ML20080G858
| ML20080G858 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 11/16/1994 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20080G855 | List: |
| References | |
| NUDOCS 9502100088 | |
| Download: ML20080G858 (464) | |
Text
{{#Wiki_filter:3, _ _ . _ J i SEQUOYAH NUCLEAR PLANT UNIT 2 CYCLE 6 FORM NIS-1 OWNER'S DATA REPORT FOR ' INSERVICE INSPECTIONS i i i i l I Prepared by % _) k' - NDE Specialist Reviewed by. [ ' Iff/[DEProgramENGR Reviewed by l/d Y NDE Lev II j Reviewed by -- cJ '" s ISI/NDTSpecialist Approved by_. ISI/NDE Supervisor ! 9502100089 950206 PDR ADOCK 0500 3 9 Q l
'f; OWNER: TENNESSEE VALLEY AUTHORITY- PLANT: SEQUOYAH NUCLEAR PLANT NUCLEAR POWER GROUP P.O. BOX 2000 1101 MARKET ST SODDY DAISY, TENNESSEE CHATTANOOGA, TENNESSEE 37402- 37379 1
UNIT: TWO CERTIFICATE OF AUTHORIZATION: NOT REQUIRED i COMMERCIAL SERVICE DATE: JUNE 1, 1982 j NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED j r ! l M APPENDIX NUMBER TITLE APPENDIX I NIS-1 OWNERS DATA REPORT APPENDIX II SCOPE APPENDIX III ISI
SUMMARY
l APPENDIX IV EXAMINATION PLAN j Part A: Po'st Outage ISI Report Part 3: 7.eexaminations Part C: Additional Samples APPENDIX V
SUMMARY
OF STEAM GENERATOR TUBING EXAMS TO ASME SECTION XI l APPENDIX VI
SUMMARY
OF NOI'S/ WESTINGHOUSE ! FLAW EVALUATION j i APPENDIX I-VI EFFECTIVE PAGES 1-141 ATTACHMENT 1 AUGMENTED EXAMINATIONS EFFECTIVE PAGES 1-9 VOLUME 2 NIS-2 " OWNERS DATA REPORT FOR REPAIR OR REPLACEMENT" l
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3 i OWNER: TENNESSEE VALLEY AUTHORITY PLANT: SEQUOYAH NUCLEAR PLANT l NUCLEAR POWER GROUP P.O. BOX 2000 ; 1101 MARKET ST SODDY DAISY, TENNESSEE : CHATTANOOGA, TENNESSEE 37402 37379 ' UNIT: TWO- CERTIFICATE OF AUTHORIZATION: NOT REQUIRED COMMERCIAL SERVICE DATE: JUNE 1, 1982 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED i APPENDIX I ( NIS-1 OWNERS DATA REPORT UNIT 2 CYCLE 6 i l l t b i I t i I. i I PAGE l i i
4 FORM NIS 1 OWNERS *' DATA REPORT FOR INSERVICE INSPECrlONS : As rzgrired by tio Pr:visi:ns of the ASME C:d Rules
; g' Tennessee Valley Authority g, o.vner Nuclear Power Group, 1101 Market Street, Chattanooga, TN 37402-2801 (
(Name and Address of Owner)
- 2. Plant Seouoyah Nuclear Plant. P.O. Box 2000. Enddy-Dninv TN 17 t70 (Name and Address of Plant)
- 3. Plant Unit 2
- 4. Owner Certificate of Authorization (if required) 'Not required
- 5. Commercial Service Date 6 /01/ A7 6. National Board Number for Uni Not recuired
- 7. Components inspected Manufacturer ,
Component or Manufacturer or installer State or National Appurtenance or Installer Serial No. Province No. Board No. Reactor 68C60-91934 Vessel Westinghouse N2M-2-3 NA NA Steam 68C60-91934 Cenerator_ _ Westinnhouse N2M-2-4 NA NA 6BC60-91934 Pressurizer Westinghouse N2M-2-6 NA ' NA 5 i
*See Appendix IV Examination Plan i
I I Note: Supplemental sheets in form of lists, sketches, or drawings may be used provided (l) site is 8% in. x 1I in., (2) information in items I through 6 on this data 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. x .- This form (E000291 rney be obtained from the Order Dept., ASME. 345 E. 47th St., New Yor k, N.Y. 10017 PAGE 1 .-
i FORM NIS 1 (back) e
- N
% Examination Dates 5-17-92 to 11-16-94 p. Inspection Interval from 6-01-82 to 10-lh95 IG Abstract of Examinations. Include a list of examinations and a statement concerning status of work re for current interval. See Appehdix IV, V, and VI
!!. Abstract of Conditions Noted. See Appendix II thru VI
- 12. Abstract of Corrective Measures Recommended and Taken See Appendix VI We certify that the statements made in this report are correct and the examinations and corrective mes-sures taken conform to the rules of the ASME Code Section XI.
Date 11U4AY 2 19 9 5 Signed TVA By . Owner W! () Certificate of Authorization No. (if applicabic) NA Expiration Date NA CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued by the National Board Inspectors and/or the State or Province of. Tennessee ila ' _llg_tti.ord. CT and employed by g,rk hYd* bait!'h'iYe'[*f pectmen i 3 , cc ,o 5-17-92 have11-16-94 to inspected the components described in this Owners' Data Report during the period ,
. and state that to the best of my knowledge and belief, the Owner has petformed examinations and taken corrective measures described in this Owners' Data Report in with the requirements of the ASME Code, Section XI.
- By signing this certificate neither the Inspector por his employer makes any warranty, expres concerting the examinations and corrective measuies described in this Owners' Data Report. Furthermore neither she Inspector nor his employer shall be liable in any manner for any personal injury or a loss o.'eny kind arising from or ennnected with this inspection.
Date / _ _ 19 _ . _^/aw f I6.spector's Sign'aturc Commissinns I#[ M4/_I
National Board, State, Province and No.
PAGE 3 -
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% j OWNER: TENNESSEE VALLEY AUTHORITY PLANT: SEQUOYAH NUCLEAR PLANT l NUCLEAR POWER GROUP P.O. BOX 2000 l 1101 MARKET ST SODDY DAISY, TENNESSEE l CHATTANOOGA, TENNESSEE 37402 37379 UNIT: TWO CERTIFICATE OF AUTHORIZATION: NOT REQUIRED ,
COMMERCIAL SERVICE DATE: JUNE 1, 1982
~
NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED 1 1 i i APPENDIX II SCOPE 1 i t I L I
*se" PAGE 4 l
i I 1 m l OWNER: TENNESSEE VALLEY AUTHORITY PLANT: SEQUOYAH NUCLEAR PLANT NUCLEAR POWER GROUP P.O. BOX 2000 1101 MARKET ST SODDY DAISY,. TENNESSEE CHATTANOOGA, TENNESSEE 37402 37379 UNIT: TWO CERTIFICATE OF AUTHORIZATION: NOT REQUIRED ? COMMERCIAL SERVICE DATE: JUNE 1, 1982 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED Scope: The scope of this appendix is to provide an overview of the inservice inspections performed during Unit 2 Cycle 6 for Class 1 and 2 components.
Introduction:
The Sequoyah Nuclear Plant Unit 2 Cycle 6 inservice inspections were performed during the period from May 17, 1992 to November 16, 1994. The Unit 2 Cycle 6 Refueling Outage began when the generator was taken off line on July 4,1994 and ended on November 16, 1994, when the generator was tied to the power grid. All NDE examinations were performed to the implementing plant Surveillance Instruction, 2-SI-SXI-000-114.0, "ASME Section XI Inservice Inspection (ISI) Program". , Examinations were performed by Southwest Research Institute (SwRI), ABB Combustion Engineering, GTS Duratek , and TVA personnel under the direction of the Site ISI/NDE Section. Westinghouse Corporation, accompanied by N.D.E. Technology and Scientific Technologies performed the steam generator tubing eddy current (ET) examinations. The Authorized Inspection Agency (AIA) services were provided by . Hartford Steam Bciler Inspection Insurance Company. v PAGE 6~
n OWNER: TENNESSEE VALLEY AUTHORITY PLANT: SEQUOYAH NUCLEAR PLANT NUCLEAR POWER GROUP P.O. BOX 2000 1101 MARKET ST SODDY DAISY, TENNESSEE CHATTANOOGA, TENNESSEE 37402 37379 UNIT: TWO CERTIFICATE OF AUTHORIZATION: NOT REQUIRED COMMERCIAL SERVICE DATE: JUNE 1, 1982 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED SECTION XI CREDIT- CYCLE 6 CLASS 1 COMPONENTS COMPONENT EXAM METHOD CODE CAT. SAMPLE NO. REACTOR VESSEL
- 1. Circumferential UT B-A 4(50')
Shell Welds
- 2. Closure Head UT B-A 14' Circ Weld
- 3. Lower Head UT B-A 38' Circ Weld
- 4. Lower Head UT B-A 6(4')
Meridional Weld
- 5. Shell-to-Flange UT B-A 50' Weld
- 6. a. Closure Head- UT B-A 15' to-Flange Weld
- b. Closure Head MT B-A 45' to Flange Flex Area.
- 7. Nozzle-to- UT B-D 8 Vessel Welds
- 8. Inside Radius UT B-D 8 Sections (Includes Integral Extensions on Outlet Nozzles PAGE 4
k s. t OWNER: TENNESSEE VALLEY AUTHORITY PLANT: SEQUOYAH NUCLEAR PLANT NUCLEAR POWER GROUP P.O. BOX 2000 ' 1101 MARKET ST SODDY DAISY, TENNESSEE ! CHATTANOOGA, TENNESSEE 37402 37379 UNIT: TWO CERTIFICATE OF AUTHORIZATION: NOT REQUIRED COMMERCIAL SERVICE DATE: JUNE 1, 1982 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED , COMPONENT EXAM METHOD - CODE C.'.T; SAMPLE NO.
- 9. Nozzle-to-Safe UT/PT B-F 8 i End Welds '
- 10. Closure Studs UT/MT B-G-1 18 and Nuts MT B-G-1 18 .
- 11. Ligaments UT B-G-1 18 Between threaded Stud Holes i
- 12. Closure Washers VT-1 B-G-1 18
- 13. Vessel Interior VT-3 B-N-1 1 ,
- 14. Removable Core VT-3 B-N-3 1 .
Support Structure ;
- 15. Control Rod UT B-O 1 i Drive Housing
- 16. RV Aux Head UT/PT B-F 2 l Adapters l Pressurizer l i
- 1. Nozzle-to- UT B-D 2 !
Vessel Welds l i I l PAGE 7 - l
i r i OWNER: TENNESSEE VALLEY AUTHORITY PLANT: SEQUOYAH NUCLEAR PLANT ! NUCLEAR POWER _ GROUP P.O. BOX 2000 i 1101 MARKET ST SODDY DAISY, TENNESSEE , CRATTANOOGA, TENNESSEE 37402 37379 i UNIT: TWO CERTIFICATE OF AUTHORIZATION: NOT REQUIRED i COMMERCIAL SERVICE DATE: JUNE 1, 1982 : NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED , I L i COMPONENT EXAM METHOD CODE CAT. SAMPLE NO. l STEAM GENERATORS !
- 1. Tubing ET B-Q
- l
- See Appendix V for Summary of Steam Generator Eddy Current !
examination. i EIEING ! A. Reactor Coolant UT/PT B-J 1 ! System Main Loop ! Cires >=4" l B. Reactor Coolant UT/PT B-J 1 l System Circs>=4" l Nom. Size ! REACTOR COOLANT PUMPS
- 1. Pressure VT-1 B-G-2 32 ,
Retaining Bolting i VALVES
- 1. Pressure Retaining :
Bolting j
- a. Safety VT-1 B-G-2 1 Injection System i
.d PAGE 8
h o- . OWNER: TENNESSEE VALLEY AUTHORITY PLANT: SEQUOYAH NUCLEAR PLANT ! NUCLEAR POWER GROUP P.O. BOX 2000 i 1101 MARKET ST SODDY DAISY, TENNESSEE CHATTANOOGA, TENNESSEE 37402 37379 - UNIT: TWO CERTIFICATE OF AUTHORIZATION: NOT REQUIRED ! COMMERCIAL SERVICE DATE: JUNE 1, 1982 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED SECTION XI CREDIT- CYCLE 6 CLASS 2 COMPONENTS COMPONENT EXAM METHOD CODE CAT. SAMPLE NO. HEAT EXCHANGERS
- 1. Residual Heat Removal Heat Exchangers :
- a. RHRHX UT C-A 1 Circumferential Shell Weld f
- b. RHRHX UT C-A 1 Circumferential Head Weld
- c. RHRHX Nozzle- PT C-B 2 to-Vessel Welds
- d. RHRHX PT C-C 1 Integrally Welded Support
- e. RHRHX VT-3 C-E 2 -
Component Support j l l l i PAGE 9
- -1
OWNER: TENNESSEE VALLEY AUTHORITY PLANT: SEQUOYAH NUCLEAR PLANT NUCLEAR POWER GROUP P.O. BOX 2000 1101 MARKET ST SODDY DAISY, TENNESSEE CHATTANOOGA, TENNESSEE 37402 37379 UNIT: TWO CERTIFICATE OF AUTHORIZATION: NOT REQUIRED COMMERCIAL SERVICE DATE: JUNE 1, 1982 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED COMPONENT EXAM METHOD CODE CAT. SAMPLE NO. TNLKS
- 1. CCP Tank (BIT)
- a. CCP Tank UT C-A 1 Circumferential Shell/ Head Weld
- b. CCP Tank MT/UT C-B 1 Nozzle to Vessel Welds
- b. CCP Tank MT C-C 2 Integrally Welded Supports
- c. CCP Tank VT-3 C-E 2 Component Supports P_iging
- 1. Integrally Welded Supports
- a. Main Steam MT C-C 3 System
- b. Feedwater MT C-C 2 System PAGE lo l
r-i
^ ,
i OWNER: TENNESSEE VALLEY AU.THORITY PLANT: SEQUOYAH NUCLEAR PLANT NUCLEAR POWER GROUP P.O. BOX 2000 ! 1101 MARKET ST SODDY DAISY, TENNESSEE ! CHATTANOOGA, TENNESSEE 37402 37379 ' UNIT: TWO CERTIFICATE OF AUTHORIZATION: NOT REQUIRED ' COMMERCIAL SERVICE DATE: JUNE-1, 1982 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED COMPONENT EXAM METHOD CODE CAT. SAMPLE NO.
?
Circumferential And Longitudinal Walds )
- a. Residual Heat Removal System !
- 1. RHR Cires UT/PT C-F 3 i
>1/2" Nom. '
Wall Thick. I
- 2. RHR Circs PT C-F 11 :
<=1/2 Nom.
Wall Thick. l
- 3. RHR Long UT/PT C-F 1 e
>1/2" Nom. '
Wall Thick. >
- 4. RHR Long PT C-F 7 t
<=1/2" Nom.
Wall Thick. l
- b. Safety Injection
- 3. SIS Circs UT/PT C-F 4 ,
>1/2" Nom. ^
Wall Thick.
- 2. SIS Circs i PT C-F 6 '
<=1/2" Nom.
Wall Thick l
- 3. SIS Long PT C-F 4 !
<=1/2" Nom. +
Wall Thick. ,
- c. Main Steam System !
- 1. MS Cires UT/MT C-F 2
>1/2" Nom.
Wall Thick. j i. 11 PAGE -
~ OWNER: TENNESSEE VALLEY AUTHORITY PLANT: SEQUOYAH NUCLEAR PLANT NUCLEAR POWER GROUP P.O. BOX 2000 1101 MARKET ST SODDY DAISY, TENNESSEE - CHATTANOOGA, TENNESSEE 37402 37379 UNIT: TWO CERTIFICATE OF AUTHORIZATION: NOT REQUIRED ; COMMERCIAL SERVICE DATE: JUNE 1, 1982 > NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED COMPONENT EXAM METHOD CODE CAT. SAMPLE NO.
- 2. MS Long UT/MT C-F 1
>1/2" nom.
Wall Thick.
- d. Feedwater System
- 1. FW Circs UT/MT C-F 2
>1/2" Nom. ,
Wall Thick. 9 P r Y f h a PAGE 12.
f i 1 i N eluum M N X k 4 1 1 1 1 I 1 I l l l 1 l
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'i OWNER: TENNESSEE VALLEY AUTHORITY PLANT: SEQUOYAH NUCLEAR PLANT :
NUCLEAR POWER GROUP' P.O. BOX 2000 1101 MARKET ST SODDY DAISY, TENNESSEE CHATTANOOGA, TENNESSEE 37402 37379 UNIT: TWO CERTIFICATE OF AUTHORIZATION: NOT REQUIRED COMMERCIAL SERVICE DATE: JUNE 1, 1982 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED i APPENDIX III ISI
SUMMARY
I t 6 1 L w# P/::r?3E la
0 l OWNER: TENNESSEE VALLEY AUTHORITY PLANT: SEQUOYAH NUCLEAR PLANT NUCLEAR POWER GROUP P.O. BOX 2000 1101 MARKET ST SODDY DAISY, TENNESSEE . CHATTANOOGA, TENNESSEE 37402 37379 l i UNIT: TWO CERTIFICATE OF AUTHORIZATION: NOT REQUIRED COMMERCIAL SERVICE DATE: JUNE 1, 1982 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED ; Summary: The Unit 2 Cycle 6 Inservice Inspection of Class 1 and 2 comp. nents included 66 Visual, 283 Ultrasonic, 51 Liquid Penetrant, and 52 Magnetic Particle examinations. This count includes additional samples and reexaminations due to Notification of Indications (NOIs). There were 8 NOIs generated for ASME Section XI, Class 1 I and 2 examinations. For NOI summary see Appendix VI. For Steam Generator Eddy Current results and number of tubes examined see ; Appendix V. ' Examinations were performed to TVA procedures with the exception of Steam Generator tubing ET examinations which were performed by Westinghouse Corporation to their procedures; and the Reactor Vessel examinations performed by Southwest Research (SwRI) to their procedures. I EERSONNELIE_QUIPMENT CERTIFICATIONS NDE personnel certification records for TVA and contractor employees are maintained by TVA's Inspection Services Organization (ISO). Any questions should be directed to the Inspection Services Organization (ISO) in Soddy Daisy, Tennessee, 37379, at (615)843-4303. TVA equipment and materials certification records are maintained by ISO, Sequoyah Site Material and Test Equipment Section, and Sequoyah Power Stores. Any questions should be directed to the Inservice Inspection Section supervisor Gary L Wade at Sequoyah Nuclear Plant in Soddy Daisy, Tennessee, 37379, at (615)843-6905. e PAGE H '
i l 1 OWNER: TENNESSEE VALLEY AUTHORITY PLANT: SEQUOYAH NUCLEAR PLANT ; NUCLEAR POWER GROUP P.O. BOX 2000 - 1101 MARKET ST SODDY DAISY, TENNESSEE CHATTANOOGA, TENNESSEE 37402 37379 i UNIT: TWO CERTIFICATE OF AUTHORIZATION: NC7r REQUIRED COMMERCIAL SERVICE DATE: JUNE 1, 1982 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED Inservice Inspection SummaIy In accordance with paragraph IWA-6220 of the Section XI ASME Boiler i and Pressure Vessel Code 1977 Edition through Summer 1978 Addenda the following information is provided.
- 1. Repair or Replacement Program at Sequoyah is Site Standard Practice 6.9, which complies with ASME Boiler and Pressure Vessel Code 1980 Edition, Winter 1981 Addenda. (see NIS-2 in Volume 2 for Repair or Replacements).
- 2. Date of documentation completion: January 23, 1995
- 3. Name of owner and address:
Tennessee Valley Authority Nuclear Power Group 1101 Market Street Chattanooga, Tennessee 37402-2801
- 4. Name and address of the nuclear generating plant:
Sequoyah Nuclear Plant P.O. Box 2000 Soddy Daisy, Tennessee 37379
- 5. Name and number assigned to the nuclear power unit by TVA:
Sequoyah Nuclear Plant, Unit 2
- 6. Commercial operation date for unit:
June 1, 1982
- 7. Numbers assigned to the components by the state:
No numbers assigned
- 8. National Board Number assigned to the components by the manufacturer:
No number assigned PAGE N
. - . . . ~ . -
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OWNER: TENNESSEE VALLEY AUTHORITY PLANT: SEQUOYAH NUCLEAR PLANT ' NUCLEAR POWER GROUP- P.O. BOX 2000 i 1101 MARKET ST' SODDY DAISY, TENNESSEE i CHATTANOOGA, TENNESSEE 37402 37379 UNIT: TWO CERTIFICATE OF AUTHORIZATION: NOT REQUIRED COMMERCIAL SERVICE DATE: JUNE 1, 1982 ; NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED .
- 9. Names of the components and descriptions including size, !'
capacity, material, location, and drawings to aid identification: The Class 1 and 2 components examined as part of this inservice inspection are listed in Appendix IV. i
- 10. Names and address of principal manufacturer and principal contract which will identify the subcontractors Manufacturers '
component identification numbers. The majority of components examined were supplied by: i Westinghouse Electric Corporation ! P.O. Box 355 i Pittsburgh, Pennsylvania, 15230 Contract Number 68C60-91934 fi NSSS N2M-2 - i
- 11. Date of completion of examinations:
November 16, 1994
- 12. Name of ANII who witnessed or otherwise verified the ;
examinations and his employer and business address: ! i Tom D. McGovern, Stephen B. Heater and Neil F. Jackson. . Hartford Steam Boiler Inspection and Insurance Company i 200 Ashford Center North, Suite 300 i Atlanta, Georgia 30338-4860 '
- 13. Abstract of examinations, conditions observed, and corrective !
measures recommended or taken: ' See Appendix IV, IV Part (A), IV Part (B), IV Part (C), V, and VI. f
- 14. Signature of ANII:
[ See NIS-1 form o PA43E- lb
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- m OWNER: TENNESSEE VALLEY AUTHORITY PLANT: SEQUOYAH. NUCLEAR PLANT NUCLEAR POWER GROUP P.O.' BOX 2000 1101 MARKET ST SODDY DAISY, TENNESSEE CHATTANOOGA, TENNESSEE 37402 37379 UNIT: TWO CERTIFICATE OF AUTHORIZATION: NOT REQUIRED '
COMMERCIAL SERVICE DATE: JUNE 1, 1982 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED APPENDIX IV EXAMINATION PLAN w PAGE 17
L -i 5 OWNER: TENNESSEE VALLEY AUTHORITY PLANT: SEQUOYAH NUCLEAR PLANT NUCLEAR POWER GROUP P.O. BOX 2000 1101 MARKET ST SODDY DAISY, TENNESSEE CHATTANOOGA, TENNESSEE 37402 37379 , UNIT: TWO CERTIFICATE OF AUTHORIZATION: NOT REQUIRED COMMERCIAL SERVICE DATE: JUNE 1, 1982 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED l Scan Plan: The management of ISI data for the maintenance and tracking of ASME Section XI and auamented examination data is maintained on a Mainframe computer.~ The computer program PRISIM (Program for ISI
' Data Management) has been engineered to facilitate the management of voluminous ISI examination data. The arrangement of this program allows users to rapidly retrieve data in order to i effectively schedule and track examinations performed during ISI activities.
Part A of this Appendix is a standardized Post Outage ISI Report designed to meet the reporting requirements of IWA-6000 of the ASME Section XI Code. This report contains Inservice Inspection data for Class 1 and 2 components. Southwest Research Institute (SwRI) performed examinations of the Reactor Vessel in accordance with SWRI scan plan and QA program approved by TVA. Examination Limitations of the RPV where ASME code coverage was not achieved are summarized at the end of Part A of this Appendix. l l l PAGE- 1R I I
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i l OWNER: TENNESSIE VALLEY AUTHORITY PLANT: SEQUOYAH NUCLEAR PLANT NUCLE 3R POWER GROUP P.O. BOX 2000. j 1101 MAPJRET ST SODDY DAIS'z, TENNESSEE t CHATTANOOGA, TENNESSEE 37402 37379 UNIT: TWO CERTIFICATE OF AUTHORIZATION: NOT REQUIRED , COMMERCIAL SERVICE DATE: JUNE 1, 1982 i NATIONAL BOARD NUMBER FOR UNIT: NOT REQ.UIRED l i I l APPENDIX IV PART A t POST OUTAGE ISI STATUS REPORT j i l I h I i PAGE 19
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- l. THESE ARE DISSIMILAR METAL WELDS CATEGORY B-F.
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ISI-0074-A 04
January 18,1995 MEMORANDUM ' 10.- G. L. Wade FROM: Steve Richter
SUBJECT:
Sequoyah Nuclear Plant, Unit 2, (SQN2) - Reactor Vessel Ten-year Examination Limitations Due To Accessibility l The ASME Code Section XI Code requires that essentially 100% of the weld length be examined. ' Code Case N-460 further defines " essentially 100%" as being equal to or greater than 90% of the weld.
~
The following list of welds for SQN2 have been evaluated in accordance with the methodology applied to SQN1, and have received less than the required 90% examination coverage.
SUMMARY
No. WELD CONFIGURATION ' 000500 W01-02 Bottom Head Cap to Bottom Head Ring ; 000400 WO2-03 Bottom Head to Lower Shell 4 000600 WO6-07 Upper Shell to Flange ! 000700 WO8-09C Closure Head to Flange 001900 N-15 Outlet Nozzle to Shell 002000 N-16 . Outlet Nozzle to Shell 002100 N-17 Outlet Nozzle to Shell 002200 N-18 Outlet Nozzle to Shell l Approved by: k M Hector Diaz, UT LexeiIII : 1 8 0'.WER: TENNESSEE VALLEY ALMHORITY PUM;SEQUOYAH NUCLEAR PUM NUCLEAR POWER GROUP P.O. BOX 2000 i 1101 MARKET STREET DAISY, TENNESSEE 37379 j CHATTAN0OGA. TENNESSEE 37401 l UNIT 2 CERTIFICATE OF AUTHORIZATION: NOT REQUIRED COMMERCIAL SERVICE DATE: JUNE 1,1982 NATIONAL BOARD NUM8ER FOR UNIT: NJ NUISER ASSGNED ! PAGE 79 ,!
( >
.. p Sequoyah Nuclear Plant Unit 2 1994 Reactor Vessel Inservice Inspection Examination Coverage Tables a fs :" . JL C ,.
kB ' 000500 WOI-02 Bottom Head Cap 0 CW 33 % 4 cm.nd am mr e si I o to Bottom Head 45 33 % u da==, i geta. - g lM 50nD 60 33% 11 % hamni amme.g.
- 8 I c. O CCW 32 % -
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l fgl Examination Coverage Tables l,ll M M IIIIA! E LIE I M IE ITEiE;il3 M d i H E fL ?
