is requesting exam coverage relief. Attachment A provided the associated Inservice Inspection Drawings and Attachment B provides excepts from the weld examination reports.

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

There are no new regulatory commitments contained in this letter. If you have any questions, please contact Mr. Jamie L. Paul at (256) 729-2636.

Respectfully, K. J. Poso Site Vice President

Enclosure:

Browns Ferry Nuclear Plant, Units 1, 2, and 3 American Society of Mechanical Engineers,Section XI Code Inservice Inspection Program, Request for Relief ISI-44 cc (w/Enclosure):

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

Enclosure Tennessee Valley Authority Browns Ferry Nuclear Plant Units 1, 2, and 3 Augmented Inservice Inspection Program Request for Relief ISI-44

Enclosure TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant, Units 1, 2, and 3 Request for Relief ISl-44 Executive Summary:

In accordance with 10 CFR 50.55a(g)(5)(iii), the Tennessee Valley Authority (TVA) is requesting relief from augmented weld examination coverage requirements for 27 full penetration austenitic stainless piping welds due to access limitations caused by design, geometry, or materials of construction of the components. Ultrasonic examinations (UT) were performed on the subject welds to the maximum extent practical due to the configuration and design using the latest ultrasonic techniques, procedures, equipment, and personnel qualified to the requirements of the Performance Demonstration Initiative (PDI) Program in accordance with 10 CFR 50.55a(g)(4) and 10 CFR 50.55a(g)(6)(ii)(C). Table 1 of this Enclosure describes the limitations preventing achieving acceptable coverage for the weld examinations. Relief is requested for the Browns Ferry Nuclear Plant (BFN) Units 1, 2, and 3, Ten-Year Inspection Interval, as listed below.

Unit:

Browns Ferry Nuclear Plant, Units 1, 2, and 3 Systems:

Residual Heat Removal (RHR) System Control Rod Drive (CRD) System Reactor Water Recirculation (RECIRC) System Reactor Water Cleanup (RWCU) System Components Affected: 27 Full Penetration Piping Welds (10)

RHR System full penetration piping welds, (6)

CRD System full penetration piping welds, (5)

RECIRC System full penetration piping welds, and (6)

RWCU System full penetration piping welds, IGSCC Category:

IGSCC Category for each weld is listed in Table 1 E-1

Enclosure TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant, Units 1, 2, and 3 Request for Relief ISI-44 Section XI Edition:

Unit 1 2001 Edition with the 2003 Addenda Unit 2 2004 Edition Unit 3 2001 Edition with the 2003 Addenda Code Requirement:

Code Case N-460 Code Requirements from Which Relief Is Requested:

Code Case N-460 When the entire examination volume or area cannot be examined due to interference by another component or part geometry, a reduction in examination coverage may be accepted provided the reduction in coverage for that weld is less than 10%.

List of Components Associated with this Request for Relief:

See Table 1 Welds RCRD-2-49 and RCRD-2-50 have been removed under Design Change Notice (DCN) 71086A. Although these welds have been removed, TVA is requesting relief for these weld inspections that were performed prior to their removal.

Reason for Request

The design configurations of the listed welds preclude a UT examination of essentially 100 percent of the required volume. It is not possible to perform the volumetric UT from both sides of each weld due to the configuration of these components.

10 CFR 50.55a(b)(2)(xv)(A)(2) states, "Where examination from both sides is not possible on austenitic welds or dissimilar metal welds, full coverage credit from a single side may be claimed only after completing a successful single-sided Appendix VIII demonstration using flaws on the opposite side of the weld." The component design configuration limits UT examination coverage of the welds to the percentages shown in Table 1 based on limitations discussed in Table 1. Only the stated coverage ranging from 12% to 88% can be claimed for these welds.

Proposed Alternative and Basis for Use:

No alternative method of examination is proposed. In lieu of the ASME Section XI Code required essentially 100 percent volumetric ultrasonic examination, TVA proposes credit for ultrasonic examination of accessible areas to the maximum extent practical for the component design configuration of the piping welds.

E-2

Enclosure TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant, Units 1, 2, and 3 Request for Relief ISI-44 Justification for Granting Relief:

The welds were 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, 2003 Addenda (Units 1 and 3), and the 2004 Edition (Unit 2), as amended by 10 CFR 50.55a(b)(2)(xv)(A) and 10 CFR 50.55a(b)(2)(xxiv), of ASME Section XI, Division 1, Appendix VIII as mandated by 10 CFR50.55a(g)(4).

These examinations were of the accessible areas to the maximum extent practical due to the design configuration of the weld joints.

10 CFR 50.55a(b)(2)(xv)(A)(2) states, 'Where examination from both sides is not possible on austenitic welds or dissimilar metal welds, full coverage credit from a single side may be claimed only after completing a successful single-sided Appendix VIII demonstration using flaws on the opposite side of the weld." The "Comments" column of Table 1 describes coverage limitations due to the inability to examine welds from both sides, when applicable.

Credit for the one-sided only ultrasonic examination provides coverage ranging from 12% to 88%. These welds are part of a larger population of welds examined in which examination coverage is not reduced for which the required coverage is attained. When considered in aggregate with the entire sample population, an adequate level of inspection occurs to provide reasonable assurance that a pattern of IGSCC degradation that, if present, could affect the overall integrity of the components would be detected.

These examinations provide an acceptable level of quality and safety, to the extent practical.

Therefore, pursuant to 10 CFR 50.55a(g)(5)(iii), TVA requests that relief be granted for the BFN Units 1, 2, and 3 for the second, fourth, and third Ten-Year ISI inspection intervals, respectively.

Implementation Schedule:

This request for relief is applicable to the following Ten-Year ISI inspection intervals for BFN:

Unit 1, Second Ten-Year Interval which began on June 2, 2008, and will end on June 1, 2017; Unit 2, Fourth Ten-Year Interval which began on May 25, 2011, and will end on May 24, 2021, and;

" Unit 3, Third Ten-Year Interval which began on November 19, 2005, and will end on November 18, 2015.

The welds described above are listed in Table I of this enclosure. The welds associated with Unit 1 were examined during the first period (Cycle 7 - Fall 2008), the second period E-3

Enclosure TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant, Units 1, 2, and 3 Request for Relief ISI-44 (Cycle 8 - Fall 2010), and the third period (Cycle 9 - Fall 2012) of the second Ten-Year inspection interval. The welds associated with Unit 2 were examined during the first period (Cycle 17 - Spring 2013) of the fourth Ten-Year inspection interval. The welds associated with Unit 3 were examined during the second period (Cycle 13 - Spring 2008), the third period (Cycle 14 - Spring 2010), and the fourth period (Cycle 15 - Spring 2012) of the third Ten-Year inspection interval.

Precedent:

This request for relief is similar to the following BFN requests for relief:

2-ISI-29, NRC approved by letter dated May 31, 2013 [ML13148A308]

" 3-1SI-25, NRC approved by letter dated January 20, 2012 [ML12003A081]

2-1S1-1 8R1, NRC approved by letter dated June 16, 2009 [ML091200040]

3-1SI-22, NRC approved by letter dated May 20, 2008 [ML080080524]

2-ISI-18, NRC approved by letter dated April 12, 2004 [ML041040375]

2-1S1-15, NRC approved by letter dated April 3, 2003 [ML030970815]

Attachments:

Attachment A - Inservice Inspection Drawings:

1-CHM-1081-C-1 1-CHM-1081-C-2 1-CHM-1088-C-1 1-CHM-1098-C-1 1-CHM-1098-C-2 1-ISI-0362-C-8 2-ISI-0221-C-1

" 2-ISI-0270-C-2

" 2-ISI-0272-C-1 3-ISI-0328-C-2 3-ISI-0330-C-1 3-ISI-0332-C-1 E-4

Enclosure TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant, Units 1, 2, and 3 Request for Relief ISI-44 Attachment B - Examination Reports:

6 a

0 0

0 0

0 S

0 0

0 0

0 0

R024 R078 R098 R237 R253 R254 R257 UT-1 0-024 UT-10-026 UT-10-028 UT-10-030 UT-12-027 UT-12-031 UT-12-039

" UT-1 2-054

" UT-12-055 UT-12-058 UT-12-060

" UT-I13-004

" UT-13-013

" UT-I13-024 UT-13-044

" UT-I13-072

" UT-13-076 UT-13-079 UT-13-080 UT-13-086 E-5

BFN Units 1, 2, and 3 Request for Relief ISI-44 Enclosure Attachment A Inservice Inspection Drawings 1-CHM-1081-C-1 1-CHM-1081-C-2 1 -CHM-1 088-C-1 I-CHM-1098-C-1 1-CHM-1098-C-2 1 -ISI-0362-C-8 2-ISI-0221-C-1 2-ISI-0270-C-2 2-ISI-0272-C-1 3-ISI-0328-C-2 3-ISI-0330-C-1 3-ISI-0332-C-1

BFN Units 1, 2, and 3 Request for Relief ISI-44 Enclosure Attachment B Weld Examination Reports R024 R078 R098 R237 R253 R254 R257 UT-1 0-024 UT-1 0-026 UT-1 0-028 UT-1 0-030 UT-12-027 UT-1 2-031 UT-1 2-039 UT-1 2-054 UT-1 2-055 UT-1 2-058 UT-12-060 UT-1 3-004 UT-1 3-013 UT-1 3-024 UT-1 3-044 UT-1 3-072 UT-1 3-076 UT-1 3-079 UT-1 3-080 UT-1 3-086

Enclosure Attachment B TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant, Units 1, 2, and 3 Request for Relief ISI-44 Weld Inspection Report Excerpts R024 (2 pages)

000064 TENNESSEE VALLEY EXAMINATION

SUMMARY

AUTHORITY AND REPORT NUMBER:

RESOLUTION DATA SHEET

• le e../

PROJECT: BFN UNIT: 3 CYCLE: 14 COMPONENT ID: DRHR-3-21 EXAMINATION METHOD SYSTEM: RHR ISi DWG. NO. 3-ISI-0330-C-0I MT []

PT El UT 0 VT LI CODE CLASS:

I CATEGORY: R-A PROCEDURE: N-UT-64 REV:II TC: N/A CONFIG.:

Elbow TO Valve EXAMINER: Tommy Brown EXAMINER: Kristen Davis EXAMINER: N/A EXAMINER: N/A LEVEL:.11 LEVEL: Trn LEVEL:

LEVEL:

I*u I

This report contains the data associated with the manual ultrasonic examination weld DR[-1R3-2 1.

The exam was performed to meet the requirements of NU0313, EXREQ B02-02 Category C and ASME Section XI 2001 Edition 2003 Addenda, Category R-A, Item R1. 16C.

This exam was performed using equipment, procedures and personnel qualified in accordance with ASME Section XI, Appendix VII1 as amended by I0CFR50.55a final rule.

This exam was performed using TVA Nuclear Procedure N-UT-64 Rev. I 1 which incorporates PDI-UT 2 Rev C Addenda No. 1, 2, and 3, for UT examination Austenitic Welds..

The component was a single sided stainless steel piping weld, 20 inch diameter schedule 80 1.03 1" nominal Elbow to Valve weld, which limited the upstream scan due to configuration.

A 450 Shear and a 600 RL was used for the axial scans and a 450 Shear for circ scans.

-5 55 Coverage Achieved.

/5 a

"ed v

/2 RESOLUTION BY: Tommy Brown LEVEL: III DATE: 03/04/2010 REVIEWED BY: Matt Welch LEVEL: III DATE:

ýle AN:

-D E:

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000068 rYA IaBcv.s4)1.Om3d

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Enclosure Attachment B TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant, Units 1, 2, and 3 Request for Relief ISI-44 Weld Inspection Report Excerpts R078 (2 pages)

000348 TENNESSEE VALLEY EXAMINATION

SUMMARY

AUTHORITY AND REPORT NUMBER:

RESOLUTION DATA SHEET

/977 PROJECT: BFN UNIT: 3 CYCLE: 13 COMPONENT ID: RWCU-3-001-071 EXAMINATION METHOD SYSTEM: PWcio ISI DWG. NO. 3-ISI-0328-C-01 MT

-T PT EU UT [

VT LI CODE CLASS:

1 CATEGORY: B-J PROCEDURE: N-UT-64 REV: 11 TC:NA COFIG.:

Valve TO Pipe EXAMINER:

EXAMINER:

EXAMINER:

EXAMINER:

75'AmeY w

)DAW oIP R

LEVEL:Z" LEVEL:

LEVEL:

The package contains the ultrasonic examination data for RWCU-3-001-071.

This exam meets the requirements of NU0313, cat. A, EXREQ 96E-02.

and ASME Section XI, cat.B-J, item B9.11, EXREQ P03-03.

The examination was performed using ASME Section XI, Appendix VII and Appendix VIII personnel, equipment and techniques as amended by the

,/

10CFR50.55a Final Rule The joint configuration is a cast SIS pipe to pipe full pen butt weld.

The examination was performed using TVA Procedure N-UT-64 which

/

implements PDI Procedure PDI-UT-2 for Austenitic pipe welds The weld was examined using 1.5 mHz., 45 and 60 degree shear waves and a 70 degree 2.25 mHz shear wave.

Accees for the exam was limited to a single side due to joint geometry.

./

The aclieved examination volume was,ý Y,

-I RESOLUTION BY:

REVIEWED BY:

AN][:

DATE:

466 LEVEL: -97 DATE: 4,1f LEVEL:-Z'1 DATE:

PG.

/

OF -7

()n n q 9; TVA WALL THICKNESS REPORT NO:

PROFILE SHEET

I PROJECT:

tv/w WELD NO:.wCCI

-.F-0/

- C-) 7t UNIT:

SYSTEM:

)fWC.v Record Thickness Measurements As Weld

• Weld Edge Indicated, Including Weld Width, Centerline Edge-To-Edge At O" 2.5""

• 2.5" Position o

90

• 90 9,o 270' 2

4

[]

• Side Side

-Flow CROWN HEIGHT:

D DIAMETER:

. 0 CROWN WIDTH:

WELD LENGTH: _

62 x. ivW)

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-.3 2(, it 9o2 0

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CAS*IX-/

eA E________________

X EVIEWED BY:____________

LEVEL:

ILEVEL: _

DATE:

DATE, DATE:

PAG TVA 19668 (\\'P-5-89) 1.1 0 -999.44

'I

Enclosure Attachment B TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant, Units 1, 2, and 3 Request for Relief ISI-44 Weld Inspection Report Excerpts R098 (5 pages)

000475 EXAMINATION

SUMMARY

TENNESSEE VALLEY AND REPORT NUMSERL AUTHORITY RESOLUTION SHEET ROTS PROJECT: BFN UNIT: 3 CYCLE: 13 COMPONENT MD: RWCU-3-001-07O EXAMINATION METHOD SYSTEM: RWCU["

ISI DWG. NO. 3-ISI-0332-C SHT I V MT

'P UT C VT [-

CODE CLASS: I ICATEGORY: B-PROCEDURE: N-UT-64 REV: I110 TC:N/A CONFIG.:

Sweep-O-let TO Valve t

ui Mahoney F.XAMINER:

Alex Zipperer EXAMNR:

EXAMINE/A I/N/A N/A LEVEL: [1 LEVEL:

LEVEL: N/A LEVEL:N/A This report contains the manual ultrasonic data associated with the exaination of Weld RWCU-3-001-070 /

The conment examined was a S/S Sweep-O-Let to Valve Weld, 6" Diameter, Schedule 80, with single sided access.

A 1.5Mhz. 450 Shear Wave, 600 Shear Wave, 1/2 Vee Path were used during the exam.

A 600 RL was used for the examination.

Maintained a 5%-20% ID Roll.

This examination satisfies the requirenrnts of ASME Section XI, Category B-J, Item number B9.11, EXREQ P03-03, and BWRVIP-75A, Cat A, EXREQ, B02-02.

