ML20199F279

Bfnp Unit 3 Cycle 8 ASME Section XI NIS-2 Data Rept

ML20199F279
Person / Time
Site:	Browns Ferry
Issue date:	12/03/1998
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18039A670	List: ML20199F272 ML20199F279
References
NUDOCS 9901210274
Download: ML20199F279 (32)

Text

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( ENCLOSURE 2 i

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TENNESSEE VALLEY AUTHORITY l BROWNS FERRY NUCLEAR PLANT (BFN)

UNIT 3 AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME),

SECTION XI, REPAIR AND REPLACEMENTS PROGRAM

SUMMARY

REPORT (NIS-2) FOR CYCLE 8 OPERATION 1

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BROWNS FERRY

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i NUCLEAR PLANT

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l UNIT 3 CYCLE 8 3

l ASME SECTION XI

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NIS-2 DATA REPORT

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OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS 1

APPENDIX I Summary of Repair and Replacement Activities APPENDIX II Form NIS-2 Owner's Report For Repairs or Replacements l

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Owner: TENNESSEE VALLEY AUTHORITY Plant: Browns Ferry Nuclear Plant 1101 Market Street P. O. Box 2000 Chattanooga, Tennessee 37402-2801 Decatur, Alabama 35609-2000 Unit: Three Certificate of Authorization: Not Required Commercial Service Date: March 1,1977 National Board Number for Unit: Not Required APPENDIX I

SUMMARY

OF REPAIR AND REPLACEMENT ACTIVITIES l

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t j Owner: TENNESSEE VALLEY AUTHORITY Plant: Browns Ferry Nuclear Plant 1101 Market Street P. O. Box 2000 Chattanooga, Tennessee 37402-2801 Decatur, Alabama 35609-2000 Unit: Three Certificate of Authorization: Not Required Commercial Service Date: March 1,1977 National Board Number for Unit: Not Required WID SYS ORG CLASS ACT!VITY T40617, Stages 1 & 2 069 MAINT 1 Replacement 98-010144-000 T40657 073 MAINT 1 Replacement 98-009875-000 T40713, Stage 1 071 MAINT 1 Replacement 98-009567-000 T40871A 001 MAINT 2 Replacement T41089A 068 MAINT 1 Repair 96-005205-000 001 MAINT 1 Replacement 97-006992-001 98-006534-000  ;

98-006535-000 97-002190-000 001 MAINT 1 Replacement 98-000514-000 068 MAINT 1 Replacement 98-001448-000 068 MAINT 1 Replacement  !

98-003255-000 073 MAINT 2 Replacement l l

98-003270-000 071 MAINT 2 Replacement 98-005505-007 073 MAINT 2 Replacement 98-010357-000 069 MAINT 1 Replacement i

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Owner: TENNESSEE VALLEY AUTHORITY Plant: Browns Ferry Nuclear Plant i101 Market Street P. O. Box 2000 Chattanooga, Tennessee 37402-2801 Decatur, Alabama 35609-2000 Unit: Three Certificate of Authorization: Not Required Commercial Service Date: March 1,1977 National Board Number for Unit: Not Required LEGEND WID - Work Implementing Document Example: A99999 refers to a Design Change Notice 99-999999-999 refers to a Work Order SYS- System 1 - Main Steam 69 - Reactor Water Cleanup 3 - Reactor Feedwater 71 - Reactor Core Isolation Cooling 8 - Turbine Drains 73 - High Pressure Coolant injection 10 - Reactor Drains, Vents 74 - Residual Heat Removal and Blowdown 75 - Core Spray 12 - Auxiliary Boiler 85 - Control Rod Drive 63 - Standby Liquid Control 68 - Reactor Water Recirculation ORG - Organization which performed the WID MAINT - TVA's Maintenance Organization GE - General Electric Company TVA - Work performed by Stone and Webster Engineering Corporation utilizing TVA's Quality Assurance Program and procedures CLASS - Refers to ASME Code Class I or 2 ACTIVITY - Classifies work activity as being repair or replacement as denoted on NIS-2 Form

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Owner: TENNESSEE VALLEY AUTHORITY Plant: Browns Ferry Nuclear Plant 1101 Market Street P. O. Box 2000 l- Chattanooga, Tennessee 37402-2801 Decatur, Alabama 35609-2000 Unit: Three Certificate of Authorization: Not Required Commercial Seivice Date: March 1,1977 National Board Number for Unit: Not Required i

APPENDIX II FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS i

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FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Requ! red by the Provisions of the ASME Code Section XI

1. Owner Tennessee Valley Authonty (TVA) Date December 2,1998 1101 Market Street Chattanooga. TN 37402-2901 Sheet 1 of 1 AGdress

2. Plant Browns Ferry Nuclear Plant (BFN) Unit 3 P. O. Box 2000, Decatur, AL 35609-2000 Design Change Notice (DCN) T40617 Stages 1 & 2 and Work Order M/0) 98-010144 000 Address Repair Organgabon P Q No , Joe No , etc

3. Work Performe< by TVA-BFN Type Code Symbol Stamp N/A Name P. O Box 2000. Decatur, AL 35609-2000 Authonzation No. N/A Accross Expiration Date N/A

4. .ldentification of System System 069. Reactor Water Cleanup (RWCU) System (valve) ASME Section 111,1989 Edition

, S.(a) Applicable Construction Code (piping) USAS B31.1.0 19 67* Edition, N/A Addenda, N-416-1 Code Case 1

(b) Applicable Editon of Section XI Utilized for Repeers or Replacements 19 89 7

6. Identificahon of Components Repared or Replaced and Replacement Components ASME Code National Repaired, Stamped Narne of Component Name of Manufacturer Manufacturer Board Other Identification Year Replaced, or (Yes or Serial No. No. Built Replacement No)

RWCU inner isolation Ar.chor/ Darling E471 A-1 1 N/A 3-FCV-069-0001 1998 Replacement No Valve 6*-900# DD Gate VIv RWCU Outer Isolation Anchor / Darling E471 A 2-2 N/A 3-FCV-069-0002 1998 Replacement No Valve 6* 900# DD Gate Viv pipsng TVA N/A N/A N/A 1998 Replacement No 1

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7. Desenption of Work Replaced the inboard and outboard RWCU containment isolation valves and some associated piping i.

' 8.' Tests Conducted: Hydrostatic 0 Pneumatic O Nominal Operating Pressure @

! Other O Pressure N/A psi Test Temp. N/A *F i

! NOTE: Supplemental Sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8% in. X 11 in . (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

t i #as amended by additional quality assurance requirements found in Contract 1241382 Supplement 1, and Design Cntena BFN 50-7069 and BFN 50-C 7105.

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l FORM NIS-2 (Back)

9. Remarks Replaced the inboard and outboard RWCU containment isolstion valves and some associated piping Apouse Manutacwors ' sata Reports to be attacned CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the

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ASME Code section XI.

Type Code Symbol Stamp N/A Certificate of Authonzation No. N/A M Expiration Date N/A Signed hM((' owner or pers cosy ree System Engineer Date /E 3 ,19 f

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CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of 7FA/AA and employed by f/647 fI of NA/ffo#d, c7 have inspected the components described in this Owner's ReportTfunng the penod /B -(,

• f'8 to /d-/2-FW , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures desenbed in this Owners Report in accordarce with the requirements of the ASME Code,Section XI.

By signing tt is certsficate nedher the inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and correctrve measures described in this Owners Report. Furthermore, neither the inspector nor his employe( shall be hable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Commissions /7 7/.3 [

i rtspectoFs Segnature P4anonal Board. State. Premnce, and Endorsements Date Dec. 3 ,9 rw l

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FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI

1. Owner Tennessee Valley Authonty (TVA) Date December 2.1998 1101 Market Street Chattanooga. TN 37402-2801 Sheet 1 of 1 A......