& 000400 WO2-03 Bottom Head to O CW 50 % 3a enmad a m n es g Lower shell 45 50 % n e.a h m., i ny or ss-60 50 % sh. h
$5* 50nD 17 %
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i Sono 0 DN 18 % 42 % l g 45 60 42 % 42 % g 5000 14 % m - unow 73 %
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i t - t , ._k _ 1 , . l 9g 000600 WO6-07 Upper Shell O CW 49 % 5 r==nd ed m i s , g ,, to Flange 45 49 % kAg g 60 49 % men. ado.e. , i-ky.ca.h y.my 5 50n0 16 % 0 CCW g gg 5 l;yj gg5
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ln Examination Coverage Tables gg . 3 ))E . IB -
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M1" N-15 OutletNozzle O CW 39 % 7 Tr - w a e. lg ggag @ 22 Deg. 45 39 % his,. - 60 39 % nos orin. i 4 ,.n a .iinia. 9 ,,, g ln,"g 5000 13 % hm si ei.e m - gm2 0 CCW 46 % g* 45 46 % R,g 60 46% gg 50nD 15 % g ,,g g - cwmcw 61%, . ! 4- 10 TWD 100 % I g 45 100 %
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- a Examination Coverage Tables gg g .._... ._
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OWNER: TENNESSEE VALLEY AUTHORITY PLANT: SEQUOYAH NUCLEAR PLANT , NUCLEAR POWER GROUP P.O. BOX 2000 1101 MARKET ST SODDY DAISY, TENNESSEE , CHATTANOOGA, TENNESSEE 37402 37379 UNIT: TWO CERTIFICATE OF AUTHORIZATION: NOT REQUIRED COMMERCIAL SERVICE DATE: JUNE 1, 1982 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED l APPENDIX V I
SUMMARY
OF STEAM GENERATOR . TUBING EXAMS f i
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. OWNER: TENNESSEE VALLEY AUTHORITY PLANT: SEQUOYAH NUCLEAR PLANT NUCLEAR POWER GROUP P.O. BOX 2000 i
1101 MARKET ST SODDY DAISY, TENNESSEE CHATTANOOGA, TENNESSEE 37402 37379 UNIT: TWO CERTIFICATE OF AUTHORIZATION: NOT REQUIRED COMMERCIAL SERVICE DATE: JUNE 1, 1982 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUI13ED
SUMMARY
OF STEAM GENERATOR EDDY CURRENT EXAMINATIONS (Unit 2 Cycle 6) EXAM TYPE S/ GEN.#1 S/ GEN.#2 S/ GEN.13 S/ GEN.#4 Full-length Bobbin Coil 3,377 3,363 3,370 3,379 Support Plate MRPC 33 27 27 27 Freespan MRPC 5 4 3 11 Top-of-Tubesheet MRPC 1,530 3,363 2,125 1,517 U-Bend MRPC 187 188 183 188 TOTAL EXAMS 5,972 7,781 6,545 5,961 TOTAL TUBES EXAM. 3,377 3,363 3,370 3,379 TUBES WITH INDICATIONS Defects (>=40% Wall Loss) PWSCC HTS 0 13 3 0 AVB Wear 0 3 0 0 ODSCC TSP O O 5 2 Cold Leg Wastage 0 0 2 0 U-Bend PWSCC 14 22 9 0 OD Indication 0 1 0 0 Note: All Defective tubes plucced. (Reference Work Request's C-049461, C-049462, C-049463 and C-049464) Degradation (>=20% and <40% Wall Loss) ODSCC TSP O 1 4 17 AVB WEAR 10 16 3 3 Cold Leg Wastage 2 10 7 3 OD Indication 0 0 1 11 Manufacturing Flaw 4 0 1 0 HTS ODSCC 0 1 6 0
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3 e OWNER: TENNESSEE VALLEY AUTHORITY PLANT: SEQUOYAH NUCLEAR PLANT NUCLEAR POWER GROUP P.O. BOX 2000 ' 1101 MARKET ST SODDY DAISY, TENNESSEE ; CHATTANOOGA, TENNESSEE 37402 37379 UNIT: TWO CERTIFICATE OF AUTHORIZATION: NOT REQUIRED COMMERCIAL SERVICE DATE: JUNE 1, 1982 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED EXAM TYPE _SIGEN.#1 S/ GEN.#2 S/ GEN.#3 S/ GEN.#4 Imperfections (<20% Wall Loss) AVB Wear 2 6 1 4 Cold Leg Wastage 1 5 2 5 : OD Indication 0 0 0 3 Manufacturing Flaw 3 2 1. O HTS ODSCC 0 0 1 2 ISI Data Report No. R-5367, R-5368, R-5369 and R-5370 i NOMENCLATURE FOR SEQUOYAH NUCLEAR PLANT STEAM GENERATOR EDDY CURRENT EXAMINATIONS l Notati_on Description HTS Top of Tubesheet - Hot Leg CTE Tube End - Cold Leg , HTE Tube End - Hot Leg ' Reporting Acronyms AVB Anti-Vibration Bar PWSCC Primary Water Stress Corrosion Cracking MRPC Motorized Rotating Pancake Probe SCC Stress Corrosion Cracking TSP Tube Support Plate Pld3E Sb
i S/G EDDY CURRENT EXAMINATION
SUMMARY
PLANT AND UNIT SEQUOYAH UNIT 2 OUTAGE CYCL 56 DATE JULY 1994 S/G # 1 GENERAL DEFECT EXAMS Exam Extent (s) Probe Type Number of Tubes HTE-CTE (Full Length) Bobbin Coil 3377 SPECIALTY EXAMS Exam Extent (s) Probe Type Number of Exams Hot Top of Tubesheet RPC 1530 Support Plate Intersection RPC 33 Freespan Test RPC 5 U-bend RPC 187 ,
.__ TOTAL NUMBER OF TUBES EXAMINED 3377 i 'ii.TE!EMt VALLEY AWHORITY PUM:SEQUOYAH NUCLEtt NUCt!/Ji POWER CROUP PLANT P.O. BOX 2000 IW ?"7KEiSTP.EET DAISY. TEN!iESSEE 37379 i i.""k EA TENT:ESSEE 374M i UN;T2 CGTHCATE OF AUTHORilATION: NOT REQUEtED CD4!RCiAL SERr.CE DATE: JUNE 1,1982 PAGE ggu. cono esta roR u.a: NJ Null 8ER ASSENED
- -~
S/G EDDY CURRENT EXA.'.4INATION
SUMMARY
PLANT AND UNIT SEQUOYAH UNIT 2 OUTAGE CYCLE 6 DATE JULY 1994 S/G # _2 GENERAL DEFECT EXAMS Exam Extent (s) Probe Type Number of Tubes HTE-CTE (Full Length) Bobbin Coil 3363 SPECIALTY EXAMS . Exam Extent (s) Probe Type Number of Exams Hot Top of Tubesheet RPC 3363 Support Plate Intersection RPC 27 : l Freespan Test RPC 4 U-bend RPC 188 UMit TnTAI MIMBER OF TUBES
- EXAMINED 3363 'l CERTIFICATE OF AUTHORIZATION: NOT REQUIRED
~ '"if4ERCIAL SERTCE DATE: JUNE 1,1982
, NAL BOARD N'JMBER FOR UNIL NJ NUMBER ASSENED bnN
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CWNER: TENNESSEE VALLEY AUTHORfTY PtANDSEQUOfAH NUCLEA't PLANT l NUCLEAR POWER GROUP P.O. 80i' 2000 1101 MARKET STREET DAISY, TENNESSEE 37379 CHATTAN00GA.TEfMESSEE 3N01 -
l L i i S/G EDDY CURRENT EXAMINATION
SUMMARY
l PLANT AND UNIT SEQUOYAH UNIT 2 i OUTAGE CYCLE 6 DATE JULY 1994 S/G # 3 GENEP.AL DEFECT EXAMS Exam Extent (s) Probe Type Number of Tubes HTE-CTE (Full Length) Bobbin Coil 3370 SPECIALTY EXAMS Exam Extent (s) Probe Type Number of Exams Hot Top of Tubesheet RPC 2125 Support Plate Intersection RPC 27 Freespan Test RPC 3 U-bend RPC 183 TOTAL NUMBER OF TUBES' EXAMINED 3370 i JM TUPfESSEE VALLEY AttTHORIT( PLANDggggyAN M4 rip [Aftf Y"t NYNER GROUP f.0.00x2006 i
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' CERTtFICATE OF Atmf0RilAT10N NOT REQ!ARED qq OMMRCIAL tER'JCE DATE: JUNE 1,im PAGE i , utiwt como Nuvun ron un na mussen AssmEn
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S/G EDDY CURRENT EXAMINATION
SUMMARY
PLANT AND UNIT SEQUOYAH UNIT 2 OUTAGE CYCLE 6 DATE JULY 1994 S/G # 4 : GENERAL DEFECT EXAMS Exam Extent (s) Probe Type Number of Tubes HTE-CTE (Full Length) Bobbin Coil 3379 SPECIALTY EXAMS Er.am Extent (s) Probe Type Number of Exams Hot Top of Tubesheet RPC 1S17 Support Plate Intersection RPC 27 Freespan Test RPC 11 U-bend RPC 188 ! l l TOTAL NUMBER OF TUBES EXAMINED 3379 '{
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I OWNER: TENNESSEE VALLEY AUTHORITY PLANT: SEQUOYAH NUCLEAR PLANT NUCLEAR POWER GROUP P.O. BOX 2000 1101 MARKET ST SODDY DAISY, TENNESSEE CHATTANOOGA, TENNESSEE 37402 37379 e UNIT: TWO CERTIFICATE OF AUTHORIZATION: NOT REQUIRED l COMMERCIAL SERVICE DATE: JUNE 1, 1982 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED . i APPENDIX VI l
SUMMARY
OF NOI'S l l I i e s i PAGE IDI - l
1 I I i N ! OWNER: TENNESSEE VALLEY AUTHORITY PLANT: SEQUOYAH NUCLEAR PLANT ; NUCLEAR POWER GROUP P.O. BOX 2000 1101 MARKET ST SODDY DAISY, TENNESSEE CHATTANOOGA, TENNESSEE 37402 37379 UNIT: TWO CERTIFICATE OF AUTHORIZATION: NOT REQUIRED COMMERCIAL SERVICE DATE: JUNE 1, 1982 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED Summary of Notifications: The Unit 2 Cycle 6 Inservice Inspection of Class 1 and 2 components at Sequoyah Nuclear Plant included a total of 8 Notifications of Indications (NOIs). The NOI listing does not include NOIs written on Class 3 components. The following is a listing of the NOIs and a brief description of each. J l l l l i l l PAGE I' l
o m OWNER: TENNESSEE VALLEY AUTHORITY PLANT: SEQUOYAH N11 CLEAR PLANT NUCLEAR POWER GROUP P.O. BOX 2000 1101 MARKET ST SODDY DAISY, TENNESSEE CHATTANOOGA, TENNESSEE 37402 37379 UNIT: TWO CERTIFICATE OF AUTHORIZATION: NOT REQUIRED COMMERCIAL SERVICE DATE: JUNE 1, 1982 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED
SUMMARY
NOTIFICATION OF INDICATION NOI NUMBER COMPONENT ID DISCREPANCY WORK INSTRUCTION RE-EXAM 2-SQ-290 SIS BIT-2 LINEAR C-214226 R5265A INDICATIONS Disposition: REMOVED BY GRINDING 2-SQ-292 RVCSUPST DEBRIS FHI-003 R5296 Disposition: REMOVED 2-SQ-293 SIS BIT-4 PLANAR SQ940652PER N/A FLAW Disposition: ACCEPTABLE FOR CONTINUED SERVICE. See attached Westinghouse evaluation. 2-SQ-294 SG#1 TUBES DEFECTIVE C-049561 R5367 Disposition: PLUGGED TUBES 2-SQ-295 SG#2 TUBES DEFECTIVE C-049562 R5368 Disposition: PLUGGED TUBES 2-SQ-296 SG#3 TUBES DEFECTIVE C-049563 R5369 Disposition: PLUGGED TUBES 2-SQ-297 SG#4 TUBES DEFECTIVE C-049564 R5370 Disposition: PLUGGED TUBES 2-SQ-298 SG#1 TUBES AXIAL C-049561 R5369 INDICATIONS IN THE PROTRUDING HOT LEG TUBE END DISPOSITION: 6 TUBES PLUGGED AND 33 TUBES WITH TECHNICAL JUSTIFICATION FOR CONTINUED SERVICE. See attached Technical Evaluation PAGE ID3
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l i OWNER: TENNESSEE VALLEY AUTHORITY PLANT: SEQUOYAH NUCLEAR PLANT , NUCLEAR POWER GROUP P.O. BOX 2000 i 1101 MARKET ST SODDY DAISY, TENNESSEE i CHATTANOOGA, TENNESSEE 37402 37379 : UNIT: TWO CERTIFICATE OF AUTHORIZATION: NOT REQUIRED COMMERCIAL SERVICE DATE: JUNE 1, 1982 , t NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED ; I WESTINGHOUSE EVALUATION OF , INDICATION IN BORON INJECTION TANK 5 I I r t f i F I f w ' pp,Gn ItA .
S : QA Record ._,. k B38 9410LO 806 Westinghouse Energy Systems Electric Corporallon - g3j5 3 ,3, 5ee 2* p3c 6e emdem va eM. TVA-94-180 Ref: MSE-SMT-347(94) . Task N94-033 Mr. Mark Burzynski, Manager October 4,1994 Department of Nuclear Engineering Tennessee Valley Authority Conbd f)c P.O. Box 2000 Soddy Daisy, TN 37379 91MP- 8630s(3
-Tek Mcf 4-o33 TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT BIT Flaw Evaluation Rc_oort
Dear Mr. Burzynski:
i
-- Enclosed is our final letter report entitled, " Integrity Evaluation of Indications in the Boron Injection Tanks for Sequoyah Units 1.and 2."
your comments. This report was finalized to include
- Please not that excluding the cladding is consistent with the rules of ASME Code Section XI for Class 1 components to which this evaluation was per The Class 2 component analysis Section (IWC-3610) refers to the Class 1 evaluatio criteria for flaws found in Class 2 components. The following is a description of ho comments were addressed in the report.
Comment 1: The request to edit first sentence in Section 4.2 was noted and the correction was made as requested. ; Comment 2: Section five was modified to address the cladding's impact on the analysis An additional paragraph was added to describe why the cladding was not modeled as part of the finite element analysis. Comment 3: An additional paragraph wa's added to explain the exclusion of the clad and the consideration of the flaws as surface flaws due to this excl Also, the paragraph which stated that the' cladding was included in the _- fracture mechanics evaluation was corrected to reflect the cladding not , being considered in the analysis. , OWIII9oftAftWff VolttV At#HORffY PLANT:SEQUOYANNUCtIARPtANT cNent0F AUTHoesA agtgg BOWER OROUP P.O. S WEf cRL SERVICE LETE:JUlf t.HE 4dGMDB99fHttT DM5Y,pX $ W.Ll 54 MAAER AS$1GNED
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i w Mr. Burzynski TVA-94-180 w October 4,1994 Comment 4: No change was made here since the other comments have clarified the lack of cladding and the 2.35 inch thickness is the thickness considered in the analysis. - If you have questions, please contact the undersigned. 9 Very truly yours, WESTINGHOUSE ELECTRIC CORPORATION y / D.W. Salak Sequoyah Project Manager TVA Projects cc: D. Lafever MJB:DML k d C.( C/Y\ t C- h ei CC: DRAFT REPLY COM INFO DUE COPY COPY DATE
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- s. SGt94acszv m OMER: TENNESSEE VALLEY LUTP00lTY PLANT:SEQUOYAN NUCLEAR PtANT NUCLEAR F0WER GROUP P.O. BOX 2000 1101 WRAEiSTREET DAISY, TENNESSEE 37379 l CHATTA'iOOGA. TENNESSEE 37401 UNIT 2 l CERTF:CATE OF AUTHORIZATION: NOT REQUIRED j 1111' CDWi;ECO:A.' SWiOE DATE: JUNE 1,1982 N/.TIONAL B0MD NUMBER FOR UNIT: NJ NUMBER ASSIGNED PAGE__1 Dlo
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INTEGRITY EVALUATION OF INDICATIONS IN THE BORON INJECTION TANKS FOR SEQUOYAH UNITS I AND 2 , SEPTEMBER 1994 W. H. BAMFORD D. E. PRAGER J. E. CONKLIN Reviewed by: " - P. l.. Strauch , L Approvedbyp #7 S A. Swamy, Mzffager Structural Mechanics Technology l Westinghouse Energy Systems , P.O. Box 355, Pittsburgh, P:A 15230 ' C 1994 Westinghouse Electric Corporation i All Rights Reserved j l PAb- IDl- !
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- TABLE OF CONTENTS Pace
1.0 INTRODUCTION
1 ;
2.0 BACKGROUND
AND HISTORY OF BORON INJECTION 1 TANKS AT SEQUOYAH PLANT 3.0 FLAW GEOMETRY: INSPECTION RESULTS 2 1 4.0 CRITERIA FOR FLAW ACCEPTABILITY: SECTION XI 3 4.1 Criteria Based on Stress Intensity Factor 4 4.2 Criteria Based on Primary Stress Limits 4 5.0 LOADS AND STRESS ANALYSIS 5 6.0 STRESS INTENSITY FACTOR CALCULATIONS 6 7.0 FRACTURE TOUGHNESS 7 8.0 FATIGUE CRACK GROWTH 8 8.1 Crack Growth Rate Reference Curves 8 8.2 Fatigue Crack Growth Results 9 9.0 FRACTURE RESULTS: ACCEPTABLE FLAW SIZE 9 9.1 Stress and Fracture Analysis 10 9.2 Description of the Flaw Evaluation Charts 10 i 9.3 Use of the Charts 11 10.0
SUMMARY
AND CONCLUSIONS 13 i
11.0 REFERENCES
13 OWNER. TENNESSEE VALLEY AUTHORITY PLANT:SEQUOYAH NUCLEAR PLANT NUCLEAR FO'AU GROUP P.O. BOX 2000 1101 tREET STREET DAISY, TENNESSEE 37379 CHATTUG/A TENNESSEE 37401 v UNIT 2 CihTE CATE OF AUTHORIZATION: NOT REQUIRED m:11349w.wpf:1WO93094 C N E C:AL SERVICE DATE: JUNE 1.1982 NATCNAI. BOARD NUMBER FOR LMT: NJ MNIER A30lGNED i FAGE lDB l
UNIT 2 CEllTIFICt.TE OF AUTHORIZATION: NOT REQ COMHERCIAL 1,tPV)CE DATE: JUNE 1.1982 n 1. INTRODUCTION NATIONAL BOARD NUM8ER FOR UNIT: The boron injection tanks for Sequoyah are four feet in inside diameter, and i fabricated of SA516 Grade 70 steel with SA240 Type 304L stainless steel roll bonded cladding. Their specified design temperature ranges from 60-300*F, and the design pressure is 2735 psi [1]. As a result of recent inspection findings, detailed in Section 3, an engineering evaluation has been carried out to establish the integrity of the tanks. The evaluation has been structured to be applicable to the boron
~
injection tanks in both Unit I and Unit 2 although the indicatior, was found in Unit 2. These tanks were designed to the ASME Code Section III,1968 edition. For the evaluations discussed in this report, the most recent published edition of Section XI (1992) was used. Although the Section XI paragraph references are from this edition, the analytical criteria for acceptance of indications have
- . remained unchanged since their original publication in 1974.
The evaluation which follows provides a technical justification for not repairing the shallow indication which has been found in the SA516 base metal near the interface with the cladding n. ear the bottom head junction with the cylindrical shell. The indication geometry is shown in Figure 1.
- 2. BACKGROUND AND HISTORY OF BORON INJECTION TANKS AT SEQUOYAH PLANT The Boron injection tank was originally designed to hold enough concentrated boric acid solution to counteract the case of the worst steam line rupture.
Electric strip heaters were attached to the tank to keep the temperature of the solution high enough to prevent precipitation of boric acid. A sparger is inserted at the tank inlet so that incoming fluid will not pass through without mixing with and forcing out the concentrated boric acid in the tank. Since TVA has eliminated the boron injection system, the tank no longer functions as a boron injection tank because it does not contain boric acid. The heaters are therefore no longer used. The tank merely functions as part .J - OWNER:TEWSEE VA;. LEY t.UTHORITY PLANT:SEQUOYAH NUCLEAR PLANT m11349w.wpt1bl093094 MW E*#.TM P.O. BOX 2000 11T "WEMTFEET CHATT;.N003A. TENNESSEE 37401 DA!SY, TENNESSEE 2PAGF ld
N of the attached piping system, and can sustain pressures as high as the system operation pressure, or 2250 psi. > During a safety injection, the charging pumps will inject the water from the l BIT into the reactor vessel via the cold legs with water from the refueling l water storage tank (RWST). When the pressure reaches that equivalent to the safety injection pumps shutoff head,1520 psi (104 bars), the SIP's will I introduce dilute boric acid solution from the RWST into the cold legs and into I the reactor vessel. The rate of introduction will increase as the RCS pressure continues to decrease. When the RCS pressure drops to 600-650 psig (41 - 45 bars), the accumulator tanks will operate. Nitrogen, at high ! pressure, will force the dilute boric acid in the accumulator tanks rapidly into the system to initiate refilling of the reactor vessel. The flow of water from the tanks will be augmented by the RHR pumps once the RCS pressure drops below approximately 195 psig (14 bars) (the shutoff head of the residual heat removal pumps) to complete recovering i ;.. ;. UMT2 CERTIFICATE OF AUTHORIZATION: NOT REQUIRED
- 3. FLAW GE0 METRY: INSPECTION RESULTS COMMERC;ALSERVICE DATE: JUNE 1.HB2 f;AT!0NAL 001RD NUMBER FOR UNIT: NJ IMSER ASSIGlED 4 l
The ultrasonic examination of the boron injection tank bottom head to shell weld (weld number BIT-4) for Sequoyah Unit 2 revealed a planar flaw which exceeds the allowable standards limits of Section XI, Table IWC 3510-1. Such ; an indication requires a flaw evaluation in accordance with Section XI to avoid a repair. j l The flaw was detected with both the 45 and 60 degree shear wave UT techniques, and also with the O degree longitudinal UT technique. The flaw is located near the fusion line on the shell side of the weld and extends parallel to the weld from 51.6 to 56.2 inches (0 inches is located at center-line of the manway proceeding clockwise when looking down on the vessel). The flaw distance from the outside surface (remaining ligament) is 2.1 inches and extends down to the clad / base metal interface. The maximum through-wall (height) dimension of the flaw is 0.25 inches. The thickness of the weld is 2.6 inches including the cla6. The clad thickness was measured ultrasonically and determined to be 0.25 inches thick. 0WNER: TEN'!ESSEEVALLEY AtRHORITY PLANT:SEQUOYAH NUCLEAR PLANT ECLE*,R eMEP OF:00P P.O. BOX 2000 m11349w.wpf:1bl093094 ;, , m yrti n t- DAISY, TENNESSEE 37379 Cn:(WiwG( EcE3SEE 37401 ( hD PAGE _
I
" ' The' evaluation process included interrogating the flaw with several different UT techniques. The techniques used were ID Creeping Wave; OD Creeping Wave; ;
45, 60, 70 Degree Shear Wave, and 45 Degree Longitudinal Wave. l The flaw length was established using Performance Demonstration Initiative (PDI) techniques with a 55 degree shear wave highly dampened transducer to maximize length accuracy. The flaw depth or remaining ligament was , established with a MSEB-4 straight beam transducer. The characterized size of the indication was therefore: l a = 0.25 in. UNIT 2 , 1 - 4.6 in. CERT!RCATE OF AUTHORIZATION: NOT REQURED : 4 CDWERCIAL SERV CE DATE: JUNE 1.1982 1/a = 18:1 IaT10ML Bot.RD NUMaER FOR UNIT: NJ NUMA ASSDED i
- 4. CRITERIA FOR FLAW ACCEPTABILITY: SECTION XI -
Section XI of the ASME Code provides acceptance criteria for flaw indications ; found during inservice inspection and operation. Since the boron injection ' tanks have received their N-stamp, Section XI criteria are applicable. j To provide assurance of the integrity of the tank in the presence of this ! indication, a fracture evaluation using the flaw acceptance criteria of Section XI was carried out. There are presently no criteria in Section XI for class 2 components, so this evaluation has e . ployed the class I criteria. Thi.; adds additional conservatism to the results. ; l Two criteria for flaw acceptability are required by Section XI and they are:
- 1) Acceptance Criteria based on Stress Intensity Factor (Section XI, ;
IWB-3612). I
- 2) Acceptance Criteria based on Primary Stress Limits (Section XI, :
IWB-3610, which requires meeting the limits of Section III, ! . NB 3000). : i These criteria are explaiaed in the following sections, and will be used to i
', establish the fim accept < ..h.. 7' ;
uOWNE n itd: EW!ESIEEVALLEY AUTHORITY PLANT:SEQUOYAH NUCLEAR PLANT fwni!.9 00?.ER 07:0LT P.O. B0X 2000 nd1349 yctbl093094 11C.*aidiSTREET DAISY,TENIESSEEM@ IN CHAGM.005A TEriNESSEE 37401 I
4.1 Criteria Based on Stress Intensity Factor These criteria are from IWB-3612 of Section XI. The term stress intensity- i factor (K,) is defined as the driving force on a crack. It is a function of the size of the crack and the applied stresses, as well as the overall geometry of the structure. In contrast, the fracture toughness (K,, K,) is a , measure of the resistance of the material to propagation of a crack. It is a material property, and a function o_f temperature. Uv2 The criteria are- - N'P.'. MmrlAT10N: No7 REQUIRED
- e c !.0". DAi;: f)NE :.108 i
U O M M4% 04 DER FOR UNIT: NJ NUMBER AS$1GNED K, s for normal conditions (upset and test conditions inclusive)
/10 K. for faulted conditions (emergency conditions inclusive)
K, s 5 OW!E. ~ ""p WV MirHCaiTY PU,NT:SE7J0YAHNUCLEARPLAlli
.?
. P.O. BOX 2000 where 3;,c ..:-F DA!SY TENNESSEE 57579 CHu .uve T2;;N MEE 37401 K, - The maximum applied stress intensity factor for the flaw size a, to which a detected flaw will grow, during the condition under consideration, at the end of design life, or to the next inspection.
K, = Fracture toughness based on crack arrest for the corresponding crack tip temperature. K,, = Fracture toughness based on fracture initiation for the corresponding crack tip temperature. 1 4.2 Criteria Based on Primary Stress Limits i In addition to satisfying the fracture criteria, IWB 3600 of Section XI l requires that the primary stress limits of Section III, paragraph NB 3000 must l l l m:11349w.wpt:1bl093094 4 l PAGE_ E l 1 l
l
' be satisfied. A local area reduction of the pressure retaining membrane was used, equal to the area of the indication, and the stresses were increased to reflect the smaller cross section. Using this criterion, the allowable flaw !
depth is 0.925 inches for the bottom head to cylindrical shell weld region. The allowable depths based on the criteria of Section 4.1 are more restrictive, and therefore the criteria of Section 4.1 were used to determine the allowable flaw depths. This calculation was included to ensure that , integrity would be maintained from _t_he standpoint of ductile failure. . UNIT 2 CERTIRCATE OF AUTHORIZATION: NOT REQUIRED
- 5. LOADS AND STRESS ANALYSIS COWE*CIAL SERVICE DATE: JUNE 1.1982 NATIONAL E0ARD NUMBER FOR UNIT: NJ 1mMR AS$101ED The applicable design transients are listed in Table 1. This is.a Class 2 tank which only functions during safety injection. The loads considered in the analysis are the pressure loads, which are the only operational transients [1]. The modification of the tank to eliminate the high concentration of boron means that the heaters are no longer used, and therefore there are no heater transients. The pressure varies from 50 psig to 2250 psig during operation, as shown in Table 1 [1]. The maximum operating pressure of 2250 psig was used in the fracture analysis.
The boron injection tank was modelled with axisymmetric isoparametric finite elements, in order to obtain an accurate portrayal of the stresses at the bottom head to shell weld. The model is shown in Figure 2, where it may be seen that there are four elements through the thickness in the head reginn and five elements through the thickness in the cylindrical shell ragion. The tank dimensions used in the model are the minimum wall thickness from the design drawing [1]. The cladding was not included in the model. It is important to discuss the role of the cladding in this evaluation. The cladding was included in the original design calculations to determine the required wall thicknesses. In the flaw evaluation process, however, no structural credit has been taken for the cladding. There are presently no flaw evaluation procedures in Section XI specifically for class 2 components; the user is referred to the procedures for class I components instead. In evaluation of class I components, no structural credit is taken for the presence of the cladding, so this evaluation has maintained that approach, which adds some conservatisl 1 t* Nth 62rE3EhSHEY LTHONTY PLANT:$EQUOYAH NUCLEM P! ANT NUC'.CU W.3 20Lt P.O. BOX 2G m11349w.wpf:1h!O93094 110: :5:utstEZU DAlsY.TesESSEE37379 CHATTAh00GA. TENNESSEE 37401 3'h W I O -
I i & The stress results are provided in Table 3, for an internal pressure of 2250 psi. Figure 3'shows the axial and hoop stresses in color contour plots, j showing the changes in stress at the thickness transition. The finite element j stresses compared well with classical results away from the discontinuity i region.
- 6. STRESS INTENSITY FACTOR CALCULATIONS One of the key elements of the critical flaw size calculations is the determination of the driving force or stress intensity factor (K,). This was done for each of the regions using expressions available from the literature. l In all cases the stress intensity factor for the critical flaw size calculations utilized a representation of the actual stress profile rather than a linearization. This was necessary to provide the most accurate determination possible of the critical flaw size and is particularly important j for consideration of emergency and faulted conditions, where the stress '
profile is generally nonlinear and often very steep. The stress profile was represented by a cubic polynomial: l W.r ; a (x) - A, + A, x + A, x + A3 x' n "c.Mm WRIZATION$ NOT REQUIRED 7 k dMi OATE: JUNE 1,1982 h where M M BE H OR M .W W AS$e sp A , Ai , A2 , and A, are stress profile curve fitting coefficients x is the coordinate distance into the wall a is the stress perpendicular to the plane of the crack The stress intensity factor of Raju and Newman [2] was used to evaluate the surface flaw. The following expression is used for calculating K,: 2 K, = G,A, + G,A,a + G,A,a + GAa] OWNER; TENNE 53!!VM. LEY tU CMY PtANT:SEQUOYAH NUCLEAR PLANT NUSU 1 Tia GE? P.O. B0X 2000 m:11349w.wpt:1bl093094 110; ." fr.* *ii SirliET DAISY,TDGEMEE37579 ! CHATTAN0OGA. TENNESSEE 37401
)
PAGE I14
p 3
- where G., G , G2 , and G are magnification factors [2] '
3 3
- < 0.5 cos'p + 8' Q"2- sin2 p dp
*s C p - parametric angl<
u{N[ 0 E C;EVA! LEY WNORITY PLANT:SEQUOYAH NUCLEAR PUWT h a - f1aw depth NU'.'.OR iTl!EGOUP P.O. BOX 2000 c = one-hal'f flaw la ngth 11W cWET 51REET DA!SY, TENNESSEE 3M9 CHATTAN0oGA. TENNESSEE 37401 The results of these calculations for a range of flaw shapes are shown in Figure 4. UMT2 i"FACATE OF AUTHORIZATION: NOT REQUIRED
!" 'i.TC'J.L SEEVICE DATE: JUNE 1.1982
- 7. FRACTURE TOUGHNC.SS NAY;0 (AL BOARD NUMBER FOR UNIT: NJ NUMBER ASSMD An essential element in the determination of critical flaw sizes is the fracture toughness of the material. The fracture toughness was taken directly from the reference curves of Appendix A, Section XI of the ASME Code. In the transition temperature region, these curves can be represented by the
~
following equations: K - 33.2 + 2.806 exp. [0.02 (T-RT + 100*F)] K, = 26.8 + 1.223 exp. [0.0145 (T-RT, + 160*F)] where K, and K, are in ksi fin. . i The upper shelf temperature regime requires utilization of a shelf toughness which is not specified in the ASME Code. A value of 200 ksi/in has been used here. This value is consistent with general practice'in such evaluations, as shown for example in reference 3, which provides the background and technical basis for Appendix A of Section XI. The other key element on the determination of the fracture toughness is the value of RT which is a parameter determined from Charpy V-notch and drop-weight tests. For this analysis, it was assumed that the RT, was O'F for the weld material in the boron injection tanks. This is considered to be an upper a m:11349w.wpf:1bm83094 7 PAGE E - t
- bound for welds of this type based on earlier work on boron injection. tanks
. and the guarantees which are available from fabricators on vessels of this !
size. The tank material (SA'516 Grade 70)'was required to have a Charpy I energy of 10 ft.1b. or greater, when tested at -20'F, as specified in the drawing. The value of RTer for the vessel shell material was determined from r the Charpy results shown on the material test certificates, through use of the NRC Standard Review Plan (4]. These results are shown in Table 2. The , analysis used a value of RT , = 0*F, which is the governing value from Table 2. g OWNER: TEN' 2EEEVALE( AUTHORITY PLANT:SEQUOYAH NUCLEAR PLAN WLE9POWMGOb? P.O. B0X 2000
- 8. FATIGUE CRACK GROWTH 1m MET 5mc DMSY, TENNESSEE 3MM ;
cHis1 TAN 00GA TENNESSEE 37401 The fatigue crack growth analysis' procedure involves postulating an initial flaw at specific regions and predicting the growth of that flaw due to an imposed series of loading transients. The input required for a fatigue crack growth analysis is basically the information necessary to calculate the parameter AK, which depends on crack and structure geometry and the range of applied stresses in the area where the crack exists. Once AK, is calculated, " _ the growth due to that particular stress cycle can be calculated by equations given in the following section and in Figure 5. This increment of growth is then added to the original crack size, and the analysis proceeds to the next transient. The procedure is continued in this manner until all the transients known to occur in the period of evaluation have been analyzed. The transients considered in the analysis are listed in Table 1, and were obtained from Reference 1. Crack growth calculations were carried out for a range of surface indications. UMT2 CPT1?C/.TE OF t.UTH0mZATION: NOT REQUIRED 8.1 Crack Growth Rate Reference Curves '] [ DER j R NE ,1 The crack growth rate curves used in the analyses were taken directly from Appendix A of Section XI of the ASME Code. Water environment curves were used for the postulated inside surface flaws. The water environment in the boron injection tanks is basically the same as primary water, with a nominal boron concentration of 2000 ppm. Therefore the reference crack growth curves of Section XI will be directly applicable. ! i m:11349w.wptib!D93094 8 PAGE lb
c For water environments the reference crack growth curves are shown in : Figure 4, and growth rate is a function of both the applied stress intensity ' factor range, and the R ratio (K,,/K.) for the transient. For R < 0.25 S (AK,< 19 ksi Vin ) bdN=(1.02 x 10-') AK " (AK, > 19 ksi /in ) = (1,01 x 10-') AK,5 where b = crack growth rate, micro-inches / cycle. _ dN g > OWNER: TENNIS!EE VALLEY AUTHORITY PLANT:SEQUOYAH NUCLEAR PLANT , tanE& PC7liR GPOUP P.O. B0X 2000 11?. . Wi! STREET DAISY,TEIESSEE 37N9 for R > 0.65 CtlAT,w00GA. TENNESSEE 37401 (AK,< 12 ksi pin ) bdN= (1.20 x 10-') AK i " > h (AK,> 12 ksi /in ) = (2.52 x 10-') AKf
- i f
For R ratio between these two extremes,, ';t:r;:ht':r E r:::x: d:d. .
- 1.H!T 2 I ^?"'rlTE OF ?'.TORIZATION:NOTREQUIRED 8.2 Fatique Crack Growth Results . : ' r? $. ! E*!C MTE: JUNE 1,1982
[ laiu E 20JD NUMBER FOR UNIT:NJIMIBER AS$1GNED Table 4 provides the fatigue crack growth results for a range of surface flaws, and shows that the crack growth is small enough to be neglected in the fracture analysis. Therefore, the fracture analysis in Section 9 to determine the largest acceptable flaw sizes was carried out without consideration of fatigue crack growth.
- 9. FRACTURE RESULTS: ACCEPTABLE FLAW SIZE To determine the largest acceptable flaw sizes for the head to shell weld l
region of the boron injection tank, calculations were carried out for a range wu349w.wptWO93094 9 : PAGE_IN - t
}
n O of flaw sizes and shapes. The results have been presented in a chart which .
. shows the largest flaw of a given shape which meets the Section XI acceptance criteria for evaluation, as contained in paragraph IWB 3600 of Section XI.