This exam was performed with equipment, procedures, and personnel qualified In accordance with ASMEE Section Xl, Appendix VIII as amended by the final rule.

There were limitations on the exam. Refer to attached drawings for calculations.

,.o 3-ý5-7 o-70/7W-Z~

AVA)o#

- 7'140:5-,040 L/

LEVEL:II DATE:

'kIi ~/1V/

LEVEL:.22r DATE:40 0?

G.O V,

000477 REPORTNo TVA WALL THICKNESS Roo NO:

PROFILE SHEET PROJECT:

2F/ (

WELD NO:

ZLkWCU Q 3 C-I O7n UNIT:

"1 C-/r-LG )"1 SYSTEM:

PU)>C-u Record Thickness Measurements As Weld Weld Edge Indicated, Including Weld Width, Centerline Edge-To-Edge At 0' 1.,

2.5"

-1L 2.5" 01 Position 0*

90*180- 270-go

~Fli ow-C R O W N H EIG H T:

"t L) S

/ý D IA M E TER :

CROWN WIDTH:%

11(0 WELD LENGTH:_

p*t..

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s-EXAMINER

REVIEWED BY:

ANI LEVEL:

LEVEL:_

DATE:

4 GE-DATE:

PAGE __A-__

OF, TVA 19668 ('N-.5-89) 1-103-9"9.4

PROJECT: T* K SYSTEM:

R WA C U Unit: '2, CYcLLE )3 WELD NO.:

Awc-\\) 3 00 1 -090 II 1*

0 00 0

C:)

000480 TVA WALL THICKNESS REPORT NO:

PROFILE SHEET PROJECT:.i*F weLD No:.WCU O7LD UNIT: ~

C~yCL~ )3SYSTEM Z

c Record Thickness Meassurements An Weld

• Weld Edge Indicated, Including Weld Width, Conte1Ine Edge-To-Edge At 0*

1-2.5" 02 Position

0.

90. 18r 270.

1 2

3 4

Fi ED U3Elim CROWN HEIGHT:

VL-L

.U DIAMETER:

(,OX-s CROWN WIDTH:

/."Z WELD LENOTH -

Rnoap-em exAm \\10L.Ume% ely I;,,

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6 \\Iow.me fAieJ" 5

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0AMEA Am-f A(&AB8LX Q) &WE5 AWNK rlb"~i 4-05e..7 b Z6 jr a' -~ 016

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TVA 1966 0-.5-89)

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I-IN-999."

000481 TVA WALL THICKNESS REPORT NO:

PROFILE SHEET 10ol PROJECT:.k_

WELD NO: AW U 3 Q

UNIT:

Ft1-SYSTEM:

LL)CL)

Record Thickness Measurements As Weld

• Weld Edge Indicated, Including Weld Width, Centerline Edge-To-Edge At 00 14 2.5" 2.5" 9-Position 0

90* 180* 270*

2 3

4 1151 Flow CROWN HEIGHT:

05.

DIAMETER:

L2-CROWN WIDTH:

l0' 11 WELD LENGTH:

A I Yq *

ý 15VU Itx

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.tAl.15r'S M 'jowms:

110 a b ~

~

~

• A z.f$ - i 5z 7-Z 7='

g*-xv sý

~vJ~P CA5T 4515 Lg~f

0. MC~EA 1ýar Fý 0 VALUR" A PPI-Y 7b L.Dirmi

)k44jg7 VJOLPAV 68C, 0ca X-

.3;10 6rti.z)-ý7.-ozs. /m./~.:ISZ.3.2"

-1.

.387.&100 1' 7 TVA I1966-NP.-54)

S-1041-99t."4

Enclosure Attachment B TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant, Units 1, 2, and 3 Request for Relief ISI-44 Weld Inspection Report Excerpts R237 (2 pages)

C DC~5 TENNESSEE VALLEY EXAMINATION

SUMMARY

REPORT NUrVHBER:

AND AUTHORITY RESOLUTION SHEET

/Z

-7 PROJECT: BFN UNIT: i CYCLE 07 COMPONENT ID: DRHR-I-2 EXAMINATION METHOD SYSTEM: RI-IR ISI DWG NO: ISI-0362-C-08 MT D

PT ED UT

[

VT.]

CONFIGURATION:

CATEGORI PROCEDURE: N-UT-82 REV TC: 0A P TO VLV IF EXAMINER:

EXAMINER:

EXAMINER:

EXAMINER:

u'7J 6 LEVEL:

LEVEL:

LEVEL:

LEVEL:

Total coverag~e calculated to be approximately *-

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TVA PROJECT: I3-iJ SYSTEM:

RH 9, REPORT NO.:

Office of Nuclear Power Unit:

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-WELD NO.: DR,g 2

/1aZ37 57

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Vi LEVEL: 1 DATE:

I o'

PAGE ___

OF_

TVA 19669 (ONP-6-88)

/

Enclosure Attachment B TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant, Units 1, 2, and 3 Request for Relief ISI-44 Weld Inspection Report Excerpts R253 (2 pages)

000399 V

TENNESSEE VALLEY EXAMINATION

SUMMARY

AUTHORITY AND REPORT NUMBER:

RESOLUTION DATA SHEET Rt--

PROJECT: BFN UNIT: I CYCLE: 07 COMPONENT ID: RCRD-I-50 EXAMINATION METHOD SYSTEM: CRD ISI DWG. NO. I-CH-M-1098-C-2 MIT 0 PT El UT Z VT 0 CODECLASS:

N/A CATEGORY: NU0313 PROCEDURE: N-UT-82 REV: 3 TC: NIA CONFIG.:

Valve TO Elbow EXAMINER: Timmny arowa EXAMINER: NIA EXAMINER: N/A EXAMINER: N/A LEVEL: 711 LEVEL:

LEVEL:

LEVEL:

A Manual Ultrasonic Examination was performed on weld RCRD-l-50. A carbon steel elbow to a stainless steel valve.

Thle exam was performed to meet the requirements of NU03 13. category C EXREQ B02-02 This exam was performed using TVA Nuclear Procedure N-UT-82 Rev. 3, which incorporates PDI-LIT 10 Rev C Addenda No. 1. the EPRI Procedure for doing UT on Dissimilar Metal Welds.

A 601 Shear. 600 RL and 70°RL was used for the axial scans. A 420 RL and 450 Shear was used for the cire scans.

No scan on the Down Stream side of the weld due to Elbow to Valve configuration.

80.6% Procedure coverage was obtained.

RESOLUTION BY: Tommy Brnwn REVIEWED BY:

ANII:

DATE:

19 LEVEL: III DATE: 11/7/08 LEVEL: ZT DATE:

'/G.

OF/1 C

000406 Rvizort* Thz.unes-. MeasuremennLr As Indicat*a, Inc2udino Vietc Wi"ih'.,

Edpe--Tt-Edgr At O" Weld 1,enterline SWale Eaon.

post ion 0190 11ja,27 IVA 1 I 1

-70 I

q q

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Sr..

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Enclosure Attachment B TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant, Units 1, 2, and 3 Request for Relief ISI-44 Weld Inspection Report Excerpts R254 (2 pages)

000407 TENNESSEE VALLEY E-XAAMATION

SUMMARY

AUTHORITY AND REPORT NUMBER:

RESOLUTION DATA SHEET

)e75t PROJECT: BFN UNIT: I CYCLE: 07 COMPONENT ID: RCRD-I-52 EXAMINATION METHOD SYSTEM: CRD ISI DWG. NO. I-CHM-1098-C-2 MT 0 P 0 UTZ VT [E CODE CLASS: N/A CATEGORY: g-o 03.1 PROCEDURE: N-UT4-2 REV: 3 TC: N/A CONFIG.:

Pipe TO vali-EXAMINER:.Tmuy Bnrew EXAMINER: N/A EXAMINER: N/A EXAMINER: N/A LEVEL: MI LEVEL:

LEVEL LEVEL A Manual Ultrasonic Examination was performed on weld RCRD-1-52. A carbon steel pipe to a stainless steel Vllve The exam was performed to meet the requirements of NU0313, category C EXREQ B02-02 This exam was performed using TVA Nuclear Procedure N-UT-82 Rev. 3, which incorporates PDI-UT 10 Rev C Addenda No. 1, the EPRI Procedure for doing UT on Dissimilar Metal Welds.