3 Plant Browns Ferry Nuclear Plant (BFN) Unit 3 sg ng/9p ,,, )

P. O. Box 2000, Decatur, AL 35609-2000 Design Change Notice (DCN) 40657 and #  !

Work Order (WO) 98-009875-000 Aeoress Repaw Organgstson P Q NO . JOB No . etc

)

3. Work Performed by TVA-BFN Type Code Symbol Stamp N/A P. O. Box 2000. Decatur A"L 35609-2000 Authonzation No. N/A Aaare Expiration Date N/A

4. Identification of System System 073. High Pressure Coolant injection (HPCI) System (valve) ASME Section ill,1989 Edition 5.(a) Applicable Construction Code (piping) USAS B31.10 19 67

• Edition, N/A Addenda. N-416-1 Code Case (b) Applicable Edition of Section XI Utdized for Repairs or Replacements 19 89

6. Identification of Components Repaired or Replaced and Replacement Components ASME i Code  !

National Repaired, Stamped Name of Component Name of Manufacturer Manufacturer Board Other identification Year Reptaced, or (Yes or Senal No. No. Built Replacement No)

HPCI Steam Supply Valve Anchor /Darkng E413A-1 1 N/A 3-FCV-073-0016 Replacement No 10"-900# DD Gate VIv pipe support- TVA N/A N/A 3-478455-626 Replacement No ptping TVA N/A N/A N/A Replacement No I

7. Desenption of Work Replaced the HPCI Steam Supply valve and some associated piping Modified associated pipe supoort G. Tests Conducted: Hydrostatic O Pneumatic 0 NominalOperating Pressure @

Other O Pressure N/A psi Test Temp. N/A *F i

NOTE: Supplemental Sheets in form of hsts, sketches, or drawmgs may be used, provided (1) size is 8% in. X 11 in.. (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

• as amended by additional quality assurance requirements found in Contract 1235902 Supplement 3. and Design Cntena BFN-50-7073 and BFN-50-C 7105.

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O. Remarks Replaced the HPCI Steam Supply valve and some associated pipina Mod. ,'ry Aed pipe support Appucanie uanufacturers oata Reports to De atta r,

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CERTIFICATE OF COMPLIANCE We cer'.ify that the statements made in the report are correct and this replacement conforms to the rules of the ASV i'.;Ne Section XI.

Type Code Symbol Stamp N/A Certificate of Authonzation No. N/A Expiraten Date N/A Signed g

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ownee oTownere Des (nee Tee

, System Enaineer Date ,,

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e CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned. holding a vahd commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of TEA //./. and employed by //$27 (3 of

• '- /Uh# T'#d/?d (T have inspected the components desenbed in this Owners' Report dunngThe penod 7-df-## to /d v $- #f , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures desenbod in this Owners Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor hs employer makes any warranty, expressed or imphed, conceming the examinations and corrective measuret % scribed in this Owners Report. Furthermore, neither the inspector nor his employer shall be hable in any manner for any personal injury or property damage or a loss of any kind ansing from or connected with this inspection.

1 Commissions N8/3 5

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Date _ b(, 3 19 [ 8 l

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FORM NIS-2 OWNER'S REPORT FOR REPAlRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI

1. Owner Tennessee Valley Authonty (TVA) Date December 2,1998 Name 1101 Market Street Chattanooga. TN 37402-2801 Sheet 1 of 1 Accress

2. P' ant Browns Ferry Nuclear Plant (BFN) Unit 3 P. O. Box 2000, Decatur, AL 35609-2000 Design Change Neix CON) T40713A, Stage 1 and Work Order (WO)98-009' 67-000 Acaress Repsw oron%soon P o No . Joe No , etc

3. Wort Performed by TVA-BFN Typt Code Symbol Stamp N/A P. O. Box 2000, Decatur AL 35609-2000 Authonzation No. *kA AcGress Expiration Date N/A

4. Identification of System System 071, Reactor Core Isolatiorping (RCIC) System (valve) ASME Sectitu lit,1995 Edition,1997 Addenda 5.(a) Applicable Construction Code (piping) USAS B? .1.0 19 67* Edition, N/A Addenda, N-416-1 Code Case (b) Apphcable Edition of Section XI Utilized for Rif ars N Replacements 19 89 G. Identification of Components Repaired oro' ,ilaced and Replacement Components ASME Code Natonal Repaired, Stamped Name of Component Wme of Manufacturer Board Other identificatrn Year Replaced, or (Yes or F.anufacturer Senal No. No. Built Replacement No)

RCIC Steam Supply A .chor/ Darling E488A-5-2 N/A J-FCV-071-0003 1998 Replacement No Outboard Isol Valve '/-900W DD Gate Viv pipe support TVA N/A N/A 3-47B456-640 1998 Replacement No i piping TVA N/A N/A N/A 1998 Replacement No l .

7, Description of Work Replaced the RCIC Steam Supply Outboard Isolation valve and some associated piping. Modified associated pipe support.

8. Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure @

l Other O Pressure N/A psi Test Temp. N/A *F l

i NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8% in. X 11 in., (2) information in items 1 through 6 on thes report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

• as amended by additional quality assurance requirements found in Contract 92ZMB45195C, and Design Cntena BFN-50 7071 and BFN-50-C-7105 I

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l FORM NIS-2 (Back) 9 Remarks Replaced the RC1C Steam Sjpr fg, gard Jsolation valve and some associated piping Modified associated pipe support

, ww .m. uanue.cturers oatsseports to a att ce.ea CERTIFICATE OF COMPLtANCE 7 We certify that the statements made in the report are correct and this replacement conforms to the rules of the repair or replacement ASME Code Section XI.

Type Code Symbol Stamp N/A Certificate of Authonzation No. N/A _ Expiration Date N/A Signed M. //

ow7nor owners cie gnalr'Titis System Engineer Date /z. 3 ,19

" f" CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned. holding a valid commissioq issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Provinge of TM# and employed by MS/J(7 of n/$8Tfdf/3 M have inspected the components desenbed in this Owners Report during the penod 9-f-#f ~

to //9-/f-F f , and state that to the best of my knowledge and belief, the Own'er has perforined examinations and taken correctue measures desenbed in this Owners Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, conceming the examinations and corrective measures desenbed in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable ir any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

anspectore segnature Commissions M/.7/8[ N 7 N5Donal board. State. Province. and Encorsements Date tf , 3 19 ,Y $

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l FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS l As Required by the Provisions of the ASME Code Section XI  !

1. Owner Tennessee Valley Authordy (TVA) Date December 2,1998 1101 Market Street Chattanooga, TN 37402-2801 Sheet 1 of 1 Ana, .

2. Plant Browns Ferry Nuclear Plant (BFN) Unit 3 P O Box 2000. Decatur. AL 35609-2000 Desian Chance Notice (DCN) T40871 A Asaress Repair Organgabon P O No . Jon No , e'C. 1

3. Work Performed by TVA-BFN Type Code Symbol Stamp N/A Name P. O. Box 2000, Decatur, AL 3S609 2000 Authonzation No. N/A Address Expiration Date N/A

d. Identification of System System 001, Main Steam System 5.(a) Apphenble Conow.c n Code USAS B31.1.0 19 67

• Edition, N/A Addenda. N/A Code Case (b) Apphcable Edition of Section XI Utilized for Repairs or Replacements 19 89

6. Identification of Components Repaired or Replaced and Replacement Components l

ASME Code National Repaired. Stamped Name of Component Name of Manufacturer Board Other Identification Year Replaced, or (Yes or Manufacturer Senal No. No. Built Replacement No)

Pipe Support TVA N/A N/A 3-47B401-66-3 Replacement No j Pipe Support TVA N/A N/A 3-47B40146-5 Replacement No Pipe Support TVA N/A N/A 3-47B401-66-8 Replacement No Pipe Support TVA N/A N/A HPASH-2 Replacement No I Ptpe Support TVA N/A N/A HPASH-7 Replacement No Pipe Support TVA N/A N/A HPASH-14 Replacement No l Pipe Support TVA N/A N/A HPASH-1 Replacement No

! (Deleted) l

7. Desenption of Work Modified 3 pipe supports, replaced 2 spnng can supports, reset 1 spnno can support setting and deleted 1 rod support.

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l 8 Tests Conducted: Hydrostatic 0 Pneumatic O Nominal Operating Pressure O Other O Pressure N/A psi Test Temp. N/A 'F NOTE: Supplemental Sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8% in. X 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

• as amended t1y additional quahty assurance requirements found in Design Cntena BFN-SO-7001, BFN-50-C-7306 and Bill of Matenals.

i L3CH 18 I

l FORM NIS-2 (Back) l 0 Remarks Modified 3 pipe supports. replaced 2 spnno can supports, reset i spnno can support setting and deleted 1 rod support App 6scaci. Manufactur.rs oata R.gorts t. D. attacn These modifications were not the result of any known failures. but were the result of a TVA initiative to improve the structural integnty certain piping components in the Turbine Building.

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CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the

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ASME Code Section XL l

I Type Code Symbol Stamp N/A Certificate of Authonzation No. N/A .

Expiration Date N/A Signed,

,Md[.n // -. a.c.