The fracture mechanics analysis ignores the presence of the cladding in determining the depth and surface proximity of the flaw, because the flaw , evaluation procedures for class I components are used. When the cladding is ignored, the indication is a surface flaw; if the cladding is included in the evaluation, the flaw is a buried flaw. This assumption adds considerable conservatism to the results, and is necessary because there are as yet no flaw , evaluation rules specifically for class 2 components. 9.1 Stress and Fracture Analysis The results of the stress analysis were Gd to calculate applied stress intensity factors for a range of flaw sites, using the methods of Section 6. The allowable flaw depth was then determined as the depth at which the applied i
^ stress intensity factor reached a value equal to the fracture toughness L - divided by /10 , as discussed in Section 4. For RT, = 0'F, this value of j i
Kg/10 equals 17.93 ksi /in . This process was carried out for a range of flaw shapes, and the allowable flaw depths were plotted in tne chart shown in Figure 5. 9.2 Descriotion of the Flaw Evaluation Charts The chart in Figure 6 is for the cylindrical shell to hemispherical head weld region. Results are shown for a range of circumferential flaw shapes. The : minimum operating temperature of the tank is 60*F. Each chart is developed with two dimensionless parameters, which together describe the complete range of possible flaw shapes. They are: UM2
. Flaw Shape Parameter a/l omem Mw!ZATION:NOT REQUIRED N '. . M UE: JJNE 1,1982 i
. Flaw Depth Parameter a/t ,
- r. ..,s.; r A3ER FOR UNIT: NJ NUMER AS$1GNED !
{ l 3
- OWNER.TEf. ' a '.4 A W iY PLANT:SEQUOYAH NUCLEAR PLANT i l
M;: . J GUP P.O. BOX 2000 mi1349w.wpf:1bl093094 CHAo 400GA, TENNESSEE 37401 PAGt HB l l
^ where:
f t - wall thickness of tank, including carbon and stainless steel ! a - flaw depth, in. 1 = flaw length, in. The cladding has not been included in the fracture mechanics calculations, and for ease of use, the allowable flaw depths are presented in the flaw l evaluation charts with the depth of the flaw measured from the clad-base metal interface. It will be helpful to describe the flaw evaluation charts, and their construction steps: I
- The flaw shape parameter a/1 was plotted as the abscissa, from a value of 0 (continuously long flaw) to 0.5 (semicircular flaw).
-
- The flaw depth parameter a/t was plotted as the ordinate.
- The curves show the maximum acceptable flaw depth for each of a ,
range of flaw shapes. The most restrictive shape is a continuous fl aw (a/1 - 0.0) . , h
. The charts have been developed fsr circumferential flaws in the bottom head to cylindrical shell weld. The stresses in this ,
region were taken from a finite element model of the boron injection tank.
- Any surface indication which falls below the curves is acceptable l for further operation, having satisfied the criteria of Section XI, IWB 3600. UNr 2 C'EiWJJE 0? AliTHORIIATION: NOT REQUIRED ,
C? aT n ZYnM DATE: JUNE 1,1982 9.3 Use of the Charts 1 . rou LMD kJEER FOR UNIT: NJ NUMBER A$$NEED When an indication is discovered, it must be characterized by its length (1) ' and depth (a). The following two parameters are then calculated: V
- OWNE t ~" "- T 'lT.D .-UT: 0ZTY PUNT:SEQUOYAH NUCLEAR PLANT
'^:7
. . P.O.BOK2000 m11349w.wpf:1b1093094 11 gg3y,yg g
, , l
(,:.. T :, .c4. TRSEE 37401 PAGE M --
i l
^ .
*' Flaw Shape Parameter a/1
- Flaw Depth Parameter a/t
~
Once these parameters have been determined, the point is simply plotted on the , appropriate chart. This can be illustrated by the indication found during the l recent inspection. The length of the indication is approximately 4.6 inches, ; while its depth is no greater than 0.25 inches. The tank thickness in the - region (excluding the clad), is 2.35 inches, so the flaw parameters are: ; a/1 = 0.054 a/t = 0.106 The indication was located in the bottom head region, so plotting this point , on Figure 6 shows this flaw is acceptable for further service. The plotted j point demonstrating acceptance is shown as a circle in Figure 7. I i OWNER:TENNESSEEVALLEY AUTHORITY PLANT:SEQUOYAH NUCLEAR PLANT ! NUOLEA't POWER G30'JP P.O. BOK 2000 1101 NAMT STREET DAISY, TENNESSEE 37379 CHAiTAN00GA. TENNESSEE 37401 tir*
' T~ :".:': Of YTH'. MAT!ON: NOT RIQU' RED ,
. .: "1 %TE: JUNE 1 l' JE2 c;JO NPaSER FOR UNIT: NJ NUMBER AS$1GNED l
1 l 1 m:11349w.wpf:1bl083094 12 PAGE 120 i
b
- 10.
SUMMARY
AND CONCLUSIONS , e As a result of recent inspection findings, an engineering evaluation has been completed to consider the effect of the small indication in the bottom head to cylindrical shell weld on the integrity of the boron injection tanks. Both fatigue crack growth and fracture calculations have been completed for the f tanks, and the results are presented in terms of an allowable flaw size chart I for a range of circumferential flaw shapes. The criteria of ASME Section XI were used to construct this chart, which shows that the indication in the tank need not be repaired. j In conclusion, it is recommended that the existing indication in the head to i shell weld be left as is without repair.
- 11. REFERENCES
- 1. 900 Gallon Tank-Boron injection - Westinghouse Drawing #113E275, December 1970.
- 2. Newman, J. C. Jr. and Raju, I. S., " Stress Intensity Factors for !
Internal Surface Cracks in Cylindrical Pressure Vessels," ASME Trans. ; Journal of Pressure Vessel Technology, Vol. 102, 1980, pp. 342-346.
- 3. Marston, T. U. et. " Flaw Evaluation Procedures: ASME Section XI",
Electric Power Research Institute Report EPRI-NP-719-SR, August 1978.
- 4. USNRC Standard Review Plan, NUREG 0800, July 1981. 1 OWNIP ' ' ,si';;F.?//..jn:CRiTV TLANT:SEQUOYAH NUOLEAR PLANT i '
% :.; :T? P.O. BOX 2000
'. DA!SY,TENIESSEE37379 i 0.:4 'i..MI55EE 37401 UtM 2 i C'T:"'C 0: @DM71.T!0N: NOT REQUIRED I
- i. 9i!:U. 3lJf.: JUNE 1,1982 j U ?.n' .U d!R TOR UNIT: NJ NUMBER ASSIGNED I
%./ mi1349w.wpf:1bf093094 13 PAGE IAI l
4 6 O TABLE 1 BORON INJECTION TANK NORMAL CONDITION TRANSIENTS (UPSET AND TEST CONDITIONS INCLUSIVE) PRESSURE TRANSIENT TRANSIENT NUMBER i TITLE (PSIG) 0F CYCLES Operating Conditions A. Pressure Variations 50-2250 at 70*F 550 [ B. Temperature Variations none nonc r A. 1, OWNER TEi:HESEEE VALtEY f.t'THORITY PLANT:SEQUOYAH NUCLEAR PLANT h';: ' T.';!.':: JU.:P P.O.80X 2000 11: 'I$ N E'
. DAlSY.TDGESSEE359 CHAL.J.00GA. TENNESSEE 37401 l UNIT 2 cirifTATE OF AUTilCRIZATION:NOTREQUIRED
; ' C.1/.E DATE: M4E 1,1982
. . ;<e4E0 f OR UNIT: NJ NUMBER ASSIGNED i v
i m11349w.wpf:1blDS3094 14 PAGE i E
' TABLE 2 CHARPY RESULTS FOR TANK MATERIALS COMPONENT HEAT NUMBER CHARPY VALUES * (ft. lb.) RT,,(*F) T t UNIT I BORON INJECTION Shell Plates C8038-69 31, 22, 25 0 Top Head A6838-62 25, 26, 19 0 Bottom Head A6829-74 35, 21, 34 0 UNIT 2 BORON INJECTION Shell Plates A7164-70 29, 29, 24 0 Bottom / Top Heads C7749-70 22, 18, 20 0 m . OWNER:TEt.'\ESEEE VALLEf AUTHORITY PLANT:SEQUOYAH NUCLEAR PLANT t....1 ,nn:V MOUP P.O. BOX 2000 4
- . ;i DAISY, TENNESSEE 37379
., ,oo An. TEdhESSEE 37401
!!!n! 2 C i'C C?'.TT !JTHoerlAT!Ott fl0i REQUIRED C ' '.?iFh. :.Ni.'.2 OATE: JUNE 1,1982
. ' 0.' *. :03 NUMBER FOR UNIT: NJ NUMBER ASSIGNED
- tests at -20*F J
net 1349w.wpt:1bes3094 15 , PAGE i 2.3
1 1 i ' - TABLE 3 j l STRESS PROFILES USED IN FRACTURE ANALYSIS INTERNAL PRESSURE - 2250 PSI l DISTANCE FROM THE INSIDE AXIAL STRESS HOOP STRESS SURFACE (IN.) (KSI) (KSI) i 0 15.14 12.57 i 0.31 13.09 11.96 0.64 11.41 11.51 l 0.94 10.68 10.64 1.25 10.15 10.62 1.56 9.77 10.55 - 1.88 9.53 10.29 2.19 9.52 10.28 2.5 9.63 10.40 t' 5 OWNER:WT":FE WiiEY /MHORiif PLANT:5EQUOYANNUCLEAR PLANT i-Ua -J Ti': 'd 12 P.O. BOX 2000 110. ? ' 7. " ' DAISY, TENNESSEE 359 CMC 4i TELESSEE 37401
.' " '! ""PO.Rr0 TION: NOT REQUIRED
. . . ' ..: die' JUNE 1,1982
- m. ~ ... ;.1) 4U:266 FOR UNIT: NJ NUMBut ASSIGNED v
m:11349w.wpf:1bl093094 16 ' PAGE IA4
i e TABLE 4-1 FATIGUE CRACK GROWTH RESULTS FOR SURFACE FLAWS i INITIAL CRACK DEPTH (IN.) AFTER YEAR CRACK DEPTH 10 20 30 40 (IN.) ASPECT RATIO (a/1) = 0.01 0.10 .1001 .1002 .1002 .1003 O.15 .1503 .1505 .1508 .1510 0.20 .2006 .2012 .2018 .2024 0.25 .2511 .2522 .2533 .2545 0.30 .3019 .3038 .3057 .3077 ! ASPECT RATIO (a/1) = 0.1667 0.10 .1000 .1001 .1001 .1001 0.15 .1501 .1502 .1503 .1504 0.20 .2002 .2004 .2006 .2008 0.25 .2504 .2507 .2511 .2514 0.30 .3006 .3011 .3017 .3022 ASPECT RATIO (a/1) - 0.5 O.30 .3000 .3001 .3001 .3002
.3501 .3502 .3503 !
0.35 .3501 0.50 .5001 .5003 .5004 .5005 0.75 .7503 .7506 .7510 .7513 i i OWNER:iEt mi:E Ti'I' W"G!TY PLANT:SEQUOYAH NUCLEAR PLANT j fxc. -,1 u ' r?.uv P.O. BOX 2000 l 10 ;.a..ir sTali! DAISY.TENIESSEE37379 l CHAITAndvGA TiNNESSEE 37401 l l O'7ATl0N:NOT SEQUIRED m:u34sw.wytiwos3094 l7,; _.._,
. , ..,. ,jj.MNQl' U N Mm PAGE las-
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{ Cylindrical !nm! -Q ! e . :. , Shell !!ng E ss e ! m:= se! - k % 55 ati?i g Gi!!8 E@si
- indication Shell-Head .
Weld s i w p Cladding ! Spherical - Head 4 Figure 1. Geometry of the bottom head to shell region, showing the location of the indication. v nd134sw.wyt:1wos2794 18 PAGE_ lab
Figure 2. Finite Element Model.
1 t I g 5 r-R m
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( 4 tmo ssep = I leersseme = t tmd step = I Iteration = I Newral Gle = INJFCT_RES
- Neutral 6te = INJECT _ItES VerinNe = 5yy Vertshie = 571.
Men.= 21618. Men. = 17950.5 Mht = -2727.4 Men. = 19 885. 216 t R. 1791n 9 17tml. 16528. f t iv 1 % 94 94 ems. 04 % 7. 5400 ' 1144n IMO. 12111
-2727.4 1IIR1 em WtM'Af491.tS W4 Aug 2419N 83 M 38 TAME Wes 9 M31 wgcAnyg,gg g4 g,g 3g g,g4 91N NTANK Ver 9M31 OWNER: TENNESSEE VALLEY AUTHORITY PLANT:SEQUOYAH NUCIEAR PLANT I
NUCLEAR POWER GROUP P O. 0012000 1101 NARKETSTREET DAISY TEHNESSEE 37379 CHATTAN00GA.TEl#6ESSEE 37#1
.o Figure 3. Stress Contours, Axial (left) and Hoop (right)
*> (Internal pressure - 2250 psi)
O T3 UN!T 2 F CERTIFICATE OF AUTHOR 8?ATiON: NOT REQUIRED
$ tr)1m gip 2m N COMMERCIAL SERVICE DATE: ANE 1,1982 NATIONAL BOARD NUMBER FOR UNIT: NJ PRIMBER ASSIGNED
tR*r 2 l CEPr:ncsTh (.3 4,.., .. i CCk;dRCut st&,e,;. *~... , ' ':GT H QLV v D 4 WIOML B030 ny,,y}*gl' HC.! l AiJIM.GERg ) i I I R:%SifE VALLE Atmn,;q' l NOCLEAR POWER Group : SEQ'JOYAM NUCLEAR PLANT
* )
1101 MARKET STREET ' l CHATTAN0A'., TEM yg S,TElinS;s4373;g 100 : Cont. t 80 18:1 c l 9amus8' 6:1 o ' --- t 60
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inscation . . . . . . .
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,,e,,, ,-
,- a m 20 -
~ / /,,. **........ ................ l 0 ' '
0 0.2 0.4 0.6 0.8 1 , Through Wall Distance (a/t) Figure 4. Stress Intensity Factor Calculations for a Range of Flaw Shapes j i l m:1134ew.wyttwos27s4 21 Ph% IM -- l
1000 _ f _-
~
700 -
+ Lineer insorpolation is recom- !
rnanded to account for ratio % [ depe der.oe.f p4 p sr-ronment , y _ curves, for 0.25 <R < 0A5 for f , shallow slope: S [ 8 = (1.01 X 10-1 102A #1B$ GN O N /
~
0 2= 3.75 R + 0.06 &
- e 4 / ig g 200 -
R = K,n. /xme . 4/ f
/ '
g.g ! gg - E:22 , E 2 100 , somrfaco fiews (air environment)
/ , $'5 M
0 3.726
/ %- W $ '
] = 10.0267 X 10 ) A Kt f p i m _
2 4 _ +,2 = g g 50 - Determine the AK at which the tow changes tw ce6culation of
/ $$ hnE g g.
f C4 o g g the intersection of the two a curas. %+ 9 g { _ ew tb Surface flows e {weser roector
/ I f
g 20 - '"'i'8"**"8I applicable for < a R 4 0.25 f f *0.25 < R < 025 R > 0$$ f c i 10 - 3 R=K nfKme x. I 7
!* I y 9
- Lineer ins,rpolation is recomrnended 5 -
/ to account for # ratio dependence
~
of weier environment curws,for f y 0.25 < R < 0.65 for steep slape:
=' l 3
- 4 j . m = n.02 x 10 > O, sx5s5
~
I/I f/I Og = 26AM 5.725 R *Kmin ) Km ,,,
/
/
, I I I I I I lil l I I l lIll 1 2 5 7 to 20 50 70 100 Stress intensity Factor Range (AK g itsi %.)
Figure 5. Reference Fatigue Crack Growth Curves for Carbon and Low Alloy Ferritic Steel J l m11349w.wpf:WO92794 22 '
4 . i k-
,f "
LEGO O J
; A -The 10,20,30 year 10,20,30 yrs. acear*=N= flow Mrnile.
; ; B -Within thle zone, the i I 70 I 1
l l II ! A by AWE Code snelyWeel I
- I I jj i creorie in IWimpOO
- I I II I I
i 60 [ I II ! I C ASME Code eNowebte- per -
^
I ! Ii i Table IWB 35101. I I II I .- $ 1 I II I 50 ! ! I i! !
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. I I iI 1 1 1 1 l l
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- !! I c
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I i 11 1 l 0 0 0.04 0.06 ~ 0.12 0.16 0.2 0.24 0.28 0.32 0.36 0.4 0.44 Om UNIT 2 FLAW SHAPE (a/A) etartricArt or autiionenTioN: Noi arguinEO
+
COMut3CtAi. 5ERVICE DATE: JUNE 1,1982 NATIONAL BOARO Null 8ER FOR LNIIT: NJ IRMER ASSIGIED Figure 6. Results for Largest Allowable Flaw Depth: Boron. Injection y, Tank Cylindrical Shell to Botton Head Weld Region - Circumferential Flaws , h
~~
OWNER 190iESSEE VAllEV .'. Uni ~.P* PLANT:SEQUOYAH NUCLEARFWR ' nd1340w.wyf:1WOS2m 23 r tccAp;m:rp:::cie P.O.30Easse 3191 IMKE15140 DAISY,TEIEESSEE37379 CHATfANOOGA. TENNESSEE 3M01 - '
^
1 I . i - LEGEND A -The 10,20,30 year 10, 20,30 yrs. acceptetdo flew limits. ' B -Within this zone, the surface flewis acceptable 70 A W ASME M @ r erlierte in IWIMe00 60 1 C - ASME Code elloweble - per Table IWB 3510-1.
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et as I i (#0
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0 0 0.04 0.08 0.12 0.16 0.2 0.24 0.26 0.32 0.36 0.4 0.44 0.48 TE OF AUTHOR!ZATION: NOT REQU! RED FLAW SHAPE (a/A) comERemsERocE onE:m i.ne: nanom.soARD HUMBER FOR UNITN NUMBER ASSWED g, Figure 7. Flaw Evaluation Results for An Existing Indication in the i tv Head Region 1-l# OWNER TDPfESSEE VALLEY AlfDIGPfTV PLANT:SEquefAH NUCLEAR PuglT , N N'JCLEAR F0fiFD CROW P.O. BOK 2000 nel1340w.wpf:1WOS2m 24 1101 f.:AFKET dME :- DAISY,TE10ESSEE 37379
- Cl!AITAN00GA. TENNE 5SEE 37401
?
. -- _m - m m__ --,.m. . . , u.-r-.. ..-#m, ..w.. . wm,--....-.e-,.c.. -,--,+em ,,e ,..--,,,,.%,-.,,m.., , , - , . , . ., ,,me.- .._.-...wy,..,.. -
. ~ . , % ..f,,,, , m., r,.s., _,
OWNER: TENNESSEE VALLEY AUTHORITY PLANT: SEQUOYAH NUCLEAR PLANT NUCLEAR POWER GROUP P.O. BOX 2000 1101 MARKET ST SODDY DAISY, TENNESSEE CHATTANOOGA, TENNESSEE 37402 37379 , UNIT: TWO COMMERCIAL SERVICE DATE:CERTIFICATE JUNE 1, 1982OF AUTHORIZATION: NOT REQUIRED : NATIONAL' BOARD NUMBER FOR UNIT: NOT REQUIRED TVA TECHNICAL EVALUATION OF
, INDICATIONS IN STEAM GENERATOR 1 HOT LEG PROTRUDING TUBE ENDS 7
t I f PAGE * -
gg 'e rWel: 5EQUDYM pe g g g 1101 alAMIET SMEET BOK 200
====r==
== n,. ,
N STEAM GENERATOR #1 ROW 1 IlOT LEG TUBE END AXIAL INDICATIONS g
, DISPOSITION N During the SQN Unit 2 Cycle 6 Refueling Outage (U2C6), Axial
~leg indications were detected in 39 row 1 tubes in SG 1 at the hot protruding tube end. This is outside the tube-to-tubesheet $p' weld. Six of the 39 tubes were plugged due to defects in other g regions of the tube. These indications were assumed to originati w from both OD and ID. The indications start from the tube-end ani extend from 0.04 to 0.22 inches in length. The tube ends extend flk .
a minimum of 0.37 inches below the bottom of the tubesheet and 0.22 inches below the tubesheet cladding. Also, each tube has had partial depth hardroll for the first 2.75 inches from the ' tube end and Westinghouse Explosive Tube Expansion (WEXTEX). for the remainder of the tubesheet regions. The preventively plugged row 1 tubes were deplugged during U2C6 by Westinghouse by a TIG shrinking process. Burn-through of some of the removed plugs was found and Westinghouse preformed unscheduled Rotating Pancake Coil (RPC) examinations of the bottom 6 inches of the row 1 tubes in SGs 1 and 4. These RPC examinations detected both single and multiple axial indications at the tube ends in SG 1. No indications were detected in SG 4. m The location of these indications are not within,fthe primary-to-secondary pressure boundary. Westinghouse performed a Safety ~ Evaluation (SECL-94-133, attached) in which the indications were assumed to be cracks and the cracks were assumed to extend such that the tube-to-tubesheet weld were no longer effective as the pressure boundary. Westinghouse concluded that the axial indications do not affect the structural and leakage integrity of the pressure boundary both during operating and accident conditions. The apparent root cause was cold working of the tube end during the plug installation. No additional examinations are required. NRC has concurred with the above and approved a Technical Specification Change to both Unit 1 (amendment 189) and Unit 2 (Amendment 181). These Technical Specification Changes incorporates clarifications regarding the evaluation of steam generator tube defects by separating the portion of the tube-to-tubesheet weld from the remainder of the tube for the purposes of sample selection and repair when defects are found in this section of a steam generator tube. Based on the above, the disposition of th,e subject indications is
" accept as is" Prepared by: 2 O E 99'
,A
- Approved by: h ci m/pc/o /
Nuclear Enginedririg PAGE IM
~
*0G S '91 12'06 MOM OPL LICENS!tG TO 86158137622
., PfGE.002/008 N VAllET AtHHORITY PLANT:$EQUOYAN NUCLEAR PLANT NUCl F.AR PMER GROUP P.O. 80K 2000 2103MAM2TSTREET DAISY, TENNESSEE 37379 MTTAN00GA TENNESSEE 3N01 SECL-94-1J3
'Nstomer Reference No(s).
] UNITE i
NM##NMf MQUIMO edtNe#CEStRYlCC MfL JUNt1,198f Westinghouse Reference No(s). j NATIONAL _edAR6IAM0l#$0NWRfhNjK ' giggy -- WESTINGHOUSE SAFETY EVALUATION CHECK LIST
- 1) NUCLEAP, PLANT (S): Seouovah Unit 2
- 2) CHECK LIST APPLICABLE TO: Steam Generator Tube End Indications
- 3) The written safety evaluation of the revised procedure, design change or modification required by 10CFR50.59 has been prepared to the extent required and is, attached. If a safety evaluation is not required or is incomplete for any reason, explairi on Page 2. Parts A and B of this Safety Evaluation Check List are to be completed only on the basis of the safety evaluation performed.
_, CHECK LIST - PART A
,, 3.1) Yes_ No_X_ A change to the plant as described in the FSAR?
3.2) Yes_ No_X_ A change to procedures as described in the FSAR? 3.3) Yes__ No.X A test or experiment not described in the FSAR? 3.4) Yes.X. No___ A change to the plant technical specifications (Appendix A to the Operating License)?
- 4) CHECK LIST - PART B (Justification for Part B answers must be included on page 2.)
4.1) Yes___ No.X. Will the probability of an accident previously evaluated in the FSAR be increased? 4.2) Yes__ No.X_ Will the consequences of an accident previously evaluated in the FSAR be increased? 4.3) Yes_ No_X_ May the possibility of an accident which is different than any already evaluated in the FSAR be created? 4.4) Yes___ No X_ Will the probability of a malfunction of equipment important to safety , previously evaluated in the FSAR be increased? l 4.5) Yes__. No_K. Will the consequences of a malfunction of equipment important to safety previously evaluated in the FSAR be in, creased? 4.6) Yes___ No X_ May the possibility of a malfunction of equipment important to safety i different than any already evaluated in the FSAR be created? 4.7) Yes__ No X. Will the margin of safety as defined in the bases to any technical ; specification be reduced? l s. Page 1 of 7 l PAGE 16 1
i4JG 25 '94 13:06 FROM CR. LICENSING TO 8615843?S22 PAGE.003/000 Omet: Tele 1ESSEEVALLEYAUTHORITY PUWT:$EQU0fAH NUCLEAR PLANT 4
. NUCLEAR POWER Gil0UP P.O. 00K M l DAISY, TENNESSEE 37379 ^ 1101 MARKE1 STREET CHATTAN00GA, TENNESSEE 37401 SECL 94-133 If the answers to any of the above questions are unknown, indicate under 5) REMARKS and g i explain below.
If the answer to any of the above questions in Part (3.4) or Part B cannot be answered in the negative, the change review requires an application for license amendment in accordance with g g lI
)
10 CFR 50.59 (c) and submitted to the NRC pursuant to 10 CFR 50.90.
- 5) REMARKS: WE
' Die answers given in Section 3, Pan A, and Section 4, Part B, of the Safety Evaluation Checidist, are based on the attached Safety Evaluation, gg M
Reference document (s): o b if FOR FSAR UPDATE
-~ ., Section: Pages: Tables: Figures:
Reason for / Description of Change:
~
( SIGNATURES Prepared By: / 9 Date: 8 J '/ ff Verified By: &7 8M Date: N f<<
,. g , / / I Reviewed By: OV N V N ('-. D ate 2 " 2 "T V' Page 2-of 7 1
PAGE 1% - l
.i ALG 25
- S4 12:07 FROt1 OPL LICENSING TO 86158437622 PAGE.004/008 LNT2 i complem0rAtmateATotNOTnEQUEED coleERCIALSEIMCE DATE: JUNE 1,1982 SECL-94-133 NATIONAL BOARD NUMBER FOR UNIT: NJ NUMBER ASEGIEDPage 3 of 7 OWNER TENNESSEEVALLEY Alml0RffY PLANT:WQU0fAHIEELEAR PLANT NUCLEAR POWER GROUP P.O.SOK2000 110t JARKET STREET 045Y TENNESSEENN9 CHATTAN0OGA TENNESSEE N401
1.0 INTRODUCTION
The roll plugs from the row I mbes in all four steam generators at Sequoyah Unit 2 were removed so that the tubes can be returned to service following u-bend heat treatment. The roll plug removal process consisted of a helical scan with a TIG torch on the inside diameter of the plug with subsequent plug removal with a pulling tool. He acceptance criteria for roll plug removal is a visual inspection with a remote camera. The visual inspection on all tubes from which plugs were removed was acceptable. Following plug removal, inspection of the roll plugs from the first :wo steam generators (Steam Generators I and 4) resulted in the identification of significant burn through on some plugs. Consequently, an unscheduled Motorized Rotating Pancake Coil (RPC) eddy current examination was performed on the bottom 6 inches of the hot leg tubes in Steam Generators 1 and 4 to verify no damage from the burn through on the roll plugs, before continuing the roll plug removal process on Steam Generators 2 and 3. Bobbin coil inspection of the row I tube ends did not detect any degradation in the tube ends in Steam Generators I and 4. Bobbin coil inspection did not detect the indications because the response from the tube ends greatly exceeds the amplitude of the indications, thus masking their presence. The RPC inspection results show that 39 Row I tubes in Steam Generator 1 (33 of which are planned to be returned to service following u-bend heat treatment) have both single and multiple axial indications near the tube ends at the bottom of the tubesheet (Reference 1). All indications are on the hot leg tube ends. Rotating pancake coil (RPC) probe data for the tubes show the indications to be within 0.04 to 0.23 inch from the bottom of the tube end. The indications appear to be very short and the indications have phase angles which suggest both tube inner and outer diameter origin. Visual and eddy current bobbin inspection of the row I tubes in Steam Generators 2 and 3 following plug removal revealed no detectable degradation at the tube ends. Each Sequoyah steam generator tube has undergone a partial depth hardroll along with Westinghouse Explosive Tube Expansion (WEXTEX) expansion'over the full depth of the tubesheet. From the design drawings, the tube ends extend a minimum of 0.37 inches below the bottom of the tubesheet and 0.22 inches below the tubesheet cladding. The locations of the axial indications observed by - RPC (remaining in service) are below the tube to tubesheet weld and the hardroll and WEXTEX expansion regions (and therefore, below the primary pressure boundary). He root cause of the indications is not known. Tennessee Valley Authority concludes that the most probable cause was the cold working of the tube ends in the roll plug installation and removal processes. Visual inspection of the tube ends show no apparent damage due to a loose part in the primary system. t ne purpose of this evaluation is to address the safety significance of subsequent plant operation with the identified steam generator Row I tubes remaining in service with the tube end indicationsand the resulting technical specification changes related to this issue. His evaluation demonstrates that: 1) the integrity of the tube bundle will be maintained with the single and multiple axial indic ations present on the tube ends in Steam Generator 1, and 2) operation of Sequoyah Unit 2 fo!'owing implementation of a technical specification change which excludes removing from service tubes with PtM:st 120
. AUG 25 '94 12:00 Fr()N OPL LICEN51HG TO 86158437622 PAGE.005/008 OWNER TDGESSEE VALLEY AtRHORfTY P1 ANT:SEQUOYAH NUCLEAR PIANT A NUCLEAR POWER GROUP P.O. 80K 2000 1101 MARKET STREET- 0415Y. TENNESSEE 37379 CHATTN TENNESSEE N g g; g ;33 UNIT 2 Page 4 of 7 CERTFICATE OF AUTHORIZATION: NOT REQUIRED COIAERCIAL SERVICE DATE: JUNE 1.1982 NATIONAL 80ARD NUMBER FOR UNIT: NJ NullBER AS$GNED degradation occurring in that portion of the tube from the tube end to the start of the tube-to-tubesheet weld does not represent an unreviewed safety question. ,
2.0 REGUL ATORY B ASIS The th!n-walled tubing of the four steam generators constitutes more than one-half of the reactor coolant pressure boundary (RCPB). Maintenance of the structural and leakage integrity of the RCPB is a requirement under Title 10 of the Code of Federal Regulations Part 50, Appendix A. Regulatory Guide 1.121, "Ba.,es for Plugging Degraded PWR Steam Generator Tubes", issued for comment, is used as a standard for assessing the operability of degraded. steam generator tubing eithin the industry. Specific requirements governing the maintenance of steam generator tube integrity are contained in the plant technical specifications and Section XI of the American Society of Mechanical Engineers. Boiler and Pressure Vessel Code (ASME Code). nese include requirements for periodic inservice inspection of the tubing, flaw acceptance criteria, and primary to secondary leakige limits. These requirements are addressed below in assuring adequate steam generator tube integrity during subsequent plant operation of Sequoyah Unit 2. 3.0 EVALUATION Tube Stmetuial Integrity Assessment The locations of the axial indications observed by RPC are currently below the tube-to-tubesheet weld and the hardroll and WEXTEX expansion regions of the Row I tubes in Steam Generator 1. Consequently, it is concluded that the axial indications do not affect the structural and leakage integrity of the pressure boundary. However, should the indications represent single or multiple axial cracks on the tube ends, the potential for crack propagation into the primary pressure boundary needs to be assessed. Tube burst is precluded for cracks within the tubesheet by the constraint provided by the tubesheet. Thus the RG 1.121 criteria are satisfied by tubesheet Eonstraint. Crack lengths do not need to be limited by burst considerations and operating leakage limits are not required to detect crack lengths associated with tube burst. Addressing the potential effect of tube crack propagation on the tubc-to-tubesheet welds, in the limiting case where the weld would no longer be effective due to the presence of cracking, it is shown x in Reference 2 that even if a tube is circumferentially degraded within the tubesheet to the extent that tube separation could occur, a length of engagement of tube can be defined that would prevent pullout of the tube and would result in negligible leakage during all plant conditions. His length of . engagement has been calculated for Sequoyah Unit 2 and is less than 5.6 inches from the bottom of mg \9
f4)G 25 '94 13 08 FROM OPL LICENSING TO 86158437622 PCE. 006/008 OWlER.TEISESSEEVAllEY AINHORifY PLANT:SEQUOfAMmREAR PLANT l NUCtIAR POWER GR0tr P.O. 90K 2000 I DAISY, TENNESSEE 37379 1101 MARKET STR{ET . l CHATTAN00GA. TENNESSEE 37401 N bCL-94-133 Page 5 of 7 LANT2 CERTFICATE OF At#HOREATION: NOT REQUIRED C01AIERCIAl. SERVICE DATE: JUNE 1,1982 NATMNIAl. BOARD NUMBER FOR UNIT: NJ NUllSER ASSIGNED the WEXTEX m.wm uansmon or approximately 15 inches above the steam generator tabe end. Should the tube end indications be stress corrosion cracking, eddy current bobbin inspection of,the indications on a cycle to cycle basis is more than sufficient to monitor steam generator tube integrity. Any tube end indications not detected by the bobbin coil probe do not compromise steam generator tube integrity. No future inspections other than typical technical specification inspections are necessary. Plant operating experience shows that PWSCC axial crack propagation rate for WEXTEX plants, which is a function of crack length, is less than 0.315 inches per effective full power year in the WEXTEX zone. Ooeratine Leakare Considerations Plant operating experience shows that primary water stress corrosion cracking (PWSCC) can occur in both the hardroll and WEXTEX expansion regions in the tubesheet of a steam generator. Extensive European operating experience has been obtained with axial PWSCC cracks left in service. His operating experience has demonstrated negligible normal operating leakage from PWSCC cracks even under free span conditions in roll transitions. PWSCC cracks (if they were to occur in WEXTEX
~ expartsions) in the tubesheet region would be even further limited by the tight tubei o-tubesheet t
~
crevice and the limited crack opening permitted by the tubesheet constraint. Consequently, negligible operating leakage would be expected from cracks in the tubesheet region of Steam Generator 1 should the Row I tube end indications be representative of cracks and should the cracks propagate into the hardroll and WEXTEX expansion region of the tubes. Accident Leakare Considerations Be accident leakage must be limited to acceptable limits established by the FSAR evaluations. The postulated steam line break (SLB) leakage remains limiting for the Sequoyah Unit 2 steam generators. Reference 2 shows that the SLB leak rate for a long crack extending to an elevation approximately 7 inches below the WEXTEX expansion transition is abou '7 X 10' gpm. His leakage rate further decreases by about 40% per inch of additional depth within tie tubesheet region and as the tubesheet radius increases. Therefore, should the tube end indications represent cracks and should the cracking propagate into the pressure boundary, total SLB leakage as a result of any crack propagation would be expected to be negligible. Loose Parts Assessment Visual inspection of the Steam Generator Row I rube ends did not show any damage due to loose part impacting. Based on this observation and because the degradation is axially oriented, no tube end loose pan fragments are expected to be generated during operation. 4.0 UNREVIEWED SAFETY OUESTION ASSESSMENT g .- Plant operation with the tube end indications in the Row I tubes of Steam Generator i of Sequoyah Unit 2 has been evaluated and determined not to involve an unreviewed safety question on the basis of the following justification. I PAGE G'I ! 1 _ _ _ _ - - - _ _ _ .l
fL
. A c * 'N 12:09 FROM OPL LICENSING TO 86158437622 PAGE.007/000 mgg "N PM: NUC11AR71ANr TT 00m. m 0415Y.TENNESIEE 37m
- ZC'. ~ 133 UNIT 2 Page 6 of 7 CElmFICATE OF AUTHoltt!ATI00t NOT REQUNIED C0AltlEACIAL SEIMCE DATE
- JUNE 1.1982 NATIONAL 00 Alt 0 NUMBER F001 UNIT: NJ NUllIER ASSIGfED
- 1. Will the probability of occurrence of an accident previously evaluated in the FSAR be increased? .