A 60O RL, 70*RL, and a 600 Shear was used for the axial scans. A 42*RL and 450 Shear was used for the circ scans No scan on the Down Stream side of the weld due to Pipe to Valve configuration.

88% Procedure coverage was obtained.

RESOLUTION BY: Tommy Brown I

000417 TVA WALL THICKNESS REPORT No:

PROFILE SHEET PROJECT:

WELD NO:

,- CID S.

UNIT:

/

SYSTEM-:

Record Thickness Measurements As Weld

• Weld Edge Indicated, Including Weld Width, Centerline Edge-To-Edge At 0' 1-2.5"

-2 Position a

90, 1

270 0E

- I

,r "Flow CROWN HEIGHT:

61Y'DIAMETER:

CROWN WIDTH:

Y"/

WELD LENGTH:

/*

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5' c-s ss-* ~

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Y75 5J,-k*--<--

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DATE:

LEVE..*,,

DATE,

(

I PAGE Oý f.A.-

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Enclosure Attachment B TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant, Units 1, 2, and 3 Request for Relief ISI-44 Weld Inspection Report Excerpts R257 (2 pages)

000439 TENNESSEE VALLEY EXAMINATION

SUMMARY

AUTHORITY AND REPORT NUMBER:

RESOLUTION DATA SHEET f? Z '7 PROJECT: BFN UNIT: I CYCLE: 07 COMPONENT [D: RCRD-I-49 EXAMINATION METHOD SYSTEM: CRDI ISI DWG. NO. I-CHM-1098-C-2 MT 0 PT 0 UT 0 VT CODE CLASS: N/A CATEGORY: NU0313 PROCEDURE: N-UT-82 REV: 3 TC: N/A CONFIG.:

Valve TO Elbow EXAMINER. Tommy ams EXAMINER: N/A EXAM[NER:- N/A EXAMINER: N/A LEVEL2)

• VL--

LEVEJL-M LEVEL:

LEVEL' LEVEL.

A Manual Ultrasonic Examination was performed on weld RCRD-1-49. A stainless steel valve to a carbon steel elbow.

The exam was performed-to meet the requirements of NU0313, category C EXREQ B02-02 This exam was performed using TVA Nuclear Procedure N-UT-82 Rev. 3, which incorporates PDI-UT 10 Rev C Addenda No. 1, the EPRI Procedure for doing UT on Dissimilar Metal Welds.

A 450 RL, 60' RL, and 70°RL was used for the axial scans. A 420 R., 400 RL, and 450 Shear was used for the circ scans.

No scan on the Up Stream side of the weld from 3.5" to 12.5" due to Valve to Elbow configuration. Scans from 0" to 3.5" and from 12.5" were in weld repair area.

80.6% Procedure coverage was obtained.

C RESOLUTION BY: Tommy Brown REVIEWED BY:

ANU:

EL:A,7 /

AT:,/0 LEVEATE:

/FDATE:

.LEVEL: III DATE: 11/7/0 LEVEILdý-Z&ATE: /409.PG.

/

OF 7

000455 TVA WALL THICKNESS P,,oR NO:

PROFILE SHEET PROJECT:- _

__WELD NO:

,PCRD - I - i/t9 UNIT:

I SYSTEM:

C1 Record Thickness Measurements As Weld

• Weld Edge Indicated, Including Weld Width, Centerline Edg*-To-Edgo At 0" 2.5" 25 Position 0 '

0 90 1180' 270' 2

Ei i

EJ,3 Flow-CROWN HEIGHT:

DIAMETER:

CROWN WIDTH:.,

z6,,"

÷ 7WELD LENGTH:

/Io"

,go 95 6 V

V.

1

~LO'J REVIEWED" BY: -_ _

LEVEL_______

0 IDATE' E

I1PA01 II e~

IA PAGE I/

Or

Enclosure Attachment B TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant, Units 1, 2, and 3 Request for Relief ISI-44 Weld Inspection Report Excerpts UT-1 0-024 (2 pages)

000201 Ultrasonic Examination Site/Unit:

BFN

/

1 Procedun Summary No.:

03122-1SI-BFN1 Procedure Re%

Workscope:

ISI Work Order No Code:

Section XI 2001 Ed/2003 Add CatJiltem:

B-JIB9.1 Drawing No.:

1-CHM-1081.C-1

==

Description:==

I System ID:

068 - REACTOR WATER RECIRCULATING SYSTE Component ID: RWR-1-001-O03 Size/

Limitations:

Single Side Austanitic Exam N-UT-4 0

1-SI-4.6.G Location:

Outage No.:

U1 R08 Report No.:

UT-10-024 Page:

1 of 7

Drywell

• M M

N/A Thickness/Diameters 1.088" /28" Comments:

See attached supplemental sheets for examination data consisting of:

- Phased Array Calibration Data Sheet (Shear)

- Phased Array Calibration Data Sheet (Longitudinal)

- Piping Examination Data Sheet

- Coverage Plot

- Indication Plot

- Wall Thickness Profile Sheet Results:

Accept 0 Reject []

Percent Of Coverage Obtained > 90%:

Info n No Reviewed Previous Data:

yes

A Supplemehrdl Report Report No.:

UT-10-024 Page:

5 of 7

Summary No.: 03122-ISI-B0NI Examiner: Nissen, Jason P Examiner:

NIA Other: Clalrday, Joey, E.

Level:

ll-PDI Level:

N/A Level:

TRN Reviewer: Matt Welch, LIII Site Review: N/A A,

ANII Review. Sam Flood Date: _______

Date:

Date: /

U I

Comments: RWR-1-001-003 Coverage Pelt I

Sketch or Photo: O:\\Iddeal._Serve~lddeaLBFN*DocumentatlonýUt R8 Scanned Data\\RWR-1-001-003 Coverage Plot.jpg

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Supplemehital Report Report No.:

Page:

Summary No.: 03155-ISI-BFNI Examiner: Nissen, Jason P.

Examiner NIA 4ý Other: PARKER, FREDDIE, J.

Level:

II-PDI Level:

N/A Level:

TRN Reviewer. Matt Welch, UII Site Review: N/A ANII Review: 9,,'ratuo*

&m. o UT-10-026 5

of 7

Date:

Date:

Date: dze&

Comments: RWR-1-002-012 Coverage Plot Sketch or Photo: O:\\Iddeal..SereitlddeaLBFlt.Documentatlon\\UIR8 Scanned Data\\RWR-1-002-012 Coverage Plot.jpg l

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41. 7¶ 0a Supplemental Report

Enclosure Attachment B TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant, Units 1, 2, and 3 Request for Relief ISI-44 Weld Inspection Report Excerpts UT-10-028 (1 page)

Supplemenial Report Report No.:

Page:

Summary No.:

Examiner.

Examiner:

Other:

03252-ISI-BFNI Nissen, Jason P.

NIA Clalrday, Joey,,.