M ,..

ystem Engineer Date /1, ,19 CERTIFICATE OF INSERVICE INSPECTION ding a vahd commission issued by the National Board gffoiler and Pressure Vessel inspectors and the State 1, the or Province of undersigned / @FA/4/ and employed by //68]*ff of

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have inspected the components desenbed in this' Owners Report durifig the penod 9 -/4 d/ f to /d -/2 - 98 , and state that to the best of my knowledge and behef, the Owner'nas'performeciexaminations and taken corrective measures desenbed in this Owners Report in accordance wtth the requirements of the ASME Code.Section XI.

By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, conceming the examinations end corrective measures described in this Owners Report. Furthermore, neither tne Inspector nor his employer shall be hable in any manner for any personal injury or property damage or a loss of any land arising from or connected with this inspection. .

, __.s.,_.

Commissions [M/3[ ~._._.s_.,_.._._

Date h8C 3 19 ((

U3CN,18

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Secticti XI

1. Owner . Tennessee Valley Authonty (TVA) Date December 2,1998 1101 Market Street Chattanooga. TN 37402-2801 Sheet 1 of 1 Address

2. Plant Browns Ferry Nuclear Plard (BFN) Unit 3 P. O. Box 2000, Decatur, AL 35609 2000 Design Change Notice (DCN) T41089A Adoress Repair OrgangaDon P Q No . Joe No , etc

3. Work Performed by TVA-BFN Type Code Symbol Stamp N/A P. O. Box 2000, Decatur)A[. 35609-2000 Author 2ation No. N/A Aaoren Expiration Date N/A

4. Identification of System System 068, Reactor Water Recirculation System 5.(a) Apohcable Construction Code USAS B31.1.0 19 67* Edition, N/A Addenda, N-416-1 Code Case (b) Applicable Edition of Section XI Utdeed for Repairs or Repiacements 19 89

6. Identification of Components Repaired or Replaced and Replacement Components ASME Code National Repaired, Stamped Name of Component Name of Manufacturer Board Other identification Year Replaced, or (Yes or Manufacturer Senal No. No. Built Replacement No)

Daiiin Connection on TVA N/A N/A Drain connection on N/A No Recirc Pump 3A Disch Viv 3-FCV-068-0003 Rdpoird

• 'L aw rfg pyiry y

7. Desenption of Work Encapsulated the drain connection on the 3A Recire Pump discharge vane.

8. Tests Conducted: Hydrostatic O Pneumatic O Nominal Operating Pressure @

Other O Pressure N/A psi Test Temp. N/A *F NOTE: Supplemental Sheets in form of hsts, sketches, or drawings may be used, provided (1) size is 8% in. X 11 in., (2)information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

• as amended by additional quakty assurance requirements found in Contract 68C37-91750 and Design Cntena BFN-50-7068 and BFN-50-C-7105.

U3C8.19

FORM NIS-2 (Back)

9. Remarks Encapsulateo the drain connection on the 3A Recare Pump discharge vane Applicabe Manufacurera Data Reports to be attacned CERTIFICATE OF COMPT.lANCEpk pg il We certify that the statements made in the report are correct and this seeissemes* con r s to the rules of the

'*"~"'"***"'

ASME Code Section XI.

Type Code Symbol Stamp N/A Certificate of Authorization No. N/A Expiration Date N/A Signed g"

4 /d Owner or Owners Gesigne6 race System Engineer Date M ,19

/

CERTIFICATE OF INSERVICE INSPECTION 1, the undersi ned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel inspectors and the State or Province of A/A/ and employed by //.587"fJ of O,MTfo#n , o T have inspected the components desenbed ,

in this Owriers Report dufing the penod /# -/J W $ to /O -/ 9- F# , and state that to the best of my knowledge and belief, the Owner has performed examinatens and taken corrective measures desent>ms h this Owners Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his emp6 oyer makes any warranty, expressed or implied, concen ing the examinations and corrective measures desenbed in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any lund ansing from or connected with this inspectiors.

" mspectors 5sgnature Commissions M3/3[ Nanones Board, state. Prtmnce and Endorsements Date M[ 19 l

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FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI l

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1. Owner Tennessee Valley Authonty (TVA) Date November 9.1998 tt01 Market Street C' attanooga. TN 37402-2801 Sheet 1 of 1 Acoross

2. Plant Bres Ferry Nuclear Plant (BFN) Unit 3 l P. O. Box 2000, Decatur, AL 35609-2000 Work Orders 98-006535 000 & 96-005205-000 1

98-006534-000 8 97-006992-001 Aooress Repair Orgenmanon P o No . Joe No , etc l

3. Work Performed by TVA-BFN Type Code Symbol Stamp N/A P. O. Box 2000, Decatur) A"L 35609 2000 Authonzation No. N/A .

Aoo,.se i Expiraton Date N/A

4. Identifcation of System System 001, Main Steam System ASME Secten lit, Artcle 9,1965 and l 5,(a) Appleable Constructxm Code ASME Section 111 19 68 Editon, Summer 1970 Addenda, N/A Code Case

(b) Appicabie Edition of Section XI Utilized for Repairs or Replacements 19 89 i

6. Identificaten of Components Repaired or Replaced and Replacement Components ASME l Code l National Repaired, Stamped l Name of Component Name of Manufacturer Board Other identifcation Year Replaced, or (Yes or

Manufacturer SenalNo. No. Built Replacement No)

I Main Steam Relief Valve Target Rock Corp. 1022 N/A 3-PCV-0010018 1968 Replaced No 7567F-000-10 Main Steam Relief Valve Target Rock Corp. 154-1028 N/A 3-PCV-001-0179 1968 Replaced No 7567F-00010

7. Desenpton of Work Replaced two Main Steam Relief valve main bodes for inspection and testing.

B. Tests Conducted: Hydrostate O Pneumate O Nominal Operatii. . ressure @

Other O Pressure N/A pal Test Temp. N/A 'F NOTE: Supplemental Sheets in form of lists. sketches, or drawings may be used, prov6ded (1) size is 8% in. X 11 in., (2) information in items 1 through 6 4 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

• as amended by additional quahty assurance requirements found in GE P. O. 205AJ600, and Design Critena BFN-50-7001 and BFN 50-C-7105.

t U3CH_04

I FORM NIS-2 (Back)

9. Remarks The main vane bodies were replaced with rebuilt vane bodies previously used on Unit 2 (same manufacturer /model number)

As a part of the Tech Spec required valve inspections WO 98-006535-000 replaced 3-PCV-001-0018 with a rebuilt vane previously used in BFN Unft 2 (2-PCV-001-0019. S/N 1022) and installed new inlet and outlet flange studs and nuts. The replacement vane was removed from Unit 2 by WO 95-017147-004 and rebuilt by WO 96-005205-000. WO 96-005205-000 replaced some additional pressure AppucaDie Manufacturer's Data Reports to be attached retaining botting and nuts which had galled dunng disassembly. Some pressure retaining nuts were replaced for ease of maintenance.

A linear indication was identified in the seat seal weld. All indications were removed by gnnding except for one which was dispositioned under PER 98-009618 000.

Due to suspected seat leatrage either through the main seat or the pilot seat WO 98-006534-000 replaced 3-PCV-001-0179 with a rebuilt vane i body previously used in BFN Unit 2 (2-PCV-001-0030 S/N 154-1028) and installed new inlet and outlet flange studs and nuts The replacement 1

vane was removed from Unit 2 by WO 97-006992-000 and rebuilt by WO 97-006992-001. WO 97 006992-001 replaced some pressure retaining bolting and nuts which galled dunng disassembly Some pressure retaining nuts were replaced for ease of maintenance Severallinear indications were identified in the seat seal weld. The indications were removed by gnnding.

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the repair or repiac ment ASME Code Section XI.

Type Cod Symbol Stamp N/A Certificate of AuthonZation No, N/A Expiration Date N/A

[/ , System Engineer /2.,-h Signed - r cwner or ownfr ro. gn. Tim.

Date ,19 CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel inspectors and the State or Province of TE N M . and employed by HAD O Cd_ ?TrT1. T-LP_. tho,4- Tm, (% of HRiZT4 M _SnAfM, _ have inspected the' components desenbed

! in this Owner's Report dunng the pedod R-16 Ci71 to C - 1 to Jr 9 , and state that

, to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures desenbed in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures desenbed in this Owner's Report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind ansing from or connected with this inspection, r

. d- Commrssions Q63R'.~ill, ... sm. -. .,.%r:1 .o- M

-- s. n ~ mn ,.. .n.