No. The condition described in this evaluation results in tube integrity considerations commensurate with Reg. Guide 1.121 criteria both analytically and empirically. If the indications are hypothetically considered as cracks, the Row I tube end indications neither adversely affect steam generator tube integrity or any other component, nor does the presence of the indications alter the function of the steam generator or any other component. Herefore, plant operation with the tube end Indications present in the Row I tubes does not increase the probability of an analyzed accident such as a steam generator tube rupture event.
- 2. Will the consequence of an accident previously evaluated in the FS'AR be increased?
No. ne accidents of interest are steam generator tube rupture, large break LOCA and steam line break. The only consequence which could be caused by plant operation or by the occurrence of a faulted condition event with the tube end indications would be negligible leakage
^
between the primary to secondary systems. Such leakage is expected to be insignificant at both normal and faulted conditions. Therefore, plant operation with the tube end' indications
~
present in Steam Generator I does not result in an increase in the consequences of a previously analyzed accident.
- 3. May the possibility of an accident of a different type than already evaluated in the FSAR be created? ,
No. Any hypothetical accident as a result of plant operation with the Row I tube end indications would be bounded by the consequences of a postulated steam generator tube rupture. Therefore, operation of the steam generator in this condition does not result in a previously unanalyzed accident.
- 4. Will the probability of a malfunction of equipment important to safety previously evaluated in the FSAR be increased?
No. Plant operation with the Row I tube end indications present in Steam Generator I will not adversely affect the integrity of the steam generator or other components. Plant operation with the tube end indications does not adversely effect the function of the steam generator or any other component.
- 5. Will the consequences'of a malfunction of equiptnent important to safety previously evaluated in the FSAR be increased?
No. The only consequeoce that could be caused by subsequent plant operation of Sequoyah Unit 2 would be negligible primary to secondary leakage during all plant conditions. The installed
} systems assumed operable to mitigate the radiological consequences of an accident per plant Technical Specifications and analysis assumptions are not adversely affected by the presence of the tube end indications.
PAGR M
i cog B5
- 9 22:10 -F:.Of1 CFL LICEN51r4 TO 56158C.'622 Fr.GE.038,008 i
l ' I gign,gggggstgy AUTHORITY Pi m :gegUUrm la n IAR W '
% langAR POWER GROUP P.O.00K 3000 1101 MARKETSTREET _ .
Ma i
. CHATTAN00GA. TENNESSEE 321 x;L.94133 i Page 7 of 7 I UNif 2 '
ggyyM: ATE OF AUTHORIZATION: HUT REQUutED ' p sERVN;E DATE:JulE 1.1982 ! MATIONE 80ARD NUMBER FOR TNT: NJ NUMBER AS$4GNED 6. May the possibility of a malfunction of equipment important to safety different than that already evaluated in the FSAR be created? No. Plant operation with the tube end indications present in Steam Generator 1 does not introduce new failure scenarios or create new failure modes. De continued operability of systems required by plant Technical Specifications or assumed in accident analyses to assure i plant safety are not adversely impacted.
- 7. Will the margin of safety as defined in the basis of any Technical Specification be reduced? '
No. De locations of the axial indications observed are currently I>elow the tube-to-tubesheet weld. Consequently, it is concluded that the axial indications do not affect the structural and ', leakage integrity of the primary presure boundary. Should the cracks be single or multiple axial , cracks on the tube ends, the effect of crack propagation was evaluated. Tube burst is precluded s. for cracks within the tubesheet by the constraint provided by the tubesheet. . Therefore, crack lengths do not need to be limited by burst considerations and operating leakag_e limits are not
~
required to detect crack lengths associated with tube burst. However, primary to secondary leakage must be shown to remain within acceptable limits during all plant conditions. Leak rate testing shows that such leakage would be negligible during all plant conditions. Since the pressure boundary integrily, acceptable leak rate, and function of the steam generator are not affected by the presence of the tube end indications, the margin to safety is not reduced. ,
5.0 CONCLUSION
Bned on the above, plant operation of Sequoyah Unit 2 with the tube end indications in the Row 1 tubes in Steam Generator 1 does not represent an unreviewed safety question as derm' ed in 10 CFR 50.59 (a)(2).
6.0 REFERENCES
1. Telecopy - David Hughes to P.J. Prabhu, *TVA S2C6 EC Row 1 Roll Plug Removal SG -1 Hot Leg RPC HTE + 6 inches for Deplugged Tube inds Indications *, 8/3/94 I 2. WCAP-13532, Rev.1,*Sequoyah Units I and 2 W* Tube Plugg ng Criteria for SG Tubesheet Region of WEXTEX Expansions *, November,1992 i w i l 1 l
'* _- l
.W i =
O ' 4 i < N
J, . OWNER: TENNESSEE VALLEY AUTHORITY PLANT: SEQUOYAH NUCLEAR PLANT NUCLEAR POWER GROUP P.O. BOX 2000 ; 1101 MARKET ST SODDY DAISY, TENNESSEE ! CHATTANOOGA, TENNESSEE 37402 37379 UNIT: TWO - CERTIFICATE OF AUTHORIZATION: NOT REQUIRED COMMERCIAL SERVICE.DATE: JUNE 1, 1982
~
NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED I i ATTACHMENT 1 AUGMENTED EXAMINATIONS i f PAGR I d. 9
OWNER TENNESSEEVAllEY AUINORRY PLANT:9EQUUfAN NUttfAR PLAHf NUCLEAR POWER GROUP P.O.30K2000 .. 1110118ARKET STPEET DASY,TBSESIEE37379 ,
- CHATTANDOGA. TENNESSEE 37401 l
l tMr2 CamFICANOF AlmOWmolt NOTREQUNIED COGNERCIAL SEllVICE DATE: JulE 1.19EE : NATIONAL 90ARD NUIRER FOR UNIT: NJ Nul10ER AttleNEO j Section 20.5, RPV Nozzle Cladding. l His augn=r=1 exammation required the reactor vessel nozzle claddmg to be ultrasomcally ev=i=d at the end of each 10-year inspection interval. hese exams were p fun..ed remotely utilizing the Southwest Research Institute's (SwRI's) Program and Remote (par) device.' No . unacceptable indications were recorded during the Unit 2 Cycle 6 RPV claddmg exammatson. ! Refer to Table 1 for a summary of the indications detected and sized. TVA g- -- =-i to perform i the ISI examination as stated below:
- 1. The volumetric exammations of the RPV nozzles will be performed over the same cladded nozzle areas required by American Society of Mechanical 1Ragia-s Code. .
- 2. The ultrasonic technique for the Unit 2 cycle 6 refueling outage exammations and future exammations will be at least as sensitive as that used to conduct the exammations during the Unit 1 Cycle 6 refueling outage. ,
- 3. De exammations to be performed during the Unit 2 Cycle 6 refueling outage will !
serve as the baseline for future exammations. l
- 4. All of the detected flaws will be sized regardicss of the percent Distance Amplitude '
Curve (DAC). ,
- 5. He results of the exammations will be submitted to NRC.
, 6. He above commitments will not be removed from the Unit 2 ISI program without r
- notifying NRC.
Section 20.3, Reactor Coolant Pump Flywheel ; he requirements for the exammation of the flywheel are included in Regulatory Position C.4.b of 5 Regulatory Guide 1.14 and required the following 10 year exammations to be performed. . A full volume ultrasonic exam of the two 8 inch thick A-533, grade B plates and a surface exam i (MT) of all exposed surfaces. No unacceptable indications were found. These exammations were performed in accordance with SQN Technical Specifications and satisfies Surveillance : Requirement 4.4.10.
]
- pAgn % @ -
OWNER TDesRIEEWMLEY AURWAR PLANI:SEQUOVAH NUCLEAR PUWIT NUCLEAR POWERGRour P.O.BOK2000-
. 1101 MARKETSTREET DAISY,TDGE3SEE37379 cuarranoceA.insesussmai m
TABLE 1 Results of the 1994 Augmented Examination For Nozzle Bore Underclad Cracking Indications Exam / Distance Through-Nozzle Indication Azimuth
- From RPV Percent Length wall **
Number Number (degrees) CL (inches) DAC (inches) (inches) N-11 117 - 1 117.5 96.1 32 0.83 0.18
-2 76.0 104.3 71 Op 0.22 :
-3 84.0 102.0 80 .. i 3 0.13
-4 255.0 93.9 16 0.45 0.15 N-12 118 - 1 45.5 101.0 46 0.84 0.18
-2 12.5 94.8 40 0.73 0.13
-3 107.0 95.0 12 0.58 0.00 .
-4 155.5 94.6 46 0.57 0.00
-5 250.5 102.9 16 0.71 0.11 :
-6 233.5 94.6 42 0.54 0.00
-7 270.5 93.8 59 0.55 0.00
-8 12.0 100.1 17 0.57 0.18 ,
-9 30.5 94.7 66 0.73 0.12 126 - 1 171.0 94.2 28 0.00 0.00
-2 172.0 94.5 20 0.65 0.19 ,
-3 202.5 94.2 27 0.77 0.41 N-13 119 - 1 336.0 92.2 37 0.69 0.19 N-14 l 120 - 1 337.5 '
92.0 52 0.58 0.18 N-15 121 - 1 147.0 87-.6 45 0.72 0.15 g 129 - 1 197.0 84.2 22 0.55 0.16 2E N-16 122 - 1 137.5 103.0 94 0.71 0.27 E -2 69.5 90.9 40 0.57 0.23 l g -3 89.0 90.4 54 0.73 0.17
-4 126.0 100.9 0.59 0.18 71
-5 204.0 90.4 82 0.57 0.11
-6 140.0 98.9 32 0.55 0.00 :
O -7 105.5 98.7 62 0.85 0.22 g -8 210.0 90.7 73 0.70 0.18 28 0.59 0.21 !
. -9 270.0 100.6 j g - 10 309.0 96.5 '
36 0.87 0.20
- 11 143.0 99.0 18 0.81 0.18 ,
- 12 114.0 95.8 56 0.57 0.22 N- 17 No Recordable Indications .
N - 18 124 - 1 l 36.5 l 93.1 41 0.98 0.22 l - l
- Flaw circumferential location measured in degrees clockwise from nozzle zero.
** If number is equal to 0, there is no measurable through-wall depth. PAGE k' 9
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Owner: Tennessee Valley Authority Plant Unitt 2 Nuclear Power Group 1101 Market Street Owner certificate of Chattanooga, Tennessee Authorisation Not Required Planta Soquoyah Nuclear Plant commercial service Dates P.O. Box 2000 June 1, 1982 Soddy-Daisy, Tennessee 37379 National Board Number for Unit Not Required sheet ! of /7O volume 2 An index of the work documents which required reporting under the inclusion of the NIS-2 Report is as follows: Work Work Work Work Work Requests Reguests Requests Requests Plans
., C001251 C125753 C197013 C222410 1057-02 C003331 C125755 C197126 C256664 6674-02 ,, C003990 C125789 C197283 C256680 C003991 C126657 C197487 C256919 C005146 C127036 C197726 C257225 l C005147 C127114 C197780 C257489 C005403 C127178 C198228 C265603 C005405 C127804 C198232 C266606 C005426 C131049 C199149 C266607 C005857 C131050 C199609 C267023 C005858 C131114 C199713 C267031 C005859 C131127 C200827 C267032 C005861 C131143 C203110 C267109 C005862 C131331 C203141 C007784 C017125 C132138 C203979 C017671 C132139 C204514 C017672 C171045 C206658 C017673 C171817 C206852 C048604 C172977 C206863 C049561 C173401 C206867 C049562 C173403 C206870 C049563 C173633 C206873 C049564 C173652 C206880 C049592 C174750 C206883 C049835 C195849 C206932 C074197 C196488 C214226 C074782 C196514 C214834 C075049 C196515 C220335 -/ C082450 C196833 C221329
~
.I 3 FORM Nis.2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 1 Owner T.V.A. Nuclear Power Group Date 6 JUL 93 ' KM l~ltHF5 1101 Market Street Chattanoona TN 37402 Address Sheet b of M l'50 2 Plant Seanovah Nuclear Plant Unit 2 Name P.O. Box 2000 Soddy Daisv TN 37379 ~ 1Jn r1r Ranumer ('001751 Address Repair Orge'nization P.0, No., Job No., etc. ,
- 3. Work Performed by ' T.V.A. Seonovah Nuclonr P1mut Type Code Symbol Stamp M/A Authorization No. M/A P.O. Box 2000 Soddv 11minv TN 17179 '
Expiration Date -M / A Address
- 4. Identification of System Mranm ('anernenr R1nudnun Cverom/OOIC
- 5. (a) Applicable Construction Code AMCT R31.7 19& Edition, Cu==ar ' 70 Addenda. M/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 Rn uinter '81 Addenda
- 6. Identifiestion of Components Repaired or Replaced and Replacement Components ASME Code National Repaired, Stamped Nome of Name of Manufacturer Board Other Year Replaced, (Yes Component Manufacturer Serial No. No. Identification Built or Replacement or No) 2" dia sch Quanex N/A N/A HT# 28082 N/A Replacemerit NO
!60 :: !O6 CS pipe I
~
- 7. Description of Work Reolacement of piping which violated minimum wall found with UT inspectio.1
- 8. Tests Conducted: Hydrostatic @ Pneumatic 0 Nominal Operating "ressure O Other O Pressure 1975 psi Test Temp. R6.4 'F i
l NOTE: Supplemental sheets in form of lists, sketches, or drawings rney be used, provided (1) size is 8% in. x 11 in., (2) Informe- ' tion 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. (12/82) Thl Form (E00030) may be obtained from the Order Dept., ASME,345 E. 47th St., New York, N.Y.10017 'V l _ - ______ _._ .______ __.m____.___ -
d i
< > l I
I FORM NIS 2 (Back)
' 9.' Remarks NONE Applicable Manufacturer's Data Reports to be attached i
t CERTIFICATE OF COMPLIANCE We certify that the statements made in the rwort are correct and this FMalea--M conforms to the rules of the ASME Code, Section XI. Type Code Symbol Stamp N/A Certificate of Authoritation No. N/A Expiration Date N/A Signed M - - 8 . /> df Dete b 19 U
~
Owp or Owner's'Oesignes, Title / / / CERTIFICATE OF INSERVICE INSPECTION t, the undersigned, holding a valid commission issued by the National Board of Bnitor and Pressure Vessel inspectors and the State or Province of Tennenaee and employed by Nmrefnrd Reemm Rni1er TAT of Hartford. Conneeticut have in ted the components described in this Owner's Report during the per b to 7' II~Ib'9 and state that m Jummu t-43 *93 to the best of my knowledge and belief, thI Owner as rmed examinations and taken corrective measures describeo 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 impaied, concerning the l examinations and corrective measures described in this Owner's Report. Furthermore, neither the inspector nor his employer shell be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspa tion.n Sk _( O Commissions . 9 \ ' insp r's Signature Notenal Board, State, Province, and Endorsements Date b 19 h8 > i U2/82) , l I
i FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner TVA-Mim1etav Dnwar r:rnun norr.a pet, /76"N 1101 Market Street AIS8*
t'h m t& r nnnrum TM 't *F A A S -S A n i Shoot of OiO Aseroes "7 Remsnumh Mim1 mar D1mnF "
- 2. Plant - -
Unit norne Sv-i TN 37379
- Asse.
W O OON3 f noosir oro.na. con p.o. no .seo we., e :
- 3. work Performed by TVA Type Code symbos stamp NA !
"*"" um P.O. Box 2000 Authorustion No.
Soddy-Daisy. TN 37379 Empiretion Dete. NA Asereas
- 4. Identification of System I h@D b MM I A WE: I
- 5. (e) Applicable Construction Code bT0M N ~19MEdition: NbO Addende_ Code Case (b) Appliceb6e Edi ion of Section XI Utillred for Repaire or Replacements 19 R 0 WR1 Addenda
- 8. Identification of Components Repeired or Replaced and Replacement Components l
. ASME Code National Repaired, Stemped Name of Name of Menufacturer Board Other Yeer Replaced, (Yes Component Manufacturer Serial No. No, identification Built or Replacement or No)
}
p-Ptv-uf'r- 'TE W T yrres> 6 pN2A I2cC t_'- D 6fA IdA 19ea wh.- Ys.s ; 7 Description of Work but e Tm M A pg Mpf N ,w7" Dg$C , $ Al2 $ %g CMC >pyPneumatic Se% u-t.c> AFTerz. Mmtmmce. VAws Wio
- 8. Tests Conducted: Hydrostat6c ominal Operating Preuure C lhNt L y A b A Sytf ,
Other Pressure psi Test Temp. *F
/
NOTE: Supplemental sheets in f arm of lists, sketches, or drowings may be used, provided til she is 8% in. x 11 in., (2) Informe. tion in items 1 through 6 on this report is included on each ebest, and (3) each ehest is numbered end the number of sheets is recorded et the op of this form. 1 (12/82) This Form (E00030) mov be obtained from the Order Dept., ASME,345 E. 47th St., New York, N.Y.10017 l i U REPRINT 12/91 l I 1 I
- i
l 4 l
?
e* A 4 FORM NIS 2 (Back)
- 9. Romerks NN j eencem. u.not.cturer . o.te n.oons to w attacw f
CERTIFICATE OF COMPLIANC 8k OD We certify that the statements mede in the report are correct snd this 'hdconforms to the rules of the ASME Code, Section XI, roosir or rootooement Type Code Symbol Stamp NA Certificate of Authorization No NA Empiration Dow NA Signed 1 Owner or oudar's Deelenes, Title M b4L Date D DMMl">O 19 'N CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission imuod by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Tennessee .nd employed by Hartford Steam Boiler Insp. & Ins. Co. og Hartford, Connecticut have inspected the components described in this Owner's Report during the period NU to N~ _ and state that to the best of my knowledge end belief, the Owner has performed examinations and taken correcttwo measures described 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, concermns the eneminations and corrective meneures described in this Owner's Report. Furthermore, neither the inspector nor his employer shall be lieb6e in any menner for any personal injury or property damage or a loss of any kind arising from or connected with this inspoetion. l 9)P9 h # **- Commissions 4 bN I enepectors Gleneture Nationet soord, State, Province, and Endorrmente Dete N O 19 $ r
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner TVA Nuclear Power Group Date 10-18 94 Name K.eio l*@'95 1101 Market Street Chattanooaa TN 37402 Sheet + of MM Address
- 2. Plant Seouovah Nuclear Plant Unit 2 Name P. O. Box 2000. Soddy-Daisy TN 37379 TVA/WR COO 3990 Address Repair Organization P.O. No., Job No., etc.
I
- 3. Work Performed By TVA Type code Symbol Stomp N/A __
Name Authorization No. N/A , P. O. Box 2000. Soddy-Daisv TN 37379 Expiration Dato N/A Address
- 4. Identification of System Main Feedwater. System 003
- 5. le) Applicable Construction Code ANSI B31.7 19J)_ Edition,1970 Addende, None Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19,B.Q_, Winter 1981 Addende n
- 6. Identification of Components Repaired or Replaced and Replacement Components ASME Repaired, Code '
National Replaced, Stamped Name of Nome of Manufacturer Board Other Year or (Yes Component Manufacturer Serial No. No. Information Built Replacement or No) 2-FDH-326 N/A N/A N/A N/A unknown Repaired No
- 7. Description of Work Repaired damaced threads on clamo stud and nut.
i
- 8. Tests Conducted: Hydrostatic o Pneumatic 8o Wel Operating Pressure D l Other a M /J psi Test Temp. 'F l
_ i NOTE: Supplemental sheete m form of lists eketches or drewmos may be used. provided til ese se 8% m. s 11 m.. (2) mfome. tion m stems 1 through 6 on this report se meluded on oech sheet and (3) each sheet as numbered and the number of sheets sa recorded at the top of thee form.
)
1 6.2/82) This Form (E000301may be obtemed from the order Dept.. ASE. 346 E. 47th St.. New York. N.Y.10017 REPRINT 12/91 j -# I I 1 l l
F O t t r ( FORM NIS-215eekt ;
- s. nom-ke 16* dia. olos ASME Class 2. Discovered durino ISlinsoection for nine weld which raauired
- Appbookie Manufactww's Data Maperte to be etteshed temporary removal of cloe clamo.
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- w. ently that me sistem-ne made m me repat ne c tr.a and see renair conf,me to me ndes of m.
ASW Code, secten XI. reper er rep 6ecament Y Typ Code symmw sien, NONE Cathceto of Authwesteen No. N/A Empwmion Det. N/A e.,n.d Wa n G. O . A nd & sar ospe, - own.re os nee.'rais o.t. OcYederr /B . , e 94 cem, cAss op seemes messerios
- i. nde,s.ned. heid., e .ebd u.. 4esued y the neoon no.4 of eene, and eveesure vessei ine, ecto,. and ih. stei.
w er.vme. .f Tennessee and on,ieved my Hartford Steam Boiler itssnaction & Insurance Comoany og Hartford CT hav. insp.ned th. componente descreied e this owner'e nsport dunno te,. pened S-f1 dip 2 to H -I (a 'A P- . and etste thei . to th. best of any knowledge and behef, the Owner has performed .somneteens and teken corr.cuve measure. described si this Owner's Aspart in accordwice with the requwemente of the ASW Code, secten XI. Dy mgnme Wue eartsficate nether the mapecte nor hee artysloyer makes any werenty, expressed or imphed. eencomme th.
.smienehens and correcove measur.s described in thes Owner's Report. Furthermore, nether the mapector nor his employer eheil be beide in my manna any personal insury or property demoge or a loses of any lund memne from er connected with thss mapectuin.
.cJft" & Conmemone $U,$ AHC t insp o,e eoo. u.tior,e -d. .... prov.,c.. and endo,_,e t.
44 ,, - l i l
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i
I ~ h I i FORM NIS-2 OWNiER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner TVA Nuclear Power Grouo Date 10-24-94 '
Name MW PMM 1101 Market Street. Chattanoona. TN 37402 Sheet b of M /70 Address i
- 2. Plant Seouovah Nuclear Plant Unit 2 Name P. O. Box 2000. Soddy-Daisv TN 37379 TVA/WR COO 3991 Address Repair Organization P.O. No., Job No., etc.
- 3. Work Perforrned By TVA Type Code Symbol Stamp N/A Name Authorization No. N/A P. O. Box 2000. Soddy-Daisy TN 37379 Expiration Date N/A Address
- 4. Identification of System Main Steam. System 001 e
- 5. (a) Applicable Construction Code ANSI B31.7 19J1 Edition.1970 Addende, None code Ceee (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 193Q, Winter 1981 Addenda m
- 6. Identification of Components Repaired or Replaced and Replacement Components i
ASME Repaired, Code National Replaced. Stomped Name of Name of Manufacturer Scard Other Year or (Yes Component Manufacturer Seriet No. No. Information Built Replacement or No) ' 2-MSH-302 N/A N/A N/A N/A unknown Replaced No . 1
- 7. Description of Work Reofaced damaaed stud and nuts for Dice clamo.
p _ ,
- 8. Tests Conducted: Hydrostatic 0 D Nominal Operating Pressure D Other Pres e osi Test Temp. 'F NOTE: suppsemental sheets m form o* bets, skete:.es, or drewmss may be used, provided 11) one e e % m. m 11 en.. (2) mforme.
een m noms 1 through 6 en this report a mceuded on sech sheet, and (3) sech sheet a numbered and the nurr6er of shoots is recorded et the top of thes form. (12/82) The Form (E00030) may be obtemed from the Order Dept.. ASME, 345 E. 47th St., New York. N.Y.10017 REPRINT 12/91 M ;
j l !- 1 I 1 i i l FORM NIS 2 (Sock! l
- s. Rwr-se 32" dia. oice. ASME Class 2, Discovered durino temporary removal of oice Clamo in suonort Applicable Manufacturer's Data Reporte to be attached of ISI oloe weld insoection.
CetTMCATE oF CotApLWACE We certify that the etetenente rnade m the report are correct and this reolacement conforms to me ruise of the - ASW Cade Secoon XI. reper er repiscement Type Code Syneos Starr, NONE Cwtsfacate of Authorsahon No. _ N/A tienst.on oat. N/A Sd SMfs A M .AteA 4>.o.t. og., e, -ro.s. nee. trds - 6h kAer 24 . ,, 94 ComnCAtt oF seemivice amersCTion I, es undweiened, holdm0 e valid comnvemon issued try the National Board of Soiler and Pressure Vessel inspectore and the State er Prewmco of Tennessee and empsoyed by Hartford Steam Boller insoection & Insurance Comoany of Hartford. CT have mopeeted the componente desenbod m eue owner e Report dunne the pw d 5-# 7-91 is il-((dr - 9+ . and state thet to the best of my knowledge and belief, the Owner has pertormed aserronetsons and taken corrective measures described in thes Owner's Report m accordmco with the regurements of the ASW Code. Sectson XI. By signm0 thee certificate nether the mopector nor fus employer makes any wanenty, expressed or miplied, concemeng the enemmatione and corrective measures described m ttus Owner's Report. Furthermore, nether the mopector nor his employer shall be hable m any enanner for any personal meury or property damage or a loose of any lund ariemg from'or connected with this inspection. Corrmsmone 94 9 AM hopector's $sgnature National Board, State, Provece, and Endorsements pote M k 19 _._______.___s
i l .m FORM Nis 2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTE As Resguired by the Provisions of the ASME Code Section XI
,,o , TVA-Nuclear Power Group o.,, /O .S- 9 4 '
1101 Market Str"E t "'8~'
- Chattanooca. TN 37402-2801 Address Sheet b of M
- 2. Pient Seauoyah Nuclear Plant unit f-P.O. Box 200 Soddy-Daisy,0TN "*"*37379 W2 d005/4a Address Repelt Orgenlastion P.O. No., Job No., etc.
- 3. work Performed by TVA Type Code symbos stamp NA ,
P.O. Box 2000 Authorization No. M Soddy-Daisy, TN 37379 Empiretion pote NA Address
- 4. Identification of System Mb/M ASwe
- 6. (el Applicable Construction CodebrOM 19MEdition, Wb Addende- NA Code Case (b) Applicabie Edition of Section XI Utilized for Repairs or Repleo monts 19 8 0 W81 Addenda
- 6. Identification of Components Repeired or Replaced and Repisoement Components ASME Code National Repeired, Stemped ,
Nome of Name of Manufacturer Board Other Yeer Rapissed, (Yes ! Component Menufacturer Serial No. No. Identification or Replacement or No) Bults N24f E"/"
'2-F:N+3-55 A?occ. I db ^M 1964- 12rcam p i
- 7. Description of Work 4/EO bMMET E A L. NM ArD-2 McA'togr/NtS k i l""O E- lVI htH~i~G d A ACE.- \
- 8. Tests Conducted: Hydrostatic Pneumatic N ' el Operating Pressure O OtherO Pressure St Temp. 'F NOTE: Supplemental shoots in form of lists, sketches, or drawings may be used, provided (1) sire is 8% in. x 11 in., (2) informe-tion in items 1 through 0 on this report is included on each sheet, and (3) each ehest is numbered sad the number of sheets is recorded at the top of this form.
d (12/82) This Form (E00030) may tm obtained from the Order Dept., ASME,345 E. 47th St., New York, N.Y.10017 REPRINT 12/91 l 1 l
)
D FORM NIS 2 (Seck)
- e. nemerks MA Applicable Manufacturer's Date Reporte to be atteched CERTIFICATE OF COMPLIAfeCE We certify that the etstements made in the report are correct and this EEk C conforms to the rules of the ASME Code, Section XI. *#****'"**'
Type Code symbol stamp NA Certificate of Authorization No. NA Empiretion o te NA sign.d YAK , MEul &lW- n,,, .5 Ocypb=A. ,, % pwner or owner's opion6e, Thie CERTIFICATE OF INSERVICE INSPECTION 1, the undereigned, holding a valid commission leeued by the National Board of Boiler end Pressure Vessel inspectors and the State
,, p,,,in,, ,, Tennes see W w ioved W Hartford Steam Boiler InsD. & Ins. Co. ,,
Hartford, Connecticut have i ted the components described in this Owner's Report during the perkd I'l 7 " 9I" to [I~Ib"TY and state that to the best of my knowledge and belief, the Owner has performed eneminations and taken corrective meneures doecribed 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 worrenty, expressed or implied, concerning the eneminations and corrective measures described in this Owner's Report. Furthermore, neither the inspector nor his employer shall be liable in any menner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. M A O M2 inspector's signature Commissions ~ National soord, State, Province, and Endorsemente Date k h 19
i a i
. FORM NIS 2 OWNER *8 REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Proensions of the ASME Code Section XI
- 1. Owner T V A - N ine=1 m a r Dnwar Crniin ~
Date N ~N N* tese HOMS 1101 Market Stre"et chat +mnnnna _ TM 't *7 A n S - 9 A n 1 7 ,/ A e a j Shoot of
~ Addreen
- 2. Plent Caminvah Mint 1 mar plant Unit A
- Nome
[lv i TN '17379
- ~ Addreen Nb bbDNI47 Repelr Orsentratten P.O. No., Job No., etc.