Level:

ll-PDI Level:

N/A Level:

TRN Reviewer: Matt Welch, LIIIl C

(."II, Site Review: N/A ANII Review. Garf

,/*-

4, 11n11-fl UT-10-028 5

of 6

Date:

Date: //_____

Date: z//g L

Comments: RWR-1-001-SO23A Coverage Plot Sketch or Photo: O:\\lddealServer*lddealBFl*Doeumentatlon\\UIR8 Scanned Data\\RWR-I-001-SO23A Coverage Ptot.Jpg Comments. RWR-1..001-S023A Coverage Plet Sketch or Photo: 0:\\IddeaL ServeeijddeaL 6FN\\Dooumentatiori\\U iR8 Scanned DatakRWR-1-001 -S023A Coverage Ptot.Jpg LK, pq,ýK-,PI-

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Enclosure Attachment B TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant, Units 1, 2, and 3 Request for Relief ISI-44 Weld Inspection Report Excerpts UT-10-030 (1 page)

I Supplemei~tdi Report Report No.:

Page:

Summary No.: 03110-ISI-BFNI Examiner:

egrJryW Examiner: NoA Other: Walker, Scott Level:

Il1(N)

Level:

NIA Level:

TRN Reviewer: MattWelch, J-I Site Review: WA ANII Review. Semrod 0

UT-10-030 3

of 4

Date:

Date:

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FIRVA Supplemelh,,, Report Report No.:

UT-12-027 Page:

3 of 4

Summary No.: 05109-ISI-BFN3 Sketch or Photo:

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COMPONENT ID: 4R-3 -(o I

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DIL)SH I DAMETER:

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Enclosure Attachment B TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant, Units 1, 2, and 3 Request for Relief ISI-44 Weld Inspection Report Excerpts UT-1 2-031 (1 page)

Supplemental Report Report No.:

UT-I2-031 Page:

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Summary No.: 05100-lSI-BFN3 Sketch or Photo:

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Supplemei.al Report Report No.:

UT-12-039 Page:

5 of A17 Summary No.: 015184SI-SFN3 Sketch or Photo:

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Enclosure Attachment B TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant, Units 1, 2, and 3 Request for Relief ISI-44 Weld Inspection Report Excerpts UT-1 2-054 (1 page)

I THICKNL AND CONTOUR Position 0

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1.17 1.,5'0 t,99.,39,

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Enclosure Attachment B TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant, Units 1, 2, and 3 Request for Relief ISI-44 Weld Inspection Report Excerpts UT-1 3-004 (1 page)

CO AGE PLOT Component ID:

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Reviewer:

ANII:

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Print name: DAi01f KIEhILTAAI Print name:

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000115 PR**EcT:

1FN I

UNIT:

2 1 CYCLE: 17I SYSTEM:

Rector Water Cleanup System lComponant: RCRD-2-49 Examiner.Reewr Print Name: David Klelr(

Print Name: Matt Welch Date:

29-Mar-13 Date:

3 t.zzf Items #

S RL Axial Full Required Exam Volume

]

15.125OL0180(Ca.6690OA91 112).

90 2

R. Axial Lower One Third Required Exam Volume 1S.125*L018B((0.223.O.163J/2)u 2.9717J Shear Axdal Full Required Exam Volume JS.nri*L0o8a. 0.69#0A91 2Z) 8.9304 Shear Axial Lower One Third Required Exam Volume zs.nr5Lii0

.1 i40.1ui 23CM 6L717-RL Full aoodwle and Cimnterocudse Scaming Required exam Volume J5.j*L0:B*(jA9#091)/)8.9304 J

Rh Lower One Thirdh Codmise and Counteradnom Scanning R en Volume Shear Full CVoimwise and Countedvfomitwise Scanning Required em Volume 15.120*/ol((0.669. A91).2).

8304 8 Shear Lower One Third Clockwise and Caunteraodiwts Scanning Required mmr Volume RL Axal Full Volume Obstructed Exam from the Elbow side

( W2 5S.US*0A91*

L3623 10 RIL.

Axial Full Volume Obstructed barn from the Valn sd ve d Rh1ir Axial Lwe One Third Volume Obstructed brnm or sn the Elbow side

-- LO8I/2 -S.135-0.163-OAS524 RSh Axial Lower One Third Volume Obstructed Exam ftr t tie Va lte side 127 (LU1/2J(2794V3*0M23=

L0106 Shear Axial Full Volume Obstructed Exam plus She ea that is not qualified by this procedure from the Elbow side 25.12S*ffogr.60712*&=

/2)m 2.2535 15 Sheer rFuVoum edEampluthe athatIs not qimifled by this procedure fom the Valve side Shear Axial Lower One Third Volume Obstructed Exam plus the ar of exam that Is not qualfed by this procedure IS from the Elbowslde 1S.123*I(a2ffi*.171)/2)/2) 0.1332 Shear Axial Lower One Third Volume Obstructed Exam plus the are of esum that Is not qualified by this proredure 16 from the Vahe side (1S.125r1(0.20"0.171)/2)/2))f1/r211L9M13)O.223) -

0.5485 17 RI. Full Clockwise and CounterClocrkwie Scanning Obstnucted exam Volume RI Lower One Third Volume Clockwise and -

Scanning Obstructed exam Volume 15.125

-22r.55.163.251))

14739 Shear Full CkKwis and CounterlockwIse Scanning Obstructed exd m Volume plus the area af exam that Is not 19 qualfled by this pro edue 15.1W0.(oA92*0.607)12)

Uses 0

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Shear Lower One Third Clockwise and CounterCodkwbs Scannin Obstructed exam Volume plus the area of "eam 20 tl Is not qualfed by ths procedure 15.1Z5((.17V.-2o6yZj.

0.2664 RL Axial Full Obtained Exam Volume from Elbow side

((Item 1M/2) - item 9 -

3.1024 RL Axial Full Obtained Exam Volume rom Valve side

((ftm )/2)- Item 10 1A334 RL Axial Lower One Third Obtained Exam Volume from the Elbow side

((Ittem 2)2) -Itemn 11 L

10334 RL Axial Lower One Third Obtained Exam Volume from dhe Valve side (ftem 2)/2 - Main 12L.753 Shear Axdal Full Obtained Exam Volume fom Elbow side (Ittem 31/2) - Itemn 13.a 2.206 26 Shear Axial Full Obtained Exanm Volume from Valve side I((Itm 3)/2)- Ite 14-

.M4 Sh2aSr Axial Lower One Third Obtained Exam Volume from the Elbow side 7 (ten 4s)1/2)-4ton 1S -

Shear Axial Lower One Third Obtained Exam Volume from the Valve side 8 ((Item 4)/2) - Item 165 0.a374 RL Full Clockwise and Countesiadcwise Scanning Obtained Exam Volunse Item S - item 17-4.41 30 RL Lower One Third Clockwise and CounterClodkwise Scanning Obtained Exam Volume Item 6-Item 18m 1.4928 3

Shear Full Cocmkwse and CounterCIodrMse Scnning Obtained Exam Vokume Item 7-Item 19n

.6719 32 Shear Lower One Third Cloctwlse and CounterClocliese ScnnIng Obtained Exam Volume Item 3 -Item 20M 2.7053 RIL Axial Full Exam Volume Percentage fom Elbow side (Item. 21/((It*m 1)/2))r100,3 69.4S %

RL Axial Full Exam Volume Percentage hom Valve side (Item 22/((ltem 1)/Z)))10,a%

32.10%

RL Axial Lower One Third Exam Volume Percentage from Elbow side (Item 23/((Iem 2)/Z)))100 -%

69.55%

R.L Axial Lower One Third Exam Volume Parcentage from Valve side (Item 24/((ltm 2m)ur)f1 3.%

Shlmr Adial Full Exam Volume Percentag hom Elbow aide (Item 25/I((tem 3)/Z3))01003 49.42%

Shear Adal Full Exam Volume Percentage fom Vai side (Item 26/1((tein 3)12))r=0 wN51M Shear Axial Lowei One Third Exam Volume Pe cage from Elbow side (Item 27/((Item 4)2))10100 *1.0,M 4

Shear AxIal Lower One Third Exam Volume Percentap from Valve side (Ruem 23/UleM 4)/;))rlw 3w%

42.90%

4 I. Cldckwise and Count@ezkodwlse Full Exam Volume Perntag 41 Item 29/Item 5)100w%

5023 RI. Clockwise and Counteroociwlse Lower One Third Exam Volume Pemantage (Itemn 30/Items 63100.%

50.23%

Shear Clockvise and CounterClockwIlse Full Exam Volume Percentag (Item 31/Item 7)0100m%

74.71%

Shear Clokwise and Counterlockwise Lower One Third Exam Volume Percentage (Item 3/ft1m 8)0lOo,%

9-04%

A I

I I

1 I

I I

I

,9

O0.0117 4

Full Exam Volume Perceantle combining Shear and RL In the Axial, Clociwise, and Counteaociwisa Dlrcstarins

_to' (otm 33 + Item 34 + Item37.+tem38+Mm41+Item 431/65 %

54.65%

Lower One Third Exam Volume Percentage comblning Shear and AL In the Axial, aockw*se, 46 and Counteraockwise Dircetlons (Rlem 35 4 t

m 36 +It.lem 39 + Rem 40 + Item 42 + Item 44)/6 w% 62.79%

COVERAGE PLOT Component ID: RCRD-2-49 Examiner" A Reviewer.