Date "fA-M 19 M ocs 04

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i

i FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS l As Required by the Provisions of the ASME Code Section XI

1. Owner Tennessee Valley Authonty (TVA) Date November 9,1998 1101 Markr' Street Chattano' sa . TN 37402-2801 Sheet 1 of 1 Aaores.

2. Plant Brr uns Ferry Nuclear Plant (BFN) Unit 3 Design Change Notme (DCN) T39906A Stage 7 and P O Box 2000 Decatur. AL 35609-2000 Work Order M/0) 97-002190-000 Address Repar organsabon P o beo , Job No , etc.

3. Work Performed by TVA-BFN - Type Code Symbol Stamp N/A Name P. O. Box 2000. Decatur AL 35609-2000 Authonzation No. N/A i A00tets Expiration Date N/A l

4. Identification of System System 001, Main Steam System l i

S.(a) Applicable Construction Code USAS B31.1.0 19 67* Edition, N/A Addenda, N/A Code Case I

(b) Appleable Edition of Section XI Utikzed for Repairs or Replacements 19 89 i

6. Identification of Components Repaired or Replaced and Replacement Components ASME Code National Repaired, Stamped Name of Component Name of Manufacturer Board Other identirmation Year Replaced, or (Yes or Manufacturer Serial No. No. Built Replacement No)

Main Steam Line C Atwood & MornN 36919 N/A 3-FCV-0010037 N/A Replacement No Outboard Isolation Valve - 20851-H I l

l f

1

7. Desenption of Work Installed a modified valve poppet and stem.

1

8. . Tests Conducted Hydrostatic O. Pneumatic O NominalOperating Pressure @

i l Other O Pressure N/A psi Test Temp. N/A 'F NOTE: Supplemental Sheets in form of lists, sketches, or drawings may be used, provided (1) size rs 8% in X 11 in., (2)information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

• as amended by additional quakty assurance requirements found in Contract 68C37-91750, GE Purchase Specification 21 A1062 Rev. O and 21 A1062AL Rev. 6 and Design Cntene BFN-50-7001 and BFN-50-C-7105.

Incs_06

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l FORM NIS-2 (Back)

I

9. Remarks Installed a modified valve poppet and stem into 3-FC%1-37. These components were previously used in Unit 2 (2-FC%1-14)

Appocacio Manufacturer's Osta Reports to es attacne.

l Both the Und 2 and Unit 3 valves are Atwood & Mornli model 20851-H-20 and are used in the same application. The valve poppet was modified under DCN T39906A Stage 7. WO 97-006387-000 removed the poppet and stem from Unit 2. WO 98-002608 003 modified the poppet and l WO 97 002190-000 installed the parts in Unit 3 1

I CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the l repast or repoecoment l ASME Code Section XI.

l Type Code Symbol Stamp N/A Certificate of Authonzation No. N/A n Expiration Date N/A i l

Signed

'[

Ms[ M Qwner or Owners Ces.gnp Tine

, System Enoineer Date /Z

/

,19 I

CERTIFICATE OF INSERVICE INSPECTION l, the undersagned, holding a valid commisskwi rasued by the Natona!grd of Bogand Pressure Vessel inspectors and the State or Province of ~TPAu. and employed by HREsFDM 6 iTTf. *2tE e -fro <.Q 4. -tm. FN. of HnEmed _ Gnww. have inspected the components desenbed in this Owners Report dunng the p'enod Q -pl)(e -q? to M13 -% -@ , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures desenbed in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures desenbed in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind ansing from or connected with this inspection.

l

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Commissionsk@E TM e R-M-1

. . _ . , . ~. ...,. .,_e .n. e e_ent.

Date lh-M 19 M l l l

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DCN,06

l l 1 l FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS l As Required by the Provisions of the ASME Code Section XI l

1. Owner Tennessee Valley Authonty (TVA) Date November 9,1998 1101 Market Street -

Chattanooga, TN 37402-2801 Sheet 1 of 1 Amarns j 2. Plant Browns Ferry Nuclear Plant (BFN) Unit 3 P. O. Box 2000 Decatur, AL 35609-2000 Work Order 98-000514 000 aoarns asp., orgamaanon P o No , ,JoD No , etc l

3. Work Performed by TVA-BFN Type Code Symbol Stamp N/A Name P. O. Box 2000 Decatur, AL 35609-2000 Authonzation No. N/A AadreSS Expiration Date N/A

4. Identification of System System 068. Reactor Water Recirculation System 5.(a) Applicable Construction Code USAS B31.1.0 19 67

• Edition, N/A Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 89 1

6. Identification of Components Repaired or Replaced and Replacement Components ASME Code National Repaired, Stamped Name of Component Name of Manufacturer Board Other identification Year Replaced, or (Yes or Manufacturer Senal No. No. Built Replacement No)

Snubber Pacific Scientific 13151 N/A 3-SNUB-068-5018 N/A Replaced No 3-SNUB-068-5018

7. Description of Work Replaced existing snubber with a new snubber.

8. Tests Conducted: Hydrostatic O Pneumatic O Nominal Operating Pressure 0 See notes.

Other O Pressure N/A psi Test Temp. N/A *F NOTE: Supplemental Sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8% in. X 11 in., (2) information in items 1 through 6 l on this report is included on each sheet. and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

! *ts amended by additonal quality assurance requirements found in Contracts 68C37-91602 & 85P73-835416 Release 1020 ,42 r 4 Design Critena BFN-50-7068 and BFN-50-C-7105.

13C8 08

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1 1

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FORM NIS-2 (Back) i 9. Remarks Replaced existing snubber with a new snubber (same manufacturer and model number). The new snubber was functionally tested Appucante Manufacturers Data Reports to De attached in accordance with 3-SI-4 6 H-2A.

I 1

i l

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code Section XI.

j Type Code Symbol Stamp N/A Certificate of Authonzation No. N/A Expiration Date N/A Signed

, d d /d M

~ ., ~ .,. n .e n .

, System Engineer Date

,/ /, 2,

,19 k 1

CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Ts: n M . and employed by%redd ETm. 9JP .4Mso. Mrs. /3A . of Mcs W rm M . G E N N. have inspected the components desenbed in this Owners Report dunng the penod' Q-3D-Q7 to +1 -- 2*7 -Q 2 . and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures desenbed in this Owners Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the Exarninations and corrective measures desenbed in this Owners Report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind ansing from or connected with this inspection.

3 . a inspectors Signature C. Commissions b 3 N M. ~ R_N3, Natmal Board. State. Provfhce, angf 6noorsements Date M-M 19 1

I 6

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l tl3C8,08 I

4

• 1 l

l FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS l As Required by the Provisions of the ASME Code Section XI 1

l

1. Owner Tennessee Valley Authority (TVA) Date November 9,1998 1101 Market Street I l

( Chattanooga TN 37402 2801 Sheet 1 of 1 l Aaar.u

2. Pfant Browns Ferry Nuclear Plant (BFN) Unit 3 P. O. Box 2000 Decatur, AL 35609-2000 Work Order 98-001448-E Aaarns Rep , org ma.cion p o no , soo No . etc

3. Work Performed by TVA-BFN Type Code Symbol Stamp N/A  ;

P. O. Box 2000. Decatur" AL 35609-2000 Authonzation No. N/A Adores.

Expiration Date N/A

4. Identification of System System 068. Reactor Water Recirculation System 5.(a) Applicable Construction Code USAS B31.1.0 19 67

• Edition, N/A Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 89 I

G. Identification of Components Repaired or Replaced and Replacement Components ASME Code National Repaired, Stamped Nameof Component Name of Manufacturer Board Other Identification Year Replaced, or (tes or Manufacturer Serial No. No. Built Replacement No)

Pipe Support TVA N/A N/A 3-47B465-2048 N/A Replaced No l

l

7. Desenption of Work Replaced studs and nuts on pipe clamp.

G. Tests Conducted: Hydrostatic O Pneumatic O Nominal Operating Pressure O visualinspecuens of boltino materials y ere performed.