- 3. Nrk Performed by TVA Type Code Symbol stamp NA P.O. Box 2000 Authorization No. um >
Soddy-Daisv, TN 37379 Empiretion Dete NA , Aderses
- 4. Identification of System MDL. 4N 67
'A M '
- 6. le) Applicable Construction Code ITME 19 N Edition; NOk Addende. NA Code Caos (b) Applicable Edition of Section XI Utilised for Repairs or Replacements 19 R 0 Wal Addenda
- 6. Identification of Componente Repaired or Repleoed and Replacement Components f ASME Code i National Repaired, Stemped i Nome of Name of Manufacturer Board Other Yeer Replaced, (Yes Component Manufacturer Serial No. No. Identification Sullt or Rapiscoment or No) i
' tat 24=eT 2.-N u t C2oc-.c_- d- MA AlA 192M 124-pa trace Yes r
- 7. Description of Work fdTAl 4Ab bNOW hML W EtaD hCE b(2.J:i:pG.rA tra M A IN K P(Ao4 C E ,
- 8. Tests Conducted: Hydrostatic Pneumatic t'ninal Operating Pressure Other O Pressure s Test Temp. *F NOTE: Supplemental sheets in form of lists, sketches, or drowings may be used, provided (1) size is 8% in. x 11 in., (2) Informa-tion in items 1 through 6 on th6s report is included on each ehest, and (3) each sheet is numbered and the number of sheets is recorded et the top of this form.
(12/82) This Form (E00030) may be obtained from the Order Dept., ASME,345 E. 47th St., New York, N.Y.10017 v REPRINT 12/91
. . _.= - -- - .
7 . f I l t W FORM Nis-2 (Back) l R.me,hs N A Applicense Manufacturer's Date Reports to be ettsche. j' , i i CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this bA O conforms to the rules of the ', ASME Code, Section XI. * ' *' t i Type Code Symbol Stamp M1 [ t Certifieste of Au lastion No. NA Expiration Date MA signed /.] R , AlecH N R- o,te 7 bccsma 38 94- -
<pwne,.ro.n.rso.s oie-
-I CERTIFICATE OF INSERVICE 19WECTION -
I, the undersigned, holding a valid commission leeued by the National Board of Boiler and Pressure Vessel inspectore and the State or Provinos of Tannaamme - id employed isy 88metford St=== Boiler inan. & Inn. C o. og i Hartford, Connecticut have ed the components descelhed in this Owner's Report during the period E*/ b to b~ _ and state that , to the best of my knowledge and belief, the Ovener has performed seeminations and taken corrective measures descrlhed in this ' Owner's Report in encortlance with the requirements of the ASME Code, Section XI. By signing this certificate neither the inspector nor his employer makes any worrenty, espressed or implied, aoneeming the i esaminatione and corrective measures described in this Owner's Report. Furthermore, neither the inspector nor his employer h shall be liable in any menner for any personal injury or property dernsee or a loss of any kind arising from or connected with thle inspection, f E- - Commissions Y#! I in.oe.iore sierw.ur. -es .en. m . ses.e, er. wine., one a - - 5 M t o_
,1 \
I m FORM Nis 2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code section XI 1 i, Owner TVA-Nuclear Power Group oste I l 9 4-1101 Market StrEt # #~#8'" chattanooca. TN 37402-2801 . sheet g of M /85 0 Address 4
- 2. Plant Saanovah Nuclear Plant Name Unit 1-o dy i TN 37379 Address WE MC5403 Repair Orsentration P.O. No., Job No., etc. '
- 3. work Performed by TVA Type Code Symbos stamp NA P.O. Box 2000 Authorization No. Ma Soddy-Daisy, TN 37379 Empiretion Date NA Address
- 4. Identification of System 2fEALTO 'D NY
~
AOWV\ tc
- 5. (e) Applicable Construction T(OM E 19 N Edition, b Addende. Code Case (b) Applicebia Edition of Section XI Utilized for Repairs or Replacements 19 8 0 Wal Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components ASME Code National Repeired, stemped Name of Name of Menutecturer Boerd Other Yeer Replaced, (Yes Component Menufacturer Serial No. No. Identification Built or Rept.oement or No)
METD4 UM - (ootAr4T L4sn ac,, - MA MA MA Ru w Osmmo do t l Yaw? I4ouw. di i
- 7. Description of Work DLAC CD E- AMI2f DM EA L- "ObLY bD
'TA L E{Pneumatic $&/\w HOblNda h0G
~
.5 .
- 8. Tests Conducted: Hydrostatic 0 Nominal Operating Pressure Other Pressure E bb psi Test Temp.9 L'D@ F NOTE: Supplememed sheets in form of lists, sketches, or drowings may be used, prcwided (1) aire is 8% in. x 11 in., (2) Informa- ,
tion in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of shoots is I recorded at the top of this form. j I v (12/82) This Form (E00030) may be obtained from the Order Dept., ASME,345 E 47th St., New York, N.Y.10017 i 1 I REPRINT 12/91
i I 1 l A i
?
i FORM Nis 2 (Back) i I S. Romerks N Applicable Manufacturer's Date Reports to be ettsched l I t CERTIFICATE OF COMPLLANCE We certify that the statements made in the report are correct and thisbW M% forms to the rules of the
- ASME Code, Section Xl. """"***'"*"'
Type code Symbol stamp NA Certif of Authorization No. NA Empiretion oste NA , Owner or C W W MG& $%L Dete \ D NOVFAtE2 ,e 9 & ge Deelense, Title CERTIFICATE OF INSERVICE INDECTION t, the undersigned, holding a welid commission issued by the National Board of Boiler and Pressure Vessel inspectors and the State
,, p,,,;,,, ,, Tennes see W omployed by Hartford Steam Boiler Insp. & Ins. Co. ,,
Hartford, Connecticut w1 ed W wts described
~
in this Owner's Report dur6ng the period 6"#7" N to ll'M . and stets that to the best of my knowledge end belief, the Owner has performed eneminations and taken corrective measures described in this Owner's Report in socordance with the requirements of the ASME Code, Section XI. , By signing this certificate neither the inspector nor his employer makes any worrenty, expressed or implied, concerning the eneminations and corrective measures described in this Owner's Report. Furthermore, neither the inspector nor his employer shall be lieble in any menner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. ; 83bee /PTE N Commissions [#I Mf inspector's 56eniture Nettonal soord, State Province, and Endorsemente Date - M 19 l 6
,,,.e 4
m FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI i, owner TVA-Nuclear Power Groun Nome osse // ~l@ 9 d 1101 Market Street -19 99-chattannoaa. TN 37402-2801 Address Sheet of Ih
- 2. Plant Roanovah Nuc1 star plant Name Unit b ob[1v i r TN 37379 N b O CO6M Address Mapelt Oreentration P.O. No., Job No., etc.
- 3. Work Performed by TVA Type Code symbol Stamp NA P.O. Box 200 Authorization No, M Soddy-Daisy,0 TN 37379 Empiretion oste NA Address
- 4. Identification of System N M TOl1 Y YNM MME*
- 5. (a) Applicable Construction CoMIN N 19 "Id Edition; DM Addende, M Code Cees (b) Applicable Edition of Section XI Utilized for Repairs or Repiscoments 19 80 W81 Addenda
- 6. Identificetkm of Components Repaired or Repieced and Replacement Components ASME Code Nationel Repaird Stamped Name of Name of Manufacturer Board Other Replaced, (Yes Year Component Manufacturer Seriet No. No, or Rapiscement or No)
Identification Built P.EAs.@t de4 - NLAr4T # Tern 4A MA NA k,acxu Fupmen: rdo j' % p p #3 Houw I i
- 7. Description ot Work @%% A M2.A ME b',At M M EMOL.v Aan n e
$l bEAv & Obi!A6) 5-D GD =
- 8. Tests Conducted: Hydrostatic Pneumatic 0 uominei Operatir.s Pressure V Other Pressure 7.2 6 O psi Test Temp.S416 'F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) ::re la 8% in. x 11 in., (2) Informe-tion 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 et the top of this form. 1 V
(12/82) This Form IE000304 mey be obtained from the Order Dept., ASME,345 E. 47th St., New York, N.Y.10017 REPRINT 12/91
FORM NIS 2 (Seck)
- 9. Romerks N b Applicable Manufacturer's Date Reports to be etteched CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this NMforms to the rules of the ASME Code, Section XI. #*****"'
Type Code Symbol Stamp NA Certificate of Author otion No NA Empiretion Dete NA w 3 C b/ /VlecH ENArz. - wner or Ops Deseenee. Tatie o,,e 15 rJoveucer2_ ,, 94 - CERTIFICATE OF INSERVICE INAPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boller and Pressure Vessel inspectors and the State or Province of Tennessee W employed by Hartford Steam Boiler Inso. & Ins. Co. of Hartford, Connecticut have inspected the components described in this Owner's Report during the period
- 9E to /blh ~ N and state thet to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Feeport in accordance with the requirements of the ASME Code, Section XI.
By signing this certificate neither the inspector nor his employer mehes any warranty, expressed of implied, concerning the eneminations and corrective measures described in this Owner's Report. Furthermore, neither the inspoetor nor his employer shell be lieble in any menner for any personal injury or property damage ur e loss of any kind erlsing from or connected with this inspection. N Commissions MI Inspector's sleneture National Board, State, Province, and Endorsements Dete l$ 0 19 1
l 1
- I
~
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 TVA-Nuclear Power Group oste f l -( (.0- 9 4-Nome genu t g.-ps, .
1101 Market Street chattanonaa. TN 37402-2801
~ Adeems Sheet /O of
- 2. Plent Sanuovah Nucina*- Plant Unit b P.O. box 200 Soddy-Daisv.0 "*""37379 TN Meses MRepelr C Oroenization oO54Z(a P.O. No., Job No., etc.
- 3. work Performed by TVA Type Code Symbol Stamp NA P.O. Box 2000 Authorization No. MA SoddV-Daisy, TN 37379 Empiretion Date NA Adorses
- 4. Identification of System ACTO L bMM '
A*6M E
- 5. (a) Applicable Construction Code Gi ff0 Al Y 19 NEdition; bN Addende. MA Code Ca.e (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 8 0 W81 Addenda
- 6. Identification of Components Repaired or Replaced and Repiscement Components ASME Code National Repaired, Stamped Name of Name of Menufacturer Board Other Year Repieced, (Yes Component Manufacturer Serial No. No. Identification Built or Replacement or No) hACTO(L
- Od*
[mosT" YCUCtt%# TNb Yh NA ha0M llQp M thO Pof*p %se.
-s*- t
- 7. Description of Work N ACGD lumme Smu Amersw A~o
- 8. Tests Conducted: Hydrostatic w i _;x so u _s i% e>ccc 5 ,
Pneumatic 0 Nominal Operating Pressure F Other Pressurei7 60 psi Test Temp.NN F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, prorided (1) size is 84 in. x 11 in., (2) Informe-tion 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. w' (12/82) This Form (E000301 mey be obtained from the Order Dept., ASME,345 E.47th St., New York, N.Y.10017 REPRINT 12/91
l l l
,D, <
l i l l FORM NIS-2 (Back)
- 9. Romerks M Appl 6 cable Manufacturer's Date Meports to be attached CERTIFICATE OF COMPLIANC
~
We certify that the statements made in the report are correct and this I OOL M E d:Nc4nforms to the rules of the ASME Code, Section X1. "'''***'"*"* Type Code symbot stamp NA , Certificate of Authorization No. NA Empiration oste NA r - . um ee Ciwner or OyejerDesighee, Title Oe,e i o A m rs e e ,, *
- CERTIFICATE OF INSERVICE INSPECTION 1, the undereigned, holding a welid commission issued by the National Board of Boiler and Proesure Vessel inspectors and the State
,,p Tennessee iN ,r,tford, enployw by Hartford Steam Boiler Insp. & Ins. Co. ,
Connecticut have inspected the components described in this Owner's Report during the period h */7* iI- to ll-lh'SI , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described 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 worrenty, expressed or 6mplied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the inspector nor his employer shall be liable in any menner for any permnal injury or property damage or a loss of any kind arising from or connected with this inspection. insoe'ctoPs signature Commissions I National soord, State. Province, and E ndorsements Dete in
./
.O FORM Nis 2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Resguired by the Provisions of the ASME Code Section XI
- 1. Owner TVA-Nuc1 mar power Croun ~
Det, II'di" N N
- nw 1-t>-FEF 1101 Market Str'*et e t'hm ti a nnnerm . TM 37d02-2R01 j
'/ ,f,, /
a Sheet of Ad*ess 2, Plant Eacninvah Nuclear plant Unit Nerne o dv i TN 37379 Ad*een M C OON nopeir orsenisesion p.o. No., see we,, eve, !
- 3. Work Pedormed tw TVA Type Code Symbai Stamp NA P.O. Box 2000 Authorization No. M1 Soddy-Daisy, TN 37379 Empiretion Dete NA ,
Address
- 4. Identification of System ED'b WT _
- 5. (e) Applicable Construction Code A R-CID Edition, M Addende MM Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 R 0 Wal Addenda
- 6. Identification of Components Repaired or Repieced and Replacement C:-;:=ts '
. .s ASME Code Nationel Repelred. Stamped ~~'
Name of Name of Manufacturer Board Other Yeer Replaced, (Yes Component Manufacturer Serial No. No. Identification Sullt or Replacement or No) VA L.M 6 R.V - 2
- JrJ-2-08-5k5 CesY eo to fS NA NA e fepe 4
- 7. Description of Work MCD bDN/V6
#7 6 W 81 1 E M CJ6F C,d I a m A spa,,._e. .
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure 7 Other O Pre ==ure 2 7-* psi Test Temp. N-5"P ;
NOD - Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 84 in. x 11 in., (2) Informe-tion 5 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. 112/82i This Form (E00030) may be obtained from the Order Dept., ASME,345 E. 47th St., New York, N.Y.10017 v REPRINT 12/91
r t FORM NIS 2 (Back)
- 9. R.merhs(cerauc nou doce: k/csruvennse CoNTner # 91934- l w nest reot-to,e, s oste nsoo,. to e,. e tenhoe OM NDDNW DUOC- l;;= ~ G (D le 7cs4- Ana (s 7co 7 n.
v l t i t CERTIFICATE OF COMPl.lANC We certify that the statements made in the report are correct and this OL AK#NMforms to the rules of the repeft or rapisoement ASME Code, Section XI. Type Code Symbol Stamp N1 : Certificate of Authorisation No. NA Empiretion Dois NA
-% SW 8 ECk bb Date EMOEM-- ,19 N owner i, owpAesiones, Titse CERTIFICATE OF INSERVICE BWECTION 1, the undersigned, holding a valid commission leeued by the National Board of Boiler and Pressure Vessel inspectore and the Stees or p,ovinos of Tennessee H employed by Hartford Steam Boiler Insp. & Ins. Co. og .;
Hartford, Connecticut have ineneeted me cornponenu described in th.s Owner's Report during the perior1 3*/7-92. ,o d.Na -94' . and steen that to the boet of my knowledge end belief, the Owner has performed eneminatione and taken corrective rnessures described in this Owner's Report in accordence with the requiremente of the ASME Code, Section XI. By signing this certificoes neither the inspector nor his employer makes any teerrenty, espressed or impiled, conseming the seeminations and corrective measures described in this Owner's Report. Furthermore, neither the inspector nor his employer { ehall be liebte in any menner for any personal injury or property damage or a loss of any kind arising from or connected with this j treaction.
# Commise6ons b NS
~ Nettonal Board, State. Provinos, one E._._.zz Inspector's signature Date /J 19 I
m FORM Nis-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Respaired by the Provisions of the ASME Code Section XI
- 1. Owner TVA-Nuclear Power Group Nome pet. II"Zl-N gm /-e-9.5 1101 Market Street p 2.
chattannnerm . TM " Adstrees
~1 7 4 0 2 - 2 R 0 1 Sheet 6 of N Ib
- 2. Plant Sanuovah Nuclmar P1 ant Nome Unit . b dv -
i TN 37379 MC NO Adessi noosi, orsenisation r.o. no., see uo., etc. l
- 3. Work Performed by TVA Type Code symbos siemp NA P.O. Box 2000 Authorization No. MA Soddy-Daisy, TN 37379 Empiration pote NA Adereas
- 4. Identification of System AL-TOE CCOL M AND t
- 5. (el Applicable Construction Code D3 k N* 19d Edition, D- Addende_ MA Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 80 W81 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components
- ASME Code National Repaired, Stemped Nome of Name of Menufacturer Bosrd Other Yeer Replaced, (Yes Component Manufacturer Serial No. No. Identification Mullt or Replacement or No)
N.As TOli' Ut4 - COO L A r4 "T' NA A NA NA M hh EP /dC fIfie 4 (r 3
- 7. Description of Work h UMLfD brd C' dD M1D Ml2EE Mt.;T 5 ON Ird LE:-T FL4aar=- To 2 -(o 6 - Sce4
- 8. Tests conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other O Pressure EDO psi Test Temp. M 1'*/D F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) sire is 8% in. x 11 in., (2) Informe-tion in items 1 through 6 on this report is included on each sheet, and (3) ooch ehest is numbered and the number of sheets is recorded at the top of this form.
(12/82) This Form (E00030) may be obtained from the Order Dept., ASME,345 E. 47th St., New York, N.Y.10017 v REPRINT 12/91
s
, i
+
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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 TVA-Mim1 mar Dnwar Crntin Name Oete II~d~ N f3U Pqp., ply 1101 Market Street /3 of 7T/ /' ~ 15o t' h m e t a n n n erm 'P M 't 7 A n?-S A n1 Shoot
' Addream
- 2. Plant Rarmnumh Mur-1mme D1 m nt- Unit b Nome r1v -
ia TN 37379
' Address b b Roselt Orsentration P.O. No., Job No., etc.
- 3. Work Performed by TVA Type Code symbol Siemp NA P.O. Box 200 Authorimion No. yy, Soddv-Daisy.0 TN 37379 Empiretion Date NA
- Address
- 4. Identifiestion of System NA NMT
- 5. (e) Applicable Construction Code E6 19 Edition; M Addende- M Code Case (1-) Applicable Edition of Section XI Utillred for Repairs or Replacements 19 g n ta91 Addenda ,
- 6. Identification of Components Repeired or Replaced and Replacement Components ASME i Code Nationet Repelred, stemped Name of Name of Manufacturer Board Other Yeer Replaced, (Yes Component Manufacturer Seriet No. No. Identification Built or Repiscement or No)
I?cueF %4G y W~ Lk-
'l <sB -*%$ [JD:> hY BotOA AA AlA (not (?mp;ep Alo
- 7. Description of Work YA6O Y'N6 LW M M 1M/1C- MT.
- 8. Tests Conducted: Hydrostatic Pneumatic O hominst Operating Pressure Other O Pressure psi Test Temp. 'F NOTE: Supplemental sheets in form of lists, sketches, or drowings may be used, prtwided (1) sire is 8% in. x 11 in., (2) Informe.
tion 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 the1oo of this form. V (12/82) This Form (E00030) may be obtained from the Order Dept., ASME,345 E. 47th St., New v erk, N.Y.10017 REPRINT 12/91
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_ 'l I I FORM NIS-2 (Sack)
- s. nemerks Geofi20c,T10N bDC: 034TilACM 654 MB aooi-o -tec,.r., s oote neco,te so t,. ett.et !
IIN OOD6 b" $77 bI(1I4- M D [3 7(.07 N . 1 f r l CERTIFICATE OF COMPLLANCE We certify that the statements made in the report are correct and thisbuhMforms to the rules of the ASME Code, section XI. "'*I"' l f i Type Code symbol stamp NA ' Certificate of Author ion No. NA gapir,iion o,i, NA . [ g . l 6 M b btb p.g. E l CN EoASE(2. ,to Ek Owner or og Deelense, Titse r CERTIFICATE OF INSERVICE INEPECTION l 1, the undereigned, holding a valid commission issued by the National Board of Boiler and Proesure Vessel Inspectors and the State { or Province ofTennessee W employed by Hartford Steam Boiler Insp. & Ins. Co. og i Hartford, Connecticut wi ed me wnents described in this Owner's Report during the period N"N"N toII~Ib . and stets that to the best of my knowledge end belief, the Owner has performed examinstions and taken corrective measums described in this j Owner's Report in accordance with the requirements of the ASME Code, Section XI. { Sy signing this certificate neither the inspector nor his employer makes any everrenty, empressed or implied, conoorning the examinstions and corrective measures described in this Owner's Report. Furthermore, neither the inspector nor his employer i shall be liable in any menner for any personal injury or property damage or a loss of any kind arising from or connected with this ! inspection. j 4 Commissions b[Mf i enepector's s6gnature Nationel 30 erd, State, Province, and E ndorsemente ! Dete 2d 19 W , j i l l l l l l
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. FORM NIS.2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Requirest by the Provisions of the ASME Code Section XI J
1, owner TVA-Wuc1mav Dower Grotin Nome gege l I*11-9@ ' 1101 Market Street u s-ses t'h a t- 4 a nnan-a - 'PM 1 ue. '7A09-9A01 Sheet. [ of
- 2. Plent Ramsnunh Nun 1mav D1 mMt- Unit 7-Nome
[1v-1 TN 37379
- M e ses WS CODON Reoelr Creenleetion P.O. No., Job No., etc.
- 3. work Performed by TVA Type Code Symbol Stamp NA P.O. Box 2000 Authorisation No. un ,
Soddy-Daisv. TN 37379 Empiretion Date NA Merees
- 4. Identification of System C D1 b W T, -
- 5. (el Applicable Construction CodebNILVA 19 NA Edition: NA Addende, Nb CodeCase (b) Applicable Edition of Section XI Utilised for Repeirs or Repiscements 19 8 0 N81 Addenda
- 6. Identification of Components Repeired or Repleoed and Replacement CA: ....ts s
ASME Code National Repaired, Stemped Name of Name of Manufacturer Board Other Year Rapiesed, (Yes : Component Manufacturer Seriet No. No. Identification Svilt or Replacement or No! ! [ g_v- z - 08-u,e-%5 C2esy ; Ec t o+ NA NA h e (do t
- 7. Description of Work b4ML("D bi*STs M/ m bOE5 N G R N b f=E=79 Y A vE_
iret.-4 A S P^ rt e .
- 8. Tests Conducted: Hydrostatic Pneumatic Nominel Operating Pressure }' ,
Other O Pressure3 bl# 0 psl Test Temp.NW'F I NOTE: Supplemental sheets in f arm of lists, sketches, or drowings mey be used, provided (11 size is BM in. x 11 in., (2) Inforrne. , tion in items 1 through 6 on this report is included on each ehest, and (3) each sheet is numbered and the number of shoots is , recorded et the top of this form. (12/82) This Form (E000301 may be obtained from the Order Dept., ASME,345 E. 47th St., New York, N.Y.10017 ' eg REPRINT 12/91 t
n FORM NIS 2 (Back) i
- s. R.m.rks (ecTauct,os Ccoe' 6mr*9(9.54 An WmT.r%HB0Se_
oo-. t.... ore os,s co , to b. e.,-,, E-Soe u 97s194 Amo Gr7 e z79 , CERTIFICATE OF COMPLlANCE :i We certify that the statements made in the report are correct and thisMM M MWNorms to the rules of the ASME Code, Section XI. '****'***'"*"' Type Code Symbol Stamp NA Certificots of Authorization No. NA Empiration Does NA Signed S- i 6 L M b l\l k b Dete b I CN O 19 o-nor or o.nse. pas.enes, n CERTIFICATE OF INSERVICE INEPECYlON 1, the undersigned, holding a valid commission issued by the National Board of Boiler end Pressure Vesent inspectors and the State or Province ofTennessee ,d employed lay Hartford Steam Boiler Insp. & Ins. Co. ,, Hartford, Connecticut have inspected descrlhed in this Owner's Report during the period b"/7 "9E- to Il~Ib'~94~ the componente _ and state that I to the boet of my knowledge and telief, the Owner has performed examinations and taken corrective enessures described in this Owner's Report in accordence with the requirements of the ASME Code, Section XI, By signing this certificate neither the inspector nor his employer enekes any worrenty, empressed or implied, concerning the examinatione end corrective meneures described in this Owner's Report. Furthermore, neither the inspector nor his employer i shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. Commiseicns b NT Insoector's siensture ~ National soord, State, Province, and Enoorsemente Data /d 10 v
FORM Nis 2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Proeisions of the ASME Code Section XI
- 1. Owner TVA-Nuc1 mar Power Groun Nome
' Date k I'M ~ W 1101 Market Street JAsl 4995 chatt annrwra . TM ~17d O7 -7A O1
- Sheet 5 of
, m jeg,c,,
m / Meeen
- 2. Plent carrunvah Mur laar D1mnt
- - Unit Name
$v -
is TN 37379
- Adeses N1nooserbN NN oreentration P.O. No., Joo No., etc.
- 3. mrk Performed by TVA Type Com Symbol stamp NA P.O. Box 2000 Authariastion No. M1 Soddy-Daisy, TN 37379 Empiretion Dete NA Adeems
- 4. Identification of System ACTCE -- ( A #4 T AN$ I
- 5. (e) Applicab6e Construction Code NI 7 '19 N Edition; 'Addende, A Code Case (b) Applicable Edition of Section XI Utitired for Repeirs or Replacements 19 B 0 Wal Addenda
- 6. Identification of Components Repelred or Replaced and Replacement Components ASME Coe National Repaired, Stamped Name of Nome of Monufacturer Board Other Year Replaced, (Yes Component Menufacturer Serief No. No. Identification or Replacement orNo)
Built
%AC.-TCil-- Og -
OWA'% A NA I 'A A NO M&M 5%U=D o Rpm
- 7. Description of Work @MWDbd d D b lD T W C3 N LTl D !rd h E lNCcT FwAC To 2-06-G(p%
- 8. Tests Conducted; Hydrostatic Pneumatic Nominst Opersting Pressure [
Other Pressure T7-@ pel Test Temp.M 2'N'F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 84 in. m 11 in., (2) Informe-tion in items 1 through 6 on this report is included on each sheet,and (3) sech sheet is numbered and the number of sheets is
! recorded et the top of this form.
(12/82) This Form (E00030) mey be obtained from the Order Dept., ASME,345 E. 47th St., New York, N.Y.10017 J REPRINT 12/91
~
r -: 1 e fx - FORM NIS 2 (Back)
- 9. Romerks k Applicable Manuf acturer's Date Reports to be etteer.ed i
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and th! Iconforms to the rules of the ASME Code, Section XI. '""**'***'"*"' Type Code Syrr.bol Stamp M1 Certificate of Authorizatio i No. MA Empiretion Date NA Signed i NN NM Date OMM- 19 h owner or ownygge6enee,' Title CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission leeued tw the National Board of Soiler and Pressure Vesent inspectors and the State or Province of Tennessee W employed try Hartford Steam Boiler Insp. & Ins. Co. ,, Hartford, Connecticut wi ed the components descritied in tNo Cwner's Report during the period b 7"E to N~ O ~ . and state thet ta the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI. By signing this certificato neither the Inspector nor his employer makes any worrenty, expewied or implied, concerneng the examenstions and corrective meneures described in this Owner's Report. Furthermore, neither the inspector nor his employer shall be listele in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. Commissions N O Y Ak/ .Z" anspector'h signature -Net 6cnol soord, State. Province, and Endorsements Date /c2 1g 9[ v
i l 1 01 , 3._ m' l 1 FORM NIS 2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS ; As Required by the Proeisions of the ASME Code Section XI ! l
- 1. Owner TVA-Mural mar Dnwar crnun N*** ~
Date ' 2M9 > 1101 Market Street W l'4-9.5 - ' chat +mnnnrum . PM *t *7 A A 9 -9 A n 1 Sheet f (, of bO
" Addess
- 2. Plant Amminunh Mtm1 ma v- D1 m nt-Unit b Nome dv als TN 37379 W (00DO6I
- Mereas Receir Orsentsetlen P.O. No., Job No., etc.
- 3. Work Podormed by TVA Type Code Symboi Stem, MA P.O. Box 2000 Authorisation No. um Soddy-Daisy, TN 37379 Empiretion pote NX Adorous
- 4. Identification of System O@@ OOM Pc:>m E-
- 6. (e) Applicable Construction TICWY19Mdition, W80 Addende. MA Code Case (b) Applicable Edition of Section XI Utillaed for Repairs or Replacements 19 A O LfA1 Addgndg S. Identification of Components Repeired or Reptoced and Replesoment Components
~. ASME Code National Repe6ted, Stemped Name of Nome of Menufacturer Board Other Yeer Replaced, (Yes Component Manufacturer Seriet No. No. Identification Built or Replecoment or No)
C- ft V-(oS- ~Ili h T
%. m (2cce 10 dA tdA L965 Os_ vx.e; Yes i
- 7. Description of Work FfXALFJ7 O(M bt% bN hi LC5T tZ, YA(.A/E.
$?d,Soiq Aa A 3pnee '
- 8. Tests Conducted: Hydrostatic Pneumatic 0 N - Operatine Pressure Other Pressure a 1 Temp. 'F NOTE: Supplemental sheets in form of lists, sketches, or drowings may be used, provided (1) size is 8% in. x 11 in., (2) Informe-tion in items 1 through 6 on this report is included on each eheet, and (3) each sheet is numbered end the number of sheets is recorded et the top of this form.