ANII:

NIA/

Print name:

Dfv~d Kleinjan Print name-Mat Welch Print name:

Date: 29 MAR 2013 Date:

Date:

~Flow_

Valve Elbow tT

~0.491 o,0.669_

0"*

.1 RL Scanning Full Required Exam Volume:

15.125 x 1.018 x ((.669+.491)/2) = 8.9304in' 1.018 Lower one third Required Exam Volume:

15.125 x 1.018 x ((.223+.163)/2) = 2.9717in'

~Shear Scanning 0.206t Full Required Exam Volume:

8.9304-(15.125 x ((.492x.607)/2)) = 6.6719in' Lower one third Required Exam Volume:

2.9717-(15.125 x ((.206x.171)/2)) = 2.7053in' 1"

N C,

COVERAGE PLOT I ". -

Component ID: RCRD-2-49

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/,A A4 A

Examiner:

Reviewer: kU

-WT ANII:

JA Print name: DalidKleinjan Print name: Man Welch Print name:

Date: 29 MAR 2013 Date:

y Date:

i Flow 11110--

Valve Elbow Shear Axial Scan R/L Axial Scan' C0 CD 02 i1 01,51ZI,

I I

COVERAGE PLOT I

Component ID: RCRD-2-49

,// -

I UF0, of 3 Examiner:

Reviewer:

ANII:

I/A Print name: DalIai Kleinjan Print name: Matt Welch Print name:

Date: 29 MAR 2013 Date:

VI Date:

Valve Elbow 0

Area of obstruction Shear Clockwise and CounterClockwise Scanning Full Exam Volume:

15.125 xl.081 x(.669x.491 )/2))=8.9304in' Lower One Third Exam Volume:

15.125 x 1.081 x ((.223x.163)/2)=2.9717in' RL Clockwise and CounterClockwise Scanning Full Obstucted Exam Volume:

8.9304-(15.125 x((.669x.255)+(.491x.251)))=4.4861in' Lower One Third Obstucted Exam Volume:

2.9717-(15.125 x((.223x.255)+(.163x.251)))=1.4928in' 00!

0 0-

Enclosure Attachment B TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant, Units 1, 2, and 3 Request for Relief ISI-44 Weld Inspection Report Excerpts UT-1 3-024 (2 pages)

COVEi.

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4A Print name: j.,4'/

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Date:

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Date:

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Enclosure Attachment B TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant, Units 1, 2, and 3 Request for Relief ISI-44 Weld Inspection Report Excerpts UT-1 3-044 (2 pages)

1\\1-UM Ultrasonic Examination 000351 Outage No.:

U2RF17 Report No.:

UT-13-044 Page:

I Of V

Site/Unit:

BFN I

2 Summary No.:

05507-lSI-BFN2 Workscope:

IsI Procedure:

Procedure Rev.:

Work Order No.:

N-UT-84 2441I Code:

ASME Section Xl 2004 Edition CatJItem:

R-AIR1.160 Location:

Reactor Building Drawing No.:

2-111-02211-C-41

==

Description:==

VLV - FH System ID:

074 - Residual Heat Removal System Component ID: DRHR-2-03 Size/Length:

N/A Thickness/Diameter:

1.219124" Limitations:

Single Sided Exam Comments:

This examination was performed using TVA ISO procedure N.UT-84, revision 1, titled" Procedure for the Phased Array Ultrasonic Examination of Austenitic and Ferriic Pipe Welds".

This procedure implements the processes and requirements of EPRI Report 1016650 which contains the procedure EPRI-PIPE-MPA-1, revision 0, tided "Procedure for Manual Phased Array Ultrasonic Examination of Austenitic and Ferritic Pipe Welds".

This examination was performed on a 24" diameter SS weld consisting of a Flued Head penetration to a cast stainless steel valve. The cast material limited the exam to single side access The exam was performed to satisfy the requirements of Risk Informed Category R-A, item R1.16D and Category D, Item NU0313.

,P44(overage of the examination volume was achieved.

s/.V/i' Ow ZZA4U~~~A-k~~"q4'3/3-3 ~

Results:

Accept VJ Reject []

Percent Of Coverage Obtained > 90%:

Info (]

51.4 w

I ReJewed Previous Data:

yes 7 a ExamIner Level I I

Date Reviewer

/

t te/*

/

Date Gatica, James A.

313112013 Matt Welch, UlII 41-I13 Examiner Level N/A S

re Date Site Review Signature Date N/A NIA

.Other N/A Level N/A Signature Date ANII Review

/,qlgnature fAbv..J

-~gj V.

eLJtj' Date I

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Print name:,A/4TWleh' Print name:,A**,-,/

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,Date:

S!311rs Date: 5/$,,"

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Enclosure Attachment B TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant, Units 1, 2, and 3 Request for Relief ISI-44 Weld Inspection Report Excerpts UT-13-072 (2 pages)

L -% 045 3 SiteAUnit:

Summary No.:

Workscope:

Ultrasonic Examination BFN 1

2 05499481-BFN2 msl Procedure:

Procedure Rev.:

Work Order No.:

N41T44 10*

24.4.6.G Outage No.:

U2RF17 Report No.:

UT-13-072 Page:

1 of 10 Code:

Section Xl 2004 Edition Catltem:

RAJR1.16C Location:

Reactor Building - Drywall Drawing No.:

24,1-0270-."2 Descritjon: P - TEE System ID:

068 - Reactor Water Recrc=ulating System Component ID: KR-2-25 Size/Length:

281 Thickness/Dianeter:

1.322/28 ULmitatlons:

See Report Comments:

This examlnation was performed using TVA ISO procedure N-UT-84, revision 1, tItled "Procedure for the Phased Array Ultrasonic Examination of Austenfitc and Ferritlc Pipe Welds".

This procedure Implements the processes and requirements of EPRI Report 1016650 which contains the procedure EPRI-PIPE-.PA-1, revision 0, titled "Procedure for Manual Phased Army Ultrasonic Examination of Austenittc and Fertlic Pipe Welds".

This examination was performed on a 28"diameter 88 Pipe to Tee weld to satisfy the requirements of Risk Informed Category R-A. item RIIBC and Category C, Item NU0313.

50% coverage of the examination volume was achieved.

No mJectable Indications Results:

Accept a

Red C Info E)

Percent Of Coverage Obtained > 90%:

so Revwmd Previous Data:

Yes Examiner Level orI,*

Date R r

..-7

,t Date Klalnjan, Michael W.

41131M 3 MW Welch. U Examiner Level iI Sig Date Site Review Signature Date Galle, JamesA.

AM/4b/zo,:

3 IA OaterALeveleMIAW k/-Am7 Date ANII Review Date WA1ov~""6 is

THICKNL i AND CONTOUR Position 0

90 180 270 1

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/3*.91 ANI1:

Print name: e, A

,p../Z Date:

Print name: /1hA7T*W 4-'#

40 Date:

Print name:

L4 vC7 L Date:

COMPONENT ID:

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Enclosure Attachment B TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant, Units 1, 2, and 3 Request for Relief ISI-44 Weld Inspection Report Excerpts UT-1 3-076 (4 pages)

She/Unit:

9FN I

2 Summary No.:

018S94SI-BFN2 Workscope:

IsI

(&0478 Ultrasonic Examination Procedure:

N.UT--4Wj Outage No.:

U2RFI7 Procedure Rev.:

4 w

i tL Report No.:

UT-13-076 Work Order No.:

2-SI.4.6.G Page:

1 of 10 Code:

Section Xf 2004 Editon Cat./Item:

R-A/R1.1GD Location:

Reactor Building - Drywall Drawing No.:

2441-0272-C-01

==

Description:==

P - P System ID:

069 - Reactor Water Cleanup System Component ID: RWCU-2-003-070 Size/Length:

61 Thickness/Diameter:

0.43216 Limitations:

See Report Comments:

This examination was performed using TVA ISO procedure N-4T-84, revision 1, titled ;Procedure forth. Phased Array Ultrasonic Examination of Austantic and Feriltic Pipe Welds".