I Other O Pressure N/A psi Test Temp. N/A 'F l

i NOTE: Supplemental Sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8% in. X 11 in., (2) information in items 1 througn 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

ts amended by additional quality assurance requirements found in Contracts 95N2G-108252 001, Release 1285773 and Design Cntena BFN-50-7068 and BFN 50 C-7105.

l a cs_o9 l

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FORM NIS-2 (Back)

8. Remarks Replaced the studs and nuts on the pioe clamp Performed visualinsoections of botting materials ApplCaDee Manufacturers osta Reports to be attacned CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the repair or rep 4.coment Type Code Symbol Stamp _N/A Certificate of Author 1tation No. N/A , Expiration Date N/A Signed

'~

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Owner or Ownefs Designes. Title

, System Engineer Date /f!.3d ,19

/

CERTIFICATE OF INSERVICE INSPECTION 1, the undeJrs' not holding a valid commission issued by the National Board of Boiler and Pressure Vessel inspectorr and the State or Province of a E A1M. and employed by Hg4EE3 sed E7ttr . Pir L ho, cs.h. (*n . of us M W ttA_ P/S u M. a ei have inspected the corriponents desenbed in this Owners Report dunng the p'enod afn . 4 QV to 'R. 2 -QS7 h 12/1ker , and state that to the best of my knowledge and belief, the Owner has performed examinations a6d taken corrective measures disenbed in this owners Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concoming the examinations and corrective measures described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any pomonal injury or property damage or a loss of any kind ansing from or connected with this inspection.

..pe-. --. Commissions hb36.TM. ~. - R-rd. M-T.

s -. - ,- e-12 - 2 Date 1/ ass ~

%S 19 N YY p l

I I l

i 1

l ncs 09 j

i l FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS l As Required by the Provisions of the ASME Code Section XI i

1. Owner Tennessee Valley Authonty (TVA) Date August 9,1998 i N.m.

1101 Market Street

)

Chattanooga, TN 37402-2801 Sheet 1 of 1 AGGreta

2. Plant Browns Ferry Nuclear Piant (BFN) Unit 3 P. O. Box 2000 Decatur, AL 35609-2000 Addresa Work Order h255 000 Repet Organgaton P o No , JoD No . etc

/ g

3. Work Performed by TVA-BFN Type Code Symbol Stamp N/A N.m.

P. O. Box 2000, Decatur, AL 35600-2000 Authonzate No. N/A l

A0 dress l Expiration Date N/A

4. Identification of System System 073, High Pressure Coolant injechon (HPC ) System l

5. (:) Applicable Construction Code USAS B31.1.0 19 67

• Editior, N/A Addenda, .N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 89

6. Idenbfication of Components Repaired or Replaced and Replacement Components ASME Code National Repaired, Stamped Name of Component Name of Manufacturer Board Other identification Year Replaced, or (Yes or Manufacturer Sertal No. No. Built Replacement No)

HPCI Turbine Exhaust Fake Metal Products Lot # N/A 3-RPD-0734713 1997 Replaced No inner Rupture Disc 16-CPV-C-BT 9723640

7. Desenption of Work Replaced rupture disc on turtxne exhaust.

8. Tests Conducted: Hydrostate O Pneumatic 0 Nominal Operating Pressure @

Other O Pressure N/A psi Test Temp. N/A *F I

i NOTE: Supplemental Sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8% in. X 11 in , (2) information in items 1 through 6

on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

• as amended by additional quality assurance requirements found an Contracts 70C53-92291-7,221688 and Design Cntens BFN-SO 7073 and BFN-50-C-7105.

t:3Cs 02

]

FORM NIS-2 (Back)  ;

I l

i

9. Remarks This activity is a normal. penodic replacement and inspection of the n.ipture disc required by ASME/ ANSI OM 10 and controlled by l Apowaos. Manufactur.rs oata R to b. attach.d i the BFN Preventive Maintenance Program. This rupture disc was replaced ea as a conservative action foHowing identified degradation on a l I

Unit 2 HPCI rupture disc (ref. BFPER 980479). No degradation was identified dunng inspection of the rupture disc removed during this subject activity.

1 CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the

' * " ~

• ASME Code Secten XI.

Type Code Symbol Stamp N/A Certificate of Authorcation No. N/A Expiration Date N/A Signed - 7 / / /IM os.rs,oa.r.c6.., .im.

. System Engineer Date 3-fk- -

, 19 CERTIFICATE OF /NSERVICE INSPECTION 1, the undersign holding a valid comrnission issued by the Ne' pal Board of Boiler and Pressure Vessel inspectors and the State or Province of

////7[d/h, C T r and empioved by 8.7AI(E of have inspected the components desenbed in this Oiwiers Report dunng the penod  %-/ 8- 98 to '/-/ 9- 97 , and state that to the best of my knowledge and belief, the Owner'has performed examsnations and taken corrective measures desenbod in this Owner s Report in accordance with the requirements of the ASME Code. Secten XI.

By signing this certificate neither the Inspector nor hra ertiployer makes any warranty, expressed or implied, concoming the examinations and corrective measures desenbod in thrs Owners Report. Furthermore, netther the inspector nor his employer shall be liable in any manner for any personalinjury or property damage or a loss of any land ansing from or connected vnth this inspection

_ . ,. a .

Commissions 7M 3/3[ ,__s_s_._.___.

C.,. 4 u ,, y l

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FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS j As Required by the Provisions of the ASME Code Section XI I

i

1. Owner Tennessee Valley Authonty (TVA) Date November 9,1998 1101 Market Street Chattanooga. TN 37402 2801 Sheet 1 of 1 Aooreu I l

2. Plant Browns Ferry Nuclear Plant (BFN) Unit 3  !

l P. O. Box 2000, Decatur, AL 35609 2000 Work Order 98-003270-000 l Aaaress Repair organganon P O No , Joe No . etc l

3 Work Performed by TVA-BFN Type Code Symbol Stamp N/A  !

Nam.

l P. O. Box 2000, Decatur, AL 35609-2000 Authonzation No. N/A l

Aagress Expiration Date N/A

4. Identification of System System 071 Reactor Core Isolation Cooling (RCIC) System l

5. (a) Apphcable Construction Code USAS B31.1.0 19 67

• Edition, N/A Addenda, N/A Code Case l

(b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 89  ;

l

6. Identificaten of Components Repaired or Replaced and Replacement Components i

ASME Code l National Repaired, Stamped Name of Component Name of Manufacturer Board Other Identification Year Replaced, or (Yes or l Manufacturer Senal No. No. Built Replacement No) l

RCIC Turbine Exhaust Fike Metal Products N/A N/A 3-RPD 0710011 A Replaced No Rupture Disc 8-CPV-C-BT l

I

7. Desenption of Work Replaced rupture disc on turbine 9xhaust.

D. Tests Conducted: Hydrostatic O Pneumaf : O Nom!nst Opersting Pressure @

Other O Pressum N/A psi Test Temp. N/A 'F l

l NOT E: Supplemental Sheets in form of hats, sketcf.ez, N drse.ogs may be used, provided (1) size is 8% in. X 11 in., (2) information in items 1 through 6 on (nra report is included on each sheet, and (3) eG 'W is numbered and the number of sheets is recorded at the top of this form.

• al amended by additional quality assurance requirements found in Contracts 70C53-92291-7 & 89NJL-80177B (ref PEG pkg 9600000598).

( and Design Criteria BFN-50-7071 and BFN 50-C 7105.

{

l i

l i

U3 Cit-ii

1 l

l l

l FORM NIS-2 (Back)

9. Remarks This activity is a normal penodx: replacement and inspection of the rupture disc required by ASME/ ANSI OM.10 and controlled by AppiscatHe Manufacturers Data Reports to os attachea the BFN Preventive Maintenance Program. This rupture disc was replaced early as a conservative action following identified degradation on a Unit 2 HPCI rupture dise (ref. BFPER 980479). No degradation was identified dunng inspection of the rupture disc removed dunng this subject activity. -

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replaced conforms to the rules of the ASME Code Section XI.