(12/S2) This Form (E00030) may be obtained from the Order Dept., ASME,345 E. 47th St., New York, N.Y.10017 REPRINT 12/91 l l
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7. J. i FORM Nis 2 (8ack)
- e. Romerk NA Applicebte Menutecturer's Data Reports to be attached CERTIFICATE OF COMPLIANC -
We certify that the statements made in the report are correct and this -NTconforms to the rules of the ! ASME Code, Section Xl. '***i'**'M Type Code Symbol Stamp M1 Certificate of Authorisation No. NA Empirst60n Does MA
, Signed '
8 MN b Date M 19 9k owner or j(agsbr's Oseasnee. Title CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a welid e. - i_::, issued by the National Board of Boiler and Pressure Vessel Inspectore and the State or Province of Tannaamaa - W employed by Martford Steam Boiler Inso. & Ins. Co. og Hartford, Connecticut have inspected the componente described in this Owner's Report during the period 5-11-9 2. to ll-He and stete that . to the best of my knowledge and belief, the Owner has performed eneminations and taken corrective measures described 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, empressed or implied, concerning the eneminatione and corrective measures described in this Owner's Report. Furthermore, neither the Insposeer nor his employer shall be liebte in any menner for any personal injury or property damage or a loss of any kind arising from or connected with this Inspection, h Commissions A MI snepector's signethre testiones soare, stete, Province, and Ensovemmente Dete N 1e r
1
PORM NIS 2 OUUNER'S REPORT POR REPAIRS OR REPLACEMENTS As Regesirest by the Proeieions of the ASRAE Code Section XI 1, Owner TVA-Nucimar Postar Groun '
os,e i 2. -G- 94.- N*** 1101 Market Street W l-19 -stS c h a t t a n n arum . TM *17 d D 2-2 R D 1 Asesen . Sheet - /7 of -/ Aa f 5# - / l 1
- 2. Plant Sacruswah Nuclear Plant
- - unit b l Nome P.O. Box 2000 -
Soddy-Daisy, TN 37379 W 2_ C O O S 6 (.a l .; AeWees Repelt Oreenlasteen P.O. No., Job No.,etc. {
- s. was Performed by. TVA Type Code Symbol Samp NA [
P.O. Box 2000 Authoriamion No. MA [ Soddy-Daisy, TN 37379 Empirmion os. NA ! Address -
- 4. Identification of System A C'I~ N MT A.*>AA Eb
- 5. (a) Applicable Construction Codo6MtE.r4 E 19MEdita,n, W PD Addende NA Cosie Case (b) Applicabas Edition of Section XI Utilised'for Repeirs or Replacements 19 80 . W81 Addenda l S. Identification of Components Repelred or Replesed and Replesoment C ate
^
ASME i Code Net.onal Repe6ted, Stemped . Name of Name of Manufacturer Soord Other Year Replesed, (Yes ! Component Manufacturer Serial No. No, identification Suigt or Replesoment or Nol l
\
M174% 0-Ftu-6r8-5 pat hc (O MA MA (955 Ghpgig, b , i i i i i A
- 7. oesc A4 don of work b$ A l e2 D MI2, hDKAT4M lx.[ [Agjong )gg t WGcb, f k<Wfa@ (p & Opf 3 9AL. dc<-b Fbca ou:.Nf % saTysy1my
- l S. Tests Conducted: Hydrostatic Pneumetl Nominal Operating Pressure ggg ggg A 3 Other O Pressure j psi Test Temp. 'F p g ,
NOTE: Supplementet sheets in form of lists, sketches, or drowings may be used, provided (1) size is 8% in, a 11 in., (2) Informs. tion in items 1 tnrough 6 on this report is included on each shoot, and (3) each shoot is numbered end the number of shoots is , recorded at the top of this form. l (12/82) This Form (E00030) may be obtained from the Order Dept., ASME,345 E. 47th St., New York, N.Y.10017
?
REPRINT 12/91 , I i L- - _ _ _ _ __ _ _ - t
l s~ FORM NIS 2 (Back)
- 9. Romerks Applicable Manufacturer's Data Reports to be etteched 1
b CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this bWi D conforms to the rules of the ASME Code, Section XI. '''''''***"*"' Type Code Symbol Stamp NA i Certificate of Authorization No. NA Expiration Date NA Signed Owner or Owners Omegnes, Title C4 bME Date b CW D- 19 I CERTIFICATE OF INSERVICE INSPECTION 1, the undo, signed, holding a welid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Tennessee ..id employed by Hartford Steam Boiler Inso. G Ins. Co. og Hartford, Connecticut wI ed the componente described in this Ow wr's Report during the period b ~N OA to YM~ . and stees that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described 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 warrenty, expressed or implied, x: .. -., the l examinations and corrective measures described in this Owner's Report. Furthermore, neither the inspector not his employer I l shall be lieble in any menner for any personal injury or property damage or a loss of any kind arising from or connected with thle l Inspection. h Commissions A M
, _ .rs . .r,.tur. ~.t.o s . .t.to. ,-r .r . r, ,e r,t.
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m PORM NIS-2 OWNER'S REPORT f;OR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI i 1 Owner TVA-Nur=1 mar power Croun pote lI'M ~9 M nom. - sno t-m].s 1101' Market Street /g g jg ('hm t-ta nnnna _
'I'M 't '7 A rd *> R n 1 Sheet of Address
- 2. Plant caminvah un t-l ea r plant
- - unit b meme PO Box 2000 Soddy-Daisv. TN 37379 WIZ C OO58(o'?-
i
- Address nopelt Organisation P.O. No., Job No., etc.
- 3. Work Pwformed by TVA Type Code Symboi Stem, NA P.O. Box 2000 Authoriastion No. M1 !
Soddy-Daisy, TN 37379 Empiration Dete NA Andress
- 4. Identification of System MT'0 2.- hAN T (M) e.e
- 5. (a) Applicable Construction Code pMM ..
Ig Edition, Addende Code Case (b) Applicable Edition of Section XI Utillaed for Repairs or Replacements 1g B 0 WB1 Addenda
- 6. Identification of Components Repelred or Repieced and Replacement Components ASME Code !
National Repaired, Stemped Name of Name of Manufacturer soord Other Year Replaced. (Yes Component Manufacturer Serial No. No. Identification Built or Rapiesement or No) [ t r 6 A E2E- M W- [ t hw.242er. d W-6T OOLOA NA NA Mm Oc%w Nt> ' 2ec < e F . VA t.-v 6 , i f 4 7, Description of Work lNMA LMt3 flG w bLt A- h i*.>C. '2 .sv1 ND b 6 Os L-T
\/A t.4 C- A *> /T .D>P A(2f-
- 8. Tests Conducted: Hydenotatic Pneumstic N si Operating Pressure O Other O Pressure est Temp. 'F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8% in. x 11 in., (2) Informe-tion in items 1 through 6 on this report is included on each sheet, and (3) each ehest is numbered and the number of sheets is recorded at the top of this form.
(12/82) This Form (E00030) may be obtained from the Order Dept., ASME,345 E. 47th St., New York, N.Y.10017 REPRINT 12/91
i i l l l l FORM NIS-2 (Back)
- e. Rom.rks Cororg.uCDes Ccce : Cosm <wr %re.54- Ae Applicebte Manufacturer's Date Reports to be ettecho.
DYldbMdM b -$D G C__ o b 7 N [.4 4 M T3 bD Uh . CERTIFICATE OF COMPLIANCE We certify thet the statements made in the report are correct and thish@N6Teonforms to the rules of the ASME Code, Section XI. #''*****"' Type Code Symbol Stamp MA Certificate of Authorization No. NA Expiration Date NA Signed Id . Mscia E6tz - oote G L %eseAfse1it. i. 9& Owner or oprp Dewghee. Title CERTIFICATE OF INSERVICE INSPECTION
- 1. the undersigned, holding a valid commission issued lyy the National Board of Soiler and Pressure Vessel inspectors and the State or Province of Tennessee demployedby Hartford Steam Boiler Inso. & Ins. Co. og Hartford, Connecticut have i ed the components described in this Owner's Report during the period bO ~N to / b~ . and stets that to the best of my knowledge and belief, the Owner has performed examinettons and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.
By signing this certificeto neither the inspector nor his employer makes any warranty, expressed or implied, concerning 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 Iriury or property demose or a loss of any kind arising from or connected with this inspection.
' I Commissions
. -o dv i -
TN 37379 W ft CO l'7/2.5 i Address Repelr Orsenization P.O. No., Job No., etc.
- 3. work Pedormed by TVA Type Code symbos stamp NA P.O. Box 2000 Authorization No, M 1_
Soddy-Daisy, TN 37379 Empiration Date NA Address
- 4. Identification of System M ,h t t M 6 A5Me.
- 5. (e) Applicable Construction Miod W 19 N Edition. OI Addende. Code Case (b) Applicable Edition of Section XI Utilised for Repairs or Replacements 19_BO_WB1 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components
.- ASME i Code National Repaired, Stamped Name of Name of Manufacturer Board Other Yeer Replaced, (Yes Component Manufacturer Serial No. No. Identification Built or Replacement or No)
T % m-T t- F5V- 43-b l Reex., d (JA td A 1984 D%,u,% i l
- 7. Description of work bA IM6 O CAJ M E~T' hL N Elah AF= TEA 2_
lZd/WOV e r4&g (T- 6i2. IVW t MT6r4 A N C e. .
' B. Tests Conducted: Hydrostatic Pneumet omine! Operating Pressure O Other O Pressure pel Test Temp. 'F NOTE: Supplemental sheets in form of lists, sketches, or drowings may be used, provided (1) size is 8% in. m 11 in., (2) Informe-tion in items 1 through 6 on this report is included on each eheet, and (3) each sheet is numbered and the number of shoots is recorded et the top of this form, w'
(12/82) This Form (E00030) may be obtained from the Ordes Dept., ASME,345 E. 47th St., New York, N.Y.10017 REPRINT 12/91
N FORM NIS-2 88eck)
- s. Romerks NA
=,n . us tect., ors oote as o,ts to i.e ette.hed l
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this DDAiW conforme to the rules of the ASME Code, Section XI. repeir buepienement Type Code Symbol Stamp NA , certificate f Authorization No, NA Empiretion Dete NA , siened M Ohe 5 &Tbissa- 3. M [ pner of owner's Desiones Tf CERTIFICATE OF INSERVSCE INAPECTION f, the undersioned, holding a valid commission issued by the National Board of Soiler and Pressure Vessel inspectors and the State or proyi. .g Tennessee W employed by Hartford Steam Boiler IneD. & Ins. Co. og Hartford, Connecticut have i ed the components descrited in this Owner's Report ouring the period bO-N to bb b . and state that to the best of my knowledge and belief, the Owner has performed eneminations and taken corrective measures described 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, cxancerning the eneminations and corrective measures described in this Owner's Report. Furthermore, neither the inspector nor his employer shall be liable in any reanner for any personal injury or property demees or a loss of any kind arising from or ::onnected with this inspection.
/559m -
Commissions AI inspo. tor's signatu/o 'Notionel soord, State, Province, and Endorsements Date Y gg fW t t l i J i
lr l FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS i As Required by the Provisions of the ASME Code section XI i 1; owner TVA-Nuclear Power Group oe,e f l - M " 94-N*** 1101 Market Street Aft /bl6-SP5 cha tta nntvra . 'PM 't 7 d D2 -9 B D 1
- ' Adeems Sheet of -umM-1 2, Pw Ranunvah Nur 1 mat- D1mnt some Unit b P.O. Box 2000 3 -
Soddy-Daisy, TN 37379 W R- C O IHe71
- Adeems Repair Oreentration P.O. No., Jets No., etc.
- 3. Work Personned by TVA Type Code symbol stamp NA P.O. Box 2000 Authorization No, n
__ Soddy-Daisy, TN 37379 Empiretion Oete NA Amorees
- 4. Identification of system bGAA Z 4 L YO W^^ E bD btTGOL '
AwG
- 5. (e) Applicable Construction CodeDMCaJ T 19 74 Edition, 5M Addende M Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 R 0 W81 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components ASME Code National Repaired, Stemped Name of Name of Manufacturer soord Other Yeer Repieced, (Yes Component Manufacturer Serial No. No, Identification Built or Replacement or No)
NQ.69 dr4~~ 2 &S9 %ER NA tJA rJA uw ww Ves
- 7. Description of Work b4M4 b b M67bdM DISC b3T' M t>MdT bit A M M i pC,4 seJ q D Eh/ff-E (e45T**A Tt o e4 -
- 8. Tests Conducted: Hydrostatic Pneumatic 0 Nominal Operating Pressure 7 Other O Pressure 71% psi Test Temp.@ ~6'5C>F '
l NOTE: Supplemental sheets in form of lists, sketches, or drowings rney be used, provided (1) sire is 8% in, a 11 in., (2) Informs. tion 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. r Q' $ (12/82) This Form (E00030) may be obtained from the Order Dept., ASME,345 E.47th St., New York, N.Y.10017 REPRINT 12/91
P i i t FORM NIS 2 (Back) ;
- s. Romerks NA Applicable Manufacturer's Date Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and thb3M4 conforms to the rules of the ASME Code, Section X1. 'M''***'"*"*
Type Code Symbol Stamp NA Certificate of Authoriretion No. NA Empiration pets NA , Signed' , Meca he.- os,e (7 evm a i.9& Owner or Onw(er'sMaignes, Title ~ ( CERTIFICATE OF INSERVICE INSPECTION t, the undersigned, holding a valid commission issued by the National Board of Boiler and Proesure Venel inspectors and the State or Province of Tennessee W employed by Hartford Stoam Boiler Insp. G Ins. Co. og Hartford, Connecticut W in d W cents krw in this Owner's Report during the period I'/7" N7-- to ll * / N - and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described 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 worrenty, expressed or implied, concerning the eneminettons and corrective measures described in this Owner's Report. Furthermore, neither the inspector nor his employer shall be liable in any :nonner for any personal irdury or property damage or a loss of any kind arising from or connected with this inspection. O Commissions I#I Alf"
. o-to, . . ne L,e ~etione .oe,o, . tete, ,0.ince, one s,,oo_,s l
1 Date / f 19 Nf" s' i
F 4 t a t FORM NIS 2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Rogssired by the Provisions of the ASME Code Section XI
,, owner TVA-Nuclaar Power Groun Dete I i - Il' N' nome 1101 Market Street ** h6-95 chattansvven. TN 37402-2R01 Sheet ey/ of jA a -/5*
--< i Aseems
- 2. Plant Sanuovah Nuclear Plant unit b m.m.
~
dy i TN 37379 N I2 O O l 7 l# 7 0 - Address Repelt Orsentsetten P.O. No., Joo No etc.
- 3. Work Performed by TVA Type Come Symbol Stemo NA l
"*"" NA P.O. Box 2000 Authoriaetion No.
Soddy-Daisy, TN 37379 Empiretion Dete NA , Asereas .
- 4. toontification of System bl~ AA Id AL- OL VM E- D ON T T2 Ol - [.02-es-
- 6. (el Applicable Construction C GGOAJ N19 WEdition. ND Adesnde_ Ald Code Case (b) Applicable Edition of Section XI Utilised for Repairs or Replacements 19 80 W81 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components
- ASME Code l National Repeived. Stanped '~
Name of Name of Menufacturer Board Other Year Replaced, (Yes Component Manufacturer Serial No. No, identification Built or Replesoment or Nel ! DC(26g ()ej -
'2.-(c'l 'l1(a w/Aiz.4Fa? tJA r4A rdA ba h b .
I F
?
1
- 7. Description of Work k@bArL6 YA4 h/C Dt oc Anc> Diza t.2.zis em Td,7.omia !
Disc b y A
- 8. Tests Conducted: Hydroetetic IO T To~ WsrALL Disc _ b>cv_Wc,I:edice , l Pneumatic Nominel Operating Pressure V j Other Pressure 77#C psi Test Temp.N 6%'F j 1
NOTE: Supplemental sheets in form of lists, sketches, or drowings may be used, provided til size is 8% in. x 11 in., (2) Informe- j tion 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. (12/82) This Form (E00030) may be obtained from the Order Dept., ASME,345 E. 47th St., New York, N.Y.10017 v REPRINT 12/91 i
~
FORM NIS 2 (Back)
- 9. Romerks Applicable Manufacturer's Data Reports to be etteched CERTIFICATE OF COMPLlANCE We certify that the etstements made in the report are corloct and th MM ASME Code, Section XI. '***I' ''***'"***hforms to the rules of the I Type Code Symbol Stomp NA NA NA Certificate of Authorirption No. g,,,,,, ion o,,,
Signed - M E. - Date OVM 19 9 w
' fwner or qge Debenee, Titte CERTIFICATE OF INSERVICE INSPECTION re Vessel inspectors and the State 1, the undersigholdi no vslid commission issued by the gationart or d gfteam Boiler and ,, ,,,MFlr oro, sgeconnect.icud So er Insp. & Ins. Co. ,,
have inspected the components described r
- in this Owner's Report during the period 8~l7~ 9A-- to I~NF ~S4 and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI. .
By signing this certificato neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the inspector nor his amployer shall be liable in any manner for say personal injury or property damage or a loss of any kind arising from or connected with this inspection. N Commissions A bY NI Inspector's s6eneture' Notenal Soord, State, Province, and Eridorsements Dete M, 19 e .g'
m FORM Nf6 2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 1, owner TVA-Nuclear Power Group oete i 1 -l "? 1101 Market StrEt .y g ,-- e[ /N N'O Chattanooga. TN 37402-2801 Sheet of Aoeems
- 2. Plent Seouovah Nuclear Plant unit b P.O. Box 2000 "*"*
Soddy-Daisy, TN 37379 W 2- CO l'ho'73 Adeses Repair Orsenization P.O. No., Jeb No., etc.
- 3. work Pwformed by TVA Type Code Symbol Stamp NA P.O. Box 2000 Authorization No. NA i Soddy-Daisy, TN 37379 Expiretion Dete NA Adereas
- 4. Identification of System H EeAZAt - OLUM E bD ^4 "I~i2O L.- M
. NAA 6
- 5. (a) Applicable Construction Code NLfaAIN 19 N Edition, b Addende b Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 19 15 0 W81 Addenda
- 6. Identification of Components Repeived or Replaced end Replacement Component's
.~
ASME Code National Repaired, Stamped Name of Name of Manufacturer Board Other Yeer Replaced, (Yes Component Manufacturer Serial No. No. Identification or Replacement or No) Built Do (24=3 d,J-
'l-fet- 71 1 Wa ease- NA eda- 'NA vm Povero Vcs
- 7. Description of Work _ k LACEh iSC A MEMBLN.
- 8. Tests Conducted: Hi drostatic Pneumatic Nominal Operating Pressure OtherO PressureAD pel Test Temp.M2 ~ 6 F NOTE: Suppetmental sheets in form of lists, sketches, or drowings may be used, provided (1) size is 8% in. x 11 in., (2) Informe-tion 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 et the top of this form.
v (12/82) This Form (E00030) may be obes;ned from the Order Dept., ASME,345 E. 47th St., New York, N.Y.10017 REPRINT 12/91
r%, l l l FORM NIS 2 (Back) l
- 9. Romerks Applicable Manufacturer's Date Meports to be ettsched CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this bt*EMTconforms to the rules of the ASME Code, Section Xl. #" "' 'spiecomer6t Type Code Symbol Stamp NA Certificate of Authorization No. NA Expiretion Date NA S ned NUflboi /V\em Sao-Cwner or 01Ars abelones, Tit 6e Oste 17 NovemeE-r_- i 94 -
CERTIFICATIE OF INSERVICE INSPECTION 4 1, the undersigned. holding a valid commission issued tw the National Board of Boller and Prosaure Vessel inspectors and the State Tennessee of or ProviErtford, Connecticut**wd employed by Hartford Steam Boiler Insp. & Ins. Co. ,,
,g ,
%; ,,, g , w in this Owner's Report during the period ION to N*NN and state that to the best of my knowledge end belief, the Owner has performed examinations and taken corrective measures described 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 worrenty, exproceed or implied, concerning 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 irdury or property damage or a loss of any kind arising from or connected with this inspection. N N Commissions bI E inspector's signature ' Notional soord, State, Province, end Endorsemente Date / /0 19 kI
..s
p o n l FORM N18-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Requiresi by the Provisions of the ASME Code Section XI !' i, o wner TVA-Nuclear Power Group pe,e lC "7 ! 1101 Market StrEt " M'"
,,,,,, C h a t t a n o o c a T N 37402-2801 ueres. sheet Z.3 o, _f M &
- 2. Plant Sequoyah Nuclear Plant unit b Nerne dy i TN 37379 NI2 O b nod
Amareas Repelr Orsenization P.O. No., Jote No., etc.
- 3. work Performed by TVA Type Code symbos siemp NA P.O. Box 200 . Authorization No, M1 Soddy-Daisy,0TN 37379 Empiration os,e NA Amores.
- 4. Identification of System WA TF42__
- 5. (e) Applicable Construction Code (~2 ILS 19 b Edition: Addende, Code Case ib) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 8 0 W81 Addenda
- 6. Identification of Components Repaired or Repieced and Replacement Components ASME Code Nationel Repaired, stemped Name of Name of Manufacturer Board Other Year Replaced, (Yes Component Manufacturer Serial No. No. Identification Built or Replacement orNo)
\/ALNG 04-G 6-SOFi ha ' MA (dA rdA Kdowa birxe s M i
-l
- 7. Description of Work Ciz PJM AA ED b r%tth h M e Al f M 6, Awh Atstg
% MVC DTCf\M bV'N OA y4D 'htWETdN DAMNT OWE
- 8. Tests Conducted: Hydrostatic Pneumatic inal Operating Pressure k@ j A./ % .
Other Pressure d Test Temp. *F NOTE: Supplemental sheets in form of lists, sketches, or drowings may be used, provided (1) size is 8% in. x 11 in., (2) Informa-tion 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 et the top of this form. j v' (12/82) This Form (E00030) may be obtained from the Order Dept., ASME,345 E. 47th St., New York, N.Y.10017 REPRINT 12/91
T 5 t 0 FORM NIS 2 (Back)
- 9. Romerks lh[# O b Y U 6 M F 7 P)rM OS bCh WES.
Aopuc.w.'u.not.ctor.r . oe= neoclis to w stuened CERTIFICATE OF COMPLIANCE We certify that the statements made in the report ero correct and this OAi % forms to the rulee of the ASME Code, Section X1. *' # "' ' s Type Code symbol Stamp NA ! Certificate of Authorization No. NA Empiration Date NA Signed l i M8Nk fnS--- Dete Nh 19 9M ner or%frer's 3 CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Soiler and Prosauro Vessel inspectors and the State or Province of Tennessee W employed by Hartford Steam Boiler Inso. G Ins. Co.of Hartford, Connecticut wi ed the components described . In this Owner's Repori during the period k 'N to N~b and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described 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 worrenty, expressed or impiled, concerning the l examinations and corrective moseures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liebte in any menner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
/h h Commissions dL No M 'I4IT I inspector's sinature Notenal Soerd, State, Province, and Endorsements t
Dete M 19
1 W FORM NIS 2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- ,, o, e, TVA-Nuclear Power Group oe,e / Z 94-1101 Market StrTet ~"
Chattanooga, TN 37402-2801 sheet N of
,M "/50
/
Aseen
- 2. Pient Sequoyah Nuclear Plant unit S P.O. Box 2 0 0 0 "***
Soddy-Daisy, TN 37379 Amese frJe C 0495G / neesir orsenteetion P.o. we., a e, we., me.
- 3. work Performed by TVA Type Code symbos siemp NA P.O. Box 2000 "'** NA Authoritetion No.
Soddy-Daisy, TN 37379 g,,i,e, ion os,e NA Aserese
- 4. Identification of System mob NMI '
W646
- 6. (a) Applicable Construction MME19[#b Edition, Addende AA Coo; Case i
(b) Applicable Edition of Section XI Utillaed for Repeirs or Maplacements tg 8 0 W81 Addenda
- 6. Identification of Components Mapeired of Repieced and Maplesoment C:-._-. J.ts ASME Code National Mapeired, Stamped Name of Name of Menufacturer Board Other Year Mapleoed, (Yes Component Manufacturer Seriet No. No. Identification Built 8' Maplesoment of No)
- STE4m WroTW'i-1 didataeA1De- Hoosa IS2 l lo6-let AJA 1918 Arsusce.- Yes Num bee- wg-I
- 7. Description of Work /2emoVeO 93 [f465 4Nb lal37ALU5b /4 b6S OV Macnesw.s<. m3 Og Born JHLESAoun OUTLET 3D63 . '
- 8. Tests Conducted: Hydrostatic Pneuma lic Nominal Operating Pressure O Other C Pressure A pel Test Temp. *F
[ NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (11 size is 8% in. x 11 in., (2) Informa-tion 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 et the top of this form. (12/82) This Form (E00030) may be obtained from the Order Dept., ASME,345 E. 47th St., New York, N.Y.10017 v' REPRINT 12/91 l l
O FORM NIS 2 (Back) e.n orms N A Applicable Manufacturer's Date Reports to be etteched i J CERTIFICATE OF COMPLIA ,_, We certify that the statements made in the report are correct and th . -% -- elonforms to the rules of the ASME Code, Section XI. 'd#'***'"*"' Type Code symbos siemp NA Certificate f Authorization No. NA g ,,3,,,,,, o ,,, E se- , M bM Dete -- 19 4 fwner or owner's t __ .. ,"_ Mt6e . CERTIFICATE OF INSERVICE INSPECTION f, the unde i olid commission issued by the ggg giggPgre g Inygg gState t.forG, Connect 1Cu *' have inspected the components described in this Owner's Report during the period U*N to l/"b"N and state that to the best of my knowledge and belief, the Owner has performed examinations and taken correctiw measures described 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 worrenty, expressed or implied, concerning the eneminet6ons and corroc eve measures described in this Owner's Report. Furthermore, neither the inspector nor his employer shall be liable in any ment v for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. N o o . n.tua Commissions ! Af in ~.. . ..,o. ...,e. ,o.... . g r,oo_,s i Date / 19 M s i
^.
FORM Nit-2 OWNER'S REPORT FOR REPAIRS OR REPLACEEENTS As Required by the Provisions of the ASME Code section XI 1, owner TVA-Nuclear Power Group
~*
oote /2 ~/ 9-94 1101 Market Street "#" Chattanooaa. TN 37402-2901 ueen. sheet ~2 5 o, /49 /So
- 2. Plent Secuovah Nuclear Plant Unit I-Nome dy i TN 37379 Meses WE CO495GZ.
Repelr Creentration P.O. No., Job No., etc.
- 3. Werk Performed by TVA Type Code symbol sterne NA P.O. Box 2000 Authorization No, n Soddy-Daisy, TN 37379 Empiretion oote NA Moreas
- 4. Identification of System M0NE Mb wa -
- 5. (e) Applicable Construction Cc TIM 19 N Edition, k Addende,-- b Code Case (b) Applicable Edition of Section XI Utillied for Repairs or Replacements 19 8 0 W81 Addenda
- 6. Identification of Components Repelred or Replaced and Replacement Components ASME Code
~
National Repaired, Stemped Nome of Name of Manufacturer Boerd Other Year Replaced, (Yes Component Menufacturer Serial No. No. Identification Sullt or Replacement or No) WEoTa%- (dre*MiveatseA7Dt. House: /327. GB 4ip3 Ale 1971 A~t % aamssa. usa y 2 ,
- 7. Description of Worit_
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating P? essure Other Pressure psi Test Temp. 'F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8% in m 11 in., (2) Informe-tion 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 et the top of this form. (12/82) This Form (E00030) may be obtained from the Order Dept., ASME,345 E. 47th St., New York, N.Y.10017 v REPRINT 12/91 I i
i ,
,~
l 0 FORM NIS 2 (Back)
- 9. Romerks MS NO MifE> DN M*
r.rs o.,e .epoes to t e .,,.e, d LAtMMen d% Born Tiwrop-..or,.t.c,.later Ao 007ter Saes.- I i i CERTIFICATE OF COMPLIANC We certify that the statements made in the report are correct and th conforms to the rules of the M'*P'***'"*"' ASME Code, Section Xl. . I Type Code symboi Stamp NA NA Empiration Date NA Certificate o Authorization No. Signed - 3 1 N O Date M Y- 19 N gwner or ownere oes%T1tre i CERTIFICATE OF INSERVICE INSPECTION
- 1. the under h a valid commission issued by the N o le ggVg gtese or Provings of and employed by of Hartford, Connecticut , g in this Owner's Report during the period 6'"O'N to O*bN and state that to the best of my knowledge end belief, the Owner has performed examinations and taken corrective measures describst!in this Owner's Report in accordance with the requirements of the ASME Code, Section XI. 1 By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the eneminations and corrective measures described in this Owner's Report. Furthermore, neither the inspector nor his employer shall be liable in any menner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
h # Commissions I MME Inspectors signe'tur's Net'onal Board, State. Province, and Endorsements Date / [ 19 l l 1 d
FORM NIS 2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Proeisions of the ASME Code Section XI
- 1. Owner TVA-Nuclear power Croun '
Dete @N~M nome near ta.sgs 1101 Market Street g .e chat t annnrva '
. 'PM ~4 7 A n ? - ? n n i Sheet of W7
' Adorses
- 2. Plant Reminvah Munlaar D1 m n t-
~ ~
Nome Unit I
$v-i TN 37379
- Address EO 9N Flecair Orsenivation P.O. No., Job No., etc.
- 3. Work Performed by TVA Type Code Symbos Stamp NA P.O. Box 2000 Authoriretion No. um Soddy-Daisy, TN 37379 Empiretion Date NA Aderees
- 4. Identification of System NNE A bNt6 -
- 6. (e) Applicable Construction M 19M Edition, Addende- A Code Case (b) Applicable Edition of Section XI Utillred for Repairs or Rootecoments 19 a o Wa l Addenda
- 6. Identification of Components Repelred or Repieced end Replacement Components i ASME Code National Repaired, Stemped Name of Nome of Manufacturer Soerd Other Yeer Replaced. (Yes Component Menufacturer Serial No. No. Identifiest'on Built or Replacement or No)
. M ui -.
Ensirvsmercur_. ss /.323 (,6-(ed Al4 m/ depomo % Naos aez. 3
- 7. Description of Work MO E b D bF [2 dM-3 M MOV6 bMIR
.$:;one Mnox5 Swan u m us, D w s. @ m a n p o a.
- 8. Tests Conducted: Hydrostetic Pneum ic Nominal Operating Pressure O Other Pressure psi Test Temp. 'F
/
NOTE: Supplemental sheets in form of lists, sketches, or drowings may be used, provided (1) size is 8% in. x 11 in., (2) Informe. tion 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 et the top of this form. (12/82) This Form (E00030) may be obtained from the Order Dept., ASME,345 E. 47th St., New York, N.Y.10017 v REPRINT 12/91
h W j FORM Nis 2 (Back)
- 9. Momerks
, acon I, -t ,-. o.te ,t.o. s . o .t t
-1 I
l j l CERTIFICATE OF COMPLBAtlCE ! We certify that the statements made in the report are correct and thlebMO conforms to the rules of the ASME Code, taction XI. '***'*" " l Type Code Symbol Stamp NA Certifieste of Authorisation No. NA Empiretion Dete NA
~
_w.r v _avsma. to daaA a. zo w - . ,, w CERTIFICATE OF INSERVICE INW'ECTION l 1, the undersioned,teoiding a valid commission issued luy the National Board of Boiler and Pressure Vessel inspectors and the 9tsee or p,,,in,,,, Tennessee and employed 1sy Hartford Steam Boiler Insp. E Ins. Co. ,, Hartford, Connecticut- w w the e descrilsed in this own.r s neport durin the p.riod 5 9 2- to It-/& . e,,d at e ti,et to the host of my knowledge and belief, the Owner has performed examinations and teken corrective enessures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI. By signing this certificato neither the inspector nor his employer makes any worrenty, expressed or implied. _.._ _ - . the esaminations and corrective meneures described in this Owner's Report. Furthermore, neither the inspector nor his employer shall be Hable in any manner for any personal iniury or property damage or a loss of any kinst arising from or connected w6th this inspection. One= Commissions d., ##f Asv7
. so or. . .e ..t _ .
s r . _ poem / ig M
i
-~...
FORM Nis 2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI !
,, m.e, TVA-Nuclear Power Group g,,, /2.;ro-gg 1 1 0 1 M a r k e t S t E &"I t MNM
_ Chattanooga, TN 37402-2801 sheet 2'7 of M /N Amee. ;
- 2. Pient_ Sequoyah Nuclear Plant . Unit 'd-P.O. Box 2 00 0 "*"*
Soddy-Daisy, TN 37379 use. LJ2 CO4954r3 mooeir oreenisecen p.o. No .sen u ., etc.
- 3. work Performed by TVA Type Code Symboi Stamp NA P.O. Box 2000 '""* n Authorimetion No.