This paroedure Implements the processes and requirements of EPRI Report 1016650 which contains the procedure EPRI-PIPE.MPA-1, revision 0, ti "Procedure for Manual Phased Array Ultrasonic Examination of Austenitic and Ferritic Pipe Welds".

This examination was performed on a 86" dianeter SS pipe to wekl-olet butt weld to satisfy the requirements of Risk Informed Category R-A, Item RI.t6D and Category D, Item NU0313.

.coverg, of the examination volume was achieved.

to,

t-nda/to 9

No rejectlbls Indica1tions.

Results:

Accept 10 Reod Percent Of Coverage Obtained 2 90%:

EJ Info[C]

.I6, Reviewted PeosOa.

Yea 0

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Enclosure Attachment B TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant, Units 1, 2, and 3 Request for Relief ISl-44 Weld Inspection Report Excerpts UT-13-079 (3 pages)

V Ultrasonic Examination Site/Unit:

Summary No.:

Workscope:

BFN I

2 01507-ISI-BFN2 AUG Procedure:

Procedure Rev.

Work Order No.:

N-UT-84 I

2-Sl-4.6.G Outage No.:

U2RF17 Report No.:

UT-1 3-079 Page:

1 of 1/

fj Code:

Section XI 2004 Edition Cat,/Item:

B-J/B9,11 Location:

Reactor Building - Drywell Drawing No.:

2-1SI-0221-C-01

==

Description:==

P - P System ID:

074 - Residual Heat Removal System Component ID: DRHR-2-09 Size/Length:

24/

Thickness/Diameter:

1.219/24 Limitations:

See Attached Report Comments:

This examination was performed using TVA ISO procedure N-UT-84. revision 1, titled "Procedure for the Phased Array Ultrasonic Examination of Austenitic and Ferritic Pipe Welds".

This procedure implements the processes and requirements of EPRI Report 1016650 which contains the procedure EPRi-PIPE.MPA-ti revision 0, titled "Procedure for Manual Phased Array Ultrasonic Examination of AustenItlc and Ferritlc Pipe Welds".

This examination was performed on a 24" diameter SS Pipe to Tee weld to satisfy the requirements of Category E, item NUO313.

This weld contains two previously recorded IGSCC flaws. Refer to UT sizing report UT-I 3-032 for additional data.

50% coverage of the examination volume was achieved.

Results:

Accept V7 Reject Percent Of Coverage Obtained > 90%:

Info I 50 Reviewed Previous Data:

Yes Examiner Level St

,jgj*tu.

e Date Reviewer p__-ia

/Pate KLEIN JAN, DAVID R 4/10/2013 Matt Welch, LIII Z

eZ'//

Examiner Level N/A

,;,10ature Date Site Review Signature Date N/A N/A Other Level N/A Signature Date ANII Review Signature Date NIA N/A q

v

THICKNEq Position 0

2*

hLL 3

,3-4*

1,3

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-180__2-70

~2-5"

__2.5",

2 3

4]DE

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Print name:

Date:

COMPONENT ID:

l*// _-

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/ i-WELD LENGTH:

CROWN HEIGHT:

DIAMETER:

/300 63,"

7.6' 5~~

a-, A14 cam

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Print name:-

VL?"/ K/em tj Date' Print name: /1--Tk.*,eV Date:

Print name:

Date:

COMPONENT ID:

DH LN-T CROWN WIDTH:

/if WELD LENGTH:

CROWN HEIGHT:

/6 DIAMETER:

/?

.. I )2 0

PIF

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Enclosure Attachment B TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant, Units 1, 2, and 3 Request for Relief ISI-44 Weld Inspection Report Excerpts UT-1 3-080 (3 pages)

V:

Site/Unit:

Summary No.:

Workscope:

Ultrasonic Examination BFN 1

2 01518-ISI-BFN2 AUG Procedure:

Procedure Rev.:

Work Order No.-

N-UT-84 I

2aS-4.6.G Outage No.:

U2RF17 Report No.:

UT-13-080 Page:

1 of Code:

Section XI 2004 Edition Cat./ltem:

B-J/B9.11 Location:

Reactor Building - Drywell Drawing No.:

2-1SI-0221-C-01

==

Description:==

VLV - P System ID:

074 - Residual Heat Removal System Component ID: DRHR-2-22 Size/Length:

201 Thickness/Diameter:

1.0311 20 Limitations:

See Attached Report Comments:

This examination was performed using TVA ISO procedure N-UT-84, revision 1, titled "Procedure for the Phased Array Ultrasonic Examination of Austenitic and Ferritic Pipe Welds".

This procedure implements the processes and requirements of EPRI Report 1016650 which contains the procedure EPRI-PIPE-MPA-I, revision 0, titled "Procedure for Manual Phased Array Ultrasonic Examination of Austenitic and Ferritic Pipe Welds".

This examination was performed on a 24" diameter SS Pipe to Tee weld to satisfy the requirements of Category E, item NU0313.

O This weld contains one previously recorded IGSCC flaws. Refer to UT sizing report UT-I 3-033 for additional data.

50% coverage of the examination volume was achieved.

Results:

Accept e Reject Percent Of Coverage Obtained > 90%.

Info --I 50 Reviewed Previous Data:

Yes Examiner Level III-

,nature KLEINJAN, DAVID R Date Reviewer 4/912013 1 Matt Welch, LIII

>~AtueZ 4 7,Dale P

Examiner Level NIA NIA 7V Jignature Dale Site Review N/A Signature Date i

!her Level N/A Signature Date ANII Review N/A Signature Date NIA r,

COVERISPLOT 0

Component ID: DR/-.a- - a Z /7-)3--O1

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Examiner:

/,

Reviewer:

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Print name: p, l

/,,,

I Print name:

Print name:

Date: iý,I, Z/3 D

Date: -o/0, D'te:

I, o*

I,*

),41,70.

~-i FLo~J 4

700SH~

VAL VC pIPE 1.7 -

~EQUI~/,7)X p1' V'OL Ur1/i L L- *,*

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-IANI,-i Examiner:

Print name:

/I 1','- Kfe',,'-'-

Date:

/0 5f 3

-Reviewer:

e- ?-T74 Print name: -YK/*Tk7-7,9:W Date: z1//z43 IF "t

III" Ci.I I Il;:m Date:

0

Enclosure Attachment B TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant, Units 1, 2, and 3 Request for Relief ISI-44 Weld Inspection Report Excerpts UT-1 3-086 (7 pages)

1PROJECT:

BFN I

UNIT:

2 1 CYCLE: 177 SYSTEM:

Rector Water Cleanup System lComponent: RCRD-2-50 Print Name: David Kleinian Print Name: Mitt Welch Date:

05-Apr-13 Dete:

j 0O570O -

Items I 1

RL Axial Full Required Exam Volume 14.7S. *.*(10..WOM8)2),"

9..U0 EL Axial Lower One Third Required Exam Volume 2 14.7S0L09*ff0.113.0.2771/2)-

3.2351 Shuer Axial Full Required Exam Volume Shear Axial Lower One Third Required Exam Volume 4-14.75510, rff13.77',

".2)5 I

E RL Full Clociwise and CmmteModmiwse Scennkn Required.m Volume 14.7-LS*n0(-0J3240.mi/2)-

.30 EtL Lower One Third Clockwise and -

Scmflnt Required earm Volume

£ Shr Lower One Third O*dwis and Cowiterockul, Scaroft Reaquired Voume U4.75sLN,0.113.0.7*7 3.1U51 E L Axial FAll Volue Obstructed Exam frm the Elbow We RL Axial Full Volum Obstructed Exam from the Valne side 10 4/2 12.7948r3

• 0.561.0.5

/23 2L31735 11 RL Axial Lower One Third Volume Obstructed Exam from the Elbow side 1'

o(1.09G/Z)*.sr((0.277,.,1U/2).

0.5314 1

EL Axial Lower One Third Volume Obstructed Exam frm the Valve aide S (1.090/23*(2."W43)6U]77.

Lu"l Shur Axia Full Volum Obstructed Exam plus the area that Is not qualified by this procedure fron the Elbow aide

13.

5s S61

),,

L1647 14~ Shear Axial Full Volume Obstructed Exam plus the area tha Is not qualifed by thi procedure frcom thes Valvo side (14.7S.((o*S63ft-V2/)j.2(IL

)('L9M*33)O.Lz2H(I(0i4900)/Wrfi9M'*3))-

L9279

[

Sheur Axial Lower one Third Volume Obstructed Eam pus the am of exam thdt Is not qualiflie by this procedure S

from the Mabw side 14.7S(I(P.29@%=U012)/2)w 0.3M9 Shw Axial we One Third Volume Obstructed Exam plus thsers of exam that bs not qualfe bythis procedure frohm the Valve side 17 EL Full Clodowire mid Cosmter~odiwlse Sceimbig Obstructed mmor Volume 14.7R0.3W((L~0.325..51 1ft2) 3-9746 S

ELlower One Third Volume Osthalse and C t

Scannn Obstructed exam Volumne 2 I.7r*0.33r0.277 1.S35 F

Shear Full CockwIse and CourterClockmise Scanrnin Obstructed exam Volume plus the arme of mm that Is not 19 qualified by this procedure 14.75((C0.S630.S61)12) *-.3.93

(,0;571 Shear Lower One Third Cockwise and Counter~locin Scanning Obstructed exam Volume p-ls the rm of exam 20 that Is not qualified by this procedure 1A.7S((0.2910JU)123.0.59 RL Aal Full Obtained xamr Volume from Elbow side 7

(11ton 1)/2). -Ite 9 -

3A4427 2

R Axial Ful Obtained Eam Volume ftom Valve sdeJ l((tern 4/2 )-ltern 0 1B 2

RL Axial Lower One Third Obtained Exam Volume from the Elbow aide (Wtern 2I2P - Iteam U a L.0362 J

24 L Axial Lower One Third Obtainted bxarn Volume forom the Valn side

((flten 2)/2- *Im U

.12 a

03.0 Shear Axial Full Obtained Exam Volume fanm Elbow side S ((Itm 3)/2)- itemn 1 w 3A978 26 Shaer Axial Full ObtaIned Exam Volume from Valve side

((Item 31.

Item-4 2.7346 Shear Adel Lower One Third Obtained Exam Volume from the Elbow side 27 p m,,,

41)*] -ite, is-L 37 2

Shear Axial Lower One Third Obtakn Exam Volume from the VaMe side (fitemn41/2) -Item 16.zL79 UL Full Clohwta and Counterzwwlse Sacnnakg Obtaled bamn Volume Item,, 5 -1w

17. a 503 30 RL Lower One Third Clockwise and CounterClxocwise Smcnnl Obtained xrnm Volume Iten 6-item 18 1.5498 31 Sheer Full Clocdise and Countejkdawise Sannlmn Obltined armn Volume UMn 7 -Itamn 1.

&.9M 1

I 32 Sheer Lower One Third Clockwise and CounterClaockwis Scaning Obta0ned Exam Volume Item 8-Item 2zo ZAS478 RL Axial F-ull xam Volume Percentage from Elbow sdde (Item 211/1tunm 1,j2I)'0bm %7.

4 RL Axial Full Exam Volume Percentage from Valve dde

[ (Itemn 22111iftem 211;1))0100 -%

M RL Axial Lower One Third Exam Volume Percentage from Elbow side 1-(Itm 24(ltm zn2II)).roo.=%

SerL Axde ow OnThrudJ Exam Vk*Pmz atp g

fro m Winv Wk e

Sheer Axial Full bEar Volume Percentage from Elbow dede l(t.mn tm/((.

• )a))20.v%

75 Sheer Axial Full bxar Volume Percentage frm Valve ddse iftemn W(Item W 100um%

1.

9 Shear Aaower Thrd ExnVolume Per tantagexfom Elbowu Pde 40 Shear Axia Lower One Third Exam Voluime Percentage from Valve side 41 RI. Glo Am Iv and Counter(lockwise Full bxarn Volume Percentoge A2 L Clockwise and Counter~lockius Lower One Third bxarn Volume Percentage (Itm 30/Item 6r*100.%

49A3%

Shear Clockwise and CountaOockwise Full Exam Volume Percentage Itern 31Item 7)100%

7m.92 44Shaear ClocwInvse and CounterClodawLse Lower One Third bxarn Volume Percentage (Itemn 32/ltem 810100.'%

711.97%

I

j 5 72 4S Full Exam Volume Percentae comblning Shear and RL In the Axial, COockwlse, and Caunterlockwise D-(hurm 33 IItem34+fteni37+ftemS tvm4l.Item 4116'm%

6L.97%

Lower One Third Exam Volume Percentage combining Sitar and tL In the Axial, Cocwi.se, 46 and CounterClockwise Dirctwlns (Item 35 +Item 36+Item 39+ Item 40 + Item 42 + tem44)/6m%

56.A3%

Wi

COVERAGE PLOT Component ID: RCRD-2-50 Examiner:

,,Reviewer.

ANII:

Print name: Ddvidfleinjan Print name: MattWelch Print name:

Date: 05 APR 2013 Date:

2,14/,I5//7 Date:

Flow Elbow Shear Axial Scanning Full Required Exam Volume:

14.75 x 1.090 x ((.332+.828)/2)=9.3250in3 Lower One Third Required Exam Volume:

14.75 x 1.090 x ((.113+.277)/2)=3.1351in 3 RL Axial Scanning Full Required Exam Volume:

14.75 x 1.090 x ((.332+.828)/2)=9.3250inI Lower One Third Required Exam Volume:

14.75 x 1.090 x ((.1 13+.277)/2)=3.1351 in3 1I" Valve

.2 1-V 0.300 0*

U1

/)4

I COVERAGE PLOT Component ID: RCRD-2-50 Examiner:

'Reviewer:

ANII:

AfM-Print name:

DtavidPKleinjan Print name: Matt Welch Print name:

Date: 05 APR 2013 I Date:

&/'/

Date:

Flow Elbow Valve Shear Clockwise and CounterClockwise Scanning

.M3 0.828 Full Required Exam Volume:

0.113 14.75 x 1.090 x ((.332+.828)/2)=9.3250in Lower One Third Required Exam Volume:

1.0o0-14.75 x 1.090 x ((.113+.277)/2)=3.1351in 3

RL Clockwise and CounterClockwise Scanning Full Required Exam Volume:

14.75 x 1.090 x ((.332+.828)12)=9.3250in3 Lower One Third Required Exam Volume:

14.75 x 1.090 x ((. 113+.277)/2)=3.1 351 in3 Area of obstruction 0.388 W

1" a

I COVERAGE PLOT Component ID: RCRD-2-50 A. Llrf4ý -051 A

Examiner:

'Reviewer:

ANII:

4-Print name:

Mviq'Kleinjan Print name: Matt Velch Print name:

Date: 05 APR 2013 Date:

Date:

Elbow Valve Shear Axial Scan R/L Axial Scan 1

C%,

a

INDICATION PLOT I

Component ID: RCRD-2-50 A

Examiner:

Reviewer:

PrANII: nam Print name: Da'd Ki6injan Print name: Malt Welch Prnt name:

Date: 05 APR 2013 Date: 41/9 Date:

Elbow Valve 1-.3/4" QO0 1

C-,

CD' 1 t, 0