Type Code Symtr,t Stamp N/A Certificate of Authonzation No. N/A E.xpiration Date N/A Signed ,((A Mj , System Engineer Date / 3d ,19 r wer or ownse. De gnes rm. /

CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of TE nu , and employed by FM*sTtT,-h4 Ern. 'URLD .,-TM*m. 4 -TM4 M. of un2rr t r.M_ c' man have inspected'the components desenbed in this Owner's Report dunng the penod 4 - t,1 W to .t c . o -Q'9 , and state that to the best of my knowledge and belief, the Owner'has ' performed examinatens and taken corrective measures desenbed in this Owners Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and correedve measures described in this Owners Report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any land ansing from or connected with this inspection.

r . - Commissions kW TM. - R-N-1 inspectors Signature Natmnas Board. State Prownce. and Endorsements Date M -@ 19 6 t

l

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FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 1, Owner Tennessee Valley Authonty (TVA) l Date August 28,1998 l Name l 1

l 1101 Market Street ' ,

- t l

Chattanooga. TN 37402 2801 Sheet 1 of 1 Address

2. Plant Browns Ferry Nuclear Plant (BFN) Unit 3 P. O. Box 2000, Decatur, AL 35609-2000 Work Order 98-005505-007 Address Repair orgamzaban P o No , JoD No . etc

3. Work Performed by TVA-BFN Type Code Symbol Stamp N/A Name l P. O. Box 2000, Decatur, AL 35609-2000 Authonzation No. N/A Address Expiration Da'e N/A

4. Identification of System System O73, High Pressure Crolant injection (HPCI) System G.(a) Applicable Con 2*ruction Code USAS B31.1.0 19 67

• Edition, N/A Addends, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 89

6. Identification of Components Repaired or Replaced and Replacement Components ASME Code Natxmal Repaired, Stamped Name of Component Name of Manufacturer Board #)ther identification Year Replaced, or (Yes or Manufacturer Serial No. No. Built Replacement No)

HPCI System Cendensate Chapman / Crane N/A N/A 3-FCV C '3 0035 N/A Replaced No Test Valve L953WE 10X8X10 l

7. Description of Work Replaced bonnet, plug and stem with parts from the same Unit 1 us e.

8. Tests Condur:ted: Hydrostatic O Pneumate O Nominal Operating fressure @

l Other O Pressure N/A ,_ psi Test Temp. N/A *F l

l NOTE: Supplemental Sheets in form of lists, sketches, oc or wvings may be used, provided (1) size is 8% in. X 11 in., (2) information in items 1 through 6 on this report is included on each shoct, and (') each styset is numbered and the number of sheets is recorded at the top of this form.

• as amended by additional quality assurance requiturrs foad in Contracts 90744 & 91750-12, and Design Cntena BFN-50-7073 and BFN-50-C-7105.

l 13C8 03 l

G6 .

FORM NIS-2 (Back)

O. Remarks Replaced bonnet, plug and stem with parts from the same Unit 1 valve Stem was bent durino valve actuator testing The valve Apphcable Manufacturers Data Reports to be attached was inspected for other indications of damage. No pressure retaining parts were identified as damaged.

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code Section XI.

Type Code Symbol Stamp N/A Certificate of Authonzation No. N/A . Expiration Date N/A Signed MJM// , System Engineer Date , 3- ,1g

[ ~ Gwner or Owneis DenVnes. Tme CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, hoiding a valid commission issued by the National Board of Boiler and Pressure Vesselinspectors and the State or Province of i G. M M , and employed by l4Miih~e04 Em,'RtB ,MkcMub 8D . of

~ ~

54m dTh oA FANm have inspected the componerits desenbed in this Gwner's Report dunng the'penod M ' "An 'C9 to 4i I4Q 49 , and state that b the best of my knowledge and belief, the Owned has porformed examinations and taken\;orre ettve measures desenbod in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concoming the examinations and corrective measures described in this Owner's Report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind ansing from or connected with this inspection. "

i o . -O' inspectora s.enature Commissions MMt R-N-1 Ns6 anni soara. '+1te. Provmce, and Encornements Date ii-19 ig @

l I

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4 U3cs_03 r

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI

1. Owner Tennessee Valley Authordy (TVA) Date November 9,1996 1101 Market Street

, Chattanooga, TN 37402-2801 Sheet 1 of 1 I l Aoor I

2. Plant Browns Ferry Nuclear Plant (BFN) Und 3 P. O. Box 2000. Decatur. AL 35609-2000 Work Order 98-010357 000 Andress Repair Organnaton P O No , JoD No . etc

3. Work Performed by TVA-BFN Type Code Symbol Stamp N/A P. O. Box 2000, Decatur) AL 35609 2000 Authonzation No. N/A A0 dress Expiration Date N/A

4. Identification of System System 069. Reactor Water Cleanup (RWCU) System i

5.(a) Appheaole Construction Code USAS B31.1.0 19 67* Edition, N/A Addenda, N/A Code Case l (b) Appucable Eddion of Section XI Utilized for Repairs or Replacements 19 89 i

6. Identifcation of Components Repaired or Replaced and Replacement Components ASME Code Natienal Repaired, Stamped Name of Component Name of Manufacturer Board Other Identification Year Replaced, or (Yes or l Manufacturer SenalNo. No. Built Replacement No)

I RWCU Sys Retum Anchor /Darhng W9223821 A N/A 3-FCV@9-0629 N/A Replaced No l Check Valve l

l

• l

7. Description of Work Replaced valve drse

8. Tests Conducted: Hydrostatic 0 Pr.eumatic 0 Naminal Operating Pressure @

Other O Pressure N/A psi Test Temp. N/A 'F i

NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8% in. X 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

• as amended by additional qualdy assurance requirements found in Contracts 97N2R-204635, and Design Cntena BFN-50-7069 and BFN-50-C 7105.

l t

l U3CK_14 I

i

i FORM NIS-2 (Back) i l

9. Remarks Replaced the valve disc with the vendor supplied part (same manufacturer and mode 0 Apphcacio Manufacturers Data Reports to De attached CERTIFICATE OF COMPLLANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the

' * ~ * * * * "

ASME Code Section XI.

Type Code Symbol Stamp N/A Certificate of Authonzation No. N/A Expiretton Date N/A Signed j[/M M , System Engineer Date ff,2. ,19

, ~ .t.c . n r.e CERTIFICATE OF INSERVICE INSPECTION

, I, the undergs ned, holding a vahd commission issued by the National Board of Boiler and Pressure Vesset inspectors and the State i or Provinca of TEhiM. and employed by HFFEagd Errt. stir. -ru-c. +Tra. eis of H R W h Eri Gew M , have inspected the components desenbed in this Owners Report dunng the peno'd 0 -m - Q 9 to < % -ife M , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures desenbod in this Owners Report in accordance with the requirements of the ASME Code,Section XI.

By s$ning this certificate netther the Inspector nor his employer makes any warranty, expressed or implied, conceming the examinations and corrective measures desenbod in this Owners Report. Furthermore, nefther the inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind ansing from or connected with this inspection.

. s mspectors Sqnature 0 - Commissions b b T hl. N - [\I. 1 tutionsa board. State. Prowmco. and Encorsements Date _ _ _ Q -T(o 19 M i

I O CN 14 l _. - _ _ _ _ _ _ - - _ _ - _ _ _ _ _ _ _ _ - - _ _ -

- . - . . - . . .. . - . - - _ . - ... ~. . . . . . . _ . - . . .. . . . .

l ENCLOSURE 3 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)

UNIT 3 AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME),

l SECTION XI, REPAIR AND REPLACEMENTS PROGRAM CORRECTED (NIS-1) DATA FOR CYCLE 5 OPERATION i

l l (SEE ATTACHED)

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I OWNER: TENNESSEE VALLEY ALTTHORITY PLANT. BROWNS FERRY NUCLEAR PLANT j

OFFICE OF NUCLEAR POWER PO BOX 2000  !

!101 MARKET STREET DECATUR, ALABAMA 35602 '

CHATTANOOGA, TENNESSEE 37402 UNIT. THREE CERTIFICATE OF ACTIBORIZATION: NOT REQUIRED l COMMERCIAL SERVICE DATE: MARCH 1,1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED.

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SUPPLEMENTAL SUBMITAL 1

The BFN unrt 3 reactor pressure vessel exanunation from the inside surface utilizing a remote

' scannmg device was conducted in 1993. Numerous indications were recorded and evaluated and the results submitted with the Inservice Inspection Summary Report. A later review idenufied errors in the data. The corrected data is included in this submrttal. This issue wu addressed in accordance with the TVA Corrective Action Program under Problem Evaluation Report (PER) #

l 98-007812-000.

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GE Nuclear Energy uoei.., s.~e., %.n,,,,,,t Nonconformance Report NCR No.: 1 HAYV-01 Project: TVA, Browns Ferry Nuclear Plant. Unit-31993 GERIS 2000 ID Project No.: 1HAYV RPV Exams Reference Documents: GE-UT-700 Revision 2 Nonconforma nce Description (State Cause. System. Locasson. Component ID. etc)

Documentation errors were identified in welds RPV-C-3-4 and RPV-V-4-B. Examination summary sheets and indication evaluation sheets were affected.

NCR Code: 051 Cause Code: G04 10CFR21 Review: O Is Ols Not Reportable./0CSuperuso,drierm,norson, Initiated By:

@ gg July 7,1998 Date:

QC Supervisor: Q -_

Date:

July 7.1998 Proposed Disposition and Technical Justification (Arioch Errra Sheers. Striches. Etc. as.Vecessary/

O ^ccept ^5 Is O Repair O Rework O Reject @ Other (if not material or items)

Correct documentation and resubmit to Browns Ferry, Project Manager: .