Soddy-Daisy, TN 37379 Empiretion Dete NA Amoreas
- 4. Identification of System MN I ASMC
- 5. (el Applicable Construction CW M 19 d6. Edition, M4 Addende_ M Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1g 8 0 W81 Addenda
- 8. Identification of Components Repolred or Repieced and Replacement Components !
.. ASME Code National Repaired, Stamped
'~~ Replaced, (Yes Name of Name of Menufacturer Boerd Other Yeer Component Menufactufer Serial No. No. Identification Built or Replacement or Nol Sream WesnN4-W70e House. /333 46To4- A/4 /,97I are- %e, 1 Naaben. Amr
.3 l
1 l l i
- 7. Description of Work M
- 8. Tests Conducted: Hydrostatic Pneu e 0 Nominal Operating Pressure Other Pressure O" psi Test Temp. 'F
/
NOTE: Supplemental sheets in form of lists. sketches, or drowings mey be used, provided (1) stae is 8% in. x 11 in., (2) Informs. ; tion 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. (12/82) This Form (E00030) mev tm obtained from the Order Dept., ASME,345 E. 47th St., New York, N.Y.10017 v .' REPRINT 12/91
i l l l l O . i' FORM NIS 2 (Back)
- 9. Romerks MS MN N [d M )
Applicable Manufact ter's Date R rts to be etteched W M M W D D u n.E T S M 5 . CERTIFICATE OF COMPLIANC We certify that the statements made in the report are correct and th'- M conforms to the rules of the ASME Code Section XI. **' ' Type Code Symbol Stamp NA Certificat f Auth laation No. NA g ,,;,,,;,, o ,,, M Sig.+ e N Date M % g Owner 4r Owner's Des @ttle' 19 CERTIFICATE OF INSERVICE INSPECTION t, the umiers ing a valid commission issued by the ggigg ogi gPgp gi i g g t g State Yartford, Connect 1Cu ! have inspected the components described in this Owner's Report during the periodb N*N toO~O and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures describod in this Owner's Report in accordance with the requirements of the ASME Code, Section XI. By signing this certificato neither the inspector nor his employer makes any warranty, expressed or implied, concerning 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 erising from or connected with this inspection. Inspector's 56snature Commissions I#I NE National goerd, State, Province, and Endorsements Date / 19 I 1 I w I
- - . ~ .
'r . FORM Nis.2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Regesired by the Provisions of the ASME Code Section XI 1, owner TVA-Nuclear Power Groun N=
~
pote /dZOSb ] 1101 Market Stre"*t e / der 1-n9-We ' chat +mnanna . -
'PM 1'7 A 09-2 A01 ue.es Sheet of- M :
1
- 2. Plant Ranunv_ ah Mur=1 mar Plant Unit dv-i TN 37379
- Adeses N k- 0495(a4- l nopelt Orsoneset6en P.O. No., Job No., etc.
- 3. Work Performed by TVA Type Come symbos stem, NA I P.O. Box 2000 Author 6*mion No, M1 I SoddV-Daisy. TN 37379 Espirei.on oeis NA >
Aemees
- 4. Identification of System -
Aaba4EE
- 5. (e) Applicable Construction C " - M 10 N Edition, b Addende bIk Code Case (b) Applicebee Edition of Section XI Utilised for Repairs or Replacements 19 8 O W81 Addenda
- 6. Identification of Componente Repaired or Rapieced and Replesoment C , _.u.te
~
ASME Code National Repeered, Stemped Name of Name of Menufacturer Board Other Year Repleoed. (Yes Component Manufacturer Serial No. No, identification Built 8' Replacement or No) t deup8>M '/DT4-44eN a mrtwa_ tiooms, l$24 (8-ta5 4 (971 te %3 N Be ES- mr d- ! lI
- 7. Description of Wor # O
- 8. Tests Conducted: Hydrostatic Pneumet Nominal Operating Preneure )
Other Prosauro psi Test Temp. 'F NOTE: Supplemental sheets in form of lists, sketches, or drowings moy be used, provided (1) sire is 8% in e 11 in., (2) Informs. tion in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the nurnber of sheets is recorded et the top of th.'s form. 112/82) This Form (E00030) may be obtained from the Order Dept., ASME,345 E. 47th St., New York, N.Y.10017 REPRINT 12/91
r 1 FORM NIS 2 (Back) I
- 9. Remarks # '-71 b dh DMnN N N wi-o uon.,ano,.es oots asto,ts to w att-h.d '
On 3%rra Imar % oo rtf r sm. CERTIFICATE OF COMPLIANC We certify that the statements made in the report are correct and this "" onforms to the rules of the ASME Code, Section XI. *I''*****"' T Type Code Symbol Stamp NA Certificate f Auth stion No. NA Empiration Date NA Signed ( yn.r.,nn.<em.m.y
. =d AAcca Gme os,e do betsmesa. ,, s4 CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued ty the National Board of Boiler and Pressure Vessel inspectors and the State ,
or Province of Tennessee and employed by Hartford Steam Boiler Insp. & Ins. Co. ,, Hartford, Connecticut how inspected the components described in this Owner's Report during the period 0*I7"92" to N~ 'N and state that , to the best of my knowledge and belief, the Owner has performed examinations and taken correctiw mesouros described in this f 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 warrenty, expressed or implied, concerning 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 irdury or property damage or a loss of any kind arising from or connected with thle inspection. S Commissions b[ MN Inspector's sgnatore National goerd, State Province, and Endorsemente Deta l 19 Y t
FORM NIS 2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. owner TVA-Nuclear Power Group oete I ( ~ ll ' 94' - ,
1101 Market StrE t a[ Chattanooaa. Ameen. TN 37402-2801 sheet SO of i' e
- 2. Pient Secuovah Nuclear Plant Unit' 1 P.O. Box 200 "*'"*
Soddy-Daisy,0 TN 37379 klE C_.o4'3 59 7-Address Repair Oreenlaation P.O. No., Job No., etc.
- 3. work Performed by TVA Type Code symbol stamp NA P.O. Box 200 Authorization No. M1 Soddy-Daisy,0 TN 37379 Expiretion oote NA Adoreas *
- 4. Identification of System MTOb 4 A> e.
- 6. (e) Applicable Construction TfDdE 19 O Edition, NA Addende f4 0 I Code Case (b) Appilcable Edition of Section XI Utilized for Repairs or Replacements 19 8 0 W81 Addanda
- 6. Identification of Components Repaired or Replaced and Replacement Components ASME Code National Repaired, Stemped Name of Name of Manufacturer Board Other Repleesd, (Yes Yeer Component Manufacturer Serial No. No. or Replacement orNo)
Identification Built 6 TEA m i h&d64LATOL lMEMi%- l D2 2.- M61'0 3 /dA 1911 hec, b j Ab q,. Nos *
- 7. Deecription of Work I FDL.AC C Or4G- 7 tMAG-M IM M WAv ST t.; t> Ao .l
- 8. Tests Conducted: Hydrostatic NOT AccemeM- l Pneumatic 0 Nominal Operating Pressure Other O Pressure 17 N pal Test Temp.9 2 ~#M F NOTE: Supplemental sheets in form of lists, sketches, or drewings trey be used, provided (1) site is 8% in. x 11 in., (2) Informe-tion 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.
%d (12/82) This Form (E00030) may be obtained from the Order Dept., ASME,345 E 47th St., New York, N.Y.10017 REPRINT 12/91
E~ s FORM Nis 2 (Back)
- e. nemerks /\/A Applicab4e Menutecturer's Date Maports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and thisbMGMISIbforms to the .ules of the ASME Code, Seetion Xl. '***IM***'"*"*
Type code Symbol Stemp NA Certificate of Authorization No. NA Empiretion Date NA Siened r ME0N bdE - Date C c'rW'5642- to 9b owner or' Owner's Desienee. Title CERTIFICATE OF INSERVICE INSPECTION t, the undersigned, holding a valid commission leeued by the National Board of Boiler and Pressure Vessel inspectors and the State
,, ,,,,;,,, ,, Tennes see W ernewed W Hartford Steam Boiler Insp. G Ins. Co. ,,
Hartford, Connecticut wi ted me eu wribed in this Owner's Report during the period b"[7"9E toIt*NF* end state that to the best of my knowtedge and belief, the Owner has performed eneminations and taken corrective measures descrlhed 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 worrenty, expressed or impiled, concerning the eneminations and corrective measures described in this Owner's Report. Furthermore, neither the inspector nor his employer shell be lieble in any menner for any personal irQury or property damage or a loss of any kind arising from or connected with this inspection. O Commissions b NI anspector's siensture National Board, State, Province, and Enesorsemente Dete Y lS 19 k
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J 4 - l i
+
m,- PORM NIS 2 OWNER'S REPORT POR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI q 1, Owner TVA-Nuclame Power Groun - new ' /O-/7" 9 4' Name puse usb-Jr.s 1101 Market Street Sheet y ' / A'I^ feier - c h a t t a n n nrum _ 'PM 't?AO9-?A01 of
" Address
- 2. Plant Caminvah Mine1 mar D1 m nt- Unit Nemo.
[tv i TN 37379 M neo ONWJ ir oreenisation p.o. N.. J.t. No., me.
- udreas
- 3. work Performed by TVA Type Code symbos stamp NA
"*'"' 'Mr P.O. Box 2000 Authoriaation No. a Soddy-Daisv, TN 37379 Espiretion Dew NA
. u dreas :
- 4. !dentificmion of sysum bwATf"WL
- 5. (a) Applicable Construction Code M 19.6/d_ Edition, Nb Addende A- code caos (b) Applicable Edition of Section XI Utilized for Repairs or Rapiscements 19 A O WA1 Addenda
- 6. Identification of Components Repoited or Repisood and Replacement Ca. _ _- ts ,
~.. ,
ASME Code National Repeived, Stemped Name of Name of Manufacturer Soord Other Yeer Replaced, (Yes l Component Manufacturer Series No. No, identification 8vilt or Rapiesement or No) i VA.v'E pt-t 60 9 k/AlstoAtTH WA AIA Apn. pan,u %g rJo l
- 7. Description of Work bMIRO T-#G MY bD b47 Y 61.2)rNde Ma '
MA(,,ttidIA6h .
- 8. Tests Conducted: Hydrostatic Pneumatic nel Operating Pressure Other O Proceurs Test Temp. 'F NOTE: Supplemental sheets in form of lists, sketches, or drawines may be used, provided (1) stre is 8% in. x 11 in., (2) Informe-tion in items 1 through 6 on this report is included on each shoot, and (3) each shoot is numbered and the number of sheets le ;
recorded et the top of this form. I w' l (12/82) This Form (E00030) mey be obtained from the Order Dept., ASME,345 E. 47th St., New York, N.Y.10017 l l REPRINT 12/91 J
I FORM NIS 2 (Back)
- e. Romerke l9k0 A TkVL' DD AFT 0LE V2 4A-Ds As w< u< s .
- AppHceble Manufacturer's Date Pleporte to be etteched CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this / ' 7MfI2-" conforms to the rules of the t ASME Code, Section XI. repeVor replacement Type Code Symbol Stomp NA t Certificate of Authoritation No- NA Empiration Date NA Signed c f / Vl0M b6E- Date /7 d7MEO *19 b4" pwner or owners CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a welid commiss6on issued by the National Board of Boiler and Pressure Vessel inspectors and the State or Province of Tennessee W employed by Hartford Steam Boller Inso. & Inn. Co. of Hartford, Connecticut have in ted the components described in this Owner's Report during the period bN to N"/I and state that t to the best of my knowledge and belief, the Owner has portormed examinations and taken corrective meneures described in this Owner's Report in accordance with the requi c .ents of the ASME Code, Section XI.
By signing this certificate neither the inspector nor his employer makes any worrenty, expressed or implied, conerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the inspector por his employer shall be liebte in any menner for 'ury or property damage or a loes of any kind arising from or connected with this I inspection. A Commissions N7 a snepectore signature' Nationel Board, State. Province, and E.ndorsemente Dete / 19 i l 4 l l i
,a n l l
FORM NIS4 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS ! As Required by the Provisions of the ASME Code Section XI i
- 1. Owner TVA-Nur=1 mar Power Groun pete ll-I d - 9 d-- :
Nome
~
Almsd t-sq.9s i 1101 Market Street t'h m e t a n n n' rum _ TM 1*1AOS-?AD1
' Aodress Sheet 3/ of _ i
- 2. Plent carninumh Mit r= 1 mm e pl a nt- Unit Nome
[tv min TN 37379
- Aodress MRepairBOW N Oreenlastion P.O. No., Jeb No., etc.
i
- 3. Work Performed by TVA Type Code Symbot Stamp NA P.O. Box 2000 Authorisation No, M Soddy-Daisy, TN 37379 Empiration Oete NA ,
Asemos "
- 4. Identification of System D8D M L AT MNAl - 3
$sCEL
- 5. (a) Applicebte Construction Code bAM 19Mdition- NA Addende. M Code Case (b) Applicable Edition of Section XI Utilised for Repairs or Replacements 19 R O WR1 AddeDda i
- 6. Identification of Components Repaired or Replaced and Replacement Components '
ASME Code i National Repeired, Stamped Nome of Name of Manufacturer Soerd Other Year Replaced, (Yes , Component Manufacturer Serial No. No. Identification Built or Replacenwnt or No) l MI2. pap t r46 Ells *xA.- NA (VA t)ra - 2 6-B h ts f4A m CL % do i l i l
- 7. Description of Workh3 L A LE D ed kJ.%o 5To meaos Na esina . !
- 8. Tests Conducted: Hydrostatic Pneumatic ominal Operating Pressure Other O Pressure Ni Test Temp. r ,
l NOTE: Supplemental sheets in form of lists, sketches, or drowings moy be used, provided (Il sire is 8% in. m 11 in., (2) Informs. I tion in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of shoots is recorded et the1op of this form. l
~
(12/82) This Form (E00030) mey be obtained from the Order Dept., ASME,345 E.47th St., New York, N.Y. 80017 REPRINT 12/91 i-
l l FORM NIS 2 (Back)
- e. Rome,es ConstrwCTloM Co DF_. : Cow T%< a *919.34 Ae moon w. u.not-tor.es o n ru to n. ene.ned WE:'>0r46 mod 5 & E -5pFC - 6~7*7 ? 2 85 A4D G7(p47 *i M b TEE !
19(A!5 DrzecT Mm E CODE. Forz. Pom.p s Ar an VAL _VE.5. A 1 CERTIFICATE OF COMPLfANC We certify that the etstements made in the report are correct and this IM orms to the n:les of the ASME Code, Section Xl. ""'"#*****"' j 5 Type Code Symbol Sump NA Certificate of Au lastion No. NA Empireiion oeie NA r; _
<p-.t .r b
. b bd b pete
, @ OWBE:E,, %
3 CERTIFICATE OF INSERVICE INSPECTION t, the undersigned, holding a valid commission leeued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Provinos of Tennessee q,gg Hartford Steam Boiler Inso. & Ins. Co. og Hartford, Connecticut Wi tM c to krlw , in this Owner's Report during the period O*/7*h2- to /I"/b"94' and state that l to the best of my knowledge end belief, the Owner has performed examinations and taken corrective meneures described in this Owner's Report in accordance with the reciuirements of the ARME Code, Section XI, By signing this certificato neither the inspector nor his employer makes any worrenty, expressed or implied, concerning the examinstens and corrective measures described in this Owner's Report. Furthermore, neither the inspector nor his employer shall be liable in any menner for any personal injury or r'operty damage or a loss of any kind arising from or connected with this inspection, dPJEddm." Commissions a h Nf inspectors 56pneture ' NatioM Soerd, State, Province, and E ndorsements Date /M I 19
+
)
i
FORM NIS 2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner TVA-Nuclamr Power Groun Nome pote l "9 '~ N Atao/48-95 i 1101 Market Street g of /A eo r
(*hattannana _ 'PM 't7An?-san 1 St.eet -
" ~ Aseees
- 2. Plent Manunvah Mitra l ma r DlanF Unit Nome
$v in TN 37379 Address NE bOMDb neoelt Orsenisetten P.O. No,, Job No.,etc.
- 3. Work Forformed by TVA Type Code symbol stamp NA P.O. Box 2000 Authorisation No, un~ [
Soddy-Daisy, TN 37379 Empiration pote NA - Address
- 4. Identification of System 'TA LMY ASA45. c
- 5. (e) Applicable Construction M 19 N. Edition; b Addende.
* ~
Code Case (b) Applicable Edition of Section XI Utilised for Repeirs or Replacements 19 R 0 WR1 Addenda
- 6. Identification of Components Repelred or Replaced and Replacement C; ac.ts
-. ASME l Code Nat6onal Repowed, Stamped ; ~ Name of Name of Manufacturar poord Other ves, Raplooed, (Yes Component Manufacturer Seriel No. No. Identification Built 8' Replacement or No) t A vs M ce+ost. ET6'io- 17-~ & 2-GS-SSZ. Mq e-s AlA MA '&y. Yes, -
- 7. Description of work MN WIlM MW IM N
% maor=% e.
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other PressureI2 M*I@ psi Test Temp. Nb 'F NOTE: Supplemental sher 9 'a form of lists, sketches, or drowings may be used, provided (1) slae is 84 in, a 11 in., (2) Informs- !
tion in items 1 through 5 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is i recorded at the top of thh form. (12/82) This Form (E00030) may be obtained from the Order Dept., ASME,345 E. 47th St., New York, N.Y.10017
+
REPRINT 12/91 l l l l
m 1 U ;
, . . l FORM NIS-2 (Back)
- 9. Romerks Applicable Manufacturer's Date Naports to be ettsched i ,
l CERTIFICATE OF COMPLIANC-We certify that the statements made in the report era correct and this Tonforms to the rules of the , ASME Code, Section XI. *I'' Type Code Symbol Stamp N A Certificate of Authortretion Pdo. NA Empiration Date NA Signed N wner # owners Deep
= b^ #,'hte Y
! T ' ~
19 ~ CERTIFICATE OF INSERVICE INSPECTION i 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Proesure Vessel inspectors and the State l or Province of Tennessee W ernplwed by Hartford Steam Boiler Insp. & Ins. Co. og Hartford, Connecticut have inspected the components described in this Owner's Report during the period I'l7'9E to //~/l# "O4" , and etets that to the best of my knowledge end belief, the Owner has performed examinations and taken corrective measures described 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 worrenty, expressed or implied, concerning the examinations and corrective measures doecribed in this Owner's Report. Furthermore, neither the inspector nor his employer shall be liable in any menner for any nel injury or property damage or e loss of any kind arising from or connected with this inspection.
/%- e w Com,nieses 6 4. vo / 4e>2 e nspector's signature ' National Soord, State, Province, and Endorsemente ,
Date / /d 19 k e
m FORM Nit 2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner TVA-Ntt ral ma r Dnwar (:rniin
- Date k Nome Aaew He-M 1101 Market Street r'ha t+ m nnnnm 'ru t '7 A n 9 -9 A n 1 Sheet 3,3 of g /9
' Address
- 2. Pient Morninva h Nit r= I mm e D1 m nt-
'" ~
Unit b Nome
$6isv5DEi N- Asdreas TN 37379 WL OM Repair Creenisetlen P.O. No., Job No., etc.
- 3. Work Performed by TVA Type Code Symbol Stemp NA
"*** um P.O. Box 2000 Authorization No.
Soddy-Daisv, TN 37379 Empiretion Date NA Adereas
- 4. Identification of System bFSTM lNr \ GLTt M AMb4
- 5. (e) Applicable Construction Code L3D I 'I 19d Edition, 10 Addende. MA CodeCo (b) Applicable Edition of Section XI Utillred for Repairs or Replacements 19 A O WAl Addenda
- 8. Identificaten of Components Repaired or Replaced and Replacement Components
% ASME Code National Repeired, Stemped Nome of Name of Menufacturer soord Other Yeer Releced, (Yes Component Manufacturer Seriet No. No. Identification Built or Replacement of No)
%peTM UN-la s e-ur,o a bl4 td 4- dA M4 Vabm 2come tdo it
- 7. Description of Work @ MGd kJM4 STom AaD Ntrrs AT
% L'k m T 2W E-l'*~7O*
- 8. Tests Conducted: Hydrostatic Pneumatic Wominal Operating Pressure O :
Other Pressure D Prvsl Test Temp. 'F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size 6: 8% in. m 11 in., (2) Informe-tion 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 et the top of this form. (12/82) This Form (E00030) may be obtained from the Order Dept., ASME,345 E. 47th St., New York, N.Y.10017 I REPRINT 12/91 ) l l l l
r-3 FORM NIS 2 (Seck)
- 9. Romerks b ,
Applicable Manufacturer's Data Reports to be attached f p CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this MM ASME Code, Section X1. '***# ''***'"Monforms
*"' to the rules of the Type Code Symbol Stamp NA .
Certificate of Authorization No. NA Empiration Date NA Signed owner or owwr' RH hA&
. Title os,e L tO V M h ,i, 9 &
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 Tennessee W employed by Hartford Steam Boiler Ineo. G Ins. Co. og Hartford, Connecticut wI ed me ets kribed in this Owner's Report during the period I'N " N to N ~ O * . and etets that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in thie Owner's Report in accordance with the requirements of the ASME Code, Section XI. By signing this certificato neither the inspector nor his employer makes any warranty, empreened or implica, concerning the eneminations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liebte in any menner for any personal Injury or property damage or a loss of any kind arising from or connected with this inspection.
# "^
Commissions a nspector's s6gnature National soord, State, Province, and Enderemmente Date lo
q i FORM Nis.2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Reesired by the Provisions of the ASME Code Section XI
, , o,,,, TVA - Nuclear Power Group 1101 Market Street N m n ,, FQ83 N Np.py ,
Chattanooga, TN 37402-2801 ue e sheet 34' of N'7 /60)
- 2. m Sequoyah Nuclear Plant unit b P. O. Box 2000 Na Soddy-Daisy, TN 37379 Adgrees N 608M N Mopelt Orpenisation P.O. No., Job No., etc.
- 3. Work Performed by TVA 1 Type Code symbol siemp NA P. O. Box 2000 ""
NA Authorization No. Soddy-Daisy. TN 37379 Empiretion Dete NA Amerses
- 4. Identification of System D b
- 5. (a) Applicable Construction Code AO N'7 19M Edition: ANO Addende_ NA Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 80 Through Winter 1981 Addenda
- 6. Identificat6on of Components Repaired or Replaced and Replacement Components I ASME
- Code l National Repeived, Stemped Name of Name of Manufacturer Board Other Yeer Replaced, (Yes Component Manufacturer Seriet No. No. Identification or Replopement Built or No) i f:>Jppol7.T # Sew SOf1L UN 1-pt>H -24+ TA M 'dA v 87czneo W % 50 No f
t
- 7. Description of Work MCE. T,4E bWER. 360 b6MM__S hDQ.AduC. $MOS261
- 8. Tests Conducted: Hydrostatic P etic ominal Operating Pressure C3%" Sons) . !
Other O Pressure psi Test Temp. 'F 1 f ' NOTE: Suppiomontal sheets in form of lists, sketches, or drowings may be used, provided (1) sire is 8% in. x 11 in., (2) Informe-tion in items 1 through 6 on this report is included on each eheet, and (3) each sheet is numbered and the number of sheets is recorded et the top of this form. (12/82) This Form (E00030) may be obtained from the Order Dept., ASME,345 E. 47th St., New York, N.Y.10017 J REPRINT 12/91
. l l
FORM NIS-2 (Back)
- 9. Romerks .
{ Aopticable Manufacturer's Date Reports to be attached 5 l 6 CERTIFICATE OF COMPLIANC We certify that the statements made in the report are correct and this ?6Tconforms to the rules of the repeir or reelecement . ASME Code, Section XI. Type Code Symbol Stamp Certificate of Authoritation No. tdA es,i,,,,,, os,e t4 A Seed A , MscA Ese_. oote \4 uW ,, 93 wner 6r owners De. Title ' N 1 CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned holding a valid commission issued by the National Board of Boiler and Preneuro Vessel inspectors and the State
,,,,,,in,,,, tennessee - id employed by Hartford Steam Boiler Inspection & Ins. So, Hartford Connecticut he inspected the te described in this Owner's Repo t
~
b stets that to the best of my kn a he neI . bids t' N oct m res ribed 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 eneminations and correctM moseures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any menner for any personal injury or property damage or a ions of any kind arising from or connected with this inspection. N Commissions 9 98 f MAI ir,so.c ors %u,e s et.o . .o.,.. .t. e. ,,o.,r .. .r . r,.o,.omems Dete #6 19
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I m I FORM Nis 2 OWNER'S REPORT FOR REPAIRS OR REPl.ACEMENTS I As Required try the Provisions of the ASME Code Section XI 1, owner TVA-Nuclear Power Group nome oote to - 4.-94 1101 Market Street mw s-4 95 chattanonera. TN 37402-2801 Address Sheet 5 of usa /- j ,
- 2. Plant ,c:arruovah Nuclear Plant Unit 'b P.O. 5ox 200 SoddV-Daisv.0 TN "*~
Address 37379 W C. Mv'153 Repair Organisetlen P O. No., Job No., etc.
- 3. Work Performed by TVA Type Code Symbol Stamp NA P.O. Box 200 Authorization No. NA Soddy-Daisy,0 TN 37379 Froiration oote NA Address
- 4. Identification of System b5 sN A L. E A T' M MOVAL
- 5. (e) Applicable Construction Code '4 N 9 Edition, NA Addende, MA Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 8 0 W81 Addenda
- 6. Identification of Competents Repaired or Repleoed and Replacement Components ASME Code Stemped '
Nationet Repaired, Name of Name of Menufacturer Board Other Yeer Replaced, (Yes Component Manufacturer Serial No. No. Identification Built or Replacement or No) P M R- %T Er% letch?J Eh cet w eg _ /r4 B StS5 & g (l (la MA 1972. _ 7 Tco g ScgucATDi?h INc ,
- 7. Description of Work O'DLAc m 3 S OF 3 G> M Aied hN (_.:it=.L N c)Ds M B d qs,
- 8. Tests Conducted: Hydrostetic P umati Nominal Operating Pressure Other Pressure, psi Test Temp. 'F NOTE: Supplementet sheets in form of lists, sketches. or drawings may be used, provided (1) size is 8% in. x 11 in., (2) Informe.
tion in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of shoots is ; recorded et the top of this form. ; v (12/82) This Form (E00030) may be obtained from the Order Dept., ASME,345 E.47th St., New York, N.Y.10017 REPRINT 12/91
i 1 I R
' FORM N18 2 (Back) ;
- e. Romerke bI A .
Aceiiesoie u.aue= tor.r e o.te neoorm t. a. ett-hed 1 I
'l l i i .
CERTIFICATE OF COMPLIANCE l We certify that the statements made in the report are correct and this EN Mforms to the rules of the i ASME Code, Section XI. "' " t Type Code symbol Stamp NA l Certificate f A thorisation No. NA Espiretion pote NA , i Signosi M0f#l bdb Date bTOf%E!I2- ,19 Ob 15stnet or own6r's Descense, d CERTIFICATE OF INSERVICE INDECTION 1, the undersigned, holding a valid commission leeued by the National Board of Boller and Pressure Vessel inspectors and the Stees or Province of T*AU'8888 W e ed W Hartford Steam Boiler Insp. G Inc. Co. ,, , Hartford, Connecticut %, , , g,w In this Owner's Report during the period 7 to IblE , and stees that to the boot of my knowledge end belief, the Owner has performed seeminations and taken corrective measures described in this Owner's Report in accordence with the requirements of the ASME Code, Section XI, ! By signing this certificato neither the inspector nor his employer makes any warranty, espressed or implied, concerning the seeminations and corrective measures described in this Owner's Report. Furthermore, neither the inspector nor his employer i shall be lieble in any menner for any personal injury or property damage or a lose of any kind arising from or connsJed with this insection. IP2sr O Commissions C M NT inspector's sienstore National Board, State, Province, one E ndernements
- Date 19 f
.s e.
7.- j FORM Nis 2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Onwr TVA-Nuclear Power Group Dete IO 'l# ~9 4~
Nome taav reps 1101 Market Street chattannnna. TN 37402-2201 Sheet p"g of 7 j
" ' Address
- 2. Plant c:anuovah Nuc1 mar plant Unit b Name ohdv i TN 37379 Aedress W/2- d /25 755 Mapelr Creenization P.O. No., Job No., etc.
- 3. work Performed by TVA Type Code Symbol Stomp NA P.O. Box 2000 Authorization No, M1 Soddy-Daisy, TN 37379 Empiration Date NA s.Ja ses
- 4. Identification of System ED'fA> AL.- E/l 7' /k10 VA L _
AWS
- 5. (a) Appinceble Construction Code C77ME19 DEdition. M Addende_ M Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 RO W81 Addenda
- 6. Identification of Components Repelred or Replaced and Replacement Components ASME Code National Repaired, Stamped Name of Name of Manufacturer poord Other Year Replaced, (Yes Component Manufacturer Serial No. No. Identification Built or Rapiscoment or No) bNfetM
[H2 /kw+7 ' AND 9172%94 II/7 'NA I972 2menw %, Ft 46 21CA TL Q 6 78 lNC.
- 1. Description of work VJOLAC6b 29 Cr3(p N4t4 hMt.aE' bi~t)M ANb Nur.S.
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other O Pressure N A' psi Test Temp. 'F
/
NOTE: Supplemental sheets in form of lists, sketches, or drowings may be used, provided (1) size is 8% in. x 11 in., (2) Informe-tion 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 et the top of this form. J (12/82) This Form (E00030) may be obtained from the Order Dept., ASME,345 E. 47th St., New York, N.Y.10017 l REPRINT 12/91
j :O l FORM NIS 2 (Back)
- 9. Romerks M Appliceede Manufacturer's Dete Reports to be entsched k
e.. ,
'?
CERTIFICATE OF COMPLI j We certify that the statements made in the report are correct and this &MT conforms to the rules of the ASME Code,Section X1. O ' * ' Type Code Symbol Stamp MA Certificate of Authorization No, NA Empiration Date NA , n M M b4K- Date N 19 9b f y or Owner's p/T#tse v i CERTIFICATE OF INSERVICE INSPECTION f, the undersigned, holding a welid commission issued by the National Board of Boiler and Proesure Vessel inspectors and the State
,,provines of Tennessee W employd by Hartford Steam Boiler Insp. G Inn. Co.og j Hartford, Connecticut have a-ted the components described ,
in this Owner's Report during the period 8"I7~YI' to I N0 *W and state that to the best of my knowledge end belief, the Owner has performed eneminations and taken corrective measures described 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 worrenty, exproceed or implied, concerning the . eneminations and corrective moseures described in this Owner's Report. Furthermore, neither the inspector nor his employer shell be liable in any menner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection, esse f N Commissions M[ Inspectorssdneture Nethnal Soerd, State, Province, and E ndorsernenu pote /eh to SV me M i i r
^ ~.
FORM N18 i ,WNER'S REPORT FOR REPAlR$ OR REPLACEMENTS t As Required by the Provisions of the ASME Code Section XI
- 1. Owner TVA-Nuc1 mar Power CronD -
Date II ~ N'N Ne=e Aw I,r 1101 Market Street fA o ,e-ys r'hatt a nrwvem . TN *17d o? -2 A 01 Sheet of -- -e f Adeems
- 2. Plent Mamlovah Nucl ear Plant Unit b Nome P.O. Box 200 '
l Soddy-Daisy,0 M C(ESM9 j
- l. A.T.Ne 37379 aso.ir oreenie..n ,.o. ... so .. e,e. u I
- 3. Work Performed by TVA Type Code symb'on Stamp NA
"*** M1' P.O. Box 200 Authoriaation No.
( Soddy-Daisy,0 TN 37379 Espiretion oote NA ) Amerees {
- 4. Identification of System W 84 TE A^4 5 se.