July 27,1998 Date:

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QC Supervisor: - - -

Date:

Final Disposition Accept-As-Is & Repair Disposition, Design Venfication is Provided Per:

Documentation resubmitted to Browns Ferry.

Client: afaegwred) QDkg Date: q,p,g ANI Review: wn,qwe,s> , , A Date:

Project Manager: k, g V Date: July 27. l998 QC Supervisor: M h, _ _

Date: July 7.1998 Presentative Action increase awareness of Data Analysts personnel to minimize typographical errors in data sheets.

July 7. l998 QC Supervisor: Date:

CLOSURE g Disposition Completed And Nonconformance Report Closed July 27.1998 QC Supervisor: , ' ' ~-

Date:

ANI: (if Ragwred)

Attachments:

Date: fW es O No Page / of_ 'l TVA-NCR 15/96

O GE Nuclear Energy Generet Ew Comoeny Browns feny Nuceer Pfant P o Box 2000. oecens. AL 35600 July 27,1998 Hal Hodges WA Browns Ferry Nuclear ISI Supervisor

Subject:

BFN-3 RPV ID Examination Report Corrections This memorandum is intended to clarify the findings during a recent review of the Browns Ferry Nuclear Unit 3 RPV examination results. The BFN Unit 3 RPV examination from the inside diameter was conducted in 1993 and resulted in numerous indications being recorded and evaluated. Another review of the data was conducted after obvious mistakes were found recently relating to indication number 12-015 which was recorded on welds C-3-4 and V-4-8. Two additional independent reviews of the data were performed by GENE personnel to assure accuracy of the information. These reviews were limited to welds that contained recordable flaw indications.

This recent review included welds V-4-8, C-2-3, C-3-4, C-4-5, and C-5-FLG with welds C-2-3, C-4-5 and C-5-FLG resulting in no errors being identified. Many of the summary sheets indicate rounded values although the calculations were performed with absolute values. Therefore to mathematically ven'y accuracy of the calculations on the summary sheets, the supporting documentation contained within the final report is required. The findings and changes to the

" Summary Sheets" for V-4-8 and C-3-4 are as follows.

Wold Indication # Changes Comments V-4-B 12-015 Z-pos changed from 1.13' to 1.16' Typo error V-4-B 12-015 S-pos. changed from 0.94* to 0.75' Clad "T" included in "S" V-4-B 12-015 T-wall changed from .44' to .444' Rounding C-3-4 12-069 T-wall changed from .34' to .339' Rounding C-3-4 12-116  % a/t allowed changed from 3.5 to 3.96 Math error C-3-4 12-144 Z-pos. changed from 0.78' to 1.10" Math error C 3-4 12-144 all changed from 0.10 to 0.08 Rounding C-3-4 12-145 "S" changed from 2.40" to 0.42' Transposition of "L' value for"S"

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l C 3-4 12 145 all changed from 0.10 to 0.08 Rounding l C 3-4 12 148 all changed from 0.10 to 0.09 Rounding The following changes were made to the " Indication Evaluation Sheets

• Weld Indication # Changes Comments l V-4-B 14-002 Separation "S" values corrected Nominal clad T included 2X for separation with clad "S" and nominal clad T included for surface separation "S*

C 3-4 12-116 Allowed "a" dim. changed from Typo errors12-117 0.227" to 0.257" l

l Additionally statements were added to the summary sheet for weld C-3-4 to clanfy the calculations performed in accordance with IWA-3390 for indication 12-116. The above mistakes were corrected and the data sheets submitted to TVA for inclusion into the final report. Although several mistakes were found, these mistakes do not change the reportability of the indications. If  !

you have any additional questions please call me at 931-596-3767.

I Sincerely Ricky Seals GENE BFN ISI PM cc: F. Hartwig C. Minor G. Nelson M. Sodemann eli

& GE Nuclear Energy GERIS 2000 Examination Summary Sheet Project; TVA. Browns Ferry Nuclear Plant. Unit 3 Systern; Reactor Pressure Vessel 1

WeldID: C-3-4 ASME Code Category: B-A l Calibrat/on Sheets c 001. C-004. C 115. C 116 and C 117 i Support /ng Data: Examination Data Sheets E 12 00 thru E-1215, indication Data Sheets 12 001 inru 12-163.

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

GERIS 2000 Setup Records and Manual Data Sheets 0-034. D-035. D-036. D-037. D-040 D-041. D-044 and D-045.

Examination Summarv The ultrasonic examination of weld C-3-4 resulted in six (6) recorded indications that exceed the allowable standards of IWB-3500. A Section XI.1986 Edition. No Addenda.

l The ASME Section XI required examination volume was examined we the GERIS 2000 System from the RPV inside surface utthring 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 97%.

The GERIS 2000 utilizes an array of search units arranged to effectrveh examins the weld and adjacent base matenai 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 six (6) unacceptable indications were recorded and sized in accordance we GE-UT-700. Rev. 2 and GE-UT-701 Rev. 2 with the results tabulated below:

Ind. No. Onented Type X Pos Y Pos Z Pos "S* T wall Length 1 Moss all  % alt  % alt j Calculated Allowed l 12-015 circ. subsurface 94.35' 525.43" 1.16 .75* 444* 1.75* 6 53* 0 13 34 2.71 l l

12-069 cire. subsurface 424 65* 524.58* 2.30* 1 94* .339* 1.75* 6 51' O.10 l 2 66 l 2.48 i 12 116 cire. subsurface 617.15* 526.14' 3 85* 2.6 62* .75* 6 49" 0 21 l 4 81 { 3 96 l 12-144 cire. subsurface 760.10* 525.11* 1.10' . 75* 325* 2.00* 6 63* 0 08 l 2 45 l 2 39 l 12-145 cire. subsurface 763.85* 525.68* 80* . 4 2" 39' 2.40" 6 44" 0 08 3 03 2 39 l 12-148 cire. subsurface, 771.35* 525.07* 87* 43* 511* 2.75* 6 44" 0 09 3 97 2 46 l Indication 12-015 was sized with 70* RL channel 5 utilizing the PATT technique. This indication was also recorded as 12 016 and 12-020. Indication 12-015 was also recorded wenn the exam volume of weid V 4-B.

Indication 12 069 was sized we 45' shear wave channel 9 utilizing the SPOT technique.

Indication 12-116 and 12117 is a combined indication in accordance we IWA-3390 and is included in the tabie above as12-116.

The individual parameters for indicatsons 12116 and 12117 are as follows indication 12-116 T wall = .311* ; all = 0 21 ; alt % allowed = 3.37% ; alt % calculated = 2.40%

Indication 12117 T-wau = .311' : a/I = 0 31 ; a't% allowed = 4 55% ; alt % calculated = 2.40%

lWA-3390 calculations (ai+a2)</= (a.+a'e)/2 or (.156*+.156*) </= ((6.49* 0337)+(6.49*.0455)/2 which = 312 </= 257 Indication 12116 calculations in accordance we IWA-3390 T-wau = 62* ( 312 *2), all = 0.21"(aspect ratio for longest individual flaw) .

% a/t calculated = 4 81 ( 312 / 6 49) ; % alt allowed = 3.96 ( 257/ 6 49) l GERIS Analyst: GE Revower- f LEVEL: DATE. N LEVEL: *K DATE1/37/98

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UTILITY Reve ANil Revew:

TITLE. DATE: TITL _ ~

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GERIS 2000 Excmim; tion Summcry

\ (Continuation)

I Indicaten 12116 and 12-117 were sized with 45' shear wave channel 7 utilizing the SPOT technque.

i Indication 12144 was sized with 70* RL channel 5 utilizing the PATT technque. This indication was also recorded as and 12157. 12 130.12 150.

I Indication 12145 was sized with 70* RL channel 4 utilizing the PATT technque. This indication was also recorded as 12 131.12 158.

12161.12-162 and 12163.

' Indication 12-148 was sized with 70* RL channel 5 utilizing the PATT technque. This indication was also recorded as 12132 and 12 160.

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

Selected areas were rescanned using 45' RL search units .

l The manual technque utilized 0* longitudinal,45' and 60* shsar wave search units both parallel and perpendicular to the weld axis in two directions to effectrvely examine the weld and adjacent base matenal.

No indications were recorded with the manual technque.

Fabncation records and previous examination results were reviewed pnor to the compietion of this examination summary.

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Surenary revised 6/11/98.

Ind 'i2-069 throughwall dimension corrected.

Inc.12-116 % a/t Allowed corrected.

Ind.12-144 Z Pos and all corrected.

i Ind.12-145 "S and all corrected.

l' Ind.12144 a/I corrected.

Added explanation for 12-116 calcu!stions i

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O GENuclearEnergy GERIS 2000 Indication Evaluation Sheet Project TVA, Browns Ferry Unit 3 Exam Data Sheet No.: E-12-12 WeldID: C-3-4 Ind. Data Sheet No.: 12116 Patch: BF-036 Indication: 12 116 Flaw ThruwellOlmension = 0.311 7 measurwd = 6.49 Flew Length "I" = 0.75 Clad Tnominsi = 0.19 Separation with clad *S* = N/A Surface Separation *S* = 2.60 Flaw is unacceptable by Table IWB-3510-1 and IWA-3390 l ASME Section XI,1986 Edition j TABLE IWB 3510-1 for 4" to 12" I

all Surface % bsurfam Surfam % Subsurfam %

0.00 1.90 2 - -

0.05 2.00 2.2 - -

! 0.10 2.20 2.5 - -

i 0.15 2.50 2.9 - -

0.20 2.80 3.3 2.87 3.37 Y j 0.25 3.30 3.8 - -

0.30 3.80 4.4 - -

0.35 4.40 5.1 - -

l 0.40 5.00 5.8 - -

l 0.45 5.10 6.7 - -

0.50 5.20 7.6 - -

l Allowed Allowed j 2.87 3.37 I

l a= 0.156 a/l value = 0.207 l Y= 1.000 Flaw is Subsurface l

Allowed a/t = 3.37 %

alt = 2.40 %

Comments: Ind.12116 combines ein Ind.12-117 in accordance mth the rules of IWA 3390.

, a e actual a dimensen if (12116 a + 12117 a) < ((12116 e +12117 e))/ 2 then. Flaw is acceptable.

e = allowed a dirnension (.156 + .156) < ((6.49 * .0337) + (6.49 * .0455)) / 2

312 < .257 i Revised 6/11/S0 Combined inecation 12-116 is unacceptable to IWB-3510-1.

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@ GENuclearEnergy GERIS 2000 Indication Evaluation Sheet l

Profect: TVA, Browns Ferry Unit 3 Eram Data sheet No.: E-12-12 r WeldID: C-3-4 Ind. Data Sheet No.: 12-117 Patch: BF 0% Indication: 12117 Flaw ThruwallDimension = 0.311 Tmeasured = 6.49 i

Flaw Length "I" = 0.50 Clad Tnominal = 0.19  !

l Separation with clad 'S' = 2.95 Surface Separation 'S' = 2.76 Flaw is unacceptable by Table IWB-3510-1 and IWA-3390 l ASME Section XI,1986 Edition .

1 TABLE IWB-35101 for 4" to 12" i aA Surfam % bsurface Surface % Subsurface % i 0.00 1.90 2 - -

l 0.05 2.00 2.2 - -

0.10 2.20 2.5 - -

0.15 2.50 2.9 - -

)

0.20 2.80 3.3 - -

0.25 3.30 3.8 - -

0.30 3.80 4.4 3.93 4.55 Y 0.35 4.40 5.1 - -

j 0.40 5.00 5.8 - -

0.45 5.10 6.7 - -

0.50 5.20 7.6 - - l Allowed Allowed j 3.93 4.55  !

a= 0.156 a/I value = 0.311 Y= 1.000 Flaw is Subsurface Allowed alt = 4.55 %

alt = 2.40%

Comments: ind.12116 combines with ind.12117 in accordann witn the raies of IwA-3390.

a = actual a dimensa if (12116 a + 12117 a) < ((12-116 e +12117 e)) / 2 then. Flaw is acceptab6e.

e = allowed a dimension (.156 + .156) < ('S.49 * .0337) + (6.49 * .0455)) / 2

.312 < .257 l

l Revised 6/11/98 Combined indice6an 12-116 is unacceptable to IWB 3510-1.

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m W GERIS 2000 Examination l GE Nuclear Energy Summary Sheet l

Project: TVA, Browns Ferry Nuclear Plant, Unit 3 System: Reactor Pressure Vessel WeldID: v-s.8 Asafe code canegory. BA Calibration Sheets: C-001 Suppciting Data: Examinanon Data Sheets E 14 00 and E 14-01, Indicanon Data Sneets14-001 thru 14 005 and G-100 tnru G-108, Indicacon Evaluanon Sheets, Screen Pnnts, Exam Patch Locanon Map, Exam Coverage Plots and GERIS 2000 Setup Records.

Examination Summarv The ultrasonic examinabon of weed V-4-8 resulted in one (1) recorded indicanon that exceeds the allowable standards of IWB-3500, ASME Section XI,1986 Edison, No Addenda The ASME Secton XI required examinabon volume was examined uth 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 examinanon coverage was calculated to be 83%.

The GERIS 2000 utilzes an array of search units arranged to effacevely examine the weed and adjacent base material parallel and perpendicular to the weed axis in two direccons The transducer package consisted of O' longitudinal,45* and 60* shear wave, and 70*

refracted longitudinal (RL) wave search units.

The one indicanon evaluated as bemg reportable to (WB-3500, ASME Seedon XI,1986 Edition, No Addenda was recorded and sized in accordance with GE-UT-700, Rev. 2 and GE-UT-701, Rev,2. This indication was recorded during the exarninacon of bcth welds V-4-8 as 14 002 and C-3-4 as12-015. The flaw dimenssons were determined from weld C-3-4 Indication Data Sheet 12-015 eth the results tabulated below:

Ind. No. Ononted Type X Pos Y Pos Z Pos *S* T wall Length T Meas all  % alt  % alt Calculated Allowed 12 C' . cire. subsurface 94.35' 525.43* 1.16* 0.75* 444* 1.75* 6.53* 0.13 3.4 2.71 This indicanon was sized with the 70*RL unitzing the PATT technique it was also recorded with the 45* and 60* shear waves.

The GERIS 2000 also recorded an indicaton with the 0* weld metal scan that was evaluated and found to be acceptable per the referenong Code secnon Geometric indicagons from the stabilizer bracket at 45' were recorded with the 0* weld metal,45* and 60*

shear wave scans.

No manual supplemental examination was HL,M from the RPV outside surface due to access restricsons.

Fabrication records and previous examinston results were reviewed prior to the comple6on of this examinanon summary.

Summary revised 6/11/98. Ind.12 015 Z Poe, *S*, and throughwell dimensions corrected GERIS Analyst GE eviewer-

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.A UTILITY Review:

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GERIS 2000 Indication l GE Ntsclear Energy 4

Evaluation Sheet Project TVA, Browns Ferry Unit 3 Exam Data Sheet No.: E-14-01 WeldID: V-4 B Ind. Data Sheet No.: 14 002 Patch: BF-048 Indication: 14-002 Flaw ThruwallOlmension = 0.444 Tmeasured = 6.53 \

Flaw Length "I" = 1.75 Clad Tnominal = 0.19 l Separation with clad "S" = 0.94 Surface Separation 'S' = 0.75 4

Flaw is unacceptable by Table IWB-3510-1 i

ASME Section XI,1986 Edition I i

TABLE IWB-3510-1 for 4" to 12" l l l

l all Surface % bsurface Surface % Subsurface % 1 1

0.00 1.90 2 - -

l 0.05 2.00 2.2 - -

0.10 2.20 2.5 2.36 2.71 Y 0.15 2.50 2.9 - -

O.20 2.80 3.3 - -

0.25 3.30 3.8 - -

0.30 3.80 4.4 - -

0.35 4.40 5.1 - -

0.40 5.00 5.8 - -

0.45 5.10 6.7 - -

0.50 5.20 7.6 - -

Allowed Allowed 2.36 2.71 a= 0.222 all value = 0.127 Y= 1.000 Flaw is Subsurface Allowed a/t = 2.71 %

alt = 3.40 %

Comments: The size of this indication was determined with information from Examination Data Sheet No. E 12-02: Indicaten Data Sheet No.12 015.

Revised 6/11/98 Separation "S" values corrected.

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l l' ENCLOSURE 4 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)

UNIT 3 i AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME),

SECTION XI, INSERVICE INSPECTION (ISI) AND REPAIR AND REPLACEMENTS PROGRAM

SUMMARY

REPORTS FOR CYCLE 8 OPERATION COMMITMENT

SUMMARY

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TVA will submit a request for relief for BFN Unit 3 by April 5, 1999, to address the reduced nondestructive j examination coverage for nine ASME,Section XI, Inservice '

Inspection, Reactor Pressure Vessel nozzle welds (ASME Section XI Code, Category B-D).

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