- 5. (e) Applicable Construction Code NN 19 M AEdition, Al A Addende. d A- Code case (b) Appliemble Edition of Section XI utilfred for Repairs or Replacements 19 a O Wal Addenda
- 6. Identification of Components Repelred or Repieced and Replacement Components ASME Code Nationes Repaired, Stemped Nome of Name of Monufacturer Board Other Year Replaced, (Yes Component Manufacturer Serial No. No. Identification Built or Replacement or Nel CuPc3 - L)*4 -
1"PCA/- l- B ddL-( AaJ e4A MA M4 wa Gk wrM l
- 7. Description of Work DZiL L% NDLED Id E L.Af 6 bd' W M G 7' M N A E.
To M@iE DA 3Mf D 2A42Af MA t M ,
- 8. Tests Conducted: Hydrostatic Pneumatic inal Operating Pressure Other Pressure _
i Test Temp. 'F l NOTE: Supplemental shoots in form of lists, sketches. or drowings may be used. provided (1) size is 8% in. e 11 in (2) Informs- ) tion in items 1 through 6 on this report le included on each eheet, and (3) each sheet is numbered and the number of sheets is l recorded at the top of this form. l (12/82) This Form (E00030) mey be obtained from the Order Dept., ASME,345 E. 47th St., New York, N.Y.10017 V REPRINT 12/91
g D l l l 1 l FORM Nis 2 (Beck)
- e. Romerks C u s. rr a ,u c- w m C o x : I 99 t3 Am E T).urT Cocc. h Applicettle Manufacturer's Date Reports to be attached PJ m p-5 /kN D \/ALN G 5 ,
CERTIFICATE OF COMPLIANCE We certify thet the statements made in the report are correct and thisb^c MMT conforms to the ruise of the ASME Code, Section XI. "'''''***'"N , Type Code Symbol Stamp NA 9 Certificate of Authorization No. NA Espiretion Dete NA . Si,ned
/.
Owner or er'
, Meca Fw6e-
,Tme oote 2.3 blevemere - i. 94- i CERTIFICATE OF INSERVICE INAPECTf0N +
1, the undersigned, holding a valid commission leeued try the National Board of Boiler and Pressure Vessel inspectors and the State cr Province of Tennessee Wemployed by Hartford Steam Boiler Insp. E Ins. Co. og Hartford, Connecticut w inspected the components hilbed in this Owner's Report during the per6od O~N to //~O Nd . and state that to the best of my knowledge and belief, the Owner has performed eneminations and taken correcthe measures described in this Owner's Report in encordance with the requirements of the ASME Code, Section XI. By signing this certificate neither the inspector nor his employer makes any warrenty, expressed or implied, concerning the seeminatione and correcthe measures described in this Owner's Report. Furthermore, neither the inspector nor his employer shall be listHe in any manner for any personal injury or property demage or a loss of any kind arising from or connected with this ' inspection.
#h
- A Commissions 98 8 A8 anspector's Sleneture National Board, State, Province, and Endorsements Dete M/ 19 V
l 1 i l
m. FORM N18 2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI t, owner TVA-Nuclear Power Group Date l I' 2 3 '9 ' Nome Anw 4-1.> 1101 Market Street u n -g chattannnesa. 'PN 37402-2801 Sheetwqg .of - ' Adeses
- 2. Plant Saauovah Nuclmar p1 ant unit 7-P.O. Box 2000 "***
Soddy-Daisv. TN 37379 Adeses W P- . C t L5'789 mooelt Orsonatellon P.O. No., Job No., etc.
- 3. work Performed by TVA Type Code symboi Samp NA P.O. Box 2000 Authorization No. M Soddy-Daisy, TN 37379 Espiretion Date NA Address
- 4. Identification of System MAIP I 'f 8E M G4
- 6. (a) Applicable Construction Code E MU h19 M AEdition, 'Addende, NA Coeio Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 8 0 W81 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components ASME Code Nationei Repaired, Stamped Name of Name of Manufacturer Board Other Year Replaced. (Yes I Component Menufacturer Serial No. No. Identification Built or Replacement or Nol
(_.o p e - LA - 2-PCV-l-6 V'd Lc Ar .A rd A MA MA 164oJ4 2f:pA4.40 6. Io l
- 7. Description of Work 6 OA t T7 CG VAL-v E. bo VG <a A u o S.>/ SmT ,,u e, b 2 EA d btD ML.V 6 Ot.-tdd\ M m -{ jt.82PALC l\/\ A L H N f M 4 ,
- 8. Tests Conducted: Hydroetatic Pneumette O 'aei Operatiae Pressure Other Pressure si best Temp. 'F f
NOTE: Supplemental sheets in form of lists, sketches, or drowings may be used, provided (1) sire is BM in. x 11 in., (2) Informe-tion in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of shoots le recorded et the top of this form. (12/82) This Form (E00030) may be obtained from the Order Dept., ASME,345 E.47th St., New York, N.Y.10017 J REPRINT 12/91 1
,= 1 ! i n_? ' f
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FORM N18 2 (Sack) j
- s. RemakeCou'$TTLO(-TaoM bne , f 9 &6 A$ME. T; 2Af= r (oce ' Gra-
.- Ao.ne i. manut-tur.r. ome nosono to t mennes :
J .wO 3 b AlD Y.4 t.V e *::.. I I f t t CERTIFICATE OF COMPL We certify that the statements made in tne report are correct and this MD 8 P confoems to the rules of the ASME Code, Section XI. " f Type Code Symbol Stamp M1 Certificate of Authorization No M1 Empiration Does MA Signed W M\ECH F m c , a _. De,o 2 =s eJovewca ,, 94 owner or ou @ Oeseense, Totte CERTIFICATE OF INSERVICE INSPECTION I, the undersegned, holding a welid commiselon leeued tsy the National Board of Boiler and Pressure Vessel inspectors and the Stees or Province of Tennessee employed try Hartford Steam Boiler Insp. E Inc. Co. ,, , Hartford, Connecticut hose W es componene desernsed - I in this Owner's Report during the period 6"I7"NE" to /I'[b"94 and etmo the to the best of my knowledge and tielief, the Owner has performed eneminatione and teken corrective measures desoribed in thle f Owner's Report in accordenes with the requiremen4 of the ASME Code, Section XI. , Dy signing this certificate neither the inspector a or his employer makes any morrenty, empressed or impiled, concoming the eneminatione and corrective measures descritied in this Owner's Report. Furthermore, neither the inspector nor his employer ~! shall he liehle in any menner for any pe injury or property domess or a loss of any kind arising from or connected with thle . Inspection. . I i h , Commissions L !#! A"Ad inspector's stoneturti ' Nationsi Boorts, State, Province, one Enseorsemente l n N/ se 9 Y l l v i
7
^ .
FORM Nit 2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI g, o wner TVA-Nuclear Power Group oote /O '6 Name 1101 Market Street A#f#/1$-75 Chattanooca. TN 37402-2801 Asarse. sheet 3 of f,m e N
- 2. Pient Sequovah Nuclear Plant unit b P.O. Box 200 Soddy-Daisy,0 "*"" TN 37379 WE C/26(#67 Aoeres. noosir orsenineian p.o. No .seo no., =c.
- 3. Work Performed by_.,T_VA Type Code symbol stamp NA P.O. Box 2000 Authorization No. M1 Soddy-Daisy, TN 37379 Empiretion pote NA Amores.
- 4. Identification of System f"5 4
- s. to) Applicabie Construction Code W to MO Edition. M Addende Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 8 0 W81 Addenda
- 6. Identifiestion of Components Repaired or Repieced and Replacement Components ASME Code National Repaired, Stamped Name of Name of Manufacturer Board Other Year Replaced, (Yes Component Manufacturer Serial No. No. Identification or Replacement or No)
Sullt .
\lAl YtS ()g-2 N/ h /AI M o/2 TN A/A /\lA AIA h Grpn% Afo j i
l i
- 7. Description of workh4/Def75 NEZA/A/6 MD MAC/f/M//V6 b Y4t- @ b M (
/ rib 7bonacT % (2n
- 8. Test Conducted: Hydrostatic Pneumatic a nt!-- MM C"TL el Operating Pressure O l
Other Pressure tTemp. 'F l f NOTE: Supplemental sheets in form of lists, sketches, or drowings may be Leod, provided (1) size is 8% in. x 11 in., (2) Informe. tion in items 1 through 6 on this toport is included on each sheet, and (3) each sheet is numbered ud the number of sheets is recorded at the top of this form. j i d (12/82) This Form (E00030) mey be obtained from the Order Dept., ASME,345 E. 47th St., New York, N.Y.10017 REPRUrr 12/91
.O '
FORM NIS 2 (Back)
- e. Re eks (%8 A wt2 baAfr Mc.c,.r.Ann o.te neo.
W0VG Gre 4.onc u.not to 0. e e. CERTIFICATE OF COMPLtANCE We certify that the statements made in the report are correct and this bole - conforms to the rules of the ASME Code, Sect 60n Xl. "#*""*"' Type Code Symbol Stamp NA
}
Certifieste of Authoriastion No NA Empiretion Dois NA ; Signed C , MG/il bd28-- Date b CId b6f2-- 10 wner or owners @ ime 8 CERTIFICATE OF INGERVICE INSPECTION 1, the undersigned, holding a valid commission issued by the National Soord of Soiler and Pressure Vessel ingmeters and the State or Provinos of Tennessee W wnployed by Hartford Steam Boiler Insp. & Ins. Co. ,, Hartford, Connecticut %, in this Owner's Report during the period 5-/ 7-92. o/N6-97 g , ,
,,,,,,,,,3, to the best of my knowledge end belief, the Owner has performed eneminations and taken corrective measures described 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, empressed or implied, concerning the eneminations and corrective measures described in this Owner's Report. Furthermore, neither the inspector nor his employer shall be liable in any menner for any personal Injury or property damage or e loss of any kind arising from or connected with this inspection. M # M7 Commissions l_ ors. u ~e, . . r.... e.p,o.r,ce..r .r orsere,or,,e Det. uh ,,14_' i 1 I l l
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FORM NIS-2 OWNER'S R8EPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI i
- 1. Owner TVA Nuclear Power Group Date 10-12 94 ;
Name K4W l'1fD-RS
- 1101 Market Street. Chattanooaa TN 37402 Address sheet 40 of M/50 2, Plant Seouoyah Nuclear Plant Unit 2 Name P. O. Box 2000. Soddy-Daisv TN 37379 TVA/WR C127036/DCN M8411 Address Repair Organization P.O. No., Job No., etc. t
- 3. Work Perforrned By TVA Type Code symbol stamp N/A Name Authoritetion No. N/A P. O. Box 2000 Soddy Daisv TN 37379 Expiration Date N/A Address
- 4. Identification of System Chemical and Volume Control. System 062 i S. (a) Applicable Construction Code ANSI B31.7 19.f1 Edition, 1970 Addenda, N4161 Code Case !
(b) Applicable Edition of Section XI Utahied for Repairs or Replacements 19.81, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components ,
ASME Repaired, Code National Replaced, Stamped Name of Name of Manufacturer Board Other Year or (Yes Component Manufacturer Serial No. No, information Built Replacement or No) Piping for TVA N/A N/A N/A unknown Replacement No e valve 2-62 660 e
- 7. Desenption of Work Reolaced elbow and oice soools in coniunction with valve teolacement.
- 8. Tests Conducted: Hydrostatic 0 Pneumatic 0 Nommal Operating Pressuref Othee Pressure U % osi Test Temp.85A ryser Nolf supplementer sheets a form of lests. sketches or crewegs may be used peovioed O f see es 8 % m a 11 m.12) mforme-teon m etems 1 through 6 on th.s report es actuoed on each sheet, end (31 each sheet es numLared and the numbee of sheets es .
escoeced at the top of this form O 218 2: This form ([00030J may be obtemed from the Oeder Dept.. ASME. 345 E. 47th St. New York. N Y.1o017 ! REPRINT 12/91
f '. l [. , 'M I. l l-I i FOM4 NIS-2 (Backl e Rom.k. 3* dia. oine. ASME Class 1. Leak Check nerformed car 2 SI-SXf-068-OO2.0. ( Apphcatne Menutectwer's Data Reports to be attached I t~ l CERTIFICATE OF C000PUAssCE we e-uy met m. sinien.nt maae a the ,ep i are c ,eci ano th,s reolacement cent.m. to the euses of the AsME Code. section x1 reper or rep 6scement I fype Cooe synes siemp NONE } l C w.cm et Authorem n No. N/A E.p.e.t a one N/A s.gned . A%d/A h, . ff,' hef Date YA Ve webor 1 ,19 N o pp . owne,=s on.enn.1.tw v
^
CERTIF9CATE OF NeSERVICE WISPECT1081
- s. me une re ened, haa.no a sw.a commiss.on .u e by the km.one sure of a and Praewe vee.w inspecies and the stm er Pre,me. .f Tennessee ana emenoveo by Hartford Steam Boiler insoection & Insurance Comoany et Hartford. CT h..tmopectee me c.wonent, oncreen a th. own. s Report sweg the per.oe E-/7 t //-/& *fiP4- ..no e m met to the best of my knowledge end belief. the owner has performed enemmetsons and namen corrective measwes sesenbod a this owner's Report m eccordance weth the reconoments of the AsME Code. section XI.
By segew'O this certificate nether the enspector nor his empsover makes any warranty, empressed or emphed. concorrung the emarrenations and correct we meeswa descreed m teus Owner's Report. Fwthermore, neither the mopector nor tus employ. shan be hable e any mannee for poisonae iniury oe property damage or a soses of any kmd eresing from or cormected with teus
- c. e, Inspecitert.
.p t..s s,n.tw.
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..t_. .o... s,....e_.e en. En...._ts Dm // JJ 1o 9 1
1 J l I i l l l l 8 I w/ l l i
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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 TVA Nuclear Power Groun Date 10-12-94 Nome ** /W 1101 Market Street Chattanoona. TN 37402 Addroe.
Sheet N of M/N
- 2. Mont Seouovah Nuclear Plant Unit 2 Name P. O. Box 2000. Soddy-Daisv TN 37379 TVA/WR C127036/DCN M8411 Address Repair Organization P.O. No., Job No., etc.
- 3. Work Performed By TVA Type Code symbol Stamp N/A Name Authorization No. N/A P. O. Box 2000. Soddy-Daisv TN 37379 Expiration Date N/A Addres.
- 4. Identification of System Chemical and Volume Control System 062
- 5. (e) Applicable Construction CodeJSME Ill 19 74 Edition,1975 Addende. N416-1 Code Cee.
(b) Applicable Edition of Section XI Utilized for Repairs or Replacemente 19.3Q_, Winter 1981 Addenda
- 8. Identification of Cornponente Repaired or Replooed and Replacement Componente
_/ ASME Repaired, Code Natibnel- Replaced. Stamped Name of Name of Manufacturer Board Other Year or (Yes Component Manufacturer Serial No. No, information Replacement Built orNo) Valve BW/IP 921A0108 N/A N/A ur*nown Replacement Yes 2-62-660
- 7. Description of Work Installed new swino check valve for suoolv to Loon 4 Cold Leo.
- 8. Teste Conducted: Hydrostatic o Pneumatic o o Nominal Operating Pressure [
Other PressureZ25() nel Test Temp.5d 2 5@F NOTE: E . .._ ast sheets et form of ksts, sketches. or drewmgs ener be used. provused (1) ese is 8 % in. s 11 an.. (2)infome ten in noms 1 through 6 en stus report is enche$ed on sech sheet. and (3) each sheet es nurremrod and the number of sheets se recorded et the top of thes form. (12/s2) Ytus Form (E0003ol may be obtemed from the Onfer Dept., ASW.,345 E. 47th St New York. N.Y.10017 REPRINT 12/91 i
i FORM MS-2 Isockl
- s. nemone 3* dia. oice ASME Class 1. Leak Check performed oer 2 SI-SXI-068-002.0. i I
Aptecews uenufact,w e one nepate se be atashed CERTFICATE OF cot 0PUA80CE We eartrfy that the statemente made in the report are correct and the reDlacement conforms to the rufee of the Atw Cede. Seeten XL reper er replacement Type Code symba st., NONE Catficate of Autherusten No. N/A tapest.on osie N/A senes lddM A, l h&A fant os,e A/o war, 7 .,, o+
' opp. - own e onen.e. T6 i/
CemFICATE OF IMedgivtCE BISPECTIO8f L me und..ywd. hektne e und _.. - issued by me weisend send of sener and ree we veesd % e end m. et- , n n n.e .f Tennessee end ompieved by Hartford Steam Boiler inspection & Insurance Company of i Hartford. CT n=.m , to //-&- 9E 'ad the e r,.nente etete thatessere,ed e en ownv ns ort mens me pared 5'/7-7& . ed te em best et av knowiedge and be6 f. me own. ha pntormed mammenene ow taken correctwo mesewee doenbod in v. Owner's Report in accordance with the requeamente of the ASW Code. Section XL Dy .gnene en certifaceto nether the inspector nor hee emplayw moh o any warranty, supressed er esiplied, conoommg the enemmetsone and correctwo meeswa owerend m thee owner e Report. Furmermore, nenher the inspector nor he employer ehen be beblo m any menner for sonal ingury or property damage er e locos of any lund sneeng from er connected enth thee mopection. dP>f h Commeomone C- Ok [
. nap.ct<. %. us,me,~ .t.t ee.co. .n. .n.e,s.,_,e -. aAedw ,,
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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 i
- 1. Owner TVA-Nucinar Power Groun ~
oete / I "IO ~% [ Nome
& /*/SQ*5 1101 Market Street c'hmttannona _ TN 37402-2801 . Sheet g of ,isajg e
- ' Amoreas _ _ _ _
- 2. Plant c:anunvah Nur=1 mmy p1 ant Unit Nome o dv-i TN 37379 O IU IIM
- Address Repair Orsenization P.O. No., Joe No., etc.
- 3. Work Performed by TVA Type Code Symbol Stamp NA P.O. Box 2000 Authorimion No, M_
Soddy-Daisv, TN 37379 Empiretion Dete NA Adorses
- 4. Identification of Systtm 9("GTv i
v i GC 1'I 04 bN DEC
- 5. (a) Applicable Construction Code bM AW 19 Lb Edition: M Addende M Code Case (b) Applicable Edition of Section XI Utillred for Repairs or Replacements 19 RO W81 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components ASME Code Nationel Repelred, Stemped Name of Name of Menufacturer soord - Obr Yeer Replaced, (Yes Component Menufacturer Serial No. No. Identification Built or Replacement or No)
Ard C t-t C)i? (JM. 2-kV-66-39 h2.1.trW, NA NA tJA m j2 epm rdo '
- 7. Description of Work bi? L A L@ ALVE DI5C3.
- 8. Tests Conducted: Hydrostatic Pneumatic inal Operating Pressure l Other O Pressure ,
pi Test Temp. 'F l 1 i NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) sire is 8% in. x 11 in., (2) Informs-tion in items 1 through 6 on this report is included on each ehest, and (3) each sheet is numbered and the number of sheets is recordrf et the top of this form. l V '
.(12/82) This Form (E00030) nisy be obtained from the Order Dept., ASME,345 E. 47th St., New York, N.Y.10017 REPRINT 12/91 ,
i l 1
-, .. . +.. . . - - - . . - . . ~ ~ . , . - - . ~ - . - . ,
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i t i FORM NIS 2 (Beek) ;
. s. Merriarke Coast 24XTior4 Cons: [or4TEAcr 919% A<< D !
-e .. r. s .so.r.o .e vJesc,isc-,acow_., W1g>ec G 187to5 Le.coas.,c> (17&2se. '
l CERTIFICATE OF COMPL We certify that the statements made in the report ero correct and thle NTponforms to the rules of the
- ABME Code, Section XI. M *"****'***"'
Type Code syrnhol stamp NA Certifieses of Authorisetson No. NA g,pi,mion os. NA signed . M a E s. c o,t, le doveu resaz_ ,, <e+ ' o r.e,- y e e ,v e 7 s !. CERTIFICATE OF INSERVICE INDECTION l t, the undersigned, heMing a solid commiselon issued luy the National Doord of Boiler and Pressure Vessel inspectore and the Stees ! or PnnainesTof ennessee s w e,y Hartford Steam Boiler Inso. & Ins. Co. og i Hartford, Connecticut W h-W l
=
in mis Owner e Report during e. p.riod 5-/7-98 to 1/ . en, ete, ,h, to the best of my knowledge and holief, the Owner has performed eneminations and taken corrective measures described in this Owner's Report in encordance with the requirements of the ASME Code, Section XI. ; By signing this sortificote neither the inspector nor his employer makes any viertenty, expressed or implied, :: ._..-., the seeminations and corrective rneesures descr6 bed in this Owner's Report. Furthermore, neither the inspector nor his employer shall be liabie in any menner for any personed injury or property damage or a ions of any kind arising from or connected with thle , inspection. i
~ Commissions I# # AJ Inspector's signature ' Noteenal Seerd, State, Province, one Entforcemente ,
tw /d gg / l l y t r a l
. , - i f
I t, h l'
s FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner TVA Nuclear Power Groua Date 10-13 94 Name AA* HF-73 1101 Market Street Chattanoona. TN 37402 Sheet b of ! M /5o '
Address
- 2. Mont Seouovah Nuclear Plant Unit 2 Name P. O. Box 2000. Soddy-Dalsv TN 37379 TVA/WR C127178 Address Repair Organiastion P.O. No., Job No., etc.
- 3. Work Perforrned By TVA Type Code Symbol stamp N/A 5 Name Authorization No. N/A P. O. Box 2000. Soddy-Daisv TN 37379 Expiration Date N/A Addrese
- 4. Identification of System Main Steam. System 001
- 5. (a) Applicable Construction Code ANSI B31.7 19.,61 Edition.1970 Addende, None Code Co (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19.jQ , Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components I
ASME Repaired. Code National Replaced, Stamped i Name of Name of Manufacturer Board Other Year or (Yes Component Manufacturer Serial No. No. Information Built Replacement or No) Loop 4 N/A N/A N/A N/A ur*nown Repair No Elbow off Steam Generator
- 7. Description of Work Removed linear indication in elbow by orindino. ;
- 8. Tests Conducted: Hydrostatic o A/
PneurWe r Other - Pressure d osi fg.-,,,,nes est Temp.operstmg *F Pressure o NOTE: Suppaemental sheets m form of hets, sketches, or drewmes may be used, promded (1) eue as 8 % m. e 11 m.. (2) mforma-tion n noms 1 through 6 en this report se mciuded on each sheet. and (3) each ehest as numbered and the number of sheets is recorded et the top of true form. (1b821 True Form lE00030) may be obtened from the Order Dept ASE. 345 L 47th St. New York N.Y.10017 REPRINT 12/91 J
em i FORM Nis-2 (Seek) e s si nwnste 32' dia oine ASME Class 2. Discovered durina ISIinsoection by Mannatic Particle ae uenufatw 's osis nepens to be attached examination. CSITFICATE OF COGApuM0CE i We certify that the statemente made m the report we correct and true renair conforms to the rules of the A8hE Code. Secten XI. reper w repienement Type Code syness stm NONE Cetre.cate W Authewetion No. N/A Exonmen osie N/A
.i.n.d ALadM. skcA ena,. #
o.to cer'o b ,/3 . , , w O@ er'06ner's Decente. True CampicATE oF unemivice sospectices
- 1. the underegned, howmo e vehd c__ _ i eued by the Neisonei seed of sean and Praew veness snepectwo and the simie or prevece ef Tennessee end ompieved by Hartford Steam Boller Insoection & Insurance Comoany of Hartford. CT hav. ed the componente decreed m thee Owner's Report dunne the pened 5-/7 84 to II-/&-9 . and etsie that to the best of rny knowledge and behof, the Ownw hee performed mammatione and taken corrective measura descreed in the.
Owner's neport m accordance untit the reguremente of the AshE Cose. Secten XI. Dy agnsng thee certfwe nether the inspector not tee eWeyer makes miy warranty, empressed er emphed, concomm0 the examneteene and sorrective measura described in thee Owner's Report. Furthermore, norther the mapector ner hee emplever shall be habie m any menner f any pereenei sneury er property damage or e lesse of any lund wising from er connected enth true mapochen. I f) Inspeder's Signature ' Comm,se,ene a 9e#' 4.>J Netsonal Board. State. Prewmce, and Endernemente
. /. 4 /
l l I l m FORM NIS 2 OWNER'S REPORT POR REPAIRS OR REPLACEMENTS ! As Required by, the Provisions of the ASME Code Section XI 1, owner TVA-Nit e= 1 m a r Dawar Crnun N* * " Dete_f*bl- % 1101 Market Stre"et /diEdu NS-A*b i m jg cha t-t a nnarum' "
- TM 't'7A n9 - 9 A n1 Sheet- of F-r/
' Addess
- 2. Plent Cam tenrm h MnM ame Dlant
- ~ Unit b Nome i
Ev - i TN 37379
' Adesse bI bN '
Repair Oreeniset60n P.O. No., Job No., etc. 3, work Performed by TVA Type Code symbol stamp NA P.O. Box 2000 Authorization No. um Soddy-Daisv. TN 37379 Empiration Date NA Adereas
- 4. Identification of System MAW MMT ELM
' ' ~
AVE
- 5. (e) Applicable Construction LO4 T- 1g 7 l Edition, dA Addende A Code Case (b) Applicable Edition of Section XI Utilized for Mopeirs or Replacements 19 R O Wal Addenda
- 6. Identification of Components Repelred or Repieced and Mepiscoment J _J.ts i
ASME Code National Mepeired. Stamped Name of Name of Monufacturer Soord Other Maplaced, Year (Yes Component Manufacturer Serial No. No, or Replecoment or No) identification Built Awyc.o L)tt-2-FcV 1z-2.z AlA ed.A r4 A % 2,pu,, e%
- 7. Description of Work MMO 4M E T STvas Asn M(rTs.
- 8. Tests Conducted: Hydrostatic Pneumati Nominal Operpting Pressure Other O Pressure pel Test Temp. *F NOTE: Supplemental sheets in form of lists, sketches, or deswings may be used, provided (1) size is 8% in. m 11 in., (2) infeme-tion in items 1 through 8 on this report is included on sech sheet, and (3) each sheet is numbered and the number of shoots is recorded et the top of this form.
(12/82) This Form (E00030) may be obtained from the Order Dept., ASME,345 E. 47th St., New York, N.Y.10017 \ .- REPRINT 12/91 l l
4-
- n. ,
, FORM NIS-2 (Seck)
- 9. Romerks Applicebee Manufacturer's Date naports to be etteched CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this *FMTconforme to the rules of the
#.SME Code, Section XI. '"N'*****"'
Type Code Symbol Stamp NA Certifieste of Authorisation No. NA Empiration Date MA Signed M6bO IN bilZ Dete IO^O bIE- 19 k
' Owner or e Ossiones, Twee CERTIFICATE OF INSERVICE INNTION 1 the undersigned, holding a welid commission leeued by the National Board of Boiler and Pressure Vessel inspectore and the Stees or pnwinos of Tennessee H employed by Hartford ' Steam Boiler Inso. & Ins. Co. og Hartford, Connecticut w W es described in thie Owner's Report during the period 5 -t 7 - 9 7.L to 8 I-Na-9 4- . and eiene that to the best of my knowledge and belief, the Owner has performed eneminations and taken corrective measures described in this Owner's Report in accordance with the requiremonte of the ASME Code, Section XI.
By signing this certWicote neither the inspector nor his employer rnekes any warranty, empressed or implied, aonestning the seeminations and corrective measures described in this Owner's Report. Furthermore, neither the inspector nor his employer shall be liebte in any menner for any personal injury of property damage or a lose of any kind erleirs from or connected with thle inspection.
#5uf -
Commissions M Inspector's signetGro National Soerd, State. Province, and E ndorsemente r,- slh ,o 9p' u i
e. FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 1, 0.nor TVA-Nuclear Power Group pate /Z " I9 ~ 94-Name 1101 Market Street Chattannewsm . TH 37d02-2R01 Sheet 4 of
/ J N /~t9-
~-/ jg Q
- ' Meem
- 2. Plant Emmiovah Nuc1 nav D1 ant Unit Nome
$V i TN 37379 Mees.
NE O I b neoes oreeniamion p.o. =o., see we., sic. f
- 3. work Perfonned by TVA Type Code Symbo Stamp NA ;
P.O. Box 200 Authorization No. 'Ma Soddy-Daisy,0 TN 37379 Empiretion o te NA i Meeen ,
- 4. Identification of System M4YM !
A
- 5. (a) Applicable Construction Code 19 Edition, 'Addende_- AIA Code Caes t (b) paplicebte Edition of Section XI Utilised for Repeirs or Replacements 19 8 0 W81 Addenda !
- 6. Identification of Components Repelred or Repieced and Replacement C:--;:.c.;ts I
ASME Code Nationet Repeired, Stemped , Name of Name of Monufacturer soord Other Yeer Replaced, (Yes Component Menufacturer Seriel No. No. Identification Built or Replacement or No) g- ! 2-stv-S-$n LJ w blA sios AIA w Dmm slo I i
- 7. Description of Work @4/N M 4WN#M k N O f NOdCbMMES* S M N W $ AO4t
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operat6ng Proseure O PW SM Md> -
Other Pressure 4 pel Test Tomo.. 'F NOTE: Su;mismental sheets in form of lists, sketches, or drowings may be used, provided (1) size is 8% in. m 11 in., (2) Informe-tion in stems 1 thr:wgh 6 on this report is included on ee$ sheet, and (3) each sheet is numbered and the numbe of sheets is recorded et the top of this form. (12/82) This Form (E000301 may be obtained from the Order Dept., ASME,345 E. 47th St., New York, N.Y.10017 v' l REPRINT 12/91 l l I I l l
C FORM Nis 2 (Back)
- e. R.n orks avoraactio4 GDe: l%B ASM5 Dirner Coog Re-Applicable Manufacturer's Data eleporth to be ottsched MMI O OYM. .
CERTIFICATE OF COMPLIANC We certify that the statements made in the rooort are correct and th . ASME Code, Section XI. '***I''***'"*"' conforms to the rules of the Type Code Symbol Stamp NA Certificate f Authortretion No. NA Empiration Dme NA s Signed . M b40 pote M MMM gg
@ner or owner's pee @te. /
CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid w.... _ n leeued try the National Board of Sofer end Pressure Vessel inspectors and the State ' or Province of Tennessee W employed t,y Hartford steam Boiler Inso. & Ins. Co. ,, Hartford, Connecticut
%i ghe e ,nponente described in this Owner's Report during the period b/74E to /bM . and state that to the best of my knowledge and belief, the Owner hee performed eneminations and taken corrective measures described in thle
- Owner's Report in accordance with the requirements of the ASME Code, Section XI.
By signing this certificate neither the inspector nor his employer rnekee any worrenty, expressed or implied, concerning the eneminatione and corrective measures described in this Owner's Report. Furthe*more, neether the inspector nor his employer ' shall tse liable in any menner for any personal Iriury or property damage or a loss of any kind arising from or connected with thle i inspection. Cr w C a nspectore sientsure Commissions C bN b8 Nettonal Soerd, State, Province, and Endorsemente Deen 19 f v l l l l
i l R l l ' " FORM N18-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS l As Required by the Provisions of the ASME Code Section XI
- 1. Owner TVA-Nurlaar Dower Croun meme - Date f 2 ~@ 9d f.fy, .93 1101 Market Street chattanrwwva" _ 'PM '1'7 A n h S A n 1 Sheet j of ! ,
' Addrama l 2, Plant Carvurnish Mu r= 1 m a v- Dlant Unit Nome
$*3Av"Off N
'rw 2727.
- Asldress M Q 3I050 Repair Orsonlastlen P.O. No., Job No., etc.